ML023020177
| ML023020177 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 09/30/2002 |
| From: | Hynes C FirstEnergy Nuclear Operating Co |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 50-334/02-301 50-334/02-301 | |
| Download: ML023020177 (46) | |
Text
RTL# A5.670.AA 1/2-ADM-1357.F11 Page 1 of 1 Revision 0 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE: Licensed Operator Initial Training SUBDIVISION: Simulator SCENARIO TITLE/NO.: 1LOT5 NRC Exam Scenario #1 COMPUTER CODE FOR L.P.: N/A
"-/- - , ---.*'. i . ,'. 7o 1 8/27/02 i
INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 2.0 Hours PREPARED BY: Western Technical Services Inc. 8/27/02 Date REVIEWED BY: R. Ernfield 8/27/02 Date APPROVED FOR IMPLEMENTATION:
Date BVPS-1 NRC Scenario 1 Page 1 of 17
Appendix D Scenario Outline Form ES-D-1 The Crew will lower power in preparation for removing a feed pump from service (FW-P-1 B);
however, when power has been lowered to approximately 72%, FW-P-1 B will trip, requiring the Crew to rapidly reduce power to less than 63% to avoid a reactor trip.
When plant conditions have stabilized, the controlling pressurizer level channel fails low, letdown isolates, charging flow increases, and actual pressurizer level will rise.
After letdown is reestablished, a controlling steam flow transmitter for the 'B' SG fails low, requiring operator action to take manual control of SG water level to avoid a reactor trip. The Unit Supervisor will also address Technical Specifications for the failure.
After SG level is stabilized, a 500 GPM SGTR will occur in "B"Steam Generator.
After the Operator has taken manual control of feedwater and stabilized SG level, the 'B' SG.
Additionally, the 3B MDAFP and the TDAFP fail to automatically start but may be started manually.
After the crew transitions to E-3, a main steam line break will occur on the "B"SG outside CNMT and upstream of the MSIVs resulting in a faulted/ruptured SG.
Expected procedure flow path is E-0 -> E-3 -> E-2 -- E-3 -> ECA-3. 1.
BVPS-1 NRC Scenario 1 Page 3 of 17
Program Title 2002 NRC Examination Initial Conditions REV 1 INITIAL CONDITIONS: IC 171 PW = 5NRCI 75% power MOL EQU XE, 1128 PPM, CB"D" = 188 steps ADDITIONAL LINEUP CHANGES STICKERS VOND MARKINGS FW-P-3A in P-T-L FW-P-3A YCT W/Red Slash N/A FW-P-3A ESF Status Light lit EQUIPMENT STATUS DATE/TIME OOS TECHNICAL SPECIFICATION(S)
FW-P-3A OOS 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior TS 3.7.1.2, Action c SHIFT TURNOVER INFORMATION
- 1. Reduce power lAW 1OM-52.4.B step IV.A.5 to remove FW-P-1B from service ASAP (1%/min) due to a motor bearing vibration.
- 2. Severe weather is forecasted for the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- 3. FW-P-3A is on clearance due to a motor ground and is not expected back this shift.
4.
SCENARIO SUPPORT MATERIAL REQUIRED
- 1. Power reduction reactivity plan
BEAVER VALLEY POWER STATION Volume 3 Training Administrative Manual Procedure 5-9 Revision 11 Figure 5-9.6 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE EVENT #1 Lower Rx Power to 63%. Following the Reactivity Plan, Crew lowers reactor power.
US directs load decrease to < 63% at 1% per minute.
PO initiates turbine load decrease.
RO initiates RCS boration as necessary to maintain Tavg-Tref EVENT #2 After power is lowered to 72% IMF FW-P-1B trips. PO recognizes feed pump trip and informs US.
FWM01B (preloaded)
Annunciator A7-37, SG Feed Pump Auto Refers to ARPs as time permits.
Stop.
Annunciator A7-39, SG Feed Pump US directs load decrease to < 63% at 5% /
Disch Flow Hi Start 2d Pump. minute.
PO decreases turbine load at 5% /minute.
RO RCS Boration to maintain Tavg-Tref.
EVENT #3 After plant conditions have stabilized:
BVPS -1 NRC Scenario 1 5 of 17
BEAVER VALLEY POWER STATION Volume 3 Training Administrative Manual Procedure 5-9 Revision 11 Figure 5-9.6 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE IMF PRS06A (0 0) 0 PZR level transmitter LT-RC-459 fails RO recognizes problem with PZR level low. channel, informs US, refers to ARP, and Instrument Failure Procedure 1.6.4.WF, Attachment 1.
PZR control level deviation low alarm A4-4.
PZR control level low alarm, A4-3. RO informs US that LT-RC-459 failed low.
LCV-CH-460A, TV-CH-200A, B, C close.
PZR heaters off Letdown isolates and actual PZR level US directs Operator to defeat level control input rises. with PZR level channel and recorder selector switches per 1.6.41F Attachment 1.
RO informs US that Channels 460 and 461 are selected.
Continue with next event when Level alarms clear, charging flow begins US directs the Operators to reestablish normal letdown has been reestablished. decreasing, high flow alarm clears. letdown, re-energize pressurizer heaters.
EVENT #4 "B" SG Steam Flow Transmitter
[FT-MS-484] fails low.
IMF MSS14C (0 0) 0 FT-MS-484 Fails low. lOM-24.4.IF BVPS -1 NRC Scenario 1 6 of 17
BEAVER VALLEY POWER STATION Volume 3 Training Administrative Manual Procedure 5-9 Revision 11 Figlure 5-9.6 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE Annunciator A7-50 "Loop 2 Feed > Stm" US determines that 1OM-24.4.IF Attachment 3 is to be implemented.
Feedwater flow decreases causing SG levels to decrease.
PO determines which channel has failed by comparing with other steam flow indicators.
SG level stabilizes. PO places "B" SG FRV in manual and stabilizes steam generator level.
PO selects redundant steam flow transmitter by placing FC-1FW-488 to FM-485 position.
PO returns "B" FRV to auto when SG level is returned to normal range.
If desired to trip bistables:
IOR XS03C23 (0 0) 1 Protection chanel III door 18 open. Crew monitors tripping of bistables associated IMF BST-RCS157 (0 0) 0 BS-488C tripped. with FT-MS-484.
IMF BST-RCS056 (0 0) 0 BS-488B tripped.
DOR XS03C23 Protection chanel III door 18 closed.
