ML19247D694
| ML19247D694 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 07/29/2019 |
| From: | Greg Werner Operations Branch IV |
| To: | South Texas |
| References | |
| Download: ML19247D694 (36) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 Facility: STPNOC Date of Exam: 07-29-2019 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 6
2 2
2 2
1 1
1 9
4 Tier Totals 5
5 5
4 4
4 27 10
- 2.
Plant Systems 1
3 2
2 4
2 2
2 3
3 3
2 28 5
2 2
0 1
2 1
0 1
1 0
1 1
10 3
Tier Totals 5
2 3
6 3
2 3
4 3
4 3
38 8
- 3. Generic Knowledge and Abilities Categories 1
3 2
3 3
2 4
2 10 1
2 3
4 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).
- 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
- These systems/evolutions must be included as part of the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the K/A catalog.
- These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan.
ES-401 2
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)
E/APE # / Name / Safety Function K
1 K
2 K
3 A
1 A
2 G*
K/A Topic(s)
IR 000007 (BW/E02&E10; CE/E02) Reactor Trip - Stabilization - Recovery / 1 000008 Pressurizer Vapor Space Accident / 3 X
2.4.3 Ability to identify post-accident instrumentation.
(CFR: 41.6 / 45.4) 3.7 1
000009 Small Break LOCA / 3 X
2.4.21 Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.
(CFR: 41.7 / 43.5 / 45.12) 4.0 2
000011 Large Break LOCA / 3 000015/17 RCP Malfunctions / 4 X
AK3.07 Knowledge of the reasons for the following responses as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): Ensuring that S/G levels are controlled properly for natural circulation enhancement.
(CFR 41.5, 41.10 / 45.6 / 45.13) 4.1 3
000022 Loss of Rx Coolant Makeup / 2 X
AA1.08 Ability to operate and / or monitor the following as they apply to the Loss of Reactor Coolant Makeup: VCT level (CFR 41.7 / 45.5 / 45.6) 3.4 4
000025 Loss of RHR System / 4 X
AK1.01 Knowledge of the operational implications of the following concepts as they apply to Loss of Residual Heat Removal System: Loss of RHRS during all modes of operation (CFR 41.8 / 41.10 / 45.3) 3.9 5
000026 Loss of Component Cooling Water / 8 X
AA2.04 Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: The normal values and upper limits for the temperatures of the components cooled by CCW (CFR: 43.5 / 45.13) 2.5 6
000027 Pressurizer Pressure Control System Malfunction / 3 X
AK2.03 Knowledge of the interrelations between the Pressurizer Pressure Control Malfunctions and the following: Controllers and positioners (CFR 41.7 / 45.7) 2.6 7
000029 ATWS / 1 X
EA1.12 Ability to operate and monitor the following as they apply to a ATWS: M/G set power supply and reactor trip breakers (CFR 41.7 / 45.5 / 45.6) 4.1 8
000038 Steam Gen. Tube Rupture / 3 X
EK1.01 Knowledge of the operational implications of the following concepts as they apply to the SGTR: Use of steam tables (CFR 41.8 / 41.10 / 45.3) 3.1 9
000040 (BW/E05; CE/E05; W/E12)
Steam Line Rupture - Excessive Heat Transfer / 4 X
AK2.02 Knowledge of the interrelations between the Steam Line Rupture and the following: Sensors and detectors (CFR 41.7 / 45.7) 2.6 10
000054 (CE/E06) Loss of Main Feedwater / 4 X
AK3.04 Knowledge of the reasons for the following responses as they apply to the Loss of Main Feedwater (MFW): Actions contained in EOPs for loss of MFW (CFR 41.5,41.10 / 45.6 / 45.13) 4.4 11 000055 Station Blackout / 6 000056 Loss of Off-site Power / 6 X
AA2.45 Ability to determine and interpret the following as they apply to the Loss of Offsite Power: Indicators to assess status of ESF breakers (tripped/not-tripped) and validity of alarms (false/not-false)
(CFR: 43.5 / 45.13) 3.6 12 000057 Loss of Vital AC Inst. Bus / 6 X
AA1.06 Ability to operate and / or monitor the following as they apply to the Loss of Vital AC Instrument Bus: Manual control of components for which automatic control is lost (CFR 41.7 / 45.5 / 45.6) 3.5 13 000058 Loss of DC Power / 6 X
2.2.37 Ability to determine operability and/or availability of safety related equipment.
(CFR: 41.7 / 43.5 / 45.12) 3.5 14 000062 Loss of Nuclear Svc Water / 4 X
AK3.01 Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear Service Water: The conditions that will initiate the automatic opening and closing of the SWS isolation valves to the nuclear service water coolers (CFR 41.4, 41.8 / 45.7 )
3.2 15 000065 Loss of Instrument Air / 8 X
AA2.08 Ability to determine and interpret the following as they apply to the Loss of Instrument Air: Failure modes of air-operated equipment.
(CFR: 43.5 / 45.13) 2.9 16 W/E04 LOCA Outside Containment / 3 W/E11 Loss of Emergency Coolant Recirc. / 4 X
EK1.3 Knowledge of the operational implications of the following concepts as they apply to the (Loss of Emergency Coolant Recirculation) Annunciators and conditions indicating signals, and remedial actions associated with the (Loss of Emergency Coolant Recirculation).
