ML030220494
| ML030220494 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/16/2002 |
| From: | Hynes C FirstEnergy Nuclear Operating Co |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 50-412/03-302 50-412/03-302 | |
| Download: ML030220494 (64) | |
Text
RTL# A5.670.AA 1/2-ADM-1357.F11 Page 1 of 1 Revision 0 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE:
SUBDIVISION:
SCENARIO TITLE/NO.:
Unit 2 LOIT NRC Exam BVPS Unit 2 Simulator NRC Scenario #1 COMPUTER CODE FOR L.P.:
INSTRUCTIONAL SETTING:
APPROXIMATE DURATION:
PREPARED BY:
General Physics Cowp.
REVIEWED BY:
APPROVED FOR IMPLEMENTATION:
N/A Simulator 1.5 Hour 8/01/2002 Date Date Date 1
10/25/02 i
Appendix D Scenario Outline Form ES-D-1 Facility:
FENOC BVPS Unit 2 Scenario No. 1 Op Test No.:
2002-02 Examiners:
Candidates:
Demonstrate the ability to safely operate the plant during normal and upset conditions in accordance with plant procedures.
Initial IC 128 PW = NRC1: 100% power, Equ. Conditions, BOL, CB "D" at 225 Conditions:
Turnover:
2FWE*P23B OOS & will not be returned. Perform a normal power reduction to remove Main Feed Pump 2FWS-P21A from service.
Critical Tasks:
FR-S.1.C, Insert RCCAs.
E-1.C, Stop RCPs.
Event Malf. No.
Event Event Description.
No.
Type*
I 1
N (US)
Normal power reduction.
N (PO)
R (RO) 2 CNH CFWl2 C (PO)
"B" SG MFRV sticks in position during power reduction, C (US)
(Manual operation available).
3 BKR HIVO1 C (PO)
Loss of 4160V bus 2AE.
BKR HIV I1 C (US) 2-1 EDG output breaker fails to close; manual closure 4
available.
C (RO)
Manual start of 2CHS*P21B.
Pressurizer Pressure Master Controller fails high.
I (US) 6 IOR XB11035C M (ALL)
PORV fails open; PORV block valve leaks after being RCS 10A closed leading to reactor trip.
7 PPLOIA C (RO)
ATWS.
PPL01B C (US) 8 BKRHIVI3 C (US)
EDG No. 2 output breaker fails to close automatically (manual closure successful).
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor BVPS-2 NRC Sim #1 Rev 1.doc 2 of 29
Appendix D Scenario Outline Form ES-D-1 After taking the shift, the crew will lower power in preparation for removing a main feed pump from service.
After lowering power, the "B" SG Main Feedwater Regulating Valve (MFRV) sticks in position as the power reduction continues, resulting in a slowly rising SG level, requiring manual control of the sticking MFRV.
When SG level is stable with the MFRV in manual, a loss of 4160 Volt Emergency Bus "2AE" results in loss of the running charging pump (2CHS*P21A). EDG No. 2-1 will automatically start but its output breaker fails to automatically close and must be manually closed. Due to loss of 2CHS*P21A, the crew may start 2CHS*P21B while evaluating the manual closure of EDG 2-1 output breaker 2E10. When EDG 2-1 breaker is closed, crew will secure 1 charging pump.
After recovering, the Pressurizer Master Pressure Controller fails high, a PORV opens, Pressurizer heaters turnoff, spray valves open, and RCS pressure decreases. Manual control of Pressurizer heaters and spray valves is available; however, the PORV will remain stuck open and Pressurizer pressure will lower until the reactor automatically trips or the Unit Supervisor directs a manual reactor trip. When the crew attempts to close the PORV block valve, the block valve will shut, but will leak. The PORV will remain open and the block valve will leak for the duration of the scenario.
After the reactor is tripped, an ATWS occurs. Also following the reactor trip, the System Station Service Transformer "2B" trips, and EDG No. 2-2 output breaker 2F10 fails to close automatically but can be closed manually, restoring power to 4160 Volt Emergency Bus "2DF".
Expected procedure flow path is E-0 -+ FR-S.1--> E-0 -- E-1.
BVPS-2 NRC Sim #1 Rev 1.doc 3 of 39
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Program Title 2002 NRC Examination INITIAL CONDITIONS:
IC 128 PW = NRC1 100% BOL EQU XE, CBD = 225, RCS boron = 1576 ppm nitial Conditions REV 1
ADDITIONAL LINEUP CHANGES STICKERS VOND MARKINGS 2FWE*P23A 2FWE*P23A YCT N/A EQUIPMENT STATUS DATE/TIME OOS TECHNICAL SPECIFICATION(S) 2FWE*P23A 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ago TS 3.7.1.2, Action b SHIFT TURNOVER INFORMATION
- 1.
100%, BOL, EQU XE 1576 ppm CB "D" 225 steps.
- 2.
Reduce power to remove 2FWS-P21B from service due to bearing high vibration.
- 3.
Severe weather is expected.
- 4.
2FWE*P23A is OOS for motor replacement. Motor is removed and the pump will not be returned this shift.
SCENARIO SUPPORT MATERIAL REQUIRED Power reduction reactivity plan.
Load Follow Procedure 20M-52.4.B, step IV.B. 1.
BVPS-2 NRC Scenario 1 4 of 4
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BEAVER VALLEL TPOWER STATION Training Administrative Manual INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE [-EXPECTED STUDENT RESPONSE Shift positions:
US RO PO EVENT #1 Lower reactor power -5%.
Turbine load and reactor power reduction at 12%/Hr or less Following the Reactivity Plan, Crew lowers reactor power toward 60%.
US directs load decrease. Initiates turbine load decrease.
PO initiates turbine load decrease.
RO initiates RCS boration as necessary to maintain Tavg - Tref.
EVENT #2 "B" FWRV sticks after power has been lowered -5%.
"B" FWRV sticks in position. "B" SG Feed flow rises. "B" NR level rises.
IMF CNH-CFW12 (0 0) 1 NOTE: Level deviation dependent on time of establishing normal MFRV control to restore "B" SG level.
Alarm received:
A6-E10, SG 2B Level Deviation from Setpoint PO notes problem with "B" SG level control, valve and takes manual control of 2FWS*FCV488, inform US.
Crew refers to ARP's.
BVPS-2 NRC Scenario I
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BEAVER VALLE r POWER STATION Training Administrative Manual
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INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE US directs PO to restore "B" SG level to program value.
US notifies I&C of 2FWS*FCV488 problem.
EVENT #3 IMF BKR-HIV01 (0 0) 0 IMF BKR-HIV11 (0 0) 2 (preload)
Loss of 4160V Emergency Bus 2AE.
2DF bus remains energized. 2AE bus is deenergized. No. 1 EDG output breaker fails to shut automatically.
Alarms received:
[A8-C2], 4160V Emer Bus 2AE Undervoltage.
[A8-A2], 4160V Emer Bus 2AE ACB 2A10/2E7 Auto Trip.
2CHS*P21B running.
PO determines 2AE bus deenergized.
Crew responds per ARPs.
US/PO determine at least one AC emergency bus energized.
RO determines that no charging pumps are operating.
US directs RO to start 2CHS*P21B.
RO closes 2CHS-FCV122 & 2CHS HIV186 then starts 2CHS*P21B.
PO recognizes failure of ACB-2E10 to auto shut and informs US.
BVPS-2 NRC Scenario 1
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BEAVER VALLEY rJOWER STATION Training Administrative Manual I
INSTRUCTION GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I
Crew responds per 20M-36.2.
Running charging pump, 2CHS*P21A, CCP pump, 2CCP*P21A, and Service Water pump, 2SWE*P21A, deenergized.
EDG No. 1 output breaker shut. 4160V bus 2AE re-energized.
Loads sequence onto 2-1 EDG.
2 charging pumps operating.
Crew discretion as to which charging pump is secured.
2CHS*P21A or B secured.
IF requested insert:
IRF DSGO05 (0 0) 1 US directs PO to shut ACB-2E10, No.
1 EDG output breaker, and reenergize bus 2AE.
PO manually shuts ACB-2E10, EDG No. 1 output breaker and re-energizes bus 2AE.
RO ensures CCP flow to all RCP thermal barriers.
RO reports charging pump status.
US directs RO to secure 1 charging pump.
RO secures 1 charging pump.
