ML22144A393
| ML22144A393 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 05/13/2019 |
| From: | Randy Baker NRC/RGN-III/DRS/OLB |
| To: | |
| Baker R | |
| Shared Package | |
| ML19220A200 | List: |
| References | |
| Download: ML22144A393 (10) | |
Text
ES-401 1 Form ES-401-1 Facility: Perry Nuclear Power Plant Date of Exam: September 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. 1 4 3 4 3 3 3 20 Emergency and N/A N/A 2 1 1 1 1 2 1 7 Abnormal Plant Evolutions Tier Totals 5 4 5 4 5 4 27 1 2 2 2 3 2 3 2 2 2 3 3 26 2.
Plant 2 1 1 1 2 1 1 1 1 1 1 1 12 Systems Tier Totals 3 3 3 5 3 4 3 3 3 4 4 38
- 3. Generic Knowledge and Abilities 1 2 3 4 Categories 3 3 2 2 10 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 #
AK2.03 - Knowledge of the interrelations 295001 (APE 1) Partial or Complete Loss of 03 between PARTIAL OR COMPLETE LOSS 3.6 1 Forced Core Flow Circulation / 1 & 4 OF FORCED CORE FLOW CIRCULATION (11) and the following: Reactor water level.
(CFR: 41.7 / 45.8)
AK3.03 - Knowledge of the reasons for the 295003 (APE 3) Partial or Complete Loss of 03 following responses as they apply to 3.5 2 AC Power / 6 PARTIAL OR COMPLETE LOSS OF A.C. (12)
POWER: Load shedding.
(CFR: 41.5 / 45.6)
AA2.01 - Ability to determine and/or interpret 295004 (APE 4) Partial or Total Loss of DC 01 the following as they apply to PARTIAL OR 3.2 3 Power / 6 COMPLETE LOSS OF D.C. POWER: Cause (13) of partial or complete loss of D.C. power.
(CFR: 41.10 / 43.5 / 45.13)
AK1.01 - Knowledge of the operational 295005 (APE 5) Main Turbine Generator Trip / 01 implications of the following concepts as they 4.0 4 3 apply to MAIN TURBINE GENERATOR (14)
TRIP: Pressure effects on reactor power.
(CFR: 41.8 to 41.10)
AK1.02 - Knowledge of the operational 295006. (APE 6) Scram / 1 02 implications of the following concepts as they 3.4 5 apply to SCRAM: Shutdown margin. (15)
(CFR: 41.8 to 41.10)
AK3.03 - Knowledge of the reasons for the 295016 (APE 16) Control Room Abandonment 03 following responses as they apply to 3.5 6
/7 CONTROL ROOM ABANDONMENT: (16)
Disabling control room controls.
(CFR: 41.5 / 45.6)
Generic K/A 2.2.37 - Ability to determine 295018 (APE 18) Partial or Complete Loss of 2.2.37 operability and/or availability of safety related 3.6 7 CCW / 8 equipment. (17)
(CFR: 41.7 / 43.5 / 45.12)
AK3.02 - Knowledge of the reasons for the 295019 (APE 19) Partial or Complete Loss of 02 following responses as they apply to 3.5 8 Instrument Air / 8 PARTIAL OR COMPLETE LOSS OF (18)
INSTRUMENT AIR: Standby air compressor operation.
(CFR: 41.5 / 45.6)
AA2.04 - Ability to determine and/or interpret 295021 (APE 21) Loss of Shutdown Cooling / 04 the following as they apply to LOSS OF 3.6 9 4 SHUTDOWN COOLING: Reactor water (19) temperature.
(CFR: 41.10 / 43.5 / 45.13)
Generic K/A 2.4.6 - Knowledge of EOP 295023 (APE 23) Refueling Accidents / 8 2.4.6 mitigation strategies. 3.7 10 (CFR: 41.10 / 43.5 / 45.13) (20)
EK3.08 - Knowledge of the reasons for the 295024 High Drywell Pressure / 5 08 following responses as they apply to HIGH 3.7 11 DRYWELL PRESSURE: Containment spray: (21)
Plant-Specific.
