ML15265A317

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2015-09 - Draft - Operating Test
ML15265A317
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 09/09/2015
From: Vincent Gaddy
Operations Branch IV
To:
Entergy Operations
References
Download: ML15265A317 (417)


Text

ANO-2-JPM-NRC-ADMIN-XTCEA A1 PAGE 1of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 01 DATE:

SYSTEM/DUTY AREA: Control Element Drive Mechanism Control System TASK: Determine CEA#1 Upper Gripper Coil Temperature JTA#: ANO2-RO-CEDM-NORM-10 Alternate Yes: No: X Time Critical Yes: X Path KA VALUE RO: 3.9 SRO: 4.0 KA

REFERENCE:

2.1.23 APPROVED FOR ADMINISTRATION TO: RO: X SRO:

TASK LOCATION: INSIDE CR: OUTSIDE CR: BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Classroom: Perform POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: LAB:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 15 Minutes REFERENCE(S): OP 2105.009 EXAMINEE'S NAME: Badge EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Stop Total Time Time Time

ANO-2-JPM-NRC-ADMIN-XTCEA A1 PAGE 2of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

Plant is at full power.

Both Main Chillers have tripped and cannot be started.

I&C is not available to obtain CEDM Coil temperatures.

OP 2203.012M, 2K13 ACA, for window C4, CEDM Cooling coils Water Flow Low is in alarm.

CEA #1 is not on the Hold Bus.

Readings obtained from the CEDM coil using a calibrated DVM are:

Upper Gripper coil voltage (Terminals #4 and #5 on TBC4C6) is equal to 44V.

Upper Gripper shunt voltage (across pins C and D) is equal to 7.12 mV.

TASK STANDARD:

Calculated CEA #01 coil amperage, resistance and determined coil temperature to be 400.042°F and 420.043°F.

TASK PERFORMANCE AIDS:

1. OP-2105.009 Exhibit 2
2. Calculator EXAMINER NOTES:

OP-2105.009 should be completed up to step 4.3.1.

ANO-2-JPM-NRC-ADMIN-XTCEA A1 PAGE 3of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:

The SM directs, As directed by OP 2203.012M, 2K13-C4, CEDM Cooling coils Water Flow Low ACA, calculate the Upper Gripper temperature for CEA 01 using 2105.009, Exhibit 2.

START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

Examiners Cue:

OP-2105.009 Exhibit 2 should be completed up to step 4.3.1 (with values filled in).

(C) 1. Utilize ohms law to calculate Examinee calculated current to N/A SAT UNSAT (Step 5) coil current (Icoil) as follows. be between 3.56 to 3.6 amps.

(Icoil) = (Vshunt) ______V ÷

.002 ohms.

(Icoil) = ______ amps (C) 2. Calculate coil resistance Examinee calculated resistance N/A SAT UNSAT (Steps (Rcoil1) as follows: of the coil to be between 12.2 6 and and 12.36 ohms.

6.1)

(Rcoil1) = (Vug)______V

÷ (Icoil) ______ amps (Rcoil1) = ______ ohms Procedure Note Lead resistance must be subtracted to obtain accurate reading. Lead resistance for CEA #1 is provided in this calculation. However, a lookup table for lead resistance is provided when using WO# 50654677 to calculate other CEA coil temperatures.

(C) 3. (Rcoil2) = ______(Rcoil1) - Examinee calculated resistance N/A SAT UNSAT (Steps .525 ohms(CEA #01 lead of the Rcoil2 to be between 6.2 and resistance). 11.675 and 11.835 ohms.

6.3)

(Rcoil2) = ______ ohms (C) 4. Obtain CEA #01 coil Examinee calculated correct (Steps temperature as follows: CEA 01 upper gripper coil 7.0 and temperature to be 413.376°F.

7.1)

Use the following to obtain Acceptable range ( 400.042°F CEA #01 coil temperature: and 420.043°F)

Coil resistance (Rcoil2) calculated in step 6.0 Table below END STOP TIME:

ANO-2-JPM-NRC-ADMIN-XTCEA A1 PAGE 4of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE Examiners COPY INITIAL CONDITIONS:

Plant is at full power.

Both Main Chillers have tripped and cannot be started.

I&C is not available to obtain CEDM Coil temperatures.

OP 2203.012M, 2K13 ACA, for window C4, CEDM Cooling coils Water Flow Low is in alarm.

CEA #1 is not on the Hold Bus.

Readings obtained from the CEDM coil using a calibrated DVM are:

o Upper Gripper coil voltage (Terminals #4 and #5 on TBC4C6) is equal to 44V.

o Upper Gripper shunt voltage (across pins C and D) is equal to 7.12 mV.

INITIATING CUE:

The CRS directs you to calculate the Upper Gripper temperature for CEA 01 using 2105.009, Exhibit 2 starting with step 5. Table interpolation not required.

Acceptable Temperature Range: ( 400.042°F and 420.043°F)

ANO-2-JPM-NRC-ADMIN-XTCEA A1 PAGE 5of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE Examinees COPY INITIAL CONDITIONS:

Plant is at full power.

Both Main Chillers have tripped and cannot be started.

I&C is not available to obtain CEDM Coil temperatures.

OP 2203.012M, 2K13 ACA, for window C4, CEDM Cooling coils Water Flow Low is in alarm.

CEA #1 is not on the Hold Bus.

Readings obtained from the CEDM coil using a calibrated DVM are:

o Upper Gripper coil voltage (Terminals #4 and #5 on TBC4C6) is equal to 44V.

o Upper Gripper shunt voltage (across pins C and D) is equal to 7.12 mV.

INITIATING CUE:

The CRS directs you to calculate the Upper Gripper temperature for CEA 01 using 2105.009, Exhibit 2 starting with step 5. Table interpolation not required.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 18 of 44 2105.009 CEDM CONTROL SYSTEM OPERATION CHANGE: 032 EXHIBIT 2 2105.009 Revised 04/24/13 CEA #01 UPPER GRIPPER COIL TEMPERATURE MEASUREMENT PAGE 1 OF 2 Exhibit provides Operations ability to measure and trend CEA-01 upper gripper coil temperature. Other historically hot CEAs (2, 4, 8, 14, 15, 18, 55, 63, and 72) can also be measured by referring to WO# 50654677 CR-ANO-2-1999-0433-004.

1.0 Obtain currently calibrated Handheld Digital Voltmeter (DVM) or equivalent multimeter (Refer to 2OPG-012 for DVM usage).

NOTE Hold Bus voltage prevents obtaining proper temperature readings.

Record absolute values of voltage readings obtained.

2.0 Check CEA #01 NOT on Hold Bus.

3.0 Obtain CEA #01 Upper Gripper coil voltage (Vug) as follows:

3.1 Locate CEA #1 power cables in panel on TBC4C6, (behind access panel to left of 2C72 door).

3.2 With DVM scale set on 200, take voltage reading across Black and White cables located on TBC4C6, terminals #4 and #5. (A typical reading is 44 VDC).

44 V (Vug) = ______

4.0 Obtain CEA #01 Upper Gripper shunt voltage (Vshunt) as follows:

4.1 Locate CEA #01 coil monitor connector on front side of 2C72. (This is a round, capped connector with (#1) located directly above it.

4.2 Remove connector cap by unscrewing.

4.3 With DVM scale set on 200mV, take voltage reading across pins C and D. (A typical reading is 8 millivolts DC.)

4.3.1 7.12 Record DVM reading = _______mV 7.12 0.00712 Convert mV to Volts:_______ mV X 1 V = ________V 1000 mV 0.00712 V Record (Vshunt) = ______

4.4 Screw connector cap back on CEA #01 coil monitor connector.

5.0 Utilize ohms law to calculate coil current (Icoil) as follows.

5.1 (Icoil) = (Vshunt) ______V ÷ .002 ohms.

5.2 (Icoil) = ______ amps

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 19 of 44 2105.009 CEDM CONTROL SYSTEM OPERATION CHANGE: 032 EXHIBIT 2 2105.009 Revised 04/24/13 CEA #01 UPPER GRIPPER COIL TEMPERATURE MEASUREMENT PAGE 2 OF 2 6.0 Calculate coil resistance (Rcoil1) as follows:

6.1 (Rcoil1) = (Vug)______V ÷ (Icoil) ______ amps (Rcoil1) = ______ ohms NOTE Lead resistance must be subtracted to obtain accurate reading. Lead resistance for CEA #1 is provided in this calculation. However, a lookup table for lead resistance is provided when using WO# 50654677 to calculate other CEA coil temperatures.

6.2 (Rcoil2) = ______(Rcoil1) - .525 ohms(CEA #01 lead resistance).

6.3 (Rcoil2) = ______ ohms 7.0 Obtain CEA #01 coil temperature as follows:

7.1 Use the following to obtain CEA #01 coil temperature:

Coil resistance (Rcoil2) calculated in step 6.0 Table below RESISTANCE TEMP RESISTANCE TEMP RESISTANCE TEMP RESISTANCE TEMP 5.6 0.022 7.5 126.695 9.4 253.368 11.3 380.041 5.7 6.689 7.6 133.362 9.5 260.035 11.4 386.708 5.8 13.356 7.7 140.029 9.6 266.702 11.5 393.375 5.9 20.023 7.8 146.696 9.7 273.369 11.6 400.042 6 26.69 7.9 153.363 9.8 280.036 11.7 406.709 6.1 33.357 8 160.03 9.9 286.703 11.8 413.376 6.2 40.024 8.1 166.697 10 293.37 11.9 420.043 6.3 46.691 8.2 173.364 10.1 300.037 12 426.71 6.4 53.358 8.3 180.031 10.2 306.704 12.1 433.377 6.5 60.025 8.4 186.698 10.3 313.371 12.2 440.044 6.6 66.692 8.5 193.365 10.4 320.038 12.3 446.711 6.7 73.359 8.6 200.032 10.5 326.705 12.4 453.378 6.8 80.026 8.7 206.699 10.6 333.372 12.5 460.045 6.9 86.693 8.8 213.366 10.7 340.039 12.6 466.705 7 93.36 8.9 220.033 10.8 346.706 12.7 473.365 7.1 100.027 9 226.7 10.9 353.373 12.8 480.025 7.2 106.694 9.1 233.367 11 360.04 12.9 493.345 7.3 113.361 9.2 240.034 11.1 366.707 13 500.050 7.4 120.028 9.3 246.701 11.2 373.374 13.1 506.665 All applicable steps are complete.

Expected system response obtained.

KEY PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 18 of 44 2105.009 CEDM CONTROL SYSTEM OPERATION CHANGE: 032 EXHIBIT 2 2105.009 Revised 04/24/13 CEA #01 UPPER GRIPPER COIL TEMPERATURE MEASUREMENT PAGE 1 OF 2 Exhibit provides Operations ability to measure and trend CEA-01 upper gripper coil temperature. Other historically hot CEAs (2, 4, 8, 14, 15, 18, 55, 63, and 72) can also be measured by referring to WO# 50654677 CR-ANO-2-1999-0433-004.

1.0 Obtain currently calibrated Handheld Digital Voltmeter (DVM) or equivalent multimeter (Refer to 2OPG-012 for DVM usage).

NOTE Hold Bus voltage prevents obtaining proper temperature readings.

Record absolute values of voltage readings obtained.

2.0 Check CEA #01 NOT on Hold Bus.

3.0 Obtain CEA #01 Upper Gripper coil voltage (Vug) as follows:

3.1 Locate CEA #1 power cables in panel on TBC4C6, (behind access panel to left of 2C72 door).

3.2 With DVM scale set on 200, take voltage reading across Black and White cables located on TBC4C6, terminals #4 and #5. (A typical reading is 44 VDC).

44 V (Vug) = ______

4.0 Obtain CEA #01 Upper Gripper shunt voltage (Vshunt) as follows:

4.1 Locate CEA #01 coil monitor connector on front side of 2C72. (This is a round, capped connector with (#1) located directly above it.

4.2 Remove connector cap by unscrewing.

4.3 With DVM scale set on 200mV, take voltage reading across pins C and D. (A typical reading is 8 millivolts DC.)

4.3.1 7.12 Record DVM reading = _______mV 7.12 0.00712 Convert mV to Volts:_______ mV X 1 V = ________V 1000 mV 0.00712 V Record (Vshunt) = ______

4.4 Screw connector cap back on CEA #01 coil monitor connector.

5.0 Utilize ohms law to calculate coil current (Icoil) as follows.

5.1 (Icoil) = (Vshunt) 0.00712

______V ÷ .002 ohms.

3.56 to 5.2 (Icoil) = ______

3.6 amps

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 19 of 44 2105.009 CEDM CONTROL SYSTEM OPERATION CHANGE: 032 EXHIBIT 2 2105.009 Revised 04/24/13 CEA #01 UPPER GRIPPER COIL TEMPERATURE MEASUREMENT PAGE 2 OF 2 6.0 Calculate coil resistance (Rcoil1) as follows:

3.56 6.1 44 (Rcoil1) = (Vug)______V ÷ (Icoil) to 3.6 amps 12.2 to (Rcoil1) = ______

12.36 ohms NOTE Lead resistance must be subtracted to obtain accurate reading. Lead resistance for CEA #1 is provided in this calculation. However, a lookup table for lead resistance is provided when using WO# 50654677 to calculate other CEA coil temperatures.

12.2 to 6.2 (Rcoil2) = ______(R 12.36 coil1) - .525 ohms(CEA #01 lead resistance).

11.675 to 6.3 11.835 ohms (Rcoil2) = ______

7.0 Obtain CEA #01 coil temperature as follows:

7.1 Use the following to obtain CEA #01 coil temperature:

Coil resistance (Rcoil2) calculated in step 6.0 Table below RESISTANCE TEMP RESISTANCE TEMP RESISTANCE TEMP RESISTANCE TEMP 5.6 0.022 7.5 126.695 9.4 253.368 11.3 380.041 5.7 6.689 7.6 133.362 9.5 260.035 11.4 386.708 5.8 13.356 7.7 140.029 9.6 266.702 11.5 393.375 5.9 20.023 7.8 146.696 9.7 273.369 11.6 400.042 6 26.69 7.9 153.363 9.8 280.036 11.7 406.709 6.1 33.357 8 160.03 9.9 286.703 11.8 413.376 6.2 40.024 8.1 166.697 10 293.37 11.9 420.043 6.3 46.691 8.2 173.364 10.1 300.037 12 426.71 6.4 53.358 8.3 180.031 10.2 306.704 12.1 433.377 6.5 60.025 8.4 186.698 10.3 313.371 12.2 440.044 6.6 66.692 8.5 193.365 10.4 320.038 12.3 446.711 6.7 73.359 8.6 200.032 10.5 326.705 12.4 453.378 6.8 80.026 8.7 206.699 10.6 333.372 12.5 460.045 6.9 86.693 8.8 213.366 10.7 340.039 12.6 466.705 7 93.36 8.9 220.033 10.8 346.706 12.7 473.365 7.1 100.027 9 226.7 10.9 353.373 12.8 480.025 7.2 106.694 9.1 233.367 11 360.04 12.9 493.345 7.3 113.361 9.2 240.034 11.1 366.707 13 500.050 7.4 120.028 9.3 246.701 11.2 373.374 13.1 506.665 All applicable steps are complete.

Expected system response obtained.

ANO-2-JPM-NRC-ADMIN-CNTMT2 (A2) PAGE 1 OF 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 002 DATE:

SYSTEM/DUTY AREA: Conduct of Operations TASK: Determine time to start CNTMT evacuation and closure JTA#: ANO2-RO-EOPAOP-OFFNORM-186 Alternate Path Yes: No: X Time Critical Yes: No: X KA VALUE RO: 3.9 SRO: 4.2 KA

REFERENCE:

2.1.25 APPROVED FOR ADMINISTRATION TO: RO: X SRO:

TASK LOCATION: INSIDE CR: OUTSIDE CR: BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform Classroom: Perform POSITION EVALUATED: RO: X SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: Classroom:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 10 Minutes REFERENCE(S): OP-2202.010, Standard Attachment 32, Containment Evacuation Checklist EXAMINEE'S NAME: Badge #:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Stop Total Time Time Time

ANO-2-JPM-NRC-ADMIN-CNTMT2 (A2) PAGE 2 OF 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

Plant is in Mode 5 in preps for a refueling outage.

RCPs are secured and not available.

Shutdown Cooling is lost at 0605 today.

CETs and RVLMS ATS are operable.

RCS conditions @ 605 after SDC was lost:

RCS CET temperature is 172 0F RCS pressure is 240 psia PZR level is 41%

RCS heatup rate is 4.33 degrees per minute.

TASK STANDARD:

Determined Saturation temperature the RCS pressure to be between 397.405 and 397 0F Determined time to boil to be between 51to 52.1 minutes.

Determined time to start containment evacuation between 0626 and 0627.1 TASK PERFORMANCE AIDS:

OP 2202.010 Standard Attachments, Attachment 32, Containment Evacuation Checklist.

Steam tables.

SIMULATOR SETUP:

NA EXAMINER'S NOTES:

ANO-2-JPM-NRC-ADMIN-CNTMT2 (A2) PAGE 3 OF 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:

The SM/CRS directs you to determine time to start CNTMT evacuation and closure using OP 2202.010, Standard Attachment 32, by performing step 2.

Start Time:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

Procedure Note:

CETs and ATS will NOT be operable with Reactor Vessel Head removed.

1. Determine time to start CNTMT Examinee determined Step is N/A SAT UNSAT (Step evacuation and closure as follows: not applicable.

2.A)

A. IF RCS in reduced inventory AND CETs NOT available, THEN perform the following:

2. IF CETs or RVLMS ATS operable, Examinee documented the N/A SAT UNSAT (Step THEN determine time to boiling as heatup rate give in the initial 2.B.1) follows: conditions.
1) Determine and record RCS heatup rate.

F/min heatup rate (C) 3. Using the steam tables and N/A SAT UNSAT (Step 2) Determine and record saturation current RCS pressure Examinee 2.B.2) temperature using steam tables determined that the staturation and temperature for 240 psia is present RCS pressure. between 397.405 0F and 397 0F F

saturation temperature (TSAT)

(C) 4. 3) Solve for time to boiling: Examinee calculated the time to N/A SAT UNSAT (Step boiling to be between 52.1 and 2.B.3) {TSAT} - {RCS temp} 51 min.

= time to boiling {t3}

{heatup rate}

{ F} - { F} = minutes

{ F/min}

5. 4) Record time to boil (t3) in step Examinee recorded time N/A SAT UNSAT (Step 2.E. calculated in step 2.B.3 in step 2.B.4) 2.E.
6. C. Record time SDC was lost {t1}. Examinee recorded time from N/A SAT UNSAT (Step initial conditions in step 2.E.

2.C)

ANO-2-JPM-NRC-ADMIN-CNTMT2 (A2) PAGE 4 OF 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

7. D. IF time to boiling can NOT be Examinee determined step is N/A SAT UNSAT (Step calculated, not applicable.

2.D) THEN record time to boil (t3) from Control Room logs in Step 2.E.

(C) 8. E. Calculate time to start CNTMT Examinee calculated to time to N/A SAT UNSAT (Step evacuation and closure as follows: start CNTMT evacuation and 2.E) closure to be between 0627.1

{ t1 } + [ { t3 } - 30 minutes] and 0626.

= { time to start Step 5 }

+ [ - 30 minutes] = .

END

ANO-2-JPM-NRC-ADMIN-CNTMT2 (A2) PAGE 5 OF 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERS COPY INITIAL CONDITIONS:

Plant is in Mode 5 in preps for a refueling outage.

RCPs are secured and not available.

Shutdown Cooling is lost at 0605.

Current time is 0610.

CETs and RVLMS ATS are operable.

RCS conditions @ 605 after SDC was lost:

RCS temperature = 172 0F RCS pressure is 240 psia PZR level is 41%

RCS heatup rate is 4.33 degrees per minute.

INITIATING CUE:

The SM/CRS directs you to determine time to start CNTMT evacuation and closure using OP 2202.010, Standard Attachment 32, by performing step 2.

Time to Start evacuation and closure:_________627.1 to 626.0_____________________

ANO-2-JPM-NRC-ADMIN-CNTMT2 (A2) PAGE 6 OF 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEES COPY INITIAL CONDITIONS:

Plant is in Mode 5 in preps for a refueling outage.

RCPs are secured and not available.

Shutdown Cooling is lost at 0605.

Current time is 0610.

CETs and RVLMS ATS are operable.

RCS conditions @ 605 after SDC was lost:

RCS temperature = 172 0F RCS pressure is 240 psia PZR level is 41%

RCS heatup rate is 4.33 degrees per minute.

INITIATING CUE:

The SM/CRS directs you to determine time to start CNTMT evacuation and closure using OP 2202.010, Standard Attachment 32, by performing step 2.

Time to Start evacuation and closure:____________________________________________

KEY ATTACHMENT 32 CNTMT EVACUATION CHECKLIST Page 1 of 3

1. IF Outage Desk manned, THEN notify Shift Outage Manager of the condition.
2. Determine time to start CNTMT evacuation and closure as follows:

NOTE CETs and ATS will NOT be operable with Reactor Vessel Head removed.

A. IF RCS in reduced inventory AND CETs NOT available, THEN perform the following:

1) Verify CNTMT purge secured using 2104.033, Containment Atmosphere Control.
2) GO TO Step 5.B of this Attachment AND initiate CNTMT evacuation and closure.

B. IF CETs or RVLMS ATS operable, THEN determine time to boiling as follows:

1) Determine and record RCS heatup rate.

4.33 F/min heatup rate

2) Determine and record saturation temperature using steam tables and present RCS pressure.

397.405 to 397 F saturation temperature (TSAT)

3) Solve for time to boiling:

{TSAT} - {RCS temp}

= time to boiling {t3}

{heatup rate}

{ 397.405 to 397 F} - { 172 F} = 51 to 52.1 minutes

{ 4.33 F/min}

4) Record time to boil (t3) in step 2.E.

(Step 2 continued on next page)

PROC NO TITLE REVISION PAGE Page 1 of 3 104 of 204

ATTACHMENT 32 CNTMT EVACUATION CHECKLIST Page 2 of 3

2. (continued)

C. Record time SDC was lost {t1}.

D. IF time to boiling can NOT be calculated, THEN record time to boil (t3) from Control Room logs in Step 2.E.

E. Calculate time to start CNTMT evacuation and closure as follows:

{ t1 } + [ { t3 } - 30 minutes] = { time to start Step 5 }

0605 + [ 52.1 to 51 - 30 minutes] = 0627.1 to 0626.

3. Verify CNTMT purge/ventilation secured using 2104.033, Containment Atmosphere Control.
4. WHEN RCS temperature greater than 180°F, THEN perform the following:

A. Locally verify "RWT RECIRC AND TEST LINE" valve (2BS-26) open.

B. Place ONE HPSI pump handswitch in NORMAL AFTER STOP.

C. WHEN RCS temperature greater than 195°F, THEN verify the following on PPS inserts:

1) HI/LO SG Level Bypass Permissive lights extinguished.
2) IF HI/LO SG Bypass Permissive lights do NOT extinguish, THEN place associated handswitch in NORMAL.
3) Verify NORMAL lights are ON.
4) Verify at least 3 channels operable.

PROC NO TITLE REVISION PAGE Page 1 of 3 105 of 204

ANO-2-JPM-NRC-ADMIN-CNTMT (A3) PAGE 1 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 002 DATE:

SYSTEM/DUTY AREA: Conduct of Operations TASK: Evaluate Containment Atmospheric Conditions JTA#: ANO2-RO-CVENT-NORM-7 Alternate Path Yes: No: X Time Critical Yes: No: X KA VALUE RO: 3.7 SRO: 4.1 KA

REFERENCE:

2.2.12 APPROVED FOR ADMINISTRATION TO: RO: X SRO:

TASK LOCATION: INSIDE CR: OUTSIDE CR: BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform Classroom: Perform POSITION EVALUATED: RO: X SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: Classroom:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 10 Minutes REFERENCE(S): OP-2104.033, Containment Atmosphere Control EXAMINEE'S NAME: Badge #:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Stop Total Time Time Time

ANO-2-JPM-NRC-ADMIN-CNTMT (A3) PAGE 2 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

Plant is in Mode 1.

PMS printer is broken and TS surveillance 4.4.6.1 needs to be completed.

The following values were recorded from PMS:

T5605-5 is 130.57 degrees F T5606-6 is not available P5601-1 is 14.02 psia P5602-2 is 13.95 psia P5603-3 is 14.01 psia P5604-4 is 14.16 psia TASK STANDARD:

Determined that Containment Temperature and Pressure are not in the acceptable region of operation.

Calculated Average Containment Temperature was 134.5 to 135 F.

Calculated Average Containment Pressure was 14.0 to 14.03 psia.

TASK PERFORMANCE AIDS:

OP 2104.033 Containment Atmosphere Control, Supplement 4, Containment Atmospheric Conditions Using Computer SIMULATOR SETUP:

NA EXAMINER'S NOTES:

ANO-2-JPM-NRC-ADMIN-CNTMT (A3) PAGE 3 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:

The SM/CRS directs you to perform an evaluation of containment atmospheric conditions using OP 2104.033, Containment Atmosphere Control, Supplement 4.

Start Time:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

1. Record containment Recorded containment N/A SAT UNSAT temperature. temperature readings in OP 2104.033 Supplement 4 Step 2.1.

(C) 2. Calculate average containment Used formulas provided in N/A SAT UNSAT temperature. OP 2104.033 Supplement 4 and given temperatures to calculate average containment temperature. (134.5 to 135 F)

Recorded average containment temperature on OP 2104.033 Supplement 4 Step 2.1.

3. Record containment pressure. Recorded containment pressure N/A SAT UNSAT readings in OP 2104.033 Supplement 4 Step 2.2.

(C) 4. Calculate average containment Used table provided in N/A SAT UNSAT pressure. OP 2104.033 Supplement 4 Step 2.2 and given pressures to calculate average containment pressure. (14.0 to 14.03 psia)

Recorded average containment pressure on OP 2104.033 Supplement 4 Step 2.2.

5. Plot average containment Plotted calculated parameters N/A SAT UNSAT pressure vs average on OP 2104.033 Supplement 4, containment temperature. Figure 1.

(C) 6. Compare containment Used containment N/A SAT UNSAT Atmospheric parameters to pressure-temperature point Technical Specification plotted on Figure 4-1 and requirements. determined containment atmospheric conditions were not within the region of acceptable operations.

Completed OP 2104.033 Supplement 4 Section 3.0 to indicate Technical Specification 3.6.1.4 non-compliance.

END

ANO-2-JPM-NRC-ADMIN-CNTMT (A3) PAGE 4 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERS COPY INITIAL CONDITIONS:

Plant is in Mode 1.

PMS printer is broken and TS surveillance 4.4.6.1 needs to be completed.

The following values were recorded from PMS:

T5605-5 = 130.57 degrees F T5606-6 is not available P5601-1 = 14.02 psia P5602-2 = 13.95 psia P5603-3 = 14.16 psia P5604-4 = 13.99 psia INITIATING CUE:

The SM/CRS directs you to perform an evaluation of containment atmospheric conditions using OP 2104.033, Containment Atmosphere Control, Supplement 4.

Average Containment temperature: ____134.5 to 135 F______

Average Containment pressure: _____14.0 to 14.03_psia__

Is the plotted point in the Acceptable Region of Figure 1? Yes / No .

ANO-2-JPM-NRC-ADMIN-CNTMT (A3) PAGE 5 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEES COPY INITIAL CONDITIONS:

Plant is in Mode 1.

PMS printer is broken and TS surveillance 4.4.6.1 needs to be completed.

The following values were recorded from PMS:

T5605-5 = 130.57 degrees F T5606-6 is not available P5601-1 = 14.02 psia P5602-2 = 13.95 psia P5603-3 = 14.16 psia P5604-4 = 13.99 psia INITIATING CUE:

The SM/CRS directs you to perform an evaluation of containment atmospheric conditions using OP 2104.033, Containment Atmosphere Control, Supplement 4.

Average Containment temperature: _________________

Average Containment pressure: __________________

Is the plotted point in the Acceptable Region of Figure 1? Yes / No .

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 80 of 85 2104.033 CONTAINMENT ATMOSPHERE CONTROL CHANGE: 074 SUPPLEMENT 4 PAGE 1 OF 2 CONTAINMENT ATMOSPHERIC CONDITIONS USING COMPUTER This supplement provides method to determine Containment Atmospheric conditions.

A PMS printout is obtained or Supplement 4 or 6 performed at least once each 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in Modes 1, 2, 3 and 4 per TS 4.6.1.4. Curves in Figure 1 bound area that is Tech Spec limit with instrument error calculations incorporated. Region 1 of curve is acceptable region when only three computer points are used. Region 2 of curve, which includes Region 1, is acceptable region when all four computer points are used.

1.0 INITIAL CONDITIONS Verify at least one CNTMT temperature AND at least three CNTMT pressure Computer Points available.

2.0 TEST METHOD 2.1 Use one of the following to determine Containment temperature based on availability of computer data points T5605-5 and T5606-6:

Average CNTMT Temp = (T5605-5 + T5606-6) 2 = _________ °F T5605-5 + 4 = _________ °F (If using only T5605-5)

T5606-6 = _________ °F (If using only T5606-6)

NOTE Average CNTMT pressure should be maintained between 13.9 and 14.2 psia to maintain cushion for loss of chill water unless raising pressure to 14.7 prior to outage.

2.2 Calculate average Containment pressure as follows:

(N/A point if not available)

P5601-1 _________ psia P5602-2 _________ psia P5603-3 _________ psia P5604-4 _________ psia Add points and divide by total number of points used.

Average CNTMT pressure = __________ psia 2.3 Plot average Containment pressure vs temperature on Figure 1.

3.0 ACCEPTANCE CRITERIA 3.1 Did plotted point fall within bounds of Figure 1? YES NO Performed By __________________________________ Date __________ Time __________

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 81 of 85 2104.033 CONTAINMENT ATMOSPHERE CONTROL CHANGE: 074 SUPPLEMENT 4 PAGE 2 OF 2 4.0 SUPERVISOR REVIEW AND ANALYSIS 4.1 Have Containment Atmospheric conditions been proven YES NO acceptable using ACCEPTANCE CRITERIA?

4.2 IF NO answered to 4.1, YES NO N/A THEN has Supplement 6 been performed?

4.3 Are all administrative requirements of this test satisfied? YES NO Supervisor __________________________________________ Date __________

FIGURE 1

{4.3.1}

17 UNACCEPTABLE R E G IO N 16 AVERAGE CNTMT PRESSURE (PSIA)

R e g io n 2 B o u n d a ry 15 AC C E PT ABLE R E G IO N R e g io n 1 B o u n d a ry 14 13 50 60 70 80 90 100 110 120 130 140 150 R e g io n 1 P o in ts A V E R A G E C N T M T T E M P E R A T U R E (OF ) R e g io n 2 P o in ts 6 1 , 1 5 .2 6 1 , 1 5 .2 5 1 3 9 , 1 5 .2 1 3 9 , 1 5 .2 5 1 3 9 ,1 4 .6 3 1 3 9 , 1 4 .5 8 1 2 5 .5 6 , 1 3 .5 1 2 5 .5 4 , 1 3 .4 5 6 1 , 1 3 .5 6 1 , 1 3 .4 5 Region 1 acceptable region when 3 computer points are used.

Region 2 includes Region 1 and area between curves and is acceptable region when all 4 computer points are used.

KEY PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 80 of 85 2104.033 CONTAINMENT ATMOSPHERE CONTROL CHANGE: 074 SUPPLEMENT 4 PAGE 1 OF 2 CONTAINMENT ATMOSPHERIC CONDITIONS USING COMPUTER This supplement provides method to determine Containment Atmospheric conditions.

A PMS printout is obtained or Supplement 4 or 6 performed at least once each 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in Modes 1, 2, 3 and 4 per TS 4.6.1.4. Curves in Figure 1 bound area that is Tech Spec limit with instrument error calculations incorporated. Region 1 of curve is acceptable region when only three computer points are used. Region 2 of curve, which includes Region 1, is acceptable region when all four computer points are used.

1.0 INITIAL CONDITIONS Verify at least one CNTMT temperature AND at least three CNTMT pressure Computer Points available.

2.0 TEST METHOD 2.1 Use one of the following to determine Containment temperature based on availability of computer data points T5605-5 and T5606-6:

Average CNTMT Temp = (T5605-5 + T5606-6) N/A 2 = _________ °F 134.57 °F T5605-5 + 4 = _________ (If using only T5605-5)

N/A T5606-6 = _________ °F (If using only T5606-6)

NOTE Average CNTMT pressure should be maintained between 13.9 and 14.2 psia to maintain cushion for loss of chill water unless raising pressure to 14.7 prior to outage.

2.2 Calculate average Containment pressure as follows:

(N/A point if not available) 14.02 psia P5601-1 _________ 13.95 psia P5602-2 _________

14.16 psia P5603-3 _________ 13.99 psia P5604-4 _________

Add points and divide by total number of points used.

14.03 Average CNTMT pressure = __________ psia 2.3 Plot average Containment pressure vs temperature on Figure 1.

3.0 ACCEPTANCE CRITERIA 3.1 Did plotted point fall within bounds of Figure 1? YES NO Performed By __________________________________ Date __________ Time __________

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 81 of 85 2104.033 CONTAINMENT ATMOSPHERE CONTROL CHANGE: 074 SUPPLEMENT 4 PAGE 2 OF 2 4.0 SUPERVISOR REVIEW AND ANALYSIS 4.1 Have Containment Atmospheric conditions been proven YES NO acceptable using ACCEPTANCE CRITERIA?

4.2 IF NO answered to 4.1, YES NO N/A THEN has Supplement 6 been performed?

4.3 Are all administrative requirements of this test satisfied? YES NO Supervisor __________________________________________ Date __________

FIGURE 1

{4.3.1}

17 UNACCEPTABLE R E G IO N 16 AVERAGE CNTMT PRESSURE (PSIA)

R e g io n 2 B o u n d a ry 15 AC C E PT ABLE R E G IO N R e g io n 1 B o u n d a ry 14 13 50 60 70 80 90 100 110 120 130 140 150 R e g io n 1 P o in ts A V E R A G E C N T M T T E M P E R A T U R E (OF ) R e g io n 2 P o in ts 6 1 , 1 5 .2 6 1 , 1 5 .2 5 1 3 9 , 1 5 .2 1 3 9 , 1 5 .2 5 1 3 9 ,1 4 .6 3 1 3 9 , 1 4 .5 8 1 2 5 .5 6 , 1 3 .5 1 2 5 .5 4 , 1 3 .4 5 6 1 , 1 3 .5 6 1 , 1 3 .4 5 Region 1 acceptable region when 3 computer points are used.

Region 2 includes Region 1 and area between curves and is acceptable region when all 4 computer points are used.

ANO-2-JPM-NRC-ADMIN-CRADMON A4 Page 1 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 2 DATE:

SYSTEM/DUTY AREA: Radiation Control TASK: Determine Condenser off gas radiation monitor setting.

JTA#: ANO2-RO-RMS-OFFNORM-13 Alternate Path Yes: No: X Time Critical Yes: No: X KA VALUE RO: 2.9 SRO: 3.1 KA

REFERENCE:

2.3.15 APPROVED FOR ADMINISTRATION TO: RO: X SRO:

TASK LOCATION: INSIDE CR: OUTSIDE CR: BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform CLASSROOM: Perform POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: CLASSROOM:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 15 Minutes REFERENCE(S): 2105.016, Radiation Monitoring and Evacuation system. Unit 2 OPS B2 CBO Log.

EXAMINEE'S NAME: Badge #:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Time Stop Time Total Time

ANO-2-JPM-NRC-ADMIN-CRADMON A4 Page 2 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

Unit 2 is in Mode 1.

2K11-A10 Secondary System radiation hi alarm is locked in due to 2RITS-0645 Condenser off gas radiation monitor.

Crew has entered Primary to Secondary leakage AOP due to a small primary to secondary leak that does not require a shutdown.

The 2RITS-0645 was logged reading 375 CPM on the OPS-B2 CBO log.

SM has given permission to adjust the alarm setpoint for 2RITS-0645.

TASK STANDARD:

Determined the new potentiometer setting for the alarm setpoint of 2RITS-0645 (potentiometer setting: 3.45) and the new voltage setting for 2RR-1057 (1.778 to 1.835) Secondary Radiation Recorder.

TASK PERFORMANCE AIDS:

2105.016, Radiation Monitoring and Evacuation system, and Unit 2 OPS-B2 CBO Log

ANO-2-JPM-NRC-ADMIN-CRADMON A4 Page 3 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:

Determine the highest allowable new potentiometer setting of 2RITS-0645, Condenser Off Gas Radiation Monitor, and highest allowable new voltage setting for 2RR-1057, Secondary Radiation Recorder, IAW 2105.016, Radiation Monitoring and Evacuation System, and OPS-B2 CBO log. Inform examiner when ready to adjust 2RITS-0645 alarm setpoint IAW step 11.3.2.

START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

1. Determine new high alarm Examinee reviewed the Unit 2 N/A SAT UNSAT (Step setpoint for 2RITS-0645 from OPS-B2 CBO Log and 2105.016 11.1) Unit 2 CBOT Electrical log and determined that the new (OPS-B2). alarm set point should be 700 cpm.

Verify setpoint within the following limits:

- Minimum high alarm setpoint of 250 cpm

- Smaller of 2 times background or 300 cpm above background

2. Obtain SM permission to adjust Examinee determined SM N/A SAT UNSAT (Step alarm setpoints for 2RITS-0645. permission was given from the 11.2) initial conditions.

(C) 3. Perform the following to change Examinee determined the new N/A SAT UNSAT (Step 2RITS-0645 high alarm setpoint setting for 2RITS-0645 is 3.45 11.3 on 2C25: from Table 1.

and 11.3.1) Determine potentiometer dial setting which corresponds to desired high alarm setpoint from Table 1 below.

4. Adjust 2RITS-0645 high alarm Examinee told examiner they N/A SAT UNSAT (Step setpoint potentiometer to were ready to adjust the 11.3.2) required setting. potentiometer per the initiating cue.

Examiner Cue: Report that the Potentiometer has been adjusted the desired setting.

ANO-2-JPM-NRC-ADMIN-CRADMON A4 Page 4 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 5. Perform the following to change Examinee determined the new N/A SAT UNSAT (Step 2RITS-0645 high alarm on voltage setting for 2RR-1057 is 11.4 Secondary Radiation Recorder 1.778 from Table 2.

and (2RR-1057) on 2C14 and SEC 11.4.1) SYS RADIATION HI (2K11-A10):

Determine voltage setting which Examiner Note: Either step 5 corresponds to desired high or step 6 is critical based on alarm setpoint from Table 2. the which method the examinee chooses to determine the new voltage setting but the voltage setting must in the following band.

1.778 to 1.835 (C) 6. IF desired setpoint NOT in Examinee determined the new N/A SAT UNSAT (Step Table 2, voltage setting to be between 11.4.2) THEN perform the following to 1.813 and 1.835 calculate corresponding voltage:

[ln(x) - ln(10)] x = desired counts y= Examiner Note: Either step 5 or step 6 is critical based on ln(10) y = required voltage setting the which method the examinee chooses to determine the new voltage setting but the voltage setting must in the following band.

1.778 to 1.835 END STOP TIME:

ANO-2-JPM-NRC-ADMIN-CRADMON A4 Page 5 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERS COPY INITIAL CONDITIONS:

Unit 2 is in Mode 1.

2K11-A10 Secondary System radiation hi alarm is locked in due to 2RITS-0645 Condenser off gas radiation monitor.

Crew has entered Primary to Secondary leakage AOP due to a small primary to secondary leak that does not require a shutdown.

The 2RITS-0645 was logged reading 375 CPM on the OPS-B2 CBO log.

SM has given permission to adjust the alarm setpoint for 2RITS-0645.

INITIATING CUE:

Determine the highest allowable new potentiometer setting of 2RITS-0645, Condenser Off Gas Radiation Monitor, and highest allowable new voltage setting for 2RR-1057, Secondary Radiation Recorder, IAW 2105.016, Radiation Monitoring and Evacuation System, and OPS-B2 CBO log. Inform examiner when ready to adjust 2RITS-0645 alarm setpoint IAW step 11.3.2.

2RITS-0645 potentiometer setting: ______3.45_______________________

2RR-1057 voltage setting: _______1.778 to 1.835_______________________

ANO-2-JPM-NRC-ADMIN-CRADMON A4 Page 6 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEES COPY

`INITIAL CONDITIONS:

Unit 2 is in Mode 1.

2K11-A10 Secondary System radiation hi alarm is locked in due to 2RITS-0645 Condenser off gas radiation monitor.

Crew has entered Primary to Secondary leakage AOP due to a small primary to secondary leak that does not require a shutdown.

The 2RITS-0645 was logged reading 375 CPM on the OPS-B2 CBO log.

SM has given permission to adjust the alarm setpoint for 2RITS-0645.

INITIATING CUE:

Determine the highest allowable new potentiometer setting of 2RITS-0645, Condenser Off Gas Radiation Monitor, and highest allowable new voltage setting for 2RR-1057, Secondary Radiation Recorder, IAW 2105.016, Radiation Monitoring and Evacuation System, and OPS-B2 CBO log. Inform examiner when ready to adjust 2RITS-0645 alarm setpoint IAW step 11.3.2.

2RITS-0645 potentiometer setting: ______________________________

2RR-1057 voltage setting: ______________________________

UNIT 2 CBOT ELECTRICAL OPS-B2 1/9/2012 Unit Two OPS 10/30/2014 Unit Two Rounds Page 13 of 42 CNTM PURGE MON SETPT REQUIRED Seq: 50 138 Equip. 2-RMS -SWITCH-2RITS-8233 Location: CR2-386-2C25 ID:

Short Instr: TS 3.3.3.1, ODCM L2.2.1 SEE LONG INSTRUCTIONS Long Instr: IF IN VENTILATE MODE, THEN MAX SETPOINT IS SMALLER OF 2X AVG BKGRD OR 3500 CPM. IF SETPT >2X AVG BKGRD, THEN ADJUST USING 2104.033. REFER TO TS 3.3.3.1, ODCM L2.2.1. b) IF CNTMT PURGE IS IN PROGRESS, THEN 2104.033 ATT C SATISFIES THE <2X BKGRD REQ.

Units: CPM Minimum: >= 10 Maximum: <= <EXPR>

Shift Time Reading Notes Recorded By Days 200 Joe RO Nights Extra Set 1 Extra Set 2 Order Description Expression Text Color 1 SETPOINT EXCEEDS 2 X BACKGROUND N(STA(138)) > N(AveLastX( 137 , 4 ))*2 SETPOINT EXCEEDS 2 X BACKGROUND 255 2 SETPOINT EXCEEDS 3500 N(STA(138)) > 3500 IF IN VENTILATE MODE, THEN MAX SETPOINT IS 255 SMALLER OF 2X AVG BKGRD OR 3500 CPM SEE LONG INSTRUCTIONS Max. Expr.: N(AveLastX( 138 , 4 ))*2 Appl. Expr.: N(STA(57))>4 2RITS-8233 READING REQUIRED Seq: 51 137 Equip. 2-RMS -SWITCH-2RITS-8233 Location: CR2-386-2C25 ID:

Short Instr: MAX=2X BACKGROUND TS 3.3.3.1 ODCM L2.2.1.

Units: CPM Shift Time Reading Notes Recorded By Days 105 Joe RO Nights Extra Set 1 Extra Set 2 SETPOINT FOR 2RITS-0645 REQUIRED Seq: 52 136 Location: CR2-386-2C25 Short Instr: SEE LONG INSTRUCTION FOR MAX CRITERIA Long Instr: IF COND VAC PUMP IS IN OPERATION, THEN THE HIGH ALARM SETPT SHALL BE THE SMALLER OF 2X BACKGROUND OR APP 300 CPM ABOVE BKGRD. MINIMUM SETPOINT IS 250 CPM.

Units: CPM Minimum: >= 250 Shift Time Reading Notes Recorded By Days 250 Joe RO Nights Extra Set 1 Extra Set 2 2RITS-0645 READING COND VAC REQUIRED Seq: 53 135 Equip. 2-RMS -SWITCH-2RITS-0645 Location: CR2-386-2C25 ID:

Short Instr: 2RITS-0645 Units: CPM Maximum: <= <EXPR>

Shift Time Reading Notes Recorded By Days 375 Joe RO Nights Extra Set 1 Extra Set 2 Order Description Expression Text Color 1 EXCEEDS HIGH ALARM SETPOINT n(sta(135))>N(STA(136)) EXCEEDS HIGH ALARM SETPOINT 255 Max. Expr.: N(STA(136))

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 14 of 36 2105.016 RADIATION MONITORING AND EVACUATION SYSTEM CHANGE: 029 11.0 HIGH ALARM SETPOINT ADJUSTMENT FOR MAIN CONDENSER OFFGAS MONITOR (2RITS-0645).

11.1 Determine new high alarm setpoint for 2RITS-0645 from Unit 2 CBOT Electrical log (OPS-B2).

Verify setpoint within the following limits:

- Minimum high alarm setpoint of 250 cpm

- Smaller of 2 times background or 300 cpm above background 11.2 Obtain SM permission to adjust alarm setpoints for 2RITS-0645.

11.3 Perform the following to change 2RITS-0645 high alarm setpoint on 2C25:

11.3.1 Determine potentiometer dial setting which corresponds to desired high alarm setpoint from Table 1 below.

11.3.2 Adjust 2RITS-0645 high alarm setpoint potentiometer to required setting.

TABLE 1 Alarm Alarm Alarm Alarm Setpoint Dial Setpoint Dial Setpoint Dial Setpoint Dial CPM Setting CPM Setting CPM Setting CPM Setting 250 = 2.77 800 = 3.78 5000 = 5.24 10000 = 5.82 300 = 2.85 900 = 3.87 6000 = 5.42 20000 = 6.35 400 = 3.10 1000 = 4.00 7000 = 5.56 30000 = 6.66 500 = 3.30 2000 = 4.51 8000 = 5.68 40000 = 6.94 600 = 3.45 3000 = 4.82 9000 = 5.74 50000 = 7.09 700 = 3.62 4000 = 5.06 11.4 Perform the following to change 2RITS-0645 high alarm on Secondary Radiation Recorder (2RR-1057) on 2C14 and SEC SYS RADIATION HI (2K11-A10):

11.4.1 Determine voltage setting which corresponds to desired high alarm setpoint from Table 2 below.

TABLE 2 Alarm Alarm Alarm Alarm Setpoint Voltage Setpoint Voltage Setpoint Voltage Setpoint Voltage CPM Setting CPM Setting CPM Setting CPM Setting 250 = 1.398 425 = 1.628 1000 = 2.000 8000 = 2.903 275 = 1.439 450 = 1.653 2000 = 2.301 9000 = 2.954 300 = 1.477 500 = 1.699 3000 = 2.477 10000 = 3.000 325 = 1.512 600 = 1.778 4000 = 2.602 20000 = 3.301 350 = 1.544 700 = 1.845 5000 = 2.699 30000 = 3.477 375 = 1.574 800 = 1.903 6000 = 2.778 40000 = 3.602 400 = 1.602 900 = 1.954 7000 = 2.845 50000 = 3.699 11.4.2 IF desired setpoint NOT in Table 2, THEN perform the following to calculate corresponding voltage:

[ln(x) - ln(10)] x = desired counts y =

ln(10) y = required voltage setting

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 15 of 36 2105.016 RADIATION MONITORING AND EVACUATION SYSTEM CHANGE: 029 11.4.3 At 2RR-1057 on Panel 2C14, open recorder front cover.

11.4.4 Press MENU key and hold for three seconds to enter SET mode.

11.4.5 Select ALARM display by using UP/DOWN keys (Display shows SET = ALARM) and press ENTER key.

11.4.6 Select Channel 3 for 2RITS-0645 using UP/DOWN keys (Display shows "3:Level=") and press ENTER key.

11.4.7 Select Level of the alarm using UP/DOWN keys (Display shows 3:LEVEL = 1) and press ENTER key.

11.4.8 Select status of alarm to ON by using UP/DOWN keys (Display shows 3/1:ALM = ON) and press ENTER key.

11.4.9 Select Type alarm by using UP/DOWN keys to select H for high alarm. (Display shows 3/1:Type = H) and press ENTER key.

11.4.10 Enter desired alarm setpoint voltage value by using UP/DOWN and RIGHT keys. (Display shows 3/1:X.XXX) and press ENTER key.

11.4.11 Display which appears should show output relay to be ON (Display shows 3/1:RLY = ON) and press ENTER key.

11.4.12 Enter relay number I03 for 2RITS-0645 using UP/DOWN keys (Display shows 3/1:R.N = I03) and press ENTER key.

11.4.13 Verify display shows SET OK.

11.4.14 IF alarm setpoint satisfactorily changed to desired setting, THEN press MENU key AND hold for three seconds to return to Operation mode.

ANO-2-JPM-NRC-ADMIN-WORK (A5) PAGE 1 OF 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 000 DATE:

SYSTEM/DUTY AREA: Conduct of Operations TASK: Determine which operators are available for call out.

JTA#:

Alternate Path Yes: No: X Time Critical Yes: No: X KA VALUE RO: 2.9 SRO: 3.9 KA

REFERENCE:

2.1.5 APPROVED FOR ADMINISTRATION TO: RO: SRO: X TASK LOCATION: INSIDE CR: OUTSIDE CR: BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Classroom: Perform POSITION EVALUATED: RO: SRO: X ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: Classroom:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 20 Minutes REFERENCE(S): EN-OM-123, Fatigue Management Program.

EXAMINEE'S NAME: Badge #:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Time Stop Time Total Time

ANO-2-JPM-NRC-ADMIN-WORK (A5) PAGE 2 OF 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

Today is August 29th.

Unit 2 has been online for 300 days.

An operator for the next shift has called in sick and coverage is required from 6 am to 6 pm on Sunday August 30th.

eSOMS PQ&S and any other work hours calculators are not available due to a network outage.

All scheduled hours are required to be worked.

Four Operators are available for the watch.

Operators have averaged hours per week over previous 4 weeks prior to Aug. 23rd:

Operator A = 40 Operator B = 53 Operator C = 46 Operator D = 43 N = Nights, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift, 6 pm to 6 am.

D = Days, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift, 6 am to 6 pm.

T = Training, 8.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> shift 7:30 am to 4 pm.

  1. = number of hours for off-shift operator who starts work at 7 am.

Sun. Mon. Tue. Wed. Thu. Fri. Sat. Sun. Mon. Tue. Wed. Thu. Fri. Sat.

Aug Aug Aug Aug Aug Aug Aug Aug Aug. Sept. Sept. Sept. Sept. Sept.

23. 24. 25. 26. 27. 28. 29. 30. 31 1 2 3. 4. 5 Operator A 8 8 8 8 D 10 10 10 10 Operator B D T T T T N N N N Operator C N N N D D D D D D Operator D D D D D D D N N N TASK STANDARD:

Determined that operator B and D are available and operator A is not available due to <34 hour break in any 9-day period and operator C is not available due > 72 work hours in any 7 day period.

TASK PERFORMANCE AIDS:

EN-OP-123 Fatigue Management program.

ANO-2-JPM-NRC-ADMIN-WORK (A5) PAGE 3 OF 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:

CRS/SM directs you to determine which operator(s) can cover without violating working hours using EN-OM-123, Fatigue Management Program.

If an operator(s) would violate working hours, then state how they would violate the working hour limits.

Start Time:_________________

PERFORMANCE CHECKLIST STANDARDS (Circle One)

Procedure Note:

Work hour tracking is accomplished using the eSOMS PQ&S software. Use of an alternate compliance tool, such as by contractors / vendors, requires approval of the site SME.

Work hour limits for covered workers may only be exceeded during Exceptions (Section 5.3) or when evaluated and approved using the Waiver Process (Section 5.9).

Procedure Step for Work hour limits:

Work hour limits for individuals performing Covered Work consist of the following:

(a) Maximum of 16 work hours in any 24-hour period.

(b) Maximum of 26 work hours in any 48-hour period.

(c) Maximum of 72 work hours in any 7-day period..

(d) Minimum 10-hour break between successive work periods, except that an 8-hour break is allowed when necessary to accommodate a crews scheduled transition between work schedules or shifts.

(e) Minimum 34-hour break in any 9-day period.

(f) 54-hour rolling average, as described in 5.2[3].

(g) Minimum Days Off (MDO), as described in 5.2[4]

[2] Limits 5.2[1](a) through (e) apply for online and offline plant conditions. Limit 5.2[1](f) must be used when the plant is online and limit 5.2[1](g) is typically applied when the plant is offline, for individuals working on outage activities. However, limit 5.2[1](f) may also be used in lieu of limit 5.2[1](g) when the plant is offline.

[3] The 54-hour rolling average limit (5.2[1](f)) is a maximum average of 54 work hours per week calculated using a rolling average period of up to 6 weeks. The requirements of the averaging calculation are modeled in the PQ&S software and include the following characteristics:

1. Review work hour limitations Examinee reviewed the limitation N/A SAT UNSAT in EN-OM-123. of section 5.2 of EN-OM-123.

(Step 5.2 (C) 2. Using EN-OM-123 Reviewed the schedule for N/A SAT UNSAT (Step requirements review operator operator A to determine if any 5.2) A schedule to determine if he work hour limitations would be can provide coverage with violated.

out violating working hour limits. Critical: Determined that Operator A can not cover the th watch on August 30 with out violating working hour limits due to not having a Minimum 34 hour3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> break in any 9 day period.

ANO-2-JPM-NRC-ADMIN-WORK (A5) PAGE 4 OF 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 3. Using EN-OM-123 Reviewed the schedule for N/A SAT UNSAT requirements review operator operator B to determine if any (Step B schedule to determine if he work hour limitations would be 5.2) can provide coverage with violated.

out violating working hour limits. Critical: Determined that Operator B can cover the watch on August 30th with out violating working hour limits.

(C) 4. Using EN-OM-123 Reviewed the schedule for N/A SAT UNSAT requirements review operator operator B to determine if any (Step C schedule to determine if he work hour limitations would be 5.2) can provide coverage with violated.

out violating working hour limits. Critical: Determined that Operator C can not cover the watch on August 30th with out violating working hour limits due to > 72 work hours in any 7-day period.

(C) 5. Using EN-OM-123 Reviewed the schedule for N/A SAT UNSAT requirements review operator operator B to determine if any (Step C schedule to determine if he work hour limitations would be 5.2) can provide coverage with violated.

out violating working hour limits. Critical: Determined that Operator B can cover the watch on August 30th with out violating working hour limits.

END Stop Time:__________________

ANO-2-JPM-NRC-ADMIN-WORK (A5) PAGE 5 OF 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERS COPY INITIAL CONDITIONS:

Today is August 29th.

Unit 2 has been online for 300 days.

An operator for the next shift has called in sick and coverage is required from 6 am to 6 pm on Sunday August 30th.

eSOMS PQ&S and any other work hours calculators are not available due to a network outage.

All scheduled hours are required to be worked.

Four Operators are available for the watch.

Operators have averaged hours per week over previous 4 weeks prior to Aug. 23rd:

Operator A = 40 Operator B = 53 Operator C = 46 Operator D = 43 N = Nights, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift, 6 pm to 6 am.

D = Days, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift, 6 am to 6 pm.

T = Training, 8.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> shift 7:30 am to 4 pm.

  1. = number of hours for off-shift operator who starts work at 7 am.

Sun. Mon. Tue. Wed. Thu. Fri. Sat. Sun. Mon. Tue. Wed. Thu. Fri. Sat.

Aug Aug Aug Aug Aug Aug Aug Aug Aug. Sept Sept. Sept. Sept. Sept.

23. 24. 25. 26. 27. 28. 29. 30. 31 .1 2 3. 4. 5 Operator A 8 8 8 8 D 10 10 10 10 Operator B D T T T T N N N N Operator C N N N D D D D D D Operator D D D D D D D N N N INITIATING CUE:

CRS/SM directs you to determine which operator(s) can cover without violating working hours using EN-OM-123, Fatigue Management Program.

Operator A: Can provide coverage with out exceeding limits: Yes/No.

If No what limit is exceeded:__Minimum 34 hour3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> break in a 9 day period____.

Operator B: Can provide coverage with out exceeding limits: Yes/No.

If No what limit is exceeded:_______________________________________.

Operator C: Can provide coverage with out exceeding limits: Yes/No.

If No what limit is exceeded:_______________________________________.

Operator D: Can provide coverage with out exceeding limits: Yes/No.

If No what limit is exceeded:___ > 72 work hours in any 7-day period _________.

ANO-2-JPM-NRC-ADMIN-WORK (A5) PAGE 6 OF 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEES COPY INITIAL CONDITIONS:

Today is August 29th.

Unit 2 has been online for 300 days.

An operator for the next shift has called in sick and coverage is required from 6 am to 6 pm on Sunday August 30th.

eSOMS PQ&S and any other work hours calculators are not available due to a network outage.

All scheduled hours are required to be worked.

Four Operators are available for the watch.

Operators have averaged hours per week over previous 4 weeks prior to Aug. 23rd:

Operator A = 40 Operator B = 53 Operator C = 46 Operator D = 43 N = Nights, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift, 6 pm to 6 am.

D = Days, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift, 6 am to 6 pm.

T = Training, 8.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> shift 7:30 am to 4 pm.

  1. = number of hours for off-shift operator who starts work at 7 am.

Sun. Mon. Tue. Wed. Thu. Fri. Sat. Sun. Mon. Tue. Wed. Thu. Fri. Sat.

Aug Aug Aug Aug Aug Aug Aug Aug Aug. Sept Sept. Sept. Sept. Sept.

23. 24. 25. 26. 27. 28. 29. 30. 31 .1 2 3. 4. 5 Operator A 8 8 8 8 D 10 10 10 10 Operator B D T T T T N N N N Operator C N N N D D D D D D Operator D D D D D D D N N N INITIATING CUE:

CRS/SM directs you to determine which operator(s) can cover without violating working hours using EN-OM-123, Fatigue Management Program.

Operator A: Can provide coverage with out exceeding limits: Yes/No.

If No what limit is exceeded:_________________________________________.

Operator B: Can provide coverage with out exceeding limits: Yes/No.

If No what limit is exceeded:_________________________________________.

Operator C: Can provide coverage with out exceeding limits: Yes/No.

If No what limit is exceeded:_________________________________________.

Operator D: Can provide coverage with out exceeding limits: Yes/No.

If No what limit is exceeded:_________________________________________.

ANO-2-JPM-NRC-ADMIN-SOPP1 (A6) PAGE 1 OF 9 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 005 DATE:

SYSTEM/DUTY AREA: Conduct of Operations TASK: Determine Shutdown Operations Protection Plan Condition JTA#: A2LP-RO-SDCC Alternate Path Yes: No: X Time Critical Yes: No: X KA VALUE RO: 2.8 SRO: 3.9 KA

REFERENCE:

2.1.40 APPROVED FOR ADMINISTRATION TO: RO: SRO: X TASK LOCATION: INSIDE CR: OUTSIDE CR: BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Classroom: Perform POSITION EVALUATED: RO: SRO: X ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: Classroom:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 25 Minutes REFERENCE(S): OP 1015.048, Shutdown Operations Protection Plan EXAMINEE'S NAME: Badge #:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Time Stop Time Total Time

ANO-2-JPM-NRC-ADMIN-SOPP1 (A6) PAGE 2 OF 9 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

Plant is in Mode 6, RCS temperature is 90 0F.

Fuel Transfer Canal level is 401 6 and connected to the SFP RCS boron is 2701 ppm Both Start Up Channels and Boron Dilution Monitors are operable RCS dilution tagout is in place Time to Boil is 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> Containment equipment hatch is open and personnel hatch door interlock has been defeated. Both are capable of being closed within 30 min. Escape hatch is closed.

OPS-B33 CNTMT Closure Log and OPS-B40 SDC Log/Task Checklist are being maintained by CRS Admin.

Red train is protected IAW OP 1015.008, Unit 2 SDC Control and OP 1015.008 Att. J, Protected Train and Operations Controlled Areas, is complete for the Red train.

Plant safety index is Yellow.

ANO switchyard gate and London Line substation gates are posted with a sign that reads ATTENTION LOSS OF POWER COULD PLACE UNIT 2 AT RISK.

Core offload is currently in progress.

The following is the plant equipment alignment:

2P-60A, LPSI pump, running and SDC train A operable 2P-60B, LPSI pump, running 2P-40A, SFP cooling pump, in service 2P-40B, SFP cooling pump, available 2E-27, SFP heat exchanger, available and in service All RCS Thot indicators are in service 2P-89C, HPSI pump, aligned to Red train and protected as the RCS make up source 2P-89A, HPSI pump, is available but in Pull-to-Lock 2P-89B, HPSI pump, is tagged out for maintenance Charging pump heaters are removed for the RCS dilution tagout

  1. 1 EDG and AAC diesel are available SU#3 transformer is in service, SU#2 transformer is tagged out for maintenance Loop 1 SW is operable with 2P-4A supplying the loop Loop 2 SW is out of service with 2P-4B and 2P-4C tagged for bay inspection 2P-66, Spent Fuel Pool Purification pump, is available with sufficient RWT inventory 2P-109A and 2P-109B, Reactor make up water pumps, are both available for makeup from the RMWT Both 2P-35A and 2P-35B, Containment Spray pumps, are tagged out for maintenance TASK STANDARD:

Determined that SOPP condition was Condition 3 and that SOPP Condition 3 was NOT MET due only to Decay Heat Removal.

TASK PERFORMANCE AIDS:

OP 1015.048, Shutdown Operations Protection Plan

ANO-2-JPM-NRC-ADMIN-SOPP1 (A6) PAGE 3 OF 9 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:

CRS/SM directs you to determine Shutdown Operations Protection Plan (SOPP) condition for the current plant alignment IAW OP 1015.048, Shutdown Operations Protection Plan. Inform examiner of current condition after you have determined the condition.

INITIATING CUE #2:

CRS/SM directs you to determine if requirements are met for determined condition using OP 1015.048, Shutdown Operations Protection Plan.

Start Time:_________________

PERFORMANCE CHECKLIST STANDARDS (Circle One)

1. Determine the status of the N/A SAT UNSAT following RCS variables:

(Step 8.2)

Fuel Location Determined that fuel was located in the Reactor Vessel and Spent Reactor Coolant System Fuel Pool.

Integrity Determined that RCS was open.

Reactor Coolant System /

Fuel Transfer Canal Inventory Determined FTC flooded >23 (C) 2. Based upon the RCS Determined that SOPP Condition N/A SAT UNSAT (Step variables, determine the 3 was applicable for Unit 2 8.3) correct SOPP.

Examiner Note: The following steps are in Att. I.

(C) 3. Determine if the Determined that Decay Heat N/A SAT UNSAT requirements are met for Removal conditions were NOT (Step SOPP condition 3 for Decay met.

2.1)

Heat Removal.

Examiner note: This is due to having only one service water pump available for Spent Fuel Pool cooling.

4. Determine if the Determined that Inventory Control N/A SAT UNSAT requirements are met for conditions were met.

(Step SOPP condition 3 for 2.2)

Inventory Control.

5. Determine if the Determined that Electrical Power N/A SAT UNSAT requirements are met for conditions were met.

(Step SOPP condition 3 for 2.3)

Electrical Power.

6. Determine if the Determined that Reactivity N/A SAT UNSAT requirements are met for Control conditions were met.

(Step SOPP condition 3 for 2.4)

Reactivity Control.

7. Determine if the Determined that Containment N/A SAT UNSAT requirements are met for conditions were met.

(Step SOPP condition 3 for 2.5)

Containment.

ANO-2-JPM-NRC-ADMIN-SOPP1 (A6) PAGE 4 OF 9 ADMINISTRATIVE JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

8. Determine if the Determined that Miscellaneous N/A SAT UNSAT requirements are met for items conditions were met.

(Step SOPP condition 3 for 2.6)

Miscellaneous items.

END Stop Time:__________________

ANO-2-JPM-NRC-ADMIN-SOPP1 (A6) PAGE 5 OF 9 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERS COPY INITIAL CONDITIONS:

Plant is in Mode 6, RCS temperature is 90 0F.

Fuel Transfer Canal level is 401 6 and connected to the SFP RCS boron is 2701 ppm Both Start Up Channels and Boron Dilution Monitors are operable RCS dilution tagout is in place Time to Boil is 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> Containment equipment hatch is open and personnel hatch door interlock has been defeated. Both are capable of being closed within 30 min. Escape hatch is closed.

OPS-B33 CNTMT Closure Log and OPS-B40 SDC Log/Task Checklist are being maintained by CRS Admin.

Red train is protected IAW OP 1015.008, Unit 2 SDC Control and OP 1015.008 Att. J, Protected Train and Operations Controlled Areas, is complete for the Red train.

Plant safety index is Yellow.

ANO switchyard gate and London Line substation gates are posted with a sign that reads ATTENTION LOSS OF POWER COULD PLACE UNIT 2 AT RISK.

Core offload is currently in progress.

The following is the plant equipment alignment:

2P-60A, LPSI pump, running and SDC train A operable 2P-60B, LPSI pump, running 2P-40A, SFP cooling pump, in service 2P-40B, SFP cooling pump, available 2E-27, SFP heat exchanger, available and in service All RCS Thot indicators are in service 2P-89C, HPSI pump, aligned to Red train and protected as the RCS make up source 2P-89A, HPSI pump, is available but in Pull-to-Lock 2P-89B, HPSI pump, is tagged out for maintenance Charging pump heaters are removed for the RCS dilution tagout

  1. 1 EDG and AAC diesel are available SU#3 transformer is in service, SU#2 transformer is tagged out for maintenance Loop 1 SW is operable with 2P-4A supplying the loop Loop 2 SW is out of service with 2P-4B and 2P-4C tagged for bay inspection 2P-66, Spent Fuel Pool Purification pump, is available with sufficient RWT inventory 2P-109A and 2P-109B, Reactor make up water pumps, are both available for makeup from the RMWT Both 2P-35A and 2P-35B, Containment Spray pumps, are tagged out for maintenance

ANO-2-JPM-NRC-ADMIN-SOPP1 (A6) PAGE 6 OF 9 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERS COPY INITIATING CUE #1:

CRS/SM directs you to determine Shutdown Operations Protection Plan (SOPP) condition for the current plant alignment IAW OP 1015.048, Shutdown Operations Protection Plan.

Inform examiner of current condition after you have determined the condition.

Current SOPP condition: _______3__________ (inform examiner when condition identified)

INITIATING CUE #2:

CRS/SM directs you to determine if requirements are met for determined condition using OP 1015.048, Shutdown Operations Protection Plan.

ANO-2-JPM-NRC-ADMIN-SOPP1 (A6) PAGE 7 OF 9 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEES COPY INITIAL CONDITIONS:

Plant is in Mode 6, RCS temperature is 90 0F.

Fuel Transfer Canal level is 401 6 and connected to the SFP RCS boron is 2701 ppm Both Start Up Channels and Boron Dilution Monitors are operable RCS dilution tagout is in place Time to Boil is 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> Containment equipment hatch is open and personnel hatch door interlock has been defeated. Both are capable of being closed within 30 min. Escape hatch is closed.

OPS-B33 CNTMT Closure Log and OPS-B40 SDC Log/Task Checklist are being maintained by CRS Admin.

Red train is protected IAW OP 1015.008, Unit 2 SDC Control and OP 1015.008 Att. J, Protected Train and Operations Controlled Areas, is complete for the Red train.

Plant safety index is Yellow.

ANO switchyard gate and London Line substation gates are posted with a sign that reads ATTENTION LOSS OF POWER COULD PLACE UNIT 2 AT RISK.

Core offload is currently in progress.

The following is the plant equipment alignment:

2P-60A, LPSI pump, running and SDC train A operable 2P-60B, LPSI pump, running 2P-40A, SFP cooling pump, in service 2P-40B, SFP cooling pump, available 2E-27, SFP heat exchanger, available and in service All RCS Thot indicators are in service 2P-89C, HPSI pump, aligned to Red train and protected as the RCS make up source 2P-89A, HPSI pump, is available but in Pull-to-Lock 2P-89B, HPSI pump, is tagged out for maintenance Charging pump heaters are removed for the RCS dilution tagout

  1. 1 EDG and AAC diesel are available SU#3 transformer is in service, SU#2 transformer is tagged out for maintenance Loop 1 SW is operable with 2P-4A supplying the loop Loop 2 SW is out of service with 2P-4B and 2P-4C tagged for bay inspection 2P-66, Spent Fuel Pool Purification pump, is available with sufficient RWT inventory 2P-109A and 2P-109B, Reactor make up water pumps, are both available for makeup from the RMWT Both 2P-35A and 2P-35B, Containment Spray pumps, are tagged out for maintenance

ANO-2-JPM-NRC-ADMIN-SOPP1 (A6) PAGE 8 OF 9 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEES COPY INITIATING CUE #1:

CRS/SM directs you to determine Shutdown Operations Protection Plan (SOPP) condition for the current plant alignment IAW OP 1015.048, Shutdown Operations Protection Plan.

Inform examiner of current condition after you have determined the condition.

