ML080870250

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2008-03-Draft Written Exam Outlines
ML080870250
Person / Time
Site: Cooper Entergy icon.png
Issue date: 03/21/2008
From: Ryan Lantz
Operations Branch IV
To:
Nebraska Public Power District (NPPD)
References
50-298/08-301
Download: ML080870250 (18)
v • d • e


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 K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

  • Total 3 4 4 3 3 3 20
1. 1 3 4 7 Emergency &

2 1 1 1 N/A 1 2 N/A 1 7 2 1 3 Abnormal Plant Evolutions Tier Totals 4 5 5 4 5 4 27 5 5 10 1 2 2 3 2 2 2 2 3 3 3 2 26 3 2 5 2.

Plant 2 1 1 1 1 2 1 1 1 1 1 1 12 1 2 3 Systems Tier Totals 3 3 4 3 4 3 3 4 4 4 3 38 4 4 8

3. Generic Knowledge and Abilities Categories 1 2 3 4 10 1 2 3 4 7 2 2 3 3 1 2 2 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).
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 K K A A G K/A Topic(s) IR #

1 2 3 1 2 AK2.01 Knowledge of the interrelations between 295001 Partial or Complete Loss of Forced Core PARTIAL OR COMPLETE LOSS OF FORCED CORE X 3.6 1 Flow Circulation / 1 & 4 FLOW CIRCULATION and the following: (CFR: 41.7 /

45.8) Recirculation system 2.1.32 Ability to explain and apply system limits and 295003 Partial or Complete Loss of AC / 6 3.4 2 X precautions. (CFR: 41.10 / 43.2 / 45.12) 3.4/ 3.8 AK1.03 Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR 295004 Partial or Total Loss of DC Pwr / 6 X 2.9 3 COMPLETE LOSS OF D.C. POWER : (CFR: 41.8 to 41.10) Electrical bus divisional separation AK1.02 Knowledge of the operational implications of the following concepts as they apply to MAIN TURBINE 295005 Main Turbine Generator Trip / 3 3.2 4 X GENERATOR TRIP : (CFR: 41.8 to 41.10) Core thermal limit considerations AA2.02 Ability to determine and/or interpret the 295006 SCRAM / 1 following as they apply to SCRAM : (CFR: 41.10 / 43.5 / 4.3 5 X

45.13)Control rod position AK3.06 Knowledge of the reasons for the following 295006 SCRAM / 1 responses as they apply to SCRAM : (CFR: 41.5 / 45.6) 3.2 6 X

Recirculation pump speed reduction: Plant-Specific....

AK3.03 Knowledge of the reasons for the following responses as they apply to CONTROL ROOM 295016 Control Room Abandonment / 7 3.5 7 X ABANDONMENT: (CFR: 41.5 / 45.6) Disabling control room controls AK1.01 Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR X

295018 Partial or Total Loss of CCW / 8 COMPLETE LOSS OF COMPONENT COOLING 3.5 8 WATER : (CFR: 41.8 to 41.10) Effects on component /

system operations 2.1.27 Knowledge of system purpose and or function.

295019 Partial or Total Loss of Inst. Air / 8 2.8 9 X (CFR: 41.7)

AK2.02 Knowledge of the interrelations between LOSS 295021 Loss of Shutdown Cooling / 4 X OF SHUTDOWN COOLING and the following: (CFR: 3.2 10 41.7 / 45.8) Reactor water cleanup AA1.06 Ability to operate and/or monitor the following X

295023 Refueling Acc / 8 as they apply to REFUELING ACCIDENTS : 3.3 11 (CFR: 41.7 / 45.6) Neutron monitoring EA2.02 Ability to determine and/or interpret the following as they apply to HIGH DRYWELL 295024 High Drywell Pressure / 5 3.9 12 X PRESSURE: (CFR: 41.10 / 43.5 / 45.13) Drywell temperature EA1.02 Ability to operate and/or monitor the following as 295025 High Reactor Pressure / 3 they apply to HIGH REACTOR PRESSURE: (CFR: 41.7 3.8 13 X

