Text

11 Final Outlines
	ML21020A096
Person / Time
Site:	Palo Verde
Issue date:	12/10/2020
From:	Greg Werner; Operations Branch IV
To:	; Arizona Public Service Co
References
	Download: ML21020A096 (28)
	v • d • e

ES-401 PWR Examination Outline Form ES-401-2 Facility: Palo Verde Date of Exam: 11/30/2020 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 2 3 4 3 3 3 18 6 Emergency and Abnormal Plant 2 1 2 1 N/A 2 2 N/A 1 9 4 Evolutions Tier Totals 3 5 5 5 5 4 27 10 1 3 2 3 3 2 2 3 3 2 2 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 4 3 3 3 4 3 3 4 38 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 3 3 2 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only 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.

Rev. 11

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; BW E02&E10; CE E02) EA2.03 Ability to determine or interpret the following Reactor Trip, Stabilization, Recovery / 1 as they apply to a reactor trip: Reactor trip breaker 4.2 1 position 000008 (APE 8) Pressurizer Vapor Space Not sampled Accident / 3 000009 (EPE 9) Small Break LOCA / 3 EA2.39 Ability to determine or interpret the following as they apply to a small break LOCA: Adequate 4.3 2 core cooling 000011 (EPE 11) Large Break LOCA / 3 2.4.47 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the 4.2 3 appropriate control room reference material.

000015 (APE 15) Reactor Coolant Pump AA2.09 Ability to determine and interpret the Malfunctions / 4 following as they apply to the Reactor Coolant 3.4 4 Pump Malfunctions (Loss of RC Flow): When to secure RCPs on high stator temperatures 000022 (APE 22) Loss of Reactor Coolant 2.4.20 Knowledge of the operational implications of 3.8 5 Makeup / 2 EOP warnings, cautions, and notes.

000025 (APE 25) Loss of Residual Heat AA1.02 Ability to operate and / or monitor the Removal System / 4 following as they apply to the Loss of Residual Heat 3.8 6 Removal System: RCS inventory 000026 (APE 26) Loss of Component AK3.04 Knowledge of the reasons for the following Cooling Water / 8 responses as they apply to the Loss of Component 3.5 7 Cooling Water: Effect on the CCW flow header of a loss of CCW 000027 (APE 27) Pressurizer Pressure AK3.03 Knowledge of the reasons for the following Control System Malfunction / 3 responses as they apply to the Pressurizer 3.7 8 Pressure Control Malfunctions: Actions contained in EOP for PZR PCS malfunction 000029 (EPE 29) Anticipated Transient EK2.06 Knowledge of the interrelations between the Without Scram / 1 and the following an ATWS: Breakers, relays, and 2.9 9 disconnects 000038 (EPE 38) Steam Generator Tube EK1.01 Knowledge of the operational implications Rupture / 3 of the following concepts as they apply to the 3.1 10 SGTR: Use of steam tables 000040 (APE 40; BW E05; CE E05; W E12) EK2.2 Knowledge of the interrelations between the Steam Line RuptureExcessive Heat (Excess Steam Demand) and the following:

Transfer / 4 Facility*s heat removal systems, including primary coolant, emergency coolant, the decay heat 3.2 11 removal systems, and relations between the proper operation of these systems to the operation of the facility.

000054 (APE 54; CE E06) Loss of Main EK1.1 Knowledge of the operational implications of Feedwater /4 the following concepts as they apply to the (Loss of 3.2 12 Feedwater) Components, capacity, and function of emergency systems.

000055 (EPE 55) Station Blackout / 6 EK3.02 Knowledge of the reasons for the following responses as the apply to the Station Blackout:

4.3 13 Actions contained in EOP for loss of offsite and onsite power 000056 (APE 56) Loss of Offsite Power / 6 Not Sampled 000057 (APE 57) Loss of Vital AC AK3.01 Knowledge of the reasons for the following Instrument Bus / 6 responses as they apply to the Loss of Vital AC 4.1 14 Instrument Bus: Actions contained in EOP for loss of vital ac electrical instrument bus Rev. 11

ES-401 3 Form ES-401-2 000058 (APE 58) Loss of DC Power / 6 2.2.22 Knowledge of limiting conditions for 4.0 15 operations and safety limits.

