ML13206A323

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Seabrook - Final Outlines (Folder 3)
ML13206A323
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 07/09/2013
From:
Operations Branch I
To: David Silk
NextEra Energy Seabrook
Jackson D
Shared Package
ML13059A103 List:
References
TAC U01870
Download: ML13206A323 (36)
v • d • e


Text

ES-401 PWR Examination Outline Form ES-401-2 II Facilit~ SEABROOK Date of Exam: 7/12113 -7/19/13 I RO KIA Categmy_ Points SRO-Only Points Tier Group K K K K K K AlA A AIG A2 G* Total 1 2 3 4 5 6 1 I 2 3 4 :

  • Total
1. 1 2 2 2 5 4 I3 18 6 Emergency &

1 Abnormal 2 0 3 I N/A 1 2 2 9 4 Plant Evolutions Tier Totals 2 I5 3 6 6 5 27 10 1 4 2 3 I 5 3 I I 2 3 I 3 I 28 5

2. 1 Plant 2 I 2 0 0 0 0 I I 2 I 2 I 10 3 Systems Tier Totals 6 2 2J 5 3 !2 2 4 4 5 2 38 8
3. Generic Knowledge and Abilities 1 2 3 I 4 10 1 2 3 4 7 Categories 2 3 2 3 Note: 1. Ensure that at least two topics from every ~pplicable 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 KlAs having an importance rating (lR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.

7.* The generic (G) KlAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KlAs.

8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license levE~I, 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.

u

ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401*2 EmerQencv and Abnormal Plant Evolutions* Tier 1fGroup 1 (RO 1 SRO)

E/APE # f Name 1 Safety Function K I< 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 Ql Trip - Stabilization* Recovery f 1 EK3 Knowledge of the reasons for the following as

, they apply to a reactor trip:

~

EK3.01 Actions contained in EOP for reactor trip 000008 Pressurizer Vapor Space X 008 Pressurizer (PZR) Vapor Space Accident 3.2 Q2 Accident I 3 (Relief Valve Stuck Open)

AK 1 Knowledge of the operational implications of the following concepts as they apply to a Pressurizer Vapor Space Accident:

AK1.01 Thermodynamics and flow characteristics of open or leaking valves 000009 Small Break LOCA 13 X 009 Small Break LOCA 4.2 Q3 EA2 Ability to determine or interpret the following as they apply to a small break LOCA:

EA2.36 Difference between overcooling and LOCA I indications 000011 Large Break LOCA I 3 X 011 Large Break LOCA 2.6 Q4 EK2 Knowledge of the interrelations between the and the following Large Break LOCA:

EK2.02 Pumps 000015/17 RCP Malfunctions 1 4 X 0151017 Reactor Coolant Pump (RCP) Malfunctions 3.4 Q5 2.2.40 Ability to apply Technical Specifications for a I system.

J 000022 Loss of Rx Coolant Makeup 12 X 022 Loss of Reactor Coolant Makeup 3.8 Q6 2.4.35 Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects.

000025 Loss of RHR System 1 4 I

000026 Loss of Component Cooling X 026 Loss of Component Cooling Water (CCW) 3.2 Q7 Water f 8 AA1 Ability to operate and I or monitor the following as they apply to the Loss of Component Cooling Water:

AA 1.02 Loads on the CCWS in the control room 000027 Pressurizer Pressure Control X 027 Pressurizer Pressure Control System (PZR 3.6 Q8 System Malfunction f 3 PCS) Malfunction AA 1 Ability to operate and I or monitor the following as they apply to the Pressurizer Pressure Control Malfunctions:

AA1.03 Pressure control when on a steam bubble

000029 ATWS 1 1 X 029 Anticipated Transient Without Scram (ATWS) 3.9 Q9 2.1.19 Ability to use plant computers to evaluate system or component status.

000038 Steam Gen. Tube Rupture 13 X 038 Steam Generator Tube Rupture (SGTR) 3.9 QIO EA1 Ability to operate and monitor the following as they apply to a SGTR:

EA1.27 Steam dump valve status lights and indicators 000040 (BW/E05; CE/E05; W/E12) X 040 Steam Line Rupture 4.1 QlI Steam Line Rupture - Excessive Heat Transfer /4 AA2 Ability to determine and interpret the following as they apply to the Steam Line Rupture:

AA2.05 When ESFAS sy'stems ma'y'be secured 000054 (CE/E06) Loss of Main Feedwater I 4 000055 Station Blackout I 6 X 055 Loss of Offsite and Onsite Power (Station 2.7 Q12 Blackout)

EK3 Knowledge of the reasons for the following responses as the apply to the Station Blackout:

EK3.01 Length of time for which battery capacity is

, designed 000056 Loss of Off-site Power / 6 X 056 Loss of Offsite Power 3.7 Q13 AK1. Knowledge of the operational implications of I 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 I 6 000058 Loss of DC Power 1 6 X 058 Loss of DC Power 3.4 Q14 AA1. Ability to operate and I or monitor the following as they apply to the Loss of DC Power:

AA1.01 Cross-tie of the affected dc bus with the alternate supply' 000062 Loss of Nuclear Svc Water I 4 I 000065 Loss of Instrument Air 1 8 Westinghouse E04 LOCA Outside Containment W/E04 LOCA Outside Containment 1 3 X 3.6 QI5 EA1. Ability to operate and I or monitor the following as they apply to the (LOCA Outside Containment)

EA1.2 Operating behavior characteristics of the facility.

, Westinghouse E11 Loss of Emergency Coolant W/E11 Loss of Emergency Coolant X ~ Recirculation 3.9 Ql6 Recirc./4 EK2. Knowledge of the interrelations between the (Loss of Emergency Coolant ReCirculation) and the following:

EK2.2 Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

Westinghouse EOS Loss of Secondary Heat Sink BW/E04; W/E05 Inadequate Heat X 3.7 Ql7 Transfer - Loss of Secondary Heat Sink 14 EA2. Ability to determine and interpret the following as they apply to the (Loss of Secondary Heat Sink)

EA2.2 Adherence to appropriate procedures and operation within the limitations in the facility's I

license and amendments.

