ML043280287

Final - Section C Operating (Folder 3)

ML043280287
Person / Time
Site:	Ginna
Issue date:	11/03/2004
From:	Maciuska F Constellation Energy Group
To:	Conte R NRC/RGN-I/DRS/OSB
Conte R
References
Download: ML043280287 (17)

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CONSTELLATION ENERGY NO.: Exam 04-2Scenario 1 REV: 0 R. E. GINNA NUCLEAR POWER PLANT I EXAMINATION SCENARIO I DATE: 9/13/04 I PAGE: i of 1 7 I Written by: Ken Masker Date : 9/13/04 Sr. License Instructor Technical Review: Joe Hoover Date : 9/16/04 Sr. License Instructor Time validated 70 minutes By: Ken Masker Date : 9/19/04 Sr. License Instructor Date of exam:

Examinees Evaluators Final review Date :

License Instructor Approved for use Date :

Director Operations Training or Designee

CONSTELLATION ENERGY NO.: Exam 04-2 Scenario 1 I REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE: NRC Exam Scenario 04-2-1 I

EXAMINATION SCENARIO I DATE: 9/13/04 I PAGE: 2of 17 I

1. SCENARIO OVERVIEW 1.1 The plant is initially at approximately 47% power following a load decrease to clean condenser water boxes. The operators are currently in procedure 0-5.2, Load Increases and are ready to start the second Main Feedwater Pump and increase power to 100% at the normal rate of 10%/hr.

The IrBlt Charging Pump is out of service for an overhaul and cannot be restored in less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

1.2 The crew will start the B MFW pump IAW 0-5.2 Load Increases, step 5.2.11 and Attachment MFW Pump B and continue with the load increase at 10%/hr.

1.3 PT-449 Przr Pressure Controlling channel fails high causing full spray and RCS pressure to decrease rapidly. The crew should take manual control of PC-431K to close the spray valves and defeat the channel per ER-INST.l. The CRF should check Tech Specs for operability requirements (defeat in 6 hrs) (Tech Spec 3.3.1).

1.4 Safeguard Bus 16 Faults causing the bus to deenergize. The crew should respond using procedure AP-ELEC.14/16 and start redundant equipment and prepare for plant shutdown. The CRF should check Tech Specs for operability requirements (Tech Spec 3.8.9).

1.5 Charging Pump IIAtt trips causing loss of all charging flow. The crew should enter AP-CVCS.3, Loss of all Charging. They should initiate a rapid shutdown.

1.6 A main steamline rupture occurs resulting in a SI and PTS condition. The operator should respond per E-0, E-2, ECA-2.1 and FR-P.l and take actions to reduce AFW Flow and Terminate SI to prevent over pressurizing the RCS.

CONSTELLATION ENERGY NO.: Exam 04-2 Scenario 1 REV: 0 R. E. GlNNA NUCLEAR POWER PLANT TITLE: NRC Exam Scenario 04-2-1 EXAMINATION SCENARIO DATE: 911 3/04 PAGE: 3 of 17

2. SCENARIO OBJECTIVES 2.1 Demonstrate the following abilities during the simulator scenario.

2.1.1 Ability to start a MFW pump and increase power at normal rates.

2.1.2 Ability to respond to a loss of PT-449 which causes a rapid RCS depressurization and to defeat the channel and restore normal operations.

2.1.3 Ability to respond to a loss of Safeguard Bus 16 and to take compensatory measures and start redundant equipment.

2.1.4 Ability to respond to a loss of all charging by performing a rapid power decrease taking the plant offline and shutting the reactor down.

2.1.5 Ability to respond to a PTS event by limiting the cooldown and terminating SI.

CONSTELLATION ENERGY NO.: Exam 04-2 Scenario I REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE: NRC Exam Scenario 04-2-1 EXAMINATION SCENARIO DATE: 911 3/04 PAGE: 4 of 1 7

3. CRITICAL TASKS (CTS)

CT FR-P.l-B Task: Control the AFW flow rate in order to minimize RCS cooldown rate before transition out of FR-P.l.

