ML051320311
| ML051320311 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/28/2004 |
| From: | Hynes C FirstEnergy Nuclear Operating Co |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| Download: ML051320311 (100) | |
Text
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RTL# A5.670.AA 1/2-ADM-1357.F11 Page 1 of 1 Revision 0 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE: License Operator T raining/Licensed Requalif ication Training SUBDIVISION: Simu1ator SCENAR IO T ITLWNO.: 2005 NRC Initial License Exam COMPUTER CODE FOR L.P.: 1LOT6 Scenario No. 1 1
Revision Na. Uate 1 12-10-04 INSTR UCTlONAL SETTlNG: Sirnulat or APPROXIMATE DURATION: 1.5 Hours PREPARED BY:
Date REVIEWED BY:
Date APPROVED FOR IMPLEMENTATION:
Date BVPS-1 NRC Scenario 1 Page 1 of 28
INITIAL CXNWITOdS: .. IC-181, PW = NRC1; 100% Power, RCS Boron PPm.
. 1CH-P-1C, HHSKharging Pump 00s.
. PCV-1RC-456, PORV leakage. MOV-1RC-536, Block Valve closed with power maintained
. Flood warnings from heavy rains.
Maintenance investigating 1RW-P-1A, River Water Pump abnormal vibration/noise.
ADDITIONAL LINEUP CHANGES I STICKERS VOND MARKINGS EQUIPMENT STATUS DATWIME 00s TECHNICAL SPECIFICATION(S)
I PCV-1RC-456 1 Yesterday 1500 I 3.4.11.a I SHIFT TURNOVER INFORMATION
- 2. AOP-1.75.2, Acts of Nature - Flood is in effect. River water level is currently 671 feet and stable.
- 3. Train 6is the Protected Train.
- 4. Reduce reactor power to 75% at 12%/hr. to remove a condenser waterbox from service for cleaning.
SCENARIO SUPPORT MATERIAL REQUIRED 1OM-52.4.B, Load Following Reactivity Plan for 12Whr. Load Reduction Protected Train B Wall Plaque
I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENT #1 Reduce power to 75% at 12% per US directs load reduction in hour accordance with Reactivity Plan.
PO initiates load reduction per 1OM-52.4.6, Step 1V.A.
Set the desired terminal load on the SETTER.
Set the desired rate on the LOAD RATE thumbwheel (5%/min.
maximum).
As the turbine load reduces, maintain the valve position limiter approximately 5% above turbine load to prevent load excursions.
Turbine load and reactor power Depress the GO pushbutton.
decreasing at 12%/hr.
BVPS -1 NRC Scenario 1 3 of 28
I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE I After the governor valves are off the limiter, transfer the turbine control to the 1 stage pressure feedback mode by depressing the lST STG IN pushbutton AND verify the following:
- 1. The 1ST STG OUT lamp is OFF.
- 2. The lST STG IN lamp is ON.
After transfer to the 1ST stage pressure feedback mode, set the desired terminal load on the SETTER.
Set the desired rate on the LOAD RATE thumbwheel (5%/min.
maximum).
As the turbine load reduces, maintain the valve position limiter approximately 5% above turbine load to prevent load excursions.
Turbine Load and Reactor Power Depress the GO pushbutton.
lowering at 12% per hour BVPS -1 NRC Scenario 1 4 of 28
I INSTRUCTIONAL GUIDELINES ] PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 RO initiates RCS boration as necessary to maintain Tavg - Tref per 1OM-7.4.L, Step 1V.A and reactivity plan.
Estimate the volume of boric acid to be added to the RCS using any of the following:
- b. WAG tables
- c. Reactor Engineer approved computer based methods Estimate the rate of boron concentration change as a function of boric acid flow rate using 1OM-7.5, Figure 7-8, Boron Addition Rate, AND Table 1, Nomograph Correction Factors.
Place the 1MU control switch to Stop for greater than 1 second to allow the blender to unarm.
BVPS -1 NRC Scenario 1 5 of 28
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I Place 43/MU control switch to Borate.
Set FCV-1CH-l13A, Boric Acid to Blender FCV to the desired boric acid flowrate.
Set Boric Acid Integrator YIC-1CH-113 for the desired quantity.
- a. Reset Boric Acid Integrator YIC-1CH-113.
Start the Reactor Makeup Control System by placing 1MU control switch to Start.
Verify boric acid to blender flow on FR-1CH-113, Boric Acid Flow.
Operate the pressurizer spray as required to limit the difference between boron concentration in the pressurizer and that of the RCS to less than 50 PPm.
BVPS -1 NRC Scenario 1 6 of 28
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Verify boration automaticalIy stops when Boric Acid Integrator YIC-1CH-113 reaches the setpoint.
When boration is complete, perform the following:
- a. Place the 1MU control switch to Stop for greater than 1 second.
- b. Place 43/MU control switch to Auto.
C. Reset Boric Acid Integrator YIC-1CH-113.
- e. Place the 1MU control switch to Start.
BVPS -1 NRC Scenario 1 7 of 28
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE ]
EVENT #2 Valve Position Limiter Failure (Load Rejection)
When directed, insert the following Crew acknowledges alarms, notifies command: Annunciators: US and investigates.
IMF TUR15 (0 0 ) 60 [A4-461, Tavg Deviation from Tref
[A4-1241, Rod Control Bank D Low Low (Possible)
[A4-12], Pressurizer Control Low Crew informs US of the loss of Pressure Deviation electrical load.
[A4-521, Delta Flux Out of Target Band Rods stepping in.
Tavg increasing US refers to AOP-1.35.2.
Steam dump valves opening.
RCS pressure increasing.
MW decreasing.
RO places control rods in AUTO.
Control rods inserting. Tavg dropping to Tref.
Crew sounds standby alarm and announces Unit 1 load rejection.
BVPS -1 NRC Scenario 1 8 of 28
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 RO may initiate emergency boration.
EHC system normal except for valve PO verifies normal EHC operation.
position limiter.
Valve position limiter failure; vibration Crew checks if governor valves have and load satisfactory for condition. closed in sequence, checks turbine vibration recorders.
Crew monitors for subsequent load reductions > 90 Mwe.
Generator load > 270 MW and vacuum Crew checks if turbine should be is greater than 27 inches HG. tripped, verifies load is greater than 270 MW and if vacuum is adequate.
Generator output breakers closed. PO verifies if the main generator is on Generator volts, amps, and power factor line.
satisfactory.
Tavg lowering to Tref value RO checks Tavg-Tref within 2°F.
PO resets steam dump controller:
BVPS -1 NRC Scenario 1 9 of 28
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Steam dump valves closed. . Verifies steam dump valves closed Steam dumps reset. Places steam dump control mode to reset Allows switch to spring return to Tave position Bistable lights extinguished. Verifies load rejection bistables NOT lit PO reduces VPL setting to prevent turbine load from returning to pre-event value.
Reduce valve position limit setting to within 5% above governor control Intermittently reduce valve position limit setting until valve limiter light just comes ON US notifies Wadsworth (FE)System Control Center and Duquesne Light System Control Center.
Crew may perform actions to US directs I&C to investigate problem recover GV control from the valve with governor valve.
position limiter per 1OM-26.4.AK.
BVPS -1 NRC Scenario 1 10 of 28
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE I US checks for load reduction of > 15%
and informs Chemistry, if necessary.
TV-1CN-100 closed. Crew checks TV-1CN-100 closed.
Supervisory limits-normal. Monitor turbine supervisory limits.
Continue with scenario when Crew should review Tech. Specs 3.2.5, limiter problem is identified and 3.1.3.6 for compliance.
Tavg-Tref are matched, or at Examiners discretion.
US will review T.S. 3.4.8 for RCS sampling requirements if power changed by >15%.
