ML023250499

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ML023250499
Person / Time
Site: Beaver Valley
Issue date: 09/30/2002
From: Hynes C
FirstEnergy Nuclear Operating Co
To: Conte R
NRC/RGN-I/DRS/OSB
Conte R
References
50-334/02-301 50-334/02-301
Download: ML023250499 (37)
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Text

ES-401 I PWR RO Examination Outline I Form ES-401-4 Facility: FENOC BVPS Unit 1 Date of Exam: 9/30/2002 Exam Level: RO Tier Group K/A Category Points Point Totals 1 2 3 4 5 6 1 2 3 4 *.

1.

Emergency& 2 4 2 2 JU2 V77 0 17 AbnormalPlant 3 0 0 1 1 0 *" 1 3 Evolutions Tier Totals 5 3 5 8 13 N 2 36

2. 1 4 0 1 4 3 0 2 3 3 2 23 Plant 2 3 2 2 2 2 1 3 1 1 2 1 20 Systems 3 0 0 0 2 1 1 1 0 0 2 8 Tier Totals 7 2 3 8 6 2 6 4 4 5 51
3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 3 3 3 4 13 Note: 1. Ensure that at least two topics from every K/A category are sampled within each tier (ie., the "Tier Totals" in each K/A 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 exam must total 100 points.
3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
4. Systems/evolutions within each group are identified on the associated outline.
5. The shaded areas are not applicable to the category/tier.

6.* The generic K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.

7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings for the SRO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.

BVPS-1 RO Outline Rev. 0 Page 1 of 1 NUREG 1021, Revision 8, (Si)

ES-401 ( BEAVER VALLEY UNIK , ARC License Examination For( _3-401-4 PWR RO Written Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1 Group 1 E/APE # / Name Safety Function G K1 K2 K3 Al A2 Number K/A Topic(s) Imp. Q#

000005 / Inoperable/Stuck Control Rod / 1 AA2.03 Ability to determine and interpret the following as they apply to 3.5 44 X the Inoperable/Stuck Control Rod: Required actions if more than one rod is stuck or inoperable.

000015/17 / RCP Malfunctions / 4 AA2.11 Ability to determine and interpret the following as they apply to 3.4 46 X the Reactor Coolant Pump Malfunctions (Loss of RC Flow):

When to jog RCPs during ICC E09 / Natural Circulation / 4 EK2.1 Knowledge of the interrelations between the Natural Circulation 3.2 95 X Operations and the following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

El0 / Natural Circ. With steam void in vessel /4 EA2.2 Ability to determine and interpret the following as they apply to 3.4 96 X the Natural Circulation with Steam Void in Vessel with/without RVLIS: Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

000024 / Emergency Boration / 1 AA1.07 Ability to operate and/or monitor the following as they apply to 3.3 47 X the Emergency Boration: BWST level.

000026 / Loss of Component Cooling Water / 8 AA1.01 Ability to operate and/or monitor the following as they apply to 3.1 48 X the Loss of Component Cooling Water: CCW temperature indications.

000027 / Pressurizer Pressure Control System AA2.07 Ability to determine and interpret the following as they apply to 3.1 60 Malfunction / 3 X the Pressurizer Pressure Control Malfunctions: Makeup flow indication.

E12 / Uncontrolled Depressurization of all SGs / 4 X 2.1.27 Conduct of Operations: Knowledge of system purpose and or 2.8 97 function.

E08/ RCS Overcooling - PTS /4 EK3.4 Knowledge of the reasons for the following responses as they 3.4 98 apply to the Pressurized Thermal Shock: RO or SRO function X within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.

000051 / Loss of Condenser Vacuum /4 AA2.02 Ability to determine and interpret the following as they apply to 3.9 50 X the Loss of Condenser Vacuum: Conditions requiring reactor and/or turbine trip.

000057 / Loss of Vital AC Elec. Inst. Bus /6 AK3.01 Knowledge of the reasons for the following responses as they 4.1 51 X apply to the Loss of Vital AC Instrument Bus: Actions contained in EOP for loss of vital AC electrical instrument bus.

000067 / Plant Fire On-site / 9 X AA1.06 Ability to operate and/or monitor the following as they apply to 3.5 52 the Plant Fire on Site: Fire alarm.

BVPS-1 RO Outline Rev. 0 Page 1 of 14 NUREG 1021, Revision 8, Supplement 1

ES-401 BEAVER VALLEY UNI1 , ARC License Examination Forl!. 8S-401-4 PWR RO Written Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1 Group 1 E/APE # / Name Safety Function G K1 K2 K3 Al A2 Number K/A Topic(s) imp. Q#

000068 / Control Room Evac. / 8 AA1.16 Ability to operate and/or monitor the following as they apply to 3.2 53 the Control Room Evacuation: Turbine throttle valve indicating lights and position indicators.

E14 / Loss of CTMT Integrity / 5 x EA1.2 Ability to operate and/or monitor the following as they apply to 3.3 99 the High Containment Pressure: Operating behavior characteristics of the facility.

000074 / Inad. Core Cooling / 4 x EA2.08 Ability to determine or interpret the following as they apply to 3.8 54 Inadequate operation onCore Cooling: The effects of turbine bypass valve RCS temperature and pressure.

(W/E06 & E07) / Degraded Core Cooling /4 EK1.2 Knowledge of the operational implications of the following 3.5 100 X concepts as they apply to the Degraded Core Cooling: Normal, abnormal and emergency operating procedures associated with yP nTo SCtg l:2Degraded Core Cooling.

K/A Category Point Totals:i 1 1 2 5 6GruPonTta:6 BVPS-1 RO Outline Rev. 0 Page 2 of 14 NUREG 1021, Revision 8, Supplement 1

ES-401 BEAVER VALLEY UNIý , ,NIRC License Examination For. ._S-401-4 PWR RO Written Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1 Group 2 E # / Name Safety Function G K1 K2 K3 Al A2 Number K/A Topic(s) Imp. Q#

000001 / Continuous Rod Withdrawal / 1 AK1.23 Knowledge of the operational implications of the following 2.6 42 X concepts as they apply to Continuous Rod Withdrawal:

Calculation of power defect: algebraic sum of moderator temperature and fuel temperature defects.

000003 / Dropped Control Rod / 1 AA2.04 Ability to determine and interpret the following as they apply 3.4 43 X to the Dropped Control Rod: Rod motion stops due to dropped rod.

000007 / Reactor Trip - Stabilization - Recovery / 1 EA2.04 Ability to determine or interpret the following as they apply to 4.6 58 X a reactor trip: If reactor should have tripped but has not done so, manually trip the reactor and carry out actions in ATWS EOP.

000008 / Pressurizer Vapor Space Accident /3 AA2.20 Ability to determine and interpret the following as they apply 3.4 59 X to the Pressurizer Vapor Space Accident: The effect of an open PORV on code safety, based on observation of plant parameters.

000009 / Small Break LOCA /3 x EA1.01 Ability to operate and/or monitor the following as they apply 4.4 62 to a small break LOCA: RCS pressure and temperature.

000011 / Large Break LOCA /3 EK2.02 Knowledge of the interrelations between the Large Break 2.6 45 LOCA and the following: Pumps.

E04 / LOCA Outside Containment / 3 EA2.2 Ability to determine and interpret the following as they apply 3.6 57 X to the LOCA Outside Containment: Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

E/01 Rediagnosis / 3 EK1.3 Knowledge of the operational implications of the following 3.1 55 x concepts as they apply to the Reactor Trip or Safety Injection/Rediagnosis: Annunciators and conditions indicating signals and remedial actions associated with the Reactor Trip or Safety Injection/Rediagnosis.

E02 /SI Termination / 3 EK1.3 Knowledge of the operational implications of the following 3.5 56 x concepts as they apply to the SI Termination: Annunciators and conditions indicating signals and remedial actions associated with the SI Termination.

