ML12353A156

Cooper Nuclear Station 2012-10 Final Outlines

ML12353A156
Person / Time
Site:	Cooper
Issue date:	10/30/2012
From:	Hedger S D Operations Branch IV
To:	Nebraska Public Power District (NPPD)
laura hurley
References
Download: ML12353A156 (30)

Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Cooper Nuclear Station Date of Examination:

10/2 9/2012 Examination Level:

Operating Test Number:

RO SRO 1 Administrative Topic (see Note)

Type Code* Describe activity to be performed Conduct of Operations D, R SKL034-50-04, Determine Time to Boil Conduct of Operations N, R SKL034-50-74, Perform DW Unidentified Leak Rate Checks Equipment Control D, R, P SKL034-50-57, Determine Isolation Boundaries Radiation Control N/A N/A Emergency Procedure/Plan N, R SKL034-50-75, Calculate Liquid Release Curie Content NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, then all 5 are required.

• Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (< 3 for ROs;

< 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (> 1) (P)revious 2 exams (< 1; randomly selected)

ES-301, Page 22 of 27

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Cooper Nuclear Station Date of Examination:

1 0/2 9/2012 Examination Level:

Operating Test Number:

RO SRO 1 Administrative Topic (see Note)

Type Code* Describe activity to be performed Conduct of Operations R, M SKL034-50-76 Determine Actions for a Control Rod Mispositioned > 2 Hours Conduct of Operations D , R SKL034-50-66, Assess Non

-scheduled Call

-Out Equipment Control D, R, P SKL034-20-113, Review Jet Pump Operability And RR Flow Checks Radiation Control D, R SKL034-50-25, Release Rate Determination Emergency Procedure/Plan R, N SKL035-50-77, EAL Tabletop 9 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, then all 5 are required.

• Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (< 3 for ROs;

< 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (> 1) (P)revious 2 exams (< 1; randomly selected)

ES-301, Page 22 of 27 Rev 01 ES-301 Control Room/In Plant Systems Outline Form ES-301-2 Facility: Cooper Nuclear Station Date of Examination:

10/29/2012 Exam Level:

Operating Test N o.: RO SRO-I SRO-U 1 Control Room Systems

@ (8 for RO); (7 for SRO

-I); (2 or 3 for SRO

-U, including 1 ESF) System / JPM Title Type Code* Safety Function a. SKL034-21-134 , Establish RPV Cooldown Using MSL Drains N, L, S 4 b. SKL 034-21-14, DG2 Shutdown from Control Room D, S 6 c. SKL034-21-135, Operate Reactor Water Sample Valves with Group 7 Present N, S 5 d. SKL 034-20-107, Lowering DEH Pressure Setpoint (Alternate Path)

D, S, A 3 e. SKL034-2 0-1 22 , Perform Attachment 3 of 2.1.5 Reactor Water Level Control (Alternate Path)

D, S, L, A 2 f. SKL034-2 2-0 1 , SGT System Support for HPCI Operation (Alternate Path)

P , D, S, A 9 g. SKL 034-2 0-1 8 , Perform APRM Gain Adjustment (With A Valid CTP Available With T wo RR Loops Operating) D , S 7 h. SKL034-21-138 , Withdrawal Of Control Rod From Position 00 (Alternate Path)

N, S , A 1 In-Plant Systems

@ (3 for RO); (3 for SRO

-I); (3 or 2 for SRO

-U) i. SKL034-10-95, Respond to NBPP Failure (Control Bldg Actions Alternate Path)

A, D, E, P 6 j. SKL034-40-84, 5.3ALT

-STRATEGY-Inject Fire Water to RHR D, E, P, L 2 k. SKL034-11-03, Place Cold Reference Leg Continuous Backfill System in Service (Alternate Path)

D, A, R 7 @ All RO and SRO

-I control room (and in

-plant) systems must be different and serve different safety functions; all 5 SRO

-U systems must serve different safety functions; in

-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO / SRO

-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in

-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 < 9 / < 8 / < 4 > 1 / > 1 / > 1 - / - / >1 (control room system)

> 1 / > 1 / > 1 > 2 / > 2 / > 1 < 3 / < 3 / < 2 (randomly selected)

