ML041190228
| ML041190228 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/02/2004 |
| From: | Maciuska F Rochester Gas & Electric Corp |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 50-244/04-301 | |
| Download: ML041190228 (67) | |
Text
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-1 R. E. GINNA NUCLEAR POWER PLANT TITLE: Ejected RCCA
--I EXAMINATION SCENARIO DATE: 1 I1 8/04 PAGE: 1 of 22 Written by: Kenneth Masker Date : 1/18/04 License Instructor Technical Review: Dous Peterson Date : 1/26/04 License Instructor Time validated 80 minutes By: K. Masker Date : 2/2/04 License Instructor Date of exam:
Examinees Evaluators b
Final. review License Instructor Date: 3,hT/oy*
Approved for use Q&M& Ah.& Date: /2qbY SutServisor License Training or Designee CLERICAL\17210
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC lflitial Exam REV: 0 Scenario 04-1 R. E. GINNA NUCLEAR POWER PLANT TITLE: Ejected RCCA
_- EXAMINATION SCENARIO DATE: 1t i 8/04 PAGE: 2 of 22
- 1. SCENARIO OVERVIEW 1.1 The plant is initially at 2-3% power during a startup following a mid cycle maintenance shutdown. Procedure 0-1.2 is complete up to starting the first MFW pump and placing MFW in service. The TDAFW Governor has failed but this has not yet been detected.
1.2 The operators will place M F W system in service and secure AFW as per procedure 0-1.2.
1.3 Przr Level Transmitter LT-427 fails low causing letdown isolation. The operators will defeat the channel per ER-INST.l and restore Letdown Operation per S-3.2~.
1.4 The "A" S/G ARV controller fails causing the valve to open fully. The operators should take manual control of the ARV and close the valve.
1.5 A leak develops on a CRDM housing ramping up to 2 5 gpm. Shortly after the leak develops, the MRPI coil stack on the associate CRDM fails (shorts) due to the coolant leak. The operator should enter AP-RCS.1.
After performing action to stabilize the RCS inventory, the operator
'L should determine that a plant shutdown is required and transition to 0-2.1 or AP-TURB.5.
1.6 The leaking CRDM housing fails causing an 8 0 0 gpm LOCA and an ejected RCC. SI will auto actuate (possibly manual actuation). "A" SI Train Sequencer fails to actuate and liBii SI pump fails to auto start resulting in inadequate SI pump running. Both MDAFW pumps fail to auto start resulting in no AFW available. The operators should trip the Rx per AP-RCS.l. step 1 and enter E-0. They should start the failed ECCS equipment and verify other action per E-0. They should then transition to E-1 and then ES-1.2. The scenario is terminated when a cooldown is started as per ES-1.2.
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-1 R. E. GINNA NUCLEAR POWER PLANT TITLE: Ejected RCCA
-.- EXAMINAT1ON SCENARIO DATE: 1/18/04 PAGE: 3 o f 22
- 2. SCENARIO OBJECTIVES 2.1 RO(s) - Demonstrate the ability to monitor and operate the MCB, diagnose events and implement step of Normal, Abnormal and Emergency Procedures, interact with other members of the crew in a manner which facilitates the crews response to events which occur. Respond to the following events:
- 1) Normal Operations
- Start MFW pump and transition to MFW
- 2) Instrument Component Malfunctions
- Przr Level LT-427 fails low/letdown isolation
- S / G ARV controller fails causing the ARV to fail open
- RCS leak requiring shutdown
- 3) Emergency Events
- Ejected Rod/SB LOCA
- ECCS equipment failures L-'
SRO - Demonstrate the ability to supervise the Control Board operators, diagnose event and choose and implement response procedures, interact with other members of the crew in a manner which facilitate the crews response to events which occur, determine Tech Spec required actions.
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-1 R. E. GINNA NUCLEAR POWER PLANT TITLE: Ejected RCCA EXAMINATION SCENARIO DATE: 1/18/04 PAGE: 4 of 22
- 3. CRITICAL TASKS (CTs)
CT #1 E-0-1 Task: Establish flow from at least two SI pumps before transition out of E-0.
Cues: SI actuated 0 RCS pressure less than SI pump shutoff head Less than two SI pumps indicating running Indication: Manipulation of controls to establish flow from at least two SI pumps Feedback: Indications that two SI pumps are running CT #2 E-I-C Task: Trip all RCP within five minutes of reaching the Trip Criteria Cues: Indications that RCP Trip Criteria are met Indication: Manipulation of controls as required to trip both RCPs Feedback: Indications all RCPs are tripped
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2 0 0 4 NRC Initial Exam REV: 0 Scenario 04-1 R. E. GINNA NUCLEAR POWER PLANT TITLE: Ejected RCCA EXAMINATION SCENARIO DATE: 1I1 8/04 PAGE: 5 of 22
- 4. INSTRUCTOR ACTIONS Problem Time Actions Notes 4.1Set up the simulator per OTG-3.2 For 2004 License Exam saved as IC-171 4.1.1 Reset simulator to IC-21 MOL Amp Xe-Free 4.1.2 Increase power to 2-3% and complete 0-1.2 up to step 5.4.3.18 and attachment MFW Pump A up to step 9.0 4.1.3 Insert MAEF FDW12 ORPM 4.2 Initial Conditions 4.2.1 LT-427 Fails Low MALF PZR03B, 0%, 0 ramp Trigger 1 4.2.2 S/G A ARV Fails Open MALF STMO4A loo%, 10 sec ramp Trigger 2 4.2.3 CRDM Leak/Coil Stack Failure MALF RCSOZA, 25 g p m , 300 sec ramp Trigger 3 MALF ROD13C-Gl1, 300 sec TD Trigger 3 4.2.4 Ejected Rod/SI and AFW Pump Fail to Start MALF SIS02A, 1 no manual Trigger 4 MALF RPS07B Trigger 4 MALF RPS07K Trigger 4 MALF RPS07L Trigger 4 MALF ROD05-Gll 800 gpm, 0 sec ramp, 10 sec TD Trigger 4 10 min 4.3 LT-427 Failure Trigger 1 L-
I ROCHESTER GAS 81 ELECTRIC CORPORATION I NO.: 2004 NRC triitial Exam I REV: 0 Scenario 04-1 I
- R. E. GlNNA NUCLEAR POWER PLANT EXAMINATION SCENARIO TITLE: Ejected RCCA DATE: 1/I 8/04 PAGE: 6 o f 22 20 min 4.4 S/G ARV Fails Open Trigger 2 If called to, manual isolate valve LOCA STM02, O I , 120 sec Ramp, 120 sec TD 25 min 4.5 RCS Leak/MRPI Coil Stack Failure Trigger 3 When called to investigate AB System No leak found 30 min 4.6 Ejected Rod/Safeguard Equipment fails to Auto Start Trigger 4 4.7 Termination Criteria Terminate scenario when a cooldown is established in ES-1.2, unless directed otherwise by the Lead Examiner.
v
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-1 R. E. GINNA NUCLEAR POWER PLANT TITLE: Ejected RCCA u EXAM I NATl ON SCENARIO DATE: 111 8/04 PAGE: 7 of 22
- 5. TURNOVER INFORMATION 5.1 The plant is at -2% power during a startup following a week long maintenance shutdown. C, - 1336 ppm Xenon Free. 0-1.2 Complete up to step 5.4.3.18 and MFW A Attachment up to step 9.0.
