ML20282A787

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ST-2020-07 Final Outlines
ML20282A787
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 07/29/2020
From: Greg Werner
Operations Branch IV
To:
South Texas
References
Download: ML20282A787 (35)
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Text

ES-401, Page 40 of 52 ES-401 PWR Examination Outline Form ES-401-2 Facility: STP Date of Exam: July 2020 Tier Group RO K/A Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

Total A2 G*

Total

1.

Emergency and Abnormal Plant Evolutions 1

2 3

3 3

4 3

18 3

3 6

2 2

1 2

1 2

1 9

2 2

4 Tier Totals 4

4 5

4 6

4 27 5

5 10

2.

Plant Systems 1

3 2

3 3

2 2

2 3

3 2

3 28 2

3 5

2 1

0 1

1 1

1 1

1 1

1 1

10 1

1 1

3 Tier Totals 4

2 4

4 3

3 4

3 4

3 4

38 4

4 8

3. Generic Knowledge and Abilities Categories 1

2 3

4 10 1

2 3

4 7

3 2

2 3

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.

ES-401 2

Form ES-401-2

ES-401, Page 41 of 52 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/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 R

EK1.06 Knowledge of the operational implications of the following concepts as they apply Reactor Trip: relationship of emergency feedwater flow to S/G and decay heat removal following reactor trip 3.7 74 000008 (APE 8) Pressurizer Vapor Space Accident / 3 S

AA2.26 Ability to determine or interpret the following as they apply to a PZR Vapor Space accident: Probable PZR steam space leakage paths other than PORV or code safety 3.4 77 000009 (EPE 9) Small Break LOCA / 3 R

EK3.21 Knowledge of the reasons for the following responses as the apply to the Small Break LOCA: Actions contained in the EOPs for a small break LOCA 4.2 52 000011 (EPE 11) Large Break LOCA / 3 R

EK2.02 Knowledge of the interrelations between a Large Break LOCA and the following: Pumps 2.6 53 000015 (APE 15) Reactor Coolant Pump Malfunctions / 4 R

AA1.02 Ability to operate and / or monitor the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC flow): RCP oil reservoir level and alarm indicators 2.8 45 000022 (APE 22) Loss of Reactor Coolant Makeup / 2 R 2.1.19 Ability to use plant computers to evaluate system or component status.

3.9 24 000025 (APE 25) Loss of Residual Heat Removal System / 4 S 2.4.41 Knowledge of the emergency action level thresholds and classifications.

4.6 83 000026 (APE 26) Loss of Component Cooling Water / 8 R

AA1.05 Ability to operate and / or monitor the following as they apply to the Loss of Component Cooling Water: The CCWS Surge Tank, including level control and level alarms, and radiation alarms.

3.1 72 000027 (APE 27) Pressurizer Pressure Control System Malfunction / 3 R

AK3.03 Knowledge of the reasons for the following responses as the apply to the PZR PCS Malfunction: Actions contained in EOP for PZR PCS malfunction.

3.7 42 000029 (EPE 29) Anticipated Transient Without Scram / 1 R

EK2.06 Knowledge of the interrelations between an ATWS and the following:

Breakers, relays, and disconnects 2.9* 47 000038 (EPE 38) Steam Generator Tube Rupture / 3 S 2.2.25 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits 4.2 99 000040 (APE 40; BW E05; CE E05; W E12)

Steam Line RuptureExcessive Heat Transfer / 4 R

2.1.20 Ability to interpret and execute procedure steps.

4.6 54 000054 (APE 54; CE E06) Loss of Main Feedwater /4 R

AA2.03 Ability to determine or interpret the following as they apply to a Loss of Main Feedwater (MFW): Conditions and reasons for AFW pump startup 4.1 27 000055 (EPE 55) Station Blackout / 6 R

EK3.01 Knowledge of the reasons for the following responses as the apply to the SBO: Length of time for which battery capacity is designed 2.7 55

ES-401, Page 42 of 52 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/SRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*

K/A Topic(s)

IR 000056 (APE 56) Loss of Offsite Power / 6 R

G2.1.32 Ability to explain and apply system limits and precautions 3.8 4

000057 (APE 57) Loss of Vital AC Instrument Bus / 6 R

AA1.04 Ability to operate and / or monitor the following as they apply to the Loss of Vital AC Instrument Bus: RWST and VCT valves 3.5 31 000058 (APE 58) Loss of DC Power / 6 R

AA2.02 Ability to determine and interpret the following as they apply to the Loss of DC Power: 125V dc bus voltage, low/critical low, alarm 3.3* 19 000062 (APE 62) Loss of Nuclear Service Water / 4 R

AA2.06 Ability to determine and interpret the following as they apply to the Loss of Nuclear Service Water: The length of time after the loss of SWS flow to a component before that component may be damaged 2.8* 56 000065 (APE 65) Loss of Instrument Air / 8 R

AA2.08 Ability to determine and interpret the following as they apply to the loss of instrument air: Failure modes of air-operated equipment 2.9* 73 000077 (APE 77) Generator Voltage and Electric Grid Disturbances / 6 R

S AK1.03 Knowledge of the operational implications of the following concepts as they apply to Generator Voltage and Electric Grid Disturbances: Under-excitation AA2.05 Ability to determine or interpret the following as they apply to Generator Voltage and Electric Grid Disturbances: Operational status of offsite circuit 3.3 3.8 25 90 (W E04) LOCA Outside Containment / 3 R

EK2.1 Knowledge of the interrelations between the (LOCA outside Containment) and the following: Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features 3.5 48 (W E11) Loss of Emergency Coolant Recirculation / 4 S

EA2.1 Ability to determine or interpret the following as they apply to Loss of Emergency Coolant Recirculation: Facility conditions and selection of appropriate procedures during abnormal and emergency conditions 4.2 89 (BW E04; W E05) Inadequate Heat TransferLoss of Secondary Heat Sink / 4 S 2.4.21 Knowledge of the parameters and 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.

