ML13210A031
| ML13210A031 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 07/26/2013 |
| From: | NRC/RGN-II |
| To: | Tennessee Valley Authority |
| References | |
| 50-390/10-301 | |
| Download: ML13210A031 (173) | |
Text
Watts Bar Nuclear Plant 2013-03 NRC Exam System JPM A
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A
2013-03 NRC Exam PAGE 2 OF 16 EVALUATION SHEET Task:
RESTORE PRT LEVEL.
Alternate Path:
While the applicant is reducing PRT level, 1-PCV-68-340 fails open after PRT level drops to less than 80%. Applicant responds by attempting to close 1-HS-68-340, PZR PORV 334 and by closing 1-HS-68-333A, BLOCK VALVE FOR PORV 340A.
Facility JPM #:
Modified (2010-08 NRC Exam JPM B.1.e)
Safety Function:
5
Title:
Containment Integrity K/A 007 A4.10 Ability to manually operate and/or monitor in the control room:
Recognition of leaking PORV/code safety.
Rating(s):
3.6/3.8 CFR:
41.7/45.5 to 45.8 Evaluation Method:
Simulator X
In-Plant Classroom
References:
SOI-68.01, Reactor Coolant System Pressurizer Relief Tank Operations, Rev. 48.
ARI 88-B, PRT LEVEL HI/LO, Rev. 25.
AOI-18, Malfunction of Pressurizer Pressure Control System, Rev. 23.
Task Number:
RO-068-SOI-68-023
Title:
Perform an alignment of the Pressurizer Relief Tank.
Task Standard:
The applicant:
- 1. Performs actions of ARI 88-B, PRT LEVEL HI/LO for a high level and reduces level to clear the PRT high level alarm.
- 2. Diagnoses the failure of PZR PORV 1-68-340 open, and terminates the depressurization by placing 1-HS-68-333A, BLOCK VALVE FOR PORV 340 in the CLOSED position.
Validation Time:
8 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
2013-03 NRC Exam PAGE 3 OF 16 SIMULATOR OPERATOR INSTRUCTIONS:
- 1.
ENSURE NRC Examination Security has been established.
- 2.
Right click on 300 and then select RESET.
- 3.
Enter the password.
- 4.
Select Yes on the INITIAL CONDITION RESET pop-up window.
- 5.
ENSURE the following information appears on the Director Summary Screen:
Key Type Event Delay Inserted Ramp Initial Final Value rc07b pzr porv pcv-68-340 fail to any position M
22 00:00:00 00:00:00 60 0
- 6.
Ensure Event 22 (PRT LEVEL) is loaded.
- 7.
Place simulator in RUN and acknowledge any alarms.
- 8.
ENSURE a marked-up copy of ARI 88-B, PRT LEVEL HI/LO corrective actions signed off (circled-and-slashed) through Step 3.
- 9.
ENSURE Extra Operator is present in the simulator.
- 10.
Place simulator in FREEZE until Examiner cue is given.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A
2013-03 NRC Exam PAGE 4 OF 16 SIMULATOR CONTINGENCY ACTIONS:
IF INITIAL CONDITION 300 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. Open 1-HS-68-303A, PRI WATER TO PRT and 1-HS-81-12, PRIMARY WATER TO PRT & STANDPIPES to raise PRT level to approximately 82%.
- 5. Enter the following using the DIRECTOR function.
Key Type Event Delay Inserted Ramp Initial Final Value rc07b pzr porv pcv-68-340 fail to any position M
22 00:00:00 00:00:00 60 0
- 6. To build Event 22, open the Event Editor and enter zaoli68300 <== 0.8. This event will enter when PRT level is less than 80%,
and will cause 1-HS-68-340 to fail to approximately 60% open.
- 7. Place simulator in RUN and acknowledge any alarms.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A
2013-03 NRC Exam PAGE 5 OF 16 JPM Step No.
Description/Role Play 3
SOI-68.01 Section 8.1, Step 1 Applicant contacts Radwaste AUO and requests current RCDT level and informs the Radwaste AUO to monitor RCDT level.
When contacted as the Radwaste AUO, the Console Operator repeats back the request for RCDT level.
Console Operator reports that RCDT level is 30% and that tank level will be monitored. If asked, report RCDT pressure is 2 psig.
4 NOTE concerning RCDT Pump B Start Applicant opens 1-FCV-68-310, PRT DRAIN TO RCDT [1-M-5].
If/When contacted as the Radwaste AUO, the Console Operator repeats back the request to check that RCDT Pump B has started. Console Operator reports that RCDT Pump B is running.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A
2013-03 NRC Exam PAGE 6 OF 16 READ TO APPLICANT DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.
INITIAL CONDITIONS:
- 1. Window 88-B, PRT LEVEL HI is LIT.
- 2. The Control Room Operator (CRO) has performed ARI 88-B, PRT LEVEL HI corrective actions through Step 3.
- 3. You are Operator at the Controls assigned to the shift.
INITIATING CUES:
The Unit Supervisor directs you to continue with the performance of ARI 88-B, PRT LEVEL HI actions, beginning at Step 4.
Inform the Unit Supervisor when PRT level has been returned to normal.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 7 of 16 START TIME: _______
EXAMINER: The following actions are taken from ARI 88-B PRT LEVEL HI/LO.
STEP 1: [4] RESTORE PRT level to normal per SOI-68.01.
STANDARD:
The applicant locates a copy of SOI-68.01 selects Section 8.1.
CUE: After the applicant has demonstrated the method of obtaining the correct instruction, then provide the applicant with HANDOUT 2.
COMMENTS:
___ SAT
___ UNSAT EXAMINER: The following actions are taken from SOI-68.01, Reactor Coolant System Pressurizer Relief Tank Operations, Section 8.1, Return PRT Level to Normal from High Level.
CAUTION RCDT pumps can easily lose suction when pumping water greater than 170°F NOTES
- 2) RCDT LEVEL should be maintained below 50% to prevent water flow into the Gas Analyzer.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 8 of 16 STEP 2: [1] ENSURE RCDT AVAILABLE to receive anticipated water volume, AND NOTIFY Radwaste AUO to MONITOR RCDT level.
STANDARD:
Applicant contacts Radwaste AUO and requests current RCDT level and informs the Radwaste AUO to monitor RCDT level.
Cue: When contacted as the Radwaste AUO, the Console Operator repeats back the request for RCDT level. Console Operator reports that RCDT level is 30% and that tank level will be monitored. If asked, report RCDT pressure is 2 psig.
COMMENTS:
___ SAT
___ UNSAT NOTE RCDT Pump B Auto-Starts when PRT drain valve opens.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 9 of 16 STEP 3: [2] OPEN 1-FCV-68-310, PRT DRAIN TO RCDT [1-M-5].
STANDARD:
The applicant locates 1-HS-68-310A, PRT DRAIN TO RCDT, and rotates the handswitch to the RIGHT to the OPEN position.
(Critical).
Applicant observes RED light LIT, GREEN light DARK.
Cue: If/When contacted as the Radwaste AUO, the Console Operator repeats back the request check that RCDT Pump B has started.
Console Operator reports that RCDT Pump B is running.
Step is critical to reestablish the proper water volume in the PRT.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT STEP 4: [4] ENSURE positive pressure maintained (1-PCV-68-304) as level drops.
STANDARD:
Applicant monitors PRT pressure on 1-PI-68-301, PRT PRESS as level is decreased.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 10 of 16 ALTERNATE PATH EXAMINER: When 88-B, PRT LEVEL HI/LO clears, malfunction rc07b will be automatically entered. This will cause 1-PCV-68-340 PZR PORV to open to 60%.
The applicant will receive alarm 91-A, PZR PORV/SAFETY OPEN.
IMMEDIATE ACTIONS of AOI-18, Malfunction of Pressurizer Pressure Control System, Section 3.2 PZR Pressure Drop Due to Failed PORV/Safety or Spray Valve, will be performed by the applicant.
Applicant may refer to AOI-18 AFTER taking actions to stop the RCS depressurization.
NOTE Step 1 and 2 are IMMEDIATE ACTION steps.
STEP 5: [1] CHECK PZR spray valves CLOSED:
- Green indicating lights LIT
- Pzr spray demand meters, 1-PIC-68-340B and 1-PIC 340D indicating ZERO [1-M-4]
STANDARD:
Applicant determines from 1-XI-68-340B, PZR SPRAY LOOP 2 and 1-XI-68-340D, PZR SPRAY LOOP 1 GREEN lights LIT, and Pzr spray demand meters, 1-PIC-68-340B and 1-PIC-68-340D indicating ZERO [1-M-4] that the spray valves are closed.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 11 of 16 STEP 6: [2] CHECK PZR PORVs CLOSED
- PORV indicating lights
- tailpipe temperature
- acoustic monitoring STANDARD:
Applicant observes sharp rise in temperature indicated on 1-TI-68-331, PORV 340A & 334 TAILPIPE TEMPS.
Applicant observes that the GREEN light is LIT on 1-HS-68-334A, which is an indication that the PORV is CLOSED.
Applicant observes that the NO lights are LIT on 1-HS-68-340, and determines that the PORV is partially open.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 12 of 16 STEP 8: 2. RESPONSE NOT OBTAINED:
IF PZR press is less than 2335, THEN CLOSE PORV OR CLOSE associated block valve STANDARD:
Applicant locates 1-HS-68-340AA, PZR PORV 340A and observes that neither the RED nor GREEN lights are LIT, indicating that the PORV is partially open.
Applicant locates 1-HS-68-334A, PZR PORV 334A and observes the RED light is DARK and GREEN light LIT, indicating that the PORV is CLOSED.
Applicant may rotate 1-HS-68-340AA, PZR PORV 340 handswitch to the LEFT to the CLOSE position.
Applicant locates 1-HS-68-333A, BLOCK VLV FOR PORV 340A, and rotates the handswitch to the LEFT to the CLOSE position. (Critical).
Applicant observes 1-HS-68-333A, BLOCK VLV FOR PORV 340A GREEN light LIT, and RED light DARK.
Step is critical to isolate the failed open PORV and stabilize RCS pressure.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 13 of 16 STEP 8: 3. VERIFY actions taken in Steps 1 and 2 have STOPPED press drop.
STANDARD:
Applicant observes 1-PI-68-340A, PZR PRESS, 1-PI-68-334, PZR PRESS, 1-PI-68-323, PZR PRESS, and/or 1-PI-68-322, PZR PRESS and determines that PZR pressure is rising.
COMMENTS:
___ SAT
___ UNSAT STEP 9: Applicant informs the Unit Supervisor that 1-PCV-68-340 PZR PORV opened and would not close manually. Applicant informs the Unit Supervisor that the block valve for PORV 68-340 is closed.
STANDARD:
Applicant informs the Unit Supervisor of the PORV and PORV block valve configurations.
CUE: Repeat back report, and then state Another operator will continue from here.
COMMENTS:
END OF TASK
___ SAT
___ UNSAT STOP TIME ________
A Handout Package 1 for Applicant
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- 1. Window 88-B, PRT LEVEL HI is LIT.
- 2. The Control Room Operator (CRO) has performed ARI 88-B, PRT LEVEL HI corrective actions through Step 3.
- 3. You are Operator at the Controls assigned to the shift.
INITIATING CUES:
The Unit Supervisor directs you to continue with the performance of ARI 88-B, PRT LEVEL HI actions, beginning at Step 4.
Inform the Unit Supervisor when PRT level has been returned to normal.
A Handout Package 2 for Applicant
Watts Bar Nuclear Plant 2013-03 NRC Exam System JPM B
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
2013-03 NRC Exam PAGE 2 OF 16 EVALUATION SHEET Task:
ESTABLISH REACTOR COOLANT SYSTEM BLEED PATH Alternate Path:
Failure of 1-PCV-68-334, PZR PORV 334 to open requires use of the Reactor Vessel Head Vent System to create adequate bleed path for RCS heat removal.
Facility JPM #:
3-OT-JPMR093, Modified.
Safety Function:
4P
Title:
Heat Removal from Reactor Core - Primary System K/A E05 EA1.1 Ability to operate and / or monitor the following as they apply to the (Loss of Secondary Heat Sink): Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
Rating(s):
4.1/4.0 CFR:
41.7 / 45.5 / 45.6 Evaluation Method:
Simulator X
In-Plant Classroom
References:
1-FR-H.1, Loss of Secondary Heat Sink, Rev. 0.
Task Number:
RO-113-FR-H.1-001
Title:
Respond to a loss of secondary heat sink.
Task Standard:
The applicant performs the actions and contingency actions required to establish a bleed path by performing Steps 18 through 20 of 1-FR-H.1, Loss of Secondary Heat Sink.
TIME COMPRESSION is utilized during the performance of this JPM.
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
2013-03 NRC Exam PAGE 3 OF 16 SIMULATOR OPERATOR INSTRUCTIONS:
- 1.
ENSURE NRC Examination Security has been established.
- 2.
RESET to Initial Condition 301 by performing the following actions:
- a.
Select ICManager on the THUNDERBAR menu (right hand side of Instructor Console Screen).
- b.
Locate IC 301.
- c.
Right click on IC 301.
- d.
Select Reset on the drop down menu.
- e.
Right click on RESET.
- f.
Enter the password for IC 301.
- 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 fw22c airbound tdafw pump M
00:00:00 00:00:00 00:00:00 Active Active fw22a airbound afw pump 1a-a M
00:00:00 00:00:00 00:00:00 Active Active fe22b airbound afw pump 1b-b M
00:00:00 00:00:00 00:00:00 Active Active fw20 feed water line break M
00:00:00 00:00:00 00:00:00 75 75 hs-68-334a hs-68-334a rcs pressurizer power relief valve sw O
00:00:00 00:00:00 00:00:00 close auto rcr06a power to reactor vent valves68-394,-397 R
1 00:00:00 00:00:00 on off rcr06b power to reactor vent valves68-395,-396 R
2 00:00:00 00:00:00 on off fwr19a high pressure fire protection spool piece to afw (sg 1&2 R
3 00:00:00 00:00:00 on off fwr19b high pressure fire protection spool piece to afw (sg 3&4 R
4 00:00:00 00:00:00 on off
- 4.
Place simulator in RUN and acknowledge any alarms.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
2013-03 NRC Exam PAGE 4 OF 16
- 5.
ENSURE Steam Generator wide range levels are 24-25% (less than 26%) to meet entry conditions for FR-H.1, Loss of Secondary Heat Sink, Bleed-and-Feed.
- 6.
ENSURE a marked-up copy of FR-H.1, Loss of Secondary Heat Sink, signed (circled-and-slashed) through Step 3.
CAUTIONS prior to Step 18 are also circled and slashed,
- 7.
ENSURE Extra Operator is present in the simulator.
- 8.
Place simulator in FREEZE until Examiner cue is given.
- 9.
When requested to restore power to RV Head Vents, set remote function rcr06a and rcr06b on to restore power to head vents.
- 10.
When requested to perform 1-AOI-7.06 to align HPFP Water to the SGs, set remote function fwr19a and fwr19b to on to install HPFP spoolpieces.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
2013-03 NRC Exam PAGE 5 OF 16 SIMULATOR CONTINGENCY ACTIONS:
IF INITIAL CONDITION 301 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.
- 4. Enter the following using the DIRECTOR function.
Key Type Event Delay Inserted Ramp Initial Final Value fw22c airbound tdafw pump M
00:00:00 00:00:00 00:00:00 Active Active fw22a airbound afw pump 1a-a M
00:00:00 00:00:00 00:00:00 Active Active fe22b airbound afw pump 1b-b M
00:00:00 00:00:00 00:00:00 Active Active fw20 feed water line break M
00:00:00 00:00:00 00:00:00 75 75 hs-68-334a hs-68-334a rcs pressurizer power relief valve sw O
00:00:00 00:00:00 00:00:00 close close rcr06a power to reactor vent valves68-394,-397 R
1 00:00:00 00:00:00 on off rcr06b power to reactor vent valves68-395,-396 R
2 00:00:00 00:00:00 on off fwr19a high pressure fire protection spool piece to afw (sg 1&2 R
3 00:00:00 00:00:00 on off fwr19b high pressure fire protection spool piece to afw (sg 3&4 R
4 00:00:00 00:00:00 on off
- 5. Place the simulator in RUN, and perform E-0, Reactor Trip or Safety Injection, through Appendix A, Equipment Verification.
