ML090790241

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Final Outlines (Folder 3)
ML090790241
Person / Time
Site: Vermont Yankee Entergy icon.png
Issue date: 02/05/2009
From:
Entergy Nuclear Operations
To: Todd Fish
Operations Branch I
Hansell S
Shared Package
ML082600332 List:
References
TAC U01743
Download: ML090790241 (23)
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Text

ES-401 Written Examination Outline Form ES-401-1

3. Generic Knowledge & Abilities Note: 1. Ensure that at least two topics from every applicable WA 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 WA category shall not be less than two).
2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to section D.1.b of ES-401, for guidance regarding elimination of inappropriate WA 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 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.
6. Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.

7.* 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. Refer to Section D.1.b of ES-401 for the applicable WA's

8. 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. If fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the WA Catalog, and enter the WA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to WAS that are linked to 10CFR55.43

2 Form ES-401-1 Vermont Yankee Written Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 AA2.02 - Ability to deterrnine and/or interpret the following as they apply to 295019 Pa~tialor Total Loss of PARTIAL OR COMPLETE LOSS OF X 3.7 76 Inst. Air i 8 INS'TRUMENT AIR : Status of safety-related instrument air system loads (see AK2.1 - AK2.19)

AA2.02 - Ability to determine and/or 295005 Main Turbine Generator interpret the following as they apply to X 2.7 77 Trip i3 MAIN TURBINE GENERATOR TRIP :

Turbine vibration AA2.03 - Ability to determine andior 295004 Partial or Total Loss of interpret the following as they apply to X 2,9 78 DC Pwr / 6 PARTIAL OR COMPLETE LOSS OF D.C. POWER : Battery voltage 2.1.19 - Conduct of Operatioris: Ability 295006 SCRAM / 1 X to use plant computers to evaluate 3.8 79 system or component status.

295001 Partial or Complete 2.2.40 - Equipment Corltrol: Ability to Loss of Forceci Core Flow X apply technical specifications for a 4.7 80 Circulation 1 & 4 system.

2.4.45 - Ability to prioritize and interpret 295025 High Reactor Pressure i X the significance of each annunciator or 4.3 81 3

alarm.

EA2.02 - Ability to determine aridlor 295028 High Drywell interpret tlie tollowing as they apply to X 3,9 82 Temperature !5 HIGH DRYWELL TEMPERATURE :

Reactor pressure AKl .O1 - Knowledge of the operational implications of the following concepts as 295005 Main Turbine X they apply to MAIN TURBINE 4.0 39 Generator Trip / 3 GENERATOR TRIP : Pressure effects on reactor power EKl.O1 - Knowledge of the operational implications of the following concepts as 295028 High Drywell X they apply to HIGH DRYWELL 3.5 40 TemperatureI5 TEMPERATURE : Reactor water level measurement EK1.O1 - Knowledge of the operational implications of the following concepts as 295030 Low Suppression Pool they apply to LOW SUPPRESSION 3.8 41 Water Level 15 POOL WATER LEVEL: Steam condensation EK2.06 - Knowledge of the interrelations between SUPPRESSION 295026 Suppression Pool High X POOL HIGH WATER TEMPERATURE 3.5 42 Water Temp. / 5 and the following: Suppression pool level AK2.04 - Knowledge of the interrelations between PARTIAL OR 295019 Partial or Total Loss of X COMPLETE LOSS OF INSTRUMENT 2.8 43 Inst. Air 1 8 AIR and the following: Reactor water cleanup AK2.04 - Knowledge of the interrelations between PLANT FIRE 600000 Plant Fire On-site 18 X 2.5 44 ON SITE and the following: Breakers, relays, and disconnects AK3.03 - Knowledge of the reasons for the following responses as they apply to 295023 Refueling Accidents X 3.3 45 REFUELING ACCIDENTS: Ventilation isolation.

2 Form ES-401-1 Vermont Yankee Written Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 AK3.04 - Knowledge of the reasons for the following responses as they apply to 295018 Partial or Total Loss of X PARTIAL OR COMPLETE LOSS OF 3.3 46 CCW / 8 COMPONENT COOLING WATER :

Starting standby pump AK3.03 - Knowledge of the reasons for 295016 Control Room the following responses as they apply to X 3,5 47 Abandonment / 7 CONTROL ROOM ABANDONMENT :

Disabling control room controls AA1.05 - Ability to operate and/or monitor the following as they apply to 700000 Generator Voltage and X GENERATOR VOLTAGE AND 3.9 48 Electric Grid Disturbances ELECTRIC GRID DISTURBANCES:

Engineered safety features.

