ML19239A403
| ML19239A403 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 08/23/2019 |
| From: | FirstEnergy Nuclear Operating Co |
| To: | NRC/RGN-III/DRS/OLB |
| demarshall j | |
| Shared Package | |
| ML17215A921 | List: |
| References | |
| Download: ML19239A403 (21) | |
Text
ES-401 1
Form ES-401-1 Facility: Perry Nuclear Power Plant Date of Exam: February 11-22, 2019 Tier Group RO K/A Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
Total A2 G*
Total
- 1.
Emergency and Abnormal Plant Evolutions 1
4 3
3 N/A 3
3 N/A 4
20 3
4 7
2 1
1 1
1 2
1 7
2 1
3 Tier Totals 5
4 4
4 5
5 27 5
5 10
- 2.
Plant Systems 1
2 2
2 3
3 3
3 2
2 2
2 26 2
3 5
2 1
1 2
1 1
1 1
1 1
1 1
12 1
1 1
3 Tier Totals 3
3 4
4 4
4 4
3 3
3 3
38 4
4 8
- 3. Generic Knowledge and Abilities Categories 1
2 3
4 10 1
2 3
4 7
3 3
2 2
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. 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-401-1 ES-401 BWR Examination Outline Form ES-401-1 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 295001 (APE 1) Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 02 AK1.02 - Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION: Power/flow distribution.
(CFR: 41.8 to 41.10) 3.3 1
295003 (APE 3) Partial or Complete Loss of AC Power / 6 2.4.3 Generic K/A 2.4.3: Ability to identify post-accident instrumentation.
(CFR: 41.6 / 45.4) 3.7 2
295004 (APE 4) Partial or Total Loss of DC Power / 6 03 AA2.03 - Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER: Battery voltage.
(CFR: 41.10 / 43.5 / 45.13) 2.8 3
295005 (APE 5) Main Turbine Generator Trip /
3 01 AA1.01 - Ability to operate and/or monitor the following as they apply to MAIN TURBINE GENERATOR TRIP:
Recirculation system: Plant-Specific.
(CFR: 41.7 / 45.6) 3.1 4
295006. (APE 6) Scram / 1 01 AK3.01 - Knowledge of the reasons for the following responses as they apply to SCRAM: Reactor water level response.
(CFR: 41.5 / 45.6) 3.8 5
295016 (APE 16) Control Room Abandonment
/ 7 02 AK2.02 - Knowledge of the interrelations between CONTROL ROOM ABANDONMENT and the following:
Local control stations: Plant-Specific.
(CFR: 41.7 / 45.8) 4.0 6
295018 (APE 18) Partial or Complete Loss of CCW / 8 01 AK1.01 - Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: Effects on component/system operations.
(CFR: 41.8 to 41.10) 3.5 7
295019 (APE 19) Partial or Complete Loss of Instrument Air / 8 2.1.7 Generic K/A 2.1.7 - Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
(CFR: 41.5 / 43.5 / 45.12 / 45.13) 4.4 8
295021 (APE 21) Loss of Shutdown Cooling /
4 01 AA2.01 - Ability to determine and/or interpret the following as they apply to LOSS OF SHUTDOWN COOLING:
Reactor water heatup/cooldown rate.
(CFR: 41.10 / 43.5 / 45.13) 3.5 9
295023 (APE 23) Refueling Accidents / 8 06 AA1.06 - Ability to operate and/or monitor the following as they apply to REFUELING ACCIDENTS: Neutron monitoring.
(CFR: 41.7 / 45.6) 3.3 10 295024 High Drywell Pressure / 5 03 EK3.03 - Knowledge of the reasons for the following responses as they apply to HIGH DRYWELL PRESSURE:
Containment venting: Mark-III.
(CFR: 41.5 / 45.6) 3.6 11 295025 (EPE 2) High Reactor Pressure / 3 08 EK2.08 - Knowledge of the interrelations between HIGH REACTOR PRESSURE and the following: Reactor/turbine pressure regulating system: Plant-Specific.
(CFR: 41.7 / 45.8) 3.7 12
ES-401 3
Form ES-401-1 295026 (EPE 3) Suppression Pool High Water Temperature / 5 02 EK1.02 - Knowledge of the operational implications of the following concepts as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: Steam condensation.
