ML17082A629
| ML17082A629 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 11/16/2016 |
| From: | Chuck Zoia NRC/RGN-III/DRS/OLB |
| To: | Exelon Generation Co |
| Shared Package | |
| ML15274A401 | List: |
| References | |
| Download: ML17082A629 (10) | |
Text
ES-401 BWR Examination Outline FORM ES-401-1 Facility Name: LaSalle Date of Exam: 10/17/2016 NRC K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
Total Total 1
4 3
3 4
3 3
20 7
2 2
1 1
1 1
1 7
3 Tier Totals 6
4 4
5 4
4 27 10 1
2 2
1 3
2 2
3 4
3 2
2 26 5
2 1
1 2
1 1
1 1
1 1
1 1
12 0
2 3
Tier Totals 3
3 3
4 3
3 4
5 4
3 3
38 8
1 2
3 4
2 2
1 2
Note: 1.
Note: 2.
Note: 3.
Note: 4.
Note: 5.
Note: 6.
Note: 7.*
Note: 8.
Note: 9.
G*
Tier Group SRO-Only Points
- 2.
Plant Systems
- 1.
Emergency &
Abnormal Plant Evolutions 1
3 3
A2 4
2 6
3 G*
1 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.
RO K/A Category Points 7
10 Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 Radiation Control K/A is allowed if the K/A is replaced by a K/A from another Tier 3 Category).
3 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.
Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems 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.
N/A N/A 2
4 2
2
- 3. Generic Knowledge and Abilities Categories 1
5 3
2 3
Generic K/As 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.
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.
Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
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.
On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (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 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.
ES-401 2
Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)
Q#
E/APE # / Name / Safety Function K
1 K
2 K
3 A
1 A
2 G
K/A Topic(s)
IR 1
295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 0
2 Knowledge of the reasons for the following responses as they apply to Partial or Complete Loss of Forced Core Flow Circulation: Reactor power response 3.7 1
2 295003 Partial or Complete Loss of AC / 6 0
4 Knowledge of the reasons for the following responses as they apply to Partial or Complete Loss of AC: Ground isolation 3.0 1
3 295004 Partial or Total Loss of DC Pwr / 6 0
1 Ability to operate and/or monitor the following as they apply to Partial or Total Loss of DC Pwr: D.C. electrical distribution systems 3.3 1
4 295005 Main Turbine Generator Trip / 3 0
4 Ability to determine and/or interpret the following as they apply to Main Turbine Generator Trip: Reactor pressure 3.7 1
5 295006 SCRAM / 1 04.
11 Knowledge of abnormal condition procedures.
4.0 1
6 295016 Control Room Abandonment / 7 0
2 Knowledge of the interrelations between Control Room Abandonment and the following: Local control stations: Plant-Specific 4.0 1
7 295018 Partial or Total Loss of CCW / 8 0
1 Knowledge of the operational implications of the following concepts as they apply to Partial or Total Loss of CCW: Effects on component/system operations 3.5 1
13 295019 Partial or Total Loss of Inst. Air / 8 0
2 Knowledge of the interrelations between Partial or Total Loss of Inst. Air and the following: Component cooling water 2.9 1
8 295021 Loss of Shutdown Cooling / 4 0
1 Ability to operate and/or monitor the following as they apply to Loss of Shutdown Cooling: Reactor water cleanup system 3.4 1
9 295023 Refueling Acc / 8 0
2 Ability to determine and/or interpret the following as they apply to Refueling Accidents: Fuel pool level 3.4 1
10 295024 High Drywell Pressure / 5 0
1 Knowledge of the operational implications of the following concepts as they apply to High Drywell Pressure: Drywell integrity: Plant-Specific 4.1 1
11 295025 High Reactor Pressure / 3 0
4 Knowledge of the operational implications of the following concepts as they apply to High Reactor Pressure: Decay heat generation 3.6 1
12 295026 Suppression Pool High Water Temp. / 5 0
3 Ability to determine and/or interpret the following as they apply to Suppression Pool High Water Temp.: Reactor pressure 3.9 1
295027 High Containment Temperature / 5 0
14 295028 High Drywell Temperature / 5 0
2 Knowledge of the operational implications of the following concepts as they apply to High Drywell Temperature: Equipment environmental qualification 2.9 1
15 295030 Low Suppression Pool Wtr Lvl / 5 0
1 Ability to operate and/or monitor the following as they apply to Low Suppression Pool Wtr Lvl: ECCS systems (NPSH considerations): Plant-Specific 3.6 1
16 295031 Reactor Low Water Level / 2 0
1 Ability to operate and/or monitor the following as they apply to Reactor Low Water Level: Low pressure coolant injection (RHR): Plant-Specific 4.4 1
17 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 0
6 Knowledge of the reasons for the following responses as they apply to SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown:
Maintaining heat sinks external to the containment 3.8 1
18 295038 High Off-site Release Rate / 9 04.
