ML17165A485

302 Draft Simulator and in Plant JPMs

ML17165A485
Person / Time
Site:	Watts Bar
Issue date:	06/14/2017
From:	NRC/RGN-II
To:	Tennessee Valley Authority
References
50-390/13-302, 50-391/13-302 50-390/OL-13, 50-391/OL-13
Download: ML17165A485 (328)

Text

Watts Bar Nuclear Plant NRC Exam 2013302 System JPM A

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A

NRC EXAM 2013-302 EVALUATION SHEET Task: Transfer from Aux Feedwater LCV to Bypass Reg Valve during Startup.

Alternate Path: During transfer from Auxiliary Feedwater to Main Feedwater level control, 1-LCV-3-156, SG 2 SUPPLY FRM PMP A-A fails OPEN, requiring the 1A-A MD AFW Pump to be stopped from the MCR.

Facility JPM #: New Safety Function: 4S

Title:

Heat Removal From Reactor Core - Secondary System K/A 059 A4.08 Ability to manually operate and/or monitor in the control room: Feed regulating valve controller.

Rating(s): 3.0/2.9 CFR: 41.7/45.5 to 45.8 Evaluation Method: Simulator X In-Plant Classroom

References:

1-SOI-3.02, Auxiliary Feedwater System," Rev. 2.

Task Number: RO-003-SOI-3.02-012

Title:

Transfer SG level control from Auxiliary to Main Feedwater.

Task Standard: The applicant:

1.) Performs the actions required to transfer feedwater supply from 1-1-LIC 156A, SG 2 SUPPLY FRM PMP A-A to 1-LIC-3-103A, SG 4 MFW BYPASS REG CONTROL.

2.) Diagnoses the failure of 1-LCV-3-156A, SG 2 SUPPLY FRM PMP A-A OPEN and places 1-HS-3-118A, AFW PMP A-A in STOP, PULL-TO-LOCK to terminate the overfill of SG 2.

Validation Time: 15 minutes Time Critical: Yes No X

===============================================================

Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

==============================================================

COMMENTS Page 2 of 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A

NRC EXAM 2013-302 SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. RESET to Initial Condition 305 by performing the following actions:

a. Select ICManager on the THUNDERBAR menu (right hand side of Instructor Console Screen).

b. Locate IC# 305.

c. Right click on IC# 305.

d. Select Reset on the drop down menu.

e. Right click on RESET.

f. Enter the password for IC# 305.

g. Select Yes on the INITIAL CONDITION RESET pop-up window.

h. Perform SWITCH CHECK.

3. ENSURE the following information appears on the Director Summary Screen:

Key Type Event Delay Inserted Ramp Initial Final Value fw27c lcv-6-105a fail position M 00:00:00 00:00:00 00:00:00 100 100 fw27d lcv-6-105b fail position M 00:00:00 00:00:00 00:00:00 100 100 fw28b lcv-6-190ba fail position M 00:00:00 00:00:00 00:00:00 100 100 mux_01c047 36-d heater a5 level hi/lo (ls-6-133a/b) M 00:00:00 00:00:00 00:00:00 On On mux_01c048 37-d heater b5 level hi/lo (ls-6-153a/b) M 00:00:00 00:00:00 00:00:00 On On mux_01c049 37-d heater c5 level hi/lo (ls-6-172a/b) M 00:00:00 00:00:00 00:00:00 On On fw87b lcv-3-156 aux fw loop 2 fail to position M 30 00:00:00 00:00:00 100 25.6644

4. ENSURE Event 30 is loaded [rxclc156<= 0.6]

5. ENSURE Extra Operator is present in the simulator.

6. PLACE simulator in FREEZE until Examiner cue is given.

Page 3 of 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A

NRC EXAM 2013-302 Event Description/Role Play 1-LCV-3-156 fails open.

ROLE PLAY: When contacted as an AUO, repeat back the request to manually close 1-LCV-3-156A. Wait 1 minute and then report that 1-LCV-3-156A is jammed in the full open position.

Page 4 of 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A

NRC EXAM 2013-302 READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. Unit 1 is at approximately 2.5% power, with a startup in progress.

2. Both motor driven AFW pumps are in service, with the associated LCVs in AUTO controlling SG level.

2. Main Feedwater System is in Long Cycle Recirculation.

3. You are the control room operator.

INITIATING CUES:

The Unit Supervisor directs you to transfer from Auxiliary Feedwater LCV to Bypass Reg valve control on SG 2 using 1-SOI-3.02, Auxiliary Feedwater System, Section 8.11, "Transfer SG Level Control from Auxiliary to Main Feedwater," beginning at Step 3.

Notify the Unit Supervisor when transfer to Bypass Reg valve control is complete.

Page 5 of 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT START TIME: _______

NOTES

1) One SG level LCV / Bypass Reg Valve control should be transferred at a time. SG level should be stable BEFORE proceeding to the next SG.

2) Actions taken in Step 8.11[3] should correlate with expected responses in Step 8.11[4].

STEP 1: [3] PLACE Bypass Reg Valves in MANUAL AND SLOWLY CRITICAL OPEN valves [1-M-3]: (NA valves NOT needed): STEP

[3.2] 1-LIC-3-48A, SG 2 MFW BYPASS REG CONTROL ___ SAT STANDARD: ___ UNSAT Applicant locates 1-LIC-3-48A, SG 2 MFW BYPASS REG CONTROL and slowly opens the valve by depressing the >> pushbutton repeatedly until an increase in flow is observed on 1-FI-3-238 SG 2 BYPASS FLOW. (Critical).

Step is critical to establish main feedwater flow to SG 2.

COMMENTS:

NOTE Aux Feedwater SG LCVs may be placed in MANUAL prior to 8.11[5] if required to maintain SG levels on program.

Page 6 of 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 2: [4] ENSURE the following Aux Feedwater SG LCVs close as CRITICAL required to maintain SG levels on program [1-M-4]: (N/A valves STEP NOT needed)

___ SAT

___ UNSAT STANDARD:

Applicant locates 1-LIC-3-156A, SG 2 SUPPLY FRM PMP A-A, and observes OUTPUT indicator moving to the left, indicating that the valve is closing. (Critical).

Step is critical to determine that 1-LIC-3-156A is responding properly.

COMMENTS:

EXAMINER: Based on the NOTE preceding Step 4, the applicant may place 1-LIC 156A in MANUAL and CLOSE the LCV if SG 2 level is off program level.

If the applicant elects to close the valve manually, THEN the following actions will be required:

Applicant depresses the R/M pushbutton on 1-LIC-3-156A to place the controller in MANUAL.

Applicant moves the slider control to the left to close the LCV.

EXAMINER:

Whenever the output of 1-LIC-3-156A drops to less than approximately 30%, either by automatic response to SG 2 level rising OR by manual operator action to close the valve, 1-LCV-3-156A will fail OPEN.

When 1-LCV-3-156A fails OPEN, the applicant will have to manually stop the 1A-A MD AFW Pump to terminate the level rise.

Page 7 of 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 3: Applicant diagnoses the failure of 1-LCV-3-156A OPEN, and ___ SAT attempts to regain control of the valve.

___ UNSAT STANDARD:

Applicant locates 1-LIC-3-156A, SG 2 SUPPLY FRM PMP A-A, depresses the M pushbutton to transfer the controller to manual, then locks the slider control to the LEFT to the CLOSE position.

Applicant may pull the handswitch out to the CLOSE, PULL-TO-LOCK position.

COMMENTS:

STEP 4: Applicant determines that 1-LCV-3-156A has failed open, and CRITICAL determines that compensatory actions are required to terminate STEP the level rise in SG 2. ___ SAT STANDARD: ___ UNSAT If the applicant dispatches an AUO to locally close 1-LCV-3-156A, provide the following cue.

Cue: When contacted as an AUO, the Console Operator will repeat back the request to manually close 1-LCV-3-156A.

Console Operator will wait 1 minute and then report that 1-LCV-3-156A is jammed in the full open position.

Applicant locates 1-HS-3-118A, A-A MD AFWP, and rotates the handswitch to the LEFT to the STOP position. Applicant may pull the handswitch out to the STOP, PULL-TO-LOCK position.

Cue: When the applicant places 1-HS-3-118A, A-A MD AFWP in the STOP, PULL-TO-LOCK position, state that another operator will continue from here.

Step is critical to terminate the uncontrolled level rise in SG 2.

COMMENTS:

END OF TASK STOP TIME ________

Page 8 of 10

A Handout Package for Applicant

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

1. Unit 1 is at approximately 2.5% power, with a startup in progress.

2. Both motor driven AFW pumps are in service, with the associated LCVs in AUTO controlling SG level.

2. Main Feedwater System is in Long Cycle Recirculation.

3. You are the control room operator.

INITIATING CUES:

The Unit Supervisor directs you to transfer from Auxiliary Feedwater LCV to Bypass Reg valve control on SG 2 using SOI-3.02, Auxiliary Feedwater System, Section 8.11, "Transfer SG Level Control from Auxiliary to Main Feedwater," beginning at Step 3.

Notify the Unit Supervisor when transfer to Bypass Reg valve control is complete.

A

Watts Bar Nuclear Plant NRC EXAM 2013302 System JPM B

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B

NRC EXAM 2013-302 EVALUATION SHEET Task: Align ECCS pumps by performing ES-1.3, Transfer to Containment Sump.

Alternate Path: During performance of ES-1.3, Transfer to Containment Sump, the applicant will be unable to fully open 1-FCV-63-73, requiring the 1B-B RHR Pump to be placed in STOP, PULL-TO-LOCK.

Facility JPM #: 3-OT-JPM 021(Modified)

Safety Function: 3

Title:

Reactor Pressure Control K/A EA1.11 Ability to operate and monitor the following as they apply to a Large Break LOCA: Long-term core cooling.

Rating(s): 4.2/4.2 CFR: 41.7 / 45.5 / 45.6 Evaluation Method: Simulator X In-Plant Classroom

References:

ES-1.3, Transfer to Containment Sump, Rev. 18 Task Number: RO-113-ES-1.3-001

Title:

Perform transfer to Containment sump.

Task Standard: The applicant:

1.) Identifies the failure of 1-FCV-63-73, CNTMT SUMP TO RHR PUMP B SUCT, to OPEN and places the 1B-B RHR Pump in STOP, PULL-TO-LOCK.

2.) Stops one of the two running Containment Spray pumps and aligns for standby.

3.) Aligns the ECCS pumps for containment sump recirculation using ES-1.3, Transfer to Containment Sump.

Validation Time: 15 minutes Time Critical: Yes No X

============================================================

Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

=============================================================

COMMENTS Page 2 of 23

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B

NRC EXAM 2013-302 SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. RESET to Initial Condition 306 by performing the following actions:

a. Select ICManager on the THUNDERBAR menu (right hand side of Instructor Console Screen).

b. Locate IC# 306.

c. Right click on IC# 306.

d. Select Reset on the drop down menu.

e. Right click on RESET.

f. Enter the password for IC# 306.

g. Select Yes on the INITIAL CONDITION RESET pop-up window.

h. Perform SWITCH CHECK.

3. ENSURE the following information appears on the Director Summary Screen:

Key Type Event Delay Inserted Ramp Initial Final Value fw27c lcv-6-105a fail position M 00:00:00 00:00:00 00:00:00 100 100 cs06g air return fan a-a fail to start on phase b M 00:00:00 00:00:00 00:00:00 Active Active cs06h air return fan b-b fail to start on phase b M 00:00:00 00:00:00 00:00:00 Active Active th02c loca - cold leg loop 3 M 1 00:00:00 00:00:00 00:00:00 100 100 fw27d lcv-6-105b fail position M 19 00:00:00 00:00:00 00:00:00 100 100 fw28b lcv-6-190b fail M 19 00:00:00 00:00:00 00:00:00 100 100 rh09 fail cnt sump to rhr b fcv-63-73 to position M 2 00:00:00 00:00:00 00:00:00 25 25

4. Place simulator in RUN and acknowledge any alarms.

5. ENSURE a marked-up copy of ES-1.3, Transfer to Containment Sump, is available for the Examiner.

6. ENSURE the Extra Operator is present in the simulator.

7. Place simulator in FREEZE until Examiner cue is given.

Page 3 of 23

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B

NRC EXAM 2013-302 SIMULATOR CONTINGENCY ACTIONS:

IF INITIAL CONDITION 306 is unavailable for any reason, the following actions must be taken to reconstruct the IC.

1. Initialize to IC 50, 100% power BOL.

2. Perform switch check.

3. ENSURE the following information appears on the Director Summary Screen:

Key Type Event Delay Inserted Ramp Initial Final Value fw27c lcv-6-105a fail position M 00:00:00 00:00:00 00:00:00 100 100 cs06g air return fan a-a fail to start on phase b M 00:00:00 00:00:00 00:00:00 Active Active cs06h air return fan b-b fail to start on phase b M 00:00:00 00:00:00 00:00:00 Active Active th02c loca - cold leg loop 3 M 1 00:00:00 00:00:00 00:00:00 100 100 fw27d lcv-6-105b fail position M 19 00:00:00 00:00:00 00:00:00 100 100 fw28b lcv-6-190b fail M 19 00:00:00 00:00:00 00:00:00 100 100 rh09 fail cnt sump to rhr b fcv-63-73 to position M 2 00:00:00 00:00:00 00:00:00 25 25

4. Place simulator in RUN and acknowledge any alarms.

Page 4 of 23

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B

NRC EXAM 2013-302 READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. A large break loss-of-coolant event occurred 22 minutes ago.

2. The crew responded using 1-E-1, Loss of Reactor or Secondary Coolant.

3. 1-E-1, Loss of Reactor or Secondary Coolant, Appendix B, 1-FCV-63-1 Breaker Operation, is complete.

4. A-A Containment Air Return fan was out-of-service for repairs, and B-B Air Return Fan tripped when it received a start signal. Both Air Return Fans are currently in STOP, PULL-TO-LOCK.

5. RWST level is currently approximately 34% and dropping.

6. ES-1.3, Transfer to Containment Sump, was entered and has been performed through Step 4.

INITIATING CUES:

The Unit Supervisor directs you to complete transfer of the Emergency Core Cooling Pump (ECCS) suctions using ES-1.3, Transfer to Containment Sump, beginning at Step 5.

Notify the Unit Supervisor when transfer to the containment sump has been completed.

Page 5 of 23

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT START TIME: _______

STEP 1: 5. ENSURE automatic switchover complete: ___ SAT

a. ENSURE cntmt sump valves 1-FCV-63-72 and 1-FCV-63-73 ___ UNSAT OPEN.

STANDARD:

Applicant locates 1-HS-63-72, CNTMT SUMP TO RHR PMP A SUCT, and determines that the valve is OPEN by observing the RED light is LIT and GREEN light is DARK.

Applicant locates 1-HS-63-73, CNTMT SUMP TO RHR PMP B SUCT, and determines that the valve is in MID-POSITION by observing the RED light is LIT and GREEN light is LIT.

Applicant may rotate 1-HS-63-73, CNTMT SUMP TO RHR PMP B SUCT, to the RIGHT to attempt to manually OPEN the valve.

Applicant determines that 1-HS-63-73 has failed to OPEN and enters the RESPONSE NOT OBTAINED column.

COMMENTS:

Page 6 of 23

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 2: 5.a. RESPONSE NOT OBTAINED: CRITICAL IF ONE cntmt sump valve can NOT be fully opened, THEN STEP STOP and PULL TO LOCK RHR pump on the associated ___ SAT train. ___ UNSAT STANDARD:

Applicant locates 1-HS-74-20A, RHR PMP B (ECCS) and rotates the handswitch to the left to the STOP position, then pulls the handswitch out. (Critical).

Applicant determines that the 1B-B RHR Pump is off by observing the RED light is DARK and GREEN light is LIT.

Step is critical since 1-FCV-63-73 must be fully open to satisfy the open interlock with 1-FCV-63-11.

COMMENTS:

STEP 3: 5. ENSURE automatic switchover complete: ___ SAT

b. ENSURE RWST to RHR suction valves 1-FCV-74-3 and 1- ___ UNSAT FCV-74-21 CLOSED.

STANDARD:

Applicant locates 1-HS-74-3A, RHR PMP A SUCTION and determines that the valve is CLOSED by observing the RED light is DARK and GREEN light is LIT.

Applicant locates 1-HS-74-21A, RHR PMP B SUCTION and determines that the valve is CLOSED by observing the RED light is DARK and GREEN light is LIT.

COMMENTS:

Page 7 of 23

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 4: 5. ENSURE automatic switchover complete: ___ SAT

c. INITIATE power restoration to 1-FCV-63-1 USING Appendix ___ UNSAT A (ES-1.3), 1-FCV-63-1 Breaker Operation.

STANDARD:

Applicant determines from the INITIAL CONDITIONS that power has been restored to 1-FCV-63-1 during performance of 1-E-1, Appendix B.

COMMENTS:

CAUTION If RWST level drops to 8%, then any charging, SI or cntmt spray pump taking suction from the RWST must be stopped.

STEP 5: 6. MONITOR RWST level greater than 8%. ___ SAT STANDARD: ___ UNSAT Applicant locates 1-LI-63-50, RWST LEVEL, 1-LI-63-51, RWST LEVEL, 1-LI-63-52, RWST LEVEL and 1-LI-63-53, RWST LEVEL, and determines level is greater than 8%.

COMMENTS:

Page 8 of 23

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 6: 7. DETERMINE if cntmt spray should be stopped: ___ SAT

a. MONITOR cntmt press less than 2.0 psig. ___ UNSAT STANDARD:

Applicant locates 1-PDI-30-42, CNTMT PRESS, 1-PDI-30-43, CNTMT PRESS, 1-PDI-30-43, CNTMT PRESS, and 1-PDI-30-42, CNTMT PRESS, and determines pressure is GREATER THAN 2 psig.

COMMENTS:

STEP 7: 7.a. RESPONSE NOT OBTAINED: ___ SAT

a. WHEN cntmt press less than 2.0 psig, THEN PERFORM ___ UNSAT Substeps 7b thru e. GO TO Step 8.

STANDARD:

Applicant acknowledges the continuous action step, and proceeds to Step 8.

COMMENTS:

STEP 8: 8. DETERMINE if ONE train cntmt spray should be stopped: ___ SAT

a. CHECK BOTH trains cntmt spray delivering flow. ___ UNSAT STANDARD:

Applicant observes 1-FI-72-34, CS PMP A FLOW and 1-FI-72-13, CS PMP B FLOW and determines both spray pumps are delivering flow.

COMMENTS:

Page 9 of 23

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 9: 8. DETERMINE if ONE train cntmt spray should be stopped: CRITICAL

b. RESET cntmt spray signal. STEP

___ SAT STANDARD:

Applicant locates 1-HS-72-43 and depresses the pushbutton to RESET Train A CS signal. Applicant observes RED CS light DARK ___ UNSAT on 1-XX-55-6C,MASTER ISOLATION SIGNAL STATUS PANEL OR Applicant locates 1-HS-72-42 and depresses the pushbutton to RESET Train B CS signal. Applicant observes RED CS light DARK on 1-XX-55-6D,MASTER ISOLATION SIGNAL STATUS PANEL Step is critical to shutdown one containment spray pump.

COMMENTS:

STEP 10: 8. DETERMINE if ONE train cntmt spray should be stopped: CRITICAL

c. STOP ONE cntmt spray pump AND PLACE in A-AUTO. STEP

___ SAT STANDARD:

___ UNSAT Applicant locates 1-HS-72-27A, CNTMT SPRAY PMP A and rotates the handswitch to the LEFT to the STOP position. Applicant observes RED light DARK and GREEN light LIT.

OR Applicant locates 1-HS-72-10A, CNTMT SPRAY PMP B and rotates the handswitch to the LEFT to the STOP position. Applicant observes RED light DARK and GREEN light LIT Step is critical to shutdown one containment spray pump to conserve inventory in the RWST while performing ECCS pump swapover.

COMMENTS:

Page 10 of 23

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 11: 8.a. RESPONSE NOT OBTAINED: CRITICAL

d. CLOSE spray discharge valve for stopped pump. STEP

___ SAT STANDARD:

___ UNSAT Applicant locates 1-HS-72-39A, CNTMT SPRAY HDR A TO CNTMT and rotates the handswitch to the LEFT to the CLOSE position.

Applicant observes RED light DARK and GREEN light LIT.

OR Applicant locates 1-HS-72-2A, CNTMT SPRAY HDR B TO CNTMT and rotates the handswitch to the LEFT to the CLOSE position.

Applicant observes RED light DARK and GREEN light LIT.

Step is critical to shutdown one containment spray pump to conserve inventory in the RWST while performing ECCS pump swapover.

COMMENTS:

STEP 12: 9. MONITOR RCS press less than 1350 psig. ___ SAT STANDARD: ___ UNSAT Applicant locates a RCS wide range pressure instrument and determines that pressure is less than 1350 psig.

COMMENTS:

CAUTION If a valve fails during the transfer sequence, any corrective action should be postponed UNTIL transfer is complete, EXCEPT as required to satisfy each step.

NOTE Each transfer sequence action is identified by a number on the control board (e.g. #1).

Page 11 of 23

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 13: 10. (#1) ISOLATE SI pump miniflow: CRITICAL

• CLOSE 1-FCV-63-3. STEP

___ SAT

• CLOSE 1-FCV-63-175.

___ UNSAT

• CLOSE 1-FCV-63-4.

STANDARD:

Applicant rotates handswitch 1-HS-63-3 to the left to the CLOSE position (Critical).

Applicant determines that the valve is CLOSED by observing the RED light is DARK and GREEN light is LIT.

Applicant rotates handswitch 1-HS-63-175 to the left to the CLOSE position (Critical).

Applicant determines that the valve is CLOSED by observing the RED light is DARK and GREEN light is LIT.

Applicant rotates handswitch 1-HS-63-4 to the left to the CLOSE position (Critical).

Applicant determines that the valve is CLOSED by observing the RED light is DARK and GREEN light is LIT.

Steps are critical since closure of the recirculation valves prevents radioactive sump water from being pumped to the RWST.

COMMENTS:

Page 12 of 23

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 14: 11. (#2) ISOLATE RHR crossties: CRITICAL

• CLOSE 1-FCV-74-33. STEP

___ SAT

• CLOSE 1-FCV-74-35.

___ UNSAT STANDARD:

Applicant rotates handswitch 1-HS-74-33 to the left to the CLOSE position (Critical).

Applicant identifies the valve is CLOSED by observing the RED light is DARK and GREEN light is LIT.

Applicant rotates handswitch 1-HS-74-35 to the left to the CLOSE position (Critical).

Applicant determines that the valve is CLOSED by observing the RED light is DARK and GREEN light is LIT.

Step is critical to provide complete separation of the two low-head SI cold leg injection headers. Also, by closing these valves, a desirable increase in the total system resistance is obtained should only one RHR pump be available, since it would deliver to only two RHR branch lines while simultaneously delivering to the suction of the operating charging and SI pumps.

COMMENTS:

Page 13 of 23

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 15: 12. (#3) ALIGN charging pump and SI pump supply from RHR: CRITICAL

• OPEN 1-FCV-63-6. STEP

___ SAT

• OPEN 1-FCV-63-7.

___ UNSAT

• ENSURE 1-FCV-63-177 OPEN.

STANDARD:

Applicant rotates handswitch 1-HS-63-6 right to the OPEN position (Critical).

Applicant identifies the valve is OPEN by observing the RED light is LIT and GREEN light is DARK.

Applicant rotates handswitch 1-HS-63-7 right to the OPEN position (Critical).

Applicant identifies the valve is OPEN by observing the RED light is LIT and GREEN light is DARK.

Applicant determines 1-HS-63-177 is OPEN observing the RED light is LIT and GREEN light is DARK.

Step is critical since this alignment is required to support long-term cooling from the containment sump.

COMMENTS:

NOTE 1-FCV-63-8 and 1-FCV-63-11 are interlocked with the SI pump miniflows being full closed.

Page 14 of 23

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 16: 13. (#4) ALIGN RHR discharge to charging pump and SI pump CRITICAL suction: STEP

a. OPEN 1-FCV-63-8. ___ SAT STANDARD: ___ UNSAT Applicant rotates handswitch 1-HS-63-8 to the right to the OPEN position (Critical).

Applicant identifies the valve is OPEN by observing the RED light is LIT and GREEN light is DARK.

Step is critical since this alignment is required to support long-term cooling from the containment sump.

COMMENTS:

STEP 17: 13. (#4) ALIGN RHR discharge to charging pump and SI pump ___ SAT suction: ___ UNSAT

b. OPEN 1-FCV-63-11.

STANDARD:

Applicant determines that 1-HS-63-11 WILL NOT open since the open interlock conditions are not met.

Applicant identifies the valve is CLOSED by observing the RED light is DARK and GREEN light is LIT.

COMMENTS:

Page 15 of 23

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 18: 13.b, RESPONSE NOT OBTAINED: ___ SAT

b. ENSURE Train A RHR operation: ___ UNSAT

• Train A RHR pump RUNNING.

