NLS2021019, CN-2021-06 Draft Outlines

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CN-2021-06 Draft Outlines
ML21230A348
Person / Time
Site: Cooper Entergy icon.png
Issue date: 02/22/2021
From: Dewhirst L, Florence J, Heather Gepford, Joe M
Nebraska Public Power District (NPPD)
To: Kelly Clayton
Operations Branch IV
References
NLS2021019
Download: ML21230A348 (17)
v • d • e


Text

N Nebraska Public Power District Alway there when you need. us NLS2021019 February 22,2021 Regional Administrator Region IV ATTN: Mr. Kelly Clayton U.S. Nuclear Regulatory Commission 1600 East Lamar Boulevard Arlington, TX 7601 1-45 1 I

Subject:

Initial Operator License Retake Examination Outline Cooper Nuclear Station, Docket No. 50-298, DPR-46

Reference:

Teleconference between the U.S. Nuclear Regulatory Commission's Mr. Kelly Clayton and Cooper Nuclear Station's Facility Reviewer James Florence on January 14,2021

Dear Sir:

Please find enclosed the operating test outlines to support the initial license retake examination scheduled in June 2021. A written examination (RO only) will be administered on June 25, 2021, and an operating test (SRO-I JPMs only) will be administered the week of June28,202l The outlines were requested by the Nuclear Regulatory Commission (NRC) Region IV offices during the NRC retake examination teleconference per the Reference.

This submittal was prepared in accordance with NUREG-1021, Revision 11 "Operator Licensing Examination Standards for Power Reactors" and provides the following documents:

. Examination Outline Quality Checklist (Form ES-201-2)

. Examination Security Agreement (Form ES-201-3)

. Administrative Topics Outline (Form ES-301-1)

. Control Room / In-Plant Systems Outline (Form ES-301-2)

. BWR Examination Outline (Form ES-401-1)

. Generic Knowledge and Abilities Outline (Tier 3) (Form ES-401-3)

. Record of Rejected I?As (Form ES-401-4)

In accordance with NUREG-1021, Revision 11, Section ES-201, "Initial Operator Licensing Examination Process," please ensure that these materials are withheld from public disclosure until after the examinations are complete.

Individuals identified in this correspondence, whether by name andlor title, which are not explicitly identified on the Examination Security Agreement, have no knowledge regarding the content of the enclosed examination outlines.

COOPER NUCTEARSTATION P.O. Box 98 / Brownville, NE 68321-0098 Telephone: (402) 825-38n / Fax: (402) 825-5211 www.nppd.com

NLS2021019 Page2 of 2 This letter contains no commitments.

Pursuant to Title 10, Section 55.40(bX3), of the Code of Federal Regulations, authorized representatives of the facility licensee approved these examination outlines being submitted to the NRC.

James B. Facility Reviewer Mi oe, Training Manager Should you have any questions or require additional information, please contact Mick Joe, Training Manager at(402) 825-5365, James B. Florence, Facility Reviewer at(402) 825-5700, or Kyle Grillis, Lead Examination Writer at (601) 953-6402.

Regulatory Affairs & Compliance Manager

/io cc Training Manager Assistant Operations Manager -

Cooper Nuclear Station Training Cooper Nuclear Station Operations Training Superintendent Cooper Nuclear Station CNS Records

ES-401 1 Form ES-401-1 Facility: Cooper Nuclear Station Date of Exam: June 2021 Tier Group RO K/A Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 3 3 4 4 3 3 20 7 Emergency and N/A N/A 2 1 1 1 1 2 1 7 3 Abnormal Plant Evolutions Tier Totals 4 4 5 5 5 4 27 10 1 2 3 2 3 2 2 3 2 3 2 2 26 5 2.

Plant 2 1 1 2 1 1 1 1 1 1 1 1 12 N/A 3 Systems Tier Totals 3 4 4 4 3 3 4 3 4 3 3 38 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 3 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 outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 radiation control K/A is allowed if it is replaced by a K/A from another Tier 3 category.)
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 outline. Systems or evolutions that do not apply at the facility should be deleted with justification. 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. 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 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 a category 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.

G* Generic K/As

  • These systems/evolutions must be included as part of the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the K/A catalog.
    • These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan.

ES-401 2 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #

AK3.04 - Knowledge of the reasons for the 295001 (APE 1) Partial or Complete Loss of 04 following responses as they apply to Partial 4.1 1 Forced Core Flow Circulation / 1 & 4 or Complete Loss of Forced Core Flow Circulation: Reactor SCRAM.

