ML071930241

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Final Outlines (Folder 3)
ML071930241
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 06/22/2007
From: St.Pierre G, Wright K
Florida Power & Light Energy Seabrook
To: Caruso J
NRC Region 1
Sykes, Marvin D.
Shared Package
ML062050109 List:
References
50-443/07-301, ES-401-2 50-443/07-301
Download: ML071930241 (37)
v • d • e


Text

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Seabrook Station 2007 NRC Written Exam Outline ES-401, Rev. 9 PWR Examination Outline Form ES-401-2 Facility:

RO KIA Category Points SRO-Only Points Tier Group K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

  • Total t q Y q - G T
1. 1 2 2 4 3 4 3 18 4 2 6 Emergency &

AbnormaI NIA NIA Plant Evolutions 2 1 1 2 2 2 I 9 2 2 4 TierTotals 3 3 6 5 6 4 27 6 4 IO 1 4 1 4 4 1 2 3 2 3 2 2 28 2 3 5 2.

Plant Systems 2 2 1 1 1 1 1 1 1 0 0 1 10 1 2 3 TierTotals 6 2 5 5 2 3 4 3 3 2 3 38 3 5 8

3. Generic Knowledge and Abilities Categories 4

1 2 2

3 2

4 2

lo CCCM 1

ES-401, Rev. 9 Form ES-401-2 Seabrook Station 2007 NRC Exam Tier ?/Group1 RO ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions -Tier IIGtOup 1(RO ISRO)

UAPE #I Name ISafety Function H IR #

3 2.1.20 Ability to execute procedure steps.

000007 (BWlE0281E10; CUE02) 4.3 I Reactor Trip Stabilization Recovery I1 (CFR: 41.10 I43.5 / 45.12) 000008 Pressurizer Vapor Space 4.1 responses as they apply to the Pressurizer Vapor Accident I3 000009 Small Break LOCA I 3 EA2.15 Ability to determine or interpret the following 3.3 as they apply to a small break LOCA.

RCS parameters 00001ILarge Break LOCA I3 2.6 000015117 RCP Malfunctions I 4 3.5 I RCP Seal Water Injection Subsystem I I I (CFR 41.7/45.5/45.6) 000022 Loss of Rx Coolant Makeup I 2 3.5 Actions contained in SOPSand EOPs for RCPs, loss of makeup, loss of charging, and abnormal

, charging.

oooO25 Loss of RHR System I 4 , (CFR 41.5/41.10/45.6/45.13) 2.4.11, Knowledge of abnormal condition procedures.

(CFR: 41.10 I43.5 I45.13) 3.4 000026 Loss of Component Cooling Water I 8 000027 Pressurizer Pressure Control 2.8 I System Malfunction I 3 ressure Control Malfunctions:

Expansion of liquids as temperature increases.

000029 ATWS I1 3.4 1 as they apply to a ATWS:

Charging Pumps.

(CFR 41.7/45.5/45.6) 000038 Steam Gen. Tube Rupture I3 000040 (BWIEOS; CEEOS; WIE12)  !.6 1 Steam Line Rupture Excessive Heat I I I I Sensors and detectors (CFR 41.7/45.7)

Transfer I 4 000054 (CUE06) Loss of Main Feedwater I 4 000055 Station Blackout I 6 4.3 I I I I onsitepower 1

r (CFR 41.5/41.10/45.6/45.13)

Seabrook Static 1.2 1 c -

000057 Loss of Vital AC lnst. Bus I 6 1.8 1 following as the apply to Loss Of Vital AC Instrument I

c 000058 Loss of DC Power I 6 1.4 1 000062 Loss of Nuclear Svc Water I 4 1.6 1 responses as they apply to the Loss Of Nuclear Service The automatic actions (alignments) within the nuclear service water resulting from the actuation of 000065 Loss of InstrumentAir I 8 1.4 1 When to commence plant shutdown if instrument WIE04 LOCA Outside ContainmentI 3 1.5 1 Outside Containment:

ssociated with the LOCA WIEl 1 Loss of EmergencyCoolant 1.4 1 Recirc. I 4 operating within the limits of the facilities licensdamendments.