- 6. STOP one hotwell pump.
- 7. Allow simulator to run until all S/G levels < 26% wide range.
- 8. PLACE the simulator in FREEZE.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
2013-03 NRC Exam PAGE 6 OF 16 READ TO APPLICANT DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.
INITIAL CONDITIONS:
- 1. The unit was at 100% RTP when a MFW line break caused a reactor trip.
- 2. All AFW pumps were removed due to steam binding; operators have been dispatched to vent the pumps.
- 3. Wide range levels on all SGs are < 26%.
- 4. You are the Operator at the Controls.
INITIATING CUES:
Beginning at Step 18.of 1-FR-H.1, Loss of Heat Sink the Unit Supervisor directs you to perform actions to establish bleed and feed.
Inform the Unit Supervisor when bleed and feed has been established.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 7 of 16 START TIME: _______
STEP 1: 18. ACTUATE SI.
STANDARD:
Applicant locates 1-HS-63-133A, SI ACTUATE TR A & B on 1-M-6 OR 1-HS-63-133B, SI ACTUATE TR A & B on 1-M-4 and rotates the selected handswitch to the RIGHT to the ACTUATE position.
Applicant determines that SI has actuated by observing 70-A, SI ACTUATED light LIT, And 76-G, SI MANUAL light LIT.
Step is critical to ensure necessary equipment running for inventory control of the RCS.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT STEP 2: 19. ENSURE at least one of the following RCS feed paths:
- At least one charging pump injecting thru BIT, OR
- At least one SI Pump running with its injection valves open.
STANDARD:
At least one charging pump is checked to be running and 1-FI-63-170 is determined to indicate flow or At least one SI pump is checked to be running and injection valve open by red light on 1-HS-63-22A.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 8 of 16 CAUTION
- When the reactor vessel head vent block valve is opened, the throttle valve will cycle open and closed.
- Slowly opening (5 seconds stroke time) the head vent valve will prevent water hammer and pipe damage.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 9 of 16 STEP 3: 20. ENSURE adequate RCS bleed path:
STANDARD:
Applicant locates and determines that 1-FCV-68-333, BLOCK VALVE FOR PORV 340A is OPEN based on GREEN indicating light DARK and RED indicating light LIT on 1-HS-68-68-333A.
Applicant locates and determines that 1-FCV-68-333A, BLOCK VALVE FOR PORV 340A is OPEN based on GREEN indicating light DARK and RED indicating light LIT on 1-HS-68-68-332A.
Applicant locates and then rotates 1-HS-68-340A, PZR PORV 340 to the right to the OPEN position. (Critical).
Applicant observes GREEN indicating light is DARK and the RED indicating light is LIT on 1-HS-68-340AA.
Applicant locates and then rotates 1-HS-68-334A, PZR PORV 334 to the right to the OPEN position.
Applicant observes GREEN indicating light is LIT and the RED indicating light is DARK on 1-HS-68-334A.
Based on the failure of 1-PCV-68-334 to OPEN, the applicant enters Step 20.a. RESPONSE NOT OBTAINED column for actions.
Step is critical because the relief capacity of one PORV is inadequate to pass sufficient fluid to depressurize the RCS and allow adequate core cooling via inventory addition. Transition to RNO establishes alternate/ additional depressurization path.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 10 of 16 STEP 4: RESPONSE NOT OBTAINED
- a. PERFORM the following:
- 1) RESTORE power to head vents:
- PLACE 1-SW-68-394-A disconnect switch to ON [125V Vital Batt Bd Rm I].
- PLACE 1-SW-68-395-B disconnect switch to ON [125V Vital Batt Bd Rm II].
STANDARD:
Applicant contacts the Control Building AUO to perform the required actions to energize the head vent valves.
Step is required since power will not be restored without the request being made. Unless power is restored, the valves cannot be opened and no bleed path can be established.
CUE: When AUO contacted to energize head vent valves, the Console Operator will repeat back request.
Console Operator inserts rcr06a and rcr06b to restore power.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 11 of 16 STEP 5: RESPONSE NOT OBTAINED
- a. PERFORM the following:
- 2) OPEN all reactor vessel head vent and block valves.
STANDARD:
Applicant locates 1-HS-68-394, RX HEAD VENT ISOL, and rotates the handswitch to the RIGHT to the OPEN position (Critical).
Applicant observes RED light LIT, GREEN light DARK.
Applicant locates 1-HS-68-395, RX HEAD VENT ISOL, and rotates the handswitch to the RIGHT to the OPEN position (Critical).
Applicant observes RED light LIT, GREEN light DARK.
Applicant locates 1-HS-68-397, RX HEAD VENT FLOW CONTROL and rotates the thumbwheel to INCREASE the valve SETPOINT to 100% (Critical).
Applicant observes 100% on the VLV POSITION scale.
Applicant locates 1-HS-68-398, RX HEAD VENT FLOW CONTROL and rotates the thumbwheel to INCREASE the valve SETPOINT to 100% (Critical).
Applicant observes 100% on the VLV POSITION scale.
Step is critical because the relief capacity of one PORV is inadequate to pass sufficient fluid to depressurize the RCS and allow adequate core cooling via inventory addition.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 12 of 16 STEP 6: RESPONSE NOT OBTAINED
- a. PERFORM the following:
- 3) ALIGN HPFP to at least one Intact S/G USING the following:
- 1-AOI-7.06, Alignment of HPFP Water to the Steam Generators.
- MI-17.018, Flood Preparation - HPFP System Spool Pieces.
STANDARD:
Applicant refers to AOI-7.06, Alignment of HPFP Water to the Steam Generators.
Applicant contacts Maintenance to perform MI-17.018, Flood Preparation - HPFP System Spool Pieces.
CUE: When AUO contacted to perform 1-AOI-7.06 and/or MI-17.018, Console Operator will repeat back request.
Console Operator inserts fwr19a and fwr19b to align HPFP spoolpieces.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 13 of 16 EXAMINER: After the applicant has addressed JPM Step 6 to align HPFP to the SGs, state that TIME COMPRESSION has occurred.
Console Operator reports that High Pressure Fire Protection has been aligned per 1-AOI-7.06.
STEP 7: RESPONSE NOT OBTAINED
- a. PERFORM the following:
- 4) WHEN one of the above low press water sources is aligned to the S/Gs, THEN DEPRESSURIZE at least one intact S/G to atmospheric press with S/G PORV.
STANDARD:
Applicant acknowledges that HPFP is aligned.
Applicant locates 1-HS-1-6A, SG 1 PORV PCV-1-5, 1-HS-1-6, SG 2 PORV PCV-1-13, 1-HS-1-24, SG 3 PORV PCV-1-24, 1-HS-1-31, SG 4 PORV PCV-1-30, and rotates at least one handswitch to the RIGHT to the OPEN position. (Critical).
Opening the PORV(s) reduces SG pressure to a point where makeup flow can be established to the SGs.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 14 of 16 STEP 8: Notify the Unit Supervisor that bleed and feed has been established.
STANDARD:
The Unit Supervisor is notified that RCS bleed and feed has been established, and that actions have been initiated to align a low pressure water source.
Cue:
Acknowledge the report using repeat back. State another operator will continue from here.
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. The unit was at 100% RTP when a MFW line break caused a reactor trip.
- 2. All AFW pumps were removed due to steam binding; operators have been dispatched to vent the pumps.
- 3. Wide range levels on all SGs are < 26%.
- 4. You are the Operator at the Controls.
INITIATING CUES:
Beginning at Step 18.of 1-FR-H.1, Loss of Heat Sink the Unit Supervisor directs you to perform actions to establish bleed and feed.
Inform the Unit Supervisor when bleed and feed has been established.
Watts Bar Nuclear Plant 2013-03 NRC Exam System JPM C
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C
2013-03 NRC Exam Page 2 of 17 EVALUATION SHEET Task:
PERFORM AN ALTERNATE DILUTION TO FLUSH THE BLENDER Alternate Path:
n/a Facility JPM #:
Modified (3-OT-JPMR050, Manual Makeup to the VCT)
Safety Function:
1
Title:
Reactivity Control K/A 004 A4.12 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. 55.
Task Number:
RO-062-SOI-62-039
Title:
Perform alternate dilution of the Reactor Coolant system or flush the boric acid line.
Task Standard:
The applicant:
1.) Aligns the CVCS system to accomplish a 50 gallon flush of the boric acid lines SOI-62.02, Boron Concentration Control, Section 6.3, Alternate Dilution or Flush.
2.) Aligns the VCT makeup controls to AUTO after the completion of the flush.
Validation Time:
8 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
2013-03 NRC Exam Page 3 of 17 SIMULATOR OPERATOR INSTRUCTIONS:
- 1.
ENSURE NRC Examination Security has been established.
- 2.
RESET to Initial Condition 303 by performing the following actions:
- a.
Select ICManager on the THUNDERBAR menu (right hand side of Instructor Console Screen).
- b.
Locate IC# 303.
- c.
Right click on IC# 303.
- d.
Select Reset on the drop down menu.
- e.
Right click on RESET.
- f.
Enter the password for IC# 303.
- 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.
ENSURE a copy of SOI-62.02, Boron Concentration Control, Section 6.3, Section 6.3, Alternate Dilution or Flush, is available for each applicant.
- 5.
ENSURE Extra Operator is present in the simulator.
- 6.
Place simulator in FREEZE until Examiner cue is given.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C
2013-03 NRC Exam Page 4 of 17 SIMULATOR CONTINGENCY ACTIONS:
IF INITIAL CONDITION 303 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. Set 1-FC-62-142, PW TO BLENDER dial to 30%.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C
2013-03 NRC Exam Page 5 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 communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.
INITIAL CONDITIONS:
- 1. A 50 gallon flush of the boric acid lines is required.
- 3. You are an extra Control Room Operator.
INITIATING CUES:
The Unit Supervisor directs you perform SOI-62.02,Boron Concentration Control, Section 6.3, Alternate Dilution or Flush, beginning at Step 3.
Inform the Unit Supervisor when the flush has been completed.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 6 of 17 START TIME: _______
STEP 1: [3] ENSURE 1-FC-62-142, PW TO BLENDER dial [1-M-6], set to 35% (70 gpm), or other setting as specified in approved instruction, and Manual-Auto toggle in AUTO.
STANDARD:
Applicant locates controller 1-FC-62-142, PW TO BLENDER 1-FCV-62-143 CONTROL and confirms that the setpoint dial is at 35% of scale, and that Manual-Auto toggle is in the AUTO (down) position.
COMMENTS:
___ SAT
___ UNSAT STEP 2: [4] ADJUST 1-FQ-62-142, PW BATCH COUNTER [1-M-6], for required quantity.
STANDARD:
Applicant determines that the required quantity of primary water is 50 gallons from the INITIAL CONDITIONS.
Applicant depresses the black pushbutton, and then lifts the red cover and enters 000050 in the display on 1-FQ-62-142. (Critical).
Step is critical to ensure proper control of reactivity is maintained COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 7 of 17 STEP 3: [5] PLACE 1-HS-62-140B, VCT MAKEUP MODE [1-M-6], in ALT DIL.
STANDARD:
Applicant rotates 1-HS-62-140B from the AUTO position four positions to the right to the ALT DIL position (Critical).
Step is critical since this action enables the proper interlocks for the alternate dilution flowpath.
COMMENTS:
___ SAT
___ UNSAT STEP 4: [6] PLACE 1-FCV-62-128, MAKEUP TO VCT INLET, in CLOSE.
STANDARD:
Applicant locates 1-FCV-62-128, MAKEUP TO VCT INLET, and rotates the handswitch to the LEFT from the P-AUTO (center) position to the CLOSE position.
Applicant observes the GREEN indicating light is LIT.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 8 of 17 STEP 5: [7] () TURN 1-HS-62-140A, VCT MAKEUP CONTROL [1-M-6],
to START.
[7.1] CHECK Red light is LIT.
STANDARD:
Applicant rotates 1-HS-62-140A, VCT MAKEUP CONTROL, to the right to the START position (Critical).
Applicant checks the RED indicating light is LIT and the GREEN indicating light is DARK.
Step is critical since this action initiates the flush.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT STEP 6: [8] ENSURE 1-HS-68-341H, BACKUP HEATER C [1-M-4], is ON, to equalize RCS-Pzr CB.
STANDARD:
Applicant locates 1-HS-68-341H, BACKUP HEATER C on panel 1-M-4 and determines that the heaters are energized by observing the RED indicating light LIT and the GREEN indicating light DARK.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 9 of 17 EXAMINER: Due to the short duration of the flush, the applicant may not have time to demonstrate that all of the parameters in the next step have been monitored.
STEP 7: [9] MONITOR the following parameters:
STANDARD:
The applicant may observe the listed parameters on 1-M-6.
1-PI-62-122, VCT PRESS 40 psig 1-LI-62-129A, VCT LEVEL 52%
1-FI-62-142, PW TO BLENDER FLOW 70 gpm 1-FQ-62-142, PW BATCH COUNTER - counting, and stopping at approximately 50 gallons, if set appropriately in previous step.
1-FQ-62-139, BA BATCH COUNTER - remaining at 0, with no indication of flow.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 10 of 17 STEP 8: [10] MONITOR NIS and Rod movement to verify expected response.
STANDARD:
Applicant monitors 1-NR-92-145, NEUTRON FLUX LEVEL RECORDER for changes to NIS power, and 1-MON-85-5000/2, CERPI MONITOR 2, Group Demand counters 1-CBDG1 CONTROL BANK D1 and 1-CBDG2 CONTROL BANK D2 for Rod movement.
COMMENTS:
___ SAT
___ UNSAT STEP 9: [11] IF 1-LI-62-129A, VCT LEVEL [1-M-6], rises to 63%, THEN ENSURE 1-FCV-62-118A, LETDOWN DIVERT TO HUT [1-M-6], diverts to HUT.
STANDARD:
Applicant locates 1-LI-62-129A, VCT LEVEL and determines that level is less than 63%.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 11 of 17 STEP 10: [12] WHEN alternate dilution is COMPLETE, THEN PERFORM the following to REALIGN makeup to AUTO:
[12.1] ENSURE 1-FC-62-142, PW TO BLENDER, on 35%
(70gpm) and Manual-Auto toggle in AUTO.
STANDARD:
Applicant locates controller 1-FC-62-142, PW TO BLENDER 1-FCV 143 CONTROL and determines that the setpoint dial is set to 35% of scale, and that Manual-Auto toggle is in the AUTO (down) position.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 12 of 17 EXAMINER: TIME COMPRESSION may be used to expedite the following step, if the applicant elects to contact Chemistry for a Boron Sample.
INITIAL CONDITIONS provides current RCS boron concentration of 757 ppm.
STEP 11: [12] WHEN alternate dilution is COMPLETE, THEN PERFORM the following to REALIGN makeup to AUTO:
[12.2] ADJUST 1-FC-62-139, BA TO BLENDER, to new RCS CB.
STANDARD:
Applicant may elect to leave 1-FC-62-139 at the current value. MOL Reactivity Thumb Rule values state that a 264 gallon dilution would result in a 3.2 ppm change in boron concentration. The 50 gallon dilution would not require a change to the setting on 1-FC-62-139.
