ML15049A418

2015-02-Draft-Outlines

ML15049A418
Person / Time
Site:	Cooper
Issue date:	01/27/2015
From:	Vincent Gaddy Operations Branch IV
To:	Nebraska Public Power District (NPPD)
References
50-298/15-002
Download: ML15049A418 (16)

Text

ES-401 BWR Examination Outline Form ES-401-1 Facility: Cooper Nuclear Station Date of Exam: February 16, 2015 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

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

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

Plant 2 1 1 1 1 1 1 1 1 2 1 1 12 0 1 2 3 Systems Tier Totals 4 3 3 3 3 3 3 3 5 4 4 38 4 4 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 2 3 2 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).

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/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.

4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.

5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher 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. Refer to Section D.1.b of ES-401 for the applicable K/As.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics 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.

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.

Revision 2

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)

E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR #

1 2 3 1 2 Knowledge of the reasons for the following responses 295001 Partial or Complete Loss of Forced X as they apply to partial or complete loss of forced core 3.4 1 Core Flow Circulation / 1 & 4 flow circulation:

(CFR: 41.5 / 45.6)

AK3.04 Reactor SCRAM Ability to operate and/or monitor the following as they 295003 Partial or Complete Loss of AC / 6 X apply to partial or complete loss of A.C. power: 4.3 2 (CFR: 41.7 / 45.6)

AA1.03 Systems necessary to assure safe plant shutdown Ability to determine and/or interpret the following as 295004 Partial or Total Loss of DC Pwr / 6 X they apply to partial or complete loss of D.C. power: 3.2 3 (CFR: 41.10 / 43.5 / 45.13)

AA2.01 Cause of partial or complete loss of D.C. power 2.1.23 Ability to perform specific system and integrated 295005 Main Turbine Generator Trip / 3 X plant procedures during all modes of plant operation. 4.3 4 (CFR: 41.10 / 43.5 / 45.2 / 45.6)

Knowledge of the operational implications of the 295006 SCRAM / 1 X following concepts as they apply to SCRAM : 3.7 5 (CFR: 41.8 to 41.10)

AK1.01 Decay heat generation and removal Knowledge of the interrelations between control room 295016 Control Room Abandonment / 7 X abandonment and the following: 2.9 6 (CFR: 41.7 / 45.8)

AK2.03 Control room HVAC 4.4 AK2.01 Remote shutdown panel: Plant-Specific Knowledge of the reasons for the following responses 295018 Partial or Total Loss of CCW / 8 X as they apply to partial or complete loss of component 3.1 7 cooling water:

(CFR: 41.5 / 45.6)

AK3.03 Securing individual components (prevent equipment damage)

Ability to operate and/or monitor the following as they 295019 Partial or Total Loss of Inst. Air / 8 X apply to partial or complete loss of instrument air: 3.3 8 (CFR: 41.7 / 45.6)

AA1.02 Instrument air system valves: Plant-Specific Ability to determine and/or interpret the following as they 295021 Loss of Shutdown Cooling / 4 X apply to loss of shutdown cooling: 2.9 9 (CFR: 41.10 / 43.5 / 45.13)

AA2.07 Reactor recirculation flow 2.2.40 Ability to apply Technical Specifications for a 295023 Refueling Acc / 8 X system. 3.4 10 (CFR: 41.10 / 43.2 / 43.5 / 45.3) 2.4.30 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 operator.

(CFR: 41.10 / 43.5 / 45.11 Revision 2

Knowledge of the operational implications of the 295024 High Drywell Pressure / 5 X following concepts as they apply to high drywell 4.1 11 pressure:

(CFR: 41.8 to 41.10)

EK1.01 Drywell integrity: Plant-Specific Knowledge of the interrelations between high reactor 295025 High Reactor Pressure / 3 X pressure and the following: 3.7 12 (CFR: 41.7 / 45.8)

EK2.07 RCIC: Plant-Specific Knowledge of the reasons for the following responses as 295026 Suppression Pool High Water X they apply to suppression pool high water temperature: 3.9 13 Temp. / 5 (CFR: 41.5 / 45.6)

