ML062700286

Draft Ginna Exam Aug. 2006 - Section C Operating Exam (Folder 2)

ML062700286
Person / Time
Site:	Ginna
Issue date:	08/03/2006
From:	Ginna
To:	Todd Fish Operations Branch I
Sykes, Marvin D.
References
50-244/06-301 50-244/06-301
Download: ML062700286 (78)

Text

CONSTELLATION ENERGY NO.:

06-1-1 Written by: Ken Masker Date: 3/23/06 Sr. License Instructor REV: 0 Technical Review: Dennis Jones Date: 5/18/06 Exam Developer R. E. GINNA NUCLEAR POWER PLANT L/

EXAMINATION SCENARIO Time validated 100 minutes By: ROY Gillow Date: 5/18/06 Shift Manager Date of exam:

Examinees Evaluators TITLE:

SCENARIO #I DATE:

03-29-06 PAGE: 1 of 2 9 I Final review Date :

License Instructor

.-.--/

Approved for use Date :

Director Operations Training or Designee ATTRIBUTE Total Malfunctions Malf after EOP entry Abnormal Events Major Transients EOP' s beyond SCRAM ECA's, FR's Critical Tasks T.S. Exercised Yes/No ff.

8 2

4 2

1 0

3 Yes

CONSTELLATION ENERGY NO.:

06-1-1

1.

SCENARIO OVERVIEW REV: 0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 1.10 R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO

'W The plant is at approximately 2% power in the process of starting up following a trip. The core is Xenon free. The startup procedure 0-1.2 is complete up to the point of swapping to condenser steam dump, starting a MFW pump and transitioning from AFW to MFW.

Per the startup procedure, the operators will start a MFW pump and place MFW in service. Once MFW is in service AFW will be secured.

TITLE:

SCENARIO #1 DATE: 03/29/06 PAGE: 2 o f 29 With MFW in service, the RO will begin increasing power in preparation for rolling the main turbine.

Spray Valve Controller PCV-431A fails resulting in 431A going full open.

Manual control is available and the operators should take manual control of PCV-431A and close the valve.

The "Aff MFW Regulating Valve fails open, manual control is available and the BOP should take manual control and control "A" S/G level manually.

Bus 16 develops a fault and the normal feed breaker opens deenergizing the bus. The operators should respond per AP-ELEC-14/16 to restore equipment and stabilize the plant (Tech Spec 3.8.9).

"Brf RCP develops high vibration. Per the AR procedures the operators should manually trip the reactor and go to E-0 and ES-0.1.

Shortly after the Hi Vibration on the "Bff RCP the Seal Package fails resulting in a SB LOCA in excess of the charging capacity.

SI fails to auto actuate require manual actuation.

Following SI Reset in E-1 offsite power is lost. The \\'AN D/G did not auto-start during the SI (and will not now). The operators must take manual action to start the "A" D/G and manually load safeguards equipment.

CONSTELLATION ENERGY R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO

'.c-/

2. SCENARIO OBJECTIVES 2.1 Perform operator actions to establish MFW and secure AFW.

2.2 Manipulate Reactivity Control Systems to increase Rx power during a startup.

2. 3 Respond to a failed spray valve controller. Take manual action to override the failed automatic control.

NO.:

06-1-1 REV: 0 TITLE: SCENARIO #1 DATE: 03/29/06 PAGE: 3 of 29 2. 4 Respond to a Feed Reg Valve failure and manually control S/G level.

2.5 Respond to a loss of a safeguards bus. Take action to restore equipment and stabilize plant parameters.

2.6 Respond to a RCP High Vibration condition requiring a manual Rx Trip.

2. 7 Respond to a SBLOCA using the EOP. Initiate SI to compensate for a 2.8 Restore electrical power to one train of AC emergency equipment and manually start SI equipment needed to respond to the SBLOCA.

failed auto signal.

W 3. CRITICAL TASKS (CtsL CONSTELLATION ENERGY NO.:

06-1-1 REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE:

SCENARIO #1 EXAMINATION SCENARIO DATE: 03/29/06 PAGE: 4 of 29 CT #1 E-0--D Task: Manually actuate at least one train of SIS actuated safeguards before:

0 Transition to any E-1, 2 or 3 series procedures.

Completion of ES-0.1 Step 8a Cues: - Indication SI is required.

Prz Pressure 5 1750 psig Exceeding SI actuation criteria of ES-0.1 foldout

- No indication or annunciation of SI Actuation Indication:

Manipulation of control to actuate at least one train of SI.

Feedback: Indication that one train of SI is actuated.

CT #2

.--J E-0--C Task:

Cues: - Indications that all AC emergency buses are deenergized.

Energize at least one AC emergency bus prior to placing safeguard switches in pull to lock in ECA-0.0.

D/G Status Bus Voltage's Normal feed breakers open

- No indication or annunciation of SI Actuation Indicator: Manipulation of controls to restore power to at least one AC Feedback:

emergency bus.

Indications that at least one AC emergency bus is energized.

u 7

~

CONSTELLATION ENERGY R. E. GINNA NUCLEAR POWER PLANT TITLE: SCENARIO #I EXAMINATION SCENARIO DATE: 03/29/06 PAGE: 5 of 29

3. CRITICAL TASKS (Cts)

NO.:

06-1-1 CT #3 REV: 0 E-0--1 Task: Establish flow from at least two SI pumps prior to proceeding in the Cue: Indication SI pumps required SI actuated RCS below SI pump and shutoff pressure procedure following the loss of power.

AND Less than 2 SI pumps injecting into the core.

Indicator:

Manipulation of control to establish flow to core from 2 SI pumps.

Feedback :

Indication that two SI pumps are injecting.

CONSTELLATION ENERGY NO.:

06-1-1 REV: 0 i r

• v'

4. INSTRUCTOR ACTIONS problem Time TITLE:

SCENARIO #I DATE: 03/29/06 PAGE: 6 of 29 R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO Act ions

4.1 (Note

Setup saved as IC-171)

- Initialize Simulator to IC-22 RX at 18%, Tur at 1800 RPM Decrease power to 2 %

Trip Turbine

- Place Hold Tag on B FW Pump and Oil pumps Insert Malfunctions MALF SIS02ArB Option 0 Manual available MALF GEN08 Option 1 A D/G 0 sec TD MALF PZRlA 100% (open) 30 sec Ramp Trigger 1 0

MALF FDW7A 100% (open) 300 sec Ramp Trigger 2 MALF EDS4B Trigger 3 MALF RCSl5B 25 mils 300 sec Ramp Trigger 4 MALF RCS15D 10 mils 300 sec Ramp 60 sec Time Delay Trigger 4 0

MALF RCSl2B 300 gpm 600 sec Ramp Trigger 5 MALF RCS13B 300 gpm 600 sec Ramp Trigger 5 Notes SI fails to actuate (Both Trains)

"A~' D/G Autostart failure PCV 431A control failure (Manual available)

"A" MFRV Auto control fails (open). Manual Control available Bus 16 Fault

'\\Brr RCP Shaft Vibration "B" RCP Seismic (Casing) Vibration "B" RCP #1 Seal Failure

\\'B" RCP #2 Seal Failure

\\W MALF RCS14B 300 gpm 0 Ramp Trigger 5 CONSTELLATION ENERGY NO.:

06-1-1 REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE:

SCENARIO #1 EXAMINATION SCENARIO DATE: 03/29/06 PAGE: 7 of 29 0

MALF EDS6 2 (Fast)

Trigger 6 OVR-FDW08A OFF OVR-FDW20A OFF OVR-FDW20C OFF "B" RCP #3 Seal Failure Station Blackout Turn off green light for MFW Pump B Oil Pump Turn off green light for MFW Pump B Brkr Turn off green light for MFW Pump B Brkr

~

~~

CONSTELLATION ENERGY TITLE:

SCENARIO #I I

NO.:

06-1-1 REV: 0 4. INSTRUCTOR ACTIONS Problem Time Actions Notes Note: Malfunction Times are approximate: Malfunction are initiated at the direction of the Lead Examiner.

0 min 4. 2 MFW Pump Start 20 min 30 min 37 min 4.3 Power escalation 4.4 PCV-431A Failure Insert Trigger 1 Insert Trigger 2 4.5 "AN MFRV Fails Open 4. 6 BUS 16 Fault Insert Trigger 3 5 0 min 62 min 65 min 8 0 min 4.7 "B" RCP Hi Vibration Insert Trigger 4 Insert Trigger 5 4.9 Station Blackout Insert Trigger 6 4.8 "B" RCP Seal Failure Align SW to A MFW pumps requested. SW not modeled Action as requested by crew Report ADFAC Alarm as "AN MFRV output card failure when requested to check printer.

Report Bus 16 is faulted after requested to investigate.

Terminate Scenario as directed by the lead examiner

CONSTELLATION ENERGY NO.:

06-1-1

5. TURNOVER INFORMATION REV: 0 5.1 The plant is at 2-3% power during a startup following a trip five days ago. The core is Xenon free. RCS boron concentration is 1335 ppm.

Procedure 0-1.2 is complete up to step 6.4.6(20). Attachment 5 Main Feed Water Pump "A" is complete through step 1.8.2.

R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO u

5.2 EquiDment Out of Service

'\\BJr MFW pump is out of service due to a gear box failure.

