ML17191B482

Exan Final Itens 2B - Delay Release 2 Yrs

ML17191B482
Person / Time
Site:	Turkey Point
Issue date:	07/10/2017
From:	NRC/RGN-II
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Download: ML17191B482 (589)

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NRC EXAM SECURE INFOMATION Appendix D Scenario Outline Form ES-D-1 L-16-1 N1 (Rev-0) Facility: Turkey Point Nuclear (PTN)

- Units 3 and 4 Scenario No.:

1 Op Test No.:

2016-301 Examiners:

Operators:

(SRO) (R C O) (BOP) Initial Conditions:

The plant is at 75% power (MOL). Online risk is green. B train is protected on both units. Turnover: The 3A RHR pump and 3A1 Circulating Water pump are OOS

. Event Malf. No. Event Type*

Event Description 1 TFH1TU59 I-R C O I-SRO (TS) LT-3-4 59 , PZR Level Transmitter

, Fails High 2 TAKPXA2 TAKPXB1 TAKPXB2 R-RCO R-SRO N-BOP 3A2 Intake Screen Blockage (Load reduction required) 3 TVS1MWED I-B O P I-S RO (TS) FT-3-474, 3A S/G Steam Flow Transmitter, Drifts High 4 TFH1TV44 I-R C O I-SRO PT-3-444, PZR Pressure Transmitter, Fails L ow 5 TFFVP6A C-BOP C-SRO 3A Condensate Pump Sheared Shaft 6 TVHHCLB M-RCO M-BOP M-SRO Large Break LOCA 7 TFQ6A2 B F P-RCO 3 B RHR Pump Fails To Auto Start 8 TFCVVSO5 TFCVOSV6 P-BOP CV-3-2826/2819, Containment Isolation IA Bleed Valves

, Fail To Auto Close * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor , (P)ost Trip NRC EXAM SECURE INFOMATION Page 1 of 3 NRC EXAM SECURE INFOMATION Appendix D Scenario Outline Form ES-D-1 L-16-1 N1 (Rev-0) Scenario Summary Event 1 Shortly after taking the watch, LT 459, PZR Level Control Transmitter, fails high causing charging flow to reduce to the minimum and Pressurizer level to start trending down. The US will enter 3

-ONO P-041.6, Pressurizer Level Control Malfunction, and direct the RCO to place Pressurizer Level Control Transfer Switch to position 3, CH.2&3. Once Pressurizer level is stabilized the US will enter 3-ONOP-049.1 , Deviation or Failure of Safety Related or Reactor Protection Channels. The RCO will verify the Pressurizer Level Control Transfer Switch has been switched to position 3 and Pressurize level control is in automatic.

Event 2 After the US evaluates Tech Specs for LT 459, the Intake Screen differential level will start rising on all running Circulating Water Pumps. The US will enter 3

-ONOP-011, Screen Wash System/Intake Malfunction. The screen differential level on the 3A2 screen will require the 3A2 Circulati ng Water Pump be secured. Prior to securing the 3A2 CWP Circulati ng Water Pump Reactor power must be reduce d to less than 60%. The crew will reduce power to less than 60% using 3

-GOP-100, Fast Load Reduction, and then secure the 3A2 Circulati ng Water Pump

. Event 3 After the crew stops the 3A2 Circulati ng Water Pump FT-3-474, 3A S/G Steam Flow Transmitter

, will drift high. The BOP will take manual control of the 3A S/G level and restore the 3A S/G level to normal. The US will enter 3

-ONOP-049.1, Deviation or Failure of Safety Related or Reactor Protection Channels , direct the BOP to select an operable channel, and restore 3A S/G level control to automatic.

Event 4 Once the US completes the Tech Spec evaluation for FT 474, Pressurizer Pressure Control Transmitter PT 444 fails low. The PZR Sprays will close and all PZR Heaters will turn on causing Pressurizer pressure to rise. The US will enter 3

-ONOP-041.5, PZR Press Control Malfunction. The RCO will take manual control of PC 444J, PZR Press Controller, and restore PZR pressure to normal.

Event 5 After the crew restores Pressurizer Pressure the crew will start the 3C Condensate pump and secure the 3A Condensate pump due to a sheared shaft on the 3A Condensate Pump

. Event 6 Once the crew completes swapping condensate pumps a Large Break LOCA will occur. The crew will manually trip the Reactor and enter 3

-EOP-0, Reactor Trip Or Safety Injection. When RCP Trip Criteria are the met the RCO will trip the RCPs.

Event 7 When SI actuates the 3B RHR pump fails to auto start. The RCO will start the 3B RHR pump following the Immediate Operator Actions of 3

-EOP-E-0. Event 8 When Phase A actuates

, CV-3-2826 and CV 2819 , IA Bleed Valves

, fail to auto close. While performing 3

-EOP-E-0 Attachment 3, Prompt Action Verifications the BOP manually closes CV-3-2826 however 3-CV-3-2819 is failed open and will no t close in auto or manual.

NRC EXAM SECURE INFOMATION Page 2 of 3 NRC EXAM SECURE INFOMATION Appendix D Scenario Outline Form ES-D-1 L-16-1 N1 (Rev-0) Scenario Summary The crew will transition from 3

-EOP-0 to 3-EOP-E-1, Loss of Reactor or Secondary Coolant. During or shortly after the transition to 3

-EOP-E-1 the crew will be required to go to 3-EOP-FR-P.1, Response to Imminent Pressurized Thermal Shock Condition due to a RED path on the Integrity Status Tree. They will verify RHR flow greater than 1100 gpm, and then return to 3

-EOP-E-1. The scenario may be terminated after the crew transitions from 3

-EOP-FR-P.1 to 3-EOP-1 at the Lead Evaluator's discretion once all Critical Task s have been evaluated.

Event Critical Tasks 6/8 CT1 Start 3B RHR Pump During a Large Break LOCA start at least one RHR pump to provide core cooling to avoid transition to 3

-EOP-ECA-1.1, Loss of Emergency Coolant Recirculation.

Safety Significance

-- Failure to manually start at least one low

-head ECCS pump prior to the transition to a contingency procedure constitutes misoperation or incorrect crew performance in which the crew does not prevent degraded emergency core cooling system capacity that may lead to or prolong core uncovery.

6/7 CT2 Close CV-3-2826 During a Large Break LOCA close containment isolation valves such that at least one valve is closed on each critical Phase A penetration before whichever of the following occurs first:

The completion of 3

-EOP-0 Attachment 3

. Within 60 minutes of the Phase A actuation signal.

Safety Significance

-- Failure to perform the critical task leads to an unnecessary release of fission products to the auxiliary building, increasing the potential for release to the environment and reducing accessibility to vital equipment within the auxiliary building. High radiation in the auxiliary building can lead to increased doses to personnel.

NRC EXAM SECURE INFOMATION Page 3 of 3 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG Site: Turkey Point Units 3 and 4 (PTN)

Title: L-16-1 NRC EXAM SCENARIO 1 LMS #: NRC 21 LMS Rev Date:

6/6/16 Rev #: 0 SEG Type: Training Evaluation Program: LOCT LOIT Other Duration: 120 minutes Developed by:

Tim Hodge / Luis Sagion 8/4/16 Instructor/Developer Date Reviewed by:

Brian Clark 8/4/16 Instructor (Instructional Review)

Date Validated by :

Sean Bloom 8/5/16 SME (Technical Review)

Date Approved by:

Mark Wilson 8/5/16 Training Supervision Date Approved by:

Sean Bloom 8/5/16 Training Program Owner (Line)

Date NRC EXAM SECURE INFO RMATION L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG SCENARIO REFERENCES DOC NO. TITLE REV PTN TECHNICAL SPECIFICATIONS 300 3-EOP-E-0 REACTOR TRIP OR SAFETY INJECTION 12 3-EOP-E-1 LOSS OF REACTOR OR SECONDARY COOLANT 8 A 3-EOP-FR-P.1 RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION 3 3-GOP-100 FAST LOAD REDUCTION 12 A 3-ONOP-011 SCREEN WASH SYSTEM/INTAKE MALFUNCTION 7 3-ONOP-041.5 PRESSURIZER PRESSURE CONTROL MALFUNCTION 1 3-ONOP-041.6 PRESSURIZER LEVEL CONTROL MALFUNCTION 2 3-ONOP-049.1 DEVIATION OR FAILURE OF SAFETY RELATED OR REACTOR PROTECTION CHANNEL 4 NRC EXAM SECURE INFORMATION Page 2 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Objective Given this simulator scenario and resources normally found in the Control Room, the operating crew will perform Control Room operations IAW approved plant procedures in order to maintain the integrity of the plant and the health and safety of the public.

Enabling Objectives:

Given this simulator scenario and resources normally found in the Control Room, operate in accordance with approved plant procedures, Operations Department Instructions, and management expectations:

1. (ALL) Demonstrate personnel SAFETY awareness in interactions with plant staff and outside agencies.

2. (ALL) Demonstrate ALARA awareness in interactions with plant staff and outside agencies.

3. (ALL) Exchange correct information using 3

-point communication/Repeat

-backs with Control Room personnel and other plant staff.

4. (ALL) Inform plant personnel and System of plant conditions, as needed.

5. (US) Employ timely and concise crew briefs where appropriate.

6. (ALL) Maintain awareness of plant status and control board indication.

7. (ALL) Correctly diagnose plant situations.

8. (ALL) Solve operational problems as they arise.

9. (RCO/BOP) Manipulate plant controls properly and safely.

10. (ALL) Demonstrate self

-checking using STAR and peer checks(when required)

11. (US) Demonstrate command and control of the crew.

12. (US) Coordinate the input of crew members and other plant staff.

13. (US) Utilize the input of crew members and other plant staff.

14. (ALL) Demonstrate conservative decision making.

15. (ALL) Demonstrate teamwork.

16. (ALL) Respond to plant events using procedural guidance (OPs/ONOPs/EOPs) as applicable in accordance with rules of usage.

17. (RCO/BOP) Implement any applicable procedural immediate operator actions without use of references.

18. (SRO) Maintain compliance with Tech Specs.

19. (ALL) Identify/enter applicable Tech Spec action statements.

20. (ALL) Respond to annunciators using ARPs (time permitting).

21. (ALL) Maintain written communication, logs, and documentation as needed to permit post

-event reconstruction.

Continued on the next page:

NRC EXAM SECURE INFORMATION Page 3 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS While addressing the following events:

1. LT-3-459, PZR Level Transmitter, Fails High 2. 3A2 Intake Screen Blockage (Load reduction required)

3. FT-3-474, 3A S/G Steam Flow Transmitter, Drifts High

4. PT-3-444, PZR Pressure Transmitter, Fails Low

5. 3A Condensate Pump Sheared Shaft

6. Large Break LOCA

7. 3B RHR Pump Fails To Auto Start

8. CV-3-2826/19, Containment Isolation IA Bleed Valves, Fail To Auto Close Prerequisites:

None Training Resources:

PTN Unit 3 Plant Simulator Development

References:

TR-AA-220-1003, Initial N RC and Audit Exam Process TR-AA-230-1003, SAT Development TR-AA-230-1007 , Conduct of Simulator Training and Evaluation 0-ADM-232, Time Critical Action Program OP-AA-100-1000 , Conduct Of Operations OP-AA-103-1000 , Reactivity Management 0-ADM-200, Operations Management Manual 0-ADM-211, Emergency and Off

-Normal Operating Procedure Usage WCAP-17711-NP, Pressurized Water Reactor Owners Group Westinghouse Emergency Response Guideline Revision 2

-Based Critical Tasks Protected Content: N/A Evaluation Method: Performance Mode Operating Experience:

None Risk Significant Operator Actions: NRC EXAM SECURE INFORMATION Page 4 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG TASKS ASSOCIATED WITH SIMULATOR EXERCISE GUIDE SRO TASK #

TASK TITLE 02009002300 INVESTIGATE SCREEN D/P ALARM 02028033500 AUTHORIZE UNIT TRIP 02041057300 RESPOND TO PRESSURIZER LEVEL CONTROL CHANNEL MALFUNCTION 02063008500 VERIFY SI OPERATION 02073030300 INVESTIGATE CONDENSATE SYSTEM ALARMS 02089026300 AUTHORIZE FAST LOAD REDUCTION 02200021500 RESPOND TO A LOSS OF COOLANT ACCIDENT 02200044500 RESPOND TO STEAM GENERATOR HIGH LEVEL RO TASK TASK TITLE 01009002300 INVESTIGATE SCREEN D/P ALARM 0 1010005100 SHUTDOWN CIRCULATING WATER PUMPS 01028015100 ADJUST POWER LEVEL 01041027100 ADJUST PRESSURIZER PRESSURE MANUALLY USING THE MASTER CONTROLLER (444 J) 01041057300 RESPOND TO PRESSURIZER LEVEL CONTROL CHANNEL MALFUNCTION 01046007100 BORATE THE RCS VIA THE BLENDER 01063008500 VERIFY SAFETY INJECTION OPERATION 01073030300 INVESTIGATE CONDENSATE SYSTEM ALARMS 01074011300 CONTROL STEAM GENERATOR LEVEL MANUALLY WITH MAIN FEED REGULATING VALVES 0 1089026300 RESPOND TO/ADJUST TURBINE DURING FAST LOAD REDUCTION 01200001500 RESPOND TO UNIT TRIP 01200021500 RESPOND TO A LOSS OF COOLANT ACCIDENT 01200044500 RESPOND TO STEAM GENERATOR HIGH LEVEL NRC EXAM SECURE INFORMATION Page 5 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG UPDATE LOG:

NOTES: Place this form with the working copies of lesson plans and/or other materials to document changes made between formal revisions. For fleet

-wide training materials, keep electronic file of this form in same folder as approved materials. Refer to TR

-AA-230-1003 SAT Development for specific directions regarding how and when this form shall be used.

Indicate in the following table any minor changes or major revisions (as defined in TR

-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR

-AA-230-1003-F16. # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE REVIEWER DATE 0-0 Initial Revision Revised for L-16-1 NRC Exam 2108338 Note 5 Note 5 Note 5 Note 5 0-1 0-2 0-3 0-4 0-5 1. Individual updating lesson plan or training material shall complete the appropriate blocks on the Update Log.

2. Describe the change to the lesson plan or training materials.

3. State the reason for the change (e.g., reference has changed, typographical error, etc.)

4. Preparer enters name/date on the Update Log and obtains Training Supervisor approval.

5. Initial dates and site approval on cover page.

NRC EXAM SECURE INFORMATION Page 6 of 4 9 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG SCENARIO

SUMMARY

Initial Conditions The plant is at 75% power (MOL). Online risk is green. B train is protected on both units

. Equipment OOS The 3A RHR pump and 3A1 Circulating Water pump are OOS.

Event 1 Shortly after taking the watch

, LT-3-459, PZR Level Control Transmitter, fails high causing charging flow to reduce to the minimum and Pressurizer level to start trending down. The US will enter 3

-ONOP-041.6, Pressurizer Level Control Malfunction, and direct the RCO to place Pressurizer Level Control Transfer Switch to position 3, CH.2&3. Once Pressurizer level is stabilized the US will enter 3-ONOP-049.1 , Deviation or Failure of Safety Related or Reactor Protection Channels. The RCO will verify the Pressurizer Level Control Transfer Switch has been switched to position 3 and Pressurize level control is in automatic.

Event 2 After the US evaluates Tech Specs for LT-3-459, the Intake Screen differential level will start rising on all running Circulating Water Pumps. The US will enter 3

-ONOP-011, Screen Wash System/Intake Malfunction. The screen differential level on the 3A2 screen will require the 3A2 Circulating Water Pump be secured. Prior to securing the 3A2 CWP Circulating Water Pump

, Reactor power must be reduce d to less than 60%. The crew will reduce power to less than 60% using 3

-GOP-100, Fast Load Reduction, and then secure the 3A2 Circulating Water Pump. Event 3 After the crew stops the 3A2 Circulating Water Pump

, FT-3-474, 3A S/G Steam Flow Transmitter, will drift high. The BOP will take manual control of the 3A S/G level and restore the 3A S/G level to normal. The US will enter 3

-ONOP-049.1, Deviation or Failure of Safety Related or Reactor Protection Channels, direct the BOP to select an operable channel, and restore 3A S/G level control to automatic.

Event 4 Once the US completes the Tech Spec evaluation for FT 474, Pressurizer Pressure Control Transmitter

, PT-3-444 fails low. The PZR Sprays will close and all PZR Heaters will turn on causing Pressurizer pressure to rise. The US will enter 3

-ONOP-041.5, PZR Press Control Malfunction. The RCO will take manual control of PC 444J, PZR Press Controller, and restore PZR pressure to normal.

Event 5 After the crew restores Pressurizer Pressure , the crew will start the 3C Condensate pump and secure the 3A Condensate pump due to a sheared shaft on the 3A Condensate Pump.

Event 6 Once the crew completes swapping condensate pumps

, a Large Break LOCA will occur. The crew will manually trip the Reactor and enter 3

-EOP-E-0, Reactor Trip Or Safety Injection. When RCP Trip Criteria are met , the RCO will trip the RCPs.

NRC EXAM SECURE INFORMATION Page 7 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG SCENARIO

SUMMARY

Event 7 When SI actuates

, the 3B RHR pump fails to auto start. The RCO will start the 3B RHR pump following the Immediate Operator Actions of 3

-EOP-E-0. Event 8 When Phase A actuates

, CV-3-2826 and CV 2819 , IA Bleed Valves

, fail to auto close. While performing 3-EOP-E-0 Attachment 3, Prompt Action Verifications the BOP manually closes CV 2826 however 3-CV-3-2819 is failed open and will no t close in auto or manual.

The crew will transition from 3

-EOP-E-0 to 3-EOP-E-1, Loss of Reactor or Secondary Coolant. During or shortly after the transition to 3-EOP-E-1 , the crew will be required to go to 3

-EOP-FR-P.1, Response to Imminent Pressurized Thermal Shock Condition

, due to a RED path on the Integrity Status Tree. They will verify RHR flow greater than 1100 gpm, and then return to 3

-EOP-E-1. The scenario may be terminated after the crew transitions from 3

-EOP-FR-P.1 to 3-EOP-E-1, or at the Lead Evaluator's discretion once all Critical Task s have been evaluated.

CRITICAL TASKS Event # Description 6/7 CT1 Start 3B RHR Pump During a Large Break LOCA start at least one RHR pump to provide core cooling to avoid transition to 3

-EOP-ECA-1.1, Loss of Emergency Coolant Recirculation.

Safety Significance

-- Failure to manually start at least one low

-head ECCS pump prior to the transition to a contingency procedure constitutes misoperation or incorrect crew performance in which the crew does not prevent degraded emergency core cooling system capacity that may lead to or prolong core uncovery.

6/8 CT2 Close CV-3-2826 During a Large Break LOCA close containment isolation valves such that at least one valve is closed on each critical Phase A penetration before whichever of the following occurs first:

The completion of 3

-EOP-0 Attachment 3

. Within 60 minutes of the Phase A actuation signal. Safety Significance -- Failure to perform the critical task leads to an unnecessary release of fission products to the auxiliary building, increasing the potential for release to the environment and reducing accessibility to vital equipment within the auxiliary building. High radiation in the auxiliary building can lead to increased doses to personnel.

NRC EXAM SECURE INFORMATION Page 8 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG SEQUENCE OF EVENTS EVENT # DESCRIPTION

1. LT-3-459, PZR Level Transmitter, Fails High

2. 3A2 Intake Screen Blockage (Load reduction required)

3. FT-3-474, 3A S/G Steam Flow Transmitter, Drifts High

4. PT-3-444, PZR Pressure Transmitter, Fails Low

5. 3A Condensate Pump Sheared Shaft

6. Large Break LOCA

7. 3B RHR Pump Fails To Auto Start

8. CV-3-2826, Containment Isolation IA Bleed Valves, Fail To Auto Close CV-3-2819, Containment Isolation IA Bleed Valves, Fail Open NRC EXAM SECURE INFORMATION Page 9 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG SIMULATOR SET UP INSTRUCTIONS Check Action ____ Restore IC

-16 (75% MOL) or equivalent IC.

____ Unfreeze the Simulator.

____ Stop the 3A1 Circ Water Pump

____ Open & execute lesson file L

-1 6-1 N1.lsn ____ Ensure the following lesson steps are triggered:

SETUP - 3A RHR PUMP OOS SETUP - 3A1 CWP OOS EVENT 7 SETUP - 3B RHR PUMP FAILS TO AUTO START EVENT 8 SETUP

- IA BLEED VLVS FAIL TO CLOSE

____ Place 3A RHR pump in PTL and hang ECO tag.

____ Place 3A1 CWP in stop and han g ECO tag. ____ Verify the trend for 3A1 Screen on the TWS DP Recorder is clear.

____ Ensure Rod Group Step Counters have completed stepping out.

____ Allow the plant to stabilize.

____ Acknowledge any alarms and freeze Simulator.

____ Ensure B train is protected train on VPA.

____ Perform the SIMULATOR OPERATOR CHECKLIST or equivalent.

____ Place TURNOVER SHEETS on RO

's desk or give to the Lead Evaluator.

NRC EXAM SECURE INFORMATION Page 10 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG BRIEFINGS Shift turnover information is attached to the back of this guide. Ensure all applicants are prior briefed on Appendix E of NUREG 1021, Policies and Guidelines For Taking NRC Examinations.

Conduct a Crew Pre

-brief to cover turnover information. Shift turnover information is attached to the back of this guide.

US: RCO: BOP: SCENARIO NOTE 0-ADM-211 , Emergency and Off-Normal Operating Procedure Usage

, Prudent Operator Actions

. If redundant stand

-by equipment is available and ready, the operator is permitted to start the redundant equipment for failed or failing operating equipment.

Immediate follow up of applicable ARPs and ONOPs (AOPs) shall occur as required.

NRC EXAM SECURE INFORMATION Page 11 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG Critical Task s are highlighted in pink. Simulator Operator Actions are highlighted in blue.

Operator Verifiable Actions are Highlighted in green EVENT 1 - LT-3-459, PZR LEVEL TRANSMITTER, FAILS HIGH 3-ONOP-041.6, PRESSURIZER LEVEL CONTROL MALFUNCTION.

TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE NOTE Ensure the Simulator is in RUN before the crew enters the Simulator.

US: Conducts shift turnover.

BOOTH OPERATOR When directed by the Lead evaluator trigger EVENT 1 - LT-3-459 FAILS HIGH RCO: Observes LT 4 59 failed high BOP: Acknowledges A8/3, A9/3, G1/1 A5/4 may alarm shortly after Reviews ARP and recommends entry into 3-ONOP-041.6, Pressurizer Level Control Malfunction.

US: Directs 3-ONOP-041.6 response

. PROCEDURE NOTES If Pressurizer Level Malfunction is a result of a failure of the 3

-459CX or 3

-460CX relays (as indicated by a loss of letdown flow with a loss of Pressurizer Heaters with no concurrent failure of Level Transmitters 3

-459A, 3-460, 3-461), use 3

-ONOP-003.6 Attachment 4, for 3

-460CX failure, OR 3

-ONOP-003.9 Attachment 4, for 3

-459CX failure as guidance for establishing Letdown flow and Pressurizer Heaters.

If the button on relays 3

-459CX or 3

-460CX are used to restore Letdown flow and Pressurizer Heaters, comply with Tech Spec Action Statement 3.4.3 Action

b. If the manual control of Heaters from the Electrical Penetration Room is used, comply with Tech Spec Action Statement 3.4.3 Action a.

NRC EXAM SECURE INFORMATION Page 12 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG EVENT 1 - LT-3-459, PZR LEVEL TRANSMITTER, FAILS HIGH 3-ONOP-041.6, PRESSURIZER LEVEL CONTROL MALFUNCTION.

TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE LEAD EVALUATOR The 3A2 INTAKE SCREEN BLOCKAGE failure in Event 2 may go undetected for up to 15 minutes. After the crew enters 3-ONOP-041.6, direct the Booth Operator to trigger Event 2 at your discretion

. RCO: Check Pressurizer level indicators LI-3-459A, LI-3-460 AND LI 461 Selects ch 2 & 3 PZR level control (Position

3) Maintains PZR level on program per 3-ONOP-041.6, Enclosure 1 May place Master Charging Pump Controller, LC 459G in manual May Start or Stop one charging pump as required.

Place LR-3-459 Channel Select Pressurizer Level Recorder to position 2 or 3. Steps 5.1

- 5.4 US: Marks Steps 5.5

- 5.7 N/A RCO: WHEN desired place LC-3-459G in Automat ic Step 5.8 US: Perform actions required by 3

-ONOP-049.1, Deviation or Failure of Safety Related or Reactor Protection Channels.

Step 5.9 NRC EXAM SECURE INFORMATION Page 13 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG EVENT 1 - LT-3-459, PZR LEVEL TRANSMITTER, FAILS HIGH 3-ONOP-049.1, DEVIATION OR FAILURE OF SAFETY RELATED OR REACTOR PROTECTION CHANNELS TIME EVALUATOR ACTIVITIES & NOTEs EXPECTED STUDENT RESPONSE US: Enters and directs actions of 3

-ONOP-049.1, Deviation or Failure of Safety Related or Reactor Protection Channels, for response RCO: Verify LT-459 failure by comparison L T-3-460/461 and known plant parameters and conditions Verify no off-normal conditions exist on L T-3-460/461 Verify ch 2 & 3 PZR level control in (Position 3)

Verify LR-3-459 Channel Selected to Pressurizer Level Recorder to position 2 or 3 Verify PZR level control function is returned to automatic

. Steps 5.1

- 5.5 US Reviews TECH Specs Tech Spec 3.3

-1 Functional Unit 9 not met. - Action 13, inoperable channel must be placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

US: Marks steps 5.7

- 5.11 N/A. US: Identify Bistables which need to be tripped. Step 5.12 US: Marks steps 5.

13 - 5.1 6 N/A. NRC EXAM SECURE INFORMATION Page 14 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG EVENT 1 - LT-3-459, PZR LEVEL TRANSMITTER, FAILS HIGH 3-ONOP-049.1, DEVIATION OR FAILURE OF SAFETY RELATED OR REACTOR PROTECTION CHANNELS TIME EVALUATOR ACTIVITIES & NOTEs EXPECTED STUDENT RESPONSE BOOTH OPERATOR WCC/I&C: Acknowledge the report. If asked I&C would like to be present when bi-stables are tripped. They will be in the control room in about 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

US: Initiate a Plant Work Order AND notify the I&C Supervisor.

Step 5.17 US: Conducts crew brief.

NRC EXAM SECURE INFORMATION Page 15 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG EVENT 2 - 3A2 INTAKE SCREEN BLOCKAGE 3-ONOP-011, SCREEN WASH SYSTEM/INTAKE MALFUNCTION TIME EVALUATOR ACTIVITIES & NOTEs EXPECTED STUDENT RESPONSE BOOTH OPERATOR When directed by the Lead evaluator trigger EVENT 2

- INTAKE SCREEN BLOCKAGE NOTE The crew may enter 3

-ONOP-011 prior to receiving the alarm.

BOOTH OPERATOR If asked to rake the grizzly screen , report the rake is stuck. Maintenance support has been requested.

NOTE The crew may swap ICW pumps.

BOP: Addresses Alarm Response for I3/3 CHECKs Intake Well DPs greater than 25" water on recorder R 2300 at VPA(3C04). Dispatches an Operator to check the following:

- Traveling Screens with HI DP are running in FAST.

- Operating Traveling Screens Spray Wash is maintaining the screen clear of debris.

- Recommends entering 3-ONOP-011, Screen Wash System /

Intake Malfunction.

US: Enters and directs the actions of 3

-ONOP-011. US: Reviews Foldout page with the crew.

Circulating Water Pump Stopping Criteria Fast Load Reduction Criteria Reactor Trip Criteria Loss of Intake Cooling Water Plant Management Notification Shift Manager Evaluation of Intake Screen Effectiveness Amertap Screen Debris Monitoring Foldout Page NRC EXAM SECURE INFORMATION Page 16 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG EVENT 2 - 3A2 INTAKE SCREEN BLOCKAGE 3-ONOP-011, SCREEN WASH SYSTEM/INTAKE MALFUNCTION TIME EVALUATOR ACTIVITIES & NOTEs EXPECTED STUDENT RESPONSE PROCEDURE NOTE To rotate a Traveling Screen manually, a 10mm wrench is required to remove the motor cover to allow access to the drive crank. When the motor cover is removed, a micro switch will de

-energize 480V power from the Screen and actuate I

-3/4, TRAVELING SCREEN GENERAL TROUBLE.

BOOTH OPERATOR When dispatched to locally start traveling screens, wait 2 minutes and then trigger EVENT 2 LOA

- START ALL PUMPS AND ALL SCREENS IN FAST BOOTH OPERATOR When the screens start

, verify EVENT 2 - REDUCE SCREEN BLOCKAGE triggers. BOOTH OPERATOR If asked all traveling screen equipment is operating normally

. BOP: Direct ANPO to:

Check Traveling Screens Operating Properly Check Traveling Screen Spray Wash Pumps Operating Properly Steps 1 & 2 BOOTH OPERATOR When dispatched to locally check ICW to CCW and TPCW heat Exchanger or strainers, wait 1-3 min, report all ICW/ CCW ICW / TPCW Strainers < 1 P. If a specific value is requested use simulator drawings COMMON SERVICES/INTAKE COOLING and COMMON SERVICES/TURBINE PLANT COOLING to report actual values. BOP: Directs SNPO

Maintain Intake Cooling Water Flow To Component Cooling Water Heat Exchangers.

Maintain Intake Cooling Water To The Turbine Plant Cooling Water Heat Exchangers Steps 3 & 4 NRC EXAM SECURE INFORMATION Page 17 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG EVENT 2 - 3A2 INTAKE SCREEN BLOCKAGE 3-ONOP-011, SCREEN WASH SYSTEM/INTAKE MALFUNCTION TIME EVALUATOR ACTIVITIES & NOTEs EXPECTED STUDENT RESPONSE BOOTH OPERATOR When I3/3,Travelin g Screen High alarms , verify EVENT 2 - STABILIZE SCREEN BLOCKAGE triggers Monitor screen level on the TWS DP recorder. If needed use the active malfunction summary page to adjust TAKPXA2 to maintain screen level less than 30 inches.

BOP: Check If Conditions Returned To Normal. (NO, Go to Step 7)

Step 5 BOOTH OPERATOR Acknowledge request for additional support. BOP: Contact WCC and Maintenance for additional support.

BOOTH OPERATOR If asked to locally check level drop behind Traveling Screens, use the Simulator Panel drawings to report the same level displayed on the control room chart recorders.

LEAD EVALUATOR After the crew evaluates step 7 have the Booth Operator call the Unit Supervisor as the Shift Manager and direct the US to reduce power to less than 60% per 3-GOP-100, Fast Load Reduction to secure the 3A2 Circulating Water Pump

. BOP: Check If One Circulating Water Pump Should Be Stopped.

Locally check that level drop behind Traveling Screens is greater than 3 feet. (NO) OR s. (No) Return to step 1 Step 7 BOOTH OPERATOR Acknowledge notifications If Chemistry is asked, request the crew maintain current blowdown flow.

US: Notify Plant Management.

NRC EXAM SECURE INFORMATION Page 18 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG EVENT 2 - 3A2 INTAKE SCREEN BLOCKAGE 3-GOP-100, FAST LOAD REDUCTION TIM E EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE US: Directs actions to reduce Rx power from 50% per 3-GOP-100. Completes Attachment 3 (Page 44) Brief the crew per Attachment 4 (Page 45) Steps 1-2 US: Reviews Foldout page with crew.

3-EOP-E-0 Transition Criteria Notify Chemistry Department Boration Stop Criteria Restore Blender to AUTO FOLDOUT PAGE BOOTH OPERATOR Acknowledge notifications.

BOP: Notify The Following Of Fast Load Reduction System Dispatcher Plant personnel using the Page Boost Chemistry to start RCS sampling is required according to Tech Spec Table 4.4-4. Ste p 3 NRC EXAM SECURE INFORMATION Page 19 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG EVENT 2 - 3A2 INTAKE SCREEN BLOCKAGE 3-GOP-100, FAST LOAD REDUCTION TIM E EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE RCO: Begin Boration For Initial Tavg Effect Set the Boric Acid Totalizer to total boric acid volume value determined on Attachment 3

(~250 gallons)

. Place the Reactor Makeup Selector Switch to BORATE.

Place the RCS Makeup Control Switch to START.

Adjust FC-3-113A, Boric Acid Flow Controller to achieve 40 gpm boric acid flow as indicated on FR 113. WHEN Tavg begins to lower from the boration, THEN, adjust FC 113A, Boric Acid Flow Controller to load reduction value from Attachment 3.

Step 4 US: Determine Turbine Load Reduction in MW CNTRL Ste p 5 BOP: Initiate Turbine Load Reduction in MW CNTRL Select MW CNTRL Set TARGET power level

- MW VALUE from Attachment 3 Set RAMP RATE

- MW/M VALUE FROM Attachment 3.

Check Tavg has lowered 1° to 2°F from the initial value prior to boration.

Depress GO Ensure FC-3-113A, Boric Acid Flow Controller, has been adjusted to the load reduction boration rate.

Go to Step 10 Step 6 NRC EXAM SECURE INFORMATION Page 20 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG EVENT 2 - 3A2 INTAKE SCREEN BLOCKAGE 3-GOP-100, FAST LOAD REDUCTION TIM E EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOP: Monitor Load Reduction Adjusts power reduction rate to maintain Tavg/Tref within limits of Attachment 3.

Monitors S/G level control to ensure feed reg valves properly maintain level control in automatic

. Refer to Enclosure 1 for expected alarms. (Page 46) Step 10 BOOTH OPERATOR Respond as SNPO. If asked, idle Charging Pump ready for start.

RCO: Maintain pressurizer level to ensure that automatic pressurizer level control maintains level on program

. If needed starts 2 nd Chg Pp and places 2 nd orifice in service.

Adjusts boration rate to maintain Tavg/Tref within limits of Attachment

3. Refer to Enclosure 1 for expected alarms. Step 10 RCO: Monitor Boration Rate Monitor for excessive rod movement by monitoring TR 409D, Rod Position Bank D. Determine if Insertion Limit and Bank D position are converging at a rate that will cause rod insertion limit alarms. Adjust power reduction rate as needed to control rod insertion Increase boration rate and/or total amount as necessary to limit control rod insertion Step 11 NRC EXAM SECURE INFORMATION Page 21 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG EVENT 2 - 3A2 INTAKE SCREEN BLOCKAGE 3-GOP-100, FAST LOAD REDUCTION TIM E EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE RCO: Monitor Annunciator B 8/1, ROD A/B/C/D BANK LO LIMIT

- CLEAR Monitor B 8/2 ROD BANK A/B/C/D EXTRA LO LIMIT - CLEAR Steps 12-13 US: Have SM refer to t he following procedures: 0-EPIP-20101, DUTIES OF EMERGENCY COORDINATOR 0-ADM-115, NOTIFICATION OF PLANT EVENTS Step 14 PROCEDURE NOTE Axial flux difference is allowed to exceed the Target Band during the load reduction without entering 3

-ONOP-059.4, AXIAL FLUX DIFFERENCE.

BOOTH OPERATOR Acknowledge notifications If Chemistry is asked, request the crew maintain current blowdown flow.

RCO: Energize Pressurizer Backup Heaters Step 15 BOOTH OPERATOR When directed to close 3 002 and 3-30-004 per step 4 of 3-NOP-010, wait 1

- 2 minutes, then trigger LOA - CLOSE 3-30-002 AND 3-30-004. Report when complete.

BOOTH OPERATOR When dispatched to monitor the 3A2 CWP discharge MOV, report it fully closed after the pump stopped. All checks are SAT. BO P: When power is reduce to <60%, stops the 3A2 CWP In Accordance With 3-NOP-010, Circulating Water System.

BOP: Verify Turbine Load is Less Than 675 MWE. Step 1 6 NRC EXAM SECURE INFORMATION Page 22 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG EVENT 2 - 3A2 INTAKE SCREEN BLOCKAGE 3-GOP-100, FAST LOAD REDUCTION TIM E EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE PROCEDURE CAUTIONS If Medium Runback Armed is ACTIVE and one of three operating Condensate Pumps is shutdown, a Turbine Runback will result.

Medium Runback Armed should be NOT ACTIVE below TIP pressure of approximately 574 psig.

BOP: Check Condensate Pump Operation

a. Check three condensate pumps running b. Verify Medium Runback Armed NOT active c. Stop one condensate pump Step 17 US: Check Desired Final Power Target

- LESS THAN 475 MWE Step 18 LEAD EVALUATOR Once power the 3A2 CWP is shutdown, or at the Lead Evaluators discretion, proceed to the next event

. NRC EXAM SECURE INFORMATION Page 23 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG EVENT 3 - FT-3-474, 3A S/G STEAM FLOW TRANSMITTER, DRIFTS HIGH 3-ONOP-049.1, DEVIATION OR FAILURE OF SAFETY RELATED OR REACTOR PROTECTION CHANNELS TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOOTH OPERATOR When directed by the lead evaluator, trigger EVENT 3 - FT-3-47 4 DRIFTS HIG H BOP: Recognizes and reports FT-3-474 is failing high.

Takes manual control of 3 A S/G level control valve FCV 478. Restores 3 A S/G level to normal.

NOTE The crew may use direction in the ARP to select alternate input signals and return 3A S/G level control to automatic before enter 3-ONOP-049.1. RCO: Addresses Alarm Response for C4/1, C5/1, C6/1 and C7/1. Ensures BOP takes Prompt Actions

- Take manual control of level.

- Return SG levels to normal.

Checks if alarm is due to instrument failure, then refers to 3

-ONOP-049.1, Deviation or Failure of Safety Related or Reactor Protection Channels.

US: Enters and directs actions of 3

-ONOP-049.1, Deviation or Failure of Safety Related or Reactor Protection Channels, for response BOOTH OPERAT OR If dispatched to reset AMSAC, wait 3 to 5 minutes and then trigger EVENT 3 LOA - RESET AMSAC. Report when complete.

BOP: Verify FT-3-474 failure by comparison to F T-3-4 7 5 and known plant parameters and conditions.

Verify no off

-normal conditions exist on F T-3-4 75 Place 3 A S/G Steam Flow Control transfer switch to F T-3-4 75. (Ch IV-Yellow) Place 3 A S/G Feed Water Flow Control transfer switch to F T-3-4 76.( Ch IV-Yellow) When 3A S/G level is returned to normal place FCV 4 78 level control valve in auto.

Steps 5.1- 5.5 NRC EXAM SECURE INFORMATION Page 24 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG EVENT 3 - FT-3-474, 3A S/G STEAM FLOW TRANSMITTER, DRIFTS HIGH 3-ONOP-049.1, DEVIATION OR FAILURE OF SAFETY RELATED OR REACTOR PROTECTION CHANNELS TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOOTH OPERATOR Acknowledge notifications and request for additional support.

If asked , I&C would like to be resent when the bi-stables are tripped. They will be in the control room as soon as their work package is ready, about an hour.

US Reviews Tech Specs Tech Spec 3.3

-1 Functional Unit 12 not met. - Action 6 , inoperable channel must be placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Tech Spec 3.3

-2 Functional Unit 1f and 4d not met. - Action 15 , inoperable channel must be placed in the tri pped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Step 5.6 US: Marks steps 5.7

- 5.11 N/A. US: Identify Bistables which need to be tripped. Step 5.12 US: Marks steps 5.

13 - 5.1 6 N/A. US: Initiate a Plant Work Order AND notify the I&C Supervisor.

Step 5.17 LEAD EVALUATOR After S/G level control is restored to auto and the Tech Spec review is complete, at the Lead Evaluators discretion, proceed to the next event.

US Conducts crew brief.

NRC EXAM SECURE INFORMATION Page 25 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG EVENT 4 - PT-3-444, PZR PRESSURE TRANSMITTER FAILS LOW 3-ONOP-041.5, PRESSURIZER PRESSURE CONTROL MALFUNCTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOOTH OPERATOR When directed by Lead Evaluator, trigger EVENT 4 - PT-3-444 FAILS LOW RCO: Reports PZR pressure rising due to PI-3-4 44 failing low.

NOTE The RCO will most likely notice this failure before Alarm A9/2 comes in. The crew may use the ARP for guidance.

BOP: Reviews ARP for A9/2 , PZR CONTROL HI/LO PRESS Check PZR pressure less than 2235 psig (NO) Check PI-3-445/444, PZR pressure greater tha n 2300 psig or Less than 2185 psig.

Refer to 3-ONOP-041.5, PZR Press Control Malfunction.

US: Directs the Action of 3

-ONOP-041.5, Pressurizer Pressure Control Malfunction.

US: Reviews the Foldout Page with the crew.

Failed Instrument Isolation 3-EOP-E-0 Transition Criteria PORV Isolation/Leaking PORV Identification Open/Leaking PZR Safety Valve Identification Spurious Actuation Of CV 311 , Auxiliary Spray Valve PROCEDURE CAUTION Th e Mast e r Co n trolle r s houl d b e o perate d c arefull y (Nor m al cont rolle r outp u t f o r 223 5 p s i g i s 42.5 percen t demand; 9 2 pe r ce n t deman d wil l ope n PCV-3-455C). I f t he following c onditions a r e met, an ex cessive incr ea se in cont roller outp u t c ould cause Power Op e rated Relief Valve PCV-3-4 55C to ope n: 1. PCV-3-4 5 5 C han d switc h i n AUTO. 2. Pressur izer press u re is greater than or e q ual to 2000 psig, o r O M S swit c h in L O Pres s O p s. NRC EXAM SECURE INFORMATION Page 26 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG EVENT 4 - PT-3-444, PZR PRESSURE TRANSMITTER FAILS LOW 3-ONOP-041.5, PRESSURIZER PRESSURE CONTROL MALFUNCTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE RCO: Check PT-3-444 - NOT FAILED (NO) - Verify PCV 455C OR MOV 536 CLOSED.

- Take manual control of PC-3-444J, PZR PRESS CONTROL. Check PT-3-445 - NOT FAILED Step 1 RCO: Check PORVs Closed PZR pressure normal or trending to normal. Check PZR Safety Valves Closed Check PZR Pressure Stable Or Increasing Check Pressurizer Pressure Above Normal Value (NO - Go to Step 10)

Step 2 - 6 RCO: Check Pressurizer Pressure Low Or Decreasing (NO- Go to Step 20)

Step 10 RCO: Check RCS Pressure Stable Step 20 BOOTH OPERATOR Acknowledge notifications and request for support. LEAD EVALUATOR After PZR Pressure is stable, then proceed with the next event

. RCO: Check If Automatic Pressure Control Can Be Established (NO) Notify the Instrument and Controls Department.

Continue efforts to establish Automatic Pressure Control.

Return to Step 20 Step 21 NRC EXAM SECURE INFORMATION Page 27 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG EVENT 5 - 3A CONDENSATE PUMP SHEARED SHAFT 3-NOP-073, CONDENSATE SYSTE M TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOOTH OPERATOR When directed by Lead Evaluator, trigger EVENT 5- 3A CONDENSATE PUMP SHEARED SHAFT

. RCO: Reviews Alarm G8/3 , COND PUMP A LO FLOW BOOTH OPERATOR If dispatched to check the 3A Condensate pump , wait 2- 3 minutes and then report you see nothing wrong with the pump.

BOP: Check Condensate Pump flow indication on DCS.

Monitor feed pump suction pressure.

Report low amps on 3A Condensate pump and high amps on the 3B Condensate pump

. US: Direct BOP to start the 3C Condensate pump and Secure the 3A Condensate pump per 3-NOP-073. BOOTH OPERATOR If asked , the 3C Condensate Pump is ready for a start. After the pump is started , report a SAT start.

BOP: Dispatch an operator to verify the 3B Condensate pump is ready to start per 3

-NOP-073. Start the 3 C Condensate Pump

. Secure the 3A Condensate Pump.

NOTE 3A Condensate Pump has restart feature that may encourage the crew to have it racked out.

LEAD EVALUATOR After the Condensate pumps are swapped , proceed to the next event.

US Notifies WCC to initiate PWO and I&C for troubleshooting.

Conducts crew brief

. NRC EXAM SECURE INFORMATION Page 28 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG EVENT 6 - LARGE BREAK LOCA 3-EOP-E-0, RX TRIP OR SAFETY INJECTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOOTH OPERATOR When directed by the Lead Evaluator trigger EVENT 6 - LB LOCA RCO: Responds to various ala r ms PZR LO Pressure and level Alarms A9/2, A9/3

. Reports lowering Pressurizer and pressure and level.

Maximizes Charging Isolates Letdown When PZR cannot be maintained recommends a Reactor trip.

NOTE Steps 1 - 4 of 3-EOP-E-0 are Immediate Operator Actions (IOAs)

. The board operators will call out the high level steps of the IOAs as each step is completed from memory.

US: Directs RCO to manually trip the Reactor.

RCO: Manually trips Reactor.

RCO/BOP: Perform IOAs of 3

-EOP-E-0. RCO: Verify Reactor Trip STEP 1 BOP: Verify Turbine STEP 2 BOP: Verify Power To Emergency 4 KV Buses STEP 3 RCO: Checks If SI Is Actuated STEP 4 US: Reviews Steps 1

- 4 of 3-EOP-E-0 with the crew. NRC EXAM SECURE INFORMATION Page 29 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG EVENT 6 - LARGE BREAK LOCA 3-EOP-E-0, RX TRIP OR SAFETY INJECTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE NOTE The crew may take Prudent Operator Actions to start the 3B RHR pump and/or close Containment Phase A Isolation valve CV-3-2826 or they may wait until directed by 3

-EOP-E-0 Attachment 3. CV-3-2819 is failed open and will no t close in auto or manual.

CT 1 Start 3B RHR Pump During a Large Break LOCA

, start at least one RHR pump to provide core cooling prior to transition to 3

-EOP-ECA-1.1, Loss of Emergency Coolant Recirculation.

RCO: Starts the 3B RHR pump CT2 Close CV-3-2826 During a Large Break LOCA

, close containment isolation valves such that at least one valve is closed on each critical Phase A penetration before whichever of the following occurs first:

The completion of 3

-EOP-0 Attachment 3 Within 60 minutes of the Phase A actuation signal.

BOP: Close CV-3-2826 US: Reviews FOP for 3

-EOP-E-0 Adverse Cntmt (Met, Temp>180°F

) RCP Trip Criteria (Met) Trips RCPs once met.

Faulted S/G Isolation Ruptured S/G Isolation AFW Sys Operation Criteria CST Makeup Water Criteria RHR System Operation Criteria Loss of Offsite Power or SI on the Other Unit Loss of Charging Criteria FOLDOUT PAGE NRC EXAM SECURE INFORMATION Page 30 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG EVENT 6 - LARGE BREAK LOCA 3-EOP-E-0, RX TRIP OR SAFETY INJECTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE NOTE The actions of Attachment 3 are listed beginning on page 38. BOP: Continues with ATTACHMENT 3 to complete The Prompt Action Verifications.

STEP 5 RCO: Check AFW Pumps

- AT LEAST TWO RUNNING STEP 6 RCO: Verify AFW Valve Alignment

- PROPER EMERGENCY ALIGNMENT STEP 7 NOTE Crew may enter 3

-EOP-FR-H.1 if total AFW flow is less than 400 gpm with all Steam Generators LESS THAN 27% Narrow Range.

RCO: Verify Proper AFW Flow:

Check Narrow Range Level in at least one S/G - GREATER THAN 7%[27%]

Maintain feed flow to S/G until Narrow Range Levels between 21%[27%]

and 50% STEP 8 RCO: All RCP Thermal Barrier Alarms

- CLEAR (NO) Trip RCPs (RCPs tripped per Foldout Page.) Check All RCP CBO temperatures

-LESS THAN 260°F SI - RESET Start one Charging Pump at minimum speed for Seal Injection.

Adjust HCV 121, Charging Flow T o Regen Heat Exchanger, to maintain proper Seal Injection flow STEP 9 NRC EXAM SECURE INFORMATION Page 31 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG EVENT 6 - LARGE BREAK LOCA 3-EOP-E-0, RX TRIP OR SAFETY INJECTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE RCO: Check RCS Temperatures:

Check RCPs

- ANY RUNNING (NO) Check RCS Cold Leg temperatures stable between 545°F and 547°F or trending down to 547°F (NO) IF TCOLD is decreasing, THEN perform the following:

Stop dumping steam.

I F cooldown continues AND is due to excessive feed flow, then reduce total feed flow to 400 gpm until Narrow Range Level greater than 7%[27%] in at least one S/G.

IF cooldown continues AND is due to excessive steam flow, THEN close Main Steamline isolation and Bypass valves.

STEP 10 RCO: Check PRZ PORVs, Spray Valves And Excess Letdown Isolated:

STEP 11 RCO: Check If RCPs Should Be Stopped:

RCPs - ANY RUNNING (NO) STEP 12 RCO: Check If S/Gs Are Faulte d: (NO) STEP 13 RCO: Check If S/G Tubes Are Ruptured:

(NO) STEP 14 NRC EXAM SECURE INFORMATION Page 32 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG EVENT 6 - LARGE BREAK LOCA 3-EOP-E-0, RX TRIP OR SAFETY INJECTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE RCO: Check If RCS Is Intact (NO) US: Perform the following:

Monitor Critical Safety Functions using 3-EOP-F-0, CRITICAL SAFETY FUNCTION STATUS TREES. INTEGRITY Critical Safety Function Status Tree is RED Go to 3-EOP-FR-P.1 , RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION STEP 15 US: Reviews the Fold Page of 3

-EOP-FR-P.1 ADVERSE CONTAINMENT CONDITIONS RCO: Check RCS Pressure

- GREATER THAN 275 PSIG [575 PSIG] (NO) Check RHR flow greater than1100 gpm. US: Returns to 3

-EOP-E-0, step 15.

Go to 3-EOP-E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1 NRC EXAM SECURE INFORMATION Page 33 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG EVENT 6 - LB LOCA 3-EOP-E-1, Loss Of Reactor Or Secondary Coolant TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOOTH OPERATOR If dispatched to start the B Standby SGFP, wait 3 minutes and then trigger START B STANDBY SGFP

. US: Conducts EOP transition brief.

Directs 3-EOP-E-1 response.

US: Reviews FOP for 3

-EOP-E-1 with the crew. Containment Adverse (YES) RCP Trip Criteria

- Tripped SI Termination Criteria Secondary Integrity Criteria.

E-3 Transition Criteria Cold Leg Recirculation Switchover Criteria. (met < 155k)

Recirculation Sump Blockage.

CST Makeup Water Criteria. Loss of Offsite Power or Unit 4 SI RHR Sys Operation Criteria Loss Of Charging Criteria FOLDOUT PAGE RCO: Check If RCPs Should Be Stopped (Tripped) STEP 1 RCO: Check If S/Gs Are NOT Faulted

. STEP 2 NRC EXAM SECURE INFORMATION Page 34 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG EVENT 6 - LB LOCA 3-EOP-E-1, Loss Of Reactor Or Secondary Coolant TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE RCO: Check Intact S/G Levels:

Any Narrow Range Level Greater Than 7%[27%].

- Maintain total feed flow greater than 400 gpm until Narrow range Level greater the 7% [27%] in at least one S/G.

Control feed flow to maintain Narrow Range Level between 21%[27%] and 50%. Narrow Range Level Less Than 50%.

STEP 3 BOOTH OPERATOR Acknowledge the request for Chemistry and HP support RCO: Check Secondary Radiation:

STEP 4 RCO: Checks PRZ PORVs And Block Valves:

STEP 5 RCO: Check SI - RESET STEP 6 RCO: Rese ts Containment Isolation Phase A and Phase B.

STEP 7 RCO: Verify Instrument Air To Containment STEP 8 RCO: Check Power Supply To All Charging Pumps - ALIGNED TO OFFSITE POWER STEP 9 NRC EXAM SECURE INFORMATION Page 35 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG EVENT 6 - LB LOCA 3-EOP-E-1, Loss Of Reactor Or Secondary Coolant TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE RCO: Check If Charging Flow Has Been Established.

Charging pumps

- AT LEAST ONE RUNNING (YES) Establish desired charging by performing ATTACHMENT 2 , step s 3 through 5.

- Place RCS Makeup Control Switch in STOP - Start additional Charging pumps if needed. - Adjust Charging Flow To Regen Heat Exchanger, HCV 121, to maintain proper seal injection flow.

- Verify charging pump suction auto transfers to RWST. - Notify Unit Supervisor That Attachment 2 Is Complete.

STEP 10 US: Check if SI Flow Should Be Terminated (NO) STEP 11 RCO: Check if Containment Spray should be stopped. (NO) STEP 12 RCO: Check If RHR Pumps Should Be Stopped. (NO) STEPS 13 NRC EXAM SECURE INFORMATION Page 36 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG EVENT 6 - LB LOCA 3-EOP-E-1, Loss Of Reactor Or Secondary Coolant TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE RCO\BOP: Check RCS And S/G Pressures Pressure in all S/Gs

- STABLE OR INCREASING RCS pressure STABLE OR DECREASING STEP 14 BOOTH OPERATOR If directed to Stop 4A and 4B EDG

, acknowledge request.

BOOTH OPERATOR If dispatched to place any stopped EDGs in standby , acknowledge request.

BOP: Check If Diesel Generators Should Be Stopped: Stop 3A and 3B EDG by placing its Normal Stop/Normal Start switch in NORMAL STOP position.

Direct Unit 4 RCO to stop any unloaded diesel generator by placing its Normal Stop/Normal Start switch in NORMAL STOP position.

Dispatch Operator to place any stopped EDGs in standby using 3/4-OP-023, EMERGENCY DIESEL GENERATOR STEP 15 BOOTH OPERATOR If dispatched to unlock and close cold leg recirc breakers, wait 2 to 3 minutes then trigger LOA - ENERGIZE TRAIN A SI RECIR MOVS and LOA - ENERGIZE TRAIN B SI RECIR MOVS US: Initiate Evaluation Of Plant Status STEP 16 The scenario may be terminated after the crew transitions from 3

-EOP-FR-P.1 to 3-EOP-E-1 at the Lead Evaluator's discreti on once all Critical Task have been evaluated.

• • • END OF SCENARIO ***

NRC EXAM SECURE INFORMATION Page 37 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG EVENT 8 - CV-3-2826/2819, CONTAINMENT ISOLATION IA BLEED VALVES, FAIL TO AUTO CLOSE 3-EOP-E-0 ATTACHMENT 3, PROMPT ACTION VERIFICATIONS TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOP: Check Load Centers Associated With Energized 4 KV Buses

- ENERGIZED STEP 1 BOP: Verify Feedwater Isolation:

STEP 2 NOTE The crew may have take n Prudent Operator Actions to close CV-3-2826 after SI Actuated.

3-CV-3-2819 is failed open and will not close in auto or manual.

BOP: Check If Main Steam Lines Should Be Isolated STEP 3 CT 2 Close CV-3-2826 During a Large Break LOCA

, close containment isolation valves such that at least one valve is closed on each critical Phase A penetration before whichever of the following occurs first:

The completion of 3

-EOP-0 Attachment 3 Within 60 minutes of the Phase A actuation signal.

BOP: Verify Containment Isolation Phase A Valve White Lights On VPB

- ALL BRIGHT (NO) Manually actuate Containment isolation Phase A.

Close CV-3-2826 STEP 4 NRC EXAM SECURE INFORMATION Page 38 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG EVENT 7 - 3B RHR PUMP FAILS TO AUTO START 3-EOP-E-0 ATTACHMENT 3

- PROMPT ACTION VERIFICATIONS TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE

CT1 NOTE The crew may have tak e n Prudent Operator Actions to start the 3B RHR pump after SI actuated. Start 3B RHR Pump During a Large Break LOCA start at least one RHR pump to provide core cooling prior to transition to 3

-EOP-ECA-1.1, Loss of Emergency Coolant Recirculation.

BOP: Verify Pump Operation:

At least two High

-Head SI Pumps

- RUNNING Both RHR Pumps

- RUNNING (NO) Starts the 3B RHR pump STEP 5 BOP: Verify Proper CCW System Operation:

CCW Heat Exchangers

- THREE IN SERVICE CCW Pumps

- ONLY TWO RUNNING CCW Headers

- TIED TOGETHER MOV-3-626, RCP Thermal Barrier CCW Outlet

- OPEN (NO Phase B)

STEP 6 BOP: Verify Proper ICW System Operation:

Verify ICW Pumps

- AT LEAST TWO RUNNING Verify ICW To TPCW Heat Exchanger

- ISOLATED: Check ICW Headers

- TIED TOGETHER STEP 7 BOP: Check Emergency Containment Coolers

- ONLY TWO RUNNING STEP 8 NRC EXAM SECURE INFORMATION Page 3 9 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG EVENT 7 - 3B RHR PUMP FAILS TO AUTO START 3-EOP-E-0 ATTACHMENT 3

- PROMPT ACTION VERIFICATIONS TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOP: Verify Unit 3 Containment Purge Exhaust And Supply Fans

- OFF STEP 9 BOP: Verify Containment Spray and Phase B actuate d. STEP 10 BOP: Verify SI

- RESET STEP 11 BOP: Verify SI Valve Amber Lights On VPB

- ALL BRIGHT STEP 12 BOP: Verify SI Flow:

RCS pressure

- LESS THAN 1625 PSIG[1950 PSIG]

High-Head SI Pump flow indicator

- CHECK FOR FLOW STEP 13 BOOTH OPERATOR When requested, trigger LOA - ALIGN U-4 HHSI s TO U3 RWST BOP: Realign SI System:

Check Procedure Entry Status

- E-0 ENTERED FROM 3

-ONOP-047.1, LOSS OF CHARGING FLOW IN MODES 1 THROUGH 4 (NO) Verify Unit 3 High

-Head SI Pumps

- TWO RUNNING Stop both Unit 4 High

-Head SI Pumps and place in standby Direct Unit 4 Reactor Operator to align Unit 4 High

-Head SI Pump suction to Unit 3 RWST using Attachment 1.

STEP 14 NRC EXAM SECURE INFORMATION Page 40 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG EVENT 7 - 3B RHR PUMP FAILS TO AUTO START 3-EOP-E-0 ATTACHMENT 3

- PROMPT ACTION VERIFICATIONS TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOP: Verify Containment Isolation Phase A

- RESET STEP 15 BOP: Reestablish RCP Cooling:

Check RCPs

- AT LEAST ONE RUNNING (NO) Go to Ste p 17 STEP 16 BOP: Verify Control Room Ventilation Isolation:

STEP 17 BOOTH OPERATOR When requested, trigger LOA - PLACE PAHM IN SERVICE , wait 3 to 5 minutes and then report task complete.

BOP: Place Hydrogen Monitors In Service Using 3-NOP-094, CONTAINMENT POST ACCIDENT MONITORING SYSTEM STEP 18 BOP: Verify All Four EDGs

- RUNNING STEP 19 BOP: Verify Power To Emergency 4 KV Buses:

STEP 20 BOP: Notify Unit Supervisor Of The Following:

Attachment 3 is complete Any safeguards equipment that is NOT running is in the required condition Status of Containment pressure continuous action STEP 21 NRC EXAM SECURE INFORMATION Page 41 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG Discussion Points are intentionally NOT included in evaluated scenarios. However, space is available below to document follow

-up questions when further information is required to determine an evaluation outcome. FOLLOW-UP QUESTIONS QUESTION #1 ________________________________________________________________________________________________________________________________________________________________________

________________________________________________________________________________

ANSWER #1 ______________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________

QUESTION #2 ________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________

ANSWER #2 ______________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________

NRC EXAM SECURE INFORMATION Page 42 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG SIMULATOR POST

-SCENARIO RESTORATION

______ 1. Restore per Simulator Operator Checklist.

______ 2. Once exams are complete, restore from SEI

-19, Simulator Exam Security.

NRC EXAM SECURE INFORMATION Page 43 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG NRC EXAM SECURE INFORMATION Page 44 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG NRC EXAM SECURE INFORMATION Page 45 of 49 L-16-1 NRC EXAM SCENARIO 1 NRC EXAM SECURE INFO RMATION SEG NRC EXAM SECURE INFORMATION Page 46 of 49 L-16-1 NRC EXAM SCENARIO 1 DRAFT L-16-1 NRC EXAM SECURE INFO RMATION SEG OPERATIONS SHIFT TURNOVER REPORT UNIT 3 RISK: GREEN (ACCEPTABLE)

PROTECTED TRAIN:

B UNIT 4 RISK: GREEN (ACCEPTABLE)

PROTECTED TRAIN: B ONCOMING CREW ASSIGNMENTS Shift Mgr:

Inside SNPO:

Field Supv.:

Outside SNPO:

Admin RCO:

ANPO: Unit 3 Unit 4 Unit Supv.:

Unit Supv.:

RCO: RCO: NPO: NPO: PLANT STATUS Unit 3 Unit 4 Mode: 1 Mode: 1 Power: 75% Power: 100% MWe: 608 MWe: 842 Gross Leakrate:

.22 gpm Gross Leakrate:

0.03 gpm RCS Boron Conc:

828 ppm RCS Boron Conc:

642 Operational Concerns:

3A RHR pump taken OOS 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago for an oil change

, expected back by the end of this shift.

3A1 Circ Water pump OOS. Tripped on over current, Electrical Mainte nance is investigating.

3 A Condensate pump was returned to service last shift following a motor bearing replacement.

Return to full power expected next shif

t. MIMS alarms are inhibited.

U3 Anticipated LCO Actions:

None U4 Anticipated LCO Actions:

None Results of Offgoing Focus Area:

NRC EXAM SECURE INFORMATION Page 47 of 49 L-16-1 NRC EXAM SCENARIO 1 DRAFT L-16-1 NRC EXAM SECURE INFO RMATION SEG UNIT 3 STATUS REACTOR OPERATOR UNIT RISK: GREEN (ACCEPTABLE) PROTECTED TRAIN:

B Mode: 1 RCS Leakrate Accumulator Ref Levels Power: 75% Gross: 0.22 GPM A 6656 MWe 608 Unidentified 0.04 GPM B 6608 Tavg: 571°F Charging Pps:

0.0 0 GPM C 6646 RCS Pressure:

22 3 5 RCS Boron Conc:

828 ppm Abnormal Annunciators:

Annunciator:

Comp Actions:

Annunciator:

Comp Actions:

Annunciator:

Comp Actions:

Annunciator:

Comp Actions:

Annunciator:

Comp Actions:

Annunciator:

Comp Actions:

Current Tech Spec Action Statements: (Does Not Include "For Tracking Only Items" T.S.A.S / Component:

3A RHR pump, 3.5.2.c

- Action g Reason: Oil Change Entry Date:

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago T.S.A.S / Component:

Reason: Entry Date:

T.S.A.S / Component:

Reason: Entry Date:

T.S.A.S / Component:

Reason: Entry Date:

T.S.A.S / Component: Reason: Entry Date:

NRC EXAM SECURE INFORMATION Page 48 of 49 L-16-1 NRC EXAM SCENARIO 1 DRAFT L-16-1 NRC EXAM SECURE INFO RMATION SEG REACTOR OPERATOR (CONT'D) UNIT RISK: GREEN (ACCEPTABLE) PROTECTED TRAIN:

B Changes to Risk Significant Equipment:

No recent changes from last shift.

