ML17158B465

2017 Perry Nuclear Power Plant Initial Licensed Operator Examination Written Exam Outline ES-401-1 and 3

ML17158B465
Person / Time
Site:	Perry
Issue date:	02/03/2017
From:	Reeser D W NRC/RGN-III/DRS/OLB
To:	FirstEnergy Nuclear Operating Co
Shared Package
ML16242A222	List: ML17158B339 ML17158B385 ML17158B414 ML17158B435 ML17158B442 ML17158B455 ML17158B465 ML17170A198 ML17170A209
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Download: ML17158B465 (10)

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E S-401 1 Form ES-401-1 Facility:: Perry Nuclear Power Plant Date of Exam: February 17, 2017 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 Emergency & Abnormal Plant Evolutions 1 3 4 4 N/A 3 3 N/A 3 20 4 3 7 2 1 1 1 2 1 1 7 2 1 3 Tier Totals 4 5 5 5 4 4 27 6 4 10 2. Plant Systems 1 2 3 3 3 2 2 3 2 2 2 2 26 2 3 5 2 1 1 1 1 1 1 1 2 1 1 1 12 1 2 3 Tier Totals 3 4 4 4 3 3 4 4 3 3 3 38 3 5 8 3. Generic Knowledge and Abilities Categories 1 2 3 4 10 1 2 3 4 7 3 3 2 2 2 2 1 2 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO

-only outline, the "Tier Totals" in each K/A category shall not be less than two). (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

E S-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 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 0 3 Knowledge of the operational implications of the following concepts as they apply to Partial Or Complete Loss Of Forced Core Flow Circulation

Thermal limits 3.6 1 295003 Partial or Complete Loss of AC / 6 0 2 Ability to determine and/or interpret the following as they apply to Partial Or Complete Loss Of A.C. Power:

Reactor power / pressure / and level 4.2 2 295004 Partial or Total Loss of DC Pwr / 6 0 2 R 2.2.37 Ability to determine operability and/or availability of safety related equipment.

SRO A2.02

- Ability to determine and/or interpret the following as they apply to Partial or Complete Loss of D.C.

Power: Extent of partial or complete loss of D.C. power. 3.6 3.9 3 76 295005 Main Turbine Generator Trip / 3 0

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

Pressure effects on reactor level 3.5 4 295006 SCRAM / 1 0

4 Knowledge of the interrelations between SCRAM and the following:

Turbine trip logic 3.6 5 295016 Control Room Abandonment / 7 0 2 Knowledge of the reasons for the following responses as they apply to Control Room Abandonment:

Turbine trip 3.7 6 295018 Partial or Total Loss of CCW / 8 0 1 Knowledge of the interrelations between Partial Or Complete Loss Of Component Cooling Water and the following:

System loads 3.3 7 295019 Partial or Total Loss of Inst. Air / 8 0 3 Knowledge of the reasons for the following responses as they apply to Partial Or Complete Loss Of Instrument Air:

Service air isolations 3.2 8 295021 Loss of Shutdown Cooling / 4 0 2 S Ability to operate and/or monitor the following as they apply to Loss Of Shutdown Cooling

RHR/shutdown cooling SRO - 2.4.30 Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.

3.5 4.1 9 77 295023 Refueling Acc / 8 0 2 0 2 RO.-.A2.02 Ability to determine and/or interpret the following as they apply to Refueling Accidents: Fuel pool level SRO - A2.02 Ability to determine and/or interpret the following as they apply to Refueling Accidents: Fuel pool level 3.4 3.7 10 78 295024 High Drywell Pressure / 5 0 3 R 2.1.28 Knowledge of the purpose and function of major system components and controls. SRO - A2.03 Ability to determine and/or interpret the following as they apply to High Drywell Pressure: Suppression pool level 4.1 3.8 1 1 79 295025 High Reactor Pressure / 3 0 4 Knowledge of the operational implications of the following concepts as they apply to High Reactor Pressure: Decay heat generation 3.6 1 2 295026 Suppression Pool High Water Temp.

/ 5 0 4 S Knowledge of the interrelations between Suppression Pool High Water Temperature and the following:

SPDS/ERIS/CRIDS/GDS SRO - 2.2.22 Knowledge of limiting conditions for operations and safety limits.

