ML17003A280

Final Outlines (Folder 3)

ML17003A280
Person / Time
Site:	Beaver Valley
Issue date:	10/24/2016
From:	FirstEnergy Nuclear Operating Co
To:	NRC Region 1
Shared Package
ML16076A416	List: IR 05000334/2016302 ML16089A007 ML16292A483 ML16342C521 ML17003A276 ML17003A277 ML17003A278 ML17003A280 ML17003A281 ML17003A282 ML17003A283 ML17003A284 ML17003A285
References
U01922
Download: ML17003A280 (28)

Text

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

BVPS UNIT 1 RO Date of Exam 10/31 thru 11/18/2016 Tier Group RO KIA Category Points K K K K K K A A A A G TOTAL 1 2 3 4 5 6 1 2 3 4

• 1 3 3 3 3 18 1. Emergency 2 1 2 1 1 & 9 Abnormal Plant Tier 4 5 4 4 27 Evolutions Totals 1 3 2 3 3 2 2 2 3 2 3 3 28 2. Plant 2 Systems 1 0 1 1 1 1 1 1 1 1 1 10 Tier 4 2 4 4 3 3 3 4 3 4 4 38 Totals 1 2 3 4 10 3. Generic Knowledge and Abilities Category 2 3 3 2 Note: 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two). (One Tier 3 Radiation Control KIA is allowed if the KIA is replaced by a KIA from another Tier 3 Category).

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 with justification; 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 (I Rs) 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 a category 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, I Rs, and point totals (#) on Form ES-401-3.

Limit SRO selections to KIAs that are linked to 10 CFR 55.43. G* Generic KIAs NUREG-1021, Revision 10 RO Page 1of13 FENOC Facsimile Rev. AG ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions -Tier 1/Group 1(RO) ll'========================r==r==r==r=9

"::/APE #I Name I Safety Function 000007 Reactor Trip / 1 [Question

1) 000008 Pressurizer Vapor Space Accident I 3 [Question

2) 000009 Small Break LOCA I 3 [Question

3) 000011 Large Break LOCA I 3 [Question

4) 15/000017 RCP Malfunctions/

4 [Question

5) 000022 Loss of Rx Coolant Makeup I 2 [Question

6) 000025 Loss of RHR System / 4 [Question

7) 000027 Pressurizer Pressure Control System Malfunction I 3 [Question

8) NUREG-1021, Revision 10 K K 1 2 KIA Topic(s) EA 1 Ability to operate and monitor the following as they apply to a reactor trip: EA 1.07 MT/G trip; verification that the MT/G has been tripped (CFR 41. 7 / 45.5 I 45.6) 2.1.20 Ability to interpret and execute procedure steps. (CFR: 41.10 / 43.5 / 45.12) IR 4.3 4.6 EA2 Ability to determine or interpret the following as 3.8 they apply to a small break LOCA: EA2.11 -Containment temperature, pressure, and humidity (CFR 43.5 / 45.13) EA2 Ability to determine or interpret the following as 3.2? they apply to a Large Break LOCA: EA2.07 -That equipment necessary for functioning of critical pump water seals is operable (CFR 43.5 / 45.13) AK3. Knowledge of the reasons for the following responses as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow) : AK3.03 -Sequence of events for manually tripping reactor and RCP as a result of an RCP malfunction (CFR 41.5,41.10

/ 45.6 / 45.13) AK1. Knowledge of the operational implications of the following concepts as they apply to Loss of Reactor Coolant Makeup: AK1 .02 -Relationship of charging flow to pressure differential between charging and RCS (CFR 41.8 I 41.10 / 45.3) AK2. Knowledge of the interrelations between the Loss of Residual Heat Removal System and the following:

AK2.03 -Service water or closed cooling water pumps (CFR 41.7 / 45.7) 11 AK2. Knowledge of the interrelations between the Pressurizer Pressure Control Malfunctions and the following:

AK2.03 -Controllers and positioners (CFR 41.7 / 45.7) 3.7 2.7 2.7 2.6 RO Page 2 of 13 FENOC Facsimile Rev. AG #

ES-401 E/APE #I Name I Safety Function 000029 A TWS I 1 [Question

9) 000038 Steam Gen. Tube Rupture/ 3 [Question 1 OJ 000056 Loss of Off-site Power I 6 [Question 11] 000058 Loss of DC Power I 6 [Question

12) 000062 Loss of Nuclear Svc Water 14 Question 13) 000065 Loss of Instrument Air I 8 [Question

14) W/E04 LOCA Outside Containment I 3 [Question

15) NUREG-1021, Revision 10 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions -Tier 1/Group 1(RO) Continued K K K 1 2 3 RO Page 3of13 KIA Topic(s) IR EA2 Ability to determine or interpret the following as 3.4* they apply to a ATWS: EA2.05 -System component valve position indications (CFR 43.5 / 45.13) 2.4.34 -Knowledge of RO tasks performed outside 4.2 the main control room during an emergency and the resultant operational effects. (CFR: 41.10 / 43.5 / 45.13) AK3. Knowledge of the reasons for the following 4.4 responses as they apply to the Loss of Offsite Power: AK3.02 -Actions contained in EOP for loss of offsite power CFR 41.5,41.10

/ 45.6 / 45.13 AK1. Knowledge of the operational implications of 2.8 the following concepts as they apply to Loss of DC Power: AK1 .01 -Battery charger equipment and instrumentation (CFR 41.8 / 41.10 / 45.3) AA 1. Ability to operate and I or monitor the 2.9 following as they apply to the Loss of Nuclear Service Water (SWS): AA 1.07 -Flow rates to the components and systems that are serviced by the SWS; interactions among the components (CFR 41. 7 I 45.5 I 45.6) AA 1. Ability to operate and I or monitor the 2.9 following as they apply to the Loss of Instrument Air: AA 1. 03 -Restoration of systems served by instrument air when pressure is regained (CFR 41. 7 I 45.5 I 45.6) EK3. Knowledge of the reasons for the following 3.4 responses as they apply to the (LOCA Outside Containment)

