ML023020177

Final - Section C Operating

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:

SUBDIVISION:

SCENARIO TITLE/NO.:

COMPUTER CODE FOR L.P.:

"-/-

. i INSTRUCTIONAL SETTING:

APPROXIMATE DURATION:

PREPARED BY:

REVIEWED BY:

Licensed Operator Initial Training Simulator 1LOT5 NRC Exam Scenario #1 N/A 7o Simulator 2.0 Hours Western Technical Services Inc.

R. Ernfield APPROVED FOR IMPLEMENTATION:

BVPS-1 NRC Scenario 1 1

8/27/02 8/27/02 Date 8/27/02 Date Date i

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:

IC 171 PW = 5NRCI 75% power MOL EQU XE, 1128 PPM, CB"D" = 188 steps 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 BVPS -1 NRC Scenario 1 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

1. Power reduction reactivity plan

2. 1OM-52.4.B, Load Following Initial Conditions REV 1

4 of 17

BEAVER VALLEY POWER STATION Training Administrative Manual Volume 3 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 FWM01B (preloaded)

FW-P-1B trips.

Annunciator A7-37, SG Feed Pump Auto Stop.

Annunciator A7-39, SG Feed Pump Disch Flow Hi Start 2d Pump.

PO recognizes feed pump trip and informs US.

Refers to ARPs as time permits.

US directs load decrease to < 63% at 5% /

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 Training Administrative Manual Volume 3 Procedure 5-9 Revision 11 Figure 5-9.6 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE PZR level transmitter LT-RC-459 fails low.

PZR control level deviation low alarm A4-4.

PZR control level low alarm, A4-3.

LCV-CH-460A, TV-CH-200A, B, C close.

RO recognizes problem with PZR level channel, informs US, refers to ARP, and Instrument Failure Procedure 1.6.4.WF,.

RO informs US that LT-RC-459 failed low.

PZR heaters off Letdown isolates and actual PZR level rises.

Continue with next event when letdown has been reestablished.

EVENT #4 "B" SG Steam Flow Transmitter

[FT-MS-484] fails low.

IMF MSS14C (0 0) 0 Level alarms clear, charging flow begins decreasing, high flow alarm clears.

FT-MS-484 Fails low.

US directs Operator to defeat level control input with PZR level channel and recorder selector switches per 1.6.41F Attachment 1.

RO informs US that Channels 460 and 461 are selected.

US directs the Operators to reestablish normal letdown, re-energize pressurizer heaters.

lOM-24.4.IF BVPS -1 NRC Scenario 1 IMF PRS06A (0 0) 0 6 of 17

BEAVER VALLEY POWER STATION Training Administrative Manual Volume 3 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" Feedwater flow decreases causing SG levels to decrease.

SG level stabilizes.

US determines that 1OM-24.4.IF Attachment 3 is to be implemented.

PO determines which channel has failed by comparing with other steam flow indicators.

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 IMF BST-RCS157 (0 0) 0 IMF BST-RCS056 (0 0) 0 DOR XS03C23 Continue with scenario at examiners discretion.

Protection chanel III door 18 open.

BS-488C tripped.

BS-488B tripped.

Protection chanel III door 18 closed.

Crew monitors tripping of bistables associated with FT-MS-484.

BVPS -1 NRC Scenario 1 7 of 17

BEAVER VALLEY POWER STATION Training Administrative Manual Volume 3 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 After appropriate delay, report N-16 monitor alarm is associated with the "B" SG.

A4-88, Steam Gen N-16 Monitor Alert/High Trouble.

A4-71, Rad Monitor High.

A4-72, Rad Monitor High High.

PZR level reducing.

PZR pressure reducing.

Charging flow increasing.

Additional Annunciators associated with degrading plant conditions actuate.

RO calls out alarms to crew.

US dispatches operator to N-16 monitor.

RO reports degrading plant conditions.

US directs RO to manually trip the reactor and crew to perform IMAs of E-0.

Crew performs immediate operator actions of E-0.

Reactor trip and bypass breakers open.

Neutron flux decreasing.

Rod bottom lights lit.

Rod position indication at 0.

Crew performs IMAs of E-0.

RO verifies reactor tripped.

RO sounds standby alarm.

BVPS -1 NRC Scenario 1 8 of 17

BEAVER VALLEY POWER STATION Training Administrative Manual Volume 3 Procedure 5-9 Revision 11 Figure 5-9.6 INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE I OBJECTIVE I EXPECTED STUDENT RESPONSE NOTE: If crew does not manually actuate SI at this time, SI will be required due to degrading overall status due to SGTR on "B" SG.