(CFR: 41.5 / 45.6)

AA1.02 - Ability to operate and/or monitor 295003 (APE 3) Partial or Complete Loss of 02 the following as they apply to Partial or 4.5 2 AC Power / 6 Complete Loss of AC Power: Emergency Generators.

(CFR: 41.7 / 45.6)

AA2.03 - Ability to determine and/or 295004 (APE 4) Partial or Total Loss of DC 03 interpret the following as they apply to 3.8 3 Power / 6 Partial or Complete Loss of DC Power:

Battery parameters.

(CFR: 41.10 / 43.5 / 45.13)

AA2.01 - Ability to determine and/or 01 interpret the following as they apply to 4.0 Partial or Complete Loss of DC Power:

Partial or complete loss of DC power.

(CFR: 41.10 / 43.5 / 45.13)

G2.4.2 - Knowledge of system setpoints, 295005 (APE 5) Main Turbine Generator Trip / 04. interlocks and automatic actions associated 4.5 4 3 02 with emergency and abnormal operating procedure entry conditions.

(CFR: 41.7 / 45.7 / 45.8)

AK1.02 - Knowledge of the operational 295006 (APE 6) Scram / 1 02 implications and/or cause and effect 3.6 5 relationships of the following as they apply to SCRAM: Shutdown margin.

(CFR: 41.8 to 41.10)

AK2.05 - Knowledge of the relationship 295016 (APE 16) Control Room Abandonment 05 between Control Room Abandonment and 3.5 6

/7 the following systems or components: DC electrical distribution.

(CFR: 41.8 / 45.8)

AK2.06 - Knowledge of the relationship 06 between Control Room Abandonment and 3.8 the following systems or components:

Safety/relief valves.

(CFR: 41.8 / 45.8)

AK3.01 - Knowledge of the reasons for the 295018 (APE 18) Partial or Complete Loss of 01 following responses or actions as they apply 3.4 7 CCW / 8 to Partial or Complete Loss of Component Cooling Water: Isolation of non-essential heat loads.

(CFR: 41.5 / 45.6)

AA1.03 - Ability to operate and/or monitor 295019 (APE 19) Partial or Complete Loss of 03 the following as they apply to Partial or 3.5 8 Instrument Air / 8 Complete Loss of Instrument Air: Air compressors.

(CFR: 41.7 / 45.6)

AA2.07 - Ability to determine and/or 295021 (APE 21) Loss of Shutdown Cooling / 07 interpret the following as they apply to Loss 3.8 9 4 of Shutdown Cooling: Reactor recirculation flow.

(CFR: 41.10 / 43.5 / 45.13)

G2.4.20 - Knowledge of the operational 295023 (APE 23) Refueling Accidents / 8 04. implications of emergency and abnormal 3.8 10 20 operating procedures warnings, cautions, and notes.

(CFR: 41.10 / 43.5 / 45.13)

ES-401 3 Form ES-401-1 EK1.01 - Knowledge of the operational 295024 High Drywell Pressure / 5 01 implications and/or cause and effect 4.3 11 relationships of the following as they apply to High Drywell Pressure: Drywell integrity.

(CFR: 41.8 to 41.10)

EK2.12 - Knowledge of the relationship 295025 (EPE 2) High Reactor Pressure / 3 12 between High Reactor Pressure and the 3.1 12 following systems or components: Main and reheat steam system.

(CFR: 41.7 / 45.8)

EK3.04 - Knowledge of the reasons for the 295026 (EPE 3) Suppression Pool High Water 04 following responses as they apply to 3.6 13 Temperature / 5 Suppression Pool High Water Temperature:

SLCS injection.

(CFR: 41.5 / 45.6) 295027 (EPE 4) High Containment Temperature (Mark III Containment Only) / 5 EA1.05 - Ability to operate and/or monitor 295028 (EPE 5) High Drywell Temperature 05 the following as they apply to High Drywell 3.8 14 (Mark I and Mark II only) / 5 Temperature: Safety relief valves.

(CFR: 41.7 / 45.6)

EA2.05 - Ability to determine and/or 295030 (EPE 7) Low Suppression Pool Water 05 interpret the following as they apply to Low 4.1 15 Level / 5 Suppression Pool Water Level: ECCS/RCIC pump flow.

(CFR: 41.10 / 43.5 / 45.13)

G2.4.18 - Knowledge of the specific bases 295031 (EPE 8) Reactor Low Water Level / 2 04. for emergency and abnormal operating 3.3 16 18 procedures.