2.5 4.7 1 3 80 E S-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 1 K 2 K 3 A 1 A 2 G K/A Topic(s)

IR # 295027 High Containment Temperature / 5 0 1 0 1 Knowledge of the reasons for the following responses as they apply to High Containment Temperature (Mark III Containment Only): Emergency depressurization: Mark-III SRO - A2.01 Ability to determine and/or interpret the following as they apply to High Containment Temperature (Mark III Containment Only): Containment temperature 3.7 3.7 1 4 81 295028 High Drywell Temperature

/ 5 295030 Low Suppression Pool Wtr Lvl / 5 0 2 Ability to operate and/or monitor the following as they apply to Low Suppression Pool Water Level:

RCIC 3.4 1 5 295031 Reactor Low Water Level / 2 0 2 Ability to determine and/or interpret the following as they apply to Reactor Low Water Level

Reactor power 4.0 1 6 295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown / 1 R 2.4.4 Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

4.5 1 7 295038 High Off

-site Release Rate / 9 0 2 S Knowledge of the operational implications of the following concepts as they apply to High Off

-Site Release Rate

Protection of the general public SRO - 2.4.50 Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

4.2 4.0 1 8 82 600000 Plant Fire On Site / 8 0

1 Knowledge of the interrelations between Plant Fire On Site and the following:

Sensors / detectors and valves 2.6 1 9 700000 Generator Voltage and Electric Grid Disturbances / 6 0

2 Knowledge of the reasons for the following responses as they apply to Generator Voltage And Electric Grid Disturbances:

Actions contained in abnormal operating procedure for voltage and grid disturbances 3.6 20 K/A Category Totals:

3 4 4 3 3/4 3/3 Group Point Total:

20/7 E S-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions

- Tier 1/Group 2 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 0 5 Knowledge of the reasons for the following responses as they apply to Loss Of Main Condenser Vacuum

Main steam isolation valve 3.4 2 1 295007 High Reactor Pressure / 3 295008 High Reactor Water Level / 2 0 1 SRO Ability to determine and/or interpret the following as they apply to High Reactor Water Level: Reactor water level 3.9 83 295009 Low Reactor Water Level / 2 295010 High Drywell Pressure / 5 0 5 Ability to operate and/or monitor the following as they apply to High Drywell Pressure

Drywell/suppression vent and purge 3.1 22 295011 High Containment Temp / 5 295012 High Drywell Temperature / 5 295013 High Suppression Pool Temp. / 5 0

1 Ability to operate and/or monitor the following as they apply to High Suppression Pool Temperature

Suppression pool cooling 3.9 23 295014 Inadvertent Reactivity Addition / 1 295015 Incomplete SCRAM

/ 1 0 2 0 1 RO - A2.02 Ability to determine and/or interpret the following as they apply to Incomplete Scram: Control rod position SRO - A2.01 Ability to determine and/or interpret the following as they apply to Incomplete SCRAM: Reactor power 4.1 4.3 24 84 295017 High Off

-site Release Rate / 9 R 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 25 295020 Inadvertent Cont. Isolation / 5 & 7 295022 Loss of CRD Pumps / 1 295029 High Suppression Pool Wtr Lvl / 5 0

1 Knowledge of the operational implications of the following concepts as they apply to High Suppression Pool Water Level: Containment integrity 3.4 26 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 S 2.4.2 Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

4.6 85 500000 High CTMT Hydrogen Conc. / 5 0

3 Knowledge of the interrelations between High

Containment Hydrogen Concentrations the following:

Containment Atmosphere Control System 3.3 27 K/A Category Point Totals:

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

7/3 E S-401 5 Form ES-401-1 E S-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions

- Tier 2/Group 1 E/APE # / Name / Safety Function 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 R 2.4.8 Knowledge of how abnormal operating procedures are used in conjunction with EOPs.