OR Applicant may contact Chemistry for an updated RCS boron concentration, and receive a value of 757 ppm.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 13 of 17 STEP 12: [12] WHEN alternate dilution is COMPLETE, THEN PERFORM the following to REALIGN makeup to AUTO:
[12.3] PLACE 1-HS-62-140B, VCT MAKEUP MODE, in AUTO.
STANDARD:
Applicant rotates 1-HS-62-140B to the left, from the ALT DIL position to the AUTO position (Critical).
Step is critical since this action enables the proper interlocks for the AUTO makeup flowpath.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 14 of 17 STEP 13: [12] WHEN alternate dilution is COMPLETE, THEN PERFORM the following to REALIGN makeup to AUTO:
[12.4] TURN 1-HS-62-140A, VCT MAKEUP CONTROL, to START.
A. CHECK Red light is LIT.
STANDARD:
Applicant rotates 1-HS-62-140A, VCT MAKEUP CONTROL, to the right to the START position (Critical).
Applicant checks the RED indicating light is LIT and the GREEN indicating light is DARK.
Step is critical since this action sets the circuitry to respond to the AUTO makeup setpoint of 21% VCT level.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 15 of 17 STEP 14: [12] WHEN alternate dilution is COMPLETE, THEN PERFORM the following to REALIGN makeup to AUTO:
[12.5] ENSURE 1-HS-62-128, MAKEUP to VCT INLET, in P-AUTO.
STANDARD:
Applicant locates 1-FCV-62-128, MAKEUP TO VCT INLET, and rotates the handswitch to the RIGHT from the CLOSE position to the P-AUTO (center) position. (Critical).
Applicant observes the GREEN indicating light is LIT.
Step is critical since this action enables the proper flowpath for an AUTO makeup.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT STEP 15: [13] IF batch is greater than or equal to 500 gal, THEN NOTIFY Chemistry to sample RCS CB.
STANDARD:
Applicant determines that the criteria for contacting Chemistry is not met and reports the status of the plant to the Unit Supervisor.
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. A 50 gallon flush of the boric acid lines is required.
- 3. You are an extra Control Room Operator.
INITIATING CUES:
The Unit Supervisor directs you perform SOI-62.02,Boron Concentration Control, Section 6.3, Alternate Dilution or Flush, beginning at Step 3.
Inform the Unit Supervisor when the flush has been completed.
Watts Bar Nuclear Plant 2013-03 NRC Exam System JPM D
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D
2013-03 NRC Exam PAGE 2 OF 18 EVALUATION SHEET Task:
ISOLATE LEAKING SG PER AOI-33, STEAM GENERATOR TUBE LEAK.
Alternate Path:
Applicant determines that SG 1 MSIV will not close, and performs Appendix B, Leaking S/G Isolation, actions in the Main Control Room.
Facility JPM #:
3-OT-JPMA054, modified to address control room actions.
Safety Function:
3
Title:
Reactor Pressure Control K/A 037 AA2.11 Ability to determine and interpret the following as they apply to the Steam Generator Tube Leak: When to isolate one or more S/Gs Rating(s):
3.8/3.8 CFR:
43.5 / 45.13 Evaluation Method:
Simulator X
In-Plant Classroom
References:
AOI-33, Steam Generator Tube Leak, Rev. 37 Task Number:
RO-113-AOI-33-001
Title:
Respond to a Steam Generator Tube Leak.
Task Standard:
The applicant 1.) Determines that 1-HS-1-4A, MSIV SG 1, will not CLOSE.
2.) Performs actions of AOI-33, Steam Generator Tube Leak. Appendix B, Leaking S/G Isolation, to compensate for the failure of 1-HS-1-4A MSIV SG 1 to close.
3.) BOP locates 1-HS-3-164A SG 1 SUPPLY LCV-3-164 CNTL and 1-HS 174 SG 1 SUPPLY LCV-3-174 CNTL. Rotates each handswitch to the ACC RESET MODULATE position, then rotates each handswitch to the CLOSE position and pulls each switch to LOCK.
Validation Time:
10 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
2013-03 NRC Exam PAGE 3 OF 18 SIMULATOR OPERATOR INSTRUCTIONS:
- 1.
ENSURE NRC Examination Security has been established.
- 2.
Right click on 310 and then select RESET.
- 3.
Enter the password.
- 4.
Select Yes on the INITIAL CONDITION RESET pop-up window.
- 5.
ENSURE the following information appears on the Director Summary Screen:
Key Type Event Delay Inserted Ramp Initial Final Value th05a steam generator tube failure sg #1 M
00:00:00 00:00:00 00:00:00 0.25 0
ms06a fail msiv 1-4 to position M
00:00:00 00:00:00 00:00:00 100 100 msr26a msiv 1-4 aux transfer switch R
21 00:00:00 00:00:00 aux normal
- 6.
Place simulator in RUN and acknowledge any alarms.
- 7.
ENSURE a marked-up copy of AOI-33, Steam Generator Tube Leak,}, signed (circled-and-slashed) through Step 21.
- 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 D
2013-03 NRC Exam PAGE 4 OF 18 JPM Step No.
Description/Role Play 1
CLOSE leaking SG MSIV and bypass valve.
If contacted as the Control Building AUO, repeat back the request to transfer 1-XS-1-4A, MSIV Loop 1, Train A, 1-FCV-1-4 and 1-XS-1-4B, MSIV Loop 1, Train B, 1-FCV-1-4 to the AUX position Enters msr26a in the AUX position.
If contacted as the Control Building AUO, repeat back the request to remove control power fuses from 1-HS-1-4, MSIV SG 1. Report back that the control power fuses have been removed 9
COORDINATE steam moisture trap isolation with RADPRO.
When contacted as the RADPRO, repeat back the request to perform surveys in support of isolating the steam moisture traps.
11 CLOSE at least one valve for each steam moisture trap manifold listed below.
When contacted as the TB AUO, repeat back the request to perform AOI-33, Appendix B Step I actions.
Wait 2 minutes then report that the step is complete.
12 CLOSE steam supply isolation and bypass for each MFPT CUE: When contacted as the TB AUO, the Console Operator will repeat back the request to perform AOI-33, Appendix B Step J actions.
The Console Operator will wait 2 minutes then report that the step is complete.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D
2013-03 NRC Exam PAGE 5 OF 18 READ TO APPLICANT DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.
INITIAL CONDITIONS:
- 1. Steam generator (SG) 1 developed a tube leak during last shift.
- 2. Unit 1 was shutdown using AOI-39, Rapid Load Reduction, and is now in Mode 3.
- 3. AOI-33,Steam Generator Tube Leak, has been performed through Step 21.
- 4. You are Control Room Operator.
INITIATING CUES:
Beginning at Step 22 of AOI-33, Steam Generator Tube Leak, the Unit Supervisor directs you to perform actions to isolate SG 1.
Inform the Unit Supervisor when SG 1 has been isolated.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 6 0F 18 START TIME: _______
STEP 1: 22. ISOLATE leaking SG.
STANDARD:
Applicant locates 1-HS-1-4A, MSIV SG 1, and rotates the handswitch to the LEFT to the CLOSE position. Applicant determines that 1-HS-1-4A, MSIV SG 1, did not close based on the RED light LIT and GREEN light DARK.
COMMENTS:
___ SAT
___ UNSAT EXAMINER: 1-HS-1-4A, MSIV SG 1 will NOT close during the performance of this JPM.
The applicant may dispatch personnel to attempt to close SG 1 MSIV by:
1.) PLACING SG1 MSIV transfer control switch in AUX position.
If contacted as the Control Building AUO, the Console Operator repeats back the request to transfer 1-XS-1-4A, MSIV Loop 1, Train A, 1-FCV-1-4 and 1-XS-1-4B, MSIV Loop 1, Train B, 1-FCV-1-4 to the AUX position Console Operator enters msr26a in the AUX position.
2.) REMOVING control power fuses from 125 V DC Vital Battery Bd 1.
If contacted as the Control Building AUO, the Console Operator repeats back the request to remove control power fuses from 1-HS-1-4, MSIV SG 1. Console Operator reports back that the control power fuses have been removed.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 7 0F 18 STEP 2: 22. RESPONSE NOT OBTAINED:
- a. IF leaking SG(s) MSIV OR bypass can NOT be closed, THEN PERFORM App B, Leaking S/G Isolation and Local Steam Moisture Trap Isolation.
STANDARD:
Applicant locates Appendix B, Leaking S/G Isolation and begins to take actions.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 8 0F 18 STEP 3: A. CLOSE INTACT SG MSIVs, and bypass valves, to isolate Ruptured SG from intact SGs:
STANDARD:
Applicant determines that SG 2, SG 3, and SG 4 are INTACT.
Applicant locates 1-HS-1-11A, MSIV SG 2, and rotates the handswitch to the LEFT to the CLOSE position. (Critical).
Applicant observes 1-HS-1-11A, MSIV SG 2, handswitch GREEN light LIT, BLUE light LIT and RED light DARK.
Applicant locates 1-HS-1-22A, MSIV SG 3, and rotates the handswitch to the LEFT to the CLOSE position. (Critical).
Applicant observes 1-HS-1-22A, MSIV SG 3, handswitch GREEN light LIT, BLUE light LIT and RED light DARK.
Applicant locates 1-HS-1-29A, MSIV SG 4, and rotates the handswitch to the LEFT to the CLOSE position. (Critical).
Applicant observes 1-HS-1-29A, MSIV SG 4, handswitch GREEN light LIT, BLUE light LIT and RED light DARK.
Applicant determines from the placards on the handswitches 1-HS 147, 1-HS-1-148, 1-HS-1-149 and 1-HS-1-150 that power is disconnected and the valves are closed.
Step is critical to complete the main control room actions required to isolate INTACT SGs.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 9 0F 18 STEP 4: B. CLOSE HP steam main isolation valves to MSRs:
STANDARD:
Applicant locates 1-HS-1-135A, MSR A2 HP STM ISOL, and rotates the handswitch to the LEFT to the CLOSE position. (Critical).
Applicant observes 1-FCV-1-135 OP RED light DARK and 1-FCV-1-135 OP GREEN light LIT on 1-XX-1-145 MSR HP STEAM SUPPLY.
Applicant locates 1-HS-1-137A, MSR B2 HP STM ISOL, and rotates the handswitch to the LEFT to the CLOSE position. (Critical).
Applicant observes 1-FCV-1-137 OP RED light DARK and 1-FCV-1-137 OP GREEN light LIT on 1-XX-1-145 MSR HP STEAM SUPPLY.
Applicant locates 1-HS-1-139A, MSR C2 HP STM ISOL, and rotates the handswitch to the LEFT to the CLOSE position. (Critical).
Applicant observes 1-FCV-1-139 OP RED light DARK and 1-FCV-1-139 OP GREEN light LIT on 1-XX-1-145 MSR HP STEAM SUPPLY.
Applicant locates 1-HS-1-141A, MSR A1 HP STM ISOL, and rotates the handswitch to the LEFT to the CLOSE position. (Critical).
Applicant observes 1-FCV-1-141 OP RED light DARK and 1-FCV-1-141 OP GREEN light LIT on 1-XX-1-145 MSR HP STEAM SUPPLY.
Applicant locates 1-HS-1-143A, MSR B1 HP STM ISOL, and rotates the handswitch to the LEFT to the CLOSE position. (Critical).
Applicant observes 1-FCV-1-143 OP RED light DARK and 1-FCV-1-143 OP GREEN light LIT on 1-XX-1-145 MSR HP STEAM SUPPLY.
Applicant locates 1-HS-1-145A, MSR C1 HP STM ISOL, and rotates the handswitch to the LEFT to the CLOSE position. (Critical).
Applicant observes 1-FCV-1-145 OP RED light DARK and 1-FCV-1-145 OP GREEN light LIT on 1-XX-1-145 MSR HP STEAM SUPPLY.
Step is critical to complete the main control room actions required to isolate S/G 1.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 10 0F 18 STEP 5: C. CLOSE HP steam bypass isolation valves to MSRs:
STANDARD:
Applicant locates 1-HS-1-235A, MSR A2 HP STM BYPASS ISOL, and rotates the handswitch to the LEFT to the CLOSE position. (Critical).
Applicant observes 1-FCV-1-235 OP RED light DARK and 1-FCV-1-235 OP GREEN light LIT on 1-XX-1-145 MSR HP STEAM SUPPLY.
Applicant locates 1-HS-1-237A, MSR B2 HP STM BYPASS ISOL, and rotates the handswitch to the LEFT to the CLOSE position. (Critical).
Applicant observes 1-FCV-1-237 OP RED light DARK and 1-FCV-1-237 OP GREEN light LIT on 1-XX-1-145 MSR HP STEAM SUPPLY.
Applicant locates 1-HS-1-239A, MSR C2 HP STM BYPASS ISOL, and rotates the handswitch to the LEFT to the CLOSE position. (Critical).
Applicant observes 1-FCV-1-239 OP RED light DARK and 1-FCV-1-239 OP GREEN light LIT on 1-XX-1-145 MSR HP STEAM SUPPLY.
Applicant locates 1-HS-1-241A, MSR A1 HP STM BYPASS ISOL, and rotates the handswitch to the LEFT to the CLOSE position. (Critical).
Applicant observes 1-FCV-1-241 OP RED light DARK and 1-FCV-1-241 OP GREEN light LIT on 1-XX-1-145 MSR HP STEAM SUPPLY.
Applicant locates 1-HS-1-243A, MSR B1 HP STM BYPASS ISOL, and rotates the handswitch to the LEFT to the CLOSE position. (Critical).
Applicant observes 1-FCV-1-243 OP RED light DARK and 1-FCV-1-243 OP GREEN light LIT on 1-XX-1-145 MSR HP STEAM SUPPLY.
Applicant locates 1-HS-1-245A, MSR C1 HP STM BYPASS ISOL, and rotates the handswitch to the LEFT to the CLOSE position. (Critical).
Applicant observes 1-FCV-1-245 OP RED light DARK and 1-FCV-1-245 OP GREEN light LIT on 1-XX-1-145 MSR HP STEAM SUPPLY.
Step is critical to complete the main control room actions required to isolate S/G 1.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 11 0F 18 STEP 6: D. CLOSE HP steam warming valves to MSRs:
STANDARD:
Applicant locates 1-HS-1-142, MSR A1 WARMING LINE, and rotates the handswitch to the LEFT to the CLOSE position. (Critical).
Applicant observes RED light DARK, GREEN light LIT.
Applicant locates 1-HS-1-136A, MSR A2 WARMING LINE, and rotates the handswitch to the LEFT to the CLOSE position. (Critical).
Applicant observes RED light DARK, GREEN light LIT.
Applicant locates 1-HS-1-144A, MSR B1 WARMING LINE, and rotates the handswitch to the LEFT to the CLOSE position. (Critical).
Applicant observes RED light DARK, GREEN light LIT.
Applicant locates 1-HS-1-138A, MSR B2 WARMING LINE, and rotates the handswitch to the LEFT to the CLOSE position. (Critical).
Applicant observes RED light DARK, GREEN light LIT.
Applicant locates 1-HS-1-146A, MSR C1 WARMING LINE, and rotates the handswitch to the LEFT to the CLOSE position. (Critical).
Applicant observes RED light DARK, GREEN light LIT.
Applicant locates 1-HS-1-140A, MSR C2 WARMING LINE, and rotates the handswitch to the LEFT to the CLOSE position. (Critical).
Applicant observes RED light DARK, GREEN light LIT.
Step is critical to complete the main control room actions required to isolate S/G 1.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 12 0F 18 STEP 7: E. CLOSE Condenser steam dumps:
STANDARD:
Applicant locates 1-HS-1-103A, STEAM DUMP FSV A, and rotates the handswitch to the LEFT from the ON position to the OFF position.
(Critical).
Applicant locates 1-HS-1-103B, STEAM DUMP FSV B, and rotates the handswitch to the LEFT from the ON position to the OFF position.