OLRM: GREEN PROTECTED TRAIN: B Upcoming Reactivity Management Activities:

Maintain current power level

+ .5% Xe is stable.

Upcoming Major POD Activities:

NONE Upcoming ECOs to Hang and /or Release:

Hang - None Release - None Evolutions or Compensatory Actions in Progress:

NONE General Information, Remarks, and Operator Work Around Status:

Weather forecast is overcast skies with scattered pockets of severe rain.

U3 supplying Aux Steam Air In-leakage = 0.0 SCFM NRC EXAM SECURE INFORMATION Page 49 of 49 NRC EXAM SECURE INFORMATIONAppendix D Scenario Outline Form ES-D-1 L-16-1 N2 (Rev-0) Facility:

Turkey Point Units 3 & 4 Scenario No.: 2 Op Test No.: 2016-301 Examiners:

Operators: (SRO) (R C O) (BOP) Initial Conditions:

The plant is at 100% power (BOL). Online risk is green. B train is protected on both units. Turnover: The 3A RHR pump and 3A1 Circulating Water pump are OOS.

Event. Malf. No. Event Type*

Event Description 1 TFB1LTLV I-RCO I-SRO LT-3-115 VCT Level Transmitter Fails Low 2 TVUTPMPA TFL10101 C-RCO C-SRO 3A Heater Drain Pump Trip (Turbine Runback) Rods Fail To Auto Insert 3 TFN1CP22 I-BOP I-S RO (TS) N-42 Loss Of Instrument Power 4 N/A R-RCO R-SRO N-BOP 3B S/G Feedwater pump High Vibration (Fast Load Reduction required) 5 TFS1M5EA I-BOP I-SRO (TS) FT-3-494 3C S/G Steam Flow Transmitter Fails As Is 6 TVFAHDR1 TVSBVL14 TAFK144 TAFK244 TAFK344 M-RCO M-BOP M-SRO Common Main Feed Header Break Common Loss Of Suction To All AFW Pumps 7 TFU10005 P- BOP Main Turbine Fails To Automatically Trip 8 TFHV55CC P-RCO PCV-3-455C Fails To Open. (PZR PORV)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (P)ost TripNRC EXAM SECURE INFORMATION Page 1 of 3 NRC EXAM SECURE INFORMATION Appendix D Scenario Outline Form ES-D-1 L-16-1 N2 (Rev-0) SCENARIO

SUMMARY

Event 1 Shortly after the crew takes the shift LT-3-115 VCT Level Transmitter Fails Low which causes auto makeup to start. The crew responds using the 3

-ONOP-046.4 , Malfunction of Boron Concentration Control System. The RCO manually stops auto makeup.

Event 2 Once the crew stabilizes VCT level the 3A Heater Drain Pump trips which causes an automatic Turbine Runback. The crew will enter 3

-ONOP-089, Turbine Runback. During the runback Control Rods fail to auto insert. The RCO will manually insert rods to maintain Tave

+ 3F. When the Runback is complete the RCO will borate as needed to clear Rod Lo Limit and Axial Flux alarms, and the BOP will reset the Steam Dumps. When the plant is stable the crew will enter 3

-ONOP-028, Reactor Control System Malfunction for the failure of Rods to auto insert.

Event 3 Once the crew resets the Steam Dumps and completes the required actions for the Reactor Control System Malfunction the N-42 Instrument Power Fuse Blows. The crew will enter 3

-ONOP-059.8, Power Range Nuclear Instrumentation Malfunction. The BOP will defeat or bypass the affect functions of N

-42 as directed by the ONOP.

Event 4 After the crew completes the actions of 3

-ONOP-059.8 Engineering reports High Vibration on the 3B SGFW pump. The SM directs the crew to start a 3-GOP-100 Fast Load Reduction to secure the 3B SGFW pump.

Event 5 When the crew starts the down power FT 494, 3C S/G Steam Flow Transmitter will be failed as is. The BOP will take manual control of the 3C S/G level and restore the 3C S/G level to normal. The US will enter 3

-ONOP-049.1, direct the BOP to select an operable channel, and restore 3C S/G level control to automatic.

Event 6 After the crew reduces power by 5 to 10% and completes the actions for the failed Steam Flow channel a Main Feed Water Header break occurs. The crew responds to the reactor trip using 3

-EOP-E-0, Reactor Trip or Safety Injection. During the loss of Main Feed Water the re's also a los s of the suction piping to all AFW pumps

. The crew will transition to 3

-EOP-FR-H.1, Response To Loss Of Secondary Heat Sink, and initiate Feed and Bleed.

Event 7 During 3-EOP-E-0, The Main Turbine fails to automatically trip. The BOP will take compensatory action to trip the Turbine manually.

Event 8 When the crew attempts to initiate Feed and Bleed one of the PZR PORVs fails to open so the crew will open all RCS Vent Valves The scenario is terminated once the RCS Vent Valves are or at the Lead Evaluator's discretion once all critical task s have been evaluated.

NRC EXAM SECURE INFORMATION Page 2 of 3 NRC EXAM SECURE INFORMATION Appendix D Scenario Outline Form ES-D-1 L-16-1 N2 (Rev-0) Event CRITICAL TASKS 6 CT1 Manually Trip the Main Turbine Manually trip the main turbine before any RCS cold leg temperature decreases by more than 100 F. Safety Significance

- Failure to trip the main turbine causes an excessive rate of RCS cooldown, well beyond the conditions typically analyzed in the FSAR. The excessive cooldown rate creates large thermal stresses in the reactor pressure vessel and causes rapid insertion of a large amount of positive reactivity. Thus, failure to manually trip the Main Turbine under the postulated conditions can result in challenges to the Integrity and Subcriticality CSFs. 6 CT2 Initiate Bleed

-And-Feed Initiate RCS bleed and feed so that the RCS depressurizes sufficiently for high

-head injection to occur.

Safety Significance

- Failure to initiate RCS bleed and feed before the RCS saturates at a pressure above which the high-head ECCS pumps can inject results in significant and sustained core uncovery. If RCS bleed is initiated so that the RCS is depressurized below the shutoff head of the high-head ECCS pumps, then core uncovery is prevented or minimized.

NRC EXAM SECURE INFORMATION Page 3 of 3 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG Site: Turkey Point Units 3 and 4 (PTN)

Title: L-16-1 NRC EXAM SCENARIO 2 LMS #: NRC 22 LMS Rev Date:

6/7/16 Rev #: 0.0 SEG Type: Training Evaluation Program: LOCT LOIT Other Duration: 1 1 0 minutes Developed by:

Brian Clark 8/4/16 Instructor/Developer Date Reviewed by:

Luis Sagion 8/4/16 Instructor (Instructional Review)

Date Validated by :

Sean Bloom 8/5/16 SME (Technical Review)

Date Approved by:

Mark Wilson 8/5/16 Training Supervision Date Approved by:

Sean Bloom 8/5/16 Training Program Owner (Line)

Date NRC EXAM SECURE INFO RMATION L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG SCENARIO REFERENCES DOC NO. TITLE REV PTN TECHNICAL SPECIFICATIONS 300 3-EOP-E-0 REACTOR TRIP OR SAFETY INJECTION 12 3-GOP-100 FAST LOAD REDUCTION 12 A 3-ONOP-028 REACTOR CONTROL SYSTEM MALFUNCTION 4 A 3-ONOP-046.4 MALFUNCTION OF BORON CONCENTRATION CONTROL SYSTEM 0 3-ONOP-049.1 DEVIATION OR FAILURE OF SAFETY RELATED OR REACTOR PROTECTION CHANNEL 4 3-ONOP-059.8 POWER RANGE NUCLEAR INSTRUMENTATION MALFUNCTION 0A 3-ONOP-089 TURBINE RUNBACK 1 A 3-OSP-059.10 DETERMINATION OF QUADRANT POWER TILT RATIO 2A NRC EXAM SECURE INFORMATION Page 2 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Objective Given this simulator scenario and resources normally found in the Control Room, the operating crew will perform Control Room operations IAW approved plant procedures in order to maintain the integrity of the plant and the health and safety of the public.

Enabling Objectives:

Given this simulator scenario and resources normally found in the Control Room, operate in accordance with approved plant procedures, Operations Department Instructions, and management expectations:

1. (ALL) Demonstrate personnel SAFETY awareness in interactions with plant staff and outside agencies.

2. (ALL) Demonstrate ALARA awareness in interactions with plant staff and outside agencies.

3. (ALL) Exchange correct information using 3

-point communication/Repe at-backs with Control Room personnel and other plant staff.

4. (ALL) Inform plant personnel and System of plant conditions, as needed.

5. (US) Employ timely and concise crew briefs where appropriate.

6. (ALL) Maintain awareness of plant status and control board indication. 7. (ALL) Correctly diagnose plant situations.

8. (ALL) Solve operational problems as they arise.

9. (RCO/BOP) Manipulate plant controls properly and safely.

10. (ALL) Demonstrate self

-checking using STAR and peer checks(when required)

11. (US) Demonstrate command and control of the crew.

12. (US) Coordinate the input of crew members and other plant staff.

13. (US) Utilize the input of crew members and other plant staff.

14. (ALL) Demonstrate conservative decision making.

15. (ALL) Demonstrate teamwork.

16. (ALL) Respond to plant events using procedural guidance (OPs/ONOPs/EOPs) as applicable in accordance with rules of usage.

17. (RCO/BOP) Implement any applicable procedural immediate operator actions without use of references.

18. (SRO) Maintain compliance with Tech Specs.

19. (ALL) Identify/enter applicable Tech Spec action statements.

20. (ALL) Respond to annunciators using ARPs (time permitting).

21. (ALL) Maintain written communication, logs, and documentation as needed to permit post

-event reconstruction.

Continued on next page NRC EXAM SECURE INFORMATION Page 3 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS While addressing the following events:

1. LT-3-115 VCT Level Transmitter Fails Low.

2. 3A Heater Drain Pump (Turbine Runback)

Rods Fail To Auto Insert

3. N-42 Loss Of Instrument Power 4. 3B S/G Feedwater pump High Vibration (Fast Load Reduction required)

5. FT-3-494 3C S/G Steam Flow Transmitter Fails As Is

6. Common Main Feed Header Break Common Loss Of Suction To All AFW Pumps

7. Main Turbine Fails To Automatically Trip

8. PCV-3-455C Fails To Open (PZR PORV)

Prerequisites:

None Training Resources:

PTN Unit 3 Plant Simulator Development Refer ences: TR-AA-220-1003, Initial N RC and Audit Exam Process TR-AA-230-1003, SAT Development TR-AA-230-1007 , Conduct of Simulator Training and Evaluation 0-ADM-232, Time Critical Action Program OP-AA-100-1000, Conduct Of Operations OP-AA-103-1000 , Reactivity Management 0-ADM-200, Operations Management Manual 0-ADM-211, Emergency and Off

-Normal Operating Procedure Usage WCAP-17711-NP, Pressurized Water Reactor Owners Group Westinghouse Emergency Response Guideline Revision 2

-Based Critical Tasks Protected Content: N/A Evaluation Method: Performance Mode Operating Experience:

None Risk Significant Operator Actions: Initiate bleed

-and-feed cooling within 36 minutes following a loss of Feed Water with a reactor trip on low SG level.

NRC EXAM SECURE INFORMATION Page 4 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG TASKS ASSOCIATED WITH THIS SIMULATOR EXERCISE GUIDE SRO TASK #

TASK TITLE 02028033500 Authorize Unit Trip 02046045300 Recover From VCT Level Transmitter Failures 02059026300 Respond To Loss Of Power Range Instrumentation Channel 02074016500 Respond To A Loss Of Heat Sink Following A Reactor Trip 02081006300 Respond To A Loss Of One Heater Drain Pump 02200046500 Respond to Steam Generator Low Level 02200009300 Respond to Unit Runback RO TASK TASK TITLE 01046045300 Recover from VCT Level Transmitter Failures 0105 9026300 Respond to Loss of Power Range Instrumentation Channel 01074006100 Stop Steam Generator Feed Pump 01074011300 Control Steam Generator Level Manually With Main Feed Regulating Valves 01074016500 Respond To A Loss Of Heat Sink Following A Reactor Trip 01081006300 Respond to a Loss of One Heater Drain Pump 01089020100 Trip Turbine Manually 01200001500 Respond To Unit Trip 01200046500 Respond to Steam Generator Low Level 01200009300 Respond to Unit Runback NRC EXAM SECURE INFORMATION Page 5 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG UPDATE LOG:

NOTES: Place this form with the working copies of lesson plans and/or other materials to document changes made between formal revisions. For fleet

-wide training materials, keep electronic file of this form in same folder as approved materials. Refer to TR

-AA-230-1003 SAT Development for specific directions regarding how and when this form shall be used.

Indicate in the following table any minor changes or major revisions (as defined in TR

-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR

-AA-230-1003-F16. # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE REVIEWER DATE 0-0 Initial Revision Revised for L-1 6-1 NRC Exam 2108338 Note 5 Note 5 Note 5 Note 5 0-1 0-2 0-3 0-4 0-5 1. Individual updating lesson plan or training material shall complete the appropriate blocks on the Update Log.

2. Describe the change to the lesson plan or training materials.

3. State the reason for the change (e.g., reference has changed, typographical error, etc.)

4. Preparer enters name/date on the Update Log and obtains Training Supervisor approval.

5. Initial dates and site approval on cover page.

NRC EXAM SECURE INFORMATION Page 6 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG SCENARIO

SUMMARY

Initial Conditions

The plant is at 100% power (BOL). Online risk is green. B train is protected on both units Equipment OOS The 3A RHR pump and 3A1 Circulating Water pump are OOS.

SCENARIO

SUMMARY

Event 1 Shortly after the crew takes the shift

, LT-3-115 , VCT Level Transmitter

, Fails Low which causes auto makeup to start. The crew responds using the 3

-ONOP-046.4, Malfunction of Boron Concentration Control System. The RCO manually stops auto makeup.

Event 2 Once the crew stabilizes VCT level

, the 3A Heater Drain Pump trips

, which causes an automatic Turbine Runback. The crew will enter 3

-ONOP-089, Turbine Runback. During the runback

, Control Rods fail to auto insert. The RCO will manually insert rods to maintain Tave

+3F. When the Runback is complete

, the RCO will borate as needed to clear Rod Lo Limit and Axial Flux alarms, and the BOP will reset the Steam Dumps.

When the plant is stable

, the crew will enter 3

-ONOP-028, Reactor Control System Malfunction

, for the failure of Rods to auto insert.

Event 3 Once the crew resets the Steam Dumps and completes the required actions for the Reactor Control System Malfunction

, the N-42 Instrument Power Fuse Blows. The crew will enter 3

-ONOP-059.8, Power Range Nuclear Instrumentation Malfunction. The BOP will defeat or bypass the functions of N

-4 2 , as directed by the ONOP.

Event 4 After the crew completes the actions of 3

-ONOP-059.8 , Engineering reports High Vibration on the 3B SGFW pump. The SM directs the crew to start a 3

-GOP-100 Fast Load Reduction to secure the 3B SGFW pump.

Event 5 When the crew starts the down power

, FT-3-494, 3C S/G Steam Flow Transmitter

, will be failed as is. The BOP will take manual control of the 3C S/G level and restore the 3C S/G level to normal.

The US will enter 3-ONOP-049.1 , Deviation or Failure of Safety Related or Reactor Protection Channels , and direct the BOP to select an operable channel, then restore 3C S/G level control to automatic.

NRC EXAM SECURE INFORMATION Page 7 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG SCENARIO

SUMMARY

Event 6 After the crew reduces power by 5 to 10% and completes the actions for the failed Steam Flow channel

, a Main Feed Water Header break occurs inside containment. The crew responds to the reactor trip using 3-EOP-E-0, Reactor Trip or Safety Injection. During the loss of Main Feed Water

, there's also a loss of the suction piping to all AFW pumps. The crew will transition to 3-EOP-FR-H.1, Response To Loss Of Secondary Heat Sink, and initiate Feed and Bleed.

Event 7 During 3-EOP-E-0, The Main Turbine fails to automatically trip. The BOP will take compensatory action to trip the Turbine manually.

Event 8 When the crew attempts to initiate Feed and Bleed

, one of the PZR PORVs fails to open so the crew will open all RCS Vent Valves The scenario is terminated once the RCS Vent Valves are open or at the Lead Evaluator's discretion once all critical task s have been evaluat ed. NRC EXAM SECURE INFORMATION Page 8 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG Event CRITICAL TASKS 7 CT1 Manually Trip the Main Turbine Manually trip the main turbine before any RCS cold leg temperature decreases by more than 100 F. Safety Significance

- Failure to trip the main turbine causes an excessive rate of RCS cooldown, well beyond the conditions typically analyzed in the FSAR. The excessive cooldown rate creates large thermal stresses in the reactor pressure vessel and causes rapid insertion of a large amount of positive reactivity. Thus, failure to manually trip t he Main Turbine under the postulated conditions can result in challenges to the Integrity and Subcriticality CSFs.

8 CT2 Initiate Bleed

-And-Feed Initiate RCS bleed and feed so that the RCS depressurizes sufficiently for high

-head injection to occur Safety Significance

- Failure to initiate RCS bleed and feed before the RCS saturates at a pressure above which the high

-head ECCS pumps can inject results in significant and sustained core uncovery. If RCS bleed is initiated so that the RCS is depressurized below the shutoff head of the high

-head ECCS pumps, then core uncovery is prevented or minimized.

NRC EXAM SECURE INFORMATION Page 9 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG SEQUENCE OF EVENTS Event # Description

1. LT-3-115 VCT Level Transmitter Fails Low

2. 3A Heater Drain Pump (Turbine Runback)

Rods Fail To Auto Insert

3. N-42 Loss Of Instrument Power 4. 3B S/G Feedwater pump High Vibration (Fast Load Reduction required)

5. FT-3-494 3C S/G Steam Flow Transmitter Fails As Is

6. Common Main Feed Header Break Common Loss Of Suction To All AFW Pumps

7. Main Turbine Fails To Automatically Trip

8. PCV-3-455C Fails To Open (PZR PORV)

NRC EXAM SECURE INFORMATION Page 10 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG SIMULATOR SET UP INSTRUCTIONS Check Action ____ Restore IC

-11 (100% BOL) or equivalent IC.

____ Place the Simulator in RUN. ____ Stop the 3A1 Circ Water Pump

____ Open & execute lesson file L

-1 6-1 N2 ____ Ensure the following lesson steps are triggered:

EVENT 6 SETUP

- LOSS OF AFW PUMP SUCTION EVENT 8 SETUP

- PORV 455C FAILED CLOSE EVENT 7 SETUP

- TURBINE FAILS TO TRIP EVENT 7 SETUP

- CV FAIL AS IS is in CONDITION state SETUP - 3A RHR PUMP OOS SETUP - 3A1 CWP OOS

____ Place 3A RHR pump in PTL and hang an ECO Card 3 A 1 CWP in stop and hang an ECO card

____ Verify the trend for 3A1 Screen on the TWS DP Recorder is clear.

____ Ensure Rod Group Step Counters have completed stepping out.

____ Allow the plant to stabilize.

____ Acknowledge any alarms and freeze Simulator.

____ Ensure B train is protected train on VPA.

____ Verify Key 13 for Reactor Head Vent valves is in the key locker (6 keys on one key ring)

____ Perform the SIMULATOR OPERATOR CHECKLIST or equivalent.

____ Place TURNOVER SHEETS on RO

's desk or give to the Lead Evaluator.

NRC EXAM SECURE INFORMATION Page 11 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG BRIEFINGS Shift turnover information is attached to the back of this guide.

Ensure all applicants are prior briefed on Appendix E of NUREG 1021, Policies and Guidelines For Taking NRC Examinations.

Conduct a Crew Pre

-brief to cover turnover information. Shift turnover information is attached to the back of this guide.

US: RCO: BOP: SCENARIO NOTE 0-ADM-211 Prudent Operator Actions

- If redundant stand

-by equipment is available and ready, the operator is permitted to start the redundant equipment for failed or failing operating equipment.

Immediate follow up of applicable ARPs and ONOPs (AOPs) shall occur as required.

NRC EXAM SECURE INFORMATION Page 12 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG Critical T ask s are highlighted in red. Simulator Operator Actions are highlight ed in blu e. Operator Verifiable Actions are Highlight ed in gree n. EVENT 1 - LT-3-115 VCT LEVEL TRANSMITTER FAILS LOW.

3-ONOP-046.4, MALFUNCTION OF BORON CONCENTRATION CONTROL SYSTEM TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE NOTE Ensure the Simulator is in RUN before the crew enters the Simulator.

US: Conducts shift turnover. BOOTH OPERATOR When directed by the Lead Evaluator, trigger EVENT 1 - LT-3-11 5 FAILS LOW RCO: Responds to Alarms A3/4 VCT AUTO MAKE-UP and A4/6 VCT HI/LOW LEVEL VERIFY Make

-Up Flow. Reports LT-3-115 failed low.

BOOTH OPERATOR If dispatched to locally check the VCT level, wait 2

-5 minutes and report LT-3-115 failed low

. No obvious cause of the failure.

BOP: Reviews ARP, refer to 3-ONOP-046.4, Malfunction of Boron Concentration Control System.

Checks VCT level on DCS Dispatches SNPO to locally check LT-3-11 5 indication in charging pump room. US: Directs response using 3-ONOP-046.4, Malfunction of Boron Concentration Control System RCO: Check Boric Acid OR Primary Water Makeup Flow Rates

- ABNORMAL (NO Go to Step 28)

Step 1 NRC EXAM SECURE INFORMATION Page 13 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG EVENT 1 - LT-3-115 VCT LEVEL TRANSMITTER FAILS LOW.

3-ONOP-046.4, MALFUNCTION OF BORON CONCENTRATION CONTROL SYSTEM TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE RCO: Check For VCT Level Transmitter, LT 115, Failing Or Failed High. (NO, Go to Step 31) Step 28 RCO Check for LI 115 Failing Or Failed Low LI-3-115 - ABNORMALLY LOW (YES) LI-3-112 - INCREASING DUE TO AUTO MAKEUP OR STABLE DUE TO LCV-3-115A DIVERTING Step 3 1 US: Review caution and note with the crew

. CAUTION With no operator action, LT 115 failed low with makeup flow greater than charging flow could result in over pressurization of the VCT.

NOTE Failure of LT 115 low will result in the following:

Annunciator Alarm A4/6 VCT HI/LO LEVEL. Auto makeup starts, but does not stop automatically.

LCV-3-115A modulating open to attempt to control level at the VCT Level Controller, LC 112, setpoint RCO: Turn RCS Makeup Control Switch To STOP Go to Step 4

1. Step 3 2 NRC EXAM SECURE INFORMATION Page 14 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG EVENT 1 - LT-3-115 VCT LEVEL TRANSMITTER FAILS LOW.

3-ONOP-046.4, MALFUNCTION OF BORON CONCENTRATION CONTROL SYSTEM TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOOTH OPERATOR Respond as WCC/I&C Notifies WCC/I&C regarding LT-3-11 5 failure. Directs PWO initiation & troubleshooting.

Determines no Tech Specs apply Steps 41/42 Performs a manual MU to the VCT using 0-OP-046, as required Step 43 BOOTH OPERATOR Acknowledge briefing on how to swap charging pump suction to RWST if required.

US: Conducts crew brief.

Briefs Operator how to manually swap charging pump suction to RWST if required.

NRC EXAM SECURE INFORMATION Page 15 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG EVENT 2 - 3A HEATER DRAIN PUMP TRIP , RODS FAIL TO AUTO INSERT 3-ONOP-089, TURBINE RUNBACK TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOOTH OPERATOR When directed by the Lead Evaluator , trigger EVENT 2 - 3A HDP TRIP BOP: Acknowledges Alarms D8/2 , HDP A/B MOTOR OVERLOAD TRIP and E2/5 , TURBINE RUNBACK

. Reports 3A Heater Drain Pump tripped, Turbine Runback in progress NOTE Steps 1 and 2 are Immediate Operator Actions. BOP: Verifies a SGFP was NOT lost. IOA-Step 1 RCO/BOP: Check for proper operation of the following:

Steam Dump s Turbine If Rods are in AUTO, then verify Auto Rod Insertion to match Tavg with Tref.

(NO) - Manually insert Rods as need to match Tavg with Tref Main Feedwater Valves Pressurizer IOA-Step 2 US: Enters and directs the actions of 3

-ONOP-089, Turbine Runba ck. Reviews Notes with the crew.

BOP: Check Steam Generator levels stabilized and on program.

Step 1 NRC EXAM SECURE INFORMATION Page 16 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG EVENT 2 - 3A HEATER DRAIN PUMP TRIP , RODS FAIL TO AUTO INSERT 3-ONOP-089, TURBINE RUNBACK TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE RCO: Check Tavg is maintained within

+3°F of Tref. Place Control Rods in Manual.

Maintain Tavg/Tref T within +3°F. Step 2 BOP: Check Steam Generator pressures stabilizing.

Step 3 RCO: Check Pressurizer Level stabilizing and trending to Program Level.

Step 4 NOTE When the plant is stabilized

, the US may also enter 3

-ONOP-028, Reactor Control System Malfunction due to the failure of rods to auto insert.

3-ONOP-028 starts on page 20. RCO: Check Pressurizer Pressure stabilizing and trending to 2235 psig. Step 5 BOOTH OPERATOR If dispatched to locally check the 3 A Heater Drain pump, wait 5 minutes

, and then report its breaker has an over current flag but nothing abnormal at the pump. BOP: Check following for proper operation:

Steam Gen Feed Pump Recirc Condensate Pump Recirc Heater Drain Pumps Heater Drain Tank Level Controls Secondary Heater Level Controls Step 6 NRC EXAM SECURE INFORMATION Page 17 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG EVENT 2 - 3A HEATER DRAIN PUMP TRIP , RODS FAIL TO AUTO INSERT 3-ONOP-089, TURBINE RUNBACK TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE NOTE The crew should monitor alarms and borate using 50 gallon batches as necessary to withdraw rods until the alarm is clear.

NOTE The crew may acknowledge LEFM inputs using DCS.

RCO/BOP: Monitor Annunciator G5/1, AXIAL FLUX T.S. LIMIT EXCEEDED

-CLEAR. Monitor Annunciator B9/2, Axial Flux Tilt - CLEAR Monitor Annunciator B8/1, ROD BANK LO LIMIT

- CLEAR. RNO Perform the following as necessary after the runback:

A. WHEN runback is complete, THEN PLACE rods in Manual.

B. SET boric acid totalizer to 50 gallons. C. DETERMINE boric acid flow rate as determined by the Unit Supervisor.

D. PLACE the Reactor Makeup Selector Switch to BORATE.

E. PLACE the RCS Makeup Control Switch to START.

F. ADJUST the setpoint on the Boric Acid Controller FC 113A to the desired flow rate as indicated on FR-3-113. G. WITHDRAW Control Rods to establish Tavg/Tref GREATER THAN Tref until Annunciator B8/1 is CLEAR. Monitor Annunciator B8/2 ROD BANK A/B/C/D EXTRA LO LIMIT

- CLEAR. Steps 7 - 10 NOTE The crew may direct personnel to rack out the 3A Heater Drain Pump breaker due to its auto start features.

BOP: When the turbine runback is complete

Match the control switch flag for the 3A Heater Drain pump

. Step s 11.a PROCEDURE NOTE Closing CV-3-2011, LP HTR BYP, can cause a minor secondary transient causing Tavg to rise by 1°F to 2°F, Reactor Power to drop 1% to 2%, and MWe output to rise. NRC EXAM SECURE INFORMATION Page 18 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG EVENT 2 - 3A HEATER DRAIN PUMP TRIP , RODS FAIL TO AUTO INSERT 3-ONOP-089, TURBINE RUNBACK TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE When the turbine runback is complete

Check CV-3-2011, LP HTR BYP CLOSED. Step s 11.b BOOTH OPERATOR Acknowledge reports of plant status and request for support.

BOP: NOTIFY Load Dispatcher of load restrictions.

(~85% and 740 MW)

Step 11c US: Informs SM to notify Plant Management and NRC Resident per 0-ADM-115, Notifications of Plant Events.

Step 11d NOTE The crew may decide to not restore Auto Makeup to AUTO due to previous failures. RCO: If boration was used , when plant conditions are stable, stop the boration and restore Auto Makeup Step 12 NOTE Since Auto Rod control is not working

, the crew should leave rods in manual.

RCO: Check Rod Control in MANUAL.

A. CHECK Tavg within +/-1.5°F of Tref B. PLACE Rod Control in AUTO Step 13 BOOTH OPERATOR Acknowledge notification to take RCS samples. BOP: IF change in Reactor Power exceeded 15%, then notify Chemistry that RCS sampling is required within 2 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> per TS 4.4.8, Table 4.4

-4, Item 6b.

Step 14 NOTE If the RO promptly inserts rods during the runback , the Steam Dumps may not arm.

BOOTH OPERATOR If crew prematurely places SDTC to manual thinking it's malfunctioned, respond appropriately and report that there are no abnormalities.

BOP: Take Steam Dump To Condenser Mode Switch to Reset, and Release to AUTO. Step 15 NRC EXAM SECURE INFORMATION Page 19 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG EVENT 2 - 3A HEATER DRAIN PUMP TRIP, RODS FAIL TO AUTO INSERT 3-ONOP-028, REACTOR CONTROL SYSTEM MALFUNCTION TIME EVALUATOR ACTIVITIES & NOTEs EXPECTED STUDENT RESPONSE US: Enters and direct the actions of 3

-ONOP-028. RCO: Verify Rods in manual.

Step 4.2.1 RCO: Do NOT increase reactor power without permission from the Reactor Engineering Supervisor and the Shift Manager. Manually position the RCC control bank to restore steady state conditions.

Notify Reactor Engineering and I&C Review Subsection 5.1.

Determine Unit Shut d ow n not required at this t i me Steps 5.2.1 - 5.2.5 LEAD EVALUATOR NOTE After plant is stabilized or at the Lead Evaluators discretion, proceed to Event 3 NRC EXAM SECURE INFORMATION Page 20 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG EVENT 3 - N-42 LOSS OF INSTURMENT POWER 3-ONOP-059.8 , POWER RANGE NUCLEAR INSTRUMENTATION MALFUNCTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOOTH OPERATOR When directed by the Lead Evaluator trigger EVENT 3 - N42 BLOWN INST PWR FUSE RCO: Respond to multiple alarms associated with the Power Range Reports N-42 Instrument Power Fuse blown. BOP: Reviews ARPs, recommend entering 3-ONOP-059.8, Power Range Nuclear Instrumentation Malfunction.

US: Enters 3-ONOP-059.8, Power Range NI Malfunction.

BOOTH OPERATOR If asked , I&C would like be present while tripping bistables. They will report to the control room in about one hour.

BOP: Place the DROPPED ROD MODE switch for N 42 channel in the BYPASS position (ANN B8/4)

Place the N4 2 ROD STOP BYPASS switch to the failed channel BYPASS position Transfer the UPPER SECTION comparator defeat switch to the N4

2. Transfer the LOWER SECTION comparator defeat switch to the N4

2. Transfer POWER MISMATCH BYPASS switch to BYPASS N4

2. Transfer the COMPARATOR CHANNEL DEFEAT switch to N4 2 Step 5.1.1.1 - 5.1.1.6 NRC EXAM SECURE INFORMATION Page 21 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG EVENT 3 - N-42 LOSS OF INSTURMENT POWER 3-ONOP-059.8 , POWER RANGE NUCLEAR INSTRUMENTATION MALFUNCTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOOTH OPERATOR Acknowledge request for assistance. If asked , the STA will monitor QPTR

. US: Notify I&C Monitor the Quadrant Power Tilt Ratio using 3-OSP-059.10, Determination Of Quadrant Power Tilt Ratio.

Step 5.1.1.9 - 5.1.1.10 US: Review Tech Specs:

TS 3.3.1, Functional Unit 2 a & b - Action 2, Trip bistables in 6 hrs and restrict power to 75% RTP or monitor QPTR TS 3.3.1, Functional Unit 5 & 6

- Action 13, Trip bistables in 6 hrs LEAD EVALUATOR Once the crew completes the steps of 3-ONOP-059.8, or at the Lead Evaluators discretion , move on the next event.

NRC EXAM SECURE INFORMATION Page 22 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG EVENT 4 - 3B S/G FEEDWATER PUMP HIGH VIBRATION 3-GOP-100, FAST LOAD REDUCTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOOTH OPERATOR When directed by the Lead Evaluator

, call as the SM to report High Vibration on the 3B SG Feedwater pump. Engineering has looked at the pump and recommends it be secured. Direct the crew to start a 3-GOP-100 , Fast Load Reduction

, to secure the 3B SG Feedwater pump

. BOOTH OPERATOR Acknowledge request for support.

NOTE Attachment 3 is available on Page 43 Attachment 4 is available on Page 44 US: Directs actions to reduce Rx power from 50% per 3-GOP-100. Completes Attachment 3 Brief the crew per Attachment 4 Steps 1-2 US: Reviews Foldout page with crew.

3-EOP-E-0 Transition Criteria Notify Chemistry Department Boration Stop Criteria Restore Blender to AUTO FOLDOUT PAGE BOOTH OPERATOR Acknowledge notifications. BOP: Notify The Following Of Fast Load Reduction System Dispatcher Plant personnel using the Page Boost Chemistry to start RCS sampling is required according to Tech Spec Table 4.4-4. Ste p 3 NRC EXAM SECURE INFORMATION Page 23 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG EVENT 4 - 3B S/G FEEDWATER PUMP HIGH VIBRATION 3-GOP-100, FAST LOAD REDUCTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE RCO: Begin Boration For Initial Tavg Effect Set the Boric Acid Totalizer to total boric acid volume value determined on Attachment 3.

Place the Reactor Makeup Selector Switch to BORATE.

Place the RCS Makeup Control Switch to START.

Adjust FC-3-113A, Boric Acid Flow Controller

, to achieve 40 gpm boric acid flow as indicated on FR 113. WHEN Tavg begins to lower from the boration, THEN adjust FC-3-113A, Boric Acid Flow Controller

, to load reduction value from Attachment 3.

Step 4 BOOTH OPERATOR When crew starts reducing power, trigger EVENT 5 - FT-3-494 FAILED AS IS US: Determine Turbine Load Reduction in MW CNTRL Ste p 5 NOTE When the crew notices the 3C Ste a m Flow Chanel

, FT-3-494 , failed as is

, the y may place the ramp on hold. The steps for the FT 494 failure start on page

27. BOP: Initiate Turbine Load Reduction in MW CNTRL Select MW CNTRL Set TARGET power level

- MW VALUE from Attachment 3 Set RAMP RATE

- MW/M VALUE FROM Attachment 3.

Check Tavg has lowered 1° to 2°F from the initial value prior to boration.

Depress GO Ensure FC-3-113A, Boric Acid Flow Controller, has been adjusted to the load reduction boration rate.

Go to Step 10 Step 6 NRC EXAM SECURE INFORMATION Page 24 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG EVENT 4 - 3B S/G FEEDWATER PUMP HIGH VIBRATION 3-GOP-100, FAST LOAD REDUCTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE

NOTE Enclosure 1 is available on Page

45. BOP: Monitor Load Reduction Adjusts power reduction rate to maintain Tavg/Tref within limits of Attachment 3.

Monitors S/G level control to ensure feed reg valves properly maintain level control in automatic

. Refer to Enclosure 1 for expected alarms. Step 10 BOOTH OPERATOR Respond as SNPO. If asked, idle Charging Pump ready for start.

RCO: Maintain pressurizer level to ensure that automatic pressurizer level control maintains level on program

. If needed , start 2 nd Chg Pp and place 2 nd orifice in service.

Adjust boration rate to maintain Tavg/Tref within limits of Attachment 3. Refer to Enclosure 1 for expected alarms. Step 10 RCO: Monitor Boration Rate Monitor for excessive rod movement by monitoring TR 409D, Rod Position Bank D. Determine if Insertion Limit and Bank D position are converging at a rate that will cause rod insertion limit alarms. Adjust power reduction rate as

needed to control rod insertion Increase boration rate and/or total amount as necessary to limit control rod insertion Step 11 NRC EXAM SECURE INFORMATION Page 25 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG EVENT 4 - 3B S/G FEEDWATER PUMP HIGH VIBRATION 3-GOP-100, FAST LOAD REDUCTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE RCO: Monitor Annunciator B 8/1, ROD BANK LO LIMIT

- CLEAR Monitor B 8/2 ROD BANK A/B/C/D EXTRA LO LIMIT - CLEAR Steps 12-13 US: Have SM refer to t he following procedures: 0-EPIP-20101, DUTIES OF EMERGENCY COORDINATOR 0-ADM-115, NOTIFICATION OF PLANT EVENTS Step 14 RCO: Energize Pressurizer Backup Heaters Ste p 15 NOTE Since the unit is not coming offline

, the crew should leave station service s on the Auxiliary Transformers

. BOP: Verify Turbine Load Less Than 675 MWE Stop one condensate pump Check Desired Final Power Target

- LESS THAN 475 M W e. LEAD EVALUAT OR Once power has been reduced by a minimum of 5%, or at the Lead Evaluators discretion, proceed to Event 6. NRC EXAM SECURE INFORMATION Page 26 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG EVENT 5 - FT-3-494 3C S/G STEAM FLOW TRANSMITTER FAILS AS IS 3-ONOP-049.1, DEVIATION OR FAILURE OF SAFETY RELATED OR REACTOR PROTECTION TI ME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOOTH OPERATOR Th is malfunction was insert ed when the crew started the fast load reduction.

BOP: Recognizes and reports 3C S/G Steam Flow FT-3-4 94 failure. Takes Prompt Actions

- Take manual control of 3 C S/G level control valve FCV 4 9 8. - Return 3 C S/G level to normal.

NOTE The crew may stop the load reduction.

RCO: Addresses Alarm Response for C6/3 , SG C Level Deviation

. CHECK LI-3-4 96 or LI-3-4 98, C STM GEN LEVEL controlling channel for SG Level deviation.

CHECK Feedwater Controllers FIC 498A or FIC-3-4 98B for indications of failure, alarm, or input signal failures.

CHECK Feedwater Controller Inputs IF alarm is due to instrument failure, THEN REFER TO 3-ONOP-049.1, Deviation or Failure of Safety Related or Reactor Protection Channels.

US: Enters and directs actions of 3

-ONOP-049.1, Deviation or Failure of Safety Related or Reactor Protection Channels, for response

. NOTE The crew may use the ARP to select an operable channel and restore automatic level control.

BOP: Verify F T-3-4 94 failure by channel check comparison

. Verify no off

-normal conditions exist on FT-3-4 95. Place 3 C S/G Steam Flow Control Transfer Switch to FT-3-4 95 (Yellow) Place 3C S/G Feed Water Flow Control Transfer Switch to FT-3-496 (Yellow) Ensure 3 C S/G level is returned to AUTO. NRC EXAM SECURE INFORMATION Page 27 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG EVENT 5 - FT-3-494 3C S/G STEAM FLOW TRANSMITTER FAILS AS IS 3-ONOP-049.1, DEVIATION OR FAILURE OF SAFETY RELATED OR REACTOR PROTECTION TI ME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOOTH OPERATOR WCC/I&C: Acknowledge the report. I&C want to be present to trip bi-stables and should be in the control room in about an hour. BOP: Notifies WCC to initiate PWO and I&C for troubleshooting.

BOOTH OPERATOR If asked to reset AMSAC, wait 2

- 3 minutes and then trigger EVENT 5

- RESET AMSAC.

US: Reviews Tech Specs Enters Tech Spec Action 3.3.1 Functional Unit 12 - Action 6 , within 6 hrs trip bistables Enters Tech Spec Action 3.3.2 Functional Unit 1.f and 4.d - Action 15, within 6 hrs trip bistables LEAD EVALUATOR If the crew stopped the Rapid Power reduction , they should resume it once the 3C S/G level control is restored to auto and the US completes a review of Tech Specs

. US: Conducts crew brief.

NRC EXAM SECURE INFORMATION Page 28 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG EVENT 6 - COMMON MAIN FEED HEADER BREAK 3-EOP-E-0, RX TRIP OR SAFETY INJECTION TIME TIME TIME BOOTH OPERATOR When directed by Lead Evaluator or if Reactor trips, verify EVENT 6 - MAIN FEED HEADER BREAK triggers. BOP Reports S/G levels lowing rapidly Recommends a Manual Rx trip and SI US: Directs RCO to manually trip the Reactor and for operators to perform their IOA's.

RCO: Manually trips Reactor.

NOTE Steps 1 - 4 of 3-EOP-E-0 are Immediate Operator Actions (IOAs). The board operators will call out the high level steps of the IOAs as each step is completed from memory.

Once the IOAs are completed, the US will read though Steps 1 - 4 with the crew.

RO/BOP: Perform IOA's.

RCO: Verifies Reactor Trip STE P 1 NRC EXAM SECURE INFORMATION Page 29 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG EVENT - 7 MAIN TURBINE FAILS TO AUTOMATICALLY TRIP 3-EOP-E-0, RX TRIP OR SAFETY INJECTION TIME TIME TIME CT1 Manually Trip the Main Turbine Manually trip the main turbine before any RCS cold leg temperature decreases by more than 100 F. BOOTH OPERATOR When the BOP trips the turbine verify EVENT 6 - STEAM LEAK INSIDE CTMT triggers. When the BOP trips the turbine verify EVENT 7 - DELETE TURBINE TRIP FAILURE triggers.

BOP: Verify Turbine Trip (NO) Manually Trips the turbine.

STEP 2 BOP: Verifies Power To Emergency 4 KV Buses STEP 3 RCO: Checks If SI Is Actuated STEP 4 US: Directs 3-EOP-E-0 response and reviews the IOAs. NRC EXAM SECURE INFORMATION Page 30 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG EVENT - 7 MAIN TURBINE FAILS TO AUTOMATICALLY TRIP 3-EOP-E-0, RX TRIP OR SAFETY INJECTION TIME TIME TIME US: Reviews FOP for 3

-EOP-E-0 with the crew Adverse Containment Conditions RCP Trip Criteria Faulted S/G Isolation Criteria Ruptured S/G Isolation Criteria AFW System Operation Criteria CST Makeup Water Criteria RHR System Operation Criteria(YES, RCO starts timer)

Loss Of Offsite Power Or SI On Other Unit Loss Of Charging Criteria FOLDOUT PAGE NOTE Attachment 3 actions start on page

37. BOP: Continues with ATTACHMENT 3 to complete The Prompt Action Verifications.

STEP 5 BOOTH OPERATOR If dispatched to check AFW pumps

, wait 3 to 5 minutes and then report there to o much steam in the area to check the pumps. RCO: Check AFW Pumps

- AT LEAST TWO RUNNING. (NO) STEP 6 RCO: Verify AFW Valve Alignment

- PROPER EMERGENCY ALIGNMENT STEP 7 RCO: Verify Proper AFW Flow: (NO) NO feed flow available STEP 8 NRC EXAM SECURE INFORMATION Page 31 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG EVENT - 7 MAIN TURBINE FAILS TO AUTOMATICALLY TRIP 3-EOP-E-0, RX TRIP OR SAFETY INJECTION TIME TIME TIME US: Monitor Critical Safety Functions using 3-EOP-F-0, Critical Safety Function Status Trees.

Go to 3-EOP-FR-H.1, Response To Loss Of Secondary Heat Sink, Step 1.

NRC EXAM SECURE INFORMATION Page 32 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG EVENT 8 - PCV-3-455C FAILS TO OPEN. (PZR PORV) 3-EOP-FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOOTH OPERATOR If dispatched to start A or B Standby S/G Feedwater Pump

, wait 2 to 3 minutes and then report DWDS 012, Standby S/G FW Pump Manual Isolation valve

, will not open. US: Enters and directs the actions of 3-EOP-FR-H.1, Response To Loss Of Secondary Heat Sink PROCEDURE CAUTION If total feed flow has been reduced to les s tha n 40 0 gp m du e t o procedural requirement s AN D 40 0 gp m tota l fee d flo w i s available , the n thi s procedure shal l NOT b e performed.

Fee d flo w shal l NOT b e re-establishe d t o an y faulte d S/G i f a non-faulted S/

G i s available.

I f a n Alternat e Lo w Pressur e Feedwate r Sourc e ha s bee n imple mented (e.g., 3-EOP-ECA-0.0, Attachmen t 15), AN D CET s ar e abl e t o be maintaine d stabl e O R decreasi n g , th e n thi s procedur e shal l NOT be performed.

RCO: Check If Secondary Heat Sink Is Required (YES) a. RCS pressure

- GREATER THAN ANY NON-FAULTED S/G PRESSURE b. RCS Hot Leg Temp

- GREATER THAN 350°F STEP 1 NOTE The transient also cause a small steam leak on the 3B Main Steam Line inside containment.

US: Reviews Foldout Page Adverse Containment Conditions (MET) Foldout Page NOTE Step 2 is a continuous action step.

RCO: Check If Bleed And Feed Is Required Stop all RCPs (Go to Step 13)

STEP 2 CAUTION Step 13 through Step 17 must be performed quickly in order to establish RCS heat removal by RCS bleed and feed. US: Reviews Caution with the crew.

NRC EXAM SECURE INFORMATION Page 33 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG EVENT 8 - PCV-3-455C FAILS TO OPEN. (PZR PORV) 3-EOP-FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE Part of CT2 RCO: Actuate SI And Containment Isolation Phase A STEP 1 3 Part of CT2 RCO: Establish maximum Charging flow Check power supply to all Charging pumps - Aligned To Offsite Power Check status of Charging pumps prior to SI actuation in Step 13

- any running (NO) Check CCW flow to RCP(s) Thermal Barrier is lost (NO) Reset SI Start all available Charging pumps Adjust Charging pump speed controllers to establish maximum charging flow Adjust HCV 121, Charging Flow To Regen Heat Exchanger, to maintain proper Seal Injection flow Place RCS Makeup Control Switch in STOP Check Charging Pump Suction

-Aligned To RWST STEP 1 4.a RCO: Check SI pumps status

- a t least two running Verify SI valve amber lights on VPB

- All Bright STEP 14.b&c NRC EXAM SECURE INFORMATION Page 34 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG EVENT 8 - PCV-3-455C FAILS TO OPEN. (PZR PORV) 3-EOP-FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE US: Reviews Caution and notes with crew CAUTION If Low PRZ Pressure SI signal is NOT blocked prior to PRZ pressure decreasing below 1730 psig, Charging Pumps started in previous step will trip NOTE PRZ pressure must be less than 1987 psig for permissive to block the Low PRZ Pressure SI signal.

Step 15 should be reviewed in advance to ensure timely performance.

CT 2 NOTE PORV-455C was failed closed during the simulator setup.

One PORV is insufficient bleed path.

Initiate Bleed

-And-Feed Initiate bleed

-and-feed cooling in accordance with 3-EOP-FR-H.1 within 36 minutes following an automatic or manual Reactor trip due to a loss of Feed Water.

RCO: Verify power to PRZ PORV Block valves - Available Verify PRZ PORV Block valves

- Both Open Check Block Low PRZ Press S.I. status light

- ON (NO) Open one PRZ PORV When Block Low PRZ Press. S.I. status light is ON Momentarily place both Safety Injection Block switches to Block and return to Neutral Verify Low PRZ Press. S.I. Blocked status light

- ON Open remaining PRZ PORV (NO, Failed Close)

STEP 15 BOP: Verify Instrument Air To Containment STEP 1 6 NRC EXAM SECURE INFORMATION Page 35 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG EVENT 8 - PCV-3-455C FAILS TO OPEN. (PZR PORV) 3-EOP-FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOOTH OPERATO R When dispatched to install the fuses for the RCS Vent valves, trigger EVENT 8 LOA - INSTALL FUSES FOR RX HEAD VENTS. RCO/BOP: Both PRZ PORVs Open (NO) Install fuses for RCS Vent valves:

WHEN power is restored to RCS vent valves, THEN open all RCS vents:

STEP 1 7 The scenario is terminated once the RCS Vent Valves are open or at the Lead Evaluator's discretion once all critical task have been evaluated.

• • • END OF SCENARIO ***

NRC EXAM SECURE INFORMATION Page 36 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG EVENT 6 - COMMON MAIN FEED HEADER BREAK 3-EOP-E-0 ATTACHMENT 3

- PROMPT ACTION VERIFICATIONS TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOP: Check Load Centers Associated With Energized 4 KV Buses

- ENERGIZED STEP 1 BOP: Verify Feedwater Isolation:

Place Main Feedwater Pump switches in STOP Feedwater Control Valves

- CLOSED Feedwater Bypass Valves

- CLOSED Feedwater Bypass Isolation Valves

- CLOSED Feedwater Isolation MOVs

- CLOSED Verify Standby Feedwater Pumps

- OFF STEP 2 BOP: Check If Main Steam Lines Should Be Isolated STEP 3 BOP: Verify Containment Isolation Phase A Valve White Lights On VPB

- ALL BRIGHT STEP 4 BOP: Verify Pump Operation:

At least two High

-Head SI Pumps

- RUNNING Only one RHR Pump Available STEP 5 NRC EXAM SECURE INFORMATION Page 37 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG EVENT 6 - COMMON MAIN FEED HEADER BREAK 3-EOP-E-0 ATTACHMENT 3

- PROMPT ACTION VERIFICATIONS TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOP: Verify Proper CCW System Operation:

CCW Heat Exchangers

- THREE IN SERVICE CCW Pumps

- ONLY TWO RUNNING CCW Headers

- TIED TOGETHER MOV-3-626, RCP Thermal Barrier CCW Outlet

- OPEN STEP 6 BOP: Verify Proper ICW System Operation:

Verify ICW Pumps

- AT LEAST TWO RUNNING Verify ICW To TPCW Heat Exchanger

- ISOLATED Check ICW Headers

- TIED TOGETHER STEP 7 BOP: Check Emergency Containment Coolers

- ONLY TWO RUNNING STEP 8 BOP: Verify Unit 3 Containment Purge Exhaust And Supply Fans

- OFF STEP 9 BOP: Verify Containment Spray NOT Required:

-STEP 10 BOP: Verify SI

- RESET STEP 11 NRC EXAM SECURE INFORMATION Page 38 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG EVENT 6 - COMMON MAIN FEED HEADER BREAK 3-EOP-E-0 ATTACHMENT 3

- PROMPT ACTION VERIFICATIONS TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOP: Verify SI Valve Amber Lights On VPB

- ALL BRIGHT STEP 12 BOP: Verify SI Flow:

RCS pressure

- LESS THAN 1625 PSIG[1950 PSIG]

(N O) STEP 13 BOOTH OPERATOR When directed by the crew, trigger LOA

- ALIGN U-4 HHSI TO U

-3 RWST. Wait 5 minute s and report local operator step s complete. BOP: Realign SI System:

Check Procedure Entry Status

- E-0 ENTERED FROM 3

-ONOP-047.1, LOSS OF CHARGING FLOW IN MODES 1 THROUGH 4 (NO) Verify Unit 3 High

-Head SI Pumps

- TWO RUNNING Direct Unit 4 Reactor Operator to align Unit 4 High

-Head SI Pump suction to Unit 3 RWST using Attachment 1.

STEP 14 BOP: Verify Containment Isolation Phase A

- RESET STEP 15 BOP: Reestablish RCP Cooling:

Check RCPs

- AT LEAST ONE RUNNING Open CCW To Normal Containment Cooler Valves:

MOV-3-1417 MOV-3-1418 Reset and start Normal Containment Coolers STEP 16 NRC EXAM SECURE INFORMATION Page 39 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG EVENT 6 - COMMON MAIN FEED HEADER BREAK 3-EOP-E-0 ATTACHMENT 3

- PROMPT ACTION VERIFICATIONS TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOP: Verify Control Room Ventilation Isolation:

STEP 17 BOOTH OPERATOR When requested by crew, trigger LOA

- PLACE PAHMS IN SERVICE

. Wait 5 minute s and report local operator step s complete. BOP: Place Hydrogen Monitors In Service Using 3-NOP-094, CONTAINMENT POST ACCIDENT MONITORING SYSTEM For Each Hydrogen Monitor A/B

- ENSURE FUNCTION SELECTOR switch is in SAMPLE.

- PLACE control switch in ANALYZE. - PRESS the REMOTE SELECTOR button. - PRESS the ALARM RESET button. Dispatch an operator to complete local step of 3

-NOP-094 STEP 18 BOP: Verify All Four EDGs

- RUNNING STEP 19 BOP: Verify Power To Emergency 4 KV Buses:

STEP 20 BOP: Notify Unit Supervisor Of The Following:

Attachment 3 is complete Any safeguards equipment that is NOT In the required condition Status of Containment pressure continuous action STEP 21 NRC EXAM SECURE INFORMATION Page 40 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG Discussion Points are intentionally NOT included in evaluated scenarios.

However, space is available below to document follow

-up questions when further information is required to determine an evaluation outcome. FOLLOW-UP QUESTIONS QUESTION #1 ________________________________________________________________________________________________________________________________________________________________________

________________________________________________________________________________

ANSWER #1 ______________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________

QUESTION #2 ________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________

ANSWER #2

______________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________

NRC EXAM SECURE INFORMATION Page 41 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG SIMULATOR POST

-SCENARIO RESTORATION

______ 1. Restore per Simulator Operator Checklist.

______ 2. Once exams are complete, restore from SEI

-19, Simulator Exam Security.

NRC EXAM SECURE INFORMATION Page 42 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG NRC EXAM SECURE INFORMATION Page 43 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG NRC EXAM SECURE INFORMATION Page 44 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO RMATION SEG NRC EXAM SECURE INFORMATION Page 45 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO R MATION SEG OPERATIONS SHIFT TURNOVER REPORT UNIT 3 RISK: GREEN (ACCEPTABLE)

PROTECTED TRAIN:

B UNIT 4 RISK: GREEN (ACCEPTABLE)

PROTECTED TRAIN: B ONCOMING CREW ASSIGNMENTS Shift Mgr:

Inside SNPO:

Field Supv.:

Outside SNPO:

Admin RCO:

ANPO: Unit 3 Unit 4 Unit Supv.

Unit Supv.:

RCO: RCO: NPO: NPO: PLANT STATUS Unit 3 Unit 4 Mode: 1 Mode: 1 Power: 100% Power: 100% MWe: 84 2 MWe: 842 Gross Leakrate:

0.25 gpm Gross Leakrate:

0.03 gpm RCS Boron Conc:

1145 RCS Boron Conc:

642 Operational Concern s: 3A RHR pump taken OOS 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago for an oil change, expected back by the end of this shift.

3A1 Circ Water pump OOS. Tripped on over current, Electrical Maintenance is investigating.

U3 Anticipated LCO Actions:

None U4 Anticipated LCO Actions:

None Results of Offgoing Focus Area:

NRC EXAM SECURE INFORMATION Page 46 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO R MATION SEG UNIT 3 STATUS REACTOR OPERATOR UNIT RISK: GREEN (ACCEPTABLE) PROTECTED TRAIN:

B Mode: 1 RCS Leakrate Accumulator Ref Levels Power: 100% Gross: 0.25 GPM A 6656 MWe 842 Unidentified 0.0 4 GPM B 6608 Tavg: 580°F Charging Pps:

0.0 0 GPM C 6646 RCS Pressure:

22 3 5 RCS Boron Conc:

1145 Abnormal Annunciators:

Annunciator:

Comp Actions:

Annunciator:

Comp Actions:

Annunciator:

Comp Actions:

Annunciator:

Comp Actions:

Annunciator:

Comp Actions:

Annunciator:

Comp Actions:

Current Tech Spec Action Statements: (Does Not Include "For Tracking Only Items" T.S.A.S / Component:

3A RHR pump, 3.5.2.c

- Action g Reason: Oil Change Entry Date:

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago T.S.A.S / Component: Reason: Entry Date:

T.S.A.S / Component:

Reason: Entry Date:

T.S.A.S / Component:

Reason: Entry Date:

T.S.A.S / Component:

Reason: Entry Date:

NRC EXAM SECURE INFORMATION Page 47 of 48 L-16-1 NRC EXAM SCENARIO 2 NRC EXAM SECURE INFO R MATION SEG REACTOR OPERATOR (CONT'D) UNIT RISK: GREEN (ACCEPTABLE) PROTECTED TRAIN:

B Changes to Risk Significant Equipment:

No recent changes from last shift.

OLRM: GREEN PROTECTED TRAIN: B Upcoming Reactivity Management Activities:

Maintain 99.5% to 100%

Upcoming Major POD Activities:

NONE Upcoming ECOs to Hang and /or Release: Hang - None Release - None Evolutions or Compensatory Actions in Progress:

NONE General Information, Remarks, and Operator Work Around Status:

Weather forecast is overcast skies with scattered pockets of severe rain.

U3 supplying Aux Steam Air In-leakage = 0.0 SCFM NRC EXAM SECURE INFORMATION Page 48 of 48 NRC EXAM SECURE INFORMATION Appendix D Scenario Outline Form ES-D-1 L-16-1 N 3 (Rev-0) Facility: Turkey Point Nuclear (PTN)

- Units 3 and 4 Scenario No.:

3 Op Test No.: 2016-301 Examiners:

Operators:

(SRO) (R C O) (BOP) Initial Conditions:

The plant is at 10

-8 Amps power (BOL). Online risk is green. B train is protected on both units. Turnover: No equipment is OOS Event Malf. No. Event Type*

Event Description 1 N/A R-RCO R-SRO N-BOP Raise Power to 3%

2 TFN1IACF I-BOP I-SRO (TS) N35 Loss Of Compensating Voltage 3 TAB1SCLC V8CG30OF TCB1SCLC C-RCO C-SRO 3C Charging Pump Speed Controller Air Leak 4 TVS1SR2O C-BOP C-SRO PT-3-1607, 3B S/G Steam Dump To Atmosphere Pressure Transmitter, drifts high 5 TFC1SOL I-SRO (TS) PS-3-2007, Containment Pressure Channel Fails High 6 TFN1IBFH TFL2RTAB TFL4AF I-RCO I-SRO N-36, Intermediate Range Nuclear Instrument fails high The Rx fails to automatically trip 7 TFLIA44 TFLIA84 P-RCO 2 Stuck Rods 8 TVSBVL14 M-RCO M-BOP M-SRO 3B S/G Faulted Inside Containment 9 TFFVV87M TFFVV89 P-BOP POV-3-487, Feedwater Bypass Isolation, and FC V-3-489, Feedwater Bypass, Valves Fail To Isolate.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (P)ost Trip L-16-1 NRC EXAM SECURE INFORMATION Page 1 of 3 NRC EXAM SECURE INFORMATION Appendix D Scenario Outline Form ES-D-1 L-16-1 N 3 (Rev-0) SCENARIO

SUMMARY

NOTE Allow 30 minutes for the crew to brief raising power before entering the control room to brief raising power from 10

-8 amps to 3%.

Event 1 After the crew takes the shift the RCO will start raising Rx power by withdrawing Control Rods per 3-GOP-301, Hot Standby to Power Operation. The BOP will manually adjust Feedwater Bypass Flow Control valves , FC V-3-47 9/48 9/49 9, to maintain Steam Generator levels Event 2 After the crew levels power at ~ 3% N35 loses compensating voltage

. The US will enter 3

-ONOP-059.7, Intermediate Range Nuclear Instrumentation and direct the BOP to place N35 in bypass

. Event 3 After the actions of 3

-ONOP-059.7 are complete an air leak will develop on the 3C Charging pump speed controller causing the controller to fail to maximum output. The US will enter 3

-ONOP-041.6, Pressurizer Level Control Malfunction and direct the RCO to start the 3B charging pump and secure the 3C charging pump. Event 4 After the charging pumps are swapped PT 1607, 3B S/G Steam Dump To Atmosphere Pressure Transmitter, will drift high causing CV-3-1607 , 3B Steam Dump To Atmosphere

, to slowly open low ering the 3B S/G pressure. The BOP will place CV 1607 in manual and reduce demand to stabilize 3B S/G pressure. Event 5 After the plant is stabilized, PS 2007, Containment Pressure Channel fails high. The US will enter 3-ONOP-049.1, Deviation or Failure of Safety Related or Reactor Protection Channel, and review Tech Specs for the failed pressure channel.

Event 6 The US complete a review of Tech Specs for PS 2007, Intermediate Range Nuclear Instrumentation Channel N36 fails high and the Rx fails to auto trip. The RCO will manually trip the Reactor. The US will enter and direct the actions 3

-EOP-E-0, Reactor Trip or Safety Injection.

Event 7 When the Rx is tripped the RCO will report 2 control rods failed to fully insert. After the crew completes the Immediate Operator Actions they will transition to 3

-EOP-ES-0.1, Reactor Trip Response. The RCO will start a boration for the 2 stuck rods.

L-16-1 NRC EXAM SECURE INFORMATION Page 2 of 3 NRC EXAM SECURE INFORMATION Appendix D Scenario Outline Form ES-D-1 L-16-1 N 3 (Rev-0) Event 8 After the boration is started a steam leak will develop on the 3B S/G inside containment. The crew will return to 3

-EOP-E-0, verify SI actuates, and isolate Aux Feed Water to the 3B S/G per the Foldout page of 3-EOP-E-0. Event 9 When SI actuates POV 487, 3B S/G Feedwater Bypass Isolation valve, 3B S/G Feedwater Bypass is failed as is, and FCV 489 will leak by. The BOP will manually close POV 487 per Attachment 3 of 3-EOP-E-0. The crew will complete the actions of 3

-EOP-E-0. About the time the crew is ready to transition to 3

-EOP-E-2, Faulted Steam Generator Isolation, a red path will develop on the RCS Integrity Status Tree. The US will transition to 3-EOP-FR-P.1, Response To Imminent Pressurized Thermal Shock Condition.