000077 Generator Voltage and Electric X 077 Generator Voltage and Electric Grid 3.6 QI8 Grid Disturbances 16 Disturbances AA2. Ability to determine and interpret the following as they apply to Generator Voltage and Electric Grid

, Disturbances:

'" AA2.04 VARs outside the capability curve i

KIA Category Totals: 2 2 2 5 4 I 3 1 Group Point Total: 18/6

o 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)

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

1 2. 3 1 2 000001 Continuous Rod Withdrawal I 1 000003 Dropped Control Rod / 1 X 003 Dropped Control Rod 3.7 Q19 AA2. Ability to determine and interpret the following as they apply to the Dropped Control Rod:

AA2.01 Rod position indication to actual rod position 000005 Inoperable/Stuck Control Rod 11 000024 Emergency Boration 11 X 024 Emergency Boration 2.1.30 Ability to locate and operate 4.4 Q20 I

components, including local controls.

000028 Pressurizer Level Malfunction 12 X 028 Pressurizer (PZR) Level Control 2.6 Q21 Malfunction AK2. Knowledge of the interrelations IJ between the Pressurizer Level Control Malfunctions and the following:

AK2.03 Controllers and positioners 000032 Loss of Source Range Nil 7

~Q33 Loss of Intermediate Ranf,le Nil 7 I 000036 (BW/A08) Fuel Handling Accident I 8  ! I 000037 Steam Generator Tube Leak I 3 X 037 Steam Generator (S/G) Tube leak 4.1 Q22 AK3. Knowledge of the reasons for the following responses as they apply to the Steam Generator Tube Leak:

AK3.08 Criteria for securing RCP 000051 Loss of Condenser Vacuum 14 r-I 000059 Accidental Liquid RadWaste Rei. I 9 X 059 Accidental Liquid Radwaste Release 2.7 Q23 AK2. Knowledge of the interrelations between the Accidental Liquid Radwaste Release and the following:

I I AK2.01 Radioactive-liquid monitors I

000060 Accidental Gaseous Radwaste ReI. 1 9 1 000061 ARM S~stem Alarms 17 000067 Plant Fire On-site 1 8 I

000068 (BW/A06) Control Room Evac. I 8

" I 000069 (\N/E14) Loss of CTMT IntegrityJ 5 000074 (W/E06&E07) Inad. Core Cooling / 4 000076 High Reactor Coolant Activity / 9 X 076 High Reactor Coolant Activity 2.5 Q24 AA2. Ability to determine and interpret the following as they apply to the High Reactor Coolant Activity:

L AA2.03 RCS radioactivity level meter

W/E01 & E02 Rediagnosis & SI Termination 13 Westinghouse E13 Steam Generator W/E 13 Steam Generator Over-pressure I 4 X 3.1 Q25 Overpressure EA1. Ability to operate and I or monitor the following as they apply to the (Steam Generator Overpressure)

EA1.3 Desired operating results during abnormal and emergency situations.

Westinghouse E15 Containment Flooding W/E 15 Containment Flooding 1 5 X 2.7 Q26 EK2. Knowledge of the interrelations between the (Containment Flooding) and the following:

EK2.2 Facility's heat removal systems, v including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

W/E16 High Containment Radiation 19 BW/AOl Plant Runback 11 BW/A02&A03 Loss of NNI-XIY 17 BW/A04 Turbine Trip 14 BW/A05 Emergency Diesel Actuation 16 BW/A07 Flooding 1 8 BW/E03 Inadequate Subcooling Margin 14 Westinghouse E03 LOCA Cooldown and BW/E08; W/E03 LOCA Cooldown - Depress. 14 X 3.7 Q27 Depressurization 2.4.3 Ability to identify post-accident instrumentation.

BW/E09; CE/A13; W/E09&El0 Natural Circ./4 BW/E13&E14 EOP Rules and Enclosures CE/A 11; W/E08 RCS Overcooling - PTS f 4 CEfA16 Excess RCS Leakage f 2 CEfE09 Functional Recovery 0 3 1 1 9/4

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2

'C"O)

System # / 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 3.1 Q28 (RCPS)

K2 Knowledge of bus power supplies to the following:

K2,01 RCPS 004 Chemical and Volume X 004 Chemical and Volume Control 2.7 Q29 Control System (CVCS)

K2 Knowledge of bus power supplies to the following:

K2.05 MOVs 005 Residual Heat Removal X X 005 Residual Heat Removal System (RHRS)

K1 Knowledge of the physical

., connections and/or cause effect relationships between the RHRS and the following systems:

K1.04CVCS 2.9 Q30 K4 Knowledge of RHRS design feature(s} and/or interlock(s) which provide or the following:

K4.10 Control of RHR heat exchanger outlet flow 3.1 Q31 006 Emergency Core Cooling X 006 Emergency Core Cooling System 4.4 Q32 (ECCS)

A4 Ability to manually operate and/or monitor in the control room:

A4.07 ECCS pumps and valves 007 Pressurizer Relief/Quench X 007 Pressurizer Relief Tank/Quench 2.7 Tank Tank System (PRTS)

  • Q34 A3 Ability to monitor automatic operation of the PRTS, including:

A3.01 Components which discharge to the PRT 008 Component Cooling Water X 008 Component Cooling Water System 3.2 Q35

, (CCWS)

  • A3 Ability to monitor automatic operation of the CCWS, including:

A3.01 Setpoints on instrument signal levels for normal operations, warnings, and trips that are applicable to the CCWS

010 Pressurizer Pressure Control 010 Pressurizer Pressure Control X X System (PZR PCS)

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

K1.01 RPS 3.9 Q36 KS Knowledge of the effect of a loss or malfunction of the following will have on the PZR PCS:

3.2 Q37 KS.03 PZR ~prays and heaters 012 Reactor Protection X 012 Reactor Protection System 3.7 Q38

. A3 Ability to monitor automatic

'" operation of the RPS, including:

i A3.0S Trip logic 013 Engineered Safety Features 013 Engineered Safety Features X X Actuation System (ESFAS)

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

43 Q39 K3.02 RCS A2 Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based Ability on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations; A2.02 Excess steam demand 43 Q40 022 Containment Cooling X X 022 Containment Cooling System (CCS)