Current SOPP condition: _________________ (inform examiner when condition identified)

ANO-2-JPM-NRC-ADMIN-SOPP1 (A6) PAGE 9 OF 9 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE #2:

CRS/SM directs you to determine if requirements are met for the condition identified using OP 1015.048, Shutdown Operations Protection Plan.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

PAGE: 54 of 76 1015.048 SHUTDOWN OPERATIONS PROTECTION PLAN CHANGE: 016 ATTACHMENT I Page 1 of 4 SOPP FOR UNIT 2 SHUTDOWN CONDITION 3 1.0 INITIAL CONDITIONS 1.1 FTC flooded > 23 above core 1.2 Fuel in Reactor Vessel 1.3 REFUELING operations in progress 2.0 REQUIREMENTS 2.1 Decay Heat Removal Equipment 2.1.1 One SDC Train shall be OPERABLE (Circle OPERABLE Train):

A SDC Train with 2P-60A B SDC Train with 2P-60B A SDC Train with 2P-35A B SDC Train with 2P-35B NOTE An SFP Cooling Train consists of a pump (2P-40A OR B),the SFP HX (2E-27A),

and EITHER of the following:

One loop of Service Water with 2 Service Water pumps.

Two Service Water loops with at least one pump for each loop.

2.1.2 Both SFP Cooling Trains shall be AVAILABLE per TRM 3.9.3.

A. 2P-40A SFP Cooling Train B. 2P-40B SFP Cooling Train

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

PAGE: 55 of 76 1015.048 SHUTDOWN OPERATIONS PROTECTION PLAN CHANGE: 016 ATTACHMENT I Page 2 of 4 NOTE Spray pumps (2P-35A/B) may only be considered as inventory makeup train if RV head is removed and pump is NOT being used for Shutdown Cooling.

2.2 Inventory Control Makeup Flow Paths 2.2.1 One OPERABLE RCS makeup flow path (Circle OPERABLE flow paths):

2P-89A 2P-89B 2P-89C (RED) 2P-89C (GREEN) 2P-35A 2P-35B Charging 2.2.2 Two AVAILABLE SFP makeup sources (Circle AVAILABLE sources): (IER L1-11-2 Rec 1)

RWT via 2P-66 RMWT via 2P-109A RMWT via 2P-109B Loop 1 SW Loop 2 SW 2T-12 2.3 Electrical Power Distribution 2.3.1 At least three electrical power sources AVAILABLE (Circle those AVAILABLE):

2EDG1 2EDG2 AACG SU3 SU2 UAT 2.3.2 Of the AVAILABLE sources, at least one DG OPERABLE (circle those OPERABLE):

2EDG1 2EDG2 AACG 2.3.3 Of the AVAILABLE sources, at least one offsite power source OPERABLE (circle those OPERABLE):

SU3 SU2 UAT

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

PAGE: 56 of 76 1015.048 SHUTDOWN OPERATIONS PROTECTION PLAN CHANGE: 016 ATTACHMENT I Page 3 of 4 2.4 Reactivity control requirements:

2.4.1 Two source range Nuclear Instruments shall be OPERABLE.

2.4.2 RCS boron concentration greater than TS 3.9.1 requirements.

2.4.3 Reactor Coolant System dilution flow paths administratively controlled (e.g. caution tags, danger tags, locks, etc.).

A. Implement dilution flow path controls until entering Mode 5 with all reactor vessel head closure bolts fully tensioned.

2.5 Containment requirements 2.5.1 At least one door on the containment personnel hatch and the emergency hatch shall be capable of being closed.

2.5.2 CNTMT closure has been established within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to CORE ALTERATIONS by OPS-B33 and documented on SDC Log/Task Checklist, OPS-B40. (TS 3.9.4)

{4.3.1} 2.5.3 The containment equipment hatch shall not be opened unless it can be closed within thirty minutes or the estimated time to boil, whichever is least.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

PAGE: 57 of 76 1015.048 SHUTDOWN OPERATIONS PROTECTION PLAN CHANGE: 016 ATTACHMENT I Page 4 of 4 3.0 MISCELLANEOUS 3.1 PROTECTED TRAIN signs and barriers (ropes, flagging, etc.) installed per Operations Protected Train Attachment J of Unit 2 SDC Control (1015.008).

3.2 WHEN KEY SAFETY FUNCTION defense in depth is reduced by ANY of the inoperable train/components listed below [SOER 09-01 Rec 2],

Inoperable Decay Heat Removal Train Inoperable offsite power source Inoperable Diesel Generator Plant Safety Index is Orange (High Risk)

THEN ensure Switchyard Access Controls are in place by performing the following:

3.2.1 Use sign headed "ATTENTION LOSS OF POWER COULD PLACE UNIT 2 AT RISK".

3.2.2 Install sign ON GATE LOCK at the following locations:

Switchyard Main Entrance Gate London Line Substation Yard Gate 3.3 Two RCS hot leg temperature indications AVAILABLE.

Performed By: Date: Time:

Send Copy of this checklist to Shift Outage Manager if the OCC is manned.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

PAGE: 54 of 76 1015.048 SHUTDOWN OPERATIONS PROTECTION PLAN CHANGE: 016 ATTACHMENT I Key Page 1 of 4 SOPP FOR UNIT 2 SHUTDOWN CONDITION 3 1.0 INITIAL CONDITIONS 1.1 FTC flooded > 23 above core 1.2 Fuel in Reactor Vessel 1.3 REFUELING operations in progress 2.0 REQUIREMENTS 2.1 Decay Heat Removal Equipment 2.1.1 One SDC Train shall be OPERABLE (Circle OPERABLE Train):

A SDC Train with 2P-60A B SDC Train with 2P-60B A SDC Train with 2P-35A B SDC Train with 2P-35B NOTE An SFP Cooling Train consists of a pump (2P-40A OR B),the SFP HX (2E-27A),

and EITHER of the following:

One loop of Service Water with 2 Service Water pumps.

Two Service Water loops with at least one pump for each loop.

2.1.2 Both SFP Cooling Trains shall be AVAILABLE per TRM 3.9.3.

A. 2P-40A SFP Cooling Train B. 2P-40B SFP Cooling Train No due to SW pumps

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

PAGE: 55 of 76 1015.048 SHUTDOWN OPERATIONS PROTECTION PLAN CHANGE: 016 ATTACHMENT I Page 2 of 4 NOTE Spray pumps (2P-35A/B) may only be considered as inventory makeup train if RV head is removed and pump is NOT being used for Shutdown Cooling.

2.2 Inventory Control Makeup Flow Paths 2.2.1 One OPERABLE RCS makeup flow path (Circle OPERABLE flow paths):

2P-89A 2P-89B 2P-89C (RED) 2P-89C (GREEN) 2P-35A 2P-35B Charging 2.2.2 Two AVAILABLE SFP makeup sources (Circle AVAILABLE sources): (IER L1-11-2 Rec 1)

RWT via 2P-66 RMWT via 2P-109A RMWT via 2P-109B Loop 1 SW Loop 2 SW 2T-12 2.3 Electrical Power Distribution 2.3.1 At least three electrical power sources AVAILABLE (Circle those AVAILABLE):

2EDG1 2EDG2 AACG SU3 SU2 UAT 2.3.2 Of the AVAILABLE sources, at least one DG OPERABLE (circle those OPERABLE):

2EDG1 2EDG2 AACG 2.3.3 Of the AVAILABLE sources, at least one offsite power source OPERABLE (circle those OPERABLE):

SU3 SU2 UAT

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

PAGE: 56 of 76 1015.048 SHUTDOWN OPERATIONS PROTECTION PLAN CHANGE: 016 ATTACHMENT I Page 3 of 4 2.4 Reactivity control requirements:

2.4.1 Two source range Nuclear Instruments shall be OPERABLE.

2.4.2 RCS boron concentration greater than TS 3.9.1 requirements.

2.4.3 Reactor Coolant System dilution flow paths administratively controlled (e.g. caution tags, danger tags, locks, etc.).

A. Implement dilution flow path controls until entering Mode 5 with all reactor vessel head closure bolts fully tensioned.

2.5 Containment requirements 2.5.1 At least one door on the containment personnel hatch and the emergency hatch shall be capable of being closed.

2.5.2 CNTMT closure has been established within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to CORE ALTERATIONS by OPS-B33 and documented on SDC Log/Task Checklist, OPS-B40. (TS 3.9.4)

{4.3.1} 2.5.3 The containment equipment hatch shall not be opened unless it can be closed within thirty minutes or the estimated time to boil, whichever is least.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

PAGE: 57 of 76 1015.048 SHUTDOWN OPERATIONS PROTECTION PLAN CHANGE: 016 ATTACHMENT I Page 4 of 4 3.0 MISCELLANEOUS 3.1 PROTECTED TRAIN signs and barriers (ropes, flagging, etc.) installed per Operations Protected Train Attachment J of Unit 2 SDC Control (1015.008).

3.2 WHEN KEY SAFETY FUNCTION defense in depth is reduced by ANY of the inoperable train/components listed below [SOER 09-01 Rec 2],

Inoperable Decay Heat Removal Train Inoperable offsite power source Inoperable Diesel Generator Plant Safety Index is Orange (High Risk)

THEN ensure Switchyard Access Controls are in place by performing the following:

3.2.1 Use sign headed "ATTENTION LOSS OF POWER COULD PLACE UNIT 2 AT RISK".

3.2.2 Install sign ON GATE LOCK at the following locations:

Switchyard Main Entrance Gate London Line Substation Yard Gate 3.3 Two RCS hot leg temperature indications AVAILABLE.

Performed By: Date: Time:

Send Copy of this checklist to Shift Outage Manager if the OCC is manned.

A2-JPM-SRO-ADMIN MSSVINOP (A7) Page 1 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 002 DATE:

SYSTEM/DUTY AREA: Equipment Control TASK: Verify RPS trip set point determination for inoperable MSSV JTA#: ANO-SRO-ADMIN-NORM-231 KA VALUE RO: 3.4 SRO: 4.7 KA

REFERENCE:

2.2.40 APPROVED FOR ADMINISTRATION TO: RO: SRO: X TASK LOCATION: INSIDE CR: OUTSIDE CR: BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform CLASSROOM: Perform POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: CLASSROOM:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 15 Minutes REFERENCE(S): Unit 2 Tech Specs EXAMINEE'S NAME: Badge #:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Time Stop Time Total Time

A2-JPM-SRO-ADMIN MSSVINOP (A7) Page 2 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

The plant is at 90% power, 440 EFPD, Steady State.

MSSV testing is in progress.

The following are the MSSV as found lift pressure reported by maintenance:

MSSV As found lift pressure MSSV As found lift pressure 2PSV-1002 1068 psig 2PSV-1052 1086 psig 2PSV-1003 1070 psig 2PSV-1053 1092 psig 2PSV-1004 1111 psig 2PSV-1054 1106 psig 2PSV-1005 1135 psig 2PSV-1055 1121 psig 2PSV-1006 1108 psig 2PSV-1056 1097 psig TASK STANDARD:

Determined that 2PSV-1003 and 2PSV-1056 are inoperable (1 MSSV per header) and determined the maximum High Linear Power Level and RPS trip set point to be 87.0% to comply with Technical Specification 3.7.1.1.

TASK PERFORMANCE AIDS: Unit 2 Tech Specs

A2-JPM-SRO-ADMIN MSSVINOP (A7) Page 3 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE #1 :

Determine operability of the MSSVs IAW with Tech Specs.

INITIATING CUE #2 :

Determine the Maximum High Linear Power Level and RPS Trip Set point per Tech Specs allowed for this condition to remain at power.

Reactor Engineering reports MTC for 440 EFPD is -2.6E-4 k/k/°F.

Start Time:_________________

PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 1. Using Tech Spec 3.7.1.1 Examinee derived that one MSSV N/A SAT UNSAT Table 3.7-5 determines on each header is inoperable.

operability of MSSVs. (2PSV-1003 and 2PSV-1056)

2. Using Tech Spec 3.7.1.1 Examinee derived from table N/A SAT UNSAT Table 3.7-1 determines new based on 1 MSSV inoperable on maximum power and RPS each header, the maximum linear power trip set point. allowable linear power level and RPS trip setpoint to be 71%.

(C) . Using Tech Spec 3.7.1.1 Examinee derived from graph N/A SAT UNSAT figure 3.7-1 determines new based on MTC of -2.6E-4 k/k/°F maximum power and RPS and knowing that one MSSV is linear power trip set point. inoperable on each header determined that maximum power and RPS linear power trip set point should be 87.0%.

END

A2-JPM-SRO-ADMIN MSSVINOP (A7) Page 4 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERS COPY INITIAL CONDITIONS:

The plant is at 90% power, 440 EFPD, Steady State.

MSSV testing is in progress.

The following are the MSSV as found lift pressure reported by maintenance:

MSSV As found lift pressure MSSV As found lift pressure 2PSV-1002 1068 psig 2PSV-1052 1086 psig 2PSV-1003 1070 psig 2PSV-1053 1092 psig 2PSV-1004 1111 psig 2PSV-1054 1106 psig 2PSV-1005 1135 psig 2PSV-1055 1121 psig 2PSV-1006 1108 psig 2PSV-1056 1097 psig INITIATING CUE #1:

Determine operability of the MSSVs IAW with Tech Specs. 2PSV-1003 and 2PSV-1056 are inoperable.

INITIAL CONDITIONS: (same as previous initial conditions)

The plant is at 90% power, 440 EFPD, Steady State.

MSSV testing is in progress.

The following are the MSSV as found lift pressure reported by maintenance:

MSSV As found lift pressure MSSV As found lift pressure 2PSV-1002 1068 psig 2PSV-1052 1086 psig 2PSV-1003 1070 psig 2PSV-1053 1092 psig 2PSV-1004 1111 psig 2PSV-1054 1106 psig 2PSV-1005 1135 psig 2PSV-1055 1121 psig 2PSV-1006 1108 psig 2PSV-1056 1097 psig INITIATING CUE #2:

Determine the Maximum High Linear Power Level and RPS Trip Set point per Tech Specs allowed for this condition to remain at power.

Reactor Engineering reports MTC for 440 EFPD is -2.6E-4 k/k/°F.

Maximum Power Level is 87% per Tech Spec figure 3.7-1

A2-JPM-SRO-ADMIN MSSVINOP (A7) Page 5 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEES COPY INITIAL CONDITIONS:

The plant is at 90% power, 440 EFPD, Steady State.

MSSV testing is in progress.

The following are the MSSV as found lift pressure reported by maintenance:

MSSV As found lift pressure MSSV As found lift pressure 2PSV-1002 1068 psig 2PSV-1052 1086 psig 2PSV-1003 1070 psig 2PSV-1053 1092 psig 2PSV-1004 1111 psig 2PSV-1054 1106 psig 2PSV-1005 1135 psig 2PSV-1055 1121 psig 2PSV-1006 1108 psig 2PSV-1056 1097 psig INITIATING CUE #1:

Determine operability of the MSSVs IAW with Tech Specs.

A2-JPM-SRO-ADMIN MSSVINOP (A7) Page 6 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIAL CONDITIONS: (same as previous initial conditions)

The plant is at 90% power, 440 EFPD, Steady State.

MSSV testing is in progress.

The following are the MSSV as found lift pressure reported by maintenance:

MSSV As found lift pressure MSSV As found lift pressure 2PSV-1002 1068 psig 2PSV-1052 1086 psig 2PSV-1003 1070 psig 2PSV-1053 1092 psig 2PSV-1004 1111 psig 2PSV-1054 1106 psig 2PSV-1005 1135 psig 2PSV-1055 1121 psig 2PSV-1006 1108 psig 2PSV-1056 1097 psig INITIATING CUE #2:

Determine the Maximum High Linear Power Level and RPS Trip Set point per Tech Specs allowed for this condition to remain at power.

Reactor Engineering reports MTC for 440 EFPD is -2.6E-4 k/k/°F.

A2-JPM-SRO-ADMIN MSSVINOP Page 1 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 001 DATE:

SYSTEM/DUTY AREA: Equipment Control TASK: Verify RPS trip set point determination for inoperable MSSV JTA#: ANO-SRO-ADMIN-NORM-231 KA VALUE RO: 3.4 SRO: 4.7 KA

REFERENCE:

2.2.40 APPROVED FOR ADMINISTRATION TO: RO: SRO: X TASK LOCATION: INSIDE CR: OUTSIDE CR: BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform CLASSROOM: Perform POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: CLASSROOM:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 15 Minutes REFERENCE(S): Unit 2 Tech Spec 3.7.1.1 EXAMINEE'S NAME: Badge #:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Time Stop Time Total Time SIGNED: DATE:

SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

A2-JPM-SRO-ADMIN MSSVINOP Page 2 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

The plant is at 90% power, 440 EFPD, Steady State.

MSSV testing is in progress.

One MSSV, 2PSV-1054 has been declared inoperable.

The value for MTC provide by Reactor Engineering for 440 EFPD is -2.6 k/k/°F.

TASK STANDARD: Determine the maximum High Linear Power Level and RPS trip set point to be 91.0% to comply with Technical Specification 3.7.1.1.

TASK PERFORMANCE AIDS: Unit 2 Tech Specs

A2-JPM-SRO-ADMIN MSSVINOP Page 3 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:

Determine the Maximum High Linear Power Level and RPS Trip Set point per Tech Specs allowed for this condition to remain at power.

PERFORMANCE CHECKLIST STANDARD (Circle One)

N/A SAT UNSAT

1. Using Tech Spec 3.7.1 Table Examinee correctly derived 3.7-1 determines new from table based on 1 MSSV maximum power and RPS inoperable, the maximum linear power trip set point to allowable linear power level be 79%. and RPS trip setpoint to be 79%.

N/A SAT UNSAT (C) 2. Using Tech Spec 3.7.1 figure Examinee correctly derived 3.7-1 determines new from graph based on MTC of maximum power and RPS -2.6 k/k/°F and knowing that linear power trip set point to one MSSV is inoperable be 91%. determined that maximum power and RPS linear power trip set point should be 91.0%.

EXAMINER's NOTE: Examinee should discuss the Tech Spec applicability at this point stating that Tech Spec 3.7.1.1 LCO to allow power operations to continue provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> power is reduced to the maximum power of 79% or as allowed by figure 3.7-1 (91%) and within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, the RPS trip set point adjusted to be less than the value of 79% or as allowed in figure 3.7-1 (91%).

END

A2-JPM-SRO-ADMIN MSSVINOP Page 4 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERS COPY JPM INITIAL TASK CONDITIONS:

The plant is at 90% power, 440 EFPD, Steady State.

MSSV testing is in progress.

One MSSV, 2PSV-1054 has been declared inoperable.

The value for MTC provided by Reactor Engineering for 440 EFPD is -2.6 k/k/°F.

INITIATING CUE:

Determine the Maximum High Linear Power Level and RPS Trip Set point per Tech Specs allowed for this condition to remain at power.

A2-JPM-SRO-ADMIN MSSVINOP Page 5 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

The plant is at 90% power, 440 EFPD, Steady State.

MSSV testing is in progress.

One MSSV, 2PSV-1054 has been declared inoperable.

The value for MTC provided by Reactor Engineering for 440 EFPD is -2.6 k/k/°F.

INITIATING CUE:

Determine the Maximum High Linear Power Level and RPS Trip Set point per Tech Specs allowed for this condition to remain at power.

ANO-2JPM-NRC-ADMIN-EMGRESPSRO (A8) PAGE 1 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 000 DATE:

SYSTEM/DUTY AREA: Radiation Control TASK: Calculated expected dose for Re-entry during an emergency and determine if entry is allowed LP#: ASLP-RO-RADP KA VALUE RO: 3.2 SRO: 3.7 KA

REFERENCE:

2.3.4 APPROVED FOR ADMINISTRATION TO: RO: SRO: X TASK LOCATION: INSIDE CR: OUTSIDE CR: BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Classroom: Perform POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: Classroom:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 20 Minutes REFERENCE(S): 1903.033 and 1903.033A form EXAMINEE'S NAME: BADGE#:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Stop Total Time Time Time

ANO-2JPM-NRC-ADMIN-EMGRESPSRO (A8) PAGE 2 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall ensure that the examinee has been briefed on NUREG 1021 Appendix E.

JPM INITIAL TASK CONDITIONS:

The plant is tripped from 100% power.

300 gpm LOCA in progress.

Loss of Offsite power is in progress.

LOCA EOP is being implemented.

RDACS indicates an off site release in progress.

A Site Area Emergency has been declared based on the RDACS dose rate.

RDACS dose rates are continuing to rise and the trend indicates they will exceed GE criteria if the release is not terminated.

Whole body dose rates in area of work are 7.3 Rem/hr.

RP estimates that it will take approximately 75 minutes to complete emergency actions and stop the release.

Joe Mechanic and Ralph RP have been selected to make the entry to stop the release but have not volunteered.

Joe Mechanic and Ralph RP have been briefed on the task and entry requirements.

Ed Engineer the Emergency Director has authorized 10CFR20 limits can be exceeded.

Joe Mechanics ERIMS dose to date is 382 mR and has badge number 20031.

Ralph RPs ERIMS dose to date 1353 mR and has badge number 20005.

TASK STANDARD:

Determine that 10CFR20 limits can be exceeded for protection of Large populations by calculating Joe Mechanics and Ralph RPs dose and complete 1903.033A form for entry.

TASK PERFORMANCE AIDS:

1903.033 Protective Action Guidelines for Recue/Repair and Damage Control Teams.

SIMULATOR SETUP:

NA EXAMINER'S NOTES:

ANO-2JPM-NRC-ADMIN-EMGRESPSRO (A8) PAGE 3 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:

The SM directs, use 1903.033 Protective Action Guidelines for Rescue/Repair and Damage control Teams determine Joe Mechanic and Ralph RPs estimated year to date total dose for repair and determine if entry is allowed.

If entry is allowed, then complete 1903.033A Authorization form for increasing exposure above 10CFR20 limits.

PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 1. Calculate Joe Mechanics Calculated Joe Mechanics N/A SAT UNSAT estimated dose estimated dose to in the following range:

9082 to 9882 mR (C) 2. Calculate Ralph RPs Calculated Ralph RPs N/A SAT UNSAT estimated dose estimated dose to in the following range:

10053 to 10853 mR (C) 3. Determine if Joe Mechanics is Determined that Joe Mechanic N/A SAT UNSAT allowed to make the entry to is allowed to make the entry for stop the release. protection of Large populations.

(C) 4. Determine if Ralph RPs is Determined that Ralph RP is N/A SAT UNSAT allowed to make the entry to allowed to make the entry for stop the release. protection of Large populations.

(C) 5. Complete 1903.033A Completed section 1 of N/A SAT UNSAT 1903.033A, selected box 2 for protection of large populations (dose < 25 Rem)

Completed section 2 of 1903.033A included Joe Mechanic and Ralph RP as exceeding 10CFR20 dose limits.

Examiner Note: If the applicant fills out the 1903.033A but does not sign the form for the TSC director or for the briefing being complete this is still considered they completed the task correctly.

END

ANO-2JPM-NRC-ADMIN-EMGRESPSRO (A8) PAGE 4 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERS COPY JPM INITIAL TASK CONDITIONS:

Given the following Plant conditions:

The plant is tripped from 100% power.

300 gpm LOCA in progress.

Loss of Offsite power is in progress.

LOCA EOP is being implemented.

RDACS indicates an off site release in progress.

A Site Area Emergency has been declared based on the RDACS dose rate.

RDACS dose rates are continuing to rise and the trend indicates they will exceed GE criteria if the release is not terminated.

Whole body dose rates in area of work are 7.3 Rem/hr.

RP estimates that it will take approximately 75 minutes to complete emergency actions and stop the release.

Joe Mechanic and Ralph RP have been selected to make the entry to stop the release but have not volunteered.

Joe Mechanic and Ralph RP have been briefed on the task and entry requirements.

Ed Engineer the Emergency Director has authorized 10CFR20 limits can be exceeded.

Joe Mechanics ERIMS dose to date is 382 mR and has badge number 20031.

Ralph RPs ERIMS dose to date 1353 mR and has badge number 20005.

INITIATING CUE:

The SM directs, use 1903.033 Protective Action Guidelines for Rescue/Repair and Damage control Teams determine Joe Mechanic and Ralph RPs estimated year to date total dose for repair and determine if entry is allowed.

If entry is allowed, then complete 1903.033A Authorization form for increasing exposure above 10CFR20 limits.

Joe Mechanics estimated TEDE dose: _______________________ mR Ralph RPs estimated TEDE dose: _______________________ mR Can Joe Mechanic perform re-entry and complete the task? YES / NO Can Ralph RP perform re-entry and complete the task? YES / NO

ANO-2JPM-NRC-ADMIN-EMGRESPSRO (A8) PAGE 5 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

Given the following Plant conditions:

The plant is tripped from 100% power.

300 gpm LOCA in progress.

Loss of Offsite power is in progress.

LOCA EOP is being implemented.

RDACS indicates an off site release in progress.

A Site Area Emergency has been declared based on the RDACS dose rate.

RDACS dose rates are continuing to rise and the trend indicates they will exceed GE criteria if the release is not terminated.

Whole body dose rates in area of work are 7.3 Rem/hr.

RP estimates that it will take approximately 75 minutes to complete emergency actions and stop the release.

Joe Mechanic and Ralph RP have been selected to make the entry to stop the release but have not volunteered.

Joe Mechanic and Ralph RP have been briefed on the task and entry requirements.

Ed Engineer the Emergency Director has authorized 10CFR20 limits can be exceeded.

Joe Mechanics ERIMS dose to date is 382 mR and has badge number 20031.

Ralph RPs ERIMS dose to date 1353 mR and has badge number 20005.

INITIATING CUE:

The SM directs, use 1903.033 Protective Action Guidelines for Rescue/Repair and Damage control Teams determine Joe Mechanic and Ralph RPs estimated year to date total dose for repair and determine if entry is allowed.

If entry is allowed, then complete 1903.033A Authorization form for increasing exposure above 10CFR20 limits.

Joe Mechanics estimated TEDE dose: _______________________ mR Ralph RPs estimated TEDE dose: _______________________ mR Can Joe Mechanic perform re-entry and complete the task? YES / NO Can Ralph RP perform re-entry and complete the task? YES / NO

Page 11 of 15 I. A Rescue/Repair and Damage Control Team has been formed. A reentry must be made for: (check one)

1. Protecting valuable property (lower dose not practicable). Planned dose shall not exceed 10 Rem TEDE.
2. Lifesaving or protection of large populations (lower dose not practicable). Planned dose shall not exceed 25 Rem TEDE.
3. >25 Rem TEDE:
a. Lifesaving or protection of large populations.
b. Only on a voluntary basis to persons fully aware of the risks involved.

II. The individuals listed below have been briefed on the requirements of the task and the guidelines in section 6.1.3. They have been authorized to exceed the dose limits of 10CFR20 if necessary to accomplish this task within the guidelines listed in Section 6.1.3.

NAME (PRINTED) SIGNATURE BADGE NUMBER III. AUTHORIZATION Print & Sign SM/EPM/ED _________________________/_________________________ _______________

(signed) (date)

May be given verbally via telephone, radio, or other means.

Signifies person has been briefed concerning guidelines for exceeding 10CFR20 dose limits (1903.033A).

cc: Personnel File Personal Dosimetry Record FORM TITLE: FORM NO. REV.

AUTHORIZATION FORM FOR INCREASING EXPOSURES ABOVE 10CFR20 LIMITS 1903.033A 023

Page 11 of 15 I. A Rescue/Repair and Damage Control Team has been formed. A reentry must be made for: (check one)

1. Protecting valuable property (lower dose not practicable). Planned dose shall not exceed 10 Rem TEDE.
2. Lifesaving or protection of large populations (lower dose not practicable). Planned dose shall not exceed 25 Rem TEDE.
3. >25 Rem TEDE:
a. Lifesaving or protection of large populations.
b. Only on a voluntary basis to persons fully aware of the risks involved.

II. The individuals listed below have been briefed on the requirements of the task and the guidelines in section 6.1.3. They have been authorized to exceed the dose limits of 10CFR20 if necessary to accomplish this task within the guidelines listed in Section 6.1.3.

NAME (PRINTED) SIGNATURE BADGE NUMBER Joe Mechanic Signed Here 20031 Ralph RP Signed Here 20005 III. AUTHORIZATION Print & Sign Signed Here Per Ed Engineer Telecon SM/EPM/ED _________________________/_________________________ _______________

(signed) (date)

May be given verbally via telephone, radio, or other means.

Signifies person has been briefed concerning guidelines for exceeding 10CFR20 dose limits (1903.033A).

cc: Personnel File Personal Dosimetry Record FORM TITLE: FORM NO. REV.

AUTHORIZATION FORM FOR INCREASING EXPOSURES ABOVE 10CFR20 LIMITS 1903.033A 023

ANO-2-JPM-NRC-ADMIN-PAR2 (A9) PAGE 1 OF 6 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 004 DATE:

SYSTEM/DUTY AREA: Emergency Plan TASK: Determine protective action recommendations JTA#: ANO-SRO-EPLAN-EMERG-301 Alternate Path Yes: No: X Time Critical Yes: X No:

KA VALUE RO: 2.4 SRO: 4.4 KA

REFERENCE:

2.1.44 APPROVED FOR ADMINISTRATION TO: RO: SRO: X TASK LOCATION: INSIDE CR: OUTSIDE CR: BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Classroom: Perform POSITION EVALUATED: RO: SRO: X ACTUAL TESTING SIMULATOR: PLANT Classroom:

ENVIRONMENT: SITE:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 15 Minutes REFERENCE(S): Emergency Response/Notification; Attachment 6, Protective Action recommendations for General Emergency.

EXAMINEE'S NAME: Badge #:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Time Stop Time Total Time

ANO-2-JPM-NRC-ADMIN-PAR2 (A9) PAGE 2 OF 6 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

Unit 2 has experienced a 500 gpm LOCA.

The site has just upgraded from SAE to a General Emergency due to FG-1 (Loss of ANY two barriers AND loss of potential loss of third barrier).

Containment barrier is considered lost.

Containment High Range radiation monitors are reading 2200 Rem/hr.

A release is in progress with EPA Protective Action Guidelines are projected to be 1500 mRem TEDE and 3000 mRem Child Thyroid outside of the site boundary and less than 2 miles from site.

RDACS projects EPA Protective Action Guidelines to NOT be exceeded in any zones outside of 2 miles.

Wind direction is from 252°.

TASK STANDARD:

A PAR 7 was declared.

Recommended evacuating to a 2 mile radius and 2-5 miles downwind. (Zones G, H,and K).

Recommended sheltering 5-10 miles downwind. (Zones I, J, L, and M)

Recommend zones N, O, P, Q, R, S, T, and U to go indoors and listen to the emergency for this event.

Completed within 15 of notifying the examiner of being ready to start.

TASK PERFORMANCE AIDS:

OP-1903.011 Emergency Response/Notification; Attachment 6, Protective Action recommendations for General Emergency.

EXAMINER NOTES:

This is a time critical JPM IAW 1903.011, Emergency Response/Notification, Attachment 6.

ANO-2-JPM-NRC-ADMIN-PAR2 (A9) PAGE 3 OF 6 JOB PERFORMANCE MEASURE INITIATING CUE:

Using 1903.011 Attachment 6, perform the following:

1. Determine the appropriate PAR for the given conditions.
2. Determine the zones to be recommended for evacuation/sheltering to the State Health Department for the given conditions.
3. Determine the zones to be recommended to go indoors to the State Health Department for the given conditions.

START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

Examiner Note:

The following steps are from the OP1903.011 Attachment 6 PAR flow chart page 1.

(C) 1. Will this be the first PAR for Examinee determined that this N/A SAT UNSAT (Flow the event? is the first PAR due to the GE chart just being declared and page answered YES.

1)

(C) 2. Is there a LOSS of the Examinee answered YES that N/A SAT UNSAT (Flow containment fission product the containment barrier is lost chart barrier in accordance with from the initial conditions.

page procedure 1903.010?

1)

(C) 3. Is Containment High Range Examinee answered NO that the N/A SAT UNSAT (Flow Rad Monitor reading > 4000 containment barrier is lost from chart R/hr. the initial conditions.

page 1)

(C) 4. Radiological release with site Examinee answered YES that N/A SAT UNSAT (Flow boundary dose > 1,000 mr there is a release with site chart TEDE or 5,000 mr CDE boundary dose greater than page Thyroid is expected in <= 1hr? 1000 mr TEDE or 5,000 mr CDE

1) Thyroid.

And determined PAR 7 is applicable.

(C) 5. Recommend evacuation of 2 Using 1903.011 Attachment 6, N/A SAT UNSAT mile radius and 2-5 miles examinee recommended (PAR 7, step downwind. Recommend Evacuating Zones G, H, and K.

2.) shelter for 5 -10 miles downwind. Recommend that AND the remainder of the EPZ go indoors. Sheltering Zones I,J,L, and M.

AND Zones to go indoors are the following: N,O,P,Q,R,S,T, and U (C) 6. JPM complete in 15 minutes. JPM completed by examinee in N/A SAT UNSAT 15 minutes with 5 minutes to read conditions.

END

ANO-2-JPM-NRC-ADMIN-PAR2 (A9) PAGE 4 OF 6 JOB PERFORMANCE MEASURE STOP TIME:

ANO-2-JPM-NRC-ADMIN-PAR2 (A9) PAGE 5 OF 6 JOB PERFORMANCE MEASURE EXAMINER'S COPY This is a time critical JPM INITIAL CONDITIONS:

Unit 2 has experienced a 500 gpm LOCA.

The site has just upgraded from SAE to a General Emergency due to FG-1 (Loss of ANY two barriers AND loss of potential loss of third barrier).

Containment barrier is considered lost.

Containment High Range radiation monitors are reading 2200 Rem/hr.

A release is in progress with EPA Protective Action Guidelines are projected to be 1500 mRem TEDE and 3000 mRem Child Thyroid outside of the site boundary and less than 2 miles from site.

RDACS projects EPA Protective Action Guidelines to NOT be exceeded in any zones outside of 2 miles.

Wind direction is from 252°.

INITIATING CUE:

Using 1903.011 Attachment 6, perform the following:

1. Determine the appropriate PAR for the given conditions.
2. Determine the zones to be recommended for evacuation/sheltering to the State Health Department for the given conditions.
3. Determine the zones to be recommended to go indoors to the State Health Department for the given conditions.

Write Answer below:

1) PAR(s) declared Par 7
2. Zones to be Evacuate Zones G, H, and K evacuated or sheltered (specify) Shelter Zones I, J, L, and M
3) Zones to go indoors Zones N,O,P,Q,R,S,T, and U

ANO-2-JPM-NRC-ADMIN-PAR2 (A9) PAGE 6 OF 6 JOB PERFORMANCE MEASURE EXAMINEE'S COPY This is a time critical JPM INITIAL CONDITIONS:

Unit 2 has experienced a 500 gpm LOCA.

The site has just upgraded from SAE to a General Emergency due to FG-1 (Loss of ANY two barriers AND loss of potential loss of third barrier).

Containment barrier is considered lost.

Containment High Range radiation monitors are reading 2200 Rem/hr.

A release is in progress with EPA Protective Action Guidelines are projected to be 1500 mRem TEDE and 3000 mRem Child Thyroid outside of the site boundary and less than 2 miles from site.

RDACS projects EPA Protective Action Guidelines to NOT be exceeded in any zones outside of 2 miles.

Wind direction is from 252°.

INITIATING CUE:

Using 1903.011 Attachment 6, perform the following:

1. Determine the appropriate PAR for the given conditions.
2. Determine the zones to be recommended for evacuation/sheltering to the State Health Department for the given conditions.
3. Determine the zones to be recommended to go indoors to the State Health Department for the given conditions.

Write Answer below:

1) PAR(s) declared
2) Zones to be evacuated or sheltered (specify)
3) Zones to go indoors

NOTE IF Wind Shifts are forecasted, THEN PAR No. 6 shall be reviewed to assist with final PAR determination.

ANO-2-JPM-NRC-SFPFL (P1) PAGE 1 OF 7 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 000 DATE:

SYSTEM/DUTY AREA: Spent Fuel Pool Cooling System TASK: Line up to fill the spent fuel pool from CVCS JTA#: ANO2-WCO-SFP-NORM-18 Alternate Path Yes: No: X Time Critical Yes: No: X KA VALUE RO: 3.1 SRO: 3.5 KA

REFERENCE:

033 A2.03 APPROVED FOR ADMINISTRATION TO: RO: X SRO: X TASK LOCATION: INSIDE CR: OUTSIDE CR: X BOTH:

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: Simulate SIMULATOR: LAB:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: LAB:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 20 Minutes REFERENCE(S): OP 2104.006, Section 10.0 EXAMINEE'S NAME: Badge #

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Stop Total Time Time Time

ANO-2-JPM-NRC-SFPFL (P1) PAGE 2 OF 7 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

The Plant is shutdown and in Mode 6 with the core off loaded.

2K11-J5, FUEL POOL LEVEL LOW is in alarm.

The Crew has entered Spent Fuel Pool emergencies.

SFP level is 401 0 due to a leak on a SFP cooling pump packing gland which is being isolated.

SFP purification is aligned to the RWT.

RCS Makeup is aligned to the charging pump suction.

The SFP tilt pit gate is installed.

TASK STANDARD:

Established a flow path to allow make up to the Spent Fuel Pool by performing closing manual makeup to the charging pump suction and opening manual make up valves to the Spent Fuel Pool:

TASK PERFORMANCE AIDS:

OP 2104.006, Fuel Pool systems, Section 10.0

ANO-2-JPM-NRC-SFPFL (P1) PAGE 3 OF 7 JOB PERFORMANCE MEASURE INITIATING CUE:

The SM/CRS directs you to align for makeup water addition to the SFP system from CVCS using OP 2104.006, Section 10.0 beginning with step 10.8. Steps 10.1 through 10.7 have been completed.

START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

Procedure Note:

SFP volume ~ 470 gal/inch SFP/Tilt Pit volume ~ 575 gal/inch (Tilt Pit gate not sealed/not installed)

SFP/CLP volume ~ 535 gal/inch (CLP gate not sealed/not installed)

SFP/Tilt Pit/CLP volume ~ 640 gal/inch (Tilt Pit AND CLP gates not sealed/not installed)

Normal SFP level maintained between 401'4" and 401'6"

1. Fuel Pool Purification pump (2P- Examinee locally stopped 2P-66 N/A SAT UNSAT (Step 66) OFF (2HS-5411). by placing 2HS-5411 in "OFF".

10.8.1)

Examiner Note: 2P-66 should be found running for this JPM. Examinee observed red light Examiner Cue: OFF; green light ON above 2HS-5411.

Describe that Fuel Pool Purification pump 2P-66 is off after applicant takes action to place the HS in off.

TRANSITION NOTE:

Go to elevation 354' RAB spent fuel pool valve gallery.

2. RWT to Fuel Pool Isol (2FP-46) Examinee closed 2FP-46 by N/A SAT UNSAT (Step closed. turning handwheel clockwise.

10.8.2)

Examiner Note: 2FP-46 should be found open for this JPM. Examinee observed stem fully Examiner Cue: inserted into the valve.

Describe that RWT to Fuel Pool Isol (2FP-46) is closed (stem inserted, resistance felt when turning clockwise) after operation.

3. Borated MU or RWT to 2P-66 Examinee closed 2FP-32 by N/A SAT UNSAT (Step (2FP-32) closed. turning handwheel clockwise.

10.8.3)

Examiner Note: 2FP-32 should be found open for this JPM. Examinee observed stem fully Examiner Cue: inserted into the valve.

Describe that Borated MU or RWT to 2P-66 (2FP-32) is closed (stem inserted, resistance felt when turning clockwise)after operation.

ANO-2-JPM-NRC-SFPFL (P1) PAGE 4 OF 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

TRANSITION NOTE:

Go to elevation 354' RAB VCT valve gallery.

(C) 4. Verify following valves closed: Examinee closed 2CVC-83 by N/A SAT UNSAT (Step pulling on right-hand side of chain 10.9) Manual Makeup to Charging (from the chain operator).

First Pump suction (2CVC-83) bullet Examinee observed valve closed Examiner Note: 2CVC-83 position indication on valve reach should be found open for this rod actuator.

JPM.

Examiner Cue:

Describe that Manual Makeup to Charging Pump suction (2CVC-83) is closed (stem inserted, resistance felt when turning clockwise) after operation.

5. Verify following valves closed: Examinee attempted to rotate N/A SAT UNSAT (Step reach rod handwheel clockwise 10.9) noting resistance to motion.

Manual Makeup to VCT Second (2CVC-68) bullet Examinee observed valve closed position indication on valve reach Examiner Note: 2CVC-68 rod actuator.

should be found closed for this JPM.

Examiner Cue:

Describe that Manual Makeup to VCT (2CVC-68) is closed (stem inserted, resistance felt when turning clockwise).

TRANSITION NOTE:

Go to elevation 354' RAB spent fuel pool valve gallery.

(C) 6. Verify following valves open: Examinee opened 2CVC-66 by N/A SAT UNSAT (Step rotating handwheel counter 10.10) clockwise.

MU to SF Pool (2CVC-66)

First bullet Examinee observed valve stem Examiner Note: 2CVC-66 fully withdrawn out of the valve.

should be found closed for this JPM.

Examiner Cue:

Describe that MU to SF Pool (2CVC-66) is open (stem extended, resistance felt in the counter clockwise direction).

ANO-2-JPM-NRC-SFPFL (P1) PAGE 5 OF 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 7. Verify following valves open: Examinee opened 2CVC-67 by N/A SAT UNSAT (Step rotating handwheel counter 10.10) clockwise.

Borated MU to Fuel Pool Second (2CVC-67) bullet Examinee observed valve stem fully withdrawn out of the valve.

Examiner Note: 2CVC-67 should be found closed for this JPM.

Examiner Cue:

Describe that Borated MU to Fuel Pool (2CVC-67) is open (stem extended, resistance felt in the counter clockwise direction).

(C) 8. Verify following valves open: Examinee opened 2FP-31 by N/A SAT UNSAT (Step Borated MU, RWT, SW to rotating handwheel counter 10.10) Fuel Pool (2FP-31) clockwise.

Third bullet Examiner Note: 2FP-31 should Examinee observed valve stem be found closed for this JPM. fully withdrawn out of the valve.

Examiner Cue:

Describe that Borated MU, RWT, SW to Fuel Pool (2FP-31) is open (stem extended, resistance felt in the counter clockwise direction).

9. Notify Control Room that Spent Using the phone or radio, N/A SAT UNSAT Fuel Pool make up alignment is examinee contacted Control complete. Room and reported that Spent Fuel Pool alignment is complete.

POSITIVE CUE:

Understand make up alignment is complete, standby to secure alignment once Spent Fuel Pool level has been restored.

END STOP TIME:

ANO-2-JPM-NRC-SFPFL (P1) PAGE 6 OF 7 JOB PERFORMANCE MEASURE EXAMINERS COPY INITIAL CONDITIONS:

The Plant is shutdown and in Mode 6 with the core off loaded.

2K11-J5, FUEL POOL LEVEL LOW is in alarm.

The Crew has entered Spent Fuel Pool emergencies.

SFP level is 401 0 due to a leak on a SFP cooling pump packing gland which is being isolated.

SFP purification is aligned to the RWT.

RCS Makeup is aligned to the charging pump suction.

The SFP tilt pit gate is installed.

INITIATING CUE:

The SM/CRS directs you to align for makeup water addition to the SFP system from CVCS using OP 2104.006, Section 10.0 beginning with step 10.8. Steps 10.1 through 10.7 have been completed.

ANO-2-JPM-NRC-SFPFL (P1) PAGE 7 OF 7 JOB PERFORMANCE MEASURE EXAMINEES Copy INITIAL CONDITIONS:

The Plant is shutdown and in Mode 6 with the core off loaded.

2K11-J5, FUEL POOL LEVEL LOW is in alarm.

The Crew has entered Spent Fuel Pool emergencies.

SFP level is 401 0 due to a leak on a SFP cooling pump packing gland which is being isolated.

SFP purification is aligned to the RWT.

RCS Makeup is aligned to the charging pump suction.

The SFP tilt pit gate is installed.

INITIATING CUE:

The SM/CRS directs you to align for makeup water addition to the SFP system from CVCS using OP 2104.006, Section 10.0 beginning with step 10.8. Steps 10.1 through 10.7 have been completed.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

PAGE: 19 of 191 2104.006 FUEL POOL SYSTEMS CHANGE: 051 10.0 NORMAL FUEL POOL MAKEUP FROM CVCS CAUTION R The following section has been determined to have a Reactivity A Addition Potential (RAP) and this activity is classified as a P Risk Level R4.

N/A 10.1 IF a Reactivity Management Brief has NOT been conducted, THEN perform a Reactivity Management Brief per COPD-030 with an SRO.

NOTE SFP volume ~ 470 gal/inch SFP/Tilt Pit volume ~ 575 gal/inch (Tilt Pit gate not sealed/not installed)

SFP/CLP volume ~ 535 gal/inch (CLP gate not sealed/not installed)

SFP/Tilt Pit/CLP volume ~ 640 gal/inch (Tilt Pit AND CLP gates not sealed/not installed)

Normal SFP level maintained between 401'4" and 401'6" N/A

{4.3.2} 10.2 IF Cask Loading Operations are in progress, THEN coordinate with Dry Fuel personnel prior to makeup.

N/A 10.3 IF makeup is due to loss from normal evaporation ONLY AND NOT desired to raise SFP Boron concentration, THEN calculate amount of water needed to restore level using NOTE above for guidance.

10.4 IF makeup for other than normal evaporation OR desired to adjust SFP Boron concentration during makeup, THEN perform applicable calculation IAW Attachment F OR Boron 2 Program.

10.5 Notify Chemistry that SFP Makeup will be aligned and if currently required the Quarterly Sample of DI water can be obtained from Sample Valve on Fuel Pool Feed Line (2CVC-122).

10.6 Verify Chemical Addition portion of CVCS available.

10.7 Verify VCT Makeup Valve (2CV-4941-2) closed.

10.8 IF Purification NOT in service OR aligned to RWT, THEN verify the following:

10.8.1 Fuel Pool Purification pump (2P-66) OFF (2HS-5411).

10.8.2 RWT to Fuel Pool Isol (2FP-46) closed.

10.8.3 Borated MU or RWT to 2P-66 (2FP-32) closed.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

PAGE: 20 of 191 2104.006 FUEL POOL SYSTEMS CHANGE: 051 10.9 Verify following valves closed:

Manual Makeup to Charging Pump suction (2CVC-83)

Manual Makeup to VCT (2CVC-68) 10.10 Verify following valves open:

MU to SF Pool (2CVC-66)

Borated MU to Fuel Pool (2CVC-67)

Borated MU, RWT, SW to Fuel Pool (2FP-31)

CRITICAL STEP NOTE If CLP (2LI-5400) used as SFP level indication during SFP drain and fill evolutions, SFP and CLP levels will differ slightly until water levels equalize through seal area.

  • 10.11 Station Operator in communication with Control Room to continuously monitor Spent Fuel Pool level until evolution complete:

SFP (2LI-5401)

CLP (2LI-5400) if gate removed or seal deflated

  • 10.12 Monitor Reactor Power during makeup to Fuel Pool to detect seat leakage from the following valves:

VCT Makeup Valve (2CV-4941-2)

Manual Makeup to VCT (2CVC-68)

Manual Makeup to Charging Pump suction (2CVC-83).

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

PAGE: 21 of 191 2104.006 FUEL POOL SYSTEMS CHANGE: 051 CAUTION If SFP overfilled, water can spill through SFP Cooling/SFP Purification pipe chase (SFP, ~ 402', SW corner) and contaminate SFP valve gallery (AB 354')

and hall near 2F-3A/B (AB 335')

If flow introduced with level > 401' 7", some overflow can occur due to wave motion of water.

10.13 Align for addition as follows:

NOTE When blending, setting controllers so boric acid addition secures ~ 50 gallons before water addition secures allows flush of boric acid from blending line.

10.13.1 IF adding water, THEN perform the following:

A. Verify either RMW pump running:

2P-109A 2P-109B B. Set RMW Flow controller (2FIC-4927) to needed flow.

C. IF NOT adding Boric Acid, THEN verify the following on Boric Acid MU Flow Controller (2FIC-4926):

Select switch in MANUAL.

Output Demand < zero.

10.13.2 IF adding Boric Acid, THEN perform the following:

A. Verify BAM Pump Select switch (2HS-4911-2) aligned to desired BAM pump:

2P-39A 2P-39B B. Start selected BAM pump:

2P-39A 2P-39B

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

PAGE: 22 of 191 2104.006 FUEL POOL SYSTEMS CHANGE: 051 C. Open associated Recirc:

2P-39A (2CV-4903-2) 2P-39B (2CV-4915-2)

D. Set Boric Acid MU Flow Controller (2FIC-4926) to needed flow.

E. IF NOT adding water, THEN verify the following on RMW Flow Controller (2FIC-4927):

Selected to MANUAL.

Output demand < zero.

10.13.3 Reset Flow totalizers to zero:

BA MU Flow (2FQI-4926)

RMW Flow (2FQI-4927) 10.13.4 Verify BAM Pump Select switch (2HS-4911-2) aligned to desired BAM pump:

2P-39A 2P-39B 10.13.5 Place MU Mode Selector switch (2HS-4928) to MANUAL.

10.13.6 IF selected BAM pump Auto starts, THEN verify associated Recirc for selected BAM pump open:

2P-39A (2CV-4903-2) 2P-39B (2CV-4915-2) 10.13.7 Verify BA MU Flow (2FIC-4926) indicates correct flow.

10.13.8 Verify RMW Flow (2FIC-4927) indicates correct flow.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

PAGE: 23 of 191 2104.006 FUEL POOL SYSTEMS CHANGE: 051 10.14 WHEN calculated amounts of boric acid and/or water added OR Operator monitoring level determines desired level reached, THEN perform the following:

10.14.1 Reposition MU Mode Selector switch (2HS-4928) as desired.

10.14.2 Verify 2CV-4927 closed.

10.14.3 Verify 2CV-4926 closed.

10.14.4 Verify applicable BAM pumps secured:

2P-39A 2P-39B 10.14.5 Verify applicable BAM Pump Recirc valves closed:

2CV-4903-2 2CV-4915-2 10.14.6 IF only Boric Acid was added to the SFP, THEN flush blending tee with ~ 50 gallons of water as follows:

A. Verify EITHER 2P-109 pump in service.

B. Set Reactor Makeup Water Flow controller (2FIC-4927) setpoint to desired flow rate.

C. Reset Reactor Makeup Water Flow totalizer (2FQI-4927) to zero so total gallons of makeup can be determined.

D. Verify the following on Boric Acid MU Flow Controller (2FIC-4926):

Select switch in MANUAL.

Output Demand < zero.

E. Place Mode selector switch (2HS-4928) to MANUAL.

F. Verify 2FIC-4927 indicates desired flowrate.

G. WHEN ~ 50 gallons of water added, THEN reposition Mode Select switch as desired.

H. Verify 2CV-4927 closed.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

PAGE: 24 of 191 2104.006 FUEL POOL SYSTEMS CHANGE: 051 10.14.7 Secure Operator from SFP level monitoring station.

10.14.8 Close the following valves:

Borated MU, RWT, SW to Fuel Pool (2FP-31)

Borated MU to Fuel Pool (2CVC-67)

MU to SF Pool (2CVC-66) 10.14.9 Return flow controllers to desired settings:

RMW Flow Controller (2FIC-4927)

BA MU Flow Controller (2FIC-4926) 10.15 Open Manual Makeup to Charging Pump Suction (2CVC-83).

10.16 IF makeup was for other than normal evaporation, THEN request Chemistry to sample SFP.

10.17 Align Purification System as desired using applicable section of this procedure.

10.18 Reset Flow totalizers to zero:

BA MU Flow (2FQI-4926)

RMW Flow (2FQI-4927)

ANO-2-JPM-NRC-DC01 (P2) PAGE 1 OF 8 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 000 DATE:

SYSTEM/DUTY AREA: 125VDC Electrical Distribution System TASK: Swap in-service Battery Chargers JTA#: ANO2-AO-125DC-NORM-8 Alternate Path Yes: X No: Time Critical Yes: No: X KA VALUE RO: 2.8 SRO: 3.1 KA

REFERENCE:

063 A4.01 APPROVED FOR ADMINISTRATION TO: RO: X SRO: X TASK LOCATION: INSIDE CR: OUTSIDE CR: X BOTH:

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: Simulate SIMULATOR: LAB:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: LAB:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 6 Minutes REFERENCE(S): OP-2107.004 Attachment B-1 EXAMINEE'S NAME: Badge #

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Stop Total Time Time Time

ANO-2-JPM-NRC-DC01 (P2) PAGE 2 OF 8 JOB PERFORMANCE MEASURE INITIAL CONDITIONS Plant is at 100% power.

2D-31A Red Train Battery Charger is in service.

2D-31B Red Train Battery Charger is secured.

Preventative Maintenance is scheduled for 2D-31A 2107.004 Attachment B-1 initial conditions have been completed (Section 1)

TASK STANDARD:

Placed 2D-31B battery charging in service by closing the AC input breaker, DC output breaker, and opening 2D-31A DC output breaker and AC input breaker. Recognized that 2D-31B did not pick up load then placed 2D-31A back in service by closing the AC input breaker then the DC output breaker.

TASK PERFORMANCE AIDS:

OP-2107.004 attachment B-1

ANO-2-JPM-NRC-DC01 (P2) PAGE 3 OF 8 JOB PERFORMANCE MEASURE INITIATING CUE:

The SM/CRS directs you to place 2D-31B Battery Charger in service using OP-2107.004 Attachment B-1 beginning with step 2.1.

START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 1. Close 2D-31B AC input On 2D-31B, closed B301 AC N/A SAT UNSAT breaker (B301). input breaker.

(Step 2.1)

Examiner note: AC input voltage and DC output voltage should rise to normal values when the breaker is closed.

Examiner Cue:

Describe that 2D-31B AC input breaker B301 indicates closed (up position).

Procedure Note:

FLOAT/EQL switch (2HS-9104) is spring return to mid-position switch.

2. Verify Green FLOAT indicating On 2D-31B, observed that the N/A SAT UNSAT light lit on 2D-31B. green float light was lit.

(Step 2.2)

Examiner Cue:

Describe that the green float light is illuminated.

3. Check the following: On 2D-31B, observed DC output N/A SAT UNSAT voltage ~ 130 volts (Step 2.3) 2D-31B DC output voltage and

~ 130 VDC (V301). On 2D-31B, observed AC input AC input voltage normal voltage ~ 480 volts

~ 480 VAC (V302).

Examiner Cue:

Describe that output voltage indicates ~130 volts and AC input voltage indicates ~480 volts by indicating the approximate readings.

(C) 4. Close 2D-31B DC output On 2D-31B, closed B302 DC N/A SAT UNSAT breaker (B302). output breaker.

(Step 2.4)

Examiner Cue:

Describe that DC output breaker B302 indicates closed (up position).

ANO-2-JPM-NRC-DC01 (P2) PAGE 4 OF 8 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

Procedure Note:

Automatic load sharing should equalize charger load within 1 minute. However it is not necessary to wait longer if load does not equalize.

5. Wait 1 minute. Monitored time to ensure 1 N/A SAT UNSAT minute elapsed prior to (Step 2.5) Examiner Note: proceeding.

The battery chargers will not load share.

Examiner Cue:

If applicant monitors load sharing describe that 2D-31B indicates zero amps and 2D-31A indicates ~115 amps by indicating the approximate readings.

Procedure Note:

Opening DC output breaker for 2D-31A (B302):

May cause its DC output voltage to drift to zero and re-flash unit lights to fade. (CR-ANO-2-2003-0423).

Will cause Bus 2D01 Charger Trouble alarm (2K01-E10).

(C) 6. Open 2D-31A DC output On 2D-31A, opened B302 DC N/A SAT UNSAT breaker (B302). output breaker.

(Step 2.6)

Examiner Cue:

Describe that 2D-31A DC output breaker B302 indicates open (down position).

EXAMINERS NOTE:

In the following step 2D-31B will not function properly and will required the operator to perform the alternate path to restart 2D-31A.

7. Check 2D-31B picks up load to Observes 2D-31B DC output N/A SAT UNSAT maintain proper DC bus voltage to determine proper (Step 2.7) voltage operation of 2D-31B.

of ~ 130 VDC.

Examiner Cue:

Describe that 2D-31B DC output voltage is lowering toward 115 volts and output amps are reading zero by indicating the approximate readings.

ANO-2-JPM-NRC-DC01 (P2) PAGE 5 OF 8 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

8. IF 2D-31A DC output voltage Observes 2D-31A DC output N/A SAT UNSAT drifted to zero when its voltage and determines step 2.8 (Step DC Output Breaker was in not applicable.

2.8) opened, THEN perform the following to prove 2D-31A operability:

Examiner Cue:

Describe that 2D-31A DC output voltage is reading ~

130 volts by indicating the approximate readings.

(C) 9. Open 2D-31A AC Input On 2D-31A, opened B302 DC N/A SAT UNSAT Breaker (B301). output breaker.

(Step 2.9)

Examiner Cue:

Describe that 2D-31A AC input breaker B302 indicates open (down position).

10. IF Charger 2D-31B does NOT Determines that 2D-31B did not N/A SAT UNSAT pick up load, pick up load by lowering output (Step THEN perform the following: voltage and no amps indicated.

2.10)

Examiner Cue:

Describe that 2D-31B DC output voltage is lowering toward 115 volts and output amps are reading zero by indicating the approximate readings.

11. Refer to Tech Specs 3.8.2.3, Contacts the SM/CRS and reports N/A SAT UNSAT 3.8.2.4 and 3.8.3. that 2D-31B did not pick up load (Step 2.10.1) and to refer to TS 3.8.2.3, 3.8.2.4, Examiner Cue: and 3.8.3 Respond that the SM/CRS will refer to TS 3.8.2.3, 3.8.2.4, and 3.8.3 (C) 12. Open 2D-31B DC output On 2D-31B, opened B302 DC N/A SAT UNSAT breaker (B302) output breaker.

(Step 2.10.2)

Examiner Cue:

Describe that 2D-31B DC output breaker B302 indicates open (down position).

ANO-2-JPM-NRC-DC01 (P2) PAGE 6 OF 8 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 13. Open 2D-31B AC input breaker On 2D-31B, opened B301 AC N/A SAT UNSAT (B301). input breaker.

(Step 2.10.3)

Examiner Cue:

Describe that 2D-31B AC input breaker B301 indicates open (down position).

14. WHEN 1 minute elapsed Ensured at least 1 minute has N/A SAT UNSAT after de-energizing 2D-31A, elapsed since 2D-31A AC input (Step 2.10.4) THEN proceed as follows: breaker was opened.

(C) 15. Close 2D-31A AC input On 2D-31A, closed B301 AC N/A SAT UNSAT breaker (B301). input breaker.

(Step 2.10.4. Examiner Cue:

A)

Describe that 2D-31A AC input breaker B301 indicates closed (up position).

(C) 16. Close 2D-31A DC output On 2D-31A, closed B302 DC N/A SAT UNSAT breaker (B302). output breaker.

(Step 2.10.4. Examiner Cue:

B)

Describe that 2D-31A DC input breaker B302 indicates closed (up position).

17. Check 2D-31A picks up load to Determined that 2D-31A did pick N/A SAT UNSAT maintain DC bus voltage. up load by observing ~ 130V (Step 2.10.4. output voltage and 200 amps C) Examiner Cue: indicated.

Describe that 2D-31A DC output voltage is reading ~

130 volts and output amps are reading ~ 200 by indicating the approximate readings.

END STOP TIME:

ANO-2-JPM-NRC-DC01 (P2) PAGE 7 OF 8 JOB PERFORMANCE MEASURE EXAMINERS COPY INITIAL CONDITIONS:

Plant is at 100% power.

2D-31A Red Train Battery Charger is in service.

2D-31B Red Train Battery Charger is secured.

Preventative Maintenance is scheduled for 2D-31A 2107.004 Attachment B-1 initial conditions have been completed (Section 1)

INITIATING CUE:

The SM/CRS directs you to place 2D-31B Battery Charger in service using OP-2107.004 Attachment B-1 beginning with step 2.1.

ANO-2-JPM-NRC-DC01 (P2) PAGE 8 OF 8 JOB PERFORMANCE MEASURE EXAMINEES COPY INITIAL CONDITIONS:

Plant is at 100% power.

2D-31A Red Train Battery Charger is in service.

2D-31B Red Train Battery Charger is secured.

Preventative Maintenance is scheduled for 2D-31A 2107.004 Attachment B-1 initial conditions have been completed (Section 1)

INITIATING CUE:

The SM/CRS directs you to place 2D-31B Battery Charger in service using OP-2107.004 Attachment B-1 beginning with step 2.1.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 22 of 102 2107.004 DC ELECTRICAL SYSTEM OPERATION CHANGE: 034 ATTACHMENT B-1 Page 1 of 5 PARALLEL TRANSFER FROM 2D-31A TO 2D-31B 1.0 INITIAL CONDITIONS 1.1 Verify at least ONE of the following running in 2D-11 Battery Room:

2VEF-61 2VEF-65 Temporary Exhaust Fan CAUTION Battery Charger cabinets contain both 480 VAC and 125 VDC.

1.2 Refer to 2107.001 Exhibit 9 for applicable Electrical Personal Protection Equipment to access electrical components.

1.3 Verify the following:

2D-31B Current Limit Setting Lower/Upper switch (2HS-9110) in UPPER position (located inside 2D-31B cabinet).

2D-31B AC input breaker (B301) open.

2D-31B DC output breaker (B302) open.

Auto Transfer switch 2D01-42/2D-31B Battery Charger breaker (2D01-33) closed.

2D-31A Battery Charger/Alternate to Auto Transfer Switch 2D01 breaker (2D01-23) closed.

N/A 2D-31B Disconnect switch (2D01-11) closed.

(This is applicable when EC-29145 is installed.)

1.4 IF 2D-31B to be powered from Red Bus, THEN verify the following:

2D-31B Input Transfer switch (2S21) in NORMAL.

Battery Charger 2D-31B (2B54-G3) closed.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 23 of 102 2107.004 DC ELECTRICAL SYSTEM OPERATION CHANGE: 034 ATTACHMENT B-1 Page 2 of 5 NOTE This alignment places two battery chargers as loads onto the Emergency Diesel Generator. This is accounted for as shown in ANO-2 DIESEL GENERATOR

  1. 1 (2K4A) and #2 (2K4B) LOADING CALC (CALC-85-S-00002-01).

N/A 1.5 IF 2D-31B to be powered from Green Bus, THEN perform the following:

1.5.1 Verify plant in Mode 5, 6 or defueled.

1.5.2 Declare battery bus 2D01 inoperable.

1.5.3 Refer to Tech Spec 3.8.2.4.

1.5.4 Align 2D-31B to Green Bus IAW Shifting Battery Charger 2D-31B AC Supply section of this procedure.

1.6 IF necessary to ensure 2D01 remains energized, AND Battery 2D-11 available, THEN verify the following:

2D-11 Battery Disconnect (2D-51) closed.

2D-41 fuses installed (2K01-D10 BATTERY 2D11 NOT AVAIL clear).

1.7 Record on-line charger current load:

40 amps AC amps (A302)_____

115 amps DC amps (A301)_____

2.0 PARALLEL TRANSFER FROM 2D-31A TO 2D-31B 2.1 Close 2D-31B AC input breaker (B301).

NOTE FLOAT/EQL switch (2HS-9104) is spring return to mid-position switch.

2.2 Verify Green FLOAT indicating light lit on 2D-31B.

2.3 Check the following:

2D-31B DC output voltage ~ 130 VDC (V301).

AC input voltage normal ~ 480 VAC (V302).

2.4 Close 2D-31B DC output breaker (B302).

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 24 of 102 2107.004 DC ELECTRICAL SYSTEM OPERATION CHANGE: 034 ATTACHMENT B-1 Page 3 of 5 NOTE Automatic load sharing should equalize charger load within 1 minute.

However it is not necessary to wait longer if load does not equalize.

2.5 Wait 1 minute.

NOTE Opening DC output breaker for 2D-31A (B302):

May cause its DC output voltage to drift to zero and re-flash unit lights to fade. (CR-ANO-2-2003-0423).

Will cause Bus 2D01 Charger Trouble alarm (2K01-E10).

CRITICAL STEP 2.6 Open 2D-31A DC output breaker (B302).

2.7 Check 2D-31B picks up load to maintain proper DC bus voltage of ~ 130 VDC.

2.8 IF 2D-31A DC output voltage drifted to zero when its DC Output Breaker was opened, THEN perform the following to prove 2D-31A operability:

2.8.1 Open 2D-31A AC input breaker (B301).

2.8.2 Wait 1 minute.

2.8.3 Close 2D-31A AC input breaker (B301).

2.8.4 IF 2D-31A DC output voltage did NOT return to

~130 VDC (V301),

THEN perform the following:

Contact Electrical Maintenance for support.

Initiate WR/WO.

Initiate Condition Report.

2.9 Open 2D-31A AC Input Breaker (B301).

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 25 of 102 2107.004 DC ELECTRICAL SYSTEM OPERATION CHANGE: 034 ATTACHMENT B-1 Page 4 of 5 2.10 IF Charger 2D-31B does NOT pick up load, THEN perform the following:

2.10.1 Refer to Tech Specs 3.8.2.3, 3.8.2.4 and 3.8.3.

2.10.2 Open 2D-31B DC output breaker (B302).

2.10.3 Open 2D-31B AC input breaker (B301).

2.10.4 WHEN 1 minute elapsed after de-energizing 2D-31A, THEN proceed as follows:

A. Close 2D-31A AC input breaker (B301).

B. Close 2D-31A DC output breaker (B302).

C. Check 2D-31A picks up load to maintain DC bus voltage.

D. Verify all alarms clear.

E. Initiate WR/WO to trouble shoot 2D-31B Charger.

F. Initiate Condition Report.

2.11 Verify all alarms clear on 2K9102 (2D-31B).

2.12 Place Alarm To Control Room Disable/Enable switch on 2D-31B (2HS-9112) in ENABLE.

2.13 Place Alarm To Control Room Disable/Enable switch on 2D-31A (2HS-9113) in DISABLE.

2.14 Verify 2K9102 (2D-31B) lamps operable by performing an annunciator test.

2.15 Verify 2K01-E10 (BATTERY 2D11 NOT AVAIL) clear.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 26 of 102 2107.004 DC ELECTRICAL SYSTEM OPERATION CHANGE: 034 ATTACHMENT B-1 Page 5 of 5 3.0 FINAL CONDITIONS 3.1 WHEN five minutes elapsed, THEN record the following data:

2D-31B AC Amps (A302) __________

2D-31B DC Amps (A301) __________

2D-31B AC Volts (V302) __________

2D-31B DC Volts (V301) __________

3.2 Check on-coming DC Charger AC amps and DC amps approximately the same as those recorded in Initial Conditions section for off-going DC Charger.

3.3 Notify Control Room to verify EOOS Risk Assessment program and Status Board updated to reflect current DC Charger Power Source Alignment.

Performed by ____________________________________________ Date ________

Supervisor ______________________________________________ Date ________

ANO-2-JPM-NRC-TLOF (P3) PAGE 1 OF 10 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 002 DATE:

SYSTEM/DUTY AREA: Condensate and Feedwater System TASK: Perform Local Actions to start D Condensate pump during a Loss of Feedwater.

JTA#: ANO2-RO-EOPAOP-EMER-28 Alternate Path Yes: No: X Time Critical Yes: No: X KA VALUE RO: 3.0 SRO: 4.2 KA

REFERENCE:

CE E06 EA2.2 APPROVED FOR ADMINISTRATION TO: RO: X SRO: X TASK LOCATION: INSIDE CR: OUTSIDE CR: X BOTH:

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: Simulate SIMULATOR: LAB:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: LAB:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 20 Minutes REFERENCE(S): OP 2202.010, Standard Attachments, Attachment 50 Condensate pump start.

EXAMINEE'S NAME: Badge #

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Stop Total Time Time Time

ANO-2-JPM-NRC-TLOF (P3) PAGE 2 OF 10 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

2P-7A Outboard Pump Bearing Replacement in-progress.

The plant has tripped from 100% power due to an inadvertent CSAS.

Busses 2A1 & 2A3 are locked out due to fire in 2A3 feeder breaker (2A309).

TASK STANDARD:

Established D Condensate pump as a feedwater source to steam generators by performing the following actions:

Opened DC control power breakers in 2A-106 and 2A-205 to defeat the trip signal.

Isolated side stream flow path by closing valves 2CS-57 and 2CS-59.

Opened D condensate pump discharge valve within 3 minutes of pump start.

TASK PERFORMANCE AIDS:

OP 2202.010, Standard Attachments, Attachment 50 Condensate pump start.

ANO-2-JPM-NRC-TLOF (P3) PAGE 3 OF 10 JOB PERFORMANCE MEASURE INITIATING CUE:

The SM/CRS directs you to perform local actions to start "D" Condensate Pump using OP 2202.010 attachment 50 starting with step 3.

START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

TRANSITION NOTE:

Go to elevation 370 Turbine Building, east of the elevator, to the 2A-1 / 2 Bus area.

(C) 1. IF MSIS AND CSAS NOT reset, The DC Control Power Breakers N/A SAT UNSAT THEN locally open DC control located in 2A106 AND 2A205 are (Step 3) power breaker in the following positioned down (open).

breaker cubicles:

CONDENSATE PUMP 2P-2C 2A106 CONDENSATE PUMP 2P-2B 2A205 Examiner Cue:

When the applicant finds the correct breaker cubicle ask them the general location of the DC control power breaker once they describe it then Show Picture #1. If the applicant wants a closer picture to read the placard Show Picture #2.