(CFR: 41.8 / 41.10 / 45.3) 3.6 17 BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 000077 Generator Voltage and Electric Grid Disturbances / 6 X
AK2.07 Knowledge of the interrelations between Generator Voltage and Electric Grid Disturbances and the following: Turbine /
generator control.
(CFR: 41.4, 41.5, 41.7, 41.10 / 45.8) 3.6 18 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
1 K
2 K
3 A
1 A
2 G*
K/A Topic(s)
IR 000001 Continuous Rod Withdrawal / 1 X
AK1.18 Knowledge of the operational implications of the following concepts as they apply to Continuous Rod Withdrawal: Fuel temperature coefficient.
(CFR 41.8 / 41.10 / 45.3) 3.4 19 000003 Dropped Control Rod / 1 000005 Inoperable/Stuck Control Rod / 1 X
AK2.02 Knowledge of the interrelations between the Inoperable / Stuck Control Rod and the following: Breakers, relays, disconnects, and control room switches (CFR 41.7 / 45.7) 2.5 20 000024 Emergency Boration / 1 000028 Pressurizer Level Malfunction / 2 000032 Loss of Source Range NI / 7 X
AK3.01 Knowledge of the reasons for the following responses as they apply to the Loss of Source Range Nuclear Instrumentation: Startup termination on source-range loss (CFR 41.5,41.10 / 45.6 / 45.13) 3.2 21 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 X
2.1.32 Ability to explain and apply system limits and precautions.
(CFR: 41.10 / 43.2 / 45.12) 4.0 22 000059 Accidental Liquid Radwaste Rel. / 9 000060 Accidental Gaseous Radwaste Rel. / 9 000061 ARM System Alarms / 7 000067 Plant Fire On-site / 8 000068 (BW/A06) Control Room Evac. / 8 000069 (W/E14) Loss of CTMT Integrity / 5 X
AK2.03 Knowledge of the interrelations between the Loss of Containment Integrity and the following: Personnel access hatch and emergency access hatch (CFR 41.7 / 45.7) 2.8 23 000074 (W/E06&E07) Inad. Core Cooling / 4 X
EA2.03 Ability to determine or interpret the following as they apply to Inadequate Core Cooling: Availability of turbine bypass valves for cooldown (CFR 43.5 / 45.13) 3.8 24 000076 High Reactor Coolant Activity / 9 W/EO1 & E02 Rediagnosis & SI Termination / 3
W/E13 Steam Generator Over-pressure / 4 X
EA1.1 Ability to operate and / or monitor the following as they apply to the (Steam Generator Overpressure)
Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
(CFR: 41.7 / 45.5 / 45.6) 3.1 25 W/E15 Containment Flooding / 5 X
EK3.2 Knowledge of the reasons for the following responses as they apply to Containment Flooding: Normal, abnormal and emergency operating procedures associated with Containment Flooding.
(CFR: 41.5 / 41.10, 45.6, 45.13) 2.8 26 W/E16 High Containment Radiation / 9 BW/A01 Plant Runback / 1 BW/A02&A03 Loss of NNI-X/Y / 7 BW/A04 Turbine Trip / 4 BW/A05 Emergency Diesel Actuation / 6 BW/A07 Flooding / 8 BW/E03 Inadequate 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 X
EK1.3 Knowledge of the operational implications of the following concepts as they apply to Pressurized Thermal Shock: Annunciators and conditions indicating signals, and remedial actions associated with Pressurized Thermal Shock.
(CFR: 41.8 / 41.10, 45.3) 3.5 27 CE/A16 Excess RCS Leakage / 2 CE/E09 Functional Recovery 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
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 003 Reactor Coolant Pump X
K4.04 Knowledge of RCPS design feature(s) and/or interlock(s) which provide for the following: Adequate cooling of RCP motor and seals (CFR: 41.7) 2.8 28 004 Chemical and Volume Control X
K5.14 Knowledge of the operational implications of the following concepts as they apply to the CVCS: Reduction process of gas concentration in RCS: vent accumulated non-condensable gases from PZR bubble space, depressurized during cooldown or by alternately heating and cooling (spray) within allowed pressure band (drive more gas out of solution)
(CFR: 41.5/45.7) 2.5 29 005 Residual Heat Removal X
2.4.4 Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
(CFR: 41.10 / 43.2 / 45.6) 4.5 30 005 Residual Heat Removal X
K1.04 Knowledge of the physical connections and/or cause-effect relationships between the RHRS and the following systems: CVCS.
(CFR: 41.2 to 41.9 / 45.7 to 45.8) 2.9 31 006 Emergency Core Cooling X
A4.11 Ability to manually operate and/or monitor in the control room:
Overpressure protection system.
(CFR: 41.7 / 45.5 to 45.8) 4.2 32 007 Pressurizer Relief/Quench Tank X
A3.01 Ability to monitor automatic operation of the PRTS, including:
Components which discharge to the PRT (CFR: 41.7 / 45.5) 2.7 33 008 Component Cooling Water X
K3.01 Knowledge of the effect that a loss or malfunction of the CCWS will have on the following: Loads cooled by CCWS 3.4 34 008 Component Cooling Water X
K2.02 Knowledge of bus power supplies to the following: CCW pump, including emergency backup.
