ML22186A203
| ML22186A203 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 11/08/2017 |
| From: | Randy Baker NRC/RGN-III/DRS/OLB |
| To: | |
| Baker R | |
| Shared Package | |
| ML17068A445 | List: |
| References | |
| L-17-281 | |
| Download: ML22186A203 (10) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 Facility: DAVIS-BESSE NUCLEAR POWER STATION Date of Exam: 02/05/2018 to 02/16/2018 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 3 3 6 Emergency and Abnormal Plant 2 2 2 2 N/A 1 1 N/A 1 9 2 2 4 Evolutions Tier Totals 5 5 5 4 4 4 27 5 5 10 1 2 2 2 3 3 2 3 3 3 3 2 28 3 2 5 2.
Plant 2 1 1 1 1 1 0 1 1 1 1 1 10 1 1 1 3 Systems Tier Totals 3 3 3 4 4 2 4 4 4 4 3 38 5 3 8
- 3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 2 2 3 2 2 1 2 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only 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.
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) 0 Reactor Trip, Stabilization, Recovery / 1 000008 (APE 8) Pressurizer Vapor Space 01 Knowledge of the operational implications of the following 3.2 1 Accident / 3 concepts as they apply to a Pressurizer Vapor Space Accident: Thermodynamics and flow characteristics of open or leaking valves 000009 (EPE 9) Small Break LOCA / 3 03 Knowledge of the interrelations between the small break 3.0 1 LOCA and the following: S/Gs 000011 (EPE 11) Large Break LOCA / 3 03 Knowledge of the reasons for the following responses as the 4.1 1 05 apply to the Large Break LOCA: Starting auxiliary feed 4.0 pumps and flow, EDG, and service water pumps Injection into Cold Leg 000015 (APE 15) Reactor Coolant Pump 21 Ability to operate and / or monitor the following as they apply 4.4 1 Malfunctions / 4 to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): Development of natural circulation flow 000022 (APE 22) Loss of Reactor Coolant 04 Ability to determine and interpret the following as they apply 2.9 1 Makeup / 2 to the Loss of Reactor Coolant Makeup: How long PZR level can be maintained within limits 000025 (APE 25) Loss of Residual Heat 01 Ability to perform specific system and integrated plant 4.3 1 Removal System / 4 -23 procedures during all modes of plant operation.
000026 (APE 26) Loss of Component Cooling 02 Ability to determine and interpret the following as they apply 2.9 1 Water / 8 to the Loss of Component Cooling Water: The cause of possible CCW loss 000027 (APE 27) Pressurizer Pressure Control 04 Ability to operate and / or monitor the following as they apply 3.9 1 System Malfunction / 3 01 to the Pressurizer Pressure Control Malfunctions: Pressure 4.0 recovery, using emergency-only heaters PZR heaters, sprays, and PORVs 000029 (EPE 29) Anticipated Transient Without 07 Knowledge of the reasons for the following responses as the 3.1 1 Scram / 1 12 apply to the ATWS: Using local turbine trip lever Actions 4.4 contained in EOP for ATWS 000038 (EPE 38) Steam Generator Tube 02 Knowledge of the operational implications of the following 3.2 1 Rupture / 3 concepts as they apply to the SGTR: Leak rate vs. pressure drop 000040(APE 40; BW E05; CE E05; W E12) 01 Knowledge of the interrelations between the Steam Line 2.6 1 Steam Line Rupture: Excessive Heat Transfer/4 Rupture and the following: Valves 000054 (APE 54; CE E06) Loss of Main 02 Knowledge of the bases in Technical Specifications for 3.2 1 Feedwater /4 -25 limiting conditions for operations and safety limits.
000055 (EPE 55) Station Blackout / 6 03 Ability to determine or interpret the following as they apply to 3.9 1 a Station Blackout: Actions necessary to restore power 000056 (APE 56) Loss of Offsite Power / 6 11 Ability to operate and / or monitor the following as they apply 3.7 1 to the Loss of Offsite Power: HPI system 000057 (APE 57) Loss of Vital AC Instrument 01 Knowledge of the reasons for the following responses as 4.1 1 Bus / 6 they apply to the Loss of Vital AC Instrument Bus: Actions contained in EOP for loss of vital ac electrical instrument bus 000058 (APE 58) Loss of DC Power / 6 01 Knowledge of the operational implications of the following 2.8 1 concepts as they apply to Loss of DC Power: Battery charger equipment and instrumentation 000062 (APE 62) Loss of Nuclear Service 02 Knowledge of less than or equal to one hour Technical 3.9 1 Water / 4 -39 Specification action statements for systems.
