ML12299A226

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Final Outlines (Folder 3)
ML12299A226
Person / Time
Site: Beaver Valley
Issue date: 09/18/2012
From: Rudolph W
FirstEnergy Nuclear Operating Co
To: David Silk
Operations Branch I
Jackson D
Shared Package
ML12136A033 List:
References
TAC U01850
Download: ML12299A226 (30)
v • d • e


Text

ES*401 PWR Examination Outline Form ES-401*2 Facility: BVPS UNIT 2 RO Date of Exam 9/24 thru 10/5 2012 Points Tier Group K K K A

A A

G 1

2 3

2 3

4

1.

1 3

3 3

3 18 Emergency 2

1 1

1 9

Abnormal Plant Evolutions Tier Totals 4 4 4

2.

1 3

2 3

3 2

3 2

2 Plant Systems 2

2 1

1 1

1 1

0 0

1 1

10 Tier 5 3 4 4 3 3 4 3 2 3 4 38 Totals 1

2 3

4

3. Generic Knowledge and 10 Abilities Category 3

2 2

3 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 KlAs having an importance rating (IR) of 2.5 or higher shall be selected.

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

6.

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

7.*

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

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.

NUREG-1021, ReviSion 9 Supplement 1 RO Page 1 of 13 FENoe FaCSimile Rev. AG

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

~=======================F=F~=F=

E/APE # / Name 1Safety Function 000008 Pressurizer Vapor Space Accident 1 3

[Question 1]

000009 Small Break LOCA 13

[Question 2]

000015/000017 Reactor Coolant Pump (RCP) Malfunctions 14

[Question 3]

000022 Loss of Reactor Coolant Makeup I 2

[Question 4]

000025 Loss of RHR System 14

[Question 5]

000027 Pressurizer Pressure Control System Malfunction 13

[Question 6]

000029 A TWS 11

[Question 7]

000038 Steam Generator Tube Rupture I 3

[Question 8]

000040 Steam Line Rupture - Excessive Heat Transfer 14

[Question 9]

KIA Topic(s}

IR AK2 Knowledge the interrelations between the Pressurizer Vapor Space Accident and the following:

2.7 1

AK2.02 Sensors and detectors (CFR 41.7/45.7)

EA2 Ability to determine or interpret the following as they apply to a small break LOCA:

4.2 1

EA2.37 Existence of adequate natural circulation (CFR 43.5 145.13)

AK2 Knowledge of the interrelations between the Reactor Coolant Pump Malfunctions (Loss of RC Flow) and the following:

2.6 AK2.08 CCWS (CFR41.7/45.7) 2.2.39 Knowledge of less than or equal to one hour Technical Specification action statements for systems.

3.9 (CFR: 41.7/41.10/43.2/45.13)

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

AA1.11 Reactor building sump level indicators 2.9 (CFR 41.7/45.5/45.6)

AA 1 Ability to operate and lor monitor the following as they apply to the Pressurizer Pressure Control Malfunctions:

4.0 AA1.01 PZR heaters, sprays, and PORVs (CFR 41.7 145.5/45.6)

EK2 Knowledge the and the following an ATWS:

EK2.06 Breakers, relays, and disconnects 2.9*

1 (CFR 41.7 145.7)

EK3 Knowledge reasons for the following responses as the apply to the SGTR:

EK3.04 Automatic actions provided by each PRM 3.9 (CFR 41.5/41.10 145.6 / 45.13) 4.2 1

AK3.01 Operation of steam line isolation valves (CFR 41.5,41.10 145.6/45.13)

NUREG-1 021, Revision 9 Supplement 1 RO Page 2 of 13 FENoe Facsimile Rev. AG

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

~======================9=9=~~

E/APE # 1Name 1Safety Function 000054 Loss of Main Feedwater I 4

[Question 10]

000055 Station Blackout 16

[Question 11]

000057 Loss of Vital AC Electrical Instrument Bus 16

[Question 12]

000058 Loss of DC Power I 6

[Question 13]

065 Loss of Instrument Air I 8

'estion 14]

000077 Generator Voltage and Electric Grid Disturbances 16

[Question 151 W/E04 LOCA Outside Containment 13

[Question 16]

W/E05 Loss of Secondary Heat Sink 14

[Question 17]

KIA Topic(s)

AK1 Knowledge of the operational implications of the following concepts as they apply to Loss of Main Feedwater (MFW):

AK1.02 Effects offeedwater introduction on dry SIG (CFR 41.8/41.10 145.3)

EK1 the operationa the following concepts as they apply to the Station Blackout:

EK1.02 Natural circulation cooling (CFR 41.8/41.10 145.3) 2.4.4 Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

(CFR: 41.10/43.2/45.6)

AK owledge of the operational implications the following concepts as they apply to Loss of DC Power:

AK1.01 Battery charger equipment and instrumentation (CFR 41.8/41.10 145.3)

AK3 Knowledge the reasons the responses as they apply to the Loss of Instrument Air:

AK3.08 Actions contained in EOP for loss of instrument air (CFR 41.5,41.10 145.6/45.13)

AA2 Ability to determine and interpret the following as they apply to Generator Voltage and Electric Grid Disturbances:

AA2.03 Generator current outside the capability curve (CFR: 41.5 and 43.5145.5, 45.7, and 45.8) 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

(CFR: 41.10/43.5 145.2 I 45.6)

EA 1 Ability to operate and I or monitor the following as they apply to the (Loss of Secondary Heat Sink)

EA 1.2 Operating behavior characteristics of the facility.

