Text

2012-10 Final Outlines
	ML12353A156
Person / Time
Site:	Cooper
Issue date:	10/30/2012
From:	Sean Hedger; Operations Branch IV
To:	; Nebraska Public Power District (NPPD)
	laura hurley
References
	Download: ML12353A156 (30)
	v • d • e

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Cooper Nuclear Station Date of Examination: 10/29/2012 Examination Level: RO SRO Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (see Note) Code*

Conduct of Operations D, R SKL034-50-04, Determine Time to Boil SKL034-50-74, Perform DW Unidentified Leak Conduct of Operations N, R Rate Checks Equipment Control D, R, P SKL034-50-57, Determine Isolation Boundaries Radiation Control N/A N/A SKL034-50-75, Calculate Liquid Release Curie Emergency Procedure/Plan N, R 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: 10/29/2012 Examination Level: RO SRO Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (see Note) Code*

SKL034-50-76 Determine Actions for a Control Conduct of Operations R, M Rod Mispositioned > 2 Hours Conduct of Operations D, R SKL034-50-66, Assess Non-scheduled Call-Out SKL034-20-113, Review Jet Pump Operability Equipment Control D, R, P 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: RO SRO-I SRO-U Operating Test No.: 1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function

a. SKL034-21-134, Establish RPV Cooldown Using MSL N, L, S 4 Drains

b. SKL034-21-14, DG2 Shutdown from Control Room D, S 6

c. SKL034-21-135, Operate Reactor Water Sample Valves N, S 5 with Group 7 Present

d. SKL034-20-107, Lowering DEH Pressure Setpoint D, S, A 3 (Alternate Path)

e. SKL034-20-122, Perform Attachment 3 of 2.1.5 Reactor D, S, L, A 2 Water Level Control (Alternate Path)

f. SKL034-22-01, SGT System Support for HPCI Operation P, D, S, A 9 (Alternate Path)

g. SKL034-20-18, Perform APRM Gain Adjustment (With A D, S 7 Valid CTP Available With Two RR Loops Operating)

h. SKL034-21-138, Withdrawal Of Control Rod From N, S, A 1 Position 00 (Alternate Path)

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 A, D, E, P 6 Actions Alternate Path)

j. SKL034-40-84, 5.3ALT-STRATEGY-Inject Fire Water to D, E, P, L 2 RHR

k. SKL034-11-03, Place Cold Reference Leg Continuous D, A, R 7 Backfill System in Service (Alternate Path)

@ 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 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank <9/<8/<4 (E)mergency or abnormal in-plant >1/>1/>1 (EN)gineered safety feature - / - / >1 (control room system)

(L)ow-Power / Shutdown >1/>1/>1 (N)ew or (M)odified from bank including 1(A) >2/>2/>1 (P)revious 2 exams < 3 / < 3 / < 2 (randomly selected)

(R)CA >1/>1/>1 (S)imulator 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: RO SRO-I SRO-U Operating Test No.: 1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function

a. SKL034-21-134, Establish RPV Cooldown Using MSL N, L, S 4 Drains

b. SKL034-21-14, DG2 Shutdown from Control Room D, S 6

c. SKL034-21-135, Operate Reactor Water Sample Valves N, S 5 with Group 7 Present

d. SKL034-20-107, Lowering DEH Pressure Setpoint D, S, A 3 (Alternate Path)

e. SKL034-20-122, Perform Attachment 3 of 2.1.5 Reactor D, S, L, A 2 Water Level Control (Alternate Path)

f. SKL034-22-01, SGT System Support for HPCI Operation P, D, S, A 9 (Alternate Path) g.

h. SKL034-21-138, Withdrawal Of Control Rod From N, S, A 1 Position 00 (Alternate Path)

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 A, D, E, P 6 Actions Alternate Path)

j. SKL034-40-84, 5.3ALT-STRATEGY-Inject Fire Water to D, E, P, L 2 RHR

k. SKL034-11-03, Place Cold Reference Leg Continuous D, A, R 7 Backfill System in Service (Alternate Path)