• 1-FCV-63-8 OPEN.

• Either 1-FCV-63-6 or 1-FCV-63-7 OPEN.

STANDARD:

Applicant locates 1-HS-74-10A, RHR PMP A (ECCS) and determines that the 1A-A RHR Pump is running by observing the RED light is LIT and GREEN light is DARK.

AND Applicant locates 1-HS-63-8 and determines the valve is OPEN by observing the RED light is LIT and GREEN light is DARK.

AND Applicant locates 1-HS-63-6 and determines the valve is OPEN by observing the RED light is LIT and GREEN light is DARK OR Applicant locates handswitch 1-HS-63-7 and determines the valve is OPEN by observing the RED light is LIT and GREEN light is DARK.

COMMENTS:

Page 16 of 23

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 19: 14. DO NOT CONTINUE this Instruction UNTIL Steps 10 thru ___ SAT 13 complete. ___ UNSAT STANDARD:

Applicant determines that all steps or related contingency actions have been completed and continues to Step 15.

COMMENTS:

CAUTION If RCS press is greater than 1350 psig, the SI pumps should NOT be restarted because the recirc path is isolated.

STEP 20: 15. RESTART any charging pumps and SI pumps as ___ SAT necessary. ___ UNSAT STANDARD:

Applicant determines that all charging and SI pumps are running.

COMMENTS:

CAUTION If offsite power is lost after SI reset, manual action will be required to restart the SI pumps and RHR pumps due to loss of SI start signal.

Page 17 of 23

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 21: 16. (#5) RESET SI, and CHECK the following: CRITICAL

• SI ACTUATED permissive DARK. STEP

___ SAT

• AUTO SI BLOCKED permissive LIT.

___ UNSAT STANDARD:

Applicant depresses each SI reset pushbutton on panel 1-M-6 and observes the SI ACTUATED permissive light DARK, and the AUTO SI BLOCKED light is LIT.

Step is critical since the valves to be operated in subsequent steps cannot be repositioned until the SI signal is reset.

COMMENTS:

STEP 22: 17. IF offsite power is lost, THEN: ___ SAT

a. PLACE charging pumps in PULL TO LOCK. ___ UNSAT

b. RESTART RHR pumps.

c. RESTART charging pumps.

d. IF RCS press less than 1350 psig, THEN RESTART SI pumps.

STANDARD:

Applicant acknowledges information in the step, and since power has not been lost, continues to the next step.

COMMENTS:

CAUTION ECCS pump discharge flow and motor amps should be monitored WHILE closing the RWST suction valves.

Page 18 of 23

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 23: 18. (#6) ISOLATE charging pump suction from RWST: CRITICAL

a. CLOSE 1-LCV-62-135. STEP

___ SAT

b. CLOSE 1-LCV-62-136.

___ UNSAT

c. ENSURE 1-HS-62-135A in A-AUTO (pushed in).

d. ENSURE 1-HS-62-136A in A-AUTO (pushed in).

STANDARD:

Applicant pushes 1-HS-62-135 handswitch in, and then rotates the handswitch to the left to the CLOSED position (Critical).

Applicant identifies the valve is closed by observing the RED light is DARK and GREEN light is LIT.

Applicant pushes 1-HS-62-136 handswitch in, and then rotates the handswitch to the left to the CLOSED position (Critical).

Applicant identifies the valve is closed by observing the RED light is DARK and GREEN light is LIT.

Applicant determines that the handswitch for 1-HS-62-135 has remained in the pushed-in position (Critical).

Applicant determines that the handswitch for 1-HS-62-136 has remained in the pushed-in position (Critical).

Step is critical to complete the alignment of ECCS pumps to establish and maintain long term core cooling.

COMMENTS:

Page 19 of 23

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 24: 19. (#7) ISOLATE SI pump suction from RWST: CRITICAL

• CLOSE 1-FCV-63-5. STEP

___ SAT STANDARD:

___ UNSAT Applicant rotates handswitch 1-HS-63-5A to the left to the CLOSED position (Critical).

Applicant identifies the valve is closed by observing the RED light is DARK and GREEN light is LIT.

Step is critical to complete the alignment of ECCS pumps to establish long term core cooling.

COMMENTS:

STEP 25: 20. (#8) ISOLATE RHR suction from RWST: CRITICAL

a. ENSURE power restored to1-FCV-63-1 USING Appendix STEP A (ES-1.3), 1-FCV-63-1 Breaker Operation. ___ SAT

b. CLOSE 1-FCV-63-1. ___ UNSAT STANDARD:

Applicant determines from the INITIAL CONDITIONS that power has been restored to 1-FCV-63-1, RWST TO RHR ECCS SUCTION.

Applicant rotates handswitch 1-HS-63-1A to the left to the CLOSED position (Critical).

Applicant identifies the valve is closed by observing the RED light is DARK and GREEN light is LIT.

Step is critical to complete the alignment of ECCS pumps to establish long term core cooling.

COMMENTS:

Page 20 of 23

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 26: Notify the Unit Supervisor that transfer to the RHR containment ___ SAT sump is complete. ___ UNSAT STANDARD:

Applicant notifies the Unit Supervisor that ECCS pumps are aligned to the containment sump, and reports portions of the system that failed to operate as expected (1-FCV-63-73 failed to close; which resulted in the OPEN interlock for 1-FCV-63-11 to fail.)

EXAMINER CUE: Another operator will continue with the alignment of containment spray RWST suction:

COMMENTS:

END OF TASK STOP TIME ________

Page 21 of 23

B Handout Package for Applicant

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

1. A large break loss-of-coolant event occurred 22 minutes ago.

2. The crew responded using 1-E-1, Loss of Reactor or Secondary Coolant.

3. 1-E-1, Loss of Reactor or Secondary Coolant, Appendix B, 1-FCV-63-1 Breaker Operation, is complete.

4. A-A Containment Air Return fan was out-of-service for repairs, and B-B Air Return Fan tripped when it received a start signal. Both Air Return Fans are currently in STOP, PULL-TO-LOCK.

5. RWST level is currently approximately 34% and dropping.

6. ES-1.3, Transfer to Containment Sump, was entered and has been performed through Step 4.

INITIATING CUES:

The Unit Supervisor directs you to complete transfer of the Emergency Core Cooling Pump (ECCS) suctions using ES-1.3, Transfer to Containment Sump, beginning at Step 5.

Notify the Unit Supervisor when transfer to the containment sump has been completed.

B

Watts Bar Nuclear Plant Unit 1 Emergency Operating Instruction ES-1.3 Transfer to Containment Sump Revision 0018 Quality Related Level of Use: Continuous Use Effective Date: 03-23-2011 Responsible Organization: OPS, Operations Prepared By: R. A. O'Rear Approved By: Gregory A. Evans Current Revision Description Conversion to Word 2007 template. Minor editorial changes: Revised Step 5 RNO to restore wording of previous revision for clarification and to give better guidance to Operators. [PCR 4319] Training feedback to clarify wording within guidelines of writer guide which did not change intent of affected steps [PCR 3552] Added Note after transfer sequence to remind Operators FRs can be implemented.

WBN Transfer to Containment Sump ES-1.3 Unit 1 Rev. 0018 1.0 PURPOSE This Instruction provides actions for transferring ECCS and containment spray suction to the containment sump for recirculation mode.

2.0 SYMPTOMS AND ENTRY CONDITIONS 2.1 Indications RWST level below 34%.

2.2 Transitions A. E-1, Loss Of Reactor Or Secondary Coolant.

B. ES-1.2, Post LOCA Cooldown.

C. FR-C.1, Inadequate Core Cooling.

D. FR-C.2, Saturated Core Cooling.

E. FR-H.1, Loss Of Secondary Heat Sink.

F. ECA-2.1, Uncontrolled Depressurization Of All Steam Generators.

G. ECA-3.1, SGTR and LOCA - Subcooled Recovery.

H. ECA-3.2, SGTR and LOCA - Saturated Recovery.

3.0 OPERATOR ACTIONS Page 2 of 25

WBN Transfer to Containment Sump ES-1.3 Unit 1 Rev. 0018 Step Action/Expected Response Response Not Obtained CAUTION

• ECCS flow to RCS must be maintained at all times to ensure adequate core cooling.

• Transfer to recirculation mode may cause high radiation in the Auxiliary Building.

NOTES

• Performance of this Instruction is a higher priority than performance of the FRs because it maintains ECCS pump suction.

• The transfer sequence should be performed without delay.

Implementation of FRs is delayed UNTIL transfer sequence is completed or transitioned from.

1. ENSURE both RHR pumps IF NO RHR pumps can be started, RUNNING. THEN

• • GO TO ECA-1.1, Loss of RHR Sump Recirculation.

Page 3 of 25

WBN Transfer to Containment Sump ES-1.3 Unit 1 Rev. 0018 Step Action/Expected Response Response Not Obtained

2. ESTABLISH CCS to RHR heat exchangers [M-27B]:

a. ENSURE RHR heat exchanger outlet valves 1-FCV-70-153 and 1-FCV-70-156 OPEN.

b. CLOSE SFP heat exchanger A CCS supply 0-FCV-70-197.

c. ENSURE CCS flow to ESF c. WHEN transfer to supply header and greater cntmt sump completed, than 5000 gpm. THEN

• Train A: 1-FI-70-159 REFER TO Appendix B (ES-1.3),

• Train B: 1-FI-70-165 CCS Operation, to adjust CCS flows as necessary.

d. MONITOR level in CCS surge tanks.

3. CHECK RWST level less than 34%. DO NOT CONTINUE this Instruction UNTIL RWST level less than 34%.

4. CHECK cntmt sump level **GO TO ECA-1.1, Loss of RHR Sump greater than or equal to 16.1 %. Recirculation.

Page 4 of 25

WBN Transfer to Containment Sump ES-1.3 Unit 1 Rev. 0018 Step Action/Expected Response Response Not Obtained

5. ENSURE automatic switchover complete:

a. ENSURE cntmt sump valves IF ONE cntmt sump valve 1-FCV-63-72 and 1-FCV-63-73 can NOT be fully opened, OPEN. THEN STOP and PULL TO LOCK RHR pump on the associated train.

IF flow from cntmt sump can NOT be established, THEN

• • GO TO ECA-1.1, Loss of RHR Sump Recirculation.

b. ENSURE RWST to RHR suction valves 1-FCV-74-3 and 1-FCV-74-21 CLOSED.

c. INITIATE power restoration to 1-FCV-63-1 USING Appendix A (ES-1.3), 1-FCV-63-1 Breaker Operation.

CAUTION If RWST level drops to 8%, then any charging, SI or cntmt spray pump taking suction from the RWST must be stopped.

6. MONITOR RWST level STOP and PULL TO LOCK pumps greater than 8%. taking suction from the RWST.

Page 5 of 25

WBN Transfer to Containment Sump ES-1.3 Unit 1 Rev. 0018 Step Action/Expected Response Response Not Obtained

7. DETERMINE if cntmt spray should be stopped:

a. MONITOR cntmt press a. WHEN cntmt press less than 2.0 psig. less than 2.0 psig, THEN PERFORM Substeps 7b thru e.

• • GO TO Step 8.

b. CHECK at least one b. **GO TO Step 9.

cntmt spray pump RUNNING.

c. RESET cntmt spray signal.

d. STOP cntmt spray pumps AND PLACE in A-AUTO.

e. CLOSE cntmt spray discharge valves 1-FCV-72-2 and 1-FCV-72-39.

f. ** GO TO Step 9.

Page 6 of 25

WBN Transfer to Containment Sump ES-1.3 Unit 1 Rev. 0018 Step Action/Expected Response Response Not Obtained

8. DETERMINE if ONE train cntmt spray should be stopped:

a. CHECK BOTH trains cntmt a. **GO TO Step 9.

spray delivering flow.

b. RESET cntmt spray signal.

c. STOP ONE cntmt spray pump AND PLACE in A-AUTO.

d. CLOSE spray discharge valve for stopped pump.

9. MONITOR RCS press less than STOP both SI pumps.

1350 psig.

Page 7 of 25

WBN Transfer to Containment Sump ES-1.3 Unit 1 Rev. 0018 Step Action/Expected Response Response Not Obtained CAUTION If a valve fails during the transfer sequence, any corrective action should be postponed UNTIL transfer is complete, EXCEPT as required to satisfy each step.

NOTE Each transfer sequence action is identified by a number on the control board (e.g. #1).

10. (#1) ISOLATE SI pump miniflow: ENSURE either:

• CLOSE 1-FCV-63-3. a. 1-FCV-63-3 CLOSED,

• CLOSE 1-FCV-63-175.

OR

• CLOSE 1-FCV-63-4. b. 1-FCV-63-4 and 1-FCV-63-175 CLOSED.

11. (#2) ISOLATE RHR crossties: ENSURE either 1-FCV-74-33 or 1-FCV-74-35 CLOSED.

• CLOSE 1-FCV-74-33.

• CLOSE 1-FCV-74-35.

12. (#3) ALIGN charging pump ENSURE either 1-FCV-63-6 and SI pump supply from RHR: or 1-FCV-63-7 OPEN.

• OPEN 1-FCV-63-6.

• OPEN 1-FCV-63-7.

• ENSURE 1-FCV-63-177 OPEN.

Page 8 of 25

WBN Transfer to Containment Sump ES-1.3 Unit 1 Rev. 0018 Step Action/Expected Response Response Not Obtained NOTE 1-FCV-63-8 and 1-FCV-63-11 are interlocked with the SI pump miniflows being full closed.

13. (#4) ALIGN RHR discharge to charging pump and SI pump suction:

a. OPEN 1-FCV-63-8. a. ENSURE Train B RHR operation:

• Train B RHR pump RUNNING.

• 1-FCV-63-11 OPEN.

• Either 1-FCV-63-6 or 1-FCV-63-7 OPEN.

b. OPEN 1-FCV-63-11. b. ENSURE Train A RHR operation:

• Train A RHR pump RUNNING.

• 1-FCV-63-8 OPEN.

• Either 1-FCV-63-6 or 1-FCV-63-7 OPEN.

14. DO NOT CONTINUE this Instruction UNTIL Steps 10 thru 13 complete.

Page 9 of 25

WBN Transfer to Containment Sump ES-1.3 Unit 1 Rev. 0018 Step Action/Expected Response Response Not Obtained CAUTION If RCS press is greater than 1350 psig, the SI pumps should NOT be restarted because the recirc path is isolated.

15. RESTART any charging pumps and SI pumps as necessary.

CAUTION If offsite power is lost after SI reset, manual action will be required to restart the SI pumps and RHR pumps due to loss of SI start signal.

16. (#5) RESET SI, and CHECK the NOTIFY IMs to block Auto SI USING following: IMI-99.040, Auto SI Block.

• SI ACTUATED permissive DARK.

• AUTO SI BLOCKED permissive LIT.

17. IF offsite power is lost, THEN

a. PLACE charging pumps in PULL TO LOCK.

b. RESTART RHR pumps.

c. RESTART charging pumps.

d. IF RCS press less than 1350 psig, THEN RESTART SI pumps.

Page 10 of 25

WBN Transfer to Containment Sump ES-1.3 Unit 1 Rev. 0018 Step Action/Expected Response Response Not Obtained CAUTION ECCS pump discharge flow and motor amps should be monitored WHILE closing the RWST suction valves.

18. (#6) ISOLATE charging pump suction from RWST:

a. CLOSE 1-LCV-62-135.

b. CLOSE 1-LCV-62-136.

c. ENSURE 1-HS-62-135A in A-AUTO (pushed in).

d. ENSURE 1-HS-62-136A in A-AUTO (pushed in).

19. (#7) ISOLATE SI pump suction from RWST:

• CLOSE 1-FCV-63-5.

20. (#8) ISOLATE RHR suction from RWST:

a. ENSURE power restored to 1-FCV-63-1 USING Appendix A (ES-1.3), 1-FCV-63-1 Breaker Operation.

b. CLOSE 1-FCV-63-1.

Page 11 of 25

WBN Transfer to Containment Sump ES-1.3 Unit 1 Rev. 0018 Step Action/Expected Response Response Not Obtained CAUTION

• The containment spray pump MUST stay aligned to the RWST UNTIL the RWST level is less than 8% to ensure sufficient sump inventory for spray pump operation.

• If containment pressure is greater than or equal to 2.0 psig, the containment spray pump suction must be aligned and pump restarted within 120 seconds.

NOTE FRs may now be implemented as required.

21. ALIGN cntmt spray RWST suction:

a. CHECK spray pumps RUNNING. a. NOTIFY TSC to evaluate starting spray pumps to pump RWST to cntmt sump.

• • GO TO Caution prior to Step 26.

b. CHECK RWST level b. WHEN RWST level less than 8%,

less than 8%. THEN CONTINUE with Substeps 21c and d through Step 25 of this instruction.

• • GO TO Caution prior to Step 26.

c. STOP both cntmt spray pumps, AND PLACE in PULL TO LOCK.

d. ISOLATE cntmt spray suction from RWST:

• CLOSE 1-FCV-72-22.

• CLOSE 1-FCV-72-21.

Page 12 of 25

WBN Transfer to Containment Sump ES-1.3 Unit 1 Rev. 0018 Step Action/Expected Response Response Not Obtained

22. ENSURE ERCW aligned for CONSULT TSC for ERCW limitations.

sump recirc operation:

• REFER TO Appendix C (ES-1.3),

ERCW Operation.

23. ALIGN cntmt spray sump suction:

a. OPEN 1-FCV-72-44 cntmt spray a. ENSURE suction from RWST suction from cntmt sump. 1-FCV-72-22 FULLY CLOSED.

b. OPEN 1-FCV-72-45 cntmt spray b. ENSURE suction from RWST suction from cntmt sump. 1-FCV-72-21 FULLY CLOSED.

24. MONITOR cntmt press INITIATE cntmt spray:

less than 2.0 psig. a. START cntmt spray pumps.

b. OPEN discharge valves 1-FCV-72-2 and 1-FCV-72-39.

c. ENSURE spray flow on 1-FI-72-34 and 1-FI-72-13.

25. ENSURE cntmt spray pumps in A-AUTO.

Page 13 of 25

WBN Transfer to Containment Sump ES-1.3 Unit 1 Rev. 0018 Step Action/Expected Response Response Not Obtained CAUTION Continued ECCS or Containment Spray pump operation following loss of suction will result in pump damage. Loss of suction to RHR pumps will require stopping all ECCS pumps.

26. MONITOR for containment sump blockage.

a. INITIATE Appendix D (ES-1.3),

Monitoring for Containment Sump Blockage.

b. CHECK for indications of b. **GO TO Note prior to Step 27.

cavitation on ECCS or Containment Spray.

c. IF sump blockage results in loss of suction to ECCS pumps, THEN STOP CCPs, SI pumps and RHR pumps, PLACE in PULL TO LOCK, AND NOTIFY TSC.

d. IF sump blockage results in loss of suction to Cntmt Spray pumps, THEN STOP Cntmt Spray pumps, PLACE in PULL TO LOCK AND NOTIFY TSC.

Step continued on next page Page 14 of 25

WBN Transfer to Containment Sump ES-1.3 Unit 1 Rev. 0018 Step Action/Expected Response Response Not Obtained

26. (continued)

e. IF ECCS or Cntmt Spray flow lost due to sump blockage, THEN

• • GO TO ECA-1.1, Loss of RHR Sump Recirculation.

NOTE Time since initiation of event and guidance for transfer to hot leg recirculation is defined in E-1, Loss of Reactor or Secondary Coolant.

27. VERIFY that this instruction CONSULT TSC for guidance was entered from E-1. on when to transfer to hot leg recirculation (ES-1.4).

28. RETURN TO Instruction in effect.

End of Section Page 15 of 25

WBN Transfer to Containment Sump ES-1.3 Unit 1 Rev. 0018 Appendix A (Page 1 of 1) 1-FCV-63-1 Breaker Operation CLOSE the following to restore power to 1-FCV-63-1:

BOARD COMPT NOMENCLATURE 480 V Reactor 1-BKR-63-1A MOV Board 2E1 RWST TO RHR SUCT 1A1-A (1-FCV-63-1)

Page 16 of 25

WBN Transfer to Containment Sump ES-1.3 Unit 1 Rev. 0018 Appendix B (Page 1 of 1)

CCS Operation 1.0 INSTRUCTIONS This Appendix provides general guidance for the operation of the Component Cooling Water System during the Containment Sump Recirculation phase.

A. If BOTH trains of Shutdown power are available:

• Spent Fuel Pool Cooling heat exchanger should be supplied from Train B or be temporarily isolated to ensure adequate cooling of the RHR heat exchanger.

B. If ONE train of Shutdown power is NOT available:

1. If Train A Shutdown power is lost, the Spent Fuel Pool Cooling heat exchanger A should be aligned to CCS heat exchanger A with the 1B-B CCS pump aligned to Train A to provide cooling flow.

2. If Train B Shutdown power is lost the CCS pump C-S should be aligned to the Train A CCS to provide additional flow capacity.

3. Nonessential equipment should be evaluated and CCS flow reduced or isolated if possible. This equipment includes:

a. Letdown heat exchanger.

b. Excess letdown heat exchanger.

c. Spent Fuel heat exchanger.

d. Reactor Coolant Pumps.

Page 17 of 25

WBN Transfer to Containment Sump ES-1.3 Unit 1 Rev. 0018 Appendix C (Page 1 of 1)

ERCW Operation 1.0 INSTRUCTIONS A. ENSURE at least two ERCW pumps running on each train.

B. ALIGN ERCW to Train A cntmt spray:

• OPEN 1-FCV-67-125, CNTMT SPRAY HX 1A INLET.

• OPEN 1-FCV-67-126, CNTMT SPRAY HX 1A RETURN.

C. ALIGN ERCW to Train B cntmt spray:

• OPEN 1-FCV-67-123, CNTMT SPRAY HX 1B INLET.

• OPEN 1-FCV-67-124, CNTMT SPRAY HX 1B RETURN.

D. IF supply flow less than 5200 gpm on 1-FI-67-136 CS HX 1A SUP FLOW or 1-FI-67-122 CS HX SUP FLOW, THEN ADJUST CCS heat exchanger outlet valves as necessary and CONSULT TSC.

Page 18 of 25

WBN Transfer to Containment Sump ES-1.3 Unit 1 Rev. 0018 Appendix D (Page 1 of 7)

Monitoring for Containment Sump Blockage 1.0 INSTRUCTIONS NOTE The following step records initial baseline readings after cold leg recirculation is established to aid in monitoring for sump blockage. This step should be repeated if parameters change due to operator action.

A. RECORD the following parameters:

Date Time INDICATOR READING CIRCLE ONE RCS Pressure (ICCM plasma display) 1-M-4 or 1-M-6 Containment Sump Level (1-LI-63-180 or 181) 180 or 181 RHR Pump A amps (1-EI-74-5A)

Pump B amps (1-EI-74-17A)

Flow to CL 2 & 3 [1-FI-63-91A (NR) NR or WR or 91B (WR)]

Flow to CL 1 & 4 [1-FI-63-92A (NR) NR or WR or 92B (WR)]

Pump A Discharge Press (1-PI-74-13)

Pump B Discharge Press (1-PI-74-26)

CCP Pump A amps (1-EI-62-108A)

Pump A amps (1-EI-62-104A)

Charging Flow (1-FI-62-93A)

Charging Header Press (1-PI-62-92A)

BIT flow (1-FI-63-170)

Page 19 of 25

WBN Transfer to Containment Sump ES-1.3 Unit 1 Rev. 0018 Appendix D (Page 2 of 7)

Monitoring for Containment Sump Blockage 1.0 INSTRUCTIONS (continued)

INDICATOR READING CIRCLE ONE SIP Pump A flow (1-FI-63-151)

Pump B flow (1-FI-63-20)

Pump A amps (1-EI-63-12A)

Pump B amps (1-EI-63-16A)

Pump A Discharge Press (1-PI-63-150)

Pump B Discharge Press (1-PI-63-19)

Containment Spray Pump A amps (1-EI-72-26A)

Pump A flow (1-FI-72-34)

Pump B amps (1-EI-72-12A)

Pump B flow (1-FI-72-13)

Page 20 of 25

WBN Transfer to Containment Sump ES-1.3 Unit 1 Rev. 0018 Appendix D (Page 3 of 7)

Monitoring for Containment Sump Blockage 1.0 INSTRUCTIONS (continued)

NOTE The following step records baseline readings after RHR spray has been initiated. If RHR spray is initiated the data recorded in Step 1.0B should be used in place of the RHR data previously recorded in Step 1.0A for monitoring for containment sump blockage.

B. IF RHR spray is placed in service, THEN RECORD the following parameters:

Date Time INDICATOR READING CIRCLE ONE RHR Pump A amps (1-EI-74-5A)

Pump B amps (1-EI-74-17A)

Pump flow to CL 2 & 3 NR or WR

[1-FI-63-91A (NR) or 91B (WR)]

Pump flow to CL 1 & 4 NR or WR

[1-FI-63-92A (NR) or 92B (WR)]

Pump A Discharge Press (1-PI-74-13)

Pump B Discharge Press (1-PI-74-26)

Page 21 of 25

WBN Transfer to Containment Sump ES-1.3 Unit 1 Rev. 0018 Appendix D (Page 4 of 7)

Monitoring for Containment Sump Blockage 1.0 INSTRUCTIONS (continued)

NOTE TSC assistance should be requested, if necessary, in evaluating the effect of RCS pressure raises on ECCS flow.

