Text

Watts Bar 2013-302 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)
	v • d • e

{{#Wiki_filter:NRCExam2013 302SystemJPMA WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A NRC EXAM 2013-302 Page 2 of 10 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-3-156A, 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 WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A NRC EXAM 2013-302 Page 3 of 10 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 (rig ht 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 th e simulator.

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

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A NRC EXAM 2013-302 Event Description/Role Play Page 4 of 10 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. WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A NRC EXAM 2013-302 Page 5 of 10 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 perf ormed 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 u nderstand your assigned task. To indicate that you have comp leted 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 6 of 10 START TIME: _______ NOTES 1) One SG level LCV / Bypass Reg Valve control should be trans ferred 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 OPEN valves [1-M-3]: (NA valves NOT needed): [3.2] 1-LIC-3-48A, SG 2 MFW BYPASS REG CONTROL STANDARD: 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:

CRITICAL STEP ___ SAT ___ UNSAT

NOTE Aux Feedwater SG LCVs may be pl aced in MANUAL prior to 8.11[ 5] if required to maintain SG levels on program. WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 7 of 10 STEP 2: [4] ENSURE the following Aux Feedwa ter SG LCVs close as required to maintain SG le vels on program [1-M-4]: (N/A valves NOT needed) 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:

CRITICAL STEP ___ SAT ___ UNSAT

EXAMINER: Based on the NOTE preceding Step 4, the applicant may place 1-LIC-3-156A 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" contro l 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. WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 8 of 10 STEP 3: Applicant diagnoses the failu re of 1-LCV-3-156A OPEN, and attempts to regain co ntrol of the valve. STANDARD: Applicant locates 1-LIC-3-156A, SG 2 SUPPLY FRM PMP A-A, depresses the "M" pushbutton to trans fer 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:

___ SAT ___ UNSAT

STEP 4: Applicant determines that 1-LCV-3-156A has failed open, and determines that compensatory ac tions are required to terminate the level rise in SG 2. STANDARD: 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 posit ion, state that another operator will continue from here. Step is critical to terminate th e uncontrolled level rise in SG 2. COMMENTS: END OF TASK CRITICAL STEP ___ SAT ___ UNSAT

STOP TIME ________

A Handout Package for Applicant

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

NRCEXAM2013 302SystemJPMB WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2013-302 Page 2 of 23 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 WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2013-302 Page 3 of 23 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2013-302 Page 4 of 23 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2013-302 Page 5 of 23 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 communica tions. 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 signa

l. 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, Tran sfer to Containment Sump," beginning at Step 5.

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

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 6 of 23 START TIME: _______ STEP 1: 5. ENSURE automatic switchover complete:

a. ENSURE cntmt sump valves 1-FCV-63-72 and 1-FCV-63-73 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 va lve 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:

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 7 of 23 STEP 2: 5.a. RESPONSE NOT OBTAINED

IF ONE cntmt sump valve can NOT be fully opened, THEN STOP and PULL TO LOCK RHR pump on the associated train. STANDARD: Applicant locates 1-HS-74-20A, RHR PMP B (ECCS) and rotates the handswitch to the left to the ST OP 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:

CRITICAL STEP ___ SAT ___ UNSAT

STEP 3: 5. ENSURE automatic switchover complete:

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

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 8 of 23 STEP 4: 5. ENSURE automatic switchover complete:

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

STANDARD: Applicant determines from the IN ITIAL CONDITIONS that power has been restored to 1-FCV-63-1 during performance of 1-E-1, Appendix B. COMMENTS:

___ SAT ___ UNSAT

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%. STANDARD: Applicant locates 1-LI-63-50, RWST LEVEL, 1-LI-63-51, RWST LEVEL, 1-LI-63-52, RWST LEVE L and 1-LI-63-53, RWST LEVEL, and determines level is greater than 8%. COMMENTS:

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 9 of 23 STEP 6: 7. DETERMINE if cntmt spray should be stopped:

a. MONITOR cntmt press less than 2.0 psig.

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 pr essure is GREATER THAN 2 psig. COMMENTS:

___ SAT ___ UNSAT

STEP 7: 7.a. RESPONSE NOT OBTAINED

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

GO TO Step 8. STANDARD: Applicant acknowledges the cont inuous action step, and proceeds to Step 8. COMMENTS:

___ SAT ___ UNSAT

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

a. CHECK BOTH trains cntmt spray delivering flow.

STANDARD: Applicant observes 1-FI-72-34, CS PMP A FLOW and 1-FI-72-13, CS PMP B FLOW and determines bot h spray pumps are delivering flow. COMMENTS:

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 10 of 23 STEP 9: 8. DETERMINE if ONE train cntmt spray should be stopped:

b. RESET cntmt spray signal.

STANDARD: Applicant locates 1-HS-72-43 and depresses the pushbutton to RESET Train A CS signal. Applicant observes RED CS light DARK on 1-XX-55-6C,MASTER ISOLATION SIGNAL STATUS PANEL OR Applicant locates 1-HS-72-42 an d 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:

CRITICAL STEP ___ SAT ___ UNSAT

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

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

STANDARD: Applicant locates 1-HS-72-27A, CNTMT SPRAY PMP A and rotates the handswitch to the LEFT to t he 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 t he 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:

CRITICAL STEP ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 11 of 23 STEP 11: 8.a. RESPONSE NOT OBTAINED:

d. CLOSE spray discharge valve for stopped pump.

STANDARD: 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:

CRITICAL STEP ___ SAT ___ UNSAT

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

___ SAT ___ UNSAT

CAUTION If a valve fails during the transfer sequence, any correcti ve 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). WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 12 of 23 STEP 13: 10. (#1) ISOLATE SI pump miniflow:

CLOSE 1-FCV-63-3.
CLOSE 1-FCV-63-175.
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 closur e of the recirculation valves prevents radioactive sump water from being pumped to the

RWST. COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 13 of 23 STEP 14: 11. (#2) ISOLATE RHR crossties:

CLOSE 1-FCV-74-33.
CLOSE 1-FCV-74-35.

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 th e total system resistance is obtained should only one RHR pum p 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:

CRITICAL STEP ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 14 of 23 STEP 15: 12. (#3) ALIGN charging pump and SI pump supply from RHR:

OPEN 1-FCV-63-6.
OPEN 1-FCV-63-7.
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 ali gnment is required to support long-term cooling from the containment sump. COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

NOTE 1-FCV-63-8 and 1-FCV-63-11 are interlocked with the SI pump miniflows being full closed. WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 15 of 23 STEP 16: 13. (#4) ALIGN RHR discharge to charging pump and SI pump suction:

a. OPEN 1-FCV-63-8.

STANDARD: 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 ali gnment is required to support long-term cooling from the containment sump. COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

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

___ SAT ___ UNSAT WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 16 of 23 STEP 18: 13.b, RESPONSE NOT OBTAINED:

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.

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 det ermines 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:

___ SAT ___ UNSAT WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 17 of 23 STEP 19: 14. DO NOT CONTINUE this Instruction UNTIL Steps 10 thru 13 complete. STANDARD: Applicant determines that all steps or related contingency actions have been completed and c ontinues to Step 15. COMMENTS:

___ SAT ___ UNSAT

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 necessary. STANDARD: Applicant determines that all charging and SI pumps are running. COMMENTS:

___ SAT ___ UNSAT

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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 18 of 23 STEP 21: 16. (#5) RESET SI, and CHECK the following:

SI ACTUATED permissive DARK.
AUTO SI BLOCKED permissive LIT.

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:

CRITICAL STEP ___ SAT ___ UNSAT

STEP 22: 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. STANDARD: Applicant acknowledges information in the step, and since power has not been lost, continues to the next step.

COMMENTS:

___ SAT ___ UNSAT

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

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 19 of 23 STEP 23: 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).

STANDARD: Applicant pushes 1-HS-62-135 h andswitch in, and then rotates the handswitch to the left to the CLOSED position (Critical). Applicant identifies the valve is cl osed by observing the RED light is DARK and GREEN light is LIT. Applicant pushes 1-HS-62-136 h andswitch in, and then rotates the handswitch to the left to the CLOSED position (Critical). Applicant identifies the valve is cl osed 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:

CRITICAL STEP ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 20 of 23 STEP 24: 19. (#7) ISOLATE SI pump suction from RWST:

CLOSE 1-FCV-63-5.

STANDARD: Applicant rotates handswitch 1-HS 5A to the left to the CLOSED position (Critical). Applicant identifies the valve is cl osed 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:

CRITICAL STEP ___ SAT ___ UNSAT

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

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

b. CLOSE 1-FCV-63-1.

STANDARD: Applicant determines from the IN ITIAL CONDITIONS that power has been restored to 1-FCV-63-1, "RWST TO RHR ECCS SUCTION." Applicant rotates handswitch 1-HS 1A to the left to the CLOSED position (Critical). Applicant identifies the valve is cl osed 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:

CRITICAL STEP ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 21 of 23 STEP 26: Notify the Unit Supervisor that transfer to the RHR containment sump is complete. 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-F CV-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 containmen t spray RWST suction: COMMENTS: END OF TASK ___ SAT ___ UNSAT

STOP TIME ________ B

Handout Package for Applicant

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

l. 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, Tran sfer to Containment Sump," beginning at Step 5.