BWIEW, WIE05 Inadequate Heat Transfer Loss of Secondary Heat Sink I 4 KIA Category Totals: 3 4 3 GroupPointTotal: 18/6 2

ES-401, Rev. 9 Form ES-401-2 Seabrook Station 2007 NRC Exam Tier IIGroupl SRO E M 1 PWR Examination Outline F O I ~ES401-2 Emergency and Abnormal Plant Evolutions -Tier IlGroup 1(RO ISRO)

EIAPE # I Name ISafety Function #

000007 (BWIEOP&ElO; CEIEO2) I Reactor Trip Stabilization Recovery I1 000008 Pressurizer Vapor Space Accident I 3 000009 Small Break LOCA I 3 000011 Large Break LOCA I3 1 000015117 RCP Malfunctions I 4 instrument interpretation.

(CFR. 43.5 I45.12 / 45.13) 000022 Loss of Rx Coolant Makeup I 2 000025 Loss of RHR System I 4 000026 Loss of Component Cooling Water I8 000027 Pressurizer Pressure Control I System Malfunction I 3 ns for emergency and 000029 ATWS I1 000038 Steam Gen. Tube Rupture I 3 I 000040 (BWIE05; CEIEOB; WIEl2)

Steam Une Rupture Excessive Heat Transfer I 4 000054 (CEIE06) Loss of Main Feedwater I 4 000055 Station Blackout I6 000056 Loss of Off-site Power I6 000057 Loss of Vital AC l n s t Bus I6 000058 Loss of DC Power I6 1

KIA Category Totals: I I I I I I Group 4 2 PointTotal: 18/6 2

ES-401, Rev. 9 Form ES-401-2 Seabrook Station 2007 NRC Exam Tier 1IGroup 2 RO ES-401 PWR Examination Outline Form E-1-2 Ememencv and Abnormal Plant Evolutions Tier 1IGrouD. 2 [RO

. ISROI ElAPE # I Name ISafety Function 000001 Continuous Rod Withdrawal I 1 000003 Dropped Control Rod I1 Dropped Control Rod:

Actions contained in the EOP for dropped 000005 InoperablelStuck Control Rod II 000024 Emergency BorationI1 000028 Pressurizer Level Malfunction I 2 Charging subsystem flow indicator and 000032 Loss of Source Range NI I7 000033 Loss of Intermediate Range NI I7 000036 fBWIAO81 Fuel Handlina Accident I 8 000037 Steam Generator Tube Leak I3 000051 Loss of Condenser Vacuum I 4 000059 Accidental Liquid RadWaste Rel. I 9 000060 Accidental Gaseous Radwaste Rei. I 9 000061 ARM System Alarms I 7

~~

000067 Plant Fire On-site I 8 000068 (BWIAO8) Control Room Evac. I 8 000069 (WIE14) Loss of CTMT Integrity I5

~

000074 (WIE06&E07) Inad. Core Cooling I 4 000076 High Reactor Coolant Activity I 9 WIEOI & E02 Rediagnosis & SI TerminationI3 WIEI 3 Steam Generator Over-pressureI 4 WIE15 Containment Flooding I 5 1

Seabrook Station 2007 NRC Exam Tier 1IGroup 2 RO (Continued) - -

WlEl6 High Containment Radiation I 9 3.1 1 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and utomatic and manual features.

BWIAOI Plant Runback I1 BWIAO2&AO3 LOSS Of NNI-X/Y I 7 BWlAW Turbine Trip I 4 BWIAOS Emergency Diesel Actuation I 6

~________

BWIAO?Flooding I 8 BWIE03 Inadequate Subcooling Margin I 4 BWIEOI; WIEO3 LOCA Cooldown Depress. I 4 3.4 Cooldown and Depressurization:

Normal, abnormal, and emergency operating procedures associated wth LOCA Cooldown and Depressunzation.