C. MONITOR for containment sump blockage:

1. CHECK for any of the following indications.

ECCS pump Flow / Amps/ Discharge Press RHR / CCP / SIP Erratic or gradually dropping (flow/amps/discharge press) (unexplained)

Containment Spray Flow / Amps CS Pump Erratic or gradually dropping

2. IF any indications of sump blockage are observed, THEN NOTIFY TSC to evaluate indications.

NOTE Containment sump level dropping indicates potential loss of sump inventory due to leakage or clogging of drain paths inside containment.

D. MONITOR containment sump level:

1. IF containment sump level is dropping, THEN NOTIFY TSC to evaluate the following.

a. Indications of dropping containment sump level,

b. Need for RWST refill.

Page 22 of 25

WBN Transfer to Containment Sump ES-1.3 Unit 1 Rev. 0018 Appendix D (Page 5 of 7)

Monitoring for Containment Sump Blockage 1.0 INSTRUCTIONS (continued)

NOTE Reducing Containment Spray flow and ECCS flow to single train operation may reduce the rate of debris accumulation on the sump screen and will reduce pressure drop across screens. Pumps should only be stopped in the following step if TSC approval has been obtained.

E. IF indications of sump blockage continue to worsen, THEN PERFORM the following:

1. IF both trains of Containment Spray running, THEN EVALUATE stopping one train of Containment Spray.

2. IF both trains of ECCS pumps running, THEN EVALUATE stopping ECCS pumps on one train.

3. INITIATE makeup to RWST:

• REFER TO SOI-62.02, Boron Concentration Control.

4. NOTIFY TSC to evaluate transferring water to RWST from the following,

• Spent fuel pit

• Holdup tank Page 23 of 25

WBN Transfer to Containment Sump ES-1.3 Unit 1 Rev. 0018 Appendix D (Page 6 of 7)

Monitoring for Containment Sump Blockage 1.0 INSTRUCTIONS (continued)

NOTE The following step records baseline readings after hot leg recirculation is established. If hot leg recirculation is initiated data recorded in Step 1.0F should be used in place of data previously recorded in Step 1.0A.

F. WHEN ES-1.4, Hot Leg Recirculation COMPLETE, THEN RECORD the following parameters:

Date Time INDICATOR READING CIRCLE ONE RCS Pressure (ICCM plasma display) 1-M-4 or 1-M-6 Containment Sump Level (1-LI-63-180 or 181) 180 or 181 RHR Pump A amps (1-EI-74-5A)

Pump B amps (1-EI-74-17A)

Flow to HL 1 & 3 (1-FI-63-173A)

Pump A Discharge Press (1-PI-74-13)

Pump B Discharge Press (1-PI-74-26)

CCP Pump A amps (1-EI-62-108A)

Pump A amps (1-EI-62-104A)

Charging Flow (1-FI-62-93A)

Charging Header Press (1-PI-62-92A)

BIT flow (1-FI-63-170)

Page 24 of 25

WBN Transfer to Containment Sump ES-1.3 Unit 1 Rev. 0018 Appendix D (Page 7 of 7)

Monitoring for Containment Sump Blockage 1.0 INSTRUCTIONS (continued)

INDICATOR READING CIRCLE ONE SIP Pump A flow (1-FI-63-151)

Pump B flow (1-FI-63-20)

Pump A amps (1-EI-63-12A)

Pump B amps (1-EI-63-16A)

Pump A Discharge Press (1-PI-63-150)

Pump B Discharge Press (1-PI-63-19)

Containment Spray Pump A amps (1-EI-72-26A)

Pump A flow (1-FI-72-34)

Pump B amps (1-EI-72-12A)

Pump B flow (1-FI-72-13)

Page 25 of 25

Watts Bar Nuclear Plant NRC EXAM 2013302 System JPM C

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C

NRC EXAM 2013-302 EVALUATION SHEET Task: Return N43 Power Range To Service.

Alternate Path: n/a Facility JPM #: 3-OT-JPMR108A, Modified. (Added DCS actions to restore N43 PRM, converted to standard JPM by removing transient after rods returned to auto).

Safety Function: 7

Title:

Instrumentation K/A 015 A4.02 Ability to manually operate and/or monitor in the control room: NIS indicators Rating(s): 3.9/3.9 CFR: 41.7 / 45.5 to 45.8 Evaluation Method: Simulator X In-Plant Classroom

References:

1-AOI-4, Nuclear Instrumentation Malfunctions, Rev. 0 1-SOI-98.01, Distributed Control System, Rev. 0 Task Number: RO-092-AOI-4-002

Title:

Respond to a failure of the power range nuclear instrumentation.

Task Standard: The applicant :

1.) Returns the following switches from the N43 position to the NORMAL.

a. DETECTOR CURRENT COMPARATOR switch for UPPER SECTION

b. DETECTOR CURRENT COMPARATOR switch for LOWER SECTION.

c. COMPARATOR CHANNEL DEFEAT 2.) Returns the following switches from the N43 position to the OPERATE position:

a. ROD STOP BYPASS,

b. POWER MISMATCH BYPASS.

3.) Performs actions of SOI-98.01, DISTRIBUTED CONTROL SYSTEM, to RESTORE 1LPY0920412R from BYPASS to NORMAL.

Validation Time: 18 minutes Time Critical: Yes No X

================================================================

Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

================================================================

COMMENTS Page 2 of 20

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C

NRC EXAM 2013-302 SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Right click on 307 and then select RESET.

3. Enter the password.

4. Select Yes on the INITIAL CONDITION RESET pop-up window.

5. Place simulator in RUN and acknowledge any alarms.

7. ENSURE N43 POWER RANGE is defeated on the DETECTOR CURRENT COMPARATOR, MISCELLANEOUS CONTROL AND INDICATION, and COMPARATOR AND RATE Sections of 1-M-13.

8. ENSURE LPY0920412R is BYPASSED (yellow BYP present) on the DCS BYPASSED TRANSMITTERS screen.

9. Place simulator in FREEZE until Examiner cue is given.

Page 3 of 20

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C

NRC EXAM 2013-302 READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. Unit at 100% RTP

2. PRM N43 failed during last shift.

3. PRM N43 has been defeated in the NIS racks.

4. 1LPY0920412R has been bypassed using the DCS terminal.

5. Work Control has notified the MCR that repairs to PRM N43 are complete and the instrument is ready to be returned to service.

6. You are the Operator at the Controls.

INITIATING CUES:

The Unit Supervisor has directed you to complete the return of PRM N43 and 1LPY0920412R to service.

Inform the Unit Supervisor when 1-AOI-4,Nuclear Instrumentation Malfunctions is complete.

Page 4 of 20

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT START TIME: _______

STEP 1: 16. WHEN PRM is to be restored, THEN: ___ SAT

b. PERFORM the appropriate attachment for returning PRM to ___ UNSAT service:

• REFER TO Attachment 1, Defeat N-41 PRM Function At NIS Rack, Step B.

• REFER TO Attachment 2, Defeat N-42 PRM Function At NIS Rack, Step B.

• REFER TO Attachment 3, Defeat N-43 PRM Function At NIS Rack, Step B.

• REFER TO Attachment 4, Defeat N-44 PRM Function At NIS Rack, Step B.

STANDARD:

Applicant selects Attachment 3, Defeat N-43 PRM Functions at NIS Rack, Step B to return PRM N43 to service.

COMMENTS:

Page 5 of 20

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT EXAMINER: The following actions are taken from 1-AOI-4, Nuclear Instrumentation Malfunctions, Attachment 3, Defeat N-43 PRM Functions At NIS Rack.

STEP 2: B. WHEN PRM is ready for return to service, THEN PERFORM CRITICAL the following Steps: STEP

1. PLACE DETECTOR CURRENT COMPARATOR switch for ___ SAT UPPER SECTION in NORMAL.

___ UNSAT STANDARD:

Detector Current Comparator Upper Section switch placed to NORMAL from the N43 position (Miscellaneous Control &

Indication Panel,1-IDWR-92-N50-G IV)

Step is critical for proper restoration of N43 upper power detector input to the current comparator.

COMMENTS:

STEP 3: B. WHEN PRM is ready for return to service, THEN PERFORM CRITICAL the following Steps: STEP

2. PLACE DETECTOR CURRENT COMPARATOR switch for ___ SAT LOWER SECTION in NORMAL.

___ UNSAT STANDARD:

Detector Current Comparator Lower Section switch placed to NORMAL from the N43 position (Miscellaneous Control &

Indication Panel, 1-IDWR-92-N50-G IV).

Step is critical for proper restoration of the N43 lower power detector input to current comparator.

COMMENTS:

Page 6 of 20

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT NOTE On the following step, annunciator window 68-C, N-43 OVERPOWER ROD STOP BYPASSED, will clear.

STEP 4: B. WHEN PRM is ready for return to service, THEN PERFORM CRITICAL the following Steps: STEP

3. PLACE ROD STOP BYPASS switch in OPERATE. ___ SAT STANDARD: ___ UNSAT Rod Stop Bypass switch is positioned from N43 to OPERATE (Miscellaneous Control & Indication Panel,1-IDWR-92-N50-G IV)

Step is critical for proper restoration to enable rod stop interlock protection from channel N43.

COMMENTS:

STEP 5: B. WHEN PRM is ready for return to service, THEN PERFORM CRITICAL the following Steps: STEP

4. PLACE POWER MISMATCH BYPASS switch in OPERATE. ___ SAT STANDARD: ___ UNSAT Power Mismatch Bypass switch is positioned from N43 to OPERATE (Miscellaneous Control & Indication Panel, 1-IDWR N50-G IV)

Step is critical to restore channel N43 input to high auctioneering circuit and power mismatch circuits.

COMMENTS:

Page 7 of 20

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT NOTE On the following step, annunciator window 82-E, NIS CHANNEL IN TEST, will clear.

STEP 6: B. WHEN PRM is ready for return to service, THEN PERFORM CRITICAL the following Steps: STEP

5. PLACE COMPARATOR CHANNEL DEFEAT switch in ___ SAT NORMAL.

___ UNSAT STANDARD:

Comparator Channel Defeat Switch is positioned to NORMAL from the N43 position (Comparator & Rate Panel, Comparator N37, 1-IDWR-92-N37 IV).

Step is critical to restore channel input to channel comparator alarm circuits.

COMMENTS:

NOTE On the following step, annunciator window 115-E, POWER RANGE FLUX RATE HI, will clear if the positive rate trip light is LIT.

Page 8 of 20

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 7: B. WHEN PRM is ready for return to service, THEN PERFORM ___ SAT the following Steps:

___ UNSAT

6. IF POSITIVE RATE TRIP is LIT, THEN RESET RATE MODE switch.

STANDARD:

Positive Rate Trip light on Power Range Upper N41A, 1-IDWR 42A II, is checked and determines light is NOT LIT and continues to next step.

COMMENTS:

STEP 8: B. WHEN PRM is ready for return to service, THEN PERFORM ___ SAT the following Steps:

___ UNSAT

7. ENSURE N-43 PRM channel RESTORED from Bypass in DCS per 1-SOI-98.01.

STANDARD:

Applicant locates 1-SOI-98.01, DISTRIBUTED CONTROL SYSTEM (DCS), Section 8.7, Restoring Instrument Loop After Auto or Manual Bypass.

COMMENTS:

Page 9 of 20

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT EXAMINER: The following actions are taken from 1-SOI-98.01, DISTRIBUTED CONTROL SYSTEM, Section 8.7, Restoring Instrument Loop After Auto or Manual Bypass.

NOTE This section is Continuous Use.

STEP 9: [1] RECORD instrument(s) to be RESTORED. Instrument ___ SAT UNID(s): _______________________

___ UNSAT STANDARD:

Applicant enters 1LPY0920412R as the instrument to be restored.

COMMENTS:

STEP 10: [2] NOTIFY SRO of instrument to be RESTORED. ___ SAT STANDARD: ___ UNSAT Applicant informs the Unit Supervisor/Examiner that 1LPY0920412R will be restored.

COMMENTS:

CAUTION Certain Eagle Rack failures will trip bistables, but freeze the inputs to DCS. DCS will NOT AUTO-BYPASS channels with this type of failure. The DCS input will be considered as good.

Page 10 of 20

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 11: [3] IF instrument has redundant channels on 1-XX-55-6B, ___ SAT RX Trip - Status Panel, THEN ENSURE bistable windows for redundant instrument channels on 1-XX- ___ UNSAT 55-6B, RX Trip - Status Panel are NOT LIT.

STANDARD:

Applicant determines that no bistable windows are lit on 1-XX 6B, RX Trip - Status Panel.

COMMENTS:

STEP 12: [4] IF any bistables associated with redundant channels ___ SAT are LIT, THEN

___ UNSAT

[4.1] NOTIFY Unit SRO of bistable conflict.

[4.2] DO NOT continue until bistable conflict has been RESOLVED.

STANDARD:

Applicant determines that this step is not applicable, and enters N/A for the step.

COMMENTS:

NOTE If both instrument channels of steam flow OR feedwater flow on a single loop are out of service AND a large change in flow has occurred, (for example, a startup at low power or a large power change) SG Level perturbations may be reduced, by manually forcing 1 ELEMENT CONTROL prior to restoring the BYPASSED channel.

Page 11 of 20

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 13: [5] IF reducing SG Level perturbations, THEN PERFORM ___ SAT Section 8.1 to FORCE 1 ELEMENT CONTROL.

___ UNSAT STANDARD:

Applicant determines that SG level perturbations are not occurring and enters N/A for the step.

COMMENTS:

STEP 14: [6] SELECT Display Screen for instrument loop to be ___ SAT RESTORED (Ref. App. A or use BYPASSED TRANSMITTERS screen). ___ UNSAT STANDARD:

Applicant selects BYPASSED TRANSMITTERS screen on the DCS computer terminal.

COMMENTS:

Page 12 of 20

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 15: [7] SELECT data point for instrument recorded in Step CRITICAL 8.7[1]. STEP STANDARD: ___ SAT Applicant selects 1LPY0920412R, which currently is displayed ___ UNSAT with a yellow BYPASSED tag.

Step is critical to restore the correct device to service.

COMMENTS:

STEP 16: [8] IF instrument is displayed with its MAINT BYP CRITICAL SIGNAL button indicating BYPASSED (red), THEN STEP

[8.1] SELECT MAINT BYP SIGNAL button for ___ SAT instrument loop.

___ UNSAT

[8.2] CHECK status color changes from red to gray.

STANDARD:

Applicant locates 1LPY0920412R MAINT BYP SIGNAL D button on the DCS screen and selects the button with the cursor, then clicks on the button.

Applicant observes the MAINT BYP SIGNAL D button change from RED to GRAY.

Step is critical to restore channel input to SG level program circuits.

COMMENTS:

Page 13 of 20

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 17: [9] SELECT RESTORE SIGNAL button. CRITICAL STEP STANDARD:

___ SAT Applicant locates the RESTORE SIGNAL D button, and selects the button with the cursor, then clicks on the button. ___ UNSAT Step is critical to restore channel input to SG level program circuits.

COMMENTS:

STEP 18: [10] CHECK yellow BYP is NOT displayed above ___ SAT associated instrument column to indicate instrument status change. ___ UNSAT STANDARD:

Applicant observes the yellow BYP indication no longer appears above 1LPY0900412R.

COMMENTS:

NOTE When instrument is BYPASSED, XMTR BYP will be displayed in yellow on the overlay screen for that instrument.

Page 14 of 20

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 19: [11] IF ALL FW (feedwater) instruments have been ___ SAT restored, THEN CHECK XMTR BYP is NOT displayed in yellow for the associated instrument ___ UNSAT (Ref. App A or use BYPASSED TRANSMITTERS screen).

STANDARD:

Applicant determines that there are NO bypassed transmitters indicated in yellow on the BYPASSED TRANSMITTERS screen.

COMMENTS:

STEP 20: [12] NOTIFY SRO that instrument is RESTORED. ___ SAT STANDARD: ___ UNSAT Applicant informs the Unit Supervisor that Power Range N43 has been restored.

COMMENTS:

Page 15 of 20

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 21: [13] IF action due to IM request, THEN NOTIFY IM ___ SAT instrument channel is RESTORED.

___ UNSAT STANDARD:

Applicant determines that step is not applicable, and marks the step N/A.

COMMENTS:

STEP 22: [14] MONITOR system parameters for effect of ___ SAT instrument restoration.

___ UNSAT STANDARD:

Applicant monitors SG 3 level for possible perturbations and determines that none are occurring.

COMMENTS:

STEP 23: [15] IF 1 ELEMENT CONTROL was forced in Step 8.7[5], ___ SAT THEN GO TO Step 8.1[10] to restore 3 ELEMENT CONTROL. . ___ UNSAT STANDARD:

Applicant determines that step is not applicable, and marks the step N/A.

COMMENTS:

Page 16 of 20

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT EXAMINER: The following actions are taken from 1-AOI-4, Nuclear Instrumentation Malfunctions, Section 3.4, STEP 24: 16. WHEN PRM is to be restored, THEN: ___ SAT

c. ENSURE TAVG and TREF within 1°F. ___ UNSAT STANDARD:

Applicant determines that TAVG and TREF are within 1°F COMMENTS:

STEP 25: 16. WHEN PRM is to be restored, THEN. ___ SAT

d. ENSURE zero demand on control rod position ___ UNSAT indication [1-M-4].

STANDARD:

Applicant determines that there is zero demand on CERPI MONITOR 1 or 2 PASSIVE SUMMER DEMAND INDICATORS, COMMENTS:

Page 17 of 20

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 26: 16. WHEN PRM is to be restored, THEN: ___ SAT

e. IF auto rod control desired, PLACE control rods in ___ UNSAT AUTO.

STANDARD:

Applicant locates 1-RBSS, ROD BANK SELECTOR and rotates the handswitch from the MAM position to the right to the AUTO position.

COMMENTS:

END OF TASK STOP TIME ________

Page 18 of 20

C Handout Package for Applicant

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

1. Unit at 100% RTP

2. PRM N43 failed during last shift.

3. PRM N43 has been defeated in the NIS racks.

4. 1LPY0920412R has been bypassed using the DCS terminal.

5. Work Control has notified the MCR that repairs to PRM N43 are complete and the instrument is ready to be returned to service.

6. You are the Operator at the Controls.

INITIATING CUES:

The Unit Supervisor has directed you to complete the return of PRM N43 and 1LPY0920412R to service.

Inform the Unit Supervisor when 1-AOI-4,Nuclear Instrumentation Malfunctions is complete.

C

Watts Bar Nuclear Plant Unit 1 Abnormal Operating Instruction 1-AOI-4 Nuclear Instrumentation Malfunctions Revision 0000 Quality Related Level of Use: Continuous Use Effective Date: 09-23-2012 Responsible Organization: OPS, Operations Prepared By: John Killian Approved By: Steven R Smith

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 Revision Log Revision Affected or Change Effective Page Number Date Numbers Description of Revision/Change 0 09/23/12 ALL Revision implements changes made by the Distributed Control System under DCN 52853.

Minor/editorial changes:

• Revision prepared using Rev 30 of AOI-4.

• Added Unit 1 designator to procedure number and reset revision to 0000.

• Updated procedures referenced in body of procedure to reflect Unit 1, Unit 2, and Common 0 designations, iaw ODM 23, in preparation for two unit operation.

• Standardized use of TAVG vs Tave and TREF.

• Updated performance references in Section 5.1.

• PCR #5921 split Attachment 1 into four Attachments in an effort to reduce potential errors when defeating PRM and RTS. One Attachment for each PRM.

• Re-defined discussion in Section 4.3 concerning PRM input to SG level setpoint.

Page 2 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 1.0 PURPOSE This Instruction provides instructions to respond to a loss of Source Range, Intermediate Range or Power Range NIS monitors.

2.0 SYMPTOMS 2.1 Alarms A. CHANNEL I SOURCE/INTERMEDIATE RANGE TROUBLE [81-A].

B. SOURCE RANGE HI FLUX AT SHUTDOWN [81-B].

C. CHANNEL II SOURCE/INTERMEDIATE RANGE TROUBLE [82-A].

D. INTERM RANGE HI FLUX ROD WD STOP [82-B].

E. POWER RANGE OVERPOWER ROD WD STOP [83-A].

F. POWER RANGE UPR DETECTOR FLUX DEVN [83-B].

G. POWER RANGE LWR DETECTOR FLUX DEVN [83-C].

H. PLANT COMPUTER GENERATED ALARM (SEE ICS) [83-D].

I. POWER RANGE CHANNEL DEVIATION [83-E].

J. DCS TROUBLE [82-F]

2.2 Indications A. Source Range Monitor (SRM) malfunction:

1. Audio count rate NOT operating.

2. Erratic or loss of indication.

3. INSTRUMENT POWER ON and/or CONTROL POWER ON lights at NIS racks DARK [1-M-13].

4. Both startup rate channels NOT indicating same startup rate.

5. NON-OPERATE light LIT [1-M-13].

Page 3 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 2.2 Indications (continued)

B. Intermediate Range Monitor (IRM) malfunction:

1. Erratic or loss of indication.

2. INSTRUMENT POWER ON and/or CONTROL POWER ON lights at NIS racks DARK [1-M-13].

3. Both startup rate channels NOT indicating same startup rate.

4. SRM does NOT energize during shutdown.

5. NON-OPERATE light LIT [1-M-13].

C. Power Range Monitor (PRM) malfunction:

1. Erratic or loss of indication.

2. Delta flux meter failed high, low, or giving erratic indications.

3. CONTROL POWER ON and/or INSTRUMENT POWER ON lights at NIS racks DARK [1-M-13].

2.3 Automatic Actions A. Source Range Monitor failure:

1. Possible source range monitor high flux Rx trip at 105 cps if SRM NOT blocked.

2. Possible Cntmt evacuation alarm at 0.5 decade above background.

B. Intermediate Range Monitor failure:

1. Intermediate range monitor 20% high flux rod stop (if NOT blocked above P-10).

2. Intermediate range monitor 25% high flux Rx trip (if NOT blocked above P-10).

3. Possible loss of P-6 block if intermediate range monitor greater than 1.66 X 10-4% power and intermediate range monitor fails low.

Page 4 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 2.3 Automatic Actions (continued)

C. Power Range Monitor failure:

1. Possible 103% power rod stop.

2. Possible actuation or loss of P-8, P-9, or P-10.

3. Temporary rod insertion if channel fails high with rods in AUTO.

Page 5 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 3.0 OPERATOR ACTIONS 3.1 Diagnostics IF GO TO PAGE Subsection Source Range Monitor malfunction 3.2 7 Intermediate Range Monitor malfunction 3.3 12 Power Range Monitor malfunction 3.4 14 Page 6 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 Step Action/Expected Response Response Not Obtained 3.2 Source Range Monitor (SRM) Failure

1. STOP positive reactivity changes or core alterations.

2. IF both SRMs required and failed, THEN OPEN Rx trip breakers

3. INITIATE performance of 1-SI-0-10, Shutdown Margin.

4. IF SOURCE RANGE HI FLUX AT SHUTDOWN alarm occurs [81-B],

THEN:

a. CHECK alarm valid. a. IF a spurious alarm occurs, THEN:

1) CHECK by other SRM that alarm was false.

2) ENSURE shutdown monitors reset [1-M-13].

3) ANNOUNCE false alarm over PA.

4) ** GO TO Step 5.

b. ENSURE Cntmt is evacuated.

c. CHECK Rx power STABLE. c. IF uncontrolled positive reactivity insertion, THEN

• • GO TO 1-AOI-34, Immediate Boration.

Page 7 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 Step Action/Expected Response Response Not Obtained 3.2 Source Range Monitor (SRM) Failure (continued)

NOTE Placing the affected channel in bypass will cause either window 64A or 65A to alarm.

5. PLACE failed channel LEVEL TRIP switch to BYPASS [1-M-13].

6. PLACE failed channel HIGH FLUX AT SHUTDOWN switch to BLOCK

[1-M-13].

7. ENSURE 1-NR-92-145 recording an operable source range channel

[1-M-4].

8. IF in MODE 2, THEN REFER TO the following TECH Specs.

• 3.3.1, Reactor Trip System Instrumentation

• 3.3.3, PAM Instruments

• 3.3.4, Remote Shutdown System Page 8 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 Step Action/Expected Response Response Not Obtained 3.2 Source Range Monitor (SRM) Failure (continued)

9. IF in MODE 3, 4, or 5, THEN:

• CHECK audio count rate audible

• PLACE audio count rate in control room. CHANNEL SELECTOR switch to operable channel [1-M-13].

• REFER TO the following Tech Specs:

• 3.3.1,Reactor Trip System Instrumentation,

• 3.3.3, PAM Instruments,

• 3.3.4, Remote Shutdown System.

