ML092810435

Initial Exam 2009-301 Draft Sim/In-Plant JPMs

ML092810435
Person / Time
Site:	Watts Bar
Issue date:	10/08/2009
From:	NRC/RGN-II
To:
References
50-390/09-301, 50-391/09-301
Download: ML092810435 (128)

Text

REV. 0 PAGE 1 0F 128 WATTS BAR NUCLEAR PLANT B.1.a

B.1.a Withdraw Shutdown Banks

REV. 0 PAGE 2 0F 128 WATTS BAR NUCLEAR PLANT B.1.a Task: Withdraw Shutdown Banks

Alternate Path:

Following failure of the group step counters, the reactor trip breakers are opened in accordance with Technical Requirement 3.1.7.

Facility JPM #: B.1.a 2009 May NRC Exam K/A Rating(s):

001 A3.05 3.5/3.5 Task Standard: Withdrawal of shutdown banks is initiated starting with Shutdown Bank A.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator __X__ In-Plant _____ Perform __X___ Simulate ___ _

References

SOI-85.0, Control Rod Drive and Position Indication System, Rev. 38. TR 3.1.7, Reactivity Control Systems, Position Indicating System - Shutdown. AOI-2, Malfunction of Reactor Control System, Rev. 37.

Task Number: RO-085-SOI-85-001 APPLICABLE FOR: RO/SRO RO-085-SOI-85-010 10CFR55.45

CFR: 41.7/45.13 Validation Time: 10 min. Time Critical:

No ===========================================================================

Applicant: ___________________________ _________________ Time Start: ________

NAME SSNTime Finish: ________

Performance Rating: SAT ____ UNSAT ____

Performance Time ___

Examiner: _____________________________

_____________________________/________ NAME SIGNATURE DATE

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

COMMENTS REV. 0 PAGE 3 0F 128 WATTS BAR NUCLEAR PLANT B.1.a SIMULATOR OPERATOR INSTRUCTIONS:

1. Initialize to IC 311. a. Ensure the following items are displayed on the Director Summary Page:

rd19 Shutdown bank a demand counter fails 0

b. Load NRC_Exam_Event_Files.evt from the NRC Exam Flash Drive. Event 20 is set when Shutdown Bank A reaches 100 steps. Malfunction rd19 will enter at this event.

c. Place the simulator in RUN momentarily, and acknowledge all alarms

3. ENSURE 1-NR-92-145 Recorder is selected to Source Range N31 and Intermediate Range N35.

4. Freeze simulator until the performer indicates understanding of the task and time is allowed for control board familiarization.

5. After performer indicates understanding of task, place simulator in run.

Tools/Equipment/Procedures Needed:

Marked copy of SOI-85.01, indicating steps have been performed to Section 5.4, Step 6.

REV. 0 PAGE 4 0F 128 WATTS BAR NUCLEAR PLANT B.1.a READ TO OPERATOR

DIRECTION TO TRAINEE:

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

INITIAL CONDITIONS:

1. A unit startup is in progress following a trip from 100% power due to a generator electrical relay malfunction that occurred 6 days ago.

2. Per the Nuclear Operating Book (NOB), Sheet 7 BANK OVERLAP AND ROD INSERTION LIMITS, the shutdown banks fully withdrawn position is 230 steps.

3. GO-2, Reactor Startup, Section 3.2 Actions Performed Before Startup, is complete to Step [13.10], WITHDRAW Shutdown Rods to fully withdrawn per SOI-85.01.

4. The US/SRO has approved shutdown bank withdrawal.

5. SOI-85.01, Control Rod Drive and Indication System, is being performed and is complete to through Section 5.4, Step 5.

INITIATING CUES:

1. You are to continue the performance of SOI-85.01 at Section 5.4 Step 6, and withdraw the shutdown banks.

2. Notify the SRO when the shutdown banks are fully withdrawn.

REV. 0 PAGE 5 0F 128 WATTS BAR NUCLEAR PLANT B.1.a **Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated

. START TIME: _______

STEP/STANDARD SAT/UNSAT STEP 1.: Obtain the appropriate procedure.

STANDARD: Performer identifies SOI-85.01 and goes to Section 5.4 "Shutdown Banks Withdrawal".

Evaluator Cue: Hand marked-up copy of SOI-85.01 to the performer after the performer successfully identifies the procedure and section.

___ SAT

___ UNSAT

STEP 2: [6] ENSURE 1-RBSS, ROD BANK SELECTOR SWITCH [1-M-4], in MANUAL.

STANDARD: Performer ensures that the Rod Bank Selector Switch RBSS-1 is in MANUAL position.

COMMENTS:

___ SAT

___ UNSAT

STEP 3: [7] OBTAIN SRO Approval to withdraw Shutdown Banks.

STANDARD: If requested, state that SRO approval has been granted.

COMMENTS:

___ SAT

___ UNSAT

REV. 0 PAGE 6 0F 128 WATTS BAR NUCLEAR PLANT B.1.a **Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated

. STEP/STANDARD SAT/UNSAT STEP 4: [8] OBSERVE the following for proper response during Bank Withdrawal:

A. Source Range (SR) ________

B. Intermediate Range (IR) ________

C. Startup Meters ________

D. Nuclear Recorders ________

STANDARD: Performer monitors above parameters as the rods are being withdrawn

COMMENTS:

___ SAT

___ UNSAT

STEP 5: [9] SELECT SD Bank A (SBA) on ROD BANK SELECTOR SWITCH, 1-RBSS.

STANDARD: Performer places Rod Bank Selector switch RBSS-1 in SBA position.

COMMENTS:

Critical Step

___ SAT

___ UNSAT

STEP 6: [10] PLACE 1-FLRM, IN-HOLD-OUT SWITCH, to OUT to begin withdrawing Shutdown Banks A1 and A2 to greater than or equal to 225 Steps.

STANDARD: Performer places 1-FLR to the OUT position and monitors shutdown bank A group A1 and A2 are responding.

COMMENTS:

Critical Step

___ SAT

___ UNSAT

REV. 0 PAGE 7 0F 128 WATTS BAR NUCLEAR PLANT B.1.a **Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated

. STEP/STANDARD SAT/UNSAT STEP 7: [11] MONITOR the following as the Bank is being withdrawn: A. Group Step Counters B. RPIs C. "In-Out" Status Lights D. Rod speed (64 Steps/Minute)

STANDARD: Performer monitors parameters as the rods are being withdrawn.

COMMENTS:

___ SAT

___ UNSAT

Note to evaluator:

Malfunction to fail step counters is to be inserted when Shutdown Bank A the rods reach approximately 100 steps.

Performer may refer to TR-3.1.7. If so, the required action is to open the Reactor Trip breakers.

STEP 9: Open the Reactor Trip Breakers.

Cue: After the reactor trip breakers have been opened state ' We will stop here"

STANDARD: Performer determines the Group 1 step counter is not capable of determining the demand position for each of the Shutdown bank A rods within +

2 steps and opens the reactor trip breakers.

COMMENTS:

Critical Step

___ SAT

___ UNSAT

STOP TIME ________

REV. 0 PAGE 8 0F 10 WATTS BAR NUCLEAR PLANT B.1.b APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO TRAINEE:

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

INITIAL CONDITIONS:

1. A unit startup is in progress following a trip from 100% power due to a generator electrical relay malfunction that occurred 6 days ago.

2. Per the Nuclear Operating Book (NOB), Sheet 7 BANK OVERLAP AND ROD INSERTION LIMITS, the shutdown banks fully withdrawn position is 230 steps.

3. GO-2, Reactor Startup, Section 3.2 Actions Performed Before Startup, is complete to Step [13.10], WITHDRAW Shutdown Rods to fully withdrawn per SOI-85.01.

4. The US/SRO has approved shutdown bank withdrawal.

5. SOI-85.01, Control Rod Drive and Indication System, is being performed and is complete to through Section 5.4, Step 5.

INITIATING CUES:

1. You are to continue the performance of SOI-85.01 at Section 5.4 Step 6, and withdraw the shutdown banks.

2. Notify the SRO when the shutdown banks are fully withdrawn.

REV. 0 PAGE 9 0F 10 WATTS BAR NUCLEAR PLANT B.1.b

B.1.b Place Excess Letdown in Service per AOI-6

REV. 0 PAGE 10 0F 10 WATTS BAR NUCLEAR PLANT B.1.b EVALUATION SHEET Task: Place Excess Letdown in Service per AOI-6.

Alternate Path:

N/A Facility JPM #: 3-OT-JPMR022 Rev 3 K/A Rating(s):

004 A4.06 [3.6/3.1] 004A 1.11 [3.0/3.0] 004 A2.22 [3.2/3.1] 004 A2.22 [3.2/3.1] 2.1.30 [3.9/3.4] 2.1.23 [3.9/4.0]

Task Standard: Excess Letdown has been placed in service per AOI-6, Step 15.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator __X__ In-Plant _____ Perform __X___ Simulate ____

References

AOI-6, "Small Reactor Coolant System Leak", Rev 32.

Task Number: RO-062-SOI-62-007 APPLICABLE FOR: RO/SRO RO-068-AOI-6-001 10CFR55.45: 6, 12 Validation Time: 10 min.

Time Critical:

No ===========================================================================

Applicant: ___________________________ _________________ Time Start: ________

NAME SSNTime Finish: ________

Performance Rating: SAT ____ UNSAT ____

Performance Time ___

Examiner: _____________________________

_____________________________/________ NAME SIGNATURE DATE

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

COMMENTS REV. 0 PAGE 11 0F 10 WATTS BAR NUCLEAR PLANT B.1.b REV. 0 PAGE 12 0F 10 WATTS BAR NUCLEAR PLANT B.1.b SIMULATOR OPERATOR INSTRUCTIONS:

1. Initialize to IC 312. a. Ensure following letdown and charging isolation valves are closed.

a. 1-FCV-62-72.

b. 1-FCV-62-73.

c. 1-FCV-62-74.

d. 1-FCV-62-76.

e. 1-FCV-62-69.

f. 1-FCV-62-70.

g. 1-FCV-62-85.

h. 1-FCV-62-86.

i. 1-FCV-62-90.

j. 1-FCV-62-91.

b. Ensure 1-FCV-62-93 is in manual and seal flow is stable at approximately 8 gpm per RCP seal.

c. Ensure pressurizer level is approximately 66% and rising slowly.

2. Acknowledge all alarms.

3. Place simulator in FREEZE until the performer indicates an understanding of the task. 4. After performer indicates understanding of the task, place simulator to RUN.

Tools/Equipment/Procedures Needed:

A marked up copy of AOI-6, signed off through Step 14, with Step 15 CIRCLED.

REV. 0 PAGE 13 0F 10 WATTS BAR NUCLEAR PLANT B.1.b READ TO OPERATOR

DIRECTION TO TRAINEE:

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

INITIAL CONDITIONS:

1. The Unit is operating at 100 % power.

2. A small leak has been found on the normal letdown path.

3. Letdown and Charging have been isolated per AOI-6, "Small Reactor Coolant System Leak".

4. The RADPRO Supervisor has been informed of the intent to establish Excess Letdown. 5. You are the Operator at the Controls.

INITIATING CUES:

1. The Unit Supervisor has directed you to establish excess letdown to the VCT per AOI-6, Section 3.0, and Step 15, RESPONSE NOT OBTAINED.

2. You are to notify the Unit Supervisor when the excess letdown has been aligned.

REV. 3 PAGE 14 0F 10 WATTS BAR NUCLEAR PLANT B.1.b START TIME: _______

STEP 1: Obtain a copy of the procedure.

STANDARD: A copy of AOI-6 has been obtained.

COMMENTS: ___ SAT

___ UNSAT

STEP 2: Check pressurizer level DROPPING or STABLE.

STANDARD: Performer observes a RISING trend on pressurizer level and enters RESPONSE NOT OBTAINED column for actions.

NOTE: Use of the RNO Column was directed by the INITIATING CUES.

COMMENTS:

___ SAT

___ UNSAT

STEP 3: If pzr level is rising, THEN PLACE excess letdown in service.

STANDARD: Performer enters the RESPONSE NOT OBTAINED column and begins procedure actions.

NOTE: Use of the RNO Column was directed by the INITIATING CUES.

COMMENTS:

___ SAT

___ UNSAT

REV. 3 PAGE 15 0F 10 WATTS BAR NUCLEAR PLANT B.1.b STEP 4 : a. OPEN 1-FCV-70-143

STANDARD: At panel 1-M-27B the perform er places 1-HS-70-143A to OPEN. Performer verifies the RED light is LIT and the GREEN light is OFF. Step is critical to establish excess letdown flow.

NOTE: When the performer opens 1-FCV-70-143, Annunciator 239-D will be received. This alarm occurs whenever 1-FCV-70-143 is OPEN and flow on 1-FS-70-8 is less than

230 gpm.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT STEP 5 : b. OPEN 1-FCV-70-85

STANDARD: At panel 1-M-27B the perform er places 1-HS-70-85A to OPEN and holds the switch to OPEN until the RED light is LIT and the GREEN light is OFF. Step is critical to establish excess letdown flow.

NOTE: When the performer opens 1-FCV-70-85, Annunciator 239-D will clear as soon as flow is greater than 230 gpm Performer may use 1-FI-70-84 (panel 1-M-27B) to monitor flow.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT STEP 6 : c. OPEN 1-FCV-62-54

STANDARD: At panel 1-M-5 the performer places 1-HS-62-54 to OPEN and holds the switch to OPEN until the RED light is LIT and the GREEN light is OFF. Step is critical to establish excess letdown flow.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

REV. 3 PAGE 16 0F 10 WATTS BAR NUCLEAR PLANT B.1.b STEP 7 : d. OPEN 1-FCV-62-55

STANDARD: At panel 1-M-5 the performer places 1-HS-62-55 to OPEN and holds the switch to OPEN until the RED light is LIT and the GREEN light is OFF. Step is critical to establish excess letdown flow.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT STEP 8 : e. ENSURE 1-FCV-62-59 is in NORMAL

STANDARD: At panel 1-M-5 the performer determines that 1-HS-62-59A is in the NORM position, with the RED seal return light LIT.

COMMENTS:

___ SAT

___ UNSAT STEP 9: f. ADJUST 1-HIC-62-56A to obtain maximum flow and maintain excess letdown hx outlet temp less than 200

°F.

