ML043280223

Draft - Section C Operating (Folder 2)

ML043280223
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: ML043280223 (31)

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CONSTELLATION ENERGY NO.: Exam 04-2 Scenario 1 REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE: NRC Exam Scenario 04-2-1 L.. EXAMINATION SCENARIO DATE: 9113/04 PAGE: 1 of 1 6 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 REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE: NRC Exam Scenario 04-2-1

\--

EXAMINATION SCENARIO DATE: 911 3/04 PAGE: 2 of 16

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 l'Bll 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).

L 1.5 Charging Pump I'A1' 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.1 and take actions to reduce AFW F l o w and Terminate SI to prevent over pressurizing the RCS.

I CONSTELLATION ENERGY NO.: Exam 04-2 Scenario 1 REV: 0 k

I R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO TITLE: NRC Exam Scenario 04-2-1 I DATE: 9/13/04 I

I PAGE: 3 o f 16

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.

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

I EXAMINATION SCENARIO I DATE: 9/13/04 I PAGE: 4 of 16

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 100°F in last 60 minutes and Cold leg temperature on either cold leg is c 285°F and AFW flow rate to faulted S/G is > 50 g p m 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.1-A Task: Terminate SI flow so that if the challenge to integrity CSF is

- severe, an extreme challenge is prevented L

- 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 R x 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: 9/13/04 PAGE: 5 of 16

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 llBll 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

-c EXAMINATION SCENARIO DATE: 9/13/04 PAGE: 6 of 16 4.3.4 Main Steam Line Rupture/Both MSIV's Stuck Open MALF STM05A, loo%, 0 sec TD MALF STM05B, loo%, 0 sec TD MALF STM03, 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 "A" Charging Pump Trip A0 reports burnt Trigger 3 insulation smell in Charging Pump Room on investigation.

55 min 4.4.5 Steamline Rupture A0 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 R . E. GINNA NUCLEAR POWER PLANT TITLE: NRC Exam Scenario 04-2-1 EXAMINATION SCENARIO DATE: 911 3/04 PAGE: 7 of 16

5. TURNOVER INFORMATION 5.1 Plant Status 47% Power MOL C, 8 5 0 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.

5.2 Ecmipment Out of Service IlBll 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 lrBrl Charging Pump overhaul 5.4 Planned Work Return to 100% power 5.5 Sisnificant Events 5.6 Remarks Start the IlBll MFW pump and increase load.

r CONSTELLATION ENERGY NO.: Exam 04-2 Scehario 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 16 Event : 1 Event

Title:

Start the llBlr MFW PumD ExDected Response/Behavior CUES: Procedure 0-5.2 directs start of the pump Response :

RATING 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

CONSTELLATION ENERGY NO.: Exam 0 4 - 2 Scenario 1 REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE: NRC Exam Scenario 04-2-1 EXAMINATION SCENARIO DATE: 9 / 1 3 / 0 4 PAGE: 9 of 16 6 EVALUATION Event : 2 Event

Title:

PT-449 Fails High Emected ResDonse/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 :

RO/BOP Notify SRO of PT-449 Failing High Rapid decreasing PRZR Pressure SRO Direct RO to place PC-431K in manual and to L 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.l 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

\. I EXAMINATION SCENARIO I DATE: 9/13/04 I PAGE: 1 0 o f 16 SRO Check Tech Spec - 3.3.1 functions 5, 7a

- 3.3.1 functions 1 and 6 (all satisfied after defeat A-52.4 or 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

- EXAM INATl ON SCENARIO DATE: 911 3/04 PAGE: 11 of 16 Event : 3 Event

Title:

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

RATING U 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 A u x Building Lighting SRO Direct A 0 to supply alternate cooling to D/G B and to cross connect the fuel oil transfer systems (ER-D/G.l)

SRO/RO Check the following

- VCT Makeup L - Charging Pump (one running)

- > 20 gpm 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: 9/13/04 PAGE: 1 2 of 16

- 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

I I I I CONSTELLATION ENERGY NO.: Exam 04-2 Scenario 1 I REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE: NRC Exam Scenario 04-2-1 EXAMINATION SCENARIO DATE: 911 3/04 PAGE: 13 of 16 Event : 4 Event

Title:

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

Motor O f f Alarm (G-25)

Response :

RATING N A SRO Recognize loss of charging Enter AP-CVCS.3 SRO Direct restart of "A" Charging 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

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

L EXAMINATION SCENARIO I DATE: 9/13/04 I PAGE: 1 4 o f 16 1 SRO Direct Checking

- Trim valves

- AMSAC

- HDT pump SRO Direct MFW Bypass Valve be placed in Auto 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

\ EXAMINAT10N SCENARIO DATE: 911 3/04 PAGE: 1 5 of 16 Event : 5 Event

Title:

Steamline Rupture Both MSIV Stuck Open Expected Response/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

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

One Train only (Bus 16 deenergized)

SRO Monitor Heat Sink 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 SRO Check S/G Secondary Sides Determine they are faulted Transition to E-2

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

L -' EXAMINATION SCENARIO 1 DATE: 9/13/04 I PAGE: 160f 16 (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 MSIVrs SRO Determine both S/G's Faulted Transition to ECA-2.1 SRO Direct attempt to isolate S/G (ECA-2.1 Step 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 - 50 gpm/SG)

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

L-'

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

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.l-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.)