5.2 EauiDment Out of Service None 5.3 work in Prowess Startup of A MFW Pump transfer to MFW securing AFW 5.4 Planned Work Turbine Roll up and Synchronization 5.5 Sisnificant Events None 5.6 Remarks Continue actions in 0-1.2 to place plant on line.
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-1 R. E. GINNA NUCLEAR POWER PLANT TITLE: Ejected RCCA u EXAMINATION SCENARIO DATE: 1I1 8/04 PAGE: 8 of 22
- 6. EVALUATION Event : 1 Event
Title:
Start MFW PumD ExDected ResDonse/Behavior CUES :
Response :
RATING XLA BOP/SRO Take MFW out of Pull Stop BOP/SRO Ensure Recirc Valves open AOV 4 1 4 7 AOV 4262 (Local call A01 BOP / SRO Start A MFW Pump BOP / sRO Open MFW Discharge Valve MOV 3 9 7 7 SRO Notify A0 to close 3977A (LOA FDW52)
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-1 R. E. GINNA NUCLEAR POWER PLANT TITLE: Ejected RCCA
' EXAMINATION SCENARIO DATE: 1 /18/04 PAGE: 9 of 2 2 BOP / SRO Verify MFW Regulating Valve and Bypass Valve Operation HCV-466 HCV-476 HCV-480 HCV-481 BOP/SRO Place MFRV/Bypass Valves in Automatic as desired BOP/SRO Stop Both AEW Pumps BOP/SRO Realign A F W for Normal Operations
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-1 R. E. GINNA NUCLEAR POWER PLANT TITLE: Ejected RCCA
-__ EXAMINATION SCENARIO DATE: 1118/04 PAGE: 10 of 22
- 6. EVALUATION Event : 2 Event
Title:
LT-427 P r z r Level Fails Low Expected ResDonse/Behavior CUES: Przr Low Level Alarm Letdown Isolation Przr Heaters Trip Charging Pump Speed Alarm VCT Level Decreases Response :
RATING %A!
RO/CRF Recognize LT-427 has failed Letdown is isolated/Przr Heaters tripped CRF Enter ER-INST.l RO/CRF Monitor Przr Pressure RO/CRF Place Charging to manual/minimize speed RO/CRF Stop one charging pump RO/CRF Adjust HCV-142 to Control Lab Seal AP RO/CRF Close AQV-427, 200A, B, 202
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-1 R. E. GINNA NUCLEAR POWER PLANT TITLE: Ejected RCCA
--.--, EXAMINATION SCENARIO DATE: 1I1 8/04 PAGE: 11 of 22 CRF Determine if excess L/D should be placed in service BOP/SRO Defeat Channel per Attachment RO/SRO Restore Przr Heaters RO/SRO Restore Normal Letdown per S-3.2E PCV-135 TCV-130 Manual @ 40%
Open 427/371 Open 200A or B Return Controllers to Auto RO Restore Charging to normal SRO Evaluate Tech Specs 3.3.1-1 Function 8 3.3.3-1 Function 2 Section 3.4.9
I I I 1 I ROCHESTER GAS & ELECTRIC CORPORATION I NO.: 2004 NRC Initial Exam I REV: 0 I Scenario 04-1 I R. E. GINNA NUCLEAR POWER PLANT TITLE: Ejected RCCA I
v EXAMINATION SCENARIO I DATE: 1/18/04 I PAGE: 12 of 22
- 6. EVALUATION Event : 3 Event
Title:
"A" S/G ARV Fails ODen ExDected ResDonse/Behavior CUES: Tavg - Decreasing A S/G Pressure Decreasing ARV indicates full open Response :
RATING N/A BOP / SRO Recognize ARV full open SRO Direct RO to close ARV manually BOP Take ARV to manual close BOP/RO/SRO Stabilize plant following transient
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Ihitial Exam REV: 0 Scenario 04-1 R. E. GINNA NUCLEAR POWER PLANT TITLE: Ejected RCCA
-L1 EXAMINATION SCENARIO DATE: 1 /18/04 PAGE: 13 of 22 7 EVALUATION Event : 4 Event
Title:
CRDM Leak ExDected ResDonse/Behavior CUES: CNMT Radiation Increasing RCS leakage increasing (charging pump speed increasing)
MRPI Failure Alarm on MRPI CRT Response :
RATING RO/SRO Recognize indications of increased leakage v
SRO Enter AP-RCS.l RCS Leak RO/SRO Monitor Przr Level Increase Charging Flow Isolate L/D if necessary RO/SRO Verify VCT Makeup System Alignment RO/SRO Verify RCS Leakage in CMUIT Rod Monitors A Sump SRO Send A0 to check Aux. Building c
ROCHESTER GAS & ELECTRIC CORPORATION NO,: 2004 NRC initial Exam REV: 0 Scenario 04-1 R. E. GINNA NUCLEAR POWER PLANT TITLE: Ejected RCCA
EXAMINATION SCENARIO DATE: 1/18/04 PAGE: 14 of 22 RO/SRO Check CCW for Leak RO/SRO Check W C S for Leak L/D Flow, Press Charging/Seal Injection Flow Aux. Building Radiation RO/SRO Check PRT for Leak Level Pressure BOP~SRO Check S / G for Leakage S/G Radiation RO/SRO Check Accumulator Levels RO/SRO Check RCP Seal Leakoff RO/SRO Check RCDT Leak Rate SRO Call A0 to check Valve Leakoff Temperature RO/SRO Stabilize Plant Conditions SRO/RO/BOP Check MCB Annunciators
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-1 R. E. GINNA NUCLEAR POWER PLANT TITLE: Ejected RCCA
-4 EXAMINATION SCENARIO DATE: 1 /18/04 PAGE: 1 5 of 22 SRO Determine a Tech Spec Shutdown Required
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-1 R. E. GlNNA NUCLEAR POWER PLANT TITLE: Ejected RCCA
-d EXAMINATION SCENARIO DATE: 111 a104 PAGE: 16 of 22
- 6. EVALUATION Event : 5 Event
Title:
MRPI Coil Stack Fails Emected ResDonse/Behavior CUES: MRPI CRT Alarm and Loss of Indication for Rod G-11 Response :
RATING N/A RO/SRO Recognize Condition SRO Enter AP-RCC.2 RCC/RPI Malfunction RO/CRF Check the following:
Dropped Rod Alarms C-14, C-29 Tavg Trend BOP/ CRF Check for G-15 Steam Dump Armed Generator Load 5 15 MW CRF Determine that AP-TuRB.1 should not be entered BOP/RO/SRO Stabilize Plant
~ ~~
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2 0 0 4 NRC Initial Exam REV: 0 Scenario 04-1 R. E. GlNNA NUCLEAR POWER PLANT TITLE: Ejected RCCA v EXAMINATION SCENARIO DATE: 1/18/04 PAGE: 17 of 2 2 RO/SRO Verify Control Rod Alignment and QPTR RO/SRO Determine that an MRPI has failed SRO Review Tech Spec 3.1.7
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-1 R. E. GINNA NUCLEAR POWER PLANT TITLE: Ejected RCCA
.._- . EXAMINATION SCENARIO DATE: 1/18/04 PAGE: 18 of 22
- 7. EVALUATION Event: 6,7,8 Event
Title:
Eiected Rod, SBLOCA ExDected ResDonse/Behavior CUES: RJC Power Increases Przr Press and Level Decrease rapidly CNMT Radiation Increases
Response
RATING &A!