The scenario is terminated once the crew transitions to 3-EOP-FR-P.1 and isolates AFW flow to the 3B Steam Generator or at the Lead Evaluator's discretion once all critical tasks have been evaluated.

Event CRITICAL TASKS 6 CT1 MANUALLY TRIP THE RX Manually trip the reactor from the control room prior to manually inserting rods.

Safety Significance:

Failure to manually trip the reactor demonstrates the inability of the crew to recognize a failure or an incorrect automatic actuation of an ESF system or component. 8 CT2 STOP AFW FLOW TO FAULTED SG During a MSLB stop AFW flow to the faulted Steam Generator prior to starting the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> soak required per 3

-EOP-FR-P.1, Response To Imminent Pressurized Thermal Shock Condition.

Safety Significance: Failure to isolate a Faulted Steam Generator that can be isolated causes an additional challenge to the Integrity Critical Safety Function. L-16-1 NRC EXAM SECURE INFORMATION Page 3 of 3 L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Site: Turkey Point Units 3 and 4 (PTN) Title: L-16-1 NRC EXAM SCENARIO 3 LMS #: NRC 23 LMS Rev Date: 5/31/16 Rev #: 0.0 SEG Type: Training Evaluation Program: LOCT LOIT Other Duration: 120 minutes Developed by:

Brian Clark 8/4/16 Instructor/Developer Date Reviewed by:

Luis Sagion 8/4/16 Instructor (Instructional Review) Date Validated by :

Sean Bloom 8/5/16 SME (Technical Review) Date Approved by:

Mark Wilson 8/5/16 Training Supervision Date Approved by:

Sean Bloom 8/5/16 Training Program Owner (Line) Date L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 2 of 42 SCENARIO REFERENCES DOC NO. TITLE REV 3-GOP-301 HOT STANDBY TO POWER OPERATION 36B 3-ONOP-059.7 INTERMEDIATE RANGE NUCLEAR INSTRUMENTATION MALFUNCTION 0 3-ONOP-041.6 PRESSURIZER LEVEL CONTROL MALFUNCTION 2 3-ONOP-049.1 DEVIATION OR FAILURE OF SAFETY RELATED OR REACTOR PROTECTION CHANNEL 4 3-EOP-E-0 REACTOR TRIP OR SAFETY INJECTION 12 3-EOP-ES-0.1 REACTOR TRIP RESPONSE 12 3-ONOP-046.1 EMERGENCY BORATION 4 3-EOP-E-2 FAULTED STEAM GENERATOR ISOLATION 4 3-EOP-FR-P.1 RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION 4 PTN TECHNICAL SPECIFICATIONS 300 L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 3 of 42 SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Objective Given this simulator scenario and resources normally found in the Control Room, the operating crew will perform Control Room operations IAW approved plant procedures in order to maintain the integrity of the plant and the health and safety of the public. Enabling Objectives: Given this simulator scenario and resources normally found in the Control Room, operate in accordance with approved plant procedures, Operations Department Instructions, and management expectations: 1. (ALL) Demonstrate personnel SAFETY awareness in interactions with plant staff and outside agencies. 2. (ALL) Demonstrate ALARA awareness in interactions with plant staff and outside agencies. 3. (ALL) Exchange correct information using 3-point communication/Repeat-backs with Control Room personnel and other plant staff. 4. (ALL) Inform plant personnel and System of plant conditions, as needed. 5. (US) Employ timely and concise crew briefs where appropriate. 6. (ALL) Maintain awareness of plant status and control board indication. 7. (ALL) Correctly diagnose plant situations. 8. (ALL) Solve operational problems as they arise. 9. (RCO/BOP) Manipulate plant controls properly and safely. 10. (ALL) Demonstrate self-checking using STAR and peer checks(when required) 11. (US) Demonstrate command and control of the crew. 12. (US) Coordinate the input of crew members and other plant staff. 13. (US) Utilize the input of crew members and other plant staff. 14. (ALL) Demonstrate conservative decision making. 15. (ALL) Demonstrate teamwork. 16. (ALL) Respond to plant events using procedural guidance (OPs/ONOPs/EOPs) as applicable in accordance with rules of usage. 17. (RCO/BOP) Implement any applicable procedural immediate operator actions without use of references. 18. (SRO) Maintain compliance with Tech Specs.

19. (ALL) Identify/enter applicable Tech Spec action statements. 20. (ALL) Respond to annunciators using ARPs (time permitting). 21. (ALL) Maintain written communication, logs, and documentation as needed to permit post-event reconstruction.

Continued on the next page:

L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 4 of 42 SIMULATOR EXERCISE GUIDE REQUIREMENTS While addressing the following events: 1. Raise Power to 3% 2. N35 Loss Of Compensating Voltage 3. 3C Charging Pump Speed Controller Air Leak 4. PT-3-1607, 3B S/G Steam Dump To Atmosphere Pressure Transmitter, Drifts High 5. PS-3-2007, Containment Pressure Channel Fails High

6. N36 Fails High, Rx Fails To Automatically Trip 7. 2 Stuck Rods 8. 3B Faulted S/G Inside Containment

9. POV-3-487, Feedwater Bypass Isolation, and FCV-3-489, Feedwater Bypass, Valves Fail To Isolate. Prerequisites: None Training Resources: PTN Unit 3 Plant Simulator Development

References:

TR-AA-220-1003, Initial NRC and Audit Exam Process TR-AA-230-1003, SAT Development TR-AA-230-1007, Conduct of Simulator Training and Evaluation 0-ADM-232, Time Critical Action Program OP-AA-100-1000, Conduct Of Operations OP-AA-103-1000, Reactivity Management 0-ADM-200, Operations Management Manual 0-ADM-211, Emergency and Off-Normal Operating Procedure Usage WCAP-17711-NP, Pressurized Water Reactor Owners Group Westinghouse Emergency Response Guideline Revision 2-Based Critical Tasks Protected Content: N/A Evaluation Method: Performance Mode Operating Experience: None Risk Significant Operator Actions: None L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 5 of 42 TASKS ASSOCIATED WITH SIMULATOR EXERCISE GUIDE SRO TASK # TASK TITLE 02028033500 AUTHORIZE UNIT TRIP 02046008300 EMERGENCY BORATE THE R.C.S. (MOV-350) 02047008300 INVESTIGATE CHARGING PUMP MALFUNCTIONS 02059008100 AUTHORIZE REMOVAL OF AN INTERMEDIATE RANGE NIS CHANNEL FROM SERVICE 02059024300 RESPOND TO LOSS OF INTERMEDIATE RANGE INSTRUMENTATION 02059027300 EVALUATE AND DIRECT TECH SPECS REQUIRED ACTIONS DUE TO NIS OUT OF SPEC / SERVICE CONDITIONS 02200002500 EVALUATE CRITICAL SAFETY FUNCTION (CSF) STATUS TREE OUTPUT 02200007500 RESPOND TO A STEAM LINE FAULT 02200022500 DIAGNOSE CAUSE OF SAFEGUARDS ACTUATION 02200023100 COORDINATE UNIT STARTUP 02200050500 RESPOND TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION RO TASK TASK TITLE 01200023100 COORDINATE UNIT STARTUP 01059024300 RESPOND TO LOSS OF INTERMEDIATE RANGE INSTRUMENTATION 01046008300 EMERGENCY BORATE THE R.C.S. (MOV-350) 01200007500 RESPOND TO A STEAM LINE FAULT 01200022500 DIAGNOSE CAUSE OF SAFEGUARDS ACTUATION 01200050500 RESPOND TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION 01047013100 START A CHARGING PUMP 01200001500 RESPOND TO UNIT TRIP 01047008300 INVESTIGATE CHARGING PUMP MALFUNCTIONS

L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 6 of 42 UPDATE LOG:

NOTES: Place this form with the working copies of lesson plans and/or other materials to document changes made between formal revisions. For fleet-wide training materials, keep electronic file of this form in same folder as approved materials. Refer to TR-AA-230-1003 SAT Development for specific directions regarding how and when this form shall be used. Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16.

1. DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE REVIEWER DATE 0-0 Initial Revision New for L-16-1 NRC Exam 2108338 Note 5 Note 5 Note 5 Note 5

1. Individual updating lesson plan or training material shall complete the appropriate blocks on the Update Log. 2. Describe the change to the lesson plan or training materials. 3. State the reason for the change (e.g., reference has changed, typographical error, etc.)

4. Preparer enters name/date on the Update Log and obtains Training Supervisor approval. 5. Initial dates and site approval on cover page.

L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 7 of 42 SCENARIO

SUMMARY

INITIAL CONDITIONS The plant is at 10

-8 Amps power (BOL). Online risk is green. B train is protected on both units. The crew will raise power to 3%. EQUIPMENT OOS: None NOTE Allow 30 minutes for the crew to brief raising power before entering the control room to brief raising power from 10

-8 amps to 3%.

Event 1 After the crew takes the shift, the RCO will start raising Rx power by withdrawing Control Rods per 3-GOP-301, Hot Standby to Power Operation. The BOP will manually adjust Feedwater Bypass Flow Control valves, FCV-3-479/489/499, to maintain Steam Generator levels.

Event 2 After the crew stabilizes power at ~ 3%, N35 loses compensating voltage. The US will enter 3-ONOP-059.7, Intermediate Range Nuclear Instrumentation, and direct the BOP to place N35 in bypass.

Event 3 After the actions of 3-ONOP-059.7 are complete, an air leak will develop on the 3C Charging pump speed controller, causing the controller to fail to maximum output. The US will enter 3-ONOP-041.6, Pressurizer Level Control Malfunction, and direct the RCO to start the 3B charging pump and secure the 3C charging pump.

Event 4 After the charging pumps are swapped, PT-3-1607, 3B S/G Steam Dump To Atmosphere Pressure Transmitter, will drift high causing CV-3-1607, 3B Steam Dump To Atmosphere, to slowly open, lowering the 3B S/G pressure. The BOP will place CV-3-1607 in manual and reduce demand to stabilize 3B S/G pressure.

Event 5 After the plant is stabilized, PS-3-2007, Containment Pressure Channel, fails high. The US will enter 3-ONOP-049.1, Deviation or Failure of Safety Related or Reactor Protection Channel, and review Tech Specs for the failed pressure channel.

Event 6 After the US completes the review of Tech Specs for PS-3-2007, Intermediate Range Nuclear Instrumentation Channel, N36, fails high and the Rx fails to auto trip. The RCO will manually trip the Reactor. The US will enter and direct the actions 3-EOP-E-0, Reactor Trip or Safety Injection.

L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 8 of 42 SCENARIO

SUMMARY

Event 7 When the Rx is tripped, the RCO will report 2 control rods failed to fully insert. After the crew completes the Immediate Operator Actions they will transition to 3-EOP-ES-0.1, Reactor Trip Response. The RCO will start a boration for the 2 stuck rods using 3-ONOP-046.1, Emergency Boration.

Event 8 After the boration is started, a steam leak will develop on the 3B S/G inside containment. The crew will return to 3-EOP-E-0, verify SI actuates, and isolate Aux Feed Water to the 3B S/G per the Foldout page of 3-EOP-E-0.

Event 9 When SI actuates, POV-3-487, 3B S/G Feedwater Bypass Isolation valve, is failed as is, and FCV-3-489, 3B FW Bypass, will leak by. The BOP will manually close POV-3-487, 3B FW Bypass Isolation, per Attachment 3 of 3-EOP-E-0. The crew will complete the actions of 3-EOP-E-0. About the time the crew is ready to transition to 3-EOP-E-2, Faulted Steam Generator Isolation, a red path will develop on the RCS Integrity Status Tree. The US will transition to 3-EOP-FR-P.1, Response To Imminent Pressurized Thermal Shock Condition.

The scenario is terminated once the crew transitions to 3-EOP-FR-P.1 and isolates AFW flow to the 3B Steam Generator or at the Lead Evaluator's discretion once all critical tasks have been evaluated.

L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 9 of 42 CREW CRITICAL TASKS Event Description 6 CT1 MANUALLY TRIP THE RX Manually trip the reactor from the control room prior to manually inserting rods.

Safety Significance: Failure to manually trip the reactor demonstrates the inability of the crew to recognize a failure or an incorrect automatic actuation of an ESF system or component.

8 CT2 STOP AFW FLOW TO FAULTED SG During a MSLB stop AFW flow to the faulted Steam Generator prior to starting the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> soak required per 3-EOP-FR-P.1, Response To Imminent Pressurized Thermal Shock Condition.

Safety Significance: Failure to isolate a Faulted Steam Generator that can be isolated causes an additional challenge to the Integrity Critical Safety Function.

L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 10 of 42 SEQUENCE OF EVENTS Event # Description 1. Raise Power to 3% 2. N35 Loss Of Compensating Voltage 3. 3C Charging Pump Speed Controller Air Leak 4. PT-3-1607, 3B S/G Steam Dump To Atmosphere Pressure Transmitter, Drifts High 5. PS-3-2007, Containment Pressure Channel Fails High 6. N36 Fails High, Rx Fails To Automatically Trip 7. 2 Stuck Rods 8. 3B Faulted S/G Inside Containment 9. POV-3-487, Feedwater Bypass Isolation, and FCV-3-489, Feedwater Bypass, Valves Fail To Isolate.

L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 11 of 42 SIMULATOR SET UP INSTRUCTIONS Check Action ____ Restore IC-181 BOL 10

-8 amps ____ Open & execute lesson file L-16-1 N3.lsn ____ Verify the following step is triggered SETUP - DEFEAT AUTO RX TRIP ____ Ensure Rod Group Step Counters have completed stepping out. ____ Allow the plant to stabilize. ____ Acknowledge any alarms and freeze Simulator. ____ Ensure B train is protected train on VPB. ____ Perform the SIMULATOR OPERATOR CHECKLIST or equivalent. ____ Place TURNOVER SHEETS on RO's desk or give to the Lead Evaluator. ____ Ensure a copy of the maneuvering guideline is available ____ Ensure a marked copy of 3-GOP-301 is available for power increase. ____ Ensure a copy of 0-ADM-200 is available for briefs. ____ Ensure a copy of ODI-44 is available for briefs.

L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 12 of 42 BRIEFINGS Shift turnover information is attached to the back of this guide.

Ensure all applicants are prior briefed on Appendix E of NUREG 1021, Policies and Guidelines For Taking NRC Examinations.

Conduct a Crew Pre-brief to cover turnover information. Shift turnover information is attached to the back of this guide US: RCO: BOP:

SCENARIO NOTE 0-ADM-211 Prudent Operator Actions - If redundant stand-by equipment is available and ready, the operator is permitted to start the redundant equipment for failed or failing operating equipment. Immediate follow up of applicable ARPs and ONOPs (AOPs) shall occur as required.

L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 13 of 42 Critical Task s are highlighted in pink. Simulator Operator Actions are highlighted in blue. Operator Verifiable Actions are Highlighted in green EVENT 1 - RAISE POWER TO 3% 3-GOP-301, HOT STANDBY TO POWER OPERATION TIME EVALUATOR ACTIVITIES & NOTEs EXPECTED STUDENT RESPONSE NOTE The Reactivity briefing will occur prior to assuming the watch in the Simulator Briefing Room. Allow up to 30 minutes for the briefing before the crew enters the control room. CREW: Participates in reactivity briefing for raising Rx power to 3% / POAH.

NOTE Maneuvering Guidelines are attached to the back of this Scenario Guide. US: Directs the evolution per 3-GOP-301, Hot Standby to Power Operation, in accordance Step 5.24.

RCO: Pull Rods to establish a startup rate not to exceed 1 dpm while below the POAH.

BOP: Adjusts Steam Dumps to Atmosphere and Feedwater flow to maintain S/G Level on program when POAH is reached.

RCO: Once above the POAH withdrawals rods continues to raise power with a startup rate not to exceed .5 dpm.

LEAD EVALUATOR Once the crew levels power above the POAH or at the lead evaluator's discretion, direct the Booth Operator to trigger the next event.

L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 14 of 42 EVENT 2 - N35 LOSS OF COMPENSATING VOLTAGE 3-ONOP-059.7, INTERMEDIATE RANGE NUCLEAR INSTRUMENTATION TIME EVALUATOR ACTIVITIES & NOTEs EXPECTED STUDENT RESPONSE BOOTH OPERATOR When directed by Lead Evaluator, trigger EVENT 2 - N-35 FAILS RCO: Recognizes / reports N-35 IR channel malfunction.

BOP: Review ARP B5/3 CHECK LOSS OF COMP VOLT light on N-35 IR channel drawer ON. Refer to 3-ONOP-059.7 US: Enters 3-ONOP-059.7, Intermediate Range Nuclear Instrumentation Malfunction.

RCO: Check If Reactor Trip Required a. Check Rx Power <P-10 b. Check Hi Flux Status Light for N35 OR N36 - ON c. Check Rx Trip Breakers - OPEN Check Annunciator B 5/3 OFF. (NO) Go to Step 4 Steps 1-2 NOTE Annunciator B8/4 expected when placing level trip switch to bypass. BOP: Places N35 level trip switch in BYPASS Verify N36 Operable RCO: Verify N-45 recorder selected to N36 Step 4 L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 15 of 42 EVENT 2 - N35 LOSS OF COMPENSATING VOLTAGE 3-ONOP-059.7, INTERMEDIATE RANGE NUCLEAR INSTRUMENTATION TIME EVALUATOR ACTIVITIES & NOTEs EXPECTED STUDENT RESPONSE RCO: Check Reactor In Mode 1 Above P-10 (NO) Check Reactor In Mode 1 Below P-10 (NO) Check Reactor In Mode 2 Above P-6 Maintain power below 5 percent until both IR channels are Operable Go to Step 10 Steps 5 - 7 BOOTH OPERATOR As WCC / I&C, inform US that ARs & WRs have been written and I&C has been notified to investigate. US: Initiate a PWO and notify I&C to check affected IR channel.

US: Reviews Tech Spec applicability. TS 3.3.1 Functional Unit 3 Action 3, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 10% TS 3.3.1 Functional Unit 17a Action 7, within 1 hr determine that the interlock is in its required state LEAD EVALUATOR Once the US completes the review of Tech Specs, or at your discretion, continue to the next event.

L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 16 of 42 EVENT 3 - 3C CHARGING PUMP SPEED CONTROLLER AIR LEAK 3-ONOP-041.6, PRESSURIZER LEVEL CONTROL MALFUNCTION TIME EVALUATOR ACTIVITIES & NOTEs EXPECTED STUDENT RESPONSE BOOTH OPERATOR When directed by Lead Evaluator, trigger EVENT 3 - 3C CHARGING PUMP SPEED CONTROLLER AIR LEAK RCO: Report Max demand on 3C Charging pump speed controller.

NOTE The US may use the guidance in the ARP to swap charging pumps prior to entering enter 3-ONOP-041.6. BOP: Review ARP G1/2, CHARGING PUMP HI SPEED Check individual charging pump controller and the master charging pump controller. IF a failure of the individual charging pump controller has occurred in automatic, THEN PLACE the individual controller in manual AND MAINTAIN pressurizer level on program. GO TO 3-ONOP-041.6, Pressurizer Level Control Malfunction IF unable to control running charging pump, THEN START a standby charging pump AND SHUTDOWN the affected pump.

US: Enter 3-ONOP-041.6, Pressurizer Level Control Malfunction L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 17 of 42 EVENT 3 - 3C CHARGING PUMP SPEED CONTROLLER AIR LEAK 3-ONOP-041.6, PRESSURIZER LEVEL CONTROL MALFUNCTION TIME EVALUATOR ACTIVITIES & NOTEs EXPECTED STUDENT RESPONSE PROCEDURE NOTE If Pressurizer Level Malfunction is a result of a failure of the 3-459CX or 3-460CX relays (as indicated by a loss of letdown flow with a loss of Pressurizer Heaters with no concurrent failure of Level Transmitters 3-459A, 3-460, 3-461), use 3-ONOP-003.6 Attachment 4, for 3-460CX failure, 3-ONOP-003.9 Attachment 4, for 3-459CX failure as guidance for establishing Letdown flow and Pressurizer Heaters. If the button on relays 3-459CX or 3-460CX are used to restore Letdown flow and Pressurizer Heaters, comply with Tech Spec Action Statement 3.4.3 Action b. If the manual control of Heaters from the Electrical Penetration Room is used, comply with Tech Spec Action Statement 3.4.3 Action a.

BOOTH OPERATOR If dispatched to check the 3C Charging Pump, wait 2 to 3 minutes and then report a large air leak on the speed controller. If asked, the 3B Charging pump is ready for a start and once it's started, report back a SAT start. RCO: Check pressurizer level indicators LI-3-459A, LI-3-460, and LI-3-461 (NO) Place Master Charging Pump Controller, LC-3-459G in Manual Place individual Charging Pump Controllers in Manual Start or stop additional pumps as necessary Steps 5.1 - 5.3 RCO: When desired, place running charge controllers and master controller in auto.

BOOTH OPERATOR When asked, acknowledge request for addition support. . US: Initiate a PWO LEAD EVALUATOR Continue with next event after the RCO swaps charging pumps.

L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 18 of 42 EVENT 4 - 3B S/G STEAM DUMP TO ATMOSPHERE PRESSURE TRANSMITTER DRIFTS HIGH 0-ADM-211, PRUDENT OPERATOR ACTIONS TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOOTH OPERATOR When directed by Lead Evaluator, trigger EVENT 4 - PT-3-1607, 3B S/G STEAM DUMP TO ATMOSPHERE PRESSURE TRANSMITTER, DRIFTS HIGH CREW: Hears steam flow.

BOP: Reports CV-3-1607, 3B Steam Dump to Atmosphere, is open.

US: Directs BOP to close CV-3-1607.

BOOTH OPERATOR As WCC, inform US that WCC/AOM has been notified, ARs & WRs were written, and proper work groups have been notified. BOP: Places CV-3-1607 in manual and reduces demand to stabilize 3B S/G pressure.

LEAD EVALUATOR After the plant is stabilized, proceed with the next event.

L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 19 of 42 EVENT 5 - PS-3-2007, CONTAINMENT PRESSURE CHANNEL FAILS HIGH 3-ONOP-049.1, DEVIATION OR FAILURE OF SAFETY RELATED OR REACTOR PROTECTION CHANNEL TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOOTH OPERATOR When directed by Lead Evaluator, trigger EVENT 5 - CTMT PRESSURE CHANNEL FAILS HIGH BOP: Review ARP, H5/1, CNTMT HI-HI/HI PRESS CHECK Containment pressure indication CHECK Status lamps on VPB(3C05) Refer to 3-ONOP-049.1 US: Enters 3-ONOP-049.1, Deviation or Failure of Safety Related or Reactor Protection Channels BOP: Verify instrument loop failure by comparison to adjacent loops and known plant parameters and conditions. Step 5.1 US: Refer to Technical Specifications Tech Spec 3.3.2, Functional units 1.c, 2.b, 3.b.3, and 4.c Action 15 - Place the inoperable channel in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Step 5.6 US:

Identifies fuses for failed channel using Attachment 7. (FU 25 & 26)

BOOTH OPERATOR WCC/I&C: Acknowledge the report. State that I&C wants to be present before removing the fuses and should be in the control room in about an hour. BOP: Notifies WCC to initiate PWO and I&C for troubleshooting.

L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 20 of 42 EVENT 5 - PS-3-2007, CONTAINMENT PRESSURE CHANNEL FAILS HIGH 3-ONOP-049.1, DEVIATION OR FAILURE OF SAFETY RELATED OR REACTOR PROTECTION CHANNEL TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE LEAD EVALUATOR After the US completes the Tech Spec review, proceed with the next event.

L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 21 of 42 EVENT 6 - N36 FAILS HIGH 3-EOP-E-0, REACTOR TRIP OR SAFETY INJECTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOOTH OPERATOR When directed by Lead Evaluator, trigger EVENT 6 - N36 FAILURE and verify EVENT 7 - 2 STUCK RODS triggers.

NOTE Record the time Annunciator C6/5 INTERM RANGE HI FLUX TRIP Alarms RCO: Reports conditions met for manual reactor trip. N-36 has failed high Associated bistables are lit Reports manual reactor trip is required US: Directs a reactor trip CT1 SAT _______ Manually Trip The Rx Manually trip the reactor from the control room prior to manually inserting rods.

RCO: Trips the reactor NOTE Steps 1 - 4 of 3-EOP-E-0 are Immediate Operator Actions (IOAs). The board operators will call out the high level steps of the IOAs as each step is completed from memory. Once the IOAs are complete the US read through steps 1 - 4 with the crew.

RCO: Verifies Reactor Trip Determines 2 rods stuck out Reports reactor trip (NO) RNO - Rx Power is <5% and lowering. Step 1 BOP: Verifies Turbine trip Step 2 BOP: Verifies Power To Emergency 4 KV Buses Step 3 RCO: Checks SI has NOT Actuated and is NOT required Step 4 L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 22 of 42 EVENT 6 - N36 FAILS HIGH 3-EOP-E-0, REACTOR TRIP OR SAFETY INJECTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE US: Directs transition to 3-EOP-ES-0.1, Reactor Trip Response Step 4 L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 23 of 42 EVENT 7 - 2 STUCK RODS 3-EOP-ES-0.1, REACTOR TRIP RESPONSE TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE US: Directs 3-EOP-ES-0.1 response CREW: Reviews FOP for 3-EOP-ES-0.1 SI Actuation Criteria Pressurizer Level Criteria S/G Level Criteria Using AFW CST Makeup Water Criteria Control Room Ventilation Manual Isolation Criteria Foldout Page PROCEDURE CAUTION If SI Actuation occurs during this procedure, 3-EOP-E-0, REACTOR TRIP OR SAFETY INJECTION, is required to be performed.

BOP: Checks RCS temperature control Checks AFW pumps - NONE running Checks RCPs - all running Checks RCS Average Temperatures using DCS - Stable between 545°F and 547°F Step 1 L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 24 of 42 EVENT 7 - 2 STUCK RODS 3-EOP-ES-0.1, REACTOR TRIP RESPONSE TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOP: Checks Feedwater Status Checks RCS Average Temperatures - LESS THAN 554°F Verifies Main Feedwater Flow Control valves - CLOSED AND IN MANUAL Manually closes Feedwater Isolation valves: MOV-3-1407 MOV-3-1408 MOV-3-1409 Checks S/G Narrow Range Levels -GREATER THAN 7% IN AT LEAST ONE S/G Stops all but one Main Feedwater Pump Step 2 RCO: Verifies ALL control rods - fully inserted (NO) (L-7 & L-9 are stuck out) Emergency Borate for stuck control rods using 3-ONOP-046.1, EMERGENCY BORATION, while continuing with Step 4. Step 3 L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 25 of 42 EVENT 7 - 2 STUCK RODS 3-EOP-ES-0.1, REACTOR TRIP RESPONSE TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE NOTE In accordance with step 4 of 3-ONOP-046.1, Emergency borate for 50 minutes for each rod not fully inserted using BAST water at 60 GPM through MOV-3-350.

(2 rods x 50 min /rod = 100 min)

LEAD EVALUATOR When emergency boration is established, continue with next event. RCO: Commences emergency boration using 3-ONOP-046.1 Verifies charging pumps - AT LEAST ONE RUNNING Turns RCS Makeup Control Switch to STOP Manually starts Boric Acid Pump 3A or 3B Opens Emergency Boration Valve, MOV-3-350 Opens Charging Flow to Regen Heat Exchanger, HCV-3-121 Verify Loop A Charging Isolation,CV-3-310A - OPEN Establishes emergency boration flow FI-3-110 > 60 GPM FI-3-122A > 45 GPM Informs US emergency boration is established NOTE The US and BOP should continue with 3-EOP-ES-0.1. BOP: Checks 4KV Power Status To Both Unit 3 And Unit 4 Checks Pressurizer Level Control Checks PRZ Pressure Control Checks S/G Levels Verifies All 4kV buses energized by OFFSITE POWER Establish S/G Pressure Control

L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 26 of 42 EVENT 8 - 3B S/G FAULTED INSIDE CONTAINMENT 3-EOP-E-0, REACTOR TRIP OR SAFETY INJECTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOOTH OPERATOR When directed by Lead Evaluator, trigger EVENT 8 - 3B S/G STEAM LEAK INSIDE CONTAINMENT When event 8 is triggered, verify EVENT 9 - 3B SG FAILS TO ISOLATE triggers RCO: Reports Tavg lowering Reports containment press rising BOP:

Reports 3B SG pressure lowering uncontrollably NOTE The Crew will transition to 3-EOP-FR-P.1 when any RCS Cold Leg is < 280°F (Orange Condition for P.1) The steps for 3-EOP-FR-P.1 start on page 30. US: Transitions to 3-EOP-E-0, Step 1, when Foldout page SI initiation criteria are met.

RCO: Verifies Reactor Trip Step 1 BOP: Verifies Turbine Trip Step 2 BOP: Verifies Power To Emergency 4 KV Buses Step 3 RCO: Checks If SI Is Actuated Step 4 US: Directs 3-EOP-E-0 response and reviews the IOAs.

L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 27 of 42 EVENT 8 - 3B S/G FAULTED INSIDE CONTAINMENT 3-EOP-E-0, REACTOR TRIP OR SAFETY INJECTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE

CT2 SAT _______ NOTE CT2 may be completed and at any time before the completion of 3-EOP-FR-P.1 Step 2. STOP AFW FLOW TO FAULTED SG During a MSLB stop AFW flow to the faulted Steam Generator prior to starting the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> soak required per 3-EOP-FR-P.1, Response To Imminent Pressurized Thermal Shock Condition.

CREW:

Reviews FOP for 3-EOP-E-0 Adverse Cntmt RCP Trip Criteria (YES) Trips RCPs when RCP trip criteria met.

Faulted S/G Isolation - (YES) Place in manual and close or reduce the controller setpoint to 0 Train 1 AFW Flow to 3B S/G CV-3-2817 Train 2 AFW Flow to 3B S/G CV-3-2832 RUPTURED S/G ISOLATION CRITERIA AFW Sys Operation Criteria - (YES) CST Makeup Water Criteria RHR System Operation Criteria - (YES Set timer) Loss of Offsite Power or SI on the Other Unit Loss of Charging Criteria Foldout Page NOTE Attachment 3 actions start on page 32.

BOP: Continues with ATTACHMENT 3 to complete the Prompt Action Verifications. Step 5 RCO: Check AFW Pumps - AT LEAST TWO RUNNING - (YES) Step 6 RCO: Verify AFW Valve Alignment - PROPER EMERGENCY ALIGNMENT - (YES) Step 7 L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 28 of 42 EVENT 8 - 3B S/G FAULTED INSIDE CONTAINMENT 3-EOP-E-0, REACTOR TRIP OR SAFETY INJECTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE RCO: Verify Proper AFW Flow: Check Narrow Range Level in at least one S/G - GREATER THAN 7%[27%] Maintain feed flow to S/G until Narrow Range Levels between 21%[27%] and 50% Step 8 RCO: Check RCP Seal Cooling

d. SI - RESET Reset SI f. Start one Charging Pump at minimum speed for Seal Injection Step 9.d & f RCO: Check RCS Temperatures Check RCPs - ANY RUNNING - (NO) Check RCS Cold Leg Temperatures -STABLE BETWEEN 545°F AND 547°F OR TRENDING DOWN TO 547°F - (NO) Stops dumping steam Step 10 RCO: Check PRZ PORVs, Spray Valves And Excess Letdown Isolated - Yes Step 11 RCO: Check If RCPs Should Be Stopped - (Not running) Step 12 RCO: Check If S/Gs Are Faulted - YES Continue to monitor CSFs Step 13 L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 29 of 42 EVENT 8 - 3B S/G FAULTED INSIDE CONTAINMENT 3-EOP-E-0, REACTOR TRIP OR SAFETY INJECTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE US: When any RCS Cold Leg is < 280°F (Orange Condition for P.1) transition to 3-EOP-FR-P.1, Response To Imminent Pressurized Thermal Shock Condition Step 13 L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 30 of 42 EVENT 8 - 3B S/G FAULTED INSIDE CONTAINMENT 3-EOP-FR-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE US: Enter 3-EOP-FR-P.1, Response To Imminent Pressurized Thermal Shock.

US: Reviews the Foldout Page ADVERSE CONTAINMENT CONDITIONS (YES) Foldout Page RCO: Check RCS Pressure - GREATER THAN 275 PSIG [575 PSIG] (NO) Step 1 BOP: RCS Cold Leg Temperatures - DECREASING

Try to stop RCS cooldown: Verify S/G Steam Dump To Atmosphere Valves - CLOSED Verify steam Dump To Condenser Valves - CLOSED IF RHR System in service THEN stop any cool down from RHR System Control feed flow to non-faulted S/G(s) to stop RCS cooldown. Steps 2a - 2b

L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 31 of 42 EVENT 8 - 3B S/G FAULTED INSIDE CONTAINMENT 3-EOP-FR-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE

CT2 SAT _______

BOOTH OPERATOR When dispatched to isolate AFW steam supply from the 3B S/G using Attachment 2, wait 1 to 2 minutes and then trigger LOA - CLOSE AND DE-ENERGIZE MOV-3-1404. Report when the step is complete.

NOTE CT2 may have been completed per the FOLDOUT Page of 3-EOP-E-0 STOP AFW FLOW TO FAULTED SG During a MSLB stop AFW flow to the faulted Steam Generator prior to starting the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> soak required per 3-EOP-FR-P.1, Response To Imminent Pressurized Thermal Shock Condition.

RCO/BOP:

Minimize cooldown from faulted S/G(s) Check S/Gs - ANY FAULTED Verify Main Steamline Isolation AND Bypass Valves closed for each Faulted S/G Close 3B MSIV Dispatch operator to isolate AFW steam supply from 3B S/G using Check all S/Gs - ANY S/G NOT FAULTED Control feed flow at 50 gpm to any Faulted S/G(s) needed for RCS temperature control Isolate Feedwater to all Faulted S/G(s) NOT needed for RCS temperature control Place in manual and close or reduce the controller setpoint to 0 Train 1 AFW Flow to 3B S/G CV-3-2817 Train 2 AFW Flow to 3B S/G CV-3-2832 Step 2.c The scenario is terminated once the crew transitions to 3-EOP-FR-P.1 and isolates AFW flow to the 3B Steam Generator or at the Lead Evaluator's discretion once all critical tasks have been evaluated.

L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 32 of 42 EVENT 9 - 3B S/G FAULTED INSIDE CONTAINMENT 3-EOP-E-0 ATTACHMENT 3 - PROMPT ACTION VERIFICATIONS TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOP: Check Load Centers - Energized Step 1 BOP: Verify Feedwater Isolation: Place Main Feedwater Pump switches in STOP Feedwater Control valves - CLOSED Feedwater Bypass valves - CLOSED Feedwater Bypass Isolation valves -NOT CLOSED Closes POV-3-487 Feedwater Isolation MOVs - CLOSED Verify Standby Feedwater Pumps -OFF Step 2 BOP:

Check If Main Steam Lines Should Be Isolated (MSIVs Closed) Step 3 BOP: Verify Containment Isolation Phase A Valve White Lights On VPB - ALL BRIGHT Step 4 BOP: Verify Pump Operation: At least two High-Head SI Pumps -RUNNING Both RHR Pumps - RUNNING Step 5 L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 33 of 42 EVENT 9 - 3B S/G FAULTED INSIDE CONTAINMENT 3-EOP-E-0 ATTACHMENT 3 - PROMPT ACTION VERIFICATIONS TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOP: Verify Proper CCW System Operation: CCW Heat Exchangers - THREE IN SERVICE CCW Pumps - ONLY TWO RUNNING CCW Headers - TIED TOGETHER MOV-3-626, RCP Thermal Barrier CCW Outlet - OPEN Step 3 BOP: Verify Containment Isolation Phase A Valve White Lights On VPB - ALL BRIGHT Step 4 BOP: Verify Pump Operation: At least two High-Head SI Pumps - RUNNING Both RHR Pumps - RUNNING Step 5 BOP: Verify Proper CCW System Operation: CCW Heat Exchangers - THREE IN SERVICE CCW Pumps - ONLY TWO RUNNING CCW Headers - TIED TOGETHER MOV-3-626, RCP Thermal Barrier CCW Outlet - OPEN Step 6 L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 34 of 42 EVENT 9 - 3B S/G FAULTED INSIDE CONTAINMENT 3-EOP-E-0 ATTACHMENT 3 - PROMPT ACTION VERIFICATIONS TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOP: Verify Proper ICW System Operation: Verify ICW Pumps - AT LEAST TWO RUNNING Verify ICW To TPCW Heat Exchanger - ISOLATED Check ICW Headers - TIED TOGETHER Step 7 BOP: Check Emergency Containment Coolers - ONLY TWO RUNNING Step 8 BOP: Verify Unit 3 Containment Purge Exhaust And Supply Fans - OFF Step 9 BOP: Verify Containment Spray Running Step 10 BOP: Verify SI - RESET Step 11 BOP: Verify SI Valve Amber Lights On VPB - ALL BRIGHT Step 12 BOP: Verify SI Flow: RCS pressure - LESS THAN 1625 PSIG[1950 PSIG] (NO) Go to Step 14. Step 13 L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 35 of 42 EVENT 9 - 3B S/G FAULTED INSIDE CONTAINMENT 3-EOP-E-0 ATTACHMENT 3 - PROMPT ACTION VERIFICATIONS TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOOTH OPERATOR When requested, trigger LOA - ALIGN U-4 HHSIs TO U3 RWST BOP: Realign SI System: Check Procedure Entry Status - E-0 ENTERED FROM 3-ONOP-047.1, LOSS OF CHARGING FLOW IN MODES 1 THROUGH 4 (NO) Verify Unit 3 High-Head SI Pumps - TWO RUNNING Step 14 BOP: Reset Phase A.

Step 15 BOP: Reestablish RCP Cooling: Check RCPs - AT LEAST ONE RUNNING (NO Go To Step 17)

Step 16 BOP: Verify Control Room Ventilation Isolation: Step 17 BOOTH OPERATOR When requested, trigger LOA - ALIGN PAHMS FOR SERVICE BOP: Place Hydrogen Monitors In Service Using 3-NOP-094, CONTAINMENT POST ACCIDENT MONITORING SYSTEM Step 18 BOP: Verify All Four EDGs - RUNNING Step 19 BOP: Verify Power To Emergency 4 KV Buses: Step 20 L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 36 of 42 EVENT 9 - 3B S/G FAULTED INSIDE CONTAINMENT 3-EOP-E-0 ATTACHMENT 3 - PROMPT ACTION VERIFICATIONS TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOP: Notify Unit Supervisor Of The Following: Attachment 3 is complete Any safeguards equipment that is NOT is in the required condition Status of Containment pressure continuous action Step 21 L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 37 of 42 Discussion Points are intentionally NOT included in evaluated scenarios. However, space is available below to document follow-up questions when further information is required to determine an evaluation outcome. FOLLOW-UP QUESTIONS QUESTION #1 ________________________________________________________________________________________________________________________________________________________________________

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L-16-1 NRC EXAM SCENARIO 3 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 38 of 42 SIMULATOR POST-SCENARIO RESTORATION

______ 1. Restore per Simulator Operator Checklist.

______ 2. Once exams are complete, restore from SEI-19, Simulator Exam Security.

L-16-1 NRC EXAM SCENARIO 3 L-16-1 NRC EXAM SECURE INFORMATION SEG DRAFT L-16-1 NRC EXAM SECURE INFORMATION Page 39 of 42 OPERATIONS SHIFT TURNOVER REPORT UNIT 3 RISK: GREEN (ACCEPTABLE) PROTECTED TRAIN: B UNIT 4 RISK: GREEN (ACCEPTABLE) PROTECTED TRAIN: B ONCOMING CREW ASSIGNMENTS Shift Mgr:

Inside SNPO:

Field Supv.:

Outside SNPO:

Admin RCO:

ANPO: Unit 3 Unit 4 Unit Supv.:

Unit Supv.:

RCO: RCO: NPO: NPO: PLANT STATUS Unit 3 Unit 4 Mode: 2 Mode: 1 Power: 10-8 amps Power: 100% MWe: 0 MWe: 842 Gross Leakrate: 0.23 gpm Gross Leakrate: 0.03 gpm RCS Boron Conc: 1670 ppm RCS Boron Conc: 642 ppm Operational Concerns:

Plant Start Up last shift following a 10 day outage to repair Feed Water Line Leak. 2 ROs and 2 SROs are in JITT for Turbine Roll and power accession. You are to raise power to 3% and hold until they return.

U3 Anticipated LCO Actions:

None U4 Anticipated LCO Actions:

None Results of Offgoing Focus Area:

L-16-1 NRC EXAM SCENARIO 3 L-16-1 NRC EXAM SECURE INFORMATION SEG DRAFT L-16-1 NRC EXAM SECURE INFORMATION Page 40 of 42 UNIT 3 STATUS REACTOR OPERATOR UNIT RISK: GREEN (ACCEPTABLE) PROTECTED TRAIN: B Mode: 2 RCS Leakrate Accumulator Ref Levels Power: .2% Gross: 0.23 GPM A 6656 MWe 0 Unidentified 0.02 GPM B 6608 Tavg: 547 °F Charging Pps: 0.00 GPM C 6646 RCS Pressure: 2235 RCS Boron Conc: 1670 ppm Abnormal Annunciators: Annunciator:

Comp Actions:

Annunciator:

Comp Actions:

Annunciator: Comp Actions: Annunciator: Comp Actions: Annunciator: Comp Actions: Annunciator: Comp Actions:

Current Tech Spec Action Statements: (Does Not Include "For Tracking Only Items" T.S.A.S / Component:

Reason: Entry Date:

T.S.A.S / Component:

Reason: Entry Date:

T.S.A.S / Component:

Reason: Entry Date:

T.S.A.S / Component: Reason: Entry Date:

T.S.A.S / Component: Reason: Entry Date:

L-16-1 NRC EXAM SCENARIO 3 L-16-1 NRC EXAM SECURE INFORMATION SEG DRAFT L-16-1 NRC EXAM SECURE INFORMATION Page 41 of 42 REACTOR OPERATOR (CONT'D) UNIT RISK: GREEN (ACCEPTABLE) PROTECTED TRAIN: B Changes to Risk Significant Equipment: No recent changes from last shift.

OLRM: GREEN PROTECTED TRAIN: B Upcoming Reactivity Management Activities: Approval granted to withdraw rods to 125 steps to raise power to Raise Power to 3% to roll the Turbine per 3-GOP-301 Step 5.45.

Place unit online and continue power increase to 30%.

Upcoming Major POD Activities: SM has approved going to Mode 1 Roll the Turbine Place the Unit Online Continue power increase to 30%.

Upcoming ECOs to Hang and /or Release:

Hang - None Evolutions or Compensatory Actions in Progress:

NONE General Information, Remarks, and Operator Work Around Status: Weather forecast is overcast skies with scattered pockets of severe rain. U4 supplying Aux Steam Air In-leakage = 0.0 SCFM

L-16-1 NRC EXAM SCENARIO 3 L-16-1 NRC EXAM SECURE INFORMATION SEG DRAFT L-16-1 NRC EXAM SECURE INFORMATION Page 42 of 42 FOR TRAINING USE ONLY TURKEY POINT Reactivity Manipulation Table (USE ONLY AS GUIDELINE) REACTOR ENGINEERING Unit 3 Cycle 28 BOC Power Ascension Rev. 0 ELAPSED TIME POWER (%)

CBD (Steps)

AFD (%) RAOC (Limit) BORON (ppm) CHANGE (ppm) DILUTE (gal) BORATE (gal) 00:00 0.1 107 -0.00 N/A 1675 * *

• 00:02 0.1 109 -0.00 N/A 1675 * *

• 00:04 0.5 111 -0.00 N/A 1675 * *

• 00:06 0.5 113 -0.00 N/A 1675 * *

• 00:08 1.0 115 -0.1 N/A 1675 * *

• 00:10 1.5 117 -0.1 N/A 1675 * *

• 00:12 2.0 117 -0.1 N/A 1675 * *

• 00:14 2.5 119 -0.2 N/A 1675 * *

• 00:16 3.0 119 -0.2 N/A 1675 * *

• 00:18 3.0 119

-0.2 N/A 1675 * *

• 00:20 3.0 119 -0.2 N/A 1675

• Note 3

• NOTEs 1. Withdraw rods to establish a SUR of 1 dpm to raise power from 10

-8 amps to the Point Of Adding Heat

2. The SUR should be limited to .5 dpm above the Point Of Adding Heat

3. Once power is leveled at ~ 3% dilute and operate control rods as required to maintain RCS temperature for current power plateau.

NRC EXAM SECURE INFORMATION Appendix D Scenario Outline Form ES-D-1 L-16-1 N4 (Rev-0) Facility: Turkey Point Nuclear (PTN)

- Units 3 and 4 Scenario No.:

4 Op Test No.:

2016-301 Examiners:

Operators:

(SRO) (R C O) (BOP) Initial Conditions:

The plant is at 100% power (MOL). Online risk is green. B train is protected on both units. Turnover: The 3A RHR pump and 3A1 Circulating Water pump are OOS.

Event Malf. No. Event Type*

Event Description 1 TVS1M6WD I-BOP I-SRO (TS) PT-3-495 3C S/G Pressure Transmitter Fails High 2 HNACSPECIFIC_VRCPSEAL1CTVV HNACSPECIFIC_VRCPSEAL2CT VV R-RCO R-SRO N-BOP 3C RCP Degraded Seals (Rapid S/D Required) 3 TCE6DG8C C-RCO C-BOP C-SRO (TS) 3P08 Loss Of Power (Power Restored) 4 HNACSPECIFIC_VRCPSEAL1CTVV /

EAL2CTVV C-RCO C-SRO 3C RCP Seal Failure, (Rx Trip Required) 5 TFP1S3GC TFE2Z51S M-RCO M-BOP M-SRO Loss of All AC 6 TFQ6X1BF P-BOP 3B 4Kv Bus Stripping Relay Failure 7 TVHHCLC M-RCO M-BOP M-SRO Small Break LOCA 8 TFL3S12D P-RCO P-BOP MOV-3-843B HHSI Discharge to Cold Leg fails to auto o pen. (Slave Relay Failure

) * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (P)ost Trip NRC EXAM SECURE INFORMATION Page 1 of 3 NRC EXAM SECURE INFORMATION Appendix D Scenario Outline Form ES-D-1 L-16-1 N4 (Rev-0) Scenario Summary Event 1 After the crew takes the shift PT-3-495 3C S/G Pressure slowly fails high. The BOP will take manual control of 3C S/G level, and restore level to normal. The crew will use the ARP or 3

-ONOP-049.1, Deviation or Failure of Safety Related or Reactor Protection Channels, to select operable channels and restore 3C S/G level control to automatic. The US will enter 3

-ONOP-049.1 to verify all required actions are complete and to determine which bistables need to be tripped.

Event 2 Once equipment is restored to automatic, the 3C RCP seals will start degrading. The US will enter 3-ONOP-041.1, Reactor Coolant Pump Off

-Normal and commence a unit shutdown using 3

-GOP-100, Fast Load Reduction.

Event 3 After the crew starts the Load reduction Vital AC Bus 3P08 loses power. The Crew will enter 3-ONOP-003.8, Loss of Vital AC Bus 3P08. The crew will dispatch an operator to 3P08 to attempt to restore power. The 3A and 3B S/G level controllers shift to manual. The 3C S/G level controller shifts to manual on the Backup Controller.

The BOP will select operable control channels for the 3A and 3B S/G and then restore automatic control. The operator dispatched to the restore power will report the Main Breaker for 3P08 will not close. Electrical Maintenance estimates it will take 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to replace the breaker. Event 4 After the US completes the Tech Spec review for the loss of 3P08, the 3C RCP Seal degrades to the point that requires a Reactor trip and stopping of the 3C RCP. The RCO will trip the Reactor, verify the Reactor is tripped, stop 3C RCP, close 3C RCP CBO Isolation Valve CV 303C, and close PCV-3-455A, PZR Spray Valve Loop C. The crew will enter 3

-EOP-E-0, Reactor Trip or Safety Injection and complete the Operator Immediate Actions.

Event 5 After the RCO completes tripping the 3C RCP, a Loss of AC Power will occur. The 3A and 3B Emergency Diesel Generators will start but neither will energize its respective 4KV bus. The crew will enter 3-EOP-ECA-0.0, Loss of All AC Power.

Event 6 The 3A 4KV Bus is locked out so the US will direct the BOP perform Attachment 2, 3B 4KV Bus Stripping. The BOP will open the 3B ICW pump, 3B CCW pump, 3C CCW pump, 3B Load Center, and 3D Lo ad Center breakers to complete bus stripping. Once Bus Stripping is complete the 3B EDG will automatically energize the 3B 4KV Bus.

Event 7 Once the 3B 4KV Bus is energized the crew will transition back to 3

-EOP-E-0. Shortly after the transition a Small Break LOCA will occur.

NRC EXAM SECURE INFORMATION Page 2 of 3 NRC EXAM SECURE INFORMATION Appendix D Scenario Outline Form ES-D-1 L-16-1 N4 (Rev-0) Scenario Summary Event 8 When SI actuates

, the slave relay which opens MOV 843B fails to actuate. The RCO may open MOV 843B any time after SI actuates. If the RCO doesn't open MOV 843B the BOP will open it during the performance of 3

-EOP-E-0 Attachment 3, Prompt Action Verifications.

When the crew is ready to transition to 3-EOP-E-1, Loss Of Reactor Or Secondary Coolant, they will notice the Integrity Critical Safety Function Status Tree is RED and will transition to 3-EOP-FR-P.1, Response To Imminent Pressurized Thermal Shock Condition.

The scenario is terminated after the crew transitions to 3

-EOP-FR-P.1 and determines a soak is required, or at the Lead Evaluator's discretion once all critical tasks have been evaluated.

Event Scenario Critical Tasks 6 CT1 Re-energize 3B 4KV Bus Following a Loss Of All AC, complete bus stripping and restore power to the 3B 4KV bus prior to actuating SI and within 30 minutes of the loss of power

.

Safety Significance: The failure to energize an AC emergency bus in a timely manner constitutes a misoperation or incorrect crew performance in which the crew does not prevent a degraded emergency power capacity.

The 30 minute time limit is based minimizing DC bus battery depleti on and the requirement to manually load a de

-energized DC bus battery charger onto the operating EDG.

(0-ADM-232, Attachment 1 , Time Critical Operator Actions

) 7 CT2 Open MOV-3-843B During a SBLOCA establish at least one train of HHSI flow prior to completing 3-EOP-E-0 Attachment 3 and within 30 minutes the HHSI pump starting

.

Safety Significance

Failure to establish at least one train HHSI flow constitutes a misoperation or incorrect crew performance in which the crew does not prevent "degraded emergency core cooling system (ECCS

) capacity." The 30 minute time limit is based on the requirement to limit the time the pump is operating at shutoff head to less than 30 minutes. (0-ADM-23 2 Attachment 1, Time Critical Operator Actions)

NRC EXAM SECURE INFORMATION Page 3 of 3 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG Site: Turkey Point Units 3 and 4 (PTN)

Title: L-16-1 NRC EXAM SCENARIO 4 LMS #: NRC 24 LMS Rev Date:

6/8/16 Rev #: 0 SEG Type: Training Evaluation Program: LOCT LOIT Other Duration: 120 minutes Developed by:

Tim Hodge / Luis Sagion 8/4/16 Instructor/Developer Date Reviewed by:

Brian Clark 8/4/16 Instructor (Instructional Review)

Date Validated by :

Sean Bloom 8/5/16 SME (Technical Review)

Date Approved by:

Mark Wilson 8/5/16 Training Supervision Date Approved by:

Sean Bloom 8/5/16 Training Program Owner (Line)

Date NRC EXAM SECURE INFORMATION Page 1 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG SCENARIO REFERENCES DOC NO. TITLE REV 3-EOP-E-0 REACTOR TRIP OR SAFETY INJECTION 12 3-EOP-ECA-0.0 LOSS OF ALL AC POWER 10 3-EOP-FR-P.1 RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION 3 3-GOP-100 FAST LOAD REDUCTION 12 A 3-ONOP-003.8 LOSS OF 120V VITAL INSTRUMENT PANEL 3P08 6 3-ONOP-041.1 REACTOR COOLANT PUMP OFF

-NORMAL 11 3-ONOP-049.1 DEVIATION OR FAILURE OF SAFETY RELATED OR REACTOR PROTECTION CHANNEL 4 PTN TECHNICAL SPECIFICATIONS 300 NRC EXAM SECURE INFORMATION Page 2 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Objective Given this simulator scenario and resources normally found in the Control Room, the operating crew will perform Control Room operations IAW approved plant procedures in order to maintain the integrity of the plant and the health and safety of the public.

Enabling Objectives:

Given this simulator scenario and resources normally found in the Control Room, operate in accordance with approved plant procedures, Operations Department Instructions, and management expectations:

1. (ALL) Demonstrate personnel SAFETY awareness in interactions with plant staff and outside agencies.

2. (ALL) Demonstrate ALARA awareness in interactions with plant staff and outside agencies.

3. (ALL) Exchange correct information using 3

-point communication/Repeat

-backs with Control Room personnel and other plant staff.

4. (ALL) Inform plant personnel and System of plant conditions, as needed.

5. (US) Employ timely and concise crew briefs where appropriate.

6. (ALL) Maintain awareness of plant status and control board indication.

7. (ALL) Correctly diagnose plant situations.

8. (ALL) Solve operational problems as they arise.

9. (RCO/BOP) Manipulate plant controls properly and safely.

10. (ALL) Demonstrate self

-checking using STAR and peer checks(when required)

11. (US) Demonstrate command and control of the crew.

12. (US) Coordinate the input of crew members and other plant staff.

13. (US) Utilize the input of crew members and other plant staff.

14. (ALL) Demonstrate conservative decision making.

15. (ALL) Demonstrate teamwork.

16. (ALL) Respond to plant events using procedural guidance (OPs/ONOPs/EOPs) as applicable in accordance with rules of usage.

17. (RCO/BOP) Implement any applicable procedural immediate operator actions without use of references.

18. (SRO) Maintain compliance with Tech Specs.

19. (ALL) Identify/enter applicable Tech Spec action statements.

20. (ALL) Respond to annunciators using ARPs (time permitting).

21. (ALL) Maintain written communication, logs, and documentation as needed to permit post

-event reconstruction.

Continued on next page NRC EXAM SECURE INFORMATION Page 3 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS While addressing the following events:

1. PT-3-495 3C S/G Pressure Transmitter Fails High

2. 3C RCP Degraded Seals

3. 3P08 Loss Of Power

4. 3C RCP Seal Failure

5. Loss of All AC

6. 3B 4Kv Bus Stripping Relay Failure

7. Small Break LOCA

8. MOV-3-843B HHSI Discharge to Cold Leg Fails To Auto Open Prerequisites:

None Training Resources:

PTN Unit 3 Plant Simulator Development

References:

TR-AA-220-1003, Initial N RC and Audit Exam Process TR-AA-230-1003, SAT Development TR-AA-230-1007 , Conduct of Simulator Training and Evaluation 0-ADM-232, Time Critical Action Program OP-AA-100-1000 , Conduct Of Operations OP-AA-103-1000 , Reactivity Management 0-ADM-200, Operations Management Manual 0-ADM-211, Emergency and Off

-Normal Operating Procedure Usage WCAP-17711-NP, Pressurized Water Reactor Owners Group Westinghouse Emergency Response Guideline Revision 2

-Based Critical Tasks Protected Content: N/A Evaluation Method: Performance Mode Operating Experience:

None Risk Significant Operator Actions: Following a Loss Of All AC, complete bus stripping and restore power to the 3B 4KV bus prior to actuating SI and within 30 minutes of the loss of power.

During a SBLOCA

, establish at least one train of HHSI flow prior to completing 3-EOP-E-0 , Attachment 3

, and within 30 minutes the HHSI pump starting.

NRC EXAM SECURE INFORMATION Page 4 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG TASKS ASSOCIATED WITH THIS SIMULATOR EXERCISE GUIDE SRO TASK #

TASK TITLE 02005015500 RESPOND TO A LOSS OF ALL A.C. POWER 02028033500 AUTHORIZE UNIT TRIP 02041029300 EVALUATE AND RESPOND TO A LOW PRESSURIZER PRESSURE 02041044300 EVALUATE AND RESPOND TO HIGH RCP NUMBER ONE SEAL LEAKOFF 02089026300 AUTHORIZE FAST LOAD REDUCTION 02200001500 RESPOND TO UNIT TRIP 02200021500 RESPOND TO LOSS OF COOLANT ACCIDENT 02200022500 DIAGNOSE CAUSE OF SAFEGUARDS ACTUATION 02200044500 RESPOND TO HIGH STEAM GENERATOR LEVEL 02200050500 RESPOND TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION RO TASK TASK TITLE 01005015500 RESPOND TO A LOSS OF ALL A.C. POWER 01041044300 EVALUATE AND RESPOND TO HIGH RCP NUMBER ONE SEAL LEAKOFF 01089026300 RESPOND TO / ADJUST TURBINE DURING FAST LOAD REDUCTION 01200001500 RESPOND TO UNIT TRIP 01200021500 RESPOND TO LOSS OF COOLANT ACCIDENT 01200 022500 DIAGNOSE CAUSE OF SAFEGUARDS ACTUATION 02200044500 RESPOND TO HIGH STEAM GENERATOR LEVEL 02200050500 RESPOND TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION NRC EXAM SECURE INFORMATION Page 5 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG UPDATE LOG:

NOTES: Place this form with the working copies of lesson plans and/or other materials to document changes made between formal revisions. For fleet

-wide training materials, keep electronic file of this form in same folder as approved materials. Refer to TR

-AA-230-1003 SAT Development for specific directions regarding how and when this form shall be used.

Indicate in the following table any minor changes or major revisions (as defined in TR

-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR

-AA-230-1003-F16. # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE REVIEWER DATE 0-0 Initial Revision Revised for L-1 6-1 NRC Exam 2108338 Note 5 Note 5 Note 5 Note 5 0-1 0-2 0-3 0-4 0-5 1. Individual updating lesson plan or training material shall complete the appropriate blocks on the Update Log.

2. Describe the change to the lesson plan or training materials.

3. State the reason for the change (e.g., reference has changed, typographical error, etc.) 4. Preparer enters name/date on the Update Log and obtains Training Supervisor approval.

5. Initial dates and site approval on cover page.

NRC EXAM SECURE INFORMATION Page 6 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG SCENARIO

SUMMARY

Initial Conditions

The plant is at 100% power (MOL). Online risk is green. B train is protected on both units.

Equipment OOS The 3A RHR pump and 3A1 Circulating Water pump are OOS.

Event 1 After the crew take s the shift , PT-3-495 , 3C S/G Pressure

, slowly fails high. The BOP will take manual control of 3C S/G level and restore level to normal. The crew will use the ARP or 3

-ONOP-049.1, Deviation or Failure of Safety Related or Reactor Protection Channels, to select operable channels and restore 3C S/G level control to automatic. The US will enter 3

-ONOP-049.1 to verify all required actions are complete and to determine which bistables need to be tripped.

Event 2 Once equipment is restored to automatic, the 3C RCP seals will start degrading. The US will enter 3-ONOP-041.1, Reactor Coolant Pump Off

-Normal , and commence a unit shutdown using 3

-GOP-100, Fast Load Reduction.

Event 3 After the crew starts the Load reduction

, Vital AC Bus 3P08 loses power. The Crew will enter 3-ONOP-003.8, Loss of Vital AC Bus 3P08. The crew will dispatch an operator to 3P08 to attempt to restore power. The 3A and 3B S/G level controllers shift to manual. The 3C S/G level controller shifts to manual on the Backup Controller.

The BOP will select operable control channels for the 3A and 3B S/G and then restore automatic control. The operator dispatched to restore power will report the Main Breaker for 3P08 will not close. Electrical Maintenance estimate s it will take 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to replace the breaker.

Event 4 After the US completes the Tech Spec review for the loss of 3P08, the 3C RCP Seal degrades to the point that requires a Reactor trip and stopping the 3C RCP. The RCO will trip the Reactor, verify the Reactor is tripped, stop 3C RCP, close 3C RCP CBO Isolation Valve

, CV-3-303C, and close PCV-3-455A, PZR Spray Valve Loop C. The crew will enter 3

-EOP-E-0, Reactor Trip or Safety Injection

, and complete the Immediate Operator Actions.

Event 5 After the RCO completes tripping the 3C RCP, a Loss of AC Power will occur. The 3A and 3B Emergency Diesel Generators will start

, but neither will energize its respective 4KV bus. The crew will enter 3-EOP-ECA-0.0, Loss of All AC Power.

NRC EXAM SECURE INFORMATION Page 7 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG SCENARIO

SUMMARY

Event 6 The 3A 4KV Bus is locked out

, so the US will direct the BOP perform Attachment 2, 3B 4KV Bus Stripping. The BOP will open the 3B ICW pump, 3B CCW pump, 3C CCW pump, 3B Load Center

, and 3D Load Center breakers to complete bus stripping. Once Bus Stripping is complete

, the 3B EDG will automatically energize the 3B 4KV Bus.

Event 7 Once the 3B 4KV Bus is energized

, the crew will transition back to 3

-EOP-E-0. Shortly after the transition

, a Small Break LOCA will occur.

Event 8 When SI actuates

, the slave relay which opens MOV 843B fails to actuate. The RCO may open MOV 843B any time after SI actuates. If the RCO doesn't open MOV 843B , the BOP will open it during the performance of 3

-EOP-E-0 Attachment 3, Prompt Action Verifications.

The scenario is terminated after the crew transitions to 3-EOP-FR-P.1 and determines a soak is required , or at the Lead Evaluator's discretion once all critical tasks have been evaluated.

Event CRITICAL TAS KS 6 CT1 Re-energize 3B 4KV Bus Following a Loss Of All AC, complete bus stripping and restore power to the 3B 4KV bus prior to actuating SI and within 30 minutes of the loss of power.

