ML083040117
| ML083040117 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 09/01/2008 |
| From: | Constellation Energy Group |
| To: | D'Antonio J Operations Branch I |
| Hansell S | |
| Shared Package | |
| ML081060454 | List: |
| References | |
| 50-220/08-302, ES-D-1, TAC U01690 50-220/08-302 | |
| Download: ML083040117 (143) | |
Text
Appendix D Scenario Outline Form ES-D-1 Op-Test No.: October 2008 Initial Conditions: Simulator IC 171
- 1. Reactor Power approximately 4%
- 1. The crew is directed to shutdown the reactor by inserting control rods
- 2. Crew is directed to perform N1-OP-09, N2 lnerting and H2-02Monitoring Systems step G.l to de-inert the Primary Containment with Rx Coolant Temp >212"F Event 1 1 RR07A 1 C(SR0)
TS fSRO)
'ump 11 seal failure, Recirc Pump must be shutdown and isolated (SOP-I .2) ure causes rising Off-Gas and Main Steam Line In, requires a reactor scram (SOP-25.2)
- (N)ormal, (R)eactivity, (I)nstrument, fC)omponent, (M)ajor NRC Scenario 1 October 2008
Facility: Nine Mile Point 1 Scenario 110.:NRC-01 OD-Test No.: October 2008 TARGET QUANTITATIVE ATTRIBUTES ACTUAL (PER SCENARIO; SEE SECTION D.5.d) ATTRIBUTES
- 1. Total malfunctions (5-8) 6 Events 2,4,5, 6,7,9
- 2. Malfunctions after EOP entry (1-2) 1 Event 9
- 3. Abnormal events (2-4) 4 Events 4,5,6,7
- 4. Major transients (1 -2) 1 Event 8
- 5. EOPs enteredhequiring substantive 1 actions (1-2)
Event 8 (EOP-6)
- 6. EOP contingencies requiring substantive 1 actions (0-2)
Events 9 (EOP-8)
- 7. Critical tasks (2-3) 2 CRITICAL TASK DESCRIPTIONS:
CT-1.O Given a fuel failure, the crew will scram the reactor and insert a manual vessel isolation when Main Steam Line radiation reaches 3.75 times normal.
CT-2.0 Given unisolable primary system leak, indications of fuel failure and rising off-site release rates approaching the General Emergency level, the crew will Derform an RPV Blowdown.
NRC Scenario 1 October 2008
NMP SIMULATOR SCENARIO NRC Scenario 1 REV. 0 No. of Pages: 31 PLANT SHUTDOWN, RECIRC PUMP SEAL FAILURE, FUEL FAILURE, UNISOLABLE EMERGENCY CONDENSIER LEAK TO THE ENVIRONMENT PREPARER VALIDATED le James, Bruce Williams DATE 5/18/08 GEN SUPERVISO OPS TRAINING DATE & ' ! S k OPERATIONS MANAGER N/A - IExam Securit DATE CONFIGURATION CONTROL N/A - IExam Securitv DATE SCENARIO
SUMMARY
Length: 90 minutes Initial Power Level: 4% with plant shutdown in progress Mitigating Strategy Code: RR4, fuel leak with a failure of EC tubes and EC fails to isolate, requires RPV Blowdown to stop release The crew assumes the shift with the plant being shutdown. The crew is directed to de-inert the containment in accordance with N1-OP-9, FJ2 lnerting and H2-02Monitoring Systems. When drywell pressure is lowered to 0 psig, the operator will secure the lineup, but one of the containment isolation valves will fail to fully close. This will require entry into Technical Specifications and ensuring a second valve in the line is isolated. Then the crew will continue the shutdown by inserting control rods.
Next Reactor Building Radiation Monitor 12 will fail upscale causing a trip of RBVS and a start of RBEVS. Additionally there will be a failure of the Reactor Building to isolate. The crew must isolate the Reactor Building to restore Secondary Containment and the SRO must address Technical Specifications. When these acticins are complete, both seals on the 1IRecirculation Pump will fail requiring the crew to shutdown and isolate the pump. Following the loss of the Recirculation Pump, a fuel failure will cause offgas and main steam line radiation levels to rise, requiring a reactor scram and vessel isolation. Multiple control rods will fail to fully insert during the scram requiring the crew to enter N1-SOP-1 and take alternate actions to insert the control rods. The rods are inserted using RMCS.
NRC Scenario 1 1 October 2008
Following the scram, the crew will diagnose an Emergency Condenser tube leak. They will try to isolate the affected EC but the isolation valves will fail to fully close. Rising off site radiation levels will require an RPV blowdown before General Emergency levels are reached.
Major Procedures: N1-SOP-1.2, N1-SOP-25.2, N1-SOP-1.1, N1-SOP-1, N1-EOP-2, N1-EOP-6, and N1-EOP-8 EAL Classification: Site Area Emergesncy, EALs 3.4.1, 5.1.3 and 5.2.4 Termination Criteria: RPV Blowdown in progress, RPV water level controlled in assigned band NRC Scenario 1 2 October 2008
I. SIMULATOR SET UP A. IC Number: IC 171 B. Presets/Function Key Assignments
- 1. Malfunctions:
- a. RMGV, RX BLDG VENT RAD MON 12, FINAL VALUE=100% TRG 1
- b. HV04, RB VENTILATION FAILS TO ISOLATE PRESET C. RROGA, RR PUMP 11 LOWf:R(INNER) SEAL FAILS, RAMP=2:OO FINAL VALUE=100% TRG 2
- e. RXOI, FUEL CLADDING FAILURE, FINAL VALUE=7% TRG 3
- f. RD33C, CONTROL ROD BANK BLOCKED BANK 3, FINAL VALUE=04 PRESET
- g. ECOGA, EMERGENCY CONDENSER TUBE LEAK 111, RAMP=I :OO,FINAL VALUE=4% TRG 4
- h. EC07A, EMERGENCY CONDENSER FAILS TO ISOLATE 11 PRESET
- 2. Remotes:
- a. None
- 3. Overrides:
- a. OVR-11DS74L05529 ON 21360 VLV201-7,9,17,31 RED LAMPS ,
DELAY TIME=O:02, FINAL VALUE=ON (201-31 RED LAMP) TRG 16
- 4. Annunciators:
- a. None
- 5. Triggers:
- a. TRG 4 - Initiates EC 11 tube failure when the mode switch is taken to shutdown
- i. Event Action: zdrpstdn==l ii. Command: None
- b. TRG 16 - Causes 201-31 red light to be overridden on when the control switch is taken to close, simulating the valve sticking in mid position
- i. Event Action: zdpcv3lo==l NRC Scenario 1 3 October 2008
ii. Command: None C. Equipment Out of Service
- 1. None D. Support Documentation
- 1. N1-OP-9, N2 INERTING AND H2-02 MONITORING SYSTEMS, Section G.l.O De-InertingNenting for Personnel Pccess-Rx Coolant Temp >212 O F marked up through step 1.5
- 2. N1-OP-43C marked up to step (3.3.13.6
- 3. Shutdown Control Rod Sequence sheets updated to current control rod.
E. Miscellaneous I.Setup trend recorder XP-I E l B on E console to trend recirc pump suction temperature.
- 3. Place yellow clearance tag on R.WM bypass keylock switch.
NRC Scenario 1 4 October 2008
II. SHIFT TURNOVER INFORMATION OFFGOINGSHIFT: [? N ID DATE: Today PART I: To be performed by the oncoming Operator before assuming the shift.
0 Control Panel Walkdown (all panels) (SM, CRS, STA, RO, CRE)
PART II: To be reviewed by the oncoining Operator before assuming the shift.
Shift Manager Log (SM, CRS, STA) 0 Shift Turnover Checklist (ALL) 0 RO Log (RO) 0 LCO Status (SM, CRS, STA) 0 Lit Control Room Annunciators 0 Computer Alarm Summary (RO)
Evolutions/GeneralInformation/Equipment Status:
Drywell entry is required for maintenance during forced outage -
Perform Containment De-lnerting per N1-OP-9 -
-Plant shutdown to continue by inserting control rods Rod Worth Minimizer is inoDerable with vellow clearance taa amlied to bvDass kevlock switch PART Ill: RemarksIPlanned Evolutions:
- 1. Perform N1-OP-9, N2 lnerting and H2-02Monitoring Systems starting at step G.1.6 to de-inert the Primary Containment with Rx Coolant Temp >212"F, raising oxygen concentration to
>19.5%
- 2. Continue shutdown from step G.3.13.E of N1-OP-43C PART IV: To be reviewed/accomplishcd shortly after assuming the shift:
Review new Clearances (SM) 0 Test Control Annunciators (CRE) 0 Shift Crew Composition (SMICRS)
NRC Scenario 1 5 October 2008
I Scenario ID INSTRUCTOR COMMENTS (Strenaths. Areas for Imwovement. OPen Items etc.)
What Happened? What we did? Why? (Goals) Other Options?
NRC Scenario 1 6 October 2008
Ill. PERFORMANCE OBJECTIVES A. Critical Tasks:
CT-1.O Given a fuel failure, the crew will scram the reactor and insert a manual vessel isolation when Main Steam Line radiation reaches 3.75 times normal, in accordancis with N1-SOP-25.2.
CT-2.0 Given an unisolable primary system leak, indications of fuel failure and rising off-site release rates approaching the General Emergency level, the crew will perform an RPV Blowdown, in accordance with N1-EOP-6 and N1-EOP-8.
B. Performance Objectives:
PO-1.o Given the plant in a shutdown, the crew will perform Primary Containment de-inerting, in accordance with N1-OP-9, N2 lnerting and H2-02 Monitoring Systems.
PO-2.0 Given a failure of a Primary Containment Isolation Valve to close, the crew will recognize the loss and take proper actions, in accordance with Technical Specifications.
PO-3.0 Given the plant in a shutdown, the crew will insert control rods, in accordance with N1-OP-5.
PO-4.0 Given a failed Reactor Building Radiation Monitor and a failure of the Reactor Building to isolate, the crew will respond to the condition and manually close the Reactor Building isolation valves, in accordance with N1-OP-I0.
PO-5.0 Given a total recirculation pump seal failure, the crew will secure and isolate the pump, in accordance with N1-SOP-I .2.
PO-6.0 Given a fuel leak, the crew will respond to rising radiation levels, in accordance with N1-SOP-25.2.
PO-7.0 Given a failure of control rods to insert during a scram, the crew will enter and execute N1-SOP-1.
PO-8.0 Given an Emergency Condenser tube leak, the crew will enter and execute N1-EOP-6.
PO-9.0 Given the plant in a condition requiring emergency classification, the SRO shall classify the events properly, complete initial notification forms, and discuss the bases for the classification in accordance with the emergency plan procedure.
NRC Scenario 1 7 October 2008
PO-I 0.0 Given the plant or a plant system in a condition requiring Technical Specification action, identify the deviation and any required actionshotifications.
NRC Scenario 1 8 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS Take the simulator out of freeze before the crew CREW enters for the pre-shift walkdown and briefing. Crew conducts pre-brief, walks down the Allow no more than 5 minutes for panel walkdown panels, assumes the shift EVENT I PO-1.o Perform Containment De-lnerting The initiation point for this event is when the SRO directs the performance of Section G.l .O of N I -
OP-9, N2 lnerting and H2-02 Monitoring Systems.
There are NO Console Operator activities related to this normal evolution.
SRO 0 Directs de-inerting the Primary Containment IAW Section G.l .O of N1-OP-9, N2 lnerting and H2-02 Monitoring Systems RO Monitors plant parameters BOP 0 Acknowledge direction from the SRO to de-inert the containment 0 Verify closed the following valves in the Control Room:
- 201-11, TORUWDRYWELL VENT TOCONDENSER
- 201-10, DW AIR VENT & PURGE ISOLATION VALVE 11
- 201-08, TOR AIR VENT &
PURGE ISOLATION VALVE 11 NRC Scenario 1 9 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 1 Continued BOP Continued
- 201-32, DW N2 VENT & PURGE ISOLATION VALVE 11 D Open 201-16, TORUS N2 VENT &
PURGE ISOLATION VALVE 11 D Start 201-35, DRYWELL & TORUS VENT & PURGE FAN B Verify open the following valves:
- 201-21, DRYWELL & TOR VENT
& PURGE FAN INLET BV
- 201-22, DRYWELL & TOR VENT
& PURGE FAN OUTLET BV Throttle open 201-17, TORUS N2 VENT & PURGE ISOLATION VALVE 12 WHEN Torus pressure drops BELOW 0 psig, perform the following:
Stop 201-35, DRYWELL &
TORUS VENT & PURGE FAN 0 Verify closed the following valves:
o 201-21, DRYWELL & TOR VENT & PURGE FAN INLET BV o 201-22, DRYWELL & TOR VENT & PURGE FAN OUTLET BV 0 Verify closed the following valves:
o 201-16, TORUS N2 VENT &
PURGE ISOLATION VALVE 11 o 201-17, TORUS N2 VENT &
PURGE ISOLATION VALVE 12 NRC Scenario 1 10 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 1 Continued BOP Continued Open 201-32, DW N2 VENT &
PURGE ISOLATION VALVE 11 Start 201-35, DRYWELL & TORUS VENT & PURGE Verify open the following valves:
201-21, DRYWELL & TOR VENT
& PURGE FAN INLET BV 201-22, DRYWELL & TOR VENT
& PURGE FAN OUTLET BV Throttle open 201-31, DW N2 VENT &
PURGE ISOLATION VALVE 12 Note: The containment vacuum breakers may WHEN Drywell pressure drops cycle during this event to equalize pressures. BELOW 0 psig, perform the following:
Stop 201-35, DRYWELL &
TORUS VENT & PURGE FAN 0 Verify closed the following valves:
o 201-21, DRYWELL & TOR VENT & PURGE FAN INLET BV o 201-22, DRYWELL & TOR VENT & PURGE FAN OUTLET BV 0 Verify closed the following valves:
o 201-32, DW N2 VENT &
PURGE ISOLATION VALVE 11 o 201-31, DW N2 VENT &
PURGE ISOLATION VALVE
-Note: 201-31 will fail to fully close, as indicated by 12 both red and green lights on, leading to the next event NRC Scenario 1 11 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 2 0-2.0 Failure of 201-31, DW N2 VENT & PURGE ISOLATION VALVE 12 to fully close following N2 Primary Containment De-lnerting When the control switch for 201-31 is taker1 to 3RO close, verify TRG 16 automatically inserts the Acknowledge report that 201-31, DW following override: N2 VENT & PURGE ISOLATION VALVE 12 did NOT fully close OVR-11DS74L05529 ON 2060 VLV201- Direct BOP to manually close 201-31 7,9,17,31 RED LAMPS , DELAY TIME=O:lD2, Acknowledge report that 201-31 DW FINAL VALUEzON (201-31 RED LAMP) did NOT fully close TRG 16 201-31 red light remains on Direct BOP to verify 201-32, DW N2 VENT & PURGE ISOLATION VALVE 11 is fully closed Enter T.S. 3.3.4.b Contact Operations Management to notify about the failure of 201-31 to Role Plav: As Operations Management, close acknowledge failure of 201-31 and direct the SRO Direct the crew to stop de-inerting and to secure from de-inerting, until the next shilt. exit N1-OP-9 Direct the SRO to continue on with control rod insertion.
RO 0 Monitors plant parameters BOP Notify Crew/SRO that 201-31 did NOT fully close Attempt to manually close 201-31 Verify 201-32 closed NRC Scenario I 12 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 3 PO-3.0 Plant Shutdown using Control Rods There are NO Console Operator activities Pelated to this normal evolution.
