ML14181A513
| ML14181A513 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 05/01/2014 |
| From: | Vincent Gaddy Operations Branch IV |
| To: | South Texas |
| laura hurley | |
| References | |
| Download: ML14181A513 (25) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 Facility: South Texas Project Date of Exam: April 30, 2014 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 3 3 6 Emergency &
Abnormal Plant 2 2 2 2 N/A 1 1 N/A 1 9 2 2 4 Evolutions Tier Totals 5 5 5 4 4 4 27 5 5 10 1 4 3 1 3 3 1 4 2 3 2 2 28 3 2 5 2.
Plant 2 1 0 1 1 1 1 1 1 1 1 1 10 0 1 2 3 Systems 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 1 2 3 4 10 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 selected.
Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
- 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.
- 8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
- 9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)
E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR Q#
1 2 3 1 2 2.4.49 Ability to perform without reference to 000007 (BW/E02&E10; CE/E02) Reactor X procedures those actions that require immediate 4.6 1 Trip - Stabilization - Recovery / 1 operation of system components and controls.
(CFR: 41.10 / 43.2 / 45.6)
AK1. Knowledge of the operational implications of 000008 Pressurizer Vapor Space X the following concepts as they apply to a 3.2 2 Accident / 3 Pressurizer Vapor Space Accident:
(CFR 41.8 / 41.10 / 45.3)
AK1.01 Thermodynamics and flow characteristics of open or leaking valves EK2 Knowledge of the interrelations between the 000009 Small Break LOCA / 3 X small break LOCA and the following: 3.0 3 (CFR 41.7 / 45.7)
EK2.03 S/Gs . .
000011 Large Break LOCA / 3 NA AK3. Knowledge of the reasons for the following 000015/17 RCP Malfunctions / 4 X responses as they apply to the Reactor Coolant 3.7 4 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.
AA1. Ability to operate and / or monitor the following 000022 Loss of Rx Coolant Makeup / 2 X as they apply to the Loss of Reactor Coolant 2.8 5 Makeup:
(CFR 41.7 / 45.5 / 45.6)
AA1.07 Excess letdown containment isolation valve switches and indicators AA2. Ability to determine and interpret the following 000025 Loss of RHR System / 4 X as they apply to the Loss of Residual Heat Removal 3.4 6 System:
(CFR: 43.5 / 45.13)
AA2.02 Leakage of reactor coolant from RHR into closed cooling water system or into reactor building atmosphere AA2. Ability to determine and interpret the following 000026 Loss of Component Cooling X as they apply to 2.8 7 Water / 8 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 2.2.38 Knowledge of conditions and limitations in 000027 Pressurizer Pressure Control X the facility license. 3.6 8 System Malfunction / 3 (CFR: 41.7/41.10/43.1/45.13)
EK1 Knowledge of the operational implications of 000029 ATWS / 1 X the following concepts as they apply to the ATWS: 2.6 9 (CFR 41.8 / 41.10 / 45.3)
EK1.02 Definition of reactivity EK3 Knowledge of the reasons for the following 000038 Steam Gen. Tube Rupture / 3 X responses as the apply to the SGTR: 4.2 10 (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 000040 (BW/E05; CE/E05; W/E12) NA Steam Line Rupture - Excessive Heat Transfer / 4 AA1. Ability to operate and / or monitor the following 000054 (CE/E06) Loss of Main X as they apply to the Loss of Main Feedwater (MFW): 3.5 11 Feedwater / 4 (CFR 41.7 / 45.5 / 45.6)
AA1.03 AFW auxiliaries, including oil cooling water supply EA2 Ability to determine or interpret the following as 000055 Station Blackout / 6 X they apply to a Station Blackout: 3.7 12 (CFR 43.5 / 45.13)
EA2.06 Faults and lockouts that must be cleared prior to re- energizing buses 2.2.21 Knowledge of pre- and post-maintenance 000056 Loss of Off-site Power / 6 X operability requirements. 2.9 13 (CFR: 41.10 / 43.2) 000057 Loss of Vital AC Inst. Bus / 6 NA AK1. Knowledge of the operational implications of 000058 Loss of DC Power / 6 X the following concepts as they apply to Loss of DC 2.8 14 Power:
(CFR 41.8 / 41.10 / 45.3)
AK1.01 Battery charger equipment and instrumentation AK3. Knowledge of the reasons for the following 000062 Loss of Nuclear Svc Water / 4 X responses as they apply to the Loss of Nuclear 3.6 15 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.
