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Final Outlines (Folder 3)
	ML16085A246
Person / Time
Site:	FitzPatrick
Issue date:	03/01/2016
From:	David Silk; Operations Branch I
To:	Kelly D; FitzPatrick
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ML15195A060	List: ML15201A472; ML16055A001; ML16063A251; ML16081A077; ML16081A159; ML16081A169; ML16081A192; ML16081A201; ML16085A246; ML16085A247; ML16085A248; ML16085A249; ML16145A369; ML16145A383;
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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 A

A A

A G

1 2

3 4

5 6

1 2

3 4

Total A2 G*

Total 1

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 4

4 4

5 5

27 Totals 5

5 5

10 1

2 2

3 3

2 3

2 26 2

3 5

2.

Plant 2

2 0

1 1

2 1

1 1

1 12 0

2 1

3 Systems Tier Totals 4

2 3

3 4

4 4

4 3

38 4

4 8

3. Generic Knowledge & Abilities 1

2 3

4 1

2 3

4 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 if the 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 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 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) KIAs 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)

AA2.09 - Ability to determine and/or interpret the following as they apply to 700000 Generator Voltage and x

GENERATOR VOLTAGE AND Electric Grid Disturbances I 6 ELECTRIC GRID DISTURBANCES:

Operational status of emergency diesel generators AA2.02 - Ability to determine and/or 295004 Partial or Complete interpret the following as they apply to Loss of DC Power I 6 x

PARTIAL OR COMPLETE LOSS OF D.C. POWER: Extent of partial or complete loss of D.C. oower AA2.02 - Ability to determine and/or interpret the following as they apply to 295019 Partial or Complete x

PARTIAL OR COMPLETE LOSS OF Loss of Instrument Air I 8 INSTRUMENT AIR: Status of safety-related instrument air system loads (see AK2.1 - AK2.19) 295001 Partial or Complete 2.1.23 - Conduct of Operations: Ability Loss of Forced Core Flow x

to perform specific system and Circulation I 1 & 4 integrated plant procedures during all modes of olant ooeration.

295003 Partial or Complete

2. 1.20 - Conduct o\\ Operations: Ability Loss of AC Power I 6 x

to interpret and execute procedure steps.

2. 1. 7 - Conduct of Operations: Ability to 295028 High Drywell evaluate plant performance and make Temperature I 5 x

operational judgments based on operating characteristics, reactor behavior, and instrument interoretation.

295037 SCRAM Condition 2.4.18 - Emergency Procedures I Plan:

Present and Reactor Power x

Knowledge of tl1e specific bases for Above APRM Downscale or EOPs.

Unknown/ 1 EK1.03 - Knowledge of the operational 295037 SCRAM Condition implications of the following concepts as Present and Reactor Power they apply to SCRAM CONDITION Above APRM Downscale or x

PRESENT AND REACTOR POWER Unknown/ 1 ABOVE APRM DOWNSCALE OR UNKNOWN: Boron effects on reactor oower <SBLC)

AK1.02 - Knowledge of the operational 295021 Loss of Shutdown x

implications of the following concepts as Cooling I 4 they apply to LOSS OF SHUTDOWN COOLING: Thermal stratification EK1.02 - Knowledge of the operational 295028 High Drywell implications of the following concepts as Temperature I 5 x

they apply to HIGH DRYWELL TEMPERATURE: Equipment environmental aualification 295025 High Reactor Pressure I EK2.01 - Knowledge of the interrelations 3

x between HIGH REACTOR PRESSURE and the followino: RPS AK2.02 - Knowledge of the interrelations 295016 Control Room x

between CONTROL ROOM Abandonment I 7 ABANDONMENT and the following:

Local control stations: Plant-Soecific AK2.04 - Knowledge of the interrelations 295003 Partial or Complete x

between PARTIAL OR COMPLETE Loss of AC Power I 6 LOSS OF A.C. POWER and the followina: A.C. electrical loads Imp.