(CFR: 41.7) 3.0 35 010 Pressurizer Pressure Control X
K6.01 Knowledge of the effect of a loss or malfunction of the following will have on the PZR PCS:
Pressure detection systems (CFR: 41.7 / 45.7) 2.7 36 012 Reactor Protection X
K5.02 Knowledge of the operational implications of the following concepts as the apply to the RPS: Power density (CFR: 41.5 / 45.7) 3.1 37
012 Reactor Protection X
A1.01 Ability to predict and/or monitor Changes in parameters (to prevent exceeding design limits) associated with operating the RPS controls including: Trip setpoint adjustment (CFR: 41.5 / 45.5) 2.9 38 013 Engineered Safety Features Actuation X
2.4.9 Knowledge of low power /
shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.
(CFR: 41.10 / 43.5 / 45.13) 3.8 39 013 Engineered Safety Features Actuation X
A2.05 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 those malfunctions or operations; Loss of dc control power (CFR: 41.5 / 43.5 / 45.3 / 45.13) 3.7 40 022 Containment Cooling X
A3.01 Ability to monitor automatic operation of the CCS, including:
Initiation of safeguards mode of operation (CFR: 41.7 / 45.5) 4.1 41 025 Ice Condenser 026 Containment Spray X
A4.05 Ability to manually operate and/or monitor in the control room:
Containment spray reset switches (CFR: 41.7 / 45.5 to 45.8) 3.5 42 039 Main and Reheat Steam X
K3.05 Knowledge of the effect that a loss or malfunction of the MRSS will have on the following: RCS (CFR: 41.7 / 45.6) 3.6 43 059 Main Feedwater X
K4.13 Knowledge of MFW design feature(s) and/or interlock(s) which provide for the following:
Feedwater fill for S/G upon loss of RCPs.
(CFR: 41.7) 2.9 44 061 Auxiliary/Emergency Feedwater X
A1.04 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the AFW controls including: AFW source tank level.
(CFR: 41.5 / 45.5) 3.9 45 061 Auxiliary/Emergency Feedwater X
K1.01 Knowledge of the physical connections and/or cause-effect relationships between the AFW and the following systems: S/G system (CFR: 41.2 to 41.9 / 45.7 to 45.8) 4.1 46
062 AC Electrical Distribution X
A2.03 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:
Consequences of improper sequencing when transferring to or from an inverter.
(CFR: 41.5 / 43.5 / 45.3 / 45.13) 2.9 47 062 AC Electrical Distribution X
K4.05 Knowledge of ac distribution system design feature(s) and/or interlock(s) which provide for the following: Paralleling of AC sources (synchroscope).
(CFR: 41.7) 2.7 48 063 DC Electrical Distribution X
A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the DC electrical systems; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Grounds (CFR: 41.5 / 43.5 / 45.3 / 45.13) 2.5 49 064 Emergency Diesel Generator X
K4.01 Knowledge of ED/G system design feature(s) and/or interlock(s) which provide for the following: Trips while loading the ED/G (frequency, voltage, speed)
(CFR: 41.7) 3.8 50 064 Emergency Diesel Generator X
K6.07 Knowledge of the effect of a loss or malfunction of the following will have on the ED/G system: Air receivers (CFR: 41.7 / 45.7) 2.7 51 073 Process Radiation Monitoring X
K1.01 Knowledge of the physical connections and/or cause-effect relationships between the PRM system and the following systems:
Those systems served by PRMs (CFR: 41.2 to 41.9 / 45.7 to 45.8) 3.6 52 076 Service Water X
K2.08 Knowledge of bus power supplies to the following: ESF-actuated MOVs (CFR: 41.7) 3.1 53 078 Instrument Air X
A3.01 Ability to monitor automatic operation of the IAS, including: Air pressure (CFR: 41.7 / 45.5) 3.1 54 103 Containment X
A4.04 Ability to manually operate and/or monitor in the control room:
Phase A and phase B resets.
(CFR: 41.7 / 45.5 to 45.8) 3.5 55 K/A Category Point Totals:
3 2 2 4 2 2 2 3 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)
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 001 Control Rod Drive 002 Reactor Coolant X
K1.07 Knowledge of the physical connections and/or cause-effect relationships between the RCS and the following systems: Reactor vessel level indication system (CFR: 41.2 to 41.9 / 45.7 to 45.8) 3.5 56 011 Pressurizer Level Control 014 Rod Position Indication X
K4.06 Knowledge of RPIS design feature(s) and/or interlock(s) which provide for the following:
Individual and group misalignment.
(CFR: 41.5 / 45.7) 3.4 57 015 Nuclear Instrumentation X
A1.05 Ability to predict and/or monitor changes in parameters to prevent exceeding design limits) associated with operating the NIS controls including: Imbalance (axial shape)
(CFR: 41.5. 45.5) 3.7 58 016 Non-Nuclear Instrumentation 017 In-Core Temperature Monitor 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 029 Containment Purge 033 Spent Fuel Pool Cooling X
A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the Spent Fuel Pool Cooling System ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of SFPCS (CFR: 41.5 / 43.5 / 45.3 / 45.13) 2.7 59 034 Fuel Handling Equipment 035 Steam Generator X
K5.01 Knowledge of operational implications of the following concepts as they apply to the S/GS: Effect of secondary parameters, pressure, and temperature on reactivity.
