Text

Nov/Dec Exam 50-390/2002-301 Final Simulator Scenarios & Outlines
	ML032481004
Person / Time
Site:	Watts Bar
Issue date:	11/26/2002
From:	; Tennessee Valley Authority
To:	; Office of Nuclear Reactor Regulation
References
	50-390/02-301, 50-391/02-301
	Download: ML032481004 (75)
	v • d • e

Final Submittal (Blue Paper)

1.

As Given Simulator Scenario Operator Actions ES-D-2 WATTS BAR EXAM 2002-301 50-390 I NOVEMBER 26 &

DECEMBER 9 - 13,2002

Scenario Outline Form ES-D-1 Appendix D Facility:

WATTS BAR Scenario No.:

1 Op-Test No.:

Examiners:

Operators:

Malf.

No.

CV51 RXl 1 (CCO7A)

(CC03A)

(TC02)

)eactivity

' GO-4, Step 5.1 but Of Service Event Type*

0 N

(BOP)

I (RO)

R I (R0,BOP 330)

.12 Event Description Power Increase Place 2nd feed pump in servlce Failure of FT-62-142 - Inhibits ability to dilute The failure will affects ROs ability to dilute. There are no alarms, so it will be necessary to require dilution in this timeframe for diagnosis of this failure. Plan to setup conditions for dilution as part of turnover, then insert this problem during second batch addition or after approximately 500 gallons has been added from the first batch (if large batch is used initially). Operators will have to determine quantitieshatch sizes for their power ascension.

P imp falls low PT-1-73 Affects auto rod control Tref program Steam dumps Should require RO to take control of control rods. BOP will have to take actions for steam dumps. To continue ramp, with this instrument failed should require the RO to manually operate the rods.

Tech Spec 3.3.1 Condition S..

CCP-1A-A Sheared Shaft with failure of Standby Pump to Auto start.

Affects A-Train Component Cooling Water, letdown, RCP cooling, etc.

Should require BOP to diagnose, and start CCP-16-6 when failure to start recognized or determination that CCP-1A-A is not pumping forward.

US will implement AOI-15 Section 3.2. RO will notice that CVCS Demin is bypassed, and after recovery of cooling may recommend restoration of flow to demin.

Tech Spec 3.7.7 Failure of EHC Auto control Turbine power begins to increase. The rate of increase is slow. The intent is to set the rate for a very slow increase. There are no alarms specific to this component failure. The BOP can terminate load increase bv Dlacina turbine control valves in

~~

~

manual or by lowing the valve position limiter. f h k is t k last event prior to the Major Transient. So if they trip, we will go straight into the MT.

(C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Facility:

WATTS BAR Scenario No.:

1 Op-Test No.:

6 (MSO2C)

Event Type*

M (ALL)

Event Description Main Steam Line Break Outside Containment At the point that the crew gets control of the turbine ramp or trips, this malfunction will be input. Assuming that they haven't tripped, the intent is to ramp this startiing at a rate similar to the rate that was caused by the EHC failure and increase it as necessary to drive them into the EOP's.

(N)ormal, (R)eaclivity, (I)nstrument, (C)omponent, (M)ajor

Scenario 1 Revision 0 Page 1 of 33 TITLE: Main Steam Line Break Outside Containment REVISION: 0 DATE: 11/22/02 PROGRAM: WBN Operator Training - Initial License PREPARED BY:

/

(Operations Instructor)

(Date)

VALIDATION BY:

I (Operations Instructor)

(Date) t 1

REVIEWED B Y I

(Lead Operations Instructor)

(Date)

APPROVED BY:

I (Operations Training Manager)

(Date)

CONCURRED:

I (Operations Superintendent)

(Date)

Scenario 1 Revision 0 Page 2 of 33 REVIS ION NUMBER 0

Nuclear Training RevisionlUsage Log DESCRIPTION OF REVISION nitial Issue DATE 1 1 /22/02 PAGES AFFECTED ALL REVIEWED BY

PROGRAM:

WBN Operator Training i

SUBJECT Simulator Examination Guide TITLE:

Main Steam Line Break Outside Containment.

LENGTH:

-1.2 Hours

REFERENCES:

Scenario 1 Revision 0 Page 3 of 33 L.

E-2 Faulted Steam Generator Isolation M. E-1 Loss of Reactor or Secondary Coolant 11 N.

ES-1.1 SI Termination 11 Please Dont Delete this line (This is hidden text)

Please Dont Delete this line (This is hidden text)

SCENARIO OBJECTIVES:

1. Evaluate the candidates ability to use normal and abnormal procedures and control the plant during normal and transient conditions.

Evaluate the candidates ability to use E-0 and E-2 in response to a Faulted Steam Generator.

2.

Scenario 1 Revision 0 Page 4 of 33 SCENARIO

SUMMARY

Initial conditions:

43% power, Cb = 141 0 ppm.

The Train Week is A. Channel Week I or 111 ok.

AI is out of target band on the high side requiring dilution to correct.

Power ascension, GO-4, Section 5.1, Step 12 in progress.

MDAFW pump 1A-A is out of service for maintenance.

Scenario Events and Sequence:

Set up simulator to IC-1 44

0. Performs dilution per Sol-62-02 to correct AI and continues power ascension.

1. Place second Main Feedwater Pump in service and continues power ascension.

2. 1-FT-62-142, Primary Water Flow Transmitter, failure.

3. Turbine Impulse Pressure Transmitter 1-PT-1-73 fails Low affecting rod control, steam dumps, and Tref program.

4. CCS Pump 1A sheared shaft with failure of standby pump to auto start.

5. Failure of EHC auto control.

6. Main Steam Line Break Outside Containment.

7. MSiV on # 3 S/G fails to close.

8. 1 B-B MD AFW Pump fails to start.

Scenario 1 Revision 0 Page 5 of 33 EVENT 0 - Raise reactor power from 43% to 100% power.

The crew continues power ascension from 43% power in accordance with General Operating Instruction, GO-4.

Malfunctions required: None Objectives:

Evaluates the candidates ability to perform dilution for AI correction.

Evaluates the candidates use of GOs to continue power escalation from 43%

power.

Evaluates the candidates ability to conduct operations associated with power escalation from 43% power including turbine load ascension and corresponding rise in reactor power.

Success Path:

Conduct power escalation from 43% power IAW GO-4.

EVENT 1 - Place the second Main Feedwater Pump in service 1 B Main Feedwater Pump is placed in service between 40 and 45% power.

Malfunctions required: None Objectives:

Evaluate the CREW use of GO-4, Normal Power Operation, and SOI-2&3.01,Condensate and Feedwater System, for placing the second Main Feedwater Pump in service.

Evaluates candidates ability to manually control Main Feedwater Pump speed and establish proper delta P for S/G level control.

Success Path:

Crew implements the appropriate procedures to place 1 B MFW Pump in service with master controller in automatic maintaining S/G level program.

Scenario 1 Revision 0 Page 6 of 33 EVENT 2 - Failure of 1-Ff-62-142, Primarv Water to Blender Flow Transmitter 1-FT-62-142 fails and after 30 seconds the PRIMARY WATER TO FLOW DEVIATION alarm will annunciate and terminate the dilution by closing 1-FCV-62-128 to the VCT. If 1 -FCV-62-128 is reopened manually, flow will be reestablished but there will be no flow indication or audible clicking from the batch counter. A dilution incident could be the result.

Malfunctions required: 1 CV51 Objectives:

Evaluate the candidates ability to recognize loss of dilution flow Evaluate the candidates ability to monitor reactor parameters to ensure dilution stopped and/or prevent from occurring.

Success Path:

Crew ensures dilution stopped and maintenance notified for repair of controller.

EVENT 3 PT-1-73. Turbine Impulse Pressure Transmitter, Fails LOW Turbine Impulse Transmitter, 1-PT-1-73, fails low causing control rods to begin insertion at a maximum rate. Operator will be required to take manual control of rods. Steam Dump control will be require to be placed in Steam Pressure Mode. Operators should respond using AOI-2.

Malfunctions required: 1 rxl1 0, Turbine Impulse Pressure Transmitter, 1-PT-1-73, fails low.

Objectives:

Evaluate the candidates ability to implement AOI-2 when Turbine Impulse Pressure Transmitter fails low.

Evaluates candidates ability to access control board indications to determine event in progress.

Success Path:

Crew implements AOI-2, section 3.2, to respond to Turbine Impulse Pressure Transmitter failure, places rod control to Manual, and places Steam Dump Control in Pressure Mode.

Scenario 1 Revision 0 Page 7 of 33 EVENT 4 - CCS Pump 1A-A Sheared Shaft with Failure of Stbv Pump to Start 1A CCS Pump shears its shaft bringing in multiple flow alarms associated with Alpha Train. The red pump light will be illuminated causing possible misdiagnosis to be made. The Bravo Train pump will not auto start on low pressure, and will require manual action to start. If not started, RCP motor temperatures will rise creating a reactor trip requirement and RCPs to be taken out of service. AOI-15 should be implemented.

Malfunctions required: 2 CC07A and CC03B Objectives:

Evaluate the candidates ability to diagnose a loss of the A Train CCS Pump from control board indicators and annunciators.

Evaluate the candidates ability to determine that automatic action should have started the 1 B CCS Pump and take manual action to start it.

Success Path:

Crew recognizes conditions for entry and implements AOI-15 in response to Component Cooling System Pump 1A sheared shaft. Conditions will dictate starting of the 1 B CCS Pump to restore flows, and the second running Thermal Barrier Booster Pump (TBBP) to be shutdown and returned to A-P Auto.

EVENT 5 - Failure of EHC Auto Control Turbine load starts to slowly rise with REFERENCE window on the turbine control panel slowly counting up. Reactor power will rise as turbine load rises and Tavg will drop giving the same indications as that of a small steam leak.

Malfunctions required: 1 TC02 ramped in over 10 minutes to 40% severity Objectives:

Evaluate candidates ability to recognize turbine control malfunctioning and take manual corrective actions.

Evaluate candidates ability to diagnose a steam leak in the plant vs. an internal problem with turbine controls.

Success Path:

Placing the turbine controls to MANUAL or placing it on the Valve Position Limiter will stop the load rise.

Scenario 1 Revision 0 Page 8 of 33 EVENT 6 - Main Steam Line Break Outside Containment

3 Steam Generator develops a leak outside containment complicating the cooldown by the above failure resulting in loss of RCS temperature control. If not monitored closely Tavg will drop below the minimum temperature for criticality setpoint. Manual reactor trip, SI, and MSlV closure should be directed. 1-FCV-1-22, MSlV on # 3 SIG will fail to close and the 1 B-B MD AFW Pump will fail to auto start.

Malfunctions: 3 MSOZC, ramped over 10 minutes to 10% severity, MSOGC, and S108H Objectives:

Evaluate the candidate's ability to diagnose a steam line break, and transition from E-0 to E-2, Faulted Steam Generator Isolation, and then to ES-1.l, SI Termination.

