ML051240190

Final - Outlines (Folder 3)

ML051240190
Person / Time
Site:	Beaver Valley
Issue date:	01/15/2005
From:	Hynes C FirstEnergy Nuclear Operating Co
To:	Conte R NRC/RGN-I/DRS/OSB
Conte R
References
Download: ML051240190 (12)

Text

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

BVPS-1 Date of Exam:

2/28/2005 Tier 1 Group

1.

Emergency Totals Abnormal Plant Evolutions Totals

2.

Plant Systems I

I 2

3 2

3 2

2 1

2 topics from every applicable WA category are sampled within each tier of the RO

.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals' in not be less than two).

3. Generic Knowledge and Abilities Categories Note

1.

Ensure that at least two and SRO-only outlines {

each WA category shall

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 fl 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.

Systemdevolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding elimination of inappropriate WA statements.

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

Absent a plant specific priority, only those KAs having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system.

On the following pages, enter the WA numbers, a brief description of each topic, the topics' importance ratings (IR) 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. Use duplicate pages for RO and SRO-only exams.

For Tier 3, select topics from Section 2 of the WA Catalog, and enter the WA numbers, descriptions, IRs, and point totals (#) on Form ES401-3. Limit SRO selections to WAS that are linked to 10CFR55.43

3.

4.

5.

6.

7.'

a.

9.

NUREG-1021 Revision 9 1

F O I ~

ES-401-2 BVPS-1 ES-401 025 I Loss of RHR System I 4 027 / Prsssurizer Pressure Control System Malfunction I 3

029 I A W S I 1 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 X

AA1.08 X

AA2.02 X

EK3.11 WA Topic@)

I Imp. I Q#

Abilny to determine and interpret the following as they apply to the Loss of Residual Heat Removal System Leakage of reactor coolant from RHR into closed cooling Abiltty to determine or interpret the following as they apply to a ATWS Reactor nuclear instrumentation Equipment Control Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.

Equipment Control Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.

t i

Emergency Procedures I Plan Knowledge of annunciators alarms and indications, and use of the response instructions.

Abil~ty to determine and interpret the following as they apply to the (Loss of Emergency Coolant Recirculation)

Facillty conditions and selection of appropriate procedures during abnormal and emergency operations.

Ability to operate and monitor the following as they apply to a reactor trip: CVCS Ability to determine and Interpret the following as they apply to the Pressurizer Vapor Space Accldent: The off& of an open PORV on code safety, based on observatlon of plant parameters Knowledge of the operational lmplicatlons of the following concepts as they apply to the Reactor Coolant Pump Malfunctions (Lo85 of RC Fl0w):Natural Circulation in a nuclear power plant Ablllty to determine and interpret the following as they apply to the Loss of Reactor Coolant Makeup' How long PZR level can be maintained within limits 3.4 4.2 3.2 3.4 4.4 2.9 Ability to operate and I or monitor the followlng as they apply to the Lobe of Residual Heat Removal System:

RHR cooler Inlet and outlet temperature indicators Abllity to determine and Interpret the following as they rrpply to the Pressurizer Pressure Control Malfunctions:

N m a l values for RCS pressure

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2.9 3.8

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44

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Knowledge of the reasons for the followlng responses as the amlY to the ATWS: Initlatina emeroencv boration NUREG-I021 Revision 9 2

ES-401 BVPS-1 Form ES-401-2 1 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 I

E/APE # / Name Safety Function Number 1 WA Topids)

Ability to operate and monitor the following as they apply to a SGTR: SIG atmospheric relief valve and secondary PORV controllers and Indicators Ability to determine and interpret the following as they apply to the Steam Line Rupture: When ESFAS systems mav be secured 038 I Steam Gen. Tube Rupture 13 EA1.16 AA2.05 040 I Steam Line Rupture - Excessive Heat Transfer I 4 054 I Loss of Maln Feedwater I 4 Ability to operate and I or monitor the following a8 they apply to the Loso of Main Feedwater (MFW): HPI, under total feedwater 1088 condklons 4.4 1 48 AA1.04

