Text

Initial Exam 2009-301 Final Sim/In-Plant JPMs
	ML092810562
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: ML092810562 (131)
	v • d • e

REV. 0 PAGE 1 0F 131 WATTS BAR NUCLEAR PLANT B.1.a ALTERNATE PATH.

B.1.a Withdraw Shutdown Banks.

REV. 0 PAGE 2 0F 131 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 Control Rod Drive System. A3.05, Ability to monitor automatic operation of the CRDS, including: Individual vs. group rod position. [3.5/3.5] (CFR: 41.7/45.13)

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-85.01, 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 SSN Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

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

COMMENTS

REV. 0 PAGE 3 0F 131 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 110 steps. Malfunction rd19 will enter at this event.

c. Place the simulator in RUN momentarily, and reset the High Flux at Shutdown alarm, and then 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 applicant indicates understanding of the task and time is allowed for control board familiarization.

5. After applicant 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 131 WATTS BAR NUCLEAR PLANT B.1.a READ TO APPLICANT DIRECTION TO APPLICANT:

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

6. All reactivity briefs required by SPP-10.4, Reactivity Management Program have been completed.

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 131 WATTS BAR NUCLEAR PLANT B.1.a START TIME: _______

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

___ UNSAT STANDARD: Applicant 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 Applicant after the Applicant successfully identifies the procedure and section.

STEP 2: [6] ENSURE 1-RBSS, ROD BANK SELECTOR SWITCH ___ SAT

[1-M-4], in MANUAL.

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

COMMENTS:

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

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

COMMENTS:

REV. 0 PAGE 6 0F 131 WATTS BAR NUCLEAR PLANT B.1.a STEP/STANDARD SAT/UNSAT STEP 4: [8] OBSERVE the following for proper response during Bank ___ SAT Withdrawal:

A. Source Range (SR) ________ ___ UNSAT B. Intermediate Range (IR) ________

C. Startup Meters ________

D. Nuclear Recorders ________

STANDARD: Applicant monitors above parameters as the rods are being withdrawn.

COMMENTS:

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

___ SAT STANDARD: Applicant places Rod Bank Selector switch RBSS-1 in SBA ___ UNSAT position.

COMMENTS:

STEP 6: [10] PLACE 1-FLRM, IN-HOLD-OUT SWITCH, to OUT to begin Critical Step withdrawing Shutdown Banks A1 and A2 to greater than or equal to 225 Steps. ___ SAT STANDARD: Applicant places 1-FLR to the OUT position and monitors ___ UNSAT shutdown bank A group A1 and A2 are responding.

COMMENTS:

REV. 0 PAGE 7 0F 131 WATTS BAR NUCLEAR PLANT B.1.a STEP/STANDARD SAT/UNSAT STEP 7: [11] MONITOR the following as the Bank is being withdrawn: ___ SAT A. Group Step Counters B. RPIs ___ UNSAT C. In-Out Status Lights D. Rod speed (64 Steps/Minute)

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

COMMENTS:

Note to evaluator:

Malfunction to fail step counters is to be inserted when Shutdown Bank A rods reach approximately 110 steps.

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

NOTE TO EVALUATOR:

If applicant has identified the failure and informs the evaluator, cue the applicant to take your appropriate actions.

STEP 9: Open the Reactor Trip Breakers. Critical Step

___ SAT STANDARD: Applicant determines the Group 1 step counter is not capable of determining the demand position for each of the ___ UNSAT Shutdown bank A rods within + 2 steps and opens the reactor trip breakers.

Cue: After the reactor trip breakers have been opened state "This completes this JPM.

COMMENTS:

STOP TIME ________

REV. 0 PAGE 8 0F 10 WATTS BAR NUCLEAR PLANT B.1.b DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. A 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.

6. All reactivity briefs required by SPP-10.4, Reactivity Management Program have been completed.

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 Chemical and Volume Control System. A4.06 Ability to manually operate and/or monitor in the control room: Letdown isolation and flow control valves. [3.6/3.1].

(CFR: 41/7 / 45.5 to 45.8).

Task Standard: Excess letdown has been placed in service per AOI-6, Small Reactor Coolant System Leak, 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 SSN Time 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 applicant indicates an understanding of the task.

4. After applicant 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 APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the 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, Small Reactor Coolant System Leak. Section 3.0, and Step 15, RESPONSE NOT OBTAINED.

2. You are to notify the Unit Supervisor when excess letdown has been aligned and pressurizer level is under control.

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

STEP 1: Obtain a copy of the procedure. ___ SAT STANDARD: A copy of AOI-6 has been obtained.

___ UNSAT COMMENTS:

STEP 2: Check pressurizer level DROPPING or STABLE.

___ SAT STANDARD: Applicant 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 ___ UNSAT CUES.

COMMENTS:

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

___ SAT STANDARD: Applicant enters the RESPONSE NOT OBTAINED column and begins procedure actions.

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

COMMENTS:

REV. 3 PAGE 15 0F 10 WATTS BAR NUCLEAR PLANT B.1.b STEP 4 : a. OPEN 1-FCV-70-143 CRITICAL STEP STANDARD: At panel 1-M-27B the applicant places 1-HS-70-143A to OPEN. Applicant verifies the RED light is LIT and the GREEN light is OFF. Step is critical to establish excess ___ SAT letdown flow.

NOTE: When the applicant opens 1-FCV-70-143, Annunciator 239-D will be received. This alarm occurs whenever 1- ___ UNSAT FCV-70-143 is OPEN and flow on 1-FS-70-8 is less than 230 gpm.

COMMENTS:

STEP 5 : b. OPEN 1-FCV-70-85 CRITICAL STEP STANDARD: At panel 1-M-27B the Applicant 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 ___ SAT establish excess letdown flow.

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

COMMENTS:

STEP 6 : c. OPEN 1-FCV-62-54 CRITICAL STEP STANDARD: At panel 1-M-5 the applicant 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 ___ SAT excess letdown flow.

COMMENTS:

___ UNSAT

REV. 3 PAGE 16 0F 10 WATTS BAR NUCLEAR PLANT B.1.b STEP 7 : d. OPEN 1-FCV-62-55 CRITICAL STEP STANDARD: At panel 1-M-5 the applicant 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 ___ SAT excess letdown flow.

COMMENTS:

___ UNSAT STEP 8 : e. ENSURE 1-FCV-62-59 is in NORMAL. ___ SAT STANDARD: At panel 1-M-5 the applicant determines that 1-HS-62-59A is in the NORM position, with the RED seal return light LIT.

___ UNSAT COMMENTS:

STEP 9: f. ADJUST 1-HIC-62-56A to obtain maximum flow and CRITICAL maintain excess letdown hx outlet temp less than 200°F. STEP STANDARD: At panel 1-M-5 the applicant opens 1-HIC-62-56A while monitoring 1-TI-62-58. Excess letdown temperature must ___ SAT remain below 200°F as indicated on 1-TI-62-58. Step is critical to establish excess letdown flow.

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

COMMENTS:

STEP 11: Notify the Unit Supervisor that Excess Letdown has been placed in service. ___ SAT STANDARD: The Unit Supervisor has been notified that Excess Letdown has been placed in service.

___ UNSAT

- CUE: When notified, acknowledge the report.

COMMENTS:

END OF TASK STOP TIME: ________

REV. 0 PAGE 18 OF 131 WATTS BAR NUCLEAR PLANT B.1.c DIRECTION TO APPLICANT:

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

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, Small Reactor Coolant System Leak. Section 3.0, and Step 15, RESPONSE NOT OBTAINED.

2. You are to notify the Unit Supervisor when excess letdown has been aligned and pressurizer level is under control.

REV. 0 PAGE 19 OF 131 WATTS BAR NUCLEAR PLANT B.1.c ALTERNATE PATH.

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

REV. 0 PAGE 20 OF 131 WATTS BAR NUCLEAR PLANT B.1.c Task: Isolate Cold Leg Accumulators per E-1.

Alternate Path: Cold Leg Accumulator #4 cannot be isolated and must be vented to comply with E-1,Loss of Reactor or Secondary Coolant, Step 26 RNO.