Continue with scenario at examiners discretion.
BVPS -1 NRC Scenario 1 7 of 17
BEAVER VALLEY POWER STATION Volume 3 Training Administrative Manual Procedure 5-9 Revision 11 Figure 5-9.6 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE EVENT #5 After the Operator has taken manual control of feedwater and stabilized SG level:
IMF RCS03B (0 0) 500 "B" SGTR 500 gpm A4-88, Steam Gen N-16 Monitor RO calls out alarms to crew.
Alert/High Trouble.
A4-71, Rad Monitor High. US dispatches operator to N-16 monitor.
A4-72, Rad Monitor High High.
After appropriate delay, report N- 16 PZR level reducing. RO reports degrading plant conditions.
monitor alarm is associated with the PZR pressure reducing.
"B" SG. Charging flow increasing.
Additional Annunciators associated with degrading plant conditions actuate.
US directs RO to manually trip the reactor and crew to perform IMAs of E-0.
Crew performs immediate operator Crew performs IMAs of E-0.
actions of E-0.
Reactor trip and bypass breakers open. RO verifies reactor tripped.
Neutron flux decreasing.
Rod bottom lights lit.
Rod position indication at 0.
RO sounds standby alarm.
BVPS -1 NRC Scenario 1 8 of 17
BEAVER VALLEY POWER STATION Volume 3 Training Administrative Manual Procedure 5-9 Revision 11 Figure 5-9.6 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE Throttle and governor valves closed. PO verifies turbine tripped.
Reheat stops and interceptors closed.
Depress reheat controller, reset PO ensures reheat steam isolated.
pushbutton.
Reheat flow control and block valves closed.
Main generator output breakers open. PO verifies generator trip.
Main Generator Volts zero.
Exciter circuit breaker open.
1AE / IDF buses energize. PO verifies power to AE/DF buses.
NOTE: If crew does not manually RCS pressure reducing. Crew checks for SI, assesses plant status and actuate SI at this time, SI will be PZR level continues to reduce. manually actuates SI if not already actuated, required due to degrading overall continues with E-0.
Crew will be required to return to E-0 at that time.
Only exceptions to Attachment 1-K US directs operator to perform Attachment l-K, are: Verification of Automatic Actions, as FW-P-3A OOS at turnover. time/manpower permit, continues with E-0.
FW-P-2 & FW-P-3B failed to auto start and were started manually.
All other checks/conditions SAT for current plant conditions.
BVPS -1 NRC Scenario 1 9 of 17
BEAVER VALLEY POWER STATION Volume 3 Training Administrative Manual Procedure 5-9 Revision 11 Figure 5-9.6 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE EXPECTED STUDENT RESPONSE CT E-0.F: FW-P-2 and FW-P-3B manually started. PO starts FW-P-2 and FW-P-3B, verifies AFW flow, and informs US.
CT-#1 Crew establishes the minimum required AFW flow to CT-#1 the SGs before transition out of E-0 unless the transition is to FR H.1 in which case the task must be initiated before RCPs are manually tripped IAW FR-HAI0 Automatic actions eventually occur:
SI, CIA, FWI.
When requested to align WR H2 Crew directs operator to place wide range H2 analyzers in service.
analyzers insert:
IMF XN02097 (0 0) 1 Annun A2-97 energizes.
IMF XN02105 (0 0) 1 Annun A2-105 energizes.
H2 analyzers in service.
and report actions to the control room VS-F-4A running. PO verifies at least one leak collection exhaust fan running.
Tavg approx 547°F and stable. RO/PO check RCS Tavg stable at or trending to 547 0 F.
BVPS -1 NRC Scenario 1 10 of 17
BEAVER VALLEY POWER STATION Volume 3 Training Administrative Manual Procedure 5-9 Revision 11 Figure 5-9.6 I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE PORVs, safeties and spray valves RO checks PRZR PORV's, safeties, spray valve indicate closed. closed.
PRT parameters as expected for current RO checks PRT conditions.
plant conditions.
PORV lineup SAT. RO checks PORV lineup.
RCPs running. RO reports RCPs running.
No SGs faulted. PO checks if any SGs are faulted.
"B" SG level rising in uncontrolled Crew identifies "B" SG as being ruptured.
manner.
Crew transitions to E-3. US exits E-0, enters E-3 and informs crew.
CREBAPS not actuated, not required. Crew checks CREBAPS status.
All RCPs running. RO checks if RCPs should be stopped, does not CCR flow, RCS/SG D/P > 200 psig. stop RCPs.
"B" SG identified. US identifies "B" S/G as the ruptured S/G, based on operator reports.
PCV-MS-101B closed. RO/PO verify "B" S/G atmospheric dump valve HCV-MS- 104 closed. and RHR valve closed.
Steam supply from ruptured SG to FW Crew determines status of steam supply to FW P-2 NOT PREVIOUSLY ISOLATED. P-2.
FW-P-3A OOS at turnover.. PO reports status of Motor driven AFW pumps.
FW-P-3B - running.
BVPS -1 NRC Scenario 1 11 of 17
BEAVER VALLEY POWER STATION Volume 3 Training Administrative Manual Procedure 5-9 Revision 11 Figure 5-9.6 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE E EXPECTED STUDENT RESPONSE MOV-MS-105 shut. US directs closure of MOV-MS- 105.
MS open. Crew addresses the fact that TDAFW supply MS closed. valve MS-16 is NSA open, it must be closed and MS-17 must be opened.
LMF MSS18B (2 0) 1E5 TV-MS-I11B shut. US directs operators to isolate flow to/from the IMF XN11026 (2 0) 1 "B" SG main steam trip, bypass and non "B" S/G.
(both pre-loaded) return valves shut.
TV-MS-1I0B Steam Leak on "B" steam line in MOV-MS-1O1B MS valve room when TV-MS NRV-MS-101B 101B is shut.
Al 1-26, Main Steam Valve Room Temp PO reports Al 1-26 alarm and indication of High. steam flow on "B" SG, and "B" SG pressure Steam Flow indicated on "B" SG. reducing.
"B" SG pressure reducing.
NOTE: Drill assumes crew identifies fault on "B" Main Steam Line and transitions to E-2 at this time based on left hand page criteria.
Crew transitions to E-2. US makes transition to E-2, and informs crew.
As U-2 operator, when requested, Bottle discharge lights lit. PO verifies CREBAPS actuated, requests Unit report proper CREBAPS actuation. Intake and exhaust dampers closed. 2 CREBAPS verification.
