Text

Watts Bar 2015-301 Final Simulator and In-Plant JPMs
	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)
	v • d • e

PAGE 1 OF 11

2015 301NRCExamSystemJPMA WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A 2015-301 NRC Exam PAGE 2 OF 11 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When Shutdown Bank D rod C-5 is withdrawn to greater than or equal to 32 steps, ALL other Shutdown Bank D rods will drop into the core.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Control System, Section 3.3, Dropped RCCA, to withdraw Shutdown Bank D rod C-5. 2) When Shutdown Bank D rod C-5 is withdrawn to greater than or equal to 32 steps diagnoses that additional Shutdown Bank D rods have dropped and performs IMMEDIATE ACTIONS by manually tripping the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 WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A 2015-301 NRC Exam PAGE 3 OF 11 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A 2015-301 NRC Exam PAGE 4 OF 11 READ TO APPLICANT DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. Unit 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 agre ed on a retrieval rate of 64 st eps 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, Secti on 3.3, Dropped RCCA, Step 17. Notify the Unit Supervisor when Shutdown Bank D, C-5 rod has been realigned.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 5 of 11 START TIME: _______

STEP 1: 17. PLACE rod control in bank select position for affected bank.

STANDARD: Applicant rotates 1-RBSS, ROD BANK SELECT to the left from the MAN position to the SDD position to select shutdown bank D.

Step is critical to assure proper bank is selected to be aligned.

COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT NOTE Computer Points for individual rods are C0009A through C0035A for shutdown banks and C0039A through C0076A for control banks. Average rod position points are U0001 through U0013.Rod step position points are U0049 through U0056. All points are in ICS GROUP DISPLAY MENU listed in SPECIAL GROUPS as SG 1.

STEP 2: 18. RECORD the value of the following:

Affected bank's step counter(s)

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:

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 6 of 11 STEP 3: 19. DISCONNECT all lift coils (toggle up) in affected bank, EXCEPT for dropped RCCA.

STANDARD: Applicant places toggle switches for rods E-13, N-11, & L-3 in the disconnect 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:

CRITICAL STEP ___ SAT ___ UNSAT 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 NO RCCA motion observed on RPI.

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:

___ SAT ___ UNSAT STEP 5: 21. SET affected step counter to 000.

STANDARD: 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:

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 7 of 11 STEP 6: 22. USE the Plant Computer to set affected bank's position to zero:

a. SELECT NSSS AND BOP.

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:

___ SAT ___ UNSAT STEP 7: 23. DO NOT CONTINUE UNTIL the following agree on a retrieval rate:

Unit SRO

Shift Manager

Reactor Engineering

STA STANDARD: Applicant determines that the above personnel have agreed to retrieval rate and maximum power level per initial conditions. CUE: 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: ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 8 of 11 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:

() USING rod control in Bank Select, position affected RCCA to bank affected position recorded in Step 18

() 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:

___ SAT

___ UNSAT

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.

STEP 9: 1. PERFORM the following:

a. CHECK ONLY ONE rod dropped STANDARD: Applicant determines that multiple rods have dropped and enters the RESPONSE NOT OBTAINED column for contingency actions. COMMENTS:

___ SAT ___ UNSAT WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE A 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 9 of 11 STEP 10: 1. PERFORM the following: RESPONSE NOT OBTAINED:

a. IF more than one rod dropped, THEN () TRIP reactor **GO TO 1-E-0, Reactor Trip or Safety Injection.

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 CRITICAL STEP ___ SAT ___ UNSAT STOP TIME ________

A A

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

A 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 agre ed on a retrieval rate of 64 st eps 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, Secti on 3.3, Dropped RCCA, Step 17. Notify the Unit Supervisor when Shutdown Bank D, C-5 rod has been realigned.

NRCEXAM2015 301SystemJPMB WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2015-301 PAGE 1 OF 19 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 WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2015-301 PAGE 2 OF 19 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2015-301 PAGE 3 OF 19 READ TO APPLICANT DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. Unit 2 is conducting pre-operational tests. 2. Unit 1 RCS pressure is approximately 1400 psig and Tavg approximately 500

ºF. 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 eval uating Technical Specifications. 5. 1-SOI-63.01, Safety Inject ion 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 PRES S HI/LO annunciators have cleared, and Section 8.3.1 is complete.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT Page 4 of 19 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 secti on 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, COMPLETE: STANDARD: Applicant determines from INITIA TING CUES that Section 5.1 is complete COMMENTS:

___ SAT

___ UNSAT

STEP 2: [2] IF RCS pressure is 1000 psig, THEN ENSURE 1-FCV-63-118, CL ACCUM 1 OUTLET, CLOSED.

STANDARD: Applicant determines that RCS pre ssure is greater than 1000 psig, at approximately 1400 psig.

Applicant determines that this step in not applicable and marks it N/A.

COMMENTS:

___ SAT

___ UNSAT

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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT Page 5 of 19 STEP 3: [3] IF RCS 1650 psig or less, AND SIP A is to be used to fill CLA 1, THEN CLOSE 1-FCV-63-152, SI PMP A TO CL 1-2-3-4 [1- M-6].

STANDARD: Applicant determines the RCS pressure IS less than 1650 psig (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 crit ical to prevent injection of water into the RCS from the safety injection pump.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

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 Head ON, THEN.... STANDARD: Applicant determines from the IINITIA L 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:

___ SAT ___ UNSAT

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).

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT Page 6 of 19 STEP 5: [5] IF in Mode 4, 5, or 6 and SIP B is to be used with Rx Vessel Head ON THEN: ... STANDARD: Applicant determines from the INITIA L 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:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT Page 7 of 19 STEP 6: [6] PERFORM the following:

STANDARD: Applicant depresses pushbutton 1-HS 187 on the CKV LEAK TEST panel (Critical). Applicant verifies GREEN light fo r 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 fo r 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 fo r 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:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT Page 8 of 19 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):

STANDARD: Applicant determines 1-HS-63-3 is OPEN by observing GREEN light for 1-HS-63-3 is DARK and RED li ght 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 li ght 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 li ght 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 li ght for 1-HS-63-47 is LIT. Applicant enters N/A for 1-FCV 48, since 1A SI pump will be used for filling the #1 CLA.

COMMENTS:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT Page 9 of 19 STEP 8: [8] PERFORM the following (N/A pump NOT selected):

NOMENCLATURE LOC POSITION UNID PERF INITIAL

SI PMP A (ECCS) 1-M-6 START 1-HS-63-10A SI PMP B (ECCS) 1-M-6 START 1-HS-63-15A STANDARD: Applicant rotates handswitch 1-HS 10A to the right to the START position (Critical).

Applicant verifies GREEN lights fo r 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 pressu re 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:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT Page 10 of 19 STEP 9: CHECK the started pumps' closing spring charged (N/A pump NOT started):

STANDARD: Applicant contacts an AUO to dete rmine 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:

___ SAT

___ UNSAT

STEP 10: [10] OPEN 1-FCV-63-115, MAKEUP TO CL ACCUM 1, [1-M-6].

STANDARD: Applicant rotates handswitch 1-HS 115A to the right to the OPEN position (Critical).

Applicant verifies GREEN light fo r 1-HS-63-115A is DARK and the RED 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:

CRITICAL STEP ___ SAT

___ UNSAT

CAUTION Due to physical location of uppe r tap, indication on 1-LI-63-89 greater than 8,030 gal should be considered "Off scale High".