Safety Significance: The failure to energize an AC emergency bus in a timely manner constitutes a misoperation or incorrect crew performance in which the crew does not prevent a degraded emergency power capacity. The 30 minute time limit is based minimizing DC bus battery depletion and the requirement to manually load a de

-energized DC bus battery charger onto the operating EDG. (0

-ADM-232, Attachment 1 , Time Critical Operator Actions) 7 CT2 Open MOV-3-843B During a SBLOCA

, establish at least one train of HHSI flow prior to completing 3-EOP-E-0 , Attachment 3

, and within 30 minutes the HHSI pump starting.

Safety Significance: Failure to establish at least one train HHSI flow constitutes a misoperation or incorrect crew performance in which the crew does not prevent "degraded emergency core cooling system (ECCS) capacity."

The 30 minute time limit is based on the requirement to limit the time the pump is operating at shutoff head to less than 30 minutes. (0

-ADM-23 2 Attachment 1, Time Critical Operator Actions)

NRC EXAM SECURE INFORMATION Page 8 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG SEQUENCE OF EVENTS Event # Description

1. PT-3-495 3C S/G Pressure Transmitter Fails High

2. 3C RCP Degraded Seals

3. 3P08 Loss Of Power

4. 3C RCP Seal Failure

5. Loss of All AC

6. 3B 4Kv Bus Stripping Relay Failure

7. Small Break LOCA

8. MOV-3-843B HHSI Discharge to Cold Leg Fails To Auto Open NRC EXAM SECURE INFORMATION Page 9 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG SIMULATOR SET UP INSTRUCTIONS Check Action ____ Restore IC

-1 (100% MOL) or equivalent IC.

____ Place the Simulator in RUN. ____ Stop the 3A1 Circ Water Pump

____ Open & execute lesson file L

-1 6-1 N4 ____ Ensure the following lesson steps are triggered:

SETUP - 3A RHR PUMP OOS SETUP - 3A1 CWP OOS SETUP EVENT 6

- 3B BUS STRIPPING FAILURE SETUP EVENT 8

- B TRAIN SLAVE RELAY FAILURE

____ Place an ECO tag on the 3A RHR pump place it in PTL:

Place an ECO tag on the 3 A 1 CWP place it in Stop.

____ Verify the trend for 3A1 Screen on the TWS DP Recorder is clear.

____ Ensure Rod Group Step Counters have completed stepping out.

____ Allow the plant to stabilize.

____ Acknowledge any alarms and freeze Simulator.

____ Ensure B train is protected train on VPA.

____ Perform the SIMULATOR OPERATOR CHECKLIST or equivalent.

____ Place TURNOVER SHEETS on RO

's desk or give to the Lead Evaluator.

NRC EXAM SECURE INFORMATION Page 10 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG BRIEFINGS Shift turnover information is attached to the back of this guide.

Ensure all applicants are prior briefed on Appendix E of NUREG 1021, Policies and Guidelines For Taking NRC Examinations.

Conduct a Crew Pre

-brief to cover turnover information. Shift turnover information is attached to the back of this guide.

US: RCO: BOP:

SCENARIO NOTE 0-ADM-211 Prudent Operator Actions

- If redundant stand

-by equipment is available and ready, the operator is permitted to start the redundant equipment for failed or failing operating equipment.

Immediate follow up of applicable ARPs and ONOPs (AOPs) shall occur as require

d. NRC EXAM SECURE INFORMATION Page 11 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG Critical T ask s are highlighted in red. Simulator Operator Actions are highlight ed in blu e. Operator Verifiable Actions are Highlight ed in gree n. EVENT 1 - PT-3-495 3C S/G PRESSURE TRANSMITTER FAILS HIGH 3-ONOP-049.1, DEVIATION OR FAILURE OF SAFETY RELATED OR REACTOR PROTECTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOOTH OPERATOR When directed by Lead Evaluator, trigger EVENT 1 - PT-3-4 95 FAILS HIGH BOP: Recognizes and reports PT-3-495 failure. PROMPT ACTIONS Takes manual control of 3 C S/G level control valve FCV 49 8. Restores 3 C S/G level to normal.

RCO: Addresses Alarm Response for C5/3 , 6/3 , SG C Level Deviation. CHECK LI-3-496 or LI-3-498, B\C STM GEN LEVEL controlling channel for SG Level deviation.

CHECK Feedwater Controllers FIC 498A or FIC 498B for indications of failure, alarm, or input signal failures.

CHECK Feedwater Controller Inputs IF alarm is due to instrument failure, THEN REFER TO 3-ONOP-049.1, Deviation or Failure of Safety Related or Reactor Protection Channels.

US: Enters and directs actions of 3

-ONOP-049.1, Deviation or Failure of Safety Related or Reactor Protection Channels, for response. NRC EXAM SECURE INFORMATION Page 12 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG EVENT 1 - PT-3-495 3C S/G PRESSURE TRANSMITTER FAILS HIGH 3-ONOP-049.1, DEVIATION OR FAILURE OF SAFETY RELATED OR REACTOR PROTECTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE NOTE The crew may use the ARP to select an operable channel and restore automatic level control.

BOOTH OPERATOR If asked to locally investigate transmitters, wait 2

-3 minutes and report no abnormalities noticed.

BOP: Verify P T-3-4 95 failure by channel check comparison.

Verify no off

-normal conditions exist on P T-3-4 96. Place 3C S/G Steam Flow Control Transfer Switch to FT 495 (Ch IV -Yellow) Place 3C S/G Feed Water Flow Control Transfer Switch to FT 496 (CH IV - Yellow) Ensure 3 C S/G level is returned to auto.

BOOTH OPERATOR WCC/I&C: Acknowledge the report. If asked , I&C would like to be present before tripping bi-stables. They will report to the control room within an hour.

BOP: Notifies WCC to initiate PWO and I&C for troubleshooting.

US: Reviews Tech Specs LCO 3.3.1 Functional Unit 12

- Action 6 within 6 h ours trip bi

-stables LCO 3.3.2 Functional Unit 1e, 1f, and 4d. - Action 15 within 6 h ours trip bi

-stables LEAD EVALUATOR After S/G level control is restored to auto and the US completes the review of Tech Specs, at the Lead Evaluators discretion, direct the Booth Operator to trigger the next event.

US: Conducts crew brief.

NRC EXAM SECURE INFORMATION Page 13 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG EVENT 2 - 3C RCP DEGRADED SEALS 3-ONOP-041.1 , REACTOR COOLANT PUMP OFF

-NORMAL TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOOTH OPERATOR When directed by the lead evaluator , trigger EVENT 2

- 3C RCP DEGRADED SEAL BOP: Reviews ARPs A6/4 , 7/4 , 7/5. Refer to 3-ONOP-041.1, Reactor Coolant Pump Off Normal.

RCO: Responds to RCP Alarms Check P2 pressure equal to or less than 1741 psig on VPA (NO) Check P3 pressure greater than 975 psig on VPA (Y ES) US: Enter and direct the actions of 3-ONOP-041.1, Reactor Coolant Pump Off Normal.

US: Reviews Foldout Page with the crew.

RCP Stopping Criteria RCP Seal Criteria For Stopping RCP Fast Load Reduction Criteria (YES, 3C RCP Seal Stage

- greater than 1700 and / or CBO exceeds 3.7 gpm) Exceeding Vibration Or Stator Temperature Limits RCP Vibration Assessment Criteria US: Enter and direct the actions of 3

-GOP-100, Fast Load Reduction NRC EXAM SECURE INFORMATION Page 14 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG EVENT 2 - 3C RCP DEGRADED SEALS 3-GOP-100, FAST LOAD REDUCTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE NOTE Attachment 3 is available on Page 41 Attachment 4 is available on Page 42 US: Directs actions to reduce Rx power per 3-GOP-100 Completes Attachment 3 Brief the crew per Attachment 4 Steps 1-2 US: Reviews Foldout page with crew.

3-EOP-E-0 Transition Criteria Notify Chemistry Department Boration Stop Criteria Restore Blender to AUTO FOLDOUT PAGE BOOTH OPERATOR Acknowledge notifications.

BOP: Notify The Following Of Fast Load Reduction System Dispatcher Plant personnel using the Page Boost Chemistry to start RCS sampling is required according to Tech Spec Table 4.4-4. Ste p 3 NRC EXAM SECURE INFORMATION Page 15 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG EVENT 2 - 3C RCP DEGRADED SEALS 3-GOP-100, FAST LOAD REDUCTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE RCO: Begin Boration For Initial Tavg Effect Set the Boric Acid Totalizer to total boric acid volume value determined on Attachment 3.

Place the Reactor Makeup Selector Switch to BORATE.

Place the RCS Makeup Control Switch to START.

Adjust FC-3-113A, Boric Acid Flow Controller

, to achieve 40 gpm boric acid flow as indicated on FR 113. WHEN Tavg begins to lower from the boration , adjust FC-3-113A, Boric Acid Flow Controller

, to load reduction value from Attachment 3.

Step 4 US: Determine Turbine Load Reduction in MW CNTRL Ste p 5 BOP: Initiate Turbine Load Reduction in MW CNTRL Select MW CNTRL Set TARGET power level

- MW VALUE from Attachment 3 Set RAMP RATE

- MW/M VALUE FROM Attachment 3

. Check Tavg has lowered 1° to 2°F from the initial value prior to boration.

Depress GO Ensure FC-3-113A, Boric Acid Flow Controller, has been adjusted to the load reduction boration rate.

Go to Step 10 Step 6 NRC EXAM SECURE INFORMATION Page 16 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG EVENT 2 - 3C RCP DEGRADED SEALS 3-GOP-100, FAST LOAD REDUCTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE NOTE Enclosure 1 is available on Pag e 43. BOP: Monitor Load Reduction Adjusts power reduction rate to Maintain Tavg/Tref within the 3. Monitors S/G level control to ensure feed reg valves properly maintain level control in automatic. Refer to Enclosure 1 for expected alarms. Step 10 BOOTH OPERATOR Respond as SNPO. If asked, report idle Charging Pump is ready for start.

RCO: Maintain pressurizer level to ensure that automatic pressurizer level control maintains level on program. If needed , start 2 nd Chg Pp and place 2 nd orifice in service.

Adjusts boration rate to Maintain identified in Attachment 3.

Refer to Enclosure 1 for expected alarms. Step 10 RCO: Monitor Boration Rate Monitor for excessive rod movement by monitoring TR 409D, Rod Position Bank D. Determine if Insertion Limit and Bank D position are converging at a rate that will cause rod insertion limit alarms. Adjust power reduction rate as needed to control rod insertion Increase boration rate and/or total amount as necessary to limit control rod insertion Step 11 NRC EXAM SECURE INFORMATION Page 17 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG EVENT 2 - 3C RCP DEGRADED SEALS 3-GOP-100, FAST LOAD REDUCTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE RCO: Monitor Annunciator B 8/1, ROD BANK LO LIMIT

- CLEAR Monitor B 8/2 ROD BANK A/B/C/D EXTRA LO LIMIT - CLEAR Steps 12-13 US: Have SM refer to t he following procedures: 0-EPIP-20101, DUTIES OF EMERGENCY COORDINATOR 0-ADM-115, NOTIFICATION OF PLANT EVENTS Step 14 LEAD EVALUATOR Once power has been reduced by a minimum of 5%, at the Lead Evaluators discretion, proceed to the next Event

. RCO: Energize Pressurizer Backup Heaters Step 15 NRC EXAM SECURE INFORMATION Page 18 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG EVENT 3 - 3P08 LOSS OF POWER 3-ONOP-003.8 , LOSS OF 120V VITAL INSTRUMENT PANEL 3P08 TIME EVALUATOR ACTIVITIES & NOTEs EXPECTED STUDENT RESPONSE BOOTH OPERATOR When directed by the Lead Evaluator

, trigger EVENT 3 - LOSS OF 3P08 RCO/BOP Respond to various alarm

s. Report a loss of power to 3P08

- Power Range N

-43 Failure (NIS Racks Channel III Lights Out)

- Loss of Channel III Vital Instrumentation/Indications

- Bottom two rows of bistable lights are out US: Enter and direct the actions of 3-ONOP-003.8 , Loss Of 120V Vital Instrument Panel 3P08. NOTE Step 1 is an immediate action step.

RCO: Check If A Reactor Trip has occurred (NO) Check If A Reactor Trip is required. (NO) STEP 1 BOOTH OPERATOR When dispatched to restore power 3P08 per Attachment 1

, wait 3 minutes and then report nothing obviously wrong

. Inform the control room you are going to attempt to re

-energize the bus , then trigger EVENT 3 - 3P08/3P23 ALL BREAKERS OFF

. US: Reviews Foldout Page with the crew.

Verify Turbine Inlet Pressure Control selected to PT 447 (CH.4 Yellow)

Dispatch operator to restore power to 3P08 using Attachment 1.

If a Reactor Trip has occurred (NO) If power available to 3P09, then perform the following:

- Place CS-3-1608, Power Selector switch for H/A 1608, to 3P09.

- Restore H/A 1608 to Auto.

FOLDOUT PAGE NRC EXAM SECURE INFORMATION Page 19 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG EVENT 3 - 3P08 LOSS OF POWER 3-ONOP-003.8 , LOSS OF 120V VITAL INSTRUMENT PANEL 3P08 PROCEDURE CAUTION Loss of power to 3PO8 when OMS is in LOW PRESSURE OPS will cause a continuous open signal to PCV-3-456. RCO/BOP: Check Unit Operating In Modes 1 Through 3 Prior To Loss Of 3P08

. STEP 2 RCO: Verify Pressurizer PORVs

- CLOSED Check Pressurizer Level control switch in Position 1 (CH 1 & 2)

Control charging flow using the 3A or 3B charging pumps in AUTO speed control - Starts 3A or 3B Charging pump

- Stop 3C Charging pump STEP 3 PROCEDURE CAUTION 3C Steam Generator Level Recorder is de

-energized.

Main Generator load should be maintained as stable as possible until all FW Control Valves are restored to automatic control.

PROCEDURE NOTE 3A and 3B Steam Generator level controllers should remain in AUTOMATIC if Feedwater flow selected to Channel IV (Yellow) and Steam Generator Level selected to the control channel.

3C Steam Generator level controllers is in MANUAL on the Backup Controller.

3A and 3B Steam Generator level controllers shift to MANUAL If Feedwater flow or Steam Generator Level selected to channel III ( Blue).

BOP: Control 3C Steam Generator Water Level by using MANUAL control on the backup Controller.

Step 4a NRC EXAM SECURE INFORMATION Page 20 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG EVENT 3 - 3P08 LOSS OF POWER 3-ONOP-003.8 , LOSS OF 120V VITAL INSTRUMENT PANEL 3P08 BOP: Check 3A Steam Generator Feedwater Primary Controller in AUTOMATIC Mode (NO) Select 3A Steam Generator Feedwater Flow Control Transfer switch to FI 476 (Ch IV - Yellow) Select 3A Steam Generator Steam Flow Control Transfer switch to FI 475 (Ch IV - Yellow) Select 3A Steam Generator Level Control Transfer switch to LI 478 (Ch I - Red) On 3A Primary Controller

, press "A" button for 2 seconds until backlit to return controller to AUTOMATIC Mode STEP 4b BOP: Check 3B Steam Generator Feedwater Primary Controller in AUTOMATIC Mode (NO) Select 3B Steam Generator Feedwater Flow Control Transfer switch to FI 486 (Ch IV - Yellow) Select 3B Steam Generator Steam Flow Control Transfer switch to FI 485 (Ch IV - Yellow) Select 3B Steam Generator Level Control Transfer switch to LI 488 (Ch II - White) On 3 B Primary Controller press "A" button for 2 seconds until backlit to return controller to AUTOMATIC Mode STEP 4c PROCEDURE CAUTION If Tavg decreases to less than 543

°F, an automatic Safety Injection will occur due to the High Steam Flow bistables already tripped by the loss of power.

RCO/BOP Maintain Plant Parameters

- STABLE STEP 5 NRC EXAM SECURE INFORMATION Page 21 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG EVENT 3 - 3P08 LOSS OF POWER 3-ONOP-003.8 , LOSS OF 120V VITAL INSTRUMENT PANEL 3P08 BOOTH OPERATOR Report the Main breaker for 3P08 will not close. Electrical Maintenance will have to replace it. Estimated repair time is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. RCO: Check Power Restored To 3P08 (NO) IF power can NOT be restored to 3P08 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, THEN perform the actions required by Technical Specifications as directed by the SM , Return to Step 1.

STEP 6 LEAD EVALUATOR This Tech Spec review can be quite extensive. The Lead evaluator m a y choose to have the US identify Tech Specs with actions statements of 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> s or less as a follow up question. When the US starts the Tech Spec review at the Lead Evaluators discretion proceed to the next event.

NOTE Per Foldout Page, cooldown will require closure of MSIVs and possible reduction of feedwater flow.

US: Review Tech Specs LCO 3.3.1 Functional Unit 17.b due to the loss of PT 4 4 6 - Action 7 - within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> determine by observation of the associated permissive annunciator window(s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3. LCO 3.4.4 due to the loss of PORV PCV-3-456 - Action a - within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV(s) to OPERABLE status or close the associated block valve(s) with power maintained to the block valve(s); otherwise be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. LCO 3.8.3.

1.h due to the loss of 3P08

- Action c - Reenergize the A.C. vital panel within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least HOT STANDBY within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. NRC EXAM SECURE INFORMATION Page 22 of 4 6 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG EVENT 4 - 3C RCP SEAL FAILURE 3-EOP-E-0, RX TRIP OR SAFETY INJECTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOOTH OPERATOR When directed by Lead Evaluator, trigger EVENT 4 - 3C RCP SEAL FAILURE RCO: Reports rising CBO Flow and #3 seal differential pressure.

RCP CBO flow exceeds 4.1 gpm or any Seal Stage differential pressure exceeds 2000 psid , recommends a Manual Rx trip

. US: Directs 3-EOP-E-0 response after auto Reactor trip.

RCO: Manually trips Reactor.

LEAD EVALUATOR When the RCO completes the required actions for the RCP seal package failure

, proceed to the next event.

RCO: Verifies Reactor Trip After verifying Rx Trip

- Trips 3C RCP

- Closes CV-3-303C, CBO Isolation valve CV-303C. - Closes P CV-3-455A, PZR Spray Valve Loop C STEP 1 BOP: Verify Turbine Trip STEP 2 BOP: Verify Power To Emergency 4 KV Buses STEP 3 RCO: Checks If SI Is Actuated STEP 4 NRC EXAM SECURE INFORMATION Page 23 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG EVENT 5 - LOSS OF ALL AC 3-EOP-ECA-0.0, LOSS OF ALL AC POWER TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOOTH OPERATOR When directed by the Lead Evaluator

, trigger EVENT 5 LOSS OF ALL AC

. CT 1 Start Time NOTE Record the time offsite power is lost for Time Critical Task verification

. NOTE Step 1 and Step 2 are IMMEDIATE ACTION steps RCO: Verify Reactor Trip STEP 1 BOP: Verify Turbine Trip STEP 2 RCO: Check If RCS Is Isolated (NO) Close Letdown Isolation valves CV-3-200A/B/C STEP 3 B OP: Verify Proper AFW Flow STEP 4 US: The Unit Supervisor shall evaluate plant conditions and establish EDG Priority. Since the 3A Bus is locked out the US determine s the 3B EDG is the prio rity. STEP 5 BOP: Try To Restore Power To 3A OR 3B 4KV Bus Check EDG Priority

- 3A (NO) Go to Step 5.o STEP 5.a NRC EXAM SECURE INFORMATION Page 24 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG EVENT 5 - LOSS OF ALL AC 3-EOP-ECA-0.0, LOSS OF ALL AC POWER TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOP: Check 3B Bus Lockout Relay

- RESET Check 3B EDG Lockout

- RESET Check 3B EDG

- RUNNING Check 3B 4KV Bus

- ENERGIZED (NO) Go to step 5.t STEP 5.o - 5.r BOP: Verify 3B 4KV bus stripping using Attachment 2

. STEP 5.t NRC EXAM SECURE INFORMATION Page 25 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG EVENT 6 - 3B 4KV BUS STRIPPING RELAY FAILURE 3-EOP-ECA-0.0, LOSS OF ALL AC POWER ATTACHMENT 2 TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOP: Step 1 is N/A STEP 1 CT 1 Stop Time NOTE The BOP will have to manually strip the loads highlighted in red. When all loads are stripped

, the 3B EDG will energize the 3B 4KV Bus.

Re-energize 3B 4KV Bus Following a Loss Of All AC, complete bus stripping and restore power to the 3B 4KV bus prior to actuating SI and within 30 minutes of the loss of power.

BOP: Verify the following breakers OPEN 3AB22, 3B 4KV BUS TIE TO 3A OR 3C 4KV BUS 3AB05, STARTUP TRANSFORMER 3B 4KV BUS SUPPLY 3AB02, AUXILIARY TRANSFORMER 3B BUS SUPPLY 3AB10, HEATER DRAIN PUMP 3B 3AB21, CONDENSATE PUMP 3B 3AB12, SAFETY INJECTION PUMP 3B 3AB15, RESIDUAL HEAT REMOVAL PUMP 3B 3AB13, COMPONENT COOLING WATER PUMP 3B 3AB01, REACTOR COOLANT PUMP 3B 3AB06, REACTOR COOLANT PUMP 3C 3AB17, INTAKE COOLING WATER PUMP 3B 3AB11, TURBINE PLANT COOLING WATER PUMP 3B 3AB16, CIRCULATING WATER PUMP 3B1 3AB18, CIRCULATING WATER PUMP 3B2 3AB09, 3B LOAD CENTER 3AB14, 3D LOAD CENTER STEP 2 BOP: Step 3 is N/A STEP 3 NRC EXAM SECURE INFORMATION Page 26 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG EVENT 6 - 3B 4KV BUS STRIPPING RELAY FAILURE 3-EOP-ECA-0.0, LOSS OF ALL AC POWER ATTACHMENT 2 TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOP: Verify 3AD05, INTAKE COOLING WATER PUMP 3C BREAKER, is open.

Verify 3AD04, COMPONENT COOLING WATER PUMP 3C BREAKER, is open STEP 4 BOP: Notify Unit Supervisor that 3B 4KV Bus stripping is complete.

STEP 5 NRC EXAM SECURE INFORMATION Page 27 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG EVENT 6 - 3B 4KV BUS STRIPPING RELAY FAILURE 3-EOP-ECA-0.0, LOSS OF ALL AC POWER TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE PROCEDURE CAUTION If an SI signal exists OR is actuated during this procedure, it must be reset to ensure restoration of a power source and to ensure controlled loading of equipment on the 4KV bus.

PROCEDURE NOTE If a Sequencer Failure has occurred AND SI has actuated, the associated EDG Output Breaker may NOT close unless SI is reset.

BOP: Verify SI

- RESET Check 3B 4KV Bus

- ENERGIZED Observe CAUTION and NOTE prior to Step 5.f, and return to Step 5.f STEPs 5.u

- 5.w Crew Verify required Safeguards equipment

- OPERATING STEP 5.f LEAD EVALUATOR When the crew returns to 3

-EOP-E-0 proceed to the next event.

US: Check status of 3

-EOP-F-0, CRITICAL SAFETY FUNCTION STATUS TREES, prior to entering this procedure

- MONITORED FOR INFORMATION ONLY. (NO) Implement FRPs as required Return to procedure and step in effect. STEP 5.g NRC EXAM SECURE INFORMATION Page 28 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG EVENT 7 - SMALL BREAK LOCA 3-EOP-E-0, RX TRIP OR SAFETY INJECTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOOTH OPERATOR When directed by the Lead Evaluator

, trigger EVENT 7 - SBLOCA RCO: Verify Reactor Trip STEP 1 BOP: Verify Turbine STEP 2 BOP: Verify Power To Emergency 4 KV Buses STEP 3 CT 2 Start Time NOTE Record the time SI actuates for Time Critical task verification RCO: Checks If SI Is Actuated STEP 4 US: Reviews Steps 1 - 4 of 3-EOP-E-0 with the crew. NRC EXAM SECURE INFORMATION Page 29 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG EVENT 7 - SMALL BREAK LOCA 3-EOP-E-0, RX TRIP OR SAFETY INJECTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE US: Reviews FOP for 3

-EOP-E-0 Adverse Cntmt (Will Be Met

) RCP Trip Criteria (Not Running

) Faulted S/G Isolation Ruptured S/G Isolation AFW Sys Operation Criteria CST Makeup Water Criteria RHR System Operation Criteria (Starts a Timer) Loss of Offsite Power or SI on the Other Unit Loss of Charging Criteria FOLDOUT PAGE NOTE The action s of Attachment 3 are listed beginning on page 35. BOP: Continues with ATTACHMENT 3 to complete The Prompt Action Verifications. STEP 5 RCO: Check AFW Pumps

- AT LEAST TWO RUNNING STEP 6 BOOTH OPERATOR If asked to manually align AFW valves

, acknowledge request but take no action. If later asked status update

, report still working on it.

RCO: Verify AFW Valve Alignment - PROPER EMERGENCY ALIGNMENT (NO) Manually align Valves STEP 7 NRC EXAM SECURE INFORMATION Page 30 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG EVENT 7 - SMALL BREAK LOCA 3-EOP-E-0, RX TRIP OR SAFETY INJECTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE RCO: Verify Proper AFW Flow:

Check Narrow Range Level in at least one S/G - GREATER THAN 7%[27%]

Maintain feed flow to S/G until Narrow Range Levels between 21%[27%]

and 50% STEP 8 RCO: All RCP Thermal Barrier Alarms

- CLEAR STEP 9 RCO: Check RCS Temperatures:

Check RCPs

- ANY RUNNING (NO) Check RCS Cold Leg temperatures stable between 545°F and 547°F or trending down to 547°F (NO) IF TCOLD is decreasing, THEN perform the following: Stop dumping steam.

If cooldown continues, and is due to excessive feed flow, then reduce total feed flow to 400 gpm until Narrow Range Level greater than 7%[27%] in at least one S/G.

IF cooldown continues AND is due to excessive steam flow, THEN close Main Steamline isolation and Bypass valves.

STEP 10 NRC EXAM SECURE INFORMATION Page 31 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG EVENT 7 - SMALL BREAK LOCA 3-EOP-E-0, RX TRIP OR SAFETY INJECTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE RCO: Check PRZ PORVs, Spray Valves

, And Excess Letdown Isolated:

STEP 11 RCO: Check If RCPs Should Be Stopped:

RCPs - ANY RUNNING (NO) STEP 12 RCO: Check If S/Gs Are Faulted:

(NO) STEP 13 RCO: Check If S/G Tubes Are Ruptured:

(NO) STEP 14 RCO: If RCS Is Intact (NO) US: Perform the following:

Monitor Critical Safety Functions using 3-EOP-F-0, CRITICAL SAFETY FUNCTION STATUS TREES. INTEGRITY Critical Safety Function Status Tree is RED Go to 3-EOP-FR-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION STEP 15 NRC EXAM SECURE INFORMATION Page 32 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG EVENT 7 - SMALL BREAK LOCA 3-EOP-FR-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE US: Conducts EOP transition brief.

Directs 3-EOP-FR-P.1 response. US: Reviews FOP for 3-EOP-FR-P.1 with the crew. Containment Adverse (YES) FOLDOUT PAGE RCO: Check RCS Pressure

- GREATER THAN 275 PSIG [575 PSIG]

Step 1 PROCEDURE CAUTION Low range flow indication is NOT available when using Main Feedwater instrumentation and an alternate source of feedwater. Changes in RCS temperature and S/G level may be used to control feedwater flow.

If the AFW Pumps are the only available source of feed flow, the steam supply to the AFW Pumps needs to be maintained from at least one S/G.

PROCEDURE NOTE A Faulted S/G is any S/G that is depressurizing in an uncontrolled manner OR is completely depressurized.

RCO: Check RCS Cold Leg Temperatures decreasing (NO) Go to Step 3 Step 2 RCO: Check PRZ PORV Block Valves Step 3 RCO: Check If PRZ PORVs Should Be Closed Step 4 NRC EXAM SECURE INFORMATION Page 33 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG EVENT 7 - SMALL BREAK LOCA 3-EOP-FR-P.1, RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE RCO: Check High

-Head SI Pumps

- ANY RUNNING Step 5 RCO: Check If SI Can Be Terminated (NO) Go to Step 23 Step 6 RCO: Determine If RCS Temperature Soak Is Required (Y ES) Step 23 The scenario is terminated after the crew transitions to 3-EOP-FR-P.1 and determines a soak is required, or at the Lead Evaluator's discretion once all critical tasks have been evaluated.

• • • END OF SCENARIO ***

NRC EXAM SECURE INFORMATION Page 34 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG EVENT 8 - MOV-3-843B HHSI DISCHARGE TO COLD LEG FAILS TO AUTO OPEN 3-EOP-E-0 Attachment 3

- Prompt Action Verifications TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOP: Check Load Centers Associated With Energized 4 KV Buses

- ENERGIZED (NO 3A & 3C no power)

STEP 1 BOOTH OPERATOR When requested , trigger LOA - CLOSE MOV 140 8 & 1409. Wait 3-5 minutes and then report task complete.

BOP: Verify Feedwater Isolation:

STEP 2 BOP: Check If Main Steam Lines Should Be Isolated STEP 3 BOOTH OPERATOR If dispatched to verify MOV 142 6 and MOV-3-1427 closed, wait 3 to 5 minutes and then report the valves are closed

. BOP: Verify Containment Isolation Phase A Valve White Lights On VPB

- ALL BRIGHT (NO) Manually actuate Containment Isolation Phase A.

Dispatch Operator to verify closed MOV-3-1426, and MOV-3-1427, MOV-3-6386 (MOV-3-281 closed)

Containment Purge Valve s (fuses pulled) STEP 4 BOP: Verify Pump Operation:

At least two High

-Head SI Pumps

- RUNNING Both RHR Pumps

- RUNNING (NO) - 3 A RHR pump OOS STEP 5 NRC EXAM SECURE INFORMATION Page 35 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG EVENT 8 - MOV-3-843B HHSI DISCHARGE TO COLD LEG FAILS TO AUTO OPEN 3-EOP-E-0 Attachment 3

- Prompt Action Verifications TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOP: Verify Proper CCW System Operation:

CCW Heat Exchangers

- THREE IN SERVICE CCW Pumps

- ONLY TWO RUNNING (NO) - Starts 3C CCW pump CCW Headers

- TIED TOGETHER MOV-3-626, RCP Thermal Barrier CCW Outlet

- OPEN STEP 6 BOP: Verify Proper ICW System Operation:

Verify ICW Pumps

- AT LEAST TWO RUNNING (NO) - Starts the 3C ICW pump Verify ICW To TPCW Heat Exchanger

- ISOLATED: Check ICW Headers

- TIED TOGETHER STEP 7 BOP: Check Emergency Containment Coolers

- ONLY TWO RUNNING STEP 8 BOP: Verify Unit 3 Containment Purge Exhaust And Supply Fans

- OFF STEP 9 BOP: Verify -Containment Spray NOT Required STEP 10 BOP: Verify SI

- RESET STEP 11 NRC EXAM SECURE INFORMATION Page 36 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG EVENT 8 - MOV-3-843B HHSI DISCHARGE TO COLD LEG FAILS TO AUTO OPEN 3-EOP-E-0 Attachment 3

- Prompt Action Verifications TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE CT 2 St op Time Open MOV-3-843B During a SBLOCA

, establish at least one train of HHSI flow prior to completing 3-EOP-E-0 Attachment 3 and within 30 minutes the HHSI pump starting.

BOP: Verify SI Valve Amber Lights On VPB

- ALL BRIGHT (NO) Opens MOV-3-843B Opens MOV-3-7 44B No power to equipment powered by the 3A Bus STEP 12 BOP: Verify SI Flow:

RCS pressure

- LESS THAN 1625 PSIG[1950 PSIG]

High-Head SI Pump flow indicator

- CHECK FOR FLOW STEP 13 BOOTH OPERATOR When requested , trigger LOA - ALIGN U-4 HHSI s TO U3 RWST. Wait 5 to 7 minutes and then report task complete.

BOP: Realign SI System:

Check Procedure Entry Status

- E-0 ENTERED FROM 3

-ONOP-047.1, LOSS OF CHARGING FLOW IN MODES 1THROUGH 4 (NO) Verify Unit 3 High

-Head SI Pumps

- TWO RUNNING (NO) - Stop one Unit 4 High

-Head SI Pump and place in standby Direct Unit 4 Reactor Operator to align Unit 4 High

-Head SI Pump suction to Unit 3 RWST using Attachment 1.

STEP 14 BOP: Verify Containment Isolation Phase A

- RESET STEP 15 NRC EXAM SECURE INFORMATION Page 37 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG EVENT 8 - MOV-3-843B HHSI DISCHARGE TO COLD LEG FAILS TO AUTO OPEN 3-EOP-E-0 Attachment 3

- Prompt Action Verifications TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOP: Reestablish RCP Cooling:

Check RCPs

- AT LEAST ONE RUNNING (NO) Go to Step 17 STEP 16 BOP: Verify Control Room Ventilation Isolation:

STEP 17 BOOTH OPERATOR When requested

, trigger LOA - PLACE PAHM IN SERVICE

. Wait 3 to 5 minutes and then report task complete.

BOP: Place Hydrogen Monitors In Service Using 3-NOP-094, CONTAINMENT POST ACCIDENT MONITORING SYSTEM STEP 18 BOP: Verify All Four EDGs

- RUNNING STEP 19 BOOTH OPERATOR If asked to start one train of chilled water, acknowledge request. No action required

. BOP: Verify Power To 3A and 3B Emergency 4KV Buse s (NO) - Inform US Check 3A and 3B 4KV buses energized from offsite power.

(NO) - Start one train of Chilled Water STEP 20 BOP: Notify Unit Supervisor Of The Following:

Attachment 3 is complete Any safeguards equipment that is NOT In the required condition Status of Containment pressure continuous action STEP 21 NRC EXAM SECURE INFORMATION Page 38 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG Discussion Points are intentionally NOT included in evaluated scenarios. However, space is available below to document follow

-up questions when further information is required to determine an evaluation outcome. FOLLOW-UP QUESTIONS QUESTION #1 ________________________________________________________________________________________________________________________________________________________________________

________________________________________________________________________________

ANSWER #1 ______________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________

QUESTION #2 ________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________

ANSWER #2 ______________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________

NRC EXAM SECURE INFORMATION Page 39 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG SIMULATOR POST

-SCENARIO RESTORATION

______ 1. Restore per Simulator Operator Checklist.

______ 2. Once exams are complete, restore from SEI

-19, Simulator Exam Security.

NRC EXAM SECURE INFORMATION Page 40 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 41 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 42 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG NRC EXAM SECURE INFORMATION Page 43 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG OPERATIONS SHIFT TURNOVER REPORT UNIT 3 RISK: GREEN (ACCEPTABLE)

PROTECTED TRAIN: B UNIT 4 RISK: GREEN (ACCEPTABLE)

PROTECTED TRAIN: B ONCOMING CREW ASSIGNMENTS Shift Mgr:

Inside SNPO:

Field Supv.:

Outside SNPO:

Admin RCO:

ANPO: Unit 3 Unit 4 Unit Supv.:

Unit Supv.:

RCO: RCO: NPO: NPO: PLANT STATUS Unit 3 Unit 4 Mode: 1 Mode: 1 Power: 100% Power: 100% MWe: 8 4 2 MWe: 842 Gross Leakrate:

.22 gpm Gross Leakrate:

0.03 gpm RCS Boron Conc:

74 5 ppm RCS Boron Conc:

642 Operational Concerns:

3A RHR pump taken OOS 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago for an oil change, expected back by the end of this shift.

3A1 Circ Water pump OOS.

Tripped on over current, Electrical Maintenance is investigating.

U3 Anticipated LCO Actions:

None U4 Anticipated LCO Actions:

None Results of Offgoing Focus Area:

NRC EXAM SECURE INFORMATION Page 44 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG UNIT 3 STATUS REACTOR OPERATOR UNIT RISK: GREEN (ACCEPTABLE) PROTECTED TRAIN: B Mode: 1 RCS Leakrate Accumulator Ref Levels Power: 100% Gross: 0.22 GPM A 6656 MWe 84 2 Unidentified 0.04 GPM B 6608 Tavg: 5 80°F Charging Pps:

0.00 GPM C 6646 RCS Pressure:

2235 RCS Boron Conc:

74 5 ppm Abnormal Annunciators: Annunciator:

Comp Actions:

Annunciator:

Comp Actions:

Annunciator:

Comp Actions:

Annunciator:

Comp Actions:

Annunciator:

Comp Actions:

Annunciator:

Comp Actions:

Current Tech Spec Action Statements: (Does Not Include "For Tracking Only Items" T.S.A.S / Component:

3A RHR pump, 3.5.2.c

- Action g Reason: Oil Change Entry Date:

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago T.S.A.S / Component:

Reason: Entry Date:

T.S.A.S / Component:

Reason: Entry Date:

T.S.A.S / Component:

Reason: Entry Date:

T.S.A.S / Component:

Reason: Entry Date:

NRC EXAM SECURE INFORMATION Page 45 of 46 L-16-1 NRC EXAM SCENARIO 4 NRC EXAM SECURE INFORMATION SEG REACTOR OPERATOR (CONT'D) UNIT RISK: GREEN (ACCEPTABLE) PROTECTED TRAIN: B Changes to Risk Significant Equipment:

No recent changes from last shift.

OLRM: GREEN PROTECTED TRAIN: B Upcoming Reactivity Management Activities:

Maintain current power level 99.5% -100% Xe is stable.

Upcoming Major POD Activities:

NONE Upcoming ECOs to Hang and /or Release:

Hang - None Release - None Evolutions or Compensatory Actions in Progress:

NONE General Information, Remarks, and Operator Work Around Status:

Weather forecast is overcast skies with scattered pockets of severe rain.

U3 supplying Aux Steam Air In-leakage = 0.0 SCFM NRC EXAM SECURE INFORMATION Page 46 of 46 EXAM SECURE INFORMATION Appendix D Scenario Outline Form ES-D-1 L-16-1 N5 (Rev-0) Facility: Turkey Point Nuclear (PTN)

- Units 3 and 4 Scenario No.:

5 Op Test No.: 2016-301 Examiners:

Operators:

(SRO) (R C O) (BOP) Initial Conditions:

The plant is at 60% power (MOL). Online risk is green. B train is protected on both units. Turnover: The 3A RHR pump and 3A1 Circulating Water pump are OOS.

Event Malf. No. Event Type*

Event Description 1 TVF1M87D I-BOP I-SRO (TS) F T-3-487 3B S/G Feed Water Flow Transmitter Drifts High 2 TFCMM2H3 TFKV609O C-RCO C-SRO R-3-17B CCW Hx Radiation Monitor Fails High &

RCV-3-609 CC W Surge Tank Vent Fails To Auto Close 3 TAKD032 C-BOP C-SRO 3A TPCW Pump Cavitation 4 TFH1TV60 I-RCO I-SRO (TS) LT-3-460 Pressurizer Level Fails Low 5 TFC1DOR TFC1DOR2 R-RCO R-SRO N-BOP 3A & 3B CRDM Fan s Trip (Fast Load Reduction required) 6 TVHHSGA M-RCO M-BOP M-SRO 3A SGTR with LOOP 7 TFP1S3GC TFP8D6MT TFP8D6BT P- BOP Control Room HVAC Fails To Align on SI 8 TFHV55CO P-RCO PCV-3-445C PZR PORV , Fails To Close During E

-3 Depressurization

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor EXAM SECURE INFORMATION Page 1 of 4 EXAM SECURE INFORMATION Appendix D Scenario Outline Form ES-D-1 L-16-1 N5 (Rev-0) Scenario #5 Event 1 Shortly after the crew takes the shift FT 487 3B S/G Feed Water Flow transmitter drifts high. The BOP will take manual control of 3B S/G level and restore level to normal. The crew may use the ARP or 3-ONOP-049.1, Deviation or Failure of Safety Related or Reactor Protection, to select operable channels and restore 3B S/G level control to automatic. The US will enter 3

-ONOP-049.1 to verify all required actions are complete and to determine which bistables need to be tripped.

Event 2 After the actions of Event 1 are complete CCW Surge Tank Radiation Monitor R

-17B fails high. CCW surge tank vent valve RCV 609 fails to close on the high radiation signal. The US will enter 3-ONOP-067, Radioactive Effluent Release, to verify the failure and direct the RCO to manually close the valve. Event 3 After the actions of Event 2 are complete the crew will respond to a TPCW low pressure alarm. The BOP will report signs of cavitation and swap TPCW pumps. The US may enter 3

-ONOP-008, Turbine Plant Cooling Water Malfunction to verify all required actions are complete.

Event 4 After the crew swaps TPCW pumps Pressurizer Level transmitter LT 460 will fail low. The PZR Heaters will trip and letdown will isolate. The US will enter 3

-ONOP-041.6, Pressurizer Level Control Malfunction. The RCO will select an operable channel, re

-establish normal letdown flow, and restore PZR heaters to automatic. The US will also enter 3

-ONOP-049.1 to verify all required actions are complete and to determine which bistables need to be tripped.

Event 5 After the actions of Event 4 are complete the 3A CRDM Fan Trips and a few minutes later the 3B CRDM Fan Trips. The crew will commence a shutdown using 3

-GOP-100, Fast Load Reduction.

Event 6 After a 5 to 10% downpower a SGTR develops over a 5 minute period on the 3A S/G. The crew will take actions to maximize Charging and to isolate Letdown. When the leakage exceeds the CVCS capacity, the US will order the RCO to trip the Reactor and enter to 3

-EOP-E-0, Reactor Trip Or Safety Injection. When the Generator trips a Loss Of Offsite Power occurs. Both Emergency Diesel Generators will start and energize their respective 4KV buses. When the Ruptured S/G Isolation Criteria are met the BOP or RCO will isolate Aux Feed Water flow to the 3A S/G.

Event 7 When SI actuates Control Room Ventilation fails to align for recirc. The BOP will manually open Emergency Inlet Dampers D

-2 and D-3 per 3-EOP-E-0 Attachment 3, Prompt Action Verifications.

EXAM SECURE INFORMATION Page 2 of 4 EXAM SECURE INFORMATION Appendix D Scenario Outline Form ES-D-1 L-16-1 N5 (Rev-0) Event 8 The crew will transition from 3

-EOP-E-0 to 3-EOP-E-3, Steam Generator Tube Rupture. The crew will isolate the 3A S/G, cooldown the RCS, Establish Charging Flow, and stop the RHR pumps. When the cooldown is complete the RCO will open PZR PORV PCV 455C to depressurize the RCS (PCV 456 is failed close). When the depressurization is complete PCV 455C will fail to close so the RCO will close block valve MOV 536 to stop the depressurization.

The scenario is terminated after the crew completes the depressurization per 3

-EOP-E-3, or at the Lead Evaluator's discretion once all critical task have been evaluated.

Event Scenario Critical Tasks 6 CT1 Isolate the Ruptured S/G During a Steam Generator Tube Rupture, isolate the ruptured S/G before a the ruptured Steam Generator pressure drops below 450 psig to prevent transition to 3

-EOP-ECA-3.1, SGTR With Loss Of Reactor Coolant

-Subcooled Recovery Desired.

Safety Significance:

Isolation of the ruptured steam generator minimizes release of radioactivity from this generator. In addition, isolation is necessary to establish a pressure differential between the ruptured and non

-ruptured steam generators in order to cool the RCS and stop primary

-to secondary leakage. If any ruptured S/G cannot be isolated from at least one intact S/G, the operator is directed to go to 3

-ECA-3.1, SGTR With Loss Of Reactor Coolant

-Subcooled Recovery Desired.

6 CT2 Control Initial RCS Cooldown During a Steam Generator Tube Rupture dump steam from intact S/Gs at maximum rate to achieve Core Exit TCs less than required temperatures based on the lowest ruptured S/G pressure without causing a transition to 3

-EOP-FR-P.1, Response to Imminent Pressurized Thermal Shock Condition, or 3

-EOP-ECA-3.1, SGTR With Loss Of Reactor Coolant-Subcooled Recovery Desired.

Safety Significance: A SGTR mitigation strategy leading to a transition from 3-EOP-E-3 to a contingency procedure constitutes an incorrect performance requiring the crew to take additional compensatory actions that complicate the event mitigation strategy. With a SGTR, there exists a breach of the RCS fission

-product and Containment barriers which allows radioactive RCS inventory to leak into the SG and associated piping. Without controlling the cooldown, the primary

-to-secondary leakage is not stopped. This continued leakage results in a larger release of radioactivity to the environment affecting the safety of the public.

EXAM SECURE INFORMATION Page 3 of 4 EXAM SECURE INFORMATION Appendix D Scenario Outline Form ES-D-1 L-16-1 N5 (Rev-0) Event Scenario Critical Tasks 6 CT3 Limit RHR Time On Recirculation When a RHR Pump starts and is operating at shutoff head, limit the operating time at shutoff head with minimum flow recirculation to no more than 44 minutes

. (0-ADM-232, Time Critical Operator Action Program

-Attachment 1)

Safety Significance:

Failure to secure the RHR Pumps operating at shutoff head leads to pump overheating and adverse vibration which would constitutes incorrect crew performance in which the crew does not prevent a degradation of the emergency core cooling system (ECCS) capacity.

6 CT4 Control Initial RCS Depressurization During a Steam Generator Tube Rupture depressurize the RCS to the ruptured S/G pressure without causing a transition to 3

-EOP-FR-P.1, Response to Imminent Pressurized Thermal Shock Condition, or 3

-EOP-ECA-3.1, SGTR With Loss Of Reactor Coolant-Subcooled Recovery Desired.

Safety Significance:

A SGTR mitigation strategy leading to a transition from 3-EOP-E-3 to a contingency procedure constitutes an incorrect performance requiring the crew to take additional compensatory actions that complicate the event mitigation strategy. With a SGTR, there exists a breach of the RCS fission

-product and Containment barriers which allows radioactive RCS inventory to leak into the SG and associated piping. Without controlling the cooldown, the primary

-to-secondary leakage is not stopped. This continued leakage results in a larger release of radioactivity to the environment affecting the safety of the public.

EXAM SECURE INFORMATION Page 4 of 4 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG Site: Turkey Point Units 3 and 4 (PTN)

Title: L-16-1 NRC EXAM SCENARIO 5 LMS #: NRC 25 LMS Rev Date:

6/9/16 Rev #: 0 SEG Type: Training Evaluation Program: LOCT LOIT Other Duration: 120 minutes Developed by:

Brian Clark 8/4/16 Instructor/Developer Date Reviewed by:

Luis Sagion 8/4/16 Instructor (Instructional Review)

Date Validated by : Sean Bloom 8/5/16 SME (Technical Review)

Date Approved by:

Mark Wilson 8/5/16 Training Supervision Date Approved by:

Sean Bloom 8/5/16 Training Program Owner (Line)

Date NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG SCENARIO REFERENCES DOC NO. TITLE REV 3-EOP-E-0 REACTOR TRIP OR SAFETY INJECTION 12 3-EOP-E-3 STEAM GENERATOR TUBE RUPTURE 9 3-ONOP-028 REACTOR CONTROL SYSTEM MALFUNCTION 4 A 3-ONOP-041.5 PRESSURIZER PRESSURE CONTROL MALFUNCTION 1 3-ONOP-049.1 DEVIATION OR FAILURE OF SAFETY RELATED OR REACTOR 4 3-ONOP-059.8 POWER RANGE NUCLEAR INSTRUMENTATION MALFUNCTION 4 3-ONOP-071.2 STEAM GENERATOR TUBE LEAKAGE 11 3-OSP-059.10 DETERMINATION OF QUADRANT POWER TILT RATIO 2 A PTN TECHNICAL SPECIFICATIONS 300 NRC EXAM SECURE INFORMATION Page 2 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS Terminal Objective Given this simulator scenario and resources normally found in the Control Room, the operating crew will perform Control Room operations IAW approved plant procedures in order to maintain the integrity of the plant and the health and safety of the public.

Enabling Objectives:

Given this simulator scenario and resources normally found in the Control Room, operate in accordance with approved plant procedures, Operations Department Instructions, and management expectations:

1. (ALL) Demonstrate personnel SAFETY awareness in interactions with plant staff and outside agencies.

2. (ALL) Demonstrate ALARA awareness in interactions with plant staff and outside agencies.

3. (ALL) Exchange correct information using 3

-point communication/Repeat

-backs with Control Room personnel and other plant staff.

4. (ALL) Inform plant personnel and System of plant conditions, as needed.

5. (US) Employ timely and concise crew briefs where appropriate.

6. (ALL) Maintain awareness of plant status and control board indication.

7. (ALL) Correctly diagnose plant situations.

8. (ALL) Solve operational problems as they arise.

9. (RCO/BOP) Manipulate plant controls properly and safely.

10. (ALL) Demonstrate self

-checking using STAR and peer checks(when required)

11. (US) Demonstrate command and control of the crew.

12. (US) Coordinate the input of crew members and other plant staff.

13. (US) Utilize the input of crew members and other plant staff.

14. (ALL) Demonstrate conservative decision making.

15. (ALL) Demonstrate teamwork.

16. (ALL) Respond to plant events using procedural guidance (OPs/ONOPs/EOPs) as applicable in accordance with rules of usage.

17. (RCO/BOP) Implement any applicable procedural immediate operator actions without use of references.

18. (SRO) Maintain compliance with Tech Specs.

19. (ALL) Identify/enter applicable Tech Spec action statements.

20. (ALL) Respond to annunciators using ARPs (time permitting).

21. (ALL) Maintain written communication, logs, and documentation as needed to permit post

-event reconstruction.

Continued on next page NRC EXAM SECURE INFORMATION Page 3 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG SIMULATOR EXERCISE GUIDE REQUIREMENTS While addressing the following events:

1. FT-3-487 3B S/G Feed Water Flow Transmitter Drifts High

2. R-3-17B CCW Hx Radiation Monitor Fails High

3. 3A TPCW Pump Cavitation

4. LT-3-460 Pressurizer Level Fails Low

5. 3A & 3B CRDM Fans Trip

6. 3A SGTR with LOOP

7. Control Room HVAC Fails To Align on SI

8. PCV-3-445C PZR PORV, Fails To Close During E

-3 Depressurization Prerequisites:

None Training Resources:

PTN Unit 3 Plant Simulator Development

References:

TR-AA-220-1003, Initial N RC and Audit Exam Process TR-AA-230-1003, SAT Development TR-AA-230-1007 , Conduct of Simulator Training and Evaluation 0-ADM-232, Time Critical Action Program OP-AA-100-1000 , Conduct Of Operations OP-AA-103-1000 , Reactivity Management 0-ADM-200, Operations Management Manual 0-ADM-211, Emergency and Off

-Normal Operating Procedure Usage WCAP-17711-NP, Pressurized Water Reactor Owners Group Westinghouse Emergency Response Guideline Revision 2

-Based Critical Tasks Protected Content: N/A Evaluation Method: Performance Mode Operating Experience:

None Risk Significant Operator Actions: Limit RHR Time On Recirculation When a RHR Pump starts and is operating at shutoff head, limit the operating time at shutoff head with minimum flow recirculation to no more than 44 minutes.

NRC EXAM SECURE INFORMATION Page 4 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG TASKS ASSOCIATED WITH THIS SIMULATOR EXERCISE GUIDE SRO TASK #

TASK TITLE 02008001300 RESPOND TO TURBINE PLANT COOLING WATER (TPCW) MALFUNCTIONS 02028033500 AUTHORIZE UNIT TRIP 02041029300 EVALUATE AND RESPOND TO A LOW PRESSURIZER PRESSURE 02041057300 RESPOND TO PRESSURIZER LEVEL CONTROL CHANNEL MALFUNCTION 02067009300 RESPOND TO PROCESS RADIATION MONITOR ALARM(S) 02089026300 AUTHORIZE FAST LOAD REDUCTION 02200001500 RESPOND TO UNIT TRIP 02200006300 INVESTIGATE AND CONTROL STEAM GENERATOR TUBE LEAK 02200008500 RESPOND TO A STEAM GENERATOR TUBE RUPTURE 02200022500 DIAGNOSE CAUSE OF SAFEGUARDS ACTUATION 02200046500 RESPOND TO STEAM GENERATOR LOW LEVEL RO TASK TASK TITLE 01008001300 RESPOND TO TURBINE PLANT COOLING WATER SYSTEM MALFUNCTION 01041029300 EVALUATE AND RESPOND TO A LOW PRESSURIZER PRESSURE 01041057300 RESPOND TO PRESSURIZER LEVEL CONTROL CHANNEL MALFUNCTION 01067009300 RESPOND TO PROCESS RADIATION MONITOR ALARM(S) 01089026300 RESPOND TO / ADJUST TURBINE DURING FAST LOAD REDUCTION 01200001500 RESPOND TO UNIT TRIP 01200006300 INVESTIGATE AND CONTROL STEAM GENERATOR TUBE LEAK 01200008500 RESPOND TO A STEAM GENERATOR TUBE RUPTURE 01200022500 DIAGNOSE CAUSE OF SAFEGUARDS ACTUATION 01200046500 RESPOND TO STEAM GENERATOR LOW LEVEL NRC EXAM SECURE INFORMATION Page 5 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG UPDATE LOG:

NOTES: Place this form with the working copies of lesson plans and/or other materials to document changes made between formal revisions. For fleet

-wide training materials, keep electronic file of this form in same folder as approved materials. Refer to TR

-AA-230-1003 SAT Development for specific directions regarding how and when this form shall be used.

Indicate in the following table any minor changes or major revisions (as defined in TR

-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR-AA-230-1003-F16. # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE REVIEWER DATE 0-0 Initial Revision Revised for L-1 6-1 NRC Exam 2108338 Note 5 Note 5 Note 5 Note 5 1. Individual updating lesson plan or training material shall complete the appropriate blocks on the Update Log.

2. Describe the change to the lesson plan or training materials.

3. State the reason for the change (e.g., reference has changed, typographical error, etc.)

4. Preparer enters name/date on the Update Log and obtains Training Supervisor approval.

5. Initial dates and site approval on cover page.

NRC EXAM SECURE INFORMATION Page 6 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG Initial Conditions

The plant is at 60% power (MOL). Online risk is green. B train is protected on both units.

Equipment OOS The 3A RHR pump and 3A1 Circulating Water pump are OOS.

SCENARIO

SUMMARY

Event 1 Shortly after the crew takes the shift

, FT-3-487 , 3B S/G Feed Water Flow transmitter

, drifts high. The BOP will take manual control of 3B S/G level and restore level to normal. The crew may use the ARP or 3-ONOP-049.1, Deviation or Failure of Safety Related or Reactor Protection, to select operable channels and restore 3B S/G level control to automatic. The US will enter 3

-ONOP-049.1 to verify all required actions are complete and to determine which bistables need to be tripped.

Event 2 After the actions of Event 1 are complete

, CCW Surge Tank Radiation Monitor

, R-17B , fails high. CCW surge tank vent valve

, RCV-3-609 , fails to close on the high radiation signal. The US will enter 3-ONOP-067, Radioactive Effluent Release, to verify the failure and direct the RCO to manually close the valve. Event 3 After the actions of Event 2 are complete

, the crew will respond to a TPCW low pressure alarm. The BOP will report signs of cavitation and swap TPCW pumps. The US may enter 3

-ONOP-008, Turbine Plant Cooling Water Malfunction

, to verify all required actions are complete.

Event 4 After the crew swaps TPCW pumps

, Pressurizer Level transmitter

, LT-3-460 , will fail low. The PZR Heaters will trip and letdown will isolate. The US will enter 3

-ONOP-041.6, Pressurizer Level Control Malfunction. The RCO will select an operable channel, re

-establish normal letdown flow, and restore PZR heaters to automatic. The US will also enter 3

-ONOP-049.1 to verify all required actions are complete and to determine which bistables need to be tripped.

Event 5 After the actions of Event 4 are complete

, the 3A CRDM Fan Tri ps. A few minutes later the 3B CRDM Fan Trips. The crew will commence a shutdown using 3

-GOP-100, Fast Load Reduction.

NRC EXAM SECURE INFORMATION Page 7 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG Event 6 After a 5 to 10% downpower

, a SGT L develops over a 5 minute period on the 3A S/G. The crew will take actions to maximize Charging and to isolate Letdown in accordance with 3

-ONOP-071.2. When the leakage exceeds the CVCS capacity, the US will order the RCO to trip the Reactor and enter to 3

-EOP-E-0, Reactor Trip Or Safety Injection. When the Generator trips a Loss Of Offsite Power occurs. Both Emergency Diesel Generators will start and energize their respective 4KV buses. When the Ruptured S/G Isolation Criteria are met

, the BOP or RCO will isolate Aux Feed Water flow to the 3A S/G.

Event 7 When SI actuates

, Control Room Ventilation fails to align for recirc. The BOP will manually open Emergency Inlet Dampers D

-2 and D-3 per 3-EOP-E-0 Attachment 3, Prompt Action Verifications.

Event 8 The crew will transition from 3

-EOP-E-0 to 3-EOP-E-3, Steam Generator Tube Rupture. The crew wi ll isolate the 3A S/G, cooldown the RCS, Establish Charging Flow, and stop the RHR pumps. When the cooldown is complete the RCO will open PZR PORV

, PCV-3-455C , to depressurize the RCS (PCV 456 is failed close). When the depressurization is complete

, PCV-3-455C will fail to close so the RCO will close block valve MOV 536 to stop the depressurization.

The scenario is terminated after the crew completes the depressurization per 3

-EOP-E-3, or at the Lead Evaluator's discretion

, once all critical task s have been evaluated.

Event CRITICAL TASKS 6 CT1 Isolate the Ruptured S/G During a Steam Generator Tube Rupture

, isolate the ruptured S/G before a the ruptured Steam Generator pressure drops below 450 psig to prevent transition to 3

-EOP-ECA-3.1, SGTR With Loss Of Reactor Coolant

-Subcooled Recovery Desired

. Safety Significance:

Isolation of the ruptured steam generator minimizes release of radioactivity from this generator. In addition, isolation is necessary to establish a pressure differential between the ruptured and non

-ruptured steam generators in order to cool the RCS and stop primary

-to secondary leakage. If any ruptured S/G cannot be isolated from at least one intact S/G, the operator is directed to go to 3

-ECA-3.1, SGTR With Loss Of Reactor Coolant -Subcooled Recovery Desired.

NRC EXAM SECURE INFORMATION Page 8 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG Event CRITICAL TASKS 6 CT2 Control Initial RCS Cooldown During a Steam Generator Tube Rupture

, dump steam from intact S/Gs at maximum rate to achieve Core Exit TCs less than required temperatures based on the lowest ruptured S/G pressure without causing a transition to 3

-EOP-FR-P.1, Response to Imminent Pressurized Thermal Shock Condition, or 3

-EOP-ECA-3.1, SGTR With Loss Of Reactor Coolant-Subcooled Recovery Desired.

Safety Significance: A SGTR mitigation strategy leading to a transition from 3-EOP-E-3 to a contingency procedure constitutes an incorrect performance requiring the crew to take additional compensatory actions that complicate the event mitigation strategy. With a SGTR, there exists a breach of the RCS fission

-product and Containment barriers which allows radioactive RCS inventory to leak into the SG and associated piping. Without controlling the cooldown, the primary

-to-secondary leakage is not stopped. This continued leakage results in a larger release of radioactivity to the environment affecting the safety of the public.

6 CT3 Limit RHR Time On Recirculation When a RHR Pump starts and is operating at shutoff head, limit the operating time at shutoff head with minimum flow recirculation to no more than 44 minutes

. (0-ADM-232, Time Critical Operator Action Program

-Attachment 1)

Safety Significance:

Failure to secure the RHR Pumps operating at shutoff head leads to pump overheating and adverse vibration which would constitutes incorrect crew performance in which the crew does not prevent a degradation of the emergency core cooling system (ECCS) capacity.

8 CT4 Control Initial RCS Depressurization During a Steam Generator Tube Rupture

, depressurize the RCS to the ruptured S/G pressure without causing a transition to 3

-EOP-FR-P.1, Response to Imminent Pressurized Thermal Shock Condition, or 3

-EOP-ECA-3.1, SGTR With Loss Of Reactor Coolant-Subcooled Recovery Desired.

Safety Significance:

A SGTR mitigation strategy leading to a transition from 3-EOP-E-3 to a contingency procedure constitutes an incorrect performance requiring the crew to take additional compensatory actions that complicate the event mitigation strategy. With a SGTR, there exists a breach of the RCS fission

-product and Containment barriers which allows radioactive RCS inventory to leak into the SG and associated piping. Without controlling the cooldown, the primary

-to-secondary leakage is not stopped. This continued leakage results in a larger release of radioactivity to the environment affecting the safety of the public

. NRC EXAM SECURE INFORMATION Page 9 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG SEQUENCE OF EVENTS Event # Description

1. FT-3-487 3B S/G Feed Water Flow Transmitter Drifts High

2. R-3-17B CCW Hx Radiation Monitor Fails High

3. 3A TPCW Pump Cavitation

4. LT-3-460 Pressurizer Level Fails Low

5. 3A & 3B CRDM Fans Trip

6. 3A SGTR with LOOP 7. Control Room HVAC Fails To Align on SI

8. PCV-3-445C PZR PORV, Fails To Close During E

-3 Depressurization NRC EXAM SECURE INFORMATION Page 10 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG SIMULATOR SET UP INSTRUCTIONS Check Action ____ Restore IC

-24 (60% MOL) or equivalent IC.

____ Place the Simulator in RUN. ____ Stop the 3A1 Circ Water Pump

____ Open & execute lesson file L

-1 6-1 N 5 ____ Ensure the following lesson steps are triggered:

SETUP - 3A RHR PUMP OOS SETUP - 3A1 CWP OOS SETUP EVENT 2

- RCV-609 FAILED OPEN SETUP EVENT 7

- CONTROL ROOM VENTILATION FANS FAIL TO START SETUP EVENT 8

- PORV 456 FAILED CLOSE

____ Place the 3A RHR pump in PTL and hang an ECO tag.

Place the 3 A 1 CWP in STOP and hang an ECO tag.

____ Verify the trend for 3A1 Screen on the TWS DP Recorder is clear.

____ Ensure Rod Group Step Counters have completed stepping out.

____ Allow the plant to stabilize.

____ Acknowledge any alarms and freeze Simulator.

____ Ensure B train is protected train on VPA.

____ Perform the SIMULATOR OPERATOR CHECKLIST or equivalent.

____ Place TURNOVER SHEETS on RO's desk or give to the Lead Evaluator.

NRC EXAM SECURE INFORMATION Page 11 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG BRIEFINGS Shift turnover information is attached to the back of this guide.