4.6 78 K/A Category Totals:

2 3

3 3 4/3 3/3 Group Point Total:

18/6

ES-401, Page 43 of 52 ES-401 3

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

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*

K/A Topic(s)

IR 000001 (APE 1) Continuous Rod Withdrawal / 1 Not sampled 000003 (APE 3) Dropped Control Rod / 1 R

AK3.08 Knowledge of the reasons for the following responses as they apply to the (Dropped Control Rod):

Criteria for inoperable control rods 3.1 41 000005 (APE 5) Inoperable/Stuck Control Rod / 1 Not sampled 000024 (APE 24) Emergency Boration / 1 R

AA2.02 Ability to determine and interpret the following as they apply to the Emergency Boration: When use of manual boration valve is needed 3.9 37 000028 (APE 28) Pressurizer (PZR) Level Control Malfunction / 2 R

AA1.01 Ability to operate and /

or monitor the following as they apply to the PZR Level Control Malfunction: PZR level reactor protection bistables 3.8* 23 000032 (APE 32) Loss of Source Range Nuclear Instrumentation / 7 Not sampled 000033 (APE 33) Loss of Intermediate Range Nuclear Instrumentation / 7 Not sampled 000036 (APE 36; BW/A08) Fuel-Handling Incidents / 8 S

AA2.03 Ability to determine and interpret the following as they apply to the Fuel Handling Incidents: Magnitude of potential release 4.2* 86 000037 (APE 37) Steam Generator Tube Leak / 3 R

AK1.02 Knowledge of the operational implications of the following concepts as they apply to Steam generator Tube Leak: Leak rate versus pressure drop 3.5 35 000051 (APE 51) Loss of Condenser Vacuum / 4 Not sampled 000059 (APE 59) Accidental Liquid Radwaste Release / 9 S 2.4.30 Knowledge of events related to system operation

/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission operator 4.1 82 000060 (APE 60) Accidental Gaseous Radwaste Release / 9 Not sampled 000061 (APE 61) Area Radiation Monitoring System Alarms

/ 7 Not sampled

ES-401, Page 44 of 52 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*

K/A Topic(s)

IR 000067 (APE 67) Plant Fire On Site / 8 R

AK3.04 Knowledge of the reasons for the following responses as they apply to the plant fire on Site: Actions contained in EOP for plant fire on site 3.3 40 000068 (APE 68; BW A06) Control Room Evacuation / 8 R

AK2.01 Knowledge of the interrelations between the control room evacuation and the following: Auxiliary shutdown panel layout 3.9 39 000069 (APE 69; W E14) Loss of Containment Integrity / 5 S

AA2.01 Ability to determine and interpret the following as they apply to the Loss of Containment Integrity:

Verification of automatic and manual means of restoring integrity 4.4 94 000074 (EPE 74; W E06 & E07) Inadequate Core Cooling /

4 Not sampled 000076 (APE 76) High Reactor Coolant Activity / 9 S 2.2.38 Knowledge of conditions and limitations in the facility license.

4.5 97 000078 (APE 78*) RCS Leak / 3 R

2.2.42 Ability to recognize system parameters that are entry-level conditions for Technical Specifications 3.9 38 (W E01 & E02) Rediagnosis & SI Termination / 3 R

E02 EK1.2 Knowledge of the operational implications of the following concepts as they apply to the (SI termination):

Normal, abnormal, and emergency operating procedures associated with SI termination.

3.4 5

(W E13) Steam Generator Overpressure / 4 Not sampled (W E15) Containment Flooding / 5 Not sampled (W E16) High Containment Radiation /9 Not sampled (BW A01) Plant Runback / 1 N/A for this design type (BW A02 & A03) Loss of NNI-X/Y/7 N/A for this design type (BW A04) Turbine Trip / 4 N/A for this design type (BW A05) Emergency Diesel Actuation / 6 N/A for this design type (BW A07) Flooding / 8 N/A for this design type (BW E03) Inadequate Subcooling Margin / 4 N/A for this design type (BW E08; W E03) LOCA CooldownDepressurization / 4 R

EA2.2 Ability to determine and interpret the following as they apply to the (LOCA Cooldown and Depressurization):

Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments 3.5 57 (BW E09; CE A13**; W E09 & E10) Natural Circulation/4 Not sampled

ES-401, Page 45 of 52 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*

K/A Topic(s)

IR (BW E13 & E14) EOP Rules and Enclosures N/A for this design type (CE A11**; W E08) RCS OvercoolingPressurized Thermal Shock / 4 Not sampled (CE A16) Excess RCS Leakage / 2 N/A for this design type (CE E09) Functional Recovery N/A for this design type (CE E13*) Loss of Forced Circulation/LOOP/Blackout / 4 N/A for this design type K/A Category Point Totals:

2 1

2 1 2/2 1/2 Group Point Total:

9/4

ES-401, Page 46 of 52 ES-401 4

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO/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 R

A3.03 Ability to monitor automatic operation of the RCP, including: Seal DP 3.2 62 004 (SF1; SF2 CVCS) Chemical and Volume Control R

R K4.01 Knowledge of CVCS design feature(s) and/or interlock(s) which provide for the following: Oxygen control in the RCS A2.11 Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of IAS 2.8 3.6 75 46 005 (SF4P RHR) Residual Heat Removal R

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

RHR Flow rate K3.01 Knowledge of the effect that a loss or malfunction of the RHRS will have on the following: RCS 3.3 3.9 63 30 006 (SF2; SF3 ECCS) Emergency Core Cooling R

S K6.18 Knowledge of the effect of a loss or malfunction on the following will have on the ECCS: Subcooling Margin indicators 2.2.25 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits 3.6 4.2 58 91 007 (SF5 PRTS) Pressurizer Relief/Quench Tank R