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Knowledge of thsoperational Imjlcations of the following concepts as they apply to the Station Blackout : Natural circulatlon cooling Abillty to operate and I or monitor the following as they apply to the Loss of Offsite Power: Auxiilarylemergency feedwater pump (motor driven) 055 I Station Blackout I 6 056 I Loss of Off-site Power 16 057 I Loss of Vital AC Inst. Bus I 6 EKI.02 AAl.10 Ability to determine and interpret the following as they apply to the Loss of Mal AC Instrument Bus: ESF system panel alarm annunciators and channel status indkators Ability to operate and I or monitor the following as they apply to the Loss of DC Power: Cross-tie of the affected dc bus with the alternate supply X -

AA2.04 AA1.Ol 058 I Loss of DC Power I 6 1 Emergency ProcedureslPlan: Ability to recognlze abnormal indications for system operating parameters which are entry level conditions for abnormal and emergency operating procedures.

Ability to determine and interpret the following as they apply to the (LOCA Outside Containment) Facility conditions and selection of appropriate procedures durlng abnormal and emergency operations.

Knowledge of the reasons for the following responses as they apply to the (Loss of Secondary Heat Sink) Normal, abnormal and emergency operating procedures associated with (Loss of Secondary Heat Sink).

Knowledge of the operational impilcations of the following concepts as they apply to the (Loes of Emergency Coolant Recirculation) Annunciators and conditions indicating signals, and remedial actions associated with the (Loss of Emeraencv Coolant Recirculation).

062 I Loss of Nuclear Svc. Water I 4 2.4.4 EA2.1 EO4 I LOCA Outside Contalnment I3 E05 I Inadequate Heat Transfer - Loss of Secondary Heat Slnk I 4 EK3.2 I

EK1.3 E l 1 I Loss of Emergency Coolant Recirc. I 4 Group Point Total: I iat6 WA Category Point Totals:

NUREG-I021 Revision 9 3

Form ES-401-2 1 BVPS-1 ES-401 4.3 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 a5 UAPE # / Name Safety Function G I K1 I K2 I K3 I AI I A2 I Number I WA Topicb)

I I

Emergency Procedures I Plan Knowledge of which events related to system operationdstatus should be reported to outside agencies.

3.6 I 82 037 I Steam Generator Tube Leak I 3 2.4.30 tt Ability to determine and interpret the following as they apply to the (Reactor Trip or Safety Injection Rediagnosis)

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

Ability to determine and interpret the following as they apply to the Natural Circulation Operations: Adherence to appropriate procedures and operation withln the limitations in the facilitv's license and amendments.

EO1 & E02 I Rediagnosis and SI Termination I 3 E09 I Natural Circulation Operations I 4

E06 I Degraded Core Cooling 14 Emergency Procedures I Plan Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

2.4.4 AMllty to operate and I or monitor the following as they swltc h Knowledge of the interrelatlons between the Dropped Control Rod and the following: Control rod drive power ruDolies and looic circuits 001 I Continuous Rod Withdrawal I 1 003 I Dropped Control Rod I 1

• Knowledge of the operational implications of the following 1 1; I concepts as they apply to Steam Generator Tube Leak:

Leak rate VI.

pressure drop Ability to determine and Interpret the followlng as they apply to tho Area Radiation Monitoring (ARM) System Alarms: ARM Panel dirDlavs 037 I Steam Generator Tube Leak 13 081 I ARM System Alarms I 7 EO1 8 E02 I Rediagnosis and SI Termlnatlon 1 3 Emergency Procedures I Plan Knowledge of annunciators Instructlons.

I 2.4.31 I alarms and lndlcatlons, and use of the response 3.3 I 61

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Knowledge of the reasons for the following responses as they apply to the (Saturated Core Coollng) Manipulation of controls required to obtain desired Operating results during abnormal and emergency situations.

Knowledge of the reasons for the followlng responses as they apply to the (Pressurized Thermal Shock) operating results during abnormal and emergency sltuations.

