ML13339A840

Initial Exam 2013-301 Draft Sim_IN-Plant JPMs

ML13339A840
Person / Time
Site:	Robinson
Issue date:	11/30/2013
From:	NRC/RGN-II
To:	Progress Energy Carolinas
References
Download: ML13339A840 (292)

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{{#Wiki_filter:DUKE ENERGY H .B. Robinson ILC-13 NRC Licensing Exam Simulator JPMs In-Plant JPMs JEI-natSubmittal AQN

LICENSE EXAMINATION JOB PERFORMANCE MEASURE ILC-13 NRC JPM A RevO Establishing RCS Cold Shutdown Boron Concentration Concurred By: Date: Operations Approved By: Date: 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 KJA Rating (RO/SRO): 004A4.18 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: Performance SAT UNSAT 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. Step 9 Critical to align the Boric Acid pump back to AUTO so that it will be aligned for an Auto Makeup.

ILC-13 NRC JPM A Page 5 of 12 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 3PM, 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 3PM. 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 lAW 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). 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 OP301, 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 ofl2 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 ( TANDARD 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-i 10 and records flow of 70 gpm. EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: 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: Candidate determines that 700 gal / 70 gpm equates to 10 minutes UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: 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 fuiiy 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-488, THEN cycle MOV-350 to maintain RCP#1 Seal Leakoff temperature Iessthanl70°F SAT (Step 10) STANDARD: Candidate checks TR-488 and determines that RCP#1 Seal Leakoff temperatures are not approaching 170°F. UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: Candidate may decide to utilize ERFIS RCP parameter indication to monitor RCP parameters. BOOTH OPERATOR CUE: NONE 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 CUE: After candidate has demonstrated that they are monitoring RCP #1 Seal Leakoff temperature and time remaining inform the candidate UNSAT that time compression has occurred and the 10 minutes has elapsed. EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE 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: CRITICAL

• Check Boric Acid Pump aligned for blend in START STEP OR
• Place Boric Acid Pump aligned for blend in AUTO SAT (Step 12)

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

3. The plant has been shutdown JAW AOP-038, Rapid Downpower, from 100% RTP.

4. No equipment is out of service.

5. The first thte 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 AOP-035 S/G TUBE LEAK Page 53 of 65 CONTINUOUS USE ATTACHMENT 3 ESTABLISHING RCS COLD SHUTDOWN BORON CONCENTRATION (Page 1 of 3)

1. Record the minimum required Mode 5 Boron concentration.

1302 ppm

2. Determine RCS boron concentration change required to establish CSD boron concentration.

1302 1000 302

                                                   =

Required CSD Latest RCS Boron Concentration Boron Sample

3. Determine volume of boric acid to be added using Station Curve Book.

700 gallons

4. 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. THEN 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 FT-lb. BORIC ACID BYPASS FLOW.

gpm

9. Determine time required to establish CSD boron concentration.

Boric Acid Volume Required (gal) = minutes Fl-lb Fbowrate (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. any RCP #1 Seal Leakoff temperature approaches 170°F as indicated by TR-448, II cycle MOV-350, BA TO CHARGING PMP SUCT, to maintain RCP #1 Seal Leakoff temperature less than 170°F.

11. )N required amount of boric acid has been added, THEN 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:

• Check Boric Acid Pump aligned for blend in START OR
• Place Boric Acid Pump aligned for blend in AUTO

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-ll3A. 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: Date: Operations Approved By: Date: 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 JPM #: Candidate ILC-13 NRC JPM 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: SAT Performance UNSAT circle one Time (mm): Examiner: Print Name Signature Date

ILC-13 NRC JPM B Page 3 of 13 COMMENTS: OUESTION 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 ofl3 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/Equipment/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, Step 8.3.10. All steps prior to step 8.3.10 have been completed. In addition, step 8.3.10.a has been completed by the Shift Manager.

ILC-13 NRC JPM B Page 7 of 13 START TIME: I FEP 1: WHEN RCS temperature is between 350°F and 3 60°F, THEN perform CRITICAL the following: STEP

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 1 80°F/hr cooldown rate on the PZR. SAT (Step 8.3.10.b)

STANDARD: Places PC-444J in Manual and raises output to lower RCS pressure OR UNSAT places PZR Spray Valve Controller(s) in manual and raises output to lower RCS pressure. 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 STEP 2: 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 SAT
• SI Accumulator B, SI-865B CLOSED o MCC-6( 1 OJ) OPEN
• SI Accumulator C, SI865C CLOSED
• MCC-5(9F) OPEN UNSAT (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 (P1-921A, 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 BOOTH OPERATOR CUE: NONE COMMENTS: (

ILC-13 NRC JPM B Page 9 of 13 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)

a. 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.lO.d(1)) TJNSAT STANDARD: Verifies breaker indication for only A SI pump is illuminated.

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

ILC-l3 NRC JPM 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)

b. 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 SAT
• SI-883L (SI-868A,B,C TEST LINE ISOLATION) LOCKED CLOSED (Step 8.3.10.d(2))

STANDARD: Candidate verifies that SI-870A!B 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 CUE: When candidate contacts AO, inform candidate that SI-895T and SI-883L are in the LOCKED CLOSED position. EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE 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)

a. 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 BOOTHOPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM B Page 12 of 13 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
• RC-536, PORV BLOCK OPEN SAT
• PZR PCV-455C Overpressure Selector Switch LOW PRESSURE
• PCV-455C, PZR PORV AUTO
• PCV-455C Position Indication CLOSED
• PZR PCV-456 Overpressure Selector Switch UNSAT LOW PRESSURE
• 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
             - Places PCV-456 Overpressure selector switch in LOW PRESSURE
             - Verifies PCV-455C and PCV-456 GREEN closed indication and in AUTO on control board EXAMINERS CUE:                  NONE XAMINERS NOTE:

1 NONE BOOTH OPERATOR CUE: NONE COMMENTS: END OF TASK Terminating Cue: When the Pressurizer PORVs are placed in LTOP mode with RCS pressure between 350 psig and 375 psig, the evaluation for this 3PM is complete. 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 JAW GP-007, Step 8.3.10. All steps prior to step 8.3.10 have been completed. In addition, step 8.3.l0.a has been completed by the Shift Manager.

Section 8.3 Page 9 of 13 INIT 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.

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

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, Recommendation 3) SM

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 54 of 120

Section 8.3 Page 10 of 13 8.3.10 (Continued) INIT 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 Sl-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 hours. 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 / SI Pump C GP-007 Rev. 97 Page55of120

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 SI.-870B (BIT OUTLET) CLOSED SI-869 (LOOPS B AND C HOT LEG INJECTIONS SHUTOFF) CLOSED

                            -    Sl-895T (BIT BYPASS) LOCKED CLOSED SI-883L (SI-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 3.4.12.a. CAUTION TAG#_______ NIT SI-870A BIT OUTLET, handwheel Sl-870B BIT OUTLET, handwheel Sl-870A BIT OUTLET, control switch SI-870B BIT OUTLET, control switch Sl-869 LOOPS BAND C HOT LEG INJECTIONS SHUTOFF, handwheel S1-869 LOOPS BAND C HOT LEG INJECTIONS SHUTOFF, control switch Sl-895T BIT BYPASS Sl-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) irr 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,FWHDRSECTION                             OPEN
                     -    V2-6A,FWHDRSECTION                            CLOSED
                     -     V2-6B, FW HDR SECTION                          OPEN
                     -     V2-6B, FW HDR SECTION                        CLOSED
                     -     V2-6C, FW HDR SECTION                          OPEN
                     -     V2-6C, FW HDR SECTION                        CLOSED GP-007                                     Rev. 97                        Page 58 of 120

LICENSE EXAMINATION JOB PERFORMANCE MEASURE ILC-13 NRC JPM C RevO Establish RCS Bleed and Feed Concurred By: Date: Operations Approved By: Date: 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 ILC-13 NRC JPM C RO/SRO K/A Rating (RO/SRO): 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: SAT UNSAT Performance circle one Time (mm): Examiner: Print Name Signature Date

ILC-13 NRC JPM C Page 3 ofl6 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 ofl6 SIMULATOR OPERATOR INSTRUCTIONS:

1. Initialize the simulator to IC-912

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-S 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 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 SNK.

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.

ILC-l3 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 S/G if an intact S/G is available. / TEP 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, JAW RNO, goes to step 3. EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM C Page 8 of 16 STEP 3: Determine If Secondary Heat Sink Is Required As Follows:

a. Check RCS pressure GREATER THAN ANY NON-FAULTED S/G PRESSURE.

b. Check RCS temperature GREATER THAN 350F [310 F]

                                      -                                                   SAT (Step 3)

STANDARD: Using available indications, Candidate DETERMINES TINSAT

a. RCS pressure is greater than all non-faulted SIG 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-410 and/or TR-413 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 STEP 5: 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 teps 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. SAT EXAMINERS CUE: NONE EXAMINERS NOTE: NONE UNSAT 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 (OOTH 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 (Step 33)

SAT STANDARD: Candidate Verifies APP-002-F7, 1NSTR AIR HDR LO PRESS is Extinguished and Places IA-1716, INSTRUMENT AIR ISO TO CV Control Switch to the OVERRIDE position and observes that the INST AIR VALVE TO CONT PCV-1716 SHUT status light on the Containment Isolation Phase UNSAT 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. 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

c. Verify PZR PORV Block Valves BOTH OPEN

d. Open both PZR PORVs 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.

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 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: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

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

• PZR PORVs BOTH OPEN
• 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. IJNSAT 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,HEADVENT
• RC-570, PZR VENT
• RC-572, CV ATMOS SAT
• RC-567,HEAD VENT
• RC-569,PZRVENT
• RC-571,PTRISO (Step 37) IJNSAT 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 OMMENTS: Time Critical Stop Time

ILC-13 NRC JPM C Page 15 of 16 CRITICAL STEP 12: Depressurize At Least One Intact S/G 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.

CONTINUOUS USE H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 PLANT OPERATING MANUAL VOLUME 3 PART 4 FUNCTION RESTORATION PROCEDURE FRP-H. 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 AN narrow range level in all S/Cs 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 H__STEP_H ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED I CAUTI ON Feed flow is not re-established to any faulted S/C if an intact S/C 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 S/G 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) W1I adequate cooling with RHR is established, THEN reset SPDS and return to procedure and step in effect.

4. Check Any Two S/G Wide Range IF any two S/G Wide Range Levels Levels - LESS THAN 10% [19%] lower to less than 10% [19%]

IIN 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.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK Page 4 of 42 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED H__STEP_H

6. Check CST level - GREATER THAN Align SW backup to the AFW Pumps 10% using OP-4O2, Auxiliary Feedwater System, while continuing with this procedure.

IF the CST is low due to catastrophic failure is inaccessable, THEN align SW backup to the MDAFW Pumps using Attachment 2, SW Backup To NDAFW 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, THEN Go To Step 14.

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

9. Try To Establish Motor Driven AFW Flow To At Least One SIC 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) 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/Cs - 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 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED __STEP_H

10. Attempt To Start SDAFW Pinup As Follows:

a. Verify STEAM DRIVEN AFW PUMP a. I the steam supply valves STM SHUTOFF Valves - OPEN can 11T be opened. N 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 FRP-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK Page 7 of 42 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED __STEP_H

   *12. Check AFW Flow To S/Gs  -   GREATER   IF feed flow to at least one S/G THAN 300 GPM                          verified. IIIIN perform the following:

a. Maintain flow to restore narrow range level to greater than 8% [18%]

b. ]1IIT narrow range level is greater than 8% [18%] .