000029 / Anticipated Transient w/o Scram / 1 x EK2.06 Knowledge of the interrelations between the ATWS and the 2.9 49 following: Breakers, relays and disconnects.

000029 / Anticipated Transient w/o Scram / 1 x EA1.01 Ability to operate and/or monitor the following as they apply 3.4 67 to a ATWS: Charging Pumps AK3.01 Knowledge of the reasons for the following responses as 3.2 61 000032 / Loss of Source Range NI/ 7 X they apply to the Loss of Source Range Nuclear Instrumentation: Startup termination on source-range loss.

BVPS-1 RO Outline Rev. 0 Page 3 of 14 NUREG 1021, Revision 8, Supplement 1

( BEAVER VALLEY UNrI , NRC License Examination For,. _S-401-4 ES-401 PWR RO Written Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1 Group 2 E/APE # / Name Safety Function G K1 K2 K3 Al A2 Number K/A Topic(s) Imp. Q#

AK3.05 Knowledge of the reasons for the following responses as 3.7 63 000037 / Steam Generator Tube Leak / 3 X they apply to the Steam Generator Tube Leak: Actions contained in procedures for radiation monitoring, RCS water inventory balance, S/G tube failure, and plant shutdown.

EA2.07 Ability to determine or interpret the following as they apply to 4.4 64 000038 / Steam Generator Tube Rupture 3 X a SGTR: Plant conditions, from survey of control room indications.

AA2.08 Ability to determine and interpret the following as they apply 2.9 65 000054 / Loss of Main Feedwater / 4 X to the Loss of Main Feedwater (MFW): Steam flow-feed trend recorder.

EKI.1 Knowledge of the operational implications of the following 3.8 68 E05 / Loss of Secondary Heat Sink /4 x concepts as they apply to the Loss of Secondary Heat Sink:

Components, capacity, and function of emergency systems.

AA2.02 Ability to determine and interpret the following as they apply 3.3 66 000058 / Loss of DC Power / 6 X to the Loss of DC Power: 125V dc bus voltage, low/critical low, alarm.

K/A Category Point Total: 0 4 2 2 2 7 Group Point Total: 17 BVPS-1 RO Outline Rev. 0 Page 4 of 14 NUREG 1021, Revision 8, Supplement 1

ES-401 BEAVER VALLY UNIT .4RC License Examination Form(. .-401-4 PWR RO Written Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1 Group 3 E/APE # / Name Safety Function G K1 K2 K3 Al A2 Number K/A Topic(s) mp.

000036 / Fuel Handling Accident / 8 x AA1.02 Ability to operate and/or monitor the following as they apply 3.1 69 to the Fuel Handling Incidents: ARM system.

000056 / Loss of Off-site Power / 6 AK3.02 Knowledge of the reasons for the following responses as 4.4 70 X they apply to the Loss of Offsite Power: Actions contained in EOP for loss of offsite power.

000065 / Loss of Instrument Air / 8 2.4.50 Emergency Procedures/Plan: Ability to verify system alarm 3.3 71 set points and operate controls identified in the alarm response manual.

K/A Category Point Totals: 1 0 0 1 1 0 Group Point Total: 3 BVPS-11 RO Outline Rev. 0 Page 5 of 14 NUREG 1021, Revision 8, Supplement 1

ES-401 BEAVER VALLEY UNI' , NRC License Examination Form -,401-4 PWR RO Written Examination Outline Plant Systems -Tier 2 Group 1 System #/Name G K1I K2 K3 K4 K5 K6 Al A2 I A3 A4 Number K/A Topics Imp. Q#

001 Control Rod Drive K4.17 Knowledge of CRDS design feature(s) and/or 2.9 1 X interlock(s) which provide for the following: Override (bypass) for rod bank motion when one rod is bottomed.

001 Control Rod Drive x K3.01 Knowledge of the effect that a loss or malfunction of the 2.9 2 CRDS will have on the following: CVCS 003 Reactor Coolant Pump A2.02 Ability to (a) predict the impacts of the following 3.7 3 malfunctions or operations on the RCPS; and (b) based X on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP.

003 Reactor Coolant Pump x A3.05 Ability to monitor automatic operation of the RCPS, 2.7 4 including: RCP lube oil and bearing lift pumps.

004 Chemical and Volume K5.08 Knowledge of the operational implications of the 2.6 6 Control X following Estimationconcepts as they of subcritical apply to the CVCS:

multiplication factor (K-eff) by means other than the 6-factor formula: relationship of count rate changes to reactivity changes.

004 Chemical and Volume K1.06 Knowledge of the physical connections and/or cause- 3.1 5 Control X effect relationships between the CVCS and the following systems: Makeup system to VCT.

013 Engineered Safety Features x 2.1.14 Conduct of Operations: Knowledge of system status 2.5 7 Actuation criteria which require the notification of plant personnel.

013 Engineered Safety Features x A4.01 Ability to manually operate and/or monitor in the control 4.5 8 Actuation room: ESFAS-initiated equipment which fails to actuate.

015 Nuclear Instrumentation K5.02 Knowledge of the operational implications of the 2.7 9 X following concepts as they apply to the NIS:

Discriminator/compensation operation.

015 Nuclear Instrumentation X A3.01 Ability to monitor automatic operation of the NIS, 3.8 10 including: Console and cabinet indications.

017 In-Core Temperature Monitor K1.01 Knowledge of the physical connections and/or cause 3.2 12 X effect relationships between the ITM system and the following systems: Plant computer.

022 Containment Cooling A1.01 Ability to predict and/or monitor changes in parameters 3.6 14 X (to prevent exceeding design limits) associated with operating the CCS controls including: Containment temperature.

BVPS-1 RO Outline Rev. 0 Page 6 of 14 NUREG 1021, Revision 8, Supplement 1

ES-401 BEAVER VALLEY UNI 4 .4RC License Examination Form ,01-4 PWR RO Written Examination Outline Plant Systems -Tier 2 Group 1 System #/Name G K1 K2 K3 K4 K5 K6 Al A2 A3 A4 Number KQA Topics imp.

022 Containment Cooling K4.04 Knowledge of CCS design features and/or interlocks 2.8 13 X which provide for the following: Cooling of control rod drive motors.

056 Condensate K1.03 Knowledge of the physical connections and/or cause- 2.6 72 X effect relationships between the Condensate System and the following system: MFW 059 Main Feedwater 2.1.23 Conduct of Operations: Ability to perform specific 3.9 73 X system and integrated plant procedures during all modes of plant operation.

059 Main Feedwater K4.16 Knowledge of MFW System design feature(s) and/or 3.1 74 x interlock(s) which provide for the following: Automatic trips for MFW pumps.

061 Auxiliary/Emergency A1.02 Ability to predict and/or monitor changes in parameters 3.3 75 Feedwater X (to prevent exceeding design limits) associated with operating the AFW System controls including: S/G pressure.

061 Auxiliary/Emergency K5.01 Knowledge of the operational implications of the 3.6 76 Feedwater X following concepts as they apply to the AFW System:

Relationship between AFW flow and RCS heat transfer.

068 Liquid Radwaste A3.02 Ability to monitor automatic operation of the Liquid 3.6 77 Radwaste System, including: Automatic isolation.

071 Waste Gas Disposal A2.03 Ability to (a) predict the impacts of the following 2.7 78 malfunctions or operations on the Waste Gas Disposal X System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Rupture disk failures.

071 Waste Gas Disposal K4.06 Knowledge of Waste Gas Disposal System design 2.7 79 feature(s) and/or interlock(s) which provide for the X following: Sampling and monitoring of waste gas release tanks.

072 Area Radiation Monitoring A2.01 Ability to (a) predict the impacts of the following 2.7 84 malfunctions or operations on the ARM system; and (b)

X based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Erratic or failed power supply.