Cues: RCS cold leg cooldown rate > 1 0 0 ° F in last 6 0 minutes and Cold leg temperature on either cold leg is c 285'F and AFW flow rate to faulted S/G is > 50 gpm Indication: Manipulation of control to throttle AFW flow to both faulted S/G to 50 g p m (within the ability to control the AFW control valves)

Feedback : RCS cooldown slow and eventually stops CT FR-P.l-A Task: Terminate SI flow so that if the challenge to integrity CSF is

- severe, an extreme challenge is prevented

- extreme, SI is terminated by the end of the scenario Cues: Indication of a red or orange challenge to the integrity CSFST and SI and Rx trip actuated and Indication that SI termination criteria are met Indication: Manipulation of controls to terminate SI flow and SI and RHR pump breakers Feedback: SI and RHR flow rate zero

CONSTELLATION ENERGY NO.: Exam 04-2 Scenario 1 REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE: NRC Exam Scenario 04-2-1 EXAMINATION SCENARIO DATE: 911 3/04 PAGE: 5 of 17

4. INSTRUCTOR ACTIONS Problem Time Actions Notes 4.1 Startup and setup the simulator per OTG-3.2 NOTE: Times may be varied at the discretion of the lead evaluator 4.2 Initial Conditions 4.2.1 IC-20 47% Power MOL Print out Xenon plant Xenon increasing for plant conditions.

(Setup saved as IC-171) 4.2.2 Verify A, C Charging Pumps A-52.4 on B Charging running. Pull Stop aB1l Pump out 4 days Charging Pump overhaul (Tracking only) TRM 3.1.1 4.2.3 Verify A MFW running Fill out 0-5.2 up to B MFW Pump in Pull'Stop Step 5.2.11 (N/A up to step 5.2.10) B MFW Att fill out up to Step 8.0 (N/A A MFW Attachment) .

4.2.4 Set up Turbine EHC for lO%/hour increase setter to 95% in Imp In, Place in Hold 4.3 Insert Malfunctions 4.3.1 PT-449 Fails High MALF PZROZD, 3100 psig, 30 sec Ramp, 0 sec TD Trigger 1 4.3.2 Bus 16 Fault MALF EDS04B, 0 sec TD Trigger 2 4.3.3 Trip of A Charging Pump MALF CVClZA, 0 sec TD, Trigger 3

CONSTELLATION ENERGY NO.: Exam 04-2 Scenario 1 REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE: NRC Exam Scenario 04-2-1 EXAMINATION SCENARIO DATE: 9/13/04 PAGE: 6 of 17 4.3.4 Main Steam Line Rupture/Both MSIV's Stuck Open MALF STM05A, loo%, 0 sec TD MALF STMOSB, loo%, 0 sec TD MALF STMO3, 5E6 lbm/hr, 0 sec Ramp, 0 sec TD, Trigger 4 4.4 Event Initiation 0 min 4.4.1 Start MFW Pump Note: If CRF calls mechanic the B MFW motor shaft has already been centered.

10 min 4.4.2 PT-449 Fails High Trigger 1 25 min 4.4.3 BUS 16 Faults When notified to Trigger 2 investigate, call back after 20 minutes, respond that it will take a few hours to repair (failed insulator on bus bar) .

40 min 4.4.4 "All Charging Pump Trip A0 reports burnt Trigger 3 insulation smell in Charging Pump Room on investigation.

55 min 4.4.5 Steamline Rupture AO cannot gain access Trigger 4 to MSIV's due to steam.

Terminate scenario at direction of Lead Examiner.

CONSTELLATION ENERGY NO.: Exam 04-2 Scenario 1 REV: 0 II R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO TITLE: NRC Exam Scenario 04-2-1 I DATE: 9/13/04 I

I PAGE: 7 o f 17

5. TURNOVER INFORMATION 5.1Plant Status 47% Power MOL CB 850 ppm, Xenon increasing slightly. Came down from 100% 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ago to look at one of the condenser water boxes (cleaned). The plant is ready to go back to 100% power. Currently at step 5.2.11 of 0-5.2.

5.2EauiDment Out of Service llB1l Charging Pump is out for a major overhaul.

It cannot be restored in less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

5.3Work in Prosress Power increase per 0-5.2 llBrl Charging Pump overhaul 5.4 Planned Work Return to 100% power 5.5 Sisnificant Events 5.6 Remarks Start the llBtl MFW pump and increase load.