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT Page 11 of 19 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 LEVEL HI/LO, NOT LIT), THEN PERFORM the following:

NOMENCLATURE LOC POSITION UNID PERF INITIAL VERIF INITIAL *MAKEUP TO CL ACCUM 1 1-M-6 CLOSED 1-FCV-63-115 CKV TEST LINE TO HUT 1-M-6 CLOSED 1-FCV-63-71 TEST LINE (1-XS063-100) ISOL 1-M-6 CLOSED 1-FCV-63-187 CLA FILL FROM SI PMPS 1-M-6 CLOSED 1-FCV-63-23 STANDARD: When accumulator level has increased to the point where Alarm 131-A is clear (greater than 7660 gallons) and Al arm 131-B (greater than 610 psig) then Applicant rotates handswitch 1-HS 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 fo r 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 fo r 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 possibl e overfill of CLA 1.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT Page 12 of 19 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 minutes, THEN PERFORM the following (N/A pump NOT selected):

NOMENCLATURE LOC POSITION UNID PERF INITIAL *SI PMP A (ECCS) 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 fo r 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:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT Page 13 of 19 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):

NOMENCLATURE LOC POSITION UNID PERF INITIAL VERIF INITIAL 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:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT Page 14 of 19 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):

NOMENCLATURE LOC POSITION UNID PERF INITIAL VERIF INITIAL SI PMP A (ECCS) 1-M-6 PULL-TO-LOCK 1-HS-63-10A SI PMP B (ECCS) 1-M-6 PULL-TO-LOCK 1-HS-63-15A STANDARD: Applicant enters N/A for Step 14, si nce both of the safety injection pumps are required to be in the A-AUTO position to support ECCS standby alignment.

COMMENTS:

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT Page 15 of 19 STEP 15: [15] CHECK the shutdown pumps' clos ing spring charged (N/A pump NOT shutdown):

STANDARD: Applicant contacts an AUO to dete rmine 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:

___ SAT

___ UNSAT

STEP 16: [16] IF 1-FCV-63-152, was closed in Step 8.3.1[3], THEN OPEN 1-FCV-63-152, SI PMP A TO CL 1-2-3-4 [1-M-6] (N/A in Mode 4, 5, 6).

STANDARD: Applicant determines that 1-FCV-63-152, SI PMP A TO CL 1-2-3-4 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 ensu re the system is returned to the proper alignment.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT Page 16 of 19 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 ACCUM 1 PRESS HI/LO, NOT LIT). STANDARD: Applicant determines that cold leg accumulator pressure is in the desired range (alarm 134-B DARK).

COMMENTS:

___ SAT ___ UNSAT

STEP 18: Applicant reports that Cold Leg Accumulator 1 has been filled.

STANDARD: Applicant informs the Unit Supervisor that Cold Leg Accumulator 1 has been filled. CUE: Repeat back the information provided by the applicant.

COMMENTS:

END OF TASK

___ SAT ___ UNSAT

STOP TIME ________

B

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

B INITIAL CONDITIONS:

1. Unit 2 is conducting pre-operational tests. 2. Unit 1 RCS pressure is approximately 1400 psig and Tavg approximately 500

ºF. 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 Inject ion 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 PRES S HI/LO annunciators have cleared, and Section 8.3.1 is complete.

2015 301NRCExamSystemJPMC WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C 2015-301 NRC Exam Page 2 of 12 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 WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C 2015-301 NRC Exam Page 3 of 12 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C 2015-301 NRC Exam Page 4 of 12 READ TO APPLICANT

DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. Unit 2 is conducting pre-operational testing.

2. A large break LOCA has occurred on Unit 1.

3. Rx MOV BD 1B1-B tripped. Other opera tors are taking actions in response to the board loss. 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 Br eaker Operation is complete. 6. You are the Control Room Operator.

INITIATING CUES:

The Unit Supervisor directs you to perfor m Step 24 of 1-E-1, Loss of Reactor or Secondary Coolant. Inform the Unit Supervisor when Step 24 has been completed.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 5 of 12 START TIME: _______

STEP 1: 24. DETERMINE if cold leg accumulators should be isolated:

a. ENSURE power to isolation valves restored USING Appendix A (1-E-1), CLA Breaker Operation.

STANDARD: Applicant determines from the IN ITIAL CONDITIONS that power has been restored to the isolation valves.

COMMENTS:

___ SAT

___ UNSAT

STEP 2: 24. DETERMINE if cold leg accumulators should be isolated:

b. CHECK RCS pressure less than 250 psig.

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:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 6 of 12 EXAMINER: In the subsequent step, the applicant will iden tify 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 dete rmine that RNO actions are required for 1-FCV-63-98, CL ACCUM 2 OUTLET and 1-FCV 67, CL ACCUM 4 OUTLET.

STEP 3: 24. DETERMINE if cold leg accumulators should be isolated:

c. CLOSE cold leg accumulator isolation valves.

STANDARD: Applicant locates 1-HS-63-118A and rotates the handswitch to the left to CLOSE (Critical). Applicant observes RED light is DARK and GREEN light is LIT.

Locates 1-HS-63-80A and rotates t he 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:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 7 of 12 STEP 4: 24. DETERMINE if cold leg accumulators should be isolated:

c. RESPONSE NOT OBTAINED: PERFORM the following:

1) RESET Phase B. STANDARD: Applicant observes that the RE D 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, M ASTER ISOLATION SIGNAL STATUS PANEL (Critical).

Applicant observes that the RE D 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, M ASTER 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:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 8 of 12 STEP 5: 24. DETERMINE if cold leg accumulators should be isolated:

c. RESPONSE NOT OBTAINED: PERFORM the following:

2) ENSURE aux air pressure to cntmt is greater than 75 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 rota ting 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 rota ting and holding 1-HS-30-110A, NON-ESS AUX AIR TO RX BLDG CI V-ØB/70 PSI D/S CLOSES to the right, until the RED light is LI T and GREEN light is DARK (Critical).

Step is critical to provide ai r to position the accumulator makeup valves used to vent nitrogen from accumulators 2 and 4.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 9 of 12 STEP 6: 24. DETERMINE if cold leg accumulators should be isolated:

c. RESPONSE NOT OBTAINED: PERFORM the following:

3) OPEN any unisolated accumulator nitrogen makeup valve:

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-FC V-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:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE C 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 10 of 12 STEP 7: 24. DETERMINE if cold leg accumulators should be isolated:

c. RESPONSE NOT OBTAINED: PERFORM the following:

4) OPEN 1-FCV-63-65 vent header.

STANDARD: Applicant locates 1-HIC-63-65A and depresses the RAMP and [>>] (raise) buttons until t he demand indicates 100% (Critical).

Step is critical since this action is taken to minimize the chance of nitrogen injection into the RCS.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

STEP 8: Notify the Unit Supervisor that 1-E-1, Step 24 is complete.

STANDARD: Applicant notifies the Unit Supervisor that Step 24 is complete. CUE: Repeat back information provided by the applicant.

COMMENTS:

END OF TASK

___ SAT

___ UNSAT

STOP TIME ________

C C

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

C INITIAL CONDITIONS:

1. Unit 2 is conducting pre-operational testing.

2. A large break LOCA has occurred on Unit 1.

3. Rx MOV BD 1B1-B tripped. Other opera tors are taking actions in response to the board loss. 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 Br eaker Operation is complete. 6. You are the Control Room Operator.

