Watts Bar July 2004 Exam 50-390/2004-301 FINAL ...WATTS BAR JULY 2004 EXAM 50-39012004-301 JULY 23,...

Final Submittal

WATTS BAR JULY 2004 EXAM 50-39012004-301

JULY 23, & JULY 26-30,2004

Appendix B Scenario Outline Form ES-D-1

Facility: WATTS BAR Scenario No.: 3 (MOD) Op-Best No.:

Examiners: Operators:

-. initial Conditions: Rx Power 75%. 1A-A Motor Driven AFW Pump is out of service. Delta I is outside target - band requiring dilution to return to target. ~ o a d escalation to 100% is in progress. Turnover: 1A-A MBAFW Pur

Event No.

1

2

3

4

5

6

(Trigger on Scram)

7

(Pre-insert)

8

- - Malf. No. - __ CV51

RXQ7C

RX1 1A

- CCOl

MS026

MSO6C

RP02B

SIOSA

> out of Service for maintenance.

Failure of FT-62-142 - Inhibits ability to dilute. The failure will affects RO's ability to dilute. There are no alarms, so it

ake MANUAL control of control rods. BOP will have r steam dumps. To continue ramp, with this should require the RO to manually operate the rods.

Should require BOP to diagnose.

CNTMT. The crew may have transition& to ES-0.1. An MSlV will be

C - RO Auto SI fails to actuate. RO may initiate MANUAL SI prior to auto actuation.

c - 80 1 BIT outlet valves fail to open automatically on SI.

* (Mjormal, (R)eactivity. (1)nstrurnent. (C)omponent. (M)ajor

Scenario 3 Revision 0 Page 1 of 33

TITLE: Main Steam Line Break Outside Containment

REVISION: 0

DATE: 07/26/04

PROGRAM: WBN Operator Training - Initial License

PREPARED BY: Albert V. White 107I26l04 (Operations Instructor) (Date)

VAblDATlON BY: I

(Operations instructor) (Date)

REVIEWED BY: I (Lead Operations Instructor) (Date)

APPROVED BY: I (Operations Training Manager) (Date)


CONCURRED: I (Operations Superintendent) (Date)


Nuclear Training

RevisionlUsage Log

Scenario 3 Revision 0 'age 4 of 33

0 initial Issue 07/26/04 ALL


PROGRAM: WBN Operator Training

SUBJECT: Simulator Examination Guide

TITLE: boss of Train "A" CCSiMain Steam Line Break Outside Containment.

LENGTH: -4.5 tiQLifS

REFERENCES:

SCENARIO OBJECTIVES:

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

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


SCENARIO SUMMARY:

Initial conditions:

* 75% power, Cb = 978 ppm. The Train Week is “A”. Channel Week 1 or 111 ok. AI is out of target band on the high side requiring dilution to correct. Unit Startup in progress following shutdown for secondary repairs. GO-4, Section 5.1 Step 35. MBAFW pump 1A-A is out of service for maintenance.

Scenario Events and Sequence:

Set up simulator to IC-151

1. Performs dilution per SO!-62-02 to correct AI and continues power ascension.

2. 1 -FT-fi2-142, Primary Water Flow Transmitter, failure.

3. Failure of Non-controlling Pressurizer Pressure channel.

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

5. CCS Train “A” Leak that will be greater than makeup capability. Affects “A” Train Component Cooling Water, RCS Letdown, RCP cooling, etc. Should require BOP to diagnose.

6. Main Stearn Line Break Outside Containment occurs after reactor is tripped..

7. MSlV on # 3 SiG fails to close; Auto SI failure; BIT outlet valves fails to auto open on SI.


EVENT 1 - Raise reactor power from 75% to 100% power.

The crew continues power ascension from 75% power in accordance with General Operating instruction, G O 4

Malfunctions required: None

0 bjectives:

e Evaluates the candidate’s ability to perform dilution for AI correction. Evaluates the candidate’s use of GOs to continue power escalation from 75% power.

rn Evaluates the candidates ability to conduct operations associated with power escalation from 75% power including turbine load ascension and corresponding rise in reactor power.

Suemss Path:

0 Conduct power escalation from 75% power IAW G O 4

EVENT 2 - Failure of 1-FP-62-142, Primary 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: I

0 cv51, Fails FT-62-142 output LOW

Objectives:

Evaluate the candidate’s ability to recognize loss of dilution flow e Evaluate the candidate’s ability to monitor reactor parameters to ensure dilution

stopped andlor prevent from occurring.

Success Path:

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


EVENT 3 - 1-FT-68-323, Non-Controlling Bzr Pressure Transmitter, Falls LOW

Non-Controlling Pressurizer Pressure transmitter, 1 -PT-68-323, fails LOW. Operator will be required to diagnose and determine that alarms and indications support the failure. Operators should respond using AOl-18.

Malfunctions required: 1

Rx07c 0, PZR Pressure Transmitter, 1-PP-68-323, fails LOW.

Objectives:

* Evaluate the candidate’s ability to implement 801-18 when Pzr Pressure Transmitter fails low.

* Evaluates candidate’s ability to access controi board indications to determine event in progress.

Success Path:

Crew implements ,401-18, section 3.0, to respond to Pressurizer Pressure Transmitter failure, determines that RCS pressure is stable and non-controlling pzr pressure channel has failed.

Tech Spec are evaluated and entered for this failure.

EVENT 4 - 1-FT-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.


rx l la 0, Turbine Impulse Pressure Transmitter, 1-PT-2-73, fails LOW.

Objectives:

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


Evaluates candidate’s 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.

EVENT 5 - CCS Leak “A” greater than makeup capability.

CCS leak occurs on the outiet of the “A” CCS Heat Exchanger bringing in CCS Surge Tank level Low alarms. Makeup to surge tank occurs but leak is greater than makeup capacity. 801-15 should be implemented.


ecO4, Component Cooling System Pump Shaft break IA-A CCS pump.

Objectives:

Evaluate the candidate’s ability to diagnose that a loss of the “A Train CCS cooling control board indicators and annunciators.

* Evaluate the candidate’s ability to implement AOI-15 for CCS leakkupture that results in loss of “A” Train CCS cooling.

Success Path:

* Crew recognizes conditions for entry and implements AOI-15 in response to Component Cooling System leakhupture. CORdibiQnS will dictate removing “ A Train ECCS components from service, manual trip of the reactor, stopping of all Reactor Coolant Pumps, and aligning ERCW to 1A-A CCP as a contingency for potential loss of 1B-B CCP.


EVENT 6 -Main Steam Line Break Outside Containment

# 3 Steam Generator becomes faulted outside containment. This failure causes excessive cooldown. MSBV closure should be directed. 1-FCV-1-22, MSIV on # 3 S/G will fail to close.

Malfunctions: 2

0 msQ2c, ramped over 10 minutes to 10% severity. msQ6c 10Q, fails SIG # 3 MSIV fully open.

0 bjectives:

Evahate the candidate’s ability to diagnose a steam line break, and transition from E-0 to E-2, Faulted Steam Generator Isolation, to E-I, Loss of Reactor or Secondary Coolant, and then to ES-1 .I, SI Termination.

Success path;

* Crew implements E-2 to identify and isolate the faulted SG and terminate SI in accordance with ES-1 .I.

EVENT 7 -AUTO SI Fails to Actuate


sp02b, Auto SI Initiation Failure

Objectives:

Evaluate the candidate’s ability to monitor SI initiation parameters and manually initiate SI when required.

Success Path:

Crew diagnoses need for Safety Injection and initiates a Manual SI. Crew determines that Steam Generator Pressure continues to drop and takes conservative action manually initiates manual Safety Injection. Crew returned to E-0, implements €4, then transitions to E-2 to isolate faulted SG, then transitions to E-I then ES-1 .I to terminate SI.

Scenario 3 Revision 0 Page 12 Qf 33


EVENT 8 - BIT Outlet Valve 1-FCV-63-25 & 1-FCV-63-26 Fail to Open Upon SI Signal

Malfunctions: 2

SiOSa, Failure of individual SI signal si09b, Failure of Individual SI signal

Objectives:

Evaluate the candidate’s abiiity to recognize a failure of BIT Outlet Valves 1- FCV-63-25 & 26 to OPEN on SI.

Success Path:

Recognize that BIT Outlet Valves failed to OPEN and manually open the valves.


CONSOLE OPEWTORS INSTRUCTIONS

rst 151 I switch check, select RUN

Turn audible sirnulator fault alarm to “off’ (down position)

Place “A” Train Week” sign

Place Dynamic AFD Display on QAC computer screen.

Place 1 HS-3-118A in PTL and tag I HS-3-118A and 1 -HS9355.

NOTE: IC 151 has been setup for this scenario. If unavailable, new setup for positive AI and power level will be required.

ior rlohs3355 close ior rlohs3355[1] off ior zlohs3355[2] off

imf msQ6c 100

imf rp02b

75 % RTP, BOh, Cb=970 ppm, Bank 3 at 193 steps.

’revents unnecessarily alerting crew i f a simulator problem that may not 2ffect simulator dynamics.

3n entrance side panel. Channel Neek I or 111 ok.

Nil1 indicate on positive side of target land. Setup to require dilution on urnover.

Simulates 1A-A MDAFWP OOS for naintenance.

Simulates 1-FCV-3-355, ?A-A vlDAFWP Recirc, tagged closed.

Simulates IA-A MDAFWP hand ;witch light out.

-ails SIG #I 3 MSlV open.

4uto SI fails to auto actuate. Manual 3 available.

Scenario 3 Revision 0

LI

0

0

D

After crew assumes shift:

When directed by the evaluator for Event 2 (insert after firsf batch dilution has been completed)

If dispatched to blender station.


CONSOLE OPERBTORS INSTRUCTIONS (Continued)

imf cv51 (e2)

imf rxO7c (e31 0

imf rxl l a (e4) 0

imf ccOl (e51 50 5:

imf ms02c (e19) 10 I O :

imf itrigger2

dmf cv51 - only if evaluator request it

1-FT-62-142, primary water to blender flow transmitter, signal fails low. Results in no flow indication or audible click.