(Critical).
Step is critical to complete the main control room actions required to isolate S/G 1.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 13 0F 18 STEP 8: F. CLOSE Steam seal supply valves:
STANDARD:
Applicant locates 1-HS-47-180A, HP STEAM SEAL SUPPLY ISOL, and rotates the handswitch to the LEFT to the CLOSE position. (Critical).
Applicant observes RED light DARK, GREEN light LIT.
Applicant locates 1-HS-1-181A, HP STEAM SEAL SUPPLY BYPASS, and rotates the handswitch to the LEFT to the CLOSE position to the OFF position and HOLDS the handswitch until the GREEN light is LIT and the RED light is DARK. (Critical).
Step is critical to complete the main control room actions required to isolate S/G 1.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT STEP 9: G. COORDINATE steam moisture trap isolation with RADPRO.
STANDARD:
Applicant contacts RADPRO for support for the Turbine Building AUO when isolating steam moisture traps in Step I.
CUE: When contacted as the RADPRO, the Console Operator will repeat back the request to perform surveys in support of isolating the steam moisture traps.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 14 0F 18 STEP 10: H. IF steam line warming in progress, THEN CLOSE at least one valve for each MSIV bypass trap isolation valve listed below:
STANDARD:
Applicant determines that steam line warming is not in progress and marks Step H N/A.
COMMENTS:
___ SAT
___ UNSAT STEP 11: I. CLOSE at least one valve for each steam moisture trap manifold listed below:
STANDARD:
Applicant contacts the Turbine Building AUO and assigns Step I actions to the Turbine Building AUO.
CUE: When contacted as the TB AUO, the Console Operator will repeat back the request to perform AOI-33, Appendix B Step I actions.
The Console Operator will wait 2 minutes then report that the step is complete.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 15 0F 18 STEP 12: J. CLOSE steam supply isolation and bypass for each MFPT:
STANDARD:
Applicant contacts the Turbine Building AUO and assigns Step J actions to the Turbine Building AUO.
CUE: When contacted as the TB AUO, the Console Operator will repeat back the request to perform AOI-33, Appendix B Step J actions.
The Console Operator will wait 2 minutes then report that the step is complete.
COMMENTS:
___ SAT
___ UNSAT STEP 13: 23. MAINTAIN leaking SG Level GREATER THAN 22%.
- a. CHECK leaking SG NR level GREATER THAN 22%.
STANDARD:
Applicant locates 1-LI-3-42, SG 1 LEVEL, 1-LI-3-39 SG 1 LEVEL and 1-LI-3-38 SG 1 LEVEL and observes levels are greater than 22%.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 16 0F 18 STEP 14: 23. MAINTAIN leaking SG Level GREATER THAN 22%.
- b. ISOLATE feed flow to leaking SG.
STANDARD:
BOP locates 1-HS-3-164A SG 1 SUPPLY LCV-3-164 CNTL and rotates to the ACC RESET MODULATE position, then rotates the handswitch to the CLOSE position and pulls the switch to lock. (Critical).
BOP may depress 1-LIC-3-164A, SG 1 SUPPLY FRM PMP A-A M pushbutton and lock the slider in the CLOSED position.
BOP locates 1-HS-3-174 SG 1 SUPPLY LCV-3-174 CNTL and rotates to the ACC RESET MODULATE position, then rotates the handswitch to the CLOSE position and pulls the switch to lock. (Critical).
BOP may depress 1-LIC-3-174A, SG 1 SUPPLY FRM TD PMP M pushbutton and lock the slider in the CLOSED position.
Step is critical to complete the main control room actions required to isolate S/G 1.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT STEP 13: Notify the Unit Supervisor steps required to isolate SG 1 are complete.
STANDARD:
Applicant informs the Unit Supervisor that AOI-33, Appendix B is complete.
COMMENTS:
END OF TASK
___ SAT
___ UNSAT STOP TIME ________
D Handout Package for Applicant
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
D INITIAL CONDITIONS:
- 1. Steam generator (SG) 1 developed a tube leak during last shift.
- 2. Unit 1 was shutdown using AOI-39, Rapid Load Reduction, and is now in Mode 3.
- 3. AOI-33,Steam Generator Tube Leak, has been performed through Step 21.
- 4. You are Control Room Operator.
INITIATING CUES:
Beginning at Step 22 of AOI-33, Steam Generator Tube Leak, the Unit Supervisor directs you to perform actions to isolate SG 1.
Inform the Unit Supervisor when SG 1 has been isolated.
Watts Bar Nuclear Plant 2013-03 NRC Exam System JPM E
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E
2013-03 NRC Exam Page 2 of 11 EVALUATION SHEET Task:
Transfer from Bypass Reg to Main Feedwater Reg Valve Alternate Path:
none 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-2&3.01, "Condensate and Feedwater System," Rev. 2.
Task Number:
RO-003-SOI-2&3-006
Title:
Transfer feedwater control from the bypass regulating valve to the main regulating valve.
Task Standard:
The applicant performs the actions required to transfer feedwater supply from 1-LIC-3-103A, SG 4 MFW BYPASS REG CONTROL to 1-FIC-3-103 SG 4 MFW REG VLV.
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 E
2013-03 NRC Exam Page 3 of 11 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.
PLACE simulator in RUN and acknowledge any alarms.
- 4.
ENSURE "FORCE 1 ELEMENT" box has been selected for 1-FIC-3-103 on DCS Monitor Display for Loop 4 Control.
- 5.
ENSURE marked up copy (for SGs 1 thru 3) of 1-SOI-2&3.01, "Condensate and Feedwater System," Section 5.6, "Bypass Reg to Main Reg Transfer (Method 1)." is available to provide to the applicant.
- 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 E
2012-12 NRC Exam Page 4 of 11 READ TO APPLICANT DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.
INITIAL CONDITIONS:
- 1. Unit 1 is at approximately 28% power, with a startup in progress.
- 2. Steam generator feedwater control has been transferred from Bypass Reg Valves to Main Feedwater Reg valves for SGs 1 thru 3.
- 3. You are the control room operator.
INITIATING CUES:
The Unit Supervisor directs you to transfer SG 4 feedwater from Bypass Reg to Main Feed Reg valve control using 1-SOI-2&3.01, "Condensate and Feedwater System,"
Section 5.6, "Bypass Reg to Main Reg Transfer (Method 1)."
Inform the Unit Supervisor when SG 4 feedwater from Bypass Reg to Main Feed Reg valve control is complete.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 5 of 11 START TIME: _______
NOTES
- 1) Steps in this Section must be completed for each SG. Steps 5.6[2] through Step 5.6[8] will be repeated for each loop transferred.
- 2) Only one Reg Bypass Reg is transferred at a time. SG level is to be stable before proceeding to next SG.
- 3) Prior to placing a Main FW Reg Valve in AUTO the operator should confirm Main FW Reg Valve is in 3 ELEMENT CONTROL by observing the DCS Monitor display for Feedwater Valve control.
STEP 1: [2] ENSURE Main FW Reg valve in 3 ELEMENT CONTROL:
Applicant determines that 1-FIC-3-103, SG 4 - MFW REG VLV, is NOT in 3 ELEMENT CONTROL by observing the DCS Monitor display for LOOP 4 Feedwater Valve Control.
Applicant will CLICK "3 ELEMENT ENABLED" in the "CONTROL MODE - MAIN" BLOCK on the DCS Monitor display for LOOP 4 Feedwater Valve Control and verify that control is transferred to 3 Element Control by observing that the "3 ELEMENT ENABLED" box is illuminated.(Critical).
Step is critical to ensure normal automatic control of 1-FIC 103, SG 4 - MFW REG VLV.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 6 of 11 STEP 2: [3] PLACE Main Reg valve in AUTO: [1-M-3]
D. 1-FIC-3-103, SG 4 - MFW REG VLV.
STANDARD:
Applicant depresses the AUTO/MAN pushbutton on controller 1-FIC-3-103 on Panel 1-M-3 and verifies AUTO half of pushbutton (backlit blue) is illuminated and MAN half of pushbutton (backlit orange) is not illuminated. (Critical).
Step is critical to ensure MFW REG Valve automatically opens as the Bypass Reg Valve is manually closed in subsequent steps.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 7 of 11 STEP 3: [4] PLACE Bypass Reg in MANUAL, AND SLOWLY REDUCE controller loading to 15% [1-M-3]:
D. 1-LIC-3-103A, SG 4 MFW BYPASS REG CONTROL.
STANDARD:
Applicant depresses the AUTO/MAN pushbutton on controller 1-LIC-3-103A on Panel 1-M-3 and verifies MAN half of pushbutton (backlit orange) is illuminated and AUTO half of pushbutton (backlit blue) is not illuminated. (Critical).
Applicant depresses the decrease "<<" pushbutton repeatedly on controller 1-LIC-3-103A on Panel 1-M-3 to JOG (~0.5% each time the button is pressed and released) the output down and slowly reduce controller loading OR Simultaneously presses the "<<" and "RAMP" pushbuttons to continuously (~full scale in 5 seconds while both buttons are depressed) reduce the controller loading. (Critical).
Step is critical since this action reduces Bypass FW flow and results in automatic opening of LOOP 4 Main FW Reg valve to transfer control to MAIN Reg Valve.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 8 of 11 STEP 5: [5] ENSURE 0.53 X 106 lb/hr (14% MFW flow) to SG [1-M-3]:
D. 1-FI-3-103A or B, SG4 MFW flow.
STANDARD:
Applicant ensures 0.53 X 106 lb/hr (14% MFW flow) to SG on 1-FI 103A or B, SG4 MFW flow on1-M-4.
COMMENTS:
___ SAT
___ UNSAT STEP 6: [6] VERIFY Blue Light LIT for SG [1-XX-3-235, [1-M-3]:
D. SG4; Flow MN > SP.
STANDARD:
Applicant verifies Blue Light LIT for SG4, Flow MN> SP on [1-XX 235, 1-M-3].
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 9 of 11 STEP 7: [7] REDUCE Bypass Reg loading to 0% [1-M-3]:
D. 1-LIC-3-103A, SG 4 MFW BYPASS REG CONTROL.
STANDARD:
Applicant depresses the decrease "<<" pushbutton repeatedly on Bypass Reg controller 1-LIC-3-103A on Panel 1-M-3 to JOG (0.5%
each time the button is pressed and released) the output down to slowly reduce controller loading to 0%
OR Simultaneously presses the "<<" and "RAMP" pushbuttons to continuously (~full scale in 5 seconds while both buttons are depressed) reduce the controller loading. (Critical).
Step is critical to completely transfer all FW flow from Bypass to MFW control.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT STEP 8: [8] IF rods were placed in MAN in Step 5.6[1], THEN PLACE rods back in AUTO when desired.
STANDARD:
Applicant locates 1-RBSS, ROD BANK SELECT on panel 1-M-4 and determines that the handswitch is selected to the MAN position and addresses placing the rods in AUTO.
CUE: As Unit supervisor cue that Control rods are to be left in manual at this time.
COMMENTS:
END OF TASK
___ SAT
___ UNSAT STOP TIME ________
E Handout Package for Applicant
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
E INITIAL CONDITIONS:
- 1. Unit 1 is at approximately 28% power, with a startup in progress.
- 2. Steam generator feedwater control has been transferred from Bypass Reg Valves to Main Feedwater Reg valves for SGs 1 thru 3.
- 3. You are the control room operator.
INITIATING CUES:
The Unit Supervisor directs you to transfer SG 4 feedwater from Bypass Reg to Main Feed Reg valve control using 1-SOI-2&3.01, "Condensate and Feedwater System,"
Section 5.6, "Bypass Reg to Main Reg Transfer (Method 1)."
Inform the Unit Supervisor when SG 4 feedwater from Bypass Reg to Main Feed Reg valve control is complete.
NOTE: JPM F is to be run in conjunction with JPM H.
Watts Bar Nuclear Plant 2013-03 NRC Exam System JPM F
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F
2013-03 NRC Exam Page 2 of 16 EVALUATION SHEET Task:
Synchronize DG 1B-B from the MCR Alternate Path:
During diesel generator synchronization, annunciator 205-B, DG LUBE OIL PRESS LO alarm is received, requiring the applicant to stop the 1B-B Diesel Generator.
Facility JPM #:
3-OT-JPMR060A Modified Safety Function:
6
Title:
Electrical Systems K/A 064 A1.03 Ability to manually operate and/or monitor in the control room: Manual start, loading, and stopping of the ED/G Rating(s):
3.9/3.9 CFR:
41.7 / 45.5 to 45.8 Evaluation Method:
Simulator X
In-Plant X
Classroom
References:
SOI-82.02, Diesel Generator (DG) B-B, Rev. 83.
ARI-202-208, Diesel Gen 1B-B, Rev. 15.
Task Number:
RO-082-SOI-82-002
Title:
Start and synchronize the emergency diesel generators.
Task Standard:
The applicant:
1.) Synchronizes 1B-B Diesel Generator to the shutdown board from the MCR, per SOI-82.01 Section 8.1.4, and then loads the DG to 4 MW and 0.75-1.25 MVARs.
2.) Determines that an emergency stop of the diesel generator is required upon receipt of annunciator 205-B, DG LUBE OIL PRESS LO and stops the 1B-B Diesel Generator.
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 F
2013-03 NRC Exam Page 3 of 16 SIMULATOR OPERATOR INSTRUCTIONS:
NOTE: The following information is displayed for JPM F. The same IC will be used for JPM H.
- 1. ENSURE NRC Examination Security has been established.
- 2.
RESET to Initial Condition 305 by performing the following actions:
- a.
Select ICManager on the THUNDERBAR menu (right hand side of Instructor Console Screen).
- b.
Locate IC 305.
- c.
Right click on IC 305.
- d.
Select Reset on the drop down menu.
- e.
Right click on RESET.
- f.
Enter the password for IC 305.
- g.
Select Yes on the INITIAL CONDITION RESET pop-up window.
- h.
Perform SWITCH CHECK.
- 3.
ENSURE the following information appears on the Director Summary Screen:
Key Type Event Delay Inserted Ramp Initial Final Value mux_07c071 205-b dg 1b-b lube oil press lo M
23 00:00:00 00:00:00 On None
- 4.
Ensure Event 23 is loaded into the simulator.
- 5.
ENSURE the 1B-B Diesel Generator is running, with Window 206A DG RUNNING annunciator LIT.
6 Place simulator in RUN and acknowledge any alarms.
- 7.
ENSURE a marked-up copy of SOI-82.02, Diesel Generator (DG) 1B-B, signed, circled-and-slashed through Step 3, is available to the Examiner.
- 8.
ENSURE Extra Operator is present in the simulator.
- 9.
Place simulator in FREEZE until Examiner cue is given.
- 10.
ENSURE STOP WATCH is available to the applicant.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F
2013-03 NRC Exam Page 4 of 16 SIMULATOR CONTINGENCY ACTIONS:
IF INITIAL CONDITION 305 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. Enter the following using the DIRECTOR function.
Key Type Event Delay Inserted Ramp Initial Final Value mux_07c071 205-b dg 1b-b lube oil press lo M
23 00:00:00 00:00:00 On None
- 4. To rebuild the Event 23, open the Event Editor and enter zaoei8240a >= 0.4. This event will enter when the diesel is loaded to approximately 3 MW.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F
2013-03 NRC Exam Page 5 of 16 READ TO APPLICANT DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.
INITIAL CONDITIONS:
- 1. Testing is being conducted on 1B-B diesel generator. It is to be paralleled to the shutdown board for a Factory Representative on site.
- 2. The 1B-B DG is running at rated speed, after performance of SOI-82.02, Diesel Generator (D/G) 1B-B, Section 8.1.3, "Idle Speed to Rated Speed."
- 3. Steps 1 through 3 of SOI-82.02, Diesel Generator (D/G) 1B-B, Section 8.1.4, Manual-Remote Synchronizing DG have been performed.
