Text

Initial Exam 2010-301 Draft Sim/IN-Plant JPMs
	ML110140224
Person / Time
Site:	Watts Bar
Issue date:	10/19/2010
From:	; NRC/RGN-II
To:	; Tennessee Valley Authority
References
	50-390/10-301
	Download: ML110140224 (149)
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WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE Bta 201 0-08 NRC Exam B.1.a Perform a Minor Dilution.

PAGE 1 OF 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.a 2010-08 NRC Exam EVALUATION SHEET Task: Perform a Minor Dilution.

Alternate Path: After the minor dilution is started, 1-FCV-62-143, PW TO BLENDER and 1-FCV-62-128, MAKEUP TO VCT INLET fail open and cannot be closed.

1-FC-62-143, PW TO BLENDER FCV-62-143 CONTROL fails, causing primary water flow rate to go to maximum.

Facility JPM #: JPM 021 (Modified)

Safety Function: 1

Title:

Reactivity Control 004 A4.07 Ability to manually operate and/or monitor in the control room:

Boration/Dilution.

Rating(s): 3.9/3.7 CFR: 41.7/45.5to45.8 Evaluation Method: Simulator X In-Plant

References:

SOI-62.02, Boron Concentration Control, Rev. 50.

AOI-3, Malfunction of Reactor Makeup Controls, Rev. 27.

Task Number: RO-062-AOI-3-001

Title:

Respond to an inadvertent dilution at power.

Task Standard: The applicant:

1.) Aligns the CVCS system to accomplish a 35 gallon primary water addition using SOl-62.02, Boron Concentration Control, Section 6.6, Minor Dilution.

2.) After the controls fail, terminates the dilution by placing 1-HS-81-3A PRIMARY WATER PMP A in the STOP position per AOI-3.

Validation Time: 8 minutes Time Critical: Yes No X Applicant: Time Start:

NAME Docket No. Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner: /

NAME SIGNATURE DATE COMMENTS PAGE 2 OF 12

WATTS BAF UCLEAR PLANT JOB PERFORMANCE MEASURE B.1.a 201 0-08 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:

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 lC# 307.

d. Select Reset on the drop down menu.

e. Right click on RESET.

f. Enter the password for lC# 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 hs-62-1 28 hs-62-1 28 boric acid blender to vct inlet sw 20 00:00:00 00:00:00 open 00:00:00 hs-62-143 hs-62-143 primary water to boric acid blender valv 20 00:00:00 00:00:00 open 00:00:00 fc-62-143 fc-62-143 primary water flow controller 20 00:00:00 00:00:00 open 00:00:00

4. Insert NRC Exam Flash Drive. Open B.ta NRC Exam JPM.evt to load the correct event file.

5. Place simulator in RUN and acknowledge any alarms.

6. ENSURE the laminated copy of SOl-62.02, Boron Concentration Control, Section 6.6, Minor Dilution, has been cleaned to remove any marks.

PAGE 3 OF 12

WATTS BAF UCLEAR PLANT JOB PERFORMANCE MEASURE B.1.a 201 0-08 NRC Exam

7. ENSURE Extra Operator is present in the simulator.

8. Place simulator in FREEZE until Examiner cue is given.

PAGE 4 OF 12

WATTS BAFUCLEAR PLANT JOB PERFORiVIANCE MEASURE B.1.a 201 0-08 NRC Exam SIMULATOR CONTINGENCY ACTIONS:

IF INITIAL CONDITION 307 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 hs-62-1 28 hs-62-1 28 boric acid blender to vct inlet sw 20 00:00:00 00:00:00 open 00:00:00 hs-62-143 hs-62-143 primary water to boric acid blender valv 20 00:00:00 00:00:00 open 00:00:00 fc-62-1 43 fc-62-1 43 primary water flow controller 20 00:00:00 00:00:00 open 00:00:00

4. Create the following event using the EVENT function:

PAGE 5 OF 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.a 2010-08 NRC Exam READ TO APPLICANT DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. A dilution of 35 gallons is required for Tavg control.

2. You are an extra Control Room Operator.

INITIATING CUES:

1. The Unit Supervisor directs you perform SOI-62.02,Boron Concentration Control, Section 6.6, Minor Dilution.

2. You are to notify Unit Supervisor when you have completed Section 6.6.

PA(F R OF 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.a 2010-08 NRC Exam STEPISTANDARD I SATIUNSAT START TIME:

NOTES

1) Section 6.6, Minor Dilution, may be reproduced, laminated, displayed, reused, etc.

as desired.

2) Minor Dilution is defined as the addition of Primary Water done several times each shift to compensate for fuel burn-up, and maintain Tavg on program.

STEP 1: [1] ENSURE 1-HS-68-341H, BACKUP HEATER C, is ON, to SAT equalize Pzr-RCS CB.

UNSAT STANDARD:

Applicant locates 1-HS-68-341H, BACKUP HEATER C on panel 1-M-5 and rotates the handswitch to the right to the ON position. Applicant verifies that the RED indicating light is LIT and the GREEN indicating light is DARK.

COMMENTS:

STEP 2: [2] ADJUST 1-FQ-62-142, PW BATCH COUNTER, for required CRITICAL quantity. STEP STANDARD: SAT Applicant determines that the required quantity of primary water is UNSAT 35 gallons from the INITIAL CONDITIONS.

depresses the black pushbutton, and then lifts the red cover and enters 000035 in the display on 1-FQ-62-142. (Critical).

Step is critical to ensure proper control of reactivity is maintained COMMENTS:

PAGE 7 OF 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.a 2010-08 NRC Exam STEPISTANDARD SAT/UNSAT STEP 3: [3] PLACE 1-HS-62-140B, VCT MAKEUP MODE in DIL. CRITICAL STEP STANDARD:

SAT rotates 1-HS-62-140B to the right, from the AUTO position to the DIL position (Critical). UNSAT Step is critical since this action enables the proper interlocks for the dilution flowpath.

COMMENTS:

STEP 4: [4] TURN 1-HS-62-140A, VCT MAKEUP CONTROL, to START. CRITICAL STEP

[4.1] CHECK Red light is LIT.

SAT STANDARD:

UNSAT rotates 1-HS-62-140A, VCT MAKEUP CONTROL, to the right to the START position (Critical).

Applicant checks the RED indicating light is LIT and the GREEN indicating light is DARK.

Step is critical since this action initiates the dilution.

COMMENTS:

EXAMINER: When 1-HS-62-140A, VCT MAKEUP CONTROL, is placed to START, 1-FCV-62-143 will fail to the full open position. This will cause dilution flow rate to go to its maximum value. The applicant will be unable to manually close 1-FCV-62-128, 1-FCV-62-143 or to manually reduce flow using 1-FC-62-143 from panel 1-M-6.

EXAMINER: Since the automatic control circuit associated with the dilution has failed the applicant may take manual actions to close the affected valves and stop the running primary water pump prior to entering AOI-3, Malfunction of Makeup Control.

PAGE8OF12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.a 2010-08 NRC Exam STEPISTANDARD I SATIUNSAT STEP 5: Applicant attempts closure of 1-FCV-62-128 and 1-FCV-62-143 SAT to terminate the dilution.

UNSAT STANDARD:

Applicant attempts to close 1-FCV-62-128, 1-FCV-62-143 by placing handswitches in the CLOSE position.

Applicant determines that neither 1-FCV-62-128 nor 1-FCV-62-143 will close and continues to the next step.

COMMENTS:

STEP 6: Refers to AOl-3, MALFUNCTION OF REACTOR MAKEUP SAT CONTROL, for actions.

UNSAT STANDARD:

Applicant refers to AOI-3,Malfunction of Reactor Makeup Control for actions.

COMMENTS:

EXAMINER: The following actions are taken from AOI-3, Malfunction of Reactor Makeup Control, Section 3.2, Inadvertent Dilution.

PAGE 9 OF 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.a 2010-08 NRC Exam STEP/STANDARD I SAT/UNSAT STEP 7: 1. PERFORM the following: CRITICAL STEP

a. CHECK PWST in normal alignment (PWST NOT in Bypass Mode). SAT

b. ENSURE standby primary water pump HS in MAN. UNSAT c STOP the running primary water pump.

d. STOP the waste gas compressors by placing Handswitches in STOP! PULL-TO-LOCK.

STANDARD:

Applicant contacts an AUO to determine PWST alignment.

CUE: If requested, report as the AUO that the primary water system is in normal alignment Applicant determines that the standby primary water pump HS is in MANUAL.

1-HS-81-7A is pushed in and GREEN indicating light is LIT, RED indicating light is DARK.

rotates 1-HS-81-3A, PRIMARY WATER PMP A to the left to the STOP positiOn. (Critical).

Applicant verifies GREEN indicating light is LIT, RED indicating light is DARK.

Applicant notifies the Auxiliary Building AUO to place the waste gas compressor switches in STOP, PULL-TO-LOCK position.

CUE: When requested, the console operator will acknowledge the request to place the Waste Gas Compressors in STOP-PULL LOCK.

Stopping the running primary water pump is critical since this action terminates primary water flow.

COMMENTS:

PAGE 10 OF 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.a 2010-08 NRC Exam STEPISTANDARD SATIUNSAT STEP 8: 2. ENSURE primary water flow to blender isolated: SAT

a. CLOSE 1-FCV-62-143, PW To Blender. UNSAT

b. CHECK 1-FI-62-142, PW To Blender Flow, ZERO.

STANDARD:

Applicant determines that 1-FCV-62-143 has remained open and enters the RESPONSE NOT OBTAINED column for actions.

COMMENTS:

STEP 9: 2. RESPONSE NOT OBTAINED: SAT Locally CLOSE 1-ISV-62-933, CVCS BA Blender PW Supply UNSAT Isol [A3V/7131.

STANDARD:

Applicant dispatches an AUO to close 1-ISV-62-933 locally.

CUE: When requested, the console operator will close 1-ISV 933 and report back that the valve has been closed.

After the request is made to locally close 1-ISV-62-933, inform the applicant that another operator will complete the actions of AOl-3.

Applicant reports the status of the plant to the Unit Supervisor.

COMMENTS:

END OF TASK STOP TIME PAGE 11 OF 12

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

DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. A dilution of 35 gallons is required for Tavg control.

2. You are Control Room Operator.

INITIATING CUES:

1. The Unit Supervisor directs you perform SOl-62.02,Boron Concentration Control, Section 6.6, Minor Dilution.

2. You are to notify Unit Supervisor when you have completed Section 6.6.

B.1.a

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.b 2010-08 NRC Exam B.1.b Fill Cold Leg Accumulator 4 PAGE 1 OF 18

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.ib 2010-08 NRC Exam EVALUATION SHEET Task: Fill Cold Leg Accumulator 4.

Alternate Path: n/a Facility JPM #: 3-OT-JPMRO27 (Modified to pressure less than 1650 psig, requiring additional procedure steps to be performed).

Safety Function: 2

Title:

Reactor Coolant System Inventory Control

!ui& 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

References:

SO1-63.01, Safety Injection System, Rev. 44.

Task Number: RO-063-SOl-63-001

Title:

Add water to cold leg accumulators while in service.

Task Standard: Applicant adds water to the cold leg accumulator using lA-A Safety Injection pump, in accordance with SOl-63.01, Safety Injection System, Section 8.3.4, Add Water to CLA 4, until 134-A, CL ACCUM 4 LEVEL HI/LO is DARK.

Validation Time: 18 minutes Time Critical: Yes No X Applicant: Time Start:

NAME Docket No. Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner: /

NAME SIGNATURE DATE COMMENTS PAGE 2 OF 18

WATTS BP NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.b 201 0-08 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. RESET to Initial Condition 309 by performing the following actions:

a. Select lCManager 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.

4. ENSURE the following annunciator windows are LIT:

a. 134-A, CL ACCUM 4 LEVEL HIILO

b. 134-B CL ACCUM 4 PRESS HIILO

5. Place simulator in RUN and acknowledge any alarms.

6. ENSURE copies of SOI-63.01, Section 8.3.4 are available forthe Examiner.

7. ENSURE Extra Operator is present in the simulator.

8. Place simulator in FREEZE until Examiner cue is given.

PAGE 3 OF 18

WATTS Bi N NUCLEAR PLANT JOB PERFORMANCE MEASURE B.ib 2010-08 NRC Exam SIMULATOR CONTINGENCY ACTIONS:

IF INITIAL CONDITION 309 is unavailable for any reason, the following actions must be taken to reconstruct the IC.

1. Initialize to.

2. Perform switch check.

3. Enter the following using the DIRECTOR function.

Key Type Event Delay Inserted Ramp Initial Final Value hs-62-1 28 hs-62-1 28 boric acid blender to vct inlet sw 20 00:00:00 00:00:00 open 00:00:00 hs-62-143 hs-62-143 primary Water to boric acid blender valv 20 00:00:00 00:00:00 open 00:00:00 fc-62-1 43 fc-62-1 43 primary water flow controller 20 00:00:00 00:00:00 open 00:00:00

4. Create the following event using the EVENT function:

PAGE 4 OF 18

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.b 201 0-08 NRC Exam READ TO APPLICANT DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. Unit I is in Mode 3, with a plant heatuplstartup in progress.

2. Annunciator window 134-A, CL ACCUM 4 LEVEL HI/LO is LIT.

3. You are an extra operator assigned to the shift.

INITIATING CUES:

1. The Unit Supervisor directs you to fill Cold Leg Accumulator (CLA) 4 using SOI 63.01, Safety Injection System, Section 8.3.4, Add Water to CLA4, using the IA-A Safety Injection pump.

2. SOl-63.01, Safety Injection System, Section 5.1, Fill & Vent SI Pumps and Piping from RWST is complete.

3. Inform the Unit Supervisor when CLA 4 has been filled and window 134-A, CL ACCUM 4 LEVEL HIILO has cleared.

PA(F 5 OF IR

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.b 2010-08 NRC Exam STEPISTANDARD SAT/UNSAT START TIME:

CAUTION Adding water to more than one CLA at a time while they are required to be operable places the plant outside design basis. This section is to be used to add water to any selected single CLA. If more than one CLA needs water, separate evolutions must be performed.

STEP 1: [1] ENSURE Sect 5.1, to Fill & Vent SI Pmps and Piping, SAT COMPLETE.

UNSAT STANDARD:

Applicant determines from INITIATING CUES that Section 5.1 is complete.

STEP 2: [2] IF RCS pressure is 1000 psig, THEN ENSURE 1-FCV SAT 67, CL ACCUM 4 OUTLET, CLOSED.

UNSAT STANDARD:

Applicant determines that RCS pressure is greater than 1000 psig, at approximately 1520 psig.

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

COMMENTS:

CAUTION If RCS is 1650 psig or less, ALL SIP flow paths must be disabled to prevent inadvertent RCS injection, If 1-FCV-63-152 is closed, then SI Pmp A is the only pump that can be used to fill CLA.

PAGE 6 OF 18

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.b 2010-08 NRC Exam STEPISTANDARD SATIUNSAT STEP 3: [3] IF RCS 1650 psig or less, AND SIP A is to be used to CRITICAL fill CLA 4, THEN CLOSE 1-FCV-63-152, SI PMP A TO STEP CL 1-2-3-4 [1- M-6].

SAT STANDARD:

UNSAT determines the RCS pressure IS less than 1650 psig (approximately 1 520 psig) and that I -FCV-63-1 52, SI PMP A TO CL 1-2-3-4 must be closed (Critical).

rotates handswitch I -HS-63-1 52 to the left to the CLOSE position (Critical).

Applicant determines that the valve is CLOSED by observing the RED light is DARK and GREEN light is LIT.

Indicated steps are critical to prevent injection of water into the RCS from the safety injection pump.

COMMENTS:

CAUTION In Mode 4, 5, 6 with the Rx Vessel Head ON, before starting SI Pmp A, 1-FCV-63-152 and 156 must be closed, with Hold tags on the handwheels and breakers (Refer to T.S.

3.4.12).

STEP 4: [4] IF in Mode 4, 5, or 6 and SIP A is to be used with Rx Vessel SAT Head ON, THEN....

UNSAT STANDARD:

Applicant determines from the IINITIAL CONDITIONS that the Unit is in Mode 3 50 Step 4 and its sub steps are not applicable. The applicant marks step 4 N/A.