EK3,3 3,8 62 EK3.3 Manlpulatlon of controls required to obtain desired 3.7 03 E07 I Inad. Core Cooling I 4 E08 I RCS Overcooling - PTS 14 NUREG-I021 Revision 9 4

ES-401 BVPS-1 Form ES-401-2 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 I

E/APE#/ Name Safety Function I G I K1 I K2 I K3 I A I E13 I Steam Generator Over-pressure 14 X

I 068 I Control Room Evacuation I 8 1 x 1 I I I WA Category Point Total:

2 / 2 1 2

2 1

A2 112 -

Number EK2.1 2.1.30 WA Topic@)

Knowledge of the lnterrelatlonr between the (Steam Generator Overpressure) and the following: Components, and functions of control and safety systems, lncludlng Instrumentation, algnals, Interlocks, fallure modes, and automatic and manual features.

Conduct of Operatlons: Ablllty to locate and operate components, including local controls.

GrouD Point TOM: I NUREG-1021 Revision 9

FORTI ES-401-2 BVPS-1 ES-401 System #/Name 003 Reactor Coolant Pump Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 2 Group 1 G

K1 K2 K3 K4 X

A3 A4 X

X X

010 Pressurizer Pressure Control I x I I

I I

01 0 Pressurizer Pressure Control 039 Main and Reheat Steam 078 lmtrument Air 103 Containment X

X 103 Containment 1 x 1 I I

I Equipment Control Knowledge of limiting condlions for operations and safety limits.

Ability to (a) predict the impacts of the following mal-functions or operations on the MRSS; and (b) based on predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Increasing steam demand, its relationship to increases in reactor power Ability to (a) predict the impacts of the following 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 Conduct of Operations: Ability to apply Technical Specifcations for a system Knowledge of the operational lmpllcatlons of the following concepts as they apply to the RCPS: Effects of RCP coastdown on RCS parameters Knowledge of the effect that a loes or malfunction of the RCPS will have on the following: S/G 4.,

3.6 2.9 4.0 2.8 3,5 003 Reactor Coolant Pump 003 Reactor Coolant Pump 004 Chemical and Volume Control 005 Resldual Heat Removal X

005 Residual Heat Removal X

I ImD.

WA ToDics Q#

86 87 88 89 90 1

2 3

4 5

6 7

Number 2.1.33 -

Conduct of Operations: Ability to recognize indications for sFtem operating parameters which are entry-level 1 4.0 conditions for technical sDecifications.

2.2.22 A2.05 A2.01 2.1.1 2

039 Main and Reheat Steam K5.02 K3.02 A4.12 3.8 -

3.1 -

3.7 Ability to manually operate and/or monitor in the control room: Boration/dilution batch control Ability to manually operate and/or monitor In the control room: Controls and indication for closed cooling water Pumps Knowledge of the effect that a loss or malfunction of the RHRS will have on the followlna: ECCS A4.04 K3.05 Ability to (a) predict the Impacts of the following 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 I operations: Condlions requiring actuation of ECCS I

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I I

006 Emergency Core Cooling A2.12 4.0 I

I I

I I

007 Pressurizer Rellef/Quench Tank A4.01 I 2.7

~ Ability to manually operate and/or monitor in the control

~ room: PRT spray supply vaive NUREG-1021 Revision 9 6

Form ES-401-2 BVPS-1 ES-401 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 2 Group 1 I Imp.

K/A Topics Ability to (a) predict the impacts of the following malfunctions or operation8 on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: High/low surge tank level Knowledge of the operational implications of the following concepts as the apply to the PZR PCS:

Determination of condition of fluid in PZR, using steam tables Knowledge d the effect of a 1088 or malfunction of the following will have on the RPS: Sensors and detectors Ability to manually operate andlor monitor in the control room: ESFAS-initiated equipment which faik to actuate 2,7 4.5

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Knowledge of CCS design feature@) and/or interlock(s) which provide for the following: Cooling of containment penetrations Knowledge of the physical connections andlor cause effect relationships m e

n the CCS and the following systems: SEC/remote monitoring systems Conduct of Operations: Ability to perform specific modes of plant operation.