(CFR: 41.10 / 43.1 / 45.13)

EK1.04 - Knowledge of the operational 295037 (EPE 14) Scram Condition Present 04 implications and/or cause and effect 3.7 17 and Reactor Power Above APRM Downscale relationships of the following as they apply or Unknown / 1 to SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown: Hot shutdown boron weight.

(CFR: 41.8 / 41.10)

EK2.09 - Knowledge of the relationship 295038 (EPE 15) High Offsite Radioactivity 09 between High Offsite Radioactivity Release 3.0 18 Release Rate / 9 Rate and the following systems or components: Post-accident sample system.

(CFR: 41.7 / 45.8)

AK3.04 - Knowledge of the reasons for the 600000 (APE 24) Plant Fire On Site / 8 04 following responses or actions as they apply 3.6 19 to Plant Fire on Site: Actions contained in the fire response procedures for a plant fire on site.

(CFR: 41.5, 41.10 / 45.6 / 45.13)

AA1.02 - Ability to operate and/or monitor 700000 (APE 25) Generator Voltage and 02 the following as they apply to Generator 3.4 20 Electric Grid Disturbances / 6 Voltage and Electric Grid Disturbances:

Turbine/generator controls.

(CFR: 41.5 / 41.10 / 45.5 / 45.7 / 45.8)

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

ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #

AA1.06 - Ability to operate and/or monitor the 295002 (APE 2) Loss of Main Condenser 06 following as they apply to Loss of Main 3.6 21 Vacuum / 3 Condenser Vacuum: Reactor/turbine pressure regulating system.

(CFR: 41.7 / 45.6) 295007 (APE 7) High Reactor Pressure / 3 295008 (APE 8) High Reactor Water Level / 2 295009 (APE 9) Low Reactor Water Level / 2 295010 (APE 10) High Drywell Pressure / 5 295011 (APE 11) High Containment Temperature (Mark III Containment only) / 5 AA2.03 - Ability to determine and/or interpret the 295012 (APE 12) High Drywell Temperature / 03 following as they apply to High Drywell 2.8 22 5 Temperature: Drywell Humidity.

(CFR: 41.10 / 43.5 / 45.13)

G2.4.31 - Knowledge of annunciator 295013 (APE 13) High Suppression Pool 04. alarms, indications, or response 4.2 23 Temperature. / 5 31 procedures.

(CFR: 41.10 / 43.5 / 45.11)

AK1.06 - Knowledge of the operational 295014 (APE 14) Inadvertent Reactivity 06 implications and/or cause and effect relationships 4.3 24 Addition / 1 of the following as they apply to Inadvertent Reactivity Addition: Reactivity changes.

(CFR: 41.8 / 41.10) 295015 (APE 15) Incomplete Scram / 1 295017 (APE 17) Abnormal Offsite Release Rate / 9 295020 (APE 20) Inadvertent Containment Isolation / 5 & 7 295022 (APE 22) Loss of Control Rod Drive Pumps / 1 EK2.01 - Knowledge of the relationship between 295029 (EPE 6) High Suppression Pool Water 01 High Suppression Pool Water Level and the 3.1 25 Level / 5 following systems or components: RHR/LPCI.

(CFR: 41.7 / 45.8) 295032 (EPE 9) High Secondary Containment Area Temperature / 5 295033 (EPE 10) High Secondary Containment Area Radiation Levels / 9 295034 (EPE 11) Secondary Containment Ventilation High Radiation / 9 EK3.02 - Knowledge of the reasons for the 295035 (EPE 12) Secondary Containment 02 following responses or actions as they apply to 3.7 26 High Differential Pressure / 5 Secondary Containment High Differential Pressure: Secondary containment ventilations alignment.

(CFR: 41.5 / 45.6) 295036 (EPE 13) Secondary Containment High Sump/Area Water Level / 5 EA2.05 - Ability to determine and/or interpret the 500000 (EPE 16) High Containment Hydrogen 05 following as they apply to High Containment 3.4 27 Concentration / 5 Hydrogen Concentration: Hydrogen concentration limits for containment.

(CFR: 41.10 / 43.5 / 45.13)

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

ES-401 5 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant SystemsTier 2/Group 1 (RO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #

203000 (SF2, SF4 RHR/LPCI) 04 K3.04 - Knowledge of the effect that a loss or 4.3 28 malfunction of the RHR/LPCI: Injection Mode will RHR/LPCI: Injection Mode have on the following systems or system parameters: Adequate core cooling.

