ML22153A527
| ML22153A527 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 01/28/2022 |
| From: | Bruce Bartlett NRC/RGN-III/DRS/OLB |
| To: | AmerGen Energy Co |
| Bartlett B | |
| Shared Package | |
| ML20136A320 | List: |
| References | |
| Download: ML22153A527 (17) | |
Text
0Facility: Clinton Date of Exam: January 17, 2022 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
3 4
3 N/A 4
3 N/A 3
20 4
3 7
2 1
1 1
2 1
1 7
2 1
3 Tier Totals 4
5 4
6 4
4 27 6
4 10
- 2.
Plant Systems 1
2 2
3 2
1 2
3 3
3 3
2 26 2
3 5
2 2
1 1
1 1
1 1
1 1
1 1
12 0
2 1
3 Tier Totals 4
3 4
3 2
3 4
4 4
4 3
38 4
4 8
- 3. Generic Knowledge and Abilities Categories 1
2 3
4 10 1
2 3
4 7
2 3
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. 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 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 X
(295001AK3.02) Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION (CFR: 41.5 / 45.6): Reactor power response 3.7 1
295003 (APE 3) Partial or Complete Loss of AC Power / 6 X
(295003 G2.4.3) Emergency Procedures /
Plan: 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 X
(295004AK2.01) Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF D.C. POWER and the following (CFR: 41.7 / 45.8): Battery charger 3.1 3
295005 (APE 5) Main Turbine Generator Trip /
3 X
(295005AK1.01) Knowledge of the operational implications of the following concepts as they apply to MAIN TURBINE GENERATOR TRIP (CFR: 41.8 to 41.10):
Pressure effects on reactor power 4
4 295006 (APE 6) Scram / 1 X
(295006AK2.05) Knowledge of the interrelations between SCRAM and the following (CFR: 41.7 / 45.8): CRD mechanism 3.1 5
295016 (APE 16) Control Room Abandonment
/ 7 X
(295016AA2.03) Ability to determine and/or interpret the following as they apply to CONTROL ROOM ABANDONMENT (CFR:
41.10 / 43.5 / 45.13): Reactor Pressure 4.3 6
295018 (APE 18) Partial or Complete Loss of CCW / 8 X
(295018AA1.01) Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER (CFR:
41.7 / 45.6): Backup systems 3.3 7
295019 (APE 19) Partial or Complete Loss of Instrument Air / 8 X
(295019AA1.03) Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR (CFR: 41.7 / 45.6):
Instrument air compressor power supplies 3
8 295021 (APE 21) Loss of Shutdown Cooling /
4 X
(295021AA2.02) Ability to determine and/or interpret the following as they apply to LOSS OF SHUTDOWN COOLING (CFR:
41.10 / 43.5 / 45.13): RHR/shutdown cooling system flow 3.4 9
295023 (APE 23) Refueling Accidents / 8 X
(295023 G2.1.20) Ability to interpret and execute procedure steps (CFR: 41.10 / 43.5
/ 45.12).