COMMENTS:

PAGE 7 OF 18

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.b 2010-08 NRC Exam STEP/STANDARD I SATIUNSAT 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).

SAT STEP 5: [5] IF in Mode 4, 5, or 6 and SIP B is to be used with Rx Vessel Head ON THEN: ... UNSAT STANDARD:

Applicant determines from the INITIAL CONDITIONS that the 1A Safety Injection pump will be used to fill the accumulator so Step 5 and its sub steps are not applicable. The applicant marks step 5 N/A.

COMMENTS:

PAGE 8 OF 18

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.b 2010-08 NRC Exam STEPISTANDARD SAT/UNSAT STEP 6: [6} PERFORM the following: CRITICAL STEP PERF NOMENCLATURE LOC POSITION UNID INITIAL SAT TEST LINE 1-M-6 DFE 1-FCV-63-187 (1.XS631DO) ISOL UNSAT CKVTESTLINETO 1-M-6 OFEF 1-FCV-63-71 H UT CLA FILL FROM SI 1-M-6 OPEI\ 1-FC\!-63-23 PMPS STANDARD:

depresses pushbutton 1-HS-30-187 on the 0KV LEAK TEST panel (Critical).

Applicant verifies GREEN light for 1-HS-30-187 is DARK and RED light for I -HS-30-1 87 is LIT.

rotates handswitch I-HS-63-71A to the right to the OPEN position (Critical).

Applicant verifies GREEN light for 1-HS-63-71A is DARK and the RED light for 1-HS-63-71A is LIT.

rotates handswitch I -HS-63-23A to the right to the OPEN position (Critical).

Applicant verifies GREEN light for 1 -HS-63-23A is DARK and the RED light for 1-HS-63-71A is LIT.

Indicated steps are critical to establish a flowpath to the accumulator to be filled.

COMMENTS:

CAUTION If 1-FCV-63-152 was closed in step 8.3.4[3], then SI Pmp A is the only pump that can beusedtofillCLA.

PAGE 9 OF 18

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.b 2010-08 NRC Exam STEP/STANDARD I_SAT/UNSAT STEP 7: [7] ENSURE the following (N/A pump NOT selected): SAT FF UNSAT NOW;E% 0L4-rUR LC NID INWAL

r.wc ECIC C i i-FCV-.

RECIR:

T i-HE E REcIR:

r i-M-E EN

V

1o :

1-M-E CEk MF A CJCT iME EN

MP i-M :EN STANDARD:

Applicant determines 1-HS-63-3 is OPEN by observing GREEN light for 1 -HS-63-3 is DARK and RED light for I -HS-63-3 is LIT.

Applicant determines 1-HS-63-4 is OPEN by observing GREEN light for 1 -HS-63-4 is DARK and RED light for 1 -HS-63-4 is LIT.

Applicant enters N/A for 1 -FCV-63-1 75, since 1 A SI pump will be used for filling the #4 CLA.

Applicant determines 1-HS-63-5 is OPEN by observing GREEN light for 1-HS-63-5 is DARK and RED light for 1-HS-63-5 is LIT.

Applicant determines 1-HS-63-47 is OPEN by observing GREEN light for I -HS-63-47 is DARK and RED light for I -HS-63-47 is LIT.

Applicant enters N/A for 1-FCV-63-48, since 1A SI pump will be used for filling the #4 CLA.

COMMENTS:

PAGE 10 OF 18

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.b 2010-08 NRC Exam STE PISTAN DARD SATIUNSAT STEP 8: [8] PERFORM the following (N/A pump NOT selected): CRITICAL STEP PERF NOMENCLATURE LOC POSITION UNID INITIAL SAT SI PMP A (ECCS) 1-M-6 START 1-HS-63-1OA SI PMP B (ECCS) 1-M-6 START 1-HS-63-15A UNSAT STANDARD:

rotates handswitch I -HS-63-1 OA to the right to the START position (Critical).

Applicant verifies GREEN lights for 1-HS-63-1OA is DARK and the RED light for 1 -HS-63-1 OA is LIT.

Applicant observes amps for the 1A SI Pump on I -EI-63-1 2A, rising.

Applicant observes discharge pressure for the 1A SI Pump on 1-PI-63-1 50, rising.

Applicant enters N/A for 1 -HS-63-1 5A, SI PMP B (ECCS).

Step is critical since the IA SI pump provides flow from the RWST tofiIICLA4.

COMMENTS:

PAGE 11 OF 18

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.b 2010-08 NRC Exam STEP/STANDARD SAT/UNSAT STEP 9: [9] OPEN 1-FCV-63-70, MAKEUP TO CL ACCUM 4, [1-M-6]. CRITICAL STEP STANDARD:

SAT rotates handswitch 1-HS-63-70A to the right to the OPEN position (Critical). UNSAT Applicant verifies GREEN light for 1-HS-63-70A is DARK and the RED light for 1-HS-63-70A is LIT.

Step is critical since opening 1-FCV-63-10 completes the flow path for filling CLA 4.

COMMENTS:

NOTE 1-Ll-63-82, CLA 4 LEVEL [1-M-6], is preferred to monitor level due to faster response than 1-Ll-63-60.

PAGE 12 OF 18

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.b 2010-08 NRC Exam STEP/STANDARD I SATIUNSAT STEP 10: [101 WHEN CLA is at desired level (Alarm 134-A, CL ACCUM 4 CRITICAL LEVEL Hl/LO, NOT LIT), THEN PERFORM the following: STEP PERF VERIF SAT NOMENCLATURE LOC POSITION UNID INITIAL INITIAL MAKEUP TO CL 1-M-6 CLOSED 1-FCV-63-70 ACCUM4 IV UNSAT CKV TEST LINE TO 1 -M-6 CLOSED 1 -FCV-63-71 HUT IV TEST LINE 1-M-6 CLOSED 1-FCV-63-187 (1-XS-63-100) ISOL IV CLA FILL FROM SI 1-M-6 CLOSED 1-FCV-63-23 PMPS IV STANDARD:

When accumulator level has increased to the point where Alarm 134-A is clear (greater than 7660 gallons) then rotates handswitch 1-HS-63-70A to the left to the CLOSED position (Critical).

Applicant verifies GREEN lights for 1-HS-63-70A is LIT and the RED light for 1-HS-63-71A is DARK.

Applicant rotates handswitch 1-HS-63-71A to the left to the CLOSED position.

Applicant verifies GREEN light for 1-HS-63-71A is LIT and the RED light for 1-HS-63-71A is DARK.

Applicant depresses pushbutton 1-HS-30-187 on the CKV LEAK TEST panel.

Applicant verifies GREEN light for 1-HS-30-187 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 4 accumulator, preventing possible overfill of CLA 4.

COMMENTS:

PAGE 13 OF 18

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.b 2010-08 NRC Exam STEP/STANDARD SAT/UNSAT STEP 11: [11] ENSURE SI pump has operated for greater than 20 CRITICAL minutes, THEN PERFORM the following (N/A pump NOT STEP selected):

SAT PE RF NOMENCLATURE LOC POSITION UNID INITIAL UNSAT SI PMPA(ECCS) 1-M-6 STOP 1-HS-63-1OA Si PMP B (ECCS) 1-M..6 STOP 1-HS-63-15A STANDARD:

rotates handswitch 1 -HS-63-1 OA to the left to the STOP position (Critical).

Applicant verifies GREEN light for 1-HS-63-IOA is LIT and the RED light for 1-HS-63-1OA 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:

NOTE Step 8.3.4[12] or 8.3.4[13] may be N/Ad based on SIPs operability requirements.

PAGE 14 OF 18

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.b 2010-08 NRC Exam STEP/STANDARD I SAT/UNSAT STEP 12: [12] ENSURE the following (N/A pump not selected): SAT PERF VERIF UNSAT NOMENCLATURE LOC POSITION UNID INITIAL INITIAL SI PMPA (ECCS) 1-M-6 A AUTO 1-HS-63-1OA IV SI PMP B (ECCS) 1-M-6 A AUTO 1-HS-63-15A IV STANDARD:

Applicant observes handswitch 1-HS-63-1OA, SI PMP A (ECCS) in the A-AUTO position (mid position on handswitch).

Applicant enters N/A for 1-HS-63-15A, SI PMP (ECCS).

COMMENTS:

STEP 13: [13] ENSURE the following (NIA pump not selected): SAT PERF VERIF UNSAT NOMENCLATURE LOC POSITION UNID INITIAL INITIAL SI PMPA(ECCS) 1-M-G PULL-TO- 1-HS-63-IOA LOCK IV SI PMP B ECCS) 1-M-6 PULL-TO- 1-HS-63-15A LOCK IV STANDARD:

Applicant enters N/A for Step 13, since the safety injection pumps are required to be in the A-AUTO position to support ECCS standby alignment.

COMMENTS:

PAGE 15 OF 18

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.b 2010-08 NRC Exam STEPISTANDARD I_SATIUNSAT STEP 14: [14] IF 1-FCV-63-152 was closed in Step 8.3.4[3], THEN OPEN CRITICAL 1-FCV-63-152, SI PMP A TO CL 1-2-3-4 [1-M-6] (N/A in STEP Mode 4, 5, 6).

SAT STANDARD:

UNSAT rotates 1 -HS-63-1 52 handswitch to the right to the OPEN position and determines that the valve is open by observing the RED light is LIT and GREEN light is DARK.

Step is critical since opening 1-FCV-63-152 aligns IA safety injection pump discharge to cold legs I through 4.

COMMENTS:

STEP 15: [15] IF 1-FCV-63-67 was closed in Step 8.3.4[2], THEN OPEN SAT 1-FCV-63-67, CL ACCUM 4 OUTLET if desired.

UNSAT STANDARD:

Applicant enters N/A for Step 15, since 1-FCV-63-67 was not closed.

COMMENTS:

NOTE CLA 4 press can be read on 1-PI-63-61 or 62.

PAGE 16 OF 18

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.b 2010-08 NRC Exam STEP/STANDARD SAT/UNSAT_I STEP 16: [16] VERIFY CLA PRESS in desired range (Alarm 1 34-B, CL SAT ACCUM 4 PRESS HI/LO, NOT LIT).

UNSAT STANDARD:

Applicant determines that cold leg accumulator pressure is in the desired range (alarm 134-B DARK).

COMMENTS:

STEP 17: Applicant reports that Cold Leg Accumulator 4 has been filled. SAT STANDARD: UNSAT Applicant informs the Unit Supervisor that Cold Leg Accumulator 4 has been filled.

COMMENTS:

END OF TASK STOP TIME PAGE 17 OF 18

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

DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

I. Unit I is in Mode 3, with a plant heatuplstartup in progress.

2. Annunciator window 134-A, CL ACCUM 4 LEVEL HIILO is LIT.

3. You are an extra operator assigned to the shift.

INITIATING CUES:

1. The Unit Supervisor directs you to fill Cold Leg Accumulator (CLA) 4 using SOI 63.01, Safety Injection System, Section 8.3.4, Add Water to CLA 4, using the IA-A Safety Injection pump.

2. S01-63.01, Safety Injection System, Section 5.1, Fill & Vent SI Pumps and Piping from RWST is complete.

3. Inform the Unit Supervisor when CLA 4 has been filled and window 134-A, CL ACCUM 4 LEVEL HI/LO has cleared.

B.1.b

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.c 2010-08 NRC Exam B.I.c Perform ES-I .3, Transfer to Containment Sump.

PAGE 1 OF 1E

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.c 201 0-08 NRC Exam EVALUATION SHEET Task: Perform ES-i .3, Transfer to Containment Sump.

Alternate Path: During performance of ES-i .3, Transfer to Containment Sump, the applicant will be unable to reposition 1-FCV-63-3 and i-FCV-63-il, requiring compensatory actions to be taken.

Facility JPM #: 3-OT-JPM 021 Safety Function: 3

Title:

Reactor Pressure Control K/A EA1 .i I Ability to operate and monitor the following as they apply to a Large Break LOCA: Long-term core cooling.

Rating(s): 4.2/4.2 CFR: 41.7 / 45.5 / 45.6 Evaluation Method: Simulator X In-Plant

References:

ES-i .3, Transfer to Containment Sump, Rev. 17.

Task Number: RO-i13-ES-i.3-00i

Title:

Perform transferto Containmentsump.

Task Standard: Applicant performs aligns the ECCS pumps for containment sump recirculation using ES-i .3, Transfer to Containment Sum p.

Validation Time: 15 minutes Time Critical: Yes No X Applicant: Time Start:

NAME Docket No. Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner: /

NAME SIGNATURE DATE COMMENTS PAGE 2 OP 16

WATTS BArIUCLEAR PLANT JOB PERFOtMANCE MEASURE B.1.c 2010-08 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:

ENSURE NRC Examination Security has been established.

2. RESET to Initial Condition 308 by performing the following actions:

a. Select lCManager on the THUNDERBAR menu (right hand side of Instructor Console Screen).

b. Locate IC# 308.

c. Right click on IC# 308.

d. Select Reset on the drop down menu.

e. Right click on RESET.

f. Enter the password for IC# 308.

g. Select Yes on the INITIAL CONDITION RESET pop-up window.

h. Perform SWITCH CHECK.

3. ENSURE the following information appears on the Director Summary Screen:

Key Type Event Delay Inserted Ramp Initial Final Value th02c loca cold leg ioop 3 M 00:00:00 00:00:00 00:00:00 80 80 hs-63-3a hs-63-3a sip recirc to rwst isolation valve sw 0 00:00:00 00:00:00 open 00:00:00 hs-63-1 I a hs-63-1 1 a rhr heat exch b discharge to ccp suction 0 00:00:00 00:00:00 open 00:00:00

4. Place simulator in RUN and acknowledge any alarms.

5. ENSURE a marked-up copy of ES-I .3, Transfer to Containment Sump, is available for the Examiner.

6. ENSURE the Extra Operator is present in the simulator.

7. Place simulator in FREEZE until Examiner cue is given.

PAGE 3 OF 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.c 2010-08 NRC Exam READ TO APPLICANT DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. A large break loss-of-coolant event occurred 22 minutes ago.

2. The crew responded using E-1, Loss of Reactor or Secondary Coolant, and transitioned to ES-I .3, Transfer to Containment Sump.

3. ES-I .3, Transfer to Containment Sump, has been performed through Step 9.

INITIATING CUES:

I. The Unit Supervisor directs you to complete transfer of the Emergency Core Cooling Pump (ECCS) suctions using ES-I .3, Transfer to Containment Sump, by performing steps 10 through 20.

2. Inform the Unit Supervisor when step 20 is complete.

PAflF 4 OF IA

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.c 2010-08 NRC Exam STEPISTANDARD I SAT/UNSAT START TIME:

CAUTION If a valve fails during the transfer sequence, any corrective action should be postponed UNTIL transfer is complete, EXCEPT as required to satisfy each step.

NOTE Each transfer sequence action is identified by a number on the control board (e.g.

1).

STEP 1: 10. (#1) ISOLATE SI pump miniflow: CRITICAL STEP

CLOSE 1-FCV-63-3.

CLOSE 1-FCV-63-175. SAT

CLOSE 1-FCV-63-4. UNSAT STANDARD:

Applicant rotates handswitch 1 -HS-63-3 left to the CLOSE position Applicant identifies the valve will NOT CLOSE by observing the RED light has remained LIT and GREEN light is DARK.

rotates handswitch 1 -HS-63-1 75 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.

rotates handswitch 1-HS-63-4 to the left to the CLOSE position (Critical).

Applicant determines that the valve is CLOSED by observing the RED light is DARK and GREEN light is LIT.

determines that the RESPONSE NOT OBTAINED column must be entered based on the failure of 1-FCV-63-3 to close (Critical).

Steps are critical since closure of the recirculation valves prevents radioactive sump water from being pumped to the RWST.

COMMENTS:

PAGE 5 OF 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.c 2010-08 NRC_Exam STEPISTANDARD SATIUNSAT STEP 2: 10. RESPONSE NOT OBTAINED: SAT ENSURE either: UNSAT

a. 1-FCV-63-3 CLOSED, OR

b. 1-FCV-63-4 and 1-FCV-63-175 CLOSED.