> 1 / > 1 / > 1 ES-301, Page 23 of 27 Rev 3 ES-301 Control Room/In Plant Systems Outline Form ES-301-2 Facility: Cooper Nuclear Station Date of Examination:

10/29/2012 Exam Level:

Operating Test N o.: RO SRO-I SRO-U 1 Control Room Systems

@ (8 for RO); (7 for SRO

-I); (2 or 3 for SRO

-U, including 1 ESF)

System / JPM Title Type Code*

Safety Function a. SKL034-21-134 , Establish RPV Cooldown Using MSL Drains N, L, S 4 b. SKL 034-21-14, DG2 Shutdown from Control Room D, S 6 c. SKL034-21-135, Operate Reactor Water Sample Valves with Group 7 Present N, S 5 d. SKL 034-20-107, Lowering DEH Pressure Setpoint (Alternate Path)

D, S, A 3 e. SKL034-2 0-122 , Perform Attachment 3 of 2.1.5 Reactor Water Level Control (Alternate Path)

D, S, L, A 2 f. SKL034-2 2-01, SGT System Support for HPCI Operation (Alternate Path)

P, D, S, A 9 g. h. SKL034-21-138 , Withdrawal Of Control Rod From Position 00 (Alternate Path)

N, S , A 1 In-Plant Systems

@ (3 for RO); (3 for SRO

-I); (3 or 2 for SRO

-U) i. SKL034-10-95, Respond to NBPP Failure (Control Bldg Actions Alternate Path)

A, D, E, P 6 j. SKL034-40-84, 5.3ALT

-STRATEGY-Inject Fire Water to RHR D, E, P, L 2 k. SKL034-11-03, Place Cold Reference Leg Continuous Backfill System in Service (Alternate Path)

D, A, R 7 @ All RO and SRO

-I control room (and in

-plant) systems must be different and serve different safety functions; all 5 SRO

-U systems must serve different safety functions; in

-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO / SRO

-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in

-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 < 9 / < 8 / < 4 > 1 / > 1 / > 1 - / - / >1 (control room system)

> 1 / > 1 / > 1 > 2 / > 2 / > 1 < 3 / < 3 / < 2 (randomly selected)

> 1 / > 1 / > 1 ES-301, Page 23 of 27 Rev 3 ES-301 Control Room/In Plant Systems Outline Form ES-301-2 Facility: Cooper Nuclear Station Date of Examination:

10/29/2012 Exam Level:

Operating Test N o.: RO SRO-I SRO-U 1 Control Room Systems

@ (8 for RO); (7 for SRO

-I); (2 or 3 for SRO

-U, including 1 ESF)

System / JPM Title Type Code*

Safety Function a. SKL034-21-134 , Establish RPV Cooldown Using MSL Drains N, L, S 4 b. SKL034-21-139, Start CS and place in test mode N, EN, S 2 c. d. e. f. g. h. In-Plant Systems

@ (3 for RO); (3 for SRO

-I); (3 or 2 for SRO

-U) i. SKL034-10-95, Respond to NBPP Failure (Control Bldg Actions Alternate Path)

A, D, E, P 6 j. SKL034-40-84, 5.3ALT

-STRATEGY-Inject Fire Water to RHR D, E, P, L 2 k. SKL034-11-03, Place Cold Reference Leg Continuous Backfill System in Service (Alternate Path)

D, A, R 7 @ All RO and SRO-I control room (and in

-plant) systems must be different and serve different safety functions; all 5 SRO

-U systems must serve different safety functions; in

-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO / SRO

-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in

-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 < 9 / < 8 / < 4 > 1 / > 1 / > 1 - / - / >1 (control room system)

> 1 / > 1 / > 1 > 2 / > 2 / > 1 < 3 / < 3 / < 2 (randomly selected)

> 1 / > 1 / > 1 ES-301, Page 23 of 27 Rev 3

Revision 02 ES-401 BWR Examination Outline Form ES-401-1 Facility: Cooper Nuclear Station (RO)

Date of Exam: November 5, 2012 Tier Group RO K/A Category Points SRO-Only Points 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. Emergency & Abnormal Plant Evolutions 1 3 3 4 N/A 4 3 N/A 3 20 7 2 1 1 1 1 2 1 7 3 Tier Totals 4 4 5 5 5 4 27 10 2. Plant Systems 1 2 2 3 2 2 3 3 2 2 3 2 26 5 2 1 1 1 1 1 2 1 1 1 1 1 12 3 Tier Totals 3 3 4 3 3 5 4 3 3 4 3 38 8 3. Generic Knowledge and Abilities Categories 1 2 3 4 10 1 2 3 4 7 3 2 2 3 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 o n 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 th at are linked to 10 CFR 55.43.