4.6 10 295024 High Drywell Pressure / 5 X
(295024EK3.09) Knowledge of the reasons for the following responses as they apply to HIGH DRYWELL PRESSURE (CFR: 41.5 /
45.6): Auxiliary Building Isolation: Plant-Specific 3.1 11 295025 (EPE 2) High Reactor Pressure / 3 X
(295025EK2.01) Knowledge of the interrelations between HIGH REACTOR PRESSURE and the following (CFR: 41.7 /
45.8): RPS 4.1 12
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 295026 (EPE 3) Suppression Pool High Water Temperature / 5 X
(295026EK3.05) Knowledge of the reasons for the following responses as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE (CFR: 41.5 / 45.6):
Reactor SCRAM 3.9 13 295027 (EPE 4) High Containment Temperature (Mark III Containment Only) / 5 X
(295027EK1.03) Knowledge of the operational implications of the following concepts as they apply to HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY) (CFR: 41.8 to 41.10): Containment integrity: Mark-III 3.8 14 295028 (EPE 5) High Drywell Temperature (Mark I and Mark II only) / 5 295030 (EPE 7) Low Suppression Pool Water Level / 5 X
(295030EA1.01) Ability to operate and/or monitor the following as they apply to LOW SUPPRESSION POOL WATER LEVEL (CFR: 41.7 / 45.6): ECCS systems (NPSH considerations): Plant-Specific 3.6 15 295031 (EPE 8) Reactor Low Water Level / 2 X
(295031EA1.04) Ability to operate and/or monitor the following as they apply to REACTOR LOW WATER LEVEL (CFR:
41.7 / 45.6): High pressure core spray:
Plant-Specific 4.3 16 295037 (EPE 14) Scram Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 X
(295037EA2.06) Ability to determine and/or interpret the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN (CFR: 41.10
/ 43.5 / 45.13): Reactor pressure 4
17 295038 (EPE 15) High Offsite Radioactivity Release Rate / 9 X
(295038EK1.02) Knowledge of the operational implications of the following concepts as they apply to HIGH OFF-SITE RELEASE RATE (CFR: 41.8 to 41.10):
Protection of the general public 4.2 18 600000 (APE 24) Plant Fire On Site / 8 X
(600000 G2.4.31) Knowledge of annunciator alarms, indications, or response procedures (CFR: 41.10 / 45.3).
4.2 19 700000 (APE 25) Generator Voltage and Electric Grid Disturbances / 6 X
(700000AK2.07) Knowledge of the interrelations between GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES and the following (CFR:
41.7 / 45.8): Turbine/generator control 3.6 20 K/A Category Totals:
3 4
3 4
3 3
Group Point Total:
20
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 X
(295007AA1.05) Ability to operate and/or monitor the following as they apply to HIGH REACTOR PRESSURE (CFR: 41.7
/ 45.6). Reactor and turbine pressure regulating system 3.7 21 295008 (APE 8) High Reactor Water Level / 2 295009 (APE 9) Low Reactor Water Level / 2 X
(295009AA1.02) Ability to operate and/or monitor the following as they apply to LOW REACTOR WATER LEVEL (CFR: 41.7 /
45.6): Reactor water level control 4
22 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 X
(295011AA2.01) Ability to determine and/or interpret the following as they apply to HIGH CONTAINMENT TEMPERATURE (Mark III Containment only) (CFR: 41.10 /
43.5 / 45.13): Containment temperature:
Mark III 3.6 23 295013 (APE 13) High Suppression Pool Temperature. / 5 295014 (APE 14) Inadvertent Reactivity Addition / 1 X
(295014AK2.02) Knowledge of the interrelations between INADVERTENT REACTIVITY ADDITION and the following (CFR: 41.7 / 45.8): Fuel thermal limits 3.7 24 295015 (APE 15) Incomplete Scram / 1 295017 (APE 17) Abnormal Offsite Release Rate / 9 295020 (APE 20) Inadvertent Containment Isolation / 5 & 7 X
(295020 G2.4.11) Knowledge of abnormal condition procedures (CFR: 41.10 / 43.5 /
45.13).