EK3.2 -Normal, abnormal and emergency operating procedures associated with (LOCA Outside Containment). (CFR: 41.5 / 41.10, 45.6, 45.13) FENOC Facsimile Rev. AG #

ES-401 E/APE #I Name I Safety Function W/E05 Inadequate Heat Transfer -Loss of Secondary Heat Sink I 4 [Question 16] W/E11 Loss of Emergency Coolant Recirc. I 4 [Question 17] W/E12 -Uncontrolled Depressurization of all Steam Generators I 4 [Question 18] _;ategory Point Totals: NUREG-1021, Revision 10 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions -Tier 1/Group 1(RO) Continued 3 3 3 3 3 3 RO Page 4of13 KIA Topic(s) EK1. Knowledge of the operational implications of the following concepts as they apply to the (Loss of Secondary Heat Sink) EK1 .3 -Annunciators and conditions indicating signals, and remedial actions associated with the Loss of Secondary Heat Sink CFR: 41.8 / 41.10, 45.3 EK2. Knowledge of the interrelations between the (Loss of Emergency Coolant Recirculation) and the following:

EK2.2 -Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility (CFR: 41.7 / 45.7) 2.4.2 -Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions. (CFR: 41.7 / 45.7 / 45.8) Group Point Total: IR 3.9 3.9 4.5 FENOC Facsimile Rev. AG # 18 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions

-Tier 1/Group 2(RO) E/APE #I Name I Safety Function K K 1 2 000036 Fuel Handling Accident I 8 [Question 19] 000061 ARM System Alarms 17 [Question 20] 000068 Control Room Evac. I 8 [Question 21] 000076 High Reactor Coolant Activity I 9 [Question 22] W/E02 SI Termination I 3 [Question 23] W/E07 Saturated Core Cooling I 4 [Question 24] W/E13 Steam Generator Over-pressure I 4 [Question 25] KIA Topic(s) AA 1. Ability to operate and I or monitor the following as they apply to the Fuel Handling Incidents:

AA 1.03 -Reactor building containment evacuation alarm enable switch (CFR 41.7 / 45.5 / 45.6) AA2. Ability to determine and interpret the following as they apply to the Area Radiation Monitoring (ARM) System Alarms: AA2.02 -Normal radiation intensity for each ARM system channel (CFR: 43.5 / 45.13) AA 1. Ability to operate and I or monitor the following as they apply to the Control Room Evacuation:

AA 1.22 -Flow control valve for RCS charging header (CFR 41.7 / 45.5 / 45.6) AK3. Knowledge of the reasons for the following responses as they apply to the High Reactor Coolant Activity:

AK3.06 -Actions contained in EOP for high reactor coolant activity (CFR 41.5,41.10 I 45.6 / 45.13) 2.4.20 -Knowledge of operational implications of EOP warnings, cautions, and notes. (CFR: 41.10 I 43.5 / 45.13) EK2. Knowledge of the interrelations between the (Saturated Core Cooling) and the following:

EK2.2 -Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility (CFR: 41.7 / 45.7) EK2. Knowledge of the interrelations between the (Steam Generator Overpressure) and the following:

EK2.1 -Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features CFR: 41.7 / 45.7 IR 3.5 2.9 4.0 3.2 3.8 3.5 3.0 NUREG-1021, Revision 10 RO Page 5 of 13 FENOC Facsimile Rev. AG #

ES-401 :=JAPE #I Name I Safety Function W/E14 Loss of CTMT Integrity I 5 [Question 26] W/E16 High Containment Radiation I 9 [Question 27] KIA Category Point Totals: NUREG-1021, Revision 10 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions -Tier 1/Group 2(RO) Continued KIA Topic(s) EK1. Knowledge of the operational implications of the following concepts as they apply to the (High 1 Containment Pressure)

EK1 .1 -Components, capacity, and function of emergency systems (CFR: 41.8 I 41.10, 45.3) EA2. Ability to determine and interpret the following as they apply to the (High Containment Radiation)

EA2.2 -Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments (CFR: 43.5 I 45.13) Group Point Total: IR 3.3 3.0 RO Page 6of13 FENOC Facsimile Rev. AG # 9 ES-401 System # I Name 003 Reactor Coolant Pump [Question 28] 003 Reactor Coolant Pump [Question 29] 004 Chemical and Volume Control [Question 30] 005 Residual Heat Removal [Question 31] 006 Emergency Core Cooling [Question 32] 007 Pressurizer Relief/Quench Tank [Question 33] 007 Pressurizer Relief/Quench Tank [Question 34] 008 Component Cooling Water [Question 35] NUREG-1021, Revision 10 PWR Examination Outline Form ES-401-2 Plant Systems K K K K K K 1 2 3 4 5 6 I -Tier 2/Group 1 (RO) KIA Topic(s) K2. Knowledge of bus power supplies to the following:

K2.02 -CCW pumps (CFR: 41.7) A4 Ability to manually operate and/or monitor in the control room: A4.05 -RCP seal leakage detection instrumentation (CFR: 41.7 I 45.5 to 45.8) K3 Knowledge of the effect that a loss or malfunction of the eves will have on the following:

K3.08 -RCP seal injection (CFR: 41.7/45/6)

K6 Knowledge of the effect of a loss or malfunction on the following will have on the RHRS: K6.03 -RHR heat exchanger (CFR: 41.7 I 45.7) K4 Knowledge of ECCS design feature(s) and/or interlock(s) which provide for the following:

K4.14 -Cross-connection of HPl/LPl/SIS (CFR: 41.7) K1 Knowledge of the physical connections and/or cause effect relationships between the PRTS and the following systems: K1 .01 -Containment system CFR: 41.2 to 41.9 I 45.7 to 45.8 A3 Ability to monitor automatic operation of the PRTS, including:

A3.01 -Components which discharge to the PRT (CFR: 41. 7 I 45.5) 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:

A2.03 -High/low CCW temperature (CFR: 41.5 I 43.5 I 45.3 I 45.13) IR 2.5* 3.1 3.6 2.5 3.9 2.9 2.7* 3.0 RO Page 7of13 FENOC Facsimile Rev. AG #

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems -Tier 2/Group 1 (RO) Continued System # I Name K K K KIA Topic(s) IR # 1 2 3 010 Pressurizer Pressure KS Knowledge of the operational implications 3.5 Control of the following concepts as the apply to the PZR PCS: [Question 36] K5.01 -Determination of condition of fluid in PZR, using steam tables CFR: 41.5 / 45.7 010 Pressurizer Pressure 2.4.31 -Knowledge of annunciator alarms, 4.2 Control indications, or response procedures.