AA1. Ability to operate and / or monitor the following 000065 Loss of Instrument Air / 8 X as they apply to the Loss of Instrument Air: 3.5 16 (CFR 41.7 / 45.5 / 45.6)
AA1.04 Emergency air compressor EK2. Knowledge of the interrelations between the W/E04 LOCA Outside Containment / 3 X (LOCA Outside Containment) and the following: 3.5 17 (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.
W/E11 Loss of Emergency Coolant NA Recirc. / 4 EK2. Knowledge of the interrelations between the BW/E04; W/E05 Inadequate Heat X (Loss of Secondary Heat Sink) and the following: 3.9 18 Transfer - Loss of Secondary Heat Sink / 4 (CFR: 41.7 / 45.7)
EK2.2 Facility*s heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.
000077 Generator Voltage and Electric NA Grid Disturbances / 6 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)
E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR Q#
1 2 3 1 2 AK2. Knowledge of the interrelations 000001 Continuous Rod Withdrawal / 1 X 3.0 19 between the Continuous Rod Withdrawal and the following:
(CFR: 41.7 / 45.7)
AK2.06 T-ave./ref. deviation meter.
000003 Dropped Control Rod / 1 NA 000005 Inoperable/Stuck Control Rod / 1 NA 000024 Emergency Boration / 1 NA AK3. Knowledge of the reasons for the 000028 Pressurizer Level Malfunction / 2 X 3.5 20 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 AK1. Knowledge of the operational 000032 Loss of Source Range NI / 7 X 2.5 21 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 000033 Loss of Intermediate Range NI / 7 NA 000036 (BW/A08) Fuel Handling Accident / 8 NA 000037 Steam Generator Tube Leak / 3 NA AK3. Knowledge of the reasons for the 000051 Loss of Condenser Vacuum / 4 X 2.8 22 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 000059 Accidental Liquid RadWaste Rel. / 9 NA AK2. Knowledge of the interrelations 000060 Accidental Gaseous Radwaste Rel. / 9 X 2.6 23 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 AA1. Ability to operate and / or monitor the 000061 ARM System Alarms / 7 X 3.6 24 following as they apply to the Area Radiation Monitoring (ARM)System Alarms:
(CFR 41.7 / 45.5 / 45.6)
AA1.01 Automatic actuation
AA2. Ability to determine and interpret the 000067 Plant Fire On-site / 8 X 3.3 25 following as they apply to the Plant Fire on Site:
(CFR: 43.5 / 45.13)
AA2.13 Need for emergency plant shutdown 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 2.1.45 Ability to identify and interpret diverse 000076 High Reactor Coolant Activity / 9 X 4.3 26 indications to validate the response of another indication.
(CFR: 41.7/ 43.5 / 45.4)
W/EO1 & E02 Rediagnosis & SI Termination / 3 NA W/E13 Steam Generator Over-pressure / 4 NA EK1. Knowledge of the operational W/E15 Containment Flooding / 5 X 2.8 27 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.
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: 2 2 2 1 1 1 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)
System # / Name K K K K K K A A A A G K/A Topic(s) IR Q#
1 2 3 4 5 6 1 2 3 4 K4 Knowledge of RCPS design 003 Reactor Coolant Pump X feature(s) and/or interlock(s) which 2.8 28 provide for the following:
(CFR: 41.7)
K4.04 Adequate cooling of RCP motor and seals.
