ML18044A246
| ML18044A246 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 12/14/2017 |
| From: | Jesse Seymour, Bielby M NRC/RGN-III/DRS/OLB |
| To: | Exelon Generation Co |
| Seymour J | |
| Shared Package | |
| ML17152A385 | List: |
| References | |
| Download: ML18044A246 (16) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 Facility: Byron Station, Units 1 and 2 Date of Exam: December 2017 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 1 1 2 N/A 2 2 N/A 1 9 2 2 4 Evolutions Tier Totals 4 4 5 5 5 4 27 5 5 10 1 3 2 3 3 2 2 3 3 3 2 2 28 2 3 5 2.
Plant 2 1 0 1 1 1 1 1 1 1 1 1 10 N/A 2 1 3 Systems Tier Totals 4 2 4 4 3 3 4 4 4 3 3 38 4 4 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/SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #
Knowledge of the operational implications of 000007 (EPE 7; BW E02&E10; CE E02) .03 the following concepts as they apply to the 3.7 1 Reactor Trip, Stabilization, Recovery / 1 reactor trip: Reasons for closing the main turbine governor valve and the main turbine stop valve after a reactor trip
.01 Ability to determine or interpret the following as 4.2 76 they apply to a reactor trip: Decreasing power level, from available indications 000008 (APE 8) Pressurizer Vapor Space Accident / 3 2.2.4 000009 (EPE 9) Small Break LOCA / 3 Ability to explain the variations in control 3.6 77 board/control room layouts, systems, instrumentation, and procedural actions between units at a facility.
000011 (EPE 11) Large Break LOCA / 3 .02 Knowledge of the interrelations between the 2.6 2 Large Break LOCA and the following: Pumps 2.1.23 000015 (APE 15) Reactor Coolant Pump Ability to perform specific system and integrated 4.3 3 Malfunctions / 4 plant procedures during all modes of plant operation.
000022 (APE 22) Loss of Reactor Coolant .01 Knowledge of the reasons for the following 2.7 4 Makeup / 2 responses as they apply to the Loss of Reactor Coolant Makeup: Adjustment of RCP seal backpressure regulator valve to obtain normal flow 000025 (APE 25) Loss of Residual Heat .04 Ability to determine and interpret the following 3.3 5 Removal System / 4 as they apply to the Loss of Residual Heat Removal System: Location and isolability of leaks 000026 (APE 26) Loss of Component 02 Knowledge of the reasons for the following 3.6 6 Cooling Water / 8 responses as they apply to the Loss of Component Cooling Water: The automatic actions (alignments) within the CCWS resulting from the actuation of the ESFAS 000027 (APE 27) Pressurizer Pressure .02 Knowledge of the operational implications of 2.8 7 Control System Malfunction / 3 the following concepts as they apply to Pressurizer Pressure Control Malfunctions:
Expansion of liquids as temperature increases
ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #
2.2.39 Knowledge of less than or equal to one hour 4.5 78 Technical Specification action statements for systems.
000029 (EPE 29) Anticipated Transient .05 Ability to determine or interpret the following as 3.2 8 Without Scram / 1 they apply to a ATWS: System component valve position indications
.05 Ability to determine or interpret the following as 3.4 79 they apply to a ATWS: System component valve position indications 000038 (EPE 38) Steam Generator Tube .04 Knowledge of the operational implications of 3.1 9 Rupture / 3 the following concepts as they apply to the SGTR: Reflux boiling 000040 (APE 40; BW E05; CE E05; W E12) Steam Line RuptureExcessive Heat Transfer / 4 000054 (APE 54; CE E06) Loss of Main .01 Ability to operate and / or monitor the following 4.5 10 Feedwater /4 as they apply to the Loss of Main Feedwater (MFW): AFW controls, including the use of alternate AFW sources 000055 (EPE 55) Station Blackout / 6 .02 Knowledge of the reasons for the following 4.3 11 responses as the apply to the Station Blackout:
Actions contained in EOP for loss of offsite and onsite power 000056 (APE 56) Loss of Offsite Power / 6 2.2.36 000057 (APE 57) Loss of Vital AC Ability to analyze the effect of maintenance 3.1 12 Instrument Bus / 6 activities, such as degraded power sources, on the status of limiting conditions for operations.