BVPS -1 NRC Scenario 1 11 of 28
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENT #3 Pressurizer Pressure Transmitter RO notes alarm and informs US. Crew PT-445 Fails High Slowly refers to ARPs, if necessary.
When directed, insert the following command: Annunciators:
IMF PRS08E (0 0 ) 2500 120 [A4-91, Pressurizer Control Press High US refers to 10M-6.4.IF, Attachment 2.
(Other malfunctions pre-loaded) [A4-121, Pressurizer Control Press Deviation
[A4-131, Pressurizer Control Press High Pwr Relief Act RO closes PORVs.
PORV 455D and 456 open.
US refers to Technical Specifications
. T.S. 3.2.5 may apply if RCS pressure below DNB setpoint.
. T.S. 3.4.11.a may be referenced, but PORV remains operable in manual, capable of being cycled.
BVPS -1 NRC Scenario 1 12 of 28
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]
EVENT #4 SG Pressure Transmitter PT-485 Fails Low When directed, insert the following Crew responds to indications and command: alarms.
An nunciators:
IMF MSS16E (0 0 ) 0 [A7-491, Loop 2 Steamline Pressure Low or Press Rate Hi
[A7-50], Loop 2 Feedwater Flow >
Steam Flow
[A7-531, Aux Feed to Stm Gen Valves Not Fully Open Train A SG B Channel 3 MSS*PT485 fails low.
SG B Channel 3 steam flow drops (density compensation input).
SG B feed flow, NR level drops. PO notes problem with SG 8 level control, takes manual control of 1 FWS*FCV488, informs US.
1 FWS*FCV488 modulates closed in automatic.
BVPS -1 NRC Scenario 1 13 of 28
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 NOTE: Level deviation is SG B level deviation. Crew determines that steam pressure dependent on time of channel MSS*PT485 failed low.
establishing normal MFRV control to restore SG level.
US refers to 1OM-24.4.IF,Attachment 4.
NR level = 44%. US directs PO to restore SG B level to program level.
PO selects redundant channel for B SG steam flow signal (PT-488).
US directs PO to return feedwater control to AUTO when SG level is within normal range.
US refers to T.S. 3.3.2.1, and Table 3.3-3, items 1.e and 4.d.
U S identifies 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> requirement to place channel in the tripped condition.
BVPS -1 NRC Scenario 1 14 of 28
I I I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 Actions to trip bistables:
IOR XSO3C23 1 Protection Channel I l l door 18 open. US directs crew to trip associated bistables per 1OM-24.4.IF, Attachment 4 Table 1.
IMF BST-RCS157 (0 0) 0 BS-488C tripped.
IMF BST-RCSO56 (0 0) 0 BS-488B tripped.
DOR XSO3C23 Protection Channel I l l door 18 closed.
IOR XSO3C23 1 Protection Channel Ill door 35 open.
IMF BST-RCS092 (0 0) 0 BS-485A tripped.
IMF BST-RCS102 (0 0) 0 BS-485B tripped.
DOR XSO3C23 Protection Channel Ill door 35 closed.
US directs I&C to investigate failure of steam pressure channel.
PRIOR to next event, insert the Condenser Steam Dump Failure following command::
IMF MSSO7 (0 0 )
When bistables have been tripped and malfunction is inserted, continue with next event.
BVPS -1 NRC Scenario 1 15 of 28
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENTS #5,6, & 7 Turbine Trip - Partial Steam Dump Failure. Reactor Trip required; Auto and Manual Reactor Trip Failure; One SG ADV Fails Partially Open IMF TURO1 (0 0) Turbine trips. Crew determines that the turbine has tripped.
IMF MSSl2A (1 0) 100 (Pre-loaded)
RCS pressure and Tavg rising. US directs a manual reactor trip.
RO places reactor trip switch to Trip.
ATWS - reactor fails to trip automatically or when manual trip is attempted.
Crew identifies that the reactor failed to trip.
RO depresses BB-A reactor trip pushbutton to attempt reactor trip.
Crew enters FR-S.l. US transitions to FR-S.l and announces entry to crew.
BVPS -1 NRC Scenario 1 16 of 28
1 INSTRUCTIONAL GUIDELINES [ PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 Turbine tripped. PO verifies turbine is tripped.
PO/RO verifies TREF is decreasing CRITICAL TASK #1:
Insert control rods or initiate RCS boration.
Control rods inserting. RO places control rod group selector in Auto and verifies rods are inserting.
RO drives rods in manual after automatic rod motion stops.
All A W pumps are running. PO verifies AFW status.
TV-IMS-l05A, B open.
MOV-1FW-151A, B, C, D, E, and F open.
RO initiates emergency boration.
CH-P-1B started manually. Verifies at least one HHSl pump running.
MOV-1CH-350 open. . Opens MOV-1CH-350, Emergency Boration Valve.
1CH-P-2A(B) running in fast speed. . Starts Inservice Boric Acid Transfer Pump in FAST speed.
BVPS -1 NRC Scenario 1 17 of 28
I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Boration flow > 30 gpm. . Verifies emergency boration flow is greater than 30 gpm.
FCV-1CH-122 indicates > 75 gpm . Opens Chg Flow to Regen Hx Inlet Control Valve to establish greater than 75 gpm flow.
PRZR pressure < 2335 psig. RO verifies PRZR pressure < 2335 psig.
When directed to locally trip US dispatches operator to locally trip reactor, insert: the reactor.
TRG! 3 RO/PO alert plant personnel by sounding Standby alarm and announcing ATWS.
R I B A open.
RTB B open (30 sec delay).
Control rods drop.
Power decreasing.
PO verifies turbine tripped:
. All throttle or all governor valves are closed.
. All reheat stop or all Interceptor valves are closed.
BVPS -1 NRC Scenario 1 18 of 28
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I PO places both steam dump control interlock selector switches in Off.
MOV-MS-1OOA. 1OOB Shut. PO ensures reheat steam isolation by depressing reheat controller reset pushbutton and checks MOV-MS-1OOA
& B shut.
SI actuated. US determines that SI has actuated.
When time permits, US directs performance of first 10 steps of E-0.
AFW flow > 630 gpm. Crew verifies required AFW flow to the steam generators > 630 gpm.
RO checks reactor is subcritical.
Power range indicates < 5%. . Power range channels < 5%.
Intermediate Range SUR negative. . Intermediate range channels negative startup rate.
RO continues boration, as necessary.
BVPS -1 NRC Scenario 1 19 of 28
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Crew returns to E-0. US transitions to E-0.
RO verifies reactor tripped:
Reactor trip and bypass breakers open . Rx trip and bypass breakers are open m Rod bottom lights are lit Rod bottom lights lit.
Rods at bottom. . Rod position indication at zero Neutron flux decreasing Neutron flux is dropping RO sounds Standby alarm and announces Unit 1 reactor trip.
Throttle and governor valves closed. PO verifies turbine trip.
Main generator output breakers open. PO verifies generator trip.
Exciter circuit breakers open.
1AE and 1DF busses energized. PO verifies power to AC emergency busses.
E-0 immediate actions complete. SI actuated. RO verifies SI actuated.
. Depresses manual SI actuation pushbuttons.
BVPS -1 NRC Scenario 1 20 of 28
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I 1 INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 PO performs Attachment 1-K, Verification of Automatic Actions (Steps listed at end of scenario guideline.)
Stuck open ADV. TAVG decreasing. RO check RCS TAVG stable at or trending to 547".
Condenser steam dumps closed. . Stop dumping steam.
MOV-1MS-1OOA, B closed. . Verify reheat steam isolation.
Total AFW flow > 355 gpm. . Reduce total feed flow to minimize cooldown.
Main steam trip and bypass valves closed.
. Close main steam trip and bypass valves.
Recirc spray pumps not running. RO checks recirc spray pump status.
PORV 456 closed but leaking. RO checks PRZR isolated.
