ML12074A095
| ML12074A095 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 04/29/2011 |
| From: | Operator Licensing and Human Performance Branch |
| To: | Tennessee Valley Authority |
| References | |
| 50-390/11-302 | |
| Download: ML12074A095 (157) | |
Text
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.a 2011-12 NRC Exam FINAL SUBMITTAL B.1.a Retrieve a Dropped RCCA (Alternate Path)
PACE 1 OF 12
- WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.a 2011-12 NRC Exam EVALUATION SHEET Task:
Retrieve dropped RCCA 0-5, using AOI-2, Malfunction of the Reactor Control System.
Alternate Path:
All rods in Shutdown Bank D drop while withdrawing dropped rod C-5, requiring a manual trip of the reactor.
Facility JPM #:
3-OT-JPMRO95C Safety Function:
1
Title:
Reactivity Control K/A 001 A2.03 Ability to operate and / or monitor the following as they apply to the Dropped Control Rod: Controls and components necessary to recover rod Rating(s):
3.5/4.2 CFR:
41.5/43.5/45.3/45.13 Evaluation Method:
Simulator X
In-Plant Classroom
References:
AOl-2, Malfunction of the Reactor Control System, Rev. 38.
TI-i 2.04 Task Number:
RO-085-AOl-2-004
Title:
Respond to a dropped RCCA.
Task Standard:
The applicant:
- 1) Performs actions of AOl-2, Malfunction of Reactor Control System, Section 3.3, Dropped RCCA, to withdraw Shutdown Bank D rod 0-5.
- 2) Diagnose that Control Bank D, RCCA H-12 has dropped, and performs Immediate Operator Actions by manually tripping the reactor.
Validation Time:
18 minutes Time Critical:
Yes No X
Applicant:
V Time Start:
NAME Docket No.
Time Finish:
Performance Rating:
SAT UNSAT Performance Time Examiner:
/
V NAME SIGNATURE DATE COMMENTS PAGE 2 OF 12
WATTS BAR JCLEAR PLANT JOB PERFORMANCE MEASURE B.1.a 2011-12 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:
ENSURE NRC Examination Security has been established.
2.
RESET to Initial Condition by performing the following actions:
a.
Select ICManager on the THUNDERBAR menu (right hand side of Instructor Console Screen).
b.
Locate IC 311.
c.
Right click on IC 311.
d.
Select Reset on the drop down menu.
e.
Right click on RESET.
f.
Enter the password for IC 311.
g.
Select Yes on the INITIAL CONDITION RESET pop-up window.
h.
Perform SWITCH CHECK.
3.
ENSURE the following information appears on the Director Summary Screen:
Key Type Event Delay Inserted Ramp Initial Final Value rdl3cddhl2d control rod fail to position control bank d h12 25 4.
Ensure Auto Event Triggers is assigned to Event 25 as follows:
Open standard trigger file. Right click on Event I trigger and select edit.
The description should be Rod C5> 34 steps. The Event Code should read, pc_rdacOO32a>30.
5.
Place simulator in RUN and acknowledge any alarms.
7.
ENSURE a marked-up copy of AOl-2, Malfunction of Reactor Control System, Section 3.3, Dropped RCCA, signed (circled-and-slashed) through Step. 16 is available for each applicant.
8.
ENSURE Extra Operator is present in the simulator.
9.
Place simulator in FREEZE until Examiner cue is given.
PAGE 3 OF 12
WATTS BAR NUCLEAR PLANT
- JOB PERFORMANCE MEASURE B.1.a 2011-12 NRC Exam 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 plant was operating at 100% power when shutdown rod C-5 dropped into the core due to a power cabinet card problem about 15 minutes ago.
- 2. AOI-2, Malfunction of Reactor Control System, Section 3.3, Dropped RCCA, was entered and has been performed through Step 16.
- 3. Reactor power was reduced to 75% per the instruction.
- 4. The problem has been repaired.
- 5. The Unit Supervisor, Shift Manager, Reactor Engineering and STA have agreed on a retrieval rate of 64 steps per minute and a maximum power level of 75%.
- 6. You are the Operator-at-the-Controls.
INITIATING CUES:
The Unit Supervisor directs you to realign C-5 rod starting at AOl-2, Malfunction of Reactor Control System, Section 3.3, Dropped RCCA, Step 17.
PAOF 4 OF 12
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
1 1.a 2011-12 NRC Exam STEPISTANDARD SATIUNSAT START TIME:
EXAMINER: Rod speed is. NOT displayed on the CERPI monitors for Shutdown Bank C or Shutdown Bank D.
When 1-RBSS, ROD BANK SELECT is in any position other than MAN or AUTO, rod speed is set at 64 steps per minute.
STEP 1: 17. PLACE rod control in bank select position for affected bank.
CRITICAL STEP STANDARD:
SAT Applicant rotates 1-RBSS, ROD BANK SELECT to the left from the UNSAT MAN position to the SBD position to select shutdown bank D.
Step is critical to assure proper bank is selected to be aligned.
COMMENTS:
Page 5 of 12
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.a 2011-12 NRC Exam STEPISTANDARD SATIUNSAT NOTE Computer Points for individual rods are C0009A through C0035A for shutdown banks and C0039A through C0076A for control banks. Average rod position points are U0001 through U0013.Rod step position points are U0049 through U0056. All points are in ICS GROUP DISPLAY MENU listed in SPECIAL GROUPS as SG 1.
STEP 2: 18. RECORD the value of the following:
- Affected banks step counter(s)
UNSAT
- Computer step indication for rods in affected bank
- Bank overlap counter (N/A for shutdown bank) [control rod drive room, el 782, panel 1-L-122]
STANDARD:
Applicant records:
Shutdown Bank Group Step Counter 1-SBDGI
- 228 steps ICS Step Indication for Shutdown Bank.D C-5 0 steps E-13 228 steps Nil 229 steps L03 229 steps Applicant determines that the Bank overlap counter is not applicable to Shutdown Bank D.
COMMENTS:
Page 6 of 12
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.a 2011-12 NRC_Exam STEP/STANDARD SATIU NSAT STEP 3: 19. DISCONNECT all lift coils (toggle up) in affected bank, CRITICAL EXCEPT for dropped RCCA.
STEP STANDARD:
_Applicant places toggle switches for rods E-1 3, N-lI, & L-3 in the UNSAT disconnect position (up position) in cabinet 1 -XS-85-I.
Step is critical to assure proper rod is selected to be aligned and the remaining rods are not inadvertently positioned in the following steps.
COMMENTS:
NOTE The next step will cause a CONTROL ROD URGENT FAILURE alarm (except for Shutdown Banks C and D). After the rods are aligned and the rod position is updated, then this alarm will be reset.
EXAMINER: During the next step, annunciator 83-D will reflash, due to rod to bank deviation.
STEP 4: 20. INSERT affected RCCA greater than 10 steps, and SAT CONTINUE until NO RCCA motion observed on RPI.
UNSAT STANDARD:
Applicant inserts rods by placing 1-FLRM, ROD MOTION CONTROL IN-OUT to the IN position to insert rod C-5 at least 10 steps on step counter 1-SBDGI, SHUTDOWN BANK DI.
COMMENTS:
Page 7 of 12
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.a 2011-12 NRC Exam STEPISTANDARD
[
SATIUNSAT STEP 5: 21. SET affected step counter to 000,.
SAT STANDARD:
UNSAT The applicant lifts the cover on I -SBDGI, SHUTDOWN BANK D 1 and depresses the reset button (center button labeled RS) to set the counter to 000. The applicant may depress the D button multiple times to set the step counter to 000. The applicant closes the cover.
COMMENTS:
STEP 6: 22. USE the Plant Computer to set affected banks position to SAT zero:
UNSAT
- b. SELECT ROD BANK UPDATE.
- c. ENTER 0 in affected bank position, THEN PRESS F3 to save.
STANDARD:
Applicant uses the ICS plant computer Rod Bank update function to set Shutdown Bank D Step Counter to 0.
NOTE: Applicant may enter RBU in the ICS Computer to call up the Rod Bank Update Screen, instead of a. and b. above.
COMMENTS:
Page8ofl2
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.a 2011-12 NRC Exam STEP/STANDARD j
SAT/UNSAT STEP 7: 23. DO NOT CONTINUE UNTIL the following agree on a retrieval SAT rate:
UNSAT
- Unit SRO
- Shift Manager
- Reactor Engineering
- STA STANDARD:
Applicant determines that the above personnel have agreed to retrieval rate and maximum power level per initial conditions.
CUE:
If any one of the above are contacted, state that the Unit SRO, Shift Manager, Rx Engineering and STA are in agreement to retrieve the rod at normal manual speed of 64 steps/minute. Maximum power level is 75%. Recover from present power level. This information is provided in the INITIAL CONDITIONS.
COMMENTS:
Page 9 of 12
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.a 2011-12 NRC Exam STEPISTANDARb SATIUNSAT NOTE Boric acid requirements can be determined using Reactivity Briefing Sheet.
EXAMINER: The applicant may refer to the REACTIVITY BRIEFING BOOK for thumb rule values for boron for possible use in Step 24 (JPM Step 8).
STEP 8: 24. ALIGN RCCA to affected bank position:
- (p) USING rod control in Bank Select, position affected UNSAT RCCA to bank affected position recorded in Step 18
- (p) BORATE RCS to maintain T-ave and T-ref within 3°F.
- MAINTAIN less than or equal to 75% Reactor power.
STANDARD:
Applicant attempts to realign the rod by placing 1-FLRM, ROD MOTION CONTROL IN-OUT to the OUT position AND determines that the rod is withdrawing. Applicant stops withdrawing rod after recognizing other rods have dropped into core.
COMMENTS:
EXAMINER: During the performance of step 24 (JPM Step 8.) when Rod C-5 has been withdrawn approximately 35 steps, Control Bank D RCCA H-12 will drop. The applicant will perform the IMMEDIATE ACTIONS of AOI-2, Malfunction of Reactor Control System, Section 3.3, Dropped RCCA.
PagelOofl2
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.a 2011-12 NRC Exam STEPISTANDARD SATIUNSAT STEP 9:
- 1. PERFORM the following:
- a. CHECK ONLY ONE rod dropped UNSAT STANDARD:
Applicant determines that multiple rods have dropped and enters the RESPONSE NOT OBTAINED column for contingency actions.
COMMENTS:
STEP 10: 1. PERFORM the following:
CRITICAL STEP RESPONSE NOT OBTAINED:
- a. IF more than one rod dropped, THEN (p) TRIP reactor TO E-0, Reactor Trip or Safety Injection.
UNSAT STANDARD:
Applicant places the Reactor Trip hand switch on 1 -M-4 or 1 -M-6 to the TRIP position. The applicant begins performance E-0, Reactor Trip or Safety Injection.
Step is critical to task performance as two or more control rods dropped requires reactor trip.
CUE:
When performer begins to perform to E-0, Reactor Trip or Safety Injection actions, inform him/her that the JPM is complete. State that another operator will continue from here.
COMMENTS:
END OF TASK STOP TIME Page 11 of 12
I0 a) th 0
-C CaI
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- 1. The plant was operating at 100% power when shutdown rod C-5 dropped into the core due to a power cabinet card problem about 15 minutes ago.
- 2. AOI-2, Malfunction of Reactor Control System, Section 3.3, Dropped RCCA, was entered and performed through Step 16.
- 3. Reactor power was reduced to 75% per the instruction.
- 4. The problem has been repaired.
- 5. The Unit Supervisor, Shift Manager, Reactor Engineering and STA have agreed on a retrieval rate of 64 steps per minute and a maximum power level of 75%.
- 6. You are the Operator-at-the-Controls.
INITIATING CUES:
The Unit Supervisor directs you to realign the C-5 rod starting at AOl-2, Malfunction of Reactor Control System, Section 3.3, Dropped RCCA, Step 17.
B.1.a
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE
- B.1.b 2011-12 NRC Exam FINAL SUBMITTAL B.1.b Evaluate Pressurizer Level Trend And Take Proper Actions.
(Alternate Path)
PAGE 1 OF 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.b 2011-12 NRC Exam EVALUATION SHEET Task:
Evaluate Pressurizer Level Trend and perform appropriate actions of AOI-6, Small Reactor Coolant System Leak.
Alternate Path:
When Step 16 is evaluated, the applicant determines that pressurizer level is rising, and performs the RESPONSE NOT OBTAINED actions to place excess letdown in service.
Facility JPM #:
3-OT-JPMRO22 Safety Function:
2
Title:
Reactor Coolant System Inventory Control 004 A4.06 Ability to manually operate and/or monitor in the control room: Letdown isolation and flow control valves.
Rating(s):
3.6/3.1 CFR:
41.7 / 45.5 to 45.8 Evaluation Method:
Simulator X
In-Plant Classroom
References:
AOI-6, Small Reactor Coolant System Leak, Rev 34.
Task Number:
RO-068-AOl-6-001 RO-
Title:
Diagnose and respond to a small Reactor Coolant System leak.
Task Standard:
The applicant:
- 1) Determines that pressurizer level is rising and enters Step 16 RESPONSE NOT OBTAINED.
- 2) Places excess letdown in service and does NOT exceed 200°F as indicated on 1-TI-62-58, EXCESS LTDN TEMP.
Validation Time:
12 minutes Time Critical:
Yes No X
Applicant:
Time Start:
NAME Docket No.
Time Finish:
Performance Rating:
SAT UNSAT Performance Time Examiner:
/
NAME SIGNATURE DATE COM MENTS PAGE 2011
WATTS BA 4UCLEAR PLANT JOB PERFORMANCE MEASURE B.1.b 2011-12 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:
1.
ENSURE NRC Examination Security has been established.
2.
RESET to Initial Condition by performing the following actions:
a.
Select lCManager on the THUNDERBAR menu (right hand side of Instructor Console Screen).
b.
Locate IC 307.
c.
Right click on IC 307.
d.
Select Reset on the drop down menu.
e.
Right click on RESET.
f.
Enter the password for IC 307.
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 marked-up copy of AOl-6, Small Reactor Coolant System Leak is available for each applicant and is signed (circled-and slashed) through Step 15. Step 16 is circled.
5.
ENSURE that HANDOUT OF 1-LR-68-339 (the laminated recorder trace for 1-LR-68-339, PZR LEVEL %,) is available for each applicant.
6 ENSURE Extra Operator is present in the simulator.
7.
Place simulator in FREEZE until Examiner cue is given.
PAGE3OF 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.b 2011-12 NRC Exam 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 % power.
- 2. A small leak has occurred.
- 3. Letdown and Charging were isolated per AOI-6, Small Reactor Coolant System Leak, at 2125. (REFER TO HANDOUT OF 1-LR-68-339.)
- 4. You are an extra operator assigned to the crew.
INITIATING CUES:
The Unit Supervisor has directed you to perform AOI-6, Small Reactor Coolant System Leak, Step 16.
- 2. You are to notify the Unit Supervisor when Step 16 is complete.
PA(F 4 (iF I I
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.b 2011-12 NRC Exam STEPISTANDARD SATIUNSAT START TIME:
EXAMINER: AOl-6, Small Reactor Coolant System Leak, RESPONSE NOT OBTAINED is broken into JPM Steps I through 8.
NOTE Pzr level must be allowed time to change following changes in charging flow.
STEP 1: 16. CHECK pzr level DROPPING or STABLE.
SAT UNSAT STANDARD:
Applicant observes a RISING trend on 1-LR-68-339 PZR LEVEL enters RESPONSE NOT OBTAINED column for actions.
Applicant may also use the ICS computer to observe pressurizer level trends.
COMMENTS:
Page 5 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.b 2011-12 NRC_Exam STEP/STANDARD SAT/UNSAT STEP 2: 16. RESPONSE NOT OBTAINED CRITICAL STEP IF pzr level RISING, OR Leak verified isolated using Appendix B THEN PLACE excess letdown in service:
- a. OPEN 1-FCV-70-143.
UNSAT STANDARD:
At panel 1-M-27B, the applicant places 1-HS-70-143A to OPEN.
Applicant verifies the RED light is LIT and the GREEN light is OFF.
NOTE:
When the applicant opens 1-FCV-70-143, Annunciator 239-D may be received. This alarm occurs whenever 1-FCV-70-143 is OPEN and flow on 1-FS-70-8 is less than 230 gpm. It will only be received if 1-FCV-70 143 travels full open w/o opening 1-FCV-70-85.
Step is critical to establish cooling water to the excess letdown heat exchanger prior to establishing flow from the RCS.
COMMENTS:
Page 6of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.b 2011-12 NRC_Exam STEPISTAN DARD SATIUNSAT STEP 3: 16. RESPONSE NOT OBTAINED CRITICAL STEP IF pzr level RISING, OR Leak verified isolated using Appendix B THEN PLACE excess letdown in service:
- b. OPEN 1-FCV-70-85.
UNSAT STANDARD:
The applicant places 1-HS-70-85A to OPEN and holds the switch to OPEN until the RED light is LIT and the GREEN light is OFF.
Applicant may use 1-FI-70-84 (panel 1-M-27B) to monitor flow.
NOTE:
When the applicant opens 1-FCV-70-85, Annunciator 239-D will clear as soon as flow is greater than 230 gpm Step is critical to establish cooling water to the excess letdown heat exchanger prior to establishing flow from the RCS.
COMMENTS:
Page 7 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.b 2011-12 NRC_Exam STEPISTANDARD SAT/UNSAT STEP 4: 16. RESPONSE NOT OBTAINED CRITICAL STEP IF pzr level RISING, OR Leak verified isolated using Appendix B THEN PLACE excess letdown in service:
- c. OPEN 1-FCV-62-54.