/ 45.6) Reactor/turbine pressure regulating system EK2.01 Knowledge of the interrelations between SUPPRESSION POOL HIGH WATER 295026 Suppression Pool High Water Temp. / 5 X 3.9 14 TEMPERATURE and the following: (CFR: 41.7 / 45.8)

Suppression pool cooling 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 K K A A G K/A Topic(s) IR #

1 2 3 1 2 EA2.05 Ability to determine and/or interpret the following as they apply to HIGH DRYWELL 295028 High Drywell Temperature / 5 3.6 15 X TEMPERATURE: (CFR: 41.10 / 43.5 / 45.13)

Torus/suppression chamber pressure: Plant-Specific EK1.01 Knowledge of the operational implications of the following concepts as they apply to LOW 295030 Low Suppression Pool Wtr Lvl / 5 3.8 16 X SUPPRESSION POOL WATER LEVEL: (CFR: 41.8 to 41.10) Steam condensation EK3.02 Knowledge of the reasons for the following 295031 Reactor Low Water Level / 2 responses as they apply to REACTOR LOW WATER 4.4 17 X

LEVEL : (CFR: 41.5 / 45.6) Core coverage 295037 SCRAM Condition Present and Power 2.1.30 Ability to locate and operate components /

3.9 18 Above APRM Downscale or Unknown / 1 X including local controls. (CFR: 41.7 / 45.7)

EK3.04 Knowledge of the reasons for the following X

295038 High Off-site Release Rate / 9 responses as they apply to HIGH OFF-SITE RELEASE 3.6 19 RATE: (CFR: 41.5 / 45.6) Emergency depressurization AK2.01 Knowledge of the interrelations between PLANT 600000 Plant Fire On Site / 8 FIRE ON SITE and the following: Sensors / detectors and 2.6 20 X

valves K/A Category Totals: 20 3 4 4 3 3 3 Group Point Total:

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 K K A A G K/A Topic(s) IR #

1 2 3 1 2 295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 AA2.04 Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE 295003 Partial or Complete Loss of AC / 6 X 3.7 76 LOSS OF A.C. POWER : (CFR: 41.10 / 43.5 / 45.13)

System Lineups 295004 Partial or Total Loss of DC Pwr / 6 295005 Main Turbine Generator Trip / 3 AA2.02 Ability to determine and/or interpret the 295006 SCRAM / 1 X following as they apply to SCRAM : (CFR: 41.10 / 43.5 / 4.4 77 45.13) Control Rod Position 2.4.6 Knowledge symptom based EOP mitigation 295006 SCRAM / 1 X 4.0 78 strategies. (CFR: 41.10 / 43.5 / 45.13) 295016 Control Room Abandonment / 7 295018 Partial or Total Loss of CCW / 8 2.4.4 Ability to recognize abnormal indications for system operating parameters which are entry conditions 295019 Partial or Total Loss of Inst. Air / 8 X 4.3 79 for emergency and abnormal operating procedures. (CFR:

41.10 / 43.2 / 45.6) 295021 Loss of Shutdown Cooling / 4 295023 Refueling Acc / 8 EA2.03 Ability to determine and/or interpret the following as they apply to HIGH DRYWELL 295024 High Drywell Pressure / 5 X 3.8 80 PRESSURE:

(CFR: 41.10 / 43.5 / 45.13) Suppression pool level 295025 High Reactor Pressure / 3 G2.1.32 Ability to explain and apply system limits and 295026 Suppression Pool High Water Temp. / 5 X 3.8 81 precautions.(CFR: 41.10 / 43.2 / 45.12) 295027 High Containment Temperature / 5 2.4.30 Knowledge of which events related to system 295028 High Drywell Temperature / 5 X operations/status should be reported to outside agencies. 3.6 82 (CFR: 43.5 / 45.11) 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 K K A A G K/A Topic(s) IR #

1 2 3 1 2 AA2.02 Ability to determine and/or interpret the following as they apply to LOSS OF MAIN CONDENSER 295002 Loss of Main Condenser Vac / 3 X 3.2 21 VACUUM: (CFR: 41.10 / 43.5 / 45.13) Reactor power:

Plant-Specific 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 AK3.02 Knowledge of the reasons for the following 295014 Inadvertent Reactivity Addition / 1 X responses as they apply to INADVERTENT REACTIVITY 3.7 22 ADDITION: (CFR: 41.5 / 45.6) Control rod blocks 295015 Incomplete SCRAM / 1 295017 High Off-site Release Rate / 9 AK2.06 Knowledge of the interrelations between 295020 Inadvertent Cont. Isolation / 5 & 7 X INADVERTENT CONTAINMENT ISOLATION and the 3.8 23 following: (CFR: 41.7 / 45.8) HPCI: Plant-Specific 295022 Loss of CRD Pumps / 1 EA1.01 Ability to operate and/or monitor the following as 295029 High Suppression Pool Wtr Lvl / 5 X they apply to HIGH SUPPRESSION POOL WATER 3.4 24 LEVEL: (CFR: 41.7 / 45.6) HPCI: Plant-Specific 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 G2.2.22 Knowledge of limiting conditions for operations X 3.4 25 Differential Pressure / 5 and safety limits. (CFR: 43.2 / 45.2)

EK1.01 Knowledge of the operational implications of the 295036 Secondary Containment High following concepts as they apply to SECONDARY X 2.9 26 Sump/Area Water Level / 5 CONTAINMENT HIGH SUMP/AREA WATER LEVEL :

(CFR: 41.8 to 41.10) Radiation releases EA2.04 Ability to determine and / or interpret the following as they apply to HIGH PRIMARY CONTAINMENT 500000 High CTMT Hydrogen Conc. / 5 X 3.3 27 HYDROGEN CONCENTRATIONS:

(CFR: 41.10 / 43.5 / 45.13) Combustible limits for wetwell 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 K K A A G K/A Topic(s) IR #

1 2 3 1 2 2.1.32 Ability to explain and apply system limits and 295002 Loss of Main Condenser Vac / 3 X 3.8 83 precautions. (CFR: 41.10 / 43.2 / 45.12) 295007 High Reactor Pressure / 3 295008 High Reactor Water Level / 2 AA2.01 Ability to determine and/or interpret the following 295009 Low Reactor Water Level / 2 X as they apply to LOW REACTOR WATER LEVEL: 4.2 84 (CFR: 41.10 / 43.5 / 45.13) Reactor water level AA2.01 Ability to determine and/or interpret the following 295010 High Drywell Pressure / 5 X as they apply to HIGH DRYWELL PRESSURE : 3.8 85 (CFR: 41.10 / 43.5 / 45.13) Leak rates 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 K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 K6.09 Knowledge of the effect that a loss or malfunction of the following will have on the 203000 RHR/LPCI: Injection RHR/LPCI: INJECTION MODE (PLANT 3.4 28 Mode X SPECIFIC) : (CFR: 41.7 / 45.7) Nuclear boiler instrumentation K1.01 Knowledge of the physical connections and/or cause-effect relationships between SHUTDOWN X

205000 Shutdown Cooling COOLING SYSTEM (RHR SHUTDOWN 3.6 29 COOLING MODE) and the following: (CFR: 41.2 to 41.9 / 45.7 to 45.8) Reactor Pressure K3.02 Knowledge of the effect that a loss or malfunction of the HIGH PRESSURE COOLANT 206000 HPCI INJECTION SYSTEM will have on following: 3.8 30 X

(CFR: 41.7 / 45.4) reactor pressure control: BWR-2,3,4 207000 Isolation (Emergency)

Condenser Note 2 A1.05 Ability to predict and/or monitor changes in parameters associated with operating the LOW X

209001 LPCS PRESSURE CORE SPRAY SYSTEM controls 3.5 31 including: (CFR: 41.5 / 45.5) Torus/suppression pool water level Note 3 209002 HPCS A3.01 Ability to monitor automatic operations of the STANDBY LIQUID CONTROL SYSTEM 211000 SLC 3.5 32 X including: (CFR: 41.7 / 45.7) Pump discharge pressure: Plant-Specific A1.04 Ability to predict and/or monitor changes in parameters associated with operating the STANDBY 211000 SLC X 3.6 33 LIQUID CONTROL SYSTEM controls including:

(CFR: 41.5 / 45.5) Valve operations G2.1.23 Ability to perform specific system and 212000 RPS integrated plant procedures during different modes of 3.9 34 X

plant operation. (CFR: 45.2 / 45.6)3.9/ 4.0 K5.01 Knowledge of the operational implications of the following concepts as they apply to 215003 IRM 2.6 35 X INTERMEDIATE RANGE MONITOR (IRM)

SYSTEM : (CFR: 41.5 / 45.3) Detector operation 2.4.49 Ability to perform without reference to X procedures those actions that require immediate 215004 Source Range Monitor 4.0 36 operation of system components and controls.

(CFR: 41.10 / 43.2 / 45.6)

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 K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 A2.05 Ability to (a) predict the impacts of the following on the SOURCE RANGE MONITOR (SRM) SYSTEM ; and (b) based on those 215004 Source Range Monitor X predictions, use procedures to correct, control, or 3.3 37 mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 / 45.6) Faulty or erratic operation of detectors/system A3.07 Ability to monitor automatic operations of the AVERAGE POWER RANGE MONITOR/LOCAL 215005 APRM / LPRM 3.8 38 X POWER RANGE MONITOR SYSTEM including:

(CFR: 41.7 / 45.7) RPS status K3.04 Knowledge of the effect that a loss or malfunction of the REACTOR CORE ISOLATION 217000 RCIC X 3.6 39 COOLING SYSTEM (RCIC) will have on following:

(CFR: 41.7 / 45.4) Adequate core cooling A4.10 Ability to manually operate and/or monitor in 217000 RCIC the control room: (CFR: 41.7 / 45.5 to 45.8) 3.6 40 X

Lights and alarms K1.02 Knowledge of the physical connections and/or cause-effect relationships between AUTOMATIC 218000 ADS X DEPRESSURIZATION SYSTEM and the following: 4.0 41 (CFR: 41.2 to 41.9 / 45.7 to 45.8) Low pressure core spray: Plant-Specific A4.10 Ability to manually operate and/or monitor in X

218000 ADS the control room: (CFR: 41.7 / 45.5 to 45.8) Lights 3.8 42 and alarms K3.16 Knowledge of the effect that a loss or malfunction of the PRIMARY CONTAINMENT 223002 PCIS/Nuclear Steam ISOLATION SYSTEM/NUCLEAR STEAM 3.2 43 Supply Shutoff X SUPPLY SHUT-OFF will have on following:

(CFR: 41.7 / 45.4) Shutdown cooling system/RHR A3.01 Ability to monitor automatic operations of the PRIMARY CONTAINMENT ISOLATION 223002 PCIS/Nuclear Steam X SYSTEM/NUCLEAR STEAM SUPPLY 3.4 44 Supply Shutoff SHUT-OFF including: (CFR: 41.7 / 45.7)

System indicating lights and alarms K5.06 Knowledge of the operational implications of X the following concepts as they apply to 239002 SRVs 2.7 45 RELIEF/SAFETY VALVES : (CFR: 41.5 / 45.3)

Vacuum breaker operation A2.01 Ability to (a) predict the impacts of the following on the REACTOR WATER LEVEL CONTROL SYSTEM ; and (b) based on those 259002 Reactor Water Level predictions, use procedures to correct, control, or 3.3 46 Control X mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 / 45.6)

Loss of any number of main steam flow inputs

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 K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 A2.04 Ability to (a) predict the impacts of the following on the STANDBY GAS TREATMENT SYSTEM ; and (b) based on those predictions, use 261000 SGTS procedures to correct, control, or mitigate the 2.5 47 X

consequences of those abnormal conditions or operations: (CFR: 41.5 / 45.6) High Train Moisture Content K2.01 Knowledge of electrical power supplies to the 262001 AC Electrical Distribution 3.3 48 X following: (CFR: 41.7) Off-site sources of power K4.01 Knowledge of UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) design feature(s) 262002 UPS (AC/DC) and/or interlocks which provide for the following: 3.1 49 X