Facility JPM #: N/A K/A Rating(s): 011 Large Break LOCA. EA1.09 Ability to operate and monitor the following as they apply to a Large Break LOCA: Core flood tank initiation. [4.3/4.3] (CFR 41.7 / 45.5 /

45.6).

Task Standard: Cold Leg Accumulators 1, 2, and 3 are isolated per E-1,Loss of Reactor or Secondary Coolant, Step 26 AER. Cold Leg Accumulator 4 is vented, per E-1,Loss of Reactor or Secondary Coolant, 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 SSN Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

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

COMMENTS

REV. 0 PAGE 21 OF 131 WATTS BAR NUCLEAR PLANT B.1.c

REV. 0 PAGE 22 OF 131 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 Applicant indicates an understanding of the task.

3. After Applicant 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 23 OF 131 WATTS BAR NUCLEAR PLANT B.1.c READ TO APPLICANT DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. A large break LOCA has occurred.

2. E-1,Loss of Reactor or Secondary Coolant,performance has just been resumed after performance of ES-1.3,Transfer to Containment Sump.

3. You are the Control Room Operator.

INITIATING CUES:

1. The Unit Supervisor directs you perform E-1,Loss of Reactor or Secondary Coolant, Step 26, DETERMINE if cold leg accumulators should be isolated.

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

REV. 0 PAGE 24 OF 131 WATTS BAR NUCLEAR PLANT B.1.c START TIME: _______

STEP 1: Obtain a copy of the procedure.

___ SAT STANDARD: A copy of E-1 has been obtained EXAMINERS CUE: After the applicant has demonstrated the method of obtaining the correct instruction, the examiner will ___ UNSAT provide a marked-up copy of the instruction.

COMMENTS:

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

STANDARD: ___ SAT EXAMINERS CUE: When asked, inform the applicant that E-1 Appendix A CLA BREAKER OPERATION is complete.

___ UNSAT COMMENTS:

REV. 0 PAGE 25 OF 131 WATTS BAR NUCLEAR PLANT B.1.c STEP 3: b. CHECK RCS pressure less than 250 psig.

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

RVLIS-ICCM PLASMA DISPLAY on 1-M-4 or 1-M-6.

Loop 4 HL PRESS 1-PI-68-70. ___ UNSAT Loop 3 HL PRESS 1-PI-68-64.

Loop 2 HL Press 1-PI-68-63.

COMMENTS:

STEP 4: c. CLOSE cold leg accumulator isolation valves. CRITICAL STEP STANDARD: Applicant places 1-HS-63-118, 1-HS-63-98, 1-HS-63-80 and 1-HS-63-67 to close. Applicant observes that 1-HS-63-67 ___ SAT 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. ___ UNSAT COMMENTS:

STEP 5: c. RESPONSE NOT OBTAINED PERFORM the following:

___ SAT STANDARD: Applicant determines that RNO actions are required since 1-FCV-63-67 did NOT CLOSE.

COMMENTS: ___ UNSAT

REV. 0 PAGE 26 OF 131 WATTS BAR NUCLEAR PLANT B.1.c STEP 6: 1) RESET Phase B CRITICAL STEP STANDARD:

___ SAT Applicant 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.

___ UNSAT Applicant depresses 1-HS-30-64D B CNTMT ISOL RESET TR-A, and observes the B light goes DARK on 1-XX-55-6C Substep is critical since this action is taken to allow the air supply to the nitrogen makeup and vent valves to be restored.

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

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

COMMENTS:

REV. 0 PAGE 27 OF 131 WATTS BAR NUCLEAR PLANT B.1.c STEP 7: 2) ENSURE aux air pressure to cntmt is greater than 75 psig CRITICAL

[M-15] AND OPEN cntmt air supply valves. STEP STANDARD: ___ SAT Applicant 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 ___ UNSAT CLOSED.

Applicant places 1-HS-30-80A 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.

Applicant places 1-HS-30-102A 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.

Applicant 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:

REV. 0 PAGE 28 OF 131 WATTS BAR NUCLEAR PLANT B.1.c STEP 8: 3) OPEN any unisolated accumulators nitrogen makeup valve. CRITICAL STEP STANDARD: Applicant determines that 1-FCV-63-63 for CLA 4 must be OPENED. ___ SAT Applicant places 1-HS-63-63A N2 TO CL ACCUM 4 to OPEN position, and verifies RED light is LIT GREEN light is DARK.

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

COMMENTS:

STEP 8: 4) OPEN 1-FCV-63-65 vent header. CRITICAL STEP STANDARD: Applicant rotates 1-HIC-63-65A in the counterclockwise direction to OPEN 1-FCV-63-65 FULLY. ___ SAT Step is critical since this action is taken to minimize the chance of nitrogen injection into the RCS.

___ UNSAT COMMENTS:

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

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

___ SAT COMMENTS:

___ UNSAT END OF TASK STOP TIME ________

REV. 6 PAGE 29 OF 131 WATTS BAR NUCLEAR PLANT B.1.d DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. A large break LOCA has occurred.

2. E-1,Loss of Reactor or Secondary Coolant,performance has just been resumed after performance of ES-1.3,Transfer to Containment Sump.

3. You are the Control Room Operator.

INITIATING CUES:

1. The Unit Supervisor directs you perform E-1,Loss of Reactor or Secondary Coolant, Step 26, DETERMINE if cold leg accumulators should be isolated.

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

REV. 6 PAGE 30 OF 131 WATTS BAR NUCLEAR PLANT B.1.d ALTERNATE PATH.

B.1.d Place RHR Spray in Service per FR-Z.1, High Containment Pressure.

REV. 6 PAGE 31 OF 131 WATTS BAR NUCLEAR PLANT B.1.d EVALUATION SHEET Task: Place RHR Spray in Service per FR-Z.1, High Containment Pressure.

Alternate Path: When the Applicant 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 Residual Heat Removal System. A4.01 Ability to manually operate and/or monitor in the control room: Controls and indication for RHR pumps [3.6/3.4] (CFR:

41.7 / 45.5 to 45.8)

Task Standard: Train A of RHR Spray has been placed in-service per FR-Z.1, High Containment Pressure.

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/EIN Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

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

COMMENTS

REV. 6 PAGE 32 OF 131 WATTS BAR NUCLEAR PLANT B.1.d

REV. 6 PAGE 33 OF 131 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 1A CS Pump - handswitch is in PULL-TO-LOCK position

3. Place simulator in FREEZE until the applicant indicates an understanding of the task.

4. After applicant 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 34 OF 131 WATTS BAR NUCLEAR PLANT B.1.d READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the 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 its 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.1, 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 35 OF 131 WATTS BAR NUCLEAR PLANT B.1.d START TIME: _______

STEP 1: Obtain a copy of the procedure.

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

EXAMINERS CUE: After the applicant has demonstrated the method of obtaining the correct instruction, the evaluator will ___ UNSAT provide a marked-up copy of the instruction.

COMMENTS:

STEP 2: [Step 10] DETERMINE if RHR Spray should be placed in ___ SAT service:

a. CHECK the following conditions:

At least one hour elapsed since beginning of the accident. ___ UNSAT

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. Applicant 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:

REV. 6 PAGE 36 OF 131 WATTS BAR NUCLEAR PLANT B.1.d STEP 3: [STEP 10b] ALIGN Train B RHR spray: ___ SAT

1) ENSURE Train B RHR pump RUNNING.

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

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

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

COMMENTS: ___ UNSAT STEP 5: [STEP 10b 3)] CLOSE RHR injection 1-FCV-63-94. CRITICAL STEP STANDARD: 1-HS-63-94-A has been placed in the CLOSED position and the Applicant recognizes that the GREEN light DOES NOT ___ SAT illuminate.

Applicant enters the RNO Column to perform actions to align Train A RHR spray.

Step is critical since the RHR system is not designed to ___ UNSAT support both RHR spray and suction requirements associated with sump recirculation.

COMMENTS:

EVALUATOR NOTE: Applicant 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 37 OF 131 WATTS BAR NUCLEAR PLANT B.1.d STEP 6: [STEP 10b RNO] ALIGN Train A RHR spray: ___ SAT

1) ENSURE Train A RHR pump RUNNING.