INITIATING CUES:

The Unit Supervisor directs you to perfor m Step 24 of 1-E-1, Loss of Reactor or Secondary Coolant. Inform the Unit Supervisor when Step 24 has been completed.

NRCEXAM2015 301SystemJPMD WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D NRC EXAM 2015-301 PAGE 1 OF 16 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 WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D NRC EXAM 2015-301 PAGE 2 OF 16 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 Pu mps, signed off (circled-and-slashed) to Step 6 is available for eac h applicant 8. Place simulator in FREEZE until Examiner cue is given.

9. ENSURE Extra Operator is available on Simulator.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D NRC EXAM 2015-301 PAGE 3 OF 16 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D NRC EXAM 2015-301 PAGE 4 OF 16 READ TO APPLICANT

DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. Unit 2 is conducting pre-operational tests.

2. Unit 1 is in Mode 3.

3. #2 RCP has been shut down 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s for repairs to the motor leads. 4. Maintenance reported the repairs have been completed.

5. An AUO has performed SOI-68.02, Appendix C, RCP Local Inspection. 6. SOI-68.02, Reactor Coolan t Pumps, Section 5.0, Startup, has been completed through Step 7. 7. Section 4.2 Field Prep arations are complete.

INITIATING CUES:

The Unit Supervisor has directed you to start #2 RCP using SOI-68.02, Reactor Coolant Pumps, Section 5.0, Start up, beginning at Step 8.

Inform the Unit Supervisor wh en Section 5.0 is complete.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT Page 5 of 16 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:

STANDARD: Applicant pulls out handswitch 1-HS-68-31AA RCP 2 NORMAL BKR&LIFT PUMP and rotates t he handswitch to the START position.(Critical)

Step is critical to assu re oil lift pressure thrust bearings to prevent metal to metal contact on bearing surfaces when pump is started from idle.

COMMENTS:

CRITICAL TASK ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT Page 6 of 16 STEP 2: [9] VERIFY #1 seal P greater than 200 psid [1-M-5].

STANDARD: 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:

___ SAT

___ UNSAT

STEP 3: [10] VERIFY 8 to 13 gpm to RCP seal [1-M-5].

STANDARD: Applicant locates 1-FI-62-14A, RCP 2 SEAL SUP FLOW and observes flow at 8 approximately gpm.

COMMENTS:

___ SAT

___ UNSAT

STEP 4: [11] ENSURE VCT press at least 15 psig [1-M-6].

STANDARD: Applicant locates 1-PI-62-122, VCT PRESS on panel 1-M-6 and observes pressure greater than 15 psig (approximately 25 psig).

COMMENTS:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT Page 7 of 16 STEP 5: [12] VERIFY #1 seal leakoff greater than 0.2 gpm, or within Normal Operating Range for existing #1 Seal P (see Appendix B).

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:

___ SAT

___ UNSAT

STEP 6: [13] IF leakoff flow is NOT established, THEN GO TO Section 8.0.

STANDARD: Applicant determines that leakoff flow is established and marks the step as N/A. COMMENTS:

___ SAT

___ UNSAT

STEP 7: [14] IF starting RCP for fill and vent only, THEN ENSURE RCS press is greater than 325 psig but less than 1000 psig.

[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:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT Page 8 of 16 NOTE Step 5.0[15] prevents excessive Rod motion upon starting RCP.

STEP 8: [15] IF restarting RCP with Control Rods withdrawn, THEN ENSURE Rod Bank Select in MANUAL. STANDARD: Applicant locates CERPI MONITO R 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:

___ SAT

___ UNSAT

CAUTION To reduce thermal shock to RCP shaft and seals, a maximum of 1°F per minute temp reduction will be observed, until bearing temp is less than 225°F.

STEP 9: [16] IF restarting RCP after stopping due to high temp limits caused by loss of Injecti on Water and High CCS temp, THEN ENSURE following parameters es tablished to prevent 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 INIT IAL CONDITIONS that the pump is not being restarted after a high temperature condition.

COMMENTS:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT Page 9 of 16 STEP 11: [17] ENSURE Aux OC Bkr, CLOSED. STANDARD: 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:

___ SAT

___ UNSAT

STEP 12: [18] IF starting RCP 1, THEN ENSURE Pzr spray, 1-PCV 340D, is CLOSED. STANDARD: Applicant marks the step as N/A since RCP 2 is being started.

COMMENTS:

___ SAT

___ UNSAT

STEP 13: [19] IF starting RCP 2, THEN ENSURE Pzr spray, 1-PCV 340B, is CLOSED. STANDARD: Applicant observes 1-XI-68-340B RED light is LIT, i ndicating that 1-PCV-68-340B is OPEN.

Applicant locates 1-HIC-68-340B, LOOP 2 SPRAY CONTROL, then depresses the AUTO/MAN pushbutton to take manual control Applicant depresses the [<<] butt on 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 poten tial for an RCS pressure transient during pump startup.

COMMENTS:

CRITICAL TASK ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT Page 10 of 16 STEP 14: [20] ANNOUNCE RCP start on PA system.

STANDARD: CUE: When the applicant addresses the PA announcement, state "another operator will handle the PA announcement."

COMMENTS:

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT Page 11 of 16 NOTE Below 15% power with station se rvice NOT transferred, the Alternate handswitch is used to start RCP.

STEP 15: [21] START selected RCP (N/A HSs NOT used): STANDARD: Applicant enters N/A for RCP 1, RCP 3 and RCP 4 handswitches. The applicant enters N/A for 1-HS 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 in dicating 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 acti on starts RCP 2, the desired RCP.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT Page 12 of 16 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 Pump (N/A HSs NOT used): 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:

___ 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. 0-GOI-7, Generic Equipment Operating Guidelines, Section 5.2.5, Motor Operating and Starting Limitations, states: [1] OPERATE motors having associated a mmeters under the following guidelines: A. Motors should NOT be operated abo ve the RED line on the ammeter except when, in the judgment of the SRO, the safe ty of the plant and/or public may be in danger.

The applicant is expected to evaluate motor amps, and trip #2 RCP.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE D NRC EXAM 2015-301 STEP/STANDARD SAT/UNSAT Page 13 of 16 EXAMINER: When 14-D, M-1 THRU M-6 MO TOR OVERLOAD annunciator is received, the Extra Operator will announce the alarm.

STEP 17: STOP and LOCK OUT #2 RCP. STANDARD: Applicant rotates 1-HS-68-31BA is to the STOP position and GREEN ACB light is LIT.

Step is critical to prevent a dditional damage to #2 RCP pump.

CUE: After RCP is stopped, state "another operator will continue from here."

COMMENTS:

END OF TASK CRITICAL STEP ___ SAT

___ UNSAT

STOP TIME ________

D

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

D INITIAL CONDITIONS:

1. Unit 2 is conducting pre-operational tests.

2. Unit 1 is in Mode 3.

3. #2 RCP has been shut down 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s for repairs to the motor leads. 4. Maintenance reported the repairs have been completed. 5. An AUO has performed SOI-68.02, Appendix C, RCP Local Inspection. 6. SOI-68.02, Reactor Coolan t Pumps, Section 5.0, Startup, has been completed through Step 7. 7. Section 4.2 Field Prep arations are complete.

INITIATING CUES:

The Unit Supervisor has directed you to start #2 RCP using SOI-68.02, Reactor Coolant Pumps, Section 5.0, Start up, beginning at Step 8.

