Text

05 Draft Outlines
	ML20174A606
Person / Time
Site:	Comanche Peak
Issue date:	05/21/2020
From:	Greg Werner; Operations Branch IV
To:	; Vistra Operating Co. (VistraOpCo)
References
	50-445/20-05, 50-446/20-05 50-445/OL-20, 50-446/OL-20
	Download: ML20174A606 (21)
	v • d • e

ES-401 PWR Examination Outline Form ES-401-2 Facility: CPNPP Date of Exam: 05/21/2020 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 3 3 3 3 3 3 18 6 Emergency and Abnormal Plant 2 1 1 1 N/A 2 2 N/A 2 9 4 Evolutions Tier Totals 4 4 4 5 5 5 27 10 1 3 2 3 2 2 2 3 2 3 3 3 28 5 2.

Plant 2 1 1 1 1 1 1 0 1 1 1 1 10 3 Systems Tier Totals 4 3 4 3 3 3 3 3 4 4 4 38 8

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 7 Categories 10 3 2 2 3 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 radiation control K/A is allowed if it is replaced by a K/A from another Tier 3 category.)

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

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

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

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

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

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

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

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

G* Generic K/As

These systems/evolutions must be included as part of the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the K/A catalog.

- These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan.

CPNPP 2020-05 NRC ES-401-2 & 3 RO Written Exam Outline Rev. 2

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

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #

000007 (EPE 7) Reactor Trip, Stabilization, EK1.04 Knowledge of the operational implications Recovery / 1 X of the following concepts as they apply to the reactor trip: Decrease in reactor power following 3.6 39 reactor trip (prompt drop and subsequent decay) 000008 (APE 8) Pressurizer Vapor Space AA2.12 Ability to determine and interpret the Accident / 3 X following as they apply to the Pressurizer Vapor 3.4 40 Space Accident: PZR level indicators 000009 (EPE 9) Small Break LOCA / 3 2.1.7 Ability to evaluate plant performance and X make operational judgments based on operating characteristics, reactor behavior, and instrument 4.4 41 interpretation.

000011 (EPE 11) Large Break LOCA / 3 EK3.14 Knowledge of the reasons for the following X responses as the apply to the Large Break LOCA: 4.1 42 RCP tripping requirement 000015 (APE 15) Reactor Coolant Pump Malfunctions / 4 000022 (APE 22) Loss of Reactor Coolant 2.4.4 Ability to recognize abnormal indications for Makeup / 2 system operating parameters that are entry-level X 4.5 43 conditions for emergency and abnormal operating procedures.

000025 (APE 25) Loss of Residual Heat AK1.01 Knowledge of the operational implications Removal System / 4 X of the following concepts as they apply to Loss of Residual Heat Removal System: Loss of RHRS 3.9 44 during all modes of operation 000026 (APE 26) Loss of Component AK3.02 Knowledge of the reasons for the following Cooling Water / 8 responses as they apply to the Loss of Component X Cooling Water: The automatic actions (alignments) 3.6 45 within the CCWS resulting from the actuation of the ESFAS 000027 (APE 27) Pressurizer Pressure AK3.03 Knowledge of the reasons for the following Control System Malfunction / 3 X responses as they apply to the Pressurizer Pressure Control Malfunctions: Actions contained 3.7 46 in EOP for PZR PCS malfunction 000029 (EPE 29) Anticipated Transient Without Scram / 1 000038 (EPE 38) Steam Generator Tube EA1.04 Ability to operate and monitor the following Rupture / 3 X as they apply to a SGTR: PZR spray, to reduce 4.3 47 coolant system pressure 000040 (APE 40; W E12) Steam Line RuptureExcessive Heat Transfer AK1.02 Knowledge of the operational implications X of the following concepts as they apply to Steam 3.2 48 Uncontrolled Depressurization of all Steam Generators / 4 Line Rupture: Leak rate versus pressure change 000054 (APE 54;) Loss of Main Feedwater

/4 000055 (EPE 55) Station Blackout / 6 EA1.06 Ability to operate and monitor the following X as they apply to a Station Blackout: Restoration of 4.1 49 power with one ED/G 000056 (APE 56) Loss of Offsite Power / 6 000057 (APE 57) Loss of Vital AC 2.1.31 Ability to locate control room switches, Instrument Bus / 6 X controls, and indications, and tol determine that 4.6 50 they correctly reflect the desired plant lineup.

