Text

Draft - Outlines (Folder 2)
	ML16081A169
Person / Time
Site:	FitzPatrick
Issue date:	12/08/2015
From:	David Silk; Operations Branch I
To:	Kelley D; Entergy Nuclear Operations
Shared Package
ML15195A060	List: ML15201A472; ML16055A001; ML16063A251; ML16081A077; ML16081A159; ML16081A169; ML16081A192; ML16081A201; ML16085A246; ML16085A247; ML16085A248; ML16085A249; ML16145A369; ML16145A383;
References
	TAC U01932
	Download: ML16081A169 (32)
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ES-401 Written Examination Outline Form ES-401-1 Facility: James A. Fitzpatrick Date of Exam: March 2016 RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G* Total 1 2 3 4 5 6 1 2 3 4

1 3 3 3 3 4 4 20 3 4 7

1. Emergency

& 2 1 1 1 2 1 1 7 2 1 3 Abnormal Plant Evolutions Tier Totals 4 4 4 5 5 5 27 5 5 10 1 2 2 2 2 3 3 2 3 2 3 2 26 2 3 5 2.

Plant 2 2 0 1 1 1 1 2 1 1 1 1 12 0 2 1 3 Systems Tier Totals 4 2 3 3 4 4 4 4 3 4 3 38 4 4 8 1 2 3 4 1 2 3 4

3. Generic Knowledge & Abilities 10 7 Categories 2 3 2 3 1 2 2 2 Note: 1. Ensure that at least two topics from every applicable KIA 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 KIA category shall not be less than two). (One Tier 3 Radiation Control KIA is allowed ifthe KIA is replaced by a KIA 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 NRG 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 KIA 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 KIAs 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 KIA categories.

7. The generic (G) KlAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA 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 KIAs.

8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (I Rs) 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 KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals(#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43.

G* Generic K\As

ES-401 Form ES-401-1 JAF 16-1 NRC Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Imp. Q#

AA2.09 - Ability to determine and/or interpret the following as they apply to 700000 Generator Voltage and GENERATOR VOLTAGE AND Electric Grid Disturbances / 6 x ELECTRIC GRID DISTURBANCES:

4.3 76 Operational status of emergency diesel generators AA2.02 - Ability to determine and/or interpret the following as they apply to 295004 Partial or Complete Loss of DC Power I 6 x PARTIAL OR COMPLETE LOSS OF 3.9 77 D.C. POWER: Extent of partial or comolete loss of D.C. oower AA2.02 - Ability to determine and/or interpret the following as they apply to 295019 Partial or Complete PARTIAL OR COMPLETE LOSS OF Loss of Instrument Air I 8 x INSTRUMENT AIR: Status of safety-3.7 78 related instrument air system loads (see AK2.1 - AK2.19) 2.1.23 - Conduct of Operations: Ability 295001 Partial or Complete to perform specific system and Loss of Forced Core Flow x integrated plant procedures during all 4.4 79 Circulation / 1 & 4 modes of plant operation.

2.1.20 - Conduct of Operations: Ability 295003 Partial or Complete Loss of AC Power I 6 x to interpret and execute procedure 4.6 80 steos.

2.1. 7 - Conduct of Operations: Ability to evaluate plant performance and make 295028 High Drywall Temperature I 5 x operational judgments based on 4.7 81 operating characteristics, reactor behavior, and instrument internretation.

295037 SCRAM Condition 2.4.18 - Emergency Procedures I Plan:

Present and Reactor Power Knowledge of the specific bases for Above APRM Downscale or x EOPs.

4.0 82 Unknown/ 1 EK1 .03 - Knowledge of the operational implications of the following concepts as 295037 SCRAM Condition they apply to SCRAM CONDITION Present and Reactor Power Above APRM Downscale or x PRESENT AND REACTOR POWER 4.2 39 ABOVE APRM DOWNSCALE OR Unknown/ 1 UNKNOWN: Boron effects on reactor power (SBLC)

AK1 .02 - Knowledge of the operational 295021 Loss of Shutdown implications of the following concepts as Cooling/ 4 x they apply to LOSS OF SHUTDOWN 3.3 40 COOLING: Thermal stratification EK1 .02 - Knowledge of the operational implications of the following concepts as 295028 High Drywall Temperature I 5 x they apply to HIGH DRYWELL 2.9 41 TEMPERATURE: Equipment environmental aualification EK2.01 - Knowledge of the interrelations 295025 High Reactor Pressure I 3

x between HIGH REACTOR PRESSURE 4.1 42 and the following: RPS AK2.02 - Knowledge of the interrelations 295016 Control Room between CONTROL ROOM Abandonment I 7 x ABANDONMENT and the following:

4.0 43 Local control stations: Plant-Specific AK2.04 - Knowledge of the interrelations 295003 Partial or Complete between PARTIAL OR COMPLETE Loss of AC Power I 6 x LOSS OF A.C. POWER and the 3.4 44 followina: A.C. electrical loads

ES-401 Form ES-401-1 JAF 16-1 NRC Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Imp. Q#

AK3.02 - Knowledge of the reasons for the following responses as they apply to 295019 Partial or Complete Loss of Instrument Air I 8 x PARTIAL OR COMPLETE LOSS OF 3.5 45 INSTRUMENT AIR: Standby air compressor operation EK3.06 - Knowledge of the reasons for 295024 High Drywell Pressure I the following responses as they apply to 5

x HIGH DRYWELL PRESSURE: Reactor 4.0 46 SCRAM EK3.07 - Knowledge of the reasons for the following responses as they apply to 295030 Low Suppression Pool Water Level I 5 x LOW SUPPRESSION POOL WATER 3.5 47 LEVEL: NPSH considerations for ECCS pumps EA 1.12 - Ability to operate and/or 295031 Reactor Low Water monitor the following as they apply to Level I 2 x REACTOR LOW WATER LEVEL:

3.9 48 Feedwater AA 1.06 - Ability to operate and I or 600000 Plant Fire On-site I 8 x monitor the following as they apply to 3.0 49 PLANT FIRE ON SITE: Fire alarm AA 1.05 - Ability to operate and/or 295001 Partial or Complete monitor the following as they apply to Loss of Forced Core Flow x PARTIAL OR COMPLETE LOSS OF 3.3 50 Circulation I 1 & 4 FORCED CORE FLOW CIRCULATION:

Recirculation flow control system AA2.01 - Ability to determine and/or interpret the following as they apply to 295018 Partial or Complete Loss of CCW I 8 x PARTIAL OR COMPLETE LOSS OF 3.3 51 COMPONENT COOLING WATER:

Component temperatures AA2.05 - Ability to determine and/or 295005 Main Turbine Generator interpret the following as they apply to Trip I 3 x MAIN TURBINE GENERATOR TRIP:

3.8 52 Reactor power EA2.03 - Ability to determine and/or 295038 High Off-site Release interpret the following as they apply to Rate I 9 x HIGH OFF-SITE RELEASE RATE:

3.5 53 Radiation levels 2.2.37 - Equipment Control: Ability to 295004 Partial or Complete Loss of DC Power I 6 x determine operability and/or availability 3.6 54 of safety related equipment.

