ML15259A411
| ML15259A411 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 09/16/2015 |
| From: | Division of Reactor Safety II |
| To: | Tennessee Valley Authority |
| References | |
| Download: ML15259A411 (340) | |
Text
Watts Bar Nuclear Plant 2015301 NRC Exam System JPM A PAGE 1 OF 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A
2015-301 NRC Exam EVALUATION SHEET Task: RETRIEVE A DROPPED ROD Alternate Path: When Shutdown Bank D rod C-5 is withdrawn to greater than or equal to 32 steps, ALL other Shutdown Bank D rods will drop into the core.
Applicant will manually trip the reactor in accordance with 1-AOI-2, Malfunction of Reactor Control System, Section 3.3, Dropped RCCA, Step 1 RNO.
Facility JPM #: 3-OT-JPMR095C 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: 41.7 / 45.5 to 45.8 Evaluation Method: Simulator X In-Plant Classroom
References:
1-AOI-2, Malfunction of the Reactor Control System, Rev. 0002.
TI-12.04, Users Guide for Abnormal and Emergency Operating Instructions, Rev. 17.
Task Number: RO-085-AOI-2-004 Title: Respond to a dropped RCCA Task Standard: The applicant:
- 1) Performs actions of 1-AOI-2, Malfunction of Reactor Control System, Section 3.3, Dropped RCCA, to withdraw Shutdown Bank D rod C-5.
- 2) When Shutdown Bank D rod C-5 is withdrawn to greater than or equal to 32 steps diagnoses that additional Shutdown Bank D rods have dropped and performs IMMEDIATE ACTIONS by manually tripping the reactor.
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 OF 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A
2015-301 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:
- 1. ENSURE NRC Examination Security has been established.
- 2. RESET to Initial Condition 307 by performing the following actions:
- a. Select ICManager 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. ENSURE the following information appears on the Director Summary Screen:
Key Type Event Delay Inserted Ramp Initial Final Value rd13sdde13 shutdown bank d e13 after 4 to 0 on event 1 M 30 00:00:00 00:00:00 Active InActive rd13sddl3 shutdown bank d l3 after 5 to 0 on event 1 M 30 00:00:00 00:00:00 Active InActive rd13sddn11 shutdown bank d n11 after 4 to 0 on event 1 M 30 00:00:00 00:00:00 Active InActive
- 4. Ensure Auto Event Triggers is assigned to Event 1 as follows: Open standard trigger file. Right click on Event 30 trigger and select edit. The description should be Rod C5 > 35 steps. The Event Code should read, pc_rdac0032a>=35.
- 5. Place simulator in RUN and acknowledge any alarms.
- 6. ENSURE a marked-up copy of 1-AOI-2, Malfunction of Reactor Control System, Section 3.3, Dropped RCCA, signed (circled-and-slashed) through Step 16 is available for each applicant.
- 7. ENSURE Extra Operator is present in the simulator.
- 8. Place simulator in FREEZE until Examiner cue is given.
PAGE 3 OF 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A
2015-301 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 2 is conducting pre-operational testing.
- 2. Unit 1 was operating at 100% power when shutdown bank D rod C-5 dropped into the core due to a power cabinet card problem about 15 minutes ago.
- 3. 1-AOI-2, Malfunction of Reactor Control System, Section 3.3, Dropped RCCA, was entered and has been performed through Step 16.
- 4. Reactor power was reduced to approximately 50%.
- 5. The problem has been repaired.
- 6. 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%.
- 7. You are the Operator-at-the-Controls.
INITIATING CUES:
The Unit Supervisor directs you to realign C-5 rod starting at 1-AOI-2, Malfunction of Reactor Control System, Section 3.3, Dropped RCCA, Step 17.
Notify the Unit Supervisor when Shutdown Bank D, C-5 rod has been realigned.
PAGE 4 OF 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _______
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 MAN position to the SDD position to select shutdown bank D. ___ UNSAT Step is critical to assure proper bank is selected to be aligned.
COMMENTS:
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: ___ SAT
- 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 may record either:
Shutdown Bank Group Step Counter 1-SBDG1 - 228 steps OR ICS Step Indication for Shutdown Bank D C-5 0 steps E-13 228 steps N11 229 steps L03 229 steps Applicant determines that the Bank overlap counter is not applicable to Shutdown Bank D.
COMMENTS:
Page 5 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT STEP 3: 19. DISCONNECT all lift coils (toggle up) in affected bank, EXCEPT for CRITICAL dropped RCCA. STEP STANDARD: ___ SAT Applicant places toggle switches for rods E-13, N-11, & L-3 in the disconnect ___ UNSAT position (up position) in cabinet 1-XS-85-1.
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 CONTINUE until ___ SAT 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-SBDG1, SHUTDOWN BANK D1.
COMMENTS:
STEP 5: 21. SET affected step counter to 000. ___ SAT STANDARD: ___ UNSAT The applicant lifts the cover on 1-SBDG1, 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:
Page 6 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT STEP 6: 22. USE the Plant Computer to set affected banks position to zero: ___ SAT
- 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.
COMMENTS:
STEP 7: 23. DO NOT CONTINUE UNTIL the following agree on a retrieval rate: ___ SAT
- Unit SRO ___ UNSAT
- 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: This information is provided in the INITIAL CONDITIONS.
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.
COMMENTS:
Page 7 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT 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: ___ SAT
- () USING rod control in Bank Select, position affected RCCA to bank affected position recorded in Step 18
___ UNSAT
- () 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, all other rods in Shutdown Bank D will drop. The applicant will perform the IMMEDIATE ACTIONS of 1-AOI-2, Malfunction of Reactor Control System, Section 3.3, Dropped RCCA.
___ SAT 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:
Page 8 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT STEP 10: 1. PERFORM the following: CRITICAL STEP RESPONSE NOT OBTAINED:
___ SAT
- a. IF more than one rod dropped, THEN () TRIP reactor **GO TO 1-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 1-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 applicant begins to perform to 1-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 9 of 11
A Handout Package for Applicant A
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- 1. Unit 2 is conducting pre-operational testing.
- 2. Unit 1 was operating at 100% power when shutdown bank D rod C-5 dropped into the core due to a power cabinet card problem about 15 minutes ago.
- 3. 1-AOI-2, Malfunction of Reactor Control System, Section 3.3, Dropped RCCA, was entered and has been performed through Step 16.
- 4. Reactor power was reduced to approximately 50%.
- 5. The problem has been repaired.
- 6. 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%.
- 7. You are the Operator-at-the-Controls.
INITIATING CUES:
The Unit Supervisor directs you to realign C-5 rod starting at 1-AOI-2, Malfunction of Reactor Control System, Section 3.3, Dropped RCCA, Step 17.
Notify the Unit Supervisor when Shutdown Bank D, C-5 rod has been realigned.
A
Watts Bar Nuclear Plant NRC EXAM 2015301 System JPM B
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
NRC EXAM 2015-301 EVALUATION SHEET Task: Fill Cold Leg Accumulator (CLA) #1.
Alternate Path: n/a Facility JPM #: 3-OT-JPMR027 Safety Function: 2 Title: Reactor Coolant System Inventory Control K/A 006 A4.07 Ability to manually operate and/or monitor in the control room: ECCS pumps and valves Rating(s): 4.4/4.4 CFR: 41.7 / 45.5 to 45.8 Evaluation Method: Simulator X In-Plant Classroom
References:
1-SOI-63.01, Safety Injection System, Rev 0004.
Task Number: RO-063-SOI-63-001 Title: Add water to cold leg accumulators while in service Task Standard: Applicant adds water to cold leg accumulator (CLA) #1using 1A-A Safety Injection pump, in accordance with 1-SOI-63.01, Safety Injection System, Section 8.3.1, Add Water to CLA 1, until 131-A, CL ACCUM 1 LEVEL HI/LO is DARK.
Validation Time: 15 minutes Time Critical: Yes No X
===============================================================
Applicant: ___________________________ _________________ Time Start: ________
NAME Docket No. Time Finish: ________
Performance Rating: SAT ____ UNSAT ____ Performance Time ___
Examiner: _____________________________ _____________________________/________
NAME SIGNATURE DATE
===============================================================
COMMENTS PAGE 1 OF 19
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
NRC EXAM 2015-301 SIMULATOR OPERATOR INSTRUCTIONS:
- 1. ENSURE NRC Examination Security has been established.
- 2. RESET to Initial Condition 308 by performing the following actions:
- a. Select ICManager on the THUNDERBAR menu (right hand side of Instructor Console Screen).
- b. Locate IC# 308.
- c. Right click on IC# 308.
- d. Select Reset on the drop down menu.
- e. Right click on RESET.
- f. Enter the password for IC# 308.
- g. Select Yes on the INITIAL CONDITION RESET pop-up window.
- h. Perform SWITCH CHECK.
- 4. ENSURE the following annunciator windows are LIT:
- a. 134-A, CL ACCUM 3 LEVEL HI/LO
- b. 134-B CL ACCUM 3 PRESS HI/LO
- 5. Place simulator in RUN and acknowledge any alarms.
- 6. ENSURE copies of SOI-63.01, Section 8.3.1 are available for the Examiner.
- 7. ENSURE Extra Operator is present in the simulator.
- 8. Place simulator in FREEZE until Examiner cue is given.
PAGE 2 OF 19
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
NRC EXAM 2015-301 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 2 is conducting pre-operational tests.
- 2. Unit 1 RCS pressure is approximately 1400 psig and Tavg approximately 500ºF.
- 3. Annunciator windows 131-A, CL ACCUM 1 LEVEL HI/LO and 131-B, CL ACCUM PRESS HI/LO are LIT.
- 4. The Unit Supervisor is evaluating Technical Specifications.
- 5. 1-SOI-63.01, Safety Injection System, Section 5.1, Fill & Vent SI Pumps and Piping from RWST is complete.
- 6. You are an extra operator assigned to the shift.
INITIATING CUES:
The Unit Supervisor directs you to fill Cold Leg Accumulator (CLA) 1 using 1-SOI-63.01, Safety Injection System, Section 8.3.1, Add Water to CLA 1, using the 1A-A Safety Injection pump.
Inform the Unit Supervisor when CLA 1 has been filled, Windows 131-A, CL ACCUM 1 LEVEL HI/LO and 131-B, CL ACCUM 1 PRESS HI/LO annunciators have cleared, and Section 8.3.1 is complete.
PAGE 3 OF 19
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT START TIME: _______
CAUTION Adding water to more than one CLA at a time while they are required to be operable places the plant outside design basis. This section is to be used to add water to any selected single CLA. If more than one CLA needs water, separate evolutions must be performed.
STEP 1: [1] ENSURE Sect 5.1, to Fill & Vent SI Pmps and Piping, ___ SAT COMPLETE:
___ UNSAT STANDARD:
Applicant determines from INITIATING CUES that Section 5.1 is complete COMMENTS:
STEP 2: [2] IF RCS pressure is 1000 psig, THEN ENSURE ___ SAT 1-FCV-63-118, CL ACCUM 1 OUTLET, CLOSED.
___ UNSAT STANDARD:
Applicant determines that RCS pressure is greater than 1000 psig, at approximately 1400 psig.
Applicant determines that this step in not applicable and marks it N/A.
COMMENTS:
CAUTION If RCS is 1650 psig or less, ALL SIP flow paths must be disabled to prevent inadvertent RCS injection. If 1-FCV-63-152 is closed, then SI Pmp A is the only pump that can be used to fill CLA.
Page 4 of 19
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT STEP 3: [3] IF RCS 1650 psig or less, AND SIP A is to be used to CRITICAL fill CLA 1, THEN CLOSE 1-FCV-63-152, SI PMP A TO STEP CL 1-2-3-4 [1- M-6].
___ SAT STANDARD:
Applicant determines the RCS pressure IS less than 1650 psig ___ UNSAT (approximately 1400 psig) and that 1-FCV-63-152, SI PMP A TO CL 1-2-3-4 must be closed (Critical).
Applicant rotates handswitch 1-HS-63-152 to the left to the CLOSE position (Critical).
Applicant determines that the valve is CLOSED by observing the RED light is DARK and GREEN light is LIT.
Indicated steps are critical to prevent injection of water into the RCS from the safety injection pump.
COMMENTS:
CAUTION In Mode 4, 5, 6 with the Rx Vessel Head ON, before starting SI Pmp A, 1-FCV-63-152 and 156 must be closed, with Hold tags on the handwheels and breakers (Refer to T.S.
3.4.12).
STEP 4: [4] IF in Mode 4, 5, or 6 and SIP A is to be used with Rx Vessel ___ SAT Head ON, THEN....
STANDARD: ___ UNSAT Applicant determines from the IINITIAL CONDITIONS that the Unit is in Mode 3 so Step 4 and its sub steps are not applicable. The applicant marks step 4 N/A.
COMMENTS:
CAUTION 1-FCV-63-22, 156, 157 MUST be closed with Hold Tags on handwheels and bkrs in Modes 4, 5, 6 with vessel head on when running SIP B. (See T.S. 3.4.12).
Page 5 of 19
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT STEP 5: [5] IF in Mode 4, 5, or 6 and SIP B is to be used with Rx Vessel
___ SAT Head ON THEN: ...
STANDARD: ___ UNSAT Applicant determines from the INITIAL CONDITIONS that the 1A Safety Injection pump will be used to fill the accumulator so Step 5 and its sub steps are not applicable. The applicant marks step 5 N/A.
COMMENTS:
Page 6 of 19
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT STEP 6: [6] PERFORM the following: CRITICAL STEP
___ SAT
___ UNSAT STANDARD:
Applicant depresses pushbutton 1-HS-63-187 on the CKV LEAK TEST panel (Critical).
Applicant verifies GREEN light for 1-HS-63-187 is DARK and RED light for 1-HS-30-187 is LIT.
Applicant rotates handswitch 1-HS-63-71A to the right to the OPEN position (Critical).
Applicant verifies GREEN light for 1-HS-63-71A is DARK and the RED light for 1-HS-63-71A is LIT.
Applicant rotates handswitch 1-HS-63-23A to the right to the OPEN position (Critical).
Applicant verifies GREEN light for 1-HS-63-23A is DARK and the RED light for 1-HS-63-71A is LIT.
Indicated steps are critical to establish a flowpath to the accumulator to be filled.
COMMENTS:
Page 7 of 19
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT CAUTION If 1-FCV-63-152 was closed in step 8.3.4[3], then SI Pmp A is the only pump that can be used to fill CLA.
STEP 7: [7] ENSURE the following (N/A pump NOT selected): ___ SAT
___ UNSAT STANDARD:
Applicant determines 1-HS-63-3 is OPEN by observing GREEN light for 1-HS-63-3 is DARK and RED light for 1-HS-63-3 is LIT.
Applicant determines 1-HS-63-4 is OPEN by observing GREEN light for 1-HS-63-4 is DARK and RED light for 1-HS-63-4 is LIT.
Applicant enters N/A for 1-FCV-63-175, since 1A SI pump will be used for filling the #1 CLA.
Applicant determines 1-HS-63-5 is OPEN by observing GREEN light for 1-HS-63-5 is DARK and RED light for 1-HS-63-5 is LIT.
Applicant determines 1-HS-63-47 is OPEN by observing GREEN light for 1-HS-63-47 is DARK and RED light for 1-HS-63-47 is LIT.
Applicant enters N/A for 1-FCV-63-48, since 1A SI pump will be used for filling the #1 CLA.
COMMENTS:
Page 8 of 19
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT STEP 8: [8] PERFORM the following (N/A pump NOT selected): CRITICAL STEP PERF NOMENCLATURE LOC POSITION UNID INITIAL ___ SAT 1-M-6 START 1-HS-63-10A
Applicant rotates handswitch 1-HS-63-10A to the right to the START position (Critical).
Applicant verifies GREEN lights for 1-HS-63-10A is DARK and the RED light for 1-HS-63-10A is LIT.
Applicant observes amps for the 1A SI Pump on 1-EI-63-12A, rising.
Applicant observes discharge pressure for the 1A SI Pump on 1-PI 150, rising.
Applicant enters N/A for 1-HS-63-15A, SI PMP B (ECCS).
Step is critical since the 1A SI pump provides flow from the RWST to fill CLA 1.
COMMENTS:
Page 9 of 19
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT STEP 9: CHECK the started pumps closing spring charged (N/A pump ___ SAT NOT started):
___ UNSAT STANDARD:
Applicant contacts an AUO to determine status of 1A-A SI Pump breaker closing spring.
CUE: When applicant contacts an AUO, repeat back the request to check the closing springs charged for 1A-A SI Pump breaker.
Report the closing spring is charged for 1-BKR-63-10.
COMMENTS:
STEP 10: [10] OPEN 1-FCV-63-115, MAKEUP TO CL ACCUM 1, [1-M-6]. CRITICAL STANDARD: STEP Applicant rotates handswitch 1-HS-63-115A to the right to the OPEN ___ SAT position (Critical).
Applicant verifies GREEN light for 1-HS-63-115A is DARK and the RED ___ UNSAT light for 1-HS-63-70A is LIT.
Step is critical since opening 1-FCV-63-115 completes the flow path for filling CLA 1.
COMMENTS:
CAUTION Due to physical location of upper tap, indication on 1-LI-63-89 greater than 8,030 gal should be considered Off scale High.
Page 10 of 19
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT EXAMINER: The INITIATING CUES direct the applicant to fill CLA 1 until BOTH 131-A, CL ACCUM 1 LEVEL HI/LO and 131-B, CL ACCUM 1 PRESS HI/LO annunciators are clear.