Ensure all applicants are prior briefed on Appendix E of NUREG 1021, Policies and Guidelines For Taking NRC Examinations.

Conduct a Crew Pre-brief to cover turnover information. Shift turnover information is attached to the back of this guide.

US: RCO: BOP:

SCENARIO NOTE 0-ADM-211 Prudent Operator Actions

- If redundant stand

-by equipment is available and ready, the operator is permitted to start the redundant equipment for failed or failing operating equipment.

Immediate follow up of applicable ARPs and ONOPs (AOPs) shall occur as required.

NRC EXAM SECURE INFORMATION Page 12 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG Critical Tasks are highlighted in pink. Simulator Operator Actions are highlighted in blue.

Operator Verifiable Actions are Highlighted in green EVENT 1 - FT-3-487 3B S/G FEED WATER FLOW TRANSMITTER DRIFTS HIGH 3-ONOP-049.1, DEVIATION OR FAILURE OF SAFETY RELATED OR REACTOR PROTECTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE NOTE Ensure the Simulator is in RUN before the crew enters the Simulator.

US: Conducts shift turnover.

BOOTH OPERATOR When directed by Lead Evaluator, trigger EVENT 1 - FT-3-487 DRIFTS HIGH BOP: Recognizes and reports FT-3-487 failure. PROMPT ACTIONS Takes manual control of 3 B S/G level control valve

, FCV-3-4 8 8. Restores 3 B S/G level to normal.

RCO: Addresses Alarm Response for C4/2 & C6/2 CHECK LI-3-486 or LI-3-488, B STM GEN LEVEL , controlling channel for SG Level deviation. CHECK Feedwater Controllers

, FIC-3-4 88A or FIC-3-4 8 8B , for indications of failure, alarm, or input signal failures.

CHECK Feedwater Controller Inputs IF alarm is due to instrument failure, THEN REFER TO 3-ONOP-049.1, Deviation or Failure of Safety Related or Reactor Protection Channels.

US: Enters and directs actions of 3

-ONOP-049.1, Deviation or Failure of Safety Related or Reactor Protection Channels, for response. NRC EXAM SECURE INFORMATION Page 13 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 1 - FT-3-487 3B S/G FEED WATER FLOW TRANSMITTER DRIFTS HIGH 3-ONOP-049.1, DEVIATION OR FAILURE OF SAFETY RELATED OR REACTOR PROTECTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE NOTE The crew may use the ARP to select an operable channel and restore automatic level control.

BOP: Verify F T-3-4 87 failure by channel check comparison.

Verify no off

-normal conditions exist on F T-3-4 8 6. Place 3B S/G Feed Water Flow Control Transfer Switch to FT 486 (Yellow)

Place 3 B S/G Steam Flow Control Transfer Switch to FT 4 8 5 (Yellow) Ensure 3 B S/G level is returned to auto.

Steps 5.1

- 5.4 BOOTH OPERATOR WCC/I&C: Acknowledge the report. I&C would like to be present when bistables are tripped. They will be in the control in one hour.

If asked to locally check FT 487 , wait 2 to 3 minutes and then report nothing visibility wrong.

BOP: Notifies WCC to initiate PWO and I&C for troubleshooting.

BOOTH OPERATOR If dispatched to reset AMSAC , wait 2 to 3 minutes and then trigger EVENT 1

- RESET AMSAC US: Reviews Tech Specs LCO 3.3.1 Functional Unit 12

- Action 6 within 6 h ours trip bi

-stables Step 5.5 - 5.6 LEAD EVALUATOR After S/G level control is restored to auto and the US has reviewed Tech Specs , at the Lead Evaluators discretion, direct the Booth Operator to trigger the next event. US: Conducts crew brief.

NRC EXAM SECURE INFORMATION Page 14 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 2 - R-3-17B CCW HX RADIATION MONITOR FAILS HIGH 3-ONOP-067 , RADIOACTIVE EFFLUENT RELEASE TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOOTH OPERATOR When directed by Lead Evaluator, trigger EVENT 2 - R-17B FAILS HIGH BOOTH OPERATOR When the RCO closes RCV-3-609, verify EVENT 2 - ALLOW RCV-609 TO CLOSE MANUALLY triggers.

BOP: Reviews ARP for H 1/4 IF alarm is on R

-17A/B, then REFER to 3-ONOP-067, Radioactive Effluent Release, for expected automatic actions. CHECK alarm valid as follows:

- CHECK FAIL/TEST light NOT LIT. - PUSH FAIL/TEST light (meter reading of 288 or 289K)

- PUSH SOURCE CHECK light (should get meter increase).

- PUSH HIGH ALARM light to determine if meter level is above high alarm setpoint US: Enter and direct the actions of 3

-ONOP-067, Radioactive Effluent Release US: Review the Foldout Page Notify plant personnel IF a Reactor Trip occurs AND any following PRMS alarms Actuate, THEN within 30 minutes of the alarm, manually align Control Room ventilation in the Emergency Recirculation Mode R

-15/19/20 IF any PRMS high alarm occurs AND automatic actions are required, THEN verify the applicable automatic actions for the occurring PRMS HIGH ALARMS: - R-17A/B HIGH ALARM, RCV 609, CCW Head Tank Vent Valve

- CLOSED NRC EXAM SECURE INFORMATION Page 15 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 2 - R-3-17B CCW HX RADIATION MONITOR FAILS HIGH 3-ONOP-067 , RADIOACTIVE EFFLUENT RELEASE TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE RCO: Closes RCV 609, CCW Head Tank Vent Valve, per fold out page.

BOP: Check High Alarm On R

-17B STEP 1 NOTE Parts of this step may have been completed using the ARP.

BOP: Check R17B readout GREATER THAN OR EQUAL TO ALARM SETPOINT Check channel operability as follows

- Depress and hold FAIL/TEST pushbutton on affected PRMS Channel - Check readout

- EQUAL TO 288K OR 289K - Release FAIL/TEST pushbutton Check affected PRMS drawer responds to source check Check for PRMS channel failure

- Check Fail indicator

- OFF - Display and recorder reading

- NOT FAILED LOW STEP 2 BOOTH OPERATOR Acknowledge reports to SM, RP and Chemistry. If asked to survey or sample CCW for elevated radiation

, wait 3 to 5 minutes and then report all radiation levels are normal.

US: Notify the Shift Manager of problem with R-17B. Direct Radiation Protection Shift Supervisor to conduct radiological surveys to confirm validity of alarm.

Direct Chemistry to perform sampling to confirm validity of alarm.

STEP 2 RNO NRC EXAM SECURE INFORMATION Page 16 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 2 - R-3-17B CCW HX RADIATION MONITOR FAILS HIGH 3-ONOP-067 , RADIOACTIVE EFFLUENT RELEASE TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE NOTE The US may discontinue use of 3-ONOP-067 once it

's determined that an actual high radiation condition does not exist. BOP: Check R-17A and R-17B High Alarms - OFF (NO) Go to Step 29 STEP 3 RCO: Check CCW System For High Activity Announce the high radiation alarm on page system and warn personnel to remain clear of all CCW piping Verify RCV 609, CCW Head Tank vent Valve

- CLOSED Direct Chemistry Department to sample CCW System to determine its activity level Route any known CCW system leakage to the WHUT floor drain STEP 29 Crew: Check Normal CCW Temperatures And Flows Out Of RCP Thermal Barriers Check Normal CCW Temperature And Flow Out Of NRHX Check Normal CCW Temperature And Flow Out Of Seal Water Heat Exchanger Check Normal CCW Temperature And Flow Out Of In

-Service Spent Fuel Pit HXs Check Normal CCW Temperature And Flow Out Of Excess Letdown HX Check 3A RHR Pump AND 3A RHR Heat Exchanger

- IN SERVICE (NO) - Go to step 37 STEP 30 - 35 NRC EXAM SECURE INFORMATION Page 17 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 2 - R-3-17B CCW HX RADIATION MONITOR FAILS HIGH 3-ONOP-067 , RADIOACTIVE EFFLUENT RELEASE TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE LEAD EVALUATOR Once the crew has verified the operability of the R-17B , go to the next event at your discretion.

RCO: Check 3B RHR Pump AND 3B RHR Heat Exchanger

- IN SERVICE (NO) Go to step 39 STEP 37 NRC EXAM SECURE INFORMATION Page 18 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 3 - 3A TPCW PUMP CAVITATION 3-ONOP-008, TURBINE PLANT COOLING WATER MALFUNCTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOOTH OPERATOR When directed by Lead Evaluator, trigger EVENT 3 - 3A TPCW PUMP CAVITATION.

BOP: Reports 3A TPCW amps and TPCW pressure fluctuating.

BOOTH OPERATOR If dispatched to check the 3A TPCW while it's running , wait 2 to 3 minutes and then report it sounds like its cavitati ng. If the 3A TPCW pump is stopped when you arrive , report it looks okay.

If asked to check out the 3B TPCW for a start , report it is ready to start. Once the pump is running

, report SAT start.

If WCC or maintenance is contacted acknowledge request for additional support. RCO: Reviews ARP I5/4 Use DCS to check TPCW Temperature IF TPCW header low pressure condition exists:

- START standby TPCW pump

- MONITOR pump amp indication on 3C04. - Locally CHECK for system leakage, including TPCW Supplemental Cooling Chiller(s)

REFER TO 3-ONOP-008, Turbine Plant Cooling Water Malfunction.

LEAD EVALU ATOR Once the TPCW pumps are swapped, move to the next event at your discretion.

BOP: Starts 3B TPCW pump Stops 3A TPCW pump NOTE The US may choose not to enter 3-ONOP-008 if the TPCW pumps are swapped per the ARP.

US: Enter and direct the actions of 3-ONOP-008. NRC EXAM SECURE INFORMATION Page 19 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 3 - 3A TPCW PUMP CAVITATION 3-ONOP-008, TURBINE PLANT COOLING WATER MALFUNCTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOOTH OPERATOR If dispatched to check TPCW equipment , report all system parameters to be normal. If asked for specific values

, use the simulator drawing or DCS to report actual value

. BOP: Check All Turbine Plant Cooling Water Pump Alarms

- OFF Verify Turbine Plant Cooling Water Pumps - AT LEAST ONE RUNNING Check Turbine Plant Cooling Water Header Pressure I5/4, TPCW HI TEMP/LO PRESS NOT LIT Check Proper Intake Cooling Water Lineup To Turbine Plant Cooling Water Heat Exchangers Check For Abnormal Surge Tank Level (NO) - Go to Step 12 STEPs 1-5 BOP: Check Cooling To Turbine Plant Cooling Water Heat Exchangers Locally Verify Turbine Plant Cooling Water Basket Strainer P - LESS THAN 1.5 PSID Check GEN RTD HI

-HI TEMP - OFF Check Generator Alarms - OFF Check Pump Alarms

- OFF Check Proper Turbine Plant Cooling Water System Operation Check Temperature Of Components Supplied By Turbine Plant Cooling Water - STABLE OR DECR EASING Go To Appropriate Plant Procedure As Determined By Shift Manager STEPs 12-17 NRC EXAM SECURE INFORMATION Page 20 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 4 - LT-3-460 PRESSURIZER LEVEL FAILS LOW 3-ONOP-041.6, PRESSURIZER LEVEL CONTROL MALFUNCTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOOTH OPERATOR When directed by the Lead evaluator

, trigger EVENT 4 - LT-3-460 FAILS LOW RCO: Reports LT-3-4 60 failed low NOTE Failure of LT-3-460 will cause Letdown to isolate and PZR Heaters to de

-energize. BOP: Acknowledges A8/4 , A9/4 CHECK LI-459A/460/461 less than or equal to 6%

. Check LCV-3-460, and CV 200A/B/C closed

. CHECK Control and Backup heaters OFF Recommends entry into 3-ONOP-041.6, Pressurizer Level Control Malfunction.

US: Directs 3-ONOP-041.6 response

. PROCEDURE NOTE If Pressurizer Level Malfunction is a result of a failure of the 3

-459CX or 3

-460CX relays (as indicated by a loss of letdown flow with a loss of Pressurizer Heaters with no concurrent failure of Level Transmitters 3

-459A, 3-460, 3-461), use 3

-ONOP-003.6 Attachment 4, for 3

-460CX failure, OR 3-ONOP-003.9 Attachment 4, for 3

-459CX failure as guidance for establishing Letdown flow and Pressurizer Heaters.

If the button on relays 3

-459CX or 3

-460CX are used to restore Letdown flow and Pressurizer Heaters, comply with Tech Spec Action Statement 3.4.3 Action b.

If the manual control of Heaters from the Electrical Penetration Room is used, comply with Tech Spec Action Statement 3.4.3 Action a.

NRC EXAM SECURE INFORMATION Page 21 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 4 - LT-3-460 PRESSURIZER LEVEL FAILS LOW 3-ONOP-041.6, PRESSURIZER LEVEL CONTROL MALFUNCTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE RCO: Check Pressurizer level indicators LI 459A, LI-3-460 AND LI 461 Selects ch 1 & 3 PZR level control (Position

2) Maintains PZR level on program per 3-ONOP-041.6, Enclosure 1 May place Master Charging Pump Controller, LC 459G , in manual May Start or Stop one charging pump as required.

Place LR-3-459 Channel Select Pressurizer Level Recorder to position 1 or 3. Steps 5.1

- 5.4 NOTE This failure may cause VCT Auto Makeup. RCO: Restore Letdown Flow Place LC-3-459G, Pzr Lvl Inst Man/Auto Station, in Manual AND adjust charging flow as required for increased letdown flow.

Throttle Low Pressure LTDN Controller, PCV 145, as necessary to prevent LTDN relief valve from lifting. Manually control Low Pressure Letdown Control Valve, PCV 145, to limit pressure spike.

Open High Pressure L/D Isol Vlv from Loop B Cold Leg

, LCV-3-460. Open L/D Isolation Valves, CV 200 A, B, or C as required to restore pressurizer level to programmed level.

Return Lower Pressure Letdown Control Valve, PCV 145 , to Automatic.

STEP 5.5 NRC EXAM SECURE INFORMATION Page 22 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 4 - LT-3-460 PRESSURIZER LEVEL FAILS LOW 3-ONOP-041.6, PRESSURIZER LEVEL CONTROL MALFUNCTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE RCO: N/A STEP 5.6 RCO: Restore PRZ heaters to automatic operation or take manual control.

Maintain pressurizer level to be consistent with programmed level as indicated in Enclosure 1.

WHEN desired, THEN place LC 459G in Automatic.

STEPs 5.7

- 5.8 US: Perform actions required by 3

-ONOP-049.1, Deviation or Failure of Safety Related or Reactor Protection Channels.

Step 5.9 NRC EXAM SECURE INFORMATION Page 23 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 4 - LT-3-460 PRESSURIZER LEVEL FAILS LOW 3-ONOP-049.1, DEVIATION OR FAILURE OF SAFETY RELATED OR REACTOR PROTECTION CHANNELS TIME EVALUATOR ACTIVITIES & NOTEs EXPECTED STUDENT RESPONSE US: Enters and directs actions of 3

-ONOP-049.1, Deviation or Failure of Safety Related or Reactor Protection Channels, for response BOP: Verify LT-3-460 failure by comparison with L T-3-459/461 and known plant parameters and conditions Verify no off-normal conditions exist on L T-3-459/461 Verify ch 1 & 3 PZR level control i n (Position

2) Verify LR-3-459 Channel Selected to Pressurizer Level Recorder to position 1 or 3 Verify PZR level control function is returned to automatic

. Steps 5.1

- 5.5 BOOTH OPERATOR If asked , I&C would like to be present when bi-stables are tripped

. They will be in the control room in one hour.

US Reviews TECH Specs Tech Spec 3.3.

-1 Functional Unit 9 not met. - Action 13 , inoperable channel must be placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

BOOTH OPERATOR WCC/I&C: Acknowledge the report.

I f asked , I&C would like to be present when bi-stables are tripped. They will be in the control room in one hour.

US Notifies WCC to initiate PWO and I&C for troubleshooting.

Notifies Plant Management IAW 0

-ADM-115. LEAD EVALUATOR After the PZR level control is restored to auto and the US completes a review of Tech Specs, proceed to the next event at the Lead Evaluators discretion US: Conducts crew brief.

NRC EXAM SECURE INFORMATION Page 24 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 5 - 3A & 3B CRDM FANS TRIP 3-GOP-100, FAST LOAD REDUCTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOOTH OPERATOR When directed by the Lead evaluator

, trigger EVENT 5 - CRDM FANS TRIP NOTE The 2 nd fan trips 60 seconds after the first fan. BOOTH OPER ATOR If dispatched to check CRMD fan breakers , wait 2 to 3 minutes and report breakers tripped. If asked to reset them

, report they will not reset.

BOP: Reviews ARP I8/5 CHECK indicating lights to determine affected CRDM Cooler on VPB.

TAKE affected CRDM Cooler control switch to OFF.

ENSURE remaining CRDM Cooler in service. IF neither fan will start, THEN PERFORM the following commence shutdown using 3

-GOP-100, Fast Load Reduction.

NOTE Attachment 3 is available on Page

49. Attachment 4 is available on Page

50. US: Directs actions to reduce Rx power per 3-GOP-100. Completes Attachment 3 Brief the crew per Attachment 4 Steps 1-2 US: Reviews Foldout page with crew.

3-EOP-E-0 Transition Criteria Notify Chemistry Department Boration Stop Criteria Restore Blender to AU TO FOLDOUT PAGE NRC EXAM SECURE INFORMATION Page 25 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 5 - 3A & 3B CRDM FANS TRIP 3-GOP-100, FAST LOAD REDUCTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOOTH OPERATOR Acknowledge notifications.

BOP: Notify The Following Of Fast Load Reduction System Dispatcher Plant personnel using the Page Boost Chemistry to start RCS sampling is required according to Tech Spec Table 4.4-4. Ste p 3 RC O: Begin Boration For Initial Tavg Effect Set the Boric Acid Totalizer to total boric acid volume value determined on Attachment 3.

Place the Reactor Makeup Selector Switch to BORATE.

Place the RCS Makeup Control Switch to START.

Adjust FC-3-113A, Boric Acid Flow Controller

, to achieve 40 gpm boric acid flow as indicated on FR 113. WHEN Tavg begins to lower from the boration, THEN adjust FC-3-113A, Boric Acid Flow Controller

, to load reduction value from Attachment 3.

Step 4 US: Determine Turbine Load Reduction in MW CNTRL Ste p 5 NRC EXAM SECURE INFORMATION Page 2 6 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 5 - 3A & 3B CRDM FANS TRIP 3-GOP-100, FAST LOAD REDUCTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOP: Initiate Turbine Load Reduction in MW CNTRL Select MW CNTRL Set TARGET power level

- MW VALUE from Attachment 3 Set RAMP RATE

- MW/M VALUE FROM Attachment 3.

Check Tavg has lowered 1° to 2°F from the initial value prior to boration.

Depress GO Ensure FC-3-113A, Boric Acid Flow Controller, has been adjusted to the load reduction boration rate.

Go to Step 10 Step 6 NOTE Enclosure 1 is available on Page

51. BOP: Monitor Load Reduction Adjusts power reduction rate to maintain Tavg/Tref within limits of Attachment 3.

Monitors S/G level control to ensure feed reg valves properly maintain level control in automatic

. Refer to Enclosure 1 for expected alarms. Step 10 BOOTH OPERATOR Respond as SNPO. If asked, idle Charging Pump ready for start.

RCO: Maintain pressurizer level to ensure that automatic pressurizer level control maintains level on program

. If needed , starts 2 nd Chg Pp and places 2 nd orifice in service.

Adjusts boration rate to maintain Tavg/Tref within +/-4°F T. Refer to Enclosure 1 for expected alarms. Step 10 NRC EXAM SECURE INFORMATION Page 27 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 5 - 3A & 3B CRDM FANS TRIP 3-GOP-100, FAST LOAD REDUCTION TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE RCO: Monitor Boration Rate Monitor for excessive rod movement by monitoring TR 409D, Rod Position Bank D. Determine if Insertion Limit and Bank D position are converging at a rate that will cause rod insertion limit alarms. Adjust power reduction rate as needed to control rod insertion Increase boration rate and/or total amount as necessary to limit control rod insertion Step 11 RCO: Monitor Annunciator B 8/1, ROD BANK LO LIMIT

- CLEAR Monitor B 8/2 ROD BANK A/B/C/D EXTRA LO LIMIT - CLEAR Steps 12-13 BOOTH OPERATOR Acknowledge notific ation to refer to E-Plan and ADM

-115. US: Have SM refer to t he following procedures: 0-EPIP-20101, DUTIES OF EMERGENCY COORDINATOR 0-ADM-115, NOTIFICATION OF PLANT EVENTS Step 14 LEAD EVALUATOR Once power has been reduced by a minimum of 5%, at the Lead Evaluators discretion, proceed to the next Event

. RCO: Energize Pressurizer Backup Heaters Step 15 NRC EXAM SECURE INFORMATION Page 28 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 6 - 3A SGTR WITH LOO P 3-ONOP-071.2 , STEAM GENERATOR TUBE LEAKAGE TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE NOTE The tube rupture ramps in over 5 minute

s. The crew will meet conditions to trip in ~ 2 minutes. The US may direct actions to maximize charging, isolate letdown

, and trip the Reactor without enter 3-ONOP-071.2. BOOTH OPERATOR When directed by the Lead Evaluator

, trigger EVENT 6 - 3A SGTR BOP: Reviews ARP for H1/4 , PRMS HI RADIATION Checks alarm on R

-15 REFER TO 3

-ONOP-071.2, Steam Generator Tube Leakage. Check S/G Feedwater flows and levels for indication of a Ruptures S/G.

RCO: Checks PZR pressure and level for indication of a S/G Tube Rupture.

US: Enters and directs the actions of 3-ONOP-071.2, Steam Generator Tube Leakage. US: Reviews the Foldout page with the crew.

3-EOP-E-0 Transition Criteria Control Room Ventilation Manual Isolation Criteria Turbine Load Within 10% Of Target Power Level Blowdown Release Path Isolation A FW Steam Supply Release Path Isolation NRC EXAM SECURE INFORMATION Page 29 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 6 - 3A SGTR WITH LOO P 3-ONOP-071.2 , STEAM GENERATOR TUBE LEAKAGE TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE RCO: Check PRZ level - STABLE OR INCREASING Start additional charging pumps as required. Reduce letdown flow as necessary.

IF PRZ level can NOT be maintained, THEN manually trip the reactor AND go to 3-EOP-E-0, REACTOR TRIP OR SAFETY INJECTION.

Step 1 BOP: Check R-15 High Alarm light

- ON Check PRMS Channel R

-15 Alarm Valid As Follows Check PRMS Channels R

-19 For Proper Operation Step 2 - 4 NRC EXAM SECURE INFORMATION Page 30 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 6 - 3A SGTR WITH LOOP 3-EOP-E-0, RX TRIP OR SAFETY INJECTION TIME TIME TIME NOTE 1. When the Generator trips, a Loss Of Offsite Power occurs and both Emergency Diesel Generators start and energize their respective 4KV buses. 2. When SI actuates

, Control Room Ventilation fails to align for recirc.

US: Directs 3-EOP-E-0 response after auto Reactor trip.

OR Directs RCO to manually trip the Reactor, then for operators to perform their IOA's.

RCO: Manually trips Reactor.

Manually actuates SI and Phase A NOTE Steps 1 - 4 of 3-EOP-E-0 are Immediate Operator Actions (IOAs). The board operators will call out the high level steps of the IOAs as each step is completed from memory.

Once the IOAs are complete , the US will read th rough Steps 1 - 4 with the crew.

RO/BOP: Perform IOA's.

CT 3 Start Time NOTE 3B RHR pumps will start when SI actuates. Record the time for verification of CT 3 to secure RHR pumps within 44 minutes. RCO: Verifies Reactor Trip STEP 1 BOP: Verify Turbine Trip STEP 2 BOOTH OPERATOR When the GEN MID BKR OPENS

, verify EVENT 6 LOOP triggers

. BOP: Verifies Power To Emergency 4 KV Buses STEP 3 RCO: Checks If SI Is Actuated STEP 4 NRC EXAM SECURE INFORMATION Page 31 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 6 - 3A SGTR WITH LOOP 3-EOP-E-0, RX TRIP OR SAFETY INJECTION TIME TIME TIME RCO: Checks if SI is required:

Manually actuate SI.

Manually actuate Containment Isolation Phase A.

STEP 4 RNO US: Directs 3-EOP-E-0 response and reviews the IOAs. CT1 Isolate the Ruptured S/G Closing CV-3-2816 & CV-3-283 1 is part of CT 1. US: Reviews FOP for 3

-EOP-E-0 with the crew

1. Adverse Containment Conditions

2. RCP Trip Criteria

3. Faulted S/G Isolation Criteria

4. Ruptured S/G Isolation Criteria (YES) When 3 A S/G narrow range level is greater than 7%[27%], close CV 2816 & CV-3-2831 5. AFW System Operation Criteria

6. CST Makeup Water Criteria

7. RHR System Operation Criteria (YES, RCO starts timer)

8. Loss Of Offsite Power Or SI On Other Unit 9. Loss Of Charging Criteria FOLDOUT PAGE PROCEDURE NOTE Hydrogen monitors should be in service within 30 minutes of a valid SI signal.

NOTE Attachment 3 actions start on page

43. BOP: Continues with ATTACHMENT 3 to complete The Prompt Action Verifications.

STEP 5 NRC EXAM SECURE INFORMATION Page 32 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 6 - 3A SGTR WITH LOOP 3-EOP-E-0, RX TRIP OR SAFETY INJECTION TIME TIME TIME . RCO: Check AFW Pumps

- AT LEAST TWO RUNNING. STEP 6 RCO: Verify AFW Valve Alignment

- PROPER EMERGENCY ALIGNMENT STEP 7 RCO: Verify Proper AFW Flow:

STEP 8 RCO: Check all RCP Thermal Barrier Alarms clear. (A 1/1, 1/2 and 1/3)

STEP 9 RCO: Check any RCPs running.

(No) Check RCS Cold Leg temperatures between 545 F and 547F or trending down to 547F. (NO) - Stop dumping steam.

- Reduce AFW flow

- Close MSIVs STEP 10 RCO: Check PRZ PORVs, Spray Valves And Excess Letdown Isolated:

STEP 11 RCO: Check If RCPs Should Be Stopped:

(Not Running) STEP 12 RCO: Check If S/Gs Are Faulted: (NO Go to Step 14) STEP 13 NRC EXAM SECURE INFORMATION Page 33 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 6 - 3A SGTR WITH LOOP 3-EOP-E-0, RX TRIP OR SAFETY INJECTION TIME TIME TIME BOOTH OPERATOR If Chemistry or RP is called, report local secondary radiation readings and samples a re highest on 3 A SG. RCO: Check If S/G Tubes Are Ruptured: (YES for 3 A SG) STEP 14 US: Monitor Critical Safety Functions using 3-EOP-F-0, CRITICAL SAFETY FUNCTION STATUS TREES Go to 3-EOP-E-3, STEAM GENERATOR TUBE RUPTURE, Step 1 NRC EXAM SECURE INFORMATION Page 34 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 6 - 3A SGTR with LOOP 3-EOP-E-3, STEAM GENERATOR TUBE RUPTURE TIM E EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE CT 3 Stop Time NOTE The crew may wait until 3-EOP-E-3 step 10 to Stop RHR Pumps.

Limit RHR Time On Recirculation When a RHR Pump starts and is operating at shutoff head, limit the operating time at shutoff head with minimum flow recirculation to no more than 44 minutes.

[0-ADM-232, Time Critical Operator Action Program

- Attachment 1]

US: Directs 3-EOP-E-3 response.

Reviews Foldout Page Adverse Containment Setpoints RCP Trip Criteria SI Re-Initiation Criteria Secondary Integrity Criteria Cold Leg Recirculation Switchover Criteria CST Makeup Water Criteria Multiple Tube Rupture Criteria Loss Of Offsite Power Or SI On Other Unit. If RHR flow is less than 1100 gpm, then the RHR Pumps shall be shut down within 44 minutes of the initial start signal.

FOP RCO: Checks If RCPs Should Be Stopped STEP 1 BOOTH OPERATOR If called as RP, report the radiation readings on 3 A SG lines are higher than normal. RCO: Identify Ruptured S/G: Identif y 3 A as the Ruptured S/G Directs RP to take rad readings on Main Steam and Blowdown Lines Evaluates DAM1 on DCS Determines ruptured SG by level increase or radiation STEP 2 NRC EXAM SECURE INFORMATION Page 35 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 6 - 3A SGTR with LOOP 3-EOP-E-3, STEAM GENERATOR TUBE RUPTURE TIM E EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE CT 1 Isolate the Ruptured S/G Adjusting 3 A S/G Steam Dump To Atmosphere controller setpoint to 1060 psig and verifying it goes closed is part of CT 1. RCO: Isolate Flow From Ruptured S/G Adjusts 3 A S/G Steam Dump To Atmosphere controller setpoint to 1060 psig Checks 3 A S/G Steam Dump To Atmosphere Closed.

WHEN ruptured S/G pressure is less than 1060 psig, THEN Verify S/G Steam Dump to Atmosphere is closed. STEP 3.a/b CT 1 BOOTH OPERATOR When directed to de

-energize MOV 1403 BKR 4D01

-28, wait 3 minutes and then trigger LOA - DEENERGIZE MOV 1403. Report when action is complete.

Isolate the Ruptured S/G Closing and de

-energizing MOV 1403 is part of CT1.

BOP: Close steam supply valves from ruptured 3 A S/G to AFW Pumps using: Attachment 1 7 Check SI reset Check AMSAC reset Check Both AFW Auto Start White Lights - OFF (3QR50 AND 3QR51

) Close 3 A Steam Generator AFW Steam Supply

, MOV-3-1403. Dispatch an Operator to de

-energize BKR 4D01-28 for MOV-3-140 3. Verify MOV 1403 - CLOSED Notify Unit Supervisor That 3 A S/G AFW Steam Supply Is Isolated and Attachment 1 7 is complete. STEP 3.c CT1 Isolate the Ruptured S/G Closing the 3 A MSIV is part of CT

1. BOP: Verify 3 A S/G Blowdown Isolation Valve , FCV-3-6275A , is closed on 3 A S/G. Closes 3 A MSIV. STEP 3.d-e NRC EXAM SECURE INFORMATION Page 36 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 6 - 3A SGTR with LOOP 3-EOP-E-3, STEAM GENERATOR TUBE RUPTURE TIM E EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOP: Check Circulating Water Pumps

- ANY RUNNING (NO) - Close 3B and 3C MSIVs STEP 3.f BOOTH OPERATOR When dispatched to Align Main Steam auxiliaries using Attachment 5, trigger LOA - ALIGN AUX STEAM SUPPLY FROM U4. After 5 minutes, report complete

. BOP: Dispatch Operator to align main steam auxiliaries using Attachment 5 STEP 3.f BOOTH OPERATOR When dispatched to close 3 321 and 3-10-896 for S/G 3C per Attachment 16

, wait 5 minutes and report steps complete.

BOP: Isolate miscellaneous flow paths from 3 A S/G using Attachment 16.

Verify 3 A S/G Blowdown Sample MOV MOV-3-142 7 - CLOSED Dispatches Operator to locally isolate

- 3 A S/G Main Steamline Steam Trap 3-10-121A - Steam Sample Valves 3-10-89 1 for S/G 3 A Inform Unit Supervisor That Attachment 16 is Complete

. STEP 3.f NRC EXAM SECURE INFORMATION Page 37 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 6 - 3A SGTR with LOOP 3-EOP-E-3, STEAM GENERATOR TUBE RUPTURE TIM E EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE CT 1 Isolate the Ruptured S/G During a Steam Generator Tube Rupture

, isolate the ruptured S/G before a the ruptured Steam Generator pressure drops below 450 psig to prevent transition to 3-EOP-ECA-3.1, SGTR With Loss Of Reactor Coolant

-Subcooled Recovery Desired. Verify 3 A S/G has been Isolated by the crew CV-3-281 8 , TRN 1 AFW controller

, in manual and closed or auto with the setpoint set to zero.

CV-3-283 1 , TRN 2 AFW controller

, in manual and closed or auto with the setpoint set to zero.

MOV-3-140 3 , 3A Steam Supply to AFW pumps , closed and de

-energize d MOV-3-140 7 , 3A S/G FW Isolation

, close d CV-3-1606 , 3A S/G Stm Dump to Atmosphere

, closed in Auto and set to 1060# 3 A MSIV CLOSED BOP: Check 3 A S/G Level Narrow Range level - GREATER THAN 7%[27%]

Verify feed flow stopped to t he 3 A S/G. STEP 4 US: Checks 3 C S/G pressure greater than 450 psig. STEP 5 NRC EXAM SECURE INFORMATION Page 38 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 6 - 3A SGTR with LOOP 3-EOP-E-3, STEAM GENERATOR TUBE RUPTURE TIM E EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE US/BOP: Initiate RCS Cooldown Determines required CET Temp for Cooldown. Check feed sources to intact S/Gs

- CAPABLE OF PROVIDING 400 GPM Check Condenser AVAILABLE (NO) Manually dump steam to atmosphere from 3 B & 3 C S/G(s) at maximum rate using Steam Dump to Atmosphere Valves. Continue with step 7

- When Core Exit TCs

- LESS THAN REQUIRED TEMPERATURE, then stops cooldown. - Maintains core exit TCs

- LESS THAN REQUIRED TEMPERATUR E. STEP 6 BOP: Check Intact S/G Level:

Any Narrow Range Level

- GREATER THAN 7%[27%].

Maintain 3 A and 3 B S/G narrow range level between 21%[27%] and 50%

. Narrow Level

- LESS THAN 50%.

STEP 7 RCO: Verify SI

- RESET STEP 8 NRC EXAM SECURE INFORMATION Page 39 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 6 - 3A SGTR with LOOP 3-EOP-E-3, STEAM GENERATOR TUBE RUPTURE TIM E EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE RCO: Establish Charging Flow: Charging Pumps

- AT LEAST ONE RUNNING Check offsite power

- AVAILABLE (NO) - Check if diesel capacity is adequate to run three Charging Pumps Start all available Charging Pumps

. Adjust speed controller as necessary to establish maximum Charging flow from the running Charging Pump(s). Place RCS Makeup Control in STOP

. Adjust HCV 121, Charging Flow To Regen Heat Exchanger, to maintain proper Seal Injection flow

. Verify Charging Pump Suction auto transfers to RWST.

STEP 9 CT 3 Stop Time Limit RHR Time On Recirculation When a RHR Pump starts and is operating at shutoff head, limit the operating time at shutoff head with minimum flow recirculation to no more than 44 minutes.

[0-ADM-232, Time Critical Operator Action Program

- Attachment 1]

RCO: Check If RHR Pumps should Be Stopped: Check RCS pressure

- GREATER THAN 275 PSIG[575 PSIG]

Check RHR flow

- LESS THAN 1100 GPM Stop RHR Pumps and place in standby. STEP 10 NRC EXAM SECURE INFORMATION Page 40 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 6 - 3A SGTR with LOOP 3-EOP-E-3, STEAM GENERATOR TUBE RUPTURE TIM E EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE RCO: Check PRZ PORVs And Block Valves:

Check Power to block valves

- AVAILABLE Check PORVs

- CLOSED Check Block valves

- AT LEAST ONE OPEN STEP 11 RCO: Reset Containment Isolation Phase A & Phase B. STEP 12 RCO: Verify Instrument Air To Containment:

Verify CV-3-2803, Instrument Air Containment Isolation

- OPEN Verify Instrument Air pressure, as indicated on PI 1444 - GREATER THAN 95 PSIG STEP 13 CT2 Control Initial RCS Cooldown When 3-EOP-E-3, Steam Generator Tube Rupture , is entered, dump steam from 3 B and 3 C SGs at maximum rate using the Condenser Steam Dump Valves or Steam Dump To Atmosphere Valves to achieve Core Exit TCs less than required temperatures based on the lowest ruptured S/G pressure without causing a required transition to 3

-EOP-FR-P.1, Response to Imminent Pressurized Thermal Shock Condition.

BOP: Check If RCS Cooldown Should be Stopped: Check CETs <

REQUIRED WHEN core exit TCs are less than required temperature Stop RCS cooldown Maintain CETs < REQUIRED STEP 14 BOP: Checks Ruptured S/G(s) Pressure STABLE or INCREASING STEP 15 NRC EXAM SECURE INFORMATION Page 41 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 6 - 3A SGTR with LOOP 3-EOP-E-3, STEAM GENERATOR TUBE RUPTURE TIM E EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOP: Check RCS Subcooling Based On Core Exit TCs

- GREATER THAN 39°F[93°F]

STEP 16 EVENT 8 - PCV-3-445C PZR PORV, FAILS TO CLOSE DURING E

-3 DEPRESSURIZATION 3-EOP-E-3, STEAM GENERATOR TUBE RUPTURE TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOOTH OPERATOR When PCV-3-455C is opened, verify EVENT 8 - PORV 455C FAILS TO CLOSE triggers.

NOTE PORV PCV-3-456 was failed close in the scenario setup.

RCO: Check Normal PRZ Spray available (NO) Go to Step 18 STEP 17 CT4 Control Initial RCS Depressurization During a Steam Generator Tube Rupture

, depressurize the RCS to the ruptured S/G pressure without causing a transition to 3

-EOP-FR-P.1, Response to Imminent Pressurized Thermal Shock Condition, or 3-EOP-ECA-3.1, SGTR With Loss Of Reactor Coolant

- Subcooled Recovery Desired. RCO: Open one PRZ PORV until any of the conditions satisfied using Attachment

6. When the conditions of Attachment 6 are satisfied close PZR PORV Close Block Valve MOV-3-536 to stop the depressurization

. STEP 18 The scenario may be terminated at the discretion of the Lead Evaluator after the RCS cooldown is complete and the crew has had the opportunity to complete all critical steps.

• • • END OF SCENARIO ***

NRC EXAM SECURE INFORMATION Page 42 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 7 - CONTROL ROOM HVAC FAILS TO ALIGN ON SI 3-EOP-E-0 ATTACHMENT 3 - PROMPT ACTION VERIFICATIONS TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOP: Check Load Centers Associated With Energized 4 KV Buses

- ENERGIZED STEP 1 BOP: Verify Feedwater Isolation:

Place Main Feedwater Pump switches in STOP STEP 2 BOP: Check If Main Steam Lines Should Be Isolated STEP 3 BOP: Verify Containment Isolation Phase A Valve White Lights On VPB

- ALL BRIGHT STEP 4 BOP: Verify Pump Operation:

STEP 5 BOP: Verify Proper CCW System Operation:

STEP 6 BOP: Verify Proper ICW System Operation:

STEP 7 BOP: Check Emergency Containment Coolers

- ONLY TWO RUNNING STEP 8 NRC EXAM SECURE INFORMATION Page 43 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 7 - CONTROL ROOM HVAC FAILS TO ALIGN ON SI 3-EOP-E-0 ATTACHMENT 3 - PROMPT ACTION VERIFICATIONS TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOP: Verify Unit 3 Containment Purge Exhaust And Supply Fans

- OFF STEP 9 BOP: Verify Containment Spray NOT Required:

-STEP 10 BOP: Verify SI

- RESET STEP 11 BOP: Verify SI Valve Amber Lights On VPB

- ALL BRIGHT STEP 12 BOP: Verify SI Flow: (NO) Go to Step 14 STEP 13 BOOTH OPERATOR When directed by the crew, trigger LOA

- ALIGN U4 HHSI TO U3 RWST.

Wait 5 minute s and report local operator step s complete. BOP: Realign SI System:

Verify Unit 3 High

-Head SI Pumps

- TWO RUNNING Stop both Unit 4 HHSI pump.

Direct Unit 4 Reactor Operator to align Unit 4 High

-Head SI Pump suction to Unit 3 RWST using Attachment 1.

Stop Unit 4 HHSI pumps STEP 14 BOP: Verify Containment Isolation Phase A

- RESET STEP 15 NRC EXAM SECURE INFORMATION Page 44 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 7 - CONTROL ROOM HVAC FAILS TO ALIGN ON SI 3-EOP-E-0 ATTACHMENT 3 - PROMPT ACTION VERIFICATIONS TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOP: Check RCPs

- AT LEAST ONE RUNNING (NO Go to Step 17)

STEP 16 BOOTH OPERATOR When the BOP opens damper D3 , verify EVENT 7 - ALLOW OPENING D3 triggers When the BOP opens damper D2 , verify EVENT 7 - ALLOW OPENING D2 triggers BOP: Verify Emergency Air Supply Fans

- at least one running Control Room Ventilation dampers

- aligned for recirc (NO) - Open Emergency Inlet Damper D Open Emergency Inlet Damper D-2 Verify Normal Flow green indicating light (4QR82)

- ON TS-0002, TSC Emergency Vent Auto Initiate Key Switch

- IN ENABLE STEP 17 BOOTH OPERATOR When requested by crew, trigger LOA

- PLACE PAHMS IN SERVICE

. Wait 5 minute s and report local operator ste p s complete. BOP: Place Hydrogen Monitors In Service Using 3-NOP-094, CONTAINMENT POST ACCIDENT MONITORING SYSTEM For Each Hydrogen Monitor A/B

- ENSURE FUNCTION SELECTOR switch is in SAMPLE.

- PLACE control switch in ANALYZE. - PRESS the REMOTE SELECTOR button. - PRESS the ALARM RESET button. Dispatch an operator to complete local step of 3

-NOP-094 (STEP 18) NRC EXAM SECURE INFORMATION Page 45 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG EVENT 7 - CONTROL ROOM HVAC FAILS TO ALIGN ON SI 3-EOP-E-0 ATTACHMENT 3 - PROMPT ACTION VERIFICATIONS TIME EVALUATOR ACTIVITIES & NOTES EXPECTED STUDENT RESPONSE BOP: Verify All Four EDGs

- RUNNING STEP 19 BOP: Check 3A AND 3B 4 KV Buses

- All Energized From Offsite power. (NO, check computer chiller running) STEP 20 BOP: Notify Unit Supervisor that Attachment 3 is complete

. STEP 21 NRC EXAM SECURE INFORMATION Page 46 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG Discussion Points are intentionally NOT included in evaluated scenarios. However, space is available below to document follow

-up questions when further information is required to determine an evaluation outcome. FOLLOW-UP QUESTIONS QUESTION #1 ________________________________________________________________________________________________________________________________________________________________________

_____________

___________________________________________________________________

ANSWER #1 ________________________________________________________________________________________________________________________________________________________________________

______________________________________________________________________________________________________________________________________________

QUESTION #2 _____________________________________________________________________________________________________________

___________________________________________________________________________________________________________________________________________

ANSWER #2 ______________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________

NRC EXAM SECURE INFORMATION Page 47 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG SIMULATOR POST

-SCENARIO RESTORATION

______ 1. Restore per Simulator Operator Checklist.

______ 2. Once exams are complete, restore from SEI

-19, Simulator Exam Security.

NRC EXAM SECURE INFORMATION Page 48 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG NRC EXAM SECURE INFORMATION Page 49 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG NRC EXAM SECURE INFORMATION Page 50 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG NRC EXAM SECURE INFORMATION Page 51 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG OPERATIONS SHIFT TURNOVER REPORT UNIT 3 RISK: GREEN (ACCEPTABLE)

PROTECTED TRAIN: B UNIT 4 RISK: GREEN (ACCEPTABL E) PROTECTED TRAIN: B ONCOMING CREW ASSIGNMENTS Shift Mgr:

Inside SNPO:

Field Supv.:

Outside SNPO:

Admin RCO:

ANPO: Unit 3 Unit 4 Unit Supv.:

Unit Supv.:

RCO: RCO: NPO: NPO: PLANT STATUS Unit 3 Unit 4 Mode: 1 Mode: 1 Power: 60% Power: 100% MWe: 46 4 MWe: 842 Gross Leakrate:

.22 gpm Gross Leakrate:

0.03 gpm RCS Boron Conc:

88 5 ppm RCS Boron Conc:

642 ppm Operational Concerns:

3A RHR pump taken OOS 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago for an oil change, expected back by the end of this shif

t. 3A1 Circ Water pump OOS. Tripped on over current, Electrical Maintenance is investigating.

3A Condensate pump was returned to service last shift following a motor bearing replacement and PMT run. Return to full power expected next shift.

U3 Anticipated LCO Actions:

None U4 Anticipated LCO Actions:

None Results of Offgoing Focus Area:

NRC EXAM SECURE INFORMATION Page 52 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG UNIT 3 STATUS REACTOR OPERATOR UNIT RISK: GREEN (ACCEPTABLE) PROTECTED TRAIN: B Mode: 1 RCS Leakrate Accumulator Ref Levels Power: 60% Gross: 0.22 GPM A 6656 MWe 46 4 Unidentified 0.04 GPM B 6608 Tavg: 565°F Charging Pps:

0.00 GPM C 6646 RCS Pressure:

2235 RCS Boron Conc:

88 5 ppm Abnormal Annunciators:

Annunciator:

Comp Actions:

Annunciator:

Comp Actions:

Annunciator:

Comp Actions:

Annunciator:

Comp Actions:

Annunciator:

Comp Actions:

Annunciator:

Comp Actions:

Current Tech Spec Action Statements: (Does Not Include "For Tracking Only Items" T.S.A.S / Component:

3A RHR pump, 3.5.2.c

- Action g Reason: Oil Change Entry Date:

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago T.S.A.S / Component:

Reason: Entry Date:

T.S.A.S / Component:

Reason: Entry Date:

T.S.A.S / Component:

Reason: Entry Date:

T.S.A.S / Component:

Reason: Entry Date:

NRC EXAM SECURE INFORMATION Page 53 of 54 L-16-1 NRC EXAM SCENARIO 5 NRC EXAM SECURE INFO RMATION SEG REACTOR OPERATOR (CONT'D) UNIT RISK: GREEN (ACCEPTABLE) PROTECTED TRAIN: B Changes to Risk Significant Equipment:

No recent changes from last shift.

OLRM: GREEN PROTECTED TRAIN: B Upcoming Reactivity Management Activities:

Maintain current power level

+ .5% Xe is stable.

Upcoming Major POD Activities:

NONE Upcoming ECOs to Hang and /or Release:

Hang - None Release - None Evolutions or Compensatory Actions in Progress:

NONE General Information, Remarks, and Operator Work Around Status:

Weather forecast is overcast skies with scattered pockets of severe rain.

U3 supplying Aux Steam Air In-leakage = 0.0 SCFM NRC EXAM SECURE INFORMATION Page 54 of 54

NRC EXAM SECURE INFORMATION

L-16-1 NRC Exam Control Room

- JPM A

NRC EXAM SECURE INFORMATION

JOB PERFORMANCE MEAS URE NRC EXAM SECURE INFORMATION JPM JPM TITLE:

Respond to Control Bank D Demanded Past ARO JPM NUMBER:

0102891630 2 REV. 1-0 TASK NUMBER(S) / TASK TITLE(S):

01 02891630 0 / Respond to Control Bank D Demanded Past ARO K/A NUMBERS:

001 A4.14 K/A VALUE:

RO 3.0 / SRO 3.4 Justification (FOR K/A VALUES <3.0):

N/A TASK APPLICABILITY:

RO SRO STA Non-Lic SRO CERT OTHER: APPLICABLE METHOD OF TESTING:

Simulate/Walkthrough:

Perform: X EVALUATION LOCATION:

In-Plant: Control Room:

Simulator:

X Other: L ab: Time for Completion:

1 5 Minutes Time Critical:

No Alternate Path [NRC]:

Yes Alternate Path [INPO]:

Yes Developed by:

Brian Clark 8/4/16 Instructor/Developer Date Reviewed by: Tim Hodge 8/4/16 Instructor (Instructional Review)

Date Validated by:

Sean Bloom 8/5/16 SME (Technical Review)

Date Approved by:

Mark Wilson 8/5/16 Training Supervision Date Approved by:

Sean Bloom 8/5/16 Training Program Ow ner Date TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM A NRC EXAM SECURE INFORMATION

01028916302 , Respond to Control Bank D Demanded Past ARO Ste ps , Rev. 1-0 NRC EXAM SECURE INFORMATION JPM Page 3 of 15 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A 1. Are all items on the signature page filled in correctly?

2. Has the JPM been reviewed and validated by SMEs?

3. Can the required conditions for the JPM be appropriately established in the simulator if required?

4. Do the performance steps accurately reflect trainee's actions in accordance with plant procedures?

5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?

6. Has the completion time been established based on validation data or incumbent experience?

7. If the task is time critical, is the time critical portion based upon actual task performance requirements?

8. Is the job level appropriate for the task being evaluated if required?

9. Is the K/A appropriate to the task and to the licensee level if required?

10. Is justification provided for tasks with K/A values less than 3.0?

11. Have the performance steps been identified and classified (Critical / Sequence / Time Critical) appropriately?

12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?

13. Are all references identified, current, accurate, and available to the trainee?

14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?

15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)

16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM? TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge.

All questions/statements must be answered "YES" or "N/A" or the JPM is not valid for use. If all questions/statements are answered "YES" or "N/A," then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.

Protected Conten t: (CAPRs, corrective actions, licensing commitments, etc. associated with this material

) N/A TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM A NRC EXAM SECURE INFORMATION

01028916302 , Respond to Control Bank D Demanded Past ARO Ste ps , Rev. 1-0 NRC EXAM SECURE INFORMATION JPM Page 4 of 15 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR

-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR

-AA-230-1003-F16. # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE SUPERVISOR DATE 0-0 New JPM N/A N/A N/A N/A 1-0 Formatting; text/grammar changes L-16-1 NRC Exam N/A N/A N/A N/A N/A TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM A NRC EXAM SECURE INFORMATION

01028916302 , Respond to Control Bank D Demanded Past ARO Ste ps , Rev. 1-0 NRC EXAM SECURE INFORMATION JPM Page 5 of 15 SIMULATOR SET

-UP: SIMULATOR SETUP INSTRUCTIONS

_____ 1. Reset to IC 1 or saved IC. _____ 2. Place simulator in RUN.

_____ 3. Ensure applicable portions of Simulator Operator Checklist are complete.

_____ 4. N/A if using saved IC Perform following setup steps

a. Place Rod Motion Control Selector Switch in MANUAL

b. Withdraw Control Bank D to 23 0 steps _____ 5. Open and execute L-16-1 NRC JPM A.lsn _____ 6. Allow plant to stabilize.

_____ 7. Acknowledge alarms and place simulator in FREEZE.

_____ 8. Save as temporary IC, if JPM will be repeated.

_____ 9. When ready to begin, then place Simulator in RUN.

SIMULATOR MALFUNCTIONS:

TFL10201: Continuous rod insertion in auto

SIMULATOR OVERRIDES:

N/A SIMULATOR REMOTE FUNCTIONS:

N/A

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM A NRC EXAM SECURE INFORMATION

01028916302 , Respond to Control Bank D Demanded Past ARO Ste ps , Rev. 1-0 NRC EXAM SECURE INFORMATION JPM Page 6 of 15 Required Materials:

HANDOUT 3-ONOP-028 HANDOUT Unit 3 COLR General

References:

3-ONOP-028 , Reactor Control System Malfunction Plant Curve Book, Unit 3 Task Standards:

Restore the Rod Control System to normal configuration with Bank D at 22 8 steps withdrawn Respond to a continuous rod insertion event by placing rods in MANUAL TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM A NRC EXAM SECURE INFORMATION

01028916302 , Respond to Control Bank D Demanded Past ARO Ste ps , Rev. 1-0 NRC EXAM SECURE INFORMATION JPM Page 7 of 15 HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.

INITIAL CONDITIONS:

Unit 3 is at 100% power. Control Bank D has been inadvertently withdrawn past 228 steps. The Control Bank D step counters currently indicate 23 0 steps. The crew entered 3

-ONOP-028, Reactor Control System Malfunction, and completed the immediate actions.

INITIATING CUE S: The Unit Supervisor directs you to restore the Rod Control System to its normal configuration by performing Section 5.5 of 3

-ONOP-028, Reactor Control System Malfunction

. The Shift Manager has authorized the return of control rods to automatic, on completion of the procedure.

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM A NRC EXAM SECURE INFORMATION

01028916302 , Respond to Control Bank D Demanded Past ARO Ste ps , Rev. 1-0 NRC EXAM SECURE INFORMATION JPM Page 8 of 15 JPM PERFORMANCE INFORMATION Start Time:

NOTE: When providing "Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically

, cues are only provided when the examinee's actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a "Y es" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step:

1 Critical: No Obtain required reference materials. Standard: Obtain 3-ONOP-028, Reactor Control System Malfunction

. Evaluator Note: If a peer check is requested for any of the following steps, then acknowledge the request and allow the operator to continue.

Evaluator Cue:

Provide examinee with copies of HANDOUT 3-ONOP-028 and HANDOUT Unit 3 COLR

. Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM A NRC EXAM SECURE INFORMATION

01028916302 , Respond to Control Bank D Demanded Past ARO Ste ps , Rev. 1-0 NRC EXAM SECURE INFORMATION JPM Page 9 of 15 Performance Step:

2 Critical: No 3-ONOP-028, prior to Step 5.5.1: C A U T I O N Demanding RCCs to step past the ARO position may cause failure of the stationary grippers and result in a misaligned, partially inserted or dropped rod. Standard: Read CAUTION and determine it is satisfactory to proceed.

Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

3 Critical: No 3-ONOP-028, Step 5.5.1

Check for indications of misaligned or dropped RCCs Standard: Observe Control Bank D's rod position indicators and determines that no rods are misaligned or dropped.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM A NRC EXAM SECURE INFORMATION

01028916302 , Respond to Control Bank D Demanded Past ARO Ste ps , Rev. 1-0 NRC EXAM SECURE INFORMATION JPM Page 10 of 15 Performance Step:

4 Critical: No 3-ONOP-028, Step 5.5.2: IF a RCC is determined to be misaligned, THEN - Standard: R ead step, compare to Initial Conditions, and determine it does not apply. Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

5 Critical: No 3-ONOP-028, Step 5.5.

3: IF a RCC is determined to be dropped , THEN - Standard: R ead step, compare to Initial Conditions, and determine it does not apply. Performance:

SATISFACTORY UNSATISFACTORY Comment s:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM A NRC EXAM SECURE INFORMATION

01028916302 , Respond to Control Bank D Demanded Past ARO Ste ps , Rev. 1-0 NRC EXAM SECURE INFORMATION JPM Page 11 of 15 Performance Step:

6 Critical: No 3-ONOP-028, Step 5.5.4:

IF Control Bank D control rods have not been withdrawn more than 230 demanded steps, THEN perform the following:

1. Verify the Rod Motion Control Selector switch is in MAN.

Standard: Recognize that switch is in MAN position.

Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

7 Critical: Yes 3-ONOP-028, Step 5.5.4:

IF Control Bank D control rods have not been withdrawn more than 230 demanded steps, THEN perform the following:

2. Insert Control Bank D to All Rods Out as defined in Core Operating Limits Report (COLR). Standard: Determine ARO to be 228 steps and insert rods 2 steps.

Evaluator Note:

Acknowledge any communication.

Performance: SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM A NRC EXAM SECURE INFORMATION

01028916302 , Respond to Control Bank D Demanded Past ARO Ste ps , Rev. 1-0 NRC EXAM SECURE INFORMATION JPM Page 12 of 15 Performance Step:

8 Critical: No 3-ONOP-028, Step 5.5.4:

IF Control Bank D control rods have not been withdrawn more than 230 demanded steps, THEN perform the following:

3. IF directed by the Shift manager, THEN Place Rod Control Selector Switch to AUTOMATIC position

. Standard: Place rod control selector switch to AUTO position.

Booth Operator Note:

When rods are placed in MANUAL, verify trigger CONTINUOUS ROD INSERTION IN AUTO triggers. Evaluator Note:

May need to call as the SM if examinee chooses to leave rods in MAN. Placing rods in AUTO is necessary as it triggers the next event.

Evaluator/Booth Cue:

If asked, respond as the SM and direct the rods to be placed in AUTO. Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM A NRC EXAM SECURE INFORMATION

01028916302 , Respond to Control Bank D Demanded Past ARO Ste ps , Rev. 1-0 NRC EXAM SECURE INFORMATION JPM Page 13 of 15 THIS BEGINS THE ALTERNATE

-PATH PORTION OF THE JPM Performance Step:

9 Critical: Yes 3-ONOP-028, Step 5.5.4:

IF Control Bank D control rods have not been withdrawn more than 230 demanded steps, THEN perform the following:

3. IF directed by the Shift manager, THEN Place Rod Control Selector Switch to AUTOMATIC position

. Standard: Recognize continuous rod insertion and place rod control selector switch to MANUAL position.

Evaluator Note:

Examinee should place the Rod Motion Selector Switch in the MAN position prior to Tavg being 6°F less than Tref (i.e., 2°F lower than transient band per 0

-ADM-211, Emergency And Off

-Normal Operating Procedure Usage). Performance:

SATISFACTORY UNSATISFACTORY Comments: Terminating Cue:

Once the Rod Control Selector Switch is placed in manual

, state "This completes the JPM.

" NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

Stop Time:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM A NRC EXAM SECURE INFORMATION

01028916302 , Respond to Control Bank D Demanded Past ARO Steps , Rev. 1-0 NRC EXAM SECURE INFORMATION JPM Page 14 of 15 Examinee: Evaluator:

RO SRO STA Non-Lic SRO CERT Date: LOIT RO LOIT SRO PERFORMANCE RESULTS:

SAT: UNSAT: Remediation required:

YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).

EXAMINER NOTE:

ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.

EVALUATOR'S SIGNATURE:

NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM A NRC EXAM SECURE INFORMATION

NRC EXAM SECURE INFORMATION JPM TURNOVER SHEET

INITIAL CONDITIONS:

Unit 3 is at 100% power. Control Bank D has been inadvertently withdrawn past 2 28 steps. The Control Bank D step counters currently indicate 23 0 steps. The crew entered 3

-ONOP-028, Reactor Control System Malfunction, and completed the immediate actions

. INITIATING CUE S: The Unit Supervisor directs you to restore the Rod Control System to its normal configuration by performing Section 5.5 of 3

-ONOP-028, Reactor Control System Malfunction

. The Shift Manager has authorized the return of control rods to automatic, on completion of the procedure.

NOTE: Ensure the turnover sheet is returned to the evaluator when the JPM is complete

. TR-AA-230-1003-F10, Revision 2 NRC EXAM SECURE INFORMATION

NRC EXAM SECURE INFORMATION

L-16-1 NRC Exam Control Room

- JPM A

NRC EXAM SECURE INFORMATION

JOB PERFORMANCE MEAS URE NRC EXAM SECURE INFORMATION JPM JPM TITLE:

Respond to Control Bank D Demanded Past ARO JPM NUMBER:

0102891630 2 REV. 1-0 TASK NUMBER(S) / TASK TITLE(S):

01 02891630 0 / Respond to Control Bank D Demanded Past ARO K/A NUMBERS:

001 A4.14 K/A VALUE:

RO 3.0 / SRO 3.4 Justification (FOR K/A VALUES <3.0):

N/A TASK APPLICABILITY:

RO SRO STA Non-Lic SRO CERT OTHER: APPLICABLE METHOD OF TESTING:

Simulate/Walkthrough:

Perform: X EVALUATION LOCATION:

In-Plant: Control Room:

Simulator:

X Other: L ab: Time for Completion:

1 5 Minutes Time Critical:

No Alternate Path [NRC]:

Yes Alternate Path [INPO]:

Yes Developed by:

Brian Clark 8/4/16 Instructor/Developer Date Reviewed by:

Luis Sagion 8/4/16 Instructor (Instructional Review)

Date Validated by:

Sean Bloom 8/5/16 SME (Technical Review)

Date Approved by:

Mark Wilson 8/5/16 Training Supervision Date Approved by:

Sean Bloom 8/5/16 Training Program Owner Date TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM A NRC EXAM SECURE INFORMATION

01028916302 , Respond to Control Bank D Demanded Past ARO Ste ps , Rev. 1-0 NRC EXAM SECURE INFORMATION JPM Page 3 of 15 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A 1. Are all items on the signature page filled in correctly?

2. Has the JPM been reviewed and validated by SMEs?

3. Can the required conditions for the JPM be appropriately established in the simulator if required?

4. Do the performance steps accurately reflect trainee's actions in accordance with plant procedures?

5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?

6. Has the completion time been established based on validation data or incumbent experience?

7. If the task is time critical, is the time critical portion based upon actual task performance requirements?

8. Is the job level appropriate for the task being evaluated if required? 9. Is the K/A appropriate to the task and to the licensee level if required?

10. Is justification provided for tasks with K/A values less than 3.0? 11. Have the performance steps been identified and classified (Critical / Sequence / Time Critical) appropriately?

12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?

13. Are all references identified, current, accurate, and available to the trainee?

14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?

15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)

16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM? TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge.

All questions/statements must be answered "YES" or "N/A" or the JPM is not valid for use. If all questions/statements are answered "YES" or "N/A," then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet. Protected Conten t: (CAPRs, corrective actions, licensing commitments, etc. associated with this material

) N/A TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM A NRC EXAM SECURE INFORMATION

01028916302 , Respond to Control Bank D Demanded Past ARO Ste ps , Rev. 1-0 NRC EXAM SECURE INFORMATION JPM Page 4 of 15 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR

-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR

-AA-230-1003-F16. # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE SUPERVISOR DATE 0-0 New JPM N/A N/A N/A N/A 1-0 Formatting; text/grammar changes L-16-1 NRC Exam N/A N/A N/A N/A N/A TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM A NRC EXAM SECURE INFORMATION

01028916302 , Respond to Control Bank D Demanded Past ARO Ste ps , Rev. 1-0 NRC EXAM SECURE INFORMATION JPM Page 5 of 15 SIMULATOR SET

-UP: SIMULATOR SETUP INSTRUCTIONS

_____ 1. Reset to IC 1 or saved IC. _____ 2. Place simulator in RUN.

_____ 3. Ensure applicable portions of Simulator Operator Checklist are complete.

_____ 4. N/A if using saved IC Perform following setup steps

a. Place Rod Motion Control Selector Switch in MANUAL

b. Withdraw Control Bank D to 23 0 steps _____ 5. Open and execute L-16-1 NRC JPM A.lsn _____ 6. Allow plant to stabilize.