000062 (APE 62) Loss of Nuclear Service AA1.02 Ability to operate and / or monitor the Water / 4 following as they apply to the Loss of Nuclear 3.2 16 Service Water (SWS): Loads on the SWS in the control room 000065 (APE 65) Loss of Instrument Air / 8 AA1.05 Ability to operate and / or monitor the following as they apply to the Loss of Instrument 3.3 17 Air: RPS 000077 (APE 77) Generator Voltage and AK2.03 Knowledge of the interrelations between Electric Grid Disturbances / 6 Generator Voltage and Electric Grid Disturbances 3.0 18 and the following: Sensors, detectors, indicators (W E04) LOCA Outside Containment / 3 N/A for CE design (W E11) Loss of Emergency Coolant N/A for CE design Recirculation / 4 (BW E04; W E05) Inadequate Heat N/A for CE design TransferLoss of Secondary Heat Sink / 4 K/A Category Totals: 3 3 3 3 3 3 Group Point Total: 18/6 Rev. 11

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 AK1.21 Knowledge of the operational implications of the following concepts as they apply 2.9 19 to Continuous Rod Withdrawal:

Integral rod worth 000003 (APE 3) Dropped Control Rod / 1 Not sampled 000005 (APE 5) Inoperable/Stuck Control Rod / 1 AA1.01 Ability to operate and / or monitor the following as they 3.6 20 apply to the Inoperable / Stuck Control Rod: CRDS 000024 (APE 24) Emergency Boration / 1 Not sampled 000028 (APE 28) Pressurizer (PZR) Level Control Not sampled Malfunction / 2 000032 (APE 32) Loss of Source Range Nuclear Not sampled Instrumentation / 7 000033 (APE 33) Loss of Intermediate Range Nuclear Not sampled Instrumentation / 7 000036 (APE 36; BW/A08) Fuel-Handling Incidents / 8 Not sampled 000037 (APE 37) Steam Generator Tube Leak / 3 Not sampled 000051 (APE 51) Loss of Condenser Vacuum / 4 Not sampled 000059 (APE 59) Accidental Liquid Radwaste Release / 9 AK2.02 Knowledge of the interrelations between the Accidental Liquid Radwaste 2.7 21 Release and the following:

Radioactive-gas monitors 000060 (APE 60) Accidental Gaseous Radwaste Release / 9 2.4.50 Ability to verify system alarm setpoints and operate controls identified in the alarm 4.2 22 response manual 000061 (APE 61) Area Radiation Monitoring System Alarms Not sampled

/7 000067 (APE 67) Plant Fire On Site / 8 Not sampled 000068 (APE 68; BW A06) Control Room Evacuation / 8 AK2.01 Knowledge of the interrelations between the Control Room Evacuation and 3.9 23 the following: Auxiliary shutdown panel layout 000069 (APE 69; W E14) Loss of Containment Integrity / 5 AK3.01 Knowledge of the reasons for the following responses as they apply to the Loss of Containment Integrity: Guidance 3.8 24 contained in EOP for loss of containment integrity 000074 (EPE 74; W E06 & E07) Inadequate Core Cooling /

Not sampled 4

000076 (APE 76) High Reactor Coolant Activity / 9 AA2.01 Ability to determine and interpret the following as they apply to the High Reactor Coolant 2.7 25 Activity: Location or process point that is causing an alarm 000078 (APE 78*) RCS Leak / 3 Not sampled (W E01 & E02) Rediagnosis & SI Termination / 3 N/A for CE design (W E13) Steam Generator Overpressure / 4 N/A for CE design (W E15) Containment Flooding / 5 N/A for CE design (W E16) High Containment Radiation /9 N/A for CE design (BW A01) Plant Runback / 1 N/A for CE design (BW A02 & A03) Loss of NNI-X/Y/7 N/A for CE design (BW A04) Turbine Trip / 4 N/A for CE design Rev. 11

ES-401 5 Form ES-401-2 (BW A05) Emergency Diesel Actuation / 6 N/A for CE design (BW A07) Flooding / 8 N/A for CE design (BW E03) Inadequate Subcooling Margin / 4 N/A for CE design (BW E08; W E03) LOCA CooldownDepressurization / 4 N/A for CE design (BW E09; CE A13**; W E09 & E10) Natural Circulation/4 AA2.2 Ability to determine and interpret the following as they apply to the (Natural Circulation Operations): Adherence to 2.9 26 appropriate procedures and operation within the limitations in the Facilitys license and amendments.

(BW E13 & E14) EOP Rules and Enclosures N/A for CE design (CE A11**; W E08) RCS OvercoolingPressurized Thermal AA1.1 Ability to operate and / or Shock / 4 monitor the following as they apply to the (RCS Overcooling)

Components, and functions of 3.3 27 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

(CE A16) Excess RCS Leakage / 2 Not sampled (CE E09) Functional Recovery Not sampled (CE E13*) Loss of Forced Circulation/LOOP/Blackout / 4 Not sampled K/A Category Point Totals: 1 2 1 2 2 1 Group Point Total: 9/4 Rev. 11

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 A2.02 Ability to (a) predict the impacts of the 3.7 28 Pump following malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP 004 (SF1; SF2 CVCS) Chemical and K3.04 Knowledge of the effect that a loss or 3.7 29 Volume Control malfunction of the CVCS will have on the following: RCPs K6.31 Knowledge of the effect of a loss or malfunction on the following CVCS 3.1 30 components: Seal injection system and limits on flow range 005 (SF4P RHR) Residual Heat A1.01 Ability to predict and/or monitor changes 3.5 31 Removal in parameters (to prevent exceeding design limits) associated with operating the RHRS controls including: Heatup/cooldown rates 2.4.46 Ability to verify that the alarms are 4.2 32 consistent with the plant conditions.