TITLE:

SCENARIO #I DATE: 03/29/06 PAGE: 9 of 29 5.3 Work in Prosress

\\'Brr MFW pump gear box repair (additional 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> to repair).

5.4 Planned Work Plant startup from approximately 2% power.

5.5 Siqnificant Events "B" MFW pump gear box failure resulted in a Rx trip five days ago.

5.6 Remarks Startup plant per 0-1.2, hold at 50% power until work is complete on the

\\\\Brr MFW pump.

CONSTELLATION ENERGY NO.:

06-1-1

6. EVALUATION Event :

1 Event

Title:

Main Feedwater Pump Start/Transition to > 5% power REV: 0 EVENT TASKS:

041-002-01-01 Shift Modes of Steam Dump Operation 041-002-01-02 Direct Steam Dump Operations 059-006-01-01 Startup the MFW System 059-012-01-02 Direct Operations of MFW System 061-007-01-01 Shutdown AFW System 061-003-01-02 Direct Operations of AFW and SAFW System R. E. GlNNA NUCLEAR POWER PLANT EXAMINATION SCENARIO

-u Expected Response/Behavior CUES :

Procedure Direction in 0-1.2 TITLE:

SCENARIO #I DATE: 03/29/06 PAGE: 10 of 29

Response

SRO BOP / SRO BOP

'b-'

RATING m

Conduct Shift Briefing for Power Increase and Syncing Generator Place Condenser Steam Dump in Service Verify Rx Trip from Turbine Trip Blocked (P-9) Light lit 0 Verify Air Ejector is in service Verify Vacuum >27.5 in Hg Lower HCV-484 to 1005 psi Verify SD valves respond 0 Setup SG ARV for Auto Operation at 1050 psig Place Blow down key switches to normal

i, Response :

CONSTELLATION ENERGY NO.:

06-1-1 REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE:

SCENARIO #I EXAMINATION SCENARIO DATE: 03/29/06 PAGE: 11 of 29 BOP/ SRO BOP SRO SRO

'Ll' BOP / SRO BOP / SRO Start the "A" MFW pump per Attachment MFW Pump A Place Blowdown key switches to Normal Start the "A" MFW pump Open MOV-3977 Dispatch A0 to close V-39977A Dispatch A0 to close valves AOV 4262 AOV 4263 V-4060 RATING Verify operation of MFW Reg and Bypass Valves Place MFW Reg and Bypass Valves in Auto (Note at this point the RO should begin to increase power to -5%)

CONSTELLATION ENERGY NO.:

06-1-1 REV: 0 BOP / SRO Secure AFW e Close MOV 4007/4008 R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO e Stop AFW Pumps TITLE: SCENARIO #1 DATE: 03/29/06 PAGE: 1 2 of 2 9 e Notify A0 to restore Blowdowns Close cross-tie 4000A/B e Open Discharges 3996/4007/4008 Open TDAFW Control Valves 4297/4298 e Close Bypass Valves 4480/4481 e AFW Defeat Switches to Normal e Verify Recirc Valves Closed

R. E. GINNA NUCLEAR POWER PLANT W'

6. EVALUATION DATE: 03/29/06 PAGE: 13 of 29 Event :

2 Event

Title:

Increase Power to Roll Turbine EVEN" TASKS: 001-023-01-01 Operate the Control Rods at Power 001-001-01-02 Direct Operations of the Rod Control System ExDected Reswonse/Behavior CUES :

Main Feedwater is in service Direction from Procedure 0-1.2 Response :

-4' RO/SRO RO/SRO Withdraw Control Rod to increase power Stop every five steps to verify power indications (Low Power Operations Attachment )

Verify RCS Pressure and Temperature are within startup limits prior to exceeding 5% power RATING ELLA

CONSTELLATION ENERGY NO.:

06-1-1

6. EVALUATION REV: 0 Event :

3 Event

Title:

PCV-431A fails Open EVENT TASKS: 010-002-04-01 Respond to a Przr Press Control Malf 011-002-04-02 Direct Response to a Przr Press Control Malf R. E. GlNNA NUCLEAR POWER PLANT EXAMINATION SCENARIO Expected Response/Behavior TITLE: SCENARIO #1 DATE: 03/29/06 PAGE: 14 of 29 CUES :

Low Pressure Alarm Przr Press Decreasing Response :

RATING Em RO SRO RO/SRO RO/SRO RO/SRO RO/SRO NOTE: Upon determining PCV-431A has failed, the operator may take action to place PCV-431A in manual and close valve without procedural guidance per A-503.1 Determine Przr Pressure decreasing Enter AP-PRZR.l Check all Channels Przr Pressure equal and tracking Check Rx power stable Check Przr Pressure Check Przr Heaters

>w RATING E&

Response :

CONSTELLATION ENERGY NO.:

06-1-1 1 REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE:

SCENARIO #I EXAMINATION SCENARIO DATE: 03/29/06 PAGE: 15 of 2 9 Check Spray Valves Determine AOV-431A open Place 431A Controller at 0% demand in manual RO/SRO RO/SRO Check 431K Master Pressure Controller RO/SRO Check PORV - closed RO/SRO Check Safeties - closed RO/SRO

\\--'

Check Aux Spray - closed RO/SRO Check Pressure trending to 2235 psi (go to step 16)

RO/SRO Check PRT normal RO/SRO Check Przr Pressure Control in Auto (leave 431A in manual)

A1 1 Check Annunciator Status SRO Notification of Supervision

CONSTELLATION ENERGY NO.:

06-1-1

6. EVALUATION Event :

4 Event

Title:

A MFR Valve Fails Open EVENT TASKS: 059-002-04-01 Respond to an Excessive Feedwater increase 059-002-04-02 Direct Response to an Excessive Feedwater increase REV: 0 Expected Response/Behavior R. E. GINNA NUCLEAR POWER PLANT I

EXAMINATION SCENARIO L

CUES :

TITLE:

SCENARIO #I DATE: 03/29/06 PAGE: 16 of 29 Alarm G-22 ADFACS System Trouble Excessive FW to A SG SG A Level rapidly increasing Response :

~ k l BOP SRO BOP/SRO SRO/BOP SRO/BOP BOP / SRO L

Recognize \\\\AN MFW Reg Valve Openning (Note per A-503.1 BOP may take manual control of valve)

Enter AP-FW.l Check MFW > SF 0 Place MFRV in Manual 0 Control Level Manually Verify power < 5 0 %

Verify one MFW pump running Check MFW Pump Suction Press RATING L A

CONSTELLATION ENERGY NO.:

06-1-1 Response :

RATING EL2 REV: 0 BOP/SRO R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO

\\d RO/SRO/

BOP TITLE:

SCENARIO #I DATE: 03/29/06 PAGE: 17 of 2 9 BOP/SRO BOP / SRO RO/BOP/

SRO BOP/SRO RO/SRO/

BOP RO/SRO SRO Verify adequate MFW flow Verify Stable Plant Conditions Tavg 0 Przr Press 0 Przr Level 0 MFW Valves Rod Insertion Limits Check MFW System Check Condensate System Bypass Valve 0 Hotwell Level Condensate Pumps (2 running)

Trim Valves Check Controls in Auto 0 Spray Valve Controllers 0 Przr Heaters Charging (Note Check EHC, MFW Reg Valves, Rods and Steam Dump but do not realign)

PCV-431K Check A F W (Not in service)

Check Annunciator Status Check if Przr mixing required Notify Higher Supervision

CONSTELLATION ENERGY NO.:

06-1-1

6.

REV: 0 EVALUATION R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO Event :

5 Event

Title:

Bus 16 Normal Feeder Breaker Trips EVENT TASKS: 062-034-04-01 Respond to the loss of an individual safesuards Bus 062-034-04-02 Direct response to a loss of an individual safesuard Bus TITLE: SCENARIO #I DATE: 03/29/06 PAGE: 18 of 29 ExDected Response/Behavior CUES :

Alarm L-5 Safeguard Bus Normal Feed Breaker Trip L-7 Bus 16 Undervoltage Bus 16 Voltage Zero Bus 16 Supplied Loads Trip Response :

-4' SRO RO/SRO BOP BOP/SRO RO/SRO RO/SRO Recognize symptoms Enter AP-ELEC.14/16 Monitor/Control Tavg Verify \\\\B" D/G Running (running but will not tie in due to bus fault)

Verify one train of AC Buses energized and check "BN D/G status Verify "A" CCW pump has auto started.