All yellow SLI marks lit. Crew verifies steam line isolation.
BVPS -1 NRC Scenario 1 12 of 17
BEAVER VALLEY POWER STATION Volume 3 Training Administrative Manual Procedure 5-9 Revision 11 FiQure 5-9.6 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE EXPECTED STUDENT RESPONSE Note: "A" and "C" SG pressures "A" and "C" SG pressure stable. PO checks for any non-faulted SG.
may be dropping due to effects of "B" SG fault, but should not be diagnosed as faulted.
"B" SG pressure dropping PO identifies "B" SG as faulted.
uncontrollably.
FCV-FW-488 closed. PO verifies "B" MFRV closed.
FCV-FW-489 closed. PO verifies "B" BPFRV closed.
MOV-FW- 151C & D closed. PO closes MOV-FW-151C & D.
As operator sent to swap steam MS-16 open. PO reports that operator is unable to shift steam supply to FW-P-2, report that you MS-17 closed. supply to FW-P-2 due to steam leak in the area.
are unable to enter the Main Steam Valve Room due to steam leak.
PCV-MS-101B closed. RO/PO verify "B" S/G atmospheric dump valve HCV-MS-104 closed. and RHR valve closed.
"B" SG previously identified as ruptured. Crew checks if SG tubes are intact.
Crew transitions back to E-3 US directs return to E-3, directs crew through High Level Action Steps previously performed.
AFW secured to ruptured S/G in E-2 PO checks ruptured SGWL and maintains AFW regardless of NR level. flow isolated to "B" SG "B" - MOV-FW- 151C & D - CLOSED.
FWI previously verified. PO re-verifies FWI has occurred.
BVPS -1 NRC Scenario 1 13 of 17
BEAVER VALLEY POWER STATION Volume 3 Training Administrative Manual Procedure 5-9 Revision 11 Fiqure 5-9.6 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE EXPECTED STUDENT RESPONSE Ruptured SG pressure > 380 psig. PO verifies ruptured SG pressure is greater than 380 psig.
Station instrument air pressure> 100 PO verifies station air pressure > 100 psig.
psig.
Target temperature determined based on US determines target temperature.
ruptured SG pressure.
1000 - 1099# -- 507F (491F adverse). SNA trends cooldown rate.
900 - 999# -- 495F (479F adverse).
Condenser steam dumps NOT available Crew initiates RCS cooldown at the maximum due to MSLI. rate to the target temperature using "A&C" Atmospheric Steam Dumps.
RCS pressure < 1950 psig. RO blocks steamline SI when RCS pressure is below 1950 psig.
Average of the 5 highest TCs at target Crew stops RCS cooldown and maintains RCS temperature. at target temperature.
Intact SG levels > 13% (30% adverse) PO checks intact SG levels, controls levels NR. between 20% (36% adverse) and 50%.
Power to all block valves, RO checks/reports status of PORVs and block All PORVs closed. valves.
All block valves open, all PORVs in auto.
BVPS -1 NRC Scenario 1 14 of 17
BEAVER VALLEY POWER STATION Volume 3 Training Administrative Manual Procedure 5-9 Revision 11 Figure 5-9.6 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE EXPECTED STUDENT RESPONSE Iz SI reset: RO resets SI, CIA, and CIB.
PNL 62-C4 NOT LIT.
PNL 62-D4 LIT.
CIA/CIB reset.
CNMT instrument air available PO checks/reports CNMT instrument air system
(> 100 psig, A6-1 10 NOT LIT). status.
RCS pressure > 300 psig (475 psig adverse).
LHSI pumps stopped/in auto. RO stops LHSI pumps, places them in auto.
PO controls RCS temperature at/below target Core exits TCs maintained < target temperature. temperature.
Ruptured SG pressure DROPPING to PO reports status of ruptured SG pressure.
W/I 250# of intact SGs.
Crew transitions to ECA-3.1 US directs transition to ECA-3.1 based on operator reports.
RWST level > 19 ft. RO verifies RWST level > 19 ft.
Previously performed. RO verifies SI, CIA and CIB reset.
Stub busses energized. PO verifies stub busses energized.
CNMT Inst Air system operating PO verifies CNMT instrument air available.
properly.
BVPS -1 NRC Scenario 1 15 of 17
BEAVER VALLEY POWER STATION Volume 3 Training Administrative Manual Procedure 5-9 Revision 11 Figure 5-9.6 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE F EXPECTED STUDENT RESPONSE All busses energized. PO verifies all AC busses - energized by offsite power.
PZR HTRS in PTL. RO places all PZR heaters in pull to lock.
CIB has not actuated. RO checks if any Quench Spray Pumps running.
"B" SG steam and feed flow isolated PO checks ruptured SG NR level > 13%, then previously. verifies "B" SG isolated regardless of SGWL.
RCS pressure greater than 300 psig. RO reports LHSI pumps previously stopped and Pressure not reducing unexpectedly. in auto.
(may be reducing due to cooldown, but not due to RCS LOCA).
Aux Building and safeguards radiation US initiates evaluation of plant status.
consistent with pre-event values. Obtain samples as required.
"B" S/G previously identified and PO checks if all SGs are faulted.
isolated. "A" and "C" intact.
"A" & "C" Narrow range level - greater PO checks intact SG levels.
than 13%.
Control feed flow to maintain "A' & "C" PO controls feed flow as required.
SG narrow range level between 20 and 50%.
BVPS -1 NRC Scenado I 16 of 17
BEAVER VALLEY POWER STATION Volume 3 Training Administrative Manual Procedure 5-9 Revision 11 Figure 5-9.6 INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE Station instrument air previously verified PO checks station air pressure.
> 100 psig.
US directs chemistry to sample RCS boron hourly for SDM verification.
ECA-3.1.B Do not exceed 100°F/hour cooldown in PO commences cooldown using "A" & "C" CT #2 - Crew initiates cooldown RCS cold leg. S/Gs atmospheric relief valves at < 100°F per of the RCS to cold shutdown hour, conditions at the highest rate CT #2 achievable but less than 100°F/hr in all RCS cold legs.
RWST level > 38 ft. US checks if subcooled recovery is appropriate and continues with the next step.
Terminate drill when crew checks if "B" SG narrow range level < 94 [83]%. PO checks ruptured SG NR level < 94%.
subcooled recovery is appropriate in ECA-3.1.
Collect logs after crew completes.