4.0 25 295022 (APE 22) Loss of Control Rod Drive Pumps / 1 X
(295022AK1.02) Knowledge of the operational implications of the following concepts as they apply to LOSS OF CRD PUMPS (CFR: 41.8 to 41.10): Reactivity control 3.6 26 295029 (EPE 6) High Suppression Pool Water Level / 5 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 295035 (EPE 12) Secondary Containment High Differential Pressure / 5
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 295036 (EPE 13) Secondary Containment High Sump/Area Water Level / 5 X
(295036EK3.02) Knowledge of the reasons for the following responses as they apply to SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL (CFR: 41.5 /
45.6): Reactor SCRAM 2.8 27 500000 (EPE 16) High Containment Hydrogen Concentration / 5 K/A Category Point Totals:
1 1
1 2
1 1
Group Point Total:
7
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 X
(203000K2.01) Knowledge of electrical power supplies to the following (CFR: 41.7): Pumps 3.5 28 X
(203000K4.08) Knowledge of RHR/LPCI:
INJECTION MODE (PLANT SPECIFIC) design feature(s) and/or interlocks which provide for the following (CFR: 41.7): Pump operability testing 3.3 29 205000 (SF4 SCS) Shutdown Cooling X
(205000A3.03) Ability to monitor automatic operations of the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) including (CFR: 41.7 / 45.7): Lights and alarms 3.5 30 206000 (SF2, SF4 HPCIS)
High-Pressure Coolant Injection 207000 (SF4 IC) Isolation (Emergency) Condenser 209001 (SF2, SF4 LPCS)
Low-Pressure Core Spray X
(209001K2.02) Knowledge of electrical power supplies to the following (CFR: 41.7): Valve power 2.5 32 209002 (SF2, SF4 HPCS)
High-Pressure Core Spray X
(209002A4.08) Ability to manually operate and/or monitor in the control room (CFR: 41.7
/ 45.5 to 45.8): Reactor water level: BWR-5/6 3.6 31 211000 (SF1 SLCS) Standby Liquid Control X
(211000A1.02) Ability to predict and/or monitor changes in parameters associated with operating the STANDBY LIQUID CONTROL SYSTEM controls including (CFR:
41.5 / 45.5): Explosive Valve indication: Plant-Specific 3.8 33 212000 (SF7 RPS) Reactor Protection X
(212000K4.05 Knowledge of REACTOR PROTECTION SYSTEM design feature(s) and/or interlocks which provide for the following (CFR: 41.7): Functional testing of the system while maintaining power operations 3.1 34 215003 (SF7 IRM)
Intermediate-Range Monitor X
(215003K3.02) Knowledge of the effect that a loss or malfunction of the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM will have on following (CFR: 41.7 / 45.4): Reactor manual control 3.6 35 215004 (SF7 SRMS) Source-Range Monitor X
(215004K5.01) Knowledge of the operational implications of the following concepts as they apply to SOURCE RANGE MONITOR (SRM)
SYSTEM (CFR: 41.5 / 45.3): Detector operation 2.6 36 215005 (SF7 PRMS) Average Power Range Monitor/Local Power Range Monitor X (215005 G2.1.23) Ability to perform specific system and integrated plant procedures during all modes of plant operation (CFR:
41.10 / 43.5 / 45.2 / 45.6).
4.3 37 217000 (SF2, SF4 RCIC) Reactor Core Isolation Cooling X
(217000A1.04) Ability to predict and/or monitor changes in parameters associated with operating the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) controls including (CFR: 41.5 / 45.5): Reactor pressure 3.6 38
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 218000 (SF3 ADS) Automatic Depressurization X
(218000A2.01) 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 (CFR: 41.5 / 45.6): Small steam line break L0CA 4.1 39 X
(218000K1.04) Knowledge of the physical connections and/or cause-effect relationships between AUTOMATIC DEPRESSURIZATION SYSTEM and the following (CFR: 41.2 to 41.9 / 45.7 to 45.8): Drywell/containment pressure: Plant-Specific 3.9 40 223002 (SF5 PCIS) Primary Containment Isolation/Nuclear Steam Supply Shutoff X
(223002A3.03) Ability to monitor automatic operations of the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF including (CFR: 41.7 /
45.7): SPDS/ERIS/CRIDS/GDS: Plant-Specific 2.5 41 X
(223002K3.05) Knowledge of the effect that a loss or malfunction of the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF will have on following (CFR: 41.7
/ 45.4): Drainage sump levels 2.7 42 239002 (SF3 SRV) Safety Relief Valves X
(239002A1.07) Ability to predict and/or monitor changes in parameters associated with operating the RELIEF/SAFETY VALVES controls including (CFR: 41.5 / 45.5): Turbine load 2.9 43 X
(239002A4.01) Ability to manually operate and/or monitor in the control room (CFR: 41.7
/ 45.5 to 45.8): SRV's 4.4 44 259002 (SF2 RWLCS) Reactor Water Level Control X
(259002K3.06) Knowledge of the effect that a loss or malfunction of the REACTOR WATER LEVEL CONTROL SYSTEM will have on following (CFR: 41.7 / 45.4): Main turbine 2.8 45 261000 (SF9 SGTS) Standby Gas Treatment X
(261000A2.11) Ability to (a) predict the impacts of the following on the STANDBY GAS TREATMENT SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations (CFR: 41.5 / 45.6): High containment pressure 3.2 46 X
(261000A3.02) Ability to monitor automatic operations of the STANDBY GAS TREATMENT SYSTEM including (CFR: 41.7
/ 45.7): Fan start 3.2 47 262001 (SF6 AC) AC Electrical Distribution X (262001 G2.4.50) Ability to verify system alarm setpoints and operate controls identified in the alarm response manual (CFR: 41.10 / 43.5 / 45.3).