Success path; Crew implements E-2 to identify and isolate the faulted SG and terminate SI IAW ES-1.1

Scenario 1 Revision 0 Page 9 of 33 I

CONSOLE OPERATORS INSTRUCTIONS rst 144, switch check, select RUN Turn audible simulator fault alarm to "off' (down position)

Place " A Train Week" sign Place Dynamic AFD Display on OAC computer screen.

Place 1 HS-3-118A in PTL and tag 1 HS-3-118A and NOTE: IC 144 has been setup for this scenario. If unavailable, new setup for positive AI and power level will be required.

1-HS-3-355.

ior zlohs3355[1] off ior zlohs3355[2] off 1

ior zlohs3118a[l] off 1

I imf ms06c 100 imf si08h I

imf cc03B

$3 % RTP, BOL, Cb=l410 ppm, Bank D at 172 steps.

Prevents unnecessarily alerting crew 3f a simulator problem that may not effect simulator dynamics.

On entrance side panel. Channel Week I or 111 ok.

Will indicate on positive side of target band. Setup to require dilution on trunover.

Simulates 1A-A MDAFWP 00s for maintenance.

Simulates 1-FCV-3-355,lA-A MDAFWP Recirc, tagged closed.

Simulates 1A-A MDAFWP hand switch light out.

Fails S/G # 3 MSlV open.

Prevents auto start of MD AFW Pump 1 B-B.

CCS Pump 1 B-B fails to auto start.

i Scenario 1 Revision 0 Page 10 of 33 0

0 0

CONSOLE OPERATORS INSTRUCTIONS (Continued) irnf cv51 (e2) 1-FT-62-142, primary water to blender flow transmitter, signal fails low.

Results in no flow indication or audible click.

imf r x l l a (e3) 0 1-PT-1-73, impulse pressure transmitter fails low.

imf ccO7a (e4)

I CCS Pump 1A-A sheared shaft.

imf tc02 (e5) 40 10:

EHC auto control failure (raises turbine load) with ramp of 10 minutes to a 40% final severity.

imf ms02c (e6) 10 10:

Main steam line break outside containment with ramp of 10 minutes to a 10% final severity.

Wer crew assumes

hift

Vhen directed by he evaluator for

vent 2 (insert juring batch jilution)

When directed by he evaluator for Event 3 When directed by he evaluator for WENT 4 Scenario 1 Revision 0 Page 11 of 33 CONSOLE OPERATORS INSTRUCTIONS (Continued) mf itrigger2 Jmf cv51 - only if

?valuator request it mf itrigger3 imf itrigger4 ROLE PLAY: As TB AUO, when requested, assist in startup of 1 B MFWPT IAW SOI-2&3.01, Section 5.10.

1-FT-62-142, primary water to blender transmitter fails low.

ROLE PLAY As Work Control, inforn the crew that the transmitter work package will be initiated.

ROLE PLAY: Iflwhen cued by the evaluator for repair of flow Tx, as maint., state the transmitter was improperly valved in and can be signed off by performing makeup as PMT.

1-PT-1-73, Turbine impulse pressure transmitter, fails low.

ROLE PLAY: As Work Control, when contacted, inform the crew that this transmitter will be added to the work scope and ask for a priority between the two transmitters.

CCS Pump 1A sheared shaft.

ROLE PLAY: As AB AUO, when requested, report the coupling on the 1A CCS Pump is broken.

ROLE PLAY As Work Control, inforn the crew maintenance will look at the pump and initiate work package.

When directed by the evaluator for EVENT 5 When directed by the evaluator for EVENT 6 Scenario 1 Revision 0 Page 12 of 33 CONSOLE OPERATORS INSTRUCTIONS (Continued)

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',i. ::....,:. -... ;I

.......,,,.,C/MF,RF/oR;.; "

imf itrigger5 imf itrigger6 EHC auto control failure causing turbine load to rise.

ROLE PLAY: As AUO, if requested, state no steam leaks can be found.

ROLE PLAY: As Work Control, inform the crew that MIG, upon their approval, will look at the EHC panel in Aux Instrument Room to assess problem. No work will be done.

Main Steam Line Break outside containment.

ROLE PLAY: As Outside AUO, if requested, report steam coming from the North Valve Vault Room.

i

Scenario 1 Revision 0 Page 13 of 33 APPENDIX A INFORMATION TO EVALUATORS

1. Assign Crew Positions: Assign positions based on evaluation requirements for personnel.

US - Unit Supervisor OAC - Operator at Controls CRO - Control Room Operator

2. Review the Shift Briefing Information with the operating crew. Provide the US with a copy of Appendix 6, Shift Turnover Checklist.

3. Allow the crew to familiarize themselves with current control panel condition (up to 10 minutes).

4. Ensure recorders are inking and recording and ICs is active and updating. Note any deficiencies during shift briefing.

5. If not previously done, review any major differences between plant and simulator.

6. Review CONSOLE OPERATORS INSTRUCTON for INITIATING CUES.

i

Scenario 1 Revision 0 Page 14 of 33 OP Test No:

Scenario No.:

1 Event No.:

1 Page 1

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5 Event

==

Description:==

Crew will continue power ascension from 43% power using GO-4.

Startup of 2"d MFW Pump and Dilution to correct AI.

CREW us us us CRO CRO CRO CRO Walks control boards down in preparation for raising power.

Reviews GO-4 and determines power level is sufficient for placing the second MFW pump in service and addresses the delta I target band concern.

Directs OAC to determine dilution requirements and setup for dilution per Sol-62.02, Section 6.2 Directs CRO to place 1B MFW Pump in service per SOI-2&3.01, Section 5.10 for hot start.

Ensures 1 -PIC-3-40, MFW Deaeration Line Backpressure, set to 1200 psia and 1-PCV-3-40 is closed.

If hot startup, then reset selected MFP Turbine with l-HS-46-36A, MFPT B Trip-Reset.

Ensures the following valves open:

1 -BW-2-749, MFPT Condenser 1 B 1 -BW-2-776, MFPT Condenser 1 B 1 -FCV-2-211 1 -FCV-2-216.

~

Ensures selected MFPT condenser valves open:

1 -FCV-2-211, MFPT B Condenser Condensate Outlet.

1 -FCV-2-216, MFPT B Condenser Condensate Outlet.

See page 17 for dilution.

These two tasks may be performed separately due to peer checks.

Scenario 1 Revision 0 Page 15 of 33 OP Test No:

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5 Event

==

Description:==

Crew will continue power ascension from 43% power using GO-4.

Startup of 2nd MFW Pump and Dilution to correct AI.

CRO CRO CRO CRO CRO Ensures local vibration monitors reset at 1 -L-792 [el. 7551.

Ensures selected MFP Recirc closed and pump casing filled:

1 -FCV-30-84, Main Feedwater Pump B Recirc.

Verify selected MFP casing within 50°F.

of suction supply.

Close selected miniflow warm-up line:

1 -HCV-3-84, Main Feedwater Pump B Recirc Warming.

Place selected MFP(s) in service:

Ensure MFP speed changer control in manual, and set to minimum 1-SIC-46-2OB, MFPT B Speed Open MFP B discharge valve, 1-Ensures miniflow control valve, 1-FCV-3-84 in auto at 65%.

Ensures 1-PI-2-129, MFW Pmps Suction Pressure as follows:

Greaterthan 100 psig (below 50% load).

Greater than 250 psig (above 50% load).

Place MFP 1 B l-HS-46-43A, MFPT B HP Stop Valve, or l-HS-46-44A, MFPT B LP Stop Valve in raise to open the LP and HP stop valves simultaneously.

Control.

FCV-3-81.

Scenario 1 Revision 0 Page 16 of 33 OP Test No:

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5 Event

==

Description:==

Crew will continue power ascension from 43% power using GO-4.

Startup of 2d MFW Pump and Dilution to correct AI.

Ensures 2 Hotwell Pumps running.

Place selected Governor Valve Positioner, 1 -HS-46-40A, to Raise to roll MFP, and verify Governor Valve Positioner is at maximum position by red light indication on controller panel (green light off).

Load the MFP Turbine as desired with l-SIC-46-20B, MFPT B Speed Control.

If placing second MFPT in selvice and Auto operation is desired, then perform the following:

Ensure MFP speed changer control in manual, l-SIC 20B, and set to minimum and bias setpoint knob set to 50%.

Slowly adjust MFP B speed controller output to match the Master Controller PC-46-20.

Place MFP B speed changer, l-SIC-36-20B, in Auto.

Adjust bias setpoint slowly to achieve desired flow balance, Ensure MFP B Recirc, 1-FIC-3-84, opens by auto or manual action within one minute after pump start, and remains open as long as TDMFP flow is less than 2 X lo6 PPH/4000 gpm.

When TD MFP flow is >2 X 1 06/4000 gpm, then ensure 1 -FCV-3-84 Main Feedwater Pump B Recirc is closed.

1 Heater Relief is set at 1650 psig.

May take recirc valve to manual.

Raising bias setpoint

(>So% will lower MFP speed, lowering setpoint

(<50%) will raise MFP speed. Should not bias 40% because it may prevent MFPT from fully loading.

Scenario 1 Revision 0 Page 17 of 33 OP Test No:

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Event

==

Description:==

Crew will continue power ascension from 43% power using GO-4.

Startup of 2"d MFW Pump and Dilution to correct AI.

CRO CRO CRO OAC OAC OAC OAC Adjust MFP B oil temp control, 1-TCV-24-56B, as necessary to maintain oil temp leaving bearings 140" to 160°F When in service MFPT is loaded greater than 40% (apporx. 3 X 1 O6 PPH), then close selected MFP Turbine drains:

1-HS-46-14, MFPT A Drain VLVS.

1-HS-46-41, MFPT B Drain VLVS.

When selected MFP is in service and will remain in service, then close the following valves; 1-BYV-1-618, MFPT I B HP Steam Warming Line Isolation.

1 -BYV-1-684, MFPT 1 B HP Steam Warming Line Isolation.

The following are OAC steps necessary for dilution:

Determines required quantity of water to achieve desired RCS Cb.

Ensures 1-FC-62-142, PW To Blender dial, set to 35% (70 gpm), and Manual-Auto toggle in Auto.

~

Adjust 1-FQ-62-142, PW Batch Counter, for required quantity.

Place 1 -HS-62-1408, VCT Makeup Mode in DIL.

tp;i+,..~.:

..',(, i..., ' ' :

Comment.(SAT/UNSAT)j

...: i, :'*. i

Scenario 1 Revision 0 Page 18 of 33 5 of 5

Page __ -

OP Test No:

Scenario No.:

1 Event No.:

1 Event

==

Description:==

Crew will continue power ascension from 43% power using GO-4.

Startup of 2d MFW Pump and Dilution to correct AI Turn l-HS-62-140A, VCT Makeup

//

I OAC I Control to Start and verify red light is lit.

Ensures 1-HS-68-341 H, Backup Heater A

I OAC I C is on to equalize Pzr-RCS Cb.

