ML12111A219

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Beaver Valley Unit 1 - Final Outlines (Folder 3)
ML12111A219
Person / Time
Site: Beaver Valley
Issue date: 04/20/2012
From: Rudolph W J
FirstEnergy Nuclear Operating Co
To: David Silk
Operations Branch I
Jackson D E
Shared Package
ML113320121 List:
References
TAC U01846
Download: ML12111A219 (29)
v • d • e


Text

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 3 2 3 2 Note: Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and 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). 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. 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. 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. 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. Select SRO topics for Tiers 1 and 2 from the shaded syst<ems and KIA categories. 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. 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. 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 FENoe Facsimile Rev 2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions

-Tier 1/Group 1 (RO)

ElAPE # / Name / Safety 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 EA2.03 Reactor trip breaker position. (CFR 41.7 / 45.51 45.6) 000008 Pressurizer Vapor Space Accident / AK2 Knowledge of the interrelations between 3 Pressurizer Vapor Space Accident and

[Question 2] AK2.01 (CFR 000009 Small Break LOCA I 3 EK2 Knowledge of the between small break LOCA and the

[Question 31 EK2.03 SlGs. (CFR 41.7/45.7) 000011 Large Break LOCA 13 EA2 Ability to determine or interpret the following as they apply to a Large Break LOCA: [Question 4] 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 EIS they apply to the Loss of Reactor Coolant Makeup:[Question 5] AA2.04 How long PZR level can be maintained within limits. (CFR: 43.5/45.13) 000025 Loss of RHR System AK1 Knowledge of the operational implications tl1e following concepts as they apply to Loss [Question 6] 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\A 1 Ability to operate and/or monitor the following 8 a.s they apply to the Loss of Component Cooling Water:[Question 7] AA 1.02 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 System Malfunction I 3 the following concepts as they apply to Pressurizer Pressure Control Malfunctions:

[Question 8] AK1.02 Expansion of liquids as temperature (CFR 000029 A TWS /1 EK3 Knowledge of the reasons for the responses as they apply to the A [Question 9] EK3.12 Actions contained in EOP for A TWS. (CFR 41.5/41.10 145.6/45.13) 2.7* 4.5 2.9 3.9 3.2 2.8 4.4 NUREG-1 021, Revision 9 Supplement 1 RO Page 2 of FENoe Facsimile Rev 2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions

-Tier 1/Group 1 (RO) Continued ElAPE # / Name / Safety Function 000038 Steam Generator Tube Rupture / 3 [Question 10] 000040 Steam Line Rupture -

Heat Transfer / [Question 11] 000054 Loss of Main Feedwater / 4 [Question 12] 000055 Station Blackout / 6 [Question 13] 000056 Loss of Oft-site Power / 6 [Question 14] 000058 Loss of DC Power / 6 [Question 15] 000062 Loss of Nuclear Service Water /4 [Question 16] 000077 Generator Voltage and Electric Disturbances [Question 17] KIA Topic(s) IR # EK1 Knowledge of the operational implications of tlhe following concepts as they apply to the SGTR: 3.2 EK1.02 Leak rate vs. pressure drop. (CFR 41.8/41/10/45.3)

J.\A 1 Ability to operate and / or monitor the following as they apply to the Steam Line Rupture: 4.5 AA 1.02 Feedwater isolation. (CFR 41.7/45.5>

/ 45.6)

Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives 8lftect plant and system conditions.

4.2 (GFR 41.5 /43.5

/ 45.12) EK3 Knowledge of the reasons for the following r<esponses as they apply to the Station Blackout:

4.3 EK3.02 Actions contained in EOP for loss of offsite and onsite power. (GFR 41.5/41.10/45.6/45.13)

AK3 Knowledge of the reasons for the following nesponses as they apply to the Loss of Offsite Power: 3.5 AK3.01 Order and time to initiation of power for the load sequencer. (GFR 41.5/41.10/45.6/45.13 ) 2:.4.47 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the a.ppropriate control room reference material.

