ML11235A638

AN1-2011-08 Draft Operating Test

ML11235A638
Person / Time
Site:	Arkansas Nuclear
Issue date:	08/29/2011
From:	NRC Region 4
To:
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Download: ML11235A638 (251)

Text

ANO 2011 Simulator JPMs

Page 1 of 5 JOB PERFORMANCE MEASURE Unit:

1 Rev 0

Date JPM ID: A1JPM-RO-A0P37 System/Duty Area: Emergency and Abnormal Operations Task: Respond to Continuous Rod Withdrawal JTA# ANO1-RO-AOP-OFFNORM-15 KA Value RO 4.3 SRO 4.2 KA

Reference:

001 AAI .05 Approved For Administration To: RO X SRO X Task Location: Inside CR X Outside CR Both Suggested Testing Environment and Meth od (Perform or Simulate):

Plant Site: Simulator: Perform Lab:

Position Evaluated: RO:

SRO:

Actual Testing Environment: Plant Site Simulator Lab Testing Method: Perform Simulate Approximate Completion Time in Minutes:

2 Minutes Reference(s): 1203.003 Control Rod Malfunction Action Section 9 Continuous Control Rod Motion Examinees Name:

KCN:

Evaluators Name:

The Examinees 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

• Signature indicates this Date JPM has been compared to its applicable proc and is current with that revision. edure by a qualified individual (not the examinee)

Page 2 of 5 JPM ID: A1JPM-RO-A0P37 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner should verify that the examinee has been briefed per the JPM Examination Briefing Sheet EN-TQ-1 14 .5.

JPM INITIAL TASK CONDITIONS:

The reactor is 7% power. CS is in manual with CRD Diamo nd panel in AUTO. Control rods are withdrawing continuously.

TASK STANDARD:

AOP 1203.003 Section 9 Continuous Rod Motion section, is complete.

• • • This is an ALTERNATE PATH JPM***

TASK PERFORMANCE AIDS:

Copy of 1203.003 Section 9 Simulator Setup: 7% power The following commands active IMF RD269 (Continuous Rod Withdrawal)

IOR DI_ICCOO1919 FALSE IOR DO_ICCOO19G11 (1 0) FALSE IOR DO_ICCOO19W18 (1 0) TRUE Attach trigger I to desired button on remote control Simulator in FREEZE until examinee says ready to begin task.

Page 3 of 5 JPM ID: A1JPM-RO-A0P37 INITIATING CUE: The CRS/SM directs you to respond to a Continuous Contro l Rod Withdrawal per 1203.003 Section 9.

Simulator in FREEZE until examinee ready to begin task.

C PERFORMANCE CHECKLIST STANDARDS N/A SAT UNSAT

1. Verify the Reactor Demand H/A On panel C03, ICS Reactor Demand H/A station MANUAL. station placed in MANUAL POSITIVE CUE:

Reactor Demand H/A station in MANUAL (White Light On)

2. Verify the Diamond Panel in On the Diamond panel the MAN-AUTO MANUAL button is depressed and the MAN lamp C is illuminated.

POSITIVE CUE:

Diamond Panel station in MANUAL (MAN light backlit)

3. Determine of Rod Motion stops On Diamond panel, OUT motion light is checked and on C03 and/or Cl 3, rod POSITIVE CUE: position is monitored and determined OUT motion light is OFF on the that rod motion continues.

Diamond Panel. Group 7 Rods have stopped moving.

NEGATIVE CUE:

OUT motion light is ON on the Diamond Panel. Group 7 Rods continue to travel inward.

4. Check SY lamp energizing and de- On Diamond panel, status of SY lamp is energizing. checked POSITIVE CUE:

SY lamp is off

5. Verify the Diamond Panel in On the Diamond panel MAN lamp is MANUAL. illuminated.

POSITIVE CUE:

Diamond Panel station in MANUAL (MAN light backlit)

CONTINUED

Page 4 of 5 JPM ID: A1JPM-RO-A0P37 INSTRUCTORS CUE For this JPM, the GROUP-AUXIL button is defeated to provide the desired results. The assigned button on the simulator remote control must be depressed as the examinee depresses the GROUP-AUXIL button to provide the expected response (GROUP lamp off and AUXIL lamp on)

6. Set GROUP-AUXIL switch to On the Diamond panel, the GROUP AUXIL. AUXIL button is depressed and the AUXIL lamp is illuminated POSITIVE CUE:

AUXIL lamp is backlit on the GROUP AUXIL switch.

7. Set the SPEED SELECTOR to JOG On the Diamond Panel, the SPEED SELECTOR switch is rotated to the JOG POSITIVE CUE: position.

Speed selector switch is selected to JOG.

8. Place the manual command switch On the Diamond Panel, the manual in the INSERT position for 3 command switch (T-Handle) is placed in seconds AND return the manual insert for 3 seconds and then returned command to neutral to normal POSITIVE CUE:

Manual command switch is placed in INSERT for 3 seconds and returned to neutral.

9. Determine of Rod Motion stops On Diamond panel, OUT motion light is checked and on C03 and/or C13, rod POSITIVE CUE: position is monitored and determined OUT motion light is OFF on the that rod motion continues.

Diamond Panel. Group 7 Rods have stopped moving.

NEGATIVE CUE:

OUT motion light is ON on the Diamond Panel. Group 7 Rods continue to travel inward.

10. Trip the Reactor. On panel C03, the reactor trip C Pushbutton has been depressed.

POSITIVE CUE:

The reactor has been tripped INSTRUCTORS CUE When the reactor is tripped, the instructor will notify the Examinee the JPM is complete.

END

Page 5 of 5 JPM ID: A1JPM-RO-A0P37 INITIAL CONDITIONS:

The reactor is 7% power. ICS is in manual with CRD Diamond panel in AUTO. Control rods are withdrawing continuously.

INITIATING CUE:

The CRSISM directs you to respond to a Continuous Control Rod Withdrawal per 1203003 Section 9.

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE DOCUMENT NO. CHANGE NO.

TITLE: CONTROL ROD DRIVE MALFUNCTION ACTION WORK PLAN EXP. DATE NIA SAFETY-RELATED IPTE SET # EYES E]NO EJYES NO TEMP MOD LEVEL OF USE L:JYES NO CONTINUOUS REFERENCE INFORMATIONAL PROGRAMMATIC EXCLUSION PER EN-LI-iQO EYES__NO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distraction/Interruption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First Shift/Last Shift Knowledge Peer Pressure Procedures Change/Off Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY DATE TIME FORM TITLE: FORM NO. CHANGE NO.

VERIFICATION COVER SHEET 1000.006A 054

CHANGE 1203.003 CONTROL ROD DRIVE MALFUNCTION ACTION 024 PAGE 41 of 48 SECTION 9 CONTINUOUS CONTROL ROD MOTION ENTRY CONDITIONS One or more of the following:

• Continuous rod motion with NO command present

• FEEDWATER IS REACTOR LIMITED (K07-C2) annunciated

CHANGE 1203.003 CONTROL ROD DRIVE MALFUNCTION ACTION 024 PAGE 42 of 48 SECTION 9 CONTINUOUS CONTROL ROD MOTION

1. Verify the following:

• Reactor demand H/A station in MANUAL.

• Diamond panel in MANUAL.

A. IF rod motion stops, THEN GO TO ICS Abnormal Operation (1203.001).

2. IF SY lamp is energizing and de-energizing (indicating control rod or group motion),

THEN set SPEED SELECTOR switch to RUN.

A. IF control rod motion stops, THEN contact I&C and SYE for assistance.

3. IF control rod motion continues, THEN perform the following:

A. Verify diamond panel in MANUAL.

B. Set GROUP-AUXIL switch to AUXIL.

C. Set SPEED SELECTOR switch to JOG.

D. Place manual command switch in the INSERT for 3 seconds AND return manual command to neutral.

4. IF control rod motion continues THEN perform the following:

A. Trip reactor.

B. Refer to Emergency Operating Procedure (1 202.XXX).

END

Page 1 of 4 JOB PERFORMANCE MEASURE Unit: 1 Rev # 0 Date:

JPM ID: A1JPM-RO-RPSO8 System/Duty Area: Reactor Protection System Task: Perform Reset of Anticipatory Reactor Trip System (ARTS) for Main Feedwater Pump JTA# ANO1 -RO-RPS-NORM-1 KA Value RO 3.3 SRO 3.3 KA

Reference:

012 A4.04 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: Plant Site Simulator Lab Testing Method: Perform Simulate Approximate Completion Time in Minutes: 10 Minutes Reference(s): 1102.002 Plant Startup (Attachment E)

Examinees Name: KCN:

Evaluators Name:

The Examinees 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.

Page 2 of 4 JPM ID: A1JPM-RO-RPSO8 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner should verify that the examinee has been briefed per the JPM Examination Briefing Sheet EN-TQ-1 14 .5.

JPM INITIAL TASK CONDITIONS:

A plant startup is in progress. Power is 2% and the first main feedwater pump has just been placed in service and the Auxiliary feedwater pump has been secured.

TASK STANDARD:

The ARTS is reset for the first main feedwater pump in the A RPS cabinet.

TASK PERFORMANCE AIDS:

1102.002, Attachment F

Page 3 of 4 JPM ID: A1JPM-RO-RPSO8 INITIATING CUE: The CRS/SM directs you to RESET RPS ARTS for the A MFW pump in the A RPS channel per 1102.002 Attachment E.

UN C PERFORMANCE CHECKLIST STANDARD N/A SAT SAT NOTE: Performance of the concurrent verification will be simulated.

1 Obtain SRO/RO Concurrent Verification of steps.

RO/SRO Concurrent Verifier is POSITIVE CUE:

available.

A RO/SRO is available to perform concurrent verification.

2. Depress test switch labeled RESET on the contact On the contact buffer lower buffer lower module for the A MEW pump.

C module in the A RPS cabinet for the A MFW Pump, RESET POSITIVE CUE:

switch is depressed.

Test switch labeled RESET is depressed.

3. Verify two red lights on the contact buffer change Observe and verify the two red state.

lights on the contact buffer for the A MEW pump change state.

POSITIVE CUE:

The top light comes on and the Top red light comes on and the bottom red light goes bottom light goes off.

off.

4. Verify the white light MEWP A TRIPPED goes Observe the white light on the DIM MEWP A TRIPPED status module changes from BRIGHT to POSITIVE CUE:

DIM.

White light on MEWP A TRIPPED goes DIM END

Page 4 of 4 JPM ID: A1JPM-RO-RPSO8 INITIAL CONDITIONS:

A plant startup is in progress. Power is 2% and the first main feedwater pump has just been placed in service and the Auxiliary feedwater pump has been secured.

INITIATING CUE:

The CRSISM directs you to reset RPS ARTS for the A MFW pump in the A RPS channel per 1102002 Attachment E.

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE DOCUMENT NO. CHANGE NO.

TITLE: PLANT STARTUP WORK PLAN EXP. DATE N/A SAFETY-RELATED IPTE SET # YES LJNO DYES NO TEMP MOD LEVEL OF USE DYES NO CONTINUOUS fl REFERENCE E INFORMATIONAL PROGRAMMATIC EXCLUSION PER EN-LI-100 DYES__NO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distraction/Interruption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First ShiftlLast Shift Knowledge Peer Pressure Procedures Change!Off Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY DATE TIME FORM TITLE: FORM NO. CHANGE NO.

VERIFICATION COVER SHEET 1000.006A 054

ATTACHMENT E Page 1 of 6 ANTICIPATORY REACTOR TRIP SYSTEM (ARTS) RESET 1.0 WHEN first Main Feedwater Pump is placed into service, THEN perform the following to reset RPS ARTS trip:

Dare/Time 1.1 In RPS Channel A Cabinet (C41) perform the foliowirg:

1.1.1 Obtain SRO/RO Concurrent Verification of steps p in this subsection.

1.1.2 Depress test switch labeled RESET on contact buffer lower module for the starred Main Feedwater Pump.

1.1.3 Verify two red lights on contact buffer change state (top comes ON, bottom goes OFF) 1.1.4 Verify white light MFWP A (B) TRIPPED (for the started MFWP) goes DIM.

In RPS Channel B Cabinet (C42) perform the following:

1.2.1 Obtain SRO/RO Concurrent Verification of steps in this subsection.

1.2.2 Depress test switch labeled RESET on contact buffer lower module for the started Main Feedwater Pump.

1.2.3 Verify two red lights on contact buffer change state (top comes ON, bottom goes OFF) 1.2.4 Verify white light MFWP A (B) TRIPPED (for the started MFWP) goes DIM.

In RPS Charnel C Cabinet (C43) perform rhe folLowing:

1.3.1 Obtain SEC/Re Concurrent Verification of steps in this subsection.

1.3.2 Depress test switch labeled RESET on contact buffer lower module for the started Main Feedwater Pump.

1.3.3 Verify two red lights on contact buffer change state (top comes ON, bottom coes OFF) 1.3.4 Verify white light MFWP A (B) TRIPPED (for tOe started MFWP) goes DIM.

FPROCJWORK PLAN NO. PROCEDURE!WORK PLAN TITLE: 122 of 186 PAGE:

[ 1102.002 PLANT STARTUP ATTACHMENT H CHANGE: 090 Paoe 2 of 6 1.4 In RPS Channel C Cabinet (C44) perform the following:

1.4.1 Obtain SRO/RO Concurrent Verification of steps p in this subsection.

1.4.2 Depress test switch labeled RESET on contact buffer lower module for the started MaO Feedwater Pump.

1.4.3 Verify two red lights or contact buffer change state (top comes ON, bottom goes OFF) 1.4.4 Verify white light MFWP A (B) TRIPPED (for the started MFWP) goes DIM.

NOTE Independent Verification is performed by a different operator than the one that reset the ARTS trip.

2.0 Perform independent verification of ARTS reset for first Main Peedwater Pump placed into service as follows:

2.1 In RPS Channel A Cabinet (C41), verify:

2.1.1 Contact buffer for the started Main Feedwater pump has top red light ON.

2.1.2 White light MFWP A (B) TRIPPED (for the started Main Feedwater pump) is DIM.

2.2 In RPS Channel B Cabinet (C42), verify:

2.2.1 Contact buffer for the started Main Feedwater pump has top red light ON.

2.2.2 White light MFWP A (B) TRIPPED (for the started Main Feedwater pimp) is DIM.

2.3 In RPS Channel C Cabinet (C43), verify:

2.3.1 Contact buffer for the started Main Feedweter pump has pp red light ON.

2.3.2 White light MEMP A (B) TRIPPED (for the started Main Feedwater pump) is DIM.

2.4 In RPS Charnel C Cabinet (C44), verify:

2.4.1 Contact buffer for the started Main Feedwater pump has top red light ON.

2 . 4 .2 White licht MEW? A (3) TRIPPED (for the started Main Feetwater ptp)

i PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

PAGE: 123 of 1102.002 PLANT STARTUP CHANGE: 090 1861 ATTACHMENT E Page 3 of 6 3.0 WHEN Main Turbine startup is complete, AND generator is ready to be loaded, THEN perform the following to reset RPS ARTS trip:

Date/Time CAUTION Depressing TRIP switch will trip the channel even if turbine trip is bypassed.

3.1 Perform the following to reset RPS trips In RPS Chnl A Cabinet (C4l) 3.1.1 Depress test switch labeled RESET on contact buffer lower module for main turbine.

3.1.2 Verify two red lights on contact buffer change state (top comes ON, bottom goes OFF) 3.1.3 Verify white light turbine tripped goes DIM.

3.2 Perform the following to reset RPS trip in RPS Chnl B Cabinet (C42) 3.2.1 Depress test switch labeled RESET on contact buffer lower module for main turbine.

3.2.2 Verify two red lights on contact buffer change state (top comes ON, bottom goes OFF) 3.2.3 Verify white light turbine tripped goes DIM.

3.3 Perform the following to reset RPS trip in RPS Chnl C Cabinet (C43) 3.3.1 Depress test sw.itch labeled*RESET on contact buffer lower :odule for main turbine.

3.3.2 Verify two red lights on contact buffer change state (top comes ON, bottom goes OFF) 3.3.3 Verify white light turbine tripped goes DIM.

3.4 Perform the ft:Ilowing to reset PPS trip in P25 Chin D Cabinet (C44) 3.4. 1 Depress test switch labeled RESET on contact buffer lower nodule for main turbine.