CONSTELLATION ENERGY NO.: Exam 04-2 Scenario 1 REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE: NRC Exam Scenario 04-2-1 EXAMINATION SCENARIO DATE: 9/13/04 PAGE: 8 of 1 7 Event : 1 Event

Title:

Start the rlBll MFW Pump Expected ResDonse/Behavior CUES: Procedure 0-5.2 directs start of the pump Response :

RATING m SRO Direct BOP to start the B MFW pump IAW 0-5.2 step 5.2.11 and Attachment B MFW pump RO/BOP Start the B MFW pump

1 I 1 CONSTELLATION ENERGY NO.: Exam 04-2 Scenario 1 I REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE: NRC Exam Scenario 04-2-1 I

EXAMINATION SCENARIO DATE: 9/13/04 PAGE: 9 of 17 6 EVALUATION Event : 2 Event

Title:

PT-449 Fails High ExDected Response/Behavior CUES: PI-449 Fails High Hi PRZR Press Alarm Lo PRZR Press Alarm Both Spray Valves Open PI-429, 430, 431 Rapidly decreasing Response :

RATING RO/BOP Notify SRO of PT-449 Failing High Rapid decreasing PRZR Pressure SRO Direct RO to place PC-431K in manual and to manually control PRZR Pressure SRO Enter AP-PRZR.l Abnormal PRZR Pressure SRO Direct RO to check PRZR Pressure Channels/Determine PT-449 has failed Refer to ER-INST.1 SRO Note that Tech Specs for R x Press c 2205 have been entered SRO Enter ER-INST.l SRO Determine that PORV do not have to be isolated and Hot leg streaming is not an issue (no power reduction required)

SRO Direct BOP to defeat PT-449 per attachment (STA or RO to peer or IV)

SRO When attachment complete, direct RO to restore PC-431K to Auto

CONSTELLATION ENERGY NO.: Exam 04-2 Scenario 1 REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE: NRC Exam Scenario 04-2-1 EXAMINATION SCENARIO DATE: 911 3/04 PAGE: 10 of 1 7 SRO Check Tech Spec - 3.3.1 functions 5, 7a

- 3.3.1 functions 1 and 6 (all satisfied after defeat A-52.4 for tracking only)

SRO Return to AP-PRZR.1 SRO Direct restoration of normal plant conditions

- PRZR Heater/Sprays

- PORV

- 431K SRO Notify Higher Supervision

~~

CONSTELLATION ENERGY NO.: Exam 04-2 Scenario 1 REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE: NRC Exam Scenario 04-2-1 I EXAMINATION SCENARIO DATE: 9113104 PAGE: 11 of 17

6. EVALUATION Event : 3 Event

Title:

Bus 16 Fault Emected Response/Behavior CUES: Breaker Trip Bus 16 deenergized B D/G starts but does not load Response :

RATING a SRO Determine Bus 16 is lost, enter AP-ELEC.14/16 SRO Direct rod be placed in manual SRO Check D/G's and Buses Determine ECA-0.0 should not be entered (Step 3 RNO)

SRO/RO/ Check Equipment BOP - CCW Pumps

- Charging Pumps

- MFW Reg Valves SRO Direct starting of redundant equipment on Bus 14

- Boric Acid Pumps

- RMW Pump

- Rx Compartment Cooling Fan

- Penetration Cooling Fan

- SFP Cooling SRO Direct A0 to Swap Aux Building Lighting SRO Direct A0 to supply alternate cooling to D/G B and to cross connect the fuel oil transfer systems (ER-D/G.1)

SRO/RO Check the following

- VCT Makeup

- Charging Pump (one running)

- > 20 g p m Charging line flow

CONSTELLATION ENERGY NO.: Exam 04-2 Scenario 1 REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE: NRC Exam Scenario 04-2-1 EXAMINATION SCENARIO DATE: 911 3/04 PAGE: 1 2 of 1 7

- Letdown line flow

- Przr Heaters

- Rod SRO Direct crew to stabilize plant condition

- Tavg

- PRZR Press

- PRZR Level SRO Determine Bus 16 not restored SRO Check DC Loads

- TDAFW Pump Oil Pump

- Battery Chargers Direct electricians crosstie B Battery to TSC

~ ~~ ~

CONSTELLATION ENERGY NO.: Exam 04-2 Scenario 1 REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE: NRC Exam Scenario 04-2-1 EXAMINATION SCENARIO DATE: 9113/04 PAGE: 13 of 17 Event : 4 Event

Title:

"A" Charging Pump Trip Expected Response/Behavior CUES: Loss of Charging Line and Seal Injection Flow Regen H x Hi Outlet Temp Alarm (A-4)

Motor Off Alarm ( G - 2 5 )

Response :

SRO Recognize loss of charging Enter AP-CVCS.3 SRO Direct restart of "At1Charging Pump SRO Direct Letdown be isolated SRO Direct RO/BOP to check the following:

- Thermal Barrier Cooling

- PRZR Level

- VCT M/U SRO Determine no Charging Pumps available Go to Step 17 (Load Reduction)