Revision 02 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 / 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 X AA1.07 - Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION:

Nuclear boiler instrumentation system 3.1 1 295003 Partial or Complete Loss of AC / 6 X 2.2.44 - Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

4.2 1 295004 Partial or Total Loss of DC Pwr / 6 X AA2.01 - Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER

Cause of partial or complete loss of D.C. power 3.2 1 295005 Main Turbine Generator Trip / 3 X AA2.07 - Ability to determine and/or interpret the following as they apply to MAIN TURBINE GENERATOR TRIP:

Reactor water level 3.5 1 295006 SCRAM / 1 X AA1.05 - Ability to operate and/or monitor the following as they apply to SCRAM:

Neutron monitoring system 4.2 1 295016 Control Room Abandonment / 7 X AK3.02 - Knowledge of the reasons for the following responses as they apply to CONTROL ROOM ABANDONMENT

Turbine trip 3.7 1 295018 Partial or Total Loss of CCW / 8 X AA1.03 - Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER :

Affected systems so as to isolate damaged portions 3.3 1 295019 Partial or Total Loss of Inst. Air / 8 X AK2.06 - Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR and the following: Offgas system 2.8 1 295021 Loss of Shutdown Cooling / 4 X AA1.01 - Ability to operate and/or monitor the following as they apply to LOSS OF SHUTDOWN COOLING:

Reactor water cleanup system 3.4 1 295023 Refueling Acc / 8 X AK2.07 - Knowledge of the interrelations between REFUELING ACCIDENTS and the following:

Standby gas treatment/FRVS 3.6 1 295024 High Drywell Pressure / 5 X EA2.06 - Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE: Suppression pool temperature 4.1 1 295025 High Reactor Pressure / 3 X EK1.03 - Knowledge of the operational implications of the following concepts as they apply to HIGH REACTOR PRESSURE:

Safety/relief valve tailpipe temperature/pressure relationships 3.6 1 295026 Suppression Pool High Water Temp. / 5 X 2.1.20 - Ability to interpret and execute procedure steps.

4.6 1 295027 High Containment Temperature / 5 For Mark-III Containments

- N/A 295028 High Drywell Temperature / 5 X EK3.02 - Knowledge of the reasons for the following responses as they apply to HIGH DRYWELL TEMPERATURE

RPV flooding 3.5 1 295030 Low Suppression Pool Wtr Lvl / 5 X EK2.04 - Knowledge of the interrelations between LOW SUPPRESSION POOL WATER LEVEL and the following:

RHR/LPCI 3.7 1 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: Core coverage 4.4 1 295037 SCRAM Condition Present

and Reactor Power Above APRM Downscale or Unknown / 1 X EK1.02 - Knowledge of the operational implications of the following concepts as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN : Reactor water level effects on reactor power 4.1 1 Revision 02 295038 High Off

-site Release Rate / 9 X EK3.04 - Knowledge of the reasons for the following responses as they apply to HIGH O FF-SITE RELEASE RATE: Emergency depressurization 3.6 1 600000 Plant Fire On Site / 8 X AK1.01 - Knowledge of the operation applications of the following concepts as they apply to Plant Fire On Site:

Fire Classifications by type 2.5 1 700000 Generator Voltage and Electric Grid Disturbances / 6 X 2.4.2 - Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

4.5 1 K/A Category Totals:

3 3 4 4 3 3 Group Point Total:

20/7 Revision 02 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 /

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 AK2.02 - Knowledge of the interrelations between LOSS OF MAIN CONDENSER VACUUM and the following:

Main turbine 3.1 1 295007 High Reactor Pressure / 3 X 2.1.7 - Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

4.4 1 295008 High Reactor Water Level / 2 X AK1.01 - Knowledge of the operational implications of the following concepts as they apply to HIGH REACTOR WATER LEVEL : Moisture carryover 3.0 1 295009 Low Reactor Water Level / 2 295010 High Drywell Pressure / 5 X AA2.0 2 - Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE

Drywell pressure 3.8 1 295011 High Containment Temp / 5 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 X AK3.04 - Knowledge of the reasons for the following responses as they apply to HIGH OFF

-SITE RELEASE RATE: Power reduction 3.6 1 295020 Inadvertent Cont. Isolation / 5 & 7 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: HPCI: Plant

-Specific 3.4 1 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 EA2.01 - Ability to determine and/or interpret the following as they apply to SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE:

Secondary containment pressure: Plant

-Specific 3.8 1 295036 Secondary Containment High Sump/Area Water Level / 5 500000 High CTMT Hydrogen Conc. / 5 K/A Category Point Totals:

1 1 1 1 2 1 Group Point Total:

7/3 Revision 02 ES-401 4 Form E S-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems

- Tier 2/Group 1 (RO / 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 X K3.01 - Knowledge of the effect that a loss or malfunction of the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) will have on following:

Reactor water level 4.3 1 205000 Shutdown Cooling X X K4.02 - Knowledge of SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) design feature(s) and/or interlocks which provide for the following:

High pressure isolation: Plant-Specific K6.08 - Knowledge of the effect that a loss or malfunction of the following will have on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE):

RHR service water: Plant

-Specific 3.7 3.5 2 206000 HPCI X K1.12 - Knowledge of the physical connections and/or cause

-effect relationships between HIGH PRESSURE COOLANT INJECTION SYSTEM and the following:

Nuclear boiler instrumentation: BWR-2,3,4 3.4 1 207000 Isolation (Emergency) Condenser Not part of plant design

- N/A 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:

Torus/suppression pool water level 3.5 1 209002 HPCS BWR-5, 6 specific K/A

- N/A 211000 SLC X X K3.02 - Knowledge of the effect that a loss or malfunction of the STANDBY LIQUID CONTROL SYSTEM will have on following:

Core spray line break detection system: Plant- Specific A1.09 - Ability to predict and/or monitor changes in parameters associated with operating the STANDBY LIQUID CONTROL SYSTEM controls including:

SBLC system lineup 3.0 4.0 2 212000 RPS X A2.12 - Ability to (a) predict the impacts of the following on the REACTOR PROTECTION SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Main turbine stop control valve closure 4.0 1 215003 IRM X X K6.02 - Knowledge of the effect that a loss or malfunction of the following will have on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM : 24/48 volt D.C. power: Plant

-Specific A3.02 - Ability to monitor automatic operations of the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM including:

Annunciator and alarm signals 3.6 3.2 2 215004 Source Range Monitor X 2.1.27 - Knowledge of system purpose and/or function. 3.9 1 Revision 02 215005 APRM / LPRM X A4.04 - Ability to manually operate and/or monitor in the control room:

LPRM back panel switches, meters and indicating lights 3.2 1 217000 RCIC X K1.02 - Knowledge of the physical connections and/or cause

-effect relationships between REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) and the following:

Nuclear boiler system 3.5 1 218000 ADS X A1.04 - Ability to predict and/or monitor changes in parameters associated with operating the AUTOMATIC DEPRESSURIZATION SYSTEM controls including:

Reactor pressure 4.1 1 223002 PCIS/Nuclear Steam Supply Shutoff X K6.08 - Knowledge of the effect that a loss or malfunction of the following will have on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT

-OFF: Reactor protection system 3.5 1 239002 SRVs X X K3.03 - Knowledge of the effect that a loss or malfunction of the RELIEF/SAFETY VALVES will have on following:

Ability to rapidly depressurize the reactor K5.04 - Knowledge of the operational implications of the following concepts as they apply to RELIEF/SAFETY VALVES :

Tail pipe temperature monitoring 4.3 3.3 2 259002 Reactor Water Level Control X A4.0 1 - Ability to manually operate and/or monitor in the control room:

All individual component controllers in the manual mode 3.8 1 261000 SGTS X A2.11 - 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: High containment pressure 3.2 1 262001 AC Electrical Distribution X 2.2.36 - Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.