(CFR: 41.8 to 41.10) 3.5 13 295027 (EPE 4) High Containment Temperature (Mark III Containment Only) / 5 2.4.46 Generic K/A 2.4.46 - Ability to verify that the alarms are consistent with the plant conditions.
(CFR: 41.10 / 43.5 / 45.3 / 45.12) 4.2 14 295028 (EPE 5) High Drywell Temperature (Mark I and Mark II only) / 5 295030 (EPE 7) Low Suppression Pool Water Level / 5 01 EA2.01 - Ability to determine and/or interpret the following as they apply to LOW SUPPRESSION POOL WATER LEVEL: Suppression pool level.
(CFR: 41.10 / 43.5 / 45.13) 4.1 15 295031 (EPE 8) Reactor Low Water Level / 2 04 EA1.04 - Ability to operate and/or monitor the following as they apply to REACTOR LOW WATER LEVEL: High pressure core spray: Plant-Specific.
(CFR: 41.7 / 45.6) 4.3 16 295037 (EPE 14) Scram Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 02 EK3.02 - Knowledge of the reasons for the following responses as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: SBLC injection.
(CFR: 41.5 / 45.6) 4.3 17 295038 (EPE 15) High Offsite Radioactivity Release Rate / 9 12 EK2.12 - Knowledge of the interrelations between HIGH OFF-SITE RELEASE RATE and the following: Feedwater leakage control: BWR-6.
(CFR: 41.7 / 45.8) 3.5 18 600000 (APE 24) Plant Fire On Site / 8 02 AK1.02 - Knowledge of the operation applications of the following concepts as they apply to Plant Fire On Site: Fire Fighting.
2.9 19 700000 (APE 25) Generator Voltage and Electric Grid Disturbances / 6 2.4.31 Generic K/A 2.4.31 - Knowledge of annunciator alarms, indications, or response procedures.
(CFR: 41.10 / 45.3) 4.2 20 K/A Category Totals:
4 3
3 3
3 4
Group Point Total:
20
ES-401 4
Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 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 295002 (APE 2) Loss of Main Condenser Vacuum / 3 295007 (APE 7) High Reactor Pressure / 3 295008 (APE 8) High Reactor Water Level / 2 05 AA2.05 - Ability to determine and/or interpret the following as they apply to HIGH REACTOR WATER LEVEL: Swel.l (CFR: 41.10 / 43.5 / 45.13) 2.9 21 295009 (APE 9) Low Reactor Water Level / 2 295010 (APE 10) High Drywell Pressure / 5 295011 (APE 11) High Containment Temperature (Mark III Containment only) / 5 01 AA1.01 - Ability to operate and/or monitor the following as they apply to HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY):
Containment ventilation/cooling system:
Mark-III.
(CFR: 41.7 / 45.6) 3.6 22 295012 (APE 12) High Drywell Temperature /
5 295013 (APE 13) High Suppression Pool Temperature. / 5 295014 (APE 14) Inadvertent Reactivity Addition / 1 02 AK3.02 - Knowledge of the reasons for the following responses as they apply to INADVERTENT REACTIVITY ADDITION: Control rod blocks.
(CFR: 41.5 / 45.6) 3.7 23 295015 (APE 15) Incomplete Scram / 1 295017 (APE 17) Abnormal Offsite Release Rate / 9 295020 (APE 20) Inadvertent Containment Isolation / 5 & 7 11 AK2.11 - Knowledge of the interrelations between INADVERTENT CONTAINMENT ISOLATION and the following: Standby gas treatment system/FRVS: Plant-Specific.
(CFR: 41.7 / 45.8) 3.2 24 295022 (APE 22) Loss of Control Rod Drive Pumps / 1 295029 (EPE 6) High Suppression Pool Water Level / 5 01 EK1.01 - Knowledge of the operational implications of the following concepts as they apply to HIGH SUPPRESSION POOL WATER LEVEL: Containment integrity.
(CFR: 41.8 to 41.10) 3.4 25 295032 (EPE 9) High Secondary Containment Area Temperature / 5 295033 (EPE 10) High Secondary Containment Area Radiation Levels / 9 295034 (EPE 11) Secondary Containment Ventilation High Radiation / 9 2.4.47 Generic K/A 2.4.47 - Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
(CFR: 41.10 / 43.5 / 45.12) 4.2 26 295035 (EPE 12) Secondary Containment High Differential Pressure / 5
ES-401 5
Form ES-401-1 295036 (EPE 13) Secondary Containment High Sump/Area Water Level / 5 500000 (EPE 16) High Containment Hydrogen Concentration / 5 03 EA2.03 - Ability to determine and / or interpret the following as they apply to HIGH PRIMARY CONTAINMENT HYDROGEN CONCENTRATIONS:
Combustible limits for drywell.