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

COMMENTS:

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

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

___ UNSAT COMMENTS:

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

___ UNSAT STEP 9: [STEP 10b RNO] 4) OPEN RHR spray 1-FCV-72-40. CRITICAL STEP 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.

___ SAT COMMENTS:

___ UNSAT

REV. 6 PAGE 38 OF 131 WATTS BAR NUCLEAR PLANT B.1.d STEP 10: Notify the Unit Supervisor that RHR spray is in service.

___ SAT STANDARD: Notify the Unit Supervisor that RHR spray has been placed in service.

- CUE: When notified, acknowledge the report using repeat ___ UNSAT back.

COMMENTS:

END OF TASK TIME STOP: ________

REV. 0 Page 39 of 131 WATTS BAR NUCLEAR PLANT B.1.e DIRECTION TO APPLICANT:

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

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 its 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.1, 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 40 of 131 WATTS BAR NUCLEAR PLANT B.1.e B.1.e Place Containment Hydrogen Recombiner A in Service per SOI-83.01, Containment Hydrogen Recombiners.

REV. 0 Page 41 of 131 WATTS BAR NUCLEAR PLANT B.1.e Task: Place Containment Hydrogen Recombiner A in Service per SOI-83.01,Containment Hydrogen Recombiners.

Alternate Path: N/A Facility JPM #: 3-OT-JPMR052.

K/A Rating(s): 028 Hydrogen Recombiner and Purge Control System. A2.01Hydrogen recombiner power setting, determined by using plant data book. [3.4/3.6] (CFR: 41.5 / 43.5 /

45.3 / 45.13).

Task Standard: Containment Hydrogen Recombiner A has been placed in service per SOI-83.01, Containment Hydrogen Recombiners.

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 SSN Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

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

COMMENTS

REV. 0 Page 42 of 131 WATTS BAR NUCLEAR PLANT B.1.e

REV. 0 Page 43 of 131 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 applicant indicates an understanding of the task.

3. After applicant indicates understanding of the task, place simulator to RUN.

Tools/Equipment/Procedures Needed:

Ensure copies of SOI-83.01 Containment Hydrogen Recombiners, and TI-83.01, Hydrogen Recombiner Required Power-vs.-Containment Pressure.

REV. 0 Page 44 of 131 WATTS BAR NUCLEAR PLANT B.1.e READ APPLICANT DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. Unit has experienced a LOCA.

2. MCR crew is implementing 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 the 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 the Unit Supervisor when the required power setting is reached.

REV. 0 Page 45 of 131 WATTS BAR NUCLEAR PLANT B.1.e START TIME: _______

STEP 1: Obtain a copy of the procedure.

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

EXAMINERS CUE: After the applicant has demonstrated the method of obtaining the correct instruction, the evaluator can ___ UNSAT provide a copy of the instruction.

COMMENTS:

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 ___ SAT 000.

STANDARD: Applicant verifies that three zeros (000) are indicated on Panel 1-M-10. ___ UNSAT COMMENTS:

REV. 0 Page 46 of 131 WATTS BAR NUCLEAR PLANT B.1.e STEP 3: [2] VERIFY the White POWER IN AVAILABLE light LIT. ___ SAT STANDARD: Applicant verifies that the White POWER IN AVAILABLE light LIT on 1-M-10. ___ UNSAT COMMENTS:

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

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

COMMENTS:

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

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

COMMENTS:

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

REV. 0 Page 47 of 131 WATTS BAR NUCLEAR PLANT B.1.e STEP 6: [5] REQUEST Chemistry to sample containment atmosphere ___ SAT for H2 concentration.

STANDARD: Applicant contacts Chemistry to sample containment ___ UNSAT atmosphere.

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

COMMENTS:

STEP 7: [6] RECORD the Date and Time on Data Sheet 1. ___ SAT STANDARD: Applicant records Date and Time on Data Sheet 1

___ UNSAT COMMENTS:

REV. 0 Page 48 of 131 WATTS BAR NUCLEAR PLANT B.1.e STEP 8: [7] RECORD CNTMT H2 % on Data Sheet 1, THEN ___ SAT INDICATE from which source H2 percentage was obtained:

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

___ UNSAT

[7.2] ANAL B CNTMT H2, 1-H21-43-210 [1-M-10]

[7.3] Chemistry sample analysis STANDARD: Applicant 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:

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

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

COMMENTS:

REV. 0 Page 49 of 131 WATTS BAR NUCLEAR PLANT B.1.e STEP 10: [9] RECORD CNTMT PRESS (psig) on Data Sheet 1, ___ SAT THEN INDICATE which indicator was used:

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

___ UNSAT

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

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

COMMENTS:

STEP 11: [10] TURN POWER OUT (MS Starter) switch to ON, and CRITICAL VERIFY switch plate Red light LIT. STEP STANDARD: Applicant places switch in the UP position, and verifies the ___ SAT RED light is LIT. Step is critical since this action provides power to the recombiner.

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

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

___ UNSAT EVALUATOR CUE: Time Compression - 10 minutes have elapsed.

COMMENTS:

REV. 0 Page 50 of 131 WATTS BAR NUCLEAR PLANT B.1.e STEP 13: [12] ADJUST POWER ADJUST potentiometer to obtain 10 CRITICAL kW on POWER OUT meter, and MAINTAIN for 10 STEP minutes.

___ SAT STANDARD: Applicant adjusts the potentiometer and obtains 10 kW on the POWER OUT meter. Step is critical to warm up the recombiner. ___ UNSAT EVALUATOR CUE: Time Compression - 10 minutes have elapsed.

COMMENTS:

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

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

EVALUATOR CUE: Time Compression - 5 minutes have elapsed.

COMMENTS:

STEP 15: [14] DETERMINE the REQUIRED POWER (kW) based on CRITICAL current CNTMT PRESSURE (psig) using Attachment 3 of STEP TI-83.01, HYDROGEN RECOMBINER REQUIRED POWER-VS-CONTAINMENT PRESSURE CURVES. ___ SAT STANDARD: Applicant uses 3 psig containment pressure and reads 70 kW off the Attachment 3 curve in TI-83.01, HYDROGEN RECOMBINER REQUIRED POWER-VS-CONTAINMENT ___ UNSAT PRESSURE CURVES.

COMMENTS:

REV. 0 Page 51 of 131 WATTS BAR NUCLEAR PLANT B.1.e STEP 16: [15] ADJUST POWER ADJUST potentiometer to obtain the CRITICAL REQUIRED POWER (kW) using Attachment 3 of TI- STEP 83.01, HYDROGEN RECOMBINER REQUIRED POWER-VS-CONTAINMENT PRESSURE CURVES. ___ SAT STANDARD: Applicant adjusts the potentiometer and obtains 70 kW on the POWER OUT meter. Step is critical to warm up the recombiner. ___ UNSAT COMMENTS:

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 ___ SAT approximately 30 minutes, THEN ADJUST POWER ADJUST potentiometer to maintain 1225 - 1400°F recombiner average temperature.

___ UNSAT STANDARD:

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

COMMENTS:

REV. 0 Page 52 of 131 WATTS BAR NUCLEAR PLANT B.1.e STEP 18: [17] NOTIFY SRO that Recombiner A is in service and will be monitored at least once every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months per Section 8.2.

___ SAT STANDARD: Applicant notifies the SRO that A Recombiner is in service.

COMMENTS:

___ UNSAT END OF TASK STOP TIME _____

REV. 6 PAGE 53 OF 131 WATTS BAR NUCLEAR PLANT B.1.f DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. Unit has experienced a LOCA.

2. MCR crew is implementing 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 the 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 the Unit Supervisor when the required power setting is reached.

REV. 6 PAGE 54 OF 131 WATTS BAR NUCLEAR PLANT B.1.f B.1.f Synchronizing DG 1B-B from the MCR per SOI-82.02, Diesel Generator (D/G) 1B-B.