Notify the Unit Supervisor when transf er to the containment sump has been completed. 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 templa te. 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 st eps [PCR 3552] Added Note after transfer sequence to remind Operators FRs can be implemented.

WBN Unit 1 Transfer to Containment Sump ES-1.3 Rev. 0018 Page 2 of 25

1.0 PURPOSE

This Instruction provides actions for transferring ECCS and containment spray suction to the containment su mp 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 WBN Unit 1 Transfer to Containment Sump ES-1.3 Rev. 0018 Page 3 of 25 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 Instruct ion 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 RUNNING. IF NO RHR pumps can be started, THEN **GO TO ECA-1.1, Loss of RHR Sump Recirculation.

WBN Unit 1 Transfer to Containment Sump ES-1.3 Rev. 0018 Page 4 of 25 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 supply header and greater

than 5000 gpm.

Train A: 1-FI-70-159
Train B: 1-FI-70-165

c. WHEN transfer to cntmt sump completed, THEN REFER TO Appendix B (ES-1.3), 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 greater than or equal to 16.1 %.

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

WBN Unit 1 Transfer to Containment Sump ES-1.3 Rev. 0018 Page 5 of 25 Step Action/Expected Response Response Not Obtained

5. ENSURE automatic switchover complete:

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

OPEN. IF ONE cntmt sump valve can NOT be fully opened, 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-FC V-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 greater than 8%.

STOP and PULL TO LOCK pumps taking suction from the RWST. WBN Unit 1 Transfer to Containment Sump ES-1.3 Rev. 0018 Page 6 of 25 Step Action/Expected Response Response Not Obtained

7. DETERMINE if cntmt spray should be stopped:

a. MONITOR cntmt press less than 2.0 psig.

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

- GO TO Step 8. b. CHECK at least one cntmt spray pump RUNNING.

b. **GO TO Step 9. 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.

WBN Unit 1 Transfer to Containment Sump ES-1.3 Rev. 0018 Page 7 of 25 Step Action/Expected Response Response Not Obtained

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

a. CHECK BOTH trains cntmt spray delivering flow.

a. **GO TO Step 9. 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 1350 psig.

STOP both SI pumps. WBN Unit 1 Transfer to Containment Sump ES-1.3 Rev. 0018 Page 8 of 25 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:

CLOSE 1-FCV-63-3.
CLOSE 1-FCV-63-175.
CLOSE 1-FCV-63-4. ENSURE either: a. 1-FCV-63-3 CLOSED, OR b. 1-FCV-63-4 and 1-FCV-63-175 CLOSED. 11. (#2) ISOLATE RHR crossties:
CLOSE 1-FCV-74-33.
CLOSE 1-FCV-74-35. ENSURE either 1-FCV-74-33 or 1-FCV-74-35 CLOSED. 12. (#3)

ALIGN charging pump and SI pump supply from RHR:

OPEN 1-FCV-63-6.
OPEN 1-FCV-63-7.
ENSURE 1-FCV-63-177 OPEN. ENSURE either 1-FCV-63-6 or 1-FCV-63-7 OPEN.

WBN Unit 1 Transfer to Containment Sump ES-1.3 Rev. 0018 Page 9 of 25 Step Action/Expected Response Response Not Obtained NOTE 1-FCV-63-8 and 1-FCV-63-11 are in terlocked 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.

WBN Unit 1 Transfer to Containment Sump ES-1.3 Rev. 0018 Page 10 of 25 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 following:

SI ACTUATED permissive DARK.
AUTO SI BLOCKED permissive LIT. NOTIFY IMs to block Auto SI USING IMI-99.040, Auto SI Block.

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.

WBN Unit 1 Transfer to Containment Sump ES-1.3 Rev. 0018 Page 11 of 25 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-FC V-63-1 Breaker Operation.

b. CLOSE 1-FCV-63-1.

WBN Unit 1 Transfer to Containment Sump ES-1.3 Rev. 0018 Page 12 of 25 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 less than 8%.

b. WHEN RWST level 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.

WBN Unit 1 Transfer to Containment Sump ES-1.3 Rev. 0018 Page 13 of 25 Step Action/Expected Response Response Not Obtained

22. ENSURE ERCW aligned for sump recirc operation:

REFER TO Appendix C (ES-1.3), ERCW Operation. CONSULT TSC for ERCW limitations.

23. ALIGN cntmt spray sump suction:

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

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

24. MONITOR cntmt press less than 2.0 psig. INITIATE cntmt spray: 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.

WBN Unit 1 Transfer to Containment Sump ES-1.3 Rev. 0018 Page 14 of 25 Step Action/Expected Response Response Not Obtained CAUTION Continued ECCS or Containment Spray pump operation following loss of suction will re sult in pump damage. Loss of suction to RHR pumps will re quire 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 cavitation on ECCS or

Containment Spray.

b. **GO TO Note prior to Step 27.

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

WBN Unit 1 Transfer to Containment Sump ES-1.3 Rev. 0018 Page 15 of 25 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 was entered from E-1. CONSULT TSC for guidance on when to transfer to hot leg

recirculation (ES-1.4).

28. RETURN TO Instruction in effect.

End of Section

WBN Unit 1 Transfer to Containment Sump ES-1.3 Rev. 0018 Page 16 of 25 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 MOV Board 1A1-A 2E1 1-BKR-63-1A RWST TO RHR SUCT (1-FCV-63-1)

WBN Unit 1 Transfer to Containment Sump ES-1.3 Rev. 0018 Page 17 of 25 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 Shut down 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.

WBN Unit 1 Transfer to Containment Sump ES-1.3 Rev. 0018 Page 18 of 25 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. WBN Unit 1 Transfer to Containment Sump ES-1.3 Rev. 0018 Page 19 of 25 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. Th is step should be repeat ed 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) or 91B (WR)] NR or WR Flow to CL 1 & 4 [1-FI-63-92A (NR) or 92B (WR)] NR or 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)

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

1.0 INSTRUCTIONS

(continued) Page 20 of 25 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)

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

1.0 INSTRUCTIONS

(continued) Page 21 of 25 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 m onitoring 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 [1-FI-63-91A (NR) or 91B (WR)] NR or WR Pump flow to CL 1 & 4 [1-FI-63-92A (NR) or 92B (WR)] NR or WR Pump A Discharge Press (1-PI-74-13) Pump B Discharge Press (1-PI-74-26)

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

1.0 INSTRUCTIONS

(continued) Page 22 of 25 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 (flow/amps/discharge press) Erratic or gradually dropping (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.

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

1.0 INSTRUCTIONS

(continued) Page 23 of 25 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 th e 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 WBN Unit 1 Transfer to Containment Sump ES-1.3 Rev. 0018 Appendix D (Page 6 of 7)

Monitoring for Containment Sump Blockage

1.0 INSTRUCTIONS

(continued) Page 24 of 25 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)

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

1.0 INSTRUCTIONS

(continued) Page 25 of 25 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)

NRCEXAM2013 302SystemJPMC WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C NRC EXAM 2013-302 Page 2 of 20 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 t he N43 position to the OPERATE position:

a. ROD STOP BYPASS,

b. POWER MISMATCH BYPASS. 3.) Performs actions of SOI-98.01, "DIS TRIBUTED 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 WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C NRC EXAM 2013-302 Page 3 of 20 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C NRC EXAM 2013-302 Page 4 of 20 READ TO APPLICANT

DIRECTION TO APPLICANT: I will explain the initial conditions, and state t he 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 ac tions when directed by you. Ensure you indicate to me when you understand your assi gned 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 5 of 20 START TIME: _______ STEP 1: 16. WHEN PRM is to be restored, THEN: 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.

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

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 6 of 20 EXAMINER: The following actions are taken from 1-AOI-4, "Nuclear Instrumentation Malfunctions," Attachment 3, "Def eat N-43 PRM Functions At NIS Rack." STEP 2: 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.

STANDARD: Detector Current Comparator U pper 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:

CRITICAL STEP ___ SAT ___ UNSAT

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

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

STANDARD: Detector Current Comparator Low er 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:

CRITICAL STEP ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 7 of 20 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 the following Steps:

3. PLACE ROD STOP BYPASS switch in OPERATE.

STANDARD: Rod Stop Bypass switch is positi oned 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:

CRITICAL STEP ___ SAT ___ UNSAT

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

4. PLACE POWER MISMATCH BYPASS switch in OPERATE.

STANDARD: 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:

CRITICAL STEP ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 8 of 20 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 the following Steps:

5. PLACE COMPARATOR CHANNEL DEFEAT switch in NORMAL. 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:

CRITICAL STEP ___ SAT ___ UNSAT

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

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 9 of 20 STEP 7: B. WHEN PRM is ready for return to service, THEN PERFORM the following Steps:

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

STANDARD: Positive Rate Trip light on Po wer Range Upper N41A, 1-IDWR 42A II, is checked and determines light is NOT LIT and continues to

next step. COMMENTS:

___ SAT ___ UNSAT

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

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:

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 10 of 20 EXAMINER: The following actions are t aken from 1-SOI-98.01, "DISTRIBUTED CONTROL SYSTEM," Section 8.7, "Restori ng Instrument Loop After Auto or Manual Bypass." NOTE This section is Continuous Use. STEP 9: [1] RECORD instrument(s) to be RESTORED. Instrument UNID(s): _______________________ STANDARD: Applicant enters 1LPY0920412R as the instrument to be restored. COMMENTS:

___ SAT ___ UNSAT

STEP 10: [2] NOTIF Y SRO of instrument to be RESTORED. STANDARD: Applicant informs the Unit Supervisor/Examiner that 1LPY0920412R will be restored. COMMENTS:

___ SAT ___ UNSAT

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".