OAC OAC Monitors the following parameters:

l-PI-62-122----VCT Press.

1 -LI-62-129A---VCT Level.

l-FI-62-142----PW to Blender Flow.

l-FQ-62-142-PW Batch Counter.

1 FQ-62-139----BA Batch Counter.

Monitors NIS and rod movement to verify Rods will insert to expected response.

depress delta 1.

OAC If 1 -LI-62-129A,VCT Level rises to 60%,

then ensure l-FCV-62-118A, Letdown Divert to HUT, diverts to the HUT.

Cue Console Operator for failure of 1-FT-62-142 EVENT 2

Scenario 1 Revision 0 Page 19 of 33 US OP Test No:

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1

~

May direct returning controls to automatic operation and notifying Work Control of malfunction.

No flow indication will be available, but flow can be established if valve to VCT is manually opened. No clicking of controller will be heard.

Event

==

Description:==

Low 1 -FT-62-142, Primary Water To Blender, Flow Transmitter Fails US OAC

~

Should postpone power ascension until primary water flow transmitter fixed.

Pulling rods with turbine ramp will not correct delta I problem.

Recognizes dilution has stopped either from flow indication going to 0, audible clicking noise from 1-FQ-62-142 stopped, or alarm window 112-E, PW TO BLENDER FLOW DEVIATION.

OAC Addresses ARI on window 1 12-E and reviews probable cause and corrective actions:

If dilution controls in Auto, then verify 1 -FCV-62-128 and 1 -FCV 144 Close.

Ensure VCT makeup control system lined up per Sol-62-02, Boron Concentration Control.

If manual operation of VCT makeup is required, then go to Sol-62.02 for system alignment and operation.

Refer to AOI-3, Malfunction of Reactor Makeup Control.

Controls will be in dilute.

Potential Critical Step (Unplanned dilution)

Reference to AOI-3 will be of no assistance unless dilution event created by the candidate.

Scenario 1 Revision 0 Page 20 of 33 OP Test No:

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0 Page 1

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Event Continue Power Ascension

==

Description:==

CRO CRO CRO CRO CRO us The following are steps associated with a power ascension if directed If power ascension is desired, cue Console Operator to delete 1 -FT-62-142 malfunction.

When reactor power is 45%, ensure Turbine Throttle Valve leakoffs Locked Open.

Ensures the following as system parameters permit:

3 HW Pumps running.

CBPs running when required.

2 MFPs running 2 # 3 HD Pumps running.

Starts the 2"d # 7 HD Pump per SOL5 &

Place remaining CCW Pumps in service to maintain maximum condenser vacuum per Sol-27.01.

Verifies generator H2 pressure sufficient for anticipated load per Sol-47-02, Appendix E, Capability Curve.

Before exceeding 50% reactor power, perform 1-SI-0-2 to verify AFD and QPTR within limits.

Cue Console Operator for 1 -PT-1-73 failure low.

EVENT 3

Scenario 1 Revision 0 Page 21 of 33 OAC us OAC OAC OAC OAC CRO

)AC/CRC

'laces rod bank selector switch in nanual, and verifies rods stop.

Rods step in at 72 steps per minute.

3efers to and implements AOI-2, Section 3.2.

I Scenario No.:

1 Event No.:

3 Page 1

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2 1-PT-1-73 Turbine Impulse Pressure Transmitter Fails Low vlaintains Tavg on program by use of

ontrol rods or adjusting turbine load

Attachment 2).

2hecks loop Tavg channels normal.

Control rods should be stepped back out to 172 steps if not moved since tu mover.

2hecks Auct Tavg normal on 1-TR 2B.

2hecks NIS power range channels iormal.

dentifies failure of PT-1-73 and places

team dumps in pressure mode.

Place steam dumps to OFF.

Place mode selector HS to STEAM PRESS.

Adjust steam dump demand to zero.

Place steam dumps to ON.

Ensure controller set at 84%.

0 0

0 Monitors core power distribution parameters:

Power range channels flux indicators Tavg LoopAT IncoreTCs Feed flow/Steam flow

Scenario 1 Revision 0 Page 22 of 33 OP Test No:

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Event

==

Description:==

1-PT-1-73 Turbine Impulse Pressure Transmitter Fails Low Notifies Work Control to have channel 1

I I repaired.

I Refer to Tech Spec and enters LCO 3.3.1.1 6. f Condition S.

I US Determines power change not greater Cue Console Operator than 15%, and Chemistry does not need to be notified.

for CCS Pump 1A sheared shaft. EVENT 4

Scenario 1 Revision 0 Page 23 of 33 CRO OP Test No:

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Event Description CCS Pump 1A Sheared Shaft When CCS returned normal, checks only one CCS pump per Train and one TBBP running.

Acknowledge multiple CCS System I I CRo I alarms.

US USlCRO Checks running pump indications for cause of alarms: Should see abnormal flows and sharp drop in pressure, if recorder is checked.

Refers to Tech Specs and enters LCO 3.7. 7 Condition A.

us Enters AOI-15, Section 3.2, for loss of CCS and directs crew actions. Sends AUO to investigate cause for pump problem.

CRO Realizes U-1 Train A header supply pump running and not pumping forward, and starts 1 B CCS Pump.

CRO Checks any Train B header supply pump running and pumping forward.

Places 1A-A CCS pump in pull-to-lock.

CRO I CRO I Checks flows returned to normal.

Checks A & B side surge tank levels I I CRo I between 57% and 85%.

Evaluates affected equipment operation using Appendix A.

US Contacts work control to initiate repairs I I I to CCS Pump.

CCS Pump 1A will have red light lit but no flow.

OAC should be aware that demineralizers will bypass due to high temp.

Stops one running TBBP and returns HS to A-P Auto.

Cue Console Operator for EHC failure. EVENT 5

Scenario 1 Revision 0 Page 24 of 33 OP Test No:

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Event

==

Description:==

Failure of EHC Auto Control CREW USlCRO CRO us CRO CRO OAC OAC OACICRO Recognizes rise in turbine load and reactor power with corresponding drop in Tavg with no operator input.

Dispatches personnel to look for steam leaks both in the inside and outside plant areas.

Places EHC Control in Manual or places the governor valves on Valve Position Limiter.

Implements AOI-38, Main Steam or Feedwater Line Leak if above step not performed.

~

Checks SIG PORVs closed.

Checks steam dump valves closed Checks reactor power less than or equal to 100%

LoopAT.

NIS power range monitors.

Ensures Tavg and Tref within 3°F.

Monitors leak less than 3% of required steam or FW flow.

Will give similar indications as a small steam leak. Rods are in manual.

REFERENCE window on Turbine Control Panel counts up at a slow rate If Turbine Trie directed, go to page

26.

This will stop the load rise.

Will not be able to be determined since no steam is being lost.

~

Scenario 1 Revision 0 Page 25 of 33 OP Test No:

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3 Event

==

Description:==

Failure of EHC Auto Control Monitors CST volume greater than 200,000 gallons.

Ensures S/G levels on program.

Checks containment conditions normal.

If Turbine Control problem not detected, directs manual turbine trip.

Temperature may sag below the minimum temperature for criticality of 555°F.

See next page.

Cue Console operator for MSLB. EVENT 6

Scenario 1 Revision 0 Page 26 of 33 OP Test No:

Scenario No.:

1 Event No.:

5 Page 3 of 3 us Alternate Path - AOI-17, Turbine Trip CRO CRO OAC CRO OAC CRO CRO CRO CREW Implements AOl-17, Section 3.2, and directs actions of the crew.

Ensures turbine trip with all stop valves closed.

Ensure steam dump or SIG PORV operation normal.

When Rx power less than 15%, then place rods in manual.

Announce turbine trip over PA system.

Reduce reactor power to within feedwater capabilities, and maintain zero startup rate:

Between 6 and 10% with MFW in service.

Less than 4% with AFW in service.

Ensure station service transferred:

6.9 KV Unit Boards RCPBoards Close extraction steam FCVs to # 1 and

2 feedwater heaters.

Ensure MFW mode switch, 1-HS-3-45, in Forward Flush.

Recognizes lowering Tavg, Pzr Level and Pressure and feedwaterlsteam flow mismatch.

Cue Console Operator for MSLB. EVENT6 Crew may trip reactor at any point while in AOI-17.

Will require manual rod insertion due to l-PT 73 failure.

Scenario 1 Revision 0 Page 27 of 33 CRO CRO CRO OP Test No:

Scenario No.:

1 Event No.:

6 Page -

1 of 4

Ensures turbine trip.

Ensures shutdown boards energized.

Identifies that 1 B-B AFWP failed to start, informs crew, and manually starts.

Ensures MFW isolation:

MFW isolation valves closed MFW bypass isolations closed MFW reg and bypass reg valves closed MFWPT A and B tripped Standby MFWP stopped Cond demin pumps tripped Cond booster pumps tripped Event Main Steam Line Break

==

Description:==

US Directs reactor trip and closure of MSIVs. May direct manual Safety Injection.

Initiates manual reactor trip/ safety injection.

Closes MSlVs as directed by US.

Informs crew that # 3 S/G MSlV failed to close.

OAC CRO Dispatch of personnel to locally close MSlV should be done after first 4 steps of E-0 completed.

US Implements E-0 and directs crew actions.

Performs immediate actions of E-0.

CREW OAC I Ensures reactor trip and safety injection. I

Scenario 1 Revision 0 Page 28 of 33 OP Test No:

Scenario No.:

1 Event No.:

6 Page -

2 of 4

Event Main Steam Line Break

==

Description:==

CRO OAC CRO us OAC OAC OAC CRO us CREW CRO Evaluate SI support systems using E-0, Appendix A.

Monitors ECCS operation by checking pumps running and alignments.

checking Phase A, and CVI on status panels.

Checks cntmt pressure < 2.8 psig.

Ensures cntmt isolations by Ensure secondary heat sink available.

AFW flow.

SG level.

May direct isolation of AFW flow to #3 SIG on completion of Step 12 E-0.

Determines RCS temperature dropping below 557°F.

Checks steam dumps closed Check steam dump controls in OFF.

Checks excess letdown valves closed (1-FCV-62-54 and 1 -FCV-62-55).

Check PZR safety valves, PORVs and PZR spray valves closed.

Determines #3 S/G pressure dropping in uncontrolled manner.

Transitions to E-2 and directs crew actions.

Commences monitoring of Status Trees Verifies MSlVs and bypasses closed.

Verifies steam dump controls are OFF.

AUOs should have been dispatched earlier to close

Scenario 1 Revision 0 Page 29 of 33 3

OP Test No:

Scenario No.:

1 Event No.:

6 Page 3 of -

4 Event Main Steam Line Break

==

Description:==

. I Position CRO CREW CRO CRO us us OAC us CRO CRO Verifies at least 1 intact S/G available.

I Determines # 3 S/G as the faulted SIG. I Isolates # 3 S/G:

Isolates AFW to # 3 S/G.