US refers to T.S. 3.0.5 and 3.8.1.1 Reset of 2-1 EDG oil pump shunt trip.
BVPS-2 NRC Scenario I
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BEAVER VALLE I POWER STATION Training Administrative Manual INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE EXPECTED STUDENT RESPONSE_]
EVENT #4 IMF CNH-PCS10A (0 0) 100 Pressurizer Master Pressure Controller,
[2RCS*PK444A], output fails high.
PORV, [2RCS*PCV455C], open, PZR control heaters turn off, spray valves open, RCS pressure decreases rapidly.
Alarms received:
[A4-A 1], Pressurizer Power/Safety Relief Valve Trouble.
[A4-D1], Pressurizer Control Pressure High/Low.
[A4-E1], Pressurizer Control Pressure Deviation High/Low.
[A4-F1], Pressurizer PORV Open Permissive.
[A4-H3], Pressurizer Relief Tank Trouble.
RO notes indications and alarms, informs US.
US refers to ARP's.
RO notes failure of Pressurizer Master Pressure Controller and informs US.
BVPS-2 NRC Scenario 1 C
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BEAVER VALLE i POWER STATION Training Administrative Manual INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE EVENT 5 (partial)
IOR XB1IO35C (0 0) 0 (preload)
PORV Block Valve leaks after closing Manual Control of PZR Master Pressure Controller fails to close PORV, fails to control heaters, and fails to control spray valves.
Spray valves close. PZR heaters energized.
PORV remains open.
RCS pressure continues to decrease due to PORV failure. Charging flow increases.
PORV Block Valve closed.
RCS pressure continues to lower due to leaking PORV Block Valve.
US directs RO to place PZR Master Pressure Controller in manual, close spray valves and PORV and take manual control of PZR heaters.
RO uses individual component controls to shut spray valves and take manual control of PZR heaters, and attempts to close PORV.
Crew identifies PORV remains open.
US directs PORV Block Valve closed.
RO closes valve.
US contacts I&C to investigate failure.
EVENT 5 At examiners discretion:
IMF RCS10A (0 0) 0.5 PORV Block Valve leaking.
RAMP SMLRCS10(1) 0.05 1.0 60 (block valve leakage increases)
RCS pressure continue to decrease due to stuck open PORV and leaking block valve. Charging flow remains high.
RCS pressure dropping. Charging flow rising.
RO monitors RCS, identifies that RCS pressure is continuing to decrease.
US directs a manual reactor trip.
BVPS-2 NRC Scenario 1
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BEAVER VALLEY HOWER STATION Training Administrative Manual I
INSTRUCTION GUIDELINES
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I
I I
PLANT STATUS OR RESPONSE I OBJECT IVE I EXPECTEID SIULENI IZ5L' UN*L I
IMF PPLO1A (0 0) 1 (preload)
IMF PPLO1B (0 0) 1 (preload)
Manual reactor trip or automatic pressurizer pressure low reactor trip.
RO places reactor trip switch to trip.
Crew identifies that the reactor failed to trip.
ATWS - Reactor fails to trip automatically or when Manual trip is attempted.
Steps 1 - 5 of FR-S. 1 are immediate actions.
CT#1 - FR-S.1.C:
Crew inserts negative reactivity into the core by inserting RCCA's before completing the immediate action steps of FR-S.1.
Operators commence immediate actions for E-0 and FR-S. 1.
US refers to E-0 and makes transition to FR-S. 1.
SNA requested to monitor CSF status trees.
RO uses auto or manual rod control to insert rods.
CT#1 S/U Crew sounds standby alarm and announces Unit 2 reactor trip failure.
Rods inserting.
BVPS-2 NRC Scenario 1
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RCI I
ST T U R
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BEAVER VALLEýr r'OWER STATION Training Administrative Manual INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE
OBJECTIVE ]EXPECTED STUDENT RESPONSE After directed to locally open RTB's, insert:
IMF PPL02A (10 120)
IMF PPL02B (10 130)
IRF LOA-CRFO07 (10 150)
IRF LOA CRF008 (10 160)
TRG! 10 Report RTB's manually opened &
MG sets secured.
Crew dispatches an operator to locally open the RTB's.
CT#1 S/U Reactor tripped (time delay).
MG sets secured (time delay).
Turbine manually tripped.
FR-S.1 immediate actions complete.
Throttle, governor, reheat stop, and interceptor valves all closed.
Steam dump bypass interlock selector switches in OFF.
MSR steam supply block valves closed.
Reheat controller reset.
PO manually trips turbine.
PO verifies turbine trip.
PO places Condenser Steam Dump Selector Switches in "OFF".
PO ensures reheat steam isolation and depresses reheat controller "RESET" pushbutton.
NOTE: The following actions will not occur until AFTER the reactor trip breakers are opened, therefore, may occur at later time in scenario.
IMF SWD02C (2 45) (preload)
IMF BKR-HIV13 (0 0) 2 (preload)
SSST 2B trips 45 seconds after reactor trip.
2-1 EDG output bkr fails to auto close.
BVPS-2 NRC Scenario 1
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K BEAVER VALLELI r'OWER STATION Training Administrative Manual INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE]
2C, 2D & 2DF buses deenergized.
2F10 closed, 2DF energized, loads sequencing on EDG.
2FWE*P23A on clearance.
2FWE*P23B running.
TDAFW pump steam supply valves open.
AFW throttle valves full open.
HHSI pumps running.
2CHS*MOV350 open.
Boric acid transfer pump running.
Emergency boration flow > 30 gpm.
Charging flow path aligned through 2CHS*FCV122 with > 40 gpm flow.
PZR pressure < 2335 psig.
A5-4G, PZR LOW PRESSURE SAFETY INJECTION/ REACTOR TRIP lit.
PO reports loss of 2B SSST and 2-1 EDG output breaker auto closure failure.
US directs PO to close 2F10 breaker and verify loads sequence on EDG.
PO closes 2F10 and reports loads sequencing.
PO verifies AFW status.
RO initiates emergency boration of RCS.
RO checks PZR pressure less than 2335 psig.
Crew checks SI signal status, performs first ten steps of E-0 when time permits.
BVPS-2 NRC Scenario 1 12 of 12
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BEAVER VALLEL r'OWER STATION Training Administrative Manual INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE EXPECTED STUDENT RESPONSE]
S/G levels < 12% NR.
2CHS*FCV1 13B closed.
2CHS*FCV1 14A closed.
2CHS*FCV1 14B closed.
Uncontrolled cooldown not in progress.
Core exit temperatures less than 12007F.
PR NI's less than 5%.
IR NI's negative SUR.
Steps 1 - 7 of E-0 are immediate actions.
Previously completed.
Reactor locally tripped.
Rods bottom lights lit.
Flux decreasing.
PO checks S/G levels, verifies AFW flow is greater than 700 gpm. PO controls feed flow to maintain 12 (31%
adverse) - 50% S/G NR level.
RO verifies dilution paths isolated.
RO monitors RCS for uncontrolled cooldown.
US transitions to Step 16 of FR-S.1.
Crew verifies core exit temperatures.
RO verifies reactor subcritical.
US makes transition from FR-S. 1 back to E-0. Directs crew to perform E-0 immediate actions.
RO verifies reactor trip.
RO sounds standby alarm and announces Unit 2 safety injection.
Previously requested.
BVPS-2 NRC Scenario 1
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BEAVER VALLE i POWER STATION Training Administrative Manual INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE
-OBJECTIVE I EXPECTED STUDENT RESPONSE-]
E-0 immediate actions complete.
Throttle or governor valves closed, reheat stops or interceptor valves closed.
MSR steam supply block valves closed.
Reheat controller reset pushbutton depressed.
Main generator output breakers open.
Main generator volts ZERO.
Exciter circuit breaker open.
2AE and 2DF busses energized.
A5-4G, PZR LOW PRESSURE SAFETY INJECTION/ REACTOR TRIP lit.
SI actuation status light, A12-1D lit.
Both trains of SI manually initiated.
Automatic actions of A-0. 11 are SAT with the following exceptions:
2FWE*P23A OOS at turnover.
PO verifies turbine trip.
PO ensures reheat steam isolation.
PO verifies generator trip.
PO verifies power to AC emergency busses.
Crew checks if SI is actuated/ required.
US directs RO to manually initiate SI (both trains).
US direct operators to verify automatic actions by performing Attachment A 0.11, "Verification of Automatic Actions" when time permits.