45 Ability to prioritize and interpret the significance of each annunciator or alarm.
4.1 1
19 600000 Plant Fire On Site / 8 04.
01 Knowledge of EOP entry conditions and immediate action steps.
4.6 1
20 700000 Generator Voltage and Electric Grid Disturbances / 6 0
3 Knowledge of the interrelations between Generator Voltage and Electric Grid Disturbances and the following: Sensors, detectors, indicators 3.0 1
K/A Category Totals:
4 3
3 4
3 3
20 ES-401, Page 34 of 50 Group Point Total:
ES-401 3
Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)
Q#
E/APE # / Name / Safety Function K
1 K
2 K
3 A
1 A
2 G
K/A Topic(s)
IR 295002 Loss of Main Condenser Vac / 3 0
295007 High Reactor Pressure / 3 0
295008 High Reactor Water Level / 2 0
22 295009 Low Reactor Water Level / 2 02.
37 Ability to determine operability and/or availability of safety related equipment.
3.6 1
26 295010 High Drywell Pressure / 5 0
3 Knowledge of the operational implications of the following concepts as they apply to High Drywell Pressure: Temperature increases 3.2 1
295011 High Containment Temp / 5 0
295012 High Drywell Temperature / 5 0
295013 High Suppression Pool Temp. / 5 0
295014 Inadvertent Reactivity Addition / 1 0
295015 Incomplete SCRAM / 1 0
295017 High Off-site Release Rate / 9 0
21 295020 Inadvertent Cont. Isolation / 5 & 7 0
6 Ability to determine and/or interpret the following as they apply to Inadvertent Cont.
Isolation: Cause of isolation 3.4 1
295022 Loss of CRD Pumps / 1 0
295029 High Suppression Pool Wtr Lvl / 5 0
23 295032 High Secondary Containment Area Temperature / 5 0
5 Knowledge of the interrelations between High Secondary Containment Area Temperature and the following: Temperature sensitive instrumentation 3.2 1
295033 High Secondary Containment Area Radiation Levels / 9 0
24 295034 Secondary Containment Ventilation High Radiation / 9 0
3 Knowledge of the reasons for the following responses as they apply to Secondary Containment Ventilation High Radiation: Personnel evacuation 4.0 1
25 295035 Secondary Containment High Differential Pressure / 5 0
2 Knowledge of the operational implications of the following concepts as they apply to Secondary Containment High Differential Pressure: Radiation release 3.7 1
295036 Secondary Containment High Sump/Area Water Level / 5 0
27 500000 High CTMT Hydrogen Conc. / 5 0
4 Ability to operate and/or monitor the following as they apply to High CTMT Hydrogen Conc.: Drywell recirculating fans 2.9 1
K/A Category Totals:
2 1
1 1
1 1
7 ES-401, Page 35 of 50 Group Point Total:
ES-401 4
Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO)
Q#
System # / Name K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
K/A Topic(s)
IR 28 203000 RHR/LPCI: Injection Mode 0
2 Knowledge of electrical power supplies to the following: Valves 2.5 1
29 205000 Shutdown Cooling 0
2 Knowledge of Shutdown Cooling design feature(s) and/or interlocks which provide for the following: High pressure isolation: Plant-Specific 3.7 1
206000 HPCI 0
207000 Isolation (Emergency)
Condenser 0
32 209001 LPCS 0
1 Ability to monitor automatic operations of the LPCS including: Valve operation 3.6 1
33 209002 HPCS 0
2 Ability to (a) predict the impacts of the following on the HPCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Pump trips: BWR-5, 6
3.6 1
34 211000 SLC 0
3 Knowledge of the effect that a loss or malfunction of the following will have on the SLC: A.C. power 3.2 1
35 212000 RPS 0
3 Ability to (a) predict the impacts of the following on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Surveillance testing 3.3 1
36 215003 IRM 0
6 Knowledge of IRM design feature(s) and/or interlocks which provide for the following: Alarm seal-in 2.6 1
37/
38 215004 Source Range Monitor 0
5 01.
