ML17158B435

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2017 Perry Nuclear Power Plant Initial Licensed Operator Examination Written Exam Outline ES-401-1 and 3 - Updated
ML17158B435
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 02/03/2017
From: David Reeser
NRC/RGN-III/DRS/OLB
To:
FirstEnergy Nuclear Operating Co
Shared Package
ML16242A222 List:
References
Download: ML17158B435 (10)
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ES-401 1 Form ES-401-1 Facility:: Perry Nuclear Power Plant Date of Exam: February 17, 2017 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 4 4
1. 1 3 3 3 3 20 4 3 7 5 3 Emergency & N/A N/A 2 1 1 1 2 1 1 7 2 1 3 Abnormal Plant Evolutions 5 5 Tier Totals 4 5 4 4 27 6 4 10 6 4 2 2 1 2 3 3 3 2 2 3 2 2 26 2 3 5 3 1 2.

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

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 Categories 3 3 2 2 10 2 2 1 2 7 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). (One Tier 3 Radiation Control K/A is allowed if the K/A 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 associated 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 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 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

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

1 2 3 1 2 Knowledge of the operational implications of the following 295001 Partial or Complete Loss of Forced 0 concepts as they apply to Partial Or Complete Loss Of 3.6 1 Core Flow Circulation / 1 & 4 3 Forced Core Flow Circulation: Thermal limits Ability to determine and/or interpret the following as they 0 apply to Partial Or Complete Loss Of A.C. Power: Reactor 295003 Partial or Complete Loss of AC / 6 4.2 2 2 power / pressure / and level 2.2.37 Ability to determine operability and/or availability of 3.6 safety related equipment. 3 0 SRO A2.02 - Ability to determine and/or interpret the 295004 Partial or Total Loss of DC Pwr / 6 R 2 following as they apply to Partial or Complete Loss of D.C. 3.9 Power: Extent of partial or complete loss of D.C. 76 power.

Knowledge of the operational implications of the following 0 concepts as they apply to Main Turbine Generator Trip:

295005 Main Turbine Generator Trip / 3 3.5 4 3 Pressure effects on reactor level 0 Knowledge of the interrelations between SCRAM and the 295006 SCRAM / 1 following: Turbine trip logic 3.6 5 4

0 Knowledge of the reasons for the following responses as they apply to Control Room Abandonment: Turbine trip 3.7 2

295016 Control Room Abandonment / 7 Knowledge of the interrelations between Control Room 6 4.0 0 Abandonment and the following: Local control stations:

2 Plant-Specific Knowledge of the interrelations between Partial Or 0 Complete Loss Of Component Cooling Water and the 295018 Partial or Total Loss of CCW / 8 3.3 7 1 following: System loads Knowledge of the reasons for the following responses as 0 they apply to Partial Or Complete Loss Of Instrument Air:

295019 Partial or Total Loss of Inst. Air / 8 3.2 8 3 Service air isolations Ability to operate and/or monitor the following as they 3.5 apply to Loss Of Shutdown Cooling: RHR/shutdown cooling 9 0

295021 Loss of Shutdown Cooling / 4 S SRO - 2.4.30 Knowledge of events related to system 2

operation/status that must be reported to internal 4.1 77 organizations or external agencies, such as the State, the NRC, or the transmission system operator.

RO.-.A2.02 Ability to determine and/or interpret the 0 following as they apply to Refueling Accidents: Fuel pool 3.4 10 2 level 295023 Refueling Acc / 8 0 SRO - A2.02 Ability to determine and/or interpret the 2 following as they apply to Refueling Accidents: Fuel pool 3.7 78 level 2.1.28 Knowledge of the purpose and function of major system components and controls. 4.1 11 0

295024 High Drywell Pressure / 5 R SRO - A2.03 Ability to determine and/or interpret the 3

following as they apply to High Drywell Pressure:

3.8 79 Suppression pool level Knowledge of the operational implications of the following 0 concepts as they apply to High Reactor Pressure: Decay 295025 High Reactor Pressure / 3 3.6 12 4 heat generation

ES-401 3 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR #

1 2 3 1 2 Knowledge of the interrelations between Suppression Pool High Water Temperature and the following: 2.5 13 295026 Suppression Pool High Water Temp. 0 SPDS/ERIS/CRIDS/GDS S

/5 4 SRO - 2.2.22 Knowledge of limiting conditions for 4.7 80 operations and safety limits.

