ML14080A504

Indian Point Station, Unit 2 - Draft Operating Exam Written Exam (Sections a, B, and C) (Folder 2)

ML14080A504
Person / Time
Site:	Indian Point
Issue date:	12/18/2013
From:	Silk D M Operations Branch I
To:	Entergy Nuclear Indian Point 2
Jackson D E
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ML13252A147	List: IR 05000247/2014301 ML14043A526 ML14080A500 ML14080A501 ML14080A502 ML14080A503 ML14080A504 ML14080A506 ML14080A507 ML14080A508 ML14091A692 ML14111A374 ML14111A375 ML14111A376
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Download: ML14080A504 (232)

Text

Appendix C Facility:

IPEC UNIT2 Job Performance Measure Worksheet Task No: 2000650102 Task Title: Replace a Watchstander due to Illness KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing: Simulated Performance Classroom 2.1.5 R0-2.9 X READ TO THE EXAMINEE Job Performance Measure No: NRC Examiner:

Date: Actual Performance Simulator Plant Form ES-C-1 RO Admin C0-1 X I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1. Today is February 7 at 1900 2. Nick Chase is On Vacation 3. Ryan Pelkey called in sick yesterday and today. 4. Joe Gaspar has become ill and was sent home at 18:30. 5. The schedule was reviewed and an individual has been called in. Task Standard:

All of the ROs on the schedule have been evaluated and a determination made regarding who can be called in without violating requirements.

Required Materials: Operations Schedule

{Included)

General

References:

EN-OM-123 I P-SMM-OP-1 03 1 of 6 Appendix C Job Performance Measure Worksheet Form ES-C-1 Initiating Cue: Review attached schedule and determine the accuracy and consequences (if any) of the recommendations.

Time Critical Task: No Validation Time: 30 Min 2 of6 Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J) 1. Performance Step: Obtain correct procedures Standard:

Obtain EN-OM-123 IP-SMM-OP-1 03 CUE: Give candidates procedure.

Comment: 2. Performance Step: Standard:

Comment: ..J 3. Performance Step: Standard:

Comment: Review Ops Schedule and procedural requirements Reviews Schedule and determines scheduling requirements Determines the following people can work the entire shift Joe Varga Mike Ruh Ross Rohla Gary Martin (Off vacation)

Pete Labuda (off vacation) 3 of 6 Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark .V) .V 4. Performance Step: Standard:

Comment: The following people cannot be called in because ... Mike Cosentino Exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in 7 days Dave Caffery Will exceed 72 in 7 days going forward Tom Alexander Scheduled for next Day Shift Eric Schimpf Scheduled for next Day Shift Roy Rowland Just completed Day Shift Fabian Ramos Just completed Day Shift Ed Bordas Worked 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> day shift not off for 10/8 hours Harry Primrose Worked 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> day shift not off for 10/8 hours Phil Mullen Worked 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> day shift not off for 10/8 hours Pete Campbell Will exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in 7 Days going forward Terminating Cue: JPM Complete 4 of 6 Appendix C Simulator Setup VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response:

Result: SAT or UNSAT Examiner's signature and date: ___________

_ 5 of 6 Form ES-C-1 Page 6 of 6 Initial Conditions:

1. Today is February 7 at 1900 2. Nick Chase is On Vacation 3. Ryan Pelkey called in sick yesterday and today. 4. Joe Gaspar has become ill and is being sent home. Mike Cosentino Joe Varga Dave Caffery Mike Ruh Ross Rohla Tom Alexander Eric Schimpf Pete Labuda Roy Rowland Fabian Ramos Gary Martin Pete Campbell Initiating Cue: Review attached schedule and determine from the list of operators who can or cannot be called in for replacing the leaving RO without waiving overtime requirements.

Include why an individual cannot be called in. File: 2000651602-1.doc Task Number: 200*065*01*02 Appendix C Facility:

IPEC UNIT2 Job Performance Measure Worksheet Task No: 0001250502 Form ES-C-1 Task Title: Determine Reactor Vessel Venting Time Per FR-1.3, Attachment 1 KIA

Reference:

2.1.25 Job Performance Measure RO Admin RO-3.9 SRO-4.2 No: C0-2 -----Examinee:

NRC Examiner:

Facility Evaluator:

Date: Method of testing: Simulated Performance X Actual Performance Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1. An event occurred 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ago that resulted in a YELLOW path condition on the Inventory Critical Safety Function Status Tree, FR-1.3. 2. The TSC has requested that the Reactor Vessel be vented in accordance with FR-1.3, Response to Voids in Reactor Vessel. 3. Given the following information:

Containment Pressure Containment Temperature Containment Hydrogen RCS Pressure 2.6 psig 172°F 2.3% 550 psig Task Standard:

Vessel Venting time is properly calculated.

Required Materials:

Calculator General

References:

2-FR-1.3 1 of 8 Appendix C Job Performance Measure Worksheet Form ES-C-1 Initiating Cue: You are the spare RO and the CRS has directed you to calculate Reactor Vessel Venting Time in accordance with FR-!.3 Attachment 1 and Figure FRI3-3. Time Critical Task: No Validation Time: 20 min 2 of 8 Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J) 1. Performance Step: Standard:

Comment: ....} 2. Performance Step: Standard:

Comment: ....} 3. Performance Step: Standard:

Comment: ....} 4. Performance Step: Standard:

Comment: Obtain correct procedure Obtains FR-1.3 Determine Containment Volume at STP (A) A= 2.61 E6 X 17.3/14.7 X 492/632 A= 2.39 E6 Determine Maximum Hydrogen volume that can be vented {B) B = (3.0 -2.3 X2.39 E6) 100 B = 1.67 E4 Determine Hydrogen flow rate as a function of RCS pressure (C) Using FR13-3; C = 1500 SCFM 3 of 8 Appendix C Page 4 Performance Information (Denote critical steps with a check mark -f) -! 5. Performance Step: Calculate maximum venting time Standard:

Comment: Time = 1.67 E4 1500 Time = 11 minutes Terminating Cue: JPM Complete 4 of 8 Form ES-C-1 Appendix C Page 5 Form ES-C-1 Number: Tit l £: Revision Number: 2-FR-!.3 RESPONSE ro VOIDS IN REACTOR VESSEL REV. 2 I'IGURE FRI3-3 Hydroge1 0 2:!0 500 750 1000 l2SC 1500 1758 20CO 2250 2500 RCS rresscll e PSIGl FIGURE FR13-3. HYDROGEN ELOWRATE VERSUS RCS PRESSURE -END-19 0 f 20 5 of 8 Appendix C Page 6 Form ES-C-1 Number: Tille: Revision Number: 2-FR-!.3 RESPONSE TO VOIDS IN REACTOR VESSEL REV. 2 ATTACHMENT l (Attachment page 1 of 11 l. INSTRUCTIONS FOR DETERMINING VENTING TIME Determine containment air volume at STP A=Z.61E6cuftx P x492°R J.1'1tL 14.7 psi a T where: P (psia) and: T (0 R) Containment pressure (psig) + 14.7 Containment temperature

(°F) +-460 2. Determine maximum hJ'ljroqen volume that can be vented= B :J, B = (3.0% Containment Hydrogen Concentration) x A 100% 3. petermine hydrogen flow rate as a function of RCS pressure a) Check RCS pressure.

b) Using FIGURE FRl3-3. read hydrogen flow rate. 4. Calculate maximum venting time: Maximum venting time B c Maximum venting time _1,_,1 __ -END-?.0 of 20 6 of 8 Appendix C Simulator Setup VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response:

Result: SAT or UNSAT Examiner's signature and date: ___________

_ 7 of 8 Form ES-C-1 Initial Conditions:

1. An event occurred 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ago that resulted in a YELLOW path condition on the Inventory Critical Safety Function Status Tree, FR-1.3. 2. The TSC has requested that the Reactor Vessel be vented in accordance with FR-1.3, Response to Voids in Reactor Vessel. 4. Given the following information:

Containment Pressure Containment Temperature Containment Hydrogen RCS Pressure Initiating Cue: 2.6 psig 172°F 2.3% 550 psig You are the spare RO and the CRS has directed you to calculate Reactor Vessel Venting Time in accordance with FR-!.3 Attachment 1 and Figure FRI3-3.

Appendix C Facility:

IPEC UNIT2 Job Performance Measure Worksheet Task No: 0430010321 Form ES-C-1 Task Title: Demonstrate Proficiency in use of Generator Capability Curve 2.2.41 KIA

Reference:

RO -3.4 SRO -3.8 Job Performance Measure No: Examinee:

Facility Evaluator:

Method of testing: Simulated Performance Classroom X READ TO THE EXAMINEE NRC Examiner:

Date: Actual Performance Simulator Plant ROAdmin EC-1 X I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

• Reactor is at 100% power, equilibrium Xenon, EOL

• An NPO incorrectly operated valves resulting in a loss of some Hydrogen from the Main Generator

• The Hydrogen vent path has been isolated Task Standard:

MVAR adjustment accurately evaluated.

Required Materials:

Ruler General

References:

Graph EL-1 Initiating Cue: You are the BOP and the CRS has directed you to determine if the Main Generator is operating within the limits of Graph EL-1 for current conditions.

Time Critical Task: No Validation Time: 15 1 of 8 Appendix C Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark -/) 1. Performance Step: Obtain correct procedure Standard:

Obtains Graph-EL-1 Comment: -! 2. Performance Step: Obtain current generator gas pressure Standard:

Determines Gas Pressure is 45 psig +/- 1 psig Comment: -! 3. Performance Step: Obtain current generator gross megawatts Standard:

Determines 950 +/- 5 MWe Comment: -1 4. Performance Step: Obtain current MVAR load Standard:

Determine MVAR load is 460 Leading Comment: 2 of 8 Appendix C Page 3 Performance Information (Denote critical steps with a check mark ...J) ...J 5. Performance Step: Evaluate conditions using Graph EL-1 Form ES-C-1 Standard:

Determines MVAR Loading is outside allowable on Graph EL-1 Comment: Terminating Cue: JPM Complete 3 of 8 Appendix C CJ [§_QQJ :5 lf4QoJ f/) a: URAl22KV [§_9.Qj Page 4 d INDIAN POINT 2 ATB 4 POLE 1,439,200 KVA.1800 RPM. 22000 VOLTS .81 PF .* 58 SCR. 75 PSIG HYDROGEN PRESSURE.

535 VOLTS EXCITA110N

' 200 400 ,-,600 -,-;1000 0.6Q Pf_: CURVE AB LIMITED BY FIELD HEATING CURVE BC LIMITED BY ARMATURE HEATING . .o.e9_PE;:.r i -0.70 p F B O.ZO PF; B :o.ao PF

• CURVE CD LIMITED BY ARMATURE CORE END HEATING DATE 1[ h {1 b Estirr.ated Cape.bilfty Cnrvos . D-w<J. ___ 483111\532 APPROVED DATE 4 of 8 Form ES-C-1 0.96 PF. 0.98 PF: r 0.95.PF EL-1 Rev. 4 . SSL 20.9 Kl/ SSL 22 Kl/ SSL 23.1 Kl/

Appendix C Simulator Setup Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response:

Result: SAT or UNSAT Examiner's signature and date: ___________

_ 5 of 8 JPM-0450010101 SIMULATOR Initial Conditions:

• Reactor is at 100% power, equilibrium Xenon, EOL

• An NPO incorrectly operated valves resulting in a loss of some Hydrogen from the Main Generator

• The Hydrogen vent path has been isolated Initiating Cue: You are the BOP and the CRS has directed you to determine if the Main Generator is operating within the limits of Graph EL-1 for current conditions 6 of 8 JPM-0450010101 OUT 400 \ 600 7 of 8 SIMULATOR I=;Et'>lEF:f.I.TOF.'

H2 F'F:EE;SIJFi'E JPM-0450010101 SIMULATOR A-C MEGAWATTS 8 of 8 Appendix C Facility:

IPEC UNIT2 Job Performance Measure Worksheet Task No: 0350040421 Form ES-C-1 Task Title: Perform a SG tube Leakrate Determination using 2-AOP-SG-1 2.3.14 Job Performance Measure RO Admin KIA

Reference:

RO-3.4 No: RC-1 -----Examinee:

NRC Examiner:

Facility Evaluator:

Date: Method of testing: Simulated Performance Actual Performance X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

• The plant is operating at 25% power

• Radiation Monitor 45 is in alert.

• The operating crew is responding in accordance with 2-AOP-SG-1 Steam Generator Tube Leak.

• Condenser air in leakage is 2. 7 SCFM

• RCS Total Gaseous Activity 1.53 X 1 o-2 IJci/cc

• Given the attached Leakrate Log Task Standard:

SG Tube Leakage calculated using 2-AOP-SG-1 Attachment 1 Required Materials:

Leakrate Log, Calculator, 2-AOP-SG-1 General

References:

2-AOP-SG-1 Attachment 1 and 2 1 of 10 Appendix C Job Performance Measure Worksheet Form ES-C-1 Initiating Cue: You are the BOP and the CRS has directed you to estimate the SG Tube Leakage, and determine sample frequency.

Time Critical Task: NA Validation Time: 15 Minutes 2 of 10 Appendix C Initial Conditions Form ES-C-1 Performance Information (Denote critical steps with a check mark --./) --./1. Performance Step: Standard:

Comment: --./2. Performance Step: Standard:

Comment: --./ 3. Performance Step: Standard:

Comment: --./4. Performance Step: Standard:

hour. Comment: Review data Candidate may use Attachment 1 or separate paper Calculate SG Tube Leakage for 1215 Determines SG Tube Leakage is 48.1 gpd Calculate SG Tube Leakage for 1230 Determines SG Tube Leakage is 50.9 gpd Calculate Delta Leakrate Determines leakrate has increased 5.3 gpd over last Appendix C Initial Conditions Performance Information (Denote critical steps with a check mark ...J) ...J 5. Performance Step: Determine sample frequency Form ES-C-1 Standard:

Determines sample frequency is every 15 minutes Comment: Terminating Cue: JPM Complete Steam Generator Tube Leak 2-AOP-SG-1 Rev. 11 Attachment 2 SG Leak Rate Data Sheet Page 41of 69 Page 1 of 1

• If leak rate is unknown, take data & determine LR every 15 minutes.

• If leak < 30 gpd, take data once every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

• If leak increases

30 gpd but < 75 gpd take data & determine LR every 15 minutes.

• If leak ;::: 30 gpd but < 75 gpd and stable for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (:::; 5 gpd increase in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />), take data every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

• If leak;::: 30 gpd but< 75 gpd and stable for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (:::; 10% increase in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />), take data at frequency for normal operation.

• If leak :2: 75 gpd, take data & determine LR every 15 minutes. DATE/ RX R-45 R-49 ATT 1 N-16 (gpd) Chemistry Grab Sample (gpd) TIME POWER (When 1/S) (When 1/S) CALC (When > 30% power) (When Chemistry provides) (When performed) (J..LCi/cc) (gpd) 21 22 23 24 21 22 23 24 1115 25% 2.39 E-05 45.4 gpd NA NA NA NA 1130 25% 2.40 E-05 45.6 gpd NA NA NA NA 1145 25% 2.46E-05 46.7 gpd NA NA NA NA 1200 25% 2.50E-05 47.5 gpd NA NA NA NA 1215 25% 2.53E-05 48.1_gpd NA NA NA NA 1230 25% 2.68E-05 50.9 gpd NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA -The difference between the two values is 5.3 gpd over the last hour. This is greater than a 5 gpd change in last hour and the frequency should be 15 minutes.

Appendix C Simulator Setup VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response:

Result: SAT or UNSAT Examiner's signature and date: ___________

_ Form ES-C-1 Initial Conditions:

• The plant is operating at 25% power

• Radiation Monitor 45 is in alert.

• The operating crew is responding in accordance with 2-AOP-SG-1 Steam Generator Tube Leak.

• Condenser air in leakage is 2. 7 SCFM

• RCS Gaseous Activity 1.53 X 1 o-2 IJci/cc

• Given the attached Leakrate Log Initiating Cue: You are the BOP and the CRS has directed you to estimate the SG Tube Leakage, and determine sample frequency.

Steam Generator Tube Leak Attachment 1 R-45 Estimated Leak Rate Page 1 of 1 NOTE 2-AOP-SG-1 Rev. 15 Page 39 of 69 For low levels of radioactivity as read on R-45, the estimated leak rate will be higher than actual. 1. Obtain the following A. RCS total gaseous activity (from Chemistry Data Book or WINCDMS)

B. Condenser air inleakage

______ SCFM C. R-45 reading ______

2. Calculate primary to secondary leak rate using the following formula per the following requirements:

• leak rate unstable or NOT positively identified as stable -every 15 minutes

• leak rate stable per Attachment 2 -Use Attachment 2 frequencies

____:_::X____1_::( X 1 0770 = (A ____ ) Primary to secondary leak rate (gpd)

Steam Generator Tube Leak 2-AOP-SG-1 Rev. 11 Attachment 2 SG Leak Rate Data Sheet Page 41of 69 Page 1 of 2

• If leak rate is unknown, take data & determine LR every 15 minutes.

• If leak < 30 gpd, take data once every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

• If leak increases

30 gpd but< 75 gpd take data & determine LR every 15 minutes.

• If leak;::: 30 gpd but < 75 gpd and stable for 1 5 gpd increase in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />), take data every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

• If leak ;::: 30 gpd but < 75 gpd and stable for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 1 0% increase in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />), take data at frequency for normal operation.

• If leak;::: 75 gpd, take data & determine LR every 15 minutes. DATE/ RX R-45 R-49 ATT 1 N-16 (gpd) Chemistry Grab Sample (gpd) TIME POWER (When 1/S) (When 1/S) CALC (When > 30% power) (When Chemistry provides) (When performed) (JlCi/cc) (gpd) 21 22 23 24 21 22 23 24 1115 25% 2.39 E-05 45.4 gpd NA NA NA NA 1130 25% 2.40 E-05 45.6 gpd NA NA NA NA 1145 25% 2.46E-05 46.7 gpd NA NA NA NA 1200 25% 2.50E-05 47.5 gpd NA NA NA NA 1215 25% 2.53E-05 NA NA NA NA 1230 25% 2.88E-05 NA NA NA NA NA NA NA NA NA NA NA NA -----NA _NA_ N6_ NA -'------__ --** --***-

Steam Generator Tube Leak 2-AOP-SG-1 Rev. 11 Attachment 2 SG Leak Rate Data Sheet Page 41of 69 Appendix C Job Performance Measure Worksheet Facility:

IPEC UNIT2 Task No: 2000650102 Task Title: Replace a Watchstander due to Illness KIA

Reference:

2.1.5 Job Performance Measure SR0-3.9 No: Examinee:

NRC Examiner:

Facility Evaluator:

Date: Method of testing: Simulated Performance Actual Performance Classroom X Simulator Plant READ TO THE EXAMINEE Form ES-C-1 SROAdmin C0-1 X I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1. Today is February 7 at 1900 2. Nick Chase is On Vacation 3. Ryan Pelkey called in sick yesterday and today. 4. Joe Gaspar came in for the night shift, has become ill, and was sent home at 18:30. Task Standard:

All of the ROs on the schedule have been evaluated and a determination made regarding who can be called in without violating requirements.

Required Materials:

Operations Schedule {Included)

General

References:

EN-OM-123 IP-SMM-OP-103 1 of 7 Appendix C Job Performance Measure Worksheet Form ES-C-1 Initiating Cue: Based on a review of the Ops schedule, Joe Varga has been called in to replace Joe Gaspar. Joe Varga estimates that he will arrive at 21:00. Review the attached schedule and results. Time Critical Task: No Validation Time: 30 Min 2 of 7 Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J) 1. Performance Step: Obtain correct procedures Standard:

Obtain EN-OM-123 IP-SMM-OP-1 03 CUE: Give candidates procedure and schedule with recommendations.

Comment: 2. Performance Step: Standard:

Comment: ..J 3. Performance Step: Standard:

Comment: Review Ops Schedule and procedural requirements Reviews Schedule and determines scheduling requirements Determines the following people can work the entire shift Joe Varga Mike Ruh Ross Rohla Gary Martin (Off vacation)

Pete Labuda (Off vacation) 3 of 7 Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark -Y) -Y 4. Performance Step: Standard:

Comment: -Y 5. Performance Step: Standard:

Comment: Determines that Mike Cosentino can NOT work the entire shift Mike would exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in 7 days if he worked his current schedule.

The following people cannot be called in because ... Mike Cosentino Exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in 7 days Dave Caffery Will exceed 72 in 7 days going forward Tom Alexander Scheduled for next Day Shift Eric Schimpf Scheduled for next Day Shift Roy Rowland Just completed Day Shift Fabian Ramos Just completed Day Shift Ed Bordas Worked 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> day shift not off for 10/8 hours Harry Primrose Worked 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> day shift not off for 10/8 hours Phil Mullen Worked 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> day shift not off for 10/8 hours Pete Campbell Will exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in 7 Days going forward 4 of 7 Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark -1) -1 6. Performance Step: Standard:

Comment: Determine Joe Varga arriving at 21 :00 is a violation of Tech Spec 5.2.2 Terminating Cue: JPM Complete 5 of 7 Appendix C Simulator Setup VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response:

Result: SAT or UNSAT Examiner's signature and date: ___________

_ 6 of 7 Form ES-C-1 Page 7 of 7 Initial Conditions:

5. Today is February 7 at 1900 6. Nick Chase is On Vacation 7. Ryan Pelkey called in sick yesterday and today. 8. Joe Gaspar has become ill and was sent home at 18:30. Initiating Cue: Based on a review of the Ops schedule, Joe Varga has been called in to replace Joe Gaspar. Joe Varga estimates that he will arrive at 21 :00. Review the attached schedule and results. File: 2000651602-1.doc Task Number: 200*065*01*02 Appendix C Facility:

IPEC UNIT2 Job Performance Measure Worksheet Task No: 0001250502 Form ES-C-1 Task Title: Review Reactor Vessel Venting Time Calculation Per FR-1.3, Attachment 1 KIA 2.1.25 Job Performance Measure SRO Admin

Reference:

RO-3.9 SRO-4.2 No: C0-2 -----Examinee:

NRC Examiner:

Facility Evaluator:

Date: Method of testing: Simulated Performance X Actual Performance Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

1. An event occurred 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ago that resulted in a YELLOW path condition on the Inventory Critical Safety Function Status Tree, FR-1.3. 2. The TSC has requested that the Reactor Vessel be vented in accordance with FR-1.3, Response to Voids in Reactor Vessel. 3. Given the following information:

Containment Pressure Containment Temperature Containment Hydrogen RCS Pressure 2.6 psig 172oF 3.2% 550 psig Task Standard:

Vessel Venting time is properly calculated.

Required Materials:

Calculator General

References:

2-FR-1.3 1 of 9 Appendix C Initiating Cue: Job Performance Measure Worksheet Form ES-C-1 You are the CRS and a spare RO has calculated Reactor Vessel Venting Time in accordance with FR-1.3 Attachment 1 and Figure FRI3-3. The SM has directed you to review the calculation.