EK3.05 Reactor SCRAM Ability to operate and/or monitor the following as they 295028 High Drywell Temperature / 5 X apply to high drywell temperature: 3.8 14 (CFR: 41.7 / 45.6)

EA1.01 Drywell spray: Mark-I&II Ability to determine and/or interpret the following as 295030 Low Suppression Pool Wtr Lvl / 5 X they apply to low suppression pool water level: 3.9 15 (CFR: 41.10 / 43.5 / 45.13)

EA2.02 Suppression pool temperature 2.4.2 Knowledge of system set points, interlocks and 295031 Reactor Low Water Level / 2 X automatic actions associated with EOP entry conditions. 4.5 16 (CFR: 41.7 / 45.7 / 45.8)

Knowledge of the operational implications of the 295037 SCRAM Condition Present X following concepts as they apply to scram condition 3.4 17 and Reactor Power Above APRM present and reactor power above APRM downscale or Downscale or Unknown / 1 unknown:

(CFR: 41.8 to 41.10)

EK1.05 Cold shutdown boron weight: Plant-Specific Knowledge of the interrelations between high off-site 295038 High Off-site Release Rate / 9 X release rate and the following: 3.6 18 (CFR: 41.7 / 45.8)

EK2.02 Offgas system Knowledge of the reasons for the following responses 600000 Plant Fire On Site / 8 X as they apply to plant fire on site: 2.8 19 AK3.04 Actions contained in the abnormal procedure for plant fire on site Ability to operate and/or monitor the following as they 700000 Generator Voltage and Electric Grid X apply to generator voltage and electric grid disturbances: 3.6 20 Disturbances / 6 (CFR: 41.5 and 41.10 / 45.5, 45.7, and 45.8 )

AA1.01 Grid frequency and voltage K/A Category Totals: 3 3 4 4 3 3 Group Point Total: 20 Revision 2

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)

E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR #

1 2 3 1 2 2.4.50 Ability to verify system alarm setpoints and operate 295002 Loss of Main Condenser Vac / 3 X controls identified in l the alarm response manual. 4.2 21 (CFR: 41.10 / 43.5 / 45.3)

Knowledge of the operational implications of the following 295013 High Suppression Pool Temp. / 5 X concepts as they apply to high suppression pool 3.0 22 temperature:

(CFR: 41.8 to 41.10)

AK1.03 Localized heating Knowledge of the interrelations between loss of CRD 295022 Loss of CRD Pumps / 1 X pumps and the following: 3.1 23 (CFR: 41.7 / 45.8)

AK2.02 CRD mechanism Knowledge of the reasons for the following responses as 295033 High Secondary Containment X they apply to high secondary containment area radiation 3.5 24 Area Radiation Levels / 9 levels:

(CFR: 41.5 / 45.6)

EK3.02 Reactor SCRAM Ability to operate and/or monitor the following as they 295034 Secondary Containment X apply to secondary containment ventilation high radiation: 4.0 25 Ventilation High Radiation / 9 (CFR: 41.7 / 45.6)

EA1.03 Secondary containment ventilation Ability to determine and/or interpret the following as they 295035 Secondary Containment High X apply to secondary containment high differential pressure: 2.8 26 Differential Pressure / 5 (CFR: 41.8 to 41.10)

EA2.02 Off-site release rate: Plant-Specific 2.4.31 Knowledge of annunciator alarms, indications, or 500000 High CTMT Hydrogen Conc. / 5 X response procedures. 4.2 27 (CFR: 41.10 / 45.3) 2.4.21 Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core 4.0 cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

(CFR: 41.7 / 43.5 / 45.12)

K/A Category Point Totals: 1 1 1 1 1 2 Group Point Total: 7 Revision 2

ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form 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 Ability to monitor automatic operations of the 203000 RHR/LPCI: Injection X RHR/LPCI: injection mode (plant specific) 3.7 28 Mode including:

(CFR: 41.7 / 45.7)

A3.03 Pump discharge pressure Ability to manually operate and/or monitor in the 205000 Shutdown Cooling X control room: 3.7 29 (CFR: 41.7 / 45.5 to 45.8)

A4.07 Reactor temperatures (moderator, vessel, flange) 2.2.25 Knowledge of the bases in Technical 206000 HPCI X Specifications for limiting conditions for 3.2 30 operations and safety limits.

