ML14181A823

Project - 2014-05 - Draft Written Outline

ML14181A823
Person / Time
Site:	South Texas
Issue date:	05/01/2014
From:	Vincent Gaddy Operations Branch IV
To:	South Texas
laura hurley
References
Download: ML14181A823 (24)

Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: South Texas Project Date of Exam: April 30, 2014 Tier Group RO K/A Category Points SRO-Only Points K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G

• Total A2 G* Total

1. Emergency &

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

2. Plant Systems 1 4 3 1 3 3 1 4 2 3 2 2 28 3 2 5 2 1 0 1 1 1 1 1 1 1 1 1 10 0 1 2 3 Tier Totals 5 3 2 4 4 2 5 3 4 3 3 38 4 4 8 3. Generic Knowledge and Abilities Categories 1 2 3 4 10 1 2 3 4 7 2 3 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 outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each K/A category shall not be less than two). 2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points. 3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements. 4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution. 5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selecte

d. 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 rel evant 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 brie f description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams. 9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emer g enc y and Abnormal Plant Evolutions -Tie r1/Grou p 1 (RO)E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 G K/A Topic(s) IR Q# 000007 (BW/E02&E10; CE/E02) Reactor Trip - Stabilization - Recovery / 1 X 2.4.49 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls. (CFR: 41.10

/ 43.2 / 45.6) 4.6 1 000008 Pressurizer Vapor Space Accident / 3 X AK1. Knowledge of the operational implications of the following concepts as they apply to a Pressurizer Vapor Space Accident:

(CFR 41.8 / 41.10 / 45.3)

AK1.01 Thermodynamics and flow characteristics of open or leaking valves 3.2 2 000009 Small Break LOCA / 3 X EK2 Knowledge of the interrelations between the small break LOCA and the following:

(CFR 41.7 / 45.7) EK2.03 S/Gs . .

3.0 3 000011 Large Break LOCA / 3 NA 000015/17 RCP Malfunctions / 4 X AK3. Knowledge of the reasons for the following responses as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow) :

(CFR 41.5,41.10 / 45.6 / 45.13) AK3.03 Sequence of events for manually tripping reactor and RCP as a result of an RCP malfunction.

3.7 4 000022 Loss of Rx Coolant Makeup / 2 X AA1. Ability to operate and / or monitor the following as they apply to the Loss of Reactor Coolant

Makeup: (CFR 41.7 / 45.5 / 45.6) AA1.07 Excess letdown containment isolation valve switches and indicators 2.8 5 000025 Loss of RHR System / 4 X AA2. Ability to determine and interpret the following as they apply to the Loss of Residual Heat Removal System:

(CFR: 43.5 / 45.13)

AA2.02 Leakage of reactor coolant from RHR into closed cooling water system or into reactor building atmosphere 3.4 6 000026 Loss of Component Cooling Water / 8 X AA2. Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water:

(CFR: 43.5 / 45.13)

AA2.06 The length of time after the loss of CCW flow to a component before that component may be damaged 2.8 7 000027 Pressurizer Pressure Control System Malfunction / 3 X 2.2.38 Knowledge of conditions and limitations in the facility license. (CFR: 41.7/41.10/43.1/45.13) 3.6 8 000029 ATWS / 1 X EK1 Knowledge of the operational implications of the following concepts as they apply to the ATWS:

(CFR 41.8 / 41.10 / 45.3)

EK1.02 Definition of reactivity 2.6 9 000038 Steam Gen. Tube Rupture / 3 X EK3 Knowledge of the reasons for the following responses as the apply to the SGTR:

(CFR 41.5 / 41.10 / 45.6 / 45.13)

EK3.06 Actions contained in EOP for RCS water inventory balance, S/G tube rupture, and plant shutdown procedures 4.2 10 000040 (BW/E05; CE/E05; W/E12) Steam Line Rupture - Excessive Heat Transfer / 4 NA 000054 (CE/E06) Loss of Main Feedwater / 4 X AA1. Ability to operate and / or monitor the following as they apply to the Loss of Main Feedwater (MFW):

(CFR 41.7 / 45.5 / 45.6) AA1.03 AFW auxiliaries, including oil cooling water supply 3.5 11 000055 Station Blackout / 6 X EA2 Ability to determine or interpret the following as they apply to a Station Blackout:

(CFR 43.5 / 45.13) EA2.06 Faults and lockouts that must be cleared prior to re- energizing buses 3.7 12 000056 Loss of Off-site Power / 6 X 2.2.21 Knowledge of pre- and post-maintenance operability requirements. (CFR: 41.10

/ 43.2) 2.9 13 000057 Loss of Vital AC Inst. Bus / 6 NA 000058 Loss of DC Power / 6 X AK1. Knowledge of the operational implications of the following concepts as they apply to Loss of DC Power:

(CFR 41.8 / 41.10 / 45.3) AK1.01 Battery charger equipment and instrumentation 2.8 14 000062 Loss of Nuclear Svc Water / 4 X AK3. Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear Service Water:

(CFR 41.4, 41.8 / 45.7 )

AK3.02 The automatic actions (alignments) within the nuclear service water resulting from actuation of the ESFAS.

3.6 15 000065 Loss of Instrument Air / 8 X AA1. Ability to operate and / or monitor the following as they apply to the Loss of Instrument Air:

(CFR 41.7 / 45.5 / 45.6) AA1.04 Emergency air compressor 3.5 16 W/E04 LOCA Outside Containment / 3 X EK2. Knowledge of the interrelations between the (LOCA Outside Containment) and the following:

(CFR: 41.7 / 45.7)

EK2.1 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

3.5 17 W/E11 Loss of Emergency Coolant Recirc. / 4 NA BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 X EK2. Knowledge of the interrelations between the (Loss of Secondary Heat Sink) and the following:

(CFR: 41.7 / 45.7)

EK2.2 Facility*s heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

3.9 18 000077 Generator Voltage and Electric Grid Disturbances / 6 NA K/A Category Totals: 3 3 333 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) E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2GK/A Topic(s) IR Q# 000001 Continuous Rod Withdrawal / 1 X AK2. Knowledge of the interrelations between the Continuous Rod Withdrawal and the following:

(CFR: 41.7 / 45.7)

AK2.06 T-ave./ref. deviation meter.

3.0 19 000003 Dropped Control Rod / 1 NA 000005 Inoperable/Stuck Control Rod / 1 NA 000024 Emergency Boration / 1 NA 000028 Pressurizer Level Malfunction / 2 X AK3. Knowledge of the reasons for the following responses as they apply to the

Pressurizer Level Control Malfunctions:

(CFR 41.5,41.10 / 45.6 / 45.13)

AK3.03 False indication of PZR level when PORV or spray valve is open and RCS saturated 3.5 20 000032 Loss of Source Range NI / 7 X AK1. Knowledge of the operational implications of the following concepts as they apply to Loss of Source Range Nuclear Instrumentation:

(CFR 41.8 / 41.10 / 45.3)

AK1.01 Effects of voltage changes on performance 2.5 21 000033 Loss of Intermediate Range NI / 7 NA 000036 (BW/A08) Fuel Handling Accident / 8 NA 000037 Steam Generator Tube Leak / 3 NA 000051 Loss of Condenser Vacuum / 4 X AK3. Knowledge of the reasons for the following responses as they apply to the Loss of Condenser Vacuum:

(CFR 41.5,41.10 / 45.6 / 45.13)

AK3.01 Loss of steam dump capability upon loss of condenser vacuum 2.8 22 000059 Accidental Liquid RadWaste Rel. / 9 NA 000060 Accidental Gaseous Radwaste Rel. / 9 X AK2. Knowledge of the interrelations between the Accidental Gaseous Radwaste Release and the following:

(CFR 41.7 / 45.7)

AK2.01 ARM system, including the normal radiation-level indications and the operability

status 2.6 23 000061 ARM System Alarms / 7 X AA1. Ability to operate and / or monitor the following as they apply to the Area Radiation Monitoring (ARM)System Alarms:

(CFR 41.7 / 45.5 / 45.6) AA1.01 Automatic actuation 3.6 24 000067 Plant Fire On-site / 8 X AA2. Ability to determine and interpret the following as they apply to the Plant Fire on

Site:

(CFR: 43.5 / 45.13) AA2.13 Need for emergency plant shutdown 3.3 25 000068 (BW/A06) Control Room Evac. / 8 NA 000069 (W/E14) Loss of CTMT Integrity / 5 NA 000074 (W/E06&E07) Inad. Core Cooling / 4 NA 000076 High Reactor Coolant Activity / 9 X2.1.45 Ability to identify and interpret diverse indications to validate the response of another indication. (CFR: 41.7

/ 43.5 / 45.4) 4.3 26 W/EO1 & E02 Rediagnosis & SI Termination / 3 NA W/E13 Steam Generator Over-pressure / 4 NA W/E15 Containment Flooding / 5 X EK1. Knowledge of the operational implications of the following concepts as they apply to the (Containment Flooding)

(CFR: 41.8 / 41.10, 45.3) EK1.1 Components, capacity, and function of emergency systems.

2.8 27 W/E16 High Containment Radiation / 9 NA BW/A01 Plant Runback / 1 NA BW/A02&A03 Loss of NNI-X/Y / 7 NA BW/A04 Turbine Trip / 4 NA BW/A05 Emergency Diesel Actuation / 6 NA BW/A07 Flooding / 8 NA BW/E03 Inadequate Subcooling Margin / 4 NA BW/E08; W/E03 LOCA Cooldown - Depress. / 4 NA BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 NA BW/E13&E14 EOP Rules and Enclosures NA CE/A11; W/E08 RCS Overcooling - PTS / 4 NA CE/A16 Excess RCS Leakage / 2 NA CE/E09 Functional Recovery NA K/A Category Point Totals:

2221 11Group Point Total: 9

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems -Tie r2/Group 1 (RO)System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G K/A Topic(s) IR Q# 003 Reactor Coolant Pump X K4 Knowledge of RCPS design feature(s) and/or interlock(s) which provide for the following:

(CFR: 41.7) K4.02 Prevention of cold water accidents or transients 2.5 28 004 Chemical and Volume Control X K5 Knowledge of the operational implications of the following concepts as they apply to the CVCS:

(CFR: 41.5/45.7)

K5.46 Reason for going solid in PZR (collapsing steam bubble): make sure no steam is in PRT when PORV is opened to drain RCS 2.5 29 005 Residual Heat Removal X K6 Knowledge of the effect of a loss or malfunction on the following will have on the RHRS:

(CFR: 41.7 / 45.7) K6.03 RHR heat exchanger 2.5 30 006 Emergency Core Cooling X K1 Knowledge of the physical connections and/or cause effect relationships between the ECCS and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8) K1.03 RCS 4.2 31 006 Emergency Core Cooling X A1 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including: (CFR: 41.5 / 45.5)

A1.17 ECCS flow rate 4.2 32 007 Pressurizer Relief/Quench Tank X A2 Ability to (a) predict the impacts of the following malfunctions or operations on the P S; and (b) based on those

predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

(CFR: 41.5 / 43.5 / 45.3 / 45.13) A2.05 Exceeding PRT high-pressure limits 3.2 33 008 Component Cooling Water X A3 Ability to monitor automatic operation of the CCWS, including:

(CFR: 41.7 / 45.5)

A3.02 Operation of the CCW pumps, including interlocks and the CCW booster pump 3.2 34 010 Pressurizer Pressure Control X K1 Knowledge of the physical connections and/or cause-effect relationships between the PZR PCS and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8) K1.01 RP 3.9 35 010 Pressurizer Pressure Control X A4 Ability to manually operate and/or monitor in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.01 PZR spray valve 3.7 36 012 Reactor Protection X K4 Knowledge of RPS design feature(s) and/or interlock(s) which provide for the following:

(CFR: 41.7) K4.08 Logic matrix testing 2.8 37 012 Reactor Protection X 2.2.18 Knowledge of the process for managing maintenance activities during shutdown operations, such as risk assessments, work prioritization, etc.