Time Critical Task: No Validation Time: 20 min 2 of 9 Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark -1) 1. Performance Step: Obtain correct procedure Standard:

Comment: Obtains FR-1.3 It is possible for the candidate to determine that the Reactor Vessel cannot be vented with containment hydrogen at 3.2% before reviewing the calculation.

-1 2. Performance Step: Determine Containment Volume at STP (A) Standard:

A= 2.61 E6 X 17.3/14.7 X 492/632 A= 2.39 E6 Determines calculation is correct. Comment: -1 3. Performance Step: Determine Maximum Hydrogen volume that can be vented (B) Standard:

8 = (3.0-3.2 X 1.32 E6) 100 8 = -4.22 E4 Comment: There are two elements wrong with this step. 1. The number used for the calculation was transposed

2. In the body of the procedure, the Reactor Vessel cannot be vented if containment hydrogen is greater than 3%. Procedure Step 17 directs consultation with the TSC if containment hydrogen is> 3.0% Terminating Cue: JPM Complete 3 of 9 Appendix C Page 4 Form ES-C-1 4 of 9 Appendix C Simulator Setup VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response:

Result: SAT or UNSAT Examiner's signature and date: ___________

_ 5 of 9 Form ES-C-1 Initial Conditions:

1. An event occurred 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ago that resulted in a YELLOW path condition on the Inventory Critical Safety Function Status Tree, FR-1.3. 2. The TSC has requested that the Reactor Vessel be vented in accordance with FR-1.3, Response to Voids in Reactor Vessel. 4. Given the following information:

Containment Pressure Containment Temperature Containment Hydrogen RCS Pressure Initiating Cue: 2.6 psig 172°F 3.2% 550 psig You are the CRS and a spare RO has calculated Reactor Vessel Venting Time in accordance with FR-!.3 Attachment 1 and Figure FRI3-3. The SM has directed you to review the calculation.

Number: Title: Revision Num 2-FR-1.3 RESPONSE TO VOIDS IN REACTOR VESSEL REV. 2 ATTACHMENT 1 (Attachment page 1 c INSTRUCTIONS FOR DETERMINING VENTING TIME 1. Determine containment air volume at STP t1.3 A= 2.61 E6 cu ft X P x 492°R where: P (psia) and: T (0 R) 14.7 psia T Containment pressure (psig) + 14.7 Containment temperature

(°F) + 460 2. Determine maximum hydrogen volume that can be vented = B B = (3.0% Containment Hydrogen Concentration) x A 100% 3. Determine hydrogen flow rate as a function of RCS pressure 1500, a) Check RCS pressure. b) Using FIGURE FRI3-3, read hydrogen flow rate. 4. Calculate maximum venting time: Maximum venting time B c Maximum venting time _i.....,l

__ -END-Number: 2-IR-1.3 0 Title: RESPONSE TO VOIDS IN REACTOR VESSEL FIGURE FRI3-3 250 500 750 1000 125() 1500 1750 2000 RCS ?ressure (JSIGl FIGURE FR13-3. UYDROCEN FLOWRATE VERSUS RCS PRESSURE -END-l9 of 20 Revision Number: REV. 2 2250 2500

Appendix C Facility:

IPEC UNIT2 Job Performance Measure Worksheet Task No: 0430010321 Form ES-C-1 Task Title: Demonstrate Proficiency in use of Generator Capability Curve 2.2.41 KIA

Reference:

RO -3.4 SRO -3.8 Job Performance Measure No: Examinee:

Facility Evaluator:

Method of testing: Simulated Performance Classroom X READ TO THE EXAMINEE X NRC Examiner:

Date: Actual Performance Simulator Plant SRO Admin EC-1 I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

• Reactor is at 100% power, equilibrium Xenon, EOL

• Main Generator Hydrogen makeup is not available

• Machine Gas High Low Pressure alarm is up on the TG Monitor Panel

• The given conditions have been stable for the last hour. Task Standard:

MVAR adjustment accurately evaluated and acceptable recommendation identified.

Required Materials:

Ruler General

References:

Graph EL-1 2-ARP-042, G. E. Unit Aux Board GE Generator 2-SOP-26.2 Hydrogen and Carbon Dioxide to Main Generator Initiating Cue: You are the CRS, evaluate the given conditions and provide recommendation and explanation.

Time Critical Task: No 1 of 9 Appendix C Validation Time: 15 Job Performance Measure Worksheet 2 of 9 Form ES-C-1 Appendix C Page 3 Performance Information (Denote critical steps with a check mark >l) 1. Performance Step: Obtain correct procedure Standard:

Obtains Graph-EL-1 Comment: >l 2. Performance Step: Obtain current generator gas pressure Standard:

Determines Gas Pressure is 45 psig +/- 1 psig Comment: Form ES-C-1 >l 3. Performance Step: Obtain current generator gross megawatts Standard:

Determines 950 +/- 5 MWe Comment: >l 4. Performance Step: Obtain current MVAR load Standard:

Determine MVAR load is 460 Leading Comment: 3 of 9 Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J) ...J 5. Performance Step: Evaluate conditions using Graph EL-1 Standard:

Determines MVAR Loading is outside allowable on Graph EL-1 Comment: ...J 6. Performance Step: Standard:

Comment: Make acceptable recommendation Based on given information, raising Machine Gas Pressure is NOT acceptable Reducing value of Leading VARS, until point on EL-1 is above URAL 22KV line, is acceptable.

Reduce Turbine Load, until point on EL-1 is above URAL 22KV line, is acceptable Terminating Cue: JPM Complete 4 of 9 Appendix C L1900 CJ @_QQJ ::5 J[4ooJ (/) a:: [2QPJ 0 0 0 0 URAL 22KV [t?_QQ] oA _;:..r -cfr t, Page 5 INDIAN POINT 2 ATB 4 POLE 1,439,200 KVA.1800 RPM. 22000 VOLTS .81 PF. .58 SCR. 75 PSIG HYDROGEN PRESSURE.

535 VOLTS EXCITATION

.-1 0.6Q PF_: URAL' -""' .--KLF ' . "0.90 PF *r--r Form ES-C-1 SSL 0.95

.1"1 --.U '* LLLJ-CURVE AB LIMITED BY FIELD HEATING CURVE BC LIMITED BY ARMATURE HEATING CURVE CD LIMITED BY ARMATURE CORE END HEATING ? DATE It/ {C,b APPROVED DATE Estimated C:>pi'tbil i ty Cnrvc s . f>:-'<J.*_

.. 48]1!/\5 32 5 of 9 EL-1 Rev. 4 .

Appendix C Simulator Setup VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response:

Result: SAT or UNSAT Examiner's signature and date: ___________

_ 6 of 9 Form ES-C-1 JPM-0450010101 SIMULATOR Initial Conditions:

• Reactor is at 100% power, equilibrium Xenon, EOL

• Main Generator Hydrogen makeup is not available

• Machine Gas High Low Pressure alarm is up on the TG Monitor Panel

• The given conditions have been stable for the last hour. Initiating Cue: You are the CRS, evaluate the given conditions and provide recommendation and explanation.

7 of 9 JPM-045001 0101 OUT 400 \ 600 t il, E (-=i A\/A F.*:=: I "-"I I I I I *-8 of 9 SIMULATOR H2 PF:EE:E:UF:E JPM-0450010101 SIMULATOR A-C MEGAWATTS 9 of 9 Appendix C Facility:

IPEC UNIT2 Job Performance Measure Worksheet Task No: 1500010522 Form ES-C-1 Task Title: Classify Emergency Events Requiring Emergency Plan Implementation 2.4.38 KIA

Reference:

SRO-4.4 Job Performance Measure No: -----------------

Examinee:

Facility Evaluator:

Method of testing: Simulated Performance Classroom X READ TO THE EXAMINEE NRC Examiner:

Date: Actual Performance Simulator Plant SROADMIN EP-1 X I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

1 of 7 Appendix C Initial Conditions:

Job Performance Measure Worksheet Form ES-C-1 Indian Point Energy Center Unit 2 was operating at 100% and has been there for 100 days. 24 Containment Fan Cooler Unit is inoperable for circuit breaker maintenance.

Unit 3 is at 100% power; no issues. Safety Injection automatically initiated due to a large break LOCA inside containment.

The following plant conditions exist:

• The team is responding per E-0, Reactor Trip or Safety Injection.

• Containment Isolation Phase A and B have been confirmed.

• 21 and 22 Containment Spray Pumps failed to start and attempts to start the pumps were unsuccessful.

• 24 Containment Fan Cooler Unit remains unavailable

• RCS Subcooling is 0.0°F

• Containment Pressure is 38 psig and stable

• R-25 is reading 19 Rlhr and R-26 is reading 21 Rlhr

• RVLIS, Full Range is reading 44% Meteorological Conditions:

• Wind Speed: 3.5 meters/second

• Wind Direction:

• Stability Class: 120 degrees @ 10 meters c I will perform duties of Offsite Communicator.

Task Standard:

Proper E-Pian Classification and Part 1 form properly filled out. Required Materials:

EAL Wall Chart. General

References:

IP-EP-115 IP-EP-120

IP-EP-210 IP-EP-410 Initiating Cue: You are the CRS and the SM is unable to get to the control room. Classify the event and complete the Radiological Emergency Data Form. Time Critical Task: Yes (Declare event in 15 minutes and Initiate notification within 15 minutes of declaration) 2 of 7 Appendix C Validation Time: 30 min Job Performance Measure Worksheet 3 of 7 Form ES-C-1 Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark -1) 1. Performance Step: Standard:

Comment: -1 2. Performance Step: Standard:

Obtain correct procedure IP-EP-120 orEAL chart Give candidate Wall Chart Evaluate Initiating Cues to determine a GE classification applies. Determine EAL FG1.1 applies Fuel Clad -C.3 Loss RCS -D.2 Loss CNMT-D.7 Potential Loss Comment: This action is time critical Mark Time when Declaration is made. -1 3. Performance Step: Standard:

Complete "New York State Radiological Emergency Data Form, Part 1" Complete IP-EP-115 Comment: Critical elements on Part 1 form are marked with an asterisk -1 4. Performance Step: Standard:

Direct Communicator to initiate notification.

Hand completed Part 1 form to evaluator and direct them to initiate notification.

CUE: Acknowledge direction to initiate notification.

Comment: This action is time critical.

Terminating Cue: JPM Complete 4 of 7 Appendix C 1. Page 5 Nevv York State Indian Pornt Energy Center RADIOLOGICfl.L EMERGEt<CY DATA FORM-PART i Form ES-C-1 Notification

1. j_ Reactor Status ACTUAL Efv1ERGENCY at UNIT 3 BOTH UNITS Unit 2 perationa!

_ < . .::L-Thts is an: ----(Date(T od

-'SM!l.(24 hr clock) hutdown rational)

• l 1 (Date) 1 ShWdown

---

I. 2. I' The.Emeraency A. Unusual Event B. Alert Classification is r;:-1 ! ---------

Emergency E Emergency Terminated 1 1 I! This Emergency Classification declared 0.1: 'T QdO>,V f: at tJ . . rqate) i 3. EAL# f6-f. I *. lb'5"S ot .5*

__ _ (Ttme) _______ _ (24 hr clock) C. Site Area Emergency

}c.lfv,J los'> --tktrc.\

4. B. Release BELOW Federal limits To Atmosphere To Water To Atmosphere To '/Vater D. Unmonitored release requiring evaluation Wind Direction: (From) __ 1...::(}::._:..0

_______ Degrees at elevation 10 meters 1 1 7* I Stability

.. __

.. --.--.--.. -.... -... ====-.. --1_1! . 8. I i,

• The fot:owir.g Protective Actions are recom'llended to be rr1plemenled as soon as practicable I A. NO NEED for PROTECTIVE ACTIONS outside the site boundary @vACUATE and IMPLEMENT the Kl PLAN for the following Sectors C. SHELTER-IN-PLACE and IMPLEMENT the Ki PLAN for :he following Sectors 2 miles around 5-miles cownwtnd*

In !he follOWing Sectors 6) (!) (f) 4 5 '3 e 9 'c >J 11 12 .! 1.5 8 2 m1les arounc 1 0-rnl\es downwin-::1 In the 'ollow<r,g Sectors: : 2 3 4 6 8 9 10 11 12 13 14 15 16 All remaining

.1\reas MONITOR the EMERGENCY ALERT SYSTEM 9. Reported by*** Communicator: (Communicatot s /\'arne) 10. Emergency Director Approval:

---.---*---------------

DateiTrrne

__ -------(iJirectot s Na:r.*e} Page *t of I Form EP-1. Rev 4 5 of7 Appendix C Simulator Setup VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response:

Result: SAT or UNSAT Examiner's signature and date: ___________

_ 6 of 7 Form ES-C-1 Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

Indian Point Energy Center Unit 2 was operating at 100% and has been there for 100 days. 24 Containment Fan Cooler Unit is inoperable for circuit breaker maintenance.

Unit 3 is at 100% power; no issues. The events below occurred today approximately 5 minutes ago. Safety Injection automatically initiated due to a large break LOCA inside containment.

The following plant conditions exist:

• The team is responding per E-0, Reactor Trip or Safety Injection.

• Containment Isolation Phase A and B have been confirmed.

• 21 and 22 Containment Spray Pumps failed to start and attempts to start the pumps were unsuccessful.

• 24 Containment Fan Cooler Unit remains unavailable

• RCS Subcooling is 0.0°F

• Containment Pressure is 38 psig and stable

• R-25 is reading 19 Rlhr and R-26 is reading 21 Rlhr

• RVLIS, Full Range is reading 44% Meteorological Conditions:

• Wind Speed:

• Wind Direction:

• Stability Class: 3.5 meters/second 120 degrees @ 10 meters c I will perform duties of Offsite Communicator.

Initiating Cue: You are the CRS and the SM is unable to get to the control room. Classify the event and complete the Radiological Emergency Data Form.

Appendix C Facility:

IPEC UNIT2 Job Performance Measure Worksheet Task No: 0350060402 Form ES-C-1 Task Title: Review a SG tube Leakrate Determination using 2-AOP-SG-1 KIA

Reference:

3_8 Performance Measure Examinee:

NRC Examiner:

Facility Evaluator:

Date: Method of testing: Simulated Performance Actual Performance X Classroom X Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

• The plant is operating at 25% power

• Radiation Monitor 45 is in alert.

• The operating crew is responding in accordance with 2-AOP-SG-1 Steam Generator Tube Leak.

• Condenser air in leakage is 2.7 SCFM

• RCS Total Gaseous Activity 1.53 X 10-2 IJci/cc

• Given the attached Leakrate Log Task Standard:

SG Tube Leakage calculation reviewed using 2-AOP-SG-1 Attachment 1 and 2 Required Materials:

Leakrate Log 1 of 9 Appendix C Job Performance Measure Worksheet General

References:

2-AOP-SG-1 Attachment 1 and 2 Form ES-C-1 Initiating Cue: You are the CRS and the SM has directed you to review the estimated SG Tube Leakage, and determine sample frequency.

Time Critical Task: NA Validation Time: 15 Minutes 2 of9 Appendix C Initial Conditions Form ES-C-1 Performance Information (Denote critical steps with a check mark >f) 1. Performance Step: Standard:

Comment: >12. Performance Step: Standard:

Comment: v 3. Performance Step: Standard:

Comment: Check Calculations Candidate may use Attachment 1 or separate paper Candidate should determine that the calculations for 1115 through 1215 are correct. Check Calculation for 1230 Determines calculation is incorrect.

The correct value is 60.81 gpd Check Calculation for 1245 Determines calculation is incorrect.

The correct value is 76.02 gpd In addition to the calculation being incorrect, The CRS should recognize that the leakrate is > 75 gpd and the plant should be placed in MODE 3 within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (procedure step 4.63).

Appendix C Initial Conditions Form ES-C-1 Performance Information (Denote critical steps with a check mark-/) -1 4. Performance Step: Standard:

Comment: -! 5. Performance Step: Standard:

Comment: 6. Performance Step: Standard:

Comment: Calculate SG Tube Leakage change over last hour Determines SG Tube Leakage has increased by:

• 13.3 gpd from 1130 to 1230

• 27.9 from 1145 to 1245. Calculate SG Tube Leakage change over last hour Determines SG Tube Leakage has increased by 13.3 gpd from 1130 to 1230. Review Sample frequency recommendation by RO Identify Sample frequency recommendation by RO is correct Terminating Cue: JPM Complete Steam Generator Tube Leak Attachment 2 SG Leak Rate Data Sheet Page 1 of 1

• If leak rate is unknown, take data & determine LR every 15 minutes.

• If leak < 30 gpd, take data once every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

• If leak increases 30 gpd but< 75 gpd take data & determine LR every 15 minutes. 2-AOP-SG-1 Page 41of69

• If leak 30 gpd but < 75 gpd and stable for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (:::; 5 gpd increase in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />), take data every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Rev. 11

• If 30 gpd but < 75 gpd and stable for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (:::; 10% increase in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />), take data at frequency for normal operation.

• If 75 gpd, take data & determine LR every 15 minutes. DATE/ RX R-45 R-49 ATT 1 N-16 (gpd) TIME POWER (When 1/S) (When 1/S) CALC (When > 30% power) (When performed) (uCi/cc) (gpd) 21 22 23 1115 25% 2.46E-05 46.75 NA NA NA 1130 25% 2.50E-05 47.51 NA NA NA 1145 25% 2.53E-05 48.08 NA NA NA 1200 25% 2.68E-05 50.93 NA NA NA 1215 25% 2.90E-05 55.11 NA NA NA 1230 25% 3.20E-05 60.81 58.81 NA NA NA 1245 25% 4.00E-05 76.02 65.02 NA NA NA NA NA NA NA NA NA The calculated value for 1230 is incorrect.

The correct value should be 60.81 gpd. The calculated value for 1245 is incorrect.

The correct value should be 76.02 gpd. 24 NA NA NA NA NA NA NA NA NA Chemistry Grab Sample (gpd) (When Chemistry provides) 21 22 23 24 The leakrate has exceeded 75 gpd and the plant should be placed in MODE 3 within an additional 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Appendix C Simulator Setup VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response:

Result: SAT or UNSAT Examiner's signature and date: ___________

_ Form ES-C-1 Initial Conditions:

• The plant is operating at 25% power

• Radiation Monitor 45 is in alert.

• The operating crew is responding in accordance with 2-AOP-SG-1 Steam Generator Tube Leak.

• Condenser air in leakage is 2. 7 SCFM

• RCS Total Gaseous Activity 1.53 X 10-2 IJci/cc

• Given the attached Leakrate Log Initiating Cue: You are the CRS and the SM has directed you to review the estimated SG Tube Leakage, and determine sample frequency.

Steam Generator Tube Leak Page 1 of 1 NOTE 2-AOP-SG-1 Rev. 15 Page 39 of 69 For low levels of radioactivity as read on R-45, the estimated leak rate will be higher than actual. 1 . Obtain the following A. RCS total gaseous activity (from Chemistry Data Book or WINCDMS) ______

B. Condenser air inleakage

______ SCFM C. R-45 reading ______

2. Calculate primary to secondary leak rate using the following formula per the following requirements:

• leak rate unstable or NOT positively identified as stable -every 15 minutes

• leak rate stable per Attachment 2 -Use Attachment 2 frequencies

....J.["-=(B'"===='-) X 1 0770 = (A, ____ ) Primary to secondary leak rate (gpd)

Steam Generator Tube Leak Attachment 2 SG Leak Rate Data Sheet Page 1 of 1

• If leak rate is unknown, take data & determine LR every 15 minutes.

• If leak< 30 gpd, take data once every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

• If leak increases 30 gpd but < 75 gpd take data & determine LR every 15 minutes. 2-AOP-SG-1 Page 41of 69

• If 30 gpd but < 75 gpd and stable for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />(::;;

5 gpd increase in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />), take data every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Rev. 15

• If 30 gpd but < 75 gpd and stable for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (::;; 10% increase in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />), take data at frequency for normal operation.

• If 75 gpd, take data & determine LR every 15 minutes. DATE/ RX R-45 R-49 ATT 1 N-16 (gpd) Chemistry Grab Sample (gpd) TIME POWER (When 1/S) (When 1/S) CALC (When > 30% power) (When Chemistry provides) (When performed)

(!lCilcc) (gpd) 21 22 23 24 21 22 23 24 1115 25% 2.46E-05 46.75 NA NA NA NA 1130 25% 2.50E-05 47.51 NA NA NA NA 1145 25% 2.53E-05 48.08 NA NA NA NA 1200 25% 2.68E-05 50.93 NA NA NA NA 1215 25% 2.90E-05 55.11 NA NA NA NA 1230 25% 3.20E-05 58.81 NA NA NA NA 1245 25% 4.00E-05 65.02 NA NA NA NA NA NA NA NA NA NA NA NA Based on calculated leakrate sample frequency should remain every 15 minutes.

Appendix C Facility:

IPEC UNIT2 Job Performance Measure Worksheet Task No: 0040420421 Task Title: Emergency Borate the RCS 004000A4.18 Job Performance Measure KIA

Reference:

RO-4.3 SRO-4.1 No: Examinee:

Facility Evaluator:

Method of testing: Simulated Performance Classroom READ TO THE EXAMINEE NRC Examiner:

Date: Actual Performance Simulator X Plant Form ES-C-1 SimA X I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

• A Reactor Trip has occurred.

• The Crew is performing ES-0.1, Reactor Trip Response

• At step 6 the crew determined 4 Control Rods did not fully insert on the trip

• RCS Tavg is 54rF.

• RCS Boron is 1100 PPM, at 100 EFPD. Task Standard:

The correct amount of boron addition determined and boration has been commenced using MOV-333 Boration Path. Required Materials:

2-SOP-3.2 General

References:

2-SOP-3.2 Initiating Cue: You are the ATC and the CRS has directed you to initiate Emergency Boration in accordance with 2-SOP-3.2 Time Critical Task: No Validation Time: 15 Min 11/18/2013 Unit 2 NRC 2014 Exam Date 02/10/2014 Performance Information (Denote critical steps with a check mark --J) 1 . Performance Step: Standard:

Comment: 2. Performance Step: Standard:

Comment: Obtain Correct Procedure Obtains 2-SOP-3.2 and Reviews Precautions and Limitations Observe NOTES before Step 4.6.5 Reviews NOTES 11/18/2013 Unit 2 NRC 2014 Exam Date 02/1 0/2014 Performance Information (Denote critical steps with a check mark --.1) -.J 3. Performance Step: Determine RCS Boron Concentration must be increased 709 ppm Standard:

1230 Minimum Shutdown Boron Concentration 11 00 Current Boron Concentration 130 ppm to achieve Min Shutdown Boron Cone. 193 ppm increase for each rod> 1 (3 rods) 193 ppm per rod X three rods = 579 579 + 130 = 709 ppm increase boron concentration required.