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 11 of 20 STEP 11: [3] IF instrument has redundant channels on 1-XX-55-6B, RX Trip - Status Panel, THEN ENSURE bistable windows for redundant instrument channels on 1-XX-55-6B, RX Trip - Status Panel are NOT LIT. STANDARD: Applicant determines that no bi stable windows are lit on 1-XX 6B, RX Trip - Status Panel. COMMENTS:

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

___ SAT ___ UNSAT

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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 12 of 20 STEP 13: [5] IF reducing SG Level perturbations, THEN PERFORM Section 8.1 to FORCE 1 ELEMENT CONTROL. STANDARD: Applicant determines that SG leve l perturbations are not occurring and enters "N/A" for the step. COMMENTS:

___ SAT ___ UNSAT

STEP 14: [6] SELECT Display Screen for instrument loop to be RESTORED (Ref. App. A or use BYPASSED

TRANSMITTERS screen). STANDARD: Applicant selects "BYPASSED TRANSMITTERS" screen on the DCS computer terminal. COMMENTS:

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 13 of 20 STEP 15: [7] SELECT data point for instrument recorded in Step 8.7[1]. STANDARD: Applicant selects 1LPY0920412R, which currently is displayed with a yellow "BYPASSED" tag. Step is critical to restore the correct device to service. COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

STEP 16: [8] IF instrument is displayed with its MAINT BYP SIGNAL button indicating BYPASSED (red), THEN [8.1] SELECT MAINT BYP SIGNAL button for instrument loop. [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:

CRITICAL STEP ___ SAT ___ UNSAT WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 14 of 20 STEP 17: [9] SELECT RESTORE SIGNAL button. STANDARD: Applicant locates the RESTORE SIGNAL D button, and selects the button with the cursor, t hen "clicks" on the button. Step is critical to restore channel input to SG level program circuits. COMMENTS:

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

status change. STANDARD: Applicant observes the yellow BYP indication no longer appears above 1LPY0900412R. COMMENTS:

___ SAT ___ UNSAT

NOTE When instrument is BYPASSED, XMTR BYP will be displayed in yellow on the overlay screen for that instrument. WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 15 of 20 STEP 19: [11] IF ALL FW (feedwater) instruments have been restored, THEN CHECK XMTR BYP is NOT displayed in yellow for the associated instrument (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:

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

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 16 of 20 STEP 21: [13] IF action due to IM request, THEN NOTIFY IM instrument channel is RESTORED.

STANDARD: Applicant determines that step is not applicable, and marks the step "N/A." COMMENTS:

___ SAT

___ UNSAT

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

STANDARD: Applicant monitors SG 3 level for possible perturbations and

determines that none are occurring.

COMMENTS:

___ SAT

___ UNSAT

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

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

COMMENTS:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 17 of 20 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: c. ENSURE TAVG and TREF within 1°F.

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

COMMENTS:

___ SAT

___ UNSAT

STEP 25: 16. WHEN PRM is to be restored, THEN. d. ENSURE zero demand on control rod position indication [1-M-4].

STANDARD: Applicant determines that there is zero demand on CERPI

MONITOR 1 or 2 PASSIVE SU MMER DEMAND INDICATORS, COMMENTS:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 18 of 20 STEP 26: 16. WHEN PRM is to be restored, THEN: e. IF auto rod control desired, PLACE control rods in 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 ___ SAT

___ UNSAT

STOP TIME ________

C

Handout Package for Applicant APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) C 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.

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 Unit 1 Nuclear Instrumentation Malfunctions 1-AOI-4 Rev. 0000 Page 2 of 37 Revision Log Revision or Change Number Effective Date Affected Page 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 T AVG vs Tave and T REF.
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.

WBN Unit 1 Nuclear Instrumentation Malfunctions 1-AOI-4 Rev. 0000 Page 3 of 37

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 GENERATE D 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 CO NTROL 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].

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

2.2 Indications

(continued) Page 4 of 37 B. Intermediate Range Monitor (IRM) malfunction: 1. Erratic or loss of indication.

2. INSTRUMENT POWER ON and/or CO NTROL 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 INST RUMENT POWER ON lights at NIS racks DARK [1-M-13]. 2.3 Automatic Actions A. Source Range Monitor failure: 1. Possible source range monito r high flux Rx trip at 10 5 cps if SRM NOT blocked. 2. Possible Cntmt evacuation ala rm 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 in termediate range monitor greater than 1.66 X 10-4% power and intermediate range monitor fails low.

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

2.3 Automatic

Actions (continued) Page 5 of 37 C. Power Range Monitor failure: 1. Possible 103% power rod stop.

2. Possible actuation or lo ss of P-8, P-9, or P-10. 3. Temporary rod insertion if c hannel fails high with rods in AUTO.

WBN Unit 1 Nuclear Instrumentation Malfunctions 1-AOI-4 Rev. 0000 Page 6 of 37

3.0 OPERATOR

ACTIONS

3.1 Diagnostics

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

3.2 Source

Range Monitor (SRM) Failure (continued) Page 8 of 37 Step Action/Expected Response Response Not Obtained 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

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

3.2 Source

Range Monitor (SRM) Failure (continued) Page 9 of 37 Step Action/Expected Response Response Not Obtained

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

CHECK audio count rate audible in control room.
PLACE audio count rate 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 in control room.
IF audible audio count rate is NOT 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 in Cntmt.

IF audible audio count rate is NOT 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.

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

3.2 Source

Range Monitor (SRM) Failure (continued) Page 10 of 37 Step Action/Expected Response Response Not Obtained

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.

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

3.2 Source

Range Monitor (SRM) Failure (continued) Page 11 of 37 Step Action/Expected Response Response Not Obtained

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 WBN Unit 1 Nuclear Instrumentation Malfunctions 1-AOI-4 Rev. 0000 Page 12 of 37 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 Instrument ation 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.

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

3.3 Intermediate

Range Monitor (IRM) Failure (continued) Page 13 of 37 Step Action/Expected Response Response Not Obtained

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 WBN Unit 1 Nuclear Instrumentation Malfunctions 1-AOI-4 Rev. 0000 Page 14 of 37 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.

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

3.4 Power

Range Monitor (PRM) Failure (continued) Page 15 of 37 Step Action/Expected Response Response Not Obtained NOTE Control rod withdrawal may NOT be possible if a PRM has failed high due to the 103% Rod Withdr awal Stop (C-2) until PRM is defeated. (Annunciator window 83-A).

4. MAINTAIN T AVG and T REF 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.

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

3.4 Power

Range Monitor (PRM) Failure (continued) Page 16 of 37 Step Action/Expected Response Response Not Obtained NOTE Inputs to 1-TR-68-2A include po wer range monitor, pressurizer pressure, T and T AVG. 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., T AVG , T REF, or NIS) changes and placing rods in AUTO, will help prevent undesired control rod movement.

9. WHEN AUTO rod control desired, THEN: a. ENSURE T AVG and T REF within 1°F. b. ENSURE zero demand on control rod position indication [1-M-4].

c. PLACE control rods in AUTO.

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

3.4 Power

Range Monitor (PRM) Failure (continued) Page 17 of 37 Step Action/Expected Response Response Not Obtained

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, THEN CHECK lights and alarms referenced in Appendix A are LIT.

CONTACT Work Control to have IMs immediately troubleshoot the problem.

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 lights and associated alarms in

Appendix A are CLEAR. NOTIFY Work Control to have IM troubleshoot problem. ENSURE trip status lights DARK before continuing this Instruction.

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

3.4 Power

Range Monitor (PRM) Failure (continued) Page 18 of 37 Step Action/Expected Response Response Not Obtained CAUTION Allowing at least 5 minutes between any rod control input (i.e., T AVG , T REF , 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 re turning 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 T AVG and T REF 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 WBN Unit 1 Nuclear Instrumentation Malfunctions 1-AOI-4 Rev. 0000 Page 19 of 37

4.0 DISCUSSION

4.1 Source Range Failure SRM channels N131 & N132 are block ed 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 fa ils high, Rx will trip at 10 5 cps unless the SRM trip is blocked. Audi o 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 ti mes 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 erra tic. One of two IRMs indicating greater than 25% power (and NOT blocked) will cause an Rx trip. WBN Unit 1 Nuclear Instrumentation Malfunctions 1-AOI-4 Rev. 0000 Page 20 of 37

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 hi gh 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 fo r 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 T AVG/T REF matched within 1 °F, rod movement could occur when the rods are returned to AUTO if rod control inputs change wh ile rods were in MANUAL.

Decay time for T AVG lead/lag modules is approximately 3 minutes.
Decay time for T REF lead/lag modules and NIS lead/lag modules is approximately 5 minutes.

Allow at least 5 minutes between any c hange to rod control inputs (i.e., T AVG , T REF , 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. WBN Unit 1 Nuclear Instrumentation Malfunctions 1-AOI-4 Rev. 0000 Page 21 of 37

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, Distri buted Control System. 5.2 Developmental A. IMI-160.001, Removal of Reactor Prot ection System Channel I From Service. B. IMI-160.002, Removal of Reactor Prot ection System Channel II From Service. C. IMI-160.003, Removal of Reactor Prot ection System Channel III From Service. D. IMI-160.004, Removal of Reactor Protec tion System Channel IV From Service. 5.3 Technical Specifications (Tech Specs) A. 3.3.1, Reactor Trip Syst em (RTS) Instrumentation. B. 3.3.3 Post Accident M onitoring (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.