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

~ K4.04 Cooling of control rod drive 2.8 Q41 motors 2.1.20 Ability to interpret and execute I

procedure steps. 4.6 Q42 025 Ice Condenser 026 Containment Spray X 026 Containment Spray System (CSS) 3.5 Q43 A4 Ability to manually operate and/or monitor in the control room:

A4.05 Containment spray reset I

switches

039 Main and Reheat Steam X X 039 Main and Reheat Steam System K4 Knowledge of MRSS design

, feature(s) and/or interlock(s) which

.,)

provide for the following:

K4.02 Utilization of T-ave. program control when steam dumping through atmospheric relief/dump valves, including T-ave, limits 3,1 Q44 K5 Knowledge of the operational implications of the following concepts as the apply to the MRSS: 2,7 Q45 K5.05 Bases for RCS cooldown limits 059 Main Feedwater X 059 Main Feedwater (MFW) System 3,1 Q46 K1 Knowledge of the physical connections and/or cause effect relationships between the MFW and the following systems:

K1.05 RCS 061 Auxiliary/Emergency X 061 Auxiliary / Emergency Feedwater 3,2 Q47 Feedwater (AFW) System K5 Knowledge of the operational implications of the following concepts as the apply to the AFW:

K5.02 Decay heat sources and magnitude 062 AC Electrical Distribution X 062 A.C, Electrical Distribution 2.7 Q48 K4 Knowledge of ac distribution system design feature(s) and/or interlock(s) which provide for the following:

K4.05 Paralleling of ac sources (synchroscope) 063 DC Electrical Distribution X 063 D.C, Electrical Distribution 3.5 Q49 K3 Knowledge of the effect that a loss or malfunction of the DC electrical system will have on the following:

K3.02 Components using DC control I power

064 Emergency Diesel Generator X X 064 Emergency Diesel Generators (ED/G)

K3 Knowledge of the effect that a loss or malfunction of the ED/G system will have 38 Q33 on the following:

  • K3.01 Systems controlled by automatic loader A2 Ability to (a) predict the impacts of the following malfunctions or Q50 operations on the ED/G system; and (b) 2.6 based on those predictions, use procedures to correct. control, or
  • mitigate the consequences of those malfunctions or operations:

, A2.18 Consequences of premature

~ opening of breaker under load 073 Process Radiation X X 013 Process Radiation Monitoring Monitoring (PRM) System K1 Knowledge of the physical connections and/or causeeffect relationships between the PRM system and the following systems:

K1.01 Those systems served by PRMs 3.6 Q51 K5 Knowledge of the operational implications as they apply to concepts as they apply to the PRM system:

K5.01 Radiation theory, including 2.5 Q52 sources, types, units, and effects 076 Service Water X 076 Service Water System (SWS) 2.6 Q53 A1 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the SWS controls including:

A1.02 Reactor and turbine building i closed COOling water temperatures 078 Instrument Air X 018 Instrument Air System (lAS) 3.1 Q54

~

A4 Ability to manually operate and/or monitor in the control room:

A4.01 Pressure gauges 103 Containment X 103 Containment System 3.1 Q55 K4 Knowledge of containment system design feature(s) and/or interlock(s) which provide for the following: i K4.06 Containment isolation system I KIA Category Point Totals: 4 2 3 51 311 II I 21 31 3 I I I Groue Point Total: I 28/5 I

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

System # / 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 011 Pressurizer Level Control 014 Rod Position Indication

! 015 Nuclear Instrumentation I I 016 Non-nuclear Instrumentation X 016 Non-Nuclear Instrumentation System 3.1 Q56 (NNIS)

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

K1.10 CCS re Temperature Monitor I

027 Containment Iodine Removal 028 Hydrogen Recombiner .~

and Purge Control 029 Containment Purge 033 Spent Fuel Pool Cooling X 033 Spent Fuel Pool Cooling System 2.7 Q57 (SFPCS)

A1 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with Spent Fuel Pool Cooling System operating I the controls including:

A 1.01 Spent fuel pool water level 034 Fuel Handling Equipment X 034 Fuel Handling Equipment System 3.5 Q58 (FHES)

A4 Ability to manually operate and/or monitor in the control room:

A4.02 Neutron levels 035 Steam Generator X 035 Steam Generator System (S/GS) 3.2 Q59 K6 Knowledge of the effect of a loss or malfunction on the following will have on the S/GS:

K6.01 MSIVs

041 Steam Dump System (SDS) and 041 Steam Dump/Turbine X Turbine Bypass Control 3.3 Q60 Bypass Control A3 Ability to monitor automatic operation of the SDS, including:

A3.02 RCS pressure, RCS temperature, and reactor power 045 Main Turbine Generator (MT/G) 045 Main Turbine Generator X System 4,6 Q61 2.4.49 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

055 Condenser Air Removal 056 Condensate X 056 Condensate System 2.6 Q62 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 X 068 Liquid Radwaste System (LRS) 2.7 Q63 K1 Knowledge of the physical connections and/or cause effect relationships between the Liquid Radwaste System and the following systems:

K1.07 Sources of liquid wastes for LRS 071 Waste Gas Disposal I

072 Area Radiation Monitoring I 075 Circulating Water X 075 Circulating Water System 3.0 Q64 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the circulating water system; and (b) based on those predictions, use procedures to correct, control. or mitigate the consequences of those malfunctions or operations:

J A2.01 Loss of intake structure 079 Station Air 086 Fire Protection X 086 Fire Protection System (FPS) 3,0 Q65 A4 Ability to manually operate and/or monitor in the control room:

A4.05 Deluge valves I

IDo 0 ,II I 2 1 2 I Group Point Total: 10/3

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

Category KJA# Topic RO SRO-Only IR # IR #

2.1. 2.1.5 Ability to use procedures related to shift staffing. such as 2.9* Q66 minimum crew complement, overtime limitations, etc,

1. 2.1. 2.1.6 Ability to manage the control room crew during plant 3.8* Q67 Conduct transients.

of Operations 2.1.

2.1.

2.1.

2.1. ,

Subtotal 2 I 2.2. 2.2.20 Knowledg'= ofthe process for managing troubleshooting 2.6 Q68 activities. I 2.2. 2.2.42 Ability to recognize system parameters that are entry- 3.9 Q69

2. level conditions for Technical Specifications.