(CFR: 41.5 / 45.6)
EA1.03 - Ability to operate and/or monitor the 295025 (EPE 2) High Reactor Pressure / 3 03 following as they apply to HIGH REACTOR 4.4 12 PRESSURE: Safety/relief valves: Plant- (22)
Specific.
(CFR: 41.7 / 45.6)
EK2.01 - Knowledge of the interrelations 295026 (EPE 3) Suppression Pool High Water 01 between SUPPRESSION POOL HIGH 3.9 13 Temperature / 5 WATER TEMPERATURE and the following: (23)
Suppression pool cooling.
(CFR: 41.7 / 45.8)
ES-401 3 Form ES-401-1 EK2.02 - Knowledge of the interrelations 295027 (EPE 4) High Containment 02 between HIGH CONTAINMENT 3.2 14 Temperature (Mark III Containment Only) / 5 TEMPERATURE (MARK III CONTAINMENT (24)
ONLY) and the following: Components internal to the containment: Mark-III.
(CFR: 41.7 / 45.8) 295028 (EPE 5) High Drywell Temperature (Mark I and Mark II only) / 5 EA1.04 - Ability to operate and/or monitor the 295030 (EPE 7) Low Suppression Pool Water 04 following as they apply to LOW 4.0 15 Level / 5 SUPPRESSION POOL WATER LEVEL: (25)
Suppression pool make-up system: Mark-III.
(CFR: 41.7 / 45.6)
EK1.02 - Knowledge of the operational 295031 (EPE 8) Reactor Low Water Level / 2 02 implications of the following concepts as they 3.8 16 apply to REACTOR LOW WATER LEVEL: (26)
Natural circulation: Plant-Specific.
(CFR: 41.8 to 41.10)
EA2.06 - Ability to determine and/or interpret 295037 (EPE 14) Scram Condition Present 06 the following as they apply to SCRAM 4.0 17 and Reactor Power Above APRM Downscale CONDITION PRESENT AND REACTOR (27) or Unknown / 1 POWER ABOVE APRM DOWNSCALE OR UNKNOWN: Reactor pressure.
(CFR: 41.10 / 43.5 / 45.13)
Generic K/A 2.1.20 - Ability to interpret and 295038 (EPE 15) High Offsite Radioactivity 2.1.20 execute procedure steps. 4.6 18 Release Rate / 9 (CFR: 41.10 / 43.5 / 45.12)) (28)
AA1.05 - Ability to operate and/or monitor the 600000 (APE 24) Plant Fire On Site / 8 05 following as they apply to PLANT FIRE ON 3.0 19 SITE: Plant and control room ventilation (29) systems.
AK1.03 - Knowledge of the operational 700000 (APE 25) Generator Voltage and 03 implications of the following concepts as they 3.3 20 Electric Grid Disturbances / 6 apply to GENERATOR VOLTAGE AND (30)
GRID DISTURBANCES: Under-excitation.
(CFR: 41.4, 41.5, 41.7, 41.10 / 45.8)
K/A Category Totals: 4 3 4 3 3 3 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 #
AK3.09 - Knowledge of the reasons for 295002 (APE 2) Loss of Main Condenser 09 the following responses as they apply to 3.2 21 Vacuum / 3 LOSS OF MAIN CONDENSER (31)
VACUUM: Reactor power reduction.
(CFR: 41.5 / 45.6) 295007 (APE 7) High Reactor Pressure / 3 AA2.04 - Ability to determine and/or 295008 (APE 8) High Reactor Water Level / 2 04 interpret the following as they apply to 3.1 22 HIGH REACTOR WATER LEVEL: (32)
Heatup rate: Plant-Specific.
(CFR: 41.10 / 43.5 / 45.13) 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 AK1.06 - Knowledge of the operational 295014 (APE 14) Inadvertent Reactivity 06 implications of the following concepts as 3.8 23 Addition / 1 they apply to INADVERTENT (33)
REACTIVITY ADDITION: Abnormal reactivity additions.
(CFR: 41.8 to 41.10) 295015 (APE 15) Incomplete Scram / 1 295017 (APE 17) Abnormal Offsite Release Rate / 9 AA1.01 - Ability to operate and/or monitor 295020 (APE 20) Inadvertent Containment 01 the following as they apply to 3.6 24 Isolation / 5 & 7 INADVERTENT CONTAINMENT (34)
ISOLATION: PCIS/NSSSS.
