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: Unit 2 LOIT NRC Exam SUBDIVISION: BVPS Unit 2 Simulator SCENARIO TITLE/NO.: NRC Scenario #1 COMPUTER CODE FOR L.P.: N/A 1 10/25/02 i
INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 1.5 Hour PREPARED BY: General Physics Cowp. 8/01/2002 Date REVIEWED BY:
Date APPROVED FOR IMPLEMENTATION:
Date
Appendix D Scenario Outline Form ES-D-1 Facility: FENOC BVPS Unit 2 Scenario No. 1 Op Test No.: 2002-02 Examiners: Candidates: CRS RO PO Objectives: 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: steps, RCS boron 1576 ppm.
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.
C (US) 5 CNH PCS IOA I (RO) 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.
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 nitial Conditions REV 1 INITIAL CONDITIONS: IC 128 PW = NRC1 100% BOL EQU XE, CBD = 225, RCS boron = 1576 ppm 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 Following the Reactivity Plan, Crew lowers reactor power toward 60%.
Lower reactor power -5%. Turbine load and reactor power reduction US directs load decrease. Initiates at 12%/Hr or less 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 "B" FWRV sticks in position. "B" SG been lowered -5%. Feed flow rises. "B" NR level rises.
IMF CNH-CFW12 (0 0) 1 NOTE: Level deviation dependent Alarm received: PO notes problem with "B" SG level on time of establishing normal A6-E10, SG 2B Level Deviation from control, valve and takes manual control MFRV control to restore "B" SG Setpoint of 2FWS*FCV488, inform US.
level.
Crew refers to ARP's.
BVPS-2 NRC Scenario I 5 of 5
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BEAVER VALLE rPOWER STATION Training Administrative Manual 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 2DF bus remains energized. 2AE bus is IMF BKR-HIV11 (0 0) 2 deenergized. No. 1 EDG output breaker (preload) fails to shut automatically.
Loss of 4160V Emergency Bus PO determines 2AE bus deenergized.
2AE.
Alarms received: Crew responds per ARPs.
[A8-C2], 4160V Emer Bus 2AE Undervoltage.
[A8-A2], 4160V Emer Bus 2AE ACB 2A10/2E7 Auto Trip.
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.
2CHS*P21B running. 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 6 of 6
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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, US directs PO to shut ACB-2E10, No.
CCP pump, 2CCP*P21A, and Service 1 EDG output breaker, and reenergize Water pump, 2SWE*P21A, deenergized. bus 2AE.
EDG No. 1 output breaker shut. 4160V PO manually shuts ACB-2E10, EDG bus 2AE re-energized. No. 1 output breaker and re-energizes bus 2AE.
Loads sequence onto 2-1 EDG. RO ensures CCP flow to all RCP thermal barriers.
2 charging pumps operating. RO reports charging pump status.
Crew discretion as to which US directs RO to secure 1 charging charging pump is secured. pump.
2CHS*P21A or B secured. RO secures 1 charging pump.
US refers to T.S. 3.0.5 and 3.8.1.1 IF requested insert:
IRF DSGO05 (0 0) 1 Reset of 2-1 EDG oil pump shunt trip.
BVPS-2 NRC Scenario I 7 of 7
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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.
RO notes indications and alarms, Alarms received: informs US.
[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.
US refers to ARP's.
RO notes failure of Pressurizer Master Pressure Controller and informs US.
BVPS-2 NRC Scenario 1 8 of 8
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BEAVER VALLE i POWER STATION Training Administrative Manual INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE Manual Control of PZR Master Pressure US directs RO to place PZR Master Controller fails to close PORV, fails to Pressure Controller in manual, close control heaters, and fails to control spray spray valves and PORV and take valves. manual control of PZR heaters.
Spray valves close. PZR heaters RO uses individual component controls EVENT 5 (partial) energized. to shut spray valves and take manual control of PZR heaters, and attempts to IOR XB1IO35C (0 0) 0 (preload) PORV remains open. close PORV.
RCS pressure continues to decrease due to PORV failure. Charging flow increases.
PORV Block Valve leaks after PORV Block Valve closed. Crew identifies PORV remains open.
closing RCS pressure continues to lower due to US directs PORV Block Valve closed.
leaking PORV Block Valve. 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 RCS pressure continue to decrease due to RO monitors RCS, identifies that RCS (block valve leakage increases) stuck open PORV and leaking block pressure is continuing to decrease.
valve. Charging flow remains high.
RCS pressure dropping. Charging flow US directs a manual reactor trip.
rising.
BVPS-2 NRC Scenario 1 9 of 9
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BEAVER VALLEY HOWER STATION Training Administrative Manual
-- -.---...- I I I
I INSTRUCTION GUIDELINES II PLANT STATUS ST
. T U ORR RESPONSE I OBJECT IVE I,P EXPECTEID SIULENI IZ5L' UN*L I I
.... S RCI IMF PPLO1A (0 0) 1 (preload) Manual reactor trip or automatic RO places reactor trip switch to trip.
IMF PPLO1B (0 0) 1 (preload) pressurizer pressure low reactor 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 Operators commence immediate actions. 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.
Rods inserting. RO uses auto or manual rod control to CT#1 - FR-S.1.C:
insert rods.