STANDARD: At panel 1-M-5 the performer opens 1-HIC-62-56A while monitoring 1-TI-62-58. Excess letdown temperature must remain below 200

°F as indicated on 1-TI-62-58. Step is critical to establish excess letdown flow.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

REV. 3 PAGE 17 0F 10 WATTS BAR NUCLEAR PLANT B.1.b STEP 10: STABILIZE pzr level by adjusting seal injection and excess letdown flows.

STANDARD: At panel 1-M-5 the performer observes pzr level trend on 1-LR-68-339. Performer may also set up a trend of pzr level on ICS computer using inputs from 1-LI-68-339A, 1-LI-68-335A and 1-LI-68-320.

COMMENTS:

___ SAT

___ UNSAT

STEP 11: Notify the Unit Supervisor that Excess Letdown has been placed in service.

STANDARD: The Unit Supervisor has been notified that Excess Letdown has been placed in service.

• • CUE: When notified, acknowledge the report.

COMMENTS:

END OF TASK

___ SAT

___ UNSAT STOP TIME: ________

REV. 0 PAGE 18 OF 128 WATTS BAR NUCLEAR PLANT B.1.c APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO TRAINEE:

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

task. INITIAL CONDITIONS:

1. The Unit is operating at 100 % power.

2. A small leak has been found on the normal letdown path.

3. Letdown and Charging have been isolated per AOI-6, "Small Reactor Coolant System Leak".

4. The RADPRO Supervisor has been informed of the intent to establish Excess Letdown. 5. You are the Operator at the Controls.

INITIATING CUES:

1. The Unit Supervisor has directed you to establish excess letdown to the VCT per AOI-6, Section 3.0, and Step 15, RESPONSE NOT OBTAINED.

2. You are to notify the Unit Supervisor when the excess letdown has been aligned.

REV. 0 PAGE 19 OF 128 WATTS BAR NUCLEAR PLANT B.1.c

B.1.c Isolate Cold Leg Accumulators per E-1

REV. 0 PAGE 20 OF 128 WATTS BAR NUCLEAR PLANT B.1.c Task: Isolate Cold Leg Accumulators per E-1

Alternate Path:

Cold Leg Accumulator cannot be isolated and must be vented to comply with E-1. Facility JPM #: N/A K/A Rating(s):

011 EA1.09 [4.3/4.3] Task Standard: Cold Leg Accumulators 1, 2, and 3 are isolated per E-1 Step 26 AER. Cold Leg Accumulator 4 is vented, per E-1, Step 26 RNO.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator __X__ In-Plant _____ Perform __X___ Simulate ___ _

References

E-1,"Loss of Reactor or Secondary Coolant", Rev. 15 Task Number: RO-063-SOI-63-003 APPLICABLE FOR: RO/SRO 10CFR55.45: 5, 6 Validation Time: 15 min.

Time Critical:

No ===========================================================================

Applicant: ___________________________ _________________ Time Start: ________

NAME SSNTime Finish: ________

Performance Rating: SAT ____ UNSAT ____

Performance Time ___

Examiner: _____________________________

_____________________________/________ NAME SIGNATURE DATE

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

COMMENTS REV. 0 PAGE 21 OF 128 WATTS BAR NUCLEAR PLANT B.1.c SIMULATOR OPERATOR INSTRUCTIONS:

1. Initialize to IC 313 a. Ensure the following items are displayed on the Director Summary Page:

th03a loca-small leak loop 1 100% severity th01a loca-hot leg loop 1 4.5% severity hs-63-67a hs-63-67a sis accumulator tank 4 flow isolation valve Open

b. Ensure that the following remote is set as indicated on the Director Remote Page. sir01 pwr to cold leg accumu isolation valves fcv-63-67, 80, 98, 119 on

c. Place the simulator in RUN momentarily, and acknowledge all alarms.

4. Place simulator in FREEZE until the performer indicates an understanding of the task. 3. After performer indicates understanding of the task, place simulator to RUN.

Tools/Equipment/Procedures Needed:

A marked-up copy of E-1, signed off through Step 25, with Step 26 circled.

REV. 0 PAGE 22 OF 128 WATTS BAR NUCLEAR PLANT B.1.c READ TO OPERATOR

DIRECTION TO TRAINEE:

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

INITIAL CONDITIONS:

1. A large LOCA has occurred.

2. E-1 performance has just been resumed after performance of ES-1.3.

3. You are Control Room Operator.

INITIATING CUES:

1. The Unit Supervisor directs you perform E-1, Step 26, DETERMINE if cold leg accumulators should be isolated.

2. You are to notify Unit Supervisor when you have completed Step 26.

REV. 0 PAGE 23 OF 128 WATTS BAR NUCLEAR PLANT B.1.c START TIME: _______

STEP 1: Obtain a copy of the procedure.

STANDARD: A copy of E-1 has been obtained EXAMINER'S CUE:

After the performer has de monstrated the method of obtaining the correct instruction, the examiner will

provide a marked-up copy of the instruction.

COMMENTS:

___ SAT

___ UNSAT STEP 2: a. ENSURE power to isolation valves restored USING Appendix A (E-1), CLA Breaker Operation.

STANDARD:

EXAMINER'S CUE: When asked, inform the performer that E-1 Appendix A CLA BREAKER OPERATION is complete.

COMMENTS:

___ SAT

___ UNSAT REV. 0 PAGE 24 OF 128 WATTS BAR NUCLEAR PLANT B.1.c STEP 3: CHECK RCS pressure less than 250 psig.

STANDARD: Performer reads RCS pressure from one of the following PAM instruments and determines that pressure is approximately 70 psig.

RVLIS-ICCM PLASMA DISPLAY on 1-M-4 or 1-M-6 Loop 4 HL PRESS 1-PI-68-70 Loop 3 HL PRESS 1-PI-68-64 Loop 2 HL Press 1-PI-68-63

COMMENTS:

___ SAT

___ UNSAT STEP 4: CLOSE cold leg accumulator isolation valves.

STANDARD: Performer places 1-HS-63-118, 1-HS-63-98, 1-HS-63-80 and 1-HS-63-67 to close. Performer observes that 1-HS-63-67 indicating lights do not change, indicating that 1-FCV-63-67, CLA 4 Isolation valve remains OPEN. Step is critical since this action is taken to minimize the chance of nitrogen injection into the RCS.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 5: c. PERFORM the following

STANDARD: Performer determines that RNO actions are required since 1-FCV-63-67 did NOT CLOSE. Step is critical since this action is taken to minimize the chance of nitrogen injection into the RCS.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT REV. 0 PAGE 25 OF 128 WATTS BAR NUCLEAR PLANT B.1.c STEP 6: 1) RESET Phase B STANDARD:

Performer observes the Phase B lights on the Master Isolation Signal Status panels 1-XX-55-6C and 1-XX-55-6D on 1-M-6 are LIT, indicating that Phase B has been actuated.

Performer depresses 1-HS-30-64D B CNTMT ISOL RESET TR-A, and observes the B light goes DARK on 1-XX-55-6C Performer depresses 1-HS-30-64E B CNTMT ISOL RESET TR-B, and observes the B light goes DARK 1-XX-55-6D.

Step is critical since this action is taken to allow the air supply to the nitrogen makeup and vent valves to be restored.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT REV. 0 PAGE 26 OF 128 WATTS BAR NUCLEAR PLANT B.1.c STEP 7: 2) ENSURE aux air pressure to cntmt is greater than 75 psig [M-15] AND OPEN cntmt air supply valves.

STANDARD:

Performer observes air pressure on 0-PI-32-104A, Aux Air A Press and 0-PI-32-105A, Aux Air Press indicate 95 psig and that 1-FCV-32-80, 1-FCV-32-102, and 1-FCV-32-110 are CLOSED.

Performer places 1-HS-30-80A in the OPEN position and holds until RED light is LIT, GREEN light is DARK.

Performer places 1-HS-30-102A in the OPEN position and holds until RED light is LIT, GREEN light is DARK.

Performer places 1-HS-30-110A in the OPEN position and holds until RED light is LIT, GREEN light is DARK.

Step is critical since this action is taken to allow the air supply to the nitrogen makeup and vent valves to be restored.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT REV. 0 PAGE 27 OF 128 WATTS BAR NUCLEAR PLANT B.1.c STEP 8: 3) OPEN any unisolated accumulator's nitrogen makeup valve.

STANDARD: Performer determines that 1-FCV-63-63 for CLA 4 must be OPENED.

Performer places 1-HS-63-63A N2 TO CL ACCUM 4 to OPEN position, and verifies RED light is LIT GREEN light is DARK.

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

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 8: 4) OPEN 1-FCV-63-65 vent header.

STANDARD: Performer rotates 1-HIC-63-65A in the counterclockwise direction to OPEN 1-FCV-63-65 FULLY.

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

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

STEP 9: Notify the Unit Supervisor that E-1, Step 26 is complete.

STANDARD: Performer notifies the Unit Supervisor that Step 26 is complete

COMMENTS:

END OF TASK

___ SAT

___ UNSAT STOP TIME ________

REV. 6 PAGE 28 OF 128 WATTS BAR NUCLEAR PLANT B.1.d APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO TRAINEE:

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

INITIAL CONDITIONS:

1. A large LOCA has occurred.

2. E-1 performance has just been resumed, after performance of ES-1.3.

3. You are Control Room Operator.

INITIATING CUES:

1. The Unit Supervisor directs you perform E-1, Step 26, DETERMINE if cold leg accumulators should be isolated.

2. You are to notify Unit Supervisor when you have completed Step 26.

REV. 6 PAGE 29 OF 128 WATTS BAR NUCLEAR PLANT B.1.d

B.1.d Place RHR Spray in Service per FR-Z.1

REV. 6 PAGE 30 OF 128 WATTS BAR NUCLEAR PLANT B.1.d EVALUATION SHEET Task: Place RHR Spray in Service per FR-Z.1 Alternate Path:

When the performer attempts to close 1-FCV-63-94, the valve will NOT close. This requires entry into the RNO in order to place Train A RHR Spray in service.

Facility JPM #: 3-OT-JPMR016A Rev 5 K/A Rating(s):

005 A4.01 [3.6/3.4]

Task Standard: Train "A" of RHR Spray has been placed in-service per FR-Z.1.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator __X__ In-Plant __ ___ Perform __X____ Simulate ____

References

FR-Z.1, "High Containment Pressure", Rev.10 Task Number: RO-113-FR-Z.1-001 APPLICABLE FOR: RO/SRO 10CFR55.45: 3, 4, 6, 7, 8 Validation Time: 10 min.

Time Critical:

No ===========================================================================

Candidate: ___________________________ _________________ Time Start: ________

NAME SSN/EINTime Finish: ________

Performance Rating: SAT ____ UNSAT ____

Performance Time ___

Examiner: _____________________________

_____________________________/________ NAME SIGNATURE DATE

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

COMMENTS REV. 6 PAGE 31 OF 128 WATTS BAR NUCLEAR PLANT B.1.d REV. 6 PAGE 32 OF 128 WATTS BAR NUCLEAR PLANT B.1.d SIMULATOR OPERATOR INSTRUCTIONS:

1. Initialize to IC 314. a. Ensure the following items are displayed on the Director Summary Page:

th03a loca-small leak loop 1 100% severity th01a loca-hot leg loop 1 4.5% severity ch01a containment pressure transmitter failure pdt-3-42 14 ch01b containment pressure transmitter failure pdt-3-43 14 ch01c containment pressure transmitter failure pdt-3-44 14 ch01d containment pressure transmitter failure pdt-3-45 14 ei-72-12a 07020 cntmt spray pmp b amps 35 fi-72-13 07010 cntmt spray pmp b flow 3000 hs-72-10a-3 06010 cntmt spray pump b mtr sw(red) on hs-72-10a-1 06010 cntmt spray pump b mtr sw(green) off hs-72-27a-1 06020 cntmt spray pump a mtr sw(green) off pdi-30-42 03160 cntmt press diff indicator 12 pdi-30-43 03170 cntmt press diff indicator 12 pdi-30-44 03180 cntmt press diff indicator 12 pdi-30-45 03190 cntmt press diff indicator 12 pdr-30-133-1 03150 cntmt annulus dp indicator 0.5 hs-72-10a hs-72-10a containment spray pump b mtr sw ptlock hs-63-94a Hs-63-94a rhr to rcs cl1_4 flow control valve s open

b. Place the simulator in RUN momentarily, and acknowledge all alarms.

2. Place Hold Order on A CS Pump - handswitch is in PULL-TO-LOCK position

3. Place simulator in FREEZE until the performer indicates an understanding of the task. 4. After performer indicates understanding of the task, place simulator to RUN.

Tools/Equipment/Procedures Needed:

Ensure marked copies of FR-Z.1 are available to the evaluators.

REV. 6 PAGE 33 OF 128 WATTS BAR NUCLEAR PLANT B.1.d READ TO OPERATOR

DIRECTION TO TRAINEE:

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

INITIAL CONDITIONS:

1. 1A-A Containment Spray Pump has been tagged out of service.

2. The unit was at 100% when a Large Break LOCA occurred.

3. 1B-B Containment Spray Pump started and has been spraying Containment.

4. The break occurred an hour and 10 minutes ago.

5. All ECCS equipment is performing it s design functions and is on Containment Sump Recirc.

6. You are the Operator at the Controls (OAC).

INITIATING CUES:

1. The Unit Supervisor directs you to perform FR-Z., "HIGH CONTAINMENT PRESSURE", Step 10, DETERMINE if RHR spray should be placed in service.

2. You are to notify the Unit Supervisor when you have completed Step 10.

REV. 6 PAGE 34 OF 128 WATTS BAR NUCLEAR PLANT B.1.d START TIME: _______

STEP 1: Obtain a copy of the procedure.

STANDARD: A copy of FR-Z.1 has been obtained.

EXAMINER'S CUE:

After the performer has de monstrated the method of obtaining the correct instruction, the evaluator will

provide a marked-up copy of the instruction.

COMMENTS:

___ SAT

___ UNSAT STEP 2: [Step 10] DETERMINE if RHR Spray should be placed in service: a. CHECK the following conditions:

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

• Cntmt Press greater than 9.5 psig.

