ML15103A567

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Draft Outlines (Folder 2)
ML15103A567
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 12/22/2014
From: David Silk
Operations Branch I
To: Bryant R
NextEra Energy Seabrook
Shared Package
ML14254A318 List:
References
TAC U01915
Download: ML15103A567 (36)
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ES-401 PWR Examination Outline Form ES-401-2 Facility: SEABROOK Date of Exam: MARCH 2015 RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

  • Total
1. 1 3 3 2 4 2 4 18 6 Emergency &

Abnormal 2 2 2 2 N/A 0 1 N/A 2 9 4 Plant Evolutions Tier Totals 5 5 4 4 3 6 27 10 1 3 2 4 3 1 4 1 3 4 2 1 28 5 2.

Plant 2 2 0 1 2 1 0 2 1 0 0 1 10 I 3 Systems Tier Totals 5 2 5 5 2 4 3 4 4 2 2 38 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 2 2 3 I I I I I I 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).
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 and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section 0.1.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 0.1.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 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.

ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emeroencv and Abnormal Plant Evolutions - Tier 1/Group 1 (RO I SRO)

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

1 2 3 1 2 007 Reactor Trip 000007 (BW/E02&E10; CE/E02) Reactor x 3.6 QI Trip - Stabilization - Recovery / 1 EK1 Knowledge of the operational implications of the following concepts as they apply to the reactor trip:

EK1 .04 Decrease in reactor power following reactor trip (prompt drop and subsequent decay) 000008 Pressurizer Vapor Space x 008 Pressurizer (PZR) Vapor Space Accident 4.1 Q2 Accident/ 3 (Relief Valve Stuck Open)

AA1. Ability to operate and I or monitor the following as they apply to the Pressurizer Vapor Space Accident:

AA1.02 HPI pump to control PZR level/pressure 000009 Small Break LOCA I 3 x 009 Small Break LOCA 4.1 Q3 EK3 Knowledge of the reasons for the following responses as the apply to the small break LOCA:

EK3.03 Reactor trip and safety initiation 000011 Large Break LOCA / 3 x 011 Large Break LOCA 4.1 Q4 EK1 Knowledge of the operational implications of the following concepts as they apply to the Large Break LOCA:

EK1.01 Natural circulation and cooling, including reflux boilino 000015/17 RCP Malfunctions I 4 x 015/017 Reactor Coolant Pump (RCP) Malfunctions 2.9 QS AK2. Knowledge of the interrelations between the Reactor Coolant Pump Malfunctions (Loss of RC Flow) and the following:

AK2.07 RCP seals 000022 Loss of Rx Coolant Makeup I 2 x 022 Loss of Reactor Coolant Makeup 2.9 Q6 AA2. Ability to determine and interpret the following as they apply to the Loss of Reactor Coolant Makeup:

AA2.04 How long PZR level can be maintained within limits 000025 Loss of RHR System I 4 x 025 Loss of Residual Heat Removal System 2.9* Q7 (RHRS)

AA 1. Ability to operate and I or monitor the following as they apply to the Loss of Residual Heat Removal System:

AA1 .08 RHR cooler inlet and outlet temperature indicators

000026 Loss of Component Cooling x 026 Loss of Component Cooling Water (CCW) 2.9 Q8 Water/ 8 AA1. Ability to operate and I or monitor the following as they apply to the Loss of Component Cooling Water:

AA 1. 07 Flow rates to the components and systems that are serviced by the CCWS; interactions among the components 000027 Pressurizer Pressure Control x 027 Pressurizer Pressure Control System (PZR 2.6 Q9 System Malfunction I 3 PCS) Malfunction AK2. Knowledge of the interrelations between the Pressurizer Pressure Control Malfunctions and the following:

AK2.03 Controllers and positioners 000029 A TWS I 1 x 029 Anticipated Transient Without Scram (ATWS) 2.9* QIO EK2 Knowledge of the interrelations between the and the following an ATWS:

EK2.06 Breakers, relays, and disconnects 000038 Steam Gen. Tube Rupture I 3 x 038 Steam Generator Tube Rupture (SGTR) 4.0 Qll EA1 Ability to operate and monitor the following as they apply to a SGTR:

EA1.40 Adding boron, to raise its ppm to the reauired shutdown concentration 000040 (BW/E05; CE/E05; W/E12)

Steam Line Rupture - Excessive Heat Transfer 14 000054 (CE/E06) Loss of Main x 054 Loss of Main Feedwater (MFW) 4.1 Ql2 Feedwater I 4 AK3. Knowledge of the reasons for the following responses as they apply to the Loss of Main Feedwater (MFW):

AK3.01 Reactor and/or turbine trip, manual and automatic 000055 Station Blackout I 6 000056 Loss of Off-site Power I 6 x 056 Loss of Offsite Power 3.7 Q13 AK1. Knowledge of the operational implications of the following concepts as they apply to Loss of Offsite Power:

AK1 .01 Principle of cooling by natural convection 000057 Loss of Vital AC Inst. Bus/ 6 x 057 Loss of Vital AC Electrical Instrument Bus 3.0 Ql4 AA2. Ability to detemline and interpret the following as they apply to the Loss of Vital AC Instrument Bus:

AA2.16 Normal and abnormal PZR level for various modes of plant operation 000058 Loss of DC Power I 6 000062 Loss of Nuclear Svc Water I 4 x 062 Loss of Nuclear Service Water 3.7 Ql5 2.2.12 Knowledge of surveillance procedures.

000065 Loss of Instrument Air I 8 x 065 Loss of Instrument Air 4.1 Ql6 2.4.45 Ability to prioritize and interpret the siQnificance of each annunciator or alarm.