Using Attachment 1 approximately 2302 gallons of . Boric Acid is required Using 3.21 gal/ppm, approximately 2276 gallons of Boric Acid is required Comment: At some point during the performance of this JPM the candidate must determine that between 2275 and 2305 gallons of boric acid are required.

The candidate may wait until boric acid addition has commenced to calculate the amount of boric acid necessary.

4. Performance Step: Observe NOTES before Step 4.6.12 Standard:

Reviews NOTES Comment: 11/18/2013 Unit 2 NRC 2014 Exam Date 02/10/2014 Performance Information (Denote critical steps with a check mark -1) 5. Performance Step: Standard:

Comment: Step 6.5.12 6. Performance Step: Standard:

Comment: 7. Performance Step: Standard:

Initiate boration using the desired method Normal Boration is identified as the Preferred method, and it is expected that the candidate will start with this method. Go To Attachment 3 Observe Caution before Step 1.0 of Attachment 3 Review CAUTION Place Makeup Mode Selector Switch to BORATE Rotate switch to BORATE Comment: Step 1 .1 of Attachment 3 Panel FCF 8. Performance Step: Set Boric Acid Integrator to 600 gallons Standard:

Set thumbwheels to 600.0 Comment: Step 1.2 of Attachment 3 Panel FBF 11/18/2013 Unit 2 NRC 2014 Exam Date 02110/2014 Performance Information (Denote critical steps with a check mark -1) 9. Performance Step: Place Makeup Control Switch to START Standard:

Rotate switch to START position Observe boration does NOT begin. Return to Step 4. 6. 12 Comment: Step 1.3 of Attachment 3 Panel FCF Candidate may make several attempts to start Boration.

10. Performance Step: Select Alternate Method for Emergency Boration Standard:

Candidate can select either MOV-333 Boration Path or' RWST Boration Path. If candidate selects MOV-333 go to JPM Step 14 Comment: Only MOV-333 path will function.

,,* Place LCV-112A, VCT !nlet to Divert Standard:

Rotate Switch to DIVERT Comment: Step 1.1 of Attachment 4 Initiating Using 1128 Boration Panel SFF 12. Performance Step: Open LCV-1128 Emergency RWST Makeup Stop Standard:

Rotate Switch to OPE:N . Observe valve does NOT OPEN Comment: Step 1 .2 qf 4 Initiating Boration Using 1128 8oration Panel SFF . ' . 11/18/2013 Unit 2 NRC 2014 Exam Date 02/10/2014 Performance Information (Denote critical steps with a check mark -1) .13. Performance Step: Return to Step 4.6.12 Select Alternate Method for Emergency Boration Standard:

Go to Attachment 5, Mov.:.333 So ration Path Comment: 14. Performance Step: *Observe CAUTION before step 1.1 Standard: . Review CAUTION Comment: ..J 15. Performance Step: NOTE in service BAST level

.:., . * .. * ... : * .. : **,.... . . .. . . ... Observe BAST le"el at approximately 63% Comment: Step 1.1 ()f Attachment 5, Panel SFF Standard:.

Rotate Switch to OPEN* Observe Valve OPEN

• Comment: Step 1.2 of Attachment 5, Panel. SFF ..J 17.

Place BOTH Boric Transfer Pumps in FAST Standard:.

Rotate switches to FAST Obse.Ve Pumps OFF lights lit)

Comment: .. Step 1*.3 of}\ttachment 5 Pumps ")'ill stop.(green light on)when switch isretated to the F}\ST position 11/18/2013 Unit 2 NRC 2014 Exam Date 02/10/2014 Performance Information (Denote critical steps with a check mark -/) -1 .18. Performance Step: Restart BOTH Boric Acid Transfer Pumps Standard:

Rotate Switches to START Observe Red Light on for Fast Speed Comment: Step 1.4 of Attachment 5 Pumps will start in Fast Speed (Red Fast Light ON) Panel FCF ...J 19. Performance Step: Place operating Charging Pump(s) control in MANUAL AND RAISE to maximum speed Place Auto-Manual transfer switch to MANUAL and rotate potentiometer to maximum output (speed) Comment: Step .. 1.S .. pf Attachment 5, Pallet I7BF 20. Performance Step:

• ADJUST maintain RCP Seal Injection

<: between 6 and.12 gpm Standard:

Rotate HVC-142 in'9pen direction to maintain6>-

12 gpm seal injectionflow Co11Jment Step 1.6 of Attachment 5, Panel SFF 11/18/2013 Unit 2 NRC 2014 Exam Date 02/10/2014 Performance Information (Denote critical steps with a check mark --1) .V 21. Performance Step: Observe NOTES before Step 1. 7 Standard:

Reviews NOTES Comment:'

Candidate should determine BAST must be lowered by 32-33% (depending on method used to determine amount of Boric Acid to add) to achieve proper boron concentration.

22. Performaqce Step: Verify level lowering in the in .service BAST Standard:

Observes Level Lowering Comment: CUE: Inform candidate that the in service BAST has lowered 33% Standard: .:. ' ," , RQtate .switch to .CLOSE. Comment.':.Step 2.1 Attachment 5, Panel SFF -. . -.* . 24. Performance Step: Return both Boric Acid Transfer Pumps to SLOW Standard:

Rotate switches to slow speed Candidate should observe Red Slow indicating light ON Comment: Step 2.2 of Attachment 5, For Time consideration the JPM can be Terminated at this point. There are no additional critical steps 11/18/2013 Unit 2 NRC 2014 Exam Date 02/10/2014 Performance Information (Denote critical steps with a check mark -Y) 25. Performance Step: Dispatch NPO to OPEN the immediately CLOSE 330, Boric Acid Blender Primary Water Bypass Stop to flush line 208 Standard:

Contact Nuc Side NPO and direct to OPEN then CLOSE 330. Comment: CUE: Acknowledge request as NPO and report valve has been OPENED and CLOSED. 26. Performance Step: Place running Charging Pump speed controller in AUTO Standard:

• Place Charging Pump Speed Controller in MAN-BAL

• ADJUST the Bias Knob until the deviation meter indicates zero

• Place Charging Pump speed controller to AUTO

• Slowly turn the Bias Knob back to zero Comment: 27. Performance Step: ADJUST HCV-142 to maintain RCP Seals between 6 and 12 gpm Standard:

Rotate potentiometer in close direction as necessary Comment: 11/18/2013 Unit 2 NRC 2014 Exam Date 02/10/2014 Performance Information (Denote critical steps with a check mark .V) 28. Performance Step: Standard:

Direct Chemistry to obtain RCS Boron Sample. Contact Chemistry and direct them to obtain RCS Boron Sample Comment: CUE Acknowledge request as Chemist 29. Performance Step: Standard:

Comment: When Chemistry reports Boron Concentration, the set FIC-11 0, Boric Acid Control for the new Boron Concentration per Graph-CVCS-1 B Sets FIC-11 0 to proper setting Terminating Cue: JPM Complete 11/18/2013 Appendix C Page 11 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response:

Result: SAT or UNSAT Form ES-C-1 Examiner's signature and date: ________________

_ 11/18/2013 Appendix C Simulator Setup Form ES-C-1 Reset the Simulator to any 100% power IC Insert the following Malfunctions for Stuck Rods Rod D-4 UNTRIP Rod H-12 UNTRIP Rod M-4 UNTRIP Rod F14 UNTRIP LCV-1128 CLOSE POS MAL-CFR001 A MAL-CFR001AJ MAL-CFR001 D MAL-CRF001 AX SWI-CVC033A SWI-CVC048 MAKEUP MODE SELECTOR SWITCH AUTO MAKEUP Trip the reactor and allow the plant to stabilize.

Freeze the Simulator Take a snapshot if JPM is to be used more than once. 11/18/2013 Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• A Reactor Trip has occurred.

• The Crew is performing ES-0.1, Reactor Trip Response

• At step 6 the crew determined 4 Control Rods did not fully insert on the trip

• RCS Tavg is 54rF.

• RCS Boron is 1100 PPM, at 100 EFPD. Initiating Cue: You are the ATC and the CRS has directed you to initiate Emergency Boration in accordance with 2-SOP-3.2 Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility:

IPEC UNIT2 Task No: 0000390521 Task Title: Perform the Required Action to Align the Sl System for Recirculation during Transfer to Cold Leg Recirculation KIA

Reference:

000011 A 1 .11 Job Performance Measure No: Sim B SRO -4.2 RO -4.2 Examinee:

Facility Evaluator:

Method of testing: Simulated Performance Classroom READ TO THE EXAMINEE NRC Examiner:

Date: Actual Performance Simulator X Plant X I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

• A large break LOCA has occurred.

• Safety Injection has been RESET in accordance with E-1, Loss of Reactor or Secondary coolant.

• The RWST level has decreased to 9.24 feet and the CRS has directed you to transfer to cold leg recirculation in accordance with ES-1.3

• All steps up through and including step 18 of E-1 have been completed.

• FSB Ventilation was previously shutdown

• The service water system is aligned for three header operation.

• The first 5 steps of ES-1.3 have been completed.

Task Standard:

Cold leg recirculation flow is established and the core is adequately cooled (i.e., adequate Recirc flow). Required Materials:

None General

References:

2-ES-1.3, Transfer to Cold Leg Recirculation 1 of 12 Appendix C Initiating Cue: Job Performance Measure Worksheet Form ES-C-1 You are the BOP and the CRS has directed you to align the plant for cold leg Recirc in accordance with ES-1.3, Transfer to Cold Leg Recirculation, commencing at step 6 up to and including the determination that adequate low head recirculation flow has been established.

Time Critical Task: No Validation Time: 20 Minutes 2 of 12 Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J) 1. Performance Step: Standard:

Comment: ...J 2. Performance Step: Standard:

Comment: Step 6 3. Performance Step: Standard:

Obtain Correct Procedure Obtain current revision of 2-ES-1.3 Place Safety Injection Recirc Switches 1 and 3 to ON Rotate Recirc Switches 1 and 3 to ON position Check 22 51 Pump Stopped Panel SBF-2 Check 21 Containment Spray Pump Stopped Panel SBF-1 Check RHR Pumps Both Stopped Panel SBF-1 Align Service Water as follows: Check Service Water Aligned for 3 header ops. Verify SWN-4 & 5 Closed Three header ops was given in Initial Conditions.

Contact Conventional NPO to verify SWN-4 & 5 Closed CUE: SWN-4 and 5 are closed. Comment: Step 7 3 of 12 Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J) 4. Performance Step: Observe NOTE before Step 8 Standard:

Reviews NOTE before Step 8 Comment: 5. Performance Step: Place Safety Injection Recirc Switch 2 to ON Standard:

Rotate Switch to ON position Comment: Step 8 Check one service water pump supplying Essential Header Yes Check 3 CCW Pumps Running Yes Stop 23 CCW Pump Panel SGF Check Function Complete Light LIT YES Panel SBF-1 Only Recirc Switch reposition is critical 6. Performance Step: Verify One RHR Heat Exchange Isolated Check 822A & B Open Check 746 & 747 Open Close 746 Standard:

Observes 822A & B Open Panel SBF-1 Check 746 & 747 Open Panel SBF-1 Rotate Switch for 7 46 to Close Panel Comment: Only action to Close 746 is critical.

4 of 12 Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark -/) 7. Performance Step: Standard:

Align Safety Injection Recirc Switch 4 as follows Manually Start 21 Recirculation Pump Rotate Switch to Start Position Observe Pump Not Running Comment: Step 10 Panel SBF-1 5 of 12 Appendix C Page 6 Performance Information (Denote critical steps with a check mark>/) 6 of 12 Form ES-C-1 Appendix C Page 7 Performance Information (Denote critical steps with a check mark ..J) 7 of 12 Form ES-C-1 Appendix C Page 8 Performance Information (Denote critical steps with a check mark -/) Standard:

Returns to Step 11 Comment: 8 of 12 Form ES-C-1 Appendix C Page 9 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J) 22. Performance Step: Determine if Adequate Low Head Recirculation Flow has been established Check ALL Flow meters (946A-D) Greater than 500 gpm Standard:

Observes all 956 indicators greater than 500 gpm Comment: Step 11 Panel SBF-2 Terminating Cue: JPM Complete 9 of 12 Appendix C Page 10 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response:

Result: SAT or UNSAT Examiner's signature and date: ___________

_ 10 of 12 Form ES-C-1 Appendix C Simulator Setup Reset Simulator to any 100% IC Insert Malfunction MAL-RCS-005A Perform the actions of E-0 including Attachment

1. Perform the first 18 steps of E-1. Perform the first 5 steps of ES-1.3 Allow RWST level to decrease to 9.24 feet. Ensure both RWST Low Low Level Alarms are up. Form ES-C-1 Ensure Three Header Operations Placard is in place at the service water header selector switch. 11 of 12 Perform the Required Actions to Align the Sl System for Recirculation during Transfer to Cold Leg Recirculation (Manual Start of 21 Recirc Pump) Page 12 of 7 Initial Conditions:

• A large break LOCA has occurred.

• Safety Injection has been RESET in accordance with E-1, Loss of Reactor or Secondary coolant.

• The RWST level has decreased to 9.24 feet and the CRS has directed you to transfer to cold leg recirculation in accordance with ES-1.3

• All steps up through and including step 18 of E-1 have been completed.

• FSB Ventilation was previously shutdown

• The service water system is aligned for three header operation.

• The first 5 steps of ES-1.3 have been completed.

Initiating Cue: You are the BOP and the CRS has directed you to align the plant for cold leg Recirc in accordance with ES-1.3, Transfer to Cold Leg Recirculation, commencing at step 6 up to and including the determination that adequate low head recirculation flow has been established.

File: (3000121601-1.doc)

Difficulty:

3 ES-1.3 Time: 20 minutes Appendix C Job Performance Measure Worksheet Facility:

IPEC UNIT2 Task No: 0100180421 Task Title: Respond to a Pressurizer Low Pressure Alarm 000027A101 Job Performance Measure KIA

Reference:

RO-4.0 SR0-3.9 No: Examinee:

NRC Examiner:

Facility Evaluator:

Date: Method of testing: Simulated Performance Actual Performance Classroom Simulator X Plant ------READ TO THE EXAMINEE Form ES-C-1 SimC X -----I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

• The plant is operating at 1 00% power

• No Equipment is Out of Service Task Standard:

Pressurizer pressure stable, reactor tripped with 23, 24 and 21or 22 RCPs tripped. Required Materials:

None General

References:

2-ARP-SAF Initiating Cue: You are the ATC. Respond to changing plant conditions or events. Time Critical Task: No Validation Time: 15 minutes 1 of 7 Appendix C Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark >!) NOTE: Candidate may diagnose failed open Spray Valve at any time during this JPM. The exact order of actions before the Reactor Trip is not important, and they may be performed in any order. The reactor must be tripped before the Reactor Coolant Pumps are tripped. 1. Performance Step: Standard:

Acknowledge Pressurizer Low Pressure 2185 psig Alarm and refer to ARP Observe alarm and retrieve ARP from holder Comment: Candidate may recognize pressure lowering before alarm annunciates.

2. Performance Step: Compare redundant Pressurizer Pressure indicators Standard:

Observe pressure decreasing on all 4 channels Comment: ARP Step 3.1 3. Performance Step: Verify Heaters and Sprays are operating properly.

Standard:

Observe Heaters energized and one spray valve opened Comment: ARP Step 3.2 Candidate may diagnose stuck open spray valve at this time 4. Performance Step: Standard:

Comment: ARP Step 3.3 Evaluate and perform the following:

• If pressure reduction is due to a rapid temperature reduction OR rapid load increase then go to appropriate procedure.

Determine pressure reduction NOT due to temperature or load change 2 of 7 Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark >/) 5. Performance Step: Standard:

Comment: ARP Step 3.4 IF the Pressurizer heaters or sprays are NOT operating properly, THEN PLACE Pressurizer Pressure Master Controller in MANUAL and ATTEMPT to establish RCS pressure at 2235 psig. Transfer controller to Manual (T-bar up) and output adjusted to Heaters (Left of null) 3 of 7 Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark --J) Go To E-0 Reactor Trip or Safety Injection Standard:

Observes conditions to verify reactor tripped Comment: ARP Step 3.5.2.4 Terminating Cue: JPM Complete NOTE: If a Safety Injection occurs during the performance of this JPM, it is likely a failure. The candidate's progress through the required actions will determine actual pass or fail grade. 4 of 7 Appendix C Page 5 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response:

Result: SAT or UNSAT Examiner's signature and date: ___________

_ 5 of 7 Form ES-C-1 Appendix C Simulator Setup Form ES-C-1 Reset Simulator to any 1 00% IC Insert Malfunction:

MAL-CVH-RCS0028 75% 120 Second Ramp. Insert Schedule:

Failed auto rx trips.sch to fail automatic reactor trip with manual trip available.

6 of 7 Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• The plant is operating at 100% power

• No Equipment is Out of Service Initiating Cue: You are the ATC. Respond to changing plant conditions or events.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility:

IPEC UNIT2 Task No: 0590060321 Task Title: Transfer Main Feed from LFBV to MFRV During Power Ascension 059000A403 Job Performance Measure KIA

Reference:

RO-2.9 SRO-2.9 No: Sim D Examinee:

Facility Evaluator:

Method of testing: Simulated Performance Classroom READ TO THE EXAMINEE NRC Examiner:

Date: Actual Performance X Simulator X Plant I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

• The plant is at approximately 30% power

• Steam and Feed Flow signals are approximately 900,000 lbm/hr

• SG level is currently being maintained by the Low Flow Bypass Valves

• An NPO is standing by 21 FRV.

• All necessary Precautions and Limitations are met. Task Standard:

21 Steam Generator Level is being control by 21 Main Feedwater Regulating Valve in Automatic.

Required Materials:

None General

References:

2-SOP-21.1, Main Feedwater System 1 of 9 Appendix C Job Performance Measure Worksheet Form ES-C-1 Initiating Cue: You are the ATC and the CRS has directed you to

• Transfer 21 SG feedwater control from the Low Flow Bypass Valve to the Main Feed Regulating Valve (MFRV) in MANUAL in accordance with 2-SOP-21.1, Main Feedwater System Step 4.2.1.1 c(1)-4.2.1.1 c(7).

• When 21 MFRV operation is verified satisfactory transfer 21 MFRV to Automatic.

Time Critical Task: No Validation Time: 15 2 of 9 Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J) 1. Performance Step: Obtain correct procedure Standard:

Obtains 2-SOP-21.1 Comment: Hand the candidate the procedure.

2. Performance Step: Standard:

Comment: 3. Performance Step: Standard:

Observe NOTES before step 4.2.1.1 Reviews NOTES Verify selected 21 FW Regulator controller on the Flight Panel is in MAN AND Closed. Observes Controller in MAN and Potentiometer rotated to 0 position Comment: Step 4.2.1.1 a Panel FBF 4. Performance Step: Standard:

Comment: If desired to transfer level control in AUTO then go to step 4.2.1.1d.

It is not desired to transfer level control in AUTO 3 of9 Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J) ...J 5. Performance Step: Standard:

SLOWLY begin closing 21 Feedwater Bypass Valve until SG level begins to trend down. Rotate 21 Feedwater Bypass Valve potentiometer in the close direction (clockwise}

Comment: Step 4.2.1.1c(1}

Panel FBF ...J 6. Performance Step: Standard:

OPEN 21 Man Feedwater Regulating Valve to restore level to program Rotate 21 Main Feedwater Regulating Valve potentiometer in the open direction (counter clockwise}

Comment: Step 4.2.1.1 c(2} Panel FBF ...J 7. Performance Step: Standard:

REPEAT steps 4.2.1.1c(1}

AND 4.2.1.1c(2}

until Feedwater Bypass Valve is Closed Rotate 21 Feedwater Bypass Valve potentiometer in close direction Rotate 21 Main Feedwater Regulating Valve potentiometer in open direction Comment: Step 4.2.1.1c(3}

Panel FBF 4 of9 Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark .Y) 8. Performance Step: Verify 21 3 element controller FC-427 in Rack 84 is in AUTO Standard:

Locate Controller in Rack 84 and observe it is in AUTO Comment: Step 4.2.1.1c(4)

Rack 84 9. Performance Step: Verify 21 SG level is on trend near programmed level Standard:

Comment: Observe 21 SG level trend; make adjustments as necessary.

This is dependent on the candidate ability to smoothly control feedwater flow in Manual Step 4.2.1.1 c(5) Panel F8F 10. Performance Step: Verify 21 SG Steam Flow and Feed Flow indication are matched Standard:

Comment: Observe 21 SG Steam Flow and Feed Flow approximately equal at 900,000 lbm/hr This is dependent on the candidate ability to smoothly control feedwater flow in Manual Step 4.2.1.1 c(6) Panel F8F 5 of9 Appendix C Page 6 Form ES-C-1 Performance Information (Denote critical steps with a check mark >f) >111. Performance Step: Place 21 FW Regulator controller to AUTO Standard:

Move switch to AUTO position Observe FRV response stable (NOT erratic) Comment: Step 4.2.1.1 c(7) Panel FBF Terminating Cue: JPM Complete 6 of9 Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• The plant is at approximately 30% power

• Steam and Feed Flow signals are approximately 900,000 lbm/hr

• SG level is currently being maintained by the Low Flow Bypass Valves

• An NPO is standing by 21 FRV.

• All necessary Precautions and Limitations are met. Initiating Cue: You are the ATC and the CRS has directed you to

• Transfer 21 SG feedwater control from the Low Flow Bypass Valve to the Main Feed Regulating Valve (MFRV) in MANUAL in accordance with 2-SOP-21.1, Main Feedwater System Step 4.2.1.1 c( 1) -4.2.1.1 c(7).

• When 21 MFRV operation is verified satisfactory transfer 21 MFRV to Automatic.

Appendix C Reset Simulator to IC 231 Place MFRVs in Manual Open LFBVs and Close MFRVs. Stabilize SG Level. Simulator Setup Take a snapshot if JPM is given more than once. 8 of9 Form ES-C-1 Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• The plant is at approximately 30% power

• Steam and Feed Flow signals are approximately 900,000 lbm/hr

• SG level is currently being maintained by the Low Flow Bypass Valves

• An NPO is standing by 21 FRV.

• All necessary Precautions and Limitations are met. Initiating Cue: You are the ATC and the CRS has directed you to

• Transfer 21 SG feedwater control from the Low Flow Bypass Valve to the Main Feed Regulating Valve (MFRV) in MANUAL in accordance with 2-SOP-21.1, Main Feedwater System Step 4.2.1.1 c( 1) -4.2.1.1 c(7).

• When 21 MFRV operation is verified satisfactory transfer 21 MFRV to Automatic.

Appendix C Facility:

IPEC UNIT2 Job Performance Measure Worksheet Task No: 0000300521 Form ES-C-1 Task Title: Perform the Required Actions to Reset FCU Services and CCR Ventilation KIA 022000A4.01 Job Performance Measure

Reference:

SRO -3.6 RO -3.6 No: Sim E Examinee:

NRC Examiner:

Facility Evaluator:

Method of testing: Simulated Performance Classroom READ TO THE EXAMINEE Date: Actual Performance Simulator X Plant ------X I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

• Sl was initiated due to a steam break in the Turbine Building.