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 QCV-10426. COND POL SEC BYP.

c. Close V5-3, COND PUMP DISCH.

d. Momentarily place V5-3 to OPEN.

e. Start one Condensate Pump.

f. feedwater pressure is greater than 300 psig, verify V5-3 full open.

g. Open HCV1459, 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 RESPONSE NOT OBTAINED I NOTE The subsequent step will defeat ]j 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 H__STEP H ACTION/EXPECTED RESPONSE f RESPONSE NOT OBTAINED

18. Check SIG Levels As Follows:

a. Level In At Least One SIC - 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

• SIC Wide Range Level -

RISING IN AT LEAST ONE SIC

b. Maintain PW flow to restore SIC Level to greater than 8%

[18%]

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

Rev. 25 FRP-H.l RESPONSE TO LOSS OF SECONDARY HEAT SINK Page 10 of 42 __STEP_H ACTION/EXPECTED RESPONSE I 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.

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

b. Open CVC-311, AUX SPRAY

c. WHEN RCS pressure is less than 1950 psig, THEN close CVC-311

d. Observe the CAUTION prior to step 21 and Co 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, THEN close the PORV.

Rev. 25 FRP-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK Page 11 of 42 H__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 2l.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 NSIVs For Remaining S/Gs With Higher Levels

Rev. 25 FRP-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK Page 12 of 42 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED __STEP_H CAUTION The SI Accumulator Discharge Valves must be closed when S/C pressure is less than 240 psig to prevent nitrogen injection into the RCS.

24. Depressurize Selected S/G 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
• Steam Line PORVs controlled by Nitrogen per Attachment 2 of AOP-017, Loss of Instrument Air

Rev. 25 FRP-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK Page 13 of 42 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4_STEP_H

25. Check Selected SIG Pressure - Isolate SI Accumulators as GREATER THA1 240 PSIG follows:

a. Locally close the breakers for the following valves:

• SI-865C, ACCUMULATOR C DISCHARGE (MCC-5, CMPT 9F)
• SI-865A, ACCUMULATOR A DISCHARGE (MCC-5, CMPT 1 4F)
• SI-865B, ACCUMULATOR B DISCHARGE (MCC-6. CMPT 1OJ)

b. Verify CLOSED all ACCUMULATOR DISCHs

• SI-865A
• SI-865B
• SI-865C Vent any unisolated accumulator as follows:

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 SIG pressure -

BETWEEN 240 PSIG AND 600 PSIG

Rev. 25 FRP-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK Page 14 of 42 j__STEP_H ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED I

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) WTj feedwater pressure is greater than 300 psig, THEN verify V5-3 goes full open.

6) Open HCV-1459, LP HEATERS BYP.

IF at least one Condensate Pump can NOT be started, THEN 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.

ESTABLISHED

28. Check SIG 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 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED -J__STEP1I

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/G 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, THEN 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 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED H__STEP_H

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) j Cold Leg Injection can NOT be verified, THEN Co To Step 6.

33. Establish Instrument Air To CV As Follows:

a. Verify APP-O02-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-1716, 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 RESPONSE NOT OBTAINED I

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

As Follows:

• PZR PORVs - BOTH OPEN
• 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 ATMOS
• RC-567, HEAD VENT
• RC-569, PZR VENT
• RC-571, PRT ISO

38. Depressurize At Least One Intact SIG To Atmospheric Pressure Using Steam Line PORVs

Rev. 25 FRPH.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK Page 18 of 42 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED H__STEP_H

39. Isolate SI Accumulators As Follows:

a. Locally close the breakers for the following valves:

• SI-865C, ACCUMULATOR C DISCHARGE (MCC-5, CMPT 9F)
• SI-865A, ACCUMULATOR A DISCHARGE (MCC-5, CMPT 1 4F)
• SI-865B, ACCUMULATOR B DISCHARGE (MCC-6, CMPT 10J)

b. Verify CLOSED all ACCUMULATOR b. Vent any unisolated DISCHs accumulator as follows:

• SI-865A 1) Verify SI-855, ACC
• SI-865B NITROGEN ISO, is closed.
• SI-865C

2) Open the appropriate ACCUM VENT Valves:

• SI-853A
• SI-853B
• SI-853C

3) Open HIC936, 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 Procedure

Rev. 25 FRP-H.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK Page 19 of 42 H__STEP H ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED I 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.1 RESPONSE TO LOSS OF SECONDARY HEAT SINK Page 20 of 42 __STEP_H ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED I

45. Establish Instrument Air To CV As Follows:

a. Check Status of PCV-1716, a. IF APP-OO2-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-OO2-F7 AND Go To Step 45.b.

IF instrument air header pressure can I1Q be established, THEN observe the NQ prior to Step 46 and Go To Step 46.

b. Momentarily place IA PCV-1716, 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-l E 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 B Rev. 0 REACTOR TRIP RESPONSE EXCESSIVE RCS - COOLDOWN Concurred By: Date: Operations Approved By: Date: Superintendent/Supervisor Training

ILC-13 NRC JPM D Page 2 of 12 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 (RO/SRO): 007.EA1.10 3 .7/3 .7 007 EA 1.03 4.2/4.1 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: 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: Performance SAT UNSAT circle one Time (mm): Examiner: Print Name Signature Date

ILC-13 NRC JPM D Page 3 ofl2 COMMENTS: OUESTION DOCUMENTATION: Question:

Response

ILC-13 NRC JPM D Page 4 of 12 COMMENTS Step 5 is critical because closing the MSIVs and MSIV bypass valves ends the overcooling Step 7 is critical because the RCS temperature must be controlled by operating the S/G PORVs

ILC-13 NRC JPM D Page 5 of 12 SIMULATOR OPERATOR INSTRUCTIONS:

1. ResettolC-910

2. Place Simulator in Run, acknowledge alarms, and then place in FREEZE.

3. Open SCN OO9jLC_13_CR_NRC_JPM_D and follow instructions

ILC-13 NRC JPM D Page 6 of 12 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 lAW EOP-ES-0. 1 commencing at step 1.

ILC-13 NRC JPM D Page 7 of 12 START TIME: AUTION If SI actuation occurs during this procedure, EOP-E-O, REACTOR TRIP OR SAFETY INJECTION, should be performed. NOTE FOLDOUT for EOP-ES-O. 1 is in effect. STEP 1: Check RCS Temperatures:

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

STANDARTh Candidate checks RCS temperature on any of the following: ERFIS computer, ICCM, TR-408, or RTGB loop Tavg indication and goes to Step 1 UNSAT RNO EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: Place Simulator in RUN at Examiners CUE

 .OMMENTS:

STEP 2: IF temperature is less than 547°F AND lowering, THEN perform the following:

a. Stop dumping steam. SAT (Step 1.aRNO)

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

ILC-13 NRC JPM D Page 8 of 12 STEP 3: Verify S/G blowdown isolation valves are closed:

• FCV-1930A&B
• FCV-l931A&B
• FCV-1932A&B SAT (Step 1 .b RNO)

STANDARD: Candidate determines S/G Blowdown Isolations are open and directs the AO or Chem Tech to close the Blowdown valves via R-19 Radiation Monitors UNSAT EXAMINERS CUE: NONE 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. When directed to close SGBD valves, wait 2 minutes and execute command to deenergize R-19A,B & C lAW SCN File. COMMENTS: STEP 4: IF cooldown continues, THEN reduce total feed flow to minimum for decay heat removal:

• Maintain total feed flow greater than 300 gpm (0.2x 106 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 CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM D Page 9 of 12 STEP 5: 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 CUE: NONE EXAMINERS NOTE: Candidate may have taken a prompt and prudent action to close the MSIVs when to told to Stop Dumping Steam in UNSAT Step 1.aRNO. BOOTH OPERATOR CUE: NONE COMMENTS: STEP 6: 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 TANDARD: Candidate determines RCS temperature is Greater than 53 0°F EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM D Page 10 of 12 STEP 7: IF temperature is greater than 547°F AND rising, THEN perform the CRITICAL following: 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 5/0 steam line PORVs. SAT (Step 1.eRNO) STANDARD: Candidate recognizes that steam dump to condenser is NOT available and manually controls the Steam Line PORV controllers to obtain 547°F UNSAT EXAMINERS CUE: NONE EXAMINERS NOTE: Temperature will initially be less than 547°F but will rise until S/G PORVs are used to control RCS Temperature. This is a Continuous Action Step. BOOTH OPERATOR CUE: NONE COMMENTS: Candidate will recognize the need to establish higher AFW flows to allow for controlling RCS Temperatures STEP 8: 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:

ILC-13 NRC JPM D Page 11 of 12 STEP 9: Check Feedwater Status

b. Main feedwater reg valves CLOSED

c. Total feed flow to S/Gs GREATER THAN 300 GPM (0.2x106 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: STEP 10: Check S/G Levels:

a. Narrow range levels GREATER Than 8%

RNO Maintain total feed flow THAN 8% greater than 300 gpm (0.2x1 06 pph) until narrow range level is greater than 8% in at least one SAT S/G. (Step 3.a RNO) STANDARD: Candidate recognizes need to adjust AFW flow to raise S/G levels and UNSAT control between 8% and 50% EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS: END OF TASK Terminating Cue: When Candidate has taken action(s) to stabilize RCS Average temperature at approximately 547°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.
• 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 lAW EOP-ES-0. 1 commencing at step 1.

CONTINUOUS USE H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 PLANT OPERATING MANUAL VOLUME 3 PART 4 EMERGENCY OPERATING PROCEDURE EOP-ES-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 -

EOP-ES-O.1 FOLDOUT FOR EOP-ES-O.1 Rev. 4

1. SI ACTUATION CRITERIA LE either condition listed below occurs. THEN manually actuate BOTH trains of SI ANI2 Go To EOP-E-0, REACTOR TRIP OR SAFETY INJECTION, Step 1:

• RCS subcooling based on core exit TCs - LESS THAN 35°F OR
• PZR level CANNOT BE MAINTAINED GREATER THAN 7%

2. LOSS OF POWER CRITERIA j power is lost. Th4 perform the following:

a. LE 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.

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 7, DC Bus Or Instrument Bus Failure.

5. LOSS OF ULTIMATE BEAT SINK CRITERIA IE attack on RNP Site is in progress A either condition listed below occurs, THEN Go To EPP-28, LOSS OF ULTIMATE HEAT SINK, Step 1:

• Total Loss Of SW OR
• Loss Of Lake Robinson Dam integrity

Rev. 4 EOP-ES-O.1 REACTOR TRIP RESPONSE Page 3 of 37 -ti-{ 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: j temperature is less than 547°F AND lowering, IIIN 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.2x1O 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. IF temperature lowers to less than 530°F, THEN borate RCS to cold shutdown boron concentration while continuing with this procedure.

(CONTINUED NEXT PAGE)

EOP-ES-O.l FOLDOUT FOR EOP-ES-O.l Rev. 4

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 OR
• PZR level - CANNOT BE MAINTAINED GREATER THAN 7%

2. LOSS OF POWER CRITERIA IF power is lost, THEN perform the following:

a. IE 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.

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. INSTRUNENT 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

j. attack on RNP Site is in progress AJ either condition listed below occurs, THEN Go To EPP-28, LOSS OF ULTIMATE HEAT SINK, Step 1:

• Total Loss Of SW OR
• Loss Of Lake Robinson Dam integrity

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

1. (CONTINUED)

IE temperature is greater than 547°F MII?. 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 SIG steam line PORVs.

2. Check Feedwater Status

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

Continue With Step 3.

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

CLOSED LE any valve(s) can IQ1 be closed, THEN manually close associated feedwater header section valve(s).

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

6 PPH) (O.2x10

• AFW OR
• Main feedwater on bypass

EOPES-O.1 FOLDOUT FOR EOP-ES-O.l Rev. 4

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 OR
• PZR level - CANNOT BE MAINTAINED GREATER THAN 7%

2. LOSS OF POWER CRITERIA j power is lost, THEN perform the following:

a. L 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.