UNSAT STANDARD:
_At panel 1-M-5, the applicant places 1-HS-62-54 to OPEN and ensures the RED light is LIT and the GREEN light is OFF.
Step is critical to establish excess letdown flow from the RCS.
COMMENTS:
STEP 5: 16. RESPONSE NOT OBTAINED CRITICAL STEP IF pzr level RISING, OR Leak verified isolated using Appendix B THEN PLACE excess letdown in service:
- d. OPEN 1-FCV-62-55.
UNSAT STANDARD:
The applicant places 1-HS-62-55 to OPEN and ensures RED light is LIT and the GREEN light is OFF.
Step is critical to establish excess letdown flow from the RCS.
COMMENTS:
Page 8 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.b 2011-12 NRC Exam STEP/STANDARD SAT/UNSAT STEP6: 16. RESPONSE NOTOBTAINED SAT IF pzr level RISING, OR Leak verified isolated using UNSAT Appendix B THEN PLACE excess letdown in service:
- e. ENSURE 1-FCV-62-59 in NORMAL.
STANDARD:
The applicant determines that 1-HS-62-59A is in the NORM position, with the RED seal return light LIT.
COMMENTS:
STEP 7: 16. RESPONSE NOT OBTAINED CRITICAL STEP IF.pzr level RISING, OR Leak verified isolated using Appendix B THEN PLACE excess letdown in service:
- f. ADJUST 1-HIC-62-56A to obtain maximum flow and UNSAT maintain excess letdown hx outlet temp less than 200 °F.
STANDARD:
The applicant opens 1-HIC-62-56A while monitoring 1-Tl-62-58. Excess letdown temperature must remain below 200°F as indicated on 1-Tl 58.
Step is critical to establish excess letdown flow from the RCS.
COMMENTS:
Page 9 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.b 2011-12 NRC Exam STEPISTANDARD SAT/UNSAT STEP 8: 16. RESPONSE NOTOBTAINED
_SAT STABILIZE pzr level by adjusting seal injection and excess UNSAT letdown flows. ** GO TO Step 20.
STANDARD:
Applicant observes pzr level trend on I -LR-68-339. Applicant may also set up a trend of pzr level on lOS computer using inputs from 1-Ll 339A, 1-Ll-68-335A and 1-Ll-68-320.
The applicant notifies the Unit Supervisor that Step 16 is complete.
CUE:
After the applicant has evaluated the trend and determined whether adjustments are to be made, state another operator will continue from here.
EXAMINER QUESTION: Based on the current level trend, what actions are required to stabilize level.
COMMENTS:
END OF TASK STOP TIME Page 10 of 11
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- 1. The Unit is operating at 100 % power.
- 2. A small leak has occurred.
- 5. Letdown and Charging were isolated per AOI-6, Small Reactor Coolant System Leak, at 2125. (REFER TO HANDOUT OF 1-LR-68-339.)
- 3. You are an extra operator assigned to the crew.
INITIATING CUES:
- 1. The Unit Supervisor has directed you to perform AOI-6, Small Reactor Coolant System Leak, Step 16.
- 2. You are to notify the Unit Supervisor when Step 16 is complete.
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WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.c 2011-12 NRC Exam FINAL SUBMITTAL B.1.c Align an RHR train for Hot Leg Recirculation per ES-1.4.
(Alternate Path)
PA(P I flF IS
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.c 2011-12 NRC Exam EVALUATION SHEET Task:
Align an RHR train for Hot Leg Recirculation per ES-i.4 Alternate Path:
During alignment of A Train, 1-FCV-74-33 Train A RHR Crosstie, will not open, therefore the operator will need to realign A Train RHR to cold leg recirc and then align B RHR Train to Hot Leg Recirc.
Facility JPM #:
3-OT-JPMRO71A Safety Function:
3
Title:
RCS Pressure Control KIA 006 A4.04 Ability to manually operate and/or monitor in the control room: RHRS.
Rating(s):
3.7 / 3.6 CFR:
41.7/45.5 to 45.8 Evaluation Method:
Simulator X
In-Plant Classroom
References:
ES-i.4, Transfer to Hot Leg Recirculation, Rev. ii.
Task Number:
RO-113-ES-i.4-00i
Title:
Task Standard:
Applicant attempts to align RHR Train A to supply hot leg recirc. Since the attempt is unsuccessful due to a valve failure, the applicant places RHR Train B in hot leg recirc.
Validation Time:
15 minutes Time Critical:
Yes No X
Applicant:
Time Start:
NAME SSN Time Finish:
Performance Rating:
SAT UNSAT Performance Time Examiner:
/
NAME SIGNATURE DATE COMMENTS PA(P 21W 15
WATTS BAR kCLEAR PLANT JOB PERFORMANCE MEASURE B.1.c 2011-12 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:
ENSURE NRC Examination Security has been established.
2.
RESET to Initial Condition by performing the following actions:
a.
Select lCManager on the THUNDERBAR menu (right hand side of Instructor Console Screen).
b.
Locate IC 312.
c.
Right click on IC 312.
d.
Select Reset on the drop down menu.
e.
Right click on RESET.
f.
Enter the password for IC 312.
g.
Select Yes on the INITIAL CONDITION RESET pop-up window.
h.
Perform SWITCH CHECK.
3.
ENSURE the following information appears on the Director Summary Screen:
Type Event Delay R
00:00:00 Key hs-74-33a hs-74-33a rhr heat exch a bypass sw 3.
Place simulator in RUN and acknowledge any alarms.
6.
Place simulator in RUN and acknowledge any alarms.
7.
Place simulator in FREEZE until Examiner cue is given.
Inserted Ramp Initial Final Value 00:00:00 close close PAGE 3 OF 15
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.c 2011-12 NRC Exam DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications.
I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
I. A Large Break LOCA has occurred.
- 2. Three hours have elapsed since the Large Break LOCA occurred.
- 4. You are the Operator at the Controls.
INITIATING CUES:
I. The Unit Supervisor directs you to align RHR for hot leg recirculation using ES-I.4, Transfer to Hot Leg Recirculation.
- 2. You are to notify the Unit Supervisor when RHR is aligned for hot leg recirculation.
PA( 4 OF 1P
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.c 2011-12 NRC Exam STEPISTANDARD I
START TIME:
NOTE If problems are encountered during transfer to hot leg, then cold leg recirc should be continued or restored during TSC evaluation of corrective actions.
STEP 1: 1. ALIGN RHR Train A for hot leg recirc:
- a. CLOSE RHR Train A cold leg isolation valve 1-FCV-63-93.
UNSAT STANDARD:
Applicant closes 1 -FCV-63-93, RHR Train A cold leg isolation valve, by rotating handswitch I -HS-63-93A, RHR TO CL 1 &4, to the left, and observing that the Red indicating light is DARK and the Green indicating light is LIT.
EXAMINER: 131-F ESF COMPONENT NOT NORMAL will alarm when 1-FCV-63-93 is closed. This is an expected alarm.
COMMENTS:
PAGE 5 OF 15
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.c 2011-12 NRC Exam STEPISTANDARD SATIUNSAT ]
STEP 2:
- 1. ALIGN RHR Train A for hot leg recirc:
SAT b.
ENSURE RHR Train B discharge crosstie valve UNSAT 1 -FCV-74-35 CLOSED.
STANDARD:
Applicant determines that 1-FCV-74-35, RHR Train B discharge crosstie valve is closed by observing 1-HS-73-35A, RHR HX B OUTLET XTIE, Red indicating light DARK and Green indicating light LIT.
COMMENTS:
STEP 3.
- 1. ALIGN RHR Train A for hot leg recirc:
- c. ENSURE RHR Train A spray valve 1-FCV-72-40 CLOSED.
UNSAT STANDARD:
Applicant determines that 1-FCV-72-40, RHR Train A spray valve is closed by observing handswitch 1 -HS-72-40A, RHR SPRAY HDR A TO CNTMT, Red indicating light DARK and Green indicating light LIT.
COMMENTS:
PAGE 6 OF 15
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
1 1.c 2011-12 NRC Exam STEPISTANDARD SATIUNSAT STEP 4.
- 1. ALIGN RHR Train A for hot leg recirc:
- d. ENSURE RHR Train B spray valve 1-FCV-72-41 CLOSED.
UNSAT STANDARD:
Applicant determines that 1-FCV-72-41, RHR Train B spray valve is closed by observing handswitch 1-HS-72-41A, RHR SPRAY HDR B TO CNTMT, Red indicating light DARK and Green indicating light LIT.
COMMENTS:
EXAMINER: An override is active which prevents the applicant from opening 1-FCV-74-33.
PAGE 7 OF 15
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.c 2011-12 NRC Exam STEPISTANDARD SATIUNSAT_I STEP 5.
- 1. ALIGN RHR Train A for hot leg recirc:
- e. OPEN RHR Train A discharge crosstie valve 1-FCV-74-33.
UNSAT STANDARD:
Applicant attempts to open 1-FCV-74-33, RHR Train A discharge crosstie valve, by rotating handswitch 1-HS-74-33A, RHR HX A OUTLET XTIE to the right. Applicant observes Red indicating light DARK and Green indicating light LIT, and states that the valve will NOT open.
EXAMINER: Valve will NOT open.
CUE:
If dispatched to determine the cause of 1-FCV-74-33 failing to open, repeat back information provided by the applicant. State that 1-FCV-74-33 appears to be jammed in the closed position.
Applicant enters RNO column, since the failure of 1-FCV-74-33 will prevent completion of Step 1 Action/Expected Response actions.
COMMENTS:
PAGE 8 OF 15
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.c 2011-12 NRC Exam STEP/STANDARD SATIUNSAT STEP 6:
Step I RESPONSE NOT OBTAINED SAT IF Train A NOT available for hot leg recirc, THEN:
UNSAT 1). RETURN RHR Train A to cold leg recirc alignment.
- 2) GO TO Step 2.
STANDARD:
Applicant opens 1-FCV-63-93, RHR Train A cold leg valve by rotating handswitch 1-HS-63-93, RHR TO CL 2&3 to the right. Applicant observes Red indicating light LIT and Green indicating light DARK.
EXAMINER:
131-F ESF COMPONENT NOT NORMAL will clear, and then re-flash when 1-FCV-63-93 is opened.
COMMENTS:
PAGE9OF 15
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.c 2011-12 NRC Exam
[
STEPISTANDARD SATIUNSAT]
STEP 7: 2. ALIGN RHR Train B for hot leg recirc:
CRITICAL STEP
- a. CLOSE RHR Train B cold leg isolation valve 1-FCV-63-94.
SAT STANDARD:
UNSAT closes 1-FCV-63-94, RHR Train B cold leg isolation valve, by rotating handswitch 1-HS-63-94, RHR TO CL 1&4 to the left, and observing that the Red indicating light is DARK and the Green indicating light is LIT.
EXAMINER:
131-F ESF COMPONENT NOT NORMAL will alarm when 1-FCV-63-94 is closed. This is an expected alarm.
Step is critical since it will allow RHR flow to be directed later to the correct hot leg.
COMMENTS:
STEP 8: 2. ALIGN RHR Train B for hot leg recirc:
SAT b.
ENSURE RHR Train A discharge crosstie valve 1-FCV UNSAT 33 CLOSED.
STANDARD:
(Applicant has already attempted to open 1-FCV-74-33 and was unsuccessfulIy)
Applicant determines that I -FCV-74-33 is closed by observing the RED indicating light DARK, GREEN indicating light LIT.
COMMENTS:
PAGE 10 OF 15
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.c 2011-12 NRC Exam
[
STEPISTANDARD STEP 9: 2. ALIGN RHR Train B for hot leg recirc:
SAT c.
ENSURE RHR Train A spray valve 1-FCV-72-40 CLOSED.
UNSAT STANDARD:
Applicant determines that 1-FCV-72-40, RHR Train A spray valve is closed by observing handswitch 1-HS-72-40A, RHR SPRAY HDR A TO CNTMT, Red indicating light DARK and Green indicating light LIT.
COMMENTS:
STEP 10: 2. ALIGN RHR Train B for hot leg recirc:
SAT d.
ENSURE RHR Train B spray valve 1-FCV-72-41 CLOSED.
UNSAT STANDARD:
Applicant determines that 1-FCV-72-40, RHR Train A spray valve is closed by observing handswitch 1-HS-72-41A, RHR SPRAY HDR B TO CNTMT, Red indicating light DARK and Green indicating light LIT.
COMMENTS:
PAGE 11 OF 15
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.c 2011-12 NRC Exam STEPISTANDARD SAT/UNSAT STEP 11: 2. ALIGN RHR Train B for hot leg recirc:
CRITICAL STEP
- e. OPEN RHR Train B discharge crosstie valve 1-FCV-74-35.
SAT STANDARD:
UNSAT
_Applicant opens 1-FCV-74-35, RHR Train B discharge crosstie valve, by rotating handswitch 1-HS-74-35A, RHR HX A OUTLET XTIE to the right. Applicant observes Red indicating light LIT and Green indicating light DARK.
Step is critical since it will allow RHR flow to be directed to the hot leg.
COMMENTS:
STEP 12: 2. ALIGN RHR Train B for hot leg recirc:
CRITICAL STEP f.
OPEN RHR hot leg injection valve 1-FCV-63-172 SAT STANDARD:
UNSAT
_Applicant opens 1-FCV-63-172, RHR hot leg injection valve, by rotating handswitch 1-HS-63-172, RHR HXA OUTLET XTIE to the right.
Applicant observes Red indicating light LIT and Green indicating light DARK.
Step is critical since it will allow RHR flow to be directed to the hot leg.
COMMENTS:
PAGE 12 OF 15
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.c 2011-12 NRC Exam
[
STEP/STANDARD I_SAT/UNSAT STEP 13: 2. ALIGN RHR Train B for hot leg recirc:
SAT g.
ENSURE RHR heat exchanger outlet 1-FCV-74-28 OPEN.
UNSAT STANDARD:
Applicant ensures 1-FCV-74-28 RHR heat exchanger outlet valve is open by observing 1-XI-74-28 RHR HX B OUTLET FLOW CNTL FCV 74-28 Red light is LIT.
COMMENTS:
STEP 14: 2. ALIGN RHR Train B for hot leg recirc:
- h. ENSURE RHR hot leg flow on 1 -FI-63-1 73.
UNSAT STANDARD:
Applicant ensures flow is indicated on 1-Fl-63-173, RHR to HL 1&3 FLOW COMMENTS:
PAGE 13 OF 15
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.c 2011-12 NRC_Exam STEP/STANDARD SATIUNSAT STEP 15: 2. ALIGN RHR Train B for hot leg recirc:
SAT i.
CLOSE RHR Train A cold leg isolation 1-FCV-63-93.
UNSAT STANDARD:
Applicant closes 1-FCV-63-93, RHR Train A cold leg isolation valve, by rotating handswitch 1-HS-63-93A, RHR TO CL 1&4, to the left, and observing that the Red indicating light is DARK and the Green indicating light is LIT.
Applicant informs the Unit Supervisor that RHR has been aligned for hot leg recirculation.
CUE:
Repeat back information provided by the applicant to the Unit Supervisor.
COMMENTS:
STOP TIME PAGE 14 OF 15
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
I. A Large Break LOCA has occurred.
- 2. Three hours have elapsed since the Large Break LOCA occurred.
- 4. You are the Operator at the Controls.
INITIATING CUES:
I. The Unit Supervisor directs you to align RHR for hot leg recirculation using ES-I.4, Transfer to Hot Leg Recirculation.
- 2. You are to notify the Unit Supervisor when RHR is aligned for hot leg recirculation.
B.1.c
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.d 2011-12 NRC Exam FINAL SUBMITTAL B.1.d Start a Reactor Coolant Pump.
(Alternate Path)
THIS JPM MAY BE CONDUCTED IN PARALLEL WITH B.1.e.
PACE I OF 20
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.d 2011-12 NRC Exam EVALUATION SHEET Task:
Start a Reactor Coolant Pump.
Alternate Path:
After RCP is started per SOl-68.02, its #1 seal will fail requiring the performer to stop the RCP based on pump bearing temperature.
Facility JPM #:
3-OT-JPMRO28A Safety Function:
4P
Title:
Heat Removal From Reactor Core KIA 003 Al.02 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RCPS controls including:
Rating(s):
2.9/2.9 CFR:
41.5/45.5 Evaluation Method:
Simulator X
In-Plant Classroom
References:
SOI-68.02 Reactor Coolant Pumps Rev. 34 AOl-24 RCP Seal Abnormalities During Pump Operation Rev 29 Task N umber:
RO-068-SOI-68-007
Title:
Task Standard:
The applicant:
1.) Performs action of SOl-68.02, Reactor Coolant Pumps, to start RCP #1.
2,) Evaluates RCP #1 bearing temperatures, determines that temperature is rising and stops RCP #1 due to high bearing temperature.
Validation Time:
18 minutes Time Critical:
Yes No X
Applicant:
Time Start:
NAME Docket No.
Time Finish:
Performance Rating:
SAT UNSAT Performance Time Examiner:
/
NAME SIGNATURE DATE COMMENTS PACE 2 OF 20
WATTS BA NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.d 2011-12 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:
ENSURE NRC Examination Security has been established.
2.
RESET to Initial Condition by performing the following actions:
a.
Select lCManager on the THUNDERBAR menu (right hand side of Instructor Console Screen).
b.
Locate IC 308.
c.
Right click on IC 308.
d.
Select Reset on the drop down menu.
e.
Right click on RESET.
f.
Enter the password for IC 308 g.
Select Yes on the INITIAL CONDITION RESET pop-up window.
h.
Perform SWITCH CHECK.
3.