Operator assigned to perform Attachment A-0. 11 reports status of Attachment to US/crew and any actions taken when completed.
BVPS-2 NRC Scenario 1 f
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BEAVER VALLE't POWER STATION Training Administrative Manual INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE Leak collection filtered exhaust fan status SAT RCS temperature trending to 547F Recirc spray pumps not running.
PZR pressure < 2310 psig.
PORV, [2RCS*PCV455C], failed open.
PORV block valve shut but leaking.
Crew enters E-1.
Radiation not in alarm status and CIB has not occurred.
CT#2 - E-1.C:
Crew trips all RCP's when RCS to highest S/G D/P criteria is exceeded and SI flow verified prior to exiting procedure E-1.
RCP's secured.
Crew verifies Leak collection filtered exhaust fan status.
RO reports Tavg status, US directs crew to control steam/feed flow as necessary to achieve desired status.
RO checks recirc spray pump status.
RO checks PZR isolated. PRT conditions normal.
RO verifies PORV Block Valve shut for open PORV.
US enters E-1 and announce entry to Crew.
PO checks Control Room habitability.
RO checks if RCP's should be stopped.
CT#2 S/U Recirc spray pumps not operating.
Both CNMT hydrogen analyzers operating.
RO reports Recirc Spray pmp status.
RO reports H2 analyzer status.
BVPS-2 NRC Scenario 1 15 of 15
BEAVER VALLE i POWER STATION Training Administrative Manual INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE EXPECTED STUDENT RESPONSE No S/G's faulted.
AFW flow > 340 gpm.
Power available to block valves.
[2RCS*MOV535] shut but leaking.
No SG levels rising in an uncontrolled manner.
Subcooling < 43'F.
Adequate secondary heat sink.
RCS pressure NOT stable or rising.
PO checks if S/G's are faulted.
PO checks intact S/G levels and control levels.
RO checks PRZR PORV and block valves.
RO verifies PORV block valve shut.
PO checks is SG tubes are intact.
Crew checks if SI flow can be terminated.
Crew determines SI flow CANNOT be terminated Terminate the scenario when the crew determines that SI flow cannot be terminated.
BVPS-2 NRC Scenario 1 I,
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RTL# A5.670.AA 1/2-ADM-1357.Fl1 Page 1 of I Revision 0 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE:
SUBDIVISION:
SCENARIO TITLE/NO.:
COMPUTER CODE FOR L.P.:
Unit 2 LOIT NRC Exam BVPS Unit 2 Simulator NRC Scenario #2 N/A INSTRUCTIONAL SETTING:
APPROXIMATE DURATION:
_______________________ I Simulator 1.5 Hour PREPARED BY:
REVIEWED BY:
General Physics Corp.
8/01/2002 Date Date APPROVED FOR IMPLEMENTATION:
Date
-I-ci 1
10/25/02 i
RTL A5.670.AA BEAVER VALLEY POWER STATION Training Administrative Manual Volume 3 Procedure 5-9 Revision 11 Figure 5-9.3 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE:
SUBDIVISION:
SCENARIO TITLE/NO.
Licensed Operator Initial Training BVPS Unit 2 Scenario #2 COMPUTER CODE FOR L.P.
INSTRUCTIONAL SETTING:
APPROXIMATE DURATION:
PREPARED BY:
SIMULATOR 1.5 Hours General Physics Corp.
REVIEWED BY:
Date APPROVED FOR IMPLEMENTATION:
Date BVPS-2 NRC Sim #2 Rev O.doc Revision No.
Date Revision No.
Date 8/1/2002 Date i
I I Of 1
Appendix D Scenario Outline Form ES-D-1 Facility:
FENOC BVPS Unit 2 Scenario No. 2 Op Test No.:
2002-02 Examiners:
Candidates:
_RO PO Obiectives:
Demonstrate the ability to safely operate the plant during normal and upset conditions in accordance with plant procedures.
Initial IC 127 PW = NRC2: 9% pwr, BOL, EQU XE, RCS boron = 2080 ppm, CB Conditions:
"D" = 116 steps.
Turnover:
Continue plant startup.
Critical Tasks:
E-0.I, Manually start HHSI pump.
E-3.A, Isolate SG.
E-3.B, Cooldown RCS.
E-3.C, Depressurize RCS.
Event Malf. No.
Event Event Description No.
Type*
1 R (RO)
Continue plant startup.
N (PO)
N (US) 2 NIS07B C (US)
Intermediate Range instrument power fuse blows.
3 XMT I (PO)
PT-464 fails low causing condenser steam dumps to MSS044A close.
I (US) 4 CNH MSS03B C (PO)
SG "B" atmospheric dump valve fails open.
C (US) 5 RCP06B C (RO)
"B" RCP high vibration with rising seal leakoff flow.
RCP01B c (Us) 6 RCS04B M (ALL)
"B" SG Tube Rupture.
Running HHSI pump trips.
PLP07A Standby HHSI pump fails to auto start (manual start 1
1_ available).
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor BVPS-2 NRC Sim #2 Rev 0.doc 2 of 2
Appendix D Scenario Outline Form ES-D-1 After taking the shift, the crew will continue the startup. An Intermediate Range channel instrument power fuse blows after power is > 10%. The RO verifies which instrument channel has failed, and the Unit Supervisor directs actions per the AOP and refers to Technical Specifications.
After referencing Technical Specifications, PT-MS-464 fails low causing the condenser steam dumps to close. Tavg rises causing automatic opening of the atmospheric steam dump valves.
Operator action is required to place the condenser steam dump controller in manual and re-open the valves.
An atmospheric steam dump valve then fails open requiring the crew to place the valve controller in manual and stabilize plant conditions.
After plant conditions have stabilized, RCP "2B" high vibration condition develops and continues to worsen. The crew will eventually trip the reactor and take the pump out of service.
Following the reactor trip, a SGTR occurs on SG "B", additionally, the running HHSI pump trips and the standby HHSI pump fails to auto start, but can be manually started.
Expected procedure flow path is EO --* E3.
BVPS-2 NRC Sim #2 Rev O.doc 3 of 3
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Program Title 2002 NRC Examination Initial Conditions REV 1
INITIAL CONDITIONS:
IC 127 PW = NRC2 9% BOL EQU XE, CBD = 116, RCS boron = 2080 ppm.
ADDITIONAL LINEUP CHANGES STICKERS VOND MARKINGS EOUIPMENT STATUS DATE/TIME OOS TECHNICAL SPECIFICATION(S)
SHIFT TURNOVER INFORMATION
- 1.
Plant is at 9% power, BOL, EQU XE, CB "D" at 116 steps, RCS boron = 2080 ppm.
- 2.
Continue the plant S/U to 100% JAW 20M-52.4.A step IV.3.
- 3.
Severe Weather is expected.
SCENARIO SUPPORT MATERIAL REQUIRED 20M-52.4.A step IV.3.
Reactivity plan.
BVPS-2 NRC Scenario 2 4 of 4
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BEAVER VALLE'Y H'OWER STATION Training Administrative Manual I INSTRUCTION GUIDELINES T
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE Shift positions:
US RO PO EVENT #1 Reactor at 9% power.
Status lights on Panel 308 actuate at 10%.
[A12-2B], NIS IR Trip Blocked, is ON.
[A12-2C], Power Range Low Setpoint Trip Blocked, is ON.
[A12-1H], NOT P-7 is OFF.
Crew commences power increase in accordance with reactivity plan.
RO commences raising reactor power to between 10 and 20%.
RO verifies P-10 bistables actuate as required as power increases to > 10%.
RO blocks the IR Trip and Rod Stop and verifies annunciator ON.
RO blocks Power Range low Overpower Trip and verifies annunciator ON.
RO verifies that annunciator NOT P-7 is OFF.
BVPS-2 NRC Scenario 2 Reactor Power Increase.
Continue reactor startup.
5 of 5
C BEAVER VALL.
,'OWER STATION Training Administrative Manual I INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE RO selects highest Power Ranges on N45.
EVENT #2 IRNI blown fuse.
After Crew has raised reactor power to greater than 10% and IR trips have been blocked, IMF NIS07B (0 0) 0 NI-36 Instrument power fuse fails.
Meters for NI-36 indicate zero and blown fuse indication exists on drawer.
[A4-4G], NIS Detector/Compensator Loss of Voltage.
RO acknowledges ANN's and identifies N-36 as the failed channel.
