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 1234561234*

al SRO-Only Points Group K K K K K K A A A A G Tot A2 G* Total Tier > 1. 1 334 43 3 20 3 4 7 Emergency Abnormal 'Iant Evolutions

& 2 N/A N/A 17 1 2 3 TierTotals 4 5 4 64 4 27 4 6 10 Note: 1. 2. 3. 4. I- -. 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. 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. 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. Systems/evolutions within each group are identified on the associated outline.

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

6.* 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.

The SRO WAS must also be linked to 10 CFR 55.43 or an SRO-level learning objective. 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. NU REG- 1 02 1 1 ES-401 295007 High Reactor Pressure / 3 Vermont Yankee NRC BWR SRO/RO Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 X Form ES-401-1 2.4.20 2,4,21 Emergency Procedures

/ Plan Knowledge of operational implications of EOP warnings/cautions/notes Emergency Procedures

/ Plan: Knowledge of the parameters and logic used to assess the status of safety functions including:

1 reactivity Control

2. Core Cooling 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 X AA1 .02 AA2.03 2,4,1, Ability to determine andlor interpret the following as they valve position ................................

Emergency ProceduredPlan: Knowledge of Abnormal Condition Procedures apply to MAIN TURBINE GENERATOR TRIP : Turbine 3. I 3.4 4.0 76 295032 High Secondary Containment Area Temp.

I5 X 4.0 77 I 3.8 Equipment Control Knowledge of SRO fuel handling responsibilities.

1 I 2.2.29 I 78 - 79 t Ability to determine andlor interpret the following as they apply to HIGH DRYWELL PRESSURE: Suppression pool Ability to determine andlor interpret the following as they apply to HIGH DRYWELL TEMPERATURE

Reactor water level 295024 High Drywell Pressure

/ 5 295028 High Drywell Temperature

/ 5 EA2.03 EA2.03 80 82 40 + Ability to determine andlor interpret the following as they apply to LOW SUPPRESSION POOL WATER LEVEL : Suppression pool level ................................

Emergency ProcedureslPlan Knowledge of Event based EOP mitigation strategies EA2.01 4.2 295030 Low Suppression Pool Water Level / 5 295031 Reactor Low Water Level I2 - 3.8 2.4.7 295001 Partial or Complete Loss of Forced Core Flow Circulation

/ I & 4 t Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION

Reactor power response..

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

POWER : Emergency generators

..................................

AK3.02 X 3.7 4.2 I AA1.02 I 295003 Partial or Complete Loss of AC I6 Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER : Systems necessary to assure safe plant shutdown..

........................

295004 Partial or Total Loss of DC Pwr I 6 3.8 41 - 42 + 295005 Main Turbine Generator Trip I3 295002 Loss of Main Condenser Vacuum I 8 43 n B NUREP 1021 ES-401 Knowledge of the reasons for the following responses as Disabling Control Room Controls..

Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER and the following: Effects on componentskystem operations they apply to CONTROL ROOM ABANDONMENT

Vermont Yankee NRC BWR SRO/RO Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 3.5 44 3.5 45 Form ES-401-1 295019 Partial or Total Loss of Inst. Air I8 295021 Loss of Shutdown Cooling I4 295023 Refueling Acc Cooling Mode I 8 X X Emergency Procedures I Plan: Knowledge of system setpointslinterlocks and automatic actions associated with EOP entry condtions.

Conduct of Operations: Ability to explain and apply all system limits and precautions. Ability to determine and/or interpret the following as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: Reactor Pressure.

3.9 49 3.4 50 3.2 51 295025 High Reactor Pressure I3 295026 Suppression Pool High Water Temp. I 5 X Abiltty to operate and/or monitor the following as they apply to High Secondary Containment Sump/Area Water Level: Affected systems so as to isolate damaged portions.