(CFR: 41.10

/ 43.5 / 45.13) 2.6 38 013 Engineered Safety Features Actuation X K1 Knowledge of the physical connections and/or cause effect relationships between the ESFAS and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.04 RPS injection 3.9 39 013 Engineered Safety Features Actuation X K2 Knowledge of bus power supplies to the following:

(CFR: 41.7)

K2.01 ESFAS/safeguards equipment

control 3.6 40 022 Containment Cooling X K2 Knowledge of power supplies to the following:

(CFR: 41.7) K2.02 Chillers 2.5 41 022 Containment Cooling X A1 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CCS controls including:

(CFR: 41.5 / 45.5)

A1.03 Containment humidity 3.1 42 025 Ice Condenser NA 026 Containment Spray X K4 Knowledge of CSS design feature(s) and/or interlock(s) which provide for the following:

(CFR: 41.7) K4.07 Adequate level in containment sump for suction (interlock) 3.8 43 039 Main and Reheat Steam X K5 Knowledge of the operational implications of the following concepts as the apply to the MRSS:

(CFR: 441.5 / 45.7)

K5.01 Definition and causes of steam/water hammer 2.9 44 039 Main and Reheat Steam X A3 Ability to monitor automatic operation of the MRSS, including:

(CFR: 41.5 / 45.5)

A3.02 Isolation of the MRSS 3.1 45 059 Main Feedwater X A1 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MFW controls including:

(CFR: 41.5 / 45.5) A1.07 Feed Pump speed, including normal control speed for ICS 2.5 46 061 Auxiliary/Emergency Feedwater X A1 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the AFW controls including:

(CFR: 41.5 / 45.5) A1.04 AFW source tank level 3.1 47 062 AC Electrical Distribution X A2 Ability to (a) predict the impacts of the 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:

(CFR: 41.5 / 43.5 / 45.3 / 45.13) A2.12 Restoration of power to a system with a fault on it 3.2 48 063 DC Electrical Distribution X K4 Knowledge of DC electrical system design feature(s) and/or interlock(s) which provide for the following:

(CFR: 41.7) K4.01 Manual/automatic transfers of controls.

2.7 49 063 DC Electrical Distribution X A3 Ability to monitor automatic operation of the DC electrical system, including:

(CFR: 41.7 / 45.5)

A3.01 Meters, annunciators, dials, recorders, and indicating lights

2.7 50 064 Emergency Diesel Generator X A4 Ability to manually operate and/or monitor in the control room:

(CFR: 41.7 / 45.5 to 45.8) A4.03 Synchroscope.

3.2 51 073 Process Radiation Monitoring X 2.1.14 Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trips, mode changes, etc. (CFR: 41.10/43.5/45.12) 3.1 52 076 Service Water X K1 Knowledge of the physical connections and/or cause- effect relationships between the SWS and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8) K1.09 Reactor building closed cooling water 3.0 53 078 Instrument Air X K2 Knowledge of bus power supplies to the following:

(CFR: 41.7) K2.01 Instrument air compressor 2.7 54 103 Containment X K3 Knowledge of the effect that a loss or malfunction of the containment system will have on the following:

(CFR: 41.7 / 45.6) K3.03 Loss of containment integrity under refueling operations 3.7 55 K/A Category Point Totals: 4 3 1 3 314232 2 Group Point Total: 28

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems -Tie r2/Group 2 (RO)System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4GK/A Topic(s) IR Q# 001 Control Rod Drive X K3 Knowledge of the effect that a loss or malfunction of the CRDS will have on the following:

(CFR: 41.7/45.6) K3.01 CVCS 2.9 56 002 Reactor Coolant NA 011 Pressurizer Level Control X K5 Knowledge of the operational implications of the following concepts as they apply to the PZR LCS:

(CFR: 41.5 / 45.7)

K5.05 Interrelation of indicated charging flow rate with volume of water required to bring PZR level back to programmed level hot/cold 2.8 57 014 Rod Position Indication NA 015 Nuclear Instrumentation NA 016 Non-nuclear Instrumentation X K4 Knowledge of NNIS design feature(s) and/or interlock(s) which provide for the following:

(CFR: 41.7) K4.03 Input to control systems 2.8 58 017 In-core Temperature Monitor NA 027 Containment Iodine Removal X A2 Ability to (a) predict the impacts of the following malfunctions or operations on the CIRS; and (b) based on those predictions, use Procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

(CFR: 41.5 / 43.5 / 45.3 / 45.13) A2.01 High temperature in the filter system 3.0 59 028 Hydrogen Recombiner and Purge Control NA 029 Containment Purge X A1 Ability to predict and/or monitor changes in parameters to prevent exceeding design limits) associated with operating the Containment Purge System controls including:

(CFR: 41.5 / 45.5) A1.03 Containment pressure, temperature, and humidity 3.0 60 033 Spent Fuel Pool Cooling NA 034 Fuel Handling Equipment NA 035 Steam Generator NA 041 Steam Dump/Turbine Bypass Control X A3 Ability to monitor automatic operation of the SDS, including:

(CFR: 41.7 / 45.5) A3.03 Steam flow 2.7 61 045 Main Turbine Generator NA 055 Condenser Air Removal NA 056 Condensate X K1 Knowledge of the physical connections and/or cause-effect relationships between the Condensate System and the following systems: (CFR: 41.2 to 41.9 / 45.7 to 45.8) K1.03 MFW 2.6 62 068 Liquid Radwaste X2.3.11 Ability to control radiation releases. (CFR: 41.11

/ 43.4 / 45.10) 3.8 63 071 Waste Gas Disposal NA 072 Area Radiation Monitoring NA 075 Circulating Water NA 079 Station Air X A4 Ability to manually operate and/or monitor in the control room:

(CFR: 41.7 / 45.5 to 45.8) A4.01 Cross-tie valves with IAS 2.7 64 086 Fire Protection X K6 Knowledge of the effect of a loss or malfunction on the Fire Protection System following will have on the :

(CFR: 41.7 / 45.7) K6.04 Fire, smoke, and heat detectors 2.6 65 K/A Category Point Totals: 1 0 1 1 111 1111Group Point Total: 10

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: South Texas Project Date of Exam: April 30, 2014Category K/A # Topic RO SRO-Only IR Q# IR #

1.

Conduct of Operations 2.1.5 2.1.5 Ability to use procedures rela ted to shift staffing, such as minimum crew complement, overtime limitations, etc. (CFR: 41.10

/ 43.5 / 45.12) 2.9 66 NA NA 2.1.39 2.1.39 Knowledge of conservative decision making practices. (CFR: 41.10

/ 43.5 / 45.12) 3.6 67 NA NA 2.1. NA NA NA 2.1. NA NA NA 2.1. NA NA NA 2.1. NA NA NA Subtotal 2 NA 2.

Equipment Control 2.2.1 2.2.1 Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity. (CFR: 41.5

/ 41.10 / 43.5 / 43.6 / 45.1) 4.5 68 NA NA 2.2.36 2.2.36 Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations. (CFR: 41.10

/ 43.2 / 45.13) 3.1 69 NA NA 2.2.37 2.2.37 Ability to determine operability and/or availability of safety related equipment. (CFR: 41.7

/ 43.5 / 45.12) 3.6 70 NA NA 2.2. NA NA NA 2.2. NA NA NA 2.2. NA NA NA Subtotal 3 NA

3. Radiation Control 2.3.5 2.3.5 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. (CFR: 41.11/41.12/43.4/45.9) 2.9 71 NA NA 2.3.12 2.3.12 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling respon sibilities, access to locked high-radiation areas, aligning filters, etc. (CFR: 41.12

/ 45.9/45.10) 3.2 72 NA NA 2.3. NA NA NA 2.3. NA NA NA 2.3. NA NA NA 2.3. NA NA NA Subtotal 2

4. Emergency Procedures / Plan 2.4.1 2.4.1 Knowledge of EOP entry conditions and immediate action steps. (CFR: 41.10

/ 43.5 / 45.13) 4.6 73 NA NA 2.4.11 2.4.11 Knowledge of abnormal condition procedures. (CFR: 41.10

/ 43.5 / 45.13) 4.0 74 NA NA 2.4.12 2.4.12 Knowledge of general operating crew responsibilities during emergency operations.

(CFR: 41.10

/ 45.12) 4.0 75 NA NA 2.4. NA NA NA 2.4. NA NA NA 2.4. NA NA NA Subtotal 3 NA Tier 3 Point Total 10 NA ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emer g enc y and Abnormal Plant Evolutions -Tie r1/Grou p 1 (SRO)E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 G K/A Topic(s) IR Q# 000007 (BW/E02&E10; CE/E02) Reactor Trip - Stabilization - Recovery / 1 X EA2 Ability to determine or interpret the following as they apply to a reactor trip:

(CFR 41.7 / 45.5 / 45.6) EA2.05 Reactor trip first-out indication 3.9 76 000008 Pressurizer Vapor Space Accident / 3 NA 000009 Small Break LOCA / 3 X EA2 Ability to determine or interpret the following as they apply to a small break LOCA: (CFR 43.5 / 45.13)

EA2.39 Adequate core cooling 4.7 77 000011 Large Break LOCA / 3 NA 000015/17 RCP Malfunctions / 4 NA 000022 Loss of Rx Coolant Makeup / 2 NA 000025 Loss of RHR System / 4 NA 000026 Loss of Component Cooling Water / 8 NA 000027 Pressurizer Pressure Control System Malfunction / 3 NA 000029 ATWS / 1 NA 000038 Steam Gen. Tube Rupture / 3 NA 000040 (BW/E05; CE/E05; W/E12) Steam Line Rupture - Excessive Heat Transfer / 4 NA 000054 (CE/E06) Loss of Main Feedwater / 4 X AA2. Ability to determine and interpret the following as they apply to the Loss of Main Feedwater (MFW):

(CFR: 43.5 / 45.13) AA2.06 AFW adjustments needed to maintain proper T-ave. and S/G level 4.3 78 000055 Station Blackout / 6 NA 000056 Loss of Off-site Power / 6 NA 000057 Loss of Vital AC Inst. Bus / 6 NA 000058 Loss of DC Power / 6 NA 000062 Loss of Nuclear Svc Water / 4 X 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. (CFR: 41.12

/ 43.4 / 45.10) 3.7 79 000065 Loss of Instrument Air / 8 X 2.1.36 Knowledge of procedures and limitations involved in core alterations. (CFR: 41.10

/ 43.6 / 45.7) 4.1 80 W/E04 LOCA Outside Containment / 3 NA W/E11 Loss of Emergency Coolant Recirc. / 4 X 2.2. 39 Knowledge of less than or equal to one hour Technical Specification action statements for systems. (CFR: 41.7 / 41.10 / 43.2 / 45.13) 4.5 81 BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 NA 000077 Generator Voltage and Electric Grid Disturbances / 6 NA K/A Category Totals: 3 3 Group Point Total: 6

ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO) E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2GK/A Topic(s) IR # 000001 Continuous Rod Withdrawal / 1 NA 000003 Dropped Control Rod / 1 NA 000005 Inoperable/Stuck Control Rod / 1 NA 000024 Emergency Boration / 1 X2.4.46 Ability to verify that the alarms are consistent with th e plant conditions. (CFR: 41.10/43.5/45.3/45.12) 4.2 82 000028 Pressurizer Level Malfunction / 2 NA 000032 Loss of Source Range NI / 7 NA 000033 Loss of Intermediate Range NI / 7 NA 000036 (BW/A08) Fuel Handling Accident / 8 NA 000037 Steam Generator Tube Leak / 3 NA 000051 Loss of Condenser Vacuum / 4 NA 000059 Accidental Liquid RadWaste Rel. / 9 NA 000060 Accidental Gaseous Radwaste Rel. / 9 X AA2. Ability to determine and interpret the following as they apply to the Accidental Gaseous Radwaste:

(CFR: 43.5 / 45.13) AA2.04 The effects on the power plant of isolating a given r adioactive-gas leak 3.4 83 000061 ARM System Alarms / 7 NA 000067 Plant Fire On-site / 8 NA 000068 (BW/A06) Control Room Evac. / 8 NA 000069 (W/E14) Loss of CTMT Integrity / 5 NA 000074 (W/E06&E07) Inad. Core Cooling / 4 NA 000076 High Reactor Coolant Activity / 9 NA W/EO1 & E02 Rediagnosis & SI Termination / 3 X EA2. Ability to determine and interpret the following as they apply to the (SI Termination) (CFR: 43.5 / 45.13)