REV. 6 PAGE 55 OF 131 WATTS BAR NUCLEAR PLANT B.1.f EVALUATION SHEET Task: Synchronizing DG 1B-B from the MCR per SOI-82.02 Diesel Generator (D/G) 1B-B.

Alternate Path: N/A Facility JPM #: 3-OT-JPMR060 K/A Rating(s): 064 Emergency Diesel Generators. A1.03 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ED/G system controls including: Operating voltages, currents, and temperatures

[3.2/3.3] (CFR: 41.5 / 45.5) 064 Emergency Diesel Generators. A4.06 Ability to manually operate and/or monitor in the control room: Manual start, loading, and stopping of the ED/G [3.9/3.9]

(CFR: 41.7 / 45.5 to 45.8)

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 4 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/ID Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

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

COMMENTS

REV. 6 PAGE 56 OF 131 WATTS BAR NUCLEAR PLANT B.1.f

REV. 6 PAGE 57 OF 131 WATTS BAR NUCLEAR PLANT B.1.f SIMULATOR OPERATOR INSTRUCTIONS:

1. Initialize to IC # 316. NOTE: If this JPM is to be run concurrently with B.1.b, Place Excess Letdown in service, then reset to IC # 312.

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

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

4. Place simulator in FREEZE until the Applicant indicates an understanding of the task.

5. After applicant indicates understanding of the task, place simulator to RUN.

Tools/Equipment/Procedures Needed:

Ensure a marked-up copy of SOI-82.02, Diesel Generator (D/G) 1B-B is available to provide to each applicant.

Stop Watch, to time Synchroscope rotation.

REV. 6 PAGE 58 OF 131 WATTS BAR NUCLEAR PLANT B.1.f READ TO OPERATOR DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. Unit 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 Representative on site.

3. The 1B-B DG is running at rated speed, after performance of SOI-82.02, Diesel Generator (D/G) 1B-B, 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, Diesel Generator (D/G) 1B-B and load it to 4 MWs.

2. SOI-82.02, Diesel Generator (D/G) 1B-B, 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 4 MWs.

REV. 6 PAGE 59 OF 131 WATTS BAR NUCLEAR PLANT B.1.f START TIME: _______

STEP 1: Obtain a copy of the instruction.

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

EXAMINERS CUE: After the applicant has demonstrated the method ___ UNSAT of obtaining the correct instruction, the evaluator can provide a copy of the instruction.

COMMENTS:

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

___ SAT 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. ___ UNSAT COMMENTS:

REV. 6 PAGE 60 OF 131 WATTS BAR NUCLEAR PLANT B.1.f STEP 3: [5] ENSURE the following sync switches for 1B-B D/G in OFF.

NOMENCLATURE LOCATION POSITION UNID MAINTENANCE 6.9 UNIT 0-M-26 OFF 1-HS-57-69 BD 1C SYNC SWITCH ALTERNATE CSST C SYNC 0-M-26 OFF 1-HS-57-115 SWITCH DG SYNC SWITCH 0-M-26 OFF 1-HS-57-74 NORMAL-CSST D SYNC 0-M-26 OFF 1-HS-57-72 SWITCH STANDARD: Applicant checks listed sync switches in OFF position ___ SAT COMMENTS:

___ UNSAT STEP 4: [6] PLACE 1-HS-57-74, DG SYNC SWITCH, to SYN. CRITICAL STEP STANDARD: 1-HS-57-74, DG SYNC SWITCH, is placed to SYN position. ___ SAT This step is critical to allow synchronization of D/G to 1B-B Shutdown board.

COMMENTS: ___ 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 61 OF 131 WATTS BAR NUCLEAR PLANT B.1.f STEP 5: [7] MATCH generator Incoming Frequency (1-XI-82-32) with CRITICAL Running Frequency (1-XI-82-33) using 1-HS-82-43, STEP SPEED CONTROL [0-M-26].

___ SAT 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. ___ UNSAT COMMENTS:

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

___ SAT STANDARD: 1-HS-82-42 is used to adjust generator voltage on 1-EI 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. ___ UNSAT COMMENTS:

REV. 6 PAGE 62 OF 131 WATTS BAR NUCLEAR PLANT B.1.f STEP 7: [9] ENSURE DG Frequency and Voltage are MATCHED CRITICAL with 6.9 kV SD Bd, AND ADJUST 1-HS-82-43, SPEED STEP CONTROL, [0-M-26] to obtain desired clockwise rotation (15 or more seconds) on 1-XI-82-31, TRAIN 1B-B

___ SAT SYNCHROSCOPE.

STANDARD: Applicant verifies running and incoming frequency and voltage are matched and that the synchroscope is moving ___ UNSAT 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 applicant may use a stopwatch to time the 15 second rotation. Provide stopwatch if asked.

COMMENTS:

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 63 OF 131 WATTS BAR NUCLEAR PLANT B.1.f STEP 8: CRITICAL

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

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

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

[11] PERFORM the following: CRITICAL STEP 9:

STEP

[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). ___ SAT 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. ___ UNSAT COMMENTS:

REV. 6 PAGE 64 OF 131 WATTS BAR NUCLEAR PLANT B.1.f 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, ___ SAT VOLTAGE REGULATOR.

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

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

CRITICAL STEP 11: [11.3] PERFORM the following:

STEP

[c] RAISE load to at least 3.3 Megawatts.

STANDARD: The generator output is raised to >2.7 MW on 0-EI-82-40A.

This step is to ensure DG is loaded per task ___ SAT assignment, and the information in the CAUTION is complied with.

___ UNSAT COMMENTS:

REV. 6 PAGE 65 OF 131 WATTS BAR NUCLEAR PLANT B.1.f 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 ___ SAT COMMENTS:

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

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

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

COMMENTS:

STEP 14: Notify the Unit Supervisor that DG 1B-B is synchronized to the shutdown board and loaded to 4 MW.

___ SAT STANDARD: The Unit Supervisor is notified that DG 1B-B is synchronized to the shutdown board and loaded to 4 MW.

___ UNSAT CUE: As Unit Supervisor, when notified, acknowledge the report.

COMMENTS:

END OF TASK TIME STOP: ________

REV. 2 PAGE 66 OF 131 WATTS BAR NUCLEAR PLANT B.1.g DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. Unit 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, Diesel Generator (D/G) 1B-B, 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, Diesel Generator (D/G) 1B-B and load it to 4 MWs.

2. SOI-82.02, Diesel Generator (D/G) 1B-B, 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 4 MWs.

REV. 2 PAGE 67 OF 131 WATTS BAR NUCLEAR PLANT B.1.g ALTERNATE PATH B.1.g Return PRM N-42 to Service per AOI-4, NUCLEAR INSTRUMENTATION MALFUNCTIONS.

REV. 2 PAGE 68 OF 131 WATTS BAR NUCLEAR PLANT B.1.g 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 applicant to return rod control to manual and then a trip of the reactor.

Facility JPM #: 3-OT-JPMR108A Rev 0 K/A Rating(s): 015 Nuclear Instrumentation System. A4.02 A4 Ability to manually operate and/or monitor in the control room: NIS indicators. [3.9/3.9] (CFR: 41.7 / 45.5 to 45.8).

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, Attachment 1 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 AOI-2, "MALFUNCTION OF REACTOR CONTROL SYSTEM," Rev 37 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/EIN Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

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

COMMENTS

REV. 2 PAGE 69 OF 131 WATTS BAR NUCLEAR PLANT B.1.g 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 applicant indicates an understanding of the task.

4. After Applicant 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 70 OF 131 WATTS BAR NUCLEAR PLANT B.1.g READ TO APPLICANT DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. Unit 1 is at 100% power.

2. Power Range Monitor N42 failed during last shift.

3. AOI-4 NUCLEAR INSTRUMENTATION MALFUNCTIONS, Section 3.4. Power Range Monitor (PRM) Failure, 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 71 OF 131 WATTS BAR NUCLEAR PLANT B.1.g START TIME: _______

STEP 1: Obtain the correct procedure.

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

EXAMINERS CUE: After the applicant has demonstrated the method of obtaining the correct instruction, the evaluator will ___ UNSAT provide a marked-up copy of the instruction.