10. IF in MODE 6, THEN:

• CHECK audio count rate audible

• IF audible audio count rate is NOT in control room. being received in the control room, THEN PLACE audio count rate CHANNEL SELECTOR switch to an operable channel [1-M-13].

• CHECK audio count rate audible IF audible audio count rate is NOT in Cntmt. being received in Cntmt, THEN:

a. TURN AMPLIFIER SELECT switch to A1 [1-M-13 switch on rear of amplifier].

b. CHECK an audible count rate in Cntmt.

• REFER TO Tech Spec 3.9.3, Nuclear Instrumentation.

Page 9 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 Step Action/Expected Response Response Not Obtained 3.2 Source Range Monitor (SRM) Failure (continued)

11. NOTIFY Operations Duty Manager and Rx Engineering of failed channel.

12. INITIATE repair of SRM.

13. DO NOT CONTINUE UNTIL SRM repair complete.

14. CHECK SRM operable:

• CHECK INSTRUMENT POWER ON and CONTROL POWER ON lights LIT at NIS racks [1-M-13].

• CHECK NON-OPERATE light DARK [1-M-13].

• CHECK audio count rate operating in control room for MODES 2 through 6.

• CHECK audio count rate operating in Cntmt for MODE 6.

• COMPARE channel output.

Page 10 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 Step Action/Expected Response Response Not Obtained 3.2 Source Range Monitor (SRM) Failure (continued)

15. IF shutdown monitor required, THEN:

a. RESET shutdown monitor:

1) ENSURE power switch on Shutdown Monitor is ON.

2) RESET the Alarm Setpoint with the black pushbutton to the right of the display.

3) RESET the Alarm with the black pushbutton to the right of the "alarm" light.

b. PLACE HIGH FLUX AT SHUTDOWN switch in NORMAL.

16. PLACE LEVEL TRIP switch in NORMAL [1-M-13].

17. IF refueling activities were stopped due to source range monitor problems, THEN OBTAIN Plant Manager approval prior to resuming refueling activities.

18. RETURN TO Instruction in effect.

End of Section Page 11 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 Step Action/Expected Response Response Not Obtained 3.3 Intermediate Range Monitor (IRM) Failure

1. IF greater than P-6 and less then P-10 with BOTH IRM channels failed, THEN STOP positive reactivity changes.

NOTE Placing the affected channel in bypass will cause either window 64B or 65B to alarm.

2. PLACE failed channel LEVEL TRIP switch to BYPASS [1-M-13].

3. ENSURE 1-NR-92-145 recording an operable IRM.

4. REFER TO Tech Spec 3.3.1, Rx Trip System Instrumentation and 3.3.3, PAM Instruments.

5. NOTIFY Operations Duty Manager and Rx Engineering of any failed channel.

6. INITIATE repair of IRM.

7. DO NOT CONTINUE UNTIL repairs are complete.

Page 12 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 Step Action/Expected Response Response Not Obtained 3.3 Intermediate Range Monitor (IRM) Failure (continued)

8. CHECK intermediate range monitor operable:

• CHECK INSTRUMENT POWER ON and CONTROL POWER ON lights LIT at NIS racks [1-M-13].

• CHECK NON-OPERATE light DARK [1-M-13].

• COMPARE channel output.

9. PLACE failed channel LEVEL TRIP switch in NORMAL [1-M-13].

10. RETURN TO Instruction in effect.

End of Section Page 13 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 Step Action/Expected Response Response Not Obtained 3.4 Power Range Monitor (PRM) Failure NOTE Steps 1and 2 are IMMEDIATE ACTION steps

1. PLACE control rods in MANUAL.

2. CHECK rod motion STOPPED. () TRIP Rx.

• • GO TO 1-E-0, Reactor Trip or Safety Injection.

3. CHECK S/G levels NORMAL ENSURE affected S/G level controls in Manual AND CONTROL S/G levels on program.

() IF S/G level RISING OR DROPPING uncontrolled, THEN TRIP reactor, and

• • GO TO 1-E-0, Reactor Trip or Safety Injection.

Page 14 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 Step Action/Expected Response Response Not Obtained 3.4 Power Range Monitor (PRM) Failure (continued)

NOTE Control rod withdrawal may NOT be possible if a PRM has failed high due to the 103% Rod Withdrawal Stop (C-2) until PRM is defeated. (Annunciator window 83-A).

4. MAINTAIN TAVG and TREF within 3°F.

5. DEFEAT failed PRM functions using the appropriate attachment:

• REFER TO Attachment 1, Defeat N-41 PRM Function At NIS Rack.

• REFER TO Attachment 2, Defeat N-42 PRM Function At NIS Rack.

• REFER TO Attachment 3, Defeat N-43 PRM Function At NIS Rack.

• REFER TO Attachment 4,Defeat N-44 PRM Function At NIS Rack.

6. ENSURE 1-NR-92-145 recording an operable PRM.

Page 15 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 Step Action/Expected Response Response Not Obtained 3.4 Power Range Monitor (PRM) Failure (continued)

NOTE Inputs to 1-TR-68-2A include power range monitor, pressurizer pressure, T and TAVG. Selection of an operable channel should consider other failures in addition to the failed power range monitor channel.

7. ENSURE 1-TR-68-2A placed to operable T/OTT/OPT channel using 1-XS-68-2B, T RCDR TR-68-2A LOOP SELECT [1-M-5].

8. INITIATE Repair on failed equipment.

CAUTION Allowing at least 5 minutes between any rod control input (i.e.,

TAVG, TREF, or NIS) changes and placing rods in AUTO, will help prevent undesired control rod movement.

9. WHEN AUTO rod control desired, THEN:

a. ENSURE TAVG and TREF within 1°F.

b. ENSURE zero demand on control rod position indication [1-M-4].

c. PLACE control rods in AUTO.

Page 16 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 Step Action/Expected Response Response Not Obtained 3.4 Power Range Monitor (PRM) Failure (continued)

10. NOTIFY Work Control to have IM trip failed channel bistables.

11. REFER TO Tech Specs:

• 3.3.1, Rx Trip System (RTS)

Instrumentation, table for minimum channels.

• 3.2.4, Quadrant Power Tilt Ratio (QPTR).

• SR 3.2.4.2 for loss of one channel may require performance of 1-SI-0-22, Incore QPTR.

CAUTION Power fuses should NOT be removed during the performance of IMI-160 until affected PRM channel is in DCS BYPASS.

12. WHEN notified bistables are tripped, CONTACT Work Control to have IMs THEN immediately troubleshoot the problem.

CHECK lights and alarms referenced in Appendix A are LIT.

13. NOTIFY Operations Duty Manager and Rx Engineering of failed channel.

14. DO NOT CONTINUE with this Instruction UNTIL failed PRM repair is completed.

15. CHECK failed channel trip status NOTIFY Work Control to have IM lights and associated alarms in troubleshoot problem.

Appendix A are CLEAR. ENSURE trip status lights DARK before continuing this Instruction.

Page 17 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 Step Action/Expected Response Response Not Obtained 3.4 Power Range Monitor (PRM) Failure (continued)

CAUTION Allowing at least 5 minutes between any rod control input (i.e., TAVG, TREF, or NIS) changes and placing rods in AUTO, will help prevent undesired control rod movement.

16. WHEN PRM is to be restored, THEN:

a. PLACE control rods in MANUAL.

b. PERFORM the appropriate attachment for returning PRM to service:

• REFER TO Attachment 1, Defeat N-41 PRM Function At NIS Rack, Step B.

• REFER TO Attachment 2, Defeat N-42 PRM Function At NIS Rack, Step B.

• REFER TO Attachment 3, Defeat N-43 PRM Function At NIS Rack, Step B.

• REFER TO Attachment 4, Defeat N-44 PRM Function At NIS Rack, Step B.

c. ENSURE TAVG and TREF within 1°F.

d. ENSURE zero demand on control rod position indication [1-M-4].

e. IF auto rod control desired, PLACE control rods in AUTO.

17. RETURN TO Instruction in effect.

End of Section Page 18 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 4.0 DISCUSSION 4.1 Source Range Failure SRM channels N131 & N132 are blocked manually above P-6. SRM channel indications are automatically removed above P-10. SRM channel failure may be evidenced by various alarms caused by loss of supply voltage, or the channel indicating high, low, and/or erratic. If one SRM channel fails high, Rx will trip at 105 cps unless the SRM trip is blocked. Audio count rate is required in Cntmt and in the Control Room when refueling operations are being conducted, and should be operating in the Control Room at all times when the source range channels are in service.

4.2 Intermediate Range Failure Malfunction of an IRM channel N135 or N136 may be evidenced by erratic or loss of indication, various alarms caused by loss of supply voltage, or by the channel indicating high, low, or erratic. One of two IRMs indicating greater than 25% power (and NOT blocked) will cause an Rx trip.

Page 19 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 4.3 Power Range Failure PRM channel malfunction may be evidenced by erratic or loss of indication, various alarms caused by loss of supply voltage, or the channel indicating high, low, or erratic. Greater than one PRM must fail high before Rx will trip on high flux.

DCS median signal selector will select the high-median value of the 4 PRM channels as NIS power to the S/G level setpoint for all four S/Gs. If two channels fail (one high and one low) the S/G level setpoint is defaulted to the Last Good Value (LGV).

The failure of one PRM to a value greater than 103% will result in an Auto/Manual Rod withdrawal block.

The rod control circuitry contains multiple lead/lag modules. Even with TAVG/TREF matched within 1 °F, rod movement could occur when the rods are returned to AUTO if rod control inputs change while rods were in MANUAL.

• Decay time for TAVG lead/lag modules is approximately 3 minutes.

• Decay time for TREF lead/lag modules and NIS lead/lag modules is approximately 5 minutes.

Allow at least 5 minutes between any change to rod control inputs (i.e., TAVG, TREF, or NIS) and placing rods in AUTO, this will help prevent undesired control rod movement.

Ensuring zero demand on the CERPI monitors in the main control room will also help prevent undesired control rod movement.

Page 20 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000

5.0 REFERENCES

5.1 Performance A. 1-E-0, Reactor Trip or Safety Injection.

B. 1-AOI-34, Immediate Boration.

C. 1-SI-0-10, Shutdown Margin.

D. 1-SI-0-22, Incore QPTR.

E. 1-SOI-98.01, Distributed Control System.

5.2 Developmental A. IMI-160.001, Removal of Reactor Protection System Channel I From Service.

B. IMI-160.002, Removal of Reactor Protection System Channel II From Service.

C. IMI-160.003, Removal of Reactor Protection System Channel III From Service.

D. IMI-160.004, Removal of Reactor Protection System Channel IV From Service.

5.3 Technical Specifications (Tech Specs)

A. 3.3.1, Reactor Trip System (RTS) Instrumentation.

B. 3.3.3 Post Accident Monitoring (PAM) Monitoring C. 3.3.4 Remote Shutdown System D. 3.2.4, Quadrant Power Tilt Ratio (QPTR), SR 3.2.4.2 for loss of one channel.

E. 3.9.3, Nuclear Instrumentation.

Page 21 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 Appendix A (Page 1 of 4)

Power Range Failure N41 Power Range Failure COMPARATOR R PANEL STATUS LIGHT ANNUNCIATOR TB-411C (overtemp R-2 [1-XX-55-5, window 10] [123-C]

delta t trip) LOOP 1 OTT TRIP OVERTEMP T TRIP TS-68-2D ALERT TB-411D (overtemp R-2 [1-XX-55-5, window 15] [123-D]

turb rbk & blk rod LOOP 1 OTT RUN OVERTEMP T withdrawal) BACK TS-68-2E TURB RUNBACK &

C-3 ROD BLOCK N/A 1-M-13 when [1-XX-55-5, window 7] [115-C]

fuses pulled PR FLUX HI NC41R POWER RANGE FLUX HI N/A 1-M-13 when [1-XX-55-5, window 8] [115-E]

fuses pulled PR HI RATE NC41U/K POWER RANGE FLUX RATE HI Page 22 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 Appendix A (Page 2 of 4)

Power Range Failure N42 Power Range Failure COMPARATOR R PANEL STATUS LIGHT ANNUNCIATOR TB-421C (overtemp R-6 [1-XX-55-5, window 30] [123-C]

delta t trip) LOOP 2 OTT TRIP OVERTEMP T TRIP TS-68-25D ALERT TB-421D (overtemp R-6 [1-XX-55-5, window 35] [123-D]

turb rbk & blk rod LOOP 2 OTT RUN OVERTEMP T withdrawal) BACK TS-68-25E TURB RUNBACK &

C-3 ROD BLOCK N/A 1-M-13 when [1-XX-55-5, window 27] [115-C]

fuses pulled PR FLUX HI NC42R POWER RANGE FLUX HI N/A 1-M-13 when [1-XX-55-5, window 28] [115-E]

fuses pulled PR HI RATE NC42U/K POWER RANGE FLUX RATE HI Page 23 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 Appendix A (Page 3 of 4)

Power Range Failure N43 Power Range Failure COMPARATOR R PANEL STATUS LIGHT ANNUNCIATOR TB-431C (overtemp R-10 [1-XX-55-5, window 50] [123-C]

delta t trip) LOOP 3 OTT TRIP OVERTEMP T TS-68-44D TRIP ALERT TB-431D (overtemp R-10 [1-XX-55-5, window 55] [123-D]

turb rbk & blk rod LOOP 3 OTT RUN BACK OVERTEMP T withdrawal) TS-68-44E TURB RUNBACK &

C-3 ROD BLOCK N/A 1-M-13 when [1-XX-55-5, window 47] [115-C]

fuses pulled PR FLUX HI NC43R POWER RANGE FLUX HI N/A 1-M-13 when [1-XX-55-5, window 48] [115-E]

fuses pulled PR HI RATE NC43U/K POWER RANGE FLUX RATE HI Page 24 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 Appendix A (Page 4 of 4)

Power Range Failure N44 Power Range Failure COMPARATOR R PANEL STATUS LIGHT ANNUNCIATOR TB-441C (overtemp R-13 [1-XX-55-5, window 70] [123-C]

delta t trip) LOOP 4 OTT TRIP OVERTEMP T TRIP TS-68-67D ALERT TB-441D (overtemp R-13 [1-XX-55-5, window 75] [123-D]

turb rbk & blk rod LOOP 4 OTT RUN OVERTEMP T withdrawal) BACK TS-68-67E TURB RUNBACK &

C-3 ROD BLOCK N/A 1-M-13 when [1-XX-55-5, window 67] [115-C]

fuses pulled PR FLUX HI NC44R POWER RANGE FLUX HI N/A 1-M-13 when [1-XX-55-5, window 68] [115-E]

fuses pulled PR HI RATE NC44U/K POWER RANGE FLUX RATE HI Page 25 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 Attachment 1 (Page 1 of 3)

Defeat N-41 PRM Function At NIS Rack 1.0 INSTRUCTIONS NOTE The following annunciators may be affected by defeating N-41 PRM channel:

• [66-C] N-41 OVERPOWER ROD STOP BYPASSED.

• [82-E] NIS CHANNEL IN TEST.

• [83-A] POWER RANGE OVERPOWER ROD WD STOP.

• [83-E] POWER RANGE CHANNEL DEVIATION.

• [115-C] POWER RANGE FLUX HI.

• [115-E] POWER RANGE FLUX RATE HI.

A. PERFORM the following steps for N-41 PRM:

1. PLACE DETECTOR CURRENT COMPARATOR switch for UPPER SECTION to PRN41.

2. PLACE DETECTOR CURRENT COMPARATOR switch for LOWER SECTION to PRN41.

NOTE On the following step, annunciator window 83-A, POWER RANGE OVERPOWER ROD WD STOP will clear (if channel failure was high) and window 66-C, N-41 OVERPOWER ROD STOP BYPASSED, will come into alarm.

3. PLACE ROD STOP BYPASS switch to BYPASS PR N41.

4. PLACE POWER MISMATCH BYPASS switch to BYPASS PR N41.

Page 26 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 Attachment 1 (Page 2 of 3)

Defeat N-41 PRM Function At NIS Rack 1.0 INSTRUCTIONS (continued)

NOTE On the following step, annunciator window 83-E, POWER RANGE CHANNEL DEVIATION, will clear and annunciator window 82-E, NIS CHANNEL IN TEST, will come into alarm.

5. PLACE COMPARATOR CHANNEL DEFEAT switch to N41.

NOTE On the following step, annunciator window 115-E, POWER RANGE FLUX RATE HI, will clear if the positive rate trip light is LIT.

6. IF POSITIVE RATE TRIP is LIT, THEN RESET RATE MODE switch.

7. PLACE N-41 in Maintenance Bypass using DCS Operator Display:

a. SELECT BYPASSED TRANSMITTERS" from the BOP MENU.

b. SELECT 1LPY0920412P.

c. SELECT MAINT BYP SIGNAL A for 1LPY0920412P.

d. CONFIRM MAINT BYP SIGNAL A changes from gray to red.

e. VERIFY yellow BYP displayed above column A.

Page 27 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 Attachment 1 (Page 3 of 3)

Defeat N-41 PRM Function At NIS Rack 1.0 INSTRUCTIONS (continued)

B. WHEN PRM is ready for return to service, THEN PERFORM the following Steps:

1. PLACE DETECTOR CURRENT COMPARATOR switch for UPPER SECTION in NORMAL.

2. PLACE DETECTOR CURRENT COMPARATOR switch for LOWER SECTION in NORMAL.

NOTE On the following step, annunciator window 66-C, N-41 OVERPOWER ROD STOP BYPASSED, will clear.

3. PLACE ROD STOP BYPASS switch in OPERATE.

4. PLACE POWER MISMATCH BYPASS switch in OPERATE.

NOTE On the following step, annunciator window 82-E, NIS CHANNEL IN TEST, will clear.

5. PLACE COMPARATOR CHANNEL DEFEAT switch in NORMAL.

NOTE On the following step, annunciator window 115-E, POWER RANGE FLUX RATE HI, will clear if the positive rate trip light is LIT.

6. IF POSITIVE RATE TRIP is LIT, THEN RESET RATE MODE switch. .

7. ENSURE N-41 PRM channel RESTORED from Bypass in DCS per 1-SOI-98.01.

Page 28 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 Attachment 2 (Page 1 of 3)

Defeat N-42 PRM Function At NIS Rack 1.0 INSTRUCTIONS NOTE The following annunciators may be affected by defeating N-42 PRM channel:

• [67-C] N-42 OVERPOWER ROD STOP BYPASSED.

• [82-E] NIS CHANNEL IN TEST.

• [83-A] POWER RANGE OVERPOWER ROD WD STOP.

• [83-E] POWER RANGE CHANNEL DEVIATION.

• [115-C] POWER RANGE FLUX HI.

• [115-E] POWER RANGE FLUX RATE HI.

A. PERFORM the following steps for N-42 PRM:

1. PLACE DETECTOR CURRENT COMPARATOR switch for UPPER SECTION to PRN42.

2. PLACE DETECTOR CURRENT COMPARATOR switch for LOWER SECTION to PRN42.

NOTE On the following step, annunciator window 83-A, POWER RANGE OVERPOWER ROD WD STOP will clear (if channel failure was high) and window 67-C, N-42 OVERPOWER ROD STOP BYPASSED, will come into alarm.

3. PLACE ROD STOP BYPASS switch to BYPASS PR N42.

4. PLACE POWER MISMATCH BYPASS switch to BYPASS PR N42.

Page 29 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 Attachment 2 (Page 2 of 3)

Defeat N-42 PRM Function At NIS Rack 1.0 INSTRUCTIONS (continued)

NOTE On the following step, annunciator window 83-E, POWER RANGE CHANNEL DEVIATION, will clear and annunciator window 82-E, NIS CHANNEL IN TEST, will come into alarm.

5. PLACE COMPARATOR CHANNEL DEFEAT switch to N42.

NOTE On the following step, annunciator window 115-E, POWER RANGE FLUX RATE HI, will clear if the positive rate trip light is LIT.

6. IF POSITIVE RATE TRIP is LIT, THEN RESET RATE MODE switch.

7. PLACE N-42 in Maintenance Bypass using DCS Operator Display:

a. SELECT BYPASSED TRANSMITTERS" from the BOP MENU.

b. SELECT 1LPY0920412Q.

c. SELECT MAINT BYP SIGNAL B for 1LPY0920412Q.

d. CONFIRM MAINT BYP SIGNAL B changes from gray to red.

e. VERIFY yellow BYP displayed above column B.

Page 30 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 Attachment 2 (Page 3 of 3)

Defeat N-42 PRM Function At NIS Rack 1.0 INSTRUCTIONS (continued)

B. WHEN PRM is ready for return to service, THEN PERFORM the following Steps:

1. PLACE DETECTOR CURRENT COMPARATOR switch for UPPER SECTION in NORMAL.

2. PLACE DETECTOR CURRENT COMPARATOR switch for LOWER SECTION in NORMAL.

NOTE On the following step, annunciator window, 67-C, N-42 OVERPOWER ROD STOP BYPASSED, will clear.

3. PLACE ROD STOP BYPASS switch in OPERATE.

4. PLACE POWER MISMATCH BYPASS switch in OPERATE.

NOTE On the following step, annunciator window 82-E, NIS CHANNEL IN TEST, will clear.

5. PLACE COMPARATOR CHANNEL DEFEAT switch in NORMAL.

NOTE On the following step, annunciator window 115-E, POWER RANGE FLUX RATE HI, will clear if the positive rate trip light is LIT.

6. IF POSITIVE RATE TRIP is LIT, THEN RESET RATE MODE switch.

7. ENSURE N-42 PRM channel RESTORED from Bypass in DCS per 1-SOI-98.01.

Page 31 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 Attachment 3 (Page 1 of 3)

Defeat N-43 PRM Function At NIS Rack 1.0 INSTRUCTIONS NOTE The following annunciators may be affected by defeating N-43 PRM channel:

• [68-C] N-43 OVERPOWER ROD STOP BYPASSED.

• [82-E] NIS CHANNEL IN TEST.

• [83-A] POWER RANGE OVERPOWER ROD WD STOP.

• [83-E] POWER RANGE CHANNEL DEVIATION.

• [115-C] POWER RANGE FLUX HI.

• [115-E] POWER RANGE FLUX RATE HI.

A. PERFORM the following steps for N-43 PRM:

1. PLACE DETECTOR CURRENT COMPARATOR switch for UPPER SECTION to PRN43.

2. PLACE DETECTOR CURRENT COMPARATOR switch for LOWER SECTION to PRN43.

NOTE On the following step, annunciator window 83-A, POWER RANGE OVERPOWER ROD WD STOP will clear (if channel failure was high) and window 68-C, N-43 OVERPOWER ROD STOP BYPASSED, will come into alarm.

3. PLACE ROD STOP BYPASS switch to BYPASS PR N43.

4. PLACE POWER MISMATCH BYPASS switch to BYPASS PR N43.

Page 32 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 Attachment 3 (Page 2 of 3)

Defeat N-43 PRM Function At NIS Rack 1.0 INSTRUCTIONS (continued)

NOTE On the following step, annunciator window 83-E, POWER RANGE CHANNEL DEVIATION, will clear and annunciator window 82-E, NIS CHANNEL IN TEST, will come into alarm.

5. PLACE COMPARATOR CHANNEL DEFEAT switch to N43.

NOTE On the following step, annunciator window 115-E, POWER RANGE FLUX RATE HI, will clear if the positive rate trip light is LIT.

6. IF POSITIVE RATE TRIP is LIT, THEN RESET RATE MODE switch.

7. PLACE N-43 in Maintenance Bypass using DCS Operator Display:

a. SELECT BYPASSED TRANSMITTER" from the BOP MENU.

b. SELECT 1LPY0920412R.

c. SELECT MAINT BYP SIGNAL D for 1LPY0920412R.

d. CONFIRM MAINT BYP SIGNAL D changes from gray to red.

e. VERIFY yellow BYP displayed above column D.

Page 33 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 Attachment 3 (Page 3 of 3)

Defeat N-43 PRM Function At NIS Rack 1.0 INSTRUCTIONS (continued)

B. WHEN PRM is ready for return to service, THEN PERFORM the following Steps:

1. PLACE DETECTOR CURRENT COMPARATOR switch for UPPER SECTION in NORMAL.

2. PLACE DETECTOR CURRENT COMPARATOR switch for LOWER SECTION in NORMAL.

NOTE On the following step, annunciator window 68-C, N-43 OVERPOWER ROD STOP BYPASSED, will clear.

3. PLACE ROD STOP BYPASS switch in OPERATE.

4. PLACE POWER MISMATCH BYPASS switch in OPERATE.

NOTE On the following step, annunciator window 82-E, NIS CHANNEL IN TEST, will clear.

5. PLACE COMPARATOR CHANNEL DEFEAT switch in NORMAL.

NOTE On the following step, annunciator window 115-E, POWER RANGE FLUX RATE HI, will clear if the positive rate trip light is LIT.