2.4.35 - Emergency Procedures I Plan:

Knowledge of local auxiliary operator 295006 SCRAM I 1 x tasks during emergency and the 3.8 55 resultant operational effects.

2.4.45 - Emergency Procedures I Plan:

Ability to prioritize and interpret the 295023 Refueling Accidents I 8 x significance of each annunciator or 4.1 56 alarm.

EA2.03 - Ability to determine and/or 295026 Suppression Pool High interpret the following as they apply to Water Temperature I 5 x SUPPRESSION POOL HIGH WATER 3.9 57 TEMPERATURE: Reactor pressure 2.4.9 - Emergency Procedures I Plan:

Knowledge of low power I shutdown 700000 Generator Voltage and Electric Grid Disturbances I 6 x implications in accident (e.g., loss of 3.8 58 coolant accident or loss of residual heat removal) mitigation strategies.

KIA Category Totals: 3 3 3 3 4/3 4/4 Group Point Total:

I 2017

ES-401 Form ES-401-1 JAF 16-1 NRC Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Imp. Q#

AA2.02 - Ability to determine and/or interpret the following as they apply to 295015 Incomplete SCRAM / 1 x INCOMPLETE SCRAM: Control rod 4.2 83 position 295034 Secondary 2.4.41 - Emergency Procedures I Plan:

Containment Ventilation High x Knowledge of the emergency action 4.6 84 Radiation/ 9 level thresholds and classifications.

EA2.03 - Ability to determine and/or 295036 Secondary interpret the following as they apply to Containment High Sump/Area x SECONDARY CONTAINMENT HIGH 3.8 85 Water Level I 5 SUMP/AREA WATER LEVEL: Cause of the high water level EK1 .01 - Knowledge of the operational 295034 Secondary implications of the following concepts as Containment Ventilation High x they apply to SECONDARY 3.8 59 Radiation I 9 CONTAINMENT VENTILATION HIGH RADIATION: Personnel protection EK2.01 - Knowledge of the interrelations 295033 High Secondary between HIGH SECONDARY Containment Area Radiation x CONTAINMENT AREA RADIATION 3.8 60 Levels/ 9 LEVELS and the following: Area radiation monitoring system AK3.06 - Knowledge of the reasons for 295002 Loss of Main the following responses as they apply to Condenser Vacuum I 3 x LOSS OF MAIN CONDENSER 2.9 61 VACUUM: Air ejector flow EA 1.01 - Ability to operate and/or monitor the following as they apply to 295036 Secondary SECONDARY CONTAINMENT HIGH Containment High Sump/Area x SUMP/AREA WATER LEVEL:

3.2 62 Water Level I 5 Secondary containment equipment and floor drain systems AA2.01 - Ability to determine and/or 295015 Incomplete SCRAM/ 1 x interpret the following as they apply to 4.1 63 INCOMPLETE SCRAM: Reactor power 295017 High Off-site Release 2.4.6 - Emergency Procedures I Plan:

Rate/ 9 x Knowledge of EOP mitigation strategies.

3.7 64 AA 1.04 - Ability to operate and/or monitor the following as they apply to 295022 Loss of CRD Pumps I 1 x LOSS OF CRD PUMPS: Reactor water 2.5 65 cleanup system: Plant-Specific KIA Category Totals: 1 1 1 2 1/2 1/1 Group Point Total:

I 7/3

ES-401 Form ES-401-1 JAF 16-1 NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A A System # I Name G Imp. Q#

1 2 3 4 5 6 1 2 3 4 A2.07 - Ability to (a) predict the impacts of the following on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC);

and (b) based on those 217000 RCIC x predictions, use procedures to 3.1 86 correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of lube oil A2.06 - Ability to (a) predict the impacts of the following on the AUTOMATIC DEPRESSURIZATION SYSTEM; and (b) based on 218000ADS x those predictions, use 4.3 87 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: ADS initiation signals present 2.4.46 - Emergency Procedures I Plan: Ability to verify that the 215005 APRM I LPRM x alarms are consistent with the 4.2 88 plant conditions.

2.2.44 - Equipment Control:

Ability to interpret control room indications to verify the status 212000 RPS x and operation of a system, and 4.4 89 understand how operator actions and directives affect plant and system conditions.

2.2.40 - Equipment Control:

400000 Component Cooling Water x Ability to apply technical 4.7 90 specifications for a system.

K1 .05 - Knowledge of the physical connections and/or 262001 AC Electrical cause-effect relationships Distribution x between A.C. ELECTRICAL 3.0 1 DISTRIBUTION and the following: Main turbine/generator K1 .02 - Knowledge of the physical connections and/or cause-effect relationships 217000 RCIC x between REACTOR CORE 3.5 2 ISOLATION COOLING SYSTEM (RCIC) and the following: Nuclear boiler system 400000 Component Cooling K2.02 - Knowledge of electrical Water x power supplies to the following: 2.9 3 CCWvalves K2.01 - Knowledge of electrical 205000 Shutdown Cooling x power supplies to the following: 3.1 4 Pump motors

ES-401 Form ES-401-1 JAF 16-1 NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A A System #I Name G Imp. Q#

1 2 3 4 5 6 1 2 3 4 K3.02 - Knowledge of the effect that a loss or malfunction of the UNINTERRUPTABLE POWER 262002 UPS (AC/DC) x SUPPLY (A.C./D.C.) will have 2.9 5 on following: Recirculation pump speed: Plant-Soecific K3.02 - Knowledge of the effect that a loss or malfunction of the AUTOMATIC 218000ADS x DEPRESSURIZATION SYSTEM 4.5 6 will have on following: Ability to rapidly depressurize the reactor K4.05 - Knowledge of STANDBY LIQUID CONTROL SYSTEM design feature(s) 211000 SLC x and/or interlocks which provide 3.4 7 for the following: Dispersal of boron upon injection into the vessel K4.06 - Knowledge of INTERMEDIATE RANGE MONITOR (IRM) SYSTEM 215003 IRM x design feature(s) and/or 2.6 8 interlocks which provide for the following: Alarm seal-in K5.06 - Knowledge of the operational implications of the following concepts as they apply to AVERAGE POWER RANGE 215005 APRM I LPRM x MONITOR/LOCAL POWER 2.5 9 RANGE MONITOR SYSTEM:

Assignment of LPRMs to specific APRM channels K5.02 - Knowledge of the operational implications of the following concepts as they apply 212000 RPS x to REACTOR PROTECTION 3.3 10 SYSTEM: Specific logic arrangements K6.10 - Knowledge of the effect that a loss or malfunction of the 203000 RHR/LPCI: Injection following will have on the Mode x RHR/LPCI: INJECTION MODE 3.0 11 (PLANT SPECIFIC): Component cooling water systems K6.05 - Knowledge of the effect that a loss or malfunction of the 215004 Source Range Monitor x following will have on the 2.6 12 SOURCE RANGE MONITOR (SRM) SYSTEM: Trip units A 1.05 - Ability to predict and/or monitor changes in parameters associated with operating the 259002 Reactor Water Level Control x REACTOR WATER LEVEL 2.9 13 CONTROL SYSTEM controls including: FWRV/startup level control position: Plant-Specific

ES-401 Form ES-401-1 JAF 16-1 NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A A System #I Name G Imp. Q#

1 2 3 4 5 6 1 2 3 4 A 1.02 - Ability to predict and/or monitor changes in parameters associated with operating the 209001 LPCS x LOW PRESSURE CORE 3.2 14 SPRAY SYSTEM controls includina: Core sprav oressure A2.03 - Ability to (a) predict the impacts of the following on the STANDBY GAS TREATMENT SYSTEM; and (b) based on those predictions, use 261000 SGTS x procedures to correct, control, or 2.9 15 mitigate the consequences of those abnormal conditions or operations: High train temoerature A2.10 - Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM 223002 PCIS/Nuclear Steam SUPPLY SHUT-OFF; and (b)

Supply Shutoff x based on those predictions, use 3.9 16 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of coolant accidents A3.08 - Ability to monitor automatic operations of the 239002 SRVs x RELIEF/SAFETY VALVES 3.6 17 includina: Liahts and alarms A3.03 - Ability to monitor automatic operations of the EMERGENCY GENERATORS 264000 EDGs x (DIESEUJET) including:

3.4 18 Indicating lights, meters, and recorders A4.02 - Ability to manually operate and/or monitor in the 206000 HPCI x control room: Flow controller:

4.0 19 BWR-2,3,4 A4.02 - Ability to manually 263000 DC Electrical operate and/or monitor in the Distribution x control room: Battery voltage 3.2 20 indicator: Plant-Soecific 2.4.31 - Emergency Procedures I Plan: Knowledge of 300000 Instrument Air x annunciator alarms, indications, 4.2 21 or resoonse orocedures.

2.4.11 - Emergency Procedures 263000 DC Electrical Distribution x I Plan: Knowledge of abnormal 4.0 22 condition procedures.

A4.02 - Ability to manually 215004 Source Range Monitor x operate and/or monitor in the 3.0 23 control room: SRM recorder

ES-401 Form ES-401-1 JAF 16-1 NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A A System #I Name G Imp. Q#

1 2 3 4 5 6 1 2 3 4 K5.01 - Knowledge of the operational implications of the following concepts as they apply 206000 HPCI x to HIGH PRESSURE COOLANT 3.3 24 INJECTION SYSTEM: Turbine ooeration: BWR-2,3,4 A2.11 - Ability to (a) predict the impacts of the following on the REACTOR PROTECTION SYSTEM; and (b) based on those predictions, use 212000 RPS x procedures to correct, control, or 4.0 25 mitigate the consequences of those abnormal conditions or operations: Main steamline isolation valve closure K6.05 - Knowledge of the effect that a loss or malfunction of the 239002 SRVs x following will have on the 3.0 26 RELIEF/SAFETY VALVES:

Discharge line vacuum breaker KIA Category Totals: 2 2 2 2 3 3 2 3/2 2 3 2/3 Group Point Total:

I 26/5

ES-401 Form ES-401-1 JAF 16-1 NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A A System # I Name G Imp. Q#

1 2 3 4 5 6 1 2 3 4 A2.03 - Ability to (a) predict the impacts of the following on the REACTOR WATER CLEANUP SYSTEM; and (b) based on those predictions, use 204000 RWCU x procedures to correct, control, 2.9 91 or mitigate the consequences of those abnormal conditions or operations: Flow control valve failure 2.1.31 - Conduct of Operations:

Ability to locate control room 272000 Radiation switches, controls, and Monitoring x indications, and to determine 4.3 92 that they correctly reflect the desired plant lineup.

A2.03 - Ability to (a) predict the impacts of the following on the FIRE PROTECTION SYSTEM; and (b) based on those predictions, use procedures to 286000 Fire Protection x correct, control, or mitigate the 3.0 93 consequences of those abnormal conditions or operations: A.C. distribution failure: Plant-Specific K1 .02 - Knowledge of the physical connections and/or cause-effect relationships 271000 Off-gas x between OFFGAS SYSTEM 3.1 27 and the following: Process radiation monitoring system K1 .03 - Knowledge of the physical connections and/or 202002 Recirculation Flow cause-effect relationships Control x between RECIRCULATION 3.7 28 FLOW CONTROL SYSTEM and the following: Reactor core flow K3.01 - Knowledge of the effect that a loss or malfunction of the MSIV LEAKAGE CONTROL 239003 MSIV Leakage Control x SYSTEM will have on following: 3.3 29 Radiation release to the environment: BWR-4,5,6 (P-Spec)

K4.06 - Knowledge of REACTOR/TURBINE 241000 Reactor/Turbine PRESSURE REGULATING Pressure Regulator x SYSTEM design feature(s) 3.6 30 and/or interlocks which provide for the following: Turbine trip K5.02 - Knowledge of the operational implications of the following concepts as they apply 201001 CRD Hydraulic x to CONTROL ROD DRIVE 2.6 31 HYDRAULIC SYSTEM: Flow indication

ES-401 Form ES-401-1 JAF 16-1 NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A A System #I Name G Imp. Q#