_____ 7. Acknowledge alarms and place simulator in FREEZE.

_____ 8. Save as temporary IC, if JPM will be repeated.

_____ 9. When ready to begin, then place Simulator in RUN.

SIMULATOR MALFUNCTIONS:

TFL10201: Continuous rod insertion in auto

SIMULATOR OVERRIDES:

N/A SIMULATOR REMOTE FUNCTIONS:

N/A

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM A NRC EXAM SECURE INFORMATION

01028916302 , Respond to Control Bank D Demanded Past ARO Ste ps , Rev. 1-0 NRC EXAM SECURE INFORMATION JPM Page 6 of 15 Required Materials:

HANDOUT 3-ONOP-028 HANDOUT Unit 3 COLR General

References:

3-ONOP-028 , Reactor Control System Malfunction Plant Curve Book, Unit 3 Task Standards:

Restore the Rod Control System to normal configuration with Bank D at 22 8 steps withdrawn Respond to a continuous rod insertion event by placing rods in MANUAL TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM A NRC EXAM SECURE INFORMATION

01028916302 , Respond to Control Bank D Demanded Past ARO Ste ps , Rev. 1-0 NRC EXAM SECURE INFORMATION JPM Page 7 of 15 HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.

INITIAL CONDITIONS:

Unit 3 is at 100% power. Control Bank D has been inadvertently withdrawn past 228 steps. The Control Bank D step counters currently indicate 23 0 steps. The crew entered 3

-ONOP-028, Reactor Control System Malfunction, and completed the immediate actions.

INITIATING CUE S: The Unit Supervisor directs you to restore the Rod Control System to its normal configuration by performing Section 5.5 of 3

-ONOP-028, Reactor Control System Malfunction

. The Shift Manager has authorized the return of control rods to automatic, on completion of the procedure.

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM A NRC EXAM SECURE INFORMATION

01028916302 , Respond to Control Bank D Demanded Past ARO Ste ps , Rev. 1-0 NRC EXAM SECURE INFORMATION JPM Page 8 of 15 JPM PERFORMANCE INFORMATION Start Time:

NOTE: When providing "Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically

, cues are only provided when the examinee's actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a "Y es" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step:

1 Critical: No Obtain required reference materials. Standard: Obtain 3-ONOP-028, Reactor Control System Malfunction

. Evaluator Note: If a peer check is requested for any of the following steps, then acknowledge the request and allow the operator to continue.

Evaluator Cue:

Provide examinee with copies of HANDOUT 3-ONOP-028 and HANDOUT Unit 3 COLR

. Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM A NRC EXAM SECURE INFORMATION

01028916302 , Respond to Control Bank D Demanded Past ARO Ste ps , Rev. 1-0 NRC EXAM SECURE INFORMATION JPM Page 9 of 15 Performance Step:

2 Critical: No 3-ONOP-028, prior to Step 5.5.1: C A U T I O N Demanding RCCs to step past the ARO position may cause failure of the stationary grippers and result in a misaligned, partially inserted or dropped rod. Standard: Read CAUTION and determine it is satisfactory to proceed.

Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

3 Critical: No 3-ONOP-028, Step 5.5.1

Check for indications of misaligned or dropped RCCs Standard: Observe Control Bank D's rod position indicators and determines that no rods are misaligned or dropped.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM A NRC EXAM SECURE INFORMATION

01028916302 , Respond to Control Bank D Demanded Past ARO Ste ps , Rev. 1-0 NRC EXAM SECURE INFORMATION JPM Page 10 of 15 Performance Step:

4 Critical: No 3-ONOP-028, Step 5.5.2: IF a RCC is determined to be misaligned, THEN - Standard: R ead step, compare to Initial Conditions, and determine it does not apply. Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

5 Critical: No 3-ONOP-028, Step 5.5.

3: IF a RCC is determined to be dropped , THEN - Standard: R ead step, compare to Initial Conditions, and determine it does not apply. Performance:

SATISFACTORY UNSATISFACTORY Comment s:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM A NRC EXAM SECURE INFORMATION

01028916302 , Respond to Control Bank D Demanded Past ARO Ste ps , Rev. 1-0 NRC EXAM SECURE INFORMATION JPM Page 11 of 15 Performance Step:

6 Critical: No 3-ONOP-028, Step 5.5.4:

IF Control Bank D control rods have not been withdrawn more than 230 demanded steps, THEN perform the following:

1. Verify the Rod Motion Control Selector switch is in MAN.

Standard: Recognize that switch is in MAN position.

Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

7 Critical: Yes 3-ONOP-028, Step 5.5.4:

IF Control Bank D control rods have not been withdrawn more than 230 demanded steps, THEN perform the following:

2. Insert Control Bank D to All Rods Out as defined in Core Operating Limits Report (COLR). Standard: Determine ARO to be 228 steps and insert rods 2 steps.

Evaluator Note:

Acknowledge any communication.

Performance: SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM A NRC EXAM SECURE INFORMATION

01028916302 , Respond to Control Bank D Demanded Past ARO Ste ps , Rev. 1-0 NRC EXAM SECURE INFORMATION JPM Page 12 of 15 Performance Step:

8 Critical: No 3-ONOP-028, Step 5.5.4:

IF Control Bank D control rods have not been withdrawn more than 230 demanded steps, THEN perform the following:

3. IF directed by the Shift manager, THEN Place Rod Control Selector Switch to AUTOMATIC position

. Standard: Place rod control selector switch to AUTO position.

Booth Operator Note:

When rods are placed in MANUAL, verify trigger CONTINUOUS ROD INSERTION IN AUTO triggers. Evaluator Note:

May need to call as the SM if examinee chooses to leave rods in MAN. Placing rods in AUTO is necessary as it triggers the next event.

Evaluator/Booth Cue:

If asked, respond as the SM and direct the rods to be placed in AUTO. Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM A NRC EXAM SECURE INFORMATION

01028916302 , Respond to Control Bank D Demanded Past ARO Ste ps , Rev. 1-0 NRC EXAM SECURE INFORMATION JPM Page 13 of 15 THIS BEGINS THE ALTERNATE

-PATH PORTION OF THE JPM Performance Step:

9 Critical: Yes 3-ONOP-028, Step 5.5.4:

IF Control Bank D control rods have not been withdrawn more than 230 demanded steps, THEN perform the following:

3. IF directed by the Shift manager, THEN Place Rod Control Selector Switch to AUTOMATIC position

. Standard: Recognize continuous rod insertion and place rod control selector switch to MANUAL position.

Evaluator Note:

Examinee should place the Rod Motion Selector Switch in the MAN position prior to Tavg being 6°F less than Tref (i.e., 2°F lower than transient band per 0

-ADM-211, Emergency And Off

-Normal Operating Procedure Usage). Performance:

SATISFACTORY UNSATISFACTORY Comments: Terminating Cue:

Once the Rod Control Selector Switch is placed in manual

, state "This completes the JPM.

" NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

Stop Time:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM A NRC EXAM SECURE INFORMATION

01028916302 , Respond to Control Bank D Demanded Past ARO Steps , Rev. 1-0 NRC EXAM SECURE INFORMATION JPM Page 14 of 15 Examinee: Evaluator:

RO SRO STA Non-Lic SRO CERT Date: LOIT RO LOIT SRO PERFORMANCE RESULTS:

SAT: UNSAT: Remediation required:

YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).

EXAMINER NOTE:

ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.

EVALUATOR'S SIGNATURE:

NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM A NRC EXAM SECURE INFORMATION

NRC EXAM SECURE INFORMATION JPM TURNOVER SHEET

INITIAL CONDITIONS:

Unit 3 is at 100% power. Control Bank D has been inadvertently withdrawn past 2 28 steps. The Control Bank D step counters currently indicate 23 0 steps. The crew entered 3

-ONOP-028, Reactor Control System Malfunction, and completed the immediate actions

. INITIATING CUE S: The Unit Supervisor directs you to restore the Rod Control System to its normal configuration by performing Section 5.5 of 3

-ONOP-028, Reactor Control System Malfunction

. The Shift Manager has authorized the return of control rods to automatic, on completion of the procedure.

NOTE: Ensure the turnover sheet is returned to the evaluator when the JPM is complete

. TR-AA-230-1003-F10, Revision 2 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC Exam Control Room

- JPM B

L-16-1 NRC EXAM SECURE INFORMATION

JOB PERFORMANCE MEAS URE L-16-1 NRC EXAM SECURE INFORMATION JPM JPM TITLE:

Place Excess Letdown in Service JPM NUMBER: 01047016102 REV. 2-0 TASK NUMBER(S) / TASK TITLE(S):

01047016100

/ Initiate Excess Letdown K/A NUMBERS:

00 4 A4.06 K/A VALUE:

RO 3.6 / SRO 3.1 Justification (FOR K/A VALUES <3.0):

N/A TASK APPLICABILITY:

RO SRO STA Non-Lic SRO CERT OTHER: APPLICABLE METHOD OF TESTING:

Simulate/Walkthrough:

Perform: X EVALUATION LOCATION:

In-Plant: Control Room:

Simulator:

X Other: L ab: Time for Completion:

15 Minutes Time Critical:

No Alternate Path [NRC]:

Yes Alternate Path [INPO]:

Yes Developed by:

Brian Clark 8/4/16 Instructor/Developer Date Reviewed by: Tim Hodge 8/4/16 Instructor (Instructional Review)

Date Validated by:

Sean Bloom 8/5/16 SME (Technical Review)

Date Approved by:

Mark Wilson 8/4/16 Training Supervision Date Approved by:

Sean Bloom 8/5/16 Training Program Owne r Date TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM B L-16-1 NRC EXAM SECURE INFORMATION

01047016102 , Place Excess Letdown in Service, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 3 of 19 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A 1. Are all items on the signature page filled in correctly?

2. Has the JPM been reviewed and validated by SMEs?

3. Can the required conditions for the JPM be appropriately established in the simulator if required?

4. Do the performance steps accurately reflect trainee's actions in accordance with plant procedures?

5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?

6. Has the completion time been established based on validation data or incumbent experience?

7. If the task is time critical, is the time critical portion based upon actual task performance requirements?

8. Is the job level appropriate for the task being evaluated if required?

9. Is the K/A appropriate to the task and to the licensee level if required?

10. Is justification provided for tasks with K/A values less than 3.0?

11. Have the performance steps been identified and classified (Critical / Sequence / Time Critical) appropriately?

12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?

13. Are all references identified, current, accurate, and available to the trainee?

14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?

15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)

16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM? TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge.

All questions/statements must be answered "YES" or "N/A" or the JPM is not valid for use. If all questions/statements are answered "YES" or "N/A," then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.

Protected Conten t: (CAPRs, corrective actions, licensing commitments, etc. associated with this material

) N/A TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM B L-16-1 NRC EXAM SECURE INFORMATION

01047016102 , Place Excess Letdown in Service, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 4 of 19 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR

-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR

-AA-230-1003-F16. # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE SUPERVISOR DATE 1-0 Updated to fleet template; text/grammar changes 2015 LOCT Annual Exam N/A N/A N/A N/A N/A 2-0 Formatting; text/grammar changes L-16-1 NRC Exam N/A N/A N/A N/A N/A TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM B L-16-1 NRC EXAM SECURE INFORMATION

01047016102 , Place Excess Letdown in Service, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 5 of 19 SIMULATOR SET

-UP: SIMULATOR SETUP INSTRUCTIONS

_____ 1. Reset to IC 1 or equivalent IC.

_____ 2. Place simulator in RUN.

_____ 3. Ensure applicable portions of Simulator Operator Checklist are complete.

_____ 4. O pen and execute L-16-1 NRC JPM B.lsn: a. Verify trigger RV-3-304 Fails Open is in CONDITION state

_____ 5. Allow plant to stabilize.

_____ 6. Acknowledge alarms and place simulator in FREEZE.

_____ 7. Save as temporary IC, if JPM will be repeated.

_____ 8. When ready to begin, then place Simulator in RUN.

SIMULATOR MALFUNCTIONS:

TFBVO304 - RV-304 Fails Open TFBVO10 - 387 Fails Open

SIMULATOR OVERRIDES:

N/A SIMULATOR REMOTE FUNCTIONS:

N/A

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM B L-16-1 NRC EXAM SECURE INFORMATION

01047016102 , Place Excess Letdown in Service, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 6 of 19 Required Materials:

HANDOUT 3-OP-047 HANDOUT 3-ONOP-041.3 General

References:

3-OP-047 , CVCS Charging and Letdown 3-ONOP-041.3, Excessive Reactor Coolant System Leakage Task Standards:

Place excess letdown in service Recognize that RV 304 has failed open Start a charging pump, per 3-ONOP-041.3, to maintain pressurizer level TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM B L-16-1 NRC EXAM SECURE INFORMATION

01047016102 , Place Excess Letdown in Service, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 7 of 19 HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.

INITIAL CONDITIONS:

Unit 3 is in M ode 1. Personnel are currently being briefed to perform maintenance and calibration on LCV 460, Letdown Isolation Valve.

INITIATING CUE S: In preparation for the isolation of normal letdown to support maintenance, the Unit Supervisor directs you to place excess letdown in service in accordance with Section 7.12 of 3-OP-047, CVCS Charging and Letdown

. All applicable prerequisites in Section 3.0 are satisfied.

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM B L-16-1 NRC EXAM SECURE INFORMATION

01047016102 , Place Excess Letdown in Service, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 8 of 19 JPM PERFORMANCE INFORMATION Start Time: NOTE: When providing "Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically

, cues are only provided when the examinee's actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a "Y es" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step:

1 Critical : No Obtain required reference materials. Standard: Obtain 3-OP-047, CVCS Charging and Letdown, Section 7.12

. Evaluator Note: If a peer check is requested for any of the following steps, then acknowledge the request and allow the operator to continue.

Evaluator Cue:

Provide examinee with a copy of HANDOUT 3-OP-047. Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM B L-16-1 NRC EXAM SECURE INFORMATION

01047016102 , Place Excess Letdown in Service, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 9 of 19 Performance Step:

2 Critical : No 3-OP-047 , Step 7.12.2.1: Verify Excess Ltdn Hx CCW Outlet, CV 739, is Open Standard: Recognize that CV-3-739 is open

. Performance:

SATISFACTORY UNSATISFACTORY Comments:

Performance Step:

3 Critical : No 3-OP-047 , Step 7.12.2.2: Verify greater than 200 gpm and less than or equal to 238 gpm CCW flow on flow indicator FI 624 (located in the Pipe and Valve Room)

Standard: Contact field operator and verify that flow on FI 624 is satisfactory

. Booth Operator Cue

When asked, report that flow is 211 gpm as indicated on FI 624. Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM B L-16-1 NRC EXAM SECURE INFORMATION

01047016102 , Place Excess Letdown in Service, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 10 of 19 Performance Step:

4 Critical : No 3-OP-047 , Step 7.12.2.3: Verify Excess Ltdn Iso Valve, CV-3-387, is Closed Standard: Recognize that CV 387 is closed

. Performance:

SATISFACTORY UNSATISFACTORY Comments:

Performance Step:

5 Critical : No 3-OP-047 , Step 7.12.2.4

Verify Excess Ltdn Divert to WDS, CV 389, is aligned to the VCT (Switch to Normal)

Standard: Recognize that CV-3-389 is aligned to the VCT

. Evaluator Note: Switch will be in the VCT

-NORM position

. Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM B L-16-1 NRC EXAM SECURE INFORMATION

01047016102 , Place Excess Letdown in Service, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 11 of 19 Performance Step:

6 Critical : No 3-OP-047 , Step 7.12.2.5

Slowly Open Excess Letdown Flow Controller, HCV 137, to allow excess letdown lines to backfill Standard: Slowly open HCV 137 by turning the controller's potentiometer clockwise. Performance:

SATISFACTORY UNSATISFACTORY Comments:

Performance Step:

7 Critical : No 3-OP-047 , Step 7.12.2.6

WHEN a minimum of 5 minutes have elapsed, THEN Close Excess Letdown Flow Controller, HCV 137 Standard: When 5 minutes have elapsed, close HCV 137 by turning the controller's potentiometer counterclockwise

. Evaluator Cue: When the requirement for the 5 minute wait is identified, state "using time compression, 5 minutes have elapsed

." Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM B L-16-1 NRC EXAM SECURE INFORMATION

01047016102 , Place Excess Letdown in Service, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 12 of 19 Performance Step:

8 Critical : Yes 3-OP-047 , Step 7.12.2.7

Open Excess Ltdn Isol Valve, CV-3-387 , AND observe Containment Sump level for indication that RV 304 may have lifted Standard: Open CV-3-387 (critical)

Monitor containment sump level and recognize that it is rising (NOT critical) Evaluator Note:

The examinee may continue with the procedure before noticing that the sump level is rising

t h is is addressed below. Annunciators G5/3 (CNTMT LEVEL INCREASING > 1 GPM) and G1/2 (CHARGING PUMP HI SPEED) will eventually actuate.

Evaluator Cue:

Acknowledge any communication to the Unit Supervisor. Booth Operator Cue

Verify that RV-3-304 Fails Open triggers when the control switch for CV-3-387 is taken to the OPEN position.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM B L-16-1 NRC EXAM SECURE INFORMATION

01047016102 , Place Excess Letdown in Service, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 13 of 19 Performance Step

9 Critical : No 3-OP-047 , Steps 7.12.2.8 and 7.12.2.9

Slowly Open Excess Letdown Flow Controller, HCV 137, allowing the heat exchanger to warm up

Monitor heat exchanger outlet temperature at Excess Ltdn Hx Temp Indicator, TI 139 Standard: Slowly open HCV 137, by turning the controller's potentiometer clockwise, and monitor TI 139. Evaluator Note: This step may not be performed i f the sump level is recognized as rising; if so, mark this step N/A

. Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM B L-16-1 NRC EXAM SECURE INFORMATION

01047016102 , Place Excess Letdown in Service, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 14 of 19 Performance Step:

10 Critical : No Review ARP for G5/3, CNTMT LEVEL INCREASING > 1 GPM Standard: Check Cntmt Sump Recorders: R

-1418 (VPA), R

-6308A/B (behind RCO desk) Monitor RCS parameters for indications of a RCS leak Monitor Component Cooling Water parameters for indication of a CCW System Leak Perform 3-OSP-041.1, Reactor Coolant System Leak Rate Calculation, to determine RCS leak rate G o to 3-ONOP-041.3, Excessive Reactor Coolant System Leakage, and take actions as directed Refer To Tech Spec 3.4.6.2 Evaluator Note: This step may be marked N/A if not used If applicable, state that the STA will perform the OSP leak rate Examinee may use 0

-ADM-211 guidance to close CV 387 and attempt to isolate the leak; CV-3-387 is failed open Evaluator Cue:

Acknowledge any communication to the Unit Supervisor. Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM B L-16-1 NRC EXAM SECURE INFORMATION

01047016102 , Place Excess Letdown in Service, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 15 of 19 Performance Step:

11 Critical : No Review ARP for G1/2 , CHARGING PUMP HI SPEED Standard: Check individual charging pump controller and the master charging pump controller IF leakage is confirmed, THEN go to 3-ONOP-041.3, Excessive Reactor Coolant System Leakage Evaluator Note: If requested, provi de examinee with a copy of handout 3-ONOP-041.3 This step may be marked N/A if not used Examinee may use 0

-ADM-211 guidance to close CV 387 and attempt to isolate the leak

CV-3-387 is failed open Evaluator Cue

Acknowledge any communication to the Unit Supervisor. Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM B L-16-1 NRC EXAM SECURE INFORMATION

01047016102 , Place Excess Letdown in Service, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 16 of 19 THIS BEGINS THE ALTERNATE

-PATH PORTION OF THE JPM Performance Step:

12 Critical : No Close CV-3-387 to isolate RCS leakage Standard: Take the control switch for CV-3-387 to CLOSE. Evaluator Note: Once the leakage is recognized the examinee may attempt to isolate the leak by closing CV 387; CV-3-387 is failed open If no attempt is made here to close CV-3-387 then mark the step N/A Evaluator Cue:

Acknowledge any communication to the Unit Supervisor. Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

13 Critical : No Enter 3-ONOP-041.3, Excessive Reactor Coolant System Leakag e Standard: Locate and enter 3-ONOP-041.3. Evaluator Note: Provide the examinee with a copy of HANDOUT 3-ONOP-041.3 If the ONOP was entered previously, mark this step as satisfactory Evaluator Cue:

Acknowledge any communication to the Unit Supervisor. Performance:

SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM B L-16-1 NRC EXAM SECURE INFORMATION

01047016102 , Place Excess Letdown in Service, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 17 of 19 Performance Step:

14 Critical : Yes 3-ONOP-0 41.3, Step 1: Maintain RCS Inventory Standard: Start additional charging pumps as necessary to maintain RCS Inventory. Evaluator Note: The examinee may first attempt to stabile pressurizer level by taking charging to manual and maximizing output Satisfactory completion of this step requires that pressurizer level is stabilized or trending to program Evaluator Cue:

Acknowledge any communication to the Unit Supervisor. Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

15 Critical : No 3-ONOP-0 41.3, Step 2: Check RCS Inventory Decreasing Standard: Recognize that RCS inventory is NOT lowering and proceed to Step 10 (per RNO). Performance:

SATISFACTORY UNSATISFACTORY Comments: Terminating Cue:

When it is recognized that RCS inventory is no longer decreasing, state "This completes the JPM.

" NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

Stop Time:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM B L-16-1 NRC EXAM SECURE INFORMATION

01047016102 , Place Excess Letdown in Service, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 18 of 19 Examinee: Evaluator:

RO SRO STA Non-Lic SRO CERT Date: LOIT RO LOIT SRO PERFORMANCE RESULTS:

SAT: UNSAT: Remediation required:

YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).

EXAMINER NOTE:

ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.

EVALUATOR'S SIGNATURE:

NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM B L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION JPM TURNOVER SHEET

INITIAL CONDITIONS:

Unit 3 is in M ode 1. Personnel are currently being briefed to perform maintenance and calibration on LCV 460, Letdown Isolation Valve

. INITIATING CUE S: In preparation for the isolation of normal letdown to support maintenance, the Unit Supervisor directs you to place excess letdown in service in accordance with Section 7.12 of 3

-OP-047, CVCS Charging and Letdown

. All applicable prerequisites in Section 3.0 are satisfied

.

NOTE: Ensure the turnover sheet is returned to the evaluator when the JPM is complete

. TR-AA-230-1003-F10, Revision 2 L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC Exam Control Room

- JPM C

L-16-1 NRC EXAM SECURE INFORMATION

JOB PERFORMANCE MEAS URE L-16-1 NRC EXAM SECURE INFORMATION JPM JPM TITLE:

Establish Auxiliary Pressurizer Spray JPM NUMBER:

010 41052100 REV. 0-0 TASK NUMBER(S) / TASK TITLE(S):

010 41052 100 / Initiate Pressurizer Auxiliary Spray K/A NUMBERS:

EPE 038 E A 1.0 4 K/A VALUE:

RO 4.3 / SRO 4.1 Justification (FOR K/A VALUES <3.0):

N/A TASK APPLICABILITY:

RO SRO STA Non-Lic SRO CERT OTHER: APPLICABLE METHOD OF TESTING:

Simulate/Walkthrough:

Perform: X EVALUATION LOCATION:

In-Plant: Control Room:

Simulator:

X Other: L ab: Time for Completion:

20 Minutes Time Critical:

No Alternate Path [NRC]:

Yes Alternate Path [INPO]:

Yes Developed by:

Brian Clark 8/4/16 Instructor/Developer Date Reviewed by: Tim Hodge 8/4/16 Instructor (Instructional Review)

Date Validated by:

Sean Bloom 8/5/16 SME (Technical Review)

Date Approved by:

Mark Wilson 8/4/16 Training Supervision Date Approved by:

Sean Bloom 8/5/16 Training Program Owne r Date TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM C L-16-1 NRC EXAM SECURE INFORMATION

01041052100 , Establish Auxiliary Pressurizer Spray , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 3 of 15 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A 1. Are all items on the signature page filled in correctly?

2. Has the JPM been reviewed and validated by SMEs?

3. Can the required conditions for the JPM be appropriately established in the simulator if required?

4. Do the performance steps accurately reflect trainee's actions in accordance with plant procedures?

5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?

6. Has the completion time been established based on validation data or incumbent experience?

7. If the task is time critical, is the time critical portion based upon actual task performance requirements?

8. Is the job level appropriate for the task being evaluated if required?

9. Is the K/A appropriate to the task and to the licensee level if required?

10. Is justification provided for tasks with K/A values less than 3.0?

11. Have the performance steps been identified and classified (Critical / Sequence / Time Critical) appropriately?

12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?

13. Are all references identified, current, accurate, and available to the trainee?

14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?

15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)

16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM? TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge.

All questions/statements must be answered "YES" or "N/A" or the JPM is not valid for use. If all questions/statements are answered "YES" or "N/A," then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.

Protected Conten t: (CAPRs, corrective actions, licensing commitments, etc. associated with this material

) N/A TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM C L-16-1 NRC EXAM SECURE INFORMATION

01041052100 , Establish Auxiliary Pressurizer Spray , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 4 of 15 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR

-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR

-AA-230-1003-F16. # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE SUPERVISOR DATE 0-0 New JPM L-16-1 NRC Exam N/A N/A N/A N/A N/A TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM C L-16-1 NRC EXAM SECURE INFORMATION

01041052100 , Establish Auxiliary Pressurizer Spray , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 5 of 15 SIMULATOR SET

-UP: SIMULATOR SETUP INSTRUCTIONS

_____ 1. Reset to IC 1 80 or saved IC. _____ 2. Place simulator in RUN.

_____ 3. Ensure applicable portions of Simulator Operator Checklist are complete.

_____ 4. N/A if using saved IC Open and execute L 1 NRC JPM C.lsn Verify PORVs FAILED CLOSE auto triggers Verify both WINDUP RESET triggers are in CONDITION state

_____ 5. Allow plant to stabilize.

_____ 6. Acknowledge alarms and place simulator in FREEZE.

_____ 7. Save as temporary IC, if JPM will be repeated.

_____ 8. When ready to begin, then place Simulator in RUN.

SIMULATOR MALFUNCTIONS:

TFHV456C: PORVs failed closed TFHV55CC: PORVs failed closed

SIMULATOR OVERRIDES:

N/A SIMULATOR REMOTE FUNCTIONS:

N/A

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM C L-16-1 NRC EXAM SECURE INFORMATION

01041052100 , Establish Auxiliary Pressurizer Spray , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 6 of 15 Required Materials:

HANDOUT 3-EOP-E-3 General

References:

3-E OP-E-3 , Steam Generator Tube Rupture Task Standards:

During RCS depressurization, recognize that the PORVs are NOT functional and, alternatively, establish auxiliary spray TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM C L-16-1 NRC EXAM SECURE INFORMATION

01041052100 , Establish Auxiliary Pressurizer Spray , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 7 of 15 HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.

INITIAL CONDITIONS:

Unit 3 tripped from full power, due to a tube failure in the 3A Steam Generator

. After the trip, a LOOP occurred and both EDGs started and loaded onto their respective bus.

The crew is performing 3-E OP-E-3 , Steam Generator Tube Rupture

. The 3A Steam Generator is isolated. The RCS cooldown has been completed.

INITIATING CUE:

The Unit Supervisor directs you to perform Step 1 8 of 3-EOP-E-3 to depressurize the RCS

.

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM C L-16-1 NRC EXAM SECURE INFORMATION

01041052100 , Establish Auxiliary Pressurizer Spray , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 8 of 15 JPM PERFORMANCE INFORMATION Start Time:

NOTE: When providing "Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically

, cues are only provided when the examinee's actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a "Y es" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step:

1 Critical : No Obtain required reference materials. Standard: Obtain 3-E OP-E-3 , Steam Generator Tube Rupture

. Evaluator Note: If a peer check is requested for any of the following steps, then acknowledge the request and allow the operator to continue.

Evaluator Cue:

Provide examinee with a cop y of HANDOUT 3-EOP-E-3. Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

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01041052100 , Establish Auxiliary Pressurizer Spray , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 9 of 15 Performance Step:

2 Critical : No 3-E OP-E-3 , prior to Step 18: C A U T I O N If a PRZ PORV is used to depressurize the RCS, the PRT rupture disk may rupture. This may result in abnormal Containment conditions

. Cycling of the PRZ PORV shall be minimized.

NOTE If RCPs are NOT running, the upper head region may void during RCS depressurization. This will result in a rapidly increasing PRZ level.

Standard: Read CAUTION/NOTE and determine it is satisfactory to proceed.

Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

3 Critical : No 3-E OP-E-3 , Step 18: Depressurize RCS Using PRZ PORV To Minimize Break Flow And Refill PRZ

a. Check PRZ PORV

- AT LEAST ONE AVAILABLE Standard: Check the pressurizer PORV light indications and recognize that both are available.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM C L-16-1 NRC EXAM SECURE INFORMATION

01041052100 , Establish Auxiliary Pressurizer Spray , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 10 of 15 THIS BEGINS THE ALTERNATE

-PATH PORTION OF THE JPM Performance Step:

4 Critical : No 3-E OP-E-3 , Step 18: Depressurize RCS Using PRZ PORV To Minimize Break Flow And Refill PRZ

b. Open one PRZ PORV until any of the following conditions satisfied-(NO) IF NO PORV can be opened, THEN establish Auxiliary Spray using Attachment 4 and return to Step 17.b. Standard: Recognize that neither PORV will open and transition to Attachment 4.

Evaluator Cue:

If examinee asks which PORV to manipulate, respond as the Unit Supervisor and state, "Use your own judgment."

Evaluator Note:

When examinee takes either PORV's handswitch to OPEN, the valve will NOT respond (i.e., it will remain closed).

Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

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01041052100 , Establish Auxiliary Pressurizer Spray , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 11 of 15 Performance Step:

5 Critical : Yes 3-E OP-E-3 , Attachment 4, Step 1

Verify Pressurizer Spray valves

- OPEN PCV-3-455A, Loop C PCV-3-455B, Loop B Standard: Open PCV-3-455B and PCV-3-455A , Pressurizer Spray Control Valves , Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

6 Critical : No 3-E OP-E-3 , Attachment 4, Step 2

Verify Aux Spray TI 123 And PRZ Temperature TI 454 Temperature Difference

- LESS THAN 320°F Standard: Verify that the difference between the indications on TI 123 , RHX Outlet Temperature Indicator

, and TI-3-454 , Pressurizer Steam Space Temperature Indicator

, are within 320°F.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM C L-16-1 NRC EXAM SECURE INFORMATION

01041052100 , Establish Auxiliary Pressurizer Spray , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 12 of 15 Performance Step:

7 Critical : Yes 3-E OP-E-3 , Attachment 4, Step 3

Open CV-3-311, Aux Spray Isolation Standard: Take the handswitch for CV 311 , Auxiliary Spray Control Valve

, to OPEN and verify that the red indicating light is lit and the green indicating light is extinguished

. Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

8 Critical : Yes 3-E OP-E-3 , Attachment 4, Step 4

Close CV-3-310A, Loop A Charging Isolation Standard: Take the handswitch for CV-3-310A , Charging to RCS Loop A Control Valve , to CLOSE and verify that the green indicating light is lit and the red indicating light is extinguished.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM C L-16-1 NRC EXAM SECURE INFORMATION

01041052100 , Establish Auxiliary Pressurizer Spray , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 13 of 15 Performance Step:

9 Critical : No 3-E OP-E-3 , Attachment 4, Step 5

Verify CV-3-310B, Loop C Charging Isolation, is CLOSED Standard: Recognize that CV 310B, Charging to RCS Loop B Control Valve, is closed (i.e., the green indicating light is lit and the red indicating light is NOT lit). Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

10 Critical : Yes 3-EOP-E-3, Attachment 4, Step 6:

Control Aux Spray as Follows:

Increase Auxiliary Spray flow by closing PCV 455A, Pressurizer Loop C, and/or PCV 455B, Pressurizer Loop B Reduce Auxiliary Spray flow by opening PCV 455A, Pressurizer Loop C, and/or PCV 455B, Pressurizer Spray Loop B Standard: Close PCV-3-455A/B as needed to increase spray flow and reduce pressurizer pressure.

Evaluator Note:

Only reducing pressurizer pressure is critical.

Performance:

SATISFACTORY UNSATISFACTORY Comments: Terminating Cue:

When RCS pressure is observed to be lowering

, state "This completes the JPM." NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

Stop Time:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM C L-16-1 NRC EXAM SECURE INFORMATION

01041052100 , Establish Auxiliary Pressurizer Spray , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 14 of 15 Examinee: Evaluator:

RO SRO STA Non-Lic SRO CERT Date: LOIT RO LOIT SRO PERFORMANCE RESULTS:

SAT: UNSAT: Remediation required:

YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).

EXAMINER NOTE:

ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.

EVALUATOR'S SIGNATURE:

NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM C L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION JPM TURNOVER SHEET

INITIAL CONDITIONS:

Unit 3 tripped from full power, due to a tube failure in the 3A Steam Generator

. After the trip, a LOOP occurred and both EDGs started and loaded onto their respective bus.

The crew is performing 3

-EOP-E-3, Steam Generator Tube Rupture.

The 3A Steam Generator is isolated.

The RCS cooldown has been completed.

INITIATING CUE

The Unit Supervisor directs you to perform Step 18 of 3

-EOP-E-3 to depressurize the RCS.

NOTE: Ensure the turnover sheet is returned to the evaluator when the JPM is complete

. TR-AA-230-1003-F10, Revision 2 L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC Exam Control Room

- JPM D

L-16-1 NRC EXAM SECURE INFORMATION

JOB PERFORMANCE MEAS URE L-16-1 NRC EXAM SECURE INFORMATION JPM JPM TITLE:

Respond to Loss of RHR JPM NUMBER:

01050004301 REV. 2-0 TASK NUMBER(S) / TASK TITLE(S):

01050004300

/ Respond to Loss of RHR K/A NUMBERS:

APE 025 AA1.03 K/A VALUE:

RO 3.4 / SRO 3.3 Justification (FOR K/A VALUES <3.0):

N/A TASK APPLICABILITY:

RO SRO STA Non-Lic SRO CERT OTHER: APPLICABLE METHOD OF TESTING:

Simulate/Walkthrough:

Perform: X EVALUATION LOCATION:

In-Plant: Control Room:

Simulator:

X Other: L ab: Time for Completion:

20 Minutes Time Critical:

No Alternate Path [NRC]:

No Alternate Path [INPO]:

No Developed by:

Brian Clark 8/4/16 Instructor/Developer Date Reviewed by: Tim Hodge 8/4/16 Instructor (Instructional Review)

Date Validated by:

Sean Bloom 8/5/16 SME (Technical Review)

Date Approved by:

Mark Wilson 8/4/16 Training Supervision Date Approved by:

Sean Bloom 8/5/16 Training Program Owner Date TR-AA-230-1 003-F10, Revision 2 NRC Control Room

- JPM D L-16-1 NRC EXAM SECURE INFORMATION

01050004301 , Respond to Loss of RHR, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 3 of 18 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A 1. Are all items on the signature page filled in correctly?

2. Has the JPM been reviewed and validated by SMEs?

3. Can the required conditions for the JPM be appropriately established in the simulator if required?

4. Do the performance steps accurately reflect trainee's actions in accordance with plant procedures?

5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?

6. Has the completion time been established based on validation data or incumbent experience?

7. If the task is time critical, is the time critical portion based upon actual task performance requirements?

8. Is the job level appropriate for the task being evaluated if required?

9. Is the K/A appropriate to the task and to the licensee level if required?

10. Is justification provided for tasks with K/A values less than 3.0?

11. Have the performance steps been identified and classified (Critical / Sequence / Time Critical) appropriately?

12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?

13. Are all references identified, current, accurate, and available to the trainee?

14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?

15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)

16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM? TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge.

All questions/statements must be answered "YES" or "N/A" or the JPM is not valid for use. If all questions/statements are answered "YES" or "N/A," then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.

Protected Conten t: (CAPRs, corrective actions, licensing commitments, etc. associated with this material

) N/A TR-AA-230-1 003-F10, Revision 2 NRC Control Room

- JPM D L-16-1 NRC EXAM SECURE INFORMATION

01050004301 , Respond to Loss of RHR, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 4 of 18 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR

-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR

-AA-230-1003-F16. # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE SUPERVISOR DATE 1-0 Updated to fleet template; text/grammar changes Updated for 2014 LOIT Annual Exam 1982463 N/A N/A N/A N/A 1-1 Validation time, Formatting , Enhance cues NRC Validation N/A Hodge 12/19/14 Wils on 12/22/14 2-0 Formatting; text/grammar changes L-16-1 NRC Exam N/A N/A N/A N/A N/A TR-AA-230-1 003-F10, Revision 2 NRC Control Room

- JPM D L-16-1 NRC EXAM SECURE INFORMATION

01050004301 , Respond to Loss of RHR, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 5 of 18 SIMULATOR SET

-UP: SIMULATOR SETUP INSTRUCTIONS

_____ 1. Reset to IC 30 or saved IC. _____ 2. NO-OP Cond & Feedwater and Steam Generators.

_____ 3. Place simulator in RUN.

_____ 4. Verify MODE 4 valve placards are in place. _____ 5. Ensure applicable portions of Simulator Operator Checklist are complete.

_____ 6. Open and execute L-16-1 NRC JPM D.lsn. _____ 7. Allow plant to stabilize (allow auto makeup to complete)

. _____ 8. Acknowledge alarms and place simulator in FREEZE.

_____ 9. Save as temporary IC, if JPM will be repeated.

_____ 10. When ready to begin, then place Simulator in RUN.

SIMULATOR MALFUNCTIONS:

TFMUM01S: 3A RHR Pump Shaft Shear IMM1S03C: MOV 750 Drifts Closed SIMULATOR OVERRIDES:

N/A SIMULATOR REMOTE FUNCTIONS:

N/A

TR-AA-230-1 003-F10, Revision 2 NRC Control Room

- JPM D L-16-1 NRC EXAM SECURE INFORMATION

01050004301 , Respond to Loss of RHR, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 6 of 18 Required Materials:

HANDOUT 3-ONOP-050 General

References:

3-ONOP-050 , Loss of RHR 3-ARP-097.CR, Annunciator Response Procedures Task Standards:

Re-open MOV-3-750 Restart 3B RHR Pump Open FCV-3-605 to restore RHR flow to the core TR-AA-230-1 003-F10, Revision 2 NRC Control Room

- JPM D L-16-1 NRC EXAM SECURE INFORMATION

01050004301 , Respond to Loss of RHR, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 7 of 18 HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.

INITIAL CONDITIONS:

Unit 3 is in Mode 4

. The 3A RHR Pump is in service and providing core cooling. INITIATING CUE:

The Unit Supervisor has directed the crew to maintain current conditions

.

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

TR-AA-230-1 003-F10, Revision 2 NRC Control Room

- JPM D L-16-1 NRC EXAM SECURE INFORMATION

01050004301 , Respond to Loss of RHR, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 8 of 18 JPM PERFORMANCE INFORMATION Start Time: NOTE: When providing "Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically

, cues are only provided when the examinee's actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a "Y es" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

NOTE: 0-ADM-211, Emergency and Off

-Normal Operating Procedure Usage (Prudent Operator Actions) - If redundant standby equipment is available and ready, the operator is permitted to start the redundant equipment for failed or failing operating equipment. Immediate follow

-up of applicable ARPs or ONOPs shall occur as required. Performance Step:

1 Critical: No Recognize closure of MOV 750 Standard: Recognize closure of MOV 750 and enter 3

-ONOP-050 , Loss of RHR

. Evaluator Note: If a peer check is requested for any of the following steps, then acknowledge the request and allow the operator to continue When ready to begin, have booth operator trigger MOV-3-750 DRIFTS CLOSE D Annunciator H 6/2 (RHR HX HI/LO FLOW

) will eventually actuate; i f the ARP is used, it will direct the use of 3-ONOP-050 Evaluator Cue:

Provide operator with a copy of HANDOUT 3-ONOP-050 If auto makeup occurs, state that "Another operator will monitor

" Booth Operator Cue:

After triggering MOV-3-750 DRIFTS CLOSE D, verify that ALLOW MOV-3-750 TO REOPEN triggers. Performance:

SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1 003-F10, Revision 2 NRC Control Room

- JPM D L-16-1 NRC EXAM SECURE INFORMATION

01050004301 , Respond to Loss of RHR, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 9 of 18 Performance Step:

2 Critical: No 3-ONOP-050 , Step 1: Check If RHR Pumps Should B e Stopped a. RCS level

- GREATER THAN 10% PRESSURIZER COLD CAL

b. RHR pumps

- ANY RUNNING

c. RHR pumps

- NOT CAVITATING Standard: Stop the 3A RHR Pump, if desired. Evaluator Note: The examinee may observe the running pump with little or no flow and elect to stop the pump as a prompt/prudent action; if this occurs, mark Step 4 below as complete (i.e., securing the 3A RHR Pump is th e critical step, but when this happens is NOT critical)

Alternatively, the examinee may elect to depress the MOV 750 "interrupt" pushbutton at this time (or earlier); if this occurs, a 3A RHR t the results as a non

-running pump and proceed to Step 2, per the Step 1.b RNO Booth Operator Note: If the "interrupt" pushbutton is depressed, verify 3A RHR PUMP SHAFT SHEAR triggers. Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1 003-F10, Revision 2 NRC Control Room

- JPM D L-16-1 NRC EXAM SECURE INFORMATION

01050004301 , Respond to Loss of RHR, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 10 of 18 Performance Step:

3 Critical: No 3-ONOP-050 , Step 2: Check Loop 3C RHR Pump Suction Stop Valves

- OPEN MOV-3-750 MOV-3-751 Standard: Recognize that MOV-3-750 is closed/closing and enter the RNO step. Performance:

SATISFACTORY UNSATISFACTORY Comments:

Performance Step:

4 Critical: Yes 3-ONOP-050 , Step 2.a (RNO):

Stop RHR Pumps Standard: Secure the 3A RHR Pump.

Evaluator Note: This action may have been performed in Step 2 above; in either case, record the completion here

. Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1 003-F10, Revision 2 NRC Control Room

- JPM D L-16-1 NRC EXAM SECURE INFORMATION

01050004301 , Respond to Loss of RHR, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 11 of 18 Performance Step:

5 Critical: Yes 3-ONOP-050 , Step 2.b (RNO):

IF a momentary pressure spike has caused either or both valves to start closing, THEN perform the following at the Pushbutton Interrupt switches: 1) Determine affected valve(s) Yellow light

- ON 2) Verify over pressure signal NOT present Blue light

- ON 3) Push Interrupt Pushbutton for affected valve(s) 4) Verify yellow light

- DEENERGIZES

5) WHEN blue light DEENERGIZES, THEN verify affected valve(s) - OPEN 6) IF both valves are open, THEN go to Step 3 Standard: Reopen MOV-3-750. Evaluator Note: The examinee may have reopened the valve previously (prior to entering the ONOP) as a prompt/prudent acti on In either case, record the completion here; opening the valve is the critical step, but when this happens is NOT critical Booth Operator:

When the "interrupt" pushbutton is depressed, verify 3A RHR PUMP SHAFT SHEAR triggers. If "interrupt" pushbutton is never pressed, trigger will NOT auto trigger. If this is the case, manually activate the trigger when the valve is taken to OPEN position.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1 003-F10, Revision 2 NRC Control Room

- JPM D L-16-1 NRC EXAM SECURE INFORMATION

01050004301 , Respond to Loss of RHR, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 12 of 18 Performance Step:

6 Critical: No 3-ONOP-050 , Step 3: Dispatch An Operator To Monitor RHR Pumps Standard: Direct a field operator to locally monitor the RHR pumps. Booth Operator Cue:

Acknowledge request to monitor RHR pumps and report that both RHR pumps are secured.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

Performance Step:

7 Critical: No 3-ONOP-050 , Step 4: Monitor RCS Heatup Rate Standard: Per the NOTE prior to Step 4, direct the STA or available operator to monitor RCS heatup rate.

Evaluator Cue: Acknowledge request to monitor RCS heatup rate.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1 003-F10, Revision 2 NRC Control Room

- JPM D L-16-1 NRC EXAM SECURE INFORMATION

01050004301 , Respond to Loss of RHR, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 13 of 18 Performance Step:

8 Critical: No 3-ONOP-050, Step 5:

Verify RHR Discharge to Cold Leg Isolation Valves

- OPEN MOV-3-744A MOV-3-744B Standard: Verify that MOV-3-744A and MOV 744B are OPEN.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

Performance Step:

9 Critical: Yes 3-ONOP-050, Step 6: Establish Conditions For Restarti ng An RHR Pump

a. RHR Pumps

- BOTH STOPPED

b. Close RHR Heat Exchanger Outlet Flow valve, HCV 758 c. Close RHR Heat Exchanger Bypass Flow valve, FCV 605 d. Verify MOV 750 and MOV 751 - OPEN Standard: Close HCV-3-758 and FCV 605. Evaluator Note: Only the valve closures are critical

. Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1 003-F10, Revision 2 NRC Control Room

- JPM D L-16-1 NRC EXAM SECURE INFORMATION

01050004301 , Respond to Loss of RHR, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 14 of 18 Performance Step:

10 Critical: No 3-ONOP-050, Step 6: Establish Conditions For Restarting An RHR Pump

e. Start the previously running RHR pump Standard: Start the 3A RHR Pump , recognize that its shaft is sheared, secure the pump, and proceed to the RNO step

. Evaluator Note:

If shaft shear recognized prior to this step, examinee may choose not to attempt to start the pump, this is acceptable Motor amps will be low (due to the sheared shaft

) and flow will be zero (due to the pump discharge valves being closed

); the examinee may not recognize the sheared shaft until Step 6.f below, when MOV 605 is opened and no flow is observed If the 3A RHR Pump is secured, t he examinee may also elect to place the pump in PTL Booth Operator Cue:

If asked about the 3A RHR Pump

's status, report the following:

If the examinee has recognized the sheared shaft, then report that the motor is running but no flow noise is heard Otherwise, report that there is nothing obviously wrong with the pump Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1 003-F10, Revision 2 NRC Control Room

- JPM D L-16-1 NRC EXAM SECURE INFORMATION

01050004301 , Respond to Loss of RHR, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 15 of 18 Performance Step:

11 Critical: Yes 3-ONOP-050, Step 6.e (RNO): Start the Standby RHR pump Standard: Start the 3 B RHR Pump. Booth Operator Cue: If contacted, report a satisfactory start of the 3B RHR Pump.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

Performance Step:

12 Critical: Yes 3-ONOP-050, Step 6

.f: Return RHR Heat Exchanger Bypass Flow valve, FCV 605, to AUTOMATIC operation increasing flow in increments of 500 gpm until desired flow is established Standard: Reopen FCV 605 and raise RHR flow until annunciator H6/2 clears

. Evaluator Note:

The examinee may not recognize until this point that the 3A RHR Pump's shaft has sheared The setpoints for annunciator H6/2 are <3000 gpm and >3750 gpm Opening the valve and clearing the alarm are critical, but NOT the incremental operation Performance:

SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1 003-F10, Revision 2 NRC Control Room

- JPM D L-16-1 NRC EXAM SECURE INFORMATION

01050004301 , Respond to Loss of RHR, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 16 of 18 Performance Step:

13 Critical: No 3-ONOP-050, Step 6

.g: Open RHR Heat Exchanger Outlet Flow valve, HCV 758, as necessary to maintain desired RCS temperature Standard: Maintain RCS temperature

. Evaluator Note:

The examinee may leave HCV-3-758 closed or throttle it open to establish a slight cooldown

either is acceptable

. Performance:

SATISFACTORY UNSATISFACTORY Comments: Terminating Cue:

When examinee has restored core cooling

, state "This completes the JPM."

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

Stop Time:

TR-AA-230-1 003-F10, Revision 2 NRC Control Room

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01050004301 , Respond to Loss of RHR, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 17 of 18 Examinee: Evaluator:

RO SRO STA Non-Lic SRO CERT Date: LOIT RO LOIT SRO PERFORMANCE RESULTS:

SAT: UNSAT: Remediation required:

YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).

EXAMINER NOTE:

ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.

EVALUATOR'S SIGNATURE:

NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.TR-AA-230-1 003-F10, Revision 2 NRC Control Room

- JPM D L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION JPM TURNOVER SHEET

INITIAL CONDITIONS:

Unit 3 is in Mode 4

. The 3A RHR Pump is in service and providing core cooling

. INITIATING CUE

The Unit Supervisor has directed the crew to maintain current conditions

.

NOTE: Ensure the turnover sheet is returned to the evaluator when the JPM is complete

. TR-AA-230-1003-F10, Revision 2 L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC Exam Control Room

- JPM E

L-16-1 NRC EXAM SECURE INFORMATION

JOB PERFORMANCE MEASURE L-16-1 NRC EXAM SECURE INFORMATION JPM JPM TITLE:

Manually Initiate Containment Spray JPM NUMBER: 0106800750 2 REV. 1-0 TASK NUMBER(S) / TASK TITLE(S):

0106800750 0 / Manually Initiate Containment Spray K/A NUMBERS:

026 A3.01 K/A VALUE:

RO 4.3 / SRO 4.5 Justification (FOR K/A VALUES <3.0):

N/A TASK APPLICABILITY:

RO SRO STA Non-Lic SRO CERT OTHER: APPLICABLE METHOD OF TESTING:

Simulate/Walkthrough:

Perform: X EVALUATION LOCATION:

In-Plant: Control Room:

Simulator:

X Other: L ab: Time for Completion:

15 Minutes Time Critical:

No Alternate Path [NRC]:

No Alternate Path [INPO]:

No Developed by:

Brian Clark 8/4/16 Instructor/Developer Date Reviewed by: Tim Hodge 8/4/16 Instructor (Instructional Review)

Date Validated by:

Sean Bloom 8/5/16 SME (Technical Review)

Date Approved by:

Mark Wilson 8/4/16 Training Supervision Date Approved by:

Sean Bloom 8/5/16 Training Program Owner Date TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM E L-16-1 NRC EXAM SECURE INFORMATION

010 68007502 , Manually Initiate Containment Spray, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 3 of 16 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A 1. Are all items on the signature page filled in correctly?

2. Has the JPM been reviewed and validated by SMEs?

3. Can the required conditions for the JPM be appropriately established in the simulator if required?

4. Do the performance steps accurately reflect trainee's actions in accordance with plant procedures?

5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?

6. Has the completion time been established based on validation data or incumbent experience?

7. If the task is time critical, is the time critical portion based upon actual task performance requirements?

8. Is the job level appropriate for the task being evaluated if required?

9. Is the K/A appropriate to the task and to the licensee level if required?

10. Is justification provided for tasks with K/A values less than 3.0?

11. Have the performance steps been identified and classified (Critical / Sequence / Time Critical) appropriately?

12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?

13. Are all references identified, current, accurate, and available to the trainee?

14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?

15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)

16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM? TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge.

All questions/statements must be answered "YES" or "N/A" or the JPM is not valid for use. If all questions/statements are answered "YES" or "N/A," then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.

Protected Conten t: (CAPRs, corrective actions, licensing commitments, etc. associated with this material

) N/A TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM E L-16-1 NRC EXAM SECURE INFORMATION

010 68007502 , Manually Initiate Containment Spray, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 4 of 16 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR

-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR

-AA-230-1003-F16. # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE SUPERVISOR DATE 0-0 New JPM 2015 LOCT Annual Exam N/A N/A N/A N/A N/A 1-0 Formatting; text/grammar changes L-16-1 NRC Exam N/A N/A N/A N/A N/A TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM E L-16-1 NRC EXAM SECURE INFORMATION

010 68007502 , Manually Initiate Containment Spray, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 5 of 16 SIMULATOR SET

-UP: SIMULATOR SETUP INSTRUCTIONS

_____ 1. Reset to IC 1 or saved IC. _____ 2. Place simulator in RUN.

_____ 3. Ensure applicable portions of Simulator Operator Checklist are complete.

_____ 4. N/A if using saved IC Open and execute L-16-1 NRC JPM E: a. Trigger lesson step LBLOCA WITH CTMT SPRAY FAILURE

b. Wait 5 minutes for other triggers to auto trigger

c. Place Main Feedwater Pump switches to STOP

_____ 5. Allow plant to stabilize.

_____ 6. Acknowledge alarms and place simulator in FREEZE.

_____ 7. Save as temporary IC, if JPM will be repeated.

_____ 8. When ready to begin, then place Simulator in RUN.

SIMULATOR MALFUNCTIONS:

TFL3S1 & TFL3S2: L3

-S1 & L3-S2 Fails to Actuate TFL3B11 & TFL3B1: L3

-CIB11 & L3

-CIB1 Fails to Actuate TVHHCLB: Large Break LOCA SIMULATOR OVERRIDES:

N/A SIMULATOR REMOTE FUNCTIONS:

N/A

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM E L-16-1 NRC EXAM SECURE INFORMATION

010 68007502 , Manually Initiate Containment Spray, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 6 of 16 Required Materials:

HANDOUT Attachment 3 General

References:

3-EOP-E-0, Reactor Trip or Safety Injection Task Standards:

Manually initiate at least one train of containment spray, by starting at least one CSP and opening its associated discharge isolation valve Manually close MOV-3-716B, MOV-3-626, and MOV 730 Stop all RCPs Secure the Unit 4 HHSI pumps TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM E L-16-1 NRC EXAM SECURE INFORMATION

010 68007502 , Manually Initiate Containment Spray, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 7 of 16 HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.

INITIAL CONDITIONS:

The Unit 3 reactor tripped due to a LOCA inside containment

. Safety injection has actuated

. Phase A containment isolation has actuated.

The crew has completed Step 5 of 3-EOP-E-0, Reactor Trip or Safety Injection

. INITIATING CUE:

You are directed to complete Attachment 3, Prompt Action Verifications, of 3

-EOP-E-0 starting with Step 8

.

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM E L-16-1 NRC EXAM SECURE INFORMATION

010 68007502 , Manually Initiate Containment Spray, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 8 of 16 JPM PERFORMANCE INFORMATION Start Time:

NOTE: When providing "Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically

, cues are only provided when the examinee's acti ons warrant receiving the information (i.e., the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a "Y es" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM. NOTE: Annunciators will be continuously coming in during the performance of th is JPM. Determine and coordinate with the Booth Operator how this will be handled prior to administering the JPM. Performance Step:

1 Critical:

No Obtain required materials. Standard: Obtain Attachment 3, Prompt Action Verifications, of 3

-EOP-E-0, Reactor Trip or Safety Injection

. Evaluator Note: If a peer check is requested for any of the following steps, then acknowledge the request and allow the operator to continue Examinee may notice at any time that phase B failed to actuate and may choose to manually initiate it

phase B will NOT initiate , but it is acceptable for them to attempt it Evaluator Cue

Provide examinee with a copy of HANDOUT Attachment 3

. Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM E L-16-1 NRC EXAM SECURE INFORMATION

010 68007502 , Manually Initiate Containment Spray, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 9 of 16 Performance Step:

2 Critical:

No 3-E OP-E-0 , Attachment 3

, Step 8: Verify Containment Cooling:

a. Check Emergency Containment Coolers

- ONLY TWO RUNNING Standard: Recognize that two ECCs are running

. Performance:

SATISFACTORY UNSATISFACTORY Comments:

Performance Step:

3 Critical:

No 3-EOP-E-0, Attachment 3, Step 9: Verify Containment Ventilation Isolation:

a. Unit 3 Containment Purge Exhaust And Supply Fans - OFF Standard: Recognize that the containment purge supply and exhaust fans are OFF

. Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM E L-16-1 NRC EXAM SECURE INFORMATION

010 68007502 , Manually Initiate Containment Spray, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 10 of 16 Performance Step:

4 Critical:

No 3-EOP-E-0, Attachment 3, Step 10: Verify Containment Spray NOT Required:

a. Containment pressure

- HAS REMAINED LESS THAN 20 PSIG PR-3-6306A PR-3-6306B Standard: Recognize that containment pressure has NOT remained <20 psig and proceed to Step 10.a (RNO)

. Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

5 Critical: Yes 3-EOP-E-0, Attachment 3, Step 10.a (RNO)

Perform the following:

1) IF Containment Spray NOT initiated, THEN manually initiate Containment Spray Standard: Start at least one CSP by taking its control switch to START Open the associated discharge valve, MOV-3-880A/B, by taking its control switch to OPEN Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM E L-16-1 NRC EXAM SECURE INFORMATION

010 68007502 , Manually Initiate Containment Spray, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 11 of 16 Performance Step:

6 Critical:

No 3-EOP-E-0, Attachment 3, Step 10.a (RNO)

Perform the following:

2) Verify Containment Isolation Phase B has actuated Standard: Recognize that Phase B containment isolation did NOT actuate and depress both Phase B Isolation pushbuttons

. Performance:

SATISFACTORY UNSATISFACTORY Comments:

Performance Step:

7 Critical: Yes 3-EOP-E-0, Attachment 3, Step 10.a (RNO)

Perform the following:

3) Verify Containment Isolation Phase B Valve white lights on VPB are all bright 4) IF any Containment Isolation Phase B Valve did NOT close, THEN manually or locally isolate affected Containment Penetration Standard: Recognize that the following valves did NOT close and take their control switches to CLOSE:

MOV-3-716B, CCW to RCP Inlet MOV-3-626, RCP Seal Cooling Water Outlet MOV-3-730, RCP Bearing Cooling Water Outlet Performance:

SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM E L-16-1 NRC EXAM SECURE INFORMATION

010 68007502 , Manually Initiate Containment Spray, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 12 of 16 Performance Step:

8 Critical: Yes 3-EOP-E-0, Attachment 3, Step 10.a (RNO):

Perform the following:

5) Stop all RCPs Standard: Secure all running RCPs.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

Performance Step:

9 Critical:

No 3-EOP-E-0, Attachment 3, Step 11:

Verify SI

- RESET Standard: Recognize that SI is NOT reset and reset SI by depressing BOTH reset pushbuttons

. Performance:

SATISFACTORY UNSATISFACTORY Comments:

Performance Step:

1 0 Critical:

No 3-EOP-E-0, Attachment 3, Step 1 2: Verify SI Valve Amber Lights On VPB

- ALL BRIGHT Standard: Recognize that all SI status lights are bright.

Performance:

SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM E L-16-1 NRC EXAM SECURE INFORMATION

010 68007502 , Manually Initiate Containment Spray, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 13 of 16 Performance Step:

1 1 Critical:

No 3-EOP-E-0, Attachment 3, Step 1 3: Verify SI Flow:

a. RCS pressure

- LESS THAN 1625 PSIG[1950 PSIG]

b. High-Head SI Pump flow indicator - CHECK FOR FLOW

c. RCS pressure

- LESS THAN 275 PSIG[575 PSIG]

d. RHR Pump flow indicator

- CHECK FOR FLOW Standard: Recognize that all pressure and flow conditions are met. Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

1 2 Critical:

No 3-EOP-E-0, Attachment 3, Step 1 4: Realign SI System:

a. Check Procedure Entry Status

- E-0 ENTERED FROM 3-ONOP-047.1, LOSS OF CHARGING FLOW IN MODES 1 THROUGH 4 Standard: Recognize that the condition is NOT met and proceed to the RNO step.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM E L-16-1 NRC EXAM SECURE INFORMATION

010 68007502 , Manually Initiate Containment Spray, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 14 of 16 Performance Step:

1 3 Critical:

No 3-EOP-E-0, Attachment 3, Step 14.a (RNO): Go to Attachment 3, Step 14.e Standard: Proceed to Step 14.e. Performance:

SATISFACTORY UNSATISFACTORY Comments:

Performance Step:

1 4 Critical:

No 3-EOP-E-0, Attachment 3, Step s 14.e and 14.f

Verify Unit 3 High

-Head SI Pumps

- TWO RUNNING Stop both Unit 4 High

-Head SI Pumps and place in Standby Standard: Recognize that both Unit 3 HHSI pumps are running and secure both Unit 4 HHSI pumps by taking their control switches to STOP

. Booth Operator Cue:

If contacted as the Unit 4 RCO, state that Unit 4 does NOT require its HHSI pumps to be running.

Performance:

SATISFACTORY UNSATISFACTORY Comments: Terminating Cue:

When the Unit 4 HHSI pumps have been secured, state "This completes the JPM."

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

Stop Time:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM E L-16-1 NRC EXAM SECURE INFORMATION

010 68007502 , Manually Initiate Containment Spray, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 15 of 16 Examinee: Evaluator:

RO SRO STA Non-Lic SRO CERT Date: LOIT RO LOIT SRO PERFORMANCE RESULTS:

SAT: UNSAT: Remediation required:

YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).

EXAMINER NOTE:

ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.

EVALUATOR'S SIGNATURE:

NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM E L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION JPM TURNOVER SHEET

INITIAL CONDITIONS:

The Unit 3 reactor tripped due to a LOCA inside containment

. Safety injection has actuated.

Phase A containment isolation has actuated.

The crew has completed Step 5 of 3

-EOP-E-0, Reactor Trip or Safety Injection

. INITIATING CUE

You are directed to complete Attachment 3, Prompt Action Verifications, of 3-EOP-E-0 starting with Step 8

.

NOTE: Ensure the turnover sheet is returned to the evaluator when the JPM is complete

. TR-AA-230-1003-F10, Revision 2 L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC Exam Control Room

- JPM F

L-16-1 NRC EXAM SECURE INFORMATION

JOB PERFORMANCE MEAS URE L-16-1 NRC EXAM SECURE INFORMATION JPM JPM TITLE:

Restore Power to the 3A 4KV Bus JPM NUMBER: 03005032300 REV. 0-0 TASK NUMBER(S) / TASK TITLE(S):

03005032300

/ Cross-Tie 3D and 4D 4KV Buses K/A NUMBERS:

EPE 0 55 E A 1.0 7 K/A VALUE:

RO 4.3 / SRO 4.5 Justification (FOR K/A VALUES <3.0):

N/A TASK APPLICABILITY:

RO SRO STA Non-Lic SRO CERT OTHER: APPLICABLE METHOD OF TESTING:

Simulate/Walkthrough:

Perform: X EVALUATION LOCATION:

In-Plant: Control Room:

Simulator:

X Other: L ab: Time for Completion:

15 Minutes Time Critical:

Yes Alternate Path [NRC]:

Yes Alternate Path [INPO]:

Yes Developed by:

Brian Clark 8/4/16 Instructor/Developer Date Reviewed by:

Tim Hodge 8/4/16 Instructor (Instructional Review)

Date Validated by:

Sean Bloom 8/5/16 SME (Technical Review)

Date Approved by:

Mark Wilson 8/4/16 Training Supervision Date Approved by:

Sean Bloom 8/5/16 Training Program Own er Date TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM F L-16-1 NRC EXAM SECURE INFORMATION

03005032300 , Restore Power to the 3A 4KV Bus , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 3 of 27 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A 1. Are all items on the signature page filled in correctly?