3.4.2 Verify two red lights on contact buffer change state (top comes ON, bottom goes OFF) 3.4.3 Verify white light turbine tripped goes DIM.

ATTACHMENT E Pane 4 of 6 NOTE Independent verification is performed by a different operator than the one that reset the ARTS trip.

4.0 Perform independent verification of ARTS reset for Main Turbine as follows:

4.1 In RPS Channel A Cabinet (C4l) verify:

4.1.1 Contact buffer for main turbine has top red light on.

4.1.2 White light turbine tripped is DIM.

4.2 In RPS Channel B Cabinet (C42) verify:

4.2.1 Contact buffer for main turbine has top red light on.

4.2.2 White light turbine tripped is DIM.

4.3 In RPS Channel C Cabinet (C43) verify:

4.3.1 Contact buffer for main turbine has top red light on.

4.3.2 White light turbine tripped is DIM.

4.4 In RPS Channel D Cabinet (C44) verify:

4.4.1 Contact buffer for main turbine has top red light on.

4.4.2 White lioht turbine tripped is DIM.

ATTACHMENT E Page 5 of 6 5.0 IF second Main Feedwater Pump is in-service, TI-EN perform the following to reset RPS ARTS trip:

Date/Time 5.1 In RPS Channel A Cabinet (C41) perform the following:

5.1.1 Obtain SRO/RO Concurrent Verification of steps p in this subsection.

5.1.2 Depress test switch labeled RESET on contact buffer lower module for the started Main Feedwater Pump.

5.1.3 Verify two red lights on contact buffer change state (top comes ON, bottom goes OFF) 5.1.4 Verify white light MFP A (B) TRIPPED (for the started MFP) goes DIM.

In R?S Channel B Cabinet (C42) perform the following:

5.2.1 Obtain SRO/RO Concurrent Verification of steps p in this subsection.

5.2.2 Depress test switch labeled RESET on contact buffer lower module for the started Main Feedwater Pump.

5.2.3 Verify two red lights on contact buffer change state (top comes ON, bottom goes OFF) 5.2 .4 Verify white light V A (B) TPIPPED (for the started MFP) goes DIM.

In RPS Channel C Cabinet (C43) perform the following:

5.3.1 Obtain SFO/RO Concurrent Verification of steps it this subsection.

5.3.2 Depress test switch labeled RESET on contact buffer lower module for the started Main Feedwater Pump.

Verify two red lights or. contact buffer change state (top cones ON, bottom goes OFF) 5.3.4 Verify white light MFP A (B) TRIPPED (for the started MFP) goes DIM.

f PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

I PAGE: 126 of 186 1102.002 PLANT STARTUP CHANGE: 090 ATTACHMENT E Page 6 of 6 5.4 In R?S Channel D Cabinet (C44) perform the following:

5.4.1 Obtain SRO/RO Concurrent Verification of steps in this subsection.

5.4.2 Depress test switch labeled RESET on contact buffer lower module for the started Main Feedwater Pump 5.4.3 Verify two red lights on contact buffer change state (top comes ON, bottom goes OFF) 5.4.4 Verify white light ME? A (B) TRIPPED (for the started ME?) goes DIM:.

NOTE Independent verification is performed by a different operator than the one that reset the ARTS trip.

6.0 Perform independent verification of ARTS reset for second Main Feedwater Pump placed into service as follows:

6.1 In RPS Channel A Cabinet (C41) verify:

6.1.1 Contact buffer for the started: Main: Feedwater pump has top reo lrgnt ON.

6.1.2 White light MFP A (B) TRIPPED (for the started Main Feedwater pump) is DIM.

6.2 In RPS Channel B Cabinet (C42) verify:

6.2.1 Contact buffer for the started Main: Feedwater pump has top red light ON.

6.2.2 White light ME? A (B) TRIPPED (for the started Main Feedwater pump) is DIM.

In R?S Channel C Cabinet (C43) verify:

6.3.1 Contact buffer for the started Main Feedwater pump has top red light ON.

White light MF? A (B) TRIPPED (for the started 1am 6.3.2 Feedwater pump) fs DIM.

6.4 In RPS Channel D Cabinet (C44) verify:

6.4.1 Contact buffer for the started Main Feedwater pump has top red lioht ON.

Whine lfght ME? A B) TRIPPED (for the started Main Feedwater Pump) is ]..DIM.

Page 1 of 4 JOB PERFORMANCE MEASURE Unit: 1 Rev # 1 Date:

JPM ID: A1JPM-RO-MUP06 System/Duty Area: Makeup and Purification Task: Perform RCS Delithiation JTA# ANO1 -RO-MU P-NORM-38 KAValue RO 3.0 SRO 3.0 KA

Reference:

004 A1.11 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: Plant Site Simulator Lab Testing Method: Perform Simulate Approximate Completion Time in Minutes: 5 Minutes Reference(s): 1104,002 MAKEUP & PURIFICATION SYSTEM OPERATION, Section 10.6 Examinees Name: KCN:

Evaluators Name:

The Examinees 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

Page 2 of 4 JPM ID: A1JPM-RO-MUPO6 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner should verify that the examinee has been briefed per the JPM Examination Briefing Sheet EN-TQ-l 14 .5.

JPM INITIAL TASK CONDITIONS:

The plant is in Mode 1. Chemistry samples require that a 10 minute RCS delithiation be performed. The difference between RCS boron and the delithiating DI is 5 ppm.

This is an Alternate Path JPM.

TASK STANDARD: Non-delithiating DI returned to service after placing the delithiating DI into service before makeup tank level lowers by >5 inches.

TASK PERFORMANCE AIDS: 1104.002 MAKEUP & PURIFICATION SYSTEM OPERATION, Section 10.6 SUGGESTED SIMULATOR SETUP:

Model. The Delithiating Letdown DI T-36A/B manual outlet valve is mispositioned (CR-ANO-1-2007-01710) in the closed position: IRF MU8A 0 or IRF MU8B 0

Page 3 of 4 JPM ID: A1JPM-RO-MUP06 10.6.

INITIATING CUE: The SM/CRS directs you to perform a 10 minute RCS delithiation per 1104.002 Section PERFORMANCE CHECKLIST STANDARD N/A SAT UNSAT C

1. Open inlet to delithiating DI:

• T-36A Purif Demineralizer Inlet (CV-i 244)

• T-36B Purif Demineralizer Inlet On panel C04, opened inlet control C (CV-1245) valve to the de-lithiating DI (CV-1244 or CV-1245).

POSITIVE CUE:

Red light ON, green light OFF for delithiating DI.

2. Close inlet to previously in-service Dl (CV-1244 or CV-1245). On panel C04, closed inlet control C valve to the non de-lithiating Dl (CV-POSITIVE CUE 1244 or CV-1245).

Green light ON, red light OFF for non de-lithiating DI.

3. Observe that letdown flow is approximately equal to previous value. Observed abnormal letdown flow and pressure on panel C09 (Fl-i 236JPl-NEGATIVE CUE: 1237).

Letdown pressure is cycling erratically on P1-1237 on C04.

4. Swap back to the previously in-service Dl as follows:

4a. Open inlet to previously in-service Dl (CV-1244 or CV-1245). Before makeup tank level lowered by C >5 inches, opened inlet to previously POSITIVE CUE in-service DI (CV-i244 or CV-1245).

Red light ON, green light OFF for previously in-service DI.

Close inlet to delithiating Dl (CV-1244 or CV-1245).

Closed inlet to delithiating DI POSITIVE CUE: (CV-1244 or CV-1245).

Green light ON, red light OFF for Delithiating Dl inlet valve.

Examinee should inform CRS that task cant be completed. JPM complete.

END

Page 4 of 4 Al JPM-RO-MUPO6 INITIAL CONDITIONS:

The plant is in Model. Chemistry samples require that a 10 minute RCS delithiation be performed. The difference between RCS boron and the delithiating Dl is 5 ppm.

INITIATING CUE:

The SMICRS directs you to perform a 10 minute RCS delithiation per 1104.002 Section 10.6.

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE TITLE: MAKEUP & PURIFICATION SYSTEM DOCUMENT NO CHANGE NO.

1104.002 071 OPERATION WORK PLAN EXP. DATE REACTIVITY IMPACT N!A DYES ØINPR DNO SAFETY-RELATED IPTE SET # EYES DNO DYES DNO TEMP MOD LEVEL OF USE DYES NO CONTINUOUS C REFERENCE C INFORMATIONAL PROGRAMMATIC EXCLUSION PER EN-LI-i 00 DYES__NO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distractionllnterruption Questioning Attitude Multiple Tasks Placekeeping Overconfidence Self Check Vague or Interpretive Guidance Peer Check First Shift/Last Shift Knowledge Peer Pressure Procedures Change/Off Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY DATE TIME FORM TITLE: FORM NO. CHANGE NO.

VERIFICATION COVER SHEET 1000.006A 055

[

PROC.!WORK PLAN NO PROCEDUREIWORK PLAN TITLE:

PAGE: 63 of 375 1104.002 MAKEUP & PURIFICATION SYSTEM OPERATION CHANGE: 071 10.6 RCS Delithia:io:n NOTE A: all nines, placing an idle DI into service may result in a change in RCS/Decay Heat boron concentration and potentially impact reactivity.

10.6.1 Obtain total desired delithiation time from Chemistry.

10.6.2 IF the reactor is critical, THEN delithiate per one of the following methods:

NOTE

• 2.5 minutes bounds the maximum expected transient of 4% power for the operation of an unborated DI with the effluent assumed to be pure water per ER OlOll5ElOl.

• Idle DI operation at power should be restricted to <2.5 minutes when actual difference between RCS and DI is >50 ppma or idle DI boron concentration is not known.

• Operating experience: T36A boron was 2600 ppm with RCS boron at 1530 ppm. T36A was periodically placed into service for RCS delithiation over a three day period, for a total of 110 minutes. Dilution of 20 ppm was required to compensate for the resulting RCS horation. From that point, T36A operation had no further impact on rod motion and Chemistry verified <50 ppmB difference between T-36A and the RCS.

A. IF the difference of RCS boron and delithiating DI is

>50 ppm, OR de lithiating DI boron concentration is NOT known, THEN perform the fcllowing:

An unborated or underborated DI dilutes the RCS while inservice.

CAUTION

1. Swap DI5 as follows:

a. Open inlet to delithiating DI:

• T36A Punif Demineralizer Inlet (CVl244)

• T3*6B HurSt Demneralizer Inlet (C7l245)

b. Close inlet to previously inservice DI:

• T36A Punt Demineralizer Inlet (CVl244)

• T363 Punt Demineralizer Inlet (CV1245)

2. Check that letdown flow is approximately equal to previous value.

PROCJWORK PLAN NO. PROCEDIJREIWORK PLAN TITLE: PAGE: 64 of 375 1104.002 MAKEUP & PURIFICATION SYSTEM OPERATION CHANGE: 071

3. WHEN no more than 2.5 minutes have elapsed, THEN swap back to the previously inservice SI as follows:

a. Open inlet to previously inservice DI:

• T36A Purif Demineralizer Inlet (CV1244)

• 36B Purif Demineralizer Inlet (CVl245)

b. Close inlet to delithiating DI:

• T36A Purif Demloeralizer Inlet (CVl244)

• T36B Purif Dernineralizer Inlet (CVl245)

4. Check that letdown flow is approximately equal to previous value.

5. Allow plant to stabilize and then repeat steps 1 through 4 as required to achieve total delithiation time.

Record completion of delithiation in the Station Log.

B. IF difference of RCS boron and delithiating DI

<50 ppm, THEN perform the following:

1. Swap DIs as follows:

a. Open inlet to delithiating DI:

• T36A Purif Demineralizer Inlet (CVl244)

• T36B Purif Demineralizer Inlet (CV1245)

b. Close inlet to previously inservice DI:

• T36A Purif Demineralizer Inlet (CV-1244)

• T36B Purif Demineralizer Inlet (CV1245)

2. Observe that letdown flow is approximately equal to prevocus value.

PROCJWORK PLAN NO, PROCEDURE/WORK PLAN TITLE: PAGE: 65 Of 375 1104.002 MAKEUP & PURIFICATION SYSTEM OPERATION CHANGE: 071 i

3. WHEN recommended delithiation time is complete, THEN swap. back to the previously inservice tI as follows:

a. Open inlet to previously inservice DI:

• T36A ?urif Den.ineralizer Inlet (CV1244)

• T36B ?urif Denineralizer Inlet (CV1245)

b. Close inlet to dellthiatlng DI:

• T36A Punt Demlneralizer Inlet (CVl244)

• T363 Purif Demineralizer Inlet (CVl245)

4. Record completion of delithlation in the StatIon Log.

NOTE At all times, placing an idle DI into service nay result in a change in RCS boron concentration and potentially impact reactivity.

10.6.3 IF shutdown, THEN delithiate as directed by Chemistry.

Page 1 of 5 JOB PERFORMANCE MEASURE Unit: 1 Rev # 5 Date:

JPM ID: A1JPM-RO-EOP15 System/Duty Area: Abnormal and Emergency Operations Task: Perform Reactor Trip Immediate Actions with a Loss of DOl JTA# ANO1-RO-AOP-OFFNORM-326 KA Value RO 3.4 SRO 3.5 KA

Reference:

058 Ml .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: Plant Site Simulator Lab Testing Method: Perform Simulate Approximate Completion Time in Minutes: 3 Minutes Reference(s): 1202.001 Reactor Trip and 1203.036 Loss of 125V DC Section 1 Loss of DOl Examinees Name: KCN:

Evaluators Name:

The Examinees 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 exam inee) and is current with that revision.

Page 2 of 5 JPM ID: A1JPM-RO-EOP15 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner should verify that the examinee has been briefed per the JPM Examination Briefing Sheet EN-TQ-1 14 .5.

JPM INITIAL TASK CONDITIONS:

The reactor has just tripped from 100% power and you are the only control board operator present.

TASK STANDARD:

Loss of DO1 recognized and Dli power swapped to emergency source. This is a faulted JPM. Alternate Success Path used due to loss of DO1.

TASK PERFORMANCE AIDS:

1202.001 Reactor Trip immediate actions and 1203.036 Loss of 125V DC Section 1 Loss of DOl.

SUGGESTED SIMULATOR SETUP:

Have the simulator at power operations (>55% power) and then insert malfunction for a Loss of DOl. Freeze the simulator as soon as the reactor trips. Go to run when the examinee is ready to take his first action.

Page 3 of 5 JPM ID: A1JPM-RO-EOP1 5 INITIATING CUE: The CRS/SM directs you to perform immediate actions for a Reactor Trip.

UN C PERFORMANCE CHECKLIST STANDARD N/A SAT SAT

1. Manually trip the reactor. Verify all rods inserted and reactor power dropping.

Depressed reactor trip pushbutton on panel C03 and verified rods POSITIVE CUE:

inserted/power dropping.

All rod bottom lights ON for groups 1-7, reactor power lowering.

2. Manually trip the Turbine. Verify Turbine throttle and governor valves closed.

Depressed turbine trip pushbutton C FAULTED CUE: on COl and identified that the turbine did not trip due to a loss of Governor and throttle valves are all open. Turbine trip DOl.

solenoid power available light is off. Breaker position indications on left side of ClO are off.

INSTRUCTOR NOTE:

Transferring Dli to the emergency power supply is a follow-up action of 1203.036. Therefore, 1203.036 may be referenced for this step. When the examinee identifies the loss of DOl act in the role of CRS to direct the examinee to transfer Dli to its emergency power supply.

At ClO, transferred 125 VDC

3. Transfer Dli to its emergency power supply.

panel Dii to its emergency momentarily placing supply by 125 VDC Panel Dii Power POSITIVE CUE:

Supply Select switch to EMERG Di 1 is powered from D02.

position.

4. If SG pressure is <900 psig, then actuate MSLI for If SG pressure dropped below affected SC(s) AND actuate EFW.

900 psig, actuated MSLI for POSITIVE CUE: affected SG(s) and EFW on the remote matrices on C09.

SG pressures at 1000 psig.

Page 4 of 5 JPM ID: A1JPM-RO-EOP15 C PERFORMANCE CHECKLIST STANDARD N/A SAT NOTE: Step 4 above is NOT a critical step because EFIC will automatically actuate MSLI/EFW at 600 psig SG pressure which will terminate the overcooling event. IF the examinee transfers Dli to D02 the turbine will trip and terminate the overcooling event in step 3 of this JPM.