1 2 3 4 5 6 1 2 3 4 K6.09 - Knowledge of the effect that a loss or malfunction of the 223001 Primary following will have on the Containment System and x PRIMARY CONTAINMENT 3.4 32 Auxiliaries SYSTEM AND AUXILIARIES:

Drywell vacuum relief system A 1.04 - Ability to predict and/or monitor changes in parameters 256000 Reactor associated with operating the Condensate x REACTOR CONDENSATE 2.9 33 SYSTEM controls including:

Hotwell level A2.04 - Ability to (a) predict the impacts of the following on the REACTOR MANUAL CONTROL SYSTEM; and (b) 201002 RMCS x based on those predictions, use 3.2 34 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Control rod block A3.02 - Ability to monitor automatic operations of the 233000 Fuel Pool Cooling/Cleanup x FUEL POOL COOLING AND 2.6 35 CLEAN-UP including: Pump trip(s)

A4.02 - Ability to manually 290003 Control Room HVAC x operate and/or monitor in the 2.8 36 control room: Fans 2.1.28 - Conduct of Operations:

Knowledge of the purpose and 204000 RWCU x function of major system 4.1 37 components and controls.

A 1.03 - Ability to predict and/or monitor changes in parameters 201003 Control Rod and associated with operating the Drive Mechanism x CONTROL ROD AND DRIVE 2.9 38 MECHANISM controls including:

CRD drive water flow KIA Category Totals: 2 0 1 1 1 1 2 1/2 1 1 1/1 Group Point Total:

I 12/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: James A. Fitzpatrick Date: March 2016 RO SRO-Only Category K/A# Topic IR Q# IR Q#

Knowledge of the fuel-handling 2.1.35 3.9 94 responsibilities of SROs.

Knowledge of conduct of operations 2.1.1 3.8 66

1. requirements.

Conduct Knowledge of individual licensed operator of Operations responsibilities related to shift staffing, 2.1.4 such as medical requirements, "no-solo" 3.3 67 operation, maintenance of active license status, 10CFR55, etc.

Subtotal 2 1 Knowledge of limiting conditions for 2.2.22 4.7 95 operations and safety limits.

Ability to recognize system parameters that 2.2.42 are entry-level conditions for Technical 4.6 100 Specifications.

2.

Equipment Knowledge of the process used to track 2.2.43 3.0 68 Control inoperable alarms.

Ability to obtain and interpret station electrical 2.2.41 3.5 69 and mechanical drawings.

Knowledge of less than one hour technical 2.2.39 3.9 74 specification action statements for systems.

Subtotal 3 2 2.3.11 Ability to control radiation releases. 4.3 96 Knowledge of Radiological Safety Procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, 2.3.13 3.8 98 containment entry requirements, fuel handling

3. responsibilities, access to locked high Radiation radiation areas, aligning filters, etc.

Control Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, 2.3.15 2.9 70 portable survey instruments, personnel monitoring equipment, etc.

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Ability to comply with radiation work permit 2.3.7 requirements during normal or abnormal 3.5 71 conditions.

Subtotal 2 2 Knowledge of RO tasks performed outside the 2.4.34 main control room during an emergency and 4.1 97 the resultant ooerational effects.

Knowledge of procedures relating to a 2.4.28 4.1 99 security event (non-safeguards information).

4.

Emergency Knowledge of EOP layout, symbols, and Procedures I 2.4.19 3.4 72 icons.

Plan Knowledge of EOP entry conditions and 2.4.1 4.6 73 immediate action steos.

Knowledge of operator response to loss of all 2.4.32 3.6 75 annunciators.

Subtotal 3 2 Tier 3 Point Total 10 7

ES-401 Record of Rejected KlAs Form ES-401-4 Tier I Randomly Selected KIA Reason for Rejection Grou 295027 High Containment This topic applies to plants with Mark Ill Temperature containments only. The facility has a Mark I 1I 1 containment.

295011 High Containment This topic applies to plants with Mark 111 Temperature containments only. The facility has a Mark I 1I 2 containment.

207000 Isolation (Emergency) This system is not installed at the facility.

2I 1 Condenser 209002 HPCS This system is not installed at the facility.

2I 1 201004 RSCS This system is no longer installed at the facility.

2/2 201005 RCIS This system is not installed at the facility.

2/2 2.2.3 Knowledge of the design, This KIA applies to multi-unit facilities only.

procedural, and operational G differences between units.

2.2.4 Ability to explain the This KIA applies to multi-unit facilities only.

variations in control board/control room layouts, G systems, instrumentation, and procedural actions between units at a facility.

Question 76 An acceptable question could not be developed for the randomly selected KIA due to lack of 700000 Generator Voltage and proceduralized Generator frequency limitations Electric Grid Disturbances related to voltage or grid disturbances at the AA2.06 - Ability to determine facility.

and/or interpret the following as Randomly re-selected KIA 700000 Generator they apply to GENERATOR 1/ 1 Voltage and Electric Grid Disturbances AA2.09 VOLTAGE AND ELECTRIC

- Ability to determine and/or interpret the GRID DISTURBANCES:

following as they apply to GENERATOR Generator frequency limitations VOLTAGE AND ELECTRIC GRID DISTURBANCES: Operational status of emergency diesel generators.

Question 80 An acceptable question could not be developed for the randomly selected generic KIA due to 295003 Partial or Complete lack of RO-specific tasks performed outside the Loss of AC Power main control room related to a loss of AC power 2.4.34 - Knowledge of RO tasks event.

1/ 1 performed outside the main Randomly re-selected KIA 295003 Partial or control room during an Complete Loss of AC Power 2.1.20 - Ability to emergency and the resultant interpret and execute procedure steps.

operational effects.

Question 82 An acceptable question could not be developed for the randomly selected generic KIA due to 295037 SCRAM Conditions lack of Technical Specification bases related to Present and Reactor Power the beyond design basis event of a failure to Above APRM Downscale or scram.

Unknown 1/ 1 Randomly re-selected KIA 295037 SCRAM 2.2.25 - Knowledge of bases in Conditions Present and Reactor Power Above technical specifications for APRM Downscale or Unknown 2.4.18 -

limiting conditions for operations Knowledge of the specific bases for EOPs.

and safety limits.

Question 84 An acceptable question could not be developed at the SRO level for the randomly selected 295034 Secondary generic KIA due to lack of documented system Containment Ventilation High limits I precautions associated with Secondary Radiation 1/2 Containment Ventilation high radiation.