Crew will be required to return to E-0 at that time.

Throttle and governor valves closed.

Reheat stops and interceptors closed.

Depress reheat controller, reset pushbutton.

Reheat flow control and block valves closed.

Main generator output breakers open.

Main Generator Volts zero.

Exciter circuit breaker open.

1AE / IDF buses energize.

RCS pressure reducing.

PZR level continues to reduce.

Only exceptions to Attachment 1-K are:

FW-P-3A OOS at turnover.

FW-P-2 & FW-P-3B failed to auto start and were started manually.

All other checks/conditions SAT for current plant conditions.

PO verifies turbine tripped.

PO ensures reheat steam isolated.

PO verifies generator trip.

PO verifies power to AE/DF buses.

Crew checks for SI, assesses plant status and manually actuates SI if not already actuated, continues with E-0.

US directs operator to perform Attachment l-K, Verification of Automatic Actions, as time/manpower permit, continues with E-0.

BVPS -1 NRC Scenario 1 9 of 17

BEAVER VALLEY POWER STATION Training Administrative Manual Volume 3 Procedure 5-9 Revision 11 Figure 5-9.6 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE EXPECTED STUDENT RESPONSE CT E-0.F:

CT-#1 Crew establishes the minimum required AFW flow to 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-HA0I 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 Automatic actions eventually occur:

SI, CIA, FWI.

When requested to align WR H2 analyzers insert:

IMF XN02097 (0 0) 1 IMF XN02105 (0 0) 1 Crew directs operator to place wide range H2 analyzers in service.

Annun A2-97 energizes.

Annun A2-105 energizes.

H2 analyzers in service.

and report actions to the control room VS-F-4A running.

Tavg approx 547°F and stable.

PO verifies at least one leak collection exhaust fan running.

RO/PO check RCS Tavg stable at or trending to 5470F.

BVPS -1 NRC Scenario 1 10 of 17

BEAVER VALLEY POWER STATION Training Administrative Manual I INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE PORVs, safeties and spray valves indicate closed.

PRT parameters as expected for current plant conditions.

PORV lineup SAT.

RCPs running.

No SGs faulted.

"B" SG level rising in uncontrolled manner.

I OBJECTIVE I Crew transitions to E-3.

CREBAPS not actuated, not required.

All RCPs running.

CCR flow, RCS/SG D/P > 200 psig.

"B" SG identified.

PCV-MS-101B closed.

HCV-MS-104 closed.

Steam supply from ruptured SG to FW P-2 NOT PREVIOUSLY ISOLATED.

FW-P-3A OOS at turnover..

FW-P-3B - running.

BVPS -1 NRC Scenario 1 I

Volume 3 Procedure 5-9 Revision 11 Figure 5-9.6 EXPECTED STUDENT RESPONSE RO checks PRZR PORV's, safeties, spray valve closed.

RO checks PRT conditions.

RO checks PORV lineup.

RO reports RCPs running.

PO checks if any SGs are faulted.

Crew identifies "B" SG as being ruptured.

US exits E-0, enters E-3 and informs crew.

Crew checks CREBAPS status.

RO checks if RCPs should be stopped, does not stop RCPs.

US identifies "B" S/G as the ruptured S/G, based on operator reports.

RO/PO verify "B" S/G atmospheric dump valve and RHR valve closed.

Crew determines status of steam supply to FW P-2.

PO reports status of Motor driven AFW pumps.

11 of 17

BEAVER VALLEY POWER STATION Training Administrative Manual Volume 3 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.

MS open.

MS closed.

LMF MSS18B (2 0) 1E5 IMF XN11026 (2 0) 1 (both pre-loaded)

Steam Leak on "B" steam line in MS valve room when TV-MS 101B is shut.

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.

TV-MS-I11B shut.

"B" SG main steam trip, bypass and non return valves shut.

TV-MS-1I0B MOV-MS-1O1B NRV-MS-101B Al 1-26, Main Steam Valve Room Temp High.

Steam Flow indicated on "B" SG.

"B" SG pressure reducing.

US directs closure of MOV-MS-105.

Crew addresses the fact that TDAFW supply valve MS-16 is NSA open, it must be closed and MS-17 must be opened.

US directs operators to isolate flow to/from the "B" S/G.

PO reports Al 1-26 alarm and indication of steam flow on "B" SG, and "B" SG pressure reducing.