(CFR: 41.7 I 45.5 I 45.6)

IR 3.6 4.1 1

4.5 2.8 3.7 3.5 4.3 3.7 NUREG-1021, Revision 9 Supplement 1 RO Page 3 of 13 FENoe Facsimile Rev. AG

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

~=======================r=r=r=F=

E/APE # I Name I Safety Function W/E11 Loss of Emergency Coolant Recirculation I 4

[Question 18]

KIA Category Point Totals:

KIA Topic(s)

EA2 Ability to determine and interpret the following as they apply to the (Loss of Emergency Coolant Recirculation):

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

(CFR: 43.5/45.13) 3 3

3 3

3 3

Group Point Total:

IR 3.4 NUREG-1021. Revision 9 Supplement 1 RO Page 4 of 13 FENoe Facsimile Rev. AG

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier lIGroup 2{RO)

E/APE # I Name I Safety Function KKK 123 000036 Fuel Handling Incidents 18

[Question 19]

000061 ARM System Alarms 17

[Question 20]

000067 Plant Fire On-site I 9

[Question 21]

000068 Control Room Evacuation I 8

[Question 22]

000076 High Reactor Coolant Activity 19

[Question 23]

Vv/E07 Saturated Core Cooling 14

[Question 24]

W/E08 RCS Overcooling - PTS 14

[Question 25]

E09 Natural Circulation Operations 14

[Question 26]

KIA Topic(s)

AA2 Ability to determine and interpret the following as they apply to the Fuel Handling Incidents:

AA2.02 Occurrence of a fuel handling incident (CFR: 43.5/45.13)

AA1. Ability to operate and lor monitor the following as they apply to the Area radiation Monitoring (ARM)

System Alarms:

AA1.01 Automatic actuation (CFR 41.7 145.5/45.6)

AK1 Knowledge of the operational implications of the following concepts as they apply to Plant Fire on Site:

AK1.02 Fire fighting (CFR 41.8 141.10 145.3)

AA 1 Ability to operate and I or monitor the following as they apply to the Control Room Evacuation:

AA 1.27 Local trip of main feed pumps and Condensate pumps (CFR 41.7 145.5/45.6) 2.1.31 Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.

(CFR:41.10/45.12)

EA 1 Ability to operate and I or monitor the following as they apply to the (Saturated Core Cooling):

EA 1.3 Desired operating results during abnormal and emergency situations.

(CFR: 41.7/45.5/45.6)

EK3 Knowledge of the reasons for the following responses as they apply to the (Pressurized Thermal Shock):

EK3.1 Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics.

(CFR: 41.5/41.10,45.6,45.13)

EA2 Ability to determine and interpret the following as they apply to the (Natural Circulation Operations)

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

(CFR: 43.5/45.13)

IR 3.4 3.6 3.1 3.2*

4.6 3.5 3.4 3.1 NUREG-1021, Revision 9 Supplement 1 RO Page 5 of 13 FENoe Facsimile Rev. AG

ES-401 PWR Examination Outline Form ES-401*2 Emergency and Abnormal Plant Evolutions* Tier 1/Group 2(RO) Continued 1F===========================T=~~=r~

E/APE # 1Name I Safety Function K

1 W/E14 High Containment Pressure 15

[Question 27]

KIA Category Point Totals:

KIA Topic(s)

EK2 Knowledge of the interrelations between the (High Containment Pressure) and the following:

EK2.1 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

(CFR: 41.7/45.7)

Group Point Total:

IR 3.4 NUREG-1021, Revision 9 Supplement 1 RO Page 6 of 13 FENoe Facsimile Rev. AG 9

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems

- Tier 2/Group 1 (RO)

System # / Name K K KIA Topic(s)

IR 1

2 003 Reactor Coolant Pump

[Question 28]

004 Chemical and Volume Control

[Question 29]

004 Chemical and Volume Control

[Question 30]

005 Residual Heat Removal

[Question 31]

005 Residual Heat Removal

[Question 32]

006 Emergency Core Cooling

[Question 33]

007 Pressurizer Relief/Quench Tank

[Question 34]

008 Component Cooling Water

[Question 35]

010 Pressurizer Pressure Control

[Question 36]

A 1 Ability to predict and/or monitor changes in 2.6 parameters (to prevent exceeding design limits) associated with operating the RCPS controls including:

A 1.03 RCP motor stator winding temperatures (CFR: 41.5/45.5)

K2 Knowledge of bus power supplies to the 2.9 1

following:

K2.02 Makeup pumps (CFR: 41.7)

K4 Knowledge of CVCS design feature(s) 2.8*

and/or interlock(s) which provide for the following:

K4.14 Control interlocks on letdown system (letdown tank bypass valve)

(CFR: 41.7) 2.1.32 Ability to explain and apply system 3.8 limits and precautions.

(CFR: 41.10 /43.2/45.12)

K1 Knowledge of the physical connections 3.3 and/or cause/effect relationships between the RHRS and the following systems:

K1.13SIS (CFR: 41.2 to 41.9/45.7 to 45.8)

K1 Knowledge of the physical connections 2.9*

and/or cause/effect relationships between the ECCS and the following systems:

K1.07 MFW System (CFR: 41.2 to 41.9/45.7 to 45.8)

A3 Ability to monitor automatic operation of the 2.7*

PRTS. including:

A3.01 Components which discharge to the PRT (CFR: 41.7 /45.5)

A1 Ability to monitor changes in 2.8 1

parameters (to prevent exceeding design limits) associated with operating the CCWS controls including:

A1.01 CCW flow rate (CFR: 41.5/45.5)

K6 Knowledge of the effect of a loss or 3.2 malfunction of the following will have on the PZR PCS:

K6.03 PZR sprays and heaters (CFR: 41.7/45.7)

NUREG-1021. ReviSion 9 Supplement 1 RO Page 7 of 13 FENoe Facsimile Rev. AG

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems F=========~======9F9F9=9=~~~

System # I Name 012 Reactor Protection

[Question 37]

013 Engineered Safety Features Actuation

[Question 38]

022 Containment Cooling

[Question 39]

026 Containment Spray

[Question 40]

039 Main and Reheat Steam

,stion 41]

059 Main Feedwater

[Question 42]

061 Auxiliary/Emergency Feedwater

[Question 43]

061 Auxiliary/Emergency Feedwater

[Question 44]

- Tier 2/Group 1 (RO) Continued KJA Topic(s)

IR 3.2*

nO~\\Ile(:lae of the effect of a loss or 2.7*

malfunction on the following will have on the ESFAS:

K6.01 Sensors and detectors (CFR: 41.7 145.5 to 45.8)

K2 Knowledge of power supplies to the 3.0*

following:

K2.01 Containment cooling fans (CFR: 41.7)

K4 Knowledge of CSS design feature(s) and/or 3.7*

interlock(s) which provide for the following:

K4.09 Prevention of path for escape of radioactivity from containment to the outside (interlock on RWST isolation after swapover).

