ML13344B144

From kanterella
Jump to navigation Jump to search
Initial Exam 2013-301 Final Sim_IN-Plant JPMs
ML13344B144
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 11/30/2013
From:
NRC/RGN-II
To:
Duke Energy Carolinas
References
Download: ML13344B144 (297)


Text

LICENSE EXAMINATION JOB PERFORMANCE MEASURE ILC13 NRC JPM A RevO Establishing RCS Cold Shutdown Boron Concentration Concurred By: Pat Lathrop Date: 5/15/13 Operations Approved By: James Conder Date: 6/5/13 Superintendent/Supervisor Training

ILC-13 NRC JPM A Page 2 of 12 LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task: 01093127904, Respond to a Steam Generator Tube Leak JAW AOP-03 5.

Alternate Path:

NO JPM#: Candidate ILC-13 NRC JPM A RO/SRO K/A Rating (RO/SRO:

004 A4.18 4.3/4.1 004 A4.04 3.2/3.6 Task Standard:

Required amount of Boric Acid added to establish RCS Cold Shutdown Boron Concentration.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate

References:

AOP-035, S/G Tube Leak Validation Time 15 Minutes Time Critical NO Time Critical Time: N/A Candidate: (N/A if not time critical)

Name Overall Critical Time Time SSN Start: Start:

Finish: Finish:

Performance Rating SAT UNSAT Performance circle one Time (mm):

Examiner:

Print Name Signature Date

ILC-13 NRC JPM A Page 3 of 12 COMMENTS:

QUESTION DOCUMENTATION:

Question:

Response

ILC-13 NRC JPM A Page 4 of 12 COMMENTS Step 2 Critical because step has the candidate open MOV-350 to align a boric acid flow path.

Step 3 Critical because step will start a Boric Acid pump to provide motive force for the boric acid.

Step 6 Critical to calculate the appropriate time that the boric acid flow may be secure. If the time is calculated incorrectly then adequate shutdown margin may not be obtained.

Step 8 Critical to close MOV-350 after the appropriate amount of boric acid has been added.

ILC-13 NRC JPM A Page 5 ofl2 SIMULATOR OPERATOR INSTRUCTIONS:

1. Initialize the simulator to IC-9 13
2. Go to RUN ensure plant conditions are stable.
3. Place simulator in FREEZE until candidate is ready to begin the JPM.
4. An extra instructor will be needed to acknowledge alarms that do not apply to this JPM.

ILC-13 NRC JPM A Page 6 of 12 Tools/Equipment/Procedures Needed:

AOP-035, S/G Tube Leak, Attachment 3, Establishing RCS Cold Shutdown Boron Concentration Calculator DIRECTIONS TO CANDIDATE:

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 facilitate the examination and better enable me to assess your level of understanding, verbalize your actions and observations while performing the JPM. To indicate that you have completed your assigned task return the Candidate Cue Sheet I provided you.

CANDIDATE INFORMATION:

Inform the candidate there are NO time critical steps in this JPM.

INITIAL CONDITIONS:

1. You are the Unit 2 Control Operator.
2. Crew is implementing AOP-035, S/G Tube Leak, for a 20 gpm leak in A S/G.
3. The plant has been shutdown JAW AOP-038, Rapid Downpower, from 100% RTP.
4. No equipment is out of service.
5. The first three steps ofAOP-035, Attachment 3, Establishing RCS Cold Shutdown Boron Concentration, has been completed and determined that 700 gallons of boric acid needs to be added to the RCS.

INITIATING CUES:

The CRS directs you to borate the RCS to the Mode 5 Shutdown Requirement using Attachment 3, Establishing RCS Cold Shutdown Boron Concentration (AOP-035 step 35). A copy of AOP-035, Attachment 3, with steps 1 3 completed has been provided.

ILC-13 NRC JPM A Page 7 of 12 START TIME:

I EXAMINERS CUE: Candidate is given a copy of AOP-035, Attachment 3, with steps 1 3 completed.

STEP 1: IF the MOV-350, BA TO CHARGING PMP SUCT Valve flowpath is unavailable, THEN Borate the RCS using OP-301, Chemical and Volume Control System (CVCS) Section RCS Boration Quick Checklist SAT (Step 4)

STANDARD: Candidate determines that MOV-350 is AVAILABLE based on information given in the cue sheet and N/As this step. UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 2: IF the MOV-350, BA TO CHARGING PMP SUCT Valve flowpath will CRITICAL be used, THEN open MOV-350, BA TO CHARGING PMP SUCT Valve. STEP (Step 5)

STANDARD: Candidate opens MOV-350 and verifies open by observing the RED open light illuminated and the GREEN closed light extinguished. SAT EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM A Page 8 of 12 STEP 3: Start Boric Acid Pump aligned for Blended Makeup. CRITICAL (Step 6) STEP STANDARD: Candidate starts A Boric Acid Pump and verifies pump started by observing the RED on light illuminated and the GREEN off light SAT extinguished.

EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 4: Record time boration commenced.

(Step 7)

SAT STANDARD: Candidate determines and records the time in blank provided.

EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM A Page 9 of 12 STEP 5: Record Flowrate indicated on Fl-i 10, BORIC ACID BYPASS FLOW.

gpm (Step 8) SAT STANDARD: Candidate observes flow indication on Fl- 110 and records flow of 60 to 70 gpm.

UNSAT EXAMINERS NOTE: NONE COMMENTS:

STEP 6: Determine time required to establish CSD boron concentration. CRITICAL STEP Boric Acid Volume Required (gal) minutes Fl- 110 Flowrate (gpm)

SAT (Step 9)

STANDARD: @ 70 gpm: Candidate determines that 700 gal/70 gpm equates to 10 mill.

UNSAT

@ 65 gpm: Candidate determines that 700 gal/65 gpm equates to 10.8 mill.

@ 60 gpm: Candidate determines that 700 gal/60 gpm equates to 11.7 mm.

EXAMINERS NOTE: NONE COMMENTS:

NOTE MOV-350 may be stroked three times per hour (EE 89-076). A stroke is defined as complete travel of a valve from either the fully open to the fully closed position or vice versa.

ILC-13 NRC JPM A Page 10 of 12 STEP 7: IF any RCP #1 Seal Leakoff temperature approaches 170°F as indicated by TR-448, THEN cycle MOV-350 to maintain RCP#1 Seal Leakoff temperature less than 170°F SAT (Step 10)

STANDARD: Candidate checks TR-448 and determines that RCP#1 Seal Leakoff temperatures are not approaching 170°F. (Checks Points 1 (TE-132), 8 UNSAT (TE-129) and 15 (TE-126)

EXAMINERS NOTE: Candidate may decide to utilize ERFIS RCP parameter indication to monitor RCP parameters.

COMMENTS:

STEP 8: WHEN required amount of boric acid has been added, THEN close MOV-350. CRITICAL (Step 11) STEP STANDARD: When 10 minutes has elapsed OR informed by Examiner that 10 minutes has elapsed the candidate closes MOV-350 and observes the GREEN SAT closed light illuminated and the RED open light extinguished.

EXAMINERS NOTE: Only use time compression if calculated time is correct AND has been verbalized by the candidate AND is greater UNSAT than 10 minutes.

EXAMINERS CUE: After candidate has demonstrated that they are monitoring RCP #1 Seal Leakoff temperature and time remaining inform the candidate that time compression has occurred and the calculated time has elapsed.

COMMENTS:

NOTE If the Boric Acid Pump aligned for blend was in START to prevent exceeding starting duty limitation, then the Boric Acid Pump should remain in START.

ILC-13 NRC JPM A Page 11 of 12 STEP 9: Restore the Boric Acid Pump aligned for blend as follows:

  • Place Boric Acid Pump aligned for blend in AUTO (Step 12)

UNSAT STANDARD: Candidate places A Boric Acid Pump control switch in AUTO.

EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 10: Notify Chemistry personnel to sample the RCS for boron concentration.

(Step 13)

SAT STANDARD: Candidate notifies Chemistry personnel to sample the RCS for boron.

EXAMINERS CUE: Inform the candidate that this concludes the JPM.

UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

END OF TASK Terminating Cue: When boric acid addition has been terminated.

TIME STOP:

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

CANDIDATE INFORMATION:

Inform the candidate there are NO time critical steps in this JPM.

INITIAL CONDITIONS:

1. You are the Unit 2 Control Operator.
2. Crew is implementing AOP-035, S/G Tube Leak, for a 20 gpm leak in A S/G.
3. The plant has been shutdown JAW AOP-038, Rapid Downpower, from 100% RTP.
4. No equipment is out of service.
5. The first three steps of AOP-035, Attachment 3, Establishing RCS Cold Shutdown Boron Concentration, has been completed and determined that 700 gallons of boric acid needs to be added to the RCS.

INITIATING CUES:

The CRS directs you to borate the RCS to the Mode 5 Shutdown Requirement using Attachment 3, Establishing RCS Cold Shutdown Boron Concentration (AOP-035 step 35).

Rev. 25 AOP035 SIG TUBE LEAK Page 53 of 65 CONTINUOUS USE ATTACHMENT 3 ESTABLISHING RCS COLD SHUTDOWN BORON CONCENTRATION (Page 1 of 3)

{. Record the minimum required Mode 5 Boron concentration.

1302 ppm Determine RCS boron concentration change required to establish CSD boron concentration.

1302 1000 302 Required CSD Latest RCS Boron Concentration Boron Sample Determine volume of boric acid to be added using Station Curve s Book.

700 gallons

4. IF the MOV-350. BA TO CHARGING PMP SUCT Valve flowpath is unavailable, THEN Borate the RCS using OP-301, Chemical and Volume Control System (CVCS) Section RCS Boration Quick Checklist
a. WHEN Boration is complete, Go To Step 13.
5. IF the MOV-350, BA TO CHARGING PMP SUCT Valve flowpath will be used, THEN open MOV-350, BA TO CHARGING PMP SUCT Valve.
6. Start Boric Acid Pump aligned for Blended Makeup.
7. Record time boration commenced.
8. Record flowrate indicated on Fl-hO, BORIC ACID BYPASS FLOW.

gpm

9. Determine time required to establish CSD boron concentration.

Boric Acid Volume Required (gal) minutes Fl-lb Flowrate (gpm)

Rev. 25 AOP-035 S/G TUBE LEAK Page 54 of 65 CONTINUOUS USE ATTACHMENT 3 ESTABLISHING RCS COLD SHUTDOWN BORON CONCENTRATION (Page 2 of 3)

NOTE MOV-350 may be stroked three times per hour (EE 89-076) . A stroke is defined as complete travel of a valve from either the fully open to the fully closed position or vice versa.

10. IF any RCP #1 Seal Leakoff temperature approaches 170°F as indicated by TR-448, cycle MOV-350, BA TO CHARGING PMP SUCT, to maintain RCP #1 Seal Leakoff temperature less than 170°F.
11. WHEN required amount of boric acid has been added, III close MOV-350, BA TO CHARGING PMP SUCT.

NOTE If the Boric Acid Pump aligned for blend was in START to prevent exceeding starting duty limitations, then the Boric Acid Pump should remain in START.

12. Restore the Boric Acid Pump aligned for blend as follows:
13. Notify Chemistry personnel to sample the RCS for boron concentration.

Rev. 25 AOP-035 S/G TUBE LEAK Page 55 of 65 CONTINUOUS USE ATTACHMENT 3 ESTABLISHING RCS COLD SHUTDOWN BORON CONCENTRATION (Page 3 of 3)

14. Adjust RCS makeup controls for blended flow at CSD boron concentration as follows:
a. Determine setpoint for FCV-113A, BORIC ACID FLOW Controller, using Station Curve Book.
b. Adjust FCV-ll3A potentiometer to required setpoint.
c. Verify RCS MAKEUP MODE Switch in AUTO.
d. Momentarily place RCS MAKEUP SYSTEM Switch to START.
15. Return to procedure and step in effect.

- END -

LICENSE EXAMINATION JOB PERFORMANCE MEASURE ILC-13 NRC JPM B RevO Place LTOP in Service Concurred By: Kirk Schauer Date: 5/15/13 Operations Approved By: James Conder Date: 6/5/13 Superintendent/Supervisor Training

ILC-13 NRC JPM B Page 2 of 13 LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task: 0101000201, Place LTOP System in Service Alternate Path:

NO 3PM #: Candidate ILC-13 NRC 1PM B RO/SRO K/A Rating (RO/SRO):

010A4.03 4.0 / 3.8 Task Standard:

LTOP has been placed in service.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate

References:

GP-007, Plant Cooldown From Hot Shutdown to Cold Shutdown Validation Time: 15 Minutes Time Critical: NO Time Critical Time: N/A Candidate: (N/A if not time critical)

Name Overall Critical Time Time SSN - Start Start Finish Finish Performance Rating Performance SAT UNSAT circle one Time (mm):

Examiner:

Print Name Signature Date

ILC.-13 NRC JPM B Page 3 of 13 COMMENTS:

QUESTION DOCUMENTATION:

Question:

Response

ILC-13 NRC JPM B Page 4 of 13 COMMENTS Step 1 Critical because RCS pressure must be lowered to within the specified pressure band prior to placing LTOP in service.

Step 2 Critical because the step places the PZR PORVs in LOW PRESSURE operation.

ILC-13 NRC JPM B Page 5 of 13 SIMULATOR OPERATOR INSTRUCTIONS:

1. Initialize the simulator to IC-9 17
2. Go to RUN ensure plant conditions are stable.
3. Pull up cooldown plot on RO ERFIS screen (QP GP-007)
4. Place simulator in FREEZE until candidate is ready to begin the JPM.
5. An extra instructor will be needed to acknowledge alarms that do not apply to this JPM

ILC-13 NRC JPM B Page 6 of 13 Tools[Eguipment/Procedures Needed:

GP-007 DIRECTIONS TO CANDIDATE:

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 facilitate the examination and better enable me to assess your level of understanding, verbalize your actions and observations while performing the JPM. To indicate that you have completed your assigned task return the Candidate Cue Sheet I provided you.

CANDIDATE INFORMATION:

Inform the candidate there are NO time critical steps in this JPM.

INITIAL CONDITIONS:

1. You are the Unit 2 Operator at Controls
2. Cooldown to Cold Shutdown is in progress.

INITIATING CUES:

The CRS directs you to place LTOP in service JAW GP-007, continuing at step 8.3.1O.b.

ILC-13 NRC JPM B Page 7 of 13 START TIME:

i NOTE: The RCS cooldown may be continued below 350 degrees F when the requirements of ITS LCO 3.5.2 and 3.4.12 are met. These requirements are met upon completion of Step 8.3.10 below.

CAUTION RCS temperature shall NOT be allowed to lower below 350 degrees F until the requirements of ITS LCO 3.5.2 and 3.4.12 are met.

STEP 1: WHEN RCS temperature is between 3 50°F and 3 60°F, THEN perform CRITICAL the following: STEP

a. While continuing with this step, the SM shall VERIFY that the Plant Equipment Status Review started in step 8.3.2 is complete AND the plant is ready to enter MODE 4. (SOER 09-1, Recommendation3) SAT
b. SLOWLY ADJUST PC-444J, PZR PRESS 444J, OR Pressurizer Spray Valves in Manual to reduce RCS pressure to between 350 psig and 375 psig without exceeding 180°F/hr cooldown rate on the PZR. UNSAT (Step 8.3.l0.b)

STANDARD: Places PC-444J in Manual and raises output to lower RCS pressure OR places PZR Spray Valve Controller(s) in manual and raises output to lower RCS pressure without exceeding 180°F/hr cooldown rate on the PZR. Maintains pressure within band of 350 psig to 375 psig. Pressure may be allowed to drift out of the band but CANNOT reach the LTOP setpoint of 400 psig.

EXAMINERS CUE: NONE EXAMINERS NOTE: An Auto-Makeup will occur during this JPM. Inform the candidate that another operator will monitor the makeup.

BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM B Page 8 of 13 NOTE: ITS LCO 3.4.12 contains a Note which amplifies when SI Accumulators are required to be isolated.

The following step is a simplified method to ensure compliance and eliminates the need to use ITS LCO 3.4.3 curves.

STEP 2: IF any SI Accumulator is pressurized, THEN VERIFY each SI Accumulator isolation valve is closed and deenergized. (ITS LCO 3.4.12)

  • MCC-5(14F) OPEN SAT
  • MCC-6(1OJ) OPEN
  • MCC-5(9F)

(Step 8.3.1O.c)

STANDARD: Candidate determines that the SI Accumulators are NOT pressurized by observing the SI Accumulators Pressure indications on the RTGB (PT 921A, 923, 925, 927, 929, 931) or ERFIS and N/As this step.

EXAMINERS CUE: If the candidate requests an AO check breaker status, report that all requested breakers are open.

EXAMINERS NOTE: NONE 300TH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM B Page 9 of 13 NOTE: ITS LCO 3.5.2 is applicable in MODE 3 and above. A Note in this LCO identifies that operation is allowed in MODE 3 with one SI Pump declared inoperable, due to the need to meet ITS LCO 3.4.12, for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

The following step ensures an SI Pump can be restored if required by AOP-020 following a loss of RHR.

STEP 3: VERIFY a maximum of one SI Pump is capable of injecting into the RCS by performing the following: (ITS LCO 3.4.12.a.2)

1. DEENERGIZE SI Pump being removed from service by pulling pump fuses (do NOT rack breaker). Circle SI Pump deenergized: SAT SI Pump A / SI Pump B / SI Pump C (Step 8.3.1O.d(1)) IJNSAT STANDARD: Verifies breaker indication for only A SI pump is illuminated.

EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC 3PM B Page 10 of 13 STEP 4: VERIFY a maximum of one SI Pump is capable of injecting into the RCS by performing the following: (ITS LCO 3.4.12.a.2)

2. VERIFY each flowpath to the RCS is ISOLATD as follows:
  • SI-870A (BIT OUTLET) CLOSED SAT
  • SI-870B (BIT OUTLET) CLOSED
  • SI-869 (LOOPS B/C HOT LEG INJECTIONS SHUTOFF) CLOSED
  • SI-895T (BIT BYPASS) LOCKED CLOSED 1SAT
  • SI-883L (SI-868A,B,C TEST LINE ISOLATION) LOCKED CLOSED (Step 8.3.10.d(2))

STANDARD: Candidate verifies that SI-870ALB and SI-869 are closed by observing their GREEN closed indication illuminated. Candidate may use the Safety Injection status lights or SPDS Containment Status which will indicate that SI-870A/B and SI-869 are closed.

Candidate will contact AO to determine the status of SI-895T and SI 883L.

EXAMINERS NOTE: NONE SOOTH OPERATOR CUE: When candidate contacts AO, inform candidate that SI 895T and SI-883L are in the LOCKED CLOSED position and have been Verified.

COMMENTS:

ILC-13 NRC JPM B Page 11 of 13 STEP 5: VERIFY a maximum of one SI Pump is capable of injecting into the RCS by performing the following: (ITS LCO 3.4.12.a.2)

3. PLACE Caution Tags/Caps on the following components stating:

Manipulating or installing this component may require entry into ITS SAT LCO 3.4.12.a.

(Step 8.3.1O.d(3))

UNSAT STANDARD: Candidate recognizes need to install Caution Tags/Caps EXAMINERS CUE: Inform the candidate that the CRS has assigned this task to another operator and requests that you continue on in GP-007 with the assigned task.

EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM B Page 12 of 13 CAUTION The Low Temperature Overpressure Protection System shall be operable in MODES 4, 5, and 6 when the RCS s not vented to containment in accordance with ITS LCO 3.4.12. If one or both PZR PORVs become inoperable, then refer to ITS LCO 3.4.12.

STEP 6: ALIGN the PZR PORVs and Block Valves as follows: CRITICAL

  • MCC-6(7J), RC-535, PZR PORV PCV-456 BLOCK breaker CLOSED STEP
  • RC-535,PORV BLOCK OPEN
  • MCC-6(8J), RC-536, PZR PORV PCV-455C BLOCK breaker CLOSED
  • PZR PCV-455C Overpressure Selector Switch LOW PRESSURE (CS)
  • PCV-455C, PZR PORV AUTO UNSAT
  • PCV-455C Position Indication CLOSED
  • PZR PCV-456 Overpressure Selector Switch LOW PRESSURE (CS)
  • PCV-456, PZR PORV AUTO
  • PCV-456 Position Indication CLOSED (Step 8.3.1O.e)

STANDARD: - Verifies RC-535 and 536 breakers closed by observing control board indicating lights

- Verifies RC 535 and 536 RED open indication on control board

- Places PCV-455C Overpressure selector switch in LOW PRESURE (CS)

- Places PCV-456 Overpressure selector switch in LOW PRESSURE (CS)

- Verifies PCV-455C and PCV-456 GREEN closed indication and in AUTO on control board EXAMINERS NOTE: (CS) Critical Step COMMENTS:

END OF TASK Terminating Cue: When the Pressurizer PORVs are placed in LTOP mode with RCS pressure between 350 psig and 375 psig and RCS temperature greater than 350°F TIME STOP:

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

CANDIDATE INFORMATION:

Inform the candidate there are NO time critical steps in this JPM.

INITIAL CONDITIONS:

1. You are the Unit 2 Control Operator.
2. Cooldown to Cold Shutdown is in progress.

INITIATING CUES:

The CRS directs you to place LTOP in service lAW GP-007, continuing at step 8 3 10 b

Section 8.3 Page 9 of 13 INIT NOTE: The RCS cooldown may be continued below 350 degrees F when the requirements of ITS LCD 3.5.2 and 3.4.12 are met. These requirements are met upon completion of Step 8.3.10 below.

CAUTION RCS temperature shall NOT be allowed to lower below 350 degrees F until the requirements of ITS LCD 3.5.2 and 3.4.12 are met.

WHEN RCS temperature is between 350°F and 360° F, THEN perform the following:

While continuing with this step, the SM shall VERIFY that the Plant Equipment Status Review started in step 8.3.2 is complete AND the plant is ready to enter MODE 4.

(SOER 09-1, Recommendation 3)

ISM

b. SLOWLY ADJUST PC-444J, PZR PRESS 444J, OR Pressurizer Spray Valves in Manual to reduce RCS pressure to between 350 psig and 375 psig without exceeding 180°F/hr cooldown rate on the PZR.

GP-007 Rev. 97 Page 54of 120

Section 8.3 Page 10 of 13 8.3.10 (Continued) ].N.iI NOTE: ITS LCO 3.4.12 contains a Note which amplifies when SI Accumulators are required to be isolated. The following step is a simplified method to ensure compliance and eliminates the need to use ITS LCO 3.4.3 curves.

c. IF any SI Accumulator is pressurized, THEN VERIFY each SI Accumulator isolation valve is closed and deenergized.

(ITS LCO 3.4.12)

SI Accumulator A SI-865A CLOSED MCC-5(14F) OPEN SI Accumulator B SI-865B CLOSED MCC-6(IOJ) OPEN SI Accumulator C SI-865C CLOSED MCC-5(9F) OPEN NOTE: ITS LCO 3.5.2 is applicable in MODE 3 and above. A Note in this LCO identifies that operation is allowed in MODE 3 with one SI Pump declared inoperable, due to the need to meet ITS LCO 3.4.12, for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

The following step ensures an SI Pump can be restored if required by AOP-020 following a loss of RHR.

d. VERIFY a maximum of one SI Pump is capable of injecting into the RCS by performing the following:

(ITS LCO 3.4.12.a.2)

(1) DEENERGIZE SI Pump being removed from service by pulling pump fuses (do NOT rack out breaker). Circle SI Pump deenergized:

SI Pump A I SI Pump B I SI Pump C GP-007 Rev. 97 Page 55 of 120

Section 8.3 Page 11 of 13 8.3.1O.d (Continued) INIT VERI (2) VERIFY each flowpath to the RCS is ISOLATED as follows:

SI-870A (BIT OUTLET) CLOSED Sl-870B (BIT OUTLET) CLOSED S 1-869 (LOOPS B AND C HOT LEG INJECTIONS SHUTOFF)

CLOSED Sl-895T (BIT BYPASS) LOCKED CLOSED SI-883L (Sl-868A, B, & C TEST LINE ISOLATION)

LOCKED CLOSED (3) PLACE Caution Tags/Caps on the following components stating: Manipulating or installing this component may require entry into ITS LCO 3.4.1 2.a.

CAUTION TAG#_______ INIT SI-870A BIT OUTLET, handwheel SI-870B - BIT OUTLET, handwheel SI-870A BIT OUTLET, control switch SI-870B BIT OUTLET, control switch SI-869 LOOPS BAND C HOT LEG INJECTIONS SHUTOFF, handwheel S1-869 LOOPS BAND C HOT LEG INJECTIONS SHUTOFF, control switch SI-895T BIT BYPASS SI-883L Sl-868A, B, & C TEST LINE ISOLATION SI Pump fuses pulled in Step 8.3.1O.d(1)

Control switch for SI Pump in Step 8.3.1O.d(1)

GP-007 Rev. 97 Page 56 of 120

Section 8.3 Page 12 of 13 8.3.10 (Continued) INIT CAUTION The Low Temperature Overpressure Protection System shall be operable in MODES 4, 5, and 6 when the RCS is not vented to containment in accordance with ITS LCO 3.4.12.

If one or both PZR PORVs become inoperable, then refer to ITS LCO 3.4.12.

e. ALIGN the PZR PORVs and Block Valves as follows:

- MCC-6(7J), RC-535, PRESSURIZER PORV PCV-456 BLOCK breaker CLOSED

- RC-535, PORV BLOCK OPEN MCC-6(8J), RC-536, PRESSURIZER PORV PCV-455C BLOCK breaker CLOSED

- RC-536, PORV BLOCK OPEN PZR PCV-455C Overpressure Selector Switch LOW PRESSURE

- PCV-455C, PZR PORV AUTO PCV-455C Position Indication CLOSED PZR PCV-456 Overpressure Selector Switch LOW PRESSURE

- PCV-456, PZR PORV AUTO PCV-456 Position Indication CLOSED GP-007 Rev. 97 Page 57 of 120

Section 8.3 Page 13 of 13 INIT CAUTION PPP-007, Feedwater Leakage Test, allows a Feed Regulating Valve to leak by at rates up to 735 gpm. Feedwater Regulating Valve leakage can lead to violation of RCS cooldown rates and overfilling of Steam Generators.

The RCS cooldown rate shall not exceed the limits shown in ITS Figure 3.4.3-2.

The ADMINISTRATIVE limits for RCS and PZR heatup and cooldown are:

  • RCS Heatup Rate: 50°F/hr
  • RCS Cooldown Rate: 80°F/hr
  • PZR Heatup Rate: 80°F/hr
  • PZR Cooldown Rate: 180°F/hr Refer to Precaution & Limitation 5.4.e if these limits must be exceeded
11. WHEN Step 8.3.10 is complete AND RCS temperature has lowered to 350°F, THEN PERFORM the following:
a. STATION an Operator locally at the Feedwater Header Section Valves to monitor the cycling of the valves.
b. CYCLE the Feedwater Header Section Valves OPEN and then CLOSED to prevent the possibility of thermal binding during cooldown of the valves (EE 89-96).

- V2-6A, FW HDR SECTION OPEN

- V2-6A, FW HDR SECTION CLOSED V2-6B, FW HDR SECTION OPEN

- V2-68, FW HDR SECTION CLOSED

- V2-6C, FW HDR SECTION OPEN

- V2-6C, FW HDR SECTION CLOSED GP-007 Rev. 97 Page58of120

LICENSE EXAMINATION JOB PERFORMANCE MEASURE ILC-13 NRC JPM C RevO Establish RCS Bleed and Feed Concurred By Kirk Schauei Date 5/15/13 Operations Approved By: James Conder Date: 6/5/13 Superintendent/Supervisor Training

ILC-13 NRC JPM C Page 2 of 16 LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task: 01113107905, Respond to Loss of Secondary Heat Sink JAW FRP-H. 1 Alternate Path:

YES JPM #: Candidate JLC-13 NRC JPM C RO/SRO K/A Rating (ROISRO):

002.A2.04 4.3 / 4.6 074.EA2.02 4.3 / 4.6 Task Standard:

RCS bleed and feed has been established by completion of FRP-H. 1 up through and including establishing an RCS bleed path by opening the RCS head vents and depressurizing at least one S/G.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate

References:

FRP-H. 1 Validation Time: 5 Minutes Time Critical: Yes Time Critical Time: 8 Minutes Candidate: (N/A if not time critical)

Name Overall Critical Time Time SSN - Start: Start:

Finish: Finish:

Performance Rating: Performance SAT UNSAT circle one Time (mm):

Examiner:

Print Name Signature Date

ILC-13 NRC JPM C Page 3 of 16 COMMENTS:

QUESTION DOCUMENTATION:

Question:

Response

ILC-13 NRC JPM C Page 4 of 16 COMMENTS Step 5 Critical because if RCPs are not secured then they will provide additional heat input to the RCS.

Step 6 Critical because safety injection pumps are utilized as the feed source for the RCS and PZR once the vent (bleed) path is established.

Step 8 Critical because IA is needed to operate the PZR PORVs.

Step 9 Critical because vent path for PZR must be established to lower RCS pressure below shutoff head of SI Pumps.

Step 11 Critical because additional vent path must be established since both PORVs cannot be verified open and are needed to lower RCS pressure to below the shutoff head of the SI pumps.

JPM is Time Critical because Heat Sink must be established in a timely manner to prevent core damage.

Time Critical Steps are steps 1 through 11 and the time for them is 8 minutes

ILC-13 NRC JPM C Page 5 of 16 SIMULATOR OPERATOR INSTRUCTIONS:

1. Initialize the simulator to IC-9 12
2. Go to RUN ensure plant conditions are stable.
3. Open SCN File 009_ILC_13_NRC_CR_JPM_C and execute.
4. Place simulator in FREEZE until candidate is ready to begin JPM.
5. An extra instructor will be needed to acknowledge alarms that do not apply to this JPM
1. If IC-9 12 is unavailable, reset simulator to IC-5 and perform the following:
2. Insert malfunction RPSO1A and RPSO1B failure to trip Auto and Manually (BOTH)
3. Activate IMF CFW- 19 (total loss of feedwater).
4. When SG WR levels <18% then manually trip the reactor
5. Verify 2 charging pumps Running
6. Freeze the simulator after SG WR levels are less than 10%

ILC-13 NRC JPM C Page 6 of 16 Tools/Equipment/Procedures Needed:

FRP-H.1 DIRECTIONS TO CANDIDATE:

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 facilitate the examination and better enable me to assess your level of understanding, verbalize your actions and observations while performing the JPM. To indicate that you have completed your assigned task return the Candidate Cue Sheet I provided you.

CANDIDATE INFORMATION:

Inform the candidate there ARE time critical steps in this JPM.

INITIAL CONDITIONS:

1 Plant was imtially at 100% power

2. A terrorist attack on the plant has resulted in a loss of all feedwater capability.
3. The reactor failed to trip automatically and from the RTGB.
4. EOP-E-0 was entered and transitioned to FRP-S. 1.
5. Upon resetting SPDS, a RED terminus exists on Heat Sink due to all S/G <8% and AFW <300 gpm
6. The crew has transitioned to FRP-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK 7 You are the Reactor Operator INITIATING CUES The CRS directs you to respond to a loss of secondary heat sink JAW FRP-H. 1.