006 (SF2; SF3 ECCS) Emergency 2.1.7 Ability to evaluate plant performance and 4.4 33 Core Cooling make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation 007 (SF5 PRTS) Pressurizer A4.09 Ability to manually operate and/or 2.5 34 Relief/Quench Tank monitor in the control room: Relationships between PZR level and changing levels of the PRT and bleed holdup tank 008 (SF8 CCW) Component Cooling K1.04 Knowledge of the physical connections 3.3 35 Water and/or cause-effect relationships between the CCWS and the following systems: RCS, in order to determine source(s) of RCS leakage into the CCWS 010 (SF3 PZR PCS) Pressurizer K4.03 Knowledge of PZR PCS design 3.8 36 Pressure Control feature(s) and/or interlock(s) which provide for the following: Over pressure control K5.01 Knowledge of the operational 3.5 37 implications of the following concepts as the apply to the PZR PCS: Determination of condition of fluid in PZR, using steam tables 012 (SF7 RPS) Reactor Protection K2.01 Knowledge of bus power supplies to the 3.3 38 following: RPS channels, components, and interconnections K4.08 Knowledge of RPS design feature(s) and/or interlock(s) which provide for the following: Logic matrix testing 2.8 39 Rev. 11

ES-401 7 Form ES-401-2 013 (SF2 ESFAS) Engineered A1.02 Ability to predict and/or monitor changes 3.9 40 Safety Features Actuation in parameters (to Prevent exceeding design limits) associated with operating the ESFAS controls including: Containment pressure, temperature, and humidity 022 (SF5 CCS) Containment Cooling 2.4.20 Knowledge of the operational 3.8 41 implications of EOP warnings, cautions, and notes.

025 (SF5 ICE) Ice Condenser N/A for PV 026 (SF5 CSS) Containment Spray K2.02 Knowledge of bus power supplies to the 2.7 42 following: MOVs A4.01 Ability to manually operate and/or monitor in the control room: CSS controls 4.5 43 039 (SF4S MSS) Main and Reheat K5.03 Knowledge of the operational 3.6 44 Steam implications of the following concepts as the apply to the MRSS: Effect of steam removal on reactivity 059 (SF4S MFW) Main Feedwater A2.12 Ability to (a) predict the impacts of the 3.1 45 following malfunctions or operations on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of feedwater regulating valves 061 (SF4S AFW) K6.01 Knowledge of the effect of a loss or 2.5 46 Auxiliary/Emergency Feedwater malfunction of the following will have on the AFW components: Controllers and positioners 062 (SF6 ED AC) AC Electrical K3.03 Knowledge of the effect that a loss or 3.7 47 Distribution malfunction of the ac distribution system will have on the following: DC system 063 (SF6 ED DC) DC Electrical K1.02 Knowledge of the physical connections 2.7 48 Distribution and/or cause effect relationships between the DC electrical system and the following systems: AC electrical system 064 (SF6 EDG) Emergency Diesel A3.07 Ability to monitor automatic operation of 3.6 49 Generator the ED/G system, including: Load Sequencing 073 (SF7 PRM) Process Radiation A1.01 Ability to predict and/or monitor changes 3.2 50 Monitoring in parameters (to prevent exceeding design limits) associated with operating the PRM system controls including: Radiation levels 076 (SF4S SW) Service Water K4.01 Knowledge of SWS design feature(s) 2.5 51 and/or interlock(s) which provide for the following: Conditions initiating automatic closure of closed cooling water auxiliary building header supply and return valves A2.02 Ability to (a) predict the impacts of the 2.7 52 following malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Service water header pressure Rev. 11