Spray valves at zero demand Safety valves closed Power available to PORV MOV's.
All other PORV MOV's open (except MOV-1-RC-537 previously closed).
BVPS -1 NRC Scenario 1 22 of 28
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE 1 EXPECTED STUDENT RESPONSE I PRT conditions normal. RO verifies PRT conditions are normal D/P between RCS and highest SG Crew checks if RCPs should be pressure > 200 psid. stopped.
Crew checks if any SGs are faulted.
SG A faulted. PO determines SG A pressure decreasing in uncontrolled manner.
Crew enters E-2. US exits E-0, enters E-2 and informs crew.
US directs STA to monitor CSF status trees.
Control room dampers shut. Timers PO initiates CREVS and verifies running; control room pressurizing. system activated.
When requested as U2 Operator, 2HVC8MOD201A-D closed. PO verifies CREVS actuated in U2 by report 2HVCkMOD201A-D closed 2HVCkMOD204A, B closed. requesting U2 CREVS status.
and 2HVCkMOD204A, B closed.
CRITICAL TASK #2:
Isolate steam flow out of and All yellow SLI marks lit. Crew verifies steam line isolation.
feed flow into faulted SG.
BVPS -1 NRC Scenario 1 23 of 28
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE EXPECTED STUDENT RESPONSE 1 SG 6 and C pressures stable. PO checks for any non-faulted SG.
SG A faulted. PO identifies SG Apressure decreasing in uncontrolled manner.
Crew isolates faulted SG.
Main and Bypass Feed Reg Valves . Check WI - previously verified.
closed.
EOP pre-emptive action. AFW throttle valves closed. (May have Close AFW throttle valves on been previously closed.) faulted SG.
. Direct locally closing MS-15.
PCV-MS-101A open. . Attempt to close atmospheric dump valve.
HCV-1MS-104 closed. . Close residual heat release valve.
When directed to close MS-23, PO directs locally closing MS-23.
insert the following command:
IMF MSS07 (0 0 ) 0 PO checks PPDWST level > 27.5 feet.
No SG levels rising in an uncontrolled Crew checks if SG tubes are intact.
manner.
BVPS -1 NRC Scenario 1 24 of 28
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I SI Termination Criteria met. Crew checks if SI flow can be reduced Crew enters ES-1.l. US transitions to ES-1.1, SI Termination and informs crew.
Scenario may be terminated upon transition to ES-1 .l.
BVPS -1 NRC Scenario 1 25 of 28
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Attachment 1-K, Verification of Automatic Actions Diesel Generators - BOTH RUNNING.
Check station instrument air header pressure - GREATER THAN 100 PSIG.
Ensure reheat steam isolation:
- a. Verify [MOV-1MS-1OOA, B]
CLOSED.
- b. Reset reheater controller.
Verify CCR Pumps - TWO RUNNING.
Align Neutron Flux Monitoring For Shutdown:
- a. Transfer NR-1NI-45, Nuclear Recorder to operable source and intermediate range displays.
Verify river water system in service.
- a. RPRW Pumps - TWO RUNNING.
BVPS -1 NRC Scenario 1 26 of 28
[ INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1
- GREATER THAN 20 PSIG.
Check If main steamline isolation required.
- a. Check the following:
. CNMT pressure - GREATER THAN 3 PSIG.
OR Steamline pressure - LESS THAN 500 PSIG.
. Steamline pressure high rate of change - ANY ANNUNCIATOR LIT.
Annunciator A7-41 Annunciato r A7-49 Annunciator A7-57
- b. Verify steamline isolation:
. YELLOW SLI marks - LIT Check CIB and CNMT spray status:
BVPS -1 NRC Scenario 1 27 of 28
I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]
. Containment pressure - HAS REMAINED LESS THAN 8 PSIG.
Verify ESF equipment status:
- b. Verify CIA by checking all ORANGE CIA marks - LIT
- c. Verify FWI by checking all GREEN FWI marks - LIT.
Verify power to both AC emergency busses.
Upon completion, report any discrepancies to SM/US.
BVPS -1 NRC Scenario 1 28 of 28
RTL# A5.670.M 1/2-ADM-1357.F11 Page 1 of 1 Revision 0 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE: License Operator Training/Licensed Requalification Training SUBDIVISION: Simulator SCENAR IO TITLUNO.: 2005 NRC Initial License Exam COMPUTER CODE FOR L.P.: 1LOT6 Scenario No. 2 Revision No. Date INSTRUCTlONAL SETTING: Simulator APPROXIMATE DURATION: 1.5 Hours PREPARED BY:
Date REVIEWED BY:
Date APPROVED FOR IMPLEMENTATION:
Date BVPS-1 NRC Scenario 2 Page 1 of 24
INITIAL CONDITIONS: . IC-182; PW = NRC2; 53% power, RCS Boron _ _ _ _ ppm
. CH-P-1C, HHSVCharging Pump 00s.
. PCV-1RC-456, PORV 456 leakage. MOV-1RC-536, Block Valve closed with power maintained
. Flood warnings due to heavy rains.
. Maintenance is investigating abnormal vibrationhoise on 1WR-P-1A, River Water Pump.
Turbine Control selected to First Stage In.
I ADDITIONAL LINEUP CHANGES I STICKERS I VOND MARKINGS I
I EQUIPMENT STATUS I DATE/TIMEOOS I TECHNICA L S PECIFICAT10N(SI I
PCV-1RC-456 Yesterday 1500 3.4.11.a SHIFT TURNOVER INFORMATION
- 1. AOP-1.75.2 is in effect. River water level is 671 feet and stable.
- 3. Train B is the Protected Train.
- 4. Reduce power to take the unit off-line due to circulating water intake clogging.
SCENARIO SUPPORT MATERIAL REQUIRED 1OM-52.4.B, Load Following Reactivity Plan for 12%/Hr Power Reduction Protected Train B Wall Plaque
r INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #1 Reduce Power US directs load reduction in accordance with Reactivity Plan.
PO initiates load reduction per 1OM-52.4.8, Step 1V.A.
Set the desired terminal load on the SETTER.
. Set the desired rate on the LOAD RATE thumbwheel (5Y0/min.
maximum).
As the turbine load reduces, maintain the valve position limiter approximately 5% above turbine load to prevent load excursions.
Turbine load and reactor power Depress the GO pushbutton.
decreasing at 12%/hr.
After the governor valves are off the limiter, transfer the turbine control to the 1 stage pressure feedback mode by depressing the lST STG IN pushbutton AND verify the following:
- 1. The lSTSTG OUT lamp is OFF.
BVPS 1- NRC Scenario 2 3 of 24
t i I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I
- 2. The lST STG IN lamp is ON After transfer to the 1ST stage pressure feedback mode, set the desired terminal load on the SETTER.
Set the desired rate on the LOAD RATE thumbwheel (5%/min.
maximum).
As the turbine load reduces, maintain the valve position limiter approximately 5% above turbine load to prevent load excursions.
Turbine load and reactor power Depress the GO pushbutton.
decreasing at 12%/hr.
RO initiates RCS boration as necessary to maintain TAVG - TREFper 1OM-7.4.L, Step 1V.A and reactivity plan.
Estimate the volume of boric acid to be added to the RCS using any of the following:
BVPS 1- NRC Scenario 2 4 of 24
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1
- b. WAG tables
- c. Reactor Engineer approved computer based methods Estimate the rate of boron concentration change as a function of boric acid flow rate using 1OM-7.5, Figure 7-8, Boron Addition Rate, AND Table 1 , Nomograph Correction Factors.
Place the 1MU control switch to Stop for greater than 1 second to allow the blender to unarm.
Place 43/MU control switch to Borate.
Set FCV-1CH-l13A, Boric Acid to Blender FCV, to the desired boric acid flowrate.