- 4. You are an extra control room operator on shift.
INITIATING CUES:
The Unit Supervisor directs you to parallel the 1B-B diesel generator to the 1B-B Shutdown Board per SOI-82.02, Diesel Generator (D/G) 1B-B and load it to 4 MWs.
Inform the Unit Supervisor when the diesel generator is loaded to 4 MWs.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 6 of 16 START TIME: _______
STEP 1: [4] PLACE 1-HS-82-48, DG MODE SELECTOR Switch, in PARALLEL [0-M-26].
STANDARD:
The applicant locates 1-HS-82-48 DG MODE SELECTOR and rotates the handswitch to the right from the UNIT to the PARALLEL position.(Critical).
This step is critical for task performance to allow proper operation of voltage regulator & DG speed droop circuits.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT STEP 2: [5] ENSURE the following sync switches for 1B-B D/G in OFF:
STANDARD:
Applicant locates each of the listed sync switches and determines that each handswitch is in the OFF position COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 7 of 16 STEP 3: [6] PLACE 1-HS-57-74, DG SYNC SWITCH, in SYN [0-M-26].
STANDARD:
Applicant locates 11-HS-57-74, DG SYNC SWITCH and rotates the switch to the right to the SYN position (Critical).
This step is critical to allow synchronization of D/G to 1B-B Shutdown board.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT CAUTION When adjusting speed and voltage, care must be taken to prevent overshooting desired values. Voltage control response is approximately five times faster than speed control response.
STEP 4: [7] MATCH generator Incoming Frequency (1-XI-82-32) with Running Frequency (1-XI-82-33) using 1-HS-82-43, SPEED CONTROL [0-M-26].
STANDARD:
Applicant operates 1-HS-82-43 to adjust generator frequency (incoming) on 1-XI-82-32 to match with board frequency (running) on 1-XI-82-33.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 8 of 16 STEP 5: [8] MATCH generator Incoming Voltage (1-EI-82-34) with Running Voltage (1-EI-82-35) using 1-HS-82-42, VOLTAGE REGULATOR [0-M-26].
STANDARD:
Applicant operates 1-HS-82-42 to adjust generator voltage on 1-EI 34 to board voltage on 1-EI-82-35.
COMMENTS:
___ SAT
___ UNSAT NOTE Steps 8.1.4[9], 8.1.4[10], and 8.1.4[11] should be read before performing.
EXAMINER: The applicant may use a stopwatch to time the 15 second rotation. Provide stopwatch if asked.
STEP 6: [9] ENSURE DG Frequency and Voltage are MATCHED with 6.9 kV SD Bd, AND ADJUST 1-HS-82-43, SPEED CONTROL,
[0-M-26] to obtain desired clockwise rotation (15 or more seconds) on 1-XI-82-31,TRAIN 1B-B SYNCHROSCOPE.
STANDARD:
Applicant observes that running and incoming frequency and voltage are matched or takes appropriate actions to make them equal.
The applicant adjusts 1-HS-82-143 SPEED CONTROL to make the synchroscope movie slowly in the clockwise direction at 15 seconds or more per rotation on the scope.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 9 of 16 NOTES
- 1) Steps 8.1.4[10] through 8.1.4[11.3] may be signed off after completion of Step 8.1.4[11.3].
- 2) Peer checking required on next step.
STEP 7:
STANDARD:
Applicant monitors 1-XI-82-31, TRAIN 1B-B SYNCHROSCOPE and when it reaches the 12 oclock position, rotates 1-HS-57-73A, 1914 - DG TO SD BD 1B-B, to the right to the CLOSE position. (Critical).
This step is critical to allow synchronization of D/G to 1B-B Shutdown board.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT NOTE Maintain outgoing Vars by periodically adjusting voltage regulator with 1-HS-82-12 while loading D/G. Controls should NOT be operated simultaneously.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 10 of 16 STEP 8: [11] PERFORM the following:
[11.1] LOAD DG promptly using 1-HS-82-43, SPEED CONTROL to at least 1.1 Megawatts as indicated on 1-EI-82-40A, DG MEGAWATTS (0-M-26).
STANDARD:
Applicant periodically rotates 1-HS-82-43 to the RAISE position to increase generator load on 1-EI-82-40A, DG MEGAWATTS to 1.1 Megawatts. (Critical).
This step is critical to ensure proper DG loading and avoid reverse power trip.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT NOTE DG Megavars may "swing" when the 6.9kV automatic tap changers engage to stabilize voltage in the system.
STEP 9:
[11.2] MAINTAIN DG MEGAVARS 0.75 to 1.25 OUTGOING on 1-EI-82-41A, with 1-HS-82-42, VOLTAGE REGULATOR.
STANDARD:
Applicant periodically adjusts 1-HS-82-42, VOLTAGE REGULATOR, to maintain Megavars between 0.75 and 1.25 OUTGOING on 1-EI-82-41A following the loading of the diesel generator to 4 MW. (Critical).
This step is critical to ensure proper DG loading and avoid reverse power trip.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 11 of 16 CAUTION Operation of the DG at load of 2.7 MW or less for extended period of time may lead to exhaust fire.
STEP 10: [11.3] RAISE load to at least 3.3 Megawatts.
STANDARD:
Applicant periodically rotates 1-HS-82-43 to the RAISE position to increase generator load on 1-EI-82-40A, DG MEGAWATTS to 3.3 Megawatts.
Applicant periodically adjusts 1-HS-82-42, VOLTAGE REGULATOR to maintain Megavars between 0.75 and 1.25 OUTGOING on 1-EI-82-41A.
COMMENTS:
___ SAT
___ UNSAT EXAMINER: When 1B-B Diesel Generator megawatts are raised above 3 MWe, Window 205-B, DG LUBE OIL PRESS LO will be received.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 12 of 16 EXAMINER: The following actions are taken from ARI 205-B, DG LUBE OIL PRESS LO.
STEP 11: Applicant responds to 205-B, DG LUBE OIL PRESS LO. on XA-55-26B.
STANDARD:
Applicant notes the Low Lube Oil Pressure Annunciation, Window 205 B on XA-55-26B and refers to the Alarm Response Instruction for the window.
COMMENTS:
___ SAT
___ UNSAT STEP 12: [1] DISPATCH Operator to check lube oil pressure indication at Diesel Generator Control Board, and local soakback oil pressure gauges.
STANDARD:
Applicant contacts an AUO to check lube oil pressure on Gen Control Board and local soak back oil pressure gauges CUE:
After AUO is notified, the Console Operator repeats back request to check local instrumentation for lube oil pressure.
CUE: Console Operator reports lube oil pressure is 12 psig.
COMMENTS:
___ SAT
___ UNSAT CAUTION If required to mitigate an accident condition the Shift manager may authorize continued DG operation at rated speed with lube oil pressure less than 20 psig.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 13 of 16 STEP 13: [2] IF DG emergency started and is NOT being tested, THEN EVALUATE DG load and the need for continued operation.
STANDARD:
Applicant determines that the step is not applicable, since the DG is running for testing.
COMMENTS:
___ SAT
___ UNSAT STEP 14: [3] IF DG is running for testing do NOT exceed the rated speed minimum lube oil pressure of 20 psig (if NOT emergency started, auto-shutdown should occur at less than or equal to 20 psig) AND NOTIFY System or Maintenance Engineer to evaluate continued operation between 20 psig and 40 psig.
STANDARD:
After receiving the report from the AUO that pressure is 12 psig, the applicant trips the DG using the emergency stop pushbutton.
This step is critical to minimize damage to the 1B-B Diesel Generator. Diesel generator should have automatically tripped when pressure dropped below 20 psig.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 14 of 16 STEP 15: Notifies the Unit Supervisor that the 1B-B Diesel Generator was shutdown using 1-HS-82-47A, EMERGENCY STOP pushbutton on 0-M-26, due to a high crankcase pressure alarm.
STANDARD:
Applicant notifies the Unit Supervisor that an emergency stop of the 1B-B Diesel Generator was performed due to high crankcase pressure, in accordance with ARI 205-B, DG LUBE OIL PRESS LO.
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. Testing is being conducted on 1B-B diesel generator. It is to be paralleled to the shutdown board for a Factory Representative on site.
- 2. The 1B-B DG is running at rated speed, after performance of SOI-82.02, Diesel Generator (D/G) 1B-B, Section 8.1.3, "Idle Speed to Rated Speed."
- 3. Steps 1 through 3 of SOI-82.02, Diesel Generator (D/G) 1B-B, Section 8.1.4, Manual-Remote Synchronizing DG, have been performed.
- 4. You are an extra control room operator on shift.
INITIATING CUES:
The Unit Supervisor directs you to parallel the 1B-B diesel generator to the 1B-B Shutdown Board per SOI-82.02, Diesel Generator (D/G) 1B-B and load it to 4 MWs.
Inform the Unit Supervisor when the diesel generator is loaded to 4 MWs.
Watts Bar Nuclear Plant 2013-03 NRC Exam System JPM G
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G
2013-03 NRC Exam Page 2 of 11 EVALUATION SHEET Task:
Return Failed RCS Temperature Channel to Service.
Alternate Path:
When rod control is returned to AUTO, Control Bank D, GROUP 1 begins to continuously withdraw. This requires the applicant to trip the reactor.
Facility JPM #:
Modified 2010-08 JPM B.1.g Safety Function:
7
Title:
Instrumentation K/A 016 A4.01 Ability to manually operate and/or monitor in the control room: NNI channel select controls.
Rating(s):
2.9/2.8 CFR:
41.7/ 45.4 to 45.8 Evaluation Method:
Simulator X
In-Plant Classroom
References:
AOI-2, Malfunction of Reactor Control System, Rev. 39 Task Number:
RO-085-AOI-2-005
Title:
Respond to a continuous control rod insertion.
Task Standard:
The applicant:
1.) Returns Loop 4 RCS Tavg and T inputs to the rod control system, using AOI-2, Malfunction of Reactor Control System.
TIME COMPRESSION may be used to address the CAUTION to wait 5 minutes before selecting AUTO rod control.
2.) Initiates a manual reactor trip upon diagnosis of the continuous rod withdrawal of Control Bank D GROUP 1.
Validation Time:
8 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
2013-03 NRC Exam Page 3 of 11 SIMULATOR OPERATOR INSTRUCTIONS:
- 1.
ENSURE NRC Examination Security has been established.
- 2.
RESET to Initial Condition 304 by performing the following actions:
- a.
Select ICManager on the THUNDERBAR menu (right hand side of Instructor Console Screen).
- b.
Locate IC# 304.
- c.
Right click on IC# 304.
- d.
Select Reset on the drop down menu.
- e.
Right click on RESET.
- f.
Enter the password for IC# 304.
- 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 rd01 uncontrolled rod withdrawal; bank d, group 1 21 00:00:00 00:00:00 Active InActive
- 4.
Ensure Event 21 (zdirbss1(6)== 1) is loaded.
- 5.
ENSURE that 1-XS-68-2D, T CHANNEL DEFEAT, and 1-XS-68-2M, TAVG CHANNEL DEFEAT, are selected to Loop 4 and the handswitches are in the PULLED OUT position.
- 6.
Place simulator in RUN and acknowledge any alarms.
- 7.
ENSURE a marked-up copy of AOI-2, Malfunction of Reactor Control System 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
2013-03 NRC Exam Page 4 of 11 SIMULATOR CONTINGENCY ACTIONS:
IF INITIAL CONDITION 304 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. Enter the following using the DIRECTOR function.
Key Type Event Delay Inserted Ramp Initial Final Value rd01 uncontrolled rod withdrawal; bank d, group 1 21 00:00:00 00:00:00 Active InActive
- 4. To build Event 21, open the Event Editor and enter zdirbss1(6)== 1 This event will enter when 1-RBSS, ROD BANK SELECT is placed in AUTO.
- 5. ENSURE that 1-XS-68-2D, T CHANNEL DEFEAT, and 1-XS-68-2M, TAVG CHANNEL DEFEAT, are selected to Loop 4 and the handswitches are in the PULLED OUT position.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G
2013-03 NRC Exam Page 5 of 11 READ TO APPLICANT DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.
INITIAL CONDITIONS:
- 1. Unit 1 is operating at 75% power.
- 2. Loop 4 RCS temperature channel failed high during the previous shift.
- 3. The channel was removed from service per AOI-2, Malfunction of Reactor Control System, Subsection 3.2, Continuous Rod Insertion/Withdrawal.
- 4. AOI-2, Subsection 3.2 has been completed through Step 10.
- 5. Work Control has just informed the Unit Supervisor that repairs have been completed.
- 6. Rod Control is in MANUAL.
- 7. You are the Operator at the Controls (OAC).
INITIATING CUES:
The Unit Supervisor has directed you return Loop 4 RCS temperature loop to service using AOI-2, Malfunction of Reactor Control System, Sub Section 3.2, Continuous Rod Insertion/Withdrawal, beginning at Step 11.
Inform the Unit Supervisor when rod control has been returned to AUTOMATIC.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 6 of 11 START TIME: _______
EXAMINER: Step 11 has been broken into 2 separate JPM steps since each action accomplished is unique and critical.
STEP 1: 11. WHEN ready to restore repaired T and loop T-avg channels, THEN:
- PUSH IN 1-XS-68-2D, T CHANNEL DEFEAT and SELECT AWAY from all channels.
STANDARD:
Applicant pushes 1-XS-68-2D, T CHANNEL DEFEAT switch IN and then rotates the switch from the Loop 4 position to the OFF position. (Critical).
Step is critical to restore the Loop 4 T input to normal.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT STEP 2: 11. WHEN ready to restore repaired T and loop T-avg channels, THEN:
- PUSH IN 1-XS-68-2M, TAVG CHANNEL DEFEAT, and SELECT AWAY from all channels.
STANDARD:
Applicant pushes 1-XS-68-2M, TAVG CHANNEL DEFEAT switch IN and then rotates the switch from the Loop 4 position to the OFF position. (Critical).
Step is critical to restore the Loop 4 Tavg input to normal.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 7 of 11 EXAMINER: To address the following CAUTION, inform the applicant that TIME COMPRESSION has occurred, and 5 minutes have elapsed.
CAUTION Allowing at least 5 minutes between any rod control input change (i.e., T-ave, T-ref, or NIS) and placing rods in AUTO, will help prevent undesired control rod movement.
EXAMINER: When the rods are placed in AUTO, Annunciator 86-A CONTROL ROD URGENT FAILURE will be occur, and Control Bank D, Group 1 will begin to continuously withdraw. Placing 1-RBSS in MANUAL will NOT STOP the continuous withdrawal.
STEP 3: 12. WHEN auto rod control desired, THEN:
- a. ENSURE T-ave and T-ref within 1F.
- b. ENSURE zero demand on control rod position indication
[1-M-4].
- c. PLACE rods in AUTO.
STANDARD:
Applicant determines that T-ave and T-ref are within 1F.
Applicant observes zero demand on CERPI display 1-MON-5000/1 OR 1-MON-5000/2, PASSIVE SUMMER ROD DEMAND Indicator.
Applicant rotates RBSS-1 Rod Bank Selector to the right from MAN to AUTO.
CUE: If requested by the applicant, state that 5 minutes have elapsed since restoring Loop 2 T and loop Tavg channels.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 8 of 11 EXAMINER: The applicant is expected to manually trip the reactor based on the continuous withdrawal of Control Bank D, Group 1.
EXAMINER: The following actions are taken from AOI-2, Subsection 3.2, Uncontrolled Rod Bank Movement.
NOTE Step 1 is an IMMEDIATE ACTION step STEP 11: 1. STOP uncontrolled rod motion:
- a. PLACE control rods in MAN.
STANDARD:
Applicant diagnoses the continuous rod insertion, locates1-RBSS, ROD BANK SELECT and then rotates the handswitch from AUTO to MAN.
