ML17319A707

09 Draft Outlines

ML17319A707
Person / Time
Site:	South Texas
Issue date:	10/09/2017
From:	Vincent Gaddy Operations Branch IV
To:	South Texas
References
Download: ML17319A707 (45)

Text

Changes Rev. 2 ES-401 PWR Examination Outline Form ES-401-2 Facility: South Texas Project (RO Exam) Date of Exam: October 9, 2017 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 3 2 3 4 3 3 18 6 Emergency and Abnormal Plant 2 2 2 1 N/A 1 2 N/A 1 9 4 Evolutions Tier Totals 5 4 4 5 5 4 27 10 1 3 2 3 3 2 2 3 2 3 2 3 28 5 2.

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

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 3 2 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 outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 radiation control K/A is allowed if it is replaced by a K/A from another Tier 3 category.)

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

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

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

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

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

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

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

9. For Tier 3, select topics from Section 2 of the K/A catalog and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

G* Generic K/As

• These systems/evolutions must be included as part of the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the K/A catalog.

• • These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan.

Page 1 of 12

Changes Rev. 2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #

2.4.2: Knowledge of system set points, interlocks 000007 (EPE 7; BW E02&E10; CE E02) X and automatic actions associated with EOP entry 4.5 11 Reactor Trip, Stabilization, Recovery / 1 conditions. (CFR: 41.7 / 45.7 / 45.8) 000008 (APE 8) Pressurizer Vapor Space Accident / 3 000009 (EPE 9) Small Break LOCA / 3 X EK3.03: Knowledge of the reasons for the following 4.1 13 responses as the apply to the small break LOCA:

Reactor trip and safety initiation (CFR 41.5 / 41.10 /

45.6 / 45.13) 000011 (EPE 11) Large Break LOCA / 3 000015 (APE 15) Reactor Coolant Pump X 2.1.23: Ability to perform specific system and 4.3 14 Malfunctions / 4 integrated plant procedures during all modes of plant operation. (CFR: 41.10 / 43.5 / 45.2 / 45.6)

AK1.04: Knowledge of the operational implications 000022 (APE 22) Loss of Reactor Coolant X of the following concepts as they apply to Loss of 2.9 15 Makeup / 2 Reactor Coolant Makeup: Reason for changing from manual to automatic control of charging flow valve controller (CFR 41.8 / 41.10 / 45.3) 000025 (APE 25) Loss of Residual Heat X AK1.01: Knowledge of the operational implications 3.9 12 Removal System / 4 of the following concepts as they apply to Loss of Residual Heat Removal System: Loss of RHRS during all modes of operation. (CFR 41.8 / 41.10 /

45.3)

AK3.02: Knowledge of the reasons for the following 000026 (APE 26) Loss of Component X responses as they apply to the Loss of Component 3.6 16 Cooling Water / 8 Cooling Water: The automatic actions (alignments) within the CCWS resulting from the actuation of the ESFAS (CFR 41.5,41.10 / 45.6 / 45.13) 000027 (APE 27) Pressurizer Pressure X AK2.03: Knowledge of the interrelations between 2.6 17 Control System Malfunction / 3 the Pressurizer Pressure Control Malfunctions and the following: Controllers and positioners (CFR 41.7

/ 45.7) 000029 (EPE 29) Anticipated Transient X EA2.08: Ability to determine or interpret the 3.4 18 Without Scram / 1 following as they apply to a ATWS: Rod bank step counters and RPI (CFR 43.5 / 45.13) 000038 (EPE 38) Steam Generator Tube X EA1.05: Ability to operate and monitor the following 4.1 19 Rupture / 3 as they apply to a SGTR: Maximum controlled depressurization rate for affected S/G (CFR 41.7 /

45.5 / 45.6) 000040 (APE 40; BW E05; CE E05; W E12)

Steam Line RuptureExcessive Heat Transfer / 4 000054 (APE 54; CE E06) Loss of Main X AK1.01: Knowledge of the operational implications 4.1 20 Feedwater /4 of the following concepts as they apply to Loss of Main Feedwater (MFW): MFW line break depressurizes the S/G (similar to a steam line break) (CFR 41.8 / 41.10 / 45.3) 000055 (EPE 55) Station Blackout / 6 AA1.04: Ability to operate and / or monitor the 000056 (APE 56) Loss of Offsite Power / 6 X following as they apply to the Loss of Offsite Power: 3.2 21 Adjustment of speed of ED/G to maintain frequency and voltage levels (CFR 41.7 / 45.5 / 45.6)

Page 2 of 12

Changes Rev. 2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #

000057 (APE 57) Loss of Vital AC X AA1.01: Ability to operate and / or monitor the 3.7 22 Instrument Bus / 6 following as they apply to the Loss of Vital AC Instrument Bus: Manual inverter swapping (CFR 41.7 / 45.5 / 45.6) 000058 (APE 58) Loss of DC Power / 6 000062 (APE 62) Loss of Nuclear Service X 2.2.44: Ability to interpret control room indications to 4.2 23 Water / 4 verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions. (CFR: 41.5 /

43.5 / 45.12) 000065 (APE 65) Loss of Instrument Air / 8 X AA2.06: Ability to determine and interpret the 2.9 24 following as they apply to the Loss of Instrument Air: When to trip reactor if instrument air pressure is decreasing (CFR: 43.5 / 45.13) 000077 (APE 77) Generator Voltage and X AA2.03: Ability to determine and interpret the 3.5 28 Electric Grid Disturbances / 6 following as they apply to Generator Voltage and Electric Grid Disturbances: Generator current outside the capability curve (CFR: 41.5 and 43.5 /

45.5, 45.7, and 45.8)

(W E04) LOCA Outside Containment / 3 X W/E04 EA1.2: Ability to operate and / or monitor the 3.6 25 following as they apply to the (LOCA Outside Containment): Operating behavior characteristics of the facility.(CFR: 41.7 / 45.5 / 45.6)

(W E11) Loss of Emergency Coolant X W/E11 EK3.3: Knowledge of the reasons for the 3.8 26 Recirculation / 4 following responses as they apply to the (Loss of Emergency Coolant Recirculation): Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations.(CFR:

41.5 / 41.10, 45.6, 45.13)

(BW E04; W E05) Inadequate Heat X W/E05 EK2.2: Knowledge of the interrelations 3.9 27 TransferLoss of Secondary Heat Sink / 4 between the (Loss of Secondary Heat Sink) and the following: 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.(CFR: 41.7 / 45.7)

K/A Category Totals: 3 2 3 4 3 3 Group Point Total: 18 Page 3 of 12

Changes Rev. 2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #

000001 (APE 1) Continuous Rod Withdrawal / 1 X AK2.06: Knowledge of the 2.9 29 interrelations between the Continuous Rod Withdrawal and the following: Rod bank step counters (CFR 41.7 / 45.7) 000003 (APE 3) Dropped Control Rod / 1 000005 (APE 5) Inoperable/Stuck Control Rod / 1 X AK3.05: Knowledge of the 3.4 30 reasons for the following responses as they apply to the Inoperable / Stuck Control Rod:

Power limits on rod misalignment (CFR 41.5,41.10 / 45.6 / 45.13) 000024 (APE 24) Emergency Boration / 1 X AK1.01: Knowledge of the 3.4 31 operational implications of the following concepts as they apply to Emergency Boration:

Relationship between boron addition and change in T-ave (CFR 41.8 / 41.10 / 45.3) 000028 (APE 28) Pressurizer (PZR) Level Control Malfunction / 2 000032 (APE 32) Loss of Source Range Nuclear Instrumentation / 7 000033 (APE 33) Loss of Intermediate Range Nuclear Instrumentation / 7 000036 (APE 36; BW/A08) Fuel-Handling Incidents / 8 X AA2.02: Ability to determine and 3.4 32 interpret the following as they apply to the Fuel Handling Incidents: Occurrence of a fuel handling incident (CFR: 43.5 /

45.13) 000037 (APE 37) Steam Generator Tube Leak / 3 X AA1.11: Ability to operate and / or 3.4 34 monitor the following as they apply to the Steam Generator Tube Leak: PZR level indicator (CFR 41.7 / 45.5 / 45.6) 000051 (APE 51) Loss of Condenser Vacuum / 4 000059 (APE 59) Accidental Liquid Radwaste Release / 9 X 2.4.31: Knowledge of annunciator 4.2 33 alarms, indications, or response procedures. (CFR: 41.10 / 45.3) 000060 (APE 60) Accidental Gaseous Radwaste Release / 9 000061 (APE 61) Area Radiation Monitoring System Alarms

/7 000067 (APE 67) Plant Fire On Site / 8 000068 (APE 68; BW A06) Control Room Evacuation / 8 X AA2.05: Ability to determine and 4.2 35 interpret the following as they apply to the Control Room Evacuation: Availability of heat sink (CFR: 43.5 / 45.13) 000069 (APE 69; W E14) Loss of Containment Integrity / 5 000074 (EPE 74; W E06 & E07) Inadequate Core Cooling /

