Text

2016-05-DRAFT Outlines
	ML16047A203
Person / Time
Site:	South Texas
Issue date:	05/04/2016
From:	Vincent Gaddy; Operations Branch IV
To:	;
References
	Download: ML16047A203 (25)
	v • d • e

ES-401 PWR Examination Outline Form ES-401-2 Facility: South Texas Project, Units 1 and 2 (RO, Rev. 1) Date of Exam: May 4, 2016 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G* A2 G* Total 1 2 3 4 5 6 1 2 3 4 Total

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

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

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

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 Categories 2 3 3 2 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 Radiation Control K/A is allowed if the K/A is replaced by a K/A from another Tier 3 Category).

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

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

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

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

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

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

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

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

G* Generic K/As

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

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

1 2 3 1 2 EK1.04 - Knowledge of the operational 000007 (BW/E02&E10; CE/E02) Reactor X 3.6 1 implications of the following Trip - Stabilization - Recovery / 1 concepts as they apply to the reactor trip: Decrease in reactor power following reactor trip (prompt drop and subsequent decay). (CFR 41.8 /

41.10 / 45.3)

AK2.01 - Knowledge of the 000008 Pressurizer Vapor Space X 2.7 2 interrelations between the Accident / 3 Pressurizer Vapor Space Accident and the following: Valves (CFR 41.7 /

45.7)

EA1.16 - Ability to operate and 000009 Small Break LOCA / 3 X 4.2 3 monitor the following as they apply to a small break LOCA: Subcooling margin monitors (CFR 41.7 / 45.5 /

45.6)

EA2.01 - Ability to determine or 000011 Large Break LOCA / 3 X 4.2 4 interpret the following as they apply to a Large Break LOCA: Actions to be taken, based on RCS temperature and pressure - saturated and superheated (CFR 43.5 / 45.13)

AK3.01 - Knowledge of the reasons for 000015/17 RCP Malfunctions / 4 X 2.5 5 the following responses as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow) :

Potential damage from high winding and/or bearing temperatures (CFR 41.5,41.10 / 45.6 / 45.13) 2.2.12 - Knowledge of surveillance 000022 Loss of Rx Coolant Makeup / 2 X 3.7 6 procedures. (CFR: 41.10 / 45.13) 2.4.8 - Knowledge of how abnormal 000025 Loss of RHR System / 4 X 3.8 7 operating procedures are used in conjunction with EOPs.(CFR: 41.10 /

43.5 / 45.13)

AA1.05 - Ability to operate and / or 000026 Loss of Component Cooling X 3.1 8 monitor the following as they apply Water / 8 to the Loss of Component Cooling Water: The CCWS surge tank, including level control and level alarms, and radiation alarm.(CFR 41.7 / 45.5 /

45.6) 000027 Pressurizer Pressure Control System Malfunction / 3 EK2.06 - Knowledge of the 000029 ATWS / 1 X 2.9 9 interrelations between the and the following an ATWS: Breakers, relays, and disconnects (CFR 41.7 / 45.7)

EK3.01 - Knowledge of the reasons for 000038 Steam Gen. Tube Rupture / 3 X 4.1 10 the following responses as the apply to the SGTR: Equalizing pressure on primary and secondary sides of ruptured S/G (CFR 41.5 / 41.10 / 45.6

/ 45.13)

AK2.02 - Knowledge of the 000040 (BW/E05; CE/E05; W/E12) X interrelations between the Steam Line 2.6 11 Steam Line Rupture - Excessive Heat Rupture and the following: Sensors Transfer / 4 and detectors (CFR 41.7 / 45.7) 000054 (CE/E06) Loss of Main Feedwater / 4

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

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

1 2 3 1 2 000055 Station Blackout / 6 000056 Loss of Off-site Power / 6 2.4.3 - Ability to identify post-000057 Loss of Vital AC Inst. Bus / 6 X 3.7 12 accident instrumentation. (CFR: 41.6