RO reports diagnosis to US.
US refers to AOP 2.2.1B, Intermediate Range Channel Malfunction. Verifies Unit is in Mode 1 and goes to Step 4.
Crew verifies power still greater than 10% and intermediate range trip is still blocked.
Crew places Level Trip Switch on failed channel to BYPASS.
BVPS-2 NRC Scenario 2
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BEAVER VALLEY POWER STATION Training Administrative Manual INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]
EVENT #3 After the startup continues IMF XMT-MSS044A (0 0) 0 2MSS*PT464 fails low.
Condenser Steam Dump Valves close.
Condenser Steam Dump demand 2RCS T1408 indicates zero.
2MSS-PI464A indicates zero.
Tavg rising.
Atmospheric Dump Valves open automatically.
Crew places Caution Tag on Source Range, which states "Manually unblock Source Range on Shutdown".
Crew places Caution tag on Level Trip Switch of failed channel.
US references Technical Specification 3.3.1.1.
US directs the Crew to continue with unit startup.
RO withdraws rods as directed.
RO/PO maintain reactor power, Tavg, and SGWL in preparation for unit synchronization.
PO determines Condenser steam dumps closed and informs US/RO.
PO identifies failure of 2MS*PT464 and informs US.
BVPS-2 NRC Scenario 2
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BEAVER VALLEY rOWER STATION Training Administrative Manual I INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE I EXPECTED STUDENT RESPONSE Alarms received:
[A6-7A], Steamline Pressure High.
Condenser Steam Dumps reopened.
US directs RO to take manual control of steam dumps.
RO opens Condenser Steam Dumps in manual.
US contacts I&C to investigate.
EVENT #4 IMF CNH-MSS03B (3 0) 100 (preload)
"B" SG Atmospheric Dump Valve fails open.
SG level deviation alarms may actuate.
PO identifies failed open Atmospheric Dump Valve and informs US.
US directs PO to take manual control of open ADV, and close the ADV.
RO places controller for "B" SG ADV in manual and closes ADV.
US requests I&C assistance.
US may refer to LR 6.1 for inoperable atmospheric dump valve.
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I INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I
EVENT #5 Insert the following:
IMF RCP01B (0 0) 1 300 IMF RCP06B (0 0) 15 IMF RCP06B (0 0) 21 1800 RCP 21B Seal Leakoff rising as indicated on 2CHS-FR154A.
[A2-5C], Reactor Coolant Pump Vibration Alert/Danger.
RCP 21B Vibration rises to >16 mils.
Shaft vibration > 15 mils and rising at >
1.0 mils/hr.
EVENT #6 IMF RCS04B (2 0) 500 (preload)
Steps 1 -7 of E-0 are immediate actions.
"B" SGTR when the reactor is tripped.
RO acknowledges RCP vibration alarm, informs US, refers to ARP A2 5C. Crew trends RCP vibration.
US enters AOP-2.6.8.
US proceeds to step 2.d of AOP 2.6.8 to address vibration problem.
When it is determined that RCP vibration is > 15 mils rising at >1 mil/Hr the US will direct a reactor trip and direct the stopping of RCP 21B after E-0 Immediate Actions are completed.
RO manually trips reactor.
RO informs US of a reactor trip.
RO/PO commence IMAs of E-0, US reference E-0 to verify IMAs.
BVPS-2 NRC Scenario 2
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BEAVER VALLEYi r'OWER STATION Training Administrative Manual I INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE I EXPECTED STUDENT RESPONSE Turbine trip due to reactor trip alarm A5 6D lit.
Rod bottom lights lit.
Neutron flux dropping.
Throttle or governor valves closed.
Reheat stops or interceptors closed.
MSR steam supply block valves closed.
Reheat controller reset pushbutton depressed.
Output breakers open.
Main generator volts ZERO.
Exciter ACB open.
2AE and 2DF busses energized.
RO verifies reactor trip.
RO sounds standby alarm, announces Unit 2 reactor trip.
PO verifies turbine trip.
PO ensures reheat steam isolation.
PO verifies generator trip.
PO verifies power to AC emergency busses.
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BEAVER VALLE'r H'OWER STATION Training Administrative Manual INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE F EXPECTED STUDENT RESPONSE NOTE: SI may not have actuated at this time however, RCS conditions are degrading due to "B" SGTR. If crew transitions to ES 0.1 at this time, they will be required to manually actuate SI and return here. This drill assumes SI is actuated at this time and the crew continues with E-O.
SI actuated on low PZR pressure A5-4H.
Immediate actions of E-0 complete.
"B" RCP secured.
Automatic actions of A-0.11 are SAT with the following exceptions:
2CHS*P21A failed to auto start on SI, manual start is successful.
2CHS*P21B tripped on SI and cannot be manually restarted.
RO reports SI status, manually actuates SI.
US directs RO to secure "B" RCP due to high vibration/seal leakoff trouble.
US direct operators to verify automatic actions by performing Attachment A 0.11, "Verification of Automatic Actions" when time permits.
Operator assigned to perform Attachment A-0. 11 reports status of Attachment to US/crew and any actions taken when completed.
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BEAVER VALLEY t POWER STATION Training Administrative Manual I INSTRUCTION GUIDELINES I
PLANT STATUS OR RESPONSE OBJECTIVE F EXPECTED STUDENT RESPONSE CT#1 - E-0.I:
Crew establishes flow from at least one high head ECCS pump before transition out of E-0.
2CHS*P21A manually started.
Leak collection filtered exhaust fan status SAT.
RCS temperature trending to 547F.
Recirc spray pumps not running.
PORVs closed (not leaking).
Spray valves closed.
Safeties closed (PSMS data).
PRT conditions normal.
PORV/block valve alignment SAT.
"B" RCP previously secured.
"A&C" RCPs running.
CCP flow normal.
No SG pressure dropping in an uncontrolled manner.
PO manually starts "A" HHSI pump &
reports actions/status to US.
Crew verifies Leak collection filtered exhaust fan status.
RO reports Tavg status, US directs crew to control steam/feed flow as necessary to achieve desired status.
RO checks recire spray pump status.
RO checks PRZR isolated.
RO checks if RCPs should be stopped.
PO checks if any SGs are faulted.
BVPS-2 NRC Scenario 2
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CT#1 - S/U 12 of 12
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I "B" SG level rising in an uncontrolled manner. Secondary rad monitors not consistent with pre-event levels.
Crew transitions to E-3.
CT#2 - E-3.A:
Crew isolates feed flow into and steam flow from the ruptured SG and directs operator to close isolations valve(s) operated from outside of the control room before a transition to ECA-3.1 occurs.
Control room habitability system not required.
"B" RCP previously secured.
"A&C" RCPs running.
CCP flow normal.
"B" SG level rising in an uncontrolled manner. Secondary rad levels higher than normal.
US directs operator to check if SG tubes are intact.
US makes transition to E-3 and informs crew.
US directs SNA to monitor status trees.
PO verifies control room habitability.
RO/PO check if RCPs should be stopped.
Crew identifies ruptured SG.
BVPS-2 NRC Scenario 2
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C BEAVER VALLEY POWER STATION Training Administrative Manual INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE -[OBJECTIVE
_ EXPECTED STUDENT RESPONSE IRF LOA-MSS010 (0 0) 0 IRF LOA-AFW026 (0 0) 0 Notify crew that 2MSS*16 is closed.
Also report 2SVS*28 closed when requested.
Adjust ruptured SG atmospheric steam dump controller setpoint to 100% and verify 2SVS*PCV101B closed.
2SVS*HCV104 - closed.
2SVS*28 - closed.
2MSS* 16 - closed.
2BDG*AOV100B 1 - closed.
2SDS*AOV1 1 1B1 - closed.
2SDS*AOV129A - closed.
2MSS*AOV101B, 102B - closed.
Verify closed "B" SG steam supply to TDAFW pump 2MSS*16 and to RHR valve 2SVS*28.
"B" SG narrow range level greater than 12%.(3 1% adverse).
2FWE*HCV100C & D closed.
Main feedwater isolation valve 2FWS*HYV157B closed.
Main feed reg valve 2FWS*FCV488 closed.
Main feed bypass valve 2FWS*FCV489 closed.
Ruptured SG pressure > 240 psig.
Crew isolates flow from ruptured SG.
CT#2 S/U PO checks ruptured SG level.
CT#2 S/U PO isolates feed flow to "B" SG.