RO/SRO Determine Leakage Exceed Charging Capacity RO Trip Rx L
RO/BOP Perform E - 0 Immediate Actions Trip Rx Turbine Stop Valve Vital Busses Energized SI RO/SRO Determine SI needed Manually Actuate CT #1 Establish flow from at least two SI pumps before SAT UNSAT I
transition out of E-0
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-1 R. E. GINNA NUCLEAR POWER PLANT TITLE: Ejected RCCA v
EXAM1NATION SC ENARIO DATE: 1118/04 PAGE: 19 of 22 RO/SRO Manually Start CNMT Recirc Fans Both AFW Pumps RO/CRF Verify CNMT Isolation SAT UNSAT CT #2 Trip all RCP with five minutes of reaching the trip criteria Two SI pumps running RCS press - Highest S/G press e 175 psid (400 adverse)
RO/CRF Verify CCW pump running RO/CRF Verify SI Flow BOP/SRO Verify AFW Valve Alignment BOP/SRO Control S/G Levels (Continuous Action)
RO/SRO Check SI/RHR Alignment
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NR6 Initial Exam REV: 0 R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO RO/SRO Check Thermal Barrier Cooling BOP / SRO Monitor Control Tavg Stop dump steam Control AFW Shut MSIVs RO/SRO Check PORVs and Block Valves SRO Determine LOCA in progress Transition to E-1 CNMT Radiation CNMT Sump Level CNMT Press BOP/SRO Check Secondary Intact (Pressure Stable)
BOP/SRO Control S/G levels (17-50%, 25-50 adverse)
BOP/SRO Check Secondary Radiation Normal RO/BOP Check PORVs RO/SRO Reset SI and CI signals
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-1 R. E. GINNA NUCLEAR POWER PLANT TITLE: Ejected RCCA L,
EXAMINATION SCENARIO DATE: 111 8/04 PAGE: 21 of 22 BOP/SRO Check SW System Direct A0 to do SD-1 BOP/SRO Restore IA to CNMT BOP/SRO Check Power Supplies for Charging RO/SRO Establish Charging Flow SRO Check SI Termination Criteria (not met)
\v RO/SRO Stop RHR pumps RO/BOP/ Check RCS and S/G Pressure (determine if LOCA SRO or steamline break)
Continue to step 16 BOP/SRO Stop Diesel Generators RO/SRO Verify CNMT Sump Recirc Capability BOP/RO/ Evaluate Status SRO
I I ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam Scenario 04-1 REV: 0 R. E. GINNA NUCLEAR POWER PLANT TITLE: Ejected RCCA I
L EXAMINATION SCENARIO I DATE: 1/18/04 I PAGE: 22 of 22 I SRO Determine Post LOCA Cooldown Required Transition to ES-1.2 (Steps 1-2 are repeat of E-o Actions)
RO/SRO Increase charging to 75 g p m BOP / SRO Setup ARV for Pressure Control and Control intact S/G levels RO/SRO Deenergize Przr Heater W
BOP/SRO Initiate 100°F/hr Cooldown to CSD If c 100°F/hr cooldown not already present from the break End Scenario
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-2 R. E. GINNA NUCLEAR POWER PLANT TITLE: Steam Generator Tube Rupture L4 EXAMINATION SCENARIO DATE: 1/I 8/04 PAGE: 1 of 23 Written by: Kenneth Masker Date : 1/18/04 License Instructor Technical Review: Doug Peterson Date : 1/26/04 License Instructor Time validated 90 minutes By: Ken Masker Date : 2/2/04 License Instructor Date of exam:
Examinees Evaluators v
~ @ - .
Final review A
License Instructor Date : TkTLf Approved for use or Designee
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-2 R. E. GINNA NUCLEAR POWER PLANT TITLE: Steam Generator Tube Rupture L
EXAMINATION SCENARIO DATE: 1I1 8/04 PAGE: 2 of 23
- 1. SCENARIO OVERVIEW 1.1 The plant is at 100% power MOL condition Xenon Equilibrium, CB 845 ppm.
The D CNMT Recirculation Fan is 00s. B and C charging pumps are running.
A charging pump is 00s.
1.2 Turbine First Stage Pressure Transmitter PT-485 fails low, this results in rod stepping in at high speed. The operators should enter AP-RCC.l Uncontrolled Rod Motion and place rods to manual. They should then defeat PT-485 per ER-INST.l.
1.3 A loss of off-site circuit results in loss of buses 16 and 17 until the diesel generator starts and restores the buses. The C Charging Pump is lost resulting in a partial loss of charging flow. The operators should respond using AP-ELEC.l.
1.4 A 10 gpm tube leak develops on the IlBll S/G. The operator should recognize this condition from the increase in Air Ejector Radiation and increased RCS Makeup. They should respond per AP-SG.1 and initiate a plant shutdown.
c 1.5 Hotwell Level Controller LT-2001 Fails high causing hotwell rejection to the CSTs. The operators should recognize the failure and manual control hot well level utilizing LT-2002.
1.6 PCV-431C (Przr PORV) fails 50% open. The operator should recognize the rapidly decreasing pressurizer level and the valve mid position and enter AP-PRZR.1 Abnormal Przr Pressure. They should isolate the valve by closing its MOV block valve.
1.7 The SG Tube Leakage increases to 500 gpm (a SG Tube Rupture). The operator should trip the Rx and go to E-0 per the guidance of AP-SG.l.
They should diagnose a SGTR and transition to E-3. When attempting to isolate the rlBrlMSIV, it fails to close requiring using the alternate isolation boundary in E-3.
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 R. E. GINNA NUCLEAR POWER PLANT
- 2. SCENARIO OBJECTIVES RO(s) - Demonstrate the ability to monitor and operate the MCB, diagnose events and implement step of Normal, Abnormal and Emergency Procedures. Interact with other members of the crew in a manner which facilitates the crews response to the events listed below.
SRO - Demonstrate the ability to supervise the Control Board operators, diagnose events and choose and implement response procedures, implement Tech Spec requirements to ensure the plant is operated within its licensed basis, interact with other members of the crew in a manner which facilitates the crews response to the events listed below.
Instrument/Component Malfunction Loss of Circuit 751 PT-485 Failure LT-2001 Failure PCV-431C Failure S / G Tube Leak Major Malfunction
--Le.
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-2 R. E. GINNA NUCLEAR POWER PLANT TITLE: Steam Generator Tube Rupture W
EXAMINATION SCENARIO DATE: 1t i 8/04 PAGE: 4 of 23 3 CRITICAL TASKS (CTs)
CT #I. E-3--A Task: Isolate feedwater flow into and steam flow from the ruptured steam generator before a transition to ECA-3.1 occurs.