(CFR: 41.7 / 45.6) 295022 (APE 22) Loss of Control Rod Drive Pumps / 1 EK2.03 - Knowledge of the interrelations 295029 (EPE 6) High Suppression Pool Water 03 between HIGH SUPPRESSION POOL 3.3 25 Level / 5 WATER LEVEL and the following: HPCS: (35)
Plant-Specific.
(CFR: 41.7 / 45.8) 295032 (EPE 9) High Secondary Containment Area Temperature / 5 EA2.03 - Ability to determine and/or 295033 (EPE 10) High Secondary 03 interpret the following as they apply to 3.7 26 Containment Area Radiation Levels / 9 HIGH SECONDARY CONTAINMENT (36)
AREA RADIATION LEVELS: Cause of high area radiation.
(CFR: 41.10 / 43.5 / 45.13) 295034 (EPE 11) Secondary Containment Ventilation High Radiation / 9 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 Generic K/A 2.1.32 - Ability to explain 500000 (EPE 16) High Containment Hydrogen 2.1.32 and apply system limits and precautions. 3.8 27 Concentration / 5 (CFR: 41.10 / 43.2 / 45.12) (37)
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) 04 A1.04 - Ability to predict and/or monitor 3.6 28 RHR/LPCI: Injection Mode changes in parameters associated with (38) operating the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) controls including: System pressure.
(CFR: 41.5 / 45.5) 205000 (SF4 SCS) Shutdown Cooling 03 K5.03 - Knowledge of the operational 2.8 29 implications of the following concepts as (39) they apply to SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE): Heat removal mechanisms.
(CFR: 41.5 / 45.3) 05 A4.05 - Ability to manually operate and/or 3.2 30 monitor in the control room: Minimum flow (40) valves.
(CFR: 41.7 / 45.5 to 45.8) 206000 (SF2, SF4 HPCIS)
High-Pressure Coolant Injection 207000 (SF4 IC) Isolation (Emergency) Condenser 209001 (SF2, SF4 LPCS) 03 A4.03 - Ability to manually operate and/or 3.7 31 Low-Pressure Core Spray monitor in the control room: Injection (41) valves.
(CFR: 41.7 / 45.5 to 45.8) 209002 (SF2, SF4 HPCS) 04 K1.04 - Knowledge of the physical 3.8 32 High-Pressure Core Spray connections and/or cause effect (42) relationships between HIGH PRESSURE CORE SPRAY SYSTEM (HPCS) and the following: HPCS diesel generator.
(CFR: 41.2 to 41.9 / 45.7 to 45.8) 03 K2.03 - Knowledge of electrical power 2.8 33 supplies to the following: Initiation logic. (43)
(CFR: 41.7) 211000 (SF1 SLCS) Standby Liquid 02 K2.02 - Knowledge of electrical power 3.1 34 Control supplies to the following: Explosive (44) valves.
(CFR: 41.7) 212000 (SF7 RPS) Reactor Protection 15 A2.15 - Ability to (a) predict the impacts of 3.7 35 the following on the REACTOR (45)
PROTECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Load rejection.
(CFR: 41.5 / 45.6) 215003 (SF7 IRM) 04 K4.04 - Knowledge of INTERMEDIATE 2.9 36 Intermediate-Range Monitor RANGE MONITOR (IRM) SYSTEM (46) design feature(s) and/or interlocks which provide for the following: Varying system sensitivity levels using range switches.
(CFR: 41.7) 215004 (SF7 SRMS) Source-Range 04 A1.04 - Ability to predict and/or monitor 3.5 37 Monitor changes in parameters associated with (47) operating the SOURCE RANGE MONITOR (SRM) SYSTEM controls including: Control rod block status.
(CFR: 41.5 / 45.5)
ES-401 7 Form ES-401-1 215005 (SF7 PRMS) Average Power 07 A2.07 - Ability to (a) predict the impacts of 3.2 38 Range Monitor/Local Power Range the following on the AVERAGE POWER (48)
RANGE MONITOR/LOCAL POWER Monitor RANGE MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Recirculation flow channels flow mismatch.