TIME CRITICAL

ILC-13 NRC JPM C Page 7 of 16 START TIME: TIME CRITICAL START TIME TEP 1: Obtain a copy of the appropriate procedure SAT STANDARD: Operator obtains a copy of FRP-H.1 from the bookcase EXAMINERS CUE: The controlled copy from the bookcase will be replaced UNSAT after the JPM EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

CAUTION Feed flow is not re-established to any faulted SIG if an intact SIG is available.

STEP 2: Check total feed flow LESS THAN 300 gpm due to operator action.

(Step 1)

STANDARD: Candidate CHECKS total feed flow < 300 gpm and no operator action SAT taken and, lAW RNO, goes to step 3.

EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM C Page 8 ofl6 STEP 3: Determine If Secondary Heat Sink Is Required As Follows:

a. Check RCS pressure GREATER THAN ANY NON-FAULTED S/G PRES SURE.
b. Check RCS temperature GREATER THAN 350°F [310 F]

- SAT (Step 3)

STANDARD: Using available indications, Candidate DETERMINES UNSAT

a. RCS pressure is greater than all non-faulted S/G pressures by observing RCS pressure on the ICCM monitor and individual S/G pressures on the RTGB edge meters or ERFIS computer.
b. RCS temperature is greater than 350 F by observing TR-408 for Tave or TR-4 10 and/or TR-4 13 for RCS Tcold and Thot temperatures.

EXAMINERS CUE: NONE EXAMINERS NOTE: Candidate checks RCS pressure, S/G pressure, and RCS temperature. Candidate determines that Secondary Heat Sink is required and proceeds to Step 4.

BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 4: Check Any Two S/G Wide Range Levels LESS THAN 10% [19%].

(Step 4)

STANDARD: Candidate DETERMINES that all 3 S/Gs levels are less than 10% wide SAT range level by observing levels on LR-477.

EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM C Page 9 of 16 STEPS: Perform The Following: CRITICAL

a. Stop all RCPs STEP
b. Observe CAUTION prior to Step 31 and Go To Step 31 (Step 5)

STANDARD: Candidate PERFORMS the following actions: SAT

a. PLACES control switches for A, B, and C RCPs to STOP and observing the GREEN off indication illuminated.
b. OBSERVES CAUTION prior to Step 31 and PROCEEDS to Step 31.

UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

CAUTION 3teps 31 through 35 must be performed quickly in order to establish RCS heat removal by RCS bleed and feed.

STEP 6: Depress the INITIATE SAFETY INJECTION Pushbutton CRITICAL (Step 31) STEP STANDARD: Candidate DEPRESSES either of the two INITATE SAFETY iNJECTION Pushbuttons. Only depressing one of the Initiate Safety SAT Injection Pushbuttons is required to meet the Critical Step.

EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM C Page 10 of 16 STEP 7: Verify RCS Injection Path As Follows:

a. Verify SI Pumps AT LEAST ONE RUNNING
b. Verify SI Valves for at least one flow path ALIGNED FOR COLD LEG INJECTION SAT (Step 32)

STANDARD: Candidate Verifies at least one SI pump is running by observing the RED UNSAT on indication illuminated for either A or C SI pump.

Candidate determines that one flow path to the core from the SI pumps is aligned by observing that valves SI-867A or B and SI-870A or B are open by observing the RED open indication illuminated.

Candidate may use the Safety Injection status lights which will indicate that all of the SI valves are properly aligned for core injection, with the exception of the SI Accumulator Discharge valves SI-865A, B and C which have their breakers open.

EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM C Page 11 of 16 STEP 8: Establish Instrument Air To CV As Follows: CRITICAL

a. Verify APP-002-F7, INSTR AIR HDR LO PRESS EXTINGUISHED

- STEP

b. Place IA-1716, INSTRUMENT AIR ISO TO CV Control Switch to the OVERRIDE position (CS)

(Step 33)

SAT STANDARD: Candidate Verifies APP-OO2-F7, INSTR AIR HDR LO PRESS is Extinguished and Places IA-1716, INSTRUMENT AIR ISO TO CV Control Switch to the OVERRIDE position (CS) and observes that the INST AIR VALVE TO CONT PCV-1716 SHUT status light on the Containment TJIJSAT Isolation Phase A status panel is extinguished.

EXAMINERS CUE: NONE EXAMINERS NOTE: PCV-1716 valve position may also be determined using the SPDS display on the ERFIS computer for Containment Phase A Status Panel display. (CS) Critical Step BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM C Page 12 of 16 STEP 9: Establish RCS Bleed Path As Follows: CRITICAL

a. Verify power to PZR PORV Block Valves AVAILABLE.

- STEP

b. Place all PZR Heater Control Switches to the OFF position (CS)

Verify PZR PORV Block Valves BOTH OPEN

d. Open both PZR PORVs (CS for PCV-456)

SAT (Step 34)

STANDARD: Candidate PERFORMS the following:

a. Candidate determines that power is available to PZR PORV block valves UNSAT RC-535 and RC-536 by observing that indication is available on the RTGB valve indication.
b. Candidate places the control switches for the PZR Control Group Heaters, Backup Group A and Backup Group B to the OFF position and observes the GREEN off indication illuminated. (CS)
c. Candidate verifies that both PZR PORV block valves are open by observing the RED open indication illuminated for each valve.
d. Candidate opens the PZR PORVs PCV-455C and PCV-456 (CS for PCV-456 only) by placing the control switches to the open position and observing the RED open indication illuminate for PCV-456. PCV-455C will indicate failed at mid-position and will have both the RED and GREEN indicators illuminated.

EXAMINERS CUE: NONE EXAMINERS NOTE: (CS) Critical Step BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM C Page 13 of 16 STEP 10: Verify Adequate RCS Bleed Path As Follows:

  • PZR PORV Block Valves BOTH OPEN SAT (Step 35)

STANDARD: Candidate determines that both PZR PORVs are NOT OPEN by observing the RED and GREEN mid-position indication illuminated for PCV-455C. U1JSAT The candidate proceeds to the RNO step, which directs transition to Step 37.

EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM C Page 14 of 16 STEP 11: Place the Key Switches for the following Vent Valves to the OPEN CRITICAL Position: STEP

  • RC-568,HEAD VENT
  • RC-570,PZRVENT
  • RC-572, CV ATMOS SAT
  • RC-567, HEAD VENT
  • RC-569, PZR VENT
  • RC-571,PTR ISO UNSAT (Step 37)

STANDARD: Candidate places the key switches for valves RC-568, 570, 572, 567, 569 and 571 to the OPEN position and observes that the RED open indication for each valve is illuminated.

EXAMINERS CUE: NONE EXAMINERS NOTE: Blank keys are inserted into the key switches. The blanks will have to be removed and the keys inserted into the switches to operate the valves.

BOOTH OPERATOR CUE: NONE COMMENTS:

Time Critical Stop Time

ILC-13 NRC JPM C Page 15 of 16 CRITICAL STEP 12: Depressurize At Least One Intact SIG To Atmospheric Pressure Using STEP Steam Line PORVs.

(Step 38)

STANDARD: Candidate depressurizes at least one of the S/Gs by opening the selected SAT Steam Line PORV by rotating the valve control potentiometer in the clockwise direction and observing RED open indication for the PORV illuminated. Minimal steam noise will be heard since all steam generators are already at very low steam pressure. UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

END OF TASK Terminating Cue: When selected SIG depressurization has commenced, evaluation on the JPM is complete.

TIME STOP:

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

CANDIDATE INFORMATION:

Inform the candidate there ARE time critical steps in this JPM.

INITIAL CONDITIONS:

1. Plant was initially at 100% power.
2. A terrorist attack on the plant has resulted in a loss of all feedwater capability.
3. The reactor failed to trip automatically and from the RTGB.
4. EOP-E-0 was entered and transitioned to FRP-S. 1.
5. Upon resetting SPDS, a RED terminus exists on Heat Sink due to all S/G <8% and AFW <300 gpm
6. The crew has transitioned to FRP-H. 1, RESPONSE TO LOSS OF SECONDARY HEAT SINK.
7. You are the Reactor Operator.

INITIATING CUES:

The CRS directs you to respond to a loss of secondary heat sink JAW FRP-H. 1.

TIME CRITICAL

CONTINUOUS USE H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 PLANT OPERATING MANUAL VOLUME 3 PART 4 FUNCTION RESTORATION PROCEDURE FRPH. 1 RESPONSE TO LOSS OF SECONDARY HEAT SINK REVISION 25 Page 1 of 42

Rev. 25 FRP-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK Page 2 of 42 Purpose and Entry Conditions (Page 1 of 1)

1. PURPOSE This procedure provides actions to respond to a loss of secondary heat sink in all Steam Generators.
2. ENTRY CONDITIONS
a. EOP-E-O, REACTOR TRIP OR SAFETY INJECTION. Step 9, when minimum AFW flow is not verified AND narrow range level in all S/Os is less than 8% [18%]
b. CSF-3. Heat Sink Critical Safety Function Status Tree on a RED condition.

- END -

Rev. 25 FRP-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK Page 3 of 42 j__STEP_H ACTION/EXPECTED RESPONSE H RESPONSE NOT OBTAINED I

CAUTION Feed flow is not re-established to any faulted S/G if an intact S/G is available.

1. Check Total Feed Flow - LESS Go To Step 3.

THAN 300 GPM DUE TO OPERATOR ACTION

2. Reset SPDS And Return To Procedure And Step In Effect
3. Determine If Secondary Heat Sink Is Required As Follows:
a. Check RCS pressure - GREATER a. Reset SPDS and return to THAN ANY NON-FAULTED SIG procedure and step in effect.

PRESSURE

b. Check RCS temperature - b. Perform the following:

GREATER THAN 350°F [310°F]

1) Place RHR System in service using Supplement I.
2) WHEN adequate cooling with RHR is established, THEN reset SPDS and return to procedure and step in effect.
4. Check Any Two SIG Wide Range any two S/G Wide Range Levels Levels - LESS THAN 10% [19%] lower to less than 10% [19%]

THEN Go To Step 5.

Go To Step 6.

5. Perform The Following:
a. Stop all RCPs
b. Observe CAUTION prior to Step 31 and Go To Step 31

Rev. 25 FRP-H.l RESPONSE TO LOSS OF SECONDARY HEAT SINK Page 4 of 42

__STEP_H ACTION/EXPECTED RESPONSE r RESPONSE NOT OBTAINED I

6. Check CST level - GREATER THAN Align SW backup to the AFW Pumps lOah using OP402, Auxiliary Feedwater System, while continuing with this procedure.

IF the CST is low due to catastrophic failure AI] is inaccessable, JJ align SW backup to the MDAFW Pumps using Attachment 2, SW Backup To MDAFW Pumps.

Go To Step 14.

7. Verify All SIG Blowdown AND Sample Isolation Valves - CLOSED
8. Check AFW Lines - INTACT Isolate break.

IF the break is isolated, THEN Go To Step 9.

IF the break can NOT be isolated, Go To Step 14.

Rev. 25 FRP-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK Page 5 of 42 STEP_H ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED

9. Try To Establish Motor Driven AFW Flow To At Least One SIG As Follows:
a. Check AFW Pump Breakers - a. Go To Step 9.c.

TRIPPED

b. Attempt to reclose any tripped breakers as follows:
1) Position the MDAFW Pump Control Switch to the STOP position
2) Reset SI
3) Position the MDAFW Pump Control Switch to the START position
4) Check MDAFW Pump - RUNNING 4) j the tripped breaker will NOT reclose, THEN contact I&C to investigate.

Go To Step 10.

c. Verify AFW HDR DISCH Valves -

OPEN:

  • V2-16A
  • V2-16B
  • V2-16C
d. Check AFW flow to S!Gs - d. Go To Step 10.

GREATER THAN 300 GPM

e. Reset SPDS and return to procedure and step in effect

Rev. 25 FRP-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK Page 6 of 42 j STEP_H ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED

10. Attempt To Start SDAFW Pump As Follows:
a. Verify STEAM DRIVEN AFW PUMP a. the steam supply valves STM SHUTOFF Valves - OPEN can 1QI be opened. 1N Go To Step 11.
  • V1-8A
  • V1-8B
  • V1-8C
b. Verify STEAM DRIVEN AFW PUMP DISCH Valves - OPEN
  • V2-14A
  • V2-14B
  • V2-14C
c. Check AFW flow to S/Gs - c. Go To Step 11.

GREATER THAN 300 GPM

d. Reset SPDS and return to procedure and step in effect
11. Locally Investigate AND Attempt To Restore AFW Flow As Follows:
a. Verify AFW Pump Suction supply is available
b. Position the MDAFW Pump LOCAL/REMOTE Switch to LOCAL
c. Attempt to start a MDAFW Pump as follows:
1) Depress the MDAFW Pump local STOP Pushbutton
2) Depress the MDAFW Pump local START Pushbutton
3) Check MDAFW Pump - STARTED 3) Place the LOCAL/REMOTE Switch to REMOTE.

Rev. 25 FRPH.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK Page 7 of 42 l STEP_H ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I

  • 12. Check AFW Flow To SIGs GREATER IF feed flow to at least one S/C ThAN 300 GPM verified, THEN perform the following:
a. Maintain flow to restore narrow range level to greater than 8% [18%]
b. Ii]Th1 narrow range level is greater than 8% [18%] , THEN reset SPDS AND return to procedure and step in effect.

Go To Step 14.

13. Reset SPDS And Return To Procedure And Step In Effect
14. Stop All RCPs
15. Check Condensate System - IN Place the Condensate System in SERVICE service as follows:
a. the Condensate System is NOT available, THEN Go To Step 30.
b. Open QCV1O426, COND POL SEC BYP.
c. Close V5-3. COND PUMP DISCH.
d. Momentarily place V5-3 to OPEN.
e. Start one Condensate Pump.
f. WHEN feedwater pressure is greater than 300 psig, THEN verify V5-3 full open.
g. Open HCV-1459, LP HEATERS BYP.

at least one Condensate Pump can NOT be started, THEN Go To Step 30.

Rev. 25 FRP-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK Page 8 of 42 H STEP H ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED I

NOTE The subsequent step will defeat FW Isolation signals which is necessary to allow starting of a Main Feedwater Pump. Manual Operator action will be required to initiate a FW Isolation.

16. Place ALL The FEEDWATER ISOLATION Key Switches In The OVRD/RESET Position
  • STMGENA
  • STMGENB
  • STMGENC NOTE Local operation of the FRV and B/P valves below is via reverse acting handwheels.
17. Attempt To Establish Feedwater Flow As Follows:
a. Verify the FW HDR SECTION Valves - CLOSED
  • V2-6A
  • V2-6B
  • V2-6C
b. Start one Main FW Pump b. Go To Step 20.
c. Open the FRV Bypass Valves: c. Locally open the FRV Bypass Valve using the Manual
  • FCV-479 Handwheel. (Requires small
  • FCV-489 Locked Valve Key.)
  • FCV-499
d. Check FW Flow - ESTABLISHED d. Go To Step 20.

Rev. 25 FRP-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK Page 9 of 42

__STEP_H ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED I

18. Check SIG Levels As Follows:
a. Level In At Least One S/C - a. Go To Step 19.

GREATER THAN 8% [18%]

b. Reset SPDS And Return To Procedure And Step In Effect
19. Determine If Feedwater Flow Is Adequate:
a. Check the following: a. Go To Step 20.
  • Core Exit T/C Temperature

- LOWERING OR

  • S/C Wide Range Level -

RISING IN AT LEAST ONE S/C

b. Maintain FW flow to restore S/C Level to greater than 8%

[18%]

c. Reset SPDS And Return To Procedure And Step In Effect

Rev. 25 FRP-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK Page 10 of 42

STEP_H ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED NOTE Supplement K is available for optimizing Auxiliary Spray below.

20. Depressurize The RCS As Follows:
a. Check letdown - IN SERVICE a. IF a PZR PORV is available, THEN Co To Step 20.e.

IF a PZR PORV is NOT available, THEN Go To Step 20.b.

b. Open CVC-3l1, AUX SPRAY
c. WHEN RCS pressure is less than 1950 psig, THEN close CVC-31l
d. Observe the CAUTION prior to step 21 and Go To Step 21
e. Open one PZR PORV to depressurize the RCS to less than 1950 psig.
f. WHEN pressure is less than 1950 psig. close the PORV.

Rev. 25 FRP-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK Page 11 of 42 j__STEP_H ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I

CAUTION Following block of automatic SI initiation, manual SI initiation may be required if conditions degrade.

  • 21 Block SAFETY INJECTION As Follows:
a. Momentarily Place the PZR PRESS/HI STM LINE DP Switch to the BLOCK position
b. Check Tavg - LESS THAN 543°F b. Tavg is less than 543°F, perform Step 21.c.

Observe the CAUTION prior to Step 22 and Go To Step 22.

c. Momentarily Place the T-AVG Switch to the BLOCK position
22. Identify SIG With Lowest Level To Select For Depresssurization
23. Verify Closed MSIVs For Remaining SIGs With Higher Levels

Rev. 25 FRP-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK Page 12 of 42 j__STEP_H ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I

CAUTION The SI Accumulator Discharge Valves must be closed when 5/0 pressure is less than 240 psig to prevent nitrogen injection into the RCS.

24. Depressurize Selected S/C With The Lowest Level To Less Than 600 PSIG By Dumping Steam At Maximum Rate Using One Of The Following Methods Listed In Order Of Preference:
  • Steam Dump to condenser via the pressure control mode OR
  • Steam Line PORVs controlled by Instrument Air OR

Rev. 25 FRP-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK Page 13 of 42 STEP ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED

25. Check Selected SIG Pressure - Isolate SI Accumulators as GREATER THAN 240 PSIG follows:
a. Locally close the breakers for the following valves:
b. Verify CLOSED all ACCUMULATOR DISCHs
  • SI865A
  • SI-865B
1) Verify SI-855, ACC NITROGEN ISO, is closed.
2) Open the appropriate ACCUM VENT Valves:
  • SI-853A
  • SI-853B
  • SI-853C
3) Open HIC-936, ACC VENT HDR FLOW.
26. Maintain Selected S/G pressure -

BETWEEN 240 PSIG AND 600 PSIG

Rev. 25 FRP-H.l RESPONSE TO LOSS OF SECONDARY HEAT SINK Page 14 of 42

__STEP H ACTION/EXPECTED RESPONSE I E RESPONSE NOT OBTAINED

27. Try To Establish Feed Flow From Condensate System As Follows:
a. Check Condensate Pump status a. Start one Condensate Pump as

- AT LEAST ONE RUNNING follows:

1) Open QCV-10426, COND POL SEC BYP.
2) Close V5-3. COND PUMP DISCH.
3) Momentarily place V5-3 control switch to OPEN.
4) Start one Condensate Pump.
5) feedwater pressure is greater than 300 psig.

verify V5-3 goes full open.

6) Open HCV-l459, LP HEATERS BYP.

IF at least one Condensate Pump can be started, Go To Step 30.

b. Open the FRV Bypass Valves b. Locally open the FRV Bypass Valve using the Manual
  • FCV-479 Handwheel. (Requires small
  • FCV-489 Locked Valve Key.)
  • FCV-499
c. Check Condensate flow - c. Go To Step 30.

ESTABLI SHED

28. Check SIC Levels As Follows:
a. Level in at least one S/G - a. Go To Step 29.

GREATER THAN 8% [18%]

b. Reset SPDS And Return To Procedure And Step In Effect

Rev. 25 FRP-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK Page 15 of 42

__STEP_H ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED I

29. Determine If Condensate Flow Is Adequate:
a. Check the following: a. Go To Step 30.
  • Core Exit T/C temperature

- LOWERING OR

  • S/G Wide Range level -

RISING IN AT LEAST ONE S/G

b. Maintain FW flow to restore S/C level to greater than 8%

[18%]

c. Reset SPDS And Return To Procedure And Step In Effect
  • 30. Any Two SIG Wide Range Levels - FW flow is restored during LESS THAN 10% [19%] steps prior to step 31. Go To Step 28.

Go To Step 3.

CAUTION Steps 31 through 35 must be performed quickly in order to establish RCS heat removal by RCS bleed and feed.

31. Depress the INITIATE SAFETY INJECTION Pushbutton

Rev. 25 FRP-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK Page 16 of 42

STEP_H ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED

32. Verify RCS Injection Path As Follows:
a. Verify SI Pumps - AT LEAST a. Go To Step 6.

ONE RUNNING

b. At the RTGB, verify SI Valves b. Perform the following:

for at least one flow path -

ALIGNED FOR COLD LEG INJECTION 1) Locally align valves.

2) Continue efforts to establish feed flow.
3) Cold Leg Injection can NOT be verified, THEN Go To Step 6.
33. Establish Instrument Air To CV As Follows:
a. Verify APP-002-F7, INSTR AIR a. Start Instrument Air HDR LO PRESS - EXTINGUISHED Compressors as required to extinguish APP-002-F7.

IF instrument air header pressure can Q] be established, THEN Go To Step 34.

b. Place IA PCV-l7l6, INSTRUMENT AIR ISO TO CV Control Switch to the OVERRIDE position
34. Establish RCS Bleed Path As Follows:
a. Verify power to PZR PORV Block Valves - AVAILABLE
b. Place all PZR Heater Control Switches to the OFF position
c. Verify PZR PORV Block Valves

- BOTH OPEN

d. Open both PZR PORVs

Rev. 25 FRP-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK Page 17 of 42

__STEP_H ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED

35. Verify Adequate RCS Bleed Path Go To Step 37.

As Follows:

  • PZR PORV Block Valves - BOTH OPEN
36. Go To Step 41
37. Place the Key Switches for the following Vent Valves to the OPEN Position:
  • RC-568. HEAD VENT
  • RC-570, PZR VENT
  • RC-572, CV ATNOS
  • RC-567, HEAD VENT
  • RC-569, PZR VENT
38. Depressurize At Least One Intact SIG To Atmospheric Pressure Using Steam Line PORVs

Rev. 25 FRP-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK Page 18 of 42

STEP_H ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I

39. Isolate SI Accumulators As Follows:
a. Locally close the breakers for the following valves:
b. Verify CLOSED all ACCUMULATOR b. Vent any unisolated DISCHs accumulator as follows:
  • SI-865A 1) Verify SI855, ACC
  • SI-865C
2) Open the appropriate ACCUM VENT Valves:
  • SI-853A
  • SI-853B
  • SI-853C
3) Open HIC-936, ACC VENT HDR FLOW.
40. Align Fire Water To The Depressurized SIG Using Attachment 1, While Continuing With This Procedure
41. Verify Auto Start Of All SI Equipment Using Supplement L, While Continuing With This P roe edure

Rev. 25 FRP-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK Page 19 of 42 l__STEP_H ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED CAUTION The RCS bleed path must be maintained even if RCS pressure remains greater than SI Pump shutoff head.

42. Maintain RCS Heat Removal As Follows:
  • Maintain Safety Injection flow
  • Maintain PZR PORVs - BOTH OPEN NOTE The Safeguards System requires 2 mm between SI initiation and reset.
43. Perform The Following:
a. Reset SAFETY INJECTION
b. Momentarily place the CONTAINMENT SPRAY Key Switch to the OVRD/RESET position AND return to the NORMAL position
44. Reset The Following Containment Isolations:
a. PHASE A
b. PHASE B

Rev. 25 FRP-H.l RESPONSE TO LOSS OF SECONDARY HEAT SINK Page 20 of 42 j STEP_H ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED

45. Establish Instrument Air To CV As Follows:
a. Check Status of PCV-1716, a. IF APP-002-F7, INSTR AIR HDR INSTRUMENT AIR ISO TO CV - IN LO PRESS is illuminated, THEN OVERRIDE POSITION Start Instrument Air Compressors as required to extinguish APP-0O2-F7 AND Go To Step 45.b.

IF instrument air header pressure can NQ1 be established, THEN observe the NOTE prior to Step 46 and Go To Step 46.

b. Momentarily place IA PCVl7l6, INSTRUMENT AIR ISO TO CV Switch, to RESET AND return to AUTO NOTE Supplement F, EDG Capability Load List, provides a listing of power requirements of loads that will be started.
46. Check Charging Pump Power Supply As Follows:
a. Check E-1 OR E-2 - ENERGIZED a. Go To Step 47.

BY EDG

b. Check EDG capacity - b. Perform the following:

AVAILABLE FOR EACH CHARGING PUMP TO BE STARTED 1) Determine Supplement F loads to shed in order to achieve EDG capacity.

2) Shed loads.

LICENSE EXAMINATION JOB PERFORMANCE MEASURE ILC-13 NRC JPM D Rev. 0 REACTOR TRIP RESPONSE EXCESSIVE RCS -

COOLDOWN Concurred By: Kirk Schauer Date: 5/15/13 Operations Approved By: James Conder Date: 6/5/13 Superintendent/Supervisor Training

ILC-13 NRC JPM D Page 2 of 19 LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task:

01118102605, Perform Actions for Post Reactor Trip Stabilization without SI Actuation JAW EOP-ES-0. 1 Alternate Path:

YES JPM#: Candidate ILC-13 NRC JPM D RO/SRO K/A Rating (ROISRO):

039 A1.05 3.2/3.3 Task Standard:

MSIVs are shut to stop the RCS cooldown AND RCS temperature controlled via S/G PORVs.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate

References:

EOP-ES-0. 1 Validation Time: 15 Minutes. Time Critical: No Time Critical Time: N/A Candidate: (N/A if not time critical)

Name Overall Critical Time Time SSN Start: Start:

Finish: Finish:

Performance Rating: Performance SAT UNSAT circle one Time (mm):

Examiner:

Print Name Signature Date COMMENTS:

ILC-13 NRC JPM D Page 3 of 19 QUESTION DOCUMENTATION:

Question:

Response

ILC-13 NRC JPM D Page 4 of 19 COMMENTS Step 6 is critical because closing the MSIVs and MSIV bypass valves ends the overcooling Step 8 is critical because the RCS temperature must be controlled by operating the S/G PORVs Step 21 is critical because RCS will be stabilized using the S/G PORVs prior to lifting a S/G Safety Valve.

ILC-13 NRC JPM D Page 5 of 19 SIMULATOR OPERATOR INSTRUCTIONS:

1. ResettolC-910
2. Place Simulator in Run, acknowledge alarms, and then place in FREEZE.
3. Open SCN 009_ILC_13CR NRC_JPMJJ and follow instructions

ILC-13 NRC JPM D Page 6 of 19 Tools/Equipment/Procedures Needed:

Marked up EOP-E-O EOP-ES-0. 1 DIRECTIONS TO CANDIDATE:

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 facilitate the examination and better enable me to assess your level of understanding, verbalize your actions and observations while performing the JPM. To indicate that you have completed your assigned task return the Candidate Cue Sheet I provided you.

CANDIDATE INFORMATION:

  • Inform the candidate there are NO time critical steps in this JPM.
  • Provide with a marked up copy of EOP-E-0 (Steps 1-4 marked)

INITIAL CONDITIONS:

1. The plant was initially at 100% power.
2. A manual reactor trip was initiated due to loss of both feed pumps.
3. EOP-E-0 complete through step 4 RNO
4. YouaretheBOP.

INITIATING CUE:

The CRS has directed you to stabilize the plant by performing EOP-ES-0. 1 steps 1 through 11.

ILC-13 NRC JPM D Page 7 of 19 START TIME:

CAUTION f SI actuation occurs during this procedure, EOP-E-0, REACTOR TRIP OR SAFETY INJECTION, should be performed.

STEP 1: NOTE: FOLDOUT for EOP-ES-0.l is in effect (EOP-ES-0. 1 NOTE prior to step 1)

SAT

1. SI ACTUATION CRITERIA IF either condition listed below occurs, THEN manually actuate BOTH trains of SI AND Go To EOP-E-O, REACTOR TRIP OR SAFETY INJECTION, Step 1:
  • RCS subcooling based on core exit TCs LESS THAN 35°F UNSAT OR
  • PZR level CANNOT BE MAINTAINED GREATER THAN 7%
2. LOSS OF POWER CRITERIA IF power is lost, THEN perform the following:
a. IF NO charging pumps are running, THEN isolate letdown.
b. Locally reset and load instrument air compressor(s) as necessary:
  • Compressor A (MCC-5 CMPT 7M)
  • Compressor B (MCC-6 CMPT 3G)
c. Restore affected controls to automatic as necessary.

. AFW SUPPLY SWITCHOVER CRITERIA IF CST level lowers to less than 10%, THEN switch to backup water supply using OP-402, Auxiliary Feedwater System.

4. DC BUS, INSTRUMENT BUS, OR MCC-5 FAILURE CRITERIA IF DC bus A, DC bus B, any instrument bus, or MCC-5 is deenergized, THEN perform Attachment 7, DC Bus Or Instrument Bus Failure.
5. LOSS OF ULTIMATE HEAT SINK CRITERIA IF attack on RNP Site is in progress AND either condition listed below occurs, THEN Go To EPP-28, LOSS OF ULTIMATE HEAT SINK, Step 1:
  • Loss Of Lake Robinson Dam integrity STANDARD: Candidate determines that NONE of the EOP-ES-0.1 FOLDOUT CRITERIA are applicable.

BOOTH OPERATOR CUE: Place Simulator in RUN at Examiners CUE COMMENTS:

ILC-13 NRC JPM D Page 8 of 19 STEP 2: Check RCS Temperatures: (Continuous Action Step)

  • With any RCP running, RCS average temperature STABLE AT OR TRENDING TO 547°F SAT (EOP-ES-O.1 Step 1)

STANDARD: Candidate checks RCS temperature on any of the following: ERFIS computer, ICCM, TR-408, or RTGB loop Tavg indication and determines UNSAT that RCS average temperature is NOT stable or trending to 547°F and goes to Step 1 RNO EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: Place Simulator in RUN at Examiners CUE COMMENTS:

STEP 3: IF temperature is less than 547°F AND lowering, THEN perform the following:

a. Stop dumping steam. SAT (Step l.a RNO)

STANDARD: Candidate determines Condenser Steam dumps and Steam Line PORVs are closed by the GREEN closed indication illuminated on RTGB UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM D Page 9 of 19 STEP 4: Verify SIG blowdown isolation valves are closed:

  • FCV-1930A&B
  • FCV-1931A&B
  • FCV-1932A&B SAT (Step 1 .b RNO)

STANDARD: Candidate determines S/G Blowdown Isolations are Closed by observing the valve positions on the SPTOP ERFIS screen. UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: If AO is called to investigate the steam leak, report back that a leak is on the main steam header. Wait 5 minutes after request to make report.

COMMENTS:

STEP 5: IF cooldown continues, THEN reduce total feed flow to minimum for decay heat removal:

  • Maintain total feed flow greater than 300 gpm (0.2x106 pph) until narrow range level is greater than 8% in at least one S/G. SAT (Step 1 .c RNO)

STANDARD: Candidate lowers or isolates AFW flow to Steam Generators. Maintains minimum required flow (> 300 gpm) until one S/G level is greater than 8 UNSAT percent.

EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM D Page 10 of 19 STEP 6: IF cooldown continues, THEN close MSIV and bypass valves. CRITICAL (Step 1 .d RNO) STEP STANDARD: Candidate locates control switches for MSIVs and takes them to CLOSE and verifies closed by observing the GREEN closed indication.

SAT EXAMINERS NOTE: Candidate may have taken a prompt and prudent action to close the MSIVs when to told to Stop Dumping Steam in Step 1.aRNO.

UNSAT BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 7: IF temperature lowers to less than 530°F, THEN borate RCS to cold shutdown boron concentration while continuing with this procedure.

(Step i.e RNO)

SAT STANDARD: Candidate determines RCS temperature is greater than 530°F and maintains RCS temperature greater than 530°F.

UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM D Page 11 of 19 STEP 8: IF temperature is greater than 547°F AND rising, THEN perform the CRITICAL following: (Continuous Action Step) STEP

  • Dump steam to condenser:
a. Place steam dump mode switch in Steam Pressure mode.
b. Adjust steam pressure controller as necessary.

OR

  • Dump steam using S/G steam line PORVs. SAT (Step i.e RNO)

STANDARD: Candidate recognizes that steam dump to condenser is NOT available and manually controls the Steam Line PORV controllers to control RCS UNSAT temperature such that an S/G Safety Valve does not lift. Temperature must be maintained above 53 0°F (or borate to cold shutdown iaw RNO step 1 .e) and below the RCS temperature that correlates to the lowest S/G Safety Valve Lift Setpoint.

EXAMINERS NOTE: Temperature will initially be less than 547°F but will rise until S/G PORVs are manually adjusted to control RCS Temperature. This is a Continuous Action Step.

The SIG PORV setpoints have been mis-calibrated and will not open automatically below the S/G Safety Valve Lift Setpoint.

BOOTH OPERATOR CUE: NONE COMMENTS: Candidate will recognize the need to establish higher AFW flows to allow for controlling RCS Temperatures

ILC-13 NRC JPM D Page 12 of 19 STEP 9: Check Feedwater Status

a. RCS average temperatures LESS THAN 554°F (Step 2.a)

SAT STANDARD: Candidate recognizes RCS average temperature is less than 554°F EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 10: Check Feedwater Status

b. Main feedwater reg valves CLOSED
c. Total feed flow to S/Gs GREATER THAN 300 GPM (0.2x1 06 PPH)

(Steps 2.b & c) SAT STANDARD: Candidate recognizes feedwater reg valves are closed and the feedwater flow is >300gpm UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM D Page 13 of 19 STEP 11: Check SIG Levels: (Continuous Action Step)

a. Narrow range levels GREATER Than 8%

RNO Maintain total feed flow THAN 8% greater than 300 gpm (0.2x106 pph) until narrow range level is greater than 8% in at least one SAT S/G.

(Step 3.aRNO)

STANDARD: Candidate recognizes need to adjust AFW flow to raise S/G levels and UNSAT control between 8% and 50%

EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 12: Check SIG Levels:

b. Control feed flow to maintain narrow range levels Between 8% and 50%.

(Step 3 .b) SAT STANDARD: Candidate recognizes need to adjust AFW flow to raise S/G levels and control between 8% and 50% UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM D Page 14 of 19 STEP 13: Check All AC Busses Energized by Offsite Power (Continuous Action Step)

(Step 4)

SAT STANDARD: Candidate determines that ALL AC Busses are energized by Offsite Power by observing that the Startup Transformer is energized and Breakers 52/12 and 52/17 are closed. Also, both A and B EDGs are secured.

UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 14: Check PZR Level Control

a. PZR Level Greater Than 14%
b. Charging In Service
c. Letdown In Service SAT
d. PZR Level Trending to 22%

(Step 5.a-d)

STANDARD: Candidate determines that PZR Level is greater than 14%, Charging and UNSAT Letdown is In Service and PZR Level is Trending to 22%.

EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM D Page 15 of 19 STEP 15: Check ALL Control Rods Fully Inserted (Step 6)

STANDARD: Candidate determines that all rods are fully inserted by observing the Rod SAT Position Indications at zero and all Rod Bottom Lights are Illuminated.

EXAMINERS NOTE: NONE UNSAT BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 16: Check PZR Pressure Control:

a. Pressure Greater Than 1715 psig
b. Pressure Stable at or Trending to 2235 psig (Step 7) SAT STANDARD: Candidate determines PZR Pressure is greater than 1715 psig and is stable at or trending to 2235 psig by observing RTGB pressure indications.

UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM D Page 16 of 19 STEP 17: Transfer Condenser Steam Dump to Pressure Control Mode:

a. Check Condenser Available (Step 8.a)

SAT STANDARD: Candidate determines that the condenser is NOT available due to the MSIVs being closed in an earlier step.

UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 18: Transfer Condenser Steam Dump to Pressure Control Mode:

Step 8.a RNO: IF condenser steam dumps are NOT available, THEN set S/G steam line PORV controllers to maintain existing S/G pressure. SAT STANDARI): Candidate adjusts the S/G steam line PORV controllers such that they just begin to open at the current RCS temperature / S/G pressure. UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM D Page 17 of 19 NOTE RCPs should be run in order of priority to provide normal PZR spray. (C, B+A, B)

STEP 19: Check RCP C- Running (Step 9)

SAT STANDARD: Candidate determines that RCP C is Running by observing the RED light is illuminated on the RTGB.

UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 20: Check If Source Range Detectors Should be Energized:

a. Intermediate Range flux Less than 1OE-10 AMPS
b. Source Range Detectors Energized SAT
c. Monitor Highest Source Range Channel (Step 10)

UNSAT STANDARD: Candidate determines that IR Flux is less than bE-b AMPS and that SR Detectors are energized by observing indication at the NI Cabinets and NR 45 on the RTGB. Observes that both Source Range Channels are displayed on NR-45.

EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC 3PM D Page 18 of 19 STEP 21: Maintain Stable Plant Conditions: CRITICAL

a. PZR Pressure At 2235 psig STEP
b. PZR Level At 22%
c. S/G Narrow Range Levels Between 8% and 50%
d. RCS temperature: SAT

. With any RCP running, RCS average temperature Stable at or Trending to 547°F

e. Check DC busses A and B Energized.

UNSAT (Step 11)

STANDARD: Candidate determines that PZR Pressure is at 2235 psig, PZR Level is at 22%, S/G Narrow Range Levels are between 8% and 50% and DC Busses A and B are energized.

Candidate will adjust the S/G PORV controllers to lower RCS temperature and stabilize RCS temperature to between 542°F and 552°F without lifting an S/G Safety Valve. (Critical Step)

EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

END OF TASK Terminating Cue: When Candidate has taken manual action(s) to stabilize RCS Average temperature between 542°F and 552°F using the SIG PORVs without lifting an SIG Safety Valve.

TIME STOP:

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

CANDIDATE INFORMATION:

  • Inform the candidate there are NO time critical steps in this JPM.
  • Provide with a marked up copy of EOP-E-0 (Steps 1-4 marked)

INITIAL CONDITIONS:

5. The plant was initially at 100% power.
6. A manual reactor trip was initiated due to loss of both feed pumps.
7. EOP-E-0 complete through step 4 RNO
8. You are the BOP.

INITIATING CUE:

The CRS has directed you to stabilize the plant by performing EOP-ES-0. 1 steps 1 through 11.

CONTINUOUS USE H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 PLANT OPERATING MANUAL VOLUME 3 PART 4 EMERGENCY OPERATING PROCEDURE EOPES-O.1 REACTOR TRIP RESPONSE REVISION 4 Page 1 of 37

Rev. 4 EOP-ES-O.1 REACTOR TRIP RESPONSE Page 2 of 37 Purpose and Entry Conditions (Page 1 of 1)

1. PURPOSE This procedure provides instructions to stabilize and control the plant following a reactor trip without a safety injection.
2. ENTRY CONDITIONS This procedure is entered from EOP-E-O. REACTOR TRIP OR SAFETY INJECTION, Step 4. when SI is neither actuated nor required.

- END -

Rev. 4 EOP-ES-O.1 REACTOR TRIP RESPONSE Page 3 of 37

-J-t ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED CAUTION If SI actuation occurs during this procedure, EOP-E-O, REACTOR TRIP OR SAFETY INJECTION, should be performed.

NOTE FOLDOUT for EOP-ES-0.1 is in effect.

  • 1. Check RCS Temperatures: JY temperature is less than 547°F AND lowering, THEN perform
  • With any RCP running, the following:

RCS average temperature -

STABLE AT OR TRENDING TO a. Stop dumping steam.

547°F

b. Verify S/G blowdown isolation OR valves are closed:
  • With NO RCP running,
  • FCV-193O A & B RCS cold leg temperatures -
  • FCV-1931 A & B STABLE AT OR TRENDING TO
  • FCV-1932 A & B 547° F
c. IF cooldown continues, THEN reduce total feed flow to minimum for decay heat removal:
  • Maintain total feed flow greater than 300 gpm 6 pph)

(O.2xlO until narrow range level is greater than 8% in at least one S/G.

d. IF cooldown continues, THEN close MSIV and bypass valves.
e. L temperature lowers to less than 530°F. THEN borate RCS to cold shutdown boron concentration while continuing with this procedure.

(CONTINUED NEXT PAGE)

Rev. 4 EOP-ES-O.1 REACTOR TRIP RESPONSE Page 4 of 37 H STEP_H ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED

1. (CONTINUED) j temperature is greater than 547°F rising. ThEN perform the following:

Dump steam to condenser:

a. Place steam dump mode switch in Steam Pressure mode.
b. Adjust steam pressure controller as necessary.

OR Dump steam using S/C steam line PORVs.

2. Check Feedwater Status
a. RCS average temperatures - a. WHEN temperature is less LESS THAN 554°F than 554°F, JJIEN do Steps 2.b through 2.c.

Continue With Step 3.

b. Main feedwater reg valves - b. Manually close valve(s).

CLO S ED J any valve(s) can be closed, THEN manually close associated feedwater header section valve(s).

c. Total feed flow to S/Cs - c. Establish feed flow to S/Gs GREATER THAN 300 GPM as necessary:

6 PPH)

(O.2x10

Rev. 4 EOPES-O.1 REACTOR TRIP RESPONSE Page 5 of 37 STEP H ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1

3. Check S/C Levels:
a. Narrow range levels - GREATER a. Maintain total feed flow THAN 8% greater than 300 gpm 6 pph) until narrow (O.2x10 range level is greater than 8% in at least one SIG.
b. Control feed flow to maintain b. narrow range level in any narrow range levels - BETWEEN S/G continues to rise, THEN 8% AND 50% stop feed flow to that S/C.

Rev. 4 EOP-ES-O.l REACTOR TRIP RESPONSE Page 6 of 37 H STEP H ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

4. Check All AC Busses - ENERGIZED Perform the following:

BY OFESITE POWER

a. any AC emergency buss(es) are NOT energized by offsite power, IHEN perform the following:
1) Verify EDG(s) running.
2) Verify EDG(s) have assumed the following loads:
3) Perform Attachment 2, EDO Support Verification, while continuing with this procedure.
b. Try to restore offsite power to AC busses. using the following resources as necessary, while continuing with this procedure:
  • Load Dispatcher
  • IC Turbines and Unit One
  • Backfeed using auxiliary transformer
  • OP-6O3. Electrical Distribution
c. L any AC emergency bus is N2 energized, ThEN try to restore power to affected bus from EDO.

(CONTINUED NEXT PAGE)

Rev. 4 EOP-ES-0.1 REACTOR TRIP RESPONSE Page 7 of 37 H STEP H ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I

4. (CONTINUED)
d. Locally load the following equipment on AC emergency buss(es) as necessary:
  • 150 KW of PZR heaters using EPP21, ENERGIZING PRESSURIZER HEATERS FROM EMERGENCY BUSSES
  • Instrument air compressor(s) after reset:
  • Compressor A (MCC-5 CMPT 7M)
  • Compressor B (MCC-6 CMPT 3G)
  • Battery chargers (within 30 minutes of power loss) using OP-601, DC Supply System.
e. Periodically check status of spent fuel pool until SEP cooling is restored:
  • Fuel pool level
  • Fuel pool temperature
f. IE DS bus is IIQ energized, THEN place DSDG in service within one hour of the power loss, as time and manpower permit. using EPP-25.

ENERGIZING SUPPLEMENTAL PLANT EQUIPMENT USING THE DSDG:

  • IE EPP-21 is NQ in effect to load PZR heaters. THEN restore power to PZR heaters using EPP-25, ENERGIZING SUPPLEMENTAL PLANT EQUIPMENT USING THE DSDG.
g. Verify emergency oil pump is running.

(CONTINUED NEXT PAGE)

Rev. 4 EOP-ESO.l REACTOR TRIP RESPONSE Page 8 of 37

STEP H ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED I

4. (CONTINUED)
h. Locally verify air side seal oil backup pump is running.

Rev. 4 EOP-ESO.l REACTOR TRIP RESPONSE Page 9 of 37

STEP H ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED I

5. Check PZR Level Control:
a. PZR Level GREATER THAN 14% a. Perform the following:
1) Verify letdown is isolated:
  • Letdown line isolation valves closed:
  • CVC-204A
  • CVC-204B
  • Letdown orifice valves closed:
  • CVC-200A
  • CVC-200B
  • CVC-200C
  • Excess letdown stop valve closed:
  • CVC-387
2) Verify all PZR heaters are off.
3) WHEN charging is available, THEN control charging to restore PZR level to greater than 14%.
4) WHEN PZR level is greater than 14% 4N] power is available, IHN reenergize PZR heaters as necessary.

(CONTINUED NEXT PAGE)

Rev. 4 EOP-ES-O.1 REACTOR TRIP RESPONSE Page 10 of 37

STEP_H ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED

5. (CONTINUED)
b. Charging - IN SERVICE b. Place charging in service:
1) Start at least one charging pump.
2) Adjust charging pump speed controllers as necessary to establish desired charging flow.
3) Adjust HIC-12l, charging flow control valve, as necessary to maintain seal injection flow between 8 gpm and 13 gpm per RCP.
4) WHEN VCT automatic makeup is available. THEN verify makeup is set for automatic control:

a) RCS makeup mode switch in auto.

b) RCS makeup system switch in start.

c. Letdown - IN SERVICE c. WHEN PZR level is greater than 14%, III1 place letdown in service using Attachment 4, Establishing Letdown.

IF letdown can NOT be established, THEN establish excess letdown using Attachment 5. Establishing Excess Letdown.

d. PZR Level - TRENDING TO 22% d. Control charging and letdown to maintain PZR level at 22%.

Rev. 4 EOP-ES-0.l REACTOR TRIP RESPONSE Page 11 of 37 STEP H ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

6. Check All Control Rods - FULLY IF two or more control rods are INSERTED NQ fully inserted. THEN emergency borate to cold shutdown boron concentration:

Use BAST:

a. Open boric acid to charging pump suction, MOV -350.
b. Start boric acid pump aligned for blend.
c. Verify boric acid flow on Fl-lb.
d. Verify total charging flow is greater than boric acid flow.

OR Use RWST:

a. Open emergency makeup to charging suction, LCV-115B.

IF LCV-bl5B can NOT be opened. IIN locally open CVC-358. RWST to charging pump suction.

b. Close VCT outlet, LCV-115C.

Rev. 4 EOP-ES-O1 REACTOR TRIP RESPONSE Page 12 of 37

STEP H ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED I

7. Check PZR Pressure Control:
a. Pressure - GREATER THAN a. Perform the following:

1715 PSIG

1) Check for SI actuation.

IF SI is NOT actuated.

THEN manually actuate BOTH trains of SI.

2) Go To EOP-E-O, REACTOR TRIP OR SAFETY INJECTION, Step 1.
b. Pressure - STABLE AT OR b. IE pressure is less than TRENDING TO 2235 PSIG 2235 psig AIIL lowering, Th1N perform the following:
1) Verify PZR PORVs are closed.

J any valve can .+/-QI be closed, THEN manually close its block valve.

2) Verify PZR spray valves are closed.

IF valve(s) can NOT be closed, THEN stop RCP(s) as necessary to stop spray flow:

  • IF PCV-455A can NOT be closed, THEN stop RCP B and RCP C.

OR

  • IF PCV-455B can NOT be closed, THEN stop RCP C.
3) WHEN power is available, THEN verify PZR heaters are on.

(CONTINUED NEXT PAGE)

Rev. 4 EOP-ES-O.1 REACTOR TRIP RESPONSE Page 13 of 37

STEP H ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

7. (CONTINUED)

IE pressure is greater than 2235 psig MIL rising, THEN perform the following:

1) Verify PZR heaters are off.
2) Control pressure using normal PZR spray:
  • PCV-455A, loop B
  • PCV-455B, loop C LE normal PZR spray is NQI available AND letdown is in service, THEN use aux spray:
  • Refer to Attachment 6, Establishing Aux Spray Without SI, as necessary.

IE auxiliary spray is available or effective, THEN use PZR PORV(s).

8. Transfer Condenser Steam Dump To IE condenser steam dumps are Qf Pressure Control Mode: available, THEN set S/C steam line PORV controllers to
a. Check condenser - AVAILABLE maintain existing S/C pressure.
b. Place steam dump mode switch in Steam Pressure mode
c. Set steam pressure controller to maintain existing S/C pressure

Rev. 4 EOP-ES--O.1 REACTOR TRIP RESPONSE Page 14 of 37 STEP H ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE RCPs should be run in order of priority to provide normal PZR spray.

(C, B+A, B)

9. Check RCP C - RUNNING Try to start RCP(s) to provide normal PZR spray:
a. Li offsite power is available, THEN establish conditions for starting RCP(s) using OP-lOl, Reactor Coolant System And Reactor Coolant Pump Startup And Operation.
b. IF conditions are established for RCP C, THEN start RCP C.

IF RCP C can NOT be started AND conditions are established for other RCP(s)

THEN try to start other RCP(s) as necessary to provide normal PZR spray (or forced flow).

IF NO RCP can be started, THEN verify natural circulation using Attachment 1. Natural Circulation Verification.

IF natural circulation can NOT be verified, ]+/-IM dump more steam.

Rev. 4 EOP-ES-O.1 REACTOR TRIP RESPONSE Page 15 of 37

STEP H ACTION/EXPECTED RESPONSE

-J RESPONSE NOT OBTAINED

10. Check If Source Range Detectors Should Be Energized:
a. Intermediate Range flux - a. WHEN flux is less than LESS THAN 10-10 AMPS 10-10 amps, THEN do Steps l0.b and 10.c.

Continue With Step 11.

b. Source Range Detectors - b. Energize Source Range ENERGIZED Detectors by depressing both PERMISSIVE P-6 DEFEAT Pushbuttons.
c. Monitor Highest Source Range Channel

Rev. 4 EOP-ESO.l REACTOR TRIP RESPONSE Page 16 of 37 H STEP_H ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

11. Maintain Stable Plant Conditions:
a. PZR pressure - AT 2235 PSIG
b. PZR level - AT 22%
c. S/G narrow range levels -

BETWEEN 8% AND 50%

d. RCS temperature:
  • With any RCP running, RCS average temperature STABLE AT OR TRENDING TO 5470 OR
  • With NO RCP running, RCS cold leg temperatures - STABLE AT OR TRENDING TO 547°F
e. Check DC busses A and B - e. Perform the following:

ENERGI ZED

  • IfDCbusAisNOT energized, THEN perform EPP-26, LOSS OF DC BUS A, while continuing with this procedure.
  • IfDCbusBisNOT energized. II+/-N perform EPP-27, LOSS OF DC BUS B, while continuing with this procedure.
12. Perform Attachment 8, Aligning Balance Of Plant, As Time Permits While Continuing With This Procedure

Rev. 4 EOP-ESO.1 REACTOR TRIP RESPONSE Page 17 of 37

] STEP_H ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED

13. Determine If Natural Circulation Cooldowri Is Required:
a. Check both the following: a. Go To appropriate plant procedure:
  • GP-OO4, Post Trip
  • Plant cooldown - REQUIRED Stabilization OR
  • As determined by Shift Manager
b. Go To EPP-5, NATURAL CIRCULATION COOLDOWN, Step 1

- END -

Rev. 4 EOP-ES-O.1 REACTOR TRIP RESPONSE Page 18 of 37 Attachment 1 Natural Circulation Verification (Page 1 of 1)

1. The Following Conditions Support Or Indicate Natural Circulation Flow:
  • RCS subcooling based on core exit TCs GREATER THAN 35°F
  • SIG pressures - STABLE OR LOWERING
  • RCS hot leg temperatures - STABLE OR LOWERING
  • Core exit TCs - STABLE OR LOWERING
  • RCS cold leg temperatures - AT SATURATION TEMPERATURE FOR S/C PRESSURE

- END -

Rev. 4 EOP-ES-O.1 REACTOR TRIP RESPONSE Page 19 of 37 j STEP H ACTION/EXPECTED RESPONSE HI Attachment 2 RESPONSE NOT OBTAINED EDO Support Verification (Page 1 of 5)

CAUTION If only one SW Pump is running, it is subject to runout until the following step is completed.

1. Check SW Header Pressure And Transition To Applicable Step From Table Below:

SW PRESSURE CONDITION STEP LESS THAN 40 PSIG 2 GREATER THAN 50 PSIG 3 BETWEEN 40 PSIG AND 50 PSIG 4

Rev. 4 EOP-ESO.l REACTOR TRIP RESPONSE Page 20 of 37 H STEP_H ACTION/EXPECTED RESPONSE Attachment 2 RESPONSE NOT OBTAINED EDG Support Verification (Page 2 of 5)

NOTE Supplement 0, Local Manual Isolation of Turbine Building Service Water, is available for use.

2. Raise SW Pressure:
a. Start additional SW pumps as a. IE all available SW pumps are necessary to obtain at least running ANO at least 40 psig 40 psig SW header pressure can NQI be obtained, THEN isolate SW to the Turbine Building by closing:
  • V6-16C, SWTURB BLDG ISO OR
  • V6-16A AND V6-16B, SW TURB BLDG SUPPLY Perform Supplement M, Component Alignment For Loss Of SW To Turbine Building, while continuing with this procedure.
b. Check SW header pressure - b. Go To Step 4.

GREATER THAN 50 PSIG

Rev. 4 EOP-ES-0.1 REACTOR TRIP RESPONSE Page 21 of 37

-tj-t ACTION/EXPECTED RESPONSE Attachment 2 RESPONSE NOT OBTAINED EDG Support Verification (Page 3 of 5)

3. Reduce SW Pressure:
a. Check number of SW pumps a. WHEN personnel are available, running - GREATER THAN 2 THEN locally perform Attachment 3, Throttling CCW Heat Exchanger SW Valves, while continuing with this procedure.

Go To Step 4.

b. Stop 1 SW pump
c. Check SW header pressure - c. Go To Step 3.e.

GREATER THAN 50 PSIG

d. Return To Step 3.a
e. Check SW header pressure - e. WHEN personnel are available.

GREATER THAN 40 PSIG THEN locally perform Attachment 3, Throttling CCW Heat Exchanger SW Valves, while continuing with this procedure.

Go To Step 4.

4. Check The Following EDG Cooling Perform the following:

Annunciators - EXTINGUISHED

a. Locally determine if a high
  • APP-O1O--E2, temperature condition exists.

EDG A LUBE OIL HI/LO TEMP b. j a high temperature

  • APP-O1O-E3, condition exists, THEN EDG B LUBE OIL locally shutdown affected EDG HI/LO TEMP by pressing EMERGENCY STOP
  • APP-O1O-F2, button.

EDG A COOL WTR HI/LO TEMP

  • APP-O1O-F3, EDG B COOL WTR HI/LO TEMP

Rev. 4 EOP-ES-O.1 REACTOR TRIP RESPONSE Page 22 of 37

-J-t ACTION/EXPECTED RESPONSE I I Attachment 2 RESPONSE NOT OBTAINED EDG Support Verification (Page 4 of 5)

5. Check EDG Fuel Oil Supplies:
a. Check EMERG DG FUEL OIL PUMP a. Perform the following:

for the running EDG(s) -

RUNNING 1) either fuel oil pump has tripped, THEN locally inspect the pump and wiring for damage.

2) IE required, THEN initiate emergency repairs to prevent loss of fuel to the EDG(s).
b. Check loss of AC power - DUE b. Go To Step 6.

TO HIGH WIND

c. Dispatch an operator to inspect the EDG FOST and Transfer Pumps for damage
6. Determine If A SW Booster Pump Should Be Started:
a. Check SW booster pumps - ALL a. Go To Step 7.

STOPPED

b. Check power available to b. WHEN power is available, THEN start a SW booster pump do Step 6.c.

Go To Step 7.

c. Start one SW Booster Pump
7. Implement Supplement S.

Emergency Diesel Generator Monitoring. While Continuing With This Procedure

Rev. 4 EOP-ESO.l REACTOR TRIP RESPONSE Page 23 of 37 j STEP H ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I

Attachment 2 EDG Support Verification (Page 5 of 5)

8. Notify The CRS Of EDG Support Status.

- END -

Rev. 4 EOP-ES-O.1 REACTOR TRIP RESPONSE Page 24 of 37 Attachment 3 Throttling CCW Heat Exchanger SW Valves (Page 1 of 2)

NOTE Throttling of SW-739, CCW HEAT EXCHANGER A RETURN, and SW-740. CCW HEAT EXCHANGER B RETURN, shall be limited to position 1 (POS 1) with 2 CCW heat exchangers in service, and position 2 (POS 2) with one heat exchanger in service. This is to prevent exceeding the capability of 2 pumps during a 2 SW pump accident response. These valve positions will permit approximately 5000 gpm flow with 2 heat exchangers in operation (POS 1) and 10,000 gpm flow with 1 heat exchanger in operation (POS 2)

1. Go To Appropriate Step For Heat Exchangers In Service:
a. LE both CCW heat exchangers are in service, THEN Go To Step 2.
b. IE only A CCW heat exchanger is in service, THEN Go To Step 3.
c. IE only B CCW heat exchanger is in service, THEN Go To Step 4.
2. Perform The Following To Restore SW Header Pressure To Between 40 PSIG And 50 PSIG:
a. Throttle both of the following valves in 1/2 turn increments to establish SW pressure between 40 psig and 50 psig as indicated by P1- 1619A:
  • SW-739, CCW HEAT EXCHANGER A RETURN
  • SW-740, CCW HEAT EXCHANGER B RETURN
b. Go To Step 5.
3. Perform The Following To Restore SW Header Pressure To Between 40 PSIG And 50 PSIG:
a. Throttle SW-739, CCW HEAT EXCHANGER A RETURN, to establish SW pressure between 40 psig and 50 psig as indicated by PI-1619A.
b. Go To Step 5.

Rev. 4 EOP-ES-O.l REACTOR TRIP RESPONSE Page 25 of 37 Attachment 3 Throttling CCW Heat Exchanger SW Valves (Page 2 of 2)

4. Perform The Following To Restore SW Header Pressure To Between 40 PSIG And 50 PSIG:
a. Throttle SW-74O, CCW HEAT EXCHANGER B RETURN, to establish SW pressure between 40 psig and 50 psig as indicated by P1-161gB.
5. Notify The CRS That SW Pressure Has Been Restored To Between 40 PSIG And 50 PSIG.

- END -

Rev. 4 EOP-ES--O.1 REACTOR TRIP RESPONSE Page 26 of 37 Attachment 4 Establishing Letdown (Page 1 of 1)

1. Establish Letdown:
a. Close Letdown Orifice Valves:
  • CVC-200A
  • CVC-200B
  • CVC-200C
b. Open Letdown Line Isolation Valves:
  • CVC-2O4A
  • CVC-204B
c. Open Letdown Line Stop Valves and return to AUTO:
  • LCV-460A
  • LCV-460B
d. Place TC-144, Non-regen Heat Exchanger Outlet Temperature Controller, in AUTO
e. Maintain adequate charging flow to Regen Heat Exchanger:
  • Start additional Charging Pump(s) and adjust Speed Controllers as necessary.
  • Adjust HIC-121, Charging Flow Control Valve, as necessary to maintain seal injection flow between 6 gpm and 20 gpm per RCP.
f. Place PCV-l45, Low Pressure Letdown Controller, in MANUAL and adjust to 45% to 55% open to limit pressure spike when opening letdown orifice isolation valves.
g. Open Letdown Orifice Valve(s) to establish desired letdown flow:
  • CVC-200A
  • CVC-200B
  • CVC-200C
h. WHEN Low Pressure Letdown pressure, as indicated on PI145, is stable, Ijj place PCV-l45 in AUTO.

- END -

Rev. 4 EOP-ES-O.1 REACTOR TRIP RESPONSE Page 27 of 37

STEP H ACTION/EXPECTED RESPONSE Attachment 5 RESPONSE NOT OBTAINED I

Establishing Excess Letdown (Page 1 of 2)

1. Establish Excess Letdown:
a. Open CCW from excess letdown heat exchanger, CC-739
b. Close excess letdown flow control valve, HCV-137
c. Place excess letdown divert valve, CVC-389, to RCDT
d. Check if seal return flow - d. WHEN seal return flow is ESTABLI SHED established, THEN excess letdown divert valve, CVC-389, may be placed to VCT if desired.

Continue With Step 1.f.

e. Place excess letdown divert valve, CVC-389, to VCT if desired
f. Slowly open excess letdown flow control valve, HCV-137
g. Close excess letdown flow control valve, HCV-137
h. Open excess letdown stop valve, CVC-387
i. Slowly open excess letdown flow controller, HCV-137
j. Maintain excess letdown heat exchanger outlet temperature, TI-139 - LESS THAN 195°F (CONTINUED NEXT PAGE)

Rev. 4 EOP-ES-O.l REACTOR TRIP RESPONSE Page 28 of 37 1__STE ACTION/EXPECTED RESPONSE Attachment 5 RESPONSE NOT OBTAINED I

Establishing Excess Letdown (Page 2 of 2)

1. (CONTINUED)
k. Check if normal letdown - k. Perform the following:

ESTABLI SHED

1) Continue efforts to establish normal letdown.

WHEN normal letdown is established, THEN stop excess letdown:

a) Close excess letdown flow control valve, HCV-137.

b) Close excess letdown stop valve, CVC-387

2) Return To procedure,and step in effect.
1. Stop excess letdown:
1) Close excess letdown flow control valve, HCV-137
2) Close excess letdown stop valve, CVC-387

- END -

Rev. 4 EOP-ES-O.1 REACTOR TRIP RESPONSE Page 29 of 37 STEP_H ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Attachment 6 Establishing Aux Spray Without SI (Page 1 of 2)

1. Check Charging Pumps - At LEAST Start at least one charging pump.

ONE RUNNING

2. Open Aux Spray Valve, CVC-311
3. Close Loop Charging Valves:
  • CVC-310A
  • CVC-31OB
4. Adjust Charging Pump Speed As Necessary To Maintain Proper Seal Injection Flow
5. Open HIC-121, Charging Flow Control Valve, As Necessary To Lower RCS Pressure

Rev. 4 EOP-ES-O.l FEACTOR TRIP RESPONSE Page 30 of 37 H STEP H ACTION/EXPECTED RESPONSE Attachment 6 I RESPONSE NOT OBTAINED Establishing Aux Spray Without SI (Page 2 of 2)

NOTE Supplement K, Auxiliary Spray Enhancement, may be used for optimizing Auxiliary Spray.

6. Control RCS Pressure:
a. Perform the following to terminate aux spray:
1) Open loop charging valve, CVC-310B or CVC-31OA
2) Close aux spray valve, 2) Isolate aux spray line:

CVC-311 a) Minimize charging.

b) Close HIC-121, charging flow control valve.

c) Adjust charging pump speed to maintain proper seal injection flow.

d) Go To Step 6.b.