(CFR: 41.7 / 45.4) 205000 (SF4 SCS) Shutdown Cooling 08 K4.08 - Knowledge of Shutdown Cooling System 4.1 29 (RHR Shutdown Cooling Mode) design features and/or interlocks that provide for the following:

Prevent inadvertent vessel draining.

(CFR: 41.7) 206000 (SF2, SF4 HPCIS) 13 K4.13 - Knowledge of High-Pressure Coolant 3.2 30 Injection System design features and/or interlocks High-Pressure Coolant Injection that provide for the following: Turbine and pump lubrication.

(CFR: 41.7)

K5.02 - Knowledge of the operational implications 02 or cause and effect relationships of the following 2.6 31 concepts as they apply to the High-Pressure Coolant Injection System: Turbine shaft sealing.

(CFR: 41.5 / 45.3) 207000 (SF4 IC) Isolation (Emergency) Condenser 209001 (SF2, SF4 LPCS) 13 K6.13 - Knowledge of the effect of the following 4.3 32 plant conditions, system malfunctions, or Low-Pressure Core Spray component malfunctions on the Low-Pressure Core Spray System: High drywell pressure.

(CFR: 41.7 / 45.7) 209002 (SF2, SF4 HPCS)

High-Pressure Core Spray 211000 (SF1 SLCS) Standby Liquid 10 A1.10 - Ability to predict or monitor changes in 3.6 33 parameters associated with operation of the Control Standby Liquid Control System, including: Lights and alarms.

(CFR: 41.5 / 45.5) 212000 (SF7 RPS) Reactor Protection 01 A2.01 - Ability to (a) predict the impacts of the 3.9 34 following on the Reactor Protection System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: RPS motor-generator set failure.

(CFR: 41.5 / 45.6) 215003 (SF7 IRM) 04 A3.04 - Ability to monitor automatic operation of 3.9 35 the Intermediate Range Monitor System, including:

Intermediate-Range Monitor Control rod block signals.

(CFR: 41.7 / 45.7) 215004 (SF7 SRMS) Source-Range 08 A4.08 - Ability to manually operate and/or monitor 3.4 36 in the control room: SRMS channel bypass.

Monitor (CFR: 41.7 / 45.5 to 45.8) 215005 (SF7 PRMS) Average Power 02 K2.02 - Knowledge of electrical power supplies to 3.7 37 the following: APRM channels.

Range Monitor/Local Power Range (CFR: 41.7)

Monitor G2.2.22 - Knowledge of limiting conditions for

02. operation and safety limits. 4.0 38 22 (CFR: 41.5 / 43.2 / 45.2) 217000 (SF2, SF4 RCIC) Reactor 09 K1.09 - Knowledge of the physical connections 3.3 39 and/or cause and effect relationships between the Core Isolation Cooling Reactor Core Isolation Cooling System and the following systems: Reactor vessel and internals.

(CFR: 41.2 to 41.9 / 45.7 to 45.8) 218000 (SF3 ADS) Automatic 01 K2.01 - Knowledge of electrical power supplies to 4.0 40 the following: ADS logic.

Depressurization (CFR: 41.7) 223002 (SF5 PCIS) Primary 15 K3.15 - Knowledge of the effect that a loss or 4.0 41 malfunction of the Primary Containment Isolation Containment Isolation/Nuclear Steam System/Nuclear Steam Supply Shutoff will have Supply Shutoff on the following system or system parameters:

Reactor core isolation cooling.

(CFR: 41.7 / 45.4)

ES-401 6 Form ES-401-1 239002 (SF3 SRV) Safety Relief 09 K4.09 - Knowledge of Safety Relief Valves design 4.0 42 features and/or interlocks that provide for the Valves following: Manual opening of the SRV.

(CFR: 41.7) 01 A3.01 - Ability to monitor automatic operation of 4.1 43 the Safety Relief Valves, including: SRV operation after ADS actuation.

(CFR: 41.7 / 45.7) 259002 (SF2 RWLCS) Reactor Water 06 K5.06 - Knowledge of the operational implications 3.2 44 or cause and effect relationships of the following Level Control concepts as they apply to the Reactor Water Level Control System: Pump runout.

(CFR: 41.5 / 45.3)

A1.07 - Ability to predict and/or monitor changes 07 in parameters associated with operation of the 3.3 45 Reactor Water Level Control System, including:

TDRFP speed.

(CFR: 41.5 / 45.5) 261000 (SF9 SGTS) Standby Gas 09 K6.09 - Knowledge of the effect of the following 3.4 46 plant conditions, system malfunctions, or Treatment component malfunctions on the Standby Gas Treatment System: Primary containment high pressure.