W/E04 LOCA Outside Containment I 3 W/E11 Loss of Emergency Coolant x W/E11 Loss of Emergency Coolant Recirculation 3.7 Ql7 Recirc. / 4 2.4.3 Ability to identify post-accident instrumentation.

BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink I 4 000077 Generator Voltage and Electric x 077 Generator Voltage and Electric Grid 4.5 Ql8 Grid Disturbances I 6 Disturbances 2.4.4 Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

KJA CateQorv Totals: 3 3 2 4 2 4 Group Point Total: 18/6

ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emeroencv and Abnormal Plant Evolutions - Tier 1/Group 2 (RO I SRO)

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

1 2 3 1 2 000001 Continuous Rod Withdrawal I 1 000003 Dropped Control Rod I 1 000005 Inoperable/Stuck Control Rod / 1 000024 Emergency Boration I 1 000028 Pressurizer Level Malfunction I 2 x 028 Pressurizer (PZR) Level Control 2.6 Q19 Malfunction AK2. Knowledge of the interrelations between the Pressurizer Level Control Malfunctions and the following:

AK2.02 Sensors and detectors 000032 Loss of Source Range NI/ 7 000033 Loss of Intermediate Range NI/ 7 000036 (BW/A08) Fuel Handling Accident I 8 000037 Steam Generator Tube Leak I 3 ff 037 Steam Generator (S/G) Tube Leak AA2. Ability to determine and interpret the 3.2 Q20 following as they apply to the Steam Generator Tube Leak:

AA2.10 Tech-Spec limits for RCS leakage 000051 Loss of Condenser Vacuum I 4 x 051 Loss of Condenser Vacuum 2.8* Q21 AK3. Knowledge of the reasons for the following responses as they apply to the Loss of Condenser Vacuum:

AK3.01 Loss of steam dump capability upon loss of condenser vacuum 000059 Accidental Liquid RadWaste Rel. I 9 000060 Accidental Gaseous Radwaste Rel. I 9 x 060 Accidental Gaseous Radwaste Release 3.8 Q22 AK3. Knowledge of the reasons for the following responses as they apply to the Accidental Gaseous Radwaste:

AK3.03 Actions contained in EOP for accidental oaseous-waste release 000061 ARM System Alarms/ 7 x 061 Area Radiation Monitoring (ARM) 2.5* Q23 System Alarms AK2. Knowledge of the interrelations between the Area Radiation Monitoring (ARM) System Alarms and the following:

AK2.01 Detectors at each ARM system location 000067 Plant Fire On-site I 8 x 067 Plant fire on site 3.8 Q24 2.4.35 Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects.

000068 (BW/A06) Control Room Evac. I 8 000069 (W/E14) Loss of CTMT lnteoritv I 5

000074 (W/E06&E07) lnad. Core Coolina / 4 000076 Hiah Reactor Coolant Activitv I 9 W/E01 & E02 Rediaanosis & SI Termination I 3 W/E13 Steam Generator Over-pressure/ 4 x W/E13 Steam Generator Overpressure 4.6 Q25 2.4.1 Knowledge of EOP entry conditions and immediate action steps ..

W/E15 Containment Flooding I 5 W/E16 High Containment Radiation/ 9 x W/E16 High Containment Radiation 2.7 Q26 EK1. Knowledge of the operational implications of the following concepts as they apply to the (High Containment Radiation)

EK1.2 Normal, abnormal and emergency operating procedures associated with (High Containment Radiation).

BW/A01 Plant Runback / 1 BW/A02&A03 Loss of NNl-XN I 7 BW/A04 Turbine Trio I 4 BW/A05 Emeraencv Diesel Actuation I 6 BW/A07 Floodina I 8 BW/E03 lnadeauate Subcooling Margin I 4 BW/E08; W/E03 LOCA Cooldown - Depress. I 4 BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 x W/E09 Natural Circulation Operations 3.0 Q27 EK1. Knowledge of the operational implications of the following concepts as they apply to the (Natural Circulation Operations)

EK1.1 Components, capacity, and function of emergency systems.

BW/E13&E14 EOP Rules and Enclosures CE/A 11; W/E08 RCS Overcoolina - PTS I 4 CE/A 16 Excess RCS Leakaae I 2 CE/E09 Functional Recovery KIA Cateaory Point Totals: 2 2 2 0 1 2 Group Point Total: 9/4

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form~~ *~* ..,

Plant Systems - Tier 2/Group 1 RO I SRO)

System # I Name K K K K K K A A A A G KIA Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump x 003 Reactor Coolant Pump System 2.8 Q28 (RCPS)

K3 Knowledge of the effect that a loss or malfunction of the RCPS will have on the following:

K3.03 Feedwater and emergency feedwater 004 Chemical and Volume x 004 Chemical and Volume Control 2.6 Q29 Control System (CVCS)

KS Knowledge of the operational implications of the following concepts as they apply to the eves:

KS.37 Effects of boron saturation on ion exchanaer behavior 005 Residual Heat Removal x 005 Residual Heat Removal System 2.7 Q30 (RHRS)

K4 Knowledge of RHRS design feature(s) and/or interlock(s) which provide or the following:

K4.06 Function of RHR pump miniflow recirculation 006 Emergency Core Cooling x x 006 Emergency Core Cooling System 3.4 Q31 (ECCS)

K6 Knowledge of the effect of a loss or malfunction on the following will have on the ECCS:

K6.02 Core flood tanks (accumulators) 3.9 Q32 2.1.27 Knowledge of system purpose and/or function.