SRO Note: Provide GAI-OPS-05 Attachment 1, SRO Conduct crew brief of shutdown REACTIVITY BRIEF CHECKLIST (may be done in activities and responsibilities pre-scenario brief) and plant shutdown RMI Conduct GAI-OPS-05 Reactivity Brief Direct Insertion of control rods for reactor shutdown in accordance with Shutdown Control Rod Sequence Provides oversight of reactivity maneuver RO Insert control rods to continue reactor shutdown in accordance with
-Note: Recommend allowing insertion of four Shutdown Control Rod Sequence control rods to allow the crew to stop at a stable 0 Observe IRM response AND range point IRM switches as required, maintaining recorder pen as follows:
- 0-125 scale between 25 and 75 nominal
- 0-40 scale between 8 and 24 nominal Monitor and maintain reactor cooldown rate less than 100"F/hr BOP Monitor Feedwater Level Control Monitor plant parameters 0 Provide peer checks as required NRC Scenario 1 13 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 4 0-4.0 Reactor Building Ventilation Radiation Monitor 12 fails UPSCALE and RB Ventilation fails to Isolate When control rod 30-47 has been inserted and directed by the examiner, insert malfunction:
RMGV, RX BLDG VENT RAD MON 12 (0-1OO%),
FINAL VALUE=IOO%
TRG I Verify the following malfunction is active:
HV04, RB VENTILATION FAILS TO ISOLATE IPRESET Expected Annunciators:
L1-4-3, RB VENT RAD MONITOR OFF NORMAL L1-1-5, RB VENT EXH FAN 11- 12 TRIP L1-3-6, MER VENT CH I 1 RELAY OPEFATE L1-4-6, MER VENT CH 12 RELAY OPERATE CREW RBVS fans trip 0 Respond to annunciators and RBEVS initiates diagnose Radiation Monitor trip with RB isolation valves remain open failure of RB to isolate SRO Acknowledges reports Enter N1-EOP-5, Secondary Containment Control, AND execute concurrently with ARPs NRC Scenario 1 14 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 4 Continued j R 0 Continued Direct manual isolation of the Reactor Building Determine that the reactor building failed to isolate and one channel of RB Rad Monitoring is inop and entry into Tech Spec 3.4.2 is required Enter LCO 3.4.4.e (7 day plant shutdown LCO when one train of EVS is inoperable)
RO Monitor plant parameters BOP Verifies Reactor Building Radiation Monitor 12 failed UPSCALE Confirm alarm on computer printout Role Plav: If contacted as RP, acknowledge Verify shutdown of RB Vent Sys and request but delay any reports on Reactor Building startup of RBEVS per N1-OP-IO radiation levels section H.2.0 or N1-EOP-HC attachment 6 Confirm the following fans started:
202-53, EVS FAN 11 202-33, EVS FAN 12 Confirm the following fans stopped:
202-01, REACTOR BLDG SUPPLY FAN 11 202-02, REACTOR BLDG SUPPLY FAN 12 0 202-05, REACTOR BLDG EXHAUST FAN 11 202-06, REACTOR BLDG EXHAUST FAN 12 NRC Scenario 1 15 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 4 Continued OP Continued Confirm open the following valves:
e 202-34, EM VENT EXHAUST FAN 11 OUTLET BV e 202-37, EM VENTILATION LOOP 11 INLET BV e 202-35, EM VENT EXHAUST FAN 12 OUTLET BV e 202-38, EM VENTILATION LOOP 12 INLET BV Confirm closed the following valves:
e 202-74, EM VENTILATION LOOP 11 COOLING BV e 202-75, EM VENTILATION LOOP 12 COOLING BV e 202-03, REACTOR BLDG SUPPLY FAN 11 INLET DAMPER e 202-04, REACTOR BLDG SUPPLY FAN 12 INLET DAMPER e 202-80, REACTOR BLDG EXHAUST FAN 1IOUTLET DAMPER e 202-81, REACTOR BLDG EXHAUST FAN 12 OUTLET DAMPER e 202-15, REACTOR BLDG SUPPLY ISOLATION VALVE 11 e 202-16, REACTOR BLDG SUPPLY ISOLATION VALVE 12 e 202-32, REACTOR BUILDING EXHAUST ISOLATION VALVE 11 e 202-31, REACTOR BUILDING EXHAUST ISOLATION VALVE 12 NRC Scenario 1 16 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 4 Continued BOP Continued 0 Notify Rad Protection, the normal Reactor Building Emergency Ventilation system has isolated AND Reactor Building Emergency Ventilation system is in service BEFORE 30 minutes has elapsed, secure one train of RBEVS:
Place EVS FAN 1 l(12)control Note: Examiner may decide to proceed with next switch to RED FLAG event before one train of RBEVS is secured Place EM VENTILATION LOOP 1 1 (12) INLET BV control switch to OPEN Verify flow approximately 1600 CFM Place EVS FAN 12(11)control switch to PULL TO LOCK Enter LCO 3.4.4.e (7 day plant shutdown LCO when one train of EVS is inoperable)
Verify closed EM VENTILATION LOOP 12(11) INLET BV 0 Verify in OFF position the following control switches:
0 REACTOR BLDG SUPPLY FAN 11 0 REACTOR BLDG SUPPLY FAN 12 REACTOR BLDG EXHAUST FAN 11 0 REACTOR BLDG EXHAUST FAN 12 NRC Scenario 1 17 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 5 PO-5.0 Recirculation Pump Seal Failure CREW When directed by examiner, insert malfunlction:
Acknowledgeheport annunciator F2-I -
1 RROGA, RR PUMP 11 LOWER(INNER) SEIAL Diagnose RRP 11 seal failure FAILS, RAMP=2:OO, FINAL VALUE=I00%
TRG 2 RROIA, RR PUMP 11 UPPER(0UTER) SEIAL FAILS, DELAY=I :30,RAMP=2:OO, FINAL VALUE=100%
TRG 2 RRP I I seal pressures lower Drywell leakage, pressure and humidity rise Expected Annunciator:
F2-1-1 REACT RECIRC PUMP-MOTOR 1.1 SRO ARP F2-1-1 directs entry into SOP-1.2 if seal Acknowledges report from crew pressure ~ 4 2 psig 5 or high seal flowAeakage Directs execution of ARP exists. Drywell conditions will begin to deteriorate Directs entry into N1-SOP-I 2,RRP and increased drywell humidity and in-leaki2ge to SEAL FAILURE the DWEDT will be indicated. When Drywell Determine the failure is catastrophic parameters are impacted, the failure is considered and pump should be tripped and catastrophicand the pump must be tripped and isolated isolated. Provide reactivity management oversight for removing the pump from service When RRP 11 has been shutdown and isolated exit N1-SOP-I .2and enter N1-OP-I, Section H, for 4 Loop Operation Review TS for impact of seal leakage and removal of pump from service NRC Scenario 1 18 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 5 Continued SRO Continued Tech Spec 3.2.5 identifies RCS leakage be limited to <2 GPM/day Role Plav: When contacted as Reactor increase for identified leakage. This Engineering, acknowledge request to verify will apply until the RRP is isolated thermal limits TS 3.1.7.e applies for partial loop operation, limits power to 90.5% until clearance applied to valve breakers Contacts Reactor Engineering to verify thermal limits RO Monitor plant parameters 0 Monitor reactor power and recirculation flow during closure of RRP suction and discharge valves e Verify operating position on the Power to Flow Map BOP ReviewdexecutesARP F2-1-1 Confirms alarm computer point A072 RRP 11 SEAL LEAK DET FL Enters N1-SOP-1.2 for seal failure Monitors containment parameters Monitors RRP seal indications Determines that both seals are failed Determines seal failure is catastrophic Place REACTOR RP MOTOR MG SET 11 control switch to STOP Close REACTOR R PUMP 11 BYPASSVALVE NRC Scenario 1 19 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 5 Continued BOP Continued Simultaneously close Suction AND Discharge Valves for RRP 11 holding switches in CLOSE position Exit N1-SOP-1.2 AND enter N1-OP-I, Section H, for 4 Loop Operation NRC Scenario 1 20 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 6 PO-6.0 Fuel Failure CREW When actions to isolate 11 RRP have been e Acknowledge/report annunciator H I completed and directed by examiner inserl: 7, OFF GAS HIGH RADIATION e Recognize rising offgas and main malfunction:
steam line radiation levels e Determine fuel failure has occurred R X O l , FUEL CLADDING FAILURE (0-loo'%),
FINAL VALUE=7%
TRG 3 Expected Annunciators:
HI-1-7, OFF GAS HIGH RADIATION (initial)
F1-2-7, MAIN STEAM RAD MONITOR CH I 1 HI/LO (later)
F4-2-2, MAIN STEAM RAD MONITOR CH 12 HI/LO (later)
Rising off-gas radiation levels Rising main steam line radiation levels SRO Acknowledge report of off-gas high radiation annunciator Enter N1-SOP-25.2 Fuel Failure/High Activity Notify Chemistry to sample reactor coolant for gross activity Classify event as an UNUSUAL EVENT per EAL 1.2.1 Brief crew on event impact Direct reactor power reduction per N1-SOP-I . I as necessary to control radiation levels NRC Scenario 1 21 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 6 Continued SRO Continued B Acknowledge report that MSL Rad Monitors are approaching/exceeding 3.75 X normal B Direct a manual scram, manual vessel isolation and entry into N I -
SOP-40.2 CT-1.O RO Perform emergency power reduction per N1-SOP-1.1 as directed When directed place Mode Switch in Shutdown Recognize/diagnose failure of all control rods to insert Perform a manual vessel isolation by placing both Vessel Isolation Ch I 1 and Ch 12 Control Switches on the E Panel t o ISOLATION IN CT-1.O BOP b l e Plav: When dispatched as Chemistry to take Execute N1-SOP-25.2 samples, acknowledge request. Notify Chemistry to sample offgas and reactor coolant for gross activity Direct NAO to close Turbine Building Role Plav: When directed to close Turbine Roof Vents, Sidewall Vents and Roll Building Roof Vents, Sidewall Vents and Roll Doors Doors, wait 2 minutes then report the Turbine Monitor ARM'S and rad monitors to Building Roof Vents, Sidewall Vents and Roll Doors determine plant radiation levels are CLOSED. Also report that RP is with you, and Notify SRO/Crew of rising Main Steam they have detected higher than normal rad levels Line Radiation Monitor levels near the offgas piping.
NRC Scenario 1 22 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 6 Continued BOP Continued 0 Notify SRO when MSL Rad Monitors approach/exceed 3.75 X normal NRC Scenario 1 23 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 7 0-7.0 Reactor Scram with failure of one bank of control ZREW rods to fully insert b Recognize and report failure of rods to fully insert The following malfunctions are preset:
RD33C, CONTROL ROD BANK BLOCKEID BANK 3, FINAL VALUE=04 SRO Acknowledge SCRAM report Acknowledge report that control rods failed to insert Directs N1-SOP-1 actions Directs RPV water level controlled 53-95 with Condensate/FW Directs RPV pressure controlled 800-1000 psig with Emergency Condensers RO D Provide scram report D Recognize/ report all control rods not inserted D Perform N1-SOP-1, Reactor Scram, scram verification actions 0 Place IRMs on range 9 0 Insert IRM and SRM detectors 0 Downrange IRMs as necessary to monitor power decrease 0 Reduce Recirc Master flow to 25-43 x I O 6 Ib/hr NRC Scenario 1 24 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE 0PER A T 0R ACTIONS EVENT 7 Continued RO Continued D Attempts to insert control rods using Note: The RO will not be able to reset the scram N1-OP-5, section H.23.0 until RPV pressure is less than 600 psig once the MSIVs are closed. This will likely delay control rod insertion.
BOP Performs N1-SOP-1, Reactor Scram, level control actions:
Restores RPV level to 53-95 inches by controlling injection and rejecting through RWCU, as necessary Determines # I 3 FWP was not running Verifies RPV water level above 53 Verifies 11/12 FWP controllers in MANUAL and set to zero output Resets HPCl signal, if required Places 11/I 2 FWP BYPASS Valve in AUTO, sets to 65-70 inches Secures 2ndFWP, if running If RPV level reaches 85 inches and rising, then:
Verifies off all Feedwater Pumps Secures CRD Pumps not required Maximizes RWCU reject flow Closes FWlVs if required Closes MSlVs if required Maintain RPV water level in assigned band Maintain RPV pressure below 1080 psig and in assigned band Performs N1-SOP-40.2 for Vessel Isolation verification NRC Scenario 1 25 October 2008
INSTRUCTOR ACT1ONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 8 PO-8.0 Failure of Emergency Condenser Tubes CREW Verify the following malfunction is automatically Recognize/report annunciator K1-1-2 inserted when the mode switch is taken to Recognize/report rising EC Vent Rad SHUTDOWN: Monitor readings ECOGA, EMERGENCY CONDENSER TUBE LEAK 111, RAMP=l :OO, FINAL VALUE=4%
TRG 4 Expected Annunciator:
K-1-1-2,EC Rad Vent I I Monitors Rising rad levels on EC Vent Rad Monitor (J panel)
SRO Acknowledges report of annunciator, K-1-1-2, EC Rad Monitors 0 Directs crew to obtain a radiation value from EC VENT RAD Monitors 0 Enters N1-EOP-6 due to EC Vent Rad Monitor above 30 mR/hr (ALERT EAL level) 0 Directdgrants permission for the isolation of 11 Emergency Condenser RO/BOP Role Plav: If requested as RP to check dose rates 0 Reports/responds to annunciator K-I-at EC piping, wait 3 minutes and report dose rates 1-2, EC Rad Monitors are 50 mWhr and rising. Wait another 3 minutes 0 Confirms alarm on computer printout and report dose rates are 200 mR/hr and rising, 0 Confirms radiation levels on J Panel you are leaving the refuel floor to perform 0 Contacts RP to check dose rates at downwind site boundary surveys. EC piping above elevation 340 NRC Scenario 1 26 October 2008
INSTRUCTOR ACTIONS PLANT RESPONSE OPERATOR ACTIONS EVENT 8 Continued RO/BOP Continued 0 Contacts Chemistry to assess for Role Plav: If requested as Chemistry to assess possible unmonitored radiological for possible unmonitored radiological release, release acknowledge request 0 Contacts RP to perform downwind site boundary radiological survey Role Play: If directed as RP/Chemistry to perform 0 Notifies crew of radiation levels a downwind site boundary radiological survey, report that you are assembling and dispatching the team. Wait 4 minutes after the above RP role plays are complete, and then report that the dose rate at the north site boundary is 750 mRern TEDE and rising. Wait another 4 minutes, and if the crew has not entered RPV Blowdown yet, report that the dose rate at the north site boundary is 950 mRem TEDE and rising.
NRC Scenario 1 27 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 9 0-9.0 Emergency Condenser Failure to Isolate CREW When an operator attempts to isolate EC 11, the D Diagnoseheport failure of EC 11 to following preset malfunctions act to prevent isolate steam isolation valve closure:
EC07, EMERGENCY CONDENSER FAILS TO ISOLATE 11 EC08A, EC LOOP 11 STM IV FAIL TO CLOSE I 11 (0-1OO%), FINAL VALUE4 00%
EC08B, EC LOOP 11 STM IV FAIL TO CLOSE 112 (0-loo%), FINAL VALUE=lOO%
SRO Acknowledges Emergency Condenser cannot be isolated Evaluates EAL matrix and determines the rising off site dose rates are approaching GeneraI Emergency levels per section 5.2.6 of EPIP-EPP-01, Emergency Action Level Matrix IF a primary system is discharing outside primary and secondary containments AND the discharge cannot be isolated, THEN before the offsite release rate reches the Emergency Plan General Emergency level:
0 Scram 0 Enter N1-EOP-2, RPV Control 0 Enter N1-EOP-8, RPV Blowdown NRC Scenario 1 28 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 9 Continued 5RO Continued q1-EOP-8. RPV Blowdown actions:
Answers Are all control rods inserted to at least position 04 YES D Answers Drywell pressure? below 3.5 psig D Directs Emergency Condenser 12 initiation B Answers Torus water level? > 8.0 ft m Directs open 3 ERVs CT-2.0 Stops at WAIT block for 120 psig RO/BOP When granted permission or directed, attempts to isolate EC I 1 by closing the following valves:
0 Places control switch for 39-07R3, EC STM ISOLATION VALVE 112 in CLOSE 0 Diagnoses failure of 39-07R to fully close 0 Places control switch for 39-09R, EC STM ISOLATION VALVE 111 in CLOSE 0 Diagnoses failure of 39-09R to fully close 0 Report failure of steam IVs to isolate Initiates Emergency Condenser 12 Places control switches for 3 ERVs to open CT-2.0 NRC Scenario 1 29 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 9 Continued ROlBOP Continued 0 Reports 3 ERVs open Restores and maintains RPV water level 53-95 inches using Condensate/FW and CRD TERMINATING CUE All control rods inserted RPV Blowdown in progress RPV Water Level controlled in i,,, n cI b nd NRC Scenario 1 30 October 2008
V. POST SCENARIO CRITIQUE A. N/A, NRC Exam VI. REFERENCE EVENTS AND COMMITMENTS A. Reference Events
- 1. None B. Commitments
- 1. None VII. LESSONS LEARNED A. None NRC Scenario 1 31 October 2008
ATTACHMENT 7: REACTIVITY MANEUVER INSTRUCTION Reason for Reactivity Maneuver: Reactor Shutdown STEP: 2 I INITIAL CONDlTlONSlSTEP DESCRIPTION I1 RE presence required in the Control Room? Yesl No-/- (check)
L
/Parameter Core Flow 1 Expected Range 39-41 Mlbslhr I L .
Actiial /
Initial Conditions to be verified prior to initiation o f step? Yes No-Parameter 1 (check)
Expected Range I Actual Critical Parameter Limit Monitor Frequency Contingency Core Flow 41 Mlblhr OPS 30 min Reduce core flow to between 39-41 Mlblhr Step Prepared by: John Smith l T&! Step Reviewed by:-Rob Cooper I Todaq RElSTA Date RElSTNSRO Date Approval to perform Step Ed Brown I Today Step Completed by: I Shift Manager Da':e SRO Date Page 23 S-REP3 Rev 03
Appendix D Scerlario Outline Form ES-D-1 Facility: Nine Mile Point 1 Scenario Ncl.: NRC42 Op-Test No.: October 2008 Examiners: Operators:
Initial Conditions: Simulator IC 172
- 1. Reactor Power approximately 90%
- 2. Four Recirculation Loops in service Turnover:
- 1. Recirc Pump 15 MG set has been mpaired and should be returned to service.
- 2. After starting Recirc Pump 15 MG set operate it for one hour while maintenance takes readings before returning to 100% power.
Event Malf. No. Event Event No.
DescriDtion Recirc Pump 15 to service Rod Drive Flow Control Valve 44-151 fails closed, g shifting to the alternate FCV (SOP-5.1) 1 - \ - - - - f I
I I I (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NRC Scenario 2 October 2008
Facility: Nine Mile Point 1 Scenario No.: NRC-02 Op-Test No.: October2008 TARGET QUANTITATIVE ATTRIBUTES (PER SCENARIO; SEE SECTION D.5.d)
- 1. Total malfunctions (5-8)
Events 3,4, 5,6, 8
- 2. Malfunctions after EOP entry (1-2)
Event 8
- 3. Abnormal events (2-4)
Events 3,4,5,6
- 4. Major transients (1-2)
Event 7
- 5. EOPs enteredhequiring substantive actions (1-2)
Events 6 and 7 (EOP-5)
- 6. EOP contingencies requiring substantive 2 actions (0-2)
- 7. Critical tasks (2-3) 3 CRlTlCAL TASK DESCRIPTlONS:
CT-1.0 Given an un-isolable RWCU leak outside primary containment and one general area temperature above the maximum safe limit, the crew will insert a manual reactor scram.
CT-2.0 Given a failure of RPS to de-energize when a scram is required, the crew will insert control rods by initiating manual Alternate Rod Insertion (ARI).
CT-3.0 Given an un-isolable RWCU leak outside primary containment and two general area temperatures above the maximum safe limit, the crew will Derform an RPV Blowdown.