Inform the Unit Supervisor wh en Section 5.0 is complete.

2015 301NRCExamSystemJPME WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E 2015-301 NRC Exam Page 2 of 13 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 WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E 2015-301 NRC Exam Page 3 of 13 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E 2015-301 NRC Exam Page 4 of 13 SIMULATOR SETUP INFORMATION JPM Step No. Proc. Step No. Description/Role Play 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..

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E 2015-301 NRC Exam Page 5 of 13 READ TO APPLICANT DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. Unit 2 is performing pre-operational testing.

2. Unit 1 is conducting a plant shutdown pe r 1-GO-4, Normal Operat ions, 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 6 of 13 START TIME: _______

STEP 1: [4] () PLACE selected MFP speed control in MANUAL and LOWER speed slowly [1-M-3]: A. 1-SIC-46-20A, MFPT A- SPEED CONTROL B. 1-SIC-46-20B, MFPT B- SPEED CONTROL:

STANDARD: 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:

CRITICAL STEP

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 7 of 13 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.

STANDARD: Applicant observes 1B MFP recirc valve opens as 1B MFP speed reduces and load shifts to 1A MFP.

COMMENTS:

___ SAT ___ UNSAT STEP 3: [6] IF other MFP is in service, THEN ENSURE the other MFP assumes the load.

STANDARD: Applicant observes 1A MFP speed increasing as 1B MFP speed is reduced. This step is critical to ensure adequate feed flow is maintained.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 4: [7] IF MFP A is being SHUT DOWN, THEN MONITOR its supervisory instruments while unloading:

STANDARD: Since the 1B MFP is being shutdown, the applicant marks the step N/A. COMMENTS:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 8 of 13 STEP 5: [8] IF MFP B is being SHUT DOWN, THEN MONITOR its MFPT and Pump Bearing Vibration on ICS while unloading: 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:

___ SAT ___ UNSAT

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: A. 1-TIC-24-56A, MFPT OIL COOLER 1A1/1A2 RCW OUTLET 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:

___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 9 of 13 STEP 7: [10] ENSURE both MFPs RESET.

STANDARD: Applicant locates 1-HS-46-9A, MFPT A TRIP - RESET and observes the RED 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:

___ SAT

___ UNSAT

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 MFP Turbine [1-M-3]:

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:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 10 of 13 STEP 9: [12] VERIFY HP and LP Stop Valves CLOSE.

STANDARD: Applicant locates 1-HS-46-43A, MFPT B MFPT B HP STOP VLV, and 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:

___ SAT

___ UNSAT

STEP 10: [13] VERIFY Governor Valves CLOSE, AND VERIFY "Governor Valve Positioner" is at minimum position by green light indication on controller panel (red light off): 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:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE E 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 11 of 13 STEP 11: [14] CLOSE the following: A. 1-HCV-3-70, MAIN FEEDWATER PUMP A RECIRC 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:

___ SAT ___ UNSAT

STEP 12: [15] IF MFW flow is above 40% (6 X 106 pph) when MFP is tripped, THEN VERIFY applicable MFP condenser valves CLOSED [1-M-2]: 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

___ SAT

___ UNSAT STOP TIME ________

E

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

E INITIAL CONDITIONS:

1. Unit 2 is performing pre-operational testing.

2. Unit 1 is conducting a plant shutdown pe r 1-GO-4, Normal Operat ions, 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.

2015 301NRCExamSystemJPMF WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F 2013-03 NRC Exam Page 2 of 13 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 WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F 2015-301 NRC Exam Page 3 of 13 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

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F 2015-301 NRC Exam Page 4 of 13 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F 2015-301 NRC Exam Page 5 of 13 READ TO APPLICANT

DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. Unit 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 perf orming 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 6 of 13 START TIME: _______

STEP 1: 10. DETERMINE if RHR spray should be placed in service:

a. CHECK the following conditions:

At least one hour has elapsed since the beginning of the accident.

Cntmt pressure is greater than 9.5 psig.

RHR suction is aligned to Cntmt sump.

At least one charging pump and one SI pump running.

STANDARD: The applicant determines from the in formation provided that all of the listed conditions exist, and proceeds to Step 10.b

. COMMENTS:

___ SAT

___ UNSAT

STEP 2: b. ALIGN Train B RHR spray:

1) ENSURE Train B RHR pump RUNNING.

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:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 7 of 13 STEP 3: 2) CLOSE RHR crosstie 1-FCV-74-35.

STANDARD: 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:

___ SAT

___ UNSAT

STEP 4: 3) CLOSE RHR injection 1-FCV-63-94.

STANDARD: Applicant locates 1-HS-63-94 and ro tates the handswitch to the left to the CLOSE position.

Applicant observes GREEN light LIT, RED light DARK indicating the valve is CLOSED.

COMMENTS:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 8 of 13 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.

STANDARD: 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 41, RHR TO CL 1&4, will NOT CLOSE, and enters Step

b. RNO for actions.

COMMENTS:

___ SAT

___ UNSAT

STEP 5: b. IF Train B RHR spray CANNOT be established, THEN PERFORM the following:

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:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 9 of 13 STEP 6: 2) IF RHR aligned for cold leg recirculation, THEN ENSURE 1-FCV-63-94 OPEN.

STANDARD: Applicant locates 1-HS-63-94 and rota tes the handswitch to the right to the OPEN position. (Critical). Applicant observes GREEN light DA RK, RED light LIT indicating the valve is OPEN.

This step is critical to ensure cold leg recirculation is maintained through the core.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

STEP 7: 3) ENSURE Train A RHR pump RUNNING.

STANDARD: 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:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 10 of 13 STEP 8: 4) CLOSE RHR crosstie 1-FCV-74-33.

STANDARD: 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:

___ SAT

___ UNSAT

STEP 9: 5) CLOSE RHR injection 1-FCV-63-93.

STANDARD: Applicant locates 1-HS-63-93, RHR TO CL 1&4, and rotates the handswitch to the left to the CLOSE position. (Critical).

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:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE F 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 11 of 13 STEP 10: 6) OPEN RHR spray 1-FCV-72-40.

STANDARD: Applicant locates 1-HS-72-40, RHR SPRAY HDR A TO CNTMT and rotates the handswitch to the right to the OPEN position. (Critical).

Applicant observes RED light LIT, GREEN light DARK, indicating the valve is OPEN.

Applicant observes containment pr essure decreasing on 1-PDI-30-42, 1-PDI-30-43, 1-PDI 44 and 1-PDI-30-45. This step is critical to ensure flow is directed to the A RHR Spray header. COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

STEP 11: Notifies the Unit Supervisor that Train A RHR Spray is in service.

STANDARD: Applicant notifies the Unit Supervi sor 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

___ SAT

___ UNSAT

STOP TIME ________

F

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

F 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 perf orming 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.

2015 301NRCExamSystemJPMG WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G 2013-03 NRC Exam Page 2 of 14 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 depr esses 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 WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G 2015-301 NRC Exam Page 3 of 14 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G 2015-301 NRC Exam Page 4 of 14 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G 2015-301 NRC Exam Page 5 of 14 READ TO APPLICANT DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. Unit 2 is conducting pre-operational tests.

2. Testing is being conducted on 1A-A diesel ge nerator. 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 parall el 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 6 of 14 START TIME: _______

STEP 1: [4] PLACE 1-HS-82-18, DG MODE SELECTOR Switch, in PARALLEL [0-M-26].