Crew inserts negative reactivity into the core by inserting RCCA's CT#1 S/U before completing the immediate action steps of FR-S.1.
Crew sounds standby alarm and announces Unit 2 reactor trip failure.
BVPS-2 NRC Scenario 1 10 of 10
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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 Crew dispatches an operator to locally RTB's, insert: open the RTB's.
IMF PPL02A (10 120) CT#1 S/U IMF PPL02B (10 130) Reactor tripped (time delay).
IRF LOA-CRFO07 (10 150) MG sets secured (time delay).
IRF LOA CRF008 (10 160)
TRG! 10 Report RTB's manually opened & SM informed to evaluate EPP.
MG sets secured.
Turbine manually tripped. PO manually trips turbine.
Throttle, governor, reheat stop, and PO verifies turbine trip.
interceptor valves all closed.
Steam dump bypass interlock selector PO places Condenser Steam Dump switches in OFF. Selector Switches in "OFF".
FR-S.1 immediate actions MSR steam supply block valves closed. PO ensures reheat steam isolation and complete. Reheat controller reset. 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) SSST 2B trips 45 seconds after reactor trip.
IMF BKR-HIV13 (0 0) 2 2-1 EDG output bkr fails to auto close.
(preload)
BVPS-2 NRC Scenario 1 11 ofll1
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. 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.
2F10 closed, 2DF energized, loads PO closes 2F10 and reports loads sequencing on EDG. sequencing.
2FWE*P23A on clearance. PO verifies AFW status.
2FWE*P23B running.
TDAFW pump steam supply valves open.
AFW throttle valves full open.
HHSI pumps running. RO initiates emergency boration of 2CHS*MOV350 open. RCS.
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. RO checks PZR pressure less than 2335 psig.
A5-4G, PZR LOW PRESSURE Crew checks SI signal status, performs SAFETY INJECTION/ REACTOR first ten steps of E-0 when time TRIP lit. 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. 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.
2CHS*FCV1 13B closed. RO verifies dilution paths isolated.
2CHS*FCV1 14A closed.
2CHS*FCV1 14B closed.
Uncontrolled cooldown not in progress. RO monitors RCS for uncontrolled cooldown.
US transitions to Step 16 of FR-S.1.
Core exit temperatures less than 12007F. Crew verifies core exit temperatures.
PR NI's less than 5%. RO verifies reactor subcritical.
IR NI's negative SUR.
US makes transition from FR-S. 1 back to E-0. Directs crew to perform E-0 immediate actions.
Steps 1 - 7 of E-0 are immediate Reactor locally tripped. RO verifies reactor trip.
actions. Rods bottom lights lit.
Flux decreasing.
Previously completed. RO sounds standby alarm and announces Unit 2 safety injection.
Previously requested. SM informed to evaluate EPP.
BVPS-2 NRC Scenario 1 13 of 13
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BEAVER VALLE i POWER STATION Training Administrative Manual INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE -OBJECTIVE I EXPECTED STUDENT RESPONSE-]
Throttle or governor valves closed, reheat PO verifies turbine trip.
stops or interceptor valves closed.
MSR steam supply block valves closed. PO ensures reheat steam isolation.
Reheat controller reset pushbutton depressed.
Main generator output breakers open. PO verifies generator trip.
Main generator volts ZERO.
Exciter circuit breaker open.
2AE and 2DF busses energized. PO verifies power to AC emergency busses.
A5-4G, PZR LOW PRESSURE Crew checks if SI is actuated/ required.
SAFETY INJECTION/ REACTOR TRIP lit.
SI actuation status light, A12-1D lit.
E-0 immediate actions complete. Both trains of SI manually initiated. 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.
Automatic actions of A-0. 11 are SAT Operator assigned to perform with the following exceptions: Attachment A-0. 11 reports status of Attachment to US/crew and any actions 2FWE*P23A OOS at turnover. taken when completed.
BVPS-2 NRC Scenario 1 14 of 14
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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 Crew verifies Leak collection filtered SAT exhaust fan status.
RCS temperature trending to 547F RO reports Tavg status, US directs crew to control steam/feed flow as necessary to achieve desired status.
Recirc spray pumps not running. RO checks recirc spray pump status.
PZR pressure < 2310 psig. RO checks PZR isolated. PRT conditions normal.
PORV, [2RCS*PCV455C], failed open.
PORV block valve shut but leaking. RO verifies PORV Block Valve shut for open PORV.
Crew enters E-1. US enters E-1 and announce entry to Crew.
Radiation not in alarm status and CIB has PO checks Control Room habitability.
not occurred.
RCP's secured. RO checks if RCP's should be stopped.
CT#2 - E-1.C:
Crew trips all RCP's when RCS to highest S/G D/P criteria is CT#2 S/U exceeded and SI flow verified prior to exiting procedure E-1.
Recirc spray pumps not operating. RO reports Recirc Spray pmp status.
Both CNMT hydrogen analyzers RO reports H2 analyzer status.
operating.
BVPS-2 NRC Scenario 1 15 of 15
I, BEAVER VALLE i POWER STATION Training Administrative Manual INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE EXPECTED STUDENT RESPONSE No S/G's faulted. PO checks if S/G's are faulted.
AFW flow > 340 gpm. PO checks intact S/G levels and control levels.