TRANSITION NOTE:

The applicant may go to elevation 330 Turbine Building, east of the Main Condenser if checking level locally, use the level gauge above the B Condensate pump or contact the control room.

2. Verify Hotwell level greater than Hotwell is checked > 38% by N/A SAT UNSAT 38%. contacting a Control Room (Step 4)

Operator, checking the local level Examiner Cue: instrument West of the Main Describe that Hotwell level Condenser in the Turbine Building indicates >38% by indicating Basement, or the gauge above the approximate reading. the B Condensate pump.

(Normal level at power is greater than 38%).

ANO-2-JPM-NRC-TLOF (P3) PAGE 4 OF 10 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

3. Verify the following Recirc 2CV-0662, 2CV-0663, 2CV-0741, N/A SAT UNSAT valves closed and 2CV-0749 are checked closed (Step 5)

AND Flow Indicating Controllers by contacting a Control Room in MANUAL at 0% demand: Operator to determine valve position and demand.

Condensate Pump Recirc 2CV-0662 (2FIC-0662)

Condensate Pump Recirc 2CV-0663 (2FIC-0663)

A MFP Recirc 2CV-0741 (2FIC-0735) (R/L then M/A and close)

B MFP Recirc 2CV-0749 (2FIC-0742) (R/L then M/A and close)

Examiner Cue:

Report as a control room operator that all recirc valves listed in the above step are closed with flow indicating controllers in manual at 0%

demand.

ANO-2-JPM-NRC-TLOF (P3) PAGE 5 OF 10 JOB PERFORMANCE MEASURE TRANSITION NOTE:

Go to elevation 330 Turbine Building, near southwest stairwell to check valve position locally.

(C) 5. Locally verify the following Examinee verified closed 2CS- N/A SAT UNSAT valves closed: 57 by turning handwheel (Step 6 first clockwise and noting resistance bullet.) to motion.

INLET TO 2PCV-4505 ISOL (2CS-57)

Examiner Cue:

Describe that 2CS-57 is closed. (stem inserted, resistance felt in the closed direction.)

(C) 6. Locally verify the following Examinee closed 2CS-59 by N/A SAT UNSAT valves closed: turning handwheel clockwise (Step 6 second until resistance to motion bullet.) occurs.

2PCV-4505 BYPASS (2CS-59)

Examiner Cue:

Describe that 2CS-59 is closed. (stem inserted, resistance felt in the closed direction.)

7. Locally open selected Examinee closed 2CS-2D by N/A SAT UNSAT Condensate Pump Discharge turning the handwheel clockwise (Step 7) valve 10 turns: until resistance is felt and then reopened the valve 10 turns by "2P-2D DISCHARGE" turning the handwheel counter (2CS-2D) clockwise.

Examiner Cue:

Describe that 2CS-2D is closed. (stem inserted, resistance felt in the closed direction.) Then describe that 2CS-2D is reopened 10 turns.

(Normally open valve.)

Procedure Caution:

Maintaining Condensate pump discharge pressure greater than 753 psig for three minutes or greater will result in pump trip.

8. Start selected Condensate Examinee contacted the control N/A SAT UNSAT pump. room to start 2P-2D condensate (Step 8) pump.

Examiner Cue:

Acknowledge communication from the applicant. Then report 2P-2D condensate pump is running and direct the applicant to perform step 9

ANO-2-JPM-NRC-TLOF (P3) PAGE 6 OF 10 JOB PERFORMANCE MEASURE (C) 9. Locally open selected Examinee opened 2CS-2D by N/A SAT UNSAT Condensate Pump Discharge turning handwheel counter (Step 9) valve: clockwise "2P-2A DISCHARGE" (2CS-2A)

"2P-2B DISCHARGE" (2CS-2B)

"2P-2C DISCHARGE" (2CS-2C)

"2P-2D DISCHARGE" (2CS-2D)

Examiner Cue:

Describe that 2CS-2D is open.

(stem extended, resistance felt in the open direction.)

END STOP TIME:

ANO-2-JPM-NRC-TLOF (P3) PAGE 7 OF 10 JOB PERFORMANCE MEASURE Picture #1

ANO-2-JPM-NRC-TLOF (P3) PAGE 8 OF 10 JOB PERFORMANCE MEASURE Picture #2

ANO-2-JPM-NRC-TLOF (P3) PAGE 9 OF 10 JOB PERFORMANCE MEASURE EXAMINERS COPY INITIAL CONDITIONS:

2P-7A Outboard Pump Bearing Replacement in-progress.

The plant has tripped from 100% power due to an inadvertent CSAS.

Busses 2A1 & 2A3 are locked out due to fire in 2A3 feeder breaker (2A309).

INITIATING CUE:

The SM/CRS directs you to perform local actions to start 2P-2D Condensate Pump using OP 2202.010 attachment 50 starting with step 3.

ANO-2-JPM-NRC-TLOF (P3) PAGE 10 OF 10 JOB PERFORMANCE MEASURE EXAMINEES COPY INITIAL CONDITIONS:

2P-7A Outboard Pump Bearing Replacement in-progress.

The plant has tripped from 100% power due to an inadvertent CSAS.

Busses 2A1 & 2A3 are locked out due to fire in 2A3 feeder breaker (2A309).

INITIATING CUE:

The SM/CRS directs you to perform local actions to start 2P-2D Condensate Pump using OP 2202.010 attachment 50 starting with step 3.

ATTACHMENT 50 CONDENSATE PUMP START Page 1 of 2 N/A 1. IF MSIS NOT reset AND it is desired, THEN reset MSIS using 2202.010 Attachment 14, MSIS Reset.

N/A 2. IF CSAS NOT reset AND it is desired, THEN reset CSAS by performing the following:

A. Verify CNTMT Spray Termination criteria met:

CNTMT pressure less than 22.5 psia.

CNTMT temperature less than 140°F.

ALL available CNTMT Cooling fans running in Emergency Mode using 2202.010 Exhibit 9, ESFAS Actuation.

TSC determines CNTMT Spray NOT required for CNTMT Iodine removal.

CNTMT Spray NOT required for decay heat removal following RAS actuation.

B. Reset CSAS using 2202.010 Attachment 45, CSAS Reset.

3. IF MSIS AND CSAS NOT reset, THEN locally open DC CONTROL POWER breaker in the following breaker cubicles:

CONDENSATE PUMP 2P-2C 2A106 CONDENSATE PUMP 2P-2B 2A205

4. Verify Hotwell level greater than 38%.
5. Verify the following Recirc valves closed AND Flow Indicating Controllers in MANUAL at 0% demand:

Condensate Pump Recirc 2CV-0662 (2FIC-0662)

Condensate Pump Recirc 2CV-0663 (2FIC-0663)

A MFP Recirc 2CV-0741 (2FIC-0735) (R/L then M/A and close)

B MFP Recirc 2CV-0749 (2FIC-0742) (R/L then M/A and close)

PROC NO TITLE REVISION PAGE 2202.010 STANDARD ATTACHMENTS 022 146 of 204

ATTACHMENT 50 CONDENSATE PUMP START Page 2 of 2

6. Locally verify the following valves closed:

INLET TO 2PCV-4505 ISOL (2CS-57) 2PCV-4505 BYPASS (2CS-59)

7. Locally open selected Condensate Pump Discharge valve 10 turns:

"2P-2A DISCHARGE" (2CS-2A)

"2P-2B DISCHARGE" (2CS-2B)

"2P-2C DISCHARGE" (2CS-2C)

"2P-2D DISCHARGE" (2CS-2D)

CAUTION Maintaining Condensate pump discharge pressure greater than 753 psig for three minutes or greater will result in pump trip.

8. Start selected Condensate pump.
9. Locally open selected Condensate Pump Discharge valve:

"2P-2A DISCHARGE" (2CS-2A)

"2P-2B DISCHARGE" (2CS-2B)

"2P-2C DISCHARGE" (2CS-2C)

"2P-2D DISCHARGE" (2CS-2D)

  • 10. Throttle Condensate Pump Recirc valves OR MFW Pump Recirc valves to maintain discharge pressure less than 700 psig.
11. Locally position the following valves as desired IAW 2106.016, Condensate and Feedwater Operations.

INLET TO 2PCV-4505 ISOL (2CS-57) 2PCV-4505 BYPASS (2CS-59)

PROC NO TITLE REVISION PAGE 2202.010 STANDARD ATTACHMENTS 022 147 of 204

ANO-2-JPM-NRC-HPSI1 (S1) PAGE 1 OF 8 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 011 DATE:

SYSTEM/DUTY AREA: Safety Injection System TASK: Align HPSI System for Hot Leg Injection JTA#: ANO2-RO-EOPAOP-EMERG-13 Alternate Path Yes: X No: Time Critical Yes: No: X KA VALUE RO: 4.2 SRO: 4.3 KA

REFERENCE:

006 A1.17 APPROVED FOR ADMINISTRATION TO: RO: X SRO: X TASK LOCATION: INSIDE CR: X OUTSIDE CR: BOTH:

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform LAB:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: LAB:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 15 Minutes REFERENCE(S): OP 2202.010 Standard Attachment 12 EXAMINEE'S NAME: Badge #

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Stop Total Time Time Time

ANO-2-JPM-NRC-HPSI1 (S1) PAGE 2 OF 8 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

A LOCA has been in progress for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

RCS MTS > 40°F.

PZR level <29%.

RVLMS LVL 01 indicates WET.

Shutdown Cooling can NOT be established within four (4) hours of the start of the LOCA.

TASK STANDARD:

Closed the red train orifice bypass valve Opened both Hot Leg injection valves Determined Total flow, Cold Leg flow range, actual Cold Leg flow, actual cold leg flow not in the acceptable range Determined Green train HPSI system is affected and throttled the Green Train Hot Leg injection MOV to establish Cold Leg flow in the acceptable range.

TASK PERFORMANCE AIDS:

OP-2202.010 Standard Attachment 12; Calculator SIMULATOR SETUP:

LOCA in progress. Both HPSI pumps running.

Close the breakers for 2CV5102-2 2B62 G2 (HPIB62G2) and 2CV5101-1 2B52 L5 (HPIB52L5). (This will allow the examiner to report that the breakers are closed on these valves (Step 1 of JPM).

Override 2CV5104-2 to deenergize the lights when operator closes the valve. It will stick at 25%.

Set a conditional trigger to NF4G1042 (2CV-5104-2 green light)

Set a trigger for CV51042 to .25, 15 second time delay.

Set a trigger for DO_HS_5104_R to off, 15 second time delay.

Set a trigger for DO_HS_5104_G to off, 15 second time delay.

ANO-2-JPM-NRC-HPSI1 (S1) PAGE 3 OF 8 JOB PERFORMANCE MEASURE INITIATING CUE:

The SM/CRS directs you to establish hot leg injection using EOP 2202.010 Attachment 12.

START Time:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

EXAMINER'S NOTE:

Breakers must be closed from simulator instructor's console.

1. Locally clear danger tags AND Directed WCO to clear danger N/A SAT UNSAT close the following breakers: tags, unlock and close 2B52-L5 (Step 1) and 2B62-G2.

HOT LEG INJ VALVE" CUE:

Report as a NLO that breakers 2B52-L5 and 2B62-G2 are closed.

Examiners Note: When 2CV-5104-2 is taken to closed position, after a 15 second time delay, the valve breaker will trip leaving 2CV-5104-2 in mid position.

(C) 2. Close BOTH HPSI Header On panel 2C16, placed hand N/A SAT UNSAT

  1. 1/2 Orifice Bypass valves switch for 2CV-5104-2 (Step 2)

(2CV-5103-1; 2CV-5104-2). "CLOSE".

On panel 2C17, closed 2CV-5103-1.

CUE:

If requested report that Observed green light ON; red breaker for 2CV-5104-2 light OFF for 2CV-5103-1 breaker 2B62-H2 is tripped.

If requested report that 2CV- AND 5104-2 will not move the hand wheel spins freely. Green light OFF, Red light OFF for 2CV-5104-2.

Procedure caution:

HPSI pump flow greater than 800 gpm indicates pump flow in excess of NPSH requirements.

(ER-ANO-2002-0528-000)

3. IF individual HPSI header flow Determined step 3 was not N/A SAT UNSAT greater than 800 gpm, applicable.

(Step 3)

THEN throttle associated Cold Leg Injection valves equally on affected train to lower flow to less than 800 gpm.

ANO-2-JPM-NRC-HPSI1 (S1) PAGE 4 OF 8 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 4. Open BOTH Hot Leg Injection On panel 2C16, opened N/A SAT UNSAT valves (2CV-5101-1; 2CV-5102-2.

(Step 4) 2CV-5102-2)

On panel 2C17, opened 2CV-5101-1.

Observed green light OFF; red light ON above each handswitch.

EXAMINER'S NOTE:

Simulator conditions will vary slightly during performance of this JPM due to the dynamic nature of the evolution. If conditions change, record values to check applicants performance and acceptable range adjusted.

(C) 5. Record HPSI Header flows Recorded HPSI Header #1 flow N/A SAT UNSAT AND add values to calculate (2FI-5101-1 or F5101-1) on (Step 5)

Total HPSI Header flow: Attachment 12.

Recorded HPSI Header #2 flow

. Attachment 12.

. "HEADER 2" flow to obtain "Total HPSI Header flow".

Total HPSI Header Recorded sum on flow = . Attachment 12 as "Total HPSI Header flow" acceptable Examiner Note: range is: 960 to 1040 Header #1 flow ~ 500gpm.

Examiner Note: Examiner Note:

Header #2 flow ~ 500gpm. Critical portions above are bolded.

Examiner Note:

Total HPSI flow ~ 1000 GPM

ANO-2-JPM-NRC-HPSI1 (S1) PAGE 5 OF 8 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 6. Perform the following Multiplied Total HPSI Header N/A SAT UNSAT calculation to determine flow by 0.60 to obtain (Step 6) acceptable band for Total maximum Total HPSI Cold Leg HPSI Cold Leg Injection flow: Injection flow.

Acceptable range = 576 to A. [Total HPSI Header flow 624 (Step 5)] X 0.60 = MAX FLOW Multiplied Total HPSI Header flow by 0.40 to obtain minimum

[ ] X 0.60 Total HPSI Cold Leg Injection

= . flow.

Acceptable range = 384 to B. [Total HPSI Header flow 416 (Step 5)] X 0.40 = MIN FLOW Recorded maximum and minimum Total HPSI Cold Leg

[ ] X 0.40 Injection flow on Attachment

= . 12.

Examiner Note:

MAX FLOW: ~ 600 gpm Examiner Note:

Critical portions above are Examiner Note: bolded.

MIN FLOW: ~ 400 gpm (C) 7. Record HPSI Cold Leg Recorded HPSI Flow to 2P32A N/A SAT UNSAT Injection flows AND add values (2FI-5014-1 or F5014-1).

(Step 7) to calculate Recorded HPSI Flow to 2P32B Total HPSI Cold Leg Injection (2FI-5034-1 or F5034-1).

flow:

  • 2FI-5054-2: . Added HPSI Cold Leg Injection flows to obtain Total HPSI Cold Leg Injection flow.

Acceptable range = 335 to 375 Total HPSI Cold Leg Injection flow = . Examiner Note:

Critical portions above are bolded.

ANO-2-JPM-NRC-HPSI1 (S1) PAGE 6 OF 8 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 8. IF Total HPSI Cold Leg Determined total HPSI Cold N/A SAT UNSAT Injection flow in Step 7 NOT Leg Injection flow NOT within (Step 8) within acceptable band the range established by calculated in Step 6, Maximum and Minimum Total THEN perform ONE of the HPSI Cold Leg Injection flow.

following:

Examiner Note:

Cold leg flow is too low (~355 gpm).

Procedure Note:

Affected train of HPSI is any train where the HPSI Header Orifice Bypass valve or Hot Leg Injection valve does not move to its required position.

(C) 9. IF EITHER HPSI train affected, Determined that green train N/A SAT UNSAT THEN perform the following: HPSI is affected.

(Step 8.A)

1) IF Total HPSI Cold Leg Injection flow greater Determined that Cold leg flow is than MAX FLOW value not greater than the MAX FLOW calculated in Step 6.A, value.

THEN throttle associated Cold Leg Injection valves equally on affected train.

2) IF Total HPSI Cold Leg Determined that cold leg Injection flow less than injection flow is less than MIN MIN FLOW value FLOW value and throttled calculated in closed 2CV-5102-2 to raise Step 6.B, flow into the acceptable band.

THEN throttle Hot Leg Injection valve on affected train.

3) IF only ONE HPSI train Determined that both HPSI operating, AND Cold Leg trains are operating.

Injection valves throttled, THEN check total HPSI flow acceptable using Examiner Note:

Exhibit 2, HPSI Flow Critical portions above are Curve. bolded.

10. Throttle both Hot Leg Injection Determined that step is Not N/A SAT UNSAT valves to establish Total HPSI applicable due to one HPSI train (Step 8.B) Cold Leg Injection flow within being affected.

acceptable band.

END STOP Time:

ANO-2-JPM-NRC-HPSI1 (S1) PAGE 7 OF 8 JOB PERFORMANCE MEASURE EXAMINERS COPY INITIAL CONDITIONS:

You are responsible for any applicable annunciators during the performance of this task.

All annunciators that are not applicable to this task will be performed by another operator.

A LOCA has been in progress for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

RCS MTS >40°F.

PZR level <29%.

RVLMS LVL 01 indicates WET.

Shutdown Cooling can NOT be established within four (4) hours of the start of the LOCA.

INITIATING CUE:

The SM/CRS directs you to establish hot leg injection using EOP 2202.010 Attachment 12.

ANO-2-JPM-NRC-HPSI1 (S1) PAGE 8 OF 8 JOB PERFORMANCE MEASURE EXAMINEES COPY INITIAL CONDITIONS:

You are responsible for any applicable annunciators during the performance of this task.

All annunciators that are not applicable to this task will be performed by another operator.

A LOCA has been in progress for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

RCS MTS >40°F.

PZR level <29%.

RVLMS LVL 01 indicates WET.

Shutdown Cooling can NOT be established within four (4) hours of the start of the LOCA.

INITIATING CUE:

The SM/CRS directs you to establish hot leg injection using EOP 2202.010 Attachment 12.

ATTACHMENT 12 HOT LEG INJECTION Page 1 of 2

1. Locally clear danger tags AND close the following breakers:
2. Close HPSI Header Orifice Bypass valves:
  • 2CV-5104-2 CAUTION HPSI pump flow greater than 800 gpm indicates pump flow in excess of NPSH requirements. (ER-ANO-2002-0528-000)
3. IF individual HPSI header flow greater than 800 gpm, THEN throttle associated Cold Leg Injection valves equally on affected train to lower flow to less than 800 gpm.
4. Open both Hot Leg Injection valves:
5. Record HPSI Header flows AND add values to calculate Total HPSI Header flow:

Total HPSI Header flow = .

6. Perform the following calculation to determine acceptable band for Total HPSI Cold Leg Injection flow:

A. [Total HPSI Header flow (Step 5)] X 0.60 = MAX FLOW

[ ] X 0.60 = .

B. [Total HPSI Header flow (Step 5)] X 0.40 = MIN FLOW

[ ] X 0.40 = .

PROC NO TITLE REVISION PAGE 2202.010 STANDARD ATTACHMENTS 022 46 of 204

ATTACHMENT 12 HOT LEG INJECTION Page 2 of 2

7. Record HPSI Cold Leg Injection flows AND add values to calculate Total HPSI Cold Leg Injection flow:

Total HPSI Cold Leg Injection flow = .

8. IF Total HPSI Cold Leg Injection flow in Step 7 NOT within acceptable band calculated in Step 6, THEN perform ONE of the following:

NOTE Affected HPSI train is ANY train where HPSI Header Orifice Bypass valve or Hot Leg Injection valve does NOT move to its required position.

A. IF EITHER HPSI train affected, THEN perform the following:

1) IF Total HPSI Cold Leg Injection flow greater than MAX FLOW value calculated in Step 6.A, THEN throttle associated Cold Leg Injection valves equally on affected train.
2) IF Total HPSI Cold Leg Injection flow less than MIN FLOW value calculated in Step 6.B, THEN throttle Hot Leg Injection valve on affected train.
3) IF only ONE HPSI train operating, AND Cold Leg Injection valves throttled, THEN check total HPSI flow acceptable using Exhibit 2, HPSI Flow Curve.

B. Throttle both Hot Leg Injection valves to establish Total HPSI Cold Leg Injection flow within acceptable band.

PROC NO TITLE REVISION PAGE 2202.010 STANDARD ATTACHMENTS 022 47 of 204

ANO-2-JPM-NRC-H2003 (S2) PAGE 1 OF 7 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 001 DATE:

SYSTEM/DUTY AREA: Hydrogen Recombiner TASK: Start Up a Hydrogen Recombiner JTA#: ANO2-RO-CONH2-NORM-3 Alternate Path Yes: No: X Time Critical Yes: No: X KA VALUE RO: 4.0 SRO: 4.0 KA

REFERENCE:

028 A4.01 APPROVED FOR ADMINISTRATION TO: RO: X SRO: X TASK LOCATION: INSIDE CR: X OUTSIDE CR: BOTH:

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform LAB:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: LAB:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 20 Minutes REFERENCE(S): OP-2104.044 Containment Hydrogen Control Operations EXAMINEE'S NAME: Badge #

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Time Stop Time Total Time

ANO-2-JPM-NRC-H2003 (S2) PAGE 2 OF 7 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

A LOCA has been in progress for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

Containment Hydrogen is >1%

TSC has directed to start one hydrogen recombiner Pre-LOCA containment temperature was 120 degrees F TASK STANDARD:

Energized the Green Train Hydrogen recombiner and raised power to the required value (54 to 56KW) to recombine hydrogen and oxygen.

TASK PERFORMANCE AIDS:

OP-2104.044 Containment Hydrogen Control Operations SIMULATOR SETUP:

LOCA in progress.

ANO-2-JPM-NRC-H2003 (S2) PAGE 3 OF 7 JOB PERFORMANCE MEASURE INITIATING CUE:

The SM/CRS directs you to place 2M055B Hydrogen Recombiner in service using OP-2104.044 starting with step 9.2.

START TIME:

PERFORMANCE CHECKLIST STANDARD (Circle One)

1. N/A SAT UNSAT Verify Power Out switch in OFF. Verifies Power Out switch in OFF (Step or down position.

9.2.1)

2. Verify Power Adjust On 2C184 Verifies Power Adjust N/A SAT UNSAT (Step potentiometer (2POTR-6891) potentiometer (2POTR-6891) set 9.2.2) set to zero (000): to zero (000).
3. Verify H2 Recombiner #2 supply Contacts a NLO to verify that N/A SAT UNSAT (Step breaker (2B-633) closed: breaker 2B-633 is closed.

9.2.3)

Examiner Cue:

When contacted as NLO report that 2B-633 breaker is closed.

4. Check white Power Available On 2C184, checks white power N/A SAT UNSAT light illuminated. light illuminated.

(Step 9.2.4)

(C) 5. Place Power Out switch to ON. On 2C184, placed power out N/A SAT UNSAT (Step switch in the ON or up position.

9.2.5)

(C) 6. Turn Power Adjust On 2C184, turned 2POTR-6891 N/A SAT UNSAT (Step potentiometer (2POTR-6891) clockwise until ~ 5 KW on 2WI-9.2.6) clockwise to raise power to 5 6893.

KW as indicated on power meter (2WI-6893).

7. Using Power Adjust On 2C184, monitored power meter N/A SAT UNSAT (Step potentiometer (2POTR-6891), to ensure power is maintained ~ 5 9.2.7) maintain power at 5 KW for KW.

10 minutes.

Examiner Cue:

When comfortable with applicant performance instruct them 10 min have elapsed.

(C) 8. Using Power Adjust On 2C184, turned 2POTR-6891 N/A SAT UNSAT (Step potentiometer (2POTR-6891), clockwise until ~ 10 KW on 2WI-9.2.8) raise power to 10 KW 6893.

(2WI-6893).

ANO-2-JPM-NRC-H2003 (S2) PAGE 4 OF 7 JOB PERFORMANCE MEASURE

9. Using Power Adjust On 2C184, monitored power meter N/A SAT UNSAT (Step potentiometer (2POTR-6891), to ensure power is maintained ~

9.2.9) maintain power at 10 KW 10 KW.

(2WI-6893) for 10 minutes.

Examiner Cue:

When comfortable with applicant performance instruct them 10 min have elapsed.

10. Determine Recombiner This attachment will not be N/A SAT UNSAT (Step Temperature Correction Factor completed by the examinee.

9.2.10) using Attachment C.

Examiner Cue:

Attachment C has been completed and will be maintained by another operator.

(C) 11. Using Power Adjust On 2C184, turned 2POTR-6891 N/A SAT UNSAT (Step potentiometer (2POTR-6891), clockwise until ~ 20 KW on 2WI-9.2.11) raise power to 20 KW 6893.

(2WI-6893).

12. Using Power Adjust On 2C184, monitored power meter N/A SAT UNSAT (Step potentiometer (2POTR-6891), to ensure power is maintained ~

9.2.12) maintain power at 20 KW 20 KW.

(2WI-6893) for 5 minutes.

Examiner Cue:

When comfortable with applicant performance instruct them 5 min have elapsed.

Examiner Note: acceptable numbers in the standards based on validation conditions check actual simulator conditions are similar.

Attachment F is at the back of this JPM.

(C) 13. Determine required Recombiner Examinee determines required N/A SAT UNSAT (Step power using Attachment F of Recombiner power is ________

9.2.13) this procedure based on KW from Attachment F.

Pre-LOCA CNTMT temperature and Post-LOCA CNTMT Acceptable value is 53 to 55 KW pressure.

Examiner Note: Post-LOCA pressure is displayed in the simulator and should be ~

17.4 psia.

(C) 14. Using Power Adjust Examinee raises power on 2WI- N/A SAT UNSAT (Step potentiometer (2POTR-6891), 6893 using 2POTR-6891 to value 9.2.14) raise power (2WI-6893) to value determined in above step.

determined in step 9.2.13.

Examiner Note: End JPM after examinee has raised power to the Attachment F value.

END Stop time: _______________

ANO-2-JPM-NRC-H2003 (S2) PAGE 5 OF 7 JOB PERFORMANCE MEASURE Procedure 2104.044 Attachment F Recombiner power requirement PRE-LOCA CNTMT TEMPERATURE 76 o

60 F o

90 F o

72 120 F REQUIRED RECOMBINER POWER (KW) 68 64 60 56 52 48 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 POST-LOCA CNTMT PRESSURE (PSIA)

ANO-2-JPM-NRC-H2003 (S2) PAGE 6 OF 7 JOB PERFORMANCE MEASURE EXAMINERS COPY INITIAL CONDITIONS:

You are responsible for any applicable annunciators during the performance of this task. All annunciators that are not applicable to this task will be performed by another operator.

A LOCA has been in progress for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

Containment Hydrogen is >1%

TSC has directed to start one hydrogen recombiner Pre-LOCA containment temperature was 120 degrees F INITIATING CUE:

The SM/CRS directs you to place 2M-55B Hydrogen Recombiner in service using OP-2104.044 starting with step 9.2.

ANO-2-JPM-NRC-H2003 (S2) PAGE 7 OF 7 JOB PERFORMANCE MEASURE EXAMINEES COPY INITIAL CONDITIONS:

You are responsible for any applicable annunciators during the performance of this task. All annunciators that are not applicable to this task will be performed by another operator.

A LOCA has been in progress for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

Containment Hydrogen is >1%

TSC has directed to start one hydrogen recombiner Pre-LOCA containment temperature was 120 degrees F INITIATING CUE:

The SM/CRS directs you to place 2M-55B Hydrogen Recombiner in service using OP-2104.044 starting with step 9.2.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 19 of 54 2104.044 CONTAINMENT HYDROGEN CONTROL OPERATIONS CHANGE: 037 9.2 Perform the following to start Hydrogen Recombiner (2M-55B):

9.2.1 Verify Power Out switch in OFF.

9.2.2 Verify Power Adjust potentiometer (2POTR-6891) set to zero (ØØØ):

9.2.3 Verify H2 Recombiner #2 Supply Breaker (2B-633) closed:

9.2.4 Check white Power Available light illuminated.

9.2.5 Place Power Out switch to ON.

9.2.6 Turn Power Adjust potentiometer (2POTR-6891) clockwise to raise power to 5 KW (2WI-6893).

9.2.7 Using Power Adjust potentiometer (2POTR-6891),

maintain power at 5 KW for 10 minutes.

9.2.8 Using Power Adjust potentiometer (2POTR-6891),

raise power to 10 KW (2WI-6893).

9.2.9 Using Power Adjust potentiometer (2POTR-6891),

maintain power at 10 KW (2WI-6893) for 10 minutes.

9.2.10 Determine Recombiner Temperature Correction Factor using Attachment C of this procedure.

9.2.11 Using Power Adjust potentiometer (2POTR-6891),

raise power to 20 KW (2WI-6893).

9.2.12 Using Power Adjust potentiometer (2POTR-6891),

maintain power at 20 KW (2WI-6893) for 5 minutes.

9.2.13 Determine required Recombiner power using Attachment F of this procedure based on Pre-LOCA CNTMT temperature and Post-LOCA CNTMT pressure.

9.2.14 Using Power Adjust potentiometer (2POTR-6891),

raise power (2WI-6893) to value determined in step 9.2.13.

Step 9.2 continued on next page.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 20 of 54 2104.044 CONTAINMENT HYDROGEN CONTROL OPERATIONS CHANGE: 037 CAUTION Do NOT exceed maximum Recombiner output power of 75 KW or functional thermocouple temperature of 1400°F.

If temperature difference between any two temperature readings exceeds 50°F during steady state operation, the temperatures should NOT be used as an indication of proper operation.

CRITICAL STEP 9.2.15 Perform the following:

A. Monitor functional thermocouple temperatures (2TI-6889) every 30 minutes B. Record functional thermocouple temperatures (2TI-6889) on Attachment C of this procedure.

C. IF 1400°F is exceeded on any functional thermocouple (2TI-6889) on 2C184, THEN perform the following:

1. Reduce Recombiner power.
2. Investigate cause.
3. Initiate Condition Report.

NOTE A power change of 1 KW will change temperature approximately 18°F.

9.2.16 WHEN 2M-55B has operated for greater than or equal to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, THEN perform the following to verify proper operation of 2M-55B:

Check H2 concentration being reduced or maintained at low concentration.

Verify Recombiner maintaining power at required value.

Verify Recombiner power less than 75 KW.

Check average corrected temperature per Attachment C of this procedure is between 1225°F and 1400°F.

9.2.17 IF H2 concentration has risen by greater than 0.5% in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OR H2 concentration exceeds 3.0%,

THEN raise Recombiner power 4 KW above previous setting.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

PAGE: 32 of 54 2104.044 CONTAINMENT HYDROGEN CONTROL OPERATIONS CHANGE: 037 ATTACHMENT F PAGE 1 OF 1 RECOMBINER POWER REQUIREMENT PRE-LOCA CNTMT TEMPERATURE 76 o

60 F o

90 F o

72 120 F REQUIRED RECOMBINER POWER (KW) 68 64 60 56 52 48 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 POST-LOCA CNTMT PRESSURE (PSIA)

ANO-2-JPM-NRC-CVCS2 (S3) PAGE 1 OF 6 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 008 DATE:

SYSTEM/DUTY AREA: Chemical and Volume Control System TASK: Perform Emergency Boration JTA#: ANO2-RO-EOPAOP-OFFNORM-193 Alternate Path Yes: X No: Time Critical Yes: No: X KA VALUE RO: 3.9 SRO: 3.7 KA

REFERENCE:

004 A4.07 APPROVED FOR ADMINISTRATION TO: RO: X SRO: X TASK LOCATION: INSIDE CR: X OUTSIDE CR: BOTH:

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform LAB:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: LAB:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 6 Minutes REFERENCE(S): OP-2203.032 Emergency Boration AOP EXAMINEE'S NAME: Badge #

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Stop Total Time Time Time

ANO-2-JPM-NRC-CVCS2 (S3) PAGE 2 OF 6 JOB PERFORMANCE MEASURE INITIAL CONDITIONS Mode 3 A Shutdown Margin is calculated following a reactor trip Shutdown Margin is found to be less than required TASK STANDARD:

Established boration of greater than or equal to 40 gallons per minute of boric acid solution.

At least one BAM pump started and Emergency Borate from BAM pumps valve (2CV-4916-

2) opened.

TASK PERFORMANCE AIDS:

OP-2203.032 Steps 2 through 6 SIMULATOR SETUP:

Select desired Mode 3 IC for this JPM.

Set each of the following to occur on a trigger with a 5 second time delay:

CV48731 = .75 (VCT outlet),

DO_HS_4873_G (VCT outlet green light) = OFF DO_HS_4873_R (VCT outlet red light) = OFF.

Set the trigger event to hg4g8731 (VCT green light coming on).

EXAMINER NOTES:

This is an alternate success path JPM.

ANO-2-JPM-NRC-CVCS2 (S3) PAGE 3 OF 6 JOB PERFORMANCE MEASURE INITIATING CUE:

The SM/CRS directs you to initiate emergency boration using BAMT Gravity Feed to Charging pump suction beginning with OP 2203.032, Emergency Boration, Step 2.

START TIME:

PERFORMANCE CHECKLIST STANDARD (Circle One)

1. Verify at least ONE Charging On panel 2C09, verified CCP(s) N/A SAT UNSAT pump running with flow greater running.

(Step

2) than 40 gpm.

Observed red light ON; green light OFF above at least one of the following handswitch(es):

2HS-4832-1, "A" CCP 2HS-4852-1, "C" CCP (red) 2HS-4853-2, "C" CCP (green) 2HS-4842-2, "B" CCP Observed flow greater than 40 gpm on Charging Header Flow (2FIS-4863).

2. Align Charging pump suction to On panel 2C09, opened BAMT N/A SAT UNSAT at least ONE of the following gravity feed valves 2CV-4920-1 sources: and/or 2CV-4921-1 (Step A. Gravity Feed: Observed red light ON and green 3.a) light OFF above handswitch(es):
1) Open at least ONE BAM Tank Gravity 2HS-4920-1 for 2CV-4920-1 Feed valve: 2HS-4921-1 for 2CV-4921-1 2CV-4920-1 2CV-4921-1 EXAMINERS NOTE:

Step 3.b and 3.c are not applicable.

In the following step the VCT outlet valve will NOT close requiring an alternate success path.

3. Close VCT Outlet valve On panel 2C09, observed that N/A SAT UNSAT (2CV-4873-1). 2CV-4873-1 did NOT go closed.

(Step 4)

Observed green light OFF; red light OFF above VCT Outlet valve handswitch (2HS-4873-1).

Examiner Note: 2CV-4873-1 breaker will trip causing the lights to go out.

ANO-2-JPM-NRC-CVCS2 (S3) PAGE 4 OF 6 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARD (Circle One)

(C) 4. IF VCT Outlet valve does NOT On panel 2C09, started 2P39A N/A SAT UNSAT close, and/or THEN perform the following: 2P39B.

(Step 4.a) Start at least ONE BAM pump.

Observed RED light ON above the BAM pump started, 2HS-4919-2 (2P39A) or 2HS-4910-2 (2P39B).

(C) 5. Open Emergency Borate From On panel 2C09, opened N/A SAT UNSAT BAM Pumps valve 2CV-4916-2.

(Step 4.b) (2CV-4916-2).

Observed red light ON; green light OFF above Emergency borate valve, 2CV-4916-2.

6. Verify Boric Acid Makeup Flow On panel 2C09, verified N/A SAT UNSAT Control valve (2CV-4926) 2CV-4926 closed.

(Step 4.c) closed.

Observed green light ON; red light OFF above Boric Acid Makeup Flow Controller (2FIC-4926).

7. Check Reactor Makeup Water On panel 2C09, verified N/A SAT UNSAT Flow Control valve (2CV-4927) 2CV-4927 closed.

(Step

5) closed.

Observed green light ON; red light OFF above Reactor Makeup Water Flow Controller (2FIC-4927).

(C) 8. Check charging header flow On panel 2C09 (upright portion), N/A SAT UNSAT indicator (2FIS-4863) greater observed flow greater than 40 (Step

6) than 40 gpm. gpm on Charging Header Flow indicator (2FIS-4863).

END STOP TIME:

ANO-2-JPM-NRC-CVCS2 (S3) PAGE 5 OF 6 JOB PERFORMANCE MEASURE EXAMINERS COPY INITIAL CONDITIONS:

You are responsible for any applicable annunciators during the performance of this task.

All annunciators that are not applicable to this task will be performed by another operator.

Mode 3 A Shutdown Margin is calculated following a reactor trip Shutdown Margin is found to be less than required INITIATING CUE:

The SM/CRS directs you to initiate emergency boration using BAMT Gravity Feed to Charging pump suction beginning with OP 2203.032, Emergency Boration, Step 2.

ANO-2-JPM-NRC-CVCS2 (S3) PAGE 6 OF 6 JOB PERFORMANCE MEASURE EXAMINEES COPY INITIAL CONDITIONS:

You are responsible for any applicable annunciators during the performance of this task.

All annunciators that are not applicable to this task will be performed by another operator.

Mode 3 A Shutdown Margin is calculated following a reactor trip Shutdown Margin is found to be less than required INITIATING CUE:

The SM/CRS directs you to initiate emergency boration using BAMT Gravity Feed to Charging pump suction beginning with OP 2203.032, Emergency Boration, Step 2.

INSTRUCTIONS CONTINGENCY ACTIONS NOTE Steps marked with (*) are continuous action steps.

1. Refer to 1903.010, Emergency Action Level Classification.
2. Verify at least ONE Charging pump running 2. Perform the following:

with flow greater than or equal to 40 gpm.

A. IF in Mode 1 or 2, THEN perform the following:

1) Trip Reactor.
2) GO TO 2202.001, Standard Post Trip Actions.

B. IF in Mode 3, 4, 5, or 6, THEN perform the following:

1) Verify TCBs open.
2) GO TO Step 8.

PROC NO TITLE REVISION PAGE 2203.032 EMERGENCY BORATION 011 2 of 14

INSTRUCTIONS CONTINGENCY ACTIONS

3. Align Charging pump suction to at least ONE of the following sources:

A. Gravity Feed:

1) Open at least ONE BAM Tank Gravity Feed valve:

2CV-4920-1 2CV-4921-1 B. Boric Acid Makeup:

1) Start at least ONE BAM pump.
2) Open Emergency Borate From BAM Pumps valve (2CV-4916-2).
3) Verify Boric Acid Makeup Flow Control valve (2CV-4926) closed.

C. RWT to Charging pumps:

1) Open Charging Pump Suction Source From RWT valve (2CV-4950-2).
4. Close VCT Outlet valve (2CV-4873-1). 4. IF VCT Outlet valve does NOT close, THEN perform the following:

A. Start at least ONE BAM pump.

B. Open Emergency Borate From BAM Pumps valve (2CV-4916-2).

C. Verify Boric Acid Makeup Flow Control valve (2CV-4926) closed.

5. Check Reactor Makeup Water Flow 5. IF 2CV-4927 NOT closed, Control valve (2CV-4927) closed. THEN close VCT Make Up Isolation valve (2CV-4941-2).

PROC NO TITLE REVISION PAGE 2203.032 EMERGENCY BORATION 011 3 of 14

INSTRUCTIONS CONTINGENCY ACTIONS

6. Check Charging Header Flow indicator 6. GO TO Step 2.

(2FIS-4863) greater than or equal to 40 gpm.

7. GO TO Step 15.
8. Check RCS pressure less than 1265 psia. 8. Reduce RCS pressure as follows:

A. Reset Low PZR Press Setpoints during pressure reduction.

B. Commence RCS pressure reduction to less than 1265 psia as follows:

1) IF RCPs running, THEN use Normal PZR spray.
2) IF ALL RCPs stopped, THEN open PZR High Point Vent To Quench Tank valves:

2SV-4636-1 2SV-4636-2 2SV-4669-1 C. Place ALL PZR Heaters in OFF.

D. Maintain RCS MTS greater than 30°F.

9. Align ONE HPSI Train as follows:

A. Verify RWT level greater than 7.5%.

B. Verify associated RWT Outlet valve open:

2CV-5630-1 2CV-5631-2 C. Start HPSI pump on recirc, refer to 2104.039, HPSI System Operation.

PROC NO TITLE REVISION PAGE 2203.032 EMERGENCY BORATION 011 4 of 14

INSTRUCTIONS CONTINGENCY ACTIONS

10. Check SDC secured. 10. Control RCS inventory as follows:

A. IF desired, THEN control RCS inventory with SDC pump Mini Recirc valves as follows:

1) Open running SDC pump Mini Recirc to RWT valve:

PUMP RECIRC VALVE 2P60A 2CV-5123-1 2P60B 2CV-5124-1 2P35A 2CV-5673-1 2P35B 2CV-5672-1

2) GO TO Step 13.

B. At SM discretion, place Letdown in service as follows:

1) Place Letdown in service using Attachment A, Placing Letdown In Service.
2) Place VCT Bypass To BMS selector switch (2CV-4826) to BMS.
3) Locally place "VACUUM DEGASIFIER INLET" valve (2CV-2211) to HOLD UP TANK.
4) Place Degas selector switch (2HS-2221) to HOLD UP TANK.
5) GO TO Step 13.

(Step 10 continued on next page)

PROC NO TITLE REVISION PAGE 2203.032 EMERGENCY BORATION 011 5 of 14

INSTRUCTIONS CONTINGENCY ACTIONS

10. (continued)

C. IF desired, THEN verify SDC purification in service using 2104.004, Shutdown Cooling System as follows:

1) Place VCT Bypass To BMS selector switch (2CV-4826) to BMS.
2) Locally place "VACUUM DEGASIFIER INLET" valve (2CV-2211) to HOLD UP TANK.
3) Place Degas selector switch (2HS-2221) to HOLD UP TANK.
4) Throttle Letdown Pressure controller (2PIC-4812) to maintain RCS inventory.
5) GO TO Step 13.

CAUTION Temperature limit downstream of Letdown HX is 150°F.

  • 11. Check RCS temperature greater than *11. IF RCS temperature less than 450°F 450°F. AND at SM discretion, THEN place Letdown in service as follows:

A. Place Letdown in service using Attachment A, Placing Letdown In Service.

B. WHEN Letdown in service, THEN GO TO Step 13.

PROC NO TITLE REVISION PAGE 2203.032 EMERGENCY BORATION 011 6 of 14

INSTRUCTIONS CONTINGENCY ACTIONS NOTE RCS Tech Spec cooldown rate limit is 100°F/HR (constant) ,

NOT to exceed 50°F in any 1/2 hour period (step),

(TS 3.4.9.1 adjusted for instrument uncertainty)

  • 12. Commence RCS cooldown as necessary to allow a makeup rate greater than or equal to 40 gpm as follows:

A. Verify a maximum of ONE RCP running in EACH loop.

B. IF RCP 2P32A or 2P32B stopped, THEN verify associated PZR Spray valve in MANUAL and closed:

2CV-4651 2CV-4652 C. Reset Low PZR Pressure and Low SG pressure setpoints during cooldown and depressurization.

D. Check IA pressure greater than D. IF IA NOT available, 65 psig. THEN perform the following:

1) Use SDBCS Upstream ADVs or Upstream ADV Isolation MOVs.
2) GO TO Step 12.K.

(Step 12 continued on next page)

PROC NO TITLE REVISION PAGE 2203.032 EMERGENCY BORATION 011 7 of 14

INSTRUCTIONS CONTINGENCY ACTIONS

12. (continued)

E. Check MSIS reset. E. IF time permits, THEN reset MSIS using 2202.010, Attachment 14, MSIS Reset.

F. Check MSIVs open. F. Perform the following:

1) IF MSIS reset, THEN perform following:

a) Open MSIV Bypass valves:

2CV-1040-1 2CV-1090-2 b) WHEN SG and Main Steam pressure equalize within 50 psi, THEN open MSIVs:

MSIV A MSIV B 2SV-1010-1A 2SV-1060-1A 2SV-1010-2A 2SV-1060-2A 2SV-1011 2SV-1066

2) IF MSIVs can NOT be opened, THEN perform the following:

a) Use SDBCS Upstream ADVs or Upstream ADV Isolation MOVs.

b) GO TO Step 12.K.

(Step 12 continued on next page)

PROC NO TITLE REVISION PAGE 2203.032 EMERGENCY BORATION 011 8 of 14

INSTRUCTIONS CONTINGENCY ACTIONS

12. (continued)

G. Check "SDBCS CONDENSER G. Perform the following:

INTERLOCK" annunciator (2K02-B14) clear. 1) Control RCS cooldown rate with SDBCS ADVs or Upstream ADV Isolation MOVs.

2) GO TO Step 12.K.

H. Control RCS cooldown rate with SDBCS Bypass valves.

I. Check at least ONE Condensate pump I. IF power available, running. THEN start ONE Condensate pump using 2106.016, Condensate and Feedwater Operations.

J. Check SU/BD DI to EFW Pump Suction J. IF EFW or AFW pump running AND valve (2EFW-0706) open. SU/BD DI in service, THEN locally unlock and open "SU/BD DI TO EFWP SUCT" valve (2EFW-0706).

K. Monitor RCS cooldown rate as follows:

1) Plot RCS pressure verses temperature using 2202.010 Attachment 1, P-T Limits,
2) Record RCS TC and PZR temperature using 2202.010 Attachment 8, RCS Cooldown Table every 15 minutes.

PROC NO TITLE REVISION PAGE 2203.032 EMERGENCY BORATION 011 9 of 14

INSTRUCTIONS CONTINGENCY ACTIONS

13. Establish HPSI flow as follows:

A. Check Train A being used AND throttle A. Throttle ONE HPSI Train B ONE HPSI Injection MOV to maintain Injection MOV to maintain PZR level:

PZR level:

2CV-5016-2 2CV-5015-1 2CV-5036-2 2CV-5035-1 2CV-5056-2 2CV-5055-1 2CV-5076-2 2CV-5075-1 B. Maintain HPSI flow to RCS greater than or equal to 40 gpm as indicated on SPDS.

  • 14. Maintain RCS pressure less than 1265 psia as follows:

A. Check RCPs running AND control A. Control RCS pressure with the RCS pressure with the following: following:

Normal Spray using 2202.010 1) Letdown Attachment 48, RCS Pressure Control. 2) Cooldown rate Cooldown rate 3) Throttling HPSI Throttling HPSI Letdown PROC NO TITLE REVISION PAGE 2203.032 EMERGENCY BORATION 011 10 of 14

ANO-2-JPM-NRC-EFW01 (S4) PAGE 1 OF 8 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 017 DATE:

SYSTEM/DUTY AREA: Emergency Feedwater System TASK: Shutdown EFW Train A with EFAS Signal Present JTA#: ANO2-RO-EFW-NORM-20 Alternate Path Yes: No: X Time Critical Yes: No: X KA VALUE RO: 3.9 SRO: 4.2 KA

REFERENCE:

061 A1.01 APPROVED FOR ADMINISTRATION TO: RO: X SRO: X TASK LOCATION: INSIDE CR: X OUTSIDE CR: BOTH:

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform LAB:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: LAB:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 15 Minutes REFERENCE(S): OP 2106.006, Emergency Feedwater System Operations EXAMINEE'S NAME: Badge #:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Stop Total Time Time Time

ANO-2-JPM-NRC-EFW01 (S4) PAGE 2 OF 8 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

Mode 3 Post Reactor trip EFAS #1 and #2 have actuated Chemistry notified to sample Main Steam to accommodate dose calculations TASK STANDARD:

Overrode 2P-7B EFW pump Flow Control valves and established sufficient flow that raised both Steam Generator levels.

Reset both trains EFAS actuation then secured 2P-7A EFW pump.

Ensured 2P-7A EFW pump Discharge valves were aligned for the Mode 3 plant configuration.

TASK PERFORMANCE AIDS:

OP 2106.006, Emergency Feedwater Operations, Section 13.0 SIMULATOR INITIAL CONDITIONS:

Mode 3 after RX trip, EFAS 1 & EFAS 2 actuated.

Ensure generator levels are cycling based on SG level setpoints.

ANO-2-JPM-NRC-EFW01 (S4) PAGE 3 OF 8 JOB PERFORMANCE MEASURE INITIATING CUE:

The CRS directs you to perform OP 2106.006, Emergency Feedwater System Operations, Section 13, Reset EFAS and Establishing Feed with 2P-7B, beginning with step 13.2.

START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

1. Verify EFW pump 2P-7B On panel 2C17, verified 2P7B N/A SAT UNSAT (2HS-0710A-1) running. running.

(Step 13.2)

Observed green light OFF; red light ON above handswitch.

Observed 2P7B discharge pressure > 950 psig on EFW-B Disch (2PIS-0710-1).

(C) 2. Reset 2P-7B flow control valve On panel 2C17, rotated N/A SAT UNSAT relays by placing handswitches handswitches 2HS-1025B-1 and (Step 13.3) to EFAS OVERRIDE: 2HS-1075B-1 to the "EFAS OVERRIDE" position.

2HS-1025B-1 2HS-1075B-1 (C) 3. Override 2P-7B Discharge On panel 2C17, placed N/A SAT UNSAT valves by placing handswitches for 2CV-1036-2 and (Step 13.4) handswitches to OPEN: 2CV-1038-2 to OPEN and released.

2CV-1038-2 (2HS-1038-2)

Observed green light OFF; red 2CV-1036-2 (2HS-1036-2) light ON over handswitches for 2CV-1036-2 and 2CV-1038-2 EXAMINER'S NOTE:

Flow rate is discretionary and a function of RCS temperature and pressure.

(C) 4. Throttle open the following On panel 2C17, adjusted N/A SAT UNSAT valves to restore S/G levels to handswitches for 2CV-1025-1 and (Step approximately 60%: 2CV-1075-1 to raise S/G levels.

13.5)

Observed green lights ON; red For A S/G, 2CV-1025-1 lights ON and movement on the (2HS-1025A-1) "Percent Open" meters over For B S/G, 2CV-1075-1 handswitches.

(2HS-1075A-1)

ANO-2-JPM-NRC-EFW01 (S4) PAGE 4 OF 8 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

5. Monitor RCS temperature and Used SPDS, Plant Computer, or N/A SAT UNSAT pressure during S/G refill. control boards indications to (Step monitor RCS temperature and 13.6) PZR pressure.
6. Verify feed flow indicated to On panel 2C17, verified flow N/A SAT UNSAT BOTH S/Gs: appropriate to restore SG levels.

(Step 13.7)

For A S/G, (2FIS-0710-1) Observed flow on EFW flow indicators 2FIS-0710-1 and For B S/G, (2FIS-0717-1) 2FIS-0717-1.

EXAMINERS NOTE:

The simulator only has 2C40 hardware. The reset will be accomplished in 2C40 only.

(C) 7. WHEN S/G levels above On panel 2C40-7 when S/G levels N/A SAT UNSAT EFAS reset setpoint, are above EFAS setpoint (~ 23 (Step 13.8) THEN depress "EFAS Lockout  %) depressed reset pushbuttons Relays Reset" pushbuttons: for EFAS-1and EFAS-2.

In 2C39 Observed Red light ON above the In 2C40 EFAS-1 pushbutton and above the EFAS-2 pushbutton.

Examiner Cue:

If asked inform applicant that 2C39 indicates the same as 2C40.

(C) 8. Stop 2P-7A by placing Steam Placed 2HS-0340-2 to CLOSE. N/A SAT UNSAT Supply (2HS-0340-2) to (Step CLOSE. Observed green light ON, red 13.9) light OFF above handswitch for 2CV-0340-2 and 2P-7A slowing down.

9. Record time Steam Supply Requested that the CRS or N/A SAT UNSAT 2CV-0340-2 closed in Station another operator record time (Step 13.10) log. 2CV-0340-2 closed in Station Log.

Examiner Cue:

Inform applicant another operator has recorded the closed time in the station log.

ANO-2-JPM-NRC-EFW01 (S4) PAGE 5 OF 8 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

10. Verify 2P-7A Discharge valves On panel 2C16, placed the N/A SAT UNSAT OPEN: handswitches for 2CV-1037-1 and (Step 13.11) 2CV-1039-1 to OPEN.

2CV-1037-1 (2HS-1037-1) 2CV-1039-1 (2HS-1039-1) AND/OR On panel 2C16, observed red light ON and green light OFF above handswitches for 2CV-1037-1 and 2CV-1039-1.

11. Perform the following to ensure On panel 2C16, placed the N/A SAT UNSAT positive seating of 2P-7A handswitches for 2CV-1026-2 and (Step 13.12) Discharge Stop Checks to 2CV-1076-2 to OPEN.

S/Gs 2EFW-7A and 2EFW-8A: AND/OR (Step On panel 2C16, observed red Verify 2P-7A Discharge valves 13.12.1) light ON and green light OFF OPEN:

above handswitches for 2CV-1026-2 and 2CV-1076-2.

2CV-1026-2 (2HS-1026-2) 2CV-1076-2 (2HS-1076-2)

(C) 12. CLOSE 2CV-1026-2 On panel 2C16, placed the N/A SAT UNSAT (2HS-1026-2). handswitch for 2CV-1026-2 to (Step 13.12.2) CLOSE.

AND On panel 2C16, observed red light OFF and green light ON above handswitch for 2CV-1026-2.

(C) 13. CLOSE 2CV-1076-2 On panel 2C16, placed the N/A SAT UNSAT (2HS-1076-2). handswitch for 2CV-1076-2 to (Step 13.12.3) CLOSE.

AND On panel 2C16, observed red light OFF and green light ON above handswitch for 2CV-1076-2.

END

ANO-2-JPM-NRC-EFW01 (S4) PAGE 6 OF 8 JOB PERFORMANCE MEASURE STOP TIME:

ANO-2-JPM-NRC-EFW01 (S4) PAGE 7 OF 8 JOB PERFORMANCE MEASURE EXAMINERS COPY INITIAL CONDITIONS:

You are responsible for any applicable annunciators during the performance of this task.

All annunciators that are not applicable to this task will be performed by another operator.

Mode 3 Post Reactor trip EFAS #1 and #2 have actuated Chemistry notified to sample Main Steam to accommodate dose calculations INITIATING CUE:

The CRS directs you to perform OP 2106.006, Emergency Feedwater System Operations, Section 13, Reset EFAS and Establishing Feed with 2P-7B, beginning with step 13.2.

ANO-2-JPM-NRC-EFW01 (S4) PAGE 8 OF 8 JOB PERFORMANCE MEASURE EXAMINEES COPY INITIAL CONDITIONS:

You are responsible for any applicable annunciators during the performance of this task.

All annunciators that are not applicable to this task will be performed by another operator.

Mode 3 Post Reactor trip EFAS #1 and #2 have actuated Chemistry notified to sample Main Steam to accommodate dose calculations INITIATING CUE:

The CRS directs you to perform OP 2106.006, Emergency Feedwater System Operations, Section 13, Reset EFAS and Establishing Feed with 2P-7B, beginning with step 13.2.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 36 of 251 2106.006 EMERGENCY FEEDWATER SYSTEM OPERATIONS CHANGE: 088 13.0 RESETTING EFAS AND ESTABLISHING FEED WITH 2P-7B 13.1 Notify Chemistry to perform the following:

Take required EFW samples. (CR-ANO-2-1999-0324)

Sample Main Steam as needed to accommodate effluent release calculations. (CR-ANO-2-1999-0324) 13.2 Verify EFW pump 2P-7B (2HS-0710A-1) running.

13.3 Reset 2P-7B flow control valve relays by placing handswitches to EFAS OVERRIDE:

2HS-1025B-1 2HS-1075B-1 13.4 Override 2P-7B Discharge valves by placing handswitches to OPEN:

2CV-1038-2 (2HS-1038-2) 2CV-1036-2 (2HS-1036-2) 13.5 Throttle open the following valves to restore S/G levels to

  • approximately 60%:

For A S/G, 2CV-1025-1 (2HS-1025A-1)

For B S/G, 2CV-1075-1 (2HS-1075A-1) 13.6 Monitor RCS temperature and pressure during S/G fill.

  • 13.7 Verify feed flow indicated to BOTH S/Gs:

For A S/G, (2FIS-0710-1)

For B S/G, (2FIS-0717-1) 13.8 WHEN S/G levels above EFAS reset setpoint, THEN depress "EFAS Lockout Relays Reset" pushbuttons:

In 2C39 In 2C40 13.9 Stop 2P-7A by placing Steam Supply (2HS-0340-2) to CLOSE.

13.10 Record time Steam Supply 2CV-0340-2 closed in Station log.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 37 of 251 2106.006 EMERGENCY FEEDWATER SYSTEM OPERATIONS CHANGE: 088 13.11 Verify 2P-7A Discharge valves OPEN:

2CV-1037-1 (2HS-1037-1) 2CV-1039-1 (2HS-1039-1) 13.12 Perform the following to ensure positive seating of 2P-7A Discharge Stop Checks to S/Gs 2EFW-7A and 2EFW-8A:

13.12.1 Verify 2P-7A Discharge valves OPEN:

2CV-1026-2 (2HS-1026-2) 2CV-1076-2 (2HS-1076-2) 13.12.2 CLOSE 2CV-1026-2 (2HS-1026-2).

13.12.3 CLOSE 2CV-1076-2 (2HS-1076-2).

13.13 Notify Chemistry of the following:

Steam Supply (2CV-0340-2) open and closed times.

Request initiation of P-7A and 2P-7A Sample Report IAW Analysis of Unit Vents (1604.015).

ANO-2-JPM-NRC-PZR008 (S5) PAGE 1 OF 7 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 000 DATE:

SYSTEM/DUTY AREA: PZR spray operation TASK: Initiate Auxiliary Spray JTA#: ANO2-RO-PZR-NORM-7 Alternate Path Yes: X No: Time Critical Yes: No: X KA VALUE RO: 3.9 SRO: 3.9 KA

REFERENCE:

010 A2.02 APPROVED FOR ADMINISTRATION TO: RO: X SRO: X TASK LOCATION: INSIDE CR: X OUTSIDE CR: BOTH:

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform CLASSROOM:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: CLASSROOM:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 15 Minutes REFERENCE(S): 2202.010 Standard Attachments, Attachment 48 RCS pressure control EXAMINEE'S NAME: Badge #:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Stop Total Time Time Time

ANO-2-JPM-NRC-PZR008 (S5) PAGE 2 OF 7 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

Mode 3 Post Reactor Trip No RCPs running The Steam Dump Bypass Control System has failed RCS Pressure >2250psia and slowly rising.

TASK STANDARD:

Determined Auxiliary Spray valve failed, and aligned RCS High point vents to lower RCS pressure.

Lowered RCS pressure within the band of 1800 to 2250 pisa and PZR code safety did not lift (~2500 psia).

TASK PERFORMANCE AIDS:

2202.010, Standard Attachment 48, RCS pressure control.

SIMULATOR SETUP:

Mode 3, All RCPs secured Pzr Pressure rising.

Steam dump emergency off actuated.

On Trigger 2 CV48242 value = 0, DO_HS_4824_G = off, and DO_HS_4824_R = off T2 set to HG4R8242 EXAMINER'S NOTES:

ANO-2-JPM-NRC-PZR008 (S5) PAGE 3 OF 7 JOB PERFORMANCE MEASURE INITIATING CUE:

The CRS directs you to establish Auxiliary Spray flow to control Pressurizer pressure to 2150 to 2250 psia using 2202.010 Standard Attachment 48 starting Step 1.D.

START Time:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 1. IF desired to use AUXILIARY On SPDS determined that CET N/A SAT UNSAT (Step Spray, MTS was greater than 30 1.D.1) THEN perform the following: degrees.

  • 1) Verify RCS MTS greater than 30 degrees.
2. Verify at least ONE Charging On Panel 2C09, verified at least N/A SAT UNSAT (Step Pump running one Charging Pump (2P36A, B, 1.D.2) C) running by observing red light ON above appropriate handswitch:

2HS-4832-1 2P36A 2HS-4852-1 2P36C 2HS-4853-2 2P36C 2HS-4842-2 2P36B 3 Close Regen HX to RCP B/C On panel 2C09, placed N/A SAT UNSAT (Step valves: handswitch for 2CV-4827-2 and 1.D.3) 2CV-4831-2 in CLOSE.

2CV-4827-2 2CV-4831-2 Observed Green light ON; Red light OFF above handswitches for 2CV-4827-2 and 2CV-4831-2.

Procedure Note:

PZR Spray Block valves 2CV-4653 and 2CV-4655 are de-energized due to degraded power supply cables.

4. Verify PZR Spray On Panel 2C09, observed N/A SAT UNSAT (Step (2CV-4651/2CV-4652) or PZR Green light ON, Red light OFF 1.D.4) Spray Isolation valves for following valves:

(2HS-4655/2HS-4653) closed. 2CV-4651 AND 2CV-4652 OR 2CV-4655 AND 2CV-4653.

Examiner Note: the following step will start the alternate path portion of this JPM.

ANO-2-JPM-NRC-PZR008 (S5) PAGE 4 OF 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 5. Throttle Aux Spray valve On Panel 2C09, placed N/A SAT UNSAT (Step (2CV-4824-2) as necessary. handswitch for Aux Spray Valve 1.D.5) (2CV-4824-2) to OPEN.

Examiner Cue: If applicant informs CRS of 2CV-4824-2 Observed Red light OFF, Green failure direct them to control light OFF due to breaker trip.

RCS pressure 2150 to 2250 psia. Critical Poirtion:

Monitored RCS pressure and determined pressure is not lowering.

Examiner Note: The applicant should transition to step 3 of attachment 48.

(C) 6. IF unable to control RCS Determined that SDBCS valves N/A SAT UNSAT (Step pressure using heater and are not available from initial

3) spray methods, conditions THEN utilize EITHER of the following for RCS pressure AND control:

Secondary heat removal On panel 2C336-1 or 2C336-2, using 2105.008 Exhibit 3, Opened 2 high point vent valves SDBCS Emergency to lower RCS pressure in one of Operation. the following combinations:

Cycle High Point Vent Valves as needed, refer to Either PZR high point vent 2SV-2202.010 Attachment 1, P- 4636-1 or 2SV-4636-2 T Limits:

OR 2SV-4636-1 Either Reactor vessel head vent 2SV-4668-1 or 2SV-4668-2.

2SV-4636-2 2SV-4668-1 AND 2SV-4668-2 2SV-4669-1 Either Quench tank 2SV-4669-1 or CNTMT vent 2SV-4670-2.

2SV-4670-2

ANO-2-JPM-NRC-PZR008 (S5) PAGE 5 OF 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 7. Cycle High Point Vent On panel 2C336-1 or 2C336-2, N/A SAT UNSAT Valves as needed, refer to Closed the appropriate valves to (Step

3) 2202.010 Attachment 1, P- stop RCS pressure reduction.

T Limits: Controlled RCS pressure between 1800 and 2250 psia.

2SV-4636-1 2SV-4636-2 2SV-4668-1 2SV-4668-2 2SV-4669-1 2SV-4670-2 END STOP Time:

ANO-2-JPM-NRC-PZR008 (S5) PAGE 6 OF 7 JOB PERFORMANCE MEASURE EXAMINERS COPY INITIAL CONDITIONS:

You are responsible for any applicable annunciators during the performance of this task.

All annunciators that are not applicable to this task will be performed by another operator.

Mode 3 Post Reactor Trip No RCPs running The Steam Dump Bypass Control System has failed and will not function.

RCS Pressure rising.

INITIATING CUE:

The CRS directs you to establish Auxiliary Spray flow to control Pressurizer pressure to 2150 to 2250 psia using 2202.010 Standard Attachment 48 starting Step 1.D.

ANO-2-JPM-NRC-PZR008 (S5) PAGE 7 OF 7 JOB PERFORMANCE MEASURE EXAMINEES COPY INITIAL CONDITIONS:

You are responsible for any applicable annunciators during the performance of this task.

All annunciators that are not applicable to this task will be performed by another operator.

Mode 3 Post Reactor Trip No RCPs running The Steam Dump Bypass Control System has failed and will not function.

RCS Pressure rising.

INITIATING CUE:

The CRS directs you to establish Auxiliary Spray flow to control Pressurizer pressure to 2150 to 2250 psia using 2202.010 Standard Attachment 48 starting Step 1.D.

ATTACHMENT 48 RCS PRESSURE CONTROL Page 1 of 3 NOTE Once method of pressure control is established, this attachment is not required in hand or continuous use.

A change to the method of pressure control will require in hand or continuous use until the new pressure control method is established.

  • 1. Maintain RCS pressure with heaters and spray using one or more of the following:

A. IF desired to use PZR Pressure controller (2PIC-4626A/B),

THEN perform the following:

  • 1) Verify RCS MTS greater than 30 degrees.
2) Adjust PZR Pressure controller (2PIC-4626A/B)setpoint to desired pressure.

B. IF desired to use PZR Heaters, THEN perform the following:

1) Cycle available PZR Backup heaters as necessary.
2) Cycle available PZR Proportional heaters as necessary.

N/A C. IF desired to use NORMAL Spray, THEN perform the following:

  • 1) Verify RCS MTS greater than 30 degrees.
2) IF PZR Spray Valve (2CV-4651) to be used, THEN perform the following:

a) Verify RCP 2P32A running.

b) Place 2HS-4651B in MANUAL.

c) Cycle PZR Spray Valve (2CV-4651) using 2HS-4651A.

3) IF PZR Spray Valve (2CV-4652) to be used, THEN perform the following:

a) Verify RCP 2P32B running.

b) Place 2HS-4652B in MANUAL.

c) Cycle PZR Spray Valve (2CV-4652) using 2HS-4652A.

4) IF RCS margin to saturation greater than 160°F, THEN complete Table 1 of this attachment.

(Step 1 continued on next page)

PROC NO TITLE REVISION PAGE 2202.010 STANDARD ATTACHMENTS 022 142 of 204

ATTACHMENT 48 RCS PRESSURE CONTROL (Step 1 continued)

Page 2 of 3 D. IF desired to use AUXILIARY Spray, THEN perform the following:

  • 1) Verify RCS MTS greater than 30 degrees.
2) Verify at least ONE Charging pump running.
3) Close Regen HX to RCP B/C valves:

2CV-4827-2 2CV-4831-2 NOTE PZR Spray Block valves 2CV-4653 and 2CV-4655 are de-energized due to degraded power supply cables.

4) Verify PZR Spray (2CV-4651/2CV-4652) or PZR Spray Isolation valves (2HS-4655/2HS-4653) closed.
5) Throttle Aux Spray valve (2CV-4824-2) as necessary.
6) IF Regen HX to RCS temperature (2TI-4825) can NOT be reduced to less than 275°F, THEN perform ONE of the following:

a) Isolate Letdown to reduce temperature.

b) Complete Table 1 of this attachment.

7) IF Regen HX to RCS (2TI-4825) AND PZR water phase (2TI-4627) differential temperature greater than 200°F AND PMS is unavailable, THEN complete Table 1 of this attachment.
2. IF HPSI in service AND HPSI maintaining elevated RCS pressure, THEN recommend HPSI termination using 2202.010 Exhibit 10, HPSI Termination/Throttling Criteria.

PROC NO TITLE REVISION PAGE 2202.010 STANDARD ATTACHMENTS 022 143 of 204

ATTACHMENT 48 RCS PRESSURE CONTROL Page 3 of 3

3. IF unable to control RCS pressure using heater and spray methods, THEN utilize EITHER of the following for RCS pressure control:

Secondary heat removal using 2105.008 Exhibit 3, SDBCS Emergency Operation.

Cycle High Point Vent Valves as needed, refer to 2202.010 Attachment 1, P-T Limits:

- 2SV-4636-1

- 2SV-4636-2

- 2SV-4668-1

- 2SV-4668-2

- 2SV-4669-1

- 2SV-4670-2 TABLE 1 TIME TEMPERATURE SPRAY SPRAY (PZR WATER 2TIS-4607 VALVE VALVE PHASE) 2TIS-4608 OPENED CLOSED 2TI-4627 2TI-4825 DIFFERENCE

4. IF Table 1 filled out, THEN forward completed form to Unit 2 Systems Engineering.

Completed by Date .

Reviewed by Date .

PROC NO TITLE REVISION PAGE 2202.010 STANDARD ATTACHMENTS 022 144 of 204

ANO-2-JPM-NRC-FP02 (S6) PAGE 1 OF 7 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 000 DATE:

SYSTEM/DUTY AREA: Fire System TASK: Respond to a Fire Panel alarm.

JTA#: ANO2-RO-FPS-OFFNORM-23 Alternate Path Yes: No: X Time Critical Yes: No: X KA VALUE RO: 3.5 SRO: 3.5 KA

REFERENCE:

086 A4.02 APPROVED FOR ADMINISTRATION TO: RO: X SRO: X TASK LOCATION: INSIDE CR: X OUTSIDE CR: BOTH:

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform CLASSROOM:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: CLASSROOM:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 10 Minutes REFERENCE(S): OP-2203.009 Fire Protection system annunciator corrective active.

EXAMINEE'S NAME: Login ID:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Stop Total Time Time Time

ANO-2-JPM-NRC-FP02 (S6) PAGE 2 OF 7 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

2K-11 A9 Fire Alarm has annunciated.