3) Adjust charging pump speed and charging flow control valve, HIC-121, as necessary to maintain proper seal injection and charging flow
b. Return To Step 2 to reinitiate aux spray as desired

- END -

Rev. 4 EOP-ES-O.l REACTOR TRIP RESPONSE Page 31 of 37 Attachment 7 DC Bus Or Instrument Bus Failure (Page 1 of 2)

1. IF DC Bus failure has occurred, TEEN perform the following:
a. IF DC Bus A fails. THEN perform the following:
1) In the Charging Pump Room, open CVC-358. RWST TO CHARGING PUMP SUCTION.
2) WILN CVC358 is open, THEN close LCV-115C, VCT Outlet from RTGB.
3) In the E-1/E-2 Room, transfer Instrument Bus 2 to MCC-8.
4) In the 416OV Bus Room, trip the Exciter Field Breaker.
5) In EDG A Room perform the following:
  • Trip EDG A Fuel Racks.
  • Close DA-21A AND DA-25A, DC A AIR START OUTLET ISOLATION valves.
b. IE DC Bus B fails. THEN perform the following:
1) In the E-1/E-2 Room, transfer Instrument Bus 3 to MCC-8.
2) In EDO B Room, perform the following:
  • Trip EDO B Fuel Racks.
  • Close DA-21B AND DA-25B, DO B AIR START OUTLET ISOLATION valves.
3) Close LCV-46O A & B, LTDN LINE STOPs.
2. IF MCC5 is energized, TEEN perform the following:
a. Verify DS bus is energized.
b. Transfer power source to DS Bus using the posted instructions at the Kirk Key Interlocked Breakers.
c. Locally reset and load instrument air compressor A (MCC-5 CMPT 7M).

Rev. 4 EOP-ES-O.1 REACTOR TRIP RESPONSE Page 32 of 37 Attachment 7 DC Bus Or Instrument Bus Failure (Page 2 of 2)

3. j Instrument Bus failure has occurred, 1D perform the following:
a. IF Instrument Bus 4 fails, THEN maintain Steam Dump in the Tavg Mode.
b. i a failure of only of the below Instrument Busses occurs, THEN transfer the failed bus to MCC-8.
  • Instrument Bus 1
  • Instrument Bus 2
  • Instrument Bus 3
  • Instrument Bus 4
c. IF more than ONE Instrument Bus requires transfer to MCC-8 for Nuclear Safety Concerns, THEN strip the affected Busses using the applicable Attachment, Load Shed Listing For Instrument Buses, of AOP-024, Loss of Instrument Bus, prior to transferring the Buss(es) to MCC-8.

- END -

Rev. 4 EOP-ES-O.1 REACTOR TRIP RESPONSE Page 33 of 37

-Ii-f ACTION/EXPECTED RESPONSE Attachment 8 RESPONSE NOT OBTAINED Aligning Balance Of Plant (Page 1 of 2)

1. Shutdown Unnecessary Plant Equipment:
a. Stop all but one main feed pump
b. Stop all heater drain pumps
c. Stop all but one condensate pump
d. Stop circulating water pump(s) as desired
2. Check Main Turbine Status:
a. Check the following valves - a. Manually open valve(s) as OPEN: necessary.
  • DV-l, DV-2, DV-3, and DV-4, main steam drain valves
  • DV-5, first stage drain valve
  • DV-6, moisture separator A drain valve
  • DV-], moisture separator B drain valve
b. Check the following pumps - b. Manually start pump(s) as RUNNING necessary.
  • Turning gear pump j any pump can LQ be
  • Seal oil backup pump started. THEN start emergency oil pump.
c. Place both EH oil pumps in the PULL-TO-LOCK:
  • Gov fluid pump A
  • Gov fluid pump B

Rev. 4 EOP-ES-O.l REACTOR TRIP RESPONSE Page 34 of 37 H STEP_H ACTION/EXPECTED RESPONSE Attachment 8 RESPONSE NOT OBTAINED I

Aligning Balance Of Plant (Page 2 of 2)

3. Check Bearing Oil Lift Pump Status:
a. Check turbine speed - LESS a. WREN turbine speed is less THAN 600 RPM than 600 rpm. ThEN do Step 3.b.

Go To Step 4.

b. Check bearing oil lift pump b. Manually start pump.

RUNNING

4. Check The Turbine Goes On The IE bearing oil pressure Turning Gear ONE MINUTE After (PI-2096A) is greater than Zero Speed Alarm Is Received 6 psig Ai the bearing oil lift pump is running, THEN manually engage the Turning Gear:
a. Place the turning gear switch in the OFF position.
b. Locally place the TURNING GEAR ENG/DISENG LEVER in the ENGAGED position.
c. Place the turning gear switch in MANUAL.

IF the turning gear and bearing oil lift pumps are running, THEN contact Engineering for instructions for placing the turbine on turning gear.

- END -

EOP-ES-O.1, Revision 4 PRR 556380 Summary Of Changes Foldout Corrected typo in PZR level setpoint from 21% to 7%.

Step 1 EOP-ES-O.1 Rev. 4 Page 35 of 37

Rev. 4 EOP-ES-O.l REACTOR TRIP RESPONSE Page 36 of 37 CONTINUOUS ACTION

SUMMARY

FOR EOP-ES-O.l

1. Check RCS Temeratures: (while in this procedure)
  • With any RCP running, RCS average temperature -

STABLE AT OR TRENDING TO 547°F OR

  • With NO RCPs running, RCS cold leg temperatures -

STABLE AT OR TRENDING TO 547° F

3. Check S/G Levels:

Maintain total feed flow greater than 300 gpm until narrow range level is greater than 8% in at least one S/G.

Control feed flow to maintain narrow range levels -

BETWEEN 8% AND 50%

4. Check All AC Busses - ENERGIZED BY OFFSITE POWER IF any AC emergency buss(es) are NQT energized by offsite power, THEN perform the following:

Verify EDG(s) running and loaded with proper cooling.

Try to restore offsite power.

Locally load equipment as necessary.

Periodically check status of spent fuel pool until SFP cooling is restored:

  • Fuel pool level
  • Fuel pool temperature

Rev. 4 EOP-ES-O.l REACTOR TRIP RESPONSE Page 37 of 37 CONTINUOUS ACTION

SUMMARY

FOR EOP-ES-O.l

1. Check RCS Temeratures: (while in this procedure)
  • With any RCP running, RCS average temperature -

STABLE AT OR TRENDING TO 547° F OR

  • With NO RCPs running, RCS cold leg temperatures -

STABLE AT OR TRENDING TO 547° F

3. Check S/G Levels:

Maintain total feed flow greater than 300 gpm until narrow range level is greater than 8% in at least one S/G.

Control feed flow to maintain narrow range levels -

BETWEEN 8% AND 50%

4. Check All AC Busses - ENERGIZED BY OFFSITE POWER IF any AC emergency buss(es) are NQ energized by offsite power, THEN perform the following:

Verify EDG(s) running and loaded with proper cooling.

Try to restore offsite power.

Locally load equipment as necessary.

Periodically check status of spent fuel pool until SFP cooling is restored:

  • Fuel pool level
  • Fuel pool temperature

LICENSE EXAMINATION JOB PERFORMANCE MEASURE ILC-13 NRC JPM E RevO Verify Phase B Containment Isolation and CV Spray Alignment Concurred By: Patrick Lathrop Date: 5/15/13 Operations Approved By: James Conder Date: 6/5/13 Superintendent/Supervisor Training

ILC-13 NRC 3PM E Page 2 of 12 LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task: 01000151705, Perform Auto Action Verification JAW EOP-E-0.

Alternate Path:

YES JPM#: Candidate ILC-13NRCJPME RO/SRO K/A Rating (RO/SRO):

026 A4.01 4.5/4.3 103 A3.01 3.9/4.2 Task Standard:

Align Phase B Isolation Valves and CV Spray Valves JAW EOP-E-0.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate

References:

EOP-E-0 Validation Time: 6 Minutes Time Critical: No Time Critical Time: N/A Candidate: (N/A if not time critical)

Name Overall Critical Time Time SSN Start: Start:

Finish: Finish:

Performance Rating: Performance SAT UNSAT circle one Time (mm):

Examiner:

Print Name Signature Date

ILC-13 NRC JPM E Page 3 of 12 COMMENTS:

QUESTION DOCUMENTATION:

Question:

Response

ILC-13 NRC JPM E Page 4 of 12 COMMENTS Step 3 Critical since at least one SJ-880 valve per train must be opened to provide spray flow.

Step 5 Critical since manual action is required to obtain the desired SAT flow.

Step 6 Critical since manual actions are required to close the Phase B valves that should have automatically closed.

Step 7 Critical since stopping the RCPs is required due to component cooling water being isolated to all RCPs.

ILC-13 NRC 3PM E Page 5 ofl2 SIMULATOR OPERATOR INSTRUCTIONS:

1. Initialize the simulator to IC-9 15
2. Go to RUN ensure plant conditions are stable, acknowledge alarms and FREEZE.
3. An extra instructor will be needed to acknowledge alarms that do not apply to this 3PM.
4. Place simulator in RUN when directed by the examiner.

ILC..13 NRC JPM E Page 6 of 12 Tools/Equipment/Procedures Needed:

Markup of EOP-E-0 up to step 9 DIRECTIONS TO CANDIDATE:

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 facilitate the examination and better enable me to assess your level of understanding, verbalize your actions and observations while performing the JPM. To indicate that you have completed your assigned task return the Candidate Cue Sheet I provided you.

CANDIDATE INFORMATION:

Inform the candidate there are NO time critical steps in this JPM.

INITIAL CONDITIONS:

1. Plant was initially at 100% RTP when a Large Break LOCA occurred.
2. Automatic Reactor Trip and Safety Injection actuated.
3. EOP-E-0 has been implemented.
4. EOP-E-0, Step 9.a CV pressure I-lAS REMAiNED LESS THAN 10 PSIG has been answered as NO.

INITIATING CUES:

The CRS has directed you to perform the RNO steps of EOP-E-O, Step 9.a.

ILC-13 NRC JPM E Page 7 of 12 START TIME:

TEP 1: Check CV spray actuated.

(RNO Step 9.a.1)

SAT STANDARD: Candidate observes that the CV Spray signal has initiated by observing annunciator APP-002-D 1, SPRAY ACTUATION and bistables for the CV High-High Pressure are illuminated. UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: Candidate may observe that neither CV Spray Pump is running and take action to start both pumps at this time, BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 2: Verify the following:

a) Both CV Spray pumps are running.

(RNO Step 9.a.2.a)

SAT STANDARD: Candidate determines that both CV Spray Pumps are operating by observing the RED on light illuminated and the GREEN off light extinguished.

UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: Candidate may note that FI-958A/B, Spray Header Flow, is reading zero flow.

BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC 3PM E Page 8 of 12 STEP 3: Verify the following: CRITICAL b) CV spray pump discharge valves are open: STEP

  • SI-880A
  • SI-880B
  • SI-880C
  • SI88OD SAT (RNO Step 9.a.2.b)

STANDARD: Candidate observes that all SI-880 valves are closed as indicated by the UNSAT RED open light extinguished and GREEN shut light illuminated.

Candidate takes manual action to open all SI-880 valves by placing the individual valve control switches momentarily to the OPEN position.

Candidate monitors valves and verifies they are all open as indicated by the RED open lights illuminated and the GREEN shut lights extinguished.

EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM E Page 9 of 12 STEP 4: Verify the following:

c) CV spray additive tank discharge valves are open:

  • SI-845A
  • SI-845B SAT (RNO Step 9.a.2.c)

STANDARD: Candidate observes that SI-845A and SI-845B are open as indicated by the UNSAT RED light illuminated and GREEN light extinguished.

EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 5: Verify the following: CRITICAL d) Spray additive tank flow is approximately 12 gpm: STEP

  • Adjust SI-845C, SAT throttling valve, as necessary.

(RNO Step 9.a.2.d)

STANDARD: Candidate observes flow indicator FI-949, Spray Additive Flow, and SAT throttles valve SI-845 C to reduce flow to approximately 12 gpm.

(Tolerance 8 16 gpm)

EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: SI-845C is a throttle valve and will have to be manipulated to reduce the Spray Additive Tank flow to 12 gpm.

BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM E Page 10 of 12 STEP 6: Verify Containment Isolation Phase B valves are closed. CRITICAL (RNO Step 9.a.3) STEP STANDARD: Candidate observes that the following Phase B isolation valves are Open:

SAT CCW-716A, CCW-716B, CCW-730, CCW-735, FCV-626, CVC-381.

This observation can be made by the individual valve(s) indication on the RTGB, the Containment Phase B status panel, SPDS Containment status UNSAT or by use of Supplement B for Phase B and CV Spray Component Alignment.

The candidate will close the following valves:

CCW-716A, CCW-716B, CCW-730, CCW-735, FCV-626, CVC-381 by positioning the control switches for each valve to the Close position and observing the GREEN closed indication illuminated and the RED open indication extinguished.

The candidate can verify the Phase B isolation by observing the Phase B Status Panel on the RTGB or SPDS Containment status.

EXAMINERS CUE: NONE XAMINERS NOTE NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM E Page 11 of 12 CRITICAL STEP 7: Stop all RCPs. STEP (RNO Step 9.a.4)

STANDARD: Candidate observes all of the RCPs operating and secures each RCP by placing the control switches for RCP A, B and C to the Stop position and observing the GREEN stop indication illuminated and the RED Start SAT indication extinguished.

EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: Candidate may note earlier in the JPM that the RCPs need to be stopped and secure them prior to reaching this step in EOP-E-0 due to meeting EOP-E-0 Foldout RCP trip criteria.

BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 8: Observe CAUTION prior to Step 10 and Go to Step 10 (RNO Step 9.a.5)

SAT STANDARD: Candidate reads step and determines that Step 9 is complete.

EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

END OF TASK Terminating Cue: When CV Spray properly aligned, all Containment Phase B valves manually closed and all RCPs secured.

TIME STOP:

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

CANDIDATE INFORMATION:

Inform the candidate there are NO time critical steps in this JPM.

INITIAL CONDITIONS:

1. Plant was initially at 100% RTP when a Large Break LOCA occurred.
2. Automatic Reactor Trip and Safety Injection actuated.
3. EOP-E-0 has been implemented.
4. EOP-E-0, Step 9.a CV pressure I-lAS REMAiNED LESS THAN 10 PSIG has been answered as NO.

INITIATING CUES:

The CRS has directed you to perform the RNO steps of EOPE-O, Step 9.a.

CONTINUOUS USE H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 PLANT OPERATING MANUAL VOLUME 3 PART 4 EMERGENCY OPERATING PROCEDURE EOPE-O REACTOR TRIP OR SAFETY INJECTION REVISION 2 Page 1 of 39

Rev. 2 EOP-E-O REACTOR TRIP OR SAFETY INJECTION Page 2 of 39 Purpose and Entry Conditions (Page 1 of 4)

1. PURPOSE This procedure provides actions to verify the proper response of the automatic protection systems following the manual or automatic actuation of a reactor trip or safety injection, to assess plant conditions, and to identify the appropriate recovery procedure.

Rev. 2 EOP-E-O REACTOR TRIP OR SAFETY INJECTION Page 3 of 39 Purpose and Entry Conditions (Page 2 of 4)

2. SYMPTOMS AND ENTRY CONDITIONS
a. The following are symptoms that require a reactor trip, if one has not occurred:

REACTOR TRIP SIGNAL LOGIC (INTERLOCK) SETPOINT SR High Flux 1/2 (P-6 and P-b) 105 CPS IR High Flux 1/2 (P-b) Current equal to 25%

PR High Flux Low Range 2/4 (P-b) 24%

PR High Flux High Range 2/4 108%

PZR High Pressure 2/3 2376 psig PZR Low Pressure 2/3 (P-7) 1844 psig PZR High Level 2/3 (P-7) 91%

Low RCS Flow 2/3 on 2/3 (P-7) 1/3 (P-8) 94.68% rated flow RCP Breaker 1/1 on 2/3 (P-7) 1/3 (P-8) Open RCP Bus IJndervoltage 2/3 busses (P-7) 75% (3120 volts)

Over Temperature AT 2/3 Variable Over Power AT 2/3 Variable Safety Injection Auto or Manual N/A Turbine Trip 2/2 SV or 2/3 AST (P-8) N/A Low-Low S/C Level 2/3 on 1/3 16%

Low S/C Level With 1/2 on 1/3 30%

Steam Flow > Feed Flow 1/2 on 1/3 0.64 x 106 lbm/hr (CONTINUED NEXT PAGE)

Rev. 2 EOP-E-O REACTOR TRIP OR SAFETY INJECTION Page 4 of 39 Purpose and Entry Conditions (Page 3 of 4)

2. (CONTINUED)
b. The following are symptoms of a reactor trip:

o Any valid reactor trip annunciator illuminated.

o Rapid reduction in neutron level indicated by nuclear instrumentation.

o All shutdown and control rods fully inserted.

o Rod bottom lights illuminated.

c. The following are symptoms that require a reactor trip and safety injection, if one has not occurred:

SAFETY INJECTION SIGNAL LOGIC SETPOINT Low PZR Pressure 2/3 1715 psig High Containment Pressure 2/3 4 psig High Steam Line 2/3 on 1/3 100 psid High Steam Flow With: 1/2 on 2/3 Variable

  • Low S/G Pressure 2/3 lines 614 psig
  • Low Tavg 2/3 loops 543°F
d. The following are symptoms of a reactor trip and safety injection:

o Any valid SI annunciator illuminated.

o SI pumps running.

o RHR pumps running.

(CONTINUED NEXT PAGE)

Rev. 2 EOP-E-O REACTOR TRIP OR SAFETY INJECTION Page 5 of 39 Purpose and Entry Conditions (Page 4 of 4)

2. (CONTINUED)
e. This procedure should also be entered:

OR

  • Anytime an SI is actuated or required while in Mode 3.

- END -

EOP-E-O FOLDOUT FOR EOP-E-0 Rev. 2

1. RCP TRIP CRITERIA IF either condition listed below occurs, THEN trip all RCPs:
  • Containment Isolation Phase B - ACTUATED OR
  • BOTH of the following satisfied:
  • SI pumps - AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW AND
  • RCS subcooling based on core exit TCs - LESS THAN 30°F [50°F]
2. FAULTED SIG AEW ISOLATION CRITERIA IF both conditions listed below are met,
  • Any 5/0 pressure is lowering in an uncontrolled manner has completely depressurized AND
  • Any S/G is IIQI faulted THEN perform the following:
a. Reset SI.
b. Close steam driven AFW pump discharge valve for faulted 5/0(s)
  • V2-14A (S/G A)
  • V2-14B (S/C B)
  • V2-14C (S/C C)
c. Close AFW header discharge valve for faulted S/C(s):
  • V2-16A (S/C A)
  • V2-16B (S/C B)
  • V2-16C (S/C C)
d. Perform Attachment 2, Deenergizing AFW Valves For Faulted S/C(s).
e. Maintain total feed flow greater than 300 gpm until narrow range level is greater than 8% [18%] in at least one S/G.
3. AFW SUPPLY SWITCHOVER CRITERIA IF CST level lowers to less than 10%, THEN switch to backup water supply using OP-402, Auxiliary Feedwater System.
4. DC BUS. INSTRUMENT BUS. OR MCC-5 FAILURE CRITERIA IF DC bus A, DC bus B, any instrument bus, or MCC-5 is deenergized, THEN perform Attachment 3, DC Bus Or Instrument Bus Failure.
5. SPENT FUEL POOL COOLING CRITERIA IE offsite power is lost, THEN periodically monitor spent fuel pool level and temperature until SFP cooling is restored.

Rev. 2 EOP-E-O REACTOR TRIP OR SAFETY INJECTION Page 6 of 39 l STEP H ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I

NO N

Steps 1 through ar IMMEDIAE ACTION steps.

I .__---

0 Check Reactor Trip: Manually trip reactor.

0 Reactor trip and bypass breakers - OPEN reactor power is greater than or equal to 5% intermediate range SUR is positive, THEN Go 0 Rod position indicators ZERO

- AT To FRP-S.1, Response To Nuclear Power Generation/ATWS, Step 1.

0 Rod Bottom lights ILLUMINATED Neutron flux - LOWERING Check Turbine Trip:

Both turbine stop valves - a. Manually trip turbine.

CLOSED IE turbine will NQ trip, THEN manually run back turbine at maximum rate until all governor valves are closed.

IF turbine can NOT be run back, THEN manually close MSIVs and MSIV bypass valves.

Close MSR purge and shutoff b. loss of power prevents MSR

) valves isolation, THEN manually close MSIV and MSIV bypass valves.

EOP-EO FOLDOUT FOR EOP-E-O Rev. 2

1. RCP TRIP CRITERIA IF either condition listed below occurs, THEN trip all RCPs:
  • Containment Isolation Phase B ACTUATED OR
  • BOTH of the following satisfied:
  • SI pumps - AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW AND
  • RCS subcooling based on core exit TCs - LESS THAN 30°F [500F]
2. FAULTED SIG AFW ISOLATION CRITERIA IF both conditions listed below are met,
  • Any S/G pressure is lowering in an uncontrolled manner has completely depressurized AND
  • Any S/C is Q] faulted ThfII perform the following:
a. Reset SI.
b. Close steam driven AFW pump discharge valve for faulted S/C(s)
  • V2-14A (S/C A)
  • V2-l4B (S/C B)
  • V2-14C (S/C C)
c. Close AFW header discharge valve for faulted S/C(s):
  • V2-16A (S/C A)
  • V2-16B (S/C B)
  • V2-l6C (S/C C)
d. Perform Attachment 2, Deenergizing AFW Valves For Faulted S/C(s).
e. Maintain total feed flow greater than 300 gpm until narrow range level is greater than 8% [18%] in at least one S/C.
3. AFW SUPPLY SWITCHOVER CRITERIA IF CST level lowers to less than 10%, THEN switch to backup water supply using OP-4O2, Auxiliary Feedwater System.
4. DC BUS. INSTRUMENT BUS. OR MCC-5 FAILURE CRITERIA IF DC bus A, DC bus B, any instrument bus, or MCC-5 is deenergized, ]N perform Attachment 3, DC Bus Or Instrument Bus Failure.
5. SPENT FUEL POOL COOLING CRITERIA

.IY offsite power is lost, THEN periodically monitor spent fuel pool level and temperature until SFP cooling is restored.

Rev. 2 EOP-E-O REACTOR TRIP OR SAFETY INJECTION Page 7 of 39

STEP H ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Check Power To AC Emergency Busses:

%E1 or E2 - AT LEAST ONE a. Go To EPP-1, Loss Of All AC ENERGIZED Power. Step 1.

E-1 and E-2 - BOTH ENERGIZED b. WHEN time permits, THEN try to restore power to deenergized AC emergency bus.

Continue With Step 4.

EOP-E0 FOLDOUT FOR EOP-E-O Rev. 2

1. RCP TRIP CRITERIA IF either condition listed below occurs, THEN trip all RCPs:
  • Containment Isolation Phase B - ACTUATED OR
  • BOTH of the following satisfied:
  • SI pumps - AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW AND
  • RCS subcooling based on core exit TCs LESS THAN 30°F [50°F]
2. FAULTED SIG AFW ISOLATION CRITERIA IF both conditions listed below are met,
  • Any S/G pressure is lowering in an uncontrolled manner has completely depressurized AND
  • Any S/G is NQ1 faulted THEN perform the following:
a. Reset SI.
b. Close steam driven AFW pump discharge valve for faulted S/G(s)
  • V2-14A (S/G A)
  • V2-14B (S/G B)
  • V2-14C (S/C C)
c. Close AFW header discharge valve for faulted S/G(s):
  • V2-16A (S/C A)
  • V2-16B (S/C B)
  • V2-16C (S/C C)
d. Perform Attachment 2, Deenergizing AFW Valves For Faulted S/C(s)
e. Maintain total feed flow greater than 300 gpm until narrow range level is greater than 8% [18%] in at least one S/C.
3. AFW SUPPLY SWITCHOVER CRITERIA IF CST level lowers to less than 10%, THEN switch to backup water supply using OP-402, Auxiliary Feedwater System.
4. DC BUS. INSTRuMENT BUS, OR MCC-5 FAILURE CRITERIA IF DC bus A, DC bus B, any instrument bus, or MCC-5 is deenergized, THEN perform Attachment 3, DC Bus Or Instrument Bus Failure.
5. SPENT FUEL POOL COOLING CRITERIA j offsite power is lost, THEN periodically monitor spent fuel pool level and temperature until SFP cooling is restored.

Rev. 2 EOP-E-O REACTOR TRIP OR SAFETY INJECTION Page 8 of 39

STEP

[f ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Check SI Status:

Check if SI is actuated: a. Check if SI is required:

SI annunciators - ANY

  • PZR pressure less than ILLUMINATED 1715 psig SI equipment - AUTO
  • Containment pressure STARTED greater than 4 psig OR
  • Steam line AP bistables illuminated OR
  • High steam flow with low Tavg or low steam pressure bistables illuminated jE SI is required, jN manually actuate BOTH trains of SI.

IE SI is NQ required, THEN perform the following:

1) Reset SPOS and initiate monitoring of Critical Safety Functions Status Trees.
2) Go To EOP-ES-O.1, Reactor Trip Response. Step 1.

Check BOTH trains of SI - b. Manually actuate BOTH trains ACTUATED of SI.

SI pumps - BOTH RUNNING RHR pumps - BOTH RUNNING

EOP-E-O FOLDOUT FOR EOP-E-O Rev. 2

1. RCP TRIP CRITERIA IF either condition listed below occurs, THEN trip all RCPs:
  • Containment Isolation Phase B - ACTUATED OR
  • BOTH of the following satisfied:
  • SI pumps AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW AND
  • RCS subcooling based on core exit TCs - LESS THAN 30°F [500F]
2. FAULTED SIG AFW ISOLATION CRITERIA IF both conditions listed below are met,
  • Any S/C pressure is lowering in an uncontrolled manner has completely depressurized AND
  • Any S/C is IQ] faulted THEN perform the following:
a. Reset SI.
b. Close steam driven AFW pump discharge valve for faulted S/C(s)
  • V2-14A (S/C A)
  • V2-14B (S/C B)
  • V2-14C (S/C C)
c. Close AFW header discharge valve for faulted S/C(s):
  • V2-16A (S/C A)
  • V2.-16B (S/C B)
  • V2-16C (S/C C)
d. Perform Attachment 2, Deenergizing AFW Valves For Faulted S/C(s).
e. Maintain total feed flow greater than 300 gpm until narrow range level is greater than 8% [18%] in at least one S/C.
3. AFW SUPPLY SWITCHOVER CRITERIA IF CST level lowers to less than 10%, IIIN switch to backup water supply using OP-4O2, Auxiliary Feedwater System.
4. DC BUS, INSTRUMENT BUS, OR MCC-5 FAILURE CRITERIA IF DC bus A, DC bus B, any instrument bus, or MCC-5 is deenergized, THEN perform Attachment 3, DC Bus Or Instrument Bus Failure.
5. SPENT FUEL POOL COOLING CRITERIA IE offsite power is lost, ThEN periodically monitor spent fuel pool level and temperature until SFP cooling is restored.

Rev. 2 EOP-E-O REACTOR TRIP OR SAFETY INJECTION Page 9 of 39 J-f ACTION/EXPECTED RESPONSE I /I RESPONSE NOT OBTAINED FOLDOUT for 3 is in effect.

C Perform Attachment 1, Auto Action Verification, While Continuing With This Procedure Check AFW Pumps - RUING Motor driven AFW pumps - BOTH a. Manually start pump(s) as

/ RUNNING necessary.

S/C levels TWO S/Gs LESS b. IF two S/C levels lower to THAN 16% less than 16%. THEN do Step 6.c.

Continue With Step 7.

%Steam driven AFW pump steam c. Manually open valve(s) as shutoff valves - ALL OPEN necessary.

Check AFW Valves - PROPER Manually align valve(s) as EMERGENCY ALl GNMENT necessary.

AFW header discharge valves - FULL OPEN AFW header section valves -

FULL OPEN Steam driven AFW pump discharge valves - FULL OPEN IF PUMP RUNNING

EOP-E-0 FOLDOUT FOR EOP-E-O Rev. 2

1. RCP TRIP CRITERIA IF either condition listed below occurs, THEN trip all RCPs:
  • Containment Isolation Phase B - ACTUATED OR
  • BOTH of the following satisfied:
  • SI pumps - AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW AND
  • RCS subcooling based on core exit TCs - LESS THAN 30°F [50°F]
2. FAULTED S/G AEW ISOLATION CRITERIA IF both conditions listed below are met,
  • Any S/G pressure is lowering in an uncontrolled manner has completely depressurized AND
  • Any S/G is faulted THEN perform the following:
a. Reset SI.
b. Close steam driven AFW pump discharge valve for faulted S/G(s):
  • V2-14A (S/C A)
  • V2-14B (S/C B)
  • V2-14C (S/C C)
c. Close AFW header discharge valve for faulted S/C(s):
  • V2-16A (S/C A)
  • V2-16B (S/C B)
  • V2-16C (S/C C)
d. Perform Attachment 2, Deenergizing AFW Valves For Faulted S/C(s)
e. Maintain total feed flow greater than 300 gpm until narrow range level is greater than 8% [18%] in at least one S/G.
3. AFW SUPPLY SWITCHOVER CRITERIA IF CST level lowers to less than 10%, IN switch to backup water supply using OP-402, Auxiliary Feedwater System.
4. DC BUS. INSTRUMENT BUS. OR MCC-5 FAILURE CRITERIA IF DC bus A, DC bus B, any instrument bus, or MCC-5 is deenergized, THEN perform Attachment 3, DC Bus Or Instrument Bus Failure.
5. SPENT FUEL POOL COOLING CRITERIA IF offsite power is lost, THEN periodically monitor spent fuel pool level and temperature until SFP cooling is restored.

Rev. 2 EOP-E-O REACTOR TRIP OR SAFETY INJECTION Page 10 of 39 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I

CAU ON If offsite power is lost after S reset, manual action may be required to restart safeguards equipment.

                                                                            • *********************t* *************

%Check Total AFW Flow:

Reset SI Control feed flow to maintain NON-faulted S!G(s) narrow range level - BETWEEN 8% [18%] AND 50%

Øheck total AFW flow - c. SIG narrow range level is GREATER THAN 300 GPM greater than 8% [18%] in any S/C, THEN control feed flow to maintain narrow range level.

I] narrow range level is less than 8% [18%] in all S/Gs, THEN perform the following:

1) Manually start pumps and align valves as necessary.
2) IF AFW flow greater than 300 gpm can NQI be established, THEN perform the following:

a) Reset SPDS and initiate monitoring of Critical Safety Functions Status Trees.

b) Go To FRP-H.l, Response To Loss Of Secondary Heat Sink. Step 1.

EOPE-O FOLDOUT FOR EOPE-O Rev. 2

1. RCP TRIP CRITERIA IF either condition listed below occurs, trip all RCPs:
  • Containment Isolation Phase B - ACTUATED OR
  • BOTH of the following satisfied:
  • SI pumps - AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW AND
  • RCS subcooling based on core exit TCs - LESS THAN 30°F [50°F]
2. FAULTED S/G AFW ISOLATION CRITERIA IF both conditions listed below are met,
  • Any S/C pressure is lowering in an uncontrolled manner has completely depressurized AND
  • Any S/G is +/-QI faulted THEN perform the following:
a. Reset SI.
b. Close steam driven AFW pump discharge valve for faulted S/C(s)
  • V2-14A (S/C A)
  • V2-14B (S/C B)
  • V2-14C (S/C C)
c. Close AFW header discharge valve for faulted S/C(s):
  • V2-l6A (S/C A)
  • V2-l6B (S/C B)
  • V2-16C (S/C C)
d. Perform Attachment 2, Deenergizing AFW Valves For Faulted S/C(s).
e. Maintain total feed flow greater than 300 gpm until narrow range level is greater than 8% [18%] in at least one 5/C.
3. AEW SUPPLY SWITCHOVER CRITERIA IF CST level lowers to less than 10%, THEN switch to backup water supply using OP-4O2, Auxiliary Feedwater System.
4. DC BUS, INSTRUMENT BUS. OR MCC-5 FAILURE CRITERIA IF DC bus A, DC bus B, any instrument bus, or MCC-5 is deenergized, THEN perform Attachment 3, DC Bus Or Instrument Bus Failure.
5. SPENT FUEL POOL COOLING CRITERIA IE offsite power is lost, THEN periodically monitor spent fuel pool level and temperature until SFP cooling is restored.

