ML12111A219

Final Outlines (Folder 3)

ML12111A219
Person / Time
Site:	Beaver Valley
Issue date:	04/20/2012
From:	Rudolph W FirstEnergy Nuclear Operating Co
To:	David Silk Operations Branch I
Jackson D
Shared Package
ML113320121	List: IR 05000334/2012301 ML11334A008 ML120900525 ML12111A189 ML12111A195 ML12111A198 ML12111A204 ML12111A212 ML12111A219 ML12111A222 ML12111A234 ML12111A239 ML12180A418 ML12180A443
References
TAC U01846
Download: ML12111A219 (29)

Text

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BVPS UNIT 1 RO Date of Exam 4/9 thru 4/20/2012 Tier 3 3 3 4 3 3 3 4 3 5 4 38 Totals 1 2 3 4

3. Generic Knowledge and 10 Abilities Category 3 2 3 2 Note:

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

2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KIA statements.

4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.

5. Absent a plant-specific priority, only those 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 syst<ems 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 SHction D.1.b of ES-401 for the applicable KlAs.

8. On the following pages, enter the KIA numbers, a brief de,scription 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-1 021, Revision 9 Supplement 1 RO Page 1 of 13 FENoe Facsimile Rev 2

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

~==============--====~~=T=T-ElAPE # / Name / Safety Function KIA Topic(s) 000007 Reactor Trip - Stabilization - EA2 Ability to determine or interpret the following as Recovery 11 they apply to a reactor trip:

[Question 11 EA2.03 Reactor trip breaker position.

(CFR 41.7 / 45.51 45.6) 000008 Pressurizer Vapor Space Accident / AK2 Knowledge of the interrelations between the 2.7*

3 Pressurizer Vapor Space Accident and the

[Question 2] following:

AK2.01 Valves.

(CFR 41.7/45.7) 000009 Small Break LOCA I 3 EK2 Knowledge of the between the small break LOCA and the following:

[Question 31 EK2.03 SlGs.

(CFR 41.7/45.7) 000011 Large Break LOCA 13 EA2 Ability to determine or interpret the following as 4.5

[Question 4] they apply to a Large Break LOCA:

EA2.10 Verification of adequate core cooling.

(CFR 43.5/45.13) 000022 Loss of Reactor Coolant Makeup / AA2 Ability to determine and interpret the following 2.9 2 EIS they apply to the Loss of Reactor Coolant

[Question 5] Makeup:

AA2.04 How long PZR level can be maintained within limits.

(CFR: 43.5/45.13) 000025 Loss of RHR System 14 AK1 Knowledge of the operational implications of 3.9

[Question 6] tl1e following concepts as they apply to Loss of Hesidual Heat Removal System:

AK1.01 Loss of RHRS during all modes of cperation.

(CFR: 41.8/ 41.1 0 / 45.3) 000026 Loss of Component Cooling Water / t\A1 Ability to operate and/or monitor the following 3.2 8 a.s they apply to the Loss of Component Cooling

[Question 7] Water:

AA1.02 Loads on the CCWS in the control room.

(CFR 41.71 45.5 1 45.6) 000027 Pressurizer Pressure Control AK1 Knowledge of the operational implications of 2.8 System Malfunction I 3 the following concepts as they apply to Pressurizer

[Question 8] Pressure Control Malfunctions:

AK1.02 Expansion of liquids as temperature rises.

(CFR 41.8/41.10/45.3) 000029 ATWS /1 EK3 Knowledge of the reasons for the following 4.4

[Question 9] responses as they apply to the ATWS:

EK3.12 Actions contained in EOP for ATWS.

(CFR 41.5/41.10 145.6/45.13)

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

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

~========================-F=r=T=T==

ElAPE # / Name / Safety Function KIA Topic(s) IR #

000038 Steam Generator Tube Rupture / 3 EK1 Knowledge of the operational implications of 3.2

[Question 10] tlhe following concepts as they apply to the SGTR:

EK1.02 Leak rate vs. pressure drop.

(CFR 41.8/41/10/45.3) 000040 Steam Line Rupture - Excessive J.\A 1 Ability to operate and / or monitor the following 4.5 Heat Transfer / 4 as they apply to the Steam Line Rupture:

[Question 11] AA1.02 Feedwater isolation.

(CFR 41.7/45.5> / 45.6) 000054 Loss of Main Feedwater / 4  ::~.2.44 Ability to interpret control room indications to 4.2

[Question 12] verify the status and operation of a system, and understand how operator actions and directives 8lftect plant and system conditions.

(GFR 41.5 /43.5 / 45.12) 000055 Station Blackout / 6 EK3 Knowledge of the reasons for the following 4.3

[Question 13] r<esponses as they apply to the Station Blackout:

EK3.02 Actions contained in EOP for loss of offsite and onsite power.

(GFR 41.5/41.10/45.6/45.13) 000056 Loss of Oft-site Power / 6 AK3 Knowledge of the reasons for the following 3.5

[Question 14] nesponses as they apply to the Loss of Offsite Power:

AK3.01 Order and time to initiation of power for the load sequencer.

(GFR 41.5/41.10/45.6/45.13 )

000058 Loss of DC Power / 6 2:.4.47 Ability to diagnose and recognize trends in 4.2

[Question 15] an accurate and timely manner utilizing the a.ppropriate control room reference material.

(GFR: 41.10/43.5/45.12) 000062 Loss of Nuclear Service Water /4 2:.4.4 4.5

[Question 16] (GFR: 41.10/43.2/45.6) 000077 Generator Voltage and Electric Grid AK2 Knowledge of the interrelations between 3.9 Disturbances /6 Generator Voltage and Electric Grid Disturbances

[Question 17] a.nd the following:

JlIK2.06 Reactor Power.

(GFR: 41.4 / 41.5 / 41.7/41.10/45.8)

NUREG-1 021, Revision 9 Supplement 1 RO Page 3 of 13 FENoe Facsimile Rev 2

ES-401 PWR Examination Outline Form E5-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1(RO) Continued

~-=-=-=-=-=-=-=-=-=-=-=-=~=P~=T=-

E/APE # I Name I Safety Function KIA Topic(s} IR #

W/E04 LOCA Outside Containment 13 EA 1 Ability to operate and lor monitor the following 3.6

[Question 18] as they apply to the (LOCA Outside Containment):

EA1.2 Operating behavior characteristics of the facility.