Cues: Indication of SGTR
- Increasing SG water level
- Steam Generator radiation and SI actuated and Rx trip actuated Indication: Manipulation of controls to isolate the rupture SG MSIV closed Local isolation by attachment Ruptured SG initiated ARV setpoint adjusted to 1050 in Auto SG blowdown and sample valve closed (verify)
TDAFW steam supply valve from ruptured SG closed M D A F W and TDAFW discharge valve to ruptured SG closed Main feed reg and bypass valve to ruptured SG closed, main feedwater pumps tripped (verify)
Feedback: Ruptured SG pressure stable or increasing. No indication of feed flow to ruptured SG.
CT #2 E-3--B Task: Establish/maintain RCS temperature so that a transition out of E-3 does not occur because the RCS temperature is in either of the following conditions:
Too high to maintain minimum subcooling or Below the orange path PTS transition temperature (285OF)
Cues: Indication of SGTR Increasing SG water level SG radiation and F!x trip actuated and SI actuated and Ruptured SG pressure greater than 300 psig
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-2 R. E. GINNA NUCLEAR POWER PLANT TITLE: Steam Generator Tube Rupture b
EXAMINATION SCENARIO DATE: 1/18/04 PAGE: 5 o f 23
- 3. CRITICAL TASKS (CTs) (continued)
Indications: Manipulation of intact SG ARV or condenser steam dump to establish the required RCS temperature.
Feedback: Indication of steam dump/ARV position Indication of RCS temperature decreasing Indications of RCS temperature less than target value CT #3 E-3--C Task: Depressurize RCS to SI termination criteria within one hour of SGTR initiation.
Cue: Indication of SGTR Ruptured SG level Ruptured SG radiation and Rx trip and SI actuated and u RCS cooled down to less than or equal to the target temperature Indications: Manipulations of control to depressurize the RCS; PRZR spray, PORV or auxiliary spray.
Feedback: Indication of PRZR pressure decreasing Indication of PRZR level increasing CT #4 CT E-3--D Task: Terminate SI within one hour of SGTR initiation and control RCS pressure and makeup so that primary and secondary inventory are stable before the end of the scenario.
Cue: Indication of increasing SG level and high radiation RCS temperature at or below target cooldown value SI termination criteria met Indications: SI pumps are stopped Feedback: SI flow indicates zero
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-2
.- R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO TITLE: Steam Generator Tube Rupture DATE: 1/I 8/04 PAGE: 6 o f 23
- 4. INSTRUCTOR ACTIONS Problem Time Actions Notes 4.1Setup simulator per OTG-3.2 4.2 Initial Conditions (Note: Saved as IC-172) 4.2.1 Initialize the simulator to IC-19 100% MOL Xenon Eq.
4.2.2 Pull stop and hold the D CNMT A-52.4 Recirc Fan TS Out 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for breaker replacement 4.2.3 Insert Malfunctions 4.2.3.1 llB1l MSIV Fails Open MALF STM05B 100%
4.2.3.2 Turbine lstStage Press PT-485 Fails low MALF TUR 16A, 0 Trigger 1 4.2.3.3 LT 2006 Fails High MALF CND03A, 4 8 , 0 Trigger 4 4.2.3.4 Loss of 751 MALF EDSOlA Trigger 2 4.2.3.5 SG Tube Leak MALF SGNO4B 10 gpm, Trigger 3 4.2.3.6 PCV431C Przr PORV MALF PZR05B, 5 0 %
Trigger 5 3 min. 4.3 Turbine latStage Press Fail Low Trigger 1 10 min. 4.4Loss Circuit 751 Trigger 2
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-2 I R. E. GINNA NUCLEAR POWER PLANT TITLE: Steam Generator Tube Rupture EXAMINATION SCENARIO DATE: 1118/04 PAGE: 7 o f 23 20 min. 4.5 SG Tube Leak Trigger 3 20 min. 4.6 Hotwell Level Fails High Trigger 4 40 min. 4.7 Przr PORV 431C Fails Open Trigger 5 4.8 SGTR Increase SGN04B to 500 gpm Terminate when directed by the Lead Examiner.
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2 0 0 4 NRC Initial Exam REV: 0 Scenario 04-2 R. E. GINNA NUCLEAR POWER PLANT TITLE: Steam Generator Tube Rupture EXAMINATION SCENARIO DATE: 1/I 8/04 PAGE: 8 o f 23
- 5. TURNOVER INFORMATION 5.1 The plant is at 100% MOL Xenon Eq, CB 845 ppm. The I'D" CNMT Recirc Fan is 00s. See the A-52.4. "A" Charging Pump is 00s. See A-52.12 5.2 EuuiDment Out of Service D CNMT Recirc. Fan out for two hours A Charging Pump Belt replacement 5.3 Work in Procrress D CNMT Recirc Fan Breaker A Charging Pump Belt replacement 5.4 Planned Work None 5.5 Sisnificant Events CNMT Recirc Fan expected to be restored within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
A Charging Pump will be out at least 24 more hours.
5.6 Remarks
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-2
- R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO TITLE: Steam Generator Tube Rupture DATE: 1/18/04 PAGE: 9 o f 23
- 6. EVALUATION Event : 1 Event
Title:
Turbine lstStase Pressure Fails Low (PT-485)
Expected Response/Behavior CUES: Tref Fails Low Control Rods step in at high speed Response :
RATING I3.B SRO Recognize rod motion, enter AP-RCC.l u
RO/SRO Verify Turbine Power Stable, place rods in manual RO/SRO Check Tavg. Manually operate rods to restore Tavg .
RO/SRO/BOP Check for Instrument Failure Tavg Turbine lscStage Press SRO Refer to ER-INST.l for Channel Defeat SRO Determine if Steam Dump should be placed in manual.