2.7 K3 the effect that a loss or 3.6 malfunction of the MFW will have on the following:

K3.02 AFW system (CFR: 41.7/45.6)

K5 Knowledge of the operational implications 3.6 1

of the following concepts as the apply to the AFW:

K5.01 Relationship between AFW flow and ReS heat transfer (CFR: 41.5/45.7)

A 1 Ability to predict and/or monitor changes in 3.9 1

parameters (to prevent exceeding design limits) associated with operating the AFW controls including:

A1.01 S/G level (CFR: 41.5/45.5)

NUREG-1021, Revision 9 Supplement 1 RO Page 8 of 13 FENoe Facsimile Rev. AG

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems

- Tier 2/Group 1 (RO) Continued System # 1Name K

KIA Topic(s)

IR 1

062 AC Electrical Distribution A4 Ability to manually operate and/or monitor 3.1" 1

in the control room:

[Question 45]

A4.07 Synchronizing and paralleling of different ac supplies (CFR: 41.7/45.51 to 45.8) 062 AC Electrical Distribution K4 Knowledge of ac distribution system design 3.1 1

[Question 46]

feature(s) and/or interlock(s) which provide for the following:

K4.10 Uninterruptable ac power sources (CFR: 41.7) 063 DC Electrical Distribution 2.1.7 Ability to evaluate plant performance and 4.4

[Question 47]

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

063 DC Electrical Distribution to (a) predict the impacts 2.5

[Question 48]

following malfunctions or operations on the DC electrical systems; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.01 Grounds (CFR: 41.5/43.5/45.3/45.13) 064 Emergency Diesel Generator A2 Ability to (a) predict the impacts of the following malfunctions or operations on the 2.6" ED/G system; and (b) based on those

[Question 49]

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

A2.13 Consequences of opening auxiliary feeder bus (ED/G sub supply)

(CFR: 41.5/43.5 145.31 45.13) 064 Emergency Diesel Generator A4 Ability to manually operate and/or monitor in the control room:

3.2*

[Question 50]

A4.04 Remote operation of the air compressor switch (different modes)

(CFR: 41.7/45.5 to 45.8) 073 Process Radiation K3 Knowledge of the effect that a loss or 3.6 1

Monitoring malfunction of the PRM system will have on the following:

[Question 51J K3.01 Radioactive effluent releases (CFR: 41.7/45.6)

A3 Ability to monitor automatic operation of the 076 Service Water 3.7 SWS, including:

, [Question 52]

A3.02 Emergency heat loads (CFR: 41.7/45.5)

NUREG-1021, Revision 9 Supplement 1 RO Page 9 of 13 FENOC Facsimile Rev. AG

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems

- Tier 2/Group 1 (RO) Continued System # 1Name K

3 KIA Topic(s)

IR 078 Instrument Air

[Question 53]

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

3.3*

K1.03 Containment air (CFR: 41.2 to 41.9/45.7 to 45.8) 103 Containment

[Question 54]

A2 Ability to (a) predict the impacts of the following malfunctions or operations on the containment system and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations A2.03 Phase A and B isolation 3.5*

103 Containment

[Question 55]

(CFR: 41.5/43.5 145.3 145.13) 2.4.6 Knowledge of EOP mitigation strategies.

(CFR: 41.10/43.5/45.13) 3.7 KIA Category Point Totals:

3 2

3 28 NUREG-1 021, Revision 9 Supplement 1 RO Page 10 of 13 FENoe Facsimile Rev. AG

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems

- Tier 2/Group 2(RO)

System # / Name KKK KIA Topic(s)

IR 123 001 Control Rod Drive System

[Question 56]

015 Nuclear Instrumentation

[Question 57]

016 Non-nuclear Instrumentation

[Question 58]

017 In-Core Temperature Monitor System (ITM)

[Question 59]

041 Steam Dump System (SDS)

Turbine Bypass Control lI:.JUestion 60]

033 Spent Fuel Pool Cooling

[Question 61]

034 Fuel Handling Equipment

[Question 62]

055 Condenser Air Removal

[Question 63]

071 Waste Gas Disposal

[Question 64]

K2 Knowledge of bus power supplies to the following:

K2.05 M/G sets 3.1*

(CFR: 41.7) 2.2.37 Ability to determine operability and/or availability of safety related equipment.

(CFR: 41.7/43.5/45.12) 3.6 K5 Knowledge of the operational implication of the following concepts as they apply to the NNIS:

2.7*

K5.01 Separation of control and protection c:i rcu its (CFR: 41.5 /45.7)

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

3.7 A1.01 Core exit temperature (CFR: 41.5 /45.7)

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

K1.02 S/G level 2.7 (CFR: 41.2 to 41.9/45.7 to 45.8)

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

K4.05 Adequate SDM (boron concentration) 3.1 (CFR: 41.7)

K6 Knowledge of the effect of a loss or malfunction on the following will have on the Fuel Handling System:

K6.02 Radiation monitoring systems 2.6*

(CFR: 41.7/45.7)

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

2.6 K1.06 PRM system (CFR: 41.2 to 41.9 /45.7 to 45.8)

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

2.6*

A4.05 Gas decay tanks, including valves, indicators, and sample line (CFR: 41.7/45.5 to 45.8)

NUREG-1 021, Revision 9 Supplement 1 RO Page 11 of 13 FENoe Facsimile Rev. AG

ES-401 PWR Examination Outline Fonn ES-401-2 Plant Systems

- Tier 2/Group 2(RO) Continued System # / Name K

1 KIA Topic(s)

IR 075 Circulating Water

[Question 65]

K3 Knowledge of the effect that a loss or malfunctions of the circulating water system will have on the following:

K3.07 ESFAS 3.4*

(CFR: 41.7 145.6) 1 0

0 1

Group Point Total:

10 NUREG-1 021. Revision 9 Supplement 1 RO Page 12 of 13 FENoe Facsimile Rev. AG

01 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401*3

~ _,dhty: BVPS UNIT 2 RO Date ofExam 9/24 thru 10/5 2012 RO Category KlA#

Topic IR

1.