(CFR: 41.5 / 41.7 / 43.2) 2.2.39 Knowledge of less than or equal to one 3.9 hour1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> Technical Specification action statements for systems.

(CFR: 41.7 / 41.10 / 43.2 / 45.13)

Knowledge of the physical connections and/or 209001 LPCS X cause-effect relationships between low pressure 3.1 31 core spray system and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Condensate storage tank: Plant-Specific Knowledge of the effect that a loss or malfunction 209002 HPCS X of the high pressure core spray system (HPCS) 3.3 32 will have on following:

259002 Reactor Water Level (CFR: 41.7 / 45.4)

Control K3.02 Standby liquid control system: Plant-Specific Knowledge of the effect that a loss or malfunction 3.7 of the REACTOR WATER LEVEL CONTROL SYSTEM will have on following (CFR: 41.7 / 45.4)

(CFR: 41.7 / 45.5 to 45.8)

K3.02 Reactor feedwater system Knowledge of electrical power supplies to the 211000 SLC X following: 3.1 33 (CFR: 41.7)

K2.02 Explosive valves Knowledge of reactor protection system design 212000 RPS X feature(s) and/or interlocks which provide for the 3.5 34 following:

(CFR: 41.7)

K4.02 The prevention of a reactor SCRAM following a single component failure Knowledge of the operational implications of the 215003 IRM X following concepts as they apply to intermediate 2.6 35 range monitor (IRM) system:

(CFR: 41.5 / 45.3)

K5.01 Detector operation Revision 2

Knowledge of the effect that a loss or malfunction 215004 Source Range Monitor X of the following will have on the source range 3.2 36 monitor (SRH) system :

(CFR: 41.7 / 45.7)

K6.01 RPS Ability to predict and/or monitor changes in 215005 APRM / LPRM X parameters associated with operating the average 3.6 37 power range monitor/local power range monitor system controls including:

(CFR: 41.5 / 45.5)

A1.03 Control rod block status Ability to (a) predict the impacts of the following 217000 RCIC X on the reactor core isolation cooling system 3.5 38 (RCIC) ; 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)

A2.16 Low condensate storage tank level Ability to monitor automatic operations of the 218000 ADS X automatic depressurization system including: 3.6 39 (CFR: 41.7 / 45.7)

A3.02 ADS valve tail pipe temperatures Ability to manually operate and/or monitor in the 223002 PCIS/Nuclear Steam X control room: 3.6 40 Supply Shutoff (CFR: 41.7 / 45.5 to 45.8)

A4.06 Confirm initiation to completion 2.1.30 Ability to locate and operate components, 239002 SRVs X including local controls. 4.4 41 (CFR: 41.7 / 45.7) 2.2.12 Knowledge of surveillance procedures. 3.7 (CFR: 41.10 / 45.13)

Knowledge of the physical connections and/or 259002 Reactor Water Level X cause-effect relationships between reactor water 2.6 42 Control level control system and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.07 Rod worth minimizer: Plant-Specific Knowledge of the effect that a loss or malfunction 261000 SGTS X of the standby gas treatment system will have on 3.6 43 following:

(CFR: 41.7 /45.6)

K3.02 Off-site release rate Knowledge of electrical power supplies to the 262001 AC Electrical X following: 3.3 44 Distribution (CFR: 41.7)

K2.01 Off-site sources of power Knowledge of uninterruptable power supply 262002 UPS (AC/DC) X (A.C./D.C.) design feature(s) and/or interlocks 3.1 45 which provide for the following:

(CFR: 41.7)

K4.01 Transfer from preferred power to alternate power supplies Knowledge of the operational implications of the 263000 DC Electrical X following concepts as they apply to D.C. electrical 2.6 46 Distribution distribution:

(CFR: 41.5 / 45.3)

K5.01 Hydrogen generation during battery charging Revision 2

Knowledge of the effect that a loss or malfunction 264000 EDGs X of the following will have on the emergency 3.5 47 generators (diesel/jet):