AA1.O1 - Ability to operate and/or monitor the following as they apply to 295004 Partial or Total Loss of X PARTIAL OR COMPLETE LOSS OF 3.3 49 DC Pwr / 6 D.C. POWER : D.C. electrical

distribution systems AA1.06 - Ability to operate and/or 295006 SCRAM 11 X monitor the following as they apply to 3.5 50 SCRAM : CRD hydraulic system AA2.05 - Ability to determine and/or 295021 Loss of Shutdown interpret the following as they apply to X 3.4 51 Cooling / 4 LOSS OF SHUTDOWN COOLING :

Reactor vessel metal temperature EA2.04 - Ability to determine and/or 295037 SCRAM Conditions interpret the following as they apply to Present and Reactor Power SCRAM CONDITION PRESENT AND X 4.0 52 Above APRM Downscale or REACTOR POWER ABOVE APRM Unknown / 1 DOWNSCALE OR UNKNOWN :

Suppression pool temperature AA2.06 - Ability to determine and/or 295001 Partial or Complete interpret the following as they apply to Loss of Forced Core Flow X PARTIAL OR COMPLETE LOSS OF 3.2 53 Circulation / 1 & 4 FORCED CORE FLOW CIRCULATION

Nuclear boiler instrumentation 2.1.30 - Conduct of Operations: Ability 295024 High Drywell Pressure /

X to locate and operate components, 4.4 54 5

including local controls. I 2.1.23 - Conduct of Operations: Ability 295038 High Off-site Release to perform specific system and 4.3 55 Rate / 9 integrated plant procedures during all modes of plant operation.

2.4.46 - Emergency ProceduresIPlan:

295031 Reactor Low Water X Ability to verify that the alarms are 4.2 56 Level / 2 consistent with the plant conditions.

AK3.01 - Knowledge of the reasons for the following responses as they apply to 295003 Partial or Complete X PARTIAL OR COMPLETE LOSS OF 3.3 57 Loss of AC / 6 A.C. POWER : Manual and auto bus transfer 2.4.34 - Emergency Procedures / Plan:

Knowledge of RO tasks performed 295025 High Reactor Pressure X outside the main control room during an 4.2 58

/3 emergency and the resultant operational effects.

WA Category Totals: 3 3 4 3 314 4/3 Group Point Total: 2017

3 Form ES-401-1 Vermont Yankee Written Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 AA2.04 - Ability to determine andior 295002 Loss of Main interpret the following as they apply to X 2,9 83 Cor?der>serVac i 3 LOSS OF MAIN CONDENSER VACUUM : Offgas system flow 2.1.23 - Conduct of Operations: Ability to 295017 High Off-site Release perform specific system and integrated 4,4 84 Rate / 9 plant procedures during all nlodes of plant operation.

2.1.25 - Ability to interpret reference 295013 High Suppression Pool materials, s ~ ~ asc hgiaptis, curves. 4.2 85 X

Temperatirre!5 tables, etc.

AK1.03 - Knowledge of the operational 295010 High Drywell Pressure implications of the following concepts as 3,2 59 15 they apply to HIGH DRYWELL PRESSURE : Temperature increases -

EK2.02 - Knowledge of the interrelations 295029 High Suppression Pool between HlGH SUPPRESSION POOL X 3,4 60 Water Level 15 WATER LEVEL and the following: HPCI:

Plant-Specilic EK3.01 - Knowledge of the reasons for 295033 High Secondary the following responses as they apply to Containment Area Radiation X HIGH SECONDARY CONTAINMENT 3.3 61 Levels 19 AREA RADIATION LEVELS :

Emergency depressurization EA1.03 - Ability to operate and monitor the following as they apply to HlGH 500000 High CTMT Hydrogen X CONTAINMENT HYDROGEN 3.4 62 Conc. / 5 CONTROL: Containment atmosphere control system EA2.01 - Ability to determine andlor I 295032 High Secondary interpret the following as they apply to Containment Area Temperature x HIGH SECONDARY CONTAINMENT 3.8 63 15 AREA TEMPERATURE : Area temperature 2.1.28 - Conduct of Operations:

Knowledge of the purpose and function 295015 Incomplete SCRAM 11 4,1 64 of major system components and controls.