COMMENTS:

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.

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

___ UNSAT COMMENTS:

REV. 2 PAGE 72 OF 131 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 CRITICAL PERFORM the following steps: STEP

a. PLACE DETECTOR CURRENT COMPARATOR switch for UPPER SECTION in NORMAL

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

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

COMMENTS:

STEP 4: [STEP 2 b] PLACE DETECTOR CURRENT COMPARATOR CRITICAL switch for LOWER SECTION in NORMAL STEP STANDARD: Detector Current Comparator Lower Section switch placed to NORMAL (Miscellaneous Control & Indication Panel, 1- ___ SAT IDWR-92-N50-G IV).

Step is critical for proper restoration of lower power detector to current comparator. ___ UNSAT COMMENTS:

REV. 2 PAGE 73 OF 131 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. CRITICAL STEP STANDARD: Rod Stop Bypass switch is positioned from N42 to OPERATE (Miscellaneous Control & Indication Panel,1- ___ SAT IDWR-92-N50-G IV)

Step is critical for proper restoration of to enable rod stop interlock protection from this channel. ___ UNSAT COMMENTS:

STEP 6: [STEP 2 d] PLACE POWER MISMATCH BYPASS switch in CRITICAL OPERATE. STEP

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

___ UNSAT Step is critical to restore channel input to high auctioneering circuit and power mismatch circuits.

COMMENTS:

REV. 2 PAGE 74 OF 131 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 CRITICAL NORMAL. STEP

___ SAT STANDARD: Comparator Channel Defeat Switch is positioned to NORMAL (Comparator & Rate Panel, Comparator N37, 1-IDWR-92-N37 IV).

___ UNSAT Step is critical to restore channel input to channel comparator alarm circuits.

COMMENTS:

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 ___ SAT 42A II, is checked and determines light is NOT LIT and continues to next step.

COMMENTS: ___ UNSAT

REV. 2 PAGE 75 OF 131 WATTS BAR NUCLEAR PLANT B.1.g NOTE TO EVALUATOR: Applicant returns to AOI-4 at step 16 c.

STEP 9: [STEP 16 c] ENSURE T-avg and T-ref within 1°.

___ SAT STANDARD: Applicant 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.

___ UNSAT COMMENTS:

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

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

CERPI Display

Plant computer

___ UNSAT COMMENTS:

REV. 2 PAGE 76 OF 131 WATTS BAR NUCLEAR PLANT B.1.g STEP 11: [STEP 16 e] IF auto rod control desired, PLACE control rods in AUTO. ___ SAT STANDARD: The rod control hand switch has been placed in AUTO position. ___ UNSAT

- 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 applicant may immediately return rod control to manual, check for rod motion stopped, and then trip the reactor before referring to AOI-2.

COMMENTS:

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.

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

NOTE: Rods will continue to step IN. ___ UNSAT COMMENTS:

REV. 2 PAGE 77 OF 131 WATTS BAR NUCLEAR PLANT B.1.g STEP 13: [STEP 2] CHECK control rod movement STOPPED.

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

___ UNSAT

- NOTE: Rods will continue to step IN.

COMMENTS:

STEP 14: [STEP 2 RNO] TRIP reactor. GO TO E-0, Reactor Trip or CRITICAL Safety Injection. STEP

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

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

- CUE: Upon transition to E-O, inform applicant This completes this JPM.

COMMENTS:

END OF TASK TIME STOP: ________

REV. 0 PAGE 78 OF 131 WATTS BAR NUCLEAR PLANT B.1.h DIRECTION TO APPLICANT:

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

INITIAL CONDITIONS:

1. Unit 1 is at 100% power.

2. Power Range Monitor N42 failed during last shift.

3. AOI-4 NUCLEAR INSTRUMENTATION MALFUNCTIONS, Section 3.4. Power Range Monitor (PRM) Failure, 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 79 OF 131 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 80 OF 131 WATTS BAR NUCLEAR PLANT B.1.h Task: Shutdown A Train EGTS Following a 10 Hour Run per SOI-65.02, Emergency Gas Treatment System.

Alternate Path: N/A Facility JPM #: 3-OT-JPMR169 K/A Rating(s): 027 Containment Iodine Removal System (CIRS) A4.01, Ability to manually operate and/or monitor in the control room CIRS controls. [3.3*/3.3*] (CFR: 41,7/45.5/to 45.8) 029 Containment Purge System (CPS) A1.05 Knowledge of the physical connections and/or cause and effect relationships between the Containment Purge System and the containment air cleanup and recirculartion system. [2.9/3.1] (CFR:

41.2 to 41.9/45.7 to 45.8)

Task Standard: EGTS A Train has been shutdown and returned to Standby alignment in accordance with SOI-65.02 Emergency Gas Treatment System.

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 SSN Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

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

COMMENTS

REV. 0 PAGE 81 OF 131 WATTS BAR NUCLEAR PLANT B.1.h

REV. 0 PAGE 82 OF 131 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 applicant indicates understanding of the task and time is allowed for control board familiarization.

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

Tools/Equipment/Procedures Needed:

Ensure clean copy of SOI-65.02 Emergency Gas Treatment System in all JPM packages.

REV. 0 PAGE 83 OF 131 WATTS BAR NUCLEAR PLANT B.1.h READ TO APPLICANT DIRECTION TO APPLICANT I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the 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 0.00278 hours 1.653439e-5 weeks 3.805e-6 months .

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

INITIATING CUES:

1. The Unit Supervisor directs you to 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 84 OF 131 WATTS BAR NUCLEAR PLANT B.1.h START TIME: _______

STEP 1: Obtain a copy of the procedure.

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

EXAMINERS CUE: After the applicant has demonstrated the method of obtaining the correct instruction, the evaluator ___ UNSAT provides a copy of the instruction.

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

COMMENTS:

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

ØA light DARK.

COMMENTS:

___ UNSAT

REV. 0 PAGE 85 OF 131 WATTS BAR NUCLEAR PLANT B.1.h STEP 3: [Step 2] Momentarily PLACE 0-HS-65-23A, EGTS FAN & CRITICAL DISCH DMPR, in STOP (returns to A-AUTO). STEP STANDARD: Applicant stops A Train EGTS Fan with 0-HS-65-23A and checks red light off and green light ON the associated handswitch. ___ SAT Step is critical to shutdown the running EGTS Fan.

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

STANDARD: Applicant checks 1-HS-65-8 and verifies red light off and green light ON for the associated hand switch ___ UNSAT COMMENTS:

STEP 5: [Step 4] PERFORM the following: CRITICAL

[a] CLOSE 1-FCV-65-10, EGTS TR-A U1 SUCT DMPR. STEP

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

___ SAT STANDARD: Applicant closes 1-FCV-65-10 with 1-HS-65-10; applicant closes 1-FC0-65-26 with 1-HS-65-26. Respective hand switches red lights are off and green lights are LIT. ___ UNSAT Step is critical to shutdown return ventilation lineup to normal following 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months run.

COMMENTS:

REV. 0 PAGE 86 OF 131 WATTS BAR NUCLEAR PLANT B.1.h STEP 6: [STEP 5] IF Train A EGTS to be returned to STANDBY, THEN: CRITICAL PERFORM the following: 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: Applicant places 1-HS-65-10 and 1-HS-65-26 to the A AUTO ___ SAT position.

Step is critical to return these hand switches to ES Standby alignment. ___ UNSAT COMMENTS:

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

STANDARD: Applicant determines that this step does not apply and ___ SAT proceeds to the next step.

COMMENTS:

___ 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: Applicant goes to Section 5.0. ___ SAT COMMENTS:

___ UNSAT

REV. 0 PAGE 87 OF 131 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: Applicant determines that ØA Cntmt Isolation signal is NOT present by checking Master Isol Signal PNLs 1-XX-55-6C & 6D ___ SAT

ØA light DARK.

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

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

COMMENTS: ___ UNSAT

REV. 0 PAGE 88 OF 131 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 Bkr 38 OFF 1-BKR-235-1/38 1-PCV-65-81/1-PCV-65-86 STANDARD: Applicant contacts the Control Building AUO (or an AUO) and ___ SAT requests performance of Step 3.