4.2 (GFR: 41.10/43.5/45.12) 2:.4.4 4.5 (GFR: 41.10/43.2/45.6)

AK2 Knowledge of the interrelations between Generator Voltage and Electric Grid Disturbances a.nd the following:

3.9 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 PWR Examination Outline Form E5-401-2 Emergency and Abnormal Plant Evolutions

-Tier 1/Group 1(RO) Continued E/APE # I Name I Safety KIA Topic(s} IR # W/E04 LOCA Outside Containment EA 1 Ability to operate and lor monitor the following as they apply to the (LOCA Outside

[Question EA 1.2 Operating behavior characteristics of (CFR: 41.7 I 45.5 I KIA Category Point Group Point Total: NUREG-1021, Revision 9 Supplement 1 RO Page 4 of FENOC Facsimile Rev 2 18 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions

-Tier 1/Group 2(RO)

E/APE # 1 Name 1 Safety Function 000028 Pressurizer Level Malfunction 12 [Question 19] 000051 Loss of Condenser Vacuum 12 [Question 20] 000061 ARM System Alarms 17 [Question 21] 000067 Plant Fire On-site / 9 [Question 22] 000068 Control Room Evacuation 1 S [Question 23] W/EOS RCS Overcooling

-PTS 1 4 [Question 24] WIE10 Natural Circulation with Steam in Vessel withlwithout RVLlS 1[Question 25] W/E14 High Containment Pressure 15 [Question 26] KIA Topic(s) AK2 Knowledge of the interrelations between the Pressurizer Level Control Malfunctions and the following:

2.6 AK2.02 Sensors and detectors. (CFR: 41.7/45.7) 2.1.20 Ability to interpret and execute procedure steps. 4.6 (CFR: 41.10/43.5/45.12)

AK1 Knowledge of the operational implications of the following concepts as they apply to Area Radiation Monitoring (ARM) System Alarms: 2.5* AK1.01 Detector limitations. (CFR 41.S/41.10 145.3) AK1 Knowledge of the operational implications of the following concepts as they apply to Plant Fire on site: 3.1 AK1.02 Fire fighting. (CFR: 41.SI 41.10 145.3) AK3 Knowledge of the reasons for the following fl9sponses as thEjY apply to the Control Room Evacuation:

3.9 AK3.10 Maintenance of PZR level, using pumps and heaters. (CFR: 41.5/41.10/45.6/45.13)

EA 1 Ability to operate and I or monitor the following a.s they apply to the (Pressurized Thermal Shock) 3.S EA 1.1 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)

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

3.3 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)

EA2 Ability to determine and interpret the following as they apply to the (High Containment Pressure):

3.3 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 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 [Question 27] as they apply to the (Containment Flooding):

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 [Question 28] K5 Knowledge of the operational implications of the following concepts as they apply to the RCPS: 3.2 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 Control K2 Knowledge of bus power supplies to the following:

2.6* [Question 29] K2.06 Control instrumentation. (CFR: 41.7) 005 Residual Heat Removal [Question 30] A4 Ability to manually operate and/or monitor in the control room: A4.03 RHR temperature, PZR heaters and flow, and nitrogen.

2.8" (CFR: 41.7/45.5 to 45.8) 006 Emergency Core Cooling [Question 31] K6 Knowledge of the effect of a loss or malfunction on the following will have on the ECCS: 2.8 K6.13 Pumps. (CFR: 41.7/45.7) 006 Emergency Core Cooling [Question 32] 2.4.4 Ability to recognize abnormal indications for system operating parameters that are entry level conditions for emergency and abnormal operating procedures.