@ 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 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank <9/<8/<4 (E)mergency or abnormal in-plant >1/>1/>1 (EN)gineered safety feature - / - / >1 (control room system)

(L)ow-Power / Shutdown >1/>1/>1 (N)ew or (M)odified from bank including 1(A) >2/>2/>1 (P)revious 2 exams < 3 / < 3 / < 2 (randomly selected)

(R)CA >1/>1/>1 (S)imulator 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: RO SRO-I SRO-U Operating Test No.: 1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function

a. SKL034-21-134, Establish RPV Cooldown Using MSL N, L, S 4 Drains

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 A, D, E, P 6 Actions Alternate Path)

j. SKL034-40-84, 5.3ALT-STRATEGY-Inject Fire Water to D, E, P, L 2 RHR

k. SKL034-11-03, Place Cold Reference Leg Continuous D, A, R 7 Backfill System in Service (Alternate Path)

@ 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 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank <9/<8/<4 (E)mergency or abnormal in-plant >1/>1/>1 (EN)gineered safety feature - / - / >1 (control room system)

(L)ow-Power / Shutdown >1/>1/>1 (N)ew or (M)odified from bank including 1(A) >2/>2/>1 (P)revious 2 exams < 3 / < 3 / < 2 (randomly selected)

(R)CA >1/>1/>1 (S)imulator ES-301, Page 23 of 27 Rev 3

ES-401 BWR Examination Outline Form ES-401-1 Facility: Cooper Nuclear Station (RO) Date of Exam: November 5, 2012 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 7 Emergency &

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

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

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

1 2 3 1 2 AA1.07 - Ability to operate and/or monitor the following 295001 Partial or Complete Loss of Forced X as they apply to PARTIAL OR COMPLETE LOSS OF 3.1 1 Core Flow Circulation / 1 & 4 FORCED CORE FLOW CIRCULATION: Nuclear boiler instrumentation system 2.2.44 - Ability to interpret control room indications to 295003 Partial or Complete Loss of AC / 6 X verify the status and operation of a system, and 4.2 1 understand how operator actions and directives affect plant and system conditions.

AA2.01 - Ability to determine and/or interpret the 295004 Partial or Total Loss of DC Pwr / 6 X following as they apply to PARTIAL OR COMPLETE 3.2 1 LOSS OF D.C. POWER: Cause of partial or complete loss of D.C. power AA2.07 - Ability to determine and/or interpret the 295005 Main Turbine Generator Trip / 3 X following as they apply to MAIN TURBINE 3.5 1 GENERATOR TRIP: Reactor water level AA1.05 - Ability to operate and/or monitor the following 295006 SCRAM / 1 X as they apply to SCRAM: Neutron monitoring system 4.2 1 AK3.02 - Knowledge of the reasons for the following 295016 Control Room Abandonment / 7 X responses as they apply to CONTROL ROOM 3.7 1 ABANDONMENT: Turbine trip AA1.03 - Ability to operate and/or monitor the following 295018 Partial or Total Loss of CCW / 8 X as they apply to PARTIAL OR COMPLETE LOSS OF 3.3 1 COMPONENT COOLING WATER : Affected systems so as to isolate damaged portions AK2.06 - Knowledge of the interrelations between 295019 Partial or Total Loss of Inst. Air / 8 X PARTIAL OR COMPLETE LOSS OF INSTRUMENT 2.8 1 AIR and the following: Offgas system AA1.01 - Ability to operate and/or monitor the following 295021 Loss of Shutdown Cooling / 4 X as they apply to LOSS OF SHUTDOWN COOLING: 3.4 1 Reactor water cleanup system AK2.07 - Knowledge of the interrelations between 295023 Refueling Acc / 8 X REFUELING ACCIDENTS and the following: Standby 3.6 1 gas treatment/FRVS EA2.06 - Ability to determine and/or interpret the 295024 High Drywell Pressure / 5 X following as they apply to HIGH DRYWELL 4.1 1 PRESSURE: Suppression pool temperature EK1.03 - Knowledge of the operational implications of 295025 High Reactor Pressure / 3 X the following concepts as they apply to HIGH 3.6 1 REACTOR PRESSURE: Safety/relief valve tailpipe temperature/pressure relationships 295026 Suppression Pool High Water X 2.1.20 - Ability to interpret and execute procedure steps. 4.6 1 Temp. / 5 295027 High Containment Temperature / 5 For Mark-III Containments - N/A EK3.02 - Knowledge of the reasons for the following 295028 High Drywell Temperature / 5 X responses as they apply to HIGH DRYWELL 3.5 1 TEMPERATURE: RPV flooding EK2.04 - Knowledge of the interrelations between LOW 295030 Low Suppression Pool Wtr Lvl / 5 X SUPPRESSION POOL WATER LEVEL and the 3.7 1 following: RHR/LPCI EK3.02 - Knowledge of the reasons for the following 295031 Reactor Low Water Level / 2 X responses as they apply to REACTOR LOW WATER 4.4 1 LEVEL: Core coverage EK1.02 - Knowledge of the operational implications of 295037 SCRAM Condition Present X the following concepts as they apply to SCRAM 4.1 1 and Reactor Power Above APRM CONDITION PRESENT AND REACTOR POWER Downscale or Unknown / 1 ABOVE APRM DOWNSCALE OR UNKNOWN :