4.2 48 262002 (SF6 UPS) Uninterruptable Power Supply (AC/DC)
X (262002A4.01) Ability to manually operate and/or monitor in the control room (CFR: 41.7
/ 45.5 to 45.8): Transfer from alternative source to preferred source 2.8 49
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 263000 (SF6 DC) DC Electrical Distribution X
(263000K6.01) Knowledge of the effect that a loss or malfunction of the following will have on the D.C. ELECTRICAL DISTRIBUTION (CFR: 41.7 / 45.7): A.C. electrical distribution 3.2 50 264000 (SF6 EGE) Emergency Generators (Diesel/Jet) EDG X
(264000K1.01) Knowledge of the physical connections and/or cause-effect relationships between EMERGENCY GENERATORS (DIESEL/JET) and the following (CFR: 41.2 to 41.9 / 45.7 to 45.8): A.C. electrical distribution 3.8 51 300000 (SF8 IA) Instrument Air X
(300000K6.07) Knowledge of the effect that a loss or malfunction of the following will have on the INSTRUMENT AIR SYSTEM (CFR:
41.7 / 45.7): Valves 2.5 52 400000 (SF8 CCS) Component Cooling Water X
(400000A2.02) Ability to (a) predict the impacts of the following on the CCWS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation (CFR: 41.5 / 45.6): High/Low surge tank level 2.8 53 510000 (SF4 SWS*) Service Water (Normal and Emergency)
K/A Category Point Totals:
2 2
3 2
1 2
3 3
3 3
2 Group Point Total:
26
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 X
(201001 G2.2.20) Knowledge of the process for managing troubleshooting activities (CFR:
41.10 / 43.5 / 45.13).
2.6 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 X
(201005A1.01) Ability to predict and/or monitor changes in parameters associated with operating the ROD CONTROL AND INFORMATION SYSTEM (RCIS) controls including (CFR: 41.5 / 45.5): First stage shell pressure/turbine load:BWR-6 3.2 55 201006 (SF7 RWMS) Rod Worth Minimizer 202001 (SF1, SF4 RS) Recirculation 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 X
(216000K2.01) Knowledge of electrical power supplies to the following (CFR: 41.7): Analog trip system: Plant-Specific 2.8 56 219000 (SF5 RHR SPC) RHR/LPCI:
Torus/Suppression Pool Cooling Mode X
(219000A3.01) Ability to monitor automatic operations of the RHR/LPCI: TORUS/
SUPPRESSION POOL COOLING MODE including (CFR: 41.7 / 45.7): Valve operation 3.3 57 223001 (SF5 PCS) Primary Containment and Auxiliaries 226001 (SF5 RHR CSS) RHR/LPCI:
Containment Spray Mode X
(226001K6.01) Knowledge of the effect that a loss or malfunction of the following will have on the RHR/LPCI: CONTAINMENT SPRAY SYSTEM MODE (CFR: 41.7 / 45.7): A.C.