(CFR: 41.7 / 45.7) 262001 (SF6 AC) AC Electrical 07 A1.07 - Ability to predict and/or monitor changes 3.2 47 in parameters associated with operation of the AC Distribution Electrical Distribution, including: System frequency.

(CFR: 41.5 / 45.5) 262002 (SF6 UPS) Uninterruptable 05 A2.05 - Ability to (a) predict the impacts of the 3.8 48 following on the Uninterruptible Power Supply Power Supply (AC/DC) (AC/DC) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: Loss of UPS.

(CFR: 41.5 / 43.5 / 45.6) 263000 (SF6 DC) DC Electrical 03 A3.03 - Ability to monitor automatic operation of 3.3 49 the DC Electrical Distribution, including: Transfers.

Distribution (CFR: 41.7 / 45.7)

A3.02 - Ability to monitor automatic operation of 02 the DC Electrical Distribution, including: 3.5 Breaker trips.

(CFR: 41.7 / 45.7) 264000 (SF6 EGE) Emergency 03 A4.03 - Ability to manually operate and/or monitor 3.6 50 in the control room: Transfer of emergency control Generators (Diesel/Jet) EDG between manual and automatic.

(CFR: 41.7 / 45.5 to 45.8) 300000 (SF8 IA) Instrument Air 01. G2.1.30 - Ability to locate and operate 4.4 51 components, including local controls.

30 (CFR: 41.7 / 45.7) 400000 (SF8 CCS) Component 18 K1.18 - Knowledge of the physical connections 3.1 52 and/or cause and effect relationships between Cooling Water Component Cooling Water System and the following systems: Reactor condensate system.

(CFR: 41.4 to 41.5 / 41.7 to 41.9 / 45.6 to 45.8)

K1.13 - Knowledge of the physical connections 13 and/or cause and effect relationships between 3.6 Component Cooling Water System and the following systems:

Reactor water cleanup system.

(CFR: 41.4 to 41.5 / 41.7 to 41.9 / 45.6 to 45.8) 510000 (SF4 SWS*) Service Water 02 K2.02 - Knowledge of electrical power supplies to 3.4 53 the following: Service water system valves (Class (Normal and Emergency) 1E).

(CFR: 41.7)

K/A Category Point Totals: 2 3 2 3 2 2 3 2 3 2 2 Group Point Total: 26

ES-401 7 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant SystemsTier 2/Group 2 (RO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #

201001 (SF1 CRDH) CRD Hydraulic 201002 (SF1 RMCS) Reactor Manual Control K3.02 - Knowledge of the effect that a 02 loss or malfunction of the Reactor Manual 3.4 54 Control System will have on the following 3.2 systems or system parameters: Rod block monitor (CFR: 41.7 / 45.4) 201003 (SF1 CRDM) Control Rod and Drive Mechanism 201004 (SF7 RSCS) Rod Sequence Control 201005 (SF1, SF7 RCIS) Rod Control and Information 201006 (SF7 RWMS) Rod Worth Minimizer K4.06 - Knowledge of Rod Worth 06 Minimizer System design features and/or 3.5 55 interlocks that provide for the following:

Correction of out-of-sequence rod positions.

(CFR: 41.7) 202001 (SF1, SF4 RS) Recirculation 202002 (SF1 RSCTL) Recirculation Flow Control K5.08 - Knowledge of the operational 08 implications or cause and effect 3.7 56 relationships of the following concepts as they apply to the Recirculation Flow Control System: Reactor water level.

(CFR: 41.5 / 45.3) 204000 (SF2 RWCU) Reactor Water Cleanup K6.02 - Knowledge of the effect of the 02 following plant conditions, system 2.6 57 malfunctions, or component malfunctions on the Reactor Water Cleanup System:

Main condenser.