STANDARD:

Applicant determines that 1 -FCV-63-4 and 1 -FCV-63-1 75 are CLOSED by observing GREEN indicating lights LIT on each handswitch.

COMMENTS:

PAGE 6 OF 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.c 2010-08 NRC Exam STEP/STANDARD I_SATIUNSAT STEP 3: 11. (#2) ISOLATE RHR crossties: CRITICAL STEP

CLOSE 1-FCV-74-33.

SAT

CLOSE 1-FCV-74-35.

UNSAT STANDARD:

rotates handswitch 1-HS-74-33 left to the CLOSE position (Critical).

Applicant identifies the valve is CLOSED by observing the RED light is DARK and GREEN light is LIT.

rotates handswitch 1-HS-74-35 to the left to the CLOSE position (Critical).

Applicant determines that the valve is CLOSED by observing the RED light is DARK and GREEN light is LIT.

Step is critical to provide complete separation of the two low-head SI cold leg injection headers. Also, by closing these valves, a desirable increase in the total system resistance is obtained should only one RHR pump be available, since it would deliver to only two RHR branch lines while simultaneously delivering to the suction of the operating charging and SI pumps.

COMMENTS:

PAGE 7 OF 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.c 2010-08 NRC Exam STEPISTANDARD SAT/UNSAT STEP 4: 12. (#3) ALIGN charging pump and SI pump supply from RHR: CRITICAL STEP

OPEN 1-FCV-63-6.

SAT

OPEN 1-FCV-63-7.

UNSAT

ENSURE 1-FCV-63-177 OPEN.

STANDARD:

rotates handswitch 1-HS-63-6 right to the OPEN position (Critical).

Applicant identifies the valve is OPEN by observing the RED light is LIT and GREEN light is DARK.

rotates handswitch I -HS-63-7 right to the OPEN position (Critical).

Applicant identifies the valve is OPEN by observing the RED light is LIT and GREEN light is DARK.

Applicant determines 1-HS-63-177 is OPEN observing the RED light is LIT and GREEN light is DARK.

Step is critical since this alignment is required to support long term cooling from the containment sump.

COMMENTS:

NOTE 1-FCV-63-8 and 1-FCV-63-11 are interlocked with the SI pump miniflows being full closed.

PAGE 8 OF 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.tc 2010-08 NRC Exam STEPISTANDARD SATIUNSAT STEP 5: 13. (#4) ALIGN RHR discharge to charging pump and SI pump CRITICAL suction: STEP

a. OPEN 1-FCV-63-8. SAT STANDARD: UNSAT rotates handswitch 1-HS-63-8 right to the OPEN position (Critical).

Applicant identifies the valve is OPEN by observing the RED light is LIT and GREEN light is DARK.

Step is critical since this alignment is required to support long-term cooling from the containment sump.

COMMENTS:

STEP 6: 13. (#4) ALIGN RHR discharge to charging pump and SI pump SAT suction:

UNSAT

b. OPEN 1-FCV-63-11.

STANDARD:

rotates handswitch 1 -HS-63-1 I right to the open position.

Applicant identifies the valve will NOT OPEN by observing the RED light has remained DARK and GREEN light is LIT.

determines that the RESPONSE NOT OBTAINED column must be entered based on the failure of 1-FCV-63-1 I to OPEN.

COMMENTS:

PAGE 9 OF 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.c 2010-08 NRC Exam STEP/STANDARD I SAT/UNSAT STEP 7: 13.b RESPONSE NOT OBTAINED: SAT ENSURE Train A RHR operation: UNSAT

Train A RHR pump RUNNING.

1-FCV-63-8 OPEN.

Either 1-FCV-63-6 or 1-FCV-63-7 OPEN.

STANDARD:

Applicant determines that the IA RHR pump is running by observing motor amps on 1-EI-74-5A, discharge pressure on 1-PI-74-13.

Applicant determines that 1 -FCV-63-8, RHR PMP A TO CHARGING PMPS SUCT is OPEN by observing RED light is LIT and GREEN light is DARK.

Applicant determines that 1-HS-63-6 is OPEN by observing the RED light is LIT and GREEN light is DARK.

Applicant determines that 1 -HS-63-7 is OPEN observing the RED light is LIT and GREEN light is DARK.

COMMENTS:

STEP 8: 14. DO NOT CONTINUE this Instruction UNTIL Steps 10 thru 13 SAT complete.

UNSAT STANDARD:

Applicant determines that all steps or related contingency actions have been completed and continues to Step 15.

COMMENTS:

PAGE 10 OF 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.l.c 2010-08 NRC Exam STEP/STANDARD SAT/UNSAT CAUTION If RCS press is greater than 1350 psig, the SI pumps should NOT be restarted because the recirc path is isolated.

STEP 9: 15. RESTART any charging pumps and SI pumps as necessary. SAT STANDARD: UNSAT Applicant determines that all charging and SI pumps are running.

COMMENTS:

CAUTION If offsite power is lost after SI reset, manual action will be required to restart the SI pumps and RHR pumps due to loss of SI start signal.

STEP 10: 16. (#5) RESET SI, and CHECK the following: CRITICAL STEP

SI ACTUATED permissive DARK.

SAT

AUTO SI BLOCKED permissive LIT.

UNSAT STANDARD:

Applicant depresses each SI reset pushbutton on panel 1-M-6 and observes the SI ACTUATED permissive light DARK, and the AUTO SI BLOCKED light is LIT.

Step is critical since the valves to be operated in subsequent steps cannot be repositioned until the SI signal is reset.

COMMENTS:

PAGE 11 OF 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.c 2010-08 NRC Exam STEPISTANDARD I SATIUNSAT STEP 11: 17. IF offsite power is lost, THEN: SAT

a. PLACE charging pumps in PULL TO LOCK. UNSAT

b. RESTART RHR pumps.

c. RESTART charging pumps.

d. IF RCS press less than 1350 psig, THEN RESTART SI pumps.

STANDARD:

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

COMMENTS:

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

PAGE 12 OF 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.c 2010-08 NRC Exam STEP/STANDARD SATIUNSAT I STEP 12: 18. (#6) ISOLATE charging pump suction from RWST: CRITICAL STEP

a. CLOSE 1-LCV-62-135.

SAT

b. CLOSE 1-LCV-62-136.

UNSAT

c. ENSURE 1-HS-62-135A in A-AUTO (pushed in).

d. ENSURE 1-HS-62-136A in A-AUTO (pushed in).

STANDARD:

pushes 1-HS-62-135 handswitch in, and then rotates the handswitch to the left to the CLOSED position (Critical).

Applicant identifies the valve is closed by observing the RED light is DARK and GREEN light is LIT.

pushes 1-HS-62-136 handswitch in, and then rotates the handswitch to the left to the CLOSED position (Critical).

Applicant identifies the valve is closed by observing the RED light is DARK and GREEN light is LIT.

determines that the handswitch for 1-HS-62-135 has remained in the pushed-in position (Critical).

determines that the handswitch for 1 -HS-62-1 36 has remained in the pushed-in position (Critical).

Step is critical to complete the alignment of ECCS pumps to establish and maintain long term core cooling.

COMMENTS:

PAGE 13 OF 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.c 2010-08 NRC Exam STEP/STANDARD SAT/UNSAT STEP 13: 19. (#7) ISOLATE SI pump suction from RWST: CRITICAL STEP

CLOSE 1-FCV-63-5.

SAT STANDARD:

UNSAT rotates handswitch 1-HS-63-5A to the left to the CLOSED position (Critical).

Applicant identifies the valve is closed by observing the RED light is DARK and GREEN light is LIT.

Step is critical to complete the alignment of ECCS pumps to establish long term core cooling.

COMMENTS:

PAGE 14 OF 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.c 2010-08 NRC Exam STEPISTANDARD I SAT/UNSAT STEP 14: 20. (#8) ISOLATE RHR suction from RWST: CRITICAL STEP

a. ENSURE power restored tol-FCV-63-1 USING Appendix A (ES-i .3), i-FCV-63-1 Breaker Operation. SAT

b. CLOSE 1-FCV-63-i.

STANDARD:

Applicant determines from the INITIAL CONDITIONS that power has been restored to 1-FCV-63-1, RWSTTO RHR ECCS SUCTION.

Applicant rotates handswitch 1-HS-63-1A to the left to the CLOSED position (Critical).

Applicant identifies the valve is closed by observing the RED light is DARK and GREEN light is LIT.

Step is critical to complete the alignment of ECCS pumps to establish long term core cooling.

COMMENTS:

STEP 15: Notify the Unit Supervisor that transfer to the RHR containment SAT sump is complete.

UNSAT STANDARD:

Applicant notifies the Unit Supervisor that ECCS pumps are aligned to the containment sump, and reports portions of the system that failed to operate as expected (1-FCV-63-3 failed to close; 1-FCV-63-1 1 failed to open.)

COMMENTS:

END OF TASK STOP TIME PAGE 15 OF 16

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

DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. A large break loss-of-coolant event occurred 22 minutes ago.

2. The crew responded using E-I, Loss of Reactor or Secondary Coolant, and transitioned to ES-I .3, Transfer to Containment Sump.

3. ES-I .3, Transfer to Containment Sump, has been performed through Step 9.

INITIATING CUES:

I. The Unit Supervisor directs you to complete transfer of the Emergency Core Cooling Pump (ECCS) suctions using ES-I.3, Transfer to Containment Sump, by performing steps 10 through 20.

2. Inform the Unit Supervisor when step 20 is complete.

B.I.c

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.d 201 0-08 NRC Exam B.1.d Respond to RHR Pump Trip per AOl-I 4.

PAGE 1 OF 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.d 2010-08 NRC Exam EVALUATION SHEET Task: Respond to RHR Pump Trip Per AOl-14.

Alternate Path: n/a Facility JPM #: 3-OT-JPMR164 Safety Function: 4P

Title:

Heat Removal From Reactor Core K/A 025 Ml .09 Ability to operate and / or monitor the following as they apply to the Loss of Residual Heat Removal System: LPI pump switches, ammeter, discharge pressure gauge, flow meter, and indicators.

Rating(s): 3.2/3.1 CFR: 41.7 / 45.5 I 45.6 Evaluation Method: Simulator X In-Plant

References:

SOl-74.01, Residual Heat Removal System, Rev. 55.

AOl-14 Loss Of RHR Shutdown Cooling Rev. 36.

Task Number: RO-074-AOl-14-002

Title:

During RHR pump operation, respond to an RHR pump trip.

Task Standard: The applicant responds to the trip of 1A RHR pump in accordance with AOl-14, Loss of RHR Shutdown Cooling, Section 3.5, RHR Pump lA-A Trip and places the 1 B RHR pump in service.

Validation Time: 25 minutes Time Critical: Yes No X Applicant: Time Start:

NAME Docket No. Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner: /

NAME SIGNATURE DATE COMMENTS PAGE 2 OF 17

WATTS B NUCLEAR PLANT JOB PERFOiMANCE MEASURE B1.d 2010-08 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:

ENSURE NRC Examination Security has been established.

2. RESET to Initial Condition 310 by performing the following actions:

a. Select ICManager on the THUNDERBAR menu (right hand side of Instructor Console Screen).

b. Locate IC# 310.

c. Right click on IC# 310.

d. Select Reset on the drop down menu.

e. Right click on RESET.

f. Enter the password for IC 310.

g. Select Yes on the INITIAL CONDITION RESET pop-up window.

h. Perform SWITCH CHECK.

3. SELECT Director on the THUNDERBAR menu (right hand side of Instructor Console Screen).

4. ENSURE the following information appears on the Director Screen:

Key Description Type Event Delay Inserted Ramp Initial Final Value csro3 containment spray pump a power R 00:00:00 00:00:00 00:00:00 off off csr04 containment spray pump b power R 00:00:00 00:00:00 00:00:00 off off siro8 si pump a power R 00:00:00 00:00:00 00:00:00 off off s1r09 si pump b power R 00:00:00 00:00:00 00:00:00 off off csr05 power to cntmt spray valves fcv-72-2, 39. R 00:00:00 00:00:00 00:00:00 off off cvr03 power removal centrifugal charge pump b R 00:00:00 00:00:00 00:00:00 off off rhrl 2 rhr spray hdr a isolation valve power, fcv-72-40 R 00:00:00 00:00:00 00:00:00 off off rhrl3 rhr spray hdr b isolation valve power, fcv-72-41 R 00:00:00 00:00:00 00:00:00 off off hs-72-40a-1 01150 hr spray hdr a isol vlv sw(green) 0 00:00:00 00:00:00 00:00:00 off off hs-72-40a-2 01150 hr spray hdra sal vlvsw(red) 0 00:00:00 00:00:00 00:00:00 off off hs-72-41a-1 01160 hr spray hdrbisol vlv sw(green) 0 00:00:00 00:00:00 00:00:00 off off PAGE 3 OF 17

WATTS BA NUCLEAR PLANT JOB PERFOMANCE MEASURE B.1.d 201 0-08 NRC Exam Key Description Type Event Delay Inserted Ramp Initial Final Value hs-72-41a-2 01160 hr spray hdrbisol vlv sw(red) 0 00:00:00 00:00:00 00:00:00 off off hs-30-38a-1 01010 air return fans a-a on/off(green) 0 00:00:00 00:00:00 00:00:00 off off hs-30-39a-1 01010 air return fans b-b on/off(green) 0 00:00:00 00:00:00 00:00:00 off off rhOla rhr pump a trip M 1 00:00:00 00:00:00 Active InActive

5. Place simulator in RUN and acknowledge any alarms.

6. Place Hold Order Tags on the following components:

1-HS-72-27A, Cntmt Spray Pmp A

1-HS-72-IOA, Cntmt Spray Pmp B

1-HS-63-IOA, SI Pmp A

1-HS-63-15A, SI Pmp B

1-HS-62-104A, CCP B-B

Air Return Fan A-A 1-HS-30-38A

Air Return Fan B-B 1-HS-30-39A

1-HS-63-26A, BIT Outlet

1-HS-63-25A, BIT Outlet

1-HS-72-40A, RHR Spray Header A to Cntmt

1-HS-72-41A, RHR Spray Header B to Cntmt

1-HS-63-72A, Cntmt Sump to RHR Pmp A Suction

1-HS-63-73A, Cntmt Sump to RHR Pmp B Suction

1-HS-72-44A, Cntmt Sump to CS Pmp A Suction

1-HS-72-45A, Cntmt Sump to CS Pmp B Suction

1-HS-72-39A, Cntmt Spray Hdr A to Cntmt

1-HS-72-2A, Cntmt Spray Hdr B to Cntmt

1-HS-63-8A, RHR Pmp A to Charging Pmp Suction

1-HS-63-IIA, RHR Pmp B to SI Pmp Suction

1-HS-3-II6AIA, ERCW to AFWP A-A Suction From Hdr A

1-HS-3-126 A/A, ERCW to AFWP B-B Suction From Hdr B

1-HS-3-136 A/A, ERCW to TD AFWP Suction From Hdr A

1-HS-3-179 AlA, ERCW to TD AFWP Suction From Hdr B

8. ENSURE Extra Operator is present in the simulator.

9. Place simulator in FREEZE until Examiner cue is given.

PAGE 4 OF 17

WATTS BA NUCLEAR PLANT JOB PERFOKMANCE MEASURE B.1.d 2010-08 NRC Exam ENSURE that 1-FCV-74-37 is closed (Display Residual Heat Removal System on Thunderview Screen)

PAGE 5017

WATTS BA UCLEAR PLANT JOB PERFOIMANCE MEASURE B.1.d 2010-08 NRC Exam Simulator Event No. DescriptionlRole Play I IA-A RHR Pump trip.

ROLE PLAY: When CB AUO contacteci, state that pump tripped on Instantaneous over current.

When AB AUO contacted state that there is evidence of cable damage to the motor pigtail, there is an order of burnt insulation but there is no smoke or fire.

2 AUD is dispatched to close 1-HCV-74-36 ROLE PLAY: When contacted to close 1-HCV-74-36, repeat back request. Enter Event 2, which will enter remote function rhO6 to close. Report back that 1-HCV-74-36 is closed.

3 AUO is dispatched to open 1-HCV-74-37 ROLE PLAY: When contacted to openl-HCV-74-37, repeat back request. Enter Event 3, which will enter remote function rhOT to open. Report back that 1-HCV-74-37 is open.