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. INSTRUNENT 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 I[EAT SINK CRITERIA IE attack on RNP Site is in progress ANJ2 either condition listed below occurs, THEN Go To EPP-28. LOSS OF ULTIMATE HEAT SINK, Step 1:

• Total Loss Of SW OR
• Loss Of Lake Robinson Dam integrity

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

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 (0.2x1O range level is greater than 8% in at least one S/C.

b. Control feed flow to maintain b. IE narrow range level in any narrow range levels - BETWEEN S/C continues to rise. THEN 8% AND 50% stop feed flow to that SIC.

EOP-ES-O.1 FOLDOUT FOR EOP-ES-O.1 Rev. 4

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:

o RCS subcooling based on core exit TCs - LESS THAN 35°F OR

• PZR level - CANNOT BE MAINTAINED GREATER THAN 7%

2. LOSS OF POWER CRITERIA IF power is lost, THEN perform the following:

a. IE 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.

3. AFW SUPPLY SWITCHOVER CRITERIA IF CST level lowers to less than 10%, IN 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 7, DC Bus Or Instrument Bus Failure.

5. LOSS OF ULTIMATE HEAT SINK CRITERIA IE attack on RNP Site is in progress ANI2 either condition listed below occurs, THEN Go To EPP-28, LOSS OF ULTIMATE HEAT SINK, Step 1:

• Total Loss Of SW OR
• Loss Of Lake Robinson Dam integrity

Rev. 4 EOP-ES-O.l REACTOR TRIP RESPONSE Page 6 of 37

STEP_H ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

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

BY OFFSITE POWER

a. any AC emergency buss(es) are IIQT energized by offsite power. THEN perform the following:

1) Verify EDG(s) running.

2) Verify EDO(s) have assumed the following loads:

• MDAFW pump
• CCW pump
• SW pump

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. IF any AC emergency bus is energized. THEN try to restore power to affected bus from EDO.

(CONTINUED NEXT PAGE)

EOPESO.1 FOLDOUT FOR EOP-ES-O.1 Rev. 4

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 OR
• PZR level - CANNOT BE MAINTAINED GREATER THAN 7%

2. LOSS OF POWER CRITERIA jj power is lost, THEN perform the following:

a. i 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.

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, THEN perform Attachment 7, DC Bus Or Instrument Bus Failure.

5. LOSS OF ULTIMATE HEAT SINK CRITERIA IE attack on RNP Site is in progress AN]2 either condition listed below occurs, THEN Go To EPP-28, LOSS OF ULTIMATE HEAT SINK, Step 1:

• Total Loss Of SW OR
• Loss Of Lake Robinson Dam integrity

Rev. 4 EOP-ES-O.l REACTOR TRIP RESPONSE Page 7 of 37 STEP H ACTION/EXPECTED RESPONSE I 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 EPP-21, 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-6O1. DC Supply System.

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

• Fuel pool level
• Fuel pool temperature

f. IE DS bus is IQI 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:

• IF EPP-21 is JfQ1 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)

EOPES-O.1 FOLDOUT FOR EOP-ES-O.1 Rev. 4

1. SI ACTUATION CRITERIA IE. either condition listed below occurs. IN 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 OR
• PZR level - CANNOT BE MAINTAINED GREATER THAN 7%

2. LOSS OF POWER CRITERIA IE power is lost, THEN perform the following:

a. LE 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 30)

c. Restore affected controls to automatic as necessary.

3. AFW SUPPLY SWITCHOVER CRITERIA I.E 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 7, DC Bus Or Instrument Bus Failure.

5. LOSS OF ULTIMATE BEAT SINK CRITERIA I.E attack on RNP Site is in progress either condition listed below occurs, THEN Go To EPP-28, LOSS OF ULTIMATE HEAT SINK, Step 1:

• Total Loss Of SW OR
• Loss Of Lake Robinson Dam integrity

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

STEP H ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

4. (CONTINUED)

h. Locally verify air side seal oil backup pump is running.

EOP-ES-O.1 FOLDOUT FOR EOP-ES-O.l Rev. 4 1.. SI ACTUATION CRITERIA IF either condition listed below occurs. THEN manually actuate BOTH trains of SI Go To EOP-E-O, REACTOR TRIP OR SAFETY INJECTION, Step 1:

• RCS subcooling based on core exit TCs - LESS THAN 35°F OR
• PZR level - CANNOT BE MAINTAINED GREATER THAN 7%

2. LOSS OF POWER CRITERIA IF power is lost, IIN perform the following:

a. LE 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.

3. AFW SUPPLY SWITCHOVER CRITERIA U1 CST level lowers to less than 10%, THEN switch to backup water supply using OP-4O2, Auxiliary Feedwater System.

4. DC BUS, INSTRUNENT BUS. OR NCC-5 FAILURE CRITERIA IF DC bus A, DC bus B, any instrument bus, or MCC-5 is deenergized. IIN perform Attachment 7, DC Bus Or Instrument Bus Failure.

5. LOSS OF ULTIMATE HEAT SINK CRITERIA IE attack on RNP Site is in progress A either condition listed below occurs. THEN Go To EPP-28, LOSS OF ULTIMATE HEAT SINK, Step 1:

• Total Loss Of SW OR
• Loss Of Lake Robinson Dam integrity

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

STEP_H ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED

5. Check PZR Level Control:

a. PZR Level - GREATER THAN 14% a. Perform the following:

1) Verify letdown is isolated:

o Letdown line isolation valves closed:

• CVC-204A
• CVC-2O4B
• 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% power is available, THEN reenergize PZR heaters as necessary.

(CONTINUED NEXT PAGE)

EOP-ESOJ FOLDOUT FOR EOPES-O.1 Rev. 4

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 OR
• PZR level - CANNOT BE MAINTAINED GREATER THAN 7%

2. LOSS OF POWER CRITERIA LE power is lost, THEN perform the following:

a. .1E 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.

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 NCC-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 I.E attack on RNP Site is in progress either condition listed below occurs, THEN Go To EPP-28, LOSS OF ULTIMATE HEAT SINK, Step 1:

• Total Loss Of SW OR
• Loss Of Lake Robinson Dam integrity

Rev. 4 EOP-ES-0.l REACTOR TRIP RESPONSE Page 10 of 37 j STEP_H ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I

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-121, 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%, THEN 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%.

EOP-ES-O.l FOLDOUT FOR EOP-ES-O.l Rev. 4

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 OR
• PZR level - CANNOT BE MAINTAINED GREATER THAN 7%

2. LOSS OF POWER CRITERIA L power is lost, IIEN 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.

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 11CC-S is deenergized, THEN perform Attachment 7, DC Bus Or Instrument Bus Failure.

5. LOSS OF ULTIMATE BEAT SINK CRITERIA

j. attack on RNP Site is in progress jj either condition listed below occurs, THEN Go To EPP-28, LOSS OF ULTIMATE HEAT SINK, Step 1:

• Total Loss Of SW OR
• Loss Of Lake Robinson Dam integrity

Rev. 4 EOP-ES-O.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-hO.

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-ll5B can NOT be opened, THEN locally open CVC-358, RWST to charging pump suction.

b. Close VCT outlet, LCV-115C.

EOP-ES-O.l FOLDOUT FOR EOP-ES-O.1 Rev. 4

1. SI ACTUATION CRITERIA IF either condition listed below occurs, THEN manually actuate BOTH trains of SI AND Go To EOP-E-0, REACTOR TRIP OR SAFETY INJECTION, Step 1:

• RCS subcooling based on core exit TCs - LESS THAN 35°F OR
• PZR level - CANNOT BE MAINTAINED GREATER THAN 7%

2. LOSS OF POWER CRITERIA LE 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.

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 7, DC Bus Or Instrument Bus Failure.

5. LOSS OF ULTIMATE HEAT SINK CRITERIA IE attack on RNP Site is in progress ANI2 either condition listed below occurs, THEN Go To EPP-28, LOSS OF ULTIMATE HEAT SINK, Step 1:

• Total Loss Of SW OR
• Loss Of Lake Robinson Dam integrity

Rev. 4 EOP-ES-O.1 REACTOR TRIP RESPONSE Page 12 of 37 f STEP_H ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED

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. i pressure is less than TRENDING TO 2235 PSIG 2235 psig ANI2 lowering, THEN perform the following:

1) Verify PZR PORVs are closed.

i any valve can NQ. be closed, THEN manually close its block valve.

2) Verify PZR spray valves are closed.

IF valve(s) can NQT. 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)

EOP-ES-0.1 FOLDOUT FOR EOP-ES-O.1 Rev. 4

1. SI ACTUATION CRITERIA IF either condition listed below occurs, THEN manually actuate BOTH trains of SI AND Go To EOP-E-0, REACTOR TRIP OR SAFETY INJECTION. Step 1:

• RCS subcooling based on core exit TCs - LESS THAN 35°F OR
• PZR level - CANNOT BE MAINTAINED GREATER THAN 7%

2. LOSS OF POWER CRITERIA IE power is lost, THEN perform the following:

a. LE NO charging pumps are running, IIIEN 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.

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. INSTRUNENT BUS. OR NCC-5 FAILURE CRITERIA IF DC bus A, DC bus B, any instrument bus, or NCC-5 is deenergized, IIIN perform Attachment 7. DC Bus Or Instrument Bus Failure.

5. LOSS OF ULTIMATE HEAT SINK CRITERIA IE attack on RNP Site is in progress ANL either condition listed below occurs, THEN Go To EPP-28. LOSS OF ULTIMATE HEAT SINK, Step 1:

• Total Loss Of SW OR
• Loss Of Lake Robinson Dam integrity

Rev. 4 EOP-ES-O.1 REACTOR TRIP RESPONSE Page 13 of 37 j STEP H ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

7. (CONTINUED)

IE pressure is greater than 2235 psig ANJ2 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 IE 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 NQI available or effective, THEN use PZR PORV(s).

8. Transfer Condenser Steam Dump To condenser steam dumps are liQ[

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

EOPESO.l FOLDOUT FOR EOPESO.l Rev. 4

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 OR
• PZR level - CANNOT BE MAINTAINED GREATER THAN 7%

2. LOSS OF POWER CRITERIA IE 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.

3. AFW SUPPLY SWITCHOVER CRITERIA IF CST level lowers to less than 10%, EM switch to backup water supply using OP-4O2, Auxiliary Feedwater System.

4. DC BUS, INSTRUMENT BUS, OR MCC5 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 j attack on RNP Site is in progress ANE either condition listed below occurs, THEN Go To EPP-28, LOSS OF ULTIMATE HEAT SINK, Step 1:

• Total Loss Of SW OR
• Loss Of Lake Robinson Dam integrity

Rev. 4 EOP-ES-O.1 REACTOR TRIP RESPONSE Page 14 of 37 j STEP H ACTION/EXPECTED RESPONSE I 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. IF offsite power is available, THEN establish conditions for starting RCP(s) using OP-id, 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, THEN dump more steam.

EOP-ES-O.1 FOLDOUT FOR EOP-ES-O.1 Rev. 4

1. SI ACTUATION CRITERIA IF either condition listed below occurs, THEN manually actuate BOTH trains of SI AND Go To EOP-E-0, REACTOR TRIP OR SAFETY INJECTION, Step 1:

• RCS subcooling based on core exit TCs - LESS THAN 35°F OR
• PZR level - CANNOT BE MAINTAINED GREATER THAN 7%

2. LOSS OF POWER CRITERIA IF power is lost, perform the following:

a. IE 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.

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 7. DC Bus Or Instrument Bus Failure.