1-FT-68-323 fails low.

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

"A" CCS header break makeup capacity ramp to 50% over 5 min.

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

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

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

ROLE PLAY: As AUO if dispatched to blender station, acknowledge request, when makeup occurs report 1-FIT-62- 142 indicates 70 gpm, when makeup stops report that flow is 0 gpm.


CONSOLE OPEWTQRS INSTRUCTIONS

When directed by the evaluator for Event 3

When directed by the evaluator for Event 4

When directed by he evaluator for EVENT 5

3 minutes after .equested to nvestigate

I

(Continued)

mf itrigger3

rnf itrigger4

Non-controlling PZR pressure channel 1-PT-68-323 fails low.

ROLE PLAY: As Work Control, when contacted, inform the MCR that IMs will be dispatched as soon as the work package is issued.

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.

mf itrigger5 “A” CCS header break makeup capacity ramp to 50% over 5 min.

ROLE PLAY: As AB AUQlRad Waste AUQ, when requested, acknowledge request to check for ieaks in CCS.

ROLE PLAY: As Aux Building AUQ, report that the 66s leak is on the outlet of the “ A CCS Heat Exchanger.

3 min after .equested to perform 4ttachrnent 1 of AOI- 15 15.

rnrf rwrO8 open ROLE PLAY: As Aux Building AUO, acknowledge request to align ERCW to 1A-A CCP per Attachment 1 of AOI-

ROLE PLAY: As Aux Building AUQ, report that ERCW has been aligned 1A-A CCP per Attachment 1 of AOI-


EVENT 6

JVhen requested

iNhen requested

Nhen requested

CONSOLE OPERATORS INSTRUCTIONS (Continued)

Auto entry on Reactor Main Steam Line Break outside trip e19 trigger containment.

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

mrf rnsr26 aux MSIV-2-22 Aux switch to Aux.

ROLE PLAY: As AUO, when contacted to take local action to close #3 MSIV, acknowledge request, wait 2 minutes, then report Aux switch has been placed to AUX position.

ROLE PLAY: As AUO, when contacted to check low analyzer temp lights NOT LIT, acknowledge request, wait 2 minutes, then report that Low

p lights on H2 Analyzers are NOT


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 B, Shift Turnover Checklist.

3. Allow the crew to familiarize themselves with current control panel condition (up to 18 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. 7. Provide copy of G O 4 “Normal Power Operation” Section 5.1 completed through step

34 for use by the Unit Supervisor.

6. Provide copy of E-0 “Reactor Trip or Safety Injection’ Appendices “A” and “B” to the CRO Evaluator.


OP Test No: - Scenario No.: 3 Event No.: 1 Page 1 of 2 - -

Event Crew will continue power ascension from 75% power using G O 4 Dilution to correct AI.

Walks control boards down in preparation for raising power and initiates load escalation to 100%

Initiates load escalation to 200% power

Determines and sets in load rate, e Uses reference control button to set

desired load. Depresses go to begin raising load.

Directs OAC to initiate dilution per SOI- 52.02 ‘Boron Concentration Control”, Section 6.2.

letermines required quantity of water to achieve desired RCS Cb by referring to Zppendix D and Appendix E of SOI- 32.02.

ENSURES 2-FC-62-142, PW TO 3LENDER dial [1-M-6], set to 35% (70 jprn), and Manual-Auto toggle in AUTO.

\DJUST 1-FQ-62-142, PW BATCH :OUNTER [1-NI-6], for required quantity rom Appendix D.

’LACE 1-HS-62-140B, VCT MAKEUP K I D € [1-M-6] in DIL.

Ippendix D 8 Appendix ! were provided as part ~f turnover information

4 quantity lower that ippendix D value may )e set in.


OP Test No: Scenario No.: 3 Event No.: 1 Page 2 of 2 - - __

Event Crew will continue power ascension from 75% power using G O 4 Description: Dilution to correct AI.

..............................

.... :.:.:.:.: ...... ..:.:.:.:.:., :- ?&$@a@ . . . ................ P

OAC

OAC

OAC

OAC

OAC

TURN I-HS-62-140A, VCT MAKEUP CONTROL [I -M-6] to START, and VERIFY Red light is LIT.

ENSURES 1-HS-68-341 H, BACKUP HEATER C [1-M-4] is ON to equalize Pnr-RCS C,.

MONITORS the following parameters: 0 1 -PI-62-122----VCT Press. 0 1 -LI-62-129A---VCT Level. 0 ?-Fl-62-142----PW to Blender Flow. 0 I-FQ-62-142---PW Batch Counter.

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

MONITORS NIS and Rod Movement to verify expected response.

IF I-LI-62-129/4, VCT LEVEL [1-M-6] rises to 63%, THEN ENSURE 1-FCV-62- 11 BA, LETDOWN DIVERT TO HUT, diverts to the HUT.

1 -M-6

Rods will insert to depress delta I.


QP Test No: Scenario No.: 3 Event No.: 2 Page 1 of 2 - - -

Event Description: LOW

1-FT-62-142, Primaw Water To Blender, Flow Transmitter Fails

:- ...................... :.:.:.:.:< T&gi&g

OAC

................ -

OAC

us

_a__/

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.

Console Operator will insert failure when first dilution batch has been completed.

Addresses ARl on window 11 2-E and reviews probable cause and corrective actions:

If dilution controls in Auto, then v ~ i i y 1 -FCV-62-128 and 1 -FCV-62- 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 SOI-62.82 for system alignment and operation. Refer to AQI-3, Malfunction of Reactor Makeup Control.

* Notify WQKk Central to initiate corrective action if necessary.

Way direct returning controls to automatic operation and notifying Work Zontrol of malfunction.

Zontrols will be in dilute.

3eference to AO8-3 will 3 8 of no assistance mless dilution event :reated by the :andidate.

\Io flow indication will be available, but flow can )e established if valve to JCT is manually Ipened. No clicking of :ontroller will be heard.


Page 2 of 2 OP Test No: Scenario No.: 3 Event No.: 2 ~ _. -

Event Description: LOW

1 -FT-62-?42, Primary Water To Blender, Flow Transmitter Fails

Should postpone power ascension until primary water flow transmitter fixed.

Directs OAC to re-initiate dilution per SOI-62.02, Section 6.2. After being notified that 1 -FT-62-142 transmitter was improperly valved in and can be signed off by performing makeup as PMT.

If power ascension is desired, w e Console Operator to delete 1 -FT- 62-142 malfunction.


Scenario No.: 3 Event No.: 3 Page ~ I of - 1

1-PT-68-323 Pressurizer Pressure Transmitter Fails LOW

Recognizes PZR pressure channel failure and informs crew. Determines that it is NOT a controlling channel.

Implement ,401-1 8 and direct crew actions.

Ensures PZR pressure stable or rising and pressure controls responding normally.

Checks 1-XS-68-340D not selected to a failed controlling of backup channel.

Notifies Work Control to remove 1-PT-68- 323 from service.

Refer to Tech. Specs and enters applicable LCO actions. Announce to the crew entry into the following LCOs: 1 LCO 3.3.1.6. Condition W 1 LCO 3.3.1.8.a & b Condition X & W 1 LCO 3.3.2.1 .d Condition D

LCO 3.3.2.8.b Condition L.

qotifies Work Control to initiate reDairs to


OP Test No: Scenario No.: 3 Event No.: 4 Page 1 of 2 - - -

Event Description:

1 -PT-I -73 Turbine Impulse Pressure Transmitter Fails LOW

rn :.*= p ................. .......... -

___.

-

TEmTmm -332

OAC

R@ ................. -

us

OAC

QAC

OAC

QAC

CRO

Places rod bank selector switch in manual, and verifies rods stop.

Rods step in at 72 steps per minute.

Refers to and implements AOl-2 “Malfunction of Reactor Control System”, Section 3.2.

Maintains Tavg on program by use of control rods or adjusting turbine load (Attachment 2).

Control rods should be stepped back out to 193 steps if not moved since

Checks Auct Tavg normal on 1-TR-68- 2B. I Shecks NIS power range channels normal.

Identifies failure of PT-1-73 and places steam 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%.

a

a

0


Scenario No.: - 3 EventNo.: 4

1-PT-1-73 Turbine Impulse Pressure Transmitter

Page 2

Fails LOW

- of 2 -

)ACICR Monitors core power distribution parameters:

Power range channels e flux indicators

Tavg * LoopAT

lncoseTCs Feed flowlSteam flow

Scenario No.: 3 EventNo.: 4

1-PT-1-73 Turbine Impulse Pressure Transmitter

US Refer to Tech Spec and enters b60 3.3.1.16. f Condition S.

US Determines power change not greater than 25%. and Chemistry does not need to be notified.

Scenario 3 Revision Q Page 28 of 33

Page 1 of 3 - - I P Pest No: Scenario No.: 3 Event No.: 5 ~

Event CCS LeaklRupture on Train “A” greater than makeup capability. Description

CRO Identifies problem with CCS by various CCS alarms. Dispatches AUQs to investigate problem with CCS.

I I

I Implements AOI-15 Section 3.2 and directs crew actions.

1 CRO Checks that no pumps have tripped and all are pumping fasward.

CRO Checks surge tank vent 1 -FCV-70-66 OPEN, determines CCS Surge Tank Bevel to be lowering, determines that Z-LCV- 70-66, U.8 Surge Tank Makeup LCV, is

I (open, CRQ Monitors A and B Surge Tank levels

greater than 10%. When “A” surge tank level is 6 10 %, stops affected CCS pumps. (IA-A CCS pump/l B-B CCS pump and both thermal barrier booster pumpsf

USlCRO Determines that lass of “A” Surge Bank Level is imminent.

Action to stop affected pumps may occur later than indicated here.

RCPs can be opefated for up to 10 minutes after loss of CCS flow.

:-

OAC

us

OAC

MGICRC

us

Starts 1B-B CCP, stops TA-A CCP.

Dispatches personnel to line up ERCW to 1A-A CCP lube oil Hx using AQl-I5 Attachment 1.

Isolates normal charging and letdown Cfoses letdown orifice isolation 1 - FCV-62-73 or 74.