2. Has the JPM been reviewed and validated by SMEs?

3. Can the required conditions for the JPM be appropriately established in the simulator if required?

4. Do the performance steps accurately reflect trainee's actions in accordance with plant procedures?

5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?

6. Has the completion time been established based on validation data or incumbent experience?

7. If the task is time critical, is the time critical portion based upon actual task performance requirements?

8. Is the job level appropriate for the task being evaluated if required?

9. Is the K/A appropriate to the task and to the licensee level if required?

10. Is justification provided for tasks with K/A values less than 3.0?

11. Have the performance steps been identified and classified (Critical / Sequence / Time Critical) appropriately?

12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?

13. Are all references identified, current, accurate, and available to the trainee?

14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?

15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)

16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM? TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge.

All questions/statements must be answered "YES" or "N/A" or the JPM is not valid for use. If all questions/statements are answered "YES" or "N/A," then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.

Protected Conten t: (CAPRs, corrective actions, licensing commitments, etc. associated with this material

) N/A TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM F L-16-1 NRC EXAM SECURE INFORMATION

03005032300 , Restore Power to the 3A 4KV Bus , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 4 of 27 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR

-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR

-AA-230-1003-F16. # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE SUPERVISOR DATE 0-0 New JPM L-16-1 NRC Exam N/A N/A N/A N/A N/A TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM F L-16-1 NRC EXAM SECURE INFORMATION

03005032300 , Restore Power to the 3A 4KV Bus , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 5 of 27 SIMULATOR SET

-UP: SIMULATOR SETUP INSTRUCTIONS

_____ 1. Reset to IC 1 or saved IC. _____ 2. Place simulator in RUN.

_____ 3. Ensure applicable portions of Simulator Operator Checklist are complete.

_____ 4. N/A if using saved IC Open and execute lesson L 1 NRC JPM F

a. Trigger SETUP - 3A EDG FAILURE & RX TRIP b. Verify SETUP - LOOP & BUS LOCKOUTS auto triggers (60 sec delay)

c. Reduce total AFW flow to between 400 and 450 gpm

d. Select "Silence All" in Main Menu of Orchid to disable the Annunciators

_____ 5. Allow plant to stabilize.

_____ 6. Acknowledge alarms and place simulator in FREEZE.

_____ 7. Ensure Key 82 is available and functions to operate SBO Tie Breaker.

_____ 8. Ensure Key Log is clean and a fresh logout page is available

. _____ 9. Save as temporary IC, if JPM will be repeat ed. _____ 10. When ready to begin, then place Simulator in RUN.

SIMULATOR MALFUNCTIONS:

TFQ5GAFS: 3A EDG START FAILURE TFE2Z51S: 3B BUS LOCKOUT TFE2Z53S: 3D BUS LOCKOUT (reset enabled)

TFP8D6MT & TFP8D6BT: LOSS OF UNIT 3 STARTUP TRANSFORMER TFP8D8MT & TFP8D8BT: LOSS OF UNIT 4 STARTUP TRANSFORMER TFP8D3MT & TFP8D3BT: LOSS OF 3C TRANSFORMER TFH2FTRA/B/C: TRIP RCPS (setup)

SIMULATOR OVERRIDES:

A302_A1_S14_3: FAILURE OF EDG EMERGENCY CONTROL SWITCH

SIMULATOR REMOTE FUNCTIONS:

TCE2E33C: CLOSE 4AD07 TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM F L-16-1 NRC EXAM SECURE INFORMATION

03005032300 , Restore Power to the 3A 4KV Bus , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 6 of 27 Required Materials:

HANDOUT 3-EOP-E CA-0.0 Key 82 General

References:

3-E OP- ECA-0.0 , Loss of All AC Power 3-EOP-E-0, Reactor Trip or Safety Injection Task Standards:

Reset lockout on 3D 3kV bus.

Realign 3D bus to 3A bus.

Close SBO tie breaker 3AD07. Restore power to 3A 4kV bus within 10 minutes.

(0-ADM-232) TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM F L-16-1 NRC EXAM SECURE INFORMATION

03005032300 , Restore Power to the 3A 4KV Bus , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 7 of 27 HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.

INITIAL CONDITIONS:

Unit 3 tripped from full power, due to a loss of offsite power

. The plant is in a normal electrical alignment.

While performing the IOAs of 3

-EOP-E-0, Reactor Trip or Safety Injection, the crew recognized the following:

The 3A EDG did NOT start.

The 3B EDG started but did not energize the 3B 4kv bus. The crew transitioned to 3-EOP-ECA-0.0, Loss of All AC Power, and have completed through Step 4. INITIATING CUE:

The Unit Supervisor directs you to perform Step 5 of 3

-EOP-ECA-0.0, with a priority on the 3B EDG. Some elements of this JPM are time-critical.

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM F L-16-1 NRC EXAM SECURE INFORMATION

03005032300 , Restore Power to the 3A 4KV Bus , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 8 of 27 JPM PERFORMANCE INFORMATION Start Time:

NOTE: When providing "Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically

, cues are only provided when the examinee's actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a "Y es" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step:

1 Critical: No Obtain required reference materials. Standard: Obtain 3-EOP-ECA-0.0 , Loss of All AC Power

. Evaluator Note: If a peer check is requested for any of the following steps, then acknowledge the request and allow the operator to continue.

Evaluator Cue:

Provide examinee with a cop y of HANDOUT 3-EOP-ECA-0.0. Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM F L-16-1 NRC EXAM SECURE INFORMATION

03005032300 , Restore Power to the 3A 4KV Bus , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 9 of 27 Performance Step:

2 Critical: No 3-E OP-E CA-0.0 , prior to Step 5: NOTE The Unit Supervisor shall evaluate plant conditions and establish EDG Priority. Standard: R ead NOTE and recognize that it is safe to proceed

. Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

3 Critical: No 3-E OP-ECA-0.0 , Step 5: Try To Restore Power To 3A OR 3B 4KV Bus

a. Check EDG Priority

- 3 A (NO) Standard: Recognize, from the Initial Conditions, that the priority is on the 3B EDG and transition to Step 5.o

. Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM F L-16-1 NRC EXAM SECURE INFORMATION

03005032300 , Restore Power to the 3A 4KV Bus , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 10 of 27 Performance Step:

4 Critical: No 3-E OP-ECA-0.0 , Step 5: Try To Restore Power To 3A OR 3B 4KV Bus

o. Check 3B Bus Lockout Relay

- RESET (NO) ) Perform the following:

1) Reset Lockout Relay.

2) IF Lockout relay can NOT be reset, AND EDG Priority was 3A, THEN go to Step 5.y.

3) IF Lockout relay can NOT be reset, THEN return to Step 5.b. Standard: Recognize that the blue light for 4KV BUS 3 B LOCKOUT RELAY is blinking and depress the associated reset pushbutton.

Recognize that the lockout relay for the 3B 4kV Bus will NOT reset , recall that the existing priority is on the 3B EDG, and transition to Step 5.b. Evaluator Note:

Under normal conditions (i.e., when the 3B 4kV Bus is NOT locked out), the blue light will be solid and NOT blinking

. When examinee attempts to reset the lockout relay for the 3B 4kV Bus , it will NOT reset (due to a fault on the 3B 4 kV Bus). Booth Operator Cue:

Ensure LOCKOUT RELAY DOES NOT RESET is triggered.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM F L-16-1 NRC EXAM SECURE INFORMATION

03005032300 , Restore Power to the 3A 4KV Bus , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 11 of 27 Performance Step:

5 Critical: No 3-E OP-ECA-0.0 , Step 5: Try To Restore Power To 3A OR 3B 4KV Bus

b. Check 3A Bus Lockout Relay

- RESET Standard: Recognize that the blue light for 4KV BUS 3A LOCKOUT RELAY is NOT flashing (i.e., the lockout relay for the 3A 4kV Bus is reset

). Evaluator Note:

If the 3AB 4kV Bus was locked out, the blue light would be flashing. Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

6 Critical: No 3-E OP-ECA-0.0 , Step 5: Try To Restore Power To 3A OR 3B 4KV Bus

c. Check 3A EDG Lockout

- RESET (NO) following:

1) Locally reset 3A EDG Start Failure relay by pressing Alarm RESET pushbutton.

2) Reset Lockout Relay.

3) IF Lockout relay can NOT be maintained reset, AND EDG Priority was 3B, THEN go to Step 5.y.

4) IF Lockout relay can NOT be maintained reset, THEN go to Step 5.o.

Standard: Recognize that the blue light for 3A EDG is flashing and go to RNO.

Dispatch operator to locally reset Start Failure and Lockout Relay.

Recognize EDG will NOT reset and 3B was priority and go to Step 5.y.

Booth Operator Cue:

When directed to reset EDG start failure, state that relay will NOT reset.

Performance:

SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM F L-16-1 NRC EXAM SECURE INFORMATION

03005032300 , Restore Power to the 3A 4KV Bus , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 12 of 27 Performance Step:

7 Critical: No 3-E OP-ECA-0.0 , Step 5: Try To Restore Power To 3A OR 3B 4KV Bus y. Check 3A AND 3B 4KV Buses

- AT LEAST ONE ENERGIZED (NO) Observe CAUTION and NOTE prior to Step 6 and go to Step 6.

Standard: Recognize that neither of Unit 3's 4 kV bus es is energized and transition to Step 6. Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

8 Critical: No 3-E OP-ECA-0.0 , prior to Step 6:

CAUTION When power is restored to 3A OR 3B 4KV Bus from a non-FLEX source, then recovery actions should continue by performing Step 26.

NO TE The following constitutes an available 4KV bus: Bus Lockout reset If bus stripping verification has been performed, then all loads are stripped Standard: R ead CAUTION/NOTE and recognize that it is safe to proceed

. Performance:

SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM F L-16-1 NRC EXAM SECURE INFORMATION

03005032300 , Restore Power to the 3A 4KV Bus , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 13 of 27 Performance Step:

9 Critical: No 3-E OP-ECA-0.0 , Step 6: Dispatch Personnel To Restore AC Power

a. Check any of the following:

• Unit 3 Startup Transformer Potential Light

- ON OR

• Opposite unit Startup Transformer Potential Light

- ON OR

• Opposite unit 4KV busses (A and B)

- ANY ENERGIZED OR

• 3C 4KV bus

- ENERGIZED Standard: Verify that the white potential lights for the Unit 3 and Unit 4 Startup Transformers are NOT lit.

Contact the Unit 4 RCO and determine that both of Unit 4's 4kV buses are energized.

Evaluator Note:

If examinee checks the status 3C 4 k V B us, it will be de

-energized.

Booth Operator Cue: When contacted as the Unit 4 RCO, state "The 4A and 4B 4kV Buses are energized from their respective EDGs."

Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM F L-16-1 NRC EXAM SECURE INFORMATION

03005032300 , Restore Power to the 3A 4KV Bus , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 14 of 27 Performance Step:

1 0 Critical: No 3-E OP-ECA-0.0 , Step 6: Dispatch Personnel To Restore AC Power

b. Initiate restoring AC power to available 4KV bus(es) using the following:

• Attachment 6, 3A 4KV Bus Restoration OR

• Attachment 7, 3B 4KV Bus Restoration Standard: Recall that the lockout relay for the 3B 4kV Bus could NOT be reset , recognize that the 3B 4kV Bus is NOT available, and transition to Attachment 6. Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

1 1 Critical: No 3-E OP-ECA-0.0, Attachment 6, Step 1:

Confirm Bus Stripping On 3A 4KV Bus

a. Check if 3A 4KV Bus Stripping was verified in Section 3.0 (NO) (RNO) Verify 3A 4KV Bus Stripping per Attachment 1.

Standard: Recognize that stripping of the 3A 4 kV Bus was NOT previously verified in Section 3 (i.e., Step 5.i) and transition to Attachment 1.

Performance:

SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM F L-16-1 NRC EXAM SECURE INFORMATION

03005032300 , Restore Power to the 3A 4KV Bus , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 15 of 27 Performance Step:

1 2 Critical: No 3-E OP-ECA-0.0, Attachment 1, Step 1:

IF 3A 4KV Bus is de

-energized AND 3D 4KV Bus is aligned to 3A 4KV Bus- Standard: Recognize that the 3D 4kV Bus is NOT aligned to the 3A 4kV Bus (i.e., it is aligned to the 3B 4kV Bus) and this step is NOT applicable.

Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

1 3 Critical: No 3-E OP-ECA-0.0, Attachment 1, Step 2:

IF 3A 4KV Bus is de

-energized AND 3D 4KV Bus is NO T aligned to 3A 4KV Bus OR Station Blackout Tie permissive blue light is OFF , THEN perform the following:

a. IF 3AA16 closed, THEN - b. IF 3AA18 closed, THEN - Standard: Recognize that the 3A 4 kV Bus is de

-energized (and the 3D 4kV Bus is NOT aligned to this bus) and the Station Blackout Tie permissive blue light is NOT lit , but breakers 3AA16 and 3AA18 are open (hence this step is NOT applicable

). Evaluator Note:

Breakers 3AA16 and 3AA18 will have automatically opened, due to the LOOP-induced bus stripping process.

Performance:

SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM F L-16-1 NRC EXAM SECURE INFORMATION

03005032300 , Restore Power to the 3A 4KV Bus , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 16 of 27 Performance Step:

1 4 Critical: No 3-E OP-ECA-0.0, Attachment 1, Step 2:

IF 3A 4KV Bus is de

-energized AND 3D 4KV Bus is NOT aligned to 3A 4KV Bus OR Station Blackout Tie permissive blue light is OFF , THEN perform the following:

c. Verify the following breakers open

3AA22, 3A 4KV BUS EMERGENCY TIE TO UNIT 4 STARTUP TRANSFORMER 3AA09, 3A 4KV BUS TIE TO 3B OR 3C 4KV BUS 3AA05, STARTUP TRANSFORMER 3A 4KV BUS SUPPLY 3AA02, AUXILIARY TRANSFORMER 3A BUS SUPPLY 3AA03, STEAM GENERATOR FEED PUMP 3A 3AA07, HEATER DRAIN PUMP 3A 3AA21, CONDENSATE PUMP 3A 3AA13, SAFETY INJECTION PUMP 3A 3AA15, RESIDUAL HEAT REMOVAL PUMP 3A 3AA12, COMPONENT COOLING WATER PUMP 3A 3AA01, REACTOR COOLANT PUMP 3A 3AA19, INTAKE COOLING WATER PUMP 3A 3AA11, TURBINE PLANT COOLING WATER PUMP 3A 3AA16, CIRCULATING WATER PUMP 3A1 (90 sec delay if MOV > 5% OPEN) 3AA18, CIRCULATING WATER PUMP 3A2 (90 sec delay if MOV > 5% OPEN) 3AA08, 3A LOAD CENTER 3AA14, 3C LOAD CENTER Standard: Recognize that the 3A 4 kV Bus is de

-energized (and the 3D 4kV Bus is NOT aligned to this bus), the Station Blackout Tie permissive blue light is NOT lit, and the listed breakers are open. Evaluator Note:

The listed breakers will have automatically opened, due to the LOOP

-induced bus stripping process.

Breakers 3AA16 and 3AA18 were verified open in the previous step.

Performance:

SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM F L-16-1 NRC EXAM SECURE INFORMATION

03005032300 , Restore Power to the 3A 4KV Bus , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 17 of 27 Performance Step:

1 5 Critical: No 3-E OP-ECA-0.0, Attachment 1, Step 3:

IF 3AD01, SUPPLY FROM 4KV BUS 3A, is open, THEN verify 3AA17, FEEDER TO 4KV BUS 3D, is open.

Standard: Recognize that breakers 3AD01 and 3AA17 are open. Evaluator Note:

The se breakers are open , as the 3D 4kV Bus is currently aligned to the 3B 4kV Bus

. Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

1 6 Critical: No 3-E OP-ECA-0.0, Attachment 1, Step 4:

IF 3AD01, SUPPLY FROM 4KV BUS 3A, is closed , THEN perform the following-Standard: Recognize (as in the previous step) that 3AD01 is open and this step is NOT applicable.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM F L-16-1 NRC EXAM SECURE INFORMATION

03005032300 , Restore Power to the 3A 4KV Bus , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 18 of 27 Performance Step:

1 7 Critical: No 3-E OP-ECA-0.0, Attachment 1, Step 5:

Notify Unit Supervisor that 3A 4KV Bus stripping is complete

. Standard: Make the appropriate notification and return to Attachment 6.

Evaluator Cue:

If addressed as the Unit Supervisor or Shift Manager, acknowledge the communication.

Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

1 8 Critical: No 3-E OP-ECA-0.0 , Attachment 6, Step 2: Verify SI

- RESET Standard: Recognize that a safety injection was NOT actuated and this step is NOT applicable

. Evaluator Note: Some examinees may elect to depress the SAFETY INJECTION RESET pushbuttons to ensure it's reset, despite the absence of an automatic actuation.

This is acceptable.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM F L-16-1 NRC EXAM SECURE INFORMATION

03005032300 , Restore Power to the 3A 4KV Bus , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 19 of 27 Performance Step:

19 Critical: No 3-E OP-ECA-0.0 , Attachment 6, Step 3:

Energize 3A 4KV Bus From Unit 3 Startup Transformer

a. Check Unit 3 Startup Transformer Potential white light is ON (NO) Go to Attachment 6, Step 4.

Standard: Recognize that the white potential light for the Unit 3 Startup Transformer is NOT lit and transition to Step 4.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

Performance Step:

2 0 Critical: No 3-E OP-ECA-0.0 , Attachment 6, Step 4:

Energize 3A 4KV Bus From Opposite Unit Startup Transformer

a. Check opposite unit Startup Transformer Potential white light

- ON (NO) Attachment 6, Step 5 and go to Attachment 6, Step

5. Standard: Recognize that the white potential light for the Unit 4 Startup Transformer is NOT lit and transition to Step 5.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM F L-16-1 NRC EXAM SECURE INFORMATION

03005032300 , Restore Power to the 3A 4KV Bus , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 20 of 27 THIS BEGINS THE TIME

-CRITICAL PORTION OF THE JPM Performance Step:

2 1 Critical: No 3-E OP-ECA-0.0 , Attachment 6, prior to Step 5:

NOTE Power needs to be restored to at least one 4KV bus (3A OR 3B) within 10 minutes to satisfy station blackout requirements.

(Record Current Time: _______

) Standard: Read NOTE, record current time, and recognize that it is safe to proceed.

Evaluator Note:

Record current time: ___________

Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

2 2 Critical: No 3-E OP-ECA-0.0 , Attachment 6, Step 5:

Check At Least One Of The Following

- ENERGIZED

• Opposite Unit A 4KV Bus

• Opposite Unit B 4KV Bus Standard: Contact the Unit 4 RCO and determine that both of Unit 4's 4kV buses are energized.

Booth Operator Cue: When contacted as the Unit 4 RCO, state "The 4A and 4B 4kV Buses are energized from their respective EDGs."

Performance:

SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM F L-16-1 NRC EXAM SECURE INFORMATION

03005032300 , Restore Power to the 3A 4KV Bus , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 21 of 27 Performance Step:

2 3 Critical: Yes 3-E OP-ECA-0.0 , Attachment 6, Step 6: Check 3D 4KV Bus Lockout Relay

- RESET (NO) Reset 3D 4KV Bus Lockout Relay Standard: Recognize that the blue light for 4KV BUS 3D LOCKOUT RELAY is blinking and depress the associated reset pushbutton.

Evaluator Note:

Under normal conditions (i.e., when the 3D 4kV Bus is NOT locked out), the blue light will be solid and NOT blinking

. Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

2 4 Critical: Yes 3-E OP-ECA-0.0 , Attachment 6, Step 7:

Check 3D 4KV Bus

- ALIGNED TO 3A 4KV BUS (NO) Perform the following:

a. Open 3AB19, Feeder To 4KV Bus 3D.

b. Open 3AD06, Supply From 4KV Bus 3B

. c. Close 3AD01, Supply From 4KV Bus 3A. d. Close 3AA17, Feeder To 4KV Bus 3D.

Standard: Recognize, per the Initial Conditions, that the 3D 4kV Bus is aligned to the 3B 4kV Bus

. Recognize breakers 3AB19 and 3AD06 are open. Close breakers 3AD01 and 3AA17. Evaluator Note:

Examinee may match flags for breakers 3AB19 and 3AD06.

Performance:

SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM F L-16-1 NRC EXAM SECURE INFORMATION

03005032300 , Restore Power to the 3A 4KV Bus , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 22 of 27 Performance Step: 2 5 Critical: No 3-E OP-ECA-0.0 , Attachment 6, Step 8:

Check Station Blackout Permissive Blue Light For 3AD07, Station Blackout Breaker - ON Standard: Recognize that the blue PERMISSIVE light for STATION BLACKOUT BREAKER 3AD07 is lit. Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

2 6 Critical: No 3-E OP-ECA-0.0 , Attachment 6, Step 9:

Check 4D 4KV Bus

- ENERGIZED Standard: Contact the Unit 4 RCO and determine that the 4D 4kV Bus is energized.

Booth Operator Cue: When contacted as the Unit 4 RCO, state "The 4D 4kV Bus is energized from the 4B 4kV Bus."

Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM F L-16-1 NRC EXAM SECURE INFORMATION

03005032300 , Restore Power to the 3A 4KV Bus , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 23 of 27 Performance Step:

2 7 Critical: No 3-E OP-ECA-0.0 , Attachment 6, Step 10:

Check 4KV Bus Supplying Power To 4D 4KV Bus - ENERGIZED BY OFFSITE POWER (NO) a. IF only one opposite Unit 4KV Bus (4A OR 4B) is energized

- b. Direct Unit 4 RO to align non-running safeguards equipment switches powered from opposite Unit 4KV bus supplying 4D 4KV Bus as follows:

Unit 4 High Head SI Pumps

- PULL-TO-LOCK Containment Spray Pumps

- PULL-TO-LOCK Emergency Containment Coolers

- STOP RHR Pumps

- PULL-TO-LOCK CCW Pumps

- PULL-TO-LOCK Standard: Contact the Unit 4 RCO and determine that the 4D 4kV Bus is NOT energized by offsite power and both the 4A and 4B 4kV Buses are energized (i.e., Step 10.a is NOT applicable)

. Direct the Unit 4 RCO to place all non

-running Unit 4 HHSI pumps, CSPs, ECCs, RHR pumps, and CCW pumps in pull

-to-lock. Booth Operator Cue: When contacted as the Unit 4 RCO, state "The 4A and 4B 4kV Buses remain energized from their respective EDGs and the 4D 4kV Bus is aligned to the 4B 4kV Bus."

When directed to place all non

-running safeguards equipment in pull

-to-lock, acknowledge the direction and state "all non-running safeguards equipment are in pull

-to-lock or stop." Performance:

SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM F L-16-1 NRC EXAM SECURE INFORMATION

03005032300 , Restore Power to the 3A 4KV Bus , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 24 of 27 Performance Step:

2 8 Critical: Yes 3-E OP-ECA-0.0 , Attachment 6, Step 11:

Energize 3A 4KV Bus From Station Blackout Tie Line

a. Close 3AD07, Station Blackout Breaker, using keylock switch (Key

82) b. Direct opposite Unit RO to close 4AD07, Station Blackout Breaker, using keylock switch (Key 82)

Standard: Obtain Key 82, insert it into the keylock at STATION BLACKOUT BREAKER 3AD07, and turn the switch to CLOSE

. Contact the Unit 4 RCO and direct that breaker 4AD07 be closed

. Evaluator Note:

Only Step 11.a is critical.

When 4AD07 is closed, record current time: ___________ (Refer to Performance Step 22; time differential may NOT exceed 10 minutes)

Booth Operator Cue: When directed to close breaker 4AD07, acknowledge the direction and trigger CLOSE 4AD07. Report when complete.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM F L-16-1 NRC EXAM SECURE INFORMATION

03005032300 , Restore Power to the 3A 4KV Bus , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 25 of 27 Performance Step:

29 Critical: No 3-E OP-ECA-0.0 , Attachment 6, Step 9:

Check 3A 4KV Bus - ENERGIZED Standard: Observe that the A 4KV BUS KILOVOLTS meter is indicating

~4160 volts

. Performance:

SATISFACTORY UNSATISFACTORY Comments: Terminating Cue:

After 3A 4kV bus voltage is checked, state "This completes the JPM."

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

Stop Time:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM F L-16-1 NRC EXAM SECURE INFORMATION

03005032300 , Restore Power to the 3A 4KV Bus , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 26 of 27 Examinee: Evaluator:

RO SRO STA Non-Lic SRO CERT Date: LOIT RO LOIT SRO PERFORMANCE RESULTS:

SAT: UNSAT: Remediation required:

YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).

EXAMINER NOTE:

ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.

EVALUATOR'S SIGNATURE:

NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM F L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION JPM TURNOVER SHEET

INITIAL CONDITIONS:

Unit 3 tripped from full power, due to a loss of offsite power

. The plant is in a normal electrical alignment.

While performing the IOAs of 3

-EOP-E-0, Reactor Trip or Safety Injection, the crew recognized the following:

The 3A EDG did NOT start.

The 3B EDG started but did not energize the 3B 4kv bus.

The crew transitioned to 3-EOP-ECA-0.0, Loss of All AC Power, and have completed through Step 4. INITIATING CUE: The Unit Supervisor directs you to perform Step 5 of 3

-EOP-ECA-0.0, with a priority on the 3B EDG. Some elements of this JPM are time-critical.

NOTE: Ensure the turnover sheet is returned to the evaluator when the JPM is complete

. TR-AA-230-1003-F10, Revision 2 L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC Exam Control Room

- JPM G

L-16-1 NRC EXAM SECURE INFORMATION

JOB PERFORMANCE MEAS URE L-16-1 NRC EXAM SECURE INFORMATION JPM JPM TITLE:

Place N-3-42 Power Range Drawer in Service JPM NUMBER:

01059016200 REV. 1-0 TASK NUMBER(S) / TASK TITLE(S):

01059016200

/ Place N-42 Power Range Drawer in Service K/A NUMBERS:

015 A4.02 K/A VALUE:

RO 3.9 / SRO 3.9 Justification (FOR K/A VALUES <3.0):

N/A TASK APPLICABILITY:

RO SRO STA Non-Lic SRO CERT OTHER: APPLICABLE METHOD OF TESTING:

Simulate/Walkthrough:

Perform: X EVALUATION LOCATION:

In-Plant: Control Room:

Simulator:

X Other: L ab: Time for Completion:

1 0 Minutes Time Critical:

No Alternate Path [NRC]:

No Alternate Path [INPO]:

No Developed by:

Brian Clark 8/4/16 Instructor/Developer Date Reviewed by: Tim Hodge 8/4/16 Instructor (Instructional Review)

Date Validated by:

Sean Bloom 8/5/16 SME (Technical Review)

Date Approved by:

Mark Wilson 8/4/16 Training Supervision Date Approved by:

Sean Bloom 8/5/16 Training Program Owner Date TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM G L-16-1 NRC EXAM SECURE INFORMATION

01059016200, Place N 42 Power Range Drawer in Service, Rev.

1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 3 of 15 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A 1. Are all items on the signature page filled in correctly?

2. Has the JPM been reviewed and validated by SMEs?

3. Can the required conditions for the JPM be appropriately established in the simulator if required?

4. Do the performance steps accurately reflect trainee's actions in accordance with plant procedures?

5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?

6. Has the completion time been established based on validation data or incumbent experience?

7. If the task is time critical, is the time critical portion based upon actual task performance requirements?

8. Is the job level appropriate for the task being evaluated if required?

9. Is the K/A appropriate to the task and to the licensee level if required?

10. Is justification provided for tasks with K/A values less than 3.0?

11. Have the performance steps been identified and classified (Critical / Sequence / Time Critical) appropriately?

12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?

13. Are all references identified, current, accurate, and available to the trainee?

14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?

15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)

16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM? TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge.

All questions/statements must be answered "YES" or "N/A" or the JPM is not valid for use. If all questions/statements are answered "YES" or "N/A," then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.

Protected Conten t: (CAPRs, corrective actions, licensing commitments, etc. associated with this material

) N/A TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM G L-16-1 NRC EXAM SECURE INFORMATION

01059016200, Place N 42 Power Range Drawer in Service, Rev.

1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 4 of 15 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR

-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR

-AA-230-1003-F16. # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE SUPERVISOR DATE 0-0 New JPM N/A N/A N/A N/A N/A N/A 1-0 Formatting; text/grammar changes L-16-1 NRC Exam N/A N/A N/A N/A N/A TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM G L-16-1 NRC EXAM SECURE INFORMATION

01059016200, Place N 42 Power Range Drawer in Service, Rev.

1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 5 of 15 SIMULATOR SET

-UP: SIMULATOR SETUP INSTRUCTIONS

_____ 1. Reset to IC 1 or saved IC. _____ 2. Place simulator in RUN.

_____ 3. Ensure applicable portions of Simulator Operator Checklist are complete.

_____ 4. N/A if using saved IC Perform switch manipulations in accordance with 3-OSP-059.4, steps 7.2.2.1-23. _____ 5. Allow plant to stabilize.

_____ 6. Acknowledge alarms and place simulator in FREEZE.

_____ 7. Save as temporary IC, if JPM will be repeated.

_____ 8. When ready to begin, then place Simulator in RUN.

SIMULATOR MALFUNCTIONS:

N/A SIMULATOR OVERRIDES:

N/A SIMULATOR REMOTE FUNCTIONS:

N/A

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM G L-16-1 NRC EXAM SECURE INFORMATION

01059016200, Place N 42 Power Range Drawer in Service, Rev.

1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 6 of 15 Required Materials:

HANDOUT 3-OSP-059.4 General

References:

3-OSP-059.4, Power Range Nuclear Instrumentation Analog Channel Operational Test Task Standards:

Place the N-3-42 Power Range drawer in service TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM G L-16-1 NRC EXAM SECURE INFORMATION

01059016200, Place N 42 Power Range Drawer in Service, Rev.

1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 7 of 15 HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.

INITIAL CONDITIONS:

Unit 3 is at 100% power.

Unit 4 is in M ode 1. 3-OSP-059.4, Power Range Nuclear Instrumentation Analog Channel Operational Test

, is in progress for N 42 and is complete through Step 7.2.2.2

3. INITIATING CUE:

You have been directed to place the N-3-42 power range drawer in service using 3-OSP-059.4 , beginning at step 7.2.2.24

.

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM G L-16-1 NRC EXAM SECURE INFORMATION

01059016200, Place N 42 Power Range Drawer in Service, Rev.

1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 8 of 15 JPM PERFORMANCE INFORMATION Start Time:

NOTE: When providing "Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically

, cues are only provided when the examinee's actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a "Y es" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step:

1 Critical: No Obtain required reference materials. Standard: Obtain 3-OSP-059.4, Power Range Nuclear Instrumentation Analog Channel Operational Test

. Evaluator Note: If a peer check is requested for any of the following steps, then acknowledge the request and allow the operator to continue.

Evaluator Cue:

Provide examinee with a copy of HANDOUT 3-OSP-059.4. Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM G L-16-1 NRC EXAM SECURE INFORMATION

01059016200, Place N 42 Power Range Drawer in Service, Rev.

1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 9 of 15 Performance Step:

2 Critical: No 3-OSP-059.4 , Step 7.2.2.24: At the N-42, Drawer A, perform the following:

a. Verify the DROPPED ROD ROD STOP Light is OFF Standard: Recognize that the DROPPED ROD ROD STOP light is NOT lit

. Performance:

SATISFACTORY UNSATISFACTORY Comments:

Performance Step:

3 Critical: Yes 3-OSP-059.4 , Step 7.2.2.24:

At the N-42, Drawer A, perform the following:

b. Place the DROPPED ROD MODE switch to NORMAL Standard: Place the DROPPED ROD MODE switch in the NORMAL position.

Evaluator Cue: Annunciator B 7/3, NIS CHANNEL IN TEST, will clear.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM G L-16-1 NRC EXAM SECURE INFORMATION

01059016200, Place N 42 Power Range Drawer in Service, Rev.

1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 10 of 15 Performance Step:

4 Critical: No 3-OSP-059.4 , Step 7.2.2.25:

Verify the N-42 ROD DROP IN BYPASS status light (VPA) is OFF Standard: Recognize that the ROD DROP IN BYPASS status light is NOT lit

. Performance:

SATISFACTORY UNSATISFACTORY Comments:

Performance Step:

5 Critical: No 3-OSP-059.4 , Step 7.2.2.26:

Verify Annunciator B 8/4, NIS TRIP BYPASSED, is OFF. Mark N/A if Annunciator B 8/4 is ON due to another NIS channel in BYPASS Standard: Recognize that annunciator B 8/4 is NOT actuated

. Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM G L-16-1 NRC EXAM SECURE INFORMATION

01059016200, Place N 42 Power Range Drawer in Service, Rev.

1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 11 of 15 Performance Step:

6 Critical: Yes 3-OSP-059.4 , Step 7.2.2.27:

At the COMPARATOR AND RATE Drawer, perform the following:

a. Place the COMPARATOR CHANNEL DEFEAT switch to NORMAL b. Verify COMPARATOR DEFEAT light is OFF Standard: Place the COMPARATOR CHANNEL DEFEAT switch in the NORMAL position and recognize that the COMPARATOR DEFEAT light is NOT lit

. Evaluator Note:

Only the switch manipulation is critical. Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

7 Critical: Yes 3-OSP-059.4 , Step 7.2.2.28:

At the MISCELLANEOUS CONTROL AND INDICATION PANEL (NIS panel), perform the following:

a. Place the ROD STOP BYPASS switch associated with PRN42 to OPERATE Standard: Place the N-42 ROD STOP BYPASS switch in the OPERATE position. Performance:

SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM G L-16-1 NRC EXAM SECURE INFORMATION

01059016200, Place N 42 Power Range Drawer in Service, Rev.

1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 12 of 15 Performance Step:

8 Critical: Yes 3-OSP-059.4 , Step 7.2.2.28:

At the MISCELLANEOUS CONTROL AND INDICATION PANEL (NIS panel), perform the following:

b. Place the POWER MISMATCH BYPASS switch associated with PRN42 to OPERATE Standard: Place the N-42 POWER MISMATCH BYPASS switch in the OPERATE position. Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

9 Critical: Yes 3-OSP-059.4 , Step 7.2.2.29:

At the DETECTOR CURRENT COMPARATOR panel, perform the following:

a. Place the UPPER SECTION defeat switch to NORMAL

1) Verify CHANNEL DEFEAT light is OFF Standard: Place the UPPER SECTION defeat switch in the NORMAL position and recognize that the CHANNEL DEFEAT light is NOT lit

. Evaluator Note:

Only the defeat switch manipulation is critical.

Performance:

SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM G L-16-1 NRC EXAM SECURE INFORMATION

01059016200, Place N 42 Power Range Drawer in Service, Rev.

1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 13 of 15 Performance Step:

10 Critical: Yes 3-OSP-059.4 , Step 7.2.2.29:

At the DETECTOR CURRENT COMPARATOR panel, perform the following:

b. Place the LOWER SECTION defeat switch to NORMAL

1) Verify CHANNEL DEFEAT light is OFF Standard: Place the LOWER SECTION defeat switch in the NORMAL position and recognize that the CHANNEL DEFEAT light is NOT lit

. Evaluator Note: Only the defeat switch manipulation is critical.

Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

11 Critical: Yes 3-OSP-059.4 , Step 7.2.2.30:

At Protection Channel II, Rack No. 11, place the Protection Channel bistable test switches in the NORMAL (Left) position:

a. BS-3-422B-1, Overpower T Trip b. BS-3-422C-1, Overtemperature T Trip Standard: Place the BS-3-422B-1 and BS-3-422C-1 bistable test switches in the NORMAL (left) positions.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

Terminating Cue:

When examinee places the bistable test switches in NORMAL, state "This completes the JPM.

"

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

Stop Time:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM G L-16-1 NRC EXAM SECURE INFORMATION

01059016200, Place N 42 Power Range Drawer in Service, Rev.

1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 14 of 15 Examinee: Evaluator:

RO SRO STA Non-Lic SRO CERT Date: LOIT RO LOIT SRO PERFORMANCE RESULTS:

SAT: UNSAT: Remediation required:

YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).

EXAMINER NOTE:

ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.

EVALUATOR'S SIGNATURE:

NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM G L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION JPM TURNOVER SHEET

INITIAL CONDITIONS:

Unit 3 is at 100% power.

Unit 4 is in Mode 1.

3-OSP-059.4, Power Range Nuclear Instrumentation Analog Channel Operational Test, is in progress for N-3-42 and is complete through Step 7.2.2.2

3. INITIATING CUE

You have been directed to place the N-3-42 power range drawer in service using 3-OSP-059.4 , beginning at step 7.2.2.24

.

NOTE: Ensure the turnover sheet is returned to the evaluator when the JPM is complete

. TR-AA-230-1003-F10, Revision 2 L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC Exam Control Room

- JPM H

L-16-1 NRC EXAM SECURE INFORMATION

JOB PERFORMANCE MEAS URE L-16-1 NRC EXAM SECURE INFORMATION JPM JPM TITLE:

Respond To Control Room Evacuation Condition

- Unit 3 RO JPM NUMBER:

01 200011301 REV. 2-0 TASK NUMBER(S) / TASK TITLE(S):

01 200011300 / Respond To Control Room Evacuation Condition

- Unit 3 RO K/A NUMBERS:

A PE 068 AA1.23 K/A VALUE:

RO 4.3 / SRO 4.4 Justification (FOR K/A VALUES <3.0):

N/A TASK APPLICABILITY:

RO SRO STA Non-Lic SRO CERT OTHER: APPLICABLE METHOD OF TESTING:

Simulate/Walkthrough:

Perform: X EVALUATION LOCATION:

In-Plant: Control Room:

Simulator:

X Other: L ab: Time for Completion:

1 0 Minutes Time Critical:

No Alternate Path [NRC]:

No Alternate Path [INPO]:

No Developed by:

Brian Clark 8/4/16 Instructor/Developer Date Reviewed by: Tim Hodge 8/4/16 Instructor (Instructional Review)

Date Validated by:

Sean Bloom 8/5/16 SME (Technical Review)

Date Approved by:

Mark Wilson 8/4/16 Training Supervision Date Approved by:

Sean Bloom 8/5/16 Training Program Owner Date TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM H L-16-1 NRC EXAM SECURE INFORMATION

01 200011301 , Respond to CR Evacuation

- Unit 3 RO, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 3 of 14 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A 1. Are all items on the signature page filled in correctly?

2. Has the JPM been reviewed and validated by SMEs?

3. Can the required conditions for the JPM be appropriately established in the simulator if required?

4. Do the performance steps accurately reflect trainee's actions in accordance with plant procedures?

5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?

6. Has the completion time been established based on validation data or incumbent experience?

7. If the task is time critical, is the time critical portion based upon actual task performance requirements?

8. Is the job level appropriate for the task being evaluated if required?

9. Is the K/A appropriate to the task and to the licensee level if required?

10. Is justification provided for tasks with K/A values less than 3.0?

11. Have the performance steps been identified and classified (Critical / Sequence / Time Critical) appropriately?

12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?

13. Are all references identified, current, accurate, and available to the trainee?

14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?

15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)

16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM? TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge.

All questions/statements must be answered "YES" or "N/A" or the JPM is not valid for use. If all questions/statements are answered "YES" or "N/A," then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.

Protected Conten t: (CAPRs, corrective actions, licensing commitments, etc. associated with this material

) N/A TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM H L-16-1 NRC EXAM SECURE INFORMATION

01 200011301 , Respond to CR Evacuation

- Unit 3 RO, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 4 of 14 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR

-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR

-AA-230-1003-F16. # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE SUPERVISOR DATE 1-0 New JPM Update for 2014 Annual Exam 01982473 N/A N/A N/A N/A 2-0 Formatting; text/grammar changes L-16-1 NRC Exam N/A N/A N/A N/A N/A TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM H L-16-1 NRC EXAM SECURE INFORMATION

01 200011301 , Respond to CR Evacuation

- Unit 3 RO, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 5 of 14 SIMULATOR SET

-UP: SIMULATOR SETUP INSTRUCTIONS

_____ 1. Reset to IC 1 or equivalent IC.

_____ 2. Place simulator in RUN.

_____ 3. Ensure applicable portions of Simulator Operator Checklist are complete.

_____ 4. Acknowledge alarms and place simulator in FREEZE.

_____ 5. Save as temporary IC, if JPM will be repeated.

_____ 6. When ready to begin, then place Simulator in RUN.

SIMULATOR MALFUNCTIONS:

N/A SIMULATOR OVERRIDES:

N/A SIMULATOR REMOTE FUNCTIONS:

N/A

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM H L-16-1 NRC EXAM SECURE INFORMATION

01 200011301 , Respond to CR Evacuation

- Unit 3 RO, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 6 of 14 Required Materials:

HANDOUT Attachment 14 General

References:

0-ONOP-105, Control Room Evacuation 3-EOP-E-0, Reactor Trip or Safety Injection Task Standards:

Trip Unit 3 reactor Close Unit 3 MSIVs Trip Unit 3 Main Feedwater Pump s Place Unit 3 SDTA controllers in manual and close the valves Close both PORV block valves Trip the Unit 3 RCPs TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM H L-16-1 NRC EXAM SECURE INFORMATION

01 200011301 , Respond to CR Evacuation

- Unit 3 RO, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 7 of 14 HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. Whe n

you complete the task successfully, the objective for this job performance measure will be satisfied.

DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.

INITIAL CONDITIONS:

Both units are at 100% power

. A fire in the North

-South Breezeway has compromised Control Room habitability

. INITIATING CUE:

The Shift Manager/Unit Supervisor directs you to perform the Unit 3 Reactor Operator immediate actions as required by Attachment 14 of 0

-ONOP-105, Control Room Evacuation

.

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM H L-16-1 NRC EXAM SECURE INFORMATION

01 200011301 , Respond to CR Evacuation

- Unit 3 RO, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 8 of 14 JPM PERFORMANCE INFORMATION Start Time:

NOTE: When providing "Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically

, cues are only provided when the examinee's actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a "Y es" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step:

1 Critical: No Obtain required reference materials. Standard: Obtain Attachment 14 of 0-ONOP-105, Control Room Evacuation

. Evaluator Note: Although the following steps are immediate actions and normally performed from memory, the examinee may use the procedure during the performance of this JPM

. If the procedure is NOT used, mark this step N/A. Evaluator C ue: Provide operator with a copy of HANDOUT Attachment 14

. Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM H L-16-1 NRC EXAM SECURE INFORMATION

01 200011301 , Respond to CR Evacuation

- Unit 3 RO, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 9 of 14 Performance Step:

2 Critical: Yes 0-ONOP-105, Attachment 14, Step 1

Perform the following:

A. TRIP Unit 3 Reacto r Standard: Trip the reactor at the operator console or VPB and verify the following:

Rod Bottom Lights - ON Reactor Trip AND Bypass Breakers

- OPEN Rod Position Indicators

- AT ZERO Neutron flux

- DECREASING Evaluator Note: Only the switch manipulation is critical.

Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

3 Critical:

No 0-ONOP-105, Attachment 14, Step 1:

Perform the following:

B. TRIP Unit 3 Main Turbine Standard: Trip the main turbine at the operator console and verify the following:

All Turbine Stop OR associated Control Valves - CLOSED Moisture Separator Reheater Steam Valves

- CLOSED: MSR Main St eam Supply Stop MOVs Reheater Timing Valves MSR Purge St eam Valves Mid and East GCBs

- OPEN (Normally 30-second delay)

Evaluator Note: Only the pushbutton manipulation is critical.

Performance:

SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM H L-16-1 NRC EXAM SECURE INFORMATION

01 200011301 , Respond to CR Evacuation

- Unit 3 RO, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 10 of 14 Performance Step:

4 Critical: Yes 0-ONOP-105, Attachment 14, Step 2: CLOSE Unit 3 MSIVs and Bypass Valves Standard: Close the Unit 3 MSIVs and their bypass valves

. Evaluator Note: Only the MSIV closures are critical

. Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM H L-16-1 NRC EXAM SECURE INFORMATION

01 200011301 , Respond to CR Evacuation

- Unit 3 RO, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 11 of 14 Performance Step:

5 Critical: Yes 0-ONOP-105, Attachment 14, Step 3: PERFORM as many of the following Manual Actions as possible prior to leaving the Control Room:

A. TRIP Unit 3 Main Feedwater Pumps 3A Main Feedwater Pump 3B Main Feedwater Pump B. TRIP A Standby S/G Feedwater Pump C. PLACE Unit 3 Steam Dump to Atmosphere Controllers in MANUAL and CLOSE the Steam Dump Valves CV-3-1606 CV-3-1607 CV-3-1608 D. ENSURE 3B Charging Pump TRIPPED E. CLOSE both PORV Block Valves MOV-3-536 MOV-3-535 F. TRIP Unit 3 Reactor Coolant Pumps 3A RCP 3B RCP 3C RCP G. OBTAIN the following:

Set of prints Radio Standard: Trip the main feedwater pumps, trip the A SSGFP, manually close the SDTAs, verify that the 3B Charging Pump is tripped, close the PORV block valves, trip the RCPs, and obtain a set of prints and a radio.

Evaluator Note: Only the main feedwater pump trips, SDTA closures, PORV block valve closures, and RCP trips are critical.

Evaluator Cue: If asked how many steps must be completed, state "There is no immediate danger; complete all steps

." Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM H L-16-1 NRC EXAM SECURE INFORMATION

01 200011301 , Respond to CR Evacuation

- Unit 3 RO, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 12 of 14 Performance Step:

6 Critical: No 0-ONOP-105, Attachment 14, Step 4: EVACUATE Control Room as follows:

A. PROCEED to Turbine Deck Work Station Standard: Evacuate the Control Room and report to the Turbine Deck Work Station. Performance:

SATISFACTORY UNSATISFACTORY Comments:

Terminating Cue:

When the examinee begins to exit the Control Room, state "This completes the JPM.

"

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

Stop Time:

TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM H L-16-1 NRC EXAM SECURE INFORMATION

01 200011301 , Respond to CR Evacuation

- Unit 3 RO, Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 13 of 14 Examinee: Evaluator:

RO SRO STA Non-Lic SRO CERT Date: LOIT RO LOIT SRO PERFORMANCE RESULTS:

SAT: UNSAT: Remediation required:

YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).

EXAMINER NOTE:

ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.

EVALUATOR'S SIGNATURE:

NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.TR-AA-230-1003-F10, Revision 2 NRC Control Room

- JPM H L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION JPM TURNOVER SHEET

INITIAL CONDITIONS:

Both units are at 100% power

. A fire in the North

-South Breezeway has compromised Control Room habitability

. INITIATING CUE

The Shift Manager/Unit Supervisor directs you to perform the Unit 3 Reactor Operator immediate actions as required by Attachment 14 of 0

-ONOP-105, Control Room Evacuation

.

NOTE: Ensure the turnover sheet is returned to the evaluator when the JPM is complete. TR-AA-230-1003-F10, Revision 2 L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC Exam In-Plant - JPM I

L-16-1 NRC EXAM SECURE INFORMATION

JOB PERFORMANCE MEAS URE L-16-1 NRC EXAM SECURE INFORMATION JPM JPM TITLE:

Locally Trip the Reactor and Turbine JPM NUMBER: 140280095 0 1 REV. 2-1 TASK NUMBER(S) / TASK TITLE(S):

14028009500

/ Respond to an ATWS K/A NUMBERS:

EPE 029 EA1.12 K/A VALUE:

RO 4.1 / SRO 4.0 Justification (FOR K/A VALUES <3.0):

N/A TASK APPLICABILITY:

RO SRO STA Non-Lic SRO CERT OTHER: APPLICABLE METHOD OF TESTING:

Simulate/Walkthrough:

X Perform: EVALUATION LOCATION:

In-Plant: X Control Room:

Simulator:

Other: Lab: Time for Completion:

15 Minutes Time Critical:

No Alternate Path [NRC]:

No Alternate Path [INPO]:

No Developed by:

Brian Clark 8/4/16 Instructor/Developer Date Reviewed by: Tim Hodge 8/4/16 Instructor (Instructional Review)

Date Validated by:

Sean Bloom 8/5/16 SME (Technical Review)

Date Approved by:

Mark Wilson 8/5/16 Training Supervision Date Approved by:

Sean Bloom 8/5/16 Training Program Owner Date TR-AA-230-1003-F10, Revision 2 NRC In-Plant - JPM I L-16-1 NRC EXAM SECURE INFORMATION

1402800950 1 , Locally Trip the Reactor and Turbine, Rev. 2-1 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 3 of 14 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A 1. Are all items on the signature page filled in correctly?

2. Has the JPM been reviewed and validated by SMEs?

3. Can the required conditions for the JPM be appropriately established in the simulator if required?

4. Do the performance steps accurately reflect trainee's actions in accordance with plant procedures?

5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?

6. Has the completion time been established based on validation data or incumbent experience?

7. If the task is time critical, is the time critical portion based upon actual task performance requirements?

8. Is the job level appropriate for the task being evaluated if required?

9. Is the K/A appropriate to the task and to the licensee level if required?

10. Is justification provided for tasks with K/A values less than 3.0?

11. Have the performance steps been identified and classified (Critical / Sequence / Time Critical) appropriately?

12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?

13. Are all references identified, current, accurate, and available to the trainee?

14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?

15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)

16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM? TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge.

All questions/statements must be answered "YES" or "N/A" or the JPM is not valid for use. If all questions/statements are answered "YES" or "N/A," then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.

Protected Conten t: (CAPRs, corrective actions, licensing commitments, etc. associated with this material

) N/A TR-AA-230-1003-F10, Revision 2 NRC In-Plant - JPM I L-16-1 NRC EXAM SECURE INFORMATION

1402800950 1 , Locally Trip the Reactor and Turbine, Rev. 2-1 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 4 of 14UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR-AA-230-1003)made to the material after initial approval. Or use separate Update Log form TR

-AA-230-1003-F16. # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE SUPERVISOR DATE 1-0 Updated to fleet template; text/grammar changes 2015 LOCT Annual Exam N/A N/A N/A N/A N/A 2-0 Added turbine trip; formatting; text/grammar changes L-16-1 NRC Exam N/A N/A N/A N/A N/A 2-1 Editorial L-16-1 Prep Week N/A Clark 8/5/16 Wilson 8//16 TR-AA-230-1003-F10, Revisi on 2NRC In-Plant - JPM I L-16-1 NRC EXAM SECURE INFORMATION

1402800950 1 , Locally Trip the Reactor and Turbine, Rev. 2-1 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 5 of 14 SIMULATOR SET

-UP: N/A Required Materials:

3(4)-EOP-FR-S.1, Response to Nuclear Power Generation/ATWS General

References:

3(4)-EOP-FR-S.1, Response to Nuclear Power Generation/ATWS Task Standards:

Locally open t he reactor trip breakers in the 3(4)B MCC Room Locally trip the main turbine at the front standard TR-AA-230-1003-F10, Revision 2 NRC In-Plant - JPM I L-16-1 NRC EXAM SECURE INFORMATION

1402800950 1 , Locally Trip the Reactor and Turbine, Rev. 2-1 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 6 of 14 HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.

INITIAL CONDITIONS:

The Unit 3(4) reactor and main turbine could NOT be tripped from the Control Room

. The crew has entered 3(4)-EOP-FR-S.1, Response to Nuclear Power Generation/ATWS

. INITIATING CUE:

You are the Admin RO and have been directed to perform RNO Step s 6.a and 6.b of 3(4)-EOP-FR-S.1.

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

TR-AA-230-1003-F10, Revision 2 NRC In-Plant - JPM I L-16-1 NRC EXAM SECURE INFORMATION

1402800950 1 , Locally Trip the Reactor and Turbine, Rev. 2-1 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 7 of 14 JPM PERFORMANCE INFORMATION Start Time:

NOTE: When providing "Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically

, cues are only provided when the examinee's actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a "Y es" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Evaluator Note:

Prior to administering, determine which unit the JPM will be performed on and provide the appropriate procedure and initiating cue.

Performance Step:

1 Critical: No Obtain required reference materials and proceed to the 3(4)B MCC Room. Standard: Obtain a copy of 3(4)-EOP-FR-S.1, Response to Nuclear Power Generation/ATWS, and proceed to the 3(4)B MCC Room

. Evaluator Note: If a peer check is requested for any of the following steps, then acknowledge the request and allow the operator to continue.

Evaluator Cue:

Provide examinee with a copy of 3(4)-EOP-FR-S.1. Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC In-Plant - JPM I L-16-1 NRC EXAM SECURE INFORMATION

1402800950 1 , Locally Trip the Reactor and Turbine, Rev. 2-1 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 8 of 14 Performance Step:

2 Critical: No 3(4)-E OP-FR-S.1 , prior to Step 6: CAUTION If an SI signal exists or occurs AND the reactor is subcritical, proper safeguards equipment alignment is required to be verified using Attachment 3 of 3(4)-EOP-E-0, REACTOR TRIP OR SAFETY INJECTION, while continuing with this procedure.

Standard: Read CAUTION and recognize that it is safe to proceed

. Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

3 Critical: Yes 3(4)-E OP-FR-S.1 , Step 6: Check If The Following Trips Have Occurred:

a. Reactor Trip (NO) (RNO) In 3(4)B MCC Room, locally trip reactor as follows:

Open 3(4)A and 3(4)B Reactor Trip Breakers.

Standard: Locally open the reactor trip breakers by pressing the TRIP button on the front of each breaker.

Evaluator Cue:

If asked initially, inform examinee that a red CLOSED flag is showing at each breaker When the breaker trips are properly simulated, state that the associated green OPEN flag s are showing Evaluator Note:

Breakers may be tripped in any order Breakers will NOT recharge after opening

only a trip sound will be heard Performance

SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 NRC In-Plant - JPM I L-16-1 NRC EXAM SECURE INFORMATION

1402800950 1 , Locally Trip the Reactor and Turbine, Rev. 2-1 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 9 of 14 Performance Step:

4 Critical: No 3 (4)-E OP-FR-S.1 , Step 6: Check If The Following Trips Have Occurred:

a. Reactor Trip (NO) In 3(4)B MCC Room, locally trip reactor as follows:

Open 3(4)A and 3(4)B Reactor Trip Bypass Breakers. Standard: Recognize that both bypass breakers are racked out and the green OPEN flags are showing

. Evaluator Cue:

When checked, state that the breaker face plates are protruding from their cubicle cover plates If asked, inform examinee that a green flag is showing on each breaker Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC In-Plant - JPM I L-16-1 NRC EXAM SECURE INFORMATION

1402800950 1 , Locally Trip the Reactor and Turbine, Rev. 2-1 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 10 of 14 Performance Step:

5 Critical:

No 3(4)-E OP-FR-S.1 , Step 6: Check If The Following Trips Have Occurred:

a. Reactor Trip (NO) In 3(4)B MCC Room, locally trip reactor as follows:

Open A/B MG Set Generator Output Breakers. Standard: Open both motor

-generator set output breakers by placing their control switches in the TRIP position.

Evaluator Cue: If asked initially, inform examinee that the associated red lights are lit and the green lights are NOT lit at each breaker When the breaker trips are properly simulated, state that the associated green lights are lit and the red lights are extinguished Evaluator Note: Breakers may be tripped in any order The output breakers are located in the MCC R oom; the breaker tripping will be heard Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC In-Plant - JPM I L-16-1 NRC EXAM SECURE INFORMATION

1402800950 1 , Locally Trip the Reactor and Turbine, Rev. 2-1 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 11 of 14 Performance Step:

6 Critical:

No 3(4)-E OP-FR-S.1 , Step 6: Check If The Following Trips Have Occurred:

a. Reactor Trip (NO) In 3(4)B MCC Room, locally trip reactor as follows:

Open A/B MG Set Generator Input Breakers. Standard: Open both motor

-generator set input breakers by placing their control switches in the TRIP position.

Evaluator Cue: If asked initially, inform examinee that the associated red lights are lit and the green lights are NOT lit at each breaker When the breaker trips are properly simulated, state that the associated green lights are lit and the red lights are extinguished Evaluator Note: Breakers may be tripped in any order The input breakers are located in the LC Room and will NOT be heard when tripped Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC In-Plant - JPM I L-16-1 NRC EXAM SECURE INFORMATION

1402800950 1 , Locally Trip the Reactor and Turbine, Rev. 2-1 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 12 of 14 Performance Step:

7 Critical: Yes 3(4)-E OP-FR-S.1 , Step 6: Check If The Following Trips Have Occurred:

b. Turbine Trip (NO) Standard. Standard: Rotate the RESET/TRIP lever, to the TRIP position.

Evaluator Cue: When the examinee identifies the trip lever box

, provide Photo A and have the examinee simulate tripping the turbine When properly simulated, and if asked, use the following cues as applicable:

Turbine stop and control valves are closing Reheat stop and intercept valves are closing Turbine shaft is slowing down Turbine rpm indicator is lowering Bearing oil pressures are lowering Evaluator Note: Switch label, HS

-3(4)-001, is on outside of box at the front standard (NOT on inside of box or in the procedure

) Note any other cues given in the comments section Performance:

SATISFACTORY UNSATISFACTORY Comments: Terminating Cue:

When the examinee locally trips the turbine, state "This completes the JPM."

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

Stop Time:

TR-AA-230-1003-F10, Revision 2 NRC In-Plant - JPM I L-16-1 NRC EXAM SECURE INFORMATION

1402800950 1 , Locally Trip the Reactor and Turbine, Rev. 2-1 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 13 of 14 Examinee: Evaluator:

RO SRO STA Non-Lic SRO CERT Date: LOIT RO LOIT SRO PERFORMANCE RESULTS:

SAT: UNSAT: Remediation required:

YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).

EXAMINER NOTE:

ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.

EVALUATOR'S SIGNATURE:

NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.TR-AA-230-1003-F10, Revision 2 NRC In-Plant - JPM I L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION JPM TURNOVER SHEET

INITIAL CONDITIONS:

The Unit 3(4) reactor and main turbine could NOT be tripped from the Control Room.

The crew has entered 3(4)-EOP-FR-S.1, Response to Nuclear Power Generation/ATWS

. INITIATING CUE:

You are the Admin RO and have been directed to perform RNO Step s 6.a and 6.b of 3(4)-EOP-FR-S.1.

NOTE: Ensure the turnover sheet is returned to the evaluator when the JPM is complete

. TR-AA-230-1003-F10, Revision 2 L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC Exam In-Plant - JPM J

L-16-1 NRC EXAM SECURE INFORMATION

JOB PERFORMANCE MEAS URE L-16-1 NRC EXAM SECURE INFORMATION JPM JPM TITLE:

Control Steam Generator Level Locally with AFW Control Valve JPM NUMBER:

040750 0 230 0 REV. 2-0 TASK NUMBER(S) / TASK TITLE(S):

040750 0 230 0 / Control Steam Generator Level Locally with Auxiliary Feedwater Control Valve K/A NUMBERS:

APE 054 AA1.01 K/A VALUE:

RO 4.5 / SRO 4.4 Justification (FOR K/A VALUES <3.0):

N/A TASK APPLICABILITY:

RO SRO STA Non-Lic SRO CERT OTHER: APPLICABLE METHOD OF TESTING:

Simulate/Walkthrough:

X Perform: EVALUATION LOCATION:

In-Plant: X Control Room:

Simulator:

Other: Lab: Time for Completion:

20 Minutes Time Critical:

No Alternate Path [NRC]:

No Alternate Path [INPO]:

No Developed by:

Brian Clark 8/4/16 Instructor/Developer Date Reviewed by: Tim Hodge 8/4/16 Instructor (Instructional Review)

Date Validated by:

Sean Bloom 8/5/16 SME (Technical Review)

Date Approved by:

Mark Wilson 8/4/16 Training Supervision Date Approved by:

Sean Bloom 8/5/16 Training Program Owner Date TR-AA-230-1003-F10, Revision 2 NRC In-Plant - JPM J L-16-1 NRC EXAM SECURE INFORMATION

0 4075002300 , Control S/G Level Locally with AFW Control Valve , Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 3 of 13 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A 1. Are all items on the signature page filled in correctly?

2. Has the JPM been reviewed and validated by SMEs?

3. Can the required conditions for the JPM be appropriately established in the simulator if required?

4. Do the performance steps accurately reflect trainee's actions in accordance with plant procedures?

5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?

6. Has the completion time been established based on validation data or incumbent experience?

7. If the task is time critical, is the time critical portion based upon actual task performance requirements?

8. Is the job level appropriate for the task being evaluated if required?

9. Is the K/A appropriate to the task and to the licensee level if required?

10. Is justification provided for tasks with K/A values less than 3.0?

11. Have the performance steps been identified and classified (Critical / Sequence / Time Critical) appropriately?

12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?

13. Are all references identified, current, accurate, and available to the trainee?

14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?

15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)

16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM? TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge.

All questions/statements must be answered "YES" or "N/A" or the JPM is not valid for use. If all questions/statements are answered "YES" or "N/A," then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.

Protected Conten t: (CAPRs, corrective actions, licensing commitments, etc. associated with this material

) N/A TR-AA-230-1003-F10, Revision 2 NRC In-Plant - JPM J L-16-1 NRC EXAM SECURE INFORMATION

0 4075002300 , Control S/G Level Locally with AFW Control Valve , Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 4 of 13 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR

-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR

-AA-230-1003-F16. # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE SUPERVISOR DATE 1-0 Updated to fleet template; text/grammar changes Updated for 2014 LOCT Annual Exam 1933041-8 N/A N/A N/A N/A 2-0 Formatting; text/grammar changes L-16-1 NRC Exam N/A N/A N/A N/A N/A TR-AA-230-1003-F10, Revision 2 NRC In-Plant - JPM J L-16-1 NRC EXAM SECURE INFORMATION

0 4075002300 , Control S/G Level Locally with AFW Control Valve , Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 5 of 13 SIMULATOR SET

-UP: N/A Required Materials:

HANDOUT 3-ONOP-075, Auxiliary Feedwater System Malfunction, Attachment 3 General

References:

3-ONOP-075, Auxiliary Feedwater System Malfunction Task Standards:

Manipulate appropriate instrument air and drain valves to support local operation of flow control valve

. Locally open CV 2818, Train 1 S/G C Feedwater Flow Control Valve TR-AA-230-1003-F10, Revision 2 NRC In-Plant - JPM J L-16-1 NRC EXAM SECURE INFORMATION

0 4075002300 , Control S/G Level Locally with AFW Control Valve , Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 6 of 13 HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.