5. LOSS OF ULTIMATE IIEAT SINK CRITERIA j attack on RNP Site is in progress either condition listed below occurs, THEN Go To EPP-28, LOSS OF ULTIMATE HEAT SINK, Step 1:

• Total Loss Of SW OR
• Loss Of Lake Robinson Dam integrity

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

ILC-13 NRC JPM E Page 2 of 12 LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task: 01000151705, Perform Auto Action Verification JAW EOP-E-O. Alternate Path: YES JPM #: Candidate ILC-13 NRC JPM E 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 lAW EOP-E-0. Preferred Evaluation Location: Preferred Evaluation Method: Simulator X In-Plant Perform X Simulate

References:

1*** EOP-E-0 Validation Time: 4 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 IJNSAT Performance circle one Time (mm): Examiner: Print Name Signature Date

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

Response

ILC-13 NRC JPM B Page 4 of 12 COMMENTS Step 3 Critical since at least one SI-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 JPM E Page 5 of 12 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 JPM.

4. Place simulator in RUN when directed by the examiner.

ILC-13 NRC JPM E Page 6 of 12 Tools/Equipment/Procedures Needed: EOP-E-0 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 HAS 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. Candidate is given a marked up copy of EOP-E-0, Step 9.

ILC-13 NRC JPM E Page 7 of 12 START TIME: fEP 1: Check CV spray actuated. (RNO Step 9.a.1) SAT STANDARD: Candidate observes that the CV Spray signal has initiated by observing armunciator APP-002-D1, 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 JPM 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
• SI-880D 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-8 80 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-845C to reduce flow to approximately 12 gpm. (Tolerance 8 16 gpm) EXAMINERS CUE: NONE U1SAT 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 LTNSAT 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 HAS 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. Candidate is given a marked up copy of EOP-E-0, Step 9.

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

9. Check CV Spray Required:

a. CV pressure - HAS REMAINED a. Perform the following:

LESS THAN 10 PSIG

1) Check CV spray actuated.

IE CV spray is NQ] 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-880A
• SI-880B
• 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-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 S/C 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 NJ 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/G C)

c. Close AFW header discharge valve for faulted S/G(s)

• V2-16A (S/G A)
• V2-16B (S/G B)
• V2-16C (S/G 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%, THEN switch to backup water supply using OP-4O2, Auxiliary Feedwater System.

4. DC BUS, INSTRUMENT BUS, OR I4CC-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 SEP 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 - 1 ACTUATED b. IE CV spray inadvertently actuated, THEN perform the following:

1) Stop all RCPs.

2) Override containment spray signal:

• Place Containment Spray key switch to OVRD/RE SET.

3) Reset containment isolation Phase B.

4) Stop CV spray pumps.

5) Close CV spray pump discharge valves:

• SI-880A
• SI-88OB
• SI-88OC
• SI-88OD

6) Close CV spray additive tank discharge valves:

• SI-845A
• SI-845B

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 [50°F]

2. FAULTED SIC AFW 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 IQ] 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 (SIC B)
• V2-l4C (S/C C)

c. Close AFW header discharge valve for faulted S/C(s):

• V2-16A (SIC A)
• V2-l6B (S/G B)
• V2-16C (SIC 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. 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.

LICENSE EXAMINATION JOB PERFORMANCE MEASURE ILC-13 NRC JPM F Rev. 0 Operation with High Switchyard Voltage Concurred By: Date: Operations Approved By: Date: 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 ILC-13 NRC JPM F RO/SRO K/A Rating (ROJSRO): 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: Performance SAT UNSAT circle one Time (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 12 is critical because starting HVH-5B will lower voltage on Bus E-2. Step 14 is critical because starting HVE-2B will lower voltage on Bus E-2. 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. 1C916

2. SCN: OO9ILC13NRCCRJPMF (Not needed. All malfunctions snapped into IC.)

3. AOP-031 performed and marked up to step 21.

4. Reset to IC 916 and place in Run, clear alarms and then place in Freeze.

5. Place simulator to Run when Candidate assumes the watch.

ILC-13 NRC JPM F Page 6 of 22 ToolslEcjuipment/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 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.

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. EXAMINERS CUE: NONE UNSAT 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 (Step 22.a.) SAT 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. EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS: STEP 4: Check EDG B Status as Follows:

b. Check EMERGENCY DIESEL GENERATOR B RUI\INING -

(Step 23.b.) SAT STANDARD: Determines that B EDG is NOT running EXAMINERS 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 RU1NTNG - 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
• EDG B PRE-LUBE OIL PUMP SAT
• Fuel Oil Transfer Pump B (Step 24)

STANDARD: Determines that NONE of these components are running. UNSAT EXAMINERS CUE: Inform candidate that another candidate will track the run times. EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM F 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) STANDARD: Candidate determines that load on Emergency Bus E-1 has NOT been raised based on information given in the Cue. JJNSAT 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 RUN1SFNG

             - HVH-3
             - HVH-4                                                SAT (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 nmning. EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM F Page 12 of 22 STEP 11: Check CRDM COOLING FAN, HVH-5B - RUNNING (Step 27.d) SAT STANDARD: Candidate Determines that HVH-5B 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: CRITICAL

1. Start HVH-5B STEP

2. Stop HVH-5A (Step 27.d RNO) 1 TANDARD: Candidate starts HVH-5B and stops HVH-5A.

SAT EXAMINERS CUE: NONE EXAMINERS NOTE: E-2 Voltage should lower to approx. 505.9 Volts. UNSAT BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM F Page 13 of22 STEP 13: Check AUX BLDG EXH FAN, HVE-2B RUI\IMNG - (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: CRITICAL

1) Start HVE-2B STEP

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

TANDARD Candidate starts HVE-2B and stops HVE-2A SAT ( EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: E-2 Voltage should lower to approx. 505.4 Volts. BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM F Page 14 of 22 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) STANDARD: Candidate determines that Bus E-2 Voltage IS greater than 505 Volts. SAT EXAMINERS CUE: NONE iXAMINERS NOTE: NONE UNSAT 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 RUNING (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 JPM F Page 16 of 22 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. XAMINERS CUE: 1 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 of 22 STEP 21: Transfer 4160V BUS 4 to the STARTUP TRANSFORMER as follows:

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

STANDARD: Candidate insets the synchroscope key into 4 KV TIES Synchroscope Key UNSAT Switch. EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS: STEP 22: Transfer 4160V BUS 4 to the STARTUP TRANSFORMER as follows: CRITICAL

b. Place the Syncbroscope Switch to the BUS 3 & 4 position STEP (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) STANDARI: 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

d. Momentarily place the Control Switch for 4KV BUS 3-4 TIE, BKR STEP 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 19 of 22 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 UNIT AUX TO 4 KV BUS 4 BKR, 52/20 OPEN -

SAT (Step 31.1) C 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

f. RNO: Perform the following STEP

• 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 TJNSAT control switch for BKR 52/20 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 position. SAT EXAMINERS CUE: NONE EXAMINERS NOTE: NONE UNSAT BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM F Page 21 of 22 STEP 29: Check the following:

• Emergency BUS E-1 Voltage LESS THAN 505 VOLTS AND
• Emergency BUS E-2 Voltage LESS THAN 505 VOLTS SAT (Step 32)

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. BOOTH OPERATOR CUE: NONE 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 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 JAC 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 H. 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 PurDose 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 NOT required for momentary spikes in system voltage caused by instability problems due to momemtary spikes caused by starting an EDG.

2. ENTRY CONDITIONS

a. High alarm on APP-036-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 Ky.

                                      - END -

Rev. 14 AOP-031 OPERATION WITH HIGH SWITCHYARD VOLTAGE Page 3 of 22 __STEP_H ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I (7 f Make PA Announcement For Procedure Entry. Check Main Generator - IN SERVICE Go To Step 4. Check Generator Reactive Load - Positio the V GE ADJUSTER

   /-    At 35 MVARS        -?       Switch, as ne ess ry to maintain reactiv lo    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, THEN Go To Step 6 Check Voltage As Follows: Return to procedure and step in

             /                                    effect.

(ri) APP-036-E3, SUT PRI

        /     OVER/UNDER VOLTAGE  -

ILLUMINATED OR WEST 115KV BUS VOLTAGE - GREATER THAN 119 KV OR Emergency BUS E-l Voltage - GREATER THAN 505 VOLTS OR Emergency BUS E-2 Voltage - GREATER THAN 505 VOLTS

Rev. 14 AOP031 OPERATION WITH HIGH SWITCHYARD VOLTAGE Page 4 of 22 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ]__STEP_H

• 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-l obtain voltage for the ELV3O21A - E-2 unavailable ERFIS points
• QP E1E2 - Plot using Attachment 1.

b. Direct an Operator to obtain Emergency Bus voltage for the unavailable ERFIS points using local indication at 1 hour intervals:

• EI-213 - 480V BUS E-l
• EI-2l4 - 480V BUS E-2

c. 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-03l OPERATION WITH HIGH SWITCHYARD VOLTAGE Page 5 of 22 ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED Implement The EALs Check Emergency BUS E-1 Voltage IF Emergency BUS B-i voltage

     - GREATER THAN 505 VOLTS                exceeds 505 volts, THEN observe the Q1 prior to Step 11 and Go To Step ii.

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-306, 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

STEP H ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED

13. Check EDG A Status As Follows:

a. Check Main Generator - ON LINE a. IF EDG A is Paralleled to Emergency Bus E-1, THEN 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
• CCW PUMP B

15. Check Emergency BUS E-1 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 __STEP H ACTION/EXPECTED RESPONSE f RESPONSE NOT OBTAINED

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 CRUM 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-20l, Residual heat Removal System, Switching RHR Pumps In The Core Cooling Mode.

Rev. 14 AOP-03l OPERATION WITH HIGH SWITCHYARD VOLTAGE Page 8 of 22 -tJ-t 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, Go To Step 32.

Go To Step 21.

20. Go To Step 32

 *21. Check Emergency BUS E-2 Voltage        IE Emergency BUS E-2 voltage
       - GREATER THAN 505 VOLTS               exceeds 505 volts, THEN Observe the IQ]E 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 H__STEP_H ACTION/EXPECTED RESPONSE I 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. IIIN 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-1 Go To Step 27.

          - HAS BEEN RAISED USING STEP 18

26. Go To Step 28.

Rev. 14 AOP031 OPERATION WITH HIGH SWITCHYARD VOLTAGE Page 10 of 22 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED H__STEP_H

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

             *    }IVH-4

c. Check CONT RM AIR HANDLING. c. Switch Control Room HVA-lB - RUNNING Ventilation to Train B using OP-9O6, 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-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

STEP H ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED I

   *28. Check Emergency BUS E-2 Voltage            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 RESPONSE NOT OBTAINED

31. Transfer 4160V BUS 4 To The STARTUP TRANSFORMER 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 52/19 to the CLOSE position

e. Check BKR 52/19 - CLOSED e. Contact I&C to check BKR 52/19.

Go To Step 3l.g.

f. Check UNIT AUX TO 4KV BUS 4 f. Perform the following:

BKR, 52/20 - OPEN

• Simultaneously depress the THINK pushbutton AND place the control switch for BKR 52/20 to the OPEN position.

OR

• Using the Control Switch At 4l60V 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 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED H__STEP_H

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-1 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
• CCW PUMP B

d. Using the applicable plant procedure, start idle loads.

   *33*  Check Voltage As Follows:            WWN   APP-036-E3 is Extinguished, West 115KV Bus voltage is less

• APP-036-E3, SUT PRI than 119 Ky, and Emergency BUS OVER/UNDER VOLTAGE - E-1 AND Emergency BUS E-2 EXTINGUISHED voltage are less than 502 volts, IiN Go To Step 34.

AND Go To Step 10.