(CFR: 41.7 / 45.7)

K6.03 Lube oil pumps Ability to monitor automatic operations of the 300000 Instrument Air X instrument air system including: 2.9 48 (CFR: 41.7 / 45.7)

A3.02 Air temperature Ability to (a) predict the impacts of the following 400000 Component Cooling X on the CCWS and (b) based on those predictions, 3.3 49 Water use procedures to correct, control, or mitigate the consequences of those abnormal operation:

(CFR: 41.5 / 45.6)

A2.01 Loss of CCW pump Ability to predict and/or monitor changes in 211000 SLC X parameters associated with operating the standby 4.3 50 liquid control system controls including:

(CFR: 41.5 / 45.5)

A1.07 Reactor power Ability to manually operate and/or monitor in the 215003 IRM X control room: 3.6 51 (CFR: 41.7 / 45.5 to 45.8)

A4.03 IRM range switches 2.4.3 Ability to identify post-accident 215004 Source Range Monitor X instrumentation. 3.7 52 (CFR: 41.6 / 45.4)

Knowledge of the physical connections and/or 217000 RCIC X cause-effect relationships between reactor core 3.3 53 isolation cooling system (RCIC) and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8) 3.1 K1.08 Line fill pump: Plant-Specific K1.07 Leak Detection K/A Category Point Totals: 3 2 2 2 2 2 2 2 3 3 3 Group Point Total: 26 Revision 2

ES-401 5 Form ES-401-1 ES-401 BWR Examination Outline Form 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 Ability to monitor automatic operations of the 201001 CRD Hydraulic X control rod drive hydraulic system including: 3.0 54 (CFR: 41.7 / 45.7)

A3.08 Drive water flow Ability to manually operate and/or monitor in the 201006 RWM X control room: 3.3 55 (CFR: 41.7 / 45.5 to 45.8)

A4.04 Rod withdrawal error indication 2.2.36 Ability to analyze the effect of maintenance 202001 Recirculation X activities, such as degraded power sources, on the 3.1 56 status of limiting conditions for operations.

(CFR: 41.10 / 43.2 / 45.13) 2.1.28 Knowledge of the purpose and function of 41 major system components and controls.

(CFR: 41.7)

Knowledge of the physical connections and/or 204000 RWCU X cause-effect relationships between reactor water 3.1 57 cleanup system and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.03 Reactor feedwater system Knowledge of electrical power supplies to the 216000 Nuclear Boiler Inst. X following: 2.8 58 (CFR: 41.7)

K2.01 Analog trip system: Plant-Specific Knowledge of the effect that a loss or malfunction 226001 RHR/LPCI: CTMT Spray Mode X of the RHR/LPCI: containment spray system mode 3.5 59 will have on following:

(CFR: 41.7 / 45.4)

K3.02 Containment/drywell/suppression chamber temperature Knowledge of RHR/LPCI: torus/suppression pool 230000 RHR/LPCI: Torus/Pool Spray X spray mode design feature(s) and/or interlocks 2.8 60 Mode which provide for the following:

(CFR: 41.7)

K4.05 Pump minimum flow protection Knowledge of the operational Implications of the 241000 Reactor/Turbine Pressure X following concepts as they apply to reactor/turbine 3.3 61 Regulator pressure regulating system :

(CFR: 41.5 / 45.3)

K5.04 Turbine inlet pressure vs. reactor pressure Knowledge of the effect that a loss or malfunction 259001 Reactor Feedwater X of the following will have on the reactor feedwater 2.8 62 system :

(CFR: 41.7 / 45.7)

K6.04 Extraction steam Ability to predict and/or monitor changes in 268000 Radwaste X parameters associated with operating the radwaste 2.6 63 controls including:

(CFR: 41.5 / 45.5)

A1.02 Off-site release Ability to (a) predict the impacts of the following 272000 Radiation Monitoring X on the radiation monitoring system; and (b) based 2.5 64 on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.15 Maintenance operations Revision 2

Ability to monitor automatic operations of the plant 288000 Plant Ventilation X ventilation systems including: 3.8 65 (CFR: 41.7 / 45.7)