EA2.2 Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

4.0 84 W/E13 Steam Generator Over-pressure / 4 NA W/E15 Containment Flooding / 5 NA W/E16 High Containment Radiation / 9 NA BW/A01 Plant Runback / 1 NA BW/A02&A03 Loss of NNI-X/Y / 7 NA BW/A04 Turbine Trip / 4 NA BW/A05 Emergency Diesel Actuation / 6 NA BW/A07 Flooding / 8 NA BW/E03 Inadequate Subcooling Margin / 4 NA BW/E08; W/E03 LOCA Cooldown - Depress. / 4 X2.4.37 Knowledge of the lines of authority during implementation of the emergency

plan. (CFR: 41.10

/ 45.13) 4.1 85 BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 NA BW/E13&E14 EOP Rules and Enclosures NA CE/A11; W/E08 RCS Overcooling - PTS / 4 NA CE/A16 Excess RCS Leakage / 2 NA CE/E09 Functional Recovery NA K/A Category Point Totals:

0000 22Group Point Total: 4

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems -Tie r2/Group 1 (SRO)System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G K/A Topic(s) IR Q# 003 Reactor Coolant Pump NA 004 Chemical and Volume Control NA 005 Residual Heat Removal X A2 Ability to (a) predict the impacts of the 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:

(CFR: 41.5 / 43.5 / 45.3 / 45.13) A2.03 RHR pump/motor malfunction 3.1 86 006 Emergency Core Cooling NA 007 Pressurizer Relief/Quench Tank NA 008 Component Cooling Water NA 010 Pressurizer Pressure Control NA 012 Reactor Protection NA 013 Engineered Safety Features Actuation X A2 Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based Ability on those predictions, use procedures to correct, control, or mitigate the consequences of thos e malfunctions or operations; (CFR: 41.5 / 43.5 / 45.3 / 45.13) A2.02 Excess steam demand 4.5 87 022 Containment Cooling X 2.2.39 Knowledge of less than or equal to one hour Technical Specification action statements for systems. (CFR: 41.10

/ 43.2 / 45.13) 4.5 88 025 Ice Condenser NA 026 Containment Spray NA 039 Main and Reheat Steam X A2 Ability to (a) predict the impacts of the following malfunctions or operations on the MRSS; and (b) based on

predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

(CFR: 41.5 / 43.5 / 45.3 / 45.13) A2.04 Malfunctioning steam dump 3.7 89 059 Main Feedwater NA 061 Auxiliary/Emergency Feedwater NA 062 AC Electrical Distribution NA 063 DC Electrical Distribution NA 064 Emergency Diesel Generator X 2.4.16 Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines such as, operating procedures, abnormal operating procedures, and severe accident management guidelines. (CFR: 41.10

/ 43.5 / 45.13) 4.4 90 073 Process Radiation Monitoring NA 076 Service Water NA 078 Instrument Air NA 103 Containment NA K/A Category Point Totals:

3 2 Group Point Total: 5

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems -Tie r2/Group 2 (SRO)System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4GK/A Topic(s) IR # 001 Control Rod Drive NA 002 Reactor Coolant NA 011 Pressurizer Level Control NA 014 Rod Position Indication NA 015 Nuclear Instrumentation X2.4.9 Knowledge of low power/shutdown implications in accident (e.g., loss of

coolant accident or loss of residual heat removal) mitigation strategies. (CFR: 41.10

/ 43.5 / 45.13) 4.2 91 016 Non-nuclear Instrumentation NA 017 In-core Temperature Monitor NA 027 Containment Iodine Removal NA 028 Hydrogen Recombiner and Purge Control NA 029 Containment Purge NA 033 Spent Fuel Pool Cooling NA 034 Fuel Handling Equipment NA 035 Steam Generator NA 041 Steam Dump/Turbine Bypass Control X A2 Ability to (a) predict the impacts of the following malfunctions or operations on the SDS; and (b) based on those predictions or mitigate the consequences of those malfunctions or operations:

(CFR: 41.5 / 43.5 / 45.3 / 45.13)

A2.02 Steam valve stuck open 3.9 92 045 Main Turbine Generator NA 055 Condenser Air Removal NA 056 Condensate NA 068 Liquid Radwaste NA 071 Waste Gas Disposal NA 072 Area Radiation Monitoring X2.1.32 Ability to explain and apply system limits and precautions. (CFR: 41.10

/ 43.2 / 45.12) 4.0 93 075 Circulating Water NA 079 Station Air NA 086 Fire Protection NA K/A Category Point Totals: 0 0 0 0 000 1002Group Point Total: 3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: South Texas Project Date of Exam: April 30, 2014Category K/A # Topic RO SRO-Only IR # IR Q#

1.