* Closes RCS letdown valves from Loop 3 1-FCV-62-69 and 70.

* Closes Charging line isolation valves 1-FCV-62-90 and 91.

STOP and LOCKOUT the following pumps:

CCS pumps 1A-A & 1 B-B CSpumplA-A

* RHR pump 1A-A

TBBPs I-A & t-B

SI pump1A-A CCP-1A-A

Directs QAC to actuate a manuai Rx trip, Verify trip, perform immediate actions, hen stop all Reactor Coolant Pumps.


AQI-15 directs that completion must be withir 10-12 min. or damage may occur if CCP-1A-A is in service.

Mofe: This action may be 3’eiayed as 5 0 fakes wiority.


OQ Test No: Scenario No.: 3 Event No.: 5 Page 3 of 3 - - -

CCS LeaWRupture on Train “ A greater than makeup capability. Description

tripped, performs immediate actions, then stops all four reactor coolant pumps.


1) OP Test No: Scenario No.: 3 Event No.: 6, 7, 8 Page - 1 of - 7

Event Main Steam Line Break, Auto SI failure to actuate. BIT outlet n Description: valves fail to Open on SI.

us

CREW

CRO

US

CREW

CREW

OAC

Implements E-0 “Reactor Trip or Safety Injection” and directs crew actions.

Performs immediate actions of E-0.

0 Ensures turbine trip. 0 Ensures shutdown boards

energized.

Transitions to ES-0.1 and directs crew actions.

Commences monitoring of Status Trees.

Monitors SI actuation Criteria.

letermines RCS temperature dropping below 557°F and informs Crew.


OP Test No: Scenario No.: 3 Event No.: 6, 7,8 Page - 2 of 7 -

Event Description:

Main Steam Line Break, Auto SI failure to actuate, BIT outlet valves fail to Open on SI.

pmif8d

us . . . . . . . . . . . . . . .

CRQ

CREW

us

OAC

us

Directs closure of MSlVs. May direct manual Safety Injection based on lowering SG pressure.

Closes MSlVs as directed by US. Informs crew that # 3 SIG MSlV failed to close.

Checks steam dumps dosed Check steam dump controls in OFF.

Determines that safety injection is imminent due to dropping SIG pressure.

Directs Safety Injection initiation.

Initiates manual safety injection.

Returns to E-0 and directs crew actions.

Critical Task

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

Event 7

Note: Auto safety injection has failed.


QP Test No: Scenario No.: 3 Event No.: 6, 7,8 Page - 3 of - 7

Event Description:

Main Steam bine Break, Auto SI failure to actuate, BIT outlet valves fail to Open on SI.

t

o Ensures reactor trip is still tripped. and safety injection.

o Monitors ECCS actuation by checking pumps running and alignments. Manually OPENS BIT outkt valve 1 -FCV-63-25 & 26

Event 8

Ensures MFW isolation: o MFW isolation valves closed

MFW bypass isolations closed MFW reg and bypass reg valves closed MFWPT A and B tripped Standby MFWP StQpped Cond demin pumps tripped Cond booster pumps tripped

Evaluate SI suppoa 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

See Attachment for copy of Appendix A & B of E-0 in back of this guide.

I

Ensure secondary heat sink available.


. . . . . . . . . . . . . . . . us

OAC

QAC

CRO

US

CRO

CRO

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

Checks excess letdown valves closed (1- FCV-62-54 and 1-FCV82-55).

- P

OP Test No: Scenario No.: 3 Event No.: 6, 7, 8 Page - 4 of - 7

Event Description:

Main Steam Line Break, Auto SI failure to actuate, BIT outlet valves fail to Open OR SI.

"<:$# ;$.&g -

-

-

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

in uncontrolled manner.

Transitions to E-2, "Faulted Steam Generator Isolation", and directs crew actions.

Verifies MSIVs and bypasses closed. Verifies steam dump controls are OFF.

Verifies at least 1 intact SIG available.


OP Test No: Scenario No.: 3 Event No.: 6, 7, 8 Page - 5 of - 7

Event Main Steam Line Break, Auto SI failure to actuate, BIT outlet Description: valves fail to Open on SI.

. . . . . . . . . . . . . . . . CREW

CRO

CRO

us

us

OAC

US

CRO

Determines # 3 SIG as the faulted SIG.

Isolates # 3 SIG: Isolates AFW to # 3 SIG.

e Ensures MFW isolated to # 3 SIG. e Ensures # 3 SIG PORV closed.

Ensures # 3 SIG Blowdown isolated. e Ensures TD AFW supplied from

intact SIG.

Monitors CST level >200,0013 gallons.

Directs CRO to control RCS temp stable with intact SIG PORV operation when Faulted SIG is blown down.

Transitions to E-? "Loss of Reactor or Secondary Coolant", and directs crew actions.

Checks RCPs off if RCS pressure < 1500 psig.

Refers to EPIP-I or notifies the SM.