- CUE: When asked as the AUO, state 1-BKR-235-1/38 is in the OFF position. ___ UNSAT COMMENTS:

STEP 12: [Step 4] ENSURE the following valves are CLOSED and PLACE 1-HS-65-83/87 in A AUTO.

NOMENCLATURE LOCATION POSITION UNID U1 EGTS-ANN P CNTLR B 0-M-27B A AUTO 1-HS-65-83/87 ISOL STANDARD: Applicant locates 1-HS-65-83/87 and places in A-AUTO. Step ___ SAT is critical to establishing EGTS configuration for automatic start after a ØA Cntmt Isolation signal.

COMMENTS: ___ UNSAT

REV. 0 PAGE 89 OF 131 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 Bkr 38 OFF 1-BKR-235-2/38 1-PCV-65-81/1-PCV-65-86 STANDARD: Applicant contacts an AUO and requests performance of Step ___ SAT 5.

- CUE: When asked as the AUO, state1-BKR-235-2/38 is in the OFF position. ___ UNSAT COMMENTS:

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: Applicant locates 0-HS-65-23A and ensures in A-AUTO. ___ SAT Applicant locates 0-HS-65-42A and ensures in A-AUTO.

COMMENTS:

___ UNSAT

REV. 0 PAGE 90 OF 131 WATTS BAR NUCLEAR PLANT B.1.h STEP 15: [STEP 7] OPEN the following valves, and PLACE the CRITICAL handswitches in A AUTO: STEP NOMENCLATURE LOCATION POSITION UNID U1 ANN VAC FANS SUCT 0-M-27B OPEN, HS in 0-HS-65-52 A AUTO U1 ANN VAC FANS SUCT 0-M-27B OPEN, HS in 0-HS-65-53 A AUTO STANDARD: Applicant locates 0-HS-65-52 and ensures OPEN and in A- ___ SAT AUTO.

Applicant locates 0-HS-65-53 and ensures OPEN and in A-AUTO.

Step is critical to establishing EGTS configuration for ___ UNSAT automatic start after a ØA Cntmt Isolation signal.

COMMENTS:

NOTES

1) The following step may be N/Ad 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 91 OF 131 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: Applicant verifies that annulus vacuum fans are running and ___ SAT N/As the step.

COMMENTS: ___ 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, A5W/737, 1-JB -292- RESET 1-HS-65-80 and EGTS CNTMT ANNULUS DP 4013-A, N. of GFFD 1-HS-65-90 RESET Rm.

PCV-65-83 and PCV-65-87, A4V/737, 1-JB-292- RESET 1-HS-65-82 and EGTS CNTMT ANNULUS DP 4015-B, S. of GFFD 1-HS-65-97 RESET Rm.

STANDARD: Applicant determines that no accident signal was present and ___ SAT N/As the step COMMENTS:

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

REV. 0 PAGE 92 OF 131 WATTS BAR NUCLEAR PLANT B.1.h STEP 18: [STEP 10] ENSURE the following controllers in AUTO:

NOMENCLATURE LOCATION POSITION UNID EGTS-ANN P 0-M-27B AUTO 1-PDIC-65-82 CONTROL EGTS-ANN P 0-M-27B AUTO 1-PDIC 80 CONTROL STANDARD: Applicant locates 1-PDIC-65-82 and ensures controller is in ___ SAT AUTO Applicant locates 1-PDIC 80 and ensures controller is in AUTO

___ UNSAT COMMENTS:

REV. 0 PAGE 93 OF 131 WATTS BAR NUCLEAR PLANT B.1.h STEP 19: [STEP 11] ENSURE the following:

NOMENCLATURE LOCATION POSITION UNID EGTS TR A DECAY 0-M-27B CLOSE 0-HS-65-28B COOLING EGTS TR A DECAY 0-M-27B CLOSE 0-HS-65-28A COOLING EGTS TR B DECAY 0-M-27B CLOSE 0-HS-65-47A COOLING EGTS TR B DECAY 0-M-27B CLOSE 0-HS-65-47B COOLING STANDARD: ___ SAT Applicant locates 0-HS-65-28B and ensures that it is CLOSED.

Applicant locates 0-HS-65-28A and ensures that it is CLOSED.

Applicant locates 0-HS-65-47A and ensures that it is CLOSED. ___ UNSAT Applicant locates 0-HS-65-47B and ensures that it is CLOSED.

COMMENTS:

REV. 0 PAGE 94 OF 131 WATTS BAR NUCLEAR PLANT B.1.h STEP 20: [STEP 12] PERFORM the following:

NOMENCLATURE LOCATION POSITION UNID EGTS TR-A U1 SUCT 0-M-27B A AUTO 1-HS-65-10 DMPR EGTS TR-A U1 SUCT 0-M-27B CLOSE 1-HS-65-8 DMPR EGTS FAN B U1 0-M-27B CLOSE 1-HS-65-51 SUCT DMPR EGTS TR-B U1 SUCT 0-M-27B A AUTO 1-HS-65-30 DMPR EGTS TO U1 SHIELD 0-M-27B A AUTO 1-HS-65-26 BLDG EGTS TO U1 SHIELD 0-M-27B A AUTO 1-HS-65-27 BLDG STANDARD:

___ SAT Applicant locates 1-HS-65-10 and ensures that it is in A-AUTO.

Applicant locates 1-HS-65-8 and ensures that it is CLOSED.

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

Applicant locates 1-HS-65-30 and ensures that it is in A-AUTO. ___ UNSAT Applicant locates 1-HS-65-26 and ensures that it is in A-AUTO.

Applicant locates 1-HS-65-27 and ensures that it is in A-AUTO.

COMMENTS:

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

STANDARD: Applicant notifies the Unit Supervisor that A Train EGTS Fan is shutdown and realigned for standby readiness. ___ UNSAT COMMENTS:

END OF TASK TIME STOP: ________

REV. 0 PAGE 95 0F 131 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 0.00278 hours 1.653439e-5 weeks 3.805e-6 months .

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

INITIATING CUES:

1. The Unit Supervisor directs you to 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 96 0F 131 WATTS BAR NUCLEAR PLANT B.1.i ALTERNATE PATH B.1.i Perform a boration of the RCS (LOCALLY) per AOI-34, IMMEDIATE BORATION.

REV. 0 PAGE 97 0F 131 WATTS BAR NUCLEAR PLANT B.1.i

REV. 0 PAGE 98 0F 131 WATTS BAR NUCLEAR PLANT B.1.i Task: Perform a Boration of the RCS (LOCALLY) per AOI-34 IMMEDIATE BORATION.

Alternate Path: 1-FCV-62-138 will not pass more than 8 gpm, 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: Total boration flow rate of 45 gpm has been established on 1-FCV-62-137A and 1-FI-62-139 after partially opening 1-FCV-62-136 and fully 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/EIN Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

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

COMMENTS

REV. 0 PAGE 99 0F 131 WATTS BAR NUCLEAR PLANT B.1.i

REV. 0 PAGE 100 0F 131 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 101 0F 131 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, IMMEDIATE BORATION, 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, IMMEDIATE BORATION, Step 6 actions to locally establish boric acid flow.

2. You are to establish a minimum boric acid flow rate of 45 gpm.

REV. 3 PAGE 102 0F 13 WATTS BAR NUCLEAR PLANT B.1.i START TIME: _______

STEP 1: Obtain a copy of the appropriate instruction.

___ SAT STANDARD:

EXAMINERS CUE: After the method of obtaining an instruction properly has been demonstrated, the evaluator ___ UNSAT provides a copy of the instruction.

COMMENTS:

STEP 2: [STEP 6.b. RNO] Locally ADJUST 1-FCV-62-138 to obtain required flow. ___ SAT 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 Applicant opens the valve by turning ___ UNSAT the hand wheel in the counter-clockwise direction.

CUE: State the motor operator hand wheel rotates a few turns (3-4) and stops.