Verify \\'A Charging Pump running RATING L A

CONSTELLATION ENERGY NO.:

06-1-1 Response :

RATING REV: 0 BOP/SRO R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO

.U*

RO/BOP/

SRO TITLE:

SCENARIO #I DATE: 03/29/06 PAGE: 19 of 2 9 SRO RO/SRO RO/SRO RO/SRO RO/SRO RO/SRO RO/SRO Verify MFW Controlling in Auto (manually control \\\\A MFRV)

Check Buses Energized/Manually start equipment 0 CCW Pump A 0 Charging Pump A 0 Przr Proportional Heaters e CNMT Recirc Fans A and D Boric Acid Pump A e RMW Pump A 0 Reactor Compartment Cooler A Penetration Cooling Fan A 0 SFP Cooling (local NLO action)

Swap Lighting (local NLO action) 0 D/G Support System (local NLO action)

Direct A0 to perform the following Swap Aux Bldg Lighting to MCC C e

Provide Alternate Room cooling to DG B e

Cross-connect DG A Fuel Oil transfer pump to DG B Check VCT MU System Check Charging Aligned to VCT Check the CVCS Operation (adjust '\\A Charging Pump 1 Check Letdown in Service Check Przr Heaters in Service Check Rod in Auto (no Action Rod cannot be placed in Auto)

L../

Response :

W T I N G H.bi CONSTELLATION ENERGY NO.:

06-1-1 REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE:

SCENARIO #I EXAMINATION SCENARIO DATE: 03/29/06 PAGE: 2 0 o f 29 RO/SRO Stabilize Plant condition 0 Tavg Przr Pressure Przr Level BOP / SRO Check if normal electrical lineup can be restored (cannot restore due to fault)

Refer to AR-L-5 SRO Check Tech Spec (3.8.9)

CONSTELLATION ENERGY R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO

• w.

6. EVALUATION Event :

6 Event

Title:

RCP B Hish Vibration EVENT TASKS:

003-003-04-01 Respond to RCP Hi Vibration 003-003-04-02 Direct Response to RCP Hiqh Vibration 012-001-05-01 Manually Trip the Reactor NO.:

06-1-1 REV: 0 TITLE:

SCENARIO #I DATE: 03/29/06 PAGE: 21 of 29 Exnected ResRonse/Behavior CUES :

Alarms AR-AA-18 RCP Vibration Alert High Vibration indicated on B RCP at Vibration Panel AR-AA-26 RCP Vibration Danger Response :

SRO

'-d RO/SRO SRO SRO RO/SRO RO BOP BOP id/'

RATING ELLA Enter AR procedure AA-18 RCP Vibration Alert Check RCP indications Notify Plant Personnel Enter AA-26 RCP Vibration Danger Determine Rx Trip required Manual Trip Rx Verify Rx is Tripped Verify Turbine Trip Verify One Train AC Buses Energized

u Response :

RATING ELLA

-~~

CONSTELLATION ENERGY NO.:

06-1-1 REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE:

SCENARIO #I EXAMINATION SCENARIO DATE: 03/29/06 PAGE: 22 of 29 BOP/RO SRO Determine SI not required Transition to ES-0.1 (NOTE RCP Seal Malfunction will start here.

Some actions in ES-0.1 Rx Trip response are possible. 1

CONSTELLATION ENERGY R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO b

6. EVALUATION Event :

7 Event

Title:

SBLOCA (RCP "B" Seals Fail)

EVENT TASKS: 002-002-05-01 Respond to a SBLOCA 002-002-05-02 Direct Response to a SBLOCA NO.:

06-1-1 REV: 0 TITLE:

SCENARIO #I DATE: 03/29/06 PAGE: 23 of 29 Expected Response/Behavior CUES :

RCP Seal Leakoff High RCP Seal High Temps CNMT Radiation Decreasing RCS Inventory Response :

RATING NOTE: Operators may go to AP-RCP.l or AP-RCS.l to address RCP Seal Failure and/or RCS Leakage indications prior to reaching SI Criteria.

.L/'

RO/SRO Determine SI Required. Manually initiate SI.

CT #1 E-0--D UNSAT Manually initiate at least one Train of SI SRO Return to E-0.

RO/BOP RO RO RO Reverify Immediate Actions Verify SI/RHR Pumps running (only A, C SI A RHR)

Verify CNMT Recirc Fans running Verify CNMT spray not required

CONSTELLATION ENERGY NO.:

06-1-1 Response :

BOP REV: 0 BOP R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO 14, BOP TITLE:

SCENARIO #1 DATE: 03/29/06 PAGE: 24 of 29 BOP RO SRO RO RO BOP BOP RO RO/SRO Check MSIV isolation Check MFW Isolation Verify AFW pump running A MDAFW TDAFW (Manual Start)

Verify two SW pumps running 0 Ensure one pump running on Bus 14 Verify CI and CVI Dispatch A0 to verify MOV-814 (Lost Power)

Verify the A CCW pump running Verify SI/RHR Flow (SI flow only above RHR shut-off head)

Check AFW Valve Alignment Monitor Heat Sink (Maintain S/G level 7-50%)

Check ECCS Valve Alignment Check CCW to Thermal Barriers RATING

%!A

CONSTELLATION ENERGY NO.:

06-1-1 Response :

BOP BOP/SRO REV: 0 RO R. E. GINNA NUCLEAR POWER PLANT f

EXAMINATION SCENARIO w

RO/SRO TITLE:

SCENARIO #I DATE: 03/29/06 PAGE: 25 of 29 RO BOP/SRO

-.4 BOP/SRO RO/SRO RO/SRO BOP / SRO BOP BOP/SRO RO

.-i Check TDAFW Pump (Do not stop)

Control Tavg at 547OF (May require throttling AFW to minimum and closing MSIVs Check PORV and Sprays closed Monitor RCP Trip Criteria Verify CREATS actuated Check S/G Secondary intact Check S/G Tube intact Check RCS Intact/Transition to E-1 Check RCP Trip Criteria Check that S/Gs are intact Control S/G levels Monitor S/G Radiation Check PORV and Block Valves RATING E.&

CONSTELLATION ENERGY NO.:

06-1-1 RO/SRO REV: 0 BOP R. E. GINNA NUCLEAR POWER PLANT b b-EXAMINATION SCENARIO SRO TITLE:

SCENARIO #I DATE: 03/29/06 PAGE: 26 of 29 Reset SI Reset CI Start a second SW pump if required.

Dispatch A0 to perform SD-1 (At this point offsite power will be lost)

CONSTELLATION ENERGY NO.:

06-1-1

6. EVALUATION REV: 0 Event :

9 Event

Title:

Loss of Offsite Power EVENT TASKS: 064-003-04-01 Load the Diesel Generator in Unit 064-003-04-02 Direct Action for a Diesel Generator that Does not start 064-003-05-01 Respond to Inadequate SI Flow

\\ v Expected Response/Behavior R. E. GINNA NUCLEAR POWER PLANT TITLE: SCENARIO #I EXAMINATION SCENARIO DATE: 03/29/06 PAGE: 270f 29 CUES :

Bus 14, 18 deenergized All SI/RHR Pumps Trip A D/G not Running Response :

.--/

SRO/BOP RO/BOP BOP RO RO/SRO L J RATING NOTE: Operators may recognize the A D/G is not running. The operators may manual start the D/G without referencing ECA-0.0 as allowed per A-503.1. The first part of the event is written as if they go to ECA-0.0 to address this problem.

Recognize loss of all AC conditions.

Transition to ECA-0.0 Verify Immediate Actions 0 Rx trip Turbine Trip Control Tavg (adjust ARVs)

Check RCP stopped Isolate RCS (check)

PORV 0 Letdown

CONSTELLATION ENERGY NO.:

06-1-1 REV: 0 Response :

BOP

.. W BOP R. E. GINNA NUCLEAR POWER PLANT TITLE:

SCENARIO #1 EXAMINATION SCENARIO DATE: 03/29/06 PAGE: 28 of 29 Verify Adequate TDAFW Flow Restore "A" D/G 0 Check Unit/Auto 0 Start "A" D/G 0 Check Voltage/Freq 0 Check Cooling Available (SW pump) 0 Start the A D/G RATING ELLA I

CT #2 E-0--C SAT UNSAT Energize at least one train of AC Emergency buses prior to placing safeguard switch to pull to lock in ECA-0.0 I

I SRO Transition back to E-0.

,ud SRO/RO Recognize SI equipment must be manually started. Go to Attachment 8.5 Loss of Offsite Power.

RO/SRO Verify CCW Pump Running BOP/SRO Verify one SW Pump Running BOP/SRO Verify TDAFW Pump Running RO/SRO Start 2 SI Pumps SAT UNSAT I

CT #3 E-o--l I

Establish flow from at least two SI pumps prior to proceeding in E-1 following loss of off-site power.

CONSTELLATION ENERGY NO.:

06-1-1 Response :

RO/SRO REV: 0 Start Equipment e RHR (not required) e CNMT Recirc Fans R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO

.v Terminate Scenario as directed by the lead examiner TITLE:

SCENARIO #1 DATE: 03/29/06 PAGE: 2 9 of 29 RATING

.W Written by: Ken Masker Sr. License Instructor CONSTELLATION ENERGY NO.:

06-1-2 I REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE: SCENARIO #2 EXAMINATION SCENARIO DATE:

04-04-06 PAGE: 1 of 24 Technical Review:

Dennis Jones Date: 3/29/06 Date: 5/18/06 Time validated 108 minutes By: Roy Gillow Date: 5/19/06 Date of exam:

Examinees Evaluators Shift Manager Final review Date :

License Instructor Approved for use Date :

Director Operations Training or Designee ATTRIBUTE Total Malfunctions Malf after EOP entry Abnormal Events Major Transients EOP's beyond SCRAM ECA's, FR's Critical Tasks T.S. Exercised Yes/No 11 7

1 5

1 2

1 5

Yes

CONSTELLATION ENERGY NO.:

06-1-2

1.