SRO Direct Load Reduction/4160V Bus Transfer SRO Direct monitoring of plant parameters

- Tavg

- IA

- PRZR Press

- MFW Reg Valves SRO Direct one MFW be secured

I I I 1 CONSTELLATION ENERGY NO.: Exam 0 4 - 2 Scenario 1 I REV: 0 R. E. GlNNA NUCLEAR POWER PLANT TITLE: NRC Exam Scenario 04-2-1 I

1 EXAMINATION SCENARIO I DATE: 9/13/04 I PAGE: 1 4 0 f 17 1 SRO Direct Checking

- Trim valves

- AMSAC

- HDT pump SRO Direct MFW Bypass Valve be placed in A u t o and systems aligned for low power operations SRO Direct Turbine Trip and Verification of Steam Dump operation SRO Direct Rx Shutdown

~

CONSTELLATION ENERGY NO.: Exam 04-2 Scenario 1 REV: 0 R. E. GlNNA NUCLEAR POWER PLANT TITLE: NRC Exam Scenario 04-2-1 EXAMINATION SCENARIO DATE: 9113/04 PAGE: 15 of 1 7 Event : 5 Event

Title:

Steamline Rupture Both MSIV Stuck Open Emected Resnonse/Behavior CUES: Loud Noise in MCR Steam Pressure decreases rapidly SI Response :

SRO Recognize SI occurred Transition to E-0 SRO Verify Immediation Actions

- Rx Trip

- Turbine Trip

- Power - 14, 17, 18 energized, 16 deenergized

- SI Actuated SRO Verify Auto Actions (step 5-13)

One Train only (Bus 16 deenergized)

- Verify SI/RHR pumps running A/C SI, A RHR

- Verify CNMT ReCirC Fans Running A/D

- Verify CNMT Spray not required SRO Check Main Steam Isolation Determine MSL should be isolated/direct CO to manually close

- Verify MEW Isolation

- Verify MDAFW Pump Verify TDAFW Pump running

- Verify SW pumps running

- Verify CI/CVI

- Check CCW Pump running

- Check SI/- flows

- Verify AFW Valve Alignment SRO Monitor Heat Sink

- Verify 5 200 gpm f l o w

I CONSTELLATION ENERGY NO.: Exam 04-2 Scenario 1 REV: 0 R. E. GINNA NUCLEAR POWER PLANT I EXAMINATION SCENARIO I DATE: 9/13/04 I PAGE: 160f 17 1 SRO Direct RO/BOP to check System Alignments

- SI/RHR

- CCW to RCP Thermal Barriers

- TDAFW (DO not stop)

NOTE: May throttle AFW to 50 gpm/SG based on ECA-2.1, Anticipatory Action.

SRO Check RCS Temp

- Decreasing uncontrollably

- Direct throttling AFW to 200 gpm total

- Attempt to close MSIV's Check PORVs and Sprays Check RCP Trip Criteria (should not be met)

SRO Check S/G Secondary Sides

-Determine they are faulted

-Transition to E-2 (Note: At some point, depending on the rate they proceed through E-2 and ECA-2.1, they will reach an Orange Path on FR-P Integrity Status Tree. When they reach that point, the SRO should transition to FR-P.l)

SRO Direct attempt to close MSIV's SRO Determine both S/G's Faulted Transition to ECA-2.1 SRO Direct attempt to isolate S/G (ECA-2.1Step 1)

SAT UNSAT CT FR P.l-B Control the AFW Flow Rate before an extreme (Red Path) challenge develops to the integrity CSFST (Throttle AFW to - 5 0 gpm/SG)

(More actions may be taken in ECA-2.1 depending on timing)

SRO Determine Orange Path exists Transition to F'R-P.l SRO Check RCS Pressure and Cold Leg Temp (Control AFW flow)

CONSTELLATION ENERGY NO.: Exam 04-2 Scenario 1 REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE: NRC Exam Scenario 04-2-1 EXAMINATION SCENARIO DATE: 911 3/04 PAGE: 1 7 of 1 7 SRO Check SI Pump Running SRO Determine SI can be terminated SRO Direct Reset of SI SRO Direct stopping all SI and RHR pumps SAT UNSAT CT FR P.1-A Terminate SI flow so that if the challenge to The integrity CSF is severe and extreme Challenging is powerful and if extreme, SI is Terminated prior to the end of the scenario.

(NOTE: Do not terminate scenario until a Red Path exists on the Integrity CSFST in order to allow for proper classification.)

End Scenario