2.1.21 Ability to verify the controlled procedure copy.

3.5*

Conduct of Operations 1-----_~-:-[Q_:_u=e,_s_:_t-io-n-6_:6_:_]_(C,_F-R-:_41_,_10_':-4_5-;-.1-;-:0_:_'-45-.-,13-;}-;---:-----:-:-:------+---+--

2.1.8 Ability to coordinate personnel activities outside the control room.

3.4

[Question 67] (CFR: 41.10/45.5/45.12/45.13) 2.1.45 Ability to identify and interpret diverse indications to validate the 4.3 response of another indication.

[Question 68] (CFR: 41.7 '43.5 145.4)

Subtotal

2.

2.2.23 Ability to track Technical Specification limiting conditions for operations.

Equipment

[Question 69] (CFR: 41.10 143.2 145.13)

Control 2.2.36 lity to maintenance as 3.1 power sources, on the status of limiting conditions for operations.

[Question 70] (CFR: 41.10 143.2 145.13)

Subtotal

3.

2.3.14 Knowledge of radiation or contamination hazards that may arise during Radiation normal, abnormal, or emergency conditions or activities.

Control

[Question 71] (CFR: 41.12 143.4 145.1 O) 2.3.4 Knowledge of radiation exposure limits under normal or emergency 3.2 1

conditions.

[Question 72] (CFR: 41.12 143.4/45.10)

Subtotal

4.

2.4.3 Ability to identify post-accident instrumentation.

Emergency

[Question 73] (CFR: 41.6 145.4)

Proceduresl Plan 2.4.13 Knowledge of crew roles and responsibilities during EOP usage.

4.0 1

[Question 74] (CFR: 41.10 145.12) 2.4.34 Knowledge of RO tasks performed outside the main control room during 4.2 an emergency and the resultant operational effects.

[Question 75] (CFR: 41.10/43.5 145.13)

Subtotal Tier 3 Point Total NUREG-1021, Revision 9 Supplement 1 RO Page 13 of 13 FENoe Facsimile Rev. AG

ES-401 PWR Examination Outline Form ES-401 ~2 Facil' SRO ONL Y Points Tier Group A2 G*

TOTAL 1

3 3

6

1.

Emergency 2

3 1

4 Abnormal Tier Plant 6

4 10 Totals Evolutions 1

3 2

5

2.

Plant 2

Systems 1 1 1

3 Tier 5

3 8

Totals 1 2 3 4

3. Generic Knowledge and 7

Abilities Category 2 1 2 2 Note:

1.

Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two).

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 ES401 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 (IR) of 2.5 or higher shall be selected.

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

6.

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

7.*

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

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 ES401-3. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.

NUREG-1021, Revision 9 Supplement 1 SRO Page 1 of 6 FENoe Facsimile Rev. AG

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

E/APE # 1Name 1Safety Function K

1 KIA Topic(s)

IR 000007 Reactor Trip -Stabilization 11

[Question 76]

2.4.20 Knowledge of the operational implications of EOP warnings, cautions, and notes.

(CFR: 41.10/43.5/45.13) 4.3 000011 Large Break LOCA 13

[Question 77]

2.4.44 Knowledge of emergency plan protective action recommendations.

(CFR: 41.10/41.12/43.5/45.11) 4.4 000026 Loss of Component Cooling Water 1 8

steps.

to interpret and execute re 4.6

[Question 78]

(CFR: 41.10/43.5/45.12) 000056 Loss of Offsite Power 1 6

[Question 79]

AA2. Ability to determine and interpret the following as they apply to the Loss of Offsite Power:

AA2.45 Indicators to assess status of ESF breakers (tripped/not-tripped) and validity of alarms (false/not false) 3.9 (CFR: 43.5/45.13) 000062 Loss of Nuclear Service Water 1 4

[Question 80]

AA2. Ability to determine and interpret as they apply to the Loss of Nuclear Service Water:

AA2.01 Location of a leak in the SWS 3.5 (CFR: 43.5/45.13)

W/E12 Steam Line Rupture - Excessive Heat Transfer 14

[Question 81]

EA2. Ability to determine and interpret ng as they apply to the (Uncontrolled Depressurization of all Steam Generators) 4.0 EA2.1 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

(CFR: 43.51 45.13)

KIA Category Point Totals:

0 0

0 0

3 3

Group Point Total:

6 NUREG-1 021. Revision 9 Supplement 1 SRO Page 2 of 6 FENoe Facsimile Rev. AG

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2(SRO) 1F=======================r=r=

E/APE # I Name 1Safety Function 000003 Dropped Control Rod 11

[Question 82]

K 1

000074 Inadequate Core Cooling 14

[Question 83]

WE02 SI Termination 13

[Question 84]

Tube Leakl 3

[Question 85]

A Category Point Totals:

KIA Topic(s)

AA2. Ability to determine and interpret the following as they apply to the Dropped Control Rod:

AA2.03 Dropped rod, using in-core/ex-core instrumentation, in-core or loop temperature measurements (CFR: 43.5 145.13) 2.1.19 Ability to use plant computers to evaluate system or component status.

(CFR: 41.10/45.12) and interpret the following as they apply to the (SI Termination)

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

(CFR: 43.5/45.13)

AA2. Ability to determine and interpret the as they apply to the Steam Generator Tube Leak:

AA2.14 Actions to be taken if SIG goes solid and water enters steam lines (CFR: 43.5/45.13)

Group Point Total:

IR 3.8 3.8 4.2 4.4 NUREG-1021, Revision 9 Supplement 1 SRO Page 3 of 6 FENOC Facsimile Rev. AG 4

ES401 PWR Examination Outline Form ES401-2 Plant Systems

- Tier 21Group 1 (SRO)

System # 1Name K

1 K

2 KIA Topic(s)

IR 10 Pressure Control System (PZR PCS)

[Question 86]

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

4.2 A2.03 PORV failures (CFR: 41.5/43.5 /45.3 / 45.13) 012 Reactor Protection System

[Question 87]

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

3.7 1

A2.07 Loss of de control power (CFR: 41.5/43.5/45.3/45.5) 013 Engineered Safety Features Actuation System (ESFAS)

[Question 88]