4 000076 (APE 76) High Reactor Coolant Activity / 9 000078 (APE 78*) RCS Leak / 3 (W E01 & E02) Rediagnosis & SI Termination / 3 (W E13) Steam Generator Overpressure / 4 (W E15) Containment Flooding / 5 Page 4 of 12

Changes Rev. 2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #

(W E16) High Containment Radiation /9 X W/E16 EK2.1: Knowledge of the 3.0 36 interrelations between the (High Containment Radiation) and the following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

(CFR: 41.7 / 45.7)

(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 Sub-cooling Margin / 4 (BW E08; W E03) LOCA CooldownDepressurization / 4 (BW E09; CE A13**; W E09 & E10) Natural Circulation/4 X W10 EK1.2: Knowledge of the 3.4 37 operational implications of the following concepts as they apply to the (Natural Circulation with Steam Void in Vessel with/without RVLIS): Normal, abnormal and emergency operating procedures associated with (Natural Circulation with Steam Void in Vessel with/without RVLIS).(CFR:

41.8 / 41.10 / 45.3)

(BW E13 & E14) EOP Rules and Enclosures (CE A11**; W E08) RCS OvercoolingPressurized Thermal Shock / 4 (CE A16) Excess RCS Leakage / 2 (CE E09) Functional Recovery (CE E13*) Loss of Forced Circulation/LOOP/Blackout / 4 K/A Category Point Totals: 2 2 1 1 2 1 Group Point Total: 9 Page 5 of 12

Changes Rev. 2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #

003 (SF4P RCP) Reactor Coolant X A4.08: Ability to manually operate and/or 3.2 1 Pump monitor in the control room: RCP cooling water supplies (CFR: 41.7 / 45.5 to 45.8)

K4.11: Knowledge of CVCS design feature(s) 004 (SF1; SF2 CVCS) Chemical and X and/or interlock(s) which provide for the 3.1 2 Volume Control following: Temperature/pressure control in letdown line: prevent boiling, lifting reliefs, hydraulic shock, piping damage, and burst (CFR: 41.7)

A3.09: Ability to monitor automatic operation of X the CVCS,including: VCT level 3.3 3 (CFR: 41.7 / 45.5)

K1.04: Knowledge of the physical connections 005 (SF4P RHR) Residual Heat X and/or cause-effect relationships between the 2.9 4 Removal RHRS and the following systems: CVCS (CFR: 41.2 to 41.9 / 45.7 to 45.8)

K6.03: Knowledge of the effect of a loss or X malfunction on the following will have on the 2.5 5 RHRS: RHR heat exchanger (CFR: 41.7 / 45.7)

K1.03: Knowledge of the physical connections 006 (SF2; SF3 ECCS) Emergency X and/or cause-effect relationships between the 4.2 6 Core Cooling ECCS and the following systems: RCS (CFR: 41.2 to 41.9 / 45.7 to 45.8)

A1.01: Ability to predict and/or monitor 007 (SF5 PRTS) Pressurizer X changes in parameters (to prevent exceeding 2.9 7 Relief/Quench Tank design limits) associated with operating the PRTS controls including: Maintaining quench tank water level within limits (CFR: 41.5 / 45.5)

A1.02: Ability to predict and/or monitor 008 (SF8 CCW) Component Cooling X changes in parameters (to prevent exceeding 2.9 8 Water design limits) associated with operating the CCWS controls including: CCW temperature (CFR: 41.5 / 45.5) 010 (SF3 PZR PCS) Pressurizer X K5.02: Knowledge of the operational 2.6 9 Pressure Control implications of the following concepts as the apply to the PZR PCS: constant enthalpy expansion through a valve (CFR: 41.5 / 45.7) 2.2.42: Ability to recognize system parameters X that are entry-level conditions for Technical 3.9 10 Specifications.

(CFR: 41.7 / 41.10 / 43.2 / 43.3 / 45.3)

A2.05: Ability to (a) predict the impacts of the 012 (SF7 RPS) Reactor Protection X following malfunctions or operations on the 3.1 38 RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Faulty or erratic operation of detectors and function generators (CFR: 41.5 / 43.5 / 45.3 / 45.5)

K3.01: Knowledge of the effect that a loss or 013 (SF2 ESFAS) Engineered X malfunction of the ESFAS will have on the 4.4 39 Safety Features Actuation following: Fuel (CFR: 41.7 / 45.6)

A3.01: Ability to monitor automatic operation of 022 (SF5 CCS) Containment Cooling X the CCS, including: Initiation of safeguards 4.1 40 mode of operation (CFR: 41.7 / 45.5)

Page 6 of 12

Changes Rev. 2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #

025 (SF5 ICE) Ice Condenser Not part of plant design K2.01: Knowledge of bus power supplies to the 026 (SF5 CSS) Containment Spray X following: Containment spray pumps 3.4 41 (CFR: 41.7)

X A3.01: Ability to monitor automatic operation of 4.3 42 the CSS, including: Pump starts and correct MOV positioning (CFR: 41.7 / 45.5)

K3.06: Knowledge of the effect that a loss or 039 (SF4S MSS) Main and Reheat X malfunction of the MRSS will have on the 2.8 43 Steam following: SDS (CFR: 41.7 / 45.6) 059 (SF4S MFW) Main Feedwater X 2.4.20: Knowledge of the operational 3.8 44 implications of EOP warnings, cautions, and notes. (CFR: 41.10 / 43.5 / 45.13)

K5.02: Knowledge of the operational 061 (SF4S AFW) X implications of the following concepts 3.2 45 Auxiliary/Emergency Feedwater as the apply to the AFW: Decay heat sources and magnitude (CFR: 41.5 / 45.7)

K6.01: Knowledge of the effect of a loss or X malfunction of the following will have on the 2.5 46 AFW components: Controllers and positioners (CFR: 41.7 / 45.7)

K2.01: Knowledge of bus power supplies to the 062 (SF6 ED AC) AC Electrical X following: Major system loads (CFR: 41.7) 3.3 47 Distribution 063 (SF6 ED DC) DC Electrical X K1.03: Knowledge of the physical connections 2.9 48 Distribution and/or cause-effect relationships between the DC electrical system and the following systems: Battery charger and battery (CFR:

41.2 to 41.9 / 45.7 to 45.8)

K4.11: Knowledge of ED/G system design 064 (SF6 EDG) Emergency Diesel X feature(s) and/or interlock(s) which provide for 3.5 49 Generator the following: Automatic load sequencer:

safeguards (CFR: 41.7)

X A1.08: Ability to predict and/or monitor 3.1 50 changes in parameters (to prevent exceeding design limits) associated with operating the ED/G system controls including: Maintaining minimum load on ED/G (to prevent reverse power) (CFR: 41.5 / 45.5) 073 (SF7 PRM) Process Radiation X A4.01: Ability to manually operate and/or 3.9 51 Monitoring monitor in the control room: Effluent release (CFR: 41.7 / 45.5 to 45.8) 076 (SF4S SW) Service Water X K4.02: Knowledge of SWS design feature(s) 2.9 52 and/or interlock(s)which provide for the following: Automatic start features associated with SWS pump controls (CFR: 41/7) 2.1.30 Ability to locate and operate 078 (SF8 IAS) Instrument Air X components, including local controls. (CFR: 4.4 53 41.7 / 45.7)

Page 7 of 12

Changes Rev. 2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO)

K/A Topic(s)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* IR #

K3.03: Knowledge of the effect that a loss or 103 (SF5 CNT) Containment X malfunction of the containment system will 3.7 54 have on the following: Loss of containment integrity under refueling operations (CFR: 41.7 / 45.6)

X A2.05: Ability to (a) predict the impacts of the 2.9 55 following malfunctions or operations on the containment system and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Emergency containment entry (CFR: 41.5 / 43.5 / 45.3 / 45.13) 053 (SF1; SF4P ICS*) Integrated Not part of plant design Control K/A Category Point Totals: 3 2 3 3 2 2 3 2 3 2 3 Group Point Total: 28 Page 8 of 12

Changes Rev. 2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 2 (RO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #

001 (SF1 CRDS) Control Rod Drive 002 (SF2; SF4P RCS) Reactor X K3.03: Knowledge of the effect that a loss or 4.2 56 Coolant malfunction of the RCS will have on the following: Containment (CFR: 41.7) 011 (SF2 PZR LCS) Pressurizer Level Control 014 (SF1 RPI) Rod Position X K4.06: Knowledge of RPIS design feature(s) 3.4 57 Indication and/or interlock(s) which provide for the following: Individual and group misalignment (CFR: 41.5 / 45.7) 015 (SF7 NI) Nuclear X A4.03: Ability to manually operate and/or 3.8 58 Instrumentation monitor in the control room: Trip bypasses (CFR: 41.7 / 45.5 to 45.8) 016 (SF7 NNI) Nonnuclear X A3.02: Ability to monitor automatic operation of 2.9 60 Instrumentation the NNIS including: Relationship between meter readings and actual parameter value (CFR: 41.7 / 45.5) 017 (SF7 ITM) In-Core Temperature Monitor 027 (SF5 CIRS) Containment Iodine X K2.01: Knowledge of bus power supplies to the 3.1 59 Removal following: Fans (CFR: 41.7) 028 (SF5 HRPS) Hydrogen Recombiner and Purge Control 029 (SF8 CPS) Containment Purge 033 (SF8 SFPCS) Spent Fuel Pool Cooling 034 (SF8 FHS) Fuel-Handling Equipment 035 (SF 4P SG) Steam Generator X K1.12: Knowledge of the physical connections 3.7 61 and/or cause-effect relationships between the S/GS and the following systems: RPS (CFR:

41.2 to 41.9 / 45.7 to 45.8) 041 (SF4S SDS) Steam Dump/Turbine Bypass Control 045 (SF 4S MTG) Main Turbine X K5.01: Knowledge of the operational 2.8 62 Generator implications of the following concepts as the apply to the MT/B System: Possible presence of explosive mixture in generator if hydrogen purity deteriorates (CFR: 41.5 / 45.7) 055 (SF4S CARS) Condenser Air Removal 056 (SF4S CDS) Condensate X 2.1.7: Ability to evaluate plant performance and 4.4 63 make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. (CFR: 41.5 / 43.5 /

45.12 / 45.13) 068 (SF9 LRS) Liquid Radwaste 071 (SF9 WGS) Waste Gas Disposal 072 (SF7 ARM) Area Radiation Monitoring 075 (SF8 CW) Circulating Water X A2.03: Ability to (a) predict the impacts of the 2.5 64 following malfunctions or operations on the Circulating Water System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Safety features and relationship between condenser vacuum, turbine trip, and steam dump (CFR: 41.5 / 43.5

/ 43.3 / 45.13)

Page 9 of 12

Changes Rev. 2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 2 (RO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #

079 (SF8 SAS**) Station Air 086 Fire Protection X A1.01: Ability to predict and/or monitor 2.9 65 changes in parameters (to prevent exceeding design limits) associated with Fire Protection System operating the controls including: Fire header pressure(CFR: 41.5 / 45.5) 050 (SF 9 CRV*) Control Room Ventilation K/A Category Point Totals: 1 1 1 1 1 0 1 1 1 1 1 Group Point Total: 10 Page 10 of 12

Changes Rev. 2 ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: South Texas Project (RO Exam) Date of Exam: October 9, 2017 Category K/A # Topic RO SRO-only IR # IR #

2.1.4 Knowledge of individual licensed operator 3.3 66 responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc. (CFR: 41.10 / 43.2)

Knowledge of procedures, guidelines, or limitations 2.1.37 4.3 67

1. Conduct of associated with reactivity management. (CFR: 41.1 /

Operations 43.6 / 45.6)

Knowledge of refueling administrative requirements.

2.1.40 2.8 68 (CFR: 41.10 / 43.5 / 45.13) 2.1.

Subtotal 3 2.2.6 Knowledge of the process for making changes to 3.0 69 procedures. (CFR: 41.10 / 43.3 / 45.13) 2.2.14 Knowledge of the process for controlling equipment 3.9 70 configuration or status. (CFR: 41.10 / 43.3 / 45.13)

2. Equipment Control 2.2.39 Knowledge of less than or equal to one hour Technical 3.9 71 Specification action statements for systems. (CFR: 41.7

/ 41.10 / 43.2 / 45.13) 2.2.

Subtotal 3 2.3.12 Knowledge of radiological safety principles pertaining to 3.2 72 licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. (CFR:

41.12 / 45.9 / 45.10)

3. Radiation Control 2.3.14 Knowledge of radiation or contamination hazards that 3.4 73 may arise during normal, abnormal, or emergency conditions or activities. (CFR: 41.12 / 43.4 / 45.10) 2.3.

Subtotal 2 2.4.9 Knowledge of low power/shutdown implications in 3.8 74 accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies. (CFR:

4. Emergency 41.10 / 43.5 / 45.13)

Procedures/Plan Knowledge of fire in the plant procedures. (CFR: 41.10 2.4.27 3.4 75

/ 43.5 / 45.13) 2.4.

Subtotal 2 Tier 3 Point Total 10 Page 11 of 12

Change Rev. 2 ES-401 (STP LOT 21 RO Exam) Record of Rejected K/As Form ES-401-4 All replacement K/As were requested from the NRC Chief Examiner per ES-401 D.1.b.

Tier/Gro Randomly Selected Reason for Rejection up K/A 1/1 APE 008 AK1.01 This K/A tests knowledge of thermodynamics of a leaking or open valve associated with a Pressurizer vapor space accident. A (Outline Question 12) question for this K/A is similar to a question written K/A 010 K5.02 (Outline Question 9) on this exam. Therefore the K/A was replaced with APE 025 AK1.01.

1/1 EPE 009 EK3.12 This K/A tests the knowledge of the reason for a letdown isolation during a SBLOCA. There were not enough plausible distractors to (Outline Question 13) answer this K/A. Therefore the K/A was replaced with EPE 009 EK3.03.

1/1 APE 065 AA2.07 This K/A tests the ability to determine if backup nitrogen supply is controlling a valve upon the loss of IA. This is not applicable at STP.

(Outline Question 24) There are no valves that have an automatic backup nitrogen supply.

Therefore the K/A was replaced with APE 065 AA2.06.

1/2 APE 001 AK2.01 This K/A tests the knowledge of relations between rod bank step counters and continuous rod withdrawal. There were not enough (Outline Question 29) plausible distractors to answer this K/A. Therefore the K/A was replaced with APE 001 AK2.06.

1/2 APE 061 AA1.01 This K/A tests the ability to operate or monitor automatic actuations associated with ARMs. There are no auto actions associated with (Outline Question 34) the ARMs at STP. Therefore the K/A was replaced with APE 037 AA1.11.

2/1 076 K4.03 This K/A tests the knowledge of the automatic opening features associated with SWS isolation valves to CCW heat exchangers.

(Outline Question 52) This does not apply at STP. These valves have no automatic opening features. Therefore the K/A was replaced with 076 K4.02.

2/1 078 G2.2.3 This K/A tests the differences between units associated with IA system. There is nothing of significance that is different with IA (Outline Question 53) between the two units at STP. Therefore the K/A was replaced with 078 G2.1.30.

2/2 033 A3.02 This K/A tests the ability to monitor automatic operations of the SFPCS. There is no auto functions associated with this K/A at STP.

(Outline Question 60) Therefore the K/A was replaced with 016 A3.02.

2/2 045 K5.18 This K/A tests the knowledge of the purpose of low power reactor trips as applied to MT/B system. There were not enough plausible (Outline Question 62) distractors to answer this K/A. Therefore the K/A was replaced with 045 K5.01.

2/2 072 A2.01 This K/A predicts the impacts of a malfunction on the ARM system and use procedures to mitigate the consequences of an erratic or (Outline Question 64) failed power supply. There were not enough plausible distractors to answer this K/A. Therefore the K/A was replaced with 075 A2.03.

3 G2.1.39 This K/A tests the knowledge of conservative decision-making. The question written was determined to have a LOD of 1. Therefore, the (Outline Question 68) K/A was replaced with G2.1.40.

Page 12 of 12

Changes Rev. 1 ES-401 PWR Examination Outline Form ES-401-2 Facility: South Texas Project (SRO Exam) Date of Exam: October 9, 2017 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 18 3 3 6 Emergency and Abnormal Plant 2 N/A N/A 9 2 2 4 Evolutions Tier Totals 27 5 5 10 1 28 3 2 5 2.

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

3. Generic Knowledge and Abilities 1 2 3 4 10 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 outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 radiation control K/A is allowed if it is replaced by a K/A from another Tier 3 category.)

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

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

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

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

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

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

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

9. For Tier 3, select topics from Section 2 of the K/A catalog and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

G* Generic K/As

• These systems/evolutions must be included as part of the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the K/A catalog.

• • These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan.

Page 1 of 10

Changes Rev. 1 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (SRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #

000007 (EPE 7; BW E02&E10; CE E02)

Reactor Trip, Stabilization, Recovery / 1 000008 (APE 8) Pressurizer Vapor Space Accident / 3 000009 (EPE 9) Small Break LOCA / 3 EA2.11: Ability to determine or interpret the 000011 (EPE 11) Large Break LOCA / 3 X following as they apply to a Large Break LOCA: 4.3 76 Conditions for throttling or stopping HPI (CFR 43.5 /

45.13) 000015 (APE 15) Reactor Coolant Pump Malfunctions / 4 000022 (APE 22) Loss of Reactor Coolant Makeup / 2 000025 (APE 25) Loss of Residual Heat Removal System / 4 000026 (APE 26) Loss of Component Cooling Water / 8 000027 (APE 27) Pressurizer Pressure Control System Malfunction / 3 000029 (EPE 29) Anticipated Transient Without Scram / 1 000038 (EPE 38) Steam Generator Tube Rupture / 3 000040 (APE 40; BW E05; CE E05; W E12) X 2.4.47: Ability to diagnose and recognize trends in 4.2 78 Steam Line RuptureExcessive Heat an accurate and timely manner utilizing the Transfer / 4 appropriate control room reference material.