• MSIVs were closed

• All required actions of E-0 have been completed.

• Sl, Phase A & B have been reset.

• The CRS is addressing the remainder of the items in step 22. Task Standard:

Fan Cooler Unit Services and CCR Ventilation have been RESET. Required Materials:

Screwdriver General

References:

2-ES-1.1 Sl Termination Initiating Cue: You are the BOP and the CRS has directed you to reset FCU Services and CCR Ventilation in accordance with ES-1.1 step 22. Time Critical Task: No Validation Time: 15 Min 1 of 7 Appendix C Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark -1) 1 . Performance Step: Obtain Correct Procedure Standard:

Obtain current revision of 2-ES-1.1 Comment: 2. Performance Step: Place the following control switches in the Standard:

position indicated:

• TCV-1104

• TCV-1105 OPEN OPEN Rotate switches to Open position Comment:Step 22 (6 1 h bullet) Panel SBF-1 3. Performance Step: Standard:

Verify the following control switches in the position indicated:

• FCU NORM OUT valves OPEN Observe Switches in OPEN Comment: Step 22 (6th bullet) Panel SBF-2 2 of 7 Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark -Y) "' 4. Performance Step: Place the following control switches in the position indicated:

• Place Mode Selector Switch to 2 Standard:

Rotate switch to position 2 Comment: Step 22 (6th bullet} Panel PY2 "' 5. Performance Step: Place the following switches to CUTOUT

• Unit -1 K-8 fan switch (OT2-3}

• OT2-1

• OT2-2 Standard:

Rotate switches to CUTOUT Comment: Step 22 (6th Bullet} Panel PY2 Back corner of Simulator Control Room 3 of 7 Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark 6. Performance Step: Depress both Reset buttons in racks E-7 and F-8 for each of the following:

• FCU service Water

• FCU ventilation

• CCR Ventilation Standard:

Reset Pushbuttons Depressed Comment: Step 22 (6th bullet) Racks E-7 and F-8 in back of Simulator Control Room Terminating Cue: JPM Complete 4 of 7 Appendix C Page 5 VERIFICATION OF COMPLETION Job Performance Measure No. Simulator E Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response:

Result: SAT or UNSAT Examiner's signature and date: ___________

_ 5 of 7 Form ES-C-1 Appendix C Simulator Setup Reset Simulator to any 100% Power I C. Manually Actuate Sl Form ES-C-1 Perform applicable actions of E-0 including Attachment 1 and ES-1.1 up to 22. Take a snapshot if JPM is to be given multiple times. 6 of 7 Perform the Required Actions to Reset FCU Services and CCR Ventilation Page 7 of 6 Initial Conditions:

• Sl was initiated due to a steam break in the Turbine Building.

• MSIVs were closed

• All required actions of E-0 have been completed.

• Sl, Phase A & B have been reset.

• The CRS is addressing the remainder of the items in step 22. Initiating Cue: You are the BOP and the CRS has directed you to reset FCU Services and CCR Ventilation in accordance with ES-1.1 step 22. File: (3001901601.doc)

Parent Task# 3000320501 Difficulty:

3 Time: 15 minutes ES-1.1 REV: 42 Appendix C Facility:

IPEC UNIT2 Job Performance Measure Worksheet Task No: Form ES-C-1 Task Title: Transfer Buses 1, 2, 3, or 4 to the Unit Auxiliary Transformer 062000A401 KIA

Reference:

RO-3.3 SRO-3.1 Examinee:

Facility Evaluator:

Method of testing: Job Performance Measure No: NRC Examiner:

Date: Actual Performance Simulated Performance Classroom Simulator X Plant READ TO THE EXAMINEE Sim F X I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

• A Plant startup is in progress in accordance with 2-POP-1.3 Plant Startup from Zero to 45% Power.

• The turbine has been synchronized with Breakers 7 and 9 closed. Task Standard:

Buses 1 -4 are transferred to the Unit Auxiliary Transformer.

Required Materials:

General

References:

2-SOP-27.1.4 Initiating Cue: You are the BOP and the CRS has directed you to transfer 6.9 kV buses to the Unit Auxiliary Transformer in accordance with 2-SOP-27 .1.4 Time Critical Task: Validation Time: 1 of 11 Appendix C Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark >f) 1. Performance Step: Standard:

Comment: 2. Performance Step: Standard:

Comment: Step 4.2.1.1 >l 3. Performance Step: Standard:

Comment: Step 4.2.1.2 4. Performance Step: Standard:

Comment: Step 4.2.1.3 Obtain Correct Procedure and Reviews Precautions and Limitations Obtains 2-SOP-27 .1.4 P&Ls reviewed VERIFY Unit Auxiliary Transformer and Station Auxiliary Transformer are within 50 volts. Observes UAT and SAT are within 50 Volts Place 6900V Bus 1 Synchroscope switch to Bus 1 -Unit Place Handle into switch location and rotate to Bus 1 Unit position Verify Synchroscope at approximately 12 o'clock Observes Synchroscope at 12 o'clock 2 of 11 Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J) ....} 5. Performance Step: Standard:

Comment: Step 4.2.1.4 ....} 6. Performance Step: Standard:

Comment: Step 4.2.1.5 ....} 7. Performance Step: Standard:

Comment: Step 4.2.1.6 8. Performance Step: Standard:

Comment:Step Step 4.2.2.1 Close Normal Feed Breaker UT-1 Rotate Normal Feed Breaker Switch to Close Open Bus 1-5 Tie Breaker UT1-ST5 Rotate Tie Breaker Switch to Open Place Synchroscope to OFF Rotate Switch to OFF VERIFY Unit Auxiliary Transformer and Station Auxiliary Transformer are within 50 volts. Observes UAT and SAT are within 50 Volts 3 of 11 Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark -Y) -Y 9. Performance Step: Standard:

Comment: Step 4.2.2.2 10. Performance Step: Standard:

Comment: Step 4.2.2.3 Place 6900V Bus 2 Synchroscope switch to Bus 2 -Unit Place Handle into switch location and rotate to Bus 2 Unit position Verify Synchroscope at approximately 12 o'clock Observes Synchroscope at 12 o'clock -Y 11. Performance Step: Close Normal Feed Breaker UT-2 Standard:

Rotate Normal Feed Breaker Switch to Close Comment: Step 4.2.2.4 -Y 12. Performance Step: Open Bus 2-5 Tie Breaker UT2-ST5 Standard:

Rotate Tie Breaker Switch to Open Comment: Step 4.2.2.5 4 of 11 Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark .V) .V 13. Performance Step: Place Synchroscope to OFF Standard:

Rotate Switch to OFF Comment: Step 4.2.2.6 14. Performance Step: Standard:

Comment:Step Step 4.2.3.1 VERIFY Unit Auxiliary Transformer and Station Auxiliary Transformer are within 50 volts. Observes UAT and SAT are within 50 Volts .V 15. Performance Step: Place 6900V Bus 3 Synchroscope switch to Bus 3-Unit Standard:

Place Handle into switch location and rotate to Bus 3 Unit position Comment: Step 4.2.3.2 16. Performance Step: Verify Synchroscope at approximately 12 o'clock Standard:

Observes Synchroscope at 12 o'clock Comment: Step 4.2.3.3 5 of 11 Appendix C Page 6 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J) ....} 17. Performance Step: Close Normal Feed Breaker UT -3 Standard:

Rotate Normal Feed Breaker Switch to Close Comment: Step 4.2.3.4 ....} 18. Performance Step: Open Bus 1-5 Tie Breaker UT3-ST6 Standard:

Rotate Tie Breaker Switch to Open Comment: Step 4.2.3.5 ....} 19. Performance Step: Place Synchroscope to OFF Standard:

Rotate Switch to OFF Comment: Step 4.2.3.6 20. Performance Step: Standard:

Comment:Step Step 4.2.4.1 VERIFY Unit Auxiliary Transformer and Station Auxiliary Transformer are within 50 volts. Observes UAT and SAT are within 50 Volts 6 of 11 Appendix C Page 7 Form ES-C-1 Performance Information (Denote critical steps with a check mark -Y) -Y 21. Performance Step: Place 6900V Bus 4 Synchroscope switch to Bus 4-Unit Standard:

Place Handle into switch location and rotate to Bus 2 Unit position Comment: Step 4.2.4.2 22. Performance Step: Verify Synchroscope at approximately 12 o'clock Standard:

Observes Synchroscope at 12 o'clock Comment: Step 4.2.4.3 -Y 23. Performance Step: Close Normal Feed Breaker UT-4 Standard:

Rotate Normal Feed Breaker Switch to Close Comment: Step 4.2.4.4 -Y 24. Performance Step: Open Bus 2-5 Tie Breaker UT4-ST6 Standard:

Rotate Tie Breaker Switch to Open Comment: Step 4.2.4.5 7 of 11 Appendix C Page 8 Performance Information (Denote critical steps with a check mark -1) -1 25. Performance Step: Place Synchroscope to OFF Standard:

Rotate Switch to OFF Comment: Step 4.2.4.6 Terminating Cue: JPM Complete 8 of 11 Form ES-C-1 Appendix C Page 9 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response:

Result: SAT or UNSAT Examiner's signature and date: ___________

_ 9 of 11 Form ES-C-1 Appendix C Simulator Setup Select Low Power IC with Generator just synchronized.

Reset to IC-232 Transfer 6.9 KV buses back to SAT Close Tie breakers for buses 1 -4 Open Normal Feed Breakers for buses 1 -4 Lower turbine load to < 40 MWe Ensure Generator Output < 40 MWe Take a Snapshot if JPM is to be used more than once. 10 of 11 Form ES-C-1 Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• A Plant startup is in progress in accordance with 2-POP-1.3 Plant Startup from Zero to 45% Power.

• The turbine has been synchronized with Breakers 7 and 9 closed. Initiating Cue: You are the BOP and the CRS has directed you to transfer 6.9 kV buses to the Unit Auxiliary Transformer in accordance with 2-SOP-27.1.4.

Appendix C Facility:

IPEC UNIT2 Job Performance Measure Worksheet Task No: 0450040421 Form ES-C-1 Task Title: Respond to Turbine First Stage Pressure Transmitter Failure 016000A2.01 Job Performance Measure KIA

Reference:

RO-3.0 SRO-3.1 No: Sim G -----Examinee:

NRC Examiner:

Facility Evaluator:

Date: Method of testing: Simulated Performance Actual Performance X Classroom Simulator X Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

• Reactor at indicated power.

• Steady State, equilibrium Xenon.

• No equipment out of service. Task Standard: . Required Materials:

None General

References:

2-AOP-INST-1, Instrument or Controller Failures 2-AOP-ROD-1, Rod Control and Indication System Malfunctions Initiating Cue: You are the ATC. Time Critical Task: No Validation Time: 10 1 of 8 Appendix C Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark>/) >/ 1. Performance Step: Standard:

Comment: >/ 2. Performance Step: Standard:

Operator takes Immediate Actions from memory (steps 3.1-3.3) Note: Immediate actions of 2-AOP-INST-1

1. Checks all parameters listed 2. Determines that PT-412A has failed low Take manual actions as necessary to control parameters and stabilize the plant Place Rod Control in Manual Comment: Procedure step 3.2 3. Performance Step: Standard:

Have all controls systems listedin step 3.1 been checked as being affected?

Observe all systems were checked during performance of immediate operator actions. Comment: Procedure step 3.3 2 of 8 Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark .../) 4. Performance Step: Has an instrument failure occurred?

Standard:

Determine an instrument failure has occurred PT -412A failed low. Comment: Procedure step 4.1 5. Performance Step: Go To applicable step for the indicated failure Standard:

Identify step 4.168 is the affected step Comment: Procedure step 4.2 6. Performance Step: Has Channel A failed low? Standard:

Determine 412A has failed low using PICS Comment: Procedure step 4.168 7 Performance Step: Are control rods in Manual? Standard:

Rod control should be in manual at this time Comment: Procedure step 4.169 3 of 8 Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J) 8. Performance Step: Maintain Tavg and Tref per graph RPC-4 (RCS T-ref vs Reactor Power) and restore delta flux to targe per CRS direction suing any of the following

• Rod Control

• Boration

• Adjust Turbine Load CUE: The CRS directs restoring Tave using Control Rods. Standard:

Withdraw Control Rods to restore Tavg Comment: Procedure step 4.170 9. Performance Step: Observe Rods continue to withdraw in Manual after Hold-Out switch released Standard:

Comment: Observe step counters and IRPI continuing outward motion The following steps are from procedure 2-AOP-ROD-1.

The candidate may just trip the reactor and go to E-0. 1 0. Performance Step: Was this procedure entered due to continuous unwarranted rod motion? Standard:

Determines YES Comment: Procedure step 4.1 (AOP-ROD-1) 4 of 8 Appendix C Page 5 Performance Information (Denote critical steps with a check mark 11. Performance Step: Is rod control in manual Standard:

Determines rod control is in manual Comment: Procedure step 4.2 Form ES-C-1 12. Performance Step: Standard:

Does continuous unwarranted rod motion exist? Determines YES Comment: Procedure step 4.3 ..J 13. Performance Step: Trip the reactor and goto E-0 Standard:

Push reactor trip pushbutton Comment: Procedure step 4.4 Terminating Cue: JPM Complete 5 of 8 Appendix C Page 6 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response:

Result: SAT or UNSAT Examiner's signature and date: ___________

_ 6 of 8 Form ES-C-1 Appendix C Simulator Setup Form ES-C-1 Any 1 00 % Power IC ENSURE GROUP 92 IS DISPLAYED ON ENG CRT PICS MONITOR SHOW GROUP 92 PT-412A, First Stage Turbine Pressure fails Low XMT -MSS053A FIXED OUTPUT: PT-412A FIRST STAGE TURBINE PRESSURE C SEVERITY -14.7 Continuous Rod Motion Insert Malfunction:

MAL-CRF004A to 72 step/min This malfunction will start when rod motion is initiated.

7 of 8 Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• Reactor at indicated power.

• Steady State, equilibrium Xenon.

• No equipment out of service. Initiating Cue: You are the ATC.

Appendix C Facility:

Indian Point 2 Job Performance Measure Worksheet Task No: 0030010101 Task Title: Start a Reactor Coolant Pump 003000A406 KIA

Reference:

RO-2.9 SRO-2.9 Examinee:

Facility Evaluator:

Method of testing: Job Performance Measure No: NRC Examiner:

Date: Actual Performance Simulated Performance Classroom Simulator X Plant READ TO THE EXAMINEE Form ES-C-1 SimH X I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

• Reactor is shutdown with RCS temperature and pressure as indicated

• 21 Reactor Coolant Pump is fully operational

• The RCS is aligned per COL 1.1

• All applicable Precautions and Limitations are satisfied

• DMIMS is in service

• An NPO is standing by 21 RCP

• The RCP has been secured for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Task Standard:

21 RCP is running and its Lift Oil Pump is secured .. Required Materials:

None General

References:

2-SOP-1.3, Reactor Coolant Pump Startup and Shutdown.

Initiating Cue: You are the BOP and the CRS has directed you to start 21 RCP in accordance with 2-SOP-1.3 steps 4.1.1 through 4.1.17 Time Critical Task: No 1 of 12 Appendix C Validation Time: 20 Job Performance Measure Worksheet 2 of 12 Form ES-C-1 Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J) 1. Performance Step: Obtain correct procedure Standard:

Obtains SOP-1.3 Comment: Evaluator may give candidate the procedure at this time 2. Performance Step: Review Precautions and Limitations Standard:

Comment: Check plant lineup and conditions Candidate was given all P&Ls were met in Initial Conditions.

Candidate may take some time to look at P&Ls but should not take time to evaluate all. 3. Performance Step: If the Containment is accessible then Standard:

• Inspect Bearing Lift Oil System for leaks if RCP secured for 30 days or longer

• lnpsect JO Bell Oil Level Alarm tubing for damage and leaks Bearing Lift Oil System Inspection is not necessary Contact NPO to inspect Oil Level Alarm CUE: NPO reports "All conditions normal for 21 RCP" Comment: Step 4.1.1 3 of 12 Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J) 4. Performance Step: Standard:

Comment: Step 4.1.2 5. Performance Step: Standard:

Comment: ..J 6. Performance Step: Standard:

Check if RCP should be rotated by hand Determine rotation is not necessary (three remaining RCPs are running. Observe NOTES before step 4.1.3 Reviews NOTES Verify Bearing Lift Pump is Running Rotate 21 Bearing Lift Pump switch to Start Observe red light (breaker closed) and white light (21 Lift Pressure) are both lit Comment: Step 4.1.3 Panel SAF 7. Performance Step: Standard:

Select Containment Microphone to the RCP (21) to be started Rotate Microphone switch to 21 RCP Comment: Step 4.1.4 CRS desk 4 of 12 Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J) 8. Performance Step: Standard:

Comment: Step 4.1.5 9. Performance Step: Standard:

Verify DMIMS Signal Recorder is in service DMIMS signal recorder is in service given in Initial Conditions.

If power is being supplied from the Station Auxiliary Transformer

• Place the Tap Changer in MANUAL

• RAISE the bus voltage to 7.2 KV Push Tap Changer Handle IN for Manual Rotate switch to RAISE to establish 7.2 KV. Comment: This is not critical because on the Simulator the RCP will Start regardless of the voltage. Step 4.1.6 Panel FCR (rear of flight panel) 10. Performance Step: Standard:

Comment: Step 4.1.7 11. Performance Step: Standard:

Comment: Step 4.1.8 If power is being supplied from GT25/26 Determine power is NOT being supplied from GT-25/26 No Action is Required Prior to starting the first of either 23 or 24 RCP, Verify that both spray valves are CLOSED to prevent a pressure transient on the RCS. Observer both 23 and 24 RCP are operating No Action Required 5 of 12 Appendix C Page 6 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J) 12. Performance Step: Standard:

Verify Bearing Lift Pump has been running for at least two minutes Determine pump has been operating for 2 minutes Comment: It is expected that two minutes has elapsed since the pump was started. If not the candidate should wait until 2 minutes has elapsed. This is NOT critical because the pump would start in less than two minutes. This is an administrative requirement.

Step 4.1.9 13. Performance Step: Standard:

Comment: 14. Performance Step: Standard:

Observe NOTE before step 4.1.1 0 Reviews the NOTE NOTIFY Security, the start of an RCP is imminent and the accompanying voltage dip may cause auto start of the Security Diesel Using phone or radio simulate contact Security and inform of imminent start of 21 RCP CUE: Acknowledge as Security the start of 21 RCP Comment: Step 4.1.10 15. Performance Step: Observe CAUTIONS and NOTES before step 4.1.11 Standard:

Reviews Cautions and Notes Comment: 6 of 12 Appendix C Page 7 Performance Information (Denote critical steps with a check mark .Y) .Y 16. Performance Step: Start the RCP Standard:

Rotate Switch for 21 RCP to Start position Observe Motor Amps off scale high Observe Flow indication increasing Form ES-C-1 Verify Reactor Coolant 21 Loop Low Flow Channel Trip 90% alarm clears before motor current returns on scale. Comment: Step 4.1.11 Panel SAF 17. Performance Step: Verify the normal running current Standard:

Observe AC Amps approximately 400 Comment: Step 4.1.12 18. Performance Step: Place the Containment Microphone to OFF Standard:

Rotate switch to OFF CUE: IF CRS asked if it is desired to turn off the microphone "Yes the CRS desires the microphone turned off" Comment: Step 4.1.13 7 of 12 Appendix C Page 8 Form ES-C-1 Performance Information (Denote critical steps with a check mark >/) 19. Performance Step: Standard:

Closely MONITOR Digital Metal Impact Monitor System DMIMS Observes DMIMS display Comment: Step 4.1.14 DMIMS rack (behind the Flight Panel) 20. Performance Step: MONITOR the following RCP parameters until stable

• RCS Pressure

• Loop flow

• ACAmps

• Steam Generator Levels

• RCP Seal 1 Leakoff flow

• Seal injection flow

• Seal inlet temperature

• Seal outlet temperature

• RCP Vibration

• RCP Bearing temperatures

• RCP Stator temperature Standard:

Observe RCP parameters Comment: Step 4.1.15 8 of 12 Appendix C Page 9 Form ES-C-1 Performance Information (Denote critical steps with a check mark -/) 21. Performance Step: Standard:

If power is being supplied from the station Auxiliary Transformer then

• RAISE the bus voltage to 7.05 to 7.15 KV

• PLACE the tap changer in AUTO Rotate switch as necessary to set bus voltage to 7.05-7.15 KV. Pull switch OUT to place tap changer in AUTO Comment: Step 4.1.16 Panel FCR (rear of flight panel) 22. Performance Step: Standard:

When the RCP has run for at least 1 minute then STOP the Bearing Lift Oil Pump Observe 1 minute has elapsed Rotate switch to STOP position Comment: Step 4.1.17 Panel SAF Terminating Cue: JPM Complete 9 of 12 Appendix C Page 10 VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response:

Result: SAT or UNSAT Examiner's signature and date: ___________

_ 10 of 12 Form ES-C-1 Appendix C Reset Simulator to IC-5 Trip 21 RCP Simulator Setup Allow simulator to run to stabilize plant conditions If JPM is to be run more than once, take a Snapshot.

11 of 12 Form ES-C-1 Page 12 of 12 Initial Conditions:

• Reactor is shutdown with RCS temperature and pressure as indicated

• 21 Reactor Coolant Pump is fully operational

• The RCS is aligned per COL 1.1

• All applicable Precautions and Limitations are satisfied

• DMIMS is in service

• An NPO is standing by 21 RCP

• The RCP has been secured for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Initiating Cue: You are the BOP and the CRS has directed you to start 21 RCP in accordance with 2-SOP-1.3 steps 4.1.1 through 4.1.17 File: 0030011601-1.doc Parent Task # 003*00 1 *0 1 *0 1 Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility:

IPEC UNIT2 Task No: 0840140421 Task Title: Align Nitrogen Bottle to 21 Atmospheric Steam Dump 039000A407 Job Performance Measure KIA

Reference:

RO-2.8 SRO-2.9 No: In Plant I Examinee:

Facility Evaluator:

Method of testing: Simulated Performance Classroom READ TO THE EXAMINEE X NRC Examiner:

Date: Actual Performance Simulator Plant I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

• Work in the transformer yard resulted in a loss of instrument air and unit trip.

• All MSIVs were closed.

• RCS temperature is slowly rising. X Task Standard:

Nitrogen Bottle is aligned to supply 21 SG Atmospheric valve operator.