Knowledge of the effect that a loss or maKunctin of the MRSS will have on the following: RCS Knowledge of the physical connections and/or cause effect relationships between the MRSS and the following systems: MFW Ability to monitor automatic operation of the M W,

includlng: Programmed levels of the S/G system and integrated plant procedures during all 3.9 3.6 2.7 2.9 Knowledge of MFW design feature($) and/or interlock(s) which provide for the following: Automatic trips for MFW Knowledge of the physical connections and/or cause effect relationships between the AFW and the following eystems: Emergency water source

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I 4.0 Abiltty to monitor automatic operation of the AFW, including: RCS cooldown during A W operations Knowledge of bus power supplies to the following: Major system loads 3.3 10 I 1 -

12 -

13 14 15 16 -

17 18 -

19 20 21 NUREG-I 021 Revision 9 7

Form ES-401-2 BVPS-1 ES-401 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 2 Group 1 System #/Name K4.02 :

A2.02 +

A3.01 KIA Topics I Imp.

Knowledge of the effect that a loss or maifunctlon of the dc electrical system will have on the followlng: ED/G Knowledge of ED/G system design feature(8) and/or inter-lock(s) which provide for the following: Trips for ED/G while operating (normal or emergency)

Ablllty to monitor automatic operatlon of the EDlG system, including: Operatlon of the governor control of frequency and voltage control in parallel operatlon Ablllty to (a) predict the Impacts of the following malfunctlons or operations on the PRM system; and (b) based on those predictions, use procedures to correct, control, or mitlgate the consequences of those malfunctions or operations: Detector failure Knowledge of bus power supplies to the following:

Service water 2.8 -

2.7 -

2.7 Knowledge of the effect that a 1088 or malfunction of the IAS will have on the following: Systems having pneumatic valves and controls Abillty to monitor automatic operation of the containment system, including: Containment isolation

'oint Total:

I Q#

22 -

23 24 -

25 26 27 28 2816 NUREG-1021 Revision 9 a

FORTI ES-401-2 BVPS-1 ES-401 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 2 Group 2 I

I I System #/Name I G I K1 I K2 I K3 I K4 1 K5 1 K6 I A I I A2 I A3 I A4 1 Number I KIA Topics I Imp. I Q# I Conduct of Operations: Abiliy to explain and apply all system limits and precautions.

2.1 32 Ability to (a) predict the impacts of the following malfunctions or operation on the SGlS system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Faulted or ruptured SG X

A2.01 Emergency Procedures I Plan Ability to verify system alarm setpoints and operate controls idenMied in the alarm response manual.

Knowledge of bus power supplies to the following: One-line diagram of power supply to MIG sets.

2.4.50 K2.01

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Knowledge of RCS design feature@) andlor interlock(s) which provide for the following: Detection of RCS leakage Knowledge of the effect that a loss or malfunction of the PZR LCS will have on the following: CVCS 3.8 I 30 K4.05 K3.01 i"

2.8 33 Ability to predict andlor monitor changes in parameter (to prevent exceeding design limits) associated with Operating the SDS controls including: Tavg; verification above lo-lo setpolnt Al.01 X

X X

2.1.27 Conduct of Operations: Knowledge of system purpose and or function.

Knowledge of the effect of a loss or malfunction on the following will have on the Fuel Handling System :

Radiation monitoring systems Knowledge of the physkal connections and/or cause-effect relatlonshlps between the MTlG system and the following systems: RPS K6.02 K1.18 X -

Ability to monitor automatic operation of the Liquid Radwaste System including: Automatic isolation Ability to predict and/or monitor changes In parameten(t0 prevent exceeding deslgn Ilmits) associated with operating the Waste Gas Disposal System controls including: Ventllatlon system A3.02 Al.06 071 Waste Gas Dlsposal NUREG-1021 Revision 9 9

ES-401 075 Circulating Water BVPS-1 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 2 Group 2 Knowledge of the physical connections and/or cause-effect relatlonships between the circulating water system and the followlng systems: Liquld radwaste discharge 2.9 38 Kl,02 X

Form ES-401 System #/Name I G I K1 I K2 I K3 I K4 [ K5 I K6 I A1 I A2 I A3 I A4 [ Number I KIA Topics I Imp. I Q#

1 1

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1 I

1 I

WA Category Point Totals:

I 112 I 2 I I I I I 1 I 0 I 1 I 2 IO/1 I I I 0 I GrwpPointTotal: I I 1013 NUREG-1021 Revision 9 10

BVPS-I I

Dateof Exam:

I 2/28/2005 RO I SRO-Only WA #

Topic 2.1.20 Abilty to execute procedure steps.