3.8 28 205000 Shutdown Cooling 0 6 Knowledge of the physical connections and/or cause-effect relationships between Shutdown Cooling System (RHR Shutdown Cooling Mode) and the following:

A.C. electrical power 3.2 29 206000 HPCI Not Applicable to Perry 207000 Isolation (Emergency)

Condenser Not Applicable to Perry 209001 LPCS 0 3 Knowledge of electrical power supplies to the

following:

Initiation logic 2.9 30 209002 HPCS 0 1 Knowledge of the effect that a loss or malfunction of the High Pressure Core Spray System (HPCS) will have on following: Reactor Water Level 3.9 3 1 211000 SLC 1 0 0 5 Knowledge of Standby Liquid Control System design feature(s) and/or interlocks which provide for the following:

Over pressure protection SRO - A2.05 Ability to (a) predict the impacts of the following on the Standby Liquid Control System ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of SBLC tank heaters 2.8 3.4 32 86 212000 RPS 0

2 Knowledge of the operational implications of the following concepts as they apply to Reactor Protection System: Specific logic arrangements 3.3 33 215003 IRM 0 4 Knowledge of the effect that a loss or malfunction of the following will have on the Intermediate Range Monitor (IRM) System

Detectors 3.0 34 215004 Source Range Monitor 0

1 0 6 K1.01 Knowledge of the physical connections and/or cause

-effect relationships between Source Range Monitor (SRM) System and the following:

Reactor protection system A1.06 Ability to predict and/or monitor changes in parameters associated with operating the Source Range Monitor (SRM) System controls including:

Lights and alarms 3.6 3.1 35 36 215005 APRM / LPRM / OPRM 0 4 0 3 K3.04 Knowledge of the effect that a loss or malfunction of the Average Power Range Monitor/Local Power Range Monitor System will have on following: Rod control and information system: A2.03 Ability to (a) predict the impacts of the following on the Average Power Range Monitor/Local Power Range Monitor System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Inoperative trip (all causes) 3.4 3.6 37 38 E S-401 6 Form ES-401-1 E S-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions

- Tier 2/Group 1 E/APE # / Name / Safety Function 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 # 217000 RCIC 0 6 0 1 S K4.06 Knowledge of reactor core isolation cooling system (RCIC) design feature(s) and/or interlocks which provide for the following:

Manual initiation A3.01 Ability to monitor automatic operations of the Reactor Core Isolation Cooling System (RCIC) including:

Valve operation SRO - 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.

3.5 3.5 4.2 39 40 87 218000 ADS 1 2 Ability to manually operate and/or monitor in the control room:

Reactor vessel water level 4.2 4 1 223002 PCIS/Nuclear Steam Supply Shutoff R S 2.2.40 Ability to apply Technical Specifications for a system.

SRO - 2.4.46 Ability to verify that the alarms are consistent with the plant conditions.

3.4 4.2 42 88 239002 SRVs 0 1 0 5 Knowledge of electrical power supplies to the following:

SRV solenoids SRO - A2.05 Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low reactor pressure 2.8 3.4 43 89 259002 Reactor Water Level Control 0 6 Knowledge of the effect that a loss or malfunction of the Reactor Water Level Control System will have on following:

Main turbine 2.8 44 261000 SGTS (AEGTS) 0 4 Knowledge of Standby Gas Treatment System design feature(s) and/or interlocks which provide for the following:

Radioactive particulate filtration 2.7 45 262001 AC Electrical Distribution 0

2 0 2 K5.02Knowledge of the operational implications of the following concepts as they apply to A.C. Electrical Distribution:

Breaker control A1.02 Ability to predict and/or monitor changes in parameters associated with operating the A.C.

Electrical Distribution controls including

Effects of loads when energizing a bus 2.6 3.1 46 47 262002 UPS (AC/DC) 0 1 Knowledge of the effect that a loss or malfunction of the following will have on the Uninterruptable Power Supply (A.C./D.C.) :

A.C. electrical power 2.7 48 263000 DC Electrical Distribution 0 1 Ability to predict and/or monitor changes in parameters associated with operating the D.C.

Electrical Distribution controls including:

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

Parallel operation of emergency generator 3.5 50 E S-401 7 Form ES-401-1 E S-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions

- Tier 2/Group 1 E/APE # / Name / Safety Function 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 # 300000 Instrument Air 0 1 0 2 K2.01 Knowledge of electrical power supplies to the following: Instrument air compressor A3.02 Ability to monitor automatic operations of the Instrument Air System including: Air temperature 2.8 2.9 51 52 400000 Component Cooling Water 0 1 S Ability to manually operate and / or monitor in the control room:

CCW indications and control SRO - 2.2.38 Knowledge of conditions and limitations in the facility license.