(CFR: 41.7 I 45.5 I 45.6)

KIA Category Point Totals: Group Point Total: 18 NUREG-1021, Revision 9 Supplement 1 RO Page 4 of 13 FENOC Facsimile Rev 2

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

E/APE # 1 Name 1 Safety Function KIA Topic(s) 000028 Pressurizer Level Malfunction 12 AK2 Knowledge of the interrelations between the 2.6 Pressurizer Level Control Malfunctions and the

[Question 19] following:

AK2.02 Sensors and detectors.

(CFR: 41.7/45.7) 000051 Loss of Condenser Vacuum 12 2.1.20 Ability to interpret and execute procedure 4.6 steps.

[Question 20]

(CFR: 41.10/43.5/45.12) 000061 ARM System Alarms 17 AK1 Knowledge of the operational implications of the 2.5*

following concepts as they apply to Area Radiation

[Question 21] Monitoring (ARM) System Alarms:

AK1.01 Detector limitations.

(CFR 41.S/41.10 145.3) 000067 Plant Fire On-site / 9 AK1 Knowledge of the operational implications of the 3.1 following concepts as they apply to Plant Fire on

[Question 22] site:

AK1.02 Fire fighting.

(CFR: 41.SI 41.10 145.3) 000068 Control Room Evacuation 1S AK3 Knowledge of the reasons for the following 3.9 fl9sponses as thEjY apply to the Control Room

[Question 23] Evacuation:

AK3.10 Maintenance of PZR level, using pumps and heaters.

(CFR: 41.5/41.10/45.6/45.13)

W/EOS RCS Overcooling - PTS 14 EA 1 Ability to operate and I or monitor the following 3.S a.s they apply to the (Pressurized Thermal Shock)

[Question 24]

EA1.1 Components and functions of control and safety systems, including instrumentation, Signals, interlocks, failure modes, and automatic and manual features.

(CFR: 41.7/45.5/45.6)

WIE10 Natural Circulation with Steam Void EK2 Knowledge of the interrelations between the 3.3 in Vessel withlwithout RVLlS 1 4 (Natural Circulation with Steam Void in Vessel withlwithout RVLlS) and the following:

[Question 25]

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

(CFR: 41.7/45.7)

W/E14 High Containment Pressure 15 EA2 Ability to determine and interpret the following 3.3 as they apply to the (High Containment Pressure):

[Question 26]

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

(CFR: 43.5/45.13)

NUREG-1021, Revision 9 Supplement 1 RO Page 5 of 13 FENoe Facsimile Rev 2

ES-401 PWR Examinatilon Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2(RO) Continued IF==========================P=P~=T-=

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

W/E15 Containment Flooding I 5 EA 1 Ability to operate and I or monitor the following 2.8 as they apply to the (Containment Flooding):

[Question 27]

EA 1.3 Desired operating results during abnormal and emergency situations.

(CFR: 41.7 I 45.S I 45.6)

KIA Category Point Totals: Group Point Total: 9 NUREG-1 021, Revision 9 Supplement 1 RO Page 6 of 13 FENoe Facsimile Rev 2

E5-401 PWR Examination Outline Form E5-401*2 Plant Systems

• Tier 21Group 1 (RO)

System # / Name KJA Topic(s) IR #

003 Reactor Coolant Pump K5 Knowledge of the operational implications 3.2 of the following concepts as they apply to the

[Question 28] RCPS:

K5.04 Effects of RCP shutdown on secondary parameters, such as steam pressure, steam flow, and feed flow.

(CFR: 41.5/45.7) 004 Chemical and Volume K2 Knowledge of bus power supplies to the 2.6*

Control following:

[Question 29] K2.06 Control instrumentation.

(CFR: 41.7) 005 Residual Heat Removal A4 Ability to manually operate and/or monitor 2.8" in the control room:

[Question 30]

A4.03 RHR temperature, PZR heaters and flow, and nitrogen.

(CFR: 41.7/45.5 to 45.8) 006 Emergency Core Cooling K6 Knowledge of the effect of a loss or 2.8 malfunction on the following will have on the

[Question 31] ECCS:

K6.13 Pumps.

(CFR: 41.7/45.7) 006 Emergency Core Cooling 2.4.4 Ability to recognize abnormal indications 4.5 for system operating parameters that are entry

[Question 32] level conditions for emergency and abnormal operating procedures.

(CFR: 41.10/43.2/45.6) 007 Pressurizer Relief/Quench A4 Ability to manually operate and/or monitor 3.B Tank in the control room:

[Question 33] A4.10 Recognition of leaking PORV/code safety (CFR: 41 ..7 / 45.5 to 45.8) 008 Component Cooling Water A3 Ability to monitor automatic operation of the 3.6*

CCWS, including:

[Question 34]

A3.0e Automatic actions associated with the CCWS that occur as a result of a safety injection signal.

(CFR: 41.7/45.5) 010 Pressurizer Pressure K6 Knowledge of the effect of a loss or 2.7 Control malfunction of the following will have on the PZR PCS:

[Question 35]

KB.01 PrElssure detection systems.

(CFR: 41.7/45.7)

NUREG-1021, Revision 9 Supplement 1 RO Page 7 of 13 FENoe Facsimile Rev 2

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2JGroup 1 (RO) Continued System # / Name KIA Topic(s) IR #

010 Pressurizer Pressure K5 Knowledge of the operational implications 3.5 Control of the following concepts as they apply to the PZR pcs:

[Question 36]

K5.01 Determining of condition of fluid in PZR, using steam tables.

(CFR: 41.5 / 45.7) 012 Reactor Protection K4 Knowledge of RPS design feature{s) and/or 3.7 interlock(s) which provide for the following:

[Question 37]

K4.01 Trip logic when one channel aac or in test.

(CFR: 41.7) 013 Engineered Safety Features K1 Knowledge of the physical connections 4.1 Actuation andlor cause-effect relationships between ESFAS and the following systems:

[Question 38]

Kl.07 AFW System.