K5 Knowledge of the operational 004 Chemical and Volume X implications of the following concepts as 2.5 29 Control 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 K6 Knowledge of the effect of a loss or 005 Residual Heat Removal X malfunction on the following will have on 2.5 30 the RHRS:
(CFR: 41.7 / 45.7)
K6.03 RHR heat exchanger K1 Knowledge of the physical 006 Emergency Core Cooling X connections and/or cause effect 4.2 31 relationships between the ECCS and the following systems:
(CFR: 41.2 to 41.9 / 45.7 to 45.8)
K1.03 RCS A1 Ability to predict and/or monitor 006 Emergency Core Cooling X changes in parameters (to prevent 4.2 32 exceeding design limits) associated with operating the ECCS controls including:
(CFR: 41.5 / 45.5)
A1.17 ECCS flow rate A2 Ability to (a) predict the impacts of 007 Pressurizer Relief/Quench X the following malfunctions or operations 3.2 33 Tank 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
A3 Ability to monitor automatic operation 008 Component Cooling Water X of the CCWS, including: 3.2 34 (CFR: 41.7 / 45.5)
A3.02 Operation of the CCW pumps, including interlocks and the CCW booster pump K1 Knowledge of the physical 010 Pressurizer Pressure Control X connections and/or cause-effect 3.9 35 relationships between the PZR PCS and the following systems:
(CFR: 41.2 to 41.9 / 45.7 to 45.8)
K1.01 RP A4 Ability to manually operate and/or 010 Pressurizer Pressure Control X monitor in the control room: 3.7 36 (CFR: 41.7 / 45.5 to 45.8)
A4.01 PZR spray valve K4 Knowledge of RPS design feature(s) 012 Reactor Protection X and/or interlock(s) which provide for the 2.8 37 following:
(CFR: 41.7)
K4.08 Logic matrix testing 2.2.18 Knowledge of the process for 012 Reactor Protection X managing maintenance activities during 2.6 38 shutdown operations, such as risk assessments, work prioritization, etc.
(CFR: 41.10 / 43.5 / 45.13)
K1 Knowledge of the physical 013 Engineered Safety Features X connections and/or cause effect 3.9 39 Actuation relationships between the ESFAS and the following systems:
(CFR: 41.2 to 41.9 / 45.7 to 45.8)
K1.04 RPS injection K2 Knowledge of bus power supplies to 013 Engineered Safety Features X the following: 3.6 40 Actuation (CFR: 41.7)
K2.01 ESFAS/safeguards equipment control K2 Knowledge of power supplies to the 022 Containment Cooling X following: 2.5 41 (CFR: 41.7)
K2.02 Chillers A1 Ability to predict and/or monitor 022 Containment Cooling X changes in parameters (to prevent 3.1 42 exceeding design limits) associated with operating the CCS controls including:
(CFR: 41.5 / 45.5)
A1.03 Containment humidity 025 Ice Condenser NA
K4 Knowledge of CSS design feature(s) 026 Containment Spray X and/or interlock(s) which provide for the 3.8 43 following:
(CFR: 41.7)
K4.07 Adequate level in containment sump for suction (interlock)
K5 Knowledge of the operational 039 Main and Reheat Steam X implications of the following concepts as 2.9 44 the apply to the MRSS:
(CFR: 441.5 / 45.7)
K5.01 Definition and causes of steam/water hammer A3 Ability to monitor automatic operation 039 Main and Reheat Steam X of the MRSS, including: 3.1 45 (CFR: 41.5 / 45.5)
A3.02 Isolation of the MRSS A1 Ability to predict and/or monitor 059 Main Feedwater X changes in parameters (to prevent 2.5 46 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 A1 Ability to predict and/or monitor 061 Auxiliary/Emergency X changes in parameters (to prevent 3.1 47 Feedwater exceeding design limits) associated with operating the AFW controls including:
(CFR: 41.5 / 45.5)
A1.04 AFW source tank level A2 Ability to (a) predict the impacts of 062 AC Electrical Distribution X the following malfunctions or operations 3.2 48 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 K4 Knowledge of DC electrical system 063 DC Electrical Distribution X design feature(s) and/or interlock(s) 2.7 49 which provide for the following:
(CFR: 41.7)
K4.01 Manual/automatic transfers of controls.