BVPS 1- NRC Scenario 2 5 of 24
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Set Boric Acid Integrator YIC-1CH-113 for the desired quantity.
- a. Reset Boric Acid Integrator YIC-1CH-113.
Start the Reactor Makeup Control System by placing 1MU control switch to Start.
Verify boric acid to blender flow on FR-1CH-113, Boric Acid Flow.
Operate the pressurizer spray as required to limit the difference between boron concentration in the pressurizer and that of the RCS to less than 50 PPm.
Verify boration automatically stops when Boric Acid Integrator YIC-1CH-113 reaches the setpoint.
BVPS 1- NRC Scenario 2 6 of 24
INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I When boration is complete, perform the following:
- a. Place the 1MU control switch to Stop for greater than 1 second.
- b. Place 43/MU control switch to Auto.
C. Reset Boric Acid Integrator YIC-1CH-113.
- e. Place the 1MU control switch to Start.
BVPS 1- NRC Scenario 2 7 of 24
[ INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENT #2 SG "B" Level Transmitter Fails High When directed, insert the following cornmand1 Annunciator:
IMF fWM16D (0 0) 100 [A7-521, SG Level 16 HI-HI PO refers to ARP NOTE: No system response US refers to 10M-24.4.lF.
occurs on failure of a single channel due to median signal select feature.
US refers to Technical Specifications TS 3.3.1.1item 14 and TS 3.3.2.1, items 5.a, 7.a.
BVPS 1- NRC Scenario 2 8 of 24
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENT #3 No. 1 EDG Trouble When directed, insert the following PO responds to alarm command: Annunciator:
IMF EPS11A (0 0 ) [A9-71, DG Trouble Crew dispatches Outside Operator to investigate local alarm.
Outside Operator reports EDG US refers to Technical Specification TS control power breaker open on No. 3.8.1.1, Action b.
1 EDG.
BVPS 1- NRC Scenario 2 9 of 24
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1 EVENT #4 Letdown Pressure Control Valve PCV-1CH-145 fails closed resulting in a Fails Closed In Auto loss of normal letdown.
When directed, insert the following RO responds to indications and command: alarms.
Annunciator:
IOR XO6AO87P (0 0 ) 1.O [A3-1071, NRHX Disch Press High RO notifies US. Refers to ARP Letdown backpressure rising. US may refer to AOP-1.6.7 or AOP-1.7.1.
Letdown flow lowering. RO reports 1CHS-FI150 indicates zero flow.
Crew minimizes any power changes in progress.
Letdown flow at 105 gpm. RO takes manual control of PCV-1CH-145 and restores letdown flow to previous value.
US contacts I&C to investigate failure Of PCV-CH-145.
BVPS 1- NRC Scenario 2 10 of 24
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #5 SG AMFRV Controller Fails In 1FWS-FCV478, Main Feed Reg Valve Auto controller fails closed.
When directed, insert the following PO recognizes feed flow problem, command informs US.
Annunciator:
IMF FWM15A (0 0) 0 300
[A7-451, Steam Generator 1A Level Deviation From Setpoint SG A feed flow lowering.
MFRV position and feed flow stabilize in US directs PO to take manual control manual control. of SG AMFRV and attempt to stabilize SG feed flow and level.
US directs I&C to investigate problem with SG A automatic MFRV control.
BVPS 1- NRC Scenario 2 11 o f 2 4
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENT #6 RCS Leak When directed, insert the following Crew responds to indications and command: alarms.
IMF RCS02A (0 0) 25 [A4-711, Radiation Monitor Hi US refers to AOP-1.6.7, Excessive Primary Plant Leakage.
[A4-721, Radiation Monitor Hi-Hi
[A1-351, Ctmt Air Total Pressure Hi/Lo RO checks if PRZR level can be Channel 1 maintained.
[A1-431, Ctmt Air Total Pressure Hi/Lo Channel 2 US requests SM to evaluate EPP.
RM-1RM-204 in alarm. RO controls charging flow as necessary to maintain PRZR level on program.
RM-1RM-215A, B in alarm. RO checks if VCT level can be maintained by normal makeup.
[RM-1MS-l02A, B, C], N-16 steam PO checks secondary plant radiation generator leak monitors normal. trends normal.
[RIS-SV1001, Condenser Air Ejector Vent normal.
BVPS 1- NRC Scenario 2 12 of 24
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1
[RM-BD-1011, High Capacity B/D monitor is normal PRT pressure, level, and temperature RO checks PRT conditions consistent normal. with pre-event values.
Slight rise in containment temperature RO checks containment temperature may not be noticeable. normal.
Aux. Bldg. radiation is normal. PO checks Aux. Bldg. radiation levels normal.
PRZR level remains stable RO isolates Charging and letdown to check for CVCS leakage NOTE: If contacted by US, SM RO restores charging and letdown.
may direct an emergency shutdown per 1OM-51.1.
US refers to T.S. 3.4.6.2.
When charging and letdown are restored, initiate the next event.
BVPS 1- NRC Scenario 2 13 of 24
I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENTS #7 & #8 RCS Leak Degrades into SBLOCA; RCS Loop B LOCA - 2000 gpm.
Train 6HHSKharging Pump Auto Start Failure; Train A ESF Components Must Be Started Manually.
When directed, insert the following command:
IMF RCS02A (0 0) 2000 300 [A4-4], Pressurizer Control Low Level Deviation Pre-loaded Commands: [A3-58], Charging Pump Discharge Flow High-Low TRGSET1 JPPLSI(IL)==l IMF SISOSA (1 0) RCS pressure and PRZR level dropping US orders reactor trip and enters E-0.
rapidly.
IMF INH40 (0 0) RO verifies reactor trip:
IMF SISlOA (0 0) Reactor trip and bypass breakers open. Reactor trip and bypass breakers open.
Power range < 5%. . Power range indication < 5%.
Crew enters E-O. Neutron flux dropping. Neutron flux dropping.
Throttle and governor valves closed. PO verifies turbine trip.
BVPS 1- NRC Scenario 2 14 of 24
I I 1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]
Main generator output breakers open. PO verifies generator trip.
Exciter circuit breaker open.
Only 1DF bus energized PO verifies power to AC emergency busses.
CRITICAL TASK #1:
Crew manually actuates at least SI Train A not actuated. RO determines Train A SI failed to one train of SIS actuated actuate automatically.
safeguards before transition to any ORP.
SI actuated both trains. RO manually actuates both SI trains.
Crew sounds Standby Alarm, announces Unit 2 Reactor Trip and Safety Injection.
1VS-F-4A Leak Coil Exhaust Fan PO checks leak collection exhaust fan running. running.
Start CTMT hydrogen analyzers.
RO verifies HHSl pumps are running.
CH-P-1B running . Manually starts HHSl Pump B.
BVPS 1- NRC Scenario 2 15 of 24
I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE 1 OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1 CH-P-1A not running. . HHSl Pump A does not start.
BIT flow indicated. RO checks high head SI to BIT flow indicated.
LHSl pumps are running. RO/PO checks both LHSl pumps are running.
MD AFW pumps not running. PO verifies AFW status.
TD AFW pump running. PO checks TO AFW pump is running.
TV-1MS-105A open. . TV-1MS-105A is open.
[A7-71 not lit. [A7-71is not lit.
All AFW MOVs open. PO verifies all AFW throttle valves are full open.
PO performs Attachment 1-K, Verification of Automatic Actions (Steps listed at end of scenario guide.)
BVPS 1- NRC Scenario 2 16 of 24
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[ INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE No SG levels rising in an uncontrolled PO checks if SG tubes are intact.
manner.
RCS pressure and PRZR level US determines RCS is not intact.
decreasing rapidly.
Crew enters E-1. US transitions to E-1 and informs crew.
CREVS not actuated or required PO checks if CREVS actuated.