Power available to block valves. RO checks PRZR PORV and block valves.
PORV open. PORV Block Valve RO verifies PORV block valve shut.
[2RCS*MOV535] shut but leaking.
No SG levels rising in an uncontrolled PO checks is SG tubes are intact.
manner.
Subcooling < 43'F. Crew checks if SI flow can be terminated.
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.
BVPS-2 NRC Scenario 1 16 of 16
RTL# A5.670.AA 1/2-ADM-1357.Fl1 Page 1 of I Revision 0 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE: Unit 2 LOIT NRC Exam SUBDIVISION: BVPS Unit 2 Simulator SCENARIO TITLE/NO.: NRC Scenario #2 COMPUTER CODE FOR L.P.: N/A ci 1 10/25/02
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_______________________ I ________________________
INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 1.5 Hour PREPARED BY: General Physics Corp. 8/01/2002 Date REVIEWED BY:
Date APPROVED FOR IMPLEMENTATION:
Date
RTL A5.670.AA BEAVER VALLEY POWER STATION Volume 3 Training Administrative Manual Procedure 5-9 Revision 11 Figure 5-9.3 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE: Licensed Operator Initial Training SUBDIVISION: BVPS Unit 2 SCENARIO TITLE/NO. Scenario #2 COMPUTER CODE FOR L.P.
Revision No. Date Revision No. Date i
I INSTRUCTIONAL SETTING: SIMULATOR APPROXIMATE DURATION: 1.5 Hours PREPARED BY: General Physics Corp. 8/1/2002 Date REVIEWED BY:
Date APPROVED FOR IMPLEMENTATION:
Date BVPS-2 NRC Sim #2 Rev O.doc 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: CRS
"_ _ _ _ _ _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.
7 PMP CHS002 C (RO) 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
- 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 Power Increase.
Crew commences power increase in accordance with reactivity plan.
Continue reactor startup. Reactor at 9% power.
RO commences raising reactor power to between 10 and 20%.
Status lights on Panel 308 actuate at RO verifies P-10 bistables actuate as 10%. required as power increases to > 10%.
[A12-2B], NIS IR Trip Blocked, is ON. RO blocks the IR Trip and Rod Stop and verifies annunciator ON.
[A12-2C], Power Range Low Setpoint RO blocks Power Range low Trip Blocked, is ON. Overpower Trip and verifies annunciator ON.
[A12-1H], NOT P-7 is OFF. RO verifies that annunciator NOT P-7 is OFF.
BVPS-2 NRC Scenario 2 5 of 5
( BEAVER VALL. ,'OWER STATION C
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 Meters for NI-36 indicate zero and blown RO acknowledges ANN's and fuse indication exists on drawer. identifies N-36 as the failed channel.
NI-36 Instrument power fuse fails.
[A4-4G], NIS Detector/Compensator RO reports diagnosis to US.
Loss of Voltage.
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 6 of 6
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BEAVER VALLEY POWER STATION (i
Training Administrative Manual INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]
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.
EVENT #3 After the startup continues 2MSS*PT464 fails low. PO determines Condenser steam dumps closed and informs US/RO.
IMF XMT-MSS044A (0 0) 0 Condenser Steam Dump Valves close. PO identifies failure of 2MS*PT464 Condenser Steam Dump demand 2RCS and informs US.
T1408 indicates zero.
2MSS-PI464A indicates zero.
Tavg rising.
Atmospheric Dump Valves open automatically.
BVPS-2 NRC Scenario 2 7 of 7
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BEAVER VALLEY rOWER STATION
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Training Administrative Manual I INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE I EXPECTED STUDENT RESPONSE Alarms received: US directs RO to take manual control of steam dumps.
[A6-7A], Steamline Pressure High.
RO opens Condenser Steam Dumps in manual.
Condenser Steam Dumps reopened. US contacts I&C to investigate.
EVENT #4 IMF CNH-MSS03B (3 0) 100 "B" SG Atmospheric Dump Valve fails PO identifies failed open Atmospheric (preload) open. Dump Valve and informs US.
SG level deviation alarms may actuate. 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.
BVPS-2 NRC Scenario 2 8 of 8
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BEAVER VALLEY H-OWER STATION
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Training Administrative Manual I INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I EVENT #5 Insert the following: RO acknowledges RCP vibration alarm, informs US, refers to ARP A2 RCP 21B Seal Leakoff rising as indicated 5C. Crew trends RCP vibration.
IMF RCP01B (0 0) 1 300 on 2CHS-FR154A.
[A2-5C], Reactor Coolant Pump US enters AOP-2.6.8.
IMF RCP06B (0 0) 15 Vibration Alert/Danger.
RCP 21B Vibration rises to >16 mils. US proceeds to step 2.d of AOP 2.6.8 IMF RCP06B (0 0) 21 1800 to address vibration problem.
Shaft vibration > 15 mils and rising at > When it is determined that RCP 1.0 mils/hr. 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.
EVENT #6 "B" SGTR when the reactor is tripped. RO informs US of a reactor trip.
IMF RCS04B (2 0) 500 (preload)
RO/PO commence IMAs of E-0, US Steps 1 -7 of E-0 are immediate reference E-0 to verify IMAs.
actions.