(CFR: 41.10 / 43.5 / 45.13) 3.3 27 K/A Category Point Totals:
1 1
1 1
2 1
Group Point Total:
7
ES-401 6
Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant SystemsTier 2/Group 1 (RO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR 203000 (SF2, SF4 RHR/LPCI)
RHR/LPCI: Injection Mode 01 06 A1.01 - Ability to predict and/or monitor changes in parameters associated with operating the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) controls including: Reactor water level.
(CFR: 41.5 / 45.5)
A2.06 - Ability to (a) predict the impacts of the following on the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Emergency generator failure.
(CFR: 41.5 / 45.6) 4.2 3.8 28 29 205000 (SF4 SCS) Shutdown Cooling 04 K6.04 - Knowledge of the effect that a loss or malfunction of the following will have on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE): Reactor water level.
(CFR: 41.7 / 45.7) 3.6 30 206000 (SF2, SF4 HPCIS)
High-Pressure Coolant Injection 207000 (SF4 IC) Isolation (Emergency) Condenser 209001 (SF2, SF4 LPCS)
Low-Pressure Core Spray 01 08 K5.01 - Knowledge of the operational implications of the following concepts as they apply to LOW PRESSURE CORE SPRAY SYSTEM: Indications of pump cavitation.
(CFR: 41.5 / 45.3)
A1.08 - Ability to predict and/or monitor changes in parameters associated with operating the LOW PRESSURE CORE SPRAY SYSTEM controls including: System lineup.
(CFR: 41.5 / 45.5) 2.6 3.3 31 32 209002 (SF2, SF4 HPCS)
High-Pressure Core Spray 02 K4.02 - Knowledge of HIGH PRESSURE CORE SPRAY SYSTEM (HPCS) design feature(s) and/or interlocks which provide for the following: Prevents over filling reactor vessel: Plant-Specific.
(CFR: 41.7) 3.4 33 211000 (SF1 SLCS) Standby Liquid Control 01 K3.01 - Knowledge of the effect that a loss or malfunction of the STANDBY LIQUID CONTROL SYSTEM will have on following:
Ability to shutdown the reactor in certain conditions.
(CFR: 41.7 / 45.4) 4.3 34
ES-401 7
Form ES-401-1 212000 (SF7 RPS) Reactor Protection 01 01 K2.01 - Knowledge of electrical power supplies to the following: RPS motor-generator sets.
(CFR: 41.7)
K6.01 - Knowledge of the effect that a loss or malfunction of the following will have on the REACTOR PROTECTION SYSTEM:
A.C. electrical distribution.
(CFR: 41.7 / 45.7) 3.2 3.6 35 36 215003 (SF7 IRM)
Intermediate-Range Monitor 01 K1.01 - Knowledge of the physical connections and/or cause effect relationships between INTERMEDIATE RANGE MONITOR (IRM) SYSTEM and the following: RPS.
(CFR: 41.2 to 41.9 / 45.7 to 45.8) 3.9 37 215004 (SF7 SRMS) Source-Range Monitor 2.4.45 Generic K/A 2.4.45 - Ability to prioritize and interpret the significance of each annunciator or alarm.
(CFR: 41.10 / 43.5 / 45.12) 4.1 38 215005 (SF7 PRMS) Average Power Range Monitor/Local Power Range Monitor 06 05 K5.06 - Knowledge of the operational implications of the following concepts as they apply to AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM: Assignment of LPRM's to specific APRM channels.
(CFR: 41.5 / 45.3)
A4.05 - Ability to manually operate and/or monitor in the control room: Trip bypasses.
(CFR: 41.7 / 45.5 to 45.8) 2.5 3.4 39 40 217000 (SF2, SF4 RCIC) Reactor Core Isolation Cooling 02 A3.02 - Ability to monitor automatic operations of the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) including: Turbine startup.