STEP 11: [11] WHEN CLA is at desired level (Alarm 131-A, CL ACCUM 1 CRITICAL LEVEL HI/LO, NOT LIT), THEN PERFORM the following: STEP PERF VERIF NOMENCLATURE LOC POSITION UNID INITIAL INITIAL ___ SAT 1-M-6 CLOSED 1-FCV-63-115
- MAKEUP TO CL ___ UNSAT ACCUM 1 CKV TEST LINE TO 1-M-6 CLOSED 1-FCV-63-71 HUT TEST LINE 1-M-6 CLOSED 1-FCV-63-187 (1-XS063-100) ISOL CLA FILL FROM SI 1-M-6 CLOSED 1-FCV-63-23 PMPS STANDARD:
When accumulator level has increased to the point where Alarm 131-A is clear (greater than 7660 gallons) and Alarm 131-B (greater than 610 psig) then Applicant rotates handswitch 1-HS-63-115A to the left to the CLOSED position (Critical).
Applicant verifies GREEN lights for 1-HS-63-115A is LIT and the RED light for 1-HS-63-71A is DARK.
Applicant rotates handswitch 1-HS-63-71A to the left to the CLOSED position.
Applicant verifies GREEN light for 1-HS-63-71A is LIT and the RED light for 1-HS-63-71A is DARK.
Applicant depresses pushbutton 1-HS-63-187 on the CKV LEAK TEST panel.
Applicant verifies GREEN light for 1-HS-63-187 is LIT and RED light for 1-HS-30-187 is DARK.
Applicant rotates handswitch 1-HS-63-23A to the left to the CLOSED position.
Applicant verifies GREEN light for 1-HS-63-23A is LIT and the RED light for 1-HS-63-23A is DARK.
Step is critical since action will terminate flow to CLA 1 accumulator, preventing possible overfill of CLA 1.
COMMENTS:
Page 11 of 19
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT EXAMINER: The next step requires TIME COMPRESSION to allow for shutting down the 1A-A SI Pump.
STEP 12: [12] ENSURE SI pump has operated for greater than 20 CRITICAL minutes, THEN PERFORM the following (N/A pump NOT STEP selected):
___ SAT PERF NOMENCLATURE LOC POSITION UNID INITIAL
___ UNSAT 1-M-6 STOP 1-HS-63-10A
SI PMP B (ECCS) 1-M-6 STOP 1-HS-63-15A STANDARD:
Applicant rotates handswitch 1-HS-63-10A to the left to the STOP position (Critical).
Applicant verifies GREEN light for 1-HS-63-10A is LIT and the RED light for 1-HS-63-10A is DARK.
Applicant enters N/A for 1-HS-63-15A, SI PMP B (ECCS).
Step is critical to returning the safety injection system to standby configuration.
CUE: After applicant addresses the requirement to run the safety injection pump for 20 minutes, inform the applicant that 20 minutes have elapsed.
COMMENTS:
Page 12 of 19
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT NOTE Step 8.3.1[13] or 8.3.1[14] may be N/Ad based on SIPs operability requirements.
STEP 13: [13] ENSURE the following (N/A pump not selected):
___ SAT PERF VERIF NOMENCLATURE LOC POSITION UNID INITIAL INITIAL ___ UNSAT SI PMP A (ECCS) 1-M-6 A-AUTO 1-HS-63-10A SI PMP B (ECCS) 1-M-6 A-AUTO 1-HS-63-15A STANDARD:
Applicant observes handswitch 1-HS-63-10A, SI PMP A (ECCS) in the A-AUTO position (mid position on handswitch).
Applicant observes handswitch 1-HS-63-15A, SI PMP B (ECCS) in the A-AUTO position (mid position on handswitch).
COMMENTS:
Page 13 of 19
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT EXAMINER: In Step [14] neither SI pump should be placed in STOP, PULL-TO-LOCK, since both are required to be OPERABLE.
If the applicant places either of the SI pumps in STOP, PULL-TO-LOCK, this would constitute failure criteria.
STEP 14: [14] ENSURE the following (N/A pump not selected): ___ SAT PERF VERIF INITIAL INITIAL ___ UNSAT NOMENCLATURE LOC POSITION UNID SI PMP A (ECCS) 1-M-6 PULL-TO- 1-HS-63-10A LOCK SI PMP B (ECCS) 1-M-6 PULL-TO- 1-HS-63-15A LOCK STANDARD:
Applicant enters N/A for Step 14, since both of the safety injection pumps are required to be in the A-AUTO position to support ECCS standby alignment.
COMMENTS:
Page 14 of 19
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT STEP 15: [15] CHECK the shutdown pumps closing spring charged (N/A ___ SAT pump NOT shutdown):
___ UNSAT STANDARD:
Applicant contacts an AUO to determine status of 1A-A SI Pump breaker closing spring.
CUE: When applicant contacts an AUO, repeat back the request to check the closing springs charged for 1A-A SI Pump breaker.
Report the closing spring is charged for 1-BKR-63-10.
COMMENTS:
STEP 16: [16] IF 1-FCV-63-152, was closed in Step 8.3.1[3], THEN OPEN CRITICAL 1-FCV-63-152, SI PMP A TO CL 1-2-3-4 [1-M-6] (N/A in STEP Mode 4, 5, 6).
___ SAT STANDARD:
Applicant determines that 1-FCV-63-152, SI PMP A TO CL 1-2-3-4 ___ UNSAT WAS closed, and rotates handswitch 1-HS-63-152 to the right to the OPEN position (Critical).
Applicant determines that the valve is OPEN by observing the RED light is LIT and GREEN light is DARK.
Indicated step is critical to ensure the system is returned to the proper alignment.
COMMENTS:
Page 15 of 19
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B
NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT NOTE CLA 4 press can be read on 1-PI-63-61 or 62.
STEP 17: [16] VERIFY CLA PRESS in desired range (Alarm 131-B, CL ___ SAT ACCUM 1 PRESS HI/LO, NOT LIT).
STANDARD: ___ UNSAT Applicant determines that cold leg accumulator pressure is in the desired range (alarm 134-B DARK).
COMMENTS:
STEP 18: Applicant reports that Cold Leg Accumulator 1 has been filled. ___ SAT STANDARD:
Applicant informs the Unit Supervisor that Cold Leg Accumulator 1 has ___ UNSAT been filled.
CUE: Repeat back the information provided by the applicant.
COMMENTS:
END OF TASK STOP TIME ________
Page 16 of 19
B Handout Package for Applicant
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- 1. Unit 2 is conducting pre-operational tests.
- 2. Unit 1 RCS pressure is approximately 1400 psig and Tavg approximately 500ºF.
- 3. Annunciator windows 131-A, CL ACCUM 1 LEVEL HI/LO and 131-B, CL ACCUM PRESS HI/LO are LIT.
- 4. The Unit Supervisor is evaluating Technical Specifications.
- 5. 1-SOI-63.01, Safety Injection System, Section 5.1, Fill & Vent SI Pumps and Piping from RWST is complete.
- 6. You are an extra operator assigned to the shift.
INITIATING CUES:
The Unit Supervisor directs you to fill Cold Leg Accumulator (CLA) 1 using 1-SOI-63.01, Safety Injection System, Section 8.3.1, Add Water to CLA 1, using the 1A-A Safety Injection pump.
Inform the Unit Supervisor when CLA 1 has been filled, Windows 131-A, CL ACCUM 1 LEVEL HI/LO and 131-B, CL ACCUM 1 PRESS HI/LO annunciators have cleared, and Section 8.3.1 is complete.
B
Watts Bar Nuclear Plant 2015301 NRC Exam System JPM C
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C
2015-301 NRC Exam EVALUATION SHEET Task: Isolate Cold Leg Accumulators per 1-E-1, Loss of Reactor or Secondary Coolant.
Alternate Path: Due to the failure of RX MOV BD 1B1-B, Cold Leg Accumulators 2 and 4 cannot be isolated from 1-M-6 panel and must be vented to comply with 1-E-1, Step 24.
Facility JPM #: 2009-05 NRC Exam Safety Function: 3 Title: Reactor Pressure Control K/A 011 EA1.09 Ability to operate and monitor the following as they apply to a Large Break LOCA: Core flood tank initiation Rating(s): 4.3/4.3 CFR: 41.7 / 45.5 / 45.6 Evaluation Method: Simulator X In-Plant Classroom
References:
1-E-1, Loss of Reactor or Secondary Coolant, Rev. 4.
Task Number: RO-063-SOI-63-003 Title: Vent nitrogen from the cold leg accumulators.
Task Standard: The applicant:
1.) Isolates Cold Leg Accumulators 1 and 3 per 1-E-1, Step 24 AER 2.) Vents Cold Leg Accumulators 2 and 4 per 1-E-1, Step 24 RNO 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 of 12
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C
2015-301 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:
- 1. ENSURE NRC Examination Security has been established.
- 2. RESET to Initial Condition 309 by performing the following actions:
- a. Select ICManager on the THUNDERBAR menu (right hand side of Instructor Console Screen).
- b. Locate IC 309.
- c. Right click on IC 309.
- d. Select Reset on the drop down menu.
- e. Right click on RESET.
- f. Enter the password for IC 309.
- g. Select Yes on the INITIAL CONDITION RESET pop-up window.
- h. Perform SWITCH CHECK.
- 3. ENSURE the following information appears on the Director Summary Screen:
Key Type Event Delay Inserted Ramp Initial Final Value th02a loca small leak loop 1 M 00:00:00 00:00:00 00:00:00 80 80 sir01 pwr to cold leg accumu isolation valves fcv-63-67, 80, 98, 119 R 00:00:00 00:00:00 00:00:00 On On ed18c loss of 480 reac mov-bd-b1 M 00:00:00 00:00:00 00:00:00 Active Active
- 6. Place simulator in RUN and acknowledge any alarms.
- 7. ENSURE a marked-up copy of 1-E-1, Loss of Reactor or Secondary Coolant, signed (circled-and-slashed) to Step 24.
- 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 C
2015-301 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 2 is conducting pre-operational testing.
- 2. A large break LOCA has occurred on Unit 1.
- 4. 1-E-1, Loss of Reactor or Secondary Coolant performance has just been resumed after performance of 1-ES-1.3, Transfer to Containment Sump.
- 5. Appendix A (1-E-1), CLA Breaker Operation is complete.
- 6. You are the Control Room Operator.
INITIATING CUES:
The Unit Supervisor directs you to perform Step 24 of 1-E-1, Loss of Reactor or Secondary Coolant.
Inform the Unit Supervisor when Step 24 has been completed.
Page 4 of 12
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _______
STEP 1: 24. DETERMINE if cold leg accumulators should be isolated: ___ SAT
- a. ENSURE power to isolation valves restored USING Appendix A (1-E-1), CLA Breaker Operation. ___ UNSAT STANDARD:
Applicant determines from the INITIAL CONDITIONS that power has been restored to the isolation valves.
COMMENTS:
STEP 2: 24. DETERMINE if cold leg accumulators should be isolated: ___ SAT
- b. CHECK RCS pressure less than 250 psig.
___ UNSAT STANDARD:
Applicant reads RCS pressure from ONE of the following PAM instruments and determines that pressure is less than 1 psig.
RVLIS-ICCM PLASMA DISPLAY on 1-M-4 or 1-M-6 Loop 4 HL PRESS 1-PI-68-70 Loop 3 HL PRESS 1-PI-68-64 Loop 2 HL Press 1-PI-68-63 COMMENTS:
Page 5 of 12
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT EXAMINER: In the subsequent step, the applicant will identify that 1-FCV-63-118A, CL ACCUM 1 OUTLET and 1-FCV-63-80A, CL ACCUM 3 OUTLET can be isolated normally.
The applicant will also determine that RNO actions are required for 1-FCV-63-98, CL ACCUM 2 OUTLET and 1-FCV-63-67, CL ACCUM 4 OUTLET.
STEP 3: 24. DETERMINE if cold leg accumulators should be isolated: CRITICAL
- c. CLOSE cold leg accumulator isolation valves. STEP STANDARD: ___ SAT Applicant locates 1-HS-63-118A and rotates the handswitch to the left to CLOSE (Critical). ___ UNSAT Applicant observes RED light is DARK and GREEN light is LIT.
Locates 1-HS-63-80A and rotates the handswitch to the left to CLOSE (Critical).
Applicant observes RED light is DARK and GREEN light is LIT.
Step is critical to minimize the chance of nitrogen injection into the RCS.
COMMENTS:
Page 6 of 12
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT STEP 4: 24. DETERMINE if cold leg accumulators should be isolated: CRITICAL
- c. RESPONSE NOT OBTAINED: STEP PERFORM the following: ___ SAT
- 1) RESET Phase B.
___ UNSAT STANDARD:
Applicant observes that the RED ØB light is LIT on 1-XX-55-6C, MASTER ISOLATION SIGNAL STATUS PANEL.
Applicant depresses 1-HS-30-64D and observes the Train A Phase B light is DARK on 1-XX-55-6C, MASTER ISOLATION SIGNAL STATUS PANEL (Critical).
Applicant observes that the RED ØB light is LIT on 1-XX-55-6D, MASTER ISOLATION SIGNAL STATUS PANEL.
Applicant depresses 1-HS-30-64E and observes the Train B Phase B light is DARK on 1-XX-55-6D, MASTER ISOLATION SIGNAL STATUS PANEL (Critical).
Step is critical to allow opening of the air supply valve required to position the associated accumulator vent valves.
COMMENTS:
Page 7 of 12
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT STEP 5: 24. DETERMINE if cold leg accumulators should be isolated: CRITICAL
- c. RESPONSE NOT OBTAINED: STEP
___ SAT PERFORM the following:
- 2) ENSURE aux air pressure to cntmt is greater than 75 ___ UNSAT psig [M-15] AND OPEN cntmt air supply valves
- 1-FCV-32-80.
- 1-FCV-32-102.
- 1-FCV-32-110.
STANDARD:
Applicant opens 1-FCV-32-80 by rotating and holding 1-HS-30-80A, AUX AIR TO RX BLDG TR A CIV-ØB/70 PSI D/S CLOSES to the right, until the RED light is LIT and GREEN light is DARK (Critical).
Applicant opens 1-FCV-32-102 rotating and holding 1-HS-30-102A, AUX AIR TO RX BLDG TR B CIV-ØB/70 PSI D/S CLOSES to the right, until the RED light is LIT and GREEN light is DARK (Critical).
Applicant opens 1-FCV-32-110 rotating and holding 1-HS-30-110A, NON-ESS AUX AIR TO RX BLDG CIV-ØB/70 PSI D/S CLOSES to the right, until the RED light is LIT and GREEN light is DARK (Critical).
Step is critical to provide air to position the accumulator makeup valves used to vent nitrogen from accumulators 2 and 4.
COMMENTS:
Page 8 of 12
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT STEP 6: 24. DETERMINE if cold leg accumulators should be isolated: CRITICAL
- c. RESPONSE NOT OBTAINED: STEP PERFORM the following: ___ SAT
- 3) OPEN any unisolated accumulator nitrogen makeup valve: ___ UNSAT
- 1-FCV-63-127 accumulator 1.
- 1-FCV-63-107 accumulator 2.
- 1-FCV-63-87 accumulator 3.
- 1-FCV-63-63 accumulator 4.
STANDARD:
Applicant determines that 1-FCV-63-107 for CLA 2 must be OPENED.
Applicant locates 1-HS-63-107A N2 TO CL ACCUM 2 and rotates the handswitch to OPEN position (Critical).
Applicant verifies RED light is LIT and GREEN light is DARK Applicant determines that 1-FCV-63-63 for CLA 4 must be OPENED.
Applicant locates 1-HS-63-63A N2 TO CL ACCUM 4 and rotates the handswitch to OPEN position (Critical).
Applicant verifies RED light is LIT and GREEN light is DARK.
Step is critical since this action is taken to minimize the chance of nitrogen injection into the RCS.
COMMENTS:
Page 9 of 12
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT STEP 7: 24. DETERMINE if cold leg accumulators should be isolated: CRITICAL
- c. RESPONSE NOT OBTAINED: STEP PERFORM the following: ___ SAT
- 4) OPEN 1-FCV-63-65 vent header.
___ UNSAT STANDARD:
Applicant locates 1-HIC-63-65A and depresses the RAMP and [>>]
(raise) buttons until the demand indicates 100% (Critical).
Step is critical since this action is taken to minimize the chance of nitrogen injection into the RCS.
COMMENTS:
STEP 8: Notify the Unit Supervisor that 1-E-1, Step 24 is complete.
___ SAT STANDARD:
Applicant notifies the Unit Supervisor that Step 24 is complete. ___ UNSAT CUE: Repeat back information provided by the applicant.
COMMENTS:
END OF TASK STOP TIME ________
Page 10 of 12
C Handout Package for Applicant C
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- 1. Unit 2 is conducting pre-operational testing.
- 2. A large break LOCA has occurred on Unit 1.
- 4. 1-E-1, Loss of Reactor or Secondary Coolant performance has just been resumed after performance of 1-ES-1.3, Transfer to Containment Sump.
- 5. Appendix A (1-E-1), CLA Breaker Operation is complete.
- 6. You are the Control Room Operator.
INITIATING CUES:
The Unit Supervisor directs you to perform Step 24 of 1-E-1, Loss of Reactor or Secondary Coolant.
Inform the Unit Supervisor when Step 24 has been completed.
C
Watts Bar Nuclear Plant NRC EXAM 2015301 System JPM D
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D
NRC EXAM 2015-301 EVALUATION SHEET Task: Start Reactor Coolant Pump #2.
Alternate Path: After #2 RCP Oil Lift Pump is stopped per SOI-68.02, motor amps will rise above the RED line, requiring the RCP to be stopped.
Facility JPM #: Modified 3-OT-JPMR028A Safety Function: 4P Title: Heat Removal From Reactor Core K/A 003 A4.02 Ability to manually operate and/or monitor in the control room: RCP motor parameters Rating(s): 2.9/2.9 CFR: 41.5 / 45.5 to 45.8 Evaluation Method: Simulator X In-Plant Classroom
References:
SOI-68.02, Reactor Coolant Pumps, Rev. 35.