007 Pressurizer Relief/Quench x x 007 Pressurizer Relief Tank/Quench 2.6 Q33 Tank Tank System (PRTS)

K4 Knowledge of PRTS design feature(s) and/or interlock(s) which provide for the following:

K4.01 Quench tank cooling 3.6 Q34 A4 Ability to manually operate and/or monitor in the control room:

A4.10 Recognition of leaking PORV/code safetv

008 Component Cooling Water x 008 Component Cooling Water System 3.1 Q35 (CCWS)

A1 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CCWS controls including:

A 1.04 Surge tank level 010 Pressurizer Pressure Control x x 010 Pressurizer Pressure Control 3.2 Q36 System (PZR PCS)

K1 Knowledge of the physical connections and/or cause-effect relationships between the PZR PCS and the following systems:

K1 .08 PZR LCS K6 Knowledge of the effect of a loss or 2.7 Q37 malfunction of the following will have on the PZR PCS:

K6.01 Pressure detection svstems 012 Reactor Protection x 012 Reactor Protection System 4.0 Q38 A3 Ability to monitor automatic operation of the RPS, including:

A3.07 Trip breakers 013 Engineered Safety Features x x 013 Engineered Safety Features 3.1 Q39 Actuation Actuation System (ESFAS)

K4 Knowledge of ESFAS design feature(s) and/or interlock(s) which provide for the following:

K4.08 Redundancy 2.7* Q40 K6 Knowledge of the effect of a loss or malfunction on the following will have on the ESFAS:

K6.01 Sensors and detectors 022 Containment Cooling x 022 Containment Cooling System (CCS) 3.0* Q41 K2 Knowledge of power supplies to the following:

K2.01 Containment cooling fans 025 Ice Condenser 026 Containment Spray x 026 Containment Spray System (CSS) 4.5 Q42 A4 Ability to manually operate and/or monitor in the control room:

A4.01 CSS controls

039 Main and Reheat Steam x 039 Main and Reheat Steam System 3.4 Q43 (MRSS)

A2 Ability to (a) predict the impacts of the following malfunctions or operations on the MRSS; and (b) based on predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.03 Indications and alarms for main steam and area radiation monitors (durina SGTR) 059 Main Feedwater x x 059 Main Feedwater (MFW) System 2.7 Q44 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.03 Overfeeding event 2.5 Q45 A3 Ability to monitor automatic operation of the MFW, including:

A3.03 Feedwater pump suction flow pressure 061 Auxiliary/Emergency x 061 Auxiliary I Emergency Feedwater 2.5 Q46 Feedwater (AFW) System KS Knowledge of the effect of a loss or malfunction of the following will have on the AFW components:

KS.01 Controllers and positioners 062 AC Electrical Distribution x x 062 A.C. Electrical Distribution 3.5 Q47 K3 Knowledge of the effect that a loss or malfunction of the ac distribution system will have on the following:

K3.01 Major system loads A2 Ability to (a) predict the impacts of 2.7 Q48 the following malfunctions or operations on the ac distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.08 Consequences of exceeding voltage limitations 063 DC Electrical Distribution x 063 D.C. Electrical Distribution 2.9 Q49 K1 Knowledge of the physical connections and/or cause effect relationships between the DC electrical system and the following systems:

K1 .03 Battery charger and battery

064 Emergency Diesel Generator x 064 Emergency Diesel Generators 3.4 Q50 (ED/G)

K1 Knowledge of the physical connections and/or cause effect relationships between the ED/G system and the following systems:

K1 .05 StartinQ air svstem 073 Process Radiation x 073 Process Radiation Monitoring (PRM) 3.6 Q51 Monitoring System.

K3 Knowledge of the effect that a loss or malfunction of the PRM system will have on the following:

K3.01 Radioactive effluent releases 076 Service Water x 076 Service Water System (SWS) 3.7 Q52 A3 Ability to monitor automatic operation of the SWS, including:

A3.02 Emeraencv heat loads 078 Instrument Air x x 078 Instrument Air System (IAS) 2.7 Q53 K2 Knowledge of bus power supplies to the following:

K2.01 Instrument air compressor K3 Knowledge of the effect that a loss or 3.1

  • Q54 malfunction of the IAS will have on the following:

K3.01 Containment air svstem 103 Containment x 103 Containment System 3.9 Q55 A3 Ability to monitor automatic operation of the containment system, including:

A3.01 Containment isolation KIA CateQorv Point Totals: 3 2 4 3 I 4 I 3 4 2 1 Grouo Point Total: 28/5

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO I SRO)

System # I Name K K K K K K A A A A G KIA Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive x 001 Control Rod Drive System 4.5 Q56 K1 Knowledge of the physical connections and/or cause effect relationships between the CRDS and the following systems:

Kl.05 NIS and RPS 002 Reactor Coolant 011 Pressurizer Level Control 014 Rod Position Indication x 014 Rod Position Indication System (RPIS) 3.2 Q57 A1 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RPIS controls, including:

A 1.02 Control rod position indication on control room panels 015 Nuclear Instrumentation x 015 Nuclear Instrumentation System 3.3* Q58 A1 Ability to predict and/or monitor changes in parameters to prevent exceeding design limits) associated with operating the NIS controls including:

A 1.07 Changes in boron concentration 016 Non-nuclear Instrumentation 017 In-core Temperature Monitor 027 Containment Iodine Removal 028 Hydrogen Recombiner x 028 Hydrogen Recombiner and Purge 3.4 Q59 and Purge Control Control System (HRPS)

KS Knowledge of the operational implications of the following concepts as they apply to the HRPS:

K5.02 Flammable hydrogen concentration 029 Containment Purge x 029 Containment Purge System (CPS) 3.2 Q60 2.2.25 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

033 Spent Fuel Pool Cooling 034 Fuel Handlina Eouioment 035 Steam Generator 041 Steam Dump/Turbine Bypass Control

045 Main Turbine Generator x 045 Main Turbine Generator (MT/G) 2.5* Q61 System K4 Knowledge of MT/G system design feature(s) and/or interlock(s) which provide for the following:

K4.02 Automatic shut of reheat stop valves as well as main control valves when trippinq turbine 055 Condenser Air Removal x 055 Condenser Air Removal System 2.6 Q62 (CARS)

K1 Knowledge of the physical connections and/or cause-effect relationships between the CARS and the following systems:

K1.06 PRM system 056 Condensate x 056 Condensate System 2.6 Q63 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the Condensate System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.04 Loss of condensate pumps 068 Liquid Radwaste 071 Waste Gas Disposal x 071 Waste Gas Disposal System (WGDS) 3.2 Q64 K3 Knowledge of the effect that a loss or malfunction of the Waste Gas Disposal System will have on the following:

KJ.05 ARM and PRM systems 072 Area Radiation Monitorinq 075 Circulating Water 079 Station Air x 079 Station Air System (SAS) 2.9 Q65 K4 Knowledge of SAS design feature(s) and/or interlock(s) which provide for the following:

K4.01 Cross-connect with IAS 086 Fire Protection KIA Cateqory Point Totals: 2 0 I 2 I 0 2 l 0 0 l Group Point Total: 10/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: SEABROOK Date of Exam: 3/23/15- 4/1/15 Category KIA# Topic RO SRO-Only IR # IR #

2.1.19 2.1.19 Ability to use plant computers to evaluate system 3.9 Q66 or component status.

1.

2.1.29 2.1.29 Knowledge of how to conduct system lineups, 4.1 Q67 Conduct such as valves, breakers, switches, etc.

of Operations 2.1.37 2.1.37 Knowledge of procedures, guidelines, or limitations 4.3 Q68 associated with reactivity manaqement.

2.1.

2.1.

2.1.

Subtotal . :~~~ 3 2.2.1 2.2.1 Ability to perform pre-startup procedures for the 4.5 Q69 facility, including operating those controls associated with plant equipment that could affect reactivity.

2.

2.2.6 2.2.6 Knowledge of the process for making changes to 3.0 Q70 Equipment Control procedures.

2.2.

2.2.

2.2.

2.2.

Subtotal  ?~?'.:;1> 2 '.' .L <

2.3.7 2.3. 7 Ability to comply with radiation work permit 3.5 Q71 requirements durini:i normal or abnormal conditions.

2.3.15 2.3.15 Knowledge of radiation monitoring systems, such 2.9 Q72 3.

as fixed radiation monitors and alarms, portable survey Radiation instruments, personnel monitorino equipment, etc.

Control 2.3.

2.3.

2.3.

2.3.

,,Ah}?' ..7,},J+tc}

Subtotal  ::..*.:** 2 _,,,_*/ "'

2.4.17 2.4.17 Knowledge of EOP terms and definitions. 3.9 Q73 2.4.23 2.4.23 Knowledge of the bases for prioritizing emergency 3.4 Q74 4.

procedure implementation durinq emerqency operations.

Emergency Procedures I 2.4.34 2.4.34 Knowledge of RO tasks performed outside the 4.2 Q75 Plan main control room during an emergency and the resultant operational effects.

2.4.

2.4.

2.4.

Subtotal Tier 3 Point Total 7

ES-401 PWR Examination Outline Form ES-401-2 Facility: SEABROOK Date of Exam: MARCH 2015 RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

  • Total
1. 1 18 2 4 6 Emergency &

Abnormal 2 N/A N/A 9 2 2 4 Plant Evolutions Tier Totals 27 4 6 10 1 28 4 I 5 2.

Plant 2 10 0 2 I 3 Systems Tier Totals 38 6 2 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 2 I 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).
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 and justified; 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 (IRs) for the applicable license level, and the point totals (#)for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in 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 KlAs that are linked to 10 CFR 55.43.

ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emeraencv and Abnormal Plant Evolutions - Tier 1/Grouo 1 (RO I SRO)

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

1 2 3 1 2 000007 (BW/E02&E10; CE/E02) Reactor x 007 Reactor Trip 4.0 Q76 Trip - Stabilization - Recovery I 1 2.1.32 Ability to explain and apply system limits and precautions.

000008 Pressurizer Vapor Space Accident/ 3 000009 Small Break LOCA I 3 x 009 Small Break LOCA 3.8 Q77 EA2 Ability to determine or interpret the following as they apply to a small break LOCA:

EA2.02 Possible leak paths 000011 Large Break LOCA I 3 x 011 Large Break LOCA 4.7 Q78 2.4.6 Knowledge of EOP mitigation strategies.

000015/17 RCP Malfunctions I 4 000022 Loss of Rx Coolant Makeup I 2 000025 Loss of RHR System I 4 000026 Loss of Component Cooling Water 18 000027 Pressurizer Pressure Control Svstem Malfunction I 3 000029 A TWS I 1 000038 Steam Gen. Tube Rupture I 3 x 038 Steam Generator Tube Rupture (SGTR) 4.3 Q79 2.4.45 Ability to prioritize and interpret the sionificance of each annunciator or alarm.