Crew transitions to E-2.

As U-2 operator, when requested, report proper CREBAPS actuation.

Bottle discharge lights lit.

Intake and exhaust dampers closed.

US makes transition to E-2, and informs crew.

PO verifies CREBAPS actuated, requests Unit 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 Training Administrative Manual Volume 3 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 may be dropping due to effects of "B" SG fault, but should not be diagnosed as faulted.

As operator sent to swap steam supply to FW-P-2, report that you are unable to enter the Main Steam Valve Room due to steam leak.

"A" and "C" SG pressure stable.

"B" SG pressure dropping uncontrollably.

FCV-FW-488 closed.

FCV-FW-489 closed.

MOV-FW-151C & D closed.

MS-16 open.

MS-17 closed.

PCV-MS-101B closed.

HCV-MS-104 closed.

"B" SG previously identified as ruptured.

Crew transitions back to E-3 AFW secured to ruptured S/G in E-2 regardless of NR level.

"B" - MOV-FW-151C & D - CLOSED.

FWI previously verified.

PO checks for any non-faulted SG.

PO identifies "B" SG as faulted.

PO verifies "B" MFRV closed.

PO verifies "B" BPFRV closed.

PO closes MOV-FW-151C & D.

PO reports that operator is unable to shift steam supply to FW-P-2 due to steam leak in the area.

RO/PO verify "B" S/G atmospheric dump valve and RHR valve closed.

Crew checks if SG tubes are intact.

US directs return to E-3, directs crew through High Level Action Steps previously performed.

PO checks ruptured SGWL and maintains AFW flow isolated to "B" SG PO re-verifies FWI has occurred.

BVPS -1 NRC Scenario 1 13 of 17

BEAVER VALLEY POWER STATION Training Administrative Manual Volume 3 Procedure 5-9 Revision 11 Fiqure 5-9.6 INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE EXPECTED STUDENT RESPONSE Ruptured SG pressure > 380 psig.

Station instrument air pressure> 100 psig.

Target temperature determined based on ruptured SG pressure.

1000 - 1099# -- 507F (491F adverse).

900 - 999#

-- 495F (479F adverse).

Condenser steam dumps NOT available due to MSLI.

RCS pressure < 1950 psig.

Average of the 5 highest TCs at target temperature.

Intact SG levels > 13% (30% adverse)

NR.

Power to all block valves, All PORVs closed.

All block valves open, all PORVs in auto.

PO verifies ruptured SG pressure is greater than 380 psig.

PO verifies station air pressure > 100 psig.

US determines target temperature.

SNA trends cooldown rate.

Crew initiates RCS cooldown at the maximum rate to the target temperature using "A&C" Atmospheric Steam Dumps.

RO blocks steamline SI when RCS pressure is below 1950 psig.

Crew stops RCS cooldown and maintains RCS at target temperature.

PO checks intact SG levels, controls levels between 20% (36% adverse) and 50%.

RO checks/reports status of PORVs and block valves.

BVPS -1 NRC Scenario 1 14 of 17

BEAVER VALLEY POWER STATION Training Administrative Manual INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE SI reset:

PNL 62-C4 NOT LIT.

PNL 62-D4 LIT.

CIA/CIB reset.

CNMT instrument air available

(> 100 psig, A6-1 10 NOT LIT).

RCS pressure > 300 psig (475 psig adverse).

LHSI pumps stopped/in auto.

Core exits TCs maintained < target temperature.

Ruptured SG pressure DROPPING to W/I 250# of intact SGs.

Crew transitions to ECA-3.1 RWST level > 19 ft.

Previously performed.

Stub busses energized.

CNMT Inst Air system operating properly.

I OBJECTIVE Volume 3 Procedure 5-9 Revision 11 Figure 5-9.6 EXPECTED STUDENT RESPONSE RO resets SI, CIA, and CIB.

PO checks/reports CNMT instrument air system status.

RO stops LHSI pumps, places them in auto.

PO controls RCS temperature at/below target temperature.

PO reports status of ruptured SG pressure.

US directs transition to ECA-3.1 based on operator reports.

RO verifies RWST level > 19 ft.

RO verifies SI, CIA and CIB reset.

PO verifies stub busses energized.

PO verifies CNMT instrument air available.

BVPS -1 NRC Scenario 1 Iz 15 of 17

BEAVER VALLEY POWER STATION Training Administrative Manual Volume 3 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.

PZR HTRS in PTL.