(CFR: 41.2 to 41.9/45.7 to 45.8) 022 Containment Cooling K2 Knowledge of bus power supplies to the 3.0' following:

[Question 39]

K2.01 Containment cooling fans.

(CFR: 41.7) 026 Containment Spray A2 Ability to (a) predict the impacts of the 3.9 following malfunctions or operations on the

[Question 40] CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.04 Failure of spray pump.

(CFR: 41.5/43.5/45.3/45.13) 026 Containment Spray 2.2.39 Knowledge of less than or equal to one 3.9 hour1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> Technical Specifications for a system.

[Question 41]

(CFR: 41.7/41.10/43.2/45.13) 039 Main and Reheat Steam K4 Knowledge of MRSS design feature(s) 3.4 and/or interlock(s) which provide for the

[Question 42] following:

K4.07 Reactor building isolation.

(CFR: 41.7) 059 Main Feedwater K3 Knowledge of the effect that a loss or 3.6 malfunction of the MFW system will have on

[Question 43] the following:

K3.02 AFW System.

(CFR: 41.7/45.6) 061 Auxiliary/Emergency K4 Knowledge of AFW design feature(s) 2.7 Feedwater and/or interlock(s) which provide for the following:

[Question 44]

K4.08 AFW Recirculation.

(CFR: 41.7)

NUREG*1021 , Revision 9 Supplement 1 RO Page 8 of 13 FENOe Facsimile Rev 2

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO) Continued

~==================~~9F9F=r=r=T=

System # / Name KIA Topic(s) IR #

062 AC Electrical Distribution A 1 Ability to predict and/or monitor changes in 3.4 parameters (to prevent exceeding design

[Question 45] limits) associated with operating the AC Distribution System controls including:

A1.01 Si~lnificance of D/G load limits.

(CFR: 41.5/ 45.5) 063 DC Electrical Distribution A 1 Ability to predict and/or monitor changes in 2.5 parameters associated with operating the DC

[Question 46] electrical system controls including:

A1.01 Battery capacity as it is affected by discharge rate.

(CFR: 41.5/ 45.5) 063 DC Electrical Distribution 2.4.11 Knowledge of abnormal condition 4.0 procedures.

[Question 47]

(CFR: 41.10/43.5/45.13) 064 Emergency Diesel A2 Ability to (a) predict the impacts of the 2.7 Generator following malfunctions or operations on the ED/G system; and (b) based on those

[Question 48] predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.08 Consequences of opening/closing breaker between buses (VARS, out-of-phase, voltage).

(CFR: 41.5/43.5/45.3/45.13) 073 Process Radiation K3 Knowledge of the effect that a loss or 3.6 Monitoring malfunction of the PRM system will have on the following:

[Question 49]

K3.01 Radioactive effluent releases.

(CFR: 41.7/45.6) 076 Service Water A2 Ability to (a) predict the impacts of the 3.5*

following malfunctions or operations on the

[Question 50] SWS system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.01 Loss of SWS.

(CFR: 41 .5 / 43.5 / 45.3 / 45.13) 076 Service Water A4 Ability to manually operate and/or monitor 3.5*

in the control room:

[Question 51]

A4.04 Emergency heat loads.

(CFR: 41.7/45.5 to 45.8)

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

ES-401 PWR Examinatil~n Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO) Continued System # / Name KIA Topic(s) IR #

078 Instrument Air K1 Knowledge of the physical connections 2.7*

and/or cause-effect relationships between lAS

[Question 52] and the f()lIowing systems:

K1.02 Service Air.

(CFR: 41 . 2 to 41.9/45.7 to 45.8) 078 Instrument Air A4 Ability to manually operate and/or monitor 3.1 in the control room:

[Question 53]

A4.01 Pressure gauges.

(CFR: 41..7 / 45.5 to 45.8) 103 Containment K3 Knowledge of the effect that a loss or 3.8 malfunction of the containment system will

[Question 54] have on the following:

K3.02 Loss of containment integrity under normal conditions.

(CFR: 41.7/45.6) 103 Containment A3 Ability to monitor automatic operation of the 3.9 containml3nt system, including:

[Question 55]

A3.01 Containment isolation.

(CFR: 41.7/45.5)

KIA Category Point Totals: Group Point Total: 28 NUREG-1021. Revision 9 Supplement 1 RO Page 1001 13 FENoe Facsimile Rev 2

E5-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 21Group 2(RO) 1~~~~~~~~~~~~=T=r=r=

System # / Name KJA Topic(s)

IR 015 Nuclear Instrumentation K5 Knowledge of the operational implications of 2.6 the following concepts as they apply to the NIS:

[Question 56]

K5.04 Factors affecting accuracy and reliability of calorimetric calibrations.

(CFR: 41.5/45.7) 016 Non-nuclear K4 Knowledge of NNIS design feature(s) and/or 2.8*

Instrumentation interlock(s) which provide for the following:

[Question 57] K4.01 Reading of NNIS channel values outside control room.

(CFR: 41.7) 017 In-Core Temperature K6 Knowledge of the effect of a loss or 2.7 Monitor System (ITM) malfunction of the ITM system components:

[Question 58] K6.01 Sensors and detectors.

(CFR: 41.7/45.7) 029 Containment Purge 2.4.9 Knowledge of low power/shutdown 3.8

[Question 59] implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

(CFR: 41.10 / 43.5 / 45.13) 045 Main Turbine Generator A 1 Ability to predict and/or monitor changes in 3.8 parameters (to prevent exceeding design limits)

[Question 60] associated with MT/G system controls including:

A 1.05 Expected response of primary plant parameters (temperature and pressure) following TJG trip.

(CFR: 41.51 45.5) 055 Condenser Air Removal Kl Knowledge of the physical connections 2.6 and/or cause-effect relationships between the

[Question 61] CARS and the following systems:

Kl.06 PRM system.

(CFR: 41.2 to 41.9 /45.7 to 45.8) 068 Liquid Radwaste A3 Ability to monitor automatic operation of the 3.6 Liquid Radwaste system including:

[Question 62]

A3.02 Automatic isolation.