Rev. 2 EOP-E-O REACTOR TRIP OR SAFETY INJECTION Page 11 of 39 f STEP H ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED

9. Check CV Spray Reqttired:
a. CV pressure - HAS REMAINED a. Perform the following:

LESS THAN 10 PSIG

1) Check CV spray actuated.

LE CV spray is actuated, THEN manually actuate BOTH trains of CV spray.

2) Verify the following:

a) Both CV spray pumps are running.

b) CV spray pump discharge valves are open:

  • SI-88OA
  • SI-88OB
  • SI-88OC
  • SI-88OD c) CV spray additive tank discharge valves are open:
  • SI-845A
  • SI-845B d) Spray additive tank flow is approximately 12 gpm:
  • Adjust SI-845C, SAT throttling valve, as necessary.
3) Verify Containment Isolation Phase B valves are closed.
4) Stop all RCPs.
5) Observe CAUTION prior to Step 10 and Go To Step 10.

(CONTINUED NEXT PAGE)

EOP-E-O FOLDOUT FOR EOP-E-0 Rev. 2

1. RCP TRIP CRITERIA IF either condition listed below occurs, trip all RCPs:
  • Containment Isolation Phase B - ACTUATED OR
  • BOTH of the following satisfied:
  • SI pumps - AT LEAST ONE RUNNING AND CAPABLE OF DELIVERING FLOW AND
  • RCS subcooling based on core exit TCs - LESS THAN 30°F [500F]
2. FAULTED S/G AEW ISOLATION CRITERIA IF both conditions listed below are met,
  • Any S/G pressure is lowering in an uncontrolled manner OR has completely depressurized AND
  • Any S/G is Q] faulted THEN perform the following:
a. Reset SI.
b. Close steam driven AFW pump discharge valve for faulted S/G(s)
  • V2-14A (S/C A)
  • V2-14B (S/G B)
  • V2-14C (S/C C)
c. Close AFW header discharge valve for faulted S/C(s):
  • V2-16A (S/G A)
  • V2-16B (S/C B)
  • V2-16C (S/C C)
d. Perform Attachment 2, Deenergizing AFW Valves For Faulted S/G(s)
e. Maintain total feed flow greater than 300 gpm until narrow range level is greater than 8% [18%] in at least one S/G.
3. AFW SUPPLY SWITCHOVER CRITERIA IF CST level lowers to less than 10%, I)]5II switch to backup water supply using OP-4O2, Auxiliary Feedwater System.
4. DC BUS. INSTRUMENT BUS. OR MCC-5 FAILURE CRITERIA IF DC bus A, DC bus B, any instrument bus, or MCC-5 is deenergized, THEN perform Attachment 3, DC Bus Or Instrument Bus Failure.
5. SPENT FUEL POOL COOLING CRITERIA IE offsite power is lost, THEN periodically monitor spent fuel pool level and temperature until SFP cooling is restored.

Rev. 2 EOP-E-O REACTOR TRIP OR SAFETY INJECTION Page 12 of 39 H STEP H ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

9. (CONTINUED)
b. CV spray - +/-Q] ACTUATED b. I.E CV spray inadvertently actuated, THEN perform the following:
1) Stop all RCPs.
2) Override containment spray signal:
3) Reset containment isolation Phase B.
4) Stop CV spray pumps.
5) Close CV spray pump discharge valves:
  • SI-880A
  • SI-S8OB
  • SI-88OC
  • SI-88OD
6) Close CV spray additive tank discharge valves:
  • SI-845A
  • SI-845B

LICENSE EXAMINATION JOB PERFORMANCE MEASURE ILC13 NRC JPM F Rev. 0 Operation with High Switchyard Voltage Concurred By Kirk Schauer Date: 5/15/13 Operations Approved By: James Conder Date: 6/5/13 Superintendent/Supervisor Training

ILC-13 NRC JPM F Page 2 of 22 LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task: 01093124604, Respond to High Switchyard Voltage JAW AOP-03 1 Alternate Path:

Yes JPM #: Candidate ILC43 NRC JPM F RO/SRO K/A Ratin (ROISRO):

062 A2.08 2.7/3.0 Task Standard:

Voltage on 480V Bus E-2 lowered to less than 505 Volts JAW AOP-03 1.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate

References:

AOP-03 1, Operation with High Switchyard Voltage Validation Time: 10 Minutes. Time Critical: No Time Critical Time: N/A Candidate: (N/A if not time critical)

Name Overall Critical Time Time SSN Start: Start:

Finish: Finish:

Performance Rating: SAT Performance UNSAT circle one Tame (mm):

Examiner:

Print Name Signature Date

ILC-13 NRC JPM F Page 3 of 22 COMMENTS:

QUESTION DOCUMENTATION:

Question:

Response

ILC-13 NRC JPM F Page 4 of 22 COMMENTS Step 21 is critical because the Synchroscope Key must be placed in the proper switch.

Step 22 is critical because the Synchroscope Key Switch must be selected to Bus 3 & 4 position.

Step 24 is critical because closing BKR 52/19 will transfer load to the SUT in an attempt to lower voltage on Bus E-2.

Step 27 is critical because BKR 52/20 should have AUTO-OPENED when BKR 52/19 was CLOSED.

Manual action by the operator is required to unparallel the SUT and UAT.

ILC-13 NRC JPM F Page 5 of 22 SIMULATOR OPERATOR INSTRUCTIONS:

1. IC 916
2. SCN: 009_ILC_1 3_NRCCR_JPM_F (Not needed. All malfunctions snapped into IC.)
3. AOP-03 1 performed and marked up to step 21.
4. Reset to IC 916 and place in Run, clear alarms and then place in Freeze.
5. Bring up QP E1E2 at the BOP Desk.
6. Place simulator to Run when Candidate assumes the watch.

ILC-13 NRC JPM F Page 6 of 22 Tools/Equipment/Procedures Needed:

AOP-031 marked up to step 21 DIRECTIONS TO CANDIDATE:

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 facilitate the examination and better enable me to assess your level of understanding, verbalize your actions and observations while performing the JPM. To indicate that you have completed your assigned task return the Candidate Cue Sheet I provided you.

CANDIDATE INFORMATION:

Inform the candidate there are NO time critical steps in this JPM.

INITIAL CONDITIONS:

1. Plant is at 100% power.
2. Due to abnormal conditions on the Grid, 480V Bus E-2 currently exceeds 505 Volts.
3. AOP-03 1, Operation with High Switchyard Voltage, has been completed up to step 21.
4. YouaretheBOP.
5. D IAC is in service with A and B JACs in AUTO.
6. The DSDG is secured and aligned for AUTO.
7. The Load on Emergency Bus E-1 has NOT been altered since entering this AOP.

INITIATING CUES:

The CRS has directed you to continue with AOP-03 1 until 480V Bus E-2 voltage is restored to less than 505 Volts.

ILC-13 NRC JPM F Page 7 of 22 START TIME:

TEP 1: Check Emergency Bus E-2 Voltage Greater than 505 Volts (Step 21).

SAT STANDARD: Candidate Determines that Bus E-2 Voltage is approximately 506.4 volts as indicated on ERFIS.

UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

NOTE: Transferring the following safety related components will cause voltage to rise. This step is designed to protect components.

STEP 2: Check Instrument Air as follows:

a. Check Instrument Air Compressor B Running in Manual SAT (Step 22.a.)

RNO: Go to Step 23 UNSAT STANDARD: Candidate determines that Instrument Air Compressor B is in AUTO as stated in the Cue. Candidate progresses to RNO: Go to Step 23.

EXAMINERS CUE: If candidate request status of IAC B, remind the candidate that the Cue sheet stated that IACs A and B were in AUTO.

EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM F Page 8 of 22 STEP 3: Check EDG B Status as Follows:

a. Check Main Generator ON LINE (Step 23.a.)

SAT STANDARD: Candidate determines that the Main Generator is ON Line based on Plant Conditions and Cue Sheet.

UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 4: Check EDG B Status as Follows:

b. Check EMERGENCY DIESEL GENERATOR B RUNNING -

(Step 23.b.)

SAT STANDARD: Determines that B EDG is NOT running jXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC- 13 NRC JPM F Page 9 of 22 STEP 5: Check EDG B Status as Follows:

b. RNO: Postpone EDG B testing while in the AOP. Go to Step 24.

Check EMERGENCY DIESEL GENERATOR B RUNNING - SAT (Step 23.b. RNO)

STANDARD: Candidate transitions to Step 24. UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 6: Log the Time That Any of the Following Equipment Is OR Was Running Above 505 Volts.

  • INSTRUMENT AIR COMPRESSOR B
  • Fuel Oil Transfer Pump B (Step 24)

UNSAT STANDARD: Determines that NONE of these components are running.

EXAMINERS CUE: Inform candidate that another candidate will track the run times.

EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13NRCJPMF Page 10 of22 STEP 7: Check Load On Emergency Bus E-1 HAS BEEN RAISED USING STEP 18.

(Step 25)

Go to Step 27 SAT (Step 25 RNO)

STANDARI: Candidate determines that load on Emergency Bus E-1 has NOT been raised based on information given in the Cue. UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 8: Raise Load On Emergency BUS E-2 As Follows:

a. Check Charging Pump C Running SAT (Step 27.a)

STANDARD: Candidate determines that Charging Pump C is running.

UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM F Page 11 of22 STEP 9: Raise Load On Emergency BUS E-2 As Follows:

b. Verify CV RECIRC FANS RUNNING

- HVH-3 SAT

- HVH-4 (Step 27.b)

UNSAT STANDARD: Determines that HVH-3 and HVH-4 are running.

EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 10: Check CONT RM AIR HANDLING HVA-1B RUNNING -

(Step 27.c)

SAT STANDARD: Determines that HVA-1B is running.

iXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM F Page 12 of22 STEP 11: Check CRDM COOLING FAN, HVH-5B - RUNNING (Step 27.d)

SAT STANDARD: Candidate Determines that HVH-SB is NOT RUNNING. Go to Step 27.d RNO.

UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 12: Transfer CRDM COOLING FANS as follows:

1. Start HVH-5B
2. Stop HVH-5A (Step 27.d RNO)

SAT STANDARD: Candidate starts HVH-5B and stops HVH-5A.

EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: E2 Voltage should lower to approx. 505.9 Volts.

BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM F Page 13 of22 STEP 13: Check AUX BLDG EXH FAN, HVR-2B RUNMNG -

(Step 27.e)

SAT STANDARD: Candidate determines that HVE-2B is NOT running. Go to Step 27.e RNO.

EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 14: Transfer AUX BLDG EXH FANs as follows:

1) Start HVE-2B
2) Stop HVE-2A (Step 27.e RNO)

SAT TANDARD: Candidate starts HVE-2B and stops HVE-2A.

UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: E-2 Voltage should lower to approx. 505.4 Volts.

BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM F Page 14 of22 STEP 15: Check RHR - IN SERVICE.

(Step 27. f)

SAT STANDARD: Candidate determines that RHR is NOT is IN SERVICE. Go to Step 27.fRNO which directs Candidate to Step 28.

EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 16: Check Emergency BUS E-2 Voltage - GREATER THAN 505 VOLTS (Step 28)

SAT STANDARD: Candidate determines that Bus E-2 Voltage IS greater than 505 Volts.

EXAMINERS CUE: NONE U1JSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM F Page 15 of22 STEP 17: Check DSDG Status As Follows:

a. Check Main Generator ON LINE (Step 29.a)

SAT STANDARD: Candidate determines that the Main Generator is ON LINE.

EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 18: Check DSDG Status As Follows:

b. Check DSDG RUNNING (Step 29.b)

SAT STANDARD: Candidate determines that the DSDG is NOT running base on Cue. Go to Step 29.b RNO. UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC 3PM F Page 16 of22 STEP 19: Check DSDG Status As Follows:

b. RNO: Postpone DSDG testing while in this AOP. Go to Step 30.

(Step 29.b RNO)

SAT STANDARD: Candidate transitions to step 30.

UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 20: Check 4KV BUS 3-4 TIE, BKR 52-19 OPEN-(Step 30)

SAT STANDARD: Candidate determines that 4KV BUS 3-4 TIE, BKR 52-19 IS OPEN.

EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: BKR 52-19 indicates OPEN (TRIP) by GREEN light lit.

BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM F Page 17 of22 STEP 21: Transfer 4160V BUS 4 to the STARTUP TRANSFORMER as follows: CRITICAL STEP

a. Insert the Synchroscope Key into 4 KV TIES Synchroscope Key Switch (Step 31.a)

SAT STANDARD: Candidate insets the synchroscope key into 4 KV TIES Synchroscope Key Switch.

UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 22: Transfer 4160V BUS 4 to the STARTUP TRANSFORMER as follows: CRITICAL STEP

b. Place the Synchroscope Switch to the BUS 3 & 4 position (Step 31.b)

SAT STANDARD: Candidate places the Synchroscope Switch to the BUS 3 & 4 position.

EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM F Page 18 of22 STEP 23: Transfer 4160V BUS 4 to the STARTUP TRANSFORMER as follows:

c. Verify the Synchroscope comes to approximately the 12 oclock position.

SAT (Step 31.c)

STANDARD: Candidate verifies that the Synchroscope is pointing to the 12 oclock UNSAT position.

EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 24: Transfer 4160V BUS 4 to the STARTUP TRANSFORMER as follows: CRITICAL STEP

d. Momentarily place the Control Switch for 4KV BUS 3-4 TIE, BKR 52/19 to the CLOSE position.

(Step 31 .d) SAT STANDARD: Candidate momentarily places the control switch for BKR 52/19 to the CLOSE position. UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM F Page 19of22 STEP 25: Transfer 4160V BUS 4 to the STARTUP TRANSFORMER as follows:

e. Check BKR 52/19 CLOSED SAT (Step 31.e)

STANDARD: Candidate confirms that BKR 52/19 is CLOSED as indicated on RTGB. UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: BKR 52-19 indicates CLOSED with RED light lit.

BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 26 Transfer 4160V BUS 4 to the STARTUP TRANSFORMER as follows

f. Check UThJIT AUX TO 4 KV BUS 4 BKR, 52/20 OPEN -

SAT (Step 31.0 TANDARD: Candidate identifies that BKR 52/20 has remained in the CLOSED position. UNSAT Transitions to Step 31 .f RNO EXAMINERS CUE: NONE EXAMINERS NOTE: BKR 52-20 indicates CLOSED with RED light lit.

BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM F Page 20 of 22 STEP 27: Transfer 4160V BUS 4 to the STARTUP TRANSFORMER as follows: CRITICAL STEP

f. RNO: Perform the following
  • Simultaneously depress the THINK pushbutton AND place the control switch for BKR 52/20 to the OPEN position. SAT (Step 31.fRNO)

STANDARD: Candidate locates and depresses the THINK pushbutton and places the UNSAT control switch for BKR 5 2/20 to the OPEN (TRIP) position. Identifies that BKR 52/20 is now OPEN.

EXAMINERS CUE: NONE EXAMINERS NOTE: BKR 52/20 indicates OPEN (TRIP) with GREEN light lit.

BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 28: Place the 4 KV TIES Synchroscope Key Switch to the mid position.

(Step 31.g)

STANDARD: Candidate places the 4KV TIES Synchroscope Key Switch to the mid SAT position.

EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM F Page 21 of22 STEP 29: Check the following:

  • Emergency BUS E-1 Voltage LESS THAN 505 VOLTS AND
  • Emergency BUS E-2 Voltage LESS THAN 505 VOLTS (Step 32) SAT STANDARD: Candidate determines that BOTH Emergency BUS E-1 and E-2 are LESS THAN 505 VOLTS UNSAT EXAMINERS CUE: When candidate identifies that BOTH Bus E-1 and E-2 are less than 505 VOLTS inform the candidate that this completes the JPM.

EXAMINERS NOTE: Bus E-2 Voltage should be approx. 496.5 Volts.

COMMENTS:

STEP 30: Check Voltage as Follows: (Continuous Action Step)

  • APP-036-E3, SUT PRI OVERIUNDER VOLTAGE - EXTINGUISHED AND
  • WEST 115KV BUS VOLTAGE LESS THAN 119 KV AND SAT
  • Emergency BUS E-1 Voltage LESS THAN 502 VOLTS AND
  • Emergency BUS E-2 Voltage LESS THAN 502 VOLTS UNSAT (Step 33)

STANDARD: Candidate determines that BOTH Emergency BUS E- 1 and E-2 are LESS THAN 502 VOLTS EXAMINERS CUE: When candidate identifies that BOTH Bus E-1 and E-2 are less than 502 VOLTS inform the candidate that this completes the JPM.

EXAMINERS NOTE: Bus E-2 Voltage should be approx. 496.5 Volts.

COMMENTS:

END OF TASK Terminating Cue: Voltage on 480V Bus E-2 lowered to less than 505 Volts.

TIME STOP:

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

CANDIDATE INFORMATION:

Inform the candidate there are NO time critical steps in this 3PM.

INITIAL CONDITIONS:

1. Plant is at 100% power.
2. Due to abnormal conditions on the Grid, 480V Bus E-2 currently exceeds 505 Volts.
3. AOP-03 1, Operation with High Switchyard Voltage, has been completed up to step 21.
4. YouaretheBOP.
5. D IAC is in service with A and B IACs in AUTO.
6. The DSDG is secured and aligned for AUTO.
7. The Load on Emergency Bus E-1 has NOT been altered since entering this AOP.

INITIATING CUES:

The CRS has directed you to continue with AOP-03 1 until 480V Bus E-2 voltage is restored to less than 505 Volts.

CONTINUOUS USE II. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 PLANT OPERATING MANUAL VOLUME 3 PART 5 ABNORMAL OPERATING PROCEDURE AOP 031 OPERATION WITH HIGH SWITCHYARD VOLTAGE REVISION 14 Page 1 of 22

Rev. 14 AOP-031 OPERATION WITH HIGH SWITCHYARD VOLTAGE Page 2 of 22 Purpose and Entry Conditions (Page 1 of 1)

1. PURPOSE
a. This procedure provides instructions in the event of high switchyard or Emergency Bus voltage. The intent of the procedure is to protect safety related loads with 440 volt motor nameplate ratings from extended operation above design voltage.

NOTE Entry to this procedure is required for momentary spikes in system voltage caused by instability problems Q, due to momemtary spikes caused by starting an EDG.

2. ENTRY CONDITIONS
a. High alarm on APP-O36-E3, SUT PRI OVER/UNDER VOLTAGE
b. ERFIS readings for Emergency Bus E-l E-2 exceed 505 volts.
c. WEST 115KV BUS VOLTAGE indication greater than 119 KV.

- END -

Rev. 14 AOP-031 OPERATION WITH HIGH SWITCHYARD VOLTAGE Page 3 of 22 j STEP_H ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED Make PA Announcement For f Procedure Entry.

Check Main Generator - IN SERVICE Go To Step 4.

Check Generator Reactive Load - Positio the V$L GE ADJUSTER At 35 MVARS > Switch, as ne/ess ry to maintain reactiv loyid at 5 MVARS.

Contact The Load Dispatcher To Take Action To Lower Grid Voltage Check Load Dispatcher Actions - the Load Dispatcher has COMPLETE completed actions to lower voltage. III Go To Step 6 Check Voltage As Follows: Return to procedure and step in effect.

APP-O36-E3, SUT PRI OVER/UNDER VOLTAGE -

ILLUMINATED OR WEST 115KV BUS VOLTAGE -

GREATER THAN 119 KV OR Emergency BUS E-1 Voltage -

GREATER THAN 505 VOLTS OR Emergency BUS E-2 Voltage -

GREATER THAN 505 VOLTS

Rev. 14 AOP-03l OPERATION WITH HIGH SWITCHYARD VOLTAGE Page 4 of 22 STEP_H ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

  • The order of preference for monitoring voltage is ERFIS, Attachment 1, then local indication.
  • The following points are found on QP E1E2.

Check The Following ERFIS Perform the following:

Points And Plots- AVAILABLE

a. Contact I&C personnel to
  • ELV3O2OA - E-1 obtain voltage for the ELV3O21A - E-2 unavailable ERFIS points
  • OP E1E2 - Plot using Attachment 1.
b. Direct an Operator to obtain Emergency Bus voltage for the unavailable ERFIS points using local indication at 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> intervals:
  • EI-2l3 - 480V BUS E-l
  • EI-2l4 - 480V BUS E-2
c. WHEN I&C has commenced obtaining voltage with Attachment 1, THEN discontinue use of local indication.

Go To Step 9.

Monitor Emergency Bus Voltage Using ERFIS

Rev. 14 AOP-031 OPERATION WITH HIGH SWITCHYARD VOLTAGE Page 5 of 22 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Implement The EALs Check Emergency BUS E-1 Voltage IF Emergency BUS E-1 voltage

- GREATER THAN 505 VOLTS exceeds 505 volts. THEN observe the NQ prior to Step 11 and Go To Step 11 Go To StePØ NOTE Transferring the following safety related components will cause voltage to rise. This step is designed to protect the components.

11. Check CCW Pumps as follows:
a. Check CCW PUMP B - RUNNING a. Go To Step 12.
b. Check CCW PUMP A AVAILABLE b. Go To Step 12.
c. Perform the following using OP-3O6, Operating CCW Pumps:
1) Start CCW PUMP A
2) Stop CCW PUMP B
12. Check Instrument Air As Follows:
a. Check INSTRUMENT AIR a. Go To Step 13.

COMPRESSOR A - RUNNING IN MANUAL

b. Check One Of The Following b. Place One Of The Following Compressors - IN SERVICE Compressors - IN SERVICE Using OP 905. Instrument And Using OP 905, Instrument And Station Air System Station Air System
  • INSTRUMENT AIR
  • INSTRUMENT AIR COMPRESSOR D COMPRESSOR D
  • PRIMARY AIR COMPRESSOR
  • PRIMARY AIR COMPRESSOR
c. Place INSTRUMENT AIR COMPRESSOR A In AUTO

Rev. 14 AOP-031 OPERATION WITH HIGH SWITCHYARD VOLTAGE Page 6 of 22 H__STEP_H ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED I

13. Check EDG A Status As Follows:
a. Check Main Generator - ON LINE a. IF EDG A is Paralleled to Emergency Bus E-1. ]IIN Go To Step 13.c.

Go To Step 14.

b. Check EMERGENCY DIESEL b. Postpone EMERGENCY DIESEL GENERATOR A - RUNNING GENERATOR A testing while in this AOP.

Go To Step 14.

c. Shutdown EMERGENCY DIESEL GENERATOR A. Using Applicable In-Progress Procedure
14. Log The Time That Any Of The Following Equipment Is Was Running Above 505 VOLTS:
  • INSTRUMENT AIR COMPRESSOR A
  • EDG A PRE-LUBE OIL PUMP
  • Fuel Oil Transfer Pump A
15. Check Emergency BUS E-l Voltage Go To Step 21.

- GREATER THAN EMERGENCY BUS E -2 VOLTAGE

16. Check Load On Emergency Bus E-2 Go To Step 18.

- HAS BEEN RAISED USING STEP 27

17. Go To Step 32.

Rev. 14 AOP-031 OPERATION WITH HIGH SWITCHYARD VOLTAGE Page 7 of 22 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

__STEP_H

18. Raise Load On Emergency Bus E-1 As Follows:
a. Check CHARGING PUMP B RUNNING a. Perform the following:
1) Start CHARGING PUMP B.
2) Stop CHARGING PUMP A C.
b. Verify CV RECIRC FANS -

RUNNING

  • HVH-1
  • HVH-2
c. Check CONT RM AIR HANDLING, c. Switch Control Room HVA-1A - RUNNING Ventilation to Train A using OP-906. Heating, Ventilation, and Air Conditioning.

Switching Control Room Ventilation System Unit in Service.

d. Check CRDM COOLING FAN. d. Transfer CRDM COOLING FANs as HVH-5A - RUNNING follows:
1) Start HVH-5A
2) Stop HVH-5B
e. Check AUX BLDG EXH FAN. e. Transfer AUX BLDG EXH FANs as HVE-2A - RUNNING follows:
1) Start HVE-2A
2) Stop HVE-2B
f. Check RHR - IN SERVICE f. Go To Step 19.
g. Check RHR PUMP A - RUNNING g. Start RHR Pump A by performing OP-201. Residual heat Removal System.

Switching RHR Pumps In The Core Cooling Mode.

Rev. 14 AOP-031 OPERATION WITH HIGH SWITCHYARD VOLTAGE Page 8 of 22

-Li-C ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED

  • 19. Check Emergecny BUS E-1 Voltage Emergency BUS E-1 voltage

- GREATER THAN 505 VOLTS rises to greater than 505 volts.

1IIN Go To Step 32.

Go To Step 21.

20. Go To Step 32 Check Emergency BUS E-2 Voltage j Emergency BUS E-2 voltage

- GREATER THAN 505 VOLTS exceeds 505 volts, THEN Observe the NQT prior to Step 22 and Go To Step 22.

Go To Step 33.

NOTE Transferring the following safety related components will cause voltage to rise. This step is designed to protect the components.

22. Check Instrument Air As Follows:
a. Check INSTRUMENT AIR a. Go To Step 23.

COMPRESSOR B - RUNNING IN MANUAL

b. Check One Of The Following b. Place One Of The Following Compressors IN SERVICE Compressors - IN SERVICE Using OP 905, Instrument And Using OP 905. Instrument And Station Air System Station Air System
  • INSTRUMENT AIR
  • INSTRUMENT AIR COMPRESSOR D COMPRESSOR D
  • PRIMARY AIR COMPRESSOR
  • PRIMARY AIR COMPRESSOR
c. Place INSTRUMENT AIR COMPRESSOR B in AUTO

Rev. 14 AOP-031 OPERATION WITH HIGH SWITCHYARD VOLTAGE Page 9 of 22

STEP H ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

23. Check EDG B Status As Follows:
a. Check Main Generator - ON LINE a. IF EDG B is Paralleled to Emergency Bus E-2, IIThN Go To Step 23.c Go To Step 24.
b. Check EMERGENCY DIESEL b. Postpone EMERGENCY DIESEL GENERATOR B - RUNNING GENERATOR B testing while in this AOP.

Go To Step 24.

c. Perform An Orderly Shutdown Of EMERGENCY DIESEL GENERATOR B, Using Applicable In-Progress Procedure
24. Log The Time That Any Of The Following Equipment Is Was Running Above 505 VOLTS
  • INSTRUMENT AIR COMPRESSOR B
  • EDG B PRE-LUBE OIL PUMP
  • Fuel Oil Transfer Pump B
25. Check Load On Emergency Bus E-l Go To Step 27.

- HAS BEEN RAISED USING STEP 18

26. Go To Step 28.

Rev. 14 AOP-031 OPERATION WITH HIGH SWITCHYARD VOLTAGE Page 10 of 22 STEP_H ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

27. Raise Load On Emergency BUS E-2 As Follows:
a. Check CHARGING PUMP C - a. Perform the following:

RUNNING

1) Start CHARGING PUMP C.
2) Stop CHARGING PUMP A , B.
b. Verify CV RECIRC FANS -

RUNNING

  • HVH-3
  • HVH-4
c. Check CONT RM AIR HANDLING, c. Switch Control Room HVA-1B - RUNNING Ventilation to Train B using OP-906. Heating, Ventilation, and Air Conditioning.

Switching Control Room Ventilation System Unit in Service.

d. Check CRDM COOLING FAN. d. Transfer CRDM COOLING FANs as HVI{-5B - RUNNING follows:
1) Start HVH-5B.
2) Stop HVH-5A.
e. Check AUX BLDG EXH FAN. e. Transfer AUX BLDG EXH FANs as HVE-2B - RUNNNING follows:
1) Start HVE-2B.
2) Stop HVE-2A.
f. Check RHR - IN SERVICE f. Go To Step 28.
g. Check RHR PUMP B - RUNNING g. Start RHR Pump B by performing OP-201. Residual Heat Removal System.

Switching RHR Pumps In The Core Cooling Mode.

Rev. 14 AOP-031 OPERATION WITH HIGH SWITCHYARD VOLTAGE Page 11 of 22 j STEP_H ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED I

  • 28. Check Emergency BUS E-2 Voltage IE Emergency BUS E-2 voltage

- GREATER THAN 505 VOLTS rises to greater than 505 volts, Go To Step 29.

Go To Step 33.

29. Check DSDG Status As Follows:
a. Check Main Generator - ON LINE a. Go To Step 30.
b. Check DSDG - RUNNING b. Postpone DSDG testing while in this AOP.

Go To Step 30.

c. Stop the DSDG. using Applicable In-Progress Procedure
30. Check 4KV BUS 3-4 TIE, BKR 52/19 Go To Step 32.

- OPEN

Rev. 14 AOP-031 OPERATION WITH HIGH SWITCHYARD VOLTAGE Page 12 of 22 H__STEP_H ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED I

31. Transfer 4160V BUS 4 To The STARTUP TRAI4SFORMER As Follows:
a. Insert the Synchroscope Key into 4 KV TIES Synchroscope Key Switch
b. Place the Synchroscope Switch to the BUS 3 & 4 position
c. Verify the Synchroscope comes to approximately the 12 oclock position
d. Momentarily place the Control Switch for 4KV BUS 3-4 TIE, BKR 5 2/19 to the CLOSE position
e. Check BKR 52/19 - CLOSED e. Contact I&C to check BKR 52/19.

Go To Step 31.g.

f. Check UNIT AUX TO 4KV BUS 4 f. Perform the following:

BKR, 52/20 - OPEN

  • Simultaneously depress the THINK pushbutton ANP place the control switch for BKR 52/20 to the OPEN position.

OR

  • Using the Control Switch At 4160V BUS 4, open BKR 52/20. UNIT AUX TO 4KV BUS 4.

OR

  • Inside Cubicle 20 trip BKR 52/20 by lifting the trip tab at the bottom of the breaker.
g. Place the 4 KV TIES Synchroscope Key Switch to the mid position

Rev. 14 AOP-031 OPERATION WITH HIGH SWITCHYARD VOLTAGE Page 13 of 22

STEP_H ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED I

32. Check The Following: Start additional plant loads as follows:
  • Emergency BUS E-1 Voltage LESS THAN 505 VOLTS a. Evaluate present plant conditions for idle loads.

AND

b. Balance loads started such
  • Emergency BUS E-2 Voltage - that voltage on BUSSES E-l LESS THAN 505 VOLTS AND E-2 are equalized.
c. Minimize the run time of the components listed below:
  • INSTRUMENT AIR COMPRESSOR A AND B
d. Using the applicable plant procedure, start idle loads.
  • 33 Check Voltage As Follows: APP-036-E3 is Extinguished, West 115KV Bus voltage is less
  • APP-036-E3, SUT PRI than 119 KV, and Emergency BUS OVER/UNDER VOLTAGE - E-1 AND Emergency BUS E-2 EXTINGUISHED voltage are less than 502 volts, i Go To Step 34.