(CFR: 41.10 / 43.5 / 45.12) 000054 (APE 54; CE E06) Loss of Main Feedwater /4 000055 (EPE 55) Station Blackout / 6 X 2.4.18: Knowledge of the specific bases for EOPs. 4.0 79 (CFR: 41.10 / 43.1 / 45.13) 000056 (APE 56) Loss of Offsite Power / 6 000057 (APE 57) Loss of Vital AC X 2.2.37: Ability to determine operability and/or 4.6 81 Instrument Bus / 6 availability of safety related equipment. (CFR: 41.7 /

43.5 / 45.12) 000058 (APE 58) Loss of DC Power / 6 X AA2.03: Ability to determine and interpret the 3.9 80 following as they apply to the Loss of DC Power:

DC loads lost; impact on ability to operate and monitor plant systems (CFR: 43.5 / 45.13) 000062 (APE 62) Loss of Nuclear Service Water / 4 000065 (APE 65) Loss of Instrument Air / 8 000077 (APE 77) Generator Voltage and Electric Grid Disturbances / 6 (W E04) LOCA Outside Containment / 3 X EA2.1: Ability to determine or interpret the following 4.3 77 as they apply to LOCA Outside Containment:

Facility conditions and selection of appropriate procedures during abnormal and emergency operations. (CFR 43.5 / 45.13)

Page 2 of 10

Changes Rev. 1 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (SRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #

(W E11) Loss of Emergency Coolant Recirculation / 4 (BW E04; W E05) Inadequate Heat TransferLoss of Secondary Heat Sink / 4 K/A Category Totals: 3 3 Group Point Total: 6 Page 3 of 10

Changes Rev. 1 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (SRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #

000001 (APE 1) Continuous Rod Withdrawal / 1 000003 (APE 3) Dropped Control Rod / 1 X 2.2.40: Ability to apply Technical 4.7 82 Specifications for a system.

(CFR: 41.10 / 43.2 / 43.5 / 45.3) 000005 (APE 5) Inoperable/Stuck Control Rod / 1 000024 (APE 24) Emergency Boration / 1 000028 (APE 28) Pressurizer (PZR) Level Control Malfunction / 2 000032 (APE 32) Loss of Source Range Nuclear Instrumentation / 7 000033 (APE 33) Loss of Intermediate Range Nuclear Instrumentation / 7 000036 (APE 36; BW/A08) Fuel-Handling Incidents / 8 000037 (APE 37) Steam Generator Tube Leak / 3 000051 (APE 51) Loss of Condenser Vacuum / 4 000059 (APE 59) Accidental Liquid Radwaste Release / 9 X Ability to approve release permits. 3.8 84 (CFR: 41.13 / 43.4 / 45.10) 000060 (APE 60) Accidental Gaseous Radwaste Release / 9 000061 (APE 61) Area Radiation Monitoring System Alarms

/7 000067 (APE 67) Plant Fire On Site / 8 000068 (APE 68; BW A06) Control Room Evacuation / 8 000069 (APE 69; W E14) Loss of Containment Integrity / 5 000074 (EPE 74; W E06 & E07) Inadequate Core Cooling /

4 000076 (APE 76) High Reactor Coolant Activity / 9 000078 (APE 78*) RCS Leak / 3 (W E01 & E02) Rediagnosis & SI Termination / 3 X W/E01 EA2.1: Facility conditions 4.0 85 and selection of appropriate procedures during abnormal and emergency operations.

(CFR: 43.5)

(W E13) Steam Generator Overpressure / 4 (W E15) Containment Flooding / 5 (W E16) High Containment Radiation /9 (BW A01) Plant Runback / 1 (BW A02 & A03) Loss of NNI-X/Y/7 (BW A04) Turbine Trip / 4 (BW A05) Emergency Diesel Actuation / 6 (BW A07) Flooding / 8 (BW E03) Inadequate Sub-cooling Margin / 4 (BW E08; W E03) LOCA CooldownDepressurization / 4 (BW E09; CE A13**; W E09 & E10) Natural Circulation/4 X W/E09 EA2.1: Ability to determine 3.8 83 and interpret the following as they apply to Natural Circulation Operations: Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

(BW E13 & E14) EOP Rules and Enclosures (CE A11**; W E08) RCS OvercoolingPressurized Thermal Shock / 4 (CE A16) Excess RCS Leakage / 2 (CE E09) Functional Recovery Page 4 of 10

Changes Rev. 1 (CE E13*) Loss of Forced Circulation/LOOP/Blackout / 4 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (SRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #

K/A Category Point Totals: 2 2 Group Point Total: 4 Page 5 of 10

Changes Rev. 1 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (SRO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #

003 (SF4P RCP) Reactor Coolant Pump 004 (SF1; SF2 CVCS) Chemical and Volume Control 005 (SF4P RHR) Residual Heat Removal 006 (SF2; SF3 ECCS) Emergency X A2.04: Ability to (a) predict the impacts of the 3.8 86 Core Cooling following malfunctions or operations on the ECCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Improper discharge pressure (CFR: 41.5 / 45.5) 007 (SF5 PRTS) Pressurizer Relief/Quench Tank 008 (SF8 CCW) Component Cooling Water 010 (SF3 PZR PCS) Pressurizer Pressure Control 012 (SF7 RPS) Reactor Protection 013 (SF2 ESFAS) Engineered X A2.02: Ability to (a) predict the impacts of the 4.5 88 Safety Features Actuation following malfunctions or operations on the ESFAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operation: Excess steam demand (CFR: 41.5 /

43.5 / 45.3 / 45.13) 022 (SF5 CCS) Containment Cooling 025 (SF5 ICE) Ice Condenser 026 (SF5 CSS) Containment Spray 039 (SF4S MSS) Main and Reheat Steam 059 (SF4S MFW) Main Feedwater 061 (SF4S AFW) X 2.2.25: Knowledge of the bases in Technical 4.2 87 Auxiliary/Emergency Feedwater Specifications for limiting conditions for operations and safety limits. (CFR: 41.5 / 41.7

/ 43.2) 062 (SF6 ED AC) AC Electrical X A2.04: Ability to (a) predict the impacts of the 3.4 89 Distribution following malfunctions or operations on the ac distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Effect on plant of de-energizing a bus (CFR: 41.5 / 43.5 / 45.3 /

45.13) 063 (SF6 ED DC) DC Electrical Distribution 064 (SF6 EDG) Emergency Diesel Generator Page 6 of 10

Changes Rev. 1 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (SRO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #

073 (SF7 PRM) Process Radiation Monitoring 076 (SF4S SW) Service Water X 2.4.8: Knowledge of how abnormal operating 4.5 90 procedures are used in conjunction with EOPs.

(CFR: 41.10 / 43.5 / 45.13) 078 (SF8 IAS) Instrument Air 103 (SF5 CNT) Containment 053 (SF1; SF4P ICS*) Integrated Control K/A Category Point Totals: 3 2 Group Point Total: 5 Page 7 of 10

Changes Rev. 1 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 2 (SRO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #

001 (SF1 CRDS) Control Rod Drive 002 (SF2; SF4P RCS) Reactor Coolant 011 (SF2 PZR LCS) Pressurizer X 2.2.12: Knowledge of surveillance procedures 4.1 91 Level Control (CFR: 41.10 / 45.13) 014 (SF1 RPI) Rod Position Indication 015 (SF7 NI) Nuclear Instrumentation 016 (SF7 NNI) Nonnuclear Instrumentation 017 (SF7 ITM) In-Core Temperature X 2.4.21: Knowledge of the parameters and logic 4.6 93 Monitor 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) 027 (SF5 CIRS) Containment Iodine Removal 028 (SF5 HRPS) Hydrogen Recombiner and Purge Control 029 (SF8 CPS) Containment Purge 033 (SF8 SFPCS) Spent Fuel Pool X A2.03: Ability to (a) predict the impacts of the 3.5 92 Cooling following malfunctions or operations on the Spent Fuel Pool Cooling; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Abnormal spent fuel pool water level or loss of water level (CFR: 41.5 / 43.5 / 45.3 / 45.5) 034 (SF8 FHS) Fuel-Handling Not selected for this sample plan Equipment 035 (SF 4P SG) Steam Generator 041 (SF4S SDS) Steam Dump/Turbine Bypass Control 045 (SF 4S MTG) Main Turbine Generator 055 (SF4S CARS) Condenser Air Removal 056 (SF4S CDS) Condensate 068 (SF9 LRS) Liquid Radwaste 071 (SF9 WGS) Waste Gas Disposal 072 (SF7 ARM) Area Radiation Monitoring 075 (SF8 CW) Circulating Water 079 (SF8 SAS**) Station Air 086 Fire Protection 050 (SF 9 CRV*) Control Room Ventilation K/A Category Point Totals: 1 2 Group Point Total: 3 Page 8 of 10

Changes Rev. 1 ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: South Texas Project (SRO Exam) Date of Exam: October 9, 2017 Category K/A # Topic RO SRO-only IR # IR #

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

(CFR: 41.10 / 43.5 / 45.12)

1. Conduct of Knowledge of the refueling process.

Operations 2.1.41 3.7 95 (CFR: 41.2 / 41.10 / 43.6 / 45.13) 2.1.