(CFR: 41.71 45.5) 071 Waste Gas Disposal A2 Ability to (a) predict the impacts of the 2.5 following malfunctions or operations on the

[Question 63] Waste Gas Disposal System; and (b) based on those on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.08 Meteorological changes.

(CFR: 41.5/43.5/45.3/45.13)

NUREG-1 021, Revision 9 Supplement 1 RO Page 11 of 13 FENoe Facsimile Rev 2

ES-401 PWR Examinatilon Outline Form ES-401-2 Plant Systems - Tier 2/Group 2(RO) Continued System # / Name KIA Topic(s)

IR #

075 Circulating Water K2 Knowledge of bus power supplies to the 2.6*

following:

[Question 64]

K2.03 Emergency/essential SWS pumps.

(CFR: 41.7) 086 Fire Protection A4 Ability to manually operate and/or monitor 3.3 in the control room:

[Question 65]

A4.01 Fire water pumps.

(CFR: 41 .7/45.5 to 45.8)

KIA Category Point Totals: Group Point Total: 10 NUREG-1 021, Revision 9 Supplement 1 RO Page 12 of 13 FENoe Facsimile Rev 2

ES401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: BVPS UNIT 1 RO Date of Exam 4/09 thru 412012012 RO Category KJA# Topic IR #

1. 2.1.7 Ability to evaluate plant performance and make operational judgments 4.4 Conduct based on operating characteristics, reactor behavior, and instrument of Operations interpretation.

(CFR: 41.5/43.5/45.121 45.13) [Question 66]

2.1.19 Ability to use plant computers to evaluate system or component status. 3.9 (CFR: 41.10 / 45.12)[Question 67]

2.1.38 Knowledge of the stations requirements for verbal communications when 3.7*

implementing procedures.

(CFR: 41.10/45.13) [Question 68]

Subtotal

2. 2.2.44 Ability to interpret control room indications to verify the status and Equipment operation of a system and understand how operator actions and Control directives affect plant and system conditions.

(CFR: 41.5/43.5/45.12) [Question 69]

2.2.43 Knowledge of the process to track inoperable alarms. 3.0 (CFR: 41.10/43.5/45.13) [Question 70]

Subtotal

3. 2.3.4 Knowledge of radiation exposure limits under normal or emergency Radiation conditions.

Control (CFR: 41.12/43.4/45.10) [Question 71]

2.3.5 Ability to use radiation monitoring systems, such as fixed radiation 2.9 monitors and alarms, portable survey instruments, personal monitoring equipment, etc.

(CFR: 41.11 141.121 43.41 45.9) [Question 72]

2.3.7 Ability to comply with radiation work permit n~quirements during normal 3.5 or abnormal conditions.

(CFR: 41.12/45.10) [Question 73]

Subtotal

4. 2.4.34 Knowledge of RD tasks performed outside the main control room during Emergency an emergency and the resultant operational effects.

Procedures/

(CFR: 41.10/43.5/45.13) [Question 74]

Plan 2.4.49 Ability to perform without references to procedures those actions that 4.6 require immediate operation of system components and controls.

(CFR: 41.10 143.2/45.6) [Question 75]

Subtotal int Total NUREG-1 021. Revision 9 Supplement 1 RO Page 13 of 13 FENoe Facsimile Rev 2

ES-401 PWR Examination Outline Form ES-401*2 rr======================================--==--===============---==--======~

SRO ONLY Points Tier Group A2 G* TOTAL 1 3 3 6 1.

Emergency 2 2 2 4

Abnormal Plant Tier 5 5 10 Evolutions Totals 3 2 2.

Plant Systems 2 0 2 1 3 Tier 5 3 8 Totals 1 2 3 4

3. Generic Knowledge and 7 Abilities Category 2 2 1 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 (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 (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 KJA 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 KJAs.

8. On the following pages, enter the KJA 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 KJA catalog, and enter the KJA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KJAs that are linked to 10 CFR 55.43.