000040 (BW/E05; CE/E05; W/E12)

Steam Line Rupture - Excessive Heat Transfer 14 000054 (CE/E06) Loss of Main Feedwater I 4 000055 Station Blackout I 6 000056 Loss of Off-site Power I 6 000057 Loss of Vital AC Inst. Bus/ 6 000058 Loss of DC Power I 6 x 058 Loss of DC Power 4.4 Q80 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

000062 Loss of Nuclear Svc Water I 4 000065 Loss of Instrument Air I 8 W/E04 LOCA Outside Containment I 3

W/E11 Loss of Emergency Coolant x W/E11 Loss of Emergency Coolant Recirculation 4.2 Q81 Recirc. / 4 EA2. Ability to determine and interpret the following as they apply to the (Loss of Emergency Coolant Recirculation)

EA2.1 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink I 4 000077 Generator Voltage and Electric Grid Disturbances / 6 KIA Cateaorv Totals: 2 4 Group Point Total: 18/6 II

ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO I SRO)

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

1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 000003 Dropped Control Rod I 1 000005 Inoperable/Stuck Control Rod / 1 000024 Emeroency Boration / 1 000028 Pressurizer Level Malfunction I 2 000032 Loss of Source Range NI / 7 000033 Loss of Intermediate Range NI I 7 000036 (BW/A08) Fuel Handling Accident I 8 000037 Steam Generator Tube Leak I 3 x 037 Steam Generator (S/G) Tube Leak 3.4 Q82 AA2. Ability to determine and interpret the following as they apply to the Steam Generator Tube Leak:

AA2.01 Unusual readings of the monitors; steps needed to verify readings 000051 Loss of Condenser Vacuum/ 4 000059 Accidental Liquid RadWaste Rel. I 9 000060 Accidental Gaseous Radwaste Rel. I 9 000061 ARM System Alarms 17 000067 Plant Fire On-site I 8 000068 (BW/A06) Control Room Evac. I 8 000069 (W/E14) Loss of CTMT Integrity 15 000074 (W/E06&E07) lnad. Core Cooling/ 4 x 074 Inadequate Core Cooling 4.0 Q83 2.4.18 Knowledge of the specific bases for EOPs.

000076 High Reactor Coolant Activity/ 9 W/E01 & E02 Rediaanosis & SI Termination I 3 W/E13 Steam Generator Over-pressure I 4 W/E15 Containment Flooding/ 5 W/E16 Hiah Containment Radiation/ 9 BW/A01 Plant Runback / 1 BW/A02&A03 Loss of NNl-X/Y I 7 BW/A04 Turbine Trip I 4 BW/A05 Emergency Diesel Actuation I 6 BW/A07 Floodinq I 8 BW/E03 Inadequate Subcooling Marain I 4

BW/E08; W/E03 LOCA Cooldown - Depress. I 4 x W/E03 LOCA Cooldown and 4.7 Q84 Depressurization 2.4.4 Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operatina procedures.

BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 BW/E13&E14 EOP Rules and Enclosures CE/A 11; W/E08 RCS Overcooling - PTS I 4 x W/EOS Pressurized Thermal Shock 4.2 Q85 EA2. Ability to determine and interpret the following as they apply to the (Pressurized Thermal Shock EA2.1 Facility conditions and selection of appropriate procedures during abnormal and emeraencv operations.

CE/A 16 Excess RCS Leakage I 2 CE/E09 Functional Recovery KIA Category Point Totals: 2 2 Group Point Total: 9/4

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Svstems - Tier 2/Grouo 1 RO I SRO)

System #I Name K K K K K K A A A A G KIA Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump 004 Chemical and Volume x 004 Chemical and Volume Control 3.9 Q86 Control System (CVCS)

A2 Ability to (a) predict the impacts of the following malfunctions or operations on the eves; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.09 High primary and/or secondary activity 005 Residual Heat Removal 006 Emeroencv Core Coolino 007 Pressurizer Relief/Quench Tank 008 Component Cooling Water 010 Pressurizer Pressure Control 012 Reactor Protection 013 Engineered Safety Features Actuation 022 Containment Coolino 025 Ice Condenser 026 Containment Spray 039 Main and Reheat Steam x 039 Main and Reheat Steam System 3.7 Q87 (MRSS)

A2 Ability to (a) predict the impacts of the following malfunctions or operations on the MRSS; and (b) based on predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.04 Malfunctionino steam dump 059 Main Feedwater

061 Auxiliary/Emergency x 061 Auxiliary I Emergency Feedwater 3.5 Q88 Feedwater (AFW) System A2 Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.07 Air or MOV failure 062 AC Electrical Distribution 063 DC Electrical Distribution 064 Emergency Diesel Generator x 064 Emergency Diesel Generators 4.7 Q89 (ED/G) 2.2.22 Knowledge of limiting conditions for operations and safety limits.

073 Process Radiation Monitorino 076 Service Water x 076 Service Water System (SWS) 3.7* Q90 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.01 Loss of SWS 078 Instrument Air 103 Containment KIA Category Point Totals: 4 1 Group Point Total: 28/5

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form E~ *~* ~

Plant S 1stems - Tier 2/Group 2 (RO I SRO)

System # I Name K K K K K K A A A A G KIA Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive 002 Reactor Coolant x 002 Reactor Coolant System (RCS) 4.4 Q91 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the RCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.01 Loss of coolant inventory 011 Pressurizer Level Control 014 Rod Position Indication 015 Nuclear Instrumentation 016 Non-nuclear Instrumentation 017 In-core Temperature Monitor x 017 In-Core Temperature Monitor System 4.1 Q92 (ITM)

A2 Ability to (a) predict the impacts of the following malfunctions or operations on the ITM system; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations:

A2.02 Core damage 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 Bypass Control 045 Main Turbine Generator 055 Condenser Air Removal 056 Condensate

068 Liquid Radwaste x 068 Liquid Radwaste System (LRS) 4.4 Q93 2.2.44 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and svstem conditions.