• RHR suction aligned to the cntmt sump.

• At least one charging pump and one SI pump running

STANDARD: 1. Performer has determined that an hour has lapsed since the beginning of the accident. [Given in initial conditions]

2. Cntmt press has been checked > 9.5 psig.

3. FCV-63-72 and FCV-63-73 verified to be open by red indicating lights. 4. 1 CCP & 1 SIP verified to be running by indicating lights or amps.

COMMENTS:

___ SAT

___ UNSAT REV. 6 PAGE 35 OF 128 WATTS BAR NUCLEAR PLANT B.1.d STEP 3: [STEP 10b]

ALIGN Train B RHR spray:

1) ENSURE Train B RHR pump RUNNING.

STANDARD: Train B RHR pump verified to be running by indicating light or amps. COMMENTS:

___ SAT

___ UNSAT

STEP 4: [STEP 10b 2)] Close RHR crosstie 1-FCV-74-35.

STANDARD: 1-HS-74-35-A has been checked in the CLOSED position and the green light illuminated on HS.

COMMENTS:

___ SAT

___ UNSAT

STEP 5: [STEP 10b 3)] CLOSE RHR injection 1-FCV-63-94.

STANDARD: 1-HS-63-94-A has been placed in the CLOSED position and the performer recognizes that the GREEN light DOES NOT illuminate.

Performer enters the RNO Colu mn to perform actions to align Train A RHR spray. Step is critical since the RHR system is not designed to support both RHR spray and suction requirements associated with sump recirculation.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT EVALUATOR NOTE: Performer may either have US dispatch personnel or will dispatch personnel to investigate the cause of the failure of 1-FCV-63-94.

REV. 6 PAGE 36 OF 128 WATTS BAR NUCLEAR PLANT B.1.d STEP 6: [STEP 10b RNO] ALIGN Train A RHR spray: 1) ENSURE Train A RHR pump RUNNING.

STANDARD: Train A RHR pump verified to be running by indicating light or amps.

COMMENTS:

___ SAT

___ UNSAT STEP 7: [STEP 10b RNO] 2) CLOSE RHR crosstie 1-FCV-74-33.

STANDARD: 1-HS-74-33-A has been placed/checked in the CLOSED position and the green light illuminated on HS.

COMMENTS:

___ SAT

___ UNSAT

STEP 8: [STEP 10b RNO] 3) CLOSE RHR injection 1-FCV-63-93.

STANDARD: 1-HS-63-93-A has been placed in the CLOSED position and the green light illuminated on HS. Step is critical to establish A Train RHR Spray.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT STEP 9: [STEP 10b RNO]

4) OPEN RHR spray 1-FCV-72-40.

STANDARD: 1-HS-72-40A has been placed/checked in the OPEN position and the Red light illuminated on hand switch. Step is critical to establish A Train RHR Spray.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT REV. 6 PAGE 37 OF 128 WATTS BAR NUCLEAR PLANT B.1.d STEP 10: Notify the Unit Supervisor that RHR spray is in service.

STANDARD: Notify the Unit Supervisor that RHR spray has been placed in service. **CUE: When notified, acknowledge the report using repeat back.

COMMENTS:

END OF TASK

___ SAT

___ UNSAT

TIME STOP: ________

REV. 0 Page 38 of 128 WATTS BAR NUCLEAR PLANT B.1.e CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO TRAINEE:

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

task. INITIAL CONDITIONS:

1. 1A-A Containment Spray Pump has been tagged out of service.

2. The unit was at 100% when a Large Break LOCA occurred.

3. 1B-B Containment Spray Pump started and has been spraying Containment.

4. The break occurred an hour and 10 minutes ago.

5. All ECCS equipment is performing it s design functions and is on Containment Sump Recirc.

6. You are the Operator at the Controls (OAC).

INITIATING CUES:

1. The Unit Supervisor directs you to perform FR-Z., "HIGH CONTAINMENT PRESSURE", Step 10, DETERMINE if RHR spray should be placed in service.

2. You are to notify the Unit Supervisor when you have completed Step 10.

REV. 0 Page 39 of 128 WATTS BAR NUCLEAR PLANT B.1.e

B.1.e Place Containment Hydrogen Recombiner "A" in Service per SOI-83.01

REV. 0 Page 40 of 128 WATTS BAR NUCLEAR PLANT B.1.e Task: Place Containment Hydrogen Recombiner A in Service per SOI-83.01.

Alternate Path:

N/A Facility JPM #: 3-OT-JPMR052 K/A Rating(s):

028A2.01 [3.4/3.6] Task Standard: Containment Hydrogen Recombiner A has been placed in service per SOI-83.01.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator __X__ In-Plant _____ Perform __X___ Simulate ___ _

References

E-1, "Loss of Reactor or Secondary Coolant", Rev. 15. SOI-83.01, "Containment Hydrogen Recombiners", Rev. 15. TI-83.01,"Hydrogen Recombiner Required Power-vs.-Containment Pressure Curves", Rev. 1.

Task Number: RO-063-SOI-63-003 APPLICABLE FOR: RO/SRO 10CFR55.45: 5, 6 Validation Time: 15 min.

Time Critical:

No ===========================================================================

Applicant: ___________________________ _________________ Time Start: ________

NAME SSNTime Finish: ________

Performance Rating: SAT ____ UNSAT ____

Performance Time ___

Examiner: _____________________________

_____________________________/________ NAME SIGNATURE DATE

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

COMMENTS REV. 0 Page 41 of 128 WATTS BAR NUCLEAR PLANT B.1.e REV. 0 Page 42 of 128 WATTS BAR NUCLEAR PLANT B.1.e SIMULATOR OPERATOR INSTRUCTIONS:

1. Initialize to IC 315. a. Ensure the following items are displayed on the Director Summary Page:

th03a loca-small leak loop 1 100% severity th01a loca-hot leg loop 1 4.5% severity mux_03c123 125-a cntmt hi-hi press steamline isol on pi-30-310 03110 containment pressure 3.5 pi-30-311 03120 containment pressure 3.5 h2i-43-200 03060 loca h2 cntmt monitor 3.5 h2i-43-210 03070 loca h2 cntmt monitor 3.5 pdi-30-42 03160 cntmt press diff indicator 4 pdi-30-43 03170 cntmt press diff indicator 4 pdi-30-44 03180 cntmt press diff indicator 4 pdi-30-45 03190 cntmt press diff indicator 4

b. Place the simulator in RUN momentarily, and acknowledge all alarms.

2. Place simulator in FREEZE until the performer indicates an understanding of the task. 3. After performer indicates understanding of the task, place simulator to RUN.

Tools/Equipment/Procedures Needed:

Ensure copies of SOI-83.01 and TI-83.01 are available for the evaluator.

REV. 0 Page 43 of 128 WATTS BAR NUCLEAR PLANT B.1.e READ TO OPERATOR

DIRECTION TO TRAINEE:

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

INITIAL CONDITIONS:

1. Unit has experienced a LOCA.

2. MCR crew is following E-1, Loss of Reactor or Secondary Coolant.

3. E-1, directs that the hydrogen recombiners be placed in service using SOI-83.01, Containment Hydrogen Recombiners.

4. You are Control Room Operator.

INITIATING CUES:

1. The Unit Supervisor has directed you to place Hydrogen Recombiner "A" in service, using SOI-83.01, Containment Hydrogen Recombiners.

2. Notify Unit Supervisor when the required power setting is reached

REV. 0 Page 44 of 128 WATTS BAR NUCLEAR PLANT B.1.e START TIME: _______

STEP 1: Obtain a copy of the procedure.

STANDARD: Obtains SOI-83.01 and goes to Section 8.1.

EXAMINER'S CUE:

After the performer has de monstrated the method of obtaining the correct instruction, the evaluator can

provide a copy of the instruction.

COMMENTS:

___ SAT

___ UNSAT CAUTION 1 Temperature of 1400°F is not to be exceeded on any operable thermocouple. CAUTION 2 On DG power, DG load should remain 4400 kW or less. CAUTION 3 If there is any indication Recombiner A is not operating properly (through recombiner instrumentation), the Recombiner should be shutdown, a WR written, and the other Recombiner placed in service.

NOTE: TI-83.01, HYDROGEN RECOMBINER REQUIRED POWER-VS-CONTAINMENT PRESSURE contains the curves that will be needed to adjust the power level for the recombiner.

STEP 2: [1] ENSURE POWER ADJUST potentiometer [1-M-10] set at 000.

STANDARD: Performer verifies that three zeros ("000") are indicated on Panel 1-M-10.

COMMENTS:

___ SAT

___ UNSAT REV. 0 Page 45 of 128 WATTS BAR NUCLEAR PLANT B.1.e STEP 3: [2] VERIFY the White POWER IN AVAILABLE light LIT.

STANDARD: Performer verifies that the White POWER IN AVAILABLE light LIT on 1-M-10.

COMMENTS:

___ SAT

___ UNSAT STEP 4: [3] ENSURE TEMPERATURE CHANNEL (thermocouple selector) is selected for channel 1, 2, or 3.

STANDARD: Performer verifies that the TEMPERATURE CHANNEL (thermocouple selector) is selected for channel 1, 2, or 3.

NOTE Any one of the three settings is acceptable.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 5: [4] ENSURE TEMPERATURE OUT (indicator dial), set on 1400°F.

STANDARD: Performer verifies that the TEMPERATURE OUT (indicator dial), set on 1400°F.

COMMENTS:

___ SAT

___ UNSAT NOTE: Red light on TEMPERATURE OUT (indicator dial) is lit when setpoint selected on indicator is reached.

REV. 0 Page 46 of 128 WATTS BAR NUCLEAR PLANT B.1.e STEP 6: [5] REQUEST Chemistry to sample containment atmosphere for H2 concentration.

STANDARD: Performer contacts Chemistry to sample containment atmosphere.

EVALUATOR CUE: Containment atmosphere has been sampled and the hydrogen concentration is 3.5%.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 7: [6] RECORD the Date and Time on Data Sheet 1.

STANDARD: Performer records Date and Time on Data Sheet 1

COMMENTS:

___ SAT

___ UNSAT REV. 0 Page 47 of 128 WATTS BAR NUCLEAR PLANT B.1.e STEP 8: [7] RECORD CNTMT H2 % on Data Sheet 1, THEN INDICATE from which source H2 percentage was obtained:

[7.1] ANAL A CNTMT H2,1-H21-43-200 [1-M-10]

[7.2] ANAL B CNTMT H2 , 1-H21 210 [1-M-10]

[7.3] Chemistry sample analysis STANDARD: Performer has data available from each of the sources and may enter a value for any of them. The containment hydrogen concentration is 3.5%.

COMMENTS:

___ SAT

___ UNSAT STEP 9: [8] IF containment H2 is greater than 5%, THEN DO NOT place H2 Recombiner in service, and NOTIFY the SM.

STANDARD: Performer confirms that hydrogen concentration is less than 5% and enters N/A for this step.

COMMENTS:

___ SAT

___ UNSAT REV. 0 Page 48 of 128 WATTS BAR NUCLEAR PLANT B.1.e STEP 10: [9] RECORD CNTMT PRESS (psig) on Data Sheet 1, THEN INDICATE which indicator was used:

[9.1] 1-PI-30-310, CNTMT WR PRESS [1-M-9]

[9.2] 1-PI-30-311, CNTMT WR PRESS [1-M-9]

STANDARD: Performer enters a value of 3 psig for either pressure indicator.

COMMENTS:

___ SAT

___ UNSAT STEP 11: [10] TURN POWER OUT (MS Starter) switch to ON, and VERIFY switch plate Red light LIT.

STANDARD: Performer places switch in the UP position, and verifies the RED light is LIT. Step is critical since this action provides power to the recombiner.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 12: [11] ADJUST POWER ADJUST potentiometer clockwise to obtain 5 kW on POWER OUT meter, and MAINTAIN for 10 minutes.

STANDARD: Performer adjusts the potentiometer and obtains 5 kW on the POWER OUT meter. Step is critical to warm up the recombiner.

EVALUATOR CUE: Time Compression - 10 minutes have elapsed.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT REV. 0 Page 49 of 128 WATTS BAR NUCLEAR PLANT B.1.e STEP 13: [12] ADJUST POWER ADJUST potentiometer to obtain 10 kW on POWER OUT meter, and MAINTAIN for 10 minutes.

STANDARD: Performer adjusts the potentiometer and obtains 10 kW on the POWER OUT meter. Step is critical to warm up the recombiner.

EVALUATOR CUE: Time Compression - 10 minutes have elapsed.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 14: [13] ADJUST POWER ADJUST potentiometer to obtain 20 kW on POWER OUT meter, and MAINTAIN for 5 minutes.

STANDARD: Performer adjusts the potentiometer and obtains 20 kW on the POWER OUT meter. Step is critical to warm up the recombiner.

EVALUATOR CUE: Time Compression - 5 minutes have elapsed.

COMMENTS:

___ SAT

___ UNSAT STEP 15: [14] DETERMINE the REQUIRED POWER (kW) based on current CNTMT PRESSURE (psig) using Attachment 3 of TI-83.01, HYDROGEN RECOMBINER REQUIRED POWER-VS-CONTAINMENT PRESSURE CURVES.

STANDARD: Performer uses 3 psig containment pressure and reads 70 kW off the Attachment 3 curve in TI-83.01, HYDROGEN RECOMBINER REQUIRED POWER-VS-CONTAINMENT PRESSURE CURVES.

COMMENTS:

___ SAT

___ UNSAT REV. 0 Page 50 of 128 WATTS BAR NUCLEAR PLANT B.1.e STEP 16: [15] ADJUST POWER ADJUST potentiometer to obtain the REQUIRED POWER (kW) using Attachment 3 of TI- 83.01, HYDROGEN RECOMBINER REQUIRED POWER-VS-CONTAINMENT PRESSURE CURVES.

STANDARD: Performer adjusts the potentiometer and obtains 70 kW on the POWER OUT meter. Step is critical to warm up the recombiner.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT NOTES 1) Periodic potentiometer adjustment is necessary to maintain Required Power setting. Temperature is obtained by selecting an average temperature of all operable thermocouples. Temperature should rise to 1150-1400°F in approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> depending on initial containment temperature. 2) Recombiner temperature should be allowed to stabilize before making power changes due to the lag time between adjustment and actual temperature change.