(CFR: 41.7 / 45.7) 214000 (SF7 RPIS) Rod Position Information 215001 (SF7 TIP) Traversing In-Core Probe 215002 (SF7 RBMS) Rod Block Monitor 216000 (SF7 NBI) Nuclear Boiler Instrumentation 219000 (SF5 RHR SPC) RHR/LPCI:

Torus/Suppression Pool Cooling Mode 223001 (SF5 PCS) Primary Containment and A3.06 - Ability to monitor automatic 06 operation of the PCS and Aux, including: 3.9 60 Auxiliaries Drywell/suppression chamber differential pressure (CFR: 41.7 / 45.7) 226001 (SF5 RHR CSS) RHR/LPCI: Containment A1.04 - Ability to predict and/or monitor 04 changes in parameters associated with 3.9 58 Spray Mode operation of the RHR/LPCI: Containment Spray System Mode, including:

Suppression pool temperature (Mark I, II)

(CFR: 41.5 / 45.5) 230000 (SF5 RHR SPS) RHR/LPCI:

Torus/Suppression Pool Spray Mode 233000 (SF9 FPCCU) Fuel Pool Cooling/Cleanup A2.14 - Ability to (a) predict the impacts 14 of the following on the Fuel Pool Cooling 3.1 59 and Cleanup and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: Low system flow.

(CFR: 41.5 / 43.5 / 45.6) 234000 (SF8 FH) Fuel-Handling Equipment 239001 (SF3, SF4 MRSS) Main and Reheat Steam A4.02 - Ability to manually operate and/or 02 monitor in the control room: Main steam 3.4 61 line drain valves.

(CFR: 41.7 / 45.5 to 45.8)

ES-401 8 Form ES-401-1 239003 (SF9 MSVLCS) Main Steam Isolation Valve G2.1.23 - Ability to perform general or

01. normal operating procedures during any 4.3 62 Leakage Control 23 plant condition.

(CFR: 41.10 / 43.5 / 45.2 / 45.6) 241000 (SF3 RTPRS) Reactor/Turbine Pressure Regulating 245000 (SF4 MTGEN) Main Turbine K2.01 - Knowledge of electrical power 01 supplies to the following: Stator water 2.9 63 Generator/Auxiliary cooling pumps.

(CFR: 41.7) 256000 (SF2 CDS) Condensate 259001 (SF2 FWS) Feedwater 268000 (SF9 RW) Radwaste 271000 (SF9 OG) Offgas K1.05 - Knowledge of the physical 05 connections and/or cause and effect 3.1 64 relationships between the Offgas System and the following systems: Radwaste system.

(CFR: 41.4 to 41.5, 41.7, 41.13 / 45.6 to 45.8) 272000 (SF7, SF9 RMS) Radiation Monitoring 286000 (SF8 FPS) Fire Protection 288000 (SF9 PVS) Plant Ventilation 290001 (SF5 SC) Secondary Containment 290003 (SF9 CRV) Control Room Ventilation K3.04 - Knowledge of the effect that a 04 loss or malfunction of the Control Room 3.4 65 Ventilation will have on the following systems or system parameters: Control room pressure.

(CFR: 41.7 / 45.6) 290002 (SF4 RVI) Reactor Vessel Internals 51001 (SF8 CWS*) Circulating Water K/A Category Point Totals: 1 1 2 1 1 1 1 1 1 1 1 Group Point Total: 12

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Cooper Nuclear Station Date of Exam: June 2021 Category K/A # Topic RO SRO-only IR # IR #

Ability to use procedures related to shift staffing, such as minimum crew complement or overtime limitations (reference 2.1.5 potential). 2.9 66 (CFR: 41.10 / 43.5 / 45.12)

Knowledge of criteria or conditions that require plantwide announcements, such as pump starts, reactor trips, and mode 2.1.14 changes. 3.1 67 (CFR: 41.10, 43.5 / 45.12)

Knowledge of RCS or balance of plant chemistry controls, 2.1.34 including parameters measures and reasons for the control. 2.7 68 (CFR: 41.0 / 43.5 / 45.12)

Subtotal 3 Knowledge of the process for making changes to procedures.

2.2.6 3.0 69 (CFR: 41.10 / 43.3 / 45.13)

Knowledge of the process for managing troubleshooting 2.2.20 activities.

(CFR: 41.10 / 43.5 / 45.13) 2.6 70

2. Equipment Control 2.2.22 Knowledge of limiting conditions for operation and safety limits 4.0 (CFR: 41.5 / 43.2 / 45.2)

Ability to obtain and interpret station electrical and mechanical 2.2.41 drawings (reference potential). 3.5 71 (CFR: 41.10 / 45.12 / 45.13)

Subtotal 3 Ability to use radiation monitoring systems, such as fixed 2.3.5 radiation monitors and alarms or personnel monitoring equipment. 2.9 72

3. Radiation Control (CFR: 41.11 / 41.12 / 43.4 / 45.9)

Ability to control radiation releases.