2.1.32 -Ability to explain and Randomly re-selected KIA 295034 Secondary apply all system limits and Containment Ventilation High Radiation 2.4.41 -

precautions.

Knowledge of the emergency action level thresholds and classifications.

Question 90 An acceptable question could not be developed at the SRO level for the randomly selected 400000 Component Cooling generic KIA due to lack of EOP entry conditions Water and immediate action steps associated with 2.4.1 - Knowledge of EOP entry Component Cooling Water.

2/1 conditions and immediate action Randomly re-selected KIA 400000 Component steps.

Cooling Water 2.2.40 - Ability to apply technical specifications for a system.

Question 10 An acceptable question could not be written for the randomly selected KIA without testing 212000 RPS minutia or GFE knowledge.

K5.01 - Knowledge of the Randomly re-selected KIA 212000 RPS K5.02 -

operational implications of the 2/1 Knowledge of the operational implications of the following concepts as they following concepts as they apply to REACTOR apply to REACTOR PROTECTION SYSTEM: Specific logic PROTECTION SYSTEM: Fuel arrangements.

thermal time constant Question 21 An acceptable question could not be developed for the randomly selected KIA at the correct 300000 Instrument Air license level due to lack of appropriate 2.2.40 - Ability to apply Technical Specifications related directly to 2/1 technical specifications for a Instrument Air.

system.

Randomly re-selected KIA 300000 Instrument Air 2.4.31 - Knowledge of annunciator alarms, indications, or response procedures.

Question 28 The facility does not have hydraulic power units related to Recirculation Flow Control.

202002 Recirculation Flow Control Randomly re-selected KIA 202002 Recirculation Flow Control K1 .03 - Knowledge 2/2 K2.02 - Knowledge of electrical of the physical connections and/or cause-effect power supplies to the following:

relationships between RECIRCULATION Hydraulic power unit: Plant-FLOW CONTROL SYSTEM and the following:

Specific Reactor core flow.

Question 37 An acceptable question could not be developed for the randomly selected KIA at the appropriate 204000 RWCU license level due to lack of safety related 2/2 2.2.37 - Ability to determine function in the RWCU system.

operability and I or availability of Randomly re-selected KIA 204000 RWCU safety related equipment.

2.1.28 - Knowledge of the purpose and function of major system components and controls.

Question 54 An acceptable question could not be developed for the randomly selected KIA due to lack of 295004 Partial or Complete association between Loss of DC Power and Loss of DC Power EOP entry conditions.

1I 1 2.4.2 - Knowledge of system set Randomly re-selected KIA 295004 Partial or points, interlocks and automatic Complete Loss of DC Power 2.2.37 - Ability to actions associated with EOP determine operability and/or availability of entry conditions.

safety related equipment.

Question 60 An acceptable question could not be developed for the randomly selected KIA due to a lack of 295033 High Secondary plant-specific interrelation between hi~h area Containment Area Radiation radiation levels and Secondary Containment Levels ventilation.

EK2.03 - Knowledge of the Randomly re-selected KIA 295033 High 1I 2 interrelations between HIGH Secondary Containment Area Radiation Levels SECONDARY CONTAINMENT EK2.01 - Knowledge of the interrelations AREA RADIATION LEVELS between HIGH SECONDARY CONTAINMENT and the following: Secondary AREA RADIATION LEVELS and the following:

containment ventilation: Plant-Area radiation monitoring system.

Specific Question 62 An acceptable question could not be developed for the randomly selected KIA without 295036 Secondary overlapping concepts tested in Question 85 due Containment High Sump/Area to limited relationship between high sump/area Water Level water levels and radiation monitoring.

EA 1.04 - Ability to operate Randomly re-selected KIA 295036 Secondary 1I 2 and/or monitor the following as Containment High Sump/Area Water Level they apply to SECONDARY EA 1.01 - Ability to operate and/or monitor the CONTAINMENT HIGH following as they apply to SECONDARY SUMP/AREA WATER LEVEL:

CONTAINMENT HIGH SUMP/AREA WATER Radiation monitoring: Plant-LEVEL: Secondary containment equipment and Specific floor drain systems.

Question 64 An acceptable question could not be developed for the randomly selected KIA due to lack of 295017 High Off-site Release reference materials related to high offsite Rate release rate that would be used by an RO.

1I 2 2.1.25 - Ability to interpret Randomly re-selected KIA 295017 High Off-site reference materials, such as Release Rate 2.4.6 - Knowledge of EOP graphs, curves, tables, etc.

mitigation strategies.

Question 22 An acceptable question could not be developed for the randomly selected KIA without testing 263000 DC Electrical minutia.

Distribution Randomly re-selected KIA 263000 DC 2I 1 2.4.50 - Ability to verify system Electrical Distribution 2.4.11 - Knowledge of alarm setpoints and operate abnormal condition procedures.

controls identified in the alarm response manual.

Question 33 Rejected KA due to low Operational value for discriminating RO level question.

256000 Reactor Condensate Randomly re-selected KIA 256000 Reactor A 1.08 - Ability to predict and/or Condensate A 1.04 - Ability to predict and/or monitor changes in parameters monitor changes in parameters associated with 212 associated with operating the operating the REACTOR CONDENSATE REACTOR CONDENSATE SYSTEM controls including: Hotwell level.

SYSTEM controls including:

System water quality Question 67 The randomly selected KIA is tested extensively on the operating exam and better suited to that 2.1.18 - Ability to make portion of the exam.

accurate, clear and concise logs, records, status boards, Randomly re-selected KIA 2.1.4 - Knowledge of 3 and reports. individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc.

Question 81 An adequate question could not be developed for the randomly selected KIA without 295028 High Drywell overlapping one of the administrative JPMs.

Temperature Randomly re-selected KIA 295028 High Drywell 2.2.22 - Knowledge of limiting 1I 1 Temperature 2.1. 7 - Ability to evaluate plant conditions for operations and performance and make operational judgments safety limits.

based on operating characteristics, reactor behavior, and instrument interpretation.

ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facility: James A. Fitzpatrick Date of Exam: March 2016 Scenario Numbers: 1/2/3/4/5 Operating Test No.:16-1 Initials QUALITATIVE ATTRIBUTES a b* c#-

1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the operators into expected events.