4 AUO is dispatched to close I-SPV-74-530 When requested, use rhrO3 to close (1-SPV-74-530 to close)

ROLE PLAY: When contacted to close 1-SPV-74-530, repeat back request. Enter Event 4, which will enter remote function rhO3 to close. Report back that 1-SPV-62-530 is closed.

5 AUO is dispatched to open 1-HCV-74-36 ROLE PLAY: When contacted to open 1-SPV-74-531, repeat back request. Enter Event 5, which will enter remote function rhO4 to open. Report back that 1-SPV-74-36 is open.

PAGE 6 OF 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.d 2010-08 NRC Exam READ TO APPLICANT DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. Unit I is in MODE 5.

2. Unit I has been cooled down.

3. lA-A RHR train is in service.

4. lB-B RHR pump is available, and was in service 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ago.

5. CVCS is in service.

6. RHR to CVCS Letdown is in service from Heat Exchanger A outlet.

7. You are the Operator at the Controls.

INITIATING CUES:

I. You are to monitor the control board as the OAC and respond to events using appropriate procedure.

2. You are to inform the Unit Supervisor when the appropriate procedure has been completed.

PA(F 7017

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.d 201 0-08 NRC Exam STEPISTANDARD SATIUNSAT START TIME:

EXAMINER: After the applicant has stated that the task is understood, cue the Console Operator enter Event I to trip the IA-A RHR pump on instantaneous overcurrent.

EXAMINER: The following actions are taken from AOl-14, Loss of RHR Shutdown Cooling, Section 3.5, RHR Pump IA-A trip.

STEP 1: 1. CHECK BOTH RHR pumps stopped. SAT UNSAT STANDARD:

Applicant placed 1-HS-74-1OA in STOP PULL-TO-LOCK in response to 14-E, M-1 THRU M-6 MOTOR TRIPOUT, which was received when the lA-A RHR pump tripped. Applicant checks 1-HS-74-20A RHR pump lB-B stopped.

CUE: If CB AUO contacted, state that pump tripped on Instantaneous over current. If AB AUO contacted state that there is evidence of cable damage to the motor pigtail, there is an odor of burnt insulation but there is no smoke or fire.

COMMENTS:

PAGE 8017

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.d 2010-08 NRC Exam STEPISTANDARD SAT/UNSAT STEP 2: 2. CHECK RCS temp less than 235°F. SAT STANDARD: UNSAT Applicant determines that RCS temperature is less than 235°F by checking the following temperature recorders (Applicant may also use plasma displays or plant computer):

1-TR-74-14 RHR Hx A Temp °F

1-TR-74-25 RHR Hx B Temp °F COMMENTS:

STEP 3: 3. ADJUST charging and letdown to maintain RCS level and SAT press.

UNSAT STANDARD:

Applicant may adjust 1-HIC-62-83 RHR LETDOWN FLOW CONTROL closed and 1-FCV-62-93 CHARGING HEADER FLOW PZR LEVEL CONTROL to minimum to slow increase in pressurizer level as observed on PZR COLD CAL Level 1-Ll-68-321. Applicant may also adjust I -FCV-62-89.

COMMENTS:

CAUTION If the running RHR pump tripped due to inadequate suction supply or alignment problems, then do NOT attempt to start standby pump until adequate supply and alignment is ensured.

PAGE 9 OF 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.d 2010-08 NRC Exam STEP/STANDARD SAT/UNSAT STEP 4: 4. CHECK RHR pump lB-B available. SAT STANDARD: UNSAT Applicant determines that I B-B RHR pump is available (given in the instructions to the Applicant).

COMMENTS:

STEP 5: 5. OPEN l-FCV-70-153, CCS to RHR HX B. SAT STANDARD: UNSAT Applicant determines that l-FCV-70-153 is open by checking l-HS 1 53A is tagged with Power Disconnected Off (PDO) tag. Applicant may check flow through heat exchanger on I -EI-70-l 55 RHR Hx B Flow.

COMMENTS:

PAGE 10 OF 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.d 2010-08 NRC Exam STEPISTANDARD I SATIUNSAT STEP 6: 6. ENSURE RCS HL to RHR suction OPEN: SAT

. 1-FCV-74-1 and 1-FCV-74-2, OR UNSAT

. I -FCV-74-8 and I -FCV-74-9.

STANDARD:

Applicant determines 1-FCV-74-1 and -2 are OPEN by checking respective control board hand switch RED light LIT and GREEN light DARK on 1-HS-74-IA and 1-HS-74-2A.

COMMENTS:

STEP 7:7. OPEN l-FCV-74-21, RHR pump lB-B suction. SAT STANDARD: UNSAT The applicant determines l-FCV-74-21 open by checking RED light LIT and GREEN light DARK on hand switch l-HS-74-21.

COMMENTS:

PAGE 11 OF 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.d 201 0-08 NRC Exam STEP/STANDARD SAT/UNSAT STEP 8: 8. CLOSE RHR Hx outlets and bypass: CRITICAL STEP

. 1-FCV-74-16, RHR Hx A outlet.

SAT e 1-FCV-74-28, RHR Hx B outlet.

UNSAT

. 1-FCV-74-32, RHR Hx bypass.

STANDARD:

closes 1-FCV-74-16 by rotating CCW to 0% using 1-HIC-74-1 6A. (Critical).

closes 1-FCV-74-32 by rotating CCW to 0% using 1-HIC-74-32A. (Critical).

checks closed I -FCV-74-28 by rotating CCW to 0% using 1 -HIC-74-28A.

This step is critical to flow path preparatory to starting lB-B RHR pump trip.

COMMENTS:

PAGE 12 OF 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.d 2010-08 NRC Exam STEPISTANDARD SATIUNSAT STEP 9: 9. ALIGN RHR pump lB-B discharge: CRITICAL STEP

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

SAT

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

UNSAT

c. CLOSE 1-FCV-74-33, RHR Hx A outlet xtie.

d. CLOSE 1-FCV-63-93, RHR A to CL 2 & 3.

STANDARD:

rotates 1-HS-63-94 to the right to the OPEN position (Critical).

Applicant observes GREEN light is DARK and RED light is LIT.

rotates 1 -HS-74-35 to the right to the OPEN position (Critical).

Applicant observes GREEN light is DARK and RED light for LIT.

rotates I -HS-74-33 to the left to the CLOSED position (Critical).

Applicant observes GREEN light is LIT and RED light is DARK.

rotates I -HS-63-93 to the left to the CLOSED position (Critical).

Applicant observes GREEN light is LIT and RED light is DARK.

This step is critical to establish proper flow path prior to start of lB-B RHR pump, and to isolate the flow path from the IA-A RHR pump.

COMMENTS:

PAGE 13 OF 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.ld 2010-08 NRC Exam STEP/STANDARD SAT/UNSAT STEP 10: 10. START RHR pump lB-B. CRITICAL STEP STANDARD:

SAT rotates 1-HS-74-20A to the right to the START position (Critical). UNSAT Applicant verifies GREEN light is DARK and the RED light LIT.

Applicant observes amps for the I B-B RHR pump on I -El-74-1 7A, rising.

Applicant observes discharge pressure for the I B-B RHR pump on 1-Pl-74-26, rising.

This step is critical to starting I B-B RHR pump and re-establishing RHR shutdown cooling.

COMMENTS:

STEP 11: 11. ADJUST I -FCV-74-28 to establish RHR flow. CRITICAL STEP STANDARD:

SAT adjusts RHR flow through 1-FCV-74-28 by rotating CW from 0% using 1-HIC-74-28A and observing rising flow on 1-Fl UNSAT 92A, RHR TO CL 1&4 NR FLOW.

This step is critical to re-establishing RHR shutdown cooling.

COMMENTS:

PAGE 14 OF 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.id 2010-08 NRC Exam STEP/STANDARD SATIUNSAT STEP 12: 12. ALIGN RHR Hx bypass flow: CRITICAL STEP

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

SAT

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

UNSAT

c. ADJUST 1-FCV-74-32, RHR Hx bypass FCV.

STANDARD:

contacts AUO to close 1 -HCV-74-36. (Critical to contact the local operator to close valve).

contacts AUO to open 1-HCV-74-37. (Critical to contact the local operator to open valve).

adjusts 1-FCV-74-32 with 1-HIC-74-32A to stabilize RCS temperature as observed on 1-TR-74-25 RHR Hx B Temp °F. (Critical).

This step is critical to establish proper flow path after start of I B-B RHR pump and control of RCS temperature.

COMMENTS:

STEP 13: 13. WHEN RHR flow greater than 1400 gpm, THEN ENSURE SAT 1-FCV-74-24, RHR pump B mini-flow CLOSED.

UNSAT STANDARD:

Applicant checks mini flow valve 1 -FCV-74-24 closed by checking GREEN light LIT on 1 -HS-74-24A when flow greater than 1400 gpm as determined by Window 113-C RHR PUMP DISCH PRESS HI/MINI FLOW CONDITION clearing.

COMMENTS:

PAGE 15 OF 17

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.d 2010-08 NRC Exam STEP/STANDARD SATIUNSAT CAUTION Rapid changes in letdown flow and RCS pressure may occur during RHR letdown realignment. The following steps should be coordinated to allow MCR adjustments as local alignments are performed especially if PZR is water solid.

STEP 14: 14. ALIGN RHR pump lB-B to CVCS: CRITICAL STEP

a. CLOSE 1-SPV-74-530, TrA [1A Hx rm1722j.

SAT

b. OPEN 1-SPV-74-531, Tr B [1 B Hx rm17221.

UNSAT STANDARD:

contacts AUO to close 1-SPV-74-530. (Critical to contact the local operator to close valve).

contacts AUO to open I -SPV-74-531. (Critical to contact the local operator to open valve).

This step is critical to establish proper flow path to CVCS after start of lB-B RHR pump.

COMMENTS:

STEP 15: 15. OPEN 1 -FCV-62-83, RHR letdown FCV. SAT STANDARD: UNSAT Applicant opens or checks open 1-FCV-62-83 with 1-HIC-62-83A.

CUE: After the applicant has demonstrated how to open 1-FCV-62-83, state that another operator will complete AOI-14 actions.

COMMENTS:

ENDOFTASK STOP TIME PAGE 16 OF 17

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

DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. Unit I is in MODE 5

2. Unit I has been cooled down.

3. IA-A RHR train is in service.

4. lB-B RHR pump is available.

5. CVCS is in service

6. RHR to CVCS Letdown is in service from Heat Exchanger A outlet.

7. You are the Operator at the Controls.

INITIATING CUES:

I. You are to monitor the control board as the OAC and respond to events using appropriate procedure.

2. You are to inform the Unit Supervisor when the appropriate procedure has been completed.

B.I.d

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE Bte 201 0-08 NRC Exam B.1.e Respond to PRT High Pressure Alarm.

PAGE 1 OF 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.e 2010-08 NRC Exam EVALUATION SHEET Task: Respond to PRT High Pressure alarm.

Alternate Path: While the applicant is reducing PRT pressure, 1-PCV-68-334 fails open when PRT pressure drops to less than 8 psig. Applicant responds by attempting to close 1-HS-68-334 PZR PORV 334 and by closing 1-HS 332 BLOCK VALVE FOR PORV 334.

Facility JPM #: 3-OT-JPMR129B Safety Function: 5

Title:

Containment Integrity 007 A4.10 Ability to manually operate and/or monitor in the control room:

Recognition of leaking PORV/code safety.

Rating(s): 3.6/3.8 CFR: 41.7/45.5 to 45.8 Evaluation Method: Simulator X In-Plant

References:

ARI 88-C, PRT PRESS HI, Rev. 19 ARI 91-A, PZR PORV/SAFETY OPEN, Rev. 19.

Task Number: RO-068-SOl-68-023

Title:

Perform an alignment of the Pressurizer Relief Tank.

Task Standard: The applicant:

1. Performs actions of ARI 88-C, PRT PRESS HI and reduces pressure to clear the PRT high pressure alarm.

2. Diagnoses the failure of PZR PORV 1-68-334 open, and terminates the depressurization by placing 1-HS-68-332A BLOCK VALVE FOR PORV 334 in the CLOSED position.

Validation Time: 8 minutes Time Critical: Yes No X Applicant: Time Start:

NAME Docket No. Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner: /

NAME SIGNATURE DATE COMMENTS PAGE 2 OF 12

WATTS BA NUCLEAR PLANT JOB PERFORMANCE MEASURE B.te 2010-08 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Right click on 311 and then select RESET.

3. Enter the password.

4. Select Yes on the INITIAL CONDITION RESET pop-up window.

5. ENSURE the following information appears on the Director Summary Screen:

Key Type Event Delay Inserted Ramp Initial Final Value rc07a pzr porv pcv-68 334 fail to any position M 23 00:00:05 00:00:00 25 0

6. Ensure NRC EXAM flash drive is loaded into the simulator computer, and that the file NRC_Exam_Events.evt is opened.

7. Place simulator in RUN and acknowledge any alarms.

8. ENSURE a marked-up copy of ARI 88-C, PRT PRESS HI corrective actions signed off (circled-and-slashed) through Step 7.

9. ENSURE Extra Operator is present in the simulator.

10. Place simulator in FREEZE until Examiner cue is given.

PAGE 3 OF 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.e 2010-08 NRC Exam READ TO APPLICANT DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. Window 88-C, PRT PRESS HI is LIT.

2. The Operator at the Controls (OAC) has performed ARI 88-C, PRT PRESS HI corrective actions through Step &a.

3. You are an extra operator assigned to the shift.

INITIATING CUES:

1. The Unit Supervisor directs you to continue with the performance of ARI 88-C, PRT PRESS HI actions, beginning at Step 8.b.

2. Inform the Unit Supervisor when actions have been completed and Window 88-C, PRT PRESS HI, is reset.

PA(F 4 OF 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.e 2010-08 NRC Exam STEP/STANDARD I SATIUNSAT START TIME:

EXAMINER: ARI- 88-C Step [8] [a] is included for cueing purposes, if the applicant requests current vent header pressure and status of the Waste Gas compressors.

STEP 1: [8] REDUCE PRT pressure to approximately 6.5 psig as follows: SAT

[a] STATION Operator at panel O-L-2 to monitor vent header UNSAT pressure and start Waste Gas Compressor if necessary.

STANDARD:

Applicant determines from the INITIAL CONDITIONS that an AUO has been stationed at panel O-L-2, and is monitoring vent header pressure.

CUE: AUO stationed at 0-L-2 reports vent header pressure is 1.5 psig and stable.

COMMENTS:

PAGE 5 OF 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.e 2010-08 NRC Exam STEP/STANDARD I SAT/UNSAT STEP 2: [8] REDUCE PRT pressure to approximately 6.5 psig as follows: CRITICAL STEP

[b] HOLD 1-HS-68-301A in the OPEN position as long as the following conditions exist: SAT

Vent Header pressure is less than 2 psig

PRT pressure is greater than 6.5 psig UNSAT STANDARD:

rotates 1-HS-68-301A, PRT VENT TO WDS VENT HDR to the right to the OPEN position (Critical).

Applicant observes GREEN light DARK, RED light LIT.

Applicant observes a decreasing trend oni -P1-68-301, PRT PRESS.

CUE: If contacted to monitor vent header pressure, repeat back request and inform the applicant that Vent Header pressure is at approximately 1.5 psig, and slowly rising.

Step is critical since PRT pressure will not be reduced until the vent path is aligned.

COMMENTS:

PAGE 6 OF 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.e 2010-08 NRC Exam

STEP/STANDARD SATIUNSAT STEP 2: [8] REDUCE PRT pressure to approximately 6.5 psig as follows: CRITICAL STEP

[C] ENSURE 1-HS-68-301A in the CLOSED position.

SAT STANDARD:

UNSAT 88-C, PRT PRESS HI clears, the applicant rotates 1-HS-68-310A, PRT VENT TO WDS VENT HDR to the left to the CLOSE position.

Applicant observes GREEN light LIT, RED light DARK.

Step is critical since to ensure that a discharge to the PRT is isolated from the vent header to ensure damage to the vent header will not occur.

