ML14246A233

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Draft - Outlines (Folder 2)
ML14246A233
Person / Time
Site: Beaver Valley
Issue date: 07/01/2014
From:
FirstEnergy Nuclear Operating Co
To: Brian Fuller
Operations Branch I
Shared Package
ML14058A120 List:
References
U01884
Download: ML14246A233 (33)
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Text

ES-401 PWR Examination Outline Form ES-401-2 Facil Date of Exam 7/7 thru 7118 2014 RO KIA Catego Points Tier Group K K K K K K A A A A G TOTAL 1 2 3 4 5 6 1 2 3 4

  • 1 3 4 2 3 18 1.

Emergency 2

& 1 2 1 1 9 Abnormal Plant Tier Evolutions Totals 4 6 3 4 27 1

2. 3 2 3 3 2 2 3 3 2 2 3 28 Plant Systems 2 0 0 1 1 1 1 1 2 1 1 1 10 Tier Totals 3 2 4 4 3 3 4 s, 3 3 4 38 1 2 3 4
3. Generic Knowledge and Abilities Category 10 3 3 2 2 Note:
1. Ensure that at least two topics from every applicable KIA cate~Jory 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 :~5 points.
3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KIA statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those KIAs having an importance rating (IR) of 2.5 or higher shall be selected.

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

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

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

8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals{#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the KIA catalog, ancl enter the KIA numbers, descriptions, IRs, and point totals(#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43.

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

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

~=======================F=r=F=F9 EIAPE #I Name I Safety Function KIA Topic(s) IR #

000007 Reactor Tripl1 EK2 Knowledge of the interrelations between a 2.6 reactor trip and the following:

[Question 1]

EK2.02 Breakers, relays and disconnects (CFR 41.7 145.7) 000008 Pressurizer (PZR) Vapor AK2 Knowledge of the interrelations between the 2.7*

Accident (Relief Valve Stuck Open)l3 Pressurizer Vapor Space Accident and the followi,ng:

[Question 2]

AK2.01 Valves (CFR 41.7 145.7) 000011 Large Break LOCA/3 EK3 Knowledge the reasons for the g 4.2 responses as the apply to the Large Break LOCA:

[Question 3]

EK3.09 Maintaining DIGs available to provide standby power (CFR 41.5 141.10 145.61 45.13) 0000151000017 Reactor Pump AK2 Knowledge of the interrelations between the 2.9 (RCP) Malfunctionsl4 Reactor Coolant Pump Malfunctions (Loss of RC Flow) and the following:

[Question 4]

AK2.07 RCP seals (CFR 41.7 145.7) 000022 Loss of Reactor Coolant Makeupl2 2.4.41' Ability to diagnose and recognize trends in 4.2 an accurate and timely manner utilizing the appropriate control room reference material.

.:stion 5]

(CFR: 41.10 143.5145.12) 000025 Loss of Residual Heat Removal AK2. Knowledge of the interrelations between the 2.6 System (RHRS)I4 Loss of Residual Heat Removal System and the following:

[Question 6]

AK2.05 Reactor building sump 000027 Pressurizer Pressure Control Ability to operate and or monitor the following 3.1

  • System (PZR PCS) Malfunctionl3 as the~y apply to the Pressurizer Pressure Control Malfunctions:

[Question 7]

M 1.02 SCR-controlled heaters in manual mode (CFR 41.7 145.5145.6) 000029 Anticipated Transient Without EK1 Knowledge of the operational implications of 2.8 Scram (ATWS)I1 the following concepts as they apply to the ATWS:

EK1.05 definition of negative temperature

[Question 8]

coefficient as applied to large PWR coolant systems (CFR 41.8 141.10 145.3)

AK1 Knowledge of the operational implications of 3.4 the following concepts as they apply to Steam Line Rupture:

[Question 9]

AK1.07 Effects of feedwater introduction on dry SIG (CFR 41.8 I 41.1 0 I 45.3)

NUREG-1021, Revision 9 Supplement 1 RO Page 2 of 13 FENOC Facsimile Rev. 1

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions- Tier 1/Group 1(RO) Continued EIAPE #I Name I Safety Function KIA Topic(s) IR #

000054 Loss of Main Feedwater (MFW)I4 AA 1 Ability to operate and I or monitor the following 3.5 as they apply to the Loss of Main Feedwater (MFW):

[Question 10]

AA 1.03 AFW auxiliaries, including oil cooling water supply (CFR 41.7 I 45.5 I 45.6) 000056 Loss of Offsite Powerl6 2.4.34 Knowledge of RO tasks performed outside 4.2 the main control room during an emergency and the resultant operational effects.

[Question 11]

(CFR: 41.10143.5 I 45.13) 000057 Loss of Vital AC Electrical AK3 Knowledge the reasons the following 4.1 Instrument Busl6 responses as they apply to the Loss of Vital AC Instrument Bus:

[Question 12] AK3.01 Actions contained in EOP for loss of vital ac electrical instrument bus (CFR 41.5 I 41.10 I 45.6 I 45.13) 000058 Loss of DC Powerl6 AK1 Knowledge of the operational implications of 2.8

[Question 13] the following concepts as they apply to Loss of DC Power:

AK1.01 Battery charger equipment and instrumentation (CFR 41.8 I 41.10 I 45.3)

IJvJ062 Loss of Nuclear Service Waterl4 AA2 Ability to determine and interpret the ng 2.8*

[Question 14] as they apply to the Loss of Nuclear Service Water:

AA2.06 The length of time after the loss of SWS flow to a component before that component may be dama!led (CFR: 43.5 I 45.13) 000065 Loss of Instrument Airl8 AA2 Ability to determine and interpret the following 2.6

[Question 15] as they apply to the Loss of Instrument Air:

AA2.03 Location and isolation of leaks (CFR: 43.5 I 45.13) 000077 Generator Voltage and Electric Grid AA2 Ability to determine and interpret the ng 3.9 Disturbancesl6 as they apply to Generator Voltage and Electric

[Question 16] Grid Disturbances:

AA2.09 Operational status of emergency diesel generators (CFR: 41.5 and 43.5 I 45.5, 45.7, and 45.8)

WIE04 LOCA Outside ContainmenU3 2.4.47 Ability to diagnose and recognize trends n 4.2

[Question 17] an acc:urate and timely manner utilizing the appropriate control room reference material.

(CFR: 41.10 I 43.5 I 45.12)

NUREG-1 021, Revision 9 Supplement 1 RO Page 3 of 13 FENOC Facsimile Rev. 1

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

~=======================r=r9F9F9 EIAPE #I Name I Safety Function K K K KIA Topic(s) IR #

1 2 3 WIE11 Loss of Emergency Coolant EA 1 Ability to operate and I or monitor the following 3. 7 Recirculationl4 as they apply to the (Loss of Emergency Coolant

[Question 18] Recirculation)

EA 1.3 Desired operating results during abnormal and emergency situations.