(CFR 41.5/41.10/45.6/45.13)

BWIEOB; CEIA13; WIE09&E10 Natural Circ. I 4 3.3 implications of the following concepts as they apply to the Natural Circulation Cooldown:

Normal, abnormal, and emergency BWIE13&E14 EOP Rules and Enclosures CEIAII; WIE08 RCS Overcooling PTS I 4 between the Pressurized Thermal Shock and 3.4 I Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and utomati and manual features.

CEIAI 6 Excess RCS Leakage I2 CEIE09 Functional Recovery KIA Category Point Totals: I G~OUD Point Total:

2

ES-401, Rev. 9 Form ES-401-2 Seabrook Station 2007 NRC Exam Tier IIGroup 2 SRO ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions -Tier IIGroup 2 (RO ISRO)

ElAPE # IName ISafety Function K H 1 2 000001 Continuous Rod Withdrawal II 000003 Dropped Control Rod II I I 000005 InoperablelStuck Control Rod I1 000024 Emergency BorationI1 000028 Pressurizer Level Malfunction I 2 000032 Loss of Source Range NI I7 000033 Loss of Intermediate Range NI I7 I I 000036 (BWIAOS) Fuel Handling Accident I 8 I I 000037 Steam Generator Tube Leak I 3 000051 Loss of Condenser Vacuum I 4 000059 Accidental Liquid RadWaste Rel. I 9 000060 Accidental Gaseous Radwaste Rel. I 9 000061 ARM System Alarms I7 000067 Plant Fire On-site I 8 I I 000068 (BWlAO6) Control Room Evac. I 8 I I 000069 (WIEl4) Loss of CTMT Integrity I5 000074 (WIEO6&EO7) Inad. Core Cooling I 4 000076 High Reactor Coolant Activity I 9 I I WIEOI & E02 Rediagnosis & SI TerminationI 3 WlEl3 Steam Generator Over-pressure I4 WIEl5 Containment Flooding I 5 WIEl6 High Containment Radiation I 9 BWlAOl Plant Runback I1 BWlAO2&AO3LOSSof NNI-XN I7 BWIAO4 Turbine Trip I 4 BWIAO5 Emergency Diesel Actuation I 6 BWIAO7 Flooding I 8 I I BWIE03 Inadequate Subcooling Margin I 4 BWIEOI; WIE03 LOCA Cooldown Depress. I 4 BWIEOQ; CElAI3; WIEOQ&E10Natural Circ. I 4 BWlEl3&E14 EOP Rules and Enclosures 1

I Seabrook Station 2007 NRC Exam Tier IIGrouD 2 SRO (Continued) I I CUE09 Functional Recoverv I I 1 1 1 1 1 I I I KIA Category Point Totals: I I I I : I : I G~OUPPoint~otel: I 9/4 2

ES-401, Rev. 9 Form ES-401-2 Seabrook Station 2007 NRC Exam Tier 2IGroup I RO ES-401 PWR ExaminationOutline F O I ES-401-2

~

Plant S! terns -Tier WGroup I (RO I SRO)

System# I Name KIA Topic(s) 4 003 Reactor Coolant Pump 1 ips between the RCPS and 004 Chemical and Volume 1 Control 005 Residual Heat Removal I have on the following:

006 Emergency Core Cooling 1 Normal water supply for SiS 007 Pressurizer ReliefIQuench 1 Tank 008 ComponentCooling Water I 010 Pressurizer Pressure I Control 012 Reactor Protection I relationships between the RPS and the following systems:

CFR 41.2 to 41.9145.7 to 45.8 013 EngineeredSafety 1 Features Actuation Input channels and logic.

022 Containment Cooling 1 1

025 Ice Condenser I I G 2.4.2, Knowledge of system set 026 Containment Spray 5.9 1 Doints. interlocks and automatic

- 7 039 Main and Reheat Steam 2.8 1 059 Main Feedwater 2.9 1 operation of the MFW, including:

Programmed levels of the SIG.