BVPS -1 NRC Scenado 1 17 of 17
RTL# A5.670.AA 1/2-ADM-1357.F1 1 Page 1 of 1 Revision 0 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE: Licensed Operator Initial Training SUBDIVISION: Simulator SCENARIO TITLE/NO.: 1LOT5 NRC Exam Scenario #2 COMPUTER CODE FOR L.P.: N/A 4W
/
IN _ _ _ _ _ _ _:: :.......
1 8/27/02 2 9/26/02 3 9/30/02 INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 2.0 Hours PREPARED BY: Western Technical Services Inc. 8/27/02 Date R. Ernfield 9/30/02 REVIEWED BY:
Date APPROVED FOR IMPLEMENTATION:
Date BVPS-1 NRC Scenario 2 Page 1 of 15
Program Title 2002 NRC Examination Initial Conditions REV 2 INITIAL CONDITIONS: IC 172 PW = 5NRC2 97% power, Equ. XE, MOL, 1055 PPM, CB"D" = 215 steps.
ADDITIONAL LINEUP CHANGES STICKERS VOND MARKINGS FW-P-3A in P-T-L FW-P-3A YCT W/Red Slash N/A FW-P-3A ESF Status Light lit EQUIPMENT STATUS DATEITIME OOS TECHNICAL SPECIFICATION(S)
FW-P-3A is OOS 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior TS 3.7.1.2 Action c SHIFT TURNOVER INFORMATION
- 1. Raise power to 100%.
- 2. Severe weather is forecasted for the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- 3. FW-P-3A is on clearance due to a motor ground and is not expected back this shift.
4.
SCENARIO SUPPORT MATERIAL REQUIRED
- 1. Power Increase reactivity plan
- 2. 1OM-52.4A, Raising Power From 5% To Full Load Operation BVPS--1 NRC Scenario 2 4 of15
Appendix D Scenario Outline Form ES-D-1 Scenario Description The Crew will raise power.
After power has been raised to 100%, and the control rods are placed in automatic, a Power Range Channel summing amplifier output failed high will cause inadvertent, automatic rod motion, requiring operator action to place rod control in manual to stop inward rod motion. The Unit Supervisor will also be required to address Technical Specifications.
After conditions have stabilized and actions have been taken for the failed Power Range Channel, the Letdown Backpressure Regulator valve PCV-CH-145 fails closed, resulting in a loss of normal letdown, increased pressure in the letdown line, and lifting of the letdown relief valve with associated alarms.
After the Letdown Backpressure Regulator valve is reopened with the controller in manual and letdown is restored, one running Component Cooling (CCR) Pump trips, and PCV-CC-100 fails requiring the operator to take manual control and restore pressure.
A CCR Supply line leak will develop in the supply line to RCP 'B' and ramp to 500 GPM over a ten minute period, requiring operator action to locate and isolate the leak.
Before the reactor can be manually tripped, RCP 'B' will experience a locked rotor resulting in an automatic reactor trip.
Following the reactor trip, the Main turbine will fail to trip automatically and the MSIVs will fail to close automatically requiring operator action to manually trip the turbine and close the MSIVs.
Also following the reactor trip, an RCS Loop "B" large break LOCA will occur at 2000 GPM, and a failure of automatic safety injection Train A and Train B will occur, requiring operator action to manually initiate safety injection.
Procedure flow path is E-0 -4 E-1.
BVPS-1 NRC Scenario 2 Page 3 of 15
BEAVER VALLEY POWER STATION Training Administrative Manual I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE OBJECTIVE I EXPECTED STUDENT RESPONSE US assumes control and directs Operators to increase reactor power to 100% IAW 1OM 52.4.A, Step A.118 EVENT 1 Raise power to 100%. Turbine load and reactor power Crew reviews/agrees with reactivity plan. US increasing at 12%/hr. approves for use. Crew begins power increase.
RO places rod control in automatic when 100%
power is reached.
EVENT 2 Power Range NI N-44 fails HIGH.
After power has been raised to 100% and control rods are placed in automatic IMF NIS03D (0 0) 200 PR Channel N44 fails high. RO notes failure and informs US/crew.
N44 power indications upscale.
Annunciator A4-69, Neutron Flux Rate RO determines failed instrument.
High alarms.
Annunciator A-465, NIS PR High Setpoint Neutron Flux High.
Control Rods insert. US directs RO to place Control Rods in MANUAL.
Rod motion stops. RO places rod control in manual.
BVPS-1 NRC Scenario 2 5 of!15
BEAVER VALLEY POWER STATION Training Administrative Manual INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE US refers to AOP 1.2.1 C, Power Range Channel Malfunction.
US directs turbine load decrease at 1%/min to maintain Tavg within 2°F of Tref PO initiates turbine load decrease.
PO removes control power supply fuses from drawer A of N-44 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
PO turns Rod Stop Bypass switch to BYPASS for N44.
PO turns the Comparator Channel Defeat switch to N44.
RO verifies vertical board recorders are selected to monitor only operable detectors.
Note: US refers to T.S. 4.2.1.1.b - directs that AFD be STA will perform (simulate) QPTR monitored and trended in accordance with 1OM and report satisfactory results. 49.4.L.
T.S. 3.2.4 - QPTR Continue with next event at Lead T.S. 3.3.3.1 Table 3.1, Item 2, Action 2 Examiner's discretion.
EVENT3 IOR X06A087P (0 0) I PCV- ICH-145 fails closed, resulting in a loss of normal letdowrn BVPS-1 NRC Scenario 2 6 of 15
BEAVER VALLEY POWER STATION Training Administrative Manual INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE Annunciator A3-107, NRHX Disch Press RO notes indications and alarms, informs US.
High.
After delay, A3-123, Regen Heat US refers to AOP 1.7.1.
Exchanger Relief Line Temp High.
RO reports zero flow indicated on 1CHS-FI150.
RO takes manual control of PCV-1CH-145 and restores letdown flow to previous value.
US contacts I&C to investigate failure of PCV CH-145.
Proceed with next event at evaluators discretion.
EVENT 4 IMF CCW3A (5 0) Running CCR Pump trips and PCV-ICC IMF CCW08B (5 0) 500 600 0 100 Fails Open IOR X16A056P (5 0) 0 TRG! 5 A6-33, Primary Comp Cool Pump Auto Crew identifies trip of running CCR pump, Start-Stop. informs US.
A6-35, Pfi Comp Cool Pump Disch Press Low.