000058 (APE 58) Loss of DC Power / 6 AA1.03 Ability to operate and / or monitor the X following as they apply to the Loss of DC Power: 3.1 51 Vital and battery bus components 000062 (APE 62) Loss of Nuclear Service AA2.03 Ability to determine and interpret the Water / 4 following as they apply to the Loss of Nuclear X Service Water: The valve lineups necessary to 2.6 52 restart the SWS while bypassing the portion of the system causing the abnormal condition CPNPP 2020-05 NRC ES-401-2 & 3 RO Written Exam Outline Rev. 2

ES-401 3 Form ES-401-2 000065 (APE 65) Loss of Instrument Air / 8 AA2.06 Ability to determine and interpret the X following as they apply to the Loss of Instrument Air: When to trip reactor if instrument air pressure is 3.6 53 de-creasing 000077 (APE 77) Generator Voltage and Electric Grid Disturbances / 6 (W E04) LOCA Outside Containment / 3 EK2.2 Knowledge of the interrelations between the (LOCA Outside Containment) and the following:

Facility*s heat removal systems, including primary X coolant, emergency coolant, the decay heat 3.8 54 removal systems, and relations between the proper operation of these systems to the operation of the facility.

(W E11) Loss of Emergency Coolant EK2.01 Knowledge of the interrelations between the Recirculation / 4 (Loss of Emergency Coolant Recirculation) and the X following: Components, and functions of control and safety systems, including instrumentation, signals, 3.6 55 interlocks, failure modes, and automatic and manual features.

W E05 Inadequate Heat TransferLoss of EK2.02 Knowledge of the interrelations between the Secondary Heat Sink / 4 (Loss of Secondary Heat Sink) and the following:

Facility*s heat removal systems, including primary X coolant, emergency coolant, the decay heat 3.9 56 removal systems, and relations between the proper operation of these systems to the operation of the facility.

K/A Category Totals: 3 3 3 3 3 3 Group Point Total: 18 CPNPP 2020-05 NRC ES-401-2 & 3 RO Written Exam Outline Rev. 2

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #

000001 (APE 1) Continuous Rod Withdrawal / 1 000003 (APE 3) Dropped Control Rod / 1 AA2.02 Ability to determine and interpret the following as they X apply to the Dropped Control 2.7 57 Rod: Signal inputs to rod control system 000005 (APE 5) Inoperable/Stuck Control Rod / 1 000024 (APE 24) Emergency Boration / 1 000028 (APE 28) Pressurizer (PZR) Level Control AK1.01 Knowledge of the Malfunction / 2 operational implications of the X following concepts as they apply 2.8 58 to Pressurizer Level Control Malfunctions: PZR reference leak abnormalities 000032 (APE 32) Loss of Source Range Nuclear AA2.02 Ability to determine and Instrumentation / 7 interpret the following as they X apply to the Loss of Source 3.6 59 Range Nuclear Instrumentation:

Expected change in source range count rate when rods are moved 000033 (APE 33) Loss of Intermediate Range Nuclear Instrumentation / 7 000036 (APE 36) Fuel Handling Incidents / 8 000037 (APE 37) Steam Generator Tube Leak / 3 000051 (APE 51) Loss of Condenser Vacuum / 4 AK3.01 Knowledge of the reasons for the following responses as X they apply to the Loss of 60 Condenser Vacuum: Loss of 2.8 steam dump capability upon loss of condenser vacuum 000059 (APE 59) Accidental Liquid Radwaste Release / 9 000060 (APE 60) Accidental Gaseous Radwaste Release / 9 000061 (APE 61) Area Radiation Monitoring System Alarms

/7 000067 (APE 67) Plant Fire On Site / 8 000068 (APE 68; BW A06) Control Room Evacuation / 8 AA1.10 Ability to operate and / or monitor the following as they X apply to the Control Room 2.9 61 Evacuation: Power distribution:

ac and dc 000069 (APE 69; W E14) Loss of Containment Integrity / 5 000074 (EPE 74; W E06 & E07) Inadequate Core Cooling /

4 000076 (APE 76) High Reactor Coolant Activity / 9 AK2.01 Knowledge of the interrelations between the High X Reactor Coolant Activity and the 2.6 62 following: Process radiation monitors 000078 (APE 78*) RCS Leak / 3 (W E01 & E02) Rediagnosis & SI Termination / 3 2.1.20 Ability to interpret and X 4.6 63 execute procedure steps.