Ensures MFW isolated to # 3 S/G.

Ensures # 3 SIG PORV closed.

Ensures # 3 S/G Blowdown isolated.

Ensures TD AFW supplied from intact S/G.

Monitors CST level >200,000 gallons.

Critical Step Directs CRO to control RCS temp stable with intact S/G PORV operation when faulted SIG is blown down.

Transitions to E-1 and directs crew actions.

Checks RCPs off if RCS pressure c 1500 psig.

Refers to EPIP-1 or notifies the SM.

I Checks S/G pressure is controlled and Faulted SG has completed, or will soon, complete blowdown.

Maintain intact SG NR levels.

Monitors levels > 10%[25%ADV]

Control level between 10% and 50%

[25% and 50% ADV].

Scenario 1 Revision 0 Page 30 of 33 OP Test No:

Scenario No.:

1 Event No.:

6 Page 4 of -

4 Event Main Steam Line Break

==

Description:==

Position CRO CRO OAC OAC IACICRC us OAC OAC OAC Checks secondary side radiation normal.

May contact Chem Lab and RADCON since MSlVs closed.

Ensures cntmt hydrogen analyzers in service to monitor concentration.

Checks PZR PORVs closed and at least one block valve open.

Determines cntmt spray never started.

Ensures pocket sump pumps stopped (1-HS-77-410 & 1-HS-77-411).

Determines that SI can be terminated and transitions to ES-1.1 and directs crew actions.

Resets SI, and Phase A.

Ensures Cntmt Air in service.

Stops one running charging pump.

I Determines RCS pressure stable or rising.

TERMINATE THE EXERCISE

APPENDIX B SHIFT TURNOVER CHECKLIST Page 1 of 3 SHIFT TURNOVER CHECKLIST page -

of -

0 SM USlMCR Unit -

0 uo Unit -

Off-going - Name 0

AUO Station 0

STA (STA Function)

On-coming - Name Part 1 - Completed by off-going shiftlReviewed by on-coming shift Cb=1410ppm Abnormal equipment lineuplconditions:

112.12 MDAFW Pump i s tapped for oil leak repsir of motor outer bemng.

LCO 3.7.5 Condition B for past 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

_ _ _ ~

Medium Risk associated with equipment out of service.

Slflest in progresslplanned (including need for new brief)

See schedule Major ActivitiedProcedures in progress/planned Rx power at 43% ready for I B MFW Pump to be plxed in service. AI is out or target band on [he positive.

side requiring dilution to Correct Volutneer Lond Coordin~or request lo3d be brought 10 100% as soon 3s practir31 due to high load demand.

Radiological changes in plant during shift:

None Part 2 - Performed by on-coming shift Review the following programs for changes since last shift turnover:

0 Standing Orders 0 LCO(s) in actions (N/A for AUOs) 0 Immediate required reading 0

TACF (NIA for AUOs A review of the Operating Log since last held shift or 3 days, whichever is less (N/A for AUOs)

A review of the Rounds sheets/Abnormal readings (AUOs only)

Part 3 - Performed by both off-going and on-coming shift A walkdown of the MCR control boards (N/A for AUOs)

Relief Time:

Relief Date:

TVA 40741 [03-2001]

Page 1 of 1 OPDP-1-1 [03-14-2001]

APPENDIX B SHIFT TURNOVER CHECKLIST Page 2 of 3 SHIFT TURNOVER CHECKLIST page __ of -

0 SM 0

USlMCR Unit -

3 uo Unit Off-going - Name 0

AUO Station 0

STA (STA Function)

On-coming - Name

'art 1 - Completed by off-going shiWAeviewed by on-coming shift:

C ~ 1 4 1 0 ppm Abnormal equipment lineup/conditions:

]A-A hlDAkW Pump is lagged for oil leak rcpair of motor outer bearing.

~~~

Slnest in progress/planned (including need for new brief) 1-SI-0-2 Other Sls will be performed by extra operators called in for plant startup.

Major Activities/Procedures in progress/planned:

Rx power at 43% ready for 1B MFW Pump to be placed in service. Hot Startup of pump is appropriate. AI is.

out of target band on the positive side.

Rx Engineering has requested a dilution to be started as soon as possible to address the AI concern.

Radiological changes in plant during shift:

'art 2. Performed by on-coming shift 0

0 Review the following programs for changes since last shift turnover:

Standing Orders 0 LCO(s) in actions (N/A for AUOs) 0 Immediate required reading 0

TACF (N/A for AUOs A review of the Operating Log since last held shift or 3 days, whichever is less (N/A for AUOs)

A review of the Rounds sheets/Abnormal readings (AUOS only)

'art 3 ~ Performed by both off-going and on-coming shift A walkdown of the MCR control boards (N/A for AUOs)

Relief Time:

Relief Date:

N A 40741 [03-20011 Page 1 of 1 OPDP-1-1 [03-14-2001]

APPENDIX B Page 3 of 3 REACTIVITY MANAGEMENT BRIEF BOL

1. Our method of maintaining the 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months average reactor power at or below 3459 MWt will be:

3 Maintain the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months average reactor power at or below 3459 MWt.

Adjustments to the main turbine governor valve position by utilizing the governor valve position limiter (VPL).

3 Maintain reactor coolant temperature 587.5"F - 588.5"F via RCS boron adjustments in appropriate size batches of water or acid, as needed.

The Boron Worth will remain at - 5.7 - 6.0 pcndppm until -8000 MWD/MTU Reference NuPOP Figure 6-21. Use TI-59 or REACTINW as required. (Preferred Method) 3 Control rod motion is acceptable (maintaining 5% target band).

In lieu of many small boron adjustments rods may be used for fine control; however, maintain rods above 212 steps. (Alternate method)

2. Our method of maintaining Delta I within the target band will be:

Moving control rods in or out in 34 or 1 step increments.

Nominal rod step @ 220 is worth:

Nominal rod step @ 212 is worth:

(Reference NuPOP Figures 6-24 and 25)

The Boron Worth will remain at - 5.7 - 6.0 pcmlppm until -8000 MWDRYITU reference

- 1.5 - 2.5 pcm.

- 3.0 - 6.5 pcm.

Our current full power Delta I target band is

(-7.4%) - (+2.6%).

Our present Delta I value is

+7

. (Fill in the blank)

Control rods are i AUTO MANUAL. (Circle one) -

3. Peer checking by another licensed person prior to performing reactivity manipulations is required.

4. In the event of a runback initiation without rod motion the boration requirement is approximately

/% Bower runback.

5. Projected reactivity effect is negative / positive none (circle one) if the idle CCP is placed in service.

a (Based on RCS CB being 1410 ppm when the idle CCP pump was last run.

6. Additional reactivity management issues:

Power ascension in progress.

~

Appendix D Scenario Outline Form ES-D-1 Event No.

1 2

3 4

(N)ormal, Facility:

WATTS BAR Scenario No.:

2 Op-Test No.:

Malf.

No.

(RX05A (CV52)

(ED12 C)

(R)eactivity,

1) Examiners:

Operators:

Initial Conditions:

Rx Power 98%

Turnover:

16 MDAFW out of service.

Maintenance has completed work on Turbine Governor Valve #2, Perform portion of TRI 47-3 for Post Maintenance Test of Turbine Governor Valve #2 Event Type*

N (BOP, SRO)

I (RO, SRO)

I - (RO)

Event Description Perform PMT on Turbine Governor Valve #2 (Normal for BOP).

Pressurizer Level Transmitter LT-68-339 Fails low Annunciators for Pzr Level HilLo and Pzr Level Lo-Heaters OFF and Letdown Closed illuminate. RO should determine an instrument failure and go to AOI-20, Malfunction of the Pzr Level Control System, Manual control of charging should be taken (normal charging may be isolated due to loss of letdown), the channel transferred and letdown returned to service.

Tech Spec 3.3.1 Condition X Fail Letdown Pressure Control Transmitter PT-62-81 High Annunciator for Letdown Pressure High Or High Letdown Flow illuminates. RO should recognize that instrument has failed high anc that PCV-62-81 is fully open due to this failure. RO should establish manual control of valve.

Loss of 125VDC Vital Battery Board 111 This event causes several annunciators, removes control power from the TDAFW pump. It starts all 4 EDG's. A number of Tech Specs will apply both electrical and AFW. The BOP to perform App C of AOI-21.03 to realign ventilation systems. The TDAFW control power transfer per AOI-21.03 will fail (preparatory to main transient) Also the MDAFW pump 1A-A will fail to auto start when initiated, and MCE pump switch will not work, but can be started locally.

(I)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1

acility:

WATTS BAR Scenario No.:

2 Op-Test No.:

Event No.

5 6

7 8

9 POST MT Malf.

No. -

FW67 C

(FW18)

(FW03 A)

B)

(FW05 (RPO1

6)

(FW06)

Event Description 1B EDG Failure due to Low Lube Oil Pressure.

possible). Lost of second pump will ensure need for load reduction.

After load reduction and Operators are borating, then role play FWP At this point there should be no feedwater available and drive the crew into FR-H.1. If Operator is dispatched to 1A MDAFW pump breaker, finds no targets or problems. If directed to close breaker locally, the pump will start. If action was taken to initiate repair the DC Transfer switch, allow repair to be completed, then transfer

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Scenario 2 Revision 0 Page 1 of 36 TITLE: Rods Fail to Move on Demand, Failure of Auto Reactor Trip, Total Loss of Feedwater REVISION: 0 DATE: 1 1 /20/02 PROGRAM: WBN Operator Training - Initial License PREPARED BY:

I (Operations Instructor)

(Date)

VALIDATION BY:

I (Operations Instructor)

(Date)

I t '

REVIEWED B Y (Lead Operations Instructor)

(Date)

APPROVED B Y I

(Operations Training Manager)

(Date)

CONCURRED:

I (Operations Superintendent)

(Date)

Scenario 2 Revision 0 Page 2 of 36 REVISION NUMBER 0

Nuclear Training RevisionlUsage Log DESCRIPTION OF REVISION nitial Issue DATE 1 1 /20/02 ALL BY

PROGRAM:

WBN Operator Training Scenario 2 Revision 0 Page 3 of 36

SUBJECT:

Simulator Examination Guide TITLE:

Rods Fail to Move on Demand, Failure of Auto Reactor Trip, Total Loss of Feedwater LENGTH:

-1.5 Hour

REFERENCES:

Please Dont Delete this line (This is hidden text)

SCENARIO OBJECTIVES:

1. Evaluate the candidates in their use of Abnormal Operating Instructions to address various failures or transients.

2. Evaluate the candidates use of E-0, Reactor Trip or Safety Injection, to respond to manual reactor trip and subsequent transition to ES-0.1, Reactor Trip Response.

3. Evaluate the candidates in their transition to FR-H.1, Loss of Secondary Heat Sink on low S1G levels after transition from ES-0.1.

I

Scenario 2 Revision 0 Page 4 of 36 SCENARIO

SUMMARY

Initial conditions:

Reactor is operating at 98% RTP, Cb = 947 ppm.

The Train Week is B. Channel Week II or IV ok.

MDAFW pump 1 B-B is out of service for maintenance.

Maintenance has completed work on Turbine Governor Valve # 2.

Portions of 1-TRI-47-3, Main Turbine Steam Inlet Valve Testing, need to be performed for Post Maintenance Testing.

Scenario Events and Sequence:

Set up simulator to IC-145

1.

2.

3.

4.

5.

6.

7.

a.

9.

10.

11.

Perform PMT on Turbine Governor Valve # 2 per 1-TRI-47-3.

Pressurizer Level Transmitter, 1 -LT-68-339, fails low requiring isolation of charging flow, defeat of channel, and re-establishment of charging and letdown.

Letdown Pressure Control Transmitter, 1 -PT-62-81, fails high requiring manual valve manipulation to control letdown pressure. 1 -Pl-62-81 indicates 600 psig with no other available control room indication.

Loss of 125VDC Vital Battery Board 111. This removes control power from the Turbine Driven AFW Pump requiring a Tech Spec shutdown on loss of two trains.

1 B DIG low oil pressure alarm annunciates requiring emergency stop of the D/G.

Intermediate Feedwater Heater String C isolates requiring local response to determine cause.

1A Main Feedwater Pump vibration high. Alarm only with vibration at 4 Mils. Vibration worsens requiring trip of pump.

3 Heater Drain Tank 1A trips on instantaneous over current (IOC).

Pump 1B trips on timed overcurrent five minutes after pump 1A requiring manual load reduction and/or turbine runback.

Rods fail to move on demand in auto and manual requiring boration to lower power to match turbine load. With two heater drain tank pumps tripped and the 1A MFWP tripped, S/G levels will drop requiring manual reactor trip.

Failure of Auto Reactor Trips ensures manual action to trip the reactor.

Entry into FR-H.1, Loss of Secondary Heat Sink, entry due to AFW flow being unavailable.

Scenario 2 Revision 0 Page 5 of 36 EVENT 1 - Perform PMT on Turbine Governor Valve # 2 per 1-TRI-47-3 Turnover has reactor power at 98% RTP with the # 4 Governor Valve at the mostly closed position for performance of 1-TRI-47-3 on the # 2 Governor Valve.

Malfunctions required: None Objectives:

Evaluates the candidates ability in the use of 1-TRI-47-3, Main Turbine Steam Inlet Valve Testing.

Success Path:

Candidates verify # 2 governor valve operates freely with no evidence of interference with valve stem movement. Valve will be cycled from full open to full closed and returned to the fully open position to verify operability.

EVENT 2 - Pressurizer Level Transmitter, 1-LT-68-339, Fails Low 1 -LT-68-339 fails low resulting in letdown isolation and subsequent manual isolation of charging flow. Manual control of charging valve controller, 1 -HIC 93A, is required. Failed channel must be defeated and charging and letdown restored. Operators should respond using AOI-20.

Malfunctions required: 1 RX05AO Objectives:

e Evaluates the candidates use of AOI-20 for failure of 1 -LT-68-339 low.

Evaluates candidates ability to properly diagnose control board indications to determine event in progress.

i Success Path:

e Crew recognizes conditions for entry and implements AOI-20 in response to PZR level transmitter, 1 -LT-68-339 (channel I) failing low.

e Manual control of PZR level established.

Stabilizes the plant and restore PZR heaters, charging and letdown to service. Returns charging flow control valve to auto position.

Determines the correct conditions to enter for the appropriate LCOs.

Scenario 2 Revision 0 Page 6 of 36 EVENT 3 - Letdown Pressure Control Transmitter, 1-PT-62-81 Fails Hiqh 1-PT-62-81 fails high causing Letdown Pressure Control Valve, 1-PCV-62-81, to come full open resulting in low letdown pressure. Flashing may occur in the letdown line with possible relief valve opening to the PRT. Manual valve control must be taken to close valve until proper letdown pressure restored.

Complicated by the lack of MCR indication to restore proper pressure setpoint of 320 psig (indication failed at 600 psig).

Malfunctions required: 1 CV52 100 Objectives:

e Evaluates the candidates ability to recognize low letdown pressure conditions.

Evaluates the candidates ability to take manual control of the Letdown Pressure Control Valve and restore normal pressure conditions using alternate means of indication.

Success Path:

e Places 1-PIC-62-81A in manual and close the valve to restore normal letdown pressure control of -320 psig.

e Dispatches personnel to verify correct valve response to MCR input.

Scenario 2 Revision 0 Page 7 of 36 EVENT 4 - Loss of 125VDC Vital Batterv Board 111 Several annunciators will alarm and control power will be removed from the TDAFW Pump. All D/Gs will auto start. Tech Specs will apply to the board loss and to the loss of the second train of AFW. Local transfer of control power to the TDAFW Pump will fail resulting in a Tech Spec driven plant shutdown.