AND Go To Step 10.

LESS THAN 119 KV AND

  • Emergency BUS E-1 Voltage -

LESS THAN 502 VOLTS AND

  • Emergency BUS E-2 Voltage -

LESS THAN 502 VOLTS

34. Terminate Monitoring Of Emergency BUS E-1 E-2 Voltage
35. Record In The Control Operators Log The Duration That Each Emergency Bus Was Greater Than 505 VOLTS

Rev. 14 AOP-031 OPERATION WITH HIGH SWITCHYARD VOLTAGE Page 14 of 22 H__STEP_H ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED I

36. Determine If Auxiliaries Should Be Transferred As Follows:
a. Check UNIT AUXILIARY a. Go To Step 38.

TRANSFORMER - AVAILABLE

b. Check 4KV BUS 3-4 TIE. BKR b. Go To Step 38.

52/19 - CLOSED

Rev. 14 AOP-03l OPERATION WITH HIGH SWITCHYARD VOLTAGE Page 15 of 22 H__STEP H ACTION/EXPECTED RESPONSE E I RESPONSE NOT OBTAINED CAUTION SAP NGCC, Electrical Safety and Arc Flash Protection, Must be reviewed for operation of breakers locally.

37. Transfer 4160V BUS 4 To The UNIT AUXILIARY TRANSFORMER As Follows:
a. Insert the Synchroscope Key into UNIT AUX TRANSF Synchroscope Key Switch
b. Place the Synchroscope Switch to the UNIT AUX BUS 4 position
c. Verify the synchroscope comes to approximately the 12 oclock position
d. Momentarily place the Control Switch for UNIT AUX TO 4KV BUS 4, BKR 52/20 to the CLOSE position
e. Check BKR 52/20 - CLOSED e. Perform the following:
1) Contact I&C to check BKR 52/20.
2) Initiate an Operability Determination due to 4KV BUS 4 being powered from the SUT.
3) When BKR 52/20 is closed, IIIN Go To Step 37.f.

(CONTINUED NEXT PAGE)

Rev. 14 AOP-031 OPERATION WITH HIGH SWITCHYARD VOLTAGE Page 16 of 22 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

__STEP_H

37. (CONTINUED)
f. Check 4KV BUS 3-4 TIE BKR, f. Perform the following:

52/19 - OPEN

  • Simultaneously depress the THINK pushbutton AND place the Control Switch for BKR 52/19 to the OPEN position.

OR

  • Using the Control Switch At 416OV BUS 4, open BKR 52/19, 4KV BUS 3-4 TIE.

OR

  • Inside Cubicle 19 trip BKR 52/19 by lifting the trip tab at the bottom of the breaker.
g. Place the UNIT AUX TRANSE Synchroscope Key Switch to the mid position
38. Restore The Following Electrical Lineups As Directed By The SM
  • CCW Pumps A and B,
  • Instrument Air Compressors A

&B

  • Any loads started or shifted as part of Steps 11 - 13. 22

- 23. AND 32

39. Restore Routine Testing Of The Emergency Diesel Generators D The DS Diesel Generator
40. Return To Procedure And Step In Effect

- END -

Rev. 14 AOP-031 OPERATION WITH HIGH SWITCHYARD VOLTAGE Page 17 of 22 CONTINUOUS USE ATTACHMENT 1 OBTAINING EMERGENCY BUS VOLTAGE USING A VOLTMETER (Page 1 of 3)

CAUTION Circuits inside Emergency BUS E-1 ANP. E-2 are energized and exposed.

Proper precautions shall be followed when working on or near energized circuits.

NOTE

  • This attachment is written to be used by an I&C Technician locally at Emergency Bus E-l AND E-2.
  • Steps 1 through 6 give the directions for obtaining voltage on Emergency BUS E1. Steps 9 through 13 are for Emergency BUS E-2.
1. Obtain a Fluke 8520A Digital Voltmeter (or similar meter with an accuracy of +/- 1.75 volts @ 100 volts).
2. IF obtaining voltage on Emergency BUS E-1 is unnecessary. IIIN Go To Step 9.
3. Open the door of Metering Cubicle 17A on Emergency BUS E1.
4. Select the appropriate range on the multimeter to allow reading at least 125 volts AC.
5. Clamp or lug the multimeter probes to the input terminals of the local voltmeter (EI-213) inside Cubicle 17A.
6. Notify the Control Room that Emergency BUS E-l voltage readings may now be taken.

Rev. 14 AOP-031 OPERATION WITH HIGH SWITCHYARD VOLTAGE Page 18 of 22 CONTINUOUS USE ATTACHMENT 1 OBTAINING EMERGENCY BUS VOLTAGE USING A VOLTMETER (Page 2 of 3)

7. Take voltage readings at hourly intervals or as directed by the Control Room as follows:
a. Use the BUS E-l VOLTMETER SWITCH on the front of Cubicle l7A to select one of the three phases.
b. Multiply the multimeter reading by 4 and report the voltage to the Control Room.
c. Repeat Step 7.a and 7.b for each of the three phases.

. MULTIMETER READING X 4 = VOLTAGE

8. WII1I notified by the Control Room that voltage monitoring is no longer required, IIEI restore as follows:
a. Remove the multimeter probes from the local voltmeter (EI-2l3).
b. Close the door on Cubicle 17A.
c. Read each phase on the installed bus voltmeter (EI-213) to ensure circuit operability.
d. Notify the Control Room that Bus E-l has been restored to normal and that this Attachment is complete.
9. Obtain a Fluke 852OA Digital Voltmeter (or similar meter with an accuracy of +/- 1.75 volts @ 100 volts).
10. Open the door of Metering Cubicle 27A on Emergency BUS E-2.
11. Select the appropriate range on the multimeter to allow reading at least 125 volts AC.
12. Clamp or lug the multimeter probes to the input terminals of the local voltmeter (EI-214) , inside Cubicle 27A.

13, Notify the Control Room that Emergency BUS E-2 voltage readings may now be taken.

Rev. 14 AOP-031 OPERATION WITH HIGH SWITCHYARD VOLTAGE Page 19 of 22 CONTINUOUS USE ATTACHMENT 1 OBTAINING EMERGENCY BUS VOLTAGE USING A VOLTMETER (Page 3 of 3)

14. Take voltage readings at hourly intervals or as directed by the Control Room as follows:
a. Use the BUS E-2 VOLTMETER SWITCH on the front of Cubicle 27A to select one of the three phases.
b. Multiply the multimeter reading by 4 and report the voltage to the Control Room.
c. Repeat Step l4.a and l4.b for each of the three phases.

. MULTIMETER READING X 4 = VOLTAGE

15. WHEN notified by the Control Room that voltage monitoring is no longer required. restore as follows:
a. Remove the multimeter probes from the local voltmeter (EI-2l4).
b. Close the door on Cubicle 27A.
c. Read each phase on the installed bus voltmeter (EI-2l4) to ensure circuit operability.
d. Notify the Control Room that Bus E2 has been restored to normal and that this attachment is complete.

- END -

Rev. 14 AOP-031 OPERATION WITH HIGH SWITCHYARD VOLTAGE Page 20 of 22 CONTINUOUS USE ATTACHMENT 2A Continuous Action Steps (Page 1 of 1)

7. WHEN I&C has commenced obtaining voltage with Attachment 1, THEN discontinue use of local indication.
10. IF Emergency BUS E-1 voltage exceeds 505 volts, THEN observe the NOTE prior to Step 11 and Go To Step 11.
19. IF Emergency BUS E-1 voltage rises to greater than 505 volts. THEN Go To Step 32.
21. IF Emergency BUS E-2 voltage exceeds 505 volts, THEN Observe the NOTE prior to Step 22 and Go To Step 22.
28. IF Emergency BUS E-2 voltage rises to greater than 505 volts. THEN Go To Step 29.
33. WHEN APP-036-E3 is Extinguished, West 115KV Bus voltage is less than 119 Ky. and 480V BUS E-l AND 480V BUS E-2 voltage are less than 502 volts. THEN Go To Step 34.

Rev. 14 AOP-031 OPERATION WITH HIGH SWITCHYARD VOLTAGE Page 21 of 22 CONTINUOUS USE ATTACHMENT 2B Continuous Action Steps (Page 1 of 1)

7. WHEN I&C has commenced obtaining voltage with Attachment 1, THEN discontinue use of local indication.
10. IF Emergency BUS E-l voltage exceeds 505 volts, THEN observe the NOTE prior to Step 11 and Go To Step 11.
19. IF Emergency BUS E-l voltage rises to greater than 505 volts, THEN Go To Step 32.
21. IF Emergency BUS E-2 voltage exceeds 505 volts. THEN Observe the NOTE prior to Step 22 and Go To Step 22.
28. IF Emergency BUS E-2 voltage rises to greater than 505 volts, THEN Go To Step 29.
33. WHEN APP-036--E3 is Extinguished, West 115KV Bus voltage is less than 119 KV, and 480V BUS E-l AND 480V BUS E-2 voltage are less than 502 volts, THEN Go To Step 34.

AOP-031, Revision 14 Summary of Changes (PRR 512566)

Main Body Step 12.b Reworded this step to allow for equalizing run time between Instrument Air Compressor D and the Primary Air Compressor.

This is consistent with the operating procedure, OP-905.

(PRR 512566)

Step 13.a Added this guidance to address the possibility that RNO Emergency Diesel Generator A is paralleled to Emergency Bus E-l with the Main Generator off line. (PRR 463792)

Step 15 This step is being added to prioritize the sequence of steps being performed.

Steps 16 Steps added to direct procedure flow path based on the and 17 possibility that Emergency Bus E-2 Load has already been raised per step 27.

Steps 18, Added these steps to provide guidance for raising load on 19 and 20 Emergency Bus E-1 in the event that E-1 voltage is greater than 505 volts. This guidance is similar to steps already in the procedure for raising load on Emergency Bus E-2.

(PRR 512566)

Step 22.b Reworded this step to allow for equalizing run time between Instrument Air Compressor D and the Primary Air Compressor.

This is consistent with the operating procedure. OP-905.

(PRR 512566)

Step 23.a Added this guidance to address the possibility that RNO Emergency Diesel Generator B is paralleled to Emergency Bus E-2 with the Main Generator off line. (PRR 463792)

Steps 25 Steps added to direct procedure flow path based on the and 26 possibility that Emergency Bus E-l Load has already been raised per step 18.

AOP03l Rev. 14 Page 22 of 22

LICENSE EXAMINATION JOB PERFORMANCE MEASURE ILC-13 NRC JPM G RevO Respond to a Loss of CCW JAW AOP-014 Concurred By: Kirk Schauer Date: 5/15/13 Operations Approved By: James Conder Date: 6/5/13 Superintendent/Supervisor Training

ILC-13 NRC JPM G Page 2 of 19 LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task: 01093109404 Respond to a Complete Loss of CCW Surge Tank Level lAW AOP-014.

Alternate Path:

NO JPM #: Candidate ILC-13 NRC JPM G RO/SRO K/A Rating (ROISRO):

008K1.02 3.3 /3.4 008K3.03 4.1 /4.2 026AK3.03 4.0 I 4.2 Task Standard:

AOP-014 actions taken to ensure the RCPs are not damaged.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate

References:

AOP-014 Validation Time: 10 Minutes Time Critical: NO Time Critical Time: N/A Candidate: (N/A if not time critical)

Name Overall Critical Time Time SSN Start: Start:

Finish: Finish:

Performance Rating: UNSAT Performance SAT circle one Time (mm)

Examiner:

Print Name Signature Date

ILC-13 NRC JPM G Page 3 of 19 COMMENTS:

QUESTION DOCUMENTATION:

Question:

Response

ILC-13 NRC JPM G Page 4 of 19 COMMENTS Step 7 Critical in order to prevent challenging a safety function prior to securing the RCPs.

Step 8 Critical in order to prevent over-heating of pump motor bearing.

Step 10 Critical to prevent the CCW pumps for auto-starting due to low pressure.

Step 22 Critical since this will isolate the CCW break in containment.

ILC-13 NRC 3PM G Page 5 of 19 SIMULATOR OPERATOR INSTRUCTIONS:

1. Initialize the simulator to Ic-i 3
2. Go to RUN ensure plant conditions are stable.
3. Place simulator in FREEZE until candidate is ready to begin the JPM.
4. Open SCN File: 009_ILC_13_NRC_CR_JPMG
5. An extra instructor will be needed to acknowledge alarms that do not apply to this JPM and to assist with locking out the CCW Pumps (if assistance requested).

ILC-13 NRC JPM G Page 6 of 19 ToolslEguipmentProcedures Needed:

APP-001-A4 AOP-014, COMPONENT COOLING WATER SYSTEM MALFUNCTION DIRECTIONS TO CANDIDATE:

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 facilitate the examination and better enable me to assess your level of understanding, verbalize your actions and observations while performing the JPM. To indicate that you have completed your assigned task return the Candidate Cue Sheet I provided you.

CANDIDATE INFORMATION:

Inform the candidate there are NO time critical steps in this JPM.

INITIAL CONDITIONS:

1. The plant is operating at 100% power.
2. No equipment is out of service.
3. You are the Reactor Operator.

INITIATING CUES:

Respond to plant conditions.

ILC-13 NRC JPM G Page 7 of 19 START TIME:

TEP 1:

1 Candidate refers to APP-001-A4 SAT STANDARD: Candidate observes rapidly lowering CCW Surge Tank Level Candidate takes recommended action from APP-00 1 -A4 and enters AOP 014, CCW System Malfunction. UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

TEP 2: Implement the EALs (Main Body Step 1)

STANDARD: Candidate notifies supervision of EAL implementation. SAT EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM G Page 8 of 19 NOTE

. A loss of inventory may be indicated by a report of leakage or lowering of surge tank level.

. CCW Pump discharge pressure less than 78 psig will cause an alarm.

. CCW low flow is defined as less than 2200 gal per pump.

. CCW high temperature is defined as greater than 105°F or greater than 125°F if in Mode 3.

STEP 3: Make PA Announcement for Procedure Entry.

(Main Body Step 2)

SAT STANDARD: Candidate makes announcement for AOP-014 entry using the PA system.

EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 4: Go to Appropriate Section for Indicated Malfunction.

(Main Body Step 3)

SAT STANDARD: Candidate determines that the appropriate section is Section A based on loss of CCW inventory.

EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM G Page 9 of 19 STEP 5: Determine if pump cavitation is Occurring OR Imminent:

  • Check Surge Tank Level Less Than 5%.

OR

  • Check CCW Pump Discharge Pressure (Local) AND Flow -WIDE SAT OSCILLATIONS.

(Section A Step 1)

STANDARD: Candidate determines that CCW Surge Tank is less than 5% level and that UNSAT pump cavitation is imminent.

EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 6: Check Reactor CRITICAL (Section A Step 2)

STANDARD: Candidate determines that the Reactor is critical. SAT EXAMINERS CUE: NONE EXAMINERS NOTE: NONE UNSAT BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM G Page 10 of 19 STEP 7: Verify Reactor TRIPPED

- CRITICAL (Section A Step 3) STEP STANDARD: Candidate depresses the Reactor Trip pushbutton to trip the Reactor and verifies the Reactor is tripped.

SAT EXAMINERS CUE: NONE EXAMINERS NOTE: NONE UNSAT BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 8: Stop ALL RCPs CRITICAL (Section A Step 4) STEP STANDARD: Candidate stops ALL Reactor Coolant Pumps using the Control Switches on the RTGB and verifies they are stopped by observing the GREEN off light is illuminated. SAT EXAMINERS CUE: NONE EXAMINERS NOTE: NONE UNSAT BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM G Page 11 of 19 STEP 9: Go to EOP-E-O, Reactor Trip or Safety Injection, while Continuing with this Procedure.

(Section A Step 5)

SAT STANDARD: Candidate informs CRS to enter EOP-E-O while the Candidate continues in AOP-014.

EXAMINERS CUE: Cue or acknowledge the candidate that the CRS and the BOP will UNSAT continue in EOP-E-O and the RO will continue in AOP-014.

EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 10: Lockout CCW Pumps As Follows: CRITICAL

a. Place AND hold all CCW Pump switches in STOP position. STEP
b. Check APP-001F5, CCW PMP LO PRESS ILLUMiNATED
c. Release CCW Pump Switches.
d. GotoStepl3 (Section A Step 6) SAT STANDARD: Candidate places ALL CCW pump switches to STOP and holds them while verifying APP-OO 1 -F5 is illuminated.

UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: Inform the Candidate that he may ask and receive assistance from the BOP to hold one of the CCW Pump Switches, if desired BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM G Page 12 of 19 STEP 11: Dispatch Operator to Perform Attachment 3, CCW Leak Search, While Continuing With Procedure.

(Section A Step 13)

SAT STANDARD: Candidate contacts the AO to perform Attachment 3 to identify the source of the leak.

EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: Acknowledge direction to perform Attachment 3.

COMMENTS:

STEP 12: Determine if RHR Must be Stopped as Follows:

a. Check CCW Pumps ALL STOPPED
b. Check RHR Pump status ANY PUMP RUNNING IN CORE COOLING MODE SAT RNO: Observe the NOTE prior to Step 18 and Go to Step 18.

(Section A Step 14)

STANDARD: Candidate recognizes that all CCW pumps are stopped (from previous UNSAT step) and determines that the RHR pumps are not in Core Cooling Mode.

EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM G Page 13 of 19 NOTE IF the location of the leak is known AND isolation is possible, THEN leak isolation may be commenced immediately.

STEP 13: Check CV for CCW Break Using Control Room Indications As Follows:

a. Monitor the following CV indications:
  • CV WATER LEVEL (White Sump Lights) SAT
  • LI-801, CHANNEL I CV WATER LEVEL
  • LI-802, CHANNEL II CV WATER LEVEL
  • RCP Abnormal Conditions
  • Check APP-OO1-F5, CCW PMP LO PRESS ILLUMiNATED UNSAT (Section A Step 18.a)

STANDARD: Candidate monitors ERFIS trends and CV WATER LEVEL (White Sump Lights) and determines that CV water level has increased.

EXAMINERS NOTE: CV Water level rises from 4.00 inches and stabilizes at a higher value.

Bottom white lights for CV Keyway Sump are illuminated.

BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 14: Check CV for CCW Break Using Control Room Indications As Follows:

b. Check CV LOCATION OF CCW BREAK (Section A Step 1 8.b)

SAT STANDARD: Candidate determines that CCW leak is in the CV.

EXAMINERS NOTE: NONE UNSAT BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM G Page 14 of 19 STEP 15: Check CV for CCW Break Using Control Room Indications As Follows:

c. Inform personnel performing leak search that the leak location is in CV.

(Section A Step 18.c) SAT STANDARD: Candidate informs AO performing leak search of leak in CV.

EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 16: Determine RCP Alarm Status:

a. Check APP-OO1-B1, RCP BRG COOL WTR LO FLOW -

ILLUMINATED (Section A Step 19.a) SAT TANDARD: Candidate determines that APP-OO1-B1 is illuminated.

EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM G Page 15 of 19 STEP 17: Determine RCP Alarm Status:

b. Check ANY RCP BEARiNG HI TEMP Alarm ILLUMINATED
  • APP-001-D3 OR
  • APP-001-F3.

RNO: UNSAT IF makeup capacity to the CCW Surge Tank is sufficient to maintain level, THEN Go to Step 64.

IF makeup capacity to the CCW Surge Tank is NOT sufficient to maintain level, THEN Go to Step 20.

(Section A Step 1 9.b)

STANDARD: Candidate recognizes that NO RCP BEARING HI TEMP Alarm is illuminated and that makeup capacity to CCW Surge Tank is not sufficient. Transitions to Step 20.

EXAMINERS CUE: NONE EXAMINERS NOTE: NONE 300TH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM G Page 16 of 19 STEP 18: Check Reactor Critical:

(Section A Step 20)

STANDARD: Candidate determines that the reactor is NOT critical. SAT EXAMINERS CUE: NONE EXAMINERS NOTE: NONE UNSAT BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 19: Perform the following:

a. Verify Control Rods Tripped.

(Section A RNO Step 20.a)

SAT STANDARD: Candidate verifies that ALL Control Rods are inserted.

EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM G Page 17 of 19 STEP 20: Perform the following:

b. Stop ALL RCPs.

(Section A RNO Step 20.b)

SAT STANDARD: Candidate verifies that ALL Reactor Coolant Pumps are stopped.

EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 21: Perform the following:

c. IF Control Rods were inserted on the trip, THEN perform the following:
1) [F RCS temperature is greater than OR equal to 3 50°F, THEN SAT Go to Step 23.
2) IF RCS temperature is less than 350°F, THEN Go to Step 24.
d. IF Control Rods were already inserted, THEN Go to Step 24.

(Section A RNO Step 20.c and d) UNSAT STANDARD: Candidate determines that the Control Rods were already inserted and transitions to Step 24.

EXAMINERS CUE: NONE EXAMINERS NOTE: If candidate mis-reads the step and transitions to Step 23 acknowledge the report to go to EOP-E-0 and inform candidate that the CRS and BOP are continuing in EOP-E-0. Direct candidate to continue in AOP-014.

BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM G Page 18 of 19 STEP 22: Close the Following Valves to Isolate CCW to the RCPs: CRITICAL

  • FCV-626, THERM BAR FLOW CONT (Section A Step 24)

STANDARD: Candidate uses RTGB switches to close the following valves: {JNSAT

  • FCV-626, THERM BAR FLOW CONT EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

END OF TASK I Terminating Cue: When CCW valves are closed to isolate CCW piping rupture in CV I TIME STOP:

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

CANDIDATE INFORMATION:

Inform the candidate there are NO time critical steps in this JPM.

INITIAL CONDITIONS:

1. The plant is operating at 100% power.
2. No equipment is out of service.
3. You are the Reactor Operator.

INITIATING CUES:

Respond to plant conditions.

LICENSE EXAMINATION JOB PERFORMANCE MEASURE ILC-13 NRC JPM H RevO Fill a Safety Injection Accumulator JAW OP-202 Concurred By: Pat Lathrop Date: 5/15/13 Operations Approved By: James Conder Date: 6/5/13 Superintendent/Supervisor Training

ILC-13 NRC JPM H Page 2 of 15 LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task: 01006100301 Fill the SI Accumulators JAW OP-202 Alternate Path:

NO JPM #: Candidate ILC-13 NRC JPM H RO/SRO K/A Rating (RO/SRO):

006 A4.01 4.1 /3.9 006 A4.02 4.0/3.8 006 A1.07 3.3/3.6 006 A1.13 3.5 /3.7 Task Standard:

SI Accumulator C filled to reset the low level alarm without exceeding specified limits.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator X In-Plant PerformX Simulate

References:

OP-202, Section 8.2.1, Filling the Safety Injection Accumulators Validation Time: 12 Minutes Time Critical: NO Time Critical Time: N/A Candidate: (N/A if not time critical)

Name Overall Critical Time Time SSN Start: Start:

Finish: Finish:

Performance Rating: SAT U1TSAT Performance circle one Time (mm):

Examiner:

Print Name Signature Date

ILC-13 NRC JPM H Page 3 of 15 COMMENTS:

QUESTION DOCUMENTATION:

Question:

Response

ILC-13 NRC JPM H Page 4 of 15 COMMENTS Step 2 Critical because control power must be aligned to the valve to allow for RTGB operation.

Step 4 Critical to open valve to align flowpath to SI Accumulator.

Step 5 Critical to start pump to provide adequate flow and pressure to fill the SI Accumulator.

Step 7 Critical to align fill path to appropriate accumulator and to secure filling at desired level without exceeding specified limits.

Step 8 Critical to secure fill source and prevent operating on recirculation for an extended period.

Step 10 Critical to realign S1-869 to its normal Mode 1 alignment.

Step 11 Critical to properly align SI-869 Control Power Defeat Switch as required for Mode 1.

ILC-13 NRC JPM H Page 5 of 15 SIMULATOR OPERATOR INSTRUCTIONS:

1. Initialize the simulator to IC-9 18
2. Go to RUN ensure plant conditions are stable.
3. No SCN required.
4. Place simulator in FREEZE until candidate is ready to begin the JPM.
5. Marked up copy of OP-202, Section 8.2.1, with Initial Conditions 8.2.1.1.a through 8.2.1.1.f.2 completed.

ILC-13 NRC JPM H Page 6 of 15 Tools/Equipment/Procedures Needed:

OP-202, Section 8.2.1 DIRECTIONS TO CANDIDATE:

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 facilitate the examination and better enable me to assess your level of understanding, verbalize your actions and observations while performing the JPM. To indicate that you have completed your assigned task return the Candidate Cue Sheet I provided you.

CANDIDATE INFORMATION:

Inform the candidate there are NO time critical steps in this JPM.

INITIAL CONDITIONS:

1. The plant is operating at 100% RTP.
2. SI ACCUM C HI/LO LVL (APP-002-E4) alarm has been received and actions have been reviewed by the RO.
3. OP-202, Section 8.2.1.1 Initial Conditions have been completed.
4. Refueling Water Purification is NOT in progress.
5. You are the Licensed Dedicated Operator referred to in OP-202.
6. Safety Injection Pump A has been walked down and pre-start checks are complete.

INITIATING CUES:

The CRS has briefed and directed you to fill SI Accumulator C to reset the low level alarm JAW OP-202, Section 8.2.1.

ILC-13 NRC JPM H Page 7 of 15 START TIME:

TEP 1: Check open SI-856A, SI PUMP RECIRC and SI-856B, SI PUMP RECIRC (Steps 8.2.1.2.a and b).

SAT STANDARD: Valves SI-856A and B checked OPEN by observing the RED open indication on the RTGB.

UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: The candidate may use ERFIS to monitor SI Accumulator C level. (ERFIS: QP ACCUM C)

BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM H Page 8 of 15 STEP 2: Verify the Control Power Defeat Switch for SI-869 is in the NORMAL CRITICAL position. (Step 8.2.1 .c) STEP STANDARD: Locates NORMAL / DEFEAT key switch behind the RTGB for SI-869 and places the switch in the NORMAL position and identifies the amber SAT light above the key switch is illuminated.

EXAMINERS CUE: If the candidate requests an AO check breaker status, report that all UNSAT requested breakers are open.

EXAMINERS NOTE: Key switch for S1-869 is located in the rear of the RTGB on the ECCS VALVES CONTROL POWER DEFEAT PANEL.

BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM H Page 9 of 15 NOTE: Based upon the numerous indications available to the Dedicated Operator of an SI actuation at the RTGB and the immediate response to isolate the SI Accumulator flowpath, an LCO declaration for SI Pump OR SI Flowpath Operability is NOT required.

The following step is a continuous action step which shall be performed when the stated condition is met.

STEP 3: IF an SI actuation is received during filling, THEN IMMEDIATELY CLOSE the applicable SI Accumulator makeup valve AND PERFORM Step 8.2.1.2.m to restore the SI System lineup. (Step 8.2.l.d)

SAT STANDARD: Candidate reads step and acknowledges continuous actions step in the event of an SI actuation.

UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 4: Open SI-869, SI HOT LEG HDR. (Step 8.2.1.2.e) CRITICAL STEP STANDARD: Valve SI-869 opened by placing the control switch to the OPEN position and noting GREEN closed light extinguished and RED open light illuminated. SAT EXAMINERS CUE: NONE EXAMINERS NOTE: NONE UNSAT BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM H Page 10 of 15 STEP 5: Start an SI Pump. (Step 8.2.1.2.0 CRITICAL STEP STANDARD: SI Pump A started by placing the control switch to the START position and observing the RED operating light illuminated and the GREEN stopped light extinguished.

SAT EXAMINERS NOTE: NONE UNSAT BOOTH OPERATOR CUE: NONE COMMENTS:

NOTE: If the cooling unit for the train of the SI pump started is NOT operable, the opposite train unit can be started by placing its AUTO/RUN switch on the power supply breaker to RUN.

STEP 6: Verify at least one SI Pump Area Cooling unit (HVH-6A OR HVH-6B OR both) is operating. (Step 8.2.1 .2.g)

,TANDARD: HVH-6A and/or 6B verified operating by noting RED operating light SAT illuminated on the HVAC display panel and the GREEN off light extinguished.

EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM H Page 11 of 15 NOTE: The following are pressure and level limits/alarms for the SI Accumulators:

. High Pressure Alarm 646 psig

. Normal Operating Pressure 630 psig

. High Level Alarm 75 percent

. Low Level Alarm 67 percent CAUTION Filling the SI Accumulators can result in rapid indicated level changes due to the narrow span (approx. 14 inches) associated with the SI Accumulator level instruments and should be closely monitored.

STEP 7: IF SI Accumulator C is to be filled, THEN perform the following: CRITICAL (Step 8.2.1.2.j) STEP

1) Open SI-851C, MAKEUP.
2) Monitor the level and pressure of SI Accumulator C.
3) When desired level is obtained, then close SI-851C.

SAT STANDARD:

1) Valve SI-851C opened by placing the control switch to the OPEN position and observing the RED open light illuminated and the GREEN closed light extinguished. UNSAT
2) Maintained> 614 psig and < 646 psig pressure limits as indicated on P1-929/931 and refills accumulator to> 67% and < 75% level limits as indicated on LI-928/930.
3) Valve SI-851C closed by placing the control switch to the CLOSED position.

EXAMINERS CUE: NONE EXAMINERS NOTE:

BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM H Page 12 of 15 STEP 8: Stop the operating SI Pump. (Step 8.2.1.2.k) CRITICAL STEP STANDARD: Operating SI Pump stopped by placing the control switch to STOP and switch returned to the MID position.

EXAMINERS CUE: NONE SAT EXAMINERS NOTE: NONE UNSAT BOOTH OPERATOR CUE: NONE COMMENTS:

STEP 9: Verify both SI Pump Area Cooling units are OFF. (Step 8.2.1.2.1)

1) HVH-6A
2) HVH-6B SAT STANDARD: Verifies HVH-6A and 6B are OFF by noting RED operating light extinguished on the HVAC display panel and the GREEN off light illuminated.

UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM H Page 13 ofl5 STEP 10: Close SI-869, SI HOT LEG HDR. (Step 8.2.1.2.m) CRITICAL STEP TANDARD: Valve SI-869 closed by placing the control switch to the CLOSED position and observing the GREEN closed light illuminated and the RED open light extinguished.

SAT EXAMINERS CUE: IF an independent verification of valve SI-869 is requested, inform the candidate that the valve has been independently verified.

UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

NOTE: In Mode 1, 2 OR 3 the Control Power Defeat switch for SI-869 should be in the DEFEAT position.

In Mode 5 OR 6 the Control Power Defeat switch for SI-869 should be in the NORMAL position. In Mode 4 the position of the Control Power Defeat switch for SI-869 is determined by GP-002 OR GP 007.

STEP 11: Verify the Control Power Defeat switch for SI-869 in the position CRITICAL determined by plant status. (Step 8.2.1.2.n) STEP STANDARD: With the plant in Mode 1, valve SI-869 control power switch positioned to DEFEAT and identify the amber light above the switch is extinguished.

Candidate will circle the word DEFEAT as the restored position. SAT EXAMINERS CUE: IF an independent verification of valve SI-869 Control Power switch is requested, inform the candidate that the switch has been independently verified. UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM H Page 14 of 15 STEP 6: IF the Refueling Water Purification Pump was stopped in Step 8.2.1.1 .f, THEN perform the following: (Step 8.2.1.2.o)

1) Open SFPC-805B, RWST RETURN. SAT
2) Start the Refueling Water Purification Pump.

