ML071410430

Final - Exam Outlines (Folder 3)

ML071410430
Person / Time
Site:	Vermont Yankee
Issue date:	04/25/2007
From:	Entergy Nuclear Vermont Yankee
To:	Todd Fish Operations Branch I
Sykes, Marvin D.
Shared Package
ML062050096	List: IR 05000271/2007301 ML071150479 ML071350523 ML071350534 ML071350540 ML071350563 ML071350583 ML071410430 ML071410431 ML071410434 ML071410436 ML071410441 ML071410442 ML071430501 ML071440138 ML071590341
References
ES-401, ES-401-1
Download: ML071410430 (18)

Text

ES-401 BWR Examination Outline Form ES-401-1 Facilitv: Vermont Yankee NRC Date of Exam: 412007 RO WA Category Points SRO-Only Points Tier Group K K K K K K A A A A G Tot A2 G* Total 1 2 3 4 5 6 1 2 3 4

• al

1. 1 3 3 4 4 3 3 20 3 4 7 Emergency

& 2 N/A N/A 1 7 1 2 3 Abnormal Iant TierTotals 4 5 4 6 4 4 27 4 6 10 Evolutions Note: 1. Ensure that at least two topics from every WA category are sampled within each tier of the RO outline (i.e., the Tier Totals in each WA category shall not be less than two).

Refer to Section D. 1.c for additional guidance regarding SRO sampling.

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 k 1 from that specified in the tabte based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Select topics from many systems and evolutions; avoid selecting more than two WA topics from a given system or evolution unless they relate to plant-specific priorities.

4. I Systems/evolutions within each group

- . are identified on the associated outline.

I 5. I The shaded areas are not applicable to the categorykier.

6.* 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. The SRO WAS must also be linked to 10 CFR 55.43 or an SRO-level learning objective.

7. 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; summarize all the SRO-only knowledge and non-A2 ability categories in the columns labeled K and A.Use duplicate pages for RO and SRO-only exams.

For Tier 3, enter the WA numbers, descriptions, importance ratings, and point totals on Form ES-401-3.

Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.

NUREG-102 1 1

ES-401 Vermont Yankee NRC Form ES-401-1 BWR SRO/RO Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 295007 High Reactor Pressure / 3 X 2.4.20 Emergency Procedures / Plan Knowledge of operational 4.0 76 implications of EOP warnings/cautions/notes Emergency Procedures / Plan: Knowledge of the parameters and logic used to assess the status of safety 295032 High Secondary Containment Area Temp. I 5 functions including: 1 reactivity Control 2. Core Cooling X 2,4,21 4.0 77 and heat removal. 3. Reactor coolant system integrity 4.

Containment conditions. 5. Radioactivity release control.

(Hi secondary containment area temps).

295023 Refueling Acc Cooling Mode / 8 X 1 I 2.2.29 I Equipment Control Knowledge of SRO fuel handling responsibilities.

I 3.8 78 295024 High Drywell Pressure / 5 t EA2.03 Ability to determine andlor interpret the following as they apply to HIGH DRYWELL PRESSURE: Suppression pool

+

79 Ability to determine andlor interpret the following as they 295028 High Drywell Temperature / 5 EA2.03 apply to HIGH DRYWELL TEMPERATURE : Reactor 80 water level Ability to determine andlor interpret the following as they 295030 Low Suppression Pool Water Level / 5 EA2.01 apply to LOW SUPPRESSION POOL WATER LEVEL : 4.2 81 Suppression pool level................................

295031 Reactor Low Water Level I 2 2.4.7 Emergency ProcedureslPlan Knowledge of Event based 3.8 82 EOP mitigation strategies t

Knowledge of the reasons for the following responses as 295001 Partial or Complete Loss of Forced Core Flow they apply to PARTIAL OR COMPLETE LOSS OF X AK3.02 3.7 39 Circulation / I& 4 FORCED CORE FLOW CIRCULATION : Reactor power response.. ..............................

I Ability to operate and/or monitor the following as they 295003 Partial or Complete Loss of AC I 6 I AA1.02 apply to PARTIAL OR COMPLETE LOSS OF A.C.

POWER : Emergency generators..................................

4.2 40

+

Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF D.C.