A3 Ability to monitor automatic operation 063 DC Electrical Distribution X of the DC electrical system, including: 2.7 50 (CFR: 41.7 / 45.5)
A3.01 Meters, annunciators, dials, recorders, and indicating lights
A4 Ability to manually operate and/or 064 Emergency Diesel Generator X monitor in the control room: 3.2 51 (CFR: 41.7 / 45.5 to 45.8)
A4.03 Synchroscope.
2.1.14 Knowledge of criteria or 073 Process Radiation X conditions that require plant-wide 3.1 52 Monitoring announcements, such as pump starts, reactor trips, mode changes, etc.
(CFR: 41.10/43.5/45.12)
K1 Knowledge of the physical 076 Service Water X connections and/or cause- effect 3.0 53 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 K2 Knowledge of bus power supplies to 078 Instrument Air X the following: 2.7 54 (CFR: 41.7)
K2.01 Instrument air compressor K3 Knowledge of the effect that a loss or 103 Containment X malfunction of the containment system 3.7 55 will have on the following:
(CFR: 41.7 / 45.6)
K3.03 Loss of containment integrity under refueling operations K/A Category Point Totals: 4 3 1 3 3 1 4 2 3 2 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)
System # / Name K K K K K K A A A A G K/A Topic(s) IR Q#
1 2 3 4 5 6 1 2 3 4 K3 Knowledge of the effect that a loss or 001 Control Rod Drive X malfunction of the CRDS will have on the 2.9 56 following:
(CFR: 41.7/45.6)
K3.01 CVCS 002 Reactor Coolant NA K5 Knowledge of the operational 011 Pressurizer Level Control X implications of the following concepts as 2.8 57 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 014 Rod Position Indication NA 015 Nuclear Instrumentation NA K4 Knowledge of NNIS design feature(s) 016 Non-nuclear Instrumentation X and/or interlock(s) which provide for the 2.8 58 following:
(CFR: 41.7)
K4.03 Input to control systems 017 In-core Temperature Monitor NA A2 Ability to (a) predict the impacts of the 027 Containment Iodine Removal X following malfunctions or operations on the 3.0 59 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 028 Hydrogen Recombiner NA and Purge Control A1 Ability to predict and/or monitor 029 Containment Purge X changes in parameters to prevent 3.0 60 exceeding design limits) associated with operating the Containment Purge System controls including:
(CFR: 41.5 / 45.5)
A1.03 Containment pressure, temperature, and humidity 033 Spent Fuel Pool Cooling NA 034 Fuel Handling Equipment NA 035 Steam Generator NA
A3 Ability to monitor automatic operation of 041 Steam Dump/Turbine X the SDS, including: 2.7 61 Bypass Control (CFR: 41.7 / 45.5)
A3.03 Steam flow 045 Main Turbine Generator NA 055 Condenser Air Removal NA K1 Knowledge of the physical connections 056 Condensate X and/or cause-effect relationships between 2.6 62 the Condensate System and the following systems:
(CFR: 41.2 to 41.9 / 45.7 to 45.8)
K1.03 MFW 2.3.11 Ability to control radiation releases.
068 Liquid Radwaste X 3.8 63 (CFR: 41.11 / 43.4 / 45.10) 071 Waste Gas Disposal NA 072 Area Radiation Monitoring NA 075 Circulating Water NA A4 Ability to manually operate and/or 079 Station Air X monitor in the control room: 2.7 64 (CFR: 41.7 / 45.5 to 45.8)
A4.01 Cross-tie valves with IAS K6 Knowledge of the effect of a loss or 086 Fire Protection X malfunction on the Fire Protection System 2.6 65 following will have on the :
(CFR: 41.7 / 45.7)
K6.04 Fire, smoke, and heat detectors K/A Category Point Totals: 1 0 1 1 1 1 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 Date of Exam: April 30, 2014 Category K/A # Topic RO SRO-Only IR Q# IR #
2.1.5 Ability to use procedures related to shift staffing, such as 2.1.5 2.9 66 NA NA minimum crew complement, overtime limitations, etc.