(CFR: 41.5 / 45.7) 3.4 60 041 Steam Dump/Turbine Bypass Control X
A4.04 Ability to manually operate and/or monitor in the control room:
Pressure mode (CFR: 41.7 / 45.5 to 45.8) 2.7 61
045 Main Turbine Generator X
K3.01 Knowledge of the effect that a loss or malfunction of the MT/G system will have on the following:
Remainder of the plant.
(CFR: 41.7 / 45.6) 2.9 62 055 Condenser Air Removal 056 Condensate X
K1.03 Knowledge of the physical connections and/or cause-effect relationships between the Condensate System and the following systems: MFW (CFR: 41.2 to 41.9 / 45.7 to 45.8) 2.6 63 068 Liquid Radwaste 071 Waste Gas Disposal 072 Area Radiation Monitoring X
2.2.44 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.
(CFR: 41.5 / 43.5 / 45.12) 4.2 64 075 Circulating Water 079 Station Air 086 Fire Protection X
K4.01 Knowledge of design feature(s) and/or interlock(s) which provide for the following:
Adequate supply of water for FPS.
(CFR: 41.7) 3.1 65 K/A Category Point Totals:
2 0 1 2 1 0 1 1 0 1 1
Group Point Total:
10
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facility: STPNOC Date of Exam: 07-29-2019 Category K/A #
Topic RO SRO-Only IR IR
- 1.
Conduct of Operations 2.1.3 Knowledge of shift or short-term relief turnover practices.
(CFR: 41.10 / 45.13) 3.7 66 2.1.44 Knowledge of RO duties in the control room during fuel handling, such as responding to alarms from the fuel handling area, communication with the fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation.
(CFR: 41.10 / 43.7 / 45.12) 3.9 67 2.1.34 2.1.34 Knowledge of primary and secondary plant chemistry limits.
(CFR: 41.10 / 43.5 / 45.12) 2.7 68 Subtotal 3
- 2.
Equipment Control 2.2.43 Knowledge of the process used to track inoperable alarms.
(CFR: 41.10 / 43.5 / 45.13) 3.0 69 2.2.13 Knowledge of tagging and clearance procedures.
(CFR: 41.10 / 45.13) 4.1 70 2.2.3 Knowledge of the design, procedural, and operational differences between units.
(CFR: 41.5 / 41.6 / 41.7 / 41.10 / 45.12) 3.8 71 Subtotal 3
- 3.
Radiation Control 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) 2.9 72 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.
(CFR: 41.12 / 43.4 / 45.10) 3.2 73 Subtotal 2
- 4.
Emergency Procedures /
Plan 2.4.25 Knowledge of fire protection procedures.
(CFR: 41.10 / 43.5 / 45.13) 3.3 74 2.4.19 Knowledge of EOP layout, symbols, and icons.
(CFR: 41.10 / 45.13) 3.4 75 Subtotal 2
Tier 3 Point Total 10 7
ES-401 Record of Rejected K/As Form ES-401-4 Tier /
Group Randomly Selected K/A Reason for Rejection 1/1 000058 G2.2.22 (Outline Question #14)
This K/A tests the knowledge of limiting conditions for operations and safety limits for the Loss of DC Power. I could not write an acceptable question due to the simplicity of the Technical Specification for DC Power. Therefore, the K/A was replaced with 000058 G2.2.37.
2/1 005 K1.10 (Outline Question #31)
This K/A tests the knowledge of the physical connections and/or cause effect relationships between the RHRS and the Containment Spray System. There are no physical connections between these two systems. Therefore, the K/A was replaced 005 K1.04.
2/1 059 K4.02 (Outline Question #44)
This K/A tests the knowledge of MFW design features(s) and/or interlock(s) which provide for the following:
Automatic turbine/reactor trip runback. There are no automatic runbacks from the MFW system. Therefore, the K/A was replaced with 059 K4.13.
2/1 062 K4.03 (Outline Question #48)
This K/A tests the knowledge of AC distribution system design feature(s) and/or interlock(s) which provide for the following: Interlocks between automatic bus transfer and breakers. There are no automatic bus transfer features at STP. Therefore, the K/A was replaced with 062 K4.05.
2/2 014 K4.05 (Outline Question #57)
This K/A tests the knowledge of RPIS design feature(s) and/or interlock(s) which provide for the following: Rod hold interlocks. There are no interlocks between DRPI and the Rod Holdout System. Therefore, the K/A was replaced with 014 K4.06.
2/2 086 K4.06 (Outline Question #65)
This K/A tests the knowledge of design feature(s) and/or interlock(s) which provide for the following: CO2. CO2 is not used in the STP Fire Protection System except for fire extinguishers. Therefore, the K/A was replaced with 086 K4.01.