3) 1 kW power change is approximately equal to 20°F recombiner temperature change.

STEP 17: [16] AFTER recombiner temperature has stabilized for approximately 30 minutes, THEN ADJUST POWER ADJUST potentiometer to maintain 1225 - 1400°F recombiner average temperature.

STANDARD: EVALUATOR CUE: Time Compression - 30 minutes have elapsed, and another operator will make adjustments to maintain temperature between 1225 - 1400°F.

COMMENTS:

___ SAT

___ UNSAT REV. 0 Page 51 of 128 WATTS BAR NUCLEAR PLANT B.1.e STEP 18: [18] NOTIFY SRO that Recombiner A is in service and will be monitored at least once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per Section 8.2.

STANDARD: Performer notifies the SRO that "A" Recombiner is in service.

COMMENTS:

END OF TASK

___ SAT

___ UNSAT STOP TIME ________

REV. 6 PAGE 52 OF 128 WATTS BAR NUCLEAR PLANT B.1.f APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO TRAINEE:

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

INITIAL CONDITIONS:

1. Unit has experienced a LOCA.

2. MCR Crew is following Emergency Instru ction E-1, Loss of Reactor or Secondary Coolant. 3. E-1, Step 30 RNO Step c. directs that the hydrogen recombiners be placed in service using SOI-83.01, Containment Hydrogen Recombiners.

4. You are Control Room Operator.

INITIATING CUES:

1. The Unit Supervisor has directed you to place Hydrogen Recombiner "A" in service, using SOI-83.01, Containment Hydrogen Recombiners.

2. Notify Unit Supervisor when the required power setting is reached

REV. 6 PAGE 53 OF 128 WATTS BAR NUCLEAR PLANT B.1.f

B.1.f Synchronizing DG 1B-B from the MCR per SOI-82.02

REV. 6 PAGE 54 OF 128 WATTS BAR NUCLEAR PLANT B.1.f EVALUATION SHEET Task: Synchronizing DG 1B-B from the MCR per SOI-82.02 Alternate Path:

N/A Facility JPM #: 3-OT-JPMR060 K/A Rating(s):

064-A1.03 [3.2/3.3 064-A4.01 [4.0/4.3] 064-A2.03 [3.1/3.1] 064-A4.03 [3.2/3.3] 064-A4.06 [3.9/3.9]

Task Standard: 1B-B Diesel Generator is synchronized to the shutdown board from the MCR per SOI-82.02 Section 8.1.4, and then loaded to 3.3 MW and 0.74-1.25 MVARs.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator __X__ In-Plant __ ___ Perform __X____ Simulate ____

References

SOI-82.02, "Diesel Generator (D/G) 1B-B" Rev. 65

Task Number: RO-082-SOI-82-002 APPLICABLE FOR: RO/SRO RO-082-SOI-82-008 RO-082-SOI-82-010 10CFR55.45

3, 4, 6, 8

Validation Time: 18 min.

Time Critical: No ===========================================================================

Candidate: ___________________________ _________________ Time Start: ________

NAME SSN/IDTime Finish: ________

Performance Rating: SAT ____ UNSAT ____

Performance Time ___

Examiner: _____________________________

_____________________________/________ NAME SIGNATURE DATE

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

COMMENTS REV. 6 PAGE 55 OF 128 WATTS BAR NUCLEAR PLANT B.1.f SIMULATOR OPERATOR INSTRUCTIONS:

1. Initialize to IC

1. 316. 2. 1B-B Diesel Generator is running unloaded, after an idle start.

b. Place the simulator in RUN momentarily, and acknowledge all alarms.

3. Place simulator in FREEZE until the performer indicates an understanding of the task. 4. After performer indicates understanding of the task, place simulator to RUN.

Tools/Equipment/Procedures Needed:

Ensure a marked-up copy of SOI-82.02 is available to provide to each performer.

Stop Watch, to time Synchroscope rotation.

REV. 6 PAGE 56 OF 128 WATTS BAR NUCLEAR PLANT B.1.f READ TO OPERATOR

DIRECTION TO TRAINEE:

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

INITIAL CONDITIONS:

1. Unit is at 100% power.

2. Testing is being conducted on 1B-B diesel generator. It is to be paralleled to the shutdown board for a Factory Rep. on site.

3. The 1B-B DG is running at rated speed , after performance of SOI-82.02, Section 8.1.3 Idle Speed to Rated Speed.

4. You are an extra control room operator on shift.

INITIATING CUES:

1. The Unit Supervisor directs you to parallel the 1B-B diesel generator to the 1B-B Shutdown Board per SOI-82.02 and load it to 3.3 MWs.

2. SOI-82.01, Section 8.1.4 Steps 1 through 3 have been performed.

3. You are to inform the Unit Supervisor when the diesel generator is loaded to 3.3 MWs.

REV. 6 PAGE 57 OF 128 WATTS BAR NUCLEAR PLANT B.1.f **Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated

. START TIME: _______

STEP 1: Obtain a copy of the instruction.

STANDARD: A copy of SOI-82.02 Section 8.1.4 has been obtained.

EXAMINER'S CUE:

After the performer has demonstrated the method of obtaining the correct instruction, the evaluator can provide a copy of the instruction.

COMMENTS:

___ SAT

___ UNSAT STEP 2: [4] PLACE 1-HS-82-48, DG MODE SELECTOR, in PARALLEL. [0-M-26].

STANDARD: 1-HS-82-48, DG MODE SELECTOR, is placed in PARALLEL. This step is critical for task performance to allow proper operation of voltage regulator & DG speed droop circuits.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

REV. 6 PAGE 58 OF 128 WATTS BAR NUCLEAR PLANT B.1.f **Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated

. STEP 3: [5] ENSURE the following sync switches for 1B-B D/G in OFF. NOMENCLATURE LOCATION POSITION UNID MAINTENANCE 6.9 UNIT BD 1C SYNC SWITCH 0-M-26 OFF 1-HS-57-69 ALTERNATE CSST C SYNC SWITCH 0-M-26 OFF 1-HS-57-115 DG SYNC SWITCH 0-M-26 OFF 1-HS-57-74 NORMAL-CSST D SYNC SWITCH 0-M-26 OFF 1-HS-57-72 STANDARD: Performer checks listed sync switches in OFF position COMMENTS:

___ SAT

___ UNSAT

STEP 4: [6] PLACE 1-HS-57-74, DG SYNC SWITCH, to SYN.

STANDARD: 1-HS-57-74, DG SYNC SWITCH, is placed to SYN position.

This step is critical to allow synchronization of D/G to 1B-B Shutdown board.

COMMENTS:

CRITICAL STEP

___ SAT

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

REV. 6 PAGE 59 OF 128 WATTS BAR NUCLEAR PLANT B.1.f **Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated

. STEP 5: [7] MATCH generator Incoming Frequency (1-XI-82-32) with Running Frequency (1-XI-82-33) using 1-HS-82-43, SPEED CONTROL [0-M-26].

STANDARD: 1-HS-82-43 is used to adjust generator frequency (incoming) on 1-XI-82-32 to match with board frequency (running) on 1-XI-82-33. This step is critical to allow synchronization of D/G to 1B-B Shutdown board.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT STEP 6: [8] MATCH generator Incoming Voltage, (1-EI-82-34) with Running Voltage (1-EI-82-35) using 1-HS-82-42, VOLTAGE REGULATOR [0-M-26].

STANDARD: 1-HS-82-42 is used to adjust generator voltage on 1-EI-82-34 to match with board voltage on 1-EI-82-35. This step is critical to allow synchronization of D/G to 1B-B Shutdown board.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT REV. 6 PAGE 60 OF 128 WATTS BAR NUCLEAR PLANT B.1.f **Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated

. STEP 7: [9] ENSURE DG Frequency and Voltage are MATCHED with 6.9 kV SD Bd, AND ADJUST 1-HS-82-43, SPEED CONTROL, [0-M-26] to obtain desired clockwise rotation (15 or more seconds) on 1-XI-82-31, TRAIN 1B-B SYNCHROSCOPE.

STANDARD: Performer verifies running and incoming frequency and voltage are matched and that the synchroscope is moving slowly in the clockwise direction at 15 seconds or more per rotation on the scope. This step is critical to ensure proper DG synchronization that is performed in the next step. NOTE TO EVALUATOR: The performer may use a stopwatch to time the 15 second rotation.

Provide stopwatch if asked.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT NOTES 1) Steps 8.1.4[10] through 8.1.4[11.3] may be signed off after completion of Step 8.1.4[11.3] 2) Peer checking required on the next step

REV. 6 PAGE 61 OF 128 WATTS BAR NUCLEAR PLANT B.1.f **Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated

. STEP 8: [10] WHEN TRAIN 1B-B SYNCHROSCOPE (1-XI-82-31) reaches 12 o'clock, THEN TURN 1-HS-57-73A, 1914 - DG TO SD 1B-B, to CLOSE.

STANDARD: ACB 1914, DG TO SD 1B-B, is closed with 1-HS-57-73A, when the synchroscope reaches 12 o'clock. This step is critical to ensure proper DG synchronization onto 1B-B Shutdown Board.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT NOTE Maintain outgoing VARS by periodically adjusting voltage regulator with 1-HS-82-42 while loading DG. Controls should not be operated simultaneously.

STEP 9: [11] PERFORM the following: [11.1] LOAD DG promptly using 1-HS-82-43, SPEED CONTROL to at least 1.1 Megawatts as indicated on 1-EI-82-40A, DG MEGAWATTS (0-M-26).

STANDARD: The generator output is increased to 1.1 MW on 0-EI 40A. This step is critical to ensure proper DG loading and avoid reverse power trip.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT REV. 6 PAGE 62 OF 128 WATTS BAR NUCLEAR PLANT B.1.f **Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated

. NOTE DG MEGAVARs may "swing" when the 6.9 KV automatic tap changers engage to stabilize the voltage in the system.

STEP 10: [11.2] PERFORM the following:

[b] MAINTAIN DG MEGAVARS 0.75 to 1.25 OUTGOING on 1-EI-82-41A, with 1-HS-82-42, VOLTAGE REGULATOR.

STANDARD: The generator megavars is adjusted to between 0.75 and 1.25 Megavars on 0-EI-82-41A.

COMMENTS:

___ SAT

___ UNSAT CAUTION Operation of the DG at load of 2.7 MW or less for extended period of time may lead to exhaust fire.

STEP 11: [11.3] PERFORM the following: [c] RAISE load to at least 3.3 Megawatts.

STANDARD: The generator output is raised to 3.3 MW on 0-EI 40A. This step is to ensure DG is loaded per task assignment.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT REV. 6 PAGE 63 OF 128 WATTS BAR NUCLEAR PLANT B.1.f **Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated

. STEP 12: [11.4] PLACE 1-HS-57-74, DG SYNC SWITCH, to OFF.

STANDARD: 1-HS-57-74, DG SYNC SWITCH, is placed to OFF

COMMENTS:

___ SAT

___ UNSAT STEP 13: [11.5] MAINTAIN DG operation for a minimum of one hour, OR until engine temperatures stabilize.

STANDARD: Performer reecognizes that the DG must be run for a minimum of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, OR until engine temperatures stabilize.

EVALUATOR CUE: If asked, state temperatures will be monitored locally until they stabilize.

COMMENTS:

___ SAT

___ UNSAT STEP 14: Notify the Unit Supervisor that DG 1B-B is synchronized to the shutdown board and loaded to 3.3 MW.

STANDARD: The Unit Supervisor is notified that DG 1B-B is synchronized to the shutdown board and loaded to 3.3 MW.

CUE: As Unit Supervisor, wh en notified, acknowledge the report.

COMMENTS:

END OF TASK

___ SAT

___ UNSAT TIME STOP: ________

REV. 2 PAGE 64 OF 128 WATTS BAR NUCLEAR PLANT B.1.g **Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated

. CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO TRAINEE:

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

INITIAL CONDITIONS:

1. Unit is at 100% rated thermal power.

2. Testing is being conducted on 1B-B diesel generator. It is to be paralleled to the shutdown board for a Factory Rep. on site.

3. The 1B-B DG is running at rated speed , after performance of SOI-82.02, Section 8.1.3 Idle Speed to Rated Speed.

4. You are an extra control room operator on shift.

INITIATING CUES:

1. The Unit Supervisor directs you to parallel the 1B-B diesel generator to the 1B-B Shutdown Board per SOI-82.02 and load it to 3.3 MWs. 2. You are to inform the Unit Supervisor when the diesel generator is loaded to 3.3 MWs.

REV. 2 PAGE 65 OF 128 WATTS BAR NUCLEAR PLANT B.1.g **Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated

.

B.1.g Return PRM N-42 to Service per AOI-4

REV. 2 PAGE 66 OF 128 WATTS BAR NUCLEAR PLANT B.1.g **Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated

. Task: Return PRM N-42 to Service per AOI-4 Alternate Path:

When rod control is returned to auto a continuous rod insertion occurs requiring performer to return rod control to manual and then a trip of the reactor. Facility JPM #: 3-OT-JPMR108A Rev 0 K/A Rating(s):

015A4.02 [3.9/3.9] 2.1.23 [3.9/4.0] 001AA1.05 [4.3/4.2]

Task Standard: The DETECTOR CURRENT COMPARATOR switch for UPPER SECTION, the DETECTOR CURRENT COMPARATOR switch for LOWER SECTION, the ROD STOP BYPASS, the POWER MISMATCH BYPASS, and the COMPARATOR CHANNEL DEFEAT have been placed in NORMAL or OPERATE as directed AOI-4, and then reactor is manually tripped due to continuous rod insertion.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator __X__ In-Plant _____ Perform __X___ Simulate ___ _

References

AOI-4, "NUCLEAR INSTRUMENTATION MALFUNCTIONS", Rev 28 Task Number: RO-092-AOI-4-002 APPLICABLE FOR: RO/SRO RO-085-AOI-2-005 10CFR55.45: 2, 3, 4, 5, 6, 12 Validation Time: 12 min.

Time Critical:

No ===========================================================================

Applicant: ___________________________ _________________ Time Start: ________

NAME SSN/EINTime Finish: ________

Performance Rating: SAT ____ UNSAT ____

Performance Time ___

Examiner: _____________________________

_____________________________/________ NAME SIGNATURE DATE

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

COMMENTS REV. 2 PAGE 67 OF 128 WATTS BAR NUCLEAR PLANT B.1.g **Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated

.