- 1. (CFR: 41.10 / 43.5 / 45.12)
Conduct 2.1.39 Knowledge of conservative decision making practices.
of Operations 2.1.39 3.6 67 NA NA (CFR: 41.10 / 43.5 / 45.12) 2.1. NA NA NA 2.1. NA NA NA 2.1. NA NA NA 2.1. NA NA NA Subtotal 2 NA 2.2.1 Ability to perform pre-startup procedures for the facility, 2.2.1 4.5 68 NA NA including operating those controls associated with plant equipment that could affect reactivity.
2.
Equipment (CFR: 41.5 / 41.10 / 43.5 / 43.6 / 45.1)
Control 2.2.36 Ability to analyze the effect of maintenance activities, such 2.2.36 3.1 69 NA NA as degraded power sources, on the status of limiting conditions for operations.
(CFR: 41.10 / 43.2 / 45.13) 2.2.37 Ability to determine operability and/or availability of safety 2.2.37 3.6 70 NA NA related equipment.
(CFR: 41.7 / 43.5 / 45.12) 2.2. NA NA NA 2.2. NA NA NA 2.2. NA NA NA Subtotal 3 NA 2.3.5 Ability to use radiation monitoring systems, such as fixed 2.3.5 2.9 71 NA NA radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.
- 3. (CFR: 41.11/41.12/43.4/45.9)
Radiation Control 2.3.12 Knowledge of radiological safety principles pertaining to 2.3.12 3.2 72 NA NA licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
(CFR: 41.12 / 45.9/45.10) 2.3. NA NA NA 2.3. NA NA NA 2.3. NA NA NA 2.3. NA NA NA Subtotal 2 2.4.1 Knowledge of EOP entry conditions and immediate action 2.4.1 4.6 73 NA NA steps.
- 4. (CFR: 41.10 / 43.5 / 45.13)
Emergency 2.4.8 Knowledge of how abnormal operating procedures are Procedures / Plan 2.4.8 3.8 74 NA NA used in conjunction with EOPs.
(CFR: 41.10 / 43.5 / 45.13)
2.4.12 Knowledge of general operating crew responsibilities 2.4.12 4.0 75 NA NA during emergency operations.
(CFR: 41.10 / 45.12) 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 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO)
E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR Q#
1 2 3 1 2 EA2 Ability to determine or interpret the following as 000007 (BW/E02&E10; CE/E02) Reactor X they apply to a reactor trip: 3.9 76 Trip - Stabilization - Recovery / 1 (CFR 41.7 / 45.5 / 45.6)
EA2.05 Reactor trip first-out indication 000008 Pressurizer Vapor Space NA Accident / 3 EA2 Ability to determine or interpret the following as 000009 Small Break LOCA / 3 X they apply to a small break LOCA: 4.7 77 (CFR 43.5 / 45.13)
EA2.39 Adequate core cooling 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 NA Water / 8 000027 Pressurizer Pressure Control NA System Malfunction / 3 000029 ATWS / 1 NA 000038 Steam Gen. Tube Rupture / 3 NA 000040 (BW/E05; CE/E05; W/E12) NA Steam Line Rupture - Excessive Heat Transfer / 4 AA2. Ability to determine and interpret the following 000054 (CE/E06) Loss of Main X as they apply to the Loss of Main Feedwater (MFW): 4.3 78 Feedwater / 4 (CFR: 43.5 / 45.13)
AA2.06 AFW adjustments needed to maintain proper T-ave. and S/G level 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 2.3.4 Knowledge of radiation exposure limits under 000062 Loss of Nuclear Svc Water / 4 X normal or emergency conditions. 3.7 79 (CFR: 41.12 / 43.4 / 45.10) 2.1.36 Knowledge of procedures and limitations 000065 Loss of Instrument Air / 8 X involved in core alterations. 4.1 80 (CFR: 41.10 / 43.6 / 45.7)
W/E04 LOCA Outside Containment / 3 NA
2.2. 39 Knowledge of less than or equal to one hour W/E11 Loss of Emergency Coolant X Technical Specification action statements for 4.5 81 Recirc. / 4 systems.