Q#

4.3 76 3.9 77 3.7 78 4.4 79 4.6 80 4.7 81 4.0 82 4.2 39 3.3 40 2.9 41 4.1 42 4.0 43 3.4 44

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)

AK3.02 - Knowledge of the reasons for 295019 Partial or Complete the following responses as they apply to x

PARTIAL OR COMPLETE LOSS OF Loss of Instrument Air I 8 INSTRUMENT AIR: Standby air compressor operation EK3.06 - Knowledge of the reasons for 295024 High Drywell Pressure I x

the following responses as they apply to 5

HIGH DRYWELL PRESSURE: Reactor SCRAM EK3.07 - Knowledge of the reasons for 295030 Low Suppression Pool the following responses as they apply to x

LOW SUPPRESSION POOL WATER Water Level I 5 LEVEL: NPSH considerations for ECCS pumps EA 1.12 - Ability to operate and/or 295031 Reactor Low Water x

monitor the following as they apply to Level I 2 REACTOR LOW WATER LEVEL:

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 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 Circulation I 1 & 4 FORCED CORE FLOW CIRCULATION:

Recirculation flow control svstem AA2.01 - Ability to determine and/or 295018 Partial or Complete interpret the following as they apply to x

PARTIAL OR COMPLETE LOSS OF Loss of CCW I 8 COMPONENT COOLING WATER:

Component temperatures AA2.05 - Ability to determine and/or 295005 Main Turbine Generator x

interpret the following as they apply to Trip I 3 MAIN TURBINE GENERATOR TRIP:

Reactor power EA2.03 - Ability to determine and/or 295038 High Off-site Release x

interpret the following as they apply to Rate I 9 HIGH OFF-SITE RELEASE RATE:

Radiation levels 295004 Partial or Complete 2.2.37 - Equipment Control: Ability to Loss of DC Power I 6 x

determine operability and/or availability of safety related equipment.

2.4.35 - Emergency Procedures I Plan:

295006 SCRAM I 1 x

Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects.

2.4.45 - Emergency Procedures I Plan:

295023 Refueling Accidents I 8 x

Ability to prioritize and interpret the significance of each annunciator or alarm.

EA2.03 - Ability to determine and/or 295026 Suppression Pool High x

interpret the following as they apply to Water Temperature I 5 SUPPRESSION POOL HIGH WATER TEMPERATURE: Reactor pressure 2.4.9 - Emergency Procedures I Plan:

700000 Generator Voltage and Knowledge of low power I shutdown Electric Grid Disturbances I 6 x

implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitiqation strateqies.

KIA Category Totals:

3 3

413 414 Group Point Total:

Imp.

Q#

3.5 45 4.0 46 3.5 47 3.9 48 3.0 49 3.3 50 3.3 51 3.8 52 3.5 53 3.6 54 3.8 55 4.1 56 3.9 57 3.8 58 I

20/7

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)

AA2.02 - Ability to determine and/or 295015 Incomplete SCRAM/ 1 x

interpret the following as they apply to INCOMPLETE SCRAM: Control rod position 295034 Secondary 2.4.41 - Emergency Procedures I Plan:

Containment Ventilation High x

Knowledge of the emergency action 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 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 Radiation/ 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 Levels/ 9 LEVELS and the following: Area radiation monitorinq system AK3.06 - Knowledge of the reasons for 295002 Loss of Main x

the following responses as they apply to Condenser Vacuum I 3 LOSS OF MAIN CONDENSER VACUUM: Air eiector flow EA 1.01 - Ability to operate and/or 295036 Secondary monitor the following as they apply to SECONDARY CONTAINMENT HIGH Containment High Sump/Area x

SUMP/AREA WATER LEVEL:

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 INCOMPLETE SCRAM: Reactor power 295017 High Off-site Release x

2.4.6 - Emergency Procedures I Plan:

Rate/ 9 Knowledge of EOP mitigation strategies.

AA 1.04 - Ability to operate and/or 295022 Loss of CRD Pumps/ 1 x

monitor the following as they apply to LOSS OF CRD PUMPS: Reactor water cleanup system: Plant-Specific KIA Category Totals:

1 1

1 2

1/2 1/1 Group Point Total:

Imp.