K5.02 Knowledge of the operational implications of the following concepts as the apply to the PRTS: Method of forming a steam bubble in the PZR 3.1 29 008 (SF8 CCW) Component Cooling Water R

K4.02 Knowledge of CCWS design feature(s) and/or interlock(s) which provide for the following: Operation of the surge tank, including the associated valves and controls 2.9 22 010 (SF3 PZR PCS) Pressurizer Pressure Control R

K3.02 Knowledge of the effect that a loss or malfunction of the PZR PCS will have on the following: RPS 4.0 21 012 (SF7 RPS) Reactor Protection R

R K2.01 Knowledge of bus power supplies to the following: RPS channels, components, and interconnections G2.1.28 Knowledge of the purpose and function of major system components and controls 3.3 4.1 33 20

ES-401, Page 47 of 52 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO/SRO)

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

K/A Topic(s)

IR 013 (SF2 ESFAS) Engineered Safety Features Actuation S

R 2.2.42 Ability to recognize system parameters that are entry-level conditions for Technical Specifications.

A2.03 Ability to (a) predict the impacts of the 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 operations: Rapid depressurization 3.9 4.7 69 88 022 (SF5 CCS) Containment Cooling R R

K1.01 Knowledge of the physical connections and/or cause-effect relationships between the CCS and the following systems: SWS/cooling system A4.05 Ability to manually operate and/or monitor in the control room: Containment readings, of temperature, pressure, and humidity.

3.5 3.8 34 18 025 (SF5 ICE) Ice Condenser N/A for this design 026 (SF5 CSS) Containment Spray S

R A2.08 Ability to (a) predict the impacts of the following malfunctions or operations on the CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Safe securing of containment spray, when it can be done.

2.2.44 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions 3.7 4.2 87 49 039 (SF4S MSS) Main and Reheat Steam R

R K1.02 Knowledge of the physical connections and/or cause-effect relationships between the MRSS and the following systems: atmospheric relief dump valves AA2.03 Ability to (a) predict the impacts of the following malfunctions or operations on the MRSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Indications and alarms for main steam and area radiation monitors (during SGTR) 3.3 3.4 17 59

ES-401, Page 48 of 52 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO/SRO)

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

K/A Topic(s)

IR 059 (SF4S MFW) Main Feedwater R

K1.04 Knowledge of the physical connections and/or cause-effect relationships between the MFW and the following systems: S/Gs water level control system 3.4 36 061 (SF4S AFW)

Auxiliary/Emergency Feedwater R

R K3.01 Knowledge of the effect that a loss or malfunction of the AFW system will have on the following: RCS A3.02 Ability to monitor automatic operation of the AFW, including: RCS cooldown during AFW operations 4.4 4.0 16 15 062 (SF6 ED AC) AC Electrical Distribution R

S K4.10 Knowledge of ED AC design feature(s) and/or interlock(s) which provide for the following: Uninterruptible power sources.

G2.2.40 Ability to apply Technical Specifications for a system.

3.1 4.7 26 95 063 (SF6 ED DC) DC Electrical Distribution R

A1.01 Ability to predict and/or monitor changes in parameters associated with operating the DC electrical system controls including: Battery capacity as it is affected by discharge rate 2.5 14 064 (SF6 EDG) Emergency Diesel Generator R

S K6.07 Knowledge of the effect of a loss or malfunction on the following will have on the EDG: Air receivers 2.2.37 Ability to determine operability and/or availability of safety related equipment 2.7 4.6 32 92 073 (SF7 PRM) Process Radiation Monitoring R

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

67 076 (SF4S SW) Service Water R

A2.02 Ability to (a) predict the impacts of the 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: Service water header pressure 2.7 13 078 (SF8 IAS) Instrument Air R

K2.01 Knowledge of bus power supplies to the following: Instrument air compressor 2.7 71 103 (SF5 CNT) Containment R

R A3.01 Ability to monitor automatic operation of the CNT system, including:

Containment isolation A4.03 Ability to manually operate and/or monitor in the control room: ESF slave relays 3.9 2.7 12 64 053 (SF1; SF4P ICS*) Integrated Control N/A for this Design

ES-401, Page 49 of 52 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO/SRO)

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

K/A Topic(s)

IR K/A Category Point Totals:

3 2 3 3 2 2 2 3/2 3 2 3/3 Group Point Total:

28/5

ES-401, Page 50 of 52 ES-401 5

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 2 (RO/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 R

K5.97, Knowledge of the following operational implications as they apply to the CRDS: Relationship of Tave to Tref.

3.3 11 002 (SF2; SF4P RCS) Reactor Coolant Not sampled 011 (SF2 PZR LCS) Pressurizer Level Control R

A2.03 Ability to (a) predict the impacts of the following malfunctions or operations on the PZR LCS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of PZR level 3.8 44 014 (SF1 RPI) Rod Position Indication S 2.2.12 Knowledge of surveillance procedures 4.1 93 015 (SF7 NI) Nuclear Instrumentation Not sampled 016 (SF7 NNI) Nonnuclear Instrumentation R

K1.12 Knowledge of the physical connections and/or cause effect relationships between the NNI system and the following systems: S/G 3.5* 10 017 (SF7 ITM) In-Core Temperature Monitor R

A4.02 Ability to manually operate and/or monitor in the control room: Temperature values used to determine RCS/RCP operation during inadequate core cooling (i.e., if applicable, average of five highest values) 3.8 60 027 (SF5 CIRS) Containment Iodine Removal Not sampled 028 (SF5 HRPS) Hydrogen Recombiner and Purge Control R 2.4.6 Knowledge of EOP mitigation strategies.