Checks SIG pressure is controlled and Faulted SG has completed, or will soon, complete blowdewn.

~~~

Critical Task


OP Test No: Scenario No.: 3 Event No.: 6, 7, 8 Page - 6 of ~ 7

Event Description:


CRQ

CRO

CRO

OAC

OAC

t ACECRQ

us

Maintain intact SG NR levels. Monitors levels > 10%[25%ADvl

e Control level between 10% and 50% [25% and 50% ADV].

Checks secondary side radiation normal. May contact Chem Lab and RABCON since MSlVs closed.

Ensures cntmt hydrogen analyzers in service to monitor concentration.

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

Determines cntrnt spray never started.

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

and transitions to ES-1 .I “SI Termination” and directs crew actions.


OQ Test No: Scenario No.: 3 Event No.: 6, 7, 8 Page - 7 of 7 -

Event Description:

~

OAC


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 I

APPENDIX B SHIFT TURNOVER CHECKLIST

Page lof 2

SHIFT TURNOVER CHECKLET - - Page of

0 SM

UO Unit Off-going -Name 0 AUB Station

STA (STA Function) On-coming - Name

US/MCR Unit _s_

-

1 ) IA-A M D M W Pump is tagged for oil leak repair of motor outer bearine

2) AI is out of target band on the positive side requiring dilution to correct. I.CO 3.7.5 Condition B for past 12 hours.

SVTest in progresdpianned (including need for new brief)

See schedule

Major Activities/Procedures in pmgresdplanned:

Radiological changes in plant during shifl:

None

'art 2 ~ Perdormad by on-coming shift

0

Review the following programs for changes since last shifl turnover: 63 Standing Orders LCO(s) in actions (N/A fer AUOs)

Immediate required reading TACF (N/A for AUOs

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

A review of the Rounds sheeWAbnormal madings (AUOs only)

'art 3 ~ Performed by both off-going and on-coming shift - P

A walkdown of the MCR control boards (N/A for AUOs)

Relief Time: Relief Date:

TVA 40741 [03-2001] Page 1 of 1 OPBP-1-1 (03-14-20011


Page 2 of 2

SHIFT TURNOVER CHECKLIST Page of - - n SM

E US/MCR Unit La uo Unit - Off-going - Name 0 AUO Station [7 STA (STA Function) On-coming -Name

-

Abnormal equipment lineup/conditions:

1.4-A MDAFW Pump is tagged for oil leak repair of mntor outer hearing.

Slrest in pKgr@§S/plann@d: (including need far new brief)

Major ActivitiedProcedures in progresdplanned: 1) Unit Startup in progress following shutdown for secondary repairs. GO-4, Section 5.1 Step 35 2) Pre Conditioned power level Is 100%. 3) Sol-62.02 Appendix E target boron for load escalation is 936.7 4) Sol-62.02 Appendix D states that 2028 gallons of primary makeup needed to obtain 100%

5) Rx Engineering has requested a dilution to be started as soon as possible to address AI concern. with Control bank 'D' at 220 steps.

Radiological changes in plant during shifl

N""R

'art 2 - Performed by on-coming shifl

0 Review th6 following programs for Chang6S since last shifl turnover

0 Standing Orders LCO(s) in actians (N/A far AUOs)

A review of the Operating Log since last held shifi or 3 days, whichever is less (N/A far ALlOs) A review of the Rounds shesWAbnorrna1 readings (AUOs only)

'art 3 - Performed by both off-going and on-coming shifl P & - -


Relief Time, Relief Dale

Appendix D Scenario Outline Form ES-D-1

P

Facility: WATTS BAR Scenario No.: 2 (MOD) @-Test No.:

Examiners: Operators:

Initial Conditions: Reactor is operating at 42 Yo with one MFW pump in service with power escalation to continue after the second MFW pump has been placed in service.

Turnover: Place the B turbine driven Main Feedwater pump in service. After the feed pump has been placed in service resume power ascension to 45% power. The train week is '4'. 1A-A Auxiliary Feedwater Pump is out of service for motor lead repair.

Event NO.

I

2

3

4

5

6

7

(Pre- insert)

8

(Pre- insert)

9 (Pre- *

- Malf. No. -

___ ni07b

~

rx24

rdOl

th02b

rp55b

Event Type*

N - BOP

8-RO N - BOP

I - RO I - BOP I - SRO

I - BQP I - SRO

c-80 C - SRO

C ~ All

C - R O

C - BOP

C -R O

P

Event Description

Place 4 B Turbine Driven Main Feedwater pump in service.

Raise reactor power to 45% ____ ~

Power Range Channel II fails high; requires S/G #2 and #3 level control to be placed in and controlled in MANUAL. Control rods must be placed in and controlled in MANUAL. Requires Tech Spec evaluation.

Feedwater Pressure Transmitter 3-1 failure high. Requires manual control of fsed pump master controller.

Continuous control rod withdrawal (requires manual reactor trip).

Loop 2 Cold Leg LOCA after transition to ES-O.1

Failure of Auto Phase A; requires manual actuation

Failure of IB-B AFW Pump to auto start; requires manual start of pump.

_ _ _ ~ ~

Failure of WHW to swapover automatically to Containment Sump.

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

Scenario 2 Rev. 0

Page 1 of 41

TITLE: Place Second MFP in Service, Power Escalation from 42% to 45%, PR- N42 Failure High, PT-3-1 Failure High, Continuous Rod Withdrawal, Cold beg LOCA, Containment Sump Recirculation.

REVISION: 0

BATE: 07/26/04

PROGRAM: WBN Operator Braining - Initial License

PREPARED BY: Albert V. White I 07/26/04 (Operations Instructor) (Date)

VALIDATION I BY:

(Operations Instructor) (Date)

REVIEWED BY: I (Lead Operations Instructor) (Date)

APPROVED BY: I (Operations Training Manager) (Bate)

Scenario 2 Rev. 0

Page 2 of 41 CONCURRED: I

(Operations Superintendent) (Date)

Scenario 2 Rev. 0

Page 3 of 41

REVISION NUMBER

0

Nuclear Training RevisionlUsage Log

DESCRIPTION OF REVISION

nitial issue

DATE

07/26/04

PAGES AFFECTED

ALL

REVIEWED BY

Scenario 2 Rev. 0

Page 4 of 41


SUBJIXT: Simulator Examination Guide

TITLE: Place Second MFP in Service, Power Escalation from 42% to 45%, PR-N42 Failure High, PT-3-1 Failure High, Continuous Rod Withdrawal, Cold Leg LOCA, Containment Sump Recirculation.

LENGTH: -1.5 Hours

REFERENCES:

1. Technical Specifications 2. SPP l Q . O (Rev 2), “Plant Operations” 3. OPDP-1 (Rev 4), “Conduct of Operations” 4. GO-4 (Rev 27), “Normal Power Operation” 5. SO1-2&3.01 (Rev 84), “Condensate And Feedwater System” 6. AOi-4 (Rev 26), “Nuclear Instrumentation Malfunctions” 7. AOI-16 (Rev 2&), “Loss of Normal Feedwater” 8. E-0 (Rev 13), “Reactor Trip or Safety Injection” 9. ES-0.1 (Rev 1 “Reactor Trip Response” I O . E-?, (Rev I O ) , “Loss Of Reactor Or Secondary Coolant” I f . FR-O (Rev 9), Status Trees 12. FR-Z.1 (Rev 7), High Containment Pressure 13. FR-P.? (Rev 8), Pressurized Thermal Shock 14. FR-C.2 (Rev 91, Degraded Core Cooling 15. €3-4.3 (Rev 91, Transfer To Containment Sump 16. EPIP-I (Rev 25), Emergency Plan Classification Flowchart


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

2. Evaluate the candidates’ use of E-0 to respond to manual reactor trip and subsequent transition to ES-0.2 ‘Reactor Trip Response”.

3. Evaluate the candidates in their transition back to E-0 and use of €-I in response to a Cold Leg LOCA

4. Evaluate the candidates in their use of ES-I .3 to place ECCS in Sump Recirculation.

Scenario 2 Rev. 0

Page 5 of 41

SCENARIO SUMMARY:

Initial conditions..

Reactor is operating at 42% with one MFP in service and power escalation to continue after the second MFW pump has been placed in service. Cb = I100 ppm, 10000 MWD/MTU. The Train Work Week is “ A Channel 1. MDAFW pump 1A-A is out of service for motor lead repair.

.-. Scenario . Events and_ -Squem

- Set up simulator to IC-145 1. 2. 3.

4.

5. 6 . 7. 8. 9.

Piace I B MFPT in service. Raise power to 45%. Power Range Channel II fails high; requires SIG #2 level control to be placed and controlled in MANUAL. Feedwater Pressure Transmitter 3-1 fails high; requires manual control of main feedwater pump speeds. Continuous control rod withdrawal (requires manual reactor trip). Loop 2 Cold Leg LBCA after transition to ES-0.1. Failure of Auto Phase A Train A; requires manual actuation. Failure of 1B-B AFW Pump to auto start; requires manual start of pump. Failure of RHR to automatically swapsver to Containment Sump.

Scenario 2 Rev. 0

Page 6 of 41 EVENT I - Place 1 B Turbine Driven 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 sewice. Evaluates candidate’s 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 El. MFW Pump in service with master controller in automatic maintaining S/G level program.

EVENT 2 - Raise Power to 45 %

Raise reactor power from 4% to 45%

Malfunctions required: NONE

Objectives: Evaluates the CREW use of GO-4 during power escalation operation. Evaluates the candidate’s ability to control feedwater to steam generators utilizing main reg valve controllers and manual control of SGs 2 & 3 NIS Bias Controllers (when event 3 to is activated). Evaluates the candidates’ ability to controllmonitor reactivity changes. *

Success Path: Use of G8-4, and appropriate use of peer checks for reactivity changes. Maintain NIS Bias controllers for S/Gs 2 & 3 matched with NIS Bias controllers for SlGs I & 4 as reactor power is raised (after event 3 has been responded to).

Scenario 2 Rev. Q

Page 7 of 41 EVENT 3 - Power Range Channel I I fails High

Power Range Channel N-42 fails HIGH causing auctioneered high NI power to rise? causing rising feedwater flows to steam generators #2 and #3 due to NIS program level rise due to this failure.

Malfunctions required: I

niQ7b, Power Range Channel I1 failure

0 bjectives:

Evaluates the CR€Ws use of AQi-4 during load escalation while on main reg valves. Evaluates candidate’s ability to manually control feedwater to steam generators utilizing main regulating valve controllers for #2 and #3 steam generators.

Success Path:

* Crew implements AQI-4, Section 3.4, taking appropriate WIV Reg controllers to manual, defeating power range channel N-42, returning main reg valves Lo auto control, and returning rod control to automatic. Continue control of SG #% & #3 NIS Bias as load is raised further.

EVENT 4 - Feedwater Prressure Transmitter 1-PT-3-1 Failure HIGH.

Feedwater pressure transmitter 3-1 fails HIGH which causes Main FW pump speed to lower requiring the operator to take manual control. This failure will cause much lowered feedwater flow and SG levels will begin to DROP until the operator takes manual control of MFW pump speed and raises pump speeds to supply adequate feedwater flow.


8x24, Main Feedwater Pressure Transmitter ’I-PT-3-1 failure to position.

Objectives:

Evaluate the candidates ability to implement AOI-I6 when Main Feedwater Pressure Transmitter I -PP-3-1 fails HIGH. Evaluates candidates ability to manually control Main FW pump speed.

Scenario 2 Rev. 0

Page 8 of 41

Scenario 2 Rev. Q

Page 9 of 41 Success Path:

Crew implements. .Ol. 6, section 3.7, to respond to the Main Feedwater Pump control circuit failure, takes manual control of the pumps and stabilizes the plant.

EVENT 5 -CONTINUOUS ROD WITHDRAWAL


rdOl , Continuous Rod Withdrawal

Objectives

* Evaluate the candidate’s ability to verify control rods malfunction during startup

Success Path:

Recognize continuous rod withdrawal without demand for movement (rod control in manual), initiate manual reactor trip and transition to E-0.

EVENT 6 - LOOP 2 Cold Leg LQCA


thQ2b LOCA Cold Leg Loop 2

Objectives:

Evaluate the candidate’s ability to diagnose a large break LOCA, transition back to E-0 from ES-0.1 and then correctly implement E-1 , Loss of Reactor 8 6 Secondary Coolant.

e Evaluate the candidate’s ability to respond to high containment pressure in accordance with FR-Z.2 I High Containment Pressure, when required by the Status Trees. Evaluate the candidate’s ability to recognize conditions requiring transfer of RHR to the containment sump and transition to E-I 3, “Transfer to RHR Containment Sump”.

Scenario 2 Rev. Q

Page 19 of 41 Success Path:

e Crew diagnoses large break LBCA, transitions to E-0 and correctly implements €-I.

e Crew responds to containment high pressure in accordance with FR-Z.l. e Crew recognizes RWST level

transitions to E-I .3. 34% and containment sump > 16.1% and

EVENT 7 - Phase A containment isolation fails to actuate


e siQ9t Failure Phase A Train A Gntmt Isolation Signal

0 bjectives:

e Evaluate the candidate’s ability to recognize a failure of Phase A to actuate and initiates manual Phase A.

Success Path:

Crew diagnoses failure of Phase A to actuate and initiates manual Phase A

EVENT 8 - Failure of 1 B-B AFW Pump to auto start


0 rp55b Failure of 1 B-B AFW Pump to auto start.

0 bjectives:

e Evaluate the candidate’s ability to recognize a failure of Start signal for 1 B-B AFW Bump, and start the pump manually.

Success Path:

e Crew diagnoses failure of 1 B-B AFW pump to start, and then get the pump started manually.

Scenario 2 Rev. 0

Page I 1 of41

EVENT 9 - Failure of auto swapover to cntmt sump

Malfunctions: "I

0 bjectives:

Evaluate the candidate's ability to respond to a failure of automatic swapover to cntmt sump

Success Path:

Operator must manually open Cntmt SUMP isolation valves 1-FCV-63-72 and 73 and ensure the RHR suction valves 1-FCV-74-3 and 21 auto open.

. . . . . . . . . . . . . . . .

. . . . . .

3m Setup

I

I

Scenario 2 Rev. 0

Page I 2 of 41

CONSOLE OPERATORS INSTRlBCPlONS

P . . . . . . . . . . . . .

. . . . . . . . . . . . . .

rst 145, switch check, select RUN

NOTE: IC 145 has been setup for this scenario. Continue with set up if IC 145 is unavailable. rst 52 and lower load to 42% and utilize fast time xenon and boron changes to establish 42% and steady state Xenon with AI in target band.

Turn audible simulator fault alarm to “off’ (down position)

Place “ A Train Week” 8,” Channel I” signs on control board

Place 1 HS-3-118A in PTL and tag 1 HS-3- Z 18A and 1-HS-3-355.

ior zlohs3355[1] off

ior zlohs3118a[l] off

DESCRIPTION

52 % RTP, MOL, Cb=llOO ppm, 10000 MWDIMTU

’revents unnecessarily alerting crew if a simulator problem that may not affect simulator dynamics.

3mulates I A-A MDAFWP 80s for naintenance.

jimuiates 1 -FCV-3-355, ’I A-A dDAFWP Recirc, tagged closed.

Simulates 1A-A MDAFWP handswitch ght out.

Scenario 2 Rev. 0

Page 13 of 41

CONSOLE QPERBTORS INSTRUCTIONS (Continued)

0 Imf rx24f (e4) 100 10

0 imf si091

8 I Imf rh02

D I imf 6hQ2b (e61 35 5:

DESCRIPTION -. . . . . . . . . . . . . . . . . . .

Power Range Channel I1 fails High.

Feedwater pressure transmitter 1-PP- 3-1 failure to 100% over 48 seconds.

Continuous Control Rod Withdrawal.

Containment Phase A Train A Auto Isolation Failure

Prevents 1-FCV-63-72 8 73 from auto opening during swapover to cntmt sump. Operator must manually open.

Auxiliary Feedwater Pump 1 €3-B Auto Start Inhibit

Cold Leg LOCA Loop 2 over 5 minute ramp (large break LOCA on loop 2 cold leg)

Scenario 2 Rev. 0

Page 14 of 41

. . . . . .

Nhen requested

When requested by ?valuator for EVENT I

Vhen requested by :valuator for EVENT 1

CQPJSC E OPEaATQRS lNSTRUCTlONS (Continued)

- . . . .

rnf itrigger3

rnf itrigger4

- RESCRIPTIQN . . . . . . . . . . . . . . . . . . .. . . . . . . . .

ROLE PLAY: As TB AUO, when requested, assist in startup of 1H MFWP'I IAW SOI-2&3.Oi, Section 5.10.

Power Range Channel II fails High.

ROLE PLAY: As Work Control, when contacted inform crew that as soon work package is issued MlG will come to control room before tripping bistables and then will initiate repairs for Power range channel N-42.

Main Feedwater Pressure Transmitter 1-PT-3-1 fails HIGH.

ROLE PLAY: AS Work CQntd, when contacted inform crew that as soon work package is issued MI6 will initiate repairs.

Scenario 2 Rev. 0

Page 15 of 41

- ELAPSED TIME -. . . . . . . . . . . . . . . . . . . . . .

Vhen requested by ?valuator for EVENT

When requested by ?valuator for EVENT i

P

Vhen requested

Vhen requested

Yhen requested


ICIMFIRFIOR . . . . . . . . . . . . ._

irnf itrigger5

irnf itrigger 6

rnrf sir04 on

mrf sir44 on

rnrf sir06 on

... -. __- DESCRIPTION -. . . . . . . . . . . . . . . . . . . . ...

Continuous Rod Withdrawal

FIGS LOCA Cold Leg Loop 2 ramps in over 5 minutes.

ROLE PLAY: As AUO, when contacted to open Ice Condenser ACBs using Appendix A of FR-2.1, acknowledge request, wait 2 minutes, then report that Ice Condenser ACBs are open per Appendix A of FR-Z.1.

ROLE PLAY: As AUO, when contacted to check low analyzer temp lights NOT LIT, acknowledge request, wait 2 minutes, then report that LOW

temp lights on H2 Analyzers are NOT LIT.

Restores power to CLA lsol Valves

Restores power to 1 -FCV-63-1


ROLE PLAY: As AUO, when requested to perform Appendices . 4cknowledge requests, wait 2 4 minutes, then report that Appendices lave been completed.

Scenario 2 Rev. 0

Page 16 of 41


1. Assign Crew Positions: (Assign positions based on evaluation requirements for personnel.) Log the positions on Appendix C.

US ~ Unit Supervisor O K ~ Operator at Controls CRQ ~ Control Room Qperator

2. Review the Shift Briefing Information with the operating crew. Provide the US with a copy of Appendix €5, Shift Briefing Information.


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.

7. Provide marked up copy of GO-4 ”Normal Power Operation, Section 5.1 (Step 12 complete) and a marked up copy of SQI-2 & 3.01 “Condensate and Feedwater System” Section 5.10 (Step 40 complete).

8. Provide copy of E-0 “Reactor Trip or Safety Injection’ Appendices “A” and “B” to the CRO Evaluator.

Scenario 2 Rev. 0

Page 17 of41

QP Test No: Scenario No.: 2 Event No.: 1 Page 1 of 3 - __ -

Event Startup of the Second MFW pump. Description: - . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

~ ...............

CREW

,ositron

us

us

CRO

CRO

___...-...........-.I -

................. ............ ............ ._ Expected ActionslBehavior

Walks control boards down in preparation for starting MFP.

Operation”.

service per SBI-2&3.01 “Condensate

hot start complete through step 40.

startup of MFP may be

Place selected MFP(s) in service: Ensure MFP speed changer control in manual, and set to minimum 0 1-SIC-46-2QB, MFPT B Speed

0 Open MFP B discharge valve, 1-

0 Ensures miniflow control valve, ’l- FCV-3-84 in auto at 65%.

Control.

FCV-3-81.

Place selected MFP(s) in service (Continued) 0 Ensures 1-PI-2-129, MFW Pmps

Suction Pressure as follows: Greater than 108 psig (below 50% load). Greater than 250 psig (above 50% load).

Scenario 2 Rev. 0

Page 18 of 41

Scenario 2 Rev. 0

Page 19 of 41

CRO

cao

CRQ

Place selected MFP(s) in service (Continued)

0 Place MFP I B 1-HS-46-43A, MFPT B HP Stop Valve, or I-HS- 46448, MFPT B LP Stop Valve in raise to open the LP and HP stop valves simultaneously.

Place selected Governor Valve Positioner, 1 -HS-46=4QA, to Raise to roll MFP, and verify Governor Valve Positioner is at maximum position by red light indication on controller panel (green light off).

0 Load the MFP Turbine as desired with I-SBC-46-20B. MFPT B Speed Control.

- Scenario No.: 2 Event No.: 1 Page - 2 of 3 -

Startup of the Second MFW pump.

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

Ensure MFP speed changer control in manual, 1-SIC-46- 208, 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-SlC-36-20B, in Auto. Adjust “bias” setpoint slowly to achieve desired flow balance,

Scenario 2 Rev. 0

Page 20 of 41

OQ Test No: - Scenario No.: 2 Event No.: 1 Page - 34 of - 3

Startup of the Second MFW pump. Event Description:

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . )ositjoa

CRO

. . . . . . . .

CRO

CRQ

CRQ

__1-

Expected ActionslBohavior .......... ...... -. ............... ._ Ensure MFP B Hecirc. 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 I O 6 PPH/4000 gpm.

m When TD MFP flow is >2 X 1O6/40O0 gpm, then ensure 1-FCV-3-84 Main Feedwater Pump B Recirc is dosed.

Contacts TB AUO to Adjust MFP B oil temp control, ?-TCV-24-56!3, as necessary to maintain oil temp leaving bearings 140" to 16QT

Nhen in service MFPT is loaded greater :han 40% (approx. 3 X 10' PPH), then :lose selected MFP Turbine drains:

1-HS-46-14, MFPT A Drain VLVS. * 1-HS-46-41, MFPT B Drain VLVS.

Nhen selected MFP is in service and will emain in service, then close the following ialves by contacting TB N O . * 1-ISV-46-451, MFPT 1 B HP STOP

VALVE DRN ISOL [T2G/730] 1-BW-1-618, MFPT 1B HP Steam Warming Line Isolation. F2H/723] 1 -BYV-1-684, MFPT 15 HP Steam

L

Scenario 2 Rev. 0

Scenario 2 Rev. 0

Page 22 of 41

OP Test No: - Scenario No.: 2 Event No.: 2 Page - 1 of - 2

Event Power Escalation to 45% Description: - .... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

- =.. ................................................. ... _____m._

Comment (SATNNSAT) I

'osition . Expected ActionslBehavior c ..................

US Directs OAC & CRO to raise turbine load and reactor to continue the power escalation.

CRO Raises turbine load while coordinating with OAC.

Sol-62.02 'Boron Concentration Controi", Section 6.2.

QAC

OAC

ENSURES 1-FC-62-242, PW PO BLENDER dial [1-M-6], set to 35% (70 gpm), and Manual-Auto toggle in AUTO.

ADJUST 1-FQ-62-142, PW BATCH COUNTER [1-M-6], for required quantity from Appendix D.

A quantity lower that Appendix B value may be set in.

OAC PLACE 1-#S-62-14QB, VCT MAKEUP MODE [1-M-6] in DIL. I

Scenario 2 Rev. 0

Page 23 of 41

Event No.: 2 Page - 2 of 2 -

Power Escalation to 45%

.-

Expected ActionslBehavior

CONTROL [1-M-6] to START, and VERIFY Red light is LIT.

............... - TURN 1 -HS-62-240A, VCT MAKEUP

ENSURES 1-HS-68-341 H, BACKUP

Pzr-RCS C,. HEATER C [1-M-4] is ON to equalize

MONITORS the following parameters: 1 -PI-62-122---VCT Press. I-LI-62-129A---VCT Level. I-FI-62-142----PW to Blender Flow. 1-FQ-62-142---PW Batch Counter. 1 FQ-62-139----BA Batch Counter.

MONITORS NlS and Rod Movement to verify expected response.

IF 1-LI-62-129A, VCT LEVEL [1-M-6] rises to 63%, THEN ENSURE 1-FCV-62- 118A, LETDOWN DIVERT TO HUT, diverts to the HUT.

P - . :omment . . . . . . . . . . . . . . . (SATIUNSAT ........ A

1-M-6

Scenario 2 Rev. 0

Page 24 of 41

OF‘ Test No: - ScenarioNo.: 2 EventNo.: 3 Page - 1 of - 3

Event Description:

Power Kange Channel N-42 Failure High

. . . . . . . . . . .......... .......... .......... .......... .......... .......... .......... /. ................ ,me:;:

. . . . . . . . . . -

-

-

P . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ................ ................ ................ ................ ................ ................ ri ..,::.: ::. :. . . . . . . . . . . . . os1 tlonri

OAC

us

OAC

OAC

CRO

CRO

-_I__-_yy______________-------------------

Expected ActionsiBehavior -.....- ...... Recognize failure of Power Range Channel N-42 and informs CEW of failure.

Indications: * Power Range N-42 rising

Alarms 0 Power Range Overpower Rod WB

Power Range Channel Deviation

Power Range Flux High

stop

Implements A014 “Nuclear Instrumentation Malfunctions” section 3.4 and directs crew actions.

Places control rods in MANUAL and verifies no rod motion.

Determines that N-42 has failed HIGH

Places Main FW Reg valves for S/G 2 and SIG 3 into MANUAL, returns S/G level to program.

Places NIS bias controllers for SlGs 2 and 3 into manual and adjusts their output to match S/Gs 1 and 4, returns all Main Keg Valve to AUTO.

+ -

Comment (SATIUNSAT) _ _ _ & _ & .... ................. ,

May use A082 to respond to Gontinuous rod insertion caused by this malfunction. (AQI-2 will direct crew back to AQI-4 when Nls checked.)

Scenario 2 Rev. 0

Scenario 2 Rev. 0

Page 26 of 41

QP Test No: Scenario No.: 2 Event No.: 3 Page - 2 of ~ 3

Event Description:

Power Range Channel N-42 Failure High

- ................. ................. ................. ................. ................. ................. ................. posiflarr. .................

. . . . . . . . . . . . . . . .

OAC

OAC

OAC

US

OAC

- . -,,,,,,,,,,,z,zz

................. Comment (SATIUNSg Expected ActionslBehavior .............

Maintain T-avg and T-ref within 3°F.

Ensures 1-NR-245 recording an operabk power range channel. Ensures 1 -XS-68-2B, for AT recorder is selected to operable power range channel.

Defeats affected PRM Functions:

Defeats upper & lower detector current comparator for N-42.

* Bypasses rod stop for N-42. * Bypasses power mismatch circuit for

Defeats comparator channel comparator for N-42. Resets positive rate trip for N-42.

N-42.

WHEN failed PRM defeated and AUTO rod control desired, directs OAC to place rod control to AUTO after ensuring zero demand on control rod position indication [l-M-4].

Adjusts control rod position with appropriate peer check to ensure zero demand on control rod position indication (CERPI Display), then places

Scenario 2 Rev. 0

Scenario 2 Rev. 0

Page 28 of 41

OP Test No: Scenario No.: 2 Event No.: 3 Page - 3 of - 3 -

Event Description:

Power Range Channel N-42 Failure High

- ................ ................ ................ ................ ................ ................ ................ !QSRI& ................

. . . . . . . . . . . . . . . .

us

US

US

us

Expected ActionslBohavior .................................................. ..

Contacts Work Control and requests instrument Maintenance to trip failed channel bistables, and initiate repairs on N-42.

Refers to Tech Specs due to NI failure and enters CCOs 3.3.1.2a Condition D, LCO 3.3.1 3.a Condition E, LCO 3.3.2.6 Condition W, LC8 3.3.1 . I6 c & d Condition S, LCO 3.3.1.16.e Condition R.

Contacts Operations Duty Manager and Rx Engineering of power range channel N-42

Returns to GO4

Comment (SATIUNSAI

Scenario 2 Rev. 0

Page 29 of 42

_____E .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ................... ................... ................... ................... ................... . . . . . . . . . . . . . . . . . . . ;Po#fibK;

OAC

. . . . . . . . . . . . . . .

US

CRO

slBe .. Recognize failure of Main Feedwater Pressure Transmitter Failure HIGH. Places rod control in manual while informing crew of failure.

Indieations: Feedwater flows to all four steam generators dropping

* Steam generator levels lowering * Main Feedwater pump speeds

Alarms: MFP 1A FLOW LOW MFP 1B FLOW LQW

lowering

Implements 801-16 section 3.7 and directs crew actions.

Determines MFWPT speed controllerjsj are NOT NORMAL. Places. Controis MFP speeds using MANUAL control of the Master Controller or individual controllers. PC-46-20 Master Controller 1-SlC-46-208 MFPT 1A Speed Controller 1 -SIC-46-28B MFPT 1 B Speed Controller

flay have been 3erformed earlier as mdent operator action.

Scenario 2 Rev. 0

Page 30 of 41

Position

QAC

CRO

CRQ

CRQ

USIOAC

OAC

US

- -.-.-.-

Expected . .. .. .. .. ActionslBehavior

When directed, places control rods in MANUAL and verities rod motion has stopped. Ensures Tavg and Tref within 3°F.

Maintains MFWP discharge pressure on PROGRAM.

Monitors SG levels returning to PROGRAM ~

Checks Steam Bump Mode switch is in T-AVG position.

Notifies Work Control to have the instrument repaired.

When directed returns control rods to Auto.

0 Ensures T-avg and Tref within 1 "F Ensures zero demand on control rod position indication [I -M4] Place rods in AUTO

Returns to instruction in effect.

Page 2 of 2 - Event No.: 4 - - Scenario No.: 2

Main Feedwater Pressure Transmitter 3-1 fails high.

)rogram: 45 psig to 195 x i g from 0% to 100%.

:Approximately 112 psig above SG pressure).

>Iackard on M-3 may be .eferenced.

+ogram: 38% to 60% 1% to 100%.

Scenario 2 Rev. 0

Page 31 of 41

Event No.: 5, 8 Page 1 of 2 OP Test No: - Scenario No.: 2 - -

Event Description: Start

Continuous Rod Withdrawal and Failure of 1 B-B AFW to Auto

ROlOAC + I CRO

P -. .-.-. __. . . . . - _-

Expected ActionslBohavior Comment (SATIUNSAT) . . . . . . . . . . . . . . . . __ _ _ _ __. .... ......

Identify rod withdrawal with rods in MANUAL and inform crew. Advocate a reactor trip.

Implement AOI-2 “Malfunction of Reactor Control System” and direct crew

Direct a manual reactor trip.

Initiate a Manual Reactor Trip.

Implement E-€I ”Reactor Trip or Safety Injection” and direct crew actions.

Perform immediate actions Qf E-0.

Ensures reactor trip.

Ensures turbine trip.

energized.

Checks SI not actuated and not required.

Scenario 2 Rev. 0

Page 32 of 41

ansitions to ES-0.1 “Reactor Trip

Scenario 2 Rev. 0

Page 33 of 44

Event No.: 5, 8 Page 2 of 2 OP Test No: Scenario No.: 2 - _. ~

Event Description: Start

Continuous Rod Withdrawal and Failure of 1 B-B AFW to Auto

- ..... . . . . . .......... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .......... .......... .......... rime . . . . . . . .

~

- ..... . . . . . . . . . . . . . . . . . . . . . . . . . . . ................ ................ ................ ................ ................ ................ posEti&k . . . . . . . . . . . . . . . .

CREW

OAC

CRO

CRO

OAC

us

CRO

-.&.-

Expected ActionslBehavior

Implements Status Tree monitoring.

Monitors RCS temperature stable or trending to 557°F.

Ensures AFW pump operation. Identifies failure of AFW 1 B-€3 to start and informs crew: * manually starts 1 5 4 AFW pump.

checks AFW LCV in AUTO.

Ensures MFW isolation: MFW isolation valves ciosed 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

Verifies all control rods fully inserted

Announces reactor trip over PA system

Monitors CST volume greater than 200,080 gal.

Event 8

Scenario 2 Rev. 0

Scenario 2 Rev. 0

Page 35 of 41

- Scenario No.: - 2 Event No.: 6, 7, 9 Page - 1 of 9 OP Test No: -

Event Description:

Loop 2 Cold Leg LOCA with Failure Of Auto Train A Phase A Cntmt Isolation, Failure of RHR to swapover automatically to Cntmt Sump.

CREW Determines major transient in progress based on Alarms and Indications.

OAC Announces Auto SI on Low PZR Pressure (May manual SI)

May direct manual SI prior to auto

ICRO~OACI Perform immediate actions of E-O. I

Remove RCPs from service based on RCS pressure 61500 psig or on 0B.

manually started.

Scenario 2 Rev. 0

Page 36 of 44

OP Test No: - Scenario No.: - 2 Event No.: 6, 7, 9 Page - 2 of - 9

Event Description:

Loop 2 Cold keg LOCA with Failure Of Auto Train A Phase A Cntmt Isolation, Failure of RHR to swapover automatically to Cntmt Sump. - . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

LAzGXL,

~

-

Appendix A; and Evaluates Phase B Pipe Break Contingencies using E-0

I

US Announces reactor tripkafety injection over PA system

Monitor ECCS operation checking pumps running and alignments:

Charging pumps running Charging pump alignment

m RHR pumps running * SI pumps running

BIT alignment

Identifies failure of Phase A Train A to actuate and informs crew and manually actuates Phase A Train A Cntmt Isolation. (May have been performed

P - 7 - p

Comment .. (SATNNSAT)

See Attachment for copy of Appendix A & B of E-0 in back of this guide.

Scenario 2 Rev. 0

Page 37 of 41

- .................. .................. .................. .................. .................. .................. .................. .................. 'i'pQsTtlon

CRO

. . . . . . . . . . . . . . . . . .

QAC

OAC

OAC

Loop 2 Cold Leg LOCA with Failure Of Auto Train A Phase A Cntmt Isolation, FaiBure of RHR to swapover automatically to Cntmt Sump.

Description:

OAC

CRO

CRO

OAC

us

Ensure secondary heat sink available. 0 AFWflow

SG level

Checks excess letdown valves dosed (4 -FCV-62-54 and 1 -FCV-62-55).

Check PZR safety valves, PORVs and

Determines RCP should not remain in service due to phase B or RCS pressure I 1500 psig. (May have been

Check SIG pressures controlled OF rising.

informs crew they are abnormal. Cntmt temp, press, radiation will ail indicate abnormal.

Secondary Coolant" and directs crew actions until RWST level drops to less than 34%.

Scenario 2 Rev. 0

Page 38 of 41

Scenario 2 Rev. 0

Page 39 of 41

- QP Test No: Scenario No.: 2 Event No.: 6, 7, 9 Page - 4 of - 9 - -

Event Description:

Loop 2 Cold Leg LQCA with Failure Of Auto Train A Phase A Cntmt Isolation, Failure of RHR to swapover automatically to Cntmt Sump.

:.-: 3,.

E x p t e d ActionslBehavior _. . . . . . . . . . . . . . . . . . ____ .

Refers to EPIP-1 or notifies the SM.

Implements FR-P.l “Pressurized Thermal Shock” iWwhen any RCS cold leg temperature is less than 240°F as identified by Status Trees.

Checks RCS pressure 5 159 psig

Verifies RHR is injecting to RCS.

Transition back to E-I from FR-P.l when it is determined that RCS pressure is 4 5 0 psig and RHR is injecting.

lmplernents FR-Z.1”High Containment Pressure” if cntmt press greater than 2.8 psig when status trees are monitored.

Impkments FR-C.2 “Degraded Core Cooling” if RVLlS level falls to 33% or less when status trees are monitored.

Checks SIG pressure and determines that pressure are not indicative of a faulted SIG.

Checks secondary side radiation normal.

Monitors CST level >200,000 gallons.

Evaluator: Go to page 36 for FR-Z.1 steps then return.

Evaluator: Go to page 37 for FR-C.2 steps then return.

Scenario 2 Rev. 0

Page 40 of 41

* At least one SG NR > 18%[25%AD4 NR SG level 6 58% and controlled.

Scenario 2 Rev. 0

Page 41 of 42