(W E13) Steam Generator Overpressure / 4 EA1.03 Ability to operate and / or monitor the following as they X apply to the (Steam Generator 3.1 64 Overpressure): Desired operating results during abnormal and emergency situations.

CPNPP 2020-05 NRC ES-401-2 & 3 RO Written Exam Outline Rev. 2

ES-401 5 Form ES-401-2 (W E15) Containment Flooding / 5 2.1.23 Ability to perform specific X system and integrated plant 4.3 65 procedures during all modes of plant operation.

(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-Depressurization / 4 (W E09 & E10) Natural Circulation/4 (BW E13 & E14) EOP Rules and Enclosures (W E08) RCS Overcooling-Pressurized Thermal Shock / 4 (CE A16) Excess RCS Leakage / 2 (CE E09) Functional Recovery (CE E13*) Loss of Forced Circulation/LOOP/Blackout / 4 K/A Category Point Totals: 1 1 1 2 2 2 Group Point Total: 9 CPNPP 2020-05 NRC ES-401-2 & 3 RO Written Exam Outline Rev. 2

ES-401 6 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #

003 (SF4P RCP) Reactor Coolant K5.02 Knowledge of the operational Pump implications of the following concepts as X 2.8 1 they apply to the RCPS: Effects of RCP coastdown on RCS parameters 004 (SF1; SF2 CVCS) Chemical and K4.16 Knowledge of CVCS design feature(s)

Volume Control and/or interlock(s) which provide for the X following: Temperature at which the temperature control valve automatically diverts 2.6 2 flow from the demineralizer to the VCT; reason for this diversion 005 (SF4P RHR) Residual Heat K2.03 Knowledge of bus power supplies to the Removal X following: RCS pressure boundary motor- 2.7 3 operated valves 006 (SF2; SF3 ECCS) Emergency 2.4.20 Knowledge of the operational Core Cooling X implications of EOP warnings, cautions, and 3.8 4 notes.

007 (SF5 PRTS) Pressurizer K1.03 Knowledge of the physical connections Relief/Quench Tank X and/or cause effect relationships between the PRTS and the following systems: RCS 3.0 5 A4.10 Ability to manually operate and/or X monitor in the control room: Recognition of leaking PORV/code safety 3.6 6 008 (SF8 CCW) Component Cooling K1.01 Knowledge of the physical connections Water 3.1 7 X and/or cause-effect relationships between the CCWS and the following systems: Service Water System K3.01 Knowledge of the effect that a loss or malfunction of the CCWS will have on the 3.4 8 X following: Loads cooled by CCWS 010 (SF3 PZR PCS) Pressurizer A1.08 Ability to predict and/or monitor changes Pressure Control X in parameters (to prevent exceeding design limits) associated with operating the PZR PCS 3.2 9 controls including: Spray nozzle DT 012 (SF7 RPS) Reactor Protection K6.02 Knowledge of the effect of a loss or X malfunction of the following will have on the 2.9 10 RPS: Redundant channels 013 (SF2 ESFAS) Engineered A1.04 Ability to predict and/or monitor changes Safety Features Actuation X in parameters (to Prevent exceeding design limits) associated with operating the ESFAS 3.4 11 controls including: S/G level 022 (SF5 CCS) Containment Cooling A3.01 Ability to monitor automatic operation of X the CCS, including: Initiation of safeguards 4.1 12 mode of operation 025 (SF5 ICE) Ice Condenser Not part of CP design 026 (SF5 CSS) Containment Spray A4.05 Ability to manually operate and/or X monitor in the control room: Containment spray 3.5 13 reset switches 039 (SF4S MSS) Main and Reheat A3.02 Ability to monitor automatic operation of Steam X 3.1 14 the MRSS, including: Isolation of the MRSS CPNPP 2020-05 NRC ES-401-2 & 3 RO Written Exam Outline Rev. 2

ES-401 7 Form ES-401-2 059 (SF4S MFW) Main Feedwater 2.2.44 Ability to interpret control room indications to verify the status and operation of X a system, and understand how operator 4.2 15 actions and directives affect plant and system conditions.