3,5 52 295028 High Drywell Temperature I 5 295030 Low Suppression Pool Water Level I5 X Knowledge of the interrelations between High Drywell temperature and the following: Drywell ventilation. Ability to operate and/or monitor the following as they HPCI.. .... . . . .. . . .. . . .. . . . . . . apply to LOW SUPPRESSION POOL WATER LEVEL : 3.6 53 3.5 54 Ability to interpret andlor determine the following as they apply to REACTOR LOW WATER LEVEL: Adequate Core Cooling. 4.6 55 I E/APE # / Name Safety Function WA Topic(s) I Imp. I Q# 1 AK3.03 295016 Control Room Abandonment I7 295018 Partial or Total Loss of CCW I8 X X X X AK1 .Ol Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR and the following: Plant ventilation.

Knowledge of the interrelations between LOSS OF SHUTDOWN COOLING and the following: RHWshutdown coolina AK2.08 AK2.03 Knowledge of the reasons for the following responses as they apply to REFUELING ACCIDENTS

Interlocks associated with fuel handling equipment

.... 1 3.4 1 48 I AK3.02 Ix/ I 2.4.2 295024 High Drywell Pressure I5 2.1.32 EA2.03 Ill 295036 High Secondary Containment SumpIArea Water Level I5 EA1.02 EK2.04 EA1.05 -~ 295031 Reactor Low Water Level I2 X - EA2.04 I I I I NUREP 1021 .if n ES-401 EK3'03 X Vermont Yankee NRC BWR SRO/RO Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 Knowledge of the reasons for the following responses as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN : Lowerina Reactor Water Level 4.1 56 Form ES-401-1 600000 Plant Fire On-site I8 WA Category Point Totals:

I ~ ~~ ~~ ~

Knowledge of the operations applications of the following Fighting X AK1.02 concepts as they apply to PLANT FIRE ON SITE: Fire 2.9 58 314 3 3 4 4 313 Group PointTotal:

2017 295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown

/ 1 c I 1 295038 High Off-site Release Rate I9 Knowledge of the operational implications of the following concepts as they apply to HIGH OFF-SITE RELEASE 1 4.2 I 57 I I I I I EK1.02 I RATE : Protection of the general public

.............................

NUREP 1021 ES-401 I 3.4 2,4,6 Emergency Procedures I Plan Knowledge of symptom 295010 High Drywell Pressure I5 X based EOP mitigation strategies Vermont Yankee NRC BWR SRO/RO Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 83 Form ES-401-1 295003 Partial or Complete loss of AC Power I6 29501 9 Partial or Total Loss of lnst. Air I 8 X AA2.04 X AK2.03 I I I 1 I I I 2,1,9 I Conduct of Operations: Ability to direct personnel activities I 4,0 I 84 I 295012 High Drywell Temperature 15 inside the control room Ability to interpret or determine the following as they apply to COMPLETE OR PARTIAL LOSS OF AC POWER: System Lineups 3.7 85 295010 High Drywell Pressure I5 -~~ Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR and the followina: Reactor Feedwater.

1 3.2 1 59 1 .. I Emergency Procedures I Plan Knowledge of the specific 2,7 X 2'4'1 bases for EOPs 295014 Inadvertent Reactivity Addition I 1 295012 High Drywell Temperature I5 295015 Incomplete SCRAM

/ 1 295033 High Secondary Containment Area Radiation Ability to determine and/or interpret the following as they apply to INADVERTENT REACTIVITY ADDITION:

Violation of Fuel Thermal Limits.

I 4.1 61 X AA2.04 X AAI .01 3.5 62 ~ ~~ Ability to operate and/or monitor the following as they Hydraulics..

.................

Knowledge of the operational implications of the following concepts as they apply to HIGH SECONDARY X AA1.01 apply to INCOMPLETE SCRAM: CRD 3.8 63 Ability to operate and/or monitor the following as they apply to HIGH DRWVELL TEMPERATURE

Drywell ventilation system

............................

Levels I9 I I I I I EK03 I I CONTAINMENTAREARADIATION LEVELS:Radiation releases..

..................................