CT#2 S/U PO verifies ruptured SG pressure greater than 240 psig.
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EXPECTED STUDENT RESPONSE CT#3 - E-3.B:
Crew establishes/maintains an RCS temperature so that transition from E-3 does not occur because the RCS temperature is in either of the following conditions: Too high to maintain minimum required subcooling for subsequent RCS depressurization, OR. Below the RCS temperature that causes a red or orange path challenge to Sub-criticality or Integrity CSF.
Based on ruptured SG pressure.
1000 - 1084 = 505F (480F).
900 - 999 = 492F (467F).
US determines target temperature for cooldown.
CT#3 S/U Steam dump is available, greater than 1 00°F per hour cooldown.
Condenser steam dump controller in auto with pot setting corresponding to current intact SG pressure.
RO blocks low steamline pressure SI when PRZR pressure is less than 1950 psig.
PO selects steam dump to steam pressure mode and dumps steam at maximum rate.
CT#3 S/U SNA monitors thermocouples.
PO stops cooldown when core exit TCs < target temperature.
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BEAVER VALLEL POWER STATION Training Administrative Manual INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE EXPECTED STUDENT RESPONSE Intact SG levels > 12% (31% adverse).
Power to PORVs & block valves SAT.
PORVs closed, not leaking.
PORV/Block alignment SAT.
Auto SI blocked A 12-1C lit.
SI signal A12-1D not lit.
Both trains of CIA reset.
CIB not actuated.
Station Air available.
Instrument air established to CNMT.
2IAC-MOV 131 - open.
2IAC-MOV 130 - open.
Inst Air HDR pressure > 85 psig.
RCS pressure > 225# (250# adverse).
LHSI Pmps stopped, in auto.
Cooldown stopped when at target temperature.
PO controls intact SG feed flow as required (340 gpm min) to achieve/maintain levels between 12%
(3 1%) and 50%.
RO verifies PORV/block valve conditions as expected.
RO resets CIA and CIB (both trains).
PO verifies/reports status of station air system.
Crew establishes Instrument Air to CNMT.
RO stops LHSI pumps and places them in auto.
Crew monitors temperature and stops cooldown at target temperature.
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BEAVER VALLE T POWER STATION Training Administrative Manual INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE IEXPECTED STUDENT RESPONSE CT#4 - E-3.C:
Crew depressurizes RCS to meet SI termination criteria before water release from the ruptured SG Safety or Atmospheric Relief Valve.
Ruptured SG pressure stable.
Subcooling > 61F (79F adverse).
PZR level < 75% (61%).
RCS subcooling > 41F (59F).
21A & 21C RCPs running.
Spray valves available. Both spray valves open.
IF AVAILABLE, 1 PORV will be used to assist depressurization.
Depressurization Termination:
PZR level >75% (61%)
OR RCS subcooling < value listed on Attachment A-5.1 OR BOTH RCS pressure < ruptured SG pressure, and PRZR level > 17% (38%).
PO verifies ruptured SG pressure stable.
Crew verifies Subcooling sat.
RO depressurizes RCS to minimize break flow and refill PRZR.
CT#4 S/U RO closes spray valves and PORV if used.
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BEAVER VALLE, POWER STATION Training Administrative Manual INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE [-EXPECTED STUDENT RESPONSE Terminate scenario upon completion of RCS depressurization.
Erase any vond marks associated with this drill.
EPP classification is an ALERT based on EPP/I-lb Tab 1.2, RCS Barrier.
SM declares an Alert within 15 minutes of entering E-3 (per TAB 1.2.4), informs crew, provides AA with notification form.
BVPS-2 NRC Scenario 2 18 of 18
RTL# A5.670.AA 1/2-ADM-1357.F11 Page 1 of 1 Revision 0 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE:
SUBDIVISION:
SCENARIO TITLE/NO.:
COMPUTER CODE FOR L.P.:
Unit 2 LOIT NRC Exam BVPS Unit 2 Simulator NRC Scenario #3 N/A INSTRUCTIONAL SETTING:
APPROXIMATE DURATION:
PREPARED BY:
REVIEWED BY:
General Physics Corp.
8/01/2002 Date Date APPROVED FOR IMPLEMENTATION:
Date 1
_ 10/25/02 Simulator 1.5 Hour i
Appendix D Scenario Outline Form ES-D-1 Facility:
FENOC BVPS Unit 2 Scenario No.: 3 Op Test No.:
2002-02 Examiners:
Candidates:
Demonstrate the ability to safely operate the plant during normal and upset conditions in accordance with plant procedures.
Initial IC 126 PW = NRC3: 100% pwr, BOL, EQU XE, RCS boron 1576 ppm, Conditions:
CB "D" = 225 steps.
Turnover:
2FWE*P23B OOS, 2FWE*P22 aligned to "B" header.
Critical Tasks:
E-O.A, Manually trip reactor.
ECA-O.O.B, Establish feedwater flow to at least one SG.
Event Malf. No.
Event Event Description No.
Type*
I 1
R (RO)
Normal power reduction.
N (PO)
N (US) 2 CNH-PCS09B I (RO)
Pressurizer level controller fails high.
I (US) 3 XMT-I (PO)
Selected feedwater flow transmitter fails high.
CFW055A I (US) 4 EHC06 C (All)
Main turbine valve position limiter failure (Load rejection).
5 HIVO0D M (All)
Loss of 4KV bus "2D" (condensate pump and feed pump trip).
6 FLX CFW07 Pipe rupture in condensate header.
7 PPLO1A C (RO)
Automatic reactor trip fails (manual trip available).
PPLO1B 8
LOA AFWOO1 Turbine driven AFW pump (2FWE*P22) fails to start.
LOA AFWO13 DSGO1B EDG No. 2 trips during loading after powering 4KV bus "2DF".
9 BKR HIV01 Loss of 4160V bus "2AE" after entering ES-0. 1.
LOA DSGO1 C (US)
EDG No. 1 fails to auto start (manual start available in ECA-0.0).
PPL07A C (PO) 2FWE*P23A fails to auto start on EDG sequencer, manual start successful.
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor BVPS-2 NRC Scenario 3 2 of 14
Appendix D Scenario Outline Form ES-D-1 After the crew has lowered reactor power, the Master Pressurizer Level Controller fails high.
Charging flow will increase causing actual Pressurizer level to rise. The crew must take manual control of Pressurizer level, halt the transient and restore level to program.
As Pressurizer level is being returned to normal, the selected feedwater flow transmitter fails high requiring manual control of feedwater flow to stabilize SG level.
Once conditions stabilize, a main turbine valve position limiter failure will result in a load rejection and the crew must stabilize the plant in accordance with the load rejection abnormal operating procedure.
When plant conditions have stabilized, a loss of 4160V bus "2D" results in a condensate pump and a main feed pump trip resulting in a reactor trip condition; however, automatic reactor trip will fail requiring the crew to manually trip the reactor.
Immediately following, a pipe rupture in the condensate header will cause a loss of suction to the remaining main feed pump. Additionally, the turbine driven AFW pump fails to start and will remain unavailable.
The loss of the 4160V bus "2D" also de-energizes 4160V bus "2DF". EDGNo. 2 will start, but trips after briefly powering the "2DF" bus. After the crew enters ES-0.1, a loss of 4160V bus "2AE" occurs and EDG No. 1 fails to automatically start when the "2AE" bus is de-energized.
EDGNo. 1, however, can be manually started in ECA-0.0 allowing the "2AE" bus to be recovered and making motor driven AFW pump (2FWE*P23 A) available.
Expected procedure flow path is EQ -
) ECA-0.0 -
ES-0.1 BVPS-2 NRC Scenario 3 3 of14
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Program Title 2002 NRC Examination Initial Conditions REV 1
INITIAL CONDITIONS:
IC 126 PW = NRC3 100% pwr, EQU XE, BOL, CB "D" 225 steps, RCS boron = 1576 ppm.
ADDITIONAL LINEUP CHANGES STICKERS VOND MARKINGS 2FWE*P23B PTL 2FWE*P23B YCT Fig 20M 24-3: 2FWE*36 closed 2FWE*102 open EQUIPMENT STATUS DATE/TIME OOS TECHNICAL SPECIFICATION(S) 2FWE*P23B OOS 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ago TS 3.7.1.2, Action b SHIFT TURNOVER INFORMATION
- 1.