TASK STANDARD:

Fire panel aligned for re-flash and 2VSF-7A/B, 2VEF-8A/B, and 2VEF-24C/D are secured.

TASK PERFORMANCE AIDS:

OP 2203.009 Fire Protection System ACA.

SIMULATOR SETUP:

FIRAL124T set to active.

Fire water flow set for trigger 1 by using code DO_CI_PO29 set to on and K11-B09 set to on.

ANO-2-JPM-NRC-FP02 (S6) PAGE 3 OF 7 JOB PERFORMANCE MEASURE INITIATING CUE:

The CRS directs, "Respond to the Fire panel alarm IAW 2203.009 section 6."

START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

Examiner Note: Give the Yellow pages to the applicant.

1. IF Fire Alarm received, On panel 2C343, observed that N/A SAT UNSAT THEN perform the following: module 1-2-4 top is in alarm for (Step 6.1 intake structure.

and Determine which module is in 6.1.1) alarm on 2C343-1, 2, or 3.

Observed red light ON, on 2C343 1-2-4 top.

(C) 2. Depress Alarm Silence switch On panel 2C343, depressed the N/A SAT UNSAT on 2C343 to enable re-flash Alarm Silence switch.

(Step capability to Fire Alarm on 6.1.2) 2K11. Not Critical:

Observed the panel alarm light flashing and recognized the alarm silence and alarm relay clicking.

3. Refer to appropriate page in Using Attachment A determined N/A SAT UNSAT Attachment A of this procedure that they should use the section (Step for alarming zone. for red fire alarm page 36 of the 6.1.3) procedure.

Examiner Note: The following are the steps from page 36 (steps for 1-2-4T) No. 2 EDG Room Red flame detector.

4. Silence alarm in accordance On panel 2C343, verified alarm N/A SAT UNSAT with Section 6.0 of this silenced.

(Step procedure.

2.1) Examiner note: The alarm has already been silenced using section 6.

5. Dispatch Operator to No. 2 Call Non-licensed operator on N/A SAT UNSAT EDG (2K4B) Room to check the radio or phone to respond to (Step for fire. the alarm.

2.2)

Examiner Cue:

State that the NLO will respond to the alarm.

Then state that there is an active fire in No. 2 EDG room

ANO-2-JPM-NRC-FP02 (S6) PAGE 4 OF 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

6. IF fire confirmed, Initiated action to have Fire or N/A SAT UNSAT THEN perform the following: Explosion AOP implemented.

(Step 2.3 and Initiate Fire or Explosion 2.3.1)

(2203.034) in conjunction with this procedure.

Examiner Cue:

State that the CRS will implement Fire or Explosion AOP.

7. Refer to Fire Plan. Initiated action to have the fire N/A SAT UNSAT plan reviewed for room 2094-Q.

(Step Examiner Cue:

2.3.2)

State that the CRS will refer to the fire plan for 2094-Q.

(C) 8. Secure Radwaste Supply fans On panel 2C22. N/A SAT UNSAT (handswitch to OFF):

(Step 2.3.3) 2HS-8401 (2VSF-7A)

Placed handswitch 2HS-2HS-8402 (2VSF-7B) 8401 for 2VSF-7A to off.

Placed handswitch 2HS-8402 for 2VSF-7B to off.

Not Critical:

Observed Green light on, Red light off for previously listed fans.

(C) 9. Verify idle Radwaste Exhaust On panel 2C22. N/A SAT UNSAT fan in PULL TO LOCK:

(Step 2.3.4) 2HS-8407 (2VEF-8A)

Placed handswitch 2HS-2HS-8408 (2VEF-8B) 8407 for 2VEF-8A to Pull to Lock.

Not Critical:

Observed Green light on, Red light off for 2VEF-8A.

(C) 10. Place running Radwaste On panel 2C22. N/A SAT UNSAT Exhaust fan in PULL TO (Step LOCK:

2.3.5) Placed handswitch 2HS-2HS-8407 (2VEF-8A) 8408 for 2VEF-8B to Pull to 2HS-8408 (2VEF-8B) Lock.

Not Critical:

Observed Green light on, Red light off for 2VEF-8B.

ANO-2-JPM-NRC-FP02 (S6) PAGE 5 OF 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

11. Locally secure #2 EDG Room Call Non-licensed operator on N/A SAT UNSAT Exhaust fans: the radio or phone to locally (Step secure the #2 EDG room fans.

2.3.6) A. Perform the following to secure 2VEF-24C at 2B62-C6:

1. Verify Local/Remote HS (2HS-8638-2S) in LOCAL.
2. Verify Local Control HS (2HS-8638-2A) in OFF.

B. Perform the following to secure 2VEF-24D at 2B62-C7:

1. Verify Local/Remote HS (2HS-8640-2S) in LOCAL.
2. Verify Local Control HS (2HS-8640-2A) in OFF.

Examiner Cue:

When requested state the NLO will place the local remote HS in local and the local control HS in off for 2VEF-24C on 2B-62-C6.

When requested state the NLO will place the local remote HS in local and the local control HS in off for 2VEF-24D on 2B-62C7.

Examiner note: When the applicant has secured the ventilation fans the JPM is complete.

END STOP TIME:

ANO-2-JPM-NRC-FP02 (S6) PAGE 6 OF 7 JOB PERFORMANCE MEASURE EXAMINERs COPY INITIAL CONDITIONS:

You are responsible for any applicable annunciators during the performance of this task.

All annunciators that are not applicable to this task will be performed by another operator.

2K-11 A9 Fire Alarm has annunciated.

INITIATING CUE:

The CRS directs, "Respond to the Fire panel alarm IAW 2203.009 using section 6."

ANO-2-JPM-NRC-FP02 (S6) PAGE 7 OF 7 JOB PERFORMANCE MEASURE EXAMINEEs COPY INITIAL CONDITIONS:

You are responsible for any applicable annunciators during the performance of this task.

All annunciators that are not applicable to this task will be performed by another operator.

2K-11 A9 Fire Alarm has annunciated.

INITIATING CUE:

The CRS directs, "Respond to the Fire panel alarm IAW 2203.009 using section 6."

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 6 of 100 2203.009 FIRE PROTECTION SYSTEM ANNUNCIATOR CORRECTIVE ACTION CHANGE: 026 6.0 INSTRUCTIONS

{4.3.3}

6.1 IF Fire Alarm received, THEN perform the following:

6.1.1 Determine which module is in alarm on 2C343-1, 2, or 3.

6.1.2 Depress Alarm Silence switch on 2C343 to enable reflash capability to Fire Alarm on 2K11.

6.1.3 Refer to appropriate page in Attachment A of this procedure for alarming zone.

6.1.4 IF firewater flow is necessary AND firewater is being used for any reason other than normal on EITHER unit (i.e., temporary cooling, etc.),

THEN isolate firewater to any other than normal component.

6.2 IF a fire occurs in any of the following locations, THEN refer to Alternate Shutdown (2203.014):

Unit 2 Control Room Cable Spreading Room Upper South Electrical Penetration Room RP Office (CA2)

Control Room Printer Room CPC Room (Old OR New) 6.3 IF Trouble Alarm received, THEN perform the following:

6.3.1 Silence alarm using Trouble Silence switch on 2C343 Alarm Control Unit.

6.3.2 Refer to Alarm Control Unit (Yellow Master Trouble Light) section of this procedure.

6.4 IF 2C343 fails, THEN implement Attachment B, Requirements for Loss of 2C343.

NOTE Physical location of specific detectors can be determined from Fire Prints (FP-2100 series).

6.5 IF specific detector number is required information, THEN refer to Open List of Fire Detector IDs database accessed from Fire Detection Database.

PROC./WORK PLAN N

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/WORK PLAN TITLE: PAGE: 7 of 100 2203.009 FIRE PROTECTION SYSTEM ANNUNCIATOR CORRECTIVE ACTION CHANGE: 026 ATTACHMENT A Page 1 of 4 2C343 ALARM INFORMATION Detection areas annotated with

  • are TRM required.

2C343-1 2C343 LOCATION PAGE ALARM AREA PREFIRE PLAN PNL-ROW-MOD RED l YELLOW NUMBER 1-1-1 24 1-1-2 (T) 19 1-1-2 (B) 20 Cable Spreading Room

  • 2098-L 1-1-4 (T) 25 23 1-1-4 (B) 28 29 1-1-5 (T) 30 23 1-1-5 (B) 32 33 1-1-7 (T) 20 Corridor to EDG Rooms
  • 2109-U 1-1-7 (B) 19 1-1-8 (T) 34 1-2-1 (T) 35 1-2-2 (T) 19 1-2-2 (B) 20 # 2 EDG Room (North)
  • 2094-Q 1-2-4 (T) 36 23 1-2-4 (B) 38 23 1-2-5 (T) 40 23 1-2-5 (B) 42 23 1-2-7 (T) 20 # 1 EDG Room (South)
  • 2093-P 1-2-7 (B) 19 1-2-8 (T) 44 1-3-4 (T) 45 23 North Containment Cable 2033-K 1-3-4 (B) 45 23 Spreading Areas
  • 1-3-5 (T) 48 23 UNEP 1-3-5 (B) 48 23 2183-J 1-3-6 (T) 50 North Electrical 1-3-7 (T) 19 Penetration Areas
  • LNEP 1-3-7 (B) 19 2112-BB 1-3-8 (T) 51 1-4-4 (T) 45 23 South Containment Cable 2032-K 1-4-4 (B) 45 23 Spreading Areas
  • 1-4-5 (T) 48 23 USEP 1-4-5 (B) 48 23 2137-I 1-4-6 (T) 52 South Electrical 1-4-7 (T) 19 Penetration Areas
  • LSEP 1-4-7 (B) 19 2111-T 1-4-8 (T) 53 1-5-1 (T) 54 1-5-2 (T) 19 Containment Preaction 2032K 1-5-2 (B) 20 Valve 2033K 1-5-3 (T) 45 23 Containment Heat
  • 1-5-5 (T) 55 23 1-5-5 (B) 57 58 Emergency Control 1-5-7 (T) 20 Room chillers
  • 2136-I 1-5-7 (B) 20 1-5-8 (T) 59

PROC./WORK PLAN N

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/WORK PLAN TITLE: PAGE: 8 of 100 2203.009 FIRE PROTECTION SYSTEM ANNUNCIATOR CORRECTIVE ACTION CHANGE: 026 ATTACHMENT A Page 2 of 4 Detection areas annotated with

  • are TRM required.

2C343-2 2C343 LOCATION PAGE ALARM AREA PREFIRE PNL-ROW-MOD RED l YELLOW PLAN NUMBER 2-1-1 (T) 21 23 CNTMT Purge Equipment Area 2156-A 2-1-1 (B) 21 23 EDG Air Intake

  • 2114-I 2-1-2 (T) 21 23 BAMT (2T6-A/B) Room 2115-I 2-1-2 (B) 21 23 UNEP Damper Room
  • 2183-J 2-1-3 (T) 21 23 RP Office Above False Ceiling
  • 2136-I 2-1-3 (B) 21 23 RP Office Below False Ceiling
  • 2136-I 2-1-4 (T) 21 23 RP Offices Cubicle Area (386)
  • 2136-I 2-1-4 (B) 21 23 Control Room
  • 2199-G 2-1-5 (T) 21 23 Control Room Supply Air Duct
  • 2199-G 2-1-5 (B) 21 23 Control Room Return Air Duct
  • 2199-G 2-1-6 (T) 21 23 Control Room Inside Panels
  • 2199-G 2-1-6 (B) 21 23 Control Room Printer Area 2119-H 2-1-7 (T) 21 23 2A4 Switchgear Room
  • 2100-Z 2-1-7 (B) 21 23 2A3 Switchgear Room
  • 2101-AA 2-1-8 (T) 21 23 Black Battery Room (West) 2103-V 2-1-8 (B) 21 23 Green Battery Room
  • 2102-Y (East Battery Room) 2-2-1 (T) 21 23 UNPP Room
  • 2081-HH 2-2-1 (B) 21 23 USPP Room
  • 2084-DD 2-2-2 (T) 21 23 MG Set Room
  • 2076-HH (North Electrical Equipment Room) 2-2-2 (B) 60 62 New CPC Room
  • 2098-C-G 2-2-4 (T) 21 21 Vacuum Degas Pump Room
  • 2106-R 2-2-4 (B) Spare (CR-ANO-2-2007-00776) 2-2-5 (T) 21 23 Corridor by Vac Degas/2B63 Room
  • 2107-N (Access Corridor From Stair 2001) 2-2-6 (T) 21 23 2Y25, 2B9/10 Room
  • 2108-S (South Electrical Equipment Room) 2-2-6 (B) 21 23 MCC 2B53 Room
  • 2091-BB 2-2-7 (T) 21 23 MCC 2B63 Room
  • 2096-M 2-2-7 (B) 21 23 SU & BD Demin Regen Room 2242-OO 2-2-8 (T) 21 23 2D02 Equipment Room
  • 2097-X 2-2-8 (B) 21 23 2Y11/13 Equipment Room
  • 2099-W (West DC Equipment Room) 2-3-1 (T) 21 23 SG Blowdown Tank
  • 2073-DD 2-3-1 (B) 21 23 VCT, 2P-43A/B 2072-R 2-3-2 (T) 21 23 Fuel Pool HX/USPP
  • 2084-DD 2-3-2 (B) 21 23 Hot Machine Shop
  • 2068-DD 2-3-3 (T) 21 23 2B62/Resin Add Area
  • 2073-DD 2-3-3 (B) 21 23 Waste Gas & Hot Lab Corridor 2073-DD (Aux Bldg. Access Corridor Area)
  • 2-3-4 (T) 21 23 Waste Gas Compressor Room
  • 2073-DD 2-3-4 (B) 21 23 2VEF-38A/B 2040-JJ 2-3-5 (T) 21 23 A EFW Pump Room 2024-JJ 2-3-5 (B) 21 23 B EFW Pump Room 2025-JJ 2-3-6 (T) 21 23 BMS Concentrator Room
  • 2040-JJ 2-3-6 (B) Spare (CR-ANO-2-2007-00776)

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/WORK PLAN TITLE: PAGE: 9 of 100 2203.009 FIRE PROTECTION SYSTEM ANNUNCIATOR CORRECTIVE ACTION CHANGE: 026 ATTACHMENT A Page 3 of 4 Detection areas annotated with

  • are TRM required.

2C343-2 2C343 LOCATION PAGE ALARM AREA PREFIRE PLAN PNL-ROW-MOD RED l YELLOW NUMBER 2-3-7 (T) 21 23 2T-21A&B and Charging Pumps

  • 2040-JJ 2-3-7 (B) 21 23 SG BD Pumps 2040-JJ 2-3-8 (T) 21 23 SFP Cooling Pumps and 2F3/2F4 2040-JJ 2-3-8 (B) 21 23 WCO Desk Area 2040-JJ 2-4-1 (T) 21 23 B HPSI Pump Area * (East) 2007-LL (Pipeway, Equipment Access Area AB Extension) 2-4-1 (B) 21 23 C HPSI Pump Room 2010-LL 2-4-2 (T) 21 23 B HPSI Pump Area (West)
  • 2007-LL (East Pump Area and Gallery B ESF Room) (Pipeway, Equipment Access Area AB Extension) 2-4-2 (B) 21 23 Tendon Gallery 2011-LL 2-4-3 (T) 21 23 A HPSI Pump Room 2014-LL 2-4-3 (B) 21 23 B LPSI Pump Area * (Pipeway, 2007-LL Equipment Access Area AB Extension))

2-4-4 (T) 21 23 SG BD HX and Storeroom Area

  • 2223-KK (Pipeway, Equipment Access Area AB Extension) 2-4-4 (B) 21 23 SG BD HX and Storeroom Area
  • 2223-KK (Pipeway, Equipment Access Area AB Extension) 2-4-5 (T) 21 23 AB Extension 335' Access Area
  • 2223-KK (Pipeway, Equipment Access Area AB Extension) 2-4-5 (B) 21 23 Waste Concentrator/ 2T12 Valve 2040-JJ Gallery
  • 2-4-7 (T) 21 23 TB 354' Old Makeup Plant Area
  • 2200-MM (Turbine Bldg. Demin Area Col 5.0-5.9 & A-C) 2-4-7 (B) 21 23 Waste Gas Tanks & 2F-15 Area 2040-JJ 2-4-8 (T) 21 23 LNPP Area
  • 2081-HH 2-4-8 (B) 21 23 LSPP Area
  • 2055-JJ Diesel Fuel EDG Fuel Oil Vault 2T-57A/B
  • Vault Unit 1, L 2-5-4 (T) 65 23 2-5-4 (B) 67 23 2-5-5 (T) 21 23 General Access Area 317'
  • 2006-LL 2-5-5 (B) 21 23 PASS Bldg Unit 2 Vol 2B PASS Bldg

PROC./WORK PLAN N

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/WORK PLAN TITLE: PAGE: 10 of 100 2203.009 FIRE PROTECTION SYSTEM ANNUNCIATOR CORRECTIVE ACTION CHANGE: 026 ATTACHMENT A Page 4 of 4 Detection areas annotated with

  • are TRM required.

2C343-3 2C343 LOCATION PAGE ALARM AREA PREFIRE PLAN PNL-ROW-MOD RED l YELLOW NUMBER CONTROL UNIT 6 17 Panel 2C343 N/A 3-2-1 (T) 21 23 Spent Fuel Pool Area 2151-A 3-2-3 (T) 21 23 Plant Computer Room 404 2152-D 3-2-3 (B) 21 23 CEDM Equipment/2C80 Room

  • 2154-E (Remote Shutdown Panels) 3-2-4 (T) 21 23 Area Above Plant Computer Room 2152-D 3-2-4 (B) 21 82 Plant Computer Cabinet & Below 2152-D False Floor 3-2-5 (T) 21 23 Room 2150 (Old CPC Room)
  • 2150-C 3-2-5 (B) 21 23 Behind TB Elevator Shaft 2200-MM 3-2-6 (T) 21 23 TB Fans 2VSF-14A, B, C 2200-MM 3-2-6 (B) 21 23 TB Fans 2VSF-14D, E, F 2200-MM 3-2-7 (T) 45 23 RCP 2P-32A Area
  • 2033-K 3-3-1 (B) 78 23 Intake Structure 2B43 * (366) Intake Structure 3-3-3 (T) 89 23 2VEF-38A/B Charcoal Filter 2040-JJ 3-3-3 (B) 91 23 2VSF-9 Charcoal Filter N/A 3-3-4 (T) 69 71 TG Bearings and LO Piping 2200-MM 3-3-4 (B) 73 23 Generator Exciter CO2 2200-MM 3-3-5 (T) 75 2HS-3217 Manual Actuation 2200-MM 3-3-6 (B) 83 85 Control Room Expansion Facility 2200-MM 3-3-8 (B) 86 88 AAC Diesel Generator Bldg 3-4-1 (T) 77 3-4-2 (T) 20 Intake 3-4-2 (B) 19 Intake Structure
  • Structure 3-4-4 (T) 78 23 3-4-4 (B) 78 23 2C234 2C234 LOCATION PAGE ALARM AREA PREFIRE PLAN PNL-ROW-MOD RED l YELLOW NUMBER 234-1-1 (T) 20 TG Bearings and Lube Oil 2200-MM 234-1-1 (B) 76 TG Bearings and Lube Oil 2200-MM 234-1-2 (T) 69 71 Zone 1 N/A 234-1-2 (B) 69 71 Zone 2 N/A 234-1-3 (T) 69 71 Zone 3 N/A 234-1-3 (B) 69 71 Zone 4 N/A 234-1-4 (T) 69 71 Zone 5 N/A 234-1-4 (B) 69 71 Zone 6 N/A 234-2-1 76 TG Bearings and Lube Oil N/A

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 36 of 100 2203.009 FIRE PROTECTION SYSTEM ANNUNCIATOR CORRECTIVE ACTION CHANGE: 026 Page 1 of 2 l-2-4 (T)

No. 2 EDG Room (North)

RED Flame Detector Alarm 1.0 CAUSES 1.1 Flame detector actuation in No. 2 EDG Room.

2.0 ACTION REQUIRED 2.1 Silence alarm in accordance with Section 6.0 of this procedure.

2.2 Dispatch Operator to No. 2 EDG (2K4B) Room to check for fire.

2.3 IF fire confirmed, THEN perform the following:

2.3.1 Initiate Fire or Explosion (2203.034) in conjunction with this procedure.

2.3.2 Refer to Fire Plan 2094-Q.

2.3.3 Secure the following fans:

Aux Bldg Supply fans (2VSF-7A and B)

Aux Bldg Exhaust fans (2VEF-8A and B)

EDG Exhaust fans (2VEF-24C and D) 2.4 IF requested by Fire Brigade Leader, THEN initiate Fire Water to fusible sprinkler heads by placing Manual Actuation switch (2HS-3230B, left) on module 1-2-2 in OPERATED position.

(No. 2 EDG Room (North) continued on next page)

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 37 of 100 2203.009 FIRE PROTECTION SYSTEM ANNUNCIATOR CORRECTIVE ACTION CHANGE: 026 Page 2 of 2 l-2-4 (T)

RED Flame Detector Alarm (Continued) 3.0 TO CLEAR ALARM 3.1 Reset 2C343 and Fire Indicating Unit (2FIU-02) by momentarily depressing the following:

3.1.1 Fire Detection Reset button (2PB-24030) on 2C22.

3.1.2 Reset/Lamp Test switch on control unit module.

NOTE If inoperable detection system is in the same area as an inoperable fire barrier, then Technical Requirement 3.7.5 action requirement may change from an hourly fire patrol to a continuous patrol.

FIU must reset to allow detector reset.

3.2 IF fire alarm will NOT reset, THEN perform the following as necessary:

3.2.1 Declare affected fire detector inoperable.

3.2.2 Establish Fire Watch per ANO Fire Impairment Program (1000.120).

3.2.3 Report Fire System Impairment in accordance with Unit 2 Technical Requirements Manual.

3.2.4 Refer to Unit 2 Technical Requirements Manual, Technical Requirements 3.3.6 and 3.7.2.

3.2.5 Review Fire Detection Database to determine if additional firewatch controls required per Technical Requirement 3.7.5.

3.2.6 Initiate WR/WO as applicable.

3.2.7 DO NOT CONTINUE.

3.3 IF the master fire alarm will not reset, THEN perform the following:

Push red master reset button located in right side of 2C343-3 (labeled "RESET").

Verify WR/WO initiated to repair Reset/Lamp Test switch.

3.4 IF Fire Water flow initiated or 2UAV-3230 tripped, THEN secure Fire Water as follows:

3.4.1 Verify Manual Actuation switch (2HS-3230B, left) on module 1-2-2 in NORMAL position.

3.4.2 Reset 2UAV-3230 using Unit 2 Fire Protection System (2104.032).

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 38 of 100 2203.009 FIRE PROTECTION SYSTEM ANNUNCIATOR CORRECTIVE ACTION CHANGE: 026 Page 1 of 2 1-2-4(B)

No. 2 EDG Room (North)

RED Smoke Detector Alarm 1.0 CAUSES 1.1 Smoke detector actuation in No. 2 EDG (2K4B) Room.

2.0 ACTION REQUIRED 2.1 Silence alarm in accordance with Section 6.0 of this procedure.

2.2 Dispatch Operator to No. 2 EDG (2K4B) Room to check for fire.

2.3 IF fire confirmed, THEN perform the following:

2.3.1 Initiate Fire or Explosion (2203.034) in conjunction with this procedure.

2.3.2 Refer to Fire Plan 2094-Q.

2.3.3 Secure the following fans:

Aux Bldg Supply fans (2VSF-7A and B)

Aux Bldg Exhaust fans (2VEF-8A and B)

EDG Exhaust fans (2VEF-24C and D) 2.4 IF requested by Fire Brigade Leader, THEN initiate Fire Water to fusible sprinkler heads by placing Manual Actuation switch (2HS-3230B, left) on module 1-2-2 in OPERATED position.

(No. 2EDG Room (North) continued on next page)

ANO-2-JPM-NRC-ELECXT (S7) PAGE 1 OF 10 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 003 DATE:

SYSTEM/DUTY AREA: A. C. Electrical Distribution TASK: Perform Synchronized Cross Connect of 480 VAC load-centers 2B1 and 2B2 JTA#: ANO2-RO-480VAC-NORM-15 Alternate Path Yes: X No: Time Critical Yes: No: X KA VALUE RO: 3.3 SRO: 3.1 KA

REFERENCE:

062 A4.01 APPROVED FOR ADMINISTRATION TO: RO: X SRO: X TASK LOCATION: INSIDE CR: X OUTSIDE CR: BOTH:

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform LAB:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: LAB:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 12 Minutes REFERENCE(S): OP 2107.001 Electrical System Operation EXAMINEE'S NAME: Badge #

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Stop Total Time Time Time

ANO-2-JPM-NRC-ELECXT PAGE 2 OF 10 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

Unit 2 is in Mode 3.

Non-Vital 4160VAC busses energized.

2B1 and 2B2 are energized.

Scheduled maintenance must be performed on 2B2 transformer.

2B-1 transformer Freon pressure has been verified adequate using 2107.001 Attachment T.

Turbine Building Cranes are powered from Unit 1 power supply.

The Operations Manager has given permission to perform Cross Connect of 2B1 and 2B2.

TASK STANDARD:

Cross connected 480VAC non-vital busses 2B1 and 2B2 with 2B2 supplied from 2B1. 2B2 supply breakers opened. Maintained 2B1 amperage less than 138 amps by either uncross tying the busses or direct loads to be reduced.

TASK PERFORMANCE AIDS:

OP 2107.001 Section 12.0.

SIMULATOR SETUP:

Mode 3.

All Non-Vital 4160VAC and 480VAC Busses energized.

REMOTE malfunction 480CURR2B2 value = 25 REMOTE malfunctions 480CURR2B1 (value = 30) and 480CURR2B2 (value = 35) are set for trigger 2.

Conditional triggerT2 should be set for the handswitch to 2B-212 green light (IC4G12CU)

ANO-2-JPM-NRC-ELECXT PAGE 3 OF 10 JOB PERFORMANCE MEASURE INITIATING CUE:

The SM/CRS directs you to cross connect 2B1 and 2B2 and separate 2B2 from 2A2 using OP 2107.001 section 12.0.

START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

Procedure Caution:

Cross-tying buses may cause overload resulting in loss of bus.

If in Mode 1-4, do not crosstie 2B1, 2B3, 2B7, 2B2, 2B4, and 2B8 except in emergency situations or as otherwise authorized by the Operations Manager. Cross-tying 2B9 and 2B10 is allowed with Ops Manager permission because loss of both buses will not cause a trip.

Time dependent overcurrent relays exist on all 480V Load Center feeder breakers. They are set at 1600 amps (equates to 185 amps on 4160V AC side). Bus load should not exceed 173 amps (including 7% tolerance).

Transformer continuous amperage rating at 4160V is 138 amps. Continuous operation > 138 amps will eventually degrade transformer.

Load Centers should not be cross connected if Loading Transformer Freon pressure is not adequate -

Refer to Transformer Temperature vs Pressure (Attachment T).

1. IF in Modes 1-4 Determined that Operations N/A SAT UNSAT AND cross connecting for Manager has given approval to (Step emergency conditions, cross connect 2B1 and 2B2 at 12.1) THEN proceed with cross-tie power.

operation, OTHERWISE obtain Operations Manager concurrence.

2. IF BOTH buses energized On Panel 2C10, summed the N/A SAT UNSAT AND combined load greater current reading of 2B1 and 2B2.

(Step than 138 amps, 12.2)

THEN adjust load as necessary Observed that the summed load to achieve less than 138 amps is less than 138 amps.

combined load.

Examiner Note: Amps should be

~112 prior to cross tie.

3. IF desired to cross connect Determined step 12.3 is N/A SAT UNSAT Load Centers 2B1 and 2B2, applicable.

(Step THEN perform the following:

12.3)

Procedure Note:

The following loads may cycle automatically and should be considered when evaluating loads on bus 2B1 and 2B2. Amperage values are at the 4160V level as indicated on 2C10:

Electrohydraulic pump 10 amps Instrument Air Compressor 10 amps

ANO-2-JPM-NRC-ELECXT PAGE 4 OF 10 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

4. Verify Turbine Building Cranes Determined from initial N/A SAT UNSAT (L-1/2L-1) powered from conditions that the turbine (Step Unit 1 Power Supply (B-433 building cranes are powered 12.3.1) and S-06). from Unit 1.
5. IF cross connecting to energize Determined step 12.3.2 is N/A. N/A SAT UNSAT a de-energized bus, (Step THEN perform the following:

12.3.2)

(C) 6. Place Synchroscope switch for On Panel 2C10, Placed N/A SAT UNSAT 2B1 - 2B2 Tie 2B132 to ON. Synchroscope switch into (Step 2B1/2B2 cross-tie slot and 12.3.3) rotated clockwise to the ON position.

7. IF cross connecting energized On Panel 2C10, Observed that N/A SAT UNSAT buses, the Synchroscope is at the 12 (Step THEN check synchroscope at oclock position with the 12.3.4) 12 o'clock position. Synchroscope switch in the ON position.

(C) 8. Close the 2B1/2B2 Cross Tie On panel 2C10, rotated the N/A SAT UNSAT breaker. Cross Tie handswitch for (Step 2B1/2B2 clockwise.

12.3.5)

Observed that the Green light turns OFF and the Red light turns ON above the Cross Tie handswitch.

9. IF desired to separate 480V Determined that step 12.3.6 is N/A SAT UNSAT bus 2B1 from 4160V AC bus N/A.

(Step 2A1, 12.3.6)

THEN open the following breakers:

(C) 10. IF desired to separate 480V On Panel 2C10, rotated the N/A SAT UNSAT (Step bus 2B2 from 4160V AC bus normal feeder supply breaker on 12.3.7) 2A2, 2B2 counter clockwise to the and THEN open the following open position. (2B212) breakers:

(Step Observed that the RED light 12.3.7.A)

LC 2B2 Supply 2B212 (52-212 went OFF and the GREEN light CS) went ON.

ANO-2-JPM-NRC-ELECXT PAGE 5 OF 10 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 11. LC 2B2 Feeder 2A202 On Panel 2C10, rotated the N/A SAT UNSAT (152-202 CS) transformer feeder breaker on (Step 2A2 to 2B2 counter clockwise to 12.3.7.B) the open position. (2A202)

Observed that the RED light went OFF and the GREEN light went ON.

Examiners Note:

The following is the Alternate path portion of this JPM (C) 12. Verify less than 138 amps on Observed that the summed load N/A SAT UNSAT (Step supplying transformer. is greater than 138 amps.

12.3.8)

EXAMINERS CUE: Directed the AO or informed CRS of need to reduce non-AO has been directed to essential loads on 2B1 and 2B2 secure non-essential loads so that combined loading is less on 2B1 and 2B2 to reduce than 130 amps.

loading on 2B1 and 2B2 to less than 138 amps.

OR EXAMINERS NOTE:

Direct operator in simulator Separated 2B1 and 2B2 using instructors station to reduce the appropriate section of loading on 2B1 and 2B2 so 2107.001. See Attachment 1 for that loading is less than 138 steps to uncross tie.

amps (use REMOTE malfunctions 480CURR2B1 and 480CURR2B2).

13. Place Synchroscope switch for On Panel 2C10, turned sync N/A SAT UNSAT (Step 2B1 - 2B2 Tie 2B132 to OFF. switch counter clockwise to the 12.3.9) OFF position.

Examiners Note:

Step 12.3.10 in procedure is not applicable for this JPM as both busses remained energized and the loads removed to reduce amperage on 2B1 will remain deenergized.

14. IF EITHER Load Center has Determined that step 12.3.10 is N/A SAT UNSAT (Step been stripped, N/A.

12.3.10 THEN perform the following:

)

ANO-2-JPM-NRC-ELECXT PAGE 6 OF 10 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

15. Maintain supplying transformer Notified AO to monitor 2B1 N/A SAT UNSAT (Step temperature less than 220°C transformer during cross 12.11) Hot Spot temperature and less connected operation and than 95°C Top temperature maintain temperature less than while buses cross-connected: 220°C.

EXAMINERS CUE:

AO has been notified to monitor 2B1 transformer and notify the control room if Hot Spot temperature exceeds 220°C or Top temperature exceeds 95 0C during cross connected operations.

Attachment 1 PERFORMANCE CHECKLIST STANDARDS (Circle One)

Examiner Note:

The following are steps to separate 480V Non-ESF buses IF desired to separate Load Determine that 2A-1 and 2A-2 N/A SAT UNSAT

1. Centers 2B1 and 2B2 after are both powered from Startup (Step cross connect, #3.

13.1) THEN perform the following:

and (Step Verify 2A1 and 2A2 13.1.1) synchronized by being powered from same electrical source.

2. Place Synchroscope switch for On Panel 2C10, Placed N/A SAT UNSAT 2B1 - 2B2 Tie 2B132 to ON. Synchroscope switch into (Step 2B1/2B2 cross-tie slot and 13.1.2) rotated clockwise to the ON position.

Procedure Note:

A current surge should be expected when closing Bus Supply breaker.

Current should return to a proper value.

3. IF 480V bus 2B1 separated Determined step 13.1.3 is N/A. N/A SAT UNSAT from 4160V AC bus 2A1, (Step THEN perform the following:

13.1.3)

ANO-2-JPM-NRC-ELECXT PAGE 7 OF 10 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

4. IF 480V bus 2B2 separated On panel 2C10, rotated the N/A SAT UNSAT from 4160V AC bus 2A2, Cross Tie handswitch for 2A-202 (Step 13.1.4)

THEN perform the following: clockwise.

OR and Close LC 2B2 Feeder 2A202 Checked 2A-202 was still (Step (152-202 CS). closed.

13.1.4.A)

Observed that the Green light OFF and the Red light ON above the 2A-202 handswitch.

(C) 5. Close LC 2B2 Supply 2B212 On Panel 2C10, rotated the N/A SAT UNSAT (52-212 CS). normal feeder supply breaker on (Step 13.1.4.B) 2B2 clockwise to the closed position. (2B212)

Observed that the Green light turns OFF and the Red light turns ON above the 2B-212 handswitch.

6. Check amperage indication On Panel 2C10, observed that N/A SAT UNSAT rises. 2B-2 amperage rose.

(Step 13.1.4.B)

8. Open 2B1 - 2B2 Tie 2B132 On panel 2C10, rotated the N/A SAT UNSAT (52-132 CS) Cross Tie handswitch for (Step 2B1/2B2 counter clockwise.

13.1.5)

Observed that the Red light turns OFF and the Geen light turns ON above the Cross Tie handswitch.

Examiners note: This JPM may be stopped after 2B-1 and 2B-2 are no longer cross tied or load is reduced less than 138 amps.

9. Place 2B1 - 2B2 Tie 2B132 Determined to place 2B132 N/A SAT UNSAT (52-132 CS) in PTL as desired. handswitch is PTL or leave in (Step normal after open.

13.1.6)

10. Check normal amp indication On Panel 2C10, observed the N/A SAT UNSAT (Step on associated buses current reading of 2B1 and 2B2.

13.1.7) (less than 138 amps).

Observed each bus load is less than 138 amps.

11. Place Synchroscope switch for On Panel 2C10, turned sync N/A SAT UNSAT 2B1 - 2B2 Tie 2B132 to OFF. switch counter clockwise to the (Step OFF position.

13.1.8

ANO-2-JPM-NRC-ELECXT PAGE 8 OF 10 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

12. IF any loads remained stripped Determined step 13.1.3 is N/A. N/A SAT UNSAT (Step from bus(es) in cross-tie 13.1.9) section, THEN verify those loads restored.

END STOP TIME:

ANO-2-JPM-NRC-ELECXT PAGE 9 OF 10 JOB PERFORMANCE MEASURE EXAMINERS COPY INITIAL CONDITIONS:

You are responsible for any applicable annunciators during the performance of this task.

All annunciators that are not applicable to this task will be performed by another operator.

Unit 2 is in Mode 3.

Non-Vital 4160VAC busses energized. 2B1 and 2B2 are energized.

Scheduled maintenance must be performed on 2B2 transformer.

2B-1 transformer Freon pressure has been verified adequate using 2107.001 Attachment T.

Turbine Building Cranes are powered from Unit 1 power supply.

The Operations Manager has given permission to perform Cross Connect of 2B1 and 2B2.

INITIATING CUE:

The SM/CRS directs you to cross connect 2B1 and 2B2 and separate 2B2 from 2A2 using OP 2107.001 section 12.0.

ANO-2-JPM-NRC-ELECXT PAGE 10 OF 10 JOB PERFORMANCE MEASURE EXAMINEES COPY INITIAL CONDITIONS:

You are responsible for any applicable annunciators during the performance of this task.

All annunciators that are not applicable to this task will be performed by another operator.

Unit 2 is in Mode 3.

Non-Vital 4160VAC busses energized. 2B1 and 2B2 are energized.

Scheduled maintenance must be performed on 2B2 transformer.

2B-1 transformer Freon pressure has been verified adequate using 2107.001 Attachment T.

Turbine Building Cranes are powered from Unit 1 power supply.

The Operations Manager has given permission to perform Cross Connect of 2B1 and 2B2.

INITIATING CUE:

The SM/CRS directs you to cross connect 2B1 and 2B2 and separate 2B2 from 2A2 using OP 2107.001 section 12.0.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 54 of 328 2107.001 ELECTRICAL SYSTEM OPERATIONS CHANGE: 112 12.0 CROSS CONNECTING 480V NON-ESF BUSES CAUTION Cross-tying buses may cause overload resulting in loss of bus.

If in Mode 1-4, do not crosstie 2B1, 2B3, 2B7, 2B2, 2B4, and 2B8 except in emergency situations or as otherwise authorized by the Operations Manager. Cross-tying 2B9 and 2B10 is allowed with Ops Manager permission because loss of both buses will not cause a trip.

Time dependent overcurrent relays exist on all 480V Load Center feeder breakers. They are set at 1600 amps (equates to 185 amps on 4160V AC side). Bus load should not exceed 173 amps (including 7% tolerance).

Transformer continuous amperage rating at 4160V is 138 amps. Continuous operation > 138 amps will eventually degrade transformer.

Load Centers should not be cross connected if Loading Transformer Freon pressure is not adequate - Refer to Transformer Temperature vs Pressure (Attachment T).

12.1 IF in Modes 1-4 AND cross connecting for emergency conditions, THEN proceed with cross-tie operation, OTHERWISE obtain Operations Manager concurrence.

12.2 IF BOTH buses energized AND combined load greater than 138 amps, THEN adjust load as necessary to achieve less than 138 amps combined load.

12.3 IF desired to cross connect Load Centers 2B1 and 2B2, THEN perform the following:

NOTE The following loads may cycle automatically and should be considered when evaluating loads on bus 2B1 and 2B2. Amperage values are at the 4160V level as indicated on 2C10:

Electrohydraulic pump 10 amps Instrument Air Compressor 10 amps 12.3.1 Verify Turbine Building Cranes (L-1/2L-1) powered from Unit 1 Power Supply (B-433 and S-06).

12.3.2 IF cross connecting to energize a de-energized bus, THEN perform the following:

A. Strip all loads from de-energized Load Center.

(Step 12.3 continued on next page)

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 55 of 328 2107.001 ELECTRICAL SYSTEM OPERATIONS CHANGE: 112 B. Verify de-energized Load Center Supply bkrs open:

LC 2B1 Supply 2B112 (52-112 CS)

LC 2B1 Feeder 2A102 (152-102 CS)

OR LC 2B2 Supply 2B212 (52-212 CS)

LC 2B2 Feeder 2A202 (152-202 CS)

C. Complete Configuration Control module entry for any repositioned breakers.

12.3.3 Place Synchroscope switch for 2B1 - 2B2 Tie 2B132 to ON.

12.3.4 IF cross connecting energized buses, THEN check synchroscope at 12 o'clock position.

12.3.5 Close 2B1 - 2B2 Tie 2B132 (52-132 CS).

12.3.6 IF desired to separate 480V bus 2B1 from 4160V AC bus 2A1, THEN open the following breakers:

A. LC 2B1 Supply 2B112 (52-112 CS)

B. LC 2B1 Feeder 2A102 (152-102 CS) 12.3.7 IF desired to separate 480V bus 2B2 from 4160V AC bus 2A2, THEN open the following breakers:

A. LC 2B2 Supply 2B212 (52-212 CS)

B. LC 2B2 Feeder 2A202 (152-202 CS) 12.3.8 Verify less than 138 amps on supplying transformer.

12.3.9 Place Synchroscope switch for 2B1 - 2B2 Tie 2B132 to OFF.

12.3.10 IF EITHER Load Center has been stripped, THEN perform the following:

A. Energize loads as directed by SM.

B. Update Configuration Control module as necessary.

  • 12.3.11 Maintain supplying transformer temperature less than 220°C Hot Spot temperature and less than 95°C Top temperature while buses cross-connected:

2TIS-6710/2TIS-6710A (2B1) 2TIS-6711/2TIS-6711A (2B2)

  • 12.3.12 Maintain less than 138 amps on supplying transformer while buses cross-connected.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 56 of 328 2107.001 ELECTRICAL SYSTEM OPERATIONS CHANGE: 112 12.4 IF desired to cross connect Load Centers 2B3 and 2B4, THEN perform the following:

NOTE The following loads may cycle automatically and should be considered when evaluating loads on bus 2B3 and 2B4. Amperage values are at the 4160V level as indicated on 2C10:

Condenser Vacuum pump 9 amps 12.4.1 IF cross connecting to energize a de-energized bus, THEN perform the following:

A. Strip all loads from de-energized Load Center.

B. Verify de-energized Load Center Supply bkrs open:

LC 2B3 Supply 2B312 (52-312 CS)

LC 2B3 Feeder 2A103 (152-103 CS)

OR LC 2B4 Supply 2B412 (52-412 CS)

LC 2B4 Feeder 2A203 (152-203 CS)

C. Complete Configuration Control module entry for any repositioned breakers.

12.4.2 Place Synchroscope switch for 2B3 - 2B4 Tie 2B433 to ON.

12.4.3 IF cross connecting energized buses, THEN check synchroscope at 12 o'clock position.

12.4.4 Close 2B3 - 2B4 Tie 2B433 (52-433 CS).

12.4.5 IF desired to separate 480V bus 2B3 from 4160V AC bus 2A1, THEN open the following breakers:

A. LC 2B3 Supply 2B312 (52-312 CS)

B. LC 2B3 Feeder 2A103 (152-103 CS) 12.4.6 IF desired to separate 480V bus 2B4 from 4160V AC bus 2A2, THEN open the following breakers:

A. LC 2B4 Supply 2B412 (52-412 CS)

B. LC 2B4 Feeder 2A203 (152-203 CS) 12.4.7 Verify less than 138 amps on supplying transformer.

12.4.8 Place Synchroscope switch for 2B3 - 2B4 Tie 2B433 to OFF.

(Step 12.4 continued on next page)

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 57 of 328 2107.001 ELECTRICAL SYSTEM OPERATIONS CHANGE: 112 12.4.9 IF EITHER Load center has been stripped, THEN perform the following:

A. Energize loads as directed by SM.

B. Update Configuration Control module as necessary.

  • 12.4.10 Maintain supplying transformer temperature less than 220°C Hot Spot temperature and less than 95°C Top temperature while buses cross-connected:

2TIS-6712/2TIS-6712A (2B3) 2TIS-6713/2TIS-6713A (2B4)

  • 12.4.11 Maintain less than 138 amps on supplying transformer while buses cross-connected.

12.5 IF desired to cross connect Load Centers 2B7 and 2B8, THEN perform the following:

NOTE MG set loads may cycle during CEA movement. Amperage values are at the 4160V level are indicated on 2C10. Minimize CEA movement while 2B7 and 2B8 are cross connected.

12.5.1 IF cross connecting to energize a de-energized bus, THEN perform the following:

A. Strip all loads from de-energized Load Center.

B. Verify de-energized Load Center Supply bkrs open:

LC 2B7 Supply 2B712 (52-712 CS)

LC 2B7 Feeder 2A104 (152-104 CS)

OR LC 2B8 Supply 2B812 (52-812 CS)

LC 2B8 Feeder 2A204 (152-204 CS)

C. Complete Configuration Control module entry for any repositioned breakers.

12.5.2 Place Synchroscope switch for 2B7 - 2B8 Tie 2B713 to ON.

12.5.3 IF cross connecting energized buses, THEN check synchroscope at 12 o'clock position.

12.5.4 Close 2B7 - 2B8 Tie 2B713 (52-713 CS).

(Step 12.5 continued on next page)

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 58 of 328 2107.001 ELECTRICAL SYSTEM OPERATIONS CHANGE: 112 12.5.5 IF desired to separate 480V bus 2B7 from 4160V AC bus 2A1, THEN open the following breakers:

A. LC 2B7 Supply 2B712 (52-712 CS)

B. LC 2B7 Feeder 2A104 (152-104 CS) 12.5.6 IF desired to separate 480V bus 2B8 from 4160V AC bus 2A2, THEN open the following breakers:

A. LC 2B8 Supply 2B812 (52-812 CS)

B. LC 2B8 Feeder 2A204 (152-204 CS) 12.5.7 Verify less than 138 amps on supplying transformer.

12.5.8 Place Synchroscope switch for 2B7 - 2B8 Tie 2B713 to OFF.

12.5.9 IF EITHER Load center has been stripped, THEN perform the following:

A. Energize loads as directed by SM.

B. Update Configuration Control module as necessary.

  • 12.5.10 Maintain supplying transformer temperature less than 220°C Hot Spot temperature and less than 95°C Top temperature while buses cross-connected:

2TIS-6716/2TIS-6716A (2B7) 2TIS-6717/2TIS-6717A (2B8)

  • 12.5.11 Maintain less than 138 amps on supplying transformer while buses cross-connected.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 59 of 328 2107.001 ELECTRICAL SYSTEM OPERATIONS CHANGE: 112 12.6 IF desired to cross connect Load Centers 2B9 and 2B10, THEN perform the following:

NOTE The following loads may cycle automatically and should be considered when evaluating loads on bus 2B9 and 2B10. Amperage values are at the 4160V level as indicated on 2C10:

Pressurizer Backup heaters 20 amps 12.6.1 IF cross connecting to energize a de-energized bus, THEN perform the following:

A. Strip all loads from de-energized Load Center.

B. Verify de-energized Load Center Supply bkrs open:

LC 2B9 Supply 2B912 (52-912 CS)

LC 2B9 Feeder 2A109 (152-109 CS)

OR LC 2B10 Supply 2B1012 (52-1012 CS)

LC 2B10 Feeder 2A209 (152-209 CS)

C. Complete Configuration Control module entry for any repositioned breakers.

12.6.2 Place Synchroscope switch for 2B9 - 2B10 Tie 2B913 to ON.

12.6.3 IF cross connecting energized buses, THEN check synchroscope at 12 o'clock position.

12.6.4 Close 2B9 - 2B10 Tie 2B913 (52-913 CS).

12.6.5 IF desired to separate 480V bus 2B9 from 4160V AC bus 2A1, THEN perform the following:

A. Verify Pressurizer Backup heater(s) selected for service (Handswitch in ON) are powered from Load Center 2B10.

B. Open LC 2B9 Supply 2B912 (52-912 CS).

C. Open LC 2B9 Feeder 2A109 (152-109 CS).

(Step 12.6 continued on next page)

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 60 of 328 2107.001 ELECTRICAL SYSTEM OPERATIONS CHANGE: 112 12.6.6 IF desired to separate 480V bus 2B10 from 4160V AC bus 2A2, THEN perform the following:

A. Verify Pressurizer Backup heater(s) selected for service (Handswitch in ON) are powered from Load Center 2B9.

B. Open LC 2B10 Supply 2B1012 (52-1012 CS).

C. Open LC 2B10 Feeder 2A209 (152-209 CS).

12.6.7 Verify less than 138 amps on supplying transformer.

12.6.8 Place Synchroscope switch for 2B9 - 2B10 Tie 2B913 to OFF.

12.6.9 IF EITHER Load center has been stripped, THEN perform the following:

A. Energize loads as directed by SM.

B. Update Configuration Control module as necessary.

  • 12.6.10 Maintain supplying transformer temperature less than 220°C Hot Spot temperature and less than 95°C Top temperature while buses cross-connected:

2TIS-6718/2TIS-6718A (2B9) 2TIS-6719/2TIS-6719A (2B10)

  • 12.6.11 Maintain less than 138 amps on supplying transformer while buses cross-connected.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 61 of 328 2107.001 ELECTRICAL SYSTEM OPERATIONS CHANGE: 112 13.0 SEPARATING 480V NON-ESF BUSES AFTER CROSS CONNECT 13.1 IF desired to separate Load Centers 2B1 and 2B2 after cross connect, THEN perform the following:

13.1.1 Verify 2A1 and 2A2 synchronized by being powered from same electrical source.

13.1.2 Place Synchroscope switch for 2B1 - 2B2 Tie 2B132 to ON.

NOTE A current surge should be expected when closing Bus Supply breaker.

Current should return to a proper value.

13.1.3 IF 480V bus 2B1 separated from 4160V AC bus 2A1, THEN perform the following:

A. Close LC 2B1 Feeder 2A102 (152-102 CS).

B. Close LC 2B1 Supply 2B112 (52-112 CS).

C. Check amperage indication rises.

13.1.4 IF 480V bus 2B2 separated from 4160V AC bus 2A2, THEN perform the following:

A. Close LC 2B2 Feeder 2A202 (152-202 CS).

B. Close LC 2B2 Supply 2B212 (52-212 CS).

C. Check amperage indication rises.

13.1.5 Open 2B1 - 2B2 Tie 2B132 (52-132 CS).

13.1.6 Place 2B1 - 2B2 Tie 2B132 (52-132 CS) in PTL as desired.

13.1.7 Check normal amp indication on associated buses (less than 138 amps).

13.1.8 Place Synchroscope switch for 2B1 - 2B2 Tie 2B132 to OFF.

13.1.9 IF any loads remained stripped from bus(es) in cross-tie section, THEN verify those loads restored.

ANO-2-JPM-NRC-CEA02 (S8) PAGE 1 OF 9 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 009 DATE:

SYSTEM/DUTY AREA: Control Element Drive Mechanism Control System TASK: Test a Reactor Trip Circuit Breaker JTA#: ANO2-RO-CEDM-SURV-15 Alternate Path Yes: No: X Time Critical Yes: No: X KA VALUE RO: 4.3 SRO: 4.3 KA

REFERENCE:

012 A4.06 APPROVED FOR ADMINISTRATION TO: RO: X SRO: X TASK LOCATION: INSIDE CR: X OUTSIDE CR: BOTH:

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform LAB:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: LAB:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 15 Minutes REFERENCE(S): OP 2105.009 CEDM Control System Operation EXAMINEE'S NAME: Badge #

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Stop Total Time Time Time

ANO-2-JPM-NRC-CEA02 (S8) PAGE 2 OF 9 JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

TCB-02 has been repaired following a component malfunction The plant is in Mode 3 Supplement 1 Section 1.0 of 2105.009 is completed An operator is standing by in the CEDM room TASK STANDARD:

TCB-2 closed then the shunt trip tested.

TCB-2 closed then the undervoltage trip tested.

TCB-2 and TCB-6 left closed.

TASK PERFORMANCE AIDS:

OP 2105.009 Supplement 1.0 section 2.1 and 2.2. TCB Close Key (Key #15).

SIMULATOR SETUP:

TCB 9 closed. TCB 2 is open.

ANO-2-JPM-NRC-CEA02 (S8) PAGE 3 OF 9 JOB PERFORMANCE MEASURE INITIATING CUE:

The CRS directs you to perform the Reactor Trip Circuit Breaker Test for TCB-2 only, using OP 2105.009 Supplement 1.0 section 2.1 and 2.2. Leave TCB-2 and TCB-6 closed.

Start Time:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

Procedure Caution:

If TCB Undervoltage Trip Device Armature NOT in contact with Air Gap Adjustment Screw, breaker may not open when required.

If a stuck out CEA exists then TCBs should not be closed since this could result in an inadequate shutdown margin.

1. Verify Undervoltage Trip Contacted operator in CEDM N/A SAT UNSAT Device Armature in contact room.

with (Step Air Gap Adjustment Screw 2.1.1) Requested verification of position IAW Plant Heatup (2102.002),

Exhibit 1, "Undervoltage Trip of UV trip device armatures for Device". TCB-2 using the local exhibit.

Examiner Cue:

CEDM Room operator reports UV Trip Device armatures for TCB-2 is in contact with air gap adjusting screw IAW Exhibit 1.

2. Obtain CPC Test/TCB close CPC Test/TCB close key (#15) N/A SAT UNSAT key (#15) from SM key locker. obtained from SM key locker.

(Step 2.1.2) Examiner Cue:

When Examinee request key 15 provide them with the key.

(C) 3. On 2C23, place applicable On 2C23, placed applicable N/A SAT UNSAT Reset Actuation Trip Path Reset Actuation Trip Path keylock keylock in UNLK. in UNLK for TCB-2/6.

(Step 2.1.3)

ANO-2-JPM-NRC-CEA02 (S8) PAGE 4 OF 9 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 4. Close TCB-2 using pushbutton Depress TCB-2 reset push button. N/A SAT UNSAT on 2C23. (critical portion)

(Step 2.1.4) On panel 2C23 or panel 2C14, verified red light ON for TCB-2.

5. On 2C23, place applicable Placed key in LOCK position. N/A SAT UNSAT Reset Actuation Trip Patch (Step keylock in LK.

2.1.5)

Perform the following to test Shunt Trip:

6. Verify TCB-2 closed per step Verified TCB-2 closed per step N/A SAT UNSAT 2.1 2.1 (Step 2.2)
7. Hold 2HS/TEST switch in UV Contacted operator in CEDM N/A SAT UNSAT Bypass position. room.

(Step 2.2) Examiner Cue: Requested 2HX/TEST switch be CEDM Room operator held in the UV Bypass position.

reports 2HS/TEST switch is in the UV Bypass Position.

(C) 8. Momentarily depress Reactor On panel 2C03, depressed push N/A SAT UNSAT Trip pushbutton (2HS-907l-2) button 2HS-9071-2.

(Step on 2C03.

2.2)

9. Verify TCB-2 open. On panel 2C14, verified TCB-2 N/A SAT UNSAT opens.

(Step 2.2)

10. Check 2K12-A10 alarm comes On annunciator panel 2K12, N/A SAT UNSAT in or reflashes. acknowledged that 2K12-A10 (Step actuated.

2.2)

ANO-2-JPM-NRC-CEA02 (S8) PAGE 5 OF 9 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

11. Contact CEDM Room operator Contact CEDM Room operator to N/A SAT UNSAT to release 2HS/TEST switch. release 2HS/TEST switch.

(Step 2.2) Examiner Cue:

CEDM Room operator reports that 2HS/TEST switch is released EVALUATORS NOTE: The simulator does model 2K426.

12. Verify reflash Unit 2K426 in In panel 2C-14, depresses R on N/A SAT UNSAT 2C14 reset. 2K426 to reset the reflash unit.

(Step 2.2)

13. Verify Undervoltage Trip Contacted operator in CEDM N/A SAT UNSAT Device Armature in contact room.

with (Step Air Gap Adjustment Screw 2.1.1) Requested verification of position IAW Plant Heatup (2102.002),

Exhibit 1, "Undervoltage Trip of UV trip device armatures for Device". TCB-2.

Examiner Cue:

CEDM Room operator reports UV Trip Device armatures for TCB-2 is in contact with air gap adjusting screw IAW Exhibit 1.

14. Obtain CPC Test/TCB close CPC Test/TCB close key (#15) N/A SAT UNSAT key (#15) from SM key locker. obtained from SM key locker.

(Step 2.1.2)

Examiner Note:

Examinee should have the key from earlier.

(C) 15. On 2C23, place applicable On 2C23, placed applicable N/A SAT UNSAT Reset Actuation Trip Path Reset Actuation Trip Path keylock (Step keylock in UNLK. in UNLK for TCB-2/6.

2.1.3)

ANO-2-JPM-NRC-CEA02 (S8) PAGE 6 OF 9 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 16. Close TCB-2 using pushbutton Depress TCB-2 reset push button. N/A SAT UNSAT on 2C23. (critical portion)

(Step 2.1.4) On panel 2C23 or panel 2C14, verified red light ON for TCB-2.

17. On 2C23, place applicable Placed key in LOCK position. N/A SAT UNSAT Reset Actuation Trip Patch (Step keylock in LK.

2.1.5)

Perform the following to test UV Trip:

18. Verify TCB-2 closed per step Verified TCB-2 closed per step N/A SAT UNSAT 2.1 2.1 (Step 2.2)
19. Hold 2HS/TEST switch in Contacted operator in CEDM N/A SAT UNSAT Shunt Bypass position. room.

(Step 2.2) Examiner Cue:

CEDM Room operator Requested 2HX/TEST switch be reports 2HS/TEST switch is held in the Shunt Bypass position.

in the Shunt Bypass Position.

(C) 20. Momentarily depress Reactor On panel 2C03, depressed push N/A SAT UNSAT Trip pushbutton (2HS-907l-2) button 2HS-9071-2.

(Step on 2C03.

2.2)

21. Verify TCB-2 opens. On panel 2C14, verified TCB-2 N/A SAT UNSAT opens.

(Step 2.2) Verified by green lights ON for TCB-2.

22. Check 2K12-A10 alarm comes On annunciator panel 2K12, N/A SAT UNSAT in or reflashes. acknowledged that 2K12-A10 (Step actuated.

2.2)

ANO-2-JPM-NRC-CEA02 (S8) PAGE 7 OF 9 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

23. Contact CEDM Room operator Contact CEDM Room operator to N/A SAT UNSAT to release 2HS/TEST switch. release 2HS/TEST switch.

(Step 2.2) Examiner Cue:

CEDM Room operator reports that 2HS/TEST switch is released EVALUATORS NOTE: The simulator does not model 2K426.

24. Verify reflash Unit 2K426 in In panel 2C-14, depresses R on N/A SAT UNSAT 2C14 reset. 2K426 to reset the reflash unit.

(Step 2.2)

25. Verify undervoltage (UV) trip Contacted operator in CEDM N/A SAT UNSAT device position for Reactor Trip room.

Circuit Breakers TCB-2 and (Step TCB-6.

2.2) Requested verification of position of UV trip device armatures for Examiner Cue: TCB-2 and TCB-6.

CEDM Room operator reports UV Trip Device armatures for TCB-2 and TCB-6 are in contact with air gap adjusting screws.

(C) 26. Close TCB-2 and TCB-6. On panel 2C23, inserted key in N/A SAT UNSAT ESF reset push button keylock.

(Step 2.2.1) Placed key in UNLOCK position for TCB-2/6.

Depress TCB-2 and TCB-6 reset push button.

On panel 2C23 or panel 2C14, verified red light ON for TCB-2 and TCB-6.

Placed key in LOCK position.

END Stop Time:

ANO-2-JPM-NRC-CEA02 (S8) PAGE 8 OF 9 JOB PERFORMANCE MEASURE EXAMINERS COPY INITIAL CONDITIONS:

You are responsible for any applicable annunciators during the performance of this task.

All annunciators that are not applicable to this task will be performed by another operator.

TCB-02 has been repaired following a component malfunction The plant is in Mode 3 Supplement 1 Section 1.0 of 2105.009 is completed An operator is standing by in the CEDM room INITIATING CUE:

The CRS directs you to perform the Reactor Trip Circuit Breaker Test for TCB-2 only, using OP 2105.009 Supplement 1.0 section 2.1 and 2.2. Leave TCB-2 and TCB-6 closed.

ANO-2-JPM-NRC-CEA02 (S8) PAGE 9 OF 9 JOB PERFORMANCE MEASURE EXAMINEES COPY INITIAL CONDITIONS:

You are responsible for any applicable annunciators during the performance of this task.

All annunciators that are not applicable to this task will be performed by another operator.

TCB-02 has been repaired following a component malfunction The plant is in Mode 3 Supplement 1 Section 1.0 of 2105.009 is completed An operator is standing by in the CEDM room INITIATING CUE:

The CRS directs you to perform the Reactor Trip Circuit Breaker Test for TCB-2 only, using OP 2105.009 Supplement 1.0 section 2.1 and 2.2. Leave TCB-2 and TCB-6 closed.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 22 of 44 2105.009 CEDM CONTROL SYSTEM OPERATION CHANGE: 032 SUPPLEMENT 1 PAGE 1 OF 6 REACTOR TRIP CIRCUIT BREAKER TEST This test completed prior to each Reactor Startup unless performed in previous seven days IAW Tech Spec Table 4.3-1 (Item 1).

1.0 INITIAL CONDITIONS All Reactor Trip signals clear.

IF in Mode 3, 4 or 5 AND CEAs are capable of being withdrawn, THEN verify requirements of TCB/CEDMCS Status log (OPS-B26) satisfied to ensure compliance with TS 3.3.1.1 and 3.1.3.3.

IF in Mode 3, 4 or 5 AND CEAs are capable of being withdrawn, THEN enter TS 3.3.1.1 Table 3.3-1 action 8.

IF desired to close TCB-9 locally, THEN close using pushbutton.

2.0 TEST METHOD CAUTION If TCB Undervoltage Trip Device Armature NOT in contact with Air Gap Adjustment Screw, breaker may not open when required.

If a stuck out CEA exists then TCBs should not be closed since this could result in an inadequate shutdown margin.

  • 2.1 WHEN closing TCBs 1 through 8 in this supplement, THEN perform the following for selected TCBs:

2.1.1 Verify Undervoltage Trip Device Armature in contact with Air Gap Adjustment Screw IAW Plant Heatup (2102.002),

Exhibit 1, "Undervoltage Trip Device".

2.1.2 Obtain CPC Test/TCB close key (#15) from SM key locker.

2.1.3 On 2C23, place applicable "Reset Actuation Trip Path keylock in UNLK.

2.1.4 Close selected TCBs using pushbuttons on 2C23.

2.1.5 On 2C23, place applicable "Reset Actuation Trip Patch" keylock in LK.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 23 of 44 2105.009 CEDM CONTROL SYSTEM OPERATION CHANGE: 032 SUPPLEMENT 1 PAGE 2 OF 6 2.2 Test TCB-2 AND TCB-6 as follows: (Complete all steps in order written for each TCB before proceeding to next TCB.)

TCB-2 TCB-6 INSTRUCTION STEP 2HS/TEST 6HS/TEST Perform the following to test Shunt Trip: N/A N/A Verify TCB closed IAW step 2.1 Hold XHS/TEST in UV Bypass position. (X is TCB #)

Momentarily depress Reactor Trip pushbutton (2HS-907l-2) on 2C03.

Verify TCB opens.

Check 2K12-A10 alarm comes in or reflashes.

Release XHS/TEST. (X is TCB #)

Verify Reflash Unit 2K426 in 2C14 reset.

Perform the following to test UV Trip: N/A N/A Verify TCB closed IAW step 2.1 Hold XHS/TEST in Shunt Bypass position. (X is TCB #)

Momentarily depress Reactor Trip pushbutton (2HS-907l-2) on 2C03.

Verify TCB opens.

Check 2K12-A10 alarm comes in or reflashes.

Release XHS/TEST. (X is TCB #)

Verify Reflash Unit 2K426 in 2C14 reset.

2.2.1 IF desired to close TCB-2 and TCB-6, THEN refer to step 2.1.

Appendix D Scenario Outline Form ES-D-1 Facility: _ANO-2_________ Scenario No.: ___1 (New)______ Op-Test No.: _2015-1___

Examiners: ___________________________ Operators: ____________________________

Initial Conditions: 100%, 250 EFPD.

Turnover: Red Train Maintenance Week. EOOS indicates Minimal Risk.

Evolution scheduled: Add N2 to A Safety injection tank using 2104.001 section 11. NLO is standing by to align Nitrogen.

Event Malf. No. Event Event No. Type* Description 1 N (BOP) Add Nitrogen to A Safety Injection Tank.

N (SRO) OP-2104.001, Safety Injections Tank Operations.

2 XRCCHAPCNT I (ATC) A Pressurizer pressure control channel fails low.

I (BOP) OP-2203.028, Pressurizer System Malfunction AOP I (SRO) 3 K05-H05 C (BOP) 2A-4 Vital 4160 Bus Room cooler belts break.

C (SRO) OP-2203.012E Annunciator 2K05 Corrective Action.

4 SGATUBE R (ATC) A Steam Generator Tube leak ramps up to 12 gpm over 5 C (BOP) min.

C (SRO) OP-2203.038, Primary to Secondary leakage AOP TS (SRO) 5 CEA49STUCK C (ATC) CEA 49 fails to respond to insertion command.

C (SRO) OP-2203.003, CEA Malfunction AOP TS (SRO) 6 SGATUBE A Steam Generator Tube leak ramps up from 12 gpm to M (All) 100 gpm over 5 min causes Reactor Trip OP-2203.038, Primary to Secondary leakage AOP and OP-2202.001, Standard Post Trip Actions (SPTAs) EOP 7 FW2PW5AAFT A Main Feed water line breaks inside containment.

M (All) OP-2202.001, Standard Post Trip Actions (SPTAs) EOP and OP-2202.009, Functional Recovery EOP.

8 BS2P35AFAL C (BOP) Red Train Containment Spray pump fails to auto start.

C (SRO) OP-2202.010 Standard Attachments EOP.

End Post Blowdown RCS temperature and pressure have been point controlled and A SG has been isolated.

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Revision 0 Page 1 of 65

Appendix D Scenario Outline Form ES-D-1 Target Quantitative Attributes (Section D.5.d) Actual Attributes Malfunctions after EOP entry (1-2) 1 Abnormal Events (2-4) 4 Major Transients (1-2) 2 EOPs entered requiring substantive actions (1-2) 1 EOP contingencies requiring substantive actions (0-1) 1 Critical Tasks (2-3) 3 Critical Task Justification References Component cooling water to Exceeding operating limits has 1015.050 Time Critical RCPs must be restored within 10 the potential to degrade the RCS Operation action program, minutes of CIAS or All RCPs pressure boundary. RCPs Attachment C must be secured within the next should be maintained in an CE EPGB Simulator CTs:

10 minutes. available condition for last-resort CT-23, Trip any RCP exceeding use if needed. operating limits (FRG-04)

EOP OP-2202.001 Standard If RCPs are allowed to operate Post Trip Actions.

for 10 minutes without CCW AOP OP-2203.025 RCP flow. OP-1015.050 requires Emergencies.

RCPs not meeting operating limits to be secured within 10 minutes.

Stabilize and control RCS If RCS heatup is allowed after CE EPGB Simulator CTs:

temperature after the ESD SG blowdown, the RCS could CT-07, Establish RCS blowdown terminates. Maintain over pressurize and result in temperature Control (SPTA-07, RCS pressure within the lifting PZR and SG safeties. ESDE-05, HR-05)

Pressure-Temperature limits of These pressure stresses added 200°F and 30°F Margin to to thermal stresses of rapid Saturation throughout cooldown could present PTS implementation of SPTAs and concerns.

Functional Recovery EOP.

Isolate A SG (2202.010 Isolating the SG will minimize CE EPGB Simulator CTs:

Attachment 10 completed) within the potential loss of the CT-14, Isolate most affected SG 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after the Reactor trip. containment boundary, thus (HR-03).

Assumption is that the operator preventing an offsite release and SAR Section 15.1.18 will diagnose within 30 minutes exceeding 10CFR100 exposure 1015.050 Time Critical and then isolate within next 30 limits at the site boundary. Operation Actions, minutes after entry into Attachment C 2202.009, Functional Recovery EOP 2202.009, Functional EOP Recovery Tech Guide Scenario #1 Objectives

1) Evaluate individual ability to add Nitrogen to Safety Injection Tanks.
2) Evaluate individual response to a failure of the in-service Pressurizer Pressure Channel.
3) Evaluate individual response to a failure of vital electrical room cooler.
4) Evaluate individual response to a Steam Generator Tube leak.
5) Evaluate individual response to a failure of CEAs to respond.
6) Evaluate crew ability to mitigate a Steam Generator Tube Rupture.
7) Evaluate crew ability to mitigate an Excess Steam Demand.
8) Evaluate individual ability to respond to a failure of Green Train Containment Spray to Actuate.
9) Evaluate individual ability to combat events using the Functional Recovery procedure.

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Appendix D Scenario Outline Form ES-D-1 SCENARIO #1 NARRATIVE Simulator session begins with the plant at 100% power steady state.

When the crew has completed their control room walk down and brief, the BOP will add Nitrogen to the A Safety Injection Tank.

When the Nitrogen has been added or cued by lead examiner, the A pressurizer pressure control channel fails low. This will cause all backup heaters to energize raising RCS pressure and the permissive controller for the SDBCS to calculate the permissive setpoint incorrectly. The RCS pressure rise will cause reactor power to increase. The ATC will report that controlling pressurizer pressure channel has failed low and actual pressure is rising. The SRO will enter the Pressurizer System Malfunction AOP. The SRO will direct the ATC to swap pressurizer pressure control channels and BOP to align the Steam Dump Bypass Control System (SDBCS) for the A Pressurizer Pressure control channel failure. [Site OE: CR-ANO-2-2011-1605, Pressurizer pressure failing high, CR-ANO-2-2011-1575, Pressurizer level transmitter failed low due to a reference line failure.]