30 Ability to (a) predict the impacts of the following on the Source Range Monitor; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Faulty or erratic operation of detectors/system; Ability to locate and operate 3.3; 4.4 2
5 Knowledge of the effect that a loss or malfunction of the APRM / LPRM will have on following: Reactor power indication 3.8 1
40 217000 RCIC 0
8 Ability to predict and/or monitor changes in parameters associated with operating the RCIC controls including: Suppression pool temperature 3.5 1
41 218000 ADS 0
2 Knowledge of ADS design feature(s) and/or interlocks which provide for the following: Allows manual initiation of ADS logic 3.8 1
42 223002 PCIS/Nuclear Steam Supply Shutoff 0
1 Ability to manually operate and/or monitor in the control room: Valve closures 3.6 1
31/
43 239002 SRVs 0
2 0
5 Knowledge of the physical connections and/or cause-effect relationships between SRVs and the following: SPDS/ERIS/CRIDS/GDS: Plant-Specific; Ability to (a) predict the impacts of the following on the SRVs; and (b) based on those predictions use procedures to correct control or mitigate the 2.5; 3.2 2
44 259002 Reactor Water Level Control 0
7 Knowledge of the operational implications of the following concepts as they apply to Reactor Water Level Control: Turbine speed control mechanisms:
TDRFP 2.7 1
45 261000 SGTS 0
8 Knowledge of the effect that a loss or malfunction of the following will have on the SGTS: Reactor vessel level: Plant-Specific 3.1 1
46/
47 262001 AC Electrical Distribution 0
1 0
3 Knowledge of the operational implications of the following concepts as they apply to AC Electrical Distribution: Principle involved with paralleling two A.C.
sources; Ability to predict and/or monitor changes in parameters associated with operating the AC Electrical Distribution controls including: Bus voltage 3.1; 2.9 2
48 262002 UPS (AC/DC) 0 1
Ability to manually operate and/or monitor in the control room: Transfer from alternative source to preferred source 2.8 1
30/
49 263000 DC Electrical Distribution 0
1 0
1 Ability to predict and/or monitor changes in parameters associated with operating the DC Electrical Distribution controls including: Battery charging/discharging rate; Ability to monitor automatic operations of the DC Electrical Distribution including: Meters dials recorders alarms and indicating 2.5; 3.2 2
50 264000 EDGs 02.
36 Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.