Equipment Control 2.2. 2.2.38 Knowledg'= of conditions and limitations in the facility 3.6 Q70 license.

2.2.

2.2.

2.2. I Subtotal 3 2.3. 2.3.4 Knowledge of radiation exposure limits under normal or 3.2 Q71 I emergency conditions.

2.3. 2.3.12 Knowledge of radiological safety principles pertaining to 3.2 Q72

3. licensed operator duties, such as containment entry Radiation requirements, fuel handling responsibilities, access to locked Control high-radiation areas, aligning filters, etc.

2.3.

2.3. i 2.3. U 2.3.

Subtotal 2 2.4. 2.4.8 Knowledge of how abnormal operating procedures are 3.8 Q73 used in conjunction with EOPs. I

4. 2.4. 2.4.41 Knowledge of the emergency action level thresholds and 2.9 Q74 Emergency classifications. I Procedures I Plan 2.4. Ability to v,erify system alarm setpoints and operate 4.2 Q75 Is identified in the alarm response manual.

2.4.

2.4.

Ii 2.4.

I Subtotal 3 Tier 3 Point Total 10 7

ES-401 PWR Examination Outline Form ES-401-2 II SEABROOK Date of Exam: 7/12/13 7/19/13 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 I 3 4 Plant

~l Evolutions ier Totals 3 7 10 1

I I 28 2 3 5 2.

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

3. Generic Knowledge and Abilities Categories 1 ~l 2 3 4 10 jJ 2 I

3 2

4 2

7 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 (Le., 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 KlAs having an importance rating (lR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.

7.* The generic (G) KlAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicablEl evolution or system. Refer to Section D.1.b of ES-401 for the applicable KlAs.

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.

U

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 Em~ E,o'"tion, - Tie, lIGm"o 1 IRO I SRO)

E/APE # 1 Name 1 Safety Function K K A A G KIA Topic(s) IR #

1 2 1 2 000007 (BW/E02&E10; CE/E02) Reactor Trip - Stabilization Recovery 11

~ X 007 Reactor Trip 4.0 Q76 2.1.32 Ability to explain and apply system limits and precautions.

000008 Pressurizer Vapor Space Accident 1 3 000009 Small Break LOCA 1 3 X 009 Small Break LOCA 3.4 Q77 EA2 Ability to determine or interpret the following as they apply to a small break LOCA:

EA2.15 RCS parameters 000011 Large Break LOCA 1 3 000015/17 RCP Malfunctions 14 000022 Loss of Rx Coolant Makeup 1 2 000025 Loss of RHR System 1 4 000026 Loss of Component Cooling Water 1 8 000027 Pressurizer Pressure Control System Malfunction 13 000029 A TWS 1 1 038 Steam Generator Tube Rupture (SGTR) 000038 Steam Gen. Tube Rupture 1 3

~X 4.8 Q78 EA2 Ability to determine or interpret the following as they apply to a SGTR:

EA2.07 Plant conditions, from survey of control room indications 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) 4.6 Q79 Feedwater I 4 2.4.41 Knowledge of the emergency action level thresholds and classifications.

000055 Station Blackout 16 000056 Loss of Off-site Power I 6 000057 Loss of Vital AC Inst. Bus 16 000058 Loss of DC Power I 6 000062 Loss of Nuclear Svc Water I 4 X 062 Loss of Nuclear Service Water 4.7 Q80 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

II Loss of Instrument Air I 8 I W/E04 LOCA Outside Containment I 3 Westinghouse E11 Loss of Emergency Coolant W/E11 Loss of Emergency Coolant X Recirculation 4.7 Q81 Recirc./4 2.4.4 Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures. I BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink 14 000077 Generator Voltage and Electric Grid Disturbances 16

')

J I: 18/6

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

E/APE # / Name / 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 / 1 000005 Inoperable/Stuck Control Rod / 1 000024 Emergency Boration / 1 000028 Pressurizer Level Malfunction /2 000032 Loss of Source Range NI / 7 000033 Loss of Intermediate Range NI / 7 000036 (BW/A08) Fuel Handling Accident / 8 X 036 Fuel Handling Incidents 4.5 Q82 2.2.39 Knowledge of less than or equal to one hour Technical Specification action statements for systems.

000037 Steam Generator Tube Leak / 3 000051 Loss of Condenser Vacuum /4 000059 Accidental Liquid RadWaste ReI. / 9 000060 Accidental Gaseous Radwaste ReI. /9 000061 ARM System Alarms / 7 000067 Plant Fire On-site / 8 X 067: Plant fire on site 4.0 Q83 2.4.18 Knowledge of the specific bases for EOPs.

000068 (BW/A06) Control Room Evac. / 8 000069 (W/E14) Loss of CTMT Integrity / 5 000074 (W/E06&E07) Inad. Core Cooling /4 000076 High Reactor Coolant Activity / 9 Westinghouse E02 SI Termination W/E01 & E02 Rediagnosis & SI Termination / 3 X 4.0 Q84 EA2. Ability to determine and interpret the following as they apply to the (SI Termination)

EA2.2 Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

W/E13 Steam Generator Over-pressure / 4 W/E15 Containment Flooding / 5 W/E16 High Containment Radiation / 9 BW/A01 Plant Runback / 1 BW/A02&A03 Loss of NNI-XIY / 7 BW/A04 Turbine Trip /4 BW/A05 Emergency Diesel Actuation / 6 BW/A07 Flooding / 8 BW/E03 Inadequate Subcooling Margin /4 BW/E08; W/E03 LOCA Cooldown - Depress. /4

,1 BW/E09; CE/A13; W/E09&E10 Natural Circ./4 BW/E13&E14 EOP Rules and Enclosures Westinghouse EOa Pressurized Thermal CE/A11; W/E08 RCS Overcooling PTS 1 4 X 4.3 Q85 Shock 2.4.20 Knowledge of the operational implications of EOP warnings, cautions, and notes.