3.1 4.5 53 90 K/A Category Point Totals:

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

26/5 E S-401 8 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions

- Tier 2/Group 2 E/APE # / Name / Safety Function 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 0 4 SRO - A2.04 Ability to (a) predict the impacts of the following on the Control Rod Drive Hydraulic System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Scram conditions 3.9 91 201002 RMCS Not Applicable to Perry 201003 Control Rod and Drive Mechanism R 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. 3.9 54 201004 RSCS Not Applicable to Perry 201005 RCIS 0 5 Knowledge of the physical connections and/or cause-effect relationships between Rod Control And Information System (RCIS) and the following:

Rod action control system: BWR

-6 3.5 55 201006 RWM Not Applicable to Perry 202001 Recirculation 0

2 Knowledge of electrical power supplies to the following:

MG sets 3.2 56 202002 Recirculation Flow Control 204000 RWCU 0 1 Knowledge of the effect that a loss or malfunction of the Reactor Water Cleanup System will have on following:

Reactor water quality 3.2 57 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 223001 Primary CTMT and Aux. S SRO - 2.2.25 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

4.2 92 226001 RHR/LPCI: CTMT Spray Mode 0 2 Knowledge of RHR/LPCI:

Containment Spray System Mode design feature(s) and/or interlocks which provide for the following:

Redundancy 2.8 58 230000 RHR/LPCI: Torus/Pool Spray Mode Not Applicable to Perry 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment 0 3 Knowledge of the operational implications of the following concepts as they apply to Fuel Handling Equipment: Water as a shield against radiation 2.9 59 239001 Main and Reheat Steam 0 8 Knowledge of the effect that a loss or malfunction of the following will have on the Main And Reheat Steam System:

Main condenser vacuum 3.3 60 239003 MSIV Leakage Control Not Applicable to Perry

E S-401 9 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions

- Tier 2/Group 2 E/APE # / Name / Safety Function 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 # 241000 Reactor/Turbine Pressure Regulator 0 2 Ability to predict and/or monitor changes in

parameters associated with operating the Reactor/Turbine Pressure Regulating System controls including:

Reactor power 4.1 6 1 245000 Main Turbine Gen. / Aux.

256000 Reactor Condensate 59001 Reactor Feedwater 0 7 Ability to (a) predict the impacts of the following on the Reactor Feedwater System ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Reactor water level control system malfunctions 3.7 62 268000 Radwaste 271000 Offgas 272000 Radiation Monitoring 0 1 Ability to (d) predict the impacts of the following on the Radiation Monitoring System ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Fuel element failure 3.7 63 286000 Fire Protection 288000 Plant Ventilation 0 1 S Ability to monitor automatic operations of the Plant Ventilation Systems including:

Isolation/initiation signals SRO - 2.2.42 Ability to recognize system parameters that are entry

-level conditions for Technical Specifications.

3.8 4.6 64 93 290001 Secondary CTMT 0 2 Ability to manually operate and/or monitor in the control room:

Reactor building area temperatures 3.3 65 290003 Control Room HVAC 290002 Reactor Vessel Internals K/A Category Point Totals:

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

12/3 E S-401 Generic Knowledge and Abilities Outline (Tier

3) Form ES-401-3 Facility: Perry Nuclear Power Plant Date of Exam: February 17, 20 17 Category K/A # Topic RO SRO-Only IR # IR # 1. Conduct of Operations 2.1.8 Ability to coordinate personnel activities outside the control room.

3.4 66 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 67 2.1.17 Ability to make accurate, clear, and concise verbal reports.

3.9 68 2.1.6 Ability to manage the control room crew during plant transients.

4.8 94 2.1.37 Knowledge of procedures, guidelines, or limitations associated with reactivity management.

4.6 95 Subtotal 3 2 2. Equipment Control 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 7 1 2.2.22 Knowledge of limiting conditions for operations and safety limits.

4.7 96 2.2.5 Knowledge of the process for making design or operating changes to the facility. 3.2 97 Subtotal 3 2 3. Radiation Control 2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

3.4 72 2.3.11 Ability to control radiation releases.

3.8 73 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.

3.7 98 Subtotal 2 1 4. Emergency Procedures /

Plan 2.4.17 Knowledge of EOP terms and definitions.

3.9 74 2.4.47 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

4.2 75 2.4.41 Knowledge of the emergency action level thresholds and classifications.

4.6 99 2.4.26 Knowledge of facility protection requirements, including fire brigade and portable fire fighting equipment usage.

3.6 100 Subtotal 2 2 Tier 3 Point Total 10 7