4.5 (CFR: 41.10/43.2/45.6) 007 Pressurizer Relief/Quench Tank A4 Ability to manually operate and/or monitor in the control room: 3.B [Question 33] A4.10 Recognition of leaking PORV/code safety (CFR: 41 ..7 / 45.5 to 45.8) 008 Component Cooling Water [Question 34] A3 Ability to monitor automatic operation of the CCWS, including:

A3.0e Automatic actions associated with the CCWS that occur as a result of a safety injection signal. 3.6* (CFR: 41.7/45.5) 010 Pressurizer Pressure Control [Question 35] K6 Knowledge of the effect of a loss or malfunction of the following will have on the PZR PCS: KB.01 PrElssure detection systems. 2.7 (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 Control [Question 36] K5 Knowledge of the operational implications of the following concepts as they apply to the PZR pcs: K5.01 Determining of condition of fluid in PZR, using steam tables. 3.5 (CFR: 41.5 / 45.7) 012 Reactor Protection

[Question 37] K4 Knowledge of RPS design feature{s) and/or interlock(s) which provide for the following:

K4.01 Trip logic when one channel aac or in test. 3.7 (CFR: 41.7) 013 Engineered Safety Features Actuation

[Question 38] K1 Knowledge of the physical connections andlor cause-effect relationships between ESFAS and the following systems: Kl.07 AFW System. 4.1 (CFR: 41.2 to 41.9/45.7 to 45.8) 022 Containment Cooling [Question 39] K2 Knowledge of bus power supplies to the following:

K2.01 Containment cooling fans. 3.0' (CFR: 41.7) 026 Containment Spray [Question 40] A2 Ability to (a) predict the impacts of the following malfunctions or operations on the CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

3.9 A2.04 Failure of spray pump. (CFR: 41.5/43.5/45.3/45.13) 026 Containment Spray [Question 41] 2.2.39 Knowledge of less than or equal to one hour Technical Specifications for a system. (CFR: 41.7/41.10/43.2/45.13) 3.9 039 Main and Reheat Steam [Question 42] K4 Knowledge of MRSS design feature(s) and/or interlock(s) which provide for the following:

3.4 K4.07 Reactor building isolation. (CFR: 41.7) 059 Main Feedwater

[Question 43] K3 Knowledge of the effect that a loss or malfunction of the MFW system will have on the following:

3.6 K3.02 AFW System. (CFR: 41.7/45.6) 061 Auxiliary/Emergency Feedwater

[Question 44] K4 Knowledge of AFW design feature(s) and/or interlock(s) which provide for the following:

K4.08 AFW Recirculation.

2.7 (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 System # / Name 062 AC Electrical

[Question 063 DC Electrical Distribution

[Question 46] 063 DC Electrical Distribution

[Question 47] 064 Emergency Diesel Generator

[Question 48] 073 Process Radiation Monitoring

[Question 49] 076 Service Water [Question 50] 076 Service Water [Question 51] -Tier 2/Group 1 (RO) Continued KIA Topic(s) IR # A 1 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the AC Distribution System controls including:

3.4 A 1.01 of D/G load limits. (CFR: 41.5/ 45.5) A 1 Ability to predict and/or monitor changes in parameters associated with operating the DC electrical system controls including:

2.5 A 1.01 Battery capacity as it is affected by discharge rate. (CFR: 41.5/ 45.5) 2.4.11 Knowledge of abnormal condition procedures.

4.0 (CFR: 41.10/43.5/45.13)

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

2.7 A2.08 Consequences of opening/closing breaker between buses (VARS, out-of-phase, voltage). (CFR: 41.5/43.5/45.3/45.13)

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

3.6 K3.01 Radioactive effluent releases. (CFR: 41.7/45.6)

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

3.5* A2.01 Loss of SWS. (CFR: 41 .5 / 43.5 / 45.3 / 45.13) A4 Ability to manually operate and/or monitor in the control room: 3.5* 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 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* [Question 52] and/or cause-effect relationships between lAS 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 [Question 53] in the control room: 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 [Question 54] malfunction of the containment system will 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 [Question 55] containml3nt system, including:

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 System # / Name 015 Nuclear

[Question 016

[Question 57] 017 In-Core Monitor System [Question 58] 029 Containment [Question 045 Main Turbine

[Question 055 Condenser Air [Question 068 Liquid

[Question 071 Waste Gas Disposal [Question 63] -Tier 21Group 2(RO) KJA Topic(s) IR K5 Knowledge of the operational implications of the following concepts as they apply to the NIS: 2.6 K5.04 Factors affecting accuracy and reliability of calorimetric calibrations. (CFR: 41.5/45.7)