(CFR: 41.7 / 41.10 / 43.2 / 45.13)
BW/E04; W/E05 Inadequate Heat NA Transfer - Loss of Secondary Heat Sink / 4 000077 Generator Voltage and Electric NA Grid Disturbances / 6 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 K K A A G K/A Topic(s) IR #
1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 NA 000003 Dropped Control Rod / 1 NA 000005 Inoperable/Stuck Control Rod / 1 NA 2.4.46 Ability to verify that the alarms are 000024 Emergency Boration / 1 X 4.2 82 consistent with the plant conditions.
(CFR: 41.10/43.5/45.3/45.12) 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 AA2. Ability to determine and interpret the 000060 Accidental Gaseous Radwaste Rel. / 9 X 3.4 83 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 radioactive-gas leak 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 EA2. Ability to determine and interpret the W/EO1 & E02 Rediagnosis & SI Termination / 3 X 4.0 84 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 facilitys license and amendments.
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
2.4.37 Knowledge of the lines of authority BW/E08; W/E03 LOCA Cooldown - Depress. / 4 X 4.1 85 during implementation of the emergency plan.
(CFR: 41.10 / 45.13)
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: 0 0 0 0 2 2 Group Point Total: 4
ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (SRO)
System # / Name K K K K K K A A A A G K/A Topic(s) IR Q#
1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump NA 004 Chemical and Volume NA Control A2 Ability to (a) predict the impacts of 005 Residual Heat Removal X the following malfunctions or operations 3.1 86 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 006 Emergency Core Cooling NA 007 Pressurizer Relief/Quench NA Tank 008 Component Cooling Water NA 010 Pressurizer Pressure Control NA 012 Reactor Protection NA A2 Ability to (a) predict the impacts of 013 Engineered Safety Features X the following malfunctions or operations 4.5 87 Actuation on the ESFAS; and (b) based Ability on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations; (CFR: 41.5 / 43.5 / 45.3 / 45.13)
A2.02 Excess steam demand 2.2.39 Knowledge of less than or equal 022 Containment Cooling X to one hour Technical Specification 4.5 88 action statements for systems.
(CFR: 41.10 / 43.2 / 45.13) 025 Ice Condenser NA 026 Containment Spray NA A2 Ability to (a) predict the impacts of 039 Main and Reheat Steam X the following malfunctions or operations 3.7 89 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 059 Main Feedwater NA 061 Auxiliary/Emergency NA Feedwater
062 AC Electrical Distribution NA 063 DC Electrical Distribution NA 2.4.16 Knowledge of EOP 064 Emergency Diesel Generator X implementation hierarchy and 4.4 90 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) 073 Process Radiation NA Monitoring 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 - Tier 2/Group 2 (SRO)
System # / Name K K K K K K A A A A G K/A Topic(s) IR #
1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive NA 002 Reactor Coolant NA 011 Pressurizer Level Control NA 014 Rod Position Indication NA 2.4.9 Knowledge of low power/shutdown 015 Nuclear Instrumentation X implications in accident (e.g., loss of 4.2 91 coolant accident or loss of residual heat removal) mitigation strategies.