100% pwr, EQU XE, BOL, CB "D" 225 steps, RCS boron = 1576 ppm.
- 2.
Reduce Power to remove 2FWS-P21B from service due to bearing high vibration.
- 3.
Severe weather is expected
- 4.
2FWE*P23B is OOS for motor replacement and will not be returned this shift. 2FWE*P22 is aligned to the "B" header.
SCENARIO SUPPORT MATERIAL REOUIRED Power reduction reactivity plan Load Follow procedure 20M-52.4.B step IV.B. 1 BVPS-2 NRC Scenario 3 (1
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PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE j Shift positions:
US RO PO EVENT 1 Lower power - 5%.
Turbine load and reactor power lowering at 12%/hr or less.
EVENT 2 US assumes control and directs Operators to lower reactor power to 60%.
Crew reviews/agrees with reactivity plan. US approves for use. Crew begins power reduction in accordance with the reactivity plan.
PO initiates turbine load reduction RO initiates RCS boration as necessary to maintain Tavg-Tref At Examiner's direction insert:
IMF CNH-PCS09B (0 0) 100 Master Pressurizer Level Controller fails high.
Charging pump flow increases.
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BEAVER VALLE' r-OWER STATION Training Administrative Manual INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE Alarms expected:
[A2-E3], Charging Flowpath Trouble
[A2-D4], Reactor Coolant Pump Seal Trouble PRZR Level Controller or Charging Pump discharge control valve in manual.
Alarms clear.
RO notes indications and alarms, -U informs US.
US directs RO to place PRZR level controller or Charging Pump Discharge Control Valve in manual.
RO takes manual control of PZR level.
US requests I&C to investigate Pressurizer Level controller failure.
EVENT 3 "C" SG Feed Flow Transmitter fails high.
IMF XMT-CFW055A (0 0) 5 Level Deviation Annunciator is dependent on operator action to manually control the "B" MFRV.
"C" SG Channel 3 Feed Flow Transmitter fails high.
PO acknowledges alarms, diagnoses problem, informs US.
"C" SG MFRV FCV-FW-498 modulates shut "C" SG level lowers.
Alarms expected:
[A6-F1 1], Loop C Feedwater Flow >
Steam Flow
[A6-D11], SG 21C Level Deviation from Setpoint BVPS-2 NRC Scenario 3
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C BEAVER VALLE'r r'OWER STATION Training Administrative Manual INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE FCV-FW-498 in manual.
US directs PO to take manual control of "C" MFRV and restore SG level to normal.
Crew refers to applicable ARPs, and Instrument Failure Procedure, 2OM 24.41F.
US informs I&C of SG steam flow transmitter problem.
EVENT #4 Insert:
IMF EHC06 (0 0) 50 Load rejection to 50% limiter position (approx. 600 MW). RCS temperature rises. SG level deviation alarms.
Condenser steam dumps open. Load rejection 15% - 50% status light A12-4A (C-7A actuated).
Crew recognizes load rejection.
US directs operators to stabilize the plant and refers to AOP-2.35.2.
US refers to AOP 2.35.2.
RO checks auto rod insertion, or drives rods and/or borates to match Tavg vs.
Tref.
Crew sounds standby alarm and announces Unit 2 load rejection.
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BEAVER VALLET r-'OWER STATION Training Administrative Manual INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE No EAL declaration is required.
VPL failed low, vibration and load satisfactory for condition. EHC Control transfers from partial to full arc mode.
Generator load > 270 MW Vacuum > 24.5 in Hg.
Generator output breakers closed.
Generator volts, amps, and p.f.
satisfactory.
Crew may perform actions to recover GV control from the valve position limiter; 20M-26.4.X is the appropriate procedure.
Load rejection bistables reset.
Crew checks operation of EHC system.
Crew checks if governor valves have closed in sequence, checks turbine vibration recorders, and EHC Control is transferring to full arc mode.
Crew monitors for subsequent load reductions > 90 MWE Crew checks if turbine should be tripped, verifies load is greater than 270 MW.
PO verifies if the main generator is on line RO checks Tavg - Tref within 5°F.
PO resets steam dump controller if necessary.
Crew notifies System Operator of load loss and reason (if determined).
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BEAVER VALLEt POWER STATION Training Administrative Manual INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE LR> 15%
2CNM-AOV 100 closed.
Supervisory limits normal.
US directs I&C to investigate problem with Valve position limiter.
US directs chemistry to sample as required for LR > 15%.
Crew checks 2CNM-AOV100 closed.
PO monitors all turbine supervisory limits, refers to 20M-26.4.ABD.
Continue with scenario when Tavg vs Tref is within 3°F OR when directed by evaluator.
EVENT 5 Insert the following:
IMF HIV1D (0 0)
IMF FLX-CFW07 (1 0) 20000 IMF PPLO1A (0 0) 0 (preload)
IMF PPL01B (0 0) 0 (preload)
TDAFW pump trips during startup IMF AFW03A (0 0) 5440 (preload)
Loss of 4KV bus "D".
Pipe rupture in Condensate Header.
Reactor fails to auto trip.
Crew identifies loss of 4KV bus "D",
2FWS-P21B, 2CNM-P21C and 2CNM-P21A.
RO notes that a reactor trip has not occurred.
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BEAVER VALLEi POWER STATION Training Administrative Manual INSTRUCTION GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE US refers to E-O to verify immediate actions while RO and PO commence immediate actions.
US directs RO to manually trip reactor.
CT#1 - E-O.A:
Crew manually trips reactor from the Control Room before performing the mitigation strategy of FR-S.1.
Steps 1 -7 of E-0 are immediate actions.
RO manually trips reactor.
CT#1 S/U RO/PO commence IMAs of E-0, US reference E-0 to verify IMAs.
Turbine trip due to reactor trip alarm A5 6D lit.
Rod bottom lights lit.
Neutron flux dropping.
RO verifies reactor trip.
RO sounds standby alarm, announces Unit 2 reactor trip.
Throttle or governor valves closed.
Reheat stops or interceptors closed.
PO verifies turbine trip.
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BEAVER VALLE" r'OWER STATION Training Administrative Manual INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE EXPECTED STUDENT RESPONSE IMF DSG01B (1 40) (preload)
MSR steam supply block valves closed.
Reheat controller reset pushbutton depressed.
Output breakers open.
Main generator volts ZERO.
Exciter ACB open.
2AE energized.
2DF de-energized, 2-2 EDG tripped during loading and will not be recovered.
No SI annunciator.
SI actuation status light not lit.
Immediate actions complete.
Transition to ES-0. 1 SI is not required.
PO ensures reheat steam isolation.
PO verifies generator trip.
PO verifies power to AC emergency busses, reports loss of DF bus and 2-2 EDG.
Crew checks if SI is actuated/required.
Crew dispatch operators to investigate loss of 2-2 EDG and 2FWE*P22.
US makes transition to ES-0. 1 and informs the Control Room.
No SI annunciator.
SNA monitors status trees.
Crew checks SI not actuated.
BVPS-2 NRC Scenario 3
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BEAVER VALLEtY POWER STATION Training Administrative Manual INSTRUCTION GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE WHEN APPROPRIATE report as turbine building operator that there is a large condensate header rupture just down stream of pumps discharge.
NOTE: After report from field, crew may opt to secure condensate pumps.
Maintain RCS temperature.
Steam Dumps in Steam Press mode, RCS Tavg > 547°F and rising. Monitor RCS temperature.
EVENT6 When steam dump control mode selector switch is placed in Steam Press position:
IMF BKR-HIV01 (2 0) 0 (preload)
IRF LOA-DSG001 (5 0) 0 (preload)
IMF PPL07A (2 1) 5 (preload)
Crew enters ECA-0.0.
When requested to check why No. 2 EDG tripped, report that the local Alarm No. 5 (overspeed trip) is actuated and there is physical damage to the EDG.
Loss of 2AE 4160V bus DG1 fails to auto start.
2FWE*P23A fails to auto start on EDG sequencer, manual start successful.
Diesel gen. 2-2 local panel trouble alarm A8-5E.
Crew checks/monitors T-avg.
PO places steam dumps in steam pressure mode.
RO reports that Tavg is stable.
PO identifies loss of 2AE 4160V bus and reports loss to US.
US determines no ESF busses are energized.
US makes transition to ECA-0.0 and informs Control Room.
SNA monitors CSF status trees for information only.