BVPS-2 NRC Scenario 2 9 of 9
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Training Administrative Manual I INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE I EXPECTED STUDENT RESPONSE Turbine trip due to reactor trip alarm A5 RO verifies reactor trip.
6D lit.
Rod bottom lights lit.
Neutron flux dropping.
RO sounds standby alarm, announces Unit 2 reactor trip.
Throttle or governor valves closed. PO verifies turbine trip.
Reheat stops or interceptors closed.
MSR steam supply block valves closed. PO ensures reheat steam isolation.
Reheat controller reset pushbutton depressed.
Output breakers open. PO verifies generator trip.
Main generator volts ZERO.
Exciter ACB open.
2AE and 2DF busses energized. PO verifies power to AC emergency busses.
BVPS-2 NRC Scenario 2 10 of 10
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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 RO reports SI status, manually actuates A5-4H. SI.
US directs RO to secure "B" RCP due Immediate actions of E-0 complete.
to high vibration/seal leakoff trouble.
"B" RCP secured. RO secures "B" RCP.
US direct operators to verify automatic actions by performing Attachment A 0.11, "Verification of Automatic Actions" when time permits.
Automatic actions of A-0.11 are SAT Operator assigned to perform with the following exceptions: Attachment A-0. 11 reports status of Attachment to US/crew and any actions 2CHS*P21A failed to auto start on SI, taken when completed.
manual start is successful.
2CHS*P21B tripped on SI and cannot be manually restarted.
BVPS-2 NRC Scenario 2 11 ofll1
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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 2CHS*P21A manually started. PO manually starts "A" HHSI pump &
CT#1 - E-0.I:
reports actions/status to US.
Crew establishes flow from at least one high head ECCS pump before transition out of E-0. CT#1 - S/U Leak collection filtered exhaust fan status Crew verifies Leak collection filtered SAT. exhaust fan status.
RCS temperature trending to 547F. RO reports Tavg status, US directs crew to control steam/feed flow as necessary to achieve desired status.
Recirc spray pumps not running. RO checks recire spray pump status.
PORVs closed (not leaking). RO checks PRZR isolated.
Spray valves closed.
Safeties closed (PSMS data).
PRT conditions normal.
PORV/block valve alignment SAT.
"B" RCP previously secured. RO checks if RCPs should be stopped.
"A&C" RCPs running.
CCP flow normal.
No SG pressure dropping in an PO checks if any SGs are faulted.
uncontrolled manner.
BVPS-2 NRC Scenario 2 12 of 12
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"B" SG level rising in an uncontrolled US directs operator to check if SG manner. Secondary rad monitors not tubes are intact.
consistent with pre-event levels.
US makes transition to E-3 and informs Crew transitions to E-3.
crew.
US directs SNA to monitor status trees.
Control room habitability system not PO verifies control room habitability.
required.
"B" RCP previously secured. RO/PO check if RCPs should be "A&C" RCPs running. stopped.
CCP flow normal.
"B" SG level rising in an uncontrolled Crew identifies ruptured SG.
CT#2 - E-3.A:
Crew isolates feed flow into and manner. Secondary rad levels higher steam flow from the ruptured SG than normal.
and directs operator to close isolations valve(s) operated from outside of the control room before a transition to ECA-3.1 occurs.
BVPS-2 NRC Scenario 2 13 of 13
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BEAVER VALLEY POWER STATION Training Administrative Manual INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE -[OBJECTIVE _ EXPECTED STUDENT RESPONSE Adjust ruptured SG atmospheric steam Crew isolates flow from ruptured SG.
dump controller setpoint to 100% and verify 2SVS*PCV101B closed. CT#2 S/U 2SVS*HCV104 - closed.
IRF LOA-MSS010 (0 0) 0 2SVS*28 - closed.
IRF LOA-AFW026 (0 0) 0 2MSS* 16 - closed.
2BDG*AOV100B 1 - closed.
2SDS*AOV1 11B1 - closed.
2SDS*AOV129A - closed.
2MSS*AOV101B, 102B - closed.
Notify crew that 2MSS*16 is Verify closed "B" SG steam supply to closed. Also report 2SVS*28 TDAFW pump 2MSS*16 and to RHR closed when requested. valve 2SVS*28.
"B" SG narrow range level greater than PO checks ruptured SG level.
12%.(3 1%adverse). CT#2 S/U 2FWE*HCV100C & D closed. PO isolates feed flow to "B" SG.
Main feedwater isolation valve CT#2 S/U 2FWS*HYV157B closed.
Main feed reg valve 2FWS*FCV488 closed.
Main feed bypass valve 2FWS*FCV489 closed.
Ruptured SG pressure > 240 psig. PO verifies ruptured SG pressure greater than 240 psig.
BVPS-2 NRC Scenario 2 14 of 14
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BEAVER VALLE) HOWER STATION Training Administrative Manual INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE - EXPECTED STUDENT RESPONSE Based on ruptured SG pressure. US determines target temperature for CT#3 - E-3.B: cooldown.
Crew establishes/maintains an 1000 - 1084 = 505F (480F).
900 - 999 = 492F (467F). CT#3 S/U 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.
RO blocks low steamline pressure SI when PRZR pressure is less than 1950 psig.
Steam dump is available, greater than PO selects steam dump to steam 100°F per hour cooldown. pressure mode and dumps steam at maximum rate.