CE/A16 Excess RCS Leakage/2 I I KIA Category Point Totals: 1 3 Group Point Total: 9/4

ES-401 4 Form ES-401-2 PWR Examination Outline Form ES-401-2 Plant S stems - Tier 2/Grou J 1 (RO / SRO)

System # f Name K 1

K 2

K 3 4 K K 5 K 6 ~I ~I A 3

A 4

G KIA Topic(s) IR #

003 Reactor Coolant Pump 004 Chemical and Volume I Control j 005 Residual Heat Removal X 005 Residual Heat Removal System 3,7 Q86 (RHRS)

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

A2.02 Pressure transient protection during cold shutdown 006 Emergency Core Cooling 007 Pressurizer Relief/Quench Tank 008 Component Cooling Water X 008 Component Cooling Water System 4,7 Q87 (CCWS) 2.2.40 Ability to apply Technical Specifications for a system, 010 Pressurizer Pressure Control 012 Reactor Protection 013 Engineered Safety Features Actuation ~

022 Containment Cooling 025 Ice Condenser

039 Main and Reheat Steam 059 Main Feedwater 061 Auxiliary/Emergency Feedwater 062 AC Electrical Distribution 063 DC Electrical Distribution 064 Emergency Diesel Generator 073 Process Radiation

076 Service Water ) X 076 Service Water System (SWS) 4.1 Q89 2.4.30 Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the i

NRC, or the transmission system i operator.

078 Instrument Air X 078 Instrument Air System (lAS) 2.9 Q90 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the lAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

i i A2.01 Air dryer and filter malfunctions 103 Containment

, KIA Category Point Totals: 2 3 I Group PointTotai: 28/5

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant S stems - Tier 21Group 2iRO / SRO)

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

1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive 002 Reactor Coolant 011 Pressurizer Level Control ~

014 Rod Position Indication

  • 015 Nuclear Instrumentation 016 Non-nuclear Instrumentation I 017 In-core Temperature Monitor 027 Containment Iodine Removal 028 Hydrogen Recombiner X 028 Hydrogen Recombiner and Purge 4.6 Q91 and Purge Control Control System (HRPS) 2.1.20 Ability to interpret and execute I procedure steps. I 029 Containment Purge 033 Spent Fuel Pool CoolinQ 034 Fuel Handling Equipment X 034 Fuel Handling Equipment System 3.3 Q92 (FHES)

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

i i K4.03 Overload protection 035 Steam Generator 041 Steam DumplTurbine Bypass Control

  • 045 Main Turbine Generator i 055 Condenser Air Removal 056 Condensate 068 Liquid Radwaste 071 Waste Gas Disposal 072 Area Radiation Monitoring X 072 Area Radiation Monitoring (ARM) 4.6 Q93 System i 2.2.42 Ability to recognize system i i parameters that are entry-level conditions for Technical Specifications. I 075 Circulating Water I 079 Station Air 086 Fire Protection I

III I KIA Category Point Totals: Group Point Total: 101 3

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

I Category KlA# I I

Topic RO SRO-Only I IR # IR #

2.1. I 2.1.4 Knowledge of individual licensed operator responsibilities 3.8 Q94

! related to shift staffing, such as medical requirements, "no-solo*

1. operation, maintenance of active license status, 10CFR55, etc. I Conduct 2.1. 2.1.41 Knowledge of the refueling process. 3.7 Q95 of Operations I I 2.1. 0 2.1.

I I 2.1.

2.1.

I Subtotal 2 2.2. 2.2.36 Ability to analyze the effect of maintenance activities, Q96 such as degraded power sources, on the status of limiting l4.2 conditions for operations. I I

2. 2.2.

Equipment Control 2.2.

2.2.

2.2.

2.2.

Subtotal 1 2.3. 2.3.5 Ability to use radiation monitoring systems, such as fixed 2.9 Q97 radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

3. 12 i .3. 2.3.11 Ability to control radiation releases. 4.3 Q98 Radiation Control  ! 2.3. ()

u

! 2.3.

2.3.

I* 2.3.

Subtotal 2 I 2.4. 2.4.5 Knowledge of the organization of the operating procedures 4.3 Q99 network for normal, abnormal, and emergency evolutions.

4. 2.4. 2.4.40 Knowledge of SRO responsibilities in emergency plan 4.5 QI00 Emergency implementation.

Procedures I Plan 2.4.

2.4.

2.4.

I 2.4.

Subtotal 2 Tier 3 Point Total 10 7 o

ES-401 Record of Rejected KlAs Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected KIA RO 027 PZR Press AA1.04 is Pressure recovery using emergency only heaters. Seabrook control system malt. does not have emergency only heaters.

1/1 AA1.04 Randomly selected AA1.03 Pressure control when on a steam bubble for replacement.

SRO 076 High Reactor 076 A2 was randomly selected for SRO exam. RO exam already contains Coolant Activity. A2 this KA in same Tier/Group.

1/2 Randomly seljlcted 036 Fuel HandlingAccident 2.2.39 as replacement.

RO BW/A01 Plant This is not applicable to Seabrook.

I Runback 1/2 Rejected and randomly selected W/E15 Containment Flooding.

RO BW/A02&A03 Loss of i This is not applicable to Seabrook.

NNI-XIY 1/2 Rejected and randomly selected 076 High Reactor Coolant Activity.

RO . BW/A05 Emergency This is not applicable to Seabrook .

Diesel actuation 1/2 Rejected and randomly selected W/E03 LOCA Cooldown - Depress.

RO 009 Small Break Randomly selected, EA2 Ability to determine or interpret the following as LOCA they apply to a small break LOCA: EA2.28 Leak rate, from change in 1/2 reactor coolant drain tank level. System interrelations and piping sizes make it unlikely to get flow to the RCDT that meet the Small Break LOCA criteria .

. Randomly selected EA2.36 Difference between overcooling and LOCA i indications.

RO 063 D.C. Electrical Randomly selected, A1 Ability to predict and/or monitor changes in Distribution parameters associated with operating the DC electrical system controls 2/1 including: A1.01 Battery capacity as it is affected by discharge rate. This is too similar to already selected 055 EK3.01. Station Blackout, Length of time for which battery capacity is designed.

Since only otl<l'er item for 063 A 1 is <2.5, randomly selected new KA. K3 Knowledge of the effect that a loss or malfunction of the DC electrical system will have on the following: K3.02, Components using DC control power.