Required Materials:

None General

References:

2-SOP-ESP-001, Local Equipment Operation and Contingency Actions Initiating Cue: You are the Conventional NPO and the CRS has directed you to align backup nitrogen to all Atmospheric Steam Dump Valves in accordance with 2-SOP-ESP-001 Section 4.12. Time Critical Task: No Validation Time: 10 Minutes 1 of 8 Appendix C Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark .Y) 1. Performance Step: Standard:

Obtain Correct Procedure Obtains 2-SOP-ESP-001 and review Precautions and Limitation CUE: Hand the candidate the procedure Comment: 2. Performance Step: Standard:

Comment: .Y3. Performance Step: Standard:

Comment: 4. Performance Step: Standard:

Comment: Step 4.12.2 Observe NOTEs before step 4.12.1 Reviews Notes To align 21 Atmospheric go to Step 4.12.2 Continues procedure with step 4.12.2 If PCV-1134 (21 ATMO) needs to be operated from the CCR, then aligh backup N 2 as follows The next 7 JPM steps will align N2to 21 ATMO 2 of 8 Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark -Y) 5. Performance Step: Verify MS 3A, (PCV-1134 Inlet Stop Main Steam Line 21 is OPEN Standard:

CUE: Comment: Locates MS-3A and observes valve position When valve is located and simulated checked open, "MS-3A is Opened". Step 4.12.2.1 -Y 6. Performance Step: Connect both Nitrogen bottle quick disconnect to the fittings upstream of SGN-522/SGN-524 Standard:

CUE: Locates quick disconnect hoses and indicates where they are to be connected.

When disconnect hoses are located and simulated connected "Quick Disconnect Hoses are connected".

Comment: Step 4.12.2.2 -Y 7 Performance Step: Open both Nitrogen bottle isolation valves Standard:

Cue: Locate Nitrogen bottle isolation valve When valves are located, Both Nitrogen bottle valves are open Comment: NOTE Only ONE nitrogen bottle valve open is critical.

3 of 8 Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J) ...J 8. Performance Step: Open one of the following valves

• N-853

• N-855 Standard:

Locate Valve and Open CUE: When either valve is located and simulated opened " The valve is open". Comment: Step 4.12.2.4 9. Performance Step: Verify both f the following regulators are set for 85 psig Standard:

CUE: Comment:

• N-850

• N-854 Locate regulators and demonstrate how to adjust pressure When regulators located and candidate demonstrates how to adjust pressure, "The Regulators are set at 85 psig" Step 4.12.2.5 ...J 10. Performance Step: Close IA-806 21 SG ATMO Relief lnst Air Stop Standard:

Locate valve and simulate closing CUE: Comment: When valve is located and simulated closed "The Valve is Closed" 4 of 8 Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark -1) 'I/ 11. Performance Step: Open SGN-522 CCR Remote Backup Nitrogen Inlet Stop to 21 ATMO Standard:

Locate valve and simulate opening CUE: When the valve is located and simulated opened "The valve is opened". Comment: Step 4.12.2. 7 12. Performance Step: Notify the CCR N 2 Bottle Supply is aligned to PCV-1134.

Standard:

Simulate calling CCR using radian CUE: Acknowledge as CCR Comment: Step 4.12.2.8 Terminating Cue: JPM Complete 5 of 8 Appendix C Initial Conditions VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response:

Result: SAT or UNSAT Examiner's signature and date: ___________

_ Form ES-C-1 Appendix C "J" (P-4) c (V-4) D N-2) E (V-3) F (V-1) G H j (P-4) (P-3) (P-2i Initial Conditions POSITIONER (P-3) . 3-27psi I t .................

.. 1Q-50ma VENT VALVE NUMBERING TABLE fOR Pi::V*1134 FQB f!i:i*1 j35 FoB

• 1136 FOR e!<V-1137 IA*80i IA-008 IA-809 IA-1207 IA-1208 IA-1209 ----SGN-500 SGN-501 SGN.-502 SGN-503 SGN-508 SGN-509 SGN-510 SGN-511 IA-1008 IA-1009 IA-1010 IA-1011 IA-1202 IA*1203 IA-1204 IA*1205 PRV-5607 PRV-5609 PRV-5611 PRV-5613 PRV-5608 PRV-5610 PRV-5612 PRV-5614 Pl-6113 Pl-6121 SGN-521 N-853 N-851 N-851 N-850 N-850 N-852 N-852 Form ES-C-1 lA SUPPLY N2 SUPPLY Quick disconnect and flex hose "0" Local nitrogen cylinder ALTERNATE N2 SUPPLY Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• Work in the transformer yard resulted in a loss of instrument air and unit trip.

• All MSIVs were closed.

• RCS temperature is slowly rising. Initiating Cue: You are the Spare RO and the CRS has directed you to align backup nitrogen to all Atmospheric Steam Dump Valves in accordance with 2-SOP-ESP-001 Section 4.12.

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility:

IPEC UNIT2 Task No: 0720060122 Task Title: Secure Discharge Lineup for 23 Large Gas Decay Tank and Lineup 24 Large Gas Decay Tank for Release. 071000A405 KIA

Reference:

RO-2.6 SRO-2.6 Job Performance Measure No: In Plant J Examinee:

NRC Examiner:

Facility Evaluator:

Date: Method of testing: Simulated Performance X Actual Performance Classroom Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

• The system is aligned in accordance with COL 5.2.1.

• Preparations are being made for a refueling outage

• Release of 23 Large Gas Decay Tank (LGDT) has just been completed

• N 2 purge of 23 LGDT will NOT be performed

• The SM has directed 24 Large Gas Decay Tank is to be released.

X

• 24 Large Gas Decay Tank had been isolated, sampled, and the sample has been analyzed.

• A PAB Exhaust Fan is Running

• Iodine and Particulate Composite Collection Device IS in place

• Release Permit has been completed and approved to release 24 LGDT in accordance with SOP-5.2.1.

• Radiation Monitor R-44 is in service

• Radiation Monitor R-44 High Alarm setpoint was NOT adjusted

• RTA for the release permit is 3.525 E-06 iJCi/cc

• Release Permit Number 140015

• TMIN 45 min

• Planned Release Time 20 min 1 of 11 Appendix C Job Performance Measure Worksheet Form ES-C-1 Task Standard:

23 Large Gas Decay Tank Lineup secured and 24 Large Gas Decay Tank is lined up for release. Required Materials:

None General

References:

2-SOP-5.2.1 Initiating Cue: You have been directed to SIMULATE securing the lineup for 23 Large Gas Decay Tank in accordance with SOP-5.2.1 step 4.4.13 and lineup 24 Large Gas Decay Tank for release in accordance with SOP-5.2.1 Attachment 4 section 1 Time Critical Task: No Validation Time: 20 minutes 2 of 11 Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark >f) >11. Performance Step: Standard:

When release has been completed,:

• If N 2 purge will not be performed then close RCV-014 and go to step 4.4.14 N 2 purge will not be performed (given in initial conditions)

Rotate regulator to left to decrease air pressure on indicator on Waste Disposal Panel CUE: Air pressure is lowering Comment: Procedure step 4.4.13.1 2. Performance Step: Enter finishing time in Unit Narrative Log Standard:

CUE: "The FSS has made the Unit Narrative Log entry". Comment: Procedure step 4.4.14 3 of 11 Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J) ...J 3. Performance Step: Standard:

Verify Gas Analyzer is returned to AUTO (sampling the in service GOT)

• Verify all Sample-Bypass Switches are BYPASSED per step 4.1. 7 with the noted exception

• Place the LGDT Sample-Bypass Switch in SAMPLE

• Place the MODE Switch in AUTO Observes all switches in BYPASS (Not Critical)

Rotate the LGDT Sample-Bypass Switch to SAMPLE Rotate the MODE Switch to AUTO CUE: hand candidate procedure 2-SOP-5.2.3 When switches are located: "All Sample-Bypass Switches are in BYPASS" "The LGDT Sample-BYPASS switch is in Sample" "The MODE Switch is in AUTO" Comment: Procedure 2-SOP-5.2.3

4. Performance Step: Standard:

Complete Section 2 of Discharge Sample Checkoff to restore normal system lineup Perform next 3 JPM Steps Comment: Procedure Step 4.4.15 4 of 11 Appendix C Page 5 Performance Information (Denote critical steps with a check mark -/) -1 5. Performance Step: Standard:

1619 23 LGDT Outlet Stop-Closed Locate Valve and Simulate Closing CUE: When valve is located, "The valve is closed" Comment: 2-SOP-5.2.1 Attachment 3 Section 2 -/6. Performance Step: Standard:

1644C PCV-1 038A Inlet Stop -OPEN Locate Valve and Simulate Closing CUE: When valve is located, "The valve is opened" Comment: 2-SOP-5.2.1 Attachment 3 Section 2 7 Performance Step: Standard:

1643C 23 LGDT Stop (Inlet and PT) -OPEN Locate Valve and Observe OPENED CUE When Valve is located, "The valve is opened". Comment: This step is not critical; the valve is expected to be opened. Form ES-C-1 8. Performance Step: Return completed applicable attachment to CCR Standard:

CUE: "The FSS will return the attachment to the CCR" Comment: 5 of 11 Appendix C Page 6 Form ES-C-1 Performance Information (Denote critical steps with a check mark -J) 9. Performance Step: Verify RCV-014 Plant Stack Discharge Valve is CLOSED Standard:

Locate Valve and observe closed indications.

CUE: When the valve is located, "The valve is closed" Comment: This step is not critical; the valve was closed at the beginning of this evolution.

10. Performance Step: Determine appropriate Discharge/Sample Checkoff Attachment to be used for discharge and Align selected GOT (Attachment 4-24 LGDT) for release by completing Section 1 Standard:

Simulate performing the next 3 JPM steps Comment: --./ 11. Performance Step: 16440 PCV-1039 Outlet Stop-CLOSED Standard:

Locate 16440 and simulate closing CUE: When the valve is located, "The valve is closed" Comment: 2-SOP-5.2.1 Attachment 4 Section 1 6 of 11 Appendix C Page 7 Performance Information (Denote critical steps with a check mark ...J) ...J 12. Performance Step: 1620 24 LGDT Outlet Stop-CLOSED Standard:

Locate 1620 and simulate closing CUE: When the valve is located, "The valve is closed" Comment: 2-SOP-5.2.1 Attachment 4 Section 1 Form ES-C-1 13. Performance Step: 1643D 24 LGDT Stop {Inlet and PT)-OPENED Standard:

Locate 1644D and simulate Verifying Open CUE: When the valve is located, "The valve is OPENED" Comment: 2-SOP-5.2.1 Attachment 4 Section 1 14. Performance Step: Standard:

Verify remaining valves on Attachment 4 -CLOSED Locate each valve and simulate checking CLOSED CUE: When valves are located, "The valve is closed". Comment: Terminating Cue: JPM Complete 7 of 11 Appendix C Page 8 Form ES-C-1 GASEOUS WASTE DISPOSAL SYSTEM No:2-SOP-5.2.1 OPERATION Page 36 of41 ATTACHMENT 3 23 LGDT Discharge I Sample Checkoff (Page 1 of 1) Release Permit Number ttloo tc.r T MIN == _4.!...-.:.l

___ min. {SEE Attachment 8} Planned Release Time (T) = ..1 D NOTE WHEN multiple LGDTs are to be sampled and released, THEN additional associated discharge stops are NOT closed as called for below. Chemistry Manager permission is required, when a 23 LGDT is >1 E-2 uCi/cc 1.0 23 Large Gas Decay Tank Start of Discharge

• 1644C PCV-1 038A Inlet Stop * * * * * * * * * * * *

• 1631 PCV-10388 1617 1618 1620 1652F 1652E 1652D 1652C 16528 1652A 1619 1643C 23 LGDT Reuse Outlet Gas Analyzer Sample Inlet 21 LGDT Outlet Stop 22 LGDT Outlet Stop 24 LGDT Outlet Stop 21 SGDT Outlet Stop 22 SGDT Outlet Stop 23 SGDT Outlet Stop 24 SGDT Outlet Stop 25 SGDT Outlet Stop 26 SGDT Outlet Stop 23 LGDT Outlet Stop 23 LGDT Stop (Inlet and PT) 2.0 Termination of Discharge

• *

• 1619 1644C 1643C 23 LGDT Outlet Stop PCV-1038A Inlet Stop 23 LGDT Stop (Inlet and PT) Position CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED OPEN OPEN CLOSED OPEN OPEN Rev:33 mim Completed by: __________

_ Date: ___ _ Time: ____ _ 8 of 11 Appendix C Page 9 Form ES-C-1 GASEOUS WASTE DISPOSAL SYSTEM No:2-SOP-5.2.1 Rev:33 OPERATION Page 37 of 41 ATTACHMENT 4 24 LGDT Discharge I Sample Checkoff (Page 1 of 1) Release Permit Number { 4 ODI (.. RrA = 3.

cE-C,. J.LCi/cc T MIN= __ Lf_c) ___ min. {SEE Attachment 8} Planned Release Time (T) = .:Jl> NOTE :>> WHEN multiple LGDTs are to be sampled and released, THEN additional associated discharge stops are NOT closed as called for below. >-Chemistry Manager permission is required, when a 24 LGDT is >1E-2 uCi/cc 1.0 24 Large Gas Decay Tank Start of Discharge

• 1644D PCV-1039A Inlet Stop * * * * * * * * * * * *

• 1632 PCV-1039B 1617 1618 1619 1652F 1652E 1652D 1652C 1652B 1652A 1620 1643D 24 LGDT Reuse Outlet Gas Analyzer Sample Inlet 21 LGDT Outlet Stop 22 LGDT Outlet Stop 23 LGDT Outlet Stop 21 SGDT Outlet Stop 22 SGDT Outlet Stop 23 SGDT Outlet Stop 24 SGDT Outlet Stop 25 SGDT Outlet Stop 26 SGDT Outlet Stop 24 LGDT Outlet Stop 24 LGDT Stop (Inlet and PT) 2.0 Termination of Discharge

• 1620 24 LGDT Outlet Stop

• 1644D PCV-1039A Inlet Stop

• 16430 24 LGDT Stop (Inlet and PT) Position lnit. Date CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED CLOSED OPEN OPEN CLOSED OPEN OPEN mim Completed by: __________

_ Date:. ___ _ Time: ____ _ 9 of 11 Appendix C Simulator Setup VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response:

Result: SAT or UNSAT Examiner's signature and date: -----------

10 of 11 Form ES-C-1 Appendix C Initial Conditions Form ES-C-1 Initial Conditions:

• The system is aligned in accordance with COL 5.2.1.

• Preparations are being made for a refueling outage

• Release of 23 Large Gas Decay Tank (LGDT) has just been completed

• N 2 purge of 23 LGDT will NOT be performed

• The SM has directed 24 Large Gas Decay Tank is to be released.

• 24 Large Gas Decay Tank had been isolated, sampled, and the sample has been analyzed.

• A PAB Exhaust Fan is Running

• Iodine and Particulate Composite Collection Device IS in place

• Release Permit has been completed and approved to release 24 LGDT in accordance with SOP-5.2.1.

• Radiation Monitor R-44 is in service

• Radiation Monitor R-44 High Alarm setpoint was NOT adjusted

• RTA for the release permit is 3.525 E-06 1JCilcc

• Release Permit Number 140015

• TMIN 45 min

• Planned Release Time 20 min Initiating Cue: You have been directed to SIMULATE securing the lineup for 23 Large Gas Decay Tank in accordance with SOP-5.2.1 step 4.4.13 and lineup 24 Large Gas Decay Tank for release in accordance with SOP-5.2.1 Attachment 4 section 1 Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility:

IPEC UNIT2 Task No: 0840330424 Task Title: Perform the Required Actions to Locally Start 21 Charging Pump Without Instrument Air Available KIA 000068A106 Job Performance Measure

Reference:

RO-4.1 SRO-4.2 No: In Plant K Examinee:

NRC Examiner:

Facility Evaluator:

Date: Method of testing: Simulated Performance X Actual Performance Classroom Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

Initial Conditions:

• The CCR has been evacuated due to a fire and 2-AOP-SSD-1, Control Room Inaccessibility Safe Shutdown Control, has been implemented

• The 480V Switchgear Room is accessible.

• An NPO is standing by in the 480V Switchgear Room. X Task Standard:

21 Charging Pump is running with speed control using the scoop tube. Required Materials:

None General

References:

2-AOP-SSD-1, Control Room Inaccessibility Safe Shutdown Control Initiating Cue: You are the RO in the PAB, and the CRS has directed you to locally start 21 Charging Pump per 2-AOP-SSD-1, Attachment 8, Step 8.1 -8.24 Time Critical Task: No Validation Time: 20

• 1 of 7 Appendix C Page 2 Form ES-C-1 Performance Information (Denote critical steps with a check mark ,f) 1. Performance Step: Obtain correct procedure Standard:

Obtain 2-AOP-SSD-1 Attachment 8 CUE: Hand candidate the procedure Comment: 2. Performance Step: Standard:

Determine accessibility of 480V Switchgear Room 480V Switchgear Room is accessible from the initiating cues Comment: Attachment 8 step 8.1 3. Performance Step: Standard:

If At Any Time 21 Charging Pump is available to start from the 480V Switchgear Room and the SM desires go to Step 8.20. Contact the SM; request to start 21 Charging pump from the 480V Switchgear Room. CUE: SM "Start 21 Charging Pump from the 480V Switchgear Room". Comment: 2 of 7 Appendix C Page 3 Form ES-C-1 Performance Information (Denote critical steps with a check mark ...J) 4. Performance Step: Determine if Instrument Air is Available Standard:

CUE: "Instrument Air is NOT available" Comment: Attachment 8 Step 8.20 ....} 5. Performance Step: Standard:

Uncouple Air Speed Controller from Scoop Tube Linkage (Above Pump) Locate Air Speed Controller and demonstrate how to disconnect CUE: When contr()Uer identified and simulated disconnected, "Air Speed Controller is disconnected from Scoop Tube". Comment: Attachment 8 Step 8.20 RNO -1/ 6. Performance Step: Place Scoop Tube in Position A Standard:

Demonstrate how scoop tube moved to Position A CUE: When Scoop Tube movement properly demonstrated "Scoop Tube is in Position A". Comment: Attachment 8 Step 8.20 RNO 3 of 7 Appendix C Page 4 Form ES-C-1 Performance Information (Denote critical steps with a check mark ..J) ..J 7 Performance Step: Standard:

Open 288 (RWST Manual Inlet Stop) (22 Charging Pump Cell) Locate Valve and simulate Opening CUE: When the valve is located "The valve is Opened". Comment: Attachment 8 Step 8.21 ..J 8. Performance Step: Standard:

Close 297 (Boric Acid Blender Outlet Stop) (Concentrates Holding Tank Cell PAB 98' near FCV-110B) Locate valve and simulate Closing. CUE: When valve is located "The valve is Closed". Comment: Attachment 8 Step 8.22 9. Performance Step: Observe Caution before step 8.23 Standard:

Reviews Caution Comment: 4 of 7 Appendix C Page 5 Form ES-C-1 Performance Information (Denote critical steps with a check mark -Y) 10. Performance Step: Standard:

Insert Key into Control Switch for 21 Charging Pump at Panel EDA56 (480V South Wall behind switchgear)

Contact NPO in 480V Switchgear to insert key into control switch CUE: As NPO Acknowledge direction and report "The key is in the control switch". Comment: Attachment 8 Step 8.23 11. Performance Step: Place 21 Charging Pump Control Switch to START Standard:

Contact NPO in 480V Switchgear to Start 21 Charging Pump CUE As NPO Acknowledge direction and report "The Pump is started".

And Inform candidate that the pump is running. Comment: Attachment 8 Step 8.24 Terminating Cue: JPM Complete 5 of 7 Appendix C Simulator Setup VERIFICATION OF COMPLETION Job Performance Measure No. Examinee's Name: Date Performed:

Facility Evaluator:

Number of Attempts:

Time to complete:

Question Documentation:

Question:

Response:

Result: SAT or UNSAT Examiner's signature and date: ___________

_ 6 of 7 Form ES-C-1 Initial Conditions:

• The CCR has been evacuated due to a fire and 2-AOP-SSD-1, Control Room Inaccessibility Safe Shutdown Control, has been implemented

• The 480V Switchgear Room is accessible.

• An NPO is standing by in the 480V Switchgear Room. Initiating Cue: You are the RO in the PAS, and the CRS has directed you to locally start 21 Charging Pump per 2-AOP-SSD-1, Attachment 8, Step 8.1 -8.24 Facility:

Indian Point 2 Scenario No.: 1 Op-Test No.: _1 Examiners:

Operators:

Initial Conditions:

Reset simulator to 90% power IC Load Simulator Schedule-Scenario1 The Plant is at 90% power. 22 Sl Pump is OOS Ensure 23 Charging Pump, 23 SWP and 26 SWP are in service Turnover:

Return plant to 100% power over the next hour. Event Malf. No. Event Event No. Type* Description 1 N/A R (ATC) N (CRS) Power Escalation N (BOP) 2 MOT-C(BOP) 23 SW Pump trips. SWS008A TS(CRS) I (ATC) 3 XMT-SGN034A I (CRS) PT-404 Steam Header Pressure fails high causing MBFPs to be placed in manual. 4 MAL-C (ALL) EPS007D TS(CRS) 480V Bus 6A fault. 5 MAL-M(ALL) Small Break LOCA RCS006A 6 BKR-PPL003/4 M(ALL) ATWS 7 MOC-C(CRS) AFW001 21 AFW Pump failure C(BOP) 8 RLY-PPL487/48 C(CRS) Automatic Safety Injection failure 8 9 RLY-C(CRS) PPL085/09 Phase A Isolation failure 0 C(BOP) * (N)ormal, (R)eactivity, (l}nstrument, (C)omponent (M)ajor U2 NRC 2014 Scenario 1: Power escalation from 90%, 23 SWP trips, PT -404 fails high, Loss of 480V Bus 6A, SBLOCA, ATWS, 21 AFW Pump failure, Auto Sl failure, Phase A failure. Page 1 of 16 SESSION OUTLINE: The evaluation begins with the plant at 90% power steady state operation.

The team has been directed to return the plant to 100%. 22 Sl pump is out of service for bearing inspection.

22 Sl Pump was removed from service 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ago, expected return in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The crew will take the watch and start increasing power. After power ascension has begun, 23 Service Water Pump will trip. BOP will diagnose and another pump will be started per the alarm response procedure.

The CRS will evaluate Tech Specs. When power ascension resumes, PT-404 (Steam Header Pressure) fails high. ATC diagnoses failure and places Main Boiler Feed Pump speed control to manual. CRS directs crew to perform AOP-INST-1, Instrument/Controller Failures.

Next, a fault occurs on Bus 6A. Team enters AOP-480V-1, Loss of 480 V Bus to stabilize the plant. The crew will start a charging pump, evaluate Tech Specs, and commence a shutdown per POP-2.1. After formulating a shutdown plan, a SBLOCA occurs. Auto reactor trip is demanded but the Reactor trip breakers do not open. The team will attempt to manually trip the reactor and then go to FR-S.1. The turbine will be manually tripped. Motor driven AFW pumps can not be started. AFW must be manually aligned using the turbine driven AFW pump. The crew will begin manually inserting control rods and then will align emergency Boration using the alternate path in the RNO because MOV 333 is energized.