Q#

4.2 83 4.6 84 3.8 85 3.8 59 3.8 60 2.9 61 3.2 62 4.1 63 3.7 64 2.5 65 I 7/3

ES-401 System #I Name K

K K

1 2

3 217000 RCIC 218000 ADS 215005 APRM I LPRM 212000 RPS 400000 Component Cooling Water 262001 AC Electrical x

Distribution 217000 RCIC x

400000 Component Cooling x

Water 205000 Shutdown Cooling x

Form ES-401-1 JAF 16-1 NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K

K K

A A

G 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);

x and (b) based on those predictions, use procedures to 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 x

those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: ADS initiation sionals present 2.4.46 - Emergency Procedures x

I Plan: Ability to verify that the alarms are consistent with the plant conditions.

2.2.44 - Equipment Control:

Ability to interpret control room indications to verify the status x

and operation of a system, and understand how operator actions and directives affect plant and svstem conditions.

2.2.40 - Equipment Control:

x Ability to apply technical specifications for a system.

K1.05 - Knowledge of the physical connections and/or cause-effect relationships between A.C. ELECTRICAL DISTRIBUTION and the followinq: Main turbine/qenerator K1.02 - Knowledge of the physical connections and/or cause-effect relationships between REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) and the followinq: Nuclear boiler system K2.02 - Knowledge of electrical power supplies to the following:

CCWvalves K2.01 - Knowledge of electrical power supplies to the following:

Pump motors Imp.

Q#

3.1 86 4.3 87 4.2 88 4.4 89 4.7 90 3.0 1

3.5 2

2.9 3

3.1 4

ES-401 K

K K

System #I Name 1

2 3

262002 UPS (AC/DC) x 218000 ADS x

211000 SLC 215003 IRM 215005 APRM I LPRM 212000 RPS 203000 RHR/LPCI: Injection Mode 215004 Source Range Monitor 259002 Reactor Water Level Control Form ES-401-1 JAF 16-1 NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K

K K

A A

G 4

5 6

1 2

3 4

K3.02 - Knowledge of the effect that a loss or malfunction of the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) will have on following: Recirculation pump speed: Plant-Specific K3.02 - Knowledge of the effect that a loss or malfunction of the AUTOMATIC DEPRESSURIZATION SYSTEM will have on following: Ability to rapidly depressurize the reactor K4.05 - Knowledge of STANDBY LIQUID CONTROL SYSTEM design feature(s) x and/or interlocks which provide for the following: Dispersal of boron upon injection into the vessel K4.06 - Knowledge of INTERMEDIATE RANGE x

MONITOR (IRM) SYSTEM design feature(s) and/or 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 x

MONITOR/LOCAL POWER RANGE MONITOR SYSTEM:

Assignment of LPRMs to specific APRM channels K5.02 - Knowledge of the operational implications of the x

following concepts as they apply to REACTOR PROTECTION SYSTEM: Specific logic arrangements K6.1 O - Knowledge of the effect that a loss or malfunction of the x

following will have on the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC}: Component cooling water svstems K6.05 - Knowledge of the effect that a loss or malfunction of the x

following will have on the SOURCE RANGE MONITOR (SRM) SYSTEM: Trip units A 1.05 - Ability to predict and/or monitor changes in parameters associated with operating the x

REACTOR WATER LEVEL CONTROL SYSTEM controls including: FWRV/startup level control position: Plant-Specific Imp.

Q#

2.9 5

4.5 6

3.4 7

2.6 8

2.5 9

3.3 10 3.0 11 2.6 12 2.9 13

ES-401 K

K K

System # I Name 1

2 3

n 209001 LPCS 261000 SGTS 223002 PCIS/Nuclear Steam Supply Shutoff 239002 SRVs 264000 EDGs 206000 HPCI 263000 DC Electrical Distribution 300000 Instrument Air 263000 DC Electrical Distribution 215004 Source Range Monitor Form ES-401-1 JAF 16-1 NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K