CT#3 S/U SNA monitors thermocouples.
Condenser steam dump controller in auto PO stops cooldown when core exit with pot setting corresponding to current TCs < target temperature.
intact SG pressure. CT#3 S/U BVPS-2 NRC Scenario 2 15 of 15
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Training Administrative Manual INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE EXPECTED STUDENT RESPONSE Intact SG levels > 12% (31% adverse). PO controls intact SG feed flow as required (340 gpm min) to achieve/maintain levels between 12%
(3 1%) and 50%.
Power to PORVs & block valves SAT. RO verifies PORV/block valve PORVs closed, not leaking. conditions as expected.
PORV/Block alignment SAT.
Auto SI blocked A 12-1C lit. RO resets SI (both trains).
SI signal A12-1D not lit.
Both trains of CIA reset. RO resets CIA and CIB (both trains).
CIB not actuated.
Station Air available. PO verifies/reports status of station air system.
Instrument air established to CNMT. Crew establishes Instrument Air to 2IAC-MOV 131 - open. CNMT.
2IAC-MOV 130 - open.
Inst Air HDR pressure > 85 psig.
RCS pressure > 225# (250# adverse). RO stops LHSI pumps and places them LHSI Pmps stopped, in auto. in auto.
Cooldown stopped when at target Crew monitors temperature and stops temperature. cooldown at target temperature.
BVPS-2 NRC Scenario 2 16 of 16
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Training Administrative Manual INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE IEXPECTED STUDENT RESPONSE Ruptured SG pressure stable. PO verifies ruptured SG pressure stable.
Subcooling > 61F (79F adverse). Crew verifies Subcooling sat.
PZR level < 75% (61%). RO depressurizes RCS to minimize CT#4 - E-3.C: break flow and refill PRZR.
Crew depressurizes RCS to meet RCS subcooling > 41F (59F).
21A & 21C RCPs running. CT#4 S/U SI termination criteria before water release from the ruptured Spray valves available. Both spray SG Safety or Atmospheric Relief valves open.
Valve. IF AVAILABLE, 1 PORV will be used to assist depressurization.
Depressurization Termination: RO closes spray valves and PORV if PZR level >75% (61%) used.
OR RCS subcooling < value listed on CT#4 S/U Attachment A-5.1 OR BOTH RCS pressure < ruptured SG pressure, and PRZR level > 17% (38%).
BVPS-2 NRC Scenario 2 17 of 17
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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: Unit 2 LOIT NRC Exam SUBDIVISION: BVPS Unit 2 Simulator SCENARIO TITLE/NO.: NRC Scenario #3 COMPUTER CODE FOR L.P.: N/A 1 _ 10/25/02 i
INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 1.5 Hour PREPARED BY: General Physics Corp. 8/01/2002 Date REVIEWED BY:
Date APPROVED FOR IMPLEMENTATION:
Date
Appendix D Scenario Outline Form ES-D-1 Facility: FENOC BVPS Unit 2 Scenario No.: 3 Op Test No.: 2002-02 Examiners: Candidates: CRS RO PO Objectives: 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 - ES-0.1 ) ECA-0.0 - ES-0.1 BVPS-2 NRC Scenario 3 3 of14
( (1 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
- 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 4 of 4
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BEAVER VALLEY POWER STATION Training Administrative Manual I INSTRUCTION GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE j Shift positions:
US RO PO US assumes control and directs Operators to lower reactor power to 60%.
EVENT 1 Lower power - 5%. Turbine load and reactor power lowering Crew reviews/agrees with reactivity at 12%/hr or less. 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 EVENT 2 At Examiner's direction insert:
IMF CNH-PCS09B (0 0) 100 Master Pressurizer Level Controller fails high.
Charging pump flow increases.
BVPS-2 NRC Scenario 3 5 of 14
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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: RO notes indications and alarms, -U
[A2-E3], Charging Flowpath Trouble informs US.
[A2-D4], Reactor Coolant Pump Seal Trouble US directs RO to place PRZR level controller or Charging Pump Discharge Control Valve in manual.
PRZR Level Controller or Charging RO takes manual control of PZR level.
Pump discharge control valve in manual.
Alarms clear. 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 "C" SG Channel 3 Feed Flow PO acknowledges alarms, diagnoses Transmitter fails high. problem, informs US.
Level Deviation Annunciator is "C" SG MFRV FCV-FW-498 modulates dependent on operator action to shut "C" SG level lowers.
manually control the "B" MFRV.
Alarms expected:
[A6-F1 1], Loop C Feedwater Flow >
Steam Flow
[A6-D11], SG 21C Level Deviation from Setpoint BVPS-2 NRC Scenario 3 6 of 6
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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 Crew recognizes load rejection.
(approx. 600 MW). RCS temperature rises. SG level deviation alarms.
Condenser steam dumps open. Load US directs operators to stabilize the rejection 15% - 50% status light A12-4A plant and refers to AOP-2.35.2.
(C-7A actuated).
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.
BVPS-2 NRC Scenario 3 7 of 7
, r 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. SM evaluates EPP.
Crew checks operation of EHC system.
VPL failed low, vibration and load Crew checks if governor valves have satisfactory for condition. EHC Control closed in sequence, checks turbine transfers from partial to full arc mode. vibration recorders, and EHC Control is transferring to full arc mode.