2. The scenarios consist mostly of related events.

3. Each event description consists of

the point in the scenario when it is to be initiated

the malfunction(s) or conditions that are entered to initiate the event

the symptoms/cues that will be visible to the crew

the expected operator actions (by shift position)

the event termination point (if applicable)

4. The events are valid with regard to physics and thermodynamics.

5. Sequencing and timing of events is reasonable, and allows the examination team to obtain complete evaluation results commensurate with the scenario objectives.

6. If time compression techniques are used, the scenario summary clearly so indicates.

Operators have sufficient time to carry out expected activities without undue time constraints.

Cues are given.

7. The simulator modeling is not altered.

8. The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated to ensure that functional fidelity is maintained while running the planned scenarios.

9. Every operator will be evaluated using at least one new or significantly modified scenario. All other scenarios have been altered in accordance with Section D.5 of ES-301.

10. All individual operator competencies can be evaluated, as verified using Form ES-301-6 (submit the form along with the simulator scenarios).

11. The scenario set provides the opportunity for each applicant to be evaluated in each of the applicable rating factors. (Competency Rating factors as described on forms ES-303-1 and ES-303-3.)

12. Each applicant will be significantly involved in the minimum number of transients and events specified on Form ES-301-5 (submit the form with the simulator scenarios).

13. The level of difficulty is appropriate to support licensing decisions for each crew position.

Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes -- -- --

1. Malfunctions after EOP entry (1-2) 3/3/2/2/2

2. Abnormal events (2-4) 2/2/4/2/3

3. Major transients (1-2) 1/1/1/1/1

4. EOPs entered/requiring substantive actions (1-2) 1/2/2/2/2

5. EOP contingencies requiring substantive actions (0-2) 1/2/2/1/1

6. EOP based Critical tasks (2-3) 2/2/3/2/2 NOTE:

The facility signature is not applicable for NRG-developed tests.

Independent NRC reviewer initial items in Column "c"; chief examiner concurrence required.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: James A. Fitzpatrick Date of Examination: March 2016 Examination Level: RO Operating Test Number: 16-1 Administrative Topic Type Describe activity to be performed (see Note) Code*

Manually Compute Average Drywell Air Temperature Conduct of Operations M,R KIA 2.1.20 (4.6), ST-40C Determine Work Hour Limitations Conduct of Operations M,R KIA 2.1.5 (2.9), EN-OM-123 Determine Tagout Isolation Boundary for CRD Pump Equipment Control D,R KIA2.2.13(4.1), EN-OP-102 Determine Worker Exposure for Emergent Work P,D,R Radiation Control KIA 2.3.4 (3.2), EN-RP-201 14-2 NRC P~n NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

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

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

(P)revious 2 exams (S 1; randomly selected)

ES-301 Administrative Topics Outline Form ES-301-1 Facility: James A. Fitz12atrick Date of Examination: March 2016 Examination Level: SRO Operating Test Number: 16-1 Administrative Topic Type Describe activity to be performed (see Note) Code*

Manually Compute Average Drywell Air Temperature, Determine Technical Specification Implications Conduct of Operations M,R KIA 2.1.20 (4.6), ST-40C Determine Work Hour Limitations and Actions for Waiver Conduct of Operations M,R KIA 2.1.5 (3.9), EN-OM-123 Review Tagout Isolation Boundary for CRD Pump Equipment Control D,R KIA 2.2.13 (4.3), EN-OP-102 Determine Worker Exposure for Emergent Work and Required Actions Radiation Control M,R KIA 2.3.4 (3.7), EN-RP-201 Determine Emergency Classification and Initiate Event P,D, R Notification Emergency Plan KIA 2.4.40 (4.5), IAP-1, IAP-2 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

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

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

(P)revious 2 exams (S 1; randomly selected)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: James A. Fitzpatrick Date of Examination: March 2016 Exam Level: RO/SRO Operating Test No.: 16-1 Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System I JPM Title Type Code* Safety Function

a. Transfer Bus 10100 from Reserve to Normal Using Single Meter Voltage Match Method P,D,A,S 6

14-1 NRC KIA 262001 A4.04 (3.6/3.7), OP-46A

b. Perform Actions for Fire in Plant D,A,S 1 KIA 600000 AA2.17 (3.1/3.6), AOP-28

c. Perform HPCI Full-Flow Test, Steam Leak with Failure to Automatically Isolate M,A, EN,S 2 KIA 206000 A4.03 (3.1/3.0), ST-4N, ARP 09-3-3-2(13)

d. Reset ARI and Scram, Perform Post Scram Reset Control Rod Position Check M, EN, S 7 KIA 212000 A4.14 (3.8/3.8), AOP-1

e. Place Shutdown Cooling in Service D, L, S 4 KIA 205000 A4.01 (3.7/3.7), AOP-30

f. Recover Turbine Building Ventilation After Exhaust Duct Radiation Monitor Trip Isolation D,S 9 KIA 288000 A4.01 (3.1/2.9), OP-52

g. Supply Ventilation Loads with Emergency Service Water N,EN,S 8 KIA 400000 A4.01 (3.1/3.0), AOP-11

h. (RO Only) Perform Main Turbine Roll N, L, S 3 KIA 241000 A4.11 (3.1/3.1 }, OP-9 In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Vent Torus to Lower Primary Containment Pressure P,D,A,E 5

KIA 295010 AA1 .05 (3.1/3.4), EP-6 14-2 NRC

j. De-energize Scram Solenoids, Scram Air Header Remains Pressurized M,A,R, E 7 KIA 295037 EA1 .01 (4.6/4.6), EP-3

k. Swap CRD Flow Control Valves D,R 1 KIA 201001 2.1.20 (4.6/4.6), OP-25

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 I SRO-I / SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank :59/:58/:54 (E)mergency or abnormal in-plant <!:1/<!:1/<!:1 (EN)gineered safety feature <!: 1 I<!: 1 I<!: 1 (control room system)

(L)ow-Power I Shutdown <!:1/<!:1/<!:1 (N)ew or (M}odified from bank including 1(A} <!:2/<!:2/<!:1 (P)revious 2 exams s 3 Is 3 Is 2 (randomly selected)

(R)CA <!:1/<!:1/<!:1 (S)imulator

Appendix D Scenario Outline Form ES-D-1 Facility: James A. Fitzpatrick Scenario No.: NRC-1 Op-Test No.: 16-1 Examiners: Operators:

Initial Conditions: The plant is operating at approximately 100% power. Core Spray A is out of service for maintenance.