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC initial Exam REV: 0 Scenario 04-2 R. E. GINNA NUCLEAR POWER PLANT TITLE: Steam Generator Tube Rupture EXAMINATION SCENARIO DATE: 1118/04 PAGE: 10 of 23 BOP/SRO Monitor S/G Levels BOP Defeat PT-485 per attachment First Stage Pressure PT-485 Trip 4 8 5 Channel 2 in the white protection rack Verify AMSAC trip status light is extinguished Veriy TL 400 Status Light extinguished (call A0 to check)
Call I & C to place TPS/485 to trip Verify AMSAC Auto Block life extinguished Delete point PO485 on PPCA BOP/RO/SRO Check Systems in Auto SRO Notify Plant Supervision
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 0 4 - 2 R. E. GINNA NUCLEAR POWER PLANT TITLE: Steam Generator Tube Rupture id EXAMINATION SCENARIO DATE: 1 /18/04 PAGE: 11 of 23 6 EVALUATION Event : 2 Event Title : Loss of Circuit 751 Expected Resuonse/Behavior CUES: Circuit 751 Deenergized Buses 16, 17 lose power B D/G starts Response :
RATING BOP/ SRO Recognize loss of 751 SRO Enter AP-ELEC.1 RO/SRO Verify Tavg > 350°F and both RCP running BOP/ SRO Verify B D/G running and both trains AC emergency buses energized BOP/SRO Verify SW pump running Manually start IVC" or lVDV1 RO/SRO Verify CCW pump running RO/SRO Verify Charging Pump running Determine none running secure letdown
ROCHESTER GAS 81 ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 0 4 - 2 R. E. GINNA NUCLEAR POWER PLANT TITLE: Steam Generator Tube Rupture EXAMINATION SCENARIO DATE: 111 8/04 PAGE: 1 2 of 23 BOP/ SRO Verify Instrument Air available BOP/SRO Verify 11A/11B energized and MFW Regulating Valve Controlling RO/SRO Check VCT Makeup System Charging Aligned to VCT RO/SRO Check VCT Makeup System Charging Aligned to VCT RO/SRO Start a Charging Pump u
RO/SRO Restore Letdown RO/SRO Restore Przr Heaters RO/SRO Restore Rod to Auto RO/SRO Stabilize Plant BOP~SRO Restore Power Alignment using ER-ELEC.l Restore power to Bus 12B (step 4.1.6)
Restore power to buses 16/17 by holding normal feeder closed while tripping D/G feeder
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-2 R. E. GINNA NUCLEAR POWER PLANT TITLE: Steam Generator Tube Rupture
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EXAMINATION SCENARIO DATE: 1118/04 PAGE: 13 of 23 BOP Secure the B D/G per T-27.4 RO/SRO Verify at least t w o CNMT Recirc Fans running RO/BOP/SRO Check Control System in Auto 431K Przr Press Heaters/Sprays Charging Pumps MFW Reg Valves Turbine EH Control Rods SRO Check Battery Chargers Dispatch A0 RO/SRO Secure one of two CCW pumps RO/SRO Check/Start Radiation Monitor Sample Pump SRO Send A0 to check Seal Oil System BOP/SRO Close Fire Pump Breaker BOP/SRO Check Aux. Building Ventilation SRO Dispatch A0 to check Waste Gas Compressors/SFP Cooling/Reset W Relay Targets
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-2 R. E. GiNNA NUCLEAR POWER PLANT TITLE: Steam Generator Tube Rupture EXAMINATION SCENARIO DATE: 1/I 8/04 PAGE: 14 of 23 6 EVALUATION Event : 3 Event
Title:
S/G Tube Leak Expected ResDonse/Behavior CUES: R-15/15A increasing Computer alarms on S/G leakage (from R-15A)
Charging Pump speed increases VCT level decreases Response :
RATING u RO/SRO Determine S / G Tube Leak has occurred from u
indications. Enter AP-SG.l Steam Generator Tube Leak RO/SRO Monitor Przr Level adjust charging to stabilize pressurizer level RO/BOP/SRO Monitor Tube Leak Rate Determine that it is > 1 gpm Go to Step 8 (Rapid Plant Shutdown)
RO/BOP/SRO Initiate Load Reduction Verify Rod in Auto Setup Turbine or 3 % min load reduction Verify Steam Dump operation Przr Backup Heater on
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-2 R. E. GINNA NUCLEAR POWER PLANT TITLE: Steam Generator Tube Rupture L,
EXAMINATION SCENARIO DATE: 1118/04 PAGE: 15 of 23
- 6. EVALUATION Event : 4 Event
Title:
Hotwell Level Channel LT-2001 Fails Hish ExDected ResDonse/Behavior CUES: LT-2001 Offscale High LT-2002 Decreasing Hotwell Level Controller Rejecting Increasing Condensate Storage Tank Levels Response :
RATING H.&
BOP Recognize symptom of LT-2001 failure SRO/BOP Place Hotwell Level control to manual Restore Hotwell Level BOP Monitor Control Hotwell Level manually SRO Notify Scheduling BOP Secure third Condensate Pump per T-5F BOP Close Condensate Bypass Valve
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-2 R. E. GlNNA NUCLEAR POWER PLANT TITLE: Steam Generator Tube Rupture u
EXAMINATION SCENARIO DATE: 1/ I 8/04 PAGE: 16 of 23
- 6. EVALUATION Event : 5 Event
Title:
Przr PORV-431C Fails Open Expected Response/Behavior CUES: Przr Pressure Decreasing PORV Tail Pipe Temp Alarm PORV-431C Indicates mid position Response :
RATING N/A RO Recognize PORV-431C partly open Attempt to close/close block valve SRO Enter AP-PRZR.l Abnormal Przr Press RO/CRF Check Przr Press Channels RO/CRF Check RCS Parameters Power Przr Pressure RO/SRO Check Przr Press Control Przr Heaters Normal Spray Press Controller 431K RO/SRO Check PORVs. Determine 431C was open and the block valve is now closed.
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-2 R. E. GINNA NUCLEAR POWER PLANT TITLE: Steam Generator Tube Rupture J
EXAMINATION SCENARIO DATE: 1118/04 PAGE: 17 of 23 RO/SRO Check Przr Safety Valves and Auxiliary Spray RO/SRO Verify Przr Press returning to normal (go to s t e p 16)
RO/SRO Check PRT
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-2 R. E. GINNA NUCLEAR POWER PLANT TITLE: Steam Generator Tube Rupture EXAMINATION SCENARIO DATE: 1/18/04 PAGE: 18 of 23
- 6. EVALUATION Event: 6.7 Event
Title:
SGTR ExDected ResDonse/Behavior CUES: Rapid Decreasing Przr Level SF/FF Mismatch Air Ejector R-15/15A Radiation increasing rapidly Response :
RATING EL&
RO/SRO Recognize Przr level decreasing Start additional Charging Pump Isolate Letdown Recognize that Przr level can't be maintained
\- Trip Rx and go to E-0 RO/BOP Check Immediate Actions (May manually initiate SI)
RO/BOP/SRO Check Status of Emergency Equipment e SI/RHR e CNMT Recirc Fans e CNMT Spray (not required) e Steamline Isolation e MFW Isolation e M D A F W Pumps e Service Water Pumps e CI/cvI e ccw 0 SI Flow e AFW Alignment
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-2 R. E. GlNNA NUCLEAR POWER PLANT TITLE: Steam Generator Tube Rupture W
EXAMINATION SCENARIO DATE: 1/l8/04 PAGE: 19 of 23 BOP/SRO Check S/G levels (should secure feeding "B1' S/G when level is > 50%)
Control intact S/G 17-50%
RO/SRO Verify SI/= Alignment RO/SRO Check CCW Cooling to RCPs RO/SRO Secure TDAFW Pump BOP / SRO Control RCS Tavg to 547'F (may need to limit AFW to A S/G)
RO/SRO Check PORVs and Sprays Closed.
BOP/RO/ Monitor RCP Trip Criteria (should not be met)
SRO BOP/SRO Check Secondary Side Intact
r
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ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-2 R. E. GlNNA NUCLEAR POWER PLANT TITLE: Steam Generator Tube Rupture L
EXAMINATION SCENARIO DATE: 1 /18/04 PAGE: 20 of 23 BOP/SRO Check for SGTR Transition to E-3 SGTR BOP/SRO Identify lrBl1S/G as ruptured Level Response R-32 Alarm UNSAT CT #1 E-3--A Isolate feedwater flow into and steam flow from the ruptured steam generator before a transition to ECA-3.1 occurs.