Commented [WG1]: Really, no ABT features at STP????? I thought every plant had some level of ABT, like from 125 vDC to 125 rectified AC.
ES-401 PWR Examination Outline Form ES-401-2 Facility: STPNOC Date of Exam: 07-29-2019 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
N/A N/A 18 3
3 6
2 9
2 2
4 Tier Totals 27 5
5 10
- 2.
Plant Systems 1
28 2
3 5
2 10 3
0 3
Tier Totals 38 5
3 8
- 3. Generic Knowledge and Abilities Categories 1
2 3
4 10 1
2 2
2 3
1 4
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).
- 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
- These systems/evolutions must be included as part of the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the K/A catalog.
- These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan.
ES-401 2
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO)
E/APE # / Name / Safety Function K
1 K
2 K
3 A
1 A
2 G*
K/A Topic(s)
IR 000007 (BW/E02&E10; CE/E02) Reactor Trip - Stabilization - Recovery / 1 000008 Pressurizer Vapor Space Accident / 3 000009 Small Break LOCA / 3 X
2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
(CFR: 41.5 / 43.5 / 45.12 / 45.13) 4.7 76 000011 Large Break LOCA / 3 000015/17 RCP Malfunctions / 4 000022 Loss of Rx Coolant Makeup / 2 X
2.4.11 Knowledge of abnormal condition procedures.
(CFR: 41.10 / 43.5 / 45.13) 4.2 77 000025 Loss of RHR System / 4 000026 Loss of Component Cooling Water / 8 000027 Pressurizer Pressure Control System Malfunction / 3 000029 ATWS / 1 X
EA2.08 Ability to determine or interpret the following as they apply to a ATWS: Rod bank step counters and RPI.
(CFR 43.5 / 45.13) 3.5 78 000038 Steam Gen. Tube Rupture / 3 000040 (BW/E05; CE/E05; W/E12)
Steam Line Rupture - Excessive Heat Transfer / 4 000054 (CE/E06) Loss of Main Feedwater / 4 X
2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation.
(CFR: 41.10 / 43.5 / 45.2 / 45.6) 4.4 79 000055 Station Blackout / 6 000056 Loss of Off-site Power / 6 000057 Loss of Vital AC Inst. Bus / 6 000058 Loss of DC Power / 6 X
AA2.03 Ability to determine and interpret the following as they apply to the Loss of DC Power: DC loads lost; impact on ability to operate and monitor plant systems.
(CFR: 43.5 / 45.13) 3.9 80 000062 Loss of Nuclear Svc Water / 4 000065 Loss of Instrument Air / 8 W/E04 LOCA Outside Containment / 3 W/E11 Loss of Emergency Coolant Recirc. / 4 BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4
000077 Generator Voltage and Electric Grid Disturbances / 6 X
AA2.05 Ability to determine and interpret the following as they apply 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) 3.8 81 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
2 G
K/A Topic(s)
IR 000001 Continuous Rod Withdrawal / 1 000003 Dropped Control Rod / 1 000005 Inoperable/Stuck Control Rod / 1 000024 Emergency Boration / 1 000028 Pressurizer Level Malfunction / 2 000032 Loss of Source Range NI / 7 000033 Loss of Intermediate Range NI / 7 X
AA2.04 Ability to determine and interpret the following as they apply to the Loss of Intermediate Range Nuclear Instrumentation: Satisfactory overlap between source-range, intermediate-range and power-range instrumentation.
(CFR: 43.5 / 45.13) 3.2 82 000036 (BW/A08) Fuel Handling Accident / 8 X
AA2.03 Ability to determine and interpret the following as they apply to the Fuel Handling Incidents: Magnitude of potential radioactive release.
(CFR: 43.5 / 45.13) 4.2 83 000037 Steam Generator Tube Leak / 3 X 2.2.22 Knowledge of limiting conditions for operations and safety limits.
(CFR: 41.5 / 43.2 / 45.2) 4.7 84 000051 Loss of Condenser Vacuum / 4 000059 Accidental Liquid Radwaste Rel. / 9 000060 Accidental Gaseous Radwaste Rel. / 9 000061 ARM System Alarms / 7 000067 Plant Fire On-site / 8 000068 (BW/A06) Control Room Evac. / 8 000069 (W/E14) Loss of CTMT Integrity / 5 000074 (W/E06&E07) Inad. Core Cooling / 4 000076 High Reactor Coolant Activity / 9 W/EO1 & E02 Rediagnosis & SI Termination / 3 W/E13 Steam Generator Over-pressure / 4 W/E15 Containment Flooding / 5 W/E16 High Containment Radiation / 9 X 2.4.2 Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.
(CFR: 41.7 / 45.7 / 45.8) 4.6 85 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:
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
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 003 Reactor Coolant Pump 004 Chemical and Volume Control X
A2.26 Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Low VCT pressure.
(CFR: 41.5/ 43/5 / 45/3 / 45/5) 3.0 86 005 Residual Heat Removal 006 Emergency Core Cooling 007 Pressurizer Relief/Quench Tank X
A2.04 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:
Overpressurization of the waste gas vent header.