[Question 37] (CFR: 41.10 I 45.3) 012 Reactor Protection K1 Knowledge of the physical connections 3.4 [Question 38] and/or cause effect relationships between the RPS and the following systems: K1 .02 -125V de system (CFR: 41.2 to 41.9 / 45.7 to 45.8) 013 Engineered Safety Features A3 Ability to monitor automatic operation of the 3.7* Actuation ESFAS including:

[Question 39] A3.01 -Input channels and logic (CFR: 41.7 / 45.5) 022 Containment Cooling A2 Ability to (a) predict the impacts of the 2.5 'Stion 40] following malfunctions or operations on the 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 I 45.3 / 45.13) 026 Containment Spray K4 Knowledge of CSS design feature(s) and/or 3.7* interlock(s) which provide for the following:

[Question 41] K4.09 -Prevention of path for escape of radioactivity from containment to the outside (interlock on RWST isolation after swapover)

CFR:41.7 039 Main and Reheat Steam 2.2.38 -Knowledge of conditions and limitations in the facility license. 3.6 [Question 42] (CFR:41.7/41.10/43.1

/45.13) 039 Main and Reheat Steam K3 Knowledge of the effect that a loss or 2.8* [Question 43] malfunction of the MRSS will have on the following:

K3.06-SDS (CFR: 41. 7 I 45.6) 059 Main Feedwater A 1 Ability to predict and/or monitor changes in 2.7* [Question 44] parameters (to prevent exceeding design limits) associated with operating the MFW controls including:

A 1.03 -Power level restrictions for operation of MFW pumps and valves. (CFR: 41.5 / 45.5) NUREG-1021, Revision 10 RO Page 8of13 FENOC Facsimile Rev. AG ES-401 PWR Examination Outline Form ES-401-2 Plant Systems ll==========================r==;===;===;====;===;==;==

System # I Name 061 Auxiliary/Emergency Feedwater

[Question 45] 062 AC Electrical Distribution

[Question 46] 063 DC Electrical Distribution

[Question 47] 063 DC Electrical Distribution

[Question 48] 064 Emergency Diesel Generator

[Question 49] 073 Process Radiation Monitoring

[Question 50] 076 Service Water [Question 51] NUREG-1021, Revision 10 K K K K 1 2 3 4 x RO Page 9of13 -Tier 2/Group 1 (RO) Continued KIA Topic(s) IR K6 Knowledge of the effect of a loss or 2.5 malfunction of the following will have on the AFW components:

K6.01 -Controllers and positioners (CFR: 41.7 / 45.7) K4 Knowledge of ac distribution system design 2.8* feature(s) and/or interlock(s) which provide for the following:

K4.03 -Interlocks between automatic bus transfer and breakers (CFR: 41.7) A4 Ability to manually operate and/or monitor in the control room: A4.01 -Major breakers and control power fuses (CFR: 41. 7 I 45.5 to 45.8) 2.8* A2 Ability to (a) predict the impacts of the 2.5 following malfunctions or operations on the DC electrical systems; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.01 -Grounds (CFR: 41.5 / 43.5 / 45.3 / 45.13) K2 Knowledge of bus power supplies to the following:

K2.01 -Air compressor CFR:41.7 K5 Knowledge of the operational implications as they apply to concepts as they apply to the PRM system: K5.01 -Radiation theory, including sources, types, units, and effects (CFR: 41.5 / 45.7) A 1 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the SWS controls including:

A 1.02 -Reactor and turbine building closed cooling water temperatures CFR: 41.5 / 45.5 2.7* 2.5 2.6* FENOC Facsimile Rev. AG #

ES-401 System # I Name 076 Service Water [Question 52] 078 Instrument Air [Question 53] 078 Instrument Air [Question 54] 103 Containment

[Question 55] l<'A Category Point Totals: NUREG-1021, Revision 10 PWR Examination Outline Form ES-401-2 Plant Systems K K K K K K A 1234561 -Tier 2/Group 1 (RO) Continued KIA Topic(s) 2.1.27 -Knowledge of system purpose and/or function.

CFR: 41.7 A4 Ability to manually operate and/or monitor in the control room: A4.01 -Pressure gauges (CFR: 41.7 I 45.5 to 45.8) K3 Knowledge of the effect that a loss or malfunction of the IAS will have on the following:

K3.02 -Systems having pneumatic valves and controls (CFR: 41. 7 I 45.6) K1 Knowledge of the physical connections and/or cause-effect relationships between the containment system and the following systems: (CFR: 41.2 to 41.9 I 45. 7 to 45.8) Group Point Total: IR 3.9 3.1 3.4 3.6 RO Page 10of13 FENOC Facsimile Rev. AG # 28 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems H======================r===;;==r==;==;==;===r====;;;

System # I Name 011 Pressurizer Level Control [Question 56] 014 Rod Position Indication