NRC Scenario 2 October 2008
NMP SIMULATOR SCENARIO NRC Scenario 2 REV. 0 No. of Pages: 29 LOSS OF POWERBOARD 11, UNISOLABLE RWCU LEAK IN THE SECONDARY CONTAINMENT PREPARER VAL1DATED Frank Payne, Kyle James, Bruce Williams DATE 5/17/08 GEN SUPERVISOR OPS TRAINING OPERATIONS
-2 DATE g / l 3 f b o r MANAGER N/A - Exam Security DATE CONFIGURAT10N CONTROL N/A - Exam Security DATE SCENARIO
SUMMARY
Length: 90 minutes Initial Power Level: 90%, 4 Loop Operation Mitigating Strategy Code: SCI, unisolable primary system leak in the Secondary Containment, RPV Blowdown required The crew assumes the shift with the plant operating at 90% power and four recirculation loops in service. Immediately after assuming the shift the crew will be directed to restore Recirculation Pump 15 to service and return to full power. The crew will assess plant conditions and lower power with Recirculation Flow until flow is less than 50 Mlbm/hr. They will then return Recirculation Pump 15 to service. After the crew has placed the pump in service, the Main Generator Auto Voltage Regulator will fail. The crew will diagnose the failure and take manual control of generator voltage and restore the correct generator output. When a normal generator output is established, the Control Rod Drive Flow Control Valve fails closed, requiring shifting to the alternate FCV. After CRD flow is returned to normal, a loss of power to Power Board 11 occurs. The SRO will address Technical Specifications.
A Reactor Water Cleanup system line break will occur in the Secondary Containment downstream of the Supply Isolation Valves. Reactor Water Cleanup will fail to isolate on high area temperature. The crew will attempt to isolate the system, but the valves will fail to fully close. This break will require a scram and RPV blowdown due to exceeding the Maximum Safe Value for general area temperatures. When the Mode Switch is placed in SHUTDOWN and/or the Reactor Trip pushbuttons on the E Panel are pushed, the reactor will NOT scram. ARI must be manually initiated to scram the control rods.
NRC Scenario 2 1 October 2008
Major Procedures: N1-SOP-I , N1-SOP-l .I, N1-SOP-I .3, N1-SOP-5. 1, N1-SOP-30.1, N1-EOP-2, N1-EOP-3, N1-EOP-5, and N1-EOP-8 EAL Classification: Site Area Emergency, EALs 3.4.1, 4.1.1 Termination Criteria: All control rods are in, RPV Blowdown in progress, RPV water level controlled in assigned band NRC Scenario 2 2 October 2008
I. SIMULATOR SET UP A. IC Number: IC 172
- 9. Presets/Function Key Assignments
- 1. Malfunctions:
- a. EG02, GENERATOR AUTO VOLTAGE REGULATOR FAILS - INCREASE TRG 1
- d. CU14, CLEANUP ISOLATION VALVES STUCK OPEN PRESET
- f. RP059, REACTOR PROTECTION SYSTEM FAILURE TO SCRAM CH 12 PRESET
- 2. Remotes:
- 3. Overrrides:
- a. OVR-9DS51LO51912 ON 1150 STATUS MOVS ARRAY 33-01 GR CLO, FINAL VALUE=ON TRG 17
- b. OVR-9DS53LO51914 ON 1150 STATUS MOVS ARRAY 33-02 GR CLO, FINAL VALUE=ON TRG 18 C. OVR-9DS55L05200 ON 1150 STATUS MOVS ARRAY 33-04 GR CLO, FINAL VALUE=Ohl TRG 19
- 4. Annunciators:
- a. None
- 5. Triggers:
- a. TRG 16 - Activates when the CRD FCV transfer switch is moved to Valve 12 to automate the corresponding field action
- i. Event Action: zdrdfcvb==l ii. Command: None
- b. TRG 17 - Activates when RLYCU IV 33-01 control switch is taken to close to override on the green light, simulating some valve movement
- i. Event Action: zdcu301c=:=l ii. Command: None
- c. TRG 18 - Activates when RLVCU IV 33-02 control switch is taken to close to override on the green light, simulating some valve movement NRC Scenario 2 3 October 2008
- i. Event Action: zdcu302c=:=I ii. Command: None
- d. TRG 19 - Activates when RWCU IV 33-04 control switch is taken to close to override on the green light, simulating some valve movement
- i. Event Action: zdcu304c=:=1 ii. Command: None C. Equipment Out of Service
- a. RRP 15 removed from service, control witch green flagged, discharge ralve closed D. Support Documentation
- 1. N1-OP-I marked up through step H.4.5
- 2. N1-OP-43B marked up through step 2.7
- 3. RMR for lowering recirc flow to 50 Mlbm/hr
- 4. RMR for power ascension to rated E. Miscellaneous
- 1. Steam Packing Exhauster 12 should be in operation at the beginning of the scenario to prevent the crew from having to swap to this division following a loss of PI3 11.
- 2. Ensure LPRM downscale pushbuttons are depressed on rod block monitor.
NRC Scenario 2 4 October 2008
II. SHI FT TURNOVER INFORMATION OFFGOINGSHIFT: 0 N ID DATE: Today PART I: To be performed by the oncoming Operator before assuming the shift.
0 Control Panel Walkdown (all panels) (SM, CRS, STA, RO, CRE)
PART II: To be reviewed by the oncorning Operator before assuming the shift.
0 Shift Supervisor Log (SM, CRS, STA) 0 Shift Turnover Checklist (ALL) 0 RO Log (RO) 0 LCO Status (SM, CRS, STA) 0 Lit Control Room Annunciators 0 Computer Alarm Summary (RO)
Evolutions/GeneralInformation/Equipment :Status:
0 Load DisDatcher was notified of Dower reduction and RRP 15 start two (2)hours aao
~
PART Ill: RemarkdPlanned Evolutions:
RRP 15 removed from service. TS 3.1.7.e. Four loop operation.
Start RRP 15 per N1-OP-I, H.4.0, and return to five-loop operation. N1-OP-I, H.4.0, signed off up to step 4.6. N1-OP-43E8signed off up to step 2.8.
Reactor power is at 90% and must be lowered until recirc flow e50 Mlbm/hr to support startina RRP 15.
After starting Recirc Pump 15 MG set, operate it for one hour whilemaintenance takes readings before returning to 100% power.
PART IV: To be reviewed/accomplishel3 shortly after assuming the shift:
0 Review new Clearances (SM) 0 Test Control Annunciators (CRE) 0 Shift Crew Composition (SM/CRS)
ATC RO BOP RO NRC Scenario 2 5 October 2008
Scenario ID I
NSTRUCTOR COMMENTS (Strengths, Areas for Improvement, Open Items etc.)
~~
What Happened? What we did? Why? (Goals) 0the r 0ptions?
NRC Scenario 2 6 October 2008
Ill. PERFORMANCE OBJECTIVES A. Critical Tasks:
CT-1.O Given an un-isolable RWCU leak outside primary containment and one general area temperature approaching or exceeding the maximum safe limit, the crew will insert a manual reactor scram, in accordance with N I -
CT-2.0 Given a failure of RP:S to de-energize when a scram is required, the crew will insert control rods by initiating manual Alternate Rod Insertion (ARI),
in accordance with N 1 -EOP-3.
CT-3.0 Given an un-isolable RWCU leak outside primary containment and two general area temperatures above the maximum safe limit, the crew will perform an RPV Blowdown, in accordance with N1-EOP-5 and NI-EOP-8.
B. Performance Objectives:
PO-I .o Given the plant at power, the crew will reduce reactor power with recirculation flow, in accordance with N1-OP-43B.
PO-2.0 Given the plant at power, the crew will return a Recirculation Pump to service, in accordance with N1-OP-I, section H.4.0.
PO-3.0 Given a voltage regulator failure on the main generator, the crew will take manual control of generator voltage, in accordance with N1-ARP-A7.
PO-4.0 Given the plant at power, the crew will respond to a failure of the operating CRD Flow Control Valve, in accordance with N1-SOP-5.1.
PO-5.0 Given the plant at power, the crew will respond to a loss of Powerboard 11, in accordance with N1-SOP-30.1.
PO-6.0 Given the plant at power, the crew will respond to a Reactor Water Cleanup leak outside of the primary containment, in accordance with N I -
NRC Scenario 2 7 October 2008
PO-7.0 Given the plant in a condition requiring emergency classification, the SRO shall classify the events properly, complete initial notification forms, and discuss the bases for the classification in accordance with the emergency plan procedure.
PO-8.0 Given the plant or a plant system in a condition requiring Technical Specification action, identify the deviation and any required actionshotifications.
NRC Scenario 2 8 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS Take the simulator out of freeze before the crew CREW enters for the pre-shift walkdown and briefing. Walkdown panels Allow no more than 5 minutes for panel walkdown. Conduct shift turnover brief Assume the shift EVENT I PO-1.o Power Reduction with Recirculation Flow SRO Note: Provide GAI-OPS-05 Attachment 1, SRO Conduct GAI-OPS-05 Reactivity Brief REACTIVITY BRIEF CHECKLIST (may be done in Reviews Reactivity Maneuver Request pre-scenario brief) and RMR Form Provides direction to ROlBOP regarding assignments RO adjusts recirculation flow BOP monitors RRPs and feed system response Directs RO to lower core flow to 6 0 Mlbm/hr IAW RMR Supervises reactivity maneuver RO Reduces recirc flow IAW RMR Continuously observes the following:
- APRMs lowering
- Recirc flow lowering
- Steam and feedwater flow lowering
- Vessel level normal Lower recirc flow until 6 0 Mlbm/hr Notify Crew of the new power level and that recirc flow is 6 0 Mlbm/hr NRC Scenario 2 9 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT IContinued BOP Monitors individual RRP for response
- Individual M/A-Speed Control stations trending uniformly
- Individual RRP indications trending normally for lowering speed Monitors feed water controls for proper response
- FWP 13 FCV responding to power change RPV Water Level remains within program band (65 - 83)
NRC Scenario 2 10 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 2 PO-2.0 Restore Reactor Recirculation Pump 15 to Service Note: Crew directed to start RRP 15 in pre-brief, starting at N1-OP-1, step H.4.6. Provide thle SRO with the RMR for RRP # I 5 recovery.
SRO Direct start up of RRP 15, using N I -
OP-I, starting at step H.4.6 Supervise reactivity manipulation Acknowledge report that RRP 15 is in service Determine TS 3.1.7.e no longer applies and the LCO Actions can be exited RO Continuously observe the following:
- APRMs
- Recirc flow Monitor P/F map and transfer from 4 loop to 5 loop map when the startup is performed BOP Acknowledge direction to start RRP 15 D Verify recirculation flow c 50 x I O 6 Ib/hr Verify RRP 15 GEMAC in MAN and matched with other four GEMACs but no greater than 50%
Verify RRP 15 discharge valve closed NRC Scenario 2 11 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 2 Continued BOP Continued Verify RRP 15 suction and discharge bypass valves are open Make a plant announcement for start of RRP 15 Place RRP 15 control switch to START and observe indications MG MOTOR starts, Amp Meter Amps increase then decrease MG Generator accelerates to proper speed (approx 50 - 60 Hz)
Generator Field Bkr closes CAUTIONS from N1-OP-I a Generator slows toward 20%
Failure to raise Recirc Pump speed during speed (Approximately 11.5 Hz) opening of discharge valve may result in stalled WHEN speed (Frequency Meter) is rotor and pump trip due to reverse flow. between 30 and 25 Hz, open To Prevent backflow thru the RRP, discharge REACTOR R PUMP DISCH VALVE valve should be opened before MG frequency Verify RRP 15 maintained less than or lowers to 20 Hz. Frequency will raise, then drop equal to OP limits quickly, then raise again before SL0WL.Y Adjust pump speed to match other lowering. Discharge BV should be openled Pumps when frequency is slowly lowering. Null RRP 15 controller and shift to BAL or AUTO Verify power/flow map updated to five loop requirements Dispatch NAO to reset 50SR Pump Role Play: As NAO sent to Aux Control Room, Motor Stalled Rotor Target (Aux wait one minute then report you have reset 50SR Control Room)
Pump Motor Stalled Rotor Target Dispatch NAO to check MG set oil temperature locally Role Play: As NAO, when requested report MG May perform N1-ARP-F2-1-5 action to set oil temperature is 120°F and stable.
depress PUMP MOTOR VIBRATION RESET pushbutton on F Panel, clearing annunciator F2-1-5 NRC Scenario 2 12 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 3 PO-3.0 Main Generator Auto Voltage Regulator Failure CREW Recognize/diagnose Auto Voltage After RRP 15 has been placed in service arid when Regulator Failure from:
directed by the examiner, insert malfunction: Amplidyne output meter will peg HI Exciter output voltage will peg HI EG02, GENERATOR AUTO VOLTAGE Generator field current will peg HI REGULATOR FAILS - INCREASE Generator mVars and terminal voltage TRG I will respond accordingly Amplidyne output meter will peg HI Annunciator A7-2-6, GEN VOLT Exciter output voltage will peg HI REGULATOR TRIP Generator field current will peg HI Expected Annunciators:
A3-1-1, TURB GEN EXC. TRANS. I TEMP RECORDER (first)
A7-2-6, GEN VOLT REGULATOR TRIP (later)
SRO 0 Acknowledge report from the crew 0 Directkupervise ARP response 0 Acknowledge voltage regulator transferred to OFF 0 Notify Power Control (National Grid)
Role Play: When contacted as Power Coritrol that the voltage regulator is in manual (National Grid), acknowledge the voltage regulator control (required within 30 minutes) in OFF and request NMPI supply 60 MVAFS to 0 Direct CSO to adjust reactive load to the bus while in manual voltage control 60 MVARS to bus RO e Execute N1-ARP-A7-2-6 for voltage regulator trip 0 Confirm computer point FO99 NRC Scenario 2 13 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 3 Continued RO Continued Monitor generator output voltage 0 Place VOLTAGE REG TRANSFER switch to OFF 0 Notify Crew/SRO 0 Coordinate with SRO to contact Power Control 0 Acknowledge direction to adjust VARS from the SRO 0 Adjust generator reactive load using exciter field rheostat to 60 MVARS to the bus (NI-OP-32)
BOP 0 Monitor plant parameters 0 Monitor Turbine and Generator parameters on the A Panel NRC Scenario 2 14 October 2008
I NSTRUCTOR ACT1ONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 4 PO-4.0 CRD Flow Control Valve Failure CREW When actions for the voltage regulator failure are D Acknowledge/report annunciator F3 complete and when directed by the examiner, 5, CRD CHARGING WTR PRESS insert malfunction: HI/LO Diagnose CRD FCV 11 is closed RD36A, CRD FCV 44-151 FAILURE - CLOSED TRG 2 CRD charging water pressure rises CRD drive water pressure lowers CRD cooling water pressure and flow lower-Expected Annunciator:
F3-1-5, CRD CHARGING WTR PRESSURE HI/LO SRO 0 Acknowledge report from the crew 0 Direct entry into N1-SOP-5.1, LOSS OF CRD 0 Acknowledge report that CRD FCV has failed 0 Acknowledge report that CRD FCV has been shifted and is in AUTO 0 Enter Technical Specifications 3.1.6.b, 7 day LCO for loss of CRD FCV 44-151 RO D Monitor plant parameters NRC Scenario 2 15 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 4 Continued BOP D Acknowledge direction from SRO D Execute N1-SOP-5.1 D Answers Is a CRD pump operating YES D Determines need to switch CRD Flow Control Valves per N1-OP-5 Section Role Plav: As NAO, when directed to transfer F.5.0:
CRD FCV, wait 1 minute and inform the control Dispatch NAO to report to RB 237 room that you are standing by and establish communications Place CRD Flow Control in MAN Role Plav: As NAO, when directed to open 44- Direct NAO open 44-148 and 44-152 148 and 44-152, wait 1 minute and report task Direct NAO to count-down to place completion RB air transfer switches in UP position while you place CRD FCV transfer Role Plav: As NAO, when directed to countdown switch in VALVE 12 position at F and swap transfer switch, give simulated panel countdown and report task completion (see note 0 Places CRD FCV transfer switch in below), as required VALVE 12 position 0 Direct NAO close 44-150 and 44-153 Note: When the control room operator taklss the 0 Monitor flow CRD Flow Control Transfer Switch to VALdE 12 0 Place CRD Flow Control in AUTO TRG 16 will automatically insert remote:
RD05, CRD FLOW CONTROL VALVE ISCbL, FINAL VALUE=nc30b TRG 16 This precludes the console operator from having to time the insertion of this remote.
Role Plav: As NAO, when directed to close 44-150 and 44-153, wait 1 minute and report tiask completion.