(CFR: 41.7) Transfer from preferred power to alternate power supplies A4.01 Ability to manually operate and/or monitor in the control room: (CFR: 41.7 / 45.5 to 45.8) 263000 DC Electrical Distribution 3.3 50 X Major breakers and control power fuses: Plant-Specific K6.09 Knowledge of the effect that a loss or malfunction of the following will have on the 264000 EDGs 3.3 51 X EMERGENCY GENERATORS (DIESEL/JET) :

(CFR: 41.7 / 45.7) D.C. power K4.03 Knowledge of (INSTRUMENT AIR SYSTEM) design feature(s) and or interlocks which 300000 Instrument Air 2.8 52 X provide for the following: (CFR: 41.7) Securing of IAS upon loss of cooling water K2.02 Knowledge of electrical power supplies to the 400000 Component Cooling Water 2.9 53 X following: (CFR: 41.7) CCW valves 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 K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 203000 RHR/LPCI: Injection Mode 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 205000 Shutdown Cooling X 2.7 86 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 206000 HPCI 207000 Isolation (Emergency)

Note 2 Condenser 209001 LPCS 209002 HPCS Note 3 211000 SLC 212000 RPS 215003 IRM 215004 Source Range Monitor G2.1.2 Knowledge of operator responsibilities 215005 APRM / LPRM during all modes of plant operation. 4.0 87 X

(CFR: 41.10 / 45.13) 217000 RCIC 2.4.4 Ability to recognize abnormal indications for system operating parameters which are entry-level 218000 ADS 4.3 88 X conditions for emergency and abnormal operating procedures. (CFR: 41.10 / 43.2 / 45.6) 223002 PCIS/Nuclear Steam Supply Shutoff A2.04 Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES ;

and (b) based on those predictions, use procedures 239002 SRVs 4.2 89 X to correct, control, or mitigate the consequences of those abnormal conditions or operations:

(CFR: 41.5 / 45.6) ADS actuation 259002 Reactor Water Level Control 261000 SGTS 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, 262001 AC Electrical Distribution 4.2 90 X 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 262002 UPS (AC/DC) 263000 DC Electrical Distribution 264000 EDGs 300000 Instrument Air 400000 Component Cooling Water K/A Category Point Totals: 5 3 2 Group Point Total:

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 K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 201001 CRD Hydraulic 201002 RMCS A2.07 Ability to (a) predict the impacts of the following on the CONTROL ROD AND DRIVE MECHANISM ; and (b) based on 201003 Control Rod and Drive those predictions, use procedures to correct, 3.1 54 Mechanism X control, or mitigate the consequences of those abnormal conditions or operations:

(CFR:41.5/45.6) Loss of CRD drive water flow 201004 RSCS Note 4 201005 RCIS Note 5 K1.08 Knowledge of the physical connections and/or cause-effect relationships between ROD X WORTH MINIMIZER SYSTEM (RWM) 201006 RWM 3.2 55 (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) 202001 Recirculation 202002 Recirculation Flow Control 204000 RWCU 214000 RPIS K4.01 Knowledge of TRAVERSING IN-CORE PROBE design feature(s) and/or interlocks which 215001 Traversing In-core Probe 3.4 56 X provide for the following: (CFR: 41.7) Primary containment isolation: Mark-I&II(Not-BWR1) 215002 RBM 216000 Nuclear Boiler Inst.

219000 RHR/LPCI: Torus/Pool K2.02 Knowledge of electrical power supplies 57 Cooling Mode X to the following: (CFR: 41.7) Pumps 3.1 223001 Primary CTMT and Aux.