• WEST 115KV BUS VOLTAGE -

LESS THAN 119 KV AND

• Emergency BUS E-l Voltage -

LESS THAN 502 VOLTS AND

• Emergency BUS E-2 Voltage LESS THAN 502 VOLTS

34. Terminate Monitoring Of Emergency BUS E-l D 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 j__STEP_H ACTION/EXPECTED RESPONSE 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 AOP031 OPERATION WITH HIGH SWITCHYARD VOLTAGE Page 15 of 22

STEP_H ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUT ION SAF 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, THEN Go To Step 37.f.

(CONTINUED NEXT PAGE)

Rev. 14 AOP-031 OPERATION WITH HIGH SWITCHYARD VOLTAGE Page 16 of 22 j__STEP_H ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED I

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 5 2/19 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 TRANSF 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 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 ATTACI{MENT 1 OBTAINING EMERGENCY BUS VOLTAGE USING A VOLTMETER (Page 1 of 3) CAUTION Circuits inside Emergency BUS E-1 AN1 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-1 AND E-2.
• Steps 1 through 6 give the directions for obtaining voltage on Emergency BUS E-l. 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. obtaining voltage on Emergency BUS E-l is unnecessary. THEN Go To Step 9.

3. Open the door of Metering Cubicle 17A on Emergency BUS E-1.

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 l7A.

6. Notify the Control Room that Emergency BUS E-1 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 B-i VOLTMETER SWITCH on the front of Cubicle 17A to select one of the three phases.

b. Multiply the muitimeter 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. WHEN notified by the Control Room that voltage monitoring is no longer required, THEN restore as follows:

a. Remove the multimeter probes from the local voltmeter (EI-213)

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 B-i has been restored to normal and that this Attachment is complete.

9. Obtain a Fluke 8520A 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.

ii. 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. WII notified by the Control Room that voltage monitoring is no longer required. THEN 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 E-2 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 KV, and 48OV BUS E-1 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-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 KV, and 48OV BUS E-1 AND 480V BUS E-2 voltage are less than 502 volts, THEN Go To Step 34.

AOP-031, Revision 14 Suimnary 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-1 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 E2 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 B-i Load has already been raised per step 18. AOP-031 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: Date: Operations Approved By: Date: 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 (RO/SRO): 008K1 .02 3.3/3.4 008K3.03 4.1/4.2 026AK3 .03 4.0/4.2 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 JPM G Page 5 of 19 SIMULATOR OPERATOR INSTRUCTIONS:

1. Initialize the simulator to IC- 13

( 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_JPM_G

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 Tools/Equipment/Procedures Needed: APP-O0 1 -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 The CRS is involved with a security situation and has told you to take the necessary actions for any alarm conditions that might arise.

ILC-13 NRC JPM G Page 7 of 19 START TIME: LEP 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: FEP 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 1PM G Page 8 ofl9 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-OO1-F5, CCW PMP LO PRESS ILLUMiNATED-

c. Release CCW Pump Switches.

d. Go to Step 13 (Section A Step 6) SAT STANDARD: Candidate places ALL CCW pump switches to STOP and holds them while verifying APP-OO1-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: NONE COMMENTS: STEP 12: Determine if RHR Must be Stopped as Follows:

a. Check CCW Pumps ALL STOPPED

b. Check RHR Pump status ANY PUMP RIThThJING TN 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 STEP 13: Check CV for CCW Break Using Control Room Indications As Follows:

a. Monitor the following CV indications:

• ERFIS CV SUMP LEVEL
• 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 SAT (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 CUE: NONE 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 OMMENTS: STEP 14: Check CV for CCW Break Using Control Room Indications As Follows:

b. Check CV LOCATION OF CCW BREAK (Section A Step 18.b)

SAT STANDARD: Candidate determines that CCW leak is in the CV. EXAMINERS CUE: NONE UNSAT EXAMINERS NOTE: NONE 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:

d. Check APP-OO1-B1, RCP BRG COOL WTR LO FLOW -

ILLUMNATED (Section A Step 19.a) SAT ( IANDARD 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:

e. Check ANY RCP BEARING HI TEMP Alarm ILLUMINATED -

• APP-00l-B3 OR SAT
• APP-001-D3 OR
• APP-001-F3.

RNO: makeup capacity to the CCW Surge Tank is NOT sufficient UNSAT to maintain level, THEN Go to Step 20. (Section A Step 19.b) STANDARD: Candidate recognizes that NO RCP BEARING HI TEMP Alarm is illuminated and that makeup capacity to CCW Surge Tank is not sufficient. EXAMINERS CUE: NONE EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS: 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:

ILC.13 NRC JPM G Page 16 of 19 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: 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. C KAMINERS CUE: NONE UNSAT EXAMINERS NOTE: NONE BOOTH OPERATOR CUE: NONE COMMENTS:

ILC-13 NRC JPM G Page 17 of 19 STEP 21: Perform the following:

c. W Control Rods were inserted on the trip, THEN perform the following:

1) IF RCS temperature is greater than Q, equal to 3 50°F, THEN SAT Go to Step 23.

2) IF RCS temperature is less than 3 50°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-O and inform candidate that the CRS and BOP are continuing in EOP-E-O. 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

• CC.716A, CCW TO RCP ISO STEP
• CC-716B, CCW TO RCP ISO
• CC-730, BRG OUTLET ISO
• CC-735, THERM BAROUT ISO SAT
• FCV-.626, THERM BAR FLOW CONT (Section A Step 24)

STANDARD: Candidate uses RTGB switches to close the following valves: UNSAT

• CC-716A, CCW TO RCP ISO
• CC-716B, CCW TO RCP ISO
• CC73O, BRG OUTLET ISO
• CC-735, THERM BAR OUT ISO
• 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 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: The CRS is involved with a security situation and has told you to take the necessary actions for any alarm conditions that might arise.

CONTINUOUS USE H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 PLANT OPERATING MANUAL VOLUME 3 PART 5 ABNORMAL OPERATING PROCEDURE AOP-014 COMPONENT COOLING WATER SYSTEM MALFUNCTION REVISION 35 Page 1 of 118

Rev. 35 AOP-014 COMPONENT COOLING WATER SYSTEM MALFUNCTION Page 2 of 118 Purpose and Entry Conditions (Page 1 of 3)

1. PURPOSE This procedure provides the instructions necessary to mitigate abnormal conditions associated with Component Cooling Water (CCW) or any reduction in cooling to components served by the CCW System. Instructions for mitigating leakage into and out of the CCW system are also provided.

Rev. 35 AOP-014 COMPONENT COOLING WATER SYSTEM MALFUNCTION Page 3 of 118 Purpose and Entry Conditions (Page 2 of 3) NOTE This procedure assumes valid indications are present. This procedure should NOT be entered for transmitter failures.

2. ENTRY CONDITIONS

a. Any abnormal condition associated with the CCW System as indicated by:

• Improper Surge Tank Level
• Low Flow
• High CCW Temperature
• Unacceptable System Leakage

b. From AOP-005. Radiation Monitoring System. following an alarm on radiation monitor R-17 a confirmed rise in CCW Surge Tank level.

(CONTINUED NEXT PAGE)

Rev. 35 AOP-014 COMPONENT COOLING WATER SYSTEM MALFUNCTION Page 4 of 118 Purpose and Entry Conditions (Page 3 of 3)

2. (CONTINUED)

c. From APP-OOl, Miscellaneous NSSS:

• APP-OOl-A1, RCP BRG COOL WTR HI TEMP
• APP-OO1-A4, CCW SURGE TIC HI/LO LVL
• APP-OO1-A8. CCW TO CRDM LO FLOW
• APF-OOl-B1. RCP BRG COOL WTR LO FLOW
• APP-OO1-B2, RCP LABYRTH SEAL LO DELTA-P
• APP-OO1-B3, RCP A BEARING HI TEMP
• APP-OOl-B7, RHR PMP A COOL WTR LO FLOW
• APP-aOl-Cl. RCP THERM BAR COOL WTR HI FLOW
• APP-OO1-C4. CCW HX A/B OUTLET HI TEMP
• APP-OOl-C7, RHR PMP B COOL WTR LO FLOW
• APP-OO1-D1, RCP THERM BAR COOL WTR LO FLOW
• APP-OOl-D3, RCP B BEARING HI TEMP
• APP-OOl-E1, RCP THERM BAR COOL WTR HI TEMP
• APP-OOl-F3, RCP C BEARING HI TEMP
• APP-OO1-F4. CCW PMP MOTOR OVLD/TRIP
• APP-OO1-F5, CCW PMP LO PRESS

                                    - END  -

Rev. 35 AOP-014 COMPONENT COOLING WATER SYSTEM MALFUNCTION Page 5 of 118 __STEP_H ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I

1. Implement The EALs

2. Make PA Announcement For Procedure Entry 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.

3. Go To Appropriate Section For Indicated Malfunction:

Loss Of CCW Inventory Go To Section A Rising CCW inventory , R-17 Alarming Go To Section B CCW Pump Discharge Pressure Low Go To Section C CCW System Low Flow OR High Temperature Go To Section D

Rev. 35 AOP-014 COMPONENT COOLING WATER SYSTEM MALFUNCTION Page 6 of 118 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED H__STEP_H

4. Determine If CCW Parameters Are Normal:

a. Check RCS temperature - LESS a. Perform one of the following:

THAN 350°F

• IF CCW HX outlet temperature is greater than 105°F, THEN Go To Step 3.

OR

• IF CCW HX outlet temperature is less than 105°F, THEN Go To Step 4.c.

b. Check CCW HX outlet b. Go To Step 3.

temperature - LESS THAN 125°F

c. Check CCW HX outlet c. Go To Step 3.

temperature - STABLE DECREASING

d. Check APP-00l-F5. CCW PMP LO d. Go To Step 3.

PRESS - EXTINGUISHED

5. Refer To Technical Specifications For Applicable LCOs

• T.S. 3.4.17 - Chemical and Volume Control System (CVCS)
• T.S. 3.5.2 - ECCS - Operating
• T.S. 3.5.3 - ECCS - Shutdown
• T.S. 3.6.6 - Containment Spray and Cooling Systems
• T.S. 3.7.6 - Component Cooling Water (CCW) System

6. Return to Procedure And Step In Effect

                                            - END -

Rev. 35 AOP-014 COMPONENT COOLING WATER SYSTEM MALFUNCTION Page 7 of 118 __STEP_H ACTION/EXPECTED RESPONSE SECTION A I RESPONSE NOT OBTAINED LOSS OF CCW INVENTORY (Page 1 of 19)

1. Determine If Pump Cavitation Is CCW Surge Tank level lowers Occuring Imminent As Follows: to less than 5% CCW Pump Cavitation occurs, THEN Go To o Check Surge Tank Level - LESS Step 2.

THAN 5% Go To Step 7. OR o Check CCW Pump Discharge Pressure (Local) AND Flow WIDE OSCILLATIONS

2. Check Reactor - CRITICAL Perform the following:

a. Verify Control Rods - TRIPPED

b. Stop ALL RCPs.

c. IF Control Rods were inserted on the trip, perform the following:

1) i RCS temperature is greater than equal to 350°F, II1S Go To Step 5.

2) RCS temperature is less than 350° F, THEN Go To Step 6.

d. j Control Rods were already inserted, THEN Go To Step 6.

3. Verify Reactor - TRIPPED

4. Stop ALL RCPs

5. Go To EOP-E-O, Reactor Trip or Safety Injection, While Continuing With This Procedure

Rev. 35 AOP-014 COMPONENT COOLING WATER SYSTEM MALFUNCTION Page 8 of 118 __STEP_H ACTION/EXPECTED RESPONSE SECTION A I RESPONSE NOT OBTAINED LOSS OF CCW INVENTORY (Page 2 of 19)

6. Lockout CCW Pumps As Follows:

a. Place A hold all CCW Pump switches in STOP position

b. Check APP-O01-F5, CCW PMP LO PRESS - ILLUMINATED

c. Release CCW Pump Switches

d. Go To Step 13

7. Verify at the RTGB, Primary Open CC-711, DEMIN WATER MAKE-UP Water Makeup To CCW As Follows: TO CC SURGE LINE.

a. Primary Water Pump - RUNNING

b. CC-832, MAKEUP - OPEN

8. Check CCW Surge Tank level WIIM CCW Surge Tank level (LI-614B) - STABLE OR RISING (LI-614B) is Stable Rising.

1N perform Step 9. Go To Step 11.