(CFR: 41.7 / 45.7) 3.6 41 218000 (SF3 ADS) Automatic Depressurization 02 A2.02 - Ability to (a) predict the impacts of the following on the AUTOMATIC DEPRESSURIZATION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Large break LOCA.
(CFR: 41.5 / 45.6) 3.5 42 223002 (SF5 PCIS) Primary Containment Isolation/Nuclear Steam Supply Shutoff 02 A1.02 - Ability to predict and/or monitor changes in parameters associated with operating the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF controls including:
Valve closures.
(CFR: 41.5 / 45.5) 3.7 43 239002 (SF3 SRV) Safety Relief Valves 04 K6.04 - Knowledge of the effect that a loss or malfunction of the following will have on the RELIEF/SAFETY VALVES: D.C. power:
Plant-Specific.
(CFR: 41.7 / 45.7) 3.0 44
ES-401 8
Form ES-401-1 259002 (SF2 RWLCS) Reactor Water Level Control 07 K5.07 - Knowledge of the operational implications of the following concepts as they apply to REACTOR WATER LEVEL CONTROL SYSTEM: Turbine speed control mechanisms: TDRFP.
(CFR: 41.5 / 45.3) 2.7 45 261000 (SF9 SGTS) Standby Gas Treatment 05 K4.05 - Knowledge of STANDBY GAS TREATMENT SYSTEM design feature(s) and/or interlocks which provide for the following: Fission product gas removal.
(CFR: 41.7) 2.6 46 262001 (SF6 AC) AC Electrical Distribution 03 K3.03 - Knowledge of the effect that a loss or malfunction of the A.C. ELECTRICAL DISTRIBUTION will have on following: D.C.
electrical distribution.
(CFR: 41.7 / 45.4) 2.9 47 262002 (SF6 UPS) Uninterruptable Power Supply (AC/DC) 19 K1.19 - Knowledge of the physical connections and/or cause-effect relationships between UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) and the following: Power range neutron monitoring system: Plant-Specific.
(CFR: 41.2 to 41.9 / 45.7 to 45.8) 2.9 48 263000 (SF6 DC) DC Electrical Distribution 01 K2.01 - Knowledge of electrical power supplies to the following: Major D.C. loads.
(CFR: 41.7) 3.1 49 264000 (SF6 EGE) Emergency Generators (Diesel/Jet) EDG 2.1.19 Generic K/A 2.1.19 - Ability to use plant computers to evaluate system or component status.
(CFR: 41.10 / 45.12) 3.9 50 300000 (SF8 IA) Instrument Air 03 02 K4.03 - Knowledge of (INSTRUMENT AIR SYSTEM) design feature(s) and or interlocks which provide for the following:
Securing of IAS upon loss of cooling water.
(CFR: 41.7)
A3.02 - Ability to monitor automatic operations of the INSTRUMENT AIR SYSTEM including: Air temperature.
(CFR: 41.7 / 45.7) 2.8 2.9 51 52 400000 (SF8 CCS) Component Cooling Water 01 A4.01 - Ability to manually operate and / or monitor in the control room: CCW indications and control.
(CFR: 41.7 / 45.5 to 45.8) 3.1 53 510000 (SF4 SWS*) Service Water (Normal and Emergency)
K/A Category Point Totals:
2 2
2 3
3 3
3 2
2 2
2 Group Point Total:
26
ES-401 9
Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant SystemsTier 2/Group 2 (RO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR 201001 (SF1 CRDH) CRD Hydraulic 03 K3.03 - Knowledge of the effect that a loss or malfunction of the CONTROL ROD DRIVE HYDRAULIC SYSTEM will have on following: Control rod drive mechanisms.
(CFR: 41.7 / 45.4) 3.1 54 201002 (SF1 RMCS) Reactor Manual Control 201003 (SF1 CRDM) Control Rod and Drive Mechanism 201004 (SF7 RSCS) Rod Sequence Control 201005 (SF1, SF7 RCIS) Rod Control and Information 201006 (SF7 RWMS) Rod Worth Minimizer 202001 (SF1, SF4 RS) Recirculation 202002 (SF1 RSCTL) Recirculation Flow Control 204000 (SF2 RWCU) Reactor Water Cleanup 11 K1.11 - Knowledge of the physical connections and/or cause-effect relationships between REACTOR WATER CLEANUP SYSTEM and the following: PCIS/NSSSS.