061 AuxiliatylEmergency 3.4 1 of the following malfunctions or Feedwater operations on the AFW, and based on those predictions, use procedures to correct, control, or mitigate the 062 AC Electrical Distribution 3.4 monitor changes in parameters associated with operating the ac 063 DC Electrical Distribution 3.5 nents using DC control 064 Emergency Diesel 3.9 Generator 073 Process Radiation 3.6 Monitoring relationships between the PRM system and the following systems:

Those systems served by PRM's.

076 Service Water 3.6 I I ESF 078 Instrument Air 3.1 Air Pressure 103 containment 3.9 1 automatic operation of the 2

Seabrook Station 2007 NRC Exam Tier 2IGroup 1 RO (Continued) 003 Reactor Coolant Pump 1 Containment isolation valves affecting RCP operation.

41.7145.5 004 Chemical and Volume 1 Control following concepts as they apply to 005 Residual Heat Removal 1 010 Pressurizer Pressure 1 Control RCS heatup and cooldown effect 012 Reactor Protection 1 or operations on the RPS, and based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions Faulty or erratic operation of detectors and function generators.

41.5i43.5i45.3145.5 059 Main Feedwater 061 AuxlllaryIEmergency Feedwater which provide for the following:

KIA Category Point Totals:

3

ES-401, Rev. 9 Form ES-401-2 Seabrook Station 2007 NRC Exam Tier 2IGroup 1 SRO ES-401 PWR Examination Outline Form ES-401-2 Plant S items Tier 2/Group I(RO ISRO)

System # I Name 003ReactorCoolantPump II I: I :II !

I 005 Residual Heat Removal 006 Emergency Core Cooling

-1 007 Pressurizer RelIeflQuench Tank 008 Component Cooling Water 010 Pressurizer Pressure Control 012 Reador Protection 013 Engineered Safety Features Actuation 022 Containment Cooling 025 Ice Condenser 039 Main and Reheat Steam 059 Main Feedwater 7 061 AuxilierylEmergency Feedwater 062 AC Electrical Distribution 064 Emergency Diesel Generator 073 Process Radiation Monitoring

Seabrook Station 2007 NRC Exam Tier 2IGroup 1 SRO (Continued) 2

ES-401, Rev. 9 Form ES-401-2 Seabrook Station 2007 NRC Exam Tier 21Group 2 RO ES-401 PWR Examination Outline Form ES-401-2 Plant Systems -Tier 2lGroup 2 (RO ISRO)

System # I Name 001 Control Rod Drive I 002 Reador Coolant I 011 Pressurizer Level Control 1 014 Rod Position Indication 015 Nuclear Instrumentation 1 016 Nonnuclear Instrumentation 017 ln-core Temperature I Monitor 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 029 Containment Purge 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment 035 Steam Generator 041 Steam Dump/Turbine I Bypass Control 045 Main Turbine Generator I 1

2 ES-401, Rev. 9 Form ES401-2 Seabrook Station 2007 NRC Exam Tier 2IGroup 2 SRO ES401 PWR Examination Outline F o ES401-2

~

Plant Systems -Tier WGroup 2 (RO ISRO)

System # I Name 001 Control Rod Drive K K H H M 1 2 3 4 5

-- 4 WA Topic(s)

I IR 002 Reador Coolant 1 011 Pressurizer Level Control 014 Rod Position Indication 015 Nuclear Instrumentation 016 Non-nuclear Instrumentation 017 ln-core Temperature Monitor 027 Containment Iodine IIIIl 028 Hydrogen Recombiner A2.03, Ability to predict the impacts of the following malfunctions or operations on the 1 Spent Fuel Pool Cooling System and based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Abnormal spent fuel pool water level or loss of water level.

and based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Dropped fuel element.

035 Steam Generator 041 Steam Dumpfrurbine Bypass Control 045 Main Turbine Generator 055 Condenser Air Removal I I I 056 Condensate 068 Liquid Radwaste I (CFR 43.4 I45.10) 071 Waste Gas Disposal I I I I I 1

2 ES-401, Rev. 9 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Seabrook Station 2007 NRC Exam Tier 3 RO Facility: Date of Exam:

Category KIA # Topic RO I -

SRO-Only IR #

2.1 .I G 2.1.1 Knowledge of conduct of operations requirements. 3.7 (CFR: 41.10 145.13) 1.