CRITICAL TASK #2: D/P between RCS pressure and highest RO checks if RCPs should be SG pressure < 200 psid. stopped.
Crew trips all RCPs when RCS to highest S/G DIP criteria is exceeded (or due to ClB) and prior to exiting E-1.
All RCPs stopped. (May have been RO stops all RCPs if not stopped previously stopped.) previously.
Recirc spray not actuated. RO/PO checks recirc spray system status.
No SG pressures dropping in an PO checks if any SGs are faulted.
uncontrolled manner.
BVPS 1- NRC Scenario 2 18 of 24
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i INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I -K, Verification of Automatic Actions No. 2 EDG is running. No. 1 EDG did Diesel Generators - BOTH RUNNING.
NOT start.
. PO may attempt to start No. 1 EDG.
Check station instrument air header pressure - GREATER THAN 100 PSIG.
Ensure reheat steam isolation:
- a. Verify [MOV-1MS-1OOA, B]
CLOSED.
- b. Reset reheater controller Verify CCR Pumps - TWO RUNNING.
Align Neutron Flux Monitoring For Shutdown:
- a. Transfer NR-1NI-45, Nuclear Recorder to operable source and intermediate range displays.
BVPS 1- NRC Scenario 2 22 of 24
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE Verify river water system in service.
- a. RPRW Pumps - TWO RUNNING
- GREATER THAN 20 PSIG.
Check If main steamline isolation required.
- a. Check the following:
' CNMT pressure - GREATER THAN 3 PSIG.
. Steamline pressure - LESS THAN 500 PSIG.
OR Steamline pressure high rate of change - ANY ANNUNCIATOR LIT.
Annunciator A7-41 Annunciator A7-49 Annunciator A7-57
- b. Verify steamline isolation:
BVPS 1- NRC Scenario 2 23 of 24
I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I
. YELLOW SLI marks - LIT.
Check CIB and CNMT spray status:
. Containment pressure - HAS REMAINED LESS THAN 8 PSIG.
Verify ESF equipment status:
- b. Verify CIA by checking all ORANGE CIA marks - LIT.
- c. Verify FWI by checking all GREEN FWI marks - LIT.
Verify power to both AC emergency busses.
Upon completion, report any discrepancies to SM/US.
BVPS 1- NRC Scenario 2 24 of 24
RTL# A5.670.M 1/2-ADM-1357.F11 Page 1 of 1 Revision 0 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE: License Operator Training/Licensed Requalification Training SUBDIVISION: Simulator SCENARIO TITLUNO.: 2005 NRC Initial License Exam COMPUTER CODE FOR L.P.: 1LOT6 Scenario No. 3 Revision No. 1 Date 1 12-10-04 I NSTRUCTlONAL SETTING: Simu1at or APPROXIMATE DURATION: 1.5 Hours PREPARED BY:
Date REVIEWED BY:
Date APPROVED FOR IM PLEM ENTAT ION:
Date BVPS-1 NRC Scenario 3 Page 1 of 24
INITIAL CONDITIONS: IC-183; PW = NRC3; 25% Power, RCS boron at ___ ppm.
PCV-1RC-456, PORV 456 leakage. MOV-1RC-536, Block Valve closed with power maintained.
Flood watch remains in effect.
Turbine Control selected to First Stage In.
ADDITIONAL LINEUP CHANGES STICKERS VOND MARKINGS EQUIPMENT STATUS DATWIME 00s TECHNICAL SPECIFICATION(S) 1 PCV-1RC-456 1 Yesterday 1500 I 3.4.11.a I SHIFT TURNOVER INFORMATION
- 1. Train 6is the Protected Train
- 2. Raise power to 100% after a trip due to loss of all circulating water.
SCENARIO SUPPORT MATERIAL REQUIRED 1OM-52.4.A, Raising Power From 5% To Full Load Operation Reactivity Plan for 12%/Hr Power Ascension Protected Train B Wall Plaque
[ INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENT #1 Raise Power To 100% US directs power increase to 100% per 1OM-52.4.Al Step IV.F.19.
Conversion Economics requests Crew reviews/agrees with reactivity raising power to 100% at 12%/hr. plan. US approves for use. Crew begins power increase.
RO initiates dilution per 1OM-7.4.Nl Step 1V.A.
Estimate the volume of makeup water to be added to the RCS using any of the following:
- b. WAG tables
- c. Reactor Engineering approved computer based methods BVPS 1 NRC Scenario 3 3 of 24
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE I Estimate the rate of boron concentration change as a function of dilution water flow using 1OM-7.5, Figure 7-10, Boron Dilution Rate, AND Table 7-1, Nomograph Correction Factors.
Place the 1MU switch in Stop for greater than 1 second to allow the blender to unarm.
Place 43/MU control switch to DIL OR ALT DIL as directed by the SWUS.
Set AM-1CH-114, Blender Total Flow Set Point to the desired flow rate.
Set blender output Integrator YIC-1CH-168A to the desired quantity.
- a. Reset blender output integrator YIC-1CH-168A.
Log the flow totalizer indication, AND add to it the number of gallons set into the batch integrator.
BVPS 1 NRC Scenario 3 4 of 24
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Turbine load and reactor power Start the reactor makeup control increasing at 12%/hr. system by placing 1MU control switch to Start.
Operate pressurizer heaters to initiate automatic spray operation as required so that the difference in boron concentration between the RCS and pressurizer is < 50 ppm.
Verify dilution automatically stops when blender output integrator YIC-1CH-168A reaches the setpoint.
When dilution is complete, perform the following:
- a. Place 1MU control switch in Stop for greater than 1 second.
- b. Place the 43/MU control switch to AUTO.
C. Reset blender output integrator YIC-1CH-168A.
- d. Place the 1MU switch to Start.
BVPS - 1 NRC Scenario 3 5 of 24
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1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENT #2 Train ARW Pump Trips. Backup 1WR-P-1A trips, IWR-P-1B fails to auto Pump Manually Started start.
When directed, insert the following PO recognizes loss of 1WR-P-1A and command: Annunciators: reports to US.
IMF AUXlOA (0 0 ) [A1-401, CC WTR HT EXCH River WTR PP Disch Line APress Low
[A1-481,CC WTR HT EXCH River WTR US refers to AOP-1.30.2, River Water, PP Disch Line B Press Low Normal Intake Structure Loss.
[A1-591, Intake Struct River WTR PP Disch Line APress Low
[A1 -671, Intake Struct River WTR PP RO checks reactor plant river water Disch Line BPress Low pump status.
[A1-821, River Water PP Auto Start-Stop RO recognizes and reports 1WR-P-1B did not auto start.
1WR-P-1 B running RO manually starts 1-WR-P-16.
RO checks PI-1RW-l13A(B), CCR Heat Exchanger RW Pressure > 20 psig.
BVPS 1 NRC Scenario 3 7 of 24
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I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENT #3 Loss of 4KV Bus 1AE 1AE bus de-energized, No. 1 EDG fails to auto start.
When directed, insert the following Crew responds to indications and alarms.
command: Annunciators:
IMF EPS04E (0 0) [A8-105],4160V Emerg Bus 1AE ACB 1A10 Auto Trip
[A8-106],4160V Emerg Bus 1AE ACB US enters AOP-1.36.2, Loss Of 4KV 1E7 Auto Trip Emergency Bus.
[A8-109],4160V Emerg Bus 1AE Undervoltage
[A9-741, 480V Emerg Trans 1-BN RO starts standby charging pump.
Unde rvolt age
[A9-100], 125V DC Battery Charger 1 Failure
[A9-108], 125V DC Battery Charger 3 Failure If 1WR-P-1C, River Water Pump was PO starts No. 1 EDG.
previously racked onto 1AE Bus, it will auto start when EDG No. 1 is started.