NRC Scenario 2 16 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 5 PO-5.0 Loss of Powerboard 11 CREW When directed by examiner, insert malfunction: Respond to annunciators and equipment trips ED04, AC POWER BOARD ELECTRICAL Diagnoseheport loss of PB 11 FAULT(PB11) Recognizeheport loss of the following:
TRG 3 0 Reactor Recirculation Pumps 11 &
Expected Annunciators: 12 A4-1-1, PB I 1 R113 TRIP 0 Drywell fans 14, 15, 16 LI-3-4, REACT BLDG/ATM DlFF PRESS 0 Condensate Pump 11 Also the following equipment trips: 0 Feedwater Booster Pump 11 Reactor Recirculation Pumps 1I & 12 0 Feedwater Pump 11 Drywell fans 14, 15, 16 0 Circulating Water Pump 11 Condensate Pump I 1 0 Service Water Pump 11 Feedwater Booster Pump 11 0 RBCLC Pump 11 Feedwater Pump I I 0 TBCLC Pump 11 Circulating Water Pump I I 0 Reactor Building Exhaust Fan 11 Service Water Pump 1I Recognize/report drop in reactor RBCLC Pump I 1 power TBCLC Pump I 1 Recognizeheport lowering condenser Reactor Building Exhaust Fan I I vacuum Recognize/report loss of Reactor Building D/P SRO Acknowledge report from crew Direct entry into N1-SOP-30.1 Direct and supervise power reduction per N1-SOP-1.1 Emergency Power Reduction to stabilize condenser vacuum, as necessary Direct entry into N1-SOP-1.3 Recirculation Pump Trip, as required NRC Scenario 2 17 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 5 Continued SRO Continued D Direct closure of Recirc Pump 11 & 12 Discharge Valves D Direct RO to re-energize PB16A and 13A-15A Enter N1-EOP-5 on loss of Reactor Building Ventilation (positive pressure in RB)
Direct entry into N1-SOP-6.1 for loss of spent fuel pool cooling pump, as time permits a Review Technical Specifications a Acknowledge that the APRMs are inoperable while the RRP discharge valves are still open 0 Determine that TS 3.1.7e Partial Loop Operations, 3 loop limitations need to be checked by Reactor Engineering Limited to 90% power in 3 loop operations a 2% MCPR penalty must be applied per COLR 0 Determine that TS 3.1.8 for HPCl operability is a 15 day LCO a Review N1-OP-19 Section H.7.0 for operation exceeding SPDES permit, as time permits 0 Direct further power reduction as necessary for compliance with SPDES permit NRC Scenario 2 18 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 5 Continued RO Acknowledge direction from SRO Confirm plant is stable by verifying:
- No thermal hydraulic Instability
- 3 Recirc pumps running
- Not operating in the Restricted Zone rn Execute N1-SOP-I .I, Emergency Power Reduction, to lower recirc flow to stabilize condenser vacuum, as required Determine plant operating point on the 3-lOOp power to flow curves BOP Execute N1-SOP-30.1, Loss of Power Board 11 Start Service Water Pump 12 Verify TBCLC pump 12 running Verify IAC 12 and/or 13 running Verify RBCLC pump(s) running Verify Steam Packing Exhauster 12 running Answers Are A4-4-6, A4-4-7, A4-1-3 OR A5-2-8 in alarm YES Determines Power Board 11 is faulted and cannot be reenergized Restores power to Power Board 16A as follows:
Opens R1041 Closes R1042 Verifies Power Board 16B amps
<962 NRC Scenario 2 19 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE 0PERATOR ACT10NS EVENT 5 Continued BOP Continued Dispatch NAO to reenergize Power Role Play: As NAO when directed to energize Boards 13A, 14A, and 15A PBI 3A-I5A, acknowledge order, but delay any Notify SRO that APRMs are action inoperable Close Recirc Pump 11 & 12 Discharge Valves Hold open for 2-3 seconds Recirc Pump 11 & 12 Discharge Valves Execute N1-SOP-I .3, Recirc Pump Trip, as required Role Plav: As NAO when directed to restore Dispatch NAO to restore Offgas offgas vacuum pump, acknowledge order, but Vacuum Pump delay any action Enter N1-SOP-6.1 for loss of spent fuel pool cooling, as time permits Role Plav: As NAO when directed to investigate Dispatch NAO to investigate loss of spent fuel pool cooling, acknowledge order, but spent fuel pool cooling, as time delay any action permits May take action to restore Turbine Building Ventilation in accordance with either N1-ARP-L1-2-3 or N1-OP-26 Respond to either annunciator:
L1-1-5, RB VENT EXH FAN 11-12 TRIP - VIB o Verify closed Reactor Building Exhaust Fan 11 outlet damper o Start Reactor Building Exhaust Fan 12 L1-3-4, REACT BLDGIATM DlFF PRESS o Start RBEVS per N1-OP-10 NRC Scenario 2 20 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 5 Continued BOP Continued Possible actions in N1-OP-I 0 Section H.l .O to start RBEVS Verify open 202-36, EM VENTILATION FROM REACTOR BLDG BV Verify closed the following valves:
202-47, EM VENTILATION TIE BV 202-74, EM VENTILATION LOOP 11 COOLING BV 202-75, EM VENTILATION LOOP 12 COOLING BV Notify Rad Protection, the Reactor Role Play: As RP, acknowledge report that Building Emergency Ventilation RBEVS is in service and RBVS is secured system will be placed in service Place 202-37(38), EM VENTILATION LOOP 11(12) INLET BV control switch to OPEN Verify open 202-37(38), EM VENTILATION LOOP 1l(12) INLET BV Start 202-53(33), EVS FAN 1l(12)
Verify open 202-34(35), EM VENT EXHAUST FAN 1l(12) OUTLET BV Confirm proper operation of 202-50(51), EM VENT EXHAUST FAN 1I(12) INLET FCV, by observing indicating lights and flow indication NRC Scenario 2 21 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENTS 6 , 7 and 8 PO-6.0, 7.0 RWCU Leak in the Secondary Containment and CREW failure of the Mode Switch and RPS Pushbuttons to Acknowledge/report:
cause a scram 0 L1-3-3, CONTIUOUS AIR RAD MONITOR When directed by examiner, insert malfunction: HI-4-8, AREA RADIATION MONITORS C u l l , COOLANT LEAK OUTSIDE OF K3-3-4, CLEAN-UP SYS LEAK DRYWELL, RAMP TIME=10:00, FINAL AREA T HI VALUE=20% Diagnose leak from RWCU into TRG 4 secondary containment Expected Annunciators: Diagnose RWCU failed to isolate Ll-3-3, CONTINUOUS AIR RAD MONITOR H 1-4-8, AREA RADIA TlON MONITORS K3-3-4, CLEAN-UP SYS LEAK AREA T HI The following malfunction is preset:
RPOSB, REACTOR PROTECTION SYSTEM FAILURE TO SCRAM CHI2 PRESET RPS Ch 12 lights do not extinguish Control rods do not insert based on automatic or manual scram signals Control rods insert once ARI is manually in,itiated NRC Scenario 2 22 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENTS 6 , 7 and 8 Continued 5RO Acknowledges report from the crew Enters N1-EOP-5 Directs RWCU system isolation Acknowledges report that RWCU failed to isolate both automatically and manually Directs dispatching of an NAO and RP Tech to obtain general area temperatures and radiation levels in the Reactor Building When Reactor Building Ventilation exhaust radiation exceeds 5 mR/hr, then directs verification of RB Vent isolation and RBEVS initiation Requests report on ARMS Determines area temperatures and radiation levels are above setpoints in Tables T and R, and transitions to circle 27 Determines a primary system is discharging into the reactor building and the discharge cannot be isolated, and transitions to circle 28 Before any area temperature or radiation level reaches 135°F or 8 Whr, respectively:
Directs manual scram and N1-SOP-1 execution CT-1.O Acknowledges scram report Acknowledges electrical failure to scram NRC Scenario 2 23 October 2008
I NSTRUCTO R ACT10NS/
PLANT RESPONSE OPERATOR ACTIONS EVENTS 6 , 7 and 8 Continued SRO Continued Enters N1-EOP-2 due to power above 6% when a scram is required Answers All rods in to at least 04?
NO Answers Will the reactor stay shutdown without boron? NO Note: Execution of the N1-EOP-3 steps listed here Exits N1-EOP-2, enters N1-EOP-3 may be bypassed if the crew manually initiates ARI Directs ADS bypassed immediately upon the electrical failure to sc:ram Directs Core Spray jumpers installed per N1-EOP-1 Attachment 4 Directs manual ARI CT-2.0 Acknowledges new scram report Acknowledges all rod in Exits N1-EOP-3, enters N1-EOP-2 Assigns RPV level band 53 to 95 inches using Condensate/Feedwater Directs RPV pressure maintained
~ 1 0 8 psig 0 using Turbine Bypass Valves May direct anticipatory blowdown with Turbine Bypass Valves and Emergency Condensers with cooldown in excess of 1OOF/hr Acknowledges reports of Reactor Building temperatures and radiation levels When report is received that 2 General Areas temperatures are above 135OF, enters N1-EOP-8, RPV Blowdown Answers Are all control rods inserted to at least position 04 YES NRC Scenario 2 24 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENTS 6 , 7 and 8 Continued SRO Continued 0 Answers Drywell pressure? c3.5 Psig 0 Directs initiation of Emergency Condensers 0 Answers Torus water level? >8 ft 0 Directs open 3 ERVs CT-3.0 RO Acknowledge direction from the SRO Rotate reactor mode switch to shutdown CT-1.O Recognizes/reports RPS CH 12 does not deenergize and control rods do not insert Depresses RPS CH 12 scram pushbutton Recognizes/reports RPS CH 12 does not deenergize and control rods do not insert Provide scram report
- Mode Switch in SHUTDOWN
- Control rods NOT all in When ARI is initiated, notify Control Room all rods are IN Provides scram report Perform N1-SOP-I , Reactor Scram, scram verification actions 0 Places IRMs on range 9 Inserts IRM and SRM detectors Downranges IRMs as necessary to monitor power decrease NRC Scenario 2 25 October 2008
1 1 INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENTS 6 , 7 and 8 Continued RO Continued 0 Reduces Recirc Master flow to 25-43 x I O 6 Ib/hr 0 Control RPV pressure 4 0 8 0 psig using Turbine Bypass Valves 0 If directed to perform anticipatory depressurization
- Open all bypass valves using BOJM
- Report all bypass valves open
- Initiate Emergency Condensers Note: No General Area temperature information is BOP available until an operator has been dispatched to 0 Attempts to isolate RWCU the Reactor Building to monitor area temperatures. 0 Closes33-02R, CU SUPPLY The following timeline of field reports may ble ISOLATION VALVE 11 (INSIDE) adjusted by examiner as necessary for evaliJation 0 Informs SRO that 33-02R, CU Supply purposes. Isolation Valve 11 has failed to fully close Role Plav: When directed as NAO and RP Tech 0 Closes33-04R, CU SUPPLY IS0 VLV to obtain general area temperatures and radiation 12 (OUTSIDE) levels in the Reactor Building: 0 Informs SRO that 33-04R, CU Supply Isolation Valve has failed to fully close Wait 4 minutes and report RB 261' east side Closes33-01R, CU RETURN IS0 temperature is 125OF and rising, radiation level is VLV 25 mr/hr and rising. Informs SRO that 33-01R, CU RETURN Isolation Valve has failed to Note: When one general area temperalure is fully close reported above 135OF and a second general Dispatches NAO and RP Tech to area temperature is reported as approaching obtain Reactor Building general area 135'F, the crew is likely to perform an temperatures and radiation levels anticipatory blowdown per N1-EOP-2 NRC Scenario 2 26 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENTS 6 , 7 and 8 Continued BOP Continued 0 If directed during N1-EOP-3 execution Role Plav Continued: - Bypasses ADS Wait an additional 3 minutes and report RB 261 - Prevents Core Spray Injection east side temperature is 14OoFand rising, radiation - Initiates Manual ARI level is 30 mr/hr and rising; RB 281 east side CT-2.0 temperature is 120°F and rising, radiation level is 0 Performs N1-SOP-?, Reactor Scram, 20 mr/hr and rising. level control actions:
0 Restores RPV level to 53-95 inches Note: When 2 general area temperatures are by controlling injection and rejecting reported above 135OF, the crew will perform an through RWCU RPV Blowdown 0 Determines # I 3 FWP running and RPV water level recovering Wait an additional 3 minutes and report RB 281 0 Verifies at least one Electric FW east side temperature is 140°F and rising, radiation Pump running level is 30 mr/hr and rising 0 Terminates 13 FWP injection as follows:
0 Places FWP 13 VALVE CONTROL in MANUAL AND closes 0 Disengages 13 FWP 0 Gives 29-10, FEEDWATER PUMP 13 BLOCKING VALVE, a CLOSE signal 0 Verifies RPV water level +53 inches and rising 0 Verifies 11/12 FWP controllers in MANUAL and set to zero output 0 Resets HPCl signal Places 11/12 FWP BYPASS Valve in AUTO, sets to 65-70 inches 0 Verifies level stable AND secures 2nd FWP, if running NRC Scenario 2 27 October 2008
I NSTRUCTOR ACT1ONSl PLANT RESPONSE OPERATOR ACTIONS EVENTS 6 , 7 and 8 Continued BOP Continued If RPV level reaches 85 inches and rising, then:
0 Verifies off all Feedwater Pumps 0 Secures CRD Pumps not required 0 Maximizes RWCU reject flow 0 Closes FWlVs if required 0 Closes MSlVs if required Maintain RPV water level in assigned band Notifies crew of reports on general area temperatures and radiation levels When N1-EOP-8, RPV Blowdown, is entered:
0 Initiates Emergency Condensers Opens3ERVs CT-3.0 TERMINATING CUE:
0 RPV Blowdown in progress 0 All control rods are in 0 RPV water level controlled in assigned band NRC Scenario 2 28 October 2008
V. POST SCENARIO CRITIQUE A. N/A, NRC Exam VI. REFERENCE EVENTS AND COMMITMENTS A. Reference Events
- 1. None B. Commitments
- 1. None VII. LESSONS LEARNED A. None NRC Scenario 2 29 October 2008
ATTACHMENT 7: FlEACTlVlTY MANEUVER INSTRUCTION Reason for Reactivity Maneuver: Recover Reactor Recirculation Pump #I 5 STEP: 1 DESCRIPTION RE presence required in the Control Room? Yes-+ No (check)
No_/- (check)
Expected Range Description of Step:
- 1. Reduce recirculation flow to approximately 50 Mlb/hr.
- 2. Recover reactor recirculation pump # 15 in accordance with N1-OP-I .
- 3. Raise recirculation flow to reach 100% rated thermal power.
Critical Parameter Limit Monitor Frequency Contingency -
None Step Prepared by:Jhn Smith I Todaq Step Reviewed by: Bob Cooper I Todaq REISTA Date REISTNSRO Date Approval to perform Step Ed Brown I Today Step Completed by: I Shift Manager Date SRO Date Page 23 S-REP-3 Rev 03
Appendix D Scenario Outline Form ES-D-1 Facility: Nine Mile Point 1 Scenario No.: NRC43 Op-Test No.: October 2008 Examiners: Operators:
Initial Conditions: Simulator IC 173
- 1. Reactor Power approximately 100% (CRD Pump 12 must be in service)
Turnover:
- 1. Turbine Surveillance Testing, NI-PM-Q7, to be performed
- 2. Feed Pump 12 is out of service because of a burned out motor pump to auto start en the turbine trips,
. - PBI 1 and 12 fail to transfer (SOP-I I 30.1, SOP-30.2)
I I cso3c I I Spray I:~I faits to start L
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NRC Scenario 3 October 2008
Facility: Nine Mile P o i n t l Scenario TARGET QUANTITATIVE ATTRIBUTES ACTUAL (PER SCENARIO: SEE SECTION D.5.d) ATTRIBUTES
- 1. Total malfunctions (5-8) 7 Events 2,3,4,5,6,8,9
- 2. Malfunctions after EOP entry (1-2) 2 Events 8 , 9
- 3. Abnormal events (2-4) 6 Events 2, 3,4, 5, 6, 8
- 4. Major transients (1-2) 1 Event 7
- 5. EOPs enteredhequiring substantive 2 actions (1-2)
- 6. EOP contingencies requiring substantive actions (0-2)
Events 7 , 9 (EOP-2 Alternate Level Leg, EOP-8)
- 7. Critical tasks (2-3)
CRITICAL TASK DESCRIPTIONS:
CT-1.O Given a LOCA with a loss of high pressure injection, the crew will execute N1-EOP-8, RPV Blowdown when RPV water level drops below -84 inches.
CT-2.0 Given a LOCA with a loss of high pressure injection and Core Spray, the crew will inject to the RPV with Condensate and Feedwater Booster pumps.
CT-3.0 Given a LOCA in the Drywell, the crew will initiate Containment Sprays to
- prevent exceeding PSP.
NRC Scenario 3 October 2008
NMP SIMULATOR SCENARIO NRC Scenario 3 REV. 0 No. of Pages: 35 LOSS OF POWERBOARD 103, FEEDWATER PROBLEMS, LOCA WITH LOSS OF HIGH PRESSURE INJECTION, RPV BLOWDOWN REQUIRED TO RESTORE RPV WATER LEVEL PREPARER VALIDATED DATE 5/17/08 GEN SUPERVIS OPS TRAINING DATE &-
OPERATIONS MANAGER DATE CONFIGURATION CONTROL NIA - Exam Security DATE SCENARIO
SUMMARY
Length: 90 minutes Initial Power Level: Approximately 1OO%, above 100% rodline Mitigating Strategy Code: RL2, Small LOCA, RPV Blowdown required to permit injection with low presisure systems to recover RPV water level above TAF
SUMMARY
The crew assumes the shift with the plant at 100% power with Feedwater Pump 12 under clearance for maintenance. The crew will perform N1-PM-Q7, Turbine Thrust Bearing Test from the Control Room. Next, APRM 13 fails. The crew will bypass the APRM and reset the half scram. Next, Powerboard 103 trips on fault. The crew will take action to secure EDG 103 and attempt to restore Powerboard 17B. F'owerboard 103 and Powerboard 17B are both faulted and are not restored. The trip of CliD Pump 12 (PB 17B) will require starting CRD Pump 11 and the SRO must address Technical Specifications.
When the necessary steps for the loss of Powerboard 103 are completed, Feedwater Booster Pump 11 will trip with a failure of the standby pump to start. The standby pump can be manually started. The SRO must again address Technical Specifications. When the standby Feedwater Booster Pump is manually started, the Master Feedwater Controller will fail as-is.
RPV water level will slowly deviate from the set level. The crew must diagnose the failure and the BOP operator will be required to take nianual control of RPV water level. With RPV water level in manual control, Feedwater Pump 11 will trip because of delayed effects from the earlier NRC Scenario 3 1 October 2008
Feedwater Booster Pump trip. This will require an entry into N1-SOP-1. I , Emergency Power Reduction to lower power to within the capacity of Feedwater Pump 13.
While troubleshooting the electrical faults and troubles with the Feedwater system, the crew recognizes a coolant leak in the containment. Drywell pressure and temperature rise, requiring the crew to insert a manual SCRAM on rising drywell pressure. When the turbine trips, Powerboards 11 and 12 fail to automatically transfer. This results in a loss of feedwater, condensate, circulating water and other loads. Operators are able to restore these power boards. RPV water level continues to drop with only one liquid poison pump and CRD pump 11 available for injection. The crew will determine they cannot restore and maintain RPV water level above -109 and enter N1-EOP-8, RPV Blowdown. While blowing down the crew must diagnose that the inboard IV for Core Spray 111 fails to open and Core Spray pump 121 fails to start. With Core Spray unavailable for injection, the crew will inject with the feedwater booster pumps using N1-EOP-1, Att 25 or 26.
