ML12047A114
| ML12047A114 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 08/29/2011 |
| From: | Bielby M Operations Branch III |
| To: | Exelon Nuclear |
| Shared Package | |
| ML11354A098 | List: |
| References | |
| Download: ML12047A114 (10) | |
Text
ES-401 BWR Examination Outline FORM ES-401-1 Facility Name: Clinton Power Station Date of Exam: 08/22/2011 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G* Total 1 2 3 4 5 6 1 2 3 4 *
- 1. 1 4 4 3 3 3 3 20 3 4 7 Emergency &
Abnormal 2 1 2 1 N/A 1 1 N/A 1 7 2 1 3 Plant Evolutions Tier Totals 5 6 4 4 4 4 27 5 5 10 1 2 3 2 3 3 2 3 2 2 2 2 26 2 3 5 2.
Plant 2 2 1 1 1 1 1 1 1 1 1 1 12 0 2 1 3 Systems Tier Totals 4 4 3 4 4 3 4 3 3 3 3 38 4 4 8
- 3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 10 7 Categories 3 2 2 3 2 2 1 2 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only 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).
Note: 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.
Note: 3. 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.
Note: 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.
Note: 5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.
Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
Note: 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
Note: 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.
Note: 8. 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.
Note: 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.
ES-401, Page 16 of 33
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)
K K K A A Q# E/APE # / Name / Safety Function G K/A Topic(s) IR #
1 2 3 1 2 295001 Partial or Complete Loss of Forced 0 48 Nuclear boiler instrumentation system 3.1 1 Core Flow Circulation / 1 & 4 7 0
53 295003 Partial or Complete Loss of AC / 6 System lineups 3.5 1 4
0 39 295004 Partial or Total Loss of DC Pwr / 6 Effect of battery discharge rate on capacity 2.8 1 4
0 58 295005 Main Turbine Generator Trip / 3 Core thermal limit considerations 3.2 1 2
0 52 295006 SCRAM / 1 Whether a reactor SCRAM has occurred 4.6 1 5
- 04. Ability to verify system alarm setpoints and operate controls 56 295016 Control Room Abandonment / 7 4.2 1 50 identified in the alarm response manual.
04.
54 295018 Partial or Total Loss of CCW / 8 Knowledge of the specific bases for EOPs. 3.3 1 18 01.
55 295019 Partial or Total Loss of Inst. Air / 8 Ability to interpret and execute procedure steps. 4.6 1 20 0
45 295021 Loss of Shutdown Cooling / 4 Raising reactor water level 3.3 1 1
0 43 295023 Refueling Acc / 8 Standby gas treatment/FRVS 3.6 1 7
295024 High Drywell Pressure / 5 0 0
41 295025 High Reactor Pressure / 3 Pressure effects on reactor water level 3.5 1 6
295026 Suppression Pool High Water 0 57 Suppression pool level 3.5 1 Temp. / 5 6 0
40 295027 High Containment Temperature / 5 Containment integrity: Mark-III 3.8 1 3
0 46 295028 High Drywell Temperature / 5 ADS 3.4 1 6
0 42 295030 Low Suppression Pool Wtr Lvl / 5 SPDS/ERIS/CRIDS/GDS: Plant-Specific 2.5 1 9
0 50 295031 Reactor Low Water Level / 2 High pressure core spray: Plant-Specific 4.3 1 4
295037 SCRAM Condition Present and 0
51 Reactor Power Above APRM Downscale or SBLC tank level 4.3 1 3
Unknown / 1 0
44 295038 High Off-site Release Rate / 9 SPDS/ERIS/CRIDS/GDS: Plant-Specific 2.6 1 8
0 49 600000 Plant Fire On Site / 8 Plant fire zone panel (including detector location) 2.5 1 9
700000 Generator Voltage and Electric Grid 0 Actions contained in abnormal operating procedure for voltage 47 3.6 1 Disturbances / 6 2 and grid disturbances K/A Category Totals: 4 4 3 3 3 3 Group Point Total: 20 ES-401, Page 17 of 33
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)
K K K A A Q# E/APE # / Name / Safety Function G K/A Topic(s) IR #
1 2 3 1 2 0
63 295002 Loss of Main Condenser Vac / 3 Condenser vacuum/absolute pressure 2.9 1 1
295007 High Reactor Pressure / 3 0 0
59 295008 High Reactor Water Level / 2 Moisture carryover 3.0 1 1
0 62 295009 Low Reactor Water Level / 2 Reactor water cleanup 2.7 1 4
02.