2.2.37 Ability to determine operability and/or availability of safety related equipment.

(CFR: 41.7/43.5/45.12) 4.6 1

039 Main and Reheat Steam System (MRSS)

[Question 89]

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:

3.6 A2.05lncreasing steam demand, its relationship to increases in reactor power (CFR: 41.5/43.5 145.3/45.13) 061 Auxiliary 1Emergency Feedwater (AFW) System

[Question 90]

2.1.2 Knowledge operator during all modes of plant operation.

(CFR: 41.10/45.13) 4.4 NUREG-1021, Revision 9 Supplement 1 SRO Page 4 of 6 FENoe Facsimile Rev. AG

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems

- Tier 2/Group 2(SRO)

~=================F=F=F=F~~=r=

System # 1Name KKK K 1 234 K

5 KIA Topic(s)

IR 015 Nuclear Instrumentation A2 Ability to (a) predict the impacts of the 3.5*

System

[Question 91]

following malfunctions or operations on the NIS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.02 Faulty or erratic operation of detectors or compensating components FR: 41.5/43.5/45.3/45 034 Fuel Handling Equipment System (FHES)

K4 Knowledge of design feature(s) andlor interlock(s) which provide for the following:

3.4 1

[Question 92]

K4.01 Fuel protection from binding and dropping (CFR: 41.7) 041 Dump System (SDS) 2.1.31 Ability to locate control room switches, 4.3 1

and Turbine Bypass Control controls, and indications, and to determine that

[Question 93]

they correctly reflect the desired plant lineup.

(CFR: 41.10 145.12)

KIA Category Point Totals:

Group Point Total:

3 NUREG*1021, Revision 9 Supplement 1 SRO Page 5 of 6 FENoe Facsimile Rev. AG

ES 401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 Facility: BVPS UNIT 2 SRO Date of Exam 9/24 thru 10/5 2012 Category

1.

Conduct of Operations

2.

Equipment Control

3.

Radiation Control Emergency Proceduresl Plan KJA#

Topic 2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

[Question 94] (CFR: 41.10 143.5/45.12) 2.1.32 Ability to explain and apply system limits and precautions.

[Question 95] (CFR: 41.10/43.2 145.12)

Subtotal 2.2.20 Knowledge of the process for managing troubleshooting activities.

[Question 96] (CFR: 41.10 143.5/45.13)

Subtotal 2.3.6 Ability to approve release permits.

[Question 97] (CFR: 41.13/43.4/45.10) 2.3.11 Ability to control radiation releases.

[Question 98] (CFR: 41.11 143.4 145.10)

Subtotal 2.4.20 Knowledge of the operational implications of EOP warnings, cautions, and notes.

[Question 99] (CFR: 41.10/43.5/45.13) 2.4.46 Ability to verify that the alarms are consistent with the plant conditions.

[Question 100] (CFR: 41.10/43.5/45.3/45.12)

Subtotal Tier 3 Point Total NUREG-1021, Revision 9 Supplement 1 SRO Page 6 of 6 FENoe Facsimile Rev. AG

ES-401 Facility: BVPS UNIT 2

=

Tier I Randomly Group Selected KIA 1/1 000022 2.2.6 1/1 000057 2.4.19 1/2 000076 2.1.5 2/1 025 K4.02

.,1 0052.1.5 2/1 025 A4.02 2/1 0632.1.39 2/2 0272.2.37 2/2 028 K1.01 NUREG-1 021, Revision 9 Supplement 1 Record of Rejected KI As Form ES-401-4 Date of Exam 9/24 thru 10/52012 Operating Test No.: 2LOT8 NRC Reason for Rejection RO OUTLINE Question # 4; ES-401 D.1.b requires exclusion of generic KlAs for Tier 1 &2.

These generic KlAs were not suppressed and therefore were not automatically omitted using PWROG Random Generator. Randomly reselected 2.2.39 from same generic group.

Question # 12; ES-401 D.1.b requires exclusion of generic KlAs for Tier 1 &2.

These generic KlAs were not suppressed and therefore were not automatically omitted using PWROG Random Generator. Randomly reselected 2.4.4 from same generic group.

Question # 23; ES-401 D.1.b requires exclusion of generic KlAs for Tier 1 &2.

These generic KlAs were not suppressed and therefore were not automatically omitted using PWROG Random Generator. Randomly reselected 2.1.31 from same generic group.

Question # 30; Beaver Valley Unit 2 does not have ice condensers. Randomly reselected 004 K4.14 as a replacement.

Question # 31; ES-401 D.1.b requires exclusion of generic KlAs for Tier 1 &2.

These generic KlAs were not suppressed and therefore were not automatically omitted using PWROG Random Generator. Randomly reselected 2.1.32 from same generic group.

Question # 44; Beaver Valley Unit 2 does not have ice condensers. Randomly reselected 061 A1.01 as a replacement.

Question # 47; ES-401 D.1.b requires exclusion of generic KlAs for Tier 1 &2.

These generic KlAs were not suppressed and therefore were not automatically omitted using PWROG Random Generator. Randomly reselected 2.1.7 from same generic group.

Question # 57; Beaver Valley Unit 2 has removed the CNMT Iodine Removal system and replaced it with a passive sodium tetra borate basket system.

Operations personnel do not have any tasks associated with this new system.

Randomly reselected the 015 system as a replacement.

Question # 60; Beaver Valley Unit 2 has removed the Hydrogen Recombiner system. Hydrogen Recombiner functions are now directed by the TSC and the equipment that will be used is on skid that will be hooked-up and utilized as necessary. Operations personnel do not currently have any tasks associated with this system. The TSC will implement the use of the recombiners during SAMG implementation. Randomly reselected 041 K1.02 as a replacement.

Page 1 of3 FENOC Facsimile Rev. AG

ES-401 Record of Rejected KlAs Form ES-401-4 Facility: BVPS UNIT 2 Date of Exam 9/24 thru 10/5 2012 Operating Test No.: 2LOT8 NRC Tier I Randomly Group Selected KIA 2/1 062 K4.05 1/1 WE042.1.27 1/2 WE08 EK3.2 2/1 007 K5.02 2/1 103 A2.04 2/2 055A3.03 1/1 000008 AK2.03 2/1 078 A3.01 3

2.1.39 3

2.2.41 3

2.3.15 Reason for Rejection Question # 46; KA is too similar to 062 A4.07 KA that was randomly selected for question # 45. Randomly reselected 062 K4.10 as a replacement.