COMMENTS:

EXAMINER: When 88-C, PRT PRESS HI clears, malfunction rcO7a will be automatically entered after a 5 second time delay. This will cause 1-PCV-68-334 PZR PORV to open to 25%. The applicant will receive alarm 91-A, PZR PORV/SAFETY OPEN, and take actions contained in the alarm response procedure.

STEP 3: [1] CHECK PZR pressure to determine if PZR PORV/Safety SAT should be open.

UNSAT STANDARD:

Applicant determines from RCS pressure below 2335 psig that the PZR PORVs and Safety Valves should be closed.

COMMENTS:

PAGE 7 OF 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.e 2010-08 NRC Exam STEP/STANDARD SAT/UNSAT STEP 4: [2] CHECK other indications to determine if PZR PORV or Safety SAT is open:

. Windows 89-A and 89-B UNSAT

. 1-TI-68-330 [1-M-4] Safety

. 1-TI-68-329 [1-M-4] Safety

. 1-Tl-68-328 [1-M-4] Safety

. 1-Tl-68-331 [1-M-4] PORV STANDARD:

Applicant observes sharp rise in temperature indicated on 1-Tl-68-331, PORV 340A & 334 TAILPIPE TEMPS.

Applicant observes that neither the RED nor GREEN indicating lights are lit on 1-HS-68-334A, which is an indication that the PORV is partially open.

Applicant observes that the GREEN indicating light is LIT on 1-HS 340.

COMMENTS:

PAGE 8 OF 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.e 201 0-08 NRC Exam

STEPISTANDARD I SAT/UNSAT STEP 5: [3] ENSURE PZR PORV and Safeties CLOSED when PZR SAT pressure is below lift setpoint.

UNSAT STANDARD:

Applicant determines from redundant indications that PORV 334 has remained PARTIALLY OPEN and should have automatically closed when RCS pressure dropped below 2315 psig.

Applicant may rotate 1-HS-68-334, PZR PORV 334, to the left to the CLOSED position. Applicant then determines that the valve is not closed based on the continued drop in pressurizer pressure, and/or lack of indicating lights.

COMMENTS:

PAGE 9 OF 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.e 2010-08 NRC Exam STEP/STANDARD i SAT/UNSAT STEP 6: [4] IF PZR PORV is NOT closed when PZR pressure is below lift CRITICAL setpoint, THEN: STEP

[a] CLOSE associated PZR PORV block valve. SAT

[b] NOTIFY SRO. UNSAT

[c] REFER TO Tech Specs.

STANDARD:

Applicant observes that neither the RED nor GREEN indicating lights are lit on I -HS-68-334A, indicating that the PORV is partially open.

rotates 1 -HS-68-332A, BLOCK VALVE FOR PORV 334 to the left, to the CLOSED position (Critical).

Applicant determines that I -HS-68-332A lights indicate that the valve is CLOSED (RED light DARK, GREEN light LIT).

CUE: If the applicant refers to Technical Specifications, inform the applicant that the Shift Manager will evaluate Technical Specifications.

COMMENTS:

PAGE 10 OF 12

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.e 2010-08 NRC Exam STEP/STANDARD I SATIUNSAT STEP 7: Applicant informs the Unit Supervisor that 1-PCV-68-334 PZR SAT PORV opened and would not close manually. Applicant informs the Unit Supervisor that the block valve for PORV 68-334 is UNSAT closed.

STANDARD:

Applicant informs the Unit Supervisor of the PORV and PORV block valve configurations in order for the Unit Supervisor to correctly apply Technical Specifications.

CUE: Another operator will continue from here.

COMMENTS:

END OF TASK STOP TIME PAGE 11 OF 12

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

DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. Window 88-C, PRT PRESS HI is lit.

2. The Operator at the Controls (OAC) has performed ARI 88-C corrective actions through Step 7.

3. You are an extra operator assigned to the shift.

INITIATING CUES:

I. The Unit Supervisor directs you to continue with the performance of ARI 88-C, PRT PRESS HI actions, beginning at Step 8.

3. Inform the Unit Supervisor when actions have been completed and Window 88-C, PRT PRESS HI, is reset.

B.I.e

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.f 2010-08 NRC Exam B.1.f Shutdown of DG from Main Control Room NOTE: This JPM may be conducted on the Simulator OR in the Main Control Room PAGE 1 OF 14

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.f 2010-08 NRC Exam EVALUATION SHEET Task: Shutdown of DG from Main Control Room.

Alternate Path: During diesel generator shutdown, a high crankcase pressure alarm is received, requiring the applicant to initiate an emergency stop of the lB-B Diesel Generator.

Facility JPM #: 3-OT-JPMRO72A Safety Function: 6

Title:

Electrical 064 A4.01 Ability to manually operate and/or monitor in the control room: Local and remote operation of the ED/G Rating(s): 4.0/4.3 CFR: 41.7/45.5 to 45.8 Evaluation Method: Simulator X In-Plant Control Room X

References:

SOl-82.02, Diesel Generator (DG) I B-B, Rev. 68.

ARI 203-D, CRANKCASE PRESS HI, Rev.13.

Task Number: RO-082-SOl-82-003

Title:

Shutdown the Diesel Generator from the Main Control Room.

Task Standard: The applicant determines that an emergency stop of the diesel generator is required upon receipt of annunciator 203-D, CRANKCASE PRESS HI and performs an emergency stop of the 1 B-B Diesel Generator.

Validation Time: 10 minutes Time Critical: Yes No X Applicant: Time Start:

NAME Docket No. Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner: /

NAME SIGNATURE DATE COMMENTS PAGE 2 OF 14

WATTS BA NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.f 2010-08 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:

IF CONDUCTED IN THE SIMULATOR, THEN PERFORM THE FOLLOWING:

I. 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. Place simulator in RUN and acknowledge any alarms.

4. ENSURE I B-B Diesel Generator is running and loaded to approximately 4 MW with approximately I MVAR outgoing.

5. ENSURE copies of SOl-82.02, Diesel Generator (DG) I B-B are available for the Examiner.

6. ENSURE Extra Operator is present in the simulator.

7. Place simulator in FREEZE until Examiner cue is given.

PAGE 3 OF 14

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.f 2010-08 NRC Exam IF CONDUCTED IN THE MAIN CONTROL ROOM, THEN:

Tools/Equipment/Procedures Needed:

ENSURE that a copy of SOI-82.02, Diesel Generator (DG) I B-B, is available to the EXAMINER, marked as EXAM MATERIAL, FOR TRAINING ONLY, for each applicant.

Begin the JPM at the Shift Managers Desk.

PACF 4 OF 14

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.f 2010-08 NRC Exam READ TO APPLICANT DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. Unit I is at 100% power.

2. lB-B Diesel Generator is running and loaded to 4 MW, and I MVAR.

3. You are an extra operator assigned to the shift.

INITIATING CUES:

I. The Unit Supervisor directs you to shut down the I B-B Diesel Generator using SOI-82.02, Diesel Generator (DG) lB-B, Section 7.1,Shutdown of DG from Main Control Room.

2. Inform the Unit Supervisor when the I B-B Diesel Generator has been shutdown.

PA(F 5 OF 14

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.f 2010-08 NRC Exam STEP/STANDARD SAT/UNSAT EXAMINER: USE PAGES 6 through 9 if conducting JPM on the Simulator.

SIMULATOR PERFORMANCE START TIME:

CAUTION If load is lowered to zero or below zero, a reverse power trip is possible. V STEP 1: [1] ADJUST Generator Output as follows: CRITICAL STEP

[1 .1] PLACE 1-HS-57-74 DG SYNC SWITCH to SYN.

SAT STANDARD:

UNSAT Applicant rotates handswitch 1-HS-57-74 DG SYNC SWITCH to the right from the OFF to the SYN position.

Step is critical to enable controls to reduce load on the diesel generator in subsequent steps.

V COMMENTS:

EXAMINER: When lB-B Diesel Generator megawatts are reduced below 2 MWe, Window 203-D, CRANKCASE PRESS HI will be received.

PAGE 6 OF 14

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.f 2010-08 NRC_Exam STEPISTANDARD [ SAT/UNSAT STEP 2: [1] ADJUST Generator Output as follows: SAT

[1.2] REDUCE megawatts (1-El-82-40A) using 1-HS-82-43, UNSAT SPEED CONTROL, and megavars (1-EI-82-41A), using I -HS-82-42, VOLTAGE REGULATOR to near zero.

STANDARD:

Applicant rotates handswitch 1-HS-82-43 to the left to the LOWER position to reduce megawatts, and periodically adjusts megavars using 1-HS-82-42 VOLTAGE REGULATOR.

COMMENTS:

EXAMINER: The following actions are taken from ARI 203-D,CRANKCASE PRESS HL PAGE 7 OF 14

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.f 2010-08 NRC Exam STEP/STANDARD I SAT/UNSAT STEP 3: [1] IF DG running with NO emergency start present, THEN CRITICAL ENSURE DG shut down by Emergency Stop: STEP

Remote Depress 1-HS-82-47A, EMERGENCY STOP

- SAT pushbutton on 0-M-26.

UNSAT

Local Depress EMERGENCY STOP pushbutton on DG Control Board.

STANDARD:

determines that the I B-B Diesel Generator is running with NO emergency start signal (Critical).

depresses 1-HS-82-37A, EMERGENCY STOP pushbutton on 0-M-26 to stop the 1 B-B Diesel Generator (Critical).

Applicant determines that the diesel is tripped by observing the following:

Window 206-A, DG RUNNING clearing.

Window 202-A, DG AUTO START LOCKED OUT in alarm.

GREEN DG RUN indicating light is LIT, RED DG RUN light is DARK.

Step is critical to STOP the diesel generator with a high crankcase pressure condition, to prevent further damage to the machine.

COMMENTS:

PAGE 8 OF 14

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.f 2010-08 NRC Exam STEP/STANDARD I SATIUNSAT STEP 8: Notifies the Unit Supervisor that the 1 B-B Diesel Generator was SAT shutdown using 1-HS-82-47A, EMERGENCY STOP pushbutton on O-M-26, due to a high crankcase pressure alarm. UNSAT STANDARD:

Performer notifies the Unit Supervisor that an emergency stop of the 1 B-B Diesel Generator was performed due to high crankcase pressure, in accordance with ARI 203-D, CRANKCASE PRESSURE HI.

COMMENTS:

END OF TASK STOP TIME PAGE 9 OF 14

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.f 2010-08 NRC Exam STEP/STANDARD I SAT/UNSAT ]

EXAMINER: USE PAGES 10 through 13 if conducting JPM in the Main Control Room.

MAIN CONTROL ROOM PERFORMANCE START TIME CAUTION If load is lowered to zero or below zero, a reverse power trip is possible.

STEP 1: [1] ADJUST Generator Output as follows: CRITICAL STEP

[1.1] PLACE 1-HS-57-74 DG SYNC SWITCH to SYN.

SAT STANDARD:

UNSAT Applicant indicates that handswitch I -HS-57-74 DO SYNC SWITCH will be rotated to the right from the OFF to the SYN position (Critical).

CUE: A click was heard when 1-HS-57-74 DG SYNC SWITCH was moved.

CUE: After the applicant has demonstrated correct placement, if asked state that meter deflection was seen on INCOMING VOLTAGE, RUNNING VOLTAGE, INCOMING FREQUENCY, and RUNNING FREQUENCY.

If applicant requests a reading, ask the applicant to identify expected readings.

Step is critical to enable controls to reduce load on the diesel generator in subsequent steps.

COMMENTS:

PAGE 10 OF 14

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.f 2010-08 NRC Exam STEP/STANDARD SAT/UNSAT STEP 2: [1] ADJUST Generator Output as follows: SAT

[1.2] REDUCE megawatts (l-El-82-40A) using 1-HS-82-43, UNSAT SPEED CONTROL, and megavars (1-El-82-41A), using 1 -HS-82-42, VOLTAGE REGULATOR to near zero.

STANDARD:

Applicant identifies handswitch 1 -HS-82-43 and indicates that the switch is rotated to the left to the LOWER position to reduce megawatts on 1-El-82-40A.

Applicant indicates that the expected response to the lowering of megawatts is a rise in megavars.

Periodic adjustments to megavars on 1-El-82-41A will be made to maintain megavars less than 1 megavar outgoing using 1-HS-82-42 VOLTAGE REGULATOR.

CUE: After applicant has demonstrated proper switch manipulations, state that Window 203-D is in alarm.

COMMENTS:

EXAMINER: The following actions are taken from ARI 203-D,CRANKCASE PRESS HI.

PAGE 11 0F14

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.f 2010-08 NRC Exam STEP/STANDARD SAT/UNSAT STEP 3: [1] IF DG running with NO emergency start present, THEN CRITICAL ENSURE DG shut down by Emergency Stop: STEP

Remote Depress 1-HS-82-47A, EMERGENCY STOP

- SAT pushbutton on O-M-26.

UNSAT

Local Depress EMERGENCY STOP pushbutton on DG Control Board.

STANDARD:

determines that the I B-B Diesel Generator is running with NO emergency start signal (Critical).

depresses 1-HS-82-37A, EMERGENCY STOP pushbutton on O-M-26 to stop the I B-B Diesel Generator (Critical).

CUE: After applicant has demonstrated how to initiate an emergency stop provide the following feedback AS REQUESTED:

Window 206-A, DG RUNNING is DARK.

Window 202-A, DG AUTO START LOCKED OUT is LIT.

GREEN DG RUN indicating light above the DG IA-A mimic is LIT, RED DG RUN light is DARK.

Step is critical to STOP the diesel generator with a high crankcase pressure condition, to prevent further damage to the machine.

COMMENTS:

PAGE 12 OF 14

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.f 2010-08 NRC Exam STEP/STANDARD SATIUNSAT ]

STEP 8: Notifies the Unit Supervisor that the 1 B-B Diesel Generator was SAT shutdown using 1-HS-82-47A, EMERGENCY STOP pushbutton on O-M-26, due to a high crankcase pressure alarm. UNSAT STANDARD:

Applicant notifies the Unit Supervisor that an emergency stop of the I B-B Diesel Generator was performed due to high crankcase pressure, in accordance with ARI 203-D, CRANKCASE PRESSURE HI.

CUE: When requested repeat back information provided by the applicant. State that another operator will continue from this point.

COMMENTS:

END OF TASK STOP TIME PAGE 13 OF 14

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

DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. Unit I is at 100% power.

2. lB-B Diesel Generator is running and loaded to 4 MW, and I MVAR.

3. You are an extra operator assigned to the shift.

INITIATING CUES:

I. The Unit Supervisor directs you to shut down the lB-B Diesel Generator using SOl-82.02, Diesel Generator (DG) lB-B, Section 7.I,Shutdown of DG from Main Control Room.

2. Inform the Unit Supervisor when the I B-B Diesel Generator has been shutdown.

B.1.f

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.tg 2010-08 NRC EXAM B.1.g Return Failed RCS Temperature Channel to Service PAGE 1 OF 9

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.g 2010-08 NRC EXAM EVALUATION SHEET Task: Return Failed RCS Temperature Channel to Service.

Alternate Path: When rod control is returned to AUTO, a continuous rod withdrawal begins, requiring the applicant to trip the reactor.

Facility JPM #: New Safety Function: 7

Title:

Instrumentation

!ui& 016 A4.01 Ability to manually operate and/or monitor in the control room: NNI channel select controls.

Rating(s): 2.9/2.8 CFR: 41.7/45.4 to 45.8 Evaluation Method: Simulator X In-Plant

References:

AOl-2, Malfunction of Reactor Control System, Rev. 37 Task Number: RO-085-AOI-2-002

Title:

During control rod operations, respond to a continuous control rod withdrawal in accordance with AOl-2, Malfunction of Reactor Control System.

Task Standard: The applicant:

1.) Returns Loop 2 RCS Tavg and zT inputs to the rod control system, using AOl-2, Malfunction of Reactor Control System.

2.) Initiates a manual reactor trip upon diagnosis of the continuous rod bank withdrawal of Control Bank D.