/ 45.4)

AK1.01 - Knowledge of the operational 000058 Loss of DC Power / 6 X 2.8 13 implications of the following concepts as they apply to Loss of DC Power: Battery charger equipment and instrumentation (CFR 41.8 / 41.10 /

45.3) 000062 Loss of Nuclear Svc Water / 4 AA2.06 - Ability to determine and 000065 Loss of Instrument Air / 8 X 3.6 14 interpret the following as they apply to the Loss of Instrument Air: When to trip reactor if instrument air pressure is de-creasing (CFR: 43.5 /

45.13)

EK1.2 - Knowledge of the operational W/E04 LOCA Outside Containment / 3 X 3.5 15 implications of the following concepts as they apply to the (LOCA Outside Containment): Normal, abnormal and emergency operating procedures associated with (LOCA Outside Containment). (CFR: 41.8 /

41.10, 45.3)

EA1.2 - Ability to operate and / or W/E11 Loss of Emergency Coolant X 3.5 16 monitor the following as they apply Recirc. / 4 to the (Loss of Emergency Coolant Recirculation): Operating behavior characteristics of the facility.

(CFR: 41.7 / 45.5 / 45.6)

EK3.1 - Knowledge of the reasons for BW/E04; W/E05 Inadequate Heat X 3.4 17 the following responses as they apply Transfer - Loss of Secondary Heat Sink / 4 to the (Loss of Secondary Heat Sink):

Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics. (CFR: 41.5

/ 41.10, 45.6, 45.13)

AA2.05 - Ability to determine and 000077 Generator Voltage and Electric X 3.2 18 interpret the following as they apply Grid Disturbances / 6 to Generator Voltage and Electric Grid Disturbances: Operational status of offsite circuit (CFR: 41.5 and 43.5 / 45.5, 45.7, and 45.8)

K/A Category Totals: 3 3 3 3 3 3 Group Point Total: 18

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

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

1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 AK1.19 - Knowledge of the 000003 Dropped Control Rod / 1 X 2.8 19 operational implications of the following concepts as they apply to Dropped Control Rod:

Differential rod worth (CFR 41.8 / 41.10 / 45.3)

AA1.05 - Ability to operate and 000005 Inoperable/Stuck Control Rod / 1 X 3.4 20

/ or monitor the following as they apply to the Inoperable /

Stuck Control Rod: RPI (CFR 41.7 / 45.5 / 45.6) 000024 Emergency Boration / 1 000028 Pressurizer Level Malfunction / 2 AK2.01 - Knowledge of the 000032 Loss of Source Range NI / 7 X 2.7 21 interrelations between the Loss of Source Range Nuclear Instrumentation and the following: Power supplies, including proper switch positions (CFR 41.7 / 45.7) 000033 Loss of Intermediate Range NI / 7 000036 (BW/A08) Fuel Handling Accident / 8 000037 Steam Generator Tube Leak / 3 000051 Loss of Condenser Vacuum / 4 000059 Accidental Liquid Radwaste Rel. / 9 000060 Accidental Gaseous Radwaste Rel. / 9 2.4.31 - Knowledge of 000061 ARM System Alarms / 7 X 4.2 22 annunciator alarms, indications, or response procedures. (CFR: 41.10 / 45.3) 000067 Plant Fire On-site / 8 AK3.02 - Knowledge of the 000068 (BW/A06) Control Room Evac. / 8 X 3.7 23 reasons for the following responses as they apply to the Control Room Evacuation: System response to turbine trip (CFR 41.5,41.10 / 45.6 / 45.13) 000069 (W/E14) Loss of CTMT Integrity / 5 EK2.08 - Knowledge of the 000074 (W/E06&E07) Inad. Core Cooling / 4 X 2.5 24 interrelations between the and the following Inadequate Core Cooling: Sensors and detectors (CFR 41.7 / 45.7) 2.2.44 - Ability to interpret 000076 High Reactor Coolant Activity / 9 X 4.2 25 control room indications to verify the status of a system, and understand how operator actions and directives affect plant and system conditions.