Question # 16; Knowledge of system purpose/function does not apply to a LOCA outside containment. Randomly reselected 2.1.23 from same generic group Question # 25; Unable to construct a discriminatory question about the reason for having procedures to address PTS. Randomly reselected EK3.1 for the same Emergency Plant evolution.

Question # 34; The PRT is no longer used at Beaver Valley Unit 2 during PZR steam bubble formation. Randomly reselected A3.01 as a replacement Question 54; Beaver Valley Unit 2 does not have any operations procedures that address how to correct a containment evacuation that has failed. This would be dealt with through the work order process. Randomly reselected A2.03 as a replacement.

Question # 63; Beaver Valley Unit 2 does not have any automatic diversion of CARS exhaust. Re-alignment of CARS exhaust is done manually. Randomly reselected K1.06 as a replacement.

Question # 1, Chief examiner requested this KIA be replaced due to over-sampling when compared to the last 2 exams. Randomly reselected AK2.02 as a replacement.

Question # 53, Chief examiner requested this KIA be replaced due to over-sampling when compared to the last 2 exams. Randomly reselected K1.03 as a replacement.

Question # 67, Chief examiner requested this KIA be replaced due to over-sampling when compared to the last 2 exams. Randomly reselected 2.1.8 from the same generic group.

Question # 70, Chief examiner requested this KIA be replaced due to over-sampling when compared to the last 2 exams. Randomly reselected 2.2.36 from the same generic group.

Question # 72, Chief examiner requested this KIA be replaced due to over-sampling when compared to the last 2 exams. Randomly reselected 2.3.4 from the same generic group.

NUREG-1021, Revision 9 Supplement 1 Page 2 of3 FENOC Facsimile Rev. AG

ES-401 Record of Rejected KI As Form ES-401-4 Facility: BVPS UNIT 2 Date of Exam 9/24 thru 10/5 2012 Operating Test No.: 2LOT8 NRC

=

Tier I Randomly Group Selected KIA 1/1 000007 2.4.26 1/2 0000742.1.36 2/1 0132.3.15 2/1 041 2.3.11 1/1 056 AA2.58 2/2 015 A2.05 1/1 000026 2.1.25 2/1 061 2.1.7 1/2 WE102.2.38 2.4.41 Reason for Rejection SRO OUTLINE Question # 76; ES-401 D.1.b requires exclusion of generic KlAs for Tier 1 &2.

These generic KlAs were not suppressed and therefore were not automatically omitted using PWROG Random Generator. Randomly reselected 2.4.20 from same generic group.

Question # 83; ES-401 D.1.b requires exclusion of generic KlAs for Tier 1 &2.

These generic KlAs were not suppressed and therefore were not automatically omitted using PWROG Random Generator. Randomly reselected 2.1.19 from same generic group.

Question # 88; ES-401 D.1.b requires exclusion of generic KlAs for Tier 1 &2.

These generic KlAs were not suppressed and therefore were not automatically omitted using PWROG Random Generator. Randomly reselected 2.2.37 as a replacement.

Question # 93; ES-401 D.1.b requires exclusion of generic KlAs for Tier 1 & 2.

These generic KlAs were not suppressed and therefore were not automatically omitted using PWROG Random Generator. Randomly reselected 2.1.31 as a replacement.

Question # 79; Unable to construct a discriminatory question at the SRO level around the air compressor indicating light status during a Loss of Offsite Power.

Randomly reselected AA2.45 as a replacement.

Question # 91, Unable to construct a discriminatory question at the SRO level around the impact of core voiding on the NIS and the procedural guidance to correct or mitigate. Randomly reselected A2.02 as a replacement.

Question # 78, Unable to construct a discriminatory question at the SRO level around the use of graphs and charts during a loss of CCW. Randomly reselected 2.1.20 as a replacement.

Question # 90, Chief examiner requested this KIA be replaced due to over-sampling when compared to the last 2 exams. Randomly reselected 2.1.2 from the same generic group.

Question # 85 Unable to construct an SRO discriminatory question for conditions and limitations in the facility license while in ES-0.4, Natural Circulation Cooldown with Steam void in the vessel W/O RVLlS. Randomly re-selected 000037 AA2.14.

Question # 100 Chief examiner requested this KIA be replaced due to exam balance. EAL thresholds are already adequately covered on the exam. Randomly reselected 2.4.46 as a replacement.

NUREG-1021, Revision 9 Supplement 1 Page 3 of 3 FENoe Facsimile Rev. AG 3

ES-301 Administrative Topics Outline Form ES-301-1 Facility:

BVPS Unit 2

'amination Level RO [8]

Administrative Topic (See Note)

Conduct of Operations (RO A.1.1)

Conduct of Operations (RO A.1.2)

Equipment Control

""'OA.2)

Radiation Control (RO A.3)

Emergency Procedures/Plan Type Code*

M,R M,R D,P,R N,R topics, when all 5 are required.

"Type Codes & Criteria Date of Examination: 9/24 thru 10/42012 Operating Test Number 2LOT8 NRC Describe activity to be performed 2.1.23 (4.3)

Ability to perform specific system and integrated plant procedures during all modes of plant operation.

(2AD-007) Perform an ECP Calculation 2.1.37 (4.3)

Knowledge of procedures, guidelines, or limitations associated with reactivity management.

(2CR-003) Perform a Quadrant Power Tilt Ratio Calculation 2.2.13 (4.1)

Knowledge of tagging and clearance procedures.

(2AD-031) Prepare a Clearance Tagout [2QSS-P21B] Quench Spray Pump 21B 2.3.7 (3.5)

Ability to comply with radiation work permit requirements during normal or abnormal conditions.

(2AD-044) Select RWP and Determine Maximum Allowable Stay Time NOT EVALUATED (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 (z: 1)

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

NUREG-1021, Revision 9 Supplement 1 FENOC Facsimile Rev. AG

II ES-301 Administrative Topics Outline Form ES-301-1 Facility:

BVPS Unit 2 Date of Examination: 9/24 thru 10/42012

'amination Level SRO IR1 Operating Test Number 2LOT8 NRC Administrative Topic (See Note)

Type Code*

Describe activity to be performed Conduct of Operations N, R 2.1.25 (4.2)

Ability to interpret reference materials, such as graphs, curves, tables, (SRO A.1.1) etc.