BVPS-1 RO Outline Rev. 0 Page 7 of 14 NUREG 1021, Revision 8, Supplement 1

C ES-401 BEAVER VALLEY UNl , ,RC License Examination Form -401-4 PWR RO Written Examination Outline Plant Systems -Tier 2 Group 1 System #/Name G I K1 I K2 I K3 I K4 I K5 I K6 I Al IA2 I A3 I A4 I Number I K/A Topics Imp. Q:§#E 072 Area Radiation Monitoring K1.04 Knowledge of the physical connections and/or cause- 3.3 81 X effect relationships between the ARM system and the following systems: Control room ventilation.

K/A Category Point Totals: 2 4 0 1 4 3 0 2 3 3 1 Group Point Total: 23 BVPS-1 RO Outline Rev. 0 Page 8 of 14 NUREG 1021, Revision 8, Supplement 1

C BEAVER VALLEY UNIý , NRC License Examination Form L 4 ES-401 PWR RO Written Examination Outline Plant Systems -Tier 2 Group 2 System #/Name G K1i K2 K3 K4 K5 K6 Al A2 A3 A4 Number K/A Topics Imp. Q I 002 / Reactor Coolant A1.13 Ability to predict and/or monitor changes in parameters 3.4 17 (to prevent exceeding design limits) associated with X operating the RCS controls including: Core exit thermocouples.

006 Emergency Core Cooling A1.14 Ability to predict and/or monitor changes in parameters 3.6 19 (to prevent exceeding design limits) associated with X operating the ECCS controls including: Reactor vessel level.

006 Emergency Core Cooling K6.05 Knowledge of the effect of a loss or malfunction of the 3.0 18 X following will have on the ECCS: HPI/LPI cooling water.

011 Pressurizer Level Control K5.15 Knowledge of the operational implications of the 3.6 22 X following concepts as they apply to the PZR LCS: PZR level indication when RCS is saturated.

011 Pressurizer Level Control X K2.01 Knowledge of bus power supplies to the following: 3.1 21 Charging pumps.

012 Reactor Protection K4.06 Knowledge of RPS design feature(s) and/or interlock(s) 3.2 23 X which provide for the following: Automatic or manual enable/disable of RPS trips.

012 Reactor Protection A2.05 Ability to (a) predict the impacts of the following 3.1 24 malfunctions or operations on the RPS; and (b) based x on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Faulty or erratic operation of detectors and function generators.

014 Rod Position Indication X A4.01 Ability to manually operate and/or monitor in the control 3.3 11 room: Rod selection control.

016 Non-Nuclear Instrumentation X K3.01 Knowledge of the effect that a loss or malfunction of 3.4 25 the NNIS will have on the following: RCS.

026 Containment Spray X A4.05 Ability to manually operate and/or monitor in the 3.5 16 Control Room: Containment spray reset switches.

026 Containment Spray X K2.02 Knowledge of bus power supplies to the following: 2.7 15 MOVs.

033 Spent Fuel Pool Cooling K4.02 Knowledge of Spent Fuel Pool Cooling System design 2.5 28 X feature(s) and/or interlock(s) which provide for the following: Maintenance of spent fuel cleanliness.

BVPS-1 RO Outline Rev. 0 Page 9 of 14 NUREG 1021, Revision 8, Supplement 1

I ES-401 BEAVER VALLEY UNIT 4RC License Examination Form E Al PWR RO Written Examination Outline Plant Systems -Tier 2 Group 2 I System #/Name G KI K2 K3 K4 K5 I K6 Al A2 A3 I A4 Number K/A Topics IImp. Q#

Ability to predict and/or monitor changes in parameters 3.5 26 (to prevent exceeding design limits) associated with operating the S/GS controls including: SG pressure.

Knowledge of the operational implications of the 3.6 29 following concepts as they apply to the MRSS: Effect of steam removal on reactivity.

Emergency Procedures/Plan: Ability to recognize 4.0 30 abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

Knowledge of the physical connections and/or cause- 2.7 82 effect relationships between the D.C. Electrical System and the following systems: AC electrical system.

Knowledge of the effect that a loss or malfunction of 4.2 83 the ED/G System will have on the following: ESFAS controlled or actuated systems.

Knowledge of the physical connections and/or cause- 3.6 20 effect relationships between the PRM System and the following systems: Those systems served by PRMs.

Knowledge of the physical connections and/or cause- 2.9 80 effect relationships between the Circulating Water System and the following systems: Liquid radwaste discharge.

Ability to monitor automatic operation of the Fire 2.9 85 Protection System including: Actuation of fire detectors.

Group Point Total: 20 BVPS-1 RO Outline Rev. 0 Page 10 of 14 NUREG 1021, Revision 8, Supplement 1

t ES-401 BEAVER VALLEY UNIl , NRC License Examination Fori(. 401-4 PWR RO Written Examination Outline Plant sv.tems -Ticer 9 (rrn 'I system #/Name G K1i K2 K3 K4 IK5 K6 Al A22A A4 Number K/A Topics Imp. O#

( I 005 Residual Heat Removal K5.02 Knowledge of the operational implications of the 3.4 31 X following concepts as they apply to the RHRS: Need

_______________________for adequate subcooling.

005 Residual Heat Removal A4.04 Ability to manually operate and/or monitor in the control 3.1 32 X room: Controls and indication for closed cooling water pumps.

028 Hydrogen Recombiner and K6.01 Knowledge of the effect of a loss or malfunction of the 2.6 27 Purge Control X following will have on the HRPS: Hydrogen recombiners.

045 Main Turbine Generator K4.43 Knowledge of MT/G system design feature(s) and/or 2.8 86 X interlock(s) which provide for the following: T-ave.

program, in relation to SDS controller.

045 Main Turbine Generator A1.06 Ability to predict and/or monitor changes in parameters 3.3 87 (to prevent exceeding design limits) associated with X operating the MT/G System controls including:

Expected response of secondary plant parameters following T/G trip.

076 Service Water 2.4.49 Emergency Procedures/Plan: Ability to perform without 4.0 88 X reference to procedures those actions that require immediate operation of system components and controls.

078 Instrument Air K4.03 Knowledge of IAS design feature(s) and/or interlock(s) 3.1 89 which provide for the following: Securing of SAS upon loss of cooling water.

078 Instrument Air x 2.1.2 Conduct of Operations: Knowledge of operator 3.0 90 responsibilities during all modes of plant operation.

K/A Category Point Totals: 2 0 0 0 2 1 1 1 0 0 1 Group Point Total: 8 BVPS-1 RO Outline Rev. 0 Page 11 of 14 NUREG 1021, Revision 8, Supplement 1

ES-401 ( BEAVER VALLEY UNI jRC License Examination Form ES-4('

PWR RO Written Examination Outline Plant-Specific Priorities System / Topic Question No. Recommended Replacement for... Reason Points 009EA1.01 62 033AA2.12 PRA Top Ten Operator Action 1 029EA1.01 67 060AA1.01 PRA Top Ten Operator Action I 003A2.02 3 003K1.01 PRA Top Ten Operator Action 1 013A4.01 8 017A3.02 PRA Top Ten Operator Action 1 061A1.01 7 013G2.1.14 Risk Important System 062K4.01 30 055G2.4.4 Risk Important System 076A4.01 88 076G2.4.49 Risk Important System 008K3.03 90 078G2.1.2 Risk Important System 4 I 4 4 I. 4

+ i I 4 4 + 4 4 4 4 *1 4 4 4 1 4 4 4 4-4 4 1 1-Plant-Specific Priority Total: (limit 10)

BVPS-1 RO Outline Rev. 0 Page 12 of 14 NUREG 1021, Revision 8, Supplement 1

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5 Facility: FENOC BVPS Unit 1 Date of Exam: 9130/2002 Exam Level: RO Category K/A # Topic Imp. Q#

2.1.25 Ability to obtain and interpret station reference 2.8 35 materials such as graphs, monographs, and tables which contain performance data.