295004 Partial or Total Loss of DC Pwr I6 X AA1 .02 3.8 41 POWER : Systems necessary to assure safe plant shutdown.. ........................

Ability to determine andlor interpret the following as they 295005 Main Turbine Generator Trip I 3 AA2.03 apply to MAIN TURBINE GENERATOR TRIP : Turbine 3.I 42 valve position................................

295002 Loss of Main Condenser Vacuum I 8 2,4,1, Emergency ProceduredPlan: Knowledge of Abnormal 3.4 43 Condition Procedures n

NUREP 1021 B

ES-401 Vermont Yankee NRC Form ES-401-1 BWR SRO/RO Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 I E/APE # / Name Safety Function WA Topic(s) I Imp. I Q# 1 Knowledge of the reasons for the following responses as 295016 Control Room Abandonment I 7 X AK3.03 they apply to CONTROL ROOM ABANDONMENT : 3.5 44 Disabling Control Room Controls..

Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE 295018 Partial or Total Loss of CCW I 8 AK1 .Ol 3.5 45 LOSS OF COMPONENT COOLING WATER and the following: Effects on componentskystem operations Knowledge of the interrelationsbetween PARTIAL OR 295019 Partial or Total Loss of Inst. Air I 8 X AK2.08 COMPLETE LOSS OF INSTRUMENT AIR and the following: Plant ventilation.

Knowledge of the interrelationsbetween LOSS OF 295021 Loss of Shutdown Cooling I 4 X AK2.03 SHUTDOWN COOLING and the following:

RHWshutdown coolina 295023 RefuelingAcc Cooling Mode I8 X AK3.02 Knowledge of the reasons for the following responses as they apply to REFUELING ACCIDENTS : Interlocks associated with fuel handling equipment....

1 1 I 3.4 48 295024 High Drywell Pressure I 5 295025 High Reactor Pressure I 3 Ix/ I X

2.4.2 2.1.32 Emergency ProceduresIPlan: Knowledge of system setpointslinterlocks and automatic actions associated with EOP entry condtions.

Conduct of Operations: Ability to explain and apply all 3.9 3.4 49 50 system limits and precautions.

Ability to determine and/or interpret the following as they 295026 Suppression Pool High Water Temp. I5 EA2.03 apply to SUPPRESSION POOL HIGH WATER 3.2 51 TEMPERATURE: Reactor Pressure.

Abiltty to operate and/or monitor the following as they 295036 High Secondary Containment SumpIArea Water Level I 5 295028 High Drywell Temperature I5 I l l X X EA1.02 EK2.04 apply to High Secondary Containment Sump/Area Water Level: Affected systems so as to isolate damaged portions.

Knowledge of the interrelations between High Drywell 3,5 3.6 52 53 temperature and the following: Drywell ventilation.

Ability to operate and/or monitor the following as they 295030 Low Suppression Pool Water Level I 5 X EA1.05 apply to LOW SUPPRESSION POOL WATER LEVEL : 3.5 54 HPCI.........................

-~

Ability to interpret andlor determine the following as they 295031 Reactor Low Water Level I 2 X EA2.04 apply to REACTOR LOW WATER LEVEL: Adequate Core 4.6 55 Cooling.

I I I I -

n NUREP 1021

.if

ES-401 Vermont Yankee NRC Form ES-401-1 BWR SRO/RO Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 I Knowledge of the reasons for the following responses as 295037 SCRAM Condition Present and Power Above they apply to SCRAM CONDITION PRESENT AND APRM Downscale or Unknown / 1 X EK3'03 4.1 56 REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN : Lowerina Reactor Water Level c

1 1 I 295038 High Off-site Release Rate I 9 I I I I I I EK1.02 I Knowledge of the operational implications of the following concepts as they apply to HIGH OFF-SITE RELEASE RATE : Protectionof the general public.............................