Conduct of Operations 2.1.15 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. (CFR: 41.10 / 43.5 / 45.12) NA NA 4.2 94 2.1.35 2.1.35 Knowledge of the fuel-handling responsibilities of SROs. (CFR: 41.10

/ 43.7) NA NA 3.9 95 2.1. NA NA NA 2.1. NA NA NA 2.1. NA NA NA 2.1. NA NA NA Subtotal NA 2 2.

Equipment Control 2.2.14 2.2.14 Knowledge of the process for controlling equipment configuration or status. (CFR: 41.10

/ 43.3 / 45.13) NA NA 4.3 96 2.2.25 2.2.25 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. (CFR: 41.5/ 41.7/ 43.2) NA NA 4.2 97 2.2. NA NA NA 2.2. NA NA NA 2.2. NA NA NA 2.2. NA NA NA Subtotal NA 2 3.

Radiation Control 2.3.15 2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. (CFR: 41.12

/ 43.4 / 45.9) NA NA 3.1 98 2.3. NA NA NA 2.3. NA NA NA 2.3. NA NA NA Subtotal NA 1 4.

Emergency Procedures / Plan 2.4.6 2.4.6 Knowledge of EOP mitigation strategies. (CFR: 41.10

/ 43.5 / 45.13) NA NA 4.7 99 2.4.41 2.4.41 Knowledge of the emergency action thresholds and clasifications. (CFR: 41.10

/ 43.5/45.11) NA NA 4.6 100 2.4. NA NA NA 2.4. NA NA NA Subtotal NA 2 Tier 3 Point Total NA 7 ES-401 Record of Rejected K/As Form ES-401-4 Tier / Group Randomly Selected K/A Reason for Rejection 1/1 APE 015/17 AK3.04 (Outline Question 4) This KA tested limits for a reduction of power due to an RCP malfunction to below the steady state power to flow limit which is not applicable to STP because any loss of flow due to an RCP malfunction would require a Reactor Trip. Therefore the KA was replaced with KA APE 015/17 AK3.03. 1/1 APE 062 AK3.04 (Outline Question 15)

This KA tested the knowledge of the reasons of the effects on nuclear service water discharge flow header due to loss of CCW. A suitable question could not be developed due to a loss of CCW having no effect on nuclear service water. Therefore the KA was replaced with KA APE 062 AK3.02. 1/2 APE 076 G2.1.44 (Outline Question 26)

This Generic KA tested RO knowledge of control room duties during refueling however this knowledge did not match with High Reactor Coolant Activity. Therefore the Generic KA was replaced with Generic KA G2.1.45. 2/1 063 K4.04 (Outline Question 49)

This KA tested DC electrical system trips of which there are none at STP. Therefore the KA was replaced with KA 063 K4.01. 2/1 064 A4.08 (Outline Question 51)

This KA tested ESF D/G operation after opening the ring bus but STP does not have a ring bus. Therefore the KA was replaced with KA 064 A4.03. 1/1 W/E11 G2.2.12 (Outline Question 81) This Generic KA tested knowledge of surveillance procedures but there was not a tie between that and Loss of Emergency Coolant Recirc.

Therefore the Generic KA was replaced with Generic KA G2.2.39 1/2 024 G2.4.40 (Outline Question 82) This Generic KA can be eliminated per ES401 D.1.b. Therefore the Generic KA was replaced with Generic KA G2.4.46. 2/1 022 G2.3.14 (Outline Question 88)

This Generic KA tested knowledge of radiation or contamination hazards operations or activities. KAs on radiation and contamination topics are determined to be over sampled. Therefore the Generic KA was replaced with Generic KA G2.2.39. 3 G2.1.15 (Outline Question 94)

This Generic KA tested knowledge of administrative requirements for temporary management directives, such as standing orders, night orders, Operations memos, however, the KA was not suitable for an SRO only question. Therefore the Generic KA was replaced with Generic KA G2.1.25. 3 G2.3.12 (Outline Question 98)

This Generic KA tested knowledge of radiological safety principles pertaining to licensed operator duties. KAs on radiation and contamination topics are determined to be over sampled. Therefore the Generic KA was replaced with Generic KA G2.4.41. NOTE: The outline question was changed from 98 to 100. Question 100 was changed to 99 and question 99 was changed to 98.