ENSURE the following information appears on the Director Summary Screen:
Type Event Delay Inserted Ramp M
1 00:00:00 00:00:00 Initial Final Value 100 0
Key cvl7a rcp 1 seal failure rcp #1 4.
Place simulator in RUN and acknowledge any alarms.
5.
ENSURE a marked-up copy of SOl-68.02, Reactor Coolant Pumps, signed off (circled-and-slashed) to Step 6 is available for each applicant 6.
ENSURE Extra Operator is present in the simulator.
7.
Place simulator in FREEZE until Examiner cue is given.
8.
When the applicant has stopped RCP I Oil lift pump, the Examiner will cue the Console Operator to enter Event 1, causing the failure of the #1 Seal Package.
PAGE 3 OF 20
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.d 2011-12 NRC Exam 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 in Mode 3, Hot Standby.
- 2. RCP # I has been shut down 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for repairs to the motor leads.
- 3. Maintenance reported the repairs have been completed.
- 5. SOI-68.02, Reactor Coolant Pumps, Section 5.0, Startup, has been completed through Step 6.
- 6. Section 4.2 Field Preparations are complete.
INITIATING CUES:
The Unit Supervisor has directed you to start RCP #1 using SOI-68.02, Reactor Coolant Pumps, Section 5.0, Startup, beginning at Step 7.
PA(P 4 flF 2fl
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.d 2011-12 NRC Exam STEPISTANDARD I
SATIUNSAT I
STARTTIME:
STEP 1:
[7] ENSURE the following parameters [0-M-27B]:
[7.1] Thermal Barrier Flow 35-50 gpm UNSAT
[7.2] LWR Oi Clr flow greater than 5 gpm
[7.3] UPR Oil Cir flow greater than 170 gpm
[7.4] RCP Seal Water Hx Flow greater than 215 gpm STANDARD:
Applicant observes Thermal Barrier (1 -Fl-70-1 15), Lower oil cooler (1-Fl-70-119), Upperoil cooler(1-Fl-70-116), and Seal Water HTX(1-Fl-70-1 76) flows within the specified ranges.
COMMENTS:
CAUTION Inadvertent RCP start may occur if RCP alternate supply breaker is left in its automatic configuration (pulled out).
NOTE Oil Lift Pump is started 2 minutes before RCP start.
Page 5of20
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.d 2011-12 NRC Exam STEPISTAN DARD SATIUNSAT STEP 2:
[8] START applicable Oil Lift Pump:
PERF NOMENCLATURE LOCATION POSITION UNID INITIAL RCP 1 NORMAL BKR & LIFT PUMP 1-N-S PULL OUT,[c,8]
1-HS-68-8AA THEN START RCP 2 NORMAL BKR & LIFT PUMP 1-M-5 PULL OUT,[c.8]
1-HS-68-31AA THEN START RCP 3 NORMAL BKR & LIFT PUMP 1-M-5 PULL OUT[c81 1-HS-68.-5OAA THEN_START RCP 4 NORMAL BKR & LIFT PUMP 1-M-5 PULL OUT,[c.8]
1-HS-68-73AA THEN START STANDARD:
Applicant pulls out handswitch 1-HS-68-8AA RCP I NORMAL BKR&LIFT PUMP and rotates the handswitch to the START position.
Step is critical to assure oil lift pressure thrust bearings to prevent metal to metal contact on bearing surfaces when pump is started from idle.
COMMENTS:
Applicant locates 1-PDI-62-8A, RCP 1 #1 SEAL AP on panel 1-M-5 and observes that the indicator is off-scale high, indicating greater than 400 psid.
COMMENTS:
CRITICAL TASK SAT UNSAT STEP 3: [9] VERIFY #1 seal tP greater than 200 psid [1-M-5].
STANDARD:
SAT UNSAT Page 6of20
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.d 2011-12 NRC_Exam STEP/STANDARD SATIUNSAT STEP 4: [10] VERIFY 8 to 13 gpm to RCP seal [1-M-5].
SAT STANDARD:
UNSAT.
Applicant locates 1-Fl-62-IA, RCP I SEAL SUP FLOW and observes flow at 8 approximately gpm.
COMMENTS:
STEP 5: [11] ENSURE VCT press at least 15 psig [1-M-6].
SAT STANDARD:
UNSAT Applicant locates 1-PI-62-122, VCT PRESS on panel 1-M-6 and observes pressure greater than 15 psig (approximately 20 psig).
COMMENTS:
Page7of2O
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.d 2011-12 NRC Exam
[
STEP/STANDARD
[
SATIUNSAT STEP 6: [12] VERIFY #1 seal leakoff greater than 0.2 gpm, or within SAT Normal Operating Range for existing #1 Seal tiP (see Appendix B).
UNSAT STANDARD:
Applicant locates 1-FR-62-23, SEAL LEAKOFF - LO RANGE
- GPM 1 &2 on panel 1 -M-5 and observes that the RED indicator is off-scale high, indicating leakoff greater than 0.2 gpm.
Applicant locates 1-FR-62-24, SEAL LEAKOFF
- HI RANGE
- GPM 1&2 on panel 1-M-5 and observes that the RED indicator is at approximately 3.5 gpm.
COMMENTS:
STEP 7: [13] IF leakoff flow is NOT established, THEN GO TO Section SAT 8.0.
UNSAT STANDARD:
Applicant determines that leakoff flow is established and marks the step as N/A.
COMMENTS:
Page 8 of 20
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.d 2011-12 NRC Exam STEPISTANDARD SATIU NSAT STEP 8: [14] IF starting RCP for fill and vent only, THEN ENSURE RCS SAT press is greater than 325 psig but less than 1000 psig.
UNSAT
[14.1] OPEN 1-FCV-62-53, #1 SEAL BYPASS [1-M-5] to VENT RCP.
[14.2] CLOSE 1-FCV-62-53, #1 SEAL BYPASS [1-M-5].
STANDARD:
Applicant determines that the RCP is NOT being started for fill and vent and marks the step as N/A.
COMMENTS:
Step 5.0[15] prevents excessive Rod motion upon starting RCP.
STEP 9: [15] IF restarting RCP with Control Rods withdrawn, THEN SAT ENSURE Rod Bank Select in MANUAL.
UNSAT STANDARD:
Applicant locates CERPI MONITOR I and CERPI MONITOR 2 on panel 1-M-4 and observes that all rods, control and shutdown are fully inserted.
Applicant marks the step as N/A.
Applicant locates 1-RBSS, ROD BANK SELECT and observes that the selector switch is in the MAN position.
COMMENTS:
NOTE Page9of2O
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.d 2011-12 NRC Exam STEPISTANDARD SAT/UNSAT CAUTION To reduce thermal shock to RCP shaft and seals, a maximum of 1°F per minute temp reduction will be observed, until bearing temp is less than 225°F.
STEP 10: [16] IF restarting RCP after stopping due to high temp limits SAT caused by loss of Injection Water and High CCS temp, THEN ENSURE following parameters established to prevent UNSAT thermal shock to RCP parts:
[16.1] CCS temp to thermal barrier less than 105°F (CCS Hx outlet)
[16.2] Seal leakoff temp less than 180°F
[16.3] 0.2 to 5 gpm seal leakoff STANDARD:
Applicant determines from the INITIAL CONDITIONS that the pump is not being restarted after a high temperature condition.
COMMENTS:
STEP 11: [17] ENSURE Aux OC Bkr, CLOSED.
SAT STANDARD:
UNSAT Applicant determines that the RED indicating light for RCP 1 Aux Overcurrent Protection ACB is LIT (light is located above 1-HS-68-8BA, RCP I ALTERANTE BKR & XFRE SELECTOR.)
COMMENTS:
Page lOof 20
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.d 2011-12 NRC_Exam STEP/STAN DARD SAT/U NSAT STEP 12: [18] IF starting RCP 1, THEN ENSURE Pzr spray, 1-PCV SAT 340D, is CLOSED.
UNSAT STANDARD:
Applicant observes 1-Xl-68-340D PZR SPRAY LOOP 1. GREEN light is LIT.
IF RED indicating light is LIT, THEN the applicant locates 1-PlC-68-340D LOOP I SPRAY CONTROL on panel 1-M-4 and lifts the toggle switch up to place the controller in MANUAL. The applicant then slides the toggle to the left and observes that 1-Xl-68-340D PZR SPRAY LOOP 1 RED indicating light is DARK and the GREEN indicating light is LIT.
COMMENTS:
STEP 13: [19] IF starting RCP 2, THEN ENSURE Pzr spray, 1-PCV SAT 340B, is CLOSED.
UNSAT STANDARD:
Applicant marks the step as N/A since RCP 1 is being started.
COMMENTS:
Page 11 of2O
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.d 2011-12 NRC Exam STEPISTANDARD SAT/UNSAT STEP 14: [20] ANNOUNCE RCP start onPA system.
SAT STANDARD:
UNSAT EXAMINER CUE: When the applicant addresses the PA announcement, state another operator will handle the PA announcement.
COMMENTS:
NOTE Below 15% power with station service NOT transferred, the Alternate handswitch is used to start RCP.
Page 12 of 20
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.d 2011-12 NRC Exam STEP/STANDARD F
SATIUNSAT STEP 15: [21] START selected RCP (NIA HSs NOT used):
STANDARD:
Applicant enters N/A for RCP 2, RCP 3 and RCP 4 handswitches.
The applicant enters N/A for 1-HS-68-AA, RCP 1 NORMAL BKR &
LIFT PUMP.
Applicant locates 1-HS-68-8BA RCP I ALTERNATE BKR & XFRE SELECTOR, observes that the handswitch is pushed in.
The applicant then rotates 1-HS-68-8BA RCP I ALTERNATE BKR &
XFRE SELECTOR to the right to the START position.
Applicant observes the RED indicating light LIT and the GREEN indicating light DARK on 1-HS-68-BA. The applicant may also observe flow rising on 1-Fl-68-6A, 6B, and 6D LOOP I FLOW indicators.
Step is critical since this action starts RCP 1, the desired RCP.
COMMENTS:
STEP SAT UNSAT CRITICAL NOMENCLATURE LOCATION POSITION UNID INITIAL RCP 1 NORMAL BKR & LIFT PUMP 1-M-5 PUSH IN. THEN 1-HS-68-8AA START RCP 1 ALTERNATE BKR & XFER 1-M-5 PUSH IN. THEN 1-HS-68-8BA SELECTOR START RCP 2 NORMAL BKR & LIFT PUMP 1-M-5 PUSH IN, THEN 1-HS-68-31M START RCP 2 ALTERNATE BKR & XFER 1-M-5 PUSH IN, THEN 1-HS-68-31 BA SELECTOR START RCP 3 NORMAL BKR & LIFT PUMP 1-M-5 PUSH IN, THEN 1-HS-68-5OAA START RCP 3 ALTERNATE BKR & XFER 1-M-5 PUSH IN, THEN 1-HS-68-5OBA SELECTOR START RCP 4 NORMAL BKR & LIFT PUMP 1-N-S PUSH IN, THEN 1-HS-68-73AA START RCP 4 ALTERNATE BKR & XFER 1-M-5 PUSH IN, 1-HS-68-73BA SELECTOR THEN START Page 13 of 20
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.d 2011-12 NRC Exam STEP/STANDARD SATIUNSAT EXAMINER:
CUE CONSOLE OPERATOR to activate Event I in the following step when oil lift pump is stopped. INSERT MALFUNCTION CVI7A @ 100% which fails the Number I seal (high pressure) on Reactor Coolant Pump 1.
EXAMINER: When the malfunction is entered, multiple alarms will be received, such as:
99-C, RCP LWR BEARING TEMPHI, 99-D, RCP SEAL lIP LO, 100-0, RCP SEAL LEAK OFF FLOW HI.
If referred to, the ARIs will direct the applicant to AOl-24, RCP MALFUNCTIONS DURING PUMP OPERATION.
STEP 16: [22] WHEN RCP has operated 1 minute, THEN STOP Oil Lift SAT Pump (N/A HSs NOT used):
UNSAT NOMENCLATURE LOCATION POSITION UNID INmAL RCP 1 NORMAL BKR & LIFT PUMP 1-M-5 PULL OUT [0.8]
1-HS-68-8AA THEN STOP RCP 2 NORMAL BKR & LIFT PUMP 1-M-5 PULL OUT [0.8],
1-HS-68-31AA THEN STOP RCP 3 NORMAL BKR & LIFT PUMP 1-M-5 PULL OUT [0.8],
1-HS-68-5OAA THEN STOP RCP 4 NORMAL BKR & LIFT PUMP 1-M-5 PULL OUT [0.8].
1-HS-68-73AA THEN STOP STANDARD:
Applicant enters N/A for RCP 2, RCP 3 and RCP 4 handswitches.
Applicant locates 1-HS-68-8AA RCP 1 NORMAL BKR&LIFT PUMP then rotates the handswitch to the STOP position.
COMMENTS:
Pagel4of2O
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.d 2011-12 NRC Exam STEP/STANDARD SAT/UNSAT EXAMINER: The following list is taken from AOI-24, RCP MALFUNCTIONS DURING PUMP OPERATION, Attachment 2.
RCP IMMEDIATE SHUTDOWN CRITERIA NOTE Exceeding any of the following setpoints will require an immediate pump shutdown.
Operating limits can be found in SQl 68.02. This list is immediate shutdown criteria only.
A. Shaft vibration greater than 20 mils or 15 mils with a rate of rise equal to 1 mil/hr (alarm at 15 mils). [Indicators located on 0-PNL-52-R139, Aux Inst Rm.}
B. Frame vibration greater than 5 mils or 3 mils with a rate of rise of 0.2 mil/hr [Readings taken by Maint. at Aux Bldg L-Panels, el.737.]
C. Motor windings temp greater than 302°F.
D. Motor bearing temp greater than 195°F.
E. Pump bearing temp greater than 225° F.
F. Loss of CCS to oil coolers for greater than 10 minutes.
G. No. I seal outlet temp greater than 225°F.
H. No. I seal flow HIGH with rising pump bearing or #1 seal leakoff temperatures.
I. No. I seal tiP less than or equal to 200 psid.
Page 15 of 20
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.d 2011-12 NRC_Exam STEPISTAN DARD SATIU NSAT STEP 17: Applicant transitions to AOl-24 OR applicant determines that the CRITICAL bearing temperature will exceed limit and stops the Reactor STEP Cooling pump.
SAT STANDARD:
UNSAT Applicant transitions to AOl-24 or
_1-HS-68-8BA is rotated to the STOP position and GREEN ACB light is LIT.
Step is critical to prevent additional damage to the #1 Seal Package on RCP 1.
The applicant may elect to stop RCP since it was just started.
COMMENTS:
EXAMINER: The following steps are from AOI-24 Section 3.3.
CAUTION A seal leakoff rise to greater than 2.0 gpm AFTER experiencing low leakoff of less than 0.8 gpm may indicate seal degradation. Plant Management should be notified of Ieakoff trends.
NOTE I Anytime #1 seal leakoff flow exceeds the values shown on Attachment I, system engineering should be requested to perform an evaluation of the #1 seal condition.
NOTE 2 During plant startup after seal maintenance, the #1 seal may require 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of run time before the seal seats fully and operates normally.
NOTE 3 The #1 seal return should be isolated between 3 and 5 minutes after tripping an RCP to allow for pump coastdown.
Page 16 of 20
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.d 2011-12 NRC_Exam STEP/STAN DARD SAT/U NSAT STEP 18:
- 1. MONITOR #1 seal leakoff equal to or greater than 6.0 gpm.
SAT STANDARD:
UNSAT Applicant determines seal leakoff flow is equal to or greater than 6 gpm by checking Seal Leakoff - High Range
- flow recorder 1-FR-62-24 Red Pen.
COMMENTS:
STEP 19: 2. MONITOR RCPs lower bearing and #1 seal outlet temp SAT STABLE or DROPPING.
UNSAT STANDARD:
Applicant determines RCP5 lower bearing and #1 seal outlet temperatures are increasing and transitions to the RNO column.
COMMENTS:
STEP 20: 2. RESPONSE NOT OBTAINED:
SAT GO TO Subsection 3.2, Step 2.
UNSAT STANDARD:
Applicant determines that a transition to Subsection 3.2, Step 2 is required.
COMMENTS:
Page 17 of 20
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.d 2011-12 NRC_Exam STEP/STANDARD SATIU NSAT STEP 21: 2. CHECK unit in Mode 1 or 2 SAT STANDARD:
UNSAT Applicant determines that the Unit is in Mode 3.
COMMENTS:
STEP 22: 2. RESPONSE NOT OBTAINED:
SAT GO TO Step 4.
UNSAT STANDARD:
Applicant determines that Step 4 is to be implemented.
COMMENTS:
Page 18 of 20
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.d 2011-12 NRC_Exam STEPISTANDARD SATIUNSAT STEP 23: 4. STOP and LOCK OUT affected RCP(s).
CRITICAL STEP STANDARD:
SAT Applicant rotates 1-HS-68-8BA is to the STOP position and GREEN ACB light is LIT.
UNSAT Step is critical to prevent additional damage to the #1 Seal Package on RCP 1.
CUE:
After RCP is stopped, state another operator will continue from here.
COMMENTS:
END OF TASK STOP TIME Page 19 of 20
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- 1. The Unit is in Mode 3, Hot Standby.
- 2. RCP # I has been shut down 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for repairs to the motor leads.
- 3. Maintenance reported the repairs have been completed.
- 5. SOI-68.02, Reactor Coolant Pumps, Section 5.0, Startup, has been completed through Step 6
- 6. Section 4.2 Field Preparations are complete.
INITIATING CUES:
The Unit Supervisor has directed you to start RCP #1 using S0I-68.02, Reactor Coolant Pumps, Section 5.0, Startup.