NUREG-1 021, Revision 9 Supplement 1 SRO Page 1 of 6 FENOC Facsimile Rev 2

ES*401 PWR Examination Outline Form ES*401*2 Emergency and Abnormal Plant Evolutions* Tier lIGroup 1(SRO)

~~~~~~~~~~~='~=T=T=

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

000015/17 RCP Malfunctions 14 A,A2 Ability to determine and interpret the following 2.9

[Question 76] as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow):

A,A2.07 Calculation of expected values of flow in the loop with RCP secured.

(CFR: 43.5/45.13) 000057 Loss of Vital AC Inst. Bus I 6 2.2.36 Ability to analyze the effect of maintenance 4.2

[Question 77] activities, such as degraded power sources, on the status of limiting conditions for operations.

(GFR 41.10/43.2/45.13) 000065 Loss of Instrument Air I 8 A.A2 Ability to determine and interpret the following 2.9

[Question 78] as they apply to the Loss of Instrument Air:

AA2.03 Location and isolation of leaks.

(CFR: 43.51 45.13)

W/E05 Inadequate Heat Transfer - Loss of EA2 Ability to determine and interpret the following 4.3 Secondary Heat Sink I 4 as they apply to the (Loss of Secondary Heat Sink)

[Question 79J EA2.2 Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

(GFR: 43.5/45.13)

W/E11 Loss of Emergency Coolant Recirc / 2.1.20 Ability to interpret and execute procedure 4.6 4 steps.

[Question 80] (CFR: 41.10/43.5/45.12)

W/E12 Steam Line Rupture - Excessive 2.1.7 Ability to evaluate plant performance and make 4.7 Heat Transfer I 4 operational judgments based on operating

[Question 81J characteristics, reactor behavior, and instrument interpretation.

(CFR: 41.5/43.5/45.12/45.13)

KIA Category Point Totals: Group Point Total: 6 NU REG-1 021, Revision 9 Supplement 1 SRO Page 2 of 6 FENoe Facsimile Rev 2

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

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

000001 Continuous Rod Withdrawal 1 1 ~~.2.44 Ability to interpret control room indications to 4.4 verify the status and operation of a system, and

[Question 82] understand how operator actions and directives affect plant and system conditions.

(CFR: 41.51 43.S 1 45.12) 000005 Inoperable 1 Stuck Control Rod 1 1 AA2 Ability to determine and interpret the following 4.4 as they apply to the Inoperable 1 Stuck Control Rod:

[Question 83]

J\A2.03 Required actions if more than one rod is stuck or inoperable.

(CFR: 43.5/45. '13) 000036 Fuel Handling Accident / 8 J\A2 Ability to determine and interpret the following 4.1 as they apply to the Fuel Handling Incidents:

[Question 84]

AA2.02 Occurrence of a fuel handling incident.

(CFR: 43.5 1 45.13)

W/E06 Inadequate Core Cooling 1 4 ~~.4.18 Knowledge of the specific bases for EOPs. 4.0

[Question 85] (CFR: 41.10/43.1/45.13)

KIA Category Point Totals: Group Point Total: 4 NUREG-1 021, Revision 9 Supplement 1 SRO Page 3 of 6 FENoe Facsimile Rev 2

ES*401 PWR Examination Outline Form E5-401*2 Plant Systems - Tier 2/Group 1(SRO)

~================F9r9~=T=r~-

System # / Name KIA Topic(s) 005 Residual Heat Removal A2 Ability to (a) predict the impacts of the following malfunctions or operations on the

[Question 86] RHRS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.04 RHR valve malfunction.

(CFR: 41 .5/ 43.5 / 45.3 /45.13) 006 Emergency Core Cooling 2.2.22 Knowledge of limiting conditions for 4.7 operations and safety limits.

[Question 87]

(CFR: 41 .5/43.2/45.2) 008 Component Cooling Water A2 Ability to (a) predict the impacts of the 3.6 following malfunctions or operations on the

[Question 88] CCWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.01 Loss of CCW pump.

(CFR: 41.5/43.5/45.3/45.13) 059 Main Feedwater 2.4.45 Ability to prioritize and interpret the 4.3 significance of each alarm or annunciator.

[Question 89]

(CFR: 41 . 10 / 43.5 /45.3/45.12) 073 Process Radiation A2 Ability to (a) predict the impacts of the 2.9*

Monitoring following malfunctions or operations on the PRM system; and (b) based on those

[Question 90] predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.01 Erratic or failed power supply.

(CFR: 41.5 / 43.5 /45.3/45.13) ry Point Totals: oint Total:

NUREG*1 021, Revision 9 Supplement 1 SRO Page 4 of 6 FENoe Facsimile Rev 2

E8-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 21Group 2(SRO)

System #- / Name KIA Topic(s)

IR #

011 Pressurizer Level Control A2 Ability to (a) predict the impacts of the 3.7 following malfunctions or operations on the PZR

[Question 91] LCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.0S Loss of PZR heaters.

(CFR: 41.S / 43.51 45.3/45.13) 014 Rod Position Indication A2 Ability to (a) predict the impacts of the 4.1 following malfunctions or operations on the

[Question 92] RPIS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

034 Fuel Handling Equipment 2.4.9 Knowledge of low power/shutdown 4.2 implications in accident (e.g., loss of coolant

[Question 93] accident or loss of residual heat removal) mitigation strategies.

(CFR: 41.10/43.5/45.13)

KIA Category Point Totals: Group PointTotal: 3 NUREG-1021, Revision 9 Supplement 1 SRO Page 5 of 6 FENoe Facsimile Rev 2

Generic Knowledge and AbilitiE!S Outline (Tier 3) Form ES-401-3 Facility: BVPS UNIT 1 SRO Date of Exam 4/09 thru 4/20/2012 SROOnly Category KlA# Topic IR #

1. Ability to evaluate plant performance and make operational 4.7 Conduct 2.1.7 judgments based on operating charactoristics, reactor behavior, of Operations and instrument interpretation.

(CFR: 41.5 / 43.5 / 45.12 / 45.13)

[Question 94]

2.1.36 Knowledge of procedures and limitations involved in Gore 4.1 alterations.

(CFR: 41.10/43.6/45.7)

[Question 95]