(CFR: 41.7 145.5 I 45.6)

KIA Category Point Totals: Group Point Total: 18 NUREG-1 021, Revision 9 Supplement 1 RO Page 4 of 13 FENOC Facsimile Rev. 1

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

IF===========================~9F=r=T~~

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

000003 Dropped Control Rod/1 Knowledge the operational implications of the 2.6 (Question 19] following concepts as they apply to Dropped Control Rod:

AK1.1 0 Definitions of core quadrant power tilt (CFR 41.8 /41.10 /45.3) 000005 Inoperable/Stuck Control Rod/1 AK2 Knowledge of the interrelations between the 2.5

[Question 20] Inoperable I Stuck Control Rod and the following:

AK2.02 Breakers, relays, disconnects, and control room switches (PZR) Level M 1 Ability to operate and I or monitor lowing 2.7 as the'y apply to the Pressurizer Level Control Malfunctions:

M 1.04 Regenerative heat exchanger and tempe!rature limits (CFR 41.7 /45.5/45.6) 000060 Accidental Gaseous to determine ret the following 2.6 Release/9 as the'y apply to the Accidental Gaseous Radwaste:

[Question 22]

M2.04 The effects on the power plant of isolating a given radioactive-gas leak (CFR: 43.5/ 45.13) 161 Area <>rto<>toron Monitoring (ARM) M 1 Ability to operate and I or monitor the following 3.6

~ Jtem Alarms/7 as the'y apply to the Area Radiation Monitoring

[Question 23] (ARM)System Alarms:

E-'I'YY""~ M 1.01 Automatic actuation (CFR 41.7 /45.5 I 45.6)

Plant fire on site/9 to determine ret the following 2.9

[Question 24] as thE!Y apply to the Plant Fire on Site:

M2.12 Location of vital equipment within fire zone (CFR: 43.5/ 45.13)

W/E06 Degraded Cooling/4 2.1.2~i Ability to interpret reference materials, such 3.9

[Question 25] as graphs, curves, tables, etc.

(CFR: 41.10 /43.5/45.12)

W/E08 Pressurized Thermal Shock/4 EK3 Knowledge of the reasons for the following 3.4 (Question 26] responses as they apply to the (Pressurized Thermal Shock)

EK3.1 Facility operating characteristics during transi,ent conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity chan~1es and operating limitations and reasons for these operating characteristics.

(CFR: 41.5/41.10 /45.6/ 45.13)

NUREG-1021, Revision 9 Supplement 1 RO Page 5 of 13 FENOC Facsimile Rev. 1

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions -Tier 1/Group 2(RO) Continued IF===========================~9F=r=r==

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

W/E 13 Steam Generator Overpressure/4 EK2 Knowledge of the interrelations between the 3.0

[Question 27] (Stearn Generator Overpressure) and the following:

EK2.2 Facility's heat removal systems, including prima1y coolant, emergency coolant, the decay heat removal systems, and relations between the proper operaltion of these systems to the operation of the facility.

(CFR: 41.7 /45.7)

KIA Category Point Totals: Group Point Total: 9 NUREG-1021, Revision 9 Supplement 1 RO Page 6 of 13 FENOC Facsimile Rev. 1

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

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

1 003 Reactor Coolant Pump K6 Knowledge of the effect of a loss or 2.6 System (RCPS) malfunction on the following will have on the

[Question 28] RCPS:

K6.14 Starting requirements (CFR: 41.7/45.5) 003 Reactor Coolant Pump K3 Knowledge of the effect that a loss or 3.5 System (RCPS) malfunction of the RCPS will have on the

[Question 29] following:

K3.02 S/G (CFR: 41.7 /45.6) 004 Chemical and Volume K4 Knowledge of CVCS design feature(s) 2.8 Control System (CVCS) and/or interlock(s) which provide for the

[Question 30] following:

K4.01 Oxygen control in RCS (CFR: 41.7) 005 Residual Heat Removal K5 Knowledge of the operational 2.9*

System (RHRS) of the following concepts as they apply the

[Question 31] RHRS:

K5.03 Reactivity effects of RHR fill water (CFR: 41.5/45.7) 006 Emergency Core Cooling K3 Knowledge of the effect that a loss or 4.2 em (ECCS) malfunction of the ECCS will have on the L'-"uestion 32] following:

007 Relief 12 Knowledge surveillance procedures. 3.7 Tank/Quench Tank System (CFR: 41.10 /45.13)

(PRTS)

[Question 33]

007 Pressurizer Relief A2 Ability to (a) predict the impacts of the 3.9 Tank/Quench Tank System following malfunctions or operations on the (PRTS) PRTS; and (b) based on those predictions, use

[Question 34] procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.01 Stuck-open PORV or code safety (CFR: 41.5/43.5 /45.3/45.13) 008 Component Cooling Water K3 Knowledge of the effect that a loss or 3.4 System (CCWS) malfunction of the CCWS will have on the

[Question 35] following:

K3.01 Loads cooled by CCWS (CFR: 41.7 /45.6)*

010 Pressurizer Pressure A4 Ability to manually operate and/or monitor 4.0 Control System (PZR PCS) in the control room:

ff"'*Jestion 36]

A4.03 PORV and block valves (CFR: 41.7 /45.5 to 45.8)

NUREG-1021, Revision 9 Supplement 1 RO Page 7 of 13 FENOC Facsimile Rev. 1

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems -Tier 2/Group 1(RO) Continued IF==================F=F9F9F9F9F=F=

System # I Name KIA Topic(s) IR #

010 Pressurizer Pressure K4 Knowledge of PZR PCS design feature(s) 2.7 Control System (PZR PCS) and/or interlock(s) which provide for the

[Question 37] following:

K4.01 Spray valve warm-up (CFR: 41.7) 012 Reactor Protection ""'"r.. ,m K2 Knowledge of bus power supplies to the 3.3

[Question 38] following:

K2.01 RPS channels, components, and interconnections (CFR: 41.7) 012 Protection System K6 Knowledge of the effect of a loss or 2.8

[Question 39] malfunction of the following will have on the RPS:

K6.01 Bistables and bistable test equipment (CFR: 41.7/45.7) 013 Engineered Safety Features K1 Knowledge of the physical connections 3.8 Actuation System (ESFAS) and/or cause effect relationships between the

[Question 40] ESFAS and the following systems:

K1.03 CCS (CFR: 41.2 to 41.9/45.7 to 45.8)

' Containment Cooling A3 Ability to monitor automatic operation the 4.1

.em (CCS) CCS, including:

[Question 41]

A3.01 Initiation of safeguards mode of operation (CFR: 41.7/45.5) 026 Containment Spray System K1 Knowledge of the physical connections 4.2 (CSS) and/or cause/effect relationships between the

[Question 42] CSS and the following systems:

K1.01 ECCS (CFR: 41.2 to 41.9/45.7 to 45.8) 026 Containment Spray System A4 Ability to manually operate and/or monitor 3.5 (CSS) in the control room:

[Question 43]

A4.05 Containment spray reset switches (CFR: 41.7 /45.5 to 45.8) 039 Main and Reheat Steam 2.2.39 Knowledge of less than or equal to one 3.9 System (MRSS) hour Technical Specification action statements

[Question 44] for systems.