L End Scenario

CONSTELLATION ENERGY NO.: Exam 0 4 - 2 Backup REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE: NRC Exam Scenario 04-2-2 L.'

EXAMINATION SCENARIO DATE: 911 3/04 PAGE: 1 of 15 Written by: Ken Masker Date : 9/13/04 Sr. License Instructor Technical Review: Joe Hoover Date : 9/16/04 Sr. License Instructor Time validated 80 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 0 4 - 2 Backup REV: 0 R. E. GlNNA NUCLEAR POWER PLANT TITLE: NRC Exam Scenario 04-2-2 EXAMINATION SCENARIO DATE: 911 3 / 0 4 PAGE: 2 of 15

1. SCENARIO OVERVIEW 1.1 The plant is at 100% power, MOL, Xenon Equilibrium condition. The rrB1rRHR pump is 00s due to a seal cooler leak and the CNMT Recirc Fan B is 00s due to a motor cooler leak.

1.2 PT-427 Przr level fails low causing a letdown isolation. The crew should respond using ER-INST.l to defeat the channel and S-3.2E to restore letdown.

1.3 Upon restoring Letdown, a leak develops in the non-regen Hx causing loss of RCS coolant to the CCW system. The crew should terminate the leak per AP-CCW.1.

1.4 RCS Flow Transmitter FT-412 fails low. The crew should defeat it per ER-INST.1.

1.5 High turbine vibration occurs. The crew should enter AP-TURB.3 and reduce load to stabilize vibration.

1.6 A SBLOCA occurs. The crew should respond using E-0 and E-1.

v- 1.7 The only available RHR pump trips. The crew should enter ECA-1.1 start a 100"F/hr cooldown and minimize the amount of injection water.

CONSTELLATION ENERGY NO.: Exam 04-2 Backup REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE: NRC Exam Scenario 04-2-2 EXAMINATION SCENARIO DATE: 9113/04 PAGE: 3 of 1 5

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

2.1.1 Ability to respond to a failure of LT-427 by placing the channel in defeat and restoring Letdown.

2.1.2 Ability to respond to a non-regen Hx leak by isolating Letdown and placing Excess Letdown in service.

2.1.3 Ability to respond to a FT-412 failure by defeating the channel per ER-INST.l.

2.1.4 Ability to respond to a High Turbine Vibration by reducing load to stabilize vibration.

2.1.5 Ability to respond to a SBLOCA by utilizing E-0 and E-1.

2.1.6 Ability to respond to a loss of emergency coolant recirculation.

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

EXAMINATION SCENARIO DATE: 9113/04 PAGE: 4 of 1 5

3. CRITICAL TASKS (CTs)

CT E-l--C Task: Trip the RCPs within 5 minutes of the time RCP trip criteria met Cues: Two SI pumps running and RCS pressure minus maximum SG pressure is c 175 psig (400 psig adverse)

Indication: RCPs are manually tripped Feedback : RCPs indicate tripped from status lights No flow indicated on loop flow instruments CT ECA-3.1-B Task: Cool down the RCS to cold shutdown conditions at highest rate achievable but less than 100°F/hr. In both RCS cold legs.

Cues: Indication that SI is required

- RCS pressure and Emergency coolant recirculation cannot be established

- RHR pump cannot be started and RWST inventory being depleted

- RWST level indicators Indication: Manipulation of controls as required to initiate RCS cooldown at the highest rate achievable but less than 100°F/hr. In both RCS cold legs.

- ARV or condenser steam dump

- Control SG water level to maintain heat sink

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

._ EXAMINATION SCENARIO DATE: 911 3/04 PAGE: 5 of 15

3. CRITICAL TASKS (CTs)

CT ECA-1.1-B Task: Minimize RWST outflow.

Cues: Indication that SI is required

- RCS pressure and Emergency coolant recirculation cannot be established

- RHR pump cannot be started and RWST inventory being depleted

- RWST level indicators and Procedure directs that SI flow be reduced Indication: Manipulation of controls to reduce injection flow in accordance with ECA-1.1.