COMMENTS:

REV. 3 PAGE 103 0F 13 WATTS BAR NUCLEAR PLANT B.1.i STEP 3: [STEP 6.c.] CHECK emergency borate flow on 1-FI-62-137A. CRITICAL STEP STANDARD: 1-FI-62-137A.has been checked and determination made that ___ SAT 8 gpm has been established, which is insufficient to meet the required flow rate. Entry into c. RNO is required, since the stated flow rate of 45 gpm is not established. Step is critical to evaluating whether a flow path has been ___ UNSAT established.

CUE: When applicant contacts the Main Control Room to check flow on 1- FI-62-137A, state the indicator reads 8 gpm.

If the applicant checks local flow indicator 1-FI-62-137B, indicate 8 gpm on the meter.

COMMENTS:

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- CRITICAL 62-929 [Blender Station/713]. STEP STANDARD: 1-ISV-62-929 is opened by turning the hand wheel in the counter-clockwise direction. Step is critical because it ___ SAT initiates boration flow.

CUE: State the hand wheel was rotated many turns in the counter-clockwise direction and has stopped. ___ UNSAT COMMENTS:

REV. 3 PAGE 104 0F 13 WATTS BAR NUCLEAR PLANT B.1.i STEP 5: [STEP 6.c. RNO continued] ENSURE BA flow control 1-FCV- ___ SAT 62-140 OPEN.

STANDARD: Applicant observes 1-FCV-62-140 and determines that the ___ UNSAT valve is OPEN COMMENTS:

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

STANDARD: Applicant contacts the MCR to determine if flow is indicated on ___ UNSAT 1-FI-62-139. The applicant determines that the combined flow rate from 1-FI-62-137A and 1-FI-62-139 of 48 gpm is greater than the required flow rate of 45 gpm.

CUE: When MCR is contacted, state1-FI-62-139 is indicating 40 gpm.

COMMENTS:

REV. 3 PAGE 105 0F 13 WATTS BAR NUCLEAR PLANT B.1.i STEP 15: [7] IF emergency boration flow established, THEN GO TO Step 9.

STANDARD: Applicant contacts MCR and reports that emergency boration flow has been established. ___ SAT CUE: Acknowledge report as MCR operator using repeat back.

COMMENTS: ___ UNSAT END OF TASK TIME STOP: ________

REV. 0 PAGE 106 0F 15 WATTS BAR NUCLEAR PLANT B.1.j DIRECTION TO APPLICANT:

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.

3. You are to establish a minimum boric acid flow rate of 45 gpm.

REV. 0 PAGE 107 0F 15 WATTS BAR NUCLEAR PLANT B.1.j B.1.j Perform E-3, Attachment 3, Steamline Isolation (Local)

REV. 0 PAGE 108 0F 15 WATTS BAR NUCLEAR PLANT B.1.j Task: Perform E-3, Steam Generator Tube Rupture, 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/EIN Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

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

COMMENTS

REV. 0 PAGE 109 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, Steam Generator Tube Rupture, Attachment 3, Steamline Isolation (Local). to applicant with applicants cue sheet.

REV. 0 PAGE 110 0F 15 WATTS BAR NUCLEAR PLANT B.1.j READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the 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, Steam Generator Tube Rupture, Attachment 3, Steamline Isolation (Local).

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

REV. 0 PAGE 111 0F 15 WATTS BAR NUCLEAR PLANT B.1.j START TIME: _______

STEP 1: Obtain a copy of the procedure.

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

EXAMINERS CUE: Provide E-3, Attachment 3,Steamline Isolation (Local) to the applicant. ___UNSAT COMMENTS:

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

STANDARD: The applicant contacts RADCON.

___SAT CUE: State The survey of steam lines has been made and is continuing periodically.

___UNSAT COMMENTS:

EXAMINER NOTE:

Applicant must locate all nine steam traps and demonstrate how to isolate one of them.

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

The applicant must locate an EOP ladder for use in operating valves located in hard to reach locations.

REV. 0 PAGE 112 0F 15 WATTS BAR NUCLEAR PLANT B.1.j STEP 3: [STEP 2] CLOSE at least one valve listed for each steam moisture CRITICAL trap manifold: STEP

[MAIN STEAM LINES]

MSTR TRAP LEVEL MSTR TRAP MSTR TRAP DRAIN LOCATION SWITCH STR ISOL ISOL 200 1-ISV-1-916 OR 1-ISV-1-922 [T1M/708]

STANDARD: The applicant 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 ___SAT 922. (Rotating hand wheel clockwise). Step is critical to isolate flow path.

CUE: State the hand wheel turns a few rotations and gets snug. ___UNSAT COMMENTS:

REV. 0 PAGE 113 0F 15 WATTS BAR NUCLEAR PLANT B.1.j STEP 4: [STEP 2 continued] CLOSE at least one valve listed for CRITICAL each steam moisture trap manifold: STEP

[MAIN STEAM LINES]

MSTR TRAP LEVEL MSTR TRAP MSTR TRAP DRAIN LOCATION SWITCH STR ISOL ISOL 201 1-ISV-1-926 OR 1-ISV-1-932 [T1M/708]

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

___UNSAT CUE: State the hand wheel turns a few rotations and gets snug.

COMMENTS:

STEP 5: [STEP 2 continued] CLOSE at least one valve listed for CRITICAL each steam moisture trap manifold: STEP

[MAIN STEAM LINES]

MSTR TRAP LEVEL MSTR TRAP MSTR TRAP DRAIN LOCATION SWITCH STR ISOL ISOL 202 1-ISV-1-936 OR 1-ISV-1-942 [T1M/708]

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

___UNSAT CUE: State the hand wheel turns a few rotations and gets snug.

COMMENTS:

REV. 0 PAGE 114 0F 15 WATTS BAR NUCLEAR PLANT B.1.j STEP 6: [STEP 2 continued] CLOSE at least one valve listed for CRITICAL each steam moisture trap manifold: STEP

[MAIN STEAM LINES]

MSTR TRAP LEVEL MSTR TRAP MSTR TRAP DRAIN LOCATION SWITCH STR ISOL ISOL 203 1-ISV-1-946 OR 1-ISV-1-952 [T1M/708]

STANDARD: The applicant 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 ___SAT 952. (Rotating hand wheel clockwise). Step is critical to isolate flow path.

CUE: State the hand wheel turns a few rotations and gets snug. ___UNSAT COMMENTS:

STEP 7: [STEP 2 continued] CLOSE at least one valve listed for CRITICAL each steam moisture trap manifold: STEP

[COMMON STEAM HEADER]

MSTR TRAP LEVEL MSTR TRAP MSTR TRAP DRAIN LOCATION SWITCH STR ISOL ISOL 204 1-ISV-1-956 OR 1-ISV-1-962 [T4J/708]

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

___UNSAT CUE: State the hand wheel turns a few rotations and gets snug.

COMMENTS:

REV. 0 PAGE 115 0F 15 WATTS BAR NUCLEAR PLANT B.1.j STEP 8: [STEP 2 continued] CLOSE at least one valve listed for CRITICAL each steam moisture trap manifold: STEP

[COMMON STEAM HEADER]

MSTR TRAP LEVEL MSTR TRAP MSTR TRAP DRAIN LOCATION SWITCH STR ISOL ISOL 206 1-ISV-1-966 OR 1-ISV-1-972 [T6J/708]

STANDARD: The applicant 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 972. (Rotating hand wheel clockwise). Step is critical to ___SAT isolate flow path.

CUE: State the hand wheel turns a few rotations and gets snug.

___UNSAT COMMENTS:

STEP 9: [STEP 2 continued] CLOSE at least one valve listed for CRITICAL each steam moisture trap manifold: STEP

[STEAM DUMP HEADER]

MSTR TRAP LEVEL MSTR TRAP MSTR TRAP DRAIN LOCATION SWITCH STR ISOL ISOL 207 1-ISV-1-976 OR 1-ISV-1-982 [T7H/708]

STANDARD: The applicant 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 ___SAT 982. (Rotating hand wheel clockwise). Step is critical to isolate flow path.