[Question 57] 016 Non-nuclear Instrumentation

[Question 58] 017 In-core Temperature Monitor [Question 59] r

• Containment Iodine oval [Question 60] 029 Containment Purge [Question 61] 055 Condenser Air Removal [Question 62] 071 Waste Gas Disposal [Question 63] NUREG-1021, Revision 10 K K K 1 2 3 RO Page 11 of 13 -Tier 2/Group 2(RO) KIA Topic(s) IR A2 Ability to (a) predict the impacts of the 3.4 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:

A2.10 -Failure of PZR level instrument

-high (CFR: 41.5 / 43.5 I 45.3 / 45.13) A4 Ability to manually operate and/or monitor in 3.3 the control room: A4.01 -Rod selection control (CFR: 41. 7 I 45.5 to 45.8) A3 Ability to monitor automatic operation of the 2.9* NNIS, including:

A3.02 -Relationship between meter readings and actual parameter value (CFR: 41. 7 I 45.5) K6 Knowledge of the effect of a loss or malfunction of the following ITM system components:

K6.01 -Sensors and Detectors (CFR: 41.7 / 45.7) K1 Knowledge of the physical connections and/or cause effect relationships between the CIRS and the following systems: K1.01 -CSS (CFR: 41.2 to 41.9 I 45. 7 to 45.8) K3 Knowledge of the effect that a loss or malfunction of the Containment Purge System will have on the following:

K3.02 -Containment entry (CFR: 41. 7 I 45.6) 2.4.34 -Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects. (CFR: 41.10 / 43.5 / 45.13) K4 Knowledge of design feature(s) and/or interlock(s) which provide for the following:

K4.03 -Tank loop seals (CFR: 41.7) 2.7 3.4* 2.9* 4.2 2.5* FENOC Facsimile Rev. AG #

ES-401 System # I Name 072 Area Radiation Monitoring

[Question 64] 086 Fire Protection

[Question 65] KIA Category Point Totals: NUREG-1021, Revision 10 K K K K 1 2 3 4 PWR Examination Outline Form ES-401-2 Plant Systems -Tier 2/Group 2(RO) Continued KIA Topic(s) K5 Knowledge of the operational implications of the following concepts as they apply to the ARM system: K5.01 -Radiation theory, including sources, types, units, and effects (CFR: 41.5 I 45. 7) IR 2.7 A1 Ability to predict and/or monitor changes in 2.9 parameters (to prevent exceeding design limits) associated with Fire Protection System operating the controls including:

A 1.01 -Fire header pressure (CFR: 41.5 / 45.5) 1 0 1 1 1 1 1 1 1 1 1 Group Point Total: RO Page 12 of 13 FENOC Facsimile Rev. AG # 10 401 Category 1. Conduct of Operations

2. Equipment Control 3. Radiation Control 4. Emergency Procedures/

Plan Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 BVPS UNIT 1 RO Date of Exam 10/31 thru 11/18/2016 KIA# Topic 2.1.19 Ability to use plant computers to evaluate system or component status. (CFR: 41.10 / 45.12) Question 66 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. (CFR: 41.10 / 45.12) Question 67 Subtotal 2.2.25 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. (CFR: 41.5 / 41.7 / 43.2) Question 68 2.2.36 Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations. (CFR: 41.10 I 43.2 / 45.13) Question 69 2.2.43 Knowledge of the process used to track inoperable alarms. (CFR: 41.10 I 43.5 I 45.13) Question 70 Subtotal 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions. (CFR: 41.12 I 45.10) Question 71 2.3.11 Ability to control radiation releases. (CFR: 41.11143.4/45.10)

Question 72 IR 3.9 3.9 3.1 3.0 3.8 2.3.12 Knowledge of radiological safety principles pertaining to licensed 3.2 Subtotal operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. (CFR: 41.12 / 45.9 / 45.10) Question 73 2.4.6 Knowledge of EOP mitigation strategies. (CFR: 41.10 / 43.5 / 45.13) Question 74 2.4.50 Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. (CFR: 41.10 I 43.5 / 45.3) Question 75 Subtotal 4.2 RO # Tier 3 Point Total NUREG-1021, Revision 10 RO Page 13of13 FENOC Facsimile Rev. AG ES-401 PWR Examination Outline Facility:

BVPS UNIT 1 SRO 11----....:;......:;:;;;:;;;::;;:;;;::;;:;;;;;;;;;;;;;

Date of Exam Tier Group 1 1. Emergency 2 & Abnormal Plant Tier Evolutions Totals 1 2. Plant 2 Systems Tier Totals 3. Generic Knowledge and Abilities Category Note: Form ES-401-2 10/31thru11/18/2016 SRO ONLY Points A2 G* TOTAL 3 3 6 2 2 4 5 5 10 3 2 5 0 2 1 3 5 3 8 1 2 3 4 7 2 2 2 1 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). (One Tier 3 Radiation Control KIA is allowed if the KIA is replaced by a KIA from another Tier 3 Category).

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 with justification; 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) Kl As 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 Kl As. 8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (I Rs) 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 a category 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, I Rs, and point totals(#)

on Form ES-401-3.

Limit SRO selections to KIAs that are linked to 1 O CFR 55.43. G* Generic KIAs NUREG-1021, Revision 10 SRO Page 1 of 6 FENOC Facsimile Rev. AG ES-401 E/APE #I Name I Safety Function 000026 Loss of Component Cooling Water I 8 [Question 76] 000040 Steam Line Rupture -Excessive Heat Transfer I 4 [Question 77] 000054 Loss of Main Feedwater I 4 [Question 78] 000055 Station Blackout/