64 295010 High Drywell Pressure / 5 Knowledge of surveillance procedures. 3.7 1 12 295011 High Containment Temp / 5 0 0
61 295012 High Drywell Temperature / 5 Increased drywell cooling 3.5 1 1
295013 High Suppression Pool Temp. / 5 0 0
65 295014 Inadvertent Reactivity Addition / 1 Neutron monitoring system 4.0 1 5
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 0
60 295029 High Suppression Pool Wtr Lvl / 5 SRV's and discharge piping 3.4 1 6
295032 High Secondary Containment Area 0
Temperature / 5 295033 High Secondary Containment Area 0
Radiation Levels / 9 295034 Secondary Containment Ventilation 0
High Radiation / 9 295035 Secondary Containment High 0
Differential Pressure / 5 295036 Secondary Containment High 0
Sump/Area Water Level / 5 500000 High CTMT Hydrogen Conc. / 5 0 K/A Category Totals: 1 2 1 1 1 1 Group Point Total: 7 ES-401, Page 18 of 33
ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO)
K K K K K K A A A A Q# System # / Name G K/A Topic(s) IR #
1 2 3 4 5 6 1 2 3 4 0
14 203000 RHR/LPCI: Injection Mode Reactor water level 4.2 1 1
0 1 205000 Shutdown Cooling Reactor water level 3.6 1 2
206000 HPCI 0 207000 Isolation (Emergency) 0 Condenser 0
5 209001 LPCS Reactor water level 3.8 1 1
0 3 209002 HPCS Valve electrical power: BWR-5, 6 2.8 1 2
0 0 Core plate differential pressure indication ; Explosive valve 2.6; 7,25 211000 SLC 2 6 4 operation 3.1 0 0 Analog trip system logic cabinets; RPS bus frequency: 2.7; 4,26 212000 RPS 2 2 5 Plant-Specific 2.6 0
9 215003 IRM Changing detector position 3.0 1 3
0 0 2.6; 10,24 215004 Source Range Monitor SRM channels/detectors ; Detector operation 2 1 1 2.6 0
19 215005 APRM / LPRM IRM/APRM recorder 3.2 1 1
0 04. Alternate supplies of water; Ability to prioritize and interpret 3.6; 21,23 217000 RCIC 2 7 45 the significance of each annunciator or alarm. 4.1 Insures adequate air supply to ADS valves: Plant-Specific; 0 01. 3.5; 8,22 218000 ADS Ability to use plant computers to evaluate system or 2 4 19 component status. 3.9 223002 PCIS/Nuclear Steam Supply 0 12 Reactor protection system 3.5 1 Shutoff 8 0
15 239002 SRVs Leaky SRV 3.1 1 2
0 17 259002 Reactor Water Level Control Runout flow control: Plant-Specific 3.0 1 1
0 11 261000 SGTS Primary containment high pressure: Plant-Specific 3.1 1 9
0 Effect on instrumentation and controls of switching power 13 262001 AC Electrical Distribution 3.1 1 1 supplies 0
18 262002 UPS (AC/DC) Transfer from preferred to alternate source 2.8 1 1
0 16 263000 DC Electrical Distribution Loss of ventilation during charging 2.6 1 2
0 Transfer of emergency control between manual and 20 264000 EDGs 3.2 1 3 automatic 0
6 300000 Instrument Air Containment air system 2.7 1 1
0 Reactor coolant system, in order to determine source (s) of 2 400000 Component Cooling Water 2.9 1 4 RCS leakage into CCWS 0
K/A Category Totals: 2 3 2 3 3 2 3 2 2 2 2 Group Point Total: 26 ES-401, Page 19 of 33
ES-401-1 5 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (RO)
K K K K K K A A A A Q# System # / Name G K/A Topic(s) IR #
1 2 3 4 5 6 1 2 3 4 201001 CRD Hydraulic 0 201002 RMCS 0 0
35 201003 Control Rod and Drive Mechanism 1 Control rod position 3.7 1 201004 RSCS 0 0
33 201005 RCIS 1 First stage shell pressure/turbine load: BWR-6 3.2 1 201006 RWM 0 202001 Recirculation 0 202002 Recirculation Flow Control 0 0
27 204000 RWCU 4 Component cooling water systems 2.9 1 214000 RPIS 0 0
38 215001 Traversing In-core Probe 2 Process computer: (Not-BWR1) 2.5 1 215002 RBM 0 216000 Nuclear Boiler Inst. 0 219000 RHR/LPCI: Torus/Pool Cooling 0
Mode 1