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

2.8* K4.01 Reading of NNIS channel values outside control room. (CFR: 41.7) K6 Knowledge of the effect of a loss or malfunction of the ITM system components:

2.7 K6.01 Sensors and detectors. (CFR: 41.7/45.7)

2.4.9 Knowledge

of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

3.8 (CFR: 41.10 / 43.5 / 45.13) A 1 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with MT/G system controls including:

3.8 A 1.05 Expected response of primary plant parameters (temperature and pressure) following TJG trip. (CFR: 41.51 45.5) Kl Knowledge of the physical connections and/or cause-effect relationships between the CARS and the following systems: 2.6 Kl.06 PRM system. (CFR: 41.2 to 41.9 /45.7 to 45.8) A3 Ability to monitor automatic operation of the Liquid Radwaste system including:

3.6 A3.02 Automatic isolation. (CFR: 41.71 45.5) A2 Ability to (a) predict the impacts of the following malfunctions or operations on the 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:

2.5 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* [Question 64] following:

K2.03 Emergency/essential SWS pumps. (CFR: 41.7) 086 Fire Protection A4 Ability to manually operate and/or monitor 3.3 [Question 65] in the control room: 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 Category KJA# 1. Conduct of Operations 2.1.7 2.1.19 2.1.38 Subtotal 2. 2.2.44 Equipment Control 2.2.43 Subtotal 3. 2.3.4 Radiation Control 2.3.5 2.3.7 Subtotal 4. 2.4.34 Emergency Procedures/

Plan 2.4.49 Subtotal int Total RO Topic IR # Ability to evaluate plant performance and make operational judgments

4.4 based

on operating characteristics, reactor behavior, and instrument interpretation. (CFR: 41.5/43.5/45.121 45.13) [Question 66] Ability to use plant computers to evaluate system or component status. 3.9 (CFR: 41.10 / 45.12)[Question 67] Knowledge of the stations requirements for verbal communications when 3.7* implementing procedures. (CFR: 41.10/45.13)

[Question 68] Ability to interpret control room indications to verify the status and operation of a system and understand how operator actions and directives affect plant and system conditions. (CFR: 41.5/43.5/45.12)

[Question 69] Knowledge of the process to track inoperable alarms. 3.0 (CFR: 41.10/43.5/45.13)

[Question 70] Knowledge of radiation exposure limits under normal or emergency conditions. (CFR: 41.12/43.4/45.10)

[Question 71] 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] Ability to comply with radiation work permit during normal 3.5 or abnormal conditions. (CFR: 41.12/45.10)

[Question 73] Knowledge of RD tasks performed outside the main control room during an emergency and the resultant operational effects. (CFR: 41.10/43.5/45.13)

[Question 74] 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] NUREG-1 021. Revision 9 Supplement 1 RO Page 13 of 13 FENoe Facsimile Rev 2 PWR Examination Outline Form ES-401*2 SRO ONLY Points Tier Group G* TOTAL 3 3 6 1. Emergency 2 2 4 Tier Plant 5 10 Totals Evolutions 2 2. Plant 0 2 1 3 Systems Tier 5 3 8 Totals 1 3 4 3. Generic Knowledge and 7 Abilities Category 2 1 2 Note: Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and 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). 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. 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. 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. 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. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories. 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. 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. 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 FENOC Facsimile Rev 2 ES*401 PWR Examination Outline Form ES*401*2 Emergency and Abnormal Plant Evolutions*

Tier lIGroup 1 (SRO)

E/APE # / Name 1 Safety Function 000015/17 RCP Malfunctions 14 [Question 76] 000057 Loss of Vital AC Inst. Bus I 6 [Question 77] 000065 Loss of Instrument Air I 8 [Question 78] W/E05 Inadequate Heat Transfer -Loss of Secondary Heat Sink I 4 [Question 79J W/E11 Loss of Emergency Coolant Recirc / [Question W/E12 Steam Line Rupture -Excessive Heat Transfer I 4 [Question 81J KIA Category Point Totals: KIA Topic(s) IR # A,A2 Ability to determine and interpret the following 2.9 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) 2.2.36 Ability to analyze the effect of maintenance 4.2 activities, such as degraded power sources, on the status of limiting conditions for operations. (GFR 41.10/43.2/45.13)