Major Procedures: N1-SOP-1, N1-SOP-1.1, N1-SOP-5.1, N1-SOP-16.1, N1-SOP-30.1, N I -
SOP-30.2, N1-EOP-I, N1-EOP-2, N1-EOP-4, N1-EOP-8 Termination Criteria: RPV Blowdown in progress, RPV water level above TAF and controlled in assigned band, containment pressure controlled in accordance with N1-EOP-1 Att 17 EAL Classification: Alert, EAL 3.1. I NRC Scenario 3 2 October 2008
I. SIMULATOR SET UP A. IC Number: IC 173 B. Presets/Function Key Assignments
- 1. Malfunctions:
- a. FWO3B, FEEDWATER PUNlP TRIP 12 PRESET
- h. CUOl, COOLANT LEAK INSIDE OF DRYWELL, RAMP TIME=10:00, FINAL \'ALUE=40% TRG 6
- i. ED26, FAILURE OF PBI 1 TO AUTO TRANSFER PRESET
- j. ED27,FAILURE OF P0?2TO AUTO TRANSFER PRESET
- k. CSOlC, CORE SPRAY PUMP TRIP 121 PRESET I. CSO3C, CORE SPRAY INBC) INJECT VLV FAIL TO OPEN 40-1 1 PRESET
- 2. Remotes:
- c. FW24, REMOVAL OF HPCl FUSES FUWFU9, FINAL VALUE=PULL TRG 26
- 3. Overrides:
- a. OVR-7S43D14116 POS-3 4H17/51-02A C FRM B, FINAL VALUE=OFF PRESET
- 4. Triggers:
- a. TRG 4 - Fails Feedwater Pump 13 FCV as-is when Feedwater Booster Pump 12 control switch is taken to start
- i. Event Action: zdfwbncb==l ii. Command: None
- 5. Equipment Out of Service:
D. Support Documentation
- 1. Nl-PM-Q7, QUARTERLY MAIN TURBINE THRUST BEARING AND GENERATOR CORE MONITOR TESTING, signed off through step 6.1, up to step 6.2 (Note 6.1 is N/A if you perform 6.2)
E. Miscellaneous
- 1. Verify CRD pump 12 is in service
- 2. Place protected equipment signs NRC Scenario 3 4 October 2008
II. SHIFT TURN OVER INFORMATION
~~~~ ~
PART I: To be performed by the oncoming Operator before assuming the shift.
0 Control Panel Walkdown (all panels) (!SM, CRS, STA, RO, CRE)
PART II: To be reviewed by the oncoining Operator before assuming the shift.
Shift Supervisor Log (SM, CRS, STA) Shift Turnover Checklist (ALL)
RO Log (RO) LCO Status (SM, CRS, STA) 0 Lit Control Room Annunciators Computer Alarm Summary (RO)
Evolutions/General Information/Equipment Status:
Power is approximately 100%.
Turbine Surveillance Testing, N1-PM-Q7, to be performed.
Feed Pump 12 is out of service because clf a burned out motor. (TS 3.1.8,day 2 of 15)
~~ ~~ ~~~
PART Ill: Remarks/Planned Evolutions:
Perform Nl-PM-Q7, QUARTERLY MAIN TURBINE THRUST BEARING AND GENERATOR CORE MONITOR TESTING, section 6.2.
PART IV: To be reviewedlaccomplished shortly after assuming the shift:
Review new Clearances (SM) 0 Test Control Annunciators (CRE)
Shift Crew Composition (SM/CRS)
ATC RO BOP RO NRC Scenario 3 5 October 2008
Scenario ID I NSTRUCTOR COMMENTS (Strengths, Areas for Improvement, Open Items etc.)
What Happened? What we did? Why? (Goals) Other Options?
NRC Scenario 3 6 October 2008
Ill. PERFORMANCE OBJECTIVES A. Critical Tasks:
CT-I .O Given a LOCA with ii loss of high pressure injection, the crew will perform an RPV Blowdown when RPV water level drops below -84 inches, in accordance with N1-EOP-8.
CT-2.0 Given a LOCA with ii loss of high pressure injection and Core Spray, the crew will inject to the RPV with Condensate and Feedwater Booster pumps, in accordance with N1-EOP-2.
CT-3.0 Given a LOCA in the Drywell, the crew will initiate Containment Sprays to prevent exceeding PSP, in accordance with N1-EOP-4.
B. Performance Objectives:
PO-1.o Given the plant operating at power, the crew will perform Main Turbine Thrust Bearing wear testing, in accordance with Nl-PM-Q7.
PO-2.0 Given a failed APRM, the crew will bypass the APRM and reset the half scram, in accordance with N1-ARP-F1.
PO-3.0 Given the plant operating at power, the crew will respond to a loss of a Powerboards 103 anld 17B, in accordance with N1-ARP-A5.
PO-4.0 Given the plant operating at power, the crew will respond to a loss of the operating CRD pump, in accordance with N 1-ARP-A5 or N1- S O P 4 1.
PO-5.0 Given a trip of Feedwater Booster Pump 11 and a failure of the standby pump to automatically start, the crew will start the standby pump, in accordance with Nl-ARP-H3.
PO-6.0 Given a failed Feedwater flow control valve, the crew will take manual control to stabilize RFW water level, in accordance with N1-SOP-16.1.
PO-7.0 Given a loss of the operating motor driven feedwater pump, the crew will lower power to within the capacity of the turbine driven feedwater pump, in accordance with N 1 -SOP-I 6.1 and N1-SOP-I . I .
PO-8.0 Given a LOCA within the Drywell, the crew will scram the reactor, in accordance with N1-SOP-I.
PO-9.0 Given a failure of Powerboards 11 and 12 to automatically transfer following a Main Turbine trip, the crew will manually transfer the Powerboards, in accclrdance with N1-SOP-30.1 and N1-SOP-30.2.
PO-10.0 Given the plant in a condition requiring emergency classification, the SRO shall classify the events properly, complete initial notification forms, NRC Scenario 3 7 October 2008
and discuss the bases for the classification in accordance with the emergency plan procedure.
PO-I 1.O Given the plant or a iplant system in a condition requiring Technical Specification action, identify the deviation and any required actionshotifications.
NRC Scenario 3 8 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS Take the simulator out of freeze before the crew CREW enters for the pre-shift walkdown and briefing. D Walkdown panels Allow no more than 5 minutes for panel walkdown. B Conduct shift turnover brief D Assume the shift EVENT 1 PO-1.o Perform N1-PM-Q7, Turbine Thrust Bearing Test There are no simulator actions required for this test and no malfunctions are intended to occur SRO 0 Directs the BOP to perform N1-PM-Q7, Quarterly Main Turbine Thrust Bearing and Generator Core Monitoring Testing, Sect 6.2, Thrust Note: Pre-job brief may be conducted prior to the Bearing Wear Test from the Control crew entering the simulator to facilitate scenario Room run-time. 0 Perform a pre-job brief RO 0 Monitors plant parameters BOP Acknowledges direction to perform turbine surveillance testing from the SRO Notifies RO of intention to perform the test Places THRUST BRG WEAR TEST SOLENOID switch in TEST NRC Scenario 3 9 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE 0PERATO R ACT10NS EVENT I Continued BOP Continued Confirms the following:
- Yellow TEST MODE 43XKBWT light illuminates
- Annunciator A2-3-3 actuates e Rotates and holds TBWT Motor switch to + READING position, until Annunciator A2-3-4 actuates e Continues holding TBWT Motor switch to + READING position until POS light is lit then records reading at which trip occurred e Rotates and holds TBWT Motor switch to - READING position until meter is zeroed, then releases switch e Confirms Annunciator A2-3-4 clears e Rotates and holds TBWT Motor switch to - READING position, until Annunciator A2-3-4 actuates e Continues holding TBWT Motor switch to - READING position until NEG light is lit then records reading at which trip occurred e Rotates and holds TBWT Motor switch to + READING position until meter is zeroed, then releases switch 0 Confirms Annunciator A2-3-4 clears e Direct the NAO at the middle standard to verify:
- Trip lights (front and rear) NOT Role Plav: As NAO, when directed, report 1:hatthe illuminated trip lights are NOT illuminated and the test handle - Test handle in normal (ZERO) is in the normal (ZERO) position at the middle position standard NRC Scenario 3 10 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 1 Continued BOP Continued Place THRUST BRG WEAR TEST SOLENOID Switch to OFF Confirm YELLOW TEST MODE 43XTTBWT light is OFF Direct the NAO at the middle standard Role Plav: As NAO, when directed, report that the of to verify TEST light NOT illuminated test light is NOT illuminated at the middle standard Confirm Annunciator A2-3-3 clears Verify reset, Flag Target 30/1 and Cue: If required inform the BOP that the flags on 30/2 on Panel B-3 3011 and 30/2 are reset Notifies SRO/RO that the Turbine Thrust Bearing test has been successfully completed NRC Scenario 3 11 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 2 PO-2.0 APRM 13 Inoperative Failure CREW When directed by the examiner, insert 0 Acknowledge/Report Annunciators:
malfunction: 0 F2-1-6, APRM I1-14 0 F3-4-4, ROD BLOCK NM21C, APRM 13 FAILURE - INOP 0 F1-1-1, RPS CH 11 NEUTRON TRG 1 MONITOR 0 F1-2-1, RPS CH 11 AUTO REACTOR Expected Annunciators:
TRIP F2-1-6, APRM 11-14 0 Diagnose failure of APRM 13 F3-4-4, ROD BLOCK F1-1-1, RPS CH 11 REACT NEUTRON MONITOR F1-2-1, RPS CH I 1 AUTO REACTOR TRIP SRO Role Play: If requested to investigate the failure of 0 Determines APRM 13 is INOP APRM 13, reply that you will investigate. 0 Contacts WWM to request troubleshooting for APRM 13 0 References TS 3.6.2.a, determines the Minimum Number of Operable Channels per Trip System is met RO 0 Monitors plant parameters 0 When directed bypasses APRM 13
- Places APRM BYPASS switch in BYPASS position
- Confirms APRM BYPASS light is ON on Panel E 0 Resets the half scram BOP 0 Investigates APRM 13 failure NRC Scenario 3 12 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 3 PO-3.0, 4.0 PB 103 and PB 178 trip on fault, loss of CRD CREW Pump 12 Acknowledge/report annunciators When directed by examiner, insert malfunctions: Recognize/report the following:
Loss of PB 103 and PB 17B ED08, AC POWER BOARD ELECTRICAL. EDG 103 started but not supplying PB FAULT(PBIO3) 103 TRG 2 R1013 tripped (PB 103 normal supply)
ED21, AC POWERBOARD ELECTRICAL R1053 tripped (PB 17B normal supply)
FAULT(PB17 SECTION B) 0 Recognize/diagnose loss of CRD TRG 2 Major Expected Annunciators A5-3-5, DSL GEN 103 START-RUN OFFNORMAL A5-3-7, POWER BD. 17 R1053 TRIP A5-4-7, POWER BD 17 LOW BUS VOLTAGE A5-4-3, POWER BD 103 BUS VOLTAGE LOW The following major loads will be lost as a result of the loss of PB 103 and PB 176:
Core Spray Pumpflopping Pumps 11W122 Containment Spray Pumps 12I / ?22 Static Batt Charger 171NB RPS UPS 172NB ESW Pump 12 CRD Pump 12 RBCLC Pump 12 Liquid Poison Pump 12 CREVS 12 RBEVS 12 EDG 103 Auxiliaries Condensate Transfer Pump 12 Emerg. Cond. 12 Inside Steam IV (39-03R)
NRC Scenario 3 13 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 3 Continued iRO Acknowledge report from crew Direct BOP/RO to execute applicable ARPs Recognize that EDG 103 auxiliaries are not powered (Raw Water Pump)
Direct shutdown of EDG 103 using N1-ARP-A5-4-3 Acknowledge report from BOP/RO that no CRD Pumps operating and CRD Pump 11 is available Direct RO/BOP to start CRD Pump 11 Role Plav: If dispatched as NAO to investigate PB IAW N1- S O P 4 1 or N1-ARP-A5-4-3 loss, wait 3 minutes then report that RIOIC;, PI3 Review loads lost as result of PB 103 Normal Supply Breaker, tripped on over- 103/17B loss current Review Tech Specs for impact of loss of PB103 TS 3.12,Liquid Poison System TS 3.1.4, Core Spray System TS 3.1 5,ADS (Requires to be less than 10 psig in 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />)
TS 3.1.6, CRD System TS 3.2.7.c, Reactor Coolant System Isolation Valves (Limiting LCO - requires initiating a normal orderly shutdown within one hour and having reactor in the cold shutdown condition within ten hours.)
TS 3.3.7, Containment Spray TS 3.6.3, Emergency Power Sources Recognize that TS 3.2.7.c is most limiting NRC Scenario 3 14 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 3 Continued SRO Continued D Notify WEC/Mgmt of impending Role Plav: When contacted as WECIMgnit, shutdown acknowledge report of impending shutdown D Brief crew on impending shutdown RO 0 Monitor plant parameters 0 May perform N1-SOP-5.1 for loss of 12 CRD pump prior to BOP starting 11 CRD pump per ARPs 0 Places 11 CRD pump control Role Plav: If directed as NAO to shift RPL level switch to START CRD backfill per N1-OP-58, H.2.0 reply that you 0 Places 12 CRD pump control will get the procedure and shift RPV level CRD switch to STOP backfill. Wait 5 minutes and report backfill has 0 Observes proper operation of 11 been shifted. CRD pump (amps, flow, alarms)
BOP 0 Executes N 1-ARP-A5-4-3 0 Confirm alarm on computer 0 If PB 103 voltage is low:
0 Verifies EDG 103 running 0 Confirm A5-4-1 AND A5-4-2 clear 0 Attempts to close R1032, EDG 103 Output Breaker 0 Recognizes/reports R1032 will not close and PB 103 cannot be re-energized If PB 103 cannot be re-energized:
0 Places R1013 in PTL 0 Places EDG 103 control switch in emergency stop 0 May start CRD Pump 11 NRC Scenario 3 15 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 3 Continued BOP Continued Verifies RBCLC header pressure >40 psig Resets Lockout 86-17 Opens R1053, PB 17B Normal Feeder Breaker Closes R1052, PB 17 A-B Tie Breaker Recognizes/reports R1052 will not close and PB 17B cannot be re-energized Role Play: If requested to develop a clear'snce to Requests clearance to prevent prevent autostart of EDG 103, acknowledgls auto-start of EDG 103 request and estimate one hour for completion.
NRC Scenario 3 16 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 4 PO-5.0 Feedwater Booster Pump 11 Trip with Failure of CREW the Standby Pump to Auto Start e Acknowledge/report annunciator H3-3-6 REACTOR FW BOOSTER P I 1 When directed by examiner, insert malfunction: TRIP Diagnose trip of Feedwater Booster FWOZA, FEEDWATER BOOSTER PUMP 'TRIP 11 Pump 11 TRG 3 The following override prevents Feedwatei?
Booster Pump 12 from Auto Starting on low header discharge pressure:
OVR-7S43D14116 POS-3 4Hl7151-02A C FRM B PRESET RPV water level slowly lowers Feedwater Booster Pump header pressure lowers Expected Annunciators:
H3-1-6REACTOR FW BOOSTER P I 1 TRI'P H3-7-7,H3-2-7,H3-3-7,REACTOR F W PUMP 17/12/13 SUCTION SRO Acknowledges report If BOP does not manually start FWBP 12, directs starting FWBP 12 Enters Tech Spec 3.1.8.c Determines redundant component inoperable in both HPCl train 11 and 12, thus normal orderly shutdown shall be initiated within one hour and the plant brought to less than 110 psig in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> NRC Scenario 3 17 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 4 Continued SRO Continued 0 Initiates surveillance requirement 4.1.8.c for redundant component operability verification 0 Notifies WEC 0 Notifies Ops Management 0 Performs crew briefhpdate RO 0 Monitors plant parameters 0 May perform Emergency Power Reduction per N1-SOP-1.1 as required to maintain RPV water level BOP 0 Report alarm and respond per H3-1-6 0 Confirms alarm on computer (E049 RX FW BOOST PMP 11 TRIP) 0 Recognizes/diagnoses failure of the standby pump to automatically start Manually starts FWBP 12 Notifies crew of failure of FWBP 12 to auto start Role Play: When dispatched as NAO to swap 0 Dispatches operators to shift HWC, wait 5 minutes and report that HWC Hydrogen Water Chemistry injection injection has been transferred from FWBP 11 to from FWBP 11 to FWBP 12 FWBP 12 NRC Scenario 3 18 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 5 PO-6.0 Failure of the Feedwater Master Controller AS-IS CREW 0 Recognize/report RPV water level is The following malfunction will be automatically deviating from setpoint inserted when the control switch for Feedwater 0 Diagnose/report failure of Feedwater Booster Pump 12 is placed in START: Master Controller FW16, FEEDWATER MASTER CONTROLLER FAILS AS IS TRG 4 RPV water level slowly deviates from setpoint Feedwater flow remains constant Expected Annunciator:
F2-3-3 REACT VESSEL LEVEL HIGH-LOW SRO 0 When notified of feedwater controller failure, directs:
- Entry into N1-SOP-16.1
- Manual control of feedwater RO Monitors plant parameters May perform Emergency Power Reduction per N1-SOP-1.I as required to maintain RPV water level BOP 0 Enters N1-SOP-16.1
- Determines problem with Feedwater Level Control
- Determines NOT a Flow Control Valve lockup NRC Scenario 3 19 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 5 Continued BOP Continued Using available FCVs, takes manual control of FWLC at MA stations Operates Feedwater FCV 11 or 13 in manual to control feedflow to restore RPV water level Controls RPV water level in MANUAL NRC Scenario 3 20 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 6 PO-7.0 Feedwater Pump 11 Trip CREW D Acknowledgeheport annunciator When the crew has restored RPV water level to m Diagnose a trip of the operating normal band and directed by examiner, insert electric feedwater pump malfunction:
FW03A, FEEDWATER PUMP I 1 TRIP TRG 5 RPV water level lowers ExpectedAnnunciator:
H3-1-7,REACTOR FW PUMP 11 TRIP OVERLOAD SUCTIONHI-LEVEL SRO Acknowledges report Directs entry into ARP Directs re-entry into N1-SOP-I 6.1 Directs BOP to maintain RPV water level with FWP 13 using FWLC in manual Directs RO to lower power IAW N I -
SOP-I . I Supervises power reduction Notifies WEC Notifies Ops Management Performs crew briefhpdate Recognizes Tech Spec 3.1.8 applies for loss of HPCl component NRC Scenario 3 21 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 6 Continued RO 0 Monitors plant parameters 0 Lowers reactor power IAW NI-SOP-
- 1. I using recirculation flow as directedkequired for RPV water level control Monitors position on P/F map BOP 0 Re-enters N1-SOP-16.1 Coordinates RPV water level control with RO during power reduction Determines problem with FW Pumps Determines level can be maintained >53 Restores level 65-83 by controlIing injection from Feedwater FCV 13 0 Enters ARP H3-1-7 0 Places 11 FW Pump Control Switch to Stop spring return to Neutral Role Play: If dispatched as NAO to check FWP 0 Confirms Aux Oil Pump running 11, wait 2 minutes and report that FWP 11 AUXOil AND FW Pump not rotating Pump is running and the FWP shaft is not rotating backwards backwards. 0 Verifies closed, 11 FW FCV (29-141) AND 11 FW Low Flow FCV Role Play: If dispatched as NAO to investigate trip (29-49) of FWP 11, wait 2 minutes and report that FWP 11 0 Dispatch NAO to investigate FWP 11 breaker tripped on overload, but there are n13 trip abnormal indications at the pump.