G2.1.30 Ability to locate and operate 226001 RHR/LPCI: CTMT Spray X components / including local controls. 58 Mode 3.9 (CFR: 41.7 / 45.7) 230000 RHR/LPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup K3.03 Knowledge of the effect that a loss or malfunction of the FUEL HANDLING 234000 Fuel Handling Equipment 59 X EQUIPMENT will have on following: 3.1 (CFR: 41.7 / 45.4) Fuel handling operations 239001 Main and Reheat Steam 239003 MSIV Leakage Control A3.08 Ability to monitor automatic operations 241000 Reactor/Turbine Pressure of the REACTOR/TURBINE PRESSURE 3.8 60 Regulator X REGULATING SYSTEM including: (CFR:

41.7 / 45.7) Steam bypass valve operation 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 K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 K5.07 Knowledge of the operational implications of the following concepts as they X

256000 Reactor Condensate apply to REACTOR CONDENSATE 2.7 61 SYSTEM : (CFR: 41.5 / 45.3) Level controller operation K6.09 Knowledge of the effect that a loss or malfunction of the following will have on the 259001 Reactor Feedwater REACTOR FEEDWATER SYSTEM : 2.8 62 X

(CFR: 41.7 / 45.7) Reactor feedwater pump lube oil system 268000 Radwaste A4.02 Ability to manually operate and/or 271000 Offgas monitor in the control room: 2.9 63 X

(CFR: 41.7 / 45.5 to 45.8) System flows 272000 Radiation Monitoring 286000 Fire Protection 288000 Plant Ventilation A1.01 Ability to predict and/or monitor changes in parameters associated with operating the 290001 Secondary CTMT SECONDARY 3.1 64 X

CONTAINMENT controls including:

(CFR: 41.5 / 45.5) System lineups 290003 Control Room HVAC K5.03 Knowledge of the operational implications of the following concepts as they 290002 Reactor Vessel Internals 2.7 65 X apply to REACTOR VESSEL INTERNALS :

(CFR: 41.5 / 45.3) Burnable poisons 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 K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 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 G2.2.22 Knowledge of limiting conditions 216000 Nuclear Boiler Inst. X for operations and safety limits. (CFR: 43.2 / 4.1 91 45.2) 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 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, 239001 Main and Reheat Steam 4.2 92 X control, or mitigate the consequences of those abnormal conditions or operations:

(CFR: 41.5 / 45.6) Main steam line high radiation 239003 MSIV Leakage Control 241000 Reactor/Turbine Pressure Regulator 245000 Main Turbine Gen. / Aux.

256000 Reactor Condensate 2.4.49 Ability to perform without reference to procedures those actions that require 259001 Reactor Feedwater 4.0 93 X immediate operation of system components and controls. (CFR: 41.10 / 43.2 / 45.6)

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 K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 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:

Category K/A # Topic RO SRO-Only IR # IR #

2.1.27 Knowledge of system purpose and or function. (CFR: 41.7) 2.8 66 Knowledge of conduct of operations requirements.

2.1.1 3.7 67

1. Conduct (CFR: 41.10 / 45.13) of Operations Ability to explain and apply system limits and precautions.

2.1.32 3.8 94 (CFR: 41.10 / 43.2 / 45.12)

Subtotal 2 1 2.2.23 Ability to track limiting conditions for operations. (CFR: 43.2 / 45.13) 2.6 68 Ability to analyze the affect of maintenance activities on LCO status.

2.2.24 2.6 69 (CFR: 43.2 / 45.13)

Knowledge of the process for determining if the proposed change / test or experiment increases the probability of occurrence or consequences

2. Equipment Control 2.2.9 3.3 95 of an accident during the change / test or experiment. (CFR: 43.3 /

45.13)

Knowledge of refueling administrative requirements.

2.2.26 3.7 96 (CFR: 43.5 / 45.13)

Subtotal 2 2 Knowledge of facility ALARA program.