(CFR: 41.7/41.10 /43.2/45.13)

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

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

~=================r=r=F=F9F9F=F=

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

1 2 039 Main and Reheat Steam A 1 Ability to predict and/or monitor changes in 2.5*

System (MRSS) parameters (to prevent exceeding design

[Question 45) limits) associated with operating the MRSS controls including:

A 1.09 Main steam line radiation monitors (CFR: 41.5 I 45.5) 059 Main Feedwater (MFW) A2 Ability to (a) predict the impacts of the 3.0*

System following malfunctions or operations on the

[Question 46) MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.11 Failure of feedwater control system (CFR: 41.5/43.5/45.3/ 45.13) 061 Auxiliary I Emergency K5 Knowledge of the operational implications 2.6 Feedwater (AFW) System of the following concepts as the apply to the

[Question 47) AFW:

K5.03 Pump head effects when control valve is shut (CFR: 41.5/ 45. 7) 062 AC Electrical Distribution A 1 Ability to predict and/or monitor changes in 3.4

~"stem parameters (to prevent exceeding design

~stion 48) limits) associated with operating the ac distribution system controls including:

A 1.01 Significance of DIG load limits (CFR: 41.5/ 45.5) 063 DC Electrical Distribution A3 Ability to monitor automatic operation of the 2. 7 System DC electrical system, including:

[Question 49)

A3.01 Meters, annunciators, dials, recorders, and indicating lights (CFR: 41.7 /45.5) 064 Emergency K1 Knowledge of the physical connections 3.6 Generator (ED/G) System and/or cause/effect relationships between the

[Question 50] ED/G system and the following systems:

K1.04 DC distribution system (CFR: 41.2 to 41.9 /45.7 to 45.8) 073 Process Radiation A 1 Ability to predict and/or monitor changes in 3.2 Monitoring (PRM) System parameters (to prevent exceeding design

[Question 51) limits) associated with operating the PRM system controls including:

A 1.01 Radiation levels (CFR: 41.5 I 45.7)

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

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

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

System # I Name KIA Topic(s) IR #

076 Service Water System K4 Knowledge of SWS design feature(s) 2.5*

(SWS) and/or interlock(s) which provide for the (Question 52] following:

K4.01 Conditions initiating automatic closure of closed cooling water auxiliary building header supply and return valves (CFR: 41.7) 078 Instrument Air System (lAS) K2 Knowledge of bus power supplies to the 2.7 (Question 53] following:

K2.01 Instrument air compressor (CFR: 41.7) 103 Containment System 2.1.19 Ability to use plant computers to 3.9

[Question 54] evaluate system or component status.

(CFR: 41.10/45.12) 103 nment System A2 Ability to (a) predict the impacts of the 3.5*

(Question 55] following malfunctions or operations on the containment system and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.03 Phase A and B isolation (CFR: 41.5/43.5 /45.3/45.13)

KIA Category Point Totals: Group Point Total: 28 NUREG-1021, Revision 9 Supplement 1 RO Page 10 of 13 FENOC Facsimile Rev. 1

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

- Tier 2/Group 2{RO)

System # I Name K K KIA Topic(s) 1 2 IR 001 Control Rod Drive System K6 Knowledge of the effect of a loss or 2.8

[Question 56] malfunction on the following CRDS components:

K6.02 Purpose and operation of sensors feeding into the CRDS (CFR: 41.7/45.7) 011 A 1 Ability to predict and/or monitor changes in 3.1 System (PZR LCS) parameters (to prevent exceeding design limits)

[Question 57] associated with operating the PZR LCS controls including:

A1.04 T-ave (CFR: 41.5/45.5) 014 Rod Position Indication 2.2.37 Ability to determine operability and/or 3.6 System (RPIS) availability of safety related equipment.

[Question 58] (CFR: 41.7 /43.5/45.12) 015 Nuclear Instrumentation K3 of the effect that a loss or 3.9 System (NIS) malfunction of the NIS will have on the

[Question 59] following:

K3.01 RPS (CFR: 41.7 /45.6) 016 Non-Nuclear A3 Ability to monitor automatic operation of the 2.9*

ln~trumentation System (NNIS) NNIS, including:

stion 60]

A3.02 Relationship between meter readings and actual parameter value (CFR: 41.7 /45.5) 034 Fuel Handling Equipment K4 Knowledge of design feature(s) and/or 2.6 System (FHES) interlock(s) which provide for the following:

[Question 61]

K4.01 Fuel protection from binding and dropping (CFR: 41.7) 041 Steam Dump System A2 Ability to (a) predict the impacts of the 2.8 (SDS)/Turbine Bypass Control following malfunctions or operations on the

[Question 62] SDS; and (b) based on those predictions use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.03 Loss of lAS (CFR: 41.5/43.5 /45.3 /45.13) 056 Condensate A2 Ability to (a) predict the impacts of the 2.6

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

A2.04 Loss of condensate pumps (CFR: 41.5/ 43.5/ 45.3/ 45.13)

NUREG-1021, Revision 9 Supplement 1 RO Page 11 of 13 FENOC Facsimile Rev. 1

ES-401 PWR Examination OIUtline Form ES-401-2 Plant Systems - Tier 2/Group 2(RO) Continued System # I Name K KIA Topic(s)

IR #

1 075 Circulating Water System A4 Ability to manually operate and/or monitor 3.2*

[Question 64] in the control room:

A4.01 Emergency/essential SWS pumps (CFR: 41.7 /45.5 to 45.8) 086 Fire Protection System K5 Knowledge of the operational 3.1 (FPS) the following concepts as they apply to the Fire

[Question 65] Protection System:

K5.03 Effect of water spray on electrical components (CFR: 41.5/45.7)

KIA Category Point Totals: 0 Group Point Total: 10 NUREG-1 021, Revision 9 Supplement 1 RO Page 12 of 13 FENOC Facsimile Rev. 1

ES 401 Generic Knowledge and Abilities C>utline (Tier 3) Form ES-401-3

.l "cility: BVPS UNIT 1 RO Date ofExam 7/7 thru 7/18 2014 RO Category KJA# Topic IR #

1. 2.1.5 Ability to use procedures related to shift staffing, :such as minimum crew 2.9*

Conduct complement, overtime limitations, etc.

of Operations (CFR: 41.10 I 43.5 I 45.12)

[Question 66]

2.1.20 Ability to interpret execute procedure steps. 4.6 (CFR: 41.10 I 43.5 I 45.12)

[Question 67]

2.1.27 Knowledge of system purpose and/or function. 3.9 (CFR: 41.7)

[Question 68]

Subtotal

2. 2.2.36 Ability to analyze the effect of maintenance activities, such as degraded Equipment power sources, on the status of limiting conditions for operations.

Control (CFR: 41.10 I 43.2 I 45.13)

[Question 69]

2.2.37 Ability to determine operability and/or availability of safety related 3.6 equipment.

(CFR: 41.7 I 43.5 I 45.12)

[Question 70]

2.2.42 Ability to recognize system parameters that are entry-level conditions for 3.9 Technical Specifications.

(CFR: 41.7 I 41.10 I 43.2 I 43.3 I 45.3)

[Question 71]

Subtotal

3. 2.3.12 Knowledge of radiological safety principles pertaining to licensed Radiation operator duties, such as containment entry requirements, fuel handling Control responsibilities, access to locked high-radiation areas, aligning filters, etc.