(CFR: 41.5 / 43.5 / 45.3 / 45.13) 2.9 87 008 Component Cooling Water 010 Pressurizer Pressure Control 012 Reactor Protection 013 Engineered Safety Features Actuation 022 Containment Cooling X
2.4.41 Knowledge of the emergency action level thresholds and classifications.
(CFR: 41.10 / 43.5 / 45.11) 4.6 88 025 Ice Condenser 026 Containment Spray 039 Main and Reheat Steam 059 Main Feedwater 061 Auxiliary/Emergency Feedwater 062 AC Electrical Distribution 063 DC Electrical Distribution 064 Emergency Diesel Generator 073 Process Radiation Monitoring X
2.1.32 Ability to explain and apply system limits and precautions.
(CFR: 41.10 / 43.2 / 45.12) 4.0 89
076 Service Water X
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) 4.2 90 078 Instrument Air 103 Containment K/A Category Point Totals:
2 3
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 (RO / 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 001 Control Rod Drive 002 Reactor Coolant 011 Pressurizer Level Control 014 Rod Position Indication 015 Nuclear Instrumentation 016 Non-Nuclear Instrumentation X
A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the NNIS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Detector failure.
(CFR: 41.5 / 43.5 / 45.3 / 45.5) 3.1 91 017 In-Core Temperature Monitor 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 029 Containment Purge 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment 035 Steam Generator X
A2.05 Ability to (a) predict the impacts of the following malfunctions or operations on the GS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Unbalanced flows to the S/Gs.
(CFR: 41.5 / 43.5 / 45.3 / 45.5) 3.4 92 041 Steam Dump/Turbine Bypass Control 045 Main Turbine Generator 055 Condenser Air Removal 056 Condensate 068 Liquid Radwaste X
A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the Liquid Radwaste System ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Lack of tank recirculation prior to release.
(CFR: 41.5 / 43.5 / 45.3 / 45.13) 2.8 93
071 Waste Gas Disposal 072 Area Radiation Monitoring 075 Circulating Water 079 Station Air 086 Fire Protection K/A Category Point Totals:
3 0
Group Point Total:
3
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facility: STPNOC Date of Exam: 07-29-2019 Category K/A #
Topic RO SRO-Only IR IR
- 1.
Conduct of Operations 2.1.26 Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).
(CFR: 41.10 / 45.12) 3.6 94 2.1.35 Knowledge of the fuel-handling responsibilities of SROs.
(CFR: 41.10 / 43.7) 3.9 95 Subtotal 2
- 2.
Equipment Control 2.2.6 Knowledge of the process for making changes to procedures.
(CFR: 41.10 / 43.3 / 45.13) 3.6 96 2.2.17 Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination with the transmission system operator.
(CFR: 41.10 / 43.5 / 45.13) 3.8 97 Subtotal 2
- 3.
Radiation Control 2.3.6 Ability to approve release permits.
(CFR: 41.13 / 43.4 / 45.10) 3.8 98 Subtotal 1
- 4.
Emergency Procedures /
Plan 2.4.5 Knowledge of the organization of the operating procedures network for normal, abnormal, and emergency evolutions.
(CFR: 41.10 / 43.5 / 45.13) 4.3 99 2.4.37 Knowledge of the lines of authority during implementation of the emergency plan.
(CFR: 41.10 / 45.13) 4.1 100 Subtotal 2
Tier 3 Point Total 10 7
ES-401 Record of Rejected K/As Form ES-401-4 Tier /
Group Randomly Selected K/A Reason for Rejection 1/1 000022 2.4.41 (Outline Question #77)
This K/A tests the knowledge of the emergency action level thresholds and classifications. No EALs exist for loss of reactor coolant makeup. Therefore, the K/A was replaced with 000022 G2.4.11.
Rev. 0 ES-301 Administrative Topics Outline Form ES-301-1 Facility: South Texas Project Date of Examination: 7-15-19 Examination Level: RO SRO Operating Test Number: LOT 23 NRC Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations A1 K/A Importance: 3.6 M,R 2.1.18 Ability to make accurate, clear, and concise logs, records, status boards, and reports.
Record Operator Logs - 0PSP03-ZQ-0028 Conduct of Operations A2 K/A Importance: 3.9 D,R 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.
Perform an RWST Blended Makeup Calculation Equipment Control A3 K/A Importance: 4.6 D,P,R 2.2.2 Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.
Determine H2 Recombiner Power Settings Radiation Control A4 K/A Importance: 3.2 D,R 2.3.4 Knowledge of radiation exposure limits under normal and emergency conditions.
Calculate Maximum Stay Time (Room M108C)
Emergency Plan N/A N/A NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).
- Type Codes and Criteria:
(C)ontrol Room, (S)imulator, Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs and RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1, randomly selected)
Rev. 0 ES-301 Administrative Topics Outline Form ES-301-1 Facility: South Texas Project Date of Examination: 7-15-18 Examination Level: RO SRO Operating Test Number: LOT 23 NRC Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations A5 K/A Importance: 3.4 D,P,R 2.1.42 Knowledge of new and spent fuel movement procedures.
Determine Close Contact Fuel Assembly Movement Conduct of Operations A6 K/A Importance: 4.4 D,R 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation.