Isolate Rupture S/G ARV 1050 psi in Auto TDAFW Steam Valve MOV 35041 closed S/G Blowdown and Sample Valves Closed Try to close llBllMSIV. When it will not Close, perform the following:
- Close "A" MSIV
- Set "Ag1ARV to 1 0 0 5 psig in AUTO
- Adjust Condenser Steam Dump to 1050 psi in AUTO
- Place Steam Dump mode switch to Manual (Pressure Control Mode)
- Adjust reheat steam supply. ? to close Reheat steam supply valves (will already be closed)
- Dispatch A0 to complete Rupture S / G Isolation (Parts A and B for the B S / G )
Check Rupture S/G Level > 5%
- Close MOV 4008
- Pull Stop MDAFW Pump llB1l
- Close TDAFW Flow Control Valve AOV 4298
- Verify MDAFW cross-tie Valves Closed MOV 4000 A/B
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-2 R. E. GINNA NUCLEAR POWER PLANT TITLE: Steam Generator Tube Rupture L-EXAMINATION SCENARIO DATE: 1/ 1 8/04 PAGE: 21 of 23 BOP/SRO Check S/G Isolation
- MSIV Closed (instruct A0 working on Attachment Rupture S/G to close Air Ejector and Flange Heat Steam Valves)
- Verify TDAFW Steam Supply Isolate
- Verify Rupture S/G Press > 300 psi BOP / SRO Adjust Intact S/G ARV to maintain S/G pressure RO/SRO Reset SI UNSAT CT #2 E-3--B Establish/maintain RCS temperature so that a transition out of E-3 does not occur because the RCS temperature is in either of the following conditions:
Too high to maintain minimum subcooling or Below the orange path PTS transition temperature (285OF)
SRO Determine required Core Exit Temp from Table BOP/SRO Dump steam from the intact S/G ARV to cooldown To less than the required temperature BOP Stabilize Core Exit Temperature
ROCHESTER GAS 81 ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-2 R. E. GINNA NUCLEAR POWER PLANT L
EXAMINATION SCENARIO DATE: 111 8/04 PAGE: 2 2 of 23 BOP/ SRO Monitor Intact S/G Level Control 17%-50%
(Note it will decrease below 17%))
RO/SRO Check at least one PORV available RO/SRO Reset CI BOP/SRO Check Normal Electrical lineup to safeguard busses RO/BOP/ Restore Instrument Air SRO - Check adequate SW
~L
- Dispatch A0 to perform AH SD-1
- Buses 13/15 normal
- Feeds closed
- SW Isolation Valve to the Turbine Building open
- Adequate Air Compressor running A and B Instrument Or C Instrument Or Service Air
- Adequate IA Press
- Open AOV 5392 IA to CNMT RO/SRO Stop RHR pump RO/SRO Establish 75 gpm Charging from RWST BOP/SRO Check Ruptured S/G Press Stable
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ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-2 R. E. GINNA NUCLEAR POWER PLANT TITLE: Steam Generator Tube Rupture EXAMINATION SCENARIO DATE: 1I1 8/04 PAGE: 23 of 23 SRO Check for > 20°F core exit subcooling SAT UNSAT CT #3 E-3--C Depressurize RCS to SI termination criteria within one hour of SGTR initiation.
RO/SRO Depressurize using normal spray until termination criteria met.
1 RO/SRO Check RCS Press Increasing RO/BOP/ Check SI Termination Criteria
'1 SRO SAT UNSAT CT #4 CT E-3--D Terminate SI within one hour of SGTR initiation and control RCS pressure and makeup so that primary and secondary inventory are stable before the end of the scenario.
I
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-3 R. E. GINNA NUCLEAR POWER PLANT TITLE: LOCA Outside CNMT
- EXAMINATION SCENARIO DATE: 1/ I 8/04 PAGE: 1 of 19 Written by: Kenneth Masker Date : 1/21/04 License Instructor Technical Review: Dous Peterson Date : 1/30/04 SRO, SS Time validated 90 minutes By: K. Masker Date : 2/7/04 License Instructor Date of exam:
Examinees Evaluators L
Final review Date: 3/2r/07 Approved for use Supervisor License Training or Designee
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-3 R. E. GINNA NUCLEAR POWER PLANT TITLE: LOCA Outside CNMT G'
EXAMINATION SCENARIO DATE: 1I1 8/04 PAGE: 2 of 19
- 1. SCENARIO OVERVIEW 1.1 The plant is initially at 100% Power Xenon Equilibrium. Auto Rod Control is 00s due to,Tavg input problems, I&C is investigating. The "C1' Condensate Booster Pump is 00s due to a motor bearing failure. PT-429 failed low and has been defeated.
1.2 The running CCW pump trips. The standby pump fails to auto start. The operator needs to recognize the trip and take action per AP-CCW.1, Loss of CCW During Power Operations, prior to exceeding the operating limits for the RCPs.
1.3 The llA1l Feed Regulating Valve fails closed in Auto. The operator needs to take manual control per AP-FW.l and control S/G levels manually.
1.4 The I1A1ICharging Pump speed controller fails causing the pump to slow to minimum speed. The operator should start the standby pump and secure the IIAII pump, then place the system back in auto control.
1.5 llBrlCondensate Booster Pump Trips leaving only the I1A"Pump Running. The operator should decrease load to prevent runout of the "A" pump per AP-
- TURB.5, Rapid Power Reduction.
1.6 A station blackout occurs causing a Turbine and Reactor Trip. Because of the PT-429 failure, an inadvertent SI occurs. The Diesel Generator fails to auto start requiring a manual start. When power is restored, MOV-852B opens on the SI signal and CV-853B fails allowing full RCS pressure to enter the RHR system. This results in an inter-system LOCA. The operators respond by implementing E-0, Reactor Trip or SI and transitioning to ECA-1.2, LOCA outside CNMT. The scenario is terminated when SI is terminated per procedure ES-1.1, SI Termination.
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2 0 0 4 NRC Initial Exam REV: 0 Scenario 04-3 R. E. GINNA NUCLEAR POWER PLANT TITLE: LOCA Outside CNMT EXAMINATION SCENARIO DATE: 1/18/04 PAGE: 3 of 1 9
- 2. SCENARIO OBJECTIVES RO(s) - Demonstrate the ability to monitor and operate the MCB, diagnose events and implement step of Normal, Abnormal and Emergency Procedures. Interact with other members of the crew in a manner which facilitates the crews response to the events listed below.
SRO - Demonstrate the ability to supervise the Control Board operators, diagnose events and choose and implement response procedures, implement Tech Spec requirements to ensure the plant is operated within its licensed basis, interact with other members of the crew in a manner which facilitates the crews response to the events listed below.