Conduct of 2.1.24 Ability to obtain and interpret station electrical and 2.8 34 Operations mechanical drawings.

2.1.18 Ability to make accurate, clear and concise logs, 2.9 33 records, status boards, and reports.

Total 3 2.2.1 Ability to perform pre-startup procedures for the 3.7 37 facility, including operating those controls associated with plant equipment that could affect reactivity.

Equipment 2.2.12 Knowledge of surveillance procedures. 3.0 36 Control 2.2.33 Knowledge of control rod programming. 2.5 38 Total 3 2.3.9 Knowledge of the process for performing a 2.5 40 containment purge.

Radiation 2.3.11 Ability to control radiation releases. 2.7 39 Control 2.3.1 Knowledge of 10CFR20 and related facility radiation 2.6 41 control requirements.

Total 3 2.4.18 Knowledge of the specific bases for EOPs. 2.7 91 Emergency 2.4.46 Ability to verify that the alarms are consistent with the 3.5 92 Procedures/ Plan plant conditions.

2.4.5 Knowledge of the organization of the operating 2.9 93 procedures network for normal, abnormal and emergency evolutions.

2.4.31 Knowledge of annunciators, alarms and indications, 3.3 94 and use of the response instructions.

Total 4 Tier 3 Point Total (RO) 13 BVPS-1 RO Outline Rev. 0 Page 13 of 14 NUREG 1021, Revision 8, S1

ES-40ý( BEAVER VALLEY UNIT ( ',C License Examination Form ES-40(

PWR RO Written E__amination Outline Record of Rejected K/As Tier/Group Randomly Selected K/A Reason for Rejection 1/1 040G2.2.22 Not RO level topic. No link to 10CFR55.41. Randomly selected 051AA2.02 to replace.

2/1 068K4.01 Difficult and potentially redundant topic to develop test item. Randomly generated 059K4.16 to replace.

2/1 056G2.1.33 Not RO level topic. No link to 10CFR55.41. Randomly selected 056K1.03 to replace.

2/1 022A1.04 Redundant topic with lower importance. Randomly selected 022K4.04 to replace.

2/2 016K3.07 Redundant K/A in same topic area. Randomly selected 035A1.02 to replace.

2/2 01 0K2.04 Facility does not have indicators. Randomly selected 073K1.01 to replace.

2/2 012A2.05 No suitable questions. Randomly selected 012K6.06 to replace.

3 G2.2.25 Not RO level Topic. No link to 1 0CFR55.41. Randomly selected 2.2.12 to replace.

3 G2.4.30 Not RO level Topic. No link to 10CFR55.41. Randomly selected 2.4.18 to replace.

I IL I I I

  • I I-I I I I i i 4 I I
  • J I 4- I 4- 4 1- 4

__ _ _ I_ I

+ i

_ ~~~~I __ ______

BVPS-1 RO Outline Rev. 0 Page 14 of 14 NUREG 1021, Revision 8, Supplement 1

ES-401 I PWR SRO Examination Outline I Form ES-401-4 Facility: FENOC BVPS Unit 1 Date of Exam: 9130/2002 Exam Level: SRO Tier Group K/A Category Points Point

-Totals 1 2 3 4 5 6 1 2

  • I
1. 1 3 2 Emergency & 2 1 1 3 2 7 16 Abnormal Plant 3 0 0 1 1 1 3 Evolutions Tier Totals 4 3 4 7 19 6 43
2. 1 2 1 1 2 2 0 1 2 2 3 3 19 Plant 2 1 1 1 2 2 2 3 4 0 0 1 17 Systems 3 0 0 0 0 1 0 0 2 0 1 0 4 Tier Totals 3 2 2 4 5 2 4 8 2 4 4 40
3. Generic Knowledge and Abilities Cat I Cat 2 Cat 3 Cat 4 6 4 5 2 17 Note: 1. Ensure that at least two topics from every K/A category are sampled within each tier (ie., the "Tier Totals" in each K/A 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 exam must total 100 points.
3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
4. Systems/evolutions within each group are identified on the associated outline.
5. The shaded areas are not applicable to the category/tier.

6.* The generic K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.

7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings for the SRO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.

BVPS-1 SRO Outline Rev. 0 Page 1 of I NUREG 1021, Revision 8, (S1)

ES-401 t BEAVER VALLEY UNIT 41 ,C License Examination Form( 401-3 PWR SRO Written Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1 Group 1 E/APE #/Name/Safety Function IG KI IK21 K31 AlI A2 Number I K Topic(s) I1rImp. I 000001 / Continuous Rod Withdrawal / 1 AK1.23 Knowledge of the operational implications of the following concepts as they 2.9 42 X apply to Continuous Rod Withdrawal: Calculation of power defect: algebraic sum of moderator temperature and fuel temperature defects.

000003 / Dropped Control Rod / 1x AA2.04 Ability to determine and interpret the following as they apply to the Dropped 3.6 43 Control Rod: Rod motion stops due to dropped rod.

000005 / Inoperable/Stuck Control Rod / 1 AA2,03 Ability to determine and interpret the following as they apply to the 4.4 44 X Inoperable/Stuck Control Rod: Required actions if more than one rod is stuck or inoperable.

000005 / Inoperable/Stuck Control Rod / 1 x 2.1.33 Conduct of Operations: Ability to recognize indications for system operating 4.0 57 parameters which are entry level conditions for Technical Specifications.

000011 / Large Break LOCA / 3 x EK2.02 Knowledge of the interrelations between the Large Break LOCA and the 2.7 45 following: Pumps.

E01 / Rediagnosis / 3 EK1.3 Knowledge of the operational implications of the following concepts as they 3.5 55 X apply to the Reactor Trip or Safety Injection/Rediagnosis: Annunciators and conditions indicating signals, and remedial actions associated with the Reactor Trip or Safety Injection/Rediagnosis.

E02 / SI Termination / 3 EK1.3 Knowledge of the operational implications of the following concepts as they 3.8 56 X apply to the SI Termination: Annunciators and conditions indicating signals, and remedial actions associated with the SI Termination.

000015/17 / RCP Malfunctions /4 X AA2.1 1 Ability to determine and interpret the following as they apply to the Reactor 3.8 46 Coolant Pump Malfunctions (Loss of RC Flow): When to jog RCPs during ICC.

E09 / Natural Circulation / 4 X EA2.2 Ability to determine and interpret the following as they apply to the Natural 3.8 76 Circulation Operations: Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

El0 / Natural Circulation with Steam Void in EA2.1 Ability to determine and interpret the following as they apply to the Natural 3.9 75 Vessel / 4 Circulation with Steam Void in Vessel with/without RVLIS: Facility conditions X and selection of appropriate procedures during abnormal and emergency operations.

000024 / Emergency Boration / 1 X AA1.07 Ability to operate and/or monitor the following as they apply to the Emergency 3.4 47 Boration: BWST level.

000026 / Loss of Component Cooling Water / 8 X AA1.01 Ability to operate and/or monitor the following as they apply to the Loss of 3.1 48 Component Cooling Water: CCW temperature indications.

000026 / Loss of Component Cooling Water / 8 X AA2.02 Ability to determine and interpret the following as they apply to the Loss of 3.6 73 Component Cooling Water: The cause of possible CCW loss.

000029 / Anticipated Transient w/o Scram / 1 X EK2.06 Knowledge of the interrelations between the ATWS and the following: 3.1 49 Breakers, relays, and disconnects.

BVPS-1 SRO Outline Rev. 0 Page 1 of 13 NUREG 1021, Revision 8, Supplement 1

ES-401 BEAVER VALLEY UNIT .1C License Examination Fonrrr -401-3 PWR SRO Written Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1 Group 1 E/APE #IName/Safety Function G KII K2 K3 Ai A2 Number K/A Topic(s) Imp. Q#

000040 / Steam Line Rupture / 4 X 2.2.22 Equipment Control: Knowledge of limiting conditions for operations and safety 4.1 50 limits.