6 [Question 79] 000057 Loss of Vital AC Inst. Bus/ 6 [Question 80] 000077 Generator Voltage and Electric Grid Disturbances I 6 [Question 81] KIA Category Point Totals: NUREG-1021, Revision 10 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions -Tier 1/Group 1(SRO) K K K A 1 2 3 1 3 3 KIA Topic(s) AA2. Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: AA2.04 -The normal values and upper limits for the temperatures of the components cooled by CCW (CFR: 43.5145.13) 2.4.41 -Knowledge of the emergency action level thresholds and classifications. (CFR: 41.10 / 43.5 / 45.11) IR 2.9* 4.6 AA2. Ability to determine and interpret the following 4.4 as they apply to the Loss of Main Feedwater (MFW): AA2.01 -Occurrence of reactor and/or turbine trip (CFR: 43.5 I 45.13) 2.2.44 -Ability to interpret control room indications to 4.4 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 AA2. Ability to determine and interpret the following 3.8* as they apply to the Loss of Vital AC Instrument Bus: AA2.02 -Core flood tank pressure and level , indicators (CFR: 43.5 I 45.13) 2.4.31 -Knowledge of annunciator alarms, indications, or response procedures. (CFR: 41.10 I 45.3) Group Point Total: 4.1 SRO Page 2 of 6 FENOC Facsimile Rev. AG # 6 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions

-Tier 1/Group 2(SRO) IF============================;==;==;==;==;

E/APE #I Name I Safety Function 000060 Accidental Gaseous Radwaste Rel. 19 [Question 82] 000074 lnad. Core Cooling/ 4 [Question 83] W/E01 Rediagnosis I 3 [Question 84] W/E10 Natural Circ. / 4 [Question 85] KIA Category Point Totals: NUREG-1021, Revision 10 K K K A 1 2 3 1 KIA Topic(s) 2.4.50 -Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. (CFR: 41.10 I 43.5 / 45.3) EA2 Ability to determine or interpret the following as they apply to Inadequate Core Cooling: EA2.08 -The effect of turbine bypass valve operation on RCS temperature and pressure (CFR 43.5 / 45.13) EA2. Ability to determine and interpret the following as they apply to the (Reactor Trip or Safety Injection Rediagnosis)

EA2.1 -Facility conditions and selection of appropriate procedures during abnormal and emergency operations (CFR: 43.5 / 45.13) 2.1.20 -Ability to interpret and execute procedure steps. CFR: 41.10 / 43.5 / 45.12 Group Point Total: IR 4.0 4.6* 4.0 4.6 SRO Page 3 of 6 FENOC Facsimile Rev. AG # 4 ES-401 System #I Name 004 Chemical and Volume Control [Question 86] 008 Component Cooling Water [Question 87] 1 059 Main Feedwater

[Question 88] 061 Auxiliary/Emergency Feedwater

[Question 89] 103 Containment

[Question 90] KIA Category Point Totals: NUREG-1021, Revision 10 PWR Examination Outline Form ES-401-2 Plant Systems K K K K K K A 1234561 -Tier 2/Group 1 (SRO) KIA Topic(s) 2.4.8 -Knowledge of how abnormal operating procedures are used in conjunction with EOPs. (CFR: 41.10 I 43.5 I 45.13) 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:

A2.02 -High/low surge tank level (CFR: 41.5 I 43.5 I 45.3 I 45.13) 2.4.6 -Knowledge of EOP mitigation strategies.

CFR: 41.10 I 43.5 I 45.13 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.02 -Loss of air to steam supply valve (CFR: 41.5 I 43.5 I 45.3 I 45.13) A2 Ability to (a) predict the impacts of the following malfunctions or operations on the containment system and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations A2.01 -Integrated leak rate test CFR: 41.5 I 43.5 I 45.3 I 45.13 Group Point Total: IR 4.5 3.5 4.7 3.6* 2.6* SRO Page 4 of 6 FENOC Facsimile Rev. AG # 5 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems -Tier 2/Group 2(SRO) System # I Name K K K K K K A KIA Topic(s) 1 2 3 4 5 6 1 IR # 015 Nuclear Instrumentation 2.2.25 -Knowledge of the bases in Technical 4.2 [Question 91] Specifications for limiting conditions for operations and safety limits. CFR: 41.5 I 41.7 I 43.2 035 Steam Generator A2 Ability to (a) predict the impacts of the 4.6 [Question 92] following malfunctions or operations on the GS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.06 -Small break LOCA (CFR: 41.5 I 43.5 I 45.3 I 45.5) 041 Steam Dump/Turbine A2 Ability to (a) predict the impacts of the 3.9 Bypass Control following malfunctions or operations on the [Question 93] SOS; and (b) based on those predictions or mitigate the consequences of those i* malfunctions or operations:

A2.02 -Steam valve stuck open CFR: 41.5 I 43.5 I 45.3 I 45.13 KIA Category Point Totals: 2 1 Group Point Total: 3 NUREG-1021, Revision 10 SRO Page 5 of 6 FENOC Facsimile Rev. AG I ES 401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 BVPS UNIT 1 SRO Date of Exam 10/31 thru 11/18/2016 L Category 1. Conduct of Operations

2. Equipment Control 3. Radiation Control 4. Emergency Procedures/

Plan KIA# Topic 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 1 OCFR55, etc. (CFR: 41.10 I 43.2) [Question 94] 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation. (CFR: 41.10 I 43.5 / 45.2 / 45.6) [Question 95] Subtotal 2.2.35 Ability to determine Technical Specification Mode of Operation. (CFR: 41.7 / 41.10 / 43.2 / 45.13) [Question 96] 2.2.37 Ability to determine operability and/or availability of safety related equipment. (CFR: 41.7 / 43.5 / 45.12) [Question 97] Subtotal 2.3.6 Ability to approve release permits. (CFR: 41.13 / 43.4 / 45.10) [Question 98] 2.3.13 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 I 43.4 / 45.9 / 45.10) [Question 99] Subtotal 2.4.5 Knowledge of the organization of the operating procedures network for normal, abnormal, and emergency evolutions. (CFR: 41.10 / 43.5 / 45.13) [Question 100] Subtotal Tier 3 Point Total NUREG-1021, Revision 10 SRO Page 6 of 6 SRO Only IR # 3.8 4.4 2 4.6 2 3.8 2 1 7 FENOC Facsimile Rev. AG ES-401 Record of Rejected Kl As Form ES-401-4 I Facility:

BVPS Unit 1 Date of Exam 10/31 thru 11/18/2016 Operating Test No.: BV1LOT16 NRC I Tier I Randomly Reason for Rejection Group Selected KIA 1 /1 000011 EA2.02 Question #4; There is no interface between Safety Injection and Residual Heat Removal (RHRS) at Beaver Valley. Randomly selected 000011 EA2.07 as a replacement.