B.1.d
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.e 2011-12 NRC Exam FINAL SUBMITTAL B.1.e Align Control Rod Drive Mechanism Coolers.
NOTE: This JPM may be conducted on the Simulator OR in the Main Control Room THIS JPM MAY BE CONDUCTED IN PARALLEL WITH B.1.d.
PAGE 1 OF 19
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.e 2011-12 NRC Exam EVALUATION SHEET Task:
Align Control Rod Drive Mechanism Coolers.
Alternate Path:
n/a Facility JPM #:
05-2009 NRC Exam Safety Function:
5
Title:
Containment Integrity K/A 022 A4.01 Ability to manually operate and/or monitor in the control room: CCS fans Rating(s):
3.6 I 3.6 CFR:
41.7 I 45.5 to 45.8 Evaluation Method:
Simulator X
In-Plant Classroom SOl-30.03, Containment HVAC and Pressure Control, Rev. 42.
RO-30-SOl-30-002
Title:
Startup/Place in Standby Alignment the Upper Compartment Coolers.
Task Standard:
Applicant shuts down CRDM coolers C-A and D-B, and places CRDM coolers A-A and B-B in service using SOl-30.03, Containment HVAC and Pressure Control.
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
References:
Task Number:
PACE 2 OF 19
WATTS BA 1UCLEAR PLANT JOB PERFORMANCE MEASURE B.1.e 2011-12 NRC Exam IF CONDUCTED IN THE SIMULATOR, THEN PERFORM THE FOLLOWING:
SIMULATOR OPERATOR INSTRUCTIONS:
1.
ENSURE NRC Examination Security has been established.
2.
RESET to Initial Condition by performing the following actions:
a.
Select ICManager on the THUNDERBAR menu (right hand side of Instructor Console Screen).
b.
Locate IC 308.
c.
Right click on IC 308.
d.
Select Reset on the drop down menu.
e.
Right click on RESET.
f.
Enter the password for IC 308.
g.
Select Yes on the INITIAL CONDITION RESET pop-up window.
h.
Perform SWITCH CHECK.
3.
Place simulator in RUN and acknowledge any alarms.
4.
ENSURE the following cooler configuration:
Lower CNTMT Coolers Upper CNTMT Coolers CRDM Coolers A - RUNNING A - RUNNING A - OFF B
- RUNNING B - RUNNING B - OFF C - RUNNING C
- RUNNING C
- RUNNING D - OFF D - OFF D - RUNNING 5.
Place simulator in FREEZE until Examiner cue is given.
PAGE 3 OF 19
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.e 2011-12 NRC Exam IF CONDUCTED IN THE MAIN CONTROL ROOM, THEN:
Tools/Equipment/Procedures Needed:
ENSURE that copies of S0I-30.03, Containment HVAC and Pressure Control, available to the EXAMINER, marked as NRC EXAM MATERIAL, FOR TRAINING ONLY, for each applicant.
Begin the JPM at the Shift Managers Desk.
PAiP 4 OF ic
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.e 2011-12 NRC Exam 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. Predictive Maintenance has requested that the IC-A CRDM Cooler be removed from service in order to perform maintenance on its 480V supply breaker.
- 2. You are an extra operator assigned to the shift.
- 3. Instrument Maintenance (MIG) has been notified of the planned realignment of CRDM coolers and has placed required instruments in service to monitor RPI indications, per SOI-30M3, Containment HVAC and Pressure Control, PRECAUTION L.
INITIATING CUES:
I. The Unit Supervisor directs you to place IA-A and lB-B CRDM Coolers in service and place IC-A and ID-B CRDM Coolers in reserve using S01-30.03, Containment HVAC and Pressure Control, Section 5.6, CRDM Shroud Cooling Alignment and CRDM Cooler Startup.
- 2. Notify the Unit Supervisor when the CRDM coolers have been aligned.
5 oP 19
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.e 2011-12 NRC Exam STEP/STANDARD SATIUNSAT EXAMINER: USE PAGES 6 through 10 if conducting JPM on the Simulator.
SIMULATOR PERFORMANCE START TIME:
CAUTION Under certain shutdown configurations, starting of CRDM Coolers has the potential to cause the ice condenser lower inlet doors to open if they are NOT properly restrained.
NOTES
- 1) Normally, two CRDM Coolers are in service and two in reserve. CRDM Coolers IA-A and lB-B should be operated together OR IC-A and ID-B should be operated together for power train separation. Deviation from this alignment requires IA-A and IC-A OR I B-B and ID-B to ensure proper air flow.
- 2) The temperature indicated on each coolers TIC is that coolers air inlet temperature. CRDM Cooler air outlet temperature is displayed on ICS points. ICS Point TIOI4A, OP REFUEL GATE, may be used to determine the temperature in the CRDM shroud area.
STEP 1: [1] IF CRDM CLR D-B isto be used to cool shroud [1-M-9], THEN SAT
[1.1] ENSURE 1-HS-30-80A, CRDM CLR D-B MTR 1&2, in UNSAT A-AUTO and 1-HS-30-81A, CRDM CLR D-B SHROUD SUCT, in P-AUTO, AND START CRDM CLR D-B with 1 -HS-30-80A.
[1.2] ENSURE CRDM CLR D-B is RUNNING.
[1.3] ENSURE 1-TCO-30-81, CRDM CLR D-B SHROUD SUCT, is OPEN, and 1-TCO-30-82, CRDM CLR D-B LWR CNTMT SUCT, is CLOSED.
STANDARD:
Applicant determines that CRDM CLR D-B is in service, and will be placed in reserve. Applicant enters N/A for this step.
COMMENTS:
Page 6 of 19
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.e 2011-12 NRC_Exam STEP/STAN DARD SATIUNSAT STEP 2: [2] IF CRDM CLR A-A is to be used to cool shroud [1 -M-9], THEN CRITICAL STEP
[2.1] ENSURE 1-HS-30-83A,CRDM CLRA-A MTR l&2, in A-AUTO and 1-HS-30-84A, CRDM CLR A-A SAT SHROUD SUCT, in P-AUTO, AND START CRDM CLR with 1 -HS-30-83A.
UNSAT
[2.2] ENSURE CRDM CLR A-A is RUNNING.
[2.3] ENSURE 1-TCO-30-84, CRDM CLR A-A SHROUD SUCT, is OPEN, and 1-TCO-30-85, CRDM CLR A-A LWR CNTMT SUCT, is CLOSED.
STANDARD:
Applicant ensures 1-HS-30-83A, CRDM CLR A-A MTR 1&2, in A-AUTO and 1-HS-30-84A, CRDM CLR A-A SHROUD SUCT, in P-AUTO.
Applicant starts CRDM CLR A-A by rotating handswitch 1 -HS-30-83A to the START position.
Step is critical to ensure CRDM CLR A-A is in service.
Applicant ensures 1 -TCO-30-84, CRDM CLR A-A SHROUD SUCT is OPEN, and 1 -TCO-30-85, CRDM CLR A-A LWR CNTMT SUCT is CLOSED.
COMMENTS:
Page 7 of 19
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.e 2011-12 NRC Exam STEPISTANDARD
]
SATIUNSAT STEP 3:
[3] IF CRDM CLR B-B is to be used to cool shroud [1-M-9],
CRITICAL THEN STEP
[3.1] ENSURE 1-HS-30-92A, CRDM CLR B-B MTR 1&2, in SAT A-AUTO and 1-HS-30-93A, CRDM CLR B-B SHROUD SUCT, in P-AUTO, AND START CRDM UNSAT CLR with 1-HS-30-92A.
[3.2] ENSURE CRDM CLR B-B is RUNNING.
[3.3] ENSURE 1-TCO-30-93, CRDM CLR B-B SHROUD SUCT, is OPEN, and 1-TCO-30-94, CRDM CLR B-B LWR CNTMT SUCT, is CLOSED.
STANDARD:
Applicant ensures 1-HS-30-92A, CRDM CLR B-B MTR 1&2, in A-AUTO and 1-HS-30-93A, CRDM CLR B-B SHROUD SUCT, in P-AUTO.
Applicant starts CRDM CLR B-B by rotating handswitch 1 -HS-30-92A to the START position.
Step is critical to ensure CRDM CLR B-B is in service.
Applicant ensures 1-TCO-30-93, CRDM CLR B-B SHROUD SUCT, is OPEN, and 1-TCO-30-94, CRDM CLR B-B LWR CNTMT SUCT, is CLOSED COMMENTS:
Page 8 of 19
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.e 2011-12 NRC_Exam STEPISTANDARD SAT/UNSAT STEP 4:
[4] IF CRDM CLR C-A is to be used to cool shroud [1-M-9],
SAT THEN UNSAT
[4.1] ENSURE 1-HS-30-88A, CRDM CLR C-A MTR 1&2, in A-AUTO and 1-HS-30-89A, CRDM CLR C-A SHROUD SUCT, in P-AUTO, AND START CRDM CLR with I -HS-30-88A.
[4.2] ENSURE CRDM CLR C-A is RUNNING.
[4.3] ENSURE 1-TCO-30-89, CRDM CLR C-A SHROUD SUCT, is OPEN, and 1-TCO-30-90, CRDM CLR C-A LWR CNTMT SUCT, is CLOSED.
STANDARD:
Applicant determines that CRDM CLR C-A is in service, and will be placed in reserve. Applicant enters N/A for this step.
COMMENTS:
Page 9 of 19
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B1 1
e 2011-12 NRC_Exam STEP/STANDARD SATIUNSAT STEP 5:
[5] IF CRDM Cooler is to be placed in reserve, THEN CRITICAL ENSURE the following: (N/A coolers in service)
STEP
[5.1] 1-HS-30-80A, CRDM CLR D-B MTR 1&2, in A-SAT AUTO, and Cooler NOT running.
UNSAT
[5.2] 1-HS-30-83A, CRDM CLRA-A MTR 1&2, in A-AUTO, and Cooler NOT running.
[5.3] 1-HS-30-92A, CRDM CLR B-B MTR 1&2, in A-AUTO, AND Cooler NOT running.
[5.4] 1-HS-30-88A, CRDM CLR C-A MTR 1&2, in A-AUTO, and Cooler NOT running.
STANDARD:
Applicant determines that CRDM CLRS D-B and C-A will be placed in reserve at this time.
Applicant enters N/A for steps 5.2 and 5.3.
performs Step 5.1, stops CRDM CLR D-B by placing 1-HS-30-80A to STOP, then returning the switch to A-AUTO.
Step is critical to ensure CRDM CLR D-B is in reserve and will auto start if required.
performs Step 5.4, stops CRDM CLR C-A by placing 1-HS-30-88A to STOP, then returning the switch to A-AUTO.
Step is critical to ensure CRDM CLR C-A is in reserve and will auto start if required.
Applicant (Extra Operator) reports that the containment coolers have been aligned as requested, per SOl-3003, Containment HVAC and Pressure Control.
COMMENTS:
END OF TASK STOP TIME Page 10 of 19
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.e 2011-12 NRC Exam STEP/STANDARD SAT/UNSAT EXAMINER: USE PAGES II through 18 if conducting JPM in the Control Room.
CONTROL ROOM PERFORMANCE START TIME:
CAUTION Under certain shutdown configurations, starting of CRDM Coolers has the potential to cause the ice condenser lower inlet doors to open if they are NOT properly restrained.
NOTES
- 1) Normally, two CRDM Coolers are in service and two in reserve. CRDM Coolers IA-A and I B-B should be operated together OR IC-A and ID-B should be operated together for power train separation. Deviation from this alignment requires IA-A and IC-A OR I B-B and ID-B to ensure proper air flow.
- 2) The temperature indicated on each coolers TIC is that coolers air inlet temperature. CRDM Cooler air outlet temperature is displayed on ICS points. ICS Point TIOI4A, OP REFUEL GATE, may be used to determine the temperature in the CRDM shroud area.
STEP 1: [1] IF CRDM CLR D-B isto be used to cool shroud [1-M-9], THEN SAT
[1.1] ENSURE 1-HS-30-80A, CRDM CLR D-B MTR 1&2, in UNSAT A-AUTO and 1-HS-30-81A, CRDM CLR D-B SHROUD SUCT, in P-AUTO, AND START CRDM CLR D-B with I -HS-30-80A.
[1.2] ENSURE CRDM CLR D-B is RUNNING.
[1.3] ENSURE 1-TCO-30-81, CRDM CLR D-B SHROUD SUCT, is OPEN, and 1-TCO-30-82, CRDM CLR D-B LWR CNTMT SUCT, is CLOSED.
STANDARD:
Applicant determines that CRDM CLR C-A is in service, and will be placed in reserve. Applicant enters N/A for this step.
COMMENTS:
Page 11 of 19
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.e 2011-12 NRC Exam STEPISTANDARD SATIUNSAT STEP 2: [2] IF CRDM CLR A-A is to be used to cool shroud [1-M-9], THEN CRITICAL STEP
[2.1] ENSURE 1-HS-30-83A, CRDM CLRA-A MTR 1&2, in A-AUTO and 1-HS-30-84A, CRDM CLR A-A SAT SHROUD SUCT, in P-AUTO, AND START CRDM CLR with 1-HS-30-83A.
UNSAT
[2.2] ENSURE CRDM CLR A-A is RUNNING.
[2.3] ENSURE 1-TCO-30-84, CRDM CLR A-A SHROUD SUCT, is OPEN, and 1-TCO-30-85, CRDM CLR A-A LWR CNTMT SUCT, is CLOSED.
STANDARD:
Applicant ensures 1-HS-30-83A, CRDM CLR A-A MTR 1&2, in A-AUTO and 1-HS-30-84A, CRDM CLR A-A SHROUD SUCT, in P-AUTO.
Applicant locates 1-HS-30-83A, CRDM CLR A-A and indicates that the handswitch will be rotated to the right to the START position.
Applicant indicates that the RED indicating light will be LIT and the GREEN indicating light will be DARK on 1-HS-30-83A, CRDM CLRA A.
Applicant locates 1-HS-30-84A, CRDM CLR A-A SHROUD SUCT and indicates that the RED indicating light will be LIT and the GREEN indicating light will be DARK.
Applicant locates 1-HS-30-85A, CRDM CLR A-A SHROUD SUCT and indicates that the RED indicating light will be DARK and the GREEN indicating light will be LIT CUE: After applicant has demonstrated proper switch manipulation, state that 1-HS-30-83A is in the IN-AUTO position. RED lights are LIT, and GREEN lights are DARK on 1-HS-30-83A and 1-HS-30-84A.
RED light is DARK and GREEN light is LIT on 1-HS-30-85A.
Step is critical to ensure CRDM CLR A-A is in service.
COMMENTS:
I a9 I 0, IJ
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.e 2011-12 NRC Exam STEP/STAN DARD SAT/U NSAT STEP 3:
[3] IF CRDM CLR B-B is to be used to cool shroud [1-M-9],
CRITICAL THEN STEP
[3.1] ENSURE 1-HS-30-92A, CRDM CLR B-B MTR 1&2, in A-AUTO and 1 -HS-30-93A, CRDM CLR B-B SAT SHROUD SUCT, in P-AUTO, AND START CRDM CLR with 1-HS-30-92A.
UNSAT
[3.2] ENSURE CRDM CLR B-B is RUNNING.
[3.3] ENSURE 1-TCO-30-93, CRDM CLR B-B SHROUD SUCT, is OPEN, and 1-TCO-30-94, CRDM CLR B-B LWR CNTMT SUCT, is CLOSED.
STANDARD:
Applicant ensures 1-HS-30-92A, CRDM CLR B-B MTR 1&2, in A-AUTO and 1-HS-30-93A, CRDM CLR B-B SHROUD SUCT, in P-AUTO.
Applicant locates 1-HS-30-92A, CRDM CLR B-B MTR 1&2, and indicates that the handswitch will be rotated to the right to the START position.
Applicant indicates that the RED indicating light will be LIT and the GREEN indicating light will be DARK on I -HS-30-92A, CRDM CLR B-B MTR 1&2.
Applicant locates 1-HS-30-93A, CRDM CLR B-B SHROUD SUCT and indicates that the RED indicating light will be LIT and the GREEN indicating light will be DARK.
Applicant locates 1-HS-30-94A, CRDM CLR B-B LWR CNTMT SUCT and indicates that the RED indicating light will be DARK and the GREEN indicating light will be LIT CUE: After applicant has demonstrated proper switch manipulation, state that 1-HS-30-92A is in the IN-AUTO position. RED lights are LIT, and GREEN lights are DARK on 1-HS-30-92A and 1-HS-30-93A.
RED light is DARK and GREEN light is LIT on 1-HS-30-94A.
Step is critical to ensure CRDM CLR B-B is in service.
COMMENTS:
Page 13 of 19
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.e 2011-12 NRC_Exam STEPISTANDARD SATIU NSAT STEP 4:
[4] IF CRDM CLR C-A is to be used to cool shroud [1-M-9],
SAT THEN
[4.1] ENSURE 1-HS-30-88A, CRDM CLR C-A MTR UNSAT 1&2, in A-AUTO and 1-HS-30-89A, CRDM CLR C-A SHROUD SUCT, in P-AUTO, AND START CRDM CLR with 1 -HS-30-88A.
[4.2] ENSURE CRDM CLR C-A is RUNNING.
[4.3] ENSURE 1-TCO-30-89, CRDM CLR C-A SHROUD SUCT, is OPEN, and 1-TCO-30-90, CRDM CLR C-A LWR CNTMT SUCT, is CLOSED.
STANDARD:
Applicant determines that CRDM CLR C-A is in service, and will be placed in reserve. Applicant enters N/A for this step.