RO 005 Residual Heat Randomly selected A4 Ability to manually operate and/or monitor in the Removal System control room: A4.03, RHR temperature, PZR heaters and flow, and 2/1 (RHRS) nitrogen. This KA describes a process of nitrogen bubble in PZR to start RCPs for bubble generation that Seabrook station does not employ.

Randomly reselected K4 Knowledge of RHRS deSign feature(s) and/or interlock(s) which provide or the following: K4.10, Control of RHR heat exc:hanger outlet flow RO 006 Emergency Core A4 Ability to manually operate and/or monitor in the control room: A4.04, Cooling System RHRS. Tier 2 Group 1 Plant systems 005, Residual Heat Removal System 2/1 (ECCS (RHRS) already has 2 KA's selected for the RHR system.

I I Randomly selected A4.07, ECCS pumps and valves to balance exam.

RO 022 Containment Generic 2.4.~ Knowledge of low power/shutdown implications in accident Cooling System (e.g., loss of coolant accident or loss of residual heat removal) mitigation 2/1 strategies. CCS is not a part of the accident mitigation strategy at Seabrook. It is tripped and locked out for SIILOP.

Randomly reselected Generic 2.1.20, Ability to interpret and execute procedure steps.

SRO W/E08 Pressurized Randomly selected Generic 2.4.4, Ability to recognize abnormal indications Thermal Shock for system operating parameters that are entry-level conditions for 1/2 emergency and abnormal operating procedures. 2.4.4 is not a KA that supports an SRO only question (ie entry conditions for major EOP is RO level).

I Randomly reselected Generic 2.4.20, Knowledge of the operational

  • implications of EOP warnings, cautions, and notes.

SRO 2.4 Emergency Randomly selected Generic 2.4.1 Knowledge of EOP entry conditions and Procedures / Plan imm4~diate action steps. This KA does not support SRO only questions.

3 Randomly reselected Generic 2.4.5 Knowledge of the organization of the operating procedures network for normal, abnormal, and emergency evolutions.

SRO 2.4 Emergency Randomly selected Generic 2.4.50 Ability to verify system alarm setpoints Procedures / Plan and operate cpntrols identified in the alarm response manual. This KA has 3 already been\6elected for Tier 3 in the RO exam.

Randomly reselected Generic 2.4.40 Knowledge of SRO responsibilities in emergency man immementation.

SRO 009 Small Break Randomly selected EA2 Ability to determine or interpret the following as LOCA they apply to a small break LOCA: EA2.37 Existence of adequate natural 1/1 circulation. This is too similar to 056 AK1.01 (Loss of Offsite Power.

Knowledge of the operational implications of the following concepts as they apply to Loss of Offsite Power: Principle of cooling by natural convection) on the RO exam.

I Randoml~reselected EA2.15 RCS parameters.

SRO 034 Fuel Handling Randomly selected K3 Knowledge of the effect that a loss or malfunction of Equipment System the Fuel Handling System will have on the following: K3.01 Containment 2/2 ventilation. FH malfunctions interact with containment ventilation via CVI.

RO exam already contains a question very similar under KA 103 K4.06 (Containment System, Knowledge of containment system design feature(s) and/or interlock(s) which provide for the following: Containment isolation system).

Randomly reselected K4 Knowledge of design feature(s) and/or interlock(s) which provide for the following: K4.03 Overload protection.

RO 005 Residual Heat Randomly selected Ai Ability to predict and/or monitor changes in Removal System parameters (to prevent exceeding design limits) associated with operating 2/1 (RHRS) the RHRS c~trols including: A1.07 Determination of test acceptability by comparison 0 recorded valve response times with Tech-Spec requirements. This KA is more oriented to the operating exam and an operationally valid written question was not able to be generated.

Randomly reselected 005 Residual Heat Removal System (RHRS). K1 i Knowledge of the phYSical connections and/or cause effect relationships between the RHRS and the following systems: K1.04 CVCS

RO 007 Pressurizer Relief Randomly selected K3 Knowledge of the effect that a loss of malfunction of Tank/Quench Tank the PRTS will have on the following: K3.01 Containment. Question 2/1 System development difficult to generate at a discriminating level. Requested by NRC to reselect KIA, a different system from the same Tier/Group.

Randomly selected 064 Emergency Diesel Generators (ED/G). Kept the same K3.01. Knowledge of the effect that a loss or malfunction of the EDG

, system will have on the following: Systems controlled by automatic loader.

RO 2.2 Equipment Control Randomly selected 2.2.22 Knowledge of limiting conditions for operations and safety limits. Question submitted was not discriminative. NRC 3 requested selection of new KIA.

Randomly re~lected 2.2.42 Ability to recognize system parameters that are entry-level conditions for Technical Specifications .

u

ES-301 Administrative Topics Outline Form ES-301-1 Seabrook Station 2013 NRC Exam JPM - RO Facility: Seabrook Date of Examination: Jul~ 2013 Examination Level: RO fZI SRO 0 Operating Test Number:

Administrative Topic (see Note)

Type Code*

! Describe activity to be performed Manual QPTR Calculation with fault (RX1703)

R,M KA: 2.1.7 Ability to evaluate plant performance and Conduct of Operations make operational judgments based on the operating c.haracteristics, reactor behavior, and instrument i interpretation.

Calculate a blended makeup for the Spent Fuel Pool.