000058 (APE 58) Loss of DC Power / 6 01 Ability to operate and / or monitor the following 3.4 13 as they apply to the Loss of DC Power: Cross-tie of the affected dc bus with the alternate supply
ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #
000062 (APE 62) Loss of Nuclear Service .07 Ability to operate and / or monitor the following 2.9 14 Water / 4 as they apply to the Loss of Nuclear Service Water (SWS): Flow rates to the components and systems that are serviced by the SWS; interactions among the components 2.2.37 000065 (APE 65) Loss of Instrument Air / 8 Ability to determine operability and/or availability of 3.6 15 safety related equipment.
.03 Ability to determine and interpret the following 2.9 80 as they apply to the Loss of Instrument Air:
Location and isolation of leaks 000077 (APE 77) Generator Voltage and .02 Knowledge of the interrelations between 3.1 16 Electric Grid Disturbances / 6 Generator Voltage and Electric Grid Disturbances and the following: Breakers, relays 2.240 Ability to apply Technical Specifications for a 4.7 81 system.
(W E04) LOCA Outside Containment / 3 (W E11) Loss of Emergency Coolant 2.1 Ability to determine and interpret the following 3.4 17 Recirculation / 4 as they apply to the (Loss of Emergency Coolant Recirculation): Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
(BW E04; W E05) Inadequate Heat 2.2 Knowledge of the interrelations between the 3.9 18 TransferLoss of Secondary Heat Sink / 4 (Loss of Secondary Heat Sink) 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.
K/A Category Totals: 3 3 3 3 3 3 Group Point Total: 18 3 3 6
ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)
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 .21 Knowledge of the operational 2.7 19 implications of the following concepts as they apply to Dropped Control Rod: Delta flux (I).
000005 (APE 5) Inoperable/Stuck Control Rod / 1 .05 Knowledge of the reasons for 3.4 20 the following responses as they apply to the Inoperable/Stuck Control Rod:
Power limits on rod misalignment 000024 (APE 24) Emergency Boration / 1 Knowledge of procedures, 3.9 21 2.1.37 guidelines, or limitations associated with reactivity management.
000028 (APE 28) Pressurizer (PZR) Level Control Malfunction / 2 000032 (APE 32) Loss of Source Range Nuclear .01 Knowledge of the interrelations 2.7 22 Instrumentation / 7 between the Loss of Source Range Nuclear Instrumentation and the following: Power supplies, including proper switch positions 000033 (APE 33) Loss of Intermediate Range Nuclear .08 Ability to determine and 3.3 23 Instrumentation / 7 interpret the following as they apply to the Loss of Intermediate Range Nuclear Instrumentation: Intermediate range channel operability 000036 (APE 36; BW/A08) Fuel-Handling Incidents / 8 000037 (APE 37) Steam Generator Tube Leak / 3 .09 Ability to determine and 3.4 82 interpret the following as they apply to the Steam Generator Tube Leak: System status, using independent readings from redundant Condensate air ejector exhaust monitor 000051 (APE 51) Loss of Condenser Vacuum / 4 .01 Knowledge of the reasons for 2.8 24 the following responses as they apply to the Loss of Condenser Vacuum: Loss of steam dump capability upon loss of condenser vacuum
ES-401 6 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #
000059 (APE 59) Accidental Liquid Radwaste Release / 9 Knowledge of events related to 4.1 83 2.4.30 system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.
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 .06 Ability to operate and / or 3.0 25 monitor the following as they apply to the Plant Fire on Site:
Fire alarm 000068 (APE 68; BW A06) Control Room Evacuation / 8 Knowledge of system purpose 4.0 84 2.1.27 and/or function.