~ ~~ ~~ ~

Knowledge of the operations applications of the following 4.2 57 600000 Plant Fire On-site I 8 X AK1.02 concepts as they apply to PLANT FIRE ON SITE: Fire 2.9 58 Fighting WA Category Point Totals: 314 3 3 4 4 313 Group PointTotal: 2017 NUREP 1021

ES-401 Vermont Yankee NRC Form ES-401-1 BWR SRO/RO Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 I II Emergency Procedures IPlan Knowledge of symptom 3.4 83 2,4,6 295010 High Drywell Pressure I 5 X based EOP mitigation strategies 295012 High Drywell Temperature 1 5 I I I 1 I 2,1,9 I Conduct of Operations: Ability to direct personnel activities inside the control room I 4,0 I 84 I Ability to interpret or determine the following as they apply 295003 Partial or Complete loss of AC Power I 6 X AA2.04 to COMPLETE OR PARTIAL LOSS OF AC POWER: 3.7 85 System Lineups 295019 Partial or Total Loss of lnst. Air I 8 X AK2.03

-~~

Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR and the followina: Reactor Feedwater.

1 1 1 I

3.2 59 Emergency Procedures IPlan Knowledge of the specific 295010 High Drywell Pressure I 5 X 2'4'1 bases for EOPs 2,7 I

Ability to determine and/or interpret the following as they 295014 Inadvertent Reactivity Addition I1 X AA2.04 apply to INADVERTENT REACTIVITY ADDITION: 4.1 61 Violation of Fuel Thermal Limits.

Ability to operate and/or monitor the following as they 295012 High Drywell Temperature I 5 X AAI .01 apply to HIGH DRWVELL TEMPERATURE : Drywell 3.5 62 ventilation system............................

~ ~~

Ability to operate and/or monitor the following as they 295015 Incomplete SCRAM / 1 X AA1.01 apply to INCOMPLETE SCRAM: CRD 3.8 63 Hydraulics...................

Knowledge of the operational implications of the following 295033 High Secondary Containment Area Radiation Levels I 9 I I I I I I I EK03 concepts as they apply to HIGH SECONDARY CONTAINMENTAREARADIATIONLEVELS:Radiation releases....................................

Knowledge of the interrelations between SECONDARY 295035 Secondary

~ .~

Containment High Differential X

.. EK2.04 CONTAiNMENT HIGH DIFFERENTIAL PRESSURE and 3.3 65 Pressure I 5 the following: Blowout PanelsIPlant Specific................... I K/A Category Point Total: 112 1 2 0 2 1/1 Group Point Total: 713 E.

NUREP 1021 4 4

ES-401 Vermont Yankee NRC Form ES-401-1 BWR SRO/RO Written Examination Outline Plant Systems Tier 2 Group 1 Ability to (a) predict the impacts of the following on the SLC SYSTEM ; and (b) based on those predictions, use A2.01 procedures to correct, control, or mitigate the 3.8 86 consequences of those abnormal conditions or operations: Pump Trip Ability to (a) predict the impacts of the following on the HIGH PRESSURE COOLANT INJECTION SYSTEM ;

and (b) based on those predictions, use procedures to A2.11 4,2 87 correct, control, or mitigate the consequences of those abnormal conditions or operations: Low reactor water level. BWR-2,3,4 Equipment Control Knowledge of bases in technical safetv limits.

for operations and 1 I 3.7 88 Emergency Procedures I Plan Ability to recognize abnormal indications for system operating parameters 2.4.4 4.3 89 which are entry-level conditions for emergency and abnormal operating procedures.

Ability to (a) predict the impacts of the following on the REACTOR WATER CLEANUP SYSTEM and (b) based on those predictions, use procedures to correct, control, A2'1 3.4 90 or mitigate the consequences of those abnormal operation: Signal received which results in a system isolation Ability to predict and/or monitor changes in parameters associated with operating the RHRILPCI: INJECTION 1 K2.01 3.9 MODE (PLANT SPECIFIC) controls including: Reactor pressure Knowledge of the operational implications of the following concepts as they apply to SHUTDOWN K5.03 2.8 COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) : Heat removal mechanisms Knowledge of the effect that a loss or malfunction of the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN K3.05 2.6 COOLING MODE) will have on following: Fuel Pool Cooling Assist Knowledge of the effect that a loss or malfunction of the following will have on the HIGH PRESSURE COOLANT K6.09 3.5 4 INJECTION SYSTEM : Condensate storage and transfer system: BWR-2,3,4 E

NURECU,IO21

4/2007 I

I RO I SRO-Only Category I Topic Ability to apply technical specificationsfor a

-IR 2.1.12 system.