Subtotal 2

2. Ability to determine the expected plant configuration using design Equipment 2.2.15 and configuration control documentation, such as drawings, line Control ups, tagouts, etc.

(CFR: 41.10/43.3/45.13)

[Question 96]

2.2.40 Ability to apply technical specifications for a system. 4.7 (CFR: 41.10/43.2/43.5/45.3)

[Question 91]

Subtotal 2

3. Knowledge of radiological safety procedures pertaining to licensed Radiation 2.3.13 operator duties, such as response to radiation monitor alarms, Control containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

(CFR: 41.12 / 43.4 / 45.9 /45.10)

[Question 98]

Subtotal 1

4. Knowledge of how abnormal operating procedures are used in Emergency 2.4.8 conjunction with EOP's.

Procedures/

Plan (CFR: 41.10/43.5/45.13)

[Question 99]

2.4.44 Knowledge of emergency plan protective action recommendations. 4.4 (CFR: 41.10 / 41.12 / 43.5 / 45.11)

[Question 100]

Subtotal 2

Tier 3 Point Total 7 NUREG-1 021, Revision 9 Supplement 1 SRO Page 6 of 6 FENoe Facsimile Rev 2

ES 401 Record 0 f R* e!Ject ed KIAs Form ES 401 4 - -

Facility: BVPS UNIT 1 Date of Exam 4/9 thru 4/20 2012 Operating Test No.: 1LOT8 NRC Tier / Randomly Reason fClr Rejection Group Selected KIA RO OUTLINE 1/1 026 AA1.03 SWS backup to CCWS is not applicable at BVPS.

026AA1.02 reselected for Ouestion #7.

1/1 027 AK1.01 Definition of saturation temperature is fundamental knowledge. Unable to construct a discriminatory question. Reselected based on 12119 discussion with Lead Examiner.

027 AK1.02 reselected for Ouestion # 8.

1/1 029 EK3.02 Starting specific charging pumps is not applicable to an ATWS at BVPS.

029 EK3.12 reselected for Ouestion # 9.

1/1 040 AA1.22 Load sequencer status lights are not applicable to BVPS.

040 AA 1.02 reselected for Ouestion # 11.

1/1 0542.2.1 *ES-401 D.1.b requires excllusion of generic KlAs for Tier 1 & 2. These generic KlAs were not suppressed and therefore were not automatically omitted using PWROG Random Generator (manually reselected from same generic group).

054 2.2.44 reselected for Question # 12.

1/1 0622.4.37

• Same as above. 2.4.1 was initially reselected. Since BVPS Loss of Nuclear Service Water AOP contains no immediate action steps another section 2.4 Generic KIA was manually reselected.

062 2.4.4 reselected for QUlestion # 16.

1/2 051 2.1.43

• Same as above.

051 2.1.20 reselected for Question # 20.

211 004 K2.02 Make-up pumps are not applicable to the BVPS design. Author/Exam Lead believed this KIA was referencing positive displacement makeup pumps. Follow-up discussion with Lead Examiner revealed this KIA is referring to Primary Make up (PG) pumps. Unit 1 currEmtly uses Unit 2 PG pumps.

004 K2.06 reselected for Question # 29.

2/1 0252.4.39 Ice Condensers are not applicable to the BVPS design.

006 2.4.4 reselected for QUl9stion # 32.

2/1 025 A4.10 Ice Condensers are not applicable to the BVPS design.

007 K5.02 reselected for Question # 33.

007A4.1 0 reselected based on NRC Lead Examiner feedback.

2/1 0262.2.41

• Same as above.

026 2.2.39 reselected for Question # 41.

2/1 0632.4.12

• Same as above.

0632.4.11 reselected for Question # 47.

2/2 0292.4.26

• Same as above.

029 2.4.9 reselected for QUl9stion # 59.

2/2 068 A3.01 Evaporators are no longer Llsed for Liquid Radwaste at BVPS.

NUREG-1 021, ReVISion 9 Supplement 1 Page 1 of 2 FENoe Facsimile Rev 2

068 A3.02 reselected for Question # 62.

3 2.1.5 KIA not an RO function at BVPS. Reselected based on 12119 discussion with Lead Examiner.

2.1 .7 reselected for Question # 66.

3 2.2.25 TS Bases is SRO level knowledge lAW Region II white paper on SRO ONLY questions.

2.2.44 reselected for Question # 69.

3 2.2.4 BVPS is not a multi-unit license plant.

2.2.43 reselected for Question # 70 SROOUTLINE 111 W/E112.1.6 *ES-401 D.1.b requires excliusion of generic KlAs for Tier 1 & 2. These generic KlAs were not suppressed and therefore were not automatically omitted using PWROG Random Generator (manually reselected from same generic group).

2.1.20 reselected for Question # 80.

1/1 W/E122.1.35

• Same as above.

2.1.7 reselected for Question # 81.

1/2 01 2.2.15

• Same as above.

2.2.44 reselected for Question # 82.

1/2 05 AA2.02 Jog and run rod speeds are not applicable to BVPS.

AA2.03 reselected for Question # 83.

1/2 W/E16 2.4.50 High Containment Radiation (FR-Z.3) was deleted at BVPS Unit 1. Not SRO KIA.

W/E06 2.4.18 reselected for Question # 85.

211 0062.2.43

• Same as above.

2.2.22 reselected for Question # 87.

2/1 008 A2.07 CCW Pump low flow auto start is not applicable to BVPS Design.

A2.01 reselected for Question # 88.

2/1 0592.3.15

• Same as above.

2.4.8 reselected for Question # 89. (manually reselected from Group 4 versus 3 since radiation control not applicable to main feedwater) 2.4.45 reselected for Question # 89 based on feedback from NRC Lead Examiner.

3 2.1.14 KIA not an SRO function at BVPS. Reselected based on 12119 discussion with Lead Examiner.

2.1.36 reselected for Question # 95.

NU REG*1 021, Revision 9 Supplement 1 Page 2012 FENOC Facsimile Rev 2

ES-301 Administrative Topics Outline Form ES-301-1 Facility: BVPS Unit 1 Date of Examination: 4/9 thru 4/20/2012 Examination Level RO [8] Operating Test Number 1LOT8 NRC Administrative Type Describe activity to be performed Topic Code*

(See Note)

Conduct of N,R 2.1.7 (4.4)

Operations Ability to evaluate plant performance and make operational judgments (RO A.1.1) based on operating characteristics, reactor behavior, and instrument interpretation.

(1 AD-30) Calculate The RCS Initial Void Volume and Final Void Volume.

Conduct of D,R 2.1.25 (3.9)