EA2.03 - Ability to determine andlor 295036 Secondary interpret the following as they apply to Containment High SumplArea X SECONDARY CONTAINMENT HIGH 3.4 65 Water Level / 5 SUMPIAREA WATER LEVEL : Cause of the high water level WA Category Totals: 1 1 1 1 211 112 Group Point Total: 713

4 Form ES-401-1 Vermont Yankee Written Written Examination Outline Plant Systems - Tier 2 Group 1 A2.14. - Abiiity to (a) predict the impacts of the following on the RHRILPCI: INJECTION MODE 203000 RHRILPCI: Injection (PLANT SPECIFIC) ; and (b)

Mode X based or) those predictions, use 3.9 86 procedures to correct. control, or mitigate the consequences of those abnormal conditions or operations: Initiating logic faiicire A2.01 - Ability to (a) predict the impacts of the following on the REACTOR WATER LEVEL CONTROL SYSTEM : and (bj 259002 Reactor Water Level based on ttiose predictions, use Control X 3.4 87 procedures to correct. control, or rnitigate the consequences of those abnormal conditions or operations: Loss of any number of rnain steam flow inputs 2.4.49 - Etnergency Procedures

!Plan: Ability to perforrn without 400000 Component Cooling reference to procedures those Water 4.4 88 actioris that require irnrnediate operatior] of system components and controls.

2.1.20 - Ability to interpret and 262002 UPS (AC!DC) 4.6 89 execute procedure steps.

A2.07 - Ability to (a) predict the impacts ot the following on the STANDBY LIQUID CONTROL SYSTEM ; and (b) based on 211000 SLC X those predictions, use 3,2 90 procedures to correct. control, or rnitigate ttie consequences of those abnormal conditions or operations: Valve clostlres K1.03 - Knowledge of the physical connections and/or cause- effect relationships 211000 SLC X between STANDBY LIQUID 2.5 1 CONTROL SYSTEM and the following: Plant air systems:

Plant-Specific K1.03 - Knowledge of the physical connections and 1or 400000 Component Cooling cause-effect relationships Water 2.7 2 between CCWS and the following: Radiation monitoring systems 263000 DC Electrical K2.01 - Knowledge of electrical X power supplies to the following: 3.1 3 Distribution Major D.C. loads K2.02 - Knowledge of electrical 205000 Shutdown Cooling X power supplies to the following: 2.5 4 Motor operated valves

4 Form ES-401-1 Vermont Yankee Written Written Examination Outline Plant Systems - Tier 2 Group 1 K3.04 - Knowledge of the effect that a loss or malfunction of the 262001 AC Electrical A.C. ELECTRICAL X 3.1 5 Distribution DISTRIBUTION will have on following: Uninterruptible power supply K3.02 - Knowledge of the effect that a loss or malfunction of the EMERGENCY GENERATORS 264000 EDGs X 3,9 (DIESEUJET) will have on following: A.C. electrical distribution K4.01 - Knowledge of STANDBY GAS TREATMENT SYSTEM design feature(s) 7 261000 SGTS X 3.7 andlor interlocks which provide for the following: Automatic system initiation K4.05 - Knowledge of RHWLPCI: INJECTION MODE 203000 RHRILPCI: Injection (PLANT SPECIFIC) design X 3.2 8 Mode feature(s) andlor interlocks which provide for the following:

Prevention of water hammer K5.01 - Knowledge of the operational implications of the following concepts as they apply 212000 RPS X 2.7 to REACTOR PROTECTION SYSTEM : Fuel thermal time constant K5.01 - Knowledge of the operational implications of the following concepts as they apply 218000 ADS X 3,8 to AUTOMATIC DEPRESSURIZATION SYSTEM

ADS logic operation K6.01 - Knowledge of the effect that a loss or malfunction of the 209001 LPCS X following will have on the LOW 3.4 11 PRESSURE CORE SPRAY SYSTEM : A.C. power K6.04 - Knowledge of the effect that a loss or malfunction of the 239002 SRVs X following will have on the 3.0 12 RELI EFISAFETY VALVES :