36 223001 Primary CTMT and Aux. 4 Hydrogen igniters: Plant-Specific 3.7 1
- 04. Ability to diagnose and recognize trends in an accurate and 37 226001 RHR/LPCI: CTMT Spray Mode 4.2 1 47 timely manner utilizing the appropriate control room reference t i l 230000 RHR/LPCI: Torus/Pool Spray Mode 0 233000 Fuel Pool Cooling/Cleanup 0 234000 Fuel Handling Equipment 0 0
28 239001 Main and Reheat Steam 1 Main steam isolation valve solenoids 3.2 1 239003 MSIV Leakage Control 0 2
29 241000 Reactor/Turbine Pressure Regulator 8 Low pressure stop and control valves: Plant-Specific 2.5 1 245000 Main Turbine Gen. / Aux. 0 256000 Reactor Condensate 0 0
31 259001 Reactor Feedwater 3 Turbine operation: TDRFP's-Only 2.8 1 268000 Radwaste 0 271000 Offgas 0 272000 Radiation Monitoring 0 286000 Fire Protection 0 0
34 288000 Plant Ventilation 3 Loss of coolant accident: Plant-Specific 3.5 1 290001 Secondary CTMT 0 0
32 290003 Control Room HVAC 4 Fire protection: Plant-Specific 2.6 1 0
30 290002 Reactor Vessel Internals 2 Separation of fluid flow paths within the vessel 3.1 1 0
K/A Category Totals: 2 1 1 1 1 1 1 1 1 1 1 Group Point Total: 12 ES-401, Page 20 of 33
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)
K K K A A Q# E/APE # / Name / Safety Function G K/A Topic(s) IR #
1 2 3 1 2 295001 Partial or Complete Loss of Forced 0 76 Neutron monitoring 3.2 1 Core Flow Circulation / 1 & 4 2 295003 Partial or Complete Loss of AC / 6 0 295004 Partial or Total Loss of DC Pwr / 6 0 295005 Main Turbine Generator Trip / 3 0 295006 SCRAM / 1 0 295016 Control Room Abandonment / 7 0 295018 Partial or Total Loss of CCW / 8 0 04.
82 295019 Partial or Total Loss of Inst. Air / 8 Knowledge of abnormal condition procedures. 4.2 1 11 295021 Loss of Shutdown Cooling / 4 0 295023 Refueling Acc / 8 0 295024 High Drywell Pressure / 5 0 295025 High Reactor Pressure / 3 0 Knowledge of RO tasks performed outside the main 295026 Suppression Pool High Water Temp. 04.
81 control room during an emergency and the resultant 4.1 1
/5 34 operational effects.
0 78 295027 High Containment Temperature / 5 Containment temperature: Mark-III 3.7 1 1
295028 High Drywell Temperature / 5 0
- 04. Knowledge of EOP entry conditions and immediate 79 295030 Low Suppression Pool Wtr Lvl / 5 4.8 1 01 action steps.
Knowledge of low power/shutdown implications in 04.
80 295031 Reactor Low Water Level / 2 accident (e.g., loss of coolant accident or loss of 4.2 1 09 residual heat removal) mitigation strategies.
295037 SCRAM Condition Present 0
77 and Reactor Power Above APRM Reactor power 4.3 1 1
Downscale or Unknown / 1 295038 High Off-site Release Rate / 9 0 600000 Plant Fire On Site / 8 0 700000 Generator Voltage and Electric Grid 0
Disturbances / 6 K/A Category Totals: 0 0 0 0 3 4 Group Point Total: 7
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)
K K K A A Q# E/APE # / Name / Safety Function G K/A Topic(s) IR #
1 2 3 1 2 295002 Loss of Main Condenser Vac / 3 0 295007 High Reactor Pressure / 3 0 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 0
85 295015 Incomplete SCRAM / 1 Control rod position 4.2 1 2
295017 High Off-site Release Rate / 9 0 295020 Inadvertent Cont. Isolation / 5 & 7 0 0
83 295022 Loss of CRD Pumps / 1 Accumulator pressure 3.6 1 1
295029 High Suppression Pool Wtr Lvl / 5 0 295032 High Secondary Containment Area 0
Temperature / 5 295033 High Secondary Containment Area 0
Radiation Levels / 9 295034 Secondary Containment Ventilation 0
High Radiation / 9 295035 Secondary Containment High 04. Knowledge of the operational implications of EOP warnings, 84 4.3 1 Differential Pressure / 5 20 cautions, and notes.