Operations Ability to interpret reference materials, such as graphs, curves, tables, (RO A.1.2) etc.

(1AD-008) Perform Shutdown Margin Calculation.

Equipment Control N,R 2.2.37 (3.6)

(RO A.2) Ability to determine operability andlor availability of safety related equipment.

(1AD-027) Completj~ Surveillance of RHR Pump Radiation Control D,R 2.3.11 (3.8)

(RO A.3) Ability to control radiation releases.

(1 AD-1 0) Determine GW Storage tank Discharge Bleed Flow Rate Emergency NOT EVALUATED ProcedureS/Plan topics, when all 5 are required.

• Type Codes & Criteria (C)ontrol Room, (S)imulator, or Class(R)oom (D)irect from bank (::; 3 for RDs; ::; 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 FENOC Facsimile Rev 2

ES-301 Administrative To ics Outline Form E5-301-1 Facility: BVPS Unit 1 Date of Examination :4/9 'lhru 4/20/2012 Examination Level SRO [8] Operating Test Number 1LOT8 NRC rative Topic Type Describe activity to be performed (See Note) Code*

Conduct of Operations N, R 2.1.43 (4.3)

(SRO A.1.1) Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant.

fuel depletion, etc.

(1AD-019) Evaluate 11M Plot and Determine Required Actions Conduct of Operations N,R 2.1.25 (4.2)

(SRO A.1.2) Ability to interpret reference materials, such as graphs, curves, tables, etc.

(1 AD-031) Review Shutdown Margin Calculation Equipment Control N,R 2.2.37 (4.6)

(SRO A.2) Ability to determine operability and/or availability of safety related equipment.

(1AD-026) Review/Approve Completed Surveillance of RHR Pump Radiation Control N,R 2.3.11 (4.3)

(SRO A.3) Ability to control radiation releases.

(1AD-023) Review/Approve LW Discharge.

Emergency N,R 2.4.40 (4.5)

ProcedureS/Plan Knowledge of SRO responsibilities in emergency plan implementation.

(SRO A.4)

(1AD-015) Comple'te Initial Noti'fication Form for a General Emergency topics, when al15 are required.

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

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

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

NUREG*1 021, Revision 9 Supplement 1 FENOC Facsimile Rev 2

E8-301 Control Room/In-Plant S stems Outline Form E8-301-2 Facility: BVPS UNIT 1 Date of Examination: 4/9 thru 4/20/2012 evel: RO r&l Operating Test No.: 1lOTa NRC Control Room Systems (8 for RO); (7 for SRo-l); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code*' Safety Function S,D,A,E 1 hronize and load #1 Emergency Diesel Genmator (1CR-524) S,N,A,EN 6 umulators During a lOCA (1 CR-64::!) S,D,A,P,EN 3 mps for Hot/Cold leg Recirculation (1 CR-570) S,D,A,E 2 ntainment Purge to Ventilation Vent (1CR-026) N,S,l a S6 - Respond to RCP #1 Seal Failure (1 CR-040) S, M, E,l 4P S7 - Control Room Evacuation (1 CR-609) S,D,A,E 4S S8 - Respond to an Intermediate Range Malfunction (1 CR-1 06) S,D,l 7 t Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P1 - Vent Charging Pump Suction Header (1 Pl-057) D,R,EN 2 P2 Transfer Control of Selected Equipment to SDP (Pl-041) D,E 7 P3 - Transfer 120VAC Vital Power (1Pl-524) N, A, E 6

@ 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 I SRO-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 ~1/~1/~1 (EN)gineered safety feature -I -f.=!: 1 (Control room system)

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

{R)CA ~1/~1/<::1

{S)imulator NUREG*1 021, Revision 9 Supplement 1 FENoe Facsimile Rev 2

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Date of Examination: 419 thru 4/20/2012 Operating Test No.: 1LOT8 NRC

(7 for SRO~I); (2 or 3 for SRO~U, including 1 ESF)

System 1 JPM Title Type Code* Safety Function S1 - Emergency Borate RCS (1 CR-511) S,D,A,E 1 S2 - Synchronize and Load #1 Emergency Diesel Generator (1CR-524) S,N,A,EN 6 S3 - Isolate SI Accumulators During a LOCA (1 CR-642) S,D,A,P,EN 3 S4 - Align SI Pumps for HoUCoid Leg Recirculation (1 CR-570) S,D,A,E 2 S5 - Establish a Containment Purge to Ventilation Vent (1 CR-026) N,S 8 S6 - Respond to RCP #1 Seal Failure (1 CR-040) S,M, 4P S7 - Control Room Evacuation (1 CR-609) S,D,A,E 4S In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

Pi - Vent Charging Pump Suction Header (1 PL-057) D,R,EN 2 P2 - Transfer Control of Selected Equipment to SDP (PL-041) D,E 7 P3 - Transfer 120VAC Vital Power (1 PL-524) N,A,E 6

@ 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 I SRO-II SRO-U (A)lternate Path 4-6/4-6 12-3

{C)ontrol room (D)irect from bank  :$9/:$8/:::;4 (E)mergency or abnormal in-plant  ;::;1/;::;1/;::;1 (EN)gineered safety feature -I-I.::. 1 (Control room system)

(L)ow-power I Shutdown  ;::;1/;::;1/2:1 (N)ew or (M)odified from bank including 1(A)  ;::;2/;::; 2 I'i!:. 1 (P)revious 2 exams $ 31 $ 3 1 S 2 (randomly selected)

(R)CA 'i!:.1/'i!:.1/'i!:.1 (S)imulator NUREG-1021, Revision 9 Supplement 1 FENOC Facsimile Rev 2

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

~ Date of Examination: 419 thru 4/20/2012

. Operating Test No.: 1LOTa NRC Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function S1 - Emergency Borate RCS (1CR-511) S,D,A,E 1 53 Isolate SI Accumulators During a LOCA (1 CR-642) S,D,A,P,EN 3 S5 - Establish a Containment Purge to Ventilation Vent (1 CR-026) N,S,L a In-Plant 5ystems@ (3 for RO); (3 for 5RO-I); (3 or 2 for SRO-U)

P1 - Vent Charging Pump Suction Header (1 PL-05?) D,R,EN 2 P3 - Transfer 120VAC Vital Power (1PL-524) N,A,E 6

@ 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 1 SRO-II SRO-U (A)ltemate 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 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 s 3/ s 3 / s 2 (randomly selected)

(R)CA  :::1/:::1/:::1 (S)imulator NUREG-1 021, Revision 9 Supplement 1 FENoe Facsimile Rev 2