Feedback: SI and charging flow Reduced depletion rate of RWST L-'

CONSTELLATION ENERGY NO.: Exam 0 4 - 2 Backup REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE: NRC Exam Scenario 04-2-2 EXAMINATION SCENARIO DATE: 9/13/04 PAGE: 6 of 1 5

4. INSTRUCTOR ACTIONS Problem Time Act ions 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 Set up Simulator to IC-19 100%

MOL (NOTE: Setup saved as IC-172) 4.2.2 Place the following components in pull stop

- RHR Pump B A-52.4 TS 3.5.2A 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> into 72 hr clock

- CNMT Recirc Fan B A-52.4 TS 3.6.6F L'

8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> into 7 day clock

- Start the C Recirc Fan 4.2.3 Insert Malfunctions 4.2.3.1 Pressurizer Level Malfunction MALF PZR03B, 0 , 10 sec ramp, 0 time delay Trigger 1 4.2.3.2 Non-Regen H x Leak MALF CLG03 2 5 gpm, 0 sec ramp, 0 time delay Trigger 2 4.2.3.3 RCS Flow Transmitter Failure MALF RCSlOB, 0, 30 sec ramp, 0 time delay Trigger 3

CONSTELLATION ENERGY NO.: Exam 04-2 Backup REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE: NRC Exam Scenario 04-2-2 EXAMINATION SCENARIO DATE: 911 3/04 PAGE: 7 of 1 5 4.2.3.4 Turbine High Vibration MALF TUR05E, 9 mils, 600 sec ramp, 0 time delay Trigger 4 4.2.3.5 RCS SBLOCA MALF RCS02B, 1000 gpm, 0 sec ramp, 0 time delay Trigger 5 4.2.3.6 RHR Pump A Trip MALF RHROlA, 0 time delay Trigger 6 4.4 Event Initiation 2 min 4.4.1 LT-427 Failure Trigger 1 15 min 4.4.2 Non-Regen H x Leak u

(After Trigger 2 Letdown restored) 25 min 4.4.3 RCS Flow Transmitter fails Trigger 3 35 min 4.4.4 Turbine High Vibration When the operator Trigger 4 decreases power by 5%, lower turbine vibration to 5 mils, 120 sec ramp 50 min 4.4.5 SB LOCA Trigger 5

-60 rnin 4.4.6 RHR Pump Trip Trigger RHR pump trip Trigger 6 immediately following transition to E-1.

Terminate scenario as directed by the Lead Examiner.

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

5. TURNOVER INFORMATION 5.1 Plant Status The plant is at 100% MOL condition, C, 845 ppm Xenon Equalibrium 5.2 Eauipment Out of Service llB1l RHR Pump (A-52.4 out for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock) lrB1l CNMT Recirc Fan (A-52.4 out for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> on a 7 day clock) 5.3 Work in Prosress I1B1l RHR Pump Cooler Repair 5.4 Planned Work v CNMT entry later this shift for work on the B CNMT Recirc Fan Cooler 5.5 Sisnificant Events None 5.6 Remarks Continue 100% power operation, restore llBrl RHR pump and llBlr CNMT Recirc Fan as soon as repairs are complete.

r I I CONSTELLATION ENERGY NO.: Exam 04-2 Backup I REV: 0 R . E. GINNA NUCLEAR POWER PLANT TITLE: NRC Exam Scenario 04-2-2 EXAMINATION SCENARIO DATE: 911 3 / 0 4 PAGE: 9 of 15 L-

6. EVALUATION Event : 1 Event

Title:

LT-427 Fails Low Expected Response/Behavior CUES: Pressurizer Lo Level Alarm (F-11)

Letdown Isolation Mismatch between LI-426, 428 and 427 Response :

RATING u SRO Recognize LT-427 Failure. Enter ER-INST.l.

SRO Direct RO to perform the following:

- Place charging to manual

- Minimize charge flow

- Adjust HCV-142

- Close AOV'S 427, 200A/B, 2 0 2 SRO Direct BOP to defeat LT-427 per Attachment PRZR LEVEL LI-427 White Channel SRO When attachment is complete, direct RO to restore PRZR Heaters and perform S-3.2E to restore Letdown SRO Check Tech Specs 3.3.1 Function 8, 3 . 3 . 3 Function 2, 3.4.9

CONSTELLATION ENERGY NO.: Exam 04-2 Backup REV: 0 R. E. GlNNA NUCLEAR POWER PLANT TITLE: NRC Exam Scenario 04-2-2 L EXAMINATION SCENARIO DATE: 911 3/04 PAGE: 10 of 15

6. EVALUATION Event : 2 Event

Title:

Non-Regen Hx Tube Leak ExDected ResDonse/Behavior CUES: R-17 CCW Surge Tank Radiation Alarm CCW Surge Tank Level increasing Response :