WBN Unit 1 Nuclear Instrumentation Malfunctions 1-AOI-4 Rev. 0000 Page 22 of 37 Appendix A (Page 1 of 4) Power Range Failure N41 Power Range Failure COMPARATOR R PANEL STATUS LIGHT ANNUNCIATOR TB-411C (overtemp delta t trip) R-2 [1-XX-55-5, window 10] LOOP 1 OTT TRIP TS-68-2D [123-C] OVERTEMP T TRIP ALERT TB-411D (overtemp turb rbk & blk rod

withdrawal) R-2 [1-XX-55-5, window 15] LOOP 1 OTT RUN BACK TS-68-2E [123-D] OVERTEMP T TURB RUNBACK & C-3 ROD BLOCK N/A 1-M-13 when fuses pulled [1-XX-55-5, window 7] PR FLUX HI NC41R [115-C] POWER RANGE FLUX HI N/A 1-M-13 when fuses pulled [1-XX-55-5, window 8] PR HI RATE NC41U/K [115-E] POWER RANGE FLUX RATE HI WBN Unit 1 Nuclear Instrumentation Malfunctions 1-AOI-4 Rev. 0000 Appendix A (Page 2 of 4) Power Range Failure Page 23 of 37 N42 Power Range Failure COMPARATOR R PANEL STATUS LIGHT ANNUNCIATOR TB-421C (overtemp delta t trip) R-6 [1-XX-55-5, window 30] LOOP 2 OTT TRIP TS-68-25D [123-C] OVERTEMP T TRIP ALERT TB-421D (overtemp turb rbk & blk rod

withdrawal) R-6 [1-XX-55-5, window 35] LOOP 2 OTT RUN BACK TS-68-25E [123-D] OVERTEMP T TURB RUNBACK & C-3 ROD BLOCK N/A 1-M-13 when fuses pulled [1-XX-55-5, window 27] PR FLUX HI NC42R [115-C] POWER RANGE FLUX HI N/A 1-M-13 when fuses pulled [1-XX-55-5, window 28] PR HI RATE NC42U/K [115-E] POWER RANGE FLUX RATE HI WBN Unit 1 Nuclear Instrumentation Malfunctions 1-AOI-4 Rev. 0000 Appendix A (Page 3 of 4) Power Range Failure Page 24 of 37 N43 Power Range Failure COMPARATOR R PANEL STATUS LIGHT ANNUNCIATOR TB-431C (overtemp delta t trip) R-10 [1-XX-55-5, window 50] LOOP 3 OTT TRIP TS-68-44D [123-C] OVERTEMP T TRIP ALERT TB-431D (overtemp turb rbk & blk rod

withdrawal) R-10 [1-XX-55-5, window 55] LOOP 3 OTT RUN BACK TS-68-44E [123-D] OVERTEMP T TURB RUNBACK & C-3 ROD BLOCK N/A 1-M-13 when fuses pulled [1-XX-55-5, window 47] PR FLUX HI NC43R [115-C] POWER RANGE FLUX HI N/A 1-M-13 when fuses pulled [1-XX-55-5, window 48] PR HI RATE NC43U/K [115-E] POWER RANGE FLUX RATE HI WBN Unit 1 Nuclear Instrumentation Malfunctions 1-AOI-4 Rev. 0000 Appendix A (Page 4 of 4) Power Range Failure Page 25 of 37 N44 Power Range Failure COMPARATOR R PANEL STATUS LIGHT ANNUNCIATOR TB-441C (overtemp delta t trip) R-13 [1-XX-55-5, window 70] LOOP 4 OTT TRIP TS-68-67D [123-C] OVERTEMP T TRIP ALERT TB-441D (overtemp turb rbk & blk rod

withdrawal) R-13 [1-XX-55-5, window 75] LOOP 4 OTT RUN BACK TS-68-67E [123-D] OVERTEMP T TURB RUNBACK & C-3 ROD BLOCK N/A 1-M-13 when fuses pulled [1-XX-55-5, window 67] PR FLUX HI NC44R [115-C] POWER RANGE FLUX HI N/A 1-M-13 when fuses pulled [1-XX-55-5, window 68] PR HI RATE NC44U/K [115-E] POWER RANGE FLUX RATE HI

WBN Unit 1 Nuclear Instrumentation Malfunctions 1-AOI-4 Rev. 0000 Page 26 of 37 Attachment 1 (Page 1 of 3) Defeat N-41 PRM Func tion 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.

WBN Unit 1 Nuclear Instrumentation Malfunctions 1-AOI-4 Rev. 0000 Attachment 1 (Page 2 of 3) Defeat N-41 PRM Func tion At NIS Rack

1.0 INSTRUCTIONS

(continued) Page 27 of 37 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 1 15-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 Bypa ss using DCS Operator Display: a. SELECT "BYPASSED TRANSM ITTERS" 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.

WBN Unit 1 Nuclear Instrumentation Malfunctions 1-AOI-4 Rev. 0000 Attachment 1 (Page 3 of 3) Defeat N-41 PRM Func tion At NIS Rack

1.0 INSTRUCTIONS

(continued) Page 28 of 37 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 1 15-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.

WBN Unit 1 Nuclear Instrumentation Malfunctions 1-AOI-4 Rev. 0000 Page 29 of 37 Attachment 2 (Page 1 of 3) Defeat N-42 PRM Func tion 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.

WBN Unit 1 Nuclear Instrumentation Malfunctions 1-AOI-4 Rev. 0000 Attachment 2 (Page 2 of 3) Defeat N-42 PRM Func tion At NIS Rack

1.0 INSTRUCTIONS

(continued) Page 30 of 37 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 1 15-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 Bypa ss using DCS Operator Display: a. SELECT "BYPASSED TRANSM ITTERS" 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.

WBN Unit 1 Nuclear Instrumentation Malfunctions 1-AOI-4 Rev. 0000 Attachment 2 (Page 3 of 3) Defeat N-42 PRM Func tion At NIS Rack

1.0 INSTRUCTIONS

(continued) Page 31 of 37 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 1 15-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.

WBN Unit 1 Nuclear Instrumentation Malfunctions 1-AOI-4 Rev. 0000 Page 32 of 37 Attachment 3 (Page 1 of 3) Defeat N-43 PRM Func tion 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.

WBN Unit 1 Nuclear Instrumentation Malfunctions 1-AOI-4 Rev. 0000 Attachment 3 (Page 2 of 3) Defeat N-43 PRM Func tion At NIS Rack

1.0 INSTRUCTIONS

(continued) Page 33 of 37 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 1 15-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 Bypa ss 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.

WBN Unit 1 Nuclear Instrumentation Malfunctions 1-AOI-4 Rev. 0000 Attachment 3 (Page 3 of 3) Defeat N-43 PRM Func tion At NIS Rack

1.0 INSTRUCTIONS

(continued) Page 34 of 37 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 1 15-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.

WBN Unit 1 Nuclear Instrumentation Malfunctions 1-AOI-4 Rev. 0000 Page 35 of 37 Attachment 4 (Page 1 of 3) Defeat N-44 PRM Func tion 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.

WBN Unit 1 Nuclear Instrumentation Malfunctions 1-AOI-4 Rev. 0000 Attachment 4 (Page 2 of 3) Defeat N-44 PRM Func tion At NIS Rack

1.0 INSTRUCTIONS

(continued) Page 36 of 37 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 1 15-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 Bypa ss 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.

WBN Unit 1 Nuclear Instrumentation Malfunctions 1-AOI-4 Rev. 0000 Attachment 4 (Page 3 of 3) Defeat N-44 PRM Func tion At NIS Rack

1.0 INSTRUCTIONS

(continued) Page 37 of 37 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 1 15-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.

NRCEXAM2013 302SystemJPMD WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D NRC EXAM 2013-302 Page 2 of 14 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 WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D NRC EXAM 2013-302 Page 3 of 14 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D NRC EXAM 2013-302 Page4 of 14 READ TO APPLICANT

DIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be per formed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and repor ts 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page5 of 14 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 h as been provided the REACTW sheet for the level increase to 27%. STEP 1: [1] PERFORM Appendix C, Calculation Of Boric Acid And Primary Water Integrator Setting For Manual Makeup OR 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 R EACTW printout provided. COMMENTS:

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page6 of 14 STEP 2: [2] PLACE controllers in MANUAL, AND CLOSE the following: [2.1] 1-FC-62-139, BA TO BLENDER.

[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: ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page7 of 14 STEP 3: [3] ADJUST Batch Counters for the desired quantity of boric acid and primary water using val ues from Appendix B or C: [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 pus hbutton, 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 a fter the red translucent cover is lowered remained at "000012."

The applicant locates 1-FQ 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 pus hbutton, 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 a fter the red translucent cover is lowered remained at "000085."