SCENARIO OVERVIEW REV: 0 "d

R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO i d 1.1 1.2 1.3 1.4 1.5 1.6 1.7

1.8 TITLE

SCENARIO #2 DATE: 03/29/06 PAGE: 2 of 2 4 The plant is at 70% power MOL conditions holding power for Chemistry after returning "B" MFW Pump to Service following maintenance. C, - 900 ppm 11,000 ppm in the BAST. The "B" MDAFW pump is 00s for motor work; out for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, expected back in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (A-52.4 submitted 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> clock). The "B" SW pump is out for motor replacement.

The 'C" Condensate Pump trips. The standby pump fails to start requiring a manual start.

Maintenance reports the "B" MFW has developed a severe oil leak and must be shut down immediately. Power must be rapidly reduced to less than 50%

using AP-TURB.5 to allow stopping the MFW Pump.

Following the power reduction RCS High Activity occurs due to a minor fuel failure. The crew should enter AP-RCS.3 and place a 60 gpm Orifice in service.

A small letdown line leak occurs (ramp up to 30 gpm) after the letdown orifice swap causing high activity in the plant vent. The operators should remove Normal Letdown from service and place excess letdown in service.

A small steam line leak occurs on the tap for PT-479 causing PT-479 to fail low. The steam leak is unisolable (upstream of the Root Isolation Valve and makes the area unaccessible). The operator should defeat PT-479 per ER-INST.l and notify higher supervision.

A SGTR occurs in the "B" SG.The operator should respond per E-0 and E-3.

Following the cooldown in E-3 ruptured S/G pressure cannot be maintained due to the steam leak and ECA-3.1 should be entered.

The "A" MDAFW Pump fails to Auto Start and TDAFW pump trips when it attempts to start.The operators should manually start the "A" MDAFW Pump and establish flow to the "A" S/G to maintain a secondary heat sink.

CONSTELLATION ENERGY R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO L

2. SCENARIO OBJECTIVES 2.1 2.2 2.3 Respond to an increase in RCS activity by increasing cleanup flow per 2.4 Respond to a letdown leak by securing letdown and placing excess letdown Respond to a Condensate Pump trip by manually starting the standby pump.

Perform a plant power reduction per AP-TURB.5, Rapid Load Reduction AP-RCS.3, High RCS Activity in service.

NO.:

06-1-2 REV: 0 TITLE: SCENARIO #2 DATE: 03/29/06 PAGE: 3 of 2 4 2.5 Respond to a failure of PT-479 and defeat the channel in accordance with ER-INST.l.

2.6 Respond to a SGTR with a secondary leak per E-0, E-3 and ECA-3.1 2.7 Respond to a Loss of AFW by manually starting the '\\A" MDAFW Pump and establishing AFW flow to the "A" S/G.

CONSTELLATION ENERGY NO.:

06-1-2 3. CRITICAL TASKS (CtS)

REV: 0 CT #1 R. E. GINNA NUCLEAR POWER PLANT EXAM I NATION SCENARIO i,

AP-CVCS. 1-A TITLE:

SCENARIO #2 DATE: 03/29/06 PAGE: 4 of 24

'*J Task: Isolate RCS leakage path from CVCS System prior to exiting AP-CVCS.1, CVCS Leak Cues: Aux. Building and Plant Vent Rad monitor alarms 0

R-13 Plant Vent Particulate R-14 Plant Vent Gas 0

Area Monitors in the Aux. Building Indications of CVCS Leakage Abnormal, Pressure, Temperature, Flows RCS Water balance indicate unknown leakage Aux. Building sump indications Indicator: Closed valve indication on isolation valves in the leak path.

Feedback: Isolation Valve indicator closed RCS water balance indicate leakage has stopped Aux. Building indication return to normal 0 Radiation 0 Sumps CT #2 E-0--F Task: Establish 200 gpm AFW flow to the S/Gs before transition out of E-0 occurs.

Cues: - Indications of SI Actuated

- Indication that AFW Flowrate is less than minimum required

- Indication \\'A" MDAFW Pump is not running

- Indication of TDAFW Pump Tripped Indicator: Manipulation of controls to establish flow to "A" S/G.

MDAFW Pump \\'A" Control Switch Feedback: Indication that at least minimum required flow is established to "A" S/G

CONSTELLATION ENERGY NO.:

06-1-2

3. CRITICAL TASKS (Cts)

CT #3 REV: 0 E-3--A Task: Isolate feedwater flow and steam flow from the ruptured S/G before a transition to ECA-3.1 occurs.

R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO

=L/

Cues: - Indications of a rupture in one S/G

- Rx Trip

- SI TITLE: SCENARIO #2 DATE: 03/29/06 PAGE: 5 of 24 Indicator: Manipulation of controls to isolate the ruptured S / G.

MSIV ARV Blowdown and Sample Valves TDAFW 0 AFW MFW 0 Local Isolation Feedback: Stable or Increasing Pressure on Ruptured S / G.

No MFW or AFW flow to Ruptured S/G.

CT #4 I

E-3--B

_c-Task: Establish/maintain RCS Temperature so transition out of E-3 does not occur because the RCS temperature is 0 Too high to obtain 20°F subcooling required by E-3.

OR An Orange or Red Path occurs on the Integrity CSFST.

Cues :

Indication that

- One S/G ruptured

- Rx Trip

- SI

- Rupture S/G > 300 psig Indicator: Manipulation of control as required to establish and maintain RCS temperature.

0 Steam Dump a ARVS Feedback: - Steam Flow

- RCS Temperature decreasing

- RCS Temperature less than target temperature c--

CONSTELLATION ENERGY NO.:

06-1-2

3. CRITICAL TASKS (CtS)

CT #5 REV: 0 ECA-3.1-B Task: Cooldown the RCS to Cold Shutdown Conditions.

Cues:

SI Required AND Indication of a FaultedjRuptured S / G Indicator: Manipulations of controls as required to initiate RCS cooldown R. E. GlNNA NUCLEAR POWER PLANT EXAMINATION SCENARIO I/

0 Steam Dump or ARVs 0 AFW to maintain intact S/G level TITLE: SCENARIO #2 DATE: 03/29/06 PAGE: 6 of 24 Feedback: RCS Temperature Decreasing Intact S/G Pressure Decreasing

• LJ

4. INSTRUCTOR ACTIONS Problem Time Actions CONSTELLATION ENERGY NO.:

06-1-2 REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE:

SCENARIO #2 EXAMINATION SCENARIO DATE: 03/29/06 PAGE: 7 o f 24 2 min.

10 min 4.1 Initialize the Simulator to IC-27 (setup saved as IC-172)

Pull stop the "B" MDAFW Pump.

(do not hold 4000A/B or 4007)

Place Block Tag on Pump Switch 0 Pull stop the \\'Bn SW Pump.

Place Block Tag on Pump Switch Insert Malfunctions

- MALF CND04C,

- OVRD CND-08F Trigger 1

- MALF RCS16, 10 pci/ml, 300 sec ramp Trigger 2

- MALF CVC2, 30 gpm, 0 ramp Trigger 3

- MALF SGN3D 0 psig 0 Ramp

- MALF STM2B, 5000 lbm/hr, 0 Ramp Trigger 4 Trigger4

- MALF SGNOIB, 300 gpm, 0 ramp Trigger 5

- LOA FDW 30, Pump Trip Trigger 30

- Set Trigger 30 T:N41B.LE.5.0

- MALF RPS07K IND-OVR-FDW21A/B OFF 4.2 Condensate Pump Trip Trigger 1 4.3 Plant Shutdown Notes C CND Pump trips B CND Auto Start failure RCS High Activity CVCS Leak PT-479 Failure Small steam leak SGTR B S/G TDAFW Pump Trip Trigger on N41<5%

\\\\A" MDAFW Pump Auto Start Failure B MDAFW Pump oil Pump Lights Call as Maintenance Supervisor to report a severe oil leak om "B" MFW Pump. Pump should be shut down immediately

L-0,.

4. INSTRUCTOR ACTIONS Problem Time Act ions CONSTELLATION ENERGY NO.:

06-1-2 REV: 0 R. E. GlNNA NUCLEAR POWER PLANT TITLE: SCENARIO #2 EXAMINATION SCENARIO DATE: 03/29/06 PAGE: 8 of 24 A s soon as 4.4 RCS High Activity Trigger 2 power decease started 3 min 4.5 CVCS Leak after Trigger 3 swapping orif ices 35 min 4.6 PT-479 Failure/Steam Leak Trigger 4 45 Min When Rx is Tripped 4.7 SGTR B Steam Generator Trigger 5 4.8 Ramp Steam leak up to 20K lbm/hr Malf STM2B 200001bm/hr, 120sec ramp Terminate Scenario per direction of the Lead Examiner Notes When RP called report back on survey area dose per AB Area Monitors Crew should declare a Local Rad. Emergency.

A0 access with RP only When called to check (or after 5 min.)

report Intermediate Bldg.

Steam Header area full of STM. Cannot get to isolation valves.

If RP called for sample request applicable sample.

Valve CV signal reset.