Validation Time: 8 minutes Time Critical: Yes No X Applicant: Time Start:

NAME Docket No. Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner: I NAME SIGNATURE DATE COMMENTS PAGE 2 OF 9

WATTS BAr IUCLEAR PLANT JOB PERFOiMANCE MEASURE B.1.g 2010-08 NRC EXAM SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. RESET to Initial Condition 313 by performing the following actions:

a. Select lCManager 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 that 1-XS-68-2D, AT CHANNEL DEFEAT, and 1-XS-68-2M, TAVG CHANNEL DEFEAT, are selected to Loop 2 and the handswitches are in the PULLED OUT position.

4. Place simulator in RUN and acknowledge any alarms.

5. ENSURE a marked-up copy of AOI-2, Malfunction of Reactor Control System is available to the Examiner.

6. ENSURE Extra Operator is present in the simulator.

7. Place simulator in FREEZE until Examiner cue is given.

PAGE 3 OF 9

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.g 2010-08 NRC EXAM READ TO APPLICANT DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. Unit I is operating at 100% power.

2. Loop 2 RCS temperature channel failed high during the previous shift.

3. The channel was removed from service per AOl-2, Malfunction of Reactor Control System, Sub Section 3.2, Continuous Rod InsertionlWithdrawal.

4. AOI-2, Sub Section 3.2 has been completed through Step 11.

5. Work Control has just informed the Unit Supervisor that repairs have been corn pleted.

6. Rod Control is in MANUAL.

7. You are the OAC.

INITIATING CUES:

1. The Unit Supervisor has directed you return Loop 2 RCS temperature loop to service using AOI-2, Malfunction of Reactor Control System, Sub Section 3.2, Continuous Rod lnsertionlWithdrawal, Steps 12 and 13.

2. Inform the Unit Supervisor when Steps 12 and 13 are complete.

PA(P 4 OF fl

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.g 2010-08 NRC EXAM STEPISTANDARD I SAT/UNSAT START TIME:

EXAMINER: Step 12 has been broken into 2 separate JPM steps since each action accomplished is unique and critical.

STEP 1: 12. IF loop AT and loop Tavg channels were defeated due to Tavg CRITICAL channel failure, and Tavg channel has been repaired, THEN STEP PUSH IN 1-XS-68-2D, AT CHANNEL DEFEAT, and 1-XS 2M, TAVG CHANNEL DEFEAT, and select away from all AT SAT and Tavg channels.

UNSAT STANDARD:

pushes 1-XS-68-2D, AT CHANNEL DEFEAT switch IN and then rotates the switch from the Loop 2 position to the OFF position.

Step is critical to restore the Loop 2 AT input to normal.

COMMENTS:

PAGE 5 OF 9

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.g 2010-08 NRC EXAM

[ STEP/STANDARD SATIUNSAT STEP 2: 12. IF loop AT and loop Tavg channels were defeated due to Tavg CRITICAL channel failure, and Tavg channel has been repaired, THEN STEP PUSH IN 1-XS-68-2D, AT CHANNEL DEFEAT, and 1-XS 2M, TAVG CHANNEL DEFEAT, and select away from all AT SAT and Tavg channels.

UNSAT STANDARD:

pushes 1-XS-68-2M, TAVG CHANNEL DEFEAT switch IN and then rotates the switch from the Loop 2 position to the OFF position.

Step is critical to restore the Loop 2 Tavg input to normal.

COMMENTS:

PAGE 6 OF 9

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.g 2010-08 NRC_EXAM STEPISTANDARD SATIUNSAT I STEP 3: 13. WHEN conditions allow auto rod control, THEN: SAT

a. ENSURE T-avg and T-ref within 1°F. UNSAT

b. ENSURE zero demand on control rod position indication

[1 -M-4].

c. PLACE rods in AUTO.

STANDARD:

Applicant determines that T-avg and T-ref are within 1°F.

Applicant observes zero demand on CERPI display 1-MON-5000/1 OR 1-MON-5000/2, PASSIVE SUMMER ROD DEMAND Indicator.

Applicant rotates RBSS-1 Rod Bank Selector to the right from MAN to AUTO.

CUE: If requested by the applicant, state that 5 minutes have elapsed since restoring Loop 2 AT and loop Tavg channels.

COMMENTS:

STEP 4: Continuous rod bank withdrawal occurs. SAT STANDARD: UNSAT Applicant diagnoses the continuous bank withdrawal, rotates RBSS-1 Rod Bank Selector from AUTO to MAN.

COMMENTS:

PAGE 7 OF 9

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.g 2010-08 NRC EXAM STEPISTANDARD SAT/UNSAT STEP 5: Applicant determines that Control Bank D, Group 1 rods continue CRITICAL to withdraw at 72 steps/minute and trips the reactor. STEP STANDARD: SAT Once MANUAL has been selected and rod motion continues, the UNSAT applicant initiates a manual reactor trip.

When applicant initiates the reactor trip, state Another operator will perform E-0 Immediate Action Steps.

COMMENTS:

END OF TASK STOP TIME PAGE 8 OF 9

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

DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. Unit I is operating at 100% power.

2. Loop 2 RCS temperature channel failed high during the previous shift.

3. The channel was removed from service per AOI-2, Malfunction of Reactor Control System, Sub Section 3.2, Continuous Rod Insertion/Withdrawal.

4. AOI-2, Sub Section 3.2 has been completed through Step 11.

5. Work Control has just informed the Unit Supervisor that repairs have been completed.

6. Rod Control is in MANUAL.

7. You are the OAC.

INITIATING CUES:

1. The Unit Supervisor has directed you return Loop 2 RCS temperature loop to service using AOI-2, Malfunction of Reactor Control System, Sub Section 3.2, Continuous Rod Insertion/Withdrawal, Steps 12 and 13.

2. Inform the Unit Supervisor when Steps 12 and 13 are complete.

B.1.g

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.h 2010-08 NRC Exam B.1.h Shutdown Instrument Room Purge NOTE: This JPM may be conducted on the Simulator OR in the Main Control Room PAGE 1 OF 113

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.h 2010-08 NRC Exam EVALUATION SHEET Task: Shutdown Instrument Room Purge.

Alternate Path: n/a Facility JPM #: New Safety Function: 8

Title:

Plant Service Systems KIA 029 A2.03 Ability to (a) predict the impacts of the following malfunctions or operations on the Containment Purge System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Startup operations and the associated required valve lineups.

Rating(s): 2.7/3.1 CFR: 41.5 / 43.5 / 45.3/45.13 Evaluation Method: Simulator X In-Plant Control Room X

References:

SOl-30.02, Containment Purge System, Rev. 54 Task Number: RO-030-SOI-30-009

Title:

Purge the incore instrument room.

Task Standard: The applicant shuts down the instrument room purge using SOl-30.02, Containment Purge System, Section 7.6, SHUTDOWN of Instrument Room Purge, through Step 4.

Validation Time: 12 minutes Time Critical: Yes No X Applicant: Time Start:

NAME Docket No. Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner: /

NAME SIGNATURE DATE COMMENTS PAGE 2 OF 16

WATTS BA 1UCLEAR PLANT JOB PERFOKMANCE MEASURE B.1.h 2010-08 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:

IF CONDUCTED IN THE SIMULA TOR, THEN PERFORM THE FOLLOWING:

1. ENSURE NRC Examination Security has been established.

2. RESET to Initial Condition 314 by performing the following actions:

a. Select lCManager on the THUNDERBAR menu (right hand side of Instructor Console Screen).

b. Locate IC# 314.

c. Right click on lC# 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 that a purge of the incore instrument room is in progress based on the damper and fan alignment on 1-M-10.

5. ENSURE copies of S0l-30.02, Containment Purge System are available for the Examiner.

6. ENSURE Extra Operator is present in the simulator.

7. Place simulator in FREEZE until Examiner cue is given.

PAGE 3 OF 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.ih 2010-08 NRC Exam IF CONDUCTED IN THE MAIN CONTROL ROOM, THEN:

ToolslEguipment/Procedures Needed:

IF CONDUCTED IN THE MAIN CONTROL ROOM, THEN:

ENSURE that a copy of SOI-30.02, Containment Purge System, is available to the EXAMINER, marked as EXAM MATERIAL, FOR TRAINING ONLY, for each applicant.

Begin the JPM at the Shift Managers Desk.

PACP 4 OF 1i

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.h 2010-08 NRC Exam READ TO APPLICANT DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. Unit I is at 100% power.

2. A purge of the Instrument Room is in progress.

3. You are an extra operator assigned to the shift.

INITIATING CUES:

1. The Unit Supervisor directs you to shutdown the Instrument Room purge by performing Steps I through 4 of SOI-30.02, Containment Purge System, Section 7.6, SHUTDOWN Instrument Room Purge.

2. Inform the Unit Supervisor when Step 4 is complete.

PA(P 5 flF 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.h 2010-08 NRC Exam STEP/STANDARD I SAT/UNSAT EXAMINER: USE PAGES 6 through 10 if conducting JPM on the Simulator.

SIMULATOR PERFORMANCE START TIME:

STEP 1: [1] ENSURE FCV-30-5, PURGE SUP FAN lB DISCH, is CRITICAL CLOSED. STEP STANDARD: SAT rotates 1-HS-30-5 to the left to the CLOSE position UNSAT (Critical).

Applicant verifies GREEN light for l-FCV-30-5 is LIT; RED light for 1-FCV-30-5 is DARK.

Step is critical to support realignment of the purge system.

COMMENTS:

STEP 2: [2] STOP INSTR RM PURGE SUP & EXH FANS AND FCO CRITICAL IIA&IIB: THEN PLACE 1-HS-30-IIA in STOP P-T-L [l-M-9]. STEP STANDARD: SAT rotates l-HS-30-1 1A to the left to the STOP position, and UNSAT then pulls the handswitch out to lock the fan control in the STOP position (Critical).

Applicant verifies GREEN lights labeled SUP and EXH are LIT; RED lights labeled SUP and EXH are DARK.

Step is critical to support realignment of the purge system.

COMMENTS:

PAGE 6 OF 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.h 2010-08 NRC Exam STEP/STANDARD I SATIUNSAT STEP 3: [3] ENSURE the following: SAT PERF UNSAT NO1lENCLATURE LOCATION POSITION UNID INITIAL DAMPER 1 -X i-3-i 1 A 1 -M-9 CLOSED FCC-3D-i 1A DA1v1PER i-XI-Q-i1 1-M- CLOSED FCO-30-1 lB PUROE SUP SUCT ISOL i-M-9 CLOSED FCO-30-294 DAMPER i-XI-3U-24 PURGE SLIP SUCT SOL i-M-9 CLOSED FCO-30-295 DAMPER 1 -XI-30-295 STANDARD:

Applicant determines damper position:

FCO-30-1 1A CLOSED by observing Damper 1-Xl-30-1 IA GREEN light LIT, RED light DARK.

FCO-30-1IB CLOSED by observing Damper l-XI-30-IIB GREEN light LIT, RED light DARK.

FCO-30-294 CLOSED by observing Damper l-Xl-30-294 GREEN light LIT, RED light DARK.

FCO-30-295 CLOSED by observing Damper I-XI-30-295 GREEN light LIT, RED light DARK.

COMMENTS:

PAGE 7 OF 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.h 2010-08 NRC Exam STEPISTANDARD I SATIUNSAT I STEP 4: [4] ENSURE the following: CRITICAL STEP PE RF NOMENCLATURE LOCATION POSITION UNID INITIAL SAT INSTR RM PURGE CLOSED I-HS-30-19 1-FCV-30-19 & 55 INSTR RM PURGE I-M-9 CLOSED i-HS-30-20 UNSAT 1-FCV-30-20 & 59 PURGE EXH FAN 1A SUCT i-M-9 CLOSED i-HS-30-1 PURGE EXH FAN 1ATO i-rvl-9 CLOSED 1-HS-30-213 SHIELD BLDG VNT STANDARD:

rotates I -HS-30-1 9 to the left to the CLOSE position (Critical).

Applicant verifies GREEN lights for 1 -FCV-30-1 9 and for 1 -FCV 58 are LIT; RED lights for 1-FCV-30-19 and for 1-FCV-30-58 are DARK.

rotates 1-HS-30-20 to the left to the CLOSE position (Critical).

Applicant verifies GREEN lights for 1-FCV-30-20 and for 1-FCV 59 are LIT; RED lights for 1-FCV-30-20 and for 1-FCV-30-59 are DARK.

rotates I -HS-30-61 to the left to the CLOSE position (Critical).

Applicant verifies GREEN light for I -FCV-30-61 is LIT; RED light for 1-FCV-30-61 is DARK.

rotates 1-HS-30-213 to the left to the CLOSE position (Critical).

Applicant verifies GREEN light for 1-FCV-30-213 is LIT; RED light for 1-FCV-30-213 is DARK.

Identified step elements are critical to support realignment of the purge system.

COMMENTS:

PAGE 8 OF 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.h 2010-08 NRC Exam STEP/STANDARD I SAT/UNSAT I STEP 7: Notifies the Unit Supervisor that Instrument Room purge has been SAT shutdown.

UNSAT STANDARD:

Applicant notifies the Unit Supervisor that instrument room purge has been shutdown, and that containment vent has been restored.

COMMENTS:

END OF TASK STOP TIME PAGE 9 OF 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.h 2010-08 NRC Exam I STEPISTANDARD I SAT/UNSAT I EXAMINER: USE PAGES 11 through 17 if conducting JPM on the Main Control Room.

MAIN CONTROL ROOM PERFORMANCE START TIME:

STEP 1: [1] ENSURE 1-FCV-30-5, PURGE SUP FAN lB DISCH, is CRITICAL CLOSED. STEP STANDARD: SAT locates l-HS-30-5 and indicates that the handswitch will UNSAT be rotated to the left to the CLOSE position (Critical).

Applicant indicates that the GREEN light for 1-FCV-30-5 will be LIT; RED light for 1-FCV-30-5 will be DARK.

CUE: After applicant has demonstrated proper switch manipulation, state that 1-HS-30-5 is in the CLOSE position, GREEN light are LIT, and RED light are DARK.

Step is critical to support realignment of the purge system.

COMMENTS:

PAGE 10 OF 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.h 2010-08 NRC Exam

[ STEP/STANDARD E SAT/UNSAT I STEP 2: [2] STOP INSTR RM PURGE SUP & EXH FANS AND FCO CRITICAL 11A&I1B: THEN PLACE 1-HS-30-1IA in STOP P-T-L [1-M-9]. STEP STANDARD:

locates 1-HS-30-1 IA and indicates that the handswitch UNSAT will be rotated to the left to the STOP position, and then pulled out to lock the fan control in the STOP position (Critical).

Applicant indicates that the GREEN lights labeled SUP and EXH will be LIT; RED lights labeled SUP and EXH will be DARK.

CUE: After applicant has demonstrated proper switch manipulation, state that 1-HS-30-IIA is in the STOP position with the handswitch pulled out, GREEN lights are LIT, and RED lights are DARK.

Step is critical to support realignment of the purge system.

COMMENTS:

PAGE 11 OF 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.h 2010-08 NRC Exam STEPISTANDARD SAT/UNSAT STEP 3: [3] ENSURE the following: SAT PERF UNSAT NOMENCLATURE LOCATION POSITiON UNID INITIAL DAMPER 1 -XI-30-i 1 A 1 -M-9 CLOSED FCC-3D-i 1 A DAMPF I -XI II B l-M-9 CLOSED FO-3O-1 I B PURCE SLIP SUCT 1SDL i-M-9 CLOSED FCO-30-294 DAMPER I -XI-30-294 PURGE SUP SUCT [SOL i-M-9 CLOSED FGO-3O-2i5 DAMPER 1 -XI-3O-2 STANDARD:

Applicant locates and indicates the proper damper position:

FCO-30-1 IA CLOSED by observing Damper 1-XI-30-1 IA GREEN light LIT, RED light DARK.

FCO-30-1 I B CLOSED by observing Damper 1 -Xl-30-1 I B GREEN light LIT, RED light DARK.

FCO-30-294 CLOSED by observing Damper 1-Xl-30-294 GREEN light LIT, RED light DARK.

FCO-30-295 CLOSED by observing Damper 1-Xl-30-295 GREEN light LIT, RED light DARK.

CUE: After applicant locates each damper position indicator and indicates the expected position of each of the dampers, indicate that GREEN lights are LIT, and RED lights are DARK.