CIB has not actuated.

"B" SG steam and feed flow isolated previously.

RCS pressure greater than 300 psig.

Pressure not reducing unexpectedly.

(may be reducing due to cooldown, but not due to RCS LOCA).

Aux Building and safeguards radiation consistent with pre-event values. Obtain samples as required.

"B" S/G previously identified and isolated. "A" and "C" intact.

"A" & "C" Narrow range level - greater than 13%.

Control feed flow to maintain "A' & "C" SG narrow range level between 20 and 50%.

PO verifies all AC busses - energized by offsite power.

RO places all PZR heaters in pull to lock.

RO checks if any Quench Spray Pumps running.

PO checks ruptured SG NR level > 13%, then verifies "B" SG isolated regardless of SGWL.

RO reports LHSI pumps previously stopped and in auto.

US initiates evaluation of plant status.

PO checks if all SGs are faulted.

PO checks intact SG levels.

PO controls feed flow as required.

BVPS -1 NRC Scenado I 16 of 17

BEAVER VALLEY POWER STATION Training Administrative Manual Volume 3 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

> 100 psig.

ECA-3.1.B CT #2 - Crew initiates cooldown of the RCS to cold shutdown conditions at the highest rate achievable but less than 100°F/hr in all RCS cold legs.

Do not exceed 1 00°F/hour cooldown in RCS cold leg.

RWST level > 38 ft.

Terminate drill when crew checks if subcooled recovery is appropriate in ECA-3.1.

Collect logs after crew completes.

"B" SG narrow range level < 94 [83]%.

PO checks station air pressure.

US directs chemistry to sample RCS boron hourly for SDM verification.

PO commences cooldown using "A" & "C" S/Gs atmospheric relief valves at < 100°F per

hour, CT #2 US checks if subcooled recovery is appropriate and continues with the next step.

PO checks ruptured SG NR level < 94%.

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:

SUBDIVISION:

SCENARIO TITLE/NO.:

COMPUTER CODE FOR L.P.:

Licensed Operator Initial Training Simulator 1LOT5 NRC Exam Scenario #2 N/A INSTRUCTIONAL SETTING:

APPROXIMATE DURATION:

PREPARED BY:

REVIEWED BY:

Western Technical Services Inc.

R. Ernfield APPROVED FOR IMPLEMENTATION:

BVPS-1 NRC Scenario 2 IN 1

8/27/02 2

9/26/02 3

9/30/02 4W





/

Simulator 2.0 Hours 8/27/02 Date 9/30/02 Date Date Page 1 of 15

Program Title 2002 NRC Examination 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 Initial Conditions REV 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 EVENT 1 Raise power to 100%.

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 Turbine load and reactor power increasing at 12%/hr.

PR Channel N44 fails high.

N44 power indications upscale.

US assumes control and directs Operators to increase reactor power to 100% IAW 1 OM 52.4.A, Step A.118 Crew reviews/agrees with reactivity plan. US approves for use. Crew begins power increase.

RO places rod control in automatic when 100%

power is reached.

RO notes failure and informs US/crew.

Annunciator A4-69, Neutron Flux Rate High alarms.

Annunciator A-465, NIS PR High Setpoint Neutron Flux High.

Control Rods insert.

Rod motion stops.

RO determines failed instrument.

US directs RO to place Control Rods in MANUAL.

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.

US refers to T.S. 4.2.1.1.b - directs that AFD be monitored and trended in accordance with 1 OM 49.4.L.

Note:

STA will perform (simulate) QPTR and report satisfactory results.

T.S. 3.2.4 - QPTR Continue with next event at Lead Examiner's discretion.

T.S. 3.3.3.1 Table 3.1, Item 2, Action 2 EVENT3 IOR X06A087P (0 0) I BVPS-1 NRC Scenario 2 PCV-I CH-145 fails closed, resulting in a loss of normal letdowrn 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 High.

After delay, A3-123, Regen Heat Exchanger Relief Line Temp High.

RO notes indications and alarms, informs US.

US refers to AOP 1.7.1.

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)

IMF CCW08B (5 0) 500 600 0 IOR X16A056P (5 0) 0 TRG! 5 Running CCR Pump trips and PCV-ICC 100 Fails Open A6-33, Primary Comp Cool Pump Auto Start-Stop.

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.

Crew identifies trip of running CCR pump, informs US.

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 directly to AOP 1.15.1 "Loss of Primary Component Cooling Water" US acknowledges reports, enters AOP 1.15.1.