Knowledge of the interrelations between SECONDARY

~ X EK2.04 CONTAiNMENT HIGH DIFFERENTIAL PRESSURE and 3.3 295035 Secondary Containment High Differential

.~ 65 NUREP 1021 4 Pressure I5 K/A Category Point Total:

E. 4 .. the following: Blowout PanelsIPlant Specific ...................

I 112 1 2 0 2 1/1 Group Point Total: 713 ES-401 Vermont Yankee NRC BWR SRO/RO Written Examination Outline Plant Systems - Tier 2 Group 1 A2.01 A2.11 Form ES-401-1 Ability to (a) predict the impacts of the following on the SLC SYSTEM

and (b) based on those predictions, use procedures to correct, control, or mitigate the 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 correct, control, or mitigate the consequences of those abnormal conditions or operations: Low reactor water level. BWR-2,3,4 3.8 4,2 86 87 Equipment Control Knowledge of bases in technical safetv limits. for operations and 1 3.7 I 88 2.4.4 Emergency Procedures I Plan Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

4.3 89 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, or mitigate the consequences of those abnormal operation: Signal received which results in a system isolation A2'1 3.4 90 K2.01 Ability to predict and/or monitor changes in parameters associated with operating the RHRILPCI:

INJECTION MODE (PLANT SPECIFIC) controls including: Reactor pressure 3.9 1 K5.03 K3.05 Knowledge of the operational implications of the following concepts as they apply to SHUTDOWN 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 COOLING MODE) will have on following: Fuel Pool Cooling Assist 2.8 2.6 K6.09 Knowledge of the effect that a loss or malfunction of the following will have on the HIGH PRESSURE COOLANT INJECTION SYSTEM : Condensate storage and transfer system: BWR-2,3,4 3.5 4 E NURECU,IO21 4/2007 RO I SRO-Only I Category I I Topic IR - 4.3 3.0 - Ability to apply technical specifications for a system. Ability to execute procedure steps. 2.1.12 2.1.20 1. Conduct of Operations 2.1.3 I Knowledge of shift turnover practices 3.8 Knowledge of the purpose and/or function of major system components and controls.

2'1 '28 Subtotal 2. Equipment Control L.L.LU requirements.

Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels. Knowledge of new and spent fuel movement orocedures.

4.0 2.2.2 2.2.28 2.6 Subtotal 2.3.4 Knowledge of radiation exposure limits and contamination controll including permissible levels in excess of those authorized.

Knowledge of facility AURA program. 2.3.2 2.5 2.9 - 3. Radiation Control Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.

2.3.10 Subtotal 2.4.25 2.4'41 2.4.49 2.4.1 1 Knowledge of fire protection procedures.

Knowledge of the emergency action level thresholds and classifications.

Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

Knowledge of abnormal condition procedures.

4.0 3.4 4. Emergency Procedures

/ Plan 3.0 2.4.10 Knowledge of annunciator response procedures.

Subtotal Tier 3 Point Total NUREG-I021 11 Reason for Rejection (Q.#46) AK2.08, randomly selected - original selection did not apply to (Q. #82) Impossible to meet KA Topic requirement at SRO level. Tier / Randomly Group Selected WA 295019 K2.13 plant. 295031 1/1 1 I4 2.1.28 295028 Randomly reselected G2.1.20 for APE. G2.4.7 randomly selected. (Q. #53). EK2.04 randomly selected - original selection not applicable at I! I 111 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 Conduct of Operations I Conduct of Operations Conduct of Operations Equipment Control Radiation Control Type Code* D. S Describe activity to be performed JPM: Perform Reactor Coolant Temperature Check 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 WA: 2.1.33 (3.4) Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications. Perform a Drywell Temperature Profile Surveillance JPM: WA: 2.2.12 (3.0)

Knowledge of Surveillance Procedures JPM: Locate and Determine Radiological 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-30 1 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 (I 3 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 A.l .a A.l .b A.2 A.3 2007 NRC Examination Summary Description of Admin Tasks 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. 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. The candidate will perform a "Drywell Temperature Profile" surveillance IAW OP 41 15. This is a bank JPM. The candidate will locate and determine radiological requirements for Inspection of RWCU valve V12-19A (CU-1 9A), 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 (see Note) Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan type Code* N D N N D Describe activity to be performed JPM: Perform a Core Thermal Hydraulic Limits 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.

JPM: Review Completed Surveillance and Take Action for Out of Spec Data WA: 2.1.12 (4.0) Ability to apply technical specifications for a system. ~- ~ JPM: Review Switching and Tagging Order WA: 2.2.13 (3.8) Knowledge of tagging and clearance procedures.