0-GOI-7, Generic Equipment Operating Guidelines, Rev. 2.
Task Number: RO-068-SOI-68-007 Title: Start a Reactor Coolant Pump.
Task Standard:
The applicant :
1.) Performs actions of SOI-68.02, Reactor Coolant Pumps, to start RCP #2.
2,) After oil lift pump is stopped, evaluates #2 RCP motor amps, determines that amps are not returning to below RED line and stops RCP #2.
Validation Time: 15 minutes Time Critical: Yes No X
============================================================
Applicant: ___________________________ _________________ Time Start: ________
NAME Docket No. Time Finish: ________
Performance Rating: SAT ____ UNSAT ____ Performance Time ___
Examiner: _____________________________ _____________________________/________
NAME SIGNATURE DATE
==============================================================
COMMENTS PAGE 1 OF 16
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D
NRC EXAM 2015-301 SIMULATOR OPERATOR INSTRUCTIONS:
- 1. ENSURE NRC Examination Security has been established.
- 2. RESET to Initial 310 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. ENSURE the following information appears on the Director Summary Screen:
Key Type Event Delay Inserted Ramp Initial Final Value rc10b rcp 2 bearing wear M 30 00:00:00 00:00:05 19 0
- 4. ENSURE Event 30 is loaded. Event 30 is activated when the applicant places 1-HS-68-31AA RCP 2 NORMAL BKR & LIFT PUMP in the STOP position, after placing 1-HS-68-31BA, RCP 2 ALTERNATE BKR & XFER SELECTOR in the START position.
- 5. Place simulator in RUN and acknowledge any alarms.
- 6. ENSURE at least 8 gpm flow indicated on 1-FI-62-14A, RCP 2 SEAL SUP FLOW.
- 7. ENSURE a marked-up copy of SOI-68.02, Reactor Coolant Pumps, signed off (circled-and-slashed) to Step 6 is available for each applicant
- 8. Place simulator in FREEZE until Examiner cue is given.
- 9. ENSURE Extra Operator is available on Simulator.
PAGE 2 OF 16
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D
NRC EXAM 2015-301 SIMULATOR CONTINGENCY ACTIONS:
IF INITIAL CONDITION 311 is unavailable for any reason, the following actions must be taken to reconstruct the IC.
- 1. Reset to IC 49.
- 2. Trip the reactor, acknowledge alarms. Clear the manual trip first out alarm.
- 3. Stop RCP #2. Place 1-HS-68-31AA and 1-HS-68-31BA to the PUSHED IN position.
- 4. Reconstruct Event 30. Open EVENTS, select slot 30 and right click. Select EDIT. Enter the following in the EVENT CODE block zlohs6831ba(3) == 1 & zlohs6831aa(4) == 1. This code should validate to FALSE. Select OK.
PAGE 3 OF 16
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D
NRC EXAM 2015-301 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 2 is conducting pre-operational tests.
- 2. Unit 1 is in Mode 3.
- 3. #2 RCP 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.
- 4. Maintenance reported the repairs have been completed.
- 6. SOI-68.02, Reactor Coolant Pumps, Section 5.0, Startup, has been completed through Step 7.
- 7. Section 4.2 Field Preparations are complete.
INITIATING CUES:
The Unit Supervisor has directed you to start #2 RCP using SOI-68.02, Reactor Coolant Pumps, Section 5.0, Startup, beginning at Step 8.
Inform the Unit Supervisor when Section 5.0 is complete.
PAGE 4 OF 16
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D
NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT START TIME: _______
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.
EXAMINERS NOTE: Alarm Window 99-B, RCP OIL LIFT PRESS LO will alarm, candidate may reference ARI-95-101, which will identify this condition as a cause and exit the ARI.
STEP 1: [8] START applicable Oil Lift Pump: CRITICAL TASK
___ SAT
___ UNSAT STANDARD:
Applicant pulls out handswitch 1-HS-68-31AA RCP 2 NORMAL BKR&LIFT PUMP and rotates the handswitch to the START position.(Critical)
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:
Page 5 of 16
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D
NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT STEP 2: [9] VERIFY #1 seal P greater than 200 psid [1-M-5]. ___ SAT STANDARD:
___ UNSAT Applicant locates 1-PDI-62-21A, RCP 2 #1 SEAL P on panel 1-M-5 and observes that the indicator is off-scale high, indicating greater than 400 psid.
COMMENTS:
STEP 3: [10] VERIFY 8 to 13 gpm to RCP seal [1-M-5]. ___ SAT STANDARD:
___ UNSAT Applicant locates 1-FI-62-14A, RCP 2 SEAL SUP FLOW and observes flow at 8 approximately gpm.
COMMENTS:
STEP 4: [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 25 psig).
COMMENTS:
Page 6 of 16
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D
NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT STEP 5: [12] VERIFY #1 seal leakoff greater than 0.2 gpm, or within ___ SAT Normal Operating Range for existing #1 Seal P (see Appendix B). ___ UNSAT STANDARD:
Applicant locates 1-FR-62-23, SEAL LEAKOFF - LO RANGE - GPM 3&4 on panel 1-M-5 and observes that the BLUE 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 BLUE indicator is at approximately 2.7 gpm.
COMMENTS:
STEP 6: [13] IF leakoff flow is NOT established, THEN GO TO Section 8.0. ___ SAT STANDARD:
___ UNSAT Applicant determines that leakoff flow is established and marks the step as N/A.
COMMENTS:
STEP 7: [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:
Page 7 of 16
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D
NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT NOTE Step 5.0[15] prevents excessive Rod motion upon starting RCP.
STEP 8: [15] IF restarting RCP with Control Rods withdrawn, THEN ___ SAT ENSURE Rod Bank Select in MANUAL.
___ UNSAT STANDARD:
Applicant locates CERPI MONITOR 1 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.
COMMENTS:
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 9: [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:
Page 8 of 16
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D
NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT STEP 11: [17] ENSURE Aux OC Bkr, CLOSED. ___ SAT STANDARD:
___ UNSAT Applicant determines that the RED indicating light for RCP 2 Aux Overcurrent Protection ACB is LIT (light is located above 1-HS 31BA, RCP 2 ALTERNATE BKR & XFRE SELECTOR.)
COMMENTS:
STEP 12: [18] IF starting RCP 1, THEN ENSURE Pzr spray, 1-PCV ___ SAT 340D, is CLOSED.
___ UNSAT STANDARD:
Applicant marks the step as N/A since RCP 2 is being started.
COMMENTS:
STEP 13: [19] IF starting RCP 2, THEN ENSURE Pzr spray, 1-PCV CRITICAL 340B, is CLOSED. TASK STANDARD:
___ SAT Applicant observes 1-XI-68-340B RED light is LIT, indicating that 1-PCV-68-340B is OPEN. ___ UNSAT Applicant locates 1-HIC-68-340B, LOOP 2 SPRAY CONTROL, then depresses the AUTO/MAN pushbutton to take manual control Applicant depresses the [<<] button and RAMP pushbuttons to close 1-PCV-68-340B. Applicant confirms valve closed by 1-XI-68-340B GREEN indicating light LIT Step is critical to limit the potential for an RCS pressure transient during pump startup.
COMMENTS:
Page 9 of 16
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D
NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT STEP 14: [20] ANNOUNCE RCP start on PA system. ___ SAT STANDARD:
___ UNSAT CUE: When the applicant addresses the PA announcement, state another operator will handle the PA announcement.
COMMENTS:
Page 10 of 16
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D
NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT NOTE Below 15% power with station service NOT transferred, the Alternate handswitch is used to start RCP.
STEP 15: [21] START selected RCP (N/A HSs NOT used): CRITICAL STEP
___ SAT
___ UNSAT STANDARD:
Applicant enters N/A for RCP 1, RCP 3 and RCP 4 handswitches. The applicant enters N/A for 1-HS-68-31AA, RCP 2 NORMAL BKR & LIFT PUMP.
Applicant locates 1-HS-68-31BA RCP 2 ALTERNATE BKR & XFRE SELECTOR, observes that the handswitch is pushed in.
The applicant locates1-HS-68-31BA RCP 2 ALTERNATE BKR & XFRE SELECTOR and rotates the handswitch to the right to the START position. (Critical)
Applicant observes the RED indicating light LIT and the GREEN indicating light DARK on 1-HS-68-31BA. The applicant may also observe flow rising on 1-FI-68-29A, 29B, and 29D LOOP 1 FLOW indicators.
Step is critical since this action starts RCP 2, the desired RCP.
COMMENTS:
Page 11 of 16
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D
NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT EXAMINER: When #2 RCP oil lift pump is stopped, #2 RCP bearings begin to seize, causing the motor amps to rise above the RED line, and not return to normal.
STEP 16: [22] WHEN RCP has operated 1 minute, THEN STOP Oil Lift ___ SAT Pump (N/A HSs NOT used):
___ UNSAT STANDARD:
Applicant enters N/A for RCP 1, RCP 3 and RCP 4 handswitches.
Applicant locates 1-HS-68-31AA RCP 2 NORMAL BKR&LIFT PUMP then rotates the handswitch to the STOP position.
COMMENTS:
EXAMINER: When #2 RCP oil lift pump is stopped, #2 RCP bearings begin to seize, causing the motor amps to rise above the RED line, and not return to normal.
0-GOI-7, Generic Equipment Operating Guidelines, Section 5.2.5, Motor Operating and Starting Limitations, states:
[1] OPERATE motors having associated ammeters under the following guidelines:
A. Motors should NOT be operated above the RED line on the ammeter except when, in the judgment of the SRO, the safety of the plant and/or public may be in danger.
The applicant is expected to evaluate motor amps, and trip #2 RCP.
Page 12 of 16
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D
NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT EXAMINER: When 14-D, M-1 THRU M-6 MOTOR OVERLOAD annunciator is received, the Extra Operator will announce the alarm.
STEP 17: STOP and LOCK OUT #2 RCP. CRITICAL STANDARD: STEP Applicant rotates 1-HS-68-31BA is to the STOP position and GREEN ___ SAT ACB light is LIT.
Step is critical to prevent additional damage to #2 RCP pump. ___ UNSAT CUE: After RCP is stopped, state another operator will continue from here.
COMMENTS:
END OF TASK STOP TIME ________
Page 13 of 16
D Handout Package for Applicant
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- 1. Unit 2 is conducting pre-operational tests.
- 2. Unit 1 is in Mode 3.
- 3. #2 RCP 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.
- 4. Maintenance reported the repairs have been completed.
- 6. SOI-68.02, Reactor Coolant Pumps, Section 5.0, Startup, has been completed through Step 7.
- 7. Section 4.2 Field Preparations are complete.
INITIATING CUES:
The Unit Supervisor has directed you to start #2 RCP using SOI-68.02, Reactor Coolant Pumps, Section 5.0, Startup, beginning at Step 8.
Inform the Unit Supervisor when Section 5.0 is complete.
D
Watts Bar Nuclear Plant 2015301 NRC Exam System JPM E
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E
2015-301 NRC Exam EVALUATION SHEET Task: Shutdown 1B Main Feedwater Pump.
Alternate Path: None Facility JPM #: New Safety Function: 4S Title:
K/A 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: 41.5/43.5/45.3/45.13 Evaluation Method: Simulator X In-Plant Classroom
References:
1-SOI-2&3.01, Condensate and Feedwater System, Rev 0011.
Task Number: RO-003-SOI-2&3.01-013 Title: Remove the CBP and MFP from service during shutdown Task Standard: The applicant performs 1-SOI-2&3.01, Condensate and Feedwater System, Section 7.3.1, TDMFP Shutdown, Steps 4 through 15 to remove the 1B MFP from service.
Validation Time: 20 minutes Time Critical: Yes No X
===============================================================
Applicant: ___________________________ _________________ Time Start: ________
NAME Docket No. Time Finish: ________
Performance Rating: SAT ____ UNSAT ____ Performance Time ___
Examiner: _____________________________ _____________________________/________
NAME SIGNATURE DATE
===============================================================
COMMENTS Page 2 of 13
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E
2015-301 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:
- 1. ENSURE NRC Examination Security has been established.
- 2. RESET to Initial Condition 311 by performing the following actions:
- a. Select ICManager on the THUNDERBAR menu (right hand side of Instructor Console Screen).
- b. Locate IC 311.
- c. Right click on IC 311.
- d. Select Reset on the drop down menu.
- e. Right click on RESET.
- f. Enter the password for IC 311.
- g. Select Yes on the INITIAL CONDITION RESET pop-up window.
- h. Perform SWITCH CHECK.
6 Place simulator in RUN and acknowledge any alarms.
- 7. ENSURE a marked-up copy of SOI-30.02, Containment Purge System, Section 5.4, Start Up Instrument Room Purge, signed, circled-and-slashed through Step 5, is available to the Examiner.
- 8. ENSURE Extra Operator is present in the simulator.
- 9. Place simulator in FREEZE until Examiner cue is given.
SIMULATOR CONTINGENCY ACTIONS:
IF INITIAL CONDITION 310 is unavailable for any reason, the following actions must be taken to reconstruct the IC.
- 1. Initialize to IC 40, 100% power BOL.
- 2. Perform switch check.
Page 3 of 13
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E
2015-301 NRC Exam SIMULATOR SETUP INFORMATION JPM Proc. Step Step No. Description/Role Play No.
6 9 MAINTAIN return oil temp 140 to 160°F.
When contacted as an AUO, repeat back the direction to maintain return oil temperature. Reports temperature is currently 152 °F.
11 14 CLOSE the following:
B. 1-HCV-3-84, MAIN FEEDWATER PUMP B RECIRC WARMING [T2H/729].
When contacted as an AUO, repeat back the direction to close 1-HCV-3-84, MAIN FEEDWATER PUMP B RECIRC WARMING. Report 1-HCV-3-84, MAIN FEEDWATER PUMP B RECIRC WARMING is closed..
Page 4 of 13
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E
2015-301 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 2 is performing pre-operational testing.
- 2. Unit 1 is conducting a plant shutdown per 1-GO-4, Normal Operations, Section 5.3, Unit Shutdown from 100% to 30% Reactor Power.
- 3. Unit 1 is currently at 45% power.
- 4. You are an extra Control Room Operator assigned to the shift.
INITIATING CUES:
The Unit Supervisor has directed you to shutdown 1B Main Feedwater pump (MFP).
You are to perform 1-SOI-2&3.01, Condensate and Feedwater, Section 7.3.1, TDMFP Shutdown, Steps 4 through 15.
Inform the Unit Supervisor when Step 15 is complete.
Page 5 of 13
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _______
STEP 1: [4] () PLACE selected MFP speed control in MANUAL and LOWER CRITICAL speed slowly [1-M-3]: STEP A. 1-SIC-46-20A, MFPT A- SPEED CONTROL
___ SAT B. 1-SIC-46-20B, MFPT B- SPEED CONTROL:
STANDARD: ___ UNSAT The applicant marks 1-SIC-46-20A, MFPT A- SPEED CONTROL AMBER N/A.
The applicant locates 1-SIC-46-20B, MFPT B- SPEED CONTROL and depresses the AUTO/MAN button to transfer the control to MAN (Critical).
The applicant observes 1-SIC-46-20B, MFPT B- SPEED CONTROL AMBER (MAN) light LIT, BLUE (AUTO) light DARK.
The applicant depresses the lower [<<] button on 1-SIC-46-20B, MFPT B-SPEED CONTROL to slowly lower 1B MFP speed (Critical).
Step is critical to properly shift load from 1B MFP to the 1A MFP.
COMMENTS:
Page 6 of 13
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT NOTE As speed is lowered, the recirc valve for the pump being removed from service will open, causing a sudden shift of load to the pump remaining in service.
STEP 2: [5] ENSURE proper operation of recirc valves as pump unloads. ___ SAT STANDARD: ___ UNSAT Applicant observes 1B MFP recirc valve opens as 1B MFP speed reduces and load shifts to 1A MFP.
COMMENTS:
STEP 3: [6] IF other MFP is in service, THEN ENSURE the other MFP CRITICAL assumes the load. STEP STANDARD: ___ SAT Applicant observes 1A MFP speed increasing as 1B MFP speed is reduced. ___ UNSAT This step is critical to ensure adequate feed flow is maintained.
COMMENTS:
STEP 4: [7] IF MFP A is being SHUT DOWN, THEN MONITOR its supervisory ___ SAT instruments while unloading:
___ UNSAT STANDARD:
Since the 1B MFP is being shutdown, the applicant marks the step N/A.
COMMENTS:
Page 7 of 13
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT STEP 5: [8] IF MFP B is being SHUT DOWN, THEN MONITOR its MFPT and ___ SAT Pump Bearing Vibration on ICS while unloading:
___ UNSAT A. Turbine Vibration, less than 3 mils [ICS mimic MFPTVIBB].
B. Pump Vibration, less than 4 mils [ICS mimic MFPTVIBB].
C. Thrust Bearing, less than 7 mils (either direction) [ICS mimic MFPTVIBB].
STANDARD:
Applicant goes to the ICS terminal and selects SECONDARY MIMICS, then MFP B VIBRATION and monitors the display while unloading 1B MFP.
COMMENTS:
CAUTION Failure to have at least 1 MFP reset will trip the turbine and start Aux Feedwater.
STEP 6: [9] MAINTAIN return oil temp 140 to 160°F: ___ SAT A. 1-TIC-24-56A, MFPT OIL COOLER 1A1/1A2 RCW OUTLET
___ UNSAT TEMP [T1H/708], Panel 1-L-255. ________
B. 1-TIC-24-56B, MFPT OIL COOLER 1B1/1B2 RCW OUTLET TEMP [T1H/708], Panel 1-L-259. ________.
STANDARD:
Applicant contacts an AUO and directs the AUO to perform Step 9 to maintain return oil temperature 140 to 160°F.