COMMENTS:
Page 14 of 19
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.e 2011-12 NRC Exam STEP/STANDARD I
SATIUNSAT EXAMINER: JPM Steps 5 through 8 evaluate Steps 5.1 through 5.4 of S0l-30.03, Containment HVAC and Pressure Control, Section 5.6, CRDM Shroud Cooling Alignment and CRDM Cooler Startup.
STEP 5:
[5] IF CRDM Cooler is to be placed in reserve, THEN CRITICAL ENSURE the following: (N/A coolers in service)
STEP
[5.1] 1-HS-30-80A, CRDM CLR D-B MTR 1&2, in SAT A-AUTO, and Cooler NOT running.
UNSAT STANDARD:
Applicant locates 1-HS-30-80A, CRDM CLR D-B MTR 1&2, and indicates that the handswitch will be rotated to the left to the STOP position, and then returned to the IN A-AUTO, mid position.
Applicant indicates that the RED indicating light will be DARK and the GREEN indicating light will be LIT on 1-HS-30-80A, CRDM CLR D-B MTR 1&2.
CUE: After applicant has demonstrated proper switch manipulation, state that 1-HS-30-80A is in the IN-AUTO position. State that the GREEN light is LIT, and RED light is DARK on 1-HS-30-80A.
Step is critical to ensure CRDM CLR D-B is in reserve and will auto start if required.
COMMENTS:
Page 15 of 19
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.e 2011-12 NRC_Exam STEPISTANDARD SAT/U NSAT STEP 6:
[5] IF CRDM Cooler is to be placed in reserve, THEN SAT ENSURE the following: (N/A coolers in service)
UNSAT
[5.2] 1-HS-30-83A, CRDM CLRA-A MTR 1&2, in A-AUTO, and Cooler NOT running.
STANDARD:
Applicant enters N/A for step 5.2 since the A-A CRDM Cooler will remain in service.
COMMENTS:
STEP 7:
[5] IF CRDM Cooler is to be placed in reserve, THEN SAT ENSURE the following: (N/A coolers in service)
UNSAT
[5.3] 1-HS-30-92A, CRDM CLR B-B MTR 1&2, in A-AUTO, AND Cooler NOT running.
STANDARD:
Applicant enters N/A for steps 5.3 since the B-B CRDM Cooler will remain in service.
COMMENTS:
Page 16 of 19
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.e 2011-12 NRC_Exam STEPISTANDARD SATIU NSAT STEP 8:
[5] IF CRDM Cooler is to be placed in reserve, THEN CRITICAL ENSURE the following: (N/A coolers in service)
STEP
[5.4] 1-HS-30-88A, CRDM CLR C-A MTR 1&2, in SAT A-AUTO, and Cooler NOT running.
STANDARD:
UNSAT Applicant locates 1-HS-30-88A, CRDM CLR C-A MTR 1&2, and indicates that the handswitch will be rotated to the left to the STOP position, and then returned to the mid position, IN A-AUTO.
Applicant indicates that the RED indicating light will be DARK and the GREEN indicating light will be LIT on 1-HS-30-88A, CRDM CLR C-A MTR 1&2.
CUE: After applicant has demonstrated proper switch manipulation, state that 1-HS-30-88A is in the IN-AUTO position. State that the GREEN light is LIT, and RED light is DARK on 1-HS-30-88A.
Step is critical to ensure CRDM CLR C-A is in reserve and will auto start if required.
COMMENTS:
Page 17 of 19
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.e 2011-12 NRC_Exam STEP/STANDARD SAT/UNSAT STEP 9:
Applicant reports that the A-A and B-B CRDM Coolers are SAT in service and the C-A and D-B CRDM Coolers are in reserve.
UNSAT STANDARD:
Applicant reports that the CRDM Coolers have been aligned as requested, per S0l-30.03, Containment HVAC and Pressure Control.
COMMENTS:
END OF TASK STOP TIME Page 18 of 19
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- 1. Predictive Maintenance has requested that the IC-A CRDM Cooler be removed from service in order to perform maintenance on its 480V supply breaker.
- 2. You are an extra operator assigned to the shift.
- 3. Instrument Maintenance (MIG) has been notified of the planned realignment of CRDM coolers and has placed required instruments in service to monitor RPI indications, per S0I-30.03, Containment HVAC and Pressure Control, PRECAUTION L INITIATING CUES:
I. The Unit Supervisor directs you to place IA-A and lB-B CRDM Coolers in service and place IC-A and ID-B CRDM Coolers in reserve using SOI-30.03, Containment HVAC and Pressure Control, Section 5.6, CRDM Shroud Cooling Alignment and CRDM Cooler Startup.
2.
Notify the Unit Supervisor when the CRDM coolers have been aligned.
B.te
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.f 2011-12 NRC Exam FINAL SUBMITTAL B.1.f Reinstate Source Range Detectors Following a Reactor Trip.
(Alternate Path)
PACE I OF Q
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.f 2011-12 NRC Exam EVALUATION SHEET Task:
Reinstate source range detectors following a reactor trip.
Alternate Path:
Applicant determines that Intermediate Range Channel 136 has failed high and manually reinstates the Source Range detectors.
Facility JPM #:
Modified from SQN.
Safety Function:
7
Title:
Instrumentation K/A 015 A4.01 A4 Ability to manually operate and/or monitor in the control room:
Selection of controlling NIS channel.
Rating(s):
3.6* / 3.6 CFR:
41.7 / 45.5 to 45.8 Evaluation Method:
Simulator X
In-Plant Classroom
References:
ES-0.1 Reactor Trip Response, Rev. 23.
Task Number:
RO-113-ES-0.1-001
Title:
Respond to a reactor trip without safety injection.
Task Standard:
Applicant determines that the Source Range detectors DID NOT re-energize as expected and takes the actions of ES-0. 1, Reactor Trip Response to manually reenergize and align the Source Range per Step 18 RESPONSE NOT OBTAINED.
Validation Time:
10 minutes Time Critical:
Yes No X
Applicant:
Time Start:
NAME Docket No.
Time Finish:
Performance Rating:
SAT UNSAT Performance Time Examiner:
1 NAME SIGNATURE DATE COMMENTS PAGE 2 OF Q
WATTS BA 1UCLEAR PLANT JOB PERFORMANCE MEASURE B.1.f 2011-12 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:
1.
ENSURE NRC Examination Security has been established.
2.
RESET to Initial Condition by performing the following actions:
a.
Select ICManager on the THUNDERBAR menu (right hand side of Instructor Console Screen).
b.
Locate IC 309.
c.
Right click on IC 309.
d.
Select Reset on the drop down menu.
e.
Right click on RESET.
f.
Enter the password for IC 309.
g.
Select Yes on the INITIAL CONDITION RESET pop-up window.
h.
Perform SWITCH CHECK.
3.
ENSURE the following information appears on the Director Summary Screen:
Key Inserted Ramp ni04b ir channel failure ir chnl 2 00:00:00 00:00:00 xi-35-60sw6 xi-35-60sw6 generator condition monitor alarm silenc 00:00:00 00:00:00 6.
Place simulator in RUN and acknowledge any alarms.
7.
ENSURE a marked-up copy of ES-0.1, Reactor Trip Response, signed (circled-and-slashed) through Step 17 and Step 18 circled, is available for each applicant.
8.
ENSURE Extra Operator is present in the simulator.
9.
Place simulator in FREEZE until Examiner cue is given.
PAGE 3 OF 9
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.f 2011-12 NRC Exam 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 I was inadvertently tripped from 100% power approximately 20 minutes ago.
2.
ES-0.1, Reactor Trip Response, was entered and the crew just completed Step 17.
INITIATING CUES:
1.
The US directs you as the OAC to ensure source range monitors are reinstated per ES-0.1, Step 18.
2.
Inform the US when the source range monitors have been reinstated and all functions of the source range monitors are in service.
PA(P 4 1W
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.f 2011-12 NRC Exam STEPISTANDARD I
SATIUNSAT 1 START TIME:
STEP 1:
- 18. ENSURE nuclear instrumentation operation:
SAT a.
CHECK intermediate range flux less than 1.66 x UNSAT 10-4%.
STANDARD:
Applicant determines that Intermediate Range N136 has failed high and is not indicative of current conditions. Applicant determines that N135 is indicating correctly and continues to step I.b.
EXAMINER: Upon recognition of the failed intermediate range channel, iflwhen the applicant states that AOl-4, Nuclear Instrumentation Malfunctions, should be implemented, provide the cue Another operator will perform AOI-4 actions.
COMMENTS:
STEP 2:
b.
CHECK source range detectors energized.
SAT STANDARD:
Applicant determines that the source range detectors are NOT UNSAT energized and enters RESPONSE NOT OBTAINED COLUMN for actions.
COMMENTS:
Page5of9
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.f 2011-12 NRC Exam STEP/STANDARD SAT/U NSAT STEP 3:
RESPONSE NOT OBTAINED CRITICAL STEP b.
Manually ENERGIZE Source Range detectors:
SAT Simultaneously PLACE 1-N33A and 1-N33B to RESET.
STANDARD:
UNSAT places 1-N33A SR TRIP TR A RESET-BLOCK P-6, and 1-N33B, SR TRIP TR B RESET-BLOCK P-6, to the RESET position SIMULTANEOUSLY (required two-handed operation.)
Step is critical since the circuit requires SIMULTANEOUS operation of 1-N33A and 1N33B to successfully energize the Source Range Detectors.
COMMENTS:
STEP 4:
c.
SELECT STARTUP SCREEN on 1-NR-92-145 to display SAT SRMs and IRMs.
STANDARD:
UNSAT Applicant uses the touch screen function on 1-NR-92-145 and selects STARTUP SCREEN on 1-NR-92-145 to display SRMs and IRM5.
COMMENTS:
Page 6 of 9
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.f 2011-12 NRC Exam
[
STEP/STANDARD SATIUNSAT STEP 5:
d.
ENSURE audio count rate operation.
SAT STANDARD:
Applicant determines that the audio count rate is functioning properly by audible confirmation.
UNSAT COMMENTS:
STEP 6:
e.
RESET shutdown monitor alarm setpoints [M-1 3].
CRITICAL STEP STANDARD:
SAT Applicant resets the shutdown monitor setpoints by depressing the ALARM SETPOINT RESET pushbutton on 1-M-13.
Step is critical to ensure the shutdown monitor alarm circuit is UNSAT properly initialized after the trip.
COMMENTS:
Page7of9
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.f 2011-12 NRC Exam STEP/STANDARD SAT/UNSAT I
STEP 7: f.
ENSURE shutdown monitor ALARM LED(s) dark, AND HIGH CRITICAL FLUX AT SHUTDOWN bistable lights dark, THEN PLACE STEP HIGH FLUX AT SHUTDOWN alarm block switches in NORMAL [M-13].
SAT STANDARD:
Applicant observes the RED ALARM light is LIT on 1-NI-92-133D UNSAT SHUTDOWN MONITOR.
The applicant depresses the RESET pushbutton adjacent to the ALARM light on 1-N 1-92-1 33D, and observes the RED ALARM light is DARK.
Applicant observes the RED ALARM light is LIT on 1-Nl-92-133E SHUTDOWN MONITOR.
The applicant depresses the RESET pushbutton adjacent to the ALARM light 1-NI-92-133E, and observes the RED ALARM light is DARK.
The applicant locates the HIGH FLUX AT SHUTDOWN switch on 1-NI-92-131-D, and rotates the switch to the left from the BLOCK to the NORMAL position.
The applicant locates the HIGH FLUX AT SHUTDOWN switch on 1-NI-92-132-E, and rotates the switch to the left from the BLOCK to the NORMAL position.
Step is critical to ensure the shutdown monitor alarm circuit is properly initialized after the trip.
Applicant determines that Step 18 has been completed and informs the Unit Supervisor of completion.
COMMENTS:
END OF TASK STOP TIME Page8of9
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
1.
Unit I was inadvertently tripped from 100% power approximately 20 minutes ago.
2.
ES-0.1, Reactor Trip Response, was entered and the crew just completed Step 17.
INITIATING CUES:
1.
The US directs you as the OAC to ensure source range monitors are reinstated per ES-0.1, Step 18.
2.
Inform the US when the source range monitors have been reinstated and all functions of the source range monitors are in service.
B.1.f
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.g 2011-12 NRC Exam FINAL SUBMITTAL B.1.g Purge Lower Containment NOTE: This JPM may be conducted on the Simulator OR in the Main Control Room THIS JPM MAY BE CONDUCTED IN PARALLEL WITH B.1.h.
PAGE 1 OF 27
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.g 2011-12 NRC Exam EVALUATION SHEET Task:
Purge Lower Containment Alternate Path:
n/a Facility JPM #:
3-OT-JPMR173A (Modified)
Safety Function:
8
Title:
Containment Systems KIA 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:
SOl-30.02, Containment Purge System, Rev. 57.
Task Number:
RO-030-SOl-30-008
Title:
Purge the Lower Containment.
Task Standard:
The applicant places Lower Containment Purge in service using SOI-30.02, Containment Purge System, Section 5.2, Start Up Lower Containment Purge, through Step 19.
Validation Time:
20 minutes Time Critical:
Yes No X
Applicant:
Time Start:
NAME Docket No.
Time Finish:
Performance Rating:
SAT UNSAT Performance Time Examiner:
/
NAME SIGNATURE DATE COMMENTS PAGE 2 OF 27
WATTS BA NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.g 2011-12 NRC Exam IF CONDUCTED IN THE SIMULATOR, THEN PERFORM THE FOLLOWING:
SIMULATOR OPERATOR INSTRUCTIONS:
1.
ENSURE NRC Examination Security has been established.
2.
RESET to Initial Condition by performing the following actions:
a.
Select ICManager on the THUNDERBAR menu (right hand side of Instructor Console Screen).
b.
Locate IC 310.
c.
Right click on IC 310.
d.
Select Reset on the drop down menu.
e.
Right click on RESET.
f.
Enter the password for IC 310.
g.
Select Yes on the INITIAL CONDITION RESET pop-up window.
h.
Perform SWITCH CHECK.
3.
Place simulator in RUN and acknowledge any alarms.
4.
ENSURE a marked-up copy of {Insert appropriate procedure here), signed (circled-and-slashed) through Step, 5.
ENSURE Extra Operator is present in the simulator.
6.
Place simulator in FREEZE until Examiner cue is given.
7.
THIS JPM MAY BE CONDUCTED IN PARALLEL WITH BRI.h.
PAGE 3 OF 27
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.g 2011-12 NRC Exam IF CONDUCTED IN THE MAIN CONTROL ROOM, THEN:
Tools/Equipment/Procedures Needed:
ENSURE that copies of SOI-3003, Containment HVAC and Pressure Control, available to the EXAMINER, marked as NRC EXAM MATERIAL, FOR TRAINING ONLY, for each applicant.
Begin the JPM at the Shift Managers Desk.
PA( 4 oP 27
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
1 1.g 2011-12 NRC Exam READ TO APPLICANT DIRECTION TO APPLICANT:
I will explain the initial condilions, 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 I is in Mode 1.
- 2. A purge of Upper Containment was just completed.
- 3. A purge of the Lower Containment is scheduled to be performed on this shift.
- 4. The area outside Unit I intake is clear of fumes and there are no running vehicles in the area.
- 5. SOI-30.02, Containment Purge System, Section 4.0, Prerequisite Actions is cornplete.
- 6. SOI-30.02, Containment Purge System, Section 5.2, Start Up Lower Containment Purge, is complete through Step 10.
- 7. You are an extra Control Room Operator assigned to the shift.
INITIATING CUES:
The Unit Supervisor has directed you to place B train Lower Containment Purge in service, beginning at Step 11.
PA(F 5 flF 27
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.g 2011-12 NRC Exam STEPISTANDARD SAT/UNSAT I
START TIME:
NOTE 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-90-415-B are in the REFUEL position.
STEP 1: [11] PERFORM the following: (NIA HS NOT used)
PERF NOMENCLATURE LOCATION POSITION UNID INITIAL PURGE EXH FAN A SUCT 1-M-9 OPEN 1HS-3O61 PURGE EXH FAN B SUCT 1-M-9 OPEN 1-HS-30-62 STANDARD:
Applicant determines from the INITATING CUES that Train B equipment will be used for the purge.
Applicant enters N/A for 1-HS-30-61, PURGE EXH FAN A SUCT.
Applicant locates 1-HS-30-62 PURGE EXH FAN B SUCT and rotates the handswitch to the right to the OPEN position.
Applicant observes the PURGE EXH FAN B SUCT is OPEN by the RED indicating light LIT and the GREEN indicating light DARK.
Step is critical to ensure proper purge flowpath is established.
COMMENTS:
EXAMINER: USE PAGES 6 through 16 if conducting JPM on the Simulator.
SIMULATOR PERFORMANCE CRITICAL STEP SAT UNSAT Page 6 of 27
PERP NOMENCLATURE LOCATION POSITION UNID INITIAL LWR CNTMT PURGE 1-M-9 OPEN 1-HS-30-14 1-FCV-30-14 & 56 LWR CNTMT PURGE 1-M-9 OPEN 1-HS3O-15 1-FCV-30-15 & 57 STANDARD:
Applicant locates 1-HS-30-14 LWR CNTMT PURGE 1-FCV-30-14 & 56 and rotates the handswitch to the right to the OPEN position.
Applicant observes the LWR CNTMT PURGE 1-FCV-30-14 is OPEN by the RED indicating light LIT and the GREEN indicating light DARK.
Applicant observes the LWR CNTMT PURGE 1-FCV-30-56 is OPEN by the RED indicating light LIT and the GREEN indicating light DARK Applicant locates 1-HS-30-15 LWR CNTMT PURGE 1-FCV-30-15 & 57 and rotates the handswitch to the right to the OPEN position.