061 (SF4S AFW) K6.01 Knowledge of the effect of a loss or Auxiliary/Emergency Feedwater X malfunction of the following will have on the 2.5 16 AFW components: Controllers and positioners 062 (SF6 ED AC) AC Electrical K3.01 Knowledge of the effect that a loss or Distribution malfunction of the ac distribution system will X 3.5 17 have on the following: Major system loads 2.4.20 Knowledge of the operational X implications of EOP warnings, cautions, and 3.8 18 notes.

063 (SF6 ED DC) DC Electrical A2.01 Ability to (a) predict the impacts of the Distribution following malfunctions or operations on the DC X electrical systems; and (b) based on those predictions, use procedures to correct, control, 2.5 19 or mitigate the consequences of those malfunctions or operations: Grounds 064 (SF6 EDG) Emergency Diesel K3.01 Knowledge of the effect that a loss or Generator malfunction of the ED/G system will have on X 3.8 20 the following: Systems controlled by automatic loader K4.02 Knowledge of ED/G system design feature(s) and/or interlock(s) which provide for 3.9 21 X the following: Trips for ED/G while operating (normal or emergency) 073 (SF7 PRM) Process Radiation K1.01 Knowledge of the physical connections Monitoring 3.6 22 and/or cause effect relationships between the X PRM system and the following systems: Those systems served by PRMs K5.02 Knowledge of the operational implications as they apply to concepts as they X 2.5 23 apply to the PRM system: Radiation intensity changes with source distance 076 (SF4S SW) Service Water A4.02 Ability to manually operate and/or X 2.6 24 monitor in the control room: SWS valves 078 (SF8 IAS) Instrument Air K2.02 Knowledge of bus power supplies to the X 3.3 25 following: Emergency air compressor A3.01 Ability to monitor automatic operation of 3.1 26 X

the IAS, including: Air Pressure CPNPP 2020-05 NRC ES-401-2 & 3 RO Written Exam Outline Rev. 2

ES-401 8 Form ES-401-2 103 (SF5 CNT) Containment A1.01 Ability to predict and/or monitor changes 3.7 27 in parameters (to prevent exceeding design limits) associated with operating the X

containment system controls including:

Containment pressure, temperature, and humidity A2.04 Ability to (a) predict the impacts of the following malfunctions or operations on the containment system and (b) based on those X predictions, use procedures to correct, control, 3.5 28 or mitigate the consequences of those malfunctions or operations Containment evacuation (including recognition of the alarm) 053 (SF1; SF4P ICS*) Integrated Not part of CP design Control K/A Category Point Totals: 3 2 3 2 2 2 3 2 3 3 3 Group Point Total: 28 CPNPP 2020-05 NRC ES-401-2 & 3 RO Written Exam Outline Rev. 2

ES-401 9 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 2 (RO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #

001 (SF1 CRDS) Control Rod Drive K4.07 Knowledge of CRDS design feature(s)

X and/or interlock(s) which provide for the 3.7 35 following: Rod Stops 002 (SF2; SF4P RCS) Reactor K1.03 Knowledge of the physical connections Coolant and/or cause-effect relationships between the X 3.8 29 RCS and the following systems: Borated water storage tank 011 (SF2 PZR LCS) Pressurizer K5.15 Knowledge of the operational Level Control X implications of the following concepts as they 3.6 30 apply to the PZR LCS: PZR level indication when RCS is saturated 014 (SF1 RPI) Rod Position K3.02 Knowledge of the effect that a loss or Indication X malfunction of the RPIS will have on the 2.5 31 following: Plant computer 015 (SF7 NI) Nuclear K2.01 Knowledge of bus power supplies to the Instrumentation X following: NIS channels, components, and 3.3 32 interconnections 016 (SF7 NNI) Nonnuclear A3.02 Ability to monitor automatic operation of Instrumentation X 2.9 37 the NNIS, including: Relationship between meter readings and actual parameter value 017 (SF7 ITM) In Core Temperature 2.4.21 Knowledge of the parameters and logic Monitor used to assess the status of safety functions, X such as reactivity control, core cooling and 4.0 33 heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