RATING %A SRO Recognize symptom of leakage into CCW Enter AP-CCW.l SRO Direct RP to perform CH-PRI-CCW-LEAK SRO/RO Determine leak not in Thermal Barrier

-2 SRO Determine leak in Non-Regen Hx Direct RO to isolate letdown SRO Determine leakage stopped Direct RO to place Excess L/D in service per Attachment 9.1 SRO Direct RO/BOP to stabilize plant SRO Determine plant operation can continue SRO Consult with RP about draining CCW Surge Tank (if > 50% level)

SRO Notify higher supervision

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

6. EVALUATION Event : 3 Event

Title:

RCS Flow Transmitter Failure Emected ResDonse/Behavior CUES: RCS Low Flow Channel Alert FI-412 Indicates Zero Response :

SRO Enter ER-INST.l SRO Direct BOP to defeat LT-412 per attachment IA-2 Rx Coolant Flow FI-412 White Channel SRO Check Tech Specs Section 3.3.1 Functions 9a and 9b

CONSTELLATION ENERGY NO.: Exam 04-2 Backup REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE: NRC Exam Scenario 04-2-2 EXAM INATl ON SCENARIO DATE: 9/13/04 PAGE: 12 of 15 i_-

6. EVALUATION Event : 4 Event

Title:

Turbine High Vibration Expected Response/Behavior CUES: High Vibration Alarm (1-27)

Response :

SRO Enter AP-TURB.3 SRO Direct BOP to monitor Turb Vib SRO When vibration greater than 7 mil, refer to AP-TURB.5 and reduce load is SRO Direct RO/BOP to initiate Load Reduction

- Rods in Auto

- EHC/Rate

- Steam Dump Operation SRO Verify vibration stabilized Direct load decrease to be stopped SRO Direct RO/BOP to stabilize plant Restore normal equipment lineup SRO Direct A0 to check turbine for noise SRO Notify higher supervision

I CONSTELLATION ENERGY NO.: Exam 0 4 - 2 Backup REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE: NRC Exam Scenario 04-2-2 EXAMINATION SCENARIO DATE: 911 3 / 0 4 PAGE: 13 of 15

6. EVALUATION Event : 5/6 Event

Title:

RCS SBLOCA/Loss Emergency Coolant Recirc Expected Response/Behavior CUES: RCS Pressure decreasing CNMT Radiation Alarms PRZR Level decreasing Response :

RATING (NOTE: May enter AP-RCS.l RCS Leak but time in this procedure will be limited SRO Recognize Rx Trip. Enter E-0.

v SRO Verify Immediate Actions (May manually actuate SI1 SRO Direct verifications of equipment status (steps 5-18)

SRO Direct throttling of AFW as necessary (16)

Control Tavg (20)

SAT UNSAT I CT E-l--C Trip the RCP within 5 minutes of RCP Trip criteria beinu m e t SRO Check for Steam Line break, SGTR, LOCA Determine LOCA has occurred, go to E-1 NOTE: At this time, the AI1 RHR will trip SRO Check Secondary Side Parameters

- Intact

- Level

- Radiation

CONSTELLATION ENERGY NO.:Exam 04-2 Backup REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE: NRC Exam Scenario 04-2-2 EXAMINATION SCENARIO DATE: 911 3/04 PAGE: 14 of 15 L

SRO Direct Reset of SI and CI SRO Direct Restoration of Inst Air

- Check SW

- Restore IA to CNMT SRO Direct Charging Flow be established SRO Determine SI cannot be terminated SRO Check RCS Temp/Pressure Continue with Step 16 (LOCA exists)

SRO Direct BOP to stop D/G SRO Determine Sump Recirc not available.

Transition to ECA-1.1.

SRO Check Recirc Equipment

- RHR Pump not available

'--- - Direct attempts to restore RHR be initiated SRO Check Recirc Fans all running and RWST z 15%

SAT UNSAT CT ECA 1.1-B Minimize RWST Outflow

- Reduce CNMT Spray per table (Step 4 )

- Establish one train of ECCS (Step 10)

- Limit RCS injection (Step 17)

SAT UNSAT CT ECA 3.1-B Cooldown the RCS to CSD at highest rate achievable but less than 100°F/hr in both Cold Legs SRO Direct RO to establish 20 gpm charging time flow SRO Check if an RCP can be started Direct start of an RCP (May not meet subcooling at this time and, therefore, not start the RCP

CONSTELLATION ENERGY NO.: Exam 0 4 - 2 Backup REV: 0 R. E. GlNNA NUCLEAR POWER PLANT TITLE: NRC Exam Scenario 04-2-2 L EXAMINATION SCENARIO DATE: 911 3/04 PAGE: 15 of 1 5 Terminate Scenario