Subtotal 2 2.2.43 Knowledge of the process used to track inoperable 3.3 96 alarms.

(CFR: 41.10 / 43.5 / 45.13)

2. Equipment 2.2.22 Knowledge of limiting conditions for operations and 4.7 97 Control safety limits.

(CFR: 41.5 / 43.2 / 45.2) 2.2.

Subtotal 2 Ability to control radiation releases.

2.3.11 4.3 98

3. Radiation (CFR: 41.11 / 43.4 / 45.10)

Control 2.3.

Subtotal 1 Knowledge of the emergency plan.

2.4.29 4.4 99 (CFR: 41.10 / 43.5 / 45.11)

4. Emergency 2.4.27 Knowledge of fire in the plant procedures. 3.9 100 Procedures/Plan (CFR: 41.10 / 43.5 / 45.13) 2.4.

Subtotal 2 Tier 3 Point Total 7 Page 9 of 10

Changes Rev. 1 ES-401 (STP LOT 21 SRO Exam) Record of Rejected K/As Form ES-401-4 All replacement K/As were requested from the NRC Chief Examiner per ES-401 D.1.b.

Tier/Group Randomly Selected Reason for Rejection K/A 1/1 EPE 025 AA2.03 This K/A tests the ability to determine an increasing RCB sump level upon a loss of RHR. This event applies to an off-normal (Outline Question 77) procedure and only 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> TS or less action statements at STP.

An SRO only question could not be written. Therefore, the K/A was replaced with W E04 EA2.1.

1/1 W E11 G2.2.37 This K/A is a generic K/A that determines operability of safety related equipment associated with the Loss of Emergency (Outline Question 81) Coolant Recirculation. There was too much overlap with this K/A and associated question with Outline Question 76 on this exam.

Therefore, the Generic portion of the K/A was kept but replaced to APE 057.

1/2 APE 037 A2.11 This K/A tests the ability to determine when to isolate a SG as it applies to the off-normal. There was no plausibility for an SRO (Outline Question 83) only question. Therefore, the K/A was replaced with W/E09 EA2.1.

1/2 APE 069 G2.2.40 This K/A is a generic K/A to test the ability to apply Tech Specs and is related to Loss of Containment Integrity. This K/A was (Outline Question 84) changed in order to avoid over sampling of TS on the SRO exam and also due to the majority of the TS associated with it being a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or less action. Therefore, the K/A was replaced with APE 059 G2.3.6.

2/1 008 G2.2.25 This K/A is a generic K/A to test knowledge of TS bases and was associated with CCW. There was no plausibility for an SRO (Outline Question 87) only question. Therefore, the Generic portion of the K/A was kept but replaced to 061 system.

2/2 041 G2.4.21 This K/A is a generic K/A to test knowledge of the parameters and logic used to assess the status of safety functions and was (Outline Question 93) associated with Steam Dumps. The generic portion of this K/A did not match the system well and an SRO only question could not be written. Therefore, the Generic portion of the K/A was kept but replaced to 017 system.

3 G2.2.1 This K/A tests the ability to perform pre-startup procedures including operating the controls associated with equipment that (Outline Question 96) could affect reactivity. A plausible SRO only question could not be written for this K/A. Therefore, the K/A was replaced with G2.2.43.

3 G2.4.45 This K/A tests the ability to prioritize alarms. A question was written for this K/A. However, it was decided to replace it to (Outline Question 100) avoid over sampling of questions regarding TS on the SRO exam. Therefore, this K/A was replaced with G2.4.27.

Page 10 of 10

Rev. 0 ES-301 Administrative Topics Outline Form ES-301-1 Facility: South Texas Project Date of Examination: 09-25-17 Examination Level: RO SRO Operating Test Number: LOT 21 NRC Administrative Topic (see Type Describe activity to be performed Note) Code*

Conduct of Operations 2.1.32 Ability to explain and apply system limits and RA(1) precautions.

N,R Calculate Time Remaining in Condenser Pressure K/A Importance: 3.8 Restricted Zone Conduct of Operations 2.1.25 Ability to interpret reference materials, such as RA(2) graphs, curves, tables, etc.

D,R Calculate RCS refill volume (without vacuum)

K/A Importance: 3.9 Equipment Control 2.1.23 Ability to perform specific and integrated plant RA(3) procedures during all modes of operation.

D,R Determine H2 Recombiner Power Settings K/A Importance: 4.3 Radiation Control N/A Emergency Plan 2.4.39 Knowledge of RO responsibilities in emergency RA(4) D,P,R plan implementation Complete an Offsite Agency Notification Message Form K/A Importance: 3.9 NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

• Type Codes and Criteria: (C)ontrol Room, (S)imulator, Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs and 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: 09-25-17 Examination Level: RO SRO Operating Test Number: LOT 21 NRC Administrative Topic (see Type Describe activity to be performed Note) Code*

Conduct of Operations 2.1.42 Knowledge of new and spent fuel movement SA(5) procedures.

N,R Determine Close Contact Fuel Assembly Movement K/A Importance: 3.4 Conduct of Operations 2.1.20 Ability to interpret and execute procedure steps SA(6) D,R Review ESF Power Availability K/A Importance: 4.6 Equipment Control 2.2.13 Knowledge of Tagging and Clearance Procedures SA(7) D,R Review faulted ECO for AFW Pump K/A Importance: 4.3 Radiation Control 2.3.13 Knowledge of radiological safety procedures SA(8) pertaining to licensed operator duties, such as response to D,P,R radiation monitor alarms, containment entry requirements, K/A Importance: 3.8 fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Initiate a Dose Extension Emergency Plan 2.4.41 Knowledge of the emergency action level thresholds and classifications.

SA(9) M,R Determine Appropriate Emergency Plan EAL K/A Importance: 4.6 NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

• Type Codes and Criteria: (C)ontrol Room, (S)imulator, Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs and RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1, randomly selected)

Rev. 0 STP LOT-21 NRC Admin JPM Description RO (A1) Calculate Time Remaining in Condenser Pressure Restricted Zone Demonstrate the ability to explain and apply the limits associated with the Main Turbine and Condenser Pressure in accordance with 0POP04-CR-0001, Low Condenser Vacuum, Addendum 3, Main Turbine Exhaust Pressure Limitations.

(A2) Calculate RCS Refill Volume (Without Vacuum)

Demonstrate the ability to calculate the volume needed to fill the RCS from the given conditions.

(A3) Determine H2 Recombiner Power Settings Demonstrate the ability to calculate the required power setting for operation of a Hydrogen Recombiner in a post-LOCA environment.

(A4) Complete An Offsite Agency Notification Message Form Demonstrate the ability to prepare an Offsite Agency Notification Message Form for approval by the Emergency Director per 0ERP01-ZV-IN02, Notifications to Offsite Agencies.

SRO (A5) Determine Close Contact Fuel Assemble Movement Demonstrate the ability to review Fuel Transfer Forms and interpret procedure guidance for Close Contact Fuel Assembly moves in accordance with 0POP08-FH-0001, Refueling Machine Operating Instructions, Addendum 4, Guidelines For Close Contact Fuel Assembly Movements.

(A6) Review ESF Power Availability Surveillance Results Demonstrate the ability to review a completed ESF Power Availability surveillance and determine Technical Specification action requirements.

(A7) Review faulted ECO for AFW Pump Demonstrate the ability perform a technical review of an ECO in accordance with 0PGP03-ZO-EC01A, Equipment Clearance Order Instructions.

(A8) Initiate a Dose Extension Demonstrate the ability to determine the requirements for a dose extension in accordance with 0PGP03-ZR-0050, Radiation Protection Program.

(A9) Determine Appropriate Emergency Plan EAL Demonstrate the ability to correctly determine an Emergency Action Level for a given condition requiring entry into the STPNOC Emergency Action Plan in accordance with 0ERP01-ZV-IN01, Emergency Classification.