A3.01 Isolation/initiation signals K/A Category Point Totals: 1 1 1 1 1 1 1 1 2 1 1 Group Point Total: 12 Revision 2

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)

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 295006 SCRAM / 1 X precautions. 4.0 76 (CFR: 41.10 / 43.2 / 45.12) 2.1.6 Ability to manage control room crew during plant 4.8 transients (CFR: 41.10 / 43.5 / 45.12/45.13)

Ability to determine and/or interpret the following as they 295018 Partial or Total Loss of CCW / 8 X apply to partial or complete loss of component cooling 3.5 77 water:

(CFR: 41.10 / 43.5 / 45.13)

AA2.03 Cause for partial or complete loss 2.4.20 Knowledge of the operational implications of EOP 295019 Partial or Total Loss of Inst. Air / 8 X warnings, cautions, and notes. 4.3 78 (CFR: 41.10 / 43.5 / 45.13) 2.4.4 Ability to recognize abnormal indications for system operating parameters that are entry-level 4.7 conditions for emergency and abnormal operating procedures..

(CFR: 41.10 / 43.2 / 45.6)

Ability to determine and/or interpret the following as they 295023 Refueling Acc / 8 X apply to refueling accidents : 4.6 79 (CFR: 41.10 / 43.5 / 45.13)

AA2.05 Entry conditions of emergency plan 2.4.46 Ability to verify that the alarms are consistent with 295027 High Containment Temperature / 5 X the plant conditions. 4.2 80 (CFR: 41.10 / 43.5 / 45.3 / 45.12) 295028 High Drywell Temperature / 5 2.4.11 Knowledge of abnormal condition procedures. 4.2 (CFR: 41.10 / 43.5 / 45.13)

Ability to determine and/or interpret the following as they 295038 High Off-site Release Rate / 9 X apply to high off-site release rate: 4.5 81 (CFR: 41.10 / 43.5 / 45.13) 295005 Main Turbine Generator Trip / 3 EA2.04 Source of off-site release 3.3 Ability to determine and/or interpret the following as they apply to MAIN TURBINE GENERATOR TRIP:

AA2.08 Electrical distribution status 2.2.44 Ability to interpret control room indications to 600000 Plant Fire On Site / 8 X verify the status and operation of a system, and 4.4 82 understand how operator actions and directives affect plant and system conditions.

(CFR: 41.5 / 43.5 / 45.12)

K/A Category Totals: 3 4 Group Point Total: 7 Revision 2

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)

E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR #

1 2 3 1 2 Ability to determine and/or interpret the following as they 295007 High Reactor Pressure / 3 X apply to high reactor pressure: 4.1 83 (CFR: 41.10 / 43.5 / 45.13)

AA2.01 Reactor pressure 2.2.14 Knowledge of the process for controlling equipment 295020 Inadvertent Cont. Isolation / 5 & 7 X configuration or status. 4.3 84 (CFR: 41.10 / 43.3 / 45.13)

Ability to determine and/or interpret the following as they 295034 Secondary Containment X apply to secondary containment ventilation high radiation: 4.2 85 Ventilation High Radiation / 9 (CFR: 41.10 / 43.5 / 45.13)

EA2.01 Ventilation radiation levels K/A Category Point Totals: Group Point Total: 3 Revision 2

ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form 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 Ability to (a) predict the impacts of the following 203000 RHR/LPCI: Injection X on the RHR/LPCI: injection mode (plant specific) 3.6 86 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)

A2.04 A.C. failures 2.1.20 Ability to interpret and execute procedure 212000 RPS X steps. 4.6 87 (CFR: 41.10 / 43.5 / 45.12)

Ability to (a) predict the impacts of the following 215003 IRM X on the intermediate range monitor (irm) system ; 3.5 88 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)

A2.05 Faulty or erratic operation of detectors/system 2.1.25 Ability to interpret reference materials, 259002 Reactor Water Level X such as graphs, curves, tables, etc. 4.7 89 Control (CFR: 41.10 / 43.5 / 45.12) 2.2.40 Ability to apply Technical Specifications for a system.