Malfunctions required: 1 ED12C 0 bjectives:

Evaluate the candidates response to a loss of 125VDC Vital Battery Bd 111 and implementation of AOI-21.03.

Evaluate the candidates ability to evaluate Technical Specifications and determine the need to enter the appropriate conditions and commence preparations for plant shutdown.

Success Path:

Recognize entry conditions and implement AOI-21.03 in response to 125VDC Vital Battery Board 111.

Determine the correct conditions to enter for the appropriate LCOs recognizing that two AFW Trains are inop and requires shutdown to Mode 3 and then Mode 4.

EVENT 4A - 1 B Diesel Generator Low Oil Pressure 1 B D/G Low Oil Pressure Alarm annunciates on 0-M-26 after D/Gs are all started five minutes after loss of the 125VDC Vital Battery Bd 111. This will require D/G 1 B to be emergency stopped since the D/Gs did not receive a valid emergency start signal.

Malfunctions required:

AN:OV:07c071 alarm Objectives:

Evaluate the candidates response to a low oil pressure alarm on a running diesel generator per ARI.

Evaluate the candidates ability to evaluate Technical Specifications and determine the need to enter the appropriate conditions.

Success Path:

Emergency stop Diesel Generator 1 B per ARI.

Determines the correct conditions to enter for the appropriate LCOs.

Scenario 2 Revision 0 Page 8 of 36 EVENT 5 - Intermediate Strinq Heaters C (Heaters 2, 3. and 4 isolate)

High level alarm will result on # 1C Feedwater heater due to bypassing flow to condenser due to intermediate string isolation. Reactor thermal power will rise but should not be a problem due to power drop to 98% for governor valve testing.

Malfunctions required: 1 FW 67C Objectives:

Evaluate the candidates response to an intermediate string of heaters isolating.

Evaluate the candidates ability to evaluate the associated ARI to determine required actions.

Success Path:

Crew responds to alarm per appropriate ARI and dispatches personnel locally to determine cause.

Monitors reactor thermal power to ensure RTP of 3459 MWt not exceeded.

EVENT 6 - 1A Main Feedwater Pump Vibration Hiclh This malfunction will bring in 1A Main Feedwater Pump Vibration High Alarm and will indicate just above alarm setpoint of 4 mils requiring monitoring but not shutdown of pump. After event 7 with inability to drive rods and boration in progress 1A MFW Pump vibration, through role play, will worsen requiring 1A MFWPT to be tripped.

Malfunctions required: 1 FW18A set to 16%

Objectives:

Evaluates the candidates ability to recognize 1A MFW Turbine high Evaluates the candidates ability to determine that turbine vibration is in a range not requiring shutdown but closer monitoring.

I 1

vibration conditions.

Success Path:

Responds to alarm per appropriate ARI and maintains 1A MFWP in service with closer monitoring of turbine vibration. May vary pump speed to lower vibration.

Remove pump from service on role play of excessive vibration with recommendation to trip pump.

Scenario 2 Revision 0 Page 9 of 36 EVENT 7 - I A and 1 B # 3 Heater Drain Tank Pumps Trip Trip of 1A # 3 Heater Drain Tank Pump (HDTP) will require a manual turbine load reduction to 900 MWe or an automatic turbine runback will occur. Trip of the 1 B # 3 HDTP five minutes later will ensure a load reduction with lower capacity to keep feedwater flow and steam flow equal. Boration will be required.

Malfunctions required: 2 FW03A and FW03B Objectives:

Evaluate the candidates ability to recognize trip of # 3 Heater Drain Tank Pumps 1A and 1 B.

Evaluate the candidates ability to assess board indications and execute AOI-37, Turbine Runback Response.

Success Path:

Recognize entry conditions and implementation of AOI-37 to respond to turbine runback event.

Recognize lowering S/G levels and need of manual reactor trip.

EVENT 8 - Rods Fail To Move On Demand Turbine load will be dropped to 5 900 MWe due to # 3 HDT pump problem but rods will not move in auto or manual to match Tavg to Tref. Lowering level in all S/Gs will result which should drive the crew to initiate a manual reactor trip.

Malfunctions required: 1 0

RD08 Rods fail to move on demand.

0 bjectives:

Evaluate candidates ability to monitor S/G levels and initiate manual Reactor trip due to approaching low levels in the S/Gs. Auto reactor trip failure will prevent automatic trip.

Success Path:

Manually trip the reactor from 1-M-4 or 1-M-6 MCR Handswitches.

Crew implements E-0 and then transitions to ES-0.1, Reactor Trip Response.

Scenario 2 Revision 0 Page 10 of 36 EVENT 9 - FR-H.1, Loss Of Secondary Heat Sink Aux Feedwater flow is not available and a transition to FR-H.l will be made when no S/G is > 10% Narrow Range level. The Standby Main Feedwater Pump will fail to start and the 1A MDAFW Pump will not start from the MCR but can be started locally.

Malfunctions required: 2 FW06 Standby Main Feeedwater Pump Failure ZDIHW3118A STOP Prevents MCR start of 1A MDAFWP Objectives:

Evaluate the candidates ability to recognize a loss of secondary heat sink and implements FR-H.l.

Evaluate the candidates ability to restore feedwater flow from available sources or initiate bleed and feed.

Success Path:

Crew diagnoses loss of secondary heat sink and implements FR-H.l.

Crew restores feed flow to the S/Gs and/or initiates bleed and feed as required by three S/G Wide Range levels 534%.

Scenario 2 Revision 0 Page 11 of 36 0

O 0

0 0

Sim Setup 0

0 0

0 CONSOLE OPERATORS INSTRUCTIONS rst 145, switch check, select RUN Turn audible simulator fault alarm to "off (down position)

Place "B" Train Week" sign on control board Reduce power to 98%

for gov valve testing Place 1 HS-3-128A in PTL and tag 1 HS 128A and 1-HS-3-359 with HO NOTE: IC 145 has been setup for this scenario. If unavailable, rst 50 and continue rest of setup.

ior zlohs3128a[l] off ior zdihs3359 ior zlohs3359[1] off ior zIohs3359[2] off ior zdihs3118a stop imf S108G imf fw06 imf rpOl b 98 % RTP, BOL, cb=947 ppm.

Prevents unnecessarily alerting crew of a simulator problem that may not effect simulator dynamics.

Entrance side panel. Channel week II or IV OK.

Lowers Governor Valve # 4 for testing of Governor Valve # 2.

Simulates 1 B-B MDAFWP 00s for maintenance.

1-HS-3128A green light off 1B MDAFWP.

1-HS-3-359 16 MDAFWP Recirc tagged.

1-HS-3-359 green light off.

1 -HS-3-359 red light off.

MCR Handswitch will not start 1A MDAFW Pump.

Failure of Auto SI and Blackout start of 1A MDAFW Pump.

Trip-out of the Standby MFW Pump on start.

Automatic reactor trip signal failure.

Scenario 2 Revision 0 Page 12 of 36 CONSOLE OPERATORS INSTRUCTIONS (Continued) 0 0

1 -LT-339, Pzr Level Transmitter, fails I low.

irnf cv52 (e3) 600 1-PT-62-81 fails high (600 psig).

irnf edl2c (e4)

Loss of 125VDC Vital Battery Bd 111.

ior an:ov:07c071 (e4) 5: on DIG 1 B-B low oil pressure alarm in 5 minutes after Battery Bd 111 loss.

irnf fw67c (e5)

I 0 1-LS-6-66D failure causing Intermediate Heater String C isolation (Heaters 2C, 3C, & 4C).

0 0

1 irnf fwl8a (e6) 16 I 1A MFWPT vibration at 4 mils.

I1 0 fw03a (e7) fw03b (e7) 5:

irnf rd08 (e8) 1A # 3 HDTP trip.

1B # 3 HDTP trip five minutes after the 1A pump trip.

Rods fail to move on demand in auto or manual positions.

i

Scenario 2 Revision 0 Page 13 of 36

.:a; ELAPSED TIME..

After crew assumes shift:

CONSOLE OPER When directed by the evaluator for EVENT 2 When directed by the evaluator for I

EVENT 3 When directed by the evaluator for EVENT 4 t

(Event 4 continued on next page) L TORS INSTRI (Continued) mf itrigger2 Use ETM Screen) mf itrigger3 Select PTP on CV1 foi

~opup on 1-PT-62-81 C o view actual press) mf itrigger4 ZTIONS 3OLE PLAY: As TB AUO, when

.equested, report the #2 Governor Jalve operates freely with no signs of

)inding when valve is stroked.

I -LT-68-339, Pzr Level Transmitter

'ails low.

?OLE PLAY: As Work Control, when Zontacted, inform the crew a work Dackage will be initiated for repairs.

1-PT-62-81, Letdown Pressure Contro Transmitter fails high.

ROLE PLAY: As AB AUO, when

?equested, report that the valve is

,esponding to control input. If AUO sent to Aux Control Room, report actual letdown pressure.

ROLE PLAY: As Work Control, when contacted, inform the crew the pressure transmitter will be added to the work scope and package initiated.

Loss of 125VDC Vital Battery Ill.

ROLE PLAY As CB AUO, when requested, report the board has no voltage but no apparent reason for the loss.

ROLE PLAY: As AB AUO, when requested to transfer control power to the TDAFW Pump, report 1-XSW DC will not move to the Emergency position.

4fter 5 minute time ielay from 125VDC lital Battery loss Nhen requested by he evaluator for WENT 5 Nhen requested by he evaluator for WENT 6 Scenario 2 Revision 0 Page 14 of 36 CONSOLE OPERATORS INSTRUCTIONS (Continued) or an:ov:07c071 (e4) mf itrigger5 mf itrigger6

,.,j'., ' e !

.(.,,,

ROLE PLAY: As Maintenance, if requested, and after an appropriate time delay, report the main battery fuse has blown and requires replacing.

Window 205 D/G LUBE OIL PRESS LO alarm ROLE PLAY: As Outside AUO, report D/G 1 B has an oil pressure of 12 psig on the 1 B1 engine. 1 B2 engine oil pressure is normal.

C Intermediate String Heaters isolate on faulty level switch.

ROLE PLAY: As TB AUO, when requested, report the levels in the # 2C &

4C Heaters are low. Cannot see reason for isolation.

ROLE PLAY: As Mainwork Control, if requested, inform the crew that 1-LS 66D shows signs of overheating and needs replacing.

Window 54D - PUMP VIBRATION HI alarm. Steady around 4.1 mils - just above alarm setpoint.

ROLE PLAY: As AUO, when requested, report some difference in vibration from beginning of shift. Request vibration personnel be notified to confirm vibration problem.

ROLE PLAY: When cued by the examiner, report to the crew as AUO that vibration is rising rapidly on 1A MFP and maintenance insist on trip of pump before it self destructs. Bad rub sounds coming from pump.

When requested by the evaluator for EVENT 7 Triqqer 8 required when rods step in -

10 steps.

After rods run in -

10 steps insert EVENT 8 On evaluator cue after bleed and feed established Scenario 2 Revision 0 Page 15 of 36 CONSOLE OPERATORS INSTRUCTIONS (Continued) imf itrigger7 imf itrigger8 dor zdihs3118a mrf edr68 aux 1A # 3 Heater Drain Tank Pump trips and 1 B # 3 Heater Drain Tank Pump trips 5 minutes after 1A Pump trip.

ROLE PLAY: As AUO, when requested, report 1A pump tripped on IOC and the 1B pump tripped on timed overcurrent.

~

Rods fail to move on demand.

ROLE PLAY: As CB AUO, if requested, report urgent failure light in logic cabinet illuminated.

ROLE PLAY: As CB AUO, report that the breaker for the 1A MD AFW Pump has been swapped out and is available for service.

As an alternative, transfer the 1 -XSW-46-DC to alternate power and inform the crew the TDAFWP is available.

i

Scenario 2 Revision 0 Page 16 of 36 APPENDIX A INFORMATION TO EVALUATORS

1. Assign Crew Positions: Assign positions based on evaluation requirements for personnel.

US - Unit Supervisor OAC - Operator at Controls CRO - Control Room Operator

2. Review the Shift Turnover Checklist with the operating crew. Provide the US with a copy of Appendix B, Shift Briefing Information.

3. Allow the crew to familiarize themselves with current control panel condition (up to 10 minutes).

4. Ensure recorders are inking and recording and ICs is active and updating.

Note any deficiencies during shift briefing.

5. If not previously done, review any major differences between plant and simulator.

6. Review CONSOLE OPERATORS INSTRUCTON for INITIATING CUES.

Scenario 2 Revision 0 Page 17 of 36 i

OP Test No:

Scenario No.:

2 Event No.:

1 Page 1

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2 Event

==

Description:==

Perform PMT on Turbine Governor Valve # 2 Walks down control boards.

Reviews Sections 3.0, and 4.0 before Performance Section 6.0 of 1-TRI-47-3 is initiated.