(CFR: 41.12 I 45.9 I 45.10)

[Question 72]

2.3.14 Knowledge of radiation or contamination hazards that may arise during 3.4 normal, abnormal, or emergency conditions or activities.

(CFR: 41.12 I 43.4 I 45.10)

[Question 73]

Subtotal

4. 2.4.2 Knowledge of system set points, interlocks and automatic actions Emergency associated with EOP entry conditions.

Procedures/ (CFR: 41.7 I 45.7 I 45.8)

Plan [Question 74]

2 .4_ 31 Knowledge of annunciator alarms, indications, or response procedures. 4.2 (CFR: 41.10 I 45.3)

[Question 75]

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

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

SRO ONLY Points Tier Group A2 G* TOTAL 1

3 3 6 1.

Emergency 2

& 2 2 4 Abnormal Plant Tier Totals 5 5 10 Evolutions 1

2. 3 2 5 Plant Systems 2 0 2 1 3 Tier Totals 5 3 8 1 2 3 4 7
3. Generic Knowledge and Abilities Category 2 1 2 2 Note:
1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two).
2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KIA statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those KIAs having an importance rating (IR) of 2.5 or higher shall be selected.

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

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

7.* The generic (G) KIAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section 0.1.b of ES-401 for the applicable KIAs.

8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (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 KIAs that are linked to 10 CFR 55.43.

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

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

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

EIAPE #I Name I Safety Function K K K KIA Topic(s) IR #

1 2 3 000009 Small Break LOCA/3 2.4.8 Knowledge of how abnormal operating 4.5

[Question 76] procedures are used in conjunction with EOPs.

(CFR: 41.10 I 43.5 I 45.13) 000026 Loss of Component Cooling Water M2 Ability to determine and interpret the following 3.6 (CCW)I8 as they apply to the Loss of Component Cooling

[Question 77] Wate1r:

M2.02 The cause of possible CCW loss (CFR: 43.5 I 45.13) 000038 Steam Generator Tube Rupture 2.1.32 Ability to explain and apply system limits and 4.0 (SGTR)I3 precautions.

[Question 78] (CFR: 41.10 I 43.2 I 45.12) 000055 Loss Offsite and Onsite Power EA2 Ability to ne or interpret the following as 3.7 (Station Blackout)l6 they apply to a Station Blackout:

[Question 79]

EA2.01 Existing valve positioning on a loss of instrument air system (CFR 43.5 I 45.13)

WIE05 Loss EA2 Ability to determine and interpret the following 4.4

[Question 80] as they apply to the (Loss of Secondary Heat Sink)

EA2:1 Facility conditions and selection of appropriate procedures during abnormal and emer1~ency operations.

(CFR: 43.5 I 45.13)

..:12 of all 2.4.4l Ability to diagnose and recognize trends in an 4.2 Steam Generatorsl4 accurate and timely manner utilizing the appropriate

[Question 81] control room reference material.

(CFR: 41.10 I 43.5 I 45.12)

KIA Category Point Totals: Group Point Total: 6 NUREG-1021, Revision 9 Supplement 1 SRO Page 2 of 6 FENOC Facsimile Rev. 1

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal P~ant Evolutions -Tier 1/Group 2(SRO) l~=======================r=r9r9F=

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

1 2 3 1 000037 Steam Generator (S/G) Tube AA2 Ability to determine and interpret the following 3.4*

Leak/3 as thElY apply to the Steam Generator Tube Leak:

[Question 82]

AA2.09 System status, using independent readings from redundant Condensate air ejector exhaust monitor (CFR: 43.5/45.13) 000059 Liquid Radwaste 2.4.4'1 Knowledge of the emergency action level 4.6 Release/9 thresholds and classifications.

[Question 83] (CFR: 41.10 I 43.5/45.11) 000076 High Reactor Activity/9 AA2 Ability to determine and interpret the following 2.5

[Question 84] as thElY apply to the High Reactor Coolant Activity:

AA2.06 Response of PZR LCS to changes in the letdown flow rate (CFR: 43.5/45.13)

W/E1 0 Natural Circulation with Steam Void 2.4.50 Ability to verify system alarm setpoints and 4.0 in Vessel with/without RVLIS/4 operate controls identified in the alarm response

[Question 85] manual.

(CFR: 41.10 /43.5 /45.3) gory Point Totals: 0 0 0 Group Point Total: 4 NUREG-1021, Revision 9 Supplement 1 SRO Page 3 of 15 FENOC Facsimile Rev. 1

ES-401 PWR Examination 01LJtline Form ES-401-2 Plant Systems -Tier 2/Group 1 (SRO)

~=================r=r=F=F9=9=9F=K System # I Name K K KIA Topic(s) IR #

1 2 004 Chemical and Volume A2 Ability to (a) predict the impacts of the 3.0 Control System following malfunctions or operations on the

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

A2.26 Low VCT pressure (CFR: 41.5/43.5/45.3/45.5) 022 Containment Cooling A2 Ability to (a) predict the impacts of the 2.7 System (CCS) following malfunctions or operations on the

[Question 87) CCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.01 Fan motor over-current (CFR: 41.5/ 43.5 /45.3/ 45.13) 063 Electrical Distribution 2.2.37 Ability to determine operability and/or 4.6 System availability of safety related equipment.

[Question 88] (CFR: 41.7 /43.5/45.12) 064 Emergency Diesel A2 Ability to (a) predict the impacts of the 2.9 Generator (ED/G) System following malfunctions or operations on the

[Question 89) ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.02 Load, VARS, pressure on air compressor, speed droop, frequency, voltage, fuel oil level, temperatures (CFR: 41.5/43.5 /45.3 I 45.13) 078 Instrument Air System (lAS) 2.2.44 Ability to interpret control room 4.4

[Question 90] 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)

KIA Category Point Totals: Group Point Total:

NUREG-1021, Revision 9 Supplement 1 SRO Page 4 of ,6 FENOC Facsimile Rev. 1

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems -Tier 2/Group 2{SRO)

System # I Name K KIA Topic(s) 1 IR #

015 Nuclear Instrumentation A2 Ability to (a) predict the impacts of the 3.9 System (NIS) following malfunctions or operations on the NIS;

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

A2.01 Power supply loss or erratic operation (CFR: 41.51 43.5 I 45.3145.5) 071 Waste Disposal A2 Ability to (a) predict the impacts of the 3.6 System (WGDS) following malfunctions or operations on the

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

A2.02 Use of waste gas release monitors, radiation, gas flow rate, and totalizer (CFR: 41.5143.5145.3145.13) 079 Station Air System 2.2.25 Knowledge of the bases in Technical 4.2

[Question 93] Specifications for limiting conditions for operations and safety limits.