COMMENTS:

PAGE 12 OF 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.h 2010-08 NRC Exam STEP/STANDARD [ SATIUNSAT STEP 4: [4] ENSURE the following: CRITICAL STEP PERF NOMENCLATURE LOCATION POSITION UNID INITIAL INSTR RM PURGE i-M-9 CLOSED i-HS-30-19 SAT i-FCV-30-19 & 58 INSTR RM PURGE i-M-9 CLOSED I-HS-3C-20 1 -FCV-30-20 & 59 UNSAT PURGE EXH FAN 1A SUCT 1-M-9 CLOSED 1-HS-30-61 PURGE EXH FAN 1A TO 1-M-9 CLOSED 1-HS-30-213 SHIELD BLDG VNT STANDARD:

locates I -HS-30-1 9 and states that the handswitch will be rotated to the left to the CLOSE position (Critical).

Applicant indicates that the GREEN lights for 1-FCV-30-19 and for 1-FCV-30-58 are LIT; RED lights for 1-FCV-30-19 and for 1-FCV-30-58 are DARK. Applicant may also indicate that Purge Dampers Mimic GREEN indicating lights for 1-FCV-30-19 and for 1-FCV-30-58 are LIT and RED lights for 1-FCV-30-19 and for 1-FCV-30-58 are DARK.

CUE: After applicant has demonstrated proper switch manipulation, state that 1-HS-30-19 is in the CLOSE position, GREEN lights are LIT, and RED lights are DARK.

locates 1 -HS-30-20 and states that the handswitch will be rotated to the left to the CLOSE position (Critical).

Applicant indicates that the GREEN lights for 1-FCV-30-20 and for 1-FCV-30-59 are LIT; RED lights for 1-FCV-30-20 and for 1-FCV-30-59 are DARK. Applicant may also indicate that Purge Dampers Mimic GREEN indicating lights for 1-FCV-30-20 and for 1-FCV-30-59 are LIT and RED lights for 1-FCV-30-20 and for 1-FCV-30-59 are DARK.

CUE: After applicant has demonstrated proper switch manipulation, state that 1-HS-30-20 is in the CLOSE position, GREEN lights are LIT, and RED lights are DARK.

EXAMINER: The actions of Step 4 are continued on the next page.

PAGE 13 OF 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.h 2010-08 NRC Exam STEP/STANDARD I SAT/UNSAT STEP 4: [4] ENSURE the following: (Continued from previous page) locates 1-HS-30-61 and states that the handswitch will be rotated to the left to the CLOSE position (Critical).

Applicant indicates that the GREEN light for 1-FCV-30-61 is LIT; RED light for I -FCV-30-61 is DARK.

CUE: After applicant has demonstrated proper switch manipulation, state that 1-HS-30-61 is in the CLOSE position, GREEN light LIT, and RED light DARK.

locates 1-HS-30-213 and states that the handswitch will be rotated to the left to the CLOSE position (Critical).

Applicant indicates that the GREEN light for I-FCV-30-213 is LIT; RED light for 1-FCV-30-213 is DARK.

CUE: After applicant has demonstrated proper switch manipulation, state that 1-HS-30-213 is in the CLOSE position, GREEN light LIT, and RED light DARK.

Identified step elements are critical to support realignment of the purge system.

COMMENTS:

PAGE 14 OF 16

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.h 2010-08 NRC Exam STEP/STANDARD SAT/UNSAT STEP 17: Notifies the Unit Supervisor that Instrument Room purge has SAT been shutdown.

UNSAT STANDARD:

Applicant notifies the Unit Supervisor that instrument room purge has been shutdown, and that containment vent has been restored.

COMMENTS:

END OF TASK STOP TIME PAGE 15 OF 16

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

DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. Unit i is at 100% power.

2. A purge of the Instrument Room is in progress.

3. You are an extra operator assigned to the shift.

INITIATING CUES:

1. The Unit Supervisor directs you to shutdown the Instrument Room purge by performing Steps I through 4 of 501-30.02, Containment Purge System, Section 7.6, SHUTDOWN Instrument Room Purge.

2. Inform the Unit Supervisor when Step 4 is complete.

B.1.h

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.i 2010-08 NRC Exam I B.1.i Bypassing 1-PCV-62-81, CVCS LETDOWN HX PRESS CNTL, for local control.

PAGE 1 OF 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.i 2010-08 NRC Exam I -

EVALUATION SHEET Task: Bypassing l-PCV-62-81, CVCS LETDOWN HX PRESS CNTL, for local control.

Alternate Path: n/a Facility JPM #: 3-OT-JMPA156 Safety Function: 2

Title:

Reactor Coolant System Inventory Control.

K/A 004 Al .11 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CVCS controls including: Letdown and charging flows.

Rating(s): 3.0/3.0 CFR: 41.5 / 45.5 Evaluation Method: Simulator In-Plant X

References:

SOl-62.0l CVCS- Charging and Letdown Rev. 58 Task Number: AUO-062-SOl-62.1-015

Title:

Bypass l-PCV-62-81, CVCS Letdown Heat Exchanger Pressure Control, for local control.

Task Standard: The applicant has manually bypassed PCV-62-81, LETDOWN PRESS CONTROL in accordance with SOl-62.0l Section 8.15, Bypassing 1-PCV 81, CVCS LETDOWN HX PRESS CNTL, for Local Control.

Validation Time: 10 minutes Time Critical: Yes No X Applicant: Time Start:

NAME Docket No. Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner: /

NAME SIGNATURE DATE COMMENTS PAGE 2 OF 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.i 201 0-08 NRC Exam I-Tools/Equipment/Procedures Needed:

Hard Hat, Safety Glasses, Hearing Protection, Plant Approved Shoes, Gloves.

SOl-62.O1 latest revision.

ALARA considerations.

Start this JPM at the Rad Waste Operators Desk.

PAGE OF 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.i 2010-08 NRC Exam I -

READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating/operating cues.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM.

SIMULATE ALL MANIPULATIONS.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Ensure that you indicate to me when you fully understand your task.

To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. Unit i is at 100% power.

2. Centrifugal charging pump IA-A is in service.

3. Letdown pressure control valve 1-PCV-62-81 has been operating in a sluggish manner, causing swings in letdown pressure.

4. Work Control has been contacted and has requested that 1-PCV-62-81 be bypassed to permit further investigation of the pressure control valve.

INITIATING CUES:

1. The Unit Operator has directed you to bypass 1-PCV-62-81, for local control of Letdown Heat Exchanger Pressure using S01-62.01 CVCS- Charging And Letdown, Section 8.15, Bypassing 1-PCV-62-81, CVCS LETDOWN HX PRESS CNTL, for Local Control, while maintaining radio contact with the MCR operator (Allowing the MCR operator to provide direction and control of letdown pressure).

2. You are to notify the Unit Operator when you have bypassed 1-PCV-62-81.

PAflP 4 OP 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.i 2010-08 NRC Exam I -

STEPISTANDARD SAT/UNSAT START TIME:

STEP 1: Obtain a copy of the procedure. SAT STANDARD: UNSAT Applicant describes how to obtain a copy of the procedure.

EXAMINERS CUE: After the performer has identified how to obtain the correct instruction, the evaluator provides a copy of the instruction.

COMMENTS:

STEP 2: [1] ESTABLISH communications with personnel at the Main SAT Control Room (or Aux Control Room) and Aux Bldg el 737 Outside the letdown heat exchanger room. UNSAT STANDARD:

Applicant establishes communication with control room.

CUE: When notified, acknowledge using repeat back.

COMMENTS:

PAGE 5 OF 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1i 2010-08 NRC Exam I -

STEPISTANDARD SATIUNSAT STEP 3: [2] PLACE 1-HIC-62-81A, LETDOWN PRESS CONTROL in SAT MANUAL.

UNSAT STANDARD:

Control room has been contacted to place valve controller in manual.

NOTE: This could have been accomplished prior to leaving the control room.

CUE: When UO contacted, acknowledge, then state that 1-HIC-62-81A is in MANUAL.

COMMENTS:

STEP 4: [3] THROTTLE CLOSED 1-ISV-62-673, CVCS LETDOWN CRITICAL HEADER ISOLATION [A5U1737] until pressure rise indicated STEP in MCR or Aux Cntl Rm.

SAT STANDARD:

UNSAT Applicant establishes contact with control room and throttles closed 1-ISV-62-673 per MCR direction by operating valve hand wheel in clockwise direction.

Step is critical for establishing proper flow path for bypassing 1-PCV-62-81.

CUE: After applicant states how to CLOSE valve, then state that valve hand wheel rotates in clockwise direction. IF control room contacted to monitor letdown pressure, then after several turns state that pressure rise is observed.

COMMENTS:

PAGE 6 OF 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.i 201 0-08 NRC Exam I -

STEP/STANDARD SAT/UNSAT NOTE The next step will cause a pressure swing in the letdown header. The MCR operator and local operator should coordinate actions to minimize the pressure swings.

STEP 5: [4] THROTTLE OPEN I -BYV-62-672, CVCS LETDOWN PCV CRITICAL 81 BYPASS [A5U1737] while CLOSING 1-ISV-62-673, CVCS STEP LETDOWN HEADER ISOLATION.

SAT STANDARD:

UNSAT Letdown line pressure has been controlled per UO directions (counter clockwise on 1-BYV-62-672 and clockwise on 1-ISV-62-673) until 1-ISV-62-673 is fully closed.

Step is critical for establishing proper flow path for bypassing 1-PCV-62-81.

CUE: If UO contacted, state that letdown pressure lowers as 1-BYV-62-672 is OPENED and rises as 1-ISV-62-673 is CLOSED.

COMMENTS:

PAGE 7 OF 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.i 2010-08 NRC Exam I -

STEPISTANDARD SATIUNSAT I STEP 6: [5] ADJUST 1-BYV-62-672, CVCS LETDOWN PCV-62-81 CRITICAL BYPASS [A5U/737] to maintain desired letdown press. STEP STANDARD: SAT Letdown line pressure has been controlled per UO directions (clockwise UNSAT on 1-BYV-62-672 to raise pressure and counter clockwise on 1-BYV 672 to lower pressure).

CUE: If UO contacted, state that letdown pressure needs to be raised slightly.

CUE: As operator operates 1-BYV-62-672 clockwise state that letdown pressure has risen enough and then state that Rad Waste AUO will be contacted to control the 1-BYV-62-672 if additional adjustments are required.

CUE: As Unit Operator state that Rad Waste AUO will monitor the operation of 1-BYV-62-672.

COMMENTS:

STEP 7: [6] WHEN desired to return 1-PCV-62-81 to service, THEN SAT PERFORM the following:

UNSAT STANDARD:

Applicant determines that this step is not applicable at this time.

COMMENTS:

PAGE 8 OF 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.i 2010-08 NRC Exam I -

STEP/STANDARD I SAT/UNSAT STEP 13: Notify the Unit Supervisor 1 -PCV-62-81 has been bypassed SAT and that letdown pressure is stable.

UNSAT STANDARD:

Applicant notifies the Unit Supervisor that 1-PCV-62-81 has been bypassed and that letdown pressure is stable.

CUE: Repeat back information provided by the applicant.

COMMENTS:

END OF TASK STOP TIME PAGE 9 OF 10

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

DIRECTION TO APPLICANT:

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating/operating cues.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM.

SIMULATE ALL MANIPULATIONS.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Ensure that you indicate to me when you fully understand your task.

To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. Unit I is at 100% power.

2. Centrifugal charging pump IA-A is in service.

3. Letdown pressure control valve 1-PCV-62-81 has been operating in a sluggish manner, causing swings in letdown pressure.

4. Work Control has been contacted and has requested that 1-PCV-62-81 be bypassed to permit further investigation of the pressure control valve.

INITIATING CUES:

1. The Unit Operator has directed you to bypass 1-PCV-62-81, for local control of Letdown Heat Exchanger Pressure per procedure while maintaining radio contact with the MCR operator (Allowing the MCR operator to provide direction and control of letdown pressure).

2. You are to notify the Unit Operator when you have bypassed 1-PCV-62-81.

B.1.i I

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B. 1.j 2010-08 NRC Exam B.1.j Transfer 250v DC TURB BLDG DIST BD #1 from Normal to Alternate.

PAGE 1 OF 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B. 1.j 2010-08 NRC Exam EVALUATION SHEET Task: Transfer 250v DC TURB BLDG DIST BD #1 from Normal to Alternate.

Alternate Path: n/a Facility JPM #: 3-OT-JPMA123 Safety Function: 6

Title:

Electrical Systems K1A 063 K4.02 Knowledge of DC electrical system design feature(s) and! or interlock(s) which provide for the following: Breaker interlocks, permissives, bypasses and cross-ties.

Rating(s): 2.9/3.2 CFR: 41.7 Evaluation Method: Simulator In-Plant X

References:

SOl-239.01, 250V Battery Board 1, Rev. 12.

Task Number: AUO-239-SOl-239.1-08

Title:

Transfer a 250V DC Turbine Building Distribution Board.

Task Standard: The applicant transfers the 250V DC Turbine Building Distribution Board #1 from its Normal to Alternate supply per SOl-239.01, 250V Battery Board 1, Section 8.7.1, Transfer from Normal to Alternate.

Validation Time: 15 minutes Time Critical: Yes No X Applicant: Time Start:

NAME Docket No. Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner: /

NAME SIGNATURE DATE COMMENTS PAGE 2 OF 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B. I .j 2010-08 NRC Exam ToolslEciuipmentlProcedures Needed:

Hard Hat, Gloves, Safety Glasses and Plant Approved Shoes.

Procedure SOl-239.O1 Section 8.7.1, Transfer from Normal to Alternate.

References:

SOl-239.O1, 250V Battery Board 1 ,Rev. 12.

PAGE 3 OF 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B .1.1 2010-08 NRC Exam READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating/operating cues.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM.

SIMULATE ALL MANIPULATIONS.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Ensure that you indicate to me when you fully understand your task.

To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. The Unit is in MODE 5.

2. Maintenance is required that will cause 250V DC Battery Board #1 to be de-energized.

3. You are an AUO on shift.

INITIATING CUES:

1. You have been instructed to transfer the 250V DC Turbine Building Distribution Board #1 to its alternate supply per the SOl-239.01.

2. You are to notify the Unit I US/SRO when the board has been transferred.

PA(F 4 OF lfl

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.j 2010-08 NRC Exam STEP/STANDARD SATIUNSAT START TIME:

STEP 1: Obtain a copy of the procedure. SAT STANDARD: UNSAT Applicant describes how to obtain a copy of the procedure.

EXAMINER: After the performer has identified how to obtain the correct instruction, provide a copy of the instruction.

COMMENTS:

NOTE The Turbine Bldg Dist Bd will auto transfer on a complete loss of DC with no time delay, or if voltage drops to 188 volts for 4 seconds. Return to normal is manual only.

STEP 2: [1] OBTAIN SRO approval prior to performing this Section. SAT STANDARD: UNSAT SRO approval is obtained prior to performing the section.

CUE: After SRO is asked, state approval granted.

COMMENTS:

PAGE 5 OF 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.j 2010-08 NRC Exam STEP/STANDARD SATIUNSAT STEP 3: [2] CHECK at least 267 volts indicated on 250 V BATTERY SAT BOARD 2 VOLTMETER on 0-DPL-239-1 250V DC TURB BLDG DIST BD 1. UNSAT STANDARD:

Applicant observes 250V BOARD 2 VOLTMETER on 0-DPL-239-i and Voltage is verified to be at least 267 volts using 250V Battery Board 2 voltmeter.

CUE: Indicate 270 volts on 250V BOARD 2 VOLTMETER on 0-DPL-239-1.

COMMENTS:

STEP 4: [3] PLACE AUTO/MANUAL SUPPLY XFER SWITCH CS-i 01, to CRITICAL the MAN position. STEP STANDARD: SAT Applicant locates CS-ioi and indicates that the transfer switch must UNSAT be rotated to the left to MAN position.

CUE: After applicant has demonstrated the proper positioning of CS-101, indicate that CS-101 is in MAN.

Step is critical to ensure that the transfer from Alternate to Normal can be accomplished.