Establishes communications between the MCR and turbine front standard.

I Records generator load and ensures load is not 505-700 MW.

I Ensures 1-XX-47-1000, EHC Control, is in OPER AUTO.

Ensures 1-XX-47-1000, EHC Control, is in IMP IN.

Records Valve Position Limit setting.

I Sets Valve Position Limit to 2 100%.

Position person locally at valve to observe smooth valve operation.

Push and hold GV Close pushbutton for 1 -FCV-1-65, Main Steam Governor Valve NO. 2 until the valve is fully closed.

Verify the following:

GV Open light is not lit.

GV Closed light is lit.

Valve position Indicator Meter for GV being tested indicates 0%.

Scenario 2 Revision 0 Page 18 of 36 OP Test No: -

Scenario No.:

2 Event No.:

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Event

==

Description:==

Perform PMT on Turbine Governor Valve # 2 Push and hold GV Open pushbutton for 1 -FCV-1-65, Main Steam governor Valve No. 2 until open and close pushbutton lights are not lit.

Check for smooth valve operation by local observation. Annotates and reports unexpected valve response.

Returns Valve Position Limit to it's as-found setting in step 141.

Reviews Section 5.0 for satisfactory completion of acceptance criteria.

Directs crew to raise power to 100%.

Not a step in the TRI but is expected at some point before or after valve stroke.

Cue Console Operator for 1 -LT-68-339 failure low. EVENT2

Scenario 2 Revision 0 Page 19 of 36 Recognize PZR level channel I failure and informs crew.

Channel I level indication fails low.

PZR level alarms:

PZR LEVEL HVLO [92-A]

PZR LEVEL LO-HTRS OFF &

LETDOWN CLOSED [92-C]

Recognizes letdown isolation and should isolate charging. (1-HS-62-90A & 1-HS-62-91A).

Implement AOI-20 and directs the actions of the crew.

Checks PZR level program signal NORMAL, recorder 1-LR-68-339. (green Pen)

Expected response to isolate charging if inventory problem does not exist.

Determines that 1 -XS-68-339E is selected to FAILED channel.

I Determines that channel I, 1-LT-68-339 failure is low.

Places 1-HIC-62-93A in Manual, and closes 1 -FCV-62-89.

I Maintains RCP seal flow between 8 and 13 gpm with 1 -HIC-62-93A.

Selects operable channel for controlling channel using 1-XS-68-339E (selects LI-Ensure operable channel selected for recording with 1-XS-68-339B. (Channel 339 not selected.)68-335 B320).

t 1

Scenario 2 Revision 0 Page 20 of 36 OP Test No:

Scenario No.:

2 Event No.:

2 Page 2

of 3

Event

==

Description:==

Controlling PZR level transmitter 1 -LT-68-339 fails low.

OAC Establishes normal charging and etdown per attachment 1 of AOI-20 Closes 1 -FCV-62-89.

Ensures Charging Pump running Openslcheck open 1 -FCV-62-90 and 1 -FCV-62-91.

Ensures 1-FCV-62-85 or -86 open Adjusts 1-FCV-62-93 to maintain 8-13 gpm seal flow.

Ensure letdown isolation valves and 1 -FCV-62-77.

Place Letdown Hx temperature control valve (1-HIC-62-78A) in MANUAL at 25% open.

Places letdown pressure control (1-HIC-62-81A) in MANUAL at 25%

open.

Establish charging flow 75 gpm or greater & 8-13 gpm seal injection flow to each RCP.

Establish letdown by opening letdown orifices as needed.

1-FCV-62-73 or 74, or 72 or 76.

Adjust letdown pressure (l-HIC 81 A) to -32Opsig and place in AUTO.

Place l-HIC-62-78A, letdown hx outlet temp TCV-70-192 cntl, in AUTO.

Returns PZR level to program Return l-HIC-62-93A, charging flow pzr level control, to AUTO.

OPEN 1 -FCV-62-69, 1-FCV-62-70

Scenario 2 Revision 0 Page 21 of 36 OP Test No:

Scenario No.:

2 Event No.:

2 Page 3

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3 Event

==

Description:==

Controlling PZR level transmitter 1 -LT-68-339 fails low.

OAC us us

,~~~

~.. :

\\:,.s: :... :."

~

'..: Expected ActionsIBehavior,'.. '

3estores pzr level control to normal:

Controls charging and letdown to return pzr level to program.

Ensures pzr control heater bank D red light lit.

Momentarily places pzr backup heater bank C HS to off.

Checks pzr program level normal on 1-LR-68-339 (green pen).

Returns charging valve controller, 1-HIC-62-93A to auto.

Votifies work control to remove failed channel from service.

Evaluates Tech Specs and enters LCOs 3.3.1.9 Condition X and 3.3.3 Condition A.

Will probably restore level to program before placing in auto.

Cue Console Operator for letdown pressure transmitter, 1 -PT-62-81 failure high. EVENT 3

Scenario 2 Revision 0 Page 22 of 36 OP Test No:

Scenario No.:

2 Event No.:

3 Page 1

of 2

Event

==

Description:==

Letdown Pressure Control Transmitter, 1 -PT-62-81 fails high OAC USIOAC Recognizes high pressure indication on letdown and informs crew.

Letdown pressure transmitter, 1-Letdown alarm:

PT-62-81 failed high.

LO PRESS LTDN FLOW/PRESS HI [l 1 OB]

Refers to Annunciator Response Instruction and considers following corrective actions:

Check letdown flow, 1-Fl-62-82, and letdown pressure, 1-PI-62-81 and determines I-PI-62-81 indicating top of scale at 600 psig.

maintaining 320 to 350 psig on 1-PI-62-81 and determines press indicating 600 psig and 1-HIC 81A indicating valve in the full open position.

Ensure proper orifices are aligned to supply letdown flow 45 to 120 gpm.

If conditions persist, then consider taking normal charging and letdown out of service and placing excess letdown in service per SOI-62.01.

Ensure 1-PCV-62-81 is us I

ALTERNATE PATH Directs taking normal charging and letdown 00s if not properly diagnosed and placing excess letdown in per Sol.

Flow is normal @ -72 gpm.

Should determine valve can be controlled in manual with failed indication. No MCR indication will be available. If AUO sent locally, determination of proper valve operation can be confirmed.

Aux Control Room will have proper letdown press indication if utilized.

If valve is taken to the closed position causing relief valve to open and LD HI TEMP alarm, the crew may decide to remove from service.

Scenario 2 Revision 0 Page 23 of 36 OP Test No:

Scenario No.:

2 Event No.:

3 Page 2

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2 Event

==

Description:==

Letdown Pressure Control Transmitter, 1 -PT-62-81 fails high

I' i

Expected AcGonslBehavior ".l ':'

'" i.'

gotifies RADCON Shift Supervisor of ntent to place excess letdown in service.

Per Sol-62.01, Section 8.3, Establishing Excess Letdown:

Opens excess letdown CCS Valves 1-HS-70-143A and 1-HS-70-85A.

Checks 1-HS-62-59, CVCS Excess Letdown Divert Flow CNTL in NORM or DIV.

Opens 1 -HS-62-54A and 1 -HS 55A, excess letdown isolation valves.

Slowly opens l-HIC-62-56A, Exces LTDN Flow Control, to maintain Excess LD Hx outlet temperature below 206°F and Excess LD Hx CCS outlet temperature below 135 O F Alarm will annunciate if letdown temperature exceeds 200°F.

Cue Console Operator for loss of Vital Battery Bd 111. EVENT 4

Scenario 2 Revision 0 Page 24 of 36 OP Test No: -

Scenario No.:

2 Event No.:

4a, 4b Page 1 of -

2 Event

==

Description:==

Loss of 125VDC Vital Battery Board 111 CRO us CRO CRO USlCRO CRO Recognize failure of 125VDC Vital Battery Board 111 and informs crew.

Indications:

All D/Gs start but do not tie onto bd.

TDAFW Pump looses control power.

Loss of control pwr to various bds.

125 DC VITAL CHGWBATT 111 ABNORMAL [19-A]

125 DC VITAL BATT BD 111 ABNORMAL [19-B]

Alarms:

6.9 SD BD 1A-A FAILURE [12-B]

480V SD BD 1 A1 -A/lA2-A FAILURE/ABN [lo-D]

UV/OV/CONTROL PWR Implements AOI-21.03, LOSS of 125V DC Vital Battery BD 111 and directs crew actions.

Dispatches personnel to restore power using Sol-236.03, 125V DC Vital Battery Board 111.

Responds to alarm on D/G panel, DG LUBE OIL PRESS LO and dispatches AUO to investigate.

Directs emergency stop of D/G 1 B after AUO verifies oil pressure of 1 B1 engine to 12 psig.

Directs l-XSW-46-DC, TD AFWP DC Man Transfer Switch to emergency.

EVENT 4b EVENT 4b Transfer switch will not operate causing loss of two trains of AFW.

Scenario 2 Revision 0 Page 25 of 36 OP Test No:

Scenario No.:

2 Event No.:

4a,4b Page 2

of 2

Event

==

Description:==

Loss of 125VDC Vital Battery Board 111

,,. c.

i Position I -:. Expected ActionslBehavior.

I Ensures ERCW flow to all running 1 D/Gs.

US/CRO US/CRO Directs AUO to transfer Shutdown Board 125V DC control power to alternate supply using Appendix A.

Directs performance of Appendix C to place ventilation in service.

~~

US/CRO Directs Handswitch 43TL, in 6.9KV Logic Panel 2A-A, be placed in the Test Position.

USKRO Directs stopping D/Gs and placing in Standby.

us us Notifies Work Control to assist in determining cause of loss.

Refers to Tech Specs and enters LCO 3.8.4 Condition A and LCO 3.7.5 Condition C. Determines that a Tech Spec shutdown is require with entry into Mode 3 in six hours due to two trains AFW inop.

I 1

ommiit SATNNSA All D/Gs are running. 1 Cue Console Operator for C Heater String Isolation. EVENT 5 I

Scenario 2 Revision 0 Page 26 of 36 OP Test No:

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2 Event No.:

5 Page -

1 of -

Event

==

Description:==

Intermediate Heater String C Isolation CRO CRO CRO us us Recognizes C Heater String isolation by feedwater inlet, outlet and extraction valves closing and/or alarm.

Alarms:

HP HEATER C1 LEVEL HI/LO [38-AI HEATER A2 LEVEL HI/LO [36-B]

HEATER B2 LEVEL HVLO [37-B]

ARI should be addressed for the alarms listed above. (Alarm for heater string that isolated will NOT be in alarm)

Dispatches AUO to investigate actual levels and cause of isolation.

Addresses thermal power concern due to loss of efficiency from heater string isolation.

Notify Work Control to generate troubleshooting package.

These heater levels will go high due to more steam flow or drain path isolation.

Completion of heater string isolation should be directed per Sol-5 &

6.01.

Will not be able to diagnose problem withoui maintenance assistance.

RTP=3459 MWt Since power started at 98%, thermal limits may not be a concern.

Cue Console Operator for 1A MFWPT vibration high. EVENT6

Scenario 2 Revision 0 Page 27 of 36 OP Test No:

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2 Event No.:

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1 of 1

Event 1A Main Feedwater Pump Vibration High

==

Description:==

CRO us Responds to and announces alarms:

MFPT 1A ABNORMAL [5O-A]

PUMP VIBRATION HI [54-D]

Refers to Annunciator Response Instruction and considers following corrective actions:

Determines affected MFP from windows 50-A and 50-8.

Monitors affected MFP vibration on ICs or panel 1-L-792 [el 7551 and determines pump vibration just above alarm setpoint of 4 mils.

Check for sounds of vibration or rubbing.

Check lube oil temperature and adjust as necessary.

Reset local indicator at I-L-792.

Evaluate unit load and condition, and adjust MFPT speed to lower vibration if possible.

If vibration problem valid and greater than or equal to 5 mils, then evaluate unit load reduction to allow MFP removal from service.

Dispatches operator to:

Notifies Work Control to initiate corrective action.

Console Operator (AUO) will request maintenance verification of alarm.

Cue Console Operator for

3 HDT Pump trips.

EVENT 7

Scenario 2 Revision 0 Page 28 of 36 OP Test No:

Scenario No.:

2 Event No.: 7, 8, 9, MT Page -

1 of -

6 Event 1A and 1 B # 3 Heater Drain Tank Pumps Trip, Rods fail to move on

==

Description:==

demand, Failure of Auto Reactor Trip, Failure of 1 A MDAFW Pump to start from MCR, & Failure of the Stby MFWP to start d\\.,..:.:'

Position I.... 'Expected Actions/Behavior...

CRO Recognizes trip of 1A # 3 Heater Drain Tank Pump and informs crew.

us Alarms:

May direct turbine load reduction per AOI-39 in anticipation of turbine runback:

Push REFERENCE control lower

3 HD TANK BYP TO CONDENSER OPEN 130-E]

3 HD TANK LEVEL HI/LO [29E]

button to set desired load in SETTER display Set LOAD RATE as required.

Push GO button.

CRO Recognizes trip of 1 B # 3 Heater Drain Tank Pump and reduces turbine load to 900 MW (75%) with Valve Position Limiter.