2.3.2 2.5 70 (CFR: 41.12 / 43.4 / 45.9 / 45.10) 2.3.11 Ability to control radiation releases. (CFR: 45.9 / 45.10) 2.7 71 Ability to perform procedures to reduce excessive levels of radiation 2.3.10 2.9 72 and guard against personnel exposure. (CFR: 43.4 / 45.10)

3. Radiation Control Knowledge of the process for performing a planned gaseous 2.3.8 3.2 97 radioactive release. (CFR: 43.4 / 45.10)

Knowledge of 10 CFR: 20 and related facility radiation control 2.3.1 3.0 98 requirements. (CFR: 41.12 / 43.4. 45.9 / 45.10)

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 Ability to interpret control room indications to verify the status and

4. Emergency 2.4.48 operation of system / and understand how operator action s and 3.8 99 Procedures / Plan directives affect plant and system conditions. (CFR: 43.5 / 45.12)

Knowledge of low power / shutdown implications in accident (e.g.

2.4.9 LOCA or loss of RHR) mitigation strategies. 3.9 100 (CFR: 41.10 / 43.5 / 45.13)

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 / Randomly Selected Reason for Rejection Group K/A K/A is for containment Temperature Mark III containment. Cooper 1/1 SRO 295024.EA2.10 Nuclear Stations does not have a Mark III containment.

K/A is for containment radiation levels Mark III containment.

1/1/ SRO 295024.EA2.07 Cooper Nuclear Stations does not have a Mark III containment.

There is no applicability to 10CFR55.43(b) for 295002 Loss of 1/2/SRO 295002.G2.1.30 condenser vacuum as it applies to 2.1.30 Ability to locate and operate components / including local controls.

This K/A is not applicable because Cooper does not have acoustic 2/1/RO 239002.K5.03 monitors on the SRVs.

No K2 with importance greater than 2.5 and no plant specific 2/1/RO 261000.K2 priority for any K2 in 261000. Reselected category randomly selected A2 as the category.

No K2 with importance greater than 2.5 reselected randomly 2/1/RO 264000.K2 selected K6 as the category. Now that K6 is oversampled changed the category for 400000 CCW to K2.

This K/A is not applicable to Cooper because cooper does not use a 2/2/RO 201006.K1.06 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.

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.

1/1/RO 295005.AK1.03 Randomly reselected K/A 295005.AK1.02 as replacement and developed a new question.

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.

1/1/RO 295006.AK3.01 Randomly reselected K/A 295005.AK3.01 as replacement and developed a new question.

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.

1/1/RO 295016.AK3.02 Randomly reselected K/A 295005.AK3.03 as replacement and developed a new question.

There is no Technical Specification related to Instrument Air.

1/1/RO 295019.G2.1.33 Randomly reselected Generic 2.1.27 as a replacement and selected a bank question.

Could not find or develop a question that is applicable to 1/2/RO 295035.G2.2.25 10CFR55.41 for 2.2.25 as it applies to 295035. Randomly selected 2.2.22 as replacement and developed a new question.

Cooper has no isolation condenser. Randomly picked K1.09 as 2/1/RO 205000.K1.12 replacement but the importance rating is less than 2.5 and no plant specific priority. Randomly picked K1.01 as a replacement and

ES-401, Rev. 9 Record of Rejected K/As Form ES-401-4 developed a new question.

Could not develop a question to this K/A as Cooper does not use 2/1/RO 206000.K3.03 HPCI for suppression pool level control. Randomly selected K3.02 as a replacement and developed a new question.

There is no relationship between refuel bridge high radiation and 2/1/RO 261000.A2.15 SGT at Cooper. Randomly picked A2.07as a replacement and developed a new.

Could not develop a psychometrically valid question with a 2/1/RO 263000.A4.03 difficulty greater than 1to this K/A randomly selected A4.01 as a replacement.

Could find no automatic to manual transfer of control associated 2/1/RO 300000.K4.01 with IAS to test randomly picked K4.03 as a replacement and developed a new question.

Could not find or develop an operationally significant test item for 2/2/RO 256000.K5.01 K5.01. Randomly selected K5.07 as a replacement and selected a test item from the bank.

Cooper is a BWR 4 this K/A is applicable to BWR 6. Randomly 2/2/RO 290001.A1.02 selected A1.01 as a replacement and developed a new question.

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