D.C. power: Plant-Specific A1.O1 - Ability to predict andlor monitor changes in parameters 259002 Reactor Water associated with operating the X 3.8 13 Level Control REACTOR WATER LEVEL CONTROL SYSTEM controls including: Reactor water level A1.04 - Ability to predict andlor monitor changes in parameters associated with operating the 215004 Source Range X SOURCE RANGE MONITOR 3.5 14 Monitor (SRM) SYSTEM controls including: Control rod block status

I 4 Form ES-401-1 Vermont Yankee Written Written Examination Outline Plant Systems - Tier 2 Group 1 A2.04 - Ability to (a) predict the impacts of the following on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM ; and (b) based on those predictions, 215003 IRM X use procedures to correct, 3.7 15 control, or mitigate the consequences of those abnormal conditions or operations: Up scale or down scale trips A2.01 - Ability to (a) predict the impacts of the following on the UNINTERRUPTABLE POWER SUPPLY (A.C.1D.C.) ; and (b) 262002 UPS (ACIDC) X based on those predictions, use 2.6 16 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Under voltage A3.01 - Ability to monitor automatic operations of the PRIMARY CONTAINMENT 223002 PClSlNuclear ISOLATION X 3.4 17 Steam Supply Shutoff SYS'TEMINUCLEAR STEAM SUPPLY SHUT-OFF including:

System indicating lights and alarms ~- - - ~

A3.05 - Ability to monitor automatic operations of the AVERAGE POWER RANGE 215005 APRM / LPRM X MONITOWLOCAL POWER 3.3 18 RANGE MONITOR SYSTEM including: Flow converter/comparatoralarms A4.05 - Ability to manually 217000 RClC operate and/or monitor in the X 4,1 19 control room: Reactor water level A4.02 - Ability to manually operate and/or monitor in the 206000 HPCl X 4.0 20 control room: Flow controller:

BWR-2,3,4 2.4.4 - Emergency Procedures /

Plan: Ability to recognize abnormal indications for system 300000 Instrument Air X operating parameters which are 4.5 21 entry-level conditions for emergency and abnormal operating procedures.

2.4.30 - Emergency Procedures

/ Plan; Knowledge of events related to system operationI 262001 AC Electrical status that must be reported to 2,7 22 Distribution internal organizations or external agencies, such as the state, the NRC, or the transmission system operator.

4 Form ES-401-1 Vermont Yankee Written Written Examination Outline Plant Systems - Tier 2 Group 1 A2.14 - Ability to (a) predict the impacts of the following on the RHWLPCI: INJECTION MODE (PLANT SPECIFIC) ; and (b) 203000 RHWLPCI: Injection X based on those predictions, use 3.8 23 Mode procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Initiating logic failure K4.03 - Knowledge of AUTOMATIC DEPRESSURIZATION SYSTEM 24 218000 ADS X 3,8 design feature@)andlor interlocks which provide for the following: ADS logic control A3.02 - Ability to monitor automatic operations of the 215004 Source Range X SOURCE RANGE MONITOR 3.4 25 Monitor (SRM) SYSTEM including:

Annunciator and alarm signals K2.02 - Knowledge of electrical 215005 APRM ILPRM X power supplies to the following: 2.6 26 APRM channels KIA Category Totals: 2 3 2 3 2 2 2 3 3 3 2 S 2 Group Point Total: 2615

5 Form ES-401-1 Vermont Yankee Written Written Examination Outline Plant Systems - Tier 2 Group 2 A2.08 - Ability to (aj predict the impacts of the following on the FIRE PROTECTION SYSTEM :

and (b) based on those predictions, use procedures to 286000 Fire Protection X 3.3 91 correct, control. or mitigate the consequences ot those abnormal conditions or operations: failure to actuate when required 2.2.36 - Equipment Control:

Ability to analyze the effect of maintenance activities, such as 268000 Rad~vaste 4.2 92 degraded power sources. or) the status of limiting conditions for operations.

2.4.6 - Enlergency Procedures /

Plan: Knowledge symptom 204000 RWCU 4.7 93 based EOP mitigation strategies.