A6-38, Pri Comp Cool Wtr Heat Exchanger 8" Disch Line Flow Low.
A6-46, Pri Comp Cool Wtr Heat Exchanger 14" Disch Line Flow Lo.
BVPS-1 NRC Scenario 2 7 of 15
BEAVER VALLEY POWER STATION Training Administrative Manual INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE EXPECTED STUDENT RESPONSE A3-75, React Cool PP Lower Brg Lube Oil Cool Water Flow Low.
A3-77, React Cool PP Stator Winding Cool Water Flow Low.
A3-83, React. Cool PP Upper BRG Lube Oil Cool Water Flow Low NOTE: Drill assumes crew goes US acknowledges reports, enters AOP 1.15.1.
directly to AOP 1.15.1 "Loss of Primary Component Cooling Water" CCR Surge tank level on scale. PO reports CCR surge tank level normal.
CC-P- lA tripped. RO reports CC-P-1B operating.
CC-P- lB in operation supplying the header.
NOTE: Leak is slowly increasing, CCR surge tank level is slowly reducing. Crew monitors surge tank level for trends.
tank level reduction at this time Auto makeup valve slowly opening.
may not be noticed by crew.
Opening of LCV-CC- 100 may not be noticed at this time but will seen as leak rate continues to increase.
1 CCR pump operating, 1 pump tripped, RO reports pump status and that second pump CCR pump discharge pressure low. cannot be started due to CC-P-i C not racked PCV-CC-100 failed open. onto ANY bus.
NOTE: Drill assumes crew will US implements actions of Attachment 3, "CCR address low pressure firsm and then Pump Discharge Pressure Low",
notice level reduction I CCR pump operating RO reports only I CCR pump available BVPS-,1 NRC Scenario 2 8 of 15
BEAVER VALLEY POWER STATION Training Administrative Manual INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE OBJECTIVE EXPECTED STUDENT RESPONSE CCR pump discharge pressure low. RO reports CCR system status, places CC-P-1A CCR temperature normal. in PTL, CCR flow low due to PCV open.
PCV-CC-100 indicates 100% demand. Crew determines PCV-CC-100 failed open.
CCR system pressure returning to US directs PO to place PCV-CC-100 in normal. "manual" and restore system pressure.
Decreasing CCR surge tank level. Crew identifies and reports leak in CCR system.
A6-37, Pri Comp Cool Wtr Surge Tank Level High-Low.
US implements actions of Attachment 1 based on continuous action step 3.
LCV-CC- 100 in manual and opened. US directs PO to place LCV-CC-100 in manual and open valve to restore level.
A1-49, Containment Sump Level High. Crew determines that CCR header leak is inside containment, Non-essential loads isolated. Crew attempts to locate the leak.
US may direct a reactor shutdown.
US will direct reactor trip per AOP 1.6.8 "Abnormal RCP Operation" for any of the following:
Pump radial brg temp >21 OF Seal leakoff temp > 225F Motor brg temp > 20OF BVPS-.1 NRC Scenario 2 9 of!15
BEAVER VALLEY POWER STATION Training Administrative Manual INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE EXPECTED STUDENT RESPONSE EVENT 5 Prior to Crews decision to manually trip the Reactor, IMF RCS09B (0 0) RCP "B" locked rotor.
The Main Turbine will fail to trip automatically following the reactor trip.
LOW Loop 2 flow indication low (< CREW - Identify/report trip of RCP with loss of 90%) RCS loop flow Loop - 3 R.C. LOW FLOW Status Panel lights lit (Chan 1 RED, Chan II WHITE, Chan III BLUE)
RO and PO commence immediate actions of E 0, US references E-0 to verify immediate actions.
Crew performs immediate operator Crew performs IMAs of E-0.
actions of E-0.
EVENT #5: Reactor trip and bypass breakers open. RO verifies reactor tripped.
Neutron flux decreasing.
IMF RCS02B (1 0 ) 2000 Rod bottom lights lit.
(preloaded) Rod position indication at 0.
2000 gpm LOCA inside CNMT when the reactor is tripped RO sounds standby alarm.
BVPS I NRC Scenario 2 10 of 15
BEAVER VALLEY POWER STATION Training Administrative Manual INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE OBJECTIVE I EXPECTED STUDENT RESPONSE EVENT #5 (cont) Throttle and governor valves OPEN. PO reports the turbine did not trip automatically.
Reheat stops and interceptors OPEN.
AUTO TURBINE TRIP FAILURE.
CT#1 E-0o.: US directs the PO to trip the main turbine Crew manually trips the main manually.
turbine before a Severe (orange path) challenge develops to either CT#1 the Sub-criticality or the Integrity CSF or before transition to ECA 2.1, whichever occurs first.
Both turbine pushbuttons depressed. PO manually trips the main turbine.
CT#1 Throttle and governor valves closed. PO verifies turbine tripped.
Reheat stops and interceptors closed.
Depress reheat controller, reset PO ensures reheat steam isolated.
pushbutton.
Reheat flow control and block valves closed.
Main generator output breakers open. PO verifies generator trip.
Main Gen volts 0.
Exciter circuit breaker open.
1AE / 1DF buses energize. PO verifies power to AE/DF buses.
BVPSol NRC Scenario 2 11 of 15
BEAVER VALLEY POWER STATION Training Administrative Manual I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE [ EXPECTED STUDENT RESPONSE CT#2 E-O.D: RCS pressure reducing. Crew checks for SI, assesses plant status and CNMT pressure/temp. increasing. manually actuates SI if not already actuated, Crew manually actuates at least continues with E-0.
one train of SIS actuated safeguards before transition to CT#2 any ORP.
Only exceptions to Attachment 1-K US directs operator to perform Attachment l-K, are: Verification of Automatic Actions, as FW-P-3A OOS at turnover time/manpower permit, continues with E-0.
AUTO SI (BOTH TRAINS) failure.
AUTO MSIV closure failure.
All other checks/conditions SAT for current plant conditions.
NOTE: MSIVs failed to auto close on low steamline pressure. Crew should close MSIVs. If not closed at this time, Crew should close MSIVs when CNMT pressure increases above 3 psig.
When requested to align the WR H 2 analyzers insert:
Crew directs operator to place wide range H2 IMF XN02097 (0 0) 1 Annun A2-97 energizes. analyzers in service.
IMF XN02105 (0 0) 1 Annun A2-105 energizes.