(RS1735)

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

Shutdown Margin Calculation for Mode 3 (RX1707)

R,M KA: 2.2.12 Knowledge of Surveillance Procedures Equipment Control Initiate a Liquid Effluent Waste Sample Request (form CP 4.1A)

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

I Emergency Procedures/Plan NOTE: All items (5 total) are requirecl 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)

Page 1 of 1

ES-301 Administrative Topics Outline Form ES-301-1 Seabrook Station 2013 NRC Exam JPM - SRO-I Facility: Seabrook Date of Examination: July' 2013 Examination Level: RO 0 SRO ~ Operating Test Number:

Administrative Topic Type Describe activity to be performed I

(see Note) Code" Verify Manual QPTR Calculation with fault (RX1703)

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 a calculated blended makeup for the Spent Fuel Pool. (RS1735)

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

Review Shutdown Margin Calculation for Mode 3 (RX1707)

Equipment Control R,M KA: 2.2.12 Knowledge of Surveillance Procedures Verify a Liquid Effluent Waste Sample Request (Form CP 4.1 A)

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

Determine Emergency Action Level-PARS Emergency Procedures/Plan R,M KA: 2.4.40 Knowledge of the Emergency Plan I

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.

i

.. 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 (2: 1)

(P)revious 2 exams (~ 1, randomly selected)

Page 1 of 1

ES-301 Administrative Topics Outline Form ES-301-1 Seabrook Station 2013 NRC Exam JPM - SRO-U Facility: Seabrook Date of Examination: Jul~ 2013 Examination Level: RO 0 SRO rgj Operating Test Number:

Administrative Topic Type Describe activity to be performed (see Note) Code* I Verify Manual QPTR Calculation with fault (RX1703)

Conduct of Operations R,M KA: 2.1.7 Ability to evaluate plant performance and make operational judgments based on the operating characteristics, reactor behavior, and instrument interpretation.

Approve a calculated blended makeup for the Spent Fuel Pool. (RS1735)

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

Review Shutdown Margin Calculation for Mode 3 (RX1707)

Equipment Control R,M KA: 2.2.12 Knowledge of Surveillance Procedures Verify a Liquid Effluent Waste Sample Request (Form CP 4.1A)

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

Determine Emergency Action Level-PARS 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. i

  • 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)re,vious 2 exams (S 1; randomly selected)

Page 1 of 1

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Seabrook Station 2013 NRC Exam JPM - RO Facility: Seabrook Date of Examination: Jul:l 2013 Exam Level: RO !8l SRO-IO SRO-U 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. PZR Level Channel fails LOW (JPM A) D,S 7
b. Transfer of SW from the Ocean to the Cooling Tower i A,M,S 4 (Secondary)

(JPM B)

c. Post LOCA Cool-down PORVoperations (JPM C) A,D,E,S 3
d. Transfer FAH to the Fuel Handling mode (JPM D) D,S 8
e. ASOV fails open ("IPM E) A,N,S 4 (Primary)
f. Raise SI Accumulator Pressure (JPM F) D,S,EN 2 i
g. Establish Charging and Letdown (JPM G) A,M,E,S 1
h. Restore offsite power to Emergency Bus 6 (JPM H) E,M,S 6 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
a. DC Start of Elgars UPS A,D,L 6
b. Locally close MSIV D,E 5
c. Align Alternate (Demin) Cooling to CCP Lube Oil Cooler D,E,R 8  !

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 1 SRO-II SRO-U (A)ltemate path 4-6 1 4-6 1 2-3 (C)ontrol room (D)irect from bank $9/$8/$4 (E)mergency or abnormal in-plant 01;1/01;1/01;1 (EN)gineered safety feature 1 - 1 ~1 (control room system)

(L)ow-Power 1 Shutdown ~1/~1/~1 (N)ew or (M)odified from bank including l(A) 01;2/2:2/~1 (P)revious 2 exams $ 3 1 $ 31 $ 2 (randomly selected)

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

ES-301 Control Roomlln-Plant Systems Outline Form ES-301*2 Seabrook Station 2013 NRC Exam JPM - SRO-I Facility: Seabrook Date of Examination: Jul~ 2013 Exam Level: RO 0 SRO-I 1.81 SRO-U 0 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 I a. PZR Level Channel fails LOW (JPM A) D,S 7

b. Transfer of SW from the Ocean to the Cooling Tower A,M,S 4 (Secondary)

(JPM B)

I i

c. Post LOCA Cool-down PORV operations (JPM C) A,D,E,S 3
d. Transfer FAH to the Fuel Handling mode (JPM D) D,S 8
e. ASDV fails open (JPM E) A,N,S 4 (Primary)
1. Establish Charging and Letdown (JPM G) i A,M,E,S 1
g. Restore offsite power to Emergency Bus 6 (JPM H) E,M,S 6 In-Plant Systems@ (3 for RO); (3 for SRO-I); (:3 or 2 for SRO-U)

A,D,L 6

! a. DC Start of Elgars UPS

b. Locally close MSIV D,E 5 D,E,R 8
c. Align Alternate (Demin) Cooling to CCP Lube Oil Cooler I 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 ! SRO-I! SRO-U (A)lternate path 4-6 ! 4-6 / 2-3 (C)ontrol room (D)irect from bank  !>9/!>8/!>4 (E)mergency or abnormal in-plant  ;::1/;::1/;::1 (EN)gineered safety feature  ! - I ;::1 (control room system)

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

{P)revious 2 exams  !> 3 I !> 3 I !> 2 (randomly selected)

I (R)CA  ;::1/;::1/;::1 II (S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Seabrook Station 2013 NRC Exam JPM - SRO-U Facility: Seabrook Date of Examination: Jul'l2013 Exam Level: RO 0 SRO-ID SRO-U f8I 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 I Type Code* Safety Function

a. Establish Charging and Letdown (..!PM G) A,M,E,S 1
b. Raise SI Accumulator Pressure (JPM F) D,S,EN 2 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) I
a. DC Start of Elgars UPS A,D,L 6
b. Locally close MSIV D,E 5 I
c. Align Alternate (Demin) Cooling to CCP Lube Oil Cooler D,E,R 8 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 { SRO-I { SRO-U (A)ltemate path 4-6/4-6/2-3 (C)ontrol room (D)irect from bank S9/S8{S4 (E)mergency or abnonnal in-plant ~1/~1/~1 (EN)gineered safety feature { ~1 (control room system)

(L)ow-Power 1 Shutdown ~1{~1{~1 (N)ew or (M)odified from bank including 1(A) ~2/~2/~1 (P)revious 2 exams S 3 1S 31 S 2 (randomly selected)

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

Appendix D Scenario Outline Form ES-D-1 Seabrook Station 2013 NRC Exam-Simulator Scenarios Facility: Seabrook Scenario No.: 1 Op-Test No.:

Examiners: D. Silk Operators:

Initial Conditions: MOL 55% power, stable xenon, CB D at 200 steps with both Main feed Pumps and one Heater Drain pump is in service (IC38).