000069 (APE 69; W E14) Loss of Containment Integrity / 5 .01 Ability to operate and / or 3.5 26 monitor the following as they apply to the Loss of Containment Integrity: Isolation valves, dampers, and electro-pneumatic devices 000074 (EPE 74; W E06 & E07) Inadequate Core Cooling / .05 Ability to determine or interpret 4.2 85 4 the following as they apply to a Inadequate Core Cooling:
Trends in water levels of PZR and makeup storage tank caused by various sized leaks in the RCS 000076 (APE 76) High Reactor Coolant Activity / 9 000078 (APE 78*) RCS Leak / 3 (W E01 & E02) Rediagnosis & SI Termination / 3
ES-401 7 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #
(W E13) Steam Generator Overpressure / 4 (W E15) Containment Flooding / 5 (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 CooldownDepressurization / 4 2.2 Ability to determine and 3.5 27 interpret the following as they apply to the (LOCA Cooldown and Depressurization):
Adherence to appropriate procedures and operation within the limitations in the facility*s license and amendments.
ES-401 8 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #
(BW E09; CE A13**; W E09 & E10) Natural Circulation/4 (BW E13 & E14) EOP Rules and Enclosures (CE A11**; W E08) RCS OvercoolingPressurized 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 2 2 2 1 Group Point Total: 9 2 2 4
ES-401 9 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO/SRO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #
003 (SF4P RCP) Reactor .03 Knowledge of the effect that a loss or 2.8 28 Coolant Pump malfunction of the RCPS will have on the following: Feedwater and emergency feedwater
.01 Ability to monitor automatic operation 3.3 29 of the RCPS, including: Seal injection flow 004 (SF1; SF2 CVCS) Chemical .18 Ability to monitor automatic operation 2.8 30 and Volume Control of the CVCS, including: Interpretation of letdown orifice isolation valve position indicators
.03 Knowledge of bus power supplies to the 3.3 55 following: Charging Pumps 005 (SF4P RHR) Residual Heat .07 Ability to predict and/or monitor 2.5 31 Removal changes in parameters (to prevent exceeding design limits) associated with operating the RHRS controls including: Determination of test acceptability by comparison of recorded valve response times with Tech-Spec requirements 2.1.30 Ability to locate and operate components, 4.4 32 including local controls.
006 (SF2; SF3 ECCS) .10 Knowledge of the operational 2.5 33 Emergency Core Cooling implications of the following concepts as they apply to ECCS: Theory of thermal stress
.10 Ability to (a) predict the impacts of the 3.9 86 following malfunctions or operations on the ECCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Low boron concentration in SIS 007 (SF5 PRTS) Pressurizer .01 Knowledge of the effect that a loss or 3.3 34 Relief/Quench Tank malfunction of the PRTS will have on the following: Containment
ES-401 10 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO/SRO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #
.01 Ability to monitor automatic operation 2.7 35 of the PRTS, including: Components which discharge to the PRT 008 (SF8 CCW) Component .02 Knowledge of the physical connections 3.3 36 Cooling Water and/or cause-effect relationships between the CCWS and the following systems: Loads cooled by CCWS 010 (SF3 PZR PCS) Pressurizer .02 Knowledge of the effect of a loss or 3.2 37 Pressure Control malfunction of the following will have on the PZR PCS: PZR 012 (SF7 RPS) Reactor .03 Ability to (a) predict the impacts of the 4.4 38 Protection following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Incorrect channel bypassing 013 (SF2 ESFAS) Engineered .01 Knowledge of bus power supplies to the 3.6 39 Safety Features Actuation following: ESFAS/safeguards equipment control
.06 Ability to (a) predict the impacts of the 3.7 40 following malfunctions or operations on the ESFAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Inadvertent ESFAS actuation 022 (SF5 CCS) Containment .01 Knowledge of the effect that a loss or 2.9 41 Cooling malfunction of the CCS will have on the following: Containment equipment subject to damage by high or low temperature, humidity, and pressure 2.2.22 Knowledge of limiting conditions for 4.7 87 operations and safety limits.