NRC Scenario 3 22 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENTS 7 , 8 and 9 PO-8.0, 9.0 RPV coolant leak in the Primary Containment CREW 0 Recognizeheport containment When the crew has restored RPV water level to parameters degrading normal band and directed by examiner, insert - DW humidity rising malfunction: - DW leakage rising
- DW pressure rising CUOl, COOLANT LEAK INSIDE OF DRYINELL, - DW temperature rising RAMP TIME=10:00, FINAL VALUE=40% 0 Diagnose RPV coolant leak TRG 6 Drywell humidity, leakage rate, pressure and temperature rise Expected Annunciators:
H2 7, DRYWELL WATER LEAK DE TECTION SYS K2-4-3, DRYWELL PRESSURE HIGH - LOW The inboard IV for Core Spray 111 fails to open and Core Spray pump 121 fails to start The following malfunctions are preset:
CSOIC, CORE SPRAY PUMP TRIP 121 IPRESET CSO3C, CORE SPRAY INBD INJECT VLV FAIL TO OPEN 40-11 IPRESET NRC Scenario 3 23 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENTS 7 , 8 and 9 Continued SRO Initial Actions for RPV Coolant Leak 0 May direct an emergency power reduction IAW Nl-SOP-1. I , if time Note: A reactor scram will be required because of permits rising Drywell pressure Brief crew on plans to insert manual scram 0 Direct the RO to place Mode Switch to SHUTDOWN 0 Enters N1-EOP-2 when RPV water level reaches 53 inches 0 Directs N1-SOP-1, Reactor Scram 0 Enters N1-EOP-2 and N1-EOP-4 when DW pressure reaches 3.5 psig Actions for failure of PB to transfer e Direct entry into Nl-SOP-30.1 0 Direct entry into N1-SOP-30.2 0 Authorizes PB 11 and PB 12 re-energized 0 Acknowledges PB 11 and PB 12 can be re-energized Subsequent SRO EOP Actions:
0 Enters N1-EOP-2 when water level reaches 53 inches:
0 Determines all control rods are in 0 Directs RPV water level controlled between 53-95 inches with CRD Directs RPV pressure controlled less than 1080 psig Adjusts level and pressure bands as coolant leak degrades RPV parameters NRC Scenario 3 24 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENTS 7 , 8 and 9 Continued SRO Continued e When RPV level can NOT be maintained >53 inches, directs use of Alternate Injection Systems, Detail E (Liquid Poison) to stay above -84 inches (TAF) e Direct MSlVs closed to minimize inventory loss and pressure control with ECs e Determines cannot stay above -84 inches (TAF) with current injection sources, and transitions to Alternate Level Control leg of N1-EOP-2 e Directs ADS bypassed e Directs EC initiation e Determines Core Spray pump 121 has failed to start e Determines 2 Detail F Subsystems are available (Core Spray Loop 11 and Condensate/Feedwater Booster Pumps 12) e Waits until level drops to -84 inches (TAF) e Determines a Detail F Subsystem is lined up with a pump running e Before level drops to -109 inches, determines an injection source is lined up with a pump running e Enters N1 -EOP-8, RPV Blowdown:
Determines all control rods are in NRC Scenario 3 25 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENTS 7,8 and 9 Continued iRO Continued Directs Emergency Condensers initiated 0 Determines torus water level is above 8.0 feet Directs open 3 ERVs CT-I -0 Directs RPV water level restored 53-95 inches using Core Spray (Nl-EOP-1 Att 4) or Condensate/Feedwater Booster pumps (Nl-EOP-1 Att 25/26)
When RPV pressure is less than 365 psig, determines Core Spray IV 40-1 1 failed to open Directs RPV water level restored 53-95 inches using Condensate/Feedwater Booster pumps (Nl-EOP-1 Att 25/26)
CT-2.0 Determines RPV water level is rising Transitions back to Normal Level Control leg of N1-EOP-2 Enters N1-EOP-4 when drywell pressure reaches 3.5 psig and/or drywell temperature reaches 150°F:
Directs lockout of Containment Spray Pumps 0 When torus pressure exceeds 13 psig or before drywell temperature exceeds 300°F:
NRC Scenario 3 26 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENTS 7 , 8 and 9 Continued SRO Continued 0 Determines plant is inside Containment Spray Initiation Limit Curve (Fig. K) 0 Directs verification that the recirculation pumps are tripped 0 Directs drywell cooling fans tripped 0 Directs initiation of containment spray IAW NI-EOP-I Att 17 CT-3.0 0 Monitors torus pressure and water level for PSP RO Places REACTOR MODE Switch in SHUTDOWN Provides Scram Report Performs N1-SOP-1, Reactor Scram, scram verification actions Places IRMs on range 9 Inserts IRM and SRM detectors Downranges IRMs as necessary to monitor power decrease 0 Reduces Recirc Master flow to 25-43 x I O 6 Ib/hr Controls RPV pressure 4 0 8 0 psig using Turbine Bypass Valves, as required BOP D Continues to control RPV Level in MANUAL NRC Scenario 3 27 October 2008
I NSTRUCTOR ACT1ON S/
PLANT RESPONSE OPERATOR ACTIONS BOP Continued 0 Performs N1-SOP-I , Reactor Scram, level control actions:
0 Restores RPV level to 53-95 inches by controlling injection and rejecting through RWCU 0 Determines # I 3 FWP running and RPV water level recovering Note: Further level control actions may not be 0 Determines no Electric FW Pump performed due to powerboard losses and coolant runninglavailable leak 0 Terminates 13 FWP injection (as required with no Electric FW Pump and LOCA in progress):
0 Places FWP 13 VALVE CONTROL in MANUAL AND closes 0 Disengages 13 FWP 0 Gives 29-10, FEEDWATER PUMP 13 BLOCKING VALVE, a CLOSE signal 0 Verifies RPV water level +53 inches and rising 0 Verifies 11/12 FWP controllers in MANUAL and set to zero output 0 Resets HPCl signal 0 If RPV level reaches 85 inches and rising, then:
Verifies off all Feedwater Pumps 0 Secures CRD Pumps not required 0 Maximizes RWCU reject flow Closes FWlVs if required 0 Closes MSlVs if required 0 Attempts to maintain RPV water level in assigned band NRC Scenario 3 28 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENTS 7 , 8 and 9 Continued ROlBOP Actions for Failure of PBs to Transfer:
When the turbine trips, Power Boards 1Iand 12 e Enters N1-SOP-30.1 for PB 11 loss fail to transfer e Enters N1-SOP-30.2 for PB 12 loss Actions from N1-SOP-30.1(30.2)
The following malfunctions cause the failure to e Verifies fault annunciators clear transfer: e Obtains permission from SRO to re-energize PB 11(12)
ED26, FAILURE OF PBI I TO AUTO TRANSFER e Verifies PB 11(12) components green PRESET flagged ED27, FAILURE OF PB12 TO AUTO TRANSFER Cleanup Pump 11(12)
PRESET Service Water Pump 11(12)
Expected Annunciators: Circ Water Pump 1l(12)
A4-1-1, POWER BD. I 1 R113 TRIP RRMG Set 11 and 12 (14 and 15)
A5-1-6, POWER BD. 12 R122 TRIP TBCLC Pump 11(12)
Major Loads Lost: FW Booster Pump 11(13)
Powerboard 7 7: Condensate Pump 1l(13)
RWCU Pump I 1 e Inserts Sync Key and rotates Service Water Pump 11 clockwise for R112(R123)
Circ Pump 11 e Closes R112(R123)
RR Pump I 1 e Confirms voltage normal on PB 11(12)
RR Pump 12 e Rotates Sync Key counterclockwise TBCLC Pump I ? and removes for R112(R123)
Condensate Pump I 1 e Determines PB 11(12) energized Feedwater Booster Pump I I e Closes RIII(124)
Powerboard 72:
e Dispatches NAO to recover RWCU Pump 12 Powerboards 13, 14, 15 Service Water Pump 12 e Reports PB 11(12) re-energized Circ Pump 12 e Moves to other SOP to re-energize RR Pump 14 PB 12(11)
RR Pump 15 e Starts Service Water Pump 1l(12)
TBCLC Pump 12 e Starts IAC 1l(12)
Condensate Pump 13 e Starts TBCLC Pump 11(12)
Feedwater Booster Pump 13 NRC Scenario 3 29 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENTS 7,8 and 9 Continued RO/BOP Continued 0 Starts an RBCLC Pump 0 Verifies fault annunciators clear Role Plav: When contacted as NAO, 0 Obtains permission from SRO to re-acknowledge order to recover PBs 13, 14, 15, but energize PB 12(11) delay any report on task completion 0 Verifies PB 12(11) components green flagged 0 Cleanup Pump 12(11) 0 Service Water Pump 12(11) 0 Circ Water Pump 12(11)
RRMG Set 14 and 15 (11 and 12) 0 TBCLC Pump 12(11) 0 FW Booster Pump 13(11) 0 Condensate Pump 13(11) 0 Inserts Sync Key and rotates clockwise for R123(R112) 0 Closes R123(R112) 0 Confirms voltage normal on PB 12(11) 0 Rotates Sync Key counterclockwise and removes for R123(R112) 0 Determines PB 12(11) energized 0 Closes R124(111) 0 Reports PB 12(11) re-energized Subsequent EOP Actions:
0 Maximizes injection with CRD and Liquid Poison to attempt to maintain level within the band assigned 0 Updates crew on failure to maintain level and pressure bands NRC Scenario 3 30 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENTS 7 , 8 and 9 Continued ROlBOP Continued Operates Emergency Condensers to maintain pressure with the band assigned and NOT exceed 1OO°F/hr cool-down rate Reports failure of Core Spray pump 121 to start Closes MSlVs when directed Locks out Containment Spray by placing 4 pump control switches in PTL Observes and reports containment parameters (torus pressure above 13 PSkl)
Verifies/reports that all recirculation pumps have been tripped Verifies/reports that all drywell cooling fans have been tripped Initiates containment spray (N1-EOP-1 Att 17)
Starts Containment Spray Pumps 111 and 112 CT-3.0 Verifies Containment Spray flow Monitors containment pressure and temperature to ensure lowering trend Terminates Containment Sprays when drywell pressure is below 3.5 psig Reports containment spray terminated NRC Scenario 3 31 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENTS 7 , 8 and 9 Continued RO/BOP Continued Monitors DWP and reports if DWP reaches 3.5 psig, after spray is terminated IF directed, initiates Containment Spray again Initiates Emergency Condensers when directed Bypasses ADS Reports RPV water level below -84 inches (TAF)
Opens 3 ERVs CT-1.O When RPV pressure lowers below 365 psig, recognizes/reports Core Spray IV 40-1 1 failed to open Attempts to manually open 40-1 1 Report inability to inject with Core spray Injects to the RPV with Condensate/Feedwater Booster pumps (Nl-EOP-1 Att 25/26)
CT-2.0 Reports RPV water level above -84 inches (TAF)
Restores and maintains RPV water level 53-95inches Possible N1-EOP-1 Att 25 actions:
WHEN Feedwater Booster HDR PR (PI-51-61A) is greater than RPV pressure, THEN:
Place LVL SETPOINT SETDOWN to OVERRIDE NRC Scenario 3 32 October 2008
INSTRUCTOR ACT1ONSl PLANT RESPONSE OPERATOR ACTIONS EVENTS 7 , 8 and 9 Continued ROlBOP Continued Verify Open, at least one of the FEEDWATER ISOLATION VALVES 11 and 12 Verify Open, FEEDWATER PUMP 13 BLOCKING VALVE Select Manual on 13 FWP Valve Control Selector Switch Turn 13 Feedwater FCV (Knurled Knob) clockwise to open Feedwater FCV Position 13 Feedwater FCV as necessary to maintain required level Possible N1-EOP-1 Att 26 actions:
WHEN Feedwater Booster HDR PR (Pl-51-61A) is greater than RPV pressure, THEN:
Verify Open at least one of the FEEDWATER ISOLATION VALVES 11 and 12 Verify Open, both FEEDWATER PUMP 11 and 12 BLOCKING VALVES Select Manual on 11 and 12 FWP Role Plav: When directed as NAO to pull fuses Valve Control Selector Switch FU-8 and FU-9, wait 2 minutes and insert iremote: Turn 11 and 12 Feedwater FCV (Knurled Knob) fully FW24, REMOVAL OF HPCl FUSES FU8/FXJ9, counterclockwise FINAL VALUE=PULL Remove the following fuses from TRG 2e Panel IS34 in the Aux Control Room:
Then report that fuses FU-8 and FU-9 have been 0 FU-8 pulled FU-9 NRC Scenario 3 33 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENTS 7 , 8 and 9 Continued ROlBOP Continued 0 Position 11 and 12 Feedwater FCV as necessary to maintain required level while maintaining less than 1.5 E6 Ibm/hr through each feed pump TERMINATING CUE 0 RPV Blowdown in progress 0 RPV water level above -84 inches (TAF) and controlled in assigned band 0 Containment pressure controlled in accordan with N1-EOP-1 Att 17 NRC Scenario 3 34 October 2008
V. POST SCENARIO CRITIQUE A. NIA, NRC Exam VI. REFERENCE EVENTS AND COMMITMENTS A. Reference Events
- 1. None B. Commitments
- 1. None VII. LESSONS LEARNED A. None NRC Scenario 3 35 October 2008
Appendix D Scenario Outline Form ES-D-1 Facility: Nine Mile Point I Scenario No.: NRC44 Op-Test No.: October 2008 Examiners: Operators:
Initial Conditions: Simulator IC 174
- 1. Reactor Power approximately 90% for a rod pattern adjustment Turnover:
- 1. Maintenance completed work on TBCLC pump 12
- 2. APRM 13 bypassed due to failed power supply
- 3. Recirc Pump 14 OOC due to high jibrations Event Malf. No. Event Event No.
Type* Description instrument line) fail low, requires manual FWLC Water Discharge Strainer high D/P requires shifting I H2-1-3 I the lntalte Structure and loss of normal heat sinks, emergelicy power reduction required (SOP-I 8.1)
\--. ' I 9 FW24 C (BOP) The crew will be unable to re-inject with feedwater/
FW28 c (SRO) condensate because the valves they used to terminate and prevent will fail closed (EOP-8)
Overrides (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NRC Scenario 4 October 2008
Facility: Nine Mile Point 1 Scenario No.: NRC-04 OD-Test No.: October 2008 TARGET QUANTITATIVE ATTRIBUTES ACTUAL (PER SCENARIO: SEE SECTION D.5.d) ATTRIBUTES
- 1. Total malfunctions (5-8) 6 Events 3,4,5, 6,8,9
- 2. Malfunctions after EOP entry (1-2) 2 Events 8,9
- 3. Abnormal events (2-4) 4 Event 3,4,5,6
- 4. Major transients (1-2) 1 Event 7
- 5. EOPs enteredhequiring substantive 1 actions (1-2)
Event 8 (EOP-4)
- 6. EOP contingencies requiring substantive 2 actions (0-2)
- 7. Critical tasks (2-3) 3 CRITICAL TASK DESCRIPTIONS:
CT-1.0 Given a failure of the reactor to scram with power above 6% or unknown and RPV water level above -41 inches, the crew will terminate and prevent all injection except boron and CRD.
CT-2.0 Given a failure of the reactor to scram with RPV water level unable to be restored and maintained above -109 inches with CondensatelFeedwater and CRD, the crew will perform an RPV Blowdown and re-establish injection with Core Spray.
CT-3.0 Given a LOCA in the Drywell, the crew will initiate Containment Sprays to
-prevent exceeding PSP.
NRC Scenario 4 . October 2008
NMP SIMULATOR SCENARIO NRC Scenario 4 REV. 0 No. of Pages: 35 FEEDWATER FLOW TRANSMITTER FAILURE, SERVICE WATER STRAINER CLOGGING, LOW LEVEL IN THE INTAKE STRUCTURE. ATWS WITH A LOCA AND FAILURE OF THE FEEDWATER ISOLATION VALVES CLOSED VALIDATED 2 u
h Az w
z ay f Bruce Williams DATE 5/18/08 GEN SUPERVISOR OPS TRAINING DATE &3&
OPERATIONS MANAGER N/A - IExam Security DATE CONFIGURAT10N CONTROL N/A - IExam Security DATE SCENARIO
SUMMARY
Length: 90 minutes Initial Power Level: Approximately 90%, 4 loop operation Mitigating Strategy Code: AT3, high power ATWS with small LOCA, Blowdown required, re-inject with Core Spray The scenario begins with the crew performing a control rod pattern adjustment. Next, the crew will be directed to return TBCLC Pump 12 to service and secure TBCLC Pump 11. When this is complete, an RPS pressure transmitter will fail low, followed closely by the in-service feedwater system pressure transmitter also failing low. The crew will be required to shift to manual feedwater level control. The crew may then shift reactor pressure/level columns and return to automatic feedwater level control. Technical Specifications must be addressed due to the RPS pressure transmitter failure.