A.A2 Ability to determine and interpret the following 2.9 as they apply to the Loss of Instrument Air: AA2.03 Location and isolation of leaks. (CFR: 43.51 45.13) EA2 Ability to determine and interpret the following 4.3 as they apply to the (Loss of Secondary Heat Sink) EA2.2 Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments. (GFR: 43.5/45.13) 2.1.20 Ability to interpret and execute procedure 4.6 steps. (CFR: 41.10/43.5/45.12)

2.1.7 Ability

to evaluate plant performance and make 4.7 operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. (CFR: 41.5/43.5/45.12/45.13)

Group Point Total:

6 NU REG-1 021, Revision 9 Supplement 1 SRO Page 2 of 6 FENoe Facsimile Rev 2 ES-401 E/APE # I Name I Safety Function 000001 Continuous Rod Withdrawal 1 1 [Question 82] 000005 Inoperable 1 Stuck Control Rod 1 1 [Question 83] 000036 Fuel Handling Accident / 8 [Question 84] W/E06 Inadequate Core Cooling 1 4 [Question 85] KIA Category Point Totals: PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions

-Tier 1/Group 2(SRO) KIA Topic(s)

Ability to interpret control room indications verify the status and operation of a system, understand how operator actions and affect plant and system (CFR: 41.51 43.S 1 AA2 Ability to determine and interpret the as they apply to the Inoperable 1 Stuck Control J\A2.03 Required actions if more than one rod stuck or (CFR: 43.5/45.J\A2 Ability to determine and interpret the as they apply to the Fuel Handling AA2.02 Occurrence of a fuel handling (CFR: 43.5 1 Knowledge of the specific bases for (CFR: 41.10/43.1/45.13Group Point IR # 4.4 4.4 4.1 4.0 NUREG-1 021, Revision 9 Supplement 1 SRO Page 3 of 6 FENoe Facsimile Rev 2 4 ES*401 PWR Examination Outline Form E5-401*2 Plant Systems System # / Name 005 Residual Heat [Question 006 Emergency Core Cooling [Question 87] 008 Component Cooling Water [Question 88] 059 Main Feedwater

[Question 89] 073 Process Radiation Monitoring

[Question 90] ry Point Totals: -Tier 2/Group 1 (SRO) KIA Topic(s) A2 Ability to (a) predict the impacts of the following malfunctions or operations on the RHRS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.04 RHR valve malfunction. (CFR: 41 .5/ 43.5 / 45.3 /45.13) 2.2.22 Knowledge of limiting conditions for operations and safety limits. 4.7 (CFR: 41 .5/43.2/45.2)

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

3.6 A2.01 Loss of CCW pump. (CFR: 41.5/43.5/45.3/45.13) 2.4.45 Ability to prioritize and interpret the significance of each alarm or annunciator.

4.3 (CFR: 41 .. 10 / 43.5 /45.3/45.12)

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

2.9* A2.01 Erratic or failed power supply. (CFR: 41.5 / 43.5 /45.3/45.13) 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 System #-/ Name 011 Pressurizer Level Control [Question 91] 014 Rod Position Indication

[Question 92] 034 Fuel Handling Equipment

[Question 93] KIA Category Point Totals: -Tier 21Group 2(SRO) KIA Topic(s) IR A2 Ability to (a) predict the impacts of the following malfunctions or operations on the PZR LCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

3.7 A2.0S Loss of PZR heaters. (CFR: 41.S / 43.51 45.3/45.13)

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

4.1 2.4.9 Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

4.2 (CFR: 41.10/43.5/45.13)

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 Category KlA# 1. 2.1.7 Conduct of Operations 2.1.36 Subtotal 2. 2.2.15 Equipment Control 2.2.40 Subtotal 3. 2.3.13 Radiation Control Subtotal 4. 2.4.8 Emergency Procedures/

Plan 2.4.44 Subtotal Topic SROOnly IR # Ability to evaluate plant performance and make operational judgments based on operating charactoristics, reactor behavior, and instrument interpretation.