(CFR: 41.10 / 43.2 / 43.5 / 45.3)

Ability to (a) predict the impacts of the following 262001 AC Electrical X on the A.C. electrical distribution ; and (b) based 3.2 90 Distribution on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.07 Energizing a dead bus A2.06 Deenergizing a Plant Bus 2.9 K/A Category Point Totals: 3 2 Group Point Total: 5 Revision 2

ES-401 5 Form ES-401-1 ES-401 BWR Examination Outline Form 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 2.1.23 Ability to perform specific system and 201006 RWM X integrated plant procedures during all modes of 4.4 91 plant operation.

(CFR: 41.10 / 43.5 / 45.2 / 45.6)

Ability to (a) predict the impacts of the following 202002 Recirculation Flow Control X on the recirculation flow control system ; and (b) 3.3 92 based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.09 Recirculation flow mismatch: Plant-Specific 3.3 A2.06 Low reactor water level: Plant-Specific 2.4.18 Knowledge of the specific bases for EOPs.

271000 Offgas X (CFR: 41.10 / 43.1 / 45.13) 4.0 93 K/A Category Point Totals: Group Point Total: 3 Revision 2

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Cooper Nuclear Station Date of Exam: February 16, 2015 Category K/A # Topic RO SRO-Only IR # IR #

Ability to coordinate personnel activities outside the control 2.1.8 3.4 66 room.

(CFR: 41.10 / 45.5 / 45.12 / 45.13) 1.

Ability to make accurate, clear, and concise logs, records, status Conduct 2.1.18 3.6 67 boards, and reports.

of Operations (CFR: 41.10 / 45.12 / 45.13)

Ability to locate control room switches, controls, and 2.1.31 4.6 68 indications, and to determine that they correctly reflect the desired plant lineup.

(CFR: 41.10 / 45.12)

Knowledge of individual licensed operator responsibilities 2.1.4 3.8 94 related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc.

(CFR: 41.10 / 43.2)

Knowledge of the refueling process.

2.1.41 3.7 95 (CFR: 41.2 / 41.10 / 43.6 / 45.13)

Subtotal 3 2 Knowledge of tagging and clearance procedures.

2.2.13 4.1 69 (CFR: 41.10 / 45.13)

Ability to obtain and interpret station electrical and mechanical 2.2.41 3.5 70 drawings.

2.

(CFR: 41.10 / 45.12 / 45.13)

Equipment Control Knowledge of the process for controlling temporary design 2.2.11 3.3 96 changes.

(CFR: 41.10 / 43.3 / 45.13)

Knowledge of maintenance work order requirements.

2.2.19 3.4 97 (CFR: 41.10 / 43.5 / 45.13)

Subtotal 2 2 Knowledge of radiation exposure limits under normal or 2.3.4 3.2 71 emergency conditions.

(CFR: 41.12 / 43.4 / 45.10)

Ability to use radiation monitoring systems, such as fixed

3. 2.3.5 2.9 72 radiation monitors and alarms, portable survey instruments, Radiation personnel monitoring equipment, etc.

Control (CFR: 41.11 / 41.12 / 43.4 / 45.9)

Knowledge of radiological safety procedures pertaining to 2.3.13 3.4 73 licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

(CFR: 41.12 / 43.4 / 45.9 / 45.10) 2.3.6 Ability to approve release permits.

2.3.6 3.8 98 (CFR: 41.13 / 43.4 / 45.10)

Subtotal 3 1 Ability to prioritize and interpret the significance of each 2.4.45 4.1 74 annunciator or alarm.

(CFR: 41.10 / 43.5 / 45.3 / 45.12)

Revision 2

4. Ability to perform without reference to procedures those 2.4.49 4.6 75 Emergency actions that require immediate operation of system Procedures / components and controls.

Plan (CFR: 41.10 / 43.2 / 45.6)

Knowledge of RO tasks performed outside the main control 2.4.34 4.1 99 room during an emergency and the resultant operational effects.

(CFR: 41.10 / 43.5 / 45.13)

Knowledge of the Emergency Plan (CFR: 41.10 / 43.5 /

2.4.29 4.4 99 45.11)

Ability to verify system alarm setpoints and operate controls 2.4.50 4.0 100 identified in the alarm response manual.