(2AD-039) Review Completed SID Margin Calculation (At Power with One Inoperable rod).

Conduct of N,R 2.1.37 (4.6)

Operations Knowledge of procedures, guidelines, or limitations associated with (SRO A.1.2) reactivity management.

(2AD-045) Review completed Quadrant Power Tilt Ratio Calculation.

2.2.17 (3.8)

Equipment Control N,R (SRO A.2)

Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination with the transmission system operator.

(2AD-041) Perform a Risk Assessment (2FWE*P23A maintenance)

Radiation Control N,R 2.3.11 (4.3)

(SRO A.3)

Ability to control radiation releases.

(2AD-042) Determine Compensatory actions for 2GWS-RQ1 04 and 2GWS-OA 100A being OOS.

Emergency N,R 2.4.41 (4.1)

Procedures/Plan Knowledge of the emergency action level thresholds and classifications.

(SRO A.4)

(2AD-046) Classify an Emergency Event (Scenario Specific)

TE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

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

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

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

~~==========================================================================~

NUREG-1021, Revision 9 Supplement 1 FENoe Facsimile Rev. AG

ES-301 ControI R oomIIn-PIant S t u me Form ES-301 -2

,ys ems o tr Facility:

BVPS UNIT 2 Date of Examination: 9/24 thru 10/4 2012 Exam Level: RO IRI Operating Test No.:

2LOT8 NRC 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 S1 - Shift from Main FfIN Reg. Vlvs to Bypasses (2CR-072)

S,D 4S 52 - Respond to Rad Monitor Alarm (leak Coli Vent) (2CR-622)

S,D 7

53 - Raise Rx PWR to 10-8 AMPS (2CR-644)

S,D,A,L 1

S4 - Isolate SI Accumulators During a LOCA (2CR-654)

S,D,A,EN 3

55 - Perform Manual Makeup to the Charging Suction (2CR-581)

S,D,A 2

S6 - X-fer 4Kv AE Emerg Bus from Emerg to Norm (2CR-597)

S,N,A 6

S7 - Containment Spray Manual Actuation (2CR-656)

S,M,A 5

S8 - Swap RHS Trains (2CR-636)

S, M, A, EN, L 4P In-Plant 5ystems@ (3 for RO); (3 for 5RO-I); (3 or 2 for SRO-U)

P1 - Align Service Water Supply to AFW Pump Suction (2PL-167)

N,R,E 4S P2 - Startup a Rod Drive MG Set (2PL-003)

D 1

P3 - Place a RPS Channel in the Tripped Condition (2PL-009)

D 7

All RO and SRO control room (and in-plant) systems must be different and serve different safety functions; all 5SRO-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 1SRO-I 1SRO-U (A)lternate Path 4-6 14-6 12-3 (C)ontrol room (D)irect from bank s9/s8/s4 (E)mergency or abnormal in-plant
1/;
:1/;::1 (EN)gineered safety feature

- / - / ~ 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 S3/S3/s2 (randomly selected)

(R)CA

1/;
:1/;::1 (S)imulator NUREG-1021, Revision 9 Supplement 1 FENOC Facsimile Rev. AG

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 BVPS UNIT 2 Date of Examination: 9/24 thru 10/4 2012

",,,,,,1:

~~O(I) [8]

Operating Test No.:

2LOT8 NRC

~

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

System I JPM Title Type Code*

Safety Function S1 - Shift from Main FIW Reg. Vlvs to Bypasses (2CR-072)

S,D 4S S2 - Respond to Rad Monitor Alarm (leak Coli Vent) (2CR-622)

S,D 7

S3 - Raise Rx PWR to 10-8 AMPS (2CR-644)

S,D,A,L 1

II S4 - Isolate SI Accumulators During a LOCA (2CR-654)

S,D,A,EN 3

S5 - Perform Manual Makeup to the Charging Suction (2CR-581)

S,D,A 2

S6 - X-fer 4Kv AE Emerg Bus from Emerg to Norm (2CR-597)

S,N,A 6

S7 - Containment Spray Manual Actuation (2CR-656)

S,M,A 5

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

Pi - Align Service Water Supply to AFW Pump Suction (2PL-167)

N, R, E 4S P2 - Startup a Rod Drive MG Set (2PL-003)

D 1

P3 - Place a RPS Channel in the Tripped Condition (2PL-009)

D 7

All RO and SRO control room (and in-plant) systems must be different and serve different safety functions; all 5SRO-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 1SRO-II 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 1ii:1/1ii:1/~1 (EN)gineered safety feature 1~ 1 (Control room system)

(L)ow-power / Shutdown 1ii:1/1ii:1/~1 (N)ew or (M)odified from bank including 1 (A) 1ii:2/?!2/?!1 (P)revious 2 exams

31
:; 31 s 2 (randomly selected)

(R)CA

?!1/1ii:1/1ii:1 (S)imulator NUREG-1021, Revision 9 Supplement 1 FENoe Facsimile Rev. AG

~

Alppend'IX D Scenano, 0 utrme Form ES D 1.

Facility:

BVPS Unit 2 Scenario No.: 1 Op Test No.:

2LOT8 NRC Examiners:

Candidates:

SRO ATC BOP Initial IC 211(7): 25% power, BOL, Xe increasing, CB "D" @ 121 steps, RCS boron ~ 1935 ppm.

Conditions:

Main feed regulating valves in service Turnover:

Increase power to 100%. 2SAS-C21 BOOS Critical Tasks:

1. E-O.E Actuate 1 train of CNMT Spray
2. E-O.P Manually actuate SLI
3. E-2.A Isolate Faulted SIG Event Malf. No.

Event Type Event Description No.

1 (R)ATC Raise power in accordance with reactivity plan.

(N) BOP, SRO (TS) SRO 2FWE*P22 (turbine driven Aux Feedwater pump) trips 2

(I) ATC, SRO 2CHS-PT145, fails high, ATC required to manually control 3

letdown pressure via 2CHS-PCV145.