(CFR: 41.5141.7143.2)

KIA Category Point Totals: Group Point Total: 3 NUREG-1021, Revision 9 Supplement 1 SRO Page 5 of (j FENOC Facsimile Rev. 1

ES 401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 F'"-~cility: BVPS UNIT 1 SRO Date ofExam 7/7 thru 7118 2014 SROOnly Category KIA# Topic IR #

1. 2.1.39 Knowledge of conservative decision making practices. 4.3 Conduct of Operations (CFR: 41.10 /43.5/45.12)

[Question 94]

2.1.31 Ability to locate control room switches, controls, and indications, and to 4.3 determine that they correctly reflect the desired plant lineup.

(CFR: 41.10 /45.12)

[Question 95]

Subtotal 2

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 96]

Subtotal 1

3. 2.3.5 Ability to use radiation monitoring systems, such as fixed radiation Radiation monitors and alarms, portable survey instrumen1ts, personnel monitoring trol equipment, etc.

(CFR: 41.11 /41.12 /43.4/45.9)

[Question 97]

2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation 3.1 monitors and alarms, portable survey instrumen1ts, personnel monitoring equipment, etc.

(CFR: 41.12 I 43.4/45.9)

[Question 98]

Subtotal 2

4. 2.4.3 Ability to identify post-accident instrumentation.

Emergency (CFR: 41.6/45.4)

Procedures/

Plan [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-1021, Revision 9 Supplement 1 SRO Page 6 of 15 FENOC Facsimile Rev. 1

ES-401 Record 0 f Rejec . te d KIAs Form ES-401 4 -

Facility: BVPS Unit 1 Date of Exam 7/7 thru 7/18 2014 Operating Test No.: BV1LOT14 NRC

<:tr I Randomly Reason for Rejection

_.oup Selected KIA RO OUTLINE 1/2 000067 AA2.06 Question #24; At Beaver Valley the need for pressurizing the control room during a plant fire on site is an SRO decision based on the SRO's judgment of the control room environment. Therefore we are unable to construct a question that will have definitive criteria for the need to pressurize the control room. Randomly selected 000067 AA2.12 as a replacement.

2/1 012 K6.07 Question #39; Beaver Valley does not have a core protection calculator.

Randomly selected 012 K6.01 as a replacement.

2/1 039 2.2.25 Question #44; Knowledge of TS bases is an SRO knowledge lAW the NRC Clarification guidance for SRO-only questions Rev. 1(3/11/1 0). Randomly selected 039 2.2.39 as a replacement.

2/1 059 A2.07 Question #46; Beaver Valley does not have MFW pump turbines. Randomly selected 059 A2. 11 as a replacement.

2/1 103 A2.05 Question #55; Beaver Valley does not have any emergency containment entry procedures. Randomly selected 103 A2.03 as a replacement.

2/2 015 K3.04 Question #59; Beaver Valley does not have ICS. Randomly selected 015 K3.01 as a replacement.

2/2 041 K2.02 Question #62; Beaver Valley does not have ICS. Randomly selected 041 A2.03 as a replacement.

3 2.3.11 Question #71; Ability to control radiation releases has already been addressed in this exam with RO and SRO JPMs as well as Q# 92 of the written exam. In order to maintain exam balance, randomly selected 2.2.42 as a replacement.

1/2 000060 AA2.04 Question #22; Beaver Valley only has a single ARM that has automatic actions and this is already being addressed in Question #23. Randomly selected 000060 AA2.04 as a replacement.

1/1 000025 AK3.02 Question #6; Beaver Valley no longer isolates RHR low pressure piping on increasing pressure. Rather, this function is accomplished with the low pressure over pressurization protection system. The system employs the PORVs to relieve pressure without isolating the RHR low pressure piping. Therefore the KIA is not applicable to Beaver Valley. Discussed with the chief examiner and the decision was made tore-select a different KIA. Randomly selected 000025 AK3.03 as a replacement.

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

ES-401 Record 0 f ReJec. ted KIAs Form ES-401-4 ity: BVPS Unit 1 Date of Exam 7/7 thru 7/18 2014 Operating Test No.: BV1LOT14 NRC SRO OUTLINE 1/1 W/E12 2.4.1 Question #81; Knowledge of EOP entry conditions and immediate actions is RO knowledge lAW the NRC Clarification guidance for SRO-only questions Rev.

1(3/11/10). Randomly selected W/E12 2.4.47 as a replacement.

2/2 027 A2.01 Question #91; Beaver Valley has retired the containment iodine removal system and replaced it with a passive s1odium tetraborate system. Randomly selected 015 A2.01 as a replacement.

3 2.1.44 Question #95; Knowledge of RO duties in the control room is RO knowledge lAW the NRC Clarification guidance for SRO-only questions Rev. 1(3/11/1 0).

Randomly selected 2.1.31 as a replacement.

3 2.4.8 Question #99; Overlap with question 76 identical KIA creates overlap and potential double-jeopardy issues. Randomly selected 2.4.3 as a replacement.

2/1 064 A2.09 Question # 89; Unable to develop a discriminatory question for the second part of the KIA which requires procedure use to address a malfunction regarding an EDG that fails to synchronize. Other than to call maintenance to effect repairs, there is no operational procedural guidance for this condition. Discussed with the chief examiner and the decision was made to re-select a different KIA Randomly selected 064 A2.02 as a replacement.

NUREG-1021, Revision 9 Supplement 1 Page 2 of2 FENOC Facsimile Rev. 1

ES-301 Administrative Topics Outline Form ES-301-1 I Facility BVPS Unit 1 Date of Examination: 717 thru 7118 2014

~amination Level RO I:R1 SROD Operating Test Number BV1LOT14 NRC Administrative Type Des<:ribe activity to be performed Topic Code*

(See Note)

Conduct of M,R 2.1.23 (4.3)

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

(RO A.1.1) (1AD-007) Perform an ECP Calculation Conduct of M,R 2.1.43 (4.1)

Operations Ability to use procedw*es to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.

(RO A.1.2)

(1AD-016) Plot and Evaluate 1/M Data

..:juipment Control N,R 2.2.13 (4.1)

Knowledge of tagging and clearance procedures.

(RO A.2) (1AD-047) Prepare a CIE~arance Tagout for FW-P-38 Radiation Control D,R 2.3.11 (3.8)

Ability to control radiation releases.

(RO A.3) (1AD-004) Perform Decay Tank Discharge Pre-Release Verification Emergency Procedures/Plan NOT EVALUATED (RO A.4)

II .. ,()T!::: 11.:: * '~ *" or SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

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

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

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

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

ES-301 Administrative Topics Outline Form ES-301-1 Facility: BVPS Unit 1 Date of Examination: 7/7 thru 7/18 2014

<amination Level RO D SRO lXI Operating Test Number BV1LOT14 NRC Administrative Type Describe activity to be performed Topic Code*

(See Note)

Conduct of M, R 2.1.23 (4.4)

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

(SRO A.1.1) (1AD-011) Review an ECP Calculation Conduct of N, R 2.1.3 (3.9)

Operations Knowledge of shift or short-term relief turnover practices.

(1AD-048) Determine Availability for Call-in (3 ROs)

(SRO A.1.2)

Equipment Control N,R 2.2.17 (3.8)

Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, and

,.:>RO A.2) coordination with the transmission system operator.