5. Check adequate sub cooling margin. On panel C04 or on ICCMDS display on panel C19, POSITIVE CUE: observed/verified that SCM is SCM at 65°F and rising, adequate (>30°F).

Note: The examiner should cue the JPM is over after SCM is verified adequate.

END

Page 5 of 5 JPM ID: A1JPM-RO-EOP15 INITIAL CONDITIONS:

The reactor has just tripped from 100% power and you are the only control board operator present.

INITIATING CUE:

The CRSISM directs you to perform immediate actions for a Reactor Trip.

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE DOCUMENT NO, CHANGE NO.

TITLE: LOSS OF 125V DC 1203.036 009 WORK PLAN EXP. DATE NIA SAFETY-RELATED IPTE SET # YES EIN0 DYES NO TEMP MOD LEVEL OF USE DYES ØNO CONTINUOUS Q REFERENCE Ei INFORMATIONAL PROGRAMMATIC EXCLUSION PER EN-LI-100 DYES__ZNO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distraction/Interruption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First ShiftlLast Shift Knowledge Peer Pressure Procedures Change/Off Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY DATE TIME FORM TITLE: FORM NO. j CHANGE NO.

VERIFICATION COVER SHEET 1000.006A 054 j

I I 1

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

PAGE: 2 of 44 1203.036 LOSS OF 125V DC CHANGE: 009 SECTION 1 LOSS OF DOl 1 . 0 SYMPTOMS 1.1 Low DC voltage alarms:

(alarms inoperable if generator output breakers open)

• D01 UNDERVOLTAGE (K01-A7)

• Dli LOSS OF VOLTAGE (K0l-B7)

• RA1 LOSS OF VOLTAGE (K0l-C7)

• DOl TROUBLE (KOl-D7)

• HI DC CONTROL POWER OFF (K02-B4)

• Al DC CONTROL POWER OFF (K02-C6)

• A3 DC CONTROL POWER OFF (K02-D6)

• SU 1 L.O. RELAY DC FAILURE (K02-Dl)

• SU 2 L.O. RELAY DC FAILURE (K02-E3)

• GENERATOR L.O. RELAY DC FAIlURE (K04-DS)

• TURBINE L.O. RELAY DC FAILURE (K04-B5)

• EOS SYSTEM TROUBLE (K04-C5) 1.2 Loss of breaker position indicator lights for plant buses on left side of ClO.

1.3 Trip Solenoid Power Available light on COl NOT lit.

2.0 IMMEDIATE ACTION NONE 3.0 FOLLOW-UP ACTIONS 3.1 At ClO, transfer Dli to EMERG SUPPLY D02.

3.2 IF reactor trips, THEN perform the following:

3.2.1 IF SG pressure is <900 psig, THEN perform the following on BOTH SGs:

• Actuate MSLI

• Actuate EFW 3.2.2 Perform RT-6.

3.2.3 Perform Emergency Operating Procedures (1202.XXX) in conjunction with this procedure.

[

PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

PAGE: 3 of 1203.036 LOSS OF 125V DC CHANGE: 009 SECTION 1 LOSS OF DOl (continued) 3.3 Notify SM to implement Emergency Action Level Classification (1903.010).

3.4 IF transfer of Dli is NOT successful, THEN attempt local transfer of Dli to D02, while continuing.

3.5 IF reactor is NOT tripped, THEN GO TO step 7.0.

3.6 IF transfer of Dli is successful, THEN GO TO step 4.0.

3.7 IF transfer of Dil is NOT successful, THEN perform the following:

3.7.1 Dispatch an operator to perform Attachment 1, while continuing.

3.7.2 IF Generator Output bkrs (5114 and 5118) do NOT trip, THEN GO TO step 5.0.

3.7.3 IF Generator Output bkrs (5114 and 5118) trip, THEN GO TO step 6.0.

4.0 IF transfer of Dll is successful, THEN perform the following:

4.1 IF EFW actuates, THEN throttle P7B EFW Isolations as necessary to limit flow.

SGA SGB CV-2670 EFW P7B ISOL CV2626 4.1.1 Perform RT-5.

4.2 verify Condenser Vacuum Pump (C-5A OR C-5B) running.

4.3 WHEN plant conditions stabilize, THEN GO TO step 7.0 for restoration.

[

PROC/WORK PLAN NO. PROCEDIJREIWORK PLAN TITLE:

PAGE: 4 of 44 1203.036 LOSS OF 125V DC CHANGE: 009 SECTION 1 LOSS OF 001 (continued) 5.0 IF transfer of Dli is NOT successful AND Generator Output Breakers do NOT trip, THEN perform the following:

5.1 At ClO, transfer A2 and H2 to an available 513 Xfmr as follows:

NOTE

• 513 1 is preferred.

• SU 2 Load Shedding is inoperable during a loss of 001.

5.1.1 IF SU 1 is available, THEN GO TO step 5.1.3.

5.1.2 IF ONLY SU 2 is available, THEN perform the following:

• Notify operator performing Attachment I that breaker operations from Control Room are commencing.

• At C19, trip VCH-1B Power Supply breaker (A-208)

• At C02, trip Condensate Pump P-2B.

• At Cl2, trip Circ Water Pumps P-3B AND P-3D.

• At Cl2, trip Heater Drain Pump PSB.

• Refer to SU 2 Transformer Loading Restrictions, Attachment E of Electrical System Operations (1107.001)

• Notify Unit 2 of intent to use SU 2.

[

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

PAGE: 5 of 44 1203.036 LOSS OF 125V DC CHANGE: 009 SECTION 1 -- LOSS OF DOl (continued) 5.1.3 Turn ON SYNC switch for desired SD Xfmr feeder to A2, either:

• Startup Xfmr #1 Feed to A2 (A-2l3)

OR

• Startup Xfmr #2 Feed to A2 (A-211) 5.1.4 Verify synchroscope at 12 oclock.

CAUTION

• High circulating currents may trip bus lockout relay if both feeder breakers remain closed.

• SYIC switch must be off to verify feeder breaker opens.

With SYNC switch on, red light for feeder breaker position goes out even if breaker does not trip.

5.1.5 Perform the following:

A. Close desired SU Xfmr feeder to A2 AND allow control switch to return to NORMAL-AFTER-CLOSE position.

B. Turn OFF SYNC switch.

C. Verify Unit Aux Xfmr Feed to A2 (A-2l2) trips.

1. IF A-212 does NOT immediately open, THEN trip it.

5.1.6 Turn ON SYNC switch for desired SU Xfmr feeder to H2, either:

• Startup Xfmr #1 Feed to H2 (H-25)

OR

• Startup Xfmr #2 Feed to H2 (16-23) 5.1.7 Verify synchroscope at 12 oclock.

[ I PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

PAGE: 6 of 44 1203.036 LOSS OF 125V DC CHANGE: 009 SECTION 1 -- LOSS OF DOl (continued)

CAUT ION

• High circulating currents may trip bus lockout relay if both feeder breakers remain closed.

• SYNC switch must be off to verify feeder breaker opens.

With SYNC switch on, red light for feeder breaker position goes out even if breaker does NOT trip.

5.1.8 Perform the following:

A. Close desired SU Xfmr feeder to H2 AND allow control switch to return to NORMAL-AFTER-CLOSE position.

B. Turn OFF SYNC switch.

C. Verify Unit Aux Xfmr Feed to H2 (H-24) trips.

1. IF H-24 does NOT immediately open, THEN trip it.

5.2 Manually transfer Al to available SU Xfmr as follows.

CAUTION Operation with the turbine tripped and generator motoring for extended period will result in turbine blade overheating.

5.2.1 Turn ON SYNC switch for desired SU Xfmr feeder to Al, either:

• Startup Xfmr #1 Feed to Al (A-113)

OR

• Startup Xfmr #2 Feed to Al (A-lll) 5.2.2 verify RUNNING voltage and INCOMING voltage match.

5.2.3 verify synchroscope at 12 oclock position.

[

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

PAGE: 7 of 44 1203.036 LOSS OF 125V DC CHANGE: 009 SECTION 1 -- LOSS OF 001 (continued)

WARNING Paralleling 4l6OV and 6900V power sources out of sync could cause personnel injury and severe equipment damage.

High circulating currents exist if both feeder breakers remain closed.

CAUTION 5.2.4 Coordinate with operator performing Attachment 1 to transfer Al to desired SU Xfmr.

5.2.5 WHEN Al is energized from SU Xfmr, THEN turn OFF SYNC switch for SU Xfmr feeder to Al.

5.3 Start available oil pumps for RCP5 P32A and P-32C.

NOTE Although position indication for 5114 and 5118 on COl is unavailable, COl handswitches will operate the breakers. ClO mimic bus should be used to verify breakers open.

5.4 At COl, trip generator output breakers 5114 and 5118.

5.4.1 Notify operator performing Attachment 1 that output breakers are open.

5.5 WHEN plant conditions stabilize, THEN GO TO step 7.0 for restoration.

i PROC.IWORK PLAN NO.

1203.036 PROCEDUREIWORK PLAN TITLE:

LOSS OF 125V DC I PAGE: 8 of 44 CHANGE: 009 SECTION 1 -- LOSS OF DOl (continued) 6.0 IF transfer of 011 is NOT successful AND Generator Output Breakers Trip, THEN perform the following:

6.1 Check that DG-2 starts and energizes A4.

6.2 Trip running RCPs.

NOTE Due to loss of inverters supplying RSl and RS3, two ESAS Analog Channels trip and cause all even Digital Channels to trip.

Odd Channels cannot trip, due to loss of power.

6.3 Override inadvertent ES actuation as follows:

6.3.1 Check RCS press >1590 psig and RB press <4 psig (18.7 psia) to verify ES actuation is inadvertent.

6.3.2 Override each actuated component using MAN pushbutton.

A. Stop RB Spray pump (P35B)

B. Stop LPI pump (P34B)

C. Place overridden components in desired position.

6.4 Place all RCP Seal Bleed off (Alternate Path to Quench Tank) handswitches in CLOSE (SV-1270, 1271, 1272, & 1273) 6.5 At ClO, verify MCC B55 & 56 powered from B6.

6.6 Control RCS makeup as follows:

6.6.1 IF P-36C OR P-36B from A4 was the OP HPI pump, THEN perform the following:

A. Override AND open ECS Makeup Block (CV-1234)

B. Slowly open PZR Level Control (CV-l235)

1. Adjust setpoint to 100 AND place in AUTO.

6.6.2 IF P-36C is ES HPI pump, THEN override AND operate HPI valves (CV-1228, 1227, 1284,

& 1285) as necessary to maintain PZR level.

f PROC/WORK PLAN NO.

1203.036 PROCEDURE/WORK PLAN TITLE:

LOSS OF 125V DC I PAGE: 9 of 44 CHANGE: 009 SECTION 1 -- LOSS OF DOl (continued) 6.7 Verify a Service Water Pump (P-4B OR P-4C) restarts on A4.

6.8 Verify EFW P-7A operating with SG levels rising to Natural Circulation setpoint (312)

NOTE

• 511 1 is preferred.

• SU 2 Load Shedding is inoperable during a loss of DOl.

6.9 At ClO, transfer A2 and H2 to an available SU Xfmr as follows:

6.9.1 IF SU 1 is available, THEN GO TO step 6.9.3.

6.9.2 IF ONLY 511 2 is available, L perform the following:

• Notify operator performing Attachment 1 that breaker operations from Control Room are commencing.

• At C19, trip VCH-1B Power Supply breaker (A-208)

• At C02, trip Condensate Pump P-25.

• At C12, trip Circ Water Pumps P-3B AND P-3D.

• At C12, trip Heater Drain Pump P-85.

• Refer to SU 2 Transformer Loading Restrictions, Attachment E of Electrical System Operations (1107.001)

• Notify Unit 2 of intent to use SU 2 Xfmr.

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

PAGE: 10 of 44 1203M36 LOSS OF 125V DC CHANGE: 009 SECTION 1 - LOSS OF DOl (continued) 6.9.3 Turn ON SYNC switch for desired SU Xfmr feeder to A2, either:

• Startup Xfmr #1 Feed Co A2 (A-213)

OR

• Startup Xfmr #2 Feed to A2 (A-211) 6.9.4 Verify tripped Unit Aux Xfmr Feed to A2 (A2l2) 6.9.5 Close desired SU Xfmr feeder to A2, either:

• Startup Xfmr #1 Feed to A2 (A-2l3)

OR

• Startup Xfmr #2 Feed to A2 (A-211) 6.9.6 Turn OFF SYNC switch.

6.9.7 Restart ICW Pumps (P-33B on non-nuclear loop, P-33C on nuclear loop) 6.9.8 Verify Condenser Vacuum Pump (C-5A OR C-SB) running.

6.9.9 Turn ON SYNC switch for desired SU Xfmr feeder to H2, either:

• Startup Xfmr #1 Feed to H2 (H-25)

OR

• Startup Xfmr #2 Feed to H2 (H-23) 6.9.10 Verify tripped Unit Aux Xfmr Feed to H2 (H-24) 6.9.11 Close desired SU Xfmr feeder to H2.

6.9.12 Turn OFF SYNC switch.

6.9.13 WHEN RCP services are available, THEN refer to Reactor Coolant Pump and Motor Emergency (1203.031), Simultaneous Loss of Seal Injection and Seal Cooling Flow section to start RCP5 (P-32B and P-32D)

NOTE Restoration of alternate source power to inverters supplying ESI and R53 will energize the odd ESAS digital channels, causing an inadvertent actuation of ES unless disabled.

6.10 Check RCS press >1590 psig and RB press <4 psig (18.7 psia) to verify ES actuation is NOT needed.

6.10.1 IF ES is NOT needed, THEN disable odd ESAS digital channels by opening breaker for ESAS Digital Subsystem No. I (P.51-4)

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

PAGE: 11 of 44 1203.036 LOSS OF 125V DC CHANGE: 009 SECTION 1 LOSS OF IDOl (continued) 6.11 WHEN loads have been stripped from Al and A3, THEN direct operator to manually close desired SD Xfmr feeder to Al, either:

• Startup Xfmr l Feed to Al (All3)

OR

• Startup Xfrnr #2 Feed to Al (Alll) 6.12 Reset tripped ES Analog Subsystem Trip Bistables:

• Analog CH 1 (C88)

• Analog CH 2 (C89)

• Analog CH 3 (C90) 6.13 Restore power to ES Digital Subsystem No. I by closing breaker RS1-4.

6.14 Reset tripped ES Digital Subsystems using reset PB(s) on C04.

6.15 Direct operator to manually start a SW pump on A3:

• Service Water Pump (P-4A) (A302)

OR

• Service Water Pump (P-4B) (A-303) 6.16 IF P-36C is ES HPI pump, THEN restore RCP seal injection and PZR level control by aligning P36C as the OP HPI pump per Makeup Purification System Operation (1104.002) 6.17 WHEN plant conditions stabilize, THEN GO TO step 7.0 for restoration.

7.0 Restoration 7.1 Determine cause for loss of D01 and initiate corrective action.

7.2 Refer to Battery and l25V DC Distribution (1107.004) to determine equipment that has lost power.

7.3 Refer to Emergency Feedwater Initiation and Control (1105.005),

Operability section for determining operability of EFW system.

PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

PAGE: 12 of 44 1203036 LOSS OF 125V DC CHANGE: 009 SECTION 1 -- LOSS OF DOl (continued)

CAUTION DII power supply transfer results in a momentary loss of power to the distribution panel.

• IF operating, DG1 will trip.

• IF operating, condenser vacuum pump C-SA will trip.

7.4 WHEN power is restored to D0l, THEN transfer Dli to NORMAL SUPPLY.

7.5 WHEN power is restored to DOl, THEN return the following inverters to normal operation per Inverter and l20V Vital AC Distribution (1107.003)

• Place Inverter Yll OR Yl5 in service supplying RS1

• Place Inverter Yl3 OR YlS in service supplying RS3 7.6 Verify EOS Channel A (SY-6650) reset.

7.6.1 Verify EOS SYSTEM TROUBLE (K04C5) clear.

Page 1 of 5 JOB PERFORMANCE MEASURE Date:

1 Rev # 1 Unit:

TUQI NUMBER: A1JPM-RO-HYD04 System/Duty Area: Hydrogen Recombiner and Purge Control System Task: Place Hydrogen Recombiner M55B in Operation JA# ANO1-RO-RBH2-NORM-1 KA Value RO 4.0 SRO 4.0 KA Reference 028 A4.01 Approved For Administration To: RO SRO Task Location: Inside CR: 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): 1104.031, Chg. 024 Examinees Name: KCN:

Evaluators Name:

The Exam inees 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.