Knowledge of the reasons for the following responses as they apply to High Containment Temperature (Mark III Containment Only): Emergency depressurization: 3.7 14 0 0 Mark-III 295027 High Containment Temperature / 5 1 1 SRO - A2.01 Ability to determine and/or interpret the 3.7 81 following as they apply to High Containment Temperature (Mark III Containment Only): Containment temperature 295028 High Drywell Temperature / 5 0 Ability to operate and/or monitor the following as they 295030 Low Suppression Pool Wtr Lvl / 5 apply to Low Suppression Pool Water Level: RCIC 3.4 15 2

0 Ability to determine and/or interpret the following as they 295031 Reactor Low Water Level / 2 apply to Reactor Low Water Level: Reactor power 4.0 16 2

2.4.34 Knowledge of RO tasks performed outside the main R control room during an emergency and the resultant 4.2 295037 SCRAM Condition Present operational effects.

and Power Above APRM Downscale 17 or Unknown / 1 2.4.4 Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for 4.5 emergency and abnormal operating procedures.

Knowledge of the operational implications of the following concepts as they apply to High Off-Site Release Rate: 4.2 18 0 Protection of the general public 295038 High Off-site Release Rate / 9 S 2

SRO - 2.4.50 Ability to verify system alarm setpoints and 4.0 82 operate controls identified in the alarm response manual.

0 Knowledge of the interrelations between Plant Fire On Site 600000 Plant Fire On Site / 8 and the following: Sensors / detectors and valves 2.6 19 1

Knowledge of the reasons for the following responses as 700000 Generator Voltage and Electric Grid 0 they apply to Generator Voltage And Electric Grid 3.6 20 Disturbances / 6 2 Disturbances: Actions contained in abnormal operating procedure for voltage and grid disturbances K/A Category Totals: 4 4 3 3 Group Point Total:

20/

3 3 / /

5 3 7 4 3

ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 K K K A A K/A Topic(s) IR #

E/APE # / Name / Safety Function G 1 2 3 1 2 0

Knowledge of the reasons for the following responses as 5 3.4 295002 Loss of Main Condenser Vac / 3 they apply to Loss Of Main Condenser Vacuum: Main 21 0 2.9 steam isolation valve Air ejector flow 6

295007 High Reactor Pressure / 3 0 SRO Ability to determine and/or interpret the following as they 295008 High Reactor Water Level / 2 3.9 83 1 apply to High Reactor Water Level: Reactor water level 295009 Low Reactor Water Level / 2 Ability to operate and/or monitor the following as they 0 apply to High Drywell Pressure: Drywell/suppression 3.1 22 295010 High Drywell Pressure / 5 5 vent and purge 295011 High Containment Temp / 5 295012 High Drywell Temperature / 5 Ability to operate and/or monitor the following as they 0 apply to High Suppression Pool Temperature: 3.9 23 295013 High Suppression Pool Temp. / 5 1 Suppression pool cooling 295014 Inadvertent Reactivity Addition / 1 0 RO - A2.02 Ability to determine and/or interpret the following 4.1 24 2 as they apply to Incomplete Scram: Control rod position 295015 Incomplete SCRAM / 1 0 SRO - A2.01 Ability to determine and/or interpret the following 1 4.3 84 as they apply to Incomplete SCRAM: Reactor power 2.2.44 Ability to interpret control room indications to verify the 295017 High Off-site Release Rate / 9 R status and operation of a system, and understand how operator 4.2 25 actions and directives affect plant and system conditions.