CONSTELLATION ENERGY NO.:

06-1-2

5. TURNOVER INFORMATION REV: 0 5.1 The plant is at 70% power holding for Chemistry following return to service of "B" MFW Pump from maintenance on the oil system. RCS Boron Concentration is 900 ppm. BAST Boron Concentration is 11,000 ppm. The A and C Service Water pumps are selected for Auto start. Control Rods are in Manual due to a problem with the Rod Speed Controller.

R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO b

5.2 Equipment Out of Service TITLE:

SCENARIO #2 DATE: 03/29/06 PAGE: 9 o f 24 "B" MDAFW pump is 00s for motor work.

"Br' SW pump is out for motor replacement.

Auto Rod Control is 00s due Rod Speed Controler Failure 5.3 Work in Proqress "B" MDAFW Pump Motor Work "B" SW Pump Motor Replacement Rod Control System Trouble Shooting 5.4 Planned Work Nothing additional.

5.5 Siqnificant Events "B" SW Pump Motor was removed from service due to overheating of the winding.

5.6 Remarks Continue power increase to 100% when Chemistry in spec.

for the "B" MDAFW pump when work is complete (6-8 hours).

Perform AFW PT

CONSTELLATION ENERGY NO.:

06-1-2

6. EVALUATION REV: 0 Event :

1 Event

Title:

Condensate Pumx, Trips EVENT TASKS: 056-001-04-01 Resx,ond to a loss of a Condensate Pump.

056-001-04-02 Direct ResDonse to a loss of a Condensate Pumx, R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO i./

Expected ResDonse/Behavior CUES :

C Condensate Pump Trip MFW Pump NPSH Alarm MFW Pump Low Suction Press Alarm Response :

TITLE:

SCENARIO #2 DATE: 03/29/06 PAGE: 10 of 24 Note the operator may also enter AP-FW.l for actions SRO

• L.--f Enter AR-H-1 BOP Check Condensate Pressure open BOP/SRO Determine that the C Condensate Pump has tripped.

BOP / SRO Start the Standby Condensate Pump BOP Check HDT pump and CND BST pump 4

BOP Check Trim Valve and Reject Valves.

RATING L A BOP Stabilize Secondary Side Close Condensate Bypass Valve

CONSTELLATION ENERGY NO.:

06-1-2 REV: 0

6. EVALUATION Event :

2 Event

Title:

Plant Shutdown to 50% power to remove "B" MFW from service EVENT TASKS:

R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO u

Expected Response/Behavior CUES :

TITLE:

SCENARIO #2 DATE: 03/29/06 PAGE: 11 of 2 4 Notification by Maintenance Supervisor of severe Oil Leak on "B" MFW Pump requiring pump Shutdown as soon as possible Response :

-.-/

SRO RO/SRO BOP/SRO RO BOP RO BOP

'b' Enter AP-TURB.5, Rapid Shutdown Verify Rod in Auto. Initiate Boration Initiate Load Reduction Monitor Tavg Verify IA available to CNMT Monitor Przr Press/Level Monitor S/G Levels RATING K A

Ll

6. EVALUATION (continued)

CONSTELLATION ENERGY NO.:

06-1-2 REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE:

SCENARIO #2 EXAMINATION SCENARIO DATE: 03/29/06 PAGE: 1 2 of 2 4 Response :

BOP RO Monitor Steam Dump Status Add Boric Acid RATING

CONSTELLATION ENERGY NO.:

06-1-2 6. EVALUATION Event :

3 Event

Title:

Hiqh RCS Activity EVENT TASKS: 002-005-04-01 Respond to Hiqh Rx Coolant Activity 002-005-04-02 Direct Response to Hish Rx Coolant Activity 344-012-04-03 A D ~ ~ v Tech Specs for Abnormal Events REV: 0 Expected ResDonse/Behavior R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO CUES :

TITLE:

SCENARIO # 2 DATE: 03/29/06 PAGE: 13 of 2 4 R-9 on Alarm Elevated Area Monitors in Aux. Building and CNMT Response :

=.J RO/SRO SRO RO/SRO SRO Recognize High Activity GO to AP-RCS.3 Direct RP to sample Place 60 gpm Letdown Orifice in service per 0 PCV-135 in Manual 0 TCV-130 in Manual 0 Close 40 gpm Orifice Open 60 gpm Orifice S-3.2P Check Tech Spec Section for RCS Activity RATING

CONSTELLATION ENERGY R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO b

6. EVALUATION NO.:

06-1-2 REV: 0 TITLE:

SCENARIO #2 DATE: 03/29/06 PAGE: 14 of 24 Event :

4 Event

Title:

Letdown Line Leak EVENT TASKS:

004-006-04-01 ResDond to a Letdown Line Leak 004-006-04-02 Direct ResDonse to a Letdown Line Leak ExDected ResDonse/Behavior CUES :

High Radiation Levels in the Auxiliary Building and Plant Vent Aux. Building Sump Alarms Abnormal Press/Temp/Flows in Letdown System Response :

SRO RO/SRO RO/SRO RO/SRO RO/SRO RO/SRO Recognize symptoms Enter AP-CVCS.1 (May also enter AP-RCS.l but this is not the optimal recovery procedure)

Monitor Przr Level (should be stable)

Check VCT M/U System 0 Align for M/U 0 Charging aligned to VCT Check for RCS Leakage Check for leak in Aux. Building Check for Charging Leak

CONSTELLATION ENERGY NO.:

06-1-2 Response :

REV: 0 RO/SRO R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO Check Letdown. Determine Abnormal Isolate Letdown.

0 Close AOV-427, 200A, B 202 0 Close 371 0 Close HCV-142 while adjusting charging 0 Close AOV-294 TITLE:

SCENARIO #2 DATE: 03/29/06 PAGE: 15 of 2 4 RATING xb CT #1 AP-CVCS.l-A SAT UNSAT Isolate leakage path from CVCS prior to exiting AP-CVCS.l, CVCS Leak RO/SRO

--4' RO/SRO RO/SRO A1 1 SRO Verify leak stopped Place Excess L/D in service Establish Auto Control Charging 0 Przr Heaters Check Annunciators Notify Higher Supervision.

CONSTELLATION ENERGY R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO

>-./

6. EVALUATION Event :

5 Event

Title:

Steam Leak on PT-479 Sensins Line NO.:

06-1-2 REV: 0 TITLE:

SCENARIO #2 DATE: 03/29/06 PAGE: 16 of 2 4 EVENT TASKS: 012-006-01-01 Place a Rx Protection Channel in the Tripped Condition Expected Response/Behavior CUES :

PT-479 Fails Low ADFAC Trouble Alarm Response :

BOP/SRO SRO SRO Note: The operator may begin to shutdown the plant Verify MFW Reg and Bypass Valves Operating Normally (AR-G-22)

Recognize PT-479 Failed Low Review Precautions Enter ER-INST. 1 (AR-G-22)

Dispatch A0 to Investigate Steam Noise

CONSTELLATION ENERGY NO.:

06-1-2 REV: 0 BOP/SRO Refer to Attachment for PT-479 R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO BOP TITLE: SCENARIO #2 DATE: 03/29/06 PAGE: 17 of 24 BOP SRO Defeat Switches or PT-479 Defeat e LoLo Press S I e Lo Press 479 LoOD B-2 475 LoOD B-2 H i g h Trip H i H i Trip Perform Computer Defeat Check Tech Specs 3.3.2-1 func le 3.3.2-1 func 4d and 4e 3.3.3-1 func 24 and 25

CONSTELLATION ENERGY NO.:

06-1-2

6. EVALUATION REV: 0 Event :

6/7 Event

Title:

SGTR "Brf S/G (Ruptured Faulted S/G)

EVENT TASKS: 035-010-05-01 Respond to a SGTR with a Faulted S/G 035-010-05-02 Direct Response to a SGTR with a Faulted S/G R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO b

Expected Response/Behavior CUES :

Przr Level decreasing R-32 Alarm R-15 Alarm TITLE: SCENARIO #2 DATE: 03/29/06 PAGE: 18 of 24 Response :

RATING EL!%

NOTE: The SGTR is fairly small, operators may perform some Action in AP-RCS.1, RCS Leak prior to Tripping an SI occurring.

SRO/RO RO/BOP RO RO Trip/verify R x Trip 0 Manual Trip Required due to failure of Auto Trip Verify Immediate Actions R x trip Turbine trip 0 Buses energized 0 SI activated Verify SI, RHR and CNMT Recirc Fans Running Verify CNMT Spray not Required

CONSTELLATION ENERGY NO.:

06-1-2 REV: 0 Response :

R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO RATING TITLE:

SCENARIO # 2 DATE: 03/29/06 PAGE: 19 of 2 4 BOP BOP BOP SRO/BOP Check if MSIV should be closed Verify MFW Isolation Verify MDAFW Pumps and TDAFW Pump running determine none is running Start "A" MDAFW Pump and establish flow to the "A" S/G SAT UNSAT Establish 200 gpm AFW flow to the S/G's before transition Out of E-0 occurs.