COMMENTS:

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page8 of 14 STEP 4: [4] PLACE 1-HS-62-140B, VCT MAKEUP MODE, in MAN. STANDARD: Applicant locates 1-HS-62-140B, VCT MAKEUP MODE, and determines that the handswitch is in the MAN position. COMMENTS:

___ SAT ___ UNSAT

STEP 5: [5] TURN 1-HS-62-140A, VCT MAKEUP CONTROL, to START, [5.1] CHECK Red light is LIT. STANDARD: Applicant locates 1-HS-62-140A, VCT MAKEUP CONTROL and rotates 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 acti on is required to initiate manual makeup. COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

NOTE When blending to VCT through 1-FCV-62-128, Chemistry c annot get a r epresentative 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-62-140D, BA TO BLENDER will fail OPEN; and 1-FC-62-139, BA TO BL ENDER FCV-62-140 CONTROL will fail. This combination of malfunctions will require the appli cant to stop the boric acid pumps to terminate the boration.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page9 of 14 STEP 6: [6] IF Borating OR Blending, THEN PERFORM the following: [6.1] OPEN 1-FCV-62-128, MAKEUP TO VCT INLET, OR 1-FCV-62-144, MAKEUP TO VCT OUTLET. STANDARD: 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:

CRITICAL STEP ___ SAT ___ UNSAT

EXAMINER: The applicant may stop the boric acid transfer pumps prior to entry into AOI-3, "Malfunction of React or Makeup Controls." TI-12.04, User's Guide For Abnormal And Em ergency Operating Instructions," states "Operators are expected to take manual c ontrol 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, "Mal function of Reactor Makeup Controls."

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page10 of 14 STEP 7: 1. ENSURE 1-FCV-62-138, Emerg Borate, CLOSED. STANDARD: 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:

___ SAT ___ UNSAT

STEP 8: 2. CHECK 1-FI-62-137A, Emerg Borate Flow, ZERO. STANDARD: Applicant locates and observes zero flow on 1-FI-62-137A, EMER BORATE FLOW. COMMENTS:

___ SAT ___ UNSAT

STEP 9: 3. CHECK VCT level greater than 20%:

1-LI-62-129A.

STANDARD: Applicant locates and observes VCT level approximately 27% on 1-LI-62-129A, VCT LEVEL. COMMENTS:

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page11 of 14 STEP 10: 4. CHECK VCT aligned to charging pump suction:

1-LCV-62-132 OPEN.
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: ___ SAT ___ UNSAT

STEP 11: 5. CHECK 1-FI-62-139, BA To Blender Flow, ZERO. STANDARD: Applicant locates and observes zero flow on 1-FI-62-137A, EMER BORATE FLOW. COMMENTS:

___ SAT ___ UNSAT

STEP 12: 6. ENSURE 1-FCV-62-140, Boric Acid To Blender, CLOSED. STANDARD: Applicant locates and determines that 1-HS-62-140D, BA TO BLENDER is OPEN by the RED light LIT and GREEN light DARK. COMMENTS:

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page12 of 14 STEP 13: [6] RESPONSE NOT OBTAINED STOP boric acid transfer pumps. 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 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 te rminates 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 CRITICAL STEP ___ SAT ___ UNSAT

STOP TIME ________

D Handout Package for Applicant APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) D 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.

NRCEXAM2013 302SystemJPME WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E NRC EXAM 2013-302 Page 2 of 10 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: S imulator X In-Plant P erform X S imulate 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 WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E NRC EXAM 2013-302 Page 3 of 10 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 availabl e for each applicant.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E NRC EXAM 2013-302 Page 4 of 10 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 5 of 10 START TIME: _______ STEP 1: [1] OBTAIN SRO approval. STANDARD: Applicant observes that SRO appr oval has already been granted by initials in Step 1. COMMENTS:

___ SAT ___ UNSAT

STEP 2. [2] ENSURE MSB has verified Time Delay Relay (TDR) 1 068- 0009 contact points 1 and 5 closed (located on left side panel in compartment 1A2 of RCP BD 1A). 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:

___ SAT ___ UNSAT

NOTE IF Unit is out of service, Bd may be energized by backfeeding from USSTs. WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 6 of 10 STEP 3: [3] CHECK voltage 6560 to 7260V to Normal ACB 2112 on 1-EI-57-57, USST 1A VOLTS [1-M-1]. STANDARD: Applicant reads voltage approx imately 7200V to Normal ACB 2112 on 1-EI-57-57, USST 1A VOLTS, on Panel 1-M-1. COMMENTS:

___ SAT ___ UNSAT

STEP 4: [4] ENSURE 1-HS-68-8AA, RCP 1 NORMAL BKR & LIFT PMP[1-M-5], PUSHED IN to place handswitch in control of ACB 2112. STANDARD: 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:

CRITICAL STEP ___ SAT ___ UNSAT

STEP 5: [5] ENSURE 1-HS-68-8BA, RCP 1 ALTERNATE BKR & XFER SELECTOR [1-M-5], PUSHED IN to place ACB 2522 auto transfer in MANUAL. STANDARD: 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:

CRITICAL STEP ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 7 of 10 STEP 6: [6] MONITOR 1-EI-68-8A, RCP 1 AMPS [1-M-5] during transfer to ensure RCP Amp load transfers to Normal supply. STANDARD: Applicant locates 1-EI-68-8A, RCP 1 AMPS and observes approximately 440 amps. COMMENTS:

___ SAT ___ UNSAT

CAUTION Release handswitches SLOWLY after transfer is complete to prevent inadvertent breaker actuation. STEP 7: Start of Critical Step(s) [7] PLACE AND HOLD 1-HS-68-8AA, RCP 1 NORMAL BKR & LIFT PMP, in START, AND PLACE 1-HS-68-8BA, RCP 1 ALTERNATE BKR & XFER SELECTOR, in STOP. End of Critical Step(s) STANDARD: ___Applicant acknowledges that this is a "two-handed" evolut ion. 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:

CRITICAL STEP ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 8 of 10 STEP 8: [8] ENSURE Normal ACB 2112 CLOSED, and Alt ACB 2522 OPEN. STANDARD: Applicant determines from the handswitches that the Normal ACB 2112 is CLOSED, and Alternate ACB 2522 is OPEN. COMMENTS: ___ SAT ___ UNSAT STEP 9: [9] IF desired to place Board Transfer in AUTO, THEN PULL 1-HS-68-8BA, RCP 1 AL TERNATE BKR & XFER SELECTOR switch, out to PULL AUTO. 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 ___ SAT ___ UNSAT STOP TIME ________ Page 9 of 10 E

Handout Package for Applicant

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

NRCExam2013 302SystemJPMF WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F NRC Exam 2013-302 Page 2 of 17 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 WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F NRC Exam 2013-302 Page 3 of 17 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F NRC Exam 2013-302 Page 4 of 17

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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F NRC Exam 2013-302 Page 5 of 17 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F NRC Exam 2013-302 Page 6 of 17 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 communica tions. 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 Cooli ng Water (CCS)," Sect ion 3.2, Loss of CCS Flow," has been performed.

3. The Unit Supervisor has evaluate d PRA Risk, Reactor Trip Risk and Applicable Tech Spec LCOs.

4. You are the Control Room Operator.

INITIATING CUES: The Unit Supervisor directs you perf orm 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F NRC Exam 2013-302 STEP/STANDARD SAT/UNSAT Page 7 of 17 START TIME: _______ STEP 1: [2] ENSURE Pump 1B-B, NOT in service. STANDARD: Applicant locates.1-HS-70-38A, CCS PMP 1B-B, and determines that the RED light is DARK and the GREEN light is LI T, indicating that the pump is STOPPED. COMMENTS: ___ SAT ___ UNSAT

STEP 2: [3] PLACE 1-HS-70-38A, CCS PMP 1B-B, in the STOP /PULL-TO-LOCK position. STANDARD: Applicant locates.1-HS-70-38A, CCS PMP 1B-B, and rotates the handswitch to the STOP position, t hen pulls the handswitch out to the PULL-TO-LOCK position. (Critical). Step is critical to prevent dama ge to the 1B-B CCS Pump during valve realignments. COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F NRC Exam 2013-302 STEP/STANDARD SAT/UNSAT Page 8 of 17 STEP 3: [4] PLACE the following breakers to ON: STANDARD: Applicant contacts the Console Operator and directs the Console Operator (as an AUO) to plac e the listed breakers to "ON." (Critical). Step is critical to apply power to deenergized valves to allow for alignments. COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

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]. WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F NRC Exam 2013-302 STEP/STANDARD SAT/UNSAT Page 9 of 17 STEP 4: [5] CLOSE the following valves: 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 Consol e Operator and requests that 1-ISV-70-507, CCS PMP 1A-A/1B-B DIS CHARGE CROSSTIE be CLOSED. Console Operator modifies ccr 07, 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:

CRITICAL STEP ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F NRC Exam 2013-302 STEP/STANDARD SAT/UNSAT Page 10 of 17 STEP 5: [6] OPEN the following valves: 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 RI GHT to the OPEN position. (Critical) Applicant observes RED light LI T, GREEN light DARK on 1-HS-70-74A, 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:

CRITICAL STEP ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F NRC Exam 2013-302 STEP/STANDARD SAT/UNSAT Page 11 of 17 STEP 6: [7] PLACE the following breakers to OFF: STANDARD: Applicant contacts the Console O perator as an AUO and directs the Console Operator (as an AUO) to pl ace the listed breakers to "OFF." (Critical) Steps are critical to allow for realignment of listed breakers to comply with OR14.10. COMMENTS: ___ SAT ___ UNSAT