(CFR: 41.2 to 41.9 / 45.7 to 45.8) 3.5 55 214000 (SF7 RPIS) Rod Position Information 215001 (SF7 TIP) Traversing In-Core Probe 215002 (SF7 RBMS) Rod Block Monitor 216000 (SF7 NBI) Nuclear Boiler Instrumentation 01 K2.01 - Knowledge of electrical power supplies to the following:
Analog trip system: Plant-Specific.
(CFR: 41.7) 2.8 56 219000 (SF5 RHR SPC) RHR/LPCI:
Torus/Suppression Pool Cooling Mode 223001 (SF5 PCS) Primary Containment and Auxiliaries 226001 (SF5 RHR CSS) RHR/LPCI:
Containment Spray Mode 230000 (SF5 RHR SPS) RHR/LPCI:
Torus/Suppression Pool Spray Mode 233000 (SF9 FPCCU) Fuel Pool Cooling/Cleanup 2.4.18 Generic K/A 2.4.18 - Knowledge of the specific bases for EOPs.
(CFR: 41.10 / 43.1 / 45.13) 3.3 57 234000 (SF8 FH) Fuel-Handling Equipment 239001 (SF3, SF4 MRSS) Main and Reheat Steam 11 A4.11 - Ability to manually operate and/or monitor in the control room:
Alternate methods of verifying valve positions.
(CFR: 41.7 / 45.5 to 45.8) 3.1 58 239003 (SF9 MSVLCS) Main Steam Isolation Valve Leakage Control
ES-401 10 Form ES-401-1 241000 (SF3 RTPRS) Reactor/Turbine Pressure Regulating 04 K5.04 - Knowledge of the operational implications of the following concepts as they apply to REACTOR/TURBINE PRESSURE REGULATING SYSTEM: Turbine inlet pressure vs. reactor pressure.
(CFR: 41.5 / 45.3) 3.3 59 245000 (SF4 MTGEN) Main Turbine Generator/Auxiliary 05 A3.05 - Ability to monitor automatic operations of the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS including: Control valve operation.
(CFR: 41.7 / 45.7) 3.0 60 256000 (SF2 CDS) Condensate 14 A2.14 - Ability to (a) predict the impacts of the following on the REACTOR CONDENSATE SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low Condensate storage tank level.
(CFR: 41.5 / 45.6) 3.3 61 259001 (SF2 FWS) Feedwater 06 A1.06 - Ability to predict and/or monitor changes in parameters associated with operating the REACTOR FEEDWATER SYSTEM controls including: Feedwater heater level.
(CFR: 41.5 / 45.5) 2.7 62 268000 (SF9 RW) Radwaste 271000 (SF9 OG) Offgas 11 K6.11 - Knowledge of the effect that a loss or malfunction of the following will have on the OFFGAS SYSTEM: Condenser vacuum.
(CFR: 41.7 / 45.7) 3.2 63 272000 (SF7, SF9 RMS) Radiation Monitoring 286000 (SF8 FPS) Fire Protection 06 K4.06 - Knowledge of FIRE PROTECTION SYSTEM design feature(s) and/or interlocks which provide for the following: Fire suppression capability that does not rely on the displacement of oxygen (Halon): Plant-Specific.
(CFR: 41.7)
(CFR: 41.5 / 45.3)
(CFR: 41.7 / 45.7)
(CFR: 41.5 / 45.5)
(CFR: 41.5 / 45.6)
(CFR: 41.7 / 45.7)
(CFR: 41.7 / 45.5 to 45.8) 3.4 64 288000 (SF9 PVS) Plant Ventilation 03 K3.03 - Knowledge of the effect that a loss or malfunction of the PLANT VENTILATION SYSTEMS will have on following: Auxiliary building temperature: Plant-Specific.
(CFR: 41.5 / 45.3) 2.5 65 290001 (SF5 SC) Secondary Containment 290003 (SF9 CRV) Control Room Ventilation 290002 (SF4 RVI) Reactor Vessel Internals 51001 (SF8 CWS*) Circulating Water K/A Category Point Totals:
1 1
2 1
1 1
1 1
1 1
1 Group Point Total:
12
ES-401 12 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 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 295001 (APE 1) Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 295003 (APE 3) Partial or Complete Loss of AC Power / 6 295004 (APE 4) Partial or Total Loss of DC Power / 6 2.4.41 Generic K/A 2.4.41 - Knowledge of the emergency action level thresholds and classifications.