1 /1 W/E04 Question #15; Unable to write a discriminatory question due to the limited EK3.1 scope of the LOCA Outside Containment procedure.

Randomly selected W/E EK3.2 as a replacement.

2/1 007 K5.02 Question #33; The PRT is not used to form a steam bubble in the PZR. Randomly selected 007 K1 .01 as a replacement.

Outside KS due to importance ratings were <2.5. 2/1 022 A2.06 Question #40; Beaver Valley does not have Containment Cooling System (CCS) pumps. Randomly selected 022 A2.01 as a replacement.

2/1 059 A1 .07 Question #44; Beaver Valley Main Feedwater pumps are motor driven pumps and do not have variable speed control. Randomly selected 059 A 1.03 as a replacement.

2/1 073 K5.02 Question #50; K5.02 -Radiation intensity changes with source distance.

Reselected due to oversampling.

KIA was similar to Q64. Randomly selected 073 K5.01 as a replacement.

212 011 A2.08 Question #56; Pressurizer level is not compensated at Beaver Valley. Randomly selected 011 A2.10 as a replacement.

2/2 027 K2.01 Question #60; Containment Iodine Removal fans are no longer used at Beaver Valley. Randomly selected 027 K1 .01 as a replacement.

2/2 072 K5.02 Question #64; Reselect per NRC feedback, oversampling of generic fundamental type questions on the exam. Randomly selected 072 K5.01 as a replacement.

212 086 A1 .02 Question #65; Beaver Valley does not have a fire water storage tank which has design limits which are monitored by the control room staff. The tank is used for fire protection outside the protected area. Randomly selected 086A1.01 as a replacement.

1 /1 054 AA2.08 Question #78, Reselect per NRC feedback, the Feed flow-steam flow SRO feed flow chart recorder response had low discriminatory value. Randomly selected 054 AA2.01 as a replacement.

1/1 000077 Question #81; Unable to write a discriminatory SRO level question for SRO 2.4.1 Knowledge of EOP entry conditions and immediate action steps. Randomly selected 000077 G2.4.31 as a replacement.

1/2 W/E10 Question #85; Reselected due to overlap with Audit Exam. Randomly SRO 2.1.32 selected W/E10 G2.1.20 as a replacement.

NUREG-1021, Revision 10 FENOC Facsimile Rev. AG ES-301 Administrative Topics Outline Form ES-301-1 Facility:

Beaver Valley Unit 1 Date of Examination:

10/31 thru 11/18 2016 *amination Level RO [8] Administrative Topic (See Note) Conduct of Operations (RO A 1.1) Conduct of Operations (RO A 1.2) Equipment Control OA2) Radiation Control (RO A 3) Emergency Plan (RO A 4) Type Code* D,R D,R N,R D,R SROD Operating Test Number BV1LOT16 NRC Describe activity to be performed 2.1.25 (3.9) Ability to interpret reference materials, such as graphs, curves, tables, etc. JPM 1AD-001 Calculating a Shutdown Margin Following a Stuck Rod 2.1.7 (4.4) Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

JPM 1AD-003 Perform a Quadrant Power Tilt Ratio Calculation 2.2.41 (3.5) Ability to obtain and interpret station electrical and mechanical drawings.

JPM 1AD-040 Identify Isolation Boundary Points on Plant VOND 2.3.7 (3.5) Ability to comply with radiation work permit requirements during normal or abnormal conditions.

JPM 1AD-012 NOT EVALUATED Select RWP and Determine Maximum Allowable Stay Time NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics (which would require all 5 items). *Type Codes & Criteria NUREG-1021, Revision 10 (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)

FENOC Facsimile Rev. 1 ES-301 Administrative Topics Outline Form ES-301-1 Facility:

Beaver Valley Unit 1 Date of Examination:

10/31thru11/18 2016 amination Level RO D SRO lR1 Operating Test Number BV1LOT16 NRC Administrative Type Describe activity to be performed Topic Code* (See Note) Conduct of D,R 2.1.20 (4.6) Operations Ability to interpret and execute procedure steps. (SRO A 1.1) JPM 1AD-029 Prepare Partial OST [1 OST-1.1] for Performance Conduct of D,R 2.1.7 (4.7) Operations Ability to evaluate plant performance and make operational judgments based (SRO A 1.2) on operating characteristics, reactor behavior, and instrument interpretation.

JPM 1AD-009 Review a Quadrant Power Tilt Ratio Calculation Equipment N,R 2.2.41 (3.9) Control Ability to obtain and interpret station electrical and mechanical drawings.

I JPM 1AD-039 Identify Isolation Boundary Points on Plant VOND, then determine diesel operability Radiation Control D,R 2.3.4 (3.7) (SRO A 3) Knowledge of radiation exposure limits under normal or emergency conditions.

JPM 1AD-038 Determine Emergency Exposure Authorization Limits Emergency Plan D,R 2.4.44 (4.4) (SRO A 4) Knowledge of emergency plan protective action recommendations.