Next the crew must respond to high D/P across one of the Service Water Pump Discharge Strainers. This will require placing another Service Water Pump in service. Once the standby Service Water Pump has been started, Main Steam Line Radiation Monitor 111 will become inoperable. The SRO will determine the Technical Specification implications. Next the intake structure traveling screens clog causing higii D/Ps. This will eventually result in a low level in the intake structure with the subsequent tripping of the Circulating Water pumps. This will require entering N1-SOP-18.1, Service Water Failure/Low Intake Level. As intake level continues to lower, the crew will insert a manual scram.
When the scram occurs the control rods will not insert. This ATWS is complicated by the total NRC Scenario 4 - October 2008
loss of the normal heat sinks. Additionally, following the ATWS, a Recirculation Line break will cause RPV water level to lower, requiring the crew to re-establish injection. When the crew attempts to re-establish Feedwater flow, the Feedwater isolation valves will not re-open. When it is determined that RPV water level cannot be restored and maintained above -109 inches, the crew will perform an RPV Blowdown, and re-inject with Core Spray.
Major Procedures: N1-SOP-I . I , N1-SOF-I 6.1, N1-SOP-I 8.1, N1-EOP-I, N1-EOP-2, N1-EOP-3, NI-EOP-:3.1, N1-EOP-4, N1-EOP-8 EAL Classification: Site Area Emergency, EAL 2.2.2 Termination Criteria: RPV Blowdown in progress, RPV water level above -109 inches and controlled in assigned band, containment pressure controlled in accordance with N1-EIOP-1 Att 17 NRC Scenario 4 October 2008
I. SIMULATOR SET UP A. IC Number: IC 174 B. Presets/FunctionKey Assignments
- 1. Malfunctions:
- a. RROID, RR PUMP 14 DRIVIE BREAKER TRIP PRESET
- d. RR92, RX VESL PRES XMTR 36-31 (LOCAL-FW CONTROL)
FAILS, DELAY TIME=15 SEC TRG 1
- f. RMIA, MAIN STEAM LINE FiAD MONITOR 111 INOP TRG 3
- g. CW12, CIRCULATING WATER INTAKE STRUCTURE BLOCKAGE (TRASH), FINAL VALUE=20% TRG 4
- h. RD33A, CONTROL ROD BANK BLOCKED BANK 1, INSERT FAIL POSITION, FINAL VALUE=12 PRESET
- i. RD33B, CONTROL ROD BANK BLOCKED BANK 2, INSERT FAIL POSITION, FINAL VALUE=12 PRESET
- j. RD33C, CONTROL ROD BANK BLOCKED BANK 3, INSERT FAIL POSITION, FINAL VALUE=18 PRESET
- k. RD33D, CONTROL ROD BANK BLOCKED BANK 4, INSERT FAIL POSITION, FINAL VALUE=12 PRESET I. RD33E, CONTROL ROD BANK BLOCKED BANK 5, INSERT FAIL POSITION, FIIVAL VALUE=12 PRESET
- 0. FW28A, HPCl MODE FAILURE TO INITIATE 11 TRG 20
- p. FW28B, HPCl MODE FAILURE TO INITIATE 12 TRG 20
- 2. Remotes:
- a. FW24, REMOVAL OF HPCl FUSES FU8/FU9, FINAL VALUE=PULL TRG 25
- 3. Overrides:
- a. OVR-5S5D1309 POS-3 1FIO/31-03A POS C, FINAL VALUE=INSYS TRG 19
- b. OVR-5S6D13012 POS-3 1Fl0/31-03A POS C, FINAL VALUE=INSYSTRG 19 NRC Scenario 4 October 2008
C. OVR-SA144PI D1354 SET 1F'27/ID15B MAN, FINAL VALUE=INSYS TRG 20
- d. OVR-5A144Pl Dl355 SET 1F'27/ID15B AUTO, FINAL VALUE=INSYS TRG 20
- e. OVR-5A144P1A13100 1F27/ID158 BAL R I , FINAL VALUE=O TRG 20
- f. OVR-5A145PI Dl356 SET 1F'28/ID1 5C MAN, FINAL VALUE=O.OO TRG 20
- g. OVR-5A145Pl Dl357 SET 1F'28/IDI 5C AUTO, FINAL VALUE=O.OO TRG 20
- h. OVR-5A145PIA13120 1F28/ID15C BAL R I , FINAL VALUE=O TRG 20
- 4. Annunciators:
- a. H2-1-3, CIRCULATING WATER PUMP INTAKE LEVEL LOW -
ON/OFF, FINAL VALUE=CRYWOLF TRG 4
- 5. Triggers;
- a. TRG 18 - Activates the coolant leak when the mode switch is taken to shutdown
- i. Event Action: zdrpstdn==l ii. Command: None
- b. TRG 19 -When both FWlV '1 1 and 12 green lights are lit, activates the FWlV 11 and 12 control switch OPEN position to off, preventing reopening of the valves
- i. Event Action: hzlfwisg(1:)==I&&hzlfwisg(2)==1 ii. Command: None
- c. TRG 20 - If both FWP 11 and 12 control switches are placed in PTL, activates malfunction to fail FW FCV 13 closed, and activates overrides on FW FCVs 11 and 12 to turn AUTO position off, MAN position on, and give a full close signal
- i. Event Action: zdfwfpk(1 )==I&&zdfwfpk(2)==1 ii. Command: None
- d. TRG 21 - Activates when the RPS jumpers are installed, ARI is overridden and RPS has been reset to allow a manual scram to achieve further inward rod movement
- i. Event Action: zdrpjbl1(5)==1&&hzlrp12g1==1&&zdrrarov==1 ii. Command: bat n08scen4RHI .bat
- 6. Batch Files:
- a. n08scen4RHI.bat - Allows further rod movement using N1-EOP-3.1
- i. dmfrd33a ii. dmf rd33b iii. dmf rd33c iv. dmf rd33d
- v. dmfrd33e NRC Scenario 4 October 2008
vi. imf rd33a (0 0) 6 vii. imf rd33b (0 0) 6 viii. imf rd33c (0 0) 10 ix. imf rd33d (0 0) 8
- x. imf rd33e (0 0) 8 C. Equipment Out of Service
- 1. APRM 13 bypassed and yellow tagged
- 2. Recirc Pump 14 control switch in PTL and yellow tagged D. Support Documentation
- 1. RMI for control rod pattern adjustment E. Miscellaneous None NRC Scenario 4 October 2008
- 11. SHIFT TURNOVER INFORMATION PART I: To be performed by the oncoming Clperator before assuming the shift.
0 Control Panel Walkdown (all panels) (SM, CRS, STA, CSO, CRE)
PART II: To be reviewed by the oncoming Operator before assuming the shift.
0 Shift Manager Log (SM,CRS, STA) 0 Shift Turnover Checklist (ALL) cso Log (CSO) 0 LCO Status (SM, CRS, STA) 0 Lit Control Room Annunciators 0 Computer Alarm Summary (CSO)
EvolutionslGeneral InformationlEquipment Statils:
Reactor Power = 90%, 4 loop operation TBCLC pump 12 motor bearing repair complete APRM 13 bypassed due to failed power supply Recirc Pump 14 OOC due to high vibrations PART 111: RemarkslPlanned Evolutions:
- 1. Control rod pattern adjustment
- 2. TBCLC pump 12 to be returned to service
- 3. Power ascension to rated PART IV: To be reviewedlaccomplishecl shortly after assuming the shift:
Review new Clearances (SM) Test Control Annunciators (CRE)
Shift Crew Composition (SM/CRS)
NRC Scenario 4 October 2008
II. PERFORMANCE OBJECTIVES A. Critical Tasks:
CT-1.O Given a failure of the reactor to scram with power above 6% or unknown and RPV water level above -41 inches, the crew will terminate and prevent all injection except boron and CRD, in accordance with N1-EOP-3.
CT-2.0 Given a failure of the reactor to scram with RPV water level unable to be restored and maintained above -109 inches with Condensatelfeedwater and CRD, the crew will perform an RPV Blowdown and re-establish injection with Core Spray, in accordance with N1-EOP-3.
CT-3.0 Given a LOCA in the Drywell, the crew will initiate Containment Sprays to prevent exceeding PSP, in accordance with N1-EOP-4.
B. Performance Objectives:
PO-I .o Given the plant at power, the crew will perform a control rod pattern adjustment, in accordance with N1-OP-5.
PO-2.0 Given the plant operating at power, the crew will shift operating TBCLC Pumps, in accordance with N1-OP-24.
PO-3.0 Given the plant operating at power and a failure of RPV pressure instruments, the crew will diagnose the failures and take manual control of RPV water level to prevent a reactor scram, in accordance with N I -
SOP-I 6.1.
PO-4.0 Given the plant operating at power with clogging of the operating Service Water Pump Discharge Strainer, the crew will shift to the alternate Service Water pump and strainer, in accordance with N1-OP-18.
PO-5.0 Given the plant operating at power and a failed Main Steam Line Radiation Monitor, the crew will determine the appropriate Technical Specification actions, in accordance with N1-ARP-F1 .
PO-6.0 Given the plant operating at power and lowering intake level, the crew will operate Circulating Water pumps, perform an emergency power reduction and scram the reactor, in accordance with N1-SOP-18.1.
NRC Scenario 4 October 2008
PO-7.0 Given the plant in a condition requiring emergency classification, the SRO shall classify the eveiits properly, complete initial notification forms, and discuss the bases for, the classification in accordance with the emergency plan procedure.
PO-8.0 Given the plant or a plant system in a condition requiring Technical Specification action, identify the deviation and any required actiondnotifications.
NRC Scenario 4 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS Take the simulator out of freeze before the crew enters for the pre-shift walkdown and briefing Allow no more than 5 minutes to walkdown panels CREW Walkdown panels Conduct shift turnover brief 0 Assume the shift EVENT 1 PO-I .o Control rod pattern adjustment Note: There are no Control Console activities required for this event SRO Note: Reactivity briefing, procedure review and 0 Conducts reactivity brief for power RMI review should occur prior to scenario start, in restoration (previously performed) secure briefing room 0 Reviews Reactivity Maneuver Instruction (previously performed) 0 Directs RO to perform control rod pattern adjustment in accordance with the RMI and N1-OP-5 Provides Reactivity SRO monitoring RO 0 Acknowledges direction from SRO 0 Obtains copy of RMI form 0 Moves control rods in accordance with N1-OP-5 and RMI 0 Reports to SRO when control rod pattern adjustment is complete NRC Scenario 4 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 1 Continued BOP Monitors feedwater controls for proper response 0 FWP 13 FCV responding to power change 0 RPV Water Level remains within program band ( 6 5 - 7 5 )
0 Provides peer checks as required NRC Scenario 4 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 2 PO-2.0 Return TBCLC Pump 12 to service and secure TBCLC Pump 11 After performing the control rod pattern adjustment, the crew shifts operating TBCLC pumps pel- N I -
OP-24, Section F.1.O Note: There are no Control Console activities required for this event SRO 0 Provide pre-evolution brief 0 Direct BOP to start TBCLC Pump 12 and secure TBCLC Pump 11 IAW N I -
OP-24, Section F . l .O RO 0 Monitor plant parameters BOP Acknowledges direction to start TBCLC Pump 12 and secure TBCLC Role Plav: When contacted as NAO to perform Pump 11 IAW N1-OP-24, Section pre-start checks, immediately report pre-sta rt F . l .O checks are SAT and you are standing by for pump Obtains and reviews N1-OP-24 start Starts TBCLC Pump 12 Directs A 0 to vent pump through 71-Role Plav: When contacted as NAO for proper 192, as follows:
pump start, immediately report pump start SAT Uncap AND open 71-192 WHEN venting complete, close Role Plav: When contacted as NAO for pump AND cap 71-192 venting, wait 1 minute and report the pump has been vented NRC Scenario 4 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 2 Continued BOP Continued Confirms standby pump is operating correctly by verify stable pump amps and discharge pressure Stops TBCLC Pump 11, then places control switch for TBCLC Pump 11 in AUTO START NRC Scenario 4 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 3 PO-3.0 Reactor pressure transmitter failures CREW 0 Acknowledge/report Annunciators When the TBCLC Pumps are shifted and directed F4-4-2, RPS CH 12 RX PRESS by examiner, insert malfunctions: LOW 0 F4-4-7, RPS CH 12 MS IS0 AUTO RPI66, RPV PT 36-076 FAILED LOW OPERATE TRG 1 F2-3-3, REACT VESSEL LEVEL RR92, RX VESL PRES XMTR 36-31 (LOCAL-FW HIGH-LOW (Delayed > I 5 sec)
CONTROL) FAILS, DELAY TIME=15 SEC 0 Diagnose failure of the pressure TRG 1 instruments on the F Panel then Two RPV pressure instruments indicate downscale diagnose failure of FWLC Controlling RPV water level instrument indicates Pressure/Level Column lower than actual Feedwater flow rises RPV water level rises Expected Annunciators:
F4-4-2, RPS CH 12 REACTOR PRESS LOW F4-4-7, RPS CH 12 MAiN STEAM iSOLATlON AUTO OPERATE F2-3-3, REACT VESSEL LEVEL HIGH-LOW (delayed >15 sec)
SRO Acknowledge report of pressure transmitter failures Diagnose the relationship between pressure transmitter 36-31 and the FWLCS Acknowledge report of RPV water level rising NRC Scenario 4 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE 0PERAT0R ACTIONS EVENT 3 Continued SRO Continued Direct entry into N1-SOP-I 6.1 for failure of FWLC Directs placing FWLC in Manual Directs Shifting Reactor Pressure/Level Columns IAW N1-OP-16, section F.10.0 Acknowledge report of pressure and level columns shifted Enter T.S. Table 3.6.2.a (o), for pressure transmitter 36-07B (Place RPS Channel 11 in the tripped condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)
Notify WEC/Ops Mgmt RO Note: Switching level columns may result in Monitor plant parameters Annunciator F2-3-3, REACT VESSEL LEVEEL If directed to shift FWLC HIGH-LOW, due to circuit interruption. pressure/level columns :
Verifies feedwater lineup
-Note: The same channel of level and pressure Verifies BOP has manual control should be selected of FWLC Shifts reactor pressure and level columns using the key lock switches on the E Panel Coordinates with BOP to return FWLC to auto:
Places FEEDWATER MASTER CONTROL M/A station mode switch in MAN NRC Scenario 4 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 3 Continued 30 Continued 0 Nulls FWP 13 VALVE CONTROL by adjusting the FEEDWATER MASTER CONTROL M/A station output with the manual knob until the deviation meter indicates 50%
on FWP 13 VALVE CONTROL GEMAC 0 Controls RPV water level with the manual knob at the FEEDWATER MASTER CONTROL LBSlHR controller in MAN mode 0 Nulls FEEDWATER MASTER CONTROL setpoint error by adjusting Thumb/Setpoint tape to align setpoint (orange arrow) directly under automatic setpoint (green band) 0 Places FEEDWATER MASTER CONTROL M/A station mode switch in AUTO or BAL 0 Confirms system response by adjusting the thumbwheel on FEEDWATER MASTER CONTROL to maintain RPV water level BOP D Enters N1-SOP-16.1 due to failure of FWLC Takes manual control of Feedwater pump 13 FCV NRC Scenario 4 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 3 Continued BOP Continued 0 Manually restores RPV water level to normal band If directed to shift FWLC pressure/level columns:
0 Coordinates with RO to return Note: Once the FWP 13 VALVE CONTROL M/A FWLC to auto:
STATION mode switch is in BAL, manual FWLC is 0 Places FWP 13 VALVE shifted to the RO at E-panel CONTROL M/A STATION mode switch in BAL Dispatch NAO to investigate Role Play: When directed as NAO to check ATS indications at ATS Cabinet cabinet indication, wait 2 minutes and report that PT 36-076 is downscale with the gross failure light lit NRC Scenario 4 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 4 PO-4.0 Service Water Pump Discharge Strainer High D/P CREW When directed by the examiner, insert Acknowledge/respond to annunciator malfunction: HI-3-2, SERVICE WTR P STR 11-12 TRIP-LO VOLT DlFF PRESS CWIGA, SW PUMP 11 STRAINER 72-05 CLOGGING, FINAL VALUE=10%
TRG 2 Expected Annunciator:
HI-3-2, SERVICE WTR P STR 11-12 TRIP-LO VOLT DlFF PRESS SRO Acknowledge report of SW Annunciator Direct entry into ARP for HI-3-2 Acknowledge report that SW strainer BV-72-408, Backwash VLV is open and that D/P is not lowering Determine the alarm cannot be cleared Direct shifting to SWP 12 per N1-OP-18 section F.2.0 Acknowledge report that SWP 12 has been started Acknowledge report of current DIP NRC Scenario 4 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 4 Continued RO B Monitor plant parameters BOP Enter ARP for H I-3-2 Role Play: When directed as NAO to investigate, Direct an NAO to the Intake area to wait two minutes, then report that Service \Water check the SW Pump Strainer pump 11 Strainer D/P is 10 psid and slowly rising IF strainer D/P is high perform the following:
Role Play: When directed as NAO to verify Confirm BV-72-408, ADAMS STRNR strainer backwash valve, 72-408 open, wait one 11 Backwash VLV open minute, then report that 72-408 is open, backwash Determine the alarm cannot be is in progress, but it does not appear to be lowering cleared D/P Start SWP 12 per N1-OP-18, Sect. F.