Following main generator trip, blackout with unit trip logic strips 480V busses resulting in rod insertion.

The team will transition back to E-0. Sl will be manually actuated.

21 Sl pump will be in service. 23 Sl pump cannot be powered. 22 Sl pump is OOS. Charging will be established after manual action to align suction to the RWST. The team will diagnose RCS not intact and transition to E-1, Loss of Reactor or Secondary Coolant. The scenario is terminated after transition to E-1 has been made. Procedure Flow path: POP-2.1, ARP-SJF, AOP-INST-1, AOP-480V-1, POP-2.1, S.1, E-0, and E-1 U2 NRC 2014 Scenario 1: Power escalation from 90%, 23 SWP trips, PT-404 fails high, Loss of 480V Bus 6A, SBLOCA, ATWS, 21 AFW Pump failure, Auto Sl failure, Phase A failure. Page 2 of 16 CRITICAL TASKS: FR-S.1 ** C E-0 ** F E-0 ** D Insert negative reactivity into the core by at least one of the following methods before step 4 of FR-S.1 is complete:

o De-energize the Rod Drive MG Sets (can be satisfied by tripping turbine) o Manually insert the rods o Establish Emergency Boration Establish at least 400 gpm AFW flow to the S/Gs before completion of FR-S.1 step 3. Manually actuate at least one train of SIS actuated safeguards before completion of E-0 step 4 EXPLANATION OF CREDITED MALFUNCTIONS:

Event 1 -Power escalation.

ATC will withdraw control rods and/or dilute. The BOP will raise turbine power. Event 2 -A running service water pump will trip. The BOP will be credited with the malfunction since another pump will be started on his panel. Event 3-PT-404 (Steam Header Pressure) will fail which affects MFW Pump speed. The ATC is credited with the malfunction since feed pump control is on his panel. Event 4 -Due to initial conditions specified in the scenario, the loss of this bus will require pumps to be started on both control board operators' panels. (ATC charging pump, BOP SW pump) Event 7 -21 AFW Pump will not start and 23 AFW Pump does not have power due to loss of Bus 6A. Therefore, 22 AFW will require manual action to place in service. This will be performed by the BOP. Event 8-A manual safety injection will be required.

This was not credited to either control board operator since it could be performed by either the ATC or BOP. Event 9 -Phase A isolation will be manually actuated.

This occurs on the BOP's panel. U2 NRC 2014 Scenario 1: Power escalation from 90%, 23 SWP trips, PT-404 fails high, Loss of 480V Bus 6A, SBLOCA, ATWS, 21 AFW Pump failure, Auto Sl failure, Phase A failure. Page 3 of 16

<SCHEDULE>

2014_scenario_l_setup_revO.sch l 00:00:00 00:00:00 None Action

• Insert remote LOA-EPS070 to OUT

• Insert malfunction RLY-PPL487 to STUCK CONTACTS Insert malfunction RLY-PPL488 to STUCK CONTACTS ' Insert malfunction RL Y-PPL085 to STUCK CONTACTS to TRIP on event 2 ; 52-SI2A SI 22 480V BKR RACK 1 OUT/RACK IN 52-SI2B SI 22 480V AL T BKR RACK OUT/IN RELAY FAILURES:

SIA-l (A) SAFETY INJECTION AUTO

• MASTERRLY RELAY F AlLURES: SIA-2 (B) SAFETY INJECTION AUTO MASTERRLY

""""'

• -* ....... RELAY F AlLURES: C-Al CONT.ISOLATION PHASE A TRAIN A 52/RTA REACTOR TRIP BKR AFl AUX FEEDW ATER PUMP MOTORN0.21 SW3 SERVICE WATER PUMP MOTOR23 Insert malfunction XMT-FIXED OUTPUT: PT -404 STM SGN034A to 1200.00000 in 120 on 'HDR PRESS COND STEAM , event 3 DUMP 1. Insert malfunction MAL-EPS007D , 480 V BUS 6 A FAULT on event 4 Insert malfunction MAL-RCS006A U2 NRC 2014 Scenario 1: Power escalation from 90%, 23 SWP trips, PT-404 fails high, Loss of 480V Bus 6A, SBLOCA, ATWS, 21 AFW Pump failure, Auto Sl failure, Phase A failure. Page 4 of 16 Simulator Setup and Instructor Directions Setup/Event INSTRUCTOR ACTIONS EXPECTED RESPONSE/INSTRUCTOR CUES IC Reset Reset Simulator to 90% power ILO I C. SES Setup Run setup schedule file and verify Removes 22 SI pump OOS. Schedule File malfunctions and over-rides have Loads 23 SW pump failure on trigger 2. been entered. Loads SIA Train A and B failures.

Loads Phase A and B failures.

Loads R TB A and B failures.

Loads 21 AFW Pump failure. Loads PT-404 failure on trigger 3. Loads Loss ofbus 6A on trigger 4. Loads SBLOCA on trigger 5. Floor Setup 1. Start 23 Charging pump Provide turnover to the crew. and secure all others. 2. Place control switch for Watch team walks the panels and assumes the 22 SI pump to pullout and watch. apply a danger tag. Put protected equipment placards on 21 and 23 SI pumps. 3. Update the protected equipment computer.

4. Perform setup checklist.

Event 1 None-Power Ascension Perform field action LOAs as requested per NPO task list. Event 2 Actuate Trigger 2 MOC-SWS008 At lead evaluator direction Event: 2 Delay: 0 Final Value: TRIP Ramp: 0 Role Play If NPO Dispatched Report motor is extremely hot. Breaker indicates overcurrent trip. Check 23 SWP and breaker Event3 Actuate Trigger 3 XMT-SGN034A At lead evaluator direction Event: 3 Delay: 0 Final Value: 1200 Ramp: 120 Role Play Acknowledge requests for I&C will develop a troubleshooting plan. I&C to troubleshoot.

U2 NRC 2014 Scenario 1 : Power escalation from 90%, 23 SWP trips, PT -404 fails high, Loss of 480V Bus 6A, SBLOCA, ATWS, 21 AFW Pump failure, Auto Sl failure, Phase A failure. Page 5 of 16 Simulator Setup and Instructor Directions Setup/Event INSTRUCTOR ACTIONS Event 4 Actuate Trigger 4 At lead evaluator direction Role Play IfNPO Dispatched If NPO dispatched align 21 BATP to blender Event 5 Actuate Trigger 5 Role Play Role Play At lead evaluator direction When NPO dispatched to locally trip the reactor wait until emergency Boration has been aligned, then Delete BKR-PPL004 and needed if turbine is not manually tripped) NOTE-not required if the bus stripping occurs. At CCR request EXPECTED RESPONSE/INSTRUCTOR CUES 1\ MAL-EPS007D 480V BUS 6A FAULT IMF MAL-EPS007D Event: 4 Delay: 0 Final Value: TRUE Ramp: 0 Acrid odor at rear of bus 6A bus work. Supply breaker tripped on short term over-current.

No smoke or fire. Close 370 and open 369 1\ MAL-RCS006A SMALL BREAK LOCA LOOP A HOTLEG (NR) IMF MAL-RCS006A Event: 5 Delay: 0 Final Value: 1.0 Ramp: 300 Perform field action LOAs as requested per NPO task list. U2 NRC 2014 Scenario 1: Power escalation from 90%, 23 SWP trips, PT-404 fails high, Loss of 480V Bus 6A, SBLOCA, ATWS, 21 AFW Pump failure, Auto Sl failure, Phase A failure. Page 6 of 16 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 1 Page 1 of 2 Event

Description:

Power Escalation Time Position Applicant's Actions or Behavior Note: The reactivity plan for the power ascension should be developed by the team in the briefing room prior to taking the watch. The plan could call for dilution and/or rod withdrawal CRS Assigns roles for power ascension ATC Reviews reactivity plan ATC If rods are withdrawn:

• Places/verifies rods are in Manual

• Withdraws rods

• Observes:

0 Proper rod motion 0 Tavg 0 Power BOP Peer checks rod withdrawal ATC If dilution is performed:

• Places RCS Makeup control to Stop

• Place RCS Makeup Mode selector to Dilute

• Adjusts integrator to desired dilution amount

• Places RCS Makeup control to Start

• Observes:

0 Proper makeup response 0 Tavg 0 Power BOP Peer check dilution U2 NRC 2014 Scenario 1: Power escalation from 90%, 23 SWP trips, PT -404 fails high, Loss of 480V Bus 6A, SBLOCA, ATWS, 21 AFW Pump failure, Auto Sl failure, Phase A failure. Page 7 of 16 Op-T est No.: 1 Scenario No.: 1 Event No.: 1 Page 1 of 2 Event

Description:

Power Escalation Lead Evaluator When the following has been demonstrated/observed:

• Sufficient load ascension .

• Sufficient normal plant operations by the BOP . Then instruct Booth to insert Event 2. U2 NRC 2014 Scenario 1: Power escalation from 90%, 23 SWP trips, PT-404 fails high, Loss of 480V Bus 6A, SBLOCA, ATWS, 21 AFW Pump failure, Auto Sl failure, Phase A failure. Page 8 of 16 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 2 Page 1 of 1 Event

Description:

23 Service Water Pump Trips Time Position Applicant's Actions or Behavior BOP Diagnose that 23 SWP has tripped. BOP ofCRS Recommend I direct starting either 21 or 22 SWP per the alarm response procedure.

BOP Starts 21 or 22 SWP Note: Although not required, it is possible that the CRS may enter AOP-RW-001 BOP Refers to ARPs for alarms CRS Evaluate Tech Specs. LCO 3.7.8 will not be satisfied.

Condition A will apply placing plant in 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> action statement.

Lead Evaluator When the following has been demonstrated/observed:

• Service Water pressure has been stabilized

• T.S. have been evaluated Then instruct Booth to insert Event 3 U2 NRC 2014 Scenario 1: Power escalation from 90%, 23 SWP trips, PT-404 fails high, Loss of 480V Bus 6A, SBLOCA, ATWS, 21 AFW Pump failure, Auto Sl failure, Phase A failure. Page 9 of 16 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 3 Page 1 of 1 Event

Description:

PT -404 Steam Header Pressure fails high causing MBFPs to be placed in manual. Time Position Applicant's Actions or Behavior ATC Diagnosis failure of PT-404 high due to changes MFW Pump speed and meter indication ATC Place MFW Pump Master Speed Controller to manual to maintain SG levels CRS Directs team to perform immediate operator actions of AOP-INST-1 ATC Checks instruments listed in AOP-INST-1 CRS Implements 2-AOP-INST-1

• Verifies no other instrument failures

• Ensures actions have been taken to stabilize the plant

• Ensures steam dumps are in temperature mode Team Contact I&C to investigate PT -404 failure Lead Evaluator When the following has been demonstrated/observed:

• MFW Pumps have been placed in manual

• SG levels are stable

• I&C contacted Then instruct Booth to insert Event 4 U2 NRC 2014 Scenario 1: Power escalation from 90%, 23 SWP trips, PT -404 fails high, Loss of 480V Bus 6A, SBLOCA, ATWS, 21 AFW Pump failure, Auto Sl failure, Phase A failure. Page 10 of 16 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 4 Page 1 of 1 Event

Description:

480V Bus 6A fault. Time Position Applicant's Actions or Behavior Team Diagnose that 480V Bus 6A CRS Will enter AOP-480V-1 ATC Start 21 or 22 Charging Pump BOP Start 24 or 25 SWP ATC Ensure Primary Water Pump is in service Team Dispatch operator to monitor EDGs BOP Initiate Attachment 3:

• 6A will be confirmed to be faulted

• 23 EDG will be shutdown CRS Direct initiating SOP 5.2.1 to maintain vent header pressure ATC Verifies that Boric Acid Transfer Pump is in service CRS Evaluate Tech Specs. The most limiting T.S. action statement is per 3.8.4. Additionally, 3.8.9, 3.8.1, and 3.5.2 should be evaluated.

Because 22 Safety Injection pump was OOS and 23 has now lost power, the plant will have to proceed to Mode 5. Note: If needed, the booth will call as the Operations Manager to direct the CRS to proceed to shutdown and cool down. CRS Will begin plans for shutdown and cooldown to MODE 5. Lead Evaluator When the following has been demonstrated/observed:

• Plant is stabilized

• Tech Specs evaluated

• Shutdown being planned Then instruct Booth to insert Event 5 U2 NRC 2014 Scenario 1: Power escalation from 90%, 23 SWP trips, PT -404 fails high, Loss of 480V Bus 6A, SBLOCA, ATWS, 21 AFW Pump failure, Auto Sl failure, Phase A failure. Page 11 of 16 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 5 Page 1 of 1 Event

Description:

Small Break LOCA II Time Position Applicant's Actions or Behavior ATC Diagnose loss of RCS inventory based on PZR level trend Note: CRS may direct entry in AOP-LEAK-1 CRS Direct reactor trip and safety injection ATC Presses reactor trip push button on flight panel ATC Notes that reactor did not trip BOP Presses reactor trip push button on supervisory panel ATC Notes that reactor did not trip BOP Trips turbine CRS Directs team to perform immediate operator actions of FR-S.1 The team will now proceed to Event 6 for the ATWS U2 NRC 2014 Scenario 1: Power escalation from 90%, 23 SWP trips, PT-404 fails high, Loss of 480V Bus 6A, SBLOCA, ATWS, 21 AFW Pump failure, Auto Sl failure, Phase A failure. Page 12 of 16 Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.: 6/7/8/9 Page 1 of 3 Event

Description:

ATWS/Loss of 21 AFW Pump/Failure of Auto SI/Failure of Auto Phase A Time Position Applicant's Actions or Behavior Critical Task: Insert negative reactivity into the core by at least one of the following methods before step 4 of FR-S.1 is complete:

0 De-energize the Rod Drive MG Sets (can be satisfied by tripping turbine) 0 Manually insert the rods 0 Establish Emergency Boration ATC Manually drive control rods CRS/BOP Dispatch operator to locally trip reactor breakers Note: The reactor trip breakers will be opened locally after emergency boration is established.

BOP Verify turbine trip Critical Task: Establish at least 400 gpm AFV\f flow to the S/Gs before completion of FR-S.1 step 3. """'""":, *. _\ : BOP Increase speed on 22 AFW Pump and adjust FCV-405A-D to establish 800 gpm AFW flow (400 gpm will satisfy critical task) BOP Initiate Emergency Boration:

• Determine MOV-333 not powered and RWST will be used

• Open LCV-112B suction from RWST

• Close LCV-112C suction from VCT

• Place makeup control switch to stop Establish maximum charging flow BOP Verify RCS pressure < 2335 psig BOP Verify ventilation isolation Note: The CRS may direct the BOP to perform steps 1-9 of E-0 based on a caution in FR-S.1 U2 NRC 2014 Scenario 1: Power escalation from 90%, 23 SWP trips, PT-404 fails high, Loss of 480V Bus 6A, SBLOCA, ATWS, 21 AFW Pump failure, Auto Sl failure, Phase A failure. Page 13 of 16 Op-Test No.: 1 Scenario No.: 1 Event No.: 6/7/8/9 Page 1 of 3 Event

Description:

ATWS/Loss of 21 AFW Pump/Failure of Auto SI/Failure of Auto Phase A If not, the following step will be performed when the CRS exits FR-S.1 Critical Task: Manually actuate at least one train of SIS actuated safeguards before completion of E-O step 4 BOP ATC CRS TEAM BOP ATC Perform E-0 steps 1-9 per caution in FR-S.1:

• Verify reactor trip (will be tripped at this point)

• Verify turbine trip (will be tripped)

• Verify power to 480V busses (all but 6A will be powered)

• Check Sl status: o Will note Sl required but Auto Sl did not actuate o Will manually Sl

• Perform Attachment 1 of E-0 o Establish charging o Check electrical status o Secure condensate pumps o Verify FW isolation o Verify SW lineup o Verify Sl pump and valve alignment o Verify FCU alignment o Verify AFW flow-may reduce flow at this point o Verify Containment isolation

-will manually actuate Phase A o Checks containment spray status o Checks CCR AC Verify reactor is subcritical:

• Power range < 5%

• Negative SUR Returns to E-0 Performs or re-performs E-0 steps 1-4:

• Verify reactor trip (will be tripped at this point)

• Verify turbine trip (will be tripped)

• Verify power to 480V busses (all but 6A will be powered)

• Check Status Performs Attachment 1 of E-0 if not already in progress Verifies AFW flow-flow may be reduced at this time if not already done. U2 NRC 2014 Scenario 1: Power escalation from 90%, 23 SWP trips, PT-404 fails high, Loss of 480V Bus 6A, SBLOCA, ATWS, 21 AFW Pump failure, Auto Sl failure, Phase A failure. Page 14 of 16 Op-Test No.: 1 Scenario No.: 1 Event No.: 6/7/8/9 Page 1 of 3 Event

Description:

ATWS/Loss of 21 AFW Pump/Failure of Auto SI/Failure of Auto Phase A ATC/BOP Verify Sl flow ATC/BOP Check RCP cooling ATC/BOP Start NESW pump ATC Check RCS temperature ATC Check PORV status ATC Check if RCPs should be stopped (trip criteria should not be met) ATC Check if SGs are faulted ATC Check if SG tubes are intact ATC Check if RCS is intact CRS Transition to E-1 Lead Evaluator Terminate scenario U2 NRC 2014 Scenario 1: Power escalation from 90%, 23 SWP trips, PT-404 fails high, Loss of 480V Bus 6A, SBLOCA, ATWS, 21 AFW Pump failure, Auto Sl failure, Phase A failure. Page 15 of 16 EMERGENCY PLAN DECLARATION Site Area Emergency EAL SS2.1 Failure of an automatic trip signal to reduce power range< 5% AND Manual trip actions taken at the reactor controls console (manual reactor trip switches) are not successful U2 NRC 2014 Scenario 1: Power escalation from 90%, 23 SWP trips, PT -404 fails high, Loss of 480V Bus 6A, SBLOCA, ATWS, 21 AFW Pump failure, Auto Sl failure, Phase A failure. Page 16 of 16 Facility:

• Indian Point 2 Scenario No.: 2 Op-T est No.: _1 Examiners:

Operators:

Initial Conditions:

Reset simulator to 100% power IC Load Simulator Schedule-Scenario2 The Plant is at 1 00% power. Ensure 25 SWP and 22 Charging Pump in service. Turnover:

Perform power reduction to 90% for turbine valve testing. Event Malf. No. Event Event No. Type* Description 1 N/A R (ATC) N (CRS) Power Reduction N{BOP) 2 MOT-C (ALL) 21 Condensate Pump trip. TS for AFD. CFW001B TS(CRS) 3 BST-C(BOP) RCP Thermal Barrier CCW Return Valve (FCV-625) spurious CCW009A C(CRS) closure. 4 MAL-C (ALL) EPS007B TS(CRS) 480V Bus 3A fault. 5 CNH-C(ATC) PCS007D C_{CRSl 22 FRV fails in auto. 6 CVH-M(ALL) 22 FRV fails in manual. CFW005A 7 MOC-AFW002 M(ALL) Failure of 22 and 23 AFW to start which along with other CVH-conditions leads to loss of heat sink. ATS017B 8 AOV-C(ALL) MSS036AI Failure of Turbine Stop/Control Valve pair. CVH-MSS030B 9 AOV-C(ALL) RCS002A Failure of PORV requiring opening of reactor head vent valves * (N)ormal, JRleactivi!Y, (l)nstrument, (C)om_ponent, (M)ajor U2 NRC 2014 Scenario 2: Power reduction, 21 Condensate Pump trip, FCV-625 spurious closure, Loss of 480V Bus 3A, MFRV failure, Loss of heat sink, Failure of turbine stop/control valve pair, PORV failure requiring opening reactor head vent valves. Page 1 of 19 SESSION OUTLINE: The evaluation begins with the plant at 100% power steady state operation with no significant equipment out of service. The team has been directed to lower power to 90% for turbine valve testing. After taking the watch, the team will begin reducing load. Once reduction is started 21 Condensate Pump will trip. This will cause the team to rapidly reduce power and challenge TS 3.2.3 for Axial Flux Difference.

When the team has stabilized the plant (or is reducing power to <50%), MOV-625 will spuriously close. This valve is the CCW return valve from the RCP thermal barriers.

The team will re-open the valve using ARP guidance.

Subsequently, a fault will occur on 480V Bus 3A. The team will take actions in accordance with AOP-480V-1, "Loss of Normal Power to any Safeguards 480V Bus." Due to the fault on Bus 3A, 22 EDG cannot re-energize the bus. TS require plant shutdown.

After the team stabilizes the plant and evaluates tech specs, 22 FRV will fail closed in automatic.

Manual control will work initially, but the valve will eventually fail closed regardless of position.

This will lead to an automatic reactor trip due to low SG level or the team will trip the reactor manually before the trip setpoint is reached. When the reactor is tripped, the turbine upper left stop and control valve pair fail to close. MSIV's must be manually closed to trip the turbine, but the valves will initially fail open requiring local action. The MSIVs will be closed when SG inventory is reduced to a value closer to bleed and feed criteria.

23 AFW Pump will not auto start and will not be able to be manually started from the Control Room due to 480V circuit breaker failure. 22 AFW Pump will not be available due to the governor valve not opening. 21 AFW pump cannot be run since 3A is not powered. The team will transition to FR-H.1, "Loss of Secondary Heat Sink" due to a loss of AFW flow. SG WR levels will lower until bleed and feed is required.

One PRZR PORV will not open when required.

The crew will open the Reactor Head Vent valves. After the head vent valves are opened, 23 AFW pump from its normal supply after racking the breaker out and back in. The team will restore AFW flow to 23 and 24 SGs. The scenario can be terminated after the head vent valves have been closed, or at the discretion of the lead evaluator.

Procedure flow path: POP-2.1, AOP-FW-1, ARP-SGF, AOP-480V-1, AOP-FW-1, E-0, FR-H.1 U2 NRC 2014 Scenario 2: Power reduction, 21 Condensate Pump trip, FCV-625 spurious closure, Loss of 480V Bus 3A, MFRV failure, Loss of heat sink, Failure of turbine stop/control valve pair, PORV failure requiring opening reactor head vent valves. Page 2 of 19 CRITICAL TASKS: E-0 --P FR-H.1 --F Manually trip the main turbine before a severe (orange-path) challenge develops to either the sub-criticality or the integrity CSF or before transition to ECA-2.1, whichever happens first Establish RCS bleed and feed when the average of the three lowest S/G levels reach 20% WR. At the discretion of the Lead Evaluator, the following CT may also be evaluated:

FR-H.1 --G Close all reactor vessel head vent valves before the end of the scenario EXPLANATION OF CREDITED MALFUNCTIONS:

Event 1: Power reduction.

The ATC gets credit for a reactivity manipulation for boration.

The BOP and CRS get credit for a normal evolution.

Event 2: 21 Condensate Pump trip will require further boration and power reduction, so all operators are credit with this malfunction.