COMMENTS:
___ SAT
___ UNSAT STEP 12: 1. STOP uncontrolled rod motion:
- b. CHECK control rod movement STOPPED.
STANDARD:
Applicant observes that RCCA D-12 is continuing to insert, based on the CERPI display.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 9 of 11 STEP 13: b. RESPONSE NOT OBTAINED:
() TRIP reactor.
GO TO E-0, Reactor Trip or Safety Injection.
STANDARD:
Applicant locates 1-RT-1, REACTOR TRIP (OR 1-RT-2, REACTOR TRIP) and rotates the handswitch to the RIGHT to the TRIP position.
(Critical).
Step is critical to terminate the continuous rod withdrawal.
When applicant initiates the reactor trip, state Another operator will perform E-0 Immediate Action Steps.
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 75% power.
- 2. Loop 4 RCS temperature channel failed high during the previous shift.
- 3. The channel was removed from service per AOI-2, Malfunction of Reactor Control System, Subsection 3.2, Continuous Rod Insertion/Withdrawal.
- 4. AOI-2, Subsection 3.2 has been completed through Step 10.
- 5. Work Control has just informed the Unit Supervisor that repairs have been completed.
- 6. Rod Control is in MANUAL.
- 7. You are the Operator at the Controls (OAC).
INITIATING CUES:
The Unit Supervisor has directed you return Loop 4 RCS temperature loop to service using AOI-2, Malfunction of Reactor Control System, Sub Section 3.2, Continuous Rod Insertion/Withdrawal, beginning at Step 11.
Inform the Unit Supervisor when rod control has been returned to AUTOMATIC.
NOTE: JPM H is to be run in conjunction with JPM F.
Watts Bar Nuclear Plant 2013-03 NRC Exam System JPM H
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H
2013-03 NRC Exam PAGE 2 OF 17 EVALUATION SHEET Task:
START UPPER CONTAINMENT PURGE Alternate Path:
n/a Facility JPM #:
3-OT-JPMR173A Safety Function:
8
Title:
Plant Systems K/A 029 A2.03 Ability to (a) predict the impacts of the following malfunctions or operations on the Containment Purge System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Startup operations and the associated required valve lineups.
Rating(s):
2.7 / 3.1 CFR:
41.5 / 43.5 / 45.3 / 45.13 Evaluation Method:
Simulator X
In-Plant Classroom
References:
SOI-30.02, Containment Purge System, Rev. 58 Task Number:
RO-030-SOI-30-007
Title:
Purge Upper Containment Task Standard:
The applicant places Upper Containment Purge in service using SOI-30.02, Containment Purge System, Section 5.1, Start Up Upper Containment Purge, steps 10 through Step 18.
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 H
2013-03 NRC Exam PAGE 3 OF 17 SIMULATOR OPERATOR INSTRUCTIONS:
NOTE:
This JPM will requires NO specific setup. It is to be run in conjunction JPM F, which uses IC 305. See JPM F for setup information.
- 1.
ENSURE NRC Examination Security has been established.
- 2.
RESET to IC 305 3
ENSURE copies of SOI-30.02, Containment Purge System, Section 5.1, Start Up Upper Containment Purge, are available for the Examiner. Copies are included in the G -Handout Package for Applicant.
- 4.
ENSURE Extra Operator is present in the simulator.
- 5.
Place simulator in FREEZE until Examiner cue is given.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H
2013-03 NRC Exam PAGE 4 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 communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.
INITIAL CONDITIONS:
- 1. Unit 1 is in Mode 1.
- 2. Train A Upper Containment Purge is being placed in service.
- 3. SOI-30.02, Containment Purge System, Section 5.1, Start Up Upper Containment Purge, has been completed through Step 9.
- 4. The area around the Service Building Air Intake is clear of fumes and there are no vehicles running in the vicinity.
- 5. Unit 1 Shield Building Exhaust Monitor and its isokinetic sampler are operable.
- 6. You are an extra operator assigned to the shift.
INITIATING CUES:
The Unit Supervisor has directed you to perform Steps 10 through 18 of SOI-30.02, Containment Purge System, Section 5.1, Start Up Upper Containment Purge.
Inform the Unit Supervisor when Step 18 is complete.
NOTE:
At Step 13, you are to use dampers 1-FCV-30-7 & 51, and 1-FCV-30-8 & 50.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 5 0F 17 START TIME: _______
STEP 1:
[10] CLOSE Containment vent filter flowpath:
STANDARD:
Applicant locates 1-HS-30-37, LWR CNTMT PURGE EXH PRESS RLF and then rotates the handswitch to the LEFT to the CLOSE position.
(Critical).
Applicant observes RED light DARK and GREEN light LIT on 1-HS-30-37, LWR CNTMT PURGE EXH PRESS RLF.
Applicant locates 1-HS-30-40, LWR CNTMT PURGE EXH PRESS RLF and then rotates the handswitch to the LEFT to the CLOSE position.
(Critical).
Applicant observes RED light DARK and GREEN light LIT on 1-HS-30-40, LWR CNTMT PURGE EXH PRESS RLF.
Step is critical to ensure proper purge flowpath is established.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 6 0F 17 STEP 2: [11] OPEN Selected Supply Fan(s) Disch damper: (N/A if NOT selected)
STANDARD:
Applicant locates 1-HS-30-2, PURGE SUP FAN DISCH, and then rotates the handswitch to the RIGHT to the OPEN position. (Critical).
Applicant observes RED light LIT and GREEN light DARK on 1-HS-30-2.
Applicant locates 1-HS-30-5, PURGE SUP FAN 1B DISCH and observes RED light DARK, GREEN light LIT. Applicant enters N/A for 1-HS-30-5, PURGE SUP FAN 1B DISCH.
Step is critical to align Train A of the purge system.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 7 0F 17 STEP 3: [12] ALIGN Exh Fans Disch Flood dampers per 5.1[12.1],
5.1[12.2], or 5.1[12.3]: (N/A subsection NOT performed).
[12.1] IF Train A will be run, THEN PERFORM the following:
STANDARD:
Applicant locates 1-HS-30-213, PURGE EXH FAN 1A TO SHIELD BLDG VNT, and then rotates the handswitch to the RIGHT to the OPEN position. (Critical).
Applicant observes RED light LIT and GREEN light DARK on 1-HS 213.
Applicant locates 1-HS-30-216, PURGE EXH FAN 1B TO SHIELD BLDG VNT and observes RED light DARK, GREEN light LIT.
Step is critical to align Train A of the purge system.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 8 0F 17 STEP 4: [12] ALIGN Exh Fans Disch Flood dampers per 5.1[12.1],
5.1[12.2], or 5.1[12.3]: (N/A subsection NOT performed).
[12.2] IF Train B will be run, THEN PERFORM the following:
STANDARD:
Applicant enters N/A for Step 12.2, since Train B will not be placed in service.
COMMENTS:
___ SAT
___ UNSAT STEP 5: [12] ALIGN Exh Fans Disch Flood dampers per 5.1[12.1],
5.1[12.2], or 5.1[12.3]: (N/A subsection NOT performed).
[12.3] IF Both Train A and B will be run, THEN PERFORM the following:
STANDARD:
Applicant enters N/A for Step 12.2, since Both Train A and Train B will not be placed in service together.
COMMENTS:
___ SAT
___ UNSAT CAUTION If Upper Containment is purged during operation, only one set of isolation valves may be open. Either set of the two supply and exhaust side valves may be open.
NOTE When FCVs 30-50 & 51 or -52 & 53 are OPEN, an air sweep of the Vessel Internals Storage Area is created for refueling operations.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 9 0F 17 EXAMINER: The INITIAL CONDITIONS state that 1-FCV-30-7 & 51 and 1-FCV-30-8 & 50 are to be opened for this performance.
STEP 6: [13] OPEN the FCVs in 5.1[13.1] & 5.1[13.2], or 5.1[13.3] &
5.1[13.4] [1-M-9]: (N/A set NOT used)
[13.1] UPR CNTMT PURGE 1-FCV-30-7 & 51 with 1-HS-30-7.
[13.2] UPR CNTMT PURGE 1-FCV-30-8 & 50 with 1-HS-30-8.
STANDARD:
Applicant locates 1-HS-30-7, UPR CNTMT PURGE 1-FCV-30-7 & 51, and then rotates the handswitch to the RIGHT to the OPEN position.
(Critical).
Applicant observes RED lights LIT and GREEN lights DARK on 51 and 7.
Applicant locates 1-HS-30-8, UPR CNTMT PURGE 1-FCV-30-8 & 50, and then rotates the handswitch to the RIGHT to the OPEN position.
(Critical).
Applicant observes RED lights LIT and GREEN lights DARK on 50 and 8.
Step is critical to ensure proper purge flowpath is established.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 10 0F 17 STEP 7: [13] OPEN the FCVs in 5.1[13.1] & 5.1[13.2], or 5.1[13.3] &
5.1[13.4] [1-M-9]: (N/A set NOT used)
[13.3] UPR CNTMT PURGE 1-FCV-30-9 & 53 with 1-HS-30-9.
[13.4] UPR CNTMT PURGE 1-FCV-30-10 & 52 with 1-HS-30-10.
STANDARD:
Applicant enters N/A for Step 13.3 and 13.4 since this flowpath will not be used.
COMMENTS:
___ SAT
___ UNSAT EXAMINER: INITIAL CONDITION 4 states that the area around the Service Building Air Intake is clear of fumes and there are no vehicles running in the vicinity.
INITIAL CONDITION 5 states that Unit 1 Shield Building Exhaust Monitor and its isokinetic sampler are operable.
CAUTIONS
- 1) PER 78024 has documented that annulus delta-P indication, and annulus vacuum, are impacted by higher Unit 1 Shield Bldg Vent flows. Operation of the A ABGTS in combination with both trains of Containment Purge is NOT presently acceptable. At 22,000 cfm flow through the Unit 1 Shield Bldg Vent, the annulus vacuum fans may automatically control annulus vacuum below the Tech Spec minimum. The 1-SI-0 (series) contains the corrected Tech Spec indicated limit.
- 2) Due to proximity of Service Bldg access to air intake, the area outside Unit 1 intake should be checked for potential fumes or running vehicle exhaust prior to starting fans. [C.2]
- 3) For normal plant operations, purge should NOT be placed in service unless the U1 shield bldg. exhaust monitor and its associated isokinetic sampler are operable.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 11 0F 17 STEP 8: [14] START Selected Purge Sup & Exh Fan(s): (N/A if NOT selected)
STANDARD:
Applicant locates 1-HS-30-1A, CNTMT PURGE SUP & EXH FANS 1A AND FCO-30-1A & 1B, pushed the handswitch in and then rotates the handswitch to the RIGHT to the START position. (Critical).
Applicant observes RED lights LIT and GREEN lights DARK on SUP and EXH.
Applicant enters N/A for 1-HS-30-4A, CNTMT PURGE SUP & EXH FANS 1B AND FCO-30-4A & 4B, since this set of fans will not be used.
Step is critical to align Train A of the purge system.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 12 0F 17 CAUTION If Ice Condenser Doors open after opening FCV-30-61 and/or -62, an out-of-balance flow may exist. System Engineering should be notified to evaluate flowrates.
NOTES
- 1) Opening 1-FCV-30-61 (Tr A) and/or -62 (Tr B) LAST ensures positive Upper-to-Lower Containment press during the startup transient.
- 2) 1-FCV-30-61 and 1-FCV-30-62 MUST remain CLOSED if moving irradiated fuel with Containment open to ABSCE spaces, UNLESS 1-HS-90-410-A and 1-HS 415-B are in the REFUEL position.
STEP 9: [15] PERFORM the following: (N/A if NOT selected)
STANDARD:
Applicant locates 1-HS-30-61A, PURGE EXH FAN A SUCT, and then rotates the handswitch to the RIGHT to the OPEN position. (Critical).
Applicant observes RED lights LIT and GREEN lights DARK on SUP and EXH.
Applicant enters N/A for 1-HS-30-62A, PURGE EXH FAN B SUCT since this flowpath will not be used.
Step is critical to align Train A of the purge system.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 13 0F 17 STEP 10: [16] ENSURE the following: (N/A Train NOT used)
STANDARD:
Applicant locates PURGE SUP SUCT ISOL DAMPER 1-XI-30-294 and observes RED light LIT, GREEN light DARK.
Applicant locates PURGE SUP SUCT ISOL DAMPER 1-XI-30-295 and observes RED light LIT, GREEN light DARK.
Applicant locates DAMPER 1-XI-30-1A and observes RED light LIT, GREEN light DARK.
Applicant locates DAMPER 1-XI-30-1B and observes RED light LIT, GREEN light DARK.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 14 0F 17 STEP 11: [16] ENSURE the following: (N/A Train NOT used)
STANDARD:
Applicant enters N/A for DAMPER 1-XI-30-4A and DAMPER 1-XI-30-4B since this flowpath is not used.
COMMENTS:
___ SAT
___ UNSAT STEP 12: [17] CHECK flow on 1-FI-90-400, SHIELD BLDG VT FLOW [1-M-9]. (N/A if FI NOT available)
STANDARD:
Applicant locates 1-FI-90-400, SHIELD BLDG VT FLOW and observes approximately 12000 -13000 cfm.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 15 0F 17 STEP 13: [18] IF FI-90-400 is NOT available, THEN ENSURE Flow being estimated per 1-SI-0-2, Shift & Daily Log.
STANDARD:
Applicant enters N/A for Step 18 since 1-FI-90-400 is available.
COMMENTS:
___ SAT
___ UNSAT STEP 15: Applicant notifies the Unit Supervisor that Upper Containment Purge is in service STANDARD:
Applicant informs the Unit Supervisor that Steps 10 through 18 of SOI-30.02, Containment Purge System, Section 5.1, Start Up Upper Containment Purge, are complete.
CUE:
Repeat back information provided by the applicant.
COMMENTS:
END OF TASK
___ SAT
___ UNSAT STOP TIME ________
H Handout Package for Applicant
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
H INITIAL CONDITIONS:
- 1. Unit 1 is in Mode 1.
- 2. Train A Upper Containment Purge is being placed in service.
- 3. SOI-30.02, Containment Purge System, Section 5.1, Start Up Upper Containment Purge, has been completed through Step 9.
- 4. The area around the Service Building Air Intake is clear of fumes and there are no vehicles running in the vicinity.
- 5. Unit 1 Shield Building Exhaust Monitor and its isokinetic sampler are operable.
- 6. You are an extra operator assigned to the shift.
INITIATING CUES:
The Unit Supervisor has directed you to perform Steps 10 through 18 of SOI-30.02, Containment Purge System, Section 5.1, Start Up Upper Containment Purge.
Inform the Unit Supervisor when Step 18 is complete.
NOTE:
At Step 13, you are to use dampers 1-FCV-30-7 & 51, and 1-FCV-30-8 & 50.
Watts Bar Nuclear Plant 2013-03 NRC Exam System JPM I
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I
2013-03 NRC Exam PAGE 2 OF 24 EVALUATION SHEET Task:
REMOVE 120V AC VITAL INVERTER 1-I FROM SERVICE PER SOI-235.01 Alternate Path:
n/a Facility JPM #:
3-OT-JPMA005 Safety Function:
6
Title:
Electrical K/A 057 AA1.01 Ability to operate and / or monitor the following as they apply to the Loss of Vital AC Instrument Bus: Manual inverter swapping.
Rating(s):
3.7/3.7 CFR:
41.7 / 45.5 / 45.6 Evaluation Method:
Simulator In-Plant X
Classroom
References:
SOI-235.01, 120V AC VITAL POWER SYSTEM 1-I, Rev. 28.
Task Number:
AUO-235-SOI-235.1-04
Title:
Remove a 120V AC Vital Inverter from service.