STANDARD: Candidate determines that the RWST purification was NOT in progress from the initial conditions and places N/As in these steps. UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

END OF TASK I Terminating Cue: SI Accumulator C has been filled to clear the low level alarm. I TIME STOP:

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

CANDIDATE INFORMATION:

Inform the candidate there are NO time critical steps in this JPM.

INITIAL CONDITIONS:

1. The plant is operating at 100% RTP.
2. SI ACCUM C HI/LO LVL (APP-002-E4) alarm has been received and actions have been reviewed by the RO.
3. OP-202, Section 8.2.1.1 Initial Conditions have been completed.
4. Refueling Water Purification is NOT in progress.
5. You are the Licensed Dedicated Operator referred to in OP-202.
6. Safety Injection Pump A has been walked down and prestart checks are complete.

INITIATING CUES:

The CRS has briefed and directed you to fill SI Accumulator C to reset the low level alarm lAW OP-202, Section 8.2.1.

CONTINUOUS USE Section 8.2.1 Page 1 of 5 INIT 8.2 Normal Operation 8.2.1 Filling the Safety Injection Accumulators

1. Initial Conditions
a. This revision has been verified to be the latest revision available.
b. A Safety Injection Pump is available for filling the SI Accumulator(s).
c. An SI Accumulator needs to be refilled OR the level raised to restore or maintain the TECH SPECS limit of 61.5 percent.

9

d. IF RCS pressure is less than 650 psig, THEN VERIFY the accumulator discharge valve(s)

(SI-865A1B/C, DISCH) of the accumulator(s) to be filled are CLOSED.

e. A licensed Dedicated Operator is available to fill the SI Accumulator(s) and isolate the accumulator(s) makeup flowpath if a Safety Injection actuation occurs.
f. IF Refueling Water Purification is in progress, THEN PERFORM the following:
1) STOP the Refueling Water Purification Pump. .4.174
2) CLOSE SFPC-805B, RWST RETURN.

OP-202 Rev. 94 Page 13 of 131

Section 8.2.1 Page 2 of 5 8.2.1 (continued) INIT

2. Instructions
a. CHECK OPEN SI-856A, SI PUMP RECIRC.
b. CHECK OPEN SI-856B, SI PUMP RECIRC.
c. VERIFY the Control Power Defeat switch for Sl-869 is in the NORMAL position.

NOTE: Based upon the numerous indications available to the Dedicated Operator of an SI actuation at the RTGB and the immediate response to isolate the SI Accumulator flowpath, an LCO declaration for SI Pump OR SI Flowpath Operability is NOT required.

The following step is a continuous action step which shall be performed when the stated condition is met.

d. IF an SI actuation is received during filling, THEN IMMEDIATELY CLOSE the applicable SI Accumulator makeup valve AND PERFORM Step 8.2.1.2.m to restore the SI System lineup.
e. OPEN SI-869, SI HOT LEG HDR.
f. START an SI Pump.

NOTE: If the cooling unit for the train of the SI pump started is NOT operable, the opposite train unit can be started by placing its AUTO/RUN switch on the power supply breaker to RUN.

g. VERIFY at least one SI Pump Area Cooling unit (HVH-6A OR HVH-6B OR both) is operating.

OP-202 Rev. 94 Page 14 of 131

Section 8.2.1 Page 3 of 5 8.2.1.2 (Continued) INIT NOTE: The following are pressure and level limits/alarms for the SI Accumulators:

- High Pressure Alarm 646 psig

- Normal Operating Pressure 630 psig

- High Level Alarm 75 percent

- Low Level Alarm 67 percent CAUTION Filling the SI Accumulators can result in rapid indicated level changes due to the narrow span (approx. 14 inches) associated with the SI Accumulator level instruments and should be closely monitored.

h. IF SI Accumulator A is to be filled, THEN PERFORM the following:
1) OPEN SI-851A, MAKEUP.
2) MONITOR the level and pressure of SI Accumulator A.
3) WHEN desired level is obtained, THEN CLOSE Sl-851A.

IF SI Accumulator B is to be filled, THEN PERFORM the following:

1) OPEN SI-851B, MAKEUP.
2) MONITOR the level and pressure of SI Accumulator B.
3) WHEN desired level is obtained, THEN CLOSE S1-851 B.

OP-202 Rev. 94 Page 15 of 131

Section 8.2.1 Page 4 of 5 8.2.1.2 (Continued) INITVERI

j. IF SI Accumulator C is to be filled, THEN PERFORM the following:
1) OPEN SI-851C, MAKEUP.
2) MONITOR the level and pressure of SI Accumulator C.
3) WHEN desired level is obtained, THEN CLOSE SI-851C.
k. STOP the operating SI Pump.

VERIFY both SI Pump Area Cooling units are OFF:

1) HVH-6A
2) HVH-6B
m. CLOSE SI-869, SI HOT LEG HDR.

NOTE: In Mode 1, 2 OR 3 the Control Power Defeat switch for SI-869 should be in the DEFEAT position. In Mode 5 OR 6 the Control Power Defeat switch for SI-869 should be in the NORMAL position. In Mode 4 the position of the Control Power Defeat switch for S 1-869 is determined by GP-002 OR GP-007.

n. VERIFY the Control Power Defeat switch for SI-869 in the position determined by plant status:

DEFEAT I NORMAL (Circle one)

OP-202 Rev. 94 Page 16 of 13J

Section 8.2.1 Page 5 of 5 8.2.1.2 (Continued) i.jj.i

o. IF the Refueling Water Purification Pump was stopped in Step 8.2.1.1.f, THEN PERFORM the following:
1) OPEN SFPC-805B, RWST RETURN.
2) START the Refueling Water Purification Pump.

CAUTION If any SI Accumulator level rises by 10% (70 gal) when the RCS pressure is greater than 1000 psig, then the affected accumulator is required to be sampled to verify boron concentration is greater than or equal to 2000 ppm and less than or equal to 2400 ppm within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. (ITS SR 3.5.1.4 and Bases)

p. IF the RCS pressure is greater than 1000 psig AND any SI Accumulator level was raised by 10%

(70 gal.), THEN REQUEST E&C to sample the affected SI Accumulator(s) for boron concentration.

q. IF SI Accumulator sample(s) were required in the previous step, THEN RECORD the affected SI Accumulator(s) boron sample results below:

(N/A those NOT required to be sampled)

SI Accum A boron concentration SI Accum B boron concentration SI Accum C boron concentration Initials Name (Print) Date Performed By: 9% Sur4- TO)4y Approved By:

Shift Manager Date OP-202 Rev. 94 Page 17 of 131

LICENSE EXAMINATION JOB PERFORMANCE MEASURE ILC-13 NRC JPM I RevO Auxiliary Building Operator Actions JAW DSP-002, Att. 3 Concurred By: Patrick Lathrop Date: 5/15/13 Operations Approved By: James Conder Date: 6/5/13 SuperintendentlSupervisor Training

ILC-13 NRC JPM I Page 2 of 16 LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task: 01104100905, Perform the Actions of the Auxiliary Building Operator JAW DSP-002 Alternate Path:

YES JPM#: Candidate ILC-13 NRC JPM I RO/SRO KJA Rating (RO/SRO):

004 G2.1.30 4.4/4.0 004 A1.11 3.0/3.0 Task Standard:

Charging flow has been established to the RCS and seal injection aligned to the RCPs.

Preferred Evaluation Location: Preferred Evaluation Method:

Simulator In-Plant X Perform Simulate X

References:

DSP-002, AU. 3 Validation Time: 14 Minutes Time Critical: YES Time Critical Time: 13 mm. to xfer to RWST 15 mm. to est. seal inj.

Candidate:

Name Overall Critical Time Time SSN Start: Start:

Finish: Finish: /

Performance Rating: Performance SAT UNSAT circle one Time (mm): /

Examiner:

Print Name Signature Date NOTE: The time critical times are based on times from the event initiation. The JPM begins with 2 minutes already elapsed.

ILC-.13 NRC JPM I Page 3 of 16 COMMENTS:

QUESTION DOCUMENTATION:

Question:

Response

ILC-13 NRC JPM I Page 4 of 16 COMMENTS Step 3 Critical because the charging pump must be in LOCAL for operator control.

Step 4 Critical to provide flowpath around HCV-121.

Step 5 Critical to isolate the flowpath through HCV- 121.

Step 6 Critical to align RWST to Charging Pump Suction.

Step 8 Critical to isolate the VCT from the Charging Pump Suction.

Step 12 Critical to provide makeup to the RCS and RCP seal injection flow.

Step 13 Critical to allow the charging pump speed to be controlled locally.

Step 14 Critical to extend the time until the PZR approaches full to greater than one hour.

Step 17 Critical to establish adequate RCP seal injection flows.

ILC-13 NRC JPM I Page 5 ofl6 Tools/Equipment/Procedures Needed:

DSP-002, Attachment 3 READ TO OPERATOR DIRECTIONS TO CANDIDATE:

I will explain the initial conditions, and state the task to be performed. All in-plant steps, including any required communications, shall be simulated for this JPM. Under no circumstances are you to operate any plant equipment. 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 facilitate the examination and better enable me to assess your level of understanding, verbalize your actions and observations while performing the JPM. To indicate that you have completed your assigned task return the Operator Cue Sheet I provided you.

CANDIDATE INFORMATION:

inform the candidate there ARE time critical steps in this JPM.

INITIAL CONDITIONS:

1. At 1200, the Control Room was evacuated due to a fire on the RTGB.
2. At the time the Control Room was evacuated, Charging Pumps B and C were running.
3. DSP-002, Hot Shutdown Using the Dedicated / Alternate Shutdown System, has been implemented.

INITIATING CUES:

You have been assigned to perform DSP-002, Attachment 3. Enter the Auxiliary Building through the normal Auxiliary Building RCS Entrance. Assume that you have all of the equipment required by Attachment 3, Step 1. Inform the Shift Manager when a Charging Pump is running at minimum speed and adequate seal injection flow is being supplied to the RCPs.

The time now is 1202.

Time Critical

ILC-13 NRC JPM I Page 6 of 16 START TIME: TIME CRITICAL START TIME:

EXAMINERS NOTE: PROVIDE THE CANDIDATE WITH THE JPM CUE SHEET AND COPY OF DSP-002, ATT. 3 AT A LOCATION OUSIDE OF THE RCA.

NOTE

  • Time Critical Action: Transfer Charging Pump Suction to the RWST within 13 minutes of event initiation per step 5.
  • Time Critical Action: Re-establish Charging/Seal Injection within 15 minutes of event initiation per step 7.
  • Time Critical Action: Establish CCW to RCPs within 93 minutes of event initiation per step 19.

STEP 1: Obtain the Following Prior to Leaving the Old Fire Equipment Building

  • Two way radio

. Flahslight SAT

  • Locked valve keys (Keys 1, 1 a or 1 b)

. Locked high rad area key (in holder near door)

(AU. 3 Step 1)

UNSAT STANDARD: N/A As Found: N/A EXAMINERS NOTE: NONE EXAMINERS CUE: Remind the candidate that the cue stated to assume that all equipment required for step 1 has been obtained.

COMMENTS:

ILC-13 NRC JPM I Page 7 of 16 STEP 2: Check Fire Location In E1/E2 ROOM (AREA A5)

(An. 3 Step 2)

STANDARD: Candidate determines, from the initial conditions, that the fire is NOT in SAT the E1/E2 Room and takes RNO path to Step 4.

As Found: N/A UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: NONE COMMENTS:

NOTE Access to the Charging Pump Room can be gained via the Nonregenerative and Seal Water Return Heat Exchanger Room on the second level of the Aux Bldg in the event of a fire in the Aux Bldg hallway.

CVC-309A is located near HCV-121 on the West Wall of the Charging Pump Room.

STEP 3: Place Transfer Switch for Charging Pump A to LOCAL CRITICAL (An. 3 Step 4.a) STEP STANDARD: Candidate simulates placing Charging Pump A Transfer Switch to LOCAL SAT As Found: Charging Pump A Transfer Switch in REMOTE.

EXAMINERS CUE: Charging Pump A Transfer Switch is in LOCAL and the UNSAT GREEN stop light is illuminated EXAMINERS NOTE: If candidate requests status of Charging Pumps inform the candidate that there is no motor or pump noise in the Charging Pump room. No charging pumps are operating.

COMMENTS:

ILC-13 NRC JPM I Page 8 of 16 STEP 4: Open CVC-309A, HCV-121 BYPASS CRITICAL (AU. 3 Step 4.b) STEP STANDARD: Candidate simulates opening CVC-309A by rotating the handwheel in the CCW direction.

SAT As Found: CVC-309A is closed.

EXAMINERS CUE: CVC-309A handwheel has stopped rotating and the stem is full out. UNSAT EXAMINERS NOTE: NONE COMMENTS:

STEP 5: Close CVC-202B, HCV-121 INLET ISOL CRITICAL (Att. 3 Step 4.c) STEP STANDARD: Candidate simulates closing CVC-202B by rotating the handwheel in the CW direction.

SAT As Found: CVC-202B is open.

EXAMINERS CUE: CVC-202B handwheel has stopped rotating and the stem is fully inserted. UNSAT EXAMINERS NOTE: NONE COMMENTS:

NOTE

  • CVC-358 is located in the overhead West of Charging Pump B.
  • LCV-115C is located in the overhead between Charging Pumps B & C

ILC-13 NRC JPM I Page 9 of 16 STEP 6: Open CVC-358, RWST TO CHARGING PUMP SUCTION CRITICAL (Aft. 3 Step 5.a) STEP STANDARD: Candidate simulates opening CVC-358 by rotating handle 90 degrees CCW to align the valve handle with the pipe. SAT As Found: CVC-358 is closed with handle perpendicular with pipe.

EXAMINERS CUE: CVC-358 handle is aligned with the pipe. UNSAT EXAMINERS NOTE: Ladder is located in the SE corner of the Charging Pump Room next to the Charging Pump Room DS Control Panel.

COMMENTS:

STEP 7: Obtain verification from the SM that the emergency buses are deenergized.

(Aft. 3 Step 5.b) SAT STANDARD: Candidate simulates using the radio to contact the SM for the status of the emergency buses.

UNSAT As Found: N/A EXAMINERS CUE: SM reports that both emergency buses are deenergized.

EXAMINERS NOTE: NONE COMMENTS:

ILC-13 NRC JPM I Page 10 of 16 STEP 8: Close LCV-115C, VCT OUTLET ISOLATION CRITICAL (Aft. 3 Step 5.c) STEP STANDARD: Candidate simulates closing valve LCV-115C by declutching the motor by downward motion of the lever and then rotating the handwheel in the CW SAT direction.

As Found: LCV-115C is open.

UNSAT EXAMINERS CUE: The motor is dc-clutched and LCV-115C handwheel has stopped rotating and the valve stem is fully inserted.

EXAMINERS NOTE: For safety purposes the candidate is allowed to point to the valve from the floor and discuss how the valve is operated.

COMMENTS:

TIME CRITICAL TIME STOP: (Aligned to RWST: 11 mm. from start of JPM)

STEP 9: Check Charging Pump A STOPPED (Aft. 3 Step 6)

SAT STANDARD: Candidate determines from initial conditions and / or observations in Charging Pump Room that Charging Pump A is stopped.

As Found: Depends on actual plant conditions. UNSAT EXAMINERS CUE: If requested, report that the charging pump room is quiet.

There is no movement on any of the pumps. Charging Pump A GREEN stop light is illuminated.

EXAMINERS NOTE: NONE COMMENTS:

NOTE A ladder is located to the left of the Charging Pump Room Control Panel if closure of the CVC-297 valves is required.

ILC-13 NRC JPM I Page 11 of 16 STEP 10: Obtain verification from the SM that the DS Bus is energized AND elapsed time since Seal Injection was lost.

(Att. 3 Step 7.a) SAT STANDARD: Candidate simulates using radio to contact the SM.

As Found: N/A UNSAT EXAMINERS CUE: SM reports that the DS Bus is energized and that seal injection has been lost for 12 minutes.

EXAMINERS NOTE: NONE COMMENTS:

STEP 11: Check elapsed time since Seal Injection Lost Less than 15 minutes.

(Aft. 3 Step 7.b)

SAT STANDARD: Candidate determines that seal injection has been lost for 12 minutes.

As Found: N/A UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: NONE COMMENTS:

ILC-13 NRC JPM I Page 12 of 16 STEP 12: Locally Start Charging Pump A CRITICAL (Aft. 3 Step 7.c) STEP STANDARD: Candidate simulates starting Charging Pump A by pushing the START pushbutton. Verifies pump start, visually and audibly. SAT As Found: Depend on actual plant conditions.

EXAMINERS CUE: - The RED run light is illuminated and Charging Pump A is UNSAT running.

- All post-start conditions are normal.

- If the candidate checks charging flow on FI-122B, state that charging flow is 35 gpm.

EXAMINERS NOTE: NONE COMMENTS:

TIME CRITICAL TIME STOP: (Re-est. seal inj. flow: 13 mm. from start of JPM)

CAUTION Attempt to minimize Charging Pump starts/stops while maintaining the PZR level band in the following steps to avoid exceeding the pump start limitation of four starts per hour. However, maintaining the PZR level band overrides_concerns_with pump_start_limitations.

STEP 13: Place the local speed control station AUTO/MAN Selector Switch to the CRITICAL MAN position. STEP (Aft. 3 Step 8.a)

STANDARD: Candidate simulates rotating the AUTO/MAN selector switch for A SAT Charging Pump Speed Controller to MAN position.

As Found: AUTO/MAN selector switch in AUTO for A CCP UNSAT EXAMINERS CUE: AUTO/MAN station for A Charging Pump has been placed in MAN.

EXAMINERS NOTE NONE COMMENTS

ILC-13 NRC JPM I Page 13 of 16 STEP 14: Rotate the speed controller COUNTER-CLOCKWISE to manually lower CRITICAL Charging Pump Speed to the minimum. STEP (Att. 3 Step 8.b)

STANDARD: Candidate simulates rotating the speed controller knurled knob in the SAT CCW direction to reduce charging pump speed to minimum. Audible is available to verify that pump speed has been lowered.

As Found: Condition based on actual plant status. UNSAT EXAMINERS CUE: Speed controller has been rotated in the CCW direction and pump speed has lowered.

EXAMINERS NOTE: Charging Pump speed controller has an arrow that indicates increasing speed in the CW direction, and visa-versa.

COMMENTS:

STEP 15: Check Seal Injection Aligned (Att. 3 Step 9)

SAT STANDARD: Candidate determines that seal injection is aligned based on information to the contrary given in cue and also observes seal injection flow at local indicators.

UNSAT As Found: Seal injection flow will be 8 12 gpm based on actual plant status.

EXAMINERS CUE: If requested or if local seal injection flow observed, inform the candidate that all seal injection flows indicate approximately 4 gpm each.

EXAMINERS NOTE: NONE COMMENTS:

ILC-13 NRC JPM I Page 14 of 16 STEP 16: Check RCP Seal Injection Flow Between 6 GPM AND 20 GPM (Aft. 3 Step 10)

SAT STANDARD: Candidate observes the local seal injection flow meters and determines that flow is NOT within the specified band.

As Found: Seal injection flow will be 8 12 gpm based on actual plant status. UNSAT EXAMINERS CUE: When local seal injection flow observed, inform the candidate that all seal injection flows indicate approximately 4 gpm each.

EXAMINERS NOTE: NONE COMMENTS:

STEP 17: Locally throttle RCP SEAL WATER FLOW CONTROL VALVEs to CRITICAL obtain flow to each RCP between 6 gpm and 20 gpm. STEP

  • CVC-297A
  • CVC-297B
  • CVC-297C (Aft. 3 Step 10 RNO) SAT STANDARD: Candidate simulates throttling open CVC-297A1B/C by rotating the handwheels in the CCW direction while periodically checking the seal injection flows. UNSAT As Found: Seal injection flow will be 8 12 gpm based on actual plant status.

EXAMINERS CUE: As the candidate throttles open the valve(s), inform the candidate that the seal injection flows are slowly rising and are slightly greater than 6 gpm as the applicable CVC-297 valve is fully opened. When all CVC-297 valves are fully open inform the candidate that all seal injection flows indicate 6.2 gpm.

EXAMINERS NOTE: NONE COMMENTS:

ILC-13 NRC JPM I Page 15 of 16 STEP 18: IF required to maintain minimum flow, THEN throttle CVC-309A, HCV 121 BYPASS, valve while maintaining Charging Pump Discharge pressure less than 2500 psig. SAT (AU. 3 Step 10 RNO)

STANDARD: Candidate determines that performance of this step is not necessary.

UNSAT As Found: CVC-309A was opened in a previous step.

EXAMINERS CUE: If requested, inform candidate that all seal injection flows remain steady at 6.2 gpm.

EXAMINERS NOTE: NONE COMMENTS:

STEP 19: Notify the SM that Charging Flow has been established AND the status of seal injection.

(Step 11) SAT TANDARD: Candidate simulates using the radio to contact the SM and reports that charging flow has been established to the RCS and that seal injection flow is within the desired range. UNSAT As Found: N/A EXAMINERS CUE: Acknowledge report as the SM.

EXAMINERS NOTE: NONE COMMENTS:

END OF TASK Terminating Cue: After the SM has been notified that charging flow has been established and that seal injection flows are in the normal range.

TIME STOP:

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

CANDIDATE INFORMATION:

Inform the candidate there ARE time critical steps in this JPM.

INITIAL CONDITIONS:

1. At 1200, the Control Room was evacuated due to a fire on the RTGB.
2. At the time the Control Room was evacuated, Charging Pumps B and C were running.
3. DSP-002, Hot Shutdown Using the Dedicated / Alternate Shutdown System, has been implemented.

INITIATING CUES:

You have been assigned to perform DSP-002, Attachment 3. Enter the Auxiliary Building through the normal Auxiliary Building RCS Entrance. Assume that you have all of the equipment required by Attachment 3, Step 1.

Inform the Shift Manager when a Charging Pump is running at minimum speed and adequate seal injection flow is being supplied to the RCPs.

The time now is 1202.

Time Critical

Rev. 47 HOT SHUTDOWN USING THE DEDICATED/ALTERNATE D S P- 00 2 SHUTDOWN SYSTEM Page 26 of 71 j__STEP_H ACTION/EXPECTED RESPONSE j RESPONSE NOT OBTAINED CONTINUOUS USE ATTACHMENT 3 AUXILIARY BUILDING OPERATOR ACTIONS (Page 1 of 14)

NOTE

  • Time Critical Action: Transfer Charging Pump Suction to the RWST within 13 minutes of event initiation per step 5.
  • Time Critical Action: Re-establish Charging / Seal Injection within 15 minutes of event initiation per step 7.
  • Time Critical Action: Establish CCW to RCPs within 93 minutes of event initiation per step 19.
1. Obtain The Following Prior To Leaving The Old Fire Equipment Building:
  • Two-way radio
  • Flashlight
  • Locked valve keys (Keys 1, la, or lb)
  • Locked high rad area key (in holder near door)
2. Check Fire Location - IN E-l/E-2 Observe the QZ prior to Step 4 ROOM (AREA A5) and Go To Step 4.

Rev. 47 HOT SHUTDOWN USING THE DEDICATED/ALTERNATE DSP 002 SHUTDOWN SYSTEM Page 27 of 71

__STEP_H ACTION/EXPECTED RESPONSE CONTINUOUS IUSE RESPONSE NOT OBTAINED ATTACHMENT 3 AUXILIARY BUILDING OPERATOR ACTIONS (Page 2 of 14)

3. Shutdown The EDGs As Follows:
a. At EDG A Perform the following:
  • Trip the Fuel Racks by depressing the EMERGENCY STOP Pushbutton
  • Unlock AND close DA-2lA, DG A UPPER AIR START OUTLET ISOLATION
  • Unlock AND close DA-25A, DG A LOWER AIR START OUTLET ISOLATION
b. At EDG B Perform the following:
  • Trip the Fuel Racks by depressing the EMERGENCY STOP Pushbutton
  • Unlock AND close DA-21B, DG B UPPER AIR START OUTLET ISOLATION
  • Unlock AND close DA-25B.

DG B LOWER AIR START OUTLET ISOLATION

c. Notify the SM that BOTH EDGs have been tripped

Rev. 47 HOT SHUTDOWN USING THE DEDICATED/ALTERNATE DSP 002 SHUTDOWN SYSTEM Page 28 of 71

__STEP H ACTION/EXPECTED RESPONSE CONTINUOUS f USE RESPONSE NOT OBTAINED I

ATTACHMENT 3 AUXILIARY BUILDING OPERATOR ACTIONS (Page 3 of 14)

NOTE

  • Access to the Charging Pump Room can be gained via the Nonregenerative and Seal Water Return Heat Exchanger Room on the second level of the Aux Bldg in the event of a fire in the Aux Bldg hallway.
  • CVC-3O9A is located near HCV-121 on the West Wall of the Charging Pump Room.
4. Locally Align Charging Flow As Follows:
a. Place Transfer Switch for CHARGING PUNP A to LOCAL
b. Open CVC-309A. HCV-12l BYPASS
c. Close CVC-202B, HCV-12l INLET I SOL

Rev. 47 HOT SHUTDOWN USING THE DEDICATED/ALTERNATE D P 002 SHUTDOWN SYSTEM Page 29 of 71 H STEP_H ACTION/EXPECTED RESPONSE CONTINUOUS

[ USE RESPONSE NOT OBTAINED I

ATTACHMENT 3 AUXILIARY BUILDING OPERATOR ACTIONS (Page 4 of 14)

NOTE

  • CVC-358 is located in the overhead West of Charging Pump B.
  • LCV-ll5C is located in the overhead between Charging Pumps B & C.
5. Locally Align RWST To Charging Pump Suction As Follows:
a. Open CVC-358, RWST TO CHARGING PUMP SUCTION
b. Obtain verification from the b. WHEN verification received, SM that the emergency buses Go To Step S.c.

are deenergized

c. Close LCV-ll5C, VCT OUTLET ISOLATION
6. Check Charging Pump A - STOPPED Go To Step 8.

Rev. 47 HOT SHUTDOWN USING THE DEDICATED/ALTERNATE DSP 002 SHUTDOWN SYSTEM Page 30 of 71 H__STEP H ACTION/EXPECTED RESPONSE CONTINUOUS IUSE RESPONSE NOT OBTAINED ATTACHMENT 3 AUXILIARY BUILDING OPERATOR ACTIONS (Page 5 of 14)

NOTE A ladder is located to the left of the Charging Pump Room Control Panel if closure of the CVC-297 valves is required.

7. At the Charging Pump Room Control Panel Start Charging Pump A As Follows:
a. Obtain verification from the a. WHEN verification is SM that the DS Bus is received, JII Go To Step 7.b.

energized PN12 elapsed time since Seal Injection was lost

b. Check elapsed time since Seal b. Perform the following:

Injection Lost - LESS THAN 15 MINUTES 1) Close the RCP SEAL WATER FLOW CONTROL VALVEs:

  • CVC-297A
  • CVC-297B
  • CVC-297C
2) WiN Pipe Alley is accessible, THEN Locally close ONE of the below valves:
  • FCV-626, THERM BARRIER OUTLET OR
  • CC-736, CC FROM RCP A, B, C THERMAL BARRIER
3) Go To Step 7.c.
c. Locally Start CHARGING PUMP A

Rev. 47

- HOT SHUTDOWN USING THE DEDICATED/ALTERNATE SHUTDOWN SYSTEM Page 31 of 71 H__STEP_H ACTION/EXPECTED RESPONSE CONTINUOUS I

USE RESPONSE NOT OBTAINED I

ATTACHMENT 3 AUXILIARY BUILDING OPERATOR ACTIONS (Page 6 of 14)

CAUTION Attempt to minimize Charging Pump starts/stops while maintaining the PZR level band in the following steps to avoid exceeding the pump start limitation of four starts per hour. However, maintaining the PZR level band overrides concerns with pump start limitations.

8. Establish Local Speed Control Of The Running Charging Pump As Follows:
a. Place the local speed control station AUTO/MAN Selector Switch to the MAN position
b. Rotate the speed controller COUNTER-CLOCKWISE to manually lower Charging Pump Speed to the minimum
9. Check Seal Injection - ALIGNED Go To Step 11.
10. Check RCP Seal Injection Flow - Locally throttle RCP SEAL WATER BETWEEN 6 GPM AND 20 GPM FLOW CONTROL VALVEs to obtain flow to each RCP between 6 gpm and 20 gpm.
  • CVC-297A
  • CVC297B
  • CVC-297C j required to maintain minimum flow, THEN throttle CVC-309A, HCV-12l BYPASS valve while maintaining Charging Pump Discharge pressure less than 2500 psig.

Rev. 47 HOT SHUTDOWN USING THE DEDICATED/ALTERNATE DSP 002 SHUTDOWN SYSTEM Page 32 of 71 H__STEP_H ACTION/EXPECTED RESPONSE CONTINUOUS IUSE RESPONSE NOT OBTAINED I

ATTACHMENT 3 AUXILIARY BUILDING OPERATOR ACTIONS (Page 7 of 14)

11. Notify The SM That Charging Flow Has Been Established AND The Status Of Seal Injection NOTE Attachment 11, Credited Instrumentation Available, provides a list of the credited instrumentation not affected by the fire based on the fire location.
12. At the Charging Pump Control Panel Perform the following:
a. Verify Transfer Switch for CCW PUMP A in LOCAL position.
b. Check CCW PUMP A Status b. RCP Seal Injection has STOPPED. been established, notify SM that CCW has been established j?j. Go To Step 15.

RCP Seal Injection has NQI been established. THEN Locally Stop CCW Pump A.

Rev. 47 HOT SHUTDOWN USING THE DEDICATED/ALTERNATE DSP-0 02 SHUTDOWN SYSTEM Page 33 of 71

-__STEP_H ACTION/EXPECTED RESPONSE CONTINUOUS USE RESPONSE NOT OBTAINED I

ATTACHMENT 3 AUXILIARY BUILDING OPERATOR ACTIONS (Page 8 of 14)

NOTE When dumping steam from the secondary a cooldown rate of 10°F/Hr is the maximum rate allowed.