025 (SF5 ICE) Ice Condenser 026 (SF5 CSS) Containment .01 Knowledge of the physical connections 4.2 42 Spray and/or cause effect relationships between the CSS and the following systems: ECCS
ES-401 11 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO/SRO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #
2.4.2 Knowledge of system set points, interlocks 4.5 43 and automatic actions associated with EOP entry conditions.
039 (SF4S MSS) Main and .08 Knowledge of the operational 3.6 44 Reheat Steam implications of the following concepts as the apply to the MRSS: Effect of steam removal on reactivity
.02 Knowledge of MRSS design feature(s) 3.1 45 and/or interlock(s) which provide for the following: Utilization of T-ave. program control when steam dumping through atmospheric relief/dump valves, including T-ave. limits 059 (SF4S MFW) Main .08 Ability to manually operate and monitor 3.0 46 Feedwater in the control room: Feed regulating valve controller 061 (SF4S AFW) .01 Ability to predict and/or monitor 3.9 47 Auxiliary/Emergency Feedwater changes in parameters (to prevent exceeding design limits) associated with operating the AFW controls including: S/G level 062 (SF6 ED AC) AC Electrical .02 Knowledge of ac distribution system 2.5 48 Distribution design feature(s) and/or interlock(s) which provide for the following: Circuit breaker automatic trips
.04 Ability to (a) predict the impacts of the 2.9 49 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: Effect on plant of de-energizing a bus.
063 (SF6 ED DC) DC Electrical .01 Ability to predict and/or monitor 2.5 50 Distribution changes in parameters associated with operating the DC electrical system controls including: Battery capacity as it is affected by discharge rate 064 (SF6 EDG) Emergency .07 Knowledge of the effect of a loss or 2.7 51 Diesel Generator malfunction of the following will have on the ED/G system: Air receivers
ES-401 12 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO/SRO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #
073 (SF7 PRM) Process .01 Ability to manually operate and/or 3.9 52 Radiation Monitoring monitor in the control room: Effluent release 2.4.35 Knowledge of local auxiliary operator tasks 4.0 88 during an emergency and the resultant operational effects.
076 (SF4S SW) Service Water .16 Knowledge of the physical connections 3.6 53 and/or cause- effect relationships between the SWS and the following systems: ESF
.02 Ability to (a) predict the impacts of the 2.7 89 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 078 (SF8 IAS) Instrument Air .01 Knowledge of IAS design feature(s) 3.1 54 and/or interlock(s) which provide for the following: Manual/automatic transfers of control 2.4.34 103 (SF5 CNT) Containment Knowledge of RO tasks performed outside 4.1 90 the main control room during an emergency and the resultant operational effects.
053 (SF1; SF4P ICS*)
Integrated Control K/A Category Point Totals: 3 2 3 3 2 2 3 3 3 2 2 Group Point Total: 28 2 3 5
ES-401 13 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 2 (RO/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 002 (SF2; SF4P RCS) Reactor .07 Ability to predict and/or monitor changes 3.3 56 Coolant in parameters (to prevent exceeding design limits) associated with operating the RCS controls including: Reactor differential temperature 011 (SF2 PZR LCS) .02 Ability to (a) predict the impacts of the 3.2 91 Pressurizer Level Control following malfunctions or operations on the PZR LCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Excessive charging 014 (SF1 RPI) Rod Position .01 Knowledge of the operational implications 2.7 57 Indication of the following concepts as they apply to the RPIS: Reasons for differences between RPIS and step counter 015 (SF7 NI) Nuclear .04 Knowledge of the effect of a loss or 3.1 58 Instrumentation malfunction on the following will have on the NIS: Bistables and logic circuits 016 (SF7 NNI) Nonnuclear Instrumentation 017 (SF7 ITM) In-Core .02 Knowledge of ITM system design 3.1 59 Temperature Monitor feature(s) and/or interlock(s) which provide for the following: Sensing and determination of location core hot spots 027 (SF5 CIRS) Containment Iodine Removal 028 (SF5 HRPS) Hydrogen Recombiner and Purge Control 029 (SF8 CPS) Containment Purge
ES-401 14 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 2 (RO/SRO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #
033 (SF8 SFPCS) Spent Fuel Knowledge of conditions and limitations in the 3.6 60 Pool Cooling 2.2.38 facility license.