RO Verify CI and CVI RO RO Check CCW Status Verify SI/RHR Flow (only SI flow)

BOP Verify AFW Alignment

CONSTELLATION ENERGY NO.:

06-1-2

Response

REV: 0 Ratinq NA R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO u

BOP TITLE:

SCENARIO #2 DATE: 03/29/06 PAGE: 20 of 24 RO RO BOP RO

=.J RO/SRO BOP BOP Monitor Heat Sink Check S/G level <50%

Check if TDAFW pump can be stopped Check SI and RHR alignment Check Tavg trending to 547OF (Action will need to be taken to control AFW and close the MSIV to control Tavg)

Check PORVs and Sprays Determine if RCP Trip Criteria is met Verify CREATS Isolation Check S/G Secondary intact BOP/SRO Check S/G Tube intact Determine SGTR occurred Transition to E-3 SRO/RO Check RCP Trip criteria BOP/SRO Identify "B" S/G as ruptured

CONSTELLATION ENERGY NO.:

06-1-2 BOP/SRO Isolate Ruptured S/G 0 ARV 1050 psi in Auto 0 TDAFW Stm Valve closed 0 Blowdown Valve closed 0 MSIV closed 0 Attachment 16.0 (A0 Dispatched)

REV: 0 BOP/SRO Check Rupture S/G Level Isolate AFW to Rupture S/G 0 MOV 4008 closed 0 B MDAFW Pump Pull Stop 0 AOV 4298 closed (TDAFW to "B" S/G) 0 MOV 4000A, B closed R. E. GlNNA NUCLEAR POWER PLANT EXAMINATION SCENARIO u

CT #3 E-3--A SAT UNSAT Isolate feed flow into and steam flow from the ruptured S/G before a transition to ECA-3.1 occurs.

TITLE: SCENARIO #2 DATE: 03/29/06 PAGE: 21 of 24 BOP/SRO Establish Temperature Control on the "A" ARV (or Condenser Steam dump if the "A" MSIV is still open.

RO/SRO Reset SI

CONSTELLATION ENERGY NO.:

06-1-2 REV: 0 R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO i J BOP/SRO Initiate RCS Cooldown 0 Determine Cooldown Temperature 0 Check Rupture MSIV closed 0 Dump Steam via A ARV (or condenser steam 0 stop Cooldown and Control 0 Tavg when less than required temp.

dump if avalible)

TITLE:

SCENARIO # 2 DATE: 03/29/06 PAGE: 2 2 of 24 I

CT #4 E-3--B SAT UNSAT Establish/maintain a RCP Temp. So that transition from E-3 does not occur because RCS Temp. Is either of the following conditions:

0 Too high to obtain 20°F subcooling (E-3 step 20) 0 Below the Red or Orange Path Criteria of the Integrity CSFST BOP

~~

~

Monitor Intact S/G levels RO Check PORV and Block Valves open RO/SRO Reset CI BOP Verify all Buses supplied by off-site power BOP SRO/RO L/

Verify adequate SW flow Establish IA to CNMT 0 13/15 Normal Feed closed 0 2 SW pumps running 0 Turbine Building SW isolation valves open 0 Verify adequate air compressor

CONSTELLATION ENERGY NO.:

06-1-2 REV: 0

- 'C" Instrument

- Service Air

- Both A and B Instruments 0 Reset XY Relay for AOV-5392 0 Verify AOV-5392 open Or Or R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO

.w' RO TITLE:

SCENARIO # 2 DATE: 03/29/06 PAGE: 23 of 24 RO BOP/SRO BOP/SRO "4

RO /BOP /

SRO RO/SRO RO BOP/SRO RO SRO /RO /

BOP L-,

Stop RHR pumps Establish Charging Flow 0 Align Charging to RWST 0 Start charging and align to get 75 gpm charging flow Check if Cooldown should be stopped (should already be stopped)

Check Rupture S / G pressure stable or increasing (Note: Pressure will be decreasing when it decreases to c 250 psig above the intact -

transition to ECA-3.1)

Verify ECA-3.1 Action (already completed in 0 Reset SI/CI (step 1,2) 0 Sw adequate (step 3) 0 IA restored to CNMT (step 4 )

0 AC Buses (step 5 )

E-3)

Deenergize Przr Heater Check CNMT Spray stopped Check Ruptured S/G level Check RHR pumps stopped Evaluate plant status Aux. Building Rad.

Samples 0 Shroud and Reactor Compartment Coolers CONSTELLATION ENERGY NO.:

06-1-2 REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE:

SCENARIO #2 EXAMINATION SCENARIO DATE: 03/29/06 PAGE: 24 of 2 4 RO Verify 75 gpm charging established L

BOP/SRO Check Secondary Sides of S/G intact (B decreasing but already isolated)

CT #5 ECA-3.1 SAT UNSAT (Initiate) Cooldown the RCS to CSD BOP Con t r o 1 A (Intact) S/G levels BOP/SRO Initiate Cooldown to Cold Shutdown Dump steam from the Art ARV Terminate the scenario when a satisfactory cooldown rate is established.

CONSTELLATION ENERGY R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO

• c Written by: Ken Masker Date: 3/30/06 Sr. License Instructor NO.: 06-1-3 REV: 0 TITLE: Scenario #3 DATE: 411 9/06 PAGE: 1 of 25 Technical Review:

Dennis Jones Date: 5/18/06 Sr. License Instructor Time validated 86 minutes By:

ROY Gillow Date: 5/18/06 Shift Manager Date of exam:

Examinees Evaluators

'd Final review Date :

License Instructor Approved for use Date :

Director Operations Training or Designee ATTRIBUTE Total Malfunctions Malf after EOP entry Abnormal Events Major Transients EOP's beyond SCRAM ECA's, FR's Critical Tasks T.S. Exercised Yes/No P

7 1

5 1

1 1

3 Yes

CONSTELLATION ENERGY NO.: 06-1-3

-i.i' REV: 0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO b-The plant is at 100% power MOL conditions RCS C, - 845 ppm, BAST C, -

11,000 ppm. Xenon is at equilibrium. The \\'A SI Pump is out of service for motor work. "Bff Charging Pump is out of service for belt replacement, '\\BN SW Pump is out of service for motor work.

A Loop '\\Bn Thot fails high. The Tavg-average Tavg rod stops fail to function. The operators should manually control rods and defeat the channel per ER-INST.l.

A 20 gpm CCW leak develops in the Seal Water Heat Exchanger. The operators respond using AP-CCW.2, Loss of CCW during Power Operation, to control CCW Surge Tank level and bypass the Seal Water Heat Exchanger.

Both Generator Bus Duct Cooling Fans trip. This requires a load decrease to approximately 70% power in 10 minutes (AR-J-4) using procedure AP-TURB.5.

During the load decrease a rod lift coil for a D Bank rod fails (blown fuse) causing a misaligned rod. The operator will respond per AP-RCC.l, RCC/RPI Manlfunction. (Tech Spec 3.1.4)

The "D" Service Water Pump trips. The operators should respond by attempting to start the \\ICfJ SW Pump per AP-SW.2, Loss of Service Water.

(Tech Spec 3.7.8. One SW Train inoperable)

The "C" Service Water Pump trips immediately when started resulting in only one SW Pump in service. The operators should respond by placing DG

\\'B" in Pull Stop and isolate non-essential loads.

An inadvertent SI occurs. When MOV 852B opens (RHR to Rx Vessel) CV-853B fails causing an inter-system LOCA (to RHR). The RHR common header fails from over pressure resulting in a LOCA outside Containment. The operators should respond per E-0, ECA-1.2 and E-1.

The "B" SI Pump fails to Auto start on the SI resulting in inadequate SI for the LOCA. The operator should resond per E-0 and manully start the "B" SI Pump.

TITLE: Scenario #3 DATE: 04/19/06 PAGE: 2 of 25

R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO v

NO.: 06-1-3 I REV: 0 TITLE: Scenario #3 DATE: 0411 9/06 PAGE: 3 of 25

2. SCENARIO OBJECTIVES 2.1 Respond to a Thot RTD failure by controlling rods in manual and defeating the effected channel.

2.2 2. 3 Perform a rapid load reduction per AP-TURB.5 in response to a loss of Bus Respond to a CCW Seal Water Heat Exchanger leak per AP-CCW.2 Duct Cooling.

Respond to a misaligned RCC during the power reduction using AP-RCC.2 (Apply Tech Spec 3.1.4) 2.4 2. 5 Respond to a SW Pump trip per AP-SW.2 (Apply Tech Spec 3.7.8) 2.6 Respond to an inadvertant SI causing a LOCA outside Containment using E-O, ECA-1.2 and E-l.