Conduct of Operations 2.1 .I 1 G 2.1.11 Knowledge of less than one hour technical 3.0 specification action statements for systems.

( C F R 43.2 I45.13) 2.1.28 2.1.28 Knowledge of the purpose and function of major 3.2 system components and controls.

(CFR: 41.7) 2.1.33 2.1.33 Ability to recognize indications for system operating 3.4 parameters which are entry-level conditions for technical specifications.

( C F R 43.2 143.3 I 45.3) 2.1.

2.1.

Subtotal

2. 2.2.1 3 2.2.13 Knowledge of tagging and clearance procedures. 3.6 Equipment (CFR:4 1.10 / 45.13)

Control 2.2.22 2.2.22 Knowledge of limiting conditions for operations and 3.4 safety limits.

(CFR: 43.2 / 45.2) 2.2.

2.2.

2.2.

2.2.

Subtotal 1

Seabrook Station 2007 NRC Exam Tier 3 RO (Continued) 2.3.1 2.3.1 Knowledge of 10 CFR: 20 and related facility 2.6 1

3. radiation control Radiation requirements.

Control (CFR. 41.12 143.4.45.9 145.10) 2.3.4 2.3.4 Knowledge of radiation exposure limits and 2.5 1 contamination control, including permissible levels in excess of those authorized.

(CFR. 43.4 / 45.10) 2.3.

2.3.

2.3.

2.3.

Subtotal

4. 2-4-27 2.4.27 Knowledge of fire in the plant procedure.

Emergency (CFR 41.10 I43.5 / 45.13)

ProceduresI Plan 2.4.49 2.4.49 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

(CFR: 41.10 / 43.2 145.6) 2.4.

2.4.

2.4.

2.4.

Subtotal Tier 3 Point Total 2

ES401, Rev. 9 Generic Knowledge and Abilities Outline (Tier 3) Form ES401-3 Seabrook Station 2007 NRC Exam Tier 3 SRO FaciIity: Date of Exam:

Category KIA # Topic RO I SRO-Only IR # IR #

1. 2.1.4 2.1.4 Knowledge of shift staffing requirements. 1 Conduct (CFR: 41.10 / 43.2) of Operations 2.1 .lo 2.1.10 Knowledge of conditions and limitations in the I facility license.

(CFR: 43.1 I45.13) 2.1.

2.1.

2.1.

2.1.

Subtotal

2. 2.2.21 2.2.21 Knowledge of pre- and post-maintenanceoperability Equipment requirements.

Control (CFR: 43.2) limiting conditions for operations and safety limits.

C F R 43.2 2.2.

2.2.

2.2.

Subtotal 2 2.3.4 2.3.4 Knowledge of radiation exposure limits and 1

3. contamination control, including permissible levels in excess Radiation of those authorized.

Control (CFR: 43.4 / 45.10) 2.3.

2.3.

2.3.

2.3.

2.3.

Subtotal I 1

Seabrook Station 2007 NRC Exam Tier 3 SRO (Continued)

4. 2.4.21 2.4.21 Knowledge of the parameters and logic used to assess Emergency the status of safety Procedures I functions including:

Plan 1. Reactivity control

2. Core cooling and heat removal
3. Reactor coolant system integrity
4. Containment conditions
5. Radioactivity release control.

(CFR. 43.5 / 45.12) 2.4.38 2.4.38 Ability to take actions called for in the facility emergency plan, including (if required) supporting or acting as emergency coordinator.

(CFR: 43.5 I45.11) 2.4.

2.4.

2.4.

2.4.

Subtotal 2 Tier 3 Point Total 7 2

ES-401, Rev. 9 Record of Rejected KIAs Form ES-401-4 Tier I Randomly Reasonfor Rejection Group Selected KIA 1I1 008 AKI . O l Original proposed exam question was reviewed by Lead NRC Examiner and deemed to be fundamentals based.

The examiner recommendedrandomly selecting a different KIA from the same category (008). A new ramdomly selected KIA, 008 AK3.03 has been selected, and an associated new exam question has been submitted.