STEP 7: [8] IF C-S CCS Pump I/S to Supply Header 1B, THEN PERFORM the following to swap to CCS Pump 1B-B: STANDARD: The applicant determines from the INITIAL CONDITIONS that the C-S CCS pump will remain out of service. COMMENTS:

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F NRC Exam 2013-302 STEP/STANDARD SAT/UNSAT Page 12 of 17 STEP 8: [9] PERFORM the following if C-S CCS Pump NOT I/S to Supply Header 1B: [9.1] UNLOCK and THROTTLE 1-ISV-70-505B, CCS PUMP 1B-B DISCHARGE ISOLATION to 25% OPEN. STANDARD: Applicant contacts an AUO and r equests 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:

___ SAT ___ UNSAT

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 Header 1B: [9.2] ENSURE a sufficient flow path to provide greater than the minimum flow allowed. STANDARD: Applicant determines that ther e is a sufficient flow path. COMMENTS:

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F NRC Exam 2013-302 STEP/STANDARD SAT/UNSAT Page 13 of 17 STEP 10: [9] PERFORM the following if C-S CCS Pump NOT I/S to Supply Header 1B: [9.3] START CCS PMP 1B-B, with 1-HS-70-38A. STANDARD: 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:

CRITICAL STEP ___ SAT ___ UNSAT

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 Header 1B: [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 r equests 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:

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F NRC Exam 2013-302 STEP/STANDARD SAT/UNSAT Page 14 of 17 STEP 12: [9] PERFORM the following if C-S CCS Pump NOT I/S to Supply Header 1B: [9.5] LOCK OPEN 1-ISV-70-505B, CCS PUMP 1B-B DISCHARGE ISOLATION. STANDARD: Applicant contacts an AUO and r equests 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:

___ SAT ___ UNSAT

STEP 13: [10] ENSURE started pump 480V ACB Closing Spring is CHARGED: [C.2] 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:

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F NRC Exam 2013-302 STEP/STANDARD SAT/UNSAT Page 15 of 17 STEP 14: [11] REFER TO Section 6.1 for temperat ure control of loop(s) placed in service. STANDARD: When applicant addresses Step 11, stat e that another oper ator will refer to Section 6.1. COMMENTS: END OF TASK ___ SAT ___ UNSAT

STOP TIME ________

F Handout Package for Applicant

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) F INITIAL CONDITIONS:

1. C-S CCS pump tripped during the last shift.

2. 1-AOI-15, "Loss of Component Cooli ng Water (CCS)," Sect ion 3.2, Loss of CCS Flow," has been performed.

3. The Unit Supervisor has evaluate d 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 C ooling 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.

NRCEXAM2013 302SystemJPMG WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G NRC EXAM 2013-302 Page 2 of 17 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 pos ition Control Bank D Group 2 rods insert. Upon diagnosis of the continuous rod insert ion, 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 System s 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 C ontrol Bank C rods 10 steps. 3. Selects the CBD position on 1-RBSS, ROD BANK SELECT.

4. Inserts, then withdraws C ontrol Bank D rods 10 steps. 5. Diagnoses the continuous inserti on 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 WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G NRC EXAM 2013-302 Page 3 of 17 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G NRC EXAM 2013-302 Event Description/Role Play Page 4 of 17 Applicant contacts the AUO stationed to support t he 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 O perator will repeat back request. The Console Operator reports the GRP SELECT light B is LIT. Applicant contacts the AUO stationed to support t he 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 O perator will repeat back request. The Console Operator reports the GRP SELECT light B is LIT. Applicant contacts the AUO stationed to support t he 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 O perator will repeat back request. The Console Operator reports the GRP SELECT light B is LIT. Applicant contacts the AUO stationed to support t he 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 O perator will repeat back request. The Console Operator reports the GRP SELECT light B is LIT. WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G NRC EXAM 2013-302 Page 5 of 17 READ TO APPLICANT

DIRECTION TO APPLICANT: I will explain the initial conditions, and state t he 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 ac tions when directed by you. Ensure you indicate to me when you understand your assi gned 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 cont rol rods are returned to the "AS FOUND" position."

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 6 of 17 START TIME: _______ EXAMINER: The following actions are taken from 1-SI-85-2, S ection 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 T avg - T ref deviation is adjusted to allow for bank movement of ten steps. STANDARD: Applicant determines that the Tavg - Tref deviation is sufficient for bank movement. COMMENTS:

___ SAT ___ UNSAT 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 t he following Step Counters: 1-CBCG1, CONTROL BANK C1:________steps. 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:

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 7 of 17 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. STANDARD: Applicant places 1-RBSS, Rod Bank Select switch, in the CBC (control bank C) position. Step is critical to allow movemen t of Control Bank C rods ONLY. COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 8 of 17 STEP 4: [4] VERIFY correct bank selected locally by GRP. SELECT Light B illuminated on: [4.1] CONTROL ROD DRIVE PAN EL 1-L-120 SOLID STATE POWER CAB (1AC) 1-PNL-85-L120. [4.2] CONTROL ROD DRIVE PAN EL 1-L-118 SOLID STATE POWER CAB (2AC) 1-PNL-85-L118. STANDARD: Applicant contacts the AUO stati oned 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 stati oned 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:

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 9 of 17 STEP 5: [5] () MOVE Control Bank C at least ten Steps in any one direction, as indicated on the appropriate Step Counter, and VERIFY movement of the rods in the proper direction is indicated on the appropriate RPIs. (Acc Crit)

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:

CRITICAL STEP ___ SAT ___ UNSAT STEP 6: [6] VERIFY Control Bank C1 and C2 Step Counters agree within plus or minus 2 steps. STANDARD: Applicant determines from 1-CBCG1 and 1-CBCG2 Step counter positions that rods are within the +/- 2 step limit. COMMENTS:

___ SAT ___ UNSAT STEP 7: [7] () RETURN Control Bank C to its original position as recorded in Step 6.7[2] of this section using 1-FLRM, ROD MOTION CONTROL. STANDARD: Applicant withdraws Control Bank C to its original position of 228 steps. COMMENTS:

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 10 of 17 STEP 8: [8] IF Rod Insertion Limit Lo Alarm 87-A does not clear, THEN

REFER TO Tech Spec LCO 3.1.7.
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:

___ SAT ___ UNSAT STEP 9: Section 6.7, Control Bank C (CBC) complete. STANDARD: Applicant determines that Section 6.7 is complete and continues to Section 6.8 CONTROL BANK D (CBD). COMMENTS:

___ SAT ___ UNSAT EXAMINER: The following actions are taken from 1-SI-85-2, S ection 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 T avg - T ref deviation is adjusted to allow for bank movement of ten steps. STANDARD: Applicant determines that the Tavg - Tref deviation is sufficient for bank movement. COMMENTS:

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 11 of 17 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 t he following Step Counters: 1-CBDG1, CONTROL BANK D1: ______________ steps.

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:

___ SAT ___ UNSAT 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 me thod will have less overall effect on reactor power. STEP 12: [3] PLACE 1-RBSS, ROD BANK SELECT, in CBD. STANDARD: Applicant places 1-RBSS, Rod Bank Select switch, in the CBD (control bank D) position. Step is critical to allow movemen t of Control Bank D rods ONLY. COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 12 of 17 STEP 13: [4] VERIFY correct bank selected locally by GRP SELECT Light B illuminated on: [4.1] CONTROL ROD DRI VE PANEL 1-L-121 SOLID STATEPOWER CAB (1BD) 1-PNL-85-L121. [4.2] CONTROL ROD DRI VE PANEL 1-L-117 SOLID STATEPOWER CAB (2BD) 1-PNL-85-L117. STANDARD: Applicant contacts the AUO stati oned 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 stati oned 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:

___ SAT ___ UNSAT 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. WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 13 of 17 STEP 14: [5] () MOVE Control Bank D at least ten Steps in any one direction, as indicated on the appropriate Step Counter, and VERIFY movement of the rods in the proper direction is indicated on the appropriate RPIs. (Acc Crit)

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:

CRITICAL STEP ___ SAT ___ UNSAT STEP 15: [6] VERIFY Control Bank D1 and D2 Step Counters agree within plus or minus 2 steps. STANDARD: Applicant determines from 1-CBDG1 and 1-CBDG2 Step counter positions that rods are within the +/- 2 step limit. COMMENTS:

___ SAT ___ UNSAT 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, CERP I 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 14 of 17 STEP 16: [7] () RETURN Control Bank D to its original position as recorded in Step [2] of this section using 1-FLRM, ROD MOTION CONTROL. STANDARD: Applicant returns Control Bank D group 1 and group 2 rods to their original position of 220 steps. Step is critical to ensure rod position is properly input into the bank overlap unit. COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT EXAMINER: Upon diagnosis of the continuous insertion of multiple rods, the applicant performs the IMMEDIATE ACTION of 1-A OI-2, "Malfunction of Reactor Control System," and trips the reactor. The following actions are taken from 1-A OI-2, "Malfunction of Reactor Control System," Section 3.2, "Uncontrolled Rod Bank Movement." STEP 17: 1. STOP uncontrolled rod motion:

a. PLACE control rods in MAN. STANDARD: Applicant determines that 1-RBSS, ROD BANK SELECT is in the "CBD" position, and that rods are in manual.