OP Test No: Scenario No.: 2 Event No.: 6, 7, 9 Page - 5 of - 9 - -

Event Description:

Loop 2 Cold Leg LOCA with Failure Of Auto Train A Phase A Cntmt Isolation, Failure of KHR to swapover automatically to Cntrnt Sump.

OAC When Cntmt pressure is 2.0 psig: Reset Cntmt Spray signal, stops Cntmt Spray pump 1 B-B, and closes discharge valve 1 -FCV-72-2.

es RHR pumps should not be

NOTE: Grew may transition to ES-1.3 when RWSTXNTMT sump conditions warrant. This may happen at some point during the following steps

Determines shutdown board I CRo I alignment.

Initiates BOP realignment using AOI- 17 "Turbine Trip". (may be done as conditions permit)

OAC Determines RCS pressure dropping or stable.

Scenario 2 Rev. 0

Page 42 of 41 n I I I R

Scenario 2 Kev. 0

Page 43 of 41

Scenario No.: - 2 Event No.: 6, 7, 9 Page 6 of - 9 - - OP Test No:

Event Description:

Loop 2 Cold Leg LOCA with Failure Of Auto Train A Phase A Cntmt Isolation, Failure of RHR to swapover automatically to

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . rime . . . . . . . . . .

-

Cntmt Sump.

CROIOAC

CRO

Dispatches AUO to perform 480V board breaker alignment. (App.A-D)

Determines if hydrogen igniters should be energized. Energizes igniters if conditions permit.

OAC

CROIOAC

Ensures RHR available for cntmt sump recirculation. Determines that

using E-I Appendix E.

CRO I Checks Auxiliary Building radiation. I Notifies Chemistry of event status and plant conditions.

OAC

OAC

Determines that RHR is injecting to RCS

containment sump.

CREW Determines that auto swapover to cntmt sump has initiated or RWST level e 34%.

US Implements ES-2 3, “Transfer to Containment Sump”.

OAC I Checks both RHR pumps running. I

Scenario 2 Rev. 0

Page 44 of 41

OP Test No: Scenario No.: 2 Event No.: 6, 7, 9 Page 7 of 9 - - - -

Event Description:

Loop 2 Cold Leg LOCA with Failure Of Auto Train A Phase A Cntmt Isolation, Failure of RHR to swapover automatically to Cntmt Sump.

- - . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . grficb' . . . . . . . . . -

-

CRO

OAC

OAC

OAC

OAC

_I

Expected ActionslBshavior . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

Establish CCS to RHR heat exchangers.

* Opens 1-FCV-70-156 Cheeks open 1-FCV-70-153

* Closes 0-FCV-70-2 97 Checks CCS Rows & Surge Tank Levels.

Check RWST IeveB <34% and Cntmt sump level >16.1%.

Identifies failure of auto switchover to Cntmt Sump:

Manually opens I-FCV-63-72 and

Ensures 1 -FCV-74-3 and 1-FCV- 74-21 close.

1-FCV-63-73.

Monitors RWST level greater than 8%.

leterrnine Cntmt Spray can be stopped: (may have been performed 2arlier)

Resets Cntmt spray signal. Stops CS pumps 1A-A and 1 B-B. Closes 1-FCV-72-2 and 1-FCV-72- 39

Critical Task

Scenario 2 Rev. 0

Page 45 of 41

OP Test No: Scenario No.: - 2 Event No.: 6, 7, 9 Page 8 of _. 9 -

Event Loop 2 Cold beg LOCA with Failure Of Auto Train A Phase A Cntmt Description: Isolation, Failure of RHR to swapover automatically to Cntmt Sump.

.. . . . . . . . . .......... .......... .......... .......... .......... .......... . . . . . . . . . . rime-

. . . . . . . . . . - -

OAC

- - ~.__y_

Expected ActionslBehavior ........ * ..... Csniment (SATIUNSAT) .................

Perform transfer to RHR cntmt sump: (#I) Isolates SIP mini-flow. (I-FCV-

(#2) Isolates RHR crossties. (I-FCV-

(#3) Aligns CCP and SIP supply from

63-3. 1-FCV-63-1 75, 1 -FCV-63-4)

74-33, 1 -FCV-74-35)

RHW. ('I-FCV-63-6, 1-FCV-63-7, 1- FCV-63-177) - (#4) Aligns RHR discharge to CCP and SIP suctions. (I-FCV-63-8, 1- FCV-63-11)

* j#5) Resets SI. (#6) Isolates CCP suction from RWST. (1-LCV-62-135 and I-LCV- 62-136 with HSs pushed in.) (#7) Isolates SIP suction from WWST.

(#8) Isolates RHR suction from ( 1 -FCV-63-5)

RWST. (1-FCV-63-1).

Critical Task

Monitors respective ECCS flows and motor amps as respective RWST suction valves are closed.

Scenario 2 Rev. 0

Page 46 of 41

__ Scenario No.: 2 Event No.: 6, 7 Page - 9 of - 9

Loop 2 Cold beg LOCA with Failure Of Auto Train A Phase A Cntmt Description: Isolation, Failure of RHR to swapover automatically to Cntmt Sump.

us Directs OAC to initiate Appendix D of ES-1.3 to monitor for containment sump blockage.

I TERMINATE THE EXERCISE I

Scenario 2 Rev. 0

Page 47 of 41

Evaluation Guide for Implementation of FR-Z.1. - ................. ................. ................. ................. ................. ................. ................. .................

. . . . . . . . . . . . . . .

US

:ROIOAC

:ROIOhC

US

P

hplements FR-Z.l “High Containment Pressure” if cntmt press greater than 2.8 psig when status trees are monitored.

Implement actions of FR-Z.1 as directed:

Ensures Cntmt Spray operation. e Ensures Cntmt isolation.

Ensures MSlVs closed. e Places Steam Dump Controls to OFF e Ensures RCPs stopped. e Ensures EGTS and ABGBS running. e Ensures Cntmt air return fans auto

start 10 min after @B.

FR-Z.1 actions continued: e Cheeks SIG pressures controolled

and all greater than 120 psig. e Directs opening ice condenser AHU

ACBs per Appendix A FR-Z.1. e Determines RHRS should not be

placed in service at this time.

Transition back to E-0 upon completion of FR-z.1.

-.--

Zornrnent (ShTIUNSAT)

Note: 1A-A CS has HO TAG

Scenario 2 Rev. 0

Page 48 of 41

OP Test No: - Scenario No.: 2 Event No.: 6% 7 Page 1 of 3 - - -

Event Evaluation Guide for Implementation of FR-C.2. Description: - ..... . . . . . . . . . . . . . . . .......... .......... .......... . . . . . . . . . . .......... . . . . . . . . . . *.. ............. .rme :: . . . . . . . . . . . . . . .

~

-

-

- ................ ................ ................ ................ ................ ................ ................ ................ prrsi:fioi.i

us . . . . . . . . . . . . . . .

OAC

OAC

Expected ActIonslBehavlor

Implements FH-C.2 "Degraded Core Cooling" if RVLlS drops to 33% or lower when status trees are nionitoretl.

...................................................

Establish RHR valve alignment as directed:

Checks RWST level greater than 34%. Ensures RHR suction valves from RWST OPEN: 1-FCV-63-1; 1-FCV- 74-3 and 21 OPEN

* Ensures RHR discharge valves

1-FCV-63-93 and d-FCV-63-94. OPEN: 1 -FCV-74-16 and 28 OPEN.

Establish SI pump valve alignment as directed: * Checks RWST level greater than

34%. * Ensures SI pump suction valves from

RWST OPEN: 1-FCV-63-5, I-FCV- 63-47, 1-FCV-63-48.

* Ensures SI pump discharge valves OPEN: 1-FCV-63-152, d-FCV-63- 153, 1-FCV-63-22.

Zornrnent (SATIUNSAq

Monitor step on RWST level will require transition to ES-I .3 when RWST level drops to 34%. GO to page 32 for auide.

Scenario 2 Rev. 0

Page 49 of 41

Page 2 of 3 - - - - OP Pest No: Scenario No.: 2 Event No.: 6, 7

Evaluation Guide for Implementation of FR-C.2. Event Description:

.......... .......... .......... .......... .......... .......... .......... . . . . . . . . . . cisrig

. . . . . . . . . . -

-

....... . . . . . . . . . . . .................. .................. .................. .................. .................. .................. .................. .................. :Pdsi:tl@i

OAC

. . . . . . . . . . . . . . . . . .

OAC

CRO

USlCRO

OAC

Establish charging pump valve alignment as directed: 0 Checks RWST Bevel greater than

0 Ensures charging pump suction 34%.

valves from RWST OPEN: 1-FCV-

Ensures BIT outlet valves OPEN: 1-

Ensure ECCS flow as directed: 0 Ensures charging pumps running

Ensures flow thru BIT. Ensures SI pumps running and has

0 Ensures RHR pumps running and flow.

62-1 35, 1 -FCV-62-136.

FCV-63-25, 1 -FCV-63-26.

flow

Ensure ECCS flow as directed: Ensures CCS from RHR heat exchangers OPEN: 1-FCV-70-153,

0 Ensures SFP heat exchanger A CCS

Initiate 480V board room alignment per Appendix A and Appendix El of FR-6.2.

1-FCV-70-256.

Supply CLOSED: 0-FCV-70-297.

Ensure PZR depressurization paths closed:

Checks PORVs , Spray Valves and Aux Spray Valves closed.

Scenario 2 Rev. 0

Page 50 of 41

Page 3 of 3 - - OP Test No: Scenario No.: 2 Event No.: 6, 7 -

Event Evaluation Guide for Implementation of FR-C.2. Description: - ................ ................ ................ ................ ................ ................ ................ ................ p&@&j

OAC

................

us

us

US

Expected ActionslBohavior .- ............... **.,_

Ensure RCS depressurization paths ISOLATED:

RCS Letdown orifice and Isolation valves.

* Excess Letdown Post accident sample valves power removed.

* Reactor Vessel head vent valves closed.

Evaluate WCP status. Attempt to establish and maintain RCP Support conditions.

Check if RCS inventory being restored.

Check RVblS greater than 44% then return to instruction in effect; if not then if RVLlS is rising return to step one of FR-C.2.

Keturns to Step 1 of this procedure or transitions back to E-I.

At this point anticipate level rising or RVblS greater than 44%.

APPENDIX €3 SHIFT TURNOVER CHECKLIST

Page 1 of 2

SHlFT TURNOVER CHECKLIST

- Page of

US/MCR Unit uo Unit AUO Station STA STA Function1

A Off-ooinq - Name_

I Qncomim - Name

'art 1 - Completed by off-going shiWRevlewed by on-comlng shin: RCS Cb = 1100

Abnormal eouinment lineun/conditions: _ _ 1) !A48 AF.W ... . . . . . . Pump is 00s . for . . . . motor . . !eadrep? j r . . (00s 1 h ! i E x 4 . h y j l

. . . . . ._ __.. IC0 3 . ~ , 5 . A ~ . ~ j q ~ a s l . ~ ~ u r 71 hours : e ~ i x

SliTest in pmgresslplanned: (including need for new brief)

None in progress - see schedule

Maior Adivities/Procedures in Droaress/slanfled: i) Power ascension to 100% inprogress, GO4 Section 5.1 Step 12 complete. Operations

Superintendent has directed crew to place B MFP in sewice and then mise p e r . 2) A hot start of B MFW pump is being performed per SOL 283.01 Section 5.10 has been

completed through Step 40. 3) Electrical Maint. is repairing the motor leads on 1A-A AFW Pump. 4) TI-124 Risk Matrix is Green. 5) PCP 100%

Radiologicai changes in plant during shift:

None

'art 2 Performed by en-coming shift

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

g] immediate required reading 0 TACF (N/A for AUOs


- _ _ _ _ l _ _ _ y _ _ _ P

A review of the Operating Log since last held shift or 3 days! whichever is less (NIA for AUOs) A review of the Rounds sheets/Abnormal readings (AUOs oniy)

Standing Orders K O @ ) in actions (N/A for AUOs)

'art 3 - Performed by both off-going and on-coming shift

Reiiif Time: Relief Date:

TVA 40741 [03-20011 Page 1 of 1 OPW-1-1 [03-14-2001]


Paae 2 of 2

1 SHIFT TURNOVER CHECKLIST Page of - -

SM

€4 uo Unit - Off-aoina - Name

0 SPA (STA Function) On-coming- . lli Name

0 US/MCR Unit - I AUO Station - _I

WTest in progresdplanned: (including need for new brief)

None in progress - see schedule

Major ActivitiedProcedures in progress/planned: I) Power ascension to 100% in pmgrsss, 60-4 Section 5.1 Step 12 complete. Operations

.................. .................................. . . . . . . . . L _. AFW Punp ..........................