JPM: Review and Approve Primary Containment Purge cumulative hours log WA: 2.3.9 (3.4) Knowledge of the process for performing a containment purge JPM: PAR Based on Plant Conditions (Shelter)

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 (s 3 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 per OP 351 1. The candidate will determine that shelter is required. The task is time critical.

This is a bank JPM. i 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 S-I 201006 Source Range Monitor I Rx startup to criticality, high reactor period S-2 261000 Standby Gas Treatment System I Secure Standby Gas Treatment S-3 241 000 ReactoriTurbine Pressure Regulating System Transfer Pressure Control From MPR to EPR I S-4 262001 A.C. Electrical Distribution System Energize Bus 4 From the Vernon Tie Line During a SBO I S5 21 7000 Reactor Core Isolation Cooling System Respond to RClC Auto Controller Failure I S-6 209001 Core Spray System I Perform Core Spray "A Quarterly Full Flow Test S-7 223002 Primary Containment Isolation System PClS Group V isolation failure I S-8 202001 Reactor Recirculation System (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) P-I 264000 Emergency Generators I Shutdown Diesel Generator Locally P-2 239002 Safety Relief Valves I Lineup to Operate SRV-71 A and B From The RClC Room P-3 21 1000 Standby Liquid Control System Perform Local Firing of Squib Valves Type Code* Safety Function 7 9 3 6 2 4 5 1 I NUREG-1021, Revision 9 I Appendix D Scenario Outline Form ES-D-1 I 11 Facility: VERMONT YANKEE Scenario No.: 1 Op Test No.: 2007 NRC Examiners: Operators:

Initial Conditions:

0 0 At 90% power for control rod pattern adjustment. Power ascension required back to 100%. Turnover : Perform weekly remote testing of Turbine Oil pumps IAW OP 41 60. 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 H P-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. RPV-ED on low level. mf HP-0 1 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 6 7 Facility:

VERMONT YANKEE Scenario No.: 2 Op Test No.: NRC 2007 Examiners:

Operators:

mfTC-04A C-ACRO EPR Oscillations (OT). mfAD-01 B C-ALL C-CRS SRV-71 B leak (OT) leads to Rx scram (1 00% over 600 sec). Initial Conditions:

0 0 100% power, preparing to chlorinate the Circ Water System APRM C is bypassed due to inability to adjust gain - I&C troubleshooting is in progress ~~ 0 RHR-39A Valve motor actuator is being repaired day LCO entered 4/28/07 per TS 3.5.B. 1 ~~ Turnover:

0 0 Place CW in Closed Cycle for chlorination. 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 1 N/A N-CRS Place CW in Closed Cycle for chlorination.

No. Type* 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) 0% I-CRS mfED-05C I C-ALL I Loss of 480V Bus 8 (TS), Failure of SBGT A to auto start. 1 mfPC-11A I-CRO Failure of manual scram.

I I-CRS I Preinsert I mfRPo'B mfRD-12A 1 M-ALL 1 45% hydraulic ATWS (A). 55% hydraulic ATWS (B).

Preinsert 1 mfRD-126 * (N)ormal, (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 0 Perform Turbine Chest Warmup IAW OP 0105 Phase 2.D. Step 1. Continue Reactor Startup (60 to 80 degree heat up rate). Critical Task: See Scenario Summary Event I Malf. No. No. I NIA 1 I NM04A I mfRD-llA mfRD-02 181 9 5 6 rfPP-06 mfSW-14A mfSW-216 mfMS-09 I mfHP-15 9 rfPP-06 mfRR-18H mfRP-01 C mfRP-O1A mfRD-O9A Event I Event Description N-ALL I Perform Turbine Chest Warmup. R-CRO Pull rods to continue power ascension.

N-CRS I-CRO IRM A fails upscale (TS). C-CRS C-CRO CRD Flow control Valve fails closed (ON). C-CRS C-CRO Stuck Control Rod 18-1 9 (ON) C-CRS C-ACRO Seismic event.

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

C-CRS RClC fails to auto isolate. M-ALL Seismic aftershock.

Group 1 isolation.

I-CRO Auto scram failure. Manual scram required.

I-CRS 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