COMMENTS:

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 15 of 17 STEP 18: 1. STOP uncontrolled rod motion:

b. CHECK control rod movement STOPPED.

STANDARD: Applicant determines from audibl e feedback associated with Control Band D Group 2 step counters, the Cont rol Bank D Group 2 step counter display and from individual rod position indicators on the CERPI

MONITORs that rod inse rtion is continuing. Applicant enters the RESPONSE NOT OBTAINED column for actions. COMMENTS:

___ SAT ___ UNSAT STEP 19: 1. STOP uncontrolled rod motion:

b. RESPONSE NOT OBTAINED:

() TRIP reactor. GO TO 1-E-0, Reactor Trip or Safety 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 CRITICAL STEP ___ SAT ___ UNSAT STOP TIME ________

G

Handout Package for Applicant APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) G 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 cont rol rods are returned to the "AS FOUND" position."

NRCEXAM2013 302SystemJPMH(ROOnly) WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H NRC EXAM 2013-302 Page 2 of 16 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 S imulator X In-Plant P erform X S imulate 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 WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H NRC EXAM 2013-302 Page 3 of 16 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H NRC EXAM 2013-302 Page 4 of 16

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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H NRC EXAM 2013-302 Simulator Event No. Description/Role Play Page 5 of 16 1 1A-A RHR Pu mp trip. ROLE PLAY: When CB AUO contacted, state that pump tripped on Instantaneous over current. When AB AUO contacted stat e that there is evidence of cable damage to the mo tor pigtail, there is an order of burnt insulation but there is no smoke or fire. 2 AUO is dispatch ed 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 dispatch ed 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-7 4-37 is open. 4 AUO is dispatch ed 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 dispatch ed 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-7 4-531 is open.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H NRC EXAM 2013-302 Page 6 of 16 READ TO APPLICANT

DIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be per formed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and repor ts 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 hours 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 7 of 16 START TIME: _______ EXAMINER: After the applicant has stated that the task is understood, cue the Console Operator enter Event 1 to tr ip 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. STANDARD: 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 repor ts that there is evidence of cable damage to the motor pigta il, there is an odor of burnt insulation but there is no smoke or fire. COMMENTS:

___ SAT ___ UNSAT

STEP 2: 2. CHECK RCS temp less than 235°F. STANDARD: 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:

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 8 of 16 STEP 3: 3. ADJUST charging and letdown to maintain RCS level and press. 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 in crease in pressurizer level as observed on PZR COLD CAL Level 1-LI-68-321. Applicant may also adjust 1-FCV-62-89. COMMENTS:

___ SAT ___ UNSAT

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. STANDARD: Applicant determines that 1B-B RHR pump is available (given in INITIAL CONDITIONS). COMMENTS:

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 9 of 16 STEP 5: 5. OPEN 1-FCV-70-153, CCS to RHR HX B. STANDARD: Applicant determines that 1-FCV-70-153 is open by checking 1-HS 153A is tagged with Power Disconnect ed Open (PDO) tag. Applicant may check flow through heat exchanger on 1-EI-70-155 RHR Hx B Flow. COMMENTS:

___ SAT ___ UNSAT

STEP 6: 6. ENSURE RCS HL to RHR suction OPEN: 1-FCV-74-1 and 1-FCV-74-2, OR 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 swit ch RED light LIT and GREEN light DARK on 1-HS-74-1A and 1-HS-74-2A. COMMENTS:

___ SAT ___ UNSAT

STEP 7: 7. OPEN 1-FCV-74-21, RHR pump 1B-B suction. STANDARD: The applicant determines 1-FCV-74-21 open by checking RED light LIT and GREEN light DARK on han d switch 1-HS-74-21. COMMENTS:

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 10 of 16 STEP 8: 8. CLOSE RHR Hx outlets and bypass: 1-FCV-74-16, RHR Hx A outlet. 1-FCV-74-28, RHR Hx B outlet. 1-FCV-74-32, RHR Hx bypass. 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:

CRITICAL STEP ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 11 of 16 STEP 9: 9. ALIGN RHR pump 1B-B discharge:

a. OPEN 1-FCV-63-94, RHR B to CL 1 & 4.

b. OPEN 1-FCV-74-35, RHR Hx B outlet xtie.

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 ro tates 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 an d 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 an d 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:

CRITICAL STEP ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 12 of 16 STEP 10: 10. START RHR pump 1B-B. STANDARD: Applicant locates1-HS-74-20A a nd rotates the handswitch to the right to the START position (Critical). Applicant verifies GREEN light is DARK and the RED light LIT. Applicant observes amps for th e 1B-B RHR pump on 1-EI-74-17A, rising. Applicant observes discharge pre ssure for the 1B-B RHR pump on 1-PI-74-26, rising. This step is critical to star ting 1B-B RHR pump and establishing RHR shutdown cooling. COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

STEP 11: 11. ADJUST 1-FCV-74-28 to establish RHR flow within the RHR Pump operating flow limits in SOI-74.01 Appendix A. STANDARD: Applicant adjusts RHR flow through 1-FCV-74-28 by rotating CW from 0% using 1-HIC-74-28A and observing rising flow on 1-FI 92A, RHR TO CL 1&4 NR FLOW. Establishing a flow of 2000 to 4000 gpm is critical to establishing RHR shutdown cooling. COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 13 of 16 STEP 12: 12. ALIGN RHR Hx bypass flow:

a. CLOSE 1-HCV-74-36, RHR Hx A bypass isol.

b. OPEN 1-HCV-74-37, RHR Hx B bypass isol.

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 36. Console Operator enters Event 4 (rhr03) and repor ts 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 37. Console Operator enters Event 4 (rhr03) and repor ts 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:

CRITICAL STEP ___ SAT ___ UNSAT

STEP 13: 13. WHEN RHR flow greater than 1400 gpm, THEN ENSURE 1-FCV-74-24, RHR pump B mini-flow CLOSED. STANDARD: Applicant checks mini flow valv e 1-FCV-74-24 closed by checking GREEN light LIT on 1-HS-74-24A w hen flow greater than 1400 gpm as determined by Window 113-C RHR PUMP DISCH PRESS HI/MINI FLOW CONDITION clearing. COMMENTS:

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 14 of 16 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:

a. CLOSE 1-SPV-74-530, Tr A [1A Hx rm/722].

b. OPEN 1-SPV-74-531, Tr B

[1B Hx rm/722]. STANDARD: Applicant contacts AUO to close 1-SPV-74-530. (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-SP V-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-SP V-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:

CRITICAL STEP ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 15 of 16 STEP 15: 15. ESTABLISH RHR letdown

a. SLOWLY OPEN 1-FCV-62-83, RHR Letdown Flow Control.

b. MONITOR 1-PI-62-81, LP Letdown Press.

STANDARD: Applicant locates 1-HIC-62-83A a nd rotates the setpoint dial COUNTER CLOCKWISE SLOWLY, while monitoring 1-PI-62-81, LP LETDOWN PRESS. EXAMINER: After the applican t has opened 1-FCV-62-83, state that "another operator will complete AOI-14 actions." COMMENTS: END OF TASK ___ SAT ___ UNSAT

STOP TIME ________ APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) H 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 hours 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.

NRCEXAM2013 302SystemJPMI WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I NRC EXAM 2013-302 Page 2 of 10 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 WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I NRC EXAM 2013-302 Page 3 of 10 Tools/Equipment/Procedures Needed: Hard Hat, Safety Glasses, Hearing Pr otection, Plant Approved Shoes, Gloves.

ALARA considerations. Start this JPM in the MCR.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I NRC EXAM 2013-302 Page 4 of 10 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 maintaini ng 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 5 of 10 START TIME: _______ STEP 1: [1] ESTABLISH communications with personnel at the Main Control Room (or Aux Control Room) and Aux Bldg el 737

Outside the letdown heat exchanger room. STANDARD: Applicant locates local phone and indicates that communication has been established to the Main Control Room.

COMMENTS:

___ SAT ___ UNSAT

STEP 2: [2] PLACE 1-HIC-62-81A, LETDOWN PRESS CONTROL in MANUAL. STANDARD: Applicant contacts the Main Contro l 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:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 6 of 10 STEP 3: [3] THROTTLE CLOSED 1-ISV-62-673, CVCS LETDOWN HEADER ISOLATION [A5U/737] until pressure rise indicated in MCR or Aux Cntl Rm.

STANDARD: Applicant locates 1-ISV-62-673, CVCS LETDOWN HEADER 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:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 7 of 10 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 81 BYPASS [A5U/737] while CLOSING 1-ISV-62-673, CVCS

LETDOWN HEADER ISOLATION.

STANDARD: Applicant locates 1-BYV-62-672, CVCS LETDOWN PCV-62-81 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 clock wise on 1-BYV-62-672 and clockwise on 1-ISV-62-673 until 1-ISV 673 is fully closed. CUE: If UO contacted, state that letdown pressure lowers as 1-BYV-62-672 is OPENED a nd rises as 1-ISV-62-673 is closed. Step is critical for establishing proper flow path for bypassing 1-

PCV-62-81 COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 8 of 10 STEP 5: [5] ADJUST 1-BYV-62-672, CVCS LETDOWN PCV-62-81 BYPASS [A5U/737] to maintain desired letdown press.

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 ___ SAT ___ UNSAT

STOP TIME ________

I

Handout Package for Applicant

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) I 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 maintaini ng 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.