E12 / Uncontrolled Depressurization of all SGs / 4 EA2.1 Ability to determine and interpret the following as they apply to the 4.0 78 X Uncontrolled Depressurization of all Steam Generators: Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

E08 / Pressurized Thermal Shock /4 EA2.1 Ability to determine and interpret the following as they apply to the 4.2 74 X Pressurized Thermal Shock: Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

000057 / Loss of Vital AC Elec. Inst. Bus / 6 X 2.4.31 Emergency Procedures/Plan: Knowledge of annunciators alarms and 3.4 51 indications, and use of the response instructions.

000059 / Accidental Liquid Radwaste Rel. / 9 X 2.1.2 Conduct of Operations: Knowledge of operator responsibilities during all 4.0 79 modes of plant operation.

000067 / Plant Fire On-site / 9 X AA1.06 Ability to operate and/or monitor the following as they apply to the Plant Fire 3.7 52 on Site: Fire alarm.

000068 / Control Room Evac. /8 AA1.16 Ability to operate and/or monitor the following as they apply to the Control 3.3 53 X Room Evacuation: Turbine throttle valve indicating lights and position indicators.

000068 / Control Room Evac, / 8 AA2.05 Ability to determine and interpret the following as they apply to the Control 4.3 77 Room Evacuation: Availability of heat sink.

000074 / Inad. Core Cooling / 4 EA2.08 Ability to determine or interpret the following as they apply to an Inadequate 4.6 54 x Core Cooling: The effect of turbine bypass valve operation on RCS temperature and pressure.

E06 / Degraded Core Cooling /4 EA2.1 Ability to determine and interpret the following as they apply to the Saturated 4.2 80 X Core Cooling: Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

K/A Category Point Totals: 4 3 2 0 4 11 ; Group Point Total: 24 BVPS-1 SRO Outline Rev. 0 Page 2 of 13 NUREG 1021, Revision 8, Supplement 1

ES-401 BEAVER VALLEY UNIT .C License Examination Form ES-401(

PWR SRO Written Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1 Group 2 E/APE #/Name/Safety Function G KI K2 K3 Al A2 Number K/A Topic(s) I Imp.

000007 / Reactor Trip - Stabilization - Recovery / EA2.04 Ability to determine or interpret the following as they apply to a reactor trip: If 1 4.4 58 reactor should have tripped but has not done so, manually trip the reactor and carry out actions in ATWS EOP.

000008 / Pressurizer Vapor Space Accident / 3 AA2.20 Ability to determine and interpret the following as they apply to the Pressurizer 3.6 59 X Vapor Space Accident: The effect of an open PORV on code safety, based on observation of plant parameters.

000009 / Small Break LOCA / 3 X EK3.13 Knowledge of the reasons for the following responses as they apply to the small break LOCA: Stopping the affected 3.7 97 RCP.

000009 / Small Break LOCA / 3 X EA1.1 Ability to operate and/or monitor the following as they apply to a small break 4.3 62 LOCA: RCS pressure and temperature.

E03 / LOCA Cooldown - Depress./ 4 x 2.4.31 Emergency Procedures/Plan: Knowledge of annunciators alarms and 3.4 100 indications, and use of the response instructions.

000025 / Loss of RHR System / 4 X AA2.06 Ability to determine and interpret the following as they apply to the Loss of 3.4 98 Residual Heat Removal System: Existence of proper RHR overpressure protection.

000027 / Pressurizer Pressure Control System X AA2.07 Ability to determine and interpret the following as they apply to the Pressurizer 3.1 60 Malfunction / 3 Pressure Control Malfunctions: Makeup flow indication.

000032 / Loss of Source Range Ni/ 7 AK3.01 Knowledge of the reasons for the following responses as they apply to the 3.6 61 X Loss of Source Range Nuclear Instrumentation: Startup termination on source-range loss.

000037 / Steam Generator Tube Leak / 3 AK3.05 Knowledge of the reasons for the following responses as they apply to the 4.0 63 Steam Generator Tube Leak: Actions contained in procedures for radiation X monitoring, RCS water inventory balance, S/G tube failure, and plant shutdown.

000038 / Steam Generator Tube Rupture / 3 I X EA2.07 Ability to determine and interpret the following as they apply to a SGTR: Plant conditions, from survey of control room indications. 4.8 64 000038 / Steam Generator Tube Rupture / 3 x EA1.16 Ability to operate and/or monitor the following as they apply to a SGTR: SG atmospheric relief valve and secondary PORV controllers and 4.3 67 indicators.

000054 / Loss of Main Feedwater / 4 X AA2.08 Ability to determine and interpret the following as they apply to the Loss of 3.3 65 Main Feedwater (MFW): Steam flow-feed trend recorder.

E05 / Loss of Secondary Heat Sink / 4 EA2.2 Ability to determine and interpret the following as they apply to the Loss of 4.3 72 X Secondary Heat Sink: Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

BVPS-1 SRO Outline Rev. 0 Page 3 of 13 NUREG 1021, Revision 8, Supplement 1

ES-401 BEAVER VALLEY UNIT ( 11C License Examination Form ES-401(

PWR SRO Written Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1 Group 2 E/APE #/NamieSafety Function G KI K2 K3 Al A2 Number K/A Topic(s) Imp. Q#t E05 / Loss of Secondary Heat Sink / 4 EKI.1 Knowledge of the operational implications of the following concepts as they 4.1 68 x apply to the Loss of Secondary Heat Sink: Components, capacity, and function of emergency systems.

000058 / Loss of DC Power / 8 x 2.1.23 Conduct of Operations: Ability to perform specific system and integrated plant 4.0 66 procedures during all modes of plant operation.

E16 / High Containment Radiation /9 EK2.2 Knowledge of the interrelations between the High Containment Radiation and 3.0 99 the following: Facility's heat removal systems, including primary coolant, X emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

K/A Category Point Total: 2 1 1 3 2 7 Group Point Total: 16 BVPS-11 SRO Outline Rev. 0 Page 4 of 13 NUREG 1021, Revision 8, Supplement 1

/ I ES-401 BEAVER VALLEY UNIT i ,C License Examination Form( .401-3 PWR SRO Written Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1 Group 3 E/APE #/Name/Safety Function G KI K2 K3 Al A2 I Number I KATopic(s) Imp. Q1#

000028 / Pressurizer Level Malfunction / 2 X AA2.06 Ability to determine and interpret the following as they apply to Pressurizer 2.8 71 Level Control Malfunctions: Letdown flow indicator.

000036 / Fuel Handling Accident / 8 X AA1.02 Ability to operate and/or monitor the following as they apply to the Fuel 3.5 69 Handling Incidents: ARM system.

000056 / Loss of Off-site Power / 6 X AK3.02 Knowledge of the reasons for the following as they apply to the Loss of Offsite 4.7 70 Power: Actions contained in EOP for loss of offsite power.

K/A Category Point Totals: 0 0 0 1 1 1 ' ) Group Point Total: 3 BVPS-1 SRO Outline Rev. 0 Page 5 of 13 NUREG 1021, Revision 8, Supplement 1

ES-401 BEAVER VALLEY UNIT ( *C License Examination Form ES-401(

PWR SRO Written Examination Outline Plant Systems -Tier 2 Group 1 System#/Name G KI K21 K3 jK4jK5 K6jAl A2lA3jA4j Number I K/ATopics ImP*

001 Control Rod Drive X K3.01 Knowledge of the effect that a loss or malfunction of the 3.0 2 CRDS will have on the following: CVCS 001 Control Rod Drive K4.17 Knowledge of CRDS design feature(s) and/or interlock(s) 3.1 1 X which provide for the following: Override (bypass) for rod bank motion when one rod is bottomed.

003 Reactor Coolant Pump A2.02 Ability to (a) predict the impacts of the following 3.9 3 malfunctions or operations on the RCPS; and (b) based on x those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP.