Review a Calorimetric Heat Balance and Evaluate Technical Specifications Equipment Control A7 K/A Importance: 4.1 D,R 2.2.12 Knowledge of surveillance procedures.
Review Completed Surveillance (ECW)
Radiation Control A8 K/A Importance: 3.8 D,R 2.3.6 Ability to approve release permits.
Approve a Liquid Waste Release Permit Emergency Plan A9 K/A Importance: 4.4 M,R 2.4.44 Knowledge of emergency plan protective action recommendations.
Determine PARs NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).
- Type Codes and Criteria:
(C)ontrol Room, (S)imulator, Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs and RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1, randomly selected)
Rev. 0 STP LOT-23 NRC Admin JPM Description RO (A1)
Record Operator Logs - 0PSP03-ZQ-0028 Demonstrate the ability to Perform Control Room Operator Logs from 0PSP03-ZQ-0028, Operator Logs, for any adverse trends and the appropriate corrective actions that would need to be taken in accordance with 0POP01-ZQ-0022, Plant Operations Shift Routines.
(A2)
Perform an RWST Blended Makeup Calculation Demonstrate the ability to set the boric acid flow integrator for a blended makeup to the RWST using 0POP02-CV-0001, Makeup to the Reactor Coolant System.
(A3)
Determine H2 Recombiner Power Settings Demonstrate the ability to calculate the required power setting for operation of a Hydrogen Recombiner in a post-LOCA environment.
(A4)
Calculate Maximum Stay Time (Room M108C)
Demonstrate the ability to determine stay times based on dose rates given in an RWP.
SRO (A5)
Determine Close Contact Fuel Assemble Movement Demonstrate the ability to review Fuel Transfer Forms and interpret procedure guidance for Close Contact Fuel Assembly moves in accordance with 0POP08-FH-0001, Refueling Machine Operating Instructions, Addendum 4, Guidelines For Close Contact Fuel Assembly Movements.
(A6)
Review a Calorimetric Heat Balance and Evaluate Technical Specifications.
Demonstrate the ability to perform a Calorimetric Verification and evaluate TSs. 0PEP02-CU-0001, Calorimetric Verification, and 0PSP03-NI-0001, Power Range NI Channel Calibration.
(A7)
Review Completed Surveillance (ECW)
Demonstrate the ability to review a completed surveillance on the Essential Cooling Water System per 0PSP03-EW-0017, Essential Cooling Water System Train A Testing, in accordance with 0PGP03-ZE-0004, Plant Surveillance Program.
(A8)
Approve completed Liquid Waste Release Permit.(alternate path actual release did not match the approved release limits)
Demonstrate the ability to review a completed Liquid Waste Release Permit and determine if it was completed correctly. 0PSP07-WL-LDP1, Liquid Effluent Permit.
(A9)
Determine Appropriate Emergency Plan Protective Action Recommendation Demonstrate the ability to correctly determine an Emergency Protective Action Recommendation for a given condition requiring entry into the STPNOC Emergency Action Plan in accordance with 0ERP01-ZV-IN07, Offsite Protective Action Recommendations.
Rev. 0 Page 1 of 5 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: South Texas Project Date of Examination: 7-15-19 Exam Level: RO SRO-I SRO-U Operating Test No.: LOT 23 NRC Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System / JPM Title Type Code*
Safety Function
- a. (S1) Re-Establish Letdown During ES-11 KA: 004 A4.06 (3.6/3.1)
A,D,E,L,S 1
- b. (S2) Isolate SI Accumulators KA: 006 A4.02 (4.0/3.8)
A,D,EN,L,P,S 2
- c. (S3) Transfer to Hot Leg Recirculation KA: 006 A4.05 (3.9/3.8)
D,E,L,S 3
A,E,L,N,S 7
- e. (S5) Start an RCP KA: 003 A4.06 (2.9/2.9)
L,M,S 4P
- f. (S6) Start ECW Pump and Lower ECP Level KA: 075 A4.01 (3.2/3.2)
D,L,S 8
- g. (S7) Place SGFPT in service from 3300 RPM KA: 039 A4.03 (2.8/2.8)
D,S 4S
- h. (S8) Roll a 13.8KV Electrical Bus KA: 062 A4.07 (3.1/3.1)
D,P,S 6
In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U
D,R 8
- j. (P2) Locally Start an ESF DG per 0POP04-ZO-0001, Control Room Evacuation, Addendum 7 KA: 064 A4.01 (4.0/4.3)
A,E,N 6
- k. (P3) Failing Air to MSIVs and MSIBs KA: 039 A4.01 (2.9/2.8)
A,D,E,L 4S All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all 5 SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO/SRO-I/SRO-U (A)lternate Path (C)ontrol Room (D)irect from Bank (E)mergency or abnormal in-plant (EN) gineered Safety Features (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1 1 / 1 / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1
Rev. 0 Page 2 of 5 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: South Texas Project Date of Examination: 7-15-18 Exam Level: RO SRO-I SRO-U Operating Test No.: LOT 23 NRC Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System / JPM Title Type Code*
Safety Function
- a. (S1) Re-Establish Letdown During ES-11 KA: 004 A4.06 (3.6/3.1)
A,D,E,L,S 1
- b. (S2) Isolate SI Accumulators KA: 006 A4.02 (4.0/3.8)
A,D,EN,L,P,S 2
- c. (S3) Transfer to Hot Leg Recirculation KA: 006 A4.05 (3.9/3.8)
D,E,L,S 3
A,E,L,N,S 7
- e. (S5) Start an RCP KA: 003 A4.06 (2.9/2.9)
L,M,S 4P
- f.