6. IF POSITIVE RATE TRIP is LIT, THEN RESET RATE MODE switch.

7. ENSURE N-43 PRM channel RESTORED from Bypass in DCS per 1-SOI-98.01.

Page 34 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 Attachment 4 (Page 1 of 3)

Defeat N-44 PRM Function At NIS Rack 1.0 INSTRUCTIONS NOTE The following annunciators may be affected by defeating N-44 PRM channel:

• [69-C] N-44 OVERPOWER ROD STOP BYPASSED.

• [82-E] NIS CHANNEL IN TEST.

• [83-A] POWER RANGE OVERPOWER ROD WD STOP.

• [83-E] POWER RANGE CHANNEL DEVIATION.

• [115-C] POWER RANGE FLUX HI.

• [115-E] POWER RANGE FLUX RATE HI.

A. PERFORM the following steps for N-44 PRM:

1. PLACE DETECTOR CURRENT COMPARATOR switch for UPPER SECTION to PRN44.

2. PLACE DETECTOR CURRENT COMPARATOR switch for LOWER SECTION to PRN44.

NOTE On the following step, annunciator window 83-A, POWER RANGE OVERPOWER ROD WD STOP will clear (if channel failure was high) and window 69-C, N-44 OVERPOWER ROD STOP BYPASSED, will come into alarm.

3. PLACE ROD STOP BYPASS switch to BYPASS PR N44.

4. PLACE POWER MISMATCH BYPASS switch to BYPASS PR N44.

Page 35 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 Attachment 4 (Page 2 of 3)

Defeat N-44 PRM Function At NIS Rack 1.0 INSTRUCTIONS (continued)

NOTE On the following step, annunciator window 83-E, POWER RANGE CHANNEL DEVIATION, will clear and annunciator window 82-E, NIS CHANNEL IN TEST, will come into alarm.

5. PLACE COMPARATOR CHANNEL DEFEAT switch to N44.

NOTE On the following step, annunciator window 115-E, POWER RANGE FLUX RATE HI, will clear if the positive rate trip light is LIT.

6. IF POSITIVE RATE TRIP is LIT, THEN RESET RATE MODE switch.

7. PLACE N-44 in Maintenance Bypass using DCS Operator Display:

a. SELECT BYPASSED TRANSMITTER" from the BOP MENU.

b. SELECT 1LPY0920412S.

c. SELECT MAINT BYP SIGNAL E for 1LPY0920412S.

d. CONFIRM MAINT BYP SIGNAL E changes from gray to red.

e. VERIFY yellow BYP displayed above column E.

Page 36 of 37

WBN Nuclear Instrumentation Malfunctions 1-AOI-4 Unit 1 Rev. 0000 Attachment 4 (Page 3 of 3)

Defeat N-44 PRM Function At NIS Rack 1.0 INSTRUCTIONS (continued)

B. WHEN PRM is ready for return to service, THEN PERFORM the following Steps:

1. PLACE DETECTOR CURRENT COMPARATOR switch for UPPER SECTION in NORMAL.

2. PLACE DETECTOR CURRENT COMPARATOR switch for LOWER SECTION in NORMAL.

NOTE On the following step, annunciator window 69-C, N-44 OVERPOWER ROD STOP BYPASSED, will clear.

3. PLACE ROD STOP BYPASS switch in OPERATE.

4. PLACE POWER MISMATCH BYPASS switch in OPERATE.

NOTE On the following step, annunciator window 82-E, NIS CHANNEL IN TEST, will clear.

5. PLACE COMPARATOR CHANNEL DEFEAT switch in NORMAL.

NOTE On the following step, annunciator window 115-E, POWER RANGE FLUX RATE HI, will clear if the positive rate trip light is LIT.

6. IF POSITIVE RATE TRIP is LIT, THEN RESET RATE MODE switch.

7. ENSURE N-44 PRM channel RESTORED from Bypass in DCS per 1-SOI-98.01.

Page 37 of 37

Watts Bar Nuclear Plant NRC EXAM 2013302 System JPM D

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D

NRC EXAM 2013-302 EVALUATION SHEET Task: Establish Manual Makeup to the VCT.

Alternate Path: When manual makeup is begun, 1-FCV-62-140, BA TO BLENDER and 1-FCV-62-128, MAKEUP TO VCT INLET or 1-FCV-62-144, MAKEUP TO VCT OUTLET fail open and cannot be closed. 1-FC-62-139, BA TO BLENDER FCV-62-140 CONTROL fails, causing boric acid flow rate to go to maximum.

Requires stopping of the boric acid transfer pumps to terminate the boration.

Facility JPM #: 3-OT-JPMR050A (Modified to add Alternate Path.)

Safety Function: 2

Title:

Inventory Control K/A 004 A1.12 Ability to manually operate and/or monitor in the control room:

Boration/dilution batch control.

Rating(s): 3.8/3.3 CFR: 41/7 / 45.5 to 45.8 Evaluation Method: Simulator X In-Plant Classroom

References:

SOI-62.02, Boron Concentration Control, Rev. 56.

AOI-3, Malfunction of Reactor Makeup Control, Rev. 29.

Task Number: RO-062-SOI-62-017

Title:

Perform manual makeup to the Volume Control Tank.

Task Standard: The applicant 1.) Aligns the makeup control system to perform a MANUAL makeup of 97 gallons, and raises VCT level from 35% to approximately 40%.

2.) After the controls fail, terminates the boration by placing 1-HS-62-230A BA PMP A and 1-HS-62-232A BA PMP B in the STOP position per AOI-3.

Validation Time: 20 minutes Time Critical: Yes No X

============================================================

Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

==============================================================

=

COMMENTS Page 2 of 14

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D

NRC EXAM 2013-302 SIMULATOR OPERATOR INSTRUCTIONS:

6

1. ENSURE NRC Examination Security has been established.

2. RESET to Initial Condition 308 by performing the following actions:

a. Select ICManager on the THUNDERBAR menu (right hand side of Instructor Console Screen).

b. Locate IC 308.

c. Right click on IC 308.

d. Select Reset on the drop down menu.

e. Right click on RESET.

f. Enter the password for IC 308.

g. Select Yes on the INITIAL CONDITION RESET pop-up window.

h. Perform SWITCH CHECK.

3. ENSURE the following information appears on the Director Summary Screen:

Key Type Event Delay Inserted Ramp Initial Final Value hs-62-140b hs-62-140b cvcs makeup mode selector sw O 00:00:00 00:00:00 00:00:00 man altdil hs-62-128 hs-62-128 boric acid blender to vct inlet sw O 29 00:00:00 00:00:00 open auto hs-62-140d hs-62-140d boric acid to blender flow control sw O 30 00:00:00 00:00:00 open auto hs-62-130 26070 boric acid flow to blender O 30 00:00:00 00:00:00 4 0 hs-62-144 hs-62-144makeup injection valve control sw O 28 00:00:00 00:00:00 open auto

4. ENSURE Events 28, 29 and 30 are loaded. [(Event 28: cvfcv62144>0) (Event 29: cvfcv62128>0)

(Event 30: cvfcv62128>0 cvfcv62144>0)]

5. Place simulator in RUN and acknowledge any alarms. ENSURE VCT level is 35% on 1-LI-62-129A, VCT LEVEL.

6. ENSURE copies of SOI-62.02, Boron Concentration Control, Section 6.5, Manual Makeup and REACTW data sheets for the VCT level change are available to the Examiner.

7. ENSURE Extra Operator is present in the simulator.

8. Place simulator in FREEZE until Examiner cue is given.

Page 3 of 14

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D

NRC EXAM 2013-302 READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. The Unit is at 100% RTP.

2. Auto Make-up from the Blender is out-of-service.

3. The STA has completed Appendix C, Calculation Of Boric Acid And Primary Water Integrator Setting For Manual Makeup, using REACTW to raise level from 35% to 40%.

INITIATING CUES:

The Unit Supervisor directs you to increase VCT level from 35% to 40%, using the Appendix C/REACTW data provided.

Notify the Unit Supervisor when the level increase has been completed.

Page4 of 14

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT START TIME: _______

CAUTION When maintaining VCT level using Manual, level must be monitored closely to avoid charging pump suction auto swap over to RWST.

NOTES

1) Manual is used when auto makeup is unavailable or if desired due to special operating conditions. As RCS CB is changed during load follow, the Manual blended solution setpoints must be adjusted. Controls are on 1-M-6.

2) RCS CB may be slightly changed during blended makeup because of the inaccuracy in flow controller settings. When this occurs, small RCS temperature changes will be seen and control rod adjustments may be required to compensate for the temperature change.

3) If batching to the VCT, use several small batches, (rather than one large batch) to allow time to evaluate possible reactivity effects between batches. A maximum batch of 100 gallons at a time is allowed EXAMINER: Ensure that the applicant has been provided the REACTW sheet for the level increase to 27%.

STEP 1: [1] PERFORM Appendix C, Calculation Of Boric Acid And ___ SAT Primary Water Integrator Setting For Manual Makeup OR ___ UNSAT USE Appendix B for Blending at greater than 2500 ppm.

STANDARD:

Applicant determines that Appendix C is complete based on INITIAL CONDITION C and utilizes the REACTW printout provided.

COMMENTS:

Page5 of 14

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 2: [2] PLACE controllers in MANUAL, AND CLOSE the following: ___ SAT

[2.1] 1-FC-62-139, BA TO BLENDER. ___ UNSAT

[2.2] 1-FC-62-142, PW TO BLENDER.

STANDARD:

Applicant locates 1-FC-62-139, BA TO BLENDER and moves the toggle switch from the AUTO (down, mid-position) to the MANUAL (up, in the slot) position.

Applicant locates 1-FC-62-142, PW TO BLENDER and moves the toggle switch from the AUTO (down, mid-position) to the MANUAL (up, in the slot) position.

COMMENTS:

Page6 of 14

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 3: [3] ADJUST Batch Counters for the desired quantity of boric acid ___ SAT and primary water using values from Appendix B or C: ___ UNSAT

[3.1] 1-FQ-62-139, BA BATCH COUNTER.

[3.2] 1-FQ-62-142, PW BATCH COUNTER.

STANDARD:

The applicant locates 1-FQ-62-139 BA BATCH COUNTER, and performs the following actions:

1. Depresses and holds the black pushbutton.

2. While holding the pushbutton, the applicant raises the red translucent cover.

3. While still holding the pushbutton, the applicant enters 000012 in the display.

4. While still holding the pushbutton, the applicant lowers the red translucent cover, and then releases the pushbutton.

5. Observes the value displayed after the red translucent cover is lowered remained at 000012.

The applicant locates 1-FQ-62-142, PW BATCH COUNTER. and performs the following actions:

1. Depresses and holds the black pushbutton.

2. While holding the pushbutton, the applicant raises the red translucent cover.

3. While still holding the pushbutton, the applicant enters 000085 in the display.

4. While still holding the pushbutton, the applicant lowers the red translucent cover, and then releases the pushbutton.

5. Observes the value displayed after the red translucent cover is lowered remained at 000085.

COMMENTS:

Page7 of 14

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 4: [4] PLACE 1-HS-62-140B, VCT MAKEUP MODE, in MAN. ___ SAT STANDARD: ___ UNSAT Applicant locates 1-HS-62-140B, VCT MAKEUP MODE, and determines that the handswitch is in the MAN position.

COMMENTS:

STEP 5: [5] TURN 1-HS-62-140A, VCT MAKEUP CONTROL, to START, CRITICAL

[5.1] CHECK Red light is LIT. STEP STANDARD: ___ SAT Applicant locates 1-HS-62-140A, VCT MAKEUP CONTROL and rotates ___ UNSAT the handswitch to the right to the START position.

The applicant observes the GREEN light is DARK and the RED light is LIT.

Step is critical since this action is required to initiate manual makeup.

COMMENTS:

NOTE When blending to VCT through 1-FCV-62-128, Chemistry cannot get a representative sample of the blender outlet.

EXAMINER: When the applicant opens either 1-HS-62-128, MAKEUP TO VCT INLET or 1-HS-62-144, MAKEUP TO VCT OUTLET, the selected valve will fail open; 1-FCV 140D, BA TO BLENDER will fail OPEN; and 1-FC-62-139, BA TO BLENDER FCV-62-140 CONTROL will fail.

This combination of malfunctions will require the applicant to stop the boric acid pumps to terminate the boration.

Page8 of 14

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 6: [6] IF Borating OR Blending, THEN PERFORM the following: CRITICAL

[6.1] OPEN 1-FCV-62-128, MAKEUP TO VCT INLET, OR STEP 1-FCV-62-144, MAKEUP TO VCT OUTLET. ___ SAT STANDARD: ___ UNSAT The applicant locates 1-FCV-62-128, MAKEUP TO VCT INLET, and rotates the handswitch from the P AUTO position to the OPEN position OR The applicant locates 1-FCV-62-144, MAKEUP TO VCT OUTLET., and rotates the handswitch from the P AUTO position to the OPEN position Step is critical since this establishes a flow path to fill the VCT.

CUE: If asked by applicant which makeup path to use, ask applicant which one they would recommend. When the applicant chooses, then state that the Unit Supervisor agrees with the path recommended.

COMMENTS:

EXAMINER: The applicant may stop the boric acid transfer pumps prior to entry into AOI-3, Malfunction of Reactor Makeup Controls.

TI-12.04, User's Guide For Abnormal And Emergency Operating Instructions, states Operators are expected to take manual control of equipment that is not responding properly in Auto due to equipment malfunction.

If the applicant exercises this path, go to JPM STEP 13.

EXAMINER: The following actions are taken from AOI-3, Malfunction of Reactor Makeup Controls.

Page9 of 14

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 7: 1. ENSURE 1-FCV-62-138, Emerg Borate, CLOSED. ___ SAT STANDARD: ___ UNSAT Applicant locates and determines that 1-FCV-62-138, Emerg Borate, is CLOSED by observing the GREEN light LIT, RED light DARK on 1-HS-62-138 EMERG BORATE.

COMMENTS:

STEP 8: 2. CHECK 1-FI-62-137A, Emerg Borate Flow, ZERO. ___ SAT STANDARD: ___ UNSAT Applicant locates and observes zero flow on 1-FI-62-137A, EMER BORATE FLOW.

COMMENTS:

STEP 9: 3. CHECK VCT level greater than 20%: ___ SAT

• 1-LI-62-129A. ___ UNSAT STANDARD:

Applicant locates and observes VCT level approximately 27% on 1-LI-62-129A, VCT LEVEL.

COMMENTS:

Page10 of 14

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 10: 4. CHECK VCT aligned to charging pump suction: ___ SAT

• 1-LCV-62-132 OPEN. ___ UNSAT

• 1-LCV-62-133 OPEN.

• 1-LCV-62-135 CLOSED.

• 1-LCV-62-136 CLOSED.

STANDARD:

Applicant locates and observes zero flow on 1-FI-62-137A, EMER BORATE FLOW.

COMMENTS:

STEP 11: 5. CHECK 1-FI-62-139, BA To Blender Flow, ZERO. ___ SAT STANDARD: ___ UNSAT Applicant locates and observes zero flow on 1-FI-62-137A, EMER BORATE FLOW.

COMMENTS:

STEP 12: 6. ENSURE 1-FCV-62-140, Boric Acid To Blender, CLOSED. ___ SAT STANDARD: ___ UNSAT Applicant locates and determines that 1-HS-62-140D, BA TO BLENDER is OPEN by the RED light LIT and GREEN light DARK.

COMMENTS:

Page11 of 14

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 13: [6] RESPONSE NOT OBTAINED CRITICAL STOP boric acid transfer pumps. STEP

___ SAT STANDARD:

Applicant locates 1-HS-62-230A BA PMP A and rotates the handswitch to the LEFT to the STOP position. Applicant observes GREEN light LIT ___ UNSAT and RED light DARK. Applicant may place the STOP-PULL-TO-LOCK position.

Applicant locates 1-HS-62-232A BA PMP B and rotates the handswitch to the LEFT to the STOP position. Applicant observes GREEN light LIT and RED light DARK. Applicant may place the STOP-PULL-TO-LOCK position.

Step is critical since this terminates the uncontrolled boration in progress.

Cue: When the applicant has stopped the boric acid transfer pumps, state another operator will continue from this point.

COMMENTS:

END OF TASK STOP TIME ________

Page12 of 14

D Handout Package for Applicant

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

1. The Unit is at 100% RTP.

2. Auto Make-up from the Blender is out-of-service.

3. The STA has completed Appendix C, Calculation Of Boric Acid And Primary Water Integrator Setting For Manual Makeup, using REACTW to raise level from 35% to 40%.

INITIATING CUES:

The Unit Supervisor directs you to increase VCT level from 35% to 40%, using the Appendix C/REACTW data provided.

Notify the Unit Supervisor when the level increase has been completed.

D

Watts Bar Nuclear Plant NRC EXAM 2013302 System JPM E

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E

NRC EXAM 2013-302 Task: Transfer 6.9 KV RCP Board 1A from Alternate to Normal.

Alternate Path: n/a Facility JPM #: 3-OT-JPMR042.

Safety Function: 6

Title:

Electrical K/A 062 A4.01 Ability to manually operate and/or monitor in the control room: All breakers (including available switchyard).

Rating(s): 3.3 / 3.1 CFR: 41.4/45.5 to 45.8 Preferred Evaluation Location: Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate

References:

SOI-202.01, 6.9KV Reactor Coolant Pump Board 1A, Rev. 8.

Task Number: RO-202-SOI-202-002

Title:

Transfer the 6.9 KV Reactor Coolant Board from Alternate to Normal Task Standard: The applicant performs actions in accordance with SOI-202.01 Section 8.1 to transfer 1A RCP Board from its ALTERNATE to NORMAL power supply and restore the RCP control switches to a normal alignment.

Validation Time: 10 minutes Time Critical: Yes No X

==========================================================

Applicant: ___________________________ _________________ Time Start: ________

NAME SSN Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

============================================================

COMMENTS Page 2 of 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E

NRC EXAM 2013-302 SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. RESET to Initial Condition 309 by performing the following actions:

a. Select ICManager on the THUNDERBAR menu (right hand side of Instructor Console Screen).

b. Locate IC# 309.

c. Right click on IC# 309.

d. Select Reset on the drop down menu.

e. Right click on RESET.

f. Enter the password for IC# 309.

g. Select Yes on the INITIAL CONDITION RESET pop-up window.

h. Perform SWITCH CHECK.

3. Place simulator in RUN and acknowledge any alarms.

4. Place simulator in FREEZE until Examiner cue is given.

5. Have copies of SOI-202.01 with all of Section 4.0 signed off and the SRO approval signed off in Section 8.1, step 1 available for each applicant.

Page 3 of 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E

NRC EXAM 2013-302 DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

1. A unit startup is in progress.

2. The 6.9 KV 6.9 KV Reactor Coolant Pump Boards are being transferred per GO-3, Unit Startup from Less than 4% Reactor Power to 30% Reactor Power, Section 5.4, Step [19.4].

3. You are the Operator-at-the Controls.

INITIATING CUES:

The Unit Supervisor has directed you to transfer 6.9 KV Reactor Coolant Pump Board 1A from ALTERNATE to NORMAL and to restore the controls to a normal alignment in accordance with SOI-202.01, 6.9KV Reactor Coolant Pump Board 1A.

Notify the Unit Supervisor when 6.9 KV Reactor Coolant Pump Board 1A has been transferred to NORMAL and the controls have been restored to normal alignment.

Page 4 of 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT START TIME: _______

STEP 1: [1] OBTAIN SRO approval. ___ SAT STANDARD:

Applicant observes that SRO approval has already been granted by ___ UNSAT initials in Step 1.

COMMENTS:

STEP 2. [2] ENSURE MSB has verified Time Delay Relay (TDR) 1 ___ SAT 068- 0009 contact points 1 and 5 closed (located on left side panel in compartment 1A2 of RCP BD 1A).

___ UNSAT STANDARD:

Applicant ensures that the MSB has verified Time Delay Relay (TDR) 1-62-068- 0009 contact points 1 and 5 closed.

CUE: When contacted as MSB, state that Time Delay Relay (TDR) 1-62-068- 0009 contact points 1 and 5 have been verified closed.

COMMENTS:

NOTE IF Unit is out of service, Bd may be energized by backfeeding from USSTs.

Page 5 of 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 3: [3] CHECK voltage 6560 to 7260V to Normal ACB 2112 on ___ SAT 1-EI-57-57, USST 1A VOLTS [1-M-1].

STANDARD: ___ UNSAT Applicant reads voltage approximately 7200V to Normal ACB 2112 on 1-EI-57-57, USST 1A VOLTS, on Panel 1-M-1.

COMMENTS:

STEP 4: [4] ENSURE 1-HS-68-8AA, RCP 1 NORMAL BKR & LIFT CRITICAL PMP[1-M-5], PUSHED IN to place handswitch in control of STEP ACB 2112. ___ SAT STANDARD: ___ UNSAT Applicant locates 1-HS-68-8AA, RCP 1 NORMAL BKR & LIFT PMP

[1-M-5] and pushes the handswitch in on Panel 1-M-5.

Step is critical to transfer the RCP motor power supply from its ALTERNATE feed breaker to its NORMAL feed breaker.

COMMENTS:

STEP 5: [5] ENSURE 1-HS-68-8BA, RCP 1 ALTERNATE BKR & CRITICAL XFER SELECTOR [1-M-5], PUSHED IN to place ACB STEP 2522 auto transfer in MANUAL. ___ SAT STANDARD: ___ UNSAT Applicant locates 1-HS-68-8BA, RCP 1 ALTERNATE BKR & XFER SELECTOR and pushes the handswitch in on Panel 1-M-5.

Step is critical to transfer the RCP motor power supply from its ALTERNATE feed breaker to its NORMAL feed breaker.

COMMENTS:

Page 6 of 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 6: [6] MONITOR 1-EI-68-8A, RCP 1 AMPS [1-M-5] during ___ SAT transfer to ensure RCP Amp load transfers to Normal ___ UNSAT supply.

STANDARD:

Applicant locates 1-EI-68-8A, RCP 1 AMPS and observes approximately 440 amps.

COMMENTS:

CAUTION Release handswitches SLOWLY after transfer is complete to prevent inadvertent breaker actuation.

STEP 7: Start of Critical Step(s) CRITICAL

[7] PLACE AND HOLD 1-HS-68-8AA, RCP 1 NORMAL BKR STEP

& LIFT PMP, in START, AND PLACE 1-HS-68-8BA, RCP ___ SAT 1 ALTERNATE BKR & XFER SELECTOR, in STOP. ___ UNSAT End of Critical Step(s)

STANDARD:

___Applicant acknowledges that this is a two-handed evolution. Applicant reads step, locates each handswitch, and then places and holds 1-HS-68-8AA, RCP 1 NORMAL BKR in START. While holding 1-HS-68-8AA in START, the applicant places 1-HS-68-8BA in STOP.

Critical step annotation is part of the actual plant procedure.

Step is critical to transfer the RCP motor power supply from its ALTERNATE feed breaker to its NORMAL feed breaker.

COMMENTS:

Page 7 of 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 8: [8] ENSURE Normal ACB 2112 CLOSED, and Alt ACB 2522 ___ SAT OPEN.

___ UNSAT STANDARD:

Applicant determines from the handswitches that the Normal ACB 2112 is CLOSED, and Alternate ACB 2522 is OPEN.

COMMENTS:

STEP 9: [9] IF desired to place Board Transfer in AUTO, THEN PULL ___ SAT 1-HS-68-8BA, RCP 1 ALTERNATE BKR & XFER SELECTOR switch, out to PULL AUTO.

___ UNSAT STANDARD:

Applicant locates 1-HS-68-8BA, RCP 1 ALTERNATE BKR & XFER SELECTOR and pulls the handswitch out to PULL AUTO position.

COMMENTS:

End of JPM STOP TIME ________

Page 8 of 10

E Handout Package for Applicant Page 9 of 10

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

1. A unit startup is in progress.

2. The 6.9 KV boards are being transferred per GO-3, Unit Startup from Less than 4% Reactor Power to 30% Reactor Power, Section 5.4, Step

[19.4].

3. You are the Operator-at-the Controls.

INITIATING CUES:

The Unit Supervisor has directed you to transfer 6.9 KV Reactor Coolant Pump Board 1A from ALTERNATE to NORMAL and to restore the controls to a normal alignment in accordance with SOI-202.01 6.9KV Reactor Coolant Pump Board 1A.

Notify the Unit Supervisor when 6.9 KV Reactor Coolant Pump Board 1A has been transferred to NORMAL and the controls have been restored to normal alignment.

E

Watts Bar Nuclear Plant NRC Exam 2013302 System JPM F

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F

NRC Exam 2013-302 EVALUATION SHEET Task: ALIGN 1B-B CCS PUMP TO SUPPLY HEADER 1B.

Alternate Path: n/a Facility JPM #: 3-OT-JPMR124 Safety Function: 8

Title:

Plant Service Systems K/A 026 AA2.03 Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: The valve lineups necessary to restart the CCWS while bypassing the portion of the system causing the abnormal condition.