After the B pressurizer pressure control channel has been placed in service and the SDBCS is aligned with one permissive in manual and cued by the lead examiner, 2VUC-2A, 2A-4 Vital 4160V bus room cooler belts will break. This will cause a 2A-4 room cooler trouble alarm in the control room and actual room temperature to rise. The BOP will refer to OP-2203.012E, 2K05 Annunciator Corrective Actions (ACA). The BOP dispatches a NLO to investigate 2VUC-2A. The NLO will report broken belts on 2VUC-2A and the BOP will use the ACA to place 2VUC-2B room cooler in service. [Site OE: CR-ANO-2-2014-1955, Fan belt broken on room cooler]

After the BOP has started the idle vital bus room cooler and cued by lead examiner, a Steam Generator (SG) Tube Leak will occur on A Steam Generator. The SRO will enter OP 2203.038, Primary to Secondary Leakage AOP. The SRO will direct the ATC to perform power reduction to take the unit offline. He will also direct the BOP to isolate steam to A EFW pump from the A steam generator. The SRO should enter TS 3.4.6.2 Action a, RCS leakage, and TS 3.7.1.2 for EFW when steam is isolated to 2P-7A EFW pump. [Industry OE: SOER 83-2, Steam Generator Tube Ruptures.]

During the power reduction CEA 49 will fail to insert. The ATC will notice CEA 49 failed to respond to the insertion command in Manual Group. The crew may attempt to align the CEA in Manual individual but it will not respond. The SRO will enter OP-2203.003, CEA malfunction AOP. The crew will contact I&C to perform CEA traces and the SRO should enter TS 3.1.3.1 b due to immovable but aligned CEA. I&C will report a Control Element Drive System problem that can be fixed. The ATC should use group P CEA to control ASI until CEA 49 is repaired. [Site OE: CR-ANO-2-2007-0128, CEA 49 fails to respond to insertion commands]

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Appendix D Scenario Outline Form ES-D-1 SCENARIO #1 NARRATIVE (continued)

After the crew has completed the required reactivity manipulation, entered the appropriate tech specs, and cued by the lead examiner, The Steam Generator Tube leak will get larger. The CRS will perform the continuous action step in Primary to Secondary Leakage AOP to trip the reactor, actuate Safety Injection Actuation Signal (SIAS), actuate Containment Cooling Actuation Signal (CCAS), and go to Standard Post Trip Actions (SPTAs). [Industry OE: SOER 83-2, Steam Generator Tube Ruptures. Steam Generator Tube Rupture response is a time critical operator action per OP-1015.050 Time Critical Operator action program.]

The crew will implement OP-2202.001, Standard Post Trip Actions (SPTA) EOP. The crew will assess safety functions. After the reactor trips a Main Feedwater line break (A SG due to pressure surge from reactor trip causing the feedwater check valve cap to leak) inside containment will cause an Excess Steam Demand. Main Steam Isolation (MSIS) and Containment Spray (CSAS) will actuate tripping Main Feedwater pumps, Condensate pumps, AFW pump, closing the MSIVs and feedwater block valves. The crew should recognize that red train Containment Spray pump failed to start. The crew should send a NLO to the breaker and to the pump. After, the NLOs report no issues the BOP should start the red train spray pump 2P-35A. Containment Isolation Action Signal (CIAS) will occur causing a loss of Component Cooling Water (CCW) to the Reactor Coolant Pumps (RCPs) the crew will secure RCPs due to the loss of CCW flow causing natural circulation of the RCS. [Industry OE for Excess Steam Demand, SOER 82-7, Reactor Vessel Pressurized Thermal Shock. CR-ANO-2-2009-375, 2P-35A Spray pump failed to respond to handswitch. CR-ANO-2-2006-0848, Component failed to respond to SIAS signal. PRA item # 5 Trip RCPs after loss of CCW in order to avert RCP seal LOCA.]

After completing SPTAs, The SRO will diagnose Excess Steam Demand and Steam Generator Tube Rupture events and enter OP-2202.009, Functional Recovery EOP. The crew will maintain post blowdown temperature and pressure of the RCS to prevent pressurized thermal shock. The BOP will steam B SG using the upstream Atmospheric Dump valve when A SG blows dry. The ATC should use Auxiliary Spray to maintain RCS pressure. The Crew will isolate the A SG using OP-2202.010 Standard Attachment 10.

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Appendix D Scenario Outline Form ES-D-1 Simulator Instructions for Scenario 1 Reset Simulator to appropriate IC.

A channel pressurizer pressure and level controllers are in service.

T1, T2, T3, & T4, set to false.

T4 on Reactor Trip.

Event Malf. No. Value/ Event No. Ramp Description Time 1 Add Nitrogen to A Safety Injection Tank.

OP-2104.001, Safety Injections Tank Operations.

2 XRCCHAPCNT 0 A Pressurizer pressure control channel fails low.

Trigger 1 OP-2203.028, Pressurizer System Malfunction AOP 3 K05-H05 active Vital Electrical 4160 Bus Room cooler belts break.

Trigger 2 OP-2203.012E Annunciator 2K05 Corrective Action.

4 SGATUBE 12 gpm A Steam Generator Tube leak ramps up to 12 gpm over Trigger 3 / 5 min. 5 min.

OP-2203.038, Primary to Secondary leakage AOP 5 CEA49STUCK 0 CEA 49 fails to respond to insertion command.

OP-2203.003, CEA Malfunction AOP 6 SGATUBE 100 / 5 A Steam Generator Tube leak ramps up from 12 gpm to min. 100 gpm over 5 min causes Reactor Trip OP-2203.038, Primary to Secondary leakage AOP and OP-2202.001, Standard Post Trip Actions (SPTAs)

EOP 7 FW2PW5AAFT 6000 A Main Feed water line breaks inside containment.

gpm/ 5 OP-2202.001, Standard Post Trip Actions (SPTAs)

Trigger 4 min. EOP and OP-2202.009, Functional Recovery EOP.

Delay =

30 sec.

8 BS2P35AFAL active Red Train Containment Spray pump fails to auto start.

OP-2202.010 Standard Attachments EOP.

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Appendix D Scenario Outline Form ES-D-1 Simulator Operator CUEs At T=0 Add Nitrogen to A Safety Injection Tank.

Cue: When Contacted as NLO to align N2, then report that high pressure Nitrogen has been aligned IAW Exhibit 7.

Cue: When Contacted as NLO to align N2, then report that high pressure Nitrogen has been secured IAW Exhibit 7.

Cued by Trigger T1 B Pressurizer pressure control channel fails low.

lead examiner Cue: If contacted as work management, state that you will contact I&C to investigate the failure.

Cued by Trigger T2 Vital Electrical 4160 Bus Room cooler belts break.

lead examiner Cue: When requested to investigate 2VSF-2A, wait one minute and then report that the belts are broken on 2VSF-2A. Fan suction is not obstructed, Fan filters are clean and Drip pan is not clogged.

Cue: If requested as work management, report that a planner will begin planning work to replace the belts.

Booth Operator Note: When 2VUC-2A is stopped return K05-H05 to normal.

Cued by Trigger T3 A Steam Generator Tube leak ramps up to 12 gpm over 5 min.

lead examiner Cue: When contacted as Chemistry, respond that you will implement 2602.001 Primary to Secondary leakage.

Cue: If contacted as the above people, acknowledge the information concerning the power reduction.

Cue: If contacted as a NLO and/or chemistry, report that you will secure Zinc injection and monitor secondary chemistry.

Cue: If contacted as chemistry, report that you will obtain an RCS sample for Iodine at the time requested.

Cued by Trigger T4 CEA 49 fails to respond to insertion command.

lead examiner Cue: When contacted as the work management or I&C to troubleshoot, wait 5 minutes and then call and report that you are going to commence troubleshooting.

Ask the control room to insert CEA 49 for traces.

Cue: After CEA 49 insertion is attempted, wait one minute then report that CEA 49 is not inserting due to a failed hall effect transducer and it will have to be replaced.

Cued by A Steam Generator Tube leak ramps up from 2 gpm to 100 gpm over lead 5 min causes Reactor Trip examiner Cue: If contacted as the STA to report to the control room, acknowledge the request.

Cue: If contacted as a NLO to perform Attachment 47 Field Operator Post Trip Actions, acknowledge request.

Cue: When contacted as Chemistry, then report you will sample A S/G for activity and Monitor RDACS for off site dose releases.

Cue: If contacted to remove the danger tags and close the LTOP breakers, then wait 2 minutes and use the remote function for 2B51-E4 and 2B51-K2 to close the breakers and inform the control room that 2B51-E4 and 2B51-K2 are closed.

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Appendix D Scenario Outline Form ES-D-1 Red Train Containment Spray pump fails to auto start.

Cue: If contacted as NLO to investigate 2P-35A spray pump and breaker, then after ~ 1 min. report the breaker is open and looks normal locally. After ~ 2 min. report that 2P-35A motor and pump look normal locally.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 1 Event

Description:

Add Nitrogen to A Safety Injection Tank.

Time Position Applicant's Actions or Behavior Procedure Note: If raising SIT level or pressure prior to/or during plant heatup, then SIT levels should be high and pressures low in operability band to ensure low level, high pressure condition will not be created when SITs heatup.

11.1 Verify HP Nitrogen Supply aligned with N2 regulator set at desired pressure using N2 System Operations (2104.009), Exhibit 7, Nitrogen BOP Manifold Operations.

Cue: When Contacted as NLO to align N2, report that high pressure Nitrogen has been aligned IAW Exhibit 7.

11.2 Open Supply Header to Containment Isolation 2CV-6207-2 (2HS-6207-2).

BOP Procedure Caution: Cross-connecting SITs via nitrogen supply valves in Modes 1, 2 and 3 (with RCS pressure greater than or equal to 700 psia) will cause associated SITs to be inoperable.

11.3 IF desired to raise pressure in SIT (2T-2A),

THEN perform the following:

11.3.1 Open N2 Supply valves 2SV-5005A/B (2HS-5005).

BOP 11.3.2 WHEN 2T-2A at desired pressure, THEN close N2 Supply valves 2SV-5005A/B (2HS-5005).

11.7 Close Supply Header to Containment Isolation 2CV-6207-2 (2HS-BOP 6207-2).

11.8 Verify HP N2 from Unit 1 secured IAW N2 System Operations BOP (2104.009), Exhibit 7, Nitrogen Manifold Operations.

Cue: When Contacted as NLO to align N2, report that high pressure Nitrogen has been secured IAW Exhibit 7.

Termination criteria: When Nitrogen has been added to the SIT or at the discretion of the lead examiner.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 2 Event

Description:

A Pressurizer pressure control channel fails low.

Time Position Applicant's Actions or Behavior Cued by Announce alarm 2K10-E6, CNTRL CH 1 PRESSURE HI/LO and B Lead ATC Channel Pressure is reading low and actual pressure is rising.

Examiner SRO Implement OP-2203.028 PZR Systems Malfunction AOP.

1. Check the following criteria:

D. Check "CNTRL CH 1/2 PRESSURE HI/LO" annunciators (2K10-SRO E6/E7) clear.

Examiners Note: Step D is not met, perform contingency D. GO TO Step 6.

SRO

6. Check "CNTRL CH 1/2 PRESSURE HI/LO" annunciators (2K10-E6/E7) clear.

SRO Examiners Note: Step 6 is not met, perform contingency

6. Perform the following:

A. Compare PZR pressure instruments to determine affected ATC channel.

B. IF BOTH PZR Pressure Control channels failed, THEN perform the following:

1) Manually control PZR Heaters and Spray Valves to restore RCS pressure 2025 psia to 2275 psia.

SRO

2) Place the SDBCS in required contingency alignment using Attachment A, SDBCS Operations.

Examiners Note: Step 6.B is N/A.

C. IF only the selected control channel affected, THEN perform the following:

ATC

1) Place PZR Pressure Channel Select switch (2HS-4626) to the unaffected channel.

Procedure Note:

Proportional Heater controller is located on Page 3.

2) Restore PZR Spray valves and Heater control to automatic.

ATC Revision 0 Page 9 of 65

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 2 Event

Description:

A Pressurizer pressure control channel fails low.

Time Position Applicant's Actions or Behavior SRO directs the BOP to perform Attachment A for the channel 1 failure.

D. IF Pressure Control Channel 1 failed, THEN place the SDBCS in required contingency alignment using Attachment A, SDBCS Operations.

E. IF Pressure Control Channel 2 failed, SRO THEN place the SDBCS in required contingency alignment using Attachment A, SDBCS Operations.

Examiners Note: Step 6.E is N/A.

BOP Implement Attachment A steps for the channel 2 failure.

Procedure Note:

Failure of PZR Pressure Control Channel 1 will result in SDBCS Main calculator producing an incorrect setpoint.

1. IF PZR Pressure Control Channel 1 failed, THEN perform the following:

A. Place SDBCS Master controller (2PIC-0300) in Auto Local.

Att. A BOP B. Adjust setpoint to 1010 psia.

Cue: If contacted as work management, state that you will contact I&C to investigate the failure.

Termination Criteria: When the Pressurizer Pressure Channels have been swapped and Attachment A action are complete or at discretion of lead examiner.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 3 Event

Description:

Vital Electrical 4160V bus room cooler belts break.

Time Position Applicant's Actions or Behavior Cued by ANY Announce annunciator 2K05-H5, 2VUC-2A/B TROUBLE/TEMP HI.

lead examiner BOP/SRO Implement ACA 2203.012E Annunciator 2K05 Corrective Action.

1.0 CAUSES 1.1 Discharge air temperature on EITHER of the following Coolers greater than 130°F:

2A-4 Room Cooler 2VUC-2A (2TIS-8654-2A) 2A-4 Room Cooler 2VUC-2B (2TIS-8654-2B) 1.2 Air flow on EITHER of the following Coolers less than 3000 cfm 20 seconds after start:

BOP/SRO 2VUC-2A (2FS-8654-2A) 2VUC-2B (2FS-8654-2B) 1.3 2VUC-2A drip pan level (2LS-8654-2A) greater than 1 inch.

1.4 2VUC-2B drip pan level (2LS-8654-2B) greater than 1 inch.

2.0 ACTION REQUIRED 2.1 Determine affected Room cooler:

2VUC-2A 2VUC-2B BOP 2.2 Verify Room coolers running as required:

2VUC-2A (2HS-8652-2) 2VUC-2B (2HS-8654-2)

Examiner Note: Normally on one room cooler is running.

2.3 Verify SW Inlet open for running fan(s):

BOP 2VUC-2A SW Inlet 2CV-1486-2 (2HS-1486-2) 2VUC-2B SW Inlet 2CV-1487-2 (2HS-1487-2)

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 3 Event

Description:

Vital Electrical 4160V bus room cooler belts break.

Time Position Applicant's Actions or Behavior The BOP should dispatch a NLO to investigate 2VSF-2A including the following items:

2.4 Check the following:

BOP Fan suction unobstructed Fan filters clean Drip pan drains unclogged Cue: When requested to investigate 2VSF-2A, wait one minute and then report that the belts are broken on 2VSF-2A. Fan suction is not obstructed, Fan filters are clean and Drip pan is not clogged.

Cue: If requested as work management, report that a planner will begin planning work to replace the belts.

2.5 IF deficiencies noted, THEN verify WR/WO submitted.

BOP/SRO Examiner Note: This may be performed later or they may contact work management to perform this action.

2.6 IF necessary to swap fans, THEN perform the following:

2.6.1 IF 2VUC-2A is the affected fan, THEN perform the following:

BOP A. Start 2VUC-2B (2HS-8654-2).

B. Verify 2VUC-2B SW Inlet (2CV-1487-2) opens.

Booth Operator Note: When 2VUC-2A is stopped return K05-H05 to normal.

BOP C. Stop 2VUC-2A (2HS-8652-2).

D. Close 2VUC-2A SW Inlet 2CV-1486-2 (2HS-1486-2).

Termination criteria: When 2VUC-2B has been placed in service or at lead examiner's discretion.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 4 Event

Description:

A Steam Generator Tube leak ramps up to 12 gpm over 5 min.

Time Position Applicant's Actions or Behavior Cued by ANY Announce alarm 2K11-A10 SEC SYS RADIATION HI.

lead examiner SRO Enter OP-2203.038, Primary to Secondary leakage AOP.

SRO 1. Open Placekeeping page.

2. Notify Control Board Operators to monitor floating steps.

Procedure Note:

N-16 monitors only calculate SG leak rates with plant power (CV-9000) greater than 20%.

  • 3. Determine Primary to Secondary leakrate by ANY of the following:

Computer RCS LKRT programs.

Check PZR level stable and use Charging and Letdown mismatch minus Controlled Bleed Off.

Check Letdown isolated and estimate RCS leak rate by total Charging flow minus Controlled Bleed Off.

ANY Chemistry leakrate calculation using 1604.013, Measurement of Primary to Secondary Leakage.

SG Tube Leak N-16 monitors.

Manual leakrate calculation.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 4 Event

Description:

A Steam Generator Tube leak ramps up to 12 gpm over 5 min.

Time Position Applicant's Actions or Behavior

4. Determine leaking SG by ANY of the following:

A. Secondary Systems Radiation Trend recorder:

2RR-1057 B. SG Sample Radiation monitors:

2RITS-5854 2RITS-5864 ANY C. Main Steam Line Radiation monitors:

2RI-1007 2RI-1057 D. SG water sample results.

E. SG Tube Leak N-16 monitors.

  • 5. Control Charging and Letdown to maintain PZR level within 5% of ATC setpoint.
6. Check BOTH of the following are true:

RCS leakage LESS than 44 gpm PZR level maintained within 10% of setpoint ANY Examiner Note: The conditions of step 6 will be true when the first time the crew completes the step however they will become not true later in the event and the SRO will transition to the contingency column.

7. Notify Chemistry to implement 2602.001, Primary to Secondary ANY Leakage.

Cue: When contacted as Chemistry, respond that you will implement 2602.001 Primary to Secondary leakage.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 4 Event

Description:

A Steam Generator Tube leak ramps up to 12 gpm over 5 min.

Time Position Applicant's Actions or Behavior Procedure Note:

Leakage (including leakage spike) is confirmed if TWO independent radiation monitors trending upward.

The probability of locating a tube leak after plant shutdown with leakrates less than 50 gpd (.035 gpm) is low.

8. WHEN confirmed primary to secondary leakrate determined, THEN perform the applicable action per the table below:

Parameter Value Action ANY SG 44 gpm GO TO Step 6.

OR TOTAL (BOTH SGs)

ANY SG > 100 gpd (> 0.069 Perform ACTION LEVEL THREE gpm) section of Attachment A while continuing with this procedure.

SRO ANY SG 75 gpd (0.052 gpm) Perform ACTION LEVEL TWO section of Attachment A while continuing with this procedure.

ANY SG 30 gpd (.021 gpm) Perform ACTION LEVEL ONE section of Attachment A while continuing with this procedure.

TOTAL 5 gpd (.0035 gpm) Perform RAISED MONITORING (both SGs) section of Attachment A while continuing with this procedure.

TOTAL (both SGs) < 5 gpd (.0035 gpm) Perform ACTION PLAN of Attachment A while continuing with this procedure.

SRO The SRO will transition to Action Level Three of Attachment A.

1. ACTION LEVEL THREE (> 100 gpd)

A. Record current time: ____________

SRO *B. IF ANY SG leakrate rises to 44 gpm THEN GO TO Step 6 in the body of this procedure.

Action level three Examiner Note: This step is not currently applicable but will become applicable when the leakrate rises.

C. IF at power, THEN perform the following:

ATC/SRO 1) Refer to applicable reactivity plan.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 4 Event

Description:

A Steam Generator Tube leak ramps up to 12 gpm over 5 min.

Time Position Applicant's Actions or Behavior

2) Perform the following using 2102.004, Power Operations OR 2203.053, Rapid Power Reduction as necessary to be < 50% power within one hour of time recorded above, AND in Mode 3 in the following two hours:
  • a) IF RCS leakage greater than or equal to 10 gpm, THEN perform RCS boration using2104.003, Chemical Addition, Attachment R, RCS Boration From theRWT OR BAMT.

b) IF leakage less than 10 gpm, SRO THEN perform EITHER of the following:

RCS boration using 2104.003, Chemical Addition, Attachment R, RCS Boration from the RWT or BAMT.

RCS boration using 2104.003, Chemical Addition, Exhibit 3, Normal RCS Boration at Power.

Examiner Note: The SRO will direct a power reduction using either power operations procedure or Rapid Power Reduction AOP.

SRO The SRO will transition to OP-2203.053 Rapid Power Reduction AOP or OP-2102.004 Power Operations emergent power reduction section.

Examiner Note: Power operations procedure steps start on page 21.

OP-2203.053Rapid Power Reduction AOP Procedure Note:

Use of this procedure may be terminated at any point if a complete shutdown is not required.

Shutdown rate shall be based on plant conditions and safety considerations. Rate may be raised or lowered as plant conditions warrant.

  • 1. IF at any time, it is determined that significant manual actions are required to EITHER maintain the plant online, OR maintain the desired maneuvering rate, THEN perform the following:

Rapid ANY Power A. Trip the Reactor.

Reduction AOP B. GO TO 2202.001, Standard Post Trip Actions.

2. Commence Power reduction using appropriate reactivity plan.

ATC ATC The ATC will transition to OP-2104.003, Chemical Addition, Attachment R to commence boration.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 4 Event

Description:

A Steam Generator Tube leak ramps up to 12 gpm over 5 min.

Time Position Applicant's Actions or Behavior Procedure Caution:

Do NOT use BAMT and RWT as boration sources at same time.

Additional CCP starts while aligned to RWT or BAMT suction will result in more boration.

With VCT isolated (Outlet closed and divert flow aligned to BMS), CBO flow will result in VCT level rise with no control process in place to limit level rise. (CR-ANO-2-2009-01786)

Procedure Caution:

The following section has been determined to have a Reactivity Addition Potential (RAP) and this activity is classified as a Risk Level R2.

Procedure Note:

For an Unplanned Reactivity Manipulation, the required controls for planned reactivity evolutions are not applicable during AOP (including ACA response) or EOP conditions IAW COPD-030.

ANY 1.0 IF a Reactivity Management Brief has NOT been conducted, THEN perform a Reactivity Management Brief per COPD-030 with an SRO.

Examiner Note: This step in N/A when an AOP has been entered.

ATC 2.0 Determine desired boration rate, dilution flow, and number of 2104.003 required charging pumps from Reactivity Plans located in Plant Data Att. R Book or by manual calculation.

boration steps.

Examiner Note: During the first 15 minutes of the power reduction the crew will run 2 charging pumps with suction from the RWT. They will dilute at ~14 gpm and insert group 6 CEAs 6 for ASI control ATC 3.0 Verify Blending Tee aligned to CCP Suction.

Procedure Note:

Placing VCT Inlet/Divert valve 2CV-4826 in BMS position will change RCS leakage indications.

ATC 4.0 IF VCT level greater than 62 percent, THEN place 2HS-4826 (VCT Inlet/Divert valve 2CV-4826) to BMS position.

2104.003 5.0 IF desired, Att. R boration THEN record initial controller data:

steps.

2FIC-4926 Setpoint: ___________ Demand: _____________

2FIC-4927 Setpoint: ___________ Demand:_____________

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 4 Event

Description:

A Steam Generator Tube leak ramps up to 12 gpm over 5 min.

Time Position Applicant's Actions or Behavior ATC 6.0 Perform the following to align for dilution:

6.1 Verify the following on Boric Acid MU Flow controller (2FIC-4926):

In MANUAL Demand set to MINIMUM 6.2 Verify EITHER Reactor Makeup pump running:

2P-109A (2HS-4965) 2P-109B (2HS-4966) 6.3 Verify Reactor Makeup Water Flow controller (2FIC-4927) set as follows:

2104.003 Att. R boration 6.3.1 Setpoint set to desired flow rate.

steps.

6.3.2 IF in MANUAL,THEN demand set to desired value.

6.4 Open VCT Makeup Isolation (2CV-4941-2) (2HS-4941-2).

7.0 Open one of the following valves from a boric acid source:

Charging Pump Suction from RWT (2CV-4950-2)

(2HS-4950-2)

BAMT (2T-6A) Gravity Feed (2CV-4920-1) (2HS-4920-1)

BAMT (2T-6B) Gravity Feed (2CV-4921-1) (2HS-4921-1)

ATC 8.0 Close VCT Outlet (2CV-4873-1) (2HS-4873-1).

Examiner Note: Step 8 starts the down power.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 4 Event

Description:

A Steam Generator Tube leak ramps up to 12 gpm over 5 min.

Time Position Applicant's Actions or Behavior ATC 9.0 Verify VCT Inlet/ Divert valve 2CV-4826 (2HS-4826) in BMS position.

  • 10.0 Perform the following to Start/Stop additional Charging pumps:

10.1 IF desired to raise flow, THEN perform the following:

A. Start additional charging pumps as necessary.

B. Adjust Reactor Makeup Water flow as necessary to maintain desired shutdown rate (2FIC-4927).

10.2 IF desired to lower flow, THEN perform the following:

A. Adjust Reactor Makeup Water flow as necessary to maintain desired shutdown rate (2FIC-4927).

2104.003 B. Secure additional Charging Pumps as necessary.

Att. R boration steps. ATC 11.0 Perform the following to initiate dilution flow:

11.1 Place Mode Select switch (2HS-4928) in MANUAL.

11.2 Verify Boric Acid MU Flow controller (2FIC-4926) indicates zero.

  • 11.3 Verify Reactor Makeup Water Flow controller (2FIC-4927) indicates desired flow rate.

11.4 Verify BAM Tank Recirc valve open for running pump:

2T-6A recirc (2HS-4903-2) 2T-6B recirc (2HS-4915-2)

SRO The SRO will continue to OP-2203.053, Rapid Power reduction AOP.

Procedure Note:

The CBOT is the preferred RO to lower turbine load so that the ATC can focus on primary plant control.

However, either individual can operate the turbine as plant conditions dictate.

BOP *3. Lower Turbine load as necessary to hold Tave within +/- 3°F of program Tref.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 4 Event

Description:

A Steam Generator Tube leak ramps up to 12 gpm over 5 min.

Time Position Applicant's Actions or Behavior Procedure Note:

CEAs should not be inserted below 80 inches withdrawn when the Reactor is at power and the CPC Aux trip is active. ASI would tend to shift back to the top of the core if CEAs are inserted more than halfway.

ASI response to power changes at the end of core life is more severe, at times significantly so.

The effects of ASI may not be seen until well into the power change.

QASI (PID 187) provides the CPC Aux Trip function at +/- 0.45.

The Reactivity Plan provides information on CEA positioning to minimize the undesired ASI response.

ATC *4. Perform the following for ASI:

Maintain ASI within Core Operating Limits Report (COLR) limits using CEA Group 6 or Group P.

Use ONE of the following to monitor ASI closely:

- COLSS (CV9198)

- IF COLSS inoperable, THEN use CPC channel ASI (PID 268) that most closely agreed with COLSS when it was operable.

Periodically monitor QASI (PID 187).

BOP *5 IF desired to transfer unit auxiliaries from Unit Aux transformer to SU #3, THEN perform Attachment A, Transferring Loads to SU #3.

BOP *6 Throttle Condensate recircs as necessary to maintain 650-750 psig Condensate Pump Discharge pressure:

2CV-0662 (2FIC-0662) 2CV-0663 (2FIC-0663)

ANY 7. Perform notifications of power reduction using Attachment B, Notifications.

ANY *8. Monitor Secondary chemistry and adjust chemical feed as needed using 2106.028, Secondary System Chemical Addition.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 4 Event

Description:

A Steam Generator Tube leak ramps up to 12 gpm over 5 min.

Time Position Applicant's Actions or Behavior ANY 9. WHEN at ~ 80% power, THEN perform the following:

A. Initiate action to perform channel calibration within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of last successful channel check (OPS-B6).

B. IF MSR Stage 2 Hi Load valves (2CV-0404/0464) have NOT closed automatically, THEN verify the following valves closed (2HS-0404):

2CV-0404 2CV-0464 Examiner Note: OP-22013.038 Primary to Secondary Leakage AOP steps are continued on Page 28.

OP-2102.004 Power Operations emergent power reduction section.

Procedure Caution:

The following section has been determined to have a Reactivity Addition Potential (RAP) and this activity is classified as a Risk Level R1.

For an Unplanned Reactivity Manipulation, the required controls for planned reactivity evolutions are not applicable during AOP (including ACA response) or EOP conditions IAW COPD-030.

12.1 IF time allows AND Reactivity Management Brief has NOT been conducted, THEN perform a Reactivity Management Brief per COPD-030 with an Power SRO.

Operation SRO power reduction.

Examiner Note: Formal Reactivity Brief is not required per COPD-030 due to AOP implementation, however a transient reactivity brief should be conducted IAW transient standards and may take place after the power reduction has started.

Procedure Note:

Power Plant parameters may be monitored using Exhibit 2, Various Parameters Vs Operation Reactor Power.

power reduction. Boron adjustment data for power change may be obtained from Reactivity curves located in Plant Data book.

12.2 IF plant must be off-line within one hour, SRO THEN refer to Attachment H, Rapid Power Reduction.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 4 Event

Description:

A Steam Generator Tube leak ramps up to 12 gpm over 5 min.

Time Position Applicant's Actions or Behavior Procedure Note:

Initially, only enough boric acid should be added to reduce power by a few percent (less than 5%). As power lowers, Xenon will start to peak causing power to drop faster. Dilution may be required to slow power reduction rate.

If one BAM Tank is out of service for Acid Reducing Chemistry, depletion of on-line BAMT during power reduction may result in TRM 3.1.8 entry.

12.3 Commence Power reduction by performing the following as necessary:

Boration using Normal Borate Mode to Charging pump suction (unless directed otherwise by Abnormal Operating Procedure).

Refer to Chemical Addition (2104.003), Exhibit 3, Normal RCS Boration at Power.

ATC Boration from RWT or BAMT using Chemical Addition (2104.003),

Attachment R, RCS Boration From The RWT or BAMT.

CEA insertion using CEDMCS Control System Operation (2105.009), Exhibit 3 CEDMCS Operations (normally for ASI control).

Examiners Note: The ATC will commence power reduction using 2104.003, Attachment R, due to the SGTR being 12 gpm.

The ATC will transition to OP-2104.003, Chemical Addition, Attachment R ATC to commence boration.

Procedure Caution:

Do NOT use BAMT and RWT as boration sources at same time.

Additional CCP starts while aligned to RWT or BAMT suction will result in more boration.

With VCT isolated (Outlet closed and divert flow aligned to BMS), CBO flow will result in VCT level rise with no control process in place to limit level rise. (CR-ANO-2-2009-01786)

Procedure Caution:

The following section has been determined to have a Reactivity Addition Potential (RAP) and this activity is classified as a Risk Level R2.

Procedure Note:

For an Unplanned Reactivity Manipulation, the required controls for planned reactivity evolutions are not applicable during AOP (including ACA response) or EOP conditions IAW COPD-030.

ANY 1.0 IF a Reactivity Management Brief has NOT been conducted, 2104.003 THEN perform a Reactivity Management Brief per COPD-030 with Att. R an SRO.

boration steps.

Examiner Note: This step in N/A when an AOP has been entered.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 4 Event

Description:

A Steam Generator Tube leak ramps up to 12 gpm over 5 min.

Time Position Applicant's Actions or Behavior 2104.003 ATC 2.0 Determine desired boration rate, dilution flow, and number of Att. R required charging pumps from Reactivity Plans located in Plant Data boration Book or by manual calculation.

steps.

Examiner Note: During the first 15 minutes of the power reduction the crew will run 2 charging pumps with suction from the RWT. They will dilute at ~45 gpm and insert group 6 CEAs 6 for ASI control ATC 3.0 Verify Blending Tee aligned to CCP Suction.

Procedure Note:

Placing VCT Inlet/Divert valve 2CV-4826 in BMS position will change RCS leakage indications.

ATC 4.0 IF VCT level greater than 62 percent, THEN place 2HS-4826 (VCT Inlet/Divert valve 2CV-4826) to BMS position.

2104.003 5.0 IF desired, Att. R boration THEN record initial controller data:

steps.

2FIC-4926 Setpoint: ___________ Demand: _____________

2FIC-4927 Setpoint: ___________ Demand:_____________

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 4 Event

Description:

A Steam Generator Tube leak ramps up to 12 gpm over 5 min.

Time Position Applicant's Actions or Behavior ATC 6.0 Perform the following to align for dilution:

6.1 Verify the following on Boric Acid MU Flow controller (2FIC-4926):

In MANUAL Demand set to MINIMUM 6.2 Verify EITHER Reactor Makeup pump running:

2P-109A (2HS-4965) 2P-109B (2HS-4966) 6.3 Verify Reactor Makeup Water Flow controller (2FIC-4927) set as follows:

2104.003 Att. R boration 6.3.1 Setpoint set to desired flow rate.

steps.

6.3.2 IF in MANUAL,THEN demand set to desired value.

6.4 Open VCT Makeup Isolation (2CV-4941-2) (2HS-4941-2).

7.0 Open one of the following valves from a boric acid source:

Charging Pump Suction from RWT (2CV-4950-2)

(2HS-4950-2)

BAMT (2T-6A) Gravity Feed (2CV-4920-1) (2HS-4920-1)

BAMT (2T-6B) Gravity Feed (2CV-4921-1) (2HS-4921-1)

ATC 8.0 Close VCT Outlet (2CV-4873-1) (2HS-4873-1).

Examiner Note: Step 8 starts the down power.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 4 Event

Description:

A Steam Generator Tube leak ramps up to 12 gpm over 5 min.

Time Position Applicant's Actions or Behavior ATC 9.0 Verify VCT Inlet/ Divert valve 2CV-4826 (2HS-4826) in BMS position.

  • 10.0 Perform the following to Start/Stop additional Charging pumps:

10.1 IF desired to raise flow, THEN perform the following:

A. Start additional charging pumps as necessary.

B. Adjust Reactor Makeup Water flow as necessary to maintain desired shutdown rate (2FIC-4927).

10.2 IF desired to lower flow, THEN perform the following:

A. Adjust Reactor Makeup Water flow as necessary to maintain desired shutdown rate (2FIC-4927).

2104.003 B. Secure additional Charging Pumps as necessary.

Att. R boration steps. ATC 11.0 Perform the following to initiate dilution flow:

11.1 Place Mode Select switch (2HS-4928) in MANUAL.

11.2 Verify Boric Acid MU Flow controller (2FIC-4926) indicates zero.

  • 11.3 Verify Reactor Makeup Water Flow controller (2FIC-4927) indicates desired flow rate.

11.4 Verify BAM Tank Recirc valve open for running pump:

2T-6A recirc (2HS-4903-2) 2T-6B recirc (2HS-4915-2)

SRO The SRO will continue to OP-2102.004, Power Operations emergent power reduction.

BOP 12.4 Lower Turbine load as necessary to hold Tave within +/- 2°F of program Tref using Exhibit 1, TAVE VS TREF.

12.4.1 IF desired to stop Turbine load OR Power reduction, 2102.004 THEN perform the following as necessary:

Power Operations A. Secure RCS Boration using Chemical Addition (2104.003).

B. Commence RCS dilution using Chemical Addition (2104.003).

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 4 Event

Description:

A Steam Generator Tube leak ramps up to 12 gpm over 5 min.

Time Position Applicant's Actions or Behavior ANY *12.5 IF any Group 6 or P CEA RSPT inoperable due to spiking, T-Mod, etc.,

THEN refer to CPC/CEAC Operations (2105.001) to perform the following as required:

IF Group 6 or P must be inserted below 138.58 inches AND all inoperable RSPTs in group input to same CEAC, THEN place affected CEAC in INOP in all operable CPCs.

IF Group 6 or P must be inserted below 138.58 inches AND inoperable RSPTs in group input to BOTH CEACs, THEN perform the following:

2102.004 Power - Place BOTH CEACs in INOP in ALL operable CPCs Operations - Restrict usage to Group 6 in accordance with TS 3.1.3.6.

IF Group 6 or P insertion required due to a transient condition before CEACs can be placed in INOP, THEN declare affected CEACs inoperable when group inserted below 138.58 inches.

SRO 12.6 IF plant shutdown/power reduction directed by TECH SPECS, THEN initiate ATTACHMENT L to determine mode specific time limits and continue with shutdown.

Examiner Note: The SRO should give attachment L to the Shift Manager to perform.

Procedure Note:

CEAs should not be inserted below 80 inches withdrawn when the Reactor is at power and the CPC Aux trip is active. ASI would tend to shift back to the top of the core if CEAs are inserted more than halfway.

ASI response to power changes at the end of core life is more severe, at times significantly so.

The effects of ASI may not be seen until well into the power change.

QASI (PID 187) provides the CPC Aux Trip function (trip setpoint +/- 0.45).

The Reactivity Plan provides information on CEA positioning to minimize the undesired ASI response.

ATC *12.7 Perform the following for ASI:

Maintain ASI (PID 268) within Core Operating Limits Report (COLR) limits using CEA Group 6 or Group P.

Periodically monitor QASI (PID 187).

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 4 Event

Description:

A Steam Generator Tube leak ramps up to 12 gpm over 5 min.

Time Position Applicant's Actions or Behavior SRO 12.9 IF unit auxiliaries powered from Unit Aux transformer AND desired to transfer electrical loads to SU #3, THEN perform the following:

12.9.1 Verify SU #3 available.

12.9.2 WHEN desired to transfer electrical loads, THEN transfer to SU #3 Transformer using Electrical System Operations (2107.001).

BOP 12.10 Throttle Condensate recircs as necessary to maintain 650-750 psig Condensate Pump Discharge pressure:

2CV-0662 (2FIC-0662) 2CV-0663 (2FIC-0663)

Procedure Note:

Do not tell Woodlands (SPO/EMO) (Power Marketing Corp.) anything other than the current status of the unit (e.g. we are going off-line). The TOC and SOC are the Entergy Transmission Organization and are responsible for monitoring the Grid System; this includes ensuring the adequacy of the ONLINE monitoring tool. Therefore, they can be given more specific information regarding the reason for the shutdown. Reference ENS-DC-201.

ANY 12.11 Notify the following of power reduction:

Chemistry Reactor Engineering Radiation Protection Little Rock Dispatcher (TOC)

Woodlands Dispatcher (SPO/EMO)

Cue: If contacted as the above people, acknowledge the information concerning the power reduction.

SRO 12.12 Perform the following for Chemistry Control:

Monitor Secondary chemistry and adjust chemical feed as needed using Secondary System Chemical Addition (2106.028).

IF reducing power less than 90%,

THEN verify Primary Zinc Injection secured per ONE of the following:

Request Chemistry secure Zinc Injection per Unit 2 Reactor Coolant System (RCS) Zinc Control (1052.037)

Perform "Securing Zinc Injection" section of Chemical Addition (2104.003).

Cue: If contacted as a NLO and/or chemistry, report that you will secure Zinc injection and monitor secondary chemistry.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 4 Event

Description:

A Steam Generator Tube leak ramps up to 12 gpm over 5 min.

Time Position Applicant's Actions or Behavior ANY 12.13 Verify FWBSCAL selected for COLSS Secondary Calorimetric at ~

95% (PID 177).

SRO 12.14 IF power change exceeds 15% within a one hour period, THEN notify Chemistry to obtain an RCS sample for Iodine between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following power change (TS 3.4.8).

Cue: If contacted as chemistry, report that you will obtain an RCS sample for Iodine at the time requested.

OP-2203.038 Primary to Secondary Leakage AOP.

ANY 9. IF plant shutdown required, THEN isolate EFW pump 2P7A Steam supply as follows:

A. Close Main Steam Supply valve to 2P7A from leaking SG:

SG A TO EMER FW PUMP TURBINE (2CV-1000-1)

SG B TO EMER FW PUMP TURBINE 2CV-1050-2 B. Refer to TS 3.7.1.2, Emergency Feedwater System.

Examiner Note: The SRO must enter TS 3.7.1.2.

ANY 10. Initiate secondary contamination control using 2202.010 Attachment 19, Control of Secondary Contamination.

Cue: If contacted as a NLO to commences Att. 19, then report you will commence standard att.

19 Control of Secondary Contamination.

ANY *11. Check VCT level 60 to 75%.

SRO *12. Notify SM to refer to the following:

Tech Specs:

3.4.5, SG Tube Integrity 3.4.6.2, Reactor Coolant System Leakage 3.7.1.4, Secondary Activity 1903.010, Emergency Action Level Classification Examiner Note: SRO must enter TS 3.4.5 and 3.4.6.2 action a Termination criteria: When the required reactivity manipulation is complete and the appropriate TS have been entered or at lead examiners discretion.

Revision 0 Page 28 of 65

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 5 Event

Description:

CEA 49 fails to respond to insertion command.

Time Position Applicant's Actions or Behavior This event ATC ATC will insert CEA for ASI control.

will occur during the first CEA insertion.

ATC Transition to Exhibit 3 of OP-2105.009 CEDM Control System Operation Procedure Note:

"CEA SELECTED" indicates selected CEA position.

"GROUP SELECTED" indicates average position of selected group.

If > 6 inch deviation occurs in any regulating group, rod motion is inhibited by PMS CEA sequencing program.

ATC 1.0 IF moving CEAs in group, THEN perform the following at 2C03:

1.1 Place Group Select switch to desired group position.

1.2 IF moving Group P CEAs, THEN place P Group Select switch to P.

1.3 Ensure Individual CEA Selection switches aligned to CEA in group selected to move.

Exhibit 3, 1.4 Place Mode Select switch to MANUAL GROUP (MG) or CEDMCS MANUAL SEQUENTIAL (MS).

Operations

  • 1.5 Observe CEAC and Pulse Counter CEA position indications to verify CEA motion and alignment as CEAs are moved.

R A 1.6 Position groups as desired using Manual Control lever.

P 1.7 Place Mode Select switch to OFF.

1.8 Verify Pulse Counter and CEAC indications match.

ATC The ATC should recognize that CEA 49 failed to move during the insertion and report to the CRS.

Examiner Note: The Crew may elect to try to insert CEA 49 individually to align it with the group.

ATC The ATC should continue the power reduction and transition to group P CEAs for ASI control using Exhibit 3.

SRO The SRO will transition to OP-2203.0 CEA malfunction AOP.

Revision 0 Page 29 of 65

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 5 Event

Description:

CEA 49 fails to respond to insertion command.

Procedure Note:

Attachment D provides trip and shutdown criteria.

Attachment E provides a list of possible Tech Spec actions to be taken within two hours of procedure entry.

Steps marked with (*) are continuous action steps.

Steps marked with ( ) are floating steps.

SRO 1. Open Placekeeping page.

SRO 2. Stop ALL CEA movement.

SRO 3. Notify Control Board Operators to monitor floating steps.

Procedure Note:

CEA misalignment is defined as a CEA misaligned from its associated Group by outward deviation more than 5 inches or inward deviation more than 7 inches.

For the purpose of defining CEA operability to satisfy TS LCO requirements, a CEA is inoperable under the following conditions:

1. CEA is known to be untrippable or immovable as a result of excessive friction or mechanical interference (TS 3.1.3.1.a).
2. CEA is known to be immovable as a result of CEDMCS malfunction (TS 3.1.3.1.b and 3.1.3.1.c).
3. CEA is misaligned from ANY other CEA in its group by greater than 7 inches and can NOT be aligned (TS 3.1.3.1.d).
4. CEA can NOT be exercised within the maximum TS surveillance time requirements of TS 4.1.3.1.2.
5. Shutdown Bank CEA withdrawn to less than its full out position except for surveillance testing (TS 3.1.3.5).

SRO 4. Refer to the following:

Tech Specs Attachment E, Tech Spec Two Hour Actions SRO *5. IF ANY CEAs immovable AND aligned, THEN GO TO Step 37.

Examiner Note: This step may be applicable or may not be applicable depending on the deviation from the group see note above. Step 37 is on page 31 of this exam.

SRO *6. IF TWO or MORE CEAs misaligned by greater than 19 inches, THEN perform the following:

A. Trip Reactor.

B. GO TO 2202.001, Standard Post Trip Actions.

Examiner Note: This step is N/A.

Revision 0 Page 30 of 65

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 5 Event

Description:

CEA 49 fails to respond to insertion command.

SRO *7. IF TWO or MORE CEAs misaligned by greater than 7 inches, THEN perform the following:

A. Commence Plant shutdown at greater than 14 %/hr using 2102.004, Power Operation.

B. Refer to TS 3.1.3.1.e., CEA Position.

Examiner Note: This step is N/A.

Procedure Note:

TAVE computer point numbers that may be used include T-AVG and T4617-B.

ANY 8. Record the following:

Start time Pre-misalignment Rx power _________

TAVE change SRO 9. Check Reactor startup in progress. (Not Met, perform contingency)

SRO 9. IF Reactor startup NOT in progress, THEN GO TO Step 17.

SRO 17. Check inward CEA misalignment exists.

SRO 17. IF outward CEA misalignment exists, THEN perform the following:

A. IF associated group less than 11.42 inches or greater than 138.58 inches withdrawn, THEN perform the following:

1) IF CEA misaligned greater than 7 inches, THEN GO TO Step 18.
2) IF CEA misaligned 7 inches or less, THEN GO TO Step 37.

Examiner Note: The CEA will be withdrawn greater than 138.58 inches. CEA 49 should be misaligned less than 7 inches.

SRO 37. IF ANY CEAs withdrawn AND immovable, THEN perform the following:

A. Notify I&C to perform CEA traces to determine affected CEAs trippable status.

B. Refer to the following TS:

3.1.3.1.b, CEA Position 3.1.3.1.c, CEA Position Examiner Note: The SRO should contact I&C to perform CEA traces and after I&Cs report the SRO should enter TS 3.1.3.1b for CEA 49.

Revision 0 Page 31 of 65

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 5 Event

Description:

CEA 49 fails to respond to insertion command.

Cue: When contacted as the work management or I&C to troubleshoot, wait 3 minutes and then call and report that you are standing by for CEA 49 troubleshooting and ask the control room to insert CEA 49 for traces.

ATC Transition to Exhibit 3 of OP-2105.009 CEDM Control System Operation to insert CEA 49 ATC 2.0 IF moving CEA individually, THEN perform the following:

2.1 Verify Group Select switch selected to group containing individual CEA.

2.2 Place Individual CEA Selection switches to desired CEA.

2.3 Place Mode Select switch to MANUAL INDIVIDUAL (MI).

Exhibit 3, CEDMCS *2.4 Observe CEAC and Pulse Counter CEA position indications Operations to verify CEA motion and alignment as CEAs are moved.

R A 2.5 Position CEA as desired using Manual Control lever.

P 2.6 WHEN individual CEA movement complete, THEN place Mode Select switch to OFF.

2.7 Verify Pulse Counter and CEAC indications match.

Cue: After CEA 49 insertion is attempted, wait one minute then report that CEA 49 is not inserting due to a failed hall effect transducer and it will have to be replaced.

Report that it will take ~ 20 minutes to replace.

Procedure Note:

A CEA is considered untrippable with CEDMCS operable AND CEA immovable.

SRO 38. IF ANY CEAs determined to be untrippable, THEN perform the following:

Examiner Note: This step is N/A.

Revision 0 Page 32 of 65

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 5 Event

Description:

CEA 49 fails to respond to insertion command.

Procedure Note:

For the purpose of defining CEA operability to satisfy TS LCO requirements, a CEA is inoperable under the following conditions:

1. CEA is known to be untrippable or immovable as a result of excessive friction or mechanical interference (TS 3.1.3.1.a).
2. CEA is known to be immovable as a result of CEDMCS malfunction (TS 3.1.3.1.b and 3.1.3.1.c).
3. CEA is misaligned from ANY other CEA in its group by greater than 7 inches and can NOT be aligned (TS 3.1.3.1.d).
4. CEA can NOT be exercised within the maximum TS surveillance time requirements of TS 4.1.3.1.2.
5. Shutdown Bank CEA withdrawn to less than its full out position except for surveillance testing (TS 3.1.3.5).

SRO 39. Check affected CEAs operable as follows:

Known to be trippable.

Known to be movable.

Aligned within 7 inches of associated group.

All surveillance requirements met.

All Shutdown banks at FULL out position.

Examiner Note: CEA 49 is not operable but is trippable and the SRO should perform the contingency.

SRO 39. Perform the following:

A. IF ANY CEA untrippable, THEN RETURN TO step 38.

Examiner Note: This step is N/A.

SRO B. IF ONE CEA remains misaligned greater than 7 inches, THEN perform the following:

Examiner Note: This step is N/A.

SRO C. IF more than ONE CEA remains misaligned greater than 7 inches, THEN perform the following:

Examiner Note: This step is N/A.

Revision 0 Page 33 of 65

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 5 Event

Description:

CEA 49 fails to respond to insertion command.

SRO D. IF ONE or more CEAs immovable but trippable and aligned within 7 inches of associated group, THEN perform the following:

1) Refer to the following TS:

3.1.3.1.b, CEA Position 3.1.3.1.c, CEA Position

2) Notify Operations management.

Examiner Note: The SRO should enter TS 3.1.3.1b for CEA 49.

Termination criteria: When the ATC has inserted group P to control ASI, traces have been performed on CEA 49 and SRO has entered the appropriate TS or at the discretion of the lead examiner.

Revision 0 Page 34 of 65

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 6, 7, & 8 Event

Description:

A Steam Generator Tube leak ramps up from 12 gpm to 100 gpm over 5 min causes Reactor Trip, A Main Feed water line breaks inside containment, and Red Train Containment Spray pump fails to auto start.

Time Position Applicant's Actions or Behavior Cued by ANY The crew should recognize that steam generator tube leak has degraded.

lead examiner SRO Direct the RCS leak rate to be assessed.

ATC/BOP Determine that the RCS leakrate is greater than 44gpm.

Direct actions from OP-2203.038 Primary to Secondary leakage.

6. IF EITHER of the following conditions exist:

RCS leakage greater than or equal to 44 gpm PZR level continues to lower with ALL available Charging pumps running AND Letdown isolated THEN perform the following:

SRO A. Verify closed Main Steam Supply valve to 2P7A from leaking SG:

SG A TO EMER FW PUMP TURBINE (2CV-1000-1)

SG B TO EMER FW PUMP TURBINE 2CV-1050-2 B. Refer to TS 3.7.1.2, Emergency Feedwater System.

Examiner Note: Steam to 2P-7A should already be isolated.

C. IF in Modes 1 or 2, THEN perform the following:

1) Trip Reactor.

ATC 2) Actuate SIAS.

3) Actuate CCAS.
4) GO TO 2202.001, Standard Post Trip Actions.

SRO Enter OP-2202.001, Standard Post Trip Actions EOP.

Examiner Note: After the crew determines that there is an excess steam demand occurring they may actuate Main Steam Isolation Signal (MSIS) and pull forward the steps from the RCS heat removal section of SPTAs to secure feedwater sources to A Steam Generator.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 6, 7, & 8 Event

Description:

A Steam Generator Tube leak ramps up from 12 gpm to 100 gpm over 5 min causes Reactor Trip, A Main Feed water line breaks inside containment, and Red Train Containment Spray pump fails to auto start.

Time Position Applicant's Actions or Behavior

1. Notify Control Board Operators to perform the following:

A. Monitor safety functions using Exhibit 7, CBO Reactor Trip SRO Checklist.

B. Perform post trip contingencies as required.

SRO 2. Open Safety Function Tracking page.

ATC 3. Check Reactivity Control established as follows:

Reactivity A. Reactor power lowering.

control Safety B. Check startup rate is negative.

Function C. ALL CEAs fully inserted by observing ANY of the following:

BOP 4. Check Maintenance of Vital Auxiliaries satisfied:

Vital A. Check Main Turbine tripped by BOTH of the following:

Auxiliaries Safety ALL Main Stop Valves closed.

Function Generator megawatts indicate zero.

BOP B. Generator Output breakers open.

BOP C. Perform EITHER of the following as required:

1) Check the following valves closed:

MSR 2E-12A Steam Supply From SG A (2CV-0400)

MSR 2E-12B Steam Supply From SG B (2CV-0460)

2) No flow indicated on the following MSR second stage flow instruments:

2FI-0402 2FI-0462 BOP D. At least ONE 6900v AC bus energized.

E. At least ONE 4160v Non-vital AC bus energized.

F. BOTH 4160v Vital AC buses energized.

G. BOTH DGs secured. (Not met, contingency is satisfied.)

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 6, 7, & 8 Event

Description:

A Steam Generator Tube leak ramps up from 12 gpm to 100 gpm over 5 min causes Reactor Trip, A Main Feed water line breaks inside containment, and Red Train Containment Spray pump fails to auto start.

Time Position Applicant's Actions or Behavior ANY Perform Step 4.G. Contingency Actions.

4. G. IF ANY DG running AND SW NOT aligned, THEN locally stop DG by unlocking and placing "ENGINE CONTROL" handswitch in LOCKOUT:

2E11 2E21 Examiner Note: Service water will be aligned to EDGs BOP H. At least ONE 125v Vital DC bus energized:

2D01 - SPDS point E2D01 2D02 - SPDS point E2D02 ATC 5. Check RCS Inventory Control established as follows:

A. PZR level:

10 to 80%.

Trending to setpoint. (May not be met due to SGTR and RCS ESD Event, then perform contingency)

Inventory B. RCS MTS 30°F or greater.

Control Safety Function SRO Perform Step 5 Contingency Actions.

A. Perform as necessary:

1) IF SIAS actuated on PPS inserts, THEN GO TO Step 6.
2) Verify PZR Level Control system restoring level to setpoint.

BOP 6. Check RCS Pressure Control:

RCS

  • 1800 to 2250 psia.

Pressure

  • Trending to setpoint. (May met due to SGTR and ESD Event, Control perform contingency)

Safety

  • Normal PZR Spray and heaters controlling pressure.

function,

  • Valid CNTMT Spray NOT in progress. (Not met due to ESD Event, perform contingency)

Revision 0 Page 37 of 65

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 6, 7, & 8 Event

Description:

A Steam Generator Tube leak ramps up from 12 gpm to 100 gpm over 5 min causes Reactor Trip, A Main Feed water line breaks inside containment, and Red Train Containment Spray pump fails to auto start.

Time Position Applicant's Actions or Behavior SRO Perform Step 6 Contingency Actions.

6. Perform as necessary:

C. IF valid CNTMT Spray in progress, THEN verify ALL RCPs tripped.

D. IF RCP 2P32A or 2P32B stopped, THEN verify associated PZR Spray valve in MANUAL and closed:

RCP A Spray Valve (2CV-4651)

RCP B Spray Valve (2CV-4652)

E. IF ALL RCPs stopped AND RCS pressure control required, THEN initiate Aux spray using Attachment 48, RCS Pressure Control.

F. IF RCS pressure lowers to 1650 psia or less, THEN perform the following:

1) Verify SIAS actuated on PPS inserts.
2) GO TO Step 7.

G. Verify PZR Pressure Control system restoring pressure to setpoint.

Critical Task: Component cooling water to RCPs must be restored within 10 minutes of CIAS or All RCPs must be secured within the next 10 minutes.

ATC Implement OP-2202.010, Standard Attachment, Attachment 48.

Attachment 48 Procedure Note:

Once method of pressure control is established, this attachment is not required in hand or continuous use.

A change to the method of pressure control will require in hand or continuous use until the new pressure control method is established.

ATC *1. Maintain RCS pressure with heaters and spray using one or more of the following:

D. IF desired to use AUXILIARY Spray, THEN perform the following:

  • 1) Verify RCS MTS greater than 30 degrees.

Steps from Attach. 48 2) Verify at least ONE Charging pump running.

3) Close Regen HX to RCP B/C valves:

2CV-4827-2 2CV-4831-2 Revision 0 Page 38 of 65

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 6, 7, & 8 Event

Description:

A Steam Generator Tube leak ramps up from 12 gpm to 100 gpm over 5 min causes Reactor Trip, A Main Feed water line breaks inside containment, and Red Train Containment Spray pump fails to auto start.

Time Position Applicant's Actions or Behavior Procedure Note:

PZR Spray Block valves 2CV-4653 and 2CV-4655 are de-energized due to degraded power supply cables.

ATC 4) Verify PZR Spray (2CV-4651/2CV-4652) or PZR Spray Isolation valves (2HS-4655/2HS-4653) closed.

5) Throttle Aux Spray valve (2CV-4824-2) as necessary.

Steps from 6) IF Regen HX to RCS temperature (2TI-4825) can NOT be Attach. 48. reduced to less than 275°F, THEN perform ONE of the following:

a) Isolate Letdown to reduce temperature.

b) Complete Table 1 of this attachment.

ATC 7) IF Regen HX to RCS (2TI-4825) AND PZR water phase (2TI-4627) differential temperature greater than 200°F AND PMS is unavailable, THEN complete Table 1 of this attachment.

TIME TEMPERATURE SPRAY SPRAY (PZR 2TIS-4607 Steps from VALVE VALVE WATER 2TIS-4608 Attach. 48. OPENED CLOSED PHASE) 2TI-4825 DIFFERENCE 2TI-4627 SRO Implement remaining steps from OP-2202.001, Standard Post Trip Actions Steps.

ATC 7. Check Core Heat Removal by forced circulation:

A. At least ONE RCP running. (Not met, perform contingency)

SRO Perform Step 7 Contingency Actions.

Core Heat Removal A. IF ALL RCPs stopped, Safety THEN perform the following:

Function.

1) Verify BOTH PZR Spray valves in MANUAL and closed.
2) GO TO Step 8.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 6, 7, & 8 Event

Description:

A Steam Generator Tube leak ramps up from 12 gpm to 100 gpm over 5 min causes Reactor Trip, A Main Feed water line breaks inside containment, and Red Train Containment Spray pump fails to auto start.

Time Position Applicant's Actions or Behavior BOP/ATC 8. Check RCS Heat Removal:

A. Check SG available by BOTH of the following:

At least ONE SG level 10 to 90%.

RCS Heat FW maintaining SG level (Not met, perform contingency)

Removal Safety Function ANY Perform Step 8.A Contingency Actions when applicable.

A. Perform the following:

1) IF SG level lowering, THEN verify EFAS actuated.

BOP/ATC B. Check MFW in RTO (Not Met, Perform contingency)

RCS Heat ANY Perform Step 8.B Contingency Actions.

Removal Safety B. Verify EITHER of the following:

Function BOTH MFW pumps tripped. (Both MFW pumps will be tripped)

SG levels controlling at setpoint ATC/BOP C. Check Feedwater line intact by the following:

RCS Heat SG level stable or rising. (Not Met, Perform contingency)

Removal Safety NO unexplained step changes or erratic FW flow.

Function NO unexplained step changes or erratic Condensate flow.

Revision 0 Page 40 of 65

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 6, 7, & 8 Event

Description:

A Steam Generator Tube leak ramps up from 12 gpm to 100 gpm over 5 min causes Reactor Trip, A Main Feed water line breaks inside containment, and Red Train Containment Spray pump fails to auto start.

Time Position Applicant's Actions or Behavior ANY Perform Step 8.B Contingency Actions.

C. IF indication of FW rupture exists, THEN perform the following as necessary:

  • For RUPTURE in MFW header:
1) Verify ALL MFW pumps tripped.

RCS Heat 2) Verify ALL Condensate pumps tripped.

Removal Safety 3) Close MFW Block valves.

Function

4) GO TO Step 8.D.
  • For RUPTURE in EFW header:
1) Verify EFW/AFW pump tripped for ruptured header.
2) Close associated EFW Block valves.

Examiner Note: The applicants may have already performed these steps.

ATC/BOP D. Check RCS TC 540°F to 555°F. (Not Met, perform Contingency)

ANY Perform Step 8.D Contingency Actions.

2) IF TC less than 540°F, THEN perform the following:

a) Verify Feedwater flow rate (MFW OR EFW) NOT causing TC to lower.

RCS Heat b) Verify SDBCS restoring TC 540°F to 555°F using Removal 2105.008 Exhibit 3, Safety SDBCS Emergency Operation.

Function c) IF MSIS actuated AND the cooldown terminates, THEN stabilize TC and maintain post-cooldown conditions as follows:

Maintain RCS pressure within P-T limits with PZR heaters and spray using Attachment 48, RCS Pressure Control.

Maintain RCS temperature by steaming intact SG using Upstream ADV or Upstream ADV Isolation MOV Revision 0 Page 41 of 65

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 6, 7, & 8 Event

Description:

A Steam Generator Tube leak ramps up from 12 gpm to 100 gpm over 5 min causes Reactor Trip, A Main Feed water line breaks inside containment, and Red Train Containment Spray pump fails to auto start.

Time Position Applicant's Actions or Behavior ATC/BOP E. Check SG pressure 950 to 1050 psia. (Not Met, perform Contingency)

ANY Perform Step 8.E Contingency Actions.

E. Perform as necessary:

1) IF SG pressure 751 psia or less, THEN perform the following:

a) Verify MSIS actuated on PPS inserts.

b) Verify feed secured to the affected SG.

RCS Heat Removal Safety ALL c) Maintain RCS post-cooldown conditions as follows:

Function Maintain RCS pressure within P-T limits with PZR heaters and spray using 2202.010 Attachment 48, RCS Pressure Control.

Maintain RCS temperature by steaming intact SG using Upstream ADV or Upstream ADV Isolation MOV.

d) GO TO Step 9.

Examiner Note: Critical Task, Maintain RCS pressure within the Pressure-Temperature limits of 200°F and 30°F Margin to Saturation throughout implementation of SPTAs and Functional Recovery EOP.

BOP Implement OP-2105.008, SDBCS Emergency Operations.

BOP 1.0 IF BOTH MSIVs closed, THEN GO TO step 5.0.

Examiner Note: MSIVs are closed.

BOP 5.0 Perform the following to determine availability of SDBCS valves:

Steam 5.1 IF the following conditions satisfied, Dump THEN Upstream ADV are available:

Exhibit 3 Instrument air available Emergency OFF (2K02-A14) clear Power available to selected controllers/valves Examiner Note: Upstream ADVs are available.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 6, 7, & 8 Event

Description:

A Steam Generator Tube leak ramps up from 12 gpm to 100 gpm over 5 min causes Reactor Trip, A Main Feed water line breaks inside containment, and Red Train Containment Spray pump fails to auto start.

Time Position Applicant's Actions or Behavior BOP 6.0 IF operation of Upstream Atmospheric Dump valve from the Control Room desired, THEN perform the following:

6.1 Verify selected HIC in MANUAL with ZERO output demand:

2HIC-1001 Upstream Atmospheric Dump valve 2HIC-1051 Upstream Atmospheric Dump valve 6.2 Place selected valve(s) permissive handswitch in MANUAL:

2CV-1001 Upstream Atmospheric Dump valve (2HS-1001) 2CV-1051 Upstream Atmospheric Dump valve (2HS-1051)

Steam Dump Exhibit 3 6.3 IF MSIS actuated, THEN override actuation for selected MOV isolation:

2CV-1002 ADV Upstream Isolation valve 2CV-1052 ADV Upstream Isolation valve

  • 6.4 Throttle open selected MOV as desired:

2CV-1002 ADV Upstream Isolation valve 2CV-1052 ADV Upstream Isolation valve

  • 6.5 Place selected HIC to desired demand:

2HIC-1001 Upstream Atmospheric Dump valve 2HIC-1051 Upstream Atmospheric Dump valve Implement remaining steps from OP-2202.001, Standard Post Trip Actions SRO Steps.

ANY 9. Check CNTMT parameters:

A. Temperature and Pressure: (Not met due to ESD Event.

Containment Perform contingency)

Safety Function Temperature less than 140°F.

Pressure less than 16 psia.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 6, 7, & 8 Event

Description:

A Steam Generator Tube leak ramps up from 12 gpm to 100 gpm over 5 min causes Reactor Trip, A Main Feed water line breaks inside containment, and Red Train Containment Spray pump fails to auto start.

Time Position Applicant's Actions or Behavior ANY Perform Step 9.A Contingency Actions.

A. Perform the following:

2) IF CNTMT pressure 18.3 psia or greater, THEN verify the following:
  • CIAS, CCAS, and SIAS actuated on PPS inserts.
  • At least ONE Emergency Penetration Room Vent Fan running.
  • CNTMT Cooling fans running in Emergency Mode.

ANY 3) IF CNTMT pressure 23.3 psia or greater, THEN verify the following:

  • Spray flow greater than 1875 gpm per header.
  • ALL RCPs stopped AND BOTH PZR Spray valves in MANUAL and closed.

ANY B. Check CNTMT Spray pumps secured. (Not Met)

Containment Safety ANY Perform Step 9.B Contingency Actions.

Function B. IF CSAS inadvertent, THEN perform the following:

1) Place BOTH CNTMT Spray pumps (2P35A/B) in PTL.

Record time: __

Examiner Note: CSAS is not inadvertent.

ANY C. NO CNTMT radiation alarms or unexplained rise in activity:

1) CAMS alarms:
2) RCS leakage alarms:
3) Check the following radiation monitors trend stable:
  • CNTMT Area
  • CAMS
  • Process Liquid Revision 0 Page 44 of 65

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 6, 7, & 8 Event

Description:

A Steam Generator Tube leak ramps up from 12 gpm to 100 gpm over 5 min causes Reactor Trip, A Main Feed water line breaks inside containment, and Red Train Containment Spray pump fails to auto start.

Time Position Applicant's Actions or Behavior ANY D. NO secondary system radiation alarms or unexplained rise in activity: (Not met)

1) "SEC SYS RADIATION HI" annunciator (2K11-A10) clear.

Containment Safety Function 2) Secondary Systems Radiation monitors trend stable:

  • Condenser Off Gas SRO 10. Notify STA to report to control room.
11. Direct NLOs to perform 2202.010 Attachment 47, Field Operator Post Trip Actions.
12. Verify Reactor trip announced on Plant page.
13. Notify SM to refer to Technical Specifications and 1903.010, Emergency Action Level Classification.

Cue: If contacted as the STA to report to the control room, acknowledge the request.

Cue: If contacted as a NLO to perform Attachment 47 Field Operator Post Trip Actions, acknowledge request.

SRO 14. Direct control board operators to acknowledge ALL annunciators and announce ALL critical alarms.

SRO 15. Check ALL safety function acceptance criteria satisfied. (All safety functions are not satisfied, perform contingency)

SRO Perform Step 15 Contingency Actions.

15. IF ANY safety function acceptance criteria NOT satisfied, THEN perform the following:

A. Notify control room staff of safety functions NOT satisfied.

B. GO TO Exhibit 8, Diagnostic Actions.

SRO Diagnose OP-2202.009, Functional Recovery EOP.

SRO Enter OP-2202.009, Functional Recovery EOP.

SRO *1. Notify Shift Technical Advisor to perform Safety Function Status Checks for appropriate success paths at the following times:

Initially after appropriate success paths identified Every 15 minutes thereafter.

Revision 0 Page 45 of 65

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 6, 7, & 8 Event

Description:

A Steam Generator Tube leak ramps up from 12 gpm to 100 gpm over 5 min causes Reactor Trip, A Main Feed water line breaks inside containment, and Red Train Containment Spray pump fails to auto start.

Time Position Applicant's Actions or Behavior SRO 2. Record present time:

  • Time .

SRO *3. Notify SM to refer to Technical Specifications and 1903.010, Emergency Action Level Classification.

ANY *4. Check RCS pressure greater than 1400 psia.

Examiner Note: RCS pressure may be less than 1400 psia due to the ESD but it also could have recovered greater than 1400 psia and all contingency action have already been performed.

ANY Step 4 Contingency Actions have already been performed.

  • 4. Perform the following:

A. IF RCS pressure less than 1400 psia, THEN perform the following:

1) Verify maximum of ONE RCP running in EACH loop.
2) IF RCP 2P32A or 2P32B stopped, THEN verify associated PZR Spray valve in MANUAL and closed.

ANY

  • 6. IF SIAS or MSIS actuated, THEN perform the following:

A. Verify at least ONE SW pump running on EACH loop.

B. Check EITHER DG running.

C. Verify running DG SW Outlet valve open:

2CV-1503-1 2CV-1504-2 D. Verify SW pump suction aligned to Lake.

E. Check 4160v Non-vital bus 2A1 OR 2A2 energized from offsite power.

F. Check 4160v Vital buses 2A3 AND 2A4 energized from offsite power.

G. Start SW pumps as needed to maintain SW header pressure.

H. Check SW to CCW restored. (Not met, perform contingency)

BOP Perform Step 6.H Contingency Actions.

H. IF CCW available, THEN restore SW to CCW, refer to 2202.010 Exhibit 5, CCW/ACW/SW Alignment.

ANY I. Check ACW restored. (Not met, perform contingency)

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 6, 7, & 8 Event

Description:

A Steam Generator Tube leak ramps up from 12 gpm to 100 gpm over 5 min causes Reactor Trip, A Main Feed water line breaks inside containment, and Red Train Containment Spray pump fails to auto start.

Time Position Applicant's Actions or Behavior BOP Perform Step 6.I Contingency Actions.

I. Restore SW to ACW, refer to 2202.010 Exhibit 5, CCW/ACW/SW Alignment.

ANY J. Maintain SW header pressure greater than 85 psig.

SRO 7. IF CCW in service to provide SG Sample Cooler cooling, THEN perform the following:

B. IF SG B has indicated water level, THEN verify the following SG B Sample Valves open:

2CV-5858 2CV-5859-2 C. Notify Chemistry to sample available SGs for activity.