CUE: When contacted as an AUO, the Console Operator will repeat back the direction to maintain return oil temperature. Console Operator reports temperature is 152 °F currently.
COMMENTS:
Page 8 of 13
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT STEP 7: [10] ENSURE both MFPs RESET.
___ SAT STANDARD:
Applicant locates 1-HS-46-9A, MFPT A TRIP - RESET and observes the RED ___ UNSAT light LIT, GREEN light DARK indicating MFPT A is RESET.
Applicant locates 1-HS-46-36A, MFPT B TRIP - RESET and observes the RED light LIT, GREEN light DARK indicating MFPT B is RESET.
COMMENTS:
CAUTION Tripping a MFP above 40% load closes its condenser inlet & outlet MOVs.
STEP 8: [11] () WHEN MFP turbine speed is approx 3300 rpm, THEN TRIP the ___ SAT MFP Turbine [1-M-3]:
___ UNSAT A. 1-HS-46-9A, MFPT A TRIP-RESET.
B. 1-HS-46-36A, MFPT B TRIP-RESET.
STANDARD:
Applicant locates 1-HS-46-36A, MFPT B TRIP - RESET and rotates THE HANDSWITCH TO THE RIGHT TO THE trip POSITION.
Applicant observes 1-HS-46-36A MFPT B TRIP - RESET RED light DARK, GREEN light LIT indicating MFPT B is TRIPPED.
COMMENTS:
Page 9 of 13
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT STEP 9: [12] VERIFY HP and LP Stop Valves CLOSE.
___ SAT STANDARD:
Applicant locates 1-HS-46-43A, MFPT B MFPT B HP STOP VLV, and ___ UNSAT observes RED light DARK, GREEN light LIT indicating the HP stop valve is closed.
Applicant locates 1-HS-46-44A, MFPT B MFPT B LP STOP VLV, and observes RED light DARK, GREEN light LIT indicating the LP stop valve is closed.
COMMENTS:
STEP 10: [13] VERIFY Governor Valves CLOSE, AND VERIFY Governor Valve
___ SAT Positioner is at minimum position by green light indication on controller panel (red light off):
___ UNSAT A. 1-HS-46-13A, MFPT A GOVERNOR VLV.
B. 1-HS-46-40A, MFPT B GOVERNOR VLV.
STANDARD:
Applicant locates 1-HS-46-40A, MFPT B GOVERNOR VLV, and observes RED light DARK, GREEN light LIT indicating the Governor valves are CLOSED.
COMMENTS:
Page 10 of 13
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT STEP 11: [14] CLOSE the following: ___ SAT A. 1-HCV-3-70, MAIN FEEDWATER PUMP A RECIRC
___ UNSAT WARMING [T2H/729].
B. 1-HCV-3-84, MAIN FEEDWATER PUMP B RECIRC WARMING [T2H/729].
STANDARD:
Applicant contacts an AUO and directs the AUO to perform Step 14 to CLOSE 1-HCV-3-84, MAIN FEEDWATER PUMP B RECIRC WARMING.
CUE: When contacted as an AUO, the Console Operator will repeat back the direction to close 1-HCV-3-84, MAIN FEEDWATER PUMP B RECIRC WARMING. Console Operator reports 1-HCV-3-84, MAIN FEEDWATER PUMP B RECIRC WARMING is closed.
COMMENTS:
STEP 12: [15] IF MFW flow is above 40% (6 X 106 pph) when MFP is ___ SAT tripped, THEN VERIFY applicable MFP condenser valves CLOSED [1-M-2]: ___ UNSAT A. MFPT A: 1-FCV-2-210, MFPT A CONDENSER CNDS INLET and 1-FCV-2-205, MFPT A CONDENSER CNDS OUTLET.
B. MFPT B: 1-FCV-2-211, MFPT B CONDENSER CNDS INLET and 1-FCV-2-216, MFPT B CONDENSER CNDS OUTLET.
STANDARD:
Applicant locates MFPT B: 1-FCV-2-211, MFPT B CONDENSER CNDS INLET and 1-FCV-2-216, MFPT B CONDENSER CNDS OUTLET and observes the GREEN light is LIT and RED light is DARK on each handswitch, indicating the valves are CLOSED.
COMMENTS:
END OF TASK STOP TIME ________
Page 11 of 13
E Handout Package for Applicant
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- 1. Unit 2 is performing pre-operational testing.
- 2. Unit 1 is conducting a plant shutdown per 1-GO-4, Normal Operations, Section 5.3, Unit Shutdown from 100% to 30% Reactor Power.
- 3. Unit 1 is currently at 45% power.
- 4. You are an extra Control Room Operator assigned to the shift.
INITIATING CUES:
The Unit Supervisor has directed you to shutdown 1B Main Feedwater pump (MFP).
You are to perform 1-SOI-2&3.01, Condensate and Feedwater, Section 7.3.1, TDMFP Shutdown, Steps 4 through 15.
Inform the Unit Supervisor when Step 15 is complete.
E
Watts Bar Nuclear Plant 2015301 NRC Exam System JPM F
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F
2013-03 NRC Exam EVALUATION SHEET Task: Place RHR Spray in service per 1-FR-Z.1, High Containment Pressure.
Alternate Path: During performance of 1-FR-Z.1, Step 10, 1-HS-72-41 fails to open. Requires performance of Step 10.b RNO to place Train A RHR spray in service.
Facility JPM #: 3-OT-JPMR016A Modified Safety Function: 5 Title: Containment Systems K/A E14 EA1.1 Ability to operate and / or monitor the following as they apply to the (High Containment Pressure) Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features Rating(s): 3.7/3.7 CFR: 41.7 / 45.5 / 45.6 Evaluation Method: Simulator X In-Plant Classroom
References:
1-FR-Z.1, High Containment Pressure, Rev. 1.
Task Number: RO-113-FR-Z.1-001 Title: Respond to Phase B Containment pressure.
Task Standard:
The applicant:
- 1. Performs actions to place Train B RHR Spray in service.
- 2. Determines 1-HS-72-41 has failed and will not open.
- 3. Enters 10.b RNO, and places Train A RHR Spray in service.
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 of 13
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F
2015-301 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:
- 1. ENSURE NRC Examination Security has been established.
- 2. RESET to Initial Condition 312 by performing the following actions:
- a. Select ICManager on the THUNDERBAR menu (right hand side of Instructor Console Screen).
- b. Locate IC 312.
- c. Right click on IC 312.
- d. Select Reset on the drop down menu.
- e. Right click on RESET.
- f. Enter the password for IC 312.
- g. Select Yes on the INITIAL CONDITION RESET pop-up window.
- h. Perform SWITCH CHECK.
- 3. ENSURE the following information appears on the Director Summary Screen:
Key Type Event Delay Inserted Ramp Initial Final Value cs06g air return fan a-a fail to start on phase b M 00:00:00 00:00:00 Active Active cs06h air return fan b-b fail to start on phase b M 00:00:00 00:00:00 Active Active th01d loca- -hot leg loop 4 M 1 00:00:00 00:00:00 100 100 hs-72-27a hs-72-27a containment spray pimp a mtr sw O 00:00:00 00:00:00 On None hs-72-10a hs-72-10a containment spray pimp b mtr sw O 00:00:00 00:00:00 On None hs-72-27a-1 06020 cntmt spray pump a mtr sw (green) O 00:00:00 00:00:00 On None hs-72-22a-1 05020 rwst spray hdr a fcv (green) O 00:00:00 00:00:00 On None hs-72-44a-1 05040 cntmt sump hdr a fcv(green) O 00:00:00 00:00:00 On None hs-72-34a-1 05060 cs pump a recirc fcv(green) O 00:00:00 00:00:00 On None hs-72-39a-1 05080 cs hdr a isol vlv sw(green) O 00:00:00 00:00:00 On None fi-72-13 07010 cntmt spray pmp b flow O 00:00:00 00:00:00 On None ei-72-12a 07020 cntmt spray pump b amps O 00:00:00 00:00:00 On None hs-72-10a-3 06010 cntmt spray pump b mtr sw (red) O 00:00:00 00:00:00 On None hs-72-10a-1 06010 cntmt spray pump b mtr sw (green) O 00:00:00 00:00:00 On None hs-72-21a hs-72-21a rwst to spray header b flow control valv O 00:00:00 00:00:00 On None hs-72-21a-2 05010 rwst spray hdr b fcv (red) O 00:00:00 00:00:00 On None Page 3 of 13
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F
2015-301 NRC Exam Key Type Event Delay Inserted Ramp Initial Final Value hs-72-41a hs-72-41a rhr spray header b isolation valve sw O 00:00:00 00:00:00 close close li-63-50 09010 sis rwst level ind O 00:00:00 00:00:00 6 31.6131 li-63-51 09020 sis rwst level ind O 00:00:00 00:00:00 6 31.6131 li-63-52 09030 sis rwst level ind O 00:00:00 00:00:00 6 31.6131 li-63-53 09040 sis rwst level ind O 00:00:00 00:00:00 6 31.6131 hs-30-38a-2 01010 air return fans a-a on/off(white) O 00:00:00 00:00:00 On Off hs-30-39a-2 01010 air return fans b-b on/off(white) O 00:00:00 00:00:00 On Off
- 4. Place simulator in RUN and acknowledge any alarms.
- 5. ENSURE a marked-up copy of 1-FR-Z.1, High Containment Pressure, signed, circled-and-slashed through Step 9, is available to the Examiner.
- 6. ENSURE Extra Operator is present in the simulator.
- 7. Place simulator in FREEZE until Examiner cue is given.
Page 4 of 13
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F
2015-301 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 2 is conducting preoperational testing.
- 2. Unit 1 was at 100% when a Large Break LOCA occurred.
- 3. 1A-A Containment Spray Pump is tagged out-of-service.
- 4. 1B-B Containment Spray Pump started and has been spraying Containment.
- 5. Both Containment Air Return Fans tripped upon receipt of a start signal.
- 6. The break occurred 75 minutes ago.
- 7. All other ECCS equipment is performing its design functions and is on Containment Sump Recirculation.
- 8. You are the Operator at the Controls (OAC).
INITIATING CUES:
The Unit Supervisor directs you to place RHR Spray in-service per 1-FR-Z.1, High Containment Pressure, Step 10.
You are to notify the Unit Supervisor when RHR Spray is in service.
Page 5 of 13
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _______
STEP 1: 10. DETERMINE if RHR spray should be placed in service: ___ SAT
- a. CHECK the following conditions:
___ UNSAT
- At least one hour has elapsed since the beginning of the accident.
- Cntmt pressure is greater than 9.5 psig.
- At least one charging pump and one SI pump running.
STANDARD:
The applicant determines from the information provided that all of the listed conditions exist, and proceeds to Step 10.b.
COMMENTS:
STEP 2: b. ALIGN Train B RHR spray: ___ SAT
- 1) ENSURE Train B RHR pump RUNNING.
___ UNSAT STANDARD:
Applicant locates 1-HS-74-20A, RHR PMP B (ECCS) and observes the RED light LIT GREEN light DARK.
Applicant may locate 1-EI-74-17A, RHR PMP B AMPS and observe amps normal.
Applicant may locate 1-PI-74-26, RHR PMP B DISCH PRESS and observe normal pressure.
COMMENTS:
Page 6 of 13
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT STEP 3: 2) CLOSE RHR crosstie 1-FCV-74-35. ___ SAT STANDARD:
___ UNSAT Applicant locates 1-FCV-74-35, RHR HX OUTLET XTIE and observes the RED light DARK, GREEN light LIT, indicating the valve is CLOSED.
COMMENTS:
STEP 4: 3) CLOSE RHR injection 1-FCV-63-94. ___ SAT STANDARD:
___ UNSAT Applicant locates 1-HS-63-94 and rotates the handswitch to the left to the CLOSE position.
Applicant observes GREEN light LIT, RED light DARK indicating the valve is CLOSED.
COMMENTS:
Page 7 of 13
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT CAUTION EXAMINER: 1-HS-72-41A, RHR SPRAY HDR B TO CNTMT, is overridden to the CLOSE position as part of the simulator setup. This will require the applicant to exercise the RNO column actions of Step b.
STEP 5: 4) OPEN RHR spray 1-FCV-72-41. ___ SAT STANDARD:
___ UNSAT Applicant locates 1-HS-72-41, RHR SPRAY HDR B TO CNTMT, and rotates the handswitch to the left to the CLOSE position.
Applicant observes RED light LIT and GREEN DARK light on the handswitch, and determines the valve has remained open.
Applicant determines that 1-HS-72-41, RHR TO CL 1&4, will NOT CLOSE, and enters Step b. RNO for actions.
COMMENTS:
STEP 5: b. IF Train B RHR spray CANNOT be established, THEN ___ SAT PERFORM the following:
___ UNSAT
- 1) ENSURE RHR spray 1-FCV-72-41 CLOSED.
STANDARD:
Applicant states that 1-HS-72-41 is CLOSED, since 1-HS-72-41 failed to OPEN the valve.
Applicant observes GREEN light LIT, RED light DARK indicating the valve is CLOSED.
COMMENTS:
Page 8 of 13
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT STEP 6: 2) IF RHR aligned for cold leg recirculation, THEN ENSURE CRITICAL 1-FCV-63-94 OPEN. STEP STANDARD:
___ SAT Applicant locates 1-HS-63-94 and rotates the handswitch to the right to the OPEN position. (Critical). ___ UNSAT Applicant observes GREEN light DARK, RED light LIT indicating the valve is OPEN.
This step is critical to ensure cold leg recirculation is maintained through the core.
COMMENTS:
STEP 7: 3) ENSURE Train A RHR pump RUNNING. ___ SAT STANDARD:
___ UNSAT Applicant locates 1-HS-74-10A, RHR PMP A (ECCS) and observes the RED light LIT GREEN light DARK.
Applicant may locate 1-EI-74-5A, RHR PMP A AMPS and observe amps normal.
Applicant may locate 1-PI-74-13, RHR PMP A DISCH PRESS and observe normal pressure COMMENTS:
Page 9 of 13
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT STEP 8: 4) CLOSE RHR crosstie 1-FCV-74-33. ___ SAT STANDARD:
___ UNSAT Applicant locates 1-FCV-74-33, RHR HX OUTLET XTIE and observes the RED light DARK, GREEN light LIT, indicating the valve is CLOSED.
COMMENTS:
STEP 9: 5) CLOSE RHR injection 1-FCV-63-93. CRITICAL STANDARD: STEP
___ SAT Applicant locates 1-HS-63-93, RHR TO CL 1&4, and rotates the handswitch to the left to the CLOSE position. (Critical).
___ UNSAT Applicant observes RED light DARK and GREEN light LIT on the handswitch.
This step is critical to ensure flow is directed to the A RHR Spray header.
COMMENTS:
Page 10 of 13
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT STEP 10: 6) OPEN RHR spray 1-FCV-72-40. CRITICAL STANDARD: STEP
___ SAT Applicant locates 1-HS-72-40, RHR SPRAY HDR A TO CNTMT and rotates the handswitch to the right to the OPEN position. (Critical).
___ UNSAT Applicant observes RED light LIT, GREEN light DARK, indicating the valve is OPEN.
Applicant observes containment pressure decreasing on 1-PDI-30-42, 1-PDI-30-43, 1-PDI-30-44 and 1-PDI-30-45.
This step is critical to ensure flow is directed to the A RHR Spray header.
COMMENTS:
STEP 11: Notifies the Unit Supervisor that Train A RHR Spray is in service. ___ SAT STANDARD:
___ UNSAT Applicant notifies the Unit Supervisor that Train A RHR Spray is in service.
Applicant reports that 1-HS-72-41 failed to OPEN its associated valve.
CUE: Repeat back information provided by the applicant.
COMMENTS:
END OF TASK STOP TIME ________
Page 11 of 13
F Handout Package for Applicant
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- 1. Unit 2 is conducting preoperational testing.
- 2. Unit 1 was at 100% when a Large Break LOCA occurred.
- 3. 1A-A Containment Spray Pump is tagged out-of-service.
- 4. 1B-B Containment Spray Pump started and has been spraying Containment.
- 5. Both Containment Air Return Fans tripped upon receipt of a start signal.
- 6. The break occurred 75 minutes ago.
- 7. All other ECCS equipment is performing its design functions and is on Containment Sump Recirculation.
- 8. You are the Operator at the Controls (OAC).
INITIATING CUES:
The Unit Supervisor directs you to place RHR Spray in-service per 1-FR-Z.1, High Containment Pressure, Step 10.
You are to notify the Unit Supervisor when RHR Spray is in service.
F
Watts Bar Nuclear Plant 2015301 NRC Exam System JPM G
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G
2013-03 NRC Exam EVALUATION SHEET Task: Synchronize DG 1A-A from the MCR Alternate Path: During diesel generator synchronization, annunciator 196-D, CRANKCASE PRESSURE HI is received, requiring the applicant to stop the 1A-A Diesel Generator.
Facility JPM #: 3-OT-JPMR060A Modified Safety Function: 6 Title: Electrical Systems K/A 064 A1.03 Ability to manually operate and/or monitor in the control room: Manual start, loading, and stopping of the ED/G Rating(s): 3.9/3.9 CFR: 41.7 / 45.5 to 45.8 Evaluation Method: Simulator X In-Plant Classroom
References:
0-SOI-82.01, Diesel Generator (DG) 1A-A, Rev. 0004.
ARI-195-201, Diesel Gen 1A-A, Rev. 16.
Task Number: RO-082-SOI-82-002 Title: Start and synchronize the emergency diesel generators.