Turnover: Perform Core Spray valve testing per ST-3PA. The procedure is in progress up to step 8.4.4. Complete section 8.4 and then hold.

Event Malf. Event Event No. No. Type* Description N- Perform Core Spray Valve Testing 1 N/A BOP, SRO ST-3PA I-ATC, APRM B Fails Upscale 2 NM14:B SRO OP-16, ARP 09-5-1-4 Remote HPCI Aux Oil Pump Power Supply Loss 3 C-SRO HP15 ARP 09-3-3-38, Technical Specifications C- Control Rod Drive Pump Trip, One Control Rod Drive Accumulator RD06 4 BOP, Low Pressure RD09 SRO AOP-69, ARP-09-5-1-43, Technical Specifications R-ATC, Main Turbine Vibration 5 TU04 SRO AOP-66, AOP-1, EOP-2 C-BOP Hydraulic ATWS 6 RD13 M-All EOP-3 C- Delayed SLC Pump Trip (first pump only, maybe after 1-2 minutes) 7 SL01 ATC, SRO EOP-3 Recirculation Flow Controllers Fail As-ls; Recirculation Pumps Fail RR02 I-ATC, 8 to Automatically Trip RR13 SRO EOP-3 C- Turbine Bypass Valves Fail Partially Closed 9 TC04 BOP, SRO EOP-3

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor

Facility: James A. Fitzpatrick Scenario No.: NRC-1 Op-Test No.: 16-1

1. Total malfunctions (5-8) 8 Events 2,3,4,5,6,7,8,9

2. Malfunctions after EOP entry (1-2) 3 Events 7,8,9

3. Abnormal events (2-4) 2 Events 4 & 5

4. Major transients (1-2) 1 Event 6

5. EOPs entered/requiring substantive actions (1-2) 1 EOP-2

6. EOP contingencies requiring substantive actions (0-2) 1 EOP-3

7. Critical tasks (2-3) 2 CRITICAL TASK DESCRIPTIONS:

CT-1: Given a failure to scram with Reactor power above 2.5%, the crew will lower Reactor power by one or more of the following methods, in accordance with EOP-3:

Terminating and preventing all RPV injection except SLC, RCIC, and CRD

Tripping Recirculation pumps

Injecting boron CT-2: Given a failure to scram, the crew will initiate Control Rod insertion, in accordance with EOP-3.

Appendix D Scenario Outline Form ES-D-1 Facility: James A. Fitzpatrick Scenario No.: NRC-2 Op-Test No.: 16-1 Examiners: Operators:

Initial Conditions: The plant is operating at approximately 73% power to support Circulating Water system maintenance and a control rod pattern adjustment. Core Spray A is out of service for maintenance.

Turnover: Swap Circulating Water pumps per OP-4 section G.5.3. Start Circulating Water pump C and then secure Circulating Water pump B.

Event Malf. Event Event No. No. Type* Description N- Swap Circulating Water Pumps 1 N/A BOP, SRO OP-4 R- Perform Control Rod Pattern Adjustment 2 NIA ATC, SRO OP-26 C- Stuck Control Rod 3 RD10 ATC, SRO OP-25 Core Spray Sparger Leak 4 Override C-SRO ARP 09-3-2-1, Technical Specifications C- Electrical Fault on 10400 Bus 5 ED19:D BOP, SRO AOP-17, AOP-8, AOP-60, Technical Specifications RR15:A Loss of Coolant Accident 6 M-All MS02:A AOP-1, EOP-2, EOP-4 C- RHR Pumps Fail to Automatically Start 7 RH14 BOP, SRO EOP-2 FW19:A C- Condensate Pump A Trips; HPCI Fails to Automatically Start 8 ATC, HP01 SRO EOP-2 HPCI Trips 9 HP02 C-All EOP-2

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor

Facility: James A. Fitzpatrick Scenario No.: NRC-2 Op-Test No.: 16-1

1. Total malfunctions (5-8) 7 Events 3,4,5,6,7,8,9

2. Malfunctions after EOP entry (1-2) 3 Events 7,8,9

3. Abnormal events (2-4) 2 Events 3 &5

4. Major transients (1-2) 1 Event&

5. EOPs entered/requiring substantive actions (1-2) 2 EOP-2, EOP-4

6. EOP contingencies requiring substantive actions (0-2) 2 EOP-2 Alt Level Leg, EOP-2 Emergency Depress Leg

7. Critical tasks (2-3) 2 CRITICAL TASK DESCRIPTIONS:

CT-1: Given a coolant leak inside the Containment, the crew will spray the Drywell, in accordance with EOP-4.

CT-2: Given a coolant leak, a loss of high pressure injection systems, and the inability to restore and maintain Reactor water level above the Top of Active Fuel (TAF), the crew will initiate actions for an Emergency RPV Depressurization, in accordance with EOP-2.

Appendix D Scenario Outline Form ES-D-1 Facility: James A. Fitzpatrick Scenario No.: NRC-3 Op-Test No.: 16-1 Examiners: Operators:

Initial Conditions: The plant is operating at approximately 100% power. A down-power is required to support water box cleaning.

Turnover: Test EHC pump B auto-start capability per OP-8 section G.2. Secure EHC pump A following the test. Then, lower Reactor power with Recirculation flow. Stop at approximately 80%

power for further Reactor Engineering direction.

Event Malf. Event Event No. No. Type* Description N- Test EHC Pump B Auto-Start, Secure EHC Pump A 1 N/A BOP, SRO OP-8 R- Lower Reactor Power with Recirculation Flow 2 N/A ATC, SRO OP-27 I-ATC, Recirculation Pump A Speed Drifts Low 3 Override SRO AOP-8, AOP-32, OP-27, Technical Specifications Remote EP09 Seismic Event with Loss of Line 3 4 C-SRO ED43:A AOP-14, AOP-72, Technical Specifications RR04:A Recirculation Pump A Seal Failure 5 C-All RR05:A ARP 09-4-2-38, AOP-8, OP-27, AOP-39, Technical Specifications Remote EP09 Seismic Event with Steam Leak in Drywell 6 C-All MS02 AOP-14, AOP-39, AOP-1, EOP-2, EOP-4 RH10 RHR Suction Piping Leak; RHR Suction Fails to Isolate 7 M-All Overrides EOP-2, EOP-4 RP01A I-ATC, RPS Fails to Scram the Reactor 8

RP01B SRO EOP-2, AOP-1 Multiple Control Rods Fail to Insert 9 RD10 C-All EOP-3, EOP-3a

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor

Facility: James A. Fitzpatrick Scenario No.: NRC-3 Op-Test No.: 16-1

1. Total malfunctions (5-8) 7 Events 3,4,5,6,7,8,9

2. Malfunctions after EOP entry (1-2) 2 Events 8 & 9

3. Abnormal events (2-4) 4 Events 3,4,5,6

4. Major transients (1-2) 1 Event7

5. EOPs entered/requiring substantive actions (1-2) 2 EOP-2, EOP-4

6. EOP contingencies requiring substantive actions (0-2) 2 EOP-3, EOP-3a

7. Critical tasks (2-3) 3 CRITICAL TASK DESCRIPTIONS:

CT-1: Given the need for a Reactor scram and failure of RPS to insert control rods, the crew will initiate ARI, in accordance with AOP-1 and/or EOP-3.