003 Reactor Coolant Pump x A3.05 Ability to monitor automatic operation of the RCPS, 2.6 4 including: RCP lube oil and bearing lift pumps.

004 Chemical and Volume K5.08 Knowledge of the operational implications of the following 3.2 6 Control concepts as they apply to the CVCS: Estimation of X subcritical multiplication factor (K-eff) by means other than the 6-factor formula: Relationship of count rate changes to reactivity changes.

004 Chemical and Volume K1.06 Knowledge of the physical connections and/or cause-effect 3.1 5 Control X relationships between the CVCS and the following systems: Makeup system to VCT.

013 Engineered Safety Features 2.1.14 Conduct of Operations: Knowledge of system status 3.3 7 Actuation criteria which require the notification of plant personnel.

013 Engineered Safety Features X A4.01 Ability to manually operate and/or monitor in the control 4.8 8 Actuation room: ESFAS-initiated equipment which fails to actuate.

014 Rod Position Indication x 2.1.27 Conduct of Operations: Knowledge of system purpose 2.9 83 and/or function.

014 Rod Position Indication X A4.01 Ability to manually operate and/or monitor in the control 3.1 11 room: Rod selection control.

015 Nuclear Instrumentation K5.02 Knowledge of the operational implications of the following 2.9 9 x concepts as they apply to the NIS: Discriminator/

compensation operation.

015 Nuclear Instrumentation x A3.01 Ability to monitor automatic operation of the NIS, including: 3.8 10 Console and cabinet indications.

017 In-Core Temperature Monitor K1.01 Knowledge of the physical connections and/or cause effect 3.2 12 X relationships between the ITM system and the following systems: Plant computer.

BVPS-1 SRO Outline Rev. 0 Page 6 of 13 NUREG 1021, Revision 8, Supplement 1

Form ES-401-(

ES-401 BEAVER VALLEY UNIT 1( . License Examination PWR SRO Written Examination Outline Plant Systems -Tier 2 Group 1 System#1Name G I Kt JK2 1K3 1K4 K5 K Al A A3 A4 Number K/A Topics Im K4.04 Knowledge of CCS design feature(s) and/or interlock(s) 3.1 13 022 Containment Cooling X which provide for the following: Cooling of control rod drive motors.

A1.01 Ability to predict and/or monitor changes in parameters (to 3.7 14 022 Containment Cooling x prevent exceeding design limits) associated with operating the CCS controls including: Containment temperature.

X A4.05 Ability to manually operate and/or monitor in the control 3.5 16 026 Containment Spray room: Containment spray reset switches.

K2.02 Knowledge of bus power supplies to the following: MOVs. 2.9 15 026 Containment Spray X 2.2.22 Equipment Control: Knowledge of limiting conditions for 4.1 82 063 DC Electrical Distribution x operations and safety limits.

A2.01 Ability to (a) predict the impacts of the following 2.9 84 072 Area Radiation Monitoring malfunctions or operations on the ARM system and X (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Erratic or failed power supply.

3 2 1 2 2 0 1 2 2 3 Group Point Total: 19 KIA Category Point Totals:

BVPS-1 SRO Outline Rev. 0 Page 7 of 13 NUREG 1021, Revision 8, Supplement I

ES-401 ( BEAVER VALLEY UNIT 1( .3 License Examination Fo , -401-3 PWR SRO Wrtten Examination Outline Plant Systems -Tier 2 Group 2 System #/Name G IK1I K2 K3 K4 K5 K6 Al A2 A3 A4 Number K/A Topics Imp.

002 Reactor Coolant A1.13 Ability to predict and/or monitor changes in parameters (to 4.0 17 x prevent exceeding design limits) associated with operating the RCS controls including: Core exit thermocouples.

006 Emergency Core Cooling x K6.05 Knowledge of the effect of a loss or malfunction of the following will have on the ECCS: HPI/LPI cooling water. 3.5 18 006 Emergency Core Cooling A1.14 Ability to predict and/or monitor changes in parameters (to 3.9 19 X prevent exceeding design limits) associated with operating the ECCS controls including: Reactor vessel level.

006 Emergency Core Cooling A2.10 Ability to (a) predict the impacts of the following 3.9 85 X malfunctions or operations on the ECCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Low boron concentration in SIS.

011 Pressurizer Level Control X K2.01 Knowledge of bus power supplies to the following: 3.2 21 Charging pumps.

011 Pressurizer Level Control K5.15 Knowledge of the operational implications of the following 4.0 22 concepts as they apply to the PZR LCS: PZR level indication when RCS is saturated.

012 Reactor Protection K4.06 Knowledge of RPS design feature(s) and/or interlock(s) 3.5 23 X which provide for the following: Automatic or manual enable/disable of RPS trips.

012 Reactor Protection A2.05 Ability to (a) predict the impacts of the following 3.2 24 malfunctions or operations on the RPS; and (b) based on X those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Faulty or erratic operation of detectors and

_ _......._function generators.

016 Non-Nuclear Instrumentation X K3.01 Knowledge of the effect that a loss or malfunction of the 3.6 25 NNIS will have on the following: RCS.

028 Hydrogen Recombiner and x K6.01 Knowledge of the effect of a loss or malfunction of the 3.1 27 Purge Control following will have on the HRPS: Hydrogen recombiners.

033 Spent Fuel Pool Cooling K4.02 Knowledge of Spent Fuel Pool Cooling System design 2.7 28 x feature(s) and/or interlock(s) which provide for the following: Maintenance of spent fuel cleanliness.

BVPS-1 SRO Outline Rev. 0 Page 8 of 13 NUREG 1021, Revision 8, Supplement 1

ES-401 BEAVER VALLEY UNIT 1( .0 License Examination Fornm( '-401-3 PWR SRO Written Examination Outline Plant Systems -Tier 2 Group 2 System #/Name G I KI I K2 I K3 I K4 K5 I K6 I Al I A2 I A3 I A4 I Number K/A Topics Imp. I Q#

Ability to (a) predict the impacts of the following 3.9 87 malfunctions or operations on the following Fuel Handling System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Dropped cask.

I Ability to predict and/or monitor changes in parameters (to 3.8 26 prevent exceeding design limits) associated with operating the S/GS controls including: S/G pressure.

Knowledge of the operational implications of the following 3.6 29 concepts as they apply to the MRSS: Effect of steam removal on reactivity.

Emergency Procedures/Plan: Ability to recognize abnormal 4.3 30 indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

Ability to (a) predict the impacts of the following 2.9 86 malfunctions or operations on the ED/G System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Unloading (reduction of generated power) in steps over a period of time.

Knowledge of the physical connections and/or cause-effect 3.9 20 relationships between the PRM System and the following systems: Those systems served by PRMs.

Group Point Total: 17 BVPS-1 SRO Outline Rev. 0 Page 9 of 13 NUREG 1021, Revision 8, Supplement I

ES-401 BEAVER VALLEY UNIT T .C License Examination Form( 401-3 PWR SRO Written Examination Outline Plant Svstems -Tie~r 2 Grniin System #/Name G K1I K2 K3 K4 K5 K6 A IA2 A3 A4 Number - K/A Topics Imp. Q#

005 Residual Heat Removal K5.02 Knowledge of the operational implications of the following 3.5 31 X concepts as they apply to the RHRS: Need for adequate subcooling.

005 Residual Heat Removal A4.04 Ability to manually operate and/or monitor in the control 2.9 32 X room: Controls and indication for closed cooling water pumps.

041 Steam Dump/Turbine Bypass A2.03 Ability to (a) predict the impacts of the following 3.1 81 Control malfunctions or operations on the SDS; and (b) based on X those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of IAS.

078 Instrument Air A2.01 Ability to (a) predict the impacts of the following 2.9 88 malfunctions or operations on the IAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Air dryer and filter malfunctions.