BVPS-2 NRC Scenario 3 12 of 12
BEAVER VALLEtY OWER STATION Training Administrative Manual I
INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE I EXPECTED STUDENT RESPONSE Annunciator A5-6D lit.
Neutron flux dropping.
RO reverifies reactor trip.
WHEN APPROPRIATE report that 2FWE*P22 has physical damage to its trip throttle valve and it will not be returned.
SLI manually actuated.
MSIVs and bypass valves closed.
Exciter and output breakers open.
PORVs closed.
L/D isolated.
RCPs stopped.
AFW flow not indicated due to loss of all AFW pumps.
SR & IR channels aligned to 2NME NR45.
RO sounds standby alarm and announces Unit 2 loss of power.
PO ensures steamlines isolated.
PO verifies generator trip.
RO verifies RCS isolated, stops running RCPs.
PO reports AFW system status, operators previously dispatched to investigate loss of 2FWE*P22.
US dispatch operator to perform Attachments A-1.12 and A-1.11 to restore AFW flow.
RO verifies source range &
intermediate NIs displayed on 2NME NR45.
BVPS-2 NRC Scenario 3
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BEAVER VALLE i POWER STATION Training Administrative Manual I
INSTRUCTION GUIDELINES I
PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE No. 1 EDG starts manually and sequences loads WITH EXCEPTION OF 2FWE*P23A.
Transition to ES-0.1 NOTE: Crew may start 2FWE*P23A when AE bus is re energized before transition to ES 0.1.
CT#2 - ECA-O.O.B:
Crew establishes the minimum required AFW flow rate to the SGs before SG dryout occurs.
Terminate scenario when AFW flow is verified following transition to ES-0.1.
EPP classification is ALERT based on EPP/I-lb Tab 3.1, Loss of AC power.
AE emergency bus energized.
2FWE*P23A failed to auto start on 2-1 EDG sequencer.
AFW flow restored to > 340 gpm.
PO tries to start No. 1 EDG and reports it started and is sequencing loads.
US directs return to ES-0. 1 step #5, (step in effect), based on repots of power restored to one 4KV Emergency bus.
PO reports no AFW pumps operating.
US directs PO to manually start 2FWE*P23A feed SGs.
PO starts 2FWE*P23A and restores feed flow to all SGs.
CT#2 S/U AFW flow > 340 gpm.
BVPS-2 NRC Scenario 3
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PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE-]
BVPS-2 NRC Scenario 3 15 of 15
RTL# A5.670.AA 1/2-ADM-1357.F11 Page 1 of 1 Revision 0 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE:
SUBDIVISION:
SCENARIO TITLE/NO.:
COMPUTER CODE FOR L.P.:
Unit 2 LOIT NRC Exam BVPS Unit 2 Simulator NRC Scenario #4 N/A INSTRUCTIONAL SETTING:
APPROXIMATE DURATION:
PREPARED BY:
General Physics Com.
REVIEWED BY:
APPROVED FOR IMPLEMENTATION:
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Simulator 1.5 Hour 8/01/2002 Date Date Date 1
1 10/25/02 Reislonljn mgle
RTL A5.670.AA BEAVER VALLEY POWER STATION Training Administrative Manual Volume 3 Procedure 5-9 Revision 11 Figure 5-9.3 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE:
SUBDIVISION:
SCENARIO TITLE/NO.
Licensed Operator Initial Training BVPS Unit 2 Scenario #4 COMPUTER CODE FOR L.P.
INSTRUCTIONAL SETTING:
APPROXIMATE DURATION:
Simulator 1.5 Hours PREPARED BY:
General Physics Corp.
8/1/02 Date REVIEWED BY:
Date APPROVED FOR IMPLEMENTATION:
BVPS-2 NRC Scenario 4 Revision No.
Date Revision No.
Date Date 1 of 1
Appendix D Scenario Outline Form ES-D-1 Facility:
FENOC BVPS Unit 2 Scenario No. 4 Op Test No.:
2002-02 Examiners:
Candidates:
Demonstrate the ability to safely operate the plant during normal and upset conditions in accordance with plant procedures.
Initial IC 125 PW = NRC4: 80% power, BOL, EQU XE, 1615 ppm boron, CB Conditions:
"D" = 172 steps.
Turnover:
2FWE*P23B OOS. Perform a normal power reduction to remove "2A" Main Feed Pump from service.
Critical Tasks:
E-O.H, Start LHSI pump.
E-O.O, Manually initiate CIB.
Event Malf. No.
Event 1
Event Description No.
Type*
1 N (US)
Normal power reduction.
N (PO)
R (RO) 2 PMP FW4 C (All) 2FWS*P21A trips at approximately 77% power.
PMP CFW008 2FWS*P24 trips 3 minutes after being started.
Running CCP pump trips.
PPL07B C (US)
Manually start standby CCP pump.
4 FLX CCP34 C (RO)
CCP supply leak to 2RCS*P21B (10 minute ramp to 450 gpm - leads to reactor trip).
C (US) 5 RCS03B M (All)
Large break LOCA.
6 PPL07A C (PO)
Both low head SI pumps fail to auto start (manual start PPL07B C (US) available).
7 BST-PCS048 C (RO)
Auto CIB failure (manual available).
BST-PCS049 C (US)
BST-PCS052 I
(N)ormal, (R)eactivity, (L)nstrament, (C)omponent, (M)ajor BVPS-2 NRC Scenario 4 2 of 2
Appendix D Scenario Outline Form ES-D-1 The crew will lower power in preparation for removing a main feed pump from service; however, when power has been lowered to approximately 77%, the pump will trip and the startup feed pump will also subsequently trip requiring the crew to rapidly reduce power to less than 60% to avoid a reactor trip.
When plant conditions have begun to stabilize, the running component cooling pump trips requiring operator action to manually start the standby component cooling pump.
After starting the standby pump, a leak will develop on the supply line to 2RCS*P21B. The leak will ramp to 450 gpm over ten minutes requiring operator action to locate and isolate the leak.
The Unit Supervisor should eventually direct a manual reactor trip.
Immediately following the reactor trip, a large break LOCA occurs. After completion of E-0 immediate actions, all RCPs should be manually tripped due to the LOCA.
Following the LOCA, Containment Isolation Phase "B" (CIB) will fail to actuate automatically requiring operator action to manually initiate CIB. Also both low head SI pumps fail to start automatically, but can be manually started by the crew.
Expected procedure flow path is EO -- El.
BVPS-2 NRC Scenario 4 3 of 3
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Program Title 2002 NRC Examination
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Initial Conditions REV 1
INITIAL CONDITIONS:
IC 125 PW = NRC4 IC 125 PW = NRC4: 80% power, BOL, EQU XE, 1615 ppm boron, CB "D" = 172 steps.
ADDITIONAL LINEUP CHANGES STICKERS VOND MARKINGS 2FWE*P23B PTL 2FWE*P23B YCT Fig 20M 24-3: 2FWE*36 closed 2FWE* 102 open EQUIPMENT STATUS DATE/TIME OOS TECHNICAL SPECIFICATION(S) 2FWE*P23B OOS 24 Hours ago TS 3.7.1.2, Action b SHIFT TURNOVER INFORMATION
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4.
80% power, BOL, EQU XE, 1615 ppm boron, CB "D" = 172 steps.
Reduce Power to remove FW-P-2A from service due to bearing high vibration.
Severe weather is expected.
2FWE*P23B is OOS for motor replacement and will not be returned this shift. 2FWE*P22 is aligned to the "B" header.
SCENARIO SUPPORT MATERIAL REQUIRED Power reduction reactivity plan.
Load follow procedure 20M-52.4.B, step IV.B.1.
BVPS-2 NRC Scenario 4
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BEAVER VALLEy POWER STATION Training Administrative Manual PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I
Shift positions:
Us RO PO EVENT #1 Lower Reactor Power to 75%.
Turbine load and reactor power reduction at 12%/Hr or less.
Following the Reactivity Plan, Crew lowers reactor power.
US directs load decrease. Initiates Turbine load reduction.
PO initiates turbine load decrease.
RO initiates RCS boration as necessary to maintain Tavg-Tref.
EVENT #2 After power is lowered to 77%
IMF PMP-CFW004 (1 0) 1 (preload)
IMF PMP-CFW008 (2 180) 1 (preload) 2FWS-P21A trips.
PO recognizes feed pump trip and informs US.
2FWS-P24 trips 3 min after startup.