027 (SF5 CIRS) Containment Iodine Removal 028 (SF5 HRPS) Hydrogen Recombiner and Purge Control 029 (SF8 CPS) Containment Purge 033 (SF8 SFPCS) Spent Fuel Pool A2.01 Ability to (a) predict the impacts of the Cooling following malfunctions or operations on the Spent Fuel Pool Cooling System; and (b)

X based on those predictions, use procedures to 3.0 34 correct, control, or mitigate the consequences of those malfunctions or operations:

Inadequate SDM 034 (SF8 FHS) Fuel Handling Equipment 035 (SF 4P SG) Steam Generator 041 (SF4S SDS) Steam Dump/Turbine Bypass Control 045 (SF 4S MTG) Main Turbine Generator 055 (SF4S CARS) Condenser Air Removal 056 (SF4S CDS) Condensate 068 (SF9 LRS) Liquid Radwaste K6.10 Knowledge of the effect of a loss or X malfunction on the following will have on the 2.5 36 Liquid Radwaste System: Radiation monitors 071 (SF9 WGS) Waste Gas Disposal 072 (SF7 ARM) Area Radiation Monitoring 075 (SF8 CW) Circulating Water 079 (SF8 SAS**) Station Air CPNPP 2020-05 NRC ES-401-2 & 3 RO Written Exam Outline Rev. 2

ES-401 10 Form ES-401-2 086 Fire Protection A4.02 Ability to manually operate and/or X monitor in the control room: Fire detection 3.5 38 panels 050 (SF 9 CRV*) Control Room Ventilation K/A Category Point Totals: 1 1 1 1 1 1 0 1 1 1 1 Group Point Total: 10 CPNPP 2020-05 NRC ES-401-2 & 3 RO Written Exam Outline Rev. 2

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: CPNPP Date of Exam: 05/21/2020 Category K/A # Topic RO SRO-only IR # IR #

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 3.9 66 facility, systems operated from the control room in support of fueling operations, and supporting instrumentation.

1. Conduct of Operations 2.1.40 Knowledge of refueling administrative requirements. 2.8 67 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical 3.3 68 requirements, no-solo operation, maintenance of active license status, 10CFR55, etc.

Subtotal 3 2.2.14 Knowledge of the process for controlling equipment 3.9 69 configuration or status.

2. Equipment Control 2.2.38 Knowledge of conditions and limitations in the facility 3.6 70 license.

Subtotal 2 2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey 2.9 71 instruments, personnel monitoring equipment, etc.

3. Radiation 2.3.13 Knowledge of radiological safety procedures pertaining Control to licensed operator duties, such as response to radiation monitor alarms, containment entry 3.4 72 requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Subtotal 2 2.4.37 Knowledge of the lines of authority during 3.0 73 implementation of the emergency plan.

2.4.13 Knowledge of crew roles and responsibilities during

4. Emergency 4.0 74 EOP usage.

Procedures/Plan 2.4.43 Knowledge of emergency communications systems and 3.2 75 techniques.

Subtotal 3 Tier 3 Point Total 10 7 CPNPP 2020-05 NRC ES-401-2 & 3 RO Written Exam Outline Rev. 2

ES-401 1 Form ES-401-2 Facility: CPNPP Date of Exam: 05/21/2020 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 18 3 3 6 Emergency and Abnormal Plant 2 N/A N/A 9 2 2 4 Evolutions Tier Totals 27 5 5 10 1 28 2 3 5 2.

Plant 2 10 2 1 3 Systems Tier Totals 38 4 4 8

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 7 Categories 10 2 2 1 2 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 radiation control K/A is allowed if it is replaced by a K/A from another Tier 3 category.)