Applicant observes the LWR CNTMT PURGE 1-FCV-30-15 is OPEN by the RED indicating light LIT and the GREEN indicating light DARK.
Applicant observes the LWR CNTMT PURGE 1-FCV-30-57 is OPEN by the RED indicating light LIT and the GREEN indicating light DARK Step is critical to ensure proper purge flowpath is established.
COMMENTS:
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.g 2011-12 NRC Exam STEP/STANDARD I
SAT/UNSAT CAUTION If Lower Containment is purged during modes 1 -4, only one set of supply isolation valves may be opened. This means supply valves 1-FCV-30-16 and -17 must remain closed.
STEP 2: [12] PERFORM the following:
CRITICAL STEP SAT UNSAT Page 7 of 27
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.g 2011-12 NRC_Exam STEP/STANDARD SAT/U NSAT STEP 3: [13] ALIGN Exh Fans Disch Flood dampers per 5.2[13.1],
SAT 5.2[13.2], or 5.2[13.3]: (NIA subsection NOT performed)
UNSAT
[13.1] IF Train A will be run, THEN PERFORM the following:
STANDARD:
Applicant refers to INITIATING CUES, determines that Train B will be placed in service and enters N/A for Step 13.1.
COMMENTS:
Page 8 of 27
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.g 2011-12 NRC Exam PERF NOMENCLATURE LOCATION POSITION UNID INITIAL PURGE EXH FAN 1A TO 1-M-9 CLOSED 1-HS-30-213 SHIELD BLDG VNT PURGE EXH FAN lB TO 1-M-9 OPEN 1-HS-30-216 SHIELD BLDG VNT STEP/STAN DARD SAT/UNSAT STEP 4: [13] ALIGN Exh Fans Disch Flood dampers per 5.2[13.1],
5.2[13.2], or 5.2[13.3]: (N/A subsection NOT performed)
[13.2] IF Train B will be run, THEN CRITICAL STEP SAT STANDARD:
UNSAT Applicant locates 1-HS-30-213 PURGE EXH FAN 1A SHIELD BDLG VNT and observes damper is CLOSED by the RED indicating light DARK and the GREEN indicating light LIT.
Applicant locates 1-HS-30-216 PURGE EXH FAN 1A SHIELD BDLG VNT and rotates the handswitch to the right to the OPEN position.
Applicant observes the damper is OPEN by the RED indicating light LIT and the GREEN indicating light DARK.
COMMENTS:
Step is critical to align Train B of the purge system.
Page9of27
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.g 2011-12 NRC_Exam STEPISTAN DARD SAT/U NSAT STEP 5: [13] ALIGN Exh Fans Disch Flood dampers per 5.2[13.1],
SAT 5.2[13.2], or 5.2[13.3]: (N/A subsection NOT performed)
UNSAT
[13.3] IF Both Train A and B will be run, THEN STANDARD:
Applicant refers to INITIATING CUES, determines that Train B will be placed in service and enters N/A for Step 13.3.
COMMENTS:
NOTE Opening I -FCV-30-2 (Tr A) and/or -5 (Tr B) LAST, ensures negative press in Lower Containment compared to Upper Containment during the Startup transient.
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 Train 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-S 1-0 (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}
CUE: IF contacted as an AUO, state that there are NO fumes or running vehicles near the Unit I intake.
- 3) For normal plant operations, purge should NOT be placed in service unless the UI shield bldg. exhaust monitor and its associated isokinetic sampler are operable.
Page 10 of 27
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.g 2011-12 NRC Exam STEPISTAN DARD SAT/U NSAT STEP 6: [14] START Selected Sup & Exh Fan: (N/A if NOT started)
PERF NOMENCLATURE LOCATION POSITION UNID INITIAL CNTMT PURGE SUP & EXH 1-M-9 START 1-HS-30-IA FANS IA AND FCO-30-1A& lB CNTMT PURGE SUP & EXH l-M9 START 1-HS-30-4A FANS lB AND FCO-30-4A & 48 STANDARD:
Applicant determines from the INITATING CUES that Train B equipment will be used for the purge.
Applicant refers to INITIATING CUES, determines that Train B will be placed in service and enters N/A for Step 14 addressing 1-HS-30-IA.
Applicant locates 1-HS-30-4A CNTMT PURGE SUP & EXH FANS lB AND FCO-30-4A & B and rotates the handswitch to the right to the START position.
Applicant observes the fans are RUNNING and dampers are OPEN by the RED indicating lights LIT and the GREEN indicating lights DARK.
Step is critical to align Train B of the purge system.
COMMENTS:
CRITICAL STEP SAT UNSAT CAUTION If Ice Condenser doors open after opening FCV-30-2 and/or 30-5, an out-of-balance flow may exist. System Engineering should be notified to evaluate flowrates.
Page 11 of27
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.g 2011-12 NRC Exam PERF NOMENCLATURE LOCATION POSITION UNID INITIAL PURGE SUP FAN 1A DISCH 1-M-9 OPEN 1-HS-30-2 PURGE SUP FAN lB DISCH l-M--9 OPEN 1-HS-30-5 STEPISTANDARD SAT/UNSAT STEP 7: [15] OPEN Selected Sup Fan Disch damper: (N/A if NOT selected)
CRITICAL STEP STANDARD:
SAT UNSAT Applicant determines from the INITATING CUES that Train B equipment will be used for the purge.
Applicant refers to INITIATING CUES, determines that Train B will be placed in service and enters N/A for Step 14 addressing 1-HS-30-2.
_Applicant locates 1-HS-30-5 PURGE FAN lB DISCH and rotates the handswitch to the right to the OPEN position.
Applicant observes the damper is OPEN by the RED indicating lights LIT and the GREEN indicating light DARK.
COMMENTS:
Step is critical to align Train B of the purge system.
Page 12 of27
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
1 1.g 2011-12 NRC Exam STE PISTAN DARD STEP 8: [16] ENSURE the following: (NIA Train NOT used)
STANDARD:
Applicant determines from the INITATING CUES that Train B equipment will be used for the purge.
Applicant observes that 1-XI-30-294, PURGE SUP SUCT ISOL DAMPER and 1-XI-30-295 RED indicating lights are LIT and GREEN indicating lights are DARK.
Applicant refers to INITIATING CUES, determines that Train B will be placed in service and enters N/A for Step 16 addressing 1-HS-30-IA and 1-HS-30-IB.
Applicant observes that damper FCO-30-4A is OPEN by the RED indicating lights LIT and the GREEN indicating light DARK on 1-XI 4A.
SAT/U NSAT UNSAT Applicant observes that damper FCO-30-4B is OPEN by the RED indicating lights LIT and the GREEN indicating light DARK on 1-XI 4B.
COMMENTS:
SAT PERF NOMENCLATURE LOCATION POSITION UNID INITIAL PURGE SUP SUCT SQL 1-M-9 OPEN FCO-30-294 DAMPER 1 -XI-30-294 PURGE SUP SUCT ISOL 1-M-9 OPEN FCO-30-295 DAMPER 1 -XI-30-295 Train A DAMPER 1-XI-30-1A 1-M-9 OPEN FCO-130-1A DAMPER 1-XI-30-1B 1.M..9 OPEN FCO-30-1B Train B DAMPER 1XI-3O-4A 1.M-9 OPEN FCO-30-4A DAMPER 1XI-3O-4B 1-M-9 OPEN FCO-30-4B Page 13 of 27
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.g 2011-12 NRC_Exam STEPISTANDARD SATIUNSAT STEP 9: [17] CHECK flow on 1 Fl-90-400, SHIELD BLDG VT FLOW SAT
[1-M-9]. (NIA if Fl NOT available)
UNSAT STANDARD:
Applicant observes flow rising on 1-Fl-90-400, SHIELD BLDG VT FLOW.
COMMENTS:
STEP 10: [18] IF FI-90-400 is NOT available, THEN ENSURE Flow being SAT estimated per 1-S1-0-2-00, Shift & Daily Log.
UNSAT STANDARD:
Applicant determines that 1-FI-90-400 is available and enters N/A for Step 18.
COMMENTS:
NOTE Ice Condenser vent curtain should be checked for proper vertical position and repositioned if necessary after starting CONTAINMENT purge.
Pagel4of27
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.g 2011-12 NRC Exam STEP/STANDARD SAT/U NSAT STEP 11: [19] NOTIFY the Chemistry Countroom of the purge start date SAT and time.
UNSAT STANDARD:
Applicant notifies the Chemistry Countroom of the purge start date and time.
CUE:
When notified, acknowledge the report. State another operator will continue from here COMMENTS:
END OF TASK STOP TIME Page 15of27
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
1.
Unit I is in Mode I.
- 2. A purge of Upper Containment was just completed.
- 3. A purge of the Lower Containment is scheduled to be performed on this shift.
- 4. The area outside Unit I intake is clear of fumes and there are no running vehicles in the area.
- 5. 501-30.02, Containment Purge System, Section 4.0, Prerequisite Actions is complete.
- 6. 501-30.02, Containment Purge System, Section 5.2, Start Up Lower Containment Purge, is complete through Step 10.
- 7. You are an extra Control Room Operator assigned to the shift.
INITIATING CUES:
The Unit Supervisor has directed you to place B train Lower Containment Purge in service, beginning at Step 11.
B.1.g
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B1Ji (RO ONLY) 2011-12 NRC Exam FINAL SUBMITTAL B.1 1
h Start Standby Main Feedwater Pump THIS JPM MAY BE CONDUCTED IN PARALLEL WITH B1 1
g.
PAflP I OF II
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.h (RO ONLY) 2011-12 NRC Exam Task:
Start Standby Main Feedwater Pump.
Alternate Path:
n/a Facility JPM #:
Modified Safety Function:
4S
Title:
Heat Removal from the Core
- Secondary KIA 059 A4.03 Ability to manually operate and monitor in the main control room:
Feedwater control during power increase and decrease.
Rating(s):
2.9 / 2.9 CFR:
41.7 / 45.5 to 45.8 Preferred Evaluation Location:
Preferred Evaluation Method:
Simulator X
In-Plant Perform X
Simulate
References:
SOI-2&3.01 Condensate And Feedwater Systems, Rev. 112.
Task Number:
RO-003-SOl-2&3-001
Title:
Operate the Standby Main Feedwater Pump Task Standard:
The applicant starts the Standby Main Feedwater pump in parallel with the Main Feedwater Pumps and adjusts Main Feedwater Pump pressure to load the Standby Main Feedwater pump to provide 4000 gpm of flow.
Validation Time:
20 minutes Time Critical:
Yes No X
Applicant:
Time Start:
NAME SSN Time Finish:
Performance Rating:
SAT UNSAT Performance Time Examiner:
/
NAME SIGNATURE DATE COMMENTS PA(P 2 flP 11
WATTS BAi NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.h (RO ONLY) 2011-12 NRC Exam 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.
Place simulator in RUN and acknowledge any alarms.
7.
ENSURE marked-up copy of SOl-2&3.01 Condensate and Feedwater Systems, is available to the Examiner. Ensure that Step 8.941] of SOI-2&3.01 is marked, NIA.
8.
Place simulator in FREEZE until Examiner cue is given.
9.
Call up THUNDERVIEW SCREEN fw3, Main Feedwater which allows for reporting positions of valves associated with SFMP startup.
PAGE 3011
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.ih (RO ONLY) 2011-12 NRC Exam DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications.
I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
1.
Unit I is at 100% power.
- 2. The SMFP is aligned for service per SOI-2&3M1, Condensate and Feedwater Systems, Section 59, Standby Main Feed Pump Operation Or Standby Alignment.
- 3. You are the Control Room Operator (CR0).
INITIATING CUES:
- 1. The Unit Supervisor has directed you to place the Standby Main Feed Pump in service using SOI-2&3.01, Condensate and Feedwater Systems, Section 8.9, Replacing Turbine Driven MFP with SMFP, or Periodic Operation of SMFP.
2.
Inform the Unit Supervisor when the Standby Main Feedwater Pump is in service, providing between 3500 and 4000 gpm of feedwater flow.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.h (RO ONLY) 2011-12 NRC Exam STEP/STANDARD SATIUNSAT START TIME:
NOTE TO EVALUATOR: The following actions are taken from SOI-2&3.01, Condensate and Feedwater System, Section 8.9, Replacing Turbine Driven MFP with SMFP, or Periodic Operation of SMFP.
CAUTIONS
- 1) MFP discharge should remain less than 1185 psig when possible. Short duration press up to 1363 psig (MFP Disch Press Admin Limit) is acceptable, but care must be taken to prevent sudden pressure elevations from lifting #1 Heater Reliefs at 1650 psig.
Runback circuitry may be verified at 1-L-262 [729, T3J] using PIS-47-13 display.
RLYI indicates load >67% and RLY3, indicates load >85%. Impulse pressure equivalent to 85% load enables the runback circuitry.
- 3) MFP I B must NOT be operated at a higher speed than MFP IA or in the resonance speed range between 4900 and 5000 rpm due to high vibration on the inboard bearing and turning gear motor. Speed controllers have been calibrated to prevent this condition; however, a WO should be generated if the controllers fail to control this occurrence.
NOTES
- 1) One MFP is capable of delivering sufficient flow to maintain 67% load.
- 2) Unit load can be maintained at 85% with the SMFP and one MFP in operation.
- 3) Unit load can be maintained at 100% for periodic operation of SMFP with one TDMFP partially unloaded.
- 4) Starting a main feed pump (SBMFP or MFPT) may cause perturbation in heater drain tank levels that may NOT be compensated for by the level controllers.
- 5) In Mode 1, entry into Tech Spec 3.3.2 condition J may be suspended for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> when removing one of two Turbine Driven Main Feedwater Pumps (TDMFWP) from service. Refer to Tech Spec 3.3.2 table 3.3.2-1.
- 6) In Mode 2, trip function of all Turbine Driven Main Feedwater Pumps (TDMFWP) is required when one or more (TDMFWP) is supplying feedwater to the Steam Generators.
Refer to Tech Spec 3.3.2 condition J.
Page 5 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.h (RO ONLY) 2011-12 NRC Exam
[
STEPISTANDARD I
SAT/UNSAT STEP 1:
[1] IF one TDMFP is to be completely shutdown, THEN SAT ENSURE Turbine Runback circuitry reset by verifying RLY3, PIS-47-13 DISPLAY NOT actuated (<85%) [Panel UNSAT 1 -L-262] [729/T3J].
STANDARD:
Applicant determines from the INITIAL CONDITIONS that the Main Feedwater pumps will remain in service, and the step is N/A.
COMMENTS:
STEP 2:
[2] ENSURE SMFP is aligned for service per Section 5.9.
SAT STANDARD:
UNSAT Applicant determines from INITIAL CONDITIONS that the SMFP is aligned per Section 5.9.
COMMENTS STEP 3:
[3] VERIFY 1-FIC-3-208 [1-FIC-3-208], STANDBY MFWP SAT RECIRC CONTROL [1-M-3], in AUTO, AND SET at 90%
(l500gpm).
UNSAT STANDARD:
Applicant determines from controller 1-FIC-3-208 on 1-M-3 panel that the controller is in AUTO and is set at 90%.
COMMENTS:
Page 6of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.h (RO ONLY) 2011-12 NRC_Exam STEPISTANDARD SATIUNSAT STEP 4:
[4] ENSURE 1-FCV-3-205 [1-HS-3-205], STANDBY MAIN SAT FEEDWATER PUMP DISCHARGE ISOL [TIJ/729], OPEN.
UNSAT STANDARD:
Applicant contacts Turbine Building AUO and asks if 1-FCV-3-205 is OPEN.
CUE:
As Turbine Building AUO, when contacted report that 1-FCV-3-205 is open.
COMMENTS:
STEP 5:
[5] ENSURE 1-FCV-2-265 [1-HS-2-265], STANDBY MAIN SAT FW PUMP SUCT ISOL [T1J1729], OPEN.
UNSAT STANDARD:
Applicant contacts Turbine Building AUO and asks if 1-FCV-2-265 is OPEN.
CUE:
As Turbine Building AUO, when contacted report that 1-FCV-2-265 is open.
COMMENTS:
Page 7 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.h (RO ONLY) 2011-12 NRC Exam STEPISTANDARD I_SATIUNSAT STEP 6:
[6] VERIFY 1-Pl-2-129, MEW PMPS SUCT PRESS [1-M-3],
SAT as follows:
UNSAT A.
Greater than 100 psig (below 50% load).
B.
Greater than 250 psig (at or above 50% load).
STANDARD:
Applicant observes 1-Pl-2-129 MEW PMPS SUCT PRESS on 1-M-3 and determines that suction pressure is approximately 41 0-430 psig, sufficient for starting the SMEP.
COMMENTS:
EXAMINER: Until the Standby Main Feedwater pump is started, 1-FIC-3-208, STANDBY MFWP RECIRC CONTROL on 1-M-3 displays DEMAND, not ACTUAL position.
STEP 7:
[7] ENSURE 1-ECV-3-208 [1-HS-3-208}, STANDBY MAIN SAT EEEDWATER PUMP MIN ELOW [TIJ/729], CLOSED.
UNSAT STANDARD:
Applicant contacts Turbine Building AUO and asks if 1-ECV-3-208 is CLOSED.
CUE:
As TB AUO, when contacted report that 1-FCV-3-208 is closed.
COMMENTS:
CAUTION Manual operation of TDMFP speed control during MFP starts/stops will minimize system fluctuations.
Page 8 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.th (RO ONLY) 2011-12 NRC Exam STEPISTAN DARD SATIUNSAT STEP 8:
[8] (p) CONTROL TDMFP speed in MAN.
CRITICAL STEP STANDARD:
SAT Applicant places 1-PC-46-20, MFPT A & B MASTER SPEED CONTROL in MANUAL.