NRCExam2013 302SystemJPMJ WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J NRC Exam 2013-302 PAGE 2 OF 16 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," Attach ment 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 WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J NRC EXAM 2013-302 PAGE 3 OF 16 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 candidate's cue sheet.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J NRC EXAM 2013-302 PAGE 4 OF 16 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 EQUIPMEN T 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 availa ble 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 wh en you have completed the task.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT PAGE 5 0F 16 START TIME: _______ STEP 1: 2. Locally CHECK 0-PCV-33-4, SERVICE AIR SUPPLY ISOLATION, CLOSED [T7M/708].

STANDARD: The applicant locates and describes how to check that 0-PCV-33-4 is in the closed position by eit her the green local indicati ng light or the stem down on the valve. CUE: When the valve is checked, st ate that green light is ON, Red light is OFF, and Stem is down, with the indicator at "C". COMMENTS:

___ SAT ___ UNSAT

STEP 2: 3. CHECK local control station al arm DARK [ Panel 0-L-240, T7M/708]. STANDARD: The applicant locates the local cont rol 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 colu mn after discovery of the high discharge air temp and high oil te mp on "A" compressor being LIT. COMMENTS:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT PAGE 6 0F 16 STEP 3: 3. RESPONSE NOT OBTAINED: IF local control station alarm LIT, THEN PERFORM the following for each air co mpressor in alarm:

a. RESET high air temp at each compressor (0-TS-32-41, -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 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:

CRITICAL STEP ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT PAGE 7 0F 16 STEP 4: 3. RESPONSE NOT OBTAINED: IF local control station alarm LIT, THEN PERFORM the following for each air co mpressor in alarm:

b. RESET high oil temp switches at each air compressor (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 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:

CRITICAL STEP ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT PAGE 8 0F 16 STEP 5: 3. RESPONSE NOT OBTAINED: IF local control station alarm LIT, THEN PERFORM the following for each air co mpressor in alarm:

c. RESET Common Alarm using 0-HS-32-25B, COMPRESSOR A, B, C RE SET [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 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:

CRITICAL STEP ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT PAGE 9 0F 16 STEP 6: 3. RESPONSE NOT OBTAINED: IF local control station alarm LIT, THEN PERFORM the following for each air co mpressor 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 hi gh oil temp, reset push buttons at compressor "A", and 0-HS 25B has been pushed, indicate to the applicant that all alarms lights on panel are

dark. COMMENTS:

___ SAT ___ UNSAT

STEP 7: 4. PLACE the following C&SS Compre ssors to HAND [0-L-240]:

A, 0-HS-32-25D.
B, 0-HS-32-26A.

STANDARD: Applicant locates and describes how to place 0-HS-32-25D for "A"

Compressor and 0-HS-32-26A for "B" Co mpressor to the HAND position. CUE: Indicate that both ha ndswitches point to HAND.

Step is critical because the hand switches enable the respective

local start pushbuttons. COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT PAGE 10 0F 16 STEP 8: 5. PLACE 0-HS-32-25A, STATION AIR COMPRESSOR SEQUENCE CONTROL, to Position 1.

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 Select or is in position 3 before operation, and indicate that Sequence Selector is in position 1 after operation. COMMENTS:

___ SAT ___ UNSAT

STEP 9: 6. START Compressor A by pushing 0-HS-32-25E.

STANDARD: Applicant locates and describes how to depress 0-HS-32-25E manual

start push button.

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:

CRITICAL STEP ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT PAGE 11 0F 16 STEP 10: 7. CHECK Compressor A loads automatically.

STANDARD: The applicant describes how to det ermine 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 load ed, state that air pressure is NOT rising (several lo cal 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:

___ SAT

___ UNSAT

STEP 11: 7. RESPONSE NOT OBTAINED: IF Compressor A does NOT Auto load, THEN PLACE 0-HS-32-43A and -43B to ON (Local 0-JB-291-226).

STANDARD: 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:

CRITICAL STEP ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT PAGE 12 0F 16 STEP 12: 7. RESPONSE NOT OBTAINED: IF Compressor A does NOT load from local panel, THEN:

a. CLOSE 0-ISV-32-578, STATION AIR COMPR A UNLOADING HDR ISOL.

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 h as been located and closed state that valve handwheel ro tated 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 ro tated counterclockwise until snug (state that air was heard venting from end of valve if asked). The applicant indicates how to det ermine 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:

CRITICAL STEP ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT PAGE 13 0F 16 STEP 13: 8. START Compressor B by pushing, 0-HS-32-26B.

STANDARD: Applicant locates and describes how to depress 0-HS-32-26B

manual start push button.

CUE: If JPM Step 7 was SAT, then when PB is depressed, if asked state that an air compr essor 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:

CRITICAL STEP ___ SAT ___ UNSAT

STEP 14: 9. CHECK Compressor B loads automatically.

STANDARD: The applicant describes how to dete rmine 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:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT PAGE 14 0F 16 STEP 15: 10. MONITOR Compressor operation: Oil press 25-30 psig on A, B, and C. 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 l oaded, 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," "Local Restart of C&SS Air Compressors" is complete through Step 10. COMMENTS:

END OF TASK ___ SAT

___ UNSAT

STOP TIME ________

PAGE 15 0F 16 J

Handout Package for Applicant

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) J 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 availa ble 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.

NRCEXAM2013 302SystemJPMK WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K NRC EXAM 2013-302 PAGE 2 OF 10 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: A UO-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 WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K NRC EXAM 2013-302 PAGE 3 OF 10 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K NRC EXAM 2013-302 PAGE 4 OF 10 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 simula te 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 ha ve 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT PAGE 5 0F 10 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 BATTERY BD 2, closing springs charged. STANDARD: \COMMENTS:

___ SAT ___ UNSAT

STEP 2: [3] CHECK at least 267 volts indi cated on 250 V BATTERY BOARD 2 VOLTMETER on 0-DPL-239-1 250V DC TURB 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:

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT PAGE 6 0F 10 STEP 3: [4] PLACE AUTO/MANUAL SUPPLY XFER SWITCH CS-101, to the MAN position. STANDARD: Applicant locates CS-101 and indicate s that the transfer switch must 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 th e transfer from Alternate to Normal can be accomplished. COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

STEP 4: [5] CLOSE and HOLD ALT SUPPLY FROM 250V BATTERY BD 2, control switch until transfer is complete. STANDARD: Applicant locates ACB 102 and indicates that the breaker switch must be rotated to the right to the CLOSE pos ition 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 th e transfer from Alternate to Normal is accomplished without power interruption. COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT PAGE 7 0F 10 STEP 5: [6] PLACE NORM SUPPLY FROM 250V BATTERY BD 1, control switch in the TRIP position. STANDARD: Applicant locates ACB 103 and indicates that the breaker switch must be rotated to the left to the TRIP position and HELD there UNTIL the transfer is verified. Step is critical to ensure that th e transfer from Alternate to Normal is accomplished without power interruption. COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

STEP 6: [7] ENSURE breakers transferred. STANDARD: Applicant ensures ACB 102 is closed (v erbalizes 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:

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT PAGE 8 0F 10 STEP 7: [8] VERIFY between 267 and 283 volts indicated on 250 V BATTERY BOARD 2 VOLTMETER on 0-DPL-239-1 250V DC TURBINE BLDG DISTRI BUTION 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:

___ SAT ___ UNSAT

STEP 8: [9] ENSURE AUTO/MANUAL SUPPLY XFER SWITCH CS-101, in MAN position. STANDARD: Applicant ensures that CS-101 is in the MAN position, which is the position that was selected dur ing Step 3 of the procedure. COMMENTS:

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT PAGE 9 0F 10 STEP 9: Notify the Unit Supervisor t hat the transfer is complete. STANDARD: The US/SRO is notified that the transfer is complete. CUE: Acknowledge the report using repeat back. COMMENTS:

END OF TASK ___ SAT ___ UNSAT

STOP TIME ________

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

ML17165A485

Text

1.0 PURPOSE

2.1 Indications

2.2 Transitions

1.0 INSTRUCTIONS

1.0 INSTRUCTIONS

1.0 INSTRUCTIONS

1.0 INSTRUCTIONS

1.0 INSTRUCTIONS

1.0 INSTRUCTIONS

1.0 INSTRUCTIONS

1.0 INSTRUCTIONS

1.0 INSTRUCTIONS

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

1.0 PURPOSE

2.0 SYMPTOMS

2.1 Alarms

2.2 Indications

2.2 Indications

2.3 Automatic

3.0 OPERATOR

3.1 Diagnostics

3.2 Source

3.2 Source

3.2 Source

3.2 Source

3.3 Intermediate

3.4 Power

3.4 Power

3.4 Power

3.4 Power

4.0 DISCUSSION

4.3 Power

5.0 REFERENCES

5.1 Performance

1.0 INSTRUCTIONS

1.0 INSTRUCTIONS

1.0 INSTRUCTIONS

1.0 INSTRUCTIONS

1.0 INSTRUCTIONS

1.0 INSTRUCTIONS

1.0 INSTRUCTIONS

1.0 INSTRUCTIONS

1.0 INSTRUCTIONS

1.0 INSTRUCTIONS

1.0 INSTRUCTIONS

1.0 INSTRUCTIONS

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

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

References:

Navigation menu

Search