071 Waste Gas Disposal 072 Area Radiation Monitoring 075 Circulatina Water 079 Station Air 086 Fire Protection KIA Cateaorv Point Totals: 2 l Group Point Total: 10/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Date of Exam:

Category KIA# Topic RO SRO-Onlv IR # IR #

2.1.7 2.1. 7 Ability to evaluate plant performance and make 4.7 Q94 operational judgments based on operating characteristics,

1. reactor behavior, and instrument interpretation.

Conduct 2.1.32 2.1.32 Ability to explain and apply system limits and 4.0 Q95 of Operations precautions.

2.1.

2.1.

2.1.

2.1.

    • dtil;;  ;'."':'

Subtotal h 2 2.2.7 2.2.7 Knowledge of the process for conducting special or 3.6 Q96 infrequent tests.

2.2.21 2.2.21 Knowledge of pre- and post-maintenance 4.1 Q97 2.

operability requirements.

Equipment Control 2.2.

2.2.

2.2.

2.2.

,,,,,,, 'c Subtotal . 2 2.3.4 2.3.4 Knowledge of radiation exposure limits under 3.7 Q98 normal or emeroencv conditions.

2.3.

3.

Radiation 2.3.

Control 2.3.

2.3.

2.3.

Subtotal ~!r *:l ""' i(;

1 2.4.8 2.4.8 Knowledge of how abnormal operating procedures 4.5 Q99 are used in coniunction with EOPs.

4.

2.4.28 2.4.28 Knowledge of procedures relating to a security 4.1 QIOO Emergency event (non-safeouards information).

Procedures I Plan 2.4.

2.4.

2.4.

2.4.

t***

1y
~1i** ****(

Subtotal 2

3 Point Total 7 ES-401 Record of Rejected KlAs Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected KIA RO CE/E09 Randomly selected CE/E09 Functional Recovery. This is a CE item not applicable to Seabrook. Randomly reselected W/E09 Natural Circulation.

1/2 RO 009 EK3.09 Randomly selected 009 EK3.09 Small Break LOCA knowledge of the reason for closing CCW surge tank vent as it applies to the Small Break 1/1 LOCA. No Abnormal or Emergency procedure at Seabrook closes the CCW surge tank vent. Randomly reselected EK3.03.

RO 003 K3.05 Randomly selected 003 K3.05 Reactor Coolant Pump system knowledge of the effect Loss/Malfunction of RCP will have on ICS. ICS is a B&W 2/1 system that is not applicable to Seabrook. Randomly reselected K3.03 SRO 011 G 2.4.34 Randomly selected generic 2.4.34. Knowledge of RO tasks outside Main Control Room during Large Break LOCA. There are no RO tasks outside 1/1 the Main Control Room during a Large Break LOCA. Randomly reselected 2.4.6 Knowledoe of EOP mitioation strateoies.

SRO 004 A2.25 Randomly selected 004 A2.25 Chemical and Volume Control System, Ability to (a) predict the impacts of the following malfunctions or operations 2/1 on the eves; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Uncontrolled boration or dilution. Was unable to create an adequate SRO only level question for this KA. Randomly reselected from the same cateoory 004 A2.09 High primary and/or secondary activity.

SRO 076 A2.02 Randomly selected 076 A2.02 Service Water System (SWS), Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; 2/1 and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Service water header pressure. Seabrook has no service water header pressure instruments, only SW pump discharge pressure instruments. Could not develop question for this KA. Reselected only other KA under 076 A2 which is A2.01 Loss of SWS.

RO 037 AA2.05 Randomly selected 037 AA2.05 Steam Generator (SIG) Tube Leak, Ability to determine and interpret the following as they apply to the Steam 1/2 Generator Tube Leak: Past history of leakage with current problem. This KA is too similar to SRO Question 82. Randomly reselected AA2.10 Tech-Spec limits for RCS leakage, from same cateoory.

RO W/E13 2.1.25 Randomly selected W/E13 2.1.25 Steam Generator Overpressure, Ability to interpret reference materials, such as graphs, curves, tables, etc. Was 1/2 unable to generate question to meet this KA. Randomly selected new KA from Generic Section. First random selection was 2.4.11 Knowledge of abnormal condition procedures. This generic does not for KA topic for EOP FR-H.2 Response to Steam Generator Overpressure. Second Random selection was 2.4.1 Knowledge of EOP entry conditions and immediate action steps.

RO 062 A2.16 Randomly selected 062 A2.16 AC Electrical Distribution System, Ability to (a) predict the impacts of the following malfunctions or operations on the ac 2/1 distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Degraded system voltages. This KA is too similar to KA and question developed for Q18. Randomly reselected from same category A2.08 Consequences of exceedino voltaoe limitations.

RANDOM SAMPLING PROCESS 2015 SEABROOK LOIT NRC WRITTEN EXAM As required by NU REG 1021, Rev 9, Supplement 1, (ES-401 D.1.b), the licensee shall submit along with the NRC examination outline, a description of the systematic and random selection process used to develop the examination outline.

The manual random sampling process described in Attachment 1 of ES-401 was used to generate the NRC Examination RO and SRO outlines.

  • During the exam outline generation the following K/A statements were eliminated as not applicable to Seabrook design.

o All K/As associated with Ice Condenser (025) - This system is N/A to Seabrook.

o All K/As associated with Containment Iodine Removal (27) -

This system is included as part of the Containment Building Spray System at Seabrook.

o Generic K/A statements 2.2.3 and 2.2.4 (multi-unit) were not sampled - Seabrook is a single unit facility.