Instrument/Component Malfunctions Running CCW Pump Trip/Without Auto Start "At1FRV Failure of Auto Control "A" Charging Pump Speed Controller Failure PT-429 Failure Low Station Blackout Diesel Generator Fails to Auto Start Reactivity Manipulations Power Reduction for Loss of Condensate Booster Pump Major Malfunctions CV-853B Fail during Inadvertent SI causing an inter-system LOCA
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-3 R. E. GINNA NUCLEAR POWER PLANT TITLE: LOCA Outside CNMT L
EXAMINATION SCENARIO DATE: 1118/04 PAGE: 4 of 19
- 3. CRITICAL TASKS (CTs)
CT #1 E-0--C Task: Energize at least one AC emergency bus before transition out of E-0 unless the transition is to ECA-0.0, in which case the critical task must be performed before placing safeguards equipment handswitches in the pull-to-lock position.
Cues: Indication and/or annunciation that all AC emergency buses are de-energized Circuit breaker position Bus voltage EDG status Indication: Manipulation of controls as required to energize at least one AC emergency bus Circuit breaker position lamps indicate closed Bus voltage indication shows nominal voltage present Feedback: Indication that at least one AC emergency bus is energized Safeguards equipment sequences into the energized bus(es)
EDG status
-v CT #2 ECA-1.2--A Task: Isolate LOCA outside containment before transition out of ECA-1.2 Cues: Indication that SI is actuated and required RCS pressure c SI pump shutoff head SI pump running and Indication that Auxiliary Building radiation is abnormally high R-lOB, 13, 14 on Alarm R-4, 9 on Alarm Indication: MOV-852B is shut to isolate leak and is not reopened Feedback: RCS pressure increasing Auxiliary Building radiation level decreasing
I I I 1 ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-3 R. E. GINNA NUCLEAR POWER PLANT TITLE: LOCA Outside CNMT u I EXAMINATION SCENARIO I DATE: 1/18/04 I PAGE: 5 o f 19 I
- 4. INSTRUCTOR ACTIONS Problem Time Actions Notes 4.1 Initial Conditions 4.2 Set up Simulator per OTG-3.2 4.2.1 IC-19 MOL 100% Xenon Equilibrium 4-2.2 Place llC1l Condensate Booster Pump in off and place hold Tag Verify and I1Blr Pump Running 4.2.3 Place llBll CCW in service secure I1A1lCCW pump 4.2.4 Enter Malfunctions 4.2.4.1 MALF CLGlO CCW Auto Start Failure MALF GEN08, 0 (both) Both DG fail to Autostart 4.2.4.2 MALF CLG2B lrB1lCCW Pump Trip Trigger 1 4.2.4.3 MALF FDWO7A, 0%, 60 sec "A" FRV Fails Closed ramp Trigger 2 4.2.4.4 MALF CVC18A, 15 gpm, 0 "Af1Charging Pump ramp Speed Control Trigger 2 Failure 4.2.4.5 MALF CNDOlB l1B1ICNDST Booster Trigger 3 Pump Trips 4.2.4.6 MALF EDS06, 0 Station Blackout Trigger 6 MALF RCSlSD, 800 g p m , 30 LOCA o/s CNM sec TD Trigger 4 4.2.5 Insert Malfunction PZR02A, 1600 Submit A-52.4 on Defeat PT-429 per ER-INST.l PT-429 out 3 days
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-3 R. E. GINNA NUCLEAR POWER PLANT TITLE: LOCA Outside CNMT
'W EXAMINATION SCENARIO DATE: 1/I 8/04 PAGE: 6 of 19 2 min 4.3 CCW Pump Trip Trigger 1 4.4 "A" FRV Fails Closed 7 .min Trigger 2 4.5 Charging Speed Failure 7 min Trigger 2 4.6 CNDST BSTR 25 min Pump Trip Trigger 4 4.8 LOCA O/S CNMT 45 min Trigger 5 Terminate Scenario when SI has to be terminated or when instructed by the Lead L Examiner.
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-3 R. E. GINNA NUCLEAR POWER PLANT TITLE: LOCA Outside CNMT
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EXAMINATION SCENARIO DATE: 1118/04 PAGE: 6 of 19 7 min 4.4 I1A1I FRV Fails Closed Trigger 2 7 min 4.5 Charging Speed Failure Trigger 2 25 min 4.6 CNDST BSTR Pump Trip Trigger 4 45 min 4.8 LOCA O/S CNMT Trigger 5 Terminate Scenario when SI has to be terminated or when instructed by the Lead Examiner.
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC initial Exam REV: 0 Scenario 04-3 R. E. GINNA NUCLEAR POWER PLANT TITLE: LOCA Outside CNMT EXAMINATION SCENARIO DATE: 1/18/04 PAGE: 7 of 19
- 5. TURNOVER INFORMATION 5.1100% Power MOL CB 845 ppm. Xenon Equilibrium.
5.2 Eauipment Out of Service Auto Rod Control due to a problem with the Average Tavg signal to rod control "C" Condensate Booster Pump due to a motor bearing problem PT-429 Failed Low A-52.4 submitted 5.3 Work in Prosress Rod Control Trouble Shooting llC1'Condensate Booster Pump Motor Replacement 5.4 Planned Work No Additional 5 . 5 Sisnificant Events Six hours ago rod began stepping out in Auto without a valid signal. I&C is investigating. Manual Rod Control is operable.
5.6 Remarks L
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2 0 0 4 NRC Initial Exam REV: 0 Scenario 04-3 R. E. GlNNA NUCLEAR POWER PLANT TITLE: LOCA Outside CNMT L
EXAMINATION SCENARIO DATE: 1/I 8/04 PAGE: 8 of 19
- 6. EVALUATION Event : 1 Event
Title:
Runnins CCW PumD TriDs/No Auto Start ExDected ResDonse/Behavior CUES: CCW Pump AR1Tripped CCW Temp and Flow Alarms RCP Temp Alarms Response :
RATING RO/SRO Recognize Loss of CCW Pump Enter AP-CCW.2, Loss of CCW during Power Operations RO/SRO Start the Standby CCW Pump RO/SRO Check Monitor Plant Conditions CCW Surge Tank Level CCW to RCPs Letdown RO/SRO Check CCW Valve Alignment RO/SRO Check for CCW Leaks Seal Water CNMT Aux Building
I I
ROCHESTER GAS & ELECTRIC CORPORATION I NO.:
I 2004 NRC Initial Exam I REV: 0 I 1 I
I Scenario 04-3
-- R. E. GINNA NUCLEAR POWER PLANT EXAMINATION SCENARIO TITLE: LOCA Outside CNMT DATE: 1f 18/04 PAGE: 9 of 19 SRO Determine that no CCW Leak exists RO/SRO Verify Letdown in service
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-3 R. E. GINNA NUCLEAR POWER PLANT TITLE: LOCA Outside CNMT L/
EXAMINATION SCENARIO DATE: 1/18/04 PAGE: 10 of 19
- 6. EVALUATION Event : 2 Event
Title:
I1A" FRV Fails Closed ExDected Response/Behavior CUES: Feedwater Flow decreases S/G "AI1level decreases S/G level deviation alarms Response :
RATING BOP/ SRO Recognize feed flow decreasing Enter AP-FW.l Abnormal Feedwater Flow L, BOP/SRO Check MFW Flow c Steam Flow BOP/SRO Check both MFW Pumps Running BOP/ SRO Check MFW Pump Suction Press BOP/SRO Check MFW Regulating Valve Determine "A" not controlling in Auto swap to manual control BOP Restore A1'S/G Level in manual