9. Throttle CC-832 OR CC-711 To Maintain Surge Tank Level (LI-614B) 47% to 53%.

10. Go To Step 13

11. Start A Second Primary Water Pump

12. Check CCW Surge Tank level Throttle CC-832 CC-71l to (LI-614B) - LOWERING maintain surge tank level 47% to 53%.

13. Dispatch Operator To Perform Attachment 3, CCW Leak Search, While Continuing With Procedure

Rev. 35 AOP-014 COMPONENT COOLING WATER SYSTEM MALFUNCTION Page 9 of 118 j STEP_H ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED SECTION A LOSS OF CCW INVENTORY (Page 3 of 19)

14. Determine If RER Must Be Stopped As Follows:

a. Check CCW Pumps - ALL STOPPED a. Observe the NOTE prior to Step 18 and Go To Step 18.

b. Check RHR Pump status - ANY b. Observe the NOTE prior to PUMP RUNNING IN CORE COOLING Step 18 and Go To Step 18.

MODE

15. Stop RHR Pumps

16. Check CV Closure Status - ALL Initiate CV Closure as follows:

PENETRATIONS CLOSED

a. the PA system is available, THEN perform the following:

1) PLACE the VLC control switch to EMERG

2) MAKE the following announcement: Containment Closure is required; all responsible personnel close your assigned penetration immediately.

3) Perform the OMM-033 Section titled Effect CV Closure while continuing

b. the PA system is not available, THEN perform the ONM-O33 Section titled Effect CV Closure while continuing

17. Go To AOP020, Loss Of ERR, While Continuing With This Procedure

Rev. 35 AOP-0l4 COMPONENT COOLING WATER SYSTEM MALFUNCTION Page 10 of 118 H__STEP_H ACTION/EXPECTED RESPONSE SECTION A I RESPONSE NOT OBTAINED LOSS OF CCW INVENTORY (Page 4 of 19) NOTE i the location of the leak is known isolation is possible, THEN leak isolation may be commenced immediately.

   *18. Check CV For CCW Break Using Control Room Indications As Follows:

a. Monitor the following CV indications:

• ERFIS CV SUMP LEVEL
• CV WATER LEVEL (White Sump Lights)
• LI-801. CHANNEL I CV WATER LEVEL
• LI-802, CHANNEL II CV WATER LEVEL
• RCP Abnormal Conditions

b. Check CV - LOCATION OF CCW b. subsequent parameters BREAK indicate location of break in the CV. THEN Go To Step 19.

Observe the NOTE Prior to Step 29 and Go To Step 29

c. Inform personnel performing leak search that the leak location is in the CV

Rev. 35 AOP-014 COMPONENT COOLING WATER SYSTEM MALFUNCTION Page 11 of 118

STEP_H ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED SECTION A LOSS OF CCW INVENTORY (Page 5 of 19)

19. Determine RCP Alarm Status:

a. Check APP-OO1-B1, RCP BRG a. makeup capacity to the CCW COOL WTR LO FLOW - ILLUMINATED Surge Tank is sufficient to maintain level, THEN Go To Step 64.

IF makeup capacity to the CCW Surge Tank is IQI sufficient to maintain level, THEN Go To Step 20.

b. Check ANY RCP BEARING HI TEMP b. j makeup capacity to the CCW Alarm - ILLUMINATED Surge Tank is sufficient to maintain level, THEN Go To

• APP-OOl-B3 Step 64.

makeup capacity to the CCW Surge Tank is sufficient

• APP-00l-D3 to maintain level, THEN Go To Step 20.

OR

• APP-OOl-F3

Rev. 35 AOP-014 COMPONENT COOLING WATER SYSTEM MALFUNCTION Page 12 of 118 H__STEP_H ACTION/EXPECTED RESPONSE SECTION A I RESPONSE NOT OBTAINED I LOSS OF CCW INVENTORY (Page 6 of 19)

20. Check Reactor - CRITICAL Perform the following:

a. Verify Control Rods - TRIPPED

b. Stop ALL RCPs.

c. IF Control Rods were inserted on the trip, perform the following:

1) j RCS temperature is greater than equal to 350°F, THEN Go To Step 23.

2) j RCS temperature is less than 350° F, THEN Go To Step 24.

d. Control Rods were already inserted, THEN Go To Step 24.

21. Verify Reactor - TRIPPED

22. Stop ALL RCPs

23. Go To EOP-E-O, Reactor Trip or Safety Injection, While Continuing With This Procedure

24. Close The Following Valves To Isolate CCW To The RCPs:

• CC-7l6A, CCW TO RCP ISO
• CC-7l6B, CCW TO RCP ISO
• CC-730, BRG OUTLET ISO
• CC-735, THERM BAR OUT ISO
• FCV-626, THERM BAR FLOW CONT

Rev. 35 AOP-014 COMPONENT COOLING WATER SYSTEM MALFUNCTION Page 13 of 118 H__STEP_H ACTION/EXPECTED RESPONSE SECTION A RESPONSE NOT OBTAINED I LOSS OF CCW INVENTORY (Page 7 of 19)

25. Check Indications - LEAKAGE Isolate CCW To The Excess STOPPED Letdown Heat Exchanger As Follows:

a. In Pipe Alley, Close CC-737A, CC TO EXCESS LETDOWN HX ISOL (Supply line to Sleeve 35)

b. WHEN CC-737A is confirmed closed, THEN at the RTGB, Close CC-739, EXCESS LTDN HX OUTLET VALVE

26. Stop Makeup To CCW As Follows:

a. Verify CC-832, MAKEUP - CLOSED

b. Verify Primary Water Pump(s)

            -  IN NORMAL

• ONE IN AUTO
• ONE IN STOP

c. Check Demin Water - BEING c. Go To Step 27.

USED FOR CCW MAKEUP

d. Verify CC-7ll, DEMIN WATER MAKE-UP TO CC SURGE LINE -

CLOSED

27. Dispatch Operator To Containment To Locate AND Isolate Any Observed Leakage

28. Go To Step 30

Rev. 35 AOP014 COMPONENT COOLING WATER SYSTEM MALFUNCTION Page 14 of 118 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED __STEP_H SECTION A LOSS OF CCW INVENTORY (Page 8 of 19) NOTE A ruler is located in the tool bag to assist the operator in determining water level.

   *29. Determine If Actions For Auxiliary Building Flooding Are Necessary As Follows:

a. Check for any of the a. at any time flooding is following indications of indicated, THEN perform flooding: Attachment 4, Flood Control In The Auxiliary Building

• Water level on Aux Bldg first floor - GREATER Go To Step 30.

THAN 6 INCHES OR

• APP-OOl-E4, RHR PIT A HI LEVEL - ILLUMINATED OR
• APP-0Ol-E5, RHR PIT B HI LEVEL - ILLUMINATED

b. Dispatch Operator to perform Attachment 4, Flood Control In The Auxiliary Building

30. Verify Letdown Isolated As Follows:

• LCV-460 A&B, LTDN LINE STOP

              - CLOSED

• HIC-142, PURIFICATION FLOW -

SET TO 0%

• CVC-387, EXCESS LTDN STOP -

CLOSED

Rev. 35 AOP-014 COMPONENT COOLING WATER SYSTEM MALFUNCTION Page 15 of 118 j__STEP_H ACTION/EXPECTED RESPONSE SECTION A RESPONSE NOT OBTAINED I LOSS OF CCW INVENTORY (Page 9 of 19)

31. Determine If Charging Pump(s)

Should Be Stopped As Follows:

a. Check Charging Pumps - ANY a. Go To Step 36.

PUMP RUNNING

b. Check RCS temperature - b. Stop ALL Charging Pumps.

GREATER THAN 150° F Go To Step 36.

32. Establish Alternate Cooling To Charging Pumps As Follows:

a. Stop ALL but one Charging Pump

b. Raise the speed of the running Charging Pump to at least 75% Demand Signal

c. Dispatch an operator to perform Attachment 1, Emergency Cooling To Charging Pumps

    *33   Check Attachment 1  -  COMPLETE          WHEN Attachment 1, EMERGENCY COOLING TO CHARGING PUMPS, has been completed, THEN perform steps 34, 35 and 36.

Go To Step 37.

34. Reduce The Speed Of The Running Charging Pump To Minimum

35. Check RCP Thermal Barrier EP - Locally throttle RCP SEAL WATER GREATER THAN 5 INCHES FLOW CONTROL VALVE(s) to obtain at least 6 gpm flow to each RCP.

• PI-131A
• PI-128A
• CVC-297A
• PI-125A
• CVC-297B
• CVC-297C

Rev. 35 AOP-014 COMPONENT COOLING WATER SYSTEM MALFUNCTION Page 16 of 118 H STEP H ACTION/EXPECTED RESPONSE SECTION A RESPONSE NOT OBTAINED LOSS OF CCW INVENTORY (Page 10 of 19)

36. Check RCP Parameters: Raise Charging Pump speed to establish RCP Thermal Barrier o RCP Thermal Barrier AP - greater than 5 inches RCP GREATER THAN 5 INCHES Seal Injection Flow at least 6 gpm to each RCP.

OR o RCP Seal Injection Flow - AT LEAST 6 GPM TO EACH RCP.

37. Notify Chemistry Personnel To Stop Any Primary Sampling In Progress

   *38. Determine If Emergency Cooling To Spent Fuel Pit Heat Exchanger Is Required As Follows:

a. Check APP-036-B4, SPENT FUEL a. at any time APP-036-B4, PIT HI TEMP - ILLUMINATED SPENT FLJLE PIT HI TEMP.

illuminates, THEN perform Step 38.b. Go To Step 39.

b. Align emergency cooling to the Spent Fuel Pit Heat Exchanger using Attachment 2, Emergency Cooling To Spent Fuel Pit Heat Exchanger, while continuing with this procedure

39. Determine If CCW May Be Restored As Follows:

a. Check CV - LOCATION OF CCW a. Go To Step 40.

BREAK

b. Check Indications - LEAKAGE b. IF CCW to Containment can NOT ISOLATED be isolated, THEN Go To Step 40

c. Go To Step 48

Rev. 35 AOP-0l4 COMPONENT COOLING WATER SYSTEM MALFUNCTION Page 17 of 118 H__STEP_H ACTION/EXPECTED RESPONSE SECTION A RESPONSE NOT OBTAINED I LOSS OF CCW INVENTORY (Page 11 of 19)

40. Check Leak Source - LOCATED WREN the source of leakage is located, Go To Step 41.

41. Check Leak Source - ISOLABLE Perform ONE of the following:

o LE Surge Tank Level is stable, IJi. Go To Step 43. OR o j CCW Pump(s) are running AND Surge Tank Level can LQ1 be maintained greater than 5%. Go To Step 1. OR o IE CCW Pumps have ALL been stopped, THEN Go To Step 45.

42. Go To Step 47

43. Consult Plant Operations Staff To Determine If This Procedure Should Be Exited While Maintenance Repairs The Break

44. Transition As Determined From Consultation:

a. Check Procedure Status - WILL a. IF determined that the EXIT procedure will remain in effect, THEN perform the following:

1) Monitor conditions AND hold at this step for repairs.