IR 3.7 2.8 Knowledge of system status criteria which require the notification of plant personnel.

Knowledge of conduct of operations requirements.

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

2.1.14

2.

2.1.25 Subtotal 4-2 96 -

Knowledge of new and spent fuel movement 2.2.28 2.2.22 3.5 4.1 68 69 70 3

procedures.

Knowledge of limiting conditions for operations and safetv limits 97 2.2.12 Knowledge of surveillance procedures.

Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.

Knowledge of RO duties in the control room during fuel handling such as alarms from fuel handling area, communication with fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation.

3.0 2.5 2.2.25 2.2.30 3.5 2

Subtotal 98 Knowledge of the process for performing a Subtotal 2.9 2.7 1

Knowledge of local auxiliary operator tasks 2.4.35 I during emergency operations including system 99 -

100 I geography and system implications I Abiltty to recognize abnormal indications for system operahg parameters which are entry-level conditions for emergency and abnormal operating procedures.

Knowledge of the emergency plan.

2'4'4 2.4.29 2.6 I

Knowledge of operational implications of EOP 2'4'20 I warninas. cautions. and notes.

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

2.4'48 Subtotal 3.5 Tier 3 Point Total NUREG-1021 Revision 9 11

1 I 1 112 Reason for Rejection ri I Randomly Group Selected WA I

I 057AA2 09 OOlAAl.04 The subject WA isnt relevant at the subject facili.

The subject KIA isnt relevant at the subject facility.

112 2 1 1 212 21 1 21 1 3

111 003AK2.03 01 2K6.11 0332.4.6 059K4.14 061K1.10 G2.2.9 027 G2.4.49 The subject WA isnt relevant at the subject facility.

The subject WA isnt relevant at the subject facility.

The subject WA isnt relevant at the subject facility.

The subjed WAS importance rating isnt equal to or greater than 2.5 for the license level of the proposed examination, and there isnt a site-specific priority that justifies keeping the WA if its importance rating is below 2.5.

The subject WA isnt relevant at the subject facility.

The subject WAS importance rating isnt equal to or greater than 2.5 for the license level of the proposed examination, and there isnt a site-specific priority that justifies keeping the WA if its importance rating is below 2.5.

The subject K/A isnt relevant at the subject facility.

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062 G2 1 posslMe to prepare a psychometrically sound question related to the subject WA 1 1 2 1 / 1 067 AA2.11 062 G2.1.23 It isnt possible to prepare a psychometrically sound question related to the subject WA.

Random selection of replacement KA was a duplicate topic 3

3 G2.4.29 G2.2.17 Duplkate of KA already selected KA deleted because 3 topics selected for Generic Section 2. Replaced with 2.4.4 I

1 I 2 I E16 G2.4.4 I Procedure no longer exists at facility 111 111 112

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It isnt possible to prepare a psych&&ically sound question related to the subject WA Plant effects are O1 AK1 062 AA2 06 061 AA2 05 mmimal. not operationally valid Double Jeopardy with Question 8.

Double Jeopardy wnh Question 90 Also, signifkant number of radiation monitoring questions on exam 112 112 21 1 037 AK1.01 E16 G2.1.30 OO6 A21 Topic not operationally valid. This event does not require use of steam tables.

Procedure no longer exists at facility It isnt possible to prepare a psychometrically sound question relevant to this WA. No procedure exists for this event, and the closest possible topic would duplicate question 54 I

2 I 1 I 103 A2.04 I It isnt possible to write a psychometrically sound SRO question to this KA 21 1 212 NUREG-1021 Revision 9 062 A2.15 045 A2.17 No procedure guidance for KA statement, and question would test same knowledge as Question 24 WA identical to event performed in dynamic simulator 12 212 1 I 1 028 Al.01 062 AA2.06 System removed (retired in place) at facility No relation to facility procedure requirements