electrical power 3
58 230000 (SF5 RHR SPS) RHR/LPCI:
Torus/Suppression Pool Spray Mode 233000 (SF9 FPCCU) Fuel Pool Cooling/Cleanup X
(233000K4.07) Knowledge of FUEL POOL COOLING AND CLEAN-UP design feature(s) and/or interlocks which provide for the following (CFR: 41.7): Supplemental heat removal capability 2.7 59 234000 (SF8 FH) Fuel-Handling Equipment 239001 (SF3, SF4 MRSS) Main and Reheat Steam X
(239001K1.22) Knowledge of the physical connections and/or cause-effect relationships between Main and Re-Heat Steam System and the following (CFR 41.2 to 41.9) Feedwater System 3.1 60 239003 (SF9 MSVLCS) Main Steam Isolation Valve Leakage Control 241000 (SF3 RTPRS) Reactor/Turbine Pressure Regulating X
(241000A4.08) Ability to manually operate and/or monitor in the control room (CFR: 41.7
/ 45.5 to 45.8): Control/governor valves (operation) 3.5 61
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 245000 (SF4 MTGEN) Main Turbine Generator/Auxiliary 256000 (SF2 CDS) Condensate X
(256000A2.09) Ability to predicts 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 (CFR: 41.7 / 45.5 to 45.8): Low feedwater heater level 2.8 62 259001 (SF2 FWS) Feedwater 268000 (SF9 RW) Radwaste 271000 (SF9 OG) Offgas 272000 (SF7, SF9 RMS) Radiation Monitoring 286000 (SF8 FPS) Fire Protection X
(286000K3.03) Knowledge of the effect that a loss or malfunction of the FIRE PROTECTION SYSTEM will have on following (CFR: 41.7 / 45.4): Plant protection 3.6 63 288000 (SF9 PVS) Plant Ventilation X
(288000K1.02) Knowledge of the physical connections and/or cause-effect relationships between plant ventilation systems and the following: (CFR: 41.2 - 41.9) Secondary containment 3.4 64 290001 (SF5 SC) Secondary Containment 290003 (SF9 CRV) Control Room Ventilation X
(290003K5.01) Knowledge of the operational implications of the following concepts as they apply to CONTROL ROOM HVAC (CFR:
41.5 / 45.3): Airborne contamination (e.g.,
radiological, toxic gas, smoke) control 3.2 65 290002 (SF4 RVI) Reactor Vessel Internals 51001 (SF8 CWS*) Circulating Water K/A Category Point Totals:
2 1
1 1
1 1
1 1
1 1
1 Group Point Total:
12
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 X
(295001AA2.04) Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION (CFR: 41.10 / 43.5 / 45.13): Individual jet pump flows: Not-BWR-1&2 3.1 76 295003 (APE 3) Partial or Complete Loss of AC Power / 6 X
(295003AA2.02) Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C.
POWER (CFR: 41.10 / 43.5 / 45.13):
Reactor power / pressure / and level 4.3 77 295004 (APE 4) Partial or Total Loss of DC Power / 6 295005 (APE 5) Main Turbine Generator Trip /
3 295006 (APE 6) Scram / 1 295016 (APE 16) Control Room Abandonment
/ 7 295018 (APE 18) Partial or Complete Loss of CCW / 8 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 295025 (EPE 2) High Reactor Pressure / 3 X
(295025EA2.01) Ability to determine and/or interpret the following as they apply to HIGH REACTOR PRESSURE (CFR: 41.10 / 43.5
/ 45.13): Reactor pressure 4.3 78 295026 (EPE 3) Suppression Pool High Water Temperature / 5 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 X
(295030 G2.1.25) Ability to interpret reference materials such as graphs, curves, tables, etc (CFR: 41.10 / 43.5).
4.2 79 295031 (EPE 8) Reactor Low Water Level / 2 295037 (EPE 14) Scram Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 X
(295037 G2.4.47) 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 80 295038 (EPE 15) High Offsite Radioactivity Release Rate / 9 X
(295038EA2.01) Ability to determine and/or interpret the following as they apply to HIGH OFF-SITE RELEASE RATE (CFR: 41.10 /
43.5 / 45.13): Off-site 4.3 81 600000 (APE 24) Plant Fire On Site / 8
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 700000 (APE 25) Generator Voltage and Electric Grid Disturbances / 6 X
(700000 G2.2.37) Ability to determine operability and/or availability of safety related equipment. (CFR: 41.7 / 43.5 /
45.12).