1I1 E l l EA2.1 Original proposed exam question was reviewed by Lead NRC Examiner and deemed to be too similar to SIMJPMO9. The examiner recommendedrandomly selecting a different KIA from the same category (El I).

A new ramdomly selected KIA, E l l EA2.2 has been selected and an associated new exam question has

~~

been submitted.

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2/1 003 K I .02 Original proposed question was reviewed by Lead NRC Examiner and deemed to be a KIA mismatch. Multiple attempts to replace the question under the same KIA resulted in unwanted duplication of material within the written exam. A new randomly selected KIA, K1.04 from the same category (003, RCPS) and K number (KI) has been selected and an associated new exam question has been submitted.

2/1 012, Reactor Original proposed KA was discussed with NRC Lead Protection Examiner per teleconference. The Examiner suggested that the KA would be difficult to apply to an SRO level 2.1.27 question. A new randomly selected KA, 061, Auxiliary Knowledge of Feedwater, 2.1.20 Ability to execute procedure steps.

system purpose (CFR: 41.I 0 I43.5 I45.1 2) and or function.

~~

2/2 033, A2.03 Original question associated with 033, A2.03 deemed to simple by Lead NRC Examiner. Due to difficulty creating an appropriate SRO level question for the KA new KA 034, A2.01 was randomly sampled. A new question has been submitted.

ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1 Seabrook Station 2007 NRC Exam Admin Topics-SRO Facility: Seabrook Date of Examination: July 9,2007 Examination Level: RO [1 SRO B Operating Test Number:

Administrative Topic (see Note) Type Code* Describe activity to be performed 2.1.6 Ability to supervise and assume a management role during plant transients and upset conditions.

Conduct of Operations Activity- Reporting Requirements For Onsite Event

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2.1 . I 2 Ability to apply technical specifications for a system.

Conduct of Operations Activity- Technical Specifications and Allowed Outage Time.

2.2.12 Knowledge of surveillance procedures.

Activity-Verify RCS Steady State Leak Rate Determination.

Equipment Control

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2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.

Radiation Control Activity-VeMy a Liquid EffluentWaste Sample Request 2.4.40 Knowledge of the SROs responsibilitiesin emergency pian S or R,N implementation.

Emergency Plan Activity-Emergency Pian Classification and NotMcation 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 ( for ROs; < 4 for SROs & RO retakes) 3I (N)ew or (M)odified from bank (2 1)

(P)revious 2 exams (< I; randomly selected)

ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1 Seabrook Station 2007 NRC Exam Admin Topics-RO Facility: Seabrook Date of Examination: July 9,2007 ExaminationLevel: RO SRO 0 Operating Test Number:

_ _ ~ ~

Administrative Topic (see Note) Type Code* Describe activity to be performed 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

Conduct of Operations Activity- Perform RCS Steady State Leakrate Calculations.

~~

2.1.25 Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data.

Conduct of Operations Activity- Calculate Shutdown Margin in Mode 2 With Dropped Rod.

2.2.1 Ability to perform pre-startup procedures for the facility, Including operating those controls associated with plant equipment that could affect reactivity.

Equipment Control Activity- Spent Fuel Pool Blended Makeup Calculation.

2.3.10 Ability to perform procedures to reduce excessive levels of radlation and guard against personnel exposure.

Radiation Control Activity- Verify COP Exhaust RY Setpoints Prior to Gaseous Effluent Release.

Emergency 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 Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (< 3 for ROs; 5 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (2 1)

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

ES-301, Rev. 9 Control Roomlln-Plant Systems Outline Form ES-301-2 Seabrook Station 2007 NRC Exam JPM-SROI Facility: Seabrook Date of Examination: July 9, 2007 ExamLevel: RO 0 SRO-I SRO-U 0 Operating Test No.:

System I JPM Title Type Code* Safety Function

a. Steam Generator SystemlSteam Header Pressure PT-507 Fails 4 Low
b. Emergency Diesel GeneratorslEmergency Trip of DG 1B
c. Nuclear Instrumentation SystemlPower Range NI Failure
d. Containment Purge SystemlPlacing COP in Service
e. Reactor Coolant SystemlDepressurize RCS Using Aux Spray 2 (E-3)
f. Containment Spray System/ Transfer To Cold Leg Recirc (CBS-V-2 Fails)
g. Emergency Core Cooling SystemlPerform SI Termination/

I 4%E, M I 5 3

Reduction h.

i. AC Electrical DistributionKransfer Vital Instrument Bus L,D 6
j. Component Cooling Water SystemlAlign Alternate Cooling To D,E,R 8 CCP Lube Oil Cooler
k. Chemical and Volume Control SystemlLocal Rapid Manual Boration I 1 1
  • Type Codes Criteria for RO ISRO-I I SRO-U

~~ ~

(A)lternate path 4-6 14-6 I 2-3 (C)ontrol room (D)irect from bank s91s81s4 (E)mergency or abnormal in-plant 2 1 121 I 2 1 (L)ow-Power I Shutdown 2 1 / 2 1I 2 1 (N)ew or (M)odified from bank including 1(A) 22122121 (P)revious 2 exams s 3 I s 3 I s 2 (randomly selected)

( W A 2 1 I 2 1 121 (S)imulator 2

ES-301,Rev. 9 Control Roomlln-Plant Systems Outline Form ES-301-2 Seabrook Station 2007 NRC Exam JPM-SROU Facility: Seabrook Date of Examination: JUIY 9,2007 Exam Level: RO 0 SRO-I 0 SRO-U OperatingTest No.:

System I JPM Title Type Code* Safety Function

a. Containment Spray System/ Transfer To Cold Leg Recirc A,S,E,N 5 (CBS-V-2 Fails)
b. Emergency Diesel GeneratorsEmergency Trip of DG 1B 6 C.

(3)

Reactor Coolant SystemlDepressurize RCS Using Aux Spray I I 2 e.

1.

9.

h.

In-Plant Systems@(3 for RO); (3 for SRO-I);(3 or 2 for SRO-U)

i. AC Electrical Distributionflransfer Vital Instrument Bus 6 L,D
j. Component Cooling Water SystemlAlign Alternate Cooling To W,R a CCP Lube Oil Cooler k.

__ ~

@ All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO ISRO-I ISRO-U (A)lternate path 4-6 I 4 6 12-3 (C)ontrol room (D)irect from bank s91sa1s4 (E)mergency or abnormal in-plant 2 1 I 2 1 />I (L)ow-Power I Shutdown 21121/21 (N)ew or (M)odified from bank including 1(A) 22/22/21 (P)revious 2 exams 5 3 I s 3 I< 2 (randomly selected)

(RFA 21121121 (S)imulator 2

\

ES-301, Rev. 9 Control Roomlln-Plant Systems Outline Form ES-301-2 Seabrook Station 2007 NRC Exam JPM-RO Facility: Seabrook Date of Examination: July 9, 2007 ExamLevel: RO SRO-I 0 SRO-U 0 OperatingTest No.:

System I JPM Title Type Code* Safety Function

~~ ~____

a. Steam Generator SystemlSteam Header Pressure PT-507 Fails I E,N
b. Emergency Diesel GeneratorslEmergency Trip of DG 1B S,A,D 6 C. Nuclear Instrumentation SystemlPower Range NI Failure W,E 7
d. Containment Purge SystemlPlacing COP in Service S,N 8
e. Reactor Coolant f.

SystemlDepressurize RCS Using Aux Spray Containment Spray System/ Transfer To Cold Leg Recirc (Loss II A,S,E,N II 2 5

of Recirculation

g. Emergency Core Cooling SystemlPerform SI Termination/ 3 Reduction 1 h.