  • During the examination development, any K/A statements eliminated and resampled were documented on ES-401-4, Record of Rejected K/As as required by ES-401, Attachment 2.

The facility lead exam developer is overseeing the audit exam development to ensure no specific subject matter overlap occurs between the exams.

Page I of I

ES-301 Administrative Topics Outline Form ES-301-1 Seabrook Station 2015 NRC Exam JPM - RO Facility: Seabrook Date of Examination: March 2015 Examination Level: RO IX! SRO D Operating Test Number:

Administrative Topic Type Describe activity to be performed (see Note) Code*

Steady State Leak Rate Calculation (OX1401.02)

R,M KA: 2.1. 7 Ability to evaluate plant performance and Conduct of Operations make operational judgments based on the operating characteristics, reactor behavior, and instrument interpretation.

ECP Calculation (RS1735)

R,M KA: 2.1.37 Knowledge of procedures, guidelines, or Conduct of Operations limitations associated with reactivity management.

Shutdown Margin Calculation for Mode 2 (RX1707)

R,M KA: 2.2.12 Knowledge of Surveillance Procedures Equipment Control COP Exhaust Rad Monitor Setpoints (OS1023.69)

R,M KA: 2.3.11 Ability to control radiation releases.

Radiation Control 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)

Page 1 of 1

ES-301 Administrative Topics Outline Form ES-301-1 Seabrook Station 2015 NRC Exam JPM - SRO-I Facility: Seabrook Date of Examination: March 2015 Examination Level: RO D SRO ~ Operating Test Number:

Administrative Topic Type Describe activity to be performed (see Note) Code*

Verify Steady State Leak Rate Calculation (OX1401.02)

R,M KA: 2.1. 7 Ability to evaluate plant performance and Conduct of Operations make operational judgments based on the operating characteristics, reactor behavior, and instrument interpretation.

Approve ECP Calculation (RS1735)

R,M KA: 2.1.37 Knowledge of procedures, guidelines, or Conduct of Operations limitations associated with reactivity management.

Review Shutdown Margin Calculation for Mode 2 (RX1707)

R,M Equipment Control KA: 2.2.12 Knowledge of Surveillance Procedures Verify COP Exhaust Rad Monitor Setpoints (OS1023.69)

R,M Radiation Control KA: 2.3.11 Ability to control radiation releases.

Post Scenario Emergency Plan Classification and Notification (ER-1.1, ER-1.2)

R,M Emergency Procedures/Plan KA: 2.4.40 Knowledge of the 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 (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)

Page 1 of 1

ES-301 Administrative Topics Outline Form ES-301-1 Seabrook Station 2015 NRC Exam JPM - SRO-U Facility: Seabrook Date of Examination: March 2015 Examination Level: RO D SRO igJ Operating Test Number:

Administrative Topic Type Describe activity to be performed (see Note) Code*

Verify Steady State Leak Rate Calculation (OX1401.02)

R,M KA: 2.1. 7 Ability to evaluate plant performance and Conduct of Operations make operational judgments based on the operating characteristics, reactor behavior, and instrument interpretation.

Approve ECP Calculation (RS1735)

R,M KA: 2.1.37 Knowledge of procedures, guidelines, or Conduct of Operations limitations associated with reactivity management.

Review Shutdown Margin Calculation for Mode 2 (RX1707)

R,M Equipment Control KA: 2.2.12 Knowledge of Surveillance Procedures Verify COP Exhaust Rad Monitor Setpoints (OS1023.69)

R,M Radiation Control KA: 2.3.11 Ability to control radiation releases.

Post Scenario Emergency Plan Classification and Notification (ER-1.1, ER-1.2)

Emergency Procedures/Plan R,M KA: 2.4.40 Knowledge of the 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 (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)

Page 1 of 1

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Seabrook Station 2015 NRC Exam JPM - RO Facility: Seabrook Date of Examination: March 2015 Exam Level: RO ~ SRO-I 0 SRO-U D Operating Test No.:

Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Function

a. Perform a Blended Makeup to the VCT A,M,S 1
b. Trip all RCPs A,D,E,S 2
c. Perform SI Termination/Reduction E,EN,M,S 3
d. Steam Header Pressure PT-507 Fails High N,S 4 (Secondary)
e. Start Hydrogen Recombiners D,E,P,S 5
f. Emergency Trip of Emergency Diesel 1B A,M,S 6
g. FR-H.1 Bleed and Feed A,E,M,S 4 (Primary)
h. Placing the Containment On-Line Purge (COP) System M,S 8 in Service In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. ASDV Local Operation D,E,R 5 M,E,L 4
j. Reset Steam Driven EFW Pump Trip Valve
k. Transfer Vital Instrument Bus D,L 6 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 S9/S8/S4 (E)mergency or abnormal in-plant 2:1/2:1/2:1 (EN)gineered safety feature - I - I <: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) <:2/2:2/2:1 (P)revious 2 exams s 3 I s 3 Is 2 (randomly selected)

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Seabrook Station 2015 NRC Exam JPM - SRO-I Facility: Seabrook Date of Examination: March 2015 Exam Level: RO D SRO-I ~ SRO-U D Operating Test No.:

Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Function

a. Perform a Blended Makeup to the VCT A,M,S 1
b. Trip all RCPs A,D,E,S 2
c. Perform SI Termination/Reduction E,EN,M,S 3
d. Steam Header Pressure PT-507 Fails High N,S 4 (Secondary)
e. Start Hydrogen Recombiners D,E,P,S 5
f. Emergency Trip of Emergency Diesel 1B A,M,S 6
g. FR-H.1 Bleed and Feed A,E,M,S 4 (Primary)