000065 (APE 65) Loss of Instrument Air / 8 0 000077 (APE 77) Generator Voltage and 05 Knowledge of the interrelations between Generator Voltage 3.1 1 Electric Grid Disturbances / 6 and Electric Grid Disturbances and the following: Pumps (W E04) LOCA Outside Containment / 3 NOT APPLICABLE 0 (W E11) Loss of Emergency Coolant NOT APPLICABLE 0 Recirculation / 4 (BW E04; W E05) Inadequate Heat Transfer 0 Loss of Secondary Heat Sink / 4 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 EvolutionsTier 1/Group 2 (RO)
E/APE # / Name / Safety Function K K K A A G* K/A Topic(s) IR #
1 2 3 1 2 000001 (APE 1) Continuous Rod Withdrawal / 1 0 000003 (APE 3) Dropped Control Rod / 1 0 000005 (APE 5) Inoperable/Stuck Control Rod/1 0 000024 (APE 24) Emergency Boration/ 1 0 000028 (APE 28) Pressurizer (PZR) Level Control Malf./ 2 0 000032 (APE 32) Loss of Source Range Nuclear Inst./ 7 0 000033 (APE 33) Loss of Intermediate Range Nuclear Inst./ 7 0 000036 (APE 36; BW/A08) Fuel-Handling Incidents / 8 0 000037 (APE 37) Steam Generator Tube Leak/ 3 0 000051 (APE 51) Loss of Condenser Vacuum / 4 04- Knowledge of low power/shutdown implications in accident (e.g., 3.8 1 09 loss of coolant accident or loss of RHR) mitigation strategies 4.2 31 annunciators, indications, or response procedures 000059 (APE 59) Accidental Liquid Radwaste Release / 9 0 000060 (APE 60)Accidental Gaseous Radwaste Release/ 9 0 000061 (APE 61) Area Radiation Monitoring System Alarms / 7 0 000067 (APE 67) Plant Fire On Site / 8 05 Ability to operate and/or monitor the following as they apply to 3.0 1 Plant Fire on Site: Plant and control room ventilation systems 000068 (APE 68; BW A06) Control Room Evacuation / 8 03 Knowledge of the interrelations between the Control Room 2.9 1 Evacuation and the following: Controllers and positioners 000069 (APE 69; W E14) Loss of Containment Integrity / 5 01 Knowledge of the operational implications of the following 2.6 1 concepts as they apply to Loss of Containment Integrity: Effect of pressure on leak rate 000074(EPE 74; W E06 & E07)Inadequate Core Cooling/ 4 NOT APPLICABLE 0 000076 (APE 76) High Reactor Coolant Activity / 9 06 Knowledge of the reasons for the following responses as they 3.2 1 apply to the High Reactor Coolant Activity: Actions contained in EOP for high reactor coolant activity 000078 (APE 78*) RCS Leak / 3 0 (W E01 & E02) Rediagnosis & SI Termination / 3 NOT APPLICABLE 0 (W E13) Steam Generator Overpressure / 4 NOT APPLICABLE 0 (W E15) Containment Flooding / 5 NOT APPLICABLE 0 (W E16) High Containment Radiation /9 NOT APPLICABLE 0 (BW A01) Plant Runback / 1 0 (BW A02 & A03) Loss of NNI-X/Y/7 02 Ability to determine and interpret the following as they apply to 4.0 1 (NNI-X): Adherence to appropriate procedures and operation within the limitations in the facility*s license and amendments (BW A04) Turbine Trip / 4 0 (BW A05) Emergency Diesel Actuation / 6 0 (BW A07) Flooding / 8 01 Knowledge of the operational implications of the following 3.5 1 concepts as they apply to (Flooding): Components, capacity, and function of emergency systems (BW E03) Inadequate Subcooling Margin / 4 02 Knowledge of the interrelations between (Inadequate Subcooling 4.3 1 Margin) and the following: Facility*s heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.