3.7 61 029 (SF8 CPS) Containment Purge Not sampled 033 (SF8 SFPCS) Spent Fuel Pool Cooling Not sampled 034 (SF8 FHS) Fuel-Handling Equipment S

A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the FHS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Dropped fuel element 4.4 98 035 (SF 4P SG) Steam Generator R

K6.02 Knowledge of the effect of a loss or malfunction on the following will have on the S/GS: secondary porv 3.1 9

041 (SF4S SDS) Steam Dump/Turbine Bypass Control R

K3.04 Knowledge of the effect that a loss or malfunction of the SDS system will have on the following: Reactor Power 3.5 8

045 (SF 4S MTG) Main Turbine Generator Not sampled 055 (SF4S CARS) Condenser Air Removal Not sampled

ES-401, Page 51 of 52 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 2 (RO/SRO)

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

K/A Topic(s)

IR 056 (SF4S CDS) Condensate Not sampled 068 (SF9 LRS) Liquid Radwaste S

A2.04 Ability to (a) predict the impacts of the following malfunctions or operations on the LRS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of automatic isolation 3.3 96 071 (SF9 WGS) Waste Gas Disposal R

K4.04 Knowledge of the design features and/or interlocks which provide for the following: Isolation of waste gas release tanks 2.9 2

072 (SF7 ARM) Area Radiation Monitoring R

A3.01 Ability to monitor automatic operation of the ARM system, including:

Changes in ventilation alignment 2.9 7

075 (SF8 CW) Circulating Water Not sampled 079 (SF8 SAS**) Station Air Not sampled 086 Fire Protection R

A1.03 Ability to predict and/or monitor changes in parameters to prevent exceeding design limits associated with operating the Fire Protection System controls, including: Fire water storage tank level 3.0 6

050 (SF 9 CRV*) Control Room Ventilation N/A until rev3 of KA catalogs K/A Category Point Totals:

1 0 1 1 1 1 1 1/2 1 1 1/1 Group Point Total:

10/3

ES-401, Page 52 of 52 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

1. Conduct of Operations 2.1.40 Knowledge of refueling administrative requirements.

2.8 68 2.1.21 Ability to verify the controlled procedure copy 3.5 66 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc.

3.8 85 2.1.36 Knowledge of procedures and limitations involved in core alterations 4.1 84 Subtotal 2

2

2. Equipment Control 2.2.3 Knowledge of the design, procedural, and operational differences between units 3.8 1

2.2.6 Knowledge of the process for making changes to procedures 3.0 3

2.2.7 Knowledge of the process for conducting special or infrequent tests 2.9 51 2.2.19 Knowledge of maintenance work order requirements 3.4 80 2.2.21 Knowledge of pre-and post-maintenance operability requirements 4.1 100 Subtotal 3

2

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

2.9 28 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions 3.5 65 2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high radiation areas, aligning filters, etc.

3.8 81 Subtotal 2

1

4. Emergency Procedures/Plan 2.4.6 Knowledge of EOP mitigation strategies.

3.7 50 2.4.9 Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

3.8 70 2.4.46 Ability to verify that the alarms are consistent with the plant conditions.

4.2 43 2.4.4 Knowledge of SRO responsibilities in emergency plan implementation.

4.5 79 2.4.20 Knowledge of the operational implications of EOP warnings, cautions, and notes.

4.3 76 Subtotal 3

2 Tier 3 Point Total 10 10 7

7

ES-401, Page 53 of 52 ES-401 Record of Rejected K/As Form ES-401-4 Tier/Group Randomly Selected K/A Reason for Rejection 1/1 RO APE 26 AA1.03 This KA tests the ability to operate and / or monitor the following as they apply to the Loss of Component Cooling Water: SWS as a backup to the CCWS. Essential Cooling Water does not act as a backup to Component Cooling Water at STP. Therefore, this KA was replaced with APE 26 AA1.05.

1/1 RO APE 27 AK3.01 This KA tests the knowledge of the reasons for the following responses as they apply to the PZR PCS Malfunction:

Isolation of PZR spray following loss of PZR heaters. This is neither an automatic feature nor an operator response if this occurs. Therefore, this KA was replaced with APE 27 AK3.03.

2/1 RO 004 A2.20 This KA tests the ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or predations: Shifting demineralizer while the divert valve is lined up to VCT. When shifting demineralizers at STP, flushing to the RHUT is always accomplished first. There is no guidance when this is not done correctly. Therefore, this KA was replaced with 004 A2.11.

2/1 RO 022 A4.03 This KA tests the ability to manually operate and/or monitor in the control room: Dampers in the CCS. We do not operate any RCFC dampers in the control room. Therefore, this KA was replaced with 022 A4.05.

2/1 RO 062 K4.03 This KA tests the knowledge of ED AC design feature(s) and/or interlock(s) which provide for the following: Interlocks between automatic bus transfer and breakers. STP does not use automatic bus transfer devices. Therefore, this KA was replaced with 062 K4.10.

2/2 RO 001 K5.12 This KA tests the knowledge of the following operational implications as they apply to the CRDS: Effects on power of inserting axial shaping rods. STP does not use axial shaping rods. Therefore, this KA was replaced with 001 K5.97.

2/1 RO 006 K3.02 Changed to system 005 K3.01 because the program office is changing their interpretation of oversampling in one system to include RO and SRO topics-so if you have two topics already on the RO exam for one system then you must move a random sample of the SRO to another system topic. I have indicated these changes in purple text for now.

2/1 RO 013 K1.18 Changed to system 022 K1.01 because the program office is changing their interpretation of oversampling in one system to include RO and SRO topics-so if you have two topics already on the RO exam for one system then you must move a random sample of the SRO to another system topic. I have indicated these changes in purple text for now.

ES-401, Page 54 of 52 Tier/Group Randomly Selected K/A Reason for Rejection 2/1 SRO 061 G2.2.40 Changed to system 062 G2.2.40 because the program office is changing their interpretation of oversampling in one system to include RO and SRO topics-so if you have two topics already on the RO exam for one system then you must move a random sample of the SRO to another system topic. I have indicated these changes in purple text for now.