034 (SF8 FHS) Fuel-Handling Equipment 035 (SF 4P SG) Steam .01 Ability to manually operate and/or monitor 3.7 61 Generator in the control room: Shift of S/G controls between manual and automatic control, by bumpless transfer 041 (SF4S SDS) Steam .01 Knowledge of the effect that a loss or 3.2 62 Dump/Turbine Bypass Control malfunction of the SDS will have on the following: S/G 045 (SF 4S MTG) Main .18 Knowledge of the physical connections and/or 3.6 63 Turbine Generator cause-effect relationships between the MT/G system and the following systems: RPS 055 (SF4S CARS) Condenser Air Removal 056 (SF4S CDS) Condensate 068 (SF9 LRS) Liquid .04 Ability to (a) predict the impacts of the 3.3 64 Radwaste 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: Failure of automatic isolation 071 (SF9 WGS) Waste Gas .02 Ability to (a) predict the impacts of the 2.5 92 Disposal following malfunctions or operations on the Waste Gas Disposal System ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Use of waste gas release monitors, radiation, gas flow rate, and totalizer
ES-401 15 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 2 (RO/SRO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #
072 (SF7 ARM) Area Radiation Monitoring 075 (SF8 CW) Circulating Ability to explain and apply system limits and 4.0 93 Water 2.1.32 precautions.
079 (SF8 SAS**) Station Air 086 Fire Protection .01 Ability to monitor automatic operation of 2.9 65 the Fire Protection System including:
Starting mechanisms of fire water pumps 050 (SF 9 CRV*) Control Room Ventilation K/A Category Point Totals: 1 0 1 1 1 1 1 1 1 1 1 Group Point Total: 10 2 1 3
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Byron Station, Units 1 and 2 Date of Exam: December 2017 Category K/A # Topic RO SRO-only IR # IR #
2.1.5 Ability to use procedures related to shift staffing, such as 2.9 66 minimum crew complement, overtime limitations, etc.
2.1.17 Ability to make accurate, clear, and concise verbal reports. 3.9 67 2.1.27 Knowledge of system purpose and/or function. 3.9 68
- 1. Conduct of Operations 2.1.26 Knowledge of industrial safety procedures (such as rotating 3.6 94 equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).
2.1.36 Knowledge of procedures and limitations involved in core 4.1 95 alterations.
Subtotal 3 2 2.2.15 Ability to determine the expected plant configuration using design 3.9 69 and configuration control documentation, such as drawings, line-ups, tag-outs, etc.
2.2.17 Knowledge of the process for managing maintenance activities 2.6 70 during power operations, such as risk assessments, work prioritization, and coordination with the transmission system
- 2. Equipment operator.
Control 2.2.19 Knowledge of maintenance work order requirements. 3.4 96 2.2.20 Knowledge of the process for managing troubleshooting 3.8 97 activities.
Subtotal 2 2 2.3.4 Knowledge of radiation exposure limits under normal or 3.2 71 emergency conditions.
2.3.5 Ability to use radiation monitoring systems, such as fixed 2.9 72 radiation monitors and alarms, portable survey instruments,
- 3. Radiation personnel monitoring equipment, etc.
Control 2.3.15 Knowledge of radiation monitoring systems, such as fixed 3.1 98 radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.
Subtotal 2 1 Knowledge of low power/shutdown implications in accident (e.g.,
2.4.9 3.7 73 loss of coolant accident or loss of residual heat removal) mitigation strategies.
2.4.30 Knowledge of events related to system operation/status that 2.7 74 must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.
- 4. Emergency 2.4.50 Ability to verify system alarm setpoints and operate controls 4.2 75 Procedures/Plan identified in the alarm response manual.
2.4.25 Knowledge of fire protection procedures. 3.7 99 2.4.41 Knowledge of the emergency action level thresholds and 4.6 100 classifications.
Subtotal 3 2 Tier 3 Point Total 10 7