REV. 2 PAGE 68 OF 128 WATTS BAR NUCLEAR PLANT B.1.g **Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated

. SIMULATOR OPERATOR INSTRUCTIONS:

1. Initialize to IC 317. a. Ensure the following items are displayed on the Director Summary Page:

rd02 Uncontrolled rod insertion, bank d, group 2 100% severity

b. Ensure the switches on 1-M-13 to the "N42" position to defeat Power Range Channel N42 inputs per AOI-4, Attachment 1, and Step 1 a. through f.

c. Place the simulator in RUN momentarily, and acknowledge all alarms.

2. Load NRC_Exam_Event_Files.evt from the NRC Exam Flash Drive. The malfunction will be entered when Rod Control Selector Switch is placed in AUTO (Event 23).

3. Place simulator in FREEZE until the performer indicates an understanding of the task. 4. After performer indicates understanding of the task, place simulator to RUN.

Tools/Equipment/Procedures Needed:

Ensure a marked-up copy of AOI-4 is available to the Evaluator and clean copies of AOI-2 in all copies of Abnormal Operating Instructions on the Simulator Floor.

REV. 2 PAGE 69 OF 128 WATTS BAR NUCLEAR PLANT B.1.g **Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated

.

READ TO OPERATOR

DIRECTION TO TRAINEE:

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

INITIAL CONDITIONS:

1. Unit 1 is at 100% power.

2. PRM N42 failed during last shift.

3. AOI-4 Section 3.4 has been completed through Step 16.a.

4. Work Control has notified the MCR that repairs to PRM N42 are complete and the instrument is ready to be returned to service.

5. You are the Operator at the Controls.

INITIATING CUES:

1. The Unit Supervisor has directed you to return PRM N42 to service.

2. You are to notify the US when the control rods have been returned to AUTO.

REV. 2 PAGE 70 OF 128 WATTS BAR NUCLEAR PLANT B.1.g START TIME: _______

STEP 1: Obtain the correct procedure.

STANDARD: A copy of AOI-4 has been obtained.

EXAMINER'S CUE:

After the performer has de monstrated the method of obtaining the correct instruction, the evaluator will

provide a marked-up copy of the instruction.

COMMENTS:

___ SAT

___ UNSAT CAUTION Allowing at least 5 minutes between any rod control input (i.e., T-avg, T-ref, or NIS) change and placing rods in AUTO, will help prevent undesired control rod movement.

STEP 2: [Step 16b]

REFER TO Attachment 1, PRM Function At NIS Rack, step 2.

STANDARD: Performer refers to Attachment 1, PRM Function At NIS Rack, Step 2 for restoration of PRM N42.

COMMENTS:

___ SAT

___ UNSAT REV. 2 PAGE 71 OF 128 WATTS BAR NUCLEAR PLANT B.1.g NOTE TO EVALUATOR: The following steps are from Attachment 1 page 2 of 2 AOI-4 STEP 3: [STEP 2] WHEN PRM is ready for return to service , THEN PERFORM the following steps:

a. PLACE DETECTOR CURRENT COMPARATOR switch for UPPER SECTION in NORMAL STANDARD: Detector Current Comparator Upper Section switch placed to "NORMAL" (Miscellaneous Control & Indication Panel,1-IDWR-92-N50-G IV)

Step is critical for proper restoration of upper power detector to current comparator.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

STEP 4: [STEP 2 b]

PLACE DETECTOR CURRENT COMPARATOR switch for LOWER SECTION in NORMAL

STANDARD: Detector Current Comparator Lower Section switch placed to "NORMAL" (Miscellaneous Control & Indication Panel, 1-IDWR-92-N50-G IV).

Step is critical for proper restoration of lower power detector to current comparator.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT REV. 2 PAGE 72 OF 128 WATTS BAR NUCLEAR PLANT B.1.g NOTE: On the following step, annunciator window 66-C, 67-C, 68-C, OR 69-C, N-(#) OVERPOWER ROD STOP BYPASSED, will clear depending on which channel is bypassed.

STEP 5: [STEP 2 c]

PLACE ROD STOP BYPASS switch in OPERATE.

STANDARD: Rod Stop Bypass switch is positioned from "N42" to "OPERATE" (Miscellaneous Control & Indication Panel,1-IDWR-92-N50-G IV)

Step is critical for proper restoration of to enable rod stop

interlock protection from this channel.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT STEP 6: [STEP 2 d]

PLACE POWER MISMATCH BYPASS switch in OPERATE.

STANDARD: Power Mismatch Bypass switch is positioned from "N42" to "OPERATE" (Miscellaneous Control & Indication Panel, 1-IDWR-92-N50-G IV)

Step is critical to rest ore channel input to high auctioneering circuit and power mismatch circuits.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

REV. 2 PAGE 73 OF 128 WATTS BAR NUCLEAR PLANT B.1.g NOTE: On the following step, annunciator window 82-E, NIS CHANNEL IN TEST, will clear.

STEP 7: [STEP 2 e]

PLACE COMPARATOR CHANNEL DEFEAT switch in NORMAL.

STANDARD: Comparator Channel Defeat Switch is positioned to "NORMAL" (Comparator & Rate Panel, Comparator N37, 1-IDWR-92-N37 IV). Step is critical to restor e channel input to channel comparator alarm circuits.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

NOTE: On the following step, annunciator window 115-E, POWER RANGE FLUX RATE HI, will clear if the positive rate trip light is LIT.

STEP 8: [STEP 2 f]

IF POSITIVE RATE TRIP is LIT, THEN RESET RATE MODE switch.

STANDARD: Positive Rate Trip light on Power Range Upper N42A, 1-IDWR-92-42A II, is checked and determines light is NOT LIT and continues to next step.

COMMENTS:

___ SAT

___ UNSAT

REV. 2 PAGE 74 OF 128 WATTS BAR NUCLEAR PLANT B.1.g NOTE TO EVALUATOR: Performer returns to AOI-4 at step 16 c.

STEP 9: [STEP 16 c]

ENSURE T-avg and T-ref within 1

°. STANDARD: Performer verifies T-avg and T-ref within 1

° by recorder 1-TR-68-2B on 1-M-5 or other T-avg - T-ref indications.

COMMENTS:

___ SAT

___ UNSAT

STEP 10: [STEP 16 d] ENSURE zero demand on control rod position indication [1-M-4].

STANDARD: Performer determines zero demand on control rod position indication CERPI display or ICS computer display for CERPI

• CERPI Display

• Plant computer

COMMENTS:

___ SAT

___ UNSAT REV. 2 PAGE 75 OF 128 WATTS BAR NUCLEAR PLANT B.1.g STEP 11: [STEP 16 e]

IF auto rod control desired, PLACE control rods in AUTO.

STANDARD: The rod control hand switch has been placed in AUTO position.

• • CUE: If asked, respond as US that auto rod control is desired.

NOTE TO EVALUATOR: Continuous rod insertion malfunction is inserted when rod control is placed in AUTO. The operator may immediately return rod control to manual, check for rod motion stopped, and then trip the reactor before referring to AOI-2.

COMMENTS:

___ SAT

___ UNSAT

NOTE TO EVALUATOR: The Following Steps are from AOI-2 Section 3.2 due to continuous rod insertion.

STEP 12: [STEP 1] PLACE control rods in MAN.

STANDARD: Rod control hand switch has been placed in Manual position.

NOTE: Rods will continue to step IN.

COMMENTS:

___ SAT

___ UNSAT

REV. 2 PAGE 76 OF 128 WATTS BAR NUCLEAR PLANT B.1.g STEP 13: [STEP 2] CHECK control rod movement STOPPED.

STANDARD: Rod control indications have been checked for movement and performer determines that rods are still inserting and goes to RNO for step.

• • NOTE: Rods will continue to step IN.

COMMENTS:

___ SAT

___ UNSAT

STEP 14: [STEP 2 RNO]

TRIP reactor.

GO TO E-0, Reactor Trip or Safety Injection.

STANDARD: Reactor Trip hand switch on 1-M-4 or 1-M-6 has been placed to the TRIP position. Performer than goes to E-0.

Critical step, as uncontrolled rod movement in manual rod control requires a reactor trip.

• • CUE: Upon transition to E-O, inform performer "WE'LL STOP HERE".

COMMENTS:

END OF TASK CRITICAL STEP

___ SAT

___ UNSAT

TIME STOP: ________

REV. 0 PAGE 77 OF 128 WATTS BAR NUCLEAR PLANT B.1.h APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO TRAINEE:

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

INITIAL CONDITIONS:

1. Unit 1 is at 100% power.

2. PRM N42 failed during last shift.

3. AOI-4 Section 3.4 has been completed through Step 16.a.

4. Work Control has notified the MCR that repairs to PRM N42 are complete and the instrument is ready to be returned to service.

5. You are the Operator at the Controls.

INITIATING CUES:

1. The Unit Supervisor has directed you to return PRM N42 to service.

2. You are to notify the US when the control rods have been returned to AUTO.

REV. 0 PAGE 78 OF 128 WATTS BAR NUCLEAR PLANT B.1.h

B.1.h Shutdown "A" Train EGTS Following a 10 Hour Run per SOI-65.02.

REV. 0 PAGE 79 OF 128 WATTS BAR NUCLEAR PLANT B.1.h Task: Shutdown "A" Train EGTS Following a 10 Hour Run per SOI-65.02.

Alternate Path:

N/A Facility JPM #: 3-OT-JPMR169 K/A Rating(s):

027A4.01 (3.3*/3.3*) Task Standard: EGTS "A" Train has been shutdown and returned to ES Standby alignment in accordance with SOI-65.02.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator __X__ In-Plant _____ Perform __X___ Simulate ___ _

References

SOI-65.02 "Emergency Gas Treatment System" Rev. 24 Task Number: RO-065-SOI-65-005 APPLICABLE FOR: RO/SRO 10CFR55.45: 3, 6, 8 Validation Time: 15 min.

Time Critical:

No ===========================================================================

Applicant: ___________________________ _________________ Time Start: ________

NAME SSNTime Finish: ________

Performance Rating: SAT ____ UNSAT ____

Performance Time ___

Examiner: _____________________________

_____________________________/________ NAME SIGNATURE DATE

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

COMMENTS REV. 0 PAGE 80 OF 128 WATTS BAR NUCLEAR PLANT B.1.h SIMULATOR OPERATOR INSTRUCTIONS:

1. Initialize to IC 318 2. Ensure the alignment for "A" Train EGTS in service:

1-FCV-65 Open.

1-FCO-65 Open.

1-HS-65-81/86 - OPEN 1-HS-65-83/87 in A-AUTO STANDBY 0-HS-65-23A - RUNNING.

3. Acknowledge all alarms.

5. Freeze simulator until the performer indicates understanding of the task and time is allowed for control board familiarization.

5. After performer indicates understanding of task, place simulator in run.

SIMULATOR OPERATOR INSTRUCTIONS:

NONE Tools/Equipment/Procedures Needed:

Ensure clean copy of SOI-65.02 in all copies of Operating Instructions on the Simulator Floor.

REV. 0 PAGE 81 OF 128 WATTS BAR NUCLEAR PLANT B.1.h READ TO OPERATOR

DIRECTION TO TRAINEE:

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

INITIAL CONDITIONS:

1. Unit 1 is at 100% power.

2. 0-SI-65-6-A "Emergency Gas Treatment System Train A 10-Hour Operation" performance in progress.

3. "A" Train EGTS Fan has been in service for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

4. You are a support operator in the control room.

INITIATING CUES:

1. The Unit Supervisor directs you shutdown the "A" Train EGTS Fan per SOI-65.02 and return EGTS to Standby Alignment per the procedure.

2. You are to notify Unit Supervisor when you have completed the task.

REV. 0 PAGE 82 OF 128 WATTS BAR NUCLEAR PLANT B.1.h START TIME: _______

STEP 1: Obtain a copy of the procedure.

STANDARD: A copy of SOI-65.02 section 7.1 has been obtained.

EXAMINER'S CUE:

After the performer has de monstrated the method of obtaining the correct instruction, the evaluator provides a copy of the instruction.

NOTE TO EVALUATOR: Performer may also identify Section 5.0 as needed to return EGTS to standby. You may provide a copy of this section when performer seeks to obtain a copy.

COMMENTS:

___ SAT

___ UNSAT CAUTION: If EGTS is in service due to an accident signal initiation, and the charcoal filter banks have decay heat, an engineering evaluation must be performed before shutting down the EGTS system.

NOTE If EGTS was Auto actuated, both Trains' shutdown sections must be performed prior to return to standby readiness.

STEP 2: [Step 1] ENSURE a ØA Cntmt Isolation signal is NOT present.

STANDARD: Performer determines that ØA Cntmt Isolation signal is NOT present by checking Master Isol Signal PNLs 1-XX-55-6C & 6D

ØA light DARK.

COMMENTS:

___ SAT

___ UNSAT REV. 0 PAGE 83 OF 128 WATTS BAR NUCLEAR PLANT B.1.h STEP 3: [Step 2] Momentarily PLACE 0-HS-65-23A, EGTS FAN & DISCH DMPR, in STOP (returns to A-AUTO).

STANDARD: Performer stops "A" Train EGTS Fan with 0-HS-65-23A and checks red light off and green light ON the associated handswitch.

Step is critical to shutdown the running EGTS Fan.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT STEP 4: [Step 3] ENSURE 1-FCV-65-8, EGTS TR-A U1 SUCT DMPR, CLOSED.

STANDARD: Performer checks 1-HS-65-8 and verifies red light off and green light ON for the associated hand switch Step is critical to shutdown return ventilation lineup to normal following 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> run.

COMMENTS:

___ SAT

___ UNSAT STEP 5: [Step 4] PERFORM the following: [a] CLOSE 1-FCO-65-10, EGTS TR-A U1 SUCT DMPR.

[b] CLOSE 1-FCO-65-26, EGTS TO U1 SHIELD BLDG.

STANDARD: Performer closes 1-FCO-65-10 with 1-HS-65-10; performer closes 1-FC0-65-26 with 1-HS-65-26. Respective hand switches red lights are off and green lights are LIT.