3.1 1 262002 UPS (AC/DC)

X A3.01 - Ability to monitor automatic operations of the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) including:

Transfer from preferred to alternate source 2.8 1 263000 DC Electrical Distribution X X K2.01 - Knowledge of electrical power supplies to the following:

Major D.C. loads K5.01 - Knowledge of the operational implications of the following concepts as they apply to D.C. ELECTRICAL DISTRIBUTION:

Hydrogen generation during battery charging 3.1 2.6 2 264000 EDGs X A4.05 - Ability to manually operate and/or monitor in the control room:

Transfer of emergency generator (with load) to grid 3.6 1 300000 Instrument Air X K4.02 - Knowledge of (INSTRUMENT AIR SYSTEM) design feature(s) and or interlocks which provide for the following: Cross-over to other air systems 3.0 1 400000 Component Cooling Water X K2.01 - Knowledge of electrical power supplies to the following:

CCW pumps 2.9 1 K/A Category Point Totals:

2 2 3 2 3 2 3 2 2 3 2 Group Point Total:

26/5 Revision 02 ES-401 5 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems

- Tier 2/Group 2 (RO / 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 X A1.03 - Ability to predict and/or monitor changes in parameters associated with operating the CONTROL ROD AND DRIVE MECHANISM controls including:

CRD drive water flow 2.9 1 201004 RSCS No RSCS at Cooper

- N/A 201005 RCIS BWR-6 Only - N/A 201006 RWM 202001 Recirculation X K4.04 - Knowledge of RECIRCULATION System design feature(s) and/or interlocks which provide for the following:

Controlled seal flow 3.0 1 202002 Recirculation Flow Control X K1.02 - Knowledge of the physical connections and/or cause

-effect relationships between RECIRCULATION FLOW CONTROL SYSTEM and the following:

Reactor power 4.2 1 204000 RWCU X 2.4.41 - Knowledge of the emergency action level thresholds and classifications.

2.9 1 214000 RPIS X K5.01 - Knowledge of the operational implications of the following concepts as they apply to ROD POSITION

INFORMATION SYSTEM :

Reed switches 2.7 1 215001 Traversing In

-core Probe 215002 RBM X A4.02 - Ability to manually operate and/or monitor in the control room:

RBM back panel switches, meters and indicating lights:

BWR-3, 4, 5 2.9 1 216000 Nuclear Boiler Inst.

219000 RHR/LPCI: Torus/Pool Cooling Mode X A3.01 - Ability to monitor automatic operations of the RHR/LPCI: TORUS/SUPPRESSION POOL COOLING MODE including: Valve operation 3.3 1 223001 Primary CTMT and Aux. 226001 RHR/LPCI: CTMT Spray Mode X K2.02 - Knowledge of electrical power supplies to the following:

Pumps 2.9 1 230000 RHR/LPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment 239001 Main and Reheat Steam X K6.09 - Knowledge of the effect that a loss or malfunction of the following will have on the MAIN AND REHEAT STEAM SYSTEM: PCIS/N SSSS 3.9 1 239003 MSIV Leakage Control 241000 Reactor/Turbine Pressure Regulator X K3.10 - Knowledge of the effect that a loss or malfunction of the REACTOR/TURBINE PRESSURE REGULATING SYSTEM will have on following: Front standard trip system 2.9 1 Revision 02 245000 Main Turbine Gen. / Aux.

X A2.05 - Ability to (a) predict the impacts of the following on the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Generator trip 3.6 1 256000 Reactor Condensate 259001 Reactor Feedwater 268000 Radwaste 271000 Offgas 272000 Radiation Monitorin g 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary CTMT X K6.08 - Knowledge of the effect that a loss or malfunction of the following will have on the SECONDARY CONTAINMENT :

Plant air systems 2.7 1 290003 Control Room HVAC 290002 Reactor Vessel Internals K/A Category Point Totals:

1 1 1 1 1 2 1 1 1 1 1 Group Point Total:

12/3 Revision 02 ES-401 Generic Knowledge and Abilities Outline (Tier

3) Form ES-401-3 Facility: Cooper Nuclear Station (RO) Date of Exam:

November 5, 2012 Category K/A # Topic RO SRO-Only IR # IR # 1. Conduct of Operations

2.1.4 Knowledge

of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no

-solo" operation, maintenance of active license status, 10CFR55, etc. 3.3 1 2.1.17 Ability to make accurate, clear, and concise verbal reports.