3.1 1
51/
52 300000 Instrument Air 0
1 0
2 Knowledge of electrical power supplies to the following: Instrument air compressor; Ability to monitor automatic operations of the Instrument Air including: Air temperature 2.8; 2.9 2
53 400000 Component Cooling Water 0
3 Knowledge of the physical connections and/or cause-effect relationships between Component Cooling Water and the following: Radiation monitoring systems 2.7 1
K/A Category Totals:
2 2
1 3
2 2
3 4
3 2
2 26 ES-401, Page 36 of 50 Group Point Total:
ES-401-1 5
Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (RO)
Q#
System # / Name K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
K/A Topic(s)
IR 54 201001 CRD Hydraulic 0
7 Ability to predict and/or monitor changes in parameters associated with operating the CRD Hydraulic System controls including: Reactor water level 3.3 1
201002 RMCS 0
201003 Control Rod and Drive Mechanism 0
201004 RSCS 0
201005 RCIS 0
201006 RWM 0
202001 Recirculation 0
202002 Recirculation Flow Control 0
55 204000 RWCU 0
7 Knowledge of RWCU design feature(s) and/or interlocks which provide for the following: Draining of reactor water to various locations 2.9 1
56 214000 RPIS 0
1 Knowledge of the effect that a loss or malfunction of the RPIS will have on following: RWM: Plant-Specific 3.0 1
215001 Traversing In-core Probe 0
215002 RBM 0
216000 Nuclear Boiler Inst.
0 219000 RHR/LPCI: Torus/Pool Cooling Mode 0
57 223001 Primary CTMT and Aux.
1 0
Knowledge of electrical power supplies to the following: Drywell chillers: Plant-Specific 2.7 1
226001 RHR/LPCI: CTMT Spray Mode 0
230000 RHR/LPCI: Torus/Pool Spray Mode 0
58 233000 Fuel Pool Cooling/Cleanup 0
3 Ability to monitor automatic operations of the Fuel Pool Cooling/Cleanup including: System indicating lights and alarms 2.6 1
59 234000 Fuel Handling Equipment 0
3 Ability to (a) predict the impacts of the following on the Fuel Handling Equipment; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those abnormal conditions or 2.8 1
239001 Main and Reheat Steam 0
239003 MSIV Leakage Control 0
241000 Reactor/Turbine Pressure Regulator 0
60 245000 Main Turbine Gen. / Aux.
0 6
Knowledge of the physical connections and/or cause-effect relationships between Main Turbine Gen. / Aux. and the following: Component cooling water systems 2.6 1
61 256000 Reactor Condensate 0
8 Knowledge of the effect that a loss or malfunction of the Reactor Condensate will have on following: SJAE 2.8 1
62 259001 Reactor Feedwater 0
7 Knowledge of the effect that a loss or malfunction of the following will have on the Reactor Feedwater: Reactor water level control system 3.8 1
268000 Radwaste 0
63 271000 Offgas 02.
40 Ability to apply Technical Specifications for a system.
3.4 1
272000 Radiation Monitoring 0
64 286000 Fire Protection 0
1 Knowledge of the operational implications of the following concepts as they apply to Fire Protection : Effect of carbon dioxide on fires 2.6 1
288000 Plant Ventilation 0
65 290001 Secondary CTMT 0
2 Ability to manually operate and/or monitor in the control room: Reactor building area temperatures: Plant-Specific 3.3 1
290003 Control Room HVAC 0
290002 Reactor Vessel Internals 0
K/A Category Totals:
1 1
2 1
1 1
1 1
1 1
1 12 ES-401, Page 37 of 50 Group Point Total:
ES-401 2
Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO)
Q#
E/APE # / Name / Safety Function K
1 K
2 K
3 A
1 A
2 G
K/A Topic(s)
IR 295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 0
295003 Partial or Complete Loss of AC / 6 0
295004 Partial or Total Loss of DC Pwr / 6 0
76 295005 Main Turbine Generator Trip / 3 04.
46 Ability to verify that the alarms are consistent with the plant conditions.
4.2 1
295006 SCRAM / 1 0
77 295016 Control Room Abandonment / 7 0
3 Ability to determine and/or interpret the following as they apply to Control Room Abandonment: Reactor pressure 4.4 1
295018 Partial or Total Loss of CCW / 8 0
295019 Partial or Total Loss of Inst. Air / 8 0
295021 Loss of Shutdown Cooling / 4 0
78 295023 Refueling Acc / 8 0
3 Ability to determine and/or interpret the following as they apply to Refueling Accidents: Airborne contamination levels 3.8 1
295024 High Drywell Pressure / 5 0
79 295025 High Reactor Pressure / 3 01.