CONSTELLATION ENERGY NO.: 06-1-3 3. CRITICAL TASKS (Cts)

CT #1 REV: 0 E-0--1 Task: Establish flow from at least two SI Pumps before transition out of E-0 Cues: Indications that SI is required SI Actuation 0

RCS Pressure less than SI shutoff head

& b AND Indication that less than 2 SI Pumps are injecting into the RCS Control Switch Position indicate that breakers for 2 SIPS are NOT closed R. E. GINNA NUCLEAR POWER PLANT TITLE: Scenario #3 PAGE: 4 of 25 EXAMINATION SCENARIO DATE: 04/19/06 Indicator: Manipulation of control required to establish flow from at least 2 SIPS Feedback: Indication at least 2 SI Pumps are injecting 0 SI Pump Flowrate

'd CT #2 E-l--C Task: Trip all RCPs within 5 minutes of reaching Trip Criteria Cues: Indications of a Small Break LOCA AND Indications of SI AND Indications of only one train of SI available AND RCP Trip Criteria met Indicator: Manipulation of controls required to trip both RCPs Feedback: Both RCPs stopped RCP Breaker postion lights 0 RCS Flow decreasing

3. CRITICAL TASKS (Cts)

CT #3 ECA-1.2--A CONSTELLATION ENERGY NO.: 06-1-3 REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE: Scenario #3 EXAMINATION SCENARIO DATE: 0411 9/06 PAGE: 5 o f 25 Task: Isolate the LOCA outside Containment before transitioning out of ECA-1.2 Cues:

Indication SI is actuated and required AND Indication of abnormally high radiation levels in the Auxiliary Building Indicator: Manipulation of control to close the isolation valve upstream of the break (MOV 852B)

Feedback: Indication of increasing RCS pressure

CONSTELLATION ENERGY NO.: 06-1-3 REV: 0 4

R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO INSTRUCTOR ACTIONS TITLE: Scenario #3 DATE: 04/19/06 PAGE: 6 o f 25 Problem Time Actions 4.1 Initialize the Simulator to IC-19 (setup saved as IC-173) 2 min 15 min Pull stop and place Hold Tags on the following components:

0 A SI Pump 0

B Charging Pump (A & C running) 0 B SW Pump (A & D running) 0 Set Lake Temp at 45OF Insert Malfunctions EVN MIS06 45, 300 sec ramp

- MALF ROD12 Option 1

- MALF CLGlC

- MALF RPS7B

- MALF RCS-11E, 980°F,300 sec ramp

- MALF CLGOG, 20 gpm, 0 ramp Trigger1 Trigger 2

- ANN OVR EDSll Trigger 3

- MALF ROD3-C7,0 Trigger 30 SET Trigger 30 T:N41B.LE.85

- MALF CLGlD Trigger 4

- MALF SIS1,l Trigger 5

- MALF RCS19D, 900 g p m Trigger 5 4.2 B Loop Thot Failure Trigger 1 4.3 Seal Water HX Leal Trigger 2 Submit A52.4 for all components Rod Stop Failure SW Pump C trip B SIP Auto Start Failure Loop B Thot Fail High Seal Water HX Leak Isophase Bus duct Cooler Alarm Rod C-7 sticks at 85%

power SW Pump D trip Inadvertant SI "B" Train LOCA to RHR System When called to check Seal Water HX flow report flow has decreased by 20 gpm from previous value

CONSTELLATION ENERGY NO.: 06-1-3 48 min REV: 0 R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO 35 min 4.4 Bus Duct Cooler Failures Trigger 3 TITLE: Scenario #3 DATE: 0411 9/06 PAGE: 7 o f 25 56 min 4.5

'IDrf SW Pump Trip Trigger 4 4.6 LOCA Outside CNMT Trigger 5 When requested report

\\\\A Fan Belt broken and \\\\Bfr Fan tripped.

During power decrease D Bank Rod will stick When requested report no visible damage or alarms at the rod drive cabinets Verify trigger 30 actuates at 85%

If called to observe start of 'C" SW Pump report no abnormal indication locally except breaker tripped immediately on closure When requested to check "D" SW Pump after trip report smell of burnt insulation.

Note Aux Building Radiation levels will be high SI Pump Discharge Breakers MOV-878B - LOA EDS037 MOV-878D - LOA EDS038 Terminate Scenario per direction of the Lead Examiner.

CONSTELLATION ENERGY NO.: 06-1-3

5. TURNOVER INFORMATION REV: 0 5.1 The plant is at 100% power. Xenon is at equilibrium. RCS Boron Concentration is 845 ppm. BAST Boron Concentration is 11,000 ppm. The A and C Service Water pumps are selected for Auto start.

R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO L.J

5.2 TITLE

Scenario #3 DATE: 0411 9/06 PAGE: 8 of 25 Equipment Out of Service

'At1 SI pump is 00s for motor work.

\\\\BN SW pump is out for motor replacement.

Generator Hydrogen Control is in Manual

\\\\BN Charging Pump 5.3 Work in Prosress "A" SI pump

\\'B1' SW Pump Motoi: Replacement "B" Charging Pump belt Replacement (See A52.4 I s )

5.4 Planned Work Nothing additional.

5.5 Siqnificant Events

\\'A

SI Pump had high vibration during testing that was traced to the inboard motor bearing "B" SW Pump Motor was removed from service due to overheating of the winding.

\\\\B" Charging pump belt failed.

5.6 Remarks Continue 100% operation.

CONSTELLATION ENERGY NO.: 06-1-3

6. EVALUATION Event :

1 Event

Title:

Loop '\\Bn Thot fails Hish REV: 0 EVENT TASKS: 001-023-01-01 Operate Control Rods in manual at Dower 012-006-01-01 Place a Reactor Protection Channel in a tripped condition R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO b

Expected Response/Behavior CUES :

TITLE: Scenario #3 DATE: 04/19/06 PAGE: 9 of 25 Rods Stepping IN Temp. Channels T403/407 failing HIGH Tavg - Tavg Alarm Response :

RATING

%!A NOTE: May enter AP-RCC.l to place rods in manual. This scenario is written for entering into AP-RCC.l I

ii BOP/ SRO Check Rod operability 0

Turbine Load Stable Place Rods in Manual 0

Verify Rod Motion Stops RO/SRO Restore Tavg to Tref RO/SRO Check Tavg Channels 0

Determine T403 Failed 0

Refer to ER-INST.l RO/BOP/SRO Defeat T403/407 per ER-INST.l RO Operate Rods in Manual BOP Check Steam Dump not operating RO RO i.'

Place Charging in Manual/Manually control PRZR Level Check RIL Alarms

CONSTELLATION ENERGY NO.: 06-1-3

6. EVALUATION (continued)

Response :

REV: 0 SRO R. E. GINNA NUCLEAR POWER PLANT i L EXAMINATION SCENARIO BOP TITLE: Scenario #3 DATE: 04/19/06 PAGE: 10 of 25 BOP BOP BOP

• W*

BOP BOP BOP Determine Hot Leg Streaming not occurring Defeat the Channel per Attachment Tavg 403 / Delta T 407 Verify Rods in Manual/ Charging in Manual RIL Rack-Place T/405F to Loop B Unit 1 RATING Steam Dump Rack-Place T/401B to Loop B Unit 1 B-1 Protection Rack-Place the following switches to TRIP 403 Loop B-1 0 High Tavg Low Tavg 407 Loop B-1 0 Over Temp Trip 0 Over Power Trip Verify Bistable Lights Delete 403/407 group from PPCS Scanning

CONSTELLATION ENERGY NO.: 06-1-3 RO/SRO Restore Control System to Auto PRZR Level Control e

Rod Control REV: 0 SRO R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO

\\

Check Tech Specs e

3.3.1 Table 3.3.1-1 5,6 0

3.3.2 Table 3.3.2-1 4.d TITLE: Scenario #3 DATE: 04/19/06 PAGE: 1 1 of 25 RO/BOP/SRO Verify Control Systems in Auto Rods EHC 0

PRZR Press.

e PRZR Level e

Steam Dump MFW ARV'S SRO Notify Supervision/Maintenance

CONSTELLATION ENERGY NO.: 06-1-3

6. EVALUATION Event :

2 Event

Title:

Seal Water Heat Exchanqer Leak EVENT TASKS: 008-011-04-01 Identify a CCW Leak 008-011-04-02 Direct identification of a CCW Leak REV: 0 Expected Response/Behavior R. E. GINNA NUCLEAR POWER PLANT

'L, EXAMINATION SCENARIO CUES :

TITLE: Scenario #3 DATE: 0411 9/06 PAGE: 12 of 25 CCW Surge Tank Level decrease VCT Level Increase RCS Tavg Increasing CCW Tank Low Level Alarm (AR-A-13)

Response :

RATING fiJLA NOTE: The CCW Leak will cause a dilution of the RCS. The operator should investigate the cause of the Tavg change RO/SRO Recognize A-13 Alarm enter AR procedure RO/SRO RO RO/SRO RO RO Determine that CCW Surge Tank Level is decreasing. Enter AP-CCW.2 Check CCW Pump status Makeup to the CCW Surge Tank Open MOV 823 e

Start RMW Pump(s) e Verify Tank level is increasing Monitor CCW Temperature Check RCP indications

CONSTELLATION ENERGY NO.: 06-1-3 RO REV: 0 RO/SRO R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO i,

SRO TITLE: Scenario #3 DATE: 04/19/06 PAGE: 13 of 25 SRO SRO RO RO SRO RO

./

Check Letdown Check CCW Valve alignment.0 (MCB).1 (NLO)

Dispatch NLO to check Seal Water HX (NLO reports flow is 20 gpm lower than normal 1 Direct NLO to bypass and isolate the Seal Water Hx Notify RP to sample the RCS for Chromates Terminate Makeup to CCW Surge Tank when level

-50%

Check for leakage in CNMT and Auxiliary Building (Step 8, 9)

Verify leak identified and isolated Verify Normal LTDN in service

-u

6. EVALUATION Event :

3 /4 Event

Title:

Isophase Bus Duct Coolinq Failure / Stuck Rod EVENT TASKS: 001-019-04-01 Restore Misaliqned Control Rod 004-013-01-01 Perform a Boration of the RCS 045-027-04-01 Respond to a Rapid Load Reduction 045-027-04-02 Direct Response to a Rapid Load Reduction CONSTELLATION ENERGY R. E. GINNA NUCLEAR POWER PLANT TITLE: Scenario #3 EXAMINATION SCENARIO DATE: 04/19/06 PAGE: 14 of 25 Expected ResDonse/Behavior CUES :

Alarm AR-J-4 Response :

BOP Check SW System

-1 SRO Dispatch an A0 to investigate Note: A0 will report no fans running SRO Direct Load Reduction to -70% power. Enter AP-TURB. 5 RO/BOP/SRO Initiate Load Reduction Verify Rods in Auto (RO) 0 EHC Rate Selected and Load Reduction initiated. (BOP)

SRO NOTE: This step is applicable only if the normal boration method is not available Determine Boration Technique 0

Dispatch A0 to open V-356 OR Borate from the RWST (Open 112B, Close 112C)

CONSTELLATION ENERGY NO.: 06-1-3

6. EVALUATION (continued)

REV: 0 Response :

R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO i,

RO BOP RO BOP RO BOP TITLE: Scenario #3 DATE: 04/19/06 PAGE: 15 of 25 Monitor Tavg 545OF - 566OF Verify IA available to CNMT Monitor PRZR Pressure Monitor S/G Level Control Monitor PRZR Level Control Monitor Steam Dump NOTE: At 85% power the Stuck Rod Malfunction will Auto Actuate

'v' RO SRO SRO/RO RO RO BOP BOP RO/BOP/SRO Determine Rod C-7 misaligned Enter AP-RCC.2 Place Rods in Manual (will need to finish Load Reduction on Boric Acid or RWST to control reactivity)

Check for Dropped Rod Check Tavg - Place EHC in Manual Check Steam Dump Check Generator Load > 15 MW Stabilize Plant conditions 0

Tavg 0

PRZR Press.

0 PRZR Level MFW RATING

CONSTELLATION ENERGY R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO U

6. EVALUATION (continued)

Response :

RO/SRO NO.: 06-1-3

[ REV: 0 TITLE: Scenario #3 DATE: 04/19/06 PAGE: 16 of 25 Check Rod Alignment SRO RO/SRO RO

-4 RO/SRO Refer to Tech spec 3.1.4 Check QPTR within limits Verify MRPI system operable Check Rod Operability RATING Ui

u.

6. EVALUATION Event :

5 Event

Title:

SW Pump Trip EVENT TASKS: 076-004-04-01 Respond to Partial Loss of SW 076-004-04-02 Direct ResDonse to Partial Loss of SW CONSTELLATION ENERGY NO.: 06-1-3 I REV: 0 R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO TITLE: Scenario #3 DATE: 0411 9/06 PAGE: 17 of 25 Expected Response/Behavior CUES :

"D" SW Pump Trips PPCS SW Header Low Pressure Alarms Response :

RO/SRO BOP BOP/SRO Recognize SW Pump Trip Enter AP-SW.2, Loss of Service Water Verify AC Emergency Busses 17 and 18 energized Verify one SW Pump running in each loop (Only one pump running)

NOTE: SW Pump C will trip upon stating BOP~SRO Start SW Pump "C" When Pump Trips go to AP-SW.2 Step 3 SRO BOP

".-..".--Z SRO Dispatch A0 to align alternate cooling to "B" DG RATING u

Isolate SW to Non-Essential Loads Screen House Air Conditioning Direct A0 to perform Attachment 2.2

CONSTELLATION ENERGY R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO W

6. EVALUATION (continued)

NO.: 06-1-3 REV: 0 TITLE: Scenario #3 DATE: 04/19/06 PAGE: 18 of 25 Response :

BOP BOP SRO SRO ii BOP Start the Service Air Compressor Stop the C Inst Air Compressor Dispatch AOs to monitor SW cooled equipment Notify Supervision Check SW System RATING m

i

.u

'Ll

6. EVALUATION Event :

6/7 Event

Title:

LOCA Outside Containment EVENT TASKS:

002-025-05-01 Respond to a LOCA Outside Containment 002-025-05-02 Direct ResDonse to a LOCA Outside Containment CONSTELLATION ENERGY NO.: 06-1-3 REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE: Scenario #3 EXAMINATION SCENARIO DATE: 04/19/06 PAGE: 19 of 25 Expected Response/Behavior CUES :

SI Actuated RX Trip PRZR Level/Press Decreasing Auxiliary Building Radiation Alarms Response :

-u SRO RO/BOP RO/SRO RO Recognize R x Trip/ SI Enter E-0 RATING rn E-0 Immediate Actions Verify Rx Trip Verify Turbine Trip Verify Busses Energized Check SI Actuated (Manually Actuate SI)

Recognize '\\BN SI Pump fail to auto start Manually Start \\\\Bf' SI Pump CT #1 E-0--1 UNSAT Establish flow from at least 2 SI pumps before transition out of E-0 I

I RO Verify CNMT Recirc Fans Running

CONSTELLATION ENERGY NO.: 06-1-3 REV: 0 R. E. GINNA NUCLEAR POWER PLANT EXAM INATlO N SCEN ARI 0

6. EVALUATION (continued)

TITLE: Scenario #3 DATE: 04/19/06 PAGE: 20 of 25 Response :

RO BOP BOP BOP BOP RO RO I

11' RO BOP BOP RO RO Verify CNMT Spray not required Check if MSIVs should be closed Verify MFW Isolation Verify MDAFW Pumps running Verify SW Pumps running Verify CI and CVI Check CCW Status Verify SI/RHR Flow (Only SI Flow)

Verify AFW Alignment Monitor Heat Sink Check S / G Level ~ 5 0 %

Secure AFW to S / G with >50% level Control SG levels between 17-50%

Check SI and RHR Alignment Check CCW to Thermal Barriers

CONSTELLATION ENERGY NO.: 06-1-3 Response :

REV: 0 BOP R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO v

BOP TITLE: Scenario #3 DATE: 04/19/06 PAGE: 21 of 25 RO Check if TDAFW Pump can be stopped 0

Stop the TDAFW Pump Check Tavg trending to 547OF Check PORVs and Spray Valves

.w-RO/SRO Determine RCP Trip Criteria is met Trip RCPs when met RATING E!.A CT #2 E-l--C UNSAT Trip RCPs within 5 minutes of reaching Trip Criteria BOP BOP BOP/SRO Verify CREAT Isolation Check S/G Secondary intact Check S/G Tubes intact

b RO/SRO Check RCS intact (No LOCA inside CTMT)

CONSTELLATION ENERGY NO.: 06-1-3 REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE: Scenario #3 EXAMINATION SCENARIO DATE: 04/19/06 PAGE: 22 of 25 RO/BOP/SRO Check SI Termination Criteria SRO BOP RO

.L/=

BOP/SRO BOP/SRO Notify STA to monitor CSFST Control S/G Levels Reset SI/CI Check SW Flow 0

Dispatch A0 to perform SD-1 Establish IA to CNMT BOP / SRO Check S/G Rad Levels

L/

6. EVALUATION (continued)

Response :

CONSTELLATION ENERGY NO.: 06-1-3 REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE: Scenario #3 EXAMINATION SCENARIO DATE: 0411 9/06 PAGE: 23 of 25 RO/SRO Check Aux Building Rad Levels Determine Rad levels are abnormal and Transistion to ECA-1.2 NOTE: The operators, based on abnormal RHR System indications may perform an anticipatory action per A-503.1 and go to the steps for isolating RHR (Step 3 )

RO RO Verify normal RHR Alignment 700/701 Closed 720/721 Closed Verify CVCS Alignment e

310/296/392A Closed e

313/371 Closed

L SRO/RO CONSTELLATION ENERGY NO.: 06-1-3 REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE: Scenario #3 EXAMINATION SCENARIO DATE: 04/19/06 PAGE: 24 of 25 Check for backflow into ECCS System SI Reset e

Close 852A e

Check for RCS pressure increase (none) e Open 852A e

Close 852B e

Verify RCS Pressure increasing I

CT #3 ECA-1.2--A Isolate the LOCA Outside Containmant before transistioning out of ECA-1.2 SAT UNSAT RO/SRO Check if Leak is isolated u

GO to E-1 NOTE: At some point SI Termination Criteria will be met. When it is, the operator should trainsition to ES-1.1, SI Termination.

NOTE: Action Step 1-9 have already been completed in E-0. Step 10 begins new actions.

CONSTELLATION ENERGY R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO L

BOP/SRO RO NO.: 06-1-3 REV: 0 TITLE: Scenario #3 DATE: 0411 9/06 PAGE: 2 5 0 f 25 RO/BOP/SRO Verify action already completed (Steps 1-9) 0 RCP Trip Criteria S/Gs intact Control S/G levels 0

Monitor Secondary Rad levels 0

PORVs 0

Reset SI/CI SW Flow 0

IA to CNMT restored Verify Normal Power to Busses 14/16 Establish Charging Flow 0

Check RCP Seal Cooling 0

Align Charging Suction to RWST Start Charging to restore PRZR level RO/BOP/SRO Check SI Termination Criteria Transition to ES-1.1