2.3.11 3.8 73 (CFR: 41.11 / 43.4 / 45.10)

Subtotal 2 Knowledge of general guidelines for emergency and abnormal 2.4.14 operating procedure usage. 3.8 74 (CFF: 41.10 / 43.1 / 45.13)

4. Emergency Knowledge of RO responsibilities in emergency plan Procedures/Plan 2.4.39 implementing procedures. 3.9 75 (CFR: 41.10 / 45.11)

Subtotal 2 Tier 3 Point Total 10

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A RO T1/G1 295004 (Q#3) Could not develop a psychometrically sound RO level question with three plausible distractors. Replaced 295004 AA2.03 with AA2.01.

295004 AA2.01 Tier totals are not affected by this change.

AA2.03 RO T1/G1 295016 (Q#6) Could not develop a psychometrically sound RO level question with three plausible distractors. Since CNS procedures for control 295016 AK2.06 room abandonment do not require actions directly related to DC AK2.05 electrical distribution, could not develop a question that satisfies the intent of Tier 1. Replaced 295016 AK2.05 with AK2.06. Tier totals are not affected by this change.

RO T3 G2.2.22 (Q#70) Could not develop a psychometrically sound RO level question with three plausible distractors. Replaced G2.2.20 with G2.2.22. Tier G2.2.20 totals are not affected by this change.

RO T2/G1 263000 (Q#49) Replaced K/A 263000 A3.03 regarding auto transfers of DC distribution with K/A 263000 A3.02, because CNS DC distribution does 263000 A3.02 not utilize auto transfers, only manual. Tier totals are not affected by A3.03 this change.

RO T2/G1 400000 (Q#52) Replaced K/A 400000 K1.18, related to reactor condensate system, with K/A 400000 K1.13, related to RWCU, because REC 400000 K1.13 (CCWS) at CNS does not interface with reactor condensate system.

K1.18 Tier totals are not affected by this change.

Revision statement:

Rev 2

  • For Q#3, replaced original K/A 295004 AA2.03 related to battery parameters with 295004 AA2.03 related to loss of DC power, since CNS procedures for loss of DC do not require operators to assess battery parameters, and assessment of battery parameters is SRO level for TS 3.8.6. Tier totals were not affected by this change.
  • For Q#6, replaced original K/A 295016 AK2.05 related to DC electrical distribution with 295016 AK2.06 related to SRVs, since CNS procedures for control room abandonment do not address actions directly related to DC electrical distribution that are at the required RO knowledge level.
  • For Q#54, corrected IR for K/A 201002 K3.02 from 3.4 to 3.2.
  • For Q#70, replaced original K/A G2.2.20 with G2.2.22 because ROs do not manage troubleshooting activities at CNS. That is SRO only level.
  • For Q#49, replaced K/A 263000 A3.03 regarding auto transfers of DC distribution with K/A 263000 A3.02, because CNS DC distribution does not utilize auto transfers, only manual.

Rev 3

  • For Q#52, replaced K/A 400000 K1.18, related to reactor condensate system, with K/A 400000 K1.13, related to RWCU, because REC (CCWS) at CNS does not interface with reactor condensate system.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Cooper Nuclear Station Date of Examination: 6/28/2021 Examination Level: RO SRO Operating Test Number: CN-2021-6 Administrative Topic (see Note) Type Describe activity to be performed Code*

A5, SKL034-20-114 - Determine shift staffing requirements for a mode change Conduct of Operations R, D (Procedure 2.0.3)

K/A G2.1.5 (3.9)

A6, Interpret plant conditions to diagnose jet Conduct of Operations pump failure and determine required action R, N (Procedure 2.4RXPWR, Attachment 2)

K/A G2.1.7 (4.7), 2.1.25 (4.2)

A7, Determine whether mode change is allowed based on plant conditions Equipment Control R, M (Modified version of NRC 2017-3 JPM A5, changed from RCIC inoperable initially to DG2 inoperable)

K/A 2.2.22 (4.7)

From Previous 2 exams randomly selected (2020-4 NRC JPM A8)

Radiation Control A8, Determine emergency dose limit, estimated R, D, P exposure, and whether KI authorization is required for operator to manually close RCIC-MO-15 K/A G2.3.14 (3.8)

A9, SKL034-50 Interpret plant conditions to determine Emergency Classification for Emergency Plan R, D ATWS <3% power (Procedure 5.7.1)

K/A G2.4.41 (4.6)

NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

  • Type Codes and Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs and RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1, randomly selected)