20 Ability to interpret and execute procedure steps.
4.6 1
295026 Suppression Pool High Water Temp. / 5 0
295027 High Containment Temperature / 5 0
295028 High Drywell Temperature / 5 0
80 295030 Low Suppression Pool Wtr Lvl / 5 0
3 Ability to determine and/or interpret the following as they apply to Low Suppression Pool Wtr Lvl: Reactor pressure 3.9 1
81 295031 Reactor Low Water Level / 2 02.
42 Ability to recognize system parameters that are entry-level conditions for Technical Specifications.
4.6 1
295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 0
82 295038 High Off-site Release Rate / 9 0
1 Ability to determine and/or interpret the following as they apply to High Off-site Release Rate: Off-site 4.3 1
600000 Plant Fire On Site / 8 0
700000 Generator Voltage and Electric Grid Disturbances / 6 0
K/A Category Totals:
0 0
0 0
4 3
7 ES-401, Page 34 of 50 Group Point Total:
ES-401 3
Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO)
Q#
E/APE # / Name / Safety Function K
1 K
2 K
3 A
1 A
2 G
K/A Topic(s)
IR 295002 Loss of Main Condenser Vac / 3 0
83 295007 High Reactor Pressure / 3 0
1 Ability to determine and/or interpret the following as they apply to High Reactor Pressure: Reactor pressure 4.1 1
295008 High Reactor Water Level / 2 0
295009 Low Reactor Water Level / 2 0
295010 High Drywell Pressure / 5 0
295011 High Containment Temp / 5 0
295012 High Drywell Temperature / 5 0
295013 High Suppression Pool Temp. / 5 0
295014 Inadvertent Reactivity Addition / 1 0
295015 Incomplete SCRAM / 1 0
295017 High Off-site Release Rate / 9 0
295020 Inadvertent Cont. Isolation / 5 & 7 0
295022 Loss of CRD Pumps / 1 0
84 295029 High Suppression Pool Wtr Lvl / 5 04.
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.
4.1 1
295032 High Secondary Containment Area Temperature / 5 0
295033 High Secondary Containment Area Radiation Levels / 9 0
295034 Secondary Containment Ventilation High Radiation / 9 0
295035 Secondary Containment High Differential Pressure / 5 0
85 295036 Secondary Containment High Sump/Area Water Level / 5 0
3 Ability to determine and/or interpret the following as they apply to Secondary Containment High Sump / Area Water Level: Cause of the high water level 3.8 1
500000 High CTMT Hydrogen Conc. / 5 0
K/A Category Totals:
0 0
0 0
2 1
3 ES-401, Page 35 of 50 Group Point Total:
ES-401 4
Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (SRO)
Q#
System # / Name K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
K/A Topic(s)
IR 203000 RHR/LPCI: Injection 0
205000 Shutdown Cooling Mode 0
206000 HPCI 0
207000 Isolation (Emergency)
Condenser 0
87 209001 LPCS 01.
23 Ability to perform specific system and integrated plant procedures during all modes of plant operation.
4.4 1
209002 HPCS 0
211000 SLC 0
212000 RPS 0
88 215003 IRM 0
4 Ability to (a) predict the impacts of the following on the IRM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Up scale or down scale trips 3.8 1
215004 Source Range Monitor 0
89 217000 RCIC 0
9 Ability to (a) predict the impacts of the following on the RCIC; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of vacuum pump 3.0 1
218000 ADS 0
223002 PCIS/Nuclear Steam Supply Shutoff 0
239002 SRVs 0
90 259002 Reactor Water Level Control 01.