(1AD-041) Perform a Risk Assessment [1 FW-P-3A] Maintenance Radiation Control N,R 2.3.11 (4.3)

Ability to control radiation releases.

(SRO A.3) (1AD-042) Determine Compensatory Actions for RM-P-1GW-108 and 02A-1GW-11 0-1 Being OOS Emergency N,S 2.4.41 (4.6)

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

(1AD-046) Classify an Emergency Event (Scenario Specific)

(SRO A.4)

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

  • Type Codes & Criteria (C)ontrol Room, (S)imulator, or Class(R)oom (O)irect from bank (5. 3 for ROs; ~ 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (;: 1)

(P)revious 2 exams (5. 1; randomly selected)

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

ES 301 Con t ro I Room /1 n-PI an t Siystems o u trme - -

Form ES 301 2 Facility: BVPS Unit 1 Date of Examination: 7171 thru 7/18 2014 I Exam Level: RO 1:&1 SRO(I) D SRO(U) D Operating Test No.: BV1LOT14 NRC Control Room Systems© (8 for RO); (7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Function S1 -Shift From Main F/W Reg. Valves to Bypasses (1 CR-072) S,D 4S S2- Discharge Laundry and Contaminated Shower Drain Tank- (High S,N,A 9 radiation alarm received - No Auto Actions occur) (1 CR-658)

S3- Rod Control Assembly Partial Movement Test- (Rod fails to move S,D,A 1 during performance of the test) (1 CR-596)

S4 - Drain SIS Accumulator - (Low pressure alarm receiv~3d during S,N,A,EN 3 draining) (1 CR-659)

S5- Place Excess Letdown in Service (1 CR-056) S,D 2 S6- Respond to High PRT Temperature- (High PRT Ieveli received during S,N,A 5 spray down of PRT) (1 CR-661)

S7 - X-Fer 4KV Emer Bus from EDG to Normal Feed - (EDG overcurrent S,N,A 6 occurs and EDG auto actions fails to occur) (1 CR-6,60)

SS - Respond to a Loss of the RHR System (RHR pump trips requiring S, D, A, L, E 4P RCP start) (1CR-594)

In-Plant Systems© (3 for RO); (3 for SR0-1); (3 or 2 for SRO-U)

P1 - Startup a Rod Drive MG (1 PL-003) D,L 1 P2- Reset the Terry Turbine Trip Throttle Valve (1 PL-004) D,R 4S P3- Place the Diesel Air Compressor in Service (1PL-031) D,E 8

@ All RO and SRO control room (and in-plant) systems m1Jst be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO I SR0-1 I SRO-U (A)Iternate Path 4-6 14-6 12-3 (C)ontrol room (D)irect from bank S91S81S4 (E)mergency or abnormal in-plant ~11~11~1 (EN)gineered safety feature -I- I~ 1 (Control room system)

(L)ow-power I Shutdown ~11~11~1 (N)ew or (M)odified from bank including 1(A) ~21~21~1 (P)revious 2 exams s 31 s 3 Is 2 (randomly selected)

(R)CA ~11~11~1 II (S)imulator NUREG-1 021, Revision 9 Supplement 1 FENOC Facsimile Rev.1

ES 301 C on t ro I Room /1 n-PI an t Siys tems o u trme - -

Form ES 301 2 Facility: BVPS Unit 1 Date of Examination: 7/7/thru 7/18 2014 Exam Level: RO D SRO(I) I2II SRO(U) D Operating Test No.: BV1LOT14 NRC I Control Room Systems@ (8 for RO); (7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Function 51 - Shift From Main FIW Reg. Valves to Bypasses (1 CR-072) S,D 4S 52- Discharge Laundry and Contaminated Shower Drain Tank- (High S,N,A 9 radiation alarm received - No Auto Actions occur) (1 CR-658) 53- Rod Control Assembly Partial Movement Test- (Rod fails to move S,D,A 1 during performance of the test) (1 CR-596) 54 - Drain SIS Accumulator- (Low pressure alarm received during S, N,A,EN 3 draining) (1 CR-659) 56- Respond to High PRT Temperature- (High PRT leve~l received during S,N,A 5 spray down of PRT) (1CR-661) 57 - X-Fer 4KV Emer Bus from EDG to Normal Feed - (EDG overcurrent S,N,A 6 occurs and EDG auto actions fails to occur) (1 CR-660) 58- Respond to a Loss of the RHR System (RHR pump trips requiring S,D,A,L,E 4P RCP start) (1CR-594)

In-Plant Systems@ (3 for RO); (3 for SR0-1); (3 or 2 for SRO-U)

P1 -Startup a Rod Drive MG (1 PL-003) D, L 1 P2- Reset the Terry Turbine Trip Throttle Valve (1 PL-004) D,R 4S P3- Place the Diesel Air Compressor in Service (1PL-03>1) D,E 8

@ All RO and SRO control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO I SR0-1 I SRO-U (A)Iternate Path 4-6 14-6 /2-3 (C)ontrol room (D)irect from bank :s;9/S8/:s;4 (E)mergency or abnormal in-plant ~1/~1/~1 (EN)gineered safety feature 1 ~ 1 (Control room system)

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

(R)CA ~1/~1/~1 11 (S)imulator NUREG-1 021, Revision 9 Supplement 1 FENOC Facsimile Rev.1

A~ppen d"1x D Scenario Outline 1L14N1 Facility: BVPS Unit 1 Scenario No. 1 Op Test No.: BV1LOT14 NRC Examiners: Candidates: SRO ATC BOP Initial IC 68(29): 100% power, EOL, Equ. XE Conditions, CB "D" @ 227 steps, RCS boron - 100 Conditions: ppm.

Turnover: Maintain 100% power.

"A" Train Priority, 1FW-P-3B is OOS with 1FW-P-2 aligned to the "B" header lAW TS 3.7.5, Condition B.

Critical Tasks: 1. CT-50 (FR-S.l.A) Crew isolates the main turbine

2. CT-3 (E-O.E) Crew manually actuates CIB
3. CT-11 (E-0.0) Crew closes cnmt isolation valves
4. CT -33 (ECA-2.1.A) Crew controls the AFW flow rate Event Event Type Event Description No.

1 (TS) SRO RCS loop 1, ch III, flow transmitter, FT-1RC-416 fails low.

2 (C) ATC, SRO River water pump, 1WR-P-1A trips, requiring manual start of (TS) SRO 1WR-P-1B.

3 "B" RCP thermal barrier leak/ TV-1 CC-1 07B fails to auto (C)ATC, SRO close on high flow, requires manual closure.

4 (R) ATC "B" S/G feedwater leak inside CNMT requiring an unplanned (N) BOP, SRO power reduction per AOP 5 "B" feedwat1;!r leak increases once power is reduced to 94%.

(M)ALL Reactor fails to trip from the control room, requires entry into FR-S.l.

6 (M)ALL Upon Rx trip, all 3 steam lines fault.