US refers to TS 3.8.1.1 Action c BVPS 1 NRC Scenario 3 9 of 24
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENT #4 Loss of Feedwater FW-P-1A trips.
When directed, insert the following Crew identifies loss of main feedwater command: Annunciators: pump and SG feed flow.
IMF RNMO1A (0 0 ) [A7-371, Steam Generator Feed Pump Auto Stop
[A7-40], Steam Generator Feed Pump US directs RO to trip reactor and Disch Equalizing Press Low enters E-0.
Crew enters E-O. [A7-291, Reactor Trip & Low Tavg or SI Main Feedwater Valve Closed SG levels dropping.
BVPS 1 NRC Scenario 3 10 of 24
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENTS #5,6,7 SG B SGTR; No. 1 EDG Failure; MDAFW Train E Pump Fails To Auto Start; CIA Fails To Auto Actuate Pre-loaded Commands RO manually trips reactor Crew continues with E-0. RO verifies reactor trip:
Reactor trip and bypass breakers open. . Reactor trip and bypass breakers open.
Power range < 5%. . Power range indication < 5%.
Neutron flux dropping. Neutron flux dropping.
Throttle or governor valves closed. PO verifies turbine trip.
Main generator output breakers open PO verifies generator trip.
Exciter breaker open.
1AE bus de-energized; 1DF bus PO verifies power to AC emergency energized from offsite power. busses.
. PO recognizes and reports trip of No. 1 EDG.
BVPS 1 NRC Scenario 3 11 of 24
L INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE ]
SI not actuated and not required. RO checks if SI is actuated.
Crew enters ES-0.1. US directs transition to ES-0.1.
US directs STA to begin monitoring CSF status trees.
Crew sounds Standby alarm and announces Unit I reactor trip.
RCS TAvGtrending to 547F. Check RCS temperature stable at or trending to 547F.
PO maintains RCS temperature:
Check at least 1 MSlV open Check condenser available Set steam header setpoint slightly above existing steam header pressure Place steam dump controller in Manual Verify demand is zero BVPS 1 NRC Scenario 3 12 of 24
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I Place steam dumps in STM PRESS Mode Place steam dump controller in AUTO Adjust controller setpoint to as necessary to maintain RCS t emperature Instrument air pressure > 100 psig. PO checks station instrument air header pressure > 100 psig.
PO checks feedwater status.
RCS TAVQ< 554F. RCS TAva - Less than 554F.
All MFRVs closed. 8 Verify Main Feedwater Reg Valves
- Closed 8
CRITICAL TASK #1: No AFW pumps running. 8 Check AFW Pumps - ANY Running Crew establishes the minimum required AFW flowrate to the B MD AFW and TD AFW pumps running.
. PO manually starts FW-P-2 and FW-P-36 SGs by manually starting an AFW pump.
Bypass FRVs closed. 8 Close Bypass FRVs MFPs stopped. 8 Stop all but one Main Feed pump BVPS 1 NRC Scenario 3 13 of 24
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[ INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I LHSl pumps running. RO/PO checks both LHSl pumps are running.
PO verifies AFW status.
AFW flow > 355 gpm. Total AFW flow > 355 gprn.
AFW throttle valves fully open. . AFW throttle valves are full open.
NOTE: CRITICAL TASK #2 is PO performs Attachment 1-K, performed as part of Attachment Verification of Automatic Actions 1-K actions. (Steps listed at end of scenario guideline.)
RCS TAVG controlled on steam dumps. PO verifies RCS TAVG stable or trending to 547*F.
Recirc spray pumps not running. RO/PO checks recirc spray pump status.
PORVs closed RO checks PRZR PORVs, safety and spray valves.
Safety valves closed.
Spray valves at zero demand.
PRT conditions normal. RO checks PRT conditions are normal.
BVPS 1 NRC Scenario 3 16 of 24
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE ]
Power available to PORV MOVs Block MOVs open (except previously closed MOV-1RC-536); PORVs in AUTO.
D/P between RCS pressure and highest RO checks if RCPs should be SG pressure < 200 psid. stopped.
No SG pressures dropping in an PO checks if any SGs are faulted.
uncont rolled manner.
Secondary radiation high.
SG B level rising in an uncontrolled PO checks if SG tubes are intact.
manner.
Crew enters E-3. US makes transition to E-3 and informs crew.
CREVS not actuated, nor required. PO checks if CREVS is actuated.
CIB not actuated.
RM-1RM-218A, B not in high alarm.
BVPS 1 NRC Scenario 3 17 of 24
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I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1 1MS-16 closed. Crew dispatches an operator to close TD AFW pump steam supply valve.
PO verifies steam supply from intact SG.
PO restarts TDAFW pump.
TV-1MS-11 1B closed. PO closes SG B pre-nrtrn drain isolation valves.
TV-1 MS-101B closed. PO closes SG B main steam trip, bypass, and non-return valves.
MOV-1MS-101B closed.
NRV-1MS-1016 closed.
SG B level > 13%. PO checks ruptured SG level.
EOP pre-emptive action. SG B AFW throttle valves closed. (May Crew isolates feed flow to SG B.
have been previously performed.)
Main feedwater isolated. PO checks FWI - previously verified.
BVPS 1 NRC Scenario 3 19 of 24
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I SG 6pressure > 380 psig. PO checks SG B pressure > 380 psig.
Instrument air header pressure > 100 PO checks instrument air header psig. pressure > 100 psig.
US determines target cooldown temperature based on SG B pressure.
US directs STA to trend cooldown rate.
Condenser steam dumps open. PO verifies condenser available and initiates cooldown at maximum rate, (or uses SG ADVs).
RCS pressure < 1950 psig. RO blocks steamline SI when RCS pressure reaches 1950 psig.
Tavg < 541°F PO defeats TAVG interlock during cooldown.
Total AFW flow > 340 gpm or SG level PO checks intact SG levels.
between 25% and 50%.
BVPS 1 NRC Scenario 3 20 of 24
I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I PORVs closed; MOVs open (except RO checks power to PORVs and block previously closed MOV-1RC-536). valves.
SI reset. RO resets SI CIA and CIB reset. RO resets CIA and CIB.
RCS at target temperature. PO stops RCS cooldown at target temperature.
Scenario may be terminated upon crew completion of cooldown to target temperature.
BVPS 1 NRC Scenario 3 21 of 24
I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 Attachment 1-K, Verification of Automatic Actions Diesel Generators - BOTH RUNNING.
Check station instrument air header pressure - GREATER THAN 100 PSIG.
Ensure reheat steam isolation:
- a. Verify [MOV-1MS-1OOA, B]
CLOSED.
- b. Reset reheater controller.
Verify CCR Pumps - TWO RUNNING.
Align Neutron Flux Monitoring For Shutdown:
- a. Transfer NR-1NI-45, Nuclear Recorder to operable source and intermediate range displays.
Verify river water system in service.
- a. RPRW Pumps - TWO RUNNING.
BVPS 1 NRC Scenario 3 22 of 24
I I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE I
- GREATER THAN 20 PSIG.
Check If main steamline isolation required.
- a. Check the following:
. CNMT pressure - GREATER THAN 3 PSIG.
. Steamline pressure - LESS THAN 500 PSIG.
OR Steamline pressure high rate of change - ANY ANNUNCIATOR LIT.
Annunciator A7-41 Annunciator A7-49 Annunciator A7-57
- b. Verify steamline isolation:
. YELLOW SLI marks - LIT.
BVPS 1 NRC Scenario 3 23 of 24
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 Check CIB and CNMT spray status:
. Containment pressure - HAS REMAINED LESS THAN 8 PSlG Verify ESF equipment status:
CRITICAL TASK #2: a. Verify SI status by checking all RED SIS marks - LIT.
Initiate at least one train of CIA b. Verify CIA by checking all prior to completion of ORANGE CIA marks - LIT attachment 1-K.