NOTE: Leak is slowly increasing, tank level reduction at this time 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.

CCR Surge tank level on scale.

CC-P-lA tripped.

CC-P-lB in operation supplying the header.

CCR surge tank level is slowly reducing.

Auto makeup valve slowly opening.

PO reports CCR surge tank level normal.

RO reports CC-P-1B operating.

Crew monitors surge tank level for trends.

1 CCR pump operating, 1 pump tripped, CCR pump discharge pressure low.

PCV-CC-100 failed open.

NOTE: Drill assumes crew will address low pressure firsm and then notice level reduction I CCR pump operating RO reports pump status and that second pump cannot be started due to CC-P-i C not racked onto ANY bus.

US implements actions of Attachment 3, "CCR Pump Discharge Pressure Low",

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 CCR pump discharge pressure low.

CCR temperature normal.

CCR flow low due to PCV open.

PCV-CC-100 indicates 100% demand.

CCR system pressure returning to normal.

Decreasing CCR surge tank level.

A6-37, Pri Comp Cool Wtr Surge Tank Level High-Low.

LCV-CC-100 in manual and opened.

A1-49, Containment Sump Level High.

Non-essential loads isolated.

OBJECTIVE EXPECTED STUDENT RESPONSE RO reports CCR system status, places CC-P-1A in PTL, Crew determines PCV-CC-100 failed open.

US directs PO to place PCV-CC-100 in "manual" and restore system pressure.

Crew identifies and reports leak in CCR system.

US implements actions of Attachment 1 based on continuous action step 3.

US directs PO to place LCV-CC-100 in manual and open valve to restore level.

Crew determines that CCR header leak is inside containment, 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 (<

90%)

Loop - 3 R.C. LOW FLOW Status Panel lights lit (Chan 1 RED, Chan II WHITE, Chan III BLUE)

CREW - Identify/report trip of RCP with loss of RCS loop flow RO and PO commence immediate actions of E 0, US references E-0 to verify immediate actions.

Crew performs immediate operator actions of E-0.

EVENT #5:

IMF RCS02B (1 0 ) 2000 (preloaded) 2000 gpm LOCA inside CNMT when the reactor is tripped Reactor trip and bypass breakers open.

Neutron flux decreasing.

Rod bottom lights lit.

Rod position indication at 0.

Crew performs IMAs of E-0.

RO verifies reactor 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)

AUTO TURBINE TRIP FAILURE.

CT#1 E-0o.:

Crew manually trips the main turbine before a Severe (orange path) challenge develops to either the Sub-criticality or the Integrity CSF or before transition to ECA 2.1, whichever occurs first.

Throttle and governor valves OPEN.

Reheat stops and interceptors OPEN.

PO reports the turbine did not trip automatically.

US directs the PO to trip the main turbine manually.

CT#1 Both turbine pushbuttons depressed.

PO manually trips the main turbine.

CT#1 Throttle and governor valves closed.

Reheat stops and interceptors closed.

Depress reheat controller, reset pushbutton.

Reheat flow control and block valves closed.

Main generator output breakers open.

Main Gen volts 0.

Exciter circuit breaker open.

1AE / 1DF buses energize.

PO verifies turbine tripped.

PO ensures reheat steam isolated.

PO verifies generator trip.

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 RCS pressure reducing.

CNMT pressure/temp. increasing.

Crew manually actuates at least one train of SIS actuated safeguards before transition to any ORP.

Only exceptions to Attachment 1-K are:

FW-P-3A OOS at turnover AUTO SI (BOTH TRAINS) failure.

AUTO MSIV closure failure.

All other checks/conditions SAT for current plant conditions.

Crew checks for SI, assesses plant status and manually actuates SI if not already actuated, continues with E-0.

CT#2 US directs operator to perform Attachment l-K, Verification of Automatic Actions, as time/manpower permit, continues with E-0.

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 H2 analyzers insert:

IMF XN02097 (0 0) 1 IMF XN02105 (0 0) 1 Annun A2-97 energizes.

Annun A2-105 energizes.

H2 analyzers in service Crew directs operator to place wide range H2 analyzers in service.

And report actions to the control roorri BVPS-1 NRC Scenario 2 CT#2 E-O.D:

12 of 15

BEAVER VALLEY POWER STATION Training Administrative Manual INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE EXPECTED STUDENT RESPONSE VS-F-4A running.

Tavg < 547°F and dropping PORVs, safeties and spray valves indicate closed.