Step is critical to shutdown return ventilation lineup to normal following 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> run.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT REV. 0 PAGE 84 OF 128 WATTS BAR NUCLEAR PLANT B.1.h STEP 6: [STEP 5] IF Train A EGTS to be returned to STANDBY, THEN: PERFORM the following:

CRITICAL STEP NOMENCLATURE LOCATION POSITION UNID EGTS TR-A U1 SUCT DMPR 0-M-27B A AUTO 1-HS-65-10 EGTS TR-A U1 SHIELD BLDG 0-M-27B A AUTO 1-HS-65-26 STANDARD: Performer places 1-HS-65-10 and 1-HS-65-26 to the A AUTO position.

Step is critical to return these hand switches to ES Standby alignment.

COMMENTS:

___ SAT

___ UNSAT

STEP 7: [Step 6] IF Train B EGTS is to be shutdown, THEN GO TO Section 7.2.

STANDARD: Performer determines that this step does not apply and proceeds to the next step.

COMMENTS:

___ SAT

___ UNSAT STEP 8: [Step 7]

IF EGTS is to be returned to STANDBY, THEN GO TO Section 5.0 to align EGTS for STANDBY.

STANDARD: Performer goes to Section 5.0.

COMMENTS:

___ SAT

___ UNSAT REV. 0 PAGE 85 OF 128 WATTS BAR NUCLEAR PLANT B.1.h NOTE TO EVALUATOR: The following performance steps are from section 5.1 of SOI-65.02.

CAUTION IF EGTS is being returned to standby after auto actuation, THEN both Sections 7.1 and 7.2 must be performed prior to Standby Readiness alignment.

STEP 9: [Step 1] ENSURE a ØA Cntmt Isolation signal is NOT present.

STANDARD: Performer determines that ØA Cntmt Isolation signal is NOT present by checking Master Isol Signal PNLs 1-XX-55-6C & 6D

ØA light DARK.

NOTE TO EVALUATOR: This was previously performed in step 2 of JPM.

COMMENTS:

___ SAT

___ UNSAT STEP 10: [Step 2] ENSURE the following valves are CLOSED and PLACE 1-HS-65-81/86 in A AUTO. CRITICAL STEP NOMENCLATURE LOCATION POSITION UNID U1 EGTS-ANN P CNTLR A ISOL 0-M-27B A AUTO 1-HS-65-81/86 STANDARD: Performer locates 1-HS-65-81/88 and places in A-AUTO. Step is critical to establishing EGTS configuration for automatic start after a ØA Cntmt Isolation signal.

COMMENTS:

___ SAT

___ UNSAT

REV. 0 PAGE 86 OF 128 WATTS BAR NUCLEAR PLANT B.1.h STEP 11: [STEP 3] ENSURE breaker position for the following:

NOMENCLATURE LOCATION POSITION UNID 120VAC VITAL INST POWER BD 1-I EGTS TRAIN A AUX RELAYS 1-PCV-65-81/1-PCV-65-86 Bkr 38 OFF 1-BKR-235-1/38 STANDARD: Performer contacts the Control Building AUO (or an AUO) and requests performance of Step 3.

• • CUE: When asked as the AU O, state "1-BKR-235-1/38 is in the OFF position".

COMMENTS:

___ SAT

___ UNSAT

STEP 12: [Step 4] ENSURE the following valves are CLOSED and PLACE 1-HS-65-83/87 in A AUTO. CRITICAL STEP NOMENCLATURE LOCATION POSITION UNID U1 EGTS-ANN P CNTLR B ISOL 0-M-27B A AUTO 1-HS-65-83/87 STANDARD: Performer locates 1-HS-65-83/87 and places in A-AUTO. Step is critical to establishing EGTS configuration for automatic start after a ØA Cntmt Isolation signal.

COMMENTS:

___ SAT

___ UNSAT

REV. 0 PAGE 87 OF 128 WATTS BAR NUCLEAR PLANT B.1.h STEP 13: [STEP 5] ENSURE breaker position for the following:

NOMENCLATURE LOCATION POSITION UNID 120VAC VITAL INST POWER BD 1-II EGTS TRAIN B AUX RELAYS 1-PCV-65-81/1-PCV-65-86 Bkr 38 OFF 1-BKR-235-2/38 STANDARD: Performer contacts an AUO and requests performance of Step

5. **CUE: When asked as the AUO, stat e"1-BKR-235-2/38 is in the OFF position".

COMMENTS:

___ SAT

___ UNSAT

STEP 14: [STEP 6] PERFORM the following:

NOMENCLATURE LOCATION POSITION UNID EGTS FAN A & DISCHG DMPR 0-M-27B A AUTO 0-HS-65-23A EGTS FAN B & DISCHG DMPR 0-M-27B A AUTO 0-HS-65-42A STANDARD: Performer locates 0-HS-65-23A and ensures in A-AUTO. Performer locates 0-HS-65-42A and ensures in A-AUTO.

COMMENTS:

___ SAT

___ UNSAT

REV. 0 PAGE 88 OF 128 WATTS BAR NUCLEAR PLANT B.1.h STEP 15: [STEP 7] OPEN the following valves, and PLACE the handswitches in A AUTO:

CRITICAL STEP NOMENCLATURE LOCATION POSITION UNID U1 ANN VAC FANS SUCT 0-M-27B OPEN, HS in A AUTO 0-HS-65-52 U1 ANN VAC FANS SUCT 0-M-27B OPEN, HS in A AUTO 0-HS-65-53 STANDARD: Performer locates 0-HS-65-52 and ensures OPEN and in A-AUTO. Performer locates 0-HS-65-53 and ensures OPEN and in A-AUTO. Step is critical to est ablishing EGTS configuration for automatic start after a ØA Cntmt Isolation signal.

COMMENTS:

___ SAT

___ UNSAT

NOTES 1) The following step may be N/A'd if annulus vacuum fans are running. 2) If a phase A signal has been present, the next step may start one Ann Vac Fan due to low flow. Either fan may be selected first. Flow should be allowed to stabilize before the second fan is placed in auto to avoid two fans running. SOI-65.01 Section 5.0 should be referenced to ensure proper damper alignment and control after fan start.

REV. 0 PAGE 89 OF 128 WATTS BAR NUCLEAR PLANT B.1.h STEP 16: [STEP 8] PLACE the following handswitches in STOP to break seal-in, AND RETURN to A-P AUTO:

NOMENCLATURE LOCATION POSITION UNID ANN VAC FAN 1A & SUCT FCO 0-M-27B A P AUTO 1-HS-65-77A ANN VAC FAN 1B & SUCT FCO 0-M-27B A P AUTO 1-HS-65-74A STANDARD: Performer verifies that annulus vacuum fans are running and N/As the step.

COMMENTS:

___ SAT

___ UNSAT

STEP 17: [STEP 9] IF an accident signal (A) has occurred and WHEN Annulus P is greater than 4.0 in. H2O, THEN: (N/A if TACF 1-07-0002-065 is in effect.) PERFORM the following

NOMENCLATURE LOCATION POSITION UNID PCV-65-81 and PCV-65-86, EGTS CNTMT ANNULUS DP

RESET A5W/737, 1-JB -292-4013-A, N. of GFFD Rm. RESET 1-HS-65-80 and 1-HS-65-90 PCV-65-83 and PCV-65-87, EGTS CNTMT ANNULUS DP RESET A4V/737, 1-JB-292-4015-B, S. of GFFD Rm. RESET 1-HS-65-82 and 1-HS-65-97 STANDARD: Performer determines that no accident signal was present and N/As the step COMMENTS:

___ SAT

___ UNSAT

CAUTION PDIC-65-80 & 82 Setpoint Thumbwheels are adjusted by MIG only.

REV. 0 PAGE 90 OF 128 WATTS BAR NUCLEAR PLANT B.1.h STEP 18: [STEP 10] ENSURE the following controllers in AUTO: CRITICAL STEP NOMENCLATURE LOCATION POSITION UNID EGTS-ANN P CONTROL 0-M-27B AUTO 1-PDIC-65-82 EGTS-ANN P CONTROL 0-M-27B AUTO 1-PDIC 80 STANDARD: Performer locates 1-PDIC-65-82 and ensures controller is in AUTO Performer locates 1-PDIC 80 and ensures controller is in AUTO Step is critical to establish EGTS standby alignment.

COMMENTS:

___ SAT

___ UNSAT

REV. 0 PAGE 91 OF 128 WATTS BAR NUCLEAR PLANT B.1.h STEP 19: [STEP 11] ENSURE the following:

NOMENCLATURE LOCATION POSITION UNID EGTS TR A DECAY COOLING 0-M-27B CLOSE 0-HS-65-28B EGTS TR A DECAY COOLING 0-M-27B CLOSE 0-HS-65-28A EGTS TR B DECAY COOLING 0-M-27B CLOSE 0-HS-65-47A EGTS TR B DECAY COOLING 0-M-27B CLOSE 0-HS-65-47B STANDARD:

Performer locates 0-HS-65-28B and ensures that it is CLOSED. Performer locates 0-HS-65-28A and ensures that it is CLOSED. Performer locates 0-HS-65-47A and ensures that it is CLOSED. Performer locates 0-HS-65-47B and ensures that it is CLOSED. COMMENTS:

___ SAT

___ UNSAT

REV. 0 PAGE 92 OF 128 WATTS BAR NUCLEAR PLANT B.1.h STEP 20: [STEP 12] PERFORM the following: CRITICAL STEP NOMENCLATURE LOCATION POSITION UNID EGTS TR-A U1 SUCT DMPR 0-M-27B A AUTO 1-HS-65-10 EGTS TR-A U1 SUCT DMPR 0-M-27B CLOSE 1-HS-65-8 EGTS FAN B U1 SUCT DMPR 0-M-27B CLOSE 1-HS-65-51 EGTS TR-B U1 SUCT DMPR 0-M-27B A AUTO 1-HS-65-30 EGTS TO U1 SHIELD BLDG 0-M-27B A AUTO 1-HS-65-26 EGTS TO U1 SHIELD BLDG 0-M-27B A AUTO 1-HS-65-27 STANDARD:

Performer locates 1-HS-65-10 and ensures that it is in A-AUTO. Performer locates 1-HS-65-8 and ensures that it is CLOSED.

Performer locates 1-HS-65-51 and ensures that it is CLOSED.

Performer locates 1-HS-65-30 and ensures that it is in A-AUTO. Performer locates 1-HS-65-26 and ensures that it is in A-AUTO. Performer locates 1-HS-65-27 and ensures that it is in A-AUTO. Step is critical to establish EGTS standby alignment.

COMMENTS:

___ SAT

___ UNSAT

STEP 21: Notify the Unit Supervisor that "A" Train EGTS Fan is shutdown and realigned for standby readiness.

STANDARD: Performer notifies the Unit Supervisor that "A" Train EGTS Fan is shutdown and realigned for standby readiness.

COMMENTS:

END OF TASK

___ SAT

___ UNSAT

TIME STOP: ________

REV. 0 PAGE 93 0F 128 WATTS BAR NUCLEAR PLANT B.1.i APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO TRAINEE:

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

INITIAL CONDITIONS:

1. Unit 1 is at 100% power.

2. 0-SI-65-6-A "Emergency Gas Treatment System Train A 10-Hour Operation" performance in progress.

3. "A" Train EGTS Fan has been in service for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

4. You are a support operator in the control room.

INITIATING CUES:

1. The Unit Supervisor directs you shutdown the "A" Train EGTS Fan per SOI-65.02 and return EGTS to Standby Alignment per the procedure.

2. You are to notify Unit Supervisor when you have completed the task.

REV. 0 PAGE 94 0F 128 WATTS BAR NUCLEAR PLANT B.1.i

B.1.j Perform a boration of the RCS (LOCALLY) per AOI-34

REV. 0 PAGE 95 0F 128 WATTS BAR NUCLEAR PLANT B.1.i Task: Perform a Boration of the RCS (LOCALLY) per AOI-34 Alternate Path:

1-FCV-62-138 will not open locally, requiring manual valve 1-ISV-62-929 to be opened locally. This also requires use of control room flow indication, since the indication of flow via this path is not available locally.

Facility JPM #: 3-OT-JPMA020B Rev 4.

K/A Rating(s):

024AA1.04 [3.6/3.7] 024AK3.01 [4.1/4.4] 024AA1.18 [3.7/3.6] 024AA1.20 [3.2/3.3]

Task Standard: Boration flow has been established on 1-FI-62-139 after opening 1-ISV-62-929 locally. Preferred Evaluation Location: Preferred Evaluation Method:

Simulator __ __ In-Plant __ X__ Perform ______ Simulate __X__

References

AOI-34, "IMMEDIATE BORATION", Rev. 23.

Task Number: AUO-062-AOI-27-001 APPLICABLE FOR: AUO/RO/SRO 10CFR55.45: 6, 8, 9, 10 Validation Time: 17 min.

Time Critical:

No ===========================================================================

Candidate: ___________________________ _________________ Time Start: ________

NAME SSN/EINTime Finish: ________

Performance Rating: SAT ____ UNSAT ____

Performance Time ___

Examiner: _____________________________

_____________________________/________ NAME SIGNATURE DATE

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

COMMENTS REV. 0 PAGE 96 0F 128 WATTS BAR NUCLEAR PLANT B.1.i REV. 0 PAGE 97 0F 128 WATTS BAR NUCLEAR PLANT B.1.i Tools/Equipment/Procedures Needed:

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

Procedure AOI-34, "Immediate Boration".

ALARA considerations NOTE: Start this JPM at the RAD WASTE DESK.

REV. 0 PAGE 98 0F 128 WATTS BAR NUCLEAR PLANT B.1.i READ TO OPERATOR

DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you.

Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS:

1. The Reactor has been tripped and AOI-34 is being performed due to an RCS cooldown resulting in temperature less than 547

°F. 2. The normal makeup controls did not function correctly to establish boric acid flow. 3. Both Boric Acid pumps are operating in FAST speed.

4. 1-FCV-62-138 did not open from the Main Control Room.

INITIATING CUES:

1. You have been assigned to perform AOI-34, Step 6 actions to locally establish boric acid flow.

2. You are to notify the MCR operator when you have established boric acid flow.

REV. 3 PAGE 99 0F 13 WATTS BAR NUCLEAR PLANT B.1.i START TIME: _______

STEP 1: Obtain a copy of the appropriate instruction.