Rev 0

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Cooper Nuclear Station Date of Examination: 6/28/2021 Exam Level: RO SRO-I SRO-U Operating Test Number: CN-2021-6 Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code* Safety Function S1. SKL034-20-22, Respond to Control Rod Drift S, M, A 1 (Alt Path - During Control Rod Exercise Testing per Procedure 6.CRD.301, control rod 26-07 will drift in, requiring the examinee to enter Procedure 2.4CRD, CRD Trouble, and fully insert the control rod)

K/A 201003 A2.03 (4.7/4.2)

S2. Place RCIC in standby from isolated condition S, N, A 2 (Alt. Path - RCIC steam line break occurs during warming and auto isolation fails, requiring manual isolation of RCIC steam supply IAW procedure 2.0.3, Conduct of Operations)

K/A 217000 A4.03 (3.8)

S3. SKL034-20-107, Lowering DEH Pressure Setpoint in TARGET S, D, L 3 Mode IAW Procedure 2.2.77.1, DEH System Operations Hard Card (If ever used for ILT NRC, not used from 2012 to present)

K/A 241000 A4.06 (4.2)

S4. SKL034-20 Conduct RR Pump Quick Restart (Mode 3) IAW S, D, A, L 4 Procedure 2.4RR, Reactor Recirculation Abnormal (Alternate Path - RR Pump A vibration will rise above the danger setpoint when the pump is started and RR-MO-53A, PUMP DISCHARGE VLV is opened, requiring the operator to trip RR Pump A IAW the alarm card.)

(For ILT NRC, this is first time used)

K/A 202001 A4.01 (4.0)

S5. Place RHR Pump B in Suppression Pool Cooling supported by S, N, A, EN, L 5 RHR Service Water Pump B IAW Procedure 2.2.69.3, RHR System Operations Hard Card and Procedure 2.2.71 (Alt. Path - After RHR Pump B is in-service, RHRSWB Pump B will trip, requiring placing RHRSWB Pump D in service IAW the alarm card)

KA 219000 A4.02 (4.2) page 1 of 2 Rev 3

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 S6. SKL034-20-26, Operate Service Water Backups for Critical S, D, L 8 Loop Cooling (Align Service Water Cross-tie to REC) IAW Procedure 5.2REC, Loss of REC (For ILT NRC, last used 2018-9) 400000 A2.01 (3.9)

S7. Start SGT B for HPCI operation for level control post-scram. S, P, D, A, 9 Procedure 2.2.73, Standby Gas Treatment System, Section 8. EN, L (Alt Path - High Moisture will alarm for the preferred SGT filter 2020-4 NRC train due to heater failure, requiring shifting SGT trains per the JPM S8 alarm card)

From Previous 2 exams randomly selected KA 261000 A4.07 (3.6) RO, SRO-I, SRO-U S8. N/A In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U P1. SKL034-10-130, Locally Align RHRSW Crosstie for RPV D, L, E 4 Injection IAW Procedure 5.8.4, Alternate Injection Subsystems (Table 4)

(For ILT NRC, last used 2017-3)

K/A 510000 K1.07 (3.5)

P2. SKL034-10-69, Conduct Alternate Pressure Control (Failure- to- D, R, L, E 3 Scram) using Steam Jet Air Ejectors (local valve alignments)

IAW Procedure 5.8.12, RPV Pressure Control Systems (Failure to Scram) (Table 12)

(If ever used for ILT NRC, not used from 2012 to present)

K/A 295025 EK1.07 (4.2), EK2.12 (3.1)

P3. SKL034-40-27, Transfer 125VDC Bus A to its emergency D 6 source IAW Procedure 2.2.25.1, 125 VDC Electrical System (Div 1)

(If ever used for ILT NRC, not used from 2012 to present)

KA 263000 K4.01 (3.5)

  • All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all five SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.
  • Type Codes Criteria for R /SRO-I/SRO-U (Actual) page 2 of 2 Rev 3

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 (A)lternate path 4-6/4-6 /2-3 (-/5/-)

(C)ontrol room (D)irect from bank 9/ 8/ 4 (-/7/-)

(E)mergency or abnormal in-plant 1/ 1/ 1 (-/2/-)

(EN)gineered safety feature 1/ 1/ 1 (control room system) (-/2/-)

(L)ow-Power/Shutdown 1/ 1/ 1 (-/7/-)

(N)ew or (M)odified from bank including 1(A) 2/ 2/ 1 (-/3/-)

(P)revious 2 exams 3/ 3/ 2 (randomly selected) (-/1/-)

(R)CA 1/ 1/ 1 (-/1/-)

(S)imulator page 3 of 2 Rev 3

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