2/1 SRO 026 A2.07 This KA tested the ability to predict the loss of CS pump suction, possibly caused by clogged sump screen, pump inlet high temperature exceeded, cavitation, voiding, or sump level below cutoff (interlock) limit, and use a procedure to correct, control, or mitigate the consequences. STP does not have procedural guidance for these malfunctions on CS pump operation. Therefore, this KA was replaced with 026 A2.08.

2/2 SRO 034 A2.02 This KA tested the ability to predict the consequences of a dropped cask, and use a procedure to correct, control, or mitigate the consequences. STP does not analyze for a dropped cask since a single failure proof crane is used.

Therefore, this KA was replaced with 034 A2.01.

Rev. 2 ES-301 Administrative Topics Outline Form ES-301-1 Facility: South Texas Project Date of Examination: 7-13-20 Examination Level: RO SRO Operating Test Number: LOT 24 NRC Administrative Topic (see Note)

Type Code*

Describe activity to be performed Conduct of Operations A1 K/A Importance: 3.8 N,R 2.1.19 Ability to use computers to evaluate system and component status.

Calculate Sub-Cooling Margin Conduct of Operations A2 K/A Importance: 3.9 N,R 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

Calculate Time to Boil on Loss of all RHR during Mid-Loop Equipment Control A3 K/A Importance: 4.1 M,R 2.2.13 Knowledge of Tagging and Clearance Procedures.

Prepare ECO for Main Turbine Lube Oil Cooler Radiation Control A4 K/A Importance: 3.5 M,R 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions.

Determine RWP Requirements for Work in RRA (SFP) 0BEmergency Plan N/A N/A 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. 2 ES-301 Administrative Topics Outline Form ES-301-1 Facility: South Texas Project Date of Examination: 7-13-20 Examination Level: RO SRO Operating Test Number: LOT 24 NRC Administrative Topic (see Note)

Type Code*

Describe activity to be performed Conduct of Operations A5 K/A Importance: 3.9 N,R 2.1.19 Ability to use computers to evaluate system and component status.

Calculate Sub-Cooling Margin and Apply TS Conduct of Operations A6 K/A Importance: 4.7 D,R 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

Review RCS Inventory and Determine TS Applicability Equipment Control A7 K/A Importance: 4.3 M,R 2.2.13 Knowledge of Tagging and Clearance Procedures.

Review Faulted ECO for Main Turbine Lube Oil Cooler Radiation Control A8 K/A Importance: 3.7 M,R 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.

Determine Personnel Exposure Limits (E-Plan) 1BEmergency Plan A9 K/A Importance: 4.6 M,R 2.4.41 Knowledge of the emergency action level thresholds and classifications.

Determine EAL 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. 2 STP LOT-24 NRC Admin JPM Description RO (A1)

Calculate Sub-Cooling Margin Demonstrate the ability to use QDPS data to manually calculate sub-cooling margin.

(A2)

Calculate Time to Boil on Loss of all RHR During Mid-Loop Demonstrate the ability, using a procedure graph, to calculate time to boil in the RCS during a loss of all RHR at mid-loop.

(A3)

Prepare ECO for Main Turbine Lube Oil Cooler Demonstrate the ability to prepare an ECO for equipment maintenance.

(A4)

Determine RWP Requirements for Work in RRA (SFP)

Demonstrate the ability to extract necessary information from survey maps and RWP to perform work in the RRA.

SRO (A5)

Calculate Sub-Cooling Margin and Apply TS Demonstrate the ability to use QDPS data to manually calculate sub-cooling margin and apply TS for a failure of QDPS.

(A6)

Review RCS Inventory and Determine TS Applicability Demonstrate the ability to review a surveillance and apply Technical Specifications when it is determined that acceptance criteria of the surveillance is not met.

(A7)

Review faulted ECO for Main Turbine Lube Oil Cooler Demonstrate the ability perform a technical review of an ECO for equipment maintenance.

(A8)

Determine Personnel Exposure Limits (E-Plan)

Demonstrate the ability to determine personnel exposure margins during an emergency and who authorizes them.

(A9)

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

Rev. 2 Page 1 of 5 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: South Texas Project Date of Examination: 7-13-20 Exam Level: RO SRO-I SRO-U Operating Test No.: LOT 24 NRC Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System / JPM Title Type Code*

Safety Function

a. (S1) Recover a Mis-Aligned Control Rod KA: 001 A4.06 (2.9/3.2)

M,S 1

b. (S2) Manually Load an ESF Bus KA: 064 A4.06 (3.9/3.9)

A,E,EN,M,S 6

c. (S3) Depress RCS during SGTR KA: 010 A2.02 (3.9/3.9)

A,D,E,L,S 3

d. (S4) Loss of Circulating Water Pump KA: 075 A2.02 (2.5/2.7)

A,N,S 8

e. (S5) Containment Spray Pump Performance Test KA: 026 A2.08 (3.2/3.7)

M,S 5

f. (S6) Transfer MFW Control from LPFRV to MFRV KA: 059 A4.08 (3.0/2.9)

D,S 4S

g. (S7) Respond to RCB Rad Monitor Alarm KA: 073 A4.01 (3.9/3.9)

A,D,S 7

h. (S8) Lower SI Accumulator Level KA: 006 A1.13 (3.5/3.7)

D,EN,S 2

In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i. (P1) MCC Power Restoration per 0POP04-ZO-0001 KA: 062 A4.04 (2.6/2.7)

E,L,N 6

j. (P2) Place RWST on Recirc followed by an SI KA: 006 A4.02 (4.0/3.8)

A,D,R 2

k. (P3) Verify Containment Isolation Phase B KA: 103 A2.03 (3.5/3.8)