STANDARD: The applicant locates 1-HS-82-18 DG MODE SELECTOR and rotates the handswitch to the right from th e UNIT to the PARALLEL position. (Critical). This step is critical for task performance to allow proper operation of voltage regulator &

DG speed droop circuits.

COMMENTS: CRITICAL STEP ___ SAT

___ UNSAT

STEP 2: [5] ENSURE the following sync switches for 1A-A D/G in OFF:

STANDARD: Applicant locates each of the list ed sync switches and determines that each handswitch is in the OFF position COMMENTS:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 7 of 14 STEP 3: [6] PLACE 1-HS-57-47, DG SYNC SW ITCH, in SYN [0-M-26].

STANDARD: Applicant locates 1-HS-57-47, DG SYNC SWITCH and rotates the switch to the right to the SYN position (Critical).

This step is critical to allow synchronization of DG to 1A-A Shutdown board.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

CAUTION When adjusting speed and voltage, care must be taken to prevent overshooting desired values. Voltage control response is approximately five times faster than speed control response.

STEP 4: [7] MATCH generator Incoming Frequency (1-XI-82-2) with Running Frequency (1-XI-82-3) using 1-HS-82-13, SPEED CONTROL [0-M-26].

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:

___ SAT

___ UNSAT

STEP 5: [8] MATCH generator Incoming Voltage (1-EI-82-4) with Running Voltage (1-EI-82-5) usi ng 1-HS-82-12, VOLTAGE REGULATOR [0-M-26].

STANDARD: Applicant operates 1-HS-82-12 to adjust generator vo ltage on 1-EI-82-4 to board voltage on 1-EI-82-5.

COMMENTS:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 8 of 14 NOTE Steps 8.1.4[9], 8.1.4[

10], and 8.1.4[11] should be read before performing. EXAMINER: The applicant may use a stopwatch to time the 15 second rotation. Provide stopwatch if asked.

STEP 6: [9] ENSURE DG Frequency and Voltage are MATCHED with 6.9 kV SD Bd, AND ADJUST 1-HS-82-13, SPEED CONTROL, [0-M-26] to obtain desired clo ckwise rotation (15 or more seconds) on 1-XI-82-1,TRAI N 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:

___ SAT

___ UNSAT

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 requ ired on next step.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 9 of 14 STEP 7: [10] WHEN 1-XI-82-1, TRAIN 1A-A SYNCHROSCOPE (1-XI-82-1) reaches 12 o'clock, THEN TURN 1-HS-57-46A, 1912 - DG TO SH BD 1A-A, to CLOSE.

STANDARD: Applicant monitors 1-XI-82-1, TRAIN 1A-A SYNCHROSCOPE and rotates 1-HS-57-46A, 1912 - DG TO SD BD 1A-A, to th e right to the CLOSE position. (Critical).

Applicant observes the RED li ght 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:

CRITICAL STEP ___ SAT ___ UNSAT

NOTE Maintain outgoing Vars by periodically adj usting voltage regulator with 1-HS-82-12 while loading D/G. Controls should NOT be operated simultaneously.

STEP 8: [11] PERFORM the following:

[11.1] LOAD DG promptly using 1-HS-82-13, SPEED CONTROL to at least 1.1 Megawatts as indicated on 1-EI-82-10A, DG MEGAWATTS (0-M-26).

STANDARD: Applicant periodically rotates 1-HS 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:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 10 of 14 NOTE DG Megavars may "swing" when the 6.9kV automatic tap changers engage to stabilize voltage in the system.

STEP 9: [11.2]

MAINTAIN DG MEGAVARS 0.75 to 1.25 OUTGOING on 1-EI-82-11A, with 1-HS-82-12, VOLTAGE REGULATOR.

STANDARD: Applicant periodically adjusts 1-HS-82-12, VOLTAGE REGULATOR, to 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:

CRITICAL STEP ___ SAT

___ UNSAT

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 MV ARS OUTGOING.

STEP 10: [11.3]

RAISE load to at least 3.3 Megawatts.

STANDARD: Applicant periodically rotates 1-HS-82-13 to the RAISE position to increase generator load on 1-EI 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:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 11 of 14 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 on XA-55-26B.

STANDARD: 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:

___ SAT

___ UNSAT

STEP 12: [1] IF DG running with NO em ergency start present, THEN ENSURE DG shutdown by Emergency Stop

Remote - Depress 1-HS-82-17A, EMERGENCY STOP pushbutton on 0-M-26. Local - Depress EMERGENCY STOP pushbutton on DG 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, CRANK CASE PRESSURE HIGH.

Time 1-HS-82-17A, EMERGENC Y STOP depressed:___________.

This step is critical to ensure th at additional damage to 1A-A DG is prevented.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE G 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 12 of 14 STEP 15: Notifies the Unit Supervisor that the 1A-A Diesel Generator was shutdown using 1-HS-82-17A, EMERGENCY STOP pushbutton

on 0-M-26, due to a high crankcase pressure alarm.

STANDARD: Applicant notifies the Unit Supervi sor 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

___ SAT

___ UNSAT

STOP TIME ________

G

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

G INITIAL CONDITIONS:

1. Unit 2 is conducting pre-operational tests.

2. Testing is being conducted on 1A-A diesel ge nerator. 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 parall el 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.

2015 301NRCExamSystemJPMH WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H 2015-301 NRC Exam Page 2 of 11 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 WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H 2015-301 NRC Exam Page 3 of 11 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H 2015-301 NRC Exam Page 4 of 11 READ TO APPLICANT DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. Unit 2 is conducting pre-operational testing.

2. Unit 1 is at 100% power.

3. A purge of the Instrument Room is sch eduled to be performed on this shift. 4. SOI-30.02, Containment Purge System, Sect ion 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 Inst rument Room Purge is in service.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 5 of 11 START TIME: _______

STEP 1: [6] CLOSE Containment vent filter flowpath:

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:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 6 of 11 STEP 2: [7] PERFORM the following:

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:

CRITICAL STEP ___ SAT ___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 7 of 11 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 & 11B with 1-HS-30-11A [1-M-9].

STANDARD: 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 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:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 8 of 11 STEP 4: [9] ENSURE the following:

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:

___ SAT

___ UNSAT

STEP 5: [10] CHECK flow on 1-FI-90-400, SHIELD BLDG VT FLOW

[1-M-9]. (N/A if FI NOT available)

STANDARD: Applicant locates 1-FI-90-400, SHIELD BLDG VENT FLOW and observes approximately 2000 SCFM COMMENTS:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE H 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 9 of 11 STEP 6: [11] IF FI-90-400 is NOT available, THEN ENSURE Flow being estimated per 1-SI-0-2, Shift & Daily Log.

STANDARD:

Applicant determines Step [11] is N/A.

COMMENTS:

___ SAT

___ UNSAT

STEP 7: Applicant notifies the Unit Supervisor that instrument room purge has been established.

STANDARD: Applicant notifies the Unit Supervisor that instrument room purge has been established. CUE: Repeat back information provided by the applicant. COMMENTS:

END OF TASK

___ SAT

___ UNSAT STOP TIME ________

H

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

H INITIAL CONDITIONS:

1. Unit 2 is conducting pre-operational testing.

2. Unit 1 is at 100% power.

3. A purge of the Instrument Room is sch eduled to be performed on this shift. 4. SOI-30.02, Containment Purge System, Sect ion 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 Inst rument Room Purge is in service.