Crew monitors for subsequent load reductions > 90 MWE Generator load > 270 MW Crew checks if turbine should be Vacuum > 24.5 in Hg. tripped, verifies load is greater than 270 MW.
Generator output breakers closed. PO verifies if the main generator is on Generator volts, amps, and p.f. line satisfactory.
RO checks Tavg - Tref within 5°F.
Crew may perform actions to Load rejection bistables reset. PO resets steam dump controller if recover GV control from the valve necessary.
position limiter; 20M-26.4.X is the appropriate procedure.
Crew notifies System Operator of load loss and reason (if determined).
BVPS-2 NRC Scenario 3 8 of 8
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Training Administrative Manual INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE US directs I&C to investigate problem with Valve position limiter.
LR> 15% US directs chemistry to sample as required for LR > 15%.
2CNM-AOV 100 closed. Crew checks 2CNM-AOV100 closed.
Supervisory limits normal. 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) Loss of 4KV bus "D". Crew identifies loss of 4KV bus "D",
2FWS-P21B, 2CNM-P21C and 2CNM-P21A.
IMF FLX-CFW07 (1 0) 20000 Pipe rupture in Condensate Header.
IMF PPLO1A (0 0) 0 (preload) Reactor fails to auto trip. RO notes that a reactor trip has not IMF PPL01B (0 0) 0 (preload) occurred.
TDAFW pump trips during startup IMF AFW03A (0 0) 5440 (preload)
BVPS-2 NRC Scenario 3 9 of 9
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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: Reactor trip. RO manually trips reactor.
Crew manually trips reactor from the Control Room before CT#1 S/U performing the mitigation strategy of FR-S.1.
Steps 1 -7 of E-0 are immediate RO/PO commence IMAs of E-0, US actions. reference E-0 to verify IMAs.
Turbine trip due to reactor trip alarm A5 RO verifies reactor trip.
6D lit.
Rod bottom lights lit.
Neutron flux dropping.
RO sounds standby alarm, announces Unit 2 reactor trip.
Throttle or governor valves closed. PO verifies turbine trip.
Reheat stops or interceptors closed.
BVPS-2 NRC Scenario 3 10 of 10
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Training Administrative Manual INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE EXPECTED STUDENT RESPONSE MSR steam supply block valves closed. PO ensures reheat steam isolation.
Reheat controller reset pushbutton depressed.
Output breakers open. PO verifies generator trip.
Main generator volts ZERO.
Exciter ACB open.
IMF DSG01B (1 40) (preload) 2AE energized. PO verifies power to AC emergency 2DF de-energized, 2-2 EDG tripped busses, reports loss of DF bus and 2-2 during loading and will not be recovered. EDG.
No SI annunciator. Crew checks if SI is actuated/required.
SI actuation status light not lit.
Immediate actions complete. Crew dispatch operators to investigate loss of 2-2 EDG and 2FWE*P22.
Transition to ES-0. 1 SI is not required. US makes transition to ES-0. 1 and informs the Control Room.
SNA monitors status trees.
No SI annunciator. Crew checks SI not actuated.
BVPS-2 NRC Scenario 3 11 of 11
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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 Maintain RCS temperature. Crew checks/monitors T-avg.
turbine building operator that there is a large condensate header rupture just down stream of pumps discharge.
NOTE: After report from field, Steam Dumps in Steam Press mode, RCS PO places steam dumps in steam crew may opt to secure condensate Tavg > 547°F and rising. Monitor RCS pressure mode.
pumps. temperature.
RO reports that Tavg is stable.
EVENT6 When steam dump control mode Loss of 2AE 4160V bus DG1 fails to PO identifies loss of 2AE 4160V bus selector switch is placed in Steam auto start. and reports loss to US.
Press position:
IMF BKR-HIV01 (2 0) 0 US determines no ESF busses are (preload) energized.
IRF LOA-DSG001 (5 0) 0 (preload)
IMF PPL07A (2 1) 5 (preload) 2FWE*P23A fails to auto start on EDG sequencer, manual start successful.
Crew enters ECA-0.0. US makes transition to ECA-0.0 and informs Control Room.
When requested to check why No. 2 Diesel gen. 2-2 local panel trouble alarm SNA monitors CSF status trees for EDG tripped, report that the local A8-5E. information only.
Alarm No. 5 (overspeed trip) is actuated and there is physical damage to the EDG.
BVPS-2 NRC Scenario 3 12 of 12
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Training Administrative Manual I INSTRUCTION GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE I EXPECTED STUDENT RESPONSE Annunciator A5-6D lit. RO reverifies reactor trip.
Neutron flux dropping.
RO sounds standby alarm and announces Unit 2 loss of power.
SLI manually actuated. PO ensures steamlines isolated.
MSIVs and bypass valves closed.
Exciter and output breakers open. PO verifies generator trip.
PORVs closed. RO verifies RCS isolated, stops L/D isolated. running RCPs.
RCPs stopped.
WHEN APPROPRIATE report AFW flow not indicated due to loss of all PO reports AFW system status, that 2FWE*P22 has physical AFW pumps. operators previously dispatched to damage to its trip throttle valve and investigate loss of 2FWE*P22.
it will not be returned.