D,E,L,R 5

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 (C)ontrol Room (D)irect from Bank (E)mergency or abnormal in-plant (EN) gineered Safety Features (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

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

Rev. 2 Page 2 of 5 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: South Texas Project Date of Examination: 7-13-20 Exam Level: RO SRO-I SRO-U Operating Test No.: LOT 24 NRC Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System / JPM Title Type Code*

Safety Function

a. (S1) Recover a Mis-Aligned Control Rod KA: 001 A4.06 (2.9/3.2)

M,S 1

b. (S2) Manually Load an ESF Bus KA: 064 A4.06 (3.9/3.9)

A,E,EN,M,S 6

c. (S3) Depress RCS during SGTR KA: 010 A2.02 (3.9/3.9)

A,D,E,L,S 3

d. (S4) Loss of Circulating Water Pump KA: 075 A2.02 (2.5/2.7)

A,N,S 8

e. (S5) Containment Spray Pump Performance Test KA: 026 A2.08 (3.2/3.7)

M,S 5

f. (S6) Transfer MFW Control from LPFRV to MFRV KA: 059 A4.08 (3.0/2.9)

D,S 4S

g. (S7) Respond to RCB Rad Monitor Alarm KA: 073 A4.01 (3.9/3.9)

A,D,S 7

h.

In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i. (P1) MCC Power Restoration per 0POP04-ZO-0001 KA: 062 A4.04 (2.6/2.7)

E,L,N 6

j. (P2) Place RWST on Recirc followed by an SI KA: 006 A4.02 (4.0/3.8)

A,D,R 2

k. (P3) Verify Containment Isolation Phase B KA: 103 A2.03 (3.5/3.8)

D,E,L,R 5

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 (C)ontrol Room (D)irect from Bank (E)mergency or abnormal in-plant (EN) gineered Safety Features (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

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

Rev. 2 Page 3 of 5 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: South Texas Project Date of Examination: 7-13-20 Exam Level: RO SRO-I SRO-U Operating Test No.: LOT 24 NRC Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System / JPM Title Type Code*

Safety Function

a. (S1) Recover a Mis-Aligned Control Rod KA: 001 A4.06 (2.9/3.2)

M,S 1

b. (S2) Manually Load an ESF Bus KA: 064 A4.06 (3.9/3.9)

A,E,EN,M,S 6

c. (S3) Depress RCS during SGTR KA: 010 A2.02 (3.9/3.9)

A,D,E,L,S 3

d.
e.
f.
g.
h.

In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i.
j. (P2) Place RWST on Recirc followed by an SI KA: 006 A4.02 (4.0/3.8)

A,D,R 2

k. (P3) Verify Containment Isolation Phase B KA: 103 A2.03 (3.5/3.8)

D,E,L,R 5

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 (C)ontrol Room (D)irect from Bank (E)mergency or abnormal in-plant (EN) gineered Safety Features (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

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

Rev. 2 Page 4 of 5 STP LOT-24 NRC Systems JPM Description Control Room Systems JPMs (S1)

Recover a Mis-Aligned Control Rod Demonstrate the ability to control reactor core reactivity while recovering a mis-aligned control rod in accordance with 0POP04-RS-0001, Control Rod Malfunction.

(S2)

Manually Load an ESF Bus 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 13.8KV or 4.16KV Bus. This is an Alternate Path JPM.

(S3)

Depress RCS During SGTR Demonstrate the ability to depress the RCS after a SGTR in accordance with 0POP05-EO-EO30, Steam Generator Tube Rupture. This is an Alternate Path JPM.

(S4)

Loss of Circulating Water Pump Demonstrate the ability to operate the Circulating Water System after a trip of a Circulating Water Pump in accordance with 0POP04-CW-0001, Loss of Circulating Water Flow. This is an Alternate Path JPM.

(S5)

Containment Spray Pump Performance Test Demonstrate the ability to operate the Containment Spray Pumps in accordance with 0POP07-CS-0001, Containment Spray Pump 1A(2A) Functional Test.

(S6)

Transfer MFW Control from LPFRV to MFRV Demonstrate the ability to operate Main Feedwater control valves in accordance with 0POP03-ZG-0005, Plant Startup to 100%.

(S7)

Respond to RCB Rad Monitor Alarm Demonstrate the ability to operate the RCB Supplemental Purge System after a Radiation Monitor high alarm in accordance with 0POP04-RA-0001, Radiation Monitoring System Alarm Response. This is an Alternate Path JPM.

(S8)

Lower Safety Injection Accumulator Level Demonstrate the ability lower Safety Injection Accumulator level in accordance with 0POP02-SI-0001, Safety Injection Accumulators.

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

Rev. 2 Page 5 of 5 STP LOT-24 NRC Systems JPM Description In Plant Systems JPMs (P1)

MCC Power Restoration per 0POP04-ZO-0001, Control Room Evacuation Demonstrate the ability to restore power to vital MCCs after a control room evacuation in accordance with 0POP04-ZO-0001, Control Room Evacuation.

(P2)

Place RWST on Recirc followed by an Safety Injection Demonstrate the ability to monitor the Safety Injection System alignments in order to prevent equipment damage in accordance with 0POP02-FC-0001, Spent Fool Pool Cooling and Cleanup System. This is an Alternate Path JPM.

(P3)

Verify Containment Isolation Phase B Demonstrate the ability to locally close Component Cooling Water valves associated with Containment Isolation Phase B in accordance with 0POP05-EO-EC00, Loss of all AC Power.

LOT 24 NRC OP-TEST SCENARIO #1 Rev 1 Page 1 of 3 SCENARIO OUTLINE Facility: South Texas Project Scenario No.: 1 Op-Test No.: LOT 24 NRC Examiners:

Operators:

Initial Conditions:

  • Mode 1 at 100% Power, MOL
  • 25-30 & 120-150 GPM Letdown Orifices are in service.

Turnover:

  • AFW Pump #11 is out of service.