Page 2 of 5 TUOI NUMBER: A1JPM-RO-HYDO4 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner should verify that the examinee has been briefed per the JPM Examination Briefing Sheet EN-TQ-114 .5.

JPM INITIAL TASK CONDITIONS:

A LOCA has occurred. Containment hydrogen concentration is 2.1%. Both hydrogen recombiners are shutdown.

Containment pressure is 20.0 psia. Pre-LOCA containment temperature was 92°F.

TASK STANDARD:

Hydrogen recombiner M55B in oneration t nwer settinci nf 53 fl 1KW to 550 1KW on il-i 001 TASK PERFORMANCE AIDS:

1104 031. section 80 nd Aft R

Page 3 of 5 TUQI NUMBER: A1JPM-RO--HYD04 INITIATING CUE: The CRS/SM directs you to place both hydrogen recombiners (M55AIB) in standby and then place M55B in operation.

Note: Your task is complete when the power you have determined for recombiner operation is achieved.

CRITICAL ELEMENTS (c): 2, 7, 8 C PERFORMANCE CHECKLIST STANDARD N/A SAT UN SAT

1. Verify power adjust potentiometers are set at zero. Verified power adjust potentiometers set to zero on C26 POSITIVE CUE: (if not already at zero used Power adjust potentiometers for M55AIB are set at zero knurled knob on power adjust on C26. potentiometers on C26 and turned to the left and set at zero using HS-7472 and HS-7473).

2. Turn hydrogen recombiners M55A and M55B on. Turned on hydrogen recombiners M55A and M55B using HS-7470 POSITIVE CUE: and HS-7471 on C26.

M55A/B red lights ON.

NEGATIVE CUE:

M55A/B green lights ON.

3. Select thermocouple #1, 2 or 3 to input to Thermocouple #1 2 or 3 selected recombiner temperature indicators TI-2300 and TI- to input to TI-2300 and TI-2301 2301. using handswitches HS-7474 and HS-7475 on C26.

POSITIVE CUE:

Thermocouple #1, 2 or 3 selected as desired to input to TI-2300 and TI-2301.

4. Increase power to 5 KW. Slowly adjusted potentiometers clockwise until power on JI-1000 POSITIVE CUE: and JI-lOOl on C26 indicated 5 Power on JI-1000 and JI-lOOl indicates 5KW. KW.

INSTRUCTOR NOTE:

Inform examinee that ten minutes have elapsed after one minute at 10 KW.

5. Slowly increase power to 10 KW and record initial Increased power to 10 KW using time. power adjust potentiometers on C26. Recorded time 10 KWwas POSITIVE CUE: achieved.

Power is at 10 KW on Jl-1 000 and JI-lOOl.

INSTRUCTOR NOTE:

Inform examinee that taking data every 30 minutes on Attachment E will be simulated.

Inform examinee that ten minutes have elapsed after achieving 10 KW.

Inform examinee that five minutes have elapsed after one minute at 20 KW.

Page 4 of 5 TUOI NUMBER: A1JPM-RO-HYDO4 STANDARD N/A SAT UN C PERFORMANCE CHECKLIST SAT

6. Slowly increase power to 20 KW on M55B and hold Increased power on M55B to 20 for 5 minutes. KW using power adjust potentiometer on C26.

POSITIVE CUE:

Power at 20 KWon JI-lOOl.

7. Determine power required from Attachment B Determined Recombiner power to based on containment pressure (20.0 psia and be from 53.0 to 55.0 KW using 92°F Pre-LOCA containment temperature). Attachment B of 1104.031.

8. Slowly increase power to 53.0-55.0 KW range. Power increased to 53.0 to 55.0 KW range using power adjust POSITIVE CUE: potentiometer on C26.

Hydrogen concentration dropping on Ql-7459 and M55B maintaining power at determined value.

NEGATIVE CUE:

Hydrogen concentration rising or steady on Ql-7459.

END

Page 5 of 5 TUOI NUMBER: A1JPM-RO-HYDO4 INITIAL CONDITIONS:

• A LOCA has occurred.

• Containment hydrogen concentration is 2.1%.

• Both hydrogen recombiners are shutdown.

• Containment pressure is 20.0 psia.

• Pre-LOCA containment temperature was 92° F.

INITIATING CUE:

The CRS/SM directs you to place both hydrogen recombiners (M55A/B) in standby and then place M55B in operation.

Note: Your task is complete when the power you have determined for recombiner operation is achieved.

ENTERGY OPERATiONS INCORPORATED ARKANSAS NUCLEAR ONE DOCUMENT NO. CHANGE NO.

TITLE: CONTAINMENT HYDROGEN CONTROL WORK PLAN EXP. DATE N/A SAFETY-RELATED IPTE SET # YES DNO DYES ZNO TEMP MOD LEVEL OF USE YES UNO CONTINUOUS Q REFERENCE DINFORMATIONAL PROGRAMMATIC EXCLUSION PER EN-LI-100 DYES__NO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distractionllnterruption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First ShiftlLast Shift Knowledge Peer Pressure Procedures ChangeiOff Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY DATE TIME =

FORM TrrLE: FORM NO. CHANGE NC.

VERIFICATION COVER SHEET J 1000.006A j 054

I i PROCJWORK PLAN NO.

1104.031 PROCEDUREIWORK PLAN TITLE:

CONTAINMENT HYDROGEN CONTROL PAGE: 9 of 69 I CHANGE: 024 CAUTION Hydrogen recombiner, MS5A or M55B, should be placed in operation following a LOCA as soon as time permits and must be in operation before hydrogen concentration reaches 3.0% as indicated on the highest reading H 2 analyzer.

8.0 Placing Hydrogen Recombiner (M55A or M55B) in Operation NOTE

• Both M55A and M55B are placed in standby, then either may be placed in operation.

• The term slowly used in this section means raising potentiometer settings slowly enough to witness KW rise without overshooting the target setting.

8.1 Place both M55A and M55B in standby as follows.

8.1.1 Place M55A in standby by performing the following:

A. Verify Power Adjust Potentiometer is set at zero for M55A.

B. Start M5SA by placing HS7470 in ON.

C. Select thermocouple #1, 2, or 3 (HS-7474) to input to M55A Temperature (TI-2300)

D. Slowly turn power adjust potentiometers clockwise to raise power to 5 KW as indicated on MSSA Power (JI-l000)

H. Slowly raise power to 10 KW.

1. Record initial time at 10 KW:

2. Maintain 10 KW output for standby service.

PROC.IWORK PLAN NO. I PROCEDUREIWORK PLAN UTLE: I PAGE: 10 of 69 1104.031 CONTAINMENT HYDROGEN CONTROL CHANGE: 024 8.1.2 Place M55B in standby by performing the following:

A. Verify Power Adjust Potentiometer is set at zero for M55B.

B. Start M55B by placing HS-747l in ON.

C. Select thermocouple #1, 2, or 3 (HS-7475) to input to M5SB Temperature (TI-230l)

D. Slowly turn power adjust potentiometers clockwise to raise power to S KW as indicated on M55B Power (JI-lOOl)

E. Slowly raise power to 10 KW.

1. Record initial time at 10 KW:

2. Maintain 10 KW output for standby service.

CAUTION Hydrogen Recombiner, M55A or M5SB, should be placed in operation following a LOCA as soon as time permits and must be in operation before hydrogen concentration reaches 3.0% as indicated on the highest reading H 2 analyzer.

8.2 Place recombiners in operation as follows:

8.2.1 Place M55A in-service by performing the following:

A. During heatup, monitor and record all three thermocouple temperatures every 30 minutes on Attachment D.

B. Verify M55A has been at 10 KW for at least 10 minutes.

C. Slowly raise power to 20 KW AND hold for 5 minutes.

D. Determine power required from Recombiner Power (M-55A)

Versus Containment Pressure, Attachment B of this procedure, page 1 of 2, based on containment pressure.

1. KW setting I CAUTION Recombiner power >75 1KW and temperature >1450°F may cause heater failure.

2. Slowly raise power to the value determined above.

PROC/WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 11 of 69 1104.031 CONTAINMENT HYDROGEN CONTROL CHANGE: 024 E. Verify proper recombiner operation by observing the following:

NOTE

• Hydrogen concentration reduction is the long-term, primary method of verification.

• H concentration reduction shall be used regardless of recombiner power or 2

temperature indication as the verification of proper recombiner operation.

• Hydrogen concentration stable or dropping at

% Hydrogen (QI-7457 and QI-7459)

• Recombiner maintaining power at value determined NOTE

• Thermocouples are nonQ and will not be reliable indicators in a post-LOCA environment.

• Recombiner temperature can aid in trending recombiner operation. The following steps are provided as guidelines.

• Recombiner temperature may be plotted on Attachment C for verifying thermocouple operation and estimating time when recombination temperature will be reached.

F. Establish validity of temperature indication by comparing AT between thermocouples.

I. IF all three thermocouples fall within a 60°F band, THEN average the three temperatures.

2. IF no two thermocouples are within 60°F of each other, THEN thermocouples should be considered inaccurate.

3. IF difference of the three temperatures >60°F, AND two temperatures are within 60°F, THEN average the closest two.

G. Monitor for indication that recombiner operating temperature of 1225°F has been reached.

PROC/WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: I PAGE: 12 of 69 1104.031 CONTAINMENT HYDROGEN CONTROL CHANGE: 024

[

NOTE Valid thermocouples show a ramp rise in temperature with H 2 concentration >2%,

indicating recombination temperature has been reached and recombination is taking place.

H. IF hydrogen concentration is >2%,

THEN monitor for a ramp rise in temperature.

I. After four hours of full power operation, log data in Attachment D once per hour.

8.2.2 Place M55B in-service by performing the following:

A. During heatup, monitor and record all three thermocouple temperatures every 30 minutes on Attachment E.

B. Verify M55B has been at 10 KW for at least 10 minutes.

C. Slowly raise power to 20 KW AND hold for 5 minutes.

D. Determine power required from Recombiner Power (M-55B)

Versus Containment Pressure Attachment B of this procedure, page 2 of 2, based on containment pressure.

1. KW setting Recombiner power >75 KW and temperature >1450°F may cause heater failure.

CAUTION

2. Slowly raise power to the value determined above.

E. Verify proper recombiner operation by observing the following:

NOTE

• Hydrogen concentration reduction is the long-term, primary method of verification.

• H concentration reduction shall be used regardless of recombiner power or 2

temperature indication as the verification of proper recombiner operation.

• Hydrogen concentration stable or dropping at

% Hydrogen (QI-7457 and QI-7459)

• Recombiner maintaining power at value determined in step 8.2.2.D.

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

PAGE: 13 of 69 1104.031 CONTAINMENT HYDROGEN CONTROL CHANGE: 024 NOTE

• Thermocouples are non-Q and will not be reliable indicators in a post-LOCA environment.

• Recombiner temperature can aid in trending recombiner operation. The following steps are provided as guidelines.

Recombiner temperature may be plotted on Attachment C for verifying thermocouple operation and estimating time when recombination temperature will be reached.

F. Establish validity of temperature indication by comparing AT between thermocouples.

1. IF all three thermocouples fall within a 60°F band, THEN average the three temperatures.

2. IF no two thermocouples are within 60°F of each other, THEN thermocouples should be considered inaccurate.

3. IF difference of the three temperatures >60°F, AND two temperatures are within 60°F, THEN average the closest two.

G. Monitor for indication that recombiner operating temperature of 1225°F has been reached.

NOTE Valid thermocouples show a ramp rise in temperature with H 2 concentration >2%,

indicating recombination temperature has been reached and recombination is taking place.

H. IF hydrogen concentration is >2%,

THEN monitor for a ramp rise in temperature.

I. After four hours of full power operation, log data in Attachment E once per hour.

8.2.3 IF proper power setting causes average valid temperature to exceed 1450°F OR in-service recombiner has insufficient capacity, THEN place standby recombiner in-service.

8.2.4 Do NOT lower recombiner power based on extreme temperature.

Maintain power until standby recombiner is heated to operating temperature of -l225°F.

8.3 Monitor Hydrogen Samplers (C178 and C179) to verify recombiner(s) maintaining or lowering hydrogen concentration.

PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: I PAGE: 22 of 69 1104.031 CONTAINMENT HYDROGEN CONTROL CHANGE: 024 ATTACHMENT B Page 1 of 2 RECOMBINER POWER (M-55A)

VERSUS CONTAINMENT PRESSURE 70 65 7_

/6 120°F 60 U

777 7/ /

55

%. ,/

z/

0 50 /

45 40 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 Post-LOCA Containment Pressure (0.2 psia increments)

Note: Use pre- LOCA average Reactor Building Temperature from SPDS (TAVRB1) from history file if available. Otherwise use logs.

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: I PAGE: 23 of 69 1104.031 CONTAINMENT HYDROGEN CONTROL CHANGE: 024

[

ATTACHMENT B Page 2 of 2 RECOMBINER POWER (M-55B)

VERSUS CONTAINMENT PRESSURE 75 60 F I900F 120°F 70 65

/

U)

/

I //_

60 7/

55 7//

. /

7/

50 7

z 45 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 Post-LOCA Containment Pressure (0.2 psia increments>

Note: Use pre- LOCA average Reactor Building Temperature from SPDS (TAVRB1) from history file if available. Otherwise use logs.

PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 24 of 69 1104.031 CONTAINMENT HYDROGEN CONTROL CHANGE: 024 ATTACHMENT C TYPICAL RECOMBINER HEATUP RATE 1300 t_A. Input 1200 1100 1000 7

800 700

/

600 500 400

/

300

/

fl 200 100 0

0 0.5 1 1.5 2 2.5 3 3.5 4 4.5 5 5.5 Time (Hours)

PROC.IWORK PLAN N

O. PROCEDURE

/WORK PLAN TITLE: PAGE: 25 of 69 1104.031 CONTAINMENT HYDROGEN CONTROL CHANGE: 024 ATTACHMENT D HYDROGEN RECOMBINER MS5A DATA Page 1 of 1 JIl000 POTENTIOMETER TEPERAITJRE (TI23OO) AVG TEvP of RB PRESS 2 H

TIME KM SETTING Ch.1 Ch.2 Ch.3 Valid Chs (SPDS) QI-7457

PROC IWORK PLAN N

O. PROCEDURE

/WORK PLAN TITLE: PAGE: 26 of 69 1104.031 CONTAINMENT HYDROGEN CONTROL CHANGE: 024 ATTACHMENT E HYDROGEN RECOMBINER M55B DATA Page 1 of 1 AVG TEMP of RB PRESS 2 %

H JP-1001 POTENTIOMETER TEMPEPAIDEE (TI-2301)

Ch.3 Valid Chs (SPDS) QI7459 TIME KW SETTING Cii.1 Ch.2

Page 1 of 5 JOB PERFORMANCE MEASURE Date:

Unit: 1 Rev # 2 JPM ID: A1JPM-RO-PZRO5 System/Duty Area: PRESSURIZER Task: Respond to Low RCS Pressure due to Stuck Open Spray Valve JTA# ANO1-RO-AOP-OFFMORM-1 15 KA Value RO 3.6 SRO 3,5 KA

Reference:

010 A3.02 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 Lab:

Position Evaluated: RO: SRO:

Actual Testing Environment: Plant Site Simulator Lab Testing Method: Perform Simulate Approximate Completion Time in Minutes: 15 Minutes Reference(s): 1203.012H Annunciator K09 corrective Action K09-C1; 1203.015 Pressurizer systems Failure Examinees Name: KCN:

Evaluators Name:

The Examinees 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.

Page 2 of 5 JPM ID: A1JPM-RO-PZRO5 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner should verify that the examinee has been briefed per the JPM Examination Briefing Sheet EN-TQ-1 14 .5.

JPM INITIAL TASK CONDITIONS:

The Reactor is at 38% power with 3 RCPs running, D RCP is secured.

SUGGESTED SIMULATOR SETUP: Have the Spray valve stuck open CV-1 008 and have the spray valve isolation valve CV-1009 failed open. Spray valve should be open slightly and have RCS pressure going down slowly with all PZR heaters on. Have RCS pressure Hi/Lo alarm in K09-C1 Simulator should be frozen until candidate is ready. Then start simulator THIS IS AN ALTERNATE PATH JPM TASK STANDARD:

Trip Reactor and Stop C RCP to stop RCS pressure decrease. Tripping the reactor must be performed prior to reaching the RPS low pressure set point. Stopping C RCP should be done prior to reaching ESAS trip set point of 1590 psig.