295020 Inadvertent Cont. Isolation / 5 & 7 295022 Loss of CRD Pumps / 1 Knowledge of the operational implications of the following 0 concepts as they apply to High Suppression Pool Water 3.4 26 295029 High Suppression Pool Wtr Lvl / 5 1 Level: Containment integrity 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 2.4.2 Knowledge of system set points, interlocks and S 4.6 295036 Secondary Containment High automatic actions associated with EOP entry conditions.

85 Sump/Area Water Level / 5 2.4.20 Knowledge of the operational implications of EOP 4.3 warnings, cautions, and notes.

Knowledge of the interrelations between High 0 Containment Hydrogen Concentrations the following: 3.3 27 500000 High CTMT Hydrogen Conc. / 5 3 Containment Atmosphere Control System 1 1 K/A Category Point Totals: 1 1 1 2 / / Group Point Total: 7/3 2 1

ES-401 5 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 E/APE # / Name / Safety Function K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4

  • 203000 RHR/LPCI: Injection 2.4.8 Knowledge of how abnormal operating R 3.8 28 Mode procedures are used in conjunction with EOPs.

Knowledge of the physical connections and/or 0 cause-effect relationships between Shutdown 205000 Shutdown Cooling 3.2 29 6 Cooling System (RHR Shutdown Cooling Mode) and the following: A.C. electrical power 206000 HPCI Not Applicable to Perry 207000 Isolation (Emergency) Not Applicable to Perry Condenser 0 Knowledge of electrical power supplies to the 209001 LPCS 2.9 30 3 following: Initiation logic 0 Knowledge of the effect that a loss or malfunction 1 of the High Pressure Core Spray System (HPCS) 3.9 209002 HPCS 31 0 will have on following: Reactor Water Level 3.3 2 Standby Liquid Control System Knowledge of Standby Liquid Control System design feature(s) and/or interlocks which provide for the following: Over pressure protection 0 SRO - A2.0504 Ability to (a) predict the impacts 2.8 32 1 5 of the following on the Standby Liquid Control 211000 SLC 0 0 System ; and (b) based on those predictions, use 4 procedures to correct, control, or mitigate the 3.4 86 consequences of those abnormal conditions or operations: Loss of SBLC tank heaters Inadequate system flow Knowledge of the operational implications of the 0 following concepts as they apply to Reactor 212000 RPS 3.3 33 2 Protection System: Specific logic arrangements Knowledge of the effect that a loss or malfunction 215003 IRM 0 of the following will have on the Intermediate 3.0 34 4 Range Monitor (IRM) System: Detectors K1.01 Knowledge of the physical connections and/or cause-effect relationships between 3.6 35 Source Range Monitor (SRM) System and the 0 following: Reactor protection system 215004 Source Range Monitor 0 6 A1.06 Ability to predict and/or monitor changes in 1

parameters associated with operating the Source 36 3.1 Range Monitor (SRM) System controls including:

Lights and alarms K3.04 Knowledge of the effect that a loss or 3.4 malfunction of the Average Power Range 3.5 37 Monitor/Local Power Range Monitor System will have on following: Rod control and information system Reactor Recirculation System; BWR 5,6 0

0 A2.03 Ability to (a) predict the impacts of the 215005 APRM / LPRM / OPRM 4 3 following on the Average Power Range 0

Monitor/Local Power Range Monitor System; and 3.6 38 2

(b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Inoperative trip (all causes)

ES-401 6 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 E/APE # / Name / Safety Function 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

1 Ability to manually operate and/or monitor in the 218000 ADS 4.2 41 2 control room: Reactor vessel water level 2.2.40 Ability to apply Technical Specifications 3.4 42 R for a system.

223002 PCIS/Nuclear Steam Supply Shutoff SRO - 2.4.46 Ability to verify that the alarms are S consistent with the plant conditions. 4.2 88 Knowledge of electrical power supplies to the following: SRV solenoids 2.8 43 SRO - A2.05 Ability to (a) predict the impacts of 0 0 the following on the RELIEF/SAFETY VALVES ;

239002 SRVs 1 5 and (b) based on those predictions, use procedures to correct, control, or mitigate the 3.4 89 consequences of those abnormal conditions or operations: Low reactor pressure Knowledge of the effect that a loss or malfunction 259002 Reactor Water Level 0 of the Reactor Water Level Control System will 2.8 44 Control 6 have on following: Main turbine Knowledge of Standby Gas Treatment System 0 design feature(s) and/or interlocks which provide 261000 SGTS (AEGTS) 2.7 45 4 for the following: Radioactive particulate filtration K5.02Knowledge of the operational implications of the following concepts as they apply to A.C.