(BW E08; W E03) LOCA CooldownDepressurization / 4 01 Knowledge of the reasons for the following responses as they 3.0 1 apply to (LOCA Cooldown): Facility operating characteristics during transient conditions, including coolant chemistry and effects of temperature, pressure, and reactivity changes and operating limitations and the reasons for these operating characteristics.
(BW E09; CE A13**; W E09 & E10) Natural Circulation/4 0 (BW E13 & E14) EOP Rules and Enclosures 0 (CE A11**; W E08) RCS OvercoolingPTS/ 4 NOT APPLICABLE 0 (CE A16) Excess RCS Leakage / 2 NOT APPLICABLE 0 (CE E09) Functional Recovery NOT APPLICABLE 0 (CE E13*) Loss of Forced Circulation/LOOP/Blackout / 4 NOT APPLICABLE 0 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 SystemsTier 2/Group 1 (RO)
System # / Name K K K K K K A A A A G* K/A Topic(s) IR #
1 2 3 4 5 6 1 2 3 4 003 (SF4P RCP) Reactor Coolant Pump 0 Ability to manually operate and/or monitor in the control room: RCP cooling water 3.2 1 8 supplies 004 (SF1; SF2 CVCS) Chemical and Volume Control 0 01- Knowledge of the effect that a loss or malfunction of the CVCS will have on the 3.8 5 28 following: PZR LCS 2 Knowledge of the purpose and function of major system components and controls. 4.1 005 (SF4P RHRS) Residual Heat Removal System 1 Knowledge of the physical connections and/or cause-effect relationships between 3.1 1 2 the RHRS and the following systems: Safeguard pumps 006 (SF2; SF3 ECCS) Emergency Core Cooling 0 Knowledge of bus power supplies to the following: ESFAS-operated valves 3.6 1 4
007 (SF5 PRTS) Pressurizer Relief/Quench Tank 0 Knowledge of PRTS design feature(s) and/or interlock(s) which provide for the 2.6 1 1 following: Quench tank cooling 008 (SF8 CCW) Component Cooling Water 0 Ability to predict and/or monitor changes in parameters (to prevent exceeding design 2.7 1 3 limits) associated with operating the CCWS controls including: CCW pressure 010 (SF3 PZR PCS) Pressurizer Pressure Control 0 Knowledge of the operational implications of the following concepts as the apply to 3.5 1 1 the PZR PCS: Determination of condition of fluid in PZR, using steam tables 012 (SF7 RPS) Reactor Protection 0 Knowledge of the effect of a loss or malfunction of the following will have on the 3.3 1 4 RPS: Bypass-block circuits 013 (SF2 ESFAS) Eng. Safety Features Actuation 0 Ability to (a) predict the impacts of the following malfunctions or operations on the 3.7 1 6 ESFAS; and (b) based Ability on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations; Inadvertent ESFAS actuation 022 (SF5 CCS) Containment Cooling 0 Ability to monitor automatic operation of the CCS, including: Initiation of safeguards 4.1 1 1 mode of operation 025 (SF5 ICE) Ice Condenser NOT APPLICABLE 0 026 (SF5 CSS) Containment Spray System 0 Ability to manually operate and/or monitor in the control room: Containment spray 3.5 1 5 (CSS) reset switches 039 (SF4S MRSS) Main and Reheat Steam System 0 04- Knowledge of MRSS design feature(s) and/or interlock(s) which provide for the 3.3 6 31 following: Prevent reverse steam flow on steam line break 2 Knowledge of annunciator alarms, indications, or response procedures. 4.2 059 (SF4S MFW) Main Feedwater 0 0 Knowledge of the physical connections and/or cause-effect relationships between 3.2 7 3 the MFW and the following systems: ICS 2 Ability to predict and/or monitor changes in parameters (to prevent exceeding design 2.7 limits) associated with operating the MFW controls including: Power level restrictions for operation of MFW pumps and valves 061 (SF4S AFW) Auxiliary/Emergency Feedwater 0 0 Knowledge of bus power supplies to the following: AFW system MOVs 3.2 1 3 Knowledge of the operational implications of the following concepts as the apply to 2 the AFW: Pump head effects when control valve is shut 2.6 062 (SF6 ED AC) AC Electrical Distribution 0 1 Knowledge of the effect that a loss or malfunction of the AC distribution system will 3.5 1 5 have on the following: Major system loads 2 Ability to (a) predict the impacts of the following malfunctions or operations on the 2.8 AC distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Consequence of paralleling out-of-phase/mismatch in volts 063 (SF6 ED DC) DC Electrical