Task Standard: The applicant:
1.) Synchronizes 1A-A Diesel Generator to the 1A-A Shutdown Board from the MCR, per 0-SOI-82.01 Section 8.1.4, and then loads the DG to 3.5 to 4 MW and 0.75-1.25 MVARs.
2.) Within 2 minutes of the receipt of annunciator 196-D, CRANKCASE PRESSURE HI, the applicant depresses 1-HS-82-17A, EMERGENCY STOP.
Validation Time: 15 minutes Time Critical: Yes No X
===============================================================
Applicant: ___________________________ _________________ Time Start: ________
NAME Docket No. Time Finish: ________
Performance Rating: SAT ____ UNSAT ____ Performance Time ___
Examiner: _____________________________ _____________________________/________
NAME SIGNATURE DATE
===============================================================
COMMENTS Page 2 of 14
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G
2015-301 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:
- 1. ENSURE NRC Examination Security has been established.
- 2. RESET to Initial Condition 313 by performing the following actions:
- a. Select ICManager on the THUNDERBAR menu (right hand side of Instructor Console Screen).
- b. Locate IC 313.
- c. Right click on IC 313.
- d. Select Reset on the drop down menu.
- e. Right click on RESET.
- f. Enter the password for IC 313.
- g. Select Yes on the INITIAL CONDITION RESET pop-up window.
- h. Perform SWITCH CHECK.
- 3. ENSURE the following information appears on the Director Summary Screen:
Key Type Event Delay Inserted Ramp Initial Final Value mux_07c048 196-d dg 1a-a crankcase press hi M 30 00:00:00 00:00:00 On None
- 4. Ensure Event 30 is loaded into the simulator.
6 Place simulator in RUN and acknowledge any alarms.
- 7. ENSURE a marked-up copy of 0-SOI-82.01, Diesel Generator (DG) 1A-A, signed, circled-and-slashed through Step 3, is available to the Examiner.
- 8. ENSURE Extra Operator is present in the simulator.
- 9. Place simulator in FREEZE until Examiner cue is given.
- 10. ENSURE STOP WATCH is available to the applicant.
Page 3 of 14
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G
2015-301 NRC Exam SIMULATOR CONTINGENCY ACTIONS:
IF INITIAL CONDITION 313 is unavailable for any reason, the following actions must be taken to reconstruct the IC.
- 1. Initialize to IC 40, 100% power BOL.
- 2. Perform switch check.
- 3. Enter the following using the DIRECTOR function.
Key Type Event Delay Inserted Ramp Initial Final Value mux_07c048 196-d dg 1a-a crankcase press hi M 30 00:00:00 00:00:00 On None
- 4. To rebuild the Event 30, open the Event Editor and enter zaoei8210a >= 0.45 & zaoei8211a >= 0.60. This event will enter when the diesel is loaded to approximately 3.5 MW and 0.7 MVARS.
Page 4 of 14
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G
2015-301 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 2 is conducting pre-operational tests.
- 2. Testing is being conducted on 1A-A diesel generator. It is to be paralleled to the shutdown board for a Factory Representative on site.
- 3. The 1A-A DG is running at rated speed, after performance of 0-SOI-82.01, Diesel Generator (DG) 1A-A, Section 8.1.3, Idle Speed to Rated Speed.
- 4. Steps 1 through 3 of 0-SOI-82.01, Diesel Generator (DG) 1A-A, Section 8.1.4, Manual-Remote Synchronizing DG, have been performed.
- 5. You are an extra control room operator on shift.
INITIATING CUES:
The Unit Supervisor directs you to parallel the 1A-A diesel generator to the 1A-A Shutdown Board per 0-SOI-82.01, Diesel Generator (DG) 1A-A and establish load between 3.5 and 4 MEGAWATTS with 0.75 and 1.25 MEGAVARS outgoing.
Inform the Unit Supervisor when the diesel generator is loaded.
Page 5 of 14
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _______
STEP 1: [4] PLACE 1-HS-82-18, DG MODE SELECTOR Switch, in CRITICAL PARALLEL [0-M-26]. STEP STANDARD:
___ SAT The applicant locates 1-HS-82-18 DG MODE SELECTOR and rotates the handswitch to the right from the UNIT to the PARALLEL position. ___ UNSAT (Critical).
This step is critical for task performance to allow proper operation of voltage regulator & DG speed droop circuits.
COMMENTS:
STEP 2: [5] ENSURE the following sync switches for 1A-A D/G in OFF: ___ SAT
___ UNSAT STANDARD:
Applicant locates each of the listed sync switches and determines that each handswitch is in the OFF position COMMENTS:
Page 6 of 14
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT STEP 3: [6] PLACE 1-HS-57-47, DG SYNC SWITCH, in SYN [0-M-26]. CRITICAL STANDARD: STEP Applicant locates 1-HS-57-47, DG SYNC SWITCH and rotates the ___ SAT switch to the right to the SYN position (Critical).
This step is critical to allow synchronization of DG to 1A-A ___ UNSAT Shutdown board.
COMMENTS:
CAUTION When adjusting speed and voltage, care must be taken to prevent overshooting desired values. Voltage control response is approximately five times faster than speed control response.
STEP 4: [7] MATCH generator Incoming Frequency (1-XI-82-2) with ___ SAT Running Frequency (1-XI-82-3) using 1-HS-82-13, SPEED CONTROL [0-M-26]. ___ UNSAT STANDARD:
Applicant operates 1-HS-82-13 to adjust generator frequency (incoming) on 1-XI-82-2 to match with board frequency (running) on 1-XI-82-3.
COMMENTS:
STEP 5: [8] MATCH generator Incoming Voltage (1-EI-82-4) with Running ___ SAT Voltage (1-EI-82-5) using 1-HS-82-12, VOLTAGE REGULATOR [0-M-26]. ___ UNSAT STANDARD:
Applicant operates 1-HS-82-12 to adjust generator voltage on 1-EI-82-4 to board voltage on 1-EI-82-5.
COMMENTS:
Page 7 of 14
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT NOTE Steps 8.1.4[9], 8.1.4[10], and 8.1.4[11] should be read before performing.
EXAMINER: The applicant may use a stopwatch to time the 15 second rotation. Provide stopwatch if asked.
STEP 6: [9] ENSURE DG Frequency and Voltage are MATCHED with 6.9 ___ SAT kV SD Bd, AND ADJUST 1-HS-82-13, SPEED CONTROL,
[0-M-26] to obtain desired clockwise rotation (15 or more ___ UNSAT seconds) on 1-XI-82-1,TRAIN 1A-A SYNCHROSCOPE.
STANDARD:
Applicant observes that running and incoming frequency and voltage are matched or takes appropriate actions to make them equal.
The applicant adjusts 1-HS-82-13 SPEED CONTROL to make the synchroscope movie slowly in the clockwise direction at 15 seconds or more per rotation on the scope.
COMMENTS:
NOTES
- 1) Steps 8.1.4[10] through 8.1.4[11.3] may be signed off after completion of Step 8.1.4[11.3].
- 2) Peer checking required on next step.
Page 8 of 14
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT STEP 7: [10] WHEN 1-XI-82-1, TRAIN 1A-A SYNCHROSCOPE CRITICAL (1-XI-82-1) reaches 12 oclock, THEN TURN 1-HS-57-46A, STEP 1912 - DG TO SH BD 1A-A, to CLOSE. ___ SAT STANDARD:
Applicant monitors 1-XI-82-1, TRAIN 1A-A SYNCHROSCOPE and ___ UNSAT rotates 1-HS-57-46A, 1912 - DG TO SD BD 1A-A, to the right to the CLOSE position. (Critical).
Applicant observes the RED light LIT, GREEN light DARK on 1-HS-57-46A.
This step is critical to ensure proper DG loading (i.e., outgoing power upon breaker closure).
COMMENTS:
NOTE Maintain outgoing Vars by periodically adjusting voltage regulator with 1-HS-82-12 while loading D/G. Controls should NOT be operated simultaneously.
STEP 8: [11] PERFORM the following: CRITICAL
[11.1] LOAD DG promptly using 1-HS-82-13, SPEED STEP CONTROL to at least 1.1 Megawatts as indicated
___ SAT on 1-EI-82-10A, DG MEGAWATTS (0-M-26).
STANDARD: ___ UNSAT Applicant periodically rotates 1-HS-82-13 to the RAISE position to increase generator load on 1-EI-82-10A, DG MEGAWATTS prior to receipt of the reverse power trip. (Critical).
This step is critical to ensure proper DG loading and avoid reverse power trip.
COMMENTS:
Page 9 of 14
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT NOTE DG Megavars may "swing" when the 6.9kV automatic tap changers engage to stabilize voltage in the system.
STEP 9: [11.2] MAINTAIN DG MEGAVARS 0.75 to 1.25 OUTGOING CRITICAL on 1-EI-82-11A, with 1-HS-82-12, VOLTAGE STEP REGULATOR.
___ SAT STANDARD:
Applicant periodically adjusts 1-HS-82-12, VOLTAGE REGULATOR, to ___ UNSAT maintain Megavars between 0.75 and 1.25 OUTGOING on 1-EI-82-11A prior to receipt of the reverse power trip. (Critical).
This step is critical to ensure proper DG loading and avoid reverse power trip.
COMMENTS:
CAUTION Operation of the DG at load of 2.7 MW or less for extended period of time may lead to exhaust fire.
EXAMINER: The applicant determines from the INITIATING CUES that the 1A-A DG is to be loaded to 3.5 to 4 MW and 0.75 to 1.25 MVARS OUTGOING.
STEP 10: [11.3] RAISE load to at least 3.3 Megawatts. ___ SAT STANDARD:
___ UNSAT Applicant periodically rotates 1-HS-82-13 to the RAISE position to increase generator load on 1-EI-82-10A, DG MEGAWATTS to 3.3 Megawatts.
Applicant periodically adjusts 1-HS-82-12, VOLTAGE REGULATOR to maintain Megavars between 0.75 and 1.25 OUTGOING on 1-EI-82-41A.
COMMENTS:
Page 10 of 14
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT EXAMINER: At 5 seconds after 1A-A Diesel Generator megawatts are raised above 3.2 MWe with greater than 0.7 MEGAVARS outgoing, Window 196-D, CRANKCASE PRESSURE HIGH will be received.
Time 196-D, CRANKCASE PRESSURE HIGH received:_____________________.
EXAMINER: The following actions are taken from ARI 196-D, CRANKCASE PRESSURE HIGH STEP 11: Applicant responds to 196-D, CRANKCASE PRESSURE HIGH ___ SAT on XA-55-26B.
STANDARD: ___ UNSAT Applicant notes the Crankcase Pressure High Annunciation, Window 196 D on XA-55-26A and refers to the Alarm Response Instruction for the window.
COMMENTS:
STEP 12: [1] IF DG running with NO emergency start present, THEN CRITICAL ENSURE DG shutdown by Emergency Stop: STEP
- Remote - Depress 1-HS-82-17A, EMERGENCY STOP
___ SAT pushbutton on 0-M-26.
- Local - Depress EMERGENCY STOP pushbutton on DG
___ UNSAT Control Board STANDARD:
Applicant locates 1-HS-82-17A, EMERGENCY STOP pushbutton on 0-M-26 and depresses the pushbutton within 2 minutes of receipt of Window 196-D, CRANKCASE PRESSURE HIGH.
Time 1-HS-82-17A, EMERGENCY STOP depressed:___________.
This step is critical to ensure that additional damage to 1A-A DG is prevented.
COMMENTS:
Page 11 of 14
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT STEP 15: Notifies the Unit Supervisor that the 1A-A Diesel Generator was ___ SAT shutdown using 1-HS-82-17A, EMERGENCY STOP pushbutton on 0-M-26, due to a high crankcase pressure alarm. ___ UNSAT STANDARD:
Applicant notifies the Unit Supervisor that an emergency stop of the 1A-A Diesel Generator was performed due to high crankcase pressure, in accordance with ARI 196-D, CRANKCASE PRESSURE HIGH.
CUE: Repeat back information provided by the applicant.
COMMENTS:
END OF TASK STOP TIME ________
Page 12 of 14
G Handout Package for Applicant
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- 1. Unit 2 is conducting pre-operational tests.
- 2. Testing is being conducted on 1A-A diesel generator. It is to be paralleled to the shutdown board for a Factory Representative on site.
- 3. The 1A-A DG is running at rated speed, after performance of 0-SOI-82.01, Diesel Generator (DG) 1A-A, Section 8.1.3, Idle Speed to Rated Speed.
- 4. Steps 1 through 3 of 0-SOI-82.01, Diesel Generator (DG) 1A-A, Section 8.1.4, Manual-Remote Synchronizing DG, have been performed.
- 5. You are an extra control room operator on shift.
INITIATING CUES:
The Unit Supervisor directs you to parallel the 1A-A diesel generator to the 1A-A Shutdown Board per 0-SOI-82.01, Diesel Generator (DG) 1A-A and establish load between 3.5 and 4 MEGAWATTS with 0.75 and 1.25 MEGAVARS outgoing.
Inform the Unit Supervisor when the diesel generator is loaded.
G
Watts Bar Nuclear Plant 2015301 NRC Exam System JPM H
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H
2015-301 NRC Exam EVALUATION SHEET Task: Start Up Instrument Room Purge.
Alternate Path: None Facility JPM #: Modified Bank JPM Safety Function: 8 Title: Plant Service Systems K/A 029 A2.03 Ability to (a) predict the impacts of the following malfunctions or operations on the Containment Purge System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Startup operations and the associated required valve lineups.
Rating(s): 2.7/3.1 CFR: 41.5/43.5/45.3/45.13 Evaluation Method: Simulator X In-Plant Classroom
References:
SOI-30.02, Containment Purge System, Rev. 60.
Task Number: RO-030-SOI-30-008 Title: Purge the Instrument Room.
Task Standard: The applicant places Instrument Room Purge in service using SOI-30.02, Containment Purge System, Section 5.4, Start Up Instrument Room Purge, steps 6 through Step 11.
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 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H
2015-301 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:
- 1. ENSURE NRC Examination Security has been established.
- 2. RESET to Initial Condition 314 by performing the following actions:
- a. Select ICManager on the THUNDERBAR menu (right hand side of Instructor Console Screen).
- b. Locate IC 314.
- c. Right click on IC 314.
- d. Select Reset on the drop down menu.
- e. Right click on RESET.
- f. Enter the password for IC 314.
- 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 SOI-30.02, Containment Purge System, Section 5.4, Start Up Instrument Room Purge, signed, circled-and-slashed through Step 5, is available to the Examiner.
- 5. ENSURE Extra Operator is present in the simulator.
- 6. Place simulator in FREEZE until Examiner cue is given.
SIMULATOR CONTINGENCY ACTIONS:
IF INITIAL CONDITION 310 is unavailable for any reason, the following actions must be taken to reconstruct the IC.
- 1. Initialize to IC 40, 100% power BOL.
- 2. Perform switch check.
Page 3 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H
2015-301 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 2 is conducting pre-operational testing.
- 2. Unit 1 is at 100% power.
- 3. A purge of the Instrument Room is scheduled to be performed on this shift.
- 4. SOI-30.02, Containment Purge System, Section 4.0, Prerequisite Actions, is complete.
- 5. SOI-30.02, Containment Purge System, Section 5.4, Start Up Instrument Room Purge, is complete through Step 5.
- 6. You are an extra Control Room Operator assigned to the shift.
INITIATING CUES:
The Unit Supervisor has directed you to place Instrument Room Purge in service, by performing Steps 6 through 11 of SOI-30.02, Containment Purge System, Section 5.4, Start Up Instrument Room Purge.
Inform the Unit Supervisor when Instrument Room Purge is in service.
Page 4 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _______
STEP 1: [6] CLOSE Containment vent filter flowpath:
CRITICAL STEP
___ SAT
___ UNSAT STANDARD:
The applicant locates 1-HS-30-37, LWR CNTMT PURGE EXH PRESS RLF and rotates the handswitch to the left to the CLOSE position. (Critical).
The applicant observes 1-HS-30-37, LWR CNTMT PURGE EXH PRESS RLF handswitch GREEN light LIT, RED light DARK indicating damper is CLOSED.
The applicant locates 1-HS-30-40, LWR CNTMT PURGE EXH PRESS RLF and rotates the handswitch to the left to the CLOSE position. (Critical).
The applicant observes 1-HS-30-40, LWR CNTMT PURGE EXH PRESS RLF handswitch GREEN light LIT; RED light DARK indicating damper is CLOSED.
Step is critical to ensure proper purge flowpath is established.
COMMENTS:
Page 5 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT STEP 2: [7] PERFORM the following: CRITICAL STEP
___ SAT
___ UNSAT STANDARD:
The applicant locates 1-HS-30-19, INSTR RM PURGE 1-FCV-30-19 & 58 and rotates the handswitch to the right to the OPEN position. (Critical).
Applicant observes GREEN FCV lights for 1-FCV-30-19, 58, DARK and RED indicating lights 1-FCV-30-19, 58 are LIT on the PURGE DAMPERS mimic The applicant locates 1-HS-30-20, INSTR RM PURGE 1-FCV-30-20 & 59 and rotates the handswitch to the right to the OPEN position. (Critical).
Applicant observes GREEN FCV lights for 1-FCV-30-20 and 59 are DARK and RED indicating lights 1-FCV-30-20 and 59 are LIT on the PURGE DAMPERS mimic.
The applicant locates 1-HS-30-61, PURGE EXH FAN 1A SUCT and rotates the handswitch to the right to the OPEN position. (Critical).
Applicant observes GREEN light for 1-FCV-30-61is DARK and RED light 1-FCV-30-61 is LIT The applicant locates 1-HS-30-5, PURGE EXH FAN 1B SUCT and rotates the handswitch to the right to the OPEN position. (Critical).