2) )I repairs are completed, THEN Go To Step 58.

b. Go To Step 58

Rev. 35 AOP-014 COMPONENT COOLING WATER SYSTEM MALFUNCTION Page 18 of 118 H__STEP_H ACTION/EXPECTED RESPONSE SECTION A RESPONSE NOT OBTAINED I LOSS OF CCW INVENTORY (Page 12 of 19)

45. Initiate Action For Emergency Repair Of The Pipe Break

46. Check Repair Status - COMPLETE WHen the repairs have been completed, THEN Go To Step 48.

47. Check CCW Leak Status - ISOLATED WHEN the leak is isolated, THEN Go To Step 48.

48. Perform Attachment 5, Restoration Of CCW Inventory

49. Check Attachment 5 - COMPLETE XN Attachment 5 is complete, WN Go To Step 50.

50. Check CCW Pump Status - ALL Go To Step 58.

STOPPED

51. Start One CCW Pump As Follows:

a. Check CCW Pumps - ALL STOPPED a. Go To Step 53.

b. Start selected pump

c. Check annunciator APP-O0l-F5 c. When APP-OOl-F5 is

             -  EXTINGUISHED                          extinguished. III Go To Step 52.

Rev. 35 AOP-0l4 COMPONENT COOLING WATER SYSTEM MALFUNCTION Page 19 of 118 -ti-{ ACTION/EXPECTED RESPONSE I I SECTION A RESPONSE NOT OBTAINED LOSS OF CCW INVENTORY (Page 13 of 19)

52. Clear The Lock Out Signal For The Standby CCW Pumps:

a. In The Cable Spreading Room, a. Reset the CCW Pump lockout Press the CCW Pump Auto Start function using the control Lockout Reset Push Button for power fuses as follows (one the Standby CCW Pumps CCW Pump at a time if this Check The Pump BX1 Relay method used for more than one Reset (Relay Plunger Out): pump)

1) Remove The Control Power CCW Pushbutton Relay Location Fuses Of The Standby CCW Pump Location Pump A ARP-2 Aux. Relay Rack HF, o CCW PUMP A - 480V BUS Location J DS (AUX COMPT 33C)

(BX1/CCW-PMP-A) OR B ARP-1 Aux. Relay Rack FD, Location G o CCW PUMP B - 480V BUS (BX1/CCW-PMP-B) E-1 (CMPT 22C) C ARP-2 Aux. Relay Rack JD, OR Location G (BXl/CCW-PMP-C) o CCW PUMP C - 480V BUS E-2 (CMPT 26C)

2) While holding the CCW Pump handswitch to STOP on the RTGB, reinstall the control power fuses for the standby CCW Pump.

53. Check Charging Pump Cooling - Contact Engineering to determine SUPPLIED BY CCW actions necessary to restore normal cooling to Charging Pumps.

54. Check Charging And Letdown - Go To Step 57.

REQUIRED

55. Verify Charging Pump - RUNNING

Rev. 35 AOP-O1i COMPONENT COOLING WATER SYSTEM MALFUNCTION Page 20 of 118 ]__STEP H ACTION/EXPECTED RESPONSE f I SECTION A RESPONSE NOT OBTAINED LOSS OF CCW INVENTORY (Page 14 of 19)

56. Establish Letdown As Follows:

a. Check Letdown status - a. Go To Step 57.

ISOLATED

b. Perform one of the following b. Establish excess letdown to establish Letdown: using Attachment 12, Placing Excess Letdown In Service.

• Establish normal letdown using Attachment 11, Restoration of Normal Letdown OR
• Establish letdown from RHR system as follows:

1) Verify RHR Pump -

RUNNING IN CORE COOLING MODE

2) Slowly open HIC-142, PURIFICATION FLOW, to establish desired letdown flowrate

57. Check Spent Fuel Pit Heat Contact Engineering to determine Exchanger Cooling - SUPPLIED BY actions necessary to restore CCW normal cooling to Spent Fuel Pit Heat Exchanger.

Rev. 35 AOP-014 COMPONENT COOLING WATER SYSTEM MALFUNCTION Page 21 of 118 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED H__STEP_H SECTION A LOSS OF CCW INVENTORY (Page 15 of 19)

   *58. Perform The Following:

a. Contact Chemistry to sample CCW for Chromates.

b. Check sample results - b. IIN the sample results are RECEIVED received, THEN adjust CCW chemistry using OP-306, Component Cooling Water.

Go To Step 59.

c. Adjust CCW chemistry using OP-306, Component Cooling Water, Chemical Addition to the Component Cooling Water System

59. Refer To Technical Specifications For Applicable LCOs

• T.S. 3.4.17 - Chemical and Volume Control System (CVCS)
• T.S. 3.5.2 - ECCS - Operating
• T.S. 3.5.3 - ECCS - Shutdown
• T.S. 3.6.6 - Containment Spray and Cooling Systems
• T.S. 3.7.6 - Component Cooling Water (CCW) System

60. Check CV - LOCATION OF CCW BREAK Return to procedure and step in effect.

61. Check Leak Source - LOCATED WIIN the source of leakage is located, 1N Go To Step 62.

62. Check Leak Source - ISOLABLE IF the leak is NOT isolable for maintenance inside the CV, THEN establish the maintenance boundary at the CV isolation valves.

Rev. 35 AOP-014 COMPONENT COOLING WATER SYSTEM MALFUNCTION Page 22 of 118 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED __STEP_H SECTION A LOSS OF CCW INVENTORY (Page 16 of 19)

63. Return to Procedure And Step In Effect

64. Isolate CCW To The Excess Letdown Heat Exchanger As Follows:

a. In Pipe Alley, Close CC-737A.

CC TO EXCESS LETDOWN HX ISOL (Supply line to Sleeve 35)

b. WHEN CC-737A is confirmed closed, THEN at the RTGB, Close CC-739, EXCESS LTDN HX OUTLET VALVE

65. Check Indications - LEAKAGE Dispatch personnel to the CV to STOPPED perform the CV portion of Attachment 3, CCW Leak Search.

Observe the NOTE prior to Step 67 and Go To Step 67.

66. RETURN TO Step 25 NOTE The following steps are dependent on completion of the respective sections of Attachment 3, CCW Leak Search, therefore the steps should be answered after the area has been investigated.

67. Check Leak Location - CRDM FAN Go To Step 69.

COOLER

Rev. 35 AOP-014 COMPONENT COOLING WATER SYSTEM MALFUNCTION Page 23 of 118 H__STEP_H ACTION/EXPECTED RESPONSE SECTION A I RESPONSE NOT OBTAINED I LOSS OF CCW INVENTORY (Page 17 of 19)

68. Perform The Following To Isolate The CRDM Fan Coolers:

a. Verify both CRDM COOLING FANs

            -  STOPPED

• HVH-5A
• HVH-5B

b. Check leak location - WITHIN b. Observe the prior to BOUNDARY VALVES BELOW Step 71 and Go To Step 71.

• CC-719D. CC TO CRD COOL
• CC-724D, CC FROM CRD COOL
• CC-719E, CC FROM CRD COOL

c. Locally close the following:

• CC-719D, CC TO CR0 COOL
• CC-724D. CC FROM CRD COOL
• CC-719E. CC FROM CRD COOL

d. Ovserve The NOTE Prior To Step 39 A RETURN TO Step 39

   *69. Check Makeup Capacity To The CCW          IE makeup becomes inadequate to Surge Tank   - UNABLE TO MAINTAIN         maintain level,      RETURN TO LEVEL                                     Step 20.

Observe the Q] prior to Step 71 and Go To Step 71.

70. RETURN TO Step 20.

Rev. 35 AOP-014 COMPONENT COOLING WATER SYSTEM MALFUNCTION Page 24 of 118 H__STEP_H ACTION/EXPECTED RESPONSE SECTION A I RESPONSE NOT OBTAINED I LOSS OF CCW INVENTORY (Page 18 of 19) NOTE Since the leak has been determined to NOT be on the CRDM Coolers OR the Excess Letdown heat Exchanger, it is on a RCP line OR common line.

71. Determine Leak Status As Follows:

a. Check leak location - CAN BE a. Contact Plant Operations REPAIRED ON LINE Staff for the following:

1) Determine shutdown rate of the plant.

2) Determine if this procedure is to remain in effect during shutdown.

3) Begin shutdown of plant per GP-006-l, Normal Plant Shutdown from Power Operation to Hot Shutdown AOP-038. Rapid Downpower.

4) IF determined that the procedure will remain in effect, THEN perform the following:

a) Monitor conditions AND hold at this step for repairs. b) )IIi repairs are completed, THEN Go To Step 58.

5) j this procedure is to be exited, THEN Go To Step 58.

b. Contact Maintenance to repair the leak.

Rev. 35 AOP-014 COMPONENT COOLING WATER SYSTEM MALFUNCTION Page 25 of 118 j STEP_H ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED SECTION A LOSS OF CCW INVENTORY (Page 19 of 19)

72. Check Leak - REPAIRED Monitor the following parameters:

• RCP Temperatures
• CCW Surge Tank Level
• CV Sump Level IF an unsafe condition becomes apparent, THEN RETURN TO Step 20.

WHEN the leak has been repaired, THEN RETURN TO Step 48.

73. RETURN TO Step 48.

                                          - END  -

LICENSE EXAMINATION JOB PERFORMANCE MEASURE ILC-13 NRC JPM H RevO Fill a Safety Injection Accumulator JAW OP-202 Concurred By: Date: Operations Approved By: Date: Superintendent/Supervisor Ti aining

ILC-13 NRC JPM H Page 2 of 15 LICENSE EXAMINATION JOB PERFORMANCE MEASURE Task: 01006100301 Fill the SI Accumulators lAW OP-202 Alternate Path: NO 3PM #: Candidate ILC-13 NRC JPM H RO/SRO KIA Rating (RO/SRO): 006 A4.01 4.1 / 3.9 006 A4.02 4.0 / 3.8 006 A1.07 3.3 / 3.6 006A1.13 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 Perform X Simulate

References:

OP-202, Section 8.2.1, Filling the Safety Injection Accumulators Validation Time: 9 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 TJNSAT 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 SI-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.athrough 8.2.1.1.f.2 completed.

ILC-13 NRC JPM H Page 6 of 15 Tools[Eguipment[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 lAW OP-202, Section 8.2.1.

ILC-13 NRC JPM H Page 7 of 15 START TIME: fEP 1: Check open SI-856A, SI PUMP RECIRC and SI-856B, SI PUMP RECIRC (Steps 8.2.l.2.aandb). 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 LTNSAT requested breakers are open. EXAMINERS NOTE: Key switch for SI-869 is located in the rear of the RTGB on the ECCS VALVES CONTROL POWER DEFEAT PANEL. BOOTH OPERATOR CUE: NONE COMMENTS: 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.

ILC-13 NRC JPM H Page 9 of 15 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 8.2.1.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 SI869, 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.f) CRITICAL STEP fANDARD: 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 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. UNSAT EXAMINERS NOTE: NONE 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. FEP 6: Verify at least one SI Pump Area Cooling unit (HVH-6A OR HVH-6B OR both) is operating. (Step 8.2.l.2.g) STANDARD: 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-851 C.

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-851 C closed by placing the control switch to the CLOSED position.

EXAMINERS CUE: NONE EXAMINERS NOTE: Technical Specification limits for SI Accumulators: Pressure band of 600 660 psig. Level band of 61.5 80.4%. 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 fANDARD: 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 of 15 STEP 10: Close SI-869, SI HOT LEG HDR. (Step 8.2.1.2.m) CRITICAL STEP LANDARD: 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. 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 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.

CONTINUOUS USE Section 8.2.1 Page 1 of 5 INIT 8.2 Normal Operation 8.2.1 Filling the Safety Injection Accumulators Initial Conditions

a. This revision has been verified to be the latest revision available.