PDP Chemical and Volume Control SystemlShifting From CCP to I S9D I 1 I In-Plant Systems" (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

I i. AC Electrical Distributionrrransfer Vital Instrument Bus I L,D I 6

j. Component Cooling Water SystemlAlign Alternate Cooling To 8 CCP Lube Oil Cooler
k. Chemical and Volume Control SystemlLocal Rapid Manual 1 Boration

@ All control room (and in-plant) systems must be different and 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 I SRO-U 1

(A)lternate path 4-6 14-6 I 2-3 (C)ontrol room (D)irect from bank <9/<8/<4 (E)mergency or abnormal in-plant 21/21/21 (L)ow-Power I Shutdown 2 1I 2 1I 2 1 (N)ew or (M)odified from bank including 1(A) 22/22/21 (P)revious 2 exams s 3 I < 3 15 2 (randomly selected)

(WA 21/21/21 (S)imulator 2

Appendix D, Rev. 9 Scenario Outline Form ES-D-1 1 Facility: Seabrook Station Scenario No.: 4 (D) Op-Test No.:

Examiners: Operators:

I/ Initial Conditions: Plant is at 30% power. Power decrease due to D Atmospheric Steam Dump leaking.

1 Turnover: Plant

!d.

at 30% power. Continue power decrease at 5Yhr. The D ASDV is leaking Malf. Event Event No. Type* Description N-ATC Power Decrease N-BOP N-SRO R-SRO R-ATC R-BOP PWPT I-BOP Tavgnref mismatch failure.

505 I-SRO I-ATC R-ATC R-SRO MfRCOl C-SRO D RCP seal failure.

6 C-ATC C-BOP MfSGOO C-SRO SG Tube Rupture @ 300 gpm.

2D C-ATC C-BOP M-SRO M-ATC M-BOP rvMSAV M-SRO D SG Safety Valve leaks past seat.

R50 M-ATC R-SRO R-ATC R-BOP

Appendix D, Rev. 9 Scenario Outline Form ES-D-I Facility: Seabrook Station Scenario No.: 2 (6) OpTest No.:

Examiners: Operators:

Initial Conditions: Middle of Life. 75% power after downpower at 20%lhr.

Turnover: Continue power increase Q 1OYdhr. SUFP is aligned to Bus 4 for breaker testing of Bus 5 SUFP breaker.

Event Malf. Event Event No. Type* DescriDtion I R-SRO Power Increase, Reactivity Change N-ATC N-BOP R-ATC R-BOP 2 CfRCLT I-SRO Controlling channel of PZR level fails low.

459 I-ATC C-ATC 3 MfCSOl C-SRO Charging pump 2A overcurrent trip.

6 C-ATC

~~

4 FWP32 C-SRO 'B' Main Feed Pump shaft shear.

B C-BOP 5 MFRPS M-SRO Failure of reactor to trip.

001 M-ATC R-SRO R-ATC R-BOP 6 RfMSVl C-BOP Turbine Driven Emergency Feedwater Pump trip.

29 C-SRO 7 MfEDO3 M-SRO Loss of Offsite Power FR-H.1.

8 M-ATC M-BOP

I* (N)orrnal, (R)eactivity, (I)nstrurnent, (C)ornponent, Atmendix D. Rev. 9 Scenario Outline Form ES-D-I l Facility: Seabrook Station Scenario No.: 1 (A)

Examiners: Operators:

Op-Test No.:

Initial Conditions: Plant is at 75% power. Middle of Life. Xenon is building in after a 20% per hour power decrease. Boron concentration is 1171 ppm.

Turnover: Raise power to 100% Q 1O%/hr.

Event Malf. Event Event No. Type* Description 1 R-SRO Power Increase, Reactivity Change N-SRO R-ATC R-BOP N-ATC N-RnD 2 CtFWFK I-BOP C Fw Reg Valve Fails to 100% output and controlling 530 C-BOP channel of SG level fails low.

C-SRO LWLT I-SRO 553 3 PtRCPT I-ATC Controlling PZR pressure instrument fails high.

455 I-SRO C-ATC C-SRO 4 MfRC04 C-SRO RCS Leak at 30 GPM to containment.

8C C-ATC N-SRO Shutdown portion of RCS leak abnormal 6

R-SRO I

R-BOP I,,

R-ATC 5 MFR005 R-SRO Pressurizer manway failure.

2 R-ATC

M-SRO M-ATC M-BOP

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