Applicant observes GREEN lights for 1-FCV-30-5 is DARK and RED light 1-FCV-30-5 is LIT The applicant locates 1-HS-30-213, PURGE EXH FAN 1A TO SHIELD BLDG VNT and rotates the handswitch to the right to the OPEN position. (Critical).
Applicant observes GREEN lights for 1-FCV-30-213 is DARK and RED light 1-FCV-30-213 is LIT This step is critical to properly align dampers to purge the instrument room.
COMMENTS:
Page 6 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT CAUTION: Initial Conditions states that Section 4.0, PREREQUISITE ACTIONS is complete.
Step 4.2[2] ensures the conditions of the CAUTION are satisfied.
CAUTION For normal plant operations, purge should NOT be placed in service unless the U1 shield bldg. exhaust monitor and its associated isokinetic sampler are operable.
STEP 3: [8] START INSTR RM PURGE SUP & EXH FANS and FCO-30-11A & CRITICAL 11B with 1-HS-30-11A [1-M-9]. STEP STANDARD:
___ SAT Applicant locates 1-HS-30-11A, INSTR RM PURGE SUP & EXH FANS and FCO-30-11A & 11B, pushes the handswitch IN and rotates the switch to the ___ UNSAT right to the START position (Critical).
Applicant observes GREEN lights for SUP and EXH DARK and RED lights LIT on 1-HS-30-11A, INSTR RM PURGE SUP & EXH FANS and FCO 11A & 11B.
This step is critical establish flow through the Instrument Room.
COMMENTS:
Page 7 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT STEP 4: [9] ENSURE the following:
___ SAT
___ UNSAT STANDARD:
The applicant locates 1-FCO-3011A, DAMPER 1-XI-30-11A and observes the RED light is LIT.
The applicant locates 1-FCO-3011B, DAMPER 1-XI-30-11B and observes the RED light is LIT.
The applicant locates FCO-30-294, PURGE SUP SUCT ISOL DAMPER 1-XI-30-294 and observes the RED light is LIT.
The applicant locates FCO-30-295, PURGE SUP SUCT ISOL DAMPER 1-XI-30-294 and observes the RED light is LIT.
COMMENTS:
STEP 5: [10] CHECK flow on 1-FI-90-400, SHIELD BLDG VT FLOW
___ SAT
[1-M-9]. (N/A if FI NOT available)
STANDARD: ___ UNSAT Applicant locates 1-FI-90-400, SHIELD BLDG VENT FLOW and observes approximately 2000 SCFM COMMENTS:
Page 8 of 11
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT STEP 6: [11] IF FI-90-400 is NOT available, THEN ENSURE Flow being estimated
___ SAT per 1-SI-0-2, Shift & Daily Log.
STANDARD: ___ UNSAT Applicant determines Step [11] is N/A.
COMMENTS:
STEP 7: Applicant notifies the Unit Supervisor that instrument room purge has
___ SAT been established.
STANDARD: ___ UNSAT Applicant notifies the Unit Supervisor that instrument room purge has been established.
CUE: Repeat back information provided by the applicant.
COMMENTS:
END OF TASK STOP TIME ________
Page 9 of 11
H Handout Package for Applicant
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- 1. Unit 2 is conducting pre-operational testing.
- 2. Unit 1 is at 100% power.
- 3. A purge of the Instrument Room is scheduled to be performed on this shift.
- 4. SOI-30.02, Containment Purge System, Section 4.0, Prerequisite Actions, is complete.
- 5. SOI-30.02, Containment Purge System, Section 5.4, Start Up Instrument Room Purge, is complete through Step 5.
- 6. You are an extra Control Room Operator assigned to the shift.
INITIATING CUES:
The Unit Supervisor has directed you to place Instrument Room Purge in service, by performing Steps 6 through 11 of SOI-30.02, Containment Purge System, Section 5.4, Start Up Instrument Room Purge.
Inform the Unit Supervisor when Instrument Room Purge is in service.
H
Watts Bar Nuclear Plant NRC EXAM 2015301 System JPM I
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I
NRC EXAM 2013-302 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.
K/A 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:
1-SOI-62.01, CVCS - Charging and Letdown, Rev. 0.
Task Number: AUO-062-SOI-62.1-014 Title: Swap Seal Injection Filters.
Task Standard: The applicant places A Seal Injection Filter in service and takes Seal injection Filter B out of service in accordance with 1-SOI-62.01, CVCS-Charging and Letdown, Section 8.9.2, Replacing Filter B with Filter A.
Validation Time: 15 minutes Time Critical: Yes No X
============================================================
Applicant: ___________________________ _________________ Time Start: ________
NAME Docket No. Time Finish: ________
Performance Rating: SAT ____ UNSAT ____ Performance Time ___
Examiner: _____________________________ _____________________________/________
NAME SIGNATURE DATE
=============================================================
COMMENTS Page 2 of 12
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I
NRC EXAM 2013-302 Tools/Equipment/Procedures Needed:
Hard-hat, Safety Glasses, Hearing Protection Plant Approved Shoes Gloves ALARA considerations Note: Have a marked up copy of 1-SOI-62.01, 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 12
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I
NRC EXAM 2013-302 READ TO APPLICANT DIRECTION TO APPLICANT:
I will explain the initial conditions, which step(s) to simulate or discuss and provide initiating/operating cues.
NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM.
SIMULATE ALL MANIPULATIONS.
When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure that you indicate to me when you fully understand your task. To indicate that you have completed your assigned task return the cue sheet I provided you. To indicate that you have completed your assigned task return the cue sheet I provided you.
INITIAL CONDITIONS:
- 1. Unit 2 is conducting pre-operational testing.
- 2. Unit 1 is at 90% power.
- 3. Seal injection filter B is in service and Window 101-D RCP SEAL INJ FILTER A/B P HI is in alarm.
- 4. You are an AUO on shift.
INITIATING CUES:
The Unit Operator has directed you to swap seal injection filters per 1-SOI-62.01, CVCS-Charging and Letdown, Section 8.9.2, Replacing Filter B with Filter A.
You are to place A seal injection filter in service and remove B seal injection filter from service.
You are to notify the Unit Operator when the seal injection filter swap is complete.
Page 4 of 12
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I
NRC EXAM 2013-302 STEP/STANDARD 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 FILTER ___ SAT B DIFF PRESS [A5T/713], indicates P 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.
- 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 5 of 12
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I
NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT 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 [A5T/713]. 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:
Page 6 of 12
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I
NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 4: [4] SLOWLY OPEN 1-ISV-62-550, CVCS SEAL WTR INJ FILTER CRITICAL A OUT ISOL [A5T/713]. STEP STANDARD: ___ SAT 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 12
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I
NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 6: [6] CHECK P 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 gauge a value of 6 psid COMMENTS:
EXAMINER: Closing either 1-ISV-62-549, CVCS SEAL WTR INJ FILTER B OUT ISOL OR 1-ISV-62-547, CVCS SEAL WTR INJ FLTR B IN ISOL terminate flow through Seal Injection Filter B. As long as the applicant performs Step 7 or Step 8 the critical aspect will be satisfied.
STEP 7: [7] CLOSE 1-ISV-62-549, CVCS SEAL WTR INJ FILTER B OUT CRITICAL ISOL [A5T/713]. 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 only if Step 8 is not performed.
COMMENTS:
Page 8 of 12
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I
NRC EXAM 2013-302 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: ___ SAT 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 only if Step 7 is not performed.
COMMENTS:
STEP 9: [9] ENSURE 1-PDIS-62-97, CVCS SEAL WTR INJECTION ___ SAT FILTER A DIFF PRESS [A5T/713], indicates P less than 20 psid. ___ UNSAT STANDARD:
Applicant locates 1-PDIS-62-97, CVCS SEAL WTR INJECTION FILTER A DIFF PRESS and Filter As P is checked to be less than 20 psid on 1-PDIS-62-96.
Cue: After P check, indicate value of 12 psid on the gauge.
COMMENTS:
Page 9 of 12
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE I
NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT 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 12
I Handout Package for Applicant
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- 1. Unit 2 is conducting pre-operational testing.
- 2. Unit 1 is at 90% power.
- 3. Seal injection filter B is in service and Window 101-D RCP SEAL INJ FILTER A/B P HI is in alarm.
- 4. You are an AUO on shift.
INITIATING CUES:
The Unit Operator has directed you to swap seal injection filters per 1-SOI-62.01, CVCS-Charging and Letdown, Section 8.9.2, Replacing Filter B with Filter A.
You are to place A seal injection filter in service and remove B seal injection filter from service.
You are to notify the Unit Operator when the seal injection filter swap is complete.
I
Watts Bar Nuclear Plant Unit 1 System Operating Instruction 1-SOI-62.01 CVCS-Charging and Letdown Revision 0000 Quality Related Level of Use: Continuous Use Effective Date: 04-08-2014 Responsible Organization: OPS, Operations Prepared By: John Killian Approved By: Mark Marinac
WBN CVCS-Charging and Letdown 1-SOI-62.01 Unit 1 Rev. 0000 Page 2 of 108 Revision Log Revision or Change Effective Affected Page Number Date Numbers Description of Revision/Change 0000 04/08/14 All Incorporated changes associated with DCN 52853, which installed portions of the Distributed Control System (DCS).
Minor/editorial changes include, but NOT limited to the following:
- Added Unit 1 designator to procedure number and reset revision to 0000. This procedure was prepared using Rev. 65 of SOI-62.01 which will be cancelled.
- Standardized use of PZR.
- Updated procedures referenced in body of procedure to reflect Unit 1, Unit 2, and Common 0 designations, iaw ODM 23, in preparation for two unit operation.
- Added Unit 1 designator to Attachments and reset revision to 0000. Attachments were revised using Rev. 60 of Att. 1P and Rev. 62 of Att. 1V of SOI-62.01.
Attachments will be cancelled.
WBN CVCS-Charging and Letdown 1-SOI-62.01 Unit 1 Rev. 0000 Page 3 of 108 Table of Contents
1.0 INTRODUCTION
.......................................................................................................... 5 1.1 Purpose ........................................................................................................................ 5 1.2 Scope............................................................................................................................ 5
2.0 REFERENCES
............................................................................................................. 6 2.1 Performance References .............................................................................................. 6 2.2 Developmental References........................................................................................... 7 3.0 PRECAUTIONS AND LIMITATIONS ........................................................................... 9 4.0 PREREQUISITE ACTIONS ........................................................................................ 13 4.1 Preliminary Actions ..................................................................................................... 13 4.2 Field Preparations ....................................................................................................... 13 4.3 Approvals and Notifications ........................................................................................ 14 5.0 STARTUP ................................................................................................................... 15 5.1 Establishing Letdown and Charging ........................................................................... 15 5.2 Establishing RCP Seal Injection ................................................................................. 23 6.0 NORMAL OPERATION .............................................................................................. 26 6.1 Normal Operating Parameters .................................................................................... 28 6.2 Swapping CCPs .......................................................................................................... 31 6.3 Adjusting Letdown Flow .............................................................................................. 34 7.0 SHUTDOWN ............................................................................................................... 37 7.1 Unit Shutdown ............................................................................................................ 37 7.2 Charging System Shutdown ....................................................................................... 39 8.0 INFREQUENT OPERATIONS .................................................................................... 41 8.1 Remove Charging and Letdown ................................................................................. 41 8.2 Reestablish Charging and Letdown ............................................................................ 43 8.3 Establishing Excess Letdown ..................................................................................... 49 8.4 Securing Excess Letdown........................................................................................... 51 8.5 Local Control of 1-FCV-62-93, CHARGING HEADER FLOW..................................... 52 8.6 Bypassing 1-FCV-62-89, CHARGING FLOW CONT, for Local Control ...................... 54 8.7 Hydrogen Concentration Control ................................................................................ 56 8.8 Oxygen Control: Hydrazine Addition ........................................................................... 59
WBN CVCS-Charging and Letdown 1-SOI-62.01 Unit 1 Rev. 0000 Page 4 of 108 Table of Contents (continued) 8.9 Seal Injection Filter Swap ........................................................................................... 63 8.9.1 Replacing Filter A with Filter B ...................................................................... 63 8.9.2 Replacing Filter B with Filter A ...................................................................... 65 8.10 pH Control: LiOH Addition........................................................................................... 66 8.11 Establishing VCT N2 Atmosphere .............................................................................. 70 8.12 Replace VCT H2 With N2 ........................................................................................... 74 8.13 Hydrogen Peroxide Addition ....................................................................................... 77 8.14 Alternating Charging Pump Suction To and From the RWST Using 1-LCV-62-135 And 136 ............................................................................................... 82 8.15 Bypassing 1-PCV-62-81, CVCS LETDOWN HX PRESS CNTL, for Local Control............................................................................................................... 84 8.16 Adjusting Hydrogen Regulator For Hydrogen Concentration Control ......................... 86 8.17 Bypassing 1-FCV-62-93, CVCS CHARGING HEADER FLOW, for Local Control ........................................................................................................................ 87 8.18 Bypassing Reactor Coolant Filter ............................................................................... 89 8.19 Restoring Reactor Coolant Filter to Normal ................................................................ 91 8.20 Burping the VCT ......................................................................................................... 93 8.21 Adjusting Letdown Heat Exchanger Outlet Temperature ............................................ 96 8.22 Placing 1-HIC-62-93A in Auto with a Deviation........................................................... 97 8.23 Bypassing Seal Water Return Filter ............................................................................ 98 8.24 Restoring Seal Water Return Filter to Normal............................................................. 98 9.0 RECORDS .................................................................................................................. 99 9.1 QA Records ................................................................................................................ 99 9.2 Non-QA Records ........................................................................................................ 99 Appendix A: Inaccessible Valve Position Verification .............................................. 100 Source Notes........................................................................................... 108 EXTERNAL ATTACHMENTS P: Power Checklist 1-62.01-1P V: Valve Checklist 1-62.01-1V
WBN CVCS-Charging and Letdown 1-SOI-62.01 Unit 1 Rev. 0000 Page 5 of 108
1.0 INTRODUCTION
1.1 Purpose To provide the instructions for operation of the Chemical and Volume Control System (CVCS).
1.2 Scope This Instruction includes operation of the following CVCS subsystems:
A. Charging B. Letdown C. RCP Seal Injection D. Chemical Addition
WBN CVCS-Charging and Letdown 1-SOI-62.01 Unit 1 Rev. 0000 Page 6 of 108
2.0 REFERENCES
2.1 Performance References A. 0-PI-OPS-17.0, 18 Month Locked Valve Verification B. 0-PI-OPS-17.1, 18 Month Locked Breaker Verification C. 1-SI-63-10.1-A, ECCS Pump and Discharge Pipe Venting-Train A Inside Containment D. 1-SI-63-10-B, ECCS Pumps Venting-Train B E. 1-SI-68-33, Measurement of Controlled Leakage of the Reactor Coolant Pump Seals F. 1-TRI-62-901, ASME Section XI Inservice System Pressure Test CVCS Inside Containment G. GOI-7, Generic Equipment Operating Guidelines H. 1-SOI-62.02, Boron Concentration Control I. 1-SOI-62.04, CVCS Purification Systems J. 0-SOI-70.01, Component Cooling System (CCS)
K. 1-SOI-74.01, Residual Heat Removal System (RHR)
L. 0-SOI-77.01, Liquid Waste Disposal M. 0-SOI-77.02, Waste Gas Disposal N. 0-SOI-77.04, Auxiliary Building Nitrogen System O. 0-SOI-77.09, Auxiliary Building Hydrogen System P. 0-SOI-81.01, Primary Makeup Water System Q. 0-SOI-90.01, Radiation Monitoring System R. 1-SOI-235.01, 120V AC Vital Power System 1-I S. 1-SOI-235.03, 120V AC Vital Power System 1-III T. 1-SOI-235.04, 120V AC Vital Power System 1-IV U. 0-SOI-236.01, 125V DC Vital Battery Board I
WBN CVCS-Charging and Letdown 1-SOI-62.01 Unit 1 Rev. 0000 Page 7 of 108 2.1 Performance References (continued)
V. 0-SOI-236.02, 125V DC Vital Battery Board II W. CM-6.24, Sampling CVCS Mixed Bed Demineralizers X. CM-5.09, Shutdown Primary Chemistry Control Y. TI-4, Part II, Plant Curve Book, Tank Curves, Turbine Curves Z. TI-59, Boron Tables AA. 1-SI-63-10.2-A, ECCS Pump and Discharge Pipe Venting-Train A Outside Containment 2.2 Developmental References A. GO-1, Plant Startup from Cold Shutdown to Hot Standby B. GO-2, Plant Startup from Hot Standby to Minimum Load C. GO-3, Plant Shutdown from Minimum Load to Cold Shutdown D. 1-SI-0-8, Monitoring Component Cyclic or Transient Limits E. N3-62-4001, Chemical and Volume Control System F. SOI-68.01, Reactor Coolant System G. TVA Drawings:
- 1. 1-45N600-62 Series
- 2. 45N706-1, -3
- 3. 45W751-1, -7
- 4. 45N760-62 Series
- 5. 45N1645-1, -2
- 6. 47B601-62
- 7. 47W809-1
- 8. 47W809-2
- 9. 47W809-9 -3, -6
- 10. 47W859-2
WBN CVCS-Charging and Letdown 1-SOI-62.01 Unit 1 Rev. 0000 Page 8 of 108 2.2 Developmental References (continued)
H. Vendor Manual WBN-VTM-F180-5350, Vendor Technical Manual for Foxboro Invensys Distributed Control System.
I. Vendor Drawing 08F734235-FD-1600 series, Foxboro Invensys Functional Diagrams
WBN CVCS-Charging and Letdown 1-SOI-62.01 Unit 1 Rev. 0000 Page 9 of 108 3.0 PRECAUTIONS AND LIMITATIONS NOTE During power changes, letdown should be maximized when possible to reduce Crud Induced Power Shift, also known as, Axial Offset Anomaly.