H2 analyzers in service And report actions to the control roorri BVPS-1 NRC Scenario 2 12 of 15
BEAVER VALLEY POWER STATION Training Administrative Manual INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE EXPECTED STUDENT RESPONSE VS-F-4A running. PO verifies at least one leak collection exhaust fan running.
Tavg < 547°F and dropping RO/PO check RCS Tavg stable at or trending to 547'F, report Cold Leg temperatures dropping.
PORVs, safeties and spray valves RO checks PRZR PORV's, safeties, spray valve indicate closed. closed.
PRT parameters as expected for current RO checks PRT conditions.
plant conditions.
PORV lineup SAT. RO checks PORV lineup.
RCPs may be secured due to loss of "A & C" RCPs running. RO reports RCPs status.
CCR flow. (may be stopped).
SGs not faulted Crew verifies no SGs faulted.
All SG Tubes intact. Crew verifies no SGTR event in progress.
Crew transitions to E-1. US makes transition to E-1, informs crew.
CREBAPS not required. PO re-checks control room habitability.
NOTE: Drill assumes that RCP trip criteria is met at this point in the drill.
CT#3 E-1.C: RCPs stopped. RO stops RCPs if not previously performed Crew trips all RCPs when RCS to when trip criteria exceeded.
highest SG D/P criteria is exceeded and SI flow verified CT#3 prior to exiting procedure E-I1 BVPS-1 NRC Scenario 2 13 of 15
BEAVER VALLEY POWER STATION Training Administrative Manual INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE EXPECTED STUDENT RESPONSE -j SGs not faulted, PO checks if any SG is faulted.
PO maintains intact SG levels 13% [30%] to 50%.
NR level 13% to [30%] 50% or total feed Crew checks intact SG level, flow > 355 gpm.
Instrument air pressure >100 psig. PO verifies PI-1IA-106 > 100 psig.
PORV shut in auto and block valve RO verifies PORVs and block valves.
energized.
No SG levels rising in an uncontrolled PO checks for ruptured SG.
manner, no secondary rad monitor alarms.
No PZR level RO/PO check if SI can be terminated.
RCS pressure reducing CIfB not actuated. US checks if CTMT spray should be stopped.
SI & CIA reset. RO resets SI & CIA.
RCS pressure > 300 PSIG and RO checks if LHSI pumps should be stopped, decreasing.. does not stop LHSI pumps.
LHSI pumps not stopped.
All SG pressures stable. PO checks SG pressures stable or rising.
R(ICS pressure reducing. RO checks RCS pressure stable or reducing BVPS-1 NRC Scenario 2 14 of 15
BEAVER VALLEY POWER STATION Training Administrative Manual INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE Terminate drill.
BVPS-1 NRC Scenario 2 15 of !5
RTL# A5.670.AA 1/2-ADM-1357.F1 1 Page 1 of 1 Revision 0 SIMULATOR EVALUATION SCENARIO COVER PAGE PROGRAM TITLE: Licensed Operator Initial Training SUBDIVISION: Simulator SCENARIO TITLE/NO.: 1LOT5 NRC Exam Scenario #3 COMPUTER CODE FOR L.P.: N/A 1 _ 8/27/02 i
INSTRUCTIONAL SETTING: Simulator APPROXIMATE DURATION: 2.0 Hours PREPARED BY: Western Technical Services Inc. 8/27/02 Date REVIEWED BY: R. Ernfield 8/27/02 Date APPROVED FOR IMPLEMENTATION:
Date BVPS-1 NRC Scenario 2 Page 1 of !7
Appendix D Scenario Outline Form ES-D-1 Scenario
Description:
The Crew shifts in-service turbine plant component cooling pumps and continues the reactor startup increasing reactor power above 10%.
After exceeding 10% power, an intermediate range instrument power fuse blows requiring the RO to verify the failed instrument channel. The Unit Supervisor should direct actions in accordance with AOP-1.2.1 B and refer to Technical Specifications.
The Pressurizer master level controller then fails low causing charging flow to decrease, backup heaters to turn off as level drops, and letdown to isolate. The RO must take manual control of the Pressurizer level controller to terminate the event.
After Pressurizer level control is re-established, the steam header pressure transmitter fails high causing the condenser steam dump valves to open. After identifying the failure, the PO will take manual control and close the steam dump valve.
When conditions have stabilized, a steam break occurs on 'C' SG inside containment followed by failure of the reactor to automatically trip; however, manual trip is available from BB "A" only Following safety injection, quench spray pump 'IA' trips and quench spray pump 'IB' fails to start automatically but can be manually started. Containment isolation phase 'B' isolation then fails to actuate automatically, but can be manually initiated by the operator.
The expected procedure flow path is E-0 --> E-2 --> ES-1.1.
BVPS-1 NRC Scenario 3 3 of 17
Program Title 2002 NRC Examination Initial Conditions REV 2 INITIAL CONDITIONS: IC 173 PW = 5NRC3 7% power, equ XE, BOL, 1868 PPM boron, CB "D" at 103 steps.
ADDITIONAL LINEUP CHANGES STICKERS VOND MARKINGS FW-P-3A in P-T-L FW-P-3A YCT W/Red Slash N/A FW-P-3A ESF Status Light lit EQUIPMENT STATUS DATE/TIME OOS TECHNICAL SPECIFICATION(S)
FW-P-3A is OOS 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago TS 3.7.1.2 Action c SHIFT TURNOVER INFORMATION
- 1. Shift the in-service CCT pumps.
- 2. Continue with the plant startup.
31 Severe weather is forecasted for the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- 4. FW-P-3A is on clearance due to a motor ground and is not expected back this shift.
SCENARIO SUPPORT MATERIAL REQUIRED
- 1. Power increase reactivity plan
- 2. 1OM-52.4A, Raising Power From 5% To Full Load Operation BVPS-. ! NRC Scenario 3 4 of17
BEAVER VALLEY POWER STATION Training Administrative Manual I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE When the shift turnover is Simulator running. Crew assumes control of the unit.
complete, place the Simulator to RUN and commence the drill.
EVENT #1 Shift in-service CCT Pumps PO shifts in-service CCT Pumps.
Verify 1CC-P-3B aligned for standby operation.
Direct local operator to verify 1CC-P 3B has adequate oil level.
ICC-P-3B running. Start 1CC-P-3B.
Direct local operator to verify proper operation.
1CC-P-3A stopped. Stop 1CC-P-3A and place control switch in automatic.