Critical Tasks:

E6 - CT13; Manually Trip Main Turbine

  • E7 - CT46; Establish RCS Bleed and Feed Event No.

Malf.

No.

Event Type*

Event Description 1

(0 min)

N/A RO (N)

Close the 25-30 GPM Letdown Orifice.

2 (10 min)

CM_RT804 6TVCLRP 1

SRO (TS ONLY)

SG 1A Main Steam Radiation Monitor RT-8046 failure.

3 (20 min) 04-03-02 0

RO (C)

SRO (C)

RCP 1B Thermal Barrier Isolation Valve goes closed after a CCW System perturbation.

4 (33 min) 05-12-04 0

BOP (I)

SRO (I & TS)

SG 1D Controlling NR level channel fails low. LT-0549 5

(43 min) 08-28-01 True BOP (C)

SRO (C)

LPHD Pump #11 Trip 6

(52 min)

Multiple All (M)

Main Generator Output Breaker trips open causing an automatic or manual RX Trip.

7 (N/A)

Multiple RO (C)

SRO (C)

On the RX Trip the Main Turbine fails to auto trip and there is an inadvertent FWI.

(Critical Task) 8 (N/A) 10-11-02 True RO (C)

SRO (C)

Train B 4160V bus lockout. (On Reactor Trip) 9 (N/A)

Multiple All (M)

Loss of Heat Sink and entry into FRH1.

(Critical Task)

(AFW Pump 11 OOS, Pump 12 No Power, Pump 13 Trips, Pump 14 overspeeds.)

10 (N/A) 08-02-01 1

BOP (C)

SRO (C)

AFW Pump 14 has an overspeed trip.

11 (N/A) 08-03-06 1

BOP (C)

SRO (C)

AFW Pump 13 trips on overcurrent.

Lot* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Technical Specification

LOT 24 NRC OP-TEST SCENARIO #1 Rev 1 Page 2 of 3 Target Quantitative Attributes (Per Scenario; See Section D.5.d)

Actual Attributes

1. Malfunctions after EOP entry (1-2) 3
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 scenario set) 1
6. Preidentified critical tasks (>2) 2 SCENARIO MISCELLANEOUS INFORMATION INSTRUCTOR NOTES:
  • Critical Tasks are indicated by "CT-##" in the position column and indicated in bold type. In some instances, an
  • will indicate that only a portion of the task listed is considered critical.
  • Shaded cells indicate procedural entry points.

LOT 24 NRC OP-TEST SCENARIO #1 Rev 1 Page 3 of 3 SCENARIO OBJECTIVES Event 1 Objective

  • Operate alternate Charging and Letdown flowpaths per 0POP02-CV-0004, Chemical Volume Control System Subsystem.

Event 2 Objective

  • Respond to Radiation System Monitoring alarms per 0POP04-RA-0001, Radiation Monitoring System Alarm Response.

Event 3 Objective

Event 4 Objective

Event 5 Objective

Event 6 and 7 Objective

Event 8 Objective

Event 9, 10 and 11 Objective

  • Respond to Loss of Heat Sink per 0POP05-EO-FRH1, Response to Loss of Secondary Heat Sink.

LOT 24 NRC OP-TEST SCENARIO #2 Rev 1 Page 1 of 3 SCENARIO OUTLINE Facility: South Texas Project Scenario No.: 2 Op-Test No.: LOT 24 NRC Examiners:

Operators:

Initial Conditions:

  • Mode 1 at 78% Power Turnover:
  • AFW Pump #11 is out of service.

Critical Tasks:

E5 - CT17; Isolate the faulted/ruptured SG.

  • E5 - CT34; Begin Cooldown of RCS.

Event No.

Malf.

No.

Event Type*

Event Description 1

(1 min) 02-20-01 1.0 RO (I)

SRO (I, TS)

PZR level channel LT-0465 fails high.

2 (11 min) 05-17-01 1.0 BOP (I)

SRO (I, TS) 1A SG PORV pressure transmitter (PT-7411) fails high.

3 (16 min) 08-23-01 True BOP (C)

SRO (C)

Condensate Pump #11 Trips 4

(21 min)

Multiple RO (R)

BOP (R)

SRO (R)

Main Generator Stator Cooling DT Alarm due to high DT across Stator Bars 36B and 36T. Including GCM alarm that leads to fast load reduction.

5 (35 min) 50-SA-11 0.25 50-HB-10 0.1 ALL (M)

Faulted and Ruptured SG 1B. Faulted on MS Line in IVC.

(2 Critical Tasks) 6 (N/A) 10-09-03 True RO (C)

BOP (C)

SRO (C)

Loss of power to ESF 4.16KV E1C. (Integral to Scenario) 7 (N/A)

Multiple RO (C)

SRO (C)

OUTP BKR, E1C/2A to LC E1C2, fails to Auto Close during loss of power to ESF 4.16KV E1C.

(Integral to Scenario) 8 (N/A)

SD-59 1.0 BOP (C)

SRO (C)

SG 1B Blowdown Isolation valve fails to close on the SI. Crew will have to close the SG 1B Blowdown Flow Control valve.

(Integral to Scenario) (Part of Critical Task for isolating SG 1B)

Lot* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Technical Specification

LOT 24 NRC OP-TEST SCENARIO #2 Rev 1 Page 2 of 3 Target Quantitative Attributes (Per Scenario; See Section D.5.d)

Actual Attributes

1. Malfunctions after EOP entry (1-2) 3
2. Abnormal events (2-4) 4
3. Major transients (1-2) 1
4. EOPs entered/requiring substantive actions (1-2) 2
5. Entry into a contingency EOP with substantive actions (>1 per scenario set) 1
6. Preidentified critical tasks (>2) 2 SCENARIO MISCELLANEOUS INFORMATION INSTRUCTOR NOTES:
  • Critical Tasks are indicated by "CT-##" in the position column and indicated in bold type. In some instances, an
  • will indicate that only a portion of the task listed is considered critical.
  • Shaded cells indicate procedural entry points.