Maintaining axial flux distribution in required band is a challenge for this event, so the CR will have to evaluate tech specs for axial flux difference.

Event 3: FCV-625 will close. The valve is on the BOP panel and will be reopened per the ARP or AOP. Event 4: Loss of 480V Bus 3A will require restoration of equipment on both the ATC and BOP panels. This will put the plant in a tech spec action statement.

Event 5: The FRV is on the ATC panel and will initially be placed in manual to control 22 SG level. Event 6: The FRV failing in manual will lead the team to trip the reactor or cause an automatic trip. Event 7: The failure of 22 and 23 AFW Pumps in conjunction with loss of 480V Bus 3A (21 AFW Pump power) will lead to a loss of heat sink. Event 8: The failure of the stop and control valve pair will require closing MSIVs and drive the team to bleed and feed criteria.

Event 9: The failure of the PORV will require the use reactor head vent valves for bleed and feed. U2 NRC 2014 Scenario 2: Power reduction, 21 Condensate Pump trip, FCV-625 spurious closure, Loss of 480V Bus 3A, MFRV failure, Loss of heat sink, Failure of turbine stop/control valve pair, PORV failure requiring opening reactor head vent valves. Page 3 of 19 2014_scenario_2_setup_rev0 At Time On , Event 00:00:00 None 00:00:00

• None '00:00:00 None i 00:00:00 None '00:00:00 None i 00:00:00 None i 00:00:00 None '00:00:00

• None 00:00:00 i None i

• 1 00:00:00 None Action , Insert malfunction MOT-CFW001 B to 100.00000 on i event 2 i Insert malfunction BST-! CCW009A to TRIP (JBST=T} ' on event 3 delete in 5 Insert malfunction MAL-* EPS007B on event 4 Insert malfunction CNH-PCS007D to 0 in 180 on event 5 Insert malfunction CVH-CFW005A to CLOSE on event 6 Insert malfunction MOC-AFW002 to ASIS

• Insert malfunction CVH-. ATS017B to 0 Insert malfunction AOV-MSS036A to FAIL AS IS Insert malfunction RCS002A to FAIL AS IS Insert malfunction MSS030B to 45.00000 on event 30 ' Description BRG 1 FAILURE: CP21 i CONDENSATE PUMP 21 MTR FAILURE: FIC-625-H FCV-625 HIGH FLOW CLOSEURE MCB CTRLR FIXED AUTO ONLY: FIC-427 SG 22 FD REG VLV CONT AIM : FAILMODE:

FCV-427 SG 22 FW REGULATOR GENERAL FAILURE: MS-863 HP TURB STOP FROM SG21 GENERAL FAILURE: PCV-455C PZR POWER . OPERA TED RELIEF VALVE U2 NRC 2014 Scenario 2: Power reduction, 21 Condensate Pump trip, FCV-625 spurious closure, Loss of 480V Bus 3A, MFRV failure, Loss of heat sink, Failure of turbine stop/control valve pair, PORV failure requiring opening reactor head vent valves. Page 4 of 19 Simulator Setup and Instructor Directions Setup/Event INSTRUCTOR ACTIONS EXPECTED RESPONSE/INSTRUCTOR CUES IC Reset 228 or saved 1 00% IC Reset Simulator to 100% power IC SES Setup Run schedule and verify Loads 22 & 23 AFW pumps failures Schedule malfunctions and over-Fails Upper Left Stop Valve File rides have been entered Loads PORV 455C failure Loads MSIV failures Loads 625 failure on event 3 Loads bus 3A fault on event 4 Loads 22 FRV auto failure on event 5 Loads 22 FRV manual failure on event 5 Floor Setup Ensure that 22 Charging Update Update the Protected Equipment Pump is in service. Computer display. Risk is green. Ensure that 25 SWP is in service. Watch team walks the panels and assumes the watch. Perform setup checklist Distribute Turn over sheets Event1 Power Reduction Provide information as requested by team. Event2 Actuate Event 2 21 Condensate Pump Trip Role Play When called about 21 Motor is very hot Condensate Pump At lead evaluator direction Event 3 Actuate Event 3 Spurious closure of MOV-625 At lead evaluator direction Role Play If NPO sent to investigate NPO reports no obvious damage, but a MOV-625 closure team is removing scaffold in the Pipe Pen. Area immediately adjacent to the flow switch and may have bumped the instrument.

U2 NRC 2014 Scenario 2: Power reduction, 21 Condensate Pump trip, FCV-625 spurious closure, Loss of 480V Bus 3A, MFRV failure, Loss of heat sink, Failure of turbine stop/control valve pair, PORV failure requiring opening reactor head vent valves. Page 5 of 19 Simulator Setup and Instructor Directions Setup/Event INSTRUCTOR ACTIONS EXPECTED RESPONSE/INSTRUCTOR CUES Event 4 Actuate Event 4 Bus 3A Fault At lead evaluator direction Role Play If NPO sent to investigate NPO reports no obvious damage, but bus Bus 3A Trip supply breaker tripped on over current and strong odor of ozone. Acknowledge requests for I&C to troubleshoot I&C will develop a troubleshooting plan Event 5 Actuate Event 5 22 FRV fails in auto At lead evaluator direction Role Play If asked to investigate 22 Valve appears normal. Cannot tell reason FRV for failure. Event 6 Actuate Event 6 22 FRV fails in manual At lead evaluator direction NOTE: When Rx is tripped Upper left stop and control valve do not close. MSIVs will not close NOTE: When SG WR Level reaches about 30%, modify the following malfunctions to 0%: AOV-SGN001 B AOV-SGN002B AOV-SGN003B AOV-SGN004B Role Play As NPO sent to close MSIVS, let the control room know that either you closed them or they had closed before you got there depending on timing. U2 NRC 2014 Scenario 2: Power reduction, 21 Condensate Pump trip, FCV-625 spurious closure, Loss of 480V Bus 3A, MFRV failure, Loss of heat sink, Failure of turbine stop/control valve pair, PORV failure requiring opening reactor head vent valves. Page 6 of 19 Simulator Setup and Instructor Directions Setup/Event INSTRUCTOR ACTIONS EXPECTED RESPONSE/INSTRUCTOR CUES Role Play AFW Status: 21 de-energized 22 governor valve will not open 23 pump appears normal. Breaker appears normal. Role Play When NPO dispatched to Close breaker for HCV-31 00 energize head vent valves 0 MCC 26A Sheet 2 (EPS 18) LOA-at MCC 26A/B EPS431 Close breaker for HCV-31 01 0 MCC 268 Sheet 2 (EPS 22) LOA-EPS523 After head vent valves Fix 23 ABFP 480V brkr: Call CCR and have been opened: request 23 ABFP control switch be placed in pullout to support breaker check. From the Director-Delete MOC-AFW002.

NPO reports that the 480V breaker for 23 ABFP has been swapped with the spare breaker. Request CCR to attempt to start 23 ABFP. Role Play At CCR request Perform various LOA's per NPO local task list U2 NRC 2014 Scenario 2: Power reduction, 21 Condensate Pump trip, FCV-625 spurious closure, Loss of 480V Bus 3A, MFRV failure, Loss of heat sink, Failure of turbine stop/control valve pair, PORV failure requiring opening reactor head vent valves. Page 7 of 19 Op-Test No.: 1 Scenario No.: 2 Event No.: 1 Page 1of 2 Event

Description:

Power Reduction Time Position Applicant's Actions or Behavior Note: The reactivity plan for the power reduction should be developed by the team in the briefing room prior to taking the watch. The plan could call for boration and/or rod insertion CRS Assigns roles for power reduction ATC Reviews reactivity plan ATC If rods are inserted:

• Places/verifies rods are in Manual

• Inserts rods specified number of steps

• Observes:

0 Proper rod motion 0 Tavg 0 Power BOP Peer checks rod insertion ATC If boration is performed:

• Energize All Pressurizer Heaters

• Places RCS Makeup control to Stop

• Place RCS Makeup Mode selector to borate

• Adjusts integrator to desired boration amount

• Places RCS Makeup control to Start

• Observes:

0 Proper makeup response 0 Tavg 0 Power BOP Peer check boration U2 NRC 2014 Scenario 2: Power reduction, 21 Condensate Pump trip, FCV-625 spurious closure, Loss of 480V Bus 3A, MFRV failure, Loss of heat sink, Failure of turbine stop/control valve pair, PORV failure requiring opening reactor head vent valves. Page 8 of 19 Op-Test No.: 1 Scenario No.: 2 Event No.: 1 Page 1of 2 Event

Description:

Power Reduction ATC/BOP Initiate Turbine Load Reduction at desired rate

• Governor (Preferred)

• Load Limit 1

• Load Limit 2 ATC Maintain the manual setpoint for the MFRV Controllers Nulled. ATC Adjust Control Rod Position per TS and Graph-RPC-16 Lead Evaluator When the following has been demonstrated/observed:

• Sufficient load reduction .

• Sufficient normal plant operations by the BOP . Then instruct Booth to insert Event 2 U2 NRC 2014 Scenario 2: Power reduction, 21 Condensate Pump trip, FCV-625 spurious closure, Loss of 480V Bus 3A, MFRV failure, Loss of heat sink, Failure of turbine stop/control valve pair, PORV failure requiring opening reactor head vent valves. Page 9 of 19 Op-Test No.: 1 Scenario No.: 2 Event No.: 2 Page 1 of 1 Event

Description:

21 Condensate Pump Trip Time Position Applicant's Actions or Behavior BOP Announces 21 Condensate Pump tripped after observing 6.9 KV Motor Trip Alarm and indications of pump trip CRS Instructs team to perform immediate operator actions of AOP-FW-1 ATC Checks MFW Pumps are both in service and announces that immediate actions are complete ATC/BOP Continue load reduction to get steam flow ::::: feed flow:

• Continue/increase boration

• Operate governor to reduce turbine load CRS Evaluate axial flux difference to determine if TS 3.2.3 is met. Depending on team response could be in:

• 15 minute action to restore AFD with additional 15 minutes to get < 90% power.

• 30 minute action to _get to< 50% Qower. ATC/BOP May neeed to remove windup from FRVs by placing in manual and returning to automatic.

ATC/BOP May place MFW master speed controller to manual ATC/BOP May place FRVs in manual Lead Evaluator When the plant has been stabilized and AFD TS has been addressed:

Then instruct Booth to insert Event 3 U2 NRC 2014 Scenario 2: Power reduction, 21 Condensate Pump trip, FCV-625 spurious closure, Loss of 480V Bus 3A, MFRV failure, Loss of heat sink, Failure of turbine stop/control valve pair, PORV failure requiring opening reactor head vent valves. Page 10 of 19 Op-Test No.: _1_ Scenario No.: __L Event No.: _L Page _1_of .1 Event

Description:

RCP Thermal Barrier CCW Return Valve (FCV-625) spurious closure. Tr Position Applicant's Actions or Behavior BOP Notes CCW Thermal Barrier Return Low Flow alarm BOP Observes FCV-625 has gone closed BOP Refers to ARP-2-ARP-SGF Note: CRS should determine based on ARP guidance and indications that the closure was spurious and re-opening the valve is appropriate.

If the valve remains closed, the scenario can continue.

BOP Re-open FCV-625 BOP Direct Nuke NPO to monitor flow at Fl-625 Lead Evaluator When valve is re-opened, or it is clear it will remain closed, instruct Booth to initiate Event 5. U2 NRC 2014 Scenario 2: Power reduction, 21 Condensate Pump trip, FCV-625 spurious closure, Loss of 480V Bus 3A, MFRV failure, Loss of heat sink, Failure of turbine stop/control valve pair, PORV failure requiring opening reactor head vent valves. Page 11 of 19 Op-Test No.: 1 Scenario No.: 2 Event No.: 4 Page 1 of 1 Event

Description:

Time Position Examinee's Actions or Behavior BOP/ATC Diagnose bus 3A de-energized:

• Numerous alarms

• 22 EDG Running

• Loss of running charging pump

• Indications for Bus 3A Normal Feed Breaker CRS Announces entry into AOP-480V-1.

ATC Start 21 or 23 Charging pump and adjust speed to match 22 prior to trip. If flashing in letdown line occurs, then first close LCV-459, start a charging pump and re-establish letdown per 2-SOP-3.1 BOP Check CCW pumps running and 625 open CRS Check SW Pressure -1 ,2,3 Header pressure is low May start 21 or 23 SWP Dispatch NPO to monitor EDGs Initiate review of the following TS to determine required actions based on plant conditions:

3.8.9 Distribution Systems-Operating Condition A Determine that bus 3A is inoperable putting plant in 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> action statement.

Based on the faulted bus the team may assume shutdown should be commenced at this time. Lead Evaluator When plant is stable and tech specs have been addressed:

Then instruct Booth to insert Event 5 U2 NRC 2014 Scenario 2: Power reduction, 21 Condensate Pump trip, FCV-625 spurious closure, Loss of 480V Bus 3A, MFRV failure, Loss of heat sink, Failure of turbine stop/control valve pair, PORV failure requiring opening reactor head vent valves. Page 12 of 19 Op-Test No.: 1 Scenario No.: 2 Event No.: 5 Page 1 of 1 Event

Description:

22 FRV fails in auto Time Position Applicant's Actions or Behavior ATC Diagnose 22 FRV failure based on lower level on all channels.

Steam Generator Level Deviation Alarm may annunciate.

ATC Places 22 FRV in manual and stabilizes 22 SG level. CRS Announces to team to perform immediate operator actions of either AOP-INST-1 or AOP-FW-1 TEAM Goes through AOP. No actions are taken other than controlling 22 SG level in manual Lead Evaluator When the SG is stable: Then instruct Booth to insert Event 6 U2 NRC 2014 Scenario 2: Power reduction, 21 Condensate Pump trip, FCV-625 spurious closure, Loss of 480V Bus 3A, MFRV failure, Loss of heat sink, Failure of turbine stop/control valve pair, PORV failure requiring opening reactor head vent valves. Page 13 of 19 Op-Test No.: 1 Scenario No.: 2 Event No.: 6 Page 1of 2 Event

Description:

22 FRV fails in manual Time Position Examinee's Actions or Behavior Note: If team did not stabilize 22 SG level for previous event, and automatic or manual reactor trip may have already occurred.

ATC Notices that 22 SG level is trending down and 22 FRV is not responding.

ATC Trips reactor CRS When Unit trips, direct team to perform immediate actions of E-0

• Verifies immediate actions using the procedure . When the CRS directs "Perform the Immediate Operator Actions of E-0, the A TC and BOP will first perform the IOAs silently only announcing unexpected conditions.

The crew will then re-perform the IOAs verbalizing each item. ATC Verifies Reactor Trip:

• Reactor trip and bypass breakers open

• Rod bottom lights lit

• IRPis < 12.5 inches

• Nuclear flux decreasing Critical Task: Manually trip the mainturbil"le before a severe (orange-path) challenge develops to either the sub-criticality or the integrity CSF or before transition to ECA-2.1, whichever happens first.. . . h .. ::.*. .. .i *** ,,, U2 NRC 2014 Scenario 2: Power reduction, 21 Condensate Pump trip, FCV-625 spurious closure, Loss of 480V Bus 3A, MFRV failure, Loss of heat sink, Failure of turbine stop/control valve pair, PORV failure requiring opening reactor head vent valves. Page 14 of 19 Op-Test No.: 1 Scenario No.: 2 Event No.: 6 Page 1of 2 Event

Description:

22 FRV fails in manual ATC Verifies Turbine Trip:

• Observes stop and control valve are not all closed

• Trip Turbine

• Takes MSIV switches to closed

• Notes MSIVs did not close

• Dispatches NPO to locally close MSIVs (MSIVs will be closed when sufficient mass has been removed from SGs to meet bleed and feed criteria without lengthy delay. BOP Check status of 480V buses:

• Observe ALL busses energized from Offsite Power except Bus 3A Note: Depending on timing, an Sl signal may be present at step 4 of E-0. The scenario will progress with or without an Sl signal at this point. If there is no Sl signal, an evaluator will have to step in as ST A when transition to ES-0.1 occurs or if CRS is looking for concurrence to go to FR-H.1 for the loss of heat sink. This will not be necessary if there is an Sl signal. ATC Check Sl status Determine Sl is Actuated

• Any Sl Annunciator

-Lit

• Sl Pumps Any Running Determines Sl NOT actuated and NOT required BOP/ATC Check AFW Status

• Observes no AFW flow

• Attempted to use 22 AFW pump to establish flow CRS Transition to ES-0.1 U2 NRC 2014 Scenario 2: Power reduction, 21 Condensate Pump trip, FCV-625 spurious closure, Loss of 480V Bus 3A, MFRV failure, Loss of heat sink, Failure of turbine stop/control valve pair, PORV failure requiring opening reactor head vent valves. Page 15 of 19 Op-Test No.: 1 Scenario No.: 2 Event No.: 7/8/9 Page 1 of 3 Event

Description:

Failure of 22 and 23 AFW to start which along with other conditions leads to loss of heat sink I Failure of Turbine Stop/Control Valve pair I Failure of PORV requiring opening of reactor head vent valves Time Position Applicant's Actions or Behavior Note: Bleed and Feed criteria of the average of the three lowest SGs being < 20% will eventually be met. How much of the early steps of FR-H.1 are performed will depend on when this happens. These steps assume that criteria are met when step 2 is read. CRS Enters FR-H.1 Team Verifies secondary heat sink is required:

RCS press > SG press RCS temp > 350F Critical.

Task: Establish RCS bleed arld.feed when.the average of the three lowest S/G levels reach 20% WR BOP/ATC Recognizes Bleed and Feed criteria are met ATC/BOP Stops all RCPs ATC/BOP Actuates Sl if not already done ATC Starts 21 and 23 charging pumps BOP Opens HCV-142 ATC Verifies HHSI pumps are running ATC/BOP Verifies Sl valve lineup ATC Opens PORV block valves ATC Attempt to open PORVs, observes 455C will not open BOP Dispatches NPO to enerQize HCV-31 00/3101 ATC/BOP Opens HCV-3100/3101 ATC/BOP Reset Sl:

• Check CCW pumps

• Place key switches in Sl reset position

• Reset Sl U2 NRC 2014 Scenario 2: Power reduction, 21 Condensate Pump trip, FCV-625 spurious closure, Loss of 480V Bus 3A, MFRV failure, Loss of heat sink, Failure of turbine stop/control valve pair, PORV failure requiring opening reactor head vent valves. Page 16 of 19 Op-Test No.: 1 Scenario No.: 2 Event No.: 7/8/9 Page 1 of 3 Event

Description:

Failure of 22 and 23 AFW to start which along with other conditions leads to loss of heat sink I Failure of Turbine Stop/Control Valve pair I Failure of PORV requiring opening of reactor head vent valves ATC/BOP Reset Phase A:

• Place IVSW switches to open for 1410, 1413, 3518, 3519

• Place containment rad monitor weld channel valves to open

• Verify airlocks in incident

• Close all remaining Phase A valve switches

• Reset Phase A Note: At this point, the FSS will call about restoring 23 AFW pump. The team will be asked to place the switch in pull to lock. After another few minutes, the team will be told that 23 AFW should be available.

CRS ATC/BOP ATC/BOP Lead Evaluator BOP Evaluate SG conditions per foldout prior to re-establishing AFW flow to 23 and 24 SGs Start 23 AFW pump Establish 400 gpm total to 23 and 24 SGs At this point the scenario could be terminated instead of waiting for the team to close reactor head vent valves. Team members may be questioned about when these valves would be closed. Perform Steps 1-9 of E-0:

• Verify reactor trip

• Verify turbine trip

• Verify power to 480V busses -3A not energized

• Check Sl status

• Perform Attachment 1 (may have already been done): o Verify charging o Check open 345KV disconnects o Reset lighting and MCCs o Stop condensate pumps o Verify FW isolation U2 NRC 2014 Scenario 2: Power reduction, 21 Condensate Pump trip, FCV-625 spurious closure, Loss of 480V Bus 3A, MFRV failure, Loss of heat sink, Failure of turbine stop/control valve pair, PORV failure requiring opening reactor head vent valves. Page 17 of 19 Op-Test No.: 1 Scenario No.: 2 Event No.: 7/8/9 Page 1 of 3 Event

Description:

Failure of 22 and 23 AFW to start which along with other conditions leads to loss of heat sink I Failure of Turbine Stop/Control Valve pair I Failure of PORV requiring opening of reactor head vent valves 0 Verify SW pumps 0 Verify HHSI pumps and valves 0 Verify containment cooling and isolation 0 Verify AFW 0 Check CCR ventilation

• Check RCP cooling ATC Check if at least one SG NR is >10% Critical Task: Close all. reactor vessel head vent valves before the end of the scenario.

This action cannot be done until SG NR > 1 0%. ATC Verify GETs are decreasing.

ATC Close reactor head vent valves Lead Evaluator Terminate scenario.

U2 NRC 2014 Scenario 2: Power reduction, 21 Condensate Pump trip, FCV-625 spurious closure, Loss of 480V Bus 3A, MFRV failure, Loss of heat sink, Failure of turbine stop/control valve pair, PORV failure requiring opening reactor head vent valves. Page 18 of 19 EMERGENCY PLAN DECLARATION Site Area Emergency EAL FS1.1 Loss or potential loss of any two barriers.

Loss of heat sink will lead to a call based on the Fission Product Barrier Matrix: Potential Loss of Fuel Cladding (A.CSFST)

Potential Loss of RCS (A.CSFST)

U2 NRC 2014 Scenario 2: Power reduction, 21 Condensate Pump trip, FCV-625 spurious closure, Loss of 480V Bus 3A, MFRV failure, Loss of heat sink, Failure of turbine stop/control valve pair, PORV failure requiring opening reactor head vent valves. Page 19 of 19 Facility:

Indian Point 2 Scenario No.: 3 Op-Test No.: _1 Examiners:

Operators:

Initial Conditions:

Reset simulator to 4% power IC Load Simulator Schedule-Scenario3 The Plant is at 4% power. 23 Charging Pump is OOS. 22 MBFP is OOS. PORV 456 is OOS Ensure 21 Charging Pump in service, Ensure 23 CCW Pump is in service Turnover:

Perform power ascension to 1 0% for turbine sync. Event Malf. No. Event Event No. Type* Description 1 N/A R (ATC) N (CRS) Power Ascension N (BOP) 2 MOT-C (ATC) CVC003B C(CRS) 21 Charging Pump trip TS(CRS) 3 MOC-C (BOP) 23 CCW pump trip with failure of other CCW pumps to CCW003A C (CRS) autostart 4 XMT-TS(CRS) Control Rod 08 IRPI fails low. CRF012A 5 XMT-C (ALL) PT-408A fails high causing 21 MFW Pump to go to minimum CFW036A speed. 6 MAL-M(ALL) 21 MFW Pump trips. ATS005A 7 MAL-RCS014D M(ALL) 24 SGTR. 8 AOV-C(ALL) Failure of air to containment making PORVs required for CAS009A depressurization.