A. Maximum letdown flow is 120 gpm.
B. If Letdown Heat Exchanger (LDHX) outlet temperature reaches 140°F, demineralizer resin damage could occur.
C. During summer months, the lowest achievable letdown heat exchanger outlet temperature is limited by the CCS temperature, which in turn is limited by river temperature (via ERCW cooling to the CCS heat exchanger). The lowest achievable letdown heat exchanger outlet temperature is approximately 6 degrees higher than the river temperature. Attempting to operate with a letdown temperature less than 6 degrees higher than the river temperature will force 1-TCV-70-192 full open rendering 1-HIC-62-78A ineffective. Letdown temperature will then vary slightly as river temperature varies throughout the day. This causes slight changes in reactor power as boron affinity changes in the demin beds as the letdown temperature changes. Therefore, 1-HIC-62-78A, LETDOWN HX OUTLET TEMP TCV-70-192 CNTL should not be allowed to control 1-TCV-70-192 at its full open position.
D. If Reactor Coolant (RC) filter is bypassed, flow through demins should be secured or diverted to the HUT to prevent resin entering RCS if the demin resin screen fails.[C.2]
E. Charging and Letdown are in service together. If Letdown isolates or Charging is lost, the other must be isolated (see exception below). If Charging is lost and Letdown remains in service, flashing or lifting of the letdown relief could occur.
If Letdown is lost and Charging remains in service, thermal shock or a positive reactivity insertion could result from cold water entering RCS.
EXCEPTION: If all the following conditions exist:
- 1. Any RCP Thermal Barrier Out Of Service
- 2. In service Charging Pump trips
- 3. RCP seal flow is required.
Then the Operator may immediately start an available charging pump.
F. RCP seal damage can occur if VCT press is below 15 psig with RCPs running.
WBN CVCS-Charging and Letdown 1-SOI-62.01 Unit 1 Rev. 0000 Page 10 of 108 3.0 PRECAUTIONS AND LIMITATIONS (continued)
G. A pneumatic relay, added to panel L-112 to limit the signal to 1-FCV-62-93, ensures 32 to 35 gpm RCP seal injection flow in the event of an Appendix R fire, by preventing valve closure. This pneumatic relay has a bypass valve on panel L-112 to allow effective flow control at low RCS pressures (i.e., heat-up and cool-down).
H. Operating CCPs on mini-flow for extended periods could cause pump damage due to the small amount of water being re-circulated at high pressure.
I. H2 concentration should be maintained 25 to 50 cc/kg (STP) of water when plant is at power.
J. Safety practices are required when handling hazardous chemicals. Face shields, rubber gloves, and protective clothing must be worn in preparation, handling, and sampling operations.
K. Lithium Hydroxide is a strong caustic and a strong irritant to the eyes, skin and membranes. It is also toxic by ingestion and inhalation. Precautions must be taken to prevent direct contact with or ingestion or inhalation of this chemical.
L. After each start of a CCP, ensure ACB closing spring recharges.
M. Explosive mixtures of hydrogen and oxygen in the VCT and the HUTs must be avoided at all times. The oxygen content in the tanks must NOT exceed 2% by volume when hydrogen concentration in the tanks exceeds 4% by volume.
Nitrogen gas may be used for purging.
N. Concurrent closure of 1-ISV-62-953 and 2-ISV-62-953 is prohibited to ensure a discharge path for the VCT and BIT relief valves.
O. When operating at a minimum charging flow rate, check that the letdown flow is being cooled below 380°F. If NOT, raise charging and/or reduce letdown flow to lower letdown temperature.
P. After significant change in letdown and charging flow, RCP seal injection flows require checking, and adjusting if necessary.
Q. Alternating between the Alternate and Normal Charging paths should be done at cold shutdown when possible to avoid charging line transients.
R. Pressure downstream of the letdown orifices must remain high enough to preclude flashing.
S. Pressure drop across #1 seals should be checked to ensure seal injection flow is adequate and labyrinth pressure drop is normal before RCS pressure exceeds approximately 380 psig.
WBN CVCS-Charging and Letdown 1-SOI-62.01 Unit 1 Rev. 0000 Page 11 of 108 3.0 PRECAUTIONS AND LIMITATIONS (continued)
T. During Cold Shutdown (Mode 5), auxiliary spray is used to provide a rapid means of cooling down the pressurizer near the end of plant cool-down. During this mode of operation, charging flow-rate shall be controlled to a maximum of 232 gpm to ensure auxiliary spray flow-rate does NOT exceed 200 gpm.
U. A minimum charging flow of 15 gpm through the regenerative HX should be maintained at all times.
V. When water Solid with letdown from RHR, FCV-62-83 RHR letdown should be full OPEN, and RCS press controlled by PCV-62-81, LETDOWN PRESS CONTROL. The normal letdown system including all orifices must remain in service.
W. Early notification of Instrument Maintenance will ensure instruments are available to support system operations.
X. Instrument Maintenance Department should be notified to ensure required instrumentation is placed in service to support system operation.
Y. Work in Radiologically Controlled Areas (RCAs) requires the use of existing Radiation Work Permits (RWPs) and may require additional ALARA Preplans.
Failure to follow posted Rad control requirements can cause unnecessary radiation exposure. Radiation Protection should be notified of work having the potential to change radiological conditions.
Z. When isolating any boron injection flow path to the core, care must be taken to ensure that the remaining available boron injection flow-paths are sufficient to meet the requirements of TR3.1.1 (Modes 4, 5, & 6), and TR3.1.2 (Modes 1, 2,
& 3).[C.8]
AA. If hydrogen peroxide is to be added prior to refueling, the RCS should be borated to the refueling boron concentration as soon as possible to achieve acidic conditions by at least 400°F.
BB. If the primary system is to be opened, then Hydrazine must NOT be added to the RCS during any phase of unit cool-down or shutdown.
CC. Before starting idle CCPs, possible reactivity effects from dilution or boration due to water trapped in local piping must be considered, e.g., different CB at last pump run.
WBN CVCS-Charging and Letdown 1-SOI-62.01 Unit 1 Rev. 0000 Page 12 of 108 3.0 PRECAUTIONS AND LIMITATIONS (continued)
DD. VCT Hydrogen and Nitrogen supply pressure limit of 15-20 psi is established to provide margin associated with APP R manual operator actions. The analysis assumes this pressure range while at the low end of VCT level range (~20%
level). It is anticipated that pressure may increase above 20 psi when evolutions that cause the VCT level to increase are in progress (i.e. burping the VCT or during boration/dilution evolutions) as a result of the raising VCT liquid level compressing the gas volume.
EE. Steps that directly affect reactivity will be preceded with the Greek symbol ().
FF. Steps within this instruction may require venting, draining or breaching radioactive components or systems to the atmosphere. Appropriate radiation protection controls must be established to prevent the spread of contamination and avoid the generation of airborne radioactivity.
WBN CVCS-Charging and Letdown 1-SOI-62.01 Unit 1 Rev. 0000 Page 65 of 108 Date ________ INITIALS 8.9.2 Replacing Filter B with Filter A 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 hand-wheel, which may result in unwanted rapid opening of the valve and loss of seal injection flow.[C.10]
[1] CHECK 1-PDIS-62-96, CVCS SEAL WTR INJECTION FILTER B DIFF PRESS [A5T/713], indicates P greater than 20 psid.(N/A if filter changed at discretion of Unit SRO) ________
[2] ENSURE RCP standpipe levels NORMAL (HI/LO alarm clear). ________
[3] SLOWLY OPEN 1-ISV-62-548, CVCS SEAL WTR INJ FLTR A IN ISOL [A5T/713]. ________
[4] SLOWLY OPEN 1-ISV-62-550, CVCS SEAL WTR INJ FILTER A OUT ISOL [A5T/713]. ________
[5] ENSURE RCP seal injection flow between 8 and 13 gpm. ________
[6] CHECK P rose on A filter prior to isolating B filter. ________
[7] CLOSE 1-ISV-62-549, CVCS SEAL WTR INJ FILTER B OUT ISOL [A5T/713]. ________
[8] CLOSE 1-ISV-62-547, CVCS SEAL WTR INJ FLTR B IN ISOL
[A5T/713]. ________
[9] ENSURE 1-PDIS-62-97, CVCS SEAL WTR INJECTION FILTER A DIFF PRESS [A5T/713], indicates P less than 20 psid. ________
[10] INITIATE SR to replace clogged filter, and NOTIFY UO to record SR number.
(N/A if open WO available for filter replacement) ________
End of Section
Watts Bar Nuclear Plant NRC EXAM 2015301 System JPM J
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J
NRC EXAM 2013-302 EVALUATION SHEET Task: PERFORM 1-ES-1.1, SI TERMINATION, APPENDIX E, OPERATION OF MOVS AT TRAIN A ELECTRICAL BOARDS.
Alternate Path: n/a Facility JPM #: New Safety Function: 3 Title: Reactor Inventory Control.
K/A 006 A2.08 Ability to (a) predict the impacts of the following malfunctions or operations on the ECCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Effect of electric power loss on valve position Rating(s): 3.0/3.3 CFR: 41.5 / 45.5 Evaluation Method: Simulator In-Plant X Classroom
References:
1-ES-1.1, SI TERMINATION, Rev. 0002.
Task Number: AUO-113-ES-1.1-004 Title: Perform ES-1.1, Appendix E/F, Operation of MOVs at Train A/B Electrical Board.
Task Standard: Applicant performs 1-ES-1.1, SI Termination, Appendix E, Operation of MOVs at Train A Electrical Boards, and describes local manipulations associated with 1-FCV-63-26, 1-FCV-62-132, AND 1-FCV-62-135.
Validation Time: 15 minutes Time Critical: Yes No X
============================================================
Applicant: ___________________________ _________________ Time Start: ________
NAME Docket No. Time Finish: ________
Performance Rating: SAT ____ UNSAT ____ Performance Time ___
Examiner: _____________________________ _____________________________/________
NAME SIGNATURE DATE
=============================================================
COMMENTS Page 2 of 18
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J
NRC EXAM 2013-302 Tools/Equipment/Procedures Needed:
Hard-hat Safety Glasses Hearing Protection Plant Approved Shoes Gloves ALARA considerations Start this JPM at elevation 713 RP Table.
Page 3 of 18
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J
NRC EXAM 2013-302 READ TO APPLICANT DIRECTION TO APPLICANT:
I will explain the initial conditions, which step(s) to simulate or discuss and provide initiating/operating cues.
NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM.
SIMULATE ALL MANIPULATIONS.
When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure that you indicate to me when you fully understand your task. To indicate that you have completed your assigned task return the cue sheet I provided you.
INITIAL CONDITIONS:
- 1. Unit 1 experienced an inadvertent safety injection (SI) actuation.
- 2. The control room crew is performing 1-ES-1.1, SI Termination.
- 3. You are an AUO assigned to the shift.
INITIATING CUES:
The Unit Operator has directed you perform 1-ES-1.1, SI Termination, Appendix E, Operation of MOVs at Train A Electrical Board, Steps A.3 through A.5.
Notify the Unit Operator when 1-ES-1.1, SI Termination, Appendix E, Operation of MOVs at Train A Electrical Board, assigned steps are complete.
Page 4 of 18
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J
NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT START TIME: _______
STEP 1: A. IF any of the following valves requires manipulation from the CRITICAL Train A Rx MOV Bd, THEN PERFORM the applicable substep STEP when directed by the UO/SRO: ___ SAT
- 3. 1-FCV-63-26, BIT Outlet Valve
___ UNSAT
- b. PLACE 1-XS-63-26 to AUX position.
STANDARD:
Applicant locates the 480V Rx MOV Board 1A1-A, Breaker Compartment 11D.
Applicant may state that he would contact the Main Control Room to inform them that the alarm indicating a switch is in AUX (Window 149-B, 480V RX MOV BD 1A1-A/1A2-A) will be received when 1-XS-63-26 is moved to the AUX position.
Applicant locates 1-XS-63-26 handswitch and states that the handswitch must be rotated to the RIGHT to the AUX position.
CUE: After the applicant has described how to position 1-XS-63-26, state the handswitch is in the selected position.
Step is critical to properly position 1-FCV-63-26 in support of 1-ES-1.1, SI Termination.
COMMENTS:
Page 5 of 18
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J
NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 2: A. IF any of the following valves requires manipulation from the CRITICAL Train A Rx MOV Bd, THEN PERFORM the applicable substep STEP when directed by the UO/SRO: ___ SAT
- 3. 1-FCV-63-26, BIT Outlet Valve
___ UNSAT
- c. PLACE 1-HS-63-26C to CLOSE position.
STANDARD:
Applicant locates 1-HS-63-26C handswitch and states that the handswitch must be rotated to the LEFT to the CLOSE position.
(Critical)
CUE: After the applicant has described how to position 1-HS-63-26C, state the handswitch is in the selected position.
Step is critical to properly position 1-FCV-63-26 in support of 1-ES-1.1, SI Termination.
COMMENTS:
Page 6 of 18
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J
NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 3: A. IF any of the following valves requires manipulation from the ___ SAT Train A Rx MOV Bd, THEN PERFORM the applicable substep when directed by the UO/SRO: ___ UNSAT
- 3. 1-FCV-63-26, BIT Outlet Valve
- d. VERIFY 1-FCV-63-26 CLOSE.
STANDARD:
Applicant locates the valve position indicating lights on Compartment 11D. Applicant states that RED light would be DARK and the GREEN light LIT, indicating the valve is CLOSED.
CUE: After the applicant has described the expected state of the valve indicating lights, the lights are in the described state.
COMMENTS:
Page 7 of 18
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J
NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 4: A. IF any of the following valves requires manipulation from the ___ SAT Train A Rx MOV Bd, THEN PERFORM the applicable substep when directed by the UO/SRO: ___ UNSAT
- 3. 1-FCV-63-26, BIT Outlet Valve
- e. WHEN directed by the UO or SRO, THEN
- PLACE 1-HS-63-26C in NORMAL position.
- PLACE 1-XS-63-26 in NORMAL position.
STANDARD:
Applicant requests direction from the US/SRO concerning the desired position of 1-HS-63-26C and 1-XS-63-26.
CUE: When contacted as the US/SRO, inform the applicant that the switches are to remain in their current positions.
EXAMINER: This step is critical ONLY if the applicant elects to position 1-HS-62-26C back to the NORMAL position.
COMMENTS:
CAUTION VCT outlet valves 1-LCV-62-132 and 1-LCV-62-133 must be open prior to closing RWST valves 1-LCV-62-135 and 1-LCV-62-136 to prevent loss of suction to the CCPs.
Page 8 of 18
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J
NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 5: A. IF any of the following valves requires manipulation from the CRITICAL Train A Rx MOV Bd, THEN PERFORM the applicable substep STEP when directed by the UO/SRO:
___ SAT
- 4. 1-LCV-62-132, VCT Outlet Valve
___ UNSAT
- b. PLACE 1-XS-62-132 to AUX position.
STANDARD:
Applicant locates the 480V Rx MOV Board 1A1-A, Breaker Compartment 8B.
Applicant may state that he would contact the Main Control Room to inform them that the alarm indicating a switch is in AUX (Window 149-B, 480V RX MOV BD 1A1-A/1A2-A) will be received when 1-XS-62-132 is moved to the AUX position.
Applicant locates 1-XS-62-132 handswitch and states that the handswitch must be rotated to the RIGHT to the AUX position.
CUE: After the applicant has described how to position 1-XS-62-132, state the handswitch is in the selected position.
Step is critical to properly position 1-FCV-62-132 in support of 1-ES-1.1, SI Termination.
COMMENTS:
Page 9 of 18
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J
NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 6: A. IF any of the following valves requires manipulation from the CRITICAL Train A Rx MOV Bd, THEN PERFORM the applicable substep STEP when directed by the UO/SRO:
___ SAT
- 4. 1-LCV-62-132, VCT Outlet Valve
___ UNSAT
- c. PLACE 1-HS-62-132C to OPEN position.
STANDARD:
Applicant locates 1-HS-62-132C handswitch and states that the handswitch must be rotated to the RIGHT to the OPEN position.
(Critical)
CUE: After the applicant has described how to position 1-HS-62-132C, state the handswitch is in the selected position.
Step is critical to properly position 1-FCV-62-132 in support of 1-ES-1.1, SI Termination.
COMMENTS:
Page 10 of 18
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J
NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 7: A. IF any of the following valves requires manipulation from the
___ SAT Train A Rx MOV Bd, THEN PERFORM the applicable substep when directed by the UO/SRO:
___ UNSAT
- 4. 1-LCV-62-132, VCT Outlet Valve
- d. VERIFY 1-FCV-62-132 OPEN.
STANDARD:
Applicant locates the valve position indicating lights on Compartment 8B.
Applicant states that RED light would be LIT and the GREEN light DARK, indicating the valve is OPEN.
CUE: After the applicant has described the expected state of the valve indicating lights, the lights are in the described state.
COMMENTS:
Page 11 of 18
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J
NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 8: A. IF any of the following valves requires manipulation from the
___ SAT Train A Rx MOV Bd, THEN PERFORM the applicable substep when directed by the UO/SRO:
___ UNSAT
- 4. 1-LCV-62-132, VCT Outlet Valve
- e. WHEN directed by the UO or SRO, THEN
- PLACE 1-HS-62-132C in P AUTO position.
- PLACE 1-XS-62-132 in NORMAL position.
STANDARD:
Applicant requests direction from the US/SRO concerning the desired position of 1-HS-63-132C and 1-XS-63-132.
CUE: When contacted as the US/SRO, inform the applicant that the switches are to remain in their current positions.