K K

A A

G 4

5 6

1 2

3 4

I I

I A 1.02 - Ability to predict and/or monitor changes in parameters x

associated with operating the LOW PRESSURE CORE SPRAY SYSTEM controls includinq: Core sorav pressure A2.03 - Ability to (a) predict the impacts of the following on the STANDBY GAS TREATMENT SYSTEM; and (b) based on x

those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High train temoerature A2.1 O - Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM x

SUPPLY SHUT-OFF; and (b) based on those predictions,* use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of coolant accidents A3.08 - Ability to monitor x

automatic operations of the RELIEF/SAFETY VALVES includino: Liohts and alarms A3.03 - Ability to monitor automatic operations of the x

EMERGENCY GENERATORS (DIESEL/JET) including:

Indicating lights, meters, and recorders A4.02 - Ability to manually x

operate and/or monitor in the control room: Flow controller:

BWR-2,3,4 A4.02 - Ability to manually x

operate and/or monitor in the control room: Battery voltage indicator: Plant-Soecific 2.4.31 - Emergency Procedures x

I Plan: Knowledge of annunciator alarms, indications, or resoonse procedures.

2.4.11 - Emergency Procedures x

I Plan: Knowledge of abnormal condition procedures.

A4.02 - Ability to manually x

operate and/or monitor in the control room: SRM recorder Imp.

Q#

3.2 14 2.9 15 3.9 16 3.6 17 3.4 18 4.0 19 3.2 20 4.2 21 4.0 22 3.0 23

ES-401 System #I Name K

K K

1 2

3 206000 HPCI 212000 RPS 239002 SRVs KIA Category Totals:,

2 2

2 Form ES-401-1 JAF 16-1 NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K

K K

A A

G 4

5 6

1 2

3 4

K5.01 - Knowledge of the operational implications of the x

following concepts as they apply to HIGH PRESSURE COOLANT INJECTION SYSTEM: Turbine operation: BWR-2,3,4 A2.11 - Ability to (a) predict the impacts of the following on the REACTOR PROTECTION SYSTEM; and (b) based on x

those predictions, use procedures to correct, control, or 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 x

following will have on the RELIEF/SAFETY VALVES:

Discharqe line vacuum breaker 2

3 3

2 3/2 2

3 2/3 Group Point Total:

Imp.

Q#

3.3 24 4.0 25 3.0 26 I 26/5

ES-401 System #I Name K

K K

1 2

3 204000 RWCU 272000 Radiation Monitoring 286000 Fire Protection 271000 Off-gas x

202002 Recirculation Flow x

Control 239003 MSIV Leakage x

Control 241000 Reactor/Turbine Pressure Regulator 201001 CRD Hydraulic Form ES-401-1 JAF 16-1 NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 2 K

K K

A A

G 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 x

those predictions, use procedures to correct, control, 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 x

switches, controls, and indications, and to determine 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 x

pretjictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: AC. distribution failure: Plant-Specific K1.02 - Knowledge of the physical connections and/or cause-effect relationships between OFFGAS SYSTEM and the following: Process radiation monitoring system K1.03 - Knowledge of the phy~ical connections and/or cause-effect relationships between RECIRCULATION 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 SYSTEM will have on following:

Radiation release to the environment: BWR-4,5,6 (P-Spec)

K4.06 - Knowledge of REACTOR/TURBINE x

PRESSURE REGULATING SYSTEM design feature(s) and/or interlocks which provide for the followinq: Turbine trip K5.02 - Knowledge of the operational implications of the x

following concepts as they apply to CONTROL ROD DRIVE HYDRAULIC SYSTEM: Flow indication Imp.