3.9 1 2.1.42 Knowledge of new and spent fuel movement procedures.

2.5 1 2.1. 2.1. 2.1. Subtotal 3

2. Equipment Control 2.2.1 Ability to perform pre

-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.

4.5 1 2.2.36 Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.

3.1 1 2.2. 2.2. 2.2. 2.2. Subtotal 2 3. Radiation Control 2.3.11 Ability to control radiation releases.

3.8 1 2.3.12 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc

. 3.2 1 2.3. 2.3. 2.3. 2.3. Subtotal 2 4. Emergency Procedures /

Plan 2.4.18 Knowledge of the specific bases for EOPs

. 3.3 1 2.4.23 Knowledge of the bases for prioritizing emergency procedure implementation during emergency operations.

3.4 1 2.4.27 Knowledge of "fire in the plant" procedures.

3.4 1 2.4. 2.4. Subtotal 3 Tier 3 Point Total 10 7 Revision 0 3 ES-401 BWR Examination Outline Form ES-401-1 Facility: Cooper Nuclear Station (SRO)

Date of Exam: November 5, 2012 Tier Group RO K/A Category Points SRO-Only Points 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. Emergency & Abnormal Plant Evolutions 1 N/A N/A 20 4 3 7 2 7 1 2 3 Tier Totals 27 5 5 10 2. Plant Systems 1 26 3 2 5 2 12 1 2 3 Tier Totals 38 4 4 8 3. Generic Knowledge and Abilities Categories 1 2 3 4 10 1 2 3 4 7 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/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 an d 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 0 3 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 / 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 X AA2.02 - Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION:

Neutron monitoring 3.2 1 295003 Partial or Complete Loss of AC / 6 295004 Partial or Total Loss of DC Pwr / 6 295005 Main Turbine Generator Trip / 3 X 2.1.32 - Ability to explain and apply system limits and precautions.

4.0 1 295006 SCRAM / 1 295016 Control Room Abandonment / 7 295018 Partial or Total Loss of CCW / 8 295019 Partial or Total Loss of Inst. Air / 8 295021 Loss of Shutdown Cooling / 4 X 2.2.38 - Knowledge of conditions and limitations in the facility license.

4.5 1 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: Suppression pool level 3.8 1 295025 High Reactor Pressure / 3 295026 Suppression Pool High Water Temp. / 5 X 2.2.39 - Knowledge of less than or equal to one hour Technical Specification action statements for systems.

4.5 1 295027 High Containment Temperature / 5 For Mark-III Containment

- N/A 295028 High Drywell Temperature / 5 295030 Low Suppression Pool Wtr Lvl / 5 X EA2.04 - Ability to determine and/or interpret the following as they apply to LOW SUPPRESSION POOL WATER LEVEL :

Drywell/ suppression chamber differential pressure:

Mark-I&II 3.7 1 295031 Reactor Low Water Level / 2 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 295038 High Off

-site Release Rate / 9 X EA2.01 - Ability to determine and/or interpret the following as they apply to HIGH OFF

-SITE RELEASE RATE : Off-site 4.3 1 600000 Plant Fire On Site / 8 700000 Generator Voltage and Electric Grid Disturbances / 6 K/A Category Totals:

4 3 Group Point Total: 20/7 Revision 0 3 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 / 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 295007 High Reactor Pressure / 3 295008 High Reactor Water Level / 2 295009 Low Reactor Water Level / 2 X AA2.03 - Ability to determine and/or interpret the following as they apply to LOW REACTOR WATER LEVEL :

Reactor water cleanup blowdown rate 2.9 1 295010 High Drywell Pressure / 5 295011 High Containment Temp / 5 295012 High Drywell Temperature / 5 295013 High Suppression Pool Temp. / 5 295014 Inadvertent Reactivity Addition / 1 X 2.4.35 - Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects.

4.0 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 X 2.4.8 - Knowledge of how abnormal operating procedures are used in conjunction with EOPs.