- g. (S7) Place SGFPT in service from 3300 RPM KA: 039 A4.03 (2.8/2.8)
D,S 4S
- h. (S8) Roll a 13.8KV Electrical Bus KA: 062 A4.07 (3.1/3.1)
D,P,S 6
In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U
D,R 8
- j. (P2) Locally Start an ESF DG per 0POP04-ZO-0001, Control Room Evacuation, Addendum 7 KA: 064 A4.01 (4.0/4.3)
A,E,L,N 6
- k. (P3) Failing Air to MSIVs and MSIBs KA: 039 A4.01 (2.9/2.8)
A,D,E,L 4S All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all 5 SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO/SRO-I/SRO-U (A)lternate Path (C)ontrol Room (D)irect from Bank (E)mergency or abnormal in-plant (EN) gineered Safety Features (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1 1 / 1 / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1
Rev. 0 Page 3 of 5 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: South Texas Project Date of Examination: 7-15-18 Exam Level: RO SRO-I SRO-U Operating Test No.: LOT 23 NRC Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System / JPM Title Type Code*
Safety Function
- a.
- b. (S2) Isolate SI Accumulators KA: 006 A4.02 (4.0/3.8)
A,D,EN,L,P,S 2
- c. (S3) Transfer to Hot Leg Recirculation KA: 006 A4.05 (3.9/3.8)
D,E,L,S 3
A,E,L,N,S 7
- e.
- f.
- g.
- h.
In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U
D,R 8
- j.
- k. (P3) Failing Air to MSIVs and MSIBs KA: 039 A4.01 (2.9/2.8)
A,D,E,L 4S All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all 5 SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO/SRO-I/SRO-U (A)lternate Path (C)ontrol Room (D)irect from Bank (E)mergency or abnormal in-plant (EN) gineered Safety Features (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1 1 / 1 / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1
Rev. 0 Page 4 of 5 STP LOT-23 NRC Systems JPM Description Control Room Systems JPMs (S1)
Re-Establish Letdown During ES-11 Demonstrate the ability to establish normal letdown flow after an SI in accordance with 0POP05-EO-ES11, SI Termination.
(S2)
Isolate SI Accumulators Demonstrate the ability to isolate SI Accumulators from the RCS by closing the discharge isolation valve and/or depressurizing the accumulator in accordance with 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant. This is an Alternate Path JPM.
(S3)
Transfer to Hot Leg Recirculation Demonstrate the ability to align ECCS Hot Leg Recirculation in accordance with 0POP05-EO-ES14, Transfer to Hot Leg Recirculation (S4)
Respond to High Alarm on RT-8033 or RT-8034 Demonstrate the ability to change ventilation alignment due to Radiation Monitor Failure in accordance with 0POP04-RA-0001, Radiation Monitoring System Alarm Response.
(S5)
Start a Reactor Coolant Pump Demonstrate the ability to operate a Reactor Coolant Pump and monitor parameters in accordance with 0POP02-RC-0004, Operation of Reactor Coolant Pump.
(S6)
Start an Essential Cooling Water Pump and Lower Essential Cooling Pond Level Demonstrate the ability to operate an Essential Cooling Water Pump and associated valves in accordance with 0POP02-EW-0001, Essential Cooling Pump Operations.
(S7)
Place a SGFPT in Service (from 3300 rpm)
Demonstrate the ability to control steam to a SGFPT while placing it in service to feed Steam Generators in accordance with 0POP02-FW-0001, S.G.F.P. Turbine.
(S8)
Roll a 13.8KV Electrical Bus Demonstrate the ability to transfer 13.8KV electrical power from one source of power to another in accordance with 0POP02-AE-0002, Transformer Normal Breaker and Switch Lineup.
NOTE: All Control Room JPMs will be performed dynamically in the Simulator. JPMs will be performed in pairs; S1 & S2 together, S3 & S4 together, S5 & S6 together and S7 & S8 together.
Rev. 0 Page 5 of 5 STP LOT-23 NRC Systems JPM Description In Plant Systems JPMs (P1)
Fill SFP from the RWST Demonstrate the ability to perform a fill of the SFP from the RWST per 0POP02-FC-0001, SFP Cooling and Cleanup System.
(P2)
Locally Start an ESF DG per 0POP04-ZO-0001, Control Room Evacuation, Add. 7 Demonstrate the ability to locally start an ESF DG during a control room evacuation in accordance with 0POP04-ZO-0001, Control Room Evacuation, Addendum 7. This is an Alternate Path JPM.
(P3)
Failing Air to MSIVs and MSIBs Demonstrate the ability to locally close Main Steam Isolation Valves and Main Steam Isolation Bypass Valves in accordance with 0POP05-EO-EC00, Loss of all AC Power, Addendum #4. This is an Alternate Path JPM.