Distribution 0 0 Knowledge of DC electrical system design feature(s) and/or interlock(s) which 2.9 2 1 provide for the following: Breaker interlocks, permissives, bypasses and cross-ties 2 Ability to monitor automatic operation of the DC electrical system, including: Meters, 2.7 annunciators, dials, recorders, and indicating lights 064 (SF6 EDG) Emergency Diesel Generator 0 0 Knowledge of the effect of a loss or malfunction of the following will have on the 2.7 7 9 EDG system: Air receivers 2 Ability to manually operate and/or monitor in the control room: Establishing power 3.2 from the ring bus (to relieve EDG) 073 (SF7 PRM) Process Radiation Monitoring 0 Knowledge of the operational implications as they apply to concepts as they apply to 2.9 1 3 the PRM system: Relationship between radiation intensity and exposure limits 076 (SF4S SWS) Service Water System 0 Ability to predict and/or monitor changes in parameters (to prevent exceeding design 2.6 1 2 limits) associated with operating the SWS controls including: Reactor and turbine building closed cooling water temperatures 078 (SF8 IAS) Instrument Air 0 Ability to monitor automatic operation of the IAS, including: Air pressure 3.1 1 1
103 (SF5 CNT) Containment 0 Ability to (a) predict the impacts of the following malfunctions or operations on the 3.5 1 4 containment system and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Containment evacuation (including recognition of the alarm) 053 (SF1; SF4P ICS*) Integrated Control System NOT APPLICABLE 0 K/A Category Point Totals: 2 2 2 3 3 2 3 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 SystemsTier 2/Group 2 (RO)
System # / Name K K K K K K A A A A G* K/A Topic(s) IR #
1 2 3 4 5 6 1 2 3 4 001 (SF1 CRDS) Control Rod Drive 0 Knowledge of the physical connections and/or cause-effect 3.6 1 2 relationships between the CRDS and the following systems:
CVCS 002 (SF2; SF4P RCS) Reactor Coolant 0 011 (SF2 PZR LCS) Pressurizer Level Control 0 Knowledge of bus power supplies to the following: Charging 3.1 1 1 pumps 014 (SF1 RPI) Rod Position Indication 0 015 (SF7 NIS) Nuclear Instrumentation System 0 Knowledge of the effect that a loss or malfunction of the NIS will 3.4 1 4 have on the following: ICS 016 (SF7 NNI) Nonnuclear Instrumentation 0 017 (SF7 ITM) In-Core Temperature Monitor 0 Knowledge of ITM system design feature(s) and/or interlock(s) 3.1 1 3 which provide for the following: Range of temperature indication 027 (SF5 CIRS) Containment Iodine Removal NOT APPLICABLE 0 028 (SF5 HRPS) Hydrogen Recombiner and NOT APPLICABLE 0 Purge Control 029 (SF8 CPS) Containment Purge 0 033 (SF8 SFPCS) Spent Fuel Pool Cooling 0 Ability to predict and/or monitor changes in parameters (to 2.8 1 2 prevent exceeding design limits) associated with Spent Fuel Pool 2.7 0 Cooling System operating the controls including: Radiation 1 monitoring systems Spent fuel pool water level 034 (SF8 FHS) Fuel-Handling Equipment 0 035 (SF 4P SGS) Steam Generator System 0 Knowledge of operational implications of the following concepts 3.4 1 1 as the apply to the SGS: Effect of secondary parameters, pressure, and temperature on reactivity 041 (SF4S SDS) Steam Dump/Turbine Bypass 0 Ability to monitor automatic operation of the SDS, including: RCS 3.3 0 Control 2 pressure, RCS temperature, and reactor power 1 045 (SF 4S MTG) Main Turbine Generator 0 Ability to (a) predict the impacts of the following malfunctions 2.8 1 8 or operation on the MTG system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those 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 Removal 0 Ability to monitor automatic operation of the CARS, including: 2.5 1 3 Automatic diversion of CARS exhaust 056 (SF4S CDS) Condensate 0 068 (SF9 LRS) Liquid Radwaste 0 071 (SF9 WGS) Waste Gas Disposal 0 072 (SF7 ARM) Area Radiation Monitoring 0 Ability to manually operate and/or monitor in the control room: 2.5 1 2 Major components 075 (SF8 CW) Circulating Water 0 079 (SF8 SAS**) Station Air 0 086 Fire Protection 04- Knowledge of system set points, interlocks and automatic 4.5 1 02 actions associated with EOP entry conditions RO tasks 4.2 34 performed outside the main control room during an emergency and the resultant operational effects.