Place the SERVICE WTR PUMP 12 control switch at H Panel in Start Role Play: When directed as NAO to repc'rt on Observe normal motor running pump start, immediately report that SWP 12 is current, system flow, and discharge operating normally pressure Role Plav: When requested as NAO after start of Service Water Pump 12, report Service Water Pump 12 Adams Strainer D/P is 3 psid, and report that Service Water Pump 11 Adams Strainer DIP is 9 psid (if still running)
NRC Scenario 4 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 5 PO-5.0 Main Steam Line Radiation Monitor 111 Fails hop CREW Acknowledge/report Annunciator FI-When directed by the examiner, insert 2-7, MAIN STEAM RAD MONITOR malfunction: CH 11 HVLO Diagnose failure of MSL Rad Monitor RMIA, MAIN STEAM LINE RAD MONlTOlR 111 111 INOP TRG 3 Expected Annunciator:
F1-2-7, MAIN STEAM RAD MONITOR CH I 1 H I/L0 SRO Acknowledges report of MSL Rad Monitor Ch 11 alarm Directs execution of ARP for F1-2-7 Acknowledges report that MSL Rad Monitor has failed Notifies WEC and requests Role Play: When requested to investigate the investigation of the failure MSL rad monitor failure, report that you will begin Enters TS Table 3.6.2.h (requires an immediate investigation placing channel in the tripped condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or verifying Mechanical Vacuum pump isolated)
Briefs crew on failure of MSL Rad Monitor RO Monitors plant parameters NRC Scenario 4 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 5 Continued 1 BOP Executes ARP for F1-2-7 Goes to back panel and determines the other MSL Rad Monitors indicate normal readings Observes downscale light on MSL Rad Monitor Ch 11 and diagnoses the Monitor is INOP Notifies crew that MSL Rad Monitor Ch 11 is INOP NRC Scenario 4 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 6 PO-6.0 Intake Structure blockage resulting in loss of the Intake Structure CREW Acknowledge/report annunciators:
When the SRO has declared the Tech Specs and H2-1-3, CIRCULATING WATER directed by examiner, insert malfunction and PUMP INTAKE LEVEL LOW annunciator: HI-4-3, SCREEN WASH PUMP-SCREEN TRIP LOW VOLT DlFF CWI2, CIRCULATING WATER INTAKE PRESS STRUCTURE BLOCKAGE(TRASH), FINAL HI-4-2 R. BUILDING SW VALUE=20% PRESS/SERV W. PUMP HDR TRG 4 PRESS H2-1-3, CIRCULATING WATER PUMP INTAKE Analyze fluctuating CW Pump amps LEVEL LOW, FINAL VALUE=CRYWOLF and diagnose loss of intake structure TRG 4 Circ Water Pumps 11 and 12 amps fluctuate Circ Water Pumps 1I and 12 eventually trip Expected Annunciators:
H2-1-3, CIRCULATING WATER PUMP IN7AKE LEVEL LOW H1-4-3, SCREEN WASH PUMP-SCREEN 'TRIP LOW VOLT DlFF PRESS H1-4-2 R. BUILDING SW PRESS/SERV W. PUMP HDR PRESS SRO Acknowledge crew reports Directs execution of ARP for H2-1-3 Directs entry into N1-SOP-18.1 Direct rapid power reduction to reduce load for one Circ Water Pump Determine intake level is NOT being restored Direct a Reactor Scram NRC Scenario 4 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 6 Continued RO D Monitor plant parameters D Rapidly lower Recirc Flow to lower power for one CW Pump operation When directed to manually scram:
Place Reactor Mode Switch in SHUTDOWN Recognize control rods did NOT fully insert BOP Execute ARP for H2-1-3 Dispatch an operator to the screen Role Plav: When dispatched as NAO to house to investigate investigate intake level, wait one minute anid report Enter N1-SOP-I 8.1 that there are some weeds on the traveling Determine problem is with intake bay screens, level in the intake is approximately 238 Trip one Circ Water pump and slowly lowering Monitor pumps taking a suction from the Forebay for abnormal operation Role Plav: When contacted as NAO to give an Request updates from NAO on intake update on intake level following a power reduction, level immediately report that intake level is 237 ;and still When directed by the SRO lowering at the same rate as before, and that the Trip the remaining CW Pump traveling screens will not rotate Verify one SW Pump operating Verify one SW Pump secured Perform actions of N1-SOP-I ,
Reactor Scram Note: When the plant is scrammed, an ATWS will Initiate Emergency Condensers occur, and subsequent actions in N1-SOP-18.1 Start ESW Pumps may be prioritized Secure SW Pump Close MSlVs Trip all Recirc Pumps NRC Scenario 4 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENTS 7 and 8 CREW ATWS and LOCA Diagnose failure of control rods to insert The following malfunctions are preset to c:ause Diagnose degrading primary an ATWS: containment parameters RD33A, CONTROL ROD BANK BLOCKED BANK 1, INSERT FAIL POSITION, FINAL VALUE=12 RD33B, CONTROL ROD BANK BLOCKED BANK 2, INSERT FAIL POSITION, FINAL VALUE=12 RD33C, CONTROL ROD BANK BLOCKED BANK 3, INSERT FAIL POSITION, FINAL VALUE=18 RD33D, CONTROL ROD BANK BLOCKED BANK 4, INSERT FAIL POSITION, FINAL VALU E=l2 RD33E, CONTROL ROD BANK BLOCKED BANK 5, INSERT FAIL POSITION, FINAL VALUE=12 Control rods partially insert Reactor power remains > 6%
When the mode switch is taken to shutdown, the following malfunction is automatically inserted:
RR29, RR LOOP RUPTURE (LOCA), DELAY TIME=3 MINUTES, RAMP TIME=4 MINUTES, FINAL VALUE=15%
TRG 18 Drywell leakage, humidity, pressure, and temperature rise NRC Scenario 4 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENTS 7 & 8 Continued ExpectedAnnunciators:
H2-4-7, DRYWELL WATER LEAK DETECTION SYS K2-4-3, DRYWELL PRESSURE HIGH - LOW SRO Acknowledges scram report Enters N1-EOP-2 due to reactor power above 6% when scram required Answers All rods in to at least 0 4 NO Answers Will the reactor stay shutdown without boron NO Exits N1-EOP-2, enters N1-EOP-3 Directs ADS bypassed Directs prevent Core Spray injection per N1-EOP-1 Att 4 Determines Reactor power is above 6% and RPV level is above -41 inches Directs terminate and prevent of all injection except boron and CRD, N1-EOP-1 Att 24 CT-1.O Directs RPV level lowered to at least
-Note: Further RPV level actions are detailed in
-41 inches Event 9 If an ERV is cycling:
Directs initiation of Emergency Condensers Directs open ERVs to lower RPV pressure to less than 965 psig Directs RPV pressure controlled below 1080 psig using Emergency Condensers and ERVs NRC Scenario 4 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENTS 7 & 8 Continued Monitors Figure M, Heat Capacity Temperature Limit Directs initiation of ARI Answers Turbine Generator on-line?
NO Answers Reactor power? above 6%
Directs Recirc Pumps tripped Directs execution of N1-EOP-3.1 Before torus temperature reaches 11OOF:
Records Liquid Poison tank level Directs Liquid Poison injection Acknowledge report that Primary Containment parameters (pressure, temperature, humidity) rising Enters N1-EOP-4 on high drywell pressure, high drywell temperature and/or high torus temperature Directs Containment Spray pumps in PTL When torus pressure exceeds 13 psig or before drywell temperature reaches 300°F:
Verifies inside Figure K, Containment Spray Initiation Limit Verifies that Recirc Pumps are tripped Directs trip of drywell cooling fans Directs initiation of Containment Spray per N I -EOP-1 Att 17 CT-3.0 Monitors Figure L, Pressure Suppression Pressure NRC Scenario 4 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENTS 7 & 8 Continued RO Provides scram report Bypasses Core Spray IV interlocks per N1-EOP-1 Att 4 by installing six jumpers inside Panel N When directed performs N1-EOP-3.1, Section 3 (driving rods) and/or 4 (manual scrams) (See actions below)
Reports when APRMs <6%
Reports status of control rod insertion
'ossible N1-EOP-3.1 Section 3 Actions:
Verify a CRD Pump running Place Reactor Mode Switch in REFUEL Place ARI OVERRIDE switch in OVERRIDE Install RPS jumpers (5, 6, 12, 13)
Reset the scram Insert rods to 00 using EMER ROD IN starting with high power regions of Note: Control rods will successfully insert using core (use LPRM indications)
RMCS If more drive pressure is required, then perform one or more of the following:
Note: RO will likely have to fully open the CRD Fully open CRD Flow Control flow control valve andlor close 44-04 in order to achieve rod movement via RMCS; these methods Valve (F panel) are preferential to closing 44-167 due to ability to 0 Close 44-04, Control Rod Drive perform from the control room and not preventing Water Cont V (F Panel) further scram attempts by blocking the charging 0 Close 44-167, Charging Water water header Header Blocking Valve (RB 237')
NRC Scenario 4 October 2008
I INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENTS 7 & 8 Continued RO Continued Possible N1-EOP-3.1 Section 4 Actions:
Place ARI OVERRIDE switch in OVERRlDE Note: When the RPS jumpers have been installed, 0 Install RPS jumpers (5, 6, 12, 13)
ARI is overridden, and the scram is reset, then 0 Reset the scram TRG 21 will activate. This runs a batch file which 0 Verify open 44-167, Charging Water deletes the following malfunctions: Header Blocking Valve (RB 237) 0 When the SDV is drained, then initiate RD33A, CONTROL ROD BANK BLOCKED a manual scram BANK 1 RD33B, CONTROL ROD BANK BLOCKED BANK 2 RD33C, CONTROL ROD BANK BLOCKED BANK 3 RD33D, CONTROL ROD BANK BLOCKED BANK 4 RD33E, CONTROL ROD BANK BLOCKED BANK 5 And inserts malfunctions:
RD33A, CONTROL ROD BANK BLOCKED BANK 1, FINAL VALUE=6 RD33B, CONTROL ROD BANK BLOCKED BANK 2, FINAL VALUE36 RD33C, CONTROL ROD BANK BLOCKEC)
BANK 3, FINAL VALUE=IO RD33D, CONTROL ROD BANK BLOCKED BANK 4, FINAL VALUE=8 RD33E, CONTROL ROD BANK BLOCKED BANK 5, FINAL VALUE=8 Control rods partially insert NRC Scenario 4 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENTS 7 & 8 Continued BOP D Bypasses ADS D Terminates and prevents all injection except boron and CRD per N1-EOP-1 Att 24:
CT-I .O Closes both FEEDWATER ISOLATION Valves 11 and 12 OR places FEEDWATER Pumps 11 Role Play: When directed as NAO to pull HPCI and 12 in PTL fuses FU-8 and FU-9, wait one minute and insert Selects Manual on 11,12 and 13 remote: FWP Valve Control selector switches FW24, REMOVAL OF HPCl FUSES FU8/FU9, Closes 11, 12 and 13 Feedwater FINAL VALUE=PULL FCV (Knurled Knob) full TRG 25 counterclockwise Directs NAO to remove fuses FU-8 Then report that HPCl fuses FU-8 and FU-9 have and FU-9 from Panel IS34 in the been pulled Aux Control Room Verifies closed, FEEDWATER PUMP 13 BLOCKING VALVE Verifies in MAN, FWP 11 BYPASS VALVE, AND set to zero output Verifies in MAN, FWP 12 BYPASS Note: Further RPV level actions are detailed in VALVE, AND set to zero output Event 9 Informs SRO when RPV water level reaches -41 inches If any ERV is cycling:
Initiates Emergency Condensers Manually opens ERVs to lower RPV pressure <965 psig NRC Scenario 4 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENTS 7 & 8 Continued BOP Continued Controls RPV pressure below 1080 psig with Emergency Condensers and ERVs Initiates ARI Verifies all Recirc Pumps tripped Initiates Liquid Poison as directed a Reports initial tank level Starts Liquid Poison pump 11 or 12 a Verifies RWCU isolated Places Containment Spray pumps in PTL Initiates Containment Spray (NI-EOP-1 Att 17)
Starts Containment Spray Pump 111 or 122 CT-3.0 Starts at least one of the other three Containment Spray Pumps May start Containment Spray Raw Water Pumps as needed for torus cooling Verifies Containment Spray flow Monitors containment pressure and temperature to ensure lowering trend Terminates Containment Sprays when drywell pressure is below 3.5 psig Reports containment spray terminated NRC Scenario 4 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS 0 Monitors DWP and reports if DWP reaches 3.5 psig, after spray is terminated 0 IF directed, initiates Containment Spray again NRC Scenario 4 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 9 Feedwater unavailablefor RPV injection CREW 0 Recognizes/reports failure of FWlVs If the crew terminates and prevents by closing the and/or FW FCVs to open FWIVs, then the following overrides will be automatically inserted to prevent re-opening of the valves :
OVR-5S5D1309 POS-3 1F10/31-03A POS C, FINAL VALUE=INSYS OVR-5S6D13012 POS-3 1F10/31-03A POS C, FINAL VALUE=INSYS TRG 19 If the crew terminates and prevents by placing FW pumps 11 and 12 in PTL, then the following malfunctions and overrides will be automatically inserted to fail all three FW FCVs closed:
FW24, FEEDWATER 13 FCV FAILS CLOSED FW28A, HPCl MODE FAILURE TO INITIATE 11 FW28B, HPCl MODE FAILURE TO INITIATE 12 OVR-SA144Pl D1354 SET IF27/1D15B MAN, FINAL VALUE=INSYS OVR-JA144Pl D1355 SET 1F27/ID15B AUTO, FINAL VALU E=lNSYS OVR-5A144P1A13100 1F27/IDl58 BAL R1, FINAL VALUE=O OVR-5Al45PlDI356 SET 1F28/ID15C MAN, FINAL VALUE=O.OO OVRBA145PI D1357 SET 1F28/ID15C AUTO, FINAL VALUE=O.OO OVRBAI 45P1AI3120 1F28/IDl5C BAL R'I, FINAL VALUE=O TRG 20 NRC Scenario 4 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 9 Continued SRO Acknowledges RPV water level below
-41 inches If torus temperature is above IIOOF, then directs level lowered until:
Power drops below 6%, OR Level drops to -84 inches (TAF)
Records final actual level Directs RPV injection with Condensate/Feedwater and CRD Acknowledge report that Condensate/Feedwater is not available for injection When RPV water level cannot be maintained above -109 inches, enters N1-EOP-8, RPV Blowdown Answers Are all control rods inserted to at least position 04?NO Answers Will the reactor stay shutdown without boron?
NO/UNKNOWN Directs terminate and prevent of all RPV injection except boron and CRD Directs Emergency Condensers initiated Answers Torus water level? Above 8 feet Directs open 3 ERVs CT-2.0 Returns to N1-EOP-3 at circle I O Answers Isany ERV open? YES NRC Scenario 4 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 9 Continued SRO Continued Waits until RPV pressure drops below 288 psig Answers Was level intentionally lowered before you entered N1-EOP-8? YES Returns to circle 9 Directs RPV injection between -109 inches and previous final actual level with Core Spray per N1-EOP-1 Att 4 CT-2.0 Acknowledges report of RPV level restored above -109 inches RO/BOP e Acknowledges direction to re-establish RPV injection with Condensate/Feedwater and CRD Attempts to re-inject with Condensate/Feedwater per N1-EOP-1 Att 24:
Reopens at least one FEEDWATER ISOLATION Valve 11 and / or 12, if closed in step 2.1 OR Restarts FEEDWATER Pumps 11 and/or 12, if shutdown in step 2.1 (if required)
NRC Scenario 4 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS EVENT 9 Continued RO/BOP Continued 0 IF RPV level restoration is required using the FEEDWATER System, THEN, Position FEEDWATER FCV 1Iand/or 12 to maintain required RPV level Reports Condensate/Feedwater not available for RPV injection Reports RPV water level below -109 inches Re-establishes terminate and prevent lineup per N1-EOP-1 Att 24 as necessary Initiates Emergency Condensers Opens 3 ERVs CT-2.0 Re-establishes RPV injection using Core Spray per Nl-EOP-1 Att. 4:
CT-2.0 0 Installs Core Spray Jumpers 0 Throttles Core Spray Inboard IV(s)
(40-01, 40-09,40-I 0,40-I 1) as necessary to restore RPV level above -109" and maintain Core Spray within NPSH limits Reports RPV water level restored above -109 inches TERMINATION CRITERIA 0 RPV Blowdown in progress 0 RPV water level above -109 inches and being controlled in assigned band 0 Containment pressure controlled in accordance with N1-EOP-1 Att 17 NRC Scenario 4 October 2008
INSTRUCTOR ACTIONS/
PLANT RESPONSE OPERATOR ACTIONS V. POST SCENARIO CRITIQUE A. N/A, NRC Exam VI. REFERENCE EVENTS AND COMMITMENTS A. Reference Events None B. Commitments
- 1. None VII. LESSONS LEARNED A. None NRC Scenario 4 October 2008
ATTACHMENT 7: R.EACTIVITYMANEUVER INSTRUCTION Reason for Reactivity Maneuver: Rod Pattern Adiustment STEP: 1 Parameter Expected Range Parameter Expected Range Actual-None Description of Step:
- 1. Lower reactor power to 90% using recirculation flow.
- 2. Perform attached control rod movement instructions.
- 3. Raise reactor power to 100% using recirculation flow at a ramp rate not to exceed 10% CTP per hour.
Critical Parameters to be verified DURING Step:
Critical Parameter I I
Limit Monitor I I
Frequency I Contingency I
None Comments I Notes:
Step Prepared by: Tohn Smith I Todau Step Reviewed by: Rob Cooper I Today REISTA Date REISTAISRO Date Approval to perform Step -Ed Brown I Today Step Completed by: I Shift Manager Dale SRO Date Page 23 S-REP3 Rev 03
UNIT ONE REACTlVlTv NEUVER REQUEST FORM Maneuver: NRC 2008 Scenr 4 Insert Cln..
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1 1
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