TASK PERFORMANCE AIDS:

Copy of 1203.015 section 6 Pressurizer Spray Valve (CV-1008) and 1203.012H Annunciator K09 corrective action for K09-C1 window RCS Pressure Hi/Lo

Page 3 of 5 JPM ID: A1JPM-RO-PZRO5 INITIATING CUE: The CRS/SM directs you to respond to Annunciator K09-C1 RCS Pressure HI/LO alarm.

C PERFORMANCE CHECKLIST STANDARD N/A SAT INSTRUCTOR NOTE: Only provide applicant the ACA procedure.

1. Confirm alarm by comparing RC pressure indications on 004.

Identified that all RCS pressure indicators are going down.

POSITIVE CUE:

All RCS pressure indicators are going down.

2. Refer to COLR figures for RC Pressure Limits. COLR limits may not be referenced during Press Transient POSITIVE CUE: Or RC Pressure Limits Checked. COLR RC Press. Limits reviewed.

3. Verify all Pressurizer heaters are on.

. Identifies all Pressurizer heaters PL,,.,I IViz UE.

are on.

All pressurizer heaters are on.

4. Verify Pressurizer Spray (CV 1008) closed. Identified Pressurizer Spray (CV 1008) open. Attempted to close NEGATIVE CUE: Pressurizer Spray (CV-i 008) and Pressurizer Spray (CV 1008) open. valve will not close

5. Verify ERV (PSV-1 000) closed.

Verified ERV (PSV-i 000) closed.

POSITIVE CUE:

ERV (PSV-i000) closed.

Examiner Cue: When asked provide applicant AOP.

Refers to Pressurizer Systems

6. Refers to Pressurizer Systems failure 1203.015. Failure 1203.015 Section 6 Pressurizer Spray valve (CV-POSITIVE CUE: 1008) Failure.

Hand student Pressurizer Systems failure 1203.01 5.

7. Close Pressurizer Spray Isolation valve CV-1 009, Attempted to close Pressurizer Spray isolation valve (CV 1009)

Negative CUE:

and valve will not close.

Pressurizer Spray Isolation valve CV-1009 open.

Page 4 of 5 C PERFORMANCE CHECKLIST STANDARD N/A SAT

8. Verify all Pressurizer heaters are on.

Verified all Pressurizer heaters POSITIVE CUE: on.

All pressurizer heaters are on.

Student Trips Reactor verifies all

9. Trip Reactor. rods are inserted and Reactor c . power is going down. This must POSITIVE CUE. be done prior to reaching an Reactor tripped, automatic RPS set point of low RCS pressure 1800 psig.

10. Verify Turbine is tripped.

Verified all throttle and governor POSITIVE CUE: valves are shut.

Turbine is tripped.

1 1. Verify Sub Cooling Margin is adequate.

Verified SCM is >30 degrees F.

POSITIVE CUE:

SCM is adequate.

12. Start C RCP HP Oil Lift pump (P63C).

Starts C RCP HP Oil Lift pump POSITIVE CUE: P63C and due to caution tag start RCP HP Oil Lift pump (P63C) starts and due to caution P-80 tag start P-80

13. Start C RCP Backstop Lube Oil pump (P81C)

Starts C RCP Backstop Lube Oil POSITIVE CUE: pump (P81C)

RCP Backstop Lube Oil pump (P81C) starts.

14. Stop C RCP (P-32C). ,,

Stopped C RCP (P-32C) prior to C RCS pressure drops below 1590 POSITIVE CUE psig ESAS set point.

C RCP (P-32C) stops.

Note to Examiner: Tell student JPM is complete.

END

Page 5 of 5 JPM ID: A1JPM-RO-PZRO5 INITIAL CONDITIONS:

The Reactor is at 38% power with 3 RCPs running, D RCP is secured.

INITIATING CUE:

The CRSISM directs you to respond Annunciator K09-Cl RCS Pressure HIILO alarm

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE DOCUMENT NO. CHANGE NO.

TITLE: ANNUNCIATOR K09 CORRECTIVE ACTION WORK PLAN EXP. DATE N/A SAFETY-RELATED IPTE SET # YES LNO DYES NO TEMP MOD LEVEL OF USE DYES NO CONTINUOUS El REFERENCE U INFORMATIONAL PROGRAMMATIC EXCLUSION PER EN-LI-lOD DYES__NO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distracti onhlnterruption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First ShiftlLast Shift Knowledge Peer Pressure Procedures ChangelOff Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY I DATE I TIME FORM TITLE: FORM NO. CHANGE NO.

VERIFICATION COVER SHEET 1000.006A 054

5 of 64 i PROC/WORK PLAN NO.

1203.012H PROCEDURE/WORK PLAN TITLE:

ANNUNCIATOR K09 CORRECTIVE ACTION PAGE:

CHANGE: 040 I Page 1 of 2 Location: C14 RC S Device and Setpoint:

PRESSURE RC Pressure Loop A Narrow Range (PS1023> 2255 psig HI/to or <2055 psi 0 RC Pressu re Loop B Narrow Range (PS-l038) 2255 psig Alarm: KS9C1 Or <2055 psi 0 liO OPERATOR ACTIONS NOTE during three RCP The following indicators should read nearly alike except Operation.

on C04.

1. Confirm alarm by comparing RC pressure indications

• RC Pressure Narrow Range Loop A recorder (PRl023)

• RC Pressure Narrow Range Loop B recorder (PR1038)

. RC Pressure Wide Range Loop B recorder (P11041)

• RC Pressure Wide Range Loop B indicator (PR-1042)

NOTE ous trip signal to A malfunctioning pressure instrument can insert an errone the RPS.

2. Refer to COLR Figures for RC pressure limits.

3. IF RC pressure is confirmed low, THEN perform the following:

A. Verify all pressurizer heaters on.

B. Verify Pressurizer Spray (CVl008) closed.

C. Verify ERV (PSV-1000) closed.

D. Refer to Pressurizer Systems Failure (1203.015).

4. IF RC pressure is confirmed high, THEN perform the following:

A. Verify Pressurizer Spray (CV1008) open.

B. Verify all pressurizer neaters are off.

C. Refer to Pressurizer Systems Failure (1203.015)

5. IF transient is caused by ItS malfunction, OR ICS instrument failure ANt refer to ICS THEN take manual control of affected H/A station Abnormal Operation (1203.001).

6. Refer to SASS MISMATCH K07B4 (1203.012F)

I

[

PROC/WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 6 of 64 1203.012H ANNUNCIATOR K09 CORRECTIVE ACTION CHANGE: 040 EQSCl Page 2 of 2 2.0 PROBAPLE CAUSES

• Malfunctioning pressure instrument

• ICS malfunction

3.0 REFERENCES

Window Arrangement Annunciator K09 (E459, sheets 14)

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE DOCUMENT NO. CHANGE NO.

TITLE: PRESSURIZER SYSTEMS FAILURE WORK PLAN EXP. DATE NIA SAFETY-RELATED IPTE QNO DYES NO SET # DYES LEVEL OF USE TEMP MOD DYES NO 0 CONTINUOUS D REFERENCE fl INFORMATIONAL PROGRAMMATIC EXCLUSION PER EN-LI-100 DYES__ONO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distractionhlnterruption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First Shift/Last Shift Knowledge Peer Pressure Procedures Change!Off Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY DATE I TIME FORM NO. CHANGE NO.

FORM TITLE:

VERIFICATION COVER SHEET 1000.006A 054

CHANGE 1203.015 PRESSURIZER SYSTEMS FAILURE 016 PAGE 16 of 24 SECTION 6 -- PRESSURIZER SPRAY VALVE (CV-1008) FAILURE ENTRY CONDITIONS One or more of the following:

• CV-1008 closed when it should be open.

- Normal operation: Opens 2205 psig Closes 2155 psig

- Power >80% and MFP trip: Opens 2080 psig Closes 2030 psig

• CV-1008 open when it should be closed.

• Abnormal change in RC pressure.

• RC pressure transmitter failure which is selected for RC pressure control.

I I CHANGE PRESSURIZER SYSTEMS FAILURE 016 PAGE 17 of 24 1203.015 1 SECTION 6-- PRESSURIZER SPRAY VALVE (CV-1008) FAILURE INSTRUCTIONS faiIed open, THEN place Pressurizer Spray Control switch in HAND AND attempt to close CV-1008 (modulating valve).

NOTE CV-1009 torque switch can be overridden in the OPEN or CLOSE direction by holding the hand switch in the respective position.

A. IF CV-1 008 will NOT close, THEN close Pressurizer Spray Isolation Valve (CV-1 009).

B. Verify Pressurizer heaters return RCS pressure to normal.

CAUTION Pressurizer spray shall not be used if the temperature difference between the Pressurizer and the spray fluid is >430°F (TRM 3.4.3). Closing CV-1009 isolates the CV-1008 bypass spray flow.

C. IF necessary, THEN control spray flow by cycling Pressurizer Spray Isolation Valve (CV-1009) open and closed.

D. IF both CV-1008 and CV-1 009 do NOT close AND RCS pressure is dropping, THEN perform the following:

1) Verify all PZR heaters ON.

2) Immediately begin reducing load to 40% at 10%/mm per Rapid Plant Shutdown (1203.045).

3) IF 4 RCPs are running AND BOTH of the following conditions are met:

• Load is reduced to 675 MWe (75% load)

• Reactor power is 75%,

THEN perform the following:

a. Start C RCP HP Oil Lift Pump (P-63C) and C RCP Backstop Lube Oil Pump (P-81 C).

b. Stop C RCP (P-32C).

c. WHEN zero speed is indicated, THEN stop P-63C and P-81C.

(continued)

CHANGE 1203.015 PRESSURIZER SYSTEMS FAILURE 016 PAGE 18 of 24 SECTION 6 -- PRESSURIZER SPRAY VALVE (CV-.1008) FAILURE NOTE In Modes 1 and 2, operation with only one RCP in each loop causes entry into TS 3.4.4 Condition A.

4) f3RCPsrunning all of the following conditions are met:

• Load is reduced to 360 MWe (40% load)

• Reactor power is 55%,

• C and D RCPs in-service THEN perform the following:

a) Start C RCP HP Oil Lift Pump (P-63C) and C RCP Backstop Lube Oil Pump (P-81 C).

b) Stop C RCP (P-32C).

c) WHEN zero speed is indicated, THEN stop P-63C and P-81C.

d) Enter TS 3.4.4 Condition A.

5) IF 3 RCPs running, AND D RCP is secured, THEN perform the following:

a) Trip Reactor.

b) Secure P-32C as follows:

(1) Start C RCP HP Oil Lift Pump (P-63C) and C RCP Backstop Lube Oil Pump (P-81C).

(2) Stop C RCP (P-32C).

(3) WHEN zero speed is indicated, THEN stop P-63C and P-81C.

C) Perform Reactor Trip (1202.001) while continuing with this procedure.

d) Enter TS 3.4.5 Condition A.

6) WHEN conditions permit a reactor building entry, THEN attempt to manually close either CV-1008 or CV-1009.

E. Contact Ops Manager.

(continued)

CHANGE I 1203.015 PRESSURIZER SYSTEMS FAILURE 016 j PAGE 19 of 24 SECTION 6 -- PRESSURIZER SPRAY VALVE (CV-1008) FAILURE

2. IFfailed closed, THEN hold the plant at steady state conditions.

A. CV-1008 is energized, THEN place Pressurizer Spray Control Mode switch in HAND AND attempt to cycle CV-1 008 (a modulating valve) open and closed.

B. Write a Condition Report to evaluate continued operation of the plant with inoperable Spray Valve.

C. Contact Ops Manager AND consider one or both of the following:

1) IFCV-lOO8will NOT open, THEN commence a shutdown per Power Reduction and Plant Shutdown (1102.016) and Plant Shutdown and Cooldown (1102.010).

• To prevent lifting of relief valves, reduce power slowly while shutting down. a

• RC pressure can be regulated by manual control of Pressurizer heaters. a

2) WHEN conditions permit a reactor building entry, THEN perform the following:

a. Close CV-1009 from C04.

b. Attempt to manually open CV-1008 in reactor building.

CAUTION Pressurizer spray shall not be used if the temperature difference between the Pressurizer and the spray fluid is >430°F (TRM 3.4.3). Closing CV-1 009 isolates the CV-1 008 bypass spray

c. f CV-1008 can be opened, THEN control RCS pressure and spray line temperature by cycling CV-1 009 open and closed.

3. IF an RC pressure transmitter which is selected for control has failed or is failing, THEN GO TO Annunciator K07 Corrective Action (1203.012F), SASS Mismatch (K07-B4).

4. Refer to RCS Pressure, Temperature and Flow DNB Surveillance Limits of the ANOI COLR (TS 3.4.1).

END

Page 1 of 4 JOB PERFORMANCE MEASURE Date:

1. 3 1 Rev Unit:

JPM ID: A1JPM-RO-EOPO8 System/Duty Area: Emergency and Abnormal Operations Task: Perform Actions required to correct Degraded Power (EFW System Operation)

JTA# ANO1-RO-EOP-EMERG-35 & ANO1-SRO-EOP-EMERG-32 KA Value RO 3.3 SRO 3.6 KA Reference 061 A1.02 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 Lab:

Position Evaluated: RO: SRO:

Actual Testing Environment: Simulator: Plant Site: Lab Testing Method: Simulate: Perform:

Approximate Completion Time In Minutes: 10 Minutes Reference(s): 1202.007 Degraded Power Examinees Name: KCN:

Evaluators Name:

The Examinees 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 Date:

Signed Signature below indicates the material utilized during this JPM has been compared to its applicable procedure by a qualified individual (not the examinee) and is current with that revision.

Page 2 of 4 JPM ID: A1JPM-RO-EOPO8 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner should verify that the examinee has been briefed per the JPM Examination Briefing Sheet EN-TQ-1 14 .5.

JPM INITIAL TASK CONDITIONS:

Degraded Power conditions exist. EFW is NOT available and HPI cooling is inadequate.

TASK STANDARD:

Both EFW pumps suction are aligned to the SW system AND EFW system aligned to feed OTSGs from the Service Water System.

TASK PERFORMANCE AIDS:

1202.007 Degraded Power Step 67A-F.

Page 3 of 4 JPM ID: A1JPM-RO-E0P08 INITIATING CUE: The CRS/SM directs you to feed both OTSGs with Service Water per step 67 of 1202.007 Degraded Power.

UN C PERFORMANCE CHECKLIST STANDARD N/A SAT SAT

1. Direct an operator to close the minimum recirc isolation valves for P-7A and P-7B (FW-1 lA/B).

Notified an operator to close FW-11A and FW-11B.

POSITIVE CUE:

Operator reports that FW-1 1A and FW-1 1 B are closed.

On C09, operated the ATM

2. Depressurize both OTSGs to zero psig.

Dump Control System C (Atmospheric Dump Isolation POSITIVE CUE: Both OTSG pressures are at 0 psig.

and Control Valves) to depressurize the OTSGs to NEGATIVE CUE: Both OTSGs are at 200 psig.

0 psig.

3. Start third Service Water Pump.

POSITIVE CUE: ALL three-service water pumps in Started third Service Water service. (Red lights indicated on panel C16 and C18.

Pump.

NEGATIVE CUE: Green light on for one service water pump.

4. Open the EFW Service Water Loop I and H On C09, opened CV-3850 Isolations (CV-3850 and CV-3851).

and CV-3851. Indicated by C

the red lights ON and green POSITIVE CUE: Red lights on.

lights OFF above HS-3850 and HS-3851.

NEGATIVE CUE: green lights on.

On C09, placed HS-2800

5. Place P-7A and P-7B suction select switches to the and HS-2802 to the SW SW position, position.

Indicated by the green lights POSITIVE CUE: CV-2800 and CV-2802 green lights C ON and red lights OFF for ON.

CV-2800 and CV-2802 AND the red lights ON and green NEGATIVE CUE: lights for CV-2800, CV-2802, CV-lights OFF for CV-2803 and 2803 and CV-2806 did not change status.