Cue: When contacted as Chemistry, then report you will sample B S/G for activity.

SRO 8. Check ALL available Hydrogen Analyzers in service using 2104.044, Containment Hydrogen Control Operations. (Not met, perform contingency)

SRO Perform Step 8 Contingency Actions.

8. Verify all available Hydrogen Analyzers in service within 70 minutes from start of event.

B. Record time from Entry Section step 2:

Time ______________

SRO 9. Open Functional Recovery Success Path Tracking page.

SRO 10. Notify Control Board Operators to perform the following:

A. Monitor floating steps.

B. Verify actuated ESFAS components using 2202.010 Exhibit 9, ESFAS Actuation.

BOP Implement OP-2202.010, Exhibit 9 ESFAS Actuation.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 6, 7, & 8 Event

Description:

A Steam Generator Tube leak ramps up from 12 gpm to 100 gpm over 5 min causes Reactor Trip, A Main Feed water line breaks inside containment, and Red Train Containment Spray pump fails to auto start.

Time Position Applicant's Actions or Behavior BOP *1.0 IF any abnormalities noted for affected ESFAS actuation, THEN notify CRS.

2.0 IF SIAS, THEN verify the following:

Red Train RWT Outlet (2CV-5630-1) open.

Red Train HPSI Pump in service with proper discharge pressure and flow.

Red Train HPSI Injection MOVs open.

Red Train Service Water Pump in service with proper discharge pressure.

Red Train LPSI Pump (2P60A) in service with proper discharge pressure and flow.

Red Train LPSI Injection MOVs open.

Green Train RWT Outlet (2CV-5631-2) open.

Green Train HPSI Pump in service with proper discharge pressure and flow.

Green Train HPSI Injection MOVs open.

Exhibit 9 Green Train Service Water Pump in service with proper discharge pressure.

ESFAS Green Train LPSI Pump (2P60B) in service with proper discharge pressure actuation. and flow.

Green Train LPSI Injection MOVs open.

Available Charging Pumps in service with proper discharge pressure and flow.

Service Water Outlet Valves open for #1 and #2 EDGs.

3.0 IF CCAS, THEN verify the following:

Red Train CNTMT Coolers in service.

Service Water aligned to Red Train CNTMT Coolers.

Red Train Bypass Dampers open.

Green Train CNTMT Coolers in service.

Service Water aligned to Green Train CNTMT Coolers.

Green Train Bypass Dampers open.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 6, 7, & 8 Event

Description:

A Steam Generator Tube leak ramps up from 12 gpm to 100 gpm over 5 min causes Reactor Trip, A Main Feed water line breaks inside containment, and Red Train Containment Spray pump fails to auto start.

Time Position Applicant's Actions or Behavior BOP 4.0 IF CSAS, THEN verify the following:

Red Train CSS Pump (2P35A) in service with proper discharge pressure and flow. (Will not be running and should be started)

Red Train CSS Header Isolation (2CV-5612-1) open.

Green Train CSS Pump (2P35B) in service with proper discharge pressure and flow.

Green Train CSS Header Isolation (2CV-5613-2) open.

Main Feedwater Block valves closed.

MSIVs closed.

Exhibit 9 Main Feed pumps tripped.

ESFAS Condensate pumps secured.

actuation. Heater Drain pumps secured.

5.0 IF MSIS, THEN verify the following:

MSIVs closed.

Main Feedwater Block valves closed.

Red Train Service Water Pump in service with proper discharge pressure.

Green Train Service Water Pump in service with proper discharge pressure.

Main Feed pumps tripped.

Condensate pumps secured.

Heater Drain pumps secured.

Cue: If contacted as NLO to investigate 2P-35A spray pump and breaker, then after ~ 1 min.

report the breaker is open and looks normal locally. After ~ 2 min. report that 2P-35A motor and pump look normal locally.

SRO Implement remaining Steps of OP-2202.009, Functional Recovery entry section.

ANY 11. Determine safety function status as follows:

A. Check Reactivity Control satisfied by EITHER of the following:

  • Maximum of ONE CEA NOT fully inserted and Reactor power lowering.
  • Reactor power less than 10-1% and stable or lowering.

Examiners Note: Reactivity will be satisfied.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 6, 7, & 8 Event

Description:

A Steam Generator Tube leak ramps up from 12 gpm to 100 gpm over 5 min causes Reactor Trip, A Main Feed water line breaks inside containment, and Red Train Containment Spray pump fails to auto start.

Time Position Applicant's Actions or Behavior ANY B. Check Vital DC Auxiliaries satisfied:

1) At least ONE 125v Vital DC bus energized:
2) At least ONE 120v Vital AC bus energized:
  • 2RS1 - SPDS point E2RS1 or E2RS1RS3
  • 2RS2 - SPDS point E2RS2 or E2RS2RS4
  • 2RS3 - SPDS point E2RS3 or E2RS1RS3
  • 2RS4 - SPDS point E2RS4 or E2RS2RS4 Examiners Note: Vital DC will be satisfied.

ANY C. Check Vital AC Auxiliaries satisfied:

1) At least ONE 4160v Vital AC bus (2A3/2A4) energized.

Examiners Note: Vital AC will be satisfied.

ANY D. Check RCS Inventory Control satisfied:

1) CVCS maintaining PZR level 10 to 80% [40 to 70%] and level stable or trending to setpoint.
2) RCS MTS 30°F or greater.
3) RVLMS LVL 03 or higher elevation indicates WET.

Examiners Note: Inventory Control may not be satisfied due to PZR level and the ESD event.

ANY E. Check RCS Pressure Control satisfied:

1) RCS pressure maintained within P-T limits, refer to Attachment 1, P-T Limits.

Examiners Note: P-T limits should be satisfied.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 6, 7, & 8 Event

Description:

A Steam Generator Tube leak ramps up from 12 gpm to 100 gpm over 5 min causes Reactor Trip, A Main Feed water line breaks inside containment, and Red Train Containment Spray pump fails to auto start.

Time Position Applicant's Actions or Behavior ANY F. Check RCS and Core Heat Removal satisfied:

1) At least ONE intact SG available for Heat Removal by EITHER of the following:
  • Level 10 to 90% [20 to 90%] with FW available.
  • Level being restored with total FW flow of 485 gpm or greater.
2) Uncontrolled SG depressurization NOT in progress.
3) IF ANY RCP operating, THEN RCS T less than 10°F and NOT rising.
4) IF ALL RCPs secured, THEN RCS T less than 50°F and NOT rising.
5) RCS TC less than 555°F and NOT rising.
6) RCS MTS 30°F or greater.
7) RVLMS LVL 01 indicates WET.

Examiners Note: RCS and Core Heat Removal will not be satisfied due to the ESD.

ANY G. Check CNTMT Isolation satisfied:

1) CNTMT parameters normal:

a) "CNTMT RADIATION HI" annunciator (2K10-A6) clear.

b) NO unexplained rise in CNTMT radiation.

c) CNTMT pressure less than 18.3 psia. (Not met, perform contingencies)

2) "SEC SYS RADIATION HI" annunciator (2K11-A10) clear.
3) NO unexplained rise in Secondary Systems Radiation monitor trends:
  • Condenser Off Gas Examiners Note: CNTMT Isolation will not be satisfied due to ESD event and SGTR event.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 6, 7, & 8 Event

Description:

A Steam Generator Tube leak ramps up from 12 gpm to 100 gpm over 5 min causes Reactor Trip, A Main Feed water line breaks inside containment, and Red Train Containment Spray pump fails to auto start.

Time Position Applicant's Actions or Behavior ANY CNTMT Isolation contingencies:

1) Verify CNTMT isolation as follows:
  • CIAS actuated components are properly aligned, using 2202.010 Attachment 5, CIAS Verification.
  • ONE Emergency Penetration Room Vent fan running.
  • EACH penetration NOT required to be open has at least ONE isolation valve closed.

Examiner Note: The SRO may prioritize the attachment 5 for later in the event due to actions that are a higher priority.

ANY COMPONENT DESCRIPTION 1.0 2.0 3.0 NUMBER LOCATION POSITION REGEN HX INLET 2CV-4821-1 2C09 CLOSED REGEN HX OUTLET 2CV-4823-2 2C09 CLOSED CNTMT PURGE SUPPLY V1 INSIDE 2CV-8289-1 2C17 CLOSED CNTMT PURGE SUPPLY V1 OUTSIDE 2CV-8283-1 2C17 CLOSED OUTSIDE CNTMT PURGE EXHAUST V2 INSIDE 2CV-8291-1 2C17 CLOSED CNTMT PURGE EXHAUST V2 OUTSIDE 2CV-8285-1 2C17 CLOSED OUTSIDE SAMPLE ISOLATION VALVE QUENCH 2SV-5878-1 2C17 CLOSED TANK LIQ SAMPLE ISOLATION VALVE RCS 2SV-5833-1* 2C17 CLOSED RCP CCW SUPPLY 2CV-5236-1* 2C17 CLOSED RCP CCW RETURN 2CV-5255-1* 2C17 CLOSED Standard CNTMT CHILL WATER SUPPLY 2CV-3852-1 2C17 CLOSED Attachment 5 CNTMT CHILL WATER RETURN 2CV-3851-1 2C17 CLOSED RX DRAIN TANK DISCH ISOL 2CV-2202-1 2C17 CLOSED CNTMT VENT HEADER ISOL 2CV-2401-1 2C17 CLOSED (1)

CNTMT SUMP DRAIN 2CV-2060-1 2C17 CLOSED RCP BLEEDOFF TO VCT 2CV-4846-1 2C17 CLOSED CNTMT AIR SAMPLE NORTH INSIDE 2SV-8265-1* 2C17 CLOSED SUPPLY CNTMT AIR SAMPLE NORTH INSIDE 2SV-8259-1* 2C17 CLOSED RETURN CNTMT AIR SAMPLE SOUTH INSIDE 2SV-8273-1* 2C17 CLOSED SUPPLY CNTMT AIR SAMPLE SOUTH INSIDE 2CV-8233-1* 2C17 CLOSED RETURN PASS SUMP SAMPLE SUPPLY ISOL 2SV-5634-1* 2C17 CLOSED PASS SUMP SAMPLE RETURN ISOL 2SV-5633-1* 2C17 CLOSED Revision 0 Page 52 of 65

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 6, 7, & 8 Event

Description:

A Steam Generator Tube leak ramps up from 12 gpm to 100 gpm over 5 min causes Reactor Trip, A Main Feed water line breaks inside containment, and Red Train Containment Spray pump fails to auto start.

Time Position Applicant's Actions or Behavior ANY H. Check CNTMT Temperature and Pressure Control satisfied:

1) CNTMT pressure less than 16 psia.
2) CNTMT temperature less than 140°F.

Examiners Note: CNTMT Temperature and Pressure Control will not be satisfied due to excess steam demand.

ANY 12. Locally remove danger tags and close the following breakers.

2B51-E4 LTOP RELIEF ISOL 2CV-4730-1 2B51-K2 LTOP RELIEF ISOL 2CV-4741-1 Cue: If contacted to remove the danger tags and close the LTOP breakers, then wait 2 minutes and use the remote function for 2B51-E4 and 2B51-K2 to close the breakers and inform the control room that 2B51-E4 and 2B51-K2 are closed.

SRO *13. Check ALL Safety Function acceptance criteria satisfied.

SRO Perform Step 13 Contingency Actions.

  • 13. Perform the following:

A. Determine appropriate success paths using Success Path Decision Trees.

B. Initiate success paths for ALL Safety Functions in the following order:

1) Jeopardized.
2) Challenged.
3) Satisfied.

C. IF higher priority Safety Function jeopardized AND lower priority safety function success path in progress, THEN GO TO appropriate success path for highest priority safety function in jeopardy.

D. WHEN success path implemented for EACH Safety Function, THEN RETURN TO Step 14 of Entry procedure.

Examiner Note: The SRO should complete the safety functions in order of hierarchy that are Jeopardized 1st, Challenged 2nd, and then the Satisfied safety functions.

SRO Examiner Note 1: If Inventory Control is not Satisfied then Diagnose IC-2 as the first Jeopardized Success path and HR-2 as the second success path.

Examiner Note 2: The SRO may determine that the inventory control was satisfied based on timing and complete the actions from HR-2 to control the ESD and isolate the SG with the tube rupture.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 6, 7, & 8 Event

Description:

A Steam Generator Tube leak ramps up from 12 gpm to 100 gpm over 5 min causes Reactor Trip, A Main Feed water line breaks inside containment, and Red Train Containment Spray pump fails to auto start.

Time Position Applicant's Actions or Behavior SRO Implement Inventory Control Steps of OP-2202.009, Functional Recovery.

ANY 1. Verify SIAS and CCAS actuated on PPS inserts.

  • 2. Verify Safety Injection flow to RCS as follows:

A. Verify at least ONE HPSI pump running.

B. Verify running HPSI Injection MOVs open.

C. Verify ALL available Charging pumps running.

D. Check RCS pressure less than 1390 psia. (May or May not be but contingencies actions are not required)

E. Check total HPSI flow acceptable using 2202.010 Exhibit 2, HPSI Flow Curve.

F. Check total LPSI flow acceptable using 2202.010 Exhibit 3, LPSI Flow Curve.

ANY *3. IF CNTMT Spray pumps are running AND ALL of the following are Steps from TRUE:

IC-2 CNTMT pressure less than 73.7 psia (59 psig).

At least two CNTMT Cooling Fans running.

SIAS actuated and flow acceptable per the following:

- 2202.010 Exhibit 2, HPSI Flow Curve

- 2202.010 Exhibit 3, LPSI Flow Curve THEN perform the following:

A. Place EITHER CNTMT Spray pump (2P35A/B) in PTL.

B. Verify CNTMT pressure maintained less than 73.7 psia (59 psig).

ANY 4. Check CCW flow aligned to RCPs.

5. Check at least ONE 4160v Vital bus energized.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 6, 7, & 8 Event

Description:

A Steam Generator Tube leak ramps up from 12 gpm to 100 gpm over 5 min causes Reactor Trip, A Main Feed water line breaks inside containment, and Red Train Containment Spray pump fails to auto start.

Time Position Applicant's Actions or Behavior ANY 6. Terminate/throttle HPSI flow as follows:

A. Check HPSI flow NOT required for Success Path RC-3, Boration Using HPSI.

B. Check the following criteria satisfied:

1) RCS MTS 30°F or greater.
2) PZR level greater than 29% [50%] and controlled.
3) RVLMS LVL 03 or higher elevation indicates WET.
4) At least ONE intact SG available for Heat Removal by EITHER of the following:
  • Level 10% to 90% [20% to 90%] AND FW available.
  • Level being restored AND total FW flow of 485 gpm or greater.

Examiner Note: HPSI Throttle criteria is may not met due to PZR level and the SRO should go to the next step.

Steps from ANY *7. Monitor HPSI termination/throttle criteria satisfied for duration of IC-2 event.

ANY 8. Override LPSI as follows:

A. Check LPSI termination criteria satisfied as follows:

RCS pressure greater than 200 psia.

RCS pressure controlled.

Examiner Note: RCS pressure is probably not controlled at this point and LPSI may not be terminated, also the priority is to control the ESD and isolate the SG.

ANY *9. Monitor LPSI termination criteria satisfied for duration of event.

ANY *10. IF possible, THEN initiate action to refill the RWT by ANY of the following:

Normal makeup per 2104.003, Chemical Addition Makeup from Holdup tanks per 2104.006, Fuel Pool Systems Makeup from SFP per 2104.006, Fuel Pool Systems Instruct TSC to consider RWT Refill strategy per SAMG.

Examiner Note: The SRO may prioritize completing this step later in the event.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 6, 7, & 8 Event

Description:

A Steam Generator Tube leak ramps up from 12 gpm to 100 gpm over 5 min causes Reactor Trip, A Main Feed water line breaks inside containment, and Red Train Containment Spray pump fails to auto start.

Time Position Applicant's Actions or Behavior ANY *11. Check LOCA in progress.

A. Check LOCA limited to CNTMT:

  • RWT level lowering with corresponding rise in CNTMT Sump level.
  • CNTMT temperature, pressure, and dewpoint greater than pre-event values.
  • Aux Building area radiation levels stable.
  • Aux Building Sump level less than 53%.
  • Waste Tanks 2T20A/B level stable.

ANY 12. WHEN "RWT LEVEL LO LO RAS PRETRIP" annunciator (2K06-A9) in alarm, THEN perform the following:

Examiner Note: The alarm will be clear.

Steps from ANY 13. WHEN RWT level less than 6%, THEN perform the following:

IC-2 Examiner Note: RWT level will be > 6%.

ANY *14. Verify Early HPSI Termination as follows:

A. Check indication(s) of CNTMT Sump Blockage as per 2202.010 Attachment 43, ECCS/CSS Pump Monitoring. (Not met due to no RAS)

A. GO TO Step 15.

ANY *15. Instruct TSC to consider Alternate RCS Injection strategy.

ANY *16. Monitor Loss of ECCS/CSS pump suction as follows:

A. Check ECCS/CSS pump suction acceptable using 2202.010 Attachment 43, ECCS/CSS Pump Monitoring. (Not applicable due to no RAS)

B. Check total HPSI flow acceptable using 2202.010 Exhibit 2, HPSI Flow Curve.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 6, 7, & 8 Event

Description:

A Steam Generator Tube leak ramps up from 12 gpm to 100 gpm over 5 min causes Reactor Trip, A Main Feed water line breaks inside containment, and Red Train Containment Spray pump fails to auto start.

Time Position Applicant's Actions or Behavior

17. Check acceptance criteria for Inventory Control satisfied:

A. CVCS requirements:

  • ALL available Charging pumps running.

OR

  • HPSI termination/throttle criteria satisfied.

OR

B. HPSI requirements:

Steps from

  • HPSI injection flow acceptable, refer to Exhibit 2, HPSI Flow SRO Curve.

IC-2 OR

  • HPSI termination/throttle criteria satisfied.

C. LPSI requirements:

  • LPSI injection flow acceptable, refer to Exhibit 3, LPSI Flow Curve.

OR

  • LPSI termination criteria satisfied.

OR

D. RVLMS LVL 06 or higher elevation indicates WET.

SRO Implement Heat Removal Steps of OP-2202.009, Functional Recovery.

Procedure Note:

Isolate leaking SG within 30 minutes of procedure entry to limit off-site release.

ANY 1. Check SIAS setpoints exceeded by EITHER of the following:

  • RCS pressure 1650 psia or less.
  • CNTMT pressure 18.3 psia or greater.

ANY 2. Verify SIAS and CCAS actuated on PPS inserts.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 6, 7, & 8 Event

Description:

A Steam Generator Tube leak ramps up from 12 gpm to 100 gpm over 5 min causes Reactor Trip, A Main Feed water line breaks inside containment, and Red Train Containment Spray pump fails to auto start.

Time Position Applicant's Actions or Behavior ANY *3. Verify Safety Injection flow to RCS as follows:

A. Check total HPSI flow acceptable using Exhibit 2, HPSI Flow Curve.

B. Check RCS pressure less than 1390 psia. (May or May not be but contingencies actions are not required)

C. Check total LPSI flow acceptable using Exhibit 3, LPSI Flow Curve.

ATC *4. IF EITHER 4160v Vital bus 2A3 OR 2A4 energized, THEN maintain shutdown margin during cooldown by EITHER of the following:

  • Verify Emergency Boration in progress, using 2202.010 Exhibit 1, Emergency Boration.

Examiners note: They should just verify emergency boration is in progress which automatically occurs when SIAS actuates.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 6, 7, & 8 Event

Description:

A Steam Generator Tube leak ramps up from 12 gpm to 100 gpm over 5 min causes Reactor Trip, A Main Feed water line breaks inside containment, and Red Train Containment Spray pump fails to auto start.

Time Position Applicant's Actions or Behavior ATC Examiner note: all actions from step 5 should already by complete.

5. IF EITHER 4160v Vital bus 2A3 OR 2A4 energized, THEN commence RCS cooldown as follows:

A. Reset Low SG Pressure setpoints during cooldown and depressurization.

B. Verify a maximum of ONE RCP running in EACH loop.

C. IF RCP 2P32A or 2P32B stopped, THEN verify associated PZR Spray valve in MANUAL and closed.

D. Monitor cooldown rate as follows:

  • Record RCS TC and PZR temperature using 2202.010 Attachment 8, RCS Cooldown Table.
  • Plot RCS pressure versus RCS TC using 2202.010 Attachment 1, P-T Limits every 15 minutes.

E. Initiate RCS cooldown using SDBCS Bypass valves or ADVs.

F. IF EFW or AFW available, THEN secure MFW flow as follows:

1) Trip running MFW pump.
2) Close ALL MFW Block valves.
3) Verify maximum of one condensate pump in service.
4) Maintain condensate header pressure less than 700 psig using condensate pump recircs and MFW pump recircs.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 6, 7, & 8 Event

Description:

A Steam Generator Tube leak ramps up from 12 gpm to 100 gpm over 5 min causes Reactor Trip, A Main Feed water line breaks inside containment, and Red Train Containment Spray pump fails to auto start.

Time Position Applicant's Actions or Behavior ANY *6. IF ALL RCPs secured, THEN perform the following:

A. Check natural circulation conditions established in at least ONE loop by ALL of the following:

  • Loop T less than 50°F.
  • TH and TC constant or lowering.
  • T between TH and average CETs less than 10°F.

SRO 7. Check BOTH 4160v Vital buses 2A3 AND 2A4 de-energized. (Not Met, perform contingency)

Step 7 contingency.

7. GO TO Step 11.

SRO 11. Check BOTH 4160v Non-vital buses 2A1 AND 2A2 de-energized.

(Not Met, perform contingency)

Step 7 contingency.

11. GO TO Step 13.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 6, 7, & 8 Event

Description:

A Steam Generator Tube leak ramps up from 12 gpm to 100 gpm over 5 min causes Reactor Trip, A Main Feed water line breaks inside containment, and Red Train Containment Spray pump fails to auto start.

Time Position Applicant's Actions or Behavior ANY 13. Check for indications of SG tube leakage by the following:

A. SG sample results indicate rising activity.

B. Secondary system activity rising:

1) Main steam lines
2) SG sample lines
3) Condenser off gas
4) Secondary Systems Radiation Trend recorder

D. SG levels.

1) Level rising faster in ONE SG with similar FW flow rates and steaming rates in BOTH SGs.
2) Rising SG level with ALL FW isolated.

E. Steam flow and FW flow prior to Reactor trip.

Procedure Note:

Goal is to isolate leaking SG within 30 minutes of procedure entry to limit off-site release.

535°F T H corresponds approximately to SG pressure of 925 psia (forced circ) or 700 psia (natural circ).

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 6, 7, & 8 Event

Description:

A Steam Generator Tube leak ramps up from 12 gpm to 100 gpm over 5 min causes Reactor Trip, A Main Feed water line breaks inside containment, and Red Train Containment Spray pump fails to auto start.

Time Position Applicant's Actions or Behavior ATC 14. Continue controlled cooldown to less than 535°F TH as follows:

A. Reset Low SG Pressure setpoint during cooldown and depressurization.

B. Check ANY RCP running.

Maintain RCS pressure within 100 psia above minimum RCP NPSH requirements, refer to 2202.010, Attachment 1, P-T Limits.

C. Initiate RCS cooldown using SDBCS Bypass valves or ADVs.

D. Notify Chemistry to monitor RDACS for offsite dose releases.

E. Check SG Blowdown aligned to SU/BD DI.

Procedure Note:

SG with highest leakage or activity is considered the ruptured SG.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 6, 7, & 8 Event

Description:

A Steam Generator Tube leak ramps up from 12 gpm to 100 gpm over 5 min causes Reactor Trip, A Main Feed water line breaks inside containment, and Red Train Containment Spray pump fails to auto start.

Time Position Applicant's Actions or Behavior ANY 15. Determine ruptured SG by comparing the following:

A. Secondary Systems Radiation Trend recorder:

E. SG levels.

1) Level rising faster in ONE SG with similar FW flow rates and steaming rates in BOTH SGs.
2) Rising SG level with ALL FW isolated.

F. Steam flow and FW flow prior to Reactor trip.

G. SG water sample results.

SRO 16. Minimize secondary contamination by performing BOTH of the following:

A. Commence isolation of ruptured SG by performing local actions ONLY of 2202.010 Attachment 10, SG Isolation.

B. 2202.010 Attachment 19, Control of Secondary Contamination.

Cue: If contacted as the AO then report after 5 min that the local portions of Attachment 10 for B S/G are complete.

Cue: When contacted as NLO to perform Att. 19, respond as requested.

BOP 17. Isolate ruptured SG Steam Supply to EFW pump 2P7A as follows:

Procedure Note:

A rise in SG level when feeding with AFW Pump 2P75 or EFW Pump 2P7B is confirmation of feed capability.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 6, 7, & 8 Event

Description:

A Steam Generator Tube leak ramps up from 12 gpm to 100 gpm over 5 min causes Reactor Trip, A Main Feed water line breaks inside containment, and Red Train Containment Spray pump fails to auto start.

Time Position Applicant's Actions or Behavior BOP A. Verify EITHER of the following running and capable of feeding SGs:

EFW Pump 2P7B (refer to 2202.010 Attachment 46, Establishing EFW Flow.)

Procedure Note:

If offsite power available, use of AFW to control SG levels is preferred to minimize waste water production.

BOP AFW Pump 2P75 using 2202.010 Attachment 52, Establishing AFW Flow.

BOP B. Stop EFW pump 2P7A as follows:

1) Override and close Steam Supply to 2P7A valve (2CV-0340-2).
2) Close Main Steam Supply valve from ruptured SG to EFW pump 2P7A:

A. Monitor RCS TH during cooldown with ANY of the following:

PMS point T4614 PMS point T4714 SPDS display B. Check opposite SG does NOT have steam line break.

C. WHEN RCS TH less than 535°F, THEN isolate ruptured SG using 2202.010 Attachment 10, SG Isolation.

D. Check MSSVs for ruptured SG closed by locally checking individual valve tail pipes for leakage.

E. Maintain ruptured SG pressure 1050 psia or less with ONE of the following:

  • Upstream ADV Revision 0 Page 64 of 65

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 6, 7, & 8 Event

Description:

A Steam Generator Tube leak ramps up from 12 gpm to 100 gpm over 5 min causes Reactor Trip, A Main Feed water line breaks inside containment, and Red Train Containment Spray pump fails to auto start.

Time Position Applicant's Actions or Behavior Examiner Note: The crew may also elect to isolate the SG earlier using floating step 31 from HR-2.

31. Isolate most affected SG using 2202.010 Attachment 10, SG Isolation.

IF affected SG still pressurized,THEN check MSSVs for affected SG closed by locally checking individual valve tail pipes for leakage.

BOP 2. Verify each component in the following table in the indicated position:

TABLE 1 COMPONENT DESCRIPTION NUMBER LOCATI POSITION ON ADV UPSTRM ISOL 2CV-1002* 2C02 CLOSED (1) 2CV-1001 PERMISSIVE 2CV-1001 2C02 OFF (1)

MSIV HEADER #1 2SV-1010-1A 2C17 CLOSED MSIV HEADER #1 2SV-1010-2A 2C16 CLOSED MSIV HEADER #1 BYP 2CV-1040-1 2C17 CLOSED (1)

MAIN STEAM TO EFWP TURB 2K03 2CV-1000-1 2C17 CLOSED FEEDWATER BLOCK VALVE TO SG-A 2CV-1024-1 2C17 CLOSED Control Room FEEDWATER BLOCK VALVE TO SG-A 2CV-1023-2 2C16 CLOSED actions for 2202.010 SG BLOWDOWN ISOLATION 2CV-1016-1 2C17 CLOSED (1)

Standard 2P7B DISCHARGE TO SG-A 2CV-1038-2* 2C17 CLOSED (1)

Attachment 10 FLOW CONTROL VALVE TO SG-A 2CV-1025-1* 2C17 CLOSED (1)

SAMPLE ISOLATION VALVE SG-A 2CV-5850 2C17 CLOSED (1) 2P7A DISCHARGE TO SG-A 2CV-1026-2* 2C16 CLOSED (1) 2P7A DISCHARGE TO SG-A 2CV-1037-1* 2C16 CLOSED (1)

SAMPLE ISOLATION VALVE STEAM GEN A 2CV-5852-2* 2C16 CLOSED (1)

  • Denotes override capability.

NOTE #1: Valves may be open at SM/CRS discretion.

Critical Task: The crew must isolate A SG (2202.010 Attachment 10 completed) within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after the Reactor trip.

Termination criteria: RCS PT limits maintained or restored and A SG isolated or at the discretion of the lead examiner.

Revision 0 Page 65 of 65

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 45 of 201 2104.001 SAFETY INJECTION TANK OPERATIONS CHANGE: 047 11.0 RAISING SAFETY INJECTION TANK PRESSURE NOTE If raising SIT level or pressure prior to/or during plant heatup, then SIT levels should be high and pressures low in operability band to ensure low level, high pressure condition will not be created when SITs heatup.

11.1 Verify HP Nitrogen Supply aligned with N2 regulator set at desired pressure using N2 System Operations (2104.009), Exhibit 7, Nitrogen Manifold Operations.

11.2 Open Supply Header to Containment Isolation 2CV-6207-2 (2HS-6207-2).

{4.3.3}

CAUTION Cross-connecting SITs via nitrogen supply valves in Modes 1, 2 and 3 (with RCS pressure greater than or equal to 700 psia) will cause associated SITs to be inoperable.

11.3 IF desired to raise pressure in SIT (2T-2A),

THEN perform the following:

CRITICAL STEP 11.3.1 Open N2 Supply valves 2SV-5005A/B (2HS-5005).

11.3.2 WHEN 2T-2A at desired pressure, THEN close N2 Supply valves 2SV-5005A/B (2HS-5005).

11.4 IF desired to raise pressure in SIT (2T-2B),

THEN perform the following:

CRITICAL STEP 11.4.1 Open N2 Supply valves 2SV-5025A/B (2HS-5025).

11.4.2 WHEN 2T-2B at desired pressure, THEN close N2 Supply valves 2SV-5025A/B (2HS-5025).

11.5 IF desired to raise pressure in SIT (2T-2C),

THEN perform the following:

CRITICAL STEP 11.5.1 Open N2 Supply valves 2SV-5045A/B (2HS-5045).

11.5.2 WHEN 2T-2C at desired pressure, THEN close N2 Supply valves 2SV-5045A/B (2HS-5045).

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 46 of 201 2104.001 SAFETY INJECTION TANK OPERATIONS CHANGE: 047 11.6 IF desired to raise pressure in SIT (2T-2D),

THEN perform the following:

CRITICAL STEP 11.6.1 Open N2 Supply valves 2SV-5065A/B (2HS-5065).

11.6.2 WHEN 2T-2D at desired pressure, THEN close N2 Supply valves 2SV-5065A/B (2HS-5065).

11.7 Close Supply Header to Containment Isolation 2CV-6207-2 (2HS-6207-2).

11.8 Verify HP N2 from Unit 1 secured IAW N2 System Operations (2104.009),

Exhibit 7, Nitrogen Manifold Operations.

Appendix D Scenario Outline Form ES-D-1 Facility: _ANO-2_________ Scenario No.: ___2 (New)______ Op-Test No.: _2015-1___

Examiners: ___________________________ Operators: ____________________________

Initial Conditions: 100%, 250 EFPD. B Pressurizer pressure and level aligned to B channel and 2P-89C aligned to green.

Turnover: Red Train Maintenance Week. EOOS indicates Minimal Risk.

Evolution scheduled: Unload and secure #1 EDG using OP-2104.036, Emergency Diesel Generator Operations.

Event Malf. No. Event Event No. Type* Description 1 N (BOP)

Unload and secure #1 EDG.

N (SRO) OP-2104.036, Emergency Diesel Generator Operations.

TS (SRO) 2 CVC4817DEM I (ATC) Letdown flow controller auto signal drifts high.

I (SRO) OP-2203.012L Annunciator 2K12 Corrective Action (ACA).

3 FW2P8BSS C (BOP) B Heater Drain pump shaft shear inside the casing.

C (SRO) OP-2203.012C Annunciator 2K03 Corrective Action.

4 CVC2P36CFAL C (ATC) 2P-36C charging pump breaker trip.

C (SRO) OP-2203.036, Loss of Charging AOP 5 DI_HS_3810_2 C (BOP) A Main chiller trip.

K13-C03 C (SRO) OP-2203.012M Annunciator 2K13 Corrective Action (ACA).

6 CV0252 C (ATC) Turbine Control Valve fails closed.

C (SRO) OP-2203.024 Loss of Turbine Load AOP.

TS (SRO) 7 M (All) Inadvertent Red train Main Steam Isolation Signal causing ESFMSIS1I a reactor trip.

OP-2202.001, Standard Post Trip Actions (SPTAs) EOP 8 M (All) Loss of Coolant accident.

RCSLOCATHB OP-2202.003, Loss of Coolant Accident EOP.

9 SIS2P89BDEG C (BOP) 2P-89B Motor overload.

ESFK311AAF C (SRO) 2CV-5035-1 High pressure safety injection and 2CV-5037-1 Low pressure safety injection valves fail to open.

OP-2202.010 Standard Attachments EOP and OP-2203.012E 2K05 ACA.

10 ESFCCAS2 C (BOP) Green train Containment Cooling fails to actuate.

C (SRO) OP-2202.010 Standard Attachments EOP End RCS cooldown in progress and Margin to Saturation > 30 point degrees.

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Revision 1 Page 1 of 43

Appendix D Scenario Outline Form ES-D-1 Target Quantitative Attributes (Section D.5.d) Actual Attributes Malfunctions after EOP entry (1-2) 2 Abnormal Events (2-4) 4 Major Transients (1-2) 2 EOPs entered requiring substantive actions (1-2) 1 EOP contingencies requiring substantive actions (0-1) 0 Critical Tasks (2-3) 3 Critical Task Justification Commence an RCS cooldown Cooling down and depressurizing CE EPGB Simulator CTs:

within 30 minutes of entry into the RCS removes decay heat and CT-20, Cool down and OP-2202.003, LOCA EOP. lowers the DP at the break, depressurize RCS (LOCA-slowing the leak rate and 09) reducing makeup volume CR-ANO-2-2010-948, required. SDC entry conditions Critical task criteria are also required for long-term cooling.

Perform one or more of the SI flow keeps the core covered, CE EPGB Simulator CTs:

following to maintain OR restore cooled, and borated. Inadequate CT-16, Establish required Margin to Saturation (MTS) > 30 SI flow could result in a net loss of SI flow (LOCA-02) degrees F. RCS inventory, pressure control, 1015.050 Time Critical Start a Green train HPSI pump and subcooling. Once subcooling Operation Actions, 2P-89C is lost, pressurizer level is no Attachment C Throttle open red train HPSI longer a valid indication of RCS valve 2CV-5035-1. mass inventory, and a reactor head void can form, both of which If MTS lowers < 30 degrees F, it complicate the event recovery.

must be restored >30 degrees F within 10 min. RCP operating limits require MTS to be >300F.

Establish RCS pressure control to Once RCS subcooling is lost, CE EPGB Simulator CTs:

maintain RCS subcooling. After PZR level is no longer a valid CT-06, Establish RCS the HPSI failures have been indication of RCS inventory. A Pressure Control (LOCA-addressed and MTS restored to reactor head void can form, and if 12)

>30 degrees F then maintain left uncontrolled, could result in pressure and temperature within core uncovery and fuel damage.

the PT limits of <2000 F and

>300F MTS throughout implementation of OP-2202.003, LOCA EOP.

Scenario #2 Objectives

1) Evaluate individual ability to unload and secure #1 Emergency Diesel Generator.
2) Evaluate individual response to a Heater Drain Pump shaft shear.
3) Evaluate individual response to a Charging pump trip.
4) Evaluate individual response to a Loss of a Main Chiller.
5) Evaluate individual response to a failure of a Letdown flow controller.
6) Evaluate a crews response to turbine control valve failing closed.
7) Evaluate a crews response to an inadvertent Main Steam Isolation Signal Actuation.
8) Evaluate crew ability to mitigate a LOCA.
9) Evaluate individual response to Safety Injection valve and pump failures.
10) Evaluate individual response to Containment cooling failures.

Revision 1 Page 2 of 43

Appendix D Scenario Outline Form ES-D-1 SCENARIO #2 NARRATIVE Simulator session begins with the plant at 100% power steady state. The BOP will unload and secure the #1 Emergency Diesel Generator. The SRO will have to enter TS 3.8.1.1 action b and TS 3.4.4 action b.

When the #1 EDG is secured and the SRO has entered the appropriate TS or when cued by the lead examiner, the letdown flow controller signal will drift high. This will cause elevated letdown flow. The ATC should recognize elevated letdown flow. The ATC should take manual control of the letdown flow controller and adjust letdown to restore PZR level near setpoint. The crew should follow up with the Annunciator corrective action. Not credited as an abnormal event since they may take action prior to alarm annunciation.

After the ATC has control of letdown flow and is restoring PZR level to setpoint, and cued by the lead examiner, 2P-8B Heater Drain pump shaft will shear. The BOP will report alarms for low flow and differential pressure on 2P-8B Heater Drain pump. The SRO should refer to the Annunciator Corrective Action and direct the BOPs actions. The BOP should investigate and determine that flow and differential pressure indicate zero. The BOP should secure 2P-8B and reduce turbine load as necessary to reactor power less than 100%. [Site OE: CR-ANO-1-2012-864, Unit 1 Service water pump shaft shear, CR-ANO-1-2013-2745, Heater drain pump degradation and failure.]

When the B Heater Drain Pump has been secured and power is stabilized <100% and cued by the lead examiner, C Charging pump will trip. The SRO will enter the Loss of Charging AOP.

The ATC will check for a suction source and discharge flow path. The ATC will then start a backup charging pump by moving the lead charging pump selector switch. [Site OE: CR-ANO-2-2015-0432, 2P-36A charging pump stopped running, CR-ANO-2-2001-0685, 2P-36C tripped.]

When a backup charging pump is in service or cued by the lead examiner, A Main Chiller will trip.

This will cause alarms on 2K-13 in the back of the control room. The BOP should assess the alarms using the Annunciator Corrective Action and direct a NLO to investigate. The loss of the Main Chiller will cause a loss of cooling to the control element drives and the Containment building coolers. The BOP should align Service Water to B Main Chiller and direct the NLO to start the B Main Chiller.

After the BOP has aligned the B Main Chiller and directed a NLO to start a Main chiller, or cued by lead examiner, #4 turbine control valve will fail closed. This will lower steam flow, raise steam pressure, raise RCS temperature and lower reactor power. The crew should recognize the signs of load rejection and determine that #4 control valve (#4CV) has failed closed. The SRO will enter OP-2203.024, Loss of Turbine Load AOP. The ATC will commence normal boration to lower Tave to Tref. The crew should contact a NLO to determine the reason control valve #4 CV has failed.

The SRO should enter TS 3.2.6 due to Tcold being out band high. The crew should contact I&C to fail #4 CV closed to prevent it from opening. [Site OE: CR-ANO-2-2009-109, Turbine Control Valve failed closed during power ascension.]

Revision 1 Page 3 of 43

Appendix D Scenario Outline Form ES-D-1 SCENARIO #2 NARRATIVE (continued)

After, the ATC has completed the required reactivity manipulation and cued by the lead examiner, an Inadvertent red train Main Steam Isolation Signal (MSIS) will occur. The MSIS will close the MSIVs, trip the Main Feedwater pumps, and Condensate pumps. RCS pressure will rise causing an automatic plant trip if the crew does not manually trip the reactor. [Site OE: CR-ANO-2-2013-005, Inadvertent SIAS, CIAS, and CCAS.]

The crew will implement OP-2202.001, Standard Post Trip Actions (SPTA) EOP. The crew will assess safety functions. The crew should recognize the signs of LOCA and actuate Safety Injection Actuation Signal (SIAS) and Containment Cooling Actuation Signal (CCAS) and the SRO should diagnose and enter OP-2202.003, Loss of Coolant Accident EOP. The BOP should recognize that two Safety Injection valves failed to open and open them. The B High Pressure Safety Injection (HPSI) pump motor will degrade and the BOP should secure the B HPSI pump.

They should also start the swing HPSI pump 2P-89C. The BOP should also recognize that green train Containment Cooling did not actuate as designed and place the green train containment coolers in emergency mode. After the crew has entered the LOCA EOP, the crew will commence a cooldown. [Industry OE: SEN-220, SEN-216, & SEN-182, RCS leakage events.]

Revision 1 Page 4 of 43

Appendix D Scenario Outline Form ES-D-1 Simulator Instructions for Scenario 2 B channel pressurizer pressure and level controllers are in service. 2P-89C aligned to green.

Loop 1 Service Water return aligned to Emergency Cooling Pond.

T1, T2, T3, T4, T5, T6 T7 & T8 set to false.

T7 = Reactor Trip Event Malf. No. Value/ Event No. Ramp Description Time 1 Unload and secure #1 EDG.

OP-2104.029, Service Water System Operations.

2 CVC4817DEM 100 / 4 Letdown flow controller auto signal drifts high.

Trigger 1 min. OP-2203.012L Annunciator 2K12 Corrective Action (ACA).

3 FW2P8BSS active B Heater Drain pump Shaft Shear inside the casing.

Trigger 2 OP-2203.012C Annunciator 2K03 Corrective Action.

4 CVC2P36CFAL active 2P-36C charging pump breaker trip.

Trigger 3 OP-2203.028, Pressurizer System Malfunction AOP 5 DI_HS_3810_2 Active A Main chiller trip.

K13-C03 On / OP-2203.012M Annunciator Corrective Action.

Trigger 4 delete in = 2 sec.

6 CV0252 0 Turbine Control Valve fails closed.

Trigger 5 OP-2203.024 Loss of Turbine Load.

7 ESFMSIS1I active Inadvertent Red train Main Steam Isolation Signal causing a reactor trip.

Trigger 6 OP-2202.001, Standard Post Trip Actions (SPTAs)

EOP 8 RCSLOCATHB 200 Loss of Coolant accident.

gpm/ 10 OP-2202.003, Loss of Coolant Accident.

Trigger 7 min.

Delay =

1 min.

9 SIS2P89BDEG 10 min. 2P-89B Motor overload.

Trigger 8 2CV-5035-1 High pressure safety injection and 2CV-active 5037-1 Low pressure safety injection valves fail to open.

ESFK311AAF OP-2202.010 Standard Attachments EOP.

10 ESFCCAS2 active Green train Containment Cooling fails to actuate.

OP-2202.010 Standard Attachments EOP Revision 1 Page 5 of 43

Appendix D Scenario Outline Form ES-D-1 Simulator Operator CUEs At T=0 Unload and secure #1 EDG.

Cue: If contacted as a NLO that the control room is going to secure #1 EDG then acknowledge the communication.

Cue: When contacted as a NLO to perform air roll, then cause the starting air trouble alarm to come in and clear, then report step 13.9 is complete.

Cued by Trigger T1 Letdown flow controller auto signal drifts high.

lead examiner Cue: When contacted as the WWM, then report that I & C planner will begin planning work on failed level instrument.

Cued by Trigger T2 B Heater Drain pump Shaft Shear inside the casing.

lead examiner Cue: If contacted as a NLO to investigate 2P-8B, after 2 min. report that the pump looks normal from the outside but has no DP and is much quieter than normal.

Cue: If contacted as a NLO to perform post stop check of 2P-8B then report that post stop checks are Sat.

Cued by Trigger T3 2P-36C charging pump breaker trip.

lead examiner Cue: If requested as a NLO to vent 2P-36C, then after 1 min report solid stream of water from the vent valve.

Cued by Trigger T4 A Main chiller trip.

lead examiner Cue: If contacted as the NLO to investigate A Main Chiller, after ~ 1 min. report that A Main Chiller does not have any power.

Cue: If requested as a NLO to check A Main Chiller breaker, after ~ 1 min. report that the B phase overcurrent relay is tripped and there is an acrid odor also the report the the relay glass has black soot on the relay glass.

Cue: When contacted as the NLO to perform step 1, after 1 min. report that the oil pump hand switch is in AUTO, The SLIDE STOP in AUTO, SEP oil temperature greater than 600F, SLIDE VALVE in AUTO, SLIDE VALVE position is less than 9% and the Emergency Stip Button is not depressed.

Cue: When contacted as the NLO to verify the chilled water flow, after 1 min report flow ~1400 gpm.

Cue: When contacted as the WWM, then report that Electrical will begin troubleshooting A Main Chiller.

Cued by Trigger T5 Turbine Control Valve fails closed.

lead examiner Cue: If asked, report that the MTG #4 CV indicates closed by local verification and If ask, report that the wires for the connector to the servo for # 4 CV are broken off and hanging to the side.

Cue: If requested as the WWM, then report that I&C will come to the Control Room to assist in failing #4 Main Turbine Generator Control valve closed.

Cue: If requested, after 5 minutes have the communicator enter the simulator control room and perform as requested by the crew.

Cue: If requested as I&C after ~ 5 min. come to the control room and respond as requested.

Cue: If requested as the Shift Manager to authorize the T-Mod to lift leads for the control valve give authorization to perform the T-Mod.

Trigger T6 Inadvertent Red train Main Steam Isolation Signal causing a reactor trip.

Revision 1 Page 6 of 43

Appendix D Scenario Outline Form ES-D-1 Cue: If contacted as the STA to report to the control room, acknowledge the request.

Cue: If contacted as a NLO to perform Attachment 47 Field Operator Post Trip Actions, acknowledge request.

Trigger T7 Loss of Coolant accident.

Tigger when 2P-89B Motor overload.

loca is entered.

Cue: If requested as a NLO to check 2A-406 current draw, then after ~ 1min. report that amps indicate the following Phase A: 108 amps, Phase B: 103 amps, Phase C: 109 amps and all phases are rising. After 2 min. call back and report amps are Phase A: 152 amps, Phase B: 148 amps, Phase C: 155 amps and all phases are still rising.

2CV-5035-1 High pressure safety injection and 2CV-5037-1 Low pressure safety injection valves fail to open.

Green train Containment Cooling fails to actuate.

Revision 1 Page 7 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 2 Event No.: 1 Event

Description:

Unload and secure #1 EDG.

Time Position Applicant's Actions or Behavior Procedure caution:

EDG may trip due to anti-motoring if opening 2A-308 is delayed at 100 KW load.

BOP B. WHEN 5 minutes time has elapsed at 1400 KW, THEN perform the following:

1. Reduce load to approximately 100 KW.
2. Open 2DG1 Output breaker 2A-308 (152-308 CS).

Cue: If contacted as a NLO that the control room is going to secure #1 EDG then acknowledge the communication.

BOP 13.3.2 IF 2DG1 post maintenance testing run in progress, THEN unload as follows using Governor Control Switch (CS 4):

Examiner Note: Step 13.3.2 is N/A.

BOP 13.4 Verify the following 2DG1 parameters:

Frequency approximately 60 Hz, using Governor Control switch (CS 4).

Voltage approximately 4160 volts, using Voltage Control switch (CS 3).

SRO 13.5 Perform the following administrative actions:

13.5.1 Verify Unit 1 has taken appropriate actions as identified in Attachment B of Control Room Emergency Air Conditioning and Ventilation (2104.007).

13.5.2 Verify entry into TS 3.8.1.1, 3.8.1.2, and 3.4.4 as applicable.

Examiner Note: The SRO must enter TS 3.8.1.1 action b and TS 3.4.4 SRO 13.5.3 Declare Diesel Engine inoperable due to START handswitch in STOP (energizes Shutdown 5 relay for 60 seconds which blocks Engine auto start).

Procedure Note:

Expect annunciator 2DG1 NOT AVAIL (2K08-F1) when stopping 2DG1.

BOP 13.6 Secure 2DG1 by placing Engine Start switch (2HS-2809-1) in STOP.

BOP 13.7 WHEN 2DG1 NOT AVAIL (2K08-F1) alarm clear, THEN EDG may be declared OPERABLE.

Revision 1 Page 8 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 2 Event No.: 1 Event

Description:

Unload and secure #1 EDG.

Time Position Applicant's Actions or Behavior BOP 13.8 Check the following pumps auto start:

Standby Lube Oil Circulating pump (2P-171A)

Standby Coolant System Circulating pump (2P-167A)

Procedure Caution:

If DC control power to Engine Governor NOT available, the engine will start when air rolled unless overspeed trip mechanism is tripped with Emergency Stop pushbutton.

Procedure Note:

The air roll of the EDG may be N/Aed or delayed with the concurrence of System Engineering and the OPS Manager.

BOP 13.9 Perform the following to air roll 2DG1:

13.9.1 Verify engine shutdown greater than 15 minutes.

SRO 13.9.2 Perform the following for EDG inoperability:

A. Verify Unit 1 has taken appropriate actions as identified in Attachment B of Control Room Emergency Air Conditioning and Ventilation (2104.007).

B. Verify entry into TS 3.8.1.1, 3.8.1.2, and 3.4.4 as applicable.

C. Declare Diesel Engine inoperable due to Local Engine Control switch in LOCKOUT.

Examiner Note: SRO must enter TS 3.8.1.1 action b and TS 3.4.4 BOP Direct a NLO to perform an Air roll IAW with step 13.9.

Cue: When contacted as a NLO to perform air roll, then cause the starting air trouble alarm to come in and clear, then report step 13.9 is complete.

SRO 13.10 WHEN ALL of the following are complete:

Engine Control switch in AUTO.

Engine Control switch key removed.

2DG1 NOT AVAIL (2K08-F1) alarm clear.

All alarms concerning 2DG1 cleared OR any concern raised by alarms is resolved.

IF Engine Air roll will be performed, THEN verify Engine Air roll completed.

THEN 2DG1 may be declared OPERABLE.

Termination criteria: When the #1 EDG is secured and the SRO has entered the appropriate TS or at lead examiner's discretion.

Revision 1 Page 9 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 2 Event No.: 2 Event

Description:

Letdown flow controller auto signal drifts high.

Time Position Applicant's Actions or Behavior Cued by ATC Determine that the letdown flow is elevated causing pressurizer level to lead lower.

examiner SRO Direct manual control of letdown.

Examiner Note: The guidance to take manual control of letdown flow is contained in the ACA for 2K-12 B1 Regen Hx to 2E-29 Temperature HI, 2K-12 C1 Letdown Heat exchanger temperature HI, and 2K-12 F1 Letdown to Purification Filters Flow HI but the letdown alarms may not come in this case prior to the crew recognizing the failure.

The SRO may elect to use the guidance contained in EN-OP-115 Conduct of Operations which states the following.

If an automatic control malfunctions, immediately place that control in manual.

ATC Implement Annunciator corrective actions as necessary for 2K-12.

2K-12 B1 ANY 2.1 Check temperature on 2TI-4820 and Computer Point (T4820).

ATC 2.2 IF Letdown Flow Controller (2HIC-4817) NOT controlling in AUTOMATIC, THEN perform the following per Chemical and Volume Control (2104.002):

2.2.1 Place 2HIC-4817 in MANUAL.

2.2.2 Stabilize flow.

2K-12 C1 ANY 2.1 Check temperature on 2TI-4815 and Computer Point (T4805).

ATC 2.2 Verify letdown flow (2FIS-4801) within 10 gpm of charging flow (2FIS-4863). Refer to Chemical and Volume Control (2104.002).

2.3 Locally verify CCW flow through Letdown Heat Exchanger (2FIS-526l).

Examiner Note: The ATC will be required to control letdown in manual for until completion of the drill.

Cue: if requested to report CCW flow to the letdown heat exchanger, then report flow is ~ 200 gpm.

2K-12 F1 ANY 2.1 Check flow on 2FIS-4801 and Computer Point (F4801).

ATC 2.2 IF Letdown Flow Controller (2HIC-4817) NOT controlling in AUTOMATIC, THEN perform the following per Chemical and Volume Control (2104.002):

2.2.1 Place 2HIC-4817 in MANUAL.

2.2.2 Reduce flow to < 128 gpm.

SRO Contact Work Week Manager to repair 2HIC-4817.

ATC Implement Annunciator corrective actions 2K-12 J1.

Revision 1 Page 10 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 2 Event No.: 2 Event

Description:

Letdown flow controller auto signal drifts high.

Time Position Applicant's Actions or Behavior 2K-12 J1 ANY Radmonitor Flow Low applicable actions:

2.3 Verify letdown flow (2FIS-4801) > 28 gpm. Refer to Chemical and Volume Control (2104.002).

2.4 Verify L/D to Rad Monitor (2CV-4804) open.

Cue: When contacted as the WWM, then report that I & C planner will begin planning work on failed level instrument.

Termination Criteria: Letdown being controlled in manual or at lead examiner's discretion.

Revision 1 Page 11 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 2 Event No.: 3 Event

Description:

B Heater Drain pump Shaft Shear inside the casing.

Time Position Applicant's Actions or Behavior Cued by ANY Announce annunciators:

lead 2K03-D7 2P-8B P HI/LO.

examiner 2K03 F7 2P-8B P DISCH FLOW LO BOP BOP should recognize that 2P-8B has zero flow and zero P.

SRO/BOP Implement 2203.012C Annunciator 2K-03 D7 Corrective Action.

Cue: If contacted as a NLO to investigate 2P-8B, after 2 min. report that the pump looks normal from the outside but has no DP and is much quieter than normal.

BOP 2.1 Check HDP 2P-8B Differential pressure (2PDIS-0723).

BOP 2.2 Check HDP 2P-8B Discharge flow (2FIS-0723).

2K03 D7 actions SRO/BOP 2.3 IF 2P-8B Differential pressure and Discharge flow normal for plant conditions, THEN no further action required.

Procedure Note:

At full power operation, securing a Heater Drain pump will result in a Reactor power rise (~ 0.15%) and a lowered megawatt output (~ 30 MW). Depending on time in core life, Reactor power change may be slightly higher (end of life) or slightly lower (beginning of life) than 0.15%.

BOP/ATC Maintain power less than 100%

BOP 2.4 IF High P alarm in for greater than seven seconds, THEN perform the following:

Examiner Note: High P alarm will not be in.

2K03 D7 actions BOP 2.5 Check proper operation of 2P-8B Recirc (2CV-0719) IAW Attachment A.3 of Conduct of Operations (1015.001).

BOP 3.0 TO CLEAR ALARM 3.2 Secure Heater Drain Pump 2P-8B (2HS-0720).

SRO/BOP Implement 2203.012C Annunciator 2K-03 F7 Corrective Action.

Procedure Note:

Heater Drain pump flow indication does not account for pump recirc flow. If recirc valve open and pump P normal, then pump has adequate flow.

Revision 1 Page 12 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 2 Event No.: 3 Event

Description:

B Heater Drain pump Shaft Shear inside the casing.

Time Position Applicant's Actions or Behavior BOP 2.1 IF BOTH of the following conditions apply:

2P-8B Recirc (2CV-0719) open Pump P NOT in alarm (2K03-D7)

THEN no further action required.

BOP 2.2 Check proper operation of 2P-8B Recirc (2CV-0719) IAW Attachment A.3 of Conduct of Operations (1015.001).

Procedure Note:

At full power operation, securing a Heater Drain pump will result in a Reactor power rise (~ 0.15%) and a lowered megawatt output (~ 30 MW). Depending on time in core life, Reactor power change may be slightly higher (end of life) or slightly lower (beginning of life) than 0.15%.

BOP 2.3 IF actual flow can not be raised greater than 1200 gpm, THEN perform the following:

2.3.1 Secure 2P-8B using Condensate and Feedwater Operations (2106.016).

BOP/ATC 2.3.2 Verify Reactor power less than 100%.

ANY 2.3.3 IF necessary to maintain MFP suction pressure greater than 450 psig, THEN start standby Condensate pump. Refer to Condensate and Feedwater Operations (2106.016).

BOP 3.0 TO CLEAR ALARM 3.1 Stop Heater Drain Pump 2P-8B (2HS-0720).

Cue: If contacted as a NLO to perform post stop check of 2P-8B then report that post stop checks are Sat.

Termination criteria: Affected channel points placed in trip or at lead examiner's discretion.

Revision 1 Page 13 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 2 Event No.: 4 Event

Description:

2P-36C charging pump breaker trip.

Time Position Applicant's Actions or Behavior Cued by ANY Announce annunciator 2K12-B3 HEADER FLOW LO is due to C lead Charging pump trip.

examiner SRO Enter OP-2203.036, Loss of Charging AOP.

ATC 1. Check Charging flow path as follows:

Suction source aligned to ANY of the following:

- VCT

- RWT

- BAMT Charging Header Isolation valve (2CV-4840-2) open.

ANY 2. Check BOTH of the following conditions exist:

Lead Charging pump STOPPED Green indicating light ON ATC 2. IF lead Charging pump STOPPED AND green indicating light OFF, THEN restore charging by performing the following:

A. Start backup charging pump by selecting a new lead pump using Charging Pumps Select Switch (2HS-4868).

B. IF Letdown isolated, THEN restore Letdown using Attachment A, Letdown Restoration.

ANY Direct NLO to vent 2P-36C.

C. Locally check AFFECTED Charging pump for gas binding using Attachment B, Charging Pump Venting.

Cue: If requested as a NLO to vent 2P-36C, then after 1 min report solid stream of water from the vent valve.

ATC B. IF desired, THEN place AFFECTED Charging pump handswitch in STOP.

Revision 1 Page 14 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 2 Event No.: 4 Event

Description:

2P-36C charging pump breaker trip.

Time Position Applicant's Actions or Behavior BOP E. IF AFFECTED Charging pump was NOT gas bound, THEN perform the following:

1) Complete actions required for shifting lead charging pumps using Attachment C, Follow Up Actions.
2) Exit this procedure.

Termination Criteria: A backup charging pump in service or at lead examiner's discretion.

Revision 1 Page 15 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 2 Event No.: 5 Event

Description:

A Main chiller trip.

Time Position Applicant's Actions or Behavior Cued by ANY Announce annunciators:

Lead 2K13-A3 Main Chiller 2VCH-1A Trouble. (In and clear)

Examine r 2K13-C3 Main Chiller 2VCH-1A Overload.

SRO/BOP Implement 2K13-A3 Annunciator Corrective Action.

2K13 A3 BOP Dispatch NLO to investigate the follow items.

actions 2.1 To determine cause of alarm check the following:

RIS 2K1564 (Local)

Alarm Display on 2VCH-1A Control panel (2C121) 2VCH-1A Remote Starter panel (IQ-1000 Module) 2.2 IF 2VCH-1A tripped OR desired to secure, THEN start 2VCH-1B using Main Chilled Water System (2104.026).

2.3 IF Supply breaker (2A-108) tripped, THEN check 2A-108 breaker cubicle for dropped flag indications.

Cue: If contacted as the NLO to investigate A Main Chiller, after ~ 1 min. report that A Main Chiller does not have any power.

Cue: If requested as a NLO to check A Main Chiller breaker, after ~ 1 min. report that the B phase overcurrent relay is tripped and there is an acrid odor also the report the the relay glass has black soot on the relay glass.

BOP Implement 2K13-C3 Annunciator Corrective Action.

2K13 C3 BOP 2.1 Check current draw for each phase at 2A-108.

actions 2.2 Check breaker 2A-108 for dropped relay flags.

2.3 IF breaker 2A-108 has tripped, THEN perform the following using Main Chilled Water System (2104.026):

2.3.1 Verify Main chiller 2VCH-1A secured.

2.3.2 Start Main chiller 2VCH-1B.

BOP Transition to OP-2104.026 Main Chilled Water System to start B Main chiller.

Revision 1 Page 16 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 2 Event No.: 5 Event

Description:

A Main chiller trip.

Time Position Applicant's Actions or Behavior Procedure Note:

Steps 1.0 and 2.0 may be performed concurrently.

Under emergency conditions, cycling the local Main Chiller disconnect open then closed will reset the 10 minute Recycle Delay. Since this defeats an interlock it should not be done without SM permission Exhibit 2 BOP Direct a NLO to perform the following locally.

Main Chiller trip 1.0 LOCALLY perform the following for Chiller to be STARTED:

response 1.1 Verify the following at Microcomputer Control Center:

Oil pump hand switch in AUTO SLIDE STOP in AUTO SEP oil temperature greater than 60ºF SLIDE VALVE in AUTO SLIDE VALVE position less than or equal to 9%

1.2 Verify Emergency Stop Button NOT depressed.

Cue: When contacted as the NLO to perform step 1, after 1 min. report that the oil pump hand switch is in AUTO, The SLIDE STOP in AUTO, SEP oil temperature greater than 600F, SLIDE VALVE in AUTO, SLIDE VALVE position is less than 9% and the Emergency Stip Button is not depressed.

BOP 2.0 IF desired to start a STANDBY chiller, THEN perform the following from the CONTROL ROOM:

2.1 IF desired to start 2VCH-1A, THEN perform the following:

Examiner Note: step 2.1 is N/A due to the chiller tripping.

BOP 2.2 IF desired to start 2VCH-1B, THEN perform the following:

2.2.1 Open the following valves 2VCH-1B Evaporator Inlet 2CV-3807 (2HS-3807) 2VCH-1B Condenser Inlet 2CV-3808 (2HS-3808) 2.2.2 Close the following valves:

2VCH-1A Evaporator Inlet 2CV-3805 (2HS-3805) 2VCH-1A Condenser Inlet 2CV-3806 (2HS-3806)

Revision 1 Page 17 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 2 Event No.: 5 Event

Description:

A Main chiller trip.

Time Position Applicant's Actions or Behavior BOP Direct the NLO:

2.3 Verify Chilled Water Flow greater than 500 gpm.

Cue: When contacted as the NLO to verify the chilled water flow, after 1 min report flow ~1400 gpm.

BOP Direct the NLO to perform step 3 to locally start the Main Chiller.

3.0 LOCALLY perform the following for Main Chiller to be STARTED:

3.1 Depress RUN key.

3.2 WHEN Slide Valve position reaches ~15%,

THEN depress MANUAL UNLOAD key to place slide valve in manual.

NOTE Compressor Discharge and Suction Pressure should be monitored closely to prevent High Discharge Pressure Cutout (greater than or equal to 270 psig) or Low Suction Pressure Cutout (less than or equal to 52.7 psig).

3.3 Raise Slide Valve position by increments of ~ 10 %

until Chill Water Temperature is ~ 46º F.

3.4 IF auto operation desired, THEN depress Slide Valve AUTO key.

3.5 Verify Power source Selection hand switch on RIS 2K1564 panel selected to the operating chiller (2VCH-1A or 2VCH-1B).

Cue: When contacted as the WWM, then report that Electrical will begin troubleshooting A Main Chiller.

Termination Criteria: When B Main Chiller is in service or at lead examiner's discretion.

Revision 1 Page 18 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 2 Event No.: 6 Event

Description:

Turbine Control Valve fails closed.

Time Position Applicant's Actions or Behavior Cued by ANY Report #4 MTG CV is failed Closed.

lead examiner SRO Enter and direct actions of AOP 2203.024, Loss of Turbine Load.

SRO 1. Open Placekeeping page.

2. Notify Control Board Operators to monitor floating steps.
3. Check Generator Protection Circuit Energized annunciator (2K02-A4) NOT in alarm.

Examiner Note: Generator Protection Circuit Energized alarm will not be in alarm.

ATC *4. Reduce Reactor power to match TAVE within 2°F of TREF using 2104.003 Exhibit 3, normal boration.

ATC Transition to OP-2104.003 Chemical Addition, Exhibit 3, normal boration Procedure Caution:

The following section has been determined to have a Reactivity Addition Potential (RAP) and this activity is classified as a Risk Level R3.

ATC 1.0 IF a Reactivity Management Brief has NOT been conducted, THEN perform a Reactivity Management Brief per COPD-030 with an SRO.

Examiner Note: This step is N/A due to being in transient standards.

ATC 2.0 IF this is the first Boration of the shift, THEN verify BAM Flow totalizer (2FQI-4926) reset.

3.0 IF desired, THEN record initial controller data:

2FIC-4926 Setpoint: ___________ Demand: _____________

4.0 Verify Boric Acid Makeup Flow controller (2FIC-4926) set as follows:

Setpoint set to desired flow rate.

IF in MANUAL, THEN demand set to desired value.

5.0 Verify desired BAM pump (2P-39A OR 2P-39B) selected for automatic operation using BAM pump Select switch (2HS-4911-2).

6.0 Place Mode Select switch (2HS-4928) to BORATE.

7.0 Verify Charging Pump Suction From Boric Acid (2CV-4930) opens (2HS-4930).

Revision 1 Page 19 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 2 Event No.: 6 Event

Description:

Turbine Control Valve fails closed.

ATC 8.0 Verify selected BAM pump running:

2P-39A (2HS-4919-2) 2P-39B (2HS-4910-2)

  • 9.0 Verify BAM Tank Recirc open for running pumps:

2T-6A recirc (2HS-4903-2) 2T-6B recirc (2HS-4915-2)

ATC *10.0 IF additional boric acid flow required, THEN manually start additional BAM pump:

2P-39A (2HS-4919-2) 2P-39B (2HS-4910-2)

Examiner Note: An additional Boric Acid Makeup pump should not be required.

ATC 11.0 Operate Boric Acid Makeup Flow Batch controller (2FQIS-4926) as follows:

11.1 Depress AND hold red pushbutton.

11.2 Verify Boric Acid Makeup Flow Batch controller (2FQIS-4926) set for desired quantity.

11.3 Release Red pushbutton.

12.0 Verify Boric Acid Makeup Flow controller (2FIC-4926) indicates desired flow rate.

13.0 Monitor the following parameters:

RCS TAVE Axial Shape Index Reactor power SRO Continue with OP-2203.024 Loss of Turbine Load.

ANY *5. Check RCS pressure 2025 to 2275 psia.

Cue: If asked, report that the MTG #4 CV indicates closed by local verification and If ask, report that the wires for the connector to the servo for # 4 CV are broken off and hanging to the side.

ANY *6. Verify SDBCS maintaining SG pressure at setpoint.

ANY 7. IF Main Turbine has NOT tripped, THEN perform the following:

Re-establish Turbine control on Load Limit Pot.

Refer to TRM 3.3.4, Turbine Overspeed Protection.

Examiner note: Turbine control will be on the load limit Pot.

Revision 1 Page 20 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 2 Event No.: 6 Event

Description:

Turbine Control Valve fails closed.

ANY 8. IF desired to fail a Turbine Control Valve closed, THEN perform the following:

A. IF necessary to maintain valve closed, THEN depress AND maintain depressed the selected Control Valve Test Switch on 2C01.

B. Refer to 2106.009, Turbine Generator Operations.

Cue: If requested as the WWM, then report that I&C will come to the Control Room to assist in failing #4 Main Turbine Generator Control valve closed.

Cue: If requested, after 5 minutes have the communicator enter the simulator control room and perform as requested by the crew.

Cue: If requested as I&C after ~ 5 min. come to the control room and respond as requested.

Cue: If requested as the Shift Manager to authorize the T-Mod to lift leads for the control valve give authorization to perform the T-Mod.

ANY 9. IF ADVs are open, THEN maintain Hotwell level 30% to 90% by performing one of the following:

Examiner Note: Atmospheric Dump valves will not be open and step is N/A ANY *10. Check RCS TC 542°F to 554.7°F using CPC PID 5, 6, 160, or 161. (Not met, perform contingency)

SRO *10. Refer to TS 3.2.6, Reactor Coolant Cold Leg Temperature.

Examiner note: The SRO must enter TS 3.2.6 or if boration has lowered temperature below the limit the SRO must log the TS 3.2.6 as been entered and exited.

Examiner note: The following steps may or may not be completed based on examiner discretion of when the required reactivity manipulation is complete.

ANY *11. Check ASI within limits as specified in Core Operating Limits Report (COLR).

ANY *12. Check CEA positions as follows:

A. ALL Regulating Group 6 CEAs above 112.5 inches.

B. ALL Regulating Group 1 through 5 CEAs fully withdrawn.

C. ALL Group P CEAs above 135 inches.

ANY *13. Check Reactor NOT tripped.

Procedure Note:

PZR level shall not exceed 82% in modes 1, 2 or 3 [less than 67% with instrument uncertainty - (910 ft3) per LI-0099 /2CAN100101]

ANY *15. Check PZR level within 5% of setpoint.

SRO 16. IF Main Turbine tripped, THEN perform the following:

Examiner Note: This step is N/A.

Revision 1 Page 21 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 2 Event No.: 6 Event

Description:

Turbine Control Valve fails closed.

ANY 17. Check Condenser pressure less than 5.3 inches Hg Abs.

Examiner Note: This step is N/A.

Termination criteria: When the require reactivity manipulation is complete and TS 3.2.6 has been entered or at lead examiners discretion.

Revision 1 Page 22 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 7, & 8 Event

Description:

Inadvertent Red MSIS causing a reactor trip. And Loss of Coolant accident.

Time Position Applicant's Actions or Behavior Cued by ANY The crew will recognize the reactor has tripped and commence SPTAs.

lead examiner SRO Enter OP-2202.001, Standard Post Trip Actions EOP.

Examiner Note: After the crew determines that there is a Loss of Coolant Accident occurring they may actuate Safety Injection Actuation Signal (SIAS) and Containment Cooling Actuation Signal (CCAS).

1. Notify Control Board Operators to perform the following:

A. Monitor safety functions using Exhibit 7, CBO Reactor Trip SRO Checklist.

B. Perform post trip contingencies as required.

SRO 2. Open Safety Function Tracking page.