(CFR: 41.5 / 43.5 / 45.12)

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

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

1 2 3 1 2 E01, EA2.1 - Ability to W/EO1 & E02 Rediagnosis & SI Termination / 3 X 3.2 26 determine and interpret the following as they apply to the (Reactor Trip or Safety Injection Rediagnosis):

Facility conditions and selection of appropriate procedures during abnormal and emergency operations (CFR: 43.5

/ 45.13)

W/E13 Steam Generator Over-pressure / 4 W/E15 Containment Flooding / 5 EA1.3 - Ability to operate and W/E16 High Containment Radiation / 9 X 2.9 27

/ or monitor the following as they apply to the (High Containment Radiation): Desired operating results during abnormal and emergency situations. (CFR: 41.7 / 45.5 /

45.6)

BW/A01 Plant Runback / 1 BW/A02&A03 Loss of NNI-X/Y / 7 BW/A04 Turbine Trip / 4 BW/A05 Emergency Diesel Actuation / 6 BW/A07 Flooding / 8 BW/E03 Inadequate Subcooling Margin / 4 BW/E08; W/E03 LOCA Cooldown - Depress. / 4 BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 BW/E13&E14 EOP Rules and Enclosures CE/A11; W/E08 RCS Overcooling - PTS / 4 CE/A16 Excess RCS Leakage / 2 CE/E09 Functional Recovery K/A Category Point Totals: 1 1 2 1 2 2 Group Point Total: 9

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO / SRO)

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

1 2 3 4 5 6 1 2 3 4 K1.08 - Knowledge of the 003 Reactor Coolant Pump X physical connections and/or 2.7 28 cause-effect relationships between the RCPS and the following systems:

Containment isolation (CFR:

41.2 to 41.9 / 45.7 to 45.8)

X K5.02 - Knowledge of the 2.8 29 operational implications of the following concepts as they apply to the RCPS:

Effects of RCP coastdown on RCS parameters (CFR: 41.5 /

45.7)

K2.04 - Knowledge of bus 004 Chemical and Volume X power supplies to the 2.6 30 Control following: BWST tank heaters (CFR: 41.7)

A4.14 - Ability to manually X operate and/or monitor in 2.8 31 the control room: Ion exchangers and demineralizers (CFR: 41/7 /

45.5 to 45.8)

A2.01 - Ability to (a) 005 Residual Heat Removal X predict the impacts of the 2.7 32 following malfunctions or operations on the RHRS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure modes for pressure, flow, pump motor amps, motor temperature, and tank level instrumentation (CFR: 41.5 /

43.5 / 45.3 / 45.13)

K6.02 - Knowledge of the 006 Emergency Core Cooling X effect of a loss or 3.4 33 malfunction on the following will have on the ECCS: Core flood tanks (accumulators)

(CFR: 41.7 / 45.7)

K5.02 - Knowledge of the 007 Pressurizer Relief/Quench X operational implications of 3.1 34 Tank the following concepts as the apply to PRTS: Method of forming a steam bubble in the PZR (CFR: 41.5 / 45.7)

2.4.50 - Ability to verify 008 Component Cooling Water X system alarm setpoints and 4.0 35 operate controls identified in the alarm response manual. (CFR: 41.10 / 43.5 /

45.3)

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

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

1 2 3 4 5 6 1 2 3 4 A3.01 - Ability to monitor 010 Pressurizer Pressure Control X automatic operation of the 3.0 36 PZR PCS, including: PRT temperature and pressure during PORV testing (CFR:

41.7 / 45.5)

K4.02 - Knowledge of PZR PCS X design feature(s) and/or 3.0 37 interlock(s) which provide for the following:

Prevention of uncovering PZR heaters. (CFR: 41.7)