Date

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.

d. IF RCS pressure is less than 650 psig, THEN VERIFY the accumulator discharge valve(s)

(Sl-865A/B/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.

2) CLOSE SFPC-805B, RWST RETURN.

OP-202 Rev. 94 Page l3of 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 SI-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 SI-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 SI-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 Sl-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 SI-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/NORMAL (Circle one) OP-202 Rev. 94 Page 16 of 131

Section 8.2.1 Page 5 of 5 8.2.1.2 (Continued) !NiI

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 hours. (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: 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, Aft. 3 Concurred By: Date: Operations Approved By: Date: Superintendent/Supervisor 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 lAW DSP-002 Alternate Path: YES JPM #: Candidate ILC-13 NRC JPM I RO/SRO K/A Rating (RO/SRO): 004 G2.1.30 4.4/4.0 004A1.11 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, Aft. 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: SAT Performance UNSAT circle one Time (mm): / Examiner: Print Name Signature Date

ILC-13 NRC JPM I Page 3 of 16 NOTE: The time critical times are based on times from the event initiation. The JPM begins with 2 minutes already elapsed. 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 of 16 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.

ILC-13 NRC JPM I Page 6 of 16 START TIME: TIME CRITICAL START TIME: )-XAMINERS 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)

(Att. 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) CRITICAL (Aft. 3 Step 2) STEP STANDARD: Candidate determines, from the initial conditions, that the fire is NOT in the E1/E2 Room and takes RNO path to Step 4. SAT As Found: N/A EXAMINERS CUE: NONE UNSAT 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 (Aft. 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 (Aft. 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 (Aft. 3 Step 4.c) STEP STANDARD: Candidate simulates closing CVC-202B by rotating the handwheel in the CS direction. SAT

.s 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-3 58 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 (Att. 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. (Att. 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-1 1 5C, VCT OUTLET ISOLATION CRITICAL (Att. 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 (Att. 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.

.s 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 (Att. 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 ( ttempt 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 (Att. 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 ( 1ANDARD 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 (AU. 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
• CVC297C (AU. 3 Step 10 RNO) SAT STANDARD: Candidate simulates throttling open CVC-297A/B/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 (Att. 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 FANDARD: 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. IJNSAT 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.

Rev. 47 HOT SHUTDOWN USING THE DEDICATED/ALTERNATE DSP 002 SHUTDOWN SYSTEM Page 26 of 71 STEP ACTION/EXPECTED RESPONSE CONTINUOUS I USE RESPONSE NOT OBTAINED I 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 1QJ prior to Step 4 ROOM (AREA AS) 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 RESPONSE NOT OBTAINED CONTINUOUS USE 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-2lB, 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 P 002 SHUTDOWN SYSTEM Page 28 of 71 j__STEP_H ACTION/EXPECTED RESPONSE CONTINUOUS 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 PUMP A to LOCAL

b. Open CVC-309A, HCV-121 BYPASS

c. Close CVC-2O2B, HCV-121 INLET ISOL

Rev. 47 HOT SHUTDOWN USING THE DEDICATED/ALTERNATE D P 002 SHUTDOWN SYSTEM Page 29 of 71 STEH ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED I CONTINUOUS USE ATTACHMENT 3 AUXILIARY BUILDING OPERATOR ACTIONS (Page 4 of 14) 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.

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 5.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

STEP H ACTION/EXPECTED RESPONSE CONTINUOUS USE RESPONSE NOT OBTAINED H-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. THEN Go To Step 7.b.

energized ANI2 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) WREN 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 DSP 002 SHUTDOWN SYSTEM Page 31 of 71

__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
• CVC-297B
• CVC-297C required to maintain minimum flow. THEN throttle CVC-309A, HCV-l2l BYPASS valve while maintaining Charging Pump Discharge pressure less than 2500 psig.

Rev. 47

      -              HOT SHUTDOWN USING THE DEDICATED/ALTERNATE SHUTDOWN SYSTEM Page 32 of 71 ACTION/EXPECTED RESPONSE                 RESPONSE NOT OBTAINED

__STEP_H CONTINUOUS USE 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. IE RCP Seal Injection has STOPPED. been established. notify SM that CCW has been established Go To Step 15.

j RCP Seal Injection has liQ]. been established. THEN Locally Stop CCW Pump A.

HOT SHUTDOWN USING THE DEDICATED/ALTERNATE Rev. 47 0 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 100F/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) j required to maintain PZR level stable, THEN coordinate with the Turbine Building Operator to dump steam from the secondary.

3) III 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 P1-660, 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 P 002 SHUTDOWN SYSTEM Page 34 of 71 __STEP_H ACTION/EXPECTED RESPONSE CONTINUOUS I USE RESPONSE NOT OBTAINED 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-66O. 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-1/E-2 ROOM 17 AUX BLDG HALL 21 ANYWHERE ELSE 16

HOT SHUTDOWN USING THE DEDICATED/ALTERNATE Rev. 47 SHUTDOWN SYSTEM Page 35 of 71 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED j__STEP_H CONTINUOUS USE 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-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

17. Check RCP Seal Injection Status Go To Step 24.

          - ALIGNED

Rev. 47 HOT SHUTDOWN USING THE DEDICATED/ALTERNATE P 002 SHUTDOWN SYSTEM Page 36 of 71 ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED __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 j flow is less than 50 gpm, THEN locally UNLOCK AND OPEN CC-932, FCV-626 and CC-735 BYPASS ISOLATION. (Pipe Alley. middle penetrations, sleeve 16) IF flow remains below 50 gpm, locally verify OPEN the following valves:

• CC-716A, COOLING WATER INLET (Located 20 feet in overhead near Sleeve 8)
• CC-716B, 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)

   -            HOT SHUTDOWN USING THE DEDICATED/ALTERNATE          Rev. 47 DSP 002 SHUTDOWN SYSTEM Page 37 of 71 ACTION/EXPECTED RESPONSE CONTINUOUS IUSE    RESPONSE NOT OBTAINED ATTACHMENT 3 AUXILIARY BUILDING OPERATOR ACTIONS (Page 12 of 14)

• 22. Check Fire - EXTINGUISHED WHEN the fire has been extinguished, THEN perform ONE of the below Steps:
• Seal Injection has been established, THEN perform Steps 17 through 19.

OR

• L Seal Injection has IIQI 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 flj 26.

Observe the NOTE prior to Step 26 and Go To Step 26.

25. Stop CHARGING PUMP A

HOT SHUTDOWN USING THE DEDICATED/ALTERNATE Rev. 47 DSP-002 SHUTDOWN SYSTEM Page 38 of 71 __STEP_H ACTION/EXPECTED RESPONSE CONTINUOUS I USE RESPONSE NOT OBTAINED I 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 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

HOT SHUTDOWN USING THE DEDICATED/ALTERNATE Rev. 47 DSP 002 SHUTDOWN SYSTEM Page 39 of 71 H__STEP_H ACTION/EXPECTED RESPONSE CONTINUOUS USE I RESPONSE NOT OBTAINED I 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, THEN close PW-48.

   *28. Check RWST Level Using LIC-947   -         4IIN RWST level is less than LESS THAN 50%                              50%, ]II4 notify the SM to contact the TSC to determine RWST makeup options.

Observe the NOTE 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: Date: Operations Approved By: Date: Superintendent/Supervisor Training

ILC-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 ILC-13 NRC JPM J RO/SRO K/A Rating (RO/SRO): 061 G2.1.30 4.4/4.0 061 K1.01 4.1 /4.1 061 K4.01 4.1 /4.2 076 K1.20 3.4/3.4 Task Standard: SW Backup Aligned to Supply Suction to SDAFW Pump JAW DSP-007, Aft. 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: Performance Rating: SAT Performance UNSAT circle one Time (mm): Examiner: Print Name Signature Date

ILC- 13 NRC JPM J Page 3 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 SW. 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 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.

ILC-13 NRC JPM J Page 6 of 13 START TIME: NOTE he 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-i, 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-i 18, 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-uS 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 ofl3 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- 1 902A)

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 3PM 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 SIG steam supply. EXAMINERS NOTE: NONE COMMENTS:

ILC- 13 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
• V1-8B, SG B Stm Supply to SDAFW Pump SAT
• V1-8C, SG C Stm Supply to SDAFW Pump (Step 5)

STANDARD: Candidate simulates opening V1-8C. Recognizes / reports V1-8C will not IJNSAT 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 SIG. V1-8C 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

• V1-8A, 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 V1-8B by rotating the MOV handwheel in the CCW direction until it will not turn anymore and is taken 1/4 turn off its UNSAT 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 UN SAT by turning the handwheel in the CW direction until the flow stops and the handwheel will not move anymore.

• 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 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.
• 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 I 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.

INITIATTNG 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 SIG.

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:

• V1-8A, SG A STM SUPPLY TO STM DRIVEN AFW PUMP
• Vl-8B, SG B STM SUPPLY TO STM DRIVEN AFW PUMP
• Vl-8C, SG C STM SUPPLY TO STM DRIVEN AFW PUMP

2. Locally Align the following valves:

a. Unlock and close AFW-l, AFW PUMPS SUCTION FROM CST.

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 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-l902A)

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 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:

• V1-8A, SG A STM SUPPLY TO STM DRIVEN AFW PUMP
• Vl-8B, SG B STM SUPPLY TO STM DRIVEN AFW PUMP T
• V1-8C, SG C STM SUPPLY TO STM DRIVEN AFW PUMP

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 EUG lAW EPP 28, ATTACHMENT 5 Concurred By: Date: Operations Approved By: Date: Superintendent/Supervisor Training

JPM NRC JPM K Page 2 of 12 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 (ROISRO): 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:

JPM NRC JPM K Page 3 ofl2 QUESTION DOCUMENTATION: Question:

Response

JPM NRC JPM K Page 4 of 12 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 12 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 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 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 perform EPP-28 Attachment 5

ILC-13 NRC JPM K Page 6 of 12 START TIME: TEP 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: NOTE i 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.

ILC-13 NRC JPM K Page 7 of 12 STEP 2: Close the normal EDG Day Tank header isolation valve for the running Critical Step EDG(s):

• A EDG 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: STEP 3: Open the EDG Day Tank Fill valve for the running EDG(s): Critical Step

• A EDG FO-26A, ALT / EMERG SUPPLY TO FUEL OIL DAY TANK A
• B 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-26A 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 8 of 12 STEP 4: Open the EDO Day Tank Solenoid Bypass valve for the tank(s) being Critical Step filled:

• A EDO 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: NOTE Only one tank should be filled at a time.

ILC-13 NRC JPM K Page 9 of 12 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-231, AFOST SUPPLY TO FUEL OIL DAY TANK NA OR o 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 FO236 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: TEP 6: 1 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:

ILC-13 NRC JPM K Page 10 of 12 STEP 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 AS FOUND: N/A UNSAT 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:

JPM NRC JPM K Page 11 of 12 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 perform 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 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.

1. Close the normal EDG Day Tank header isolation valve for the running EDO(s):

• A EDO - FO-25A DIESEL OIL DAY TANK A HEADER ISOLATION
• B EDO - FO-25B, DIESEL OIL DAY TANK B HEADER ISOLATION

2. Open the EDG 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 EDG Day Tank Solenoid Bypass valve for the tank(s) being filled:

• A EDG - 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, open the AFOST SUPPLY TO FUEL OIL DAY TANK for the day tank to be filled:

o F0-231, AFOST SUPPLY TO FUEL OIL DAY TANK A OR o FO-236, 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 FO-231. AFOST SUPPLY TO FUEL OIL DAY TANK A OR o P0-236, AFOST SUPPLY TO FUEL OIL DAY TANK B

6. Inform the Control Room the EDG(s) is being filled from Alternate Fuel.

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