NRCEXAM2015 301SystemJPM WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE INRC EXAM 2013-302 Page 2 of 12 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 WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE INRC EXAM 2013-302 Page 3 of 12 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 Filt er A, to give to the applicant.

Note: START THIS JPM AT THE RADWASTE AUO DESK WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE INRC EXAM 2013-302 Page 4 of 12 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 sw ap 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE INRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 5 of 12 START TIME: _______

NOTE Opening valves slowly when placing the seal wa ter injection filters in service allows the pressure to equalize across filter and prevents f ilter 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 r apid opening of the valve and loss of seal injection flow.

STEP 1: [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 discr etion of Unit SRO)

STANDARD: Applicant may either: a. N/A this step based on Initiating Cues.

OR b. Elect to Locate 1-PDIS-62-96, CVCS SEAL WTR INJECTION FILTER B DIFF PRESS and check indicated differential pressure. If

this is the case, provide the cue below.

Cue: After located and checked, indicate a value of 22 psid.

COMMENTS:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE INRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 6 of 12 STEP 2: [2] ENSURE RCP standpipe levels NORMAL (HI/LO alarm clear).

STANDARD: Applicant contacts the Operator-a t-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:

___ SAT

___ UNSAT

STEP 3: [3] SLOWLY OPEN 1-ISV-62-548, CVCS SEAL WTR INJ FLTR A IN ISOL [A5T/713].

STANDARD: Applicant locates 1-ISV-62-548, CVCS SEAL WTR INJ FLTR A IN 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:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE INRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 7 of 12 STEP 4: [4] SLOWLY OPEN 1-ISV-62-550, CVCS SEAL WTR INJ FILTER A OUT ISOL [A5T/713].

STANDARD: Applicant locates 1-ISV-62-550, CVCS SEAL WTR INJ FILTER A OUT 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:

CRITICAL STEP ___ SAT

___ UNSAT

STEP 5: [5] ENSURE RCP seal injection flow between 8 and 13 gpm.

STANDARD: 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:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE INRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 8 of 12 STEP 6: [6] CHECK P rose on A filter prior to isolating B filter.

STANDARD: 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:

___ SAT

___ UNSAT

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 applican t 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 ISOL [A5T/713].

STANDARD: Applicant locates 1-ISV-62-549, CVCS SEAL WTR INJ FILTER B OUT 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:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE INRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 9 of 12 STEP 8: [8] CLOSE 1-ISV-62-547, CVCS SEAL WTR INJ FLTR B IN ISOL

[A5T/713].

STANDARD: Applicant locates 1-ISV-62-547, CVCS SEAL WTR INJ FLTR B IN 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 7 is not performed.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

STEP 9: [9] ENSURE 1-PDIS-62-97, CVCS SEAL WTR INJECTION FILTER A DIFF PRESS [A5T/713], indicates P less than 20 psid.

STANDARD: Applicant locates 1-PDIS-62-97, CVCS SEAL WTR INJECTION FILTER A DIFF PRESS and Filter A's 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:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE INRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 10 of 12 STEP 10: [10] INITIATE SR to replace clogged filter, and NOTIFY UO to record SR number. (N/A if open SR available for filter replacement)

STANDARD: Applicant indicates that a Service Request (SR) must be initiated and that the Unit Operator mu st 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

___ SAT

___ UNSAT

STOP TIME ________

I

Handout Package for Applicant

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

IINITIAL 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 sw ap 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.

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 Unit 1 CVCS-Charging and Letdown 1-SOI-62.01 Rev. 0000 Page 2 of 108 Revision Log Revision or Change Number Effective Date Affected Page Numbers Description of Revision/Change 0000 04/08/14 All Incorporat ed 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 reflec t Unit 1, Unit 2, and Common 0 designations, iaw ODM 23, in preparation for tw o 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 Unit 1 CVCS-Charging and Letdown 1-SOI-62.01 Rev. 0000 Page 3 of 108 Table of Contents

1.0 INTRODUCTION

.......................................................................................................... 5 1.1 Pur pose ...................................................................................................................

..... 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 PREREQUISI

TE ACTIONS ........................................................................................ 13

4.1 Preliminar

y Actions ..................................................................................................... 1 3 4.2 Field Preparations .......................................................................................................

13 4.3 Approvals and No tifications ........................................................................................ 14 5.0 STAR TUP ................................................................................................................... 15 5.1 Establishing Let down and Char ging ........................................................................... 15 5.2 Establishing RCP Seal Inje ction ................................................................................. 23 6.0 NORMAL O PERATION .............................................................................................. 26 6.1 Normal Operati ng Parameters .................................................................................... 28

6.2 Swappi

ng CCPs .......................................................................................................... 31 6.3 Adjusting Le tdown Flow .............................................................................................. 34 7.0 SHUTDOWN ............................................................................................................... 37 7.1 Unit Shutdown ............................................................................................................

37 7.2 Charging Syst em Shutdown ....................................................................................... 39 8.0 INFREQUENT OPERATIONS .................................................................................... 41 8.1 Remove Chargi ng and Letdown ................................................................................. 41 8.2 Reestablish Char ging 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 Loc al Control ...................... 54 8.7 Hydrogen Concentra tion Control ................................................................................ 56 8.8 Oxygen Control: Hy drazine Addition ........................................................................... 59 WBN Unit 1 CVCS-Charging and Letdown 1-SOI-62.01 Rev. 0000 Page 4 of 108 Table of Contents (continued) 8.9 Seal Injection Filter Swap ........................................................................................... 63 8.9.1 Replacing Filter A with Filt er B ...................................................................... 63 8.9.2 Replacing Filter B with Filt er A ...................................................................... 65 8.10 pH Control: LiOH Addition

........................................................................................... 66 8.11 Establishing VCT N2 Atmo sphere .............................................................................. 70 8.12 Replace VCT H2 With N2 ........................................................................................... 74 8.13 Hydrogen Peroxi de Addition ....................................................................................... 77 8.14 Alternating Charging Pump Suction To and From the RWST Using 1-LCV-62-135 A nd 136 ............................................................................................... 82 8.15 Bypassing 1-PCV-62-81, CVCS LETDOWN HX PRESS CNTL, for Local Control

............................................................................................................... 84 8.16 Adjusting Hydrogen Regulator Fo r Hydrogen Concentra tion 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 Cool ant Filter to Normal ................................................................ 91 8.20 Burping the VCT .........................................................................................................

93 8.21 Adjusting Letdown Heat Exchanger Outlet Te mperature ............................................ 96 8.22 Placing 1-HIC-62-93A in Auto with a Deviation

........................................................... 97 8.23 Bypassing Seal Wate r Return Filter ............................................................................ 98 8.24 Restoring Seal Water Return Filter to Normal

............................................................. 98 9.0 RECO RDS ..................................................................................................................