K/A Category Point Totals: 0 0 0 0 0 1 0 0 2 0 1 i Group Point Total: 4 BVPS-1 SRO Outline Rev. 0 Page 10 of 13 NUREG 1021, Revision 8, Supplement 1

ES-401 BEAVER VALLEY UNIT ý C License Examination Form ES-401(

PWR SRO Written Examination Outline Plant-Specific Priorities I System / Topic Question No. Recommended Replacement for... Reason 009EA1.01 62 033AA2.12 PRA Top Ten Operator Action 038EA1.16 67 060AA1.01 PRA Top Ten Operator Action 013A4.01 11 017A3.02 PRA Top Ten Operator Action 061A1.01 7 013G2.1.14 Risk Important System 062K4.01 30 055G2.4.4 Risk Important System 4 4- +

4 t t 4 + 4

.4- 4 4 I- .4 Plant-Specific Priority Total: (limit 10)

BVPS-1 SRO Outline Rev. 0 Page 11 of 13 NUREG 1021, Revision 8, Supplement 1

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5 Facility: FENOC BVPS Unit I Date of Exam: 9/30/2002 Exam Level: SRO Category K/A # Topic Imp. Q#

2.1.12 Ability to apply technical specifications for a system. 4.0 94 2.1.25 Ability to obtain and interpret station reference 3.1 35 materials such as graphs, monographs, and tables which contain performance data.

2.1.8 Ability to coordinate personnel activities outside the 3.6 96 control room.

Conduct Of 2.1.26 Knowledge of non-nuclear safety procedures (e.g. 2.6 92 Operations rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).

2.1.24 Ability to obtain and interpret station electrical and 3.1 34 mechanical drawings.

2.1.18 Ability to make accurate, clear and concise logs, 3.0 33 records, status boards, and reports.

Total 6 2.2.25 Knowledge of bases in technical specifications for 3.7 36 limiting conditions for operations and safety limits.

2.2.1 Ability to perform pre-startup procedures for the 3.6 37 facility, including operating those controls associated with plant equipment that could affect reactivity.

Equipment 2.2.33 Knowledge of control rod programming. 2.9 38 Control 2.2.11 Knowledge of the process for controlling temporary 3.4 95 changes.

Total 4 2.3.5 Knowledge of use and function of personnel 2.5 93 monitoring equipment.

2.3.10 Ability to perform procedures to reduce excessive 3.3 89 levels of radiation and guard against personnel exposure.

Radiation 2.3.11 Ability to control radiation releases. 3.2 39 Control 2.3.9 Knowledge of the process for performing a 3.4 40 containment purge.

2.3.1 Knowledge of 10CFR20 and related facility radiation 3.0 41 control requirements.

Total 5 Emergency 2.4.1 Knowledge of EOP entry conditions and immediate 4.6 90 Procedures/ action steps.

Plan 2.4.36 Knowledge of chemistry/health physics tasks during 2.8 91 emergency operations.

Total 2 Tier 3 Point Total (SRO) 17 NUREG 1021, Revision 8, S1 BVPS-1 SRO Outline Rev. 0 Page 12 of 13

ES-401 BEAVER VALLEY UNIT 1 IC License Examination Form ES-401-3 (

PWR SRO Written' LAamination Outline Record of Rejected K/As Tier/Group Randomly Selected K/A Reason for Rejection 2/1 022A1.04 Redundant K/A in same topic area with lower importance. Randomly selected 022K4.04 to replace.

2/2 016K3.07 Redundant K/A in same topic area. Randomly selected 035A1.02 to replace.

2/2 01 0K2.04 Facility does not have indicators. Randomly selected 073K1.01 to replace.

2/2 012A2.05 No suitable questions. Randomly selected 012K6.06 to replace.

2/2 064A2.10 No suitable questions. Randomly selected 010K4.03 to replace.

t 1 1 1 1- 1 1- 4 t I r 1 1 I 1- 1 I I I I r 1 1- 1 I I 1- 1 1 I 1- 1 t i 1 I BVPS-1 SRO Outline Rev. 0 Page 13 of 13 NUREG 1021, Revision 8, Supplement I

ES-301 Administrative Topics Outline Form ES-301-1 (R8, $1)

ES3 diitaieTpc uln omES-301-1(8 I Facility: FENOC BVPS Unit 1 Date of Examination: 9/30/2002 Examination Level (circle one): SRO Operating Test Number. 2002-01 Administrative Describe method of evaluation:

Topic/Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A.1 Conduct of 2.1.3 (3.4) Knowledge of Shift Turnover Practices Operations JPM: Shift Relief and Tumover (1300-001-03-023) 2.1.25 (3.1) Ability to obtain and interpret station reference Conduct of materials such as graphs, monographs, and Operations tables which contain performance data JPM: Review SDM Calculation (1340-007-03-023)

A.2 Equipment 2.2.17 (3.5) Knowledge of the process for managing Control maintenance activities during power operations JPM: Evaluate Removing Equipment From Service (1300-027-03-023)

A.3 Radiation 2.3.10 (3.3) Ability to perform procedures to reduce excessive levels of radiation and guard against personnel Control exposure JPM: Determine Radiological Conditions for Personnel Exposure A.4 2.4.41 (4.1) Knowledge of the emergency action level Emergency thresholds and classifications Preparedness JPM: Classify an EPP Event (1350-004-03-023)

BVPS 1 LOT5 SRO Admin Rev. 3 NUREG-1021, Rev. 8 ($1)

ES-301 Administrative Topics Outline Form ES-301-1 (R8, $1)

Facility: FENOC BVPS Unit 1 Date of Examination: 9/30/2002 Examination Level (circle one): RO Operating Test Number: 2002-01 Administrative Describe method of evaluation:

Topic/Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A. 1 Conduct of 2.1.3 (3.0) Knowledge of Shift Turnover Practices Operations JPM: Shift Relief and Turnover (0481-006-03-013) 2.1.25 (2.8) Ability to obtain and interpret station reference Conduct of materials such as graphs, monographs, and Operations tables which contain performance data JPM: Perform SDM Calculation (0011-006-01-013)

A.2 Equipment 2.2.13 (3.6) Knowledge of tagging and clearance procedures Control JPM: Review a Clearance Tagout (0481-020-03-013)

A.3 2.3.10 (2.9) Ability to perform procedures to reduce excessive Radiation levels of radiation and guard against personnel Control exposure JPM: Determine Radiological Conditions for Personnel Exposure A.4 2.4.39 (3.3) Knowledge of RO's responsibilities in emergency plan implementation Emergency QUESTION: For a Site Area Emergency, state the time requirement mepargednc for initial notification and methods by which the official Preparedness notifications can be made.

2.4.29 (2.6) Knowledge of the Emergency Plan QUESTION: Describe the location of the OSC and the Alternate OSC and when each must be activated.

BVPS 1 LOT5 RO Admin Rev. 2 NUREG-1021, Rev. 8 ($1)

ES-301 Control Room Systems and Facility Walk-Through Test Outline Form-301-2 Facility: FENOC BVPS Unit 1 Date of Examination: 9/30/2002 Exam Level: RO / SRO(I) Operating Test No.: 2002-01 B1.I Control Room Systems System JPM Description Type Safety Code* Function S1i 003 Start Reactor Coolant Pump D, A, S, L 4 RCP (Repeat)

S2 004 Emergency Borate the Reactor Coolant System D, A, S, E 1 CVCS (Repeat)

S3 006 Transfer to Hotleg Recirculation N, S, E _

2 ECCS S4 103 Calculate and Restore Containment Air Partial M, S 5 Containment Pressure S5 062 Transfer Bus 1 AE from Emergency to Normal Feed D, S 6 AC Distribution S6 078 Start the Containment Instrument Air Compressor D, S 8 Instrument Air S7 010 Place Overpressure Protection System in service D, S, L 3 PPCS (PORV Stroke test)

B.2 Facility Walk-Through P1 061 Startup the Dedicated Auxiliary Feedwater Pump M, A, E 4 AFW [FW-P-4]

P2 033 Respond to a SFP Low Level Alarm N, A, R 8 SFP P3 001/012 Locally Trip the Reactor D, E, A 1 Rod Control/RPS

  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)Itemate path, (C)ontrol Room, (S)imulator, (L)ow-Power, (R)CA, (E)OP/AB O~A~~

Koss - C(\~ ?c~t~~TeM5 c.k~ o~eL ujMbe. c-ovýe.c*6c -2 T'ime. Yc oC(-1 R eV..U QcerTn ho.