2.1.20 Ability to execute procedure steps. 4.3 1.

Conduct of 2.1.3 I Knowledgeof shift turnover practices 3.0 Operations Knowledgeof the purpose and/or function of 2'1 '28 3.8 major system components and controls.

Subtotal L.L.LU

2. requirements.

Equipment Control Ability to manipulate the console controls as 2.2.2 requiredto operate the facility between 4.0 shutdown and designated power levels.

2.2.28 Knowledge of new and spent fuel movement orocedures. 2.6 Subtotal Knowledgeof radiation exposure limits and 2.3.4 contamination controll including permissible levels in excess of those authorized.

2.3.2 Knowledge of facility AURA program. 2.5 3.

RadiationControl Ability to perform procedures to reduce 2.3.10 excessive levels of radiation and guard against 2.9 personnel exposure.

Subtotal 2.4.25 Knowledgeof fire protection procedures.

2.4'41 Knowledge of the emergency action level thresholds and classifications.

Ability to perform without reference to

4. 2.4.49 procedures those actions that require immediate 4.0 Emergency operation of system components and controls.

Procedures/ Plan 2.4.1 1 Knowledge of abnormal condition procedures. 3.4 2.4.10 Knowledge of annunciator response procedures. 3.0 Subtotal Tier 3 Point Total NUREG-I021 11

Tier / Randomly Reason for Rejection Group Selected WA 1/1 295019 -

(Q.#46)AK2.08, randomly selected original selection did not apply to K2.13 plant.

1 I 4 295031 (Q. #82) Impossible to meet KA Topic requirement at SRO level.

I ! I 2.1.28 Randomly reselected G2.1.20 for APE. G2.4.7 randomly selected.

1 1 1 295028 (Q. #53). EK2.04 randomly selected - original selection not applicable at NUREG-1021 12

NUREG-1021 13 ES-301 Administrative Topics Outline Form ES-301-1 Examination Level (circle one): RO / SRO Operating Test Number: 2007 NRC

( Administrative Topic 7 Type Code*

Describe activity to be performed I

JPM: Perform Reactor Coolant Temperature Check Conduct of Operations WA: 2.1.7 (3.7)

Ability to evaluate plant performance and make operational judgments based on operating characteristics / reactor behavior /

and instrument interpretation.

JPM: Perform Shutdown CRO Rounds Conduct of Operations WA: 2.1.33 (3.4)

Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.

D. S JPM: Perform a Drywell Temperature Profile Equipment Control Surveillance WA: 2.2.12 (3.0)

Knowledge of Surveillance Procedures JPM: Locate and Determine Radiological Radiation Control Requirements for Inspection of RCU Valve V12-19A (CU-19A)

WA: 2.3.1 (2.6)

Knowledge of 10 CFR: 20 and related facility radiation control requirements.

N/A NUREG-1021, Revision 9

ES-301 Administrative Topics Outline Form ES-301-1 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 Class( R)oom (D)irect from bank (I3 for ROs; I for SROs & RO retakes)

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

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

(S)imulator 2007 NRC Examination Summary Description of Admin Tasks A.l .a The candidate will perform reactor coolant temperature checks. This is a bank JPM. The candidate is required to recognize that the temperature difference is greater than 145 deg F and determine that the recirculation pump may not be started. This is a bank JPM.

A.l .b The candidate will perform a portion of the Shutdown CRO Rounds. The candidate is required to recognize abnormal and out of spec conditions which are entry-level conditions for technical specifications. This is a new JPM.

A.2 The candidate will perform a Drywell Temperature Profile surveillance IAW OP 41 15. This is a bank JPM.

A.3 The candidate will locate and determine radiological requirements for Inspection of RWCU valve V12-19A (CU-19A), including a calculation of stay time, determination of areas with the lowest dose, and determination of areas with the lowest contamination levels. This is a bank JPM. This JPM was used on the 2005 NRC exam; however, task conditions will be modified to result a different stay time and new areas of low dose and contamination levels.