STANDARD: EXAMINER'S CUE: After the method of obtaining an instruction properly has been demonstrated, the evaluator provides a copy of the instruction.

COMMENTS:

___ SAT

___ UNSAT STEP 2: [STEP 6.b. RNO] Locally ADJUST 1-FCV-62-138 to obtain required flow.

STANDARD: 1-FCV-138-B, EMERGENCY BORATION FLOW CONTROL, is located. The manual lever is pushed to the manual position (in direction of arrow) and the performer opens the valve by turning the hand wheel in the counter-clockwise direction.

Step is critical to establish flow path.

CUE: After performer indicates how to open the valve state "the motor operator hand wheel will NOT rotate."

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT REV. 3 PAGE 100 0F 13 WATTS BAR NUCLEAR PLANT B.1.i STEP 3: [STEP 6.c.]

CHECK emergency borate flow on 1-FI-62-137A.

STANDARD: 1-FI-62-137A.has been located and checked and determination made that no flow has been established. Entry into c. RNO is therefore required. Step is critical to evaluating whether a flow path has been established.

CUE: When performer checks FI-62-137A, state "the indicator reads "0".

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT

Note: The following step is required since valve could not be operated electrically STEP 4: [STEP 6c. RNO] Locally OPEN manual boration valve 1-ISV-62-929 [Blender Station/713].

STANDARD: 1-ISV-62-929 is opened by turning the hand wheel in the counter-clockwise direction. Step is critical because it initiates boration flow.

CUE: After performer indicates how to open the valve, state, "the hand wheel was rotated many turns in the counter-clockwise direction and has stopped."

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT REV. 3 PAGE 101 0F 13 WATTS BAR NUCLEAR PLANT B.1.i STEP 5: [STEP 6.c. RNO continued]

ENSURE BA flow control 1-FCV-62-140 OPEN.

STANDARD: Performer observes 1-FCV-62-140 and determines that the valve is OPEN. Step is critical because 1-FCV-62-140 is in series with 1-ISV-62-929 and must be in the OPEN position in order to establish boration flow.

COMMENTS:

CRITICAL STEP

___ SAT

___ UNSAT STEP 6: [STEP c. RNO continued] ENSURE BA to Blender, 1-FI-62-139, indicating flow.

STANDARD: Performer contacts the MCR to determine if flow is indicated on 1-FI-62-139.

CUE: When MCR is contacted, state"1-FI-62-139 is indicating 40 gpm".

COMMENTS:

___ SAT

___ UNSAT REV. 3 PAGE 102 0F 13 WATTS BAR NUCLEAR PLANT B.1.i STEP 15: [7] IF emergency boration flow established , THEN GO TO Step 9.

STANDARD: Performer contacts MCR and reports that emergency boration flow has been established.

CUE: Acknowledge report as MCR operator using repeat back.

COMMENTS:

END OF TASK

___ SAT

___ UNSAT TIME STOP: ________

REV. 0 PAGE 103 0F 15 WATTS BAR NUCLEAR PLANT B.1.j CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you.

Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS:

1. The Reactor has been tripped and AOI-34 is being performed due to an RCS cooldown resulting in temperature less than 547

°F. 2. The normal makeup controls did not function correctly to establish boric acid flow. 3. Both Boric Acid pumps are operating in FAST speed.

4. 1-FCV-62-138 did not open from the Main Control Room. INITIATING CUES:

1. You have been assigned perform AOI-34, Step 6.b RNO actions to locally establish boric acid flow.

2. You are to notify the MCR operator when you have established boric acid flow.

REV. 0 PAGE 104 0F 15 WATTS BAR NUCLEAR PLANT B.1.j

B.1.j Perform E-3, Attachment 3, Steamline Isolation (Local)

REV. 0 PAGE 105 0F 15 WATTS BAR NUCLEAR PLANT B.1.j Task: Perform E-3, Attachment 3, Steamline Isolation (Local)

Alternate Path:

N/A Facility JPM #: 3-OT-JPMA054 Rev 3 K/A Rating(s):

038 EA1.32 [4.6/4.7] 2.1.30 [3.9/3.4]

Task Standard: All nine steam line traps have been located. One steam trap has been isolated (all others are isolated the same way). Main steam supplies to each MFP turbine have been located and isolated.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator __ __ In-Plant __ X__ Perform ______ Simulate __X__

References

E-3, Steam Generator Tube Rupture, Rev. 22 Task Number: RO-113-EOP-3-001 APPLICABLE FOR: AUO/RO/SRO 10CFR55.45: 5.6 Validation Time: 20 min.

Time Critical: No ===========================================================================

Candidate: ___________________________ _________________ Time Start: ________

NAME SSN/EINTime Finish: ________

Performance Rating: SAT ____ UNSAT ____

Performance Time ___

Examiner: _____________________________

_____________________________/________ NAME SIGNATURE DATE

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

COMMENTS REV. 0 PAGE 106 0F 15 WATTS BAR NUCLEAR PLANT B.1.j Tools/Equipment/Procedures Needed:

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

E-3, Attachment 3.

SAFETY Considerations:

High Temperature Pipes, Ladder Safety, ALARA considerations.

NOTE: Start this JPM in the MCR.

EVALUATOR NOTE: Provide copy of E-3, Attachment 3, "Steamline Isolation (Local)" to performer with candidate's cue sheet.

REV. 0 PAGE 107 0F 15 WATTS BAR NUCLEAR PLANT B.1.j READ TO OPERATOR

DIRECTION TO TRAINEE:

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

INITIAL CONDITIONS:

1. Unit 1 is in Mode 3 after a Steam Generator tube rupture on S/G # 2.

2. The Main Steam Isolation Valve (MSIV) on S/G # 2 has failed to close.

3. Main Steam line warming is NOT in progress.

INITIATING CUES:

1. The MCR operator has directed you to locally isolate the steam traps and Main Feed Pump Turbine on the main steam system by performing E-3, Attachment 3, Steamline Isolation (Local).

2. You are to notify the MCR operator when E-3, Attachment 3 has been completed.

REV. 0 PAGE 108 0F 15 WATTS BAR NUCLEAR PLANT B.1.j START TIME: _______

STEP 1: Obtain a copy of the procedure.

___SAT

___UNSAT STANDARD: A copy of E-3, Attachment 3, Steamline Isolation (Local) is obtained.

EXAMINER'S CUE: Provide E-3, Attachment 3,"Steamline Isolation (Local)" to the performer.

COMMENTS:

STEP 2: [Step 1] COORDINATE steam trap isolation with RADPROT.

___SAT

___UNSAT STANDARD: The performer contacts RADCON.

CUE: As RADCON when contacted, state "that survey of steam lines has been made and is continuing periodically".

COMMENTS:

EXAMINER NOTE: the performer must locate all nine steam traps and demonstrate how to isolate one of them.

The performer may use a flashlight to point out the hard to reach moisture traps.

The performer must locate an "EOP ladder" for use in operating valves, located in hard to reach locations

REV. 0 PAGE 109 0F 15 WATTS BAR NUCLEAR PLANT B.1.j STEP 3: [STEP 2] CLOSE at least one valve listed for each steam moisture trap manifold: [MAIN STEAM LINES]

CRITICAL STEP MSTR TRAP LEVEL SWITCH ###

MSTR TRAP ### STR ISOL MSTR TRAP DRAIN ISOL LOCATION 200 1-ISV-1-916 OR1-ISV-1-922 [T1M/708]

STANDARD: The performer locates each moisture trap. Demonstration of the isolation of the trap associated with 1-LS-200 can be accomplished by either closing 1-ISV-1-916 or closing 1-ISV-1-922. (Rotating hand wheel clockwise). Step is critical to isolate flow path.

CUE: After the performer has demonstrated how to close the valve, state "the hand wheel turns a few rotations and gets snug".

___SAT

___UNSAT COMMENTS:

REV. 0 PAGE 110 0F 15 WATTS BAR NUCLEAR PLANT B.1.j STEP 4: [STEP 2 continued]

CLOSE at least one valve listed for each steam moisture trap manifold: [MAIN STEAM LINES] CRITICAL STEP MSTR TRAP LEVEL SWITCH ###

MSTR TRAP ### STR ISOL MSTR TRAP DRAIN ISOL LOCATION 201 1-ISV-1-926 OR1-ISV-1-932 [T1M/708]

___SAT

___UNSAT STANDARD: The performer locates each moisture trap. Demonstration of the isolation of the trap associated with 1-LS-201 can be accomplished by either closing 1-ISV-1-926 or closing 1-ISV-1-932. (Rotating hand wheel clockwise) Step is critical to isolate flow path.

CUE: After the performer has demonstrated how to close the valve, state " the hand wheel turns a few rotations and gets snug".

COMMENTS:

STEP 5: [STEP 2 continued]

CLOSE at least one valve listed for each steam moisture trap manifold: [MAIN STEAM LINES]

CRITICAL STEP MSTR TRAP LEVEL SWITCH ###

MSTR TRAP ### STR ISOL MSTR TRAP DRAIN ISOL LOCATION 202 1-ISV-1-936 OR1-ISV-1-942 [T1M/708]

___SAT

___UNSAT STANDARD: The performer locates each moisture trap. Demonstration of the isolation of the trap associated with 1-LS-202 can be accomplished by either closing 1-ISV-1-936 or closing 1-ISV-1-942. (Rotating hand wheel clockwise). Step is critical to isolate flow path.

CUE: After the performer has demonstrated how to close the valve, state that the hand wheel turns a few rotations a nd gets snug".

COMMENTS:

REV. 0 PAGE 111 0F 15 WATTS BAR NUCLEAR PLANT B.1.j STEP 6: [STEP 2 continued]

CLOSE at least one valve listed for each steam moisture trap manifold: [MAIN STEAM LINES] CRITICAL STEP MSTR TRAP LEVEL SWITCH ###

MSTR TRAP ### STR ISOL MSTR TRAP DRAIN ISOL LOCATION 203 1-ISV-1-946 OR1-ISV-1-952 [T1M/708]

STANDARD: The performer locates each moisture trap. Demonstration of the isolation of the trap associated with 1-LS-203 can be accomplished by either closing 1-ISV-1-946 or closing 1-ISV-1-952. (Rotating hand wheel clockwise). Step is critical to isolate flow path.

CUE: After the performer has demonstrated how to close the valve, state that the hand wheel turns a few rotations a nd gets snug".

___SAT

___UNSAT COMMENTS:

STEP 7: [STEP 2 continued]

CLOSE at least one valve listed for each steam moisture trap manifold: [COMMON STEAM HEADER]

CRITICAL STEP MSTR TRAP LEVEL SWITCH ###

MSTR TRAP ### STR ISOL MSTR TRAP DRAIN ISOL LOCATION 204 1-ISV-1-956 OR1-ISV-1-962 [T4J/708]

___SAT

___UNSAT STANDARD: The performer locates each moisture trap. Demonstration of the isolation of the trap associated with 1-LS-204 can be accomplished by either closing 1-ISV-1-956 or closing 1-ISV-1-962. (Rotating hand wheel clockwise). Step is critical to isolate flow path.

CUE: After the performer has demonstrated how to close the valve, state that the hand wheel turns a few rotations a nd gets snug".

COMMENTS:

REV. 0 PAGE 112 0F 15 WATTS BAR NUCLEAR PLANT B.1.j STEP 8: [STEP 2 continued]

CLOSE at least one valve listed for each steam moisture trap manifold: [COMMON STEAM HEADER]

CRITICAL STEP MSTR TRAP LEVEL SWITCH ###

MSTR TRAP ### STR ISOL MSTR TRAP DRAIN ISOL LOCATION 206 1-ISV-1-966 OR1-ISV-1-972 [T6J/708]

STANDARD: The performer locates each moisture trap. Demonstration of the isolation of the trap associated with 1-LS-206 can be accomplished by either closing 1-ISV-1-966 or closing 1-ISV-1-972. (Rotating hand wheel clockwise). Step is critical to isolate flow path.

CUE: After the performer has demonstrated how to close the valve, state that the hand wheel turns a few rotations a nd gets snug".

___SAT

___UNSAT COMMENTS:

STEP 9: [STEP 2 continued]

CLOSE at least one valve listed for each steam moisture trap manifold: [STEAM DUMP HEADER]

CRITICAL STEP MSTR TRAP LEVEL SWITCH ###

MSTR TRAP ### STR ISOL MSTR TRAP DRAIN ISOL LOCATION 207 1-ISV-1-976 OR1-ISV-1-982 [T7H/708]

STANDARD: The performer locates each moisture trap. Demonstration of the isolation of the trap associated with 1-LS-207 can be accomplished by either closing 1-ISV-1-976 or closing 1-ISV-1-982. (Rotating hand wheel clockwise). Step is critical to isolate flow path.

CUE: After the performer has demonstrated how to close the valve, state that the hand wheel turns a few rotations a nd gets snug".

___SAT

___UNSAT COMMENTS:

REV. 0 PAGE 113 0F 15 WATTS BAR NUCLEAR PLANT B.1.j STEP 10: [STEP 2 continued]

CLOSE at least one valve listed for each steam moisture trap manifold: [STEAM DUMP HEADER] CRITICAL STEP MSTR TRAP LEVEL SWITCH ###

MSTR TRAP ### STR ISOL MSTR TRAP DRAIN ISOL LOCATION 208 1-ISV-1-986 OR1-ISV-1-992 [T7G/708]

STANDARD: The performer locates each moisture trap. Demonstration of the isolation of the trap associated with 1-LS-208 can be accomplished by either closing 1-ISV-1-986 or closing 1-ISV-1-992. (Rotating hand wheel clockwise). Step is critical to isolate flow path.

CUE: After the performer has demonstrated how to close the valve, state that the hand wheel turns a few rotations a nd gets snug".