EVENT #2 Reactor Power Increase Continue with plant startup. Reactor at 7% power. Crew commences power increase in accordance with reactivity plan.
US references 1OM-52.4.A, Step 4.b to continue the power increase.
BVPS-1 NRC Scenario 3 5 of 17
BEAVER VALLEY POWER STATION Training Administrative Manual INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE RO commences raising reactor power to between 10 and 20%.
Status lights on Panel 176 actuate at RO verifies P-i10 bistables actuate as 10%. required as power increases to > 10%.
Status light Intermediate Range Rx Trip RO blocks the IR Trip and Rod Stop blocked is on. and verifies status lights on.
Status light Power Range Low Setpoint RO blocks Power Range low Blocked in on. Overpower Trip and verifies status lights on.
NOT P-7 is off. RO verifies that status light NOT P-7 is off.
RO selects highest power range channels on NR-45 recorder.
EVENT #3 Intermediate Range NI-3 5 Failure Meters for NI-3 5 indicate zero and blown fuse indication exists on drawer.
After Crew has raised reactor power to greater than 10% and IR trips have been blocked, insert:
IR Channel NI-3 5 Instpwr, fuse blows, I[MF NIS07A (0 0) 0 BVPS-1 NRC Scenario 3 6 of!17
BEAVER VALLEY POWER STATION Training Administrative Manual INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE EXPECTED STUDENT RESPONSE Rod block alarms actuated. Loss of detector/compensating voltage.
A4-93, NIS Intermediate Range Loss Of RO acknowledges alarms and performs CH I Detector Voltage a channel check to identify NI-3 5 as the failed channel.
A4-94, NIS Intermediate Range Loss Of US refers to AOP-1.2. lB. Verifies CH I Compensation Voltage 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 a caution tag on source range channels.
US references Technical Specification 3.3.1.1.
US directs the Crew to continue with the Unit startup.
RO withdraws rods to raise reactor power to 15 to 18%.
RO/PO maintain reactor power, Tavg, and SG level in preparation for Unit synchronization.
BVPS-1 NRC Scenario 3 -7of 17
BEAVER VALLEY POWER STATION Training Administrative Manual INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE 1 EXPECTED STUDENT RESPONSE I EVENT #4 IMF PRS013 (0 0) 0 PZR Level Controller Fails Low Charging pump flow decreases. Backup heaters may turn off as level drops.
Letdown isolation may occur.
A3-58, Charging Pump Disch Flow RO notes indications and alarm, High/Low informs US.
US refers to ARP's.
PZR level control in manual. US directs RO to take manual PZR level control.
RO takes manual control of PZR level controller.
US requests I&C to investigate controller failure.
EVENT #5 IMF MSS11 (0 0) 1400 45 PT-1MS-464 Fails High over 45 sec.
Condenser steam dump valves open. PO recognizes steam dumps opening and diagnoses failure of PT-IMS-464.
BVPS-1 NRC Scenario 3 8 of 17
BEAVER VALLEY POWER STATION Training Administrative Manual I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE OBJECTIVE I EXPECTED STUDENT RESPONSE ]
US directs PO to take manual control of steam dump valve controller.
Steam dump valves closed. PO takes manual control of AM- IMS 464B and closes steam dump valves.
US contacts I&C to investigate failure.
EVENT #6 IMF MSS1C (0 0) 9E5 120 SG "C" Main Steam Line Break Inside Containment Containment temperature and pressure US directs manual reactor trip due to rising. rising containment pressure.
LMF CRF12A (pre-loaded) Reactor fails to automatically trip. RO and PO commence Immediate Operator Actions of E-0.
RO informs US of failure of reactor trip and first out annunciators.
US directs RO to manually trip the reactor.
CT#1 E-O.A: Reactor trip from BB "B" unsuccessful. RO reports failure to trip from BB "B" Crew manually trips the reactor and attempts manual trip from BB "A" from the control room before Reactor trip from BB "A" successful. and reports trip successful.
performing the mitigation strategy of FR-S. ., CT#1 BVPS-1 NRC Scenario 3 9 of 17
BEAVER VALLEY POWER STATION Training Administrative Manual I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE ]
Reactor trips, turbine trips, RCS pressure drops.
Crew performs immediate operator Crew performs IMAs of E-0.
actions of E-0.
Reactor trip and bypass breakers open. RO verifies reactor tripped.
Neutron flux decreasing.
Rod bottom lights lit.
Rod position indication at 0.
RO sounds standby alarm.
Throttle and governor valves closed. PO verifies turbine tripped.
Reheat stops and interceptors closed.
Depress reheat controller, reset PO ensures reheat steam isolated.
pushbutton.
Reheat flow control and block valves closed, Main generator output breakers open. P0 verifies generator trip.
Main Generator Volts zero.
Exciter circuit breaker open.
1AE / 1DF buses energize. PO verifies power to AE/DF buses.
BVPS-1 NRC Scenario 3 *10 of 17
BEAVER VALLEY POWER STATION Training Administrative Manual I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE NOTE: If crew does not manually RCS pressure reducing. Crew checks for SI, assesses plant actuate SI at this time, SI will be CNMT pressure/temp. increasing. status and manually actuates SI if not required due to degrading overall "C" S/G pressure reducing more than "A already actuated, continues with E-0.
status due to steam break on "C" & B" S/Gs.
SG. Crew will be required to return to E-0 at that time.
Only exceptions to Attachment I-K US directs operator to perform are: Attachment l-K, Verification of Automatic Actions, as time/manpower FW-P-3A OOS at turnover. permit, continues with E-0.
Auto CIB failed to actuate.
QS-P-1B failed to auto start.
QS-P-1A trips after startup.
All other checks/conditions SAT for current plant conditions.
NOTE: Plant/containment Automatic actions eventually occur:
conditions will degrade due to SI, CIA, FWI, MSLI.
steam break.
The following actions to satisfy CNMT pressure > 8 psig. RO reports CNMT status and that CIB CT#2 may be performed at some CIB not actuated. has not occurred.
later time in the drill if CIB conditions have not been exceeded US directs RO to manually actuate at this time. CIB.
BVPS--1 NRC Scenario 3 11 of 17
BEAVER VALLEY POWER STATION Training Administrative Manual INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE F EXPECTED STUDENT RESPONSE CT#2 E-O.E: RO manually actuates CIB by pressing Crew manually actuates at least 4 PBs (2 per train) and reports actions the minimum required to US.
complement of CNMT cooling equipment before an Extreme CT#2 (red path) challenge develops to containment. RO stops RCPs after CfB initiation, informs US.