(CFR: 41.10 / 43.5 / 45.13) 016 Non-nuclear Instrumentation NA 017 In-core Temperature Monitor NA 027 Containment Iodine Removal NA 028 Hydrogen Recombiner NA and Purge Control 029 Containment Purge NA 033 Spent Fuel Pool Cooling NA 034 Fuel Handling Equipment NA 035 Steam Generator NA A2 Ability to (a) predict the impacts of the 041 Steam Dump/Turbine X following malfunctions or operations on the 3.9 92 Bypass Control 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 045 Main Turbine Generator NA 055 Condenser Air Removal NA 056 Condensate NA 068 Liquid Radwaste NA 071 Waste Gas Disposal NA 2.1.32 Ability to explain and apply system 072 Area Radiation Monitoring X limits and precautions. 4.0 93 (CFR: 41.10 / 43.2 / 45.12) 075 Circulating Water NA 079 Station Air NA 086 Fire Protection NA
K/A Category Point Totals: 0 0 0 0 0 0 0 1 0 0 2 Group 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, 2014 Category K/A # Topic RO SRO-Only IR # IR Q#
2.1.25 Ability to interpret reference materials, such as graphs, 2.1.25 NA NA 4.2 94 curves, tables, etc.
- 1. (CFR: 41.10 / 43.5 / 45.12)
Conduct 2.1.35 Knowledge of the fuel-handling responsibilities of SROs.
of Operations 2.1.35 NA NA 3.9 95 (CFR: 41.10 / 43.7) 2.1. NA NA NA 2.1. NA NA NA 2.1. NA NA NA 2.1. NA NA NA Subtotal NA 2 2.2.14 Knowledge of the process for controlling equipment 2.2.14 NA NA 4.3 96 configuration or status.
(CFR: 41.10 / 43.3 / 45.13)
- 2. 2.2.25 Knowledge of the bases in Technical Specifications for Equipment 2.2.25 NA NA 4.2 97 limiting conditions for operations and safety limits.
Control (CFR: 41.5/ 41.7/ 43.2) 2.2. NA NA NA 2.2. NA NA NA 2.2. NA NA NA 2.2. NA NA NA Subtotal NA 2 2.3.15 Knowledge of radiation monitoring systems, such as fixed 2.3.15 NA NA 3.1 98 radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.
- 3. (CFR: 41.12 / 43.4 / 45.9)
Radiation Control 2.3. NA NA NA 2.3. NA NA NA 2.3. NA NA NA Subtotal NA 1 2.4.6 Knowledge of EOP mitigation strategies.
2.4.6 NA NA 4.7 99 (CFR: 41.10 / 43.5 / 45.13)
- 4. 2.4.41 Knowledge of the emergency action thresholds and Emergency 2.4.41 NA NA 4.6 100 clasifications.
Procedures / Plan (CFR: 41.10 / 43.5/45.11) 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/ Randomly Selected Reason For Rejection Group K/A 1/1 APE 015/17 AK3.04 This KA tested limits for a reduction of power due to an RCP (Outline Question 4) 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 This KA tested the knowledge of the reasons of the effects on (Outline Question 15) 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 This Generic KA tested RO knowledge of control room duties (Outline Question 26) 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.
2/1 003 K4.02 This KA tested RCP design features or interlocks associated with (Outline Question 28) cold water accidents or transients of which there are none at STP. Therefore the KA was replaced with KA 003 K4.04.
2/1 063 K4.04 This KA tested DC electrical system trips of which there are (Outline Question 49) none at STP. Therefore the KA was replaced with KA 063 K4.01.
2/1 064 A4.08 This KA tested ESF D/G operation after opening the ring bus but (Outline Question 51) STP does not have a ring bus. Therefore the KA was replaced with KA 064 A4.03.
3 G2.4.11 This generic KA tested knowledge of abnormal condition (Outline Question 74) procedures. At STP the procedure describing abnormal procedure use is very generic and straight forward. Therefore a suitable question could not be developed. Therefore the Generic KA was replaced with KA G2.4.8.
1/1 W/E11 G2.2.12 This Generic KA tested knowledge of surveillance procedures (Outline Question 81) 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 This Generic KA can be eliminated per ES401 D.1.b. Therefore (Outline Question 82) the Generic KA was replaced with Generic KA G2.4.46.
2/1 022 G2.3.14 This Generic KA tested knowledge of radiation or contamination (Outline Question 88) 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 This Generic KA tested knowledge of administrative (Outline Question 94) 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 This Generic KA tested knowledge of radiological safety (Outline Question 98) 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.