- c. Verify NVI by checking all GREEN FWI marks - LIT.
Verify power to both AC emergency busses.
Upon completion, report any discrepancies to SWUS.
BVPS 1 NRC Scenario 3 24 of 24
RTL# A5.670.M 1/2-ADM-1357.F11 Page 1 of 1 Revision 0 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE: License Operator Training/Licensed Requalification Training SUBDIVISION: Si mu lator SCENARIO TITLUNO. : 2005 NRC Initial License Exam COMPUTER CODE FOR L.P.: 1LOT6 Scenario No. 4 I Revision No.
1 1 Date 12-10-04 I 1 Revision No. I, Date 1 INSTR UCTlONAL SETTlNG: SimuIator AP PR 0X IMATE DURATION: 1.5 Hours PREPARED BY:
Date REVIEWED BY:
Date APPROVED FOR I MPLEMENTATION:
Date BVPS-1 NRC Scenario 4 Page 1 of 24
i i INITIAL CONDITIONS: .. IC-184; PW = NRC4; 75% Power, RCS boron at ppm.
PCV-1RC-456, PORV leakage. MOV-1RC-536, Block Valve closed with power maintained.
River water level has receded. Flood watch cancelled on last shift.
1WR-P-1A, River Water Pump 0 0 s .
Turbine control selected to First Stage In.
ADDITIONAL LINEUP CHANGES STICKERS VOND MARKINGS EQUIPMENT STATUS II DATEAIME 00s Yesterday 1500 II TECHNICAL SPECIFICATION(S) 3.4.11.a PCV-1RC-456 I I SHIFT TURNOVER INFORMATION
- 1. Protected Train is Train B.
- 2. Continue raising power to 100°/~at 12/70 per hour SCENARIO SUPPORT MATERIAL REQUIRED 1OM-52.4.BI Load Following Reactivity Plan for 12%/Hr Power Ascension Protected Train B Wall Plaque
I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #1 Raise Power US directs power increase to 100% per 1OM-52.4.B, Step IV.B.13.
NOTE: This event is not required to satisfy the qualitative or quantitative requirements of NUREG-1021 but may be performed at Chief Examiners discretion.
Crew reviews/agrees with reactivity plan. US approves for use. Crew begins power increase.
PO initiates turbine load increase.
- a. Set the desired terminal load on the SETTER.
- b. Set the desired rate on the LOAD RATE thumbwheel (5%/min.
maximum).
C. As the turbine load increases, maintain the valve position limiter approximately 5% above turbine load to prevent load excursions.
Turbine load and reactor power d. Depress the GO pushbutton.
increasing at 12%/hr.
RO initiates RCS dilution as necessary to maintain TnvG- THEFper 1OM-7.4.N, Step 1V.A.
BVPS 1- NRC Scenario 4 3 of 24
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Estimate the volume of makeup water to be added to the RCS using any of the following:
- b. WAG tables
- c. Reactor Engineering approved computer based methods Estimate the rate of boron concentration change as a function of dilution water flow using 10M-7.5, Figure 7-10, Boron Dilution Rate, AND Table 7-1, Nomograph Correction Factors.
Place the 1MU switch in Stop for greater than 1 second to allow the blender to unarm.
Place 43/MU control switch to DIL OR ALT DIL as directed by the SM/US.
Set AM-1CH-114, Blender Total Flow Set Point to the desired flow rate.
BVPS 1- NRC Scenario 4 4 of 24
[ INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]
Set YIC-1CH-l68A, Blender Output Integrator to the desired quantity.
- a. Reset Blender Output Integrator YIC-1CH-168A.
Log the flow totalizer indication AND add to it the number of gallons set into the batch integrator.
Start the reactor makeup control system by placing 1MU control switch to Start.
Operate pressurizer heaters to initiate automatic spray operation as required so that the difference in boron concentration between the RCS and pressurizer is < 50 ppm.
Verify dilution automatically stops when YIC-1CH-l68A, Blender Output Integrator reaches the setpoint.
BVPS 1- NRC Scenario 4 5 of 24
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I When dilution is complete, perform the following:
- a. Place 1MU control switch in Stop for greater than 1 second.
- b. Place the 43/MU control switch to Auto.
C. Reset YIC-1CH-l68A,Blender Output Integrator.
- d. Place the 1 MU switch to Start.
BVPS 1- NRC Scenario 4 6 of 24
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #t2 B MFW Pump Trip; Load FW-P-1B Trips. Crew responds to indications and Reduction Required alarms.
When directed, insert the following command: Annunciators:
IMF FWMO1 B (0 0 ) [A7-371, Steam Generator Feed Pump PO determines that 6Main Feed Auto Stop Pump tripped.
[A7-391, Steam Generator Fet 3 Pump Disch Flow Hi Start 2ndPump
[A7-451, Steam Generator 1A .eve1 US enters AOP-1.24.1, Loss of Main Deviation from Setpoint Feedwater.
[A7-53], Steam Generator 1B .eve1 Deviation from Setpoint
[A7-611, Steam Generator 1C Level PO verifies condensate pumps and Deviation from Setpoint heater drain pumps running.
Only FW-P-1A running. RO determines reactor power is >
65%.
If requested, SM should direct a US directs load reduction to 65%
load reduction at rate of 5%/minute. power at 5% per minute in accordance with AOP-1.51.l.
Crew alerts plant personnel of emergency shutdown.
PORVs 455C and 455D are available. Verify PORVs available.
BVPS 1- NRC Scenario 4 7 of 24
[ INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]
Crew initiates a plant shutdown.
PO sets turbine load setter at 5"/6 per minute.
RO determines required boration using the reactivity plan for rapid power reduction.
RO initiates emergency borating by performing 1OM-7.4.S, Emergency Boration.
Turbine load decreasing. PO depresses the reference control GO pushbutton.
After the governor valves are off the limiter:
Transfer turbine control to the 1
stage pressure feedback by depressing the 1 stage IN
. pushbutton.
Verify 1 stage OUT lamp is OFF and 1" stage IN lamp is ON.
Governor valves responding normally. Verify governor valve movement not excessive during load reduction.
BVPS 1- NRC Scenario 4 8 of 24
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Control rods in Auto. RO places control rods in AUTO and verifies Tavg is within +/- 5 F of Tref.
All PRZR heaters energized. RO places all PRZR heaters to On.
PO maintains valve position limit at 5%
above existing turbine load during the load reduction.
BVPS 1- NRC Scenario 4 9 of 24
1 INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENT #3 Dropped Control Rod K-6 Rod K-6 drops due to stationary gripper failure.
Insert malfunction following load Crew responds to indications and reduction, after crew has control of alarms.
SG level and TAVG is within 2F of TREF. Annunciators:
IMF CRF04BV (0 0 ) 1 [A4-591, NIS Power Range Low Setpoint Flux Deviation or Auto Defeat
[A4-67], NIS Power Range High Setpoint US refers to AOP-1.1.8, Rod Flux Deviation or Auto Defeat Inope rabiIity .
[A4-681, NIS Power Range Comparator
[A4-76], Computer Alarm Rod RO checks only 1 rod dropped.
Deviation/Seq Rod K-6dropped. US confirms 1 control rod dropped.
RO places control bank selector switch in Manual.
RCS TAVG> 541 F and stable. Crew checks RCS TAva > 541 F, within
+/- 4F of Tref and stable.
US determines power operation may continue if within 1 hour:
. Rod declared inoperable
. Verify shutdown margin requirements of TS 3.1.1.1 BVPS 1- NRC Scenario 4 10 of 24
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 Power reduced to less than 75%
High Neutron Flux Setpoint reduced to less than 85% within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
' Verify shutdown margin once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
' Request RE perform lncore Flux Map As Manager, Operations direct that US requests guidance from Manager, conditions remain stable while Operations on whether to withdraw determining cause of rod problem. misaligned rod.