99 9.1 QA Re cords ................................................................................................................ 99 9.2 Non-QA Records ........................................................................................................ 99 Appendix A: Inaccessible Valve Position Verification .............................................. 100 Source Notes

........................................................................................... 108 EXTERNAL ATTACHMENTS Attachment 1P: Power Checklist 1-62.01-1P Attachment 1V: Valve Checklist 1-62.01-1V

WBN Unit 1 CVCS-Charging and Letdown 1-SOI-62.01 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 Unit 1 CVCS-Charging and Letdown 1-SOI-62.01 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 Lo cked Breaker Verification C. 1-SI-63-10.1-A, ECCS Pump and Di scharge 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 Inservic e 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, Primar y 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 Vi tal 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 Unit 1 CVCS-Charging and Letdown 1-SOI-62.01 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 Pr imary 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 Di scharge 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 Unit 1 CVCS-Charging and Letdown 1-SOI-62.01 Rev. 0000 Page 8 of 108 2.2 Developmental References (continued)

H. Vendor Manual WBN-VTM-F180-5350, Vendor Technica l Manual for Foxboro Invensys Distributed Control System. I. Vendor Drawing 08F734235-FD-1600 series, Foxboro In vensys Functional Diagrams WBN Unit 1 CVCS-Charging and Letdown 1-SOI-62.01 Rev. 0000 Page 9 of 108 3.0 PRECAUTIONS AND LIMITATIONS NOTE During power changes, letdown should be ma ximized 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 ac hievable letdown heat exchanger outlet temperature is limited by the CCS temperature, which in turn is limited by river temperature (via ERCW cooling to t he CCS heat exchanger). The lowest achievable letdown heat exchanger outlet temperature is approximately 6 degrees higher than the river temperat ure. Attempting to operate with a letdown temperature less than 6 degrees higher than t he 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 te mperature changes.

Therefore, 1-HIC-62-78A, LETDOWN HX OUTLET TEMP TCV-70-192 CNTL should not

be allowed to control 1-TCV 192 at its full open position.

D. If Reactor Coolant (RC) filter is by passed, flow through demins should be secured or diverted to the HUT to prevent resin enteri ng RCS if the demin resin screen fails.

[C.2] E. Charging and Letdown are in service t ogether. If Letdown is olates or Charging is lost, the other must be isolated (see exception below). If Charging is lost and Letdown remains in service, flashing or li fting 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 Unit 1 CVCS-Charging and Letdown 1-SOI-62.01 Rev. 0000 Page 10 of 108 3.0 PRECAUTIONS AND LIMI TATIONS (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. Th is pneumatic relay has a bypass valve on panel L-112 to allow effective flow cont rol at low RCS pressures (i.e., heat-up and cool-down). H. Operating CCPs on mini-flow for ex tended periods could cause pump damage due to the small amount of water being re-circulated at high pressure. I. H 2 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 cl othing 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 ingesti on 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, ens ure ACB closing spring recharges. M. Explosive mixtures of hydrogen and oxygen in the VCT and the HUTs must be avoided at all times. The ox ygen 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-I SV-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 mu st 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 Unit 1 CVCS-Charging and Letdown 1-SOI-62.01 Rev. 0000 Page 11 of 108 3.0 PRECAUTIONS AND LIMI TATIONS (continued)

T. During Cold Shutdown (Mode 5), auxilia ry 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 in cluding 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 Ar eas (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. Radi ation Protection should be not ified of work having the potential to change radiological conditions. Z. When isolating any boron injection flow pat h to the core, care must be taken to ensure that the remaining available boron injection flow-paths are sufficient to meet the requirements of TR 3.1.1 (Modes 4, 5, & 6), and TR3.1.2 (Modes 1, 2, & 3).[C.8] AA. If hydrogen peroxide is to be added prio r to refueling, the RCS should be borated to the refueling boron concentrati on 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 reac tivity effects from dilution or boration due to water trapped in local piping must be considered, e.g., different CB at last pump run.

WBN Unit 1 CVCS-Charging and Letdown 1-SOI-62.01 Rev. 0000 Page 12 of 108 3.0 PRECAUTIONS AND LIMI TATIONS (continued)

DD. VCT Hydrogen and Nitrogen supp ly 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 Unit 1 CVCS-Charging and Letdown 1-SOI-62.01 Rev. 0000 Page 65 of 108 Date ________ INITIALS 8.9.2 Replacing Filter B with Filter A NOTE Opening valves slowly when placi ng 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 betw een 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 fi lter, and NOTIFY UO to record SR number.

(N/A if open WO available for filter replacement) ________

End of Section

NRCEXAM2015 301SystemJPMJ WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J NRC EXAM 2013-302 Page 2 of 18 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 WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J NRC EXAM 2013-302 Page 3 of 18 Tools/Equipment/Procedures Needed:

Hard-hat Safety Glasses Hearing Protection Plant Approved Shoes Gloves ALARA considerations Start this JPM at elevation 713' RP Table.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J NRC EXAM 2013-302 Page 4 of 18 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 obj ective 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 pe rforming 1-ES-1.1, SI Termination. 3. You are an AUO assigned to the shift.

INITIATING CUES:

The Unit Operator has directed you perf orm 1-ES-1.1, SI Termination, Appendix E, Operation of MOVs at Train A Elect rical 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 5 of 18 START TIME: _______

STEP 1: A. IF any of the following valves r equires manipulation from the Train A Rx MOV Bd, THEN PERFORM the applicable substep when directed by the UO/SRO:

3. 1-FCV-63-26, BIT Outlet Valve

a. GO TO 480V Rx MOV Bd 1A1-A, Compt. 11D.

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 c ontact 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:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 6 of 18 STEP 2: A. IF any of the following valves r equires manipulation from the Train A Rx MOV Bd, THEN PERFORM the applicable substep when directed by the UO/SRO:

3. 1-FCV-63-26, BIT Outlet Valve

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 t he 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:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 7 of 18 STEP 3: A. IF any of the following valves r equires manipulation from the Train A Rx MOV Bd, THEN PERFORM the applicable substep when directed by the UO/SRO:

3. 1-FCV-63-26, BIT Outlet Valve

d. VERIFY 1-FCV-63-26 CLOSE.

STANDARD: Applicant locates the valve positi on 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 light s are in the described state."

COMMENTS:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 8 of 18 STEP 4: A. IF any of the following valves r equires manipulation from the Train A Rx MOV Bd, THEN PERFORM the applicable substep when directed by the UO/SRO:

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:

___ SAT

___ UNSAT

CAUTION VCT outlet valves 1-LCV-62-132 and 1-LCV 133 must be open prior to closing RWST valves 1-LCV-62-135 and 1-LCV-62-136 to pr event loss of suction to the CCPs.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 9 of 18 STEP 5: A. IF any of the following valves r equires manipulation from the Train A Rx MOV Bd, THEN PERFORM the applicable substep when directed by the UO/SRO:

4. 1-LCV-62-132, VCT Outlet Valve

a. GO TO 480V Rx MOV Bd 1A1-A, Compt. 8B.

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 c ontact 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 hands witch 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:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 10 of 18 STEP 6: A. IF any of the following valves r equires manipulation from the Train A Rx MOV Bd, THEN PERFORM the applicable substep when directed by the UO/SRO:

4. 1-LCV-62-132, VCT Outlet Valve

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:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 11 of 18 STEP 7: A. IF any of the following valves r equires manipulation from the Train A Rx MOV Bd, THEN PERFORM the applicable substep when directed by the UO/SRO:

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 light s are in the described state."

COMMENTS:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 12 of 18 STEP 8: A. IF any of the following valves r equires manipulation from the Train A Rx MOV Bd, THEN PERFORM the applicable substep when directed by the UO/SRO:

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:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 13 of 18 STEP 9: A. IF any of the following valves r equires manipulation from the Train A Rx MOV Bd, THEN PERFORM the applicable substep when directed by the UO/SRO:

5. 1-LCV-62-135, RWST to VCT Valve

a. GO TO 480V Rx MOV Bd 1A1-A, Compt. 9A.