Rating(s): 2.6/2.9 CFR: 43.5 / 45.13 Evaluation Method: Simulator X In-Plant Classroom

References:

SOI-70.01, Component Cooling Water (CCS) System, Rev 79.

Task Number: RO-070-SOI-70-005

Title:

Align Component Cooling Water system pump 1B-B in service to train 1B supply header.

Task Standard: The applicant:

1.) Performs valve manipulations to align CCS Pump 1B-B to the 1B Supply header.

2.) Performs actions required to start CCS Pump 1B-B.

Validation Time: 18 minutes Time Critical: Yes No X

============================================================

Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

==============================================================

COMMENTS Page 2 of 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F

NRC Exam 2013-302 SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. RESET to Initial Condition 310 by performing the following actions:

a. Select ICManager on the THUNDERBAR menu (right hand side of Instructor Console Screen).

b. Locate IC# 310.

c. Right click on IC# 310.

d. Select Reset on the drop down menu.

e. Right click on RESET.

f. Enter the password for IC# 310.

g. Select Yes on the INITIAL CONDITION RESET pop-up window.

h. Perform SWITCH CHECK.

3. ENSURE the following information appears on the Director Summary Screen:

Key Type Event Delay Inserted Ramp Initial Final Value ccr15 power to appendix r valve 70-26 R 1 00:00:00 00:00:00 on off ccr16 power to appendix r valve 70-27 R 2 00:00:00 00:00:00 on off ccr18 power to appendix r valve 70-34 R 3 00:00:00 00:00:00 on off ccr20 power to appendix r valve 70-64 R 4 00:00:00 00:00:00 on off ccr21 power to appendix r valve 70-74 R 5 00:00:00 00:00:00 on off ccr07 1-70-507 ccs pump 1a-a/1b-b xtie valve R 6 00:00:00 00:00:00 close 00:00:00 ccr15 power to appendix r valve 70-26 R 21 00:00:00 00:00:00 off on ccr16 power to appendix r valve 70-27 R 22 00:00:00 00:00:00 off on ccr18 power to appendix r valve 70-34 R 23 00:00:00 00:00:00 off on ccr20 power to appendix r valve 70-64 R 24 00:00:00 00:00:00 off on ccr21 power to appendix r valve 70-74 R 25 00:00:00 00:00:00 off on

4. Place simulator in RUN and acknowledge any alarms.

Page 3 of 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F

NRC Exam 2013-302

5. ENSURE 2-HS-70-33A, CCS PMP 2B-B RED light LIT, GREEN light DARK and 2-HS-70-51A, CCS PMP C-S NORMAL ACB RED light DARK, GREEN light LIT, with handswitch in the STOP, PULL-TO-LOCK position.

6. ENSURE Extra Operator is present in the simulator.

7. Place simulator in FREEZE until Examiner cue is given.

Page 4 of 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F

NRC Exam 2013-302 SIMULATOR CONTINGENCY ACTIONS:

IF INITIAL CONDITION 310 is unavailable for any reason, the following actions must be taken to reconstruct the IC.

1. Initialize to IC 40, 100% power BOL.

2. Perform switch check.

3. ENSURE the following information appears on the Director Summary Screen:

Key Type Event Delay Inserted Ramp Initial Final Value ccr15 power to appendix r valve 70-26 R 1 00:00:00 00:00:00 on off ccr16 power to appendix r valve 70-27 R 2 00:00:00 00:00:00 on off ccr18 power to appendix r valve 70-34 R 3 00:00:00 00:00:00 on off ccr20 power to appendix r valve 70-64 R 4 00:00:00 00:00:00 on off ccr21 power to appendix r valve 70-74 R 5 00:00:00 00:00:00 on off ccr07 1-70-507 ccs pump 1a-a/1b-b xtie valve R 6 00:00:00 00:00:00 close 00:00:00 ccr15 power to appendix r valve 70-26 R 21 00:00:00 00:00:00 off on ccr16 power to appendix r valve 70-27 R 22 00:00:00 00:00:00 off on ccr18 power to appendix r valve 70-34 R 23 00:00:00 00:00:00 off on ccr20 power to appendix r valve 70-64 R 24 00:00:00 00:00:00 off on ccr21 power to appendix r valve 70-74 R 25 00:00:00 00:00:00 off on

4. . Place simulator in RUN.

5. PLACE 2-HS-70-33A, CCS PMP 2B-B handswitch in the START position, and verify RED light LIT, GREEN light DARK.

6. PLACE 2-HS-70-51A, CCS PMP C-S NORMAL ACB handswitch in the STOP, PULL-TO-LOCK position and verify RED light DARK, GREEN light LIT.

7. Acknowledge and reset any alarms.

8. Save JPM to an open simulator IC location and PASSWORD PROTECT the IC.

Page 5 of 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F

NRC Exam 2013-302 READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. C-S CCS pump tripped during the last shift.

2. 1-AOI-15, Loss of Component Cooling Water (CCS), Section 3.2, Loss of CCS Flow, has been performed.

3. The Unit Supervisor has evaluated PRA Risk, Reactor Trip Risk and Applicable Tech Spec LCOs.

4. You are the Control Room Operator.

INITIATING CUES:

The Unit Supervisor directs you perform SOI-70.01, Component Cooling Water (CCS), Section 8.1, Align Pump 1B-B to Supply Header 1B, beginning at Step 2.

Inform the Unit Supervisor when the alignment has been completed.

Page 6 of 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F

NRC Exam 2013-302 STEP/STANDARD SAT/UNSAT START TIME: _______

STEP 1: [2] ENSURE Pump 1B-B, NOT in service. ___ SAT STANDARD: ___ UNSAT Applicant locates.1-HS-70-38A, CCS PMP 1B-B, and determines that the RED light is DARK and the GREEN light is LIT, indicating that the pump is STOPPED.

COMMENTS:

STEP 2: [3] PLACE 1-HS-70-38A, CCS PMP 1B-B, in the STOP/PULL- CRITICAL TO-LOCK position. STEP STANDARD: ___ SAT Applicant locates.1-HS-70-38A, CCS PMP 1B-B, and rotates the ___ UNSAT handswitch to the STOP position, then pulls the handswitch out to the PULL-TO-LOCK position. (Critical).

Step is critical to prevent damage to the 1B-B CCS Pump during valve realignments.

COMMENTS:

Page 7 of 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F

NRC Exam 2013-302 STEP/STANDARD SAT/UNSAT STEP 3: [4] PLACE the following breakers to ON: CRITICAL STEP

___ SAT

___ UNSAT STANDARD:

Applicant contacts the Console Operator and directs the Console Operator (as an AUO) to place the listed breakers to ON. (Critical).

Step is critical to apply power to deenergized valves to allow for alignments.

COMMENTS:

CAUTION Step 8.1[5] must be completed prior to continuing to prevent CCS headers 1-A and 1-B from being tied together.

NOTE Independent Verification of Step 8.1[5] and 8.1[6] may be delayed until prior to Step 8.1[7].

Page 8 of 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F

NRC Exam 2013-302 STEP/STANDARD SAT/UNSAT STEP 4: [5] CLOSE the following valves: CRITICAL STEP

___ SAT

___ UNSAT STANDARD:

Applicant locates 1-HS-70-34A, CCS PMPS 1A & 1B SUCT XTIE and rotates the handswitch to the LEFT to the CLOSE position. (Critical)

The applicant contacts the Console Operator and requests that 1-ISV-70-507, CCS PMP 1A-A/1B-B DISCHARGE CROSSTIE be CLOSED.

Console Operator modifies ccr07, 1-70-507 ccs pump 1a-a/1b-b xtie valve to open. Console Operator reports back as the AUO that 1-ISV-70-507 is OPEN.

Step is critical to allow for alignment of the 1B-B CCS pump to Supply Header 1B.

COMMENTS:

Page 9 of 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F

NRC Exam 2013-302 STEP/STANDARD SAT/UNSAT STEP 5: [6] OPEN the following valves: CRITICAL STEP

___ SAT

___ UNSAT STANDARD:

Applicant locates 1-HS-70-26A, CCS PMP 1B TO C-S DISCH XTIE, and rotates the handswitch to the RIGHT to the OPEN position.

(Critical)

Applicant observes RED light LIT, GREEN light DARK on 1-HS-70-26A, CCS PMP 1B TO C-S DISCH XTIE.

Applicant locates 1-HS-70-27A, CCS PMP 1B TO C-S DISCH XTIE, and rotates the handswitch to the RIGHT to the OPEN position.

(Critical)

Applicant observes RED light LIT, GREEN light DARK on 1-HS-70-27A, CCS PMP 1B TO C-S DISCH XTIE.

Applicant locates 1-HS-70-64A, CCS PMP 1B TO C-S SUCT XTIE, and rotates the handswitch to the RIGHT to the OPEN position. (Critical)

Applicant observes RED light LIT, GREEN light DARK on 1-HS-70-64A, CCS PMP 1B TO C-S SUCT XTIE.

Applicant locates 1-HS-70-74A, CCS PMP 1B TO C-S SUCT XTIE, and rotates the handswitch to the RIGHT to the OPEN position. (Critical)

Applicant observes RED light LIT, GREEN light DARK on 1-HS 74A, CCS PMP 1B TO C-S SUCT XTIE.

Steps are critical to allow for alignment of the 1B-B CCS pump to Supply Header 1B.

COMMENTS:

Page 10 of 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F

NRC Exam 2013-302 STEP/STANDARD SAT/UNSAT STEP 6: [7] PLACE the following breakers to OFF: ___ SAT

___ UNSAT STANDARD:

Applicant contacts the Console Operator as an AUO and directs the Console Operator (as an AUO) to place the listed breakers to OFF.

(Critical)

Steps are critical to allow for realignment of listed breakers to comply with OR14.10.

COMMENTS:

STEP 7: [8] IF C-S CCS Pump I/S to Supply Header 1B, THEN PERFORM ___ SAT the following to swap to CCS Pump 1B-B: ___ UNSAT STANDARD:

The applicant determines from the INITIAL CONDITIONS that the C-S CCS pump will remain out of service.

COMMENTS:

Page 11 of 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F

NRC Exam 2013-302 STEP/STANDARD SAT/UNSAT STEP 8: [9] PERFORM the following if C-S CCS Pump NOT I/S to Supply ___ SAT Header 1B:

___ UNSAT

[9.1] UNLOCK and THROTTLE 1-ISV-70-505B, CCS PUMP 1B-B DISCHARGE ISOLATION to 25% OPEN.

STANDARD:

Applicant contacts an AUO and requests that 1-ISV-70-505B, CCS PUMP 1B-B DISCHARGE ISOLATION be unlocked and throttled to 25%

OPEN.

CUE: When contacted as an AUO, the Console Operator will repeat back the request to open 1-ISV-70-505B, CCS PUMP 1B-B DISCHARGE ISOLATION to 25%. Console Operator reports back that 1-ISV-70-505B is 25% open.

COMMENTS:

CAUTION CCS Pump damage may occur below 900 gpm per pump.

NOTE Pump starting guidelines are in GOI-7.

STEP 9: [9] PERFORM the following if C-S CCS Pump NOT I/S to Supply ___ SAT Header 1B:

___ UNSAT

[9.2] ENSURE a sufficient flow path to provide greater than the minimum flow allowed.

STANDARD:

Applicant determines that there is a sufficient flow path.

COMMENTS:

Page 12 of 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F

NRC Exam 2013-302 STEP/STANDARD SAT/UNSAT STEP 10: [9] PERFORM the following if C-S CCS Pump NOT I/S to Supply CRITICAL Header 1B: STEP

[9.3] START CCS PMP 1B-B, with 1-HS-70-38A. ___ SAT STANDARD: ___ UNSAT Applicant locates 1-HS-70-38A, CCSPMP 1B-B, and rotates the handswitch to the START position. (Critical).

Steps are critical to provide flow from the 1B-B CCS pump to Supply Header 1B COMMENTS:

NOTE 1B Supply Header flow can be verified locally on 0-FI-70-201, [0-PNL-276-L643, A5-S/713].

STEP 11: [9] PERFORM the following if C-S CCS Pump NOT I/S to Supply ___ SAT Header 1B: ___ UNSAT

[9.4] OPEN SLOWLY 1-ISV-70-505B, CCS PUMP 1B-B DISCHARGE ISOLATION, THEN VERIFY flow between 900-6900 gpm.

STANDARD:

Applicant contacts an AUO and requests that 1-ISV-70-505B, CCS PUMP 1B-B DISCHARGE ISOLATION be opened slowly, and to verify flow between 900-6900 gpm.

CUE: When contacted as an AUO, the Console Operator will repeat back the request to slowly open 1-ISV-70-505B, CCS PUMP 1B-B DISCHARGE ISOLATION. Console Operator reports back that 1-ISV-70-505B is open, and that flow is 6000 gpm.

COMMENTS:

Page 13 of 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F

NRC Exam 2013-302 STEP/STANDARD SAT/UNSAT STEP 12: [9] PERFORM the following if C-S CCS Pump NOT I/S to Supply ___ SAT Header 1B:

___ UNSAT

[9.5] LOCK OPEN 1-ISV-70-505B, CCS PUMP 1B-B DISCHARGE ISOLATION.

STANDARD:

Applicant contacts an AUO and requests that 1-ISV-70-505B, CCS PUMP 1B-B DISCHARGE ISOLATION be locked open.

CUE: When contacted as an AUO, the Console Operator will repeat back the request to lock open 1-ISV-70-505B, CCS PUMP 1B-B DISCHARGE ISOLATION. Console Operator reports back that 1-ISV-70-505B is locked open.

COMMENTS:

STEP 13: [10] ENSURE started pump 480V ACB Closing Spring is ___ SAT CHARGED: [C.2] ___ UNSAT STANDARD:

Applicant contacts an AUO and requests that the charging springs are charged on 1-BKR-70-38, CCS PUMP 1B-B.

CUE: When contacted as an AUO, the Console Operator will repeat back the request to ensure the closing spring is charged on 1-BKR-70-38, CCS PUMP 1B-B (1-PMP-70-38).

COMMENTS:

Page 14 of 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F

NRC Exam 2013-302 STEP/STANDARD SAT/UNSAT STEP 14: [11] REFER TO Section 6.1 for temperature control of loop(s) ___ SAT placed in service.

___ UNSAT STANDARD:

When applicant addresses Step 11, state that another operator will refer to Section 6.1.

COMMENTS:

END OF TASK STOP TIME ________

Page 15 of 17

F Handout Package for Applicant

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

1. C-S CCS pump tripped during the last shift.

2. 1-AOI-15, Loss of Component Cooling Water (CCS), Section 3.2, Loss of CCS Flow, has been performed.

3. The Unit Supervisor has evaluated PRA Risk, Reactor Trip Risk and Applicable Tech Spec LCOs.

4. You are the Control Room Operator.

INITIATING CUES:

The Unit Supervisor directs you perform SOI-70.01, Component Cooling Water (CCS),

Section 8.1, Align Pump 1B-B to Supply Header 1B, beginning at Step 2.

Inform the Unit Supervisor when the alignment has been completed.

F

Watts Bar Nuclear Plant NRC EXAM 2013302 System JPM G

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G

NRC EXAM 2013-302 EVALUATION SHEET Task: Complete 1-SI-85-2, Reactivity Control Systems Movable Control Assemblies (Modes 1 and 2)

Alternate Path: After Control bank D is inserted to 210 steps, when the applicant attempts to withdraw Control Bank D to its previous position Control Bank D Group 2 rods insert.

Upon diagnosis of the continuous rod insertion, the applicant trips the reactor.

Facility JPM #: 2009-10 NRC Exam JPM B.1.a Safety Function: 1

Title:

Reactivity Control K/A 001 A4.03 Ability to manually operate and/or monitor in the control room: CRDS mode control.

Rating(s): 4.0 / 3.7 CFR: 41.7/45.5 to 45.8 Evaluation Method: Simulator X In-Plant Classroom

References:

1-SI-85-2,Reactivity Control Systems Movable Control Assemblies (Modes 1 and 2), Rev. 13 Task Number: RO-085-SOI-85-2-001

Title:

Verify operability of each control bank/shutdown bank.

Task Standard: The applicant:

1. Selects the CBC position on 1-RBSS, ROD BANK SELECT.

2. Inserts, then withdraws Control Bank C rods 10 steps.

3. Selects the CBD position on 1-RBSS, ROD BANK SELECT.

4. Inserts, then withdraws Control Bank D rods 10 steps.

5. Diagnoses the continuous insertion of Control Bank D Group 2 rods.

6. Performs a reactor trip in response to the continuous insertion of the Group 2 rods.

Validation Time: 15 minutes Time Critical: Yes No X

=================================================================

Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

================================================================

COMMENTS Page 2 of 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G

NRC EXAM 2013-302 SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. RESET to Initial Condition 311 by performing the following actions:

a. Select ICManager on the THUNDERBAR menu (right hand side of Instructor Console Screen).

b. Locate IC# 311.

c. Right click on IC# 311.

d. Select Reset on the drop down menu.

e. Right click on RESET.

f. Enter the password for IC# 311.

g. Select Yes on the INITIAL CONDITION RESET pop-up window.

h. Perform SWITCH CHECK.

3. ENSURE the following information appears on the Director Summary Screen:

Key Type Event Delay Inserted Ramp Initial Final Value rd02 uncontrolled rod insertion; bank d, group 2. M 30 00:00:00 00:00:00 00:00:00 100 0

4. ENSURE Event 30 is loaded.

[Control Bank D in Bank Select and inserted to 210 steps] zdirbss1(10)==1 & pc_rdu0052<=210.

6. PLACE simulator in FREEZE until Examiner cue is given.

7. ENSURE a marked-up copy of 1-SI-85-2 is available to the Examiner.

8. ENSURE Extra Operator is present in the simulator.

9. Place simulator in FREEZE until Examiner cue is given.

Page 3 of 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G

NRC EXAM 2013-302 Event Description/Role Play Applicant contacts the AUO stationed to support the surveillance at CONTROL ROD DRIVE PANEL 1-L-120 SOLID STATE POWER CAB (1AC) 1-PNL-85-L120 and requests the status of the GRP SELECT light B.

ROLE PLAY: When contacted as the AUO, the Console Operator will repeat back request. The Console Operator reports the GRP SELECT light B is LIT.

Applicant contacts the AUO stationed to support the surveillance at CONTROL ROD DRIVE PANEL 1-L-118 SOLID STATEPOWER CAB (2AC) 1-PNL-85-L118 and requests the status of the GRP SELECT light B.

ROLE PLAY: When contacted as the AUO, the Console Operator will repeat back request. The Console Operator reports the GRP SELECT light B is LIT.

Applicant contacts the AUO stationed to support the surveillance at CONTROL ROD DRIVE PANEL 1-L-121 SOLID STATE POWER CAB (1BD) 1-PNL-85-L121 and requests the status of the GRP SELECT light B.

ROLE PLAY: When contacted as the AUO, the Console Operator will repeat back request. The Console Operator reports the GRP SELECT light B is LIT.

Applicant contacts the AUO stationed to support the surveillance at CONTROL ROD DRIVE PANEL 1-L-117 SOLID STATEPOWER CAB (2BD) 1-PNL-85-L117 and requests the status of the GRP SELECT light B.

ROLE PLAY: When contacted as the AUO, the Console Operator will repeat back request. The Console Operator reports the GRP SELECT light B is LIT.

Page 4 of 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G

NRC EXAM 2013-302 READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

1. Unit 1 is operating at 100% power.

2. Performance of 1-SI-85-2,Reactivity Control Systems Movable Control Assemblies (Modes 1 and 2), is in progress.

3. An AUO is stationed at the CONTROL ROD DRIVE PANELS to support performance of 1-SI-85-2.

4. The procedure has been completed through Section 6.6 for Control Bank B.

INITIATING CUES:

The Unit Supervisor has directed you to complete 1-SI-85-2,Reactivity Control Systems Movable Control Assemblies (Modes 1 and 2).

Notify the Unit Supervisor when the control rods are returned to the AS FOUND position.

Page 5 of 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT START TIME: _______

EXAMINER: The following actions are taken from 1-SI-85-2, Section 6.7, CONTROL BANK C (CBC).

NOTE 1 Between rod bank movements, Tavg - Tref deviation may be adjusted using manual rod control or by adjusting turbine load.

NOTE 2 Rod movement is verified by monitoring (RPIs) and Step Counters.

STEP 1: [1] ENSURE Tavg - Tref deviation is adjusted to allow for bank ___ SAT movement of ten steps.

___ UNSAT STANDARD:

Applicant determines that the Tavg - Tref deviation is sufficient for bank movement.

COMMENTS:

NOTE 1-XA-55-4B-87A, ROD INSERTION LIMIT LO, may actuate during the following test sections.

STEP 2: [2] RECORD the initial position of the following Step Counters: ___ SAT 1-CBCG1, CONTROL BANK C1:________steps. ___ UNSAT 1-CBCG2, CONTROL BANK C2:________steps.

STANDARD:

Applicant records rod position for Control Bank C group 1 rods as 228 steps from demand counter 1-CBCG1 on 1-M-4.

Applicant records rod position for Control Bank C group 2 rods as 228 steps from demand counter 1-CBCG2 on 1-M-4.

COMMENTS:

Page 6 of 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT CAUTION If rod movement demand exists via any of the following methods, the rod bank select switch should be moved through AUTO rapidly to avoid undesired rod movement:

• Tavg is not within 1 °F of program,

• Less than 5 minutes has elapsed since any change in rod control input (i.e, Tavg, Tref, or NIS),

• Demand is indicated on the Computer Enhanced Rod Position Indication (CERPI) monitors

[1-M-4].

STEP 3: [3] PLACE 1-RBSS, ROD BANK SELECT, in CBC. CRITICAL STANDARD: STEP Applicant places 1-RBSS, Rod Bank Select switch, in the CBC ___ SAT (control bank C) position.

___ UNSAT Step is critical to allow movement of Control Bank C rods ONLY.

COMMENTS:

Page 7 of 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 4: [4] VERIFY correct bank selected locally by GRP. SELECT Light ___ SAT B illuminated on:

___ UNSAT

[4.1] CONTROL ROD DRIVE PANEL 1-L-120 SOLID STATE POWER CAB (1AC) 1-PNL-85-L120.

[4.2] CONTROL ROD DRIVE PANEL 1-L-118 SOLID STATE POWER CAB (2AC) 1-PNL-85-L118.

STANDARD:

Applicant contacts the AUO stationed to support the surveillance at CONTROL ROD DRIVE PANEL 1-L-120 SOLID STATE POWER CAB (1AC) 1-PNL-85-L120 and requests the status of the GRP SELECT light B.

ROLE PLAY: When contacted as the AUO, the Console Operator will repeat back request. The Console Operator reports the GRP SELECT light B is LIT.

Applicant contacts the AUO stationed to support the surveillance at CONTROL ROD DRIVE PANEL 1-L-118 SOLID STATE POWER CAB (2AC) 1-PNL-85-L118 and requests the status of the GRP SELECT light B.

ROLE PLAY: When contacted as the AUO, the Console Operator will repeat back request. The Console Operator reports the GRP SELECT light B is LIT.

COMMENTS:

Page 8 of 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT CRITICAL STEP 5: [5] () MOVE Control Bank C at least ten Steps in any one STEP direction, as indicated on the appropriate Step Counter, and VERIFY movement of the rods in the proper direction is ___ SAT indicated on the appropriate RPIs. (Acc Crit)

___ UNSAT STANDARD:

Applicant will insert CBC rods ten steps.

Step is critical since it is used to determine if Control Bank C motion meets acceptance criteria of the surveillance procedure.

COMMENTS:

STEP 6: [6] VERIFY Control Bank C1 and C2 Step Counters agree within ___ SAT plus or minus 2 steps.

___ UNSAT STANDARD:

Applicant determines from 1-CBCG1 and 1-CBCG2 Step counter positions that rods are within the +/- 2 step limit.

COMMENTS:

STEP 7: [7] () RETURN Control Bank C to its original position as ___ SAT recorded in Step 6.7[2] of this section using 1-FLRM, ROD MOTION CONTROL. ___ UNSAT STANDARD:

Applicant withdraws Control Bank C to its original position of 228 steps.

COMMENTS:

Page 9 of 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 8: [8] IF Rod Insertion Limit Lo Alarm 87-A does not clear, THEN ___ SAT

• REFER TO Tech Spec LCO 3.1.7. ___ UNSAT

• CONTACT System Engineer to reset 87-A USING ICS.

STANDARD:

Applicant determines that the Limit Lo Alarm 87-A has cleared and marks the step as N/A.

COMMENTS:

STEP 9: Section 6.7, Control Bank C (CBC) complete. ___ SAT STANDARD: ___ UNSAT Applicant determines that Section 6.7 is complete and continues to Section 6.8 CONTROL BANK D (CBD).

COMMENTS:

EXAMINER: The following actions are taken from 1-SI-85-2, Section 6.8, CONTROL BANK D (CBD).

NOTE 1 Between rod bank movements, Tavg - Tref deviation may be adjusted using manual rod control or by adjusting turbine load.