(CFR: 41.10 / 43.5 / 45.11) 4.6 76 295005 (APE 5) Main Turbine Generator Trip /
3 03 AA2.03 - Ability to determine and/or interpret the following as they apply to MAIN TURBINE GENERATOR TRIP:
Turbine valve position.
(CFR: 41.10 / 43.5 / 45.13) 3.1 77 295006 (APE 6) Scram / 1 295016 (APE 16) Control Room Abandonment
/ 7 295018 (APE 18) Partial or Complete Loss of CCW / 8 2.2.44 Generic K/A 2.2.44 - Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.
(CFR: 41.5 / 43.5 / 45.12) 4.4 78 295019 (APE 19) Partial or Complete Loss of Instrument Air / 8 295021 (APE 21) Loss of Shutdown Cooling /
4 295023 (APE 23) Refueling Accidents / 8 295024 High Drywell Pressure / 5 02 EA2.02 - Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE: Drywell temperature.
(CFR: 41.10 / 43.5 / 45.13) 4.0 79 295025 (EPE 2) High Reactor Pressure / 3 2.2.40 Generic K/A 2.2.40 - Ability to apply Technical Specifications for a system.
(CFR: 41.10 / 43.2 / 43.5 / 45.3) 4.7 80 295026 (EPE 3) Suppression Pool High Water Temperature / 5 01 EA2.01 - Ability to determine and/or interpret the following as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: Suppression pool water temperature.
(CFR: 41.10 / 43.5 / 45.13) 4.2 81 295027 (EPE 4) High Containment Temperature (Mark III Containment Only) / 5 295028 (EPE 5) High Drywell Temperature (Mark I and Mark II only) / 5 295030 (EPE 7) Low Suppression Pool Water Level / 5 295031 (EPE 8) Reactor Low Water Level / 2 295037 (EPE 14) Scram Condition Present and Reactor Power Above APRM Downscale or Unknown / 1
ES-401 13 Form ES-401-1 295038 (EPE 15) High Offsite Radioactivity Release Rate / 9 600000 (APE 24) Plant Fire On Site / 8 700000 (APE 25) Generator Voltage and Electric Grid Disturbances / 6 2.1.20 Ability to interpret and execute procedure steps.
(CFR: 41.10 / 43.5 / 45.12) 4.6 82 K/A Category Totals:
0 0
0 0
3 4
Group Point Total:
7
ES-401 14 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 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 295002 (APE 2) Loss of Main Condenser Vacuum / 3 02 AA2.02 - Ability to determine and/or interpret the following as they apply to LOSS OF MAIN CONDENSER VACUUM: Reactor power: Plant-Specific.
(CFR: 41.10 / 43.5 / 45.13) 3.3 83 295007 (APE 7) High Reactor Pressure / 3 295008 (APE 8) High Reactor Water Level / 2 295009 (APE 9) Low Reactor Water Level / 2 295010 (APE 10) High Drywell Pressure / 5 295011 (APE 11) High Containment Temperature (Mark III Containment only) / 5 295012 (APE 12) High Drywell Temperature /
5 295013 (APE 13) High Suppression Pool Temperature. / 5 295014 (APE 14) Inadvertent Reactivity Addition / 1 295015 (APE 15) Incomplete Scram / 1 295017 (APE 17) Abnormal Offsite Release Rate / 9 295020 (APE 20) Inadvertent Containment Isolation / 5 & 7 295022 (APE 22) Loss of Control Rod Drive Pumps / 1 2.1.25 Generic K/A 2.1.25 - Ability to interpret reference materials, such as graphs, curves, tables, etc.
(CFR: 41.10 / 43.5 / 45.12) 4.2 84 295029 (EPE 6) High Suppression Pool Water Level / 5 295032 (EPE 9) High Secondary Containment Area Temperature / 5 02 EA2.02 - Ability to determine and/or interpret the following as they apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE: Equipment operability.