Q#

2.9 91 4.3 92 3.0 93 3.1 27 3.7 28 3.3 29 3.6 30 2.6 31

ES-401 System # I Name K

K K

1 2

3 223001 Primary Containment System and Auxiliaries 256000 Reactor Condensate 201002 RMCS 233000 Fuel Pool Cooling/Cleanup 290003 Control Room HVAC 204000 RWCU 201003 Control Rod and Drive Mechanism K/A Category Totals:

2 0

1 Form ES-401-1 JAF 16-1 NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 2 K

K K

A A

G 4

5 6

1 2

3 4

K6.09 - Knowledge of the effect that a loss or malfunction of the following will have on the x

PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES:

Drvwell vacuum relief system A 1.04 - Ability to predict and/or monitor changes in parameters x

associated with operating the REACTOR CONDENSATE SYSTEM controls including:

Hotwell level A2.04 - Ability to (a) predict the impacts of the following on the REACTOR MANUAL CONTROL SYSTEM; and (b) x based on those predictions, use 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 x

FUEL POOL COOLING AND CLEAN-UP including: Pump trip(s)

A4.02 - Ability to manually x

operate and/or monitor in the control room: Fans 2.1.28 - Conduct of Operations:

x Knowledge of the purpose and function of major system components and controls.

A 1.03 - Ability to predict and/or monitor changes in parameters x

associated with operating the CONTROL ROD AND DRIVE MECHANISM controls including:

CRD drive water flow 1

1 1

2 1/2 1

1 1/1 Group Point Total:

Imp.

Q#

3.4 32 2.9 33 3.2 34 2.6 35 2.8 36 4.1 37 2.9 38 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 KIA#

Topic Q#

Q#

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

2.1.1 Knowledge of conduct of operations 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, 1 OCFR55, etc.

Subtotal 2

1 2.2.22 Knowledge of limiting conditions for 4.7 95 operations and safatv limits.

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

2.

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

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

2.2.39 Knowledge of less than one hour technical 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 2.3.13 response to radiation monitor alarms, 3.8 98 containment entry requirements, fuel handling

3.

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

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

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

4.

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

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

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

Subtotal 3

2 Tier 3 Point Total 10 7

ES-401 Record of Rejected Kl As Form ES-401-4 Tier I Randomly Selected KIA Reason for Rejection Group The following topics I K!As were excluded from the systematic and random sampling process:

295027 High Containment This topic applies to plants with Mark 111 1 I 1 Temperature containments only. The facility has a Mark I containment.

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

207000 Isolation (Emergency)

This system is not installed at the facility.

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

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

212 201005 RCIS This system is not installed at the facility.

212 2.2.3 Knowledge of the design, This KIA applies to multi-unit facilities only.

G procedural, and operational 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.

The followina Kl As were reiected followina the svstematic and random samolina orocess:

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 1 I 1 they apply to GENERA TOR Voltage and Electric Grid Disturbances AA2.09 VOLTAGE AND ELECTRIC

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

following as they apply to GENERA TOR 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 I 1 performed outside the main Randomly re-selected KJA 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 Randomly re-selected KIA 295037 SCRAM 1 I 1 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 Containment Ventilation high radiation.

1 I 2 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 400000 Component Cooling at the SRO level for the randomly selected generic KIA due to lack of EOP entry conditions Water and immediate action steps associated with 2 / 1 2.4.1 - Knowledge of EOP entry Component Cooling Water.

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 212000 RPS the randomly selected KIA without testing minutia or GFE knowledge.

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

2 / 1 operational implications of the 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 I

Question 21 An acceptable question could not be developed 300000 Instrument Air for the randomly selected KIA at the correct 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 202002 Recirculation Flow related to Recirculation Flow Control.

Control Randomly re-selected KIA 202002 K2.02 - Knowledge of electrical Recirculation Flow Control K1.03 - Knowledge 212 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 204000 RWCU for the randomly selected KIA at the appropriate license level due to lack of safety related 212 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.

1 I 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 1 I 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 r<;idiation 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 1 I 2 and/or monitor the following as Containment High Sump/Area Water Level they apply to SECONDARY EA1.O~ - 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.

1 I 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 263000 DC Electrical for the randomly selected KIA without testing Distribution minutia.

2.4.50 - Ability to verify system Randomly re-selected KIA 263000 DC 2 I 1 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 256000 Reactor Condensate discriminating RO level question.

A1.08 - Ability to predict and/or Randomly re-selected KIA 256000 Reactor Condensate A 1.04 - Ability to predict and/or 212 monitor changes in parameters monitor changes in parameters associated with 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 2.1.18 - Ability to make on the operating exam and better suited to that accurate, clear and concise portion of the exam.