UNSAT Step is critical to ensure that feedwater oscillations are avoided when starting the SMFP.
COMMENTS:
STEP 9:
[9] (p) IF SMFP to operate with TDMFP, THEN SAT SLOWLY RAISE TDMFP speed until SMFP minimum flow head is achieved (above 1200 psig).
UNSAT STANDARD:
Applicant ensures pressure is slightly above 1200 psig using 1-Pl-3-66A (MFWP A DISCH PRESS) or 1-PI-3-80A (MFWP B DISCH PRESS) or 1-P1-3-I (#1 HTR INLET PRESS). Applicant may increase TDMFP speed if necessary.
COMMENTS:
Page 9 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.h(RO ONLY) 2011-12 NRC_Exam STEP/STANDARD SATIUNSAT STEP 10:
[10] (p) IF SMFP to operate with TDMFP, THEN START CRITICAL SMFP with 1-HS-3-200A, STANDBY MFWP, AND STEP LOWER TDMFP flow, OR SHUTDOWN TDMFP per Section 7.3.
SAT STANDARD:
UNSAT Applicant starts SMFP with 1-HS-3-200A, observes amps on 1-EI-3-200, STANDBY MFWP AMPS, and pressure on 1-PI-3-203A, STANDBY MFWP DISCH PRESS.
Applicant reduces TDMFP flow by reducing the control signal from 1-PC-46-20, MFPT A & B MASTER SPEED CONTROL, and observes a rise in flow from the SMFP. Per the INITIATING CUES the applicant will load the SMFP to between 3500 and 4000 gpm.
CUE:
When the applicant has loaded the SMFP to between 3500 and 4000 gpm, then state another operator will perform the remainder of the section.
Step is critical to ensure that the SMFP is properly loaded.
COMMENTS:
STOP TIME Page 10 of 11
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- 1. Unit I is at 100% power.
- 2. The SMFP is aligned for service per SOI-2&3.01, Condensate and Feedwater Systems, Section 5.9, Standby Main Feed Pump Operation Or Standby Alignment.
- 3. You are the Control Room Operator (CR0).
INITIATING CUES:
- 1. The Unit Supervisor has directed you to place the Standby Main Feed Pump in service using SOI-2&3.01, Condensate and Feedwater Systems, Section 8.9, Replacing Turbine Driven MFP with SMFP, or Periodic Operation of SMFP.
- 2. Inform the Unit Supervisor when the Standby Main Feedwater Pump is in service, providing between 3500 and 4000 gpm of feedwater flow.
B.1.h (RO ONLY)
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.i 2011-12 NRC Exam FINAL SUBMITTAL B.1.i Bypass I -FCV-62-89 Charging Flow for Local Control PACE I OF 9
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B1.i 2011-12 NRC Exam EVALUATION SHEET Task:
Bypassing of 1-FCV-62-89, charging flow cont vlv, for the purposes of local control per SOI-62.01 Alternate Path:
N/A Facility JPM #:
3-OT-JPMAO1 1 Rev 5 Safety Function:
2
Title:
Inventory Control KIA 004 A4.08 Ability to manually operate and/or monitor in the control room: Charging Rating(s):
3.8/3.4 CFR:
41/7 I 45.5 to 45.8 Evaluation Method:
Simulator In-Plant X
Classroom
References:
SOl-62.01 Rev 62 CVCS Charging and Letdown Task Number:
AUO-062-SOI-62. 1-007
Title:
Bypassing 1 -FCV-62-89, Charging Flow Control, for Local Control Task Standard:
1-FCV-62-89, Charging Flow Control Valve has been bypassed in accordance with SOl-62.01, CVCS-Charging and Letdown, Section 8.6, Bypassing 1-FCV-62-89, CHARGING FLOW CONT, for Local Control and Seal Flow to the RCPs has been returned to normal range (8 to 13 gpm).
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 PACE 2 OF 9
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.i 2011-12 NRC Exam TOOLSIEQUIPMENTIPROCEDURES NEEDED:
Hard-hat, Safety Glasses, Hearing Protection Plant Approved Shoes Gloves ALARA considerations Note: Have a marked up copy of SOI-62.O1, CVCS-Charging and Letdown, Section 8.6, Bypassing 1-FCV-62-89, CHARGING FLOW CONT, for Local Control to give to each applicant.
START THIS JPM AT THE, RAD WASTE AUO DESK.
PAGE 3 OF 9
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.ii 2011-12 NRC Exam READ TO APPLICANT DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications.
I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the cue sheet I provided you.
INITIAL CONDITIONS:
1.
Unit at 100% power.
2.
1-FCV-62-89 is malfunctioning and cannot be controlled from the Main Control Room (MCR).
3.
Seal flow is at 6 gpm per RCP.
4.
Charging flow is at 55 gpm.
5.
You are an AUO on shift.
INITIATING CUES:
The Unit Operator has directed you to establish communications with the MCR, bypass 1-FCV-62-89, and take local control of the seal injection flow using SOI 62.01, CVCS-Charging and Letdown, Section 8.6, Bypassing 1-FCV-62-89, CHARGING FLOW CONT, for Local Control, while establishing and maintaining 8 to 13 gpm to each of the RCP seals.
PA(P 4 OF 9
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.i 2011-12 NRC Exam STEPISTANDARD I
SATIUNSAT START TIME:
STEP 1: [1] ESTABLISH communications with personnel at the following SAT areas as required:
[1.1]
Blenderarea [PNL 1-L-348, eI 713].
UNSAT
[1.2]
At least one Charging Flow indication area:
A.
Main Control Room [1-M-6] 1-Fl-62-93A, CHARGING FLOW.
B.
Aux Control Room [1-L-1O] 1-FI-62-93C, CHARGING FLOW.
C.
PNL 1-L-112A [el 692] 1-FI-62-93B, CVCS CHARGING HEADER FLOW.
STANDARD:
Applicant establishes communications with the Main Control Room.
CUE:
When MCR contacted, the current charging flow is 55 gpm and the seal flow is 6 gpm per RCP.
EXAMINER:
When in the area of 1-FCV-62-89 isolation valves (penetration room) the applicant may use the radio or phone to contact the MCR.
COMMENTS:
PAGE 5 OF 9
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.i 2011-12 NRC_Exam STEP/STAN DARD SATIU NSAT STEP 2: [2] OPEN 1-BYV-62-538, CVCS CHARGING FCV-62-89 CRITICAL BYPASS, until full open OR until charging flow rises.
STEP STANDARD:
_Applicant locates 1-BYV-62-538 and throttles it open (turned in the UNSAT counter-clockwise direction).
CUE:
After the bypass valve is throttled in the open direction, inform the applicant that there has been an increase in charging flowS Step is critical to establish a flow path around the malfunctioning valve.
COMMENTS:
PAGE 6 OF 9
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.i 2011-12 NRC Exam STEP/STANDARD
[
SAT/UNSAT STEP 3: [3]
CLOSE one of the following to isolate I -FCV-62-89 (N/A valve NOT closed):
PERF NOMENCLATURE LOCATION UNID INITIAL CVCS CHARGING A4U/692 1-ISV-62-537 HEADER ISOLATION CVCS CHARGING A4U/692 1-ISV-62-539 HEADER ISOLATION STANDARD:
Applicant locates 1 -ISV-62-537 or 1 -ISV-62-539 and closes either valve (turned in the clockwise direction).
Applicant enters N/A for valve not closed.
CUE:
After the applicant indicates the valve closes in the clockwise direction, inform the applicant that the hand wheel turns several turns and stops.)
CUE:
After the applicant closes either valve, inform the applicant that RCP seal flow is 14 gpm per pump.
Step is critical to isolate the flow path thru the malfunctioning valve.
COMMENTS:
CLOSING 1-BYV-62-538 raises seal flow.
NOTE CRITICAL STEP SAT UNSAT PAGE 7 OF 9
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.i 2011-12 NRC Exam STEPISTANDARD SATIUNSAT STEP 4: [4]
ADJUST 1-BYV-62-538, CVCS CHARGING FCV-62-89 CRITICAL BYPASS [A4U/692], to maintain between 8 and 13 gpm to STEP each RCP.
SAT STANDARD:
UNSAT Applicant indicates 1 -BYV-62-538 is throttled open (turned counterclockwise) to decrease seal flow and stabilized between 8 to 13 gpm.
CUE:
After valve throttled counterclockwise to open, state that seal flow is now 9 gpm.
CUE:
After 9 gpm seal flow has been established, state the Rad Waste AUO will take over and maintain the seal flow.
Step is critical to ensure adequate seal flow to each RCP.
COMMENTS:
END OF TASK STOP TIME PAGE 8 OF 9
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
1.
Unit at 100% power.
2.
1-FCV-62-89 is malfunctioning and cannot be controlled from the Main Control Room (MCR).
3.
Seal flow is at 6 gpm per RCP.
4.
Charging flow is at 55 gpm.
5.
You are an AUO on shift.
INITIATING CUES:
The Unit Operator has directed you to establish communications with the MCR, bypass 1-FCV-62-89, and take local control of the seal injection flow using SOI 62.01, CVCS-Charging and Letdown, Section &6, Bypassing 1-FCV-62-89, CHARGING FLOW CONT, for Local Control, while establishing and maintaining 8 to 13 gpm to each of the RCP seals.
B.1.i
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.j
- TRAIN A 2011-12 NRC Exam FINAL SUBMITTAL B.1.j TRAIN A Restore IA-A DG to Operable Following Rolling to Check for Water in Cylinders Per SOl-82.OI Page 1 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.lj - TRAIN A 2011-12 NRC Exam EVALUATION SHEET Task:
Restore lA-A DG to Operable Following Rolling to Check for Water in Cylinders per SOl-82.01.
Alternate Path:
N/A Facility JPM #:
3-OT-JPMA048 Safety Function:
6
Title:
Electrical (Emergency Diesel Generators)
K/A:
064 A2.1 5 Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (Water buildup in cylinders).
Rating(s):
2.6/3.1 CFR:
41.5 / 43.5 I 45.3 / 45.13 Evaluation Method:
Simulator In-Plant X
Classroom
References:
SO1-82.01, Diesel Generator (DG) lA-A, Section 8.2, Rolling DG to Check for Water in Cylinders Rev 76.
Task Number:
AUO-082-SOI-82.1-006
Title:
Roll a Diesel Generator to check for water in the cylinders.
Task Standard:
DG lA-A is returned to OPERABLE status after rolling one revolution.
Validation Time:
15 minutes Time Critical:
Yes No X
Applicant:
Time Start:
NAME Docket No.
Time Finish:
Performance Rating:
SAT UNSAT Performance Time Examiner:
I NAME SIGNATURE DATE COMMENTS Page 2 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.j
- TRAIN A 2011-12 NRC Exam TOOLSIEQUIPMENTIPROCEDURES NEEDED:
Hard-hat, Safety Glasses, Hearing Protection Plant Approved Shoes Gloves ALARA considerations Note: Have a marked up copy of SOI-82.O1, Diesel Generator lA-A, Section 8.2, Rolling DG to Check for Water in Cylinders, to give to each applicant.
START THIS JPM IN THE SERVICE BUILDING CORRIDOR ABOVE MAINTENANCE SHOPS, ELEVATION 729, NEAR THE NORTH EXIT FROM BUILDING (ROLL-UP DOOR),
OR OTHER LOCATION SUCH AS THE DG BUILDING AT EVALUATORS DISCRETION.
Page 3 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.j
- TRAIN A 2011-12 NRC Exam 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 I is in Mode I with all equipment operable.
- 2. Preplanned surveillance testing requires rolling of DG IA-A.
4.
DG IA-A is presently being rolled per SOI-82.01, Diesel Generator IA-A, Section 8.2, Rolling DG to Check for Water in Cylinders.
- 5. You are an AUO on shift.
INITIATING CUES:
I. The Control Room Operator directs you to complete SOI-82.01, Diesel Generator IA-A, Section 8.2, Rolling DG to Check for Water in Cylinders, beginning at Step 14.
2.
Notify the Main Control Room when the task is complete.
Page 4 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.lj TRAIN A 2011-12 NRC Exam STEPISTANDARD SATIUNSAT I
START TIME:
STEP 1: [14] PERFORM the following:
NOMENCLATURE LOCATION POSITION UNID DG ENG 1A1 AIR START DGB LOCKED 1-ISV-82-520A1 MOTOR SUPPLY ISOL OPEN DG ENG 1A1 AIR START DGB LOCKED 1-ISV-82-528A1 MOTOR SUPPLY ISOL OPEN DG ENG 1A2 AIR START DGB LOCKED 1-ISV-82-554A2 MOTOR SUPPLY ISOL OPEN DG ENG 1A2 AIR START DGB LOCKED 1-ISV-82-562A2 MOTOR SUPPLY ISOL OPEN STANDARD:
Applicants locates and describes opening the above listed valves.
Valves are opened by turning their handles counter clockwise.
CUE:
The applicant determines that the as-found position of the valves would be closed. Cue that their handles are 90 deg. to pipe.
NOTE: Back front valve handle is down others are up.
CUE:
As applicant locates and addresses opening the valves, cue that their handles turned counter clockwise and are parallel to the pipe.
CUE:
If the operator requests an CV, acknowledge the request.
NOTE: Valves may be operated in any sequence.
This step is critical to line air to the air start motors for the DG.
COMMENTS:
CRITICAL STEP SAT UNSAT Page5ofll
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.j TRAIN A 2011-12 NRC_Exam STEP/STANDARD SATIUNSAT STEP 2: [15] CLOSE 1-SW-82-A/1, DG IA-A DISCONNECT SWITCH, CRITICAL
[Local Switchgear PnI, IA-A DG Rm]
STEP STANDARD:
_Applicant indicates I-SW-82-AJ1, DG IA-A DISCONNECT SWITCH, UNSAT would be closed by moving the handle to the up position.
CUE:
The applicant determines that the as-found position of the switch would be OPEN with the handle in down position. Target indicates GREEN and SW OPEN.
CUE:
When applicant addresses closing the switch by moving the handle up cue that the handle is in the up position.
Target indicates RED and SW CLOSED.
CUE:
If the operator requests an IV, acknowledge the request.
This step is critical to restore DG operability.
COMMENTS:
Page 6 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.j TRAIN A 2011-12 NRC_Exam STEPISTANDARD SAT/U NSAT STEP 2: [16] PLACE 1-HS-82-23, MAINT-AUTO SWITCH GEN lA-A, in CRITICAL AUTO [l-PNL-82-A/2, Diesel Engine IAIIIA2 Control STEP Panel].
SAT STANDARD:
UNSAT
_Applicant locates switch 1-HS-82-23, MAINT-AUTO SWITCH GEN IA-A, and indicates it would be rotated to the AUTO position.
CUE:
The applicant determines that the as-found position of the switch would be the MAINT position, cue that it is in the MAINT position. GREEN light is LIT.
CUE:
When rotating the switch to the AUTO position is addressed, cue that it is in the AUTO position. RED light is LIT.
CUE:
If the operator requests an IV, acknowledge the request.
This step is critical to enable DG operation.
COMMENTS:
NOTE If returning to Section 8.1.2 upon completion of this section, then Steps 8.2[17] and 8.2[18]
are N/A.
CUE: Section &1.2 will not be performed.
Page 7 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B1J TRAIN A 2011-12 NRC_Exam STEP/STAN DARD SATIU NSAT STEP 3: [17] PLACE 1-RLY-82-LRXIA, DG lA-A LOCAL/REMOTE CRITICAL CONTROL LOCKOUT, in REMOTE [1 -ARB-82-A/1, STEP Diesel Generator lA-A Relay Board].
SAT STANDARD:
UNSAT
_Applicant indicates 1-RLY-82-LRXIB, DG IA-A LOCAL/REMOTE CONTROL LOCKOUT would be rotated to the REMOTE position.
(Vertical Position).
CUE:
The applicant determines that the as-found position of 1-RLY-82-LRXIB, DG IA-A LOCAL/REMOTE CONTROL LOCKOUT is in the LOCAL position CUE:
When rotating the relay to the REMOTE position is addressed, cue that it is in the REMOTE position.
CUE:
If the operator requests an IV, acknowledge the request.
This step is critical to allow return to standby of DG.
COMMENTS:
Page8ofll
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.j TRAIN A 2011-12 NRC_Exam STEP/STAN DARD SATIUNSAT STEP 4: [18] PLACE 1-HS-82-18, DG MODE SELECTOR, in UNIT CRITICAL (PUSH IN position) [O-M-26].
STEP STANDARD:
SAT Applicant contacts the MCR to place 1-HS-82-18, DG MODE UNSAT SELECTOR, in UNIT.
CUE:
When contacted, repeat back, and then report that 1-HS-82-18 has been placed in UNIT.
CUE:
If the operator requests an IV, acknowledge the request.
This step is critical to allow return to standby of DG.
COMMENTS:
STEP 5: [19] NOTIFY SRO to evaluate exiting LCD 3.8.1.
SAT STANDARD:
UNSAT Applicant contacts Unit Supervisor to evaluate exiting LCD 3.8.1 for DG IA-A.
CUE:
AS Unit Supervisor, acknowledge request, then state that you will make entry into LCO tracking log.
COMMENTS:
Page9ofll
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.j TRAIN A 2011-12 NRC Exam STEPISTANDARD SAT/UNSAT STEP 6: [20] ENSURE 0-S 1-82-9 has been updated (Diesel Generator out SAT of service log).
UNSAT STANDARD:
Applicant contacts the MCR to update 0-S1-82-9 (Diesel Generator Out Of Service Log).
CUE:
When contacted, repeat back, then report O-SI-82-9 has been updated.