Appen d Ix 0 Scenarol outrme Facility: BVPS Unit 1 Scenario No.:2 Op Test No.: lLOT8 NRC Examiners: Candidates: SRO ATC BOP Initial IC 237: 5% power, EOL, Xe increasing, CB "D" @ 115 steps, RCS boron - 664 ppm.

Conditions:

Turnover: Continue power increase IAW reactivity plan and commence turbine roll PCV-IRC-456 isolated due to seat leakage, block valve closed. TS 3.4.11, Condition A Critical Tasks: 1. E-3.A Isolate Ruptured S/G

2. E-3.B Establish/maintain RCS temperature

3. ECA-3.3.A Terminate Safety Injection Event Malf. No. Event Type Event Description No.

1 N/A (R)ATC Raise power (N)SRO IMP PRS08E (0 0) (I)ATC,SRO PT-IRC-445 fails high, PORV's 455D & 456 open, ATC 2

2500 15 (TS)SRO required to manually close PORV, PCV-IRC-455D IMFPRS04B IMF BST-CCW006 (C) BOP, SRO "A" CCR pump trips, Auto start failure or"B" CCR pump 3

IMPCCW3A (TS) SRO IMF MSS11 (00) (C)BOP, SRO Steam Dump pressure setpoint drifts low, steam dumps open in 4

1400 1200 response, BOP required to manually control steam dumps IMP RCSIOB (00) (C)ATC, SRO "B" RCP high vibration - will require RCPlRx trip 5

10.6 TRO 6 'IMF RCS 1OB (0 120) 16.4 60010.6' IMF RCS03A (1 120) (M) - ALL "A" SG - 450 gpm tube rupture 6

450 IMP MSS08A (5 0) 50 (C)BOP, SRO Steam dump, PCV-1 MS-1 06A fails at 50% following 7

cooldown during E-3. Crew required to isolate steam lines and control RCS temperature via atmospheric steam dumps 8 IMFPRS09A (10) 0 (C)ATC, SRO Pzr spray valves and remaining PORV fail to open during IMF PRS09B (1 0) 0 depressurization in E-3, will require transition to ECA-3.3 lOR X0710970 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG*1 021. Revision 9 Supplemen11 FENOC Facsimile Rev. 2

Appendix 0 Scenario OutIi ne Facility: BVPSUnitl Scenario No.:3 OpTestNo.: 1 LOT8 NRC Examiners: Candidates: SRO ATC BOP Initial IC 238 (18): 100% power, MOL, Equ. XE Conditions, CB "D" @ 225 steps, RCS boron Conditions: 1019 ppm.

Turnover: Maintain 100% power.

PCV-lRC-456 isolated due to seat leakage, block valve closed. TS 3.4.11, Condition A FW-P-2 Out of service, TS 3.7.5, Condition B Control Rods are in manual due to a circuit malfunction, I&C is investigating the problem using work order instructions, automatic rod control is not available.

Critical Tasks: 1. E-O.C Energize 1 AC Emergency Bus

2. E-O.D Manually actuate 1 train of Safety Injection

3. FR-H.l.A Establish feed flow to SG before Feed and Bleed is required

4. E-2.A Isolate faulted SG I Event Malf. No. Event Type Event Description No.

1 IMF PRS08D (0 0) (I) ATC, SRO PT-IRC-444 fails high, requires ATe to close PORV and 2500 15 (TS)SRO manually control RCS pressure.

2 lOR X12I027L (l2 0) (TS) SRO OCB-92 trips open, de-energizes SSST-IA ON 3 IMFAUX02A (C) BOP, SRO "A" Station air compressor trips, "B" fails to auto start - BOP manually starts "B" air compressor, Diesel Air compressor fails to auto start but will start locally.

IMF MSS18C (00) . (R)ATC "C" SG Fault in MSVR, causes Rx overpower, requires 4

2.5E5 300 0 (N) SRO, BOP emergency power reduction.

S IMF CRF04BV (22) (C)ATC, SRO 2 Rods drop during power reduction - requires manual Rx trip.

1 Loss of 4kv busses, "A", "B" and AE occurs on Rx trip IMF CRF04BT (24) 1 6 TRG3 'IMP (M)ALL "C" SG Steam Break occurs on Rx trip - causes Safety Inj.

MSS18C (00) 6E5' 7 IMF SISIOA (C) ATC, SRO Automatic SI fails to actuate - requires manual actuation.

IMF srSlOB 8 IMF EPSllB (1 30) (C)BOP, SRO "B" train 4kv emergency bus de-energizes, #2 EDG trips while IMP INH53 (0 0) loading, #1 EDG auto start inhibited, will start manually.

IMF EPS04F (1 10) 9 IMPFWMllC (4 30) (M)ALL Loss of all Aux Feedwater flow, requires entry into FR-H.l IMF FWMI1A (00)

(N)onnal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Supplement 1 FENOC Facsimile Rev. 2

Appendix 0 . 0 utrme S cenano Facility: BVPS Unitl Scenario No.:4 Op Test No.: lLOT8 NRC Examiners: Candidates: SRO ATC BOP Initial IC 255(10): 100% power, BOL, Equ. XE Conditions, CB "D" @ 225 steps, RCS boron-Conditions: 1434 ppm.

Turnover: Maintain 100% power.

PCV-IRC-456 isolated due to seat leakage, block valve closed. TS 3.4.11, Condition A Critical Tasks: 1. FR-S.l.C Initiate negative reactivity

2. FR-S.l.B Start Auxiliary Feedwater pumps

3. E-O.O Close cnmt isolation valves Event Malf. No. Event Type Event Description No.

1 IMP PRS06A (0 0) 0 (I)ATC, SRO LT-IRC459 fails low, letdown isolates, crew removes 5 (TS) SRO channel from service.

2 N/A (N)BOP, SRO Restores letdown 3 IMP TUR15 (0 0) 78 (C)ATC, SRO Turbine valve position limiter fails low, causes - 100 mw load 10 (TS) SRO reduction, 1 Rod stuck at ARO position.

IMP CRFIIBR 0 4 IMP FWM09C (1 0) (C) BOP, SRO "C"SG Feedwater valve, FCV-IFW-498, begins oscillating, 250 requiring BOP to manually control level.

5 IMF TUR03E (0 0) (C) BOP, SRO Turbine high bearing vibration requires crew to manually trip 158 the unit.

6 IMP CRF02A (5 0) (M)ALL Reactor fails to trip from the control room, requires entry into IMFCRFl2A FR-S.1, ATC manually inserts control rods.

IMFCRF12B 7 IMFINH20 (C)BOP, SRO All Aux Feedwater pumps fail to automatically start, requires IMFINH21 BOP to start AFW pumps.

IMFINH35 IMFINH36 8 IMP MSS02C (4 0) (M)ALL Main steam line break downstream of MSIV's, causes safety 3.5E6200 injection actuation.

9 IMPINH49 (C)ATC, SRO Train "A" CIA fails to actuate along with train "B" valve IMP VLV -SEAl 0 (0 MOV-1 CH-381 failing to automatically close, ATC must

0) 1000100 manually actuate CIA or close MOV-ICH-38L (N)onnal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1 021, Revision 9 Supplement 1 FENoe Facsimile Rev. 2