Continue with scenario when US may refer to Technical Technical Specifications have Specification 3.1.3.1 Action c.3.
been addressed.
BVPS 1- NRC Scenario 4 11 of 24
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #4 Pressurizer Master Pressure RC-PK-444A fails in Auto, Manual Control Output Fails High control available.
When directed, insert the following Crew responds to indications and alarms.
command: Annunciators:
IOR X07A090P (0 0) 0 600 [A4-121, Pressurizer Control Low Pressure Deviation
[A4-11], Pressurizer Control Pressure RO takes manual control of PRZR Low Master Pressure Controller.
[A4-5], Pressurizer Power Oper. Relief Valve Open Spray valves open. RO reduces output of controller to close PORV and spray valves.
PORV 455C opens.
PRZR heaters energized. RO energizes PRZR heaters, as required.
US refers to TS 3.2.1 BVPS 1- NRC Scenario 4 12 of 24
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #5 Feed Flow Transmitter Fails High FT-1FW-497, SG C Channel 3 fails high slowly.
When directed, insert the following Crew responds to indications and command: alarms.
IMF FWM14F (0 0 ) 5E6 [A7-581, Loop 3 Feedwater Flow Greater Than Steam Flow
[A7-611, Steam Generator 1C Level Deviation from Setpoint
[A7-631, Steam Generator 1C Level Low
[A7-641, Loop 3 Steam Flow Greater US refers to 10M-24.4.IF, Attachment Than Feedwater Flow 2.
FCV-1FW-498 closes slowly. PO takes manual control of SG C Feed Reg Valve and adjusts SG level, as required.
FC-1FW-498 selected to FM-496 PO selects redundant feed flow position. transmitter for control.
FCV-1FW-498 in Auto. PO returns SG C Feed Reg Valve to Auto when SG level is stable within normal range.
BVPS 1- NRC Scenario 4 13 of 24
1 INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 When directed to trip bistables, insert the following:
IOR XSO3C23 (0 0 ) 1 Protection Rack 18 door open. US contacts I&C to direct tripping of bistables.
IMF BST-RCS058 (0 0) 0 BS-498B tripped.
IMF BST-RCSO59 (0 0) 0 BS-498C tripped.
DOR XSO3C23 Protection Rack 18 door closed.
US contacts I&C to investigate failure of FT-1FW-497.
BVPS 1- NRC Scenario 4 14 of 24
i I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE I EVENT #6 SG "C" Feedwa t e r ReguIating FCV-1FW-498 fails closed. Manual Valve Fails Closed control unsuccessful. Reactor Trip required.
When directed, insert the following PO takes manual control of SG "C" command: Feed Reg Valve.
IMF RNM07C (0 0) 0 120 US determines FRV failure is not recoverable.
Crew enters E-O. US directs RO to manually trip reactor and enters E-0.
RO verifies reactor trip:
Reactor trip and bypass breakers open. . Reactor trip and bypass breakers open.
Power range .:5%. . Power range indication < 5%.
Neutron flux dropping. . Neutron flux dropping.
Throttle or governor valves closed. PO verifies turbine trip.
Main generator output breakers open PO verifies generator trip.
BVPS 1- NRC Scenario 4 15 of 24
[ INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Exciter circuit breaker open.
1AE and 1DF busses energized by PO verifies power to AC emergency offsite power. busses.
SI not actuated and not required RO checks if SI is actuated.
Crew enters ES-0.1. US directs transition to ES-0.1 US directs STA to begin monitoring CSF status trees.
BVPS 1- NRC Scenario 4 16 of 24
[ INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE 1 OBJECTIVE I EXPECTED STUDENT RESPONSE 1 EVENT #7 Main Steam Line Break With MSlV Steam break downstream of MSlV B.
Failure When directed, insert the following Crew sounds Standby alarm and command: announces Unit 1 reactor trip.
IMF MSS02B (0 0 ) 1E7 Preloaded command for MSlV RCS temperature dropping. RO checks RCS temperature stable at failure. or trending to 547F.
CRITICAL TASK #1: Steam dump valves closed. . Stop dumping steam Close MSIVs prior to an Orange condition on the Integrity CSF MOV-1MS-1OOA, B closed. . Verify reheat steam isolation status tree.
SG blowdown valves closed. Verify SG blowdown isolated AFW flow throttled to < 355 gpm. . Throttle total feed flow > 355 gpm.
SG B MSlV open. . Close valves with YELLOW SLI marks SI actuated. US directs SI initiation or SI actuates.
Crew re-enters E-0. US re-enters E-0 and announces entry to crew.
Reactor tripped. RO reverifies reactor trip.
BVPS 1- NRC Scenario 4 17 of 24
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I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE 1 LHSl pumps running RO/PO check both LHSl pumps are running.
All red SIS lights lit. RO/PO checks all valves indicating lights with RED marks are LIT.
MD AFW and TD AFW pumps running. PO reverifies AFW status.
All SG AFW throttle valves open. PO verifies SG AFW throttle valves are full open.
PO performs Attachment 1-K, Verification of Automatic Actions (Steps listed at end of scenario guideline.)
TAVG stabilizing after MSlV closure. PO verifies RCS Tavg stable or trending to 547QF.
Recirc spray pumps not running. RO/PO checks recirc spray pump status.
PORVs closed. RO checks PZR PORVs, safety and spray valves.
BVPS 1- NRC Scenario 4 19 of 24
1 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Safety valves closed.
Spray valves at zero demand.
PORV MOVs open (except previously closed MOV-1RC-536).
D/P between RCS pressure and highest RO checks if RCPs should be SG pressure < 200 psid. stopped.
No SG pressures dropping in an PO checks if any SGs are faulted.
uncontrolled manner.
No SG levels rising in an uncontrolled PO checks if SG tubes are intact.
manner.
CNMT radiation, pressure and sump RO checks if RCS is intact.
levels at pre-event values.
Crew checks if SI flow should be reduced.
Crew enters ES-1.l,if SI US transitions to ES-1.1 and informs Termination criteria is satisfied. crew.
BVPS 1- NRC Scenario 4 20 of 24
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[ INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I Attachment 1-K, Verification of Automatic Act ions Diesel Generators - BOTH RUNNING.
Check station instrument air header pressure - GREATER THAN 100 PSIG.
Ensure reheat steam isolation:
- a. Verify [MOV-1MS-1OOA, B]
CLOSED.
- b. Reset reheater controller.
Verify CCR Pumps - TWO RUNNING.
Align Neutron Flux Monitoring For Shutdown:
- a. Transfer NR-1NI-45, Nuclear Recorder to operable source and intermediate range displays.
Verify river water system in service.
- a. RPRW Pumps - W O RUNNING BVPS 1- NRC Scenario 4 22 of 24
[ INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I
- GREATER THAN 20 PSIG.
Check If main steamline isolation required.
- a. Check the following:
. CNMT pressure - GREATER THAN 3 PSIG.
OR Steamline pressure - LESS THAN 500 PSIG.
. Steamline pressure high rate of change - ANY ANNUNCIATOR LIT.
Annunciator A7-41 Annunciator A7-49 Annunciator A7-57
- b. Verify steamline isolation:
YELLOW SLI marks - LIT.
BVPS 1- NRC Scenario 4 23 of 24
I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE 1 Check CIB and CNMT spray status:
. Containment pressure - HAS REMAINED LESS THAN 8 PSIG.
Verify ESF equipment status:
- b. Verify CIA by checking all ORANGE CIA marks - LIT
- c. Verify FWI by checking all GREEN FWI marks - LIT.
Verify power to both AC emergency busses.
Upon completion, report any discrepancies to SM/US.
BVPS 1- NRC Scenario 4 24 of 24