ATC 3. Check Reactivity Control established as follows:

Reactivity A. Reactor power lowering.

control Safety B. Check startup rate is negative.

Function C. ALL CEAs fully inserted by observing ANY of the following:

BOP 4. Check Maintenance of Vital Auxiliaries satisfied:

A. Check Main Turbine tripped by BOTH of the following:

Vital Auxiliaries ALL Main Stop Valves closed.

Safety Generator megawatts indicate zero.

Function BOP B. Generator Output breakers open.

Revision 1 Page 23 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 7, & 8 Event

Description:

Inadvertent Red MSIS causing a reactor trip. And Loss of Coolant accident.

Time Position Applicant's Actions or Behavior BOP C. Perform EITHER of the following as required:

1) Check the following valves closed:

MSR 2E-12A Steam Supply From SG A (2CV-0400)

MSR 2E-12B Steam Supply From SG B (2CV-0460)

2) No flow indicated on the following MSR second stage flow instruments:

Vital 2FI-0402 Auxiliaries Safety 2FI-0462 Function BOP D. At least ONE 6900v AC bus energized.

E. At least ONE 4160v Non-vital AC bus energized.

F. BOTH 4160v Vital AC buses energized.

G. BOTH DGs secured.

BOP H. At least ONE 125v Vital DC bus energized:

2D01 - SPDS point E2D01 2D02 - SPDS point E2D02 ATC 5. Check RCS Inventory Control established as follows:

RCS A. PZR level:

Inventory Control 10 to 80%.

Safety Trending to setpoint. (May not be met due to LOCA, Function perform contingency)

B. RCS MTS 30°F or greater.

SRO Perform Step 5 Contingency Actions.

RCS A. Perform as necessary:

Inventory Control 1) IF SIAS actuated on PPS inserts, THEN GO TO Step 6.

Safety Function 2) Verify PZR Level Control system restoring level to setpoint.

Revision 1 Page 24 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 7, & 8 Event

Description:

Inadvertent Red MSIS causing a reactor trip. And Loss of Coolant accident.

Time Position Applicant's Actions or Behavior BOP 6. Check RCS Pressure Control:

  • 1800 to 2250 psia.
  • Trending to setpoint. (Not met due to LOCA Event, perform contingency)
  • Normal PZR Spray and heaters controlling pressure.
  • Valid CNTMT Spray NOT in progress.

Examiner Note a CNTMT spray will be in progress but it is not valid and the crew should leave RCPs running.

SRO Perform Step 6 Contingency Actions.

6. Perform as necessary:

A. IF RCS pressure lowers to less than 1400 psia, RCS THEN trip ONE RCP in EACH loop.

Pressure D. IF RCP 2P32A or 2P32B stopped, Control THEN verify associated PZR Spray valve in MANUAL and Safety function, closed:

RCP A Spray Valve (2CV-4651)

RCP B Spray Valve (2CV-4652)

F. IF RCS pressure lowers to 1650 psia or less, THEN perform the following:

1) Verify SIAS actuated on PPS inserts.
2) GO TO Step 7.

G. Verify PZR Pressure Control system restoring pressure to setpoint.

ATC 7. Check Core Heat Removal by forced circulation:

A. At least ONE RCP running.

B. CCW flow aligned to RCPs.

Core Heat Removal C. Loop delta T less than 10°F.

Safety Function. D. RCS MTS 30°F or greater.

E. Check SW aligned to CCW. (Not Met, Perform Contingency)

F. IF SIAS or MSIS actuated, THEN maintain SW header pressure greater than 85 psig.

SRO Perform Step 7 Contingency Action.

Core Heat Removal Safety E. IF CCW available, Function. THEN restore SW to CCW, refer to Exhibit 5, CCW/ACW/SW Alignment.

Revision 1 Page 25 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 7, & 8 Event

Description:

Inadvertent Red MSIS causing a reactor trip. And Loss of Coolant accident.

Time Position Applicant's Actions or Behavior BOP/ATC 8. Check RCS Heat Removal:

A. Check SG available by BOTH of the following:

At least ONE SG level 10 to 90%.

FW maintaining SG level (Not met, perform contingency)

ANY Perform Step 8.A Contingency Actions when applicable.

A. Perform the following:

1) IF SG level lowering, THEN verify EFAS actuated.

BOP/ATC B. Check MFW in RTO (Not Met, Perform contingency)

RCS Heat Removal Safety ANY Perform Step 8.B Contingency Actions.

Function B. Verify EITHER of the following:

BOTH MFW pumps tripped. (Both MFW pumps will be tripped due to CNTMT Spray)

SG levels controlling at setpoint ATC/BOP C. Check Feedwater line intact by the following:

SG level stable or rising.

NO unexplained step changes or erratic FW flow.

NO unexplained step changes or erratic Condensate flow.

Examiner Note: The crew will not have any indication for the feedline due to CSAS tripping all the feedwater pumps.

ATC/BOP D. Check RCS TC 540°F to 555°F (Not Met, perform contingencies)

Revision 1 Page 26 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 7, & 8 Event

Description:

Inadvertent Red MSIS causing a reactor trip. And Loss of Coolant accident.

Time Position Applicant's Actions or Behavior ATC/BOP Perform Step 8.D Contingency Actions.

D. Perform as necessary:

___ 1) IF TC greater than 555º F, THEN perform the following:

a) Verify level being restored to at least one SG.

b) Verify SDBCS restoring TC 540°F to 555°F using 2105.008 Exhibit 3, SDBCS Emergency Operation.

c) IF SDBCS NOT restoring TC, THEN check MSSVs operating to control SG pressure RCS Heat 1050 psia to 1100 psia.

Removal Safety Function ATC/BOP E. Check SG pressure 950 to 1050 psia. (Not Met, perform contingencies)

ATC/BOP Perform Step 8.E Contingency Actions.

E. Perform as necessary:

2) Verify SDBCS restoring SG pressure 950 psia to 1050 psia using 2105.008 Exhibit 3, SDBCS Emergency Operation.
4) IF SG pressure greater than 1050 psia, THEN check MSSVs operating to control SG pressure 1050 psia to1100 psia.

BOP Implement OP-2105.008, SDBCS Emergency Operations.

BOP 1.0 IF BOTH MSIVs closed, Steam THEN GO TO step 5.0.

Dump Exhibit 3 Examiner Note: MSIVs are closed.

Revision 1 Page 27 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 7, & 8 Event

Description:

Inadvertent Red MSIS causing a reactor trip. And Loss of Coolant accident.

Time Position Applicant's Actions or Behavior BOP 5.0 Perform the following to determine availability of UPSTREAM SDBCS valves:

5.1 IF the following conditions satisfied:

Instrument air available EMERGENCY OFF (2K02-A14) annunciator clear Power available to selected controllers/valves, THEN Upstream ADVs are available.

5.2 IF the following conditions satisfied:

EMERGENCY OFF (2K02-A14) clear or Upstream ADV locally failed open Power available, THEN ADV Upstream Isolation valve(s) are available.

Examiner Note: Upstream ADVs are available.

Revision 1 Page 28 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 7, & 8 Event

Description:

Inadvertent Red MSIS causing a reactor trip. And Loss of Coolant accident.

Time Position Applicant's Actions or Behavior BOP 6.0 IF operation of Upstream Atmospheric Dump valve from the Control Room desired, THEN perform the following:

6.1 Verify selected HIC in MANUAL with ZERO output demand:

Hdr #1 UPSTM ADV 2CV-1001 (2HIC-1001)

Hdr #2 UPSTM ADV 2CV-1051 (2HIC-1051) 6.2 Place selected valve(s) permissive handswitch in MANUAL:

2CV-1001 Permissive (2HS-1001) 2CV-1051 Permissive (2HS-1051)

Steam 6.3 IF MSIS actuated, Dump THEN override MSIS CLOSE actuation for selected Exhibit 3 MOV isolation:

ADV Upstream Isolation valve (2CV-1002)

ADV Upstream Isolation valve (2CV-1052)

  • 6.4 Throttle open selected MOV as desired:

ADV Upstream Isolation valve (2CV-1002)

ADV Upstream Isolation valve (2CV-1052)

  • 6.5 Place selected HIC to desired demand:

Hdr #1 UPSTM ADV 2CV-1001 (2HIC-1001)

Hdr #2 UPSTM ADV 2CV-1051 (2HIC-1051)

Implement remaining steps from OP-2202.001, Standard Post Trip Actions SRO Steps.

ATC/BOP F. IF MSIVs open, RCS Heat AND desired, THEN place SDBCS Master Controller in Removal Auto/Local with setpoint of 960 psia using 2105.008 Exhibit 3, Safety Function SDBCS Emergency Operation.

Examiner Note: MSIVs are not open step is N/A.

Revision 1 Page 29 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 7, & 8 Event

Description:

Inadvertent Red MSIS causing a reactor trip. And Loss of Coolant accident.

Time Position Applicant's Actions or Behavior ANY 9. Check CNTMT parameters:

A. Temperature and Pressure: (May not be met due to LOCA Event. Perform contingency)

Temperature less than 140°F.

Pressure less than 16 psia.

ANY Perform Step 9.A Contingency Actions.

A. Perform the following:

1) IF CNTMT pressure less than 18.3 psia, THEN verify ALL available CNTMT Cooling fans running with cooling water aligned.

Containment Safety Function ANY B. Check CNTMT Spray pumps secured.

ANY C. NO CNTMT radiation alarms or unexplained rise in activity:

1) CAMS alarms:
2) RCS leakage alarms:
3) Check the following radiation monitors trend stable:
  • CNTMT Area (Not Met)
  • CAMS
  • Process Liquid ANY D. NO secondary system radiation alarms or unexplained rise in activity:
1) "SEC SYS RADIATION HI" annunciator (2K11-A10) clear.

Containment Safety Function 2) Secondary Systems Radiation monitors trend stable:

  • Condenser Off Gas Revision 1 Page 30 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 7, & 8 Event

Description:

Inadvertent Red MSIS causing a reactor trip. And Loss of Coolant accident.

Time Position Applicant's Actions or Behavior SRO 10. Notify STA to report to control room.

11. Direct NLOs to perform 2202.010 Attachment 47, Field Operator Post Trip Actions.
12. Verify Reactor trip announced on Plant page.
13. Notify SM to refer to Technical Specifications and 1903.010, Emergency Action Level Classification.

Cue: If contacted as the STA to report to the control room, acknowledge the request.

Cue: If contacted as a NLO to perform Attachment 47 Field Operator Post Trip Actions, acknowledge request.

SRO 14. Direct control board operators to acknowledge ALL annunciators and announce ALL critical alarms.

SRO 15. Check ALL safety function acceptance criteria satisfied. (All safety functions are not satisfied, perform contingency)

SRO Perform Step 15 Contingency Actions.

15. IF ANY safety function acceptance criteria NOT satisfied, THEN perform the following:

A. Notify control room staff of safety functions NOT satisfied.

B. GO TO Exhibit 8, Diagnostic Actions.

SRO Diagnose OP-2202.003, Loss of Coolant Accident EOP.

SRO Enter OP-2202.003, Loss of Coolant Accident EOP.

Revision 1 Page 31 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 7, & 8 Event

Description:

Inadvertent Red MSIS causing a reactor trip. And Loss of Coolant accident.

Time Position Applicant's Actions or Behavior SRO *1. Confirm diagnosis of LOCA as follows:

A. Check SFSC acceptance criteria satisfied every 15 minutes.

B. IF CCW in service to provide SG Sample Cooler cooling, THEN perform the following:

1) Verify SG Sample valves open.

2CV-5852-2 2CV-5859-2 2CV-5850 2CV-5858

2) Notify Chemistry to sample SGs for activity.

C. IF SGs indicate primary to secondary leakage within TS limits, THEN continue with this procedure using SG with lowest leak rate for cooldown.

SRO *2. Notify SM to refer to Technical Specifications and 1903.010, Emergency Action Level Classification.

3. Open Placekeeping page.
4. Record present time:

Time ANY 5. Verify SIAS and CCAS actuated on PPS inserts.

ANY 6. Notify Control Board Operators to perform the following:

A. Monitor floating steps.

B. Verify actuated ESFAS components using 2202.010, Exhibit 9, ESFAS Actuation.

BOP Implement OP-2202.010, Exhibit 9 ESFAS Actuation.

See events 9 and 10.

ANY *7. Verify the following for any operating RCP:

A. CSAS NOT actuated.

B. Proper seal staging.

ANY 8. Check CCW flow aligned to RCPs.

ANY 9. Check RCS pressure greater than 1400 psia. (Not met, but contingencies are already done)

ANY 10. Restore ESF/Non-ESF systems post-SIAS using 2202.010 Attachment 51, Post ESFAS Actuation System Restoration.

BOP Perform OP 2202.010, Standard Attachments, Attachment 51 and Exhibit 5.

Revision 1 Page 32 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 7, & 8 Event

Description:

Inadvertent Red MSIS causing a reactor trip. And Loss of Coolant accident.

Time Position Applicant's Actions or Behavior Attach. 51 BOP 1. Verify at least ONE SW pump running on EACH loop.

Procedure Caution:

Operation of loaded DG without Service Water for greater than three minutes may cause engine damage.

BOP 2. IF ANY EDG in operation, THEN perform the following:

A. Check running EDG SW Outlet valve open:

2DG-1 SW Outlet (2CV-1503-1) 2DG-2 SW Outlet (2CV-1504-2)

B. IF running EDG Service Water valve did NOT open automatically, THEN open valve with Control Room handswitch.

Attach. 51 C. IF SW Outlet valve can NOT be opened from Control Room, THEN locally perform the following for the affected DG:

Examiner Note: Both EDGs will be running and the SW outlet valves will be open.

BOP 3. Verify SW pump suction aligned to Lake.

BOP 4. IF SW pump suction can NOT be aligned to Lake, THEN perform the following:

Examiner Note: This step is N/A BOP 5. IF NEITHER 2A1 OR 2A2 energized from offsite power, THEN perform the following:

Examiner Note: This step is N/A BOP 6. IF BOTH 4160v Vital buses 2A3 AND 2A4 energized from offsite power, THEN start SW pumps as needed to maintain SW header pressure.

BOP 7. IF NO 4160V busses energized, THEN return to procedure in effect.

Attach. 51 Examiner Note: This step is N/A BOP *8. IF only ONE 4160v Vital bus energized from offsite power AND additional SW pump start desired to maintain SW header pressure, THEN perform the following:

Examiner Note: This step is N/A BOP 9. IF EITHER 4160v Vital Bus supplied by EDG, THEN verify only one SW pump running on train supplied by EDG.

Examiner Note: This step is N/A Revision 1 Page 33 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 7, & 8 Event

Description:

Inadvertent Red MSIS causing a reactor trip. And Loss of Coolant accident.

Time Position Applicant's Actions or Behavior BOP *10. Maintain Service Water header pressure greater than 85 psig while performing the following using 2202.010 Exhibit 5, CCW/ACW/SW Alignment:

A. IF Loop 2 CCW available, THEN restore Service Water to Component Cooling Water.

B. Restore Service Water to Auxiliary Cooling Water.

BOP 11. IF SW header pressure can NOT be maintained greater than 85 psig, THEN perform the following:

Examiner Note: This step is N/A BOP Perform OP 2202.010, Standard Attachments, Exhibit 5.

BOP 1. IF SW suction NOT aligned to lake, THEN RETURN TO procedure in effect.

BOP 2. IF SW NOT aligned to CCW AND CCW available, THEN perform the following:

BOP A. IF RCP seal temperatures less than 180°F, Exhibit 5 THEN restore SW to CCW by performing the following:

1). Override and open at least ONE SW to CCW/ACW Return valve:

Supplying ACW flow and CCW cooling from a single SW pump may result in low SW header pressure.

BOP 2). Override and throttle open at least ONE SW to CCW /Main Chillers Supply valve:

Exhibit 5 BOP 3. IF CCW flow NOT aligned to RCPs AND offsite power available, THEN perform the following:

Examiner Note: CCW flow should not be re-aligned to RCPs due to the RCS to CCW leak.

Revision 1 Page 34 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 7, & 8 Event

Description:

Inadvertent Red MSIS causing a reactor trip. And Loss of Coolant accident.

Time Position Applicant's Actions or Behavior BOP 4. IF SW NOT aligned to ACW, THEN perform the following:

A. Verify at least ONE SW to CCW/ACW Return valve open:

2CV-1543-1 2CV-1542-2 Exhibit 5 B. Override and throttle open ACW Supply valves:

2CV-1425-1 2CV-1427-2 C. Maintain SW header pressure greater than 85 psig.

SRO Perform OP 2202.003, Loss of Coolant Accident.

ANY 11. IF Circ Water flow lost to the Main Condenser, THEN perform the following:

BOP *12. Verify Safety Injection flow to RCS as follows:

A. Check total HPSI flow acceptable using 2202.010 Exhibit 2, HPSI Flow Curve.

B. Check total LPSI flow acceptable using 2202.010 Exhibit 3, LPSI Flow Curve.

ANY 13. Check SG levels greater than 22.2%.

BOP 14. Align feedwater as follows:

A. Verify EFW pump 2P7B capable of feeding intact SG using 2202.010 Attachment 46, Establishing EFW Flow.

BOP Perform OP 2202.010, Standard Attachments, Attachment 46, Establishing EFW flow.

BOP

  • 1. IF EFW pump running OR will be started AND pump suction aligned to Q CST, THEN monitor level to ensure Tech Spec requirements satisfied.

Att. 46

2. IF EFAS or MSIS is actuated THEN GO TO step 5.

Examiner Note: MSIS and EFAS are actuated go to step 5.

Revision 1 Page 35 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 7, & 8 Event

Description:

Inadvertent Red MSIS causing a reactor trip. And Loss of Coolant accident.

Time Position Applicant's Actions or Behavior BOP 5. IF desired to manually control EFW using 2P7B AND EFAS or MSIS actuated, THEN perform the following:

A. Verify 2P7B running.

B. IF desired to feed SG A, THEN perform the following:

1) Override 2P7B Discharge to SG A (2CV-1038-2) by placing handswitch to MSIS override AND then to EFAS override.
2) Override 2P7B Feed to SG A (2CV-1025-1) by placing 2HS-1025B-1 to MSIS override AND then to EFAS override.
3) Throttle 2CV-1025-1 to control SG A level.

Att. 46 C. IF desired to feed SG B, THEN perform the following:

1) Override 2P7B Discharge to SG B (2CV-1036-2) by placing handswitch to MSIS override AND then to EFAS override.
2) Override 2P7B Feed to SG B (2CV-1075-1) by placing 2HS-1075B-1 to MSIS override AND then to EFAS override.
3) Throttle 2CV-1075-1 to control SG B level.

D. IF 2P7A is running AND will not be used to feed the SGs, THEN secure 2P7A by overriding and closing Steam to EFW Pump Turbine Valve (2CV-0340-2).

SRO Perform OP 2202.003, Loss of Coolant Accident.

BOP B. IF running, THEN stop EFW pump 2P7A by overriding and closing (2CV-0340-2).

C. Verify running MFW pump secured.

D. Verify ALL MFW Block valves closed.

Revision 1 Page 36 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 7, & 8 Event

Description:

Inadvertent Red MSIS causing a reactor trip. And Loss of Coolant accident.

Time Position Applicant's Actions or Behavior ANY 15. Isolate LOCA as follows:

A. Verify letdown isolated.

B. Verify RCS Sample Isolation valves closed:

  • CCW Surge Tanks level stable.

D. Verify non-actuated valve positions using 2202.010 Attachment 17, LOCA Isolation.

Examiner Note: The SRO may elect to prioritize this attachment to be performed later in the event.

ANY 16. Check LOCA limited to CNTMT:

  • CNTMT Sump level rising.
  • CNTMT temperature, dewpoint, and pressure greater than pre-LOCA values.
  • Aux Building area radiation levels stable.
  • Aux Building Sump level less than 53%.
  • Waste Tanks 2T20A and 2T20B levels stable.

ANY 17. Check CNTMT isolation parameters:

A. CNTMT pressure trend has NOT exceeded 18.3 psia.

B. "CNTMT RADIATION HI" annunciator (2K10-A6) clear.

ANY 18. Check CNTMT pressure trend has NOT exceeded 23.3 psia.

ANY *19. IF CNTMT Spray operating, THEN terminate CNTMT Spray as follows:

Examiner Note: CNTMT Spray should not be operating.

BOP 20. Verify ALL available miscellaneous CNTMT Building ventilation operating using 2202.010 Exhibit 13, Miscellaneous Containment Building Ventilation.

BOP Perform OP 2202.010, Standard Attachments, Exhibit 13.

Revision 1 Page 37 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 7, & 8 Event

Description:

Inadvertent Red MSIS causing a reactor trip. And Loss of Coolant accident.

Time Position Applicant's Actions or Behavior BOP 1.0 Verify ALL available CNTMT Building Recirculation Fans in operation:

  • 2VSF-31D 2.0 Verify ALL available Reactor Cavity Cooling Fans in operation:

Exhibit 13

  • 2VSF-34B 3.0 Verify a maximum of three CEDM Shroud Cooling Units in operation:
  • 2VSF-35D SRO Continue to perform OP 2202.003, Loss of Coolant Accident.

ANY 21. Check ALL AC and Vital DC buses energized.

ANY 22. Check IA pressure greater than 65 psig.

ANY 23. Check for isolated LOCA:

  • RCS pressure controlled.
  • RCS leakage less than available Charging pump capacity.

Examiner Note: LOCA is not considered isolated.

SRO 1. Perform controlled cooldown to 275°F TC as follows:

A. Check RCS TC greater than 275°F.

ATC B. Reset Low PZR Pressure and Low SG Pressure setpoints during cooldown and depressurization.

C. Verify maximum of ONE RCP running in EACH loop.

D. IF RCP 2P32A or 2P32B stopped, THEN verify associated PZR Spray valve in MANUAL and closed.

Revision 1 Page 38 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 7, & 8 Event

Description:

Inadvertent Red MSIS causing a reactor trip. And Loss of Coolant accident.

Time Position Applicant's Actions or Behavior ATC E. Monitor cooldown rate as follows:

CRITICAL TASK

  • Record RCS TC and PZR temperature using 2202.010 Attachment 8, RCS Cooldown Table.

The crew

  • Plot RCS pressure versus RCS TC using 2202.010 must commence Attachment 1, a cooldown P-T Limits every 15 minutes.

within 30 minutes of entry into F. Initiate RCS cooldown using the LOCA SDBCS bypass valves or ADVs.

EOP.

BOP G. Control S/G levels with EITHER of the following:

  • EFW using 2202.010 Attachment 46, Establishing EFW Flow
  • AFW using 2202.010 Attachment 52, Establishing AFW Flow H. Secure running MFW pump.

I. Close ALL MFW Block valves.

J. Verify maximum of one condensate pump in service.

K. Maintain condensate header pressure less than 700 psig using condensate pump recircs and MFW pump recircs.

BOP *2. Maintain SG levels 45% to 90%

[55% to 90%] throughout cooldown using the following as desired:

2202.010 Attachment 46, Establishing EFW Flow.

2202.010 Attachment 52, Establishing AFW Flow.

ANY *3. Check EFW pump CST level as follows:

  • IF aligned to Q CST, THEN check level greater than 17.5 feet.
  • IF aligned to A or B CST, THEN check level greater than 82%

ANY 4. IF Condensate pump start desired for performance of cooldown, THEN perform the following:

Examiner Note: Condensate pump should already be running and step should be N/A.

Revision 1 Page 39 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 7, & 8 Event

Description:

Inadvertent Red MSIS causing a reactor trip. And Loss of Coolant accident.

Time Position Applicant's Actions or Behavior ATC 5. Restore PZR level as follows:

A. Check PZR level greater than or recovering to 29% [50%].

B. Maintain PZR level 29% to 80%

[50% to 70%].

Examiner Note: May not be met, Perform Contingencies if required.

SRO Perform Step 5 contingencies if required.

A. Perform the following:

1) Perform the following as necessary to restore PZR level greater than 29% [50%]:

Operate Charging and HPSI pumps Control RCS pressure using Attachment 48, RCS Pressure Control

2) GO TO Step 6.

SRO 6. Check ALL available Hydrogen Analyzers in service using 2104.044, Containment Hydrogen Control Operations.

Examiner Note: Not be met, Perform Contingencies as time allows.

BOP Perform Step 6 contingencies as time allows.

6. Verify all available Hydrogen Analyzers in service within 70 minutes from start of event.

Record time from Entry Section step 4:

Time ______________

SRO *7. IF ALL RCPs secured, THEN perform the following:

Examiner Note: RCPs should be running.

SRO 8. IF ANY RCP running, THEN GO TO Step 12.

ANY *12. Check RCS void-free during cooldown as follows:

A. PZR level stable while using PZR spray.

B. RVLMS LVL 01 indicates WET.

C. Upper head thermocouple temperature indicates subcooled conditions:

  • SPDS point CV2DOMEB Revision 1 Page 40 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 1 Event No.: 7, & 8 Event

Description:

Inadvertent Red MSIS causing a reactor trip. And Loss of Coolant accident.

Time Position Applicant's Actions or Behavior ANY *13. Maintain RCS P-T limits and RCP NPSH requirements, refer to 2202.010 Attachment 1, P-T Limits.

Critical Task: Establish RCS pressure control to maintain RCS subcooling. After the HPSI failures have been addressed and MTS restored to >30 degrees F then maintain pressure and temperature within the PT limits of <2000 F and >300F MTS throughout implementation of OP-2202.003, LOCA EOP.

Termination criteria: RCS cooldown commenced or at the discretion of the lead examiner.

Revision 1 Page 41 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 2 Event No.: 9 Event

Description:

2P-89B Motor overload. 2CV-5035-1 High pressure safety injection and 2CV-5037-1 Low pressure safety injection valves fail to open. Green train Containment Cooling fails to actuate.

Time Position Applicant's Actions or Behavior BOP Implement OP-2202.010, Exhibit 9 ESFAS Actuation SIAS failures.

BOP *1.0 IF any abnormalities noted for affected ESFAS actuation, THEN notify CRS.

2.0 IF SIAS, THEN verify the following:

Red Train RWT Outlet (2CV-5630-1) open.

Red Train HPSI Pump in service with proper discharge pressure and flow.

Red Train HPSI Injection MOVs open. (BOP should open 2CV-5035-1)

Red Train Service Water Pump in service with proper discharge pressure.

Red Train LPSI Pump (2P60A) in service with proper discharge pressure and flow.

Red Train LPSI Injection MOVs open. (BOP should open 2CV-5037-1)

Green Train RWT Outlet (2CV-5631-2) open.

Green Train HPSI Pump in service with proper discharge pressure and flow.

Green Train HPSI Injection MOVs open.

Green Train Service Water Pump in service with proper discharge pressure.

Green Train LPSI Pump (2P60B) in service with proper discharge pressure and flow.

Green Train LPSI Injection MOVs open.

Available Charging Pumps in service with proper discharge pressure and Exhibit 9 flow.

ESFAS Service Water Outlet Valves open for #1 and #2 EDGs.

actuation. 3.0 IF CCAS, THEN verify the following:

Red Train CNTMT Coolers in service.

Service Water aligned to Red Train CNTMT Coolers.

Red Train Bypass Dampers open.

Green Train CNTMT Coolers in service. (BOP should start 2VSF-1C)

Service Water aligned to Green Train CNTMT Coolers. (BOP should service water to the green train CNTMT coolers)

Green Train Bypass Dampers open. (BOP should open the bypass dampers)

Critical Task: Perform one or more of the following to maintain OR restore Margin to Saturation (MTS) > 30 degrees F.

Start a Green train HPSI pump 2P-89C Throttle open red train HPSI valve 2CV-5035-1.

If MTS lowers < 30 degrees F, it must be restored >30 degrees F within 10 min.

BOP Implement OP-2203.012E, 2K-05 ACA.

Revision 1 Page 42 of 43

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 2 Event No.: 9 Event

Description:

2P-89B Motor overload. 2CV-5035-1 High pressure safety injection and 2CV-5037-1 Low pressure safety injection valves fail to open. Green train Containment Cooling fails to actuate.

Time Position Applicant's Actions or Behavior Procedure Note:

The following are 2P-89B Motor data and Overcurrent relays settings:

Motor Full Load Current (FLC) per phase: 75.5 amps (Expected current at full load, not a trip setpoint)

Phase B Time Delay Overcurrent relay (TOC, 151) setpoint: 90 amps (Phase B is used to alarm an Overload condition.)

Phase A & C Time Delay Overcurrent relay (TOC, 151) setpoint: 100 amps (Actuation of these relays do not cause a bkr trip until IOC-B picks up.)

Instantaneous Overcurrent relay (IOC-B, 150) trip setpoint: 160 amps (Actuation of IOC-B combined with A or C TOC relays will trip the bkr.)

Instantaneous Overcurrent relay (IOC-A, 150) trip setpoint: 1000 amps (Actuation of this relay will trip the bkr instantaneously.)

BOP 2.1 Check current draw for each phase at 2A-406.

Cue: If requested as a NLO to check 2A-406 current draw, then after ~ 1min. report that amps indicate the following Phase A: 108 amps, Phase B: 103 amps, Phase C: 109 amps and all phases are rising. After 2 min. call back and report amps are Phase A: 152 amps, Phase B: 148 amps, Phase C: 155 amps and all phases are still rising.

BOP 2.2 IF current greater than or equal to 90 amps, THEN perform the following:

2.2.1 IF during SIAS, THEN verify ONE HPSI Pump running on Red train:

2P-89A (2HS-5078-1) 2P-89C (2HS-5080-1)

BOP 2.2.2 IF 2P-89C available, THEN perform the following using HPSI System Operation (2104.039):

A. Verify 2P-89C aligned to Green train (2HS-5080-2).

Examiner Note: The BOP should contact a NLO to align 2P-89C to green train.

Cue: If requested as a NLO to align 2P-89C to the green train then, ???

BOP 2.2.3 IF NOT required for SIAS OR current approaches 160 amps, THEN secure 2P-89B (2HS-5079-2).

Termination criteria: When 2CV-5035-1 is open and Green train CNTMT coolers aligned or at examiners discretion.

Revision 1 Page 43 of 43

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 36 of 303 2104.036 EMERGENCY DIESEL GENERATOR OPERATIONS CHANGE: 087 13.0 MANUAL SHUTDOWN OF 2DG1 NOTE If 2DG1 is run unloaded for greater than ten minutes OR multiple starts performed, the engine should be operated at full load for one hour prior to securing.

N/A 13.1 IF SIAS is actuated, THEN reset SIAS per Attachment 13 of Standard Attachments (2202.010).

N/A 13.2 IF 2A3 Supply breaker (2A-309) open AND necessary to supply 2A3 from offsite power, THEN perform the following:

13.2.1 Verify 2A1 available to supply 2A3.

NOTE Neutral Overvolt (2K127-3) alarm clears when ENGINE/GEN TROUBLE (2K08-J1) is cleared.

13.2.2 Verify Neutral Overvolt (2K127-3) alarm clear.

13.2.3 Place 2A-309 Synchronize switch (152-309/SS) to ON.

13.2.4 Adjust Generator voltage (Incoming) using Voltage Regulator switch (CS 3) as per BOTH of the following:

Generator voltage (Incoming) approximately 100 volts higher than System voltage (Running) by 2C-33 indication.

Generator voltage (Incoming) higher than System voltage (Running) by SPDS indication (NA if SPDS indication not available).

13.2.5 Adjust frequency to cause synchroscope to rotate slowly in FAST direction using Governor Control switch (CS 4).

CAUTION 2DG1 load will lower when 2A-309 is closed because the governor control circuit shifts to DROOP.

13.2.6 Perform the following to close 2A-309:

A. WHEN synchroscope approaches the 12 o'clock position, THEN close 2A-309 (152-309 CS).

B. Immediately raise 2DG1 load to approximately 1400 KW to prevent a reverse power trip using Governor Control switch (CS 4).

13.2.7 Adjust Generator KVARs between 600 KVARs IN and 1800 KVARs OUT using Voltage Regulator switch (CS 3).

(Preferred range is 0 to 100 OUT) 13.2.8 Place 2A-309 Synchronize switch (152-309/SS) in OFF.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 37 of 303 2104.036 EMERGENCY DIESEL GENERATOR OPERATIONS CHANGE: 087 13.3 Perform ONE of the following to unload 2DG1:

13.3.1 IF 2DG1 fully loaded for normal run, THEN unload as follows using governor Control switch (CS 4):

A. In approximately 700 KW increments with approximately 5 minute wait at each increment until loaded to approximately 1400 KW.

CAUTION EDG may trip due to anti-motoring if opening 2A-308 is delayed at 100 KW load.

CRITICAL STEP B. WHEN 5 minutes time has elapsed at 1400 KW, THEN perform the following:

1. Reduce load to approximately 100 KW.
2. Open 2DG1 Output breaker 2A-308 (152-308 CS).

13.3.2 IF 2DG1 post maintenance testing run in progress, THEN unload as follows using Governor Control Switch (CS 4):

A. Unload 2DG1 as directed by System Engineering.

CAUTION EDG may trip due to anti-motoring if opening 2A-308 is delayed at 100 KW load.

CRITICAL STEP B. WHEN 2DG1 load reduced to approximately 100 KW, THEN open 2DG1 Output breaker 2A-308 (152-308 CS).

13.4 Verify the following 2DG1 parameters:

Frequency approximately 60 Hz, using Governor Control switch (CS 4).

Voltage approximately 4160 volts, using Voltage Control switch (CS 3).

13.5 Perform the following administrative actions:

13.5.1 Verify Unit 1 has taken appropriate actions as identified in Attachment B of Control Room Emergency Air Conditioning and Ventilation (2104.007).

13.5.2 Verify entry into TS 3.8.1.1, 3.8.1.2, and 3.4.4 as applicable.

13.5.3 Declare Diesel Engine inoperable due to START handswitch in STOP (energizes Shutdown 5 relay for 60 seconds which blocks Engine auto start).

NOTE Expect annunciator 2DG1 NOT AVAIL (2K08-F1) when stopping 2DG1.

13.6 Secure 2DG1 by placing Engine Start switch (2HS-2809-1) in STOP.

13.7 WHEN 2DG1 NOT AVAIL (2K08-F1) alarm clear, THEN EDG may be declared OPERABLE.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 38 of 303 2104.036 EMERGENCY DIESEL GENERATOR OPERATIONS CHANGE: 087 13.8 Check the following pumps auto start:

Standby Lube Oil Circulating pump (2P-171A)

{4.3.2} Standby Coolant System Circulating pump (2P-167A)

CAUTION If DC control power to Engine Governor NOT available, the engine will start when air rolled unless overspeed trip mechanism is tripped with Emergency Stop pushbutton.

NOTE The air roll of the EDG may be N/Aed or delayed with the concurrence of System Engineering and the OPS Manager.

13.9 Perform the following to air roll 2DG1:

13.9.1 Verify engine shutdown greater than 15 minutes.

13.9.2 Perform the following for EDG inoperability:

A. Verify Unit 1 has taken appropriate actions as identified in Attachment B of Control Room Emergency Air Conditioning and Ventilation (2104.007).

B. Verify entry into TS 3.8.1.1, 3.8.1.2, and 3.4.4 as applicable.

C. Declare Diesel Engine inoperable due to Local Engine Control switch in LOCKOUT.

NOTE Expect annunciator 2DG1 NOT AVAIL (2K08-F1), ENGINE/EXCITER SHUTDOWN (2K08-C2), and ESF ELECT SYS INOP (2K07-J2) when placing 2HS-2815-1 to LOCKOUT.

13.9.3 Unlock and place local Engine Control switch (2HS-2815-1) to LOCKOUT.

13.9.4 Close Bearing Oil Booster Isol (2ED-1049A).

NOTE Expect annunciator START AIR TROUBLE (2K08-H1) when air rolling EDG.

13.9.5 Perform the following to manually operate EITHER Air Start Solenoid (2SV-2809-1 or 2SV-2810-1):

A. Slowly rotate Manual Operator stem clockwise until engine starts to rotate.

B. WHEN engine has rotated at least two revolutions, THEN rotate Manual Operator counter-clockwise.

13.9.6 Open Bearing Oil Booster Isol (2ED-1049A).

13.9.7 Place Engine Control switch (2HS-2815-1) to AUTO.

13.9.8 Remove key from Engine Control switch (2HS-2815-1).

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 39 of 303 2104.036 EMERGENCY DIESEL GENERATOR OPERATIONS CHANGE: 087 13.10 WHEN ALL of the following are complete:

Engine Control switch in AUTO.

Engine Control switch key removed.

2DG1 NOT AVAIL (2K08-F1) alarm clear.

All alarms concerning 2DG1 cleared OR any concern raised by alarms is resolved.

IF Engine Air roll will be performed, THEN verify Engine Air roll completed.

THEN 2DG1 may be declared OPERABLE.

13.11 IF 2VSF-8A/B Outside Air Intake damper (2HVD-72) was closed, THEN restore 2VSF-8A/B Outside Air Intake damper (2HVD-72).

13.12 WHEN 2DG1 has been shutdown for 30 minutes, THEN close 2DG1 SW Outlet valve 2CV-1503-1 (2HS-1503-1).

13.13 Complete EDG Start/Load/Run Information sheet (Form 2104.036A).

13.14 Inform Unit 1 to verify placard removed from MTG Voltage regulator.

Appendix D Scenario Outline Form ES-D-1 Facility: _ANO-2_________ Scenario No.: ___3 (New)______ Op-Test No.: _2015-1___

Examiners: ___________________________ Operators: ____________________________

Initial Conditions: ~2% power, 250 EFPD. B Channel Pressurizer Pressure and Level in service. 2P-89C and 2P-4B aligned to green power.

Turnover: Red Train Maintenance Week. EOOS indicates Minimal Risk. 2% power B Main Feedwater pump idling. Turbine warm up complete.

Evolution scheduled: Place the B Main Feedwater pump in service using OP-2106.007 Main Feedwater Pump and FWCS Operations starting with step 13.8. Then commence power escalation to 15% for turbine tie on using OP-2102.004 Power Operations section 8 beginning with step 8.2. Logs will be completed by the test team.

Event Malf. No. Event Event No. Type* Description 1 N (BOP) Place the B Main Feedwater pump in service.

N (SRO) OP-2106.007, Main Feedwater Pump and FWCS Operations.

2 R (ATC) Power escalation.

N (SRO) OP-2102.004, Power Operations.

3 XRCCHBPLVL I (ATC) B Pressurizer level control channel fails high.

I (SRO) OP-2203.028, Pressurizer System Malfunction AOP TS (SRO) 4 SW2P4C C (BOP) 2P-4C Service water pump trip.

C (SRO) OP-2203.022, Loss of Service Water AOP 5 ESFSIAS2I C (ATC) Inadvertent Green train safety injection.

K04-G08 C (BOP) OP-2203.018, Inadvertent SIAS AOP K04-H08 C (SRO)

TS (SRO) 6 RCP2P32APV A RCP High Vibrations.

RCP2P32AMV M (All) OP-2203.025 RCP Emergencies AOP.

OP-2202.001, Standard Post Trip Actions (SPTAs) EOP 7 LOSE161 Loss of Offsite power.

M (All)

LOSE500 OP-2202.007, Loss of Offsite Power EOP 8 C (BOP) #1 Emergency Diesel Generator low voltage.

C (SRO) OP-2202.001, Standard Post Trip Actions (SPTAs) EOP 9 A308 #1 Emergency Diesel Generator output breaker will trip open.

C (BOP)

EDGDG2LOIL #2 Emergency Diesel Generator will trip due to a loss of lube oil.

C (SRO)

OP-2202.008, Station Blackout EOP One vital bus restored.

End point

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Revision 0 Page 1 of 46

Appendix D Scenario Outline Form ES-D-1 Target Quantitative Attributes (Section D.5.d) Actual Attributes Malfunctions after EOP entry (1-2) 2 Abnormal Events (2-4) 3 Major Transients (1-2) 2 EOPs entered requiring substantive actions (1-2) 1 EOP contingencies requiring substantive actions (0-1) 0 Critical Tasks (2-3) 3 Critical Task Justification References Maintain RCS pressure within the RCS pressure must be CE EPGB Simulator CTs:

Pressure-Temperature limits of maintained in these limits to allow CT-05, Establish RCS Pressure 200°F and 30°F Margin to natural circulation of the RCS and Control (LOOP-02)

Saturation and less than 2500 prevent over pressurizing the EOP 2202.007 Loss of Offsite psia. RCS boundary. Power EOP.

EOP 2202.007 Loss of Offsite power EOP Tech Guide A RCP must be secured within The out-of-limits condition could 1015.050 Time Critical 10 min of the reactor trip. result in shaft seal damage, and Operation action program, then shaft seal failure could result Attachment C in increased RCS leakage out the CE EPGB Simulator CTs:

seal to the containment CT-23, Trip any RCP exceeding atmosphere, which would worsen operating limits.

the event severity. CR-ANO-2-2010-948, Critical task criteria Energize at least one vital AC bus Without any AC power available CE EPGB Simulator CTs:

with in 10 minutes of entering the for ESF pumps, the ability to CT-03, Energize at least one station blackout EOP. maintain the plant in a safe state vital AC bus.

is severely degraded since no EOP 2202.007 Loss of Offsite makeup water can be added to Power EOP.

the RCS for inventory control EOP 2202.008 Station Blackout purposes. EOP.

ANO-2 SAR table 8.3.7, Reg Guide 1.155 and DCP 92-2011.

Scenario #3 Objectives

1) Evaluate individual ability to place the first Main Feedwater pump in service.
2) Evaluate individual ability to perform a power escalation.
3) Evaluate individual response to a Pressurizer level control channel failing high.
4) Evaluate individual response to a loss of a service water pump.
5) Evaluate individual response to an Inadvertent Safety Injection Actuation Signal.
6) Evaluate individual and crews response to Reactor Coolant Pump High Vibrations.
7) Evaluate individual response to a low voltage on an Emergency Diesel Generator.
8) Evaluate individual response to a loss of both vital 4160 busses.
9) Evaluate crews ability to mitigate a Loss of Offsite power and Station blackout event.

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Appendix D Scenario Outline Form ES-D-1 SCENARIO #3 NARRATIVE Simulator session begins with the plant at ~2% power.

When the crew has completed their control room walk down and brief, the BOP will place the B Main Feedwater pump in service to allow power escalation. After the B Main Feedwater pump has been placed in service the crew will commence a power escalation by withdrawing control rods and diluting as designated by the reactivity plan.

When the required reactivity manipulation has been completed or when cued by the lead examiner, Channel B pressurizer level control channel will fail high. This will cause letdown to rise to maximum output. The SRO will enter the PZR System Malfunction AOP. The ATC will take manual control of letdown and lower flow. The ATC will shift level control channels from B to A and then restore letdown to automatic. The SRO will enter TS 3.3.3.5 for remote shutdown and TS 3.3.3.6 for post accident instrumentation. [Site OE: CR-ANO-2-2000-175, Pressurizer Channel 2 indication failed low.]

When letdown has been restored to automatic or cued by lead examiner, 2P-4C service water pump will trip. The ATC/BOP should report 2P-4C breaker trip alarm and announce that 2P-4C has tripped. The SRO will enter the OP-2203.022 Loss of Service Water AOP. The BOP will verify the B Service Water pump aligned to supply Loop 2 Service Water. He will then start 2P-4B Service Water pump to restore green train service water. [Site OE: CR-ANO-2-2003-178, 2P-4C Service Water pump trip.]

When 2P-4B is supplying Loop 2 service water, or cued by the lead examiner, a Green Train Safety Injection Actuation Signal (SIAS) will occur. The SRO will enter Inadvertent SIAS AOP OP-2203.028. The BOP will override and open the auxiliary cooling water valve and component cooling water valves. The ATC will secure all charging pumps. The SRO will enter Tech Specs for ECCS components 3.5.2 and for 3.7.3.1 for service water. [Site OE: CR-ANO-2-2013-005, Inadvertent SIAS, CIAS, and CCAS. Industry OE: ICES # 140474, failure of relay cause auto ESF start of AFW]

When the crew has restored Service water to ACW/CCW, secured charging, and entered the appropriate Tech Specs or at the lead examiners cue, A Reactor Coolant Pump (RCP) vibrations will increase requiring a reactor trip and the pump to be secured. The crew will trip the reactor and secure A RCP. After A RCP is secured a loss of Offsite Power (LOOP) will occur. The SRO will enter OP 2202.001, Standard Post Trip Actions (SPTAs). The crew will assess safety functions.

Due to the LOOP both Emergency Diesel Generators will start. #1 Emergency Diesel Generator will have low voltage and the BOP should recognize the low voltage condition and raise voltage allowing the output breaker to close and supply 2A-3 4160 volt vital bus. The ATC will have to align for Auxiliary spray due to the loss of RCPs and control RCS pressure which will be trending up due to steam generator pressure rising and loss of forced circulation. The crew will actuate Emergency Feedwater Actuation Signal (EFAS). [Industry OE: ICES-295297 Manual shutdown due to RCP vibrations, ICES- 160561 High RCP vibs, SEN-274 RCP seal failure due to high vibs.

SOER 99-01 Loss of grid}

The SRO will diagnose and enter OP-2202.007, Loss of Offsite Power EOP. Once LOOP has been entered #1 EDG output breaker will trip open due to an internal issue and #2 Emergency Diesel will trip due to a lube oil gasket rupture. The SRO should re-diagnose and enter Station Blackout. The BOP will restore power to either 2A-3 or 2A-4 Vital 4160 volt bus from the Alternate AC generator. [Industry OE: SOER 03-01 emergency power reliability.]

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Appendix D Scenario Outline Form ES-D-1 Simulator Instructions for Scenario 3 Reset simulator to MOL ~2 % power IC steady state.

T1, T2, T3, T4, T5, & T6 set to false.

T5 = GH4G4620 T6 = NE4R3402 T7 =

Event Malf. No. Value/ Event No. Ramp Description Time 1 Place the B Main Feedwater pump in service.

OP-2106.007, Main Feedwater Pump and FWCS Operations.

2 Power escalation.

OP-2102.004, Power Operations.

3 XRCCHBPLVL 100 / 15 B Pressurizer level control channel fails high.

Trigger 1 sec. OP-2203.028, Pressurizer System Malfunction AOP 4 SW2P4C active 2P-4C Service water pump trip.

Trigger 2 OP-2203.022, Loss of Service Water AOP 5 ESFSIAS2I Active Inadvertent Green train Safety injection.

K04-G08 on OP-2203.018, Inadvertent SIAS AOP K04-H08 on Trigger 3 6 RCP2P32APV 30/ 5 A RCP High Vibrations.

min. OP-2203.025 RCP Emergencies AOP.

RCP2P32AMV 26/ 5 OP-2202.001, Standard Post Trip Actions (SPTAs)

Trigger 4 min. EOP 7 LOSE161 active Loss of Offsite power.

LOSE500 active OP-2202.007, Loss of Offsite Power EOP Trigger 5 8 #1 Emergency Diesel Generator low voltage.

OP-2202.001, Standard Post Trip Actions (SPTAs)

EOP 9 A308 LCK_OP #1 Emergency Diesel Generator output breaker will trip Active / open.

EDGDG2LOIL delay 3 #2 Emergency Diesel Generator will trip due to a loss of Trigger 6 min. lube oil.

OP-2202.008, Station Blackout EOP Revision 0 Page 4 of 46

Appendix D Scenario Outline Form ES-D-1 Simulator Operator CUEs Place the B Main Feedwater pump in service.

Cue: If requested as the NLO, report that B Main Feedwater pump is running sat.

Power escalation.

Cue: If requested as the NLO, report that 2CV-0748 and 2CV-0740 are not jacked closed or pinned and the jacking sleeve is in the neutral position.

Cued by Trigger T1 B Pressurizer level control channel fails high.

lead examiner Cue: When contacted as the WWM/engineering, then report that a planner will begin planning work on the Reactor Reg and/or engineering will investigate Reactor Reg.

Cued by Trigger T2 2P-4C Service water pump trip.

Lead Examiner Cue: If asked report that the motor for C Service Water Pump is hot to touch, but no fire or smoke is evident.

Cue: If requested when B Service Water pump is started, report as AO that B Service Water pump post start checks are satisfactory.

Cue: If asked report that the breaker for C service water pump has overcurrent flags dropped.

Cue: When contacted as the WWM, then report that the electrical planner will begin planning work on failed pump.

Cued by Trigger T3 Inadvertent Green train Safety injection (SIAS).

lead examiner Cue: If contacted as a NLO to monitor EDG operations report that #2 EDG is running sat.

Cue: If the contacted as a NLO, to check A Main Chiller after ~ 1min. report that A Main Chiller is running sat.

Cue: If the contacted as the WWM, then report that I&C will start investigating the inadvertent SIAS Cued by Trigger T4 A RCP High Vibrations.

lead examiner A RCP Trigger T5 Loss of Offsite power.

secured Cue: If contacted as the STA to report to the control room, acknowledge the request.

Cue: If contacted as a NLO to perform Attachment 47 Field Operator Post Trip Actions, acknowledge request.

  1. 1 Emergency Diesel Generator low voltage.

Cued by #1 Emergency Diesel Generator output breaker will trip open.

lead examiner #2 Emergency Diesel Generator will trip due to a loss of lube oil.

Cue: If contacted as a NLO to manually locally close 2A308, then after one minute report that 2A308 would not close locally.

Cue: If contacted as Unit 1, then report that Unit 1 does not need any power.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 1 Event

Description:

Place the B Main Feedwater pump in service.

Time Position Applicant's Actions or Behavior Examiner note: B Main feedwater pump will be idling ready to be placed in service.

BOP 13.8 WHEN desired to place MFWP speed controller (2HIC-0310) in AUTO, THEN perform the following:

13.8.1 Display Speed Demand Tracking on EITHER of the following:

Page 2 of MFRV controller (2HIC-0740)

PMS point (PMPDMDTB)

BOP 13.8.2 Slowly adjust demand on Feed Pump speed controller to match Speed Demand Tracking value within 1% output.

Examiner note: This step should be done slowly to allow the feedwater control system time to respond and control SG levels. B Main Feedwater pump will start feeding when discharge pressure becomes slightly higher than SG pressure.

Cue: If requested as the NLO, report that B Main Feedwater pump is running sat.

BOP 13.8.3 Place Feed Pump Speed controller (2HIC-0310) in AUTO.

Examiner note: The simulator update rate may cause the controller to not shift to auto or shift back to manual during when this is first attempted and the operator may have to try more than once. It is due to 1/4 sec. simulator update rate and a momentary depress on the A/M button.

BOP 13.8.4 Verify B Feed Reg Valve controller (2HIC-0740) returned to page 1.

Termination criteria: When B Main Feedwater pump is running in automatic or at lead examiner's discretion.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 2 Event

Description:

Power escalation.

Time Position Applicant's Actions or Behavior T=0 Examiner note: Crew will conduct Reactivity Management Brief per COPD-030 prior to reaching to simulator and may elect to conduct a short re-focus brief in the simulator.

SRO Direct applicable actions of OP, 2102.004 Power Operations.

Procedure Note:

Steps may be performed in any order as plant conditions allow.

Plant parameters may be monitored using Exhibit 2, Various Parameters Vs Reactor Power.

Boron adjustment data for power change may be obtained from Reactivity curves located in Plant Data book.

Applicable steps in this section would be performed following removal of Main Turbine Generator from grid with Reactor maintained critical.

SRO 8.2 Verify the following initial conditions:

RCS temperature within 2ºF of program value per Exhibit 1, TAVE VS TREF.

PZR pressure in TS band [If reduced pressure desired, then refer to Pressurizer Operations (2103.005)].

S/G levels ~ 60% with MFW in AUTO or MANUAL.

All required logs initiated per Mode Changes section of Unit Two Operations Logs (1015.003B).

SRO/ATC

  • 8.3 During power escalation, use Attachment A of this procedure for ASI control.

SRO

  • 8.4 IF any Group 6 or P CEA RSPT inoperable due to spiking, T-Mod, etc., THEN refer to CPC/CEAC Operations (2105.001) to perform the following as required:

Examiner note: No RSPTs will be spiking step is N/A SRO 8.5 Verify Turbine warm-up commenced using Turbine Generator Operations (2106.009).

Examiner note: Turbine warm up is complete IAW turnover.

Procedure Caution:

Failure to position the jack sleeve to neutral position can cause failure of valve to fully close during remote actuation. (CR-ANO-2-2012-01432)

Neutral position is defined as alignment of the pointer on jack sleeve with neutral position indicator.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 2 Event

Description:

Power escalation.

Time Position Applicant's Actions or Behavior ANY 8.6 Verify Main Feedwater Regulating valves NOT jacked closed or pinned:

2CV-0748 2CV-0740 Cue: If requested as the NLO, report that 2CV-0748 and 2CV-0740 are not jacked closed or pinned and the jacking sleeve is in the neutral position.

SRO 8.7 IF available, THEN idle second MFWP to minimize O2 ingress and enhance system reliability using Main Feedwater Pump and FWCS Operation (2106.007).

Examiner note: Both MFWP are already idling.

ATC 8.8 Commence raising power by performing the following as necessary:

Dilution using Chemical Addition (2104.003).

CEA withdrawal using CEDMCS Control System Operation (2105.009).

ATC Commence Dilution using Chemical Addition (2104.003).

Procedure Caution:

The following section has been determined to have a Reactivity Addition Potential (RAP) and this activity is classified as a Risk Level R3.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 2 Event

Description:

Power escalation.

Time Position Applicant's Actions or Behavior ATC 1.0 Verify EITHER Reactor Makeup pump (2P-109A OR 2P-109B) running.

2.0 Verify Mode Select switch (2HS-4928) in DILUTE.

3.0 Verify Reactor Makeup Water Flow controller (2FIC-4927) set up as follows:

In MANUAL OR AUTO.

Demand set to less than Charging flow.

4.0 Verify VCT Makeup Isol valve (2CV-4941-2) open.

5.0 Operate Reactor Makeup Water Flow Batch controller (2FQIS-4927) as follows:

5.1 Depress Red pushbutton.

5.2 Verify 2FQIS-4927 set for desired quantity.

2104.003 Chemical 5.3 Verify 2FIC-4927 indicates desired flow rate.

Addition Exhibit 2

  • 6.0 Monitor the following parameters:

RCS Tave Axial Shape Index Reactor power 7.0 IF desired to terminate dilution, THEN reset 2FQIS-4927 to zero.

8.0 WHEN 2FQIS-4927 at zero, THEN verify the following:

RMW Flow Control valve (2CV-4927) closes.

No flow indicated on 2FIC-4927.

9.0 Repeat steps 5.0 through 8.0 as required.

10.0 Close 2CV-4941-2.

11.0 Verify 2FQIS-4927 Batch Volume placard updated to current batch volume.

ATC Commence CEA withdrawal to raise power using CEDMCS Control System Operation.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 2 Event

Description:

Power escalation.

Time Position Applicant's Actions or Behavior 2105.009 Procedure note:

CEA SELECTED indicates selected CEA position.

GROUP SELECTED indicates average position of selected group.

If > 6 inch deviation occurs in any regulating group, then rod motion is inhibited by PMS CEA sequencing 1.0 IF moving CEAs in group, THEN perform the following at 2C03:

1.1 Place Group Select switch to desired group position.

1.2 IF moving Group P CEAs, THEN place P Group Select switch to P.

1.3 Ensure Individual CEA Selection switches aligned to CEA in group selected to move.

1.4 Place Mode Select switch to MANUAL GROUP (MG) or MANUAL SEQUENTIAL (MS).

  • 1.5 Observe CEAC and Pulse Counter CEA position indications to verify CEA motion and alignment as CEAs are moved.

1.6 Position groups as desired using Manual Control lever.

2105.009 R A 1.7 Place Mode Select switch to OFF.

CEDMCS operations P 1.8 Verify Pulse Counter and CEAC indications match.

Exhibit 3 2.0 IF moving CEA individually, THEN perform the following:

2.1 Verify Group Select switch selected to group containing individual CEA.

2.2 Place Individual CEA Selection switches to desired CEA.

2.3 Place Mode Select switch to MANUAL INDIVIDUAL (MI).

  • 2.4 Observe CEAC and Pulse Counter CEA position indications to verify CEA motion and alignment as CEAs are R moved.

A P 2.5 Position CEA as desired using Manual Control lever.

2.6 WHEN individual CEA movement complete, THEN place Mode Select switch to OFF.

2.7 Verify Pulse Counter and CEAC indications match.

SRO Continue with Power Operation section for startup to 20%

ANY

  • 8.9 Monitor CPC Raw Powers using PQASI screen on PMS.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 2 Event

Description:

Power escalation.

Time Position Applicant's Actions or Behavior Procedure Note:

At low powers, the CPC axial power distribution is based on a fixed, pre-calculated shape (canned value). When in use, the pre-calculated axial shape will result in CPC core average ASI (PID 268) reading approximately 1E-2. When raising power, the point at which CPCs change from using the pre-calculated axial shape to the real shape indicated by excore detectors is when raw excore power exceeds an average of 17%. When lowering power, CPCs will switch back to using a pre-calculated axial shape when raw power reaches an average of 14.5%. These power thresholds also correspond to the enabling and disabling of the PQASI auxiliary trip, respectively.

CPC core average ASI (PID 268) may therefore be used as a secondary indication of whether the PQASI trip is enabled or disabled in a CPC channel.

ANY 8.10 WHEN CPC Raw Power exceeds 3% (average of PID 10, 11 &

12), THEN use PQASI (PID 266) for ASI control.

Procedure Note:

Consider ASI control prior to placing the turbine on line. If difficulty achieving + 0.45 > PQASI > -

0.45 is expected, consider leaving the turbine off line until PQASI is within limits. This may prevent holds at low turbine load which contribute to vibration problems.

SRO 8.11 WHEN BOTH conditions are met:

Reactor power greater than or equal to 4%

Turbine warming complete, THEN perform the following anytime during power escalation:

8.11.1 Roll and test Turbine Generator using Turbine Generator Operations (2106.009).

8.11.2 Synchronize and block load Turbine Generator using Turbine Generator Operations (2106.009).

BOP

  • 8.12 Maintain the following limits while Raising power using Turbine Generator Operations (2106.009) OR SDBCS:

Tref within +/- 2°F of program Tave (Exhibit 1, TAVE VS TREF).

Power escalation limits of Attachment A of this procedure.

Procedure Note:

During unit startup, RCS lithium out-of-spec hours commence 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after entering Mode 1 or at Xenon equilibrium, whichever occurs first.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 2 Event

Description:

Power escalation.

Time Position Applicant's Actions or Behavior SRO 8.13 WHEN Reactor power greater than 5%,

THEN perform the following: (N/A if Mode 2 was not entered)

Verify PMS Mode correct on Plant Mode Assignment (PMA).

Record entry into Mode 1 in Station log.

Make open item Station Log entry; RCS Lithium required to be within its proper control band within the next 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after entering Mode 1 or at Xenon equilibrium, whichever occurs first - _______/_______.

Time Date Make Shift Relief Sheet entry; RCS Lithium required to be within its proper control band within the next 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after entering Mode 1 or at Xenon equilibrium, whichever occurs first - _______/_______.

Time Date Termination criteria: When reactivity manipulations are satisfied or at the discretion of the lead examiner.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 3 Event

Description:

B Pressurizer level control channel fails high.

Time Position Applicant's Actions or Behavior Cued by ANY Announce annunciator 2K10-J7 CNTRL CH 2 LEVEL HI is due to B level lead channel High level.

examiner ANY Compare Pressurizer level channels and determine that B Pressurizer level channel has failed high and Pressurizer level is actually lowering.

SRO Enter OP-2203.028, PZR Systems Malfunctions AOP.

SRO 1. Check the following criteria:

A. IF any PZR spray valve failed open, THEN GO TO Step 2.

B. IF any PZR spray valve failed closed, THEN GO TO Step 4.

C. Check RRS TROUBLE annunciator (2K10-H2) clear.

D. Check "CNTRL CH 1/2 PRESSURE HI/LO" annunciators (2K10-E6/E7) clear.

E. Check the following PZR level annunciators clear: (Not Met, perform contingency)

SRO 7. Check the following PZR level annunciators clear: (Not Met, perform contingency)

  • "CNTRL CH 1/2 LEVEL HI" 2K10-J6/J7 ANY Perform Step 7 Contingency Actions.
7. Perform the following:

A. Compare PZR level instruments to determine affected channel.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 3 Event

Description:

B Pressurizer level control channel fails high.

Time Position Applicant's Actions or Behavior SRO B. IF BOTH PZR level control channels failed, THEN GO TO Step 8.

Examiner Note: This step is not applicable.

ATC C. IF only the selected control channel affected, THEN perform the following:

1) Perform the following for Letdown Flow controller (2HIC-4817):
2) Restore PZR Spray valves and Heater control to automatic.

a) Place controller in MANUAL.

b) Adjust output to control PZR level within 5% of setpoint.

2) Place PZR Level Channel Select switch (2HS-4628) to unaffected channel.
3) Place PZR Low Level Cutoff select switch (2HS-4642) to unaffected channel.
4) Verify PZR heaters and Normal Spray operating to restore RCS pressure 2025 psia to 2275 psia.
5) WHEN Letdown Flow controller (2HIC-4817) automatic and manual signals matched, THEN restore 2HIC-4817 controller to AUTO using 2104.002, Chemical and Volume Control.

ANY D. IF non-selected control channel failed, THEN perform the following:

1) Place PZR Low Level Cutoff select switch (2HS-4642) to unaffected channel.
2) Verify PZR heaters and Normal Spray operating to restore RCS pressure 2025 psia to 2275 psia.

Examiner Note: This step is not applicable.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 3 Event

Description:

B Pressurizer level control channel fails high.

Time Position Applicant's Actions or Behavior BOP E. IF Letdown Radiation monitor isolated due to high temperature AND Letdown HX Outlet temperature lowered to less than 140°F, THEN restore Letdown Radiation Monitor flow by opening Letdown Rad Monitor Isolation, 2CV-4804 (2HS-4804).

F. Refer to TS 3.3.3.5, Remote Shutdown Instrumentation and SRO 3.3.3.6, Post-Accident Instrumentation.

Examiner Note: TS 3.3.3.5 and TS 3.3.3.6 action 1.

Termination Criteria: PZR level control selected to channel A and Tech Specs are entered or at lead examiner's discretion.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 4 Event

Description:

2P-4C Service water pump breaker trips.

Time Position Applicant's Actions or Behavior Cued by ANY Report 2K05-B5 2P4C BREAKER TRIP lead examiner SRO Enter and direct actions of AOP 2203.022, Loss of Service Water SRO *1. Check the following criteria satisfied:

A. Breaker trip annunciators clear (2K06-B5/2K05-B4, B5). (Not Met, Perform contingency)

SRO A. GO TO Step 8.

SRO 8. Check "2P4A BREAKER TRIP" annunciator (2K06-B5) clear.

9. Check "2P4B BREAKER TRIP" annunciator (2K05-B4) clear.

SRO 10. Check "2P4C BREAKER TRIP" annunciator (2K05-B5) clear. (Not Met, Perform contingency)

BOP 10. IF 2P4C tripped, THEN perform the following:

A. IF 2P4B aligned to Loop 2, THEN verify 2P4B running.

Cue: If asked report that the motor for C Service Water Pump is hot to touch, but no fire or smoke is evident.

Cue: If requested when B Service Water pump is started, report as AO that B Service Water pump post start checks are satisfactory.

Cue: If asked report that the breaker for C service water pump has overcurrent flags dropped.

ANY 11. Check "2P4A/B/C STRAINER P" annunciators (2K06-E5/2K05-E4/2K05-E5) clear.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 4 Event

Description:

2P-4C Service water pump breaker trips.

Time Position Applicant's Actions or Behavior ANY 12. Perform the following:

A. IF procedure entered due to low Lake level, THEN perform 2203.008, Natural Emergencies (Loss of Lake Dardanelle) in conjunction with the remainder of this procedure.

B. Verify running SW pump sluice gates aligned to lake or ECP:

PUMP LAKE ECP 2P4A 2CV-1470-1 2CV-1471-1 2P4B 2CV-1472-5 2CV-1473-5 2P4C 2CV-1474-2 2CV-1475-2 Procedure Caution:

Continuous operation on the ECP may result in loss of ECP level due to ACW and CCW returning to the lake or cooling tower.

ANY 13. IF ANY running SW Pump bay aligned to ECP, THEN perform the following:

Examiner note: Step 13 is N/A Procedure Note:

SW Return header return path may be aligned to Cooling Tower, lake, or BOTH, as desired to aid in draining ruptured SW loop.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 4 Event

Description:

2P-4C Service water pump breaker trips.

Time Position Applicant's Actions or Behavior ANY 14. Verify intact SW Return headers alignment as follows:

A. SW Return aligned to Cooling Tower:

1) Makeup Water to Cooling Tower valve (2CV-1540) open.
2) Intact SW loop CCW/ACW Return Isolation valve open:

2CV-1543-1 2CV-1542-2

3) GO TO Step 15.

B. SW Return aligned to lake:

1) Verify Cooling Tower Basin Level Control (2LIC-1207A) in MANUAL.
2) Verify Cooling Tower Basin Level Control valve (2CV-1460) open as necessary to provide for the following:

Control of Cooling Tower Basin level.

Maintain a discharge path for SW.

3) Intact SW loop SW Return to Lake valve open:

2CV-1481-1 2CV-1480-2 ANY 15. Check Plant in Mode 1, 2, 3, or 4.

16. Check BOTH SW loops operating with at least one pump running on each loop.

Procedure Note:

SW Loop Operability is NOT dependent upon B Bay Sluice Gate Power Alignment.

ANY 17. Check BOTH SW loops operable.

Examiner note: Both Loops of service water are operable.

SRO 17. IF EITHER SW loop NOT operable, THEN perform the following:

A. Notify SM to perform Attachment B, Tech Spec and TRM Evaluation.

Examiner Note: This step is N/A.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 4 Event

Description:

2P-4C Service water pump breaker trips.

Time Position Applicant's Actions or Behavior ANY 18. Check BOTH of the following are TRUE:

"ACW PRESS LO" annunciator (2K06-E6) clear.

ACW pressure greater than 55 psig (2PI-1603).

ANY 19. Verify SW pump 2P4B fully aligned to intact SW Loop using 2104.029, Service Water System Operations.

SRO Contact work management.

Cue: When contacted as the WWM, then report that the electrical planner will begin planning work on failed pump.

Termination criteria: When B service water pump is placed in service or at lead examiners discretion.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 5 Event

Description:

Inadvertent Green train Safety injection.

Time Position Applicant's Actions or Behavior Cued by ANY Announce alarms 2K04-G8 2C-40 power supply trouble, 2K04-H8 2C-40 lead power supply ground.

examiner ANY Determine that an Inadvertent Safety injection is occurring.

Procedure Note:

Steps marked with (*) are continuous action steps.

SRO Enter and Implement AOP 2203.018, Inadvertent SIAS.

SRO 1. Record start time. __________

ANY *2. Check SIAS actuated without Reactor trip.

Examiner note: The Reactor will not be tripped.

ANY 3. Determine validity of SIAS actuation as follows:

Check RCS pressure greater than SIAS variable setpoint.

Check CNTMT pressure less than 18.3 psia.

BOP 4. Restore SW to non-ESF systems by performing the following:

A. Override AND open SW to ACW Supply valves as necessary:

2CV-1425-1 2CV-1427-2 B. Override AND open CCW/ACW Return valves as necessary:

2CV-1543-1 2CV-1542-2 C. Override AND open SW to CCW/Main Chillers Supply valves as necessary:

2CV-1530-1 2CV-1531-2 ANY 5. Check turbine runback NOT in progress.

SRO 6. GO TO step 13.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 5 Event

Description:

Inadvertent Green train Safety injection.

Time Position Applicant's Actions or Behavior ATC 13. IF plant in Mode 1 or 2, THEN perform the following:

A. Verify ALL Charging pumps (2P36A/B/C) in STOP.

B. Adjust Turbine load AND match TREF within 2°F of TAVE.

SRO 14. Notify SM to evaluate SW operability using Attachment B, Tech Spec and TRM Evaluation.

SRO 15. Perform the following:

A. IF SIAS actuation has occurred on BOTH Red AND Green Trains, THEN GO TO Section 2, Both Trains.

B. IF SIAS actuation has occurred on ONLY the Red Train, THEN GO TO Section 3, Red Train.

C. IF SIAS actuation has occurred on ONLY the Green Train, THEN GO TO Section 4, Green Train.

Cue: If contacted as a NLO to monitor EDG operations report that #2 EDG is running sat.

SRO SRO transition to Section 4 for Green Train BOP 1. Place the following pumps in PTL:

HPSI pump 2P89B HPSI pump 2P89C (Green side ONLY)

LPSI pump 2P60B Boric Acid pump 2P39A Boric Acid pump 2P39B Revision 0 Page 21 of 46

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 5 Event

Description:

Inadvertent Green train Safety injection.

Time Position Applicant's Actions or Behavior SRO 2. IF plant in Mode 1, 2, 3, or 4, THEN perform the following:

A. Record time SIAS components placed in PTL ________.

B. Notify SM to refer to TS/TRM using Attachment B, Tech Spec and TRM Evaluation.

Examiner note: The SRO may not refer to the attachment during the performance of the procedure this is normally a duty of the SM but he would still be responsible for being able to correctly determine TS after the scenario.