NOTE 2 Rod movement is verified by monitoring (RPIs) and Step Counters.

STEP 10: [1] ENSURE Tavg - Tref deviation is adjusted to allow for bank ___ SAT movement of ten steps.

___ UNSAT STANDARD:

Applicant determines that the Tavg - Tref deviation is sufficient for bank movement.

COMMENTS:

Page 10 of 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT NOTE 1-XA-55-4B-87A, ROD INSERTION LIMIT LO, may actuate during the following test sections.

STEP 11: [2] RECORD the initial position of the following Step Counters: ___ SAT 1-CBDG1, CONTROL BANK D1: ______________ steps. ___ UNSAT 1-CBDG2, CONTROL BANK D2: ______________ steps.

STANDARD:

Applicant records rod position for Control Bank D group 1 rods as 220 steps from demand counter 1-CBDG1 on 1-M-4.

Applicant records rod position for Control Bank D group 2 rods as 220 steps from demand counter 1-CBDG2 on 1-M-4.

COMMENTS:

NOTE The operator has the option of moving Control Bank D five Steps in one direction, then 10 steps in the opposite direction and then return to normal. This method will have less overall effect on reactor power.

STEP 12: [3] PLACE 1-RBSS, ROD BANK SELECT, in CBD. CRITICAL STANDARD: STEP Applicant places 1-RBSS, Rod Bank Select switch, in the CBD ___ SAT (control bank D) position.

___ UNSAT Step is critical to allow movement of Control Bank D rods ONLY.

COMMENTS:

Page 11 of 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 13: [4] VERIFY correct bank selected locally by GRP SELECT Light ___ SAT B illuminated on:

___ UNSAT

[4.1] CONTROL ROD DRIVE PANEL 1-L-121 SOLID STATEPOWER CAB (1BD) 1-PNL-85-L121.

[4.2] CONTROL ROD DRIVE PANEL 1-L-117 SOLID STATEPOWER CAB (2BD) 1-PNL-85-L117.

STANDARD:

Applicant contacts the AUO stationed to support the surveillance at CONTROL ROD DRIVE PANEL 1-L-121 SOLID STATE POWER CAB (1BD) 1-PNL-85-L121 and requests the status of the GRP SELECT light B.

ROLE PLAY: When contacted as the AUO, the Console Operator will repeat back request. The Console Operator reports the GRP SELECT light B is LIT.

Applicant contacts the AUO stationed to support the surveillance at CONTROL ROD DRIVE PANEL 1-L-117 SOLID STATE POWER CAB (2BD) 1-PNL-85-L117 and requests the status of the GRP SELECT light B.

ROLE PLAY: When contacted as the AUO, the Console Operator will repeat back request. The Console Operator reports the GRP SELECT light B is LIT.

COMMENTS:

NOTE 1-XA-55-4A-64F, C-11 BANK D AUTO WITHDRAWAL BLOCKED, will actuate if Control Bank D Rods are withdrawn past 220 Steps.

Page 12 of 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT CRITICAL STEP 14: [5] () MOVE Control Bank D at least ten Steps in any one STEP direction, as indicated on the appropriate Step Counter, and VERIFY movement of the rods in the proper direction is ___ SAT indicated on the appropriate RPIs. (Acc Crit)

___ UNSAT STANDARD:

Applicant may either:

Comply with the information contained in the NOTE preceding Step 3 OR Insert rods ten steps, and then withdraw the rods back to their original position.

Step is critical since it is used to determine if Control Bank D motion meets acceptance criteria of the surveillance procedure.

COMMENTS:

STEP 15: [6] VERIFY Control Bank D1 and D2 Step Counters agree ___ SAT within plus or minus 2 steps.

___ UNSAT STANDARD:

Applicant determines from 1-CBDG1 and 1-CBDG2 Step counter positions that rods are within the +/- 2 step limit.

COMMENTS:

EXAMINER: When the applicant begins to withdraw Control Bank D, a Slave Cycler mechanical failure; associated with Control Bank D, Group 2 This will cause 86-A, CONTROL ROD URGENT FAILURE to occur. The ROD TO BANK DEVIATION alarm will be indicated on 1-MON-85-5000/1, CERPI MONITOR 1 and 1-MON-85-5000/2, CERPI MONITOR 2.

Upon diagnosis of the continuous insertion of multiple rods, the applicant performs the IMMEDIATE ACTION of 1-AOI-2, Malfunction of Reactor Control System, and trips the reactor.

Page 13 of 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 16: [7] () RETURN Control Bank D to its original position as CRITICAL recorded in Step [2] of this section using 1-FLRM, ROD STEP MOTION CONTROL.

___ SAT STANDARD:

Applicant returns Control Bank D group 1 and group 2 rods to their ___ UNSAT original position of 220 steps.

Step is critical to ensure rod position is properly input into the bank overlap unit.

COMMENTS:

EXAMINER: Upon diagnosis of the continuous insertion of multiple rods, the applicant performs the IMMEDIATE ACTION of 1-AOI-2, Malfunction of Reactor Control System, and trips the reactor.

The following actions are taken from 1-AOI-2, Malfunction of Reactor Control System, Section 3.2, Uncontrolled Rod Bank Movement.

STEP 17: 1. STOP uncontrolled rod motion: ___ SAT

a. PLACE control rods in MAN. ___ UNSAT STANDARD:

Applicant determines that 1-RBSS, ROD BANK SELECT is in the CBD position, and that rods are in manual.

COMMENTS:

Page 14 of 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 18: 1. STOP uncontrolled rod motion: ___ SAT

b. CHECK control rod movement STOPPED. ___ UNSAT STANDARD:

Applicant determines from audible feedback associated with Control Band D Group 2 step counters, the Control Bank D Group 2 step counter display and from individual rod position indicators on the CERPI MONITORs that rod insertion is continuing.

Applicant enters the RESPONSE NOT OBTAINED column for actions.

COMMENTS:

STEP 19: 1. STOP uncontrolled rod motion: CRITICAL STEP

b. RESPONSE NOT OBTAINED:

___ SAT

() TRIP reactor. GO TO 1-E-0, Reactor Trip or Safety

___ UNSAT Injection.

STANDARD:

Applicant locates 1-RT-1, REACTOR TRIP and rotates the handswitch to the RIGHT to the TRIP position.

Step is critical to place the reactor in a known condition.

COMMENTS:

END OF TASK STOP TIME ________

Page 15 of 17

G Handout Package for Applicant

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

1. Unit 1 is operating at 100% power.

2. Performance of 1-SI-85-2,Reactivity Control Systems Movable Control Assemblies (Modes 1 and 2), is in progress.

3. An AUO is stationed at the CONTROL ROD DRIVE PANELS to support performance of 1-SI-85-2.

4. The procedure has been completed through Section 6.6 for Control Bank B.

INITIATING CUES:

The Unit Supervisor has directed you to complete 1-SI-85-2,Reactivity Control Systems Movable Control Assemblies (Modes 1 and 2).

Notify the Unit Supervisor when the control rods are returned to the AS FOUND position.

G

Watts Bar Nuclear Plant NRC EXAM 2013302 System JPM H (RO Only)

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H

NRC EXAM 2013-302 EVALUATION SHEET Task: RESPOND TO RHR PUMP TRIP PER AOI-14.

Alternate Path: n/a Facility JPM #: 3-OT-JPMR164 Safety Function: 4P

Title:

Heat Removal From Reactor Core K/A 025 AA1.09 Ability to operate and / or monitor the following as they apply to the Loss of Residual Heat Removal System: LPI pump switches, ammeter, discharge pressure gauge, flow meter, and indicators.

Rating(s): 3.2/3.1 CFR: 41.7 / 45.5 / 45.6 Simulator X In-Plant Perform X Simulate

References:

SOI-74.01, Residual Heat Removal System, Rev. 61.

AOI-14 Loss Of RHR Shutdown Cooling Rev. 37.

Task Number: RO-074-AOI-14-002

Title:

During RHR pump operation, respond to an RHR pump trip.

Task Standard: The applicant responds to the trip of 1A RHR pump in accordance with AOI-14, Loss of RHR Shutdown Cooling, Section 3.5, RHR Pump 1A-A Trip and places the 1B RHR pump in service.

Validation Time: 25 minutes Time Critical: Yes No X

=

Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

==============================================================

=

COMMENTS Page 2 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H

NRC EXAM 2013-302 SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. RESET to Initial Condition 312 by performing the following actions:

a. Select ICManager on the THUNDERBAR menu (right hand side of Instructor Console Screen).

b. Locate IC# 312.

c. Right click on IC# 312.

d. Select Reset on the drop down menu.

e. Right click on RESET.

f. Enter the password for IC 312.

g. Select Yes on the INITIAL CONDITION RESET pop-up window.

h. Perform SWITCH CHECK.

3. SELECT Director on the THUNDERBAR menu (right hand side of Instructor Console Screen).

4. ENSURE the following information appears on the Director Screen:

Key Description Type Event Delay Inserted Ramp Initial Final Value csr03 containment spray pump a power R 00:00:00 00:00:00 00:00:00 off off csr04 containment spray pump b power R 00:00:00 00:00:00 00:00:00 off off sir08 si pump a power R 00:00:00 00:00:00 00:00:00 off off sir09 si pump b power R 00:00:00 00:00:00 00:00:00 off off csr05 power to cntmt spray valves fcv-72-2, 39. R 00:00:00 00:00:00 00:00:00 off off cvr03 power removal centrifugal charge pump b R 00:00:00 00:00:00 00:00:00 off off rhr12 rhr spray hdr a isolation valve power, fcv-72-40 R 00:00:00 00:00:00 00:00:00 off off rhr13 rhr spray hdr b isolation valve power, fcv-72-41 R 00:00:00 00:00:00 00:00:00 off off hs-30-38a-1 01010 air return fans a-a on/off(green) O 00:00:00 00:00:00 00:00:00 off off hs-30-39a-1 01010 air return fans b-b on/off(green) O 00:00:00 00:00:00 00:00:00 off off rh01a rhr pump a trip M 1 00:00:00 00:00:00 Active InActive rhr06 hr htx bypass valve hcv-74-36 R 2 00:00:00 00:00:00 0 1 rhr07 hr htx bypass valve hcv-74-37 R 3 00:00:00 00:00:00 1 0 rhr03 hr valve 74-530 to cvcs letdown R 4 00:00:00 00:00:00 0 1 rhr04 hr valve 74-531 to cvcs letdown R 5 00:00:00 00:00:00 1 0

5. Place simulator in RUN and acknowledge any alarms.

Page 3 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H

NRC EXAM 2013-302

6. Place GREEN Tags on the following components:

• 1-HS-72-27A, Cntmt Spray Pmp A

• 1-HS-72-10A, Cntmt Spray Pmp B

• 1-HS-63-10A, SI Pmp A

• 1-HS-63-15A, SI Pmp B

• 1-HS-62-104A, CCP B-B

• Air Return Fan A-A 1-HS-30-38A

• Air Return Fan B-B 1-HS-30-39A

• 1-HS-63-26A, BIT Outlet

• 1-HS-63-25A, BIT Outlet

• 1-HS-72-40A, RHR Spray Header A to Cntmt

• 1-HS-72-41A, RHR Spray Header B to Cntmt

• 1-HS-63-72A, Cntmt Sump to RHR Pmp A Suction

• 1-HS-63-73A, Cntmt Sump to RHR Pmp B Suction

• 1-HS-72-44A, Cntmt Sump to CS Pmp A Suction

• 1-HS-72-45A, Cntmt Sump to CS Pmp B Suction

• 1-HS-72-39A, Cntmt Spray Hdr A to Cntmt

• 1-HS-72-2A, Cntmt Spray Hdr B to Cntmt

• 1-HS-63-8A, RHR Pmp A to Charging Pmp Suction

• 1-HS-63-11A, RHR Pmp B to SI Pmp Suction

• 1-HS-3-116A/A, ERCW to AFWP A-A Suction From Hdr A

• 1-HS-3-126 A/A, ERCW to AFWP B-B Suction From Hdr B

• 1-HS-3-136 A/A, ERCW to TD AFWP Suction From Hdr A

• 1-HS-3-179 A/A, ERCW to TD AFWP Suction From Hdr B

8. ENSURE Extra Operator is present in the simulator.

9. Place simulator in FREEZE until Examiner cue is given.

Page 4 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H

NRC EXAM 2013-302 Simulator Event No. Description/Role Play 1 1A-A RHR Pump trip.

ROLE PLAY: When CB AUO contacted, state that pump tripped on Instantaneous over current.

When AB AUO contacted state that there is evidence of cable damage to the motor pigtail, there is an order of burnt insulation but there is no smoke or fire.

2 AUO is dispatched to close 1-HCV-74-36 ROLE PLAY: When contacted as an AUO to close 1-HCV-74-36, repeat back request. Enter Event 2, which will enter remote function rh06 to close. Report back that 1-HCV-74-36 is closed.

3 AUO is dispatched to open 1-HCV-74-37 ROLE PLAY: When contacted as an AUO to open 1-HCV-74-37, repeat back request. Enter Event 3, which will enter remote function rh07 to open. Report back that 1-HCV-74-37 is open.

4 AUO is dispatched to close 1-SPV-74-530 ROLE PLAY: When contacted as an AUO to close 1-SPV-74-530, repeat back request. Enter Event 4, which will enter remote function rh03 to close. Report back that 1-SPV-62-530 is closed.

5 AUO is dispatched to open 1-HCV-74-36 ROLE PLAY: When contacted as an AUO to open 1-SPV-74-531, repeat back request. Enter Event 5, which will enter remote function rh04 to open. Report back that 1-SPV-74-531 is open.

Page 5 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H

NRC EXAM 2013-302 READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. Unit 1 is in MODE 4.

2. Unit 1 has been cooled down.

3. 1A-A RHR train is in service.

4. 1B-B RHR pump is available, and was in service 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ago.

5. CVCS is in service.

6. RHR to CVCS Letdown is in service from RHR Heat Exchanger A outlet.

7. You are the Operator at the Controls.

INITIATING CUES:

Monitor the control board and respond to events using appropriate procedure.

Page 6 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT START TIME: _______

EXAMINER: After the applicant has stated that the task is understood, cue the Console Operator enter Event 1 to trip the 1A-A RHR pump on instantaneous overcurrent.

EXAMINER: The following actions are taken from AOI-14, Loss of RHR Shutdown Cooling, Section 3.5, RHR Pump 1A-A trip.

STEP 1: 1. CHECK BOTH RHR pumps stopped. ___ SAT STANDARD: ___ UNSAT Applicant placed 1-HS-74-10A in STOP PULL-TO-LOCK in response to 14-E, M-1 THRU M-6 MOTOR TRIPOUT, which was received when the 1A-A RHR pump tripped. Applicant checks 1-HS-74-20A RHR pump 1B-B stopped.

When contacted as an AUO, the Console Operator will repeat back the request to determine why 1A-A RHR Pump has tripped. Console Operator reports that there is evidence of cable damage to the motor pigtail, there is an odor of burnt insulation but there is no smoke or fire.

COMMENTS:

STEP 2: 2. CHECK RCS temp less than 235°F. ___ SAT STANDARD: ___ UNSAT Applicant determines that RCS temperature is less than 235°F by checking the following temperature recorders (Applicant may also use plasma displays or plant computer):

• 1-TR-74-14 RHR Hx A Temp °F

• 1-TR-74-25 RHR Hx B Temp °F COMMENTS:

Page 7 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 3: 3. ADJUST charging and letdown to maintain RCS level and ___ SAT press. ___ UNSAT STANDARD:

Applicant may adjust 1-HIC-62-83 RHR LETDOWN FLOW CONTROL closed and 1-FCV-62-93 CHARGING HEADER FLOW PZR LEVEL CONTROL to minimum to slow increase in pressurizer level as observed on PZR COLD CAL Level 1-LI-68-321. Applicant may also adjust 1-FCV-62-89.

COMMENTS:

CAUTION If the running RHR pump tripped due to inadequate suction supply or alignment problems, then do NOT attempt to start standby pump until adequate supply and alignment is ensured.

STEP 4: 4. CHECK RHR pump 1B-B available. ___ SAT STANDARD: ___ UNSAT Applicant determines that 1B-B RHR pump is available (given in INITIAL CONDITIONS).

COMMENTS:

Page 8 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 5: 5. OPEN 1-FCV-70-153, CCS to RHR HX B. ___ SAT STANDARD: ___ UNSAT Applicant determines that 1-FCV-70-153 is open by checking 1-HS 153A is tagged with Power Disconnected Open (PDO) tag. Applicant may check flow through heat exchanger on 1-EI-70-155 RHR Hx B Flow.

COMMENTS:

STEP 6: 6. ENSURE RCS HL to RHR suction OPEN: ___ SAT

• 1-FCV-74-1 and 1-FCV-74-2, OR ___ UNSAT

• 1-FCV-74-8 and 1-FCV-74-9.

STANDARD:

Applicant determines 1-FCV-74-1 and -2 are OPEN by checking respective control board hand switch RED light LIT and GREEN light DARK on 1-HS-74-1A and 1-HS-74-2A.

COMMENTS:

STEP 7: 7. OPEN 1-FCV-74-21, RHR pump 1B-B suction. ___ SAT STANDARD: ___ UNSAT The applicant determines 1-FCV-74-21 open by checking RED light LIT and GREEN light DARK on hand switch 1-HS-74-21.

COMMENTS:

Page 9 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 8: 8. CLOSE RHR Hx outlets and bypass: CRITICAL STEP

• 1-FCV-74-16, RHR Hx A outlet.

• 1-FCV-74-28, RHR Hx B outlet. ___ SAT

• 1-FCV-74-32, RHR Hx bypass. ___ UNSAT STANDARD:

Applicant locates 1-HIC-74-16 and closes by rotating CCW to the stop. (Critical).

Applicant locates 1-HIC-74-32 and closes by rotating CCW to the stop. (Critical).

Applicant locates 1-HIC-74-28 and checks closed by rotating CCW to the CLOSE stop.

This step is critical to flow path alignment prior to starting 1B-B RHR pump to limit starting current.

COMMENTS:

Page 10 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 9: 9. ALIGN RHR pump 1B-B discharge: CRITICAL

a. OPEN 1-FCV-63-94, RHR B to CL 1 & 4. STEP

___ SAT

b. OPEN 1-FCV-74-35, RHR Hx B outlet xtie.

___ UNSAT

c. CLOSE 1-FCV-74-33, RHR Hx A outlet xtie.

d. CLOSE 1-FCV-63-93, RHR A to CL 2 & 3.

STANDARD:

Applicant locates 1-HS-63-94 and rotates the handswitch to the right to the OPEN position (Critical).

Applicant observes GREEN light is DARK and RED light is LIT.

Applicant locates 1-HS-74-35 and rotates the handswitch to the right to the OPEN position (Critical).

Applicant observes GREEN light is DARK and RED light for LIT.

Applicant locates 1-HS-74-33 and rotates the handswitch to the left to the CLOSED position (Critical).

Applicant observes GREEN light is LIT and RED light is DARK.

Applicant locates 1-HS-63-93 and rotates the handswitch to the left to the CLOSED position (Critical).

Applicant observes GREEN light is LIT and RED light is DARK.

This step is critical to establish proper flow path prior to start of 1B-B RHR pump, and to isolate the flow path from the 1A-A RHR pump.

COMMENTS:

Page 11 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 10: 10. START RHR pump 1B-B. CRITICAL STANDARD: STEP

___ SAT Applicant locates1-HS-74-20A and rotates the handswitch to the right to the START position (Critical). ___ UNSAT Applicant verifies GREEN light is DARK and the RED light LIT.

Applicant observes amps for the 1B-B RHR pump on 1-EI-74-17A, rising.

Applicant observes discharge pressure for the 1B-B RHR pump on 1-PI-74-26, rising.

This step is critical to starting 1B-B RHR pump and establishing RHR shutdown cooling.

COMMENTS:

STEP 11: 11. ADJUST 1-FCV-74-28 to establish RHR flow within the RHR CRITICAL Pump operating flow limits in SOI-74.01 Appendix A. STEP STANDARD:

Applicant adjusts RHR flow through 1-FCV-74-28 by rotating CW ___ SAT from 0% using 1-HIC-74-28A and observing rising flow on 1-FI ___ UNSAT 92A, RHR TO CL 1&4 NR FLOW.

Establishing a flow of 2000 to 4000 gpm is critical to establishing RHR shutdown cooling.

COMMENTS:

Page 12 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 12: 12. ALIGN RHR Hx bypass flow: CRITICAL

a. CLOSE 1-HCV-74-36, RHR Hx A bypass isol. STEP

___ SAT

b. OPEN 1-HCV-74-37, RHR Hx B bypass isol.

___ UNSAT

c. ADJUST 1-FCV-74-32, RHR Hx bypass FCV.

STANDARD:

Applicant contacts AUO to close 1-HCV-74-36. (Critical to contact the local operator to close valve).

When contacted as an AUO, the Console Operator will repeat back the request to close 1-HCV-74-36. Console Operator enters Event 4 (rhr03) and reports back that 1-HCV-74-36 is CLOSED.

Applicant contacts AUO to open 1-HCV-74-37. (Critical to contact the local operator to open valve).

When contacted as an AUO, the Console Operator will repeat back the request to close 1-HCV-74-37. Console Operator enters Event 4 (rhr03) and reports back that 1-HCV-74-37 is CLOSED.

Applicant locates 1-HIC-74-32A and adjusts to stabilize RCS temperature as observed on 1-TR-74-25 RHR Hx B Temp °F.

(Critical).

This step is critical to prevent cooling down to Mode 5.

COMMENTS:

STEP 13: 13. WHEN RHR flow greater than 1400 gpm, THEN ENSURE ___ SAT 1-FCV-74-24, RHR pump B mini-flow CLOSED.

___ UNSAT STANDARD:

Applicant checks mini flow valve 1-FCV-74-24 closed by checking GREEN light LIT on 1-HS-74-24A when flow greater than 1400 gpm as determined by Window 113-C RHR PUMP DISCH PRESS HI/MINI FLOW CONDITION clearing.

COMMENTS:

Page 13 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT CAUTION Rapid changes in letdown flow and RCS pressure may occur during RHR letdown realignment. The following steps should be coordinated to allow MCR adjustments as local alignments are performed especially if PZR is water solid.

STEP 14: 14. ALIGN RHR pump 1B-B to CVCS: CRITICAL

a. CLOSE 1-SPV-74-530, Tr A [1A Hx rm/722]. STEP

b. OPEN 1-SPV-74-531, Tr B [1B Hx rm/722].

___ SAT STANDARD:

Applicant contacts AUO to close 1-SPV-74-530. (Critical to ___ UNSAT contact the local operator to close valve).

When contacted as an AUO, the Console Operator will repeat back the request to close 1-SPV-74-530. Console Operator enters Event 4 (rhr03) and reports back that 1-SPV-70-530 is CLOSED.

Applicant contacts AUO to open 1-SPV-74-531. (Critical to contact the local operator to open valve).

When contacted as an AUO, the Console Operator will repeat back the request to open 1-SPV-74-531. Console Operator enters Event 5 (rhr04) and reports back that 1-SPV-70-531 is OPEN.

This step is critical to establish proper flow path to CVCS after start of 1B-B RHR pump.

COMMENTS:

Page 14 of 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 15: 15. ESTABLISH RHR letdown ___ SAT

a. SLOWLY OPEN 1-FCV-62-83, RHR Letdown Flow Control. ___ UNSAT

b. MONITOR 1-PI-62-81, LP Letdown Press.

STANDARD:

Applicant locates 1-HIC-62-83A and rotates the setpoint dial COUNTER CLOCKWISE SLOWLY, while monitoring 1-PI-62-81, LP LETDOWN PRESS.

EXAMINER: After the applicant has opened 1-FCV-62-83, state that another operator will complete AOI-14 actions.

COMMENTS:

END OF TASK STOP TIME ________

Page 15 of 16

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

1. Unit 1 is in MODE 4.

2. Unit 1 has been cooled down.

3. 1A-A RHR train is in service.

4. 1B-B RHR pump is available, and was in service 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ago.

5. CVCS is in service.

6. RHR to CVCS Letdown is in service from RHR Heat Exchanger A outlet.

7. You are the Operator at the Controls.

INITIATING CUES:

Monitor the control board and respond to events using appropriate procedure.

H

Watts Bar Nuclear Plant NRC EXAM 2013302 System JPM I

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I

NRC EXAM 2013-302 EVALUATION SHEET Task: BYPASS1-PCV-62-81, CVCS LETDOWN HX PRESS CNTL, FOR LOCAL CONTROL Alternate Path: n/a Facility JPM #: 3-OT-JMPA156A Safety Function: 2

Title:

Reactor Pressure Control.

K/A 004 A4.05 Ability to manually operate and/or monitor in the control room: Letdown pressure and temperature control valves Rating(s): 3.6/3.1 CFR: 41.7 / 45.5 to 45.8 Evaluation Method: Simulator In-Plant X Classroom

References:

SOI-62.01, CVCS - Charging and Letdown, Rev. 64.