(C) BOP, SRO Loss of2AE 4kv Emergency bus 12-1 Emergency Diesel fails 4

(TS) SRO to auto start. BOP required to manually start EDG 2-1.

(C)ATC A TC manually aligns cooling water flow to EDG 2-1 (C) BOP, SRO 2CCS-P21A sheared shaft, auto start failure of2CCS-P21B, 5

requires manually starting standby pump.

(M)ALL Feedline break inside CNMT.

6 (C) ATC, SRO CIB actuation failure 7

(C) BOP, SRO MSLI actuation failure with 2SDS* AOVl11's failing to auto 8

close, requires BOP to manually actuate MSLI and close all 6 2SDS*AOVlll 's (C) BOP, SRO "B" train CREV's fails to actuate, requires BOP to manually 9

actuate.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Supplement 1 FENOC Facsimile Rev. AG

Appendix 0 Scenario Outline Form ES-D-1 Facility:

BVPS Unit 2 Scenario No.:2 Op Test No.:

2LOT8 NRC Examiners:

Candidates:

SRO ATC BOP Initial IC 219(17): 72% power, MOL, Eq Xe, CB "D"@180 steps, RCS boron - 1140 ppm.

Conditions:

Turnover:

Maintain steady state power at 72%, 2FWE*P23A OOS, 2SAS-C21 BOOS Critical Tasks:

1. E-O.A Manually trip the Reactor
2. E-O.Q Manually trip the turbine
3. FR-H.1.A Establish feedwater flow before Feed and Bleed criteria Event No.

(C)ATC, SRO 1

(TS) SRO (R)ATC 2

(C) BOP, SRO (TS) SRO 3

(M)ALL 4

(C) BOP, SRO 5

(M) ALL 6

(C) BOP, SRO 7

(C) BOP, SRO S

9 Event Description N44 fails high, rods automatically step in.

2FWS-P21B trips! reduce power to 52%

Misaligned Rod 2RCS*P21B locked rotor trip with Automatic Reactor trip failure and 400 gpm SBLOCA Automatic turbine trip failure Loss of all auxiliary feed water, entry into FR-H.l Failure of2FWS-P24, 2FWS-P21A and P21B (requires secondary depressurization and use ofcondensate pump.

2HVS-FN204A and B trip, requires manual starting of at least 1 fan.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Supplement 1 FENoe Facsimile Rev. AG

A d'

~ppen IX D S

cenana 0 tr u me Farm ES D 1 Facility:

BVPS Unit 2 Scenario No.:4 Op Test No.:

2LOT8 NRC Examiners:

Candidates:

SRO ATC BOP Initial IC 214(18): 100% power, MOL, Eq Xe, CB "D" @ 225 steps, RCS boron 1044 ppm.

Conditions:

Turnover:

Maintain steady state power at 100%, 2FWE*P23A ~OS, 2SAS-e21 BOOS Critical Tasks:

1. E-O.O Close CNMT isolation valves
2. E-1.C Stop RCP's
3. FR-S.1.C Insert RCCA's Event Malf. No.

Event Type Event Description No.

(I) ATC, SRO 2RCS*LT459 fails low.

1 (TS) SRO (N) ATe, SRO Restore letdown to service 2

(R)ATe Valve position limiter failure causes load rejection with Auto 3

(1) ATC, SRO rod malfunction, ATC required to insert negative reactivity.

(e) BOP, SRO During load rejection, "A" Main Feed Regulating Valve 4

controller holds valve in position, BOP required to manually control "A" S/G level.

(e) ATC, SRO 2ReS*PT445 fails high, 2 PORV's open, 2ReS*peV456 fails 5

(TS) SRO to 18% open with Block valve failed open, requiring crew to manually trip the reactor.

(M) ALL ATWS, crew enters FR-S.l.

6 (M) ALL 2000 gpm SBLOCA on return to E-O.

7 I

(e) BOP, SRO Train B CIA failure with 2eHS*MOV378 failing to auto close 8

9 (N)orrnal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Supplement 1 FENoe Facsimile Rev. AG

A d'

~ppen IX D s

cenano 0 tr u me Form ES D 1 Facility:

BVPS Unit 2 Scenario No.:5 Op Test No.:

2LOT8 NRC Examiners:

Candidates:

SRO ATC BOP Initial IC 217(10): 100% power, BOL, Eq Xe, CB "D" @ 225 steps, RCS boron 1458 ppm.

Conditions:

Turnover:

Maintain steady state power at 100%, 2FWE*P23A OOS, 2SAS-C21 BOOS Critical Tasks:

1. E-O.D Crew manually actuates at least one train of SIS
2. E-O.F Crew establishes the minimum required AFW flow
3. E-O.M Crew closes the upstream block MOV of the stuck open Pzr PORV
4. E-O.I Establish flow from at least 1 High head ECCS pump Event Malf. No.

Event Type Event Description No.

(I) ATe, SRO 2ReS*PT444 drifts low, requires ATC to manually control 1

RCS pressure.

(TS) SRO 2FWS-LT485 fails high 2

(C) BOP, SRO Voltage regulator failure causes main generator over 3

excitation, requires BOP to turn voltage regulator off and manually lower excitation.

(C) ATC, SRO 25 gpm ReS leak on HA" Loop.

4 (TS) SRO (M)ALL 500 gpm RCS leak on "A" Loop.

5 (e) ATC, SRO 2RCS-peV455D fails open on Rx trip, requires ATC to close 6

block valve.

(C) BOP, SRO AFW malfunctions, 2FWE*P23A OOS on turnover, 7

2FWE*P23B auto start failure, requires BOP to manually start.

2FWE*P22 running with reduced flow << 340 gpm) 8 (C) ATe, SRO Auto SIS inhibited, requires ATe to manually actuate SIS.

(e) ATC, SRO 2SIS*MOV867's fail to open on SIS actuation signal, ATe 9

required to manually open valves to initiate Safety Injection flow.

(N)ormal, (R)eactivity, (I)nstrument, (e)omponent, (M)ajor NUREG-1021, Revision 9 Supplement 1 FENoe Facsimile Rev. AG

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