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 c ontact 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 hands witch 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:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 14 of 18 STEP 10: A. IF any of the following valves r equires manipulation from the Train A Rx MOV Bd, THEN PERFORM the applicable substep when directed by the UO/SRO:

4. 1-LCV-62-135, RWST to VCT Valve

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 t he 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:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 15 of 18 STEP 11: A. IF any of the following valves r equires manipulation from the Train A Rx MOV Bd, THEN PERFORM the applicable substep when directed by the UO/SRO:

3. 1-FCV-63-135, RWST to VCT Valve.

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 light s are in the described state."

COMMENTS:

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE J NRC EXAM 2013-302 STEP/STANDARD SAT/UNSAT Page 16 of 18 STEP 12: A. IF any of the following valves r equires manipulation from the Train A Rx MOV Bd, THEN PERFORM the applicable substep when directed by the UO/SRO:

5. 1-LCV-62-135, RWST to VCT Valve

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 t he 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:

___ SAT

___ UNSAT

STEP 13: Applicant reports that 1-ES-1.1, SI Termination, Appendix E, Steps 3 through 5 are complete STANDARD: Applicant reports to the Unit Operat or 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

___ SAT

___ UNSAT

STOP TIME ________

J

Handout Package for Applicant

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

J INITIAL CONDITIONS:

1. Unit 1 experienced an inadvertent safety injection (SI) actuation. 2. The control room crew is pe rforming 1-ES-1.1, SI Termination. 3. You are an AUO assigned to the shift.

INITIATING CUES:

The Unit Operator has directed you perf orm 1-ES-1.1, SI Termination, Appendix E, Operation of MOVs at Train A Elect rical 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.

WBN Unit 1 SI Termination 1-ES-1.1 Rev. 0002 Page 28 of 36 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

a. GO TO 480V Rx MOV Bd 1A1-A, Compt. 7B.

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

a. GO TO 480V Rx MOV Bd 1A1-A, Compt. 7A.

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.

WBN Unit 1 SI Termination 1-ES-1.1 Rev. 0002 Appendix E (Page 2 of 3)

Operation of MOVs at Train A Electrical Board 1.0 INSTRUCTIONS (continued)

Page 29 of 36

3. 1-FCV-63-26, BIT Outlet Valve

a. GO TO 480V Rx MOV Bd 1A1-A, Compt. 11D.

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

a. GO TO 480V Rx MOV Bd 1A1-A, Compt. 8B.

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.

WBN Unit 1 SI Termination 1-ES-1.1 Rev. 0002 Appendix E (Page 3 of 3)

Operation of MOVs at Train A Electrical Board 1.0 INSTRUCTIONS (continued)

Page 30 of 36

5. 1-LCV-62-135, RWST to VCT Valve

a. GO TO 480V Rx MOV Bd 1A1-A, Compt. 9A.

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.

2015 301NRCExamSystemJPMK WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K 2015-301 NRC Exam Page 2 of 12 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 WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K 2015-301 NRC Exam Page 3 of 12 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 WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K 2015-301 NRC Exam Page 4 of 12 READ TO APPLICANT

DIRECTION TO APPLICANT:

I will explain the initial conditions, which step(s) to simulate or discuss and provide initiating/operating cues. NO MANIPULATION OF PLANT EQUIPMEN T SHALL OCCUR DURING THIS JPM.

SIMULATE ALL MANIPULATIONS. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure that you indicate to me when you fully understand your task. To indicate that you have completed your assigned task return the cue sheet I provided you. 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.

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 5 of 12 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 RET ISOL [A4T/692].

STANDARD: 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 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 ha ndle is perpendicular to the pipe. COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 6 of 12 STEP 2: 2. CLOSE 1-ISV-70-553A, CCP 1A-A OIL COOLER CCS INLET ISOLATION.

STANDARD: The applicant locates 1-ISV-70-553A, CCP 1A-A OIL COOLER CCS 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:

CRITICAL STEP ___ SAT

___ UNSAT

STEP 3: 3. CLOSE 1-THV-70-554A, CCP 1A-A OIL COOLERS CCS OUTLET THROTTLE.

STANDARD: The applicant locates 1-THV-70-554A , CCP 1A-A OIL COOLERS CCS OUTLET THROTTLE and demonstrate s 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-THV-70-554A, state that the handwheel rotated several turns in the clockwise direction and has stopped COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 7 of 12 STEP 4: 4. CLOSE 1-DRV-67-1017B, CCP OIL CLR ERCW SUP XTIE HDR DRAIN.

STANDARD: The applicant locates 1-DRV-67-1017B, CCP OIL CLR ERCW SUP 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:

CRITICAL STEP ___ SAT

___ UNSAT

NOTE This step will result in dischar ging ERCW to the floor drain.

STEP 5: 5. ESTABLISH ERCW flow to lube oil cooler:

a. OPEN 1-ISV-67-1015B, CCP OIL CLR ERCW SUP XTIE ISOL. STANDARD: 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:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 8 of 12 STEP 6: 5. ESTABLISH ERCW flow to lube oil cooler:

b. OPEN 1-ISV-67-1016B, CCP OIL CLR ERCW SUP XTIE ISOL. STANDARD: 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:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 9 of 12 STEP 7: 5. ESTABLISH ERCW flow to lube oil cooler:

c. ENSURE cap removed, THEN OPEN 1-DRV-70-782A, CCP 1A-A OIL COOLERS CCS OUTL ET DRAIN to establish ERCW flow to oil coolers.

STANDARD: The applicant locates the pipe cap ju st downstream of 1-DRV-70-782A, CCP 1A-A OIL COOLERS CCS OUTL ET 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 fr om the hose fitting connected to the line.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE K 2015-301 NRC Exam STEP/STANDARD SAT/UNSAT Page 10 of 12 STEP 8: Notifies the Unit Operator that ERCW has been aligned to the 1A-A CCP Lube Oil Cooler.

STANDARD:

Applicant notifies the Unit Oper ator 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

___ SAT

___ UNSAT

STOP TIME ________

K

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

K 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.

WBN Unit 1 Loss of Component Cooling Water (CCS) 1-AOI-15 Rev. 0003 Page 41 of 48 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 602A, CVCS CCP ROOM CLR 1A-A ERCW RET ISOL, which is outside the room [A4T/692]

1. CLOSE 1-ISV-67-602A, CVCS CCP ROOM CLR 1A-A ERCW RET ISOL

[A4T/692].

2. CLOSE 1-ISV-70-553A, CCP 1A-A OIL COOLER CCS INLET ISOLATION.

3. CLOSE 1-THV-70-554A, CCP 1A-A OIL COOLERS CCS OUTLET THROTTLE.

4. CLOSE 1-DRV-67-1017B, CCP OIL CLR ERCW SUP XTIE HDR DRAIN.

NOTE This step will result in discharging ERCW to the floor drain.

5. ESTABLISH ERCW flow to lube oil cooler:

a. OPEN 1-ISV-67-1015B, CCP OIL CL R ERCW SUP XTIE ISOL.

b. OPEN 1-ISV-67-1016B, CCP OIL CL R ERCW SUP XTIE ISOL.

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.

ML15259A411

Text

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

1.0 INTRODUCTION

2.0 REFERENCES

4.0 PREREQUISI

4.1 Preliminar

6.2 Swappi

1.0 INTRODUCTION

2.0 REFERENCES

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

Navigation menu

Search