K1.04 - Knowledge of the physical connections andlor cause- effect relationships between ROD WORTH 201006 RWM X 3'1 27 MINIMIZER SYSTEM (RWM)

(PLANT SPECIFIC) and the following: Steam flowlreactor power: P-Spec(Not-BWR6)

K2.08 - Knowledge of electrical 223001 Primaty CTMT and power supplies to the following:

X 2.7 28 Aux. Containment cooling air handling units: Plant-Specific K3.04 - Knowledge of the effect that a loss or malfunction of the 256000 Reactor X REACTOR CONDENSATE 3.6 29 Condensate SYSTEM will have on following:

Reactor Feedwater System K4.02 - Knowledge of RHRILPCI:

TORUSISLIPPRESSION POOL 230000 RH WLPCI:

X SPRAY MODE design 3.1 30 ToruslPool Spray Mode feature@)and/or interlocks which provide for the following:

Redundancy K5.07 - Knowledge of the operational implications of the 290002 Reactor Vessel X following concepts as they apply 3.9 31 lnternals to REACTOR VESSEL INTERNALS: Safety Limits K6.01 - Knowledge of the effect that a loss or malfunction of the following will have on the 201002 RMCS X 2.5 32 REACTOR MANUAL CONTROL SYSTEM : Select matrix power A1.07 - Ability to predict and/or monitor changes in parameters 233000 Fuel Pool associated with operating the X 2,7 33 CoolinglCleanup FUEL POOL COOLING AND CLEAN-UP controls including:

System temperature

5 Form ES-401-1 Vermont Yankee Written Written Examination Outline Plant Systems - Tier 2 Group 2 A2.08 - Ability to (a) predict the impacts of the following on the RECIRCULATION SYSTEM ;

and (b) based on those predictions, use procedures to 202001 Recirculation X 3,1 34 correct, control, or mitigate the consequences of those abnormal conditions or operations: Recirculation flow mismatch: Plant-Specific A3.10 - Ability to monitor automatic operations of the 259001 Reactor Feedwater X 3.4 35 REACTOR FEEDWATER SYSTEM including: Pump trips A4.02 - Ability to manually 234000 Fuel Handling operate and/or monitor in the X 3,4 36 Equipment control room: Control rod drive system 2.2.37 - Equipment Control:

Ability to determine operability 290001 Secondary CTMT 3,6 37 and / or availability of safety related equipment.

2.4.47 - Emergency Procedures IPlan: Ability to diagnose and 272000 Radiation recognize trends in an accurate 4,2 38 Monitoring and timely manner utilizing the appropriate control room reference material.

WA Category Totals: 1 1 1 1 1 1 1 1 / 1 1 1 2 1 2 Group Point Total: 1213

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Vermont Yankee Written Date: 07117/08 RO SRO-Only Category WA # Topic IR Q# IR Q#

Knowledge of conservat~vedecisran mak~ng

.39 4.3 94 practices.

Ab~l~ty to Interpret reference mater~als,such 2'125 4.2 100 as graphs, curves, tables, etc, Ability to coordinate personnel activities

1. 2'1'8 3.4 66 outside the control room.

Conduct Knowledge of individual licensed operator of Operations responsibilities related to shift staffing, such 2.1.4 as medical requirements, "no-solo" operation, 3.3 67 maintenance of active license status, 10CFR55, etc.

Subtotal 2 2 Ab~lityto determ~neTechn~calSpecification 2'2'35 4.5 95 Mode of Operation.

Knowledge of pre and post-ma~ntenance 2.2'21 4.1 99 operab~ltyrequlrements.

2.

Knowledge of tagging and clearance Equipment 2.2.1 3 4.1 68 procedures Control Ability to apply technical specifications for a 2.2.40 3.4 69 system.

Ability to determine operability and/or 2'2'37 3.6 75 availability of safety related lequipment.

Subtotal 3 2 2.3.11 Ability to control rad~atianreleases. 4.3 96 Knowledge of Radiological Safety Principles

3. pertaining to licensed operator duties, such as Radiation 2.3.1 2 containment entry requirements, fuel handling 3.2 70 Control responsib~lities, access to locked high-radiation areas, aligning filters, etc.