Reactor water level effects on reactor power Revision 02

EK3.04 - Knowledge of the reasons for the following 295038 High Off-site Release Rate / 9 X responses as they apply to HIGH OFF-SITE RELEASE 3.6 1 RATE: Emergency depressurization AK1.01 - Knowledge of the operation applications of the 600000 Plant Fire On Site / 8 X following concepts as they apply to Plant Fire On Site: 2.5 1 Fire Classifications by type 2.4.2 - Knowledge of system set points, interlocks and 700000 Generator Voltage and Electric Grid X automatic actions associated with EOP entry conditions. 4.5 1 Disturbances / 6 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 K K A A G K/A Topic(s) IR #

1 2 3 1 2 AK2.02 - Knowledge of the interrelations between LOSS 295002 Loss of Main Condenser Vac / 3 X OF MAIN CONDENSER VACUUM and the following: 3.1 1 Main turbine 2.1.7 - Ability to evaluate plant performance and make 295007 High Reactor Pressure / 3 X operational judgments based on operating characteristics, 4.4 1 reactor behavior, and instrument interpretation.

AK1.01 - Knowledge of the operational implications of the 295008 High Reactor Water Level / 2 X following concepts as they apply to HIGH REACTOR 3.0 1 WATER LEVEL : Moisture carryover 295009 Low Reactor Water Level / 2 AA2.02 - Ability to determine and/or interpret the following 295010 High Drywell Pressure / 5 X as they apply to HIGH DRYWELL PRESSURE: Drywell 3.8 1 pressure 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 AK3.04 - Knowledge of the reasons for the following 295017 High Off-site Release Rate / 9 X responses as they apply to HIGH OFF-SITE RELEASE 3.6 1 RATE: Power reduction 295020 Inadvertent Cont. Isolation / 5 & 7 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 1 LEVEL: 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 EA2.01 - Ability to determine and/or interpret the following 295035 Secondary Containment High X as they apply to SECONDARY CONTAINMENT HIGH 3.8 1 Differential Pressure / 5 DIFFERENTIAL PRESSURE: Secondary containment pressure: Plant-Specific 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 ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO / 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 K3.01 - Knowledge of the effect that a loss or 203000 RHR/LPCI: Injection X malfunction of the RHR/LPCI: INJECTION 4.3 1 Mode MODE (PLANT SPECIFIC) will have on following: Reactor water level K4.02 - Knowledge of SHUTDOWN COOLING 205000 Shutdown Cooling X X SYSTEM (RHR SHUTDOWN COOLING 3.7 2 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 3.5 malfunction of the following will have on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE): RHR service water: Plant-Specific K1.12 - Knowledge of the physical connections 206000 HPCI X and/or cause-effect relationships between HIGH 3.4 1 PRESSURE COOLANT INJECTION SYSTEM and the following: Nuclear boiler instrumentation:

BWR-2,3,4 207000 Isolation (Emergency) Not part of plant design - N/A Condenser A1.05 - Ability to predict and/or monitor changes 209001 LPCS X in parameters associated with operating the LOW 3.5 1 PRESSURE CORE SPRAY SYSTEM controls including: Torus/suppression pool water level 209002 HPCS BWR-5, 6 specific K/A - N/A K3.02 - Knowledge of the effect that a loss or 211000 SLC X X malfunction of the STANDBY LIQUID 3.0 2 CONTROL SYSTEM will have on following:

Core spray line break detection system: Plant-Specific A1.09 - Ability to predict and/or monitor changes 4.0 in parameters associated with operating the STANDBY LIQUID CONTROL SYSTEM controls including: SBLC system lineup A2.12 - Ability to (a) predict the impacts of the 212000 RPS X following on the REACTOR PROTECTION 4.0 1 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 K6.02 - Knowledge of the effect that a loss or 215003 IRM X X malfunction of the following will have on the 3.6 2 INTERMEDIATE RANGE MONITOR (IRM)

SYSTEM : 24/48 volt D.C. power: Plant-Specific A3.02 - Ability to monitor automatic operations of 3.2 the INTERMEDIATE RANGE MONITOR (IRM)

SYSTEM including: Annunciator and alarm signals 2.1.27 - Knowledge of system purpose and/or 215004 Source Range Monitor X function. 3.9 1 Revision 02

A4.04 - Ability to manually operate and/or 215005 APRM / LPRM X monitor in the control room: LPRM back panel 3.2 1 switches, meters and indicating lights K1.02 - Knowledge of the physical connections 217000 RCIC X and/or cause-effect relationships between 3.5 1 REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) and the following: Nuclear boiler system A1.04 - Ability to predict and/or monitor changes 218000 ADS X in parameters associated with operating the 4.1 1 AUTOMATIC DEPRESSURIZATION SYSTEM controls including: Reactor pressure K6.08 - Knowledge of the effect that a loss or 223002 PCIS/Nuclear Steam X malfunction of the following will have on the 3.5 1 Supply Shutoff PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF: Reactor protection system K3.03 - Knowledge of the effect that a loss or 239002 SRVs X X malfunction of the RELIEF/SAFETY VALVES 4.3 2 will have on following: Ability to rapidly depressurize the reactor K5.04 - Knowledge of the operational implications 3.3 of the following concepts as they apply to RELIEF/SAFETY VALVES : Tail pipe temperature monitoring A4.01 - Ability to manually operate and/or 259002 Reactor Water Level X monitor in the control room: All individual 3.8 1 Control component controllers in the manual mode A2.11 - Ability to (a) predict the impacts of the 261000 SGTS X following on the STANDBY GAS TREATMENT 3.2 1 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 2.2.36 - Ability to analyze the effect of 262001 AC Electrical X maintenance activities, such as degraded power 3.1 1 Distribution sources, on the status of limiting conditions for operations.

A3.01 - Ability to monitor automatic operations of 262002 UPS (AC/DC) X the UNINTERRUPTABLE POWER SUPPLY 2.8 1 (A.C./D.C.) including: Transfer from preferred to alternate source K2.01 - Knowledge of electrical power supplies to 263000 DC Electrical X X the following: Major D.C. loads 3.1 2 Distribution K5.01 - Knowledge of the operational implications of the following concepts as they apply to D.C. 2.6 ELECTRICAL DISTRIBUTION: Hydrogen generation during battery charging A4.05 - Ability to manually operate and/or 264000 EDGs X monitor in the control room: Transfer of 3.6 1 emergency generator (with load) to grid K4.02 - Knowledge of (INSTRUMENT AIR 300000 Instrument Air X SYSTEM) design feature(s) and or interlocks 3.0 1 which provide for the following: Cross-over to other air systems 400000 Component Cooling X K2.01 - Knowledge of electrical power supplies to 2.9 1 Water the following: CCW pumps 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 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 A1.03 - Ability to predict and/or monitor 201003 Control Rod and Drive X changes in parameters associated with 2.9 1 Mechanism operating the CONTROL ROD AND DRIVE MECHANISM controls including:

CRD drive water flow No RSCS at Cooper - N/A 201004 RSCS 201005 RCIS BWR-6 Only - N/A 201006 RWM K4.04 - Knowledge of RECIRCULATION 202001 Recirculation X System design feature(s) and/or interlocks 3.0 1 which provide for the following: Controlled seal flow K1.02 - Knowledge of the physical 202002 Recirculation Flow Control X connections and/or cause-effect relationships 4.2 1 between RECIRCULATION FLOW CONTROL SYSTEM and the following:

Reactor power 204000 RWCU X 2.4.41 - Knowledge of the emergency action 2.9 1 level thresholds and classifications.

K5.01 - Knowledge of the operational 214000 RPIS X implications of the following concepts as 2.7 1 they apply to ROD POSITION INFORMATION SYSTEM : Reed switches 215001 Traversing In-core Probe A4.02 - Ability to manually operate and/or 215002 RBM X monitor in the control room: RBM back 2.9 1 panel switches, meters and indicating lights:

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

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

K2.02 - Knowledge of electrical power 226001 RHR/LPCI: CTMT Spray Mode X supplies to the following: Pumps 2.9 1 230000 RHR/LPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment K6.09 - Knowledge of the effect that a loss 239001 Main and Reheat Steam X or malfunction of the following will have on 3.9 1 the MAIN AND REHEAT STEAM SYSTEM: PCIS/NSSSS 239003 MSIV Leakage Control K3.10 - Knowledge of the effect that a loss 241000 Reactor/Turbine Pressure X or malfunction of the REACTOR/TURBINE 2.9 1 Regulator PRESSURE REGULATING SYSTEM will have on following: Front standard trip system Revision 02

A2.05 - Ability to (a) predict the impacts of 245000 Main Turbine Gen. / Aux. X the following on the MAIN TURBINE 3.6 1 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 256000 Reactor Condensate 259001 Reactor Feedwater 268000 Radwaste 271000 Offgas 272000 Radiation Monitoring 286000 Fire Protection 288000 Plant Ventilation K6.08 - Knowledge of the effect that a loss 290001 Secondary CTMT X or malfunction of the following will have on 2.7 1 the SECONDARY CONTAINMENT : Plant air systems 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 #

Knowledge of individual licensed operator responsibilities 2.1.4 3.3 1 related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, 1.

etc.

Conduct of Operations 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.

Subtotal 3 Ability to perform pre-startup procedures for the facility, 2.2.1 4.5 1 including operating those controls associated with plant equipment that could affect reactivity.

Ability to analyze the effect of maintenance activities, such as

2. 2.2.36 3.1 1 degraded power sources, on the status of limiting conditions for Equipment operations.

Control 2.2.

2.2.

Subtotal 2 2.3.11 Ability to control radiation releases. 3.8 1 Knowledge of radiological safety principles pertaining to 2.3.12 3.2 1 licensed operator duties, such as containment entry

3. requirements, fuel handling responsibilities, access to locked Radiation high-radiation areas, aligning filters, etc.

Control 2.3.

2.3.

Subtotal 2 2.4.18 Knowledge of the specific bases for EOPs. 3.3 1 Knowledge of the bases for prioritizing emergency procedure 2.4.23 3.4 1

4. implementation during emergency operations.

Emergency Procedures / 2.4.27 Knowledge of fire in the plant procedures. 3.4 1 Plan 2.4.

2.4.

Subtotal 3 Tier 3 Point Total 10 7 Revision 02

ES-401 BWR Examination Outline Form ES-401-1 Facility: Cooper Nuclear Station (SRO) Date of Exam: November 5, 2012 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 20 4 3 7 Emergency &

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

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

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