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BEAVER VALLE& COWER STATION Training Administrative Manual PLANT STATUS OR RESPONSE OBJECTIVE EXPECTED STUDENT RESPONSE-]
US refers to AOP-2.24.1, Loss of Main Feedwater.
US verifies reactor power <90%.
Alarm received:
[A6-A1O], SG Feed Pump 21A/B Auto Stop.
2FWS-P24 started.
2FWS-P24 trips 3 minutes after starting.
Turbine load reduction at 5%/minute.
At discretion of examiner, proceed with next event.
EVENT #3 (following are preloaded)
IMF PMP-CCP001 (0 0) 1 IMF PMP-CCP002 (0 0) 1 TRGSET 3 'XB41009T =1' TRG 3 'DMF PMP-CCP002' Running CCP Pump trips. Standby CCP Pump manually started.
Refers to ARPs as time permits.
US directs starting 2FWS-P24, SG Startup Feed Pump.
PO starts 2FWS-P24 and dispatches operator to locally check pump.
PO reports trip of 2FWS-P24 after starting.
US refers to AOP 2.51.1 and directs load decrease to < 60% at 5% / minute.
PO decreases turbine load at 5% /
minute.
RO performs RCS boration to maintain Tavg-Tref.
PO manually starts standby CCP Pump.
BVPS-2 NRC Scenario 4 6 of 6
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BEAVER VALLEt r'OWER STATION Training Administrative Manual PLANT STATUS OR RESPONSE I OBJECTIVE [EXPECTED STUDENT RESPONSE EVENT #4 IMF FLX-CCP34 (3 0) 450 600 (preload)
Alarms Received:
[A6-G1], Pri Comp Cooling Pump Auto Start/Auto Stop.
[A6-H1], Pri Comp Cooling Water System Trouble.
CCP leak when standby pump started.
Decreasing CCP Surge Tank level on 2CCP*LI100B.
Increasing Containment sump levels.
Increasing RCP B motor and bearing temperatures.
1 CCP pump operating.
Level control in manual with maximum makeup.
Determine CCP header leak inside containment.
US refers to AOP 2..15.1, Loss of Primary Comp. Cooling Water.
RO/PO Check CCP system status.
RO/PO Place Surge Tank Level Control Valve in MAN and adjust control signal to maximize makeup to Surge Tank level.
NOTE: Due to the rapidly degrading CCP system, it is expected that the crew will conservatively trip the reactor (based on surge tank level) and secure RCPs.
BVPS-2 NRC Scenario 4
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BEAVER VALLI:, POWER STATION Training Administrative Manual PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE-]
Non-essential loads isolated.
Surge tank continues to decrease.
Cavitation of CCP pumps possible.
Leakage excessive.
Crew monitors RCP Motor Bearing upper and lower temperatures for RCPs.
Crew attempts to locate the leak.
Crew - If any RCP temperatures are approaching limits OR operating CCP pumps discharge pressure and current indicates cavitation, or if leakage is determined to be excessive:
Manually trip the reactor.
Perform IMAs.
Trip all RCPs.
EVENT #5 (preloaded)
IMF PPLO7A (0 0) 4 IMF PPL07B (0 0) 4 IMF RCS03B (4 0)
IMF BST-PCS048 (0 0) 2 IMF BST-PCS049 (0 0) 2 IMF BST-PCS052 (0 0) 2 Steps 1 - 7 of E-0 are immediate actions.
2SIS*P21A auto start failure.
2SIS*P21B auto start failure.
DBA LOCA on reactor trip.
Auto CIB failure.
Auto CIB failure.
Auto CID failure.
Rod bottom lights lit. Neutron flux dropping.
First Out: A5-6D, TURBINE TRIP DUE TO REACTOR TRIP.
US directs manual reactor trip.
RO manually trips reactor.
RO verifies reactor trip.
BVPS-2 NRC Scenario 4 8 of 8
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BEAVER VALLE' I POWER STATION Training Administrative Manual PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE Throttle or governor valves closed, reheat stops or interceptors closed.
MSR steam supply block valves closed.
Reheat controller reset pushbutton depressed.
Main generator output breakers open.
Main Gen volts zero.
Exciter circuit breaker opens.
2AE and 2DF busses energized.
E-0 immediate actions completed.
SI actuated.
Manual reactor trip resulted in a DBA LOCA on RCS Loop B.
RCS pressure, PZR level off scale low.
CNMT parameters degrade rapidly.
RO sounds standby alarm, announces Unit 2 reactor trip.
PO verifies turbine trip.
PO ensures reheat steam isolation.
PO verifies generator trip.
PO verifies power to at least one AC emergency bus.
RO checks if SI is actuated, manually actuates SI pushbuttons.
US directs manual trip of all RCPs.
BVPS-2 NRC Scenario 4
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BEAVER VALLEt POWER STATION Training Administrative Manual I
I PLANT STATUS OR RESPONSE I OBJECTIVE F EXPECTED STUDENT RESPONSE Automatic actions of A-0. 11 are SAT with the following exceptions:
2FWE*P23B OOS at turnover.
Both LHSI pumps failed to auto start and were manually started. (CT#1)
CIB failed to auto actuate and was manually actuated. (CT#2)
US direct operators to verify automatic actions by performing Attachment A 0.11, "Verification of Automatic Actions" when time permits.
Operator assigned to perform Attachment A-0. 11 reports status of Attachment to US/crew and any actions taken when completed.
CT#1 - E-O.H:
Crew manually starts at least one low head ECCS pump before transition out of E-0.
LHSI pumps manually started.
PO manually starts both LHSI pumps during performance of Attachment A 0.11 and reports actions to US when complete.
CT#1 S/U BVPS-2 NRC Scenario 4 10 of 10
BEAVER VALLEi POWER STATION Training Administrative Manual PLANT STATUS OR RESPONSE T OBJECTIVE I EXPECTED STUDENT RESPONSE CT#2 - E-0.E:
Crew manually actuates at least the minimum required complement of containment cooling equipment before an Extreme (red path) challenge develops to the Containment CSF.
CIB/Spray manually actuated.
PO manually actuates CfI & CNMT Spray during performance of Attachment A-0. 11 and reports actions to US when complete.
CT#2 S/U Leak collection filtered exhaust fan status SAT.
Plant rapidly cooled down due to DBA LOCA.
Recirc spray pumps will start after CIB and appropriate time delay.
RCS Pressure at CNMT pressure due to DBA LOCA.
PZR PORVs, Safeties, Spray Vlvs closed.
PORVs/block vlvs alignment sat.
RCPs previously secured.
SGs not faulted.
Crew verifies Leak collection filtered exhaust fan status.
RO reports RCS cold leg temperature and cooldown caused by LOCA.
RO checks recirc spray pump status.
RO checks PZR isolated. PRT conditions normal.
RO verifies PORV alignment sat.
Crew determines no faulted SGs.
BVPS-2 NRC Scenario 4
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Transition to E-1.
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BEAVER VALLEY POWER STATION Training Administrative Manual PLANT STATUS OR RESPONSE OBJECTIVE SG Tubes intact.
CNMT parameters not consistent with pre-event, indicate large LOCA in progress.
CIB actuated.
RCP's previously secured.
Recirc spray pumps operating.
Both CNMT hydrogen analyzers operating.
No S/G's faulted.
AFW flow > 340 gpm.
Power available to block valves.
PORV/Block vlv alignment sat.
No SG levels rising in an uncontrolled manner.
Subcooling < 43°F.
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BVPS-2 NRC Scenario 4 12 of 12
-I EXPECTED STUDENT RESPONSE Crew determines no SGTR event in progress.
US enters E-1 and announce entry to Crew.
PO checks Control Room habitability systems actuated.
RO reports Recirc Spray pmp status.
RO reports H2 analyzer status.
PO checks if S/G's are faulted.
PO checks intact S/G levels and control levels.
RO checks PORV and block valves alignment.
PO chec*k G tubes are intact.
Crew checkq)I flow can be terminated.
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BEAVER VALLEY tPOWER STATION Training Administrative Manual PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE Adequate secondary heat sink.
Crew determines SI flow CANNOT be terminated.
RCS pressure NOT stable or rising.
Terminate the scenario when the crew determines that SI flow cannot be terminated.
US evaluates EPP and declares ALERT due to Loss of RCS Barrier (TAB 1.2).
BVPS-2 NRC Scenario 4
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