NUREG-1021, Revision 9

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

Examination Level (circle one): RO / SRO Operating Test Number: 2007 NRC Administrative Topic type Describe activity to be performed (see Note) Code*

N JPM: Perform a Core Thermal Hydraulic Limits Conduct of Operations Evaluation.

K/A: 2.1.7 (4.4)

Ability to evaluate plant performance and make operational judgments based on operating characteristics / reactor behavior and instrument interpretation.

D JPM: Review Completed Surveillance and Take Conduct of Operations Action for Out of Spec Data WA: 2.1.12 (4.0)

Ability to apply technical specifications for a system.

~- ~

N JPM: Review Switching and Tagging Order Equipment Control WA: 2.2.13 (3.8)

Knowledge of tagging and clearance procedures.

N JPM: Review and Approve Primary Containment Radiation Control Purge cumulative hours log WA: 2.3.9 (3.4)

Knowledge of the process for performing a containment purge D JPM: PAR Based on Plant Conditions (Shelter)

Emergency Plan WA: 2.4.44 (4.0)

Knowledge of emergency plan protective action recommendations 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.

NUREG-1021, Revision 9

ES-301 Administrative Topics Outline FOIITI ES-301-1

• Type Codes & Criteria: (C)ontrol room (D)irect from bank (s3 for ROs; 4 I for SROs & RO retakes)

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

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

(S)imulator 2007 NRC Examination Summary Description of Admin Tasks A. 1.a The candidate will perform a core thermal limits hydraulic evaluation IAW OP 4401 and determine that one thermal limit is out of spec requiring a TS entry. This is a new JPM.

A. 1.b The candidate will review a completed RHR system surveillance and take action for out of spec data. This is a bank JPM.

A.2 The candidate will review a switching and tagging order for A CRD pump, identify tagging errors, and determine that the tagout cannot be approved as written. This is a new JPM.

A.3 The candidate will review the containment purge cumulative hours log in preparation for a containment purge. The hours log will be inaccurate and the candidate must determine that the purge can not be approved. This a new JPM.

A.4 The candidate will make the initial PAR based during a LOCA event with a release in progress i per OP 3511. The candidate will determine that shelter is required. The task is time critical.

This is a bank JPM.

NUREG-1021, Revision 9

ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 Facility: Vermont Yankee Date of Examination:

Exam Level (circle one): RO / SRO(I) / SRO (U) Operating Test No.: NRC 2007

~~

Control Room Systems* (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function I S-I 201006 Source Range Monitor Rx startup to criticality, high reactor period 7

I S-2 261000 Standby Gas Treatment System Secure Standby Gas Treatment 9

I S-3 241000 ReactoriTurbinePressure Regulating System Transfer Pressure Control From MPR to EPR 3

I S-4 262001 A.C. Electrical Distribution System Energize Bus 4 From the Vernon Tie Line During a SBO 6

I S5 217000 Reactor Core Isolation Cooling System Respond to RClC Auto Controller Failure 2

I S-6 209001 Core Spray System Perform Core Spray A Quarterly Full Flow Test 4

I S-7 S-8 223002 Primary Containment Isolation System PClS Group V isolation failure 202001 Reactor Recirculation System 5

1 (RO) Recirc Pump Start With failed Field Breaker During Startup I Inplant Systems@(3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

I P-I 264000 Emergency Generators Shutdown Diesel Generator Locally I P-2 P-3 239002 Safety Relief Valves Lineup to Operate SRV-71 A and B From The RClC Room 211000 Standby Liquid Control System Perform Local Firing of Squib Valves I

NUREG-1021, Revision 9

I Appendix D Scenario Outline Form ES-D-1 I 1 Facility: VERMONT YANKEE Scenario No.: 1 Op Test No.: 2007 NRC Examiners: Operators:

Initial Conditions: 0 At 90% power for control rod pattern adjustment.

0 Power ascension required back to 100%.

Turnover: Perform weekly remote testing of Turbine Oil pumps IAW OP 4160.

6 rnfRD-051831 C-CRO Control Rod 18-31 drifts outward (OT).

100% C-CRS 7 RC04 I-ACRO Inadvertent HPCl initiation (TS).

100% I-CRS 8 mfED-17 M-ALL Loss of Offsite power.

9 mf HP-04 C-ACRO HPCl Flow Controller Failure.