ES-401 8 Form ES-401-2 078 (SF8 IAS) Instrument Air K1.05 Knowledge of the physical connections 3.4 53 and/or cause-effect relationships between the IAS and the following systems: MSIV air A3.01 Ability to monitor automatic operation of 3.1 54 the IAS, including: Air pressure 103 (SF5 CNT) Containment K3.01 Knowledge of the effect that a loss or 3.3 55 malfunction of the containment system will have on the following: Loss of containment integrity under shutdown conditions 053 (SF1; SF4P ICS*) Int. Control N/A for CE design K/A Category Point Totals: 3 2 3 3 2 2 3 3 3 2 3 Group Point Total: 28/5 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 A3.06 Ability to monitor automatic operation of the CRDS, including: RCS temperature and 3.9 56 pressure 002 (SF2; SF4P RCS) Reactor A4.02 Ability to manually operate and/or Coolant monitor in the control room: Indications necessary to verify natural circulation from 4.3 57 appropriate level, flow, and temperature indications and valve positions upon loss of forced circulation 011 (SF2 PZR LCS) Pressurizer Not Sampled Level Control 014 (SF1 RPI) Rod Position 2.1.31 Ability to locate control room switches, Indication controls, and indications, and to determine that 4.6 58 they correctly reflect the desired plant lineup.

015 (SF7 NI) Nuclear Not Sampled Instrumentation 016 (SF7 NNI) Nonnuclear Not Sampled Instrumentation 017 (SF7 ITM) In-Core Temperature K6.01 Knowledge of the effect of a loss or Monitor malfunction of the following ITM system 2.7 59 components: Sensors and detectors 027 (SF5 CIRS) Containment Iodine K1.01 Knowledge of the physical connections Removal and/or cause effect relationships between the 3.4 60 CIRS and the following systems: CSS 028 (SF5 HRPS) Hydrogen K2.01 Knowledge of bus power supplies to the 2.5 61 Recombiner and Purge Control following: Hydrogen recombiners 029 (SF8 CPS) Containment Purge Not Sampled 033 (SF8 SFPCS) Spent Fuel Pool Not Sampled Cooling 034 (SF8 FHS) Fuel-Handling Not Sampled Equipment 035 (SF 4P SG) Steam Generator Not Sampled 041 (SF4S SDS) Steam K3.02 Knowledge of the effect that a loss or Dump/Turbine Bypass Control malfunction of the SDS will have on 3.8 62 the following: RCS Rev. 11

ES-401 9 Form ES-401-2 045 (SF 4S MTG) Main Turbine A2.08 Ability to (a) predict the impacts of the Generator following malfunctions or operation on the MT/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those 2.8 63 malfunctions or operations: Steam dumps are not cycling properly at low load, or stick open at higher load (isolate and use atmospheric reliefs when necessary) 055 (SF4S CARS) Condenser Air Not Sampled Removal 056 (SF4S CDS) Condensate Not Sampled 068 (SF9 LRS) Liquid Radwaste Not Sampled 071 (SF9 WGS) Waste Gas K4.04 Knowledge of design feature(s) and/or Disposal interlock(s) which provide for the following: 2.9 64 Isolation of waste gas release tanks 072 (SF7 ARM) Area Radiation K5.01 Knowledge of the operational Monitoring implications of the following concepts as they apply to the ARM system: Radiation theory, 2.7 65 including sources, types, units, and effects 075 (SF8 CW) Circulating Water Not Sampled 079 (SF8 SAS**) Station Air Not Sampled 086 Fire Protection Not Sampled K/A Category Point Totals: 1 1 1 1 1 1 0 1 1 1 1 Group Point Total: 10/3 Rev. 11

Facility: Palo Verde Date of Exam:

Category K/A # Topic RO SRO-only IR # IR #

2.1.3 Knowledge of shift or short-term relief turnover 3.7 66 practices.

2.1.15 Knowledge of administrative requirements for temporary management directives, such as standing orders, night 2.7 67

1. Conduct of orders, Operations memos, etc.

Operations 2.1.

2.1.

Subtotal 2 2.2.12 Knowledge of surveillance procedures 3.7 68 2.2.13 Knowledge of tagging and clearance procedures. 4.1 69 2.2.17 Knowledge of the process for managing maintenance activities during power operations, such as risk 2.6 70

2. Equipment assessments, work prioritization, and coordination with Control the transmission system operator.

2.2.

Subtotal 3 2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry 3.4 71 requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

2.3.12 Knowledge of radiological safety principles pertaining to

3. Radiation licensed operator duties, such as containment entry Control 3.2 72 requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

2.3.4 Knowledge of radiation exposure limits under normal or 3.4 73 emergency conditions.

2.3.

Subtotal 3 2.4.29 Knowledge of the emergency plan. 3.1 74 2.4.26 Knowledge of facility protection requirements, including 3.1 75 fire brigade and portable firefighting equipment usage.

4. Emergency 2.4.

Procedures/Plan 2.4.

2.4.

Subtotal 2 Tier 3 Point Total 10 10 Rev. 11

ES-401 PWR Examination Outline Form ES-401-2 Facility: Palo Verde Date of Exam:

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 1 1 1 3 Systems Tier Totals 38 4 4 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 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.)