Task Number: AUO-062-SOI-62.1-015

Title:

Bypass 1-PCV-62-81, CVCS Letdown Heat Exchanger Pressure Control, for local control.

Task Standard: Applicant performs SOI-62.01, CVCS - Charging and Letdown, Section 8.15, Bypass 1-PCV-62-81, CVCS LETDOWN HX PRESS CNTL, for Local Control, and stabilizes pressure.

Validation Time: 15 minutes Time Critical: Yes No X

============================================================

Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

=============================================================

COMMENTS Page 2 of 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I

NRC EXAM 2013-302 Tools/Equipment/Procedures Needed:

Hard Hat, Safety Glasses, Hearing Protection, Plant Approved Shoes, Gloves.

ALARA considerations.

Start this JPM in the MCR.

Page 3 of 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I

NRC EXAM 2013-302 READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating/operating cues.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM.

SIMULATE ALL MANIPULATIONS.

When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure that you indicate to me when you fully understand your task. To indicate that you have completed your assigned task return the cue sheet I provided you. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. Unit is at 100% RTP.

2. Centrifugal Charging Pump 1A-A is in service.

3. Letdown Pressure Control Valve 1-PCV-62-81 has been operating in a sluggish manner causing swings in letdown pressure.

4. Work Control has been contacted and has requested that 1-PCV-62-81 be bypassed to permit further investigation of the pressure control valve.

INITIATING CUES:

The Unit Operator has directed you to bypass 1-PCV-62-81, for local control of Letdown Heat Exchanger Pressure per procedure while maintaining radio contact with the MCR operator (Allowing the MCR operator to provide direction and control of letdown pressure).

Notify the Unit Operator when you have bypassed 1-PCV-62-81.

Page 4 of 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT START TIME: _______

STEP 1: [1] ESTABLISH communications with personnel at the Main ___ SAT Control Room (or Aux Control Room) and Aux Bldg el 737 Outside the letdown heat exchanger room. ___ UNSAT STANDARD:

Applicant locates local phone and indicates that communication has been established to the Main Control Room.

COMMENTS:

STEP 2: [2] PLACE 1-HIC-62-81A, LETDOWN PRESS CONTROL in ___ SAT MANUAL.

___ UNSAT STANDARD:

Applicant contacts the Main Control room to ensure that the UO has placed the valve controller in manual.

CUE: When UO contacted, acknowledge, then state that 1-HIC-62-81A is in MANUAL COMMENTS:

Page 5 of 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 3: [3] THROTTLE CLOSED 1-ISV-62-673, CVCS LETDOWN CRITICAL HEADER ISOLATION [A5U/737] until pressure rise indicated in STEP MCR or Aux Cntl Rm.

STANDARD: ___ SAT Applicant locates 1-ISV-62-673, CVCS LETDOWN HEADER ___ UNSAT ISOLATION, and states that to throttle the valve closed, the handwheel must be rotated in the clockwise direction.

• • CUE: After performer states how to CLOSE valve, then state that valve hand wheel rotates in clockwise direction. IF control room contacted to monitor letdown pressure, then after several turns state that a pressure rise is observed.

Step is critical for establishing proper flow path for bypassing 1-PCV-62-81.

COMMENTS:

Page 6 of 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT NOTE The next step will cause a pressure swing in the letdown header. The MCR operator and local operator should coordinate actions to minimize the pressure swings.

STEP 4: [4] THROTTLE OPEN 1-BYV-62-672, CVCS LETDOWN PCV CRITICAL 81 BYPASS [A5U/737] while CLOSING 1-ISV-62-673, CVCS STEP LETDOWN HEADER ISOLATION.

STANDARD: ___ SAT Applicant locates 1-BYV-62-672, CVCS LETDOWN PCV-62-81 ___ UNSAT BYPASS ISOLATION, and states that to throttle the valve open, the handwheel must be rotated in the counter clockwise direction.

Applicant indicates that letdown line pressure has been controlled per UO directions (counter clockwise on 1-BYV-62-672 and clockwise on 1-ISV-62-673 until 1-ISV-62-673 is fully closed.

CUE: If UO contacted, state that letdown pressure lowers as 1-BYV-62-672 is OPENED and rises as 1-ISV-62-673 is closed.

Step is critical for establishing proper flow path for bypassing 1-PCV-62-81 COMMENTS:

Page 7 of 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 5: [5] ADJUST 1-BYV-62-672, CVCS LETDOWN PCV-62-81 ___ SAT BYPASS [A5U/737] to maintain desired letdown press.

___ UNSAT STANDARD:

Applicant responds to cues and controls letdown line pressure per UO directions (clockwise on 1-BYV-62-672 to raise pressure and counter clockwise on 1-BYV-62-672 to lower pressure).

CUE: If UO contacted, state that letdown pressure needs to be raised slightly.

• • CUE: As operator operates 1-BYV-62-672 clockwise state that letdown pressure has risen enough and then state that Rad Waste AUO will be contacted to control the 1-BYV-62-672 if additional adjustments are required.

• • CUE: As Unit Operator state that Rad Waste AUO will monitor the operation of 1-BYV-62-672.

COMMENTS:

END OF TASK STOP TIME ________

Page 8 of 10

I Handout Package for Applicant

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

1. Unit is at 100% RTP.

2. Centrifugal Charging Pump 1A-A is in service.

3. Letdown Pressure Control Valve 1-PCV-62-81 has been operating in a sluggish manner causing swings in letdown pressure.

4. Work Control has been contacted and has requested that 1-PCV-62-81 be bypassed to permit further investigation of the pressure control valve.

INITIATING CUES:

The Unit Operator has directed you to bypass 1-PCV-62-81, for local control of Letdown Heat Exchanger Pressure per procedure while maintaining radio contact with the MCR operator (Allowing the MCR operator to provide direction and control of letdown pressure).

Notify the Unit Operator when you have bypassed 1-PCV-62-81.

I

Watts Bar Nuclear Plant NRC Exam 2013302 System JPM J

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J

NRC Exam 2013-302 EVALUATION SHEET Task: LOCAL RESTART OF C&SS AIR COMPRESSORS.

Alternate Path: Compressor A has high discharge air temperature and high oil temperature indication lights. Compressor A fails to auto load.

Facility JPM #: 3-OT-JPMA001C Rev 5 Safety Function: 8

Title:

Plant Service Systems K/A 065 AK3.08 Knowledge of the reasons for the following responses as they apply to the Loss of Instrument Air: Actions contained in EOP for loss of instrument air.

Rating(s): 3.7/3.9 CFR: 41.5,41.10 / 45.6 / 45.13 Evaluation Method: Simulator In-Plant X

References:

1-AOI-10 Loss of Control Air Rev. 1 Task Number: AUO-032-AOI-010-002

Title:

Perform Attachment 1 of AOI-10, Local Restart of Control and Station Service Air Compressors.

Task Standard: The applicant has aligned and started A and B Air Compressors using AOI-10, Loss of Control Air, Attachment 1, Local Restart of C&SS Air Compressors. Control Air (Non-Essential) pressure has been re-established.

Validation Time: 15 minutes Time Critical: Yes No X

=================================================================

Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

=================================================================

COMMENTS PAGE 2 OF 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J

NRC EXAM 2013-302 Tools/Equipment/Procedures Needed:

Hard Hat, Safety Glasses, Hearing Protection, Gloves and Plant Approved Shoes.

AOI-10 Attachment 1.

High Noise Area; energized rotating equipment that can auto start.

EVALUATOR NOTE: Provide a copy of AOI-10 Attachment 1 to performer with candidates cue sheet.

PAGE 3 OF 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J

NRC EXAM 2013-302 READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating/operating cues.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM.

SIMULATE ALL MANIPULATIONS.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Ensure that you indicate to me when you fully understand your task.

To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. A Station Blackout has occurred.

2. The Diesel Generators have started and are feeding the Shutdown Boards.

3. The Control and Service Air compressors were aligned normal with "C" air compressor in the lead prior to the Blackout.

4. A loss of Non-essential and Service air has occurred (Air pressure is at 75 psig decreasing).

5. Essential Air is being supplied by the Aux. Air compressors.

6. The 480V Auxiliary Building Common Board does not have voltage available on its normal or alternate supply.

7. Local control power is available to the air compressors.

8. You are a support AUO on shift.

INITIATING CUES:

1. The Unit Operator has dispatched you with a copy of Attachment 1 of AOI-10 with instructions to perform steps 2 through 10.

2. Notify the Unit Operator when you have completed the task.

PAGE 4 OF 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT START TIME: _______

STEP 1: 2. Locally CHECK 0-PCV-33-4, SERVICE AIR SUPPLY ___ SAT ISOLATION, CLOSED [T7M/708].

___ UNSAT STANDARD:

The applicant locates and describes how to check that 0-PCV-33-4 is in the closed position by either the green local indicating light or the stem down on the valve.

CUE: When the valve is checked, state that green light is ON, Red light is OFF, and Stem is down, with the indicator at C.

COMMENTS:

STEP 2: 3. CHECK local control station alarm DARK [ Panel 0-L-240, ___ SAT T7M/708].

___ UNSAT STANDARD:

The applicant locates the local control station (Panel 0-L-240) alarms and indicates how to check the alarms.

CUE: When checked, indicate that Compressor "A" high discharge air temp and high oil temp lights are illuminated.

The applicant proceeds to RNO column after discovery of the high discharge air temp and high oil temp on A compressor being LIT.

COMMENTS:

PAGE 5 0F 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 3: 3. RESPONSE NOT OBTAINED: CRITICAL STEP IF local control station alarm LIT, THEN PERFORM the following for each air compressor in alarm: ___ SAT

a. RESET high air temp at each compressor (0-TS-32-41, ___ UNSAT

-36,-31).

STANDARD:

Applicant locates and describes how to depress the High Air Temp reset push button, 0-TS-32-41, (on west side of A air compressor).

CUE: When checked, and after applicant indicates how to depress pushbutton for 0-TS-32-41, state that the pushbutton is as you see it (reset).

Step is critical because A compressor cannot be started with the alarm switch NOT reset.

COMMENTS:

PAGE 6 0F 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 4: 3. RESPONSE NOT OBTAINED: CRITICAL STEP IF local control station alarm LIT, THEN PERFORM the following for each air compressor in alarm: ___ SAT

b. RESET high oil temp switches at each air compressor ___ UNSAT (0-TS-32-40, -35, -30).

STANDARD:

Applicant locates and describes how to depress the High oil Temp reset push button, 0-TS-32-40, (on east side of A air compressor).

CUE: When checked, and after applicant indicates how to depress pushbutton for 0-TS-32-40, state that the pushbutton is as you see it (reset).

Step is critical because A compressor cannot be started with the alarm switch NOT reset.

COMMENTS:

PAGE 7 0F 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 5: 3. RESPONSE NOT OBTAINED: CRITICAL STEP IF local control station alarm LIT, THEN PERFORM the following for each air compressor in alarm: ___ SAT

c. RESET Common Alarm using 0-HS-32-25B, ___ UNSAT COMPRESSOR A, B, C RESET [0-L-240, yellow PB].

STANDARD:

Applicant locates and describes how to depress 0-HS-32-25B COMPRESSOR A, B, C RESET pushbutton.

CUE: When checked, and after applicant indicates how to depress pushbutton for 0-TS-32-40, state that the pushbutton is as you see it (reset).

Step is critical because A compressor cannot be started without using pushbutton to reset trip logic.

COMMENTS:

PAGE 8 0F 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 6: 3. RESPONSE NOT OBTAINED: ___ SAT IF local control station alarm LIT, THEN PERFORM the ___ UNSAT following for each air compressor in alarm:

d. CHECK common and all compressor local alarms DARK.

STANDARD:

The applicant locates the alarms and requests the status of each alarm on panel.

CUE: After high air temp and high oil temp, reset push buttons at compressor "A", and 0-HS-32-25B has been pushed, indicate to the applicant that all alarms lights on panel are dark.

COMMENTS:

STEP 7: 4. PLACE the following C&SS Compressors to HAND [0-L-240]: CRITICAL STEP

• A, 0-HS-32-25D.

___ SAT

• B, 0-HS-32-26A.

___ UNSAT STANDARD:

Applicant locates and describes how to place 0-HS-32-25D for A Compressor and 0-HS-32-26A for B Compressor to the HAND position.

CUE: Indicate that both handswitches point to HAND.

Step is critical because the hand switches enable the respective local start pushbuttons.

COMMENTS:

PAGE 9 0F 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 8: 5. PLACE 0-HS-32-25A, STATION AIR COMPRESSOR ___ SAT SEQUENCE CONTROL, to Position 1.

___ UNSAT STANDARD:

Applicant locates and describes how to rotate 0-HS-32-25A, Station Air Compressor Sequence Selector Control, to select Position 1.

CUE: Indicate that Sequence Selector is in position 3 before operation, and indicate that Sequence Selector is in position 1 after operation.

COMMENTS:

STEP 9: 6. START Compressor A by pushing 0-HS-32-25E. CRITICAL STEP STANDARD:

___ SAT Applicant locates and describes how to depress 0-HS-32-25E manual start push button. ___ UNSAT CUE: If JPM Steps 4, 5, 6, and 7 were SAT, then when PB is depressed, if asked, state that an air compressor start was heard. If JPM Steps 4, 5, 6, or 7 were UNSAT, if asked, state that compressor start was not heard.

Step is critical to start air compressor.

COMMENTS:

PAGE 10 0F 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 10: 7. CHECK Compressor A loads automatically. ___ SAT STANDARD: ___ UNSAT The applicant describes how to determine that air compressor "A" is loaded, by observing the loading solenoids, or by the sound changing at Compressor A.

CUE: When checked, state that the air compressor sound indicates that it has NOT loaded, state that air pressure is NOT rising (several local gauges), or, if both solenoids are checked to be magnetized, state that they are de-energized.

Applicant proceeds to RNO column after being cued to the failure of A compressor to load.

COMMENTS:

STEP 11: 7. RESPONSE NOT OBTAINED: CRITICAL STEP IF Compressor A does NOT Auto load, THEN PLACE 0-HS-32-43A and -43B to ON (Local 0-JB-291-226). ___ SAT STANDARD: ___ UNSAT Applicant locates and describes how to place 0-HS-32-43A and 0-HS-32-43B to the ON positions.

CUE: After hand switches have been placed to the ON position and when checked, state that the air compressor sound indicates that it has not loaded, the air pressure is dropping, or, if both solenoids are checked to be magnetized, state that they are de-energized.

COMMENTS:

PAGE 11 0F 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 12: 7. RESPONSE NOT OBTAINED: CRITICAL STEP IF Compressor A does NOT load from local panel, THEN:

___ SAT

a. CLOSE 0-ISV-32-578, STATION AIR COMPR A UNLOADING HDR ISOL. ___ UNSAT

b. VENT 0-TV-32-579, STATION AIR COMPR A UNLOADING HDR TEST.

STANDARD:

Applicant locates and describes how to close 0-ISV-32-578 by stating that the valve handwheel must be rotated clockwise.

CUE: After Valve 0-ISV-32-578 has been located and closed state that valve handwheel rotated clockwise until snug and valve stem moved into valve body.

Applicant locates and describes how to open 0-TV-32-579 by stating that the valve handwheel must be rotated counter-clockwise.

CUE: After Valve 0-TV-32-579 has been located and opened state that valve handwheel rotated counterclockwise until snug (state that air was heard venting from end of valve if asked).

The applicant indicates how to determine air compressor "A" is has loaded after 0-TV-32-579 is open.

CUE: IF asked and when checked state that the compressor sound indicated it has loaded and air pressure is rising.

Steps are critical to bleed air to force compressor to load.

COMMENTS:

PAGE 12 0F 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 13: 8. START Compressor B by pushing, 0-HS-32-26B. CRITICAL STEP STANDARD:

___ SAT Applicant locates and describes how to depress 0-HS-32-26B manual start push button. ___ UNSAT CUE: If JPM Step 7 was SAT, then when PB is depressed, if asked state that an air compressor start was heard. If JPM Step 7 was UNSAT, if asked, state that compressor start was not heard.

Step is critical to start air compressor.

COMMENTS:

STEP 14: 9. CHECK Compressor B loads automatically. ___ SAT STANDARD: ___ UNSAT The applicant describes how to determine that air compressor "B" is loaded, by observing the loading solenoids, or by the sound changing at Compressor "B".

CUE: When checked, state that the air compressor sound indicates that it has loaded or, if both solenoids are checked to be magnetized, state that they are energized.

COMMENTS:

PAGE 13 0F 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 15: 10. MONITOR Compressor operation: ___ SAT

• Oil press 25-30 psig on A, B, and C. ___ UNSAT

• Cooling water flow.

• Compressors auto-loading.

STANDARD:

Applicant locates oil pressure indicators (Compressor A, 0-PI-32-40; Compressor B, 0-PI-32-35) and states that oil pressure on both compressors should be 25-30 psig.

Applicant locates discharge drains and states that cooling water flow should be seen at the drain points.

Applicant determines from previous steps that Compressor A Compressors was manually loaded, and that Compressor B automatically loaded. Applicant states that Compressor C is shutdown due to the loss of power.

CUE: After the applicant has described the status of Compressor A and B, state that another operator will continue Attachment 1 performance from this point.

Applicant notifies the Unit Operator that AOI-10, Loss of Control Air, Attachment 1 Local Restart of C&SS Air Compressors is complete through Step 10.

COMMENTS:

END OF TASK STOP TIME ________

PAGE 14 0F 16

J Handout Package for Applicant PAGE 15 0F 16

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

1. A Station Blackout has occurred.

2. The Diesel Generators have started and are feeding the Shutdown Boards.

3. The Control and Service Air compressors were aligned normal with "C" air compressor in the lead prior to the Blackout.

4. A loss of Non-essential and Service air has occurred (Air pressure is at 75 psig decreasing).

5. Essential Air is being supplied by the Aux. Air compressors.

6. The 480V Auxiliary Building Common Board does not have voltage available on its normal or alternate supply.

7. Local control power is available to the air compressors.

8. You are a support AUO on shift.

INITIATING CUES:

The Unit Operator has dispatched you with a copy of Attachment 1 of 1-AOI-10 with instructions to perform steps 2 through 10.

Notify the Unit Operator when you have completed the task.

J

Watts Bar Nuclear Plant NRC EXAM 2013302 System JPM K

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K

NRC EXAM 2013-302 EVALUATION SHEET Task: TRANSFER 250V DC TURB BLDG DIST BD #1 FROM NORMAL TO ALTERNATE.

Alternate Path: n/a Facility JPM #: 3-OT-JPMA123 Safety Function: 6

Title:

Electrical System K/A 063 K4.02 Knowledge of DC electrical system design feature(s) and/ or interlock(s) which provide for the following: Breaker interlocks, permissives, bypasses and cross-ties.

Rating(s): 2.9/3.2 CFR: 41.7/45.5 to 45.8 Evaluation Method: Simulator X In-Plant Classroom

References:

SOI-239.01, 250V Battery Board 1, Rev. 15.

Task Number: AUO-239-SOI-239.1-08

Title:

Transfer a 250V DC Turbine Building Distribution Board.

Task Standard: The applicant transfers the 250V DC Turbine Building Distribution Board #1 from its Normal to Alternate supply per SOI-239.01, 250V Battery Board 1, Section 8.7.1, Transfer from Normal to Alternate.

Validation Time: 15 minutes Time Critical: Yes No X

===============================================================

Applicant: ___________________________ _________________ Time Start: ________

NAME Docket No. Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

==============================================================

COMMENTS PAGE 2 OF 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K

NRC EXAM 2013-302 Tools/Equipment/Procedures Needed:

Hard Hat, Gloves, Safety Glasses and Plant Approved Shoes.

Procedure SOI-239.01 Section 8.7.1, Transfer from Normal to Alternate.

References:

SOI-239.01, 250V Battery Board 1,Rev. 15.

PAGE 3 OF 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K

NRC EXAM 2013-302 READ TO APPLICANT DIRECTION TO APPLICANT:

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM.

SIMULATE ALL MANIPULATIONS I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating/operating cues. .When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure that you indicate to me when you fully understand your task. To indicate that you have completed your assigned task return the cue sheet I provided you. To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. The Unit is in MODE 5.

2. Maintenance is required that will cause 250V DC Battery Board #1 to be de-energized.

3. You are an AUO on shift.

INITIATING CUES:

You have been instructed to transfer the 250V DC Turbine Building Distribution Board #1 to its alternate supply per the SOI-239.01, Section 8.7.1.

Notify the Unit 1 US/SRO when the board has been transferred.

PAGE 4 OF 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT START TIME: _______

NOTE The Turbine Bldg Dist Bd will auto transfer on a complete loss of DC with no time delay, or if voltage drops to 188 volts for 4 seconds. Return to normal is manual only.

STEP 1: ((2] ENSURE 0-BKR-239-1A102, ALT SUPPLY FROM 250V ___ SAT BATTERY BD 2, closing springs charged. ___ UNSAT STANDARD:

\COMMENTS:

STEP 2: [3] CHECK at least 267 volts indicated on 250 V BATTERY ___ SAT BOARD 2 VOLTMETER on 0-DPL-239-1 250V DC TURB ___ UNSAT BLDG DIST BD 1.

STANDARD:

Applicant observes 250V BOARD 2 VOLTMETER on 0-DPL-239-1 and Voltage is verified to be at least 267 volts using 250V Battery Board 2 voltmeter.

CUE: Indicate 270 volts on 250V BOARD 2 VOLTMETER on 0-DPL-239-1.

COMMENTS:

PAGE 5 0F 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 3: [4] PLACE AUTO/MANUAL SUPPLY XFER SWITCH CS-101, to CRITICAL the MAN position. STEP STANDARD: ___ SAT Applicant locates CS-101 and indicates that the transfer switch must ___ UNSAT be rotated to the left to MAN position.

CUE: After applicant has demonstrated the proper positioning of CS-101, indicate that CS-101 is in MAN.

Step is critical to ensure that the transfer from Alternate to Normal can be accomplished.

COMMENTS:

STEP 4: [5] CLOSE and HOLD ALT SUPPLY FROM 250V BATTERY BD CRITICAL 2, control switch until transfer is complete. STEP STANDARD: ___ SAT Applicant locates ACB 102 and indicates that the breaker switch must be ___ UNSAT rotated to the right to the CLOSE position and held there UNTIL after the normal supply switch is placed in the TRIP position and transfer is verified.

Step is critical to ensure that the transfer from Alternate to Normal is accomplished without power interruption.

COMMENTS:

PAGE 6 0F 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 5: [6] PLACE NORM SUPPLY FROM 250V BATTERY BD 1, control CRITICAL switch in the TRIP position. STEP STANDARD: ___ SAT Applicant locates ACB 103 and indicates that the breaker switch must be ___ UNSAT rotated to the left to the TRIP position and HELD there UNTIL the transfer is verified.

Step is critical to ensure that the transfer from Alternate to Normal is accomplished without power interruption.

COMMENTS:

STEP 6: [7] ENSURE breakers transferred. ___ SAT STANDARD: ___ UNSAT Applicant ensures ACB 102 is closed (verbalizes that a RED target is expected on ACB 102) and ACB 103 is open (verbalizes that a GREEN target is expected on ACB 103.)

CUE: After checked, if asked confirm that ACB 102 has red target and ACB 103 has green target.

COMMENTS:

PAGE 7 0F 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 7: [8] VERIFY between 267 and 283 volts indicated on 250 V ___ SAT BATTERY BOARD 2 VOLTMETER on 0-DPL-239-1 250V DC ___ UNSAT TURBINE BLDG DISTRIBUTION BOARD 1.

STANDARD:

Applicant observes 250V BOARD 2 VOLTMETER on 0-DPL-239-1 and Voltage is verified to be at least 267 volts using 250V Battery Board 2 voltmeter.

CUE: Indicate 270 volts on 250V BOARD 2 VOLTMETER on 0-DPL-239-1.

Step is critical to ensure that sufficient voltage exists after transfer from Normal to Alternate.

COMMENTS:

STEP 8: [9] ENSURE AUTO/MANUAL SUPPLY XFER SWITCH CS-101, ___ SAT in MAN position. ___ UNSAT STANDARD:

Applicant ensures that CS-101 is in the MAN position, which is the position that was selected during Step 3 of the procedure.

COMMENTS:

PAGE 8 0F 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K

NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 9: Notify the Unit Supervisor that the transfer is complete. ___ SAT STANDARD: ___ UNSAT The US/SRO is notified that the transfer is complete.

CUE: Acknowledge the report using repeat back.

COMMENTS:

END OF TASK STOP TIME ________

PAGE 9 0F 10

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

1. The Unit is in MODE 5.

2. Maintenance is required that will cause 250V DC Battery Board #1 to be de-energized.

3. You are an AUO on shift.

INITIATING CUES:

You have been instructed to transfer the 250V DC Turbine Building Distribution Board #1 to its alternate supply per the SOI-239.01, Section 8.7.1.

Notify the Unit 1 US/SRO when the board has been transferred.

K