4.7 (CFR: 41.5 / 43.5 / 45.12 / 45.13) [Question 94] Knowledge of procedures and limitations involved in Gore alterations.

4.1 (CFR: 41.10/43.6/45.7)

[Question 95] 2 Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, ups, tagouts, etc. (CFR: 41.10/43.3/45.13)

[Question 96] Ability to apply technical specifications for a system. 4.7 (CFR: 41.10/43.2/43.5/45.3)

[Question 91] 2 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, 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] 1 Knowledge of how abnormal operating procedures are used in conjunction with EOP's. (CFR: 41.10/43.5/45.13)

[Question 99] Knowledge of emergency plan protective action recommendations.

4.4 (CFR: 41.10 / 41.12 / 43.5 / 45.11) [Question 100] 2 Tier 3 Point Total NUREG-1 021, Revision 9 Supplement 1 SRO Page 6 of 6 FENoe Facsimile Rev 2 7 ES-Facility:

BVPS UNIT 1 Tier /

Group Selected 1/1 026 AA1.03 1/1 027 AK1.01 1/1 029 EK3.02 1/1 040 AA1.22 1/1 0542.2.1 1/1 0622.4.37 1/2 051 2.1.43 211 004 K2.02 2/1 0252.4.39 2/1 025 A4.10 2/1 0262.2.41 2/1 0632.4.12 2/2 0292.4.26 2/2 068 A3.01 ..NUREG-1 021, ReVISion 9 Supplement 1 R ecor d 0 f R*e!Jec t e d KIA s F orm ES-401 -4 Date of Exam 4/9 thru 4/20 2012 Operating Test No.: 1 LOT8 NRC Reason fClr Rejection RO OUTLINE SWS backup to CCWS is not applicable at 026AA1.02 reselected for Ouestion Definition of saturation temperature is fundamental knowledge.

Unable construct a discriminatory question.

Reselected based on 12119 discussion Lead 027 AK1.02 reselected for Ouestion # Starting specific charging pumps is not applicable to an ATWS at 029 EK3.12 reselected for Ouestion # Load sequencer status lights are not applicable to 040 AA 1.02 reselected for Ouestion # *ES-401 D.1.b requires excllusion of generic KlAs for Tier 1 & 2. These KlAs were not suppressed and therefore were not automatically omitted PWROG Random Generator (manually reselected from same generic 054 2.2.44 reselected for Question # 12.

  • Same as above. 2.4.1 was initially reselected.

Since BVPS Loss of Service Water AOP contains no immediate action steps another section Generic KIA was manually 062 2.4.4 reselected for QUlestion

  1. 16.
  • Same as 051 2.1.20 reselected for Question # Make-up pumps are not applicable to the BVPS design. Author/Exam believed this KIA was referencing positive displacement makeup pumps. Follow-up discussion with Lead Examiner revealed this KIA is referring to Primary up (PG) pumps. Unit 1 currEmtly uses Unit 2 PG pumps. 004 K2.06 reselected for Question # Ice Condensers are not applicable to the BVPS 006 2.4.4 reselected for QUl9stion
  1. Ice Condensers are not applicable to the BVPS 007 K5.02 reselected for Question # 007 A4.1 0 reselected based on NRC Lead Examiner
  • Same as 026 2.2.39 reselected for Question #
  • Same as above. 0632.4.11 reselected for Question # 47.
  • Same as 029 2.4.9 reselected for QUl9stion
  1. Evaporators are no longer Llsed for Liquid Radwaste at 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 1 LOT8 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)

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 Facility:

BVPS Unit 1 Examination Level SRO [8] rative Topic Type (See Note) Code* Conduct of Operations N, R (SRO A.1.1) Conduct of Operations N,R (SRO A.1.2) Equipment Control N,R (SRO A.2) Radiation Control N,R (SRO A.3) Emergency N,R ProcedureS/Plan (SRO A.4) topics, when al15 are required.