PRT parameters as expected for current plant conditions.

PORV lineup SAT.

PO verifies at least one leak collection exhaust fan running.

RO/PO check RCS Tavg stable at or trending to 547'F, report Cold Leg temperatures dropping.

RO checks PRZR PORV's, safeties, spray valve closed.

RO checks PRT conditions.

RO checks PORV lineup.

RCPs may be secured due to loss of CCR flow.

"A & C" RCPs running.

(may be stopped).

SGs not faulted All SG Tubes intact.

Crew transitions to E-1.

CREBAPS not required.

RO reports RCPs status.

Crew verifies no SGs faulted.

Crew verifies no SGTR event in progress.

US makes transition to E-1, informs crew.

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:

Crew trips all RCPs when RCS to highest SG D/P criteria is exceeded and SI flow verified prior to exiting procedure E-I1 BVPS-1 NRC Scenario 2 RCPs stopped.

RO stops RCPs if not previously performed when trip criteria exceeded.

CT#3 13 of 15

BEAVER VALLEY POWER STATION Training Administrative Manual INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE SGs not faulted, NR level 13% to [30%] 50% or total feed flow > 355 gpm.

Instrument air pressure >100 psig.

PORV shut in auto and block valve energized.

No SG levels rising in an uncontrolled manner, no secondary rad monitor alarms.

No PZR level RCS pressure reducing CIfB not actuated.

SI & CIA reset.

RCS pressure > 300 PSIG and decreasing..

LHSI pumps not stopped.

All SG pressures stable.

R(ICS pressure reducing.

EXPECTED STUDENT RESPONSE PO checks if any SG is faulted.

PO maintains intact SG levels 13% [30%] to 50%.

Crew checks intact SG level, PO verifies PI-1IA-106 > 100 psig.

RO verifies PORVs and block valves.

PO checks for ruptured SG.

RO/PO check if SI can be terminated.

US checks if CTMT spray should be stopped.

RO resets SI & CIA.

RO checks if LHSI pumps should be stopped, does not stop LHSI pumps.

PO checks SG pressures stable or rising.

RO checks RCS pressure stable or reducing BVPS-1 NRC Scenario 2

-j 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:

SUBDIVISION:

SCENARIO TITLE/NO.:

COMPUTER CODE FOR L.P.:

INSTRUCTIONAL SETTING:

APPROXIMATE DURATION:

PREPARED BY:

REVIEWED BY:

Licensed Operator Initial Training Simulator 1LOT5 NRC Exam Scenario #3 N/A Simulator 2.0 Hours Western Technical Services Inc.

R. Ernfield APPROVED FOR IMPLEMENTATION:

BVPS-1 NRC Scenario 2 1

8/27/02 i

8/27/02 Date 8/27/02 Date Date Page 1 of !7

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 Scenario Outline Form ES-D-1 Appendix D 3 of 17

Program Title 2002 NRC Examination INITIAL CONDITIONS: IC 173 PW = 5NRC3 7% power, equ XE, BOL, 1868 PPM boron, CB "D" at 103 steps.

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 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 Initial Conditions REV 2

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 complete, place the Simulator to RUN and commence the drill.

EVENT #1 Shift in-service CCT Pumps Simulator running.

Crew assumes control of the unit.

PO shifts in-service CCT Pumps.

Verify 1CC-P-3B aligned for standby operation.

Direct local operator to verify 1 CC-P 3B has adequate oil level.

ICC-P-3B running.

1CC-P-3A stopped.

Start 1 CC-P-3B.

Direct local operator to verify proper operation.

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 Status lights on Panel 176 actuate at 10%.

Status light Intermediate Range Rx Trip blocked is on.

Status light Power Range Low Setpoint Blocked in on.

NOT P-7 is off.

RO commences raising reactor power to between 10 and 20%.

RO verifies P-i10 bistables actuate as required as power increases to > 10%.

RO blocks the IR Trip and Rod Stop and verifies status lights on.

RO blocks Power Range low Overpower Trip and verifies status lights on.

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 After Crew has raised reactor power to greater than 10% and IR trips have been blocked, insert:

I[MF NIS07A (0 0) 0 Meters for NI-3 5 indicate zero and blown fuse indication exists on drawer.

IR Channel NI-3 5 Instpwr, fuse blows, 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 CH I Detector Voltage A4-94, NIS Intermediate Range Loss Of CH I Compensation Voltage RO acknowledges alarms and performs a channel check to identify NI-3 5 as the failed channel.