Task Standard:
The applicant completes SOI-235.01, 120V AC VITAL POWER SYSTEM 1-I, Section 7.1, Shutdown of 120V AC Vital Inverter 1-I, to remove the inverter from service.
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 I
2013-03 NRC Exam PAGE 3 OF 24 Tools/Equipment/Procedures Needed:
Hard Hat, Safety Glasses, Hearing Protection, Plant Approved Shoes, Gloves.
ALARA considerations.
Start this JPM in the Main Control Room, near the steps into the Control Building.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I
2013-03 NRC Exam PAGE 4 OF 24 READ TO APPLICANT DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.
INITIAL CONDITIONS:
- 1. The Unit is operating at 100% RTP.
- 2. Inverter 1-I is currently in service.
- 3. The CB AUO on the previous shift transferred 120V AC Vital Power Board 1-I to Spare 120V AC Inverter 0-1 per SOI-235.01, 120V AC Vital Power System 1-I, Section 8.3, Transfer 120V AC Vital Instrument Power Board 1-I to Spare 120V AC Vital Inverter 0-I.
- 4. The Shift Manager and Unit Supervisor have referenced Tech. Specs.
- 5. Maintenance has requested that Inverter 1-I be de-energized and tagged to allow them to make a minor circuit repair.
- 6. You are an AUO on shift.
INITIATING CUES:
The Unit Supervisor has directed you to de-energize 120V AC Vital Inverter 1-I per procedure to prepare it for tagging using SOI-235.01, 120V AC Vital Power System 1-I, Section 7.1, Shutdown of 120V AC Vital Inverter 1-I.
You are to inform the Unit Supervisor when the procedure is completed.
NOTE: A Unit Supervisor will write and place clearance tags at a later time.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 5 of 24 START TIME: _______
NOTE Steps 7.1[1] through 7.1[14] below will still provide output to the 120V AC VITAL INSTRUMENT POWER BD 1-I through the Regulated Transformer Bypass Source even though Inverter 1-I will be shutdown.
CAUTION Step 7.1[17] will remove all power sources to 120V AC VITAL INSTRUMENT POWER BD 1-I unless Spare Inverter 0-I is in service to the board.
STEP 1: [1] NOTIFY SRO that removing 120V AC Vital Inverter 1-I from service may require entry into LCOs, AND OBTAIN SRO approval prior to performing this Section.
STANDARD:
SRO approval has been obtained. This is given in the INITIAL CONDITIONS. The applicant may or may not repeat this step.
CUE:
If asked, inform applicant that SRO approval has been obtained.
COMMENTS:
___ SAT
___ UNSAT NOTE All steps in this section are performed at 1-INV-235-1, 120V AC Vital Inverter 1-I, A3R/772, unless otherwise noted.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 6 of 24 STEP 2: [2] CHECK 1-XI-235-1/P3, IN SYNC, LIT.
STANDARD:
Applicant locates 1-XI-235-1/P3, IN SYNC, and indicates that it is LIT.
CUE:
When the light is checked, state that the GREEN light is LIT.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 7 of 24 STEP 3: [3] PRESS AND RELEASE 1-HS-235-1/SW202, BYPASS TO LOAD.
STANDARD:
Applicant locates 1-HS-235-1/SW202, BYPASS TO LOAD and demonstrates pressing and releasing the switch.
CUE:
After applicant demonstrates how to operate the switch, state that the switch has been pressed and released.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 8 of 24 STEP 4: [4] CHECK 1-XI-235-1/P1, INVERTER SUPPLYING LOAD, DARK.
STANDARD:
Applicant locates 1-XI-235-1/P1, INVERTER SUPPLYING LOAD, and describes that the light is DARK.
CUE:
When the light is checked, state that the light is DARK.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 9 of 24 STEP 5: [5] CHECK 1-XI-235-1/P2, BYPASS SOURCE SUPPLYING LOAD, LIT.
STANDARD:
Applicant locates 1-XI-235-1/P2, BYPASS SOURCE SUPPLYING LOAD, determines has been checked to be LIT.
CUE:
When the light is checked, state that the AMBER light is LIT.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 10 of 24 STEP 6: [6] PLACE 1-BKR-235-1/CB2, INVERTER OUTPUT, to OFF.
STANDARD:
Applicant locates 1-BKR-235-1/CB2, INVERTER OUTPUT, and indicates that the breaker switch must be pushed down to place the breaker in the OFF position. (Critical).
CUE:
After applicant demonstrates how to open the breaker, state that the breakers handle is down.
(Picture below shows initial position of 1-BKR-235-1/CB2.)
Step is critical to de-energize the inverter.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 11 of 24 STEP 7: [7] PLACE 1-HS-235-1/SW1, MANUAL BYPASS SWITCH, TO BYPASS TO LOAD POSITION.
STANDARD:
Applicant locates 1-HS-235-1/SW1, MANUAL BYPASS SWITCH, indicates how to place the switch to the BYPASS TO LOAD POSITION.
CUE:
After applicant demonstrates how to operate the switch, state that the switch is in the BYPASS TO LOAD POSITION.
(Picture below shows initial position of 1-HS-235-1/SW1).
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 12 of 24 STEP 8: PLACE 1-BKR-235-1/CB1, BATTERY INPUT, to OFF.
STANDARD:
Applicant locates 1-BKR-235-1/CB1, BATTERY INPUT and indicates that the breaker switch must be pushed down to place the breaker in the OFF position.
CUE:
After applicant demonstrates how to open the breaker, state that the breakers handle is down.
(Picture below shows initial position of 1-BKR-235-1/CB1.)
Step is critical to de-energize the inverter.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 13 of 24 STEP 9: [9] PLACE 1-BKR-235-1/CB301, AC INPUT TO RECTIFIER, to OFF.
STANDARD:
Applicant locates 1-BKR-235-1/CB301, AC INPUT TO RECTIFIER and indicates that the breaker switch must be pushed down to place the breaker in the OFF position. (Critical).
CUE:
After applicant demonstrates how to open the breaker, state that the breakers handle is down.
(Picture below shows initial position of 1-BKR-235-1/CB301.)
Step is critical to de-energize the inverter.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 14 of 24 EXAMINER: The following meter is in a TRIP SENSITIVE AREA. Inform the applicant that the meter is reading ZERO.
STEP 10: [10] CHECK 1-EI-235-1/V1, INVERTER OUTPUT, APPROXIMATELY ZERO.
STANDARD:
Applicant locates1-EI-235-1/V1, INVERTER OUTPUT, and indicates that the meter should be reading approximately zero.
CUE:
After applicant demonstrates how to read 1-EI-235-1/V1, inform the applicant that the meter is at ZERO.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 15 of 24 EXAMINER: The following meter is in a TRIP SENSITIVE AREA. Inform the applicant that the meter is reading ZERO.
STEP 11: [11] CHECK 1-EI-235-1/V301, RECTIFIER DC OUTPUT, APPROXIMATELY ZERO.
STANDARD:
Applicant locates 1-EI-235-1/V301, RECTIFIER DC OUTPUT, and indicates that the meter should be reading approximately zero.
CUE:
After applicant demonstrates how to read 1-EI-235-1/V301, inform the applicant that the meter is at ZERO.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 16 of 24 STEP 12: [12] PLACE 1-BKR-235-1/CB4, BYPASS SOURCE AC INPUT, to OFF.
STANDARD:
Applicant locates 1-BKR-235-1/CB4, BYPASS SOURCE AC INPUT and indicates that the breaker switch must be pushed down to place the breaker in the OFF position. (Critical).
CUE:
After applicant demonstrates how to open the breaker, state that the breakers handle is down.
(Picture below shows initial position of 1-BKR-235-1/CB4.)
Step is critical to de-energize the inverter.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 17 of 24 STEP 13: [13] PERFORM the following independent verifications at 120V AC VITAL INVERTER 1-I:
STANDARD:
Applicant requests that an Independent Verification be performed by another qualified person.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 18 of 24 STEP 14: [14] ENSURE 1-HS-235-1/SW2, AN1 ANNUNCIATOR DISABLE, in DISABLE.
STANDARD:
Applicant locates 1-HS-235-1/SW2, AN1 ANNUNCIATOR DISABLE and indicates that the toggle switch must be moved to the RIGHT to the DISABLE position.
CUE:
After applicant demonstrates how to operate the switch, state that the switch is in the DISABLE position.
(Picture below shows initial position of 1-HS-235-1/SW2.)
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT CAUTION 120V AC VITAL INSTRUMENT POWER BD 1-I is now supplied through the Regulated Transformer Bypass Source unless the Spare Inverter 0-I is in service to the board. To remove this supply to the Instrument Power Board and perform complete Inverter 1-I shutdown, continue performance of the following steps.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 19 of 24 STEP 15: [15] ENSURE 120V AC VITAL INSTRUMENT POWER BD 1-I is supplied from Spare Inverter 0-I unless the board to be deenergized per Section 7.3, Shutdown of 120V AC Vital Instrument Power Board 1-I.
STANDARD:
Applicant recalls from INITIAL CONDITIONS that Spare Inverter 0-1 is supplying 120V AC Vital Instrument Power Board 1-I.
COMMENTS:
___ SAT
___ UNSAT STEP 16: [16] ENSURE the present configuration is NOT required for maintenance activities.
STANDARD:
Applicant verifies the present configuration is required for maintenance activities.
CUE:
State that the present configuration is not required for maintenance activities.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 20 of 24 STEP 17: [17] PLACE 1-BKR-235-1/CB701, AC INPUT TO ISOLIMITER, to OFF.
STANDARD:
Applicant locates 1-BKR-235-1/CB701, AC INPUT TO ISOLIMITER and indicates that the breaker switch must be pushed down to place the breaker in the OFF position. (Critical).
CUE:
After applicant demonstrates how to open the breaker, state that the breakers handle is down.
(Picture below shows initial position of 1-HS-235-1/CB701.)
Step is critical to de-energize the inverter.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 21 of 24 STEP 18: [18] ENSURE 1-HS-235-1/SW3, AN2 ANNUNCIATOR DISABLE, in DISABLE.
STANDARD:
Applicant locates 1-HS-235-1/SW3, AN2 ANNUNCIATOR DISABLE and indicates that the toggle switch will be moved to the RIGHT to place the switch in DISABLE. (Critical).
CUE:
After applicant demonstrates how to operate the switch, state that the switch is in the DISABLE position.
(Picture below shows initial position of 1-HS-235-1/SW3.)
Step is critical to de-energize the inverter.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT Page 22 of 24 STEP 19: [19] NOTIFY Unit Operator that Vital Inverter 1-I has been shutdown and alarms associated with ANNUNCIATOR 17-C, 120 AC VITAL INVERTER 1-I / 0-I ABNORMAL should be reset.
STANDARD:
Applicant notifies Unit Operator that Vital Inverter 1-I has been shutdown and alarms associated with ANNUNCIATOR 17-C, 120 AC VITAL INVERTER 1-I / 0-I ABNORMAL should be reset.
CUE:
When contacted as the Unit Operator, repeat back the information provided.
COMMENTS:
END OF TASK
___ SAT
___ UNSAT STOP TIME ________
I I
Handout Package for Applicant
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
I INITIAL CONDITIONS:
- 1. The Unit is operating at 100% RTP.
- 2. Inverter 1-I is currently in service.
- 3. The CB AUO on the previous shift transferred 120V AC Vital Power Board 1-I to Spare 120V AC Inverter 0-1 per SOI-235.01, 120V AC Vital Power System 1-I, Section 8.3, Transfer 120V AC Vital Instrument Power Board 1-I to Spare 120V AC Vital Inverter 0-I.
- 4. The Shift Manager and Unit Supervisor have referenced Tech. Specs.
- 5. Maintenance has requested that Inverter 1-I be de-energized and tagged to allow them to make a minor circuit repair.
- 6. You are an AUO on shift.
INITIATING CUES:
The Unit Supervisor has directed you to de-energize 120V AC Vital Inverter 1-I per procedure to prepare it for tagging using SOI-235.01, 120V AC Vital Power System 1-I, Section 7.1, Shutdown of 120V AC Vital Inverter 1-I.
You are to inform the Unit Supervisor when the procedure is completed.
NOTE: A Unit Supervisor will write and place clearance tags at a later time.
Watts Bar Nuclear Plant 2013-03 NRC Exam System JPM J
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J
2013-03 NRC EXAM PAGE 2 OF 16 EVALUATION SHEET Task:
LOCAL OPERATION OF TURBINE DRIVEN AFW PUMP.
Alternate Path:
The applicant will have to reset trip and throttle per section 8.3 to complete task.
Facility JPM #:
3-OT-JPMA015A Safety Function:
4S
Title:
Heat Removal From Reactor Core, Secondary System K/A 061 A2.04 Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: pump failure or improper operation.
Rating(s):
3.4/3.8 CFR:
41.5 / 43.5 / 45.3 / 45.13 Evaluation Method:
Simulator In-Plant X
Classroom
References:
1-ECA-0.0, Loss of Shutdown Power, Rev. 0.
SOI-3.02, Auxiliary Feedwater System, Rev.52.
Task Number:
AUO-003-SOI-3.02-003
Title:
Manual startup of the Turbine Driven Auxiliary Feedwater pump.
Task Standard:
The applicant:
1.) Transfers control power to the local control station.
2.) Resets the mechanical overspeed device.
3.) Locally latches 1-FCV-1-51 motor drive to the valve stem.
3.) Starts the AFW Pump A-S from the local station.
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 J
2013-03 NRC EXAM PAGE 3 OF 16 Tools/Equipment/Procedures Needed:
Hard Hat, Safety Glasses, Hearing Protection, Plant Approved Shoes, Gloves.
ALARA considerations.
Start this JPM at the Rad Waste Desk in the Auxiliary Building.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J
2013-03 NRC EXAM PAGE 4 OF 16 READ TO APPLICANT DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.
INITIAL CONDITIONS:
- 1. Unit 1 has experienced a total loss of all AC.
- 2. The crew is in the process of implementing 1-ECA-0.0, Loss of Shutdown Power.
- 4. 1-HS-46-56A-S, T-D AFWP T&T VLV has no lights and appears to have lost power.
INITIATING CUES:
The OAC has directed you, the Aux. Bldg. AUO to locally operate the Unit 1 TD AFW pump using SOI-3.02, Auxiliary Feedwater System.
Inform the OAC when you have completed SOI-3.02 and the TD AFW pump is in service.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J
2013-03 NRC EXAM STEP/STANDARD SAT/UNSAT PAGE 5 0F 16 START TIME: _______
EXAMINER: DO NOT hand the applicant the copy of SOI-3.02, Auxiliary Feedwater System, Section 8.3, Resetting AFWT Overspeed Trip, until the applicant identifies the need to implement the section in the JPM Step 4.
CAUTION Large gauges at top of Panel 1-L-381 are Wide Range instruments. The Narrow Range gauges, which provide a more accurate SG Level indication, are on the Level Indicating Controllers.
NOTE This section normally is NOT necessary for performance unless MCR is inaccessible. This section may be used for troubleshooting or other testing.
STEP 1: [1] PERFORM the following:
[1.1] PLACE 1-XS-46-57, TD AFW PMP CONTROLS TRANSFER SWITCH to AUX. [behind CCS seal leakage tank]
STANDARD:
Applicant locates 1-XS-46-57, TD AFW PMP CONTROLS TRANSFER SWITCH and indicates that the switch must be rotated from the NORMAL (vertical) position to the RIGHT to the AUX position. (Critical).
CUE:
If/when asked, indicate that the switch is vertical (normal) position, and after switch is rotated, indicate switch is in the AUX position.