Knowledge of radiation exposure limits under 2'3'4 3.2 71 normal or emergency conditions.

Subtotal 2 1

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 peration of system components

ES-401 Record of Rejected WA's Form ES-401-4 Topic does not apply to VY. Randomly selected EA1.03, correct, control, or mitigate the consequences of those abnormal conditions or operations: D.C. distribution failure: Plant-Specific Topic does not lend itself to a discriminating question (system function) Randomly selected A2.08, Ability to (a)

PROTECTION SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Failure to actuate when required 204000 / 2.4.3 256000 1 K3.07 multi unit license. Randomly selected 2.2.1 3, 201006 / K1.08 ECIFIC) and the following: Steam

Record of Rejected WA's Form ES-401-4 VY has electric feed pumps could not write a specific 295023 1 AK3.05 not apply to VY, randomly selected AK3.03 Low LOD for a discriminating SRO level question for this

ES-301 Administrative Topics Outline Form ES-301-1 I Facility: Vermont Yankee Date of Examination: 2/09 I

I Examination Level: RO Operating Test Number: N09-1 I

I Administrative Topic (see Note) I Typecode* 1 Describe activity to be performed I

2.1.29 (4.1) Knowledge of how to conduct system lineups, such as valves, breakers, switches, N, S etc.

1 JPM: Perform the RHR System Valve Lineup I 2.2.12 (3.7) Knowledge of Surveillance Procedures Equipment Control N, S JPM: Perform a Drywell Temperature Profile 1 2.3.11 (3.8) Ability to control radiation releases I

JPM: Determine Offgas Release Rate without ERFlS 2.4.43 (3.2) Knowledge of Emergency Communications Emergency Systems and techniques ProceduresIPlan D, S JPM: Perform Control Room Emergency Communications Checks I NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking onlv the administrative to~ics,when 5 are required. II

  • Type Codes & Criteria: (C)ontrol room (0), (S)imulator (3),or Class(R)oom (1)

(D)irect from bank (5 3 for ROs; 5 4 for SROs & RO retakes) (1)

(N)ew or (M)odified from bank (2 1) (3)

(P)revious2 exams (51 ; randomly selected) (0)

NUREG-1021, Revision 9

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Vermont Yankee Examination Level: SRO Date of Examination:

Operating Test Number:

2/09 N09-1 I Administrative Topic Type Code* Describe activity to be performed (see Note) 2.1.29 (4.0) Knowledge of how to conduct system Conduct of Operations lineups, such as valves, breakers, switches, N, S etc.

I 1 JPM: 1 Conduct of Operations 1 2.1.7 (4.7)

Perform the RHR System Valve Lineup Ability to evaluate plant performance and make operational judgments based on I operating characteristics, reactor behavior, and instrument interpretation I JPM:

Perform a Core Thermal Hydraulic Limits Evaluation I

2.2.12 (4.1) Knowledge of Surveillance Procedures Equipment Control JPM: Review a Surveillance 2.3.11 (4.3) Ability to control radiation releases Radiation Control JPM: Determine Offgas Release Rate without ERFlS 2.4.44 (4.4) Knowledge of Emergency Plan Protective Emergency Action Recommendations ProceduresIPlan JPM: Off-Site Protective Action Recommendations (evacuate)

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

  • Type Codes & Criteria: (C)ontrol room, (0) (S)imulator, (3) or Class(R)oom (2)

(D)irect from bank (5 3 for ROs; 2 4 for SROs & RO retakes) (1)

(N)ew or (M)odified from bank (21) (4)

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

NUREG-1 021, Revision 9

ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 Transformer APE 295037 Scram Condition Present and Reactor Power Above APRM Downscale or Unknown WA: EA1.10 3.713.9 NUREG-1021, Revision 9

/ Appendix D Scenario Outline Form ES-D-1 1 Facility: VERMONT YANKEE Scenario No.: 1 Op Test No.: 2009 NRC Examiners: Operators: SRO -

RO -

BOP - I Initial Conditions: At 100% power DG " A has been operating for 30 minutes for Monthly Diesel Generator Slow Start Operability Test (Tech Spec) per OP 4126, Sect 6. The test is being performed following a-diesel lube oil change. The test must be run for at least two hours at I 2700 to 2750 kW and 1600 f 50 kVAR OUT.