(CFR: 41.5 / 45.6) 217000 (SF2, SF4 RCIC) Reactor 2.2.12 Generic K/A 2.2.12 - Knowledge of 3.7 39 Core Isolation Cooling surveillance procedures. (49)
(CFR: 41.10 / 45.13) 218000 (SF3 ADS) Automatic 05 A4.05 - Ability to manually operate and/or 4.2 40 Depressurization monitor in the control room: ADS timer (50) reset.
(CFR: 41.7 / 45.5 to 45.8)
K5.01 Knowledge of the operational 3.8 48 01 implications of the following concepts as (58) they apply to AUTOMATIC DEPRESSURIZATION SYSTEM: ADS logic operation 223002 (SF5 PCIS) Primary 08 K4.08 - Knowledge of PRIMARY 3.3 41 Containment Isolation/Nuclear Steam CONTAINMENT ISOLATION (51)
SYSTEM/NUCLEAR STEAM SUPPLY Supply Shutoff SHUT-OFF design feature(s) and/or interlocks which provide for the Following: Manual defeating of selected isolations during specified emergency conditions.
(CFR: 41.7)
K6.04 - Knowledge of the effect that a 3.3 42 04 loss or malfunction of the following will (52) have on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF: Nuclear boiler instrumentation.
(CFR: 41.7 / 45.7) 239002 (SF3 SRV) Safety Relief 03 A3.03 - Ability to monitor automatic 3.6 43 Valves operations of the RELIEF/SAFETY (53)
VALVES including: Tail pipe temperatures.
(CFR: 41.7 / 45.7) 259002 (SF2 RWLCS) Reactor Water 02 K3.02 - Knowledge of the effect that a 3.7 44 Level Control loss or malfunction of the REACTOR (54)
WATER LEVEL CONTROL SYSTEM will have on following: Reactor feedwater system.
(CFR: 41.7 / 45.4) 261000 (SF9 SGTS) Standby Gas 01 K6.01 - Knowledge of the effect that a 2.9 45 Treatment loss or malfunction of the following will (55) have on the STANDBY GAS TREATMENT SYSTEM: A.C. electrical distribution.
(CFR: 41.7 / 45.7) 262001 (SF6 AC) AC Electrical 03 K1.03 - Knowledge of the physical 3.4 46 Distribution connections and/or cause-effect (56) relationships between A.C. ELECTRICAL DISTRIBUTION and the following: Off-site power sources.
(CFR: 41.2 to 41.9 / 45.7 to 45.8)
ES-401 8 Form ES-401-1 262002 (SF6 UPS) Uninterruptable 14 K3.14 - Knowledge of the effect that a 2.8 47 Power Supply (AC/DC) loss or malfunction of the (57)
UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) will have on following: Rx power: Plant-Specific.
(CFR: 41.7 / 45.4) 263000 (SF6 DC) DC Electrical 2.4.31 Generic K/A 2.4.31 - Knowledge of 4.2 49 Distribution annunciator alarms, indications, or (59) response procedures.
(CFR: 41.10 / 45.3) 264000 (SF6 EGE) Emergency 01 K6.01 - Knowledge of the effect that a 3.8 50 Generators (Diesel/Jet) EDG loss or malfunction of the following will (60) have on the EMERGENCY GENERATORS (DIESEL/JET): Starting air.
(CFR: 41.7 / 45.7) 4.2 51 2.4.50 Generic K/A 2.4.50 - Ability to verify (61) alarm setpoints and operate controls identified in the alarm response manual.
(CFR: 41.10 / 43.5 / 45.3) 300000 (SF8 IA) Instrument Air 02 K4.02 - Knowledge of (INSTRUMENT AIR 3.0 52 SYSTEM) design feature(s) and or (62) interlocks which provide for the following:
Cross-over to other air systems.
(CFR: 41.7) 400000 (SF8 CCS) Component 01 A3.01 - Ability to monitor automatic 3.0 53 Cooling Water operations of the CCWS including: (63)
Setpoints on instrument signal levels for normal operations, warnings, and trips that are applicable to the CCWS.