CV2806 On C09, opened CV-2670,

6. Open EFW isolation valves (CV-2670 and CV-227 CV-2627, CV-2620 and CV-for SG A. CV-2620 and CV-2626 for SG B).

2626 in manual C Indicated by red lights ON POSITIVE CUE: Red lights ON.

and green lights OFF above HS-2670, HS-2627, HS NEGATIVE CUE: Green Iight(s)ON.

2620 and HS-2626..

7. Open EFW control valves (CV-2645 and CV-2646 On C09, opened CV-2645, for SG A. CV-2647 and CV-2648 for SG B).

CV-2646, CV-2647 and CV 2648 in manual.

C POSITIVE CUE: EFW flow to both OTSGs indicated on Indicated by 100% on scale C09.

above HIC-2645, HIC-2646, NEGATIVE CUE: no flow indicated on COg. (K02-HIC-2647 and HIC-2648.

D4/F6),

END

Page 4 of 4 JPM ID: A1JPM-RO-EOPO8 INITIAL CONDITIONS:

Degraded Power conditions exist. EFW is NOT available AND HPI cooling is inadequate.

INITIATING CUE:

The CRSISM directs you to feed both OTSGs with Service Water per step 67 of 1202.007 Degraded Power.

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE DOCUMENT NO. CHANGE NO.

TITLE: DEGRADED POWER WORK PLAN EXP. DATE NIA SAFETY-RELATED IPTE SET # DYES DNO DYES NO TEMP MOD LEVEL OF USE DYES NO CONTINUOUS D REFERENCE D INFORMATIONAL PROGRAMMATIC EXCLUSION PER EN-LI-100 DYES__NO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distractionllnterruption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First ShiftlLast Shift Knowledge Peer Pressure Procedures ChangelOff Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY I DATE I TIME FORM TITLE: FORM NO. CHANGE NO.

VERIFICATION COVER SHEET 1000.006A 054

CHANGE 1202.007 DEGRADED POWER 009 PAGE 33 of 64 INSTRUCTIONS CONTINGENCY ACTIONS

65. f CET temps are superheated AND moving away from the saturation line, THEN GO TO 1202.005, INADEQUATE CORE COOLING procedure while attempting to restore buses per step 71 of this procedure.

66. IF EFW is expected to become available before CET temps indicate superheated, THEN RETURN TO step 62.

NOTE

• Service Water feed alone may only slow the rate of heatup.

• SG level will not be established if feed is from service water.

67. IF no EFW is available, THEN feed SGs with Service Water via EFW system as follows:

A. Dispatch an operator to close Minimum RECIRC ISOL for P-7A and B (FW-11A and B).

B. Operate ATM Dump Control System to B. IF ATM Dump ISOL valve is de-energized, depressurize SGs to 0 psig. THEN dispatch an operator to hand jack associated ATM Dump CNTRL Valve fully SGA SGB open (Refer to Alternate Shutdown CV-2676 ATM Dump CV-2619 (1203.002), Exhibit A).

ISOL CV-2668 ATM Dump CV-2618 CNTRL C. Perform the following to start the third C. GO TO step 67.D.

Service Water pump:

1) IF ESAS has actuated, THEN verify one pair of Service Water Crossties open.

P4A to P4B CV-3644 & 3646 P4B to P4C CV-3640 & 3642

2) Start third Service Water pump D. Open EFW SERV WTR Loop I and II Isolations (CV-3850 and 3851).

(67. CONTINUED ON NEXT PAGE)

CHANGE 1202.007 DEGRADED POWER 009 PAGE 34 of 64 INSTRUCTIONS CONTINGENCY ACTIONS

67. (Continued).

E. Take P-7A and B SUCT Select switches to SW.

F. Open all EFW ISOL and EFW CNTRL valves in MANUAL while maintaining EFW flow to each SG 200 gpm.

(modulating valves).

68. Check CET temps begin to drop. 68. Hold at this point until one of the following conditions is met, while attempting to restore buses per step 71.

A. IF EFW becomes available, THEN GO TO step 70.

B. IF CET temps begin to drop, THEN GO TO 1202.011, HPI COOLDOWN while attempting to restore buses per step 71 of this procedure.

C. if CET temps are superheated AND moving away from the saturation line, THEN GO TO 1202.005, INADEQUATE CORE COOLING procedure while attempting to restore buses per step 71 of this procedure.

69. GO TO 1202.011, HPI COOLDOWN while attempting to restore buses per step 71 of this procedure.

70. IF EFW becomes available, THEN perform the following:

A. Dispatch an operator to open Minimum RECIRC ISOL for P7A and B (FW-1 1A and B).

(70. CONTINUED ON NEXT PAGE)

Page 1 of 5 JOB PERFORMANCE MEASURE Date:

Unit: 1 Rev # 9 JPM ID: A1JPM-RO-1CW02 System/Duty Area: Intermediate Cooling Water Task: Perform Switching of ICW Pumps (P-33A/B/C)

JTA# ANO1-RO-ICW-NORM-27 KA Value RO 3.3 SRO 3.6 KA

Reference:

008 A2.01 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: Plant Site Simulator Lab Testing Method: Perform Simulate Approximate Completion Time in Minutes: 10 Minutes Reference(s): 1104.028 Section 1 0.0 Examinees Name: KCN:

Evaluators Name:

The Examinees 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.

Page 2 of 5 JPM ID: A1JPM-RO-ICWO2 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner should verify that the examinee has been briefed per the JPM Examination Briefing Sheet EN-TQ-1 14 .5.

JPM INITIAL TASK CONDITIONS:

Unit 1 is at 100% power steady state conditions. The lAO reports that P-33A has high vibrations and is making an unusual noise. P-33A and P-33C ICW Pumps are presently in service. P-33B ICW pump has NOT been drained and it is NOT desired to install the plug on the ICW surge tank drain.

TASK STANDARD:

P-33B ICW Pump supplying non-nuclear ICW, ICW Pump P-33A is secured.

TASK PERFORMANCE AIDS:

1104.028 Section 10.0

Page 3 of 5 JPM ID: A1JPM-RO-ICWO2 INITIATING CUE: The CRS/SM directs you to start P-33B ICW Pump and then secure P-33A ICW pump using 1104.028 Section 10.0.

C PERFORMANCE CHECKLIST STANDARD N/A SAT UNSAT lIE desired, THEN install plug on the ICW surge tank drain line Plug is not installed on the ICW surge POSITIVE CUE: tank drain line.

It is not desired to install a plug on the ICS surge tank drain line.

2. Open ICW Pumps (P-33A to P-33B)

Suction Crossconnect valve CV-2240, POSITIVE CUE:

has red light ON and green CV-2240 Opened CV-2240 on panel C09.

NEGATIVE CUE:

CV-2240 has green light ON and red light OFF.

3. Open ICW Pumps (P-33A to P-33B)

Discharge Crossconnect valve CV-2238.

POSITIVE CUE:

C CV-2238 has red light ON and green Opened CV-2238 on panel C09.

light OFF.

NEGATIVE CUE:

CV-2238 has green light on and red light off.

INSTRUCTOR CUE: Inform Examinee that it is not necessary to vent P-33B ICW Pump at this time.

4. Start ICW Pump P-33B.

POSITIVE CUE:

Started ICW Pump P-33B using C Red light ON green light OFF for P-33B.

handswitch on panel C09.

NEGATIVE CUE:

Green light ON red light OFF for P-33B.

5. Stop ICW Pump P-33A.

POSITIVE CUE: Waited 3 minutes and then placed C Green light ON red light OFF for P-33A, the handswitch for ICW Pump P-33A in the trip/stop position.

NEGATIVE CUE:

Red light ON green light OFF for P-33A,

Page 4 of 5

6. Verify flow is normal on ICW Coolers Inlet Flow Non-Nuc indicator (Fl 2218) on C09. Verified normal ICW flow on FI-2218 on C09 for the Non-Nuclear loop.

POSITIVE CUE:

Flow is 1800-2000 gpm on FI-2218.

7. If desired, THEN station operator to monitor ICW surge tanks for overflow.

ICW surge tanks are monitored for overflow.

POSITIVE CUE:

An operator has been stationed to monitor for ICS surge tank overflow.

END

Page 5 of 5 JPM ID: A1JPM-RO-ICWO2 INITIAL CONDITIONS:

Unit I is at 100% power steady state conditions. The lAO reports that P-33A has high vibrations and is making an unusual noise. P-33A and P-33C ICW Pumps are presently in service. P-33B ICW pump has NOT been drained and it is NOT desired to install the plug on the ICW surge tank drain.

INITIATING CUE:

The CRSISM directs you to start P-33B ICW Pump and then secure P-33A ICW pump using 1104.028 Section 10.0.

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE DOCUMENT NO. CHANGE NO.

TITLE: ICW SYSTEM OPERATING PROCEDURE WORK PLAN EXP. DATE NIA SAFETY-RELATED IPTE SET# EYES EJNO EYES INO TEMP MOD LEVEL OF USE YES QNO CONTINUOUS E REFERENCE EJ INFORMATIONAL PROGRAMMATIC EXCLUSION PER EN-LI-i 00 EJYES__NO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distraction/Interruption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First Shift/Last Shift Knowledge Peer Pressure Procedures ChangelOff Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY I DATE I TIME FORM TITLE: FORM NO. CHANGE NO.

VERIFICATION COVER SHEET 1000.006A 054

i PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

PAGE: 31 of 118 1104.028 ICW SYSTEM OPERATING PROCEDURE CHANGE: 029 NOTE Stopping an ICW pump can cause CRD SUPPLY FILTER AP HI (K08-Dl) and RCP MOTOR COOLING FLOW LO (K08-E6).

10.0 Switching 1CM Pumps (P33A, B, or C)

CAUTION When switching ICW Pump alignment, running both pumps in parallel for 3 minutes reduces the possibility of trapped air causing a system transient.

NOTE The Non-Nuclear loop normally has a higher activity level than the nuclear loop. If both loops are crossconnected via the 1CM Surge Tank drain line, Non-Nuclear loop process monitor activity will lower and nuclear loop process monitor activity will rise, possibly to the alarm setpoint.

10.1 IF desired to start P33B AND secure P33A, WHEN P33A and P-33C are running, THEN perform the following:

CAUTION

• During filling of P-33A ICW pump following maintenance, air entrained in the ICW system following venting was carried throughout the system resulting air binding of 1CM components. CRANO-l-2006006l2

• Restoration of an ICW pump following maintenance with ONLY one train of CRD cooling available should be evaluated prior to starting. Air entrained in the ICW pump discharge can degrade CR0 cooling flow.

• Leakage between ICW loops can foul CRD Filters. When there is leakage between loops, raise monitoring of CRD Prefilters (F6lA & B) and CRD Cooling Water Filters (F20A & B)

• Opening the ICW pump discharge cross-connect valve(s) prior to opening the suction crossconnect valve(s) can result in overflowing the Nuclear ICW Surge Tank due to pressure differences in the ICW loops.

10.1.1 IF P-33B has been drained, THEN perform the following:

A. Verify the following valves closed:

• ICW Pump P33B Disch Isol (ICW3B)

• ICW Pump P-33B Suct Isol (ICWlB)

• ICW Pump P-33B Vent (ICWll9l)

• 1CM Pump P33B Disch Line Drain (ICW-ll77A)

• 1CM Pump P-33B Suct Line Drain (ICW-l177B)

B. Periodicaiiy monitor 1CM expansion tank ievei during refiii.

PROC IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

PAGE: 32 of 118 1104.028 ICW SYSTEM OPERATING PROCEDURE CHANGE: 029 C. Slowly open ICW-lB.

D. Throttle open ICWll77A.

E. WHEN air is vented, THEN close ICWll77A.

F. Open ICW-3B.

G. Vent all of the CRD Cooling system components per Venting CRD Cooling System Components, exhibit of this procedure.

10.1.2 IF desired, THEN install plug on the ICW surge tanks drain line.

A. Open the following valves:

• ICW Surge Tk T37A Drn to Aux Bldg (ICW-l3OA)

• ICW Surge Tk T37B Drn to Aux Bldg (ICW130B) 10.1.3 Open A/B crossconnect valves:

A. ICW Pumps Suction Crossconnect (CV-2240)

B. ICW Pumps Discharge Crossconnect (CV-2238) 10.1.4 Vent P-33B as necessary by opening ICW Pump P-33B Vent (ICW-llSl)

A. Close ICWll9l.

10.1.5 Start P-33B.

A. IF CRD cooling pumps indicate air binding (i.e.

lowering pump discharge pressure, flow oscillations or standby pump start),

THEN perform Venting CRD Cooling System Components, exhibit of this procedure.

NOTE Pressure and flow instabilities from stopping P33A in the next step can cause a CRD cooling pump (P-79A/B) to auto-start.

10.1.6 WHEN P33B has run at least 3 minutes, THEN stop P33A.

10.1.7 Verify flow is normal (-2000 gpm) on ICW Coolers Inlet Flow Non-Nuc (FI-22l8) (C09) 10.1.8 IF desired, THEN station operator to monitor ICW Surge Tanks for overflow.

i PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: I PAGE: 33 of 118 1104.028 ICW SYSTEM OPERATING PROCEDURE CHANGE: 029 10.2 IF desired to start 1GW pump P-33B AND secure P-33C, WHEN P33A and P-33C are running, THEN perform the following:

CAUTION

• During filling of P-33A 1GW pump following maintenance, air entrained in the 1GW system following venting was carried throughout the system resulting air binding of 1GW components. CR-ANO-l-2006-006l2

• Restoration of an ICW pump following maintenance with ONLY one train of CRD cooling available should be evaluated prior to starting. Air entrained in the 1GW pump discharge can degrade CRD cooling flow.

• Leakage between 1GW loops can foul GRD Filters. When there is leakage between loops, raise monitoring of GRD Pre-filters (F-6lA & B) and GRD Cooling Water Filters (F20A & B)

• Opening the 1GW pump discharge cross-connect valve(s) prior to opening the suction cross-connect valve(s) can result in overflowing the Nuclear 1GW Surge Tank due to pressure differences in the 1GW loops.

10.2.1 IF P33B has been drained, THEN perform the following:

A. Verify the following valves closed:

• 1GW Pump P33B Disch Isol (IGW-3B)

• 1GW Pump P33B Suct Isol (IGW-lB)

• 1GW Pump P33B Vent (IGW-ll9l)

• 1GW Pump P33B Disch Line Drain (IGW-1177A)

• 1GW Pump P33B Suct Line Drain (IGWll77B)

B. Periodically monitor 1GW expansion tank level during refill.

C. Slowly open 1GW-lB.

D. Throttle open IGW1177A.

E. WHEN air is vented, THEN close IGW1177A.

F. Open IGW-3B.

G. Vent all of the GRD Cooling system components per Venting GRD Cooling System Components, exhibit of this procedure.

10.2.2 IF desired, THEN install plug on the 1GW surge tan&s drain line.

A. Open the following valves:

• 1GW Surge Tk T-37A Drn to Aux Bldg (IGW-l3OA)

• 1GW Surge Tk T-37B Drn to Aux Bldg (IGW-130B)

PROC/WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: I PAGE: 34 of 118 1104.028 ICW SYSTEM OPERATING PROCEDURE CHANGE: 029 10.2.3 Open 3/C crosscornect valves:

A. ICW Pumps Suction Crossconnect (CV2241)

B. ICW Pumps Discharge Crossconnect (CV2239) 10.2.4 Vent P-33B as necessary by opening ICW Pump P33B Vent (ICW-ll9l)

A. Close ICW119l.

10.2.5 Start P33B.

A. IF CR0 cooling pumps indicate air binding (i.e.

lowering pump discharge pressure, flow oscillations or standby pump start),

THEN perform Ventino CRD Cooling System Components, exhibit of this procedure.

]C.2.6 WHEN P-33B has run at least 3 minutes, THEN stop P-33C.

10.2.7 Verify flow is normal (2000 gpm) on ICW Coolers Inlet Plow Nuclear (P1-2219) (C09) 10.2.8 IF desired, THEN station operator to monitor ICW Surge Tanks for overflow.

10.3 IF desired to star: ICW Pump P-33A AND secure P331*,

WHEN P33B and P33C are running, THEN perform the following:

CAUTION

• During filling of P-33A ICW pump following maintenance, air entrained in the ICW system following venting was carried throughout the system resulting air binding of ICW components. CR-ANO-1-2006-006l2

• Restoration of an ICW pump following maintenance with ONLY one train of CRD cooling available should be evaluated prior to starting. Air entrained in the ICW pump discharge can degrade CR0 cooling flow.