7 Automatic main steam line isolation failure, requires manual (I) BOP, SRO main steam line isolation.

8 Train "B" CIA fails to actuate along with train "A" valve (I) ATC, SRO MOV-1CH-378 failing to automatically close, ATC must manually actuate CIA or close MOV-1CH-378.

9 (I)ATC, SRO Automatic CIB actuation failure, requires manual actuation.

10 Control room dampers, 1VS-D-40-1A, 1B, 1C and 1D fail to (C) BOP, SRO automatically close, requires manual closing.

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

Appendix D Scenario Outline 1L14N1

  • fter taking the shift at 100% power, RCS loop flow transmitter, FT-1RC-416 fails low. The crew will

.agnose the indications and the SRO will address Tech Specs for the failed transmitter.

The 1A Reactor Plant River Water Pump, 1WR-P-1A then trips with an auto start failure of the standby pump, 1WR-P-1B. The SRO will direct the crew to perform the actions of AOP 1.30.2, River Water/ Main Intake Structure Loss, to start 1WR-P-1B and restore river water. The SRO will address Tech Specs.

A leak will then occur in the "B" RCP thermal barrier heat exchanger. The isolation valve, TV -1 CC-1 07B, will fail to auto close on high flow and will require manual closure. The BOP will refer to the alarm response procedure and the SRO will direct closure of the valve.

A feed water leak will occur inside of the containment, the SRO will direct the crew to commence a rapid power reduction IA W AOP 1.51.1, "Unplanned Power Reduction".

The feedwater leak will increase in size during the power reduction, due to degrading conditions, the SRO will direct the A TC to trip the reactor.

The reactor will fail to trip from the control room. The SRO will direct the ATC and BOP to perform the lOA's ofFR-S.1, "Response to Nuclear Power Generation- ATWS. The turbine will also fail to automatically trip and must be manually tripped. The reactor will be tripped via a local operator after being dispatched and the crew will return to E-0.

When the reactor is tripped, all three main steam lines will fault inside of containment.

'T'l:le main steam line isolation signal will fail to occur and the valves must be manually aligned.

The safety injection that occurred as a result of the MSLB will fail to actuate the train "B" CIA signal, and train "A" CIA valve, MOV-1CH-378 will fail to automatically close. The ATC will recognize the failure and isolate the containment penetration via either manually actuating Train "B" CIA or manually closing MOV-1CH-378.

A CIB signal will fail to actuate on high containment pressure requiring the ATC to manually initiate CIB actuation. The control room ventilation dampers 1VS-D-40-ll A through 1D will not close on the CIB signal requiring the BOP to manually close the dampers.

The SRO will transition to EOP E-2, "Faulted Steam Generator Isolation" based upon the rapid depressurization of the Steam Generators, then transition to ECA-2.1, "Uncontrolled Depressurization of All Steam Generators".

The scenario will be terminated after the crew evaluates if th~~ LHSI pumps are to be secured in ECA-2.1.

Expected procedure flow path is E-0 ._ FR-S.1 ._ E-0 ._ E-2 ._ ECA-2.1 NUREG-1021, Revision 9 Supplement 1 FENOC Facsimile Rev. 1

A~ppen d"IX D s cenar1o

  • outmer 1L14N2 Facility: BVPS Unit 1 Scenario No.: 2 Op Test No.: BV1LOT14 NRC Examiners: Candidates: SRO ATC BOP Initial IC 67(17): 65% power, MOL, Equ. XE Conditions, CB "D" @ 177 steps, RCS boron -

Conditions: 1102 ppm.

Turnover: Maintain current power level.

1FW-P-3B OOS for maintenance, with lFW-P-2 aligned to "B" header lAW TS 3.7.5, Condition B.

Control rods are in manual due to I&C MSP in progress.

Critical Tasks: 1. CT-4 (E-O.F) Establish AFW flow

2. CT -18 (E-3.A) Isolate ruptured SG
3. CT -20 (E-3.C) Crew depressurizes RCS
4. CT-21 (E-3.D) Crew terminates SI Event Malf. No. Event Type Event Description No.

1 (C) ATC, SRO lA charging pump trip, requires manual starting of lB.

(TS) SRO 2 (C) ATC, SRO 200 gpd "B" steam generator tube leak (TS) SRO 3 (R) ATC Main feed pump, lFW-P-lB trips, requires rapid power (N) BOP, SRO reduction (AOP 1.24.1) 4 "B" Main feed regulating valve, FCV-lFW-488 fails shut, (M)ALL leads to a Rx trip with a loss of offsite power.

5 Turbine driven aux feed pump, lFW-P-2 trips on overspeed (C) BOP, SRO and motor driven aux feed pump, 1FW-P-3A fails to auto start, requiring manual start of 1FW-P-3A.

6 (M)ALL 500 gpm SGTR in the "B" steam generator.

7 Main steam line isolation valve on the ruptured SG, TV-lMS-(C) BOP, SRO 101 B failed open, requires the crew to perform an alternate MSLI alignment.

8 PRZR PORV fails open during depressurization requires (C) ATC, SRO closing ofblock valve.

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

Appendix D Scenario Outline 1L14N2

  • fter taking the shift at 65% power, the running charging pum.p will trip. The SRO will enter AOP 1.7.1 to

,drt the standby pump. The standby pump must be started and the backup pump will be aligned to replace the failed pump. Charging and letdown will be isolated per the AOP. The SRO will address Technical Specifications for the failed charging pump.

Subsequently, a 200 gpd SG tube leak will develop on the "B'" SG. AOP 1.6.4 will be implemented. AOP 1.6.4 will provide direction to enter Mode 3 within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. The SRO will address Technical Specifications which also will require Mode 3 entry.

1FW-P-1B will trip, requiring the crew to rapidly reduce power to< 52% lAW AOP 1.24.1.

The "B" SG main feedwater regulating valve fails closed, resulting in a reactor trip.

Following the reactor trip, offsite power is lost.

Additionally, the 3A motor driven aux feed pump fails to automatically start but may be started manually, The turbine driven aux feed pump will start but trips during startup and can be recovered if requested.

As a result of the reactor trip, a 500 gpm steam generator tube rupture will occur in the "B" SG.

When isolating the "B" SG, the "B" main steam line isolation valve will fail open requiring the crew to close the "A" and "C" MSIV's .

.tbsequently, the PRZR PORV used to depressurize the RCS will fail open and require the motor operated block valve be closed to stop the PORV leakage.

The scenario will be terminated when the crew has terminated safety injection.

Expected procedure flow path is EO ~ E3.

NUREG-1 021, Revision 9 Supplement 1 FENOC Facsimile Rev. 1

A~_pen d'1x D s cenano

  • o utme r 1L14N3 Facility: BVPS Unit 1 Scenario No.: 3 Op Test No.: BV1LOT14 NRC Examiners: Candidates: SRO ATC BOP Initial IC 211: 5% power, BOL, Equ. XE Conditions, CB "D"@ 114 steps, RCS boron- 1851 Conditions: ppm.

Turnover: Raise Power to 10-14% to place turbine online.