050 (SF 9 CRV*) Control Room Ventilation NOT APPLICABLE 0 K/A Category Point Totals: 1 1 1 1 1 0 1 1 1 1 1 Group Point Total: 10
ES-401 6 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #
000007 (EPE 7; BW E02&E10; CE E02) 0 Reactor Trip, Stabilization, Recovery / 1 000008 (APE 8) Pressurizer Vapor Space 0 Accident / 3 000009 (EPE 9) Small Break LOCA / 3 0 000011 (EPE 11) Large Break LOCA / 3 01- Ability to evaluate plant performance and make 4.7 1 07 operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
000015 (APE 15) Reactor Coolant Pump 0 Malfunctions / 4 000022 (APE 22) Loss of Reactor Coolant 0 Makeup / 2 000025 (APE 25) Loss of Residual Heat 03 Ability to determine and interpret the following as they 3.8 1 Removal System / 4 apply to the Loss of Residual Heat Removal System:
Increasing reactor building sump level 000026 (APE 26) Loss of Component 0 Cooling Water / 8 000027 (APE 27) Pressurizer Pressure 0 Control System Malfunction / 3 000029 (EPE 29) Anticipated Transient 0 Without Scram / 1 000038 (EPE 38) Steam Generator Tube 04- Ability to perform without reference to procedures those 4.4 1 Rupture / 3 49 actions that require immediate operation of system components and controls.
000040 (APE 40; BW E05; CE E05; W E12) 0 Steam Line RuptureExcessive Heat Transfer / 4 000054 (APE 54; CE E06) Loss of Main 0 Feedwater /4 000055 (EPE 55) Station Blackout / 6 0 000056 (APE 56) Loss of Offsite Power / 6 06 Ability to determine and interpret the following as they 3.6 1 apply to the Loss of Offsite Power: Operational status of CCW pump 000057 (APE 57) Loss of Vital AC 0 Instrument Bus / 6 000058 (APE 58) Loss of DC Power / 6 0 000062 (APE 62) Loss of Nuclear Service 0 Water / 4 000065 (APE 65) Loss of Instrument Air / 8 0 000077 (APE 77) Generator Voltage and 04- Knowledge of local auxiliary operator tasks during an 4.0 1 Electric Grid Disturbances / 6 35 emergency and the resultant operational effects.
(W E04) LOCA Outside Containment / 3 NOT APPLICABLE 0 (W E11) Loss of Emergency Coolant NOT APPLICABLE 0 Recirculation / 4 (BW E04; W E05) Inadequate Heat 01 Ability to determine and interpret the following as they 4.4 1 TransferLoss of Secondary Heat Sink / 4 apply to the (Inadequate Heat Transfer): Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
K/A Category Totals: 3 3 Group Point Total: 6
ES-401 7 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #
000001 (APE 1) Continuous Rod Withdrawal / 1 0 000003 (APE 3) Dropped Control Rod / 1 04- Ability to prioritize and interpret the 4.3 1 45 significance of each annunciator or alarm.