Implements AOI-37, Section 3.2 and us I directs crew actions.

OAC I Ensures Tavg and Tref within 3°F.

OAC us Inform US that ROD URGENT FAILURE alarm is in and rods are not inserting.

Directs boration to compensate for failure of rods to move.

OAC I Establishes boration of RCS.

5 minutes after trip of the 1A Pump.

May have run back to 900 MW automatically.

EVENT 8 - Occurs after rods insert - 10 steps.

Approx. 37 gals per per

% power drop w/o rod motion per reactivity mgmt brief.

Scenario 2 Revision 0 Page 29 of 36 t I OP Test No: -

Scenario No.: 2 Event No.: 7, 8, 9, MT Page -

2 of 6 Event 1A and 1B # 3 Heater Drain Tank Pumps Trip, Rods fail to move on

==

Description:==

demand, Failure of Auto Reactor Trip, Failure of 1A MDAFW Pump to start from MCR, & Failure of the Stby MFWP to start CRO

-I USICRO USICRO L I CRO/OAC I

Monitors the following to determine if main turbine free of water induction:

0 Htr level alarms.

0 Turbine Vibration.

0 Turbine Metal Temperature (1-TR-47-2).

Ensure SIG levels returning to program Dispatches personnel to determine cause of # 3 HDT Pump trips.

Trips 1A MFW Pump upon direction from AUO and Maintenance personnel monitoring vibration.

Determines that feedwater flow can not keep up with steam flow with existing conditions resulting in lowering S/G levels.

Directs manual reactor trip in anticipation of 10-10 S/G levels or trips the reactor upon First-Out Reactor Trip Annuciation and failure of reactor to trip and enters E-0.

Performs immediate actions of E-0.

Ensures reactor trip.

Ensures turbine trip.

Ensures 6.9KV Shutdown boards energized.

Cue Console Operator for elevated vibration and removal of pump.

EVENT 9 Auto Reactor Trip Failure.

Critical Task

Scenario 2 Revision 0 Page 30 of 36 OP Test No:

Scenario No.: 2 Event No.: 7, 8, 9, MT Page -

3 of 6

Event 1A and 1 B # 3 Heater Drain Tank Pumps Trip, Rods fail to move on

==

Description:==

demand, Failure of Auto Reactor Trip, Failure of 1A MDAFW Pump to start from MCR, & Failure of the Stby MFWP to start 7

rime: P;b;sition I OAC us CREW OAC CRO CRO OAC i '. + '.,, :

Y,: . Expected ActionsIBehavior'.

b

. ~.

Checks SI not actuated and not required.

Transitions to ES-0.1.

Implements Status Tree monitoring.

Monitors RCS temperature stable or trending to 557°F.

Ensures AFW Pump operation.

Identifies failure of AFW Pump 1A-A to start and informs crew:

Manually attempts start and reports pump failure to start.

Checks AFW LCVs in Auto.

Ensures MFW isolation:

0 MFW isolation valves closed MFW bypass isolations closed MFW reg and bypass reg valves closed 0

MFWPT A and B tripped Standby MFWP stopped 0

Cond demin pumps tripped 0

Cond booster pumps tripped Verifies all control rods fully inserted Announces reactor trip over PA system Transitions to FR-H.1 on red path due to all S/G levels e 10% NR.

Dispatches AUO to check pump breaker compartment.

Scenario 2 Revision 0 Page 31 of 36 OP Test No:

Scenario No.: -

2 Event No 7, 8, 9, MT Page 4 of -

6 Event 1A and 1 B # 3 Heater Drain Tank Pumps Trip, Rods fail to move on

==

Description:==

demand, Failure of Auto Reactor Trip, Failure of 1A MDAFW Pump to start from MCR, & Failure of the Stby MFWP to start OAC OAC CREW OAC OAC OAC OAC Checks secondary heat sink required.

RCS pressure greater than any intact S/G pressure.

RCS temperature greater than 375°F.

Ensures at least one charging pump running.

Determines that RCS bleed and feed required:

Any three S/G WR levels less than or equal to 34% OR RCS pressure greater than or equal to 2335 psig.

Actuates SI.

Establishes at least one of the following RCS feed paths:

At least one charging pump injecting thru BIT, OR At least one SI Pump running with its injection valves open.

Resets SI after 90 seconds, and checks the following:

SI ACTUATED permissive DARK.

AUTO SI BLOCKED permissive LIT.

Resets Containment Isolation Phase A.

Goes to caution prior to step 18.

Critical Step

Scenario 2 Revision 0 Page 32 of 36 OP Test No:

Scenario No.: 2 Event No 7, 8, 9, MT Page 5 of -

6 Event 1A and 1 B # 3 Heater Drain Tank Pumps Trip, Rods fail to move on

==

Description:==

demand, Failure of Auto Reactor Trip, Failure of 1A MDAFW Pump to start from MCR, & Failure of the Stby MFWP to start OAC i I

OAC CRO Ensures containment air in service:

Aux air pressure greater than 75 psig.

Containment air supply valves open:

1 -FCV-32-80.

1 -FCV-32-102.

1 -FCV-32-110.

Ensures adequate RCS bleed path:

Both pzr PORVs open.

Both pzr PORV block valves open.

Performs Steps 1 thru 11 of E-0, Reactor Trip or Safety Injection, while continuing with this instruction.

Maintains RCS bleed and feed paths:

Maintains charging pump injection thru BIT.

Maintains SI Pump flow.

Maintains both pzr PORVs and block valves open.

Determines Cntmt Spray never started.

Ensures CCS alignment for RHR operation:

RHR heat exchanger B outlet 1-FCV-70-153 open.

RHR heat exchanger A outlet 1-FCV-70-156 open.

SFP heat exchanger A supply 0-FCV-70-197 closed.

Critical Step'

Scenario 2 Revision 0 Page 33 of 36 OP Test No:

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2 Event No 7, 8, 9, MT Page -

6 of -

6 Event 1 A and 1 B # 3 Heater Drain Tank Pumps Trip, Rods fail to move on

==

Description:==

demand, Failure of Auto Reactor Trip, Failure of 1A MDAFW Pump to start from MCR, & Failure of the Stby MFWP to start CREW CRO Evaluates the following to restore level in at least one S/G:

AFW pumps.

MFWpumps.

Condensate pumps.

ERCW valves to AFW suction.

HPFP spool piece (AOI-7.06).

Starts 1A MD AFW Pump OR starts the TD AFW Pump after personnel in field indicate pump availability.

TEMMINATE SCENARIO AFTER BLEEDANDFEEDPATH ESTABLISHED AND AFW REESTABLISHED TO SlGs Request for assistance at the pump breaker or transfer switch will provide success path.

APPENDIX B SHIFT TURNOVER CHECKLIST Page 1 of 3 istructions: Do not alter form format! Use TAB keys instead of SHIFT TURNOVER CHECKLIST page -

of -

0 SM

[XI US/MCR Unit 0

uo Unit Off-going - Name 0

AUO Station 0

STA (STA Funclion)

On-coming - Name Cb = 947 ppm

)art 1 - Completed by off-going shiWReviewed by on-coming shift:

Abnormal equipment lineup/conditions:

1 B-B MDAFWP 00s for maintenance to replace outboard motor bearing. ETR 25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months .

Maintenance has completed work on # 2 main turbine governor valve after leak repair.

Medium risk associated with out of service equipment.

LCO 3.7.5 condition B - For 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

Sl/Test in progresslplanned (including need for new brief)

See schedule Major ActivitieslProcedures in progress/planned:

Power was lowered on previous shift to 98% lo lower # 4 governor valve in prep for PMT on # 2 governor valve.

Maintain 98% RTP until governor valve PMT completed, then raise power back lo 100% RTP.

~

Radiological changes in plant during shift:

None Part 2 ~ Performed by on-coming shift 0

0 Review the following programs for changes since last shifl turnover:

0 Standing Orders 0

LCO(s) in actions (N/A for AUOs) 0 Immediate required reading 0

TACF (N/A for AUOs A review of the Operating Log since last held shift or 3 days, whichever is less (N/A for AUOs)

A review of the Rounds sheels/Abnormal readings (AUOs only)

Part 3 -Performed by both off-going and on-coming shift 0 A walkdown of the MCR control boards (N/A for AUOs)

Relief Time:

Relief Date:

N A 40741 [03-20011 Page 1 of 1 OPDP-1-1 [03-14-2001]

APPENDIX B SHIFT TURNOVER CHECKLIST Page 2 of 3 istructions: Do not alter form format! Use TAB keys instead of SHIFT TURNOVER CHECKLIST page __ of -

SM US/MCR Unit Off-going - Name IXI uo Unit -

AUO Station 0 STA (STA Function)

On-coming - Name Cb = 947 ppm

>art 1 - Completed by off-going shiftlReviewed by on-coming shift:

Abnormal equipment lineup/conditions:

18-B MDAFWP 00s for maintenance to replace outboard motor bearing. ETR 25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months .

Maintenance has completed work on # 2 main turbine governor valve after leak repair.

Slnest in progress/planned: (including need for new brief) 1-51-0-2 1-TRI-47-3 needs prior'ty attention to pedorm PMT lor d 2 Governor Valve only.

Major ActivitieslProcedures in propresdplanned Power was lowered on previous shill to 98% to lower # 4 governor valve in prep for PMT on # 2 governor valve.

1-TRI-47-3 for governor valve P 2, then raise power to 100% RTP.

Radiological changes in plant during shin None Part 2 - Performed by on-coming shift 0

Review the following programs for changes since last shift turnover:

0 Standing Orders LCO(S) in actions (N/A for AUOS) 0 Immediate required reading 0 TACF (N/A for AUOs A review of the Operating Log since last held shift or 3 days, whichever is less (N/A for AUOs)

A review of the Rounds sheetdAbnormal readings (AUOs only)

Part 3 - Performed by both off-going and on-coming shift 0 A walkdown of the MCR control boards (N/A for AUOs)

Relief Time:

Relief Date:

N A 40741 [03-2001]

Page 1 of 1 OPDP-1-1 [03-14-2001]

APPENDIX B Page 3 of 3 REACTIVITY MANAGEMENT BRIEF Last Updated For 100% MOL Simulator

1. Our method of maintaining the 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months average reactor power at or below 3459 MWt will be:

Maintain the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months average reactor power at or below 3459 MWt.

Adjustments to the main turbine governor valve position by utilizing the governor valve position limiter (VPL).

a RCS Dilution expected is 120 to 220 gallons per shift.

From TI-59/REACT (-1 PPM = 72 gallons Water) or (+I PPM = 10 gallons Boric Acid).

Maintain reactor coolant temperature 587.5"F - 588.5"F via RCS boron adjustments in appropriate size batches of water or acid, as needed.

The Boron Worth will remain at - 5.7 - 6.0 pcm/ppm until -8000 MWD/MTU Reference NuPOP Figure 6-21. Use TI-59 or REACTINW as required. (Preferred Method)

2. Our method of maintaining Delta I within the target band will be:

Moving control rods in or out in Yz or 1 step increments.

Nominal rod step @ 220 is worth Nominal rod step @ 212 is worth:

(Reference NuPOP Figures 6-24 and 25)

The Boron Worth will remain at - 5.7 - 6.0 pcm/ppm until -8000 MWD/MTU reference

- 1.5 - 2.5 pcm.

- 3.0 - 6.5 pcm.

Our current full power Delta I target band is

(-8.1%) - 1+1.9%1.

Our present Delta I value is

-4

. (Fill in the blank)

Control rods are i AUTO MANUAL. (Circle one) -

3. Peer checking by another licensed person prior to performing reactivity manipulations is required.

4. In the event of a runback initiation without rod motion the boration requirement is approximately u l l o n s / % oower runback.

1

5. Projected reactivity effect is negative I wositiv circle one) if the idle CCP is placed in service.

(Based on RCS Cs being 947 ppm when the pump was last run.

6. Additional reactivity management issues:

ES-501 Post-Examination Check Sheet Form ES-501-1 (R8, Sl)

Task Description

1.

Facility written exam comments or graded exams received and verified comolete Date Complete 11/26/02

2.

Facility written exam comments reviewed and incorporated and NRC grading completed, if necessary Operating tests graded by NRC examiners

3.

II

4.

NRC Chief examiner review of written exam and operating test I grading completed 12/16/02 12/16/02 12/16/02

5.

Responsible supervisor review completed

6.

Management (licensing official) review completed II 7.

License and denial letters mailed I

II 1 ai 8/02 12/18/02

8.

Facility notified of results

9.

Examination report issued (refer to NRC MC 0612) 11 10.

Reference material returned after final resolution of any I

II 1 ai 8/02 appeals

ML032481004

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ML032481004

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