JPM 1AD-037 Determine Protective Action Recommendations (Part 1) NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics (which would require all 5 items). *Type Codes & Criteria (C)ontrol Room, (S)imulator, or Class(R)oom (D)irect from 3 for ROs; =::, 4 for SROs & RO retakes) (N)ew or (M)odified from bank e_ 1) (P)revious 2 exams 1; randomly selected)

NUREG-1021, Revision 10 FENOC Facsimile Rev. 1 ES 301 -C t IR on ro /I Pl t S t oom n-an 'YS ems o r ut me F orm ES 301 2 --Facility:

Beaver Unit 1 Date of Examination:

10/31/ thru 11/18 2016 Exam Level: RO l:RI SRO(I) D SRO(U) D Operating Test No.: BV1LOT16 NRC Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U) System I JPM Title Type Code* Safety Function S1 -Withdraw Shutdown Bank "A" (1CR-085)

S, M, L 1 S2 -Perform Manual Makeup to the Charging Pump Suction (1 CR-581) S,D,A 2 S3 -Depressurize RCS During SGTR (1 CR-638) S,D,A 3 S4 -Respond to a Loss of the RHR System (1 CR-694) S, M, L,A 4P SS -Transfer from Bypass to Main Feed Regulating Valve (1 CR-520) S,D,A 4S S6 -Manually Actuate CIB (1 CR-578) S,D,A,EN 5 S7 -Transfer Bus 1AE From Emergency To Normal Feed (1CR-097)

S,D 6 S8 -Verify CREVs Isolation (1 CR-662) S,N,A 7 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) P1 -Vent the Charging Pump Suction Header (1 PL-057) R,D,EN, P 2 P2 -Startup the Dedicated Auxiliary Feedwater Pump [FW-P-4] (1 PL-007) D,E 4S P3 -Locally Start the No. 1 Emergency Diesel Generator (1 PL-606) D,E,EN 6 @ 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 SRO-I I SRO-U (A)lternate Path 4-6 14-6 /2-3 (C)ontrol room (D)irect from bank S9/S8/S4 (E)mergency or abnormal in-plant :2:1/:2:1/:2:1 (EN)gineered safety feature ;:: 1 I;:: 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/<!2/:2:1 (P)revious 2 exams s 3/ s 3 Is 2 (randomly selected) (R)CA :2:1/<!1/<!1 (S)imulator NUREG-1021, Revision 10 FENOC Facsimile Rev. 1 ES 301 -C t IR on ro /I Pl t S t oom n-an *ys ems o r utme F orm ES 301 2 --Facility:

Beaver Unit 1 Date of Examination:

10/31/ thru 11/18 2016 Exam Level: RO D SRO(I) [RI SRO(U) D Operating Test No.: BV1LOT16 NRC Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U) System I JPM Title Type Code* Safety Function S1 -Withdraw Shutdown Bank "A" (1CR-085)

S, M, L 1 S2 -Perform Manual Makeup to the Charging Pump Suction (1 CR-581) S,D,A 2 S3 -Depressurize RCS During SGTR (1 CR-638) S,D,A 3 S5 -Transfer from Bypass to Main Feed Regulating Valve (1 CR-520) S,D,A 4S S6 -Manually Actuate CIB (1 CR-578) S,D,A,EN 5 S7 -Transfer Bus 1ae From Emergency To Normal Feed (1 CR-097) S,D 6 S8 -Verify CREVs Isolation (1 CR-662) S,N,A 7 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) P1 -Vent the Charging Pump Suction Header (1 PL-057) R, D,EN, P 2 P2 -Startup the Dedicated Auxiliary Feedwater Pump [FW-P-4] (1 PL-007) D,E 4S P3 -Locally Start the No. 1 Emergency Diesel Generator (1 PL-606) D,E,EN 6 @ 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 SRO-I I SRO-U (A)lternate Path 4-6 14-6 12-3 (C)ontrol room (D)irect from bank S9/S8/S4 (E)mergency or abnormal in-plant ;::1/;::1/;::1 (EN)gineered safety feature ;:: 1 I;:: 1 1 (control room system) (L)ow-power I Shutdown ;::1/;::1/;::1 (N)ew or (M)odified from bank including 1 (A) ;::21;::2/;::1 (P)revious 2 exams s 3/ s 3 Is 2 (randomly selected) (R)CA ;::11;::11;::1 (S)imulator NUREG-1021, Revision 10 FENOC Facsimile Rev. 1 A d" D ,ppen 1x s . 0 tr cenano u me 1L 16N1 Facility:

BVPS Unit 1 Scenario No. 1 Op Test No.: BV1LOT16 NRC Examiners:

Candidates:

SRO ATC BOP Initial IC-62 (17): 67% power, MOL, Equ. XE Conditions, CB "D"@ 177 steps, Conditions:

RCS boron -985 ppm, 1FW-P-3A OOS Turnover:

Maintain 67% power. Critical Tasks: 1. CT-2 (E-0.D) Crew manually actuates at least 1 train of SIS 2. CT-51 (FR-S.1.B)

Crew starts AFW pumps 3. CT-52 (FR-S.1.C)

Crew inserts negative reactivity Event Malf. No. Event Type Event Description No. 1 PRS06A (I,A) A TC, SRO Pressurizer level transmitter, LT-lRC-459 drifts low. (TS) SRO 2 XMT-MSS021A (I,A) BOP, SRO PT-1 MS-446 fails low. (TS) SRO 3 CHS03 (C,A) ATC, SRO Isolable 25 gpm RCS leak on letdown line. (AOP 1.6.7) 4 FWMOlA (R) ATC Main feedwater pump trip, requires turbine runback and (C,A) BOP, SRO manual rod insertion.

5 GENOl, (M) ALL Spurious Gen Trip with auto & manual Rx trip failures.

CRF12A, 12B (ATWS) 6 IOR X06i068C (C) ATC, SRO MOV-lCH-350 failed closed. 7 INH20,21,36 (C) BOP, SRO All AFW pumps fail to auto start. 8 RCS02A (M) ALL 950 gpm LOCA 9 VLV-MSS03,04 (C) BOP, SRO Reheat steam failure to auto isolate. 10 SIS 1 OA, SIS 1 OB (C) ATC, SRO Automatic SI actuation failure. (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal E-0 ___,. FR-S.1 ___,. E-0 ___,. E-1 ___,. Terminate after evaluating SI termination criteria.