INITIAL CONDITIONS:

Unit 3 is in M ode 3, following a reactor trip with an AFW auto

-start. All systems responded as designed.

The plant is in a normal electrical alignment

. The AFW System is intact.

CV-3-2833 , Train 2 AFW Flow Control Valve to 3C S/G

, is OOS for maintenance.

Control Room operators are unable to establish feedwater flow to the 3C S/G

, due to CV-3-2818 NOT responding to the controller

. All other components operate as designed.

INITIATING CUE:

T he Field Supervisor provides the required key and directs you to restore feedwater flow to the 3C S/G , by manually controlling CV 2818 in accordance with Attachment 3 of 3

-ONOP-075.

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

TR-AA-230-1003-F10, Revision 2 NRC In-Plant - JPM J L-16-1 NRC EXAM SECURE INFORMATION

0 4075002300 , Control S/G Level Locally with AFW Control Valve , Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 7 of 13 JPM PERFORMANCE INFORMATION Start Time:

NOTE: When providing "Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically

, cues are only provided when the examinee's actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a "Y es" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step:

1 Critical: No Obtain required reference materials. Standard: Obtain Attachment 3 of 3-ONOP-075, Auxiliary Feedwater System Malfunction

. Evaluator Note: If a peer check is requested for any of the following steps, then acknowledge the request and allow the operator to continue.

Evaluator Cue:

Provide examinee with a copy of HANDOUT 3-ONOP-075 , Attachment 3

. Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC In-Plant - JPM J L-16-1 NRC EXAM SECURE INFORMATION

0 4075002300 , Control S/G Level Locally with AFW Control Valve , Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 8 of 13 Performance Step: 2 Critical: Yes 3-ON OP-075 , Attachment 3, Step 1

PERFORM the following for the applicable feed flow control valve:

TO MANUALLY OPERATE CV-3-2818 (Train 1 AFW Flow Control Valve to 3C S/G), CLOSE VALVES 3-40-268 (Air/N 2 Station #1 Train 1 to AFW C V-3-2818 Root) and 3 269 (Air/N 2 Station #1 Train 2 to AFW CV 2818 Root)

Standard: Cut seal wire and close valve 3 268 Verify that 3 269 is closed Evaluator Note:

3-40-268 is normally sealed open and 3

-4 0-269 is normally sealed closed Closing 3-40-268 is the only critical activity in this step Evaluator Cue:

When examinee properly identifies 3 268 and simulates cutting the seal wire and closing the valve, tell examinee that the valve handle turned clockwise 1/4 turn and is perpendicular to the piping When examinee properly identifies 3 269 and simulates checking the valve closed, tell examinee that the valve handle is perpendicular to the piping Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC In-Plant - JPM J L-16-1 NRC EXAM SECURE INFORMATION

0 4075002300 , Control S/G Level Locally with AFW Control Valve , Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 9 of 13 Performance Step:

3 Critical: Yes 3-ON OP-075 , Attachment 3, Step 2:

OPEN drain valves below the two pressure regulators associated with each control valve AND BLEED off the air/nitrogen pressure Standard: Open both regulator drain valves on CV 281 8. Evaluator Note: The Evaluator Cue may be given for each regulator drain valve or after examinee simulates opening both drain valves

. Evaluator Cue: When examinee properly identifies/simulates opening the regulator drain valves, tell examinee that flow noise is initially heard from the drain valves and flow eventually stops.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC In-Plant - JPM J L-16-1 NRC EXAM SECURE INFORMATION

0 4075002300 , Control S/G Level Locally with AFW Control Valve , Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 10 of 13 Performance Step:

4 Critical: Yes 3-ON OP-075 , Attachment 3, Step 3:

UNLOCK control valve handwheel AND OPEN the valve until flow is detected on either of the following:

Upper platform: FI 1458A1 Standard: Unlock the handwheel for CV 2818, open the valve, and verify flow to the 3C S/G

. Evaluator Cue: When examinee properly identifies/simulates unlocking and opening CV-3-2818, indicate that the position indicator is in the throttled position and flow noise is heard When examinee properly identifies/simulates checking FI 1458A1, indicate that flow is approximately 150 gpm (or whatever flow rate examinee targeted)

If examinee identifies FI 1458A1 and simulates adjusting CV 2818 while watching flow indicator, indicate that flow is approximately 150 gpm (or whatever flow rate examinee targeted)

Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC In-Plant - JPM J L-16-1 NRC EXAM SECURE INFORMATION

0 4075002300 , Control S/G Level Locally with AFW Control Valve , Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 11 of 13 Performance Step:

5 Critical: No 3-ON OP-075 , Attachment 3, Step 4:

ADJUST AFW flow to maintain S/G levels at approximately 60% wide range, as indicated on any of the following

LI-3-497B, S/G C Wide Range Level Indicator Standard: Observe the 3C S/G level locally on LI 497B. Evaluator Cue:

When examinee properly identifies LI-3-497B, indicat e that the 3C S/G's wide range level is 60%

. Performance:

SATISFACTORY UNSATISFACTORY Comments: Terminating Cue:

When examinee attains 60% wide range level in the 3C S/G, state "This completes the JPM.

"

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

Stop Time:

TR-AA-230-1003-F10, Revision 2 NRC In-Plant - JPM J L-16-1 NRC EXAM SECURE INFORMATION

0 4075002300 , Control S/G Level Locally with AFW Control Valve , Rev. 2-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 12 of 13 Examinee: Evaluator:

RO SRO STA Non-Lic SRO CERT Date: LOIT RO LOIT SRO PERFORMANCE RESULTS:

SAT: UNSAT: Remediation required:

YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).

EXAMINER NOTE:

ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.

EVALUATOR'S SIGNATURE:

NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily.

If unsatisfactory performance is demonstrated, the entire JPM should be retained.TR-AA-230-1003-F10, Revision 2 NRC In-Plant - JPM J L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION JPM TURNOVER SHEET

INITIAL CONDITIONS:

Unit 3 is in Mode 3, following a reactor trip with an AFW auto

-start. All systems responded as designed.

The plant is in a normal electrical alignment.

The AFW System is intact.

CV-3-2833 , Train 2 AFW Flow Control Valve to 3C S/G

, is OOS for maintenance.

Control Room operators are unable to establish feedwater flow to the 3C S/G, due to CV-3-2818 NOT responding to the controll er. All other components operate as designed.

INITIATING CUE:

T he Field Supervisor provides the required key and directs you to restore feedwater flow to the 3C S/G, by manually controlling CV 2818 in accordance with Attachment 3 of 3

-ONOP-075.

NOTE: Ensure the turnover sheet is returned to the evaluator when the JPM is complete

. TR-AA-230-1003-F10, Revision 2 L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC Exam In-Plant - JPM K

L-16-1 NRC EXAM SECURE INFORMATION

JOB PERFORMANCE MEAS URE L-16-1 NRC EXAM SECURE INFORMATION JPM Page 2 of 16 JPM TITLE:

Align Emergency Service Water to the Charging Pumps JPM NUMBER:

24030009300 REV. 2-1 TASK NUMBER(S) / TASK TITLE(S):

24030009300

/ Align Emergency Service Water to the Charging Pumps K/A NUMBERS:

APE 026 AA1.03 K/A VALUE:

RO 3.6 / SRO 3.6 Justification (FOR K/A VALUES <3.0):

N/A TASK APPLICABILITY:

RO SRO STA Non-Lic SRO CERT OTHER: APPLICABLE METHOD OF TESTING:

Simulate/Walkthrough:

X Perform: EVALUATION LOCATION:

In-Plant: X Control Room:

Simulator:

Other: Lab: Time for Completion:

15 Minutes Time Critical:

No Alternate Path [NRC]:

No Alternate Path [INPO]:

No Developed by:

Brian Clark 8/4/16 Instructor/Developer Date Reviewed by: Tim Hodge 8/4/16 Instructor (Instructional Review)

Date Validated by:

Sean Bloom 8/5/16 SME (Technical Review)

Date Approved by:

Mark Wilson 8/4/16 Training Supervision Date Approved by:

Sean Bloom 8/5/16 Training Program Owner Date TR-AA-230-1003-F10, Revision 2 NRC In

-Plant - JPM K L-16-1 NRC EXAM SECURE INFORMATION

24030009300 , Align Emergency Service Water to the Charging Pumps, Rev. 2-1 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 3 of 16 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A 1. Are all items on the signature page filled in correctly?

2. Has the JPM been reviewed and validated by SMEs?

3. Can the required conditions for the JPM be appropriately established in the simulator if required?

4. Do the performance steps accurately reflect trainee's actions in accordance with plant procedures?

5. Is the standard for each performance item specific as to what controls, indications and ranges are required to evaluate if the trainee properly performed the step?

6. Has the completion time been established based on validation data or incumbent experience?

7. If the task is time critical, is the time critical portion based upon actual task performance requirements?

8. Is the job level appropriate for the task being evaluated if required?

9. Is the K/A appropriate to the task and to the licensee level if required?

10. Is justification provided for tasks with K/A values less than 3.0?

11. Have the performance steps been identified and classified (Critical / Sequence / Time Critical) appropriately?

12. Have all special tools and equipment needed to perform the task been identified and made available to the trainee?

13. Are all references identified, current, accurate, and available to the trainee?

14. Have all required cues (as anticipated) been identified for the evaluator to assist task completion?

15. Are all critical steps supported by procedural guidance? (e.g., if licensing, EP or other groups were needed to determine correct actions, then the answer should be NO.)

16. If the JPM is to be administered to an LOIT student, has the required knowledge been taught to the individual prior to administering the JPM? TPE does not have to be completed, but the JPM evaluation may not be valid if they have not been taught the required knowledge.

All questions/statements must be answered "YES" or "N/A" or the JPM is not valid for use. If all questions/statements are answered "YES" or "N/A," then the JPM is considered valid and can be performed as written. The individual(s) performing the initial validation shall sign and date the cover sheet.

Protected Conten t: (CAPRs, corrective actions, licensing commitments, etc. associated with this material

) N/A TR-AA-230-1003-F10, Revision 2 NRC In

-Plant - JPM K L-16-1 NRC EXAM SECURE INFORMATION

24030009300 , Align Emergency Service Water to the Charging Pumps, Rev. 2-1 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 4 of 16 UPDATE LOG: Indicate in the following table any minor changes or major revisions (as defined in TR

-AA-230-1003) made to the material after initial approval. Or use separate Update Log form TR

-AA-230-1003-F16. # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE SUPERVISOR DATE 1-0 Updated to fleet template; text/grammar changes 2015 LOCT Annual Exam N/A N/A N/A N/A N/A 2-0 Formatting; text/grammar changes L-16-1 NRC Exam N/A N/A N/A N/A N/A 2-1 Editorial L-16-1 Prep Week N/A Clark 8/5/16 Wilson 8/5/16 TR-AA-230-1003-F10, Revision 2 NRC In

-Plant - JPM K L-16-1 NRC EXAM SECURE INFORMATION

24030009300 , Align Emergency Service Water to the Charging Pumps, Rev. 2-1 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 5 of 16 SIMULATOR SET

-UP: N/A Required Materials:

HANDOUT 3(4)-ONOP-030, Component Cooling Water Malfunction

, Attachment 1 General

References:

3(4)-ONOP-030, Component Cooling Water Malfunction Task Standards:

Establis h emergency cooling water to the Unit 3(4) charging pump s TR-AA-230-1003-F10, Revision 2 NRC In

-Plant - JPM K L-16-1 NRC EXAM SECURE INFORMATION

24030009300 , Align Emergency Service Water to the Charging Pumps, Rev. 2-1 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 6 of 16 HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

DURING THE JPM, ENSURE PROPER SAFETY PRECAUTIONS, FME, AND/OR RADIOLOGICAL CONCERNS AS APPLICABLE ARE FOLLOWED.

INITIAL CONDITIONS:

Level in the CCW Surge Tank can NOT be maintai ned. The crew has entered 3(4)-ONOP-030, Component Cooling Water Malfunction

. INITIATING CUE:

You have been directed to perform Attachment 1 , Control of Emergency Cooling Water to Charging Pumps, of 3(4)-ONOP-030 for the B Charging Pump

.

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

TR-AA-230-1003-F10, Revision 2 NRC In

-Plant - JPM K L-16-1 NRC EXAM SECURE INFORMATION

24030009300 , Align Emergency Service Water to the Charging Pumps, Rev. 2-1 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 7 of 16 JPM PERFORMANCE INFORMATION Start Time:

NOTE: When providing "Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically

, cues are only provided when the examinee's actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a "Y es" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Evaluator Note:

Prior to administering, determine which unit the JPM will be performed on and provide the appropriate procedure and initiating cue.

Evaluator Note:

Cam lock fittings are types of quick disconnects. When the procedure refers to a cam lock fitting on one end of the hose and quick disconnect on the other, it is considering the female end to be the "cam lock" and male end to be the "quick disconnect".

Performance Step: 1 Critical: No Obtain required reference materials, proceed to Unit 3(4) Charging Pump Room, and retrieve emergency cooling hoses from the storage box. Standard: Obtain Attachment 1, Control of Emergency Cooling Water to Charging Pumps, of 3(4

)-ONOP-030, Component Cooling Water Malfunction Simulate removing the emergency cooling hoses from the storage box Evaluator Note: If a peer check is requested for any of the following steps, then acknowledge the request and allow the operator to conti nue. Evaluator Cue:

Provide examinee with a copy of HANDOUT 3(4)-ONOP-030 , Attachment 1

. Performance:

SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 NRC In

-Plant - JPM K L-16-1 NRC EXAM SECURE INFORMATION

24030009300 , Align Emergency Service Water to the Charging Pumps, Rev. 2-1 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 8 of 16 Performance Step:

2 Critical: Yes 3(4)-ON OP-0 30 , Attachment 1, Step 1: CONNECT cam lock fitting end of emergency cooling water supply hose to 3-70-179A (4-70-118B), Service Water Connection Inside (Outside) Unit 3(4) Charging Pump Room

. Standard: Identify the correct valve and connect the supply hose to the cam lock fitting. Evaluator Note:

3-70-179A is located inside of the Unit 3 Charging Pump Room; 4 118B is located outside of the Unit 4 Charging Pump Room The emergency cooling water supply hose has a quick disconnect fitting on one end and a cam lock fitting on the other en d Evaluator Cue:

When the examinee properly simulates installing the supply hose on the valve, inform the examinee that the hose is connected.

Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

3 Critical: No 3(4)-ON OP-030 , Attachment 1, Step 2: CONSULT with Unit 3(4) Reactor Operator to determine desired charging pump

. Standard: Recognize from the Initial Conditions that the Unit 3(4) B Charging Pump is to be cooled.

Evaluator Note:

If asked, refer the examinee to the Initiating Cue.

Performance:

SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 NRC In

-Plant - JPM K L-16-1 NRC EXAM SECURE INFORMATION

24030009300 , Align Emergency Service Water to the Charging Pumps, Rev. 2-1 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 9 of 16 Performance Step:

4 Critical: No 3(4)-ON OP-030 , Attachment 1, Step 3: ENSURE desired Charging Pump is STOPPED OR running at maximum speed. Standard: Check the appropriate pump's status.

Evaluator Cue:

When the correct pump is identified/checked, inform the examinee that the shaft is NOT rotating and no pump or motor noise is heard.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

Performance Step:

5 Critical: Yes 3(4)-ON OP-030 , Attachment 1, Step 4: CONNECT quick disconnect fitting end of emergency cooling water supply hose to emergency hose connection on desired Charging Pump:

3(4)-10-2 89, Emergency Hose Connectio n to Charging Pump B Oil Cooler Supply Standard: Identify the correct pump and connect the quick disconnect fitting on the supply hose to the pump's quick disconnect supply fitting. Evaluator Note:

The emergency cooling water supply hose has a quic k disconnect fitting on one end and a cam lock fitting on the other end.

Evaluator Cue:

When the examinee identifies the correct fitting and properly simulates installing the supply hose on the pump, inform the examinee that the hose is connected.

Performance:

SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 NRC In

-Plant - JPM K L-16-1 NRC EXAM SECURE INFORMATION

24030009300 , Align Emergency Service Water to the Charging Pumps, Rev. 2-1 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 10 of 16 Performance Step:

6 Critical: Yes 3(4)-ON OP-030 , Attachment 1, Step 5: CONNECT quick disconnect fitting end of emergency cooling water outlet hose to emergency hose connection on desired Charging Pump

3(4)-10-288, Emergency Hose Connection to Charging Pump B Oil Cooler Return Standard: Identify the correct pump and connect the quick disconnect fitting on the outlet hose to the pump's quick disconnect return fitting. Evaluator Note: The emergency cooling water outlet hose has a quick disconnect fitting on one end and no fitting on the other end.

Evaluator Cue:

When the examinee identifies the correct fitting, simulates removing the pipe plug, and properly simulates installing the outlet hose on the pump , inform the examinee that the hose is connected.

Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

7 Critical: No 3(4)-ON OP-030 , Attachment 1, Step 6:

REMOVE cover from floor drain to be used in Charging Pump Room.

Standard: Identify the appropriate floor drain and remove its cover.

Evaluator Cue: When the examinee identifies the appropriate floor drain and simulates removing its cover, inform the examinee that the cover is remov ed. Performance:

SATISFACTORY UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 NRC In

-Plant - JPM K L-16-1 NRC EXAM SECURE INFORMATION

24030009300 , Align Emergency Service Water to the Charging Pumps, Rev. 2-1 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 11 of 16 Performance Step:

8 Critical: No 3(4)-ON OP-030 , Attachment 1, Step 7:

ROUTE open end of emergency cooling water outlet hose to floor drain being used in Charging Pump Room

. Standard: Place the open end of the outlet hose near the appropriate floor drain

. Evaluator Cue:

When the examinee places the open end of the outlet hose near the appropriate floor drain , inform the examinee that the outlet hose is properly route d. Performance:

SATISFACTORY UNSATISFACTORY Comments:

Performance Step:

9 Critical: Yes 3(4)-ON OP-030 , Attachment 1, Step 8:

ISOLATE CCW to hydraulic oil cooler on desired Charging Pump:

CLOSE 3(4)-825 C, CCW to B Charging Pump Oil Cooler Inlet Standard: Identify/close the CCW valve to the appropriate charging pump.

Evaluator Cue: When the examinee identifies the correct valve and properly simulates closing it , inform the examinee that the valve is closed.

Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC In

-Plant - JPM K L-16-1 NRC EXAM SECURE INFORMATION

24030009300 , Align Emergency Service Water to the Charging Pumps, Rev. 2-1 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 12 of 16 Performance Step:

10 Critical: Yes 3(4)-ON OP-030 , Attachment 1, Step 9:

ISOLATE CCW from hydraulic oil cooler on desired Charging Pump:

CLOSE 3(4)-825 D, CCW from B Charging Pump Oil Cooler Inlet Standard: Identify/close the CCW valve from the appropriate charging pump.

Evaluator Cue: When the examinee identifies the correct valve and properly simulates closing it , inform the examinee that the valve is closed.

Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

11 Critical: Yes 3(4)-ON OP-030 , Attachment 1, Step 10 (10.a): OPEN 3-70-179, Service Water Root Valve Outside Unit 3 Charging Pump Room (4-70-118B , Service Water Connection Outside Unit 4 Charging Pump Room)

. Standard: Identify/open the appropriate service water valve.

Evaluator Cue:

When the examinee identifies the correct valve and properly simulates opening it , inform the examinee that the valve is open. Performance:

SATISFACTOR Y UNSATISFACTORY Comments: TR-AA-230-1003-F10, Revision 2 NRC In

-Plant - JPM K L-16-1 NRC EXAM SECURE INFORMATION

24030009300 , Align Emergency Service Water to the Charging Pumps, Rev. 2-1 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 13 of 16 Performance Step:

12 Critical: Yes 3(4)-ON OP-030 , Attachment 1, Step 11 (10.b):

OPEN 3-70-179 A, Service Water Connection Inside Unit 3 Charging Pump Room (4-70-118 , Service Water Root Valve Outside Unit 4 Charging Pump Room)

. Standard: Identify/open the appropriate service water valve.

Evaluator Cue:

When the examinee identifies the correct valve and properly simulates opening it , inform the examinee that the valve is open. Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

13 Critical: Yes 3(4)-ON OP-030 , Attachment 1, Step 12 (11):

ESTABLISH Service Water to desired Charging Pump:

OPEN 3(4)-10-2 89, Emergency Hose Connection to Charging Pump B Oil Cooler Suppl y Standard: Identify/open the appropriate service water valve.

Evaluator Cue:

When the examinee identifies the correct valve and properly simulates opening it , inform the examinee that the valve is open. Performance:

SATISFACTORY UNSATISFACTORY Comments:

TR-AA-230-1003-F10, Revision 2 NRC In

-Plant - JPM K L-16-1 NRC EXAM SECURE INFORMATION

24030009300 , Align Emergency Service Water to the Charging Pumps, Rev. 2-1 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 14 of 16 Performance Step:

14 Critical: Yes 3(4)-ON OP-030 , Attachment 1, Step 13 (12):

ADJUST Service Water flow from desired charging pump to provide maximum flow:

OPEN 3(4)-10-2 88, Emergency Hose Connection to Charging Pump B Oil Cooler Return Standard: Identify/open the appropriate service water valve.

Evaluator Cue:

When the examinee identifies the correct valve and properly simulates opening it , inform the examinee that the valve is open. Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step:

15 Critical: No 3(4)-ON OP-030 , Attachment 1, Step 14 (13):

IF Service Water flow is NOT obtained, THEN PLACE Service Water System in service per 0-NOP-012, Service Water System, using any available pump including the diesel driven SWP D.

Standard: Verify that service water flow is obtained.

Evaluator Cue:

When the examinee checks the open end of the discharge hose at the floor drain , inform the examinee that service water flow is observed.

Performance:

SATISFACTORY UNSATISFACTORY Comments: Terminating Cue:

When service water flow has been verified, state "This completes the JPM."

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

Stop Time:

TR-AA-230-1003-F10, Revision 2 NRC In

-Plant - JPM K L-16-1 NRC EXAM SECURE INFORMATION

24030009300 , Align Emergency Service Water to the Charging Pumps, Rev. 2-1 L-16-1 NRC EXAM SECURE INFORMATION JPM Page 15 of 16 Examinee: Evaluator:

RO SRO STA Non-Lic SRO CERT Date: LOIT RO LOIT SRO PERFORMANCE RESULTS:

SAT: UNSAT: Remediation required:

YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).

EXAMINER NOTE:

ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.

EVALUATOR'S SIGNATURE:

NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.TR-AA-230-1003-F10, Revision 2 NRC In

-Plant - JPM K L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION JPM TURNOVER SHEET

INITIAL CONDITIONS:

Level in the CCW Surge Tank can NOT be maintained

. The crew has entered 3(4)-ONOP-030, Component Cooling Water Malfunction

. INITIATING CUE

You have been directed by the Unit 3(4) RCO to perform Attachment 1, Control of Emergency Cooling Water to Charging Pumps, of 3(4)-ONOP-030 for the B Charging Pump

.

NOTE: Ensure the turnover sheet is returned to the evaluator when the JPM is complete

. TR-AA-230-1003-F10, Revision 2 L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC Exam Admin - JPM RO A1a

L-16-1 NRC EXAM SECURE INFORMATION JOB PERFORMANCE MEAS URE L-16-1 NRC EXAM SECURE INFORMATION JPM JPM TITLE: JPM NUMBER: R EV. TASK NUMBER(S) / TASK TITLE(S): K/A NUMBERS:

K/A VALUE: Justification (FOR K/A VALUES <3.0):

TASK APPLICABILITY:

RO SRO STA Non-Lic SRO CERT OTHER: APPLICABLE METHOD OF TESTING:EVALUATION LOCATION: Developed by:

Alan Schilk 8/4/16 Reviewed by: Luis Sagion8/4/16 Validated by:

Sean Bloom 8/5/16 Approved by:

Mark Wilson 8/4/16 Approved by:

Sean Bloom8/5/16 L-16-1 NRC EXAM SECURE INFORMATION

0 1046046101 , Calculat e a Manual Makeup to the VCT, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A Protected Conten t: L-16-1 NRC EXAM SECURE INFORMATION

0 1046046101 , Calculat e a Manual Makeup to the VCT, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM UPDATE LOG: # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE SUPERVISOR DATE L-16-1 NRC EXAM SECURE INFORMATION

0 1046046101 , Calculat e a Manual Makeup to the VCT, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM SIMULATOR SET

-UP:

Required Materials: General

References:

Task Standards:

L-16-1 NRC EXAM SECURE INFORMATION

0 1046046101 , Calculat e a Manual Makeup to the VCT, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME

INITIAL CONDITIONS:

INITIATING CUES:

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

L-16-1 NRC EXAM SECURE INFORMATION

0 1046046101 , Calculat e a Manual Makeup to the VCT, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM JPM PERFORMANCE INFORMATION Start Time:

NOTE: When providing "Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically, cues are only provided when the examinee's actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a "Y es" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step: 1 Critical: No Obtain required reference materials.

Standard: Evaluator Cue:

Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step: 2 Critical: No 0-OP-046, Step 5.4.1.1:

Standard: Performance:

SATISFACTORY UNSATISFACTORY Comments: L-16-1 NRC EXAM SECURE INFORMATION

0 1046046101 , Calculat e a Manual Makeup to the VCT, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Performance Step: 3 Critical: No 0-OP-046, prior to Step 5.4.2.1:

CAUTION Instrument uncertainties for the Boric Acid and Primary Water flow transmitters can result in the actual amount of Boric Acid or Primary Water added to be either more or less than the amount calculated. Thus, care is needed to ensure that excessive reduction in RCS boron concentration does NOT occur due to the uncertainties.

NOTE VCT level is 14.15 gallons per percent level indication.

Standard: Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step: 4 Critical: No 0-OP-046, Step 5.4.2.1:

Standard: Evaluator Cue:

Performance:

SATISFACTORY UNSATISFACTORY Comments: L-16-1 NRC EXAM SECURE INFORMATION

0 1046046101 , Calculat e a Manual Makeup to the VCT, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Performance Step: 5 Critical: Yes Determine the appropriate primary water flow needed to obtain the desired blend, using the blended flow calculation in Section III of the Plant Curve Book. Standard: Evaluator Note:

oo Performance:

SATISFACTORY UNSATISFACTORY Comments:

L-16-1 NRC EXAM SECURE INFORMATION

0 1046046101 , Calculat e a Manual Makeup to the VCT, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Performance Step: 6 Critical: Yes Determine the appropriate boric acid and primary water volumes and to raise VCT level from 20% to 37%. Standard: Evaluator Note:

ooo Performance:

SATISFACTORY UNSATISFACTORY Comments:

L-16-1 NRC EXAM SECURE INFORMATION

0 1046046101 , Calculat e a Manual Makeup to the VCT, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Performance Step: 7 Critical: Yes Based on the available information, determine the potentiometer settings for the following controllers:

Boric Acid Flow Controller (FC-3-113A) Primary Water Flow Controller (FC-3-114A) Standard: Evaluator Note:

Performance: SATISFACTORY UNSATISFACTORY Comments: Terminating Cue:

When the examinee completes Step 7, state "This completes the JPM."

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

Stop Time:

L-16-1 NRC EXAM SECURE INFORMATION

0 1046046101 , Calculat e a Manual Makeup to the VCT, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Examinee: Evaluator:

RO SRO STA Non-Lic SRO CERT Date: LOIT RO LOIT SRO PERFORMANCE RESULTS:

SAT: UNSAT: Remediation required:

YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).

EXAMINER NOTE:

ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.

EVALUATOR'S SIGNATURE:

NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION JPM TURNOVER SHEET

INITIAL CONDITIONS:

INITIATING CUES:

NOTE: Ensure the turnover sheet is returned to the evaluator when the JPM is complete. L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC Exam Admin - JPM RO A1b

L-16-1 NRC EXAM SECURE INFORMATION JOB PERFORMANCE MEAS URE L-16-1 NRC EXAM SECURE INFORMATION JPM JPM TITLE: JPM NUMBER:

REV. TASK NUMBER(S) / TASK TITLE(S): K/A NUMBERS:

K/A VALUE: Justification (FOR K/A VALUES <3.0):

TASK APPLICABILITY:

RO SRO STA Non-Lic SRO CERT OTHER: APPLICABLE METHOD OF TESTING:EVALUATION LOCATION: Developed by:

Alan Schilk 8/4/16 Reviewed by: Luis Sagion8/4/16 Validated by:

Sean Bloom8/5/16 Approved by:

Mark Wilson8/4/16 Approved by:

Sean Bloom8/5/16 L-16-1 NRC EXAM SECURE INFORMATION

0 1041046101 , Determine Heatup of the RCS, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A Protected Conten t: L-16-1 NRC EXAM SECURE INFORMATION

0 1041046101 , Determine Heatup of the RCS, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM UPDATE LOG: # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE SUPERVISOR DATE L-16-1 NRC EXAM SECURE INFORMATION

0 1041046101 , Determine Heatup of the RCS, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM SIMULATOR SET

-UP:

Required Materials: General

References:

Task Standards:

L-16-1 NRC EXAM SECURE INFORMATION

0 1041046101 , Determine Heatup of the RCS, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME

INITIAL CONDITIONS:

INITIATING CUES:

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

L-16-1 NRC EXAM SECURE INFORMATION

0 1041046101 , Determine Heatup of the RCS, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM JPM PERFORMANCE INFORMATION Start Time:

NOTE: When providing "Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically, cues are only provided when the examinee's actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a "Y es" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step: 1 Critical: No Obtain required reference materials.

Standard: Evaluator Cue:

Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step: 2 Critical: No Review heatup data (Attachment 2) and identify discrepancy.

Standard: Performance:

SATISFACTORY UNSATISFACTORY Comments: L-16-1 NRC EXAM SECURE INFORMATION

0 1041046101 , Determine Heatup of the RCS, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Performance Step: 3 Critical: Yes Complete remaining procedural steps and record any discrepancies and required subsequent actions in Section 5.2. Standard:

Evaluator Cue:

Evaluator Note:

Performance:

SATISFACTORY UNSATISFACTORY Comments: L-16-1 NRC EXAM SECURE INFORMATION

0 1041046101 , Determine Heatup of the RCS, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Terminating Cue:

When the examinee completes Step 3, state "This completes the JPM."

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

Stop Time:

L-16-1 NRC EXAM SECURE INFORMATION

0 1041046101 , Determine Heatup of the RCS, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Examinee: Evaluator:

RO SRO STA Non-Lic SRO CERT Date: LOIT RO LOIT SRO PERFORMANCE RESULTS:

SAT: UNSAT: Remediation required:

YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).

EXAMINER NOTE:

ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.

EVALUATOR'S SIGNATURE:

NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION JPM TURNOVER SHEET

INITIAL CONDITIONS:

INITIATING CUES:

NOTE: Ensure the turnover sheet is returned to the evaluator when the JPM is complete. L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC Exam Admin - JPM RO A 2

L-16-1 NRC EXAM SECURE INFORMATION JOB PERFORMANCE MEAS URE L-16-1 NRC EXAM SECURE INFORMATION JPM JPM TITLE: JPM NUMBER: REV. TASK NUMBER(S) / TASK TITLE(S): K/A NUMBERS:

K/A VALUE: Justification (FOR K/A VALUES <3.0):

TASK APPLICABILITY:

RO SRO STA Non-Lic SRO CERT OTHER: APPLICABLE METHOD OF TESTING:EVALUATION LOCATION: Developed by:

Alan Schilk 8/4/16 Reviewed by: Luis Sagion 8/4/16 Validated by:

Sean Bloom 8/5/16 Approved by:

Mark Wilson 8/4/16 Approved by:

Sean Bloom 8/5/16 L-16-1 NRC EXAM SECURE INFORMATION

01201013104 , Review an ECO for the 3A Heater Drain Pump , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A

Protected Conten t: L-16-1 NRC EXAM SECURE INFORMATION

01201013104 , Review an ECO for the 3A Heater Drain Pump , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM UPDATE LOG: # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE SUPERVISOR DATE L-16-1 NRC EXAM SECURE INFORMATION

01201013104 , Review an ECO for the 3A Heater Drain Pump , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM SIMULATOR SET

-UP:

Required Materials: General

References:

Task Standards:

L-16-1 NRC EXAM SECURE INFORMATION

01201013104 , Review an ECO for the 3A Heater Drain Pump , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TI ME

INITIAL CONDITIONS:

INITIATING CUES:

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

L-16-1 NRC EXAM SECURE INFORMATION

01201013104 , Review an ECO for the 3A Heater Drain Pump , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

L-16-1 NRC EXAM SECURE INFORMATION

01201013104 , Review an ECO for the 3A Heater Drain Pump , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM JPM PERFORMANCE INFORMATION Start Time:

NOTE: When providing "Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically, cues are only provided when the examinee's actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a "Y es" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step: 1 Critical: No Obtain required reference materials.

Standard: Evaluator Cue:

Performance:

SATISFACTORY UNSATISFACTORY Comments:

L-16-1 NRC EXAM SECURE INFORMATION

01201013104 , Review an ECO for the 3A Heater Drain Pump , Rev. 0-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Performance Step: 2 Critical: Yes Review ECO package for completeness/correctness and identify any concerns. Standard: Evaluator Note: Evaluator Cue: Performance:

SATISFACTORY UNSATISFACTORY Comments:

Terminating Cue:

When the examin ee completes the ECO revision

, state "This completes the JPM."

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

Stop Time:

L-16-1 NRC EXAM SECURE INFORMATION

01201013104 , Review an ECO for the 3A Heater Drain Pump , Rev. 0-0 DRAFT L-16-1 NRC EXAM SECURE INFORMATION JPM Examinee: Evaluator:

RO SRO STA Non-Lic SRO CERT Date: LOIT RO LOIT SRO PERFORMANCE RESULTS:

SAT: UNSAT: Remediation required:

YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).

EXAMINER NOTE:

ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.

EVALUATOR'S SIGNATURE:

NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION JPM TURNOVER SHEET INITIAL CONDITIONS:

INITIATING CUES:

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION JPM NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC Exam Admin - JPM RO A 3

L-16-1 NRC EXAM SECURE INFORMATION JOB PERFORMANCE MEAS URE L-16-1 NRC EXAM SECURE INFORMATION JPM JPM TITLE: JPM NUMBER:

REV. TASK NUMBER(S) / TASK TITLE(S): K/A NUMBERS:

K/A VALUE: Justification (FOR K/A VALUES <3.0):

TASK APPLICABILITY:

RO SRO STA Non-Lic SRO CERT OTHER: APPLICABLE METHOD OF TESTING:EVALUATION LOCATION: Developed by:

Alan Schilk 8/4/16 Reviewed by: Luis Sagion8/4/16 Validated by:

Sean Bloom8/5/16 Approved by:

Mark Wilson8/4/16 Approved by:

Sean Bloom8/5/16 L-16-1 NRC EXAM SECURE INFORMATION

01038034100 , Evaluate Conditions for Restart of Refueling Pre-shuffle in the Spent Fuel Pit, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A Protected Conten t: L-16-1 NRC EXAM SECURE INFORMATION

01038034100 , Evaluate Conditions for Restart of Refueling Pre-shuffle in the Spent Fuel Pit, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM UPDATE LOG: # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE SUPERVISOR DATE L-16-1 NRC EXAM SECURE INFORMATION

01038034100 , Evaluate Conditions for Restart of Refueling Pre-shuffle in the Spent Fuel Pit, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM SIMULATOR SET

-UP:

Required Materials: General

References:

Task Standards:

L-16-1 NRC EXAM SECURE INFORMATION

01038034100 , Evaluate Conditions for Restart of Refueling Pre-shuffle in the Spent Fuel Pit, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME

INITIAL CONDITIONS:

INITIATING CUE:

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

L-16-1 NRC EXAM SECURE INFORMATION

01038034100 , Evaluate Conditions for Restart of Refueling Pre-shuffle in the Spent Fuel Pit, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM JPM PERFORMANCE INFORMATION Start Time:

NOTE: When providing "Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically, cues are only provided when the examinee's actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a "Y es" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step: 1 Critical: No Obtain required reference materials.

Standard: Evaluator Cue:

Performance: SATISFACTORY UNSATISFACTORY Comments:

L-16-1 NRC EXAM SECURE INFORMATION

01038034100 , Evaluate Conditions for Restart of Refueling Pre-shuffle in the Spent Fuel Pit, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Performance Step: 2 Critical: No 3-NOP-040.03, Step 4.2.1.20:

PERFORM Standard: Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step: 3 Critical: No 3-NOP-040.03, Attachment 2:

Standard: Performance:

SATISFACTORY UNSATISFACTORY Comments:

L-16-1 NRC EXAM SECURE INFORMATION

01038034100 , Evaluate Conditions for Restart of Refueling Pre-shuffle in the Spent Fuel Pit, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Performance Step: 4 Critical: Yes 3-NOP-040.03, Attachment 2:

Standard: Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step: 5 Critical: No 3-NOP-040.03, Attachment 2:

Standard: Performance:

SATISFACTORY UNSATISFACTORY Comments:

L-16-1 NRC EXAM SECURE INFORMATION

01038034100 , Evaluate Conditions for Restart of Refueling Pre-shuffle in the Spent Fuel Pit, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Performance Step: 6 Critical: No 3-NOP-040.03, Attachment 2:

Standard: Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step: 7 Critical: Yes 3-NOP-040.03, Attachment 2:

NOT INSTALL Standard: Performance:

SATISFACTORY UNSATISFACTORY Comments:

L-16-1 NRC EXAM SECURE INFORMATION

01038034100 , Evaluate Conditions for Restart of Refueling Pre-shuffle in the Spent Fuel Pit, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Performance Step: 8 Critical: No 3-NOP-040.03, Attachment 2:

Standard: Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step: 9 Critical: No 3-NOP-040.03, Attachment 2:

Standard: Performance:

SATISFACTORY UNSATISFACTORY Comments:

L-16-1 NRC EXAM SECURE INFORMATION

01038034100 , Evaluate Conditions for Restart of Refueling Pre-shuffle in the Spent Fuel Pit, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Performance Step: 10 Critical: No 3-NOP-040.03, Attachment 2:

Standard: Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step: 11 Critical: No 3-NOP-040.03, Attachment 2:

Standard: Performance:

SATISFACTORY UNSATISFACTORY Comments:

L-16-1 NRC EXAM SECURE INFORMATION

01038034100 , Evaluate Conditions for Restart of Refueling Pre-shuffle in the Spent Fuel Pit, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Performance Step: 13 Critical: Yes 3-NOP-040.03, Attachment 2:

Standard: Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step: 14 Critical: Yes 3-NOP-040.03, Attachment 2:

Standard: Evaluator Cue:

Performance:

SATISFACTORY UNSATISFACTORY Comments: Terminating Cue:

When the examinee completes the attachment

, state "This completes the JPM."

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

Stop Time:

L-16-1 NRC EXAM SECURE INFORMATION

01038034100 , Evaluate Conditions for Restart of Refueling Pre-shuffle in the Spent Fuel Pit, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Examinee: Evaluator:

RO SRO STA Non-Lic SRO CERT Date: LOIT RO LOIT SRO PERFORMANCE RESULTS:

SAT: UNSAT: Remediation required:

YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory). EXAMINER NOTE: ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.

EVALUATOR'S SIGNATURE:

NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION JPM TURNOVER SHEET

INITIAL CONDITIONS:

INITIATING CUE:

NOTE: Ensure the turnover sheet is returned to the evaluator when the JPM is comple te. L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC Exam Admin - JPM SRO A1a

L-16-1 NRC EXAM SECURE INFORMATION JOB PERFORMANCE MEAS URE L-16-1 NRC EXAM SECURE INFORMATION JPM JPM TITLE: JPM NUMBER: REV. TASK NUMBER(S) / TASK TITLE(S): K/A NUMBERS:

K/A VALUE: Justification (FOR K/A VALUES <3.0):

TASK APPLICABILITY:

RO SRO STA Non-Lic SRO CERT OTHER: APPLICABLE METHOD OF TESTING:EVALUATION LOCATION: Developed by:

Alan Schilk 8/5/16 Reviewed by: Luis Sagion8/5/16 Validated by:

Sean Bloom8/5/16 Approved by:

Mark Wilson8/5/16 Approved by:

Sean Bloom8/5/16 L-16-1 NRC EXAM SECURE INFORMATION

0 1046046101 , Calculat e a Manual Makeup to the VCT, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A Protected Conten t: L-16-1 NRC EXAM SECURE INFORMATION

0 1046046101 , Calculat e a Manual Makeup to the VCT, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM UPDATE LOG: # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE SUPERVISOR DATE L-16-1 NRC EXAM SECURE INFORMATION

0 1046046101 , Calculat e a Manual Makeup to the VCT, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM SIMULATOR SET

-UP:

Required Materials: General

References:

Task Standards:

L-16-1 NRC EXAM SECURE INFORMATION

0 1046046101 , Calculat e a Manual Makeup to the VCT, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME

INITIAL CONDITIONS:

INITIATING CUES:

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

L-16-1 NRC EXAM SECURE INFORMATION

0 1046046101 , Calculat e a Manual Makeup to the VCT, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM JPM PERFORMANCE INFORMATION Start Time:

NOTE: When providing "Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically, cues are only provided when the examinee's actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a "Y es" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step: 1 Critical: No Obtain required reference materials.

Standard: Evaluator Cue:

Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step: 2 Critical: No 0-OP-046, Step 5.4.1.1:

Standard: Performance:

SATISFACTORY UNSATISFACTORY Comments: L-16-1 NRC EXAM SECURE INFORMATION

0 1046046101 , Calculat e a Manual Makeup to the VCT, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Performance Step: 3 Critical: No 0-OP-046, prior to Step 5.4.2.1:

CAUTION Instrument uncertainties for the Boric Acid and Primary Water flow transmitters can result in the actual amount of Boric Acid or Primary Water added to be either more or less than the amount calculated. Thus, care is needed to ensure that excessive reduction in RCS boron concentration does NOT occur due to the uncertainties.

NOTE VCT level is 14.15 gallons per percent level indication.

Standard: Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step: 4 Critical: No 0-OP-046, Step 5.4.2.1:

Standard: Evaluator Cue:

Performance:

SATISFACTORY UNSATISFACTORY Comments: L-16-1 NRC EXAM SECURE INFORMATION

0 1046046101 , Calculat e a Manual Makeup to the VCT, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Performance Step: 5 Critical: Yes Determine the appropriate primary water flow needed to obtain the desired blend, using the blended flow calculation in Section III of the Plant Curve Book. Standard: Evaluator Note:

oo Performance:

SATISFACTORY UNSATISFACTORY Comments:

L-16-1 NRC EXAM SECURE INFORMATION

0 1046046101 , Calculat e a Manual Makeup to the VCT, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Performance Step: 6 Critical: Yes Determine the appropriate boric acid and primary water volumes and to raise VCT level from 20% to 37%. Standard: Evaluator Note:

ooo Performance:

SATISFACTORY UNSATISFACTORY Comments:

L-16-1 NRC EXAM SECURE INFORMATION

0 1046046101 , Calculat e a Manual Makeup to the VCT, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Performance Step: 7 Critical: Yes Based on the available information, determine the potentiometer settings for the following controllers:

Boric Acid Flow Controller (FC-3-113A) Primary Water Flow Controller (FC-3-114A) Standard: Evaluator Note:

Performance: SATISFACTORY UNSATISFACTORY Comments: Terminating Cue:

When the examinee completes Step 7, state "This completes the JPM."

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

Stop Time:

L-16-1 NRC EXAM SECURE INFORMATION

0 1046046101 , Calculat e a Manual Makeup to the VCT, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Examinee: Evaluator:

RO SRO STA Non-Lic SRO CERT Date: LOIT RO LOIT SRO PERFORMANCE RESULTS:

SAT: UNSAT: Remediation required:

YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).

EXAMINER NOTE:

ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.

EVALUATOR'S SIGNATURE:

NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION JPM TURNOVER SHEET

INITIAL CONDITIONS:

INITIATING CUES:

NOTE: Ensure the turnover sheet is returned to the evaluator when the JPM is complete. L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC Exam Admin - JPM SRO A1b

L-16-1 NRC EXAM SECURE INFORMATION JOB PERFORMANCE MEAS URE L-16-1 NRC EXAM SECURE INFORMATION JPM JPM TITLE: JPM NUMBER:

REV. TASK NUMBER(S) / TASK TITLE(S): K/A NUMBERS:

K/A VALUE: Justification (FOR K/A VALUES <3.0):

TASK APPLICABILITY:

RO SRO STA Non-Lic SRO CERT OTHER: APPLICABLE METHOD OF TESTING:EVALUATION LOCATION: Developed by:

Alan Schilk 8/4/16 Reviewed by: Luis Sagion8/4/16 Validated by:

Sean Bloom8/5/16 Approved by:

Mark Wilson8/4/16 Approved by:

Sean Bloom8/5/16 L-16-1 NRC EXAM SECURE INFORMATION

0 1041046101 , Determine Heatup of the RCS, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A Protected Conten t: L-16-1 NRC EXAM SECURE INFORMATION

0 1041046101 , Determine Heatup of the RCS, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM UPDATE LOG: # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE SUPERVISOR DATE L-16-1 NRC EXAM SECURE INFORMATION

0 1041046101 , Determine Heatup of the RCS, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM SIMULATOR SET

-UP:

Required Materials: General

References:

Task Standards: L-16-1 NRC EXAM SECURE INFORMATION

0 1041046101 , Determine Heatup of the RCS, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME

INITIAL CONDITIONS:

INITIATING CUES:

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

L-16-1 NRC EXAM SECURE INFORMATION

0 1041046101 , Determine Heatup of the RCS, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM JPM PERFORMANCE INFORMATION Start Time:

NOTE: When providing "Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically, cues are only provided when the examinee's actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a "Y es" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step: 1 Critical: No Obtain required reference materials.

Standard: Evaluator Cue:

Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step: 2 Critical: No Review heatup data (Attachment 2) and identify discrepancy.

Standard: Performance:

SATISFACTORY UNSATISFACTORY Comments: L-16-1 NRC EXAM SECURE INFORMATION

0 1041046101 , Determine Heatup of the RCS, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Performance Step: 3 Critical: Yes Complete remaining procedural steps and record any discrepancies and required subsequent actions in Section 5.2. Standard:

Evaluator Cue:

Evaluator Note:

Performance:

SATISFACTORY UNSATISFACTORY Comments: L-16-1 NRC EXAM SECURE INFORMATION

0 1041046101 , Determine Heatup of the RCS, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Terminating Cue:

When the examinee completes Step 3, state "This completes the JPM."

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

Stop Time:

L-16-1 NRC EXAM SECURE INFORMATION

0 1041046101 , Determine Heatup of the RCS, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Examinee: Evaluator:

RO SRO STA Non-Lic SRO CERT Date: LOIT RO LOIT SRO PERFORMANCE RESULTS:

SAT: UNSAT: Remediation required:

YES N O COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).

EXAMINER NOTE:

ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.

EVALUATOR'S SIGNATURE:

NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION JPM TURNOVER SHEET

INITIAL CONDITIONS:

INITIATING CUES:

NOTE: Ensure the turnover sheet is returned to the evaluator when the JPM is complete. L-16-1 NR C EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC Exam Admin - JPM SRO A 2

L-16-1 NRC EXAM SECURE INFORMATION JOB PERFORMANCE MEAS URE L-16-1 NRC EXAM SECURE INFORMATION JPM JPM TITLE: JPM NUMBER:

REV. TASK NUMBER(S) / TASK TITLE(S): K/A NUMBERS:

K/A VALUE: Justification (FOR K/A VALUES <3.0):

TASK APPLICABILITY:

RO SRO STA Non-Lic SRO CERT OTHER: APPLICABLE METHOD OF TESTING:EVALUATION LOCATION: Developed by:

Alan Schilk 8/4/16 Reviewed by: Luis Sagion8/4/16 Validated by:

Sean Bloom8/5/16 Approved by:

Mark Wilson8/4/16 Approved by:

Sean Bloom8/5/16 L-16-1 NRC EXAM SECURE INFORMATION

02051013101 , Evaluate TS Conditions While Performing a Valve Operability Test, Rev. 1-2 L-16-1 NRC EXAM SECURE INFORMATION JPM JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A Protected Conten t: L-16-1 NRC EXAM SECURE INFORMATION

02051013101 , Evaluate TS Conditions While Performing a Valve Operability Test, Rev. 1-2 L-16-1 NRC EXAM SECURE INFORMATION JPM UPDATE LOG: # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE SUPERVISOR DATE L-16-1 NRC EXAM SECURE INFORMATION

02051013101 , Evaluate TS Conditions While Performing a Valve Operability Test, Rev. 1-2 L-16-1 NRC EXAM SECURE INFORMATION JPM SIMULATOR SET

-UP:

Required Materials: General

References:

Task Standards:

L-16-1 NRC EXAM SECURE INFORMATION

02051013101 , Evaluate TS Conditions While Performing a Valve Operability Test, Rev. 1-2 L-16-1 NRC EXAM SECURE INFORMATION JPM HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME

INITIAL CONDITIONS:

INITIATING CUE:

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

L-16-1 NRC EXAM SECURE INFORMATION

02051013101 , Evaluate TS Conditions While Performing a Valve Operability Test, Rev. 1-2 L-16-1 NRC EXAM SECURE INFORMATION JPM JPM PERFORMANCE INFORMATION Start Time:

NOTE: When providing "Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically, cues are only provided when the examinee's actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a "Y es" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step: 1 Critical: No Obtain required reference materials.

Standard: Evaluator Cue:

Performance:

SATISFACTORY UNSATISFACTORY Comments:

L-16-1 NRC EXAM SECURE INFORMATION

02051013101 , Evaluate TS Conditions While Performing a Valve Operability Test, Rev. 1-2 L-16-1 NRC EXAM SECURE INFORMATION JPM Performance Step: 2 Critical: No Review Technical Specification 3.3.2, Engineered Safety Features Actuation System Instrumentation , and identify any required actions. Standard: Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step: 3 Critical: Yes Review Technical Specification 3.3.3.3, Accident Monitoring

Instrumentation , and identify any required actions. Standard: o

Evaluator Note: Performance:

SATISFACTORY UNSATISFACTORY Comments: L-16-1 NRC EXAM SECURE INFORMATION

02051013101 , Evaluate TS Conditions While Performing a Valve Operability Test, Rev. 1-2 L-16-1 NRC EXAM SECURE INFORMATION JPM Performance Step: 4 Critical: Yes Review Technical Specification 3.6.4, Containment Isolation Valves , and identify any required actions. Standard: o

Evaluator Cue:

Evaluator Note:

Performance:

SATISFACTORY UNSATISFACTORY Comments: Terminating Cue:

When the examinee completes Step 4, state "This completes the JPM."

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

Stop Time:

L-16-1 NRC EXAM SECURE INFORMATION

02051013101 , Evaluate TS Conditions While Performing a Valve Operability Test, Rev. 1-2 L-16-1 NRC EXAM SECURE INFORMATION JPM Examinee: Evaluator:

RO SRO STA Non-Lic SRO CERT Date: LOIT RO LOIT SRO PERFORMANCE RESULTS:

SAT: UNSAT: Remediation required:

YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).

EXAMINER NOTE:

ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.

EVALUATOR'S SIGNATURE:

NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION JPM TURNOVER SHEET

INITIAL CONDITIONS:

INITIATING CUE:

NOTE: Ensure the turnover sheet is returned to the evaluator when the JPM is complete. L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC Exam Admin - JPM SRO A 3

L-16-1 NRC EXAM SECURE INFORMATION JOB PERFORMANCE MEAS URE L-16-1 NRC EXAM SECURE INFORMATION JPM JPM TITLE: JPM NUMBER:

REV. TASK NUMBER(S) / TASK TITLE(S): K/A NUMBERS:

K/A VALUE: Justification (FOR K/A VALUES <3.0):

TASK APPLICABILITY:

RO SRO STA Non-Lic SRO CERT OTHER: APPLICABLE METHOD OF TESTING:EVALUATION LOCATION: Developed by:

Alan Schilk 8/4/16 Reviewed by: Luis Sagion8/4/16 Validated by:

Sean Bloom8/5/16 Approved by:

Mark Wilson8/4/16 Approved by:

Sean Bloom8/5/16 L-16-1 NRC EXAM SECURE INFORMATION

0220001050 1 , Authorize Emergency Exposure Limits, Rev. 0-1 L-16-1 NRC EXAM SECURE INFORMATION JPM JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A Protected Conten t: L-16-1 NRC EXAM SECURE INFORMATION

0220001050 1 , Authorize Emergency Exposure Limits, Rev. 0-1 L-16-1 NRC EXAM SECURE INFORMATION JPM UPDATE LOG: # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE SUPERVISOR DATE L-16-1 NRC EXAM SECURE INFORMATION

0220001050 1 , Authorize Emergency Exposure Limits, Rev. 0-1 L-16-1 NRC EXAM SECURE INFORMATION JPM SIMULATOR SET

-UP:

Required Materials: General

References:

Task Standards:

L-16-1 NRC EXAM SECURE INFORMATION

0220001050 1 , Authorize Emergency Exposure Limits, Rev. 0-1 L-16-1 NRC EXAM SECURE INFORMATION JPM HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME

INITIAL CONDITIONS:

INITIATING CUE:

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

L-16-1 NRC EXAM SECURE INFORMATION

0220001050 1 , Authorize Emergency Exposure Limits, Rev. 0-1 L-16-1 NRC EXAM SECURE INFORMATION JPM JPM PERFORMANCE INFORMATION Start Time:

NOTE: When providing "Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically, cues are only provided when the examinee's actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a "Y es" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step: 1 Critical: No Obtain required reference materials.

Standard: Evaluator Cue:

Performance:

SATISFACTORY UNSATISFACTORY Comments:

L-16-1 NRC EXAM SECURE INFORMATION

0220001050 1 , Authorize Emergency Exposure Limits, Rev. 0-1 L-16-1 NRC EXAM SECURE INFORMATION JPM Performance Step: 2 Critical: No Determine whether the rescuers could receive radiation exposures in excess of the regulatory limit (5 rem/year). Standard: Evaluator Note:

Performance:

SATISFACTORY UNSATISFACTORY Comments:

L-16-1 NRC EXAM SECURE INFORMATION

0220001050 1 , Authorize Emergency Exposure Limits, Rev. 0-1 L-16-1 NRC EXAM SECURE INFORMATION JPM Performance Step: 3 Critical: Yes Exclude individuals as Rescue Team members, based on volunteer and declared

-pregnancy status. Standard: Evaluator Note:

This and the following steps may be performed in any order. Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step: 4 Critical: Yes Exclude individuals as Rescue Team members, based on age/youth. Standard: Evaluator Note:

Performance:

SATISFACTORY UNSATISFACTORY Comments: L-16-1 NRC EXAM SECURE INFORMATION

0220001050 1 , Authorize Emergency Exposure Limits, Rev. 0-1 L-16-1 NRC EXAM SECURE INFORMATION JPM Performance Step: 5 Critical: Yes Determine that the rescuers could receive thyroid exposures as high as 5 rem and exclude individuals as Rescue Team members, based on iodine sensitivity. Standard: Evaluator Note:

NOT Performance:

SATISFACTORY UNSATISFACTORY Comments:

L-16-1 NRC EXAM SECURE INFORMATION

0220001050 1 , Authorize Emergency Exposure Limits, Rev. 0-1 L-16-1 NRC EXAM SECURE INFORMATION JPM Performance Step: 6 Critical: Yes Exclude individuals as Rescue Team members, based on staffing requirements. Standard: Evaluator Cue:

Evaluator Note:

Performance:

SATISFACTORY UNSATISFACTORY Comments: Performance Step: 7 Critical: Yes Identify selectedRescue Team members and the need to issue potassium iodide to same. Standard: Evaluator Note:

Performance:

SATISFACTORY UNSATISFACTORY Comments: L-16-1 NRC EXAM SECURE INFORMATION

0220001050 1 , Authorize Emergency Exposure Limits, Rev. 0-1 L-16-1 NRC EXAM SECURE INFORMATION JPM Terminating Cue:

When the examinee completes Step 7 , state "This completes the JPM.

"

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

Stop Time:

L-16-1 NRC EXAM SECURE INFORMATION

0220001050 1 , Authorize Emergency Exposure Limits, Rev. 0-1 L-16-1 NRC EXAM SECURE INFORMATION JPM Exami nee: Evaluator:

RO SRO STA Non-Lic SRO CERT Date: LOIT RO LOIT SRO PERFORMANCE RESULTS:

SAT: UNSAT: Remediation required:

YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).

EXAMINER NOTE:

ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.

EVALUATOR'S SIGNATURE:

NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION JPM TURNOVER SHEET

INITIAL CONDITIONS:

INITIATING CUE:

NOTE: Ensure the turnover sheet is returned to the evaluator when the JPM is complete

.L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION JPM TURNOVER SHEET ADDENDUM List of Available Rescue Team Members

NOTE: Ensure the addendum sheet is returned to the evaluator when the JPM is complete.L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC Exam Admin - JPM SRO A 4

L-16-1 NRC EXAM SECURE INFORMATION JOB PERFORMANCE MEAS URE L-16-1 NRC EXAM SECURE INFORMATION JPM JPM TITLE: JPM NUMBER: REV. TASK NUMBER(S) / TASK TITLE(S): K/A NUMBERS:

K/A VALUE: Justification (FOR K/A VALUES <3.0):

TASK APPLICABILITY:

RO SRO STA Non-Lic SRO CERT OTHER: APPLICABLE METHOD OF TESTING:EVALUATION LOCATION: Developed by:

Alan Schilk 8/4/16 Reviewed by:

Luis Sagion8/4/16 Validated by:

S ean Bloom8/5/16 Approved by:

Mark Wilson8/4/16 Approved by:

S ean Bloom8/5/16 L-16-1 NRC EXAM SECURE INFORMATION

02201052320, Classify Event and Fill Out SNF, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM JOB PERFORMANCE MEASURE VALIDATION CHECKLIST ALL STEPS IN THIS CHECKLIST ARE TO BE PERFORMED PRIOR TO USE.

REVIEW STATEMENTS YES NO N/A

Protected Conten t: L-16-1 NRC EXAM SECURE INFORMATION

02201052320, Classify Event and Fill Out SNF, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM UPDATE LOG: # DESCRIPTION OF CHANGE REASON FOR CHANGE AR/TWR# PREPARER DATE SUPERVISOR DATE L-16-1 NRC EXAM SECURE INFORMATION

02201052320, Classify Event and Fill Out SNF, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM SIMULATOR SET

-UP:

Required Materials:

General

References:

Task Standards:

L-16-1 NRC EXAM SECURE INFORMATION

02201052320, Classify Event and Fill Out SNF, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME

INITIAL CONDITIONS:

SUBSEQUENT CONDITIONS (UNIT 3): INITIATING CUES:

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

L-16-1 NRC EXAM SECURE INFORMATION

02201052320, Classify Event and Fill Out SNF, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM JPM PERFORMANCE INFORMATION Start Time:

NOTE: When providing "Evaluator Cues" to the examinee, care must be exercised to avoid prompting the examinee. Typically, cues are only provided when the examinee's actions warrant receiving the information (i.e., the examinee looks or asks for the indication).

NOTE: Critical steps are marked with a "Y es" below the performance step number. Failure to meet the standard for any critical step shall result in failure of this JPM.

Performance Step: 1 Critical: No Obtain required reference materials.

Standard: Evaluator Cue:

Performance:

SATISFACTORY UNSATISFACTORY Comments:

L-16-1 NRC EXAM SECURE INFORMATION

02201052320, Classify Event and Fill Out SNF, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Performance Ste p: 2 Critical: No Review Turkey Point EAL Classification Tables (F668 and F669) and 0-EPIP-20101 (Duties of Emergency Coordinator), based on the given conditions. Standard: Performance: SATISFACTORY UNSATISFACTORY Comments: Performance Step: 3 Critical: Yes Determine the highest emergency classification level and EAL number using F669 (Turkey Point EAL Classification Tables

[Cold]). Standard: Evaluator Note: Evaluator Cue: Performance:

SATISFACTORY UNSATISFACTORY Comments: L-16-1 NRC EXAM SECURE INFORMATION

02201052320, Classify Event and Fill Out SNF, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Performance Step: 4 Critical: Yes Complete a Florida Nuclear Plant Emergency Notification Form (F439), in accordance with 0

-EPIP-20134 (Offsite Notifications and Protective Action Recommendations). Standard: Evaluator Note: Performance:

SATISFACTORY UNSATISFACTORY Comments: Terminating Cue:

When the examinee submits the Florida Nuclear Plant Emergency Notification Form (F439), state "This completes the JPM.

"

NOTE: Ensure the turnover sheet that was given to the examinee is returned to the evaluator.

Stop Time:

L-16-1 NRC EXAM SECURE INFORMATION

02201052320, Classify Event and Fill Out SNF, Rev. 1-0 L-16-1 NRC EXAM SECURE INFORMATION JPM Examinee: Evaluator:

RO SRO STA Non-Lic SRO CERT Date: LOIT RO LOIT SRO PERFORMANCE RESULTS:

SAT: UNSAT: Remediation required:

YES NO COMMENTS/FEEDBACK: (Comments shall be made for any steps graded unsatisfactory).

EXAMINER NOTE:

ENSURE ALL EXAM MATERIAL IS COLLECTED AND PROCEDURES CLEANED, AS APPROPRIATE.

EVALUATOR'S SIGNATURE:

NOTE: Only this page needs to be retained in examinee's record if completed satisfactorily. If unsatisfactory performance is demonstrated, the entire JPM should be retained.L-16-1 NRC EXAM SECURE INFORMATION

L-16-1 NRC EXAM SECURE INFORMATION JPM TURNOVER SHEET

INITIAL CONDITIONS:

SUBSEQUENT CONDITIONS (UNIT 3):

INITIATING CUES:

NOTE: Ensure the turnover sheet is returned to the evaluator when the JPM is complete. L-16-1 NRC EXAM SECURE INFORMATION