CUE: State the hand wheel turns a few rotations and gets snug. ___UNSAT COMMENTS:

REV. 0 PAGE 116 0F 15 WATTS BAR NUCLEAR PLANT B.1.j STEP 10: [STEP 2 continued] CLOSE at least one valve listed for CRITICAL each steam moisture trap manifold: STEP

[STEAM DUMP HEADER]

MSTR TRAP LEVEL MSTR TRAP MSTR TRAP DRAIN LOCATION SWITCH STR ISOL ISOL 208 1-ISV-1-986 OR 1-ISV-1-992 [T7G/708]

STANDARD: The applicant 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 ___SAT 992. (Rotating hand wheel clockwise). Step is critical to isolate flow path.

CUE: State the hand wheel turns a few rotations and gets snug. ___UNSAT COMMENTS:

REV. 0 PAGE 117 0F 15 WATTS BAR NUCLEAR PLANT B.1.j STEP 11: [STEP 2 continued] CLOSE at least one valve listed for CRITICAL each steam moisture trap manifold: STEP

[STEAM DUMP HEADER]

MSTR TRAP LEVEL MSTR TRAP MSTR TRAP DRAIN LOCATION SWITCH STR ISOL ISOL 209 1-ISV-1-996 OR 1-ISV-1-1002 [T7F/708]

STANDARD: The applicant 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 ___SAT 1002. (Rotating hand wheel clockwise). Step is critical to isolate flow path.

CUE: State the hand wheel turns a few rotations and gets snug. ___UNSAT COMMENTS:

STEP 12: [STEP 3] CLOSE steam supply isolation and bypass for CRITICAL each Main Feed Pump Turbine: STEP MFPT NOMENCLATURE LOCATION POSITION UNID 1A MFPT 1A HP STEAM T2J/729 CLOSED 1-ISV-1-611 SUPPLY ISOL STANDARD: The applicant locates valve and closes valve (rotating hand wheel clockwise). Step is critical to isolate flow path.

___SAT CUE: State the hand wheel turns a few rotations and gets snug.

___UNSAT COMMENTS:

REV. 0 PAGE 118 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 T2J/729 CLOSED 1-IBV-1-613 SUPPLY ISOL BYPASS STANDARD: The applicant locates valve and checks valve closed (rotating hand wheel clockwise).

CUE: State the hand wheel turns a few rotations and gets snug. ___SAT COMMENTS: ___UNSAT STEP 14: [STEP 3 continued] CLOSE steam supply isolation and CRITICAL bypass for each Main Feed Pump Turbine: STEP MFPT NOMENCLATURE LOCATION POSITION UNID 1B MFPT 1B HP STEAM T2H/729 CLOSED 1-ISV-1-612 SUPPLY ISOL STANDARD: The applicant locates valve and closes valve (rotating hand wheel clockwise). Step is critical to isolate flow path.

___SAT CUE: State the hand wheel turns a few rotations and gets snug.

___UNSAT COMMENTS:

REV. 0 PAGE 119 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 T2H/729 CLOSED 1-IBV-1-614 SUPPLY ISOL BYPASS STANDARD: The applicant locates valve and checks valve closed (rotating hand wheel clockwise).

___SAT CUE: State the hand wheel does not move with clockwise force on hand wheel.

___UNSAT COMMENTS:

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

STANDARD: The MCR Operator has been notified that local main steam isolation has been performed per E-3, Attachment 3. ___SAT CUE: When notified, acknowledge the report.

COMMENTS: ___UNSAT END OF TASK TIME STOP: ________

REV. 4 PAGE 120 0F 131 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 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, Steam Generator Tube Rupture, Attachment 3, Steamline Isolation (Local).

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

REV. 4 PAGE 121 0F 131 WATTS BAR NUCLEAR PLANT B.1.k B.1.k Place the CVCS Cation Demineralizer in Service per SOI-62.04, CVCS PURIFICATION SYSTEM.

REV. 4 PAGE 122 0F 131 WATTS BAR NUCLEAR PLANT B.1.k Task: Place the CVCS Cation Demineralizer in Service per SOI-62.04, CVCS PURIFICATION SYSTEM, 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, CVCS PURIFICATION SYSTEM.

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 SSN Time Finish: ________

Performance Rating: SAT ____ UNSAT ____ Performance Time ___

Examiner: _____________________________ _____________________________/________

NAME SIGNATURE DATE

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

COMMENTS

REV. 4 PAGE 123 0F 131 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 124 0F 131 WATTS BAR NUCLEAR PLANT B.1.k READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the 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 776 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, CVCS PURIFICATION SYSTEM, 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 125 0F 131 WATTS BAR NUCLEAR PLANT B.1.k START TIME: _______

STEP 1: Obtain a copy of the procedure. ___ SAT STANDARD: Applicant has obtained a copy of SOI-62.04, CVCS PURIFICATION SYSTEM, Section 8.2

___ UNSAT EXAMINERS CUE: After the applicant has demonstrated the method of obtaining the correct instruction, the evaluator can provide a copy of the instruction.

COMMENTS:

STEP 2: [1] ENSURE CB FILLED and VENTED per Section 8.1. ___ SAT STANDARD: Applicant determines the Cation Bed is filled and vented per the INITIAL CONDITIONS provided. ___ UNSAT EXAMINERS CUE: If asked, inform the applicant that Section 8.1 is complete.

COMMENTS:

Due to the location of one of the valve handwheels that will be operated, the applicant 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 126 0F 131 WATTS BAR NUCLEAR PLANT B.1.k STEP 3: [2] PERFORM the following:

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

EVALUATOR CUE: State The handwheel will not rotate.

___ UNSAT COMMENTS:

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

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

___ UNSAT EVALUATOR CUE: State the handwheel will not rotate.

COMMENTS:

REV. 0 PAGE 127 0F 131 WATTS BAR NUCLEAR PLANT B.1.k STEP 5: [4] REVIEW Attachment 1, Resin Status Sheet to ensure CB is ___ SAT FILLED and BORATED.

STANDARD: Applicant determines that the CB is filled and borated (given in initial conditions) and proceeds to the next step. ___ UNSAT EVALUATOR CUE: Hand the applicant the Attachment 1 Resin Status Sheet.

COMMENTS:

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

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

COMMENTS:

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 128 0F 131 WATTS BAR NUCLEAR PLANT B.1.k STEP 7: [6] OPEN 1-ISV-62-915, CVCS CATION DEMIN BED INLET. CRITICAL STEP STANDARD: 1-ISV-62-915 has been located and opened (turned in the counter-clockwise direction). ___ SAT EVALUATOR CUE: State the hand wheel rotates several turns and stops.

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

Step is critical to establish flow through the cation demineralizer.

COMMENTS:

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

STANDARD: Applicant determines that flush is not required (per EVALUATOR CUE) and N/As step. ___ UNSAT EVALUATOR CUE: State that flush is not necessary, nor desired at this time.

COMMENTS:

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 129 0F 131 WATTS BAR NUCLEAR PLANT B.1.k STEP 9: [8] SLOWLY OPEN 1-ISV-62-916, CVCS CATION DEMIN CRITICAL BED OUTLET. STEP STANDARD: 1-ISV-62-916 has been located and opened slowly (turned in ___ SAT the counter-clockwise direction).

EVALUATOR CUE: State the hand wheel rotates several turns and stops. ___ UNSAT If indicator checked, indicate it points to the open position.

Step is critical to establish flow through the cation demineralizer.

COMMENTS:

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

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

EVALUATOR CUE: State the hand wheel rotates several turns and ___ UNSAT 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 flow through the cation demineralizer.

COMMENTS:

REV. 0 PAGE 130 0F 131 WATTS BAR NUCLEAR PLANT B.1.k 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, ___ SAT Resin Status Sheet.

STANDARD: The applicant addresses entry of the Date, Time and Flow rate that the Cation Bed was placed in service is recorded on ___ UNSAT Attachment 1.

COMMENTS:

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

STANDARD: The applicant notifies Chemistry of Time, Date, and Flowrate ___ SAT when CB was placed in service COMMENTS:

___ UNSAT END OF TASK STOP TIME ________

APPLICANT CUE SHEET (RETURN 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 776 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, CVCS PURIFICATION SYSTEM, 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.

ML092810562

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