13. At the Charging Pump Control Panel Start CCW PUMP A As Follows:
a. Check RCP Seal Injection - a. Perform the following:

ESTABLI SHED

1) Locally Raise speed on the Charging Pump to 100%.
2) required to maintain PZR level stable, ILN coordinate with the Turbine Building Operator to dump steam from the secondary.
3) WHEN FCV-626 OR CC-736 is closed, THEN Go To Step 14.
b. Start CCW PUMP A
c. Locally Check CCW flow on c. Locally Verify Charging Pump FI-660, CHARGING PUMP OIL A CCW alignment correct:

COOLER RETURN FLOW - FLOW INDICATED

  • CC-825C, CC TO CHG PUMP A OIL COOL - OPEN

. CC-825F, CC FROM CHG PUMP A OIL COOL - OPEN

d. Notify the SM that CCW flow has been established
e. Go To Step 15

Rev. 47 HOT SHUTDOWN USING THE DEDICATED/ALTERNATE DSP 002 SHUTDOWN SYSTEM Page 34 of 71

STEP_H ACTION/EXPECTED RESPONSE CONTINUOUS IUSE RESPONSE NOT OBTAINED I

ATTACHMENT 3 AUXILIARY BUILDING OPERATOR ACTIONS (Page 9 of 14)

  • 14. Perform The Following:
a. At the Charging Pump Room Control Panel Start CCW PUMP A
b. Notify the SM that CCW flow has been established
c. Check CCW flow on FI-660. c. Verify Charging Pump A CCW CHARGING PUMP OIL COOLER alignment correct:

RETURN FLOW - FLOW INDICATED

  • CC-825C. CC TO CHG PUMP A OIL COOL OPEN
  • CC-825F, CC FROM CHG PUMP A OIL COOL - OPEN
d. Maintain PZR Level between 15% and 25% by a combination of the following:
  • Local control of Charging Pump speed
  • Dumping steam on the secondary
  • Starting and stopping Charging Pump A as required
15. Go To The Appropriate Step Based On Fire Location:

FIRE LOCATION STEP E-l/E-2 ROOM 17 AUX BLDG HALL 21 ANYWHERE ELSE 16

Rev. 47 HOT SHUTDOWN USING THE DEDICATED/ALTERNATE D P 002 SHUTDOWN SYSTEM Page 35 of 71 H__STEP_H ACTION/EXPECTED RESPONSE CONTINUOUS IUSE RESPONSE NOT OBTAINED ATTACHMENT 3 AUXILIARY BUILDING OPERATOR ACTIONS (Page 10 of 14)

  • 16 Shutdown The EDGs As Follows:
a. At EDG A Perform the following:
  • Trip the Fuel Racks by depressing the EMERGENCY STOP Pushbutton
  • Unlock AND close DA-21A.

DG A UPPER AIR START OUTLET ISOLATION

  • Unlock AND close DA-25A.

DG A LOWER AIR START OUTLET ISOLATION

b. At EDG B Perform the following:
  • Trip the Fuel Racks by depressing the EMERGENCY STOP Pushbutton
  • Unlock AND close DA-21B, DG B UPPER AIR START OUTLET ISOLATION
  • Unlock AND close DA-25B, DG B LOWER AIR START OUTLET ISOLATION
c. Notify the SM that BOTH EDGs have been tripped
17. Check RCP Seal Injection Status Go To Step 24.

- ALIGNED

Rev. 47 HOT SHUTDOWN USING THE DEDICATED/ALTERNATE DSP 002 SHUTDOWN SYSTEM Page 36 of 71 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED H__STEP_H CONTINUOUS USE ATTACHMENT 3 AUXILIARY BUILDING OPERATOR ACTIONS (Page 11 of 14)

  • 18. Check CCW Flow From The Thermal Pipe Alley is accessible, Barrier On FIC-626 - GREATER THEN check flow.

THAN 50 GPM IE flow is less than 50 gpm, locally UNLOCK OPEN CC-932, FCV-626 and CC-735 BYPASS ISOLATION. (Pipe Alley, middle penetrations, sleeve 16) flow remains below 50 gpm.

jjfl locally verify OPEN the following valves:

  • CC-716A, COOLING WATER INLET (Located 20 feet in overhead near Sleeve 8)
  • CC-7l6B, COOLING WATER INLET (Located 20 feet in overhead near sleeve 8.)
19. Notify The SM That CCW Flow To The RCPs Has Been Established
20. Go To Step 24
21. Direct The Electrical Operator To Locally Trip Both Emergency Diesel Generators AND Isolate The Air Start Outlet Isolation Valves When The Fire Is Out (Step 16)

Rev. 47 HOT SHUTDOWN USING THE DEDICATED/ALTERNATE 002 SHUTDOWN SYSTEM Page 37 of 71 H__STEP_H ACTION/EXPECTED RESPONSE CONTINUOUS I

USE RESPONSE NOT OBTAINED I

ATTACHMENT 3 AUXILIARY BUILDING OPERATOR ACTIONS (Page 12 of 14)

  • 22. Check Fire - EXTINGUISHED WHEN the fire has been extinguished, perform ONE of the below Steps:
  • Seal Injection has been established, IIId perform Steps 17 through 19.

OR

  • j Seal Injection has IQ been established, THEN leave FCV-626 OR CC-736 closed AND Go To Step 24.

Go To Step 24.

23. Check Seal Injection Status - Go To Step 17.

ISOLATED

  • 24. Check PZR Level - GREATER THAN IF PZR Level rises to 90%, THEN 90% perform Steps 25 26.

Observe the IQ1 prior to Step 26 and Go To Step 26.

25. Stop CHARGING PUMP A

Rev. 47 HOT SHUTDOWN USING THE DEDICATED/ALTERNATE DSP 002 SHUTDOWN SYSTEM Page 38 of 71 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

__STEP_H CONTINUOUS USE ATTACHMENT 3 AUXILIARY BUILDING OPERATOR ACTIONS (Page 13 of 14)

NOTE PZR level control may be assisted by dumping steam from the secondary as long as a cooldown rate of 10°F/Hr is jQ exceeded.

  • 26. Maintain PZR Level As Follows:
a. Check RCP Seal Cooling - a. Go To Step 26.d.

ALIGNED

b. Maintain PZR Level between 27% And 73% by a combination of the following:
  • Local control of Charging Pump speed
  • Dumping steam on the secondary
  • Starting and stopping Charging Pump A as required
c. Go To Step 27
d. Maintain PZR Level between 15% And 25% by a combination of the following:
  • Local control of Charging Pump speed
  • Dumping steam on the secondary
  • Starting and stopping Charging Pump A as required

Rev. 47 HOT SHUTDOWN USING THE DEDICATED/ALTERNATE D 002 SHUTDOWN SYSTEM Page 39 of 71 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

__STEP_H CONTINUOUS USE ATTACHMENT 3 AUXILIARY BUILDING OPERATOR ACTIONS (Page 14 of 14)

  • 27. Periodically Monitor Charging Perform the following:

Pump A Seal Lubricating Tank -

Level Normal a. Open PW-48.

b. WHEN tank level is in the normal range, close PW-48.
  • 28. Check RWST Level Using LIC-947 WN RWST level is less than LESS THAN 50% 50%, Ii notify the SM to contact the TSC to determine RWST makeup options.

Observe the IQ prior to Step 30 and Go To Step 30.

  • 29. Notify The SM To Contact The TSC To Determine RWST Makeup Options NOTE Portable generators and blowers are available in a cabinet on the 2nd level of the Turbine Building.
30. Notify The SM To Have Portable Cooling Powered From Portable Generators Installed In The Charging Pump Room As Additional Personnel Become Available

- END -

LICENSE EXAMINATION JOB PERFORMANCE MEASURE ILC-13 NRC JPM J RevO ALIGNING SW BACKUP TO SDAFW PUMP SUCTION JAW DSP-007, Attachment 7 Concurred By: Kirk Schauer Date: 5/15/13 Operations Approved By: James Conder Date: 6/5/13 Superintendent/Supervisor Training

JLC-13 NRC JPM J Page 2 of 13 LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task: 04061101001, Aligning SW Backup to SDAFW Pump Suction 01104104205, Perform Cooldown to CSD Using the Dedicated/Alternate Shutdown System JAW DSP-007.

Alternate Path:

YES JPM #: Candidate JLC-13 NRC JPM J RO/SRO K/A Rating (RO/SRO):

061 G2.l.30 4.4/4.0 061K1.01 4.1/4.1 061 K4.01 4.1 /4.2 076K1.20 3.4/3.4 Task Standard:

SW Backup Aligned to Supply Suction to SDAFW Pump JAW DSP-007, Att. 7 Preferred Evaluation Location: Preferred Evaluation Method:

Simulator In-Plant X Perform Simulate X

References:

DSP-007, Att. 7 Validation Time: 15 Minutes Time Critical: NO Time Critical Time: N/A Candidate: (N/A if not time critical)

Name Overall Critical Time Time SSN Start: Start:

Finish: Finish:

Perforniance Rating: SAT UNSAT Performance circle one Time (mm):

Examiner:

Print Name Signature Date

ILC-13 NRC JPM J Page3 of 13 COMMENTS:

QUESTION DOCUMENTATION:

Question:

Response

ILC-13 NRC JPM J Page 4 of 13 COMMENTS Step 1 Critical because these actions will ensure the SDAFW pump is NOT in service while swapping the supply from CST to 5W Step 2 Critical because the supply from the CST must be isolated to prevent SW flow back to the CST. Also because actions ensure the drain is closed and opens the supply from SW to SDAFW pump.

Step 3 Critical because the pump must be vented to ensure water is up to the pump.

Step 6 Critical because a steam supply valve must be opened to start the pump, the initial valve chose by the CRS is stuck closed and the operator must open another steam supply valve to start the pump.

Step 7 Critical because venting the pump casing ensures there is not trapped air that may not have vented using the SW supply line in a previous step.

ILC-13 NRC JPM J Page 5 of 13 Tools/Equipment/Procedures Needed:

DSP-007, Attachment 7 READ TO OPERATOR DIRECTIONS TO CANDIDATE:

I will explain the initial conditions, and state the task to be performed. All in-plant steps, including any required communications, shall be simulated for this JPM. Under no circumstances are you to operate any plant equipment. 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 facilitate the examination and better enable me to assess your level of understanding, verbalize your actions and observations while performing the JPM. To indicate that you have completed your assigned task return the Operator Cue Sheet I provided you.

CANDIDATE INFORMATION:

Inform the candidate there are NO time critical steps in this 1PM.

INITIAL CONDITIONS:

1. DSP-007, Cold Shutdown Using the Dedicated / Alternate Shutdown System, has been implemented and the CRS has determined the need to initiate cool down to cold shutdown.
2. The CRS has determined it is necessary to align SW to the suction of SDAFW pump.
3. You have all equipment and tools necessary to complete this assignment.
4. Due to plant conditions, all communications outside the Control Room will be via radio.

INITIATING CUES:

The CRS directs you to complete DSP-007, Attachment 7 to align SW to the suction of the SDAFW pump. When SW is aligned to supply the pump, start it by opening the steam supply valve from C S/G.

ILC-13 NRC JPM J Page 6 of 13 START TIME:

NOTE ne maximum allowable flow rate for the SDAFW Pump is 345 gpm. This total includes 90 gpm seal leak off and 165 gpm flow to prevent exceeding the 600 gpm maximum designed flow with the SW System as a backup source of water to AFW.

STEP 1: Verify CLOSED, Steam Supply to SDAFW Pump Valves: CRITICAL

  • V1-8A, SG A Stm Supply to SDAFW Pump STEP
  • V1-8B, SG B Stm Supply to SDAFW Pump
  • V1-8C, SG C Stm Supply to SDAFW Pump (Step 1)

SAT STANDARD: Simulates declutching the motor by pushing the lever down, and closing the valve by rotating the handwheel in the CW direction.

As Found: N/A UNSAT EXAMINERS CUE: Motor declutch lever lowered, handwheel turned in the CW direction and will no longer move.

Once the operator has demonstrated manipulation of one of the valves, tell him the other two valves are closed.

XAMINERS NOTE: If necessary, inform the operator that the Control Room is evacuated and local actions are necessary. All 3 valves operate the same and are in the same area.

COMMENTS:

ILC-13 NRC JPM J Page 7 of 13 STEP 2: Locally align the following valves: CRITICAL

a. Unlock and close AFW-1, AFW Pumps suction from CST STEP
b. Unlock and close AFW-104, AFW Pumps suction from CST
c. Close AFW-24A, AFW Suction From SW Emergency B/U Tell-Tail Drain
d. Unlock and OPEN AFW-24, AFW Suction Isolation From SW SAT Emergency Backup
e. Unlock and OPEN SW-118, SW Emergency Backup to AFW Suction.

(Step 2)

UNSAT STANDARD: Simulates unlocking and closing AFW-1 and AFW-104.

Simulates closing AFW-24A.

Simulates unlocking and opening AFW-24 and SW-118.

As Found: Both AFW-1 and AFW-104 are open, stem extended. There is one chain and lock shared between the valve handwheels.

Tell-tail drain AFW-24A is open.

AFW-24 and SW-118 are locked closed.

EXAMINERS CUE: - Lock is removed; AFW-1 and AFW-104 handwheels turned in the CW direction until it will not move anymore, the stem is inserted.

- AFW-24A tell-tail handwheel is turned in the CW direction until it will not move anymore, the stem is inserted.

- The lock is removed from AFW-24; the handwheel is turned in the CCW direction until it will not move anymore and the stem is extended.

- The lock is removed from SW-118; the handwheel turned in the CCW direction until it will not move anymore and the stem is extended.

EXAMINERS NOTE: NONE COMMENTS:

ILC-13 NRC JPM J Page 8 of 13 STEP 3: Vent the SDAFW Pump by performing the following: CRITICAL

a. Remove cap from AFW-7, SDAFW Pump Suction Vent (10 ft in STEP overhead, above TCV-1902A)
b. OPEN AFW-7, SDAFW Pump Suction Vent
c. WHEN a solid stream of water issues from AFW-7, THEN Close AFW-7 SAT
d. Install cap on AFW-7 (Step 3)

UNSAT STANDARD: Simulates venting the SDAFW Pump as follows:

Removes cap from AFW-7 tail pipe.

Turns handwheel in the CCW direction until water issues.

Monitors the flow until a solid stream is observed, THEN turns handwheel in the CW direction unit it stops moving and observes NO flow of water.

Installs the cap on AFW-7 tail pipe.

As Found: AFW-7 closed with cap installed.

EXAMINERS CUE: - Cap is removed from AFW-7 tail pipe.

- Handwheel is turned in the CCW direction until water issues.

- Flow begins to issue and is now a solid stream, THEN handwheel turns in the CW direction until stops and no flow of water.

- The cap is installed on AFW-7 tail pipe.

EXAMINERS NOTE: If candidate attempts to go to WCC for a pipe wrench inform the candidate that all tools were provided as stated in the JPM CUE.

AFW-7 is 10 feet overhead above the TCV-1902A. It will suffice for the Operator to point at the valve, preferably with a flashlight and describe where he would obtain a ladder and describe his actions.

COMMENTS:

ILC-13 NRC JPM J Page 9 of 13 STEP 4: Notify Shift Manager that the SDAFW Pump is ready to be started.

(Step 4)

STANDARD: Simulates contacting SM / CRS and reports the SW has been aligned to SAT supply the SDAFW pump, and the pump has been vented and is ready to start.

As Found: N/A UNSAT EXAMINERS CUE: Acknowledge the report and direct starting the pump using the C S/G steam supply.

EXAMINERS NOTE: NONE COMMENTS:

ILC-l3 NRC JPM J Page 10 of 13 STEP 5: Locally WHEN directed by the Shift Manager start the SDAFW Pump by opening one of the following valves:

  • V1-8A, SG A Stm Supply to SDAFW Pump
  • V1-8C, SG C Stm Supply to SDAFW Pump (Step 5)

STANDARD: Candidate simulates opening V1-8C. Recognizes / reports V1-8C will not UNSAT open.

As Found: The valves were verified closed in Step 1, the motor clutch is disengaged.

EXAMINERS CUE: Direct the Operator to start the SDAFW pump by opening the steam supply valve from the C S/G.

Vl-8C handwheel did NOT move in the CCW direction.

When contacted, respond as CRS/SM and direct candidate use the steam supply valve from B SIG.

EXAMINERS NOTE: The Operator may NOT push the clutch lever, it was disengaged in the first step and remains disengaged until the motor is actuated.

V1-8C valve is STUCK in the closed position, the Operator must contact the Control Room to inform them and choose a different SIG for steam supply.

COMMENTS:

ILC- 13 NRC JPM J Page 11 of 13 STEP 6: Locally WHEN directed by the Shift Manager start the SDAFW Pump by CRITICAL opening on of the following valves: STEP

  • Vl-8A, SG A Stm Supply to SDAFW Pump
  • V1-8B, SG B Stm Supply to SDAFW Pump
  • Vl-8C, SG C Stm Supply to SDAFW Pump SAT (Step 5 continued)

STANDARD: Candidate simulates opening Vl-8B by rotating the MOV handwheel in the CCW direction until it will not turn anymore and is taken 1/4 turn off its SAT backseat.

As Found: The valves were verified closed in Step 1, the motor clutch is disengaged.

EXAMINERS CUE: V1-8B MOV handwheel is turned in the CCW direction until it will not turn anymore.

EXAMINERS NOTE: The operator may decide NOT to push the clutch level since it was disengaged in the first step and remains disengaged until the motor is actuated.

COMMENTS:

ILC-13 NRC JPM J Page 12 of 13 CRITICAL STEP 7: Locally Vent SDAFW Pump by performing the following: STEP Open AFW-18, SDAFW pump vent.

WHEN the SDAFW Pump is vented, THEN close AFW-18.

(Step 6)

SAT STANDARD: Candidate simulates venting the SDAFW Pump as follows:

  • Turns AFW- 18 handwheel in the CCW direction until water issues from the vent.
  • When a solid stream of water is observed, candidate closes AFW- 18 UNSAT by turning the handwheel in the CW direction until the flow stops and the handwheel will not move anymore.

a Candidate contacts the Control Room to inform them the SDAFW Pump is running and has been vented.

As Found: AFW-18 closed.

EXAMINERS CUE: When located:

  • AFW-18 handwheel is turned in the CCW direction and water begins to issue.

a A solid stream of water is observed, the handwheel is then turned in the CW direction until flow is stopped and the handwheel will not move anymore.

a Acknowledge the report that the SDAFW Pump is running and has been vented.

EXAMINERS NOTE: NONE COMMENTS:

END OF TASK Terminating Cue: When the SDAFW Pump has been started and vented.

TIME STOP:

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

CANDIDATE INFORMATION:

Inform the candidate there are NO time critical steps in this JPM.

INITIAL CONDITIONS:

1. DSP-007, Cold Shutdown Using the Dedicated / Alternate Shutdown System, has been implemented and the CRS has determined the need to initiate cool down to cold shutdown.
2. The CRS has determined it is necessary to align SW to the suction of SDAFW pump.
3. You have all equipment and tools necessary to complete this assignment.
4. Due to plant conditions, all communications outside the Control Room will be via radio.

INITIATING CUES:

The CRS directs you to complete DSP-007, Attachment 7 to align SW to the suction of the SDAFW pump. When SW is aligned to supply the pump, start it by opening the steam supply valve from C S/G.

Rev. 29 COLD SHUTDOWN USING THE DEDICATED/ALTERNATE DSP-007 SHUTDOWN SYSTEM Page 104 of 166 CONTINUOUS USE ATTACHMENT 7 ALIGNING SW BACKUP TO SDAFW PUMP SUCTION (Page 1 of 2)

NOTE The maximum allowable flow rate for the SDAFW Pump is 345 gpm. This total includes 90 gpm seal leak off and 165 gpm recirc flow to prevent exceeding the 600 gpm maximum designed flow with the SW System as a backup source of water to AFW.

1. Locally Verify CLOSED, Steam Supply to SDAFW Pump Valves:
2. Locally Align the following valves:
a. Unlock and close AFW-l, AFW PUMPS SUCTION FROM CST.
b. Unlock and close AFW-l04, AFW PUMPS SUCTION FROM CST.
c. Close AFW-24A, AFW SUCTION FROM SW EMERGENCY B/U TELL-TAIL DRAIN
d. Unlock and open AFW24, AFW SUCTION ISOLATION FROM SW EMERGENCY BACKUP.
e. Unlock and open SW-ll8, SW EMERGENCY BACKUP TO AFW SUCTION.
3. Locally Vent the SDAFW Pump by performing the following:
a. Remove cap from AFW-7, SDAFW PUMP SUCTION VENT (10 ft in overhead, above TCV-1902A)
b. Open AFW-7, SDAFW PUMP SUCTION VENT.
c. WHEN a solid stream of water issues from AFW-7, THEN close AFW- 7.
d. Install cap on AFW-7, SDAFW PUMP SUCTION VENT.
4. Notify Shift Manager that the SDAFW Pump is ready to be started.

Rev. 29 COLD SHUTDOWN USING THE DEDICATED/ALTERNATE DSP 007 SHUTDOWN SYSTEM Page 105 of 166 CONTINUOUS USE ATTACHMENT 7 ALIGNING SW BACKUP TO SDAFW PUMP SUCTION (Page 2 of 2)

5. Locally WHEN directed by the Shift Manager start the SDAFW Pump by opening one of the following valves:
6. Locally Vent SDAFW Pump by performing the following:
a. Open AFW-18, SDAFW PUMP VENT.
b. WHEN the SDAFW PUMP is vented, THEN close AFW-18.

- END -

LICENSE EXAMINATION JOB PERFORMANCE MEASURE ILC-13 NRC JPM K RevO ALIGN BACKUP FUEL OIL TO THE B EDG lAW EPP 28, ATTACHMENT 5 Concurred By: Patrick Lathrop Date: 5/15/13 Operations -

Approved By: James Conder Date: 6/5/13 Superintendent/Supervisor Training

JPM NRC JPM K Page 2 of 11 LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task: 04118117205, Perform the Local Actions to Align Backup Fuel Oil from the Alternate Fuel Oil Storage Tanks to the EDGs Day Tanks JAW EPP-28 (Commitment) 01118115705, Respond to EPP-28 Loss of Ultimate Heat Sink (Commitment)

Alternate Path:

NO JPM #: Candidate ILC-13 NRC JPM K RO/SRO K/A Rating (RO/SRO):

062.AK3.03 4.0/4.2 064.K1.03 3.6/4.0 064.K6.08 3.2/3.3 Task Standard:

Backup fuel oil is aligned to the B EDG JAW EPP-28 Attachment 5 Preferred Evaluation Location: Preferred Evaluation Method:

Simulator In-Plant X Perform Simulate X

References:

EPP-28, Attachment 5 Validation Time: 15 Minutes Time Critical: NO Time Critical Time: N/A Candidate: (N/A if not time critical)

Name Overall Critical Time Time SSN - Start: Start:

Finish: Finish:

Performance Rating: Performance SAT UNSAT circle one Time (mm):

Examiner:

Print Name Signature Date COMMENTS:

JPMNRCJPMK Page 3 of 11 QUESTION DOCUMENTATION:

Question:

Response

JPM NRC JPM K Page 4 of 11 COMMENTS Steps 2, 3 & 4 Critical to establish a flowpath from the AFOST to the EDG Day Tank.

Step 5 & 6 Critical to control EDG Day Tank Level.

JPM NRC JPM K Page 5 of 11 Tools/Equipment/Procedures Needed:

EPP-28, Attachment 5 READ TO OPERATOR DIRECTIONS TO CANDIDATE:

I will explain the initial conditions, and state the task to be performed. All in-plant steps, including any required communications, shall be simulated for this 3PM. Under no circumstances are you to operate any plant equipment. 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 facilitate the examination and better enable me to assess your level of understanding, verbalize your actions and observations while performing the 3PM. To indicate that you have completed your assigned task return the Operator Cue Sheet I provided you.

CANDIDATE INFORMATION:

Inform the candidate there are NO time critical steps in this 3PM.

INITIAL CONDITIONS:

1. You are the Inside Auxiliary Operator.
2. A hostile action has resulted in a loss of off-site power and severely damaged the intake, with a subsequent loss of the ability to move water from the lake to cool plant equipment.
3. The Security Event has been terminated.
4. EPP-28 (Loss of Ultimate Heat Sink) has been implemented.
5. The B EDG is running and A EDG is secured.

INITIATING CUES:

The CRS has directed you to Align Back Up Fuel Oil in accordance with EPP-28 Attachment 5.

ILC-13 NRC JPM K Page 6 of 11 START TIME:

STEP 1: Obtain a copy of the appropriate procedure (Step 1)

SAT STANDARD: Candidate obtains and verifies current copy of EPP-28.

As Found: N/A UNSAT EXAMINERS CUE: After Candidate locates and verifies the revision of the procedure, hand the candidate a copy of EPP-28, Attachment 5.

EXAMINERS NOTE: NONE COMMENTS:

ILC-13 NRC JPM K Page 7 of 11 NOTE

  • The Alternate Fuel Oil Storage Tanks (AFOSTs) should only be used to supply the EDG Day Tanks during a design basis threat. The use of the AFOSTs for any other reason may constitute a violation of the renewed operating license. Reference RNP-L/LR-0009 Section 3.4.3.1.
  • Operators are NOT required for performance of this attachment.
  • A fill rate from the Alternate Fuel Oil Tanks of 30 gpm is expected.
  • The intent of the two C/A steps is to open and close the fill valve to maintain level between 1/4 and 3/4 full.

STEP 2: Close the normal EDG Day Tank header isolation valve for the running Critical Step EDG(s):

. A EDO FO-25A, DIESEL OIL DAY TANK A HEADER ISOLATION

. B EDG FO-25B, DIESEL OIL DAY TANK B HEADER SAT ISOLATION (Step 1)

STANDARD: Candidate Simulates closing FO..25B by rotating the handwheel in the CW UNSAT direction.

AS FOUND: Open EXAMINERS CUE: FO-25B is turned in the CW direction until it will not move anymore, the stem is inserted.

EXAMINERS NOTE: Valve is located at the Day Tank COMMENTS:

ILC-13 NRC JPM K Page 8 of 11 STEP 3: Open the EDG Day Tank Fill valve for the running EDG(s): Critical Step

  • A EDG FO-26A, ALT I EMERG SUPPLY TO FUEL OIL DAY TANK A
  • Bt EDG FO-26B, ALT I EMERG SUPPLY TO FUEL OIL DAY TANK B SAT (Step 2)

STANDARD: Candidate Simulates opening FO-26B by rotating the handwheel fully CCW. UNSAT AS FOUND: Closed EXAMINERS CUE: FO-26B has been rotated fully counter-clockwise and placed approximately 1/4 turn off its backseat. (stem fully withdrawn)

EXAMINERS NOTE: Valve is located at the Day Tank COMMENTS:

STEP 4: Open the EDG Day Tank Solenoid Bypass valve for the tank(s) being Critical Step filled:

  • A EDG FO-28A, DIESEL OIL DAY TANK A SOLENOID BYPASS
  • B EDG FO-28B, DIESEL OIL DAY TANK B SOLENOID SAT BYPASS (Step 3)

STANDARD: Candidate Simulates Opening FO-28B by rotating the handwheel fully UNSAT CCW.

AS FOUND: Closed EXAMINERS CUE: FO-28B has been rotated fully counter-clockwise and placed approximately 1/4 turn off its backseat. (stem fully withdrawn)

EXAMINERS NOTE: Valve is located at the Day Tank COMMENTS:

ILC-13 NRC JPM K Page 9 of 11 NOTE Only one tank should be filled at a time.

STEP 5: WHEN day tank level reaches 1/4 full, THEN open the AFOST SUPPLY Critical Step TO FUEL OIL DAY TANK for the day tank to be filled:

  • FO-23 1, AFOST SUPPLY TO FUEL OIL DAY TANK A OR
  • FO-236, AFOST SUPPLY TO FUEL OIL DAY TANK B SAT (Step 4)

STANDARD: Candidate locates Day Tank Level indication and simulates reading level and then simulates opening FO-236 by rotating the valve handle until it is UNSAT in line with the pipe.

AS FOUND: Closed EXAMINERS CUE: Inform Candidate the Day Tank level is at 1/4 full FO-236 valve handle has been rotated in line with the pipe and is open.

EXAMINERS NOTE: Valve is located at the Day Tank

/ COMMENTS:

ILC-13 NRC 3PM K Page lOofil STEP 6: WHEN the day tank reaches 3/4 full, THEN close the AFOST SUPPLY Critical Step TO FUEL OIL DAY TANK for the day tank filled:

. FO-236, AFOST SUPPLY TO FUEL OIL DAY TANK B STANDARD: Candidate Simulates monitoring the Day Tank Level and then SAT closing FO-236 by rotating the valve handle until it is perpendicular with the pipe.

AS FOUND: Open UNSAT EXAMINERS CUE: Inform Candidate that time compression has occurred.

Inform Candidate the Day Tank level is now % full FO-236 handle has been rotated perpendicular to the pipe and is closed.

EXAMINERS NOTE: NONE COMMENTS:

3TEP 7: Inform the Control Room the EDG(s) is being filled from Alternate Fuel.

(Step 6)

SAT STANDARD: Candidate Simulates contacting the Control Room to report EDG Day Tank refilled UNSAT AS FOUND: N/A EXAMINERS CUE: When CRS or SM notified, respond as the CRS or SM and acknowledge the report EXAMINERS NOTE: NONE COMMENTS:

END OF TASK Terminating Cue: When CRS or SM notified that the EDG Day Tank has been refilled.

TIME STOP:

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

CANDIDATE INFORMATION:

Inform the candidate there are NO time critical steps in this JPM.

INITIAL CONDITIONS:

1. You are the Inside Auxiliary Operator.
2. A hostile action has resulted in a loss of off-site power and severely damaged the intake, with a subsequent loss of the ability to move water from the lake to cool plant equipment.
3. The Security Event has been terminated.
4. EPP-28 (Loss of Ultimate Heat Sink) has been implemented.
5. The B EDG is running and A EDG is secured.

INITIATING CUES:

The CRS has directed you to Align Back Up Fuel Oil in accordance with EPP-28 Attachment 5.

Rev. 13 EPP-28 LOSS OF ULTIMATE HEAT SINK Page 159 of 215 ATTACHMENT 5 Backup Fuel Oil Alignment (Page 1 of 2)

NOTE

  • The Alternate Fuel Oil Storage Tanks (AFOSTs) should only be used to supply the EDO Day Tanks during a design basis threat. The use of the AFOSTs for any other reason may constitute a violation of the renewed operating license. Reference RNP-L/LR-0009 Section 3.4.3.1.
  • Operators are 1IQ1 required for performance of this attachment.
  • A fill rate from the Alternate Fuel Oil Tanks of 30 gpm is expected.
  • The intent of the two C/A steps is to open and close the fill valve to maintain level between 1/4 and 3/4 full.
1. Close the normal EDO Day Tank header isolation valve for the running EDG(s):
  • A EDG - FO-25A DIESEL OIL DAY TANK A HEADER ISOLATION
  • B EDO - FO-25B, DIESEL OIL DAY TANK B HEADER ISOLATION
2. Open the EDO Day Tank Fill valve for the running EDO(s):
  • A EDO - FO-26A ALT / EMERO SUPPLY TO FUEL OIL DAY TANK A
  • B EDO - FO-26B, ALT / EMERO SUPPLY TO FUEL OIL DAY TANK B
3. Open the EDO Day Tank Solenoid Bypass valve for the tank(s) being filled:
  • A EDO - FO-28A DIESEL OIL DAY TANK A SOLENOID BYPASS
  • B EDO - FO-28B, DIESEL OIL DAY TANK B SOLENOID BYPASS

Rev. 13 EPP-28 LOSS OF ULTIMATE HEAT SINK Page 160 of 215 ATTACHMENT 5 Backup Fuel Oil Alignment (Page 2 of 2)

NOTE Only one tank should be filled at a time.

4. WREN day tank level reaches 1/4 full, THEN open the AFOST SUPPLY TO FUEL OIL DAY TANK for the day tank to be filled:

o FO231, AFOST SUPPLY TO FUEL OIL DAY TANK A OR o FO236, AFOST SUPPLY TO FUEL OIL DAY TANK B

5. the day tank reaches 3/4 full, THEN close the AFOST SUPPLY TO FUEL OIL DAY TANK for the day tank filled:

o F0-231, AFOST SUPPLY TO FUEL OIL DAY TANK A OR o FO236, AFOST SUPPLY TO FUEL OIL DAY TANK B

6. Inform the Control Room the EDG(s) is being filled from Alternate Fuel.

- END -