EXAMINER: This step is critical ONLY if the applicant elects to position 1-HS-62-132C back to the NORMAL position.
COMMENTS:
Page 12 of 18
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J
NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 9: A. IF any of the following valves requires manipulation from the CRITICAL Train A Rx MOV Bd, THEN PERFORM the applicable substep STEP when directed by the UO/SRO:
___ SAT
___ UNSAT
- b. PLACE 1-XS-62-133 to AUX position.
STANDARD:
Applicant locates the 480V Rx MOV Board 1A1-A, Breaker Compartment 9A.
Applicant may state that he would contact the Main Control Room to inform them that the alarm indicating a switch is in AUX (Window 149-B, 480V RX MOV BD 1A1-A/1A2-A) will be received when 1-XS-62-135 is moved to the AUX position.
Applicant locates 1-XS-62-135 handswitch and states that the handswitch must be rotated to the RIGHT to the AUX position.
CUE: After the applicant has described how to position 1-XS-62-135, state the handswitch is in the selected position.
Step is critical to properly position 1-FCV-62-135 in support of 1-ES-1.1, SI Termination.
COMMENTS:
Page 13 of 18
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J
NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 10: A. IF any of the following valves requires manipulation from the CRITICAL Train A Rx MOV Bd, THEN PERFORM the applicable substep STEP when directed by the UO/SRO:
___ SAT
___ UNSAT
- c. PLACE 1-HS-62-135C to CLOSE position.
STANDARD:
Applicant locates 1-XS-62-135C handswitch and states that the handswitch must be rotated to the LEFT to the CLOSE position.
(Critical)
CUE: After the applicant has described how to position 1-XS-62-135C, state the handswitch is in the selected position.
Step is critical to properly position 1-FCV-62-135 in support of 1-ES-1.1, SI Termination.
COMMENTS:
Page 14 of 18
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J
NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 11: A. IF any of the following valves requires manipulation from the ___ SAT Train A Rx MOV Bd, THEN PERFORM the applicable substep when directed by the UO/SRO: ___ UNSAT
- d. VERIFY 1-FCV-63-135 CLOSE.
STANDARD:
Applicant locates the valve position indicating lights on Compartment 9A.
Applicant states that RED light would be DARK and the GREEN light LIT, indicating the valve is CLOSED.
CUE: After the applicant has described the expected state of the valve indicating lights, the lights are in the described state.
COMMENTS:
Page 15 of 18
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J
NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT STEP 12: A. IF any of the following valves requires manipulation from the ___ SAT Train A Rx MOV Bd, THEN PERFORM the applicable substep when directed by the UO/SRO: ___ UNSAT
- e. WHEN directed by the UO or SRO, THEN
- PLACE 1-HS-62-135C in P AUTO position.
- PLACE 1-XS-62-135 in NORMAL position.
STANDARD:
Applicant requests direction from the UO or SRO concerning the desired position of 1-HS-63-135C and 1-XS-63-135.
CUE: When contacted as the US/SRO, inform the applicant that the switches are to remain in their current positions.
EXAMINER: This step is critical ONLY if the applicant elects to position 1-HS-62-135C back to the NORMAL position.
COMMENTS:
STEP 13: Applicant reports that 1-ES-1.1, SI Termination, Appendix E, ___ SAT Steps 3 through 5 are complete STANDARD: ___ UNSAT Applicant reports to the Unit Operator that 1-ES-1.1, SI Termination, Appendix E, Steps A.3 through A.5 are complete.
CUE: Repeat back information provided by the applicant.
COMMENTS:
END OF TASK STOP TIME ________
Page 16 of 18
J Handout Package for Applicant
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- 1. Unit 1 experienced an inadvertent safety injection (SI) actuation.
- 2. The control room crew is performing 1-ES-1.1, SI Termination.
- 3. You are an AUO assigned to the shift.
INITIATING CUES:
The Unit Operator has directed you perform 1-ES-1.1, SI Termination, Appendix E, Operation of MOVs at Train A Electrical Board, Steps A.3 through A.5.
Notify the Unit Operator when 1-ES-1.1, SI Termination, Appendix E, Operation of MOVs at Train A Electrical Board, assigned steps are complete.
J
WBN SI Termination 1-ES-1.1 Unit 1 Rev. 0002 Appendix E (Page 1 of 3)
Operation of MOVs at Train A Electrical Board 1.0 INSTRUCTIONS A. IF any of the following valves requires manipulation from the Train A Rx MOV Bd, THEN PERFORM the applicable substep when directed by the UO/SRO:
- 1. 1-FCV-62-90, Charging Isolation Valve
- b. PLACE 1-XS-62-90 to AUX position.
- c. PLACE 1-HS-62-90C to OPEN position.
- d. VERIFY 1-FCV-62-90 OPEN.
- e. WHEN directed by the UO or SRO, THEN
- PLACE 1-HS-62-90C in NORMAL position.
- PLACE 1-XS-62-90 in NORMAL position.
- 2. 1-FCV-62-63, Seal Return Valve
- b. PLACE 1-XS-62-63 to AUX position.
- c. PLACE 1-HS-62-63C to OPEN position.
- d. VERIFY 1-FCV-62-63 OPEN.
- e. WHEN directed by the UO or SRO, THEN
- PLACE 1-HS-62-63C in NORMAL position.
- PLACE 1-XS-62-63 in NORMAL position.
Page 28 of 36
WBN SI Termination 1-ES-1.1 Unit 1 Rev. 0002 Appendix E (Page 2 of 3)
Operation of MOVs at Train A Electrical Board 1.0 INSTRUCTIONS (continued)
- 3. 1-FCV-63-26, BIT Outlet Valve
- b. PLACE 1-XS-63-26 to AUX position.
- c. PLACE 1-HS-63-26C to CLOSE position.
- d. VERIFY 1-FCV-63-26 CLOSE.
- e. WHEN directed by the UO or SRO, THEN
- PLACE 1-HS-63-26C in NORMAL position.
- PLACE 1-XS-63-26 in NORMAL position.
CAUTION VCT outlet valves 1-LCV-62-132 and 1-LCV-62-133 must be open prior to closing RWST valves 1-LCV-62-135 and 1-LCV-62-136 to prevent loss of suction to the CCPs.
- 4. 1-LCV-62-132, VCT Outlet Valve
- b. PLACE 1-XS-62-132 to AUX position.
- c. PLACE 1-HS-62-132C to OPEN position.
- d. VERIFY 1-FCV-62-132 OPEN.
- e. WHEN directed by the UO or SRO, THEN
- PLACE 1-HS-62-132C in P AUTO. position.
- PLACE 1-XS-62-132 in NORMAL position.
Page 29 of 36
WBN SI Termination 1-ES-1.1 Unit 1 Rev. 0002 Appendix E (Page 3 of 3)
Operation of MOVs at Train A Electrical Board 1.0 INSTRUCTIONS (continued)
- b. PLACE 1-XS-62-135 to AUX position.
- c. PLACE 1-HS-62-135C to CLOSE position.
- d. VERIFY 1-FCV-62-135 CLOSED.
- e. WHEN directed by the UO or SRO, THEN
- PLACE 1-HS-62-135C in P AUTO. position.
- PLACE 1-XS-62-135 in NORMAL position.
Page 30 of 36
Watts Bar Nuclear Plant 2015301 NRC Exam System JPM K
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K
2015-301 NRC Exam EVALUATION SHEET Task: Perform 1-AOI-15, Loss of Component Cooling Water (CCS), Attachment 1.
Alternate Path: None Facility JPM #: 3-OT-JPMR022 Modified Safety Function: 8 Title: Plant Service Systems K/A 008 A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: High/low surge tank level Rating(s): 3.2/3.5 CFR: 41.5 / 43.5 /45.3 / 45.13 Evaluation Method: Simulator In-Plant X Classroom
References:
1-AOI-15, Loss of Component Cooling Water (CCS), Rev 6.
Task Number: AUO-067-AOI-15-001 Title: Align ERCW to CCP 1A-A Lube Oil Cooler.
Task Standard: Using the material provided, the applicant performs actions of 1-AOI-15, Loss of Component Cooling (CCS), Attachment 1, Alignment of ERCW to CCP 1A-A Lube Oil Coolers.
Validation Time: 15 minutes Time Critical: Yes No X
===============================================================
Applicant: ___________________________ _________________ Time Start: ________
NAME Docket No. Time Finish: ________
Performance Rating: SAT ____ UNSAT ____ Performance Time ___
Examiner: _____________________________ _____________________________/________
NAME SIGNATURE DATE
===============================================================
COMMENTS Page 2 of 12
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K
2015-301 NRC Exam Tools/Equipment/Procedures Needed:
Hard-hat Safety Glasses Double Hearing Protection High Noise Dosimetry Plant Approved Shoes Gloves ALARA considerations Note: Have a copy of 1-AOI-15, Loss of Component Cooling (CCS), Attachment 1, Alignment of ERCW to CCP 1A-A Lube Oil Coolers to give to the applicant.
Note: START THIS JPM AT THE RADWASTE AUO DESK Page 3 of 12
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K
2015-301 NRC Exam READ TO APPLICANT DIRECTION TO APPLICANT:
I will explain the initial conditions, which step(s) to simulate or discuss and provide initiating/operating cues.
NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM.
SIMULATE ALL MANIPULATIONS.
When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure that you indicate to me when you fully understand your task. To indicate that you have completed your assigned task return the cue sheet I provided you. To indicate that you have completed your assigned task return the cue sheet I provided you.
INITIAL CONDITIONS:
- 1. A leak has developed on the Component Cooling Water System.
- 2. 1A CCS Surge Tank level has dropped to less than 10%.
- 3. You are an extra operator assigned to the shift.
INITIATING CUES:
Using the materials provided, the Unit Operator directs you to perform 1-AOI-15, Loss of Component Cooling Water (CCS), Attachment 1, Alignment of ERCW to CCP 1A-A Lube Oil Coolers.
Inform the Unit Operator when Attachment 1 is complete.
Page 4 of 12
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _______
CAUTION CCP may survive for only 10 to 12 minutes after loss of CCS to lube oil cooler.
NOTES
- 1) This page is reproduced on a placard and posted in the CCP 1A-A pump room. This placard must be revised if the instructions on this page are revised. A change to the revision number or page number does NOT constitute a revision to this attachment.
- 2) All valves are located in CCP 1A-A room except 1-ISV-67-602A, CVCS CCP ROOM CLR 1A-A ERCW RET ISOL, which is outside the room [A4T/692]
STEP 1: 1. CLOSE 1-ISV-67-602A, CVCS CCP ROOM CLR 1A-A ERCW CRITICAL RET ISOL [A4T/692]. STEP STANDARD: ___ SAT The applicant locates 1-ISV-67-602A, CVCS CCP ROOM CLR 1A-A ERCW RET ISOL and describes that to close the valve, the orange ___ UNSAT handle must be pulled 90° (aligned perpendicular to the pipe.)(Critical).
This step is critical to properly align the flowpath.
CUE: After the applicant has demonstrated the method for closing 1-ISV-67-602A, state that the handle is perpendicular to the pipe.
COMMENTS:
Page 5 of 12
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT STEP 2: 2. CLOSE 1-ISV-70-553A, CCP 1A-A OIL COOLER CCS INLET CRITICAL ISOLATION. STEP
___ SAT STANDARD:
The applicant locates 1-ISV-70-553A, CCP 1A-A OIL COOLER CCS ___ UNSAT INLET ISOLATION and demonstrates that the handwheel must be rotated in the clockwise direction to close the valve. (Critical).
This step is critical to properly align the flowpath.
CUE: After the applicant has demonstrated the method for closing 1-ISV-67-602A, state that the handwheel rotated several turns in the clockwise direction and has stopped.
COMMENTS:
STEP 3: 3. CLOSE 1-THV-70-554A, CCP 1A-A OIL COOLERS CCS CRITICAL OUTLET THROTTLE. STEP STANDARD: ___ SAT The applicant locates 1-THV-70-554A, CCP 1A-A OIL COOLERS CCS OUTLET THROTTLE and demonstrates that the handwheel must be ___ UNSAT rotated in the clockwise direction to close the valve. (Critical).
This step is critical to properly align the flowpath.
CUE: After the applicant has demonstrated the method for closing 1-THV-70-554A, state that the handwheel rotated several turns in the clockwise direction and has stopped COMMENTS:
Page 6 of 12
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT CRITICAL STEP 4: 4. CLOSE 1-DRV-67-1017B, CCP OIL CLR ERCW SUP XTIE STEP HDR DRAIN.
STANDARD: ___ SAT The applicant locates 1-DRV-67-1017B, CCP OIL CLR ERCW SUP ___ UNSAT XTIE HDR DRAIN and demonstrates that the handwheel must be rotated in the clockwise direction to close the valve. (Critical).
This step is critical to properly align the flowpath.
CUE: After the applicant has demonstrated the method for closing 1-DRV-67-1017B, state that the handwheel rotated several turns in the clockwise direction and has stopped COMMENTS:
NOTE This step will result in discharging ERCW to the floor drain.
STEP 5: 5. ESTABLISH ERCW flow to lube oil cooler: CRITICAL
- a. OPEN 1-ISV-67-1015B, CCP OIL CLR ERCW SUP XTIE STEP ISOL. ___ SAT STANDARD: ___ UNSAT The applicant locates 1-ISV-67-1015B, CCP OIL CLR ERCW SUP XTIE ISOL and demonstrates that the handwheel must be rotated in the counter-clockwise direction to open the valve. (Critical).
This step is critical to properly align the flowpath.
CUE: After the applicant has demonstrated the method for opening 1-ISV-67-1015B, state that the handwheel rotated several turns in the counter-clockwise direction and has stopped COMMENTS:
Page 7 of 12
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT STEP 6: 5. ESTABLISH ERCW flow to lube oil cooler: CRITICAL
- b. OPEN 1-ISV-67-1016B, CCP OIL CLR ERCW SUP XTIE STEP ISOL. ___ SAT STANDARD: ___ UNSAT The applicant locates 1-ISV-67-1016B, CCP OIL CLR ERCW SUP XTIE ISOL and demonstrates that the handwheel must be rotated in the counter-clockwise direction to open the valve. (Critical).
This step is critical to properly align the flowpath.
CUE: After the applicant has demonstrated the method for opening 1-ISV-67-1016B, state that the handwheel rotated several turns in the counter-clockwise direction and has stopped COMMENTS:
Page 8 of 12
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT STEP 7: 5. ESTABLISH ERCW flow to lube oil cooler: CRITICAL
- c. ENSURE cap removed, THEN OPEN 1-DRV-70-782A, CCP STEP 1A-A OIL COOLERS CCS OUTLET DRAIN to establish ___ SAT ERCW flow to oil coolers.
___ UNSAT STANDARD:
The applicant locates the pipe cap just downstream of 1-DRV-70-782A, CCP 1A-A OIL COOLERS CCS OUTLET DRAIN and demonstrates that the pipe cap must be rotated in the counter-clockwise direction to be removed. (Critical).
This step is critical to properly align the flowpath.
CUE: After the applicant has demonstrated the method for removing the pipe cap, state that the pipe cap rotated several turns in the counter-clockwise direction and is removed.
The applicant locates 1-DRV-70-782A, CCP 1A-A OIL COOLERS CCS OUTLET DRAIN and demonstrates that the handwheel must be rotated in the counter-clockwise direction to open the valve. (Critical).
This step is critical to properly align the flowpath.
CUE: After the applicant has demonstrated the method for opening 1-DRV-70-782A, state that the handwheel rotated several turns in the counter-clockwise direction and has stopped.
CUE: If asked, provided that pipe cap was removed, water is gushing into the floor drain from the hose fitting connected to the line.
COMMENTS:
Page 9 of 12
WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K
2015-301 NRC Exam STEP/STANDARD SAT/UNSAT STEP 8: Notifies the Unit Operator that ERCW has been aligned to ___ SAT the 1A-A CCP Lube Oil Cooler.
___ UNSAT STANDARD:
Applicant notifies the Unit Operator 1-AOI-15, Loss of Component Cooling Water (CCS), Attachment 1, ERCW Alignment to CCP 1A-A Lube Oil Coolers, has been completed.
CUE: When notified acknowledge the report using repeat back.
COMMENTS:
END OF TASK STOP TIME ________
Page 10 of 12
K Handout Package for Applicant
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
INITIAL CONDITIONS:
- 1. A leak has developed on the Component Cooling Water System.
- 2. 1A CCS Surge Tank level has dropped to less than 10%.
- 3. You are an extra operator assigned to the shift.
INITIATING CUES:
Using the materials provided, the Unit Operator directs you to perform 1-AOI-15, Loss of Component Cooling Water (CCS), Attachment 1, Alignment of ERCW to CCP 1A-A Lube Oil Coolers.
Inform the Unit Operator when Attachment 1 is complete.
K
WBN Loss of Component Cooling Water 1-AOI-15 Unit 1 (CCS) Rev. 0003 Attachment 1 (Page 1 of 1)
Alignment of ERCW to CCP 1A-A Lube Oil Coolers CAUTION CCP may survive for only 10 to 12 minutes after loss of CCS to lube oil cooler.
NOTES
- 1) This page is reproduced on a placard and posted in the CCP 1A-A pump room. This placard must be revised if the instructions on this page are revised. A change to the revision number or page number does NOT constitute a revision to this attachment.
- 2) All valves are located in CCP 1A-A room except 1-ISV-67-602A, CVCS CCP ROOM CLR 1A-A ERCW RET ISOL, which is outside the room [A4T/692]
[A4T/692].
NOTE This step will result in discharging ERCW to the floor drain.
- c. ENSURE cap removed, THEN OPEN 1-DRV-70-782A, CCP 1A-A OIL COOLERS CCS OUTLET DRAIN to establish ERCW flow to oil coolers.
Page 41 of 48