4.6 82 K/A Category Totals:
4 3
Group Point Total:
7
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 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 X
(295011AA2.02) Ability to determine and/or interpret the following as they apply to HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY) (CFR:
41.10 / 43.5 / 45.13): Containment pressure: Mark-III 4.0 83 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 X
(295017AA2.05) Ability to determine and/or interpret the following as they apply to HIGH OFF-SITE RELEASE RATE (CFR: 41.10 / 43.5 / 45.13): Meteorological data 3.8 84 295020 (APE 20) Inadvertent Containment Isolation / 5 & 7 295022 (APE 22) Loss of Control Rod Drive Pumps / 1 295029 (EPE 6) High Suppression Pool Water Level / 5 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 295035 (EPE 12) Secondary Containment High Differential Pressure / 5 X
(295035 G2.4.2) Knowledge of system setpoints, interlocks and automatic actions associated with EOP entry conditions.
(CFR: 41.7 / 45.7 / 45.8).
4.6 85 295036 (EPE 13) Secondary Containment High Sump/Area Water Level / 5 500000 (EPE 16) High Containment Hydrogen Concentration / 5 K/A Category Point Totals:
2 1
Group Point Total:
3
ES-401 BWR Examination Outline Form ES-401-1 Plant SystemsTier 2/Group 1 (SRO)
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 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 211000 (SF1 SLCS) Standby Liquid Control X
(211000A2.01) Ability to (a) predict the impacts of the following on the STANDBY LIQUID CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations (CFR: 41.5 / 45.6): Pump trip 3.8 86 212000 (SF7 RPS) Reactor Protection X (212000 G2.2.38) Knowledge of conditions and limitations in the facility license. (CFR:
41.7 / 41.1 / 43.1 / 45.13).
4.5 87 215003 (SF7 IRM)
Intermediate-Range Monitor 215004 (SF7 SRMS) Source-Range Monitor 215005 (SF7 PRMS) Average Power Range Monitor/Local Power Range Monitor X
(215005A2.01) Ability to (a) predict the impacts of the following on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations (CFR: 41.5 / 45.6): Power supply degraded 3.1 88 217000 (SF2, SF4 RCIC) Reactor Core Isolation Cooling X (217000 G2.2.36) Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations (CFR: 41.10 / 43.2 /
45.13).
4.2 89 218000 (SF3 ADS) Automatic Depressurization 223002 (SF5 PCIS) Primary Containment Isolation/Nuclear Steam Supply Shutoff 239002 (SF3 SRV) Safety Relief Valves 259002 (SF2) Reactor Water Level Control 261000 (SF9 SGTS) Standby Gas Treatment 262001 (SF6 AC) AC Electrical Distribution 262002 (SF6 UPS) Uninterruptable Power Supply (AC/DC)
ES-401 BWR Examination Outline Form ES-401-1 Plant SystemsTier 2/Group 1 (SRO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR 263000 (SF6 DC) DC Electrical Distribution 264000 (SF6 EGE) Emergency Generators (Diesel/Jet) EDG 300000 (SF8 IA) Instrument Air X (300000 G2.2.44) 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. Emergency and abnormal operating procedures. (CFR: 41.10
/ 43.2 / 45.6).
4.7 90 400000 (SF8 CCS) Component Cooling Water 510000 (SF4 SWS*) Service Water (Normal and Emergency)
K/A Category Point Totals:
2 3
Group Point Total:
5
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 201002 (SF1 RMCS) Reactor Manual Control 201003 (SF1 CRDM) Control Rod and Drive Mechanism X
(201003A2.10) Ability to (a) predict the impacts of the following on the CONTROL ROD AND DRIVE MECHANISM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations (CFR: 41.5 / 45.6): Excessive SCRAM time for a given drive mechanism 3.4 91 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 X
(202002 G2.4.21) Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.(CFR 41.7 / 43.5 / 45.12) 4.6 92 204000 (SF2 RWCU) Reactor Water Cleanup 214000 (SF7 RPIS) Rod Position Information X
(214000 A2.01)) Ability to (a) predict the impacts of the following on the rod position information system and (b) based on those predictions use procedures to correct, control, or mitigate the consequences of those anormal conditions or operations (CFR 41.5 /
45.6) Failed reed switches 3.6 93 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 239001 (SF3, SF4 MRSS) Main and Reheat Steam 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
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 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:
2 1
Group Point Total:
3