1 I I I ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-3 R. E. GINNA NUCLEAR POWER PLANT TITLE: LOCA Outside CNMT EXAMINATION SCENARIO DATE: 1/ I 8/04 PAGE: 1 1 of 19 RO/BOP/ Stabilize Plant Conditions SRO Tavg Przr Press Przr Level S/G Level RIL Alarms BOP/SRO Check MFW System 0 Pump Suction Press Auto Control (not available)
BOP / SRO Check Condensate System CNDST Bypass Valve Hotwell Level Only two Condensate Pumps Running Trim Valves in Auto RO/BOP/ Establish Control System in Auto SRO Przr Press/Level EHC Steam Dump
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2 0 0 4 NRC Initial Exam REV: 0 Scenario 04-3 R. E. GINNA NUCLEAR POWER PLANT TITLE: LOCA Outside CNMT EXAMINATION SCENARIO DATE: 1118 / 0 4 PAGE: 1 2 of 19 6 EVALUATION Event : 3 Event
Title:
Charsinq Pump Speed Controller Failure ExDected Response/Behavior CUES : Charging Pump Speed Alarm (F-14)
Charging flow decreases Przr Level decreases Response :
RATING N/A RO/SRO Recognize abnormal indication in CVCS Determine "At1Charging pump speed has failed to minimum RO/SRO Control Charging pump speed manually to control Przr Level (cannot control in manual)
RO/SRO Swap Charging Pump Auto Speed control to the IIBII or II C II Pump SRO Notify plant management of problem
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-3 R. E. GINNA NUCLEAR POWER PLANT TITLE: LOCA Outside CNMT v
EXAMINATION SCENARIO DATE: 111 8/04 PAGE: 1 3 of 19
- 6. EVALUATION Event : 4 Event
Title:
l'Blr CNDST Booster Pump Trip Expected Response/Behavior CUES: Low Feedwater Suction Pressure 4KV Motor Overload Alarm (6-8)
Feedwater Pump NPSH Alarm Condensate Bypass Valve Opens Response :
RATING u BOP/SRO Recognize Booster Pump Trip Verify MFW Suction Press > 185 psi SRO Determine power must be reduced to e 90% in 30 minutes. (AR-AA-10)
SRO Enter 0-5.1 for power reduction SRO Verify 0-5.1 Initial Conditions RO/BOP/SRO Make preparation for decreasing load Notify Energy Operations Przr Back Heaters on Select rate on EHC Notify plant personnel
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2 0 0 4 NRC Initial Exam REV: 0 Scenario 04-3 R. E. GINNA NUCLEAR POWER PLANT TITLE: LOCA Outside CNMT
-.--, EXAMINATlON SCENARIO DATE: 1 /18/04 PAGE: 1 4 of 19 RO/BOP/SRO Perform Load Reduction Rods in manual Add Boric Acid as necessary Lower Tube Load using EHC
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-3 R. E. GINNA NUCLEAR POWER PLANT TITLE: LOCA Outside CNMT u
EXAMINATION SCENARIO DATE: 1118/04 PAGE: 15 of 19
- 6. EVALUATION Event: 6.7,8 Event
Title:
Station Black out Rx TriD, SI, LOCA O / S CNMT ExDected ResDonse/Behavior CUES: R x Trip SI Signal Present Response :
RATING HLA SRO Recognize Rx Trip, direct Board Operators to perform immediate actions RO/BOP Perform immediate actions of E-0 SAT UNSAT CT #1 E-0--M Manually start at least one Emergency Diesel Generator (see Section 3.0)
SRO Determine SI Actuated, continue in E - 0
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-3 R. E. GINNA NUCLEAR POWER PLANT TITLE: LOCA Outside CNMT L e EXAMINATION SCENARIO DATE: 1/18/04 PAGE: 16 of 19 SRO/RO/BOP Verify Auto Actions e SI/- Pump Running 0 CNMT Recirc Fans Running e CNMT Spray not required e Main Steamline Isolation not required e MFW Isolation e M D A F W Pump Running e SW Pump Running e CI and CVI 0 One CCW Pump Running 0 SI F l o w e AFW Alignment BOP/SRO Monitor S/G Levels Control at 17-50%
RO/SRO Check SI/RHR Alignment RO/SRO Check RCP Cooling BOP/SRO Stop TDAFW Pump BOP/SRO Control Tavg at 547F AFW Steaming (may need to shut MSIVs)
RO/SRO Check Przr PORVs and Spray
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-3 R. E. GINNA NUCLEAR POWER PLANT TITLE: LOCA Outside CNMT EXAMINATION SCENARIO DATE: 1/I 8/04 PAGE: 17 of 19 SRO/BOP/ Perform diagnostic step RO S/G Intact S/G Tubes Intact No LOCA in CNMT Continue in E-0 SRO Determine SI cannot be Terminated BOP/SRO Control S/G Levels 17-50%
BOP/ SRO Check Secondary Radiation Levels
.__ RO/SRO Reset SI and CI BOP/SRO Verify adequate SW Three pumps running
- Start third pump Send A0 to do SD-1 Attachment BOP/SRO Establish IA to CNMT Close 13-14 and 15-16 cross tie breakers Open Turbine Building SW Isolation Valves Start Adequate IA Compressors IIAII and I l g t l Or II cII Or Service Air Open AOV-5392
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-3 R. E. GINNA NUCLEAR POWER PLANT TITLE: LOCA Outside CNMT L
EXAMINATION SCENARIO DATE: 1I18/04 PAGE: 18 of 19 SRO Check Aux Building Radiation Determine that it is abnormal from a LOCA O/S CNMT Transition to ECA-1.2 RO/SRO Verify Proper Valve Alignments MOV 700, 701, 7 2 0 , 7 2 1 closed AOV 310, 296, 392A closed MOV 313 and 371 closed RO/SRO Check for back flow into RHR Close MOV 852A Monitor for pressure increase. Determine pressure not increasing Open MOV 852A SAT UNSAT v
CT #2 ECA-1.2--A Isolate LOCA O/S CNMT for Transition out Of ECA-1.2 Close MOV 852B Determine pressure is increasing Leave 852B closed SRO Verify pressure is increasing Transition to E-1, Loss of Reactor or Secondary Coolant Note: Examinees will perform actions in E-1 until SI Termination Criteria is met (Step 12 or Foldout Page) just actions not previously performed are listed
ROCHESTER GAS & ELECTRIC CORPORATION NO.: 2004 NRC Initial Exam REV: 0 Scenario 04-3 R. E. GINNA NUCLEAR POWER PLANT TITLE: LOCA Outside CNMT -
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EXAMINATION SCENARIO DATE: 1I1 8/04 PAGE: 19 of 19 RO/SRO Establish Charging to Restore Przr Level HC%-142 open Align Charging Suction to the RWST
- 112B open
- 112C closed Start Charging Pumps SRO Check SI Termination Criteria Determine it is met go to ES-1.1 SI Termination (Only step not done in E-0 and E - 1 appear here)
RO/SRO Maintain Przr Press 1800-2235 psig Reset Przr Heater RO/SRO Stop SI and EUHR pumps End Scenario