~~~ .~

is standing by B MFW pump with copy of SO1 2 &3.01 Section 5.10.

I Kadiological changes in plant during shifl:

None

I

0 A review of the Rounds sheetdAbnormai readings (AUOs only)

Relief Date: Relief Time:

TVA 40741 (03-ZOOI] Page 1 of 1 OPBP-1-1 [03-14-2001)

Appendix D Scenario Outline Form ES-D-1

Facility: WATTS BAR Scenario No.: 1 (NEW) Op-Test No.: I Operators: 1 Examiners:

I! Turnover ~ ~

Event

li I I N - S R O I

11 -6 I h05a I C - All 1 #1 SIG tube ruptures. Rx trip and SI required.

(N)ormal, (R)eactivity, (I)nstrument, (C)ornpenent, (M)ajor NUKEG-1021, Draft Revision 9

Appendix D WBN NRC Simulator Exam Scenario 1

Rev. 0 Page 1 of 39

TITLE: Steam Generator Tube RupturelMain Steam bine Break Inside Cntml (SG Ruptured and Faulted)

REVISION: 0

DATE: 07/26/04

PROGRAM: WBN Operator Training - Initial License

PREPARED BY: Albert V. White I 07/26/04 (Operations Instructor) (Date)

VALIDATION I BY:

(Operations Instructor) (Date)

REVIEWED BY: i (Lead Operations Instructor) (Date)

APPROVED BY: I

Scenario I

Page 2 of 39 Appendix D WBN NRC Simulator Exam Rev. 0

(Operations Training Manager) (Date)

CONCURRED: I (Operations Superintendent) (Date)

Appendix B WBN NRC Simulator Exam Scenario 1

Rev. 0 Page 3 of 39

REVISION NUMBER

0

Nuclear Training RevisionlUsage Log

DESCRIPTION OF REVISION

!nitial issue

DATE

07/26/04

PAGES

ALL

REVIEWED BY


Rev. 0 Page 4 of 39


SUBJECT: Simulator Examination Guide

TITLE: Steam Generator Tube Rupture/Main Steam Line Break Inside Cntmt (SS Ruptured and Faulted)

LENGTH: -1.5 Hours

REFERENCES:

I ~ Technical Specifications 2. SPP 10.0 (Rev 2), Plant Operations 3. OPDP-1 (Rev4), Conduct of Operations 4. EPIP-1 (Rev 211, Emergency Pian Classification Flow Chart 5. GO-4 (Rev 271, Normal Power Operation 6. ,401-33 (Rev 29 ), Steam Generator Tube beak 7. ,401-16 (Rev ai'), Loss of Normal Feedwater 8. ,401-20 (Rev 23, Malfunction of Pressurizer Level Control System 9. AOE-38 (Rev 38), Main Steam or Feedwater Line Leak I O . 5 0 (Rev 24), Reactor Trip or Safety Injection 11. E-2 (Rev IO) , Faulted Steam Generator Isolation 12. E-I (Rev 13), Loss of Reactor or Secondary Coolant 13. €4, (Rev 20), Steam Generator Tube Rupture 14. ECA3.1 (Revg), SGTR and LQCA Subcooled Recovery 15. FR-Z.1 (Rev 8) High Containment Pressure


1.

2.

3.

4.

5.

6.

Evaluate the candidates in their use of Abnormal Operating Instructions to address various failures or transients. Evaluate the candidates in their use of E-0 to respond to a reactor trip and SI. Evaluate the candidates in their use of E-3 in response to a Steam Generator Rupture (SGTR & Faulted). Evaluate the candidates in their use of E-3 in response to a Steam Generator Rupture that is faulted inside containment. Evaiuate the candidates in their use of FR-Z.l in response to High High Containment pressure. Evaluate the candidates in their use of ECA-3.1 in response to a faulted and ruptured SG inside containment.


Rev. 0 Page 5 of 39

SCENARIO SUMMARY:

Initial conditions:

75% power, Cb = 951 ppm, 10000 MWDIMTU. e Rod Control is in MANUAL, Maintenance is troubleshooting Auto Rod

Control Circuit. Chemistry is taking routine samples of primary and secondary systems. Unit Startup in progress following shutdown for secondary repairs. 60-4, Section 5.1 Step 35. Immediately resume power escalation to 100% while maintaining AI in target band.

e

...... Scenario Events and Sequ.gm

1. 2.

3.

4.

5.

6 . 7. 8. 9.

I O .

Resume power escalation. Tagging AUO reports to Control Room with two Hold Order Tags for tagging out 1A-A MD AFW pump. Reports to Unit Supervisor that Operations Superintendent has requested an immediate clearance to be placed on 1A-A MD AFW pump to prevent damage to pump. The data taken pump during Surveillance run last shift, on review by Engineering, indicates action required due to high vibrations. Chem Lab report of 10 gallonlday tube leak in # I SG, which requires operator to enhance monitoring of leak rate. Main Steam Pressure Transmitter, 1-PT-1-33, fails HIGH which causes the main feedwater pumps to raise speed and requires the operator to take manual control of pump speed. Pressurizer Level Transmitter, 1 -LT-68-339, faiis LOW requiring isolation of charging flow, defeat of channel, and re-establishment of charging and letdown. Chem Lab reports that #1 SG tube leak has elevated to 0.15 gpm. Main Steam Line leak #I SG inside containment. Auto SI fails to actuate. VGT Outlet valves fail to close on SI. Steam Generator tube rupture on #I SG on transition from E-%.

Scenario 1

Page 6 of 39 Appendix B WBN NRC Simulator Exam Rev. 0

EVENT 1 -Continue load escalation

The crew continues plant startup from 75% power in accordance with General Operating Instruction, (30-4.

Malfunctions required: rdO9 Failure of rods to move in auto (part of simulator setup.

Objectives:

Evaluates the candidates use of GOs to continue power escalation from 75% power. Evaluates the candidates ability to conduct operations associated with power escalation from 95% power including raising turbine load and corresponding effect on reactor power (rod control in manual). Opportunities for peer checks of reactivity changes.

Success Path:

0 Conduct power escalation from 75% power.

EVENT 2 - Remove 1A-A AFW pump