A1.01 - Ability to predict 012 Reactor Protection X and/or monitor Changes in 2.9 38 parameters (to prevent exceeding design limits) associated with operating the RPS controls including:

Trip setpoint adjustment (CFR: 41.5 / 45.5)

K1.07 - Knowledge of the 013 Engineered Safety Features X physical connections and/or 4.1 39 Actuation cause effect relationships between the ESFAS and the following systems: AFW System (CFR: 41.2 to 41.9 /

45.7 to 45.8)

A2.03 - Ability to (a)

X predict the impacts of the 4.4 40 following malfunctions or operations on the ESFAS; and (b) based Ability on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations; Rapid depressurization (CFR: 41.5

/ 43.5 / 45.3 / 45.13)

A4.04 - Ability to manually 022 Containment Cooling X operate and/or monitor in 3.1 41 the control room: Valves in the CCS (CFR: 41.7 / 45.5 to 45.8) 025 Ice Condenser Not part of the plant design A3.01 - Ability to monitor 026 Containment Spray X automatic operation of the 4.3 42 CSS, including: Pump starts and correct MOV positioning (CFR: 41.7 / 45.5)

K5.01 - Knowledge of the 039 Main and Reheat Steam X operational implications of 2.9 43 the following concepts as the apply to the MRSS:

Definition and causes of steam/water hammer (CFR:

441.5 / 45.7)

K4.13 - Knowledge of MFW 059 Main Feedwater X design feature(s) and/or 2.9 44 interlock(s) which provide for the following: Feedwater fill for S/G upon loss of RCPs (CFR: 41.7)

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

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

1 2 3 4 5 6 1 2 3 4 K2.01 - Knowledge of bus 061 Auxiliary/Emergency X power supplies to the 3.2 45 Feedwater following: AFW system MOVs (CFR: 41.7)

X K4.07 - Knowledge of AFW 3.1 46 design feature(s) and/or interlock(s)which provide for the following: Turbine trip, including overspeed (CFR: 41.7)

A1.01 - Ability to predict 062 AC Electrical Distribution X and/or monitor changes in 3.4 47 parameters (to prevent exceeding design limits) associated with operating the ac distribution system controls including:

Significance of D/G load limits (CFR: 41.5 / 45.5)

A4.03 - Ability to manually 063 DC Electrical Distribution X operate and/or monitor in 3.0 48 the control room: Battery discharge rate (CFR: 41.7 /

45.5 to 45.8)

K3.03 - Knowledge of the 064 Emergency Diesel Generator X effect that a loss or 3.6 49 malfunction of the ED/G system will have on the following: ED/G (manual loads) (CFR: 41.7 / 45.6)

X K6.07 - Knowledge of the 2.7 50 effect of a loss or malfunction of the following will have on the ED/G system: Air receivers (CFR:

41.7 / 45.7) 073 Process Radiation Monitoring X A1.01 - Ability to predict 3.2 51 and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PRM system controls including: Radiation levels (CFR: 41.5 / 45.7)

076 Service Water X A3.02 - Ability to monitor 3.7 52 automatic operation of the SWS, including: Emergency heat loads (CFR: 41.7 /

45.5) 078 Instrument Air X K2.02 - Knowledge of bus 3.3 53 power supplies to the following: Emergency air compressor (CFR: 41.7)

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

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

1 2 3 4 5 6 1 2 3 4 K3.02 - Knowledge of the 103 Containment X effect that a loss or 3.8 54 malfunction of the containment system will have on the following: Loss of containment integrity under normal operations (CFR: 41.7

/ 45.6) 2.1.31 - Ability to locate X control room switches, 4.6 55 controls, and indications, and to determine that they correctly reflect the desired plant lineup. (CFR:

41.10 / 45.12)

K/A Category Point Totals: 2 3 2 3 3 2 3 2 3 3 2 Group Point Total: 28

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO / SRO)