NUREG-1021, Revision 10 FENOC Facsimile Rev AG Appendix D Scenario Outline 1L16N2 Facility:

BVPS Unit 1 Scenario No. 2 Op Test No.: BV1LOT16 NRC Examiners:

Candidates:

SRO ATC BOP Initial IC-64 (18): 100% power, MOL, Equ. XE Conditions, CB "D"@ 228 steps, Conditions:

RCS boron -870 ppm. 1FW-P-3A OOS Turnover:

Maintain 100% power. Critical Tasks: 1. CT-18 (E-3.A) Crew isolates ruptured SG 2. CT-19 (E-3.B) Crew establishes/maintains temperature Event Malf. No. Event Type Event Description No. "C" SG, selected Main steam flow transmitter, lMS-FT-494 1 XMT-MSS039A (I,A) BOP, SRO fails low, requires manual control of feedwater and placing alternate channel in service. 2 PRS08D (I,A) ATC, SRO PRZR pressure control transmitter, PT-lRC-444 fails high, (TS) SRO requires closing PORV and manual PRZR pressure control. 3 RCS03A (C,A) ATC, SRO 22 gpm SG Tube leak on "A" SG. (AOP 1.6.4) (TS) SRO 4 (R) ATC SG tube leak requires plant S/D IA W AOP 1.51.1. (N) BOP, SRO 5 RCS03A (M) ALL 650 gpm SGTR occurs on "A" SG during S/D. 6 INH40 (C)ATC, SRO "B" HHSI pump auto start failure on SI. 7 VLV-SGBOI,02,03 (C) BOP, SRO SG BD isolation failure, requires manual valve closure. 8 MSS08C (C) BOP, SRO Condenser steam dump valves fail open following cooldown, requires Main steam line isolation. (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal E-0-+ E-3 NUREG-1021, Revision 10 FENOC Facsimile Rev AG Appendix D Scenario Outline 1L 16N3 Facility:

BVPS Unit 1 Scenario No. 3 Op Test No.: BV1LOT16 NRC Examiners:

Candidates:

SRO ATC BOP Initial IC-66(5): power, BOL, CB "D"@ 109 steps, RCS boron -1750 ppm. Conditions:

Turnover:

Raise Rx power and place turbine online. Critical Tasks: 1. CT-1 (E-0.A) Crew manually trips the reactor. 2. CT-24 (E-0.C) Energize 1 AC emer bus 3. CT-9 (E-0.L) Establish flow from RPRW pump Event Malf. No. Event Type Event Description No. 1 (R) ATC Power increase to> P-10. (N) SRO 2 FWM08B (C,A) BOP, SRO "B" Bypass feed regulating valve fails asis in Auto. Requires manual control 3 CHS22 (C,A) ATC, SRO Failure ofFCV-lCH-122 controller, requires manual control X06D088M of PRZR lvl. 4 (N) BOP, SRO Startup standby Turbine plant River water pump 5 NIS08B (C,A) BOP, SRO N-42 Instrument power fuse blown. (>P6 and< PIO) (TS) SRO 6 XMT-CNM004A (TS) SRO CH 2, CNMT Pressure transmitter fails High, PT-lLM-lOOB 7 SISlOB (M) All Inadvertent Train "A" SI with Rx trip failure. 8 (C,A) ATC, SRO Manual Rx trip 9 EPS04E,04F (C) BOP, SRO Loss of lAE and lDF 4kv Busses on Rx trip w/ EDG auto INH53, 54 start failures.

10 INH32, 33 (C) BOP, SRO Reactor plant River water pump auto start failures on Sequencer, requires manually starting WR-P-lA and lB. 11 CHS21A (C) ATC, SRO Letdown isolation on SI unable to be recovered due to failure of LCV -1 CH-460A, requires Excess letdown. (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal E-0 -ES-1.1 NUREG-1021, Revision 10 FENOC Facsimile Rev AG Appendix D Scenario Outline 1L 16N5 Facility:

BVPS Unit 1 Scenario No. 5 Op Test No.: BV1LOT16 NRC Examiners:

Candidates:

SRO ATC BOP Initial IC-68 (10): 100% power, BOL, Equ. XE Conditions, CB "D" @ 228 steps, Conditions:

RCS boron -1210 ppm, 1FW-P-3A OOS Turnover:

Maintain 100% power. Critical Tasks: 1. CT-10 (E-0.M) Crew closes failed PORV valves. 2. CT-11 (E-0.0) Crew closes CNMT isolation valves. 3. CT-43 (FR-H.1.A)

Crew establishes feedwater flow before feed and bleed required.

Event Malf. No. Event Type Event Description No. 1 CHS20B (I,A) ATC, SRO VCT Level Transmitter, LT-lCH-115 fails low causing auto makeup to occur. "A" Feedwater flow transmitter fails high, requires manual 2 FWM14B (C,A) BOP, SRO control of Feedwater control valve and placing alternate channel in service and return to auto control. 3 NIS03D (C,A) ATC, SRO N44 failed high, control rods automatically insert. (AOP 1.1.3) (TS) SRO 4 (N) BOP, SRO N44 removal from service. (AOP 1.2.lC) (TS) SRO 5 CRF04 (C,A) BOP, SRO Dropped Rod, requires turbine load reduction (AOP 1.1.8) (TS) SRO 6 CRF04BP (C,A) A TC, SRO 2nd Dropped Rod, requires manual Rx trip. 7 (M)ALL Reactor Trip 8 PRS08E C)ATC, SRO PT-lRC-445 fails high on Rx trip, PORVs open, requires closing valves. 9 INH49 (C) BOP, SRO Train "B" CIA Actuation failure with MOV-lCH-378 (Tm A) VLV-SEA09 auto close failure. 10 (M) ALL Loss of ALL Feedwater

-FR-H.1 with main feed pump recovery. (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal E-0 FR-H.1 E-0 NUREG-1021, Revision 10 FENOC Facsimile Rev AG