9 AOV-C(ALL) RCS002A PORV will not close causing team to transition to ECA-3.1 * (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor U2 NRC 2014 Scenario 3: Power ascension, charging pump trip, IRPI failure, PT-408A failure, MFW pump trip, SGTR, instrument air failure, PORV failure. Page 1 of 19 SESSION OUTLINE: The evaluation begins with the plant at 4% power during startup. The following equipment is out of service:

• PORV 456 due to blowing fuses.

• 23 Charging Pump for seal replacement.

• 22 MBFP since forced outage work is not complete.

When the team takes the watch, they will raise power in anticipation of putting the MTG in service. Following some power ascension, 21 Charging Pump will trip. 22 Charging Pump will be placed in service. TR0-3.1.8.1 will not be met putting the plant in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> AOT. 23 CCW Pump will trip and the low pressure auto start has been disabled for 21 and 22 CCW Pumps. The BOP will start a CCW Pump per ARP-SGF. Control Rod 08 IRPI fails low. The team will take actions in accordance with AOP-ROD-1, "Rod Control and Indication Systems Malfunction." PT-408A will fail high causing 21 MBFP to slow down to minimum. If the team does not recognize the failure and place 21 MBFP in manual, the reactor will trip on low SG level. If the team places the pump in manual, an overspeed trip of the MFW pump will eventually be inserted.

With power above 4%, the team will manually trip the reactor. If power is < 4% and the team does not trip the reactor, the SGTR can be initiated which will drive a trip and Sl. When the reactor trips, a SGTR will occur in 24 SG. The team will take actions per E-0, "Reactor Trip or Safety Injection".

The team will then transition to E-3, "Steam Generator Tube Rupture." When Sl is reset, PCV-1228 (Instrument Air to Containment) will fail in the closed position.

The team will need to use a Pressurizer PORV to depressurize.

When the team goes to close the PORV, the valve will fail open. This will cause the team to ultimately go to ECA-3.1 for recovery.

Procedure flow path: POP-1.3, AOP-CVCS-1, ARP-SGF, AOP-ROD-1, AOP-AIR-1, O, E-3, ECA-3.1 U2 NRC 2014 Scenario 3: Power ascension, charging pump trip, IRPI failure, PT-408A failure, MFW pump trip, SGTR, instrument air failure, PORV failure. Page 2 of 19 CRITICAL TASKS: E-3 --A E-3 --B Isolate feedwater flow to and steam flow from the ruptured SG before transition to ECA-3.1 occurs. Establish and maintain RCS temperature so that transition from E-3 does not occur due to either of the following:

• RCS temperature TOO HIGH to maintain required sub-cooling in E-3 step16 table, OR

• RCS temperature TOO LOW results in a severe challenge to the Sub-criticality or Integrity CSF. EXPLANATION OF CREDITED MALFUNCTIONS:

Event 1 -Power ascension.

This is a reactivity manipulation for ATC. BOP will be controlling SG levels manually and CRS will be supervising evolution.

Event 2 -Charging pump trip. The ATC will start another charging pump. Since two charging pumps are now inoperable, the CRS will have to determine that the plant is in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> action statement.

Event 3 -The running CCW pump will trip and the other two will have all auto starts blocked. The BOP will have to start a CCW pump. Event 4-IRPI for rod D-8 will fail. The CRS will evaluate TS 3.1. 7 for the inoperable IRPI. Event 5 -PT -408A (MFW pressure) fails high which causes the MFW pump to go to minimum speed. The ATC will have to place MFW control in manual. The BOP will have to make adjustments to Low Flow FRVs. Event 6 -The only MFW pump trips which will require a reactor trip if power when above 4%. Event 7-SGTR in 24 SG causes Sl to be initiated.

Diagnosis is a challenge at low power since there will be less radiation monitor response.

Event 8 -Failure of instrument air to containment needs to be diagnosed by the BOP and will change the depressurization method used by the ATC. Event 9 -The PORV failing to close will lead team to contingency procedure.

U2 NRC 2014 Scenario 3: Power ascension, charging pump trip, IRPI failure, PT-408A failure, MFW pump trip, SGTR, instrument air failure, PORV failure. Page 3 of 19 2014 _scenario_

3 _setup _revO. html At Time . 00:00:00 ' None i Create event 30 jbkrta==O -desc jbkrta 1 rx trip a ! 00:00:00 None 00:00:00 1 None 00:00:00 None Insert malfunction MOC-1 AFW002 to AUT CLS Insert remote LOA-EPS012 to OUT Insert malfunction CVC003B to 100.00000 on event 2 . Insert malfunction / CCW017B to 0 i Insert malfunction CCW003 to TRIP on event 3 1 Insert malfunction XMT-1 CRF012A to 1.4013e-045 on event 4 Insert malfunction XMT-. CFW036A to 1400.00000 in 30 on event 5 Insert malfunction ATS005A on event 6 . Insert malfunction MAL-00:00:00 None RCS014D to 10.00000 on event 30 : Insert malfunction AOV-. 00:00:00

• None CAS009A to CLOSE on event 1 29 Insert malfunction AOV-1 RCS002A to OPEN on event 9 pb/rs-1 pushbutton AF3 AUX FEEDW ATER PUMP MOTORN0.23 52-C3 C 23 480V BKR RACK OUT/RACK IN i BRG 1 FAILURE: C1 CHARGING PMP21 MOTOR SETPOINT DRIFT: PC-600-L ACS/COMP CLNG PUMP DISCH PRESS FIXED OUTPUT: LVDT-D8 LVDT FORCRDMD8 FIXED OUTPUT: PT -408A 26 HTRS COMMON OUTLET PRESSURE MBFP 21 OVERSPEED STEAM GENERA TOR 24 TUBE LEAK(NR) GENERAL FAILURE: PCV-1228 AIR FILTER DISCHARGE

-CONT BLDG GENERAL FAILURE: PCV-455C I PZR POWER OPERA TED RELIEF VALVE 535 PZR PORV ISOLATION VALVE U2 20 5 14 3: Pov.:er charging pump trip, IRPI failure, PT -408A failure MFW pump tnp, GTR, mstrument a1r fa1lure, PORV failure. ' Page 4 of 19 Simulator Setup and Instructor Directions Setup/Event INSTRUCTOR ACTIONS EXPECTED RESPONSE/INSTRUCTOR CUES IC Reset Reset Simulator to 4% power IC SES Setup Run setup schedule file and Schedule verify malfunctions and over-File rides have been entered Floor Setup Ensure 21 Charging Pump in HANG PROTECTED EQUIPMENT tags service for: Ensure 23 CCW Pump in 21 and 22 Charging Pumps service Update the Protected Equipment Display PC Place 23 Charging pump in TPO and apply Danger Tags Place PCV-456 in closed and 536 in TPO and apply Danger Tags Distribute Turn over sheets Event1 Power Ascension Respond to notifications Event 2 Actuate Trigger 2 Initiates trip of 21 Charging Pump At lead evaluator direction Role Play When called about Charging 21 Charging Pump is hot and breaker Pumps and breakers appears to have tripped on overcurrent.

22 Charging Pump is running sat after being placed in service. Event 3 Actuate Trigger 3 Initiates trip of 23 CCW Pump At lead evaluator direction Role Play When called about CCW You cannot tell why 23 tripped. Which ever Pumps. pump is started appears to being running sat. Event 4 Actuate Trigger 4 Initiates IRP failure for 08: At lead evaluator direction U2 NRC 2014 Scenario 3: Power ascension, charging pump trip, IRPI failure, PT-408A failure, MFW pump trip, SGTR, instrument air failure, PORV failure. Page 5 of 19 Simulator Setup and Instructor Directions Setup/Event INSTRUCTOR ACTIONS EXPECTED RESPONSE/INSTRUCTOR CUES Role Play If I&C asked to investigate Report that technicians will be sent to investigate.

The problem will not be solved during the scenario.

Event 5 Actuate Trigger 5 Initiates failure of PT-408A high. At lead evaluator direction Role Play If I&C asked to investigate Report that technicians will be sent to investigate.

The problem will not be solved during the scenario.

Event6 Actuate Trigger 6 Initiates trip of 21 MFW Pump At lead evaluator direction Role Play If asked to investigate Report that personnel will be sent to investigate.

The problem will not be solved during the scenario.

Role Play If NPO sent to investigate Report the following:

There is a large air PCV-1228 leak near PCV-1228.

The NPO may be able to wrap the leak and reduce the air leakage. This repair will not be completed before the scenario is terminated Event9 When PORV is opened to Initiates failure of PORV and Block Valve. depressurize RCS: Activate Trigger 9 Role Play As requested by Control Perform various LOA's per NPO Local Task Room List. U2 NRC 2014 Scenario 3: Power ascension, charging pump trip, IRPI failure, PT-408A failure, MFW pump trip, SGTR, instrument air failure, PORV failure. Page 6 of 19 Op-Test No.: _1_ Scenario No.: __l Event No.: _1_ Page _1_of 2. Event

Description:

Power Ascension Time Position Applicant's Actions or Behavior Note: The reactivity plan for the power ascension should be developed by team in briefing room prior to taking the watch. The plan could call for dilution and/or rod withdrawal.

CRS Assigns roles for power ascension ATC Reviews reactivity plan ATC If rods are withdrawn:

• Places/verifies rods are in Manual

• Withdraws rods

• Observes:

0 Proper rod motion 0 Tavg 0 Power BOP Peer checks rod withdrawal ATC If dilution is performed:

• Places RCS Makeup control to Stop

• Place RCS Makeup Mode selector to Dilute

• Adjusts integrator to desired dilution amount

• Places RCS Makeup control to Start

• Observes:

0 Proper makeup response 0 Tavg 0 Power BOP Peer check dilution Adjust Low Flow Feed Reg Valves to maintain SG levels. U2 NRC 2014 Scenario 3: Power ascension, charging pump trip, IRPI failure, PT-408A failure, MFW pump trip, SGTR, instrument air failure, PORV failure. Page 7 of 19 Op-T est No.: _1_ Scenario Event No.: _1_ Page_1_ of _l Event

Description:

Power Ascension Lead Evaluator When the following has been demonstrated/observed:

• Sufficient load ascension .

• Sufficient normal plant operations by the BOP . Then instruct Booth to insert Event 2. U2 NRC 2014 Scenario 3: Power ascension, charging pump trip, IRPI failure, PT-408A failure, MFW pump trip, SGTR, instrument air failure, PORV failure. Page 8 of 19 Op-Test No.: 1 Scenario No.: 3 Event No.: 2 Page 1 of 1 Event

Description:

21 Charging Pump Trip T;.....,...,.

Position Applicant's Actions or Behavior BOP Notes 480V Motor Trip Alarm ATC Diagnoses that 21 Charging Pump has tripped CRS Announces entry in AOP-CVCS-1 ATC/BOP Verify there is no gas binding or issue preventing start of 22 Charging Pump ATC Starts 22 Charging Pump CRS Evaluates TRM TRO 3.1.B.1 and determines plant is in 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> action statement Lead Evaluator When the following has been demonstrated/observed:

Then instruct Booth to insert Event 3 U2 NRC 2014 Scenario 3: Power ascension, charging pump trip, IRPI failure, PT-408A failure, MFW pump trip, SGTR, instrument air failure, PORV failure. Page 9 of 19 Op-Test No.: _1_ Scenario No.: _l_ Event No.: _l_ Page _1_of J. Event

Description:

Trip of 23 CCW pump. Time Position Applicant's Actions or Behavior BOP Diagnose that 23 CCW pump has tripped: BOP Realize that a standby pump should have started and did not. Start 21 or 22 CCW as directed by ARP-SGF which may be referenced after starting the pump. CRS May Enter 2-AOP-CCW-1 CRS/BOP If prior actions have not been taken based on Auto-Start Failure Pump starts described above will be directed at Step 1 of the procedure.

CRS CRS will evaluate TS 3.7.7 and determine that the plant is in a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> actions statement due to having two CCW Pumps out of service. Lead Evaluator When CCW is restored initiate Event 4 U2 NRC 2014 Scenario 3: Power ascension, charging pump trip, IRPI failure, PT-408A failure, MFW pump trip, SGTR, instrument air failure, PORV failure. Page 10 of 19 Op-Test No.: 1 Scenario No.: 3 Event No.: 4 Page 1 of 1 Event

Description:

Control Rod D8 IRPI fails low Time Position Applicant's Actions or Behavior BOP Acknowledge Rod Bottom Rod Stop alarm ATC Diagnose that an IRPI has failed (may announce actual dropped rod):

• D8 IRPI reading 0 and rod bottom light lit

• No power change

• No NIS Dropped Rod alarm

• No QPTR tilt indications CRS Announce entry into AOP-ROD-1 CRS/ATC Determine failed IRPI CRS Refers toTS 3.1.7 and determines that immediate compensatory actions are needed. Lead Evaluator When the following has been demonstrated/observed:

TS evaluated Then instruct Booth to insert Event 5 U2 NRC 2014 Scenario 3: Power ascension, charging pump trip, IRPI failure, PT-408A failure, MFW pump trip, SGTR, instrument air failure, PORV failure. Page 11 of 19 Op-Test No.: 1 Scenario No.: 3 Event No.: 5 Page 1 of 1 Event

Description:

PT-408A fails high causing MBFP to go to minimum speed Time Position Applicant's Actions or Behavior ATC Diagnoses failure based on:

• Changing speed on 21 MFW Pump

• Changing SG Levels

• Possible SG Level Deviation Alarm

• Meter indication for PT-408A ATC Places MFW master speed controller or 21 MFW speed controller in manual to control speed. BOP Adjusts Low Flow FRVs to maintain SG Levels CRS Directs team to perform immediate operator actions of AOP-INST -1 ATC Checks all instruments listed in AOP-INST-1 CRS Implements AOP-INST-1

• Verifies no other instrument failures

• Ensures actions have been taken to stabilize the plant Lead Evaluator When the following has been demonstrated/observed:

SG levels stable Then instruct Booth to insert Event 6 U2 NRC 2014 Scenario 3: Power ascension, charging pump trip, IRPI failure, PT-408A failure, MFW pump trip, SGTR, instrument air failure, PORV failure. Page 12 of 19 Op-Test No.: 1 Scenario No.: 3 Event No.: 6 Page 1 of 1 Event

Description:

21 MFW Pump trips . '"" Position Applicant's Actions or Behavior ATC May notice speed increasing on 21 MFW pump before it trips on overs peed ATC Notice 21 MBFPT Turbine Trip alarm and indication that pump has tripped. CRS Instructs team to perform immediate operator actions of AOP-FW-1 ATC Notes no MFW in service above 4% and trips reactor TEAM Transitions to E-0 Lead Evaluator If the team does not trip the reactor because power is< 4%: Then instruct Booth to insert Event 7 using Trigger 30 U2 NRC 2014 Scenario 3: Power ascension, charging pump trip, IRPI failure, PT-408A failure, MFW pump trip, SGTR, instrument air failure, PORV failure. Page 13 of 19 Op-Test No.: _1_ Scenario No.: _2_ Event No.: 7/8/9 Page _1_of _§. Event

Description:

24 SGTR, loss of instrument air to containment, PORV fails open Tim Position Applicant's Actions or Behavior e Note: The diagnoses of 24 SGTR will happen during the performance of E-0 ATC Diagnose that SGTR exits in 24 SG:

• Decreasing PZR level

• VCT lowering level

• 24 SG level increasing without feed CRS Directs ATC to trip Reactor if not already done Directs ATC or BOP to Initiate Sl ATC Trips reactor if not already done ATCor Initiates Safety Injection BOP CRS Directs Operators to perform immediate operator actions of EO. ATC Verifies Reactor Trip:

• Checks trip breakers open

• Checks flux decreasing

• Checks rod bottom lights lit

• Checks IRPis <12.5 inches ATC Verifies Turbine Trip by observing all Turbine Stop Valves closed. BOP Verifies Power to 480V Busses:

• 2A, 3A, SA and 6A are energized ATC Checks Sl Status:

• Sl Annunciators are lit

• Sl Pumps are running

• Both Trains of Sl are actuated U2 NRC 2014 Scenario 3: Power ascension, charging pump trip, IRPI failure, PT-408A failure, MFW pump trip, SGTR, instrument air failure, PORV failure. Page 14 of 19 Op-Test No.: _1_ Scenario No.: ...2_ Event No.: 7/8/9 Page _1_of _§ Event

Description:

24 SGTR, loss of instrument air to containment, PORV fails open Note: The first 4 steps of E-0 are performed twice. Once by the A TC and BOP using placards, and a second time with the CRS reading the procedure.

CRS Directs BOP to_Q_erform Attachment 1 of E-0 BOP Performs Attachment 1 in parallel with the CRS/ATC progressing through E-0:

• Start a charging pump and align suction to RWST by opening LCV-112B and closing LCV-112C.

• Dispatch NPO to reset lighting and MCCS 24A, 27 A, and 29A.

• Stop condensate pumps .

• Use 22 AFWP to align AFW flow to 23 and 24 SGs if not already done . CRS/ATC Increases speed on 22 AFW pump to supply 23 SG (24 will be fed if team does not realize that it is ruptured)

CRS/ATC Verify Sl System Flow: Checks RCS Pressure Checks Sl Flow indicated if RCS Pressure is below 1720 psig Secures and places one RHR Pump in Pullout. CRS/ATC Check RCP Seal Cooling:

• Checks CCW

• Direct Service Water Valves SWN-4, SWN-5 be closed locally

• When valves are closed start NESW pump CRS/ATC Check RCS Temperature:

AFW Flow may be throttled back to just above 400 gpm at this point to maintain RCS Temperature.

CRS/ATC Will check that Spray, Aux Spray, and PORVs are all closed. CRS/ATC Check if RCPs should be stopped: They will be left in service CRS/ATC Check for Faulted SG U2 NRC 2014 Scenario 3: Power ascension, charging pump trip, IRPI failure, PT -408A failure, MFW pump trip, SGTR, instrument air failure, PORV failure. Page 15 of 19 Op-Test No.: _1_ Scenario No.: _l_ Event No.: 7/8/9 Page _1_of _§. Event

Description:

24 SGTR, loss of instrument air to containment, PORV fails open CRS/ATC Check for Ruptured SG:

• 24 SG Level will be increasing in an uncontrolled manner Team will identify 24 SG is ruptured.

CRS Transition to E-3 Steam Generator Tube Rupture CRS/ATC Check if RCPs should be stopped: RCPs are already secured CRS Identifies 24 SG as ruptured Critical Task 1 Isolate Feedwate( flow to c:md flow from the ruptured SG before transition to ECA-3.1 occurs. Isolating AFW Flow to 24 SG and adjusting the ADV may have occurred in E-0 when level reached 10% as a Prudent Operator Action. ATC/BOP Secure feeding 24 SG CRS/ATC Adjust 24 SG ADV to 1 030 psig if not already done CRS/ATC Trip 22 AFW Pump CRS/ATC Direct closure of MS-42 (22AFW Pump may be restarted after closure) CRS/ATC Verify blowdown isolated from 24 SG CRS/ATC Direct closure of steam traps upstream of 24 SG CRS/ATC Direct check that MS-55D (MSIV bypass) is closed. CRS/ATC Close 24 MSIV CRS/ATC Check 24 SG level > 1 0% CRS/ATC Check 24 SG pressure > 440 psig (will be 1030 psig) CRS/ATC Determine CET target temperature (will be 51 OF) U2 NRC 2014 Scenario 3: Power ascension, charging pump trip, IRPI failure, PT -408A failure, MFW pump trip, SGTR, instrument air failure, PORV failure. Page 16 of 19 Op-Test No.: _1_ Scenario No.: _L Event No.: 7/8/9 Page _1_of _§. Event

Description:

24 SGTR, loss of instrument air to containment, PORV fails open Critical Task 2 Establish/Maintain RCS temperature to ensure transition out of E-3 does not occur due to either of the following:

• RCS temperature too high to maintain required subcooling (This could be caused by team allowing CET temperature to come back up above target value).

• RCS temperature too low resulting in severe challenge to the subcriticality or integrity CSF. (Procedure specifies.

maintain temperature below target value without giving a specified band, however,pperators are trained to keep temperature close to target. Overcooling which leads to integrity challenge constitutes failure).

CRS/ATC Commence Cooldown to target CET temperature:

Note: ADVs will be used if RCPs not proactively tripped earlier.

• Place HP Steam Dumps in Pressure Mode and Manual

• Initiate Cooldown

• Do not exceed 0.5E6 lbs/hr on each of 21, 22, 24 SG Team will continue in procedure while GETs are lowering When CET temperatures are less than target:

• Stop cooldown by closing HP Steam Dumps Maintain CET temperature below target temperture CRS/ATC Check SG Levels and maintain AFW flow CRS/ATC Check PORVs and Block Valves. A block valve will be opened. CRS/ATC Reset Sl: CRS/BO p

• Place CCW Pumps in Trip Pullout

• Close MFRV and Bypass FRVs

• Place Sl Defeat Key Switches in Defeat

• Press Sl Reset Pushbuttons Reset Phase A:

• Place switches in open for IVSW valves 141, 1413, SOV-3518, SOV-3519

• Place Containment Rad Monitor WCPS Valve Switch to open

• Place VC Hatch switches in incident

• Place all remaining Phase A Valve switches to close

• Depress Phase A reset pushbuttons U2 NRC 2014 Scenario 3: Power ascension, charging pump trip, IRPI failure, PT-408A failure, MFW pump trip, SGTR, instrument air failure, PORV failure. Page 17 of 19 Op-Test No.: _1_ Scenario No.: _l_ Event No.: 7/8/9 Page _1_of ...§. Event

Description:

24 SGTR, loss of instrument air to containment, PORV fails open CRS/BO Attempt to establish instrument air to containment.

1228 will not open p CRS/BO Secure remaining in service RHR Pump p CRS/ATC Start the remaining Char!=lingPump and establish maximum char!=lin!=l flow CRS/ATC After cooldown stopped, check 24 SG Pressure stable or increasing.

It will be stable CRS/ATC Check subcooling

> 43F CRS Determine that PORV will be needed to de_Qressurize RCS CRS/ATC Use PORV PCV-455C to depressurize CRS/ATC When depressurizing termination criteria are met:

• Attempt to close PCV-455C

• Attempt to close block valve CRS Transition to ECA-3.1 I Lead . Evaluator I Terminate scenario.

U2 NRC 2014 Scenario 3: Power ascension, charging pump trip, IRPI failure, PT-408A failure, MFW pump trip, SGTR, instrument air failure, PORV failure. Page 18 of 19 I EMERGENCY PLAN DECLARATION Alert FA 1 .1 Any loss or potential loss of fuel clad or RCS From the fission product barrier matrix, RCS will be lost (D. Inventory Rupture SG results in ECCS actuation)

U2 NRC 2014 Scenario 3: Power ascension, charging pump trip, IRPI failure, PT-408A failure, MFW pump trip, SGTR, instrument air failure, PORV failure. Page 19 of 19