US dispatch operator to perform Attachments A- 1.12 and A- 1.11 to restore AFW flow.
SR & IR channels aligned to 2NME RO verifies source range &
NR45. intermediate NIs displayed on 2NME NR45.
BVPS-2 NRC Scenario 3 13 of 13
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Training Administrative Manual I INSTRUCTION GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE No. 1 EDG starts manually and PO tries to start No. 1 EDG and reports sequences loads WITH EXCEPTION it started and is sequencing loads.
OF 2FWE*P23A.
Transition to ES-0.1 AE emergency bus energized. US directs return to ES-0. 1 step #5, (step in effect), based on repots of power restored to one 4KV Emergency bus.
NOTE: Crew may start 2FWE*P23A failed to auto start on 2-1 PO reports no AFW pumps operating.
2FWE*P23A when AE bus is re EDG sequencer.
energized before transition to ES 0.1.
US directs PO to manually start 2FWE*P23A feed SGs.
CT#2 - ECA-O.O.B: AFW flow restored to > 340 gpm. PO starts 2FWE*P23A and restores Crew establishes the minimum feed flow to all SGs.
required AFW flow rate to the SGs before SG dryout occurs. CT#2 S/U Terminate scenario when AFW AFW flow > 340 gpm.
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.
BVPS-2 NRC Scenario 3 14 of 14
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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: Unit 2 LOIT NRC Exam SUBDIVISION: BVPS Unit 2 Simulator SCENARIO TITLE/NO.: NRC Scenario #4 COMPUTER CODE FOR L.P.: N/A Reislonljn mgle 1 1 10/25/02
+ -I-
+ +
INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 1.5 Hour PREPARED BY: General Physics Com. 8/01/2002 Date REVIEWED BY:
Date APPROVED FOR IMPLEMENTATION:
Date
RTL A5.670.AA BEAVER VALLEY POWER STATION Volume 3 Training Administrative Manual Procedure 5-9 Revision 11 Figure 5-9.3 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE: Licensed Operator Initial Training SUBDIVISION: BVPS Unit 2 SCENARIO TITLE/NO. Scenario #4 COMPUTER CODE FOR L.P.
Date Revision No. Date Revision No.
INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 1.5 Hours PREPARED BY: General Physics Corp. 8/1/02 Date REVIEWED BY:
Date APPROVED FOR IMPLEMENTATION:
Date BVPS-2 NRC Scenario 4 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: CRS RO PO Objectives: 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.
3 PMP CCP01 C (RO) 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 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
- 1. 80% power, BOL, EQU XE, 1615 ppm boron, CB "D" = 172 steps.
- 2. Reduce Power to remove FW-P-2A 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 REQUIRED Power reduction reactivity plan.
Load follow procedure 20M-52.4.B, step IV.B.1.
BVPS-2 NRC Scenario 4 4 of 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 Following the Reactivity Plan, Crew at 12%/Hr or less. 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% 2FWS-P21A trips. PO recognizes feed pump trip and IMF PMP-CFW004 (1 0) 1 informs US.
(preload)
IMF PMP-CFW008 (2 180) 1 2FWS-P24 trips 3 min after startup.
(preload)
BVPS-2 NRC Scenario 4 5 of 5
( 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: Refers to ARPs as time permits.
[A6-A1O], SG Feed Pump 21A/B Auto Stop.
2FWS-P24 started. US directs starting 2FWS-P24, SG Startup Feed Pump.
PO starts 2FWS-P24 and dispatches operator to locally check pump.
2FWS-P24 trips 3 minutes after starting. PO reports trip of 2FWS-P24 after starting.
Turbine load reduction at 5%/minute. 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 At discretion of examiner, proceed Tavg-Tref.
with next event.
EVENT #3 (following are preloaded)
IMF PMP-CCP001 (0 0) 1 Running CCP Pump trips. Standby CCP PO manually starts standby CCP Pump.
IMF PMP-CCP002 (0 0) 1 Pump manually started.
TRGSET 3 'XB41009T =1' TRG 3 'DMF PMP-CCP002' BVPS-2 NRC Scenario 4 6 of 6
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Training Administrative Manual PLANT STATUS OR RESPONSE I OBJECTIVE [EXPECTED STUDENT RESPONSE Alarms Received:
[A6-G1], Pri Comp Cooling Pump Auto Start/Auto Stop.
[A6-H1], Pri Comp Cooling Water System Trouble.
EVENT #4 CCP leak when standby pump started.
IMF FLX-CCP34 (3 0) 450 600 Decreasing CCP Surge Tank level on Determine CCP header leak inside (preload) 2CCP*LI100B. containment.
Increasing Containment sump levels. US refers to AOP 2..15.1, Loss of Primary Comp. Cooling Water.
Increasing RCP B motor and bearing temperatures.
1 CCP pump operating. RO/PO Check CCP system status.
Level control in manual with maximum RO/PO Place Surge Tank Level makeup. 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 7 of 7
BEAVER VALLI:, POWER STATION Training Administrative Manual PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE-]
Crew monitors RCP Motor Bearing upper and lower temperatures for RCPs.
Non-essential loads isolated. Crew attempts to locate the leak.