000005 (APE 5) Inoperable/Stuck Control Rod / 1 0 000024 (APE 24) Emergency Boration / 1 0 000028 (APE 28) Pressurizer (PZR) Level Control Malfunction / 2 0 000032 (APE 32) Loss of Source Range Nuclear Instrumentation 0
/7 000033 (APE 33) Loss of Intermediate Range Nuclear 0 Instrumentation / 7 000036 (APE 36; BW/A08) Fuel-Handling Incidents / 8 03 Ability to determine and interpret the 4.2 1 following as they apply to the Fuel Handling Incidents: Magnitude of potential radioactive release 000037 (APE 37) Steam Generator Tube Leak / 3 0 000051 (APE 51) Loss of Condenser Vacuum / 4 0 000059 (APE 59) Accidental Liquid Radwaste Release / 9 0 000060 (APE 60) Accidental Gaseous Radwaste Release / 9 0 000061 (APE 61) Area Radiation Monitoring System Alarms / 7 0 000067 (APE 67) Plant Fire On Site / 8 0 000068 (APE 68; BW A06) Control Room Evacuation / 8 0 000069 (APE 69; W E14) Loss of Containment Integrity / 5 0 000074 (EPE 74; W E06 & E07) Inadequate Core Cooling / 4 02- Ability to determine operability and/or 4.6 1 37 availability of safety related equipment.
000076 (APE 76) High Reactor Coolant Activity / 9 0 000078 (APE 78*) RCS Leak / 3 0 (W E01 & E02) Rediagnosis & SI Termination / 3 NOT APPLICABLE 0 (W E13) Steam Generator Overpressure / 4 NOT APPLICABLE 0 (W E15) Containment Flooding / 5 NOT APPLICABLE 0 (W E16) High Containment Radiation /9 NOT APPLICABLE 0 (BW A01) Plant Runback / 1 0 (BW A02 & A03) Loss of NNI-X/Y/7 0 (BW A04) Turbine Trip / 4 0 (BW A05) Emergency Diesel Actuation / 6 02 Ability to determine and interpret the 3.8 1 following as they apply to the (Emergency Diesel Actuation): Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.
(BW A07) Flooding / 8 0 (BW E03) Inadequate Subcooling Margin / 4 0 (BW E08; W E03) LOCA CooldownDepressurization / 4 0 (BW E09; CE A13**; W E09 & E10) Natural Circulation/4 0 (BW E13 & E14) EOP Rules and Enclosures 0 (CE A11**; W E08) RCS OvercoolingPTS/ 4 NOT APPLICABLE 0 (CE A16) Excess RCS Leakage / 2 NOT APPLICABLE 0 (CE E09) Functional Recovery NOT APPLICABLE 0 (CE E13*) Loss of Forced Circulation/LOOP/Blackout / 4 NOT APPLICABLE 0 K/A Category Point Totals: 2 2 Group Point Total: 4
ES-401 8 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (SRO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #
003 (SF4P RCP) Reactor Coolant Pump 02 Ability to (a) predict the impacts of the following 3.9 1 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 Volume 0 Control 005 (SF4P RHR) Residual Heat Removal 0 006 (SF2; SF3 ECCS) Emergency Core Cooling 0 007 (SF5 PRTS) Pressurizer Relief/Quench Tank 0 008 (SF8 CCW) Component Cooling Water 02- Knowledge of surveillance procedures. 4.1 1 12 010 (SF3 PZR PCS) Pressurizer Pressure Control 03 Ability to (a) predict the impacts of the following 4.2 1 malfunctions or operations on the PZR PCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: PORV failures 012 (SF7 RPS) Reactor Protection 0 013 (SF2 ESFAS) Engineered Safety Features 0 Actuation 022 (SF5 CCS) Containment Cooling 0 025 (SF5 ICE) Ice Condenser NOT APPLICABLE 0 026 (SF5 CSS) Containment Spray 0 039 (SF4S MSS) Main and Reheat Steam 0 059 (SF4S MFW) Main Feedwater 0 061 (SF4S AFW) Auxiliary/Emergency Feedwater 0 062 (SF6 ED AC) AC Electrical Distribution 0 063 (SF6 ED DC) DC Electrical Distribution 0 064 (SF6 EDG) Emergency Diesel Generator 02- Ability to recognize system parameters that are entry- 4.6 1 42 level conditions for Technical Specifications.