Step is critical to enable local controls.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J
2013-03 NRC EXAM STEP/STANDARD SAT/UNSAT PAGE 6 0F 16 STEP 2: [1] PERFORM the following:
[1.2] PLACE 1-XS-46-57A, TD AFW PMP FW DISCH FLOW IND CNTLR XFER SW to AUX. [Behind Panel 1-L-381 on outside corner wall of pump room]
STANDARD:
Applicant locates 1-XS-46-57A, TD AFW PMP FW DISCH FLOW IND CNTLR XFER SW to AUX and indicates that the switch must be rotated from the NORMAL (vertical) position to the RIGHT to the AUX position.
(Critical).
CUE:
If/when asked, indicate that the switch is vertical (normal) position, and after switch rotated indicate switch is in the AUX position.
Step is critical to enable local controls.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J
2013-03 NRC EXAM STEP/STANDARD SAT/UNSAT PAGE 7 0F 16 STEP 3: [2] ENSURE 1-FCV-1-51, TD AUX FEEDWATER PMP TRIP &
THROTTLE VALVE is RESET. (REFER TO Section 8.3)
STANDARD:
Applicant locates 1-FCV-1-51 and ensures the trip and throttle valve is reset by observing lever/linkage position. (Critical).
CUE:
If/when asked, indicate the mechanical overspeed trip rod is moved toward the pump (in the tripped position),
and the latch pieces are not meshed.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT EXAMINER: When asked, provide the applicant Handout J - 2, SOI-3.02, Auxiliary Feedwater System, Section 8.3, Resetting AFWT Overspeed Trip.
The following actions are taken from SOI-3.02, Auxiliary Feedwater System, Section 8.3, Resetting AFWT Overspeed Trip.
NOTES
- 1) Following an Overspeed Trip, the 1-HS-46-56B, TD AFW PMP TRIP/THV 1-FCV-1-51 POS CNTL, local limit lights will show valve CLOSED.
- 2) Figure 1 provides additional information for local operation.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J
2013-03 NRC EXAM STEP/STANDARD SAT/UNSAT PAGE 8 0F 16 STEP 4: [1] IF a Mechanical Overspeed Trip occurred, THEN RELATCH the Mechanical Overspeed Trip Device locally.
STANDARD:
Applicant locates the Mechanical Overspeed Linkage and indicates how to reset by describing that the connecting rod must be moved towards the T&T valve by pulling the reset connecting rod towards the trip and throttle valve till movement stops. (Critical).
CUE:
If/when asked, after performer demonstrates proper method to reset trip device, then state the trip lever remains in the engaged position but the valve stem pieces are not meshed.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT STEP 5: [2] IF in the MCR, THEN PLACE 1-HS-46-56A-S, T-D AFWP T&T VLV, in CLOSE, AND HOLD for 30 seconds to latch 1-FCV 51 motor drive to the valve stem.
STANDARD:
Applicant N/As step based upon task assignment initial conditions and proceeds to next step.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J
2013-03 NRC EXAM STEP/STANDARD SAT/UNSAT PAGE 9 0F 16 STEP 6: [3] IF local [A3T/692], THEN:
[3.1] PLACE 1-XS-46-57, TD AFW PMP CONTROLS TRANSFER SWITCH to AUX. [behind CCS seal leakage tank]
STANDARD:
Applicant determines 1-XS-46-57 had been placed in the AUX position (JPM Step 2). If not, then the applicant locates 1-XS-46-57 and places it to AUX position. (Critical).
CUE:
If/when asked, indicate that the switch is vertical (normal) position, and after switch rotated indicate switch is in the AUX position.
Step is critical to latch motor operator to the valve stem.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J
2013-03 NRC EXAM STEP/STANDARD SAT/UNSAT PAGE 10 0F 16 STEP 7: [3] IF local [A3T/692], THEN:
[3.2] DEPRESS 1-HS-46-56B, TD AFW PMP and TRIP/THV 1-FCV-1-51 POS CNTL, to CLOSE, AND HOLD for 30 seconds to latch 1-FCV-1-51 motor drive to the valve stem.
STANDARD:
Applicant locates 1-HS-46-56B and indicates that the CLOSE position push button must be depressed. (Critical).
CUE:
After performer demonstrates depressing 1-HS-46-56B, when asked, state that the motor can be heard, and the latch has engaged.
Step is critical to latch motor operator to the valve stem.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT STEP 8: [4] IF Turbine will NOT be restarted immediately, THEN ENSURE motor drive is latched to valve stem (locally).
STANDARD:
Applicant determines from the INITIAL CONDITIONS that the pump will be restarted immediately, and enters N/A for this step.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J
2013-03 NRC EXAM STEP/STANDARD SAT/UNSAT PAGE 11 0F 16 STEP 9: [5] IF the overspeed trip occurred due to 1-FIC-46-57A, T-D AFWP FLOW CONTROLLER, failing to control automatically, THEN:
[5.1] PLACE 1-HS-46-57-S, T-D AFWP CONTROL, for 1-FIC-46-57A-S [M-4], in RESET.
[5.2] PLACE 1-FIC-46-57A-S, T-D AFWP FLOW CONTROLLER, in MANUAL.
[5.3] ENSURE controller is at minimum speed.
STANDARD:
Applicant determines from feedback from the Main Control Room that the 1-FIC-46-57A controller was not the cause of the overspeed.
CUE: If Main Control Room contacted, report that the controller was not the reason for the overspeed.
COMMENTS:
___ SAT
___ UNSAT STEP 10: [6] IF TD AFW PMP to be restarted from MCR, THEN PLACE 1-XS-46-57 TD AFW PMP CONTROLS TRANSFER SWITCH to NORMAL. [behind CCS seal leakage tank] AND GO TO Section 8.1.3.
STANDARD:
Applicant determines from the INITIAL CONDITIONS that this step is N/A and proceeds to the next step.
COMMENTS:
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J
2013-03 NRC EXAM STEP/STANDARD SAT/UNSAT PAGE 12 0F 16 STEP 11: [7] IF TD AFW PMP to be restarted locally THEN GO TO Section 8.4.
STANDARD:
Applicant returns to Section 8.4 for additional actions.
COMMENTS:
___ SAT
___ UNSAT STEP 12: [3] OPEN 1-FCV-1-51 using 1-HS-46-56B, TD AFW PMP TRIP/THV 1-FCV-1-51 POS CNTL (On Wall N. of Pump).
STANDARD:
Applicant locates 1-HS-46-56B, TD AFW PMP TRIP/THV 1-FCV-1-51 POS CNTL and indicates that the OPEN pushbutton is to be depressed and that when the valve is open the RED indicating light will be LIT and the GREEN indicating light will be DARK. (Critical)
CUE:
Inform the performer after push button has been depressed that lights for 1-HS-46-56B indicate RED LIT, green DARK.
CUE:
If asked, 1-FCV-1-51 is traveling OPEN and Turbine can be heard spinning up, governor action can be seen.
Step is critical to open steam supply to TD AFW pump governor valve.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J
2013-03 NRC EXAM STEP/STANDARD SAT/UNSAT PAGE 13 0F 16 STEP 13: [4] VERIFY pump comes to operating speed of 3900 to 4000 rpm.
STANDARD:
Applicant locates SI-46-56B and indicates that speed should be between 3900 and 4000 rpm.
CUE:
When checked, SI-46-56B indicates 4000 rpm.
COMMENTS:
___ SAT
___ UNSAT STEP 14: [5] NOTIFY Unit Operator that pump is in service.
STANDARD:
Applicant notifies the ACR operator that the AFW Pump A-S is in service.
CUE:
When notified, acknowledge the report using repeat back.
COMMENTS:
END OF TASK
___ SAT
___ UNSAT STOP TIME ________
J - 1 J - 1 Handout Package for Applicant
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
J - 1 INITIAL CONDITIONS:
- 1. Unit 1 has experienced a total loss of all AC power.
- 2. The crew is in the process of implementing ECA-0.0, 1-ECA-0.0, Loss of Shutdown Power.
- 4. 1-HS-46-56A-S, T-D AFWP T&T VLV has no lights and appears to have lost power.
INITIATING CUES:
The OAC has directed you, the Aux. Bldg. AUO to locally operate the Unit 1 TD AFW pump using SOI-3.02, Auxiliary Feedwater System.
Inform the OAC when you have completed SOI-3.02 and the TD AFW pump is in service.
J - 2 EXAMINER:
DO NOT hand to the applicant until the applicant identifies the need tor additional procedure steps.
J - 2 Handout Package 2 for Applicant
Watts Bar Nuclear Plant 2013-03 NRC Exam System JPM K
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K
2013-03 NRC Exam PAGE 2 OF 11 EVALUATION SHEET Task:
ALIGN UPPER CONTAINMENT MONITOR TO THE LOWER CONTAINMENT LOCALLY Alternate Path:
n/a Facility JPM #:
3-OT-JPMA044, modified to address local actions.
Safety Function:
7
Title:
Instrumentation K/A 073 A4.02 Ability to manually operate and/or monitor in the control room: Radiation monitoring system control panel.
Rating(s):
3.7 / 3.7 CFR:
41.7 / 45.5 to 45.8 Evaluation Method:
Simulator In-Plant X
Classroom
References:
SOI-90.02 Gaseous Process Radiation Monitors, Rev.52.
Task Number:
AUO-090-SOI-90.2-020
Title:
Align Upper Containment Monitor to lower containment.
Task Standard:
The applicant:
1.) Identifies the running sample pumps, and stops the pumps using 1-HS-90-106A and 1-HS-90-112A.
2.) Locates and demonstrates how to opens 1-ISIV-90-112A, LOWER CONTAINMENT SUP TO 1-RE-90-112 CROSS TIE.
3.) Locates 1-RE-90-112 IODINE LOW FLOW ALARM and resets the alarm using 1-HS-90-112JB.
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
2013-03 NRC Exam PAGE 3 OF 11 Tools/Equipment/Procedures Needed:
Hard Hat, Safety Glasses, Flashlight, Hearing Protection, Gloves and Plant Approved Shoes.
Start this JPM at the Rad Waste Desk in the Auxiliary Building.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K
2013-03 NRC Exam PAGE 4 OF 11 READ TO APPLICANT DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.
INITIAL CONDITIONS:
- 1. 1-RM-90-106 CNTMT BLDG LOWER COMPARTMENT AIR MONITOR and 1-RM-90-112 CNTMT BLDG UPPER COMPARTMENT AIR MONITOR are aligned and are sampling their respective containments (normal alignment).
- 2. Maintenance has requested that 1-RM-90-106 be removed from service in preparation for maintenance, and that 1-RM-90-112 be aligned to lower containment.
INITIATING CUES:
You have been directed by the Unit Supervisor to perform Steps 3 through 7 of SOI-90.02, Gaseous Process Radiation Monitors, Section 8.1, Align Upper Containment Monitor to Lower Containment," to align 1-RM-90-112 to sample lower containment.
You are to notify the Unit Supervisor when Step 7 is complete.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 5 0F 11 START TIME: _______
NOTE If 1-RM-90-112 is aligned in place of 1-RM-90-106, it is inoperable until Instrument Maintenance completes PM 639W (1-LPR-090-0112A-B file 2), which recalibrates the monitor alarm setpoints.
STEP 1: [3] ENSURE 1-RE-90-106 and 1-RE-90-112 pumps are OFF before aligning monitor. The following handswitches control power to the sample pumps: [A3U/737 on top of monitor enclosure]:
- 1-HS-90-106A
- 1-HS-90-106B
- 1-HS-90-112A
- 1-HS-90-112B STANDARD:
Applicant locally checks 106 and 112 monitor sample pumps.
CUE:
IF asked and when checked, state the following for respective monitor:
- RM-106, sample pump 106A RED on light is LIT and GREEN off light is DARK.
- RM-106, sample pump 106B RED on light is DARK and 106B GREEN off light is LIT.
- RM-112, sample pump 112A in service RED on light is LIT and 112A GREEN off light is LIT.
RM-112, sample pump 112B in service RED on light is DARK and sample pump 112B GREEN off light is LIT.
Applicant locates 1-HS-90-106A, and states that 1-HS-90-106A STOP pushbutton must be depressed.
CUE:
Sample pump for 106A GREEN light is LIT when 1-HS 106A STOP pushbutton is depressed.
Applicant locates 1-HS-90-112A, and states that 1-HS-90-112A STOP pushbutton must be depressed.
CUE:
Sample pump for 112A GREEN light is LIT when 1-HS 112A STOP pushbutton is depressed.
Step is critical prevent failure of 1-RE-90-106 and 1-RE-90-112 sample pumps during subsequent valve alignments.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 6 0F 11 STEP 2: [4] INITIAL the monitor sample pump STOPPED (N/A pump NOT stopped):
[4.1] 1-HS-90-112A
[4.2] 1-HS-90-112B STANDARD:
Applicant records that the sample pump was stopped with 1-HS 112A.
COMMENTS:
___ SAT
___ UNSAT EXAMINER: JPM steps 3 and 4 are part of the same procedure step, and can be performed in any order.
STEP 3: [5] PERFORM the following:
STANDARD:
Applicant locates 1-ISIV-90-112A and states that the hand wheel must be rotated counter clockwise until valve is fully open CUE: After applicant indicates how to open the valve, state that the valve handle rotated several turns in the counter clockwise direction and stopped.
Step is critical align to upper containment monitor to lower containment.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 7 0F 11 STEP 4: [5] PERFORM the following:
STANDARD:
Applicant contacts the Main Control Room to have the remaining valves placed in the correct positions. (Critical aspect is contacting the Main Control Room to complete alignment.)
CUE: After applicant discusses contacting the Main Control Room, state that the listed valves have been placed in the appropriate positions.
Step is critical align to upper containment monitor to lower containment, and ensure that the 1-RM-90-106 is isolated.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 8 0F 11 STEP 5: [6] START the monitor sample pump STOPPED in Step 8.1[3]
(N/A pump NOT started):
[6.1] 1-HS-90-112A
[6.2] 1-HS-90-112B STANDARD:
Applicant refers back to Step 3, and identifies that handswitch 1-HS 112A was placed in STOP.
Applicant locates 1-HS-90-112A, and states that 1-HS-90-112A START pushbutton must be depressed Step is critical since this establishes flow through 1-RE-90-112 radiation monitor from the lower containment.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K
2013-03 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 9 0F 11 STEP 6: [7] IF IODINE LOW FLOW ALARM on skid comes in, THEN RESET with 1-HS-90-112JB.
STANDARD:
Applicant locates the IODINE LOW FLOW ALARM on 1-RE-90-112 skid.
CUE:
IF asked and when checked, state the IODINE LOW FLOW ALARM is in alarm.
Applicant locates 1-HS-90-112JB, and states that 1-HS-90-112A switch must be rotated to the RESET position and then will spring return to the FLOW position.
Step is critical to clear local alarms.
COMMENTS:
CRITICAL STEP
___ SAT
___ UNSAT STEP 7: Applicant reports that 1-RE-90-112 has been aligned to the lower containment.
STANDARD:
Applicant informs the Unit Supervisor that 1-RE-90-112 has been aligned to the lower containment.
CUE:
Repeat back information.
COMMENTS:
END OF TASK
___ SAT
___ UNSAT STOP TIME ________
K Handout Package for Applicant
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
K INITIAL CONDITIONS:
- 1. 1-RM-90-106 CNTMT BLDG LOWER COMPARTMENT AIR MONITOR and 1-RM-90-112 CNTMT BLDG UPPER COMPARTMENT AIR MONITOR are aligned and are sampling their respective containments (normal alignment).
- 2. Maintenance has requested that 1-RM-90-106 be removed from service in preparation for maintenance and 1-RM-90-112 be aligned to lower containment.
INITIATING CUES:
You have been directed by the Unit Supervisor to perform Steps 3 through 7 of SOI-90.02, Gaseous Process Radiation Monitors, Section 8.1, Align Upper Containment Monitor to Lower Containment," to align 1-RM-90-112 to sample lower containment.
You are to notify the Unit Supervisor when Step 7 is complete.