Rev. 0 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: South Texas Project Date of Examination: 09-25-17 Exam Level: RO SRO-I SRO-U Operating Test No.: LOT 21 NRC Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U Safety System / JPM Title Type Code*

Function

a. (S1) Place H2 Monitoring in Service KA: 028 A4.03 (3.1/3.3) D,L,S 5

b. (S2) Start a CCW Pump KA: 008 A4.01 (3.3/3.1) D,S 8

c. (S3) Isolate SI Accumulators KA: 006 A4.02 (4.0/3.8) A,D, EN,L,S 3

d. (S4) Transfer 4.16KV Bus from EDG to Offsite Power KA: 064 D,L,P,S 6 A4.01 (4.0/4.3)

e. (S5) Transfer MFW from LPFRVs to MFRVs KA: 035 A4.01 D,P,S 4S (3.7/3.6)

f. (S6) Remove a 2nd Letdown Orifice from Service KA: 004 A4.06 N,S 2 (3.6/3.1)

g. (S7) Respond to a FHB Rad Monitor Alarm KA: 072 A3.01 A,D,EN,S 7 (2.9/3.1)

h. (S8) Return Normal Letdown to Service KA: 004 A4.05 (3.6/3.1) A,M,S 1 In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i. (P1) Locally Re-Align Charging Pump Suction from the VCT to D,E,L,R 2 the RWST KA: G2.1.20 (4.6/4.6)

j. (P2) Startup the GWPS following PMT KA: 071 A2.02 (3.3/3.6) A,D,P,R 9

k. (P3) Place a 1E Battery Charger in Service KA: 063 A3.01 A,D 6 (2.7/3.1)

• 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, and in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO/SRO-I/SRO-U (A)lternate Path 4-6 / 4-6 / 2-3 (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 Page 1 of 5

Rev. 0 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: South Texas Project Date of Examination: 09-25-17 Exam Level: RO SRO-I SRO-U Operating Test No.: LOT 21 NRC Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U Safety System / JPM Title Type Code*

Function a.

b. (S2) Start a CCW Pump KA: 008 A4.01 (3.3/3.1) D,S 8

c. (S3) Isolate SI Accumulators KA: 006 A4.02 (4.0/3.8) A,D,EN,L,S 3

d. (S4) Transfer 4.16KV Bus from EDG to Offsite Power KA: 064 D,L,P,S 6 A4.01 (4.0/4.3)

e. (S5) Transfer MFW from LPFRVs to MFRVs KA: 035 A4.01 D,P,S 4S (3.7/3.6)

f. (S6) Remove a 2nd Letdown Orifice from Service KA: 004 A4.06 N,S 2 (3.6/3.1)

g. (S7) Respond to a FHB Rad Monitor Alarm KA: 072 A3.01 A,D,EN,S 7 (2.9/3.1)

h. (S8) Return Normal Letdown to Service KA: 004 A4.05 (3.6/3.1) A,M,S 1 In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i. (P1) Locally Re-Align Charging Pump Suction from the VCT to D,E,L,R 2 the RWST KA: G2.1.20 (4.6/4.6)

j. (P2) Startup the GWPS following PMT KA: 071 A2.02 (3.3/3.6) A,D,P,R 9

k. (P3) Place a 1E Battery Charger in Service KA: 063 A3.01 A,D 6 (2.7/3.1)

• 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, and in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO/SRO-I/SRO-U (A)lternate Path 4-6 / 4-6 / 2-3 (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 Page 2 of 5

Rev. 0 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: South Texas Project Date of Examination: 09-25-17 Exam Level: RO SRO-I SRO-U Operating Test No.: LOT 21 NRC Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U Safety System / JPM Title Type Code*

Function a.

b.

c.

d. (S4) Transfer 4.16KV Bus from EDG to Offsite Power KA: 064 D,L,P,S 6 A4.01 (4.0/4.3) e.

f.

g. (S7) Respond to a FHB Rad Monitor Alarm KA: 072 A3.01 A,D,EN,S 7 (2.9/3.1)

h. (S8) Return Normal Letdown to Service KA: 004 A4.05 (3.6/3.1) A,M,S 1 In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i. (P1) Locally Re-Align Charging Pump Suction from the VCT to D,E,L,R 2 the RWST KA: G2.1.20 (4.6/4.6)

j. (P2) Startup the GWPS following PMT KA: 071 A2.02 (3.3/3.6) A,D,P,R 9 k.

• 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, and in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO/SRO-I/SRO-U (A)lternate Path 4-6 / 4-6 / 2-3 (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 Page 3 of 5

Rev. 0 STP LOT-21 NRC Systems JPM Description Control Room Systems JPMs (S1) Place Containment H2 Monitoring in Service Demonstrate the ability to align the Containment H2 Monitoring System in order to monitor H2 concentration in accordance with Addendum 1 of 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant.

(S2) Start CCW Pump 1C Demonstrate the ability to start a 2nd CCW Pump and monitor system flow and pressure in accordance with 0POP02-CC-0001, Component Cooling Water.

(S3) Isolate SI Accumulators Demonstrate the ability to isolate SI Accumulators from the RCS by closing the discharge isolation valve and/or depressurizing the accumulator in accordance with 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant. This is an Alternate Path JPM.

(S4) Transfer 4.16KV Bus from EDG to Offsite Power Demonstrate the ability to control the Emergency Diesel Generators to transfer power to the Standby 13.8KV Bus in accordance with 0POP02-DG-0001, Emergency Diesel Generator 11(21).

(S5) Transfer MFW from LPFRV to MFRV Demonstrate the ability to control Steam Generator levels when aligning Main Feedwater flow from the Low Power Feedwater Regulation Valve to the Main Feedwater Regulation Valve in accordance with 0POP03-ZG-0005, Plant Startup to 100%.

(S6) Remove a 2nd Letdown Orifice from Service Demonstrate the ability to control CVCS letdown while changing letdown flow through the letdown orifices in accordance with 0POP02-CV-0004, Chemical and Volume Control Subsystem.

(S7) Respond to FHB Radiation Monitor Alarm Demonstrate the ability to properly align and control FHB HVAC after a high radiation actuation in accordance with 0POP04-RA-0001, Radiation Monitoring System Alarm Response. This is an Alternate Path JPM.

(S8) Return Normal Letdown to Service Demonstrate the ability to align and control Excess Letdown when it is determined that Normal Letdown is not working properly in accordance with Addendum 2 of 0POP05-EO-ES01, Reactor Trip Response. This is an Alternate Path JPM.

NOTE: All Control Room JPMs will be performed dynamically in the Simulator. The following JPMs will be performed in pairs; S1 & S3 together, S2 & S7 together, S4 & S8 together and S5 & S6 together.

Page 4 of 5

Rev. 0 STP LOT-21 NRC Systems JPM Description In Plant Systems JPMs (P1) Locally Re-Align charging Pump Suction from the VCT to the RWST Demonstrate the ability to locate and then align Charging Pump suction sources in accordance with 0POP05-EO-EC00, Loss of All AC Power. This is an Alternate Path JPM.

(P2) Startup of GWPS following PMT Demonstrate the ability to place a N2 purge on the GWPS prior to system startup in accordance with 0POP02-WG-0001, Gaseous Waste Processing System Operations.

This is an Alternate Path JPM.

(P3) Place a 1E Battery Charger inservice Demonstrate the ability to operate and monitor Class 1E Battery Chargers in accordance with 0POP02-EE-0001, ESF (Class1E) DC Distribution System. This is an Alternate Path JPM.

Page 5 of 5

Rev. 0 ES-301 Transient and Event Checklist Form ES-301-5 Facility: South Texas Project Date of Exam: 09-25-17 Operating Test No.: LOT 21 NRC Scenarios A E P V 1 2 3 4 T M P E O I L N T N I T C

A I A T L M N Y U T P M(*)

E CREW POSITION CREW POSITION CREW CREW POSITION POSITION Crew A S A B S A B S A B S A B R I U U1,U2, R T O R T O R T O R T O RO1 O C P O C P O C P O C P U1 1 1 0 RX RO 1 1 1 NOR SRO-I 3,4,5 2,6 4 4 2 I/C ,7 6 4 2 2 1 SRO-U MAJ TS 2,3 0 2 2 U2 1 1 0 RX RO 1 1 1 NOR SRO-I 3,7 2,3,5 4 4 2 I/C

,6 SRO-U MAJ 6 4 2 2 1 TS 2,3 0 2 2 RO1 4 1 1 0 RX RO NOR 1 1 1 1 1 1 4,5 3,5,6 6 4 4 2 SRO-I I/C 6 4 5,7 2 2 1 SRO-U MAJ TS 0 2 2 1 1 0 RX RO 1 1 1 NOR SRO-I 4 4 2 I/C SRO-U 2 2 1 MAJ TS 0 2 2 Instructions:

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

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

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

4. For licensees that use the ATC operator primarily for monitoring plant parameters, the chief examiner may place SRO-I applicants in either the ATC or BOP position to best evaluate the SRO-I in manipulating plant controls.

Rev. 0 ES-301 Transient and Event Checklist Form ES-301-5 Facility: South Texas Project Date of Exam: 09-25-17 Operating Test No.: LOT 21 NRC Scenarios A E P V 1 2 3 4 T M P E O I L N T N I T C

A I A T L M N Y U T P M(*)

E CREW POSITION CREW POSITION CREW CREW POSITION POSITION S A B S A B S A B S A B R I U Crew B R T O R T O R T O R T O U3, I1, O C P O C P O C P O C P I2 U3 1 1 0 RX RO 1 1 1 NOR SRO-I 3,4,5 2,6 4 4 2 I/C ,7 SRO-U MAJ 6 4 2 2 1 TS 2,3 0 2 2 I1 4 1 1 0 RX RO 1 1 1 NOR SRO-I 3,7 2,3,5 2 4 4 2 I/C

,6 SRO-U 6 4 5,7 2 2 1 MAJ TS 2,3 0 2 2 I2 4 1 1 0 RX RO 1 1 1 1 1 SRO-I NOR 4,5 3,5,6 2,6 4 4 2 I/C SRO-U 6 4 5,7 2 2 1 MAJ TS 2,3 0 2 2 1 1 0 RX RO 1 1 1 NOR SRO-I 4 4 2 I/C SRO-U 2 2 1 MAJ TS 0 2 2 Instructions:

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

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

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

8. For licensees that use the ATC operator primarily for monitoring plant parameters, the chief examiner may place SRO-I applicants in either the ATC or BOP position to best evaluate the SRO-I in manipulating plant controls.