Electrical Distribution: Breaker control 2.6 46 0 0 262001 AC Electrical Distribution A1.02 Ability to predict and/or monitor changes in 2 2 parameters associated with operating the A.C. 3.1 47 Electrical Distribution controls including: Effects of loads when energizing a bus Knowledge of the effect that a loss or malfunction 0 of the following will have on the Uninterruptable 262002 UPS (AC/DC) 2.7 48 1 Power Supply (A.C./D.C.) : A.C. electrical power Ability to predict and/or monitor changes in 0 parameters associated with operating the D.C.

263000 DC Electrical Distribution 2.5 49 1 Electrical Distribution controls including: Battery charging/discharging rate Ability to (a) predict the impacts of the following on the Emergency Generators (Diesel/Jet) ; and 0 (b) based on those predictions, use procedures 264000 EDGs 3.5 50 1 to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Parallel operation of emergency generator

ES-401 7 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 E/APE # / Name / Safety Function 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

  • K2.01 Knowledge of electrical power supplies to the following: Instrument air compressor 2.8 51 0 0 A3.02 Ability to monitor automatic operations of 1 2 the Instrument Air System including: Air 2.9 temperature 300000 Instrument Air A2.01 Ability to (a) predict the impacts of the following on the INSTRUMENT AIR SYSTEM 0 and (b) based on those predictions, use 2.8 52 1 procedures to correct, control, or mitigate the consequences of those abnormal operation: Air dryer and filter malfunctions Ability to manually operate and / or monitor in the 3.1 53 0 control room: CCW indications and control 400000 Component Cooling Water S 1 SRO - 2.2.38 Knowledge of conditions and limitations in the facility license. 4.5 90 2

2 3 2 26/

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

/ 1 5 3

2

ES-401 8 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 E/APE # / Name / Safety Function 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

  • SRO - A2.04 Ability to (a) predict the impacts of the following on the Control Rod Drive Hydraulic 0 System; and (b) based on those predictions, use 201001 CRD Hydraulic 3.9 91 4 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Scram conditions 201002 RMCS Not Applicable to Perry 201003 Control Rod and Drive 2.1.25 Ability to interpret reference materials, R 3.9 54 Mechanism such as graphs, curves, tables, etc.

201004 RSCS Not Applicable to Perry Knowledge of the physical connections and/or 0 cause-effect relationships between Rod Control 201005 RCIS 3.5 55 5 And Information System (RCIS) and the following: Rod action control system: BWR-6 201006 RWM Not Applicable to Perry 0 Knowledge of electrical power supplies to the 202001 Recirculation 3.2 56 2 following: MG sets 202002 Recirculation Flow Control Knowledge of the effect that a loss or 0 malfunction of the Reactor Water Cleanup 204000 RWCU 3.2 57 1 System will have on following: Reactor water quality 214000 RPIS Not Applicable to Perry 215001 Traversing In-core Probe 215002 RBM Not Applicable to Perry 216000 Nuclear Boiler Inst.

219000 RHR/LPCI: Torus/Pool Cooling Mode SRO - 2.2.25 Knowledge of the bases in 223001 Primary CTMT and Aux. S Technical Specifications for limiting conditions 4.2 92 for operations and safety limits.