(CFR: 41.7 / 45.7) 510000 (SF4 SWS*) Service Water (Normal and Emergency)
K/A Category Point Totals: 2 2 2 3 2 3 2 2 2 3 3 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 201002 (SF1 RMCS) Reactor Manual Control 201003 (SF1 CRDM) Control Rod and Drive 02 K4.02 Knowledge of CONTROL 3.8 55 Mechanism ROD AND DRIVE MECHANISM (65) design feature(s) and/or interlocks which provide for the following:
Detection of an uncoupled rod 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 A2.08 - Ability to (a) predict the 08 impacts of the following on the 3.1 54 RECIRCULATION SYSTEM; and (64)
(b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Recirculation flow mismatch: Plant-Specific.
(CFR: 41.5 / 45.6) 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 K6.01 - Knowledge of the effect 01 that a loss or malfunction of the 3.1 56 Instrumentation (66) following will have on the NUCLEAR BOILER INSTRUMENTATION: A.C.
electrical distribution.
(CFR: 41.7 / 45.7) 219000 (SF5 RHR SPC) RHR/LPCI:
Torus/Suppression Pool Cooling Mode 223001 (SF5 PCS) Primary Containment and A4.01 - Ability to manually operate 01 and/or monitor in the control room: 3.5 57 Auxiliaries (67)
Containment relief valves: Mark-III.
(CFR: 41.7 / 45.5 to 45.8) 226001 (SF5 RHR CSS) RHR/LPCI: K4.02 - Knowledge of RHR/LPCI:
02 CONTAINMENT SPRAY SYSTEM 2.8 58 Containment Spray Mode (68)
MODE design feature(s) and/or interlocks which provide for the following: Redundancy.
(CFR: 41.7) 230000 (SF5 RHR SPS) RHR/LPCI:
Torus/Suppression Pool Spray Mode 233000 (SF9 FPCCU) Fuel Pool Cooling/Cleanup
ES-401 10 Form ES-401-1 234000 (SF8 FH) Fuel-Handling Equipment K1.07 - Knowledge of the physical 07 connections and/or cause-effect 3.0 59 relationships between FUEL (69)
HANDLING EQUIPMENT and the following: Fuel transfer tube system: Mark-III.
(CFR: 41.2 to 41.9 / 45.7 to 45.8) 239001 (SF3, SF4 MRSS) Main and Reheat K2.01 - Knowledge of electrical 01 power supplies to the following: 3.2 60 Steam (70)
Main steam isolation valve solenoids.
(CFR: 41.7) 239003 (SF9 MSVLCS) Main Steam Isolation Valve Leakage Control 241000 (SF3 RTPRS) Reactor/Turbine A1.15 - Ability to predict and/or 15 monitor changes in parameters 3.1 61 Pressure Regulating (71) associated with operating the REACTOR/TURBINE PRESSURE REGULATING SYSTEM controls including: Maximum combined flow limit.
(CFR: 41.5 / 45.5) 245000 (SF4 MTGEN) Main Turbine Generator/Auxiliary 256000 (SF2 CDS) Condensate A3.06 - Ability to monitor automatic 06 operations of the REACTOR 3.0 62 CONDENSATE SYSTEM including: (72)
Hotwell level.
(CFR: 41.7 / 45.7) 259001 (SF2 FWS) Feedwater 268000 (SF9 RW) Radwaste 271000 (SF9 OG) Offgas 2.1.28 Generic K/A 2.1.28 - Knowledge of 4.1 63 the purpose and function of major system components and controls. (73)
(CFR: 41.7) 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 K3.01 - Knowledge of the effect 01 that a loss or malfunction of the 3.5 64 CONTROL ROOM HVAC will have (74) on following: Control room habitability.
(CFR: 41.7 / 45.6) 290002 (SF4 RVI) Reactor Vessel Internals K5.05 - Knowledge of the 05 operational implications of the 3.1 65 following concepts as they apply to (75)
REACTOR VESSEL INTERNALS:
Brittle fracture.
(CFR: 41.5 / 45.3) 51001 (SF8 CWS*) Circulating Water K/A Category Point Totals: 1 1 1 2 1 1 1 1 1 1 1 Group Point Total: 12