COMMENTS:
END OF TASK STOP TIME Page 10 of 11
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- 1. Unit I is in Mode I with all equipment operable.
- 2. Preplanned surveillance testing requires rolling of DG IA-A.
4.
DG IA-A is presently being rolled per S0l-82.OI, Diesel Generator IA-A, Section 8.2, Rolling DG to Check for Water in Cylinders.
- 5. You are an AUO on shift.
INITIATING CUES:
I. The Control Room Operator directs you to complete SOl-82.OI, Diesel Generator IA-A, Section 8.2, Rolling DG to Check for Water in Cylinders, beginning at Step 14.
- 2. Notify the Main Control Room when the task is complete.
B.1.j TRAIN A
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.j TRAIN B 2011-12 NRC Exam FINAL SUBMITTAL B1.j TRAIN B Restore lB-B DG to Operable Following Rolling to Check for Water in Cylinders Per SOl-82.02 Page 1 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.lj TRAIN B 2011-12 NRC Exam EVALUATION SHEET Task:
Restore I B-B DG to Operable Following Rolling to Check for Water in Cylinders per SOl-82.02 Alternate Path:
N/A Facility JPM #:
3-OT-JPMAO48 Safety Function:
6
Title:
Electrical (Emergency Diesel Generators)
K/A:
064 A2.15 Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (Water buildup in cylinders).
Rating(s):
2.6I31 CFR:
41.5 / 43.5 / 45.3 / 45.13 Evaluation Method:
Simulator In-Plant X
Classroom
References:
SOl-82.02, Diesel Generator (DG) I B-B, Section 8.2, Rolling DG to Check for Water in Cylinders Rev 75.
Task Number:
AUO-082-SOl-82.1-006
Title:
Roll a Diesel Generator to check for water in the cylinders.
Task Standard:
DG I B-B is returned to OPERABLE status after rolling one revolution.
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 Page2ofll
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.ij TRAIN B 2011-12 NRC Exam TOOLSIEQUIPMENTIPROCEDURES NEEDED:
Hard-hat, Safety Glasses, Hearing Protection Plant Approved Shoes Gloves ALARA considerations Note: Have a marked up copy of SOl-82.02, Diesel Generator 1 B-B, Section 8.2, Rolling DG to Check for Water in Cylinders, to give to each applicant.
START THIS JPM IN THE SERVICE BUILDING CORRIDOR ABOVE MAINTENANCE SHOPS, ELEVATION 729, NEAR THE NORTH EXIT FROM BUILDING (ROLL-UP DOOR),
OR OTHER LOCATION SUCH AS THE DG BUILDING AT EVALUATORS DISCRETION.
Page3ofll
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.lj TRAIN B 2011-12 NRC Exam 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 I is in Mode I with all equipment operable.
- 2. Preplanned surveillance testing requires rolling of DG lB-B.
4.
DG lB-B is presently being rolled per SOl-82.02, Diesel Generator lB-B, Section 8.2, Rolling DG to Check for Water in Cylinders.
- 5. You are an AUO on shift.
INITIATING CUES:
I. The Control Room Operator directs you to complete SOI-82.02, Diesel Generator I B-B, Section 8.2, Rolling DG to Check for Water in Cylinders, beginning at Step 14.
2.
Notify the Main Control Room when the task is complete.
Page 4 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.j TRAIN B 2011-12 NRC Exam STEP/STANDARD SATIUNSAT START TIME:
STEP 1: [14] PERFORM the following:
NOMENCLATURE LOCATION POSITION UNID DO ENG 1B1 AIR START 0GB LOCKED 1-ISV-82-520B1 MOTOR SUPPLY ISOL OPEN DO ENG 181 AIR START DGB LOCKED 1-ISV-82-52881 MOTOR SUPPLY ISOL OPEN DO ENG 182 AIR START DOS LOCKED 1-ISV-82-554B2 (1OTOR SUPPLY ISOL OPEN DO ENG 1B2 A1R START 0GB LOCKED 1-ISV-82-562B2 MOTOR SUPPLY ISOL OPEN STANDARD:
Applicants locates and describes opening the above listed valves.
Valves are opened by turning their handles counter clockwise.
CUE:
The applicant determines that the as-found position of the valves would be closed. Cue that their handles are 90 deg. to pipe.
NOTE: All handles are down.
CUE:
As applicant locates and addresses opening the valves, cue that their handles turned counter clockwise and are parallel to the pipe.
CUE:
If the operator requests a CV, acknowledge the request.
CRITICAL STEP SAT UNSAT NOTE: Valves may be operated in any sequence.
This step is critical to align air to the air start motors for the DG.
COMMENTS:
Page 5 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.j TRAIN B 2011-12 NRC_Exam STEPISTAN DARD SAT/U NSAT STEP 2: [15] CLOSE 1-SW-82-B/1, DG lB-B DISCONNECT SWITCH, CRITICAL
[Local Switchgear Pnl, 1 B-B DG Rm]
STEP STANDARD:
SAT Applicant indicates 1-SW-82-B/1, DG lB-B DISCONNECT SWITCH, UNSAT would be closed by moving the handle to the up position.
CUE:
The applicant determines that the as-found position of the switch would be OPEN with the handle in down position. Target indicates GREEN and SW OPEN.
CUE:
When applicant addresses closing the switch by moving the handle up cue that the handle is in the up position.
Target indicates RED and SW CLOSED.
CUE:
If the operator requests an IV, acknowledge the request.
This step is critical to restore DG operability.
COMMENTS:
Page 6 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.j TRAIN B 2011-12 NRC Exam STEPISTANDARD SAT/UNSAT STEP 2: [16] PLACE 1-HS-82-53, MAINT-AUTO SWITCH GEN lB-B, in CRITICAL AUTO. [1-PNL-82-B/2, Diesel Engine 1BI/1B2 Control STEP Panel].
SAT STANDARD:
UNSAT Applicant locates switch 1 -HS-82-53, MAINT-AUTO SWITCH GEN 1 B-B, and indicates it would be rotated to the AUTO position.
CUE:
The applicant determines that the as-found position of the switch would be the MAINT position, cue that it is in the MAINT position. GREEN light is LIT.
CUE:
When rotating the switch to the AUTO position is addressed, cue that it is in the AUTO position. RED light is LIT.
CUE:
If the operator requests an IV, acknowledge the request This step is critical to enable DG operation.
COMMENTS:
NOTE If returning to Section 8.1.2 upon completion of this section, then Steps 8.2[17] and 8.2[18]
are N/A.
CUE: Section 8.1.2 will not be performed.
Page 7 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.j TRAIN B 2011-12 NRC Exam STEPISTANDARD SATIUNSAT STEP 3: [17] PLACE 1-RLY-82-LRX1B, DG lB-B LOCAL/REMOTE CRITICAL CONTROL LOCKOUT, in REMOTE [1-ARB-82-B/1 Diesel STEP Generator 1 B-B Relay Board].
SAT STANDARD:
UNSAT Applicant indicates 1-RLY-82-LRX1B, DG lB-B LOCAL/REMOTE CONTROL LOCKOUT would be rotated to the REMOTE position.
(Vertical Position).
CUE:
The applicant determines that the as-found position of 1-RLY-82-LRXIB, DG lB-B LOCAL/REMOTE CONTROL LOCKOUT is in the LOCAL position CUE:
When rotating the relay to the REMOTE position is addressed, cue that it is in the REMOTE position.
CUE:
If the operator requests an IV, acknowledge the request.
This step is critical to allow return to standby of 0G.
COMMENTS:
Page 8 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B1.j TRAIN B 2011-12 NRC Exam STEPISTAN DARD SATIU NSAT STEP 4: [18] PLACE 1-HS-82-48, DG MODE SELECTOR, in UNIT CRITICAL (PUSHED IN position) [O-M-26]
STEP STANDARD:
_Applicant contacts the MCR to place 1-HS-82-48, DG MODE SELECTOR, in UNIT.
UNSAT CUE:
When contacted, repeat back, and then report that 1-HS-82-48 has been placed in UNIT.
CUE:
If the operator requests an IV, acknowledge the request.
This step is critical to allow return to standby of DG.
COMMENTS:
STEP 5: [19] NOTIFY SRO to evaluate exiting LCO 3.8.1.
SAT STANDARD:
UNSAT Applicant contacts Unit Supervisor to evaluate exiting LCO 3.8.1 for DG lB-B.
CUE:
AS Unit Supervisor, acknowledge request, then state that you will make entry into LCO tracking log.
COMMENTS:
Page 9 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.j TRAIN B 2011-12 NRC_Exam STEPISTANDARD SAT/UNSAT STEP 6: [20] ENSURE O-Sl-82-9 has been updated (Diesel Generator out SAT of service log).
UNSAT STANDARD:
Applicant contacts the MCR to update O-Sl-82-9 (Diesel Generator Out Of Service Log).
CUE:
When contacted, repeat back, then report O-SI-82-9 has been updated.
COMMENTS:
END OF TASK STOP TIME Page 10 of 11
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- 1. Unit I is in Mode I with all equipment operable.
- 2. Preplanned surveillance testing requires rolling of DG lB-B.
4.
DG lB-B is presently being rolled per SOl-82.02, Diesel Generator lB-B, Section 8.2, RoIling DG to Check for Water in Cylinders.
- 5. You are an AUO on shift.
INITIATING CUES:
I. The Control Room Operator directs you to complete S01-82.02, Diesel Generator I B-B, Section 8.2, Rolling DG to Check for Water in Cylinders, beginning at Step 14.
2.
Notify the Main Control Room when the task is complete.
B.l.j TRAIN B
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.k 2011-12 NRC Exam FINAL SUBMITTAL B.1.k Swap Seal Injection Filters PAGE 1 OF 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.k 2011-12 NRC Exam EVALUATION SHEET Task:
Swap Seal Injection Filters.
Alternate Path:
n/a Facility JPM #:
3-OT-JPMA116 Safety Function:
4P
Title:
Heat Removal from Reactor Core KIA 003 A4.01 Ability to manually operate and/or monitor in the control room: Seal injection Rating(s):
3.3/3.2 CFR:
41.7 / 45.5 to 45.8 Evaluation Method:
Simulator In-Plant X
Classroom
References:
- CHARGING AND LETDOWN, Rev. 62.
Task Number:
AUO-062-SOI-62.1-014
Title:
Swap Seal Injection Filters.
Task Standard:
Seal Injection Filters have been swapped with A in service and B out of service in accordance with S01-62.01, CVCS-Charging and Letdown, Section 8.9.2, Replacing Filter B with Filter A.
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 PAGE 2 OP 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
1 1.k 2011-12 NRC Exam Tools/EguipmentlProcedures Needed:
Hard-hat, Safety Glasses, Hearing Protection Plant Approved Shoes Gloves ALARA considerations Note: Have a marked up copy of SOl-62.O1, CVCS-Charging and Letdown, Section 8.9.2, Replacing Filter B with Filter A, to give to the applicant.
Note: START THIS JPM AT THE RADWASTE AUO DESK.
PAGE 3 OF 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.k 2011-12 NRC Exam 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 I is at9O% power.
- 3. You are an AUO on shift.
INITIATING CUES:
I. The Unit Operator has directed you to swap seal injection filters per SOl-62.01, CVCS-Charging and Letdown, Section 8.9.2, Replacing Filter B with Filter A.
- 2. You are to place A seal injection filter in service and remove B seal injection filter from service.
- 3. You are to notify the Unit Operator when the seal injection filter swap is complete.
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.k 2011-12 NRC Exam STEP/STANDARD I
SAT/UNSAT START TIME:
NOTE Opening valves slowly when placing the seal water injection filters in service allows the pressure to equalize across filter and prevents filter cartridge failure. Slow operation also minimizes the potential for torque storage in the cable coupling between the reach rod and the handwheel, which may result in unwanted rapid opening of the valve and loss of seal injection flow.
STEP 1: [1] CHECK 1-PDIS-62-96, CVCS SEAL WTR INJECTION SAT FILTER B DIFF PRESS [A5T1713], indicates tiP greater than 20 psid.(N/A if filter changed at discretion of Unit SRO)
UNSAT STANDARD:
Applicant may either:
a.
N/A this step based on Initiating Cues.
OR b.
Elect to Locate 1-PDIS-62-96, CVCS SEAL WTR INJECTION FILTER B DIFF PRESS and check indicated differential pressure.
If this is the case, provide the cue below.
Cue:
After located and checked, indicate a value of 22 psid.
COMMENTS:
PAGE 5011
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.k 2011-12 NRC_Exam STEPISTANDARD SATIUNSAT STEP 2: [2] ENSURE RCP standpipe levels NORMAL (HI/LO alarm clear).
SAT STANDARD:
UNSAT Applicant contacts the Operator-at-the-Controls (OAC) and requests status of the RCP Standpipe level alarms.
Cue:
After OAC is contacted, state that there are NO alarms or other indication of abnormal stand pipe level.
COMMENTS:
STEP 3:
[3] SLOWLY OPEN 1-ISV-62-548, CVCS SEAL WTR INJ FLTR A CRITICAL IN ISOL [A5T1713].
STEP STANDARD:
SAT Applicant locates 1-ISV-62-548, CVCS SEAL WTR INJ FLTR A IN ISOL UNSAT and demonstrates how to open the valve (rotating hand wheel in the counter clockwise direction.)
Cue:
After hand wheel is rotated CCW, state that the hand wheel turns several rotations and stops.
Step is critical to proper alignment of flow path.
COMMENTS:
PAGE6OF 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.k 2011-12 NRC_Exam STEPISTANDARD SAT/U NSAT STEP 4:
[4] SLOWLY OPEN 1-ISV-62-550, CVCS SEAL WTR INJ FILTER CRITICAL A OUT ISOL [A5T1713].
STEP STANDARD:
_Applicant locates 1-ISV-62-550, CVCS SEAL WTR INJ FILTER A OUT UNSAT ISOL and demonstrates how to open the valve (rotating hand wheel in the counter clockwise direction.).
Cue:
After hand wheel is rotated CCW, state that the hand wheel turns several rotations and stops.
Step is critical to proper alignment of flow path.
COMMENTS:
STEP 5: [5] ENSURE RCP seal injection flow between 8 and 13 gpm.
SAT STANDARD:
UNSAT Applicant contacts the Operator-at-the-Controls (OAC) and requests that RCP seal injection flows be checked between 8 and 13 gpm.
Cue:
After MCR called, state the seal flow is 9 gpm per pump.
COMMENTS:
PAGE 7 OF 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.k 2011-12 NRC_Exam STEP/STANDARD SAT/UNSAT STEP 6:
[6] CHECK LiP rose on A filter prior to isolating B filter.
SAT STANDARD:
UNSAT Applicant locates 1-PDIS-62-97, CVCS SEAL WTR INJECTION FILTER A DIFF PRESS and checks for a rise in pressure prior to isolating B filter.
Cue:
When 1-PDIS-62-97, CVCS SEAL WTR INJECTION FILTER A DIFF PRESS is checked indicate on gage a value of 6 psid COMMENTS:
STEP 7: [7] CLOSE 1-ISV-62-549, CVCS SEAL WTR INJ FILTER B OUT CRITICAL ISOL [A5T1713].
STEP STANDARD:
SAT Applicant locates 1-ISV-62-549, CVCS SEAL WTR INJ FILTER B OUT UNSAT ISOL and demonstrates how to close the valve (rotating hand wheel in the clockwise direction.)
Cue:
After hand wheel is rotated CW, state that the hand wheel turns several rotations and stops.
Step is critical to proper alignment of flow path.
COMMENTS:
PAGE 8 OF 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.k 2011-12 NRC Exam STEP/STANDARD SAT/UNSAT STEP 8: [8] CLOSE 1-ISV-62-547, CVCS SEAL WTR INJ FLTR B IN ISOL CRITICAL
[A5T/713].
STEP STANDARD:
_Applicant locates 1-ISV-62-547, CVCS SEAL WTR INJ FLTR B IN ISOL UNSAT and demonstrates how to close the valve (rotating hand wheel in the clockwise direction.)
Cue:
After hand wheel is rotated CW, state that the hand wheel turns several rotations and stops.
Step is critical to proper alignment of flow path.
COMMENTS:
STEP 9: [9] ENSURE 1-PDIS-62-97, CVCS SEAL WTR INJECTION SAT FILTER A DIFF PRESS [A5T1713], indicates IXP less than 20 psid.
UNSAT STANDARD:
Applicant locates 1-PDIS-62-97, CVCS SEAL WTR INJECTION FILTER A DIFF PRESS and Filter As APis checked to be <20 psid on 1-PDIS-62-96.
Cue:
AfterAP check, indicate value of 12 psid on the gage.
COMMENTS:
PAGE9OF 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.k 2011-12 NRC_Exam STEPISTANDARD SATIUNSAT STEP 10: [10] INITIATE SR to replace clogged filter, and NOTIFY UO to SAT record SR number. (N/A if open SR available for filter replacement)
UNSAT STANDARD:
Applicant indicates that a Service Request (SR) must be initiated, and that the Unit Operator must be informed of SR number.
Cue:
When notified, state that another operator will initiate the Service Request and inform the UO of the SR number.
Cue:
When notified, repeat back the information provided by the applicant.
COMMENTS:
END OF TASK STOP TIME PAGE 10 OF 11
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- 1. Unit I is at 90% power.
- 3. You are an AUO on shift.
INITIATING CUES:
I. The Unit Operator has directed you to swap seal injection filters per SOI-62.0I, CVCS-Charging and Letdown, Section 8.9.2, Replacing Filter B with Filter A.
- 2. You are to place A seal injection filter in service and remove B seal injection filter from service.
- 3. You are to notify the Unit Operator when the seal injection filter swap is complete.
B.1.k