(CFR: 41.10 / 43.5 / 45.3) 2.4.5 Knowledge of the organization of the operating 4.3 100 procedures network for normal, abnormal, and emergency evolutions. (CFR: 41.10 / 43.5 / 45.13)

Subtotal 2 2 Tier 3 Point Total 10 7 Revision 2

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Group Randomly Selected K/A Reason for Rejection Tier 1/Group Question 6: There are no actions or interrelations at CNS for control room 1 (RO) 295016 AK2.03 abandonment and the control room HVAC system. Using poker chips randomly re-selected from same system AK2.01 Tier 1/Group Question 10: Could not write a question to match the KA. The event and the generic 1 (RO) 2.2.40 ability are not amendable to an operationally valid question. Randomly re-selected 2.4.30. EJJ Tier 1/Group Question 27: CNS procedures have limited procedural response to H2 concentration.

2 (RO) 2.4.31 Using poker chips, randomly re-selected Generic 2.4.21 from the list of Emergency Procedures / Plan Generics Tier 2/Group Question 30: CNS does not require ROs to know Technical Specification bases.

1 (RO) 2.2.25 Using poker chips, randomly re-selected Generic 2.2.39 from the list of Equipment Control Generics Tier 2/Group Question 32: CNS design does not contain a HPCS system. Using random 1 (RO) 209002 generator re-selected Tier 2/Group 1 system 259002 Reactor Water Level Control.

Maintained the K3.02 K/A topic number. EJJ Tier 2/Group Question 41: There is no local operation of SRVs, therefore, matching the K&A is not 1 (RO) 2.1.45 possible. Randomly re-selected Generic 2.2.12 from the list of generics in ES-401 D.1.b. EJJ Tier 2/Group Question 53: There is no RCIC keep fill pump at CNS, using poker chips randomly 217000 RCIC K1.08 1 (RO) re-selected from the same system K1.07 Tier 2/Group Question 56: Could not write a operationally relevant question at the RO level.

2.2.36 2 (RO) Randomly selected 2.1.28. EJJ Question 78: CNS design does not tie instrument air to Generic 2.4.20 of EOP Tier 1/Group 2.4.20 warnings, cautions, and notes. Using random generator, re-selected Generic 2.4.4 1 (SRO) from the list of generics in ES-401 D.1.b. EJJ Question 80: CNS design does not contain a Mark III containment. CNS Tier 1/Group 295027G2.4.46 containment is a Mark I design. Stayed with the same safety function and similar 1 (SRO) system and randomly selected 295028. Could not write an SRO level question based on drywell temperature alarms. Randomly selected 2.4.11. EJJ Question 81: Could not develop a question to match the KA where determining the Tier 1/Group 295038 EA 2.04 source of radiation release was not above a difficulty of 1. Very basic knowledge 1 (SRO) needed to answer that question. Randomly reselected another Tier 1/Group 1 evolution, 295005 and randomly selected an associated A2 ability statement AA2.08.

EJJ.

Tier 3 (SRO) 2.4.39 Question 99: Cannot write an SRO-Only question on the RO's tasks in the emergency plan as the RO is expected to know this information as well. Randomly selected 2.4.29. EJJ Tier 3 (SRO) 2.4.50 Question 100: Cannot write an SRO-Only question to verifying alarms and use of controls, etc. Randomly selected 2.4.5. EJJ Tier 1/Group 2.1.32 Question 76: Cannot write SRO-Only question applying system limits and 1 (SRO) precautions associated with a scram (295026). Randomly selected 2.1.6. EJJ Tier 2/Group 2.1.25 Question 89: Cannot write an SRO-Only question that is operationally valid.

1 (SRO) Randomly selected 2.2.40. EJJ Tier 2/Group 262001 A2.07 Question 90: Cannot write another SRO-Only question differing greatly from the 1 (SRO) previous NRC exam. Randomly selected A2.07. EJJ Tier 2/Group 202002 A2.04 Question 92: The flow mismatch has no effect on CNS RR flow control system and 1 (SRO) is N/A to CNS. Randomly selected A2.06. EJJ Revision 2