US refers to AOP-1.2. lB. 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 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 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 High/Low RO notes indications and alarm, 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 IMF PRS013 (0 0) 0 8 of 17

BEAVER VALLEY POWER STATION Training Administrative Manual I INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE OBJECTIVE I EXPECTED STUDENT RESPONSE ]

Steam dump valves closed.

US directs PO to take manual control of steam dump valve controller.

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 LMF CRF12A (pre-loaded)

CT#1 E-O.A:

Crew manually trips the reactor from the control room before performing the mitigation strategy of FR-S..,

SG "C" Main Steam Line Break Inside Containment Containment temperature and pressure rising.

Reactor fails to automatically trip.

Reactor trip from BB "B" unsuccessful.

Reactor trip from BB "A" successful.

US directs manual reactor trip due to rising containment pressure.

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.

RO reports failure to trip from BB "B" and attempts manual trip from BB "A" and reports trip successful.

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 actions of E-0.

Reactor trip and bypass breakers open.

Neutron flux decreasing.

Rod bottom lights lit.

Rod position indication at 0.

Throttle and governor valves closed.

Reheat stops and interceptors closed.

Depress reheat controller, reset pushbutton.

Reheat flow control and block valves

closed, Main generator output breakers open.

Main Generator Volts zero.

Exciter circuit breaker open.

1AE / 1DF buses energize.

Crew performs IMAs of E-0.

RO verifies reactor tripped.

RO sounds standby alarm.

PO verifies turbine tripped.

PO ensures reheat steam isolated.

P0 verifies generator trip.

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 actuate SI at this time, SI will be required due to degrading overall status due to steam break on "C" SG. Crew will be required to return to E-0 at that time.

NOTE: Plant/containment conditions will degrade due to steam break.

The following actions to satisfy CT#2 may be performed at some later time in the drill if CIB conditions have not been exceeded at this time.

RCS pressure reducing.

CNMT pressure/temp. increasing.

"C" S/G pressure reducing more than "A

& B" S/Gs.

Only exceptions to Attachment I-K are:

FW-P-3A OOS at turnover.

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.

Automatic actions eventually occur:

SI, CIA, FWI, MSLI.

CNMT pressure > 8 psig.

CIB not actuated.

Crew checks for SI, assesses plant status and manually actuates SI if not already actuated, continues with E-0.

US directs operator to perform Attachment l-K, Verification of Automatic Actions, as time/manpower permit, continues with E-0.

RO reports CNMT status and that CIB has not occurred.

US directs RO to manually actuate 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:

Crew manually actuates at least the minimum required complement of CNMT cooling equipment before an Extreme (red path) challenge develops to containment.

QS-P-1B does not auto start.

Q S-P-1 A trips 15 seconds after start.

When requested to align WR H2 analyzers insert:

Annun A2-97 energizes.

Annun A2-105 energizes.

H2 analyzers in service.

RO manually actuates CIB by pressing 4 PBs (2 per train) and reports actions to US.

CT#2 RO stops RCPs after CfB initiation, informs US.

RO notes failure of Q S-P-i B to start, manually starts pump, reports action to US.

CT#2 Crew notes loss of QS-P-IA, reports to US.

Crew directs operator to place wide range 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 Tavg reducing due to faulted SG.

I OBJECTIVE PORVs, safeties and spray valves indicate closed.

PRT parameters as expected for current plant conditions.

PORV lineup SAT.

RCPs NOT running due to CIB "C" SG pressure dropping.

Crew transitions to E-2.

As U-2 operator, when requested, report proper CREBAPS actuation.

Note: "A" and "B" SG pressures may be dropping due to effects of "C" SG fault, but should not be diagnosed as faulted.

Bottle discharge lights lit.

Intake and exhaust dampers closed.

All yellow SLI marks lit.

"A" and "B" SG pressure stable.

BVPS-I NRC Scenario 3 13 of 17 I

EXPECTED STUDENT RESPONSE RO/PO check RCS Tavg stable at or trending to 547'F.

RO checks PRZR PORV's, safeties, spray valve closed.

RO checks PRT conditions.

RO checks PORV lineup.

RO reports RCPs status.

PO checks if any SGs are faulted.

US makes transition to E-2, and informs crew.

US directs SNA to monitor status trees.

PO verifies CREBAPS actuated, requests Unit 2 CREBAPS verification.

Crew verifies steam line isolation.

PO checks for any non-faulted SG.