4.5 1 K/A Category Point Totals:

1 2 Group Point Total:

7/3 Revision 0 3 ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems

- Tier 2/Group 1 (RO / 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 206000 HPCI 207000 Isolation (Emergency) Condenser 209001 LPCS X A2.09 - Ability to (a) predict the impacts of the following on the LOW PRESSURE CORE SPRAY SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Low suppression pool level 3.3 1 209002 HPCS 211000 SLC 212000 RPS 215003 IRM 215004 Source Range Monitor X A2.03 - 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:

Stuck detector 3.3 1 215005 APRM / LPRM 217000 RCIC 218000 ADS X 2.4.21 - Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc

. 4.6 1 223002 PCIS/Nuclear Steam Supply Shutoff 239002 SRVs 259002 Reactor Water Level Control 261000 SGTS 262001 AC Electrical Distribution 262002 UPS (AC/DC)

X 2.4.9 - Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

4.2 1 Revision 0 3 263000 DC Electrical Distribution 264000 EDGs 300000 Instrument Air X A2.01 - Ability to (a) predict the impacts of the following on the INSTRUMENT AIR SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:

Air dryer and filter malfunctions 2.8 1 400000 Component Cooling Water K/A Category Point Totals:

3 2 Group Point Total:

26/5 Revision 0 3 ES-401 5 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems

- Tier 2/Group 2 (RO / 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 201005 RCIS 201006 RWM 202001 Recirculation 202002 Recirculation Flow Control 204000 RWCU 214000 RPIS 215001 Traversing In

-core Probe 215002 RBM 216000 Nuclear Boiler Inst.

X A2.01 Ability to (a) predict the impacts of the following on the NUCLEAR BOILER INSTRUMENTATION ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Detector equalizing valve leaks 3.2 1 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 239003 MSIV Leakage Control 241000 Reactor/Turbine Pressure Regulator 245000 Main Turbine Gen. / Aux.

256000 Reactor Condensate 259001 Reactor Feedwater X 2.4.3 - Ability to identify post

-accident instrumentation.

3.9 1 268000 Radwaste 271000 Offgas 272000 Radiation Monitoring 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC

Revision 0 3 290002 Reactor Vessel Internals X 2.4.46 - Ability to verify that the alarms are consistent with the plant conditions.

4.2 1 K/A Category Point Totals:

1 2 Group Point Total:

12/3 Revision 0 3 ES-401 Generic Knowledge and Abilities Outline (Tier

3) Form ES-401-3 Facility: Cooper Nuclear Station (SRO) Date of Exam: November 5, 2012 Category K/A # Topic RO SRO-Only IR # IR # 1. Conduct of Operations

2.1.5 Ability

to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, et

c. 3.9 1 2.1. 2.1. 2.1. 2.1. 2.1. Subtotal 1 2. Equipment Control 2.2.37 Ability to determine operability and/or availability of safety related equipment.

4.6 1 2.2.18 Knowledge of the process for managing maintenance activities during shutdown operations, such as risk assessments, work prioritization, etc.

3.9 1 2.2. 2.2. 2.2. 2.2. Subtotal 2

3. Radiation Control 2.3.5 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

2.9 1 2.3.6 Ability to approve release permits.

3.8 1 2.3. 2.3. 2.3. 2.3. Subtotal 2 4. Emergency Procedures

/ Plan 2.4.6 Knowledge of EOP mitigation strategies.

4.7 1 2.4.32 Knowledge of operator response to loss of all annunciators

. 4.0 1 2.4. 2.4. 2.4. 2.4. Subtotal 2 Tier 3 Point Total 10 7 ES-401 Record of Rejected K/As Form ES-401-4 ES-401, Page 27 of 33 Tier / Group Randomly Selected K/A Reason for Rejection 2/1 215004G2.4.34 RO has no outside the main control room tasks during an emergency associated with the Source Range Monitor System.

Therefore, another Generic K/A was randomly selected for 215004: G 2.1.27.

2/1 259002A4.09 CNS TDRFP control system has been modified to a Triconex system that has no lockout attributes.

Therefore, A4.01 was randomly selected to replace this K/A.

2/2 201004K3.01 CNS design does not contain a RSCS system.

Another event and K/A was randomly selected to replace this: 241000, K3.10.

2/2 216000A2.01 After attempts a SRO question could not be written to the K/A statement. Sampled and re

-selected A2.01 to replace A2.12.