Knowledge of RHR/LPCI: Containment Spray 226001 RHR/LPCI: CTMT Spray 0 System Mode design feature(s) and/or 2.8 58 Mode 2 interlocks which provide for the following:

Redundancy 230000 RHR/LPCI: Torus/Pool Spray Mode Not Applicable to Perry 233000 Fuel Pool Cooling/Cleanup Knowledge of the operational implications of the 0 following concepts as they apply to Fuel 234000 Fuel Handling Equipment 2.9 59 3 Handling Equipment: Water as a shield against radiation Knowledge of the effect that a loss or 0 malfunction of the following will have on the 239001 Main and Reheat Steam 3.3 60 8 Main And Reheat Steam System: Main condenser vacuum 239003 MSIV Leakage Control Not Applicable to Perry

ES-401 9 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 E/APE # / Name / Safety Function K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4

  • Ability to predict and/or monitor changes in 241000 Reactor/Turbine Pressure 0 parameters associated with operating the 4.1 61 Regulator 2 Reactor/Turbine Pressure Regulating System controls including: Reactor power 245000 Main Turbine Gen. / Aux.

256000 Reactor Condensate Ability to (a) predict the impacts of the following on the Reactor Feedwater System ; and (b) based on those predictions, use procedures to 0

59001 Reactor Feedwater correct, control, or mitigate the consequences 3.7 62 7

of those abnormal conditions or operations:

Reactor water level control system malfunctions 268000 Radwaste 271000 Offgas Ability to (a) predict the impacts of the following on the Radiation Monitoring System ; and (b) 0 based on those predictions, use procedures to 272000 Radiation Monitoring 3.7 63 1 correct, control, or mitigate the consequences of those abnormal conditions or operations:

Fuel element failure 286000 Fire Protection Ability to monitor automatic operations of the Plant Ventilation Systems including: 3.8 64 0 Isolation/initiation signals 288000 Plant Ventilation S 1 SRO - 2.2.42 Ability to recognize system parameters that are entry-level conditions for 4.6 93 Technical Specifications.

Ability to manually operate and/or monitor in the 0

290001 Secondary CTMT control room: Reactor building area 3.3 65 2

temperatures 290003 Control Room HVAC 290002 Reactor Vessel Internals 2 1 12/

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

3 2 1

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Perry Nuclear Power Plant Date of Exam: February 17, 2017 RO SRO-Only Category K/A # Topic IR # IR #

2.1.8 Ability to coordinate personnel activities outside the control room. 3.4 66 2.1.41 Knowledge of the refueling process 2.8 Knowledge of individual licensed operator responsibilities related to shift 2.1.4 staffing, such as medical requirements, no-solo operation, maintenance 3.3 67 of active license status, 10CFR55, etc.

1. Conduct of 2.1.17 Ability to make accurate, clear, and concise verbal reports. 3.9 68 Operations 2.1.6 Ability to manage the control room crew during plant transients. 4.8 94 Knowledge of procedures, guidelines, or limitations associated with 2.1.37 4.6 95 reactivity management.

Subtotal 3 2 2.2.21 Knowledge of pre- and post-maintenance operability requirements. 2.9 69 2.2.13 Knowledge of tagging and clearance procedures. 4.1 70 2.2.43 Knowledge of the process used to track inoperable alarms. 3.0 71

2. Equipment Control 2.2.22 Knowledge of limiting conditions for operations and safety limits. 4.7 96 Knowledge of the process for making design or operating changes to the 2.2.5 3.2 97 facility.

Subtotal 3 2 Knowledge of radiation or contamination hazards that may arise during 2.3.14 3.4 72 normal, abnormal, or emergency conditions or activities.

2.3.11 Ability to control radiation releases. 3.8 73

3. Radiation Control Knowledge of radiation exposure limits under normal or emergency 2.3.4 3.7 98 conditions.

Subtotal 2 1 2.4.17 Knowledge of EOP terms and definitions. 3.9 74 Ability to diagnose and recognize trends in an accurate and timely 2.4.47 4.2 75 manner utilizing the appropriate control room reference material.

4. Emergency Procedures /

Plan 2.4.41 Knowledge of the emergency action level thresholds and classifications. 4.6 99 Knowledge of facility protection requirements, including fire brigade and 2.4.26 3.6 100 portable fire fighting equipment usage.

Subtotal 2 2 Tier 3 Point Total 10 7

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