Rev. 0 ES-301 Transient and Event Checklist Form ES-301-5 Facility: South Texas Project Date of Exam: 09-25-17 Operating Test No.: LOT 21 NRC Scenarios A E P V 1 2 3 4 T M P E O I L N BOP is a T N I T C

surrogate for A I A T this scenario. L M N Y U T P M(*)

E CREW POSITION CREW POSITION CREW CREW POSITION POSITION S A B S A B S A B S A B R I U Crew C R T O R T O R T O R T O U4, I3, O C P O C P O C P O C P I4 U4 1 1 0 RX RO 1 1 1 NOR SRO-I 3,4,5 2,6 4 4 2 I/C ,7 SRO-U 6 4 2 2 1 MAJ TS 2,3 0 2 2 I3 4 1 1 0 RX RO 1 1 1 NOR SRO-I 3,7 2,3,5 2 4 4 2 I/C

,6 SRO-U 6 4 5,7 2 2 1 MAJ TS 2,3 0 2 2 I4 4 1 1 0 RO RX 1 1 1 1 1 SRO-I NOR 4,5 3,5,6 2,6 4 4 2 I/C SRO-U 6 4 5,7 2 2 1 MAJ TS 2,3 0 2 2 1 1 0 RX RO 1 1 1 NOR SRO-I 4 4 2 I/C SRO-U 2 2 1 MAJ TS 0 2 2 Instructions:

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

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

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

12. For licensees that use the ATC operator primarily for monitoring plant parameters, the chief examiner may place SRO-I applicants in either the ATC or BOP position to best evaluate the SRO-I in manipulating plant controls.

Rev. 0 Appendix D Scenario Outline Form ES-D-1 Facility: South Texas Project Scenario No.: 1 Op-Test No.: LOT 21 NRC Examiners: Operators:

Initial Conditions:

• Unit 1 is at 100% Reactor Power. BOL (IC #190)

Turnover:

• The Crew will start FWBP #13 and place FWBP #12 in Auto.

• ESF DG #12 is OOS for Maintenance.

Event Malf. Event Event No. No. Type* Description 1 N/A BOP (N) Start FWBP #13 and place FWBP #12 in Auto.

(0 min)

SRO (TS 2 CM-39 Only) RT-8011 malfunction. Condition DARK BLUE loss of sample flow.

(10 min) 0 See 3 NOTE RO (C) EAB Battery Room Exhaust Fan 11C develops sheared shaft. When (17 min) below SRO (C, TS) RO tries to start Battery Room Exhaust Fan 11B the fan trips.

4 05-14-01 BOP (I) Main Steam Header Pressure Transmitter PT-557 Fails to an (27min) SRO (I) intermediate position. (Ramped in over 60 seconds) (LOT 19 Failed 0.4 High) 02-07-03 5 BOP (C) RCS Loop C Low Flow due to RCP 1C sheared shaft.

(35 min) 1 SRO (C) 01-12-02 Reactor does not trip until Crew manually opens Load Center 1 Breakers for Rod Drive MG Sets (Auto Rx Trip failure is initial condition of Lesson Plan)

(Critical Task) 6 08-06-03 ALL (M) SG 1C Loss of Feedwater inside containment. (10 minutes after Crew (45 min) trips Reactor) (LOT 19 Main Steam) 0.5 (Critical Task)

New 7 Failure RO (C) RCB Atmosphere Radiation Monitor Isolation Valves fail to (N/A No Malf. # SRO (C) automatically close. (Initial condition of Lesson Plan) min)

Lot* (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) 1

2. Abnormal events (2-4) 3

3. Major transients (1-2) 1

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

5. Entry into a contingency EOP with substantive actions (>1 per 0 scenario set)

6. Preidentified critical tasks (>2) 2 NOTE: Malfunction numbers for Event #3 - Cl_3V111VFM012TFShear - 1 & POSBBARV32733TCC - 1

Rev. 0 STP LOT-21 NRC Scenario #1 Description Initial Conditions: Unit 1 is at 100% Reactor Power. In preparation for an Engineering evaluation of FWBP #12, the Crew is to start FWBP #13 and place FWBP #12 in Auto after taking the watch.

ESF DG #12 is OOS for Maintenance.

Event 1: The BOP will start FWBP #13 and place FWBP #12 in Auto using 0POP02-FW-0001, Main Feedwater.

Event 2: RT-8011 malfunction. (Dark Blue) The crew will respond using 0POP04-RA-0001, Radiation Monitoring System Alarm Response. The SRO will address Tech Spec implications.

Event 3: EAB Battery Room Exhaust Fan 11C develops sheared shaft. When RO tries to start Battery Room Exhaust Fan 11B the fan trips. The crew will respond using 0POP09-AN-22M3, C3 and D3, BATT ROOM EXH FAN TRBL & BATT RM EXH FLOW LO. The SRO will address Tech Spec implications.

Event 4: Main Steam Header Pressure Transmitter PT-557 Fails to an intermediate position. The Crew will respond using 0POP04-FW-0002, Steam Generator Feed Pump Trip.

Event 5: RCP 1C develops a sheared shaft but the reactor does not trip. The reactor will trip from the control room when the Crew opens the 480 volt LC breakers that feed the Rod Control MG sets. The Crew will respond using 0POP05-EO-EO00, Reactor Trip or Safety Injection and transition to 0POP05-EO-ES01, Reactor Trip Response if an SI does not occur. (Critical Task)

Event 6: After the Reactor trip breakers are opened, a feedwater rupture will develop in containment on SG 1C. Leak will ramp in over 10 minutes. The Crew will transition back to or stay in 0POP05-EO-EO00, Reactor Trip or Safety Injection and then transition to 0POP05-EO-EO20, Faulted Steam Generator Isolation. (Critical Task)

Event 7: During performance of 0POP05-EO-EO00, Reactor Trip or Safety Injection, the crew will notice that the RCB Atmosphere Radiation Monitor Isolation Valves failed to automatically close and will have to use the RNO step to manually close the valves.

Rev. 0 STP LOT-21 NRC Scenario #1 Description Termination: Exit 0POP05-EO-EO20, Faulted Steam Generator Isolation.

Critical Tasks:

• CT-1, Manually Trip the Reactor

• CT-17, Isolate Faulted SG Source: New

Rev. 0 Appendix D Scenario Outline Form ES-D-1 Facility: South Texas Project Scenario No.: 2 Op-Test No.: LOT 21 NRC Examiners: Operators:

Initial Conditions:

• Unit 1 is at 100% Reactor Power. BOL (IC #190)

Turnover:

• The Crew is scheduled to remove Train C FHB HVAC Supply and Exhaust from service and place Train B in service due to a hot spot on the breaker for FHB HVAC Exhaust Fan 11C. Electrical Maintenance will perform a visual inspection of the breaker later in the shift.

• ESF DG #12 is OOS for Maintenance.

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

N/A RO (N) Secure FHB HVAC Train C Supply and Exhaust and start Train B (0 min) per 0POP02-HF-0001, FHB HVAC.

2 05-22-01 BOP (I) SG 1A controlling Steam pressure channel PT-0514 fails high. (LOT (5 min) SRO (I, TS) 19 Failed Low on SG 1D PT-0545) 1 3

01-07-07 RO (C) One Dropped Control Rod M12.

(15 min) SRO (C, TS) 1 4

10-14-01 ALL (M) Loss of Offsite Power, 345KV, causes a Reactor Trip.

(35 min) 1 5 04-09-01 RO (C) ECW Pump 1A fails to re-start on the LOOP forcing the crew to (N/A) 1 SRO (C) secure ESF DG #11. (Trips on restart after LOOP)

(Critical Task) 6 50-GD-06 1 ALL (C) ESF DG #13 trips. Crew will enter 0POP05-EO-EC00, Loss of All AC (N/A) Power. (Trips 10 minutes after LOOP)

(2 Critical Tasks)

• (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. Entry into a contingency EOP with substantive actions (>1 per 1 scenario set)

6. Preidentified critical tasks (>2) 3

Rev. 0 STP LOT-21 NRC Scenario #2 Description Initial Conditions: Unit 1 is at 100% Reactor Power. The Crew is scheduled to remove Train C FHB HVAC Supply and Exhaust from service and place Train B in service for maintenance later in the shift on Train C.

ESF DG #12 is OOS for Maintenance.

Event 1: The Crew will remove Train C FHB HVAC Supply and Exhaust from service and place Train B in service for maintenance later in the shift on Train C.

Event 2: SG 1A controlling Steam pressure channel PT-0514 fails high. The Crew will respond using 0POP04-FW-0001, Loss of Steam Generator Level Control. The SRO will address Tech Spec implications.

Event 3: The unit will experience a dropped Control Rod (M12). The Crew will respond using 0POP04-RS-0001, Control Rod Malfunction. The SRO will address Tech Spec implications.