Surge tank continues to decrease. Crew - If any RCP temperatures are approaching limits OR operating CCP Cavitation of CCP pumps possible. pumps discharge pressure and current indicates cavitation, or if leakage is Leakage excessive. determined to be excessive:
Manually trip the reactor.
Perform IMAs.
Trip all RCPs.
EVENT #5 (preloaded)
IMF PPLO7A (0 0) 4 2SIS*P21A auto start failure. US directs manual reactor trip.
IMF PPL07B (0 0) 4 2SIS*P21B auto start failure.
IMF RCS03B (4 0) DBA LOCA on reactor trip.
IMF BST-PCS048 (0 0) 2 Auto CIB failure.
IMF BST-PCS049 (0 0) 2 Auto CIB failure.
IMF BST-PCS052 (0 0) 2 Auto CID failure.
RO manually trips reactor.
Steps 1 - 7 of E-0 are immediate Rod bottom lights lit. Neutron flux RO verifies reactor trip.
actions. dropping.
First Out: A5-6D, TURBINE TRIP DUE TO REACTOR TRIP.
BVPS-2 NRC Scenario 4 8 of 8
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Training Administrative Manual PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE RO sounds standby alarm, announces Unit 2 reactor trip.
Throttle or governor valves closed, reheat PO verifies turbine trip.
stops or interceptors closed.
MSR steam supply block valves closed. PO ensures reheat steam isolation.
Reheat controller reset pushbutton depressed.
Main generator output breakers open. PO verifies generator trip.
Main Gen volts zero.
Exciter circuit breaker opens.
2AE and 2DF busses energized. PO verifies power to at least one AC emergency bus.
E-0 immediate actions completed. SI actuated. RO checks if SI is actuated, manually actuates SI pushbuttons.
Manual reactor trip resulted in a DBA US directs manual trip of all RCPs.
RCS pressure, PZR level off scale low. RO trips all RCPs.
CNMT parameters degrade rapidly.
BVPS-2 NRC Scenario 4 9 of 9
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BEAVER VALLEt POWER STATION Training Administrative Manual I I PLANT STATUS OR RESPONSE I OBJECTIVE F EXPECTED STUDENT RESPONSE US direct operators to verify automatic actions by performing Attachment A 0.11, "Verification of Automatic Actions" when time permits.
Automatic actions of A-0. 11 are SAT Operator assigned to perform with the following exceptions: Attachment A-0. 11 reports status of Attachment to US/crew and any actions 2FWE*P23B OOS at turnover. taken when completed.
Both LHSI pumps failed to auto start and were manually started. (CT#1)
CIB failed to auto actuate and was manually actuated. (CT#2)
CT#1 - E-O.H: LHSI pumps manually started. PO manually starts both LHSI pumps during performance of Attachment A Crew manually starts at least one 0.11 and reports actions to US when low head ECCS pump before complete.
transition out of E-0. CT#1 S/U BVPS-2 NRC Scenario 4 10 of 10
( (i BEAVER VALLEi POWER STATION Training Administrative Manual PLANT STATUS OR RESPONSE T OBJECTIVE I EXPECTED STUDENT RESPONSE CIB/Spray manually actuated. PO manually actuates CfI & CNMT CT#2 - E-0.E: Spray during performance of Crew manually actuates at least Attachment A-0. 11 and reports actions the minimum required to US when complete.
complement of containment CT#2 S/U cooling equipment before an Extreme (red path) challenge develops to the Containment CSF.
Leak collection filtered exhaust fan status Crew verifies Leak collection filtered SAT. exhaust fan status.
Plant rapidly cooled down due to DBA RO reports RCS cold leg temperature LOCA. and cooldown caused by LOCA.
Recirc spray pumps will start after CIB RO checks recirc spray pump status.
and appropriate time delay.
RCS Pressure at CNMT pressure due to DBA LOCA.
PZR PORVs, Safeties, Spray Vlvs RO checks PZR isolated. PRT closed. conditions normal.
PORVs/block vlvs alignment sat. RO verifies PORV alignment sat.
RCPs previously secured. RO reports RCP status.
SGs not faulted. Crew determines no faulted SGs.
BVPS-2 NRC Scenario 4 11 ofll1
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BEAVER VALLEY POWER STATION
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Training Administrative Manual I I PLANT STATUS OR RESPONSE OBJECTIVE -I EXPECTED STUDENT RESPONSE SG Tubes intact. Crew determines no SGTR event in progress.
Transition to E- 1. CNMT parameters not consistent with US enters E-1 and announce entry to pre-event, indicate large LOCA in Crew.
progress.
PO checks Control Room habitability CIB actuated.
systems actuated.
RCP's previously secured. RO reports RCP status.
Recirc spray pumps operating. RO reports Recirc Spray pmp status.
Both CNMT hydrogen analyzers RO reports H2 analyzer status.
operating.
No S/G's faulted. PO checks if S/G's are faulted.
AFW flow > 340 gpm. PO checks intact S/G levels and control levels.
Power available to block valves. RO checks PORV and block valves PORV/Block vlv alignment sat. alignment.
No SG levels rising in an uncontrolled PO chec*k G tubes are intact.
manner.
Subcooling < 43°F. Crew checkq)I flow can be terminated.
BVPS-2 NRC Scenario 4 12 of 12
BEAVER VALLEY tPOWER STATION
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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 13 of 13