25 Ability to interpret reference materials, such as graphs, curves, tables, etc.
4.2 1
86 261000 SGTS 0
6 Ability to (a) predict the impacts of the following on the SGTS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Valve closures 2.9 1
262001 AC Electrical Distribution 0
262002 UPS (AC/DC) 0 263000 DC Electrical Distribution 0
264000 EDGs 0
300000 Instrument Air 0
400000 Component Cooling Water 0
K/A Category Totals:
0 0
0 0
0 0
0 3
0 0
2 5
ES-401, Page 36 of 50 Group Point Total:
ES-401 5
Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (SRO)
Q#
System # / Name K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
K/A Topic(s)
IR 201001 CRD Hydraulic 0
201002 RMCS 0
201003 Control Rod and Drive Mechanism 0
201004 RSCS 0
201005 RCIS 0
91 201006 RWM 0
1 Ability to (a) predict the impacts of the following on the RWM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Power supply loss:
2.8 1
202001 Recirculation 0
202002 Recirculation Flow Control 0
204000 RWCU 0
214000 RPIS 0
92 215001 Traversing In-core Probe 02.
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 4.4 1
215002 RBM 0
216000 Nuclear Boiler Inst.
0 219000 RHR/LPCI: Torus/Pool Cooling Mode 0
223001 Primary CTMT and Aux.
0 226001 RHR/LPCI: CTMT Spray Mode 0
230000 RHR/LPCI: Torus/Pool Spray Mode 0
233000 Fuel Pool Cooling/Cleanup 0
234000 Fuel Handling Equipment 0
239001 Main and Reheat Steam 0
239003 MSIV Leakage Control 0
93 241000 Reactor/Turbine Pressure Regulator 1
6 Ability to (a) predict the impacts of the following on the Reactor/Turbine Pressure Regulator; and (b) based on those predictions, use procedures to correct control or mitigate the consequences of those abnormal conditions or 3.4 1
245000 Main Turbine Gen. / Aux.
0 256000 Reactor Condensate 0
259001 Reactor Feedwater 0
268000 Radwaste 0
271000 Offgas 0
272000 Radiation Monitoring 0
286000 Fire Protection 0
288000 Plant Ventilation 0
290001 Secondary CTMT 0
290003 Control Room HVAC 0
290002 Reactor Vessel Internals 0
K/A Category Totals:
0 0
0 0
0 0
0 2
0 0
1 3
ES-401, Page 37 of 50 Group Point Total:
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facility Name:LaSalle Date of Exam:10/17/2016 NRC Q#
IR IR 94 2.1. 35 Knowledge of the fuel-handling responsibilities of SROs.
2.2 3.9 1
66 2.1. 39 Knowledge of conservative decision making practices.
3.6 1
4.3 67 2.1. 19 Ability to use plant computers to evaluate system or component status.
3.9 1
3.8 68 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.
4.1 1
4.3 98 2.1. 07 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
4.4 4.7 1
2.1.
Subtotal 3
2 95 2.2. 15 Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, tag-outs, etc.
3.9 4.3 1
96 2.2. 17 Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination with the transmission system operator.
2.6 3.8 1
69 2.2. 22 Knowledge of limiting conditions for operations and safety limits.
4.0 1
4.7 70 2.2. 23 Ability to track Technical Specification limiting conditions for operations.
3.1 1
4.6 2.2.
2.2.
Subtotal 2
2 97 2.3. 06 Ability to approve release permits.
2.0 3.8 1
2.3.
71 2.3. 12 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
3.2 1
3.7 72 2.3. 05 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.
2.9 1
2.9 73 2.3. 07 Ability to comply with radiation work permit requirements during normal or abnormal conditions.
3.5 1
3.6 2.3.
Subtotal 3
1 99 2.4. 05 Knowledge of the organization of the operating procedures network for normal, abnormal, and emergency evolutions.
3.7 4.3 1
100 2.4. 50 Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
4.2 4.0 1
74 2.4. 47 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
4.2 1
4.2 75 2.4. 14 Knowledge of general guidelines for EOP usage.
3.8 1
4.5 2.4.
2.4.
Subtotal 2
2 10 7
RO SRO-Only Category Topic
- 1.
Conduct of Operations ES-401, Page 43 of 50 Tier 3 Point Total
- 3.
Radiation Control
- 4.
Emergency Procedures
/ Plan
- 2.
Equipment Control K/A #