073 (SF7 PRM) Process Radiation Monitoring 0 076 (SF4S SW) Service Water 0 078 (SF8 IAS) Instrument Air 01 Ability to (a) predict the impacts of the following 2.9 1 malfunctions or operations on the IAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Air dryer and filter malfunctions 103 (SF5 CNT) Containment 0 053 (SF1; SF4P ICS*) Integrated Control NOT APPLICABLE 0 K/A Category Point Totals: 3 2 Group Point Total: 5
ES-401 9 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 2 (SRO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #
001 (SF1 CRDS) Control Rod Drive 0 002 (SF2; SF4P RCS) Reactor 0 Coolant 011 (SF2 PZR LCS) Pressurizer 0 Level Control 014 (SF1 RPI) Rod Position 04 Ability to (a) predict the impacts of the following 3.9 1 Indication malfunctions or operations on the RPIS; and (b) based on those on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Misaligned rod 015 (SF7 NI) Nuclear 0 Instrumentation 016 (SF7 NNI) Nonnuclear 0 Instrumentation 017 (SF7 ITM) In-Core Temperature 0 Monitor 027 (SF5 CIRS) Containment Iodine NOT APPLICABLE 0 Removal 028 (SF5 HRPS) Hydrogen NOT APPLICABLE 0 Recombiner and Purge Control 029 (SF8 CPS) Containment Purge 0 033 (SF8 SFPCS) Spent Fuel Pool 0 Cooling 034 (SF8 FHS) Fuel-Handling 02 Ability to predict and/or monitor changes in 3.7 1 Equipment parameters (to prevent exceeding design limits) associated with operating the Fuel Handling System controls including: Water level in the refueling canal 035 (SF 4P SG) Steam Generator 0 041 (SF4S SDS) Steam 0 Dump/Turbine Bypass Control 045 (SF 4S MTG) Main Turbine 0 Generator 055 (SF4S CARS) Condenser Air 0 Removal 056 (SF4S CDS) Condensate 0 068 (SF9 LRS) Liquid Radwaste 0 071 (SF9 WGS) Waste Gas 01 Ability to explain and apply system limits and 4.0 1 Disposal - precautions.
32 072 (SF7 ARM) Area Radiation 0 Monitoring 075 (SF8 CW) Circulating Water 0 079 (SF8 SAS**) Station Air 0 086 Fire Protection 0 050 (SF 9 CRV*) Control Room NOT APPLICABLE 0 Ventilation K/A Category Point Totals: 1 1 1 Group Point Total: 3
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: DAVIS-BESSE NUCLEAR POWER STATION Date of Exam: 02/05/2018 to 02/16/2018 Category K/A # Topic RO SRO-only IR # IR #
2.1.1 Knowledge of conduct of operations requirements. 3.8 1 - -
2.1.15 Knowledge of administrative requirements for temporary 2.7 1 - -
management directives, such as standing orders, night orders, Operations memos, etc.
2.1.25 Ability to interpret reference materials, such as graphs, curves, - - 4.2 1
- 1. Conduct of tables, etc.
Operations 2.1.40 Knowledge of refueling administrative requirements. - - 3.9 1 2.1.43 Ability to use procedures to determine the effects on reactivity 4.1 1 - -
of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.
Subtotal 3 2 2.2.7 Knowledge of the process for conducting special or infrequent - - 3.6 1 tests.
2.2.35 Ability to determine Technical Specification Mode of Operation. - - 4.5 1
- 2. Equipment 2.2.36 Ability to analyze the effect of maintenance activities, such as 3.1 1 - -
Control degraded power sources, on the status of limiting conditions for operations.
2.2.43 Knowledge of the process used to track inoperable alarms. 3.0 1 - -
Subtotal 2 2 2.3.6 Ability to approve release permits. - - 3.8 1 2.3.12 Knowledge of radiological safety principles pertaining to 3.2 1 - -
licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked
- 3. Radiation Control high-radiation areas, aligning filters, etc.
2.3.14 Knowledge of radiation or contamination hazards that may arise 3.4 1 - -
during normal, abnormal, or emergency conditions or activities.
Subtotal 2 1 2.4.23 Knowledge of the bases for prioritizing emergency procedure - - 4.4 1 implementation during emergency operations.
2.4.27 Knowledge of fire in the plant procedures. 3.4 1 - -
2.4.32 Knowledge of operator response to loss of all annunciators. 3.6 1 - -
- 4. Emergency Procedures/Plan 2.4.41 Knowledge of the emergency action level thresholds and - - 4.6 1 classifications.
2.4.47 Ability to diagnose and recognize trends in an accurate and 4.2 1 - -
timely manner utilizing the appropriate control room reference material.
Subtotal 3 2 Tier 3 Point Total 10 7