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

1 2 3 4 5 6 1 2 3 4 K1.04 - Knowledge of the 001 Control Rod Drive X physical connections and/or 3.2 56 cause-effect relationships between the CRDS and the following systems: RCS (CFR:

41.2 to 41.9 / 45.7 to 45.8) 002 Reactor Coolant K2.02 - Knowledge of bus power 011 Pressurizer Level Control X supplies to the following: PZR 3.1 57 heaters (CFR: 41.7) 014 Rod Position Indication K3.06 - Knowledge of the 015 Nuclear Instrumentation X effect that a loss or 2.9 58 malfunction of the NIS will have on the following: Reactor regulating system (CFR: 41.7 /

45.6)

A3.01 - Ability to monitor 016 Non-Nuclear Instrumentation X automatic operation of the 2.9 59 NNIS, including: Automatic selection of NNIS inputs to control systems (CFR: 41.7 /

45.5)

A1.01 - Ability to predict 017 In-Core Temperature Monitor X and/or monitor changes in 3.7 60 parameters (to prevent exceeding design limits) associated with operating the ITM system controls including:

Core exit temperature (CFR:

41.5 / 45.7)

A4.03 - Ability to manually 027 Containment Iodine Removal X operate and/or monitor in the 3.3 61 control room: CIRS fans. (CFR:

41.7 / 45.5 to 45.8) 028 Hydrogen Recombiner and Purge Control A2.04 - Ability to (a) predict 029 Containment Purge X the impacts of the following 2.5 62 malfunctions or operations on the Containment Purge System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Health physics sampling of containment atmosphere (CFR:

41.5 / 43.5 / 45.3 / 45.13) 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment 035 Steam Generator 041 Steam Dump/Turbine Bypass Control

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

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

1 2 3 4 5 6 1 2 3 4 K4.01 - Knowledge of MT/G 045 Main Turbine Generator X system design feature(s) 2.7 63 and/or interlock(s) which provide for the following:

Programmed controller for relationship between steam pressure at T/G inlet (impulse, first stage) and plant power level (CFR: 41.7) 055 Condenser Air Removal 056 Condensate 068 Liquid Radwaste 071 Waste Gas Disposal 2.1.19 - Ability to use plant 072 Area Radiation Monitoring X computers to evaluate system 3.9 64 or component status. (CFR:

41.10 / 45.12) 075 Circulating Water 079 Station Air K5.03 - Knowledge of the 086 Fire Protection X operational implication of the 3.1 65 following concepts as they apply to the Fire Protection System: Effect of water spray on electrical components (CFR:

41.5 / 45.7)

K/A Category Point Totals: 1 1 1 1 1 0 1 1 1 1 1 Group Point Total: 10

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: South Texas Project, Units 1 and 2 (RO, Rev. 0) Date of Exam: May 4, 2016 Category K/A # Topic RO SRO-Only IR # IR #

Ability to interpret reference materials, such as graphs, 2.1.25 3.9 66 curves, tables, etc. (CFR: 41.10 / 43.5 / 45.12)

Knowledge of refueling administrative requirements.

2.1.40 2.8 67 (CFR: 41.10 / 43.5 / 45.13) 1.

Conduct of 2.1.

Operations 2.1.

2.1.

Subtotal 2 Knowledge of the design, procedural, and operational 2.2.3 3.8 68 differences between units. (CFR: 41.5 / 41.6 / 41.7 /

41.10 / 45.12)

Ability to analyze the effect of maintenance activities, 2.2.36 3.1 69 such as degraded power sources, on the status of limiting

2. conditions for operations. (CFR: 41.10 / 43.2 / 45.13)

Equipment Knowledge of less than or equal to one hour Technical 2.2.39 3.9 70 Control Specification action statements for systems. (CFR: 41.7 /

41.10 / 43.2 / 45.13) 2.2.

2.2.