10.3.1 IF P-13A has been drained, THEN perorm tOC followIng:

A. Verify the following vaLves closed:

• ICH PUrLp P33A Disch Isol (ICW3A)

• ICW Pump P-33A Suct Isol (ICWlA)

• ICW Pump P-33A Vent (ICW-ll93)

• ICW Pump P-33A Eisch Line Drain (ICW-ll76A)

• ICW Pump P-33A Suct Line Drain (ICW-1l76B)

B. Periodically monitor ICY expans.i.on tank leceL dorhnc IL. p

I PROC/WORK PLAN NO. I PROCEDUREIWORK PLAN TITLE: I PAGE: 35 of 118 1 1104.028 ICW SYSTEM OPERATING PROCEDURE CHANGE: 029 C. Slowly open ICW-1A.

C. Throttle open ICW1l76A.

B. WHEN air is vented, THEN close ICW1176A.

F. Open ICW-3A.

G. Vent all of the CRD Cooling system components per Venting CRD Cooling System Components, exhibit of this procedure.

10.3.2 Vent P33A as necessary by opening NonNuc ICW Pump P33A Vent (ICWll93)

A. Close ICWl193.

10.3.3 Start P-33A.

A. IF CRD cooling pumps indicate air binding (i.e.

lowering puop discharge pressure, flow oscillations or standby pump start),

THEN perform Venting CRD Cooling System Components, exhibit of this procedure.

10.3.4 WHEN P33A has run at least 3 minutes, THEN stop P33B.

10.3.5 Verify flow is normal (2000 gpm) on ICW Coolers Inlet Flow Non-Nuc (FI-2218) (C09) 10.3.6 Close A/B crossccrmect valves:

A. ICH Pumps Discharge Crossconnect (CV2238)

B. ICW Pumps Suction Crossconnect (CV-2240) 10.3.7 IF installed, THEN perform the following to remove the plug installed on the ICW surge tanks drain line:

A. Close the following valves:

• 10W Surge 1K 1-i IA Drn to Aux 3idg (ICW-T3CA)

• ICW Surge Tk T-37B Drc to Aux Bldg (ICW-l3OB>

B. Remove plug from ICW surge tanks drain line.

PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

PAGE: 36 of 118 1104.028 ICW SYSTEM OPERATING PROCEDURE CHANGE: 029 10.4 IF desired to start lOW Pump P33C AND secure P-333, WHEN P-33A and P-33B are running, THEN perform the following:

CAUTION During filling of P-33A ICW pump following maintenance, air entrained in the ICW system following venting was carried throughout the system resulting air 10.4.1 IF P33C has been drained, THEN perform the following:

A. Verify the following valves closed:

• lOW Pump P33C Disch Isol (1CW30)

• TOW Pump P330 Suct Tsoi (IOWlC)

• lOW Pump P-33C Vent (ICW-ll94)

• ICH Pump P33C Disch Line Drain (ICW-ll78A)

• lOW Pump P33C Suct tine Drain (IOW-ll78B)

B. leriodically monitor ION expansion rank level during refill.

C. Slowly open TCW-lC.

P. Throttle open ICWll78A.

H. WHEN air is vented, THEN close IOWll7SA.

F. Open ICW-3C.

C. Vent all of the CRD Cooling System Components per Venting ORD Cooling System Components, exhibit of otis procedure.

f PROC/WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: I PAGE: 37 of 118 1104.028 ICW SYSTEM OPERATING PROCEDURE CHANGE: 029 10.4.2 Vent ?-33C as necessary by opening Nuc ICW Pump P33C Vent (ICW1l94)

A. Close ICW1194.

10.4.3 Start P-33C.

A. IF CRD cooling pumps indicate air binding (i.e.

lowering pump discharge pressure, flow oscillations or standby pump start),

THEN perform Venting CRD Cooling System Components, exhibit of this procedure 10.4.4 WHEN P-33C has run at least 3 minutes, THEN stop P33B.

10.4.5 Verify flow is normal (2000 gpm) on ICW Coolers Inlet Flow Nuclear (P12219) (C09) 10.4.6 Close B/C Crossconnect Valves:

A. ICW Pump Discharge Crossconnect (CV2239)

B. ICW Pump Suction Crossconnect (CV224l) 10.4.7 IF installed, THEN perform the following to remove the plug installed on the ICW surge tanks drain line:

A. Close the following valves:

• ICW Surge Tk T37A Drn to Aux Bldg (ICW-l3OA)

• ICW Surge Tk T37B Cm to Aux Bldg (ICWl3OB)

B. Remove plug from ICW surge tanks drain line.

ANO 2011 In-Plant JPMs

Page 1 of 4 JOB PERFORMANCE MEASURE Date:

9 1 Rev #

Unit:

JPM ID: A1JPM-RO-EFWO2 System/Duty Area: Emergency Feedwater Task: Manual Control of Emergency Feedwater Pump P-7A at the Turbine JTA# ANO1-RO-EFW-NORM-7 KA Value RO 3.1 SRO 3.4 KA

Reference:

061 A205 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: Plant Site X Simulator Lab Testing Method: Perform Simulate Approximate Completion Time in Minutes: 10 Minutes Reference(s): 1106.006 EFW Pump Operation Exhibit C (Manual Control of EFW Pump P-7A)

Examinees Name: KCN:

Evaluators Name:

The Examinees 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.

Page 2 of 4 JPM ID: A1JPM-RO-EFWO2 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner should verify that the examinee has been briefed per the JPM Examination Briefing Sheet EN-TQ-1 14 .5.

JPM INITIAL TASK CONDITIONS:

• EFW Pump Turbine K3 tripped on overspeed due to a loss of electric signal to the speed controller.

• Power is unavailable to the speed controller/turbine control cabinet.

• P-7A turbine has been reset per Exhibit A (EFW Pump P-7A Overspeed Trip Reset).

INSTRUCTOR NOTE: FYI EFW Pump Turbine K3 steam admission valves are closed and the trip throttle valve is opened in 1106.006 Exhibit A.

TASK STANDARD:

EFW Pump P-7A running per section 1.0 of 1106.006 Exhibit C (at -14OO discharge pressure).

TASK PERFORMANCE AIDS:

Copy of 1106.006 Exhibit C (Manual Control of EFW Pump P-7A).

Page 3 of 4 JPM ID: A1JPM-RO-EFWO2 INITIATING CUE: The CRS/SM directs you to manually start EFW Pump P-7A and control at approximately 1400 psig discharge pressure per 1106.006 Exhibit C.

UN C PERFORMANCE CHECKLIST STANDARD N/A SAT SAT TRANSITION NOTE: Proceed to EFW pump room on 335 elevation in Controlled Access of Auxiliary Building.

1. Close EFW Turbine K3 Trip/Throttle Valve (CV- Closed CV-6601A by rotating hand 6601A). wheel in close direction C (clockwise).

POSITIVE CUE:

Handwheel does NOT move any further, valve is closed.

2. Request control room to open EFW Turbine K3 Called control room and requested Steam Admission valve (CV-261 3 or CV-2663). CV-261 3 or CV-2663 to be opened.

POSITIVE CUE:

Control Room reports valve is open.

3. Open EFW Turbine K3 Trip/Throttle valve (CV- Slowly opened CV-6601A (counter 6601A). clockwise) until approximately 1400 psig discharge pressure was C POSITIVE CUE: attained.

Pump discharge pressure is approximately 1400 psig.

NEGATIVE CUE:

Pump discharge pressure is approximately 500 psig.

4. Monitor turbine speed indication (if available) to Checked turbine speed locally at ensure turbine does not exceed 3776 RPM or approximately 3650 RPM pump discharge pressure at 1400 psig. monitored pump discharge pressure indication and maintained POSITIVE CUE: at 1400 psig.

Turbine speed is 3650 RPM or pump discharge pressure 1400 psig.

1_____________________________________________

END

Page 4 of 4 JPM ID: A1JPM-RO-EFWO2 INITIAL CONDITIONS:

• EFW Pump Turbine K3 tripped on over speed due to a loss of electric signal to the speed controller.

• Power is unavailable to the speed controller/turbine control cabinet.

• P-7A turbine has been reset per Exhibit A (EFW Pump P-7A Overspeed Trip Reset).

INITIATING CUE:

The CRSISM directs you to manually start EFW Pump P-7A and control at approximately 1400 psig discharge pressure per 1106.006 Exhibit C.

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE DOCUMENT NO. CHANGE NO.

TITLE: EMERGENCY FEEDWATER PUMP 1106.006 080 OPERATION WORK PLAN EXP. DATE NIA SAFETY-RELATED IPTE SET# ZYES QNO DYES QNO TEMP MOD LEVEL OF USE EYES QNO CONTINUOUS Q REFERENCE Q INFORMATIONAL PROGRAMMATIC EXCLUSION PER EN-LI-100 CYES NO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distraction/Interruption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First Shift/Last Shift Knowledge Peer Pressure Procedures ChangelOff Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY DATE TIME FORM TITLE: j FORM NO. CHANGE NO.

VERIFICATION COVER SHEET j 1000.006A 054

I I PROCJWORK PLAN NO.

1106.006 PROCEDUREIWORK PLAN TITLE:

EMERGENCY FEEDWATER PUMP OPERATION PAGE:

CHANGE:

86 of 217 080 I

1106 .006 04 / 03 / 04 EXHIBIT C Page 1 of 2 MANUAL CONTROL OF EMERGENCY FEEDWATER PUMP P-7A NOTE Loss of electrical signal to the speed controller or loss of control oil pressure will allow EFW Turbine K3 Gov Servo (CV660lB) to travel full open and cause an overspeed trip of the turbine.

1.0 IF FEW Pump Turbine 53 tripped either on loss of electroc sognal to speea controller OR on loss of control oil pressure AND fault cannot be corrected, THEN turbine speed may be manually controlled as follows:

1.1 Reset trip per Exhibit A, Emergency Feedwater Pump P-7A Overspeed Trip Reset.

1.2 Close FEW Turbine KS Trip/Throttle Valve (CV-66ClA) by turning handwheel fully clockwise.

1.3 Open EFW Pump Turbine K3 Steam Admission Valve (CV26l3 or CV2663) 1.4 Slowly open CV660lA by turning handwheel counterclockwise until desired turbine speed or discharge pressure is reached.

CAUTION Exceeding turbine speed of 3776 RPM may result in excessive discharge pressure with P7A suction aligned to Service Water.

1.5 Monitor turbine speed OR pump discharge pressure.

1.5.1 Throttle CV660lA as necessary to maintain pump discharge pressure -1400 psig a: FEW P 7A Discharge Pressure (PI28llA) OR as directed by control room personnel.

1.5.2 IF turbine speed indication is available, THEN control turbine speed 3650 RPM.

1.5.3 WHEN failure is corrected, THEN slowly open CV6601A fully while monitoring for proper speed control by the governor valve A. Close CV6601A 3/4 turn tc prevent binding on beatup.

1.5.4 Verify PIA TURBINE TRIP (K12B5) clear.

PROC/WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: I PAGE: 87 of 217 1106.006 EMERGENCY FEEDWATER PUMP OPERATION I CHANGE: 080 1106 .006 04/03/04 EXHIBIT C Page 2 of 2 MANUAL CONTROL OF EMERGENCY FEE DWATER lUMP P-7A 2.0 IF EFW Pump Turbine K3 is in operation, AND manual control is being taken to avoid loss of P-7A due to anticipated loss of control power, THEN perform the following:

NOTE The following step will result in a P7A TURBINE TRIP (K12B5) alarm.

2.1 Slowly throttle closed on EFW Turbine K3 Trip/Throttle Valve (CV-660lA) , until FEW Turbine K3 Gov Servo (CV6601B) is full open, AND FEW P7A Discharge Pressure (PI2811A) drops slightly.

2.2 Notify control room personnel of the following:

• Manual control of P7A has been established

• EFW P7A Turbine Control Power breaker (D2l-30) may be opened, if requi red CAUTION Exceeding turbine speed of 3776 RPM may result in excessive discharge pressure with P7A suction aligned to Service Water.

2.3 Monitor turbine speed or pump discharge pressure.

2.3.1 Throttle CV6601A as necessary to maintain pump discharge pressure l400 psig at FEW P7A Discharge Pressure (PI28llA> OR as directed by control room personnel.

2.3.2 IF turbine speed indication is available, THEN control turbine speed 3650 RPM.

2.4 WHEN failures are corrected AND control power is regained, THEN perform the following:

2.4.1 Verify breaker D2130 is closed.

2.4.2 Siowly open CV-660lA fully while monitoring for proper speed control by the governor valve.

A. Close CV6601A 3/4 turn to prevent binding on heatup.

Page 1 of 5 JOB PERFORMANCE MEASURE Date:

1 Rev #

1 Unit:

JPM ID: A1JPM-RO-ED022 System/Duty Area: Electrical Distribution System Task: Inverter Yl 1 Shutdown with RS1 Supplied from Y-1 1 Alternate AC Source JTA# ANO1-RO-12OAC-NORM-1 1 KA Value RO 3.1 SRO 3.1 KA

Reference:

062 A4.07 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: Plant Site X Simulator Lab Testing Method: Perform Simulate X Approximate Completion Time in Minutes: 10 Minutes Reference(s): 1107.003 Section 8.6 Examinees Name: KCN:

Evaluators Name:

The Examinees performance was evaluated against the standards contained in this JPM and is determined to be:

Satisfactory: Unsatisfactory:

Performance Checklist Comments:

Stop Time Total Time Time Start

• 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.

Page 2 of 5 JPM ID: A1JPM-RO-LD022 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner should verify that the examinee has been briefed per the JPM Examination Briefing Sheet EN-TQ-1 14 .5.

JPM INITIAL TASK CONDITIONS:

Plant is in Cold Shutdown MODE 5. Electricians are standing by in their shop if needed.

TASK STANDARD:

Inverter Y-1 1 is shutdown and inverter loads are being supplied from Alternate AC Power Source.

TASK PERFORMANCE AIDS:

1107.003 Inverter and 120V Vital AC Distribution, Section 8.6.

Page 3 of 5 JPM ID: A1JPM-RO-ED022 INITIATING CUE: The CRS/SM directs you to perform Inverter Yll Shutdown with RS1 to remain in service supplied from Yl 1 Alternate Source. The CRS/SM has entered all applicable TS Conditions and associated time clocks.

C PERFORMANCE CHECKLIST STANDARD N/A SAT UNSAT

1. Check Inverter Yl 1 UNIT IN SYNC Verified Yl 1 UNIT IN SYNC light ON light is ON and frequency is between and frequency between 59.7 and 59.7 and 60.3 hertz. 60.3 hertz.

POSITIVE CUE:

Yl 1 unit in Sync light is ON and frequency is 60 hertz.

2. Shift inverter Yl 1 to the alternate Depressed Yl 1 ALTERNATE AC source. SOURCE TO LOAD push-button (PB-1101).

C POSITIVE CUE:

Inverter Yl 1 ALTERNATE SOURCE TO LOAD push-button depressed.

3. At inverter Yl 1 verify ALTERNATE Verified alternate source supplying SOURCE SUPPLYING LOAD light load by observing ALTERNATE ON and INVERTER SUPPLYING SOURCE SUPPLYING LOAD light LOAD light OFF. ON and INVERTER SUPPLYING LOAD light OFF.

POSITIVE CUE:

Alternate source supplying load light ON and inverter supplying load light OFF.

NEGATIVE CUE:

Inverter supplying load light ON and alternate source supplying load light OFF.

4. Place Yl 1 manual selector switch Placed the Yl 1 manual selector (HS-1 122) in the ALTERNATE switch (bottom switch) to the SOURCE TO LOAD position. ALTERNATE SOURCE TO LOAD C position.

POSITIVE CUE:

Yl 1 manual selector switch is in the ALTERNATE SOURCE TO LOAD position.

Page 4 of 5 STANDARD N/A SAT UNSAT PERFORMANCE CHECKLIST

5. Open Inverter Yl 1 INVERTER Inverter Yl 1 INVERTER OUTPUT OUTPUT breaker on front of Inverter breaker was moved to the open Yl 1 position.

C POSITIVE CUE:

Inverter Output breaker indicates open.

6. Open inverterYll DC INPUT InverterYll DC INPUT breaker was breaker on front of Inverter Yl 1. moved to the open position.

C POSITIVE CUE:

Inverter Output Volt Meter indicates zero.