___SAT

___UNSAT COMMENTS:

REV. 0 PAGE 114 0F 15 WATTS BAR NUCLEAR PLANT B.1.j STEP 11: [STEP 2 continued]

CLOSE at least one valve listed for each steam moisture trap manifold: [STEAM DUMP HEADER]

CRITICAL STEP MSTR TRAP LEVEL SWITCH ###

MSTR TRAP ### STR ISOL MSTR TRAP DRAIN ISOL LOCATION 209 1-ISV-1-996 OR1-ISV-1-1002 [T7F/708]

STANDARD: The performer locates each moisture trap. Demonstration of the isolation of the trap associated with 1-LS-209 can be accomplished by either closing 1-ISV-1-996 or closing 1-ISV-1-1002. (Rotating hand wheel clockwise). Step is critical to isolate flow path.

CUE: After the performer has demonstrated how to close the valve, state that the hand wheel turns a few rotations a nd gets snug".

___SAT

___UNSAT COMMENTS:

STEP 12: [STEP 3] CLOSE steam supply isolation and bypass for each Main Feed Pump Turbine:

CRITICAL STEP MFPT NOMENCLATURE LOCATION POSITION UNID 1A MFPT 1A HP STEAM SUPPLY ISOL T2J/729 CLOSED 1-ISV-1-611 STANDARD: The performer locates valve and closes valve (rotating hand wheel clockwise). Step is critical to isolate flow path.

CUE: After the performer has demonstrated how to close the valve, state that the hand wheel turns many rotations a nd gets snug".

___SAT

___UNSAT COMMENTS:

REV. 0 PAGE 115 0F 15 WATTS BAR NUCLEAR PLANT B.1.j STEP 13: [STEP 3 continued]

CLOSE steam supply isolation and bypass for each Main Feed Pump Turbine:

MFPT NOMENCLATURE LOCATION POSITION UNID 1A MFPT 1A HP STEAM SUPPLY ISOL BYPASS T2J/729 CLOSED 1-IBV-1-613 STANDARD: The performer locates valve and checks valve closed (rotating hand wheel clockwise).

CUE: After the performer has demonstrated how to close the valve, state "the hand wheel does not move with clockwise force on hand wheel".

___SAT

___UNSAT COMMENTS:

STEP 14: [STEP 3 continued]

CLOSE steam supply isolation and bypass for each Main Feed Pump Turbine:

CRITICAL STEP MFPT NOMENCLATURE LOCATION POSITION UNID 1B MFPT 1B HP STEAM SUPPLY ISOL T2H/729 CLOSED 1-ISV-1-612 STANDARD: The performer locates valve and closes valve (rotating hand wheel clockwise). Step is critical to isolate flow path.

___SAT

___UNSAT CUE: After the performer has demonstrated how to close the valve, state that the hand wheel turns many rotations a nd gets snug".

COMMENTS:

REV. 0 PAGE 116 0F 15 WATTS BAR NUCLEAR PLANT B.1.j STEP 16: [STEP 3] CLOSE steam supply isolation and bypass for each MFPT:

MFPT NOMENCLATURE LOCATION POSITION UNID 1B MFPT 1B HP STEAM SUPPLY ISOL BYPASS T2H/729 CLOSED 1-IBV-1-614 STANDARD: The performer locates valve and checks valve closed (rotating hand wheel clockwise).

CUE: After the performer has demonstrated how to close the valve, state "the hand wheel does not move with clockwise force on hand wheel".

___SAT

___UNSAT

COMMENTS:

STEP 17: Notify the MCR Operator that local main steam isolation has been completed per E-3, Attachment 3.

___SAT

___UNSAT STANDARD: The MCR Operator has been notified that local main steam isolation has been performed per E-3, Attachment 3.

CUE: When notified, acknowledge the report.

COMMENTS:

END OF TASK TIME STOP: ________

REV. 4 PAGE 117 0F 128 WATTS BAR NUCLEAR PLANT B.1.k CANDIDATE CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO TRAINEE:

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

INITIAL CONDITIONS:

1. Unit 1 is in Mode 3 after suffering a Steam Generator tube rupture on S/G # 2.

2. The Main Steam Isolation Valve (MSIV) on S/G # 2 has failed to close.

3. Main Steam line warming is NOT in progress.

INITIATING CUES:

1. The MCR operator has directed you to locally isolate the steam traps and MFPT on the main steam system by performing E-3, Attachment 3, Steamline Isolation (Local). 2. You are to notify the MCR operator when E-3, Attachment 3 has been completed.

REV. 4 PAGE 118 0F 128 WATTS BAR NUCLEAR PLANT B.1.k

B.1.k Place the CVCS Cation Demineralizer in Service per SOI-62.04

REV. 4 PAGE 119 0F 128 WATTS BAR NUCLEAR PLANT B.1.k Task: Place the CVCS Cation Demineralizer in Service per SOI-62.04

Alternate Path:

N/A Facility JPM #: 3-OT-JPMA041 K/A Rating(s):

004A1.07 [2.7/3.1] Task Standard: The appropriate valves have been located and opened to place the CVCS cation bed in service per SOI-62.04.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator ____ In-Plant __X___ Perform __X___ Simulate ___ _

References

SOI-62.04, CVCS PURIFICATION SYSTEM, Rev. 53 Task Number: AUO-062-AOI-028-001 APPLICABLE FOR: RO/SRO 10CFR55.45: 8, 9 Validation Time: 20 min.

Time Critical:

No ===========================================================================

Applicant: ___________________________ _________________ Time Start: ________

NAME SSNTime Finish: ________

Performance Rating: SAT ____ UNSAT ____

Performance Time ___

Examiner: _____________________________

_____________________________/________ NAME SIGNATURE DATE

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

COMMENTS REV. 4 PAGE 120 0F 128 WATTS BAR NUCLEAR PLANT B.1.k Tools/Equipment/Procedures Needed:

Hard Hat, Safety Glasses, Hearing Protection, Gloves and Plant Approved Shoes Copy of SOI-62.04, CVCS PURIFICATION SYSTEM, Rev. 53, Section 8.2 and Attachment 1 with data entered.

SAFETY CONSIDERATIONS

Hot pipes, high noise, and heat.

Radiation levels.

Ladder use to reach valve handwheels.

REV. 4 PAGE 121 0F 128 WATTS BAR NUCLEAR PLANT B.1.k READ TO OPERATOR

DIRECTION TO TRAINEE:

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

INITIAL CONDITIONS:

1. The Unit is at 100% power.

2. Letdown orifice valve 1-FCV-62-74 is open and letdown flow (as indicated in MCR) is 75 gpm.

3. RCS boron concentration is 870 ppm.

4. Chemistry has requested that cation bed be placed in service for 53 minutes.

5. The Cation bed has been filled and vented.

6. SOI-62.04, Attachment 1, Resin Status Sheet indicates that the Cation Bed is at the same boron concentration of the RCS.

INITIATING CUES:

1. The MCR operator has directed you to place the CVCS Cation Bed in service per procedure.

2. You are to notify the MCR when the CVCS Cation Bed is in service.

REV. 0 PAGE 122 0F 128 WATTS BAR NUCLEAR PLANT B.1.k **Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated

. START TIME: _______

STEP 1: Obtain a copy of the procedure.

STANDARD: Performer has obtained a copy of SOI-62.04, Section 8.2 EXAMINER'S CUE:

After the performer has de monstrated the method of obtaining the correct instruction, the evaluator can

provide a copy of the instruction.

COMMENTS:

___ SAT

___ UNSAT STEP 2: [1] ENSURE CB FILLED and VENTED per Section 8.1.

STANDARD: Performer determines the Cation Bed is filled and vented per the INITIAL CONDITIONS provided.

EXAMINER'S CUE: If asked, inform the performer that Section 8.1 is complete.

COMMENTS:

___ SAT

___ UNSAT Due to the location of one of the valve handwheels that will be operated, the performer may require a ladder to reach the valve handwheel. If required, a general use ladder, NOT an EOP ladder, must be located by the operator.

REV. 0 PAGE 123 0F 128 WATTS BAR NUCLEAR PLANT B.1.k **Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated

. STEP 3: [2] PERFORM the following:

NOMENCLATURE LOCATION POSITION UNID CVCS CATION DEMIN BED INLET A3T/713 CLOSED 1-ISV-62-915 CVCS CATION DEMIN BED OUTLET A3T/713 CLOSED 1-ISV-62-916 CVCS CATION DEMIN BED VENT A3T/713 CLOSED 1-VTV-62-917 CVCS CATION DEMIN BED RESIN FILL A5U/737 CLOSED 1-ISV-62-918 CVCS CATION DEMIN BED RESIN DISCH A7U/713 CLOSED 1-ISV-62-919 CVCS CATION DEMIN BED DRAIN A3T/713 CLOSED 1-DRV-62-920 CVCS CATION BED FLUSH A3T/713 CLOSED 1-FLV-62-921 STANDARD: The above listed valves have been located and checked closed (clockwise to close).

EVALUATOR CUE: If the performer attempts to move the handwheel clockwise then countercl ockwise, state" the handwheel will not rotate".

COMMENTS:

___ SAT

___ UNSAT STEP 4: [3] ENSURE 1-ISV-62-922, CVCS MIXED BED DEMIN OUTLET [A3T/713], is OPEN.

STANDARD: 1-ISV-62-922 is verified to be open.

EVALUATOR CUE: If the performer attempts to move the handwheel clockwise then countercl ockwise, state" the handwheel will not rotate".

COMMENTS:

___ SAT

___ UNSAT REV. 0 PAGE 124 0F 128 WATTS BAR NUCLEAR PLANT B.1.k **Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated

. STEP 5: [4] REVIEW Attachment 1, Resin Status Sheet to ensure CB is FILLED and BORATED.

STANDARD: Performer determines that the CB is filled and borated (given in initial conditions) and proceeds to the next step.

EVALUATOR CUE: If asked, state "the Resin Status Sheet indicates the CB is filled and vented and borated to the 870 ppm, the same concentration as the RCS)".

COMMENTS:

___ SAT

___ UNSAT STEP 6: [5] NOTIFY SRO of intent to place CB in service, and its current boron concentration as recorded on Attachment 1, Resin Status Sheet.

STANDARD: The performer contacts SRO and notifies them of intent to place cation Bed in service, advises them of boron concentration recorded on Attachment 1.

NOTE TO EVALUATOR: Task assignment sheet provides the boron concentration derived from Attachment 1. The Rad Waste desk contains the current for cation bed which will be different than task assignment sheet.

COMMENTS:

___ SAT

___ UNSAT CAUTION Cation Bed may need to be flushed to minimize reactivity effects if cation bed boron concentration varies more than 20 ppm from that of the RCS boron concentration or if a new cation bed is being placed in service.

REV. 0 PAGE 125 0F 128 WATTS BAR NUCLEAR PLANT B.1.k **Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated

. STEP 7: [6] OPEN 1-ISV-62-915, CVCS CATION DEMIN BED INLET.

STANDARD: 1-ISV-62-915 has been located and opened (turned in the counter-clockwise direction).

EVALUATOR CUE: After valve hand wheel is moved in the counterclockwise direction, state "the hand wheel rotates several turns and stops."

If indicator checked, indicate it points to the open position.

Step is critical to establish fl ow through the cation demineralizer.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 8: [7] IF flush is desired for cation bed, THEN GO TO Section 8.7, Flushing Cation Bed to Adjust Boron Prior to Use.

STANDARD: Performer determines that flush is not required (per EVALUATOR CUE) and N/As step.

EVALUATOR CUE: State that flush is not necessary, nor desired at this time.

COMMENTS:

___ SAT

___ UNSAT CAUTION Maximum Cation Bed flow is 75 gpm. May be read locally at 1-FI-62-113 (Panel 1-L-57 at A3T/713).

REV. 0 PAGE 126 0F 128 WATTS BAR NUCLEAR PLANT B.1.k **Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated

. STEP 9: [8] SLOWLY OPEN 1-ISV-62-916, CVCS CATION DEMIN BED OUTLET.

STANDARD: 1-ISV-62-916 has been located and opened slowly (turned in the counter-clockwise direction).

EVALUATOR CUE: After valve hand wh eel is moved in the counter-clockwise direction, state that the hand wheel rotates several turns and stops.

If indicator checked, indicate it points to the open position.

Step is critical to establish fl ow through the cation demineralizer.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 10: [9] SLOWLY THROTTLE CLOSE 1-ISV-62-922, CVCS MIXED BED DEMIN OUTLET, until desired cation bed flow rate achieved.

STANDARD: 1-ISV-62-922 has been located and closed slowly (turned in the clockwise direction).

EVALUATOR CUE: After valve hand wheel is moved in the clockwise direction, state "the hand wheel rotates several turns and stops." If indicator checked, indicate it points to the closed position.

EVALUATOR CUE: When 1 FI-62-113 is checked by the local indicator OR the CRT Monitor located near the demineralizer control valves, state it indicates 75 gpm. IF the MCR is contacted, state the letdown flow is 75 gpm.

Step is critical to establish fl ow through the cation demineralizer.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT REV. 0 PAGE 127 0F 128 WATTS BAR NUCLEAR PLANT B.1.k **Italicized Cues Are To Be Used Only If JPM Performance Is Being Simulated

. STEP 11: [10] RECORD Time, Date, and Flowrate when CB was placed in service on Attachment 1, Resin Status Sheet.

CUE: Another operator will enter the information on Attachment 1, Resin Status Sheet.

STANDARD: The performer addresses entry of the Date, Time and Flow rate that the Cation Bed was placed in service is recorded on

.

COMMENTS:

___ SAT

___ UNSAT STEP 12: [11] NOTIFY Chemistry of Time, Date, and Flowrate when CB was placed in service.

STANDARD: The Performer notifies Chemistry of Time, Date, and Flowrate when CB was placed in service

COMMENTS:

END OF TASK

___ SAT

___ UNSAT STOP TIME ________

APPLICANT CUE SHEET (TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO TRAINEE:

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

INITIAL CONDITIONS:

1. The Unit is at 100% power.

2. Letdown orifice valve 1-FCV-62-74 is open and letdown flow (as indicated in MCR) is 75 gpm.

3. RCS boron concentration is 870 ppm.

4. Chemistry has requested that cation bed be placed in service for 53 minutes.

5. The Cation bed has been filled and vented.

6. SOI-62.04, Attachment 1, Resin Status Sheet indicates that the Cation Bed is at the same boron concentration of the RCS.

INITIATING CUES:

1. The MCR operator has directed you to place the CVCS Cation Bed in service per procedure.

2. You are to notify the MCR when the CVCS Cation Bed is in service.