Subtotal 3 Ability to comply with radiation work permit requirements 2.3.7 3.5 71 during normal or abnormal conditions. (CFR: 41.12 /

45.10)

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

2.3.11 3.8 72 45.10)

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

2.3.

Subtotal 3 Knowledge of EOP mitigation strategies. (CFR: 41.10 /

2.4.6 3.7 74 43.5 / 45.13)

Knowledge of the emergency plan. (CFR: 41.10 / 43.5 /

2.4.29 3.1 75

4. 45.11)

Emergency 2.4.

Procedures /

Plan 2.4.

2.4.

Subtotal 2 Tier 3 Point Total 10

ES-401 Record of Rejected K/As Form ES-401-4 NOTE: All replacement KAs were randomly selected picking a KA from a group of associated KA numbers that were placed in a container.

Tier / Randomly Selected Reason for Rejection Group K/A 1/1 APE 025 G2.4.30 The generic portion of the KA tests knowledge an SRO needs for making notifications. It is more suited for an (Outline Question 7) SRO question. Therefore the KA was replaced with APE 025 G2.4.8.

1/1 APE 026 AA1.04 This KA tests knowledge of CCW and how it relates to CRDM high temperature alarms. At STP, CRDMs are not (Outline Question 8) directly cooled by CCW. Therefore the KA was replaced with APE 026 AA1.05.

1/2 APE 076 G2.2.3 The generic portion of the KA tests knowledge of the differences between Unit 1 and 2 in regards to High (Outline Question 25) Reactor Coolant Activity. There is no difference between the Units associated with High Reactor Coolant Activity.

Therefore the KA was replaced with APE 076 G2.2.44.

2/1 006 K6.18 This KA tests knowledge of subcooling margin indicators as it relates to ECCS. A question for this (Outline Question 33)

KA would be similar to a question for KA EPE 009 EA1.16. (Outline Question 3) Therefore the KA was replaced with 006 K6.02.

2/1 008 G2.4.21 The generic portion of the KA tests knowledge of Safety Function parameters and logic. Component (Outline Question 35)

Cooling Water does not input into Safety Function parameters and logic. Therefore the KA was replaced with 008 G.2.4.50.

2/1 010 K4.02 NOTE: A Tier 2, Group 4, K4 question was missing from the original outline. 010 K4.02 was randomly (Outline Question 37) selected to make up for the missing question.

2/1 022 A4.03 This KA tests the ability to operate and/or monitor Containment Cooling dampers. There are no (Outline Question 40)

Containment Cooling dampers to operate or monitor. Therefore the KA was replaced with 022 A4.04.

2/1 103 A3.07 NOTE: This is an administrative change only. There is no KA 103 A3.07. The KA should have been 103 (Outline Question 53)

A3.02 and has been properly corrected.

2/2 027 A4.02 This KA tests knowledge of remote operation of Containment Iodine filters. At STP, operations has (Outline Question 61) no interface with the Containment Iodine filters.

Therefore the KA was replaced with 027 A4.03.

Tier / Randomly Selected Reason for Rejection Group K/A 2/2 072 G2.2.4 The generic portion of this KA tests the variations in control board/control room layouts and other (Outline Question 64) differences between the Units associated with Area Radiation Monitoring. At STP there are no differences between the Units associated with Area Radiation Monitoring. Therefore the KA was replaced with 072 G.2.1.19.

3/2 G2.2.17 This generic KA tests knowledge of managing maintenance activities. It is better suited for an SRO (Outline Question 68) question. Therefore the KA was replaced with G.2.2.3.

ES-401 PWR Examination Outline Form ES-401-2 Facility: South Texas Project, Units 1 and 2 (SRO, Rev. 1) Date of Exam: May 4, 2016 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G* A2 G* Total 1 2 3 4 5 6 1 2 3 4 Total

1. 1 3 3 6 Emergency &

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

Plant 2 2 1 3 Systems Tier Totals 5 3 8

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