LOT 24 NRC OP-TEST SCENARIO #2 Rev 1 Page 3 of 3 SCENARIO OBJECTIVES Event 1 Objective

  • Respond to a pressurizer level control malfunction in accordance with per 0POP04-RP-0002, Loss of Automatic Pressurizer Level Control.

Event 2 Objective

  • Respond to an excessive steam demand per 0POP04-MS-0001, Excessive Steam Demand.

Event 3 Objective

  • Respond to a Condensate Pump trip per 0POP04-CD-0001, Loss of Condensate Flow.

Event 4 Objective

Event 5 Objective

Event 6 Objective

Event 7 & 8 Objective

LOT 24 NRC OP-TEST SCENARIO #4 Rev 1 Page 1 of 3 SCENARIO OUTLINE Facility: South Texas Project Scenario No.: 4 Op-Test No.: LOT 24 NRC Examiners:

Operators:

Initial Conditions:

  • Mode 1 at 48% Power, BOC Turnover:
  • AFW Pump #11 is out of service.

Critical Tasks:

E5 - CT2; Manually Actuate SI

  • E7 - CT36; Manually Align Cold Leg Recirc Event No.

Malf.

No.

Event Type*

Event Description 1

(0 min)

N/A BOP (N)

Start EHC Pump #12 and secure EHC Pump #11. However, EHC Pump #12 has a leak and EHC Pump #11 must be restarted.

2 (5 min)

ME Schemat ic bmp003 RO (C)

SRO (C, TS)

CCP 1B develops a sheared shaft.

3 (15 min) 01 09 (True)

RO (C)

SRO (C, TS)

One Dropped Control Rod. Control Rod D-12 4

(N/A) 08 03 (True)

BOP (C)

SRO (C)

SG 1C MFRV Stuck in current position.

(Inserted with Dropped Control Rod Malfunction) 5 (40 min) 02 03 0.5 ALL (M)

LBLOCA. (Integral to Scenario)

(Critical Task) 6 (N/A) 04 08 1

BOP (C)

SRO (C)

Failure of Train B Essential Chiller to start - (Integral to scenario) 7 (N/A) 50-L2-24, 25, 26 1 RO (C)

SRO (C)

The auto swap over to cold leg recirculation will fail and the crew will have to manually align. (Integral to Scenario)

(Critical Task)

Lot* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Technical Specification

LOT 24 NRC OP-TEST SCENARIO #4 Rev 1 Page 2 of 3 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) 2
5. Entry into a contingency EOP with substantive actions (>1 per scenario set) 0
6. Preidentified critical tasks (>2) 2 SCENARIO MISCELLANEOUS INFORMATION INSTRUCTOR NOTES:
  • Critical Tasks are indicated by "CT-##" in the position column and indicated in bold type. In some instances, an
  • will indicate that only a portion of the task listed is considered critical.
  • Shaded cells indicate procedural entry points.

LOT 24 NRC OP-TEST SCENARIO #4 Rev 1 Page 3 of 3 SCENARIO OBJECTIVES Event 1 Objective

Event 2 Objective

Event 3 Objective

Event 4 Objective

Event 5 Objective

Event 6 Objective

Event 7 Objective

  • Respond to a failure of automatic transfer to Cold Leg Recirculation per 0POP05-EO-ES13, Transfer to Cold Leg Recirculation.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SCENARIO OUTLINE Facility: South Texas Project Scenario No.: 5 Op-Test No.: LOT 24 NRC Examiners:

Operators:

Initial Conditions:

  • Mode 1 at 100% Power, EOC Turnover:
  • AFW Pump #11 is out of service.

Critical Tasks:

E5 - CT16; Trip RCPs

Malf. No.

Event Type*

Event Description 1

(1 min)

N/A SRO (TS Only)

Oil sight glass broken on Containment Spray Pump 1B 2

(5 min)

ME Schematic cap003 BOP (C)

SRO (C)

CRDM Vent Fan 11A Trouble 3

(10 min) 02-19-03 0

RO (I)

SRO (I, TS)

Pressurizer PT-0457 fails low.

4 (22 min) 07-04-03 1

08-12-04 (True)

RO (R)

BOP (R)

SRO (R)

SGFPT #13 Trips and SU SGFP #14 trips on O/C. Crew will down power to 80%.

5 (32 min) 01-11-03 1

ALL (M)

Ejected Control Rod LOCA - H8 (Critical Task) 6 (N/A) 01-12-04A 01-12-04B 01-12-04C (True)

RO (C)

SRO (C)

Failure of Phase A to automatically actuate. Manual switches work. (Integral to scenario) 7 (N/A)

Multiple BOP (C)

SRO (C)

Containment Normal Sump Discharge ED-FV-7800 stuck open. ED-MOV-0064 fails to auto close and must be manually closed. (Critical Task)

Lot* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Technical Specification Total Estimated Time: 55 minutes

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) 2
5. Entry into a contingency EOP with substantive actions (>1 per scenario set) 0
6. Preidentified critical tasks (>2) 2 SCENARIO MISCELLANEOUS INFORMATION INSTRUCTOR NOTES:
  • Critical Tasks are indicated by "CT-##" in the position column and indicated in bold type. In some instances, an
  • will indicate that only a portion of the task listed is considered critical.
  • Shaded cells indicate procedural entry points.

SCENARIO OBJECTIVES Event 1 Objective

  • Interpret Technical Specifications.

Event 2 Objective

Event 3 Objective

  • Respond to Pressurizer Pressure Control System alarms per 0POP04-RP-0001, Loss of Automatic Pressurizer Pressure Control.

Event 4 Objective

Event 5 Objective

Event 6 and 7 Objective

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