295036 Secondary Containment High 0
Sump/Area Water Level / 5 500000 High CTMT Hydrogen Conc. / 5 0 K/A Category Totals: 0 0 0 0 2 1 Group Point Total: 3 ES-401, Page 18 of 33
ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (SRO)
K K K K K K A A A A Q# System # / Name G K/A Topic(s) IR #
1 2 3 4 5 6 1 2 3 4 01.
88 203000 RHR/LPCI: Injection Ability to explain and apply system limits and precautions. 4.0 1 32
- 04. Knowledge of the emergency action level thresholds and 90 205000 Shutdown Cooling Mode 4.6 1 41 classifications.
206000 HPCI 0 207000 Isolation (Emergency) 0 Condenser 209001 LPCS 0 209002 HPCS 0 211000 SLC 0 212000 RPS 0 215003 IRM 0 215004 Source Range Monitor 0 0
86 215005 APRM / LPRM Power supply degraded 3.1 1 1
217000 RCIC 0 218000 ADS 0 223002 PCIS/Nuclear Steam Supply 0
Shutoff 239002 SRVs 0 259002 Reactor Water Level Control 0 261000 SGTS 0 262001 AC Electrical Distribution 0 262002 UPS (AC/DC) 0 263000 DC Electrical Distribution 0
- 02. Knowledge of limiting conditions for operations and safety 89 264000 EDGs 4.7 1 22 limits.
300000 Instrument Air 0 0
87 400000 Component Cooling Water High/low CCW temperature 3.0 1 3
0 K/A Category Totals: 0 0 0 0 0 0 0 2 0 0 3 Group Point Total: 5 ES-401, Page 19 of 33
ES-401 5 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (SRO)
K K K K K K A A A A Q# System # / Name G K/A Topic(s) IR #
1 2 3 4 5 6 1 2 3 4 0
91 201001 CRD Hydraulic 3 Power supply failures 3.1 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 204000 RWCU 0 0
93 214000 RPIS 2 Reactor scram 3.7 1 215001 Traversing In-core Probe 0 215002 RBM 0
- 02. Ability to determine operability and/or availability of safety 92 216000 Nuclear Boiler Inst. 4.6 1 37 related equipment.
219000 RHR/LPCI: Torus/Pool Cooling 0
Mode 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 241000 Reactor/Turbine Pressure Regulator 0 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 0
K/A Category Totals: 0 0 0 0 0 0 0 2 0 0 1 Group Point Total: 3 ES-401, Page 20 of 33
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility Name:Clinton Power Station Date of Exam:08/22/2011 RO SRO-Only Category K/A # Topic Q# IR # IR #
Knowledge of criteria or conditions that require plant-wide announcements, such as pump 94 2.1. 14 starts, reactor trips, mode changes, etc. 3.1 1 99 2.1. 34 Knowledge of primary and secondary plant chemistry limits. 3.5 1
- 1. 2.1.
Conduct of 66 2.1. 30 Ability to locate and operate components, including local controls. 4.4 1 Operations Ability to use procedures related to shift staffing, such as minimum crew complement, 67 2.1. 05 overtime limitations, etc. 2.9 1 Ability to identify and interpret diverse indications to validate the response of another 75 2.1. 45 indicator. 4.3 1 Subtotal 3 2 95 2.2. 21 Knowledge of pre- and post-maintenance operability requirements. 4.1 1 100 2.2. 05 Knowledge of the process for making design or operating changes to the facility. 3.2 1
- 2. 2.2.
Equipment 2.2.
Control 68 2.2. 14 Knowledge of the process for controlling equipment configuration or status. 3.9 1 69 2.2. 23 Ability to track Technical Specification limiting conditions for operations. 3.1 1 Subtotal 2 2 96 2.3. 11 Ability to control radiation releases. 4.3 1 2.3.
- 3. 2.3.
Radiation 2.3.
Control 70 2.3. 04 Knowledge of radiation exposure limits under normal or emergency conditions. 3.2 1 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, 71 2.3. 14 or emergency conditions or activities. 3.4 1 Subtotal 2 1 Knowledge of the bases for prioritizing emergency procedure implementation during 97 2.4. 23 emergency operations. 4.4 1 98 2.4. 44 Knowledge of emergency plan protective action recommendations. 4.4 1
- 4. 2.4.
Emergency 72 Procedures 2.4. 06 Knowledge of EOP mitigation strategies. 3.7 1
/ Plan 73 2.4. 46 Ability to verify that the alarms are consistent with the plant conditions. 4.2 1 74 2.4. 29 Knowledge of the emergency plan. 3.1 1 Subtotal 3 2 Tier 3 Point Total 10 7 ES-401, Page 26 of 33