RHR Pump B is OOS for severe vibrations that occurred during surveillance testing and is tagged out for Maintenance investigation.

i Turnover: RHR Pump B is OOS for severe v~brationsthat occurred during surve~llancetesting and is tagged out for Maintenance investigation.

DG " A is in operation for the Monthly Diesel Generator Slow Start Operability Test I

per OP 4126, Sect B. This requires DG A being declared inop IAW T.S. 3.10.8.1 I

You are requested to bring voltage to 358 KV by VELCO I I

5 I

Critical Tasks: 1. With a reactor scram required and the reactor not shutdown, INHIBIT ADS to prevent an uncontrolled RPV depressurization to prevent causing a significant power excursion. I I

2. During an ATWS w~thconditions met to perform powerllevel control TERMINATE I'

AND PREVENT INJECTION into the RPV using appendix GG, unt~lconditions are met to re-establish injection. 1 I

I

3. With a reactor scram required and the reactor not shutdown, TAKE ACTION TO REDUCE POWER by injecting boron and/or inserting control rods, to prevent exceeding the primary containment design limits. I I

I /

Event Malf. No. Event Event Description I No. Type* i P

1 -

1 NIA N - BOP Raise Main Generator output to heavy load schedule and

,- SRO maximum Lagging (OUT) VAR Load IAW OP 2140, Sect. H.

2 m ~ ~ - 0 3R -~RO Turbine Vibration respond per ARS 7-F-2 (lower power stop test) ,

60% over R - SRO Lower power OP 0105, Reactor Operations (vibrations stop after 300 sec. lowering generator load) 3 mfAN08G5 - DG A -Jacket Water Leak requlres removing DG from service I

SPURIOUS C - SRO I 4 mfRR-11B I-RO "B" Recirc speed controller will fail and will begin to run away I 100% over I - SRO requiring the RO to take manual control and rebalance flows.

600 sec I l

I Appendix D Scenario Outline Form ES-D-1 I I 5 mfED-05Da - R0 Loss of MCC-9A with a failure of the Group 3 Isolation (AC-6B will

- Sflo not auto close) Consult Tech Specs TS - SRO 6 r n f ~ ~ 0 5 ~C b- BOP 480V MCC-8B will trip causing a half scram (if RPS B was

- Sflo transferred to its alternate supply) also the loss of the bus will TS - SRO challenge DW pressure by the loss of power to RRUs 1A and 1B, alternate RRUs must be started. (This power lost will affect ATWS recovery by preventing the use of cooling water flow to insert the control rods.) The SRO will address TS 7 mfRP-02A M- ALL Loss of RPS MG Set A, Hydraulic ATWS with MSlV closure mf RD-I2A mf RD-12B (20120%)

8 mfSL-02A C - RO SLC Squib Valve " A failure (the loss of 88 takes away SLC Pump

- Sflo B) Candidate must recognize that the Squib Valves must be fired locally using the battery.

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

I Appendix D Scenario Outline Form ES-D-1 I Facility: VERMONT YANKEE Scenario No.: 2 Op Test No.: 2009 NRC Examiners: Operators: SRO -

RO -

BOP -

Initial Conditions: At -1 % power, Startup in progress. OP 0105, Phase 2.D Step 10 "A" IRM failed upscale during the startup and is bypassed.

RHR Pump "C" is OOS 1

Turnover: Indefinite LC0 due to IRM "A" OOS (TS Table 3.1.1 and TRM 3.2.5)

RHR Pump "C" is OOS for severe vibrations during surveillance testing. Tagged out on previous shift; estimated return to service is 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, 7-day L C 0 due to RHR Pump "C" OOS (TS 3.5.A.3)

MSlV Isolation Testing is NOT required Critical Task: 1. Following a Loss of Normal Power diagnoses " B DG failed to auto-start and manually starts " B DG and places on 4KV Bus 4.

2. With the reactor shutdown and reactor pressure greater than the shutoff head of the low pressure systems, initiate RPV-ED BEFORE RPV level reaches -1 9 inches
3. Restore and maintain RPV level above TAF (+6 inches)

Event 110.

I Malf. No.