BVPS-1 JPM Outline

Appendix D Scenario Outline Form ES-D-1 Facility: FENOC - BVPS Unit 1 Scenario No.: 1 Op Test No.: 2002 NRC 01 Examiners: Candidates: CRS RO PO Objectives: In accordance with plant procedures:

Initial Conditions: Power 78%.

Turnover: FW-P-3A OOS. Reduce power to remove FW-P-1 B from service. Severe weather expected.

Critical Tasks: E-O.F, Establish AFW Flow; ECA-3.1B, Cooldown RCS Event Malf. No. Event No. Type* Event Description R (RO) Normal Power Reduction.

N (US)

N (PO) 2 FWM01B C (PO) FW-P-1 B trips at approximately 73% power.

C(RO)

C (US) 3 PRS06A I (RO) Pressurizer Level Channel (459) fails low.

I (US) 4 MSS-146 I (PO) SG 'B' controlling steam flow transmitter fails low.

l(US) 5 FWM07B M (All) FCV-FW-488 fails shut ('B' SG), Rx Trip.

MSS07 Condenser steam dumps fails to operate.

MSS12B SG 'B' Atmospheric Dump opens on Rx Trip and fails open.

INH20 C (PO) FW-P-2 and FW-P-3B fail to auto start (Manual start available).

INH21 C (US) 6 RCS03B M (All) SG 'B' Tube Rupture 500 GPM.

('B' SG Faulted/Ruptured, ECA-3.1).

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor BVPS-1 NRC SSG #1.doc

Appendix D Scenario Outline Form ES-D-1 Facility: FENOC - BVPS Unit 1 Scenario No.: 2 Op Test No.: 2002-NRC-01 Examiners: Candidates: CRS RO PO Obiectives: In accordance with plant procedures:

Initial Conditions: 85% power.

Turnover: FW-P-3A OOS. Return power to 100%.

Critical Tasks: E-O.Q, Turbine Trip E-0.D, Manual Safety Injection E-lC, Trip all RCPs Event Malf. Event No. No. Type* Event Description 1N (US) Normal power ascension.

N (PO)

R (RO) 2 NIS03D I (RO) PRNI N-44 Summing Amplifier fails high, control rods step in.

I (US) 3 IORX06A I (RO) PCV-CH-145, Letdown Backpressure Regulator fails shut.

087P I (US) 4 CCW03A C (PO) CC-P-1A and CC-P-1 B trip (manually start standby pump).

CCW03B C (US)

CCW08B C (All) CCR Supply leak to ' B' RCP (10 minute ramp to 500 GPM).

5 RCS09B M (All) RCP 'B' locked rotor, automatic Rx trip.

INH48 C (PO) Main turbine fails to automatically trip (manual trip available).

C (US)

RCS02B M (All) LOCA Loop 'B'- 900 GPM.

SIS1 OA C (RO) Failure of automatic safety injection Train 'A'and Train 'B'.

SIS10B C (US)

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor BVPS-1 NRC SSG #2.doc

Appendix D Scenario Outline Form ES-D-1 Facility: FENOC - BVPS Unit 1 Scenario No.: 3 Op Test No.: 2002-NRC-01 Examiners: Candidates: CRS RO PO Objectives: In accordance with plant procedures:

Initial Conditions: 97% power.

Turnover: FW-P-3A OOS. Lower reactor power to remove FW-P-1 B from service.

Severe weather expected.

Critical Tasks: E-O.C, energize at least one AC Emergency Bus FR-H.1.A, Establish feedwater flow before RCS feed and bleed is required Event Malf. No. Event No. Type* Event Description 1 R (RO) Normal Power Reduction N (PO)

N (US) 2 I (RO) Inadvertent Boration due to Integrator failure I (US) 3 EPS03B C (US) Loss of System Station Service Transformer 1B 4 PRS07 I (RO) TAVE reference to pressurizer level controller fails low I (US) 5 FWM14B I (PO) FT-FW-477 fails low (90 second ramp), 'A'FWRV opens I (US) 6 CND01A M(All) CND-P-1A trips CND03 Condensate header rupture EPS11B DIG No. 2 trips 30 seconds after output breaker closes FWM11C C (PO) FW-P-2 trips, can be recovered with Operator action C (US)

EPS04E C (PO) 4160V bus 1AE trips INH C (US) D/G No. 1 output breaker fails to automatically close

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor BVPS-1 NRC SSG #3.doc

Appendix D Scenario Outline Form ES-D-1 Facility: FENOC - BVPS Unit 1 Scenario No.: 4 Op Test No.: 2002-NRC-01 Examiners: Candidates: CRS RO PO Obiectives: In accordance with plant procedures:

Initial Conditions: 48% power.

Turnover: FW-P-3A OOS. Raise power to 100%. Severe weather expected.

Critical Tasks: FR-S-I.C, Insert RCCAs E-O.1, Manually Start HHSI Pump E-1.C, Trip all RCPs Event Malf. No. Event No. Type* Event Description 1 N (US) Normal power ascension.

N (PO)

R (RO) 2 FWM-15A I (PO) Steam Generator Level controller (AM-FW-478) fails high.

I (US) 3 TUR16 I (PO) Turbine EHC Impulse Pressure transmitter (PT-MS-216) fails high.

I (RO) (Load rejection)

I (US) 4 PRS12 I (RO) Pressurizer Master Controller fails high, PORV 455C opens.

I (US)

PRS03A C (RO) PORV 455C leaks after lifting (Block Valve can be shut).

C (US) 5 PRS05 M (All) Pressurizer vapor space leak. (400 GPM 300 second ramp.)

CRF12A ATWS CRF12B SIS05A C (RO) Running High Head Sl pump (CH-P-1A) trips on SI.

INH40 C (US) CH-P-1 B fails to auto start (manual start available).

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor BVPS-1 NRC SSG #4.doc

Appendix D Scenario Outline Form ES-D-1 Facility: FENOC - BVPS Unit 1 Scenario No.: 5 Op Test No.: 2002-01 Examiners: Candidates: CRS RO PO Objectives: In accordance with plant procedures:

Initial Conditions: 7% power.

Turnover: FW-P-3A OOS. Severe weather is expected. Shift in-service CCT Pumps.

Critical Tasks: E-O.A, Trip Reactor E-O.E, Manually start Quench Spray Pump E-O.O, Close Containment Isolation Valves Event Malf. No. Event No. Type* Event Description 1 N (PO) Shift in-service CCT Pumps.

N (US) 2 R (RO) The Crew continues plant startup.

N (US) 3 NIS07A I (RO) N-35 instrument power fuse blows.

I (US) 4 PRS013 I (RO) Pressurizer Level Controller fails low.

I(US) 5 MSS11 I (PO) PT-MS-464 fails high (45 sec ramp), Steam Dumps open.

I (US) (Manual control available) 6 FWM-8A C (PO) Feedwater Regulating Valve Bypass Valve fails open.

C (ANSS) 7 MSS-1C M (All) 'C' S/G faulted inside containment.

CRF-12A C (RO) Automatic Rx trip failure.

C (US)

SIS-2A QS-P-1A trips 15 seconds after start.

INH43 C (RO) QS-P-1 B fails to start automatically (manual start available).

C (US)

INH50 C (RO) Auto CIB failure (manual available).

c (US)

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor BVPS-1 NRC SSG #5.doc
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