Critical Tasks: 1. CT-12 (E-O.P), Manually actuate SLI

2. CT -17 (E-2.A), Isolate faulted SG
3. CT -48 (FR-P.l.A), Terminate ECCS flow I challenge to the integrity CSF Event Malf. No. Event Type Event Description No.

(R) ATC 1 Raise Power to 10-14%

(N) SRO (C) BOP, SRO Leak collection exhaust fan, 1VS-F-4A trips, requiring manual 2

(TS) SRO start of 1VS ..f-4B Charging flow control valve, FCV-1CH-122 fails shut in 3 (C)ATC, SRO AUTO, requires manual control ofPRZR level.

Main steam header pressure transmitter, PT-1MS-464 fails 4 (I) BOP, SRO low, requiring manual control of condenser steam dumps.

SG atmospheric reliefvalve, PCV-1MS-101B fails open, (C) BOP, SRO 5 requires manual control of condenser steam dumps during (TS) SRO failure and local operator isolation.

6 (M) ALL Steam Break inside cnmt on "B" SG 7 (I) BOP, SRO SLI auto actuation failure, requires manual MSLI.

Aux feedwater control valve failed open, requires alternate 8 (C) BOP, SRO isolation method.

Control room emergency ventilation system fails to actuate on 9 (I) BOP, SRO CIB signal, requiring manual initiation.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1 021, Revision 9 Supplement 1 FENOC Facsimile Rev 1

Appendix D Scenario Outline 1L14N3

~1.e crew will assume the shift at 5% power with instructions to raise power to 10-14% to place the turbine

.1line lAW the reactivity plan and 1OM-52.4.A. The ATC will initiate a dilution and withdraw control rods.

After the power has raised to 6.4%, 1VS-F-4A will trip, the crew will respond using the ARP which will direct the BOP to manually start 1VS-F-4B. The SRO will address applicable TS.

After the power has raised to 8.0%, FCV-1 CH-122 will fail closed in Auto, the ATC will be required to identify the failure and manually control FCV-1CH-122 to maintain Pzr level.

2 minutes after the crew blocks the Power Range Low Overpower Reactor trip, the main steam header pressure transmitter, MS-1PT-464 will fail low causing the condenser steam dumps to close in response. The ensuing RCS heatup will cause SG atmospheric steam relief valve, PCV-1MS-101B to fail open, causing Rx power to rise and Tavg to drop due to the increased steam flow. The BOP will restore Rx power and Tavg by manually controlling the condenser steam dumps. The crew will unsuc,cessfully attempt to close the valve from the control room and then dispatch an operator to locally isolate. The BOP will control the condenser steam dumps while a local operator isolates the failed open SG atmospheric: valve.

A large steam break will then occur on the "B" SG inside of CNMT.

The crew will enter E-0 and transition to E-2 after diagnosing a faulted SG. The steam break is of a magnitude that will cause conditions for an Integrity Red Path and require the crew to transition to FR-P.l.

"' additional malfunctions occur during the event;

1. Automatic SLI fails to automatically actuate
2. "A" header AFW control valve will fail to close from the control room.
3. The control room emergency ventilation system, CREV's, fails to automatically actuate.

The scenario will be terminated when the crew has established normal charging flow in FR-P .1.

Expected procedure flow path is E E FR-P.l.

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

A.ppen d"IX D s cenano Outline 1L14N4 Facility: BVPS Unit 1 Scenario No.: 4 Op Test No.: BV1LOT14 NRC Examiners: Candidates: SRO ATC BOP Initial IC 62(18): 81% power, MOL, Equilibrium Xe, CB "D"@ 206 steps, RCS boron- 1012 Conditions: ppm.

Turnover: Rx is at 81% power due to isolating the condenser "D" Waterbox for cleaning.

"A" Train Priority, 1FW-P-3B is OOS with 1FW-P-2 aligned to the "B" header lAW TS 3.7.5, Condition B.

Critical Tasks: 1. CT-1 (E-O.A) - Manually Trip Rc~actor

2. CT-6 (E-0.1) - Establish 1 train of HHSI
3. CT-16 (E-l.C)- Manually trip RCPs Event Malf. No. Event Type Event Description No.

1 (C)ATC, SRO The 1A bori1;; acid transfer pump trips requiring aligning the (TS) SRO standby train for service.

2 (TS) SRO Ch 2, cnmt pressure transmitter, PT-1LM-100B, fails high.

3 (R) ATC Cooling tower pump, CT -P-1 C trips, causing degraded (N) BOP, SRO condenser vacuum, requiring power reduction.

4 Auto rod insertion fails on load reduction, A TC manually (I) ATC, SRO controls Tavg.

5 Condenser Low-Low vacuum causes turbine trip.

(M)ALL 6 Auto Rx trip fails to occur, requires ATC to manually trip the (I)ATC, SRO reactor from BB-A.

7 Exciter circuit breaker fails to auto open on Rx trip, requires (C) BOP, SRO BOP to manually trip the exciter circuit breaker.

8 (M)ALL 1500 GPM LOCA one minute after Rx trip.

9 "A" charging pump, 1CH-P-1A trips, and "B" charging pump, (C) ATC, SRO 1CH-P-1B f::tils to auto start on Safety Injection, requiring manual start.

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

Appendix D Scenario Outline 1L14N4

~er taking the shift, boric acid transfer pump, 1CH-P-2A will trip. SRO will direct placing the 2B boric acid

.~dllsfer pump in service IA W 1OM-7 .4.R, "Transfer of Inservice Boric Acid Tank". SRO will also address Technical Specifications.

After the crew has reestablished a boric acid flowpath, containment pressure ch 2 transmitter, PT-1LM-100B fails high. The SRO will enter 10M-1.4.IF and review the Technical Specifications. The SRO will then contact I&C to trip the applicable bistables.

The "C" cooling tower pump will trip causing condenser vacuum to degrade. The crew will enter AOP 1.26.2, "Loss of Condenser Vacuum". While working through the Loss of Condenser Vacuum AOP, they will recognize the need to reduce turbine load to prevent exceeding hotwell temperature of 130 °F. At this point the SRO will enter AOP - 1.51.1, "Unplanned Power Reduction" and reduce turbine load.

The control rods will fail to auto insert during the turbine load reduction. The ATC will have to insert control rods in manual to maintain Tavg to Tref.

During the load reduction the turbine will trip due to low condenser vacuum, the plant will be greater than 49%

power (P-9), but the Rx will fail to auto trip. The ATC will successfully trip the reactor from Bench board "A".

During the immediate operator actions ofE-0, the BOP will be required to manually open the exciter circuit breaker due to an auto open failure.

"ne minute after the Rx is manually tripped a 1500 GPM LOCA will occur on the "B" RCS loop. The LOCA

.11 cause a Safety Injection actuation due to low RCS pressure. Upon the SI actuation the "A" charging pump will trip, and the "B" charging pump will fail to auto start, requiring the ATC to manually start the "B" charging pump to restore high head safety injection flow.

The crew will enter E-0, transition to E-1 due to containment parameters, and then to ES-1.2 to cooldown the RCS.

The scenario will be terminated when RCS cooldown is commenced in ES-1.2.

Expected procedure flow path is E E ES-1.2.

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

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