BEAVER VALLEY POWER STATION Training Administrative Manual INSTRUCTIONAL GUIDELINES I

PLANT STATUS OR RESPONSE OBJECTIVE I EXPECTED STUDENT RESPONSE NOTE: If"C" SG has completely blown down by this time, conditions to terminate SI will be met and crew will transition to ES 1.1. If so, skip to page 16 for ES 1.1 actions. If SI termination criteria not met, crew transitions to E-1.

"C" SG pressure dropping uncontrollably.

FCV-FW-498 closed.

FCV-FW-499 closed.

MOV-FW-151A & B closed, MS-17 NSA closed.

PCV-MS-101C closed.

HCV-MS-104 closed.

No SG level rising in an uncontrolled manner.

Subcooling > 43 [58]'.

Secondary heat sink sufficient.

RCS pressure stable or rising.

PRZR level > 18 [37]%.

PO identifies "C" SG as faulted.

PO verifies "C" MFRV closed.

PO verifies "C" BPFRV closed.

PO closes MOV-FW-151A & B.

Crew addresses the fact that TDAFW supply valve MS-17 is NSA closed.

RO/PO verify "C" S/G atmospheric dump valve and RHR valve closed.

Crew checks if SG tubes are intact.

RO/PO check if SI can be terminated and if so, transition to ES-1.1.

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 I

INSTRUCTIONALGUIDELINES I

PLANT STATUS OR RESPONSE CREBAPS actuated per E-2.

RCPs NOT running.

"C" SG previously diagnosed as faulted and isolated (pending reports of local operator actions).

I OBJECTIVE I EXPECTED STUDENT RESPONSE I PO re-checks control room habitability.

RO checks if RCPs should be stopped.

PO checks if any SG is faulted.

NR level 13% to [30%] 50% or total feed flow > 355 gpm.

Instrument air pressure >100 psig.

PORV shut in auto and block valve energized.

No SG levels rising in an uncontrolled manner, no secondary rad monitor alarms.

Subcooling > 43 [58]o.

Secondary heat sink sufficient.

RCS pressure stable or rising.

PRZR level > 18 [37]%.

PO maintains intact SG levels 13%

[30%] to 50%.

Crew checks intact SG level.

PO verifies PI-1IA-106 > 100 psig.

RO verifies PORVs and block valves.

PO checks for ruptured SG.

RO/PO check if SI can be terminated.

BVPS-.1 NRC Scenario 3 15 ot 17 S

I

BEAVER VALLEY POWER STATION Training Administrative Manual INSTRUCTIONAL GUIDELINES PLANT STATUS OR RESPONSE OBJECTIVE EXPECTED STUDENT RESPONSE US makes transition to ES-1.1, informs crew.

US directs RO to reset SI and CIA.

Report 8N22 and 9P21 closed.

IRF EPS138 (0 0) 1 RF EPS140 (0 0) 1 Two HHSI pumps running.

One HHSI pump running.

I AE and 1DF 4KV stub busses energized.

CCR pumps in P-T-L.

Aux RW Pumps in P-T-L.

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.

480V stub busses energized.

Automatic cold leg recirc change over reset.

Chiller verified in service US directs RO to secure one HHSI pump.

RO secures one HHSI pump.

PO re-energizes stub busses.

RO/PO directs 480V stub busses energized.

RO resets automatic cold leg recirc change over (both trains).

PO starts CNMT instrument air compressors.

BVPS-1 NRC Scenario 3 SI reset.

CIA reset.

CIB reset.

Crew transitions to ES-1. 1.

16 of 17

BEAVER VALLEY POWER STATION Training Administrative Manual I INSTRUCTIONAL GUIDELINES Terminate the drill in after the BIT is isolated, BVPS-1 NRC Scenario 3 17 of '17 I

PLANT STATUS OR RESPONSE TV-I CC-I I OD and F2 open.

TV-ICC-110E2 and E3 open.

CNMT instrument air compressor running.

CNMT air header pressure > 85 psig.

RCS pressure stable or rising.

MOV-CH-289 and 310 open.

FCV-CH-122 throttled to maintain Pressurizer level.

MOV-SI-867A through D shut.

I OBJECTIVE I EXPECTED STUDENT RESPONSE PO opens containment recirc cooling coils AC/RW outlet.

PO opens containment recirc cooling coils AC inlet containment isolation valves.

PO starts an available containment IA compressor.

RO checks RCS pressure.

RO establishes normal charging flow.

RO isolates the BIT.