COMMENTS:

PAGE 6 OF 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.j 2010-08 NRC Exam STEP/STANDARD I SAT/UNSAT STEP 5: [4] CLOSE and HOLD ALT SUPPLY FROM 250V BATTERY BD CRITICAL 2, control switch until transfer is complete. STEP STANDARD:

Applicant locates ACB 102 and indicates that the breaker switch must UNSAT be rotated to the right to the CLOSE position and held there UNTIL after the normal supply switch is placed in the TRIP position and transfer is verified.

Step is critical to ensure that the transfer from Alternate to Normal is accomplished without power interruption.

COMMENTS:

STEP 6: [5] PLACE NORM SUPPLY FROM 250V BATTERY BD 1, control CRITICAL switch in the TRIP position. STEP STANDARD:

Applicant locates ACB 103 and indicates that the breaker switch must UNSAT be rotated to the left to the TRIP position and HELD there UNTIL the transfer is verified.

Step is critical to ensure that the transfer from Alternate to Normal is accomplished without power interruption.

COMMENTS:

PAGE 7 OF 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.j 2010-08 NRC Exam STEP/STANDARD I SAT/UNSAT STEP 7: [6] ENSURE breakers transferred. SAT STANDARD: UNSAT Applicant ensures ACB 102 is closed (verbalizes that a RED target is expected on ACB 1 02) and ACB 103 is open (verbalizes that a GREEN target is expected on ACB 103.)

CUE: After checked, if asked confirm that ACB 102 has red target and ACB 103 has green target.

COMMENTS:

STEP 8: [7] VERIFY between 267 and 283 volts indicated on 250 V SAT BATTERY BOARD 2 VOLTMETER on 0-DPL-239-1 250V DC TURBINE BLDG DISTRIBUTION BOARD 1. UNSAT STANDARD:

Applicant observes 250V BOARD 2 VOLTMETER on 0-DPL-239-1 and Voltage is verified to be at least 267 volts using 250V Battery Board 2 voltmeter.

CUE: Indicate 270 volts on 250V BOARD 2 VOLTMETER on 0-DPL-239-1.

Step is critical to ensure that sufficient voltage exists after transfer from Normal to Alternate.

COMMENTS:

PAGE 8 OF 10

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.j 2010-08 NRC Exam STEPISTANDARD SATIUNSAT STEP 9: [8] ENSURE AUTO/MANUAL SUPPLY XFER SWITCH CS-i 01, SAT in MAN position.

UNSAT STANDARD:

Applicant ensures that CS-i0i is in the MAN position, which is the position that was selected during Step 3 of the procedure.

COMMENTS:

STEP 10: Notify the Unit Supervisor that the transfer is complete. SAT STANDARD: UNSAT The US/SRO is notified that the transfer is complete.

CUE: Acknowledge the report using repeat back.

COMMENTS:

END OF TASK STOP TIME PAGE 9 OF 10

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

DIRECTION TO APPLICANT:

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating/operating cues.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM.

SIMULATE ALL MANIPULATIONS.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Ensure that you indicate to me when you fully understand your task.

To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

4. The Unit is in MODE 5.

5. Maintenance is required that will cause 250V DC Battery Board #1 to be de-energized.

6. You are an AUO on shift.

INITIATING CUES:

3. You have been instructed to transfer the 250V DC Turbine Building Distribution Board #1 to its alternate supply per the SOI-239.O1.

4. You are to notify the Unit I US/SRO when the board has been transferred.

B.1.j -I

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.k 2010-08 NRC Exam B.1.k Local Restart of C&SS Air Compressors PAGE 1 OF 15

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.k 2010-08 NRC Exam EVALUATION SHEET Task: Local Restart of C&SS Air Compressors.

Alternate Path: Compressor A has high discharge air temperature and high oil temperature indication lights. Compressor A fails to auto load.

Facility JPM #: 3-OT-JPMAOO1 C Rev 5 Safety Function: 8

Title:

Plant Service Systems 065 AK3.08 Knowledge of the reasons for the following responses as they apply to the Loss of Instrument Air: Actions contained in EOP for loss of instrument air.

Rating(s): 3.7/3.9 CFR: 41.5,41.10 / 45.6 / 45.13 Evaluation Method: Simulator In-Plant X

References:

AOl-b Loss of Control Air Rev. 39 Task Number: AUO-032-AOl-010-002

Title:

Perform Attachment I of AOl-i 0, Local Restart of Control and Station Service Air Compressors.

Task Standard: The applicant has aligned and started A and B Air Compressors using AOl-I 0, Loss of Control Air, Attachment 1, Local Restart of C&SS Air Compressors. Control Air (Non-Essential) pressure has been re established.

Validation Time: 15 minutes Time Critical: Yes No X Applicant: Time Start:

NAME Docket No. Time Finish:

Performance Rating: SAT UNSAT Performance Time Examiner: /

NAME SIGNATURE DATE COMMENTS PAGE 2 OF 15

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.k 2010-08 NRC Exam Tools/Equipment/Procedures Needed:

Hard Hat, Safety Glasses, Hearing Protection, Gloves and Plant Approved Shoes.

AOl-i 0 Attachment 1.

High Noise Area; energized rotating equipment that can auto start.

EVALUATOR NOTE: Provide a copy of AOl-b Attachment I to performer with candidates cue sheet.

PAGE 3 OF 15

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.k 201 0-08 NRC Exam READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating/operating cues.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Ensure that you indicate to me when you fully understand your task.

To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. A Station Blackout has occurred.

2. The Diesel Generators have started and are feeding the SD Bds.

3. The Control and Service Air compressors were aligned normal with C air compressor in the lead prior to the Blackout.

4. A loss of Non-essential and Service air has occurred (Air pressure is at 75 psig decreasing).

5. Essential Air is being supplied by the Aux. Air compressors.

6. The 480V Auxiliary Building Common Board does not have voltage available on its normal or alternate supply.

7. Local control power is available to the air compressors.

8. You are a support AUO on shift.

INITIATING CUES:

1. The Unit Operator has dispatched you with a copy of Attachment I of AOl-b with instructions to perform steps 2 through 10.

2. Notify the Unit Operator when you have completed the task.

PA( 4 OF 15

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.k 201 0-08 NRC Exam START TIME:

STEP 1: 2. Locally CHECK O-PCV-33-4, SERVICE AIR SUPPLY SAT ISOLATION, CLOSED [T7M/708].

UNSAT STANDARD:

The applicant locates and describes how to check that O-PCV-33-4 is in the closed position by either the green local indicating light or the stem down on the valve.

CUE: When the valve is checked, state that green light is ON, Red light is OFF, and Stem is down, with the indicator at C.

COMMENTS:

STEP 2: 3. CHECK local control station alarm DARK [ Panel O-L-240, SAT T7M/708].

UNSAT STANDARD:

The applicant locates the local control station (Panel O-L-240) alarms and indicates how to check the alarms.

CUE: When checked, indicate that Compressor A high discharge air temp and high oil temp lights are illuminated.

The applicant proceeds to RNO column after discovery of the high discharge air temp and high oil temp on A compressor being LIT.

COMMENTS:

PAGE 5 OF 15

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.k 2010-08 NRC Exam STEP 3: 3. RESPONSE NOT OBTAINED: CRITICAL STEP IF local control station alarm LIT, THEN PERFORM the following for each air compressor in alarm: SAT

a. RESET high air temp at each compressor (O-TS-32-41, UNSAT

-36,-31).

STANDARD:

Applicant locates and describes how to depress the High Air Temp reset push button, O-TS-32-41, (on west side of A air compressor).

CUE: When checked, and after applicant indicates how to depress pushbutton for O-TS-32-41, state that the pushbutton is as you see it (reset).

Step is critical because A compressor cannot be started with the alarm switch NOT reset.

COMMENTS:

PAGE 6 OF 15

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.k 2010-08 NRC Exam STEP 4: 3. RESPONSE NOT OBTAINED: CRITICAL STEP IF local control station alarm LIT, THEN PERFORM the following for each air compressor in alarm: SAT

b. RESET high oil temp switches at each air compressor UNSAT (0-TS-32-40, -35, -30).

STANDARD:

Applicant locates and describes how to depress the High oil Temp reset push button, 0-TS-32-40, (on east side of A air compressor).

CUE: When checked, and after applicant indicates how to depress pushbutton for O-TS-32-40, state that the pushbutton is as you see it (reset).

Step is critical because A compressor cannot be started with the alarm switch NOT reset.

COMMENTS:

PAGE 7 OF 15

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.k 2010-08 NRC Exam STEP 5: 3. RESPONSE NOT OBTAINED: CRITICAL STEP IF local control station alarm LIT, THEN PERFORM the following for each air compressor in alarm: SAT

c. RESET Common Alarm using O-HS-32-25B, UNSAT COMPRESSOR A, B, C RESET [O-L-240, yellow PB].

STANDARD:

Applicant locates and describes how to depress O-HS-32-25B COMPRESSOR A, B, C RESET pushbutton.

CUE: When checked, and after applicant indicates how to depress pushbutton for O-TS-32-40, state that the pushbutton is as you see it (reset).

Step is critical because A compressor cannot be started without using pushbutton to reset trip logic.

COMMENTS:

PAGE 8 OF 15

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.k 2010-08 NRC Exam STEP6: 3. RESPONSE NOTOBTAINED: SAT IF local control station alarm LIT, THEN PERFORM the UNSAT following for each air compressor in alarm:

d. CHECK common and all compressor local alarms DARK.

STANDARD:

The applicant locates the alarms and requests the status of each alarm on panel.

CUE: After high air temp and high oil temp, reset push buttons at compressor A and O-HS-32-25B has been pushed, indicate to the applicant that all alarms lights on panel are dark.

COMMENTS:

STEP 7: 4. PLACE the following C&SS Compressors to HAND [O-L-240]: CRITICAL STEP

A, O-HS-32-25D.

SAT

B, O-HS-32-26A.

UNSAT STANDARD:

Applicant locates and describes how to place O-HS-32-25D for A Compressor and O-HS-32-26A for B Compressor to the HAND position.

CUE: Indicate that both handswitches point to HAND.

Step is critical because the hand switches enable the respective local start pushbuttons.

COMMENTS:

PAGE 9 OF 15

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.k 2010-08 NRC Exam STEP 8: 5. PLACE O-HS-32-25A, STATION AIR COMPRESSOR SAT SEQUENCE CONTROL, to Position 1.

UNSAT STANDARD:

Applicant locates and describes how to rotate O-HS-32-25A, Station Air Compressor Sequence Selector Control, to select Position 1.

CUE: Indicate that Sequence Selector is in position 3 before operation, and indicate that Sequence Selector is in position I after operation.

COMMENTS:

STEP 9: 6. START Compressor A by pushing O-HS-32-25E. CRITICAL STEP STANDARD:

SAT Applicant locates and describes how to depress O-HS-32-25E manual start push button. UNSAT CUE: If JPM Steps 4, 5, 6, and 8 were SAT, then when PB is depressed, if asked, state that an air compressor start was heard. If JPM Steps 4, 5, 6, or 8 were UNSA 7. if asked, state that compressor start was not heard.

Step is critical to start air compressor.

COMMENTS:

PAGE 10 OF 15

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.k 2010-08 NRC Exam STEP 10: 7. CHECK Compressor A loads automatically. SAT STANDARD: UNSAT The applicant describes how to determine that air compressor A is loaded, by observing the loading solenoids, or by the sound changing at Compressor A.

CUE: When checked, state that the air compressor sound indicates that it has NOT loaded, state that air pressure is NOT rising (several local gauges), or if both solenoids are checked to be magnetized, state that they are de-energized.

Applicant proceeds to RNO column after being cued to the failure of A compressor to load.

COMMENTS:

STEP 11: 7. RESPONSE NOT OBTAINED: CRITICAL STEP IF Compressor A does NOT Auto load, THEN PLACE 0-HS-32-43A and -43B to ON (Local 0-JB-291-226). SAT STANDARD: UNSAT locates and describes how to place 0-HS-32-43A and 0-HS-32-43B to the ON positions.

CUE: After hand switches have been placed to the ON position and when checked, state that the air compressor sound indicates that it has not loaded, the air pressure is dropping, or. if both solenoids are checked to be magnetized, state that they are de-energized.

COMMENTS:

PAGE 11 OF 15

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.k 2010-08 NRC Exam STEP 12: 7. RESPONSE NOT OBTAINED: CRITICAL STEP IF Compressor A does NOT load from local panel, THEN:

SAT

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

b. VENT O-TV-32-579, STATION AIR COMPR A UNLOADING HDR TEST.

STANDARD:

locates and describes how to close O-ISV-32-578 by stating that the valve handwheel must be rotated clockwise.

CUE: After Valve 0-IS V.32-578 has been located and closed state that valve handwheel rotated clockwise until snug and valve stem moved into valve body.

locates and describes how to open O-TV-32-579 by stating that the valve handwheel must be rotated counter-clockwise.

CUE: After Valve 0-TV-32-579 has been located and opened state that valve handwheel rotated counterclockwise until snug (state that air was heard venting from end of valve if asked).

The applicant indicates how to determine air compressor A is has loaded after O-TV-32-579 is open.

CUE: IF asked and when checked state that compressor sound indicated it has loaded and when checked, the air compressor sound indicates that it has loaded, the air pressure is rising.

Steps are critical to bleed air to force compressor to load.

COMMENTS:

PAGE 12 OF 15

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.k 2010-08 NRC Exam STEP 13: 8. START Compressor B by pushing, O-HS-32-26B. CRITICAL STEP STANDARD:

SAT locates and describes how to depress O-HS-32-26B manual start push button. UNSAT CUE: If JPM Step 8 was SAT, then when PB is depressed, if asked state that an air compressor start was heard. If JPM Step 8 was UNSA 7, if asked, state that compressor start was not heard.

Step is critical to start air compressor.

COMMENTS:

STEP 14: 9. CHECK Compressor B loads automatically. SAT STANDARD: UNSAT The applicant describes how to determine that air compressor B is loaded, by observing the loading solenoids, or by the sound changing at Compressor B.

CUE: When checked, state that the air compressor sound indicates that it has loaded or if both solenoids are checked to be magnetized, state that they are energized.

COMMENTS:

PAGE 13 OF 15

WATTS BAR NUCLEAR PLANT JOB PERFORMANCE MEASURE B.1.k 2010-08 NRC Exam STEP 15: 10. MONITOR Compressor operation: SAT

Oil press 25-30 psig on A, B, and C. UNSAT

Cooling water flow.

Compressors auto-loading.

STANDARD:

Applicant locates oil pressure indicators (Compressor A, 0-PI-32-40; Compressor B, 0-Pl-32-35) and states that oil pressure on both compressors should be 25-30 psig.

Applicant locates discharge drains and states that cooling water flow should be seen at the drain points.

Applicant determines from previous steps that Compressor A Compressors was manually loaded, and that Compressor B automatically loaded. Applicant states that Compressor C is shutdown due to the loss of power.

CUE: After the applicant has described the status of Compressor A and B, state that another operator will continue Attachment I performance from this point.

Applicant notifies the Unit Operator that AOl-i 0, Loss of Control Air, Attachment 1 Local Restart of C&SS Air Compressors is complete through Step 10.

COMMENTS:

END OF TASK STOP TIME PAGE 14 OF 15

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

DIRECTION TO APPLICANT:

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating/operating cues.

NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS.

When you complete the task successfully, the objective for this job performance measure will be satisfied.

Ensure that you indicate to me when you fully understand your task.

To indicate that you have completed your assigned task return the cue sheet I provided you.

INITIAL CONDITIONS:

1. A Station Blackout has occurred.

2. The Diesel Generators have started and are feeding the SD Bds.

3. The Control and Service Air compressors were aligned normal with C air compressor in the lead prior to the Blackout.

4. A loss of Non-essential and Service air has occurred (Air pressure is at 75 psig decreasing).

5. Essential Air is being supplied by the Aux. Air compressors.

6. The 480V Auxiliary Building Common Board does not have voltage available on its normal or alternate supply.

7. Local control power is available to the air compressors.

8. You are a support AUO on shift.

INITIATING CUES:

1. The Unit Operator has dispatched you with a copy of Attachment I of AOI-IO with instructions to perform steps 2 through 10.

2. Notify the Unit Operator when you have completed the task.

B.1.k

ML110140224

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