(CFR: 41.10 / 43.5 / 45.13) 3.5 85 295033 (EPE 10) High Secondary Containment Area Radiation Levels / 9 295034 (EPE 11) Secondary Containment Ventilation High Radiation / 9 295035 (EPE 12) Secondary Containment High Differential Pressure / 5 295036 (EPE 13) Secondary Containment High Sump/Area Water Level / 5 500000 (EPE 16) High Containment Hydrogen Concentration / 5
ES-401 15 Form ES-401-1 K/A Category Point Totals:
0 0
0 0
2 1
Group Point Total:
3
ES-401 16 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant SystemsTier 2/Group 1 (SRO)
System # / Name K
1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR 203000 (SF2, SF4 RHR/LPCI)
RHR/LPCI: Injection Mode 2.4.20 Generic K/A 2.4.20 - Knowledge of the operational implications of EOP warnings, cautions, and notes.
(CFR: 41.10 / 43.5 / 45.13) 4.3 86 205000 (SF4 SCS) Shutdown Cooling 206000 (SF2, SF4 HPCIS)
High-Pressure Coolant Injection 207000 (SF4 IC) Isolation (Emergency) Condenser 209001 (SF2, SF4 LPCS)
Low-Pressure Core Spray 209002 (SF2, SF4 HPCS)
High-Pressure Core Spray 05 A2.05 - Ability to (a) predict the impacts of the following on the HIGH PRESSURE CORE SPRAY SYSTEM (HPCS); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: D.C. electrical failure: BWR-5,6.
(CFR: 41.5 / 45.6) 2.9 87 211000 (SF1 SLCS) Standby Liquid Control 2.4.6 Generic K/A 2.4.6 - Knowledge of EOP mitigation strategies.
(CFR: 41.10 / 43.5 / 45.13) 4.7 88 212000 (SF7 RPS) Reactor Protection 215003 (SF7 IRM)
Intermediate-Range Monitor 215004 (SF7 SRMS) Source-Range Monitor 215005 (SF7 PRMS) Average Power Range Monitor/Local Power Range Monitor 217000 (SF2, SF4 RCIC) Reactor Core Isolation Cooling 12 A2.12 - Ability to (a) predict the impacts of the following on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC);
and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Valve openings.
(CFR: 41.5 / 45.6) 3.0 89 218000 (SF3 ADS) Automatic Depressurization 223002 (SF5 PCIS) Primary Containment Isolation/Nuclear Steam Supply Shutoff 239002 (SF3 SRV) Safety Relief Valves 259002 (SF2 RWLCS) Reactor Water Level Control 261000 (SF9 SGTS) Standby Gas Treatment 262001 (SF6 AC) AC Electrical Distribution
ES-401 17 Form ES-401-1 262002 (SF6 UPS) Uninterruptable Power Supply (AC/DC) 263000 (SF6 DC) DC Electrical Distribution 264000 (SF6 EGE) Emergency Generators (Diesel/Jet) EDG 2.2.42 Generic K/A 2.2.42 - Ability to recognize system parameters that are entry-level conditions for Technical Specifications.
(CFR: 41.7 / 41.10 / 43.2 / 43.3 / 45.3) 4.6 90 300000 (SF8 IA) Instrument Air 400000 (SF8 CCS) Component Cooling Water 510000 (SF4 SWS*) Service Water (Normal and Emergency)
K/A Category Point Totals:
0 0 0
0 0
0 0
2 0
0 3
Group Point Total:
5
ES-401 18 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant SystemsTier 2/Group 2 (SRO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR 201001 (SF1 CRDH) CRD Hydraulic 06 A2.06 - Ability to (a) predict the impacts of the following on the CONTROL ROD DRIVE HYDRAULIC SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Suction strainer(s) becoming plugged.
(CFR: 41.5 / 45.6) 2.9 91 201002 (SF1 RMCS) Reactor Manual Control 201003 (SF1 CRDM) Control Rod and Drive Mechanism 201004 (SF7 RSCS) Rod Sequence Control 201005 (SF1, SF7 RCIS) Rod Control and Information 201006 (SF7 RWMS) Rod Worth Minimizer 202001 (SF1, SF4 RS) Recirculation 2.4.30 Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.