0% C-CRS 10 mfRR-O1A M-ALL Recirc loop rupture (initially, 0.7% over 300 sec). HPCl trip.

mf HP-0 1 RPV-ED on low level.

11 mfCS-03A C-CRS CS-12A and CS-12B failure to auto open.

Preinsert mfCS-03B C-ACRO Preinsert mfRH-07A RHR 27A failure to auto open.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D NUREG 1021 Revision 9

1 Appendix D Scenario Outline Form ES-D-1 I Facility: VERMONT YANKEE Scenario No.: 2 Op Test No.: NRC 2007 Examiners: Operators:

Initial Conditions: 0 100% power, preparing to chlorinate the Circ Water System 0 APRM C is bypassed due to inability to adjust gain - I&Ctroubleshooting is in progress

~~

0 RHR-39A Valve motor actuator is being repaired day LCO entered 4/28/07 per TS 3.5.B. 1

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Turnover: 0 Place CW in Closed Cycle for chlorination.

0 Reduce reactor power in preparation for a control rod pattern adjustment. Per RE Guidance, the Rapid Shutdown Sequence will be used to reduce power to 80-85%.

Critical Task: See Scenario Summarv Event Malf. No. Event Event Description No. Type*

1 N/A N-CRS Place CW in Closed Cycle for chlorination.

N-ACRO 2 I N/A I R-CRO I Power Reduction IAW OP 0105.

N-CRS 3 W-O9A C-CRS Feedwater regulating valve lockup (OT).

C-CRO 4 mfNM-05A I-CRO APRM A fails downscale (TS) 1 0%

mfED-05C mfPC-11A I I-CRS C-ALL I Loss of 480V Bus 8 (TS), Failure of SBGT A to auto start.

6 mfTC-04A C-ACRO EPR Oscillations (OT).

C-CRS 7 mfAD-01 B C-ALL SRV-71B leak (OT) leads to Rx scram (100% over 600 sec).

Preinsert I mfRPoB I1 I-CRO I-CRS I1 Failure of manual scram.

Preinsert 1 mfRD-12A mfRD-126 (N)ormal, M-ALL 45% hydraulic ATWS (A). 55% hydraulic ATWS (B).

(R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D NUREG 1021 Revision 9

[ Appendix D Scenario Outline Form ES-D-1 1 Facility: VERMONT YANKEE Scenario No.: 3 ~ Op TestNo.: 2007 NRC Examiners: Operators:

Initial Conditions: 0 Power is -2% with a reactor startup in progress.

Turnover: OP 0105 is complete thru Phase 2.C.

0 Perform Turbine Chest Warmup IAW OP 0105 Phase 2.D. Step 1.

0 Continue Reactor Startup (60 to 80 degree heat up rate).

Critical Task: See Scenario Summary Event No.

I Malf. No. Event II Event Description 1

I NAI N-ALL R-CRO Perform Turbine Chest Warmup.

Pull rods to continue power ascension.

N-CRS I NM04A I-CRO C-CRS IRM A fails upscale (TS).

I mfRD-Al C-CRO C-CRS CRD Flow control Valve fails closed (ON).

5 6 mfRD-02 1819 rfPP-06 C-CRO C-CRS C-ACRO Stuck Control Rod 18-19 (ON)

Seismic event.

mfSW-14A C-CRO TBCCW A Pump Trip w/ TBCCW 8 Pump Failure to auto start mfSW-216 mfMS-09 C-ACRO Gland Seal Regulator Fails Closed C-CRS C-ACRO RClC steam leak (TS).

I mfHP-15 C-CRS RClC fails to auto isolate.

9 rfPP-06 M-ALL Seismic aftershock. Group 1 isolation.

mfRR-18H mfRP-01 C I-CRO Auto scram failure. Manual scram required.

mfRP-O1A I-CRS mfRD-O9A I-ACRO Scram Discharge Valves 33A, 336 fail open.

I-CRS Appendix D NUREG 1021 Revision 9

1 Appendix D Scenario Outline Form ES-0-1 ]

12 mfPC-10 M-ALL Torus leak at A RHR suction (50% over 900 secs).

PRV-ED on low Torus level.

Appendix D NUREG 1021 Revision 9