QS-P-1B does not auto start. RO notes failure of Q S-P-i B to start, manually starts pump, reports action to US.
CT#2 QS-P-1 A trips 15 seconds after start. Crew notes loss of QS-P-IA, reports to US.
When requested to align WR H2 Annun A2-97 energizes. Crew directs operator to place wide analyzers insert: Annun A2-105 energizes. range H2 analyzers in service.
H2 analyzers in service.
IMF XN02097 (0 0) 1 IMF XN02105 (0 0) 1 and report actions to the control room VS-F-4A running. PO verifies at least one leak collection exhaust fan running.
BVPS-1 NRC Scenario 3 12 of 17
BEAVER VALLEY POWER STATION Training Administrative Manual I INSTRUCTIONAL GUIDELINES 1 PLANT STATUS OR RESPONSE I OBJECTIVE I
EXPECTED STUDENT RESPONSE Tavg reducing due to faulted SG. RO/PO check RCS Tavg stable at or trending to 547'F.
PORVs, safeties and spray valves RO checks PRZR PORV's, safeties, indicate closed. spray valve closed.
PRT parameters as expected for current RO checks PRT conditions.
plant conditions.
PORV lineup SAT. RO checks PORV lineup.
RCPs NOT running due to CIB RO reports RCPs status.
"C" SG pressure dropping. PO checks if any SGs are faulted.
Crew transitions to E-2. US makes transition to E-2, and informs crew.
US directs SNA to monitor status trees.
PO verifies CREBAPS actuated, As U-2 operator, when requested, Bottle discharge lights lit.
report proper CREBAPS actuation. Intake and exhaust dampers closed. requests Unit 2 CREBAPS verification.
All yellow SLI marks lit. Crew verifies steam line isolation.
Note: "A" and "B" SG pressures "A" and "B" SG pressure stable. PO checks for any non-faulted SG.
may be dropping due to effects of "C" SG fault, but should not be diagnosed as faulted.
BVPS-I NRC Scenario 3 13 of 17
BEAVER VALLEY POWER STATION Training Administrative Manual INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE OBJECTIVE I EXPECTED STUDENT RESPONSE "C" SG pressure dropping PO identifies "C" SG as faulted.
uncontrollably.
FCV-FW-498 closed. PO verifies "C" MFRV closed.
FCV-FW-499 closed. PO verifies "C" BPFRV closed.
MOV-FW-151A & B closed, PO closes MOV-FW-151A & B.
MS-17 NSA closed. Crew addresses the fact that TDAFW supply valve MS-17 is NSA closed.
PCV-MS- 101C closed. RO/PO verify "C" S/G atmospheric HCV-MS- 104 closed. dump valve and RHR valve closed.
No SG level rising in an uncontrolled Crew checks if SG tubes are intact.
manner.
NOTE: If"C" SG has completely Subcooling > 43 [58]'. RO/PO check if SI can be terminated blown down by this time, Secondary heat sink sufficient. and if so, transition to ES- 1.1.
conditions to terminate SI will be RCS pressure stable or rising.
met and crew will transition to ES PRZR level > 18 [37]%.
1.1. If so, skip to page 16 for ES 1.1 actions. If SI termination criteria not met, crew transitions to E-1.
Crew transitions to E-1. US makes transition to E-1, informs crew BVPS..1 NRC Scenario 3 14 of 17
BEAVER VALLEY POWER STATION Training Administrative Manual S
................ ............ I I INSTRUCTIONALGUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE I CREBAPS actuated per E-2. PO re-checks control room habitability.
RCPs NOT running. RO checks if RCPs should be stopped.
"C" SG previously diagnosed as faulted PO checks if any SG is faulted.
and isolated (pending reports of local operator actions).
PO maintains intact SG levels 13%
[30%] to 50%.
NR level 13% to [30%] 50% or total feed Crew checks intact SG level.
flow > 355 gpm.
Instrument air pressure >100 psig. PO verifies PI-1IA-106 > 100 psig.
PORV shut in auto and block valve RO verifies PORVs and block valves.
energized.
No SG levels rising in an uncontrolled PO checks for ruptured SG.
manner, no secondary rad monitor alarms.
Subcooling > 43 [58]o. RO/PO check if SI can be terminated.
Secondary heat sink sufficient.
RCS pressure stable or rising.
PRZR level > 18 [37]%.
BVPS-.1 NRC Scenario 3 15 ot 17
BEAVER VALLEY POWER STATION Training Administrative Manual INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE EXPECTED STUDENT RESPONSE Crew transitions to ES- 1. 1. US makes transition to ES-1.1, informs crew.
SI reset. US directs RO to reset SI and CIA.
CIA reset.
CIB reset.
Two HHSI pumps running. US directs RO to secure one HHSI pump.
One HHSI pump running. RO secures one HHSI pump.
I AE and 1DF 4KV stub busses energized.
CCR pumps in P-T-L. PO re-energizes stub busses.
Aux RW Pumps in P-T-L.
Report 8N22 and 9P21 closed. CNMT air recirc fans in P-T-L.
CRDM shroud fans in P-T-L.
PRZR heaters 2A and 2B in P-T-L.
CNMT instrument air compressors in P-T-L.
IRF EPS138 (0 0) 1 480V stub busses energized. RO/PO directs 480V stub busses RF EPS140 (0 0) 1 energized.
Automatic cold leg recirc change over RO resets automatic cold leg recirc reset. change over (both trains).
Chiller verified in service PO starts CNMT instrument air compressors.
BVPS-1 NRC Scenario 3 16 of 17
BEAVER VALLEY POWER STATION Training Administrative Manual I INSTRUCTIONAL GUIDELINES I PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE TV- ICC- I IOD and F2 open. PO opens containment recirc cooling coils AC/RW outlet.
TV- ICC-110E2 and E3 open. PO opens containment recirc cooling coils AC inlet containment isolation valves.
CNMT instrument air compressor PO starts an available containment IA running. compressor.
CNMT air header pressure > 85 psig.
RCS pressure stable or rising. RO checks RCS pressure.
MOV-CH-289 and 310 open. RO establishes normal charging flow.
FCV-CH-122 throttled to maintain Pressurizer level.
MOV-SI-867A through D shut. RO isolates the BIT.
Terminate the drill in after the BIT is isolated, BVPS-1 NRC Scenario 3 17 of '17