Event 4: Loss of Offsite Power (LOOP) causes a Reactor Trip. The Crew will respond using 0POP05-EO-EO00, Reactor Trip or Safety Injection.

Event 5: On the LOOP, ECW PUMP 1A fails to re-start forcing the Crew to have to emergency stop ESF DG #11. (Critical Task)

Event 6: After transitioning to 0POP05-EO-ES01, Reactor Trip Response, ESF DG #13 trips.

This forces the crew to enter 0POP05-EO-EC00, Loss of All AC Power. (2 Critical Tasks)

Rev. 0 STP LOT 21 NRC Scenario #2 Description Termination: When the Crew energizes AC ESF bus Train C per Addendum 1, Transfer ESF Busses to the Emergency Transformer, of 0POP05-EO-EC00, Loss of All AC Power.

Critical Tasks:

• CT-9, Manually Trip Diesel Generator prior to an automatic Diesel Generator Trip

• EC00-H, Manually start the PDP and align seal injection during a loss of seal injection event.

• CT-24, Energize at least one AC emergency bus before transition out of EO00, unless the transition is to EC00, in which case the critical task must be performed before placing safeguards equipment handswitches in the PTL position.

Source: New

Rev. 0 Appendix D Scenario Outline Form ES-D-1 Facility: South Texas Project Scenario No.: 3 Op-Test No.: LOT 21 NRC Examiners: Operators:

Initial Conditions:

• Unit 1 is at 100% Reactor Power. BOL (IC #190)

Turnover:

• The Crew is scheduled to start ACW-OL Pump #11 and place ACW-OL Pump #12 in Auto for equipment rotation.

• ESF DG #12 is OOS for Maintenance.

Event Malf. Event Event No. No. Type* Description 1 N/A BOP (N) Start OL-ACW Pump #11 and place OL-ACW Pump #12 in (0 min) Auto.

2 04-01-01 RO (C) Component Cooling Water Pump 1A Trips.

(10 min) SRO (C, TS) 1 See NOTE 3 below SRO (TS SG 1A Main Steam Radiation Monitor RT-8046 failure.

(35 min) ONLY) 4 11-01-07 RO (R) An Open Loop System leak requires the Crew to perform a load (45 min) BOP (R) reduction.

0.2 SRO (R) 5 02-01-02 ALL (M) SBLOCA on LOOP B Cold Leg. (SBLOCA and LBLOCA were both (55 min) on LOT 19 exam but they were in different scenarios.)

.005 (Critical Task) 6 Multiple BOP (C) CCW fails to transfer to the RCFC coolers on Train B. Operator will (N/A) Malfunctio SRO (C) manually align CCW to RCFC coolers if RCB temperature 116°F.

n (Initial condition of Lesson Plan) 7 02-01-02 ALL (M) LBLOCA on LOOP B Cold Leg. (SBLOCA and LBLOCA were both (N/A) on LOT 19 exam but they were in different scenarios.)

0.4 (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) 1

2. Abnormal events (2-4) 4

3. Major transients (1-2) 2

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

5. Entry into a contingency EOP with substantive actions (>1 per 1 scenario set)

6. Preidentified critical tasks (>2) 2

Rev. 0 STP LOT-21 NRC Scenario #3 Description Initial Conditions: Unit 1 is at 100% Reactor Power. The Crew is to start OL-ACW Pump #11 and place OL-ACW Pump #12 in Auto for equipment rotation.

ESF DG #12 is OOS for Maintenance.

Event 1: The BOP will start OL-ACW Pump #11 and place OL-ACW Pump #12 in Auto using 0POP02-OC-0001, Open Loop Auxiliary Cooling System.

Event 2: Component Cooling Water Pump 1A trips. The Crew will respond using 0POP09-AN-02M3 A-5, CCW PUMP 1A(2A) TRIP. The SRO will address Tech Spec implications.

Event 3: A failure will occur on SG 1A Main Steam Line Radiation Monitor, RT-8046. The Crew will respond using 0POP04-RA-0001, Radiation Monitoring System Alarm Response. The SRO will address Tech Spec implications.

Event 4: An Open Loop System leak will occur. The Crew will respond using 0POP04-OC-0001, Loss of Open Loop Auxiliary Cooling Water. The failure will force the Crew to perform a load reduction.

Event 5: During the load reduction a SBLOCA will occur which will require the Crew to trip the Reactor and perform a Safety Injection. The Crew will respond using 0POP05-EO-EO00, Reactor Trip or Safety Injection and 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant.

(Critical Task)

Event 6: On the Safety Injection, CCW fails to transfer to the RCFC coolers on Train B. The Crew must manually align CCW to RCFC coolers if RCB temperature is 116°F.

Event 7: After resetting SI and the ESF Load Sequencers, a LBLOCA will occur. Because SI and the ESF Load Sequencers are reset the Crew will have to manually start the Containment Spray Pumps. (Critical Task)

Rev. 0 STP LOT-21 NRC Scenario #3 Description Termination: When the Crew starts at least 2 Containment Spray Pumps and ensures they are properly aligned with flow to containment.

Critical Tasks:

• CT-16, Manually Trip the Reactor Coolant Pumps

• CT-3, Manually Actuate Containment Cooling Source: New

Rev. 0 Appendix D Scenario Outline Form ES-D-1 Facility: South Texas Project Scenario No.: 4 Op-Test No.: LOT 21 NRC Examiners: Operators:

Initial Conditions:

• Unit 1 is at 100% Reactor Power. BOL (IC #190)

Turnover:

• The Crew will start CW Pump #13 and secure CW Pump #14.

• ESF DG #12 is OOS for Maintenance.

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

(0 min) N/A BOP (N) Start CW Pump #13 and Secure CW Pump #14.

2 (20 min) 02-19-03 RO (I) Controlling Channel of Pressurizer Pressure, PT-0457, fails low. (LOT SRO (I, TS) 19 and LOT 20 however, in both cases PT-0457 failed high.)

0.0 3 FT427TV (30 min) SP SRO (TS) Loop 2, Channel 1 RCS Flow Transmitter, FT-0427, fails low.

0.0 4 HCPD96 (35 min) 23REV RO (C) CRDM Vent Fan 11A Trouble.

1 SRO (C) 5 08-28-01 (45 min) 1 BOP (C) LPHD Pump #11 Trip.

SRO (C) 6 (60 min) 05-03-02 ALL (M) SG 1B Tube Rupture. (LOT 19 and LOT 20 however, in both cases the SG was ruptured and faulted.) (~300 GPM & Ramps in over 2 0.3 minute period.)

(3 Critical Tasks) 7 PV7485 (N/A) PV7489 BOP (C) Group 1 Steam Dumps fail to open. Crew will use SG PORVs to PV7493 SRO (C) perform SGTR cooldown. (Initial condition of Lesson Plan) 0.0

• (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) 1 2 Abnormal events (2-4) 4

3. Major transients (1-2) 1

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

5. Entry into a contingency EOP with substantive actions (>1 per 0 scenario set)

6. Preidentified critical tasks (>2) 3

Rev. 0 STP LOT-21 NRC Scenario #4 Description Initial Conditions: Unit 1 is at 100% Reactor Power. Due to an issue with Circulating Water Seal Water to CW Pump #14, the Crew is to secure CW Pump #14 after taking the watch.

ESF DG #12 is OOS for Maintenance.

Event 1: The BOP will start CW Pump #13 and secure CW Pump #14 using 0POP02-CW-0001, Circulating Water System Pump Operation.

Event 2: The controlling channel of Pressurizer Pressure, PT-0457, will fail low. The Crew will respond using 0POP04-RP-0001, Loss of Automatic Pressurizer Pressure Control. The SRO will address Tech Spec implications.

Event 3: Loop 2, Channel 1 RCS Flow Transmitter, FT-0427, will fail low. The Crew will respond using 0POP04-RP-0003, Failure of RCS Loop Flow Transmitter. The SRO will address Tech Spec implications.

Event 4: CRDM Vent Fan 11A will develop a problem that causes a reduction in air flow and require starting CRDM Vent Fan 11C. The Crew will respond using 0POP09-AN-22M1, F-2, CRDM VENT FAN TRBL.

Event 5: LPHD Pump #11 trips. The Crew will respond using 0POP04-CD-0001, Loss of Condensate Flow.

Event 6: A SGTR will occur on SG 1B. The Crew will respond using 0POP05-EO-EO00, Reactor Trip or Safety Injection, and transition to 0POP05-EO-EO30, Steam Generator Tube Rupture.

Event 7: The Steam Dumps will have an integral failure of the Group 1 cooldown valves. The crew will have to use the SG PORVs to perform the SGTR cooldown below 563°F in 0POP05-EO-EO30, Steam Generator Tube Rupture.

Rev. 0 STP LOT-21 NRC Scenario #4 Description Termination: After the crew secures HHSI pumps Critical tasks:

• CT-18, Isolate a Ruptured SG

• CT-19, Depressurize RCS to SI Termination Criteria

• CT-20, Terminate SI Source: New