END

Page 5 of 5 JPM ID: A1JPM-RO-ED022 INITIAL CONDITIONS:

Plant is in Cold Shutdown MODE 5. Electricians are standing by in their shop if needed.

INITIATING CUE:

The CRSISM directs you to perform Inverter Yl I Shutdown with RSI to remain in service supplied from Yll Alternate Source.

The CRSISM has entered all applicable TS Conditions and associated time clocks.

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE DOCUMENT NO. CHANGE NO.

TITLE: INVERTER AND 120V VITAL AC WORK PLAN EXP. DATE REACTIVITY IMPACT NIA DYES DINPR NO SAFETY-RELATED IPTE SET # EYES DNO DYES NO TEMP MOD LEVEL OF USE DYES NO CONTINUOUS D REFERENCE D INFORMATIONAL PROGRAMMATIC EXCLUSION PER EN-LI-100 DYES__NO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distractionhlnterruption Questioning Attitude Multiple Tasks Placekeeping Overconfidence Self Check Vague or Interpretive Guidance Peer Check First ShiftlLast Shift Knowledge Peer Pressure Procedures ChangelOff Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY I DATE I TIME FORM TITLE: FORM NO. CHANGE NO.

VERIFICATION COVER SHEET 1OOOOO6A 055

i PROC/WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 50 of 247 1107M03 INVERTER AND 120V VITAL AC DISTRIBUTION CHANGE: 020 CAUTION Improper breaker operation can result in loss of power to a vital 120V AC panel that could cause a plant trip or upset.

NOTE

• In Modes 14, maintaining RS1 energized from inverter Alternate Source requires entry into TS 3.8.7 Condition A.

• If in Mode 5 or 6, any TS component required by TS 3.8.10 which is supplied by an Inverter on Alternate Source, requires entry into TS 3.8.8 Condition A.

• Steps in this section are expected to bring in alarm RS1 INVERTER TROUBLE K0l-A5.

• Due to past problems with inverter transfers, it is recommended that Electrical Maintenance personnel are present for routine inverter transfers.

8.6 Inverter Yll Shutdown with RS1 to Remain in Service Supplied from Yll Alternate Source 8.6.1 Enter applicable TS Condition and associated time clock.

8.6.2 IF RS1 NOT on Yll Alternate Source, THEN perform the following to transfer RS1 to Y11 Alternate Source:

A. Check Inverter Yll UNIT IN SYNC light is ON by direct observation OR Electrical Maintenance verification.

B. Check Inverter Yll frequency is between 59.7 and 60.3 hertz.

CAUTION Transferring out of sync can cause loss of load. If UNIT IN SYNC light is IOT on, Electrical Maintenance assistance is required.

C. Depress Yll ALTERNATE SOURCE TO LOAD pushbutton (PB-llOl)

D. Check Yll ALTERNATE SOURCE SUPPLYING LOAD light ON by direct observation OR Electrical Maintenance verification.

E. Check Yli INVERTER SUPPLYING LOAD light off.

PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: I PAGE: 51 of 247 1107.003 INVERTER AND 120V VITAL AC DISTRIBUTION CHANGE: 020 NOTE

• If ALTERNATE SOURCE SUPPLYING LOAD light is on, the load remains on Alternate Source regardless of position of manual selector switch.

• If manual selector switch is in ALTERNATE SOURCE TO LOAD position, the load remains on Alternate Source regardless of position of static switch.

8.6.3 Place Yll manual selector switch (HS-1122) in ALTERNATE SOURCE TO LOAD position.

NOTE

• Idle inverters should be shut down to minimize extra heat generation in the room.

• Idle inverters may remain energized for maintenance activities.

8.6.4 Perform the following to shutdown Inverter Yll:

A. Open Inverter Yll INVERTER OUTPUT breaker on front of Inverter Yll.

B. Open Inverter Yll DC INPtT breaker on front of Inverter Yll.

Electrical or N/A

Page 1 of 4 JOB PERFORMANCE MEASURE Date:

1 # 0 Rev Unit:

JPM ID: A1JPM-RO-LRWO1 System/Duty Area: Radioactivity Release Task: Perform Liquid Radiation Release of T-16A TWMT JTA# ANO1-WCO-CZ-NORM-1 1 KA Value RO 3.8 SRO 4.3 KA Reference 2.3.11 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: X Simulator: Perform Lab:

Position Evaluated: RO: SRO:

Actual Testing Environment: Simulator: Plant Site: X Lab:

Testing Method: Simulate: X Perform:

Approximate Completion Time In Minutes: 10 Minutes Reference(s): OP-i 104.020 Clean Waste System Operation Examinees Name: KCN:

Evaluators Name:

The Examinees 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.

Page 2 of 4 JPM ID: A1JPM-RO-LRW01 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner should verify that the examinee has been briefed per the JPM Examination Briefing Sheet EN-TQ-114 .5.

JPM INITIAL TASK CONDITIONS:

The plant is at 100% power operations.

Treated Waste Monitor Tank (TWMT) T-16A Liquid Release Permit 1104.020 Attachment Bi is complete through Step 3.6. The release is ready to be performed beginning at step 4.0 of Attachment Bi.

TASK STANDARD:

Commence T-16A TWMT Release per Step 4.0 This is an Alternate Success Path JPM.

TASK PERFORMANCE AIDS: 1104.020 Attachment Bi.

Page 3 of 4 JPM ID: A1JPM-RO-LRW01 INITIATING CUE: The SM/CRS directs you to commence a T-16A TWMT release per Step 4.0 of OP-i 104.020 Attachment Bi.

C PERFORMANCE CHECKLIST STANDARD N/A SAT 1 Verify CZ Disch to Flume Flow (CV-4642) closed. Verified CZ Disch to Flume Flow (CV-4642) closed (on Clean Waste Panel Cii2).

POSITIVE CUE:

CV-4642 closed, green light ON, red light OFF

2. Verify T-16A X-fer Pump (P-47A) stopped. Verified T-16A X-fer Pump (P 47A) stopped (on Clean Waste Panel C112 or at local POSITIVE CUE: handswitches on 326 in Aux Bldg).

P-47A stopped, green light ON, red light OFF.

3. Verify Treated Waste Monitor Tank T-16A Inlet Verified Treated Waste Monitor (CZ-47A) closed. Tank T-16A Inlet (CZ-47A) closed (in T16AJB Tank Room 335 Aux Bldg).

POSITIVE CUE:

Valve stem fully inserted into valve body.

Treated Waste Monitor Tank T-16A Inlet (CZ-47A) verified closed by holding chain and moving the valve hand wheel in the closed direction

4. Verify Treated Waste Monitor Tank T-16A Inlet Verified Treated Waste Monitor (CZ-47A) tagged. Tank T-16A Inlet (CZ-47A) is tagged, identified tag is missing.

C FAULTED CUE:

Treated Waste Monitor Tank T-16A Inlet (CZ-47A) TAG IS MISSING.

5. Terminate release. Operator recognizes requirement and does not proceed with the C release.

INSTRUCTOR CUE Once operator recognizes the release process cannot continue inform the candidate, This JPM is complete.

END

Page 4 of 4 JPM ID: A1JPM-RO-LRWO1 INITIAL CONDITIONS:

The plant is at 100% power operations.

Treated Waste Monitor Tank (TWMT) T-16A Liquid Release Permit 1104.020 Attachment BI is complete through Step 3.6.

The release is ready to be performed beginning at step 4.0 of Attachment BI.

INITIATING CUE:

The SMICRS directs you to commence a T-16A TWMT release per Step 4.0 of OP-1104 020 Attachment BI.

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE DOCUMENT NO. CHANGE NO.

TITLE: CLEAN WASTE SYSTEM OPERATION WORK PLAN EXP. DATE NIA SAFETY-RELATED IPTE SET # DYES QNO DYES NO TEMP MOD LEVEL OF USE EYES CNO CONTINUOUS Q REFERENCE Q INFORMATIONAL PROGRAMMATIC EXCLUSION PER EN-LI-IGO DYES__NO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distractionhl nterruption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First ShiftlLast Shift Knowledge Peer Pressure Procedures ChangelOff Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY DATE TIME FORM TITLE: FORM NO. CHANGE NO.

VERIFICATION COVER SHEET 1000.006A 054

PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 143 of 176 1104.020 CLEAN WASTE SYSTEM OPERATION CHANGE: 051 ATTACHMENT El Page 5 of 9 4.0 Release (Operations)

CAUTION Unauthorized discharge to Lake Dardanelle via the flume shall be avoided.

4.1 Verify Liquid Haste Dump to Flume (CV4642) closed.

4.2 Verify T-l6A X-fer Pump (P47A) stopped.

NOTE Tag contains information to remind personnel that tank is isolated for chemistry sample.

4.3 Verify Treated Haste Monitor Tank T16A Inlet (CZ47A) closed AND tagged.

4.3.1 IF tag is missing OR has been removed since tank was last sampled, THEN perform the following:

A. Terminate this release.

B. Install tag on Treated Haste Monitor T16A Inlet (CZ-47A)

C. Submit new release permit to Chemistry.

4.4 Verify Treated Waste Monitor Tank Tl6A Outlet (CZ-48A) open.

4.5 Verify LRW Disch Filter (F560) inservice by performing the following:

4.5.1 Verify the following valves open:

• tRW Disch Filter F560 bier (CZ74)

• LRW Disch Filter F-560 Outlet (CZ-77) 4.5.2 Verify LRW Disch Filter F-560 Bypass (CZ-83) closed.

4.6 Verify Treated Waste Disctarge Valve to Header from P47B (CZ55B) closed.

4.7 Verify Treated Haste Nonitcr Tank T16A Recirc Inlet (CZ54A) closed.

4.8 Open Treated Waste Discharge Valve to Header from P47A (CZ55A) 4.9 Open Treated Waste Discharge to Circ Water Flume (0358).

PROC/WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 144 of 176 1104.020 CLEAN WASTE SYSTEM OPERATION CHANGE: 051 ATTACHMENT Bl Page 6 of 9 4.10 Verify Treated Waste Monitor Pump Discharge to Clean Waste Tanks (CZ-57) closed.

4.11 Verify Unit 1/Unit 2 Liquid Radwaste Manifold Isol (CZ87) closed.

4.12 Verify Suction Crossover on Treated Waste Monitor Pumps (CZ50) closed.

4.13 IF Liquid Radwaste Process Monitor (RI4642) is inoperable OR unavailable, THEN perform the following (ODCM App.l, L2,l.l) 4.13.1 verify FWMT Disch to CW Plumes (DZ25) closed.

4.13.2 Verify LZ Drain Pump P45 Discharge to Flume (LZ-5) closed.

4.13.3 Person qualified as Waste Control Operator, independently verify release path valve alignment prior to release (ODCM App.l, Table 2.11).

Verified by 4.14 Notify control room of intent to begin release.

4.15 Commence Treated Waste Monitor Tank (T-16A) release as follows:

4.15.1 Start T-l6 X-fer Pmp (P-47A) 4.15.2 Place Liquid Waste Dump to Flume (CV-4642) handswitch to OPEN.

CAUTION Use of flow rate greater than allowable by the release permit may violate ODCM limits for release and nay be NRC reportable.

NOTE Allowable Release Flow Rate is listed in the Max Waste (CPM) column cf the Preliminary Report.

4.15.3 Note Max Flow rate from Preliminary Report (gpo).

4.15.4 Open/ti-irottle open Liquid Waste Dump to Flume (CV4642) by turning CS Disch to Flume Flow Controller (FIC-4642) Sanual Adjust knob clockwise to commence release, while NOT exceeding Max Flow rate entered above.

i PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: I PAGE: 145 of 176 I 1104.020 CLEAN WASTE SYSTEM OPERATION 051 CHANGE:

ATTACHMENT 81 Page 7 of 9 4.16 WHEN release has started, THEN perform the following:

4.16.1 Perform one of the following AND mark the other N/A:

• IF Discharge Flow to Flume (FI4642) is operable, THEN Control Room personnel shall observe FI-4642 AND verify release flow rate is allowable release flow rate for total ciro water flow.

(Ref. ODCM App. 1, Table 2.1-2)

• IF Discharge Flow to Flume (FI-4642) is inoperable, THEN release may continue provided:

Estimate flow rate at least once every four hours during release.

Refer to ODCM App. 1, Table 2.1-1.

Document occurrence with a Condition Report.

NOTE If a Elant Computer tabular tog (DUMP) is used instead of Process Radiation Monitoring Effluent Recorder (RR4830), then the tabular log shall contain at least points R4642, R36l8 and be set at 5 minute intervals and cover the duration of the release.

4.16.2 IF Process Radiation Monitoring Effluent Recorder (FR4830) is available, THEN record the following data on RR-4830.

OTHERWISE verify Plant Computer tabular log is activated and record data on it.

A. Release start time Date B. Release permit number C. Nane and number of tank being released: TWMT (T16A) 4.16.3 Notify RP that Treated Waste Monitor Tank (T-l6A) release has started and LRW Disch Filter (F560) should be periodically monitored for red levels.

4.16.4 Notify Chemistry that Treated Waste Monitor Tank (Tl6A) release has started.

PROC.IWORK PLAN NO. PROCEDUREJWORK PLAN TITLE: I PAGE: 146 of 176 1104.020 CLEAN WASTE SYSTEM OPERATION CHANGE: 051 ATTACHMENT Bl Page 8 of 9 CAUTION nt in bottom of tank Pumping radioactive liquid tanks empty can cause sedime This can produc e higher radiation to be deposited in discharge piping.

discha rge piping than previo usly existed.

areas in the vicinity of the 4.17 Check Treated Waste Monitor Tanks (T16A/B) levels AND verify only T-l6A is being released.

NOTE Liquid Radwaste Disch Filter (F560) inlet press should not exceed 25 psig.

4.17.1 Monitor tRW Disch Filter (F560) during release for a rise in inlet pressure.

4.17.2 IF tRW Disch Filter F560 Inlet Press (P14606)

>25 psig, THEN perform the following:

A. Stop Tl6 Xfer Pmp (P47A)

B. Place Liquid Waste Dump to Flume (CV-4642) handswitch to Close.

C. Perform Backflushing the Liquid Radwaste Discharge Filter (F560) section of this procedure.

D. WHEN backflush is complete, THEN recommence release at step 4.15 of otis attachment.

4.18 WHEN release is complete, THEN perform the following:

4.18.1 Verify Tl6 Xfer Pop (P47A) handswitch in nosmal afterstop.

4.18.2 Verify discharge flow zero gpm.

4.18.3 Notify RP tiat Treated Waste Monitor Tank (Tl6A) release is complete AND that tRW Disch Filter (F560) scuid Se surveyed for red levels to determine the need to back flush F-560.

4.18.4 Pack flush tRW Disch Filter (F560) 5 necessary per RP survey.

Notify conorol room that Treated Waste Monitor Tank (T16A) 4.19 release is complete.

PROC IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

PAGE: 147 of 176 1104.020 CLEAN WASTE SYSTEM OPERATION CHANGE: 051 ATTACHMENT Hi Page 9 of 9 4.20 IF Process Radiation Monitoring Effluent Recorder (RR-4830) is available, THEN record the following data on RR4830.

OTHERWISE record on Plant Computer tabular logsheets.

• Release stop time Date

• Release permit number 4.21 Flush clean waste to discharge flume piping as follows:

4.21.1 Close Treated Waste Discharge Valve to Header from P47A (CZ55A) 4.21.2 Close Treated Waste Discharge to Circ Water Flume (CZ58) 4.21.3 Align demineralized water to discharge piping by opening Condensate Flush Disch Hdr (CS256) 4.21.4 WHEN piping flushed 5 minutes, THEN close Condensate Flush to Disch Header (CS256) 4.22 Place Liquid Waste Dump to Flume CV4642 handswitch (HS4642) to CLOSE.

4.22.1 Check Liquid Waste Dump to Flume (CV-4642) indicating lights show valve closed.

4.23 Verify CS Disch to Flume Flow Controller (FIC4642) in manual.

4.24 Turn FIC4642 Manual Adjust knob fully counter-clockwise to the CLOSED position.

4.25 Record final Treated Waste Monitor Tank (T-16A) level 4.26 Remove tag from Treated Waste Monitor T-l6A Inlet (CZ47A) 4.27 Return release permit with all attachments to CRS/SM.

Performed by Date Reviewed by CRS/SM Date 4.26 Return the following to Chemistry:

• This attachment

• Release permit

• Tabular loqsheens, if used.