(CFR: 41.10 / 43.5 / 45.11) 4.1 92 202002 (SF1 RSCTL) Recirculation Flow Control 204000 (SF2 RWCU) Reactor Water Cleanup 214000 (SF7 RPIS) Rod Position Information 215001 (SF7 TIP) Traversing In-Core Probe 215002 (SF7 RBMS) Rod Block Monitor 216000 (SF7 NBI) Nuclear Boiler Instrumentation 219000 (SF5 RHR SPC) RHR/LPCI:
Torus/Suppression Pool Cooling Mode 223001 (SF5 PCS) Primary Containment and Auxiliaries 226001 (SF5 RHR CSS) RHR/LPCI:
Containment Spray Mode 230000 (SF5 RHR SPS) RHR/LPCI:
Torus/Suppression Pool Spray Mode 233000 (SF9 FPCCU) Fuel Pool Cooling/Cleanup 234000 (SF8 FH) Fuel-Handling Equipment 07 K1.07 - Knowledge of the physical connections and/or cause-effect relationships between FUEL HANDLING EQUIPMENT and the following:
Fuel transfer tube system: Mark-III.
(CFR: 41.2 to 41.9 / 45.7 to 45.8) 3.4 93 239001 (SF3, SF4 MRSS) Main and Reheat Steam
ES-401 19 Form ES-401-1 239003 (SF9 MSVLCS) Main Steam Isolation Valve Leakage Control 241000 (SF3 RTPRS) Reactor/Turbine Pressure Regulating 245000 (SF4 MTGEN) Main Turbine Generator/Auxiliary 256000 (SF2 CDS) Condensate 259001 (SF2 FWS) Feedwater 268000 (SF9 RW) Radwaste 271000 (SF9 OG) Offgas 272000 (SF7, SF9 RMS) Radiation Monitoring 286000 (SF8 FPS) Fire Protection 288000 (SF9 PVS) Plant Ventilation 290001 (SF5 SC) Secondary Containment 290003 (SF9 CRV) Control Room Ventilation 290002 (SF4 RVI) Reactor Vessel Internals 51001 (SF8 CWS*) Circulating Water K/A Category Point Totals:
1 0
0 0
0 0
0 1
0 0
1 Group Point Total:
3
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facility: Perry Nuclear Power Plant Date of Exam: February 11-22, 2019 Category K/A #
Topic RO SRO-only IR IR
- 1. Conduct of Operations 2.1.32 Ability to explain and apply system limits and precautions.
(CFR: 41.10 / 43.2 / 45.12) 3.8 66 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc.
(CFR: 41.10 / 43.2) 3.3 67 2.1.39 Knowledge of conservative decision making practices.
(CFR: 41.10 / 43.5 / 45.12) 3.6 68 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation.
(CFR: 41.10 / 43.5 / 45.2 / 45.6) 4.4 94 2.1.43 Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.
(CFR: 41.10 / 43.6 / 45.6) 4.3 95 Subtotal 3
2
- 2. Equipment Control 2.2.43 Knowledge of the process used to track inoperable alarms.
(CFR: 41.10 / 43.5 / 45.13) 3.0 69 2.2.12 Knowledge of surveillance procedures.
(CFR 41.10 / 45.13) 3.7 70 2.2.38 Knowledge of conditions and limitations in the facility license.
(CFR: 41.7 / 41.10 / 43.1 / 45.13) 3.6 71 2.2.25 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.
(CFR: 41.5 / 41.7 / 43.2) 4.2 96 2.2.14 Knowledge of the process for controlling equipment configuration or status.
(CFR: 41.10 / 43.3 / 45.13) 4.3 97 Subtotal 3
2
- 3. Radiation Control 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions.
(CFR: 41.12 / 45.10) 3.5 72 2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.
(CFR: 41.12 / 43.4 / 45.9) 2.9 73 2.3.11 Ability to control radiation releases.
(CFR: 41.11 / 43.4 / 45.10) 4.3 98 Subtotal 2
1
- 4. Emergency Procedures/Plan 2.4.12 Knowledge of general operating crew responsibilities during emergency operations.
(CFR: 41.10 / 45.12) 4.0 74 2.4.26 Knowledge of facility protection requirements, including fire brigade and portable fire fighting equipment usage.
(CFR: 41.10 / 43.5 / 45.12) 3.1 75 2.4.32 Knowledge of operator response to loss of all annunciators.
(CFR: 41.10 / 43.5 / 45.13) 4.0 99 2.4.11 Knowledge of abnormal condition procedures.
(CFR: 41.10 / 43.5 / 45.13) 4.2 100
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Subtotal 2
2 Tier 3 Point Total 10 7