Turnover:

  • Plant has been at 55% power for 3 days for maintenance.
  • Maintenance is complete and power increase has been authorized.
  • Procedure OS1000.05, Power Increase is being performed and is completed to step 4.2.39.
  • Maintain AFD on target.
  • Increase power to 75% at 5%/hour.

Event Malf. No. Event Event I No. Type* Description 1 PSOR Crew begins a 5%/hr power increase.

BOPN USN 2 ItFWLT551 BOPI 'A' SG Level Instrument controlling channel fails low.

USI, TS 3 cCCV341 PSOC CC-V-341 fails closed. Crew is forced to use excess letdown.

USC 4 mfSM001 PSOC Seismic event causes rod H8 to drop.

mfCP018 80PC I USC, TS I 5 USTS CBS-P-98 INOP. (Will cause entry into FR-Z.1 later.) I 6 mfCP011 PSOM While I&C is checking fuses for dropped rod recovery, rod F8 drops, mfMS049C BOPM requiring a manual reactor trip. On reactor trip the 'C' SG faults inside USM containment. ~

I I 7 mfCS002 PSOC When SI occurs, CS-P-2A trip and lockout. CS-P-2-B blocked from .

L mfCS016 starting on SI. CS-P-2B must be manually started by PSO. I 8 FWFV4234A BOPC Defeat the auto isolation for the 'C' SG. Manual action to close the I

'I I FWFV42348 valves will be required. I I * (N)ormal, (R)eactlVlty, (l)nstrumen1., (C)omponent, (M)aJor Note: Anticipated AOP/EOP flow-path: OS1235.03, OS1202.01, OS1210.05, E-O, ES-0.1 pOSSible, E-O, E-2, FR-Z.1, E-2, E-1, ES-1.1

Appendix D Scenario Outline Form ES-D-1 Seabrook Station 2013 NRC Exam-Simulator Scenarios Facility: Seabrook Scenario No.: 2 Op-Test No.:

Examiners: D. Silk Operators:

Initial Conditions: MOL 75% power, power increase in progress, CB D at 207 steps with both Heater Drain pump in service (IC32).

Turnover:

  • Plant is at 75% power.
  • Procedure OS1000.05, Power Increase is being performed and completed up to step 4.2,49.
  • Raise power at 10% per hour.
  • Maintain AFD on target.

Event Malt. No. Event Event No. Type* Description I

1 PSOR Crew begins a 10%/hr power increase.  !

BOPN USN 2 ptFWPT505 PSOI MS-PT-505 fails high causing outward rod motion.

BOPI US I, TS 3 mfSW014 BOPC SW-P-41-A trip and lockout, standby pump C fails to auto start and cSWV20 US C, TS cannot be manually started requiring manual TA. SW-V-20 fails to mfSWOO1 auto actuate but can be manually aligned, 4 mfRC020 PSOC 'A' RCP vibration ramps up, requiring a reactor trip.

I USC 5 mfRC050A PSOM When 'A' RCP is secured after immediate actions, trigger starts 300 I mfED038 BOPM USM gpm RCP seal leak (simulated with int leg leak).

Also triggers a loss of offsite power. 'B' EDG trips due to lube oil failure.

6 mfED031 mfED034 BOPC 'A' EDG fails to auto start, Operator emergency starts using the slave relay in ECA-O.O. SW-V-16 fails to automatically open and may be I

I opened manually.

(l)ns_t_ru_m_e_n_t_,_(c_)_o_m_p_o_ne_n_t,_(_M_)a_~O_r 7 mfCC012 PSOC CC-P-11-A fails to auto start. RMO must be reset and either A Train CC eume may be started manually.

bonna,.(R)eactiV,ty. _ _ _ _ _ _ _ _ _ _ _,_ _----'

Note: Anticipated AOP/EOP flow-path: OS1235.05, OS1216.01, OS1202.01, E-O, ECA-O.O, E-O, E-1

Appendix 0 Scenario Outline Form ES-D-1 Seabrook Station 2013 NRC Exam-Simulator Scenarios Facility: Seabrook Scenario No.: 4 Op-Test No.:

Examiners: D. Silk Operators:

Initial Conditions: IVIOL 100% power, Rods in Auto, CB 0 at 230 steps (IC30).

Turnover:

  • Plant is at 100% power.
  • Experiencing intermittent high vibrations on A MFP. Begin 1O%/hr down power to 50% when take the watch. OS1 000.06 complete up to step 4.3.

Event Malf. No. Event Event No. Type* Description 1 PSOR Crew begins a 1O%/hr power decrease.

BOPN USN 2 cCCP322B PSOC CC-P-322-B trips and standby pump fails to auto start, can be started cCCP322A USC manually.

3 mfED025 PSOC Loss of EDE-PP-1A due to EDE-I-1A failure. Instrument Bus 1A BOPC . recovered on maintenance supply. Requires manual control of FRV's US C,TS and charging.

4 ptRCPT455 USTS On loss of EDE-PP-1A, PC-PT-455 will fail low. This will be I discovered when Instrument Bus 1A is recovered on its maintenance I supply.

5 mfAR005B BOPC AR-P-50-B trips, auto start of third blocked but can be manually USC started.

6 mfFW038 PSOM FW-P-32-A trips. Power level too high for Setback to be successful.

bkCPRTA BOPM Auto and Manual Rx trips blocked resulting in A TWS.

I bkCPRTA USM i

7 mfCP005 PSOC Auto rod insertion blocked, manual rod insertion required.

8 avMSVSV2 BOPC On manual turbine trip, turbine Stop Valve 2 and Control Valve 2 stick avMSVCV2 open, requiring manual MSI.

9 avRCPCV456A PSOC When crew enters ES-0.1 the A PORV will fail open. This will require the PSO to close the A PORV. It will not close and the PSO will close the A PORV Block Valve.

N)orm (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Note: Anticipated AOP/EOP flow-path: OS1000.06, OS1201.01, OS1247.01, OS1201.05, VAS F5118, ON1233.01, OS1231.03 (possible), E-O, FR-S.1, E-O, ES-0.1

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