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, 1 OCFR55, etc.

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

2.2.22 - Knowledge of limiting Randomly re-selected KIA 295028 High Drywell 1 I 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.

Question 71 Removed based on Chief Examiner discretion.

2.3. 7 - Ability to comply with Randomly re-selected KIA 2.3.14-Knowledge 3

radiation work permit of radiation or contamination hazards that may requirements during normal or arise during normal, abnormal, or emergency abnormal conditions.

conditions or activities.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: James A. Fitz~atrick 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 KIA 2.2.13 (4.1), EN-OP-102 Determine Worker Exposure for Emergent Work Radiation Control P,D,R 14-2 NRC KIA 2.3.4 (3.2), EN-RP-201 Emergency Procedures/Plan 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 Code:s & 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. Fitz[;1atrick 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 Drywall 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 KIA2.1.5(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(:::: 3 for ROs;::; 4 for SROs & RO retakes)

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

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

ES-301 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 P,D,A,S Voltage Match Method 6

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

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 KIA 400000 A4.01 (3.1/3.0), AOP-11 N,EN,S 8

h. (RO Only) Perform Main Turbine Roll N,L,S 3

Kl A 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 AA 1.05 (3.1 /3.4 ), EP-6 14-2 NRC

j. Vent the Scram Air Header D,R,E 8

KIA 400000 2.4.35 (3.8/4.0), 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

9/:::::8/:::::4 (E)mergency or abnormal in-plant 2:1/2:1/2:1 (EN)gineered safety feature 2: 1 I 2: 1 I 2: 1 (control room system)

(L)ow-Power I Shutdown 2:1/2:1/2:1 (N)ew or (M)odified from bank including 1 (A) 2:2/2:2/2:1 (P)revious 2 exams

3 /: :::; 3 /::::; 2 (randomly selected)

(R)CA 2:1/2:1/2:1 (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 2

NM14:B I-ATC, APRM B Fails Upscale SRO OP-16, ARP 09-5-1-4 3

Remote C-SRO HPCI Aux Oil Pump Power Supply Loss HP15 ARP 09-3-3-38, Technical Specifications RD06 C-Control Rod Drive Pump Trip, One Control Rod Drive Accumulator 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 6

RD13 M-All Hydraulic ATWS EOP-3 C-Delayed SLC Pump Trip (first pump only, maybe after 1-2 minutes) 7 SL01

ATC, SRO EOP-3 RR02 I-ATC, Recirculation Flow Controllers Fail As-ls; Recirculation Pumps Fail 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 Events

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

N/A

ATC, SRO OP-26 C-Stuck Control Rod 3

RD10

ATC, SRO OP-25 4

Override C-SRO Core Spray Sparger Leak 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 9

HP02 C-All HPCI Trips 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 6

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 3

Override I-ATC, Recirculation Pump A Speed Drifts Low SRO AOP-8, AOP-32, OP-27, Technical Specifications Remote Seismic Event with Loss of Line 3 4

EP09 C-SRO ED43:A AOP-14, AOP-72, Technical Specifications RR04:A Recirculation Pump A Seal Failure 5

C-All ARP 09-4-2-38, AOP-8, OP-27, AOP-39, Technical Specifications RR05:A Remote Seismic Event with Steam Leak in Drywell 6

EP09 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 9

RD10 C-All Multiple Control Rods Fail to Insert 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

NIA

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 4

Remote I-BOP, LPCI Inverter Trips ED23 SRO ARP 09-8-3-2, Technical Specifications CU07 C-5 CU10

BOP, RWCU Pump Seal Fails; RWCU Automatic Isolation Fails CU12 SRO ARP 09-3-3-2(12), EOP-5, Technical Specifications C-RCIC Inadvertently Initiates 6

RC06

BOP, SRO AOP-77, Technical Specifications RC09 7

RC12 M-All RCIC Steam Leak; RCIC Fails to Isolate 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 Event 7

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.