  • Type Codes & Criteria NUREG*1 021, Revision 9 Supplement 1 Administrative To ics Outline Form E5-301-1 Date of Examination
4/9 'lhru 4/20/2012 Operating Test Number 1 LOT8 NRC Describe activity to be performed 2.1.43 (4.3) 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 2.1.25 (4.2) Ability to interpret reference materials, such as graphs, curves, (1 AD-031) Review Shutdown Margin 2.2.37 Ability to determine operability and/or availability of safety (1AD-026)

Review/Approve Completed Surveillance of RHR 2.3.11 Ability to control radiation (1AD-023)

Review/Approve LW 2.4.40 Knowledge of SRO responsibilities in emergency plan (1AD-015)

Comple'te Initial Noti'fication Form for a General (C)ontrol Room, (S)imulator, or (D)irect from bank G;, 3 for ROs; S 4 for SROs & RO (N)ew or (M)odified from bank (P)revious 2 exams G;, 1:; randomly FENOC Facsimile Rev 2 Control Room/In-Plant S stems Outline Form E8-301-2 Facility:

BVPS UNIT Date of Examination:

4/9 thru 4/20/2012 evel: RO r&l Operating Test No.: 1 lOTa 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 (E}mergency or abnormal in-plant (EN)gineered safety feature -I -f.=!: 1 (Control room system) (L)ow-power

/ Shutdown (N}ew or (M}odified from bank including 1 (A) (P)revious 2 exams 31 3 12 (randomly selected)

{R)CA

{S)imulator NUREG*1 021, Revision 9 Supplement 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.: 1 LOT8 NRC ; (7 for (2 or 3 for 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 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 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.: 1 LOTa 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 FENoe Facsimile Rev 2 d 0 Appen Ix lor Scenaro ut me 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 Turnover:

Continue power increase IA W reactivity plan and commence turbine 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. N/A (R)ATC Raise power 1 (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 1 OB (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 IMFPRS09A (10) 0 (C)ATC, SRO Pzr spray valves and remaining PORV fail to open during 8 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 Out Ii 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.

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

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

IMF CRF04BV (22) (C)ATC, SRO 2 Rods drop during power reduction

-requires manual Rx trip.S 1 Loss of 4kv busses, "A", "B" and AE occurs on Rx trip IMF CRF04BT (24) 1 TRG3 'IMP (M)ALL "C" SG Steam Break occurs on Rx trip -causes Safety Inj. 6 MSS18C (00) 6E5' IMF SISIOA (C) ATC, SRO Automatic SI fails to actuate -requires manual actuation.

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

IMF EPS04F (1 10) IMPFWMllC (4 30) (M)ALL Loss of all Aux Feedwater flow, requires entry into FR-H.l 9 IMF FWMI1A (00) (N)onnal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Supplement FENOC Facsimile Rev. 2 Appendix 0 cenano u meS . 0 tr 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.

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. IMP PRS06A (0 0) 0 (I)ATC, SRO LT-IRC459 fails low, letdown isolates, crew removes 1 5 (TS) SRO channel from service. N/A (N)BOP, SRO Restores letdown 2 IMP TUR15 (0 0) 78 (C)ATC, SRO Turbine valve position limiter fails low, causes -100 mw load 3 10 (TS) SRO reduction, 1 Rod stuck at ARO position.

IMP CRFIIBR 0 IMP FWM09C (1 0) (C) BOP, SRO "C"SG Feedwater valve, FCV-IFW-498, begins oscillating, 4 250 requiring BOP to manually control level. IMF TUR03E (0 0) (C) BOP, SRO Turbine high bearing vibration requires crew to manually trip 5 158 the unit. IMP CRF02A (5 0) (M)ALL Reactor fails to trip from the control room, requires entry into 6 IMFCRFl2A FR-S.1, ATC manually inserts control rods. IMFCRF12B IMFINH20 (C)BOP, SRO All Aux Feedwater pumps fail to automatically start, requires 7 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.

IMPINH49 (C)ATC, SRO Train "A" CIA fails to actuate along with train "B" valve 9 IMP VL V -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 FENoe Facsimile Rev. 2

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