SRO Refer to TS/TRM using Attachment B.

SRO 1. Perform the following to evaluate Service Water operability:

Procedure Note:

If SW MOVs have been actuated closed by SIAS, overriding SW MOVs will cause the associated SW loop to be inoperable. Overriding SW MOVs on both trains will cause both SW loops to be inoperable.

SRO A. IF SW MOVs on BOTH SW headers overridden, THEN perform the following:

Examiner note: This step is N/A.

SRO B. IF SW MOVs on only ONE SW header overridden, THEN perform the following:

1) Declare associated SW loop inoperable.
2) Determine if entry into TS 3.0.3 required by reviewing the following:

LCO Tracking Records Status boards Ongoing maintenance activities

3) Notify Unit 1 to refer to TS 3.7.10, Control Room Emergency Air Conditioning System (CREACS).

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 5 Event

Description:

Inadvertent Green train Safety injection.

Time Position Applicant's Actions or Behavior SRO C. Refer to the following additional TS/TRM:

TS 3.0.5 TS 3.4.4, Pressurizer TS 3.5.2, ECCS Modes 1-3 TS 3.5.3, ECCS Modes 3, 4 TS 3.6.1.4, CTMNT Pressure/Temperature TS 3.6.2.1, CTMNT Spray TS 3.6.2.3, CTMNT Coolers TS 3.7.1.2, EFW TS 3.7.3.1, Service Water TS 3.7.6.1, CREVS/CREACS TS 3.8.1.1, AC Sources Modes 1-4 TS 3.8.1.2, AC Sources Modes 5, 6 TRM 3.6.4, H2 Analyzers Examiner Note: SRO must enter TS 3.4.4, 3.5.3, 3.6.2.1, 3.6.2.3, and 3.7.3.1, and 3.8.1.1.

Procedure Note:

Per Licensing and TRM Bases statement, "The boration systems described in these TROs, including the Charging pumps are not credited in any accident mitigation." Charging pump auto start is not required for functionality.

SRO 2. IF SIAS actuated components are placed in PTL or overridden, THEN refer to the following TS/TRM as applicable:

TS 3.0.5 TS 3.5.2, HPSI/LPSI TS 3.5.3, HPSI/LPSI TRM 3.1.2, Flowpaths TRM 3.1.4, Charging pump TRM 3.1.6, Boric Acid Makeup Pumps SRO Continue with the remaining step of Inadvertent SIAS procedure.

ANY *3. Monitor RCP seals for proper performance.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 5 Event

Description:

Inadvertent Green train Safety injection.

Time Position Applicant's Actions or Behavior ANY *4. Control RCS inventory as follows:

A. Operate Charging pumps to maintain PZR level within 4% of setpoint.

B. Record charging header data using 2202.010 Attachment 44, Charging Header Data.

Procedure Note:

CNTMT temperature and pressure may rise if a Main Chiller is tripped due to the inadvertent SIAS.

SRO 5. Check Main Chiller 2VCH-1A running.

Examiner note: A Main Chiller will be running.

Cue: If the contacted as a NLO, to check A Main Chiller after ~ 1min. report that A Main Chiller is running sat.

SRO 6. IF Reactor power change greater than 15% in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, THEN notify Chemistry to sample RCS for Iodine within 2 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, refer to TS 3.4.8, Specific Activity.

ANY 7. Check CNTMT pressure less than 18.3 psia AND RCS pressure greater than SIAS setpoints.

BOP *8. IF needed to maintain Cooling Tower Basin level, THEN perform the following as necessary:

A. Align Loop 2 Service Water return to the Lake by performing the following:

1) Override AND close Loop 2 Emerg Pond RTN (2CV-1560-2) by taking handswitch 2HS-1560-2 to OPEN then to CLOSE.
2) WHEN Loop 2 Emerg Pond RTN (2CV-1560-2) begins closing, THEN verify Loop 2 SW Return Hdr to Dardanelle (2CV-1480-2) begins opening.

B. IF Loop 1 SW supplying ACW, THEN cycle Loop 2 CCW/ACW Return Isol 2CV-1542-2 as needed.

C. IF Loop 2 SW supplying ACW, THEN cycle Loop 1 CCW/ACW Return Isol 2CV-1543-1 as needed.

Examiner note: No actions should be required to maintain cooling tower basin level at the current power level.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 5 Event

Description:

Inadvertent Green train Safety injection.

Time Position Applicant's Actions or Behavior Procedure Note:

If SIAS is only partially actuated, 2305.003, ESF Response Time Test, may assist in determining affected components or relays.

ANY 9. Reset SIAS actuation on PPS panels using 2202.010 Attachment 13, SIAS Reset.

Examiner Note: The crew may determine that SIAS will not reset without performing attachment 13 due to the power supply trouble and ground alarms Cue: If the contacted as the WWM, then report that I&C will start investigating the inadvertent SIAS Termination Criteria: When the crew has place the SIAS components listed in step 1 of section 4 in PTL or at the discretion of the lead examiner.

Revision 0 Page 25 of 46

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 6, 7, 8 & 9 Event

Description:

A High Vibrations, #1 EDG low voltage, Loss of Offsite power, #1 EDG output breaker trip, and #2 EDG loss of lube oil.

Time Position Applicant's Actions or Behavior Cued by ANY Announce alarm 2K11-G6 RCP Vibration Hi.

lead examiner SRO Implement OP-2203.025, RCP Emergencies.

SRO *1. Check the following criteria for EACH RCP satisfied:

A. CCW flow aligned to RCPs.

B. In-service CCW Surge Tank level greater than 13% following restoration of CCW to RCPs.

C. Vapor Seal pressure less than 1500 psia.

D. Seal Stage P greater than 50 psid.

E. Controlled Bleedoff temperature less than 180°F.

F. Controlled Bleedoff flow less than 3.0 gpm.

G. Bearing and Motor Temperature annunciators clear.

H. Upper and Lower Oil Reservoir annunciators clear.

I. High Vibration annunciator clear. (Not Clear, perform contingency)

J. Normal RCP amps and D/P SRO I. GO TO Step 11.

SRO *11. Perform the following:

A. Refer to Attachment E, RCP Motor and Pump Shaft Vibration.

Procedure Note:

Indications should be validated by checking multiple parameters (i.e., other vibration probes, bearing temperatures, oil pressure and flow, seal parameters, etc.).

Revision 0 Page 26 of 46

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 6, 7, 8 & 9 Event

Description:

A High Vibrations, #1 EDG low voltage, Loss of Offsite power, #1 EDG output breaker trip, and #2 EDG loss of lube oil.

Time Position Applicant's Actions or Behavior SRO ATTACHMENT E RCP MOTOR AND PUMP SHAFT VIBRATION Plant HI Vibration Alarm HI HI Vibration Trip Reactor Condition Alarm and Secure Affected RCP (NOTES 1 & 2)

Normal Evaluate bearing Evaluate rate of Motor >20 mils Power temperatures and vibration increase. Shaft >25 mils Operations rate of vibration If vibration spiking increase. Contact but not remaining OR Predictive above alarm set- rapidly rising Maintenance or the point, contact PdM trend with System Engineer. and System other Engineering. parameters If vibration on a also indicating rising trend, make a problem preparations to secure the RCP Off Normal Evaluate bearing Evaluate bearing Motor > 20 Operations temperatures, seal temperatures, seal mils (Low RCS parameters, and parameters, and Shaft >25 mils pressure, plant conditions. plant conditions.

temperature, Vibration levels Vibration levels OR or < 4 pump typically exceed typically exceed rapidly rising operations) alarm set-points alarm set-points trend with during plant startup, during plant startup, other shutdown, and other shutdown, and other parameters abnormal operating abnormal operating also indicating modes. modes. a problem NOTE 1) ALL Motor Bearing Vibration probes and B, C, D Pump Shaft ProbesPlant Computer indication for RCP vibration is only good up to 26 mils. Above 26 mils, the quality changes to BAD and the value is not displayed. If a rapid upward vibration trend is followed by loss of vibe data AND a BAD quality indicator, vibes are greater than 26 mils.

NOTE 2) A Pump Shaft ProbePump shaft vibration is scaled for 0 to 30 mils. Plant Computer will display values up to 35 mils.

Values above 35 mils are suspect due to exceeding linear range of the vibration probes. At some value above 35 mils, point quality will change to BAD and no data will be displayed.

Examiner Note: The SRO should determine that vibrations are high on A RCP and use step 11 to trip the reactor and A RCP.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 6, 7, 8 & 9 Event

Description:

A High Vibrations, #1 EDG low voltage, Loss of Offsite power, #1 EDG output breaker trip, and #2 EDG loss of lube oil.

Time Position Applicant's Actions or Behavior Critical ATC B. Monitor and record data on Task: A Attachment C, RCP Data.

RCPs must be C. IF Attachment E Vibration Trip limits exceeded secured AND in Mode 1 or 2, within 10 THEN perform the following:

min of the reactor 1) Trip the Reactor.

trip.

2) Stop any affected RCP.
3) IF only one RCP affected, AND desired to balance reactor coolant loop temperatures, THEN verify one RCP secured in each loop.
4) IF RCP 2P32A OR 2P32B stopped, THEN verify associated PZR Spray valve in MANUAL and closed:

2CV-4651 2CV-4652

5) GO TO 2202.001, Standard Post Trip Actions.

SRO Enter OP-2202.001, Standard Post Trip Actions EOP.

SRO 1. Notify Control Board Operators to perform the following:

A. Monitor safety functions using Exhibit 7, CBO Reactor Trip Checklist.

B. Perform post trip contingencies as required.

2. Open Safety Function Tracking page.

ATC 3. Check Reactivity Control established as follows:

A. Reactor power lowering.

Reactivity B. Check startup rate is negative.

Control Safety C. ALL CEAs fully inserted by observing ANY of the following:

Function 1) CEA Rod bottom lights illuminated.

2) CEAC 1 indicates ALL CEAs fully inserted.
3) CEAC 2 indicates ALL CEAs fully inserted.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 6, 7, 8 & 9 Event

Description:

A High Vibrations, #1 EDG low voltage, Loss of Offsite power, #1 EDG output breaker trip, and #2 EDG loss of lube oil.

Time Position Applicant's Actions or Behavior BOP 4. Check Maintenance of Vital Auxiliaries satisfied:

A. Check Main Turbine tripped by BOTH of the following:

ALL Main Stop Valves closed.

Generator megawatts indicate zero.

B. Generator Output breakers open.

BOP C. Perform EITHER of the following as required:

1) Check the following valves closed:

MSR 2E-12A Steam Supply From SG A (2CV-0400)

Vital MSR 2E-12B Steam Supply From Auxiliaries SG B (2CV-0460)

Safety Function 2) No flow indicated on the following MSR second stage flow instruments:

2FI-0402 2FI-0462 BOP D. At least ONE 6900v AC bus energized (Not met)

E. At least ONE 4160v Non-vital AC bus energized. (Not met)

F. BOTH 4160v Vital AC buses energized. (Not met, perform contingency)

G. BOTH DGs secured. (Not met, contingency is satisfied.)

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 6, 7, 8 & 9 Event

Description:

A High Vibrations, #1 EDG low voltage, Loss of Offsite power, #1 EDG output breaker trip, and #2 EDG loss of lube oil.

Time Position Applicant's Actions or Behavior BOP Perform Step 4.F and 4 .G. Contingency Actions.

F. Perform the following:

1) IF de-energized 4160v Vital AC bus available AND associated EDG available, THEN verify associated EDG supplying bus.

Examiner Note: The BOP should raise voltage allowing the #1 EDG output breaker to close.

Vital Auxiliaries G. IF ANY DG running AND SW NOT aligned, Safety THEN locally stop DG by unlocking and placing "ENGINE Function CONTROL" handswitch in LOCKOUT:

2E11 2E21 Examiner Note: Service water will be aligned both after #1 EDG voltage is raised EDGs ANY H. At least ONE 125v Vital DC bus energized:

2D01 - SPDS point E2D01 2D02 - SPDS point E2D02 ATC 5. Check RCS Inventory Control established as follows:

A. PZR level:

10 to 80%.

Trending to setpoint. (May not met due to charging being RCS secured, If not met perform contingency)

Inventory B. RCS MTS 30°F or greater.

Control Safety Function SRO Perform Step 5 Contingency Actions.

A. Perform as necessary:

1) IF SIAS actuated on PPS inserts, THEN GO TO Step 6.
2) Verify PZR Level Control system restoring level to setpoint.

ATC The ATC should start charging pumps as necessary to restore PZR level.

ATC 6. Check RCS Pressure Control:

RCS

  • 1800 to 2250 psia.

Pressure

  • Trending to setpoint.

Control Safety

  • Normal PZR Spray and heaters controlling pressure. (Not met, Function perform contingency actions)
  • Valid CNTMT Spray NOT in progress.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 6, 7, 8 & 9 Event

Description:

A High Vibrations, #1 EDG low voltage, Loss of Offsite power, #1 EDG output breaker trip, and #2 EDG loss of lube oil.

Time Position Applicant's Actions or Behavior Perform Step 5 Contingency Actions as necessary:

6. Perform as necessary:

D. IF RCP 2P32A or 2P32B stopped, THEN verify associated PZR Spray valve in MANUAL and closed.

RCP A Spray Valve (2CV-4651)

RCP B Spray Valve (2CV-4652)

E. IF ALL RCPs stopped AND RCS pressure control required, THEN initiate Aux spray using Attachment 48, RCS Pressure Control.

RCS Pressure F. IF RCS pressure lowers to 1650 psia or less, Control ATC THEN perform the following:

Safety Function 1) Verify SIAS actuated on PPS inserts.

2) GO TO Step 7.

G. Verify PZR Pressure Control system restoring pressure to setpoint.

Examiner Note: RCS pressure will be rising due to loss of forced circulation the ATC will have to align for auxiliary spray to arrest the pressure rise.

Critical Task: Maintain RCS pressure within the Pressure-Temperature limits of 200°F and 30°F Margin to Saturation and less than 2500 psia.

ATC Implement OP-2202.010, Standard Attachment, Attachment 48.

Attachment 48 Procedure Note:

Once method of pressure control is established, this attachment is not required in hand or continuous use.

A change to the method of pressure control will require in hand or continuous use until the new pressure control method is established.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 6, 7, 8 & 9 Event

Description:

A High Vibrations, #1 EDG low voltage, Loss of Offsite power, #1 EDG output breaker trip, and #2 EDG loss of lube oil.

Time Position Applicant's Actions or Behavior ATC *1. Maintain RCS pressure with heaters and spray using one or more of the following:

D. IF desired to use AUXILIARY Spray, THEN perform the following:

  • 1) Verify RCS MTS greater than 30 degrees.

Steps from Attach. 48 2) Verify at least ONE Charging pump running.

3) Close Regen HX to RCP B/C valves:
a. 2CV-4827-2
b. 2CV-4831-2 Procedure Note:

PZR Spray Block valves 2CV-4653 and 2CV-4655 are de-energized due to degraded power supply cables.

ATC 4) Verify PZR Spray (2CV-4651/2CV-4652) or PZR Spray Isolation valves (2HS-4655/2HS-4653) closed.

5) Throttle Aux Spray valve (2CV-4824-2) as necessary.

Steps from 6) IF Regen HX to RCS temperature (2TI-4825) can NOT be Attach. 48. reduced to less than 275°F, THEN perform ONE of the following:

a) Isolate Letdown to reduce temperature.

b) Complete Table 1 of this attachment.

ATC 7) IF Regen HX to RCS (2TI-4825) AND PZR water phase (2TI-4627) differential temperature greater than 200°F AND PMS is unavailable, THEN complete Table 1 of this attachment.

TIME TEMPERATURE SPRAY SPRAY (PZR 2TIS-4607 Steps from VALVE VALVE WATER 2TIS-4608 Attach. 48. OPENED CLOSED PHASE) 2TI-4825 DIFFERENCE 2TI-4627 Revision 0 Page 32 of 46

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 6, 7, 8 & 9 Event

Description:

A High Vibrations, #1 EDG low voltage, Loss of Offsite power, #1 EDG output breaker trip, and #2 EDG loss of lube oil.

Time Position Applicant's Actions or Behavior SRO Implement remaining steps from OP-2202.001, Standard Post Trip Actions Steps.

ATC 7. Check Core Heat Removal by forced circulation:

A. At least ONE RCP running. (Not met, perform contingency)

SRO Perform Step 7 Contingency Actions.

Core Heat Removal A. IF ALL RCPs stopped, safety THEN perform the following:

function.

1) Verify BOTH PZR Spray valves in MANUAL and closed.
2) GO TO Step 8.
8. Check RCS Heat Removal:

A. Check SG available by BOTH of the following:

ANY

  • At least ONE SG level 10 to 90%.
  • FW maintaining SG level. (Not met)

Perform Step 8.A Contingency Action.

RCS Heat A. Perform the following:

Removal Safety ANY

1) IF SG level lowering, Function THEN verify EFAS actuated.

SRO B. Check MFW in RTO. (Not met)

Perform Step 8.B Contingency Action if required.

B. Verify EITHER of the following:

SRO

  • BOTH MFW pumps tripped.
  • SG levels controlling at setpoint Revision 0 Page 33 of 46

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 6, 7, 8 & 9 Event

Description:

A High Vibrations, #1 EDG low voltage, Loss of Offsite power, #1 EDG output breaker trip, and #2 EDG loss of lube oil.

Time Position Applicant's Actions or Behavior ANY C. Check Feedwater line intact by the following:

  • SG level stable or rising.
  • NO unexplained step changes or erratic FW flow.
  • NO unexplained step changes or erratic Condensate flow.

RCS Heat BOP D. Check RCS TC 540 to 555°F Removal Safety E. Check SG pressure 950 to 1050 psia.

Function F. IF desired, THEN perform the following for SDBCS Master Controller using 2105.008 Exhibit 3, SDBCS Emergency Operation:

1) Place controller in Auto/Local.
2) Set setpoint at 960 psia.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 6, 7, 8 & 9 Event

Description:

A High Vibrations, #1 EDG low voltage, Loss of Offsite power, #1 EDG output breaker trip, and #2 EDG loss of lube oil.

Time Position Applicant's Actions or Behavior ANY 9. Check CNTMT parameters:

A. Temperature and Pressure:

  • Temperature less than 140°F.
  • Pressure less than 16 psia.

B. Check CNTMT Spray pumps secured.

C. NO CNTMT radiation alarms or unexplained rise in activity:

1) CAMS alarms:
2) RCS leakage alarms:

Containment clear.

Safety Function * "PROC LIQUID RADIATION HI/LO" annunciator (2K11-C10) clear.

3) Check the following radiation monitors trend stable:
  • CNTMT Area
  • CAMS
  • Process Liquid D. NO secondary system radiation alarms or unexplained rise in activity:
1) "SEC SYS RADIATION HI" annunciator (2K11-A10) clear.
2) Secondary Systems Radiation monitors trend stable:
  • Condenser Off Gas SRO 10. Notify STA to report to control room.
11. Direct NLOs to perform 2202.010 Attachment 47, Field Operator Post trip actions.
12. Verify Reactor trip announced on Plant page.
13. Notify SM to refer to Technical Specifications and 1903.010, Emergency Action Level Classification.
14. Direct control board operators to acknowledge ALL annunciators and announce ALL critical alarms.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 6, 7, 8 & 9 Event

Description:

A High Vibrations, #1 EDG low voltage, Loss of Offsite power, #1 EDG output breaker trip, and #2 EDG loss of lube oil.

Time Position Applicant's Actions or Behavior Cue: If contacted as the STA to report to the control room, acknowledge the request.

Cue: If contacted as a NLO to perform Attachment 47 Field Operator Post Trip Actions, acknowledge request.

SRO 15. Check ALL safety function acceptance criteria satisfied. (All safety functions are not satisfied, perform contingency)

SRO Perform Step 15 Contingency Actions if necessary.

15. IF ANY safety function acceptance criteria NOT satisfied, THEN perform the following:

A. Notify control room staff of safety functions NOT satisfied.

B. GO TO Exhibit 8, Diagnostic Actions.

SRO Diagnose OP-2202.007, Loss of Offsite Power EOP.

SRO Enter OP-2202.007, Loss of Offsite Power EOP.

Procedure Caution:

Failure to use average CETs to monitor MTS with ALL RCPs stopped may result in misleading evaluation of core conditions.

SRO *1. Confirm diagnosis of Loss Of Feedwater by checking SFSC acceptance criteria satisfied every 15 minutes.

  • 2. Notify SM to refer to Technical Specifications and 1903.010, Emergency Action Level Classification.
3. Open Placekeeping Page.
4. Notify Control Board Operators to perform the following:

A. Monitor floating steps.

B. Verify actuated ESFAS components using 2202.010 Exhibit 9, ESFAS Actuation.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 6, 7, 8 & 9 Event

Description:

A High Vibrations, #1 EDG low voltage, Loss of Offsite power, #1 EDG output breaker trip, and #2 EDG loss of lube oil.

Time Position Applicant's Actions or Behavior ANY *5. Perform the following to protect Main Condenser:

A. Close MSIVs.

B. Close SG Blowdown Isolation valves:

ANY *6. Check SG pressure greater than 950 psia.

ANY *7. Evaluate operation of DGs as follows:

Examiner Note: The manual trigger for loss of both EDGs should be insert near at this point or before this point.

Based on the timing of the EDG failures in event 9 the crew may perform the actions of step 7 or transition to the blackout EOP.

ANY Recognize that #1 EDG output breaker has tripped open and dispatch an operator to investigate.

ANY A. Check BOTH DGs running.

ANY B. Check running DG Output breakers closed. (Not met perform contingency)

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 6, 7, 8 & 9 Event

Description:

A High Vibrations, #1 EDG low voltage, Loss of Offsite power, #1 EDG output breaker trip, and #2 EDG loss of lube oil.

Time Position Applicant's Actions or Behavior SRO Perform Step 7.B Contingency Action.

B. Perform the following:

1) Verify the following breakers open:

2A309, 2A3 Supply Breaker 2A310, 2A3-2A4 Tie Breaker 2A409, 2A4 Supply Breaker 2A410, 2A3-2A4 Tie Breaker

2) Verify running DG voltage and frequency:
  • 4100 to 4200v
  • 59.5 to 60.5 Hz
3) IF NO 4160v Vital bus lockouts exist, THEN perform the following:

a) Place running DG synch switch in ON position.

b) Close running DG Output breaker.

c) IF DG Output breaker will NOT close from 2C33, THEN locally close running DG Output breaker:

  • 2A308, "2DG 1 OUTPUT BREAKER"
  • 2A408, "2DG 2 OUTPUT BREAKER" Cue: If contacted as a NLO to manually locally close 2A308, then after one minute report that 2A308 would not close locally.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 6, 7, 8 & 9 Event

Description:

A High Vibrations, #1 EDG low voltage, Loss of Offsite power, #1 EDG output breaker trip, and #2 EDG loss of lube oil.

Time Position Applicant's Actions or Behavior SRO 4) IF bus can NOT be energized from DG, THEN perform the following:

a) Locally stop affected DG by unlocking and placing "ENGINE CONTROL" switch in LOCKOUT at respective cabinet:

  • 2E11/2E21 b) Start AACG AND align to associated 4160v Vital bus using 2104.037, Alternate AC Diesel Generator Operations, Attachment E.

Examiner Note: The SRO may elect to allow a RO to start the AACG and energize a vital 4160V bus prior to evaluate the need to transition to blackout EOP. However the Safety Function Status Checks are not met for LOOP EOP and therefore they should not remain in LOOP for an extended period of time.

SRO 8. Check BOTH Vital AC buses energized as follows:

A. Voltage 4100 to 4200v on 4160v Vital buses 2A3 and 2A4. (Not Met Perform contingencies)

BOP 8. Perform EITHER of the following:

IF one vital AC bus energized, THEN GO TO Step 9.

IF ALL Vital buses de-energized, THEN GO TO 2202.008, Station Blackout.

Examiner Note: The crew should go to Station Blackout EOP when both vital 4160 volt busses are de-energized.

SRO Transition to OP-2202.008, Station Blackout EOP.

Procedure Caution:

Failure to use average CETs to monitor MTS with ALL RCPs stopped may result in misleading evaluation of core conditions.

Procedure Note:

The AACG is required to be started and loaded within ten minutes of entering Station Blackout per SAR Table 8.3-7, Reg Guide 1.155 AND DCP 92-2011.

Revision 0 Page 39 of 46

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 6, 7, 8 & 9 Event

Description:

A High Vibrations, #1 EDG low voltage, Loss of Offsite power, #1 EDG output breaker trip, and #2 EDG loss of lube oil.

Time Position Applicant's Actions or Behavior SRO *1 Confirm diagnosis of Station Blackout by checking SFSC acceptance criteria satisfied every 15 minutes.

  • 2. Notify SM to refer to Technical Specifications and 1903.010, Emergency Action Level Classification.
3. Open Placekeeping page.
4. Record time of Blackout occurrence:

Time

5. Notify Control Board Operators to monitor floating steps.

Examiner Note: The SRO may elect to commence floating step #2 Energize 4160 V busses if the BOP has not be directed to energize a vital bus from the Alternate AC Generator.

SRO 11. Energize 4160v Vital buses as follows:

A. Determine DG availability by checking annunciator panels 2K08 and 2K09.

B. IF DG tripped AND cause of trip has been corrected, THEN locally reset DGs using 2202.010 Exhibit 4, DG Local Reset.

C. Check at least ONE DG available. (Not Met, perform contingency)

BOP C. IF BOTH DGs unavailable, THEN perform the following:

1) Start AACG AND align to associated 4160v Vital bus using 2104.037, Alternate AC Diesel Generator Operations, Attachment E.
2) IF AACG started AND EITHER 4160v Vital bus 2A3 OR 2A4 energized, THEN GO TO 2202.007, Loss of Offsite Power.

BOP Transition to OP- 2104.037 Alternate AC diesel Generator Operations BOP 1.0 IF A PLC available, THEN reset PLC using an AACG Annunciator Screen or Att. E handswitch on 2C435.

Procedure Note:

AACG can be started and tied to bus(es) from either of the PCs (2C14 or 2C435) as long as both Network PLCs (PLC-A and PLC-C) are operable.

Revision 0 Page 40 of 46

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 6, 7, 8 & 9 Event

Description:

A High Vibrations, #1 EDG low voltage, Loss of Offsite power, #1 EDG output breaker trip, and #2 EDG loss of lube oil.

Time Position Applicant's Actions or Behavior BOP 2.0 IF EITHER of AACG network PLC (PLC-A or PLC-C) fails, Att. E OR both PCs failed, THEN perform a local start using Exhibit 1 of this procedure.

BOP 3.0 Perform the following to start AAC Generator:

3.1 Touch ELECTRICAL BUS CONTROL.

3.2 Touch 4160 V BREAKERS.

3.3 Verify the following breakers open:

2A901, AAC to 4.16KV Switchgear A3 2A902, AAC to 4.16KV Switchgear 2A4 2A903, AAC to 4.16KV Switchgear A1 2A904, AAC to 4.16KV Switchgear 2A1 Att. E 3.4 Touch ENGINE START/STOP.

3.5 Touch START SCREEN.

3.6 Touch START button.

3.7 IF engine does not start in ~ 35 seconds due to pre-lube interlock, THEN touch and hold EMERGENCY START until engine speed reaches 180 RPM.

3.8 Verify Generator frequency ~ 60 Hz (900 RPM) and voltage ~ 4160 volts.

Revision 0 Page 41 of 46

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 6, 7, 8 & 9 Event

Description:

A High Vibrations, #1 EDG low voltage, Loss of Offsite power, #1 EDG output breaker trip, and #2 EDG loss of lube oil.

Time Position Applicant's Actions or Behavior BOP 4.0 Perform the following to verify AAC Electrical System alignment:

4.1 Touch ELECTRICAL BUS CONTROL.

4.2 Touch 4160V BREAKERS.

4.3 Verify AAC Generator Output breaker (2A1001) closed.

4.4 Touch ELECTRICAL BUS CONTROL.

4.5 Touch 480V BREAKERS.

4.6 Verify Offsite Main Breaker M1 (2B16-A1) open.

Att. E 4.7 Verify Generator Main Breaker M2 (2B16-B1) closed.

4.8 Touch MONITOR 4.9 Touch ANNUNCIATOR SCREEN 4.10 Verify the following alarms clear:

Loss of 480 VAC POWER 120 VAC UPS TROUBLE BOP 5.0 Coordinate with Unit 1 to determine electrical power status.

Cue: If contacted as Unit 1, then report that Unit 1 does not need any power.

Procedure Note In Modes 1-4, 2A3 and 2A4 should NOT be supplied at the same time EXCEPT to satisfy a safety function.

If powering Safety Related loads on BOTH Unit 1 and Unit 2, ongoing efforts should be pursued to restore normal offsite power and/or EDGs in order to minimize the vulnerability of total reliance upon the AACG by both units.

Revision 0 Page 42 of 46

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 6, 7, 8 & 9 Event

Description:

A High Vibrations, #1 EDG low voltage, Loss of Offsite power, #1 EDG output breaker trip, and #2 EDG loss of lube oil.

Time Position Applicant's Actions or Behavior BOP 6.0 IF desired to energize 2A3 from the AACG (Dead-bus transfer only),

THEN perform the following:

6.1 Verify 2A3 - 2A4 Tie breaker (2A310) open.

6.2 Verify 2A3 Supply breaker (2A309) in PTL.

6.3 Verify 2DG1 Output breaker (2A308) in PTL.

6.4 IF 2A4 NOT energized from AAC Generator, THEN perform the following:

Att. E 6.4.1 Verify 2A3 - 2A4 Tie breaker (2A410) open.

Critical 6.4.2 IF PLC available, Task: THEN perform the following:

Energize at least A. Touch ELECTRICAL BUS one vital CONTROL.

AC bus with in 10 minutes of B. Touch 4160 V BREAKERS.

entering the station C. Touch 2A902.

blackout EOP. 6.4.3 Perform the following as needed to close 2A902:

Touch CLOSE on PLC.

Use 2A902 Control switch (2HS-7101).

Locally operate 2A902 per Exhibit 4.

6.5 Close and hold 2A3 - 2A4 Tie (2A310) in close position for 3 seconds.

6.6 Verify 2A3 voltage indicates ~ 4160 volts.

BOP 6.7 IF 2A3 AND 2A4 energized from the AAC Generator in Modes 1-4, Att. E THEN enter Tech Spec 3.0.3.

Examiner Note: This step is N/A.

Revision 0 Page 43 of 46

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 6, 7, 8 & 9 Event

Description:

A High Vibrations, #1 EDG low voltage, Loss of Offsite power, #1 EDG output breaker trip, and #2 EDG loss of lube oil.

Time Position Applicant's Actions or Behavior BOP 6.8 Start desired loads on 2A3 not to exceed the following limits:

Any combination of Unit 1 and Unit 2 vital and non-vital buses may be energized as long as total load remains less than 4400 KW.

(4600 KW for 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />, 5320 KW for 30 minutes)

Potential Unit 1 and Unit 2 loads are as follows:

COMPONENT UNIT 1 LOAD UNIT 2 LOAD Att. E CHARGING PUMP N/A 50 KW SERVICE WATER PUMP 261 KW 640 KW HPI/HPSI PUMP 522 KW 420 KW LPI/LPSI PUMP 261 KW 340 KW SPRAY PUMP 186 KW 340 KW EFW PUMP 522 KW 500 KW PZR PROPORTIONAL HTRS N/A 0-180 KW ESF BUS 800 KW N/A Examiner Note: The crew should start a red train service water pump but use the loss of feedwater attachment to restore feedwater.

SRO Continue with OP-2202.008, Station blackout EOP.

Revision 0 Page 44 of 46

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 6, 7, 8 & 9 Event

Description:

A High Vibrations, #1 EDG low voltage, Loss of Offsite power, #1 EDG output breaker trip, and #2 EDG loss of lube oil.

Time Position Applicant's Actions or Behavior ANY 6. Verify the following valve handswitches in CLOSE:

A. Regen HX Outlet valve (2CV-4823-2).

B. Controlled Bleedoff valve (2CV-4847-2).

C. RCS Sample valves:

  • 2CV-1016-1 2CV-1066-1 ANY *7. Maintain adequate RCS Heat Removal by the following:

A. At least ONE SG level 10% to 90%.

B. At least ONE SG pressure 950 psia to 1050 psia by performing necessary steps of Manual Operation of Upstream Atmospheric Dump Valves Exhibit 2 of 2105.008, Steam Dump and Bypass Control System Operations.

ANY *8. Check SG levels greater than 22.2%.

Revision 0 Page 45 of 46

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2015-1 Scenario No.: 3 Event No.: 6, 7, 8 & 9 Event

Description:

A High Vibrations, #1 EDG low voltage, Loss of Offsite power, #1 EDG output breaker trip, and #2 EDG loss of lube oil.

Time Position Applicant's Actions or Behavior ANY 9. Verify the following for ALL XFMR Feeder Breakers:

A. Breaker handswitch is in PTL.

B. Breaker is open.

  • 2H13, SU #2 Feeder to 2H1
  • 2H14, Unit Aux Feeder to 2H1
  • 2H15, SU #3 Feeder to 2H1
  • 2H23, SU #2 Feeder to 2H2
  • 2H24, Unit Aux Feeder to 2H2
  • 2H25, SU #3 Feeder to 2H2
  • 2A111, SU #2 Feeder to 2A1
  • 2A112, Unit Aux Feeder to 2A1
  • 2A113, SU #3 Feeder to 2A1
  • 2A211, SU #2 Feeder to 2A2
  • 2A212, Unit Aux Feeder to 2A2
  • 2A213, SU #3 Feeder to 2A2 Procedure Caution:

Operation of loaded DG without SW flow for greater than 3 minutes may cause engine damage.

ANY *10. Evaluate operation of DGs as follows:

A. Check ANY DG running. (Not Met, Perform contingency)

BOP A. IF BOTH DGs failed to start, THEN GO TO Step 11.

Examiner Note: Step 11 is the step to restore power from the alternate EDG and it is a floating step listed earlier in the guide.

Termination criteria: Power restored to at least one 4160 volt vital bus or at the discretion of the lead examiner.

Revision 0 Page 46 of 46

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 48 of 114 2106.007 MAIN FEEDWATER PUMP AND FWCS OPERATION CHANGE: 054 13.8 WHEN desired to place MFWP speed controller (2HIC-0310) in AUTO, THEN perform the following:

13.8.1 Display Speed Demand Tracking on EITHER of the following:

Page 2 of MFRV controller (2HIC-0740)

PMS point (PMPDMDTB) 13.8.2 Slowly adjust demand on Feed Pump speed controller to match Speed Demand Tracking value within 1% output.

13.8.3 Place Feed Pump Speed controller (2HIC-0310) in AUTO.

13.8.4 Verify B Feed Reg Valve controller (2HIC-0740) returned to page 1.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 13 of 98 2102.004 POWER OPERATION CHANGE: 058 8.0 STARTUP MODE TO 20% POWER CAUTION R The following section has been determined to have a Reactivity A Addition Potential (RAP) and this activity is classified as a P Risk Level R1.

8.1 IF a Reactivity Management Brief has NOT been conducted, THEN perform a Reactivity Management Brief per COPD-030 with an SRO.

NOTE Steps in section 7.0 and 8.0 may be performed in any order as plant conditions allow.

Plant parameters may be monitored using Exhibit 2, Various Parameters Vs Reactor Power.

Boron adjustment data for power change may be obtained from Reactivity curves located in Plant Data book.

Applicable steps in this section would be performed following removal of Main Turbine Generator from grid with Reactor maintained critical.

8.2 Verify the following initial conditions:

RCS temperature within 2ºF of program value per Exhibit 1, TAVE VS TREF.

PZR pressure in TS band [If reduced pressure desired, then refer to Pressurizer Operations (2103.005)].

S/G levels ~ 60% with MFW in AUTO or MANUAL.

All required logs initiated per Mode Changes section of Unit Two Operations Logs (1015.003B).

{4.3.1}

8.3 During power escalation, use Attachment A of this procedure

  • for ASI control.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 14 of 98 2102.004 POWER OPERATION CHANGE: 058

  • 8.4 IF any Group 6 or P CEA RSPT inoperable due to spiking, T-Mod, etc.,

THEN refer to CPC/CEAC Operations (2105.001) to perform the following as required:

IF Group 6 or P must be inserted below 138.58 inches AND all inoperable RSPTs in group input to same CEAC, THEN place affected CEAC in INOP in all operable CPCs.

IF Group 6 or P must be inserted below 138.58 inches AND inoperable RSPTs in group input to BOTH CEACs, THEN perform the following:

- Place BOTH CEACs in INOP in ALL operable CPCs

- Restrict usage to Group 6 in accordance with TS 3.1.3.6.

IF Group 6 or P insertion required due to a transient condition before CEACs can be placed in INOP, THEN declare affected CEACs inoperable when group inserted below 138.58 inches.

8.5 Verify Turbine warm-up commenced using Turbine Generator Operations (2106.009).

CAUTION Failure to position the jack sleeve to neutral position can cause failure of valve to fully close during remote actuation.

(CR-ANO-2-2012-01432)

Neutral position is defined as alignment of the pointer on jack sleeve with neutral position indicator.

8.6 Verify Main Feedwater Regulating valves NOT jacked closed or pinned:

2CV-0748 2CV-0740 8.7 IF available, THEN idle second MFWP to minimize O2 ingress and enhance system reliability using Main Feedwater Pump and FWCS Operation (2106.007).

CRITICAL STEP 8.8 Commence raising power by performing the following as necessary:

Dilution using Chemical Addition (2104.003).

CEA withdrawal using CEDMCS Control System Operation (2105.009).

8.9 Monitor CPC Raw Powers using PQASI screen on PMS.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 15 of 98 2102.004 POWER OPERATION CHANGE: 058 NOTE At low powers, the CPC axial power distribution is based on a fixed, pre-calculated shape (canned value). When in use, the pre-calculated axial shape will result in CPC core average ASI (PID 268) reading approximately 1E-2. When raising power, the point at which CPCs change from using the pre-calculated axial shape to the real shape indicated by excore detectors is when raw excore power exceeds an average of 17%. When lowering power, CPCs will switch back to using a pre-calculated axial shape when raw power reaches an average of 14.5%. These power thresholds also correspond to the enabling and disabling of the PQASI auxiliary trip, respectively. CPC core average ASI (PID 268) may therefore be used as a secondary indication of whether the PQASI trip is enabled or disabled in a CPC channel.

  • 8.10 WHEN CPC Raw Power exceeds 3% (average of PID 10, 11 & 12),

THEN use PQASI (PID 266) for ASI control.

NOTE Consider ASI control prior to placing the turbine on line. If difficulty achieving + 0.45 > PQASI > - 0.45 is expected, consider leaving the turbine off line until PQASI is within limits. This may prevent holds at low turbine load which contribute to vibration problems.

8.11 WHEN BOTH conditions are met:

Reactor power greater than or equal to 4%

Turbine warming complete, THEN perform the following anytime during power escalation:

8.11.1 Roll and test Turbine Generator using Turbine Generator Operations (2106.009).

8.11.2 Synchronize and block load Turbine Generator using Turbine Generator Operations (2106.009).

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 16 of 98 2102.004 POWER OPERATION CHANGE: 058

  • 8.12 Maintain the following limits while Raising power using Turbine Generator Operations (2106.009) OR SDBCS:

Tref within +/- 2°F of program Tave (Exhibit 1, TAVE VS TREF).

Power escalation limits of Attachment A of this procedure.

NOTE During unit startup, RCS lithium out-of-spec hours commence 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after entering Mode 1 or at Xenon equilibrium, whichever occurs first.

8.13 WHEN Reactor power greater than 5%,

THEN perform the following: (N/A if Mode 2 was not entered)

Verify PMS Mode correct on Plant Mode Assignment (PMA).

Record entry into Mode 1 in Station log.

Make open item Station Log entry; RCS Lithium required to be within its proper control band within the next 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after entering Mode 1 or at Xenon equilibrium, whichever occurs first _______/_______.

Time Date Make Shift Relief Sheet entry; RCS Lithium required to be within its proper control band within the next 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after entering Mode 1 or at Xenon equilibrium, whichever occurs first _______/_______.

Time Date 8.14 Verify SDBCS aligned for power operation using Steam Dump and Bypass Control System Operations (2105.008).

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 17 of 98 2102.004 POWER OPERATION CHANGE: 058 8.15 Verify Emergency Feedwater NOT in service:

2P-7A 2P-7B 8.16 Verify Auxiliary Feedwater (2P-75) NOT in service.

8.17 Prior to exceeding 10% power, lock closed EFW Pumps Suction from S/U & Blowdown DI (2EFW-0706).

Verify 2EFW-0706 closed using indication on 2C33.

CAUTION QASI Aux Trip (PID 187) enabled by raw neutron flux average power of 17%

as calculated by: [(PID 10 + PID 11 + PID 12) 3].

Other power indications may read 4 to 5% lower than raw power.

If QASI > +/- 0.45 when raw power reaches 17%, CPC channel will trip.

CRITICAL STEP

{4.3.2} 8.18 Perform the following prior to exceeding 12% raw neutron flux average power on any CPC:

8.18.1 IF PQASI (PID 266) < +/- 0.4 on ALL operable CPCs, THEN power escalation may continue.

8.18.2 IF PQASI (PID 266) > +/- 0.4 on ANY operable CPC, THEN raise power as directed by Shift Manager and Reactor Engineering.

  • 8.18.3 IF PQASI (PID 266) NOT within +/- 0.45 on any operable CPC, THEN DO NOT exceed 14% power.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 18 of 98 2102.004 POWER OPERATION CHANGE: 058 8.19 WHEN BOTH conditions are met:

Above ~ 12% turbine power (8.5 psig cross-around pressure on Intermediate Pressure 2PI-0467)

Less than 15% turbine power (CR-ANO-2-2000-1065)

THEN perform the following to place Second Stage Reheater in service:

8.19.1 Open Scavenging valves:

2E-12A (2RS-46) 2E-12B (2RS-47) 8.19.2 Perform the following to open 2CV-0400 AND 2CV-0460:

A. Verify 2CV-0404/0464 Handswitch (2HS-0404) in AUTO.

B. Verify 2CV-0402 and 2CV-0462 closed with HS in AUTO:

2CV-0402 (2HIC-0402) (2E-12A) 2CV-0462 (2HIC-0462) (2E-12B)

C. IF 2CV-0402 and 2CV-0462 NOT closed in AUTO, THEN control in MANUAL using 2nd Stage Low Load Manual Control [Attachment F of Turbine Generator Operations (2106.009)].

D. Throttle open MSR Steam Supply valves using 2HS-0400 until intermediate position indicated:

2E-12A (2CV-0400) 2E-12B (2CV-0460)

E. WHEN 3 minutes have elapsed, THEN fully open MSR Steam Supply valves using 2HS-0400:

2CV-0400 2CV-0460 NOTE Step 8.20 should be performed in conjunction with step 8.22.1. Step 8.22.1 will allow calibration to be performed prior to 18%-20% power and within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of reaching 15% power as required by TS Table 4.3-1. This will allow COLSS indicated power to shift from Calibrated T to Secondary Cal Power for more stable and reliable conditions for calibration.

8.20 WHEN Reactor power between 15 and 20%,

THEN check Excore linear, CPC neutron, and CPC T powers between - 0.5% and + 10% of COLSS power.

IF any power indication out of spec, THEN record in Station log and initiate calibration per step 8.22.1 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 19 of 98 2102.004 POWER OPERATION CHANGE: 058 8.21 WHEN at ~ 17% Reactor power, THEN perform the following:

A /B /C /D 8.21.1 Check QASI Aux Trip (PID 187) enabled __/__/__/__

by checking EITHER of the following:

Average of PID 10, 11, and 12 greater than or equal to 17%

(displayed on PQASI screen for each channel).

ASI (PID 268) is calculating (vice reading a canned value of -1.0000E-2) for each channel.

8.21.2 Verify the following at FWCS Engineering Work Station (EWS):

ALL Signal RESETs on ALL Signal Validation Screens are Reset OR reason known and desired to continue.

NO unexplained alarms present.

KEY in OPERATE AND removed.

8.22 Stabilize Reactor power at 18% to 20% power (PID 177) while performing the following in any order:

8.22.1 Check Excore linear, CPC neutron, and CPC T powers between - 0.5% and + 10% of COLSS power.

IF any power indication out of spec, THEN record in Station log and initiate calibration within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Refer to Unit Two Operations Linear Power Adjustment (2305.051).

8.22.2 Complete CEA Position surveillance using CPC/CEAC Operations (2105.001).

8.22.3 Using Attachment D of this procedure, verify programmed CEA withdrawal for ALL fully withdrawn CEAs.

8.22.4 Verify COLSS Monthly Operability Test (2105.013, Supplement 1) completed within last 31 days (TS 4.2.3.c).

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 20 of 98 2102.004 POWER OPERATION CHANGE: 058 8.22.5 Verify ONE of the following:

Planar Radial Peaking Factor Verification (2302.005) completed within last 31 days of accumulated operation in Mode 1.

(TS 4.2.2.2.b)

IF Startup following a Refueling Outage, THEN Special Test Exception invoked.

(TS 3.10.2) 8.22.6 WHEN stable reactor power ( 2%) maintained for 15 minutes with minimal rod motion, THEN execute CHECK computer program using N9 on PMS.

8.22.7 IF any Incore detectors inoperable, THEN remove from scan using COLSS Operations (2105.013).

8.22.8 Verify the required number of Incore detectors operable with at least one operable Incore detector in each quadrant at each level per SAR section 7.7.1.1.7.

8.22.9 Verify required number of Incore detector locations operable per SAR section 7.7.1.1.7.

8.22.10 Verify sufficient operable Incore detectors to perform at least six tilt estimates with at least one estimate at each of three levels per SAR section 7.7.1.1.7.

8.22.11 IF COLSS Azimuthal Tilt calculation has NOT been verified by Reactor Engineering per TS 4.2.3.d within last 31 days, THEN notify Reactor Engineering to perform COLSS Aztilt Calculation using Azimuthal Power Tilt Verification (2302.056) prior to exceeding 20%

power.

8.22.12 Compare CPC Az Tilt Allowance (PID 063) to minimum allowable value using the formula below:

CPC PID 063 CV9008 + 1.005

___________ ________ + 1.005 8.22.13 IF ANY of the following conditions apply, THEN use Attachment I of this procedure to change Azimuthal Tilt constants:

Any CPC PID 063 less than COLSS Az Tilt plus 1.005. (required prior to exceeding 20% power)

COLSS Az Tilt NOT verified per TS 4.2.3.d.

(required prior to exceeding 20% power)

Desired to change CPC and COLSS Az Tilt constants. (performed at any steady state power)

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 21 of 98 2102.004 POWER OPERATION CHANGE: 058 CRITICAL STEP 8.23 Prior to exceeding 20% Reactor power, verify ASI being maintained within limits of TS 3.2.7.

8.24 Close ONLY the valves listed for 2C11 in Attachment G of this procedure.

8.25 IF normal startup (Special Test Exceptions NOT invoked),

THEN perform the following:

Commence plotting ASI.

Control ASI using Attachment A of this procedure.

IF BOTH conditions are met:

- CEA Group 6 or P inserted below LTSSIL

- Reactor power raised to 20%,

THEN record time on CEA Insertion Log (Form 2102.004A).

8.26 IF BOTH conditions are met:

Power Ascension is following refueling Special Test Exception 3.10.2 was invoked THEN perform the following prior to raising power above 20%:

Commence plotting ASI.

Check CEAs are at ARO unless required to prevent exceeding ASI limits (TS 3.2.7).

8.27 IF desired to transfer loads to Unit Aux, THEN verify the following for 6900v and 4160v Unit Aux Transformer Feeder breakers AND breaker racked up:

UA to 2A1 (2A-112) Danger tag removed.

2A-112 racked up.

UA to 2A2 (2A-212) Danger tag removed.

2A-212 racked up.

UA to 2H1 (2H-14) Danger tag removed.

2H-14 racked up.

UA to 2H2 (2H-24) Danger tag removed.

2H-24 racked up.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 22 of 98 2102.004 POWER OPERATION CHANGE: 058 8.28 Verify the following final conditions:

Reactor power ~ 20%

Tave at Tref +/- 2°F per Attachment C, RCS Temperature VS Reactor Power.

PZR level on setpoint per Attachment E, Pressurizer Level Program.

PZR pressure in TS band [If reduced pressure desired, then refer to Pressurizer Operations (2103.005)].

Two Condensate pumps and one MFWP feeding S/Gs.

CEDMCS in required mode for desired CEA operation and in OFF when motion complete.

All CEAs above LTSSIL or time that 20% power was reached recorded on CEA Insertion Log (Form 2102.004A).

All fully withdrawn CEAs positioned per Attachment D.

Hotwell level 38 to 94% per Hotwell Inventory Control section of Condensate and Feedwater Operations (2106.016).

Comments ______________________________________________________________

Performed By __________________________________________ Date __________

Supervisor ____________________________________________ Date __________

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 64 of 98 2102.004 POWER OPERATION CHANGE: 058 ATTACHMENT A PAGE 1 OF 10 REACTOR MANEUVERING RATES AND ASI CONTROL DURING MANEUVERS 1.0 PURPOSE This attachment provides guidance for controlling Axial Shape Index (ASI) and power escalation rates. General guidance that applies to power escalation or reduction is included in Section 3.0. Reactor maneuvering rates and ASI limits associated with reactor maneuvering rates are in Section 4.0. When raising power, ASI control is described in Section 5.0. When reducing power, ASI control is included in Section 6.0.

This Attachment satisfies NRC Commitment P9095.

2.0 DISCUSSION Raising or reducing Reactor power when above 20% power should be accomplished using dilution and boration for reactivity control when possible.

CEA Group 6 or P should be used for ASI control. ASI stability while changing power is dependent upon distribution of Xenon concentration in the core. Control of power escalation rates based on fuel preconditioning ensures there is reduced probability of fuel failures.

3.0 GENERAL GUIDELINES 3.1 Use ONE of the following to monitor ASI closely:

COLSS (CV9198)

IF COLSS inoperable, THEN use CPC channel ASI (PID 268) that most closely agreed with COLSS when it was operable.

Place COLSS ASI on PMS trend recorder with negative ASI assigned to upper scale and positive ASI assigned to lower scale.

3.2 WHEN operating above 20% power, THEN maintain ASI within TS 3.2.7 limits.

3.3 The following apply unless directed otherwise by this procedure:

Unless allowed by an approved Reactivity Plan, CEAs should be withdrawn and inserted in small frequent movements (less than or equal to 3 inches) rather than large movements.

Do NOT exceed CEA withdrawal of 10 inches in any 15-minute period.

After CEA movement, observe ASI for several minutes for any impact of CEA motion prior to additional motion.

3.4 IF any CPC DNBR margin (PID 107) drops to pretrip setpoint or 0.1 THEN consider performance of ONE or BOTH of the following:

Cease CEA insertion AND begin to borate CEAs back out slowly.

Reduce power to clear DNBR pretrip and maintain DNBR margin 0.1.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 65 of 98 2102.004 POWER OPERATION CHANGE: 058 ATTACHMENT A PAGE 2 OF 10 3.5 CEA Insertion Log (Form 2102.004A) shall be completed as applicable during operation from 20 to 100% with CEA Group 6 or P inserted below Long Term Steady State Insertion Limit (TS 3.1.3.6).

3.6 During power maneuvers refer to the following:

TS 3.1.3.6 COLR for Group 6 and P transient insertion limits 3.7 IF BOTH CEACs in INOP, THEN perform the following:

Use ONLY Group 6 for ASI control.

Maintain Group 6 above 127.5 inches per TS 3.1.3.6.b.

3.8 CEA Group 5 shall NOT be inserted for ASI control.

CAUTION During power distribution changes, COLSS DNBR and LPD POLs are considered critical parameters and should be monitored as such.

3.9 WHEN ASI >.05 from ESI, THEN monitor and trend COLSS POLs to ensure awareness of margin to Operating Limit.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 66 of 98 2102.004 POWER OPERATION CHANGE: 058 ATTACHMENT A PAGE 3 OF 10 4.0 REACTOR MANEUVERING GUIDELINES AND RATES NOTE Section 4.1 limits apply until 100% power maintained for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following initial power ascension.

  • The conditioned power is any power level that the current cycle core operated at for at least 72 cumulative hours in the last 7 days at power. Time spent at < 2% or subcritical is not considered operating at power.

Example of Conditioned Power* Level: Initial ascension from refueling reaches 68% and maintains for 2 days on either side of a day spent at 50%

(4 days total at 68%). Plant then trips from 68% and remains shutdown for 8 days. On re-start, conditioned power level is 68%.

4.1 Initial Power Ascension from Refueling 4.1.1 Reactor Engineering determine Conditioned Power* Level.

Conditioned Power* = _______________%

4.1.2 Determine the power ascension rate limit from the following table:

While the following conditions are true : The power ascension rate limit is:

Power is < 50% 15% / hour 50% Power < Conditioned Power* Per Table A-1 below.

3% / hour 7% over any 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> time period Conditioned Power* Power 10% over any 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> time period No single step change in power shall exceed 3%.

4.1.3 IF power is > 75% and ASI/ESI difference is > 0.03, THEN stop power ascension unless Reactor Engineering predicts magnitude of ASI swings following power ascension will remain within +/-0.03.

4.1.4 IF CEAs are being withdrawn during power ascension at

> 1%/hour and ANY of the following are true:

CEAs are being withdrawn above a position previously reached at power.

Power is > 50% and beyond the conditioned power level, THEN the rate of CEA withdrawal should be limited to 3 steps per hour. This limit may be increased to 6 steps per hour above 75% when needed to maintain ASI/ESI difference within 0.03.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 67 of 98 2102.004 POWER OPERATION CHANGE: 058 ATTACHMENT A PAGE 4 OF 10 4.2 Power Ascension After Extended ( 27 Days) Reduced Power Operation 4.2.1 Reactor Engineering determine Conditioned Power* Level.

Conditioned Power* = _______________%

NOTE

  • The conditioned power is any power level sustained for at least 72 cumulative hours in the last 30 days of operation at power. Time spent at < 2% or subcritical is not considered operating at power.

Example: Power for the month of March doesnt exceed 65% except on the 15th, 18th and 19th when minimum power is 80% each day. The plant is shutdown for significant repairs on March 30th. The forced outage lasts 35 days. On re-start, the conditioned power level is 80%.

4.2.2 Determine the power ascension rate limit from the following table:

While the following conditions are true: The power ascension rate limit is:

Power is < 50% 15% / hour 50% Power < Conditioned Power* Per Table A-1 below.

3% / hour Conditioned Power* Power 10% over any 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> time period No single step change in power shall exceed 10%.

4.2.3 IF power is > 75% and ASI/ESI difference is > 0.03, THEN stop power ascension unless Reactor Engineering predicts magnitude of ASI swings following power ascension will remain within +/-0.03.

TABLE A-1 ASI/ESI Difference Rate Limit 0.01 15%/hour

> 0.01 to 0.02 10%/hour

> 0.02 to 0.03 5%/hour 3%/hour (if allowed by

> 0.03 step 4.2.3)

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 68 of 98 2102.004 POWER OPERATION CHANGE: 058 ATTACHMENT A PAGE 5 OF 10 4.3 Power Ascension Following Mid-Cycle Shutdowns or Short Term (< 27 Days) Reduced Power Operation 4.3.1 IF power has been maintained 90% for at least 3 of the last 30 days of operation AT POWER, THEN the rate of power ascension is 15%/hour when operating at < 50% power and as shown in Table A-2 when > 50% power, ELSE apply the requirements of section 4.2.

TABLE A-2 ASI/ESI Difference Rate Limit 0.01 15%/hour

> 0.01 to 0.02 12%/hour

> 0.02 to 0.03 9%/hour

> 0.03 to 0.04 6%/hour

> 0.04 to 0.05 3%/hour (if allowed by step 4.3.2) 4.3.2 IF power is > 75% and ASI/ESI difference is > 0.05, THEN stop power ascension unless Reactor Engineering predicts magnitude of ASI swings following power ascension will remain within +/-0.05.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 69 of 98 2102.004 POWER OPERATION CHANGE: 058 ATTACHMENT A PAGE 6 OF 10 5.0 ASI CONTROL WHILE RAISING POWER CAUTION R The following section has been determined to have a Reactivity A Addition Potential (RAP) and this activity is classified as a P Risk Level R1.

5.1 IF a Reactivity Management Brief has NOT been conducted, THEN perform a Reactivity Management Brief per COPD-030 with an SRO.

5.2 During power escalation, it is desirable to maintain ASI within

+/- 0.01 of ESI. However, power escalation may continue provided TS ASI limits and power level rate limits of the preceding section are observed.

5.3 ASI Control Following Startup 5.3.1 Except at beginning of cycle with deep CEA insertions, ASI will always be negative upon startup. PQASI (CPC PID 266) should be monitored closely to ensure ASI is maintained within QASI aux trip limits. Steps 5.3.2 and 5.3.3 are guidelines intended to facilitate efficient control of ASI at low powers. These guidelines may otherwise be specified by Reactor Engineering. Maintaining PQASI within limits takes precedence over meeting the targets in steps 5.3.2 and 5.3.3.

5.3.2 IF PQASI (CPC PID 266) is equal to or more positive than -0.2, THEN use withdrawal of Group P and/or dilution to raise power and maintain PQASI within limits.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 70 of 98 2102.004 POWER OPERATION CHANGE: 058 ATTACHMENT A PAGE 7 OF 10 5.3.3 IF PQASI (CPC PID 266) is more negative than -0.2 THEN begin power escalation with Group P inserted to approximately 90 inches withdrawn.

Dilution and/or xenon decay (if a transient) should be used to raise power to less than or equal to 10%.

Insert Group 6 according to the following table:

Burnup (EFPD) Target Group 6 position at 10% power 325 Programmed Insertion Limit 325 140 inches 350 132 inches 375 124 inches 400 118 inches 425 110 inches 450 101 inches 475+ 90 inches Group 6 insertion to the above targets may proceed as quickly as normal control methods allow. The CEA position targets are predicted to result in PQASI being approximately -0.2 at 10% power.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 71 of 98 2102.004 POWER OPERATION CHANGE: 058 ATTACHMENT A Page 8 of 10 5.3.4 Above 10% power, as power rises, ASI will tend to become more positive requiring CEA withdrawal to control ASI.

IF Group P and Group 6 are inserted to control ASI, THEN withdraw CEAs as necessary to control ASI at desired target.

- Preference should be given to withdrawal of Group P prior to Group 6 to avoid PDIL curve problems at higher power levels.

- Preference should also be given to exiting long or short term steady state insertion limits.

Group P shall be above LTSSIL prior to exceeding 60% power to comply with TS 3.1.3.6.

Group P may be inserted up to limits established by COLR to control ASI.

5.3.5 IF power will be raised above 20%,

AND ASI outside required TS limit (3.2.7),

THEN hold power 20% and bring ASI within limits.

5.4 ASI Control While Raising Power Following Power Reduction IF following power reduction, CEAs (Group 6 or Group P) were partially inserted to control ASI, THEN power should be raised by dilution accompanied by CEA withdrawal to maintain ASI at ESI +/- 0.01.

IF Group P and Group 6 are used for ASI control, THEN withdraw CEAs as necessary to control ASI at ESI +/- 0.01 as a function of power level. Preference should be given to withdrawal of Group P prior to Group 6 to avoid PDIL curve problems at higher power levels.

Group P shall be above LTSSIL of TS 3.1.3.6 prior to exceeding 60%

power.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 72 of 98 2102.004 POWER OPERATION CHANGE: 058 ATTACHMENT A PAGE 9 OF 10 6.0 ASI CONTROL DURING POWER REDUCTION CAUTION R The following section has been determined to have a Reactivity A Addition Potential (RAP) and this activity is classified as a P Risk Level R1.

6.1 IF a Reactivity Management Brief has NOT been conducted, THEN perform a Reactivity Management Brief per COPD-030 with an SRO.

NOTE Except in cases where rapid Reactor power reduction required, the following general technique should be used for power reduction.

As power lowers, reduced temperature in top of core will cause ASI to shift toward top (negative). CEA insertion will be required to maintain ASI within control band.

CEAs should not be inserted below 80 inches withdrawn when the Reactor is at power and the CPC Aux trip is active. ASI would tend to shift back to the top of the core if CEAs are inserted more than halfway.

6.2 Power reduction rates should be chosen such that reactivity control with boration/dilution is not difficult. Shutdown from full power, particularly late in cycle, should not take longer than two hours to avoid difficulty with ASI control.

6.3 Unless otherwise directed by Reactor Engineering, the ASI target for maneuvering is as follows:

IF the magnitude of power reduction is small (< 10%)

AND reduced power will be maintained for short duration < 12hrs),

THEN ASI should be maintained within +/- 0.05 of pre-power reduction ESI (e.g., 100% power ESI).

IF the magnitude of power reduction is larger (> 10%)

OR reduced power will be maintained for longer duration (> 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and including shutdown),

THEN ASI should be controlled within +/- 0.05 of power dependent ESI.

NOTE Maintaining ASI within +/- 0.05 of ESI may become more difficult from mid to end-of-cycle resulting in operation outside this band. This is allowed during power reduction for shutdown provided TS ASI limits are observed.

6.4 As power lowered and ASI shifts negative, CEAs should be inserted to maintain ASI at ESI +/- 0.05.

Preference should be given to insertion of Group 6 prior to Group P to avoid PDIL curve problems if the cause for the power reduction is corrected and power is to be escalated.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 73 of 98 2102.004 POWER OPERATION CHANGE: 058 ATTACHMENT A PAGE 10 OF 10 6.5 Dilution may be required for ANY of the following:

Compensate for CEA insertion for ASI control.

Reduce rate of power reduction due to Xenon buildup.

Level power at final desired value.

6.6 WHEN final desired power level reached, THEN use CEAs to control ASI at selected ESI value using Attachment B.

6.7 IF rapid power reduction necessary, THEN perform the following:

6.7.1 Use CEA insertion to reduce power.

6.7.2 WHEN final desired power level reached, THEN use CEAs to control ASI at selected ESI value using Attachment B of this procedure.

PROCEDURE/WORK PLAN TITLE:

PROC./WORK PLAN NO. PAGE: 56 of 63 COPD-030 ANO REACTIVITY MANAGEMENT PROGRAM CHANGE: 009 EXHIBIT 1 COPD-030 Revised 4/11/2014 R1, R2 REACTIVITY BRIEF CHECKLIST Page 1 of 3 Repeat reactivity manipulations required to be done several times during the course of a shift do not require a re-brief using this checklist as long as the conditions established in the initial brief have not deviated.

This pre-job brief checklist covers the applicable elements of EN-HU-102 Pre-Job Brief Checklist Attachment 9.5 and provides further detail for this specific planned reactivity manipulation. The use of both checklists is not required.

___ WHAT ARE WE DOING?

Discuss the Reactivity Manipulation using the appropriate work plan or controlling document, including the following as necessary:

Reactivity Management Risk Level Classification is R1 or R2, or brief of this level is directed by the Supervisor.

Sequence of events and procedural hold points Any identified procedure issues are resolved with supervision prior to task performance Clear instructions are provided to perform task Review basic P&ID flowpath Limits and precautions and initial conditions Expected alarms during this evolution Summarize CRITICAL steps and expected results of the evolution (SAFER)

Conditional steps (i.e. IF or WHEN), identify these conditions and requirements How is system status verified prior to starting (1015.001, step 6.5)

How are manipulated components restored to their required position.

Positive reactivity additions are to be performed using one method at a time unless in accordance with an approved procedure or reactivity plan.

All planned reactivity manipulations (i.e. boric acid additions, primary water additions, and rod control movements) shall be verified / peer checked by one of the following: a licensed operator, a SRO, or a Shift Technical Advisor.

Actual or potential effect on reactivity Parameters to monitor and expected response, including monitoring frequency Identify plant parameters to be monitored and indications that will be used to ensure the reactivity changes observed are appropriate for the change made.

Continually monitor Reactor Power, Tave, and ASI (if applicable) for expected responses.

PROCEDURE/WORK PLAN TITLE:

PROC./WORK PLAN NO. PAGE: 57 of 63 COPD-030 ANO REACTIVITY MANAGEMENT PROGRAM CHANGE: 009 COPD-030 - EXHIBIT 1 Page 2 of 3

____ WHO IS RESPONSIBLE FOR WHAT?

Who is responsible for what (roles and responsibilities) including termination requirements and authority.

SM/CRS (SRO) permission is required for reactivity changes.

SM/CRS and operators involved with reactivity changes remain dedicated to that task.

Individuals discuss duties and responsibilities with their relief prior to turn over.

IF Reactor Engineering is assisting, THEN authority and responsibilities between Ops and Reactor Engineering personnel is delineated.

___ WHAT COULD GO WRONG? / CONTINGENCIES and DEFENSES Defenses to be used from Attachment 9.4 for R1 or R2 activity Summarize any critical steps - SAFER Anticipate error-likely situations - SAFER. Identify traps associated with this task and the tools used to combat each trap.

Limits (if reached) at which evolution shall be terminated Past problems/lessons learned/OE (Foresee consequences / Review Relevant OE - SAFER)

Any Abnormal Operating Procedures which might be required Contingency actions that may be required (Evaluate defenses - SAFER)

Human Performance Focus Area (HUPIG Hot Topic)

Are there procedures in progress that could affect this evolution?

Is there any reason (i.e. operational constraint) NOT to perform this task?

IF reactivity manipulations during turnover or briefings can not be avoided, THEN determine actions to minimize the distractions to individuals performing the reactivity changes.

Minimize or stop activities inside the Control Room area.

Restrict access to the at-the-controls area by installing Reactivity Manipulation In Progress signs.

Place phone shields in effect and consider notifying the non-Control Room watchstanders. What is the impact to reactor safety Evaluate plant risk and timing of the Reactivity Manipulation.

Discuss the importance of conservative decisions associated with Reactivity Manipulations.

Evaluate Integrated Plant Risk (EN-WM-104) and timing of the Reactivity Manipulation. Consider Mitigating Actions.

PROCEDURE/WORK PLAN TITLE:

PROC./WORK PLAN NO. PAGE: 58 of 63 COPD-030 ANO REACTIVITY MANAGEMENT PROGRAM CHANGE: 009 COPD-030 - EXHIBIT 1 Page 3 of 3

___ WHAT SAFETY AND/OR RADIATION PROTECTION PRECAUTIONS ARE NEEDED?

Identification and impact to personnel and overall plant safety Control of energy sources (electrical and mechanical)

Special precautions (chemical, fall hazard, hot surfaces, etc)

Radiation work permits and ALARA requirements Personnel protective equipment Accessing areas where safety issues not yet evaluated

___ REACTIVITY MANIPULATION EXPECTATIONS Pre-Evolution Checks:

SM and CRS (SRO) permission obtained.

Notify Control Room operators (ROs and STA).

Minimize or stop activities inside the Control Room.

Install Reactivity Manipulation In Progress signs.

Place phone shields in effect.

Consider notifying outside watchstanders Post Evolution Checks:

  • Remove Reactivity Manipulation In Progress signs as desired.

Notify CRS to remove phone shields as desired.

During steady state approximately 30 minutes after Reactivity Manipulation, inform SM/CRS that desired responses were obtained.

Prep. By: ZMU ANO-2 Cycle 24: 250 EFPD Power Ascension - Rev. 0 Rev. By:

Actual Conditions Shaded CVCS Group 6 Group P COLSS ASI Rel Time Time Power Acid GPM H20 GPM Actual Target Actual Target Actual Target Actual Comments 8/15/15 0:00 1.0 7 (109 Gal) 148 95 -0.081 8/15/15 0:15 4.0 3 (40 Gal) 148 98 -0.100 8/15/15 0:30 7.0 4 (59 Gal) 148 103 -0.130 8/15/15 0:45 10.0 3 (40 Gal) 148 106 -0.159 8/15/15 1:00 13.0 3 (49 Gal) 148 110 -0.190 8/15/15 1:15 15.0 1 (17 Gal) 148 113 -0.209 8/15/15 1:30 15.0 2 (28 Gal) 148 113 -0.210 8/15/15 1:45 15.0 2 (25 Gal) 148 113 -0.210 8/15/15 2:00 15.0 2 (28 Gal) 148 113 -0.209 8/15/15 2:15 15.0 2 (35 Gal) 148 113 -0.209 8/15/15 2:30 15.0 148 114 -0.209 Start Maneuver at Time: 8/15/15 0:00 Est. Gallons Water for Maneuver: 429 ESI @ Initial Condition: -0.081 Notes:

- Adjust dilution rates to raise / lower rate of power change.

- Predicted CVCS quantities are those needed to proceed from current to next time step.

- Target CEA positions & ASI predictions are tied to power level more than time.

- CEA positions are those expected to maintain ASI on target. Adjust CEAs as needed to maintain ASI on target.

- Predictions based on maintaining Tave @ Tref. It is acceptable to lead with either the Turbine or Reactor.

Critical Parameters (for heightened attention):

- Monitor CEA positions vs. power closely until Group P is clear of Long Term Steady State Insertion Limits.

- Monitor CPC PQASI closely at low power to avoid trip at +/- 0.45 Warnings:

- CPC QASI trips become active when raising power once the average of raw excore subchannel powers reaches 17% (or DKSUM=51).