CT-2: Given an un-isolable Torus water leak and the inability to maintain Torus water level above 10.75',

the crew will initiate a manual HPCI turbine trip, in accordance with EOP-4.

CT-3: Given an un-isolable Torus water leak and the inability to maintain Torus water level above 9.58',

the crew will perform an Emergency RPV Depressurization, in accordance with EOP-3a.

Appendix D Scenario Outline Form ES-D-1 Facility: James A. Fitzpatrick Scenario No.: NRC-4 Op-Test No.: 16-1 Examiners: Operators:

Initial Conditions: The plant is operating at approximately 7% power. A startup is in progress. The RWM is inoperable and bypassed.

Turnover: Transition to Mode 1 and withdraw IRMs. Then continue withdrawing control rods per the startup sequence.

Event Malf. Event Event No. No. Type* Description N- Transition to Mode 1 1 N/A BOP, SRO OP-65 R- Withdraw Control Rods 2 N/A ATC, SRO OP-65, OP-26 C- Control Rod Double Notches 3 RD08 ATC, SRO OP-26 Remote I-BOP, LPCI Inverter Trips 4

ED23 SRO ARP 09-8-3-2, Technical Specifications CU07 C- RWCU Pump Seal Fails; RWCU Automatic Isolation Fails 5 CU10 BOP, SRO ARP 09-3-3-2(12), EOP-5, Technical Specifications CU12 C- RCIC Inadvertently Initiates 6 RC06 BOP, SRO AOP-77, Technical Specifications RC09 RCIC Steam Leak; RCIC Fails to Isolate 7 RC12 M-All EOP-5, AOP-1, EOP-2 Remote C- Bypass Opening Jack Fails 8 Override ATC, SRO EOP-2 C- Multiple SRVs Fail to Open 9 ADO? BOP, SRO EOP-2

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor

Facility: James A. Fitzpatrick Scenario No.: NRC-4 Op-Test No.: 16-1

1. Total malfunctions (5-8) 7 Events 3,4,5,6,7,8,9

2. Malfunctions after EOP entry (1-2) 2 Events 8 & 9

3. Abnormal events (2-4) 2 Events 5 &6

4. Major transients (1-2) 1 Event7

5. EOPs entered/requiring substantive actions (1-2) 2 EOP-2, EOP-5

6. EOP contingencies requiring substantive actions (0-2) 1 EOP-2 Emergency Depressurization Leg

7. Critical tasks (2-3) 2 CRITICAL TASK DESCRIPTIONS:

CT-1: Given the plant operating at power with an un-isolable primary system discharging into Secondary Containment, the crew will insert a manual Reactor scram, in accordance with EOP-5.

CT-2: Given an un-isolable primary system discharging into Secondary Containment and two areas exceeding Maximum Safe Temperatures, the crew will perform an emergency RPV depressurization, in accordance with EOP-5.

Appendix D Scenario Outline Form ES-D-1 Facility: James A. Fitzpatrick Scenario No.: NRC-5 Op-Test No.: 16-1 Examiners: Operators:

Initial Conditions: The plant is operating at approximately 95% power. SRV A is inoperable.

Turnover: Start RBCLC pump A and then secure RBCLC pump B per OP-40 section G.1. Then, raise Reactor power with Recirculation flow.

Event Malf. Event Event No. No. Type* Description N- Swap RBCLC Pumps 1 N/A BOP, SRO OP-40 R- Raise Reactor Power with Recirculation Flow 2 N/A ATC, SRO OP-27 SLC Squib Valve Continuity Loss 3 SL04:A C-SRO ARP 09-3-3-30, Technical Specifications C- SRV Inadvertently Opens 4 AD06:C BOP, SRO AOP-36, Technical Specifications FW05:A Feedwater Pump Vibration and Delayed Pump Trip 5 C-All FW01:A ARP 09-6-4-11, AOP-41 Fuel Failure 6 RX01 C-All AOP-3, AOP-1, EOP-2 MS05 Main Steam Leak in Turbine Building; One Main Steam Line Fails 7 MS08B M-All to Isolate; Turbine Building Ventilation Fails to Isolate Remote AOP-40, EOP-2, EOP-6 I-BOP, MSIVs Fail to Automatically Isolate 8 RP12 SRO AOP-40, EOP-2, EOP-6 I-ATC, Master Feedwater Level Controller Fails Low 9 Overrides SRO AOP-1, EOP-2

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor

Facility: James A. Fitzpatrick Scenario No.: NRC-5 Op-Test No.: 16-1

1. Total malfunctions (5-8) 7 Events 3,4,5,6,7,8,9

2. Malfunctions after EOP entry (1-2) 2 Events 8 & 9

3. Abnormal events (2-4) 3 Events 4,5,6

4. Major transients (1-2) 1 Event 7

5. EOPs entered/requiring substantive actions (1-2) 2 EOP-2, EOP-6

6. EOP contingencies requiring substantive actions (0-2) 1 EOP-2 Emergency Depressurization Leg

7. Critical tasks (2-3) 2 CRITICAL TASK DESCRIPTIONS:

CT-1: Given a fuel failure, the crew will scram the Reactor, in accordance with AOP-3.

CT-2: Given an un-isolable primary system discharging outside of primary and secondary containments and off-site radioactivity release rates approaching the General Emergency level, the crew will perform an emergency RPV depressurization, in accordance with EOP-6.

ES-401 Written Examination Outline Form ES-401-1 Facility: James A. Fitzpatrick Date of Exam: March 2016 RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G* Total 1 2 3 4 5 6 1 2 3 4

1 3 3 3 3 4 4 20 3 4 7