I Event Type*

Event Description 2

1 I N'A mfNM-03C I : I I-RO Withdraw control rods to continue the startup IRM " C lnop Failure, results in half scam.

(100%) I-SRO 1 ;:%I TS - SRO Transfer Reactor Mode switch to RUN and continuethe startup.

4 MfRD-15 I- RO Failure of CRD Flow Controller Automatic Output Signal I- SRO 5 mf~p-03 C-BOP HPCl inadvertently injects to the vessel with a controller failure mf H P-04 C-SRO (low - to prevent a reactor scram). The crew will confirm that the T ~ - ~ HPCl R ~ injection is spurious and trip the HPCl turbine. Requires 6 1 rnfED-02A mf ED-02B 1 M - ALL 1 T.S. 3.5.E entry Loss of the startup transformers which will result in a LNP and reactor scram.

7 mfDG-OsA C - BOP Both DGs fail to auto start, DG " A cannot be started, DG " B can mfDG-08B C-SRO be manually started.

I Appendix D Scenario Outline Form ES-D-1 I 8 m f ~M - ~ ALL - Core ~spray l ~ line "B" break in the Drywell between the RPV and OVRD ANN injection check valve resulting in a LOCA and loss of the remaining Core Spray system.

9 mfRC C - BOP RClC Controller Fails in AUTO, then isolates RClC flow C-SRO controller failure mfRC RClC inadvertent Isolation

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

I Appendix D Scenario Outline Form ES-D-1 I Facility: VERMONT YANKEE Scenario No.: 3 Op Test No.: 2009 NRC Examiners: Operators: SRO -

RO -

BOP -

Initial Conditions: 85% power IC-807 "A" RHR OOS for severe vibration, maintenance is investigating.

Turnover: RHR Pump "A" is OOS while maintenance investigates high vibration. It was tagged out on the previous shift; estimated return to service is 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, 7-day L C 0 due to RHR Pump "A" OOS (TS 3.5.A.3)

Perform OP 4160 Oncemeek Pump Performance Test Section 1.a and b.

Critical Tasks: 1. When drywell temperature cannot be restored and maintained below 280QF, initiate RPV-ED (andlor anticipate ED and use bypass valves).

2. IF Reactor water level cannot be determined, Enters EOP-6, RPV Flooding, opens all SRVs and commences injection using Shutdown RPV Flooding Systems until the Main Steam lines are flooded. OR
3. Restores RPV water level and containment parameters with Condensate injecting directly into the RPV AND/OR aligns alternate injection systems such as RHR.

Event Malf. No. Event Event Description No. Type*

1 N/A N - RO Perform OP 4160 OnceNVeek Pump Performance Test Section

- SRO 1.a and b.

R - SRO 2 mfFW-28A I - RO Feedwater flow transmitter slow failure upscale, causing the crew 50% over 60 sec

, - SRO to take manual control of feedwater in order to recover and stabilize RPV level.

3 m f ~ ~ - 0 B1 (if SRO - TS Call from the Southeast RHR Corner Room that RHR Pump "B" necessary) lower motor bearing oil indicating sight glass is empty. Tech Specs Sections 3.5 and determine that a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> LCO, requiring a plant shutdown, has been entered.

/ Appendix D Scenario Outline Form ES-D-1 1 IOR C - BOP " B Recirc Pump discharge valve full open indication fails causing RRlo042AS7B C -SRO the " B Recirc Pump to runback to minimum flow.

IOR RRdi042AS7B R-RO Insert control rods to get below MELLA IOR R-SRO RRlo042AS7B IRF rfRR-12 - - - - -

mfEDO6A C-RO Trip of CRD Pump B with a loss of 125 VDC Bus 1 (Inops 4 KV C-SRO Bus 3 ECCS equipment). The crew will implement ON 3159, Loss of Bus DC 1. The SSISRO will review Tech Specs Sections 3.10 and 3.5 and determine that a second 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> LCO, requiring a I 1 TS - SRO plant shutdown, has been entered. (STG 04)

EPR Oscillations OT 3115, Reactor Pressure Transients - Place MPR in service.

M -CREW Main Steam Line Break in the Drywell 8 mfFW-08A Failure of the Reactor Feedwater Pumps and Core Spray Pump A mf FW-086 Injection Valve require lining up Condensate Pumps to restore mfFW-08C RPV water level.

mfCS-03A

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