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

i. ASDV Local Operation D,E,R 5 M,E,L 4
j. Reset Steam Driven EFW Pump Trip Valve
k. Transfer Vital Instrument Bus D,L 6 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 S9/S8/S4 (E)mergency or abnormal in-plant <::1/<::1/<::1 (EN)gineered safety feature - I - 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 / s 2 (randomly selected)

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Seabrook Station 2015 NRC Exam JPM -SRQ-U Facility: Seabrook Date of Examination: March 2015 Exam Level: RO D SRO-I 0 SRO-U 1:8:1 Operating Test No.:

Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Function

b. Trip all RCPs A,D,E,S 2
c. Perform SI Termination/Reduction E,EN,M,S 3
f. Emergency Trip of Emergency Diesel 1B A,M,S 6 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

D,E,R 5

i. ASDV Local Operation
j. Reset Steam Driven EFW Pump Trip Valve M,E,L 4 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 S9/S8/S4 (E)mergency or abnormal in-plant ~1/~1/~1 (EN)gineered safety feature - I - I ~1 (control room system)

(L)ow-Power I Shutdown 1I 1 I~ 1 (N)ew or (M)odified from bank including 1(A) 21 21~1 (P)revious 2 exams 3/ 3 Is 2 (randomly selected)

(R)CA 1I 1 I~ 1 (S)imulator

Appendix D Scenario Outline Form ES-D-1 Seabrook Station 2015 NRC Exam-Simulator Scenario Facility: SEABROOK Scenario No.: A Op-Test No.: 2015 Examiners: Operators:

Initial Conditions: MOL 100% power with stable Xenon, Boron Concentration at 1058 ppm, CB D at 230 steps.

Turnover:

Event Malt. No. Event Event No. Type* Description PSOR 1 BOPN Rapid down power to 800 MW electric in 30 minutes.

USN PSOI 2 ltRCLT459 RC-LT-459 fails low.

USI, TS BOPI 3 ptFWPT508 FW-PT-508 fails high.

USI PSOM mfED038 4 BOPM Loss of offsite power with no EOG response.

mfED033 USM mfCC013 5 PSOC 'B' Train of PCCW fails to auto start.

mfCC015 mfSW013 6 BOPC 'B' Train of SW fails to auto start.

mfSW015

  • (N)ormal, (R)eactivitv, (l)nstrument, (C)omoonent, (M)aior Anticipated AOP/EOP flow-path: OS1231.04, OS1201.07, ON1230.01, E-0, ECA-0.0

Appendix D Scenario Outline Form ES-D-1 Seabrook Station 2015 NRC Exam-Simulator Scenario Facility: SEABROOK Scenario No.: B Op-Test No.: 2015 Examiners: Operators:

Initial Conditions: MOL 75% power with stable Xenon, Boron Concentration at 1166 ppm, CB D at 187 steps and both Heater Drain pumps in service.

Turnover:

  • The crew will begin a power increase at 10%/hr to 90% power.

Event Malf. No. Event Event No. Type* Description PSOR 1 BOPN Crew begins a 10%/hr power increase.

USN PSOI 2 ptRCPT455 RC-PT-455 Failed Low.

USl,TS PSOC 3 mfCSP2B CS-P-2B overcurrent trip.

USC, TS BOPI 4 ltFWLT551 FW-LT-551 fails high.

USl,TS PSOM 600 gpm RCS leak (simulated with int leg leak). Reactor trip 5 mfRC050A BOPM and Safety injection required which also triggers a loss of USM offsite power.

BOPC SW-V16, 'A' EOG Service Water supply isolation valve fails to 6 cSWV16 USC auto open.

mfMSPCV BOPC On reactor trip 'D' SG ASDV fails open and will not close from 7

3004 USC the MCB.

  • (N)ormal, (R)eactivitv, (l)nstrument, (C)omponent, (M)aior Anticipated AOP/EOP flow-path: OS1202.02, OS1235.03, E-0, E-2, E-1

Appendix D Scenario Outline Form ES-D-1 Seabrook Station 2015 NRC Exam-Simulator Scenario Facility: SEABROOK Scenario No.: c Op-Test No.: 2015 Examiners: Operators:

Initial Conditions: MOL 55% power with Rods in Auto, boron concentration at 1254 ppm and CB D at 156 steps and both Main Feed pumps in service.

Turnover:

  • The crew will begin a rapid down power at 25%/hr to 45% power for FW-P-32-A high vibrations.

Event Malf. No. Event Event No. Type* Description PSOR Crew begins a 25%/hr rapid down power for FW-P-32-A high 1 BOPN vibrations.

USN PSOC

'A' RCP vibration levels increase requiring tripping of the 'A' 2 mfRC020 BOPC RCP.

USC,TS BOPI 3 trFWFT520 'B' SG Controlling Feed Flow Channel fails high.

USI PSOC 4 mfSG001A 'A' SG 30 gpm tube leak.

USC, TS svMSV92 PSOM 'D' MSIV fails closed requiring manual reactor trip. ATWS 5 mfRPS001 BOPM requiring NSO to locally trip the Reactor followed by 'A' SG mfRPS002 USM tube rupture requiring SI.

  • (N)ormal, (R)eactivitv, (l)nstrument, (C)omoonent, (M)aior Anticipated AOP/EOP flow-path: OS1231.04, OS1201.01, OS1235.04, OS1227.02, E-0, FR-S.1, E-3
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