ML080870256
| ML080870256 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 03/21/2008 |
| From: | Ryan Lantz Operations Branch IV |
| To: | Nebraska Public Power District (NPPD) |
| References | |
| 50-298/08-301 | |
| Download: ML080870256 (18) | |
Text
ES-401, Rev. 9 BWR Examination Outline Form ES-401-1 Facility: Cooper Nuclear Station Date of Exam:
March 2008 RO K/A Category Points SRO-Only Points Tier Group K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
Total A2 G*
Total 1
3 4
4 3
3 3
20 3
4 7
2 1
1 11 1
2 1
7 2
1 3
- 1.
Emergency &
Abnormal Plant Evolutions Tier Totals 4
5 55 N/A 4
5 N/A 4
27 5
5 10 1
2 2
3 2
2 2
2 3
3 3
2 26 3
2 5
2 1
1 1
1 2
1 1
1 1
1 1
12 1
2 3
- 2.
Plant Systems Tier Totals 3
3 4
3 4
3 3
4 4
4 3
38 4
4 8
1 2
3 4
1 2
3 4
- 3. Generic Knowledge and Abilities Categories 2
2 3
3 10 1
2 2
2 7
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).
- 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 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 ES-401, Attachment 2, 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.
a)
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.
- 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.
- 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.
i)
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, Rev. 9 2
Form ES-401-1 ES-401 BWR Examination OutlineForm ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)
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 X
AK2.01 Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION and the following: (CFR: 41.7 /
45.8) Recirculation system 3.6 1
295003 Partial or Complete Loss of AC / 6 X
2.1.32 Ability to explain and apply system limits and precautions. (CFR: 41.10 / 43.2 / 45.12) 3.4/ 3.8 3.4 2
295004 Partial or Total Loss of DC Pwr / 6 X
AK1.03 Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER : (CFR: 41.8 to 41.10) Electrical bus divisional separation 2.9 3
295005 Main Turbine Generator Trip / 3 X
AK1.02 Knowledge of the operational implications of the following concepts as they apply to MAIN TURBINE GENERATOR TRIP : (CFR: 41.8 to 41.10) Core thermal limit considerations 3.2 4
295006 SCRAM / 1 X
AA2.02 Ability to determine and/or interpret the following as they apply to SCRAM : (CFR: 41.10 / 43.5 /
45.13)Control rod position 4.3 5
295006 SCRAM / 1 X
AK3.06 Knowledge of the reasons for the following responses as they apply to SCRAM : (CFR: 41.5 / 45.6)
Recirculation pump speed reduction: Plant-Specific....
3.2 6
295016 Control Room Abandonment / 7 X
AK3.03 Knowledge of the reasons for the following responses as they apply to CONTROL ROOM ABANDONMENT: (CFR: 41.5 / 45.6) Disabling control room controls 3.5 7
295018 Partial or Total Loss of CCW / 8 X
AK1.01 Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER : (CFR: 41.8 to 41.10) Effects on component /
system operations 3.5 8
295019 Partial or Total Loss of Inst. Air / 8 X
2.1.27 Knowledge of system purpose and or function.
(CFR: 41.7) 2.8 9
295021 Loss of Shutdown Cooling / 4 X
AK2.02 Knowledge of the interrelations between LOSS OF SHUTDOWN COOLING and the following: (CFR:
41.7 / 45.8) Reactor water cleanup 3.2 10 295023 Refueling Acc / 8 X
AA1.06 Ability to operate and/or monitor the following as they apply to REFUELING ACCIDENTS :
(CFR: 41.7 / 45.6) Neutron monitoring 3.3 11 295024 High Drywell Pressure / 5 X
EA2.02 Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE: (CFR: 41.10 / 43.5 / 45.13) Drywell temperature 3.9 12 295025 High Reactor Pressure / 3 X
EA1.02 Ability to operate and/or monitor the following as they apply to HIGH REACTOR PRESSURE: (CFR: 41.7
/ 45.6) Reactor/turbine pressure regulating system 3.8 13 295026 Suppression Pool High Water Temp. / 5 X
EK2.01 Knowledge of the interrelations between SUPPRESSION POOL HIGH WATER TEMPERATURE and the following: (CFR: 41.7 / 45.8)
Suppression pool cooling 3.9 14 295027 High Containment Temperature / 5 Note 1
ES-401, Rev. 9 2
Form ES-401-1 ES-401 BWR Examination OutlineForm ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)
E/APE # / Name / Safety Function K
1 K
2 K
3 A
1 A
2 G
K/A Topic(s)
IR 295028 High Drywell Temperature / 5 X
EA2.05 Ability to determine and/or interpret the following as they apply to HIGH DRYWELL TEMPERATURE: (CFR: 41.10 / 43.5 / 45.13)
Torus/suppression chamber pressure: Plant-Specific 3.6 15 295030 Low Suppression Pool Wtr Lvl / 5 X
EK1.01 Knowledge of the operational implications of the following concepts as they apply to LOW SUPPRESSION POOL WATER LEVEL: (CFR: 41.8 to 41.10) Steam condensation 3.8 16 295031 Reactor Low Water Level / 2 X
EK3.02 Knowledge of the reasons for the following responses as they apply to REACTOR LOW WATER LEVEL : (CFR: 41.5 / 45.6) Core coverage 4.4 17 295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown / 1 X
2.1.30 Ability to locate and operate components /
including local controls. (CFR: 41.7 / 45.7) 3.9 18 295038 High Off-site Release Rate / 9 X
EK3.04 Knowledge of the reasons for the following responses as they apply to HIGH OFF-SITE RELEASE RATE: (CFR: 41.5 / 45.6) Emergency depressurization 3.6 19 600000 Plant Fire On Site / 8 X
AK2.01 Knowledge of the interrelations between PLANT FIRE ON SITE and the following: Sensors / detectors and valves 2.6 20 K/A Category Totals:
3 4
4 3
3 3
Group Point Total:
20
ES-401, Rev. 9 2
Form ES-401-1 ES-401 BWR Examination OutlineForm ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 SRO)
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 295003 Partial or Complete Loss of AC / 6 X
AA2.04 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)
System Lineups 3.7 76 295004 Partial or Total Loss of DC Pwr / 6 295005 Main Turbine Generator Trip / 3 295006 SCRAM / 1 X
AA2.02 Ability to determine and/or interpret the following as they apply to SCRAM : (CFR: 41.10 / 43.5 /
45.13) Control Rod Position 4.4 77 295006 SCRAM / 1 X 2.4.6 Knowledge symptom based EOP mitigation strategies. (CFR: 41.10 / 43.5 / 45.13) 4.0 78 295016 Control Room Abandonment / 7 295018 Partial or Total Loss of CCW / 8 295019 Partial or Total Loss of Inst. Air / 8 X
2.4.4 Ability to recognize abnormal indications for system operating parameters which are entry conditions for emergency and abnormal operating procedures. (CFR:
41.10 / 43.2 / 45.6) 4.3 79 295021 Loss of Shutdown Cooling / 4 295023 Refueling Acc / 8 295024 High Drywell Pressure / 5 X
EA2.03 Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE:
(CFR: 41.10 / 43.5 / 45.13) Suppression pool level 3.8 80 295025 High Reactor Pressure / 3 295026 Suppression Pool High Water Temp. / 5 X G2.1.32 Ability to explain and apply system limits and precautions.(CFR: 41.10 / 43.2 / 45.12) 3.8 81 295027 High Containment Temperature / 5 295028 High Drywell Temperature / 5 X
2.4.30 Knowledge of which events related to system operations/status should be reported to outside agencies.
(CFR: 43.5 / 45.11) 3.6 82 295030 Low Suppression Pool Wtr Lvl / 5 295031 Reactor Low Water Level / 2 295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown / 1 295038 High Off-site Release Rate / 9 600000 Plant Fire On Site / 8 K/A Category Totals:
3 4
Group Point Total:
7
ES-401, Rev. 9 3
Form ES-401-1 ES-401 BWR Examination OutlineForm ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)
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 X
AA2.02 Ability to determine and/or interpret the following as they apply to LOSS OF MAIN CONDENSER VACUUM: (CFR: 41.10 / 43.5 / 45.13) Reactor power:
Plant-Specific 3.2 21 295007 High Reactor Pressure / 3 295008 High Reactor Water Level / 2 295009 Low Reactor Water Level / 2 295010 High Drywell Pressure / 5 295011 High Containment Temp / 5 Note 1 295012 High Drywell Temperature / 5 295013 High Suppression Pool Temp. / 5 295014 Inadvertent Reactivity Addition / 1 X
AK3.02 Knowledge of the reasons for the following responses as they apply to INADVERTENT REACTIVITY ADDITION: (CFR: 41.5 / 45.6) Control rod blocks 3.7 22 295015 Incomplete SCRAM / 1 295017 High Off-site Release Rate / 9 295020 Inadvertent Cont. Isolation / 5 & 7 X
AK2.06 Knowledge of the interrelations between INADVERTENT CONTAINMENT ISOLATION and the following: (CFR: 41.7 / 45.8) HPCI: Plant-Specific 3.8 23 295022 Loss of CRD Pumps / 1 295029 High Suppression Pool Wtr Lvl / 5 X
EA1.01 Ability to operate and/or monitor the following as they apply to HIGH SUPPRESSION POOL WATER LEVEL: (CFR: 41.7 / 45.6) HPCI: Plant-Specific 3.4 24 295032 High Secondary Containment Area Temperature / 5 295033 High Secondary Containment Area Radiation Levels / 9 295034 Secondary Containment Ventilation High Radiation / 9 295035 Secondary Containment High Differential Pressure / 5 X G2.2.22 Knowledge of limiting conditions for operations and safety limits. (CFR: 43.2 / 45.2) 3.4 25 295036 Secondary Containment High Sump/Area Water Level / 5 X
EK1.01 Knowledge of the operational implications of the following concepts as they apply to SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL :
(CFR: 41.8 to 41.10) Radiation releases 2.9 26 500000 High CTMT Hydrogen Conc. / 5 X
EA2.04 Ability to determine and / or interpret the following as they apply to HIGH PRIMARY CONTAINMENT HYDROGEN CONCENTRATIONS:
(CFR: 41.10 / 43.5 / 45.13) Combustible limits for wetwell 3.3 27 K/A Category Point Totals:
1 1
1 1
2 1
Group Point Total:
7
ES-401, Rev. 9 3
Form ES-401-1 ES-401 BWR Examination OutlineForm ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO)
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 X 2.1.32 Ability to explain and apply system limits and precautions. (CFR: 41.10 / 43.2 / 45.12) 3.8 83 295007 High Reactor Pressure / 3 295008 High Reactor Water Level / 2 295009 Low Reactor Water Level / 2 X
AA2.01 Ability to determine and/or interpret the following as they apply to LOW REACTOR WATER LEVEL:
(CFR: 41.10 / 43.5 / 45.13) Reactor water level 4.2 84 295010 High Drywell Pressure / 5 X
AA2.01 Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE :
(CFR: 41.10 / 43.5 / 45.13) Leak rates 3.8 85 295011 High Containment Temp / 5 Note 1 295012 High Drywell Temperature / 5 295013 High Suppression Pool Temp. / 5 295014 Inadvertent Reactivity Addition / 1 295015 Incomplete SCRAM / 1 295017 High Off-site Release Rate / 9 295020 Inadvertent Cont. Isolation / 5 & 7 295022 Loss of CRD Pumps / 1 295029 High Suppression Pool Wtr Lvl / 5 295032 High Secondary Containment Area Temperature / 5 295033 High Secondary Containment Area Radiation Levels / 9 295034 Secondary Containment Ventilation High Radiation / 9 295035 Secondary Containment High Differential Pressure / 5 295036 Secondary Containment High Sump/Area Water Level / 5 500000 High CTMT Hydrogen Conc. / 5 K/A Category Point Totals:
2 1
Group Point Total:
3
ES-401, Rev. 9 4
Form ES-401-1 ES-401BWR Examination OutlineForm ES-401-1 Plant Systems - Tier 2/Group 1 (RO)
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 Mode X
K6.09 Knowledge of the effect that a loss or malfunction of the following will have on the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) : (CFR: 41.7 / 45.7) Nuclear boiler instrumentation 3.4 28 205000 Shutdown Cooling X
K1.01 Knowledge of the physical connections and/or cause-effect relationships between SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) and the following: (CFR: 41.2 to 41.9 / 45.7 to 45.8) Reactor Pressure 3.6 29 206000 HPCI X
K3.02 Knowledge of the effect that a loss or malfunction of the HIGH PRESSURE COOLANT INJECTION SYSTEM will have on following:
(CFR: 41.7 / 45.4) reactor pressure control: BWR-2,3,4 3.8 30 207000 Isolation (Emergency)
Condenser Note 2 209001 LPCS X
A1.05 Ability to predict and/or monitor changes in parameters associated with operating the LOW PRESSURE CORE SPRAY SYSTEM controls including: (CFR: 41.5 / 45.5) Torus/suppression pool water level 3.5 31 209002 HPCS Note 3 211000 SLC X
A3.01 Ability to monitor automatic operations of the STANDBY LIQUID CONTROL SYSTEM including: (CFR: 41.7 / 45.7) Pump discharge pressure: Plant-Specific 3.5 32 211000 SLC X
A1.04 Ability to predict and/or monitor changes in parameters associated with operating the STANDBY LIQUID CONTROL SYSTEM controls including:
(CFR: 41.5 / 45.5) Valve operations 3.6 33 212000 RPS X
G2.1.23 Ability to perform specific system and integrated plant procedures during different modes of plant operation. (CFR: 45.2 / 45.6)3.9/ 4.0 3.9 34 215003 IRM X
K5.01 Knowledge of the operational implications of the following concepts as they apply to INTERMEDIATE RANGE MONITOR (IRM)
SYSTEM : (CFR: 41.5 / 45.3) Detector operation 2.6 35 215004 Source Range Monitor X
2.4.49 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
(CFR: 41.10 / 43.2 / 45.6) 4.0 36
ES-401, Rev. 9 4
Form ES-401-1 ES-401BWR Examination OutlineForm ES-401-1 Plant Systems - Tier 2/Group 1 (RO)
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 215004 Source Range Monitor X
A2.05 Ability to (a) predict the impacts of the following on the SOURCE RANGE MONITOR (SRM) 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) Faulty or erratic operation of detectors/system 3.3 37 215005 APRM / LPRM X
A3.07 Ability to monitor automatic operations of the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM including:
(CFR: 41.7 / 45.7) RPS status 3.8 38 217000 RCIC X
K3.04 Knowledge of the effect that a loss or malfunction of the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) will have on following:
(CFR: 41.7 / 45.4) Adequate core cooling 3.6 39 217000 RCIC X
A4.10 Ability to manually operate and/or monitor in the control room: (CFR: 41.7 / 45.5 to 45.8)
Lights and alarms 3.6 40 218000 ADS X
K1.02 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) Low pressure core spray: Plant-Specific 4.0 41 218000 ADS X
A4.10 Ability to manually operate and/or monitor in the control room: (CFR: 41.7 / 45.5 to 45.8) Lights and alarms 3.8 42 223002 PCIS/Nuclear Steam Supply Shutoff X
K3.16 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) Shutdown cooling system/RHR 3.2 43 223002 PCIS/Nuclear Steam Supply Shutoff X
A3.01 Ability to monitor automatic operations of the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF including: (CFR: 41.7 / 45.7)
System indicating lights and alarms 3.4 44 239002 SRVs X
K5.06 Knowledge of the operational implications of the following concepts as they apply to RELIEF/SAFETY VALVES : (CFR: 41.5 / 45.3)
Vacuum breaker operation 2.7 45 259002 Reactor Water Level Control X
A2.01 Ability to (a) predict the impacts of the following on the REACTOR WATER LEVEL 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)
Loss of any number of main steam flow inputs 3.3 46
ES-401, Rev. 9 4
Form ES-401-1 ES-401BWR Examination OutlineForm ES-401-1 Plant Systems - Tier 2/Group 1 (RO)
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 261000 SGTS X
A2.04 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 Train Moisture Content 2.5 47 262001 AC Electrical Distribution X
K2.01 Knowledge of electrical power supplies to the following: (CFR: 41.7) Off-site sources of power 3.3 48 262002 UPS (AC/DC)
X K4.01 Knowledge of UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) design feature(s) and/or interlocks which provide for the following:
(CFR: 41.7) Transfer from preferred power to alternate power supplies 3.1 49 263000 DC Electrical Distribution X
A4.01 Ability to manually operate and/or monitor in the control room: (CFR: 41.7 / 45.5 to 45.8)
Major breakers and control power fuses: Plant-Specific 3.3 50 264000 EDGs X
K6.09 Knowledge of the effect that a loss or malfunction of the following will have on the EMERGENCY GENERATORS (DIESEL/JET) :
(CFR: 41.7 / 45.7) D.C. power 3.3 51 300000 Instrument Air X
K4.03 Knowledge of (INSTRUMENT AIR SYSTEM) design feature(s) and or interlocks which provide for the following: (CFR: 41.7) Securing of IAS upon loss of cooling water 2.8 52 400000 Component Cooling Water X
K2.02 Knowledge of electrical power supplies to the following: (CFR: 41.7) CCW valves 2.9 53 K/A Category Point Totals:
2 2
3 2
2 2
2 3
3 3
2 Group Point Total:
26
ES-401, Rev. 9 4
Form ES-401-1 ES-401BWR Examination OutlineForm ES-401-1 Plant Systems - Tier 2/Group 1 (SRO)
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 Mode 205000 Shutdown Cooling X
A2.07 Ability to (a) predict the impacts of the following on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) ; 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) Loss of motor cooling: Plant-Specific 2.7 86 206000 HPCI 207000 Isolation (Emergency)
Condenser Note 2 209001 LPCS 209002 HPCS Note 3 211000 SLC 212000 RPS 215003 IRM 215004 Source Range Monitor 215005 APRM / LPRM X
G2.1.2 Knowledge of operator responsibilities during all modes of plant operation.
(CFR: 41.10 / 45.13) 4.0 87 217000 RCIC 218000 ADS X
2.4.4 Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures. (CFR: 41.10 / 43.2 / 45.6) 4.3 88 223002 PCIS/Nuclear Steam Supply Shutoff 239002 SRVs X
A2.04 Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES ;
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) ADS actuation 4.2 89 259002 Reactor Water Level Control 261000 SGTS 262001 AC Electrical Distribution X
A2.04 Ability to (a) predict the impacts of the following on the A.C. ELECTRICAL DISTRIBUTION ; 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)
Types of loads that, if deenergized, would degrade or hinder plant operation 4.2 90 262002 UPS (AC/DC) 263000 DC Electrical Distribution 264000 EDGs 300000 Instrument Air 400000 Component Cooling Water K/A Category Point Totals:
3 2
Group Point Total:
5
ES-401, Rev. 9 5
Form ES-401-1 ES-401BWR Examination OutlineForm ES-401-1 Plant Systems - Tier 2/Group 2 (RO)
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 201002 RMCS 201003 Control Rod and Drive Mechanism X
A2.07 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) Loss of CRD drive water flow 3.1 54 201004 RSCS Note 4 201005 RCIS Note 5 201006 RWM X
K1.08 Knowledge of the physical connections and/or cause-effect relationships between ROD WORTH MINIMIZER SYSTEM (RWM)
(PLANT SPECIFIC) and the following: (CFR:
41.2 to 41.9 / 45.7 to 45.8) Reactor power (turbine first stage pressure): P-Spec(Not-BWR6) 3.2 55 202001 Recirculation 202002 Recirculation Flow Control 204000 RWCU 214000 RPIS 215001 Traversing In-core Probe X
K4.01 Knowledge of TRAVERSING IN-CORE PROBE design feature(s) and/or interlocks which provide for the following: (CFR: 41.7) Primary containment isolation: Mark-I&II(Not-BWR1) 3.4 56 215002 RBM 216000 Nuclear Boiler Inst.
219000 RHR/LPCI: Torus/Pool Cooling Mode X
K2.02 Knowledge of electrical power supplies to the following: (CFR: 41.7) Pumps 3.1 57 223001 Primary CTMT and Aux.
226001 RHR/LPCI: CTMT Spray Mode X
G2.1.30 Ability to locate and operate components / including local controls.
(CFR: 41.7 / 45.7) 3.9 58 230000 RHR/LPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment X
K3.03 Knowledge of the effect that a loss or malfunction of the FUEL HANDLING EQUIPMENT will have on following:
(CFR: 41.7 / 45.4) Fuel handling operations 3.1 59 239001 Main and Reheat Steam 239003 MSIV Leakage Control 241000 Reactor/Turbine Pressure Regulator X
A3.08 Ability to monitor automatic operations of the REACTOR/TURBINE PRESSURE REGULATING SYSTEM including: (CFR:
41.7 / 45.7) Steam bypass valve operation 3.8 60 245000 Main Turbine Gen. / Aux.
ES-401, Rev. 9 5
Form ES-401-1 ES-401BWR Examination OutlineForm ES-401-1 Plant Systems - Tier 2/Group 2 (RO)
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 256000 Reactor Condensate X
K5.07 Knowledge of the operational implications of the following concepts as they apply to REACTOR CONDENSATE SYSTEM : (CFR: 41.5 / 45.3) Level controller operation 2.7 61 259001 Reactor Feedwater X
K6.09 Knowledge of the effect that a loss or malfunction of the following will have on the REACTOR FEEDWATER SYSTEM :
(CFR: 41.7 / 45.7) Reactor feedwater pump lube oil system 2.8 62 268000 Radwaste 271000 Offgas X
A4.02 Ability to manually operate and/or monitor in the control room:
(CFR: 41.7 / 45.5 to 45.8) System flows 2.9 63 272000 Radiation Monitoring 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary CTMT X
A1.01 Ability to predict and/or monitor changes in parameters associated with operating the SECONDARY CONTAINMENT controls including:
(CFR: 41.5 / 45.5) System lineups 3.1 64 290003 Control Room HVAC 290002 Reactor Vessel Internals X
K5.03 Knowledge of the operational implications of the following concepts as they apply to REACTOR VESSEL INTERNALS :
(CFR: 41.5 / 45.3) Burnable poisons 2.7 65 K/A Category Point Totals:
1 1
1 1
2 1
1 1
1 1
1 Group Point Total:
12
ES-401, Rev. 9 5
Form ES-401-1 ES-401, Rev. 9 5
Form ES-401-1 ES-401BWR Examination OutlineForm ES-401-1 Plant Systems - Tier 2/Group 2 (SRO)
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 201002 RMCS 201003 Control Rod and Drive Mechanism 201004 RSCS Note 4 201005 RCIS Note 5 201006 RWM 202001 Recirculation 202002 Recirculation Flow Control 204000 RWCU 214000 RPIS 215001 Traversing In-core Probe 215002 RBM 216000 Nuclear Boiler Inst.
X G2.2.22 Knowledge of limiting conditions for operations and safety limits. (CFR: 43.2 /
45.2) 4.1 91 219000 RHR/LPCI: Torus/Pool Cooling Mode 223001 Primary CTMT and Aux.
226001 RHR/LPCI: CTMT Spray Mode 230000 RHR/LPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment 239001 Main and Reheat Steam X
A2.05 Ability to (a) predict the impacts of the following on the MAIN AND REHEAT STEAM 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) Main steam line high radiation 4.2 92 239003 MSIV Leakage Control 241000 Reactor/Turbine Pressure Regulator 245000 Main Turbine Gen. / Aux.
256000 Reactor Condensate 259001 Reactor Feedwater X
2.4.49 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls. (CFR: 41.10 / 43.2 / 45.6) 4.0 93
ES-401, Rev. 9 5
Form ES-401-1 ES-401BWR Examination OutlineForm ES-401-1 Plant Systems - Tier 2/Group 2 (SRO)
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 268000 Radwaste 271000 Offgas 272000 Radiation Monitoring 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC 290002 Reactor Vessel Internals K/A Category Point Totals:
1 2
Group Point Total:
3
ES-401, Rev. 9 Generic Knowledge and Abilities Outline Form ES-401-3 Facility: Date of Exam:
RO SRO-Only Category K/A #
Topic IR IR 2.1.27 Knowledge of system purpose and or function. (CFR: 41.7) 2.8 66 2.1.1 Knowledge of conduct of operations requirements.
(CFR: 41.10 / 45.13) 3.7 67 2.1.32 Ability to explain and apply system limits and precautions.
(CFR: 41.10 / 43.2 / 45.12) 3.8 94
- 1. Conduct of Operations Subtotal 2
1 2.2.23 Ability to track limiting conditions for operations. (CFR: 43.2 / 45.13) 2.6 68 2.2.24 Ability to analyze the affect of maintenance activities on LCO status.
(CFR: 43.2 / 45.13) 2.6 69 2.2.9 Knowledge of the process for determining if the proposed change / test or experiment increases the probability of occurrence or consequences of an accident during the change / test or experiment. (CFR: 43.3 /
45.13) 3.3 95 2.2.26 Knowledge of refueling administrative requirements.
(CFR: 43.5 / 45.13) 3.7 96
- 2. Equipment Control Subtotal 2
2 2.3.2 Knowledge of facility ALARA program.
(CFR: 41.12 / 43.4 / 45.9 / 45.10) 2.5 70 2.3.11 Ability to control radiation releases. (CFR: 45.9 / 45.10) 2.7 71 2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure. (CFR: 43.4 / 45.10) 2.9 72 2.3.8 Knowledge of the process for performing a planned gaseous radioactive release. (CFR: 43.4 / 45.10) 3.2 97 2.3.1 Knowledge of 10 CFR: 20 and related facility radiation control requirements. (CFR: 41.12 / 43.4. 45.9 / 45.10) 3.0 98
- 3. Radiation Control Subtotal 3
2 2.4.29 Knowledge of the emergency plan. (CFR: 43.5 / 45.11) 2.6 73 2.4.17 Knowledge of EOP terms and definitions. (CFR: 41.10 / 45.13) 3.1 74 2.4.18 Knowledge of the specific bases for EOPs. (CFR: 41.10 / 45.13) 2.7 75 2.4.48 Ability to interpret control room indications to verify the status and operation of system / and understand how operator action s and directives affect plant and system conditions. (CFR: 43.5 / 45.12) 3.8 99 2.4.9 Knowledge of low power / shutdown implications in accident (e.g.
LOCA or loss of RHR) mitigation strategies.
(CFR: 41.10 / 43.5 / 45.13) 3.9 100
- 4. Emergency Procedures / Plan Subtotal 3
2 Tier 3 Point Total 10 7
ES-401, Rev. 9 Record of Rejected K/As Form ES-401-4 Justification for Systems/Evolutions not included for selection in the Outline Note 1: Cooper Nuclear Station does not have a Mark III containment and therefore this category is not applicable to Cooper.
Note 2: This category is not applicable to Cooper because Cooper does not have an isolation condenser.
Note 3: This category is not applicable to Cooper because Cooper does not have a HPCS system.
Note 4: Cooper no longer uses a RSCS.
Note 5: Cooper does not have a RCIS.
ES-401, Rev. 9 Record of Rejected K/As Form ES-401-4 Tier /
Group Randomly Selected K/A Reason for Rejection 1/1 SRO 295024.EA2.10 K/A is for containment Temperature Mark III containment. Cooper Nuclear Stations does not have a Mark III containment.
1/1/ SRO 295024.EA2.07 K/A is for containment radiation levels Mark III containment.
Cooper Nuclear Stations does not have a Mark III containment.
1/2/SRO 295002.G2.1.30 There is no applicability to 10CFR55.43(b) for 295002 Loss of condenser vacuum as it applies to 2.1.30 Ability to locate and operate components / including local controls.
2/1/RO 239002.K5.03 This K/A is not applicable because Cooper does not have acoustic monitors on the SRVs.
2/1/RO 261000.K2 No K2 with importance greater than 2.5 and no plant specific priority for any K2 in 261000. Reselected category randomly selected A2 as the category.
2/1/RO 264000.K2 No K2 with importance greater than 2.5 reselected randomly selected K6 as the category. Now that K6 is oversampled changed the category for 400000 CCW to K2.
2/2/RO 201006.K1.06 This K/A is not applicable to Cooper because cooper does not use a Rod Sequence Control System.
2/2/RO 215001.K4.02 Importance rating less than 2.5 with no plant specific priority.
2/2/RO 256000.K5.06 Importance rating less than 2.5 with no plant specific priority.
3/RO 2.2.5 Importance rating less than 2.5 with no plant specific priority.
3/RO 2.3.8 Importance rating less than 2.5 with no plant specific priority.
3/RO 2.3.3 Importance rating less than 2.5 with no plant specific priority.
3/RO 2.3.5 Importance rating less than 2.5 with no plant specific priority.
3/RO 2.4.33 Importance rating less than 2.5 with no plant specific priority.
1/1/RO 295005.AK1.03 Could not find in the bank and could not develop a test item with a difficulty level greater than one (1) that matches this K/A.
Randomly reselected K/A 295005.AK1.02 as replacement and developed a new question.
1/1/RO 295006.AK3.01 Could not find in the bank and could not develop a test item with a difficulty level greater than one (1) that matches this K/A.
Randomly reselected K/A 295005.AK3.01 as replacement and developed a new question.
1/1/RO 295016.AK3.02 Could not find in the bank and could not develop a test item with a difficulty level greater than one (1) that matches this K/A.
Randomly reselected K/A 295005.AK3.03 as replacement and developed a new question.
1/1/RO 295019.G2.1.33 There is no Technical Specification related to Instrument Air.
Randomly reselected Generic 2.1.27 as a replacement and selected a bank question.
1/2/RO 295035.G2.2.25 Could not find or develop a question that is applicable to 10CFR55.41 for 2.2.25 as it applies to 295035. Randomly selected 2.2.22 as replacement and developed a new question.
1/2/RO 295036.EK1.01 Could not find or develop a question that is applicable to this K/A that had a 10CFR50.41 component. Randomly selected 295036.EK3.1 for the replacement question.
ES-401, Rev. 9 Record of Rejected K/As Form ES-401-4 2/1/RO 205000.K1.12 Cooper has no isolation condenser. Randomly picked K1.09 as replacement but the importance rating is less than 2.5 and no plant specific priority. Randomly picked K1.01 as a replacement and developed a new question.
2/1/RO 206000.K3.03 Could not develop a question to this K/A as Cooper does not use HPCI for suppression pool level control. Randomly selected K3.02 as a replacement and developed a new question.
2/1/RO 261000.A2.15 There is no relationship between refuel bridge high radiation and SGT at Cooper. Randomly picked A2.07as a replacement and developed a new.
2/1/RO 263000.A4.03 Could not develop a psychometrically valid question with a difficulty greater than 1to this K/A randomly selected A4.01 as a replacement.
2/1/RO 300000.K4.01 Could find no automatic to manual transfer of control associated with IAS to test randomly picked K4.03 as a replacement and developed a new question.
2/2/RO 256000.K5.01 Could not find or develop an operationally significant test item for K5.01. Randomly selected K5.07 as a replacement and selected a test item from the bank.
2/2/RO 290001.A1.02 Cooper is a BWR 4 this K/A is applicable to BWR 6. Randomly selected A1.01 as a replacement and developed a new question.
2/2/RO 234000.K3.03 Could not develop a psychometrically valid question with a 10CFR50.41 component. Randomly selected K/A 234000.K4.02 and developed a question for an RO.
3/SRO 2.4.48 Could not develop a psychometrically valid question with a 10CFR50.43 component. Randomly selected K/A 2.4.30 and developed a question for an SRO.
1/1/RO 295038.EK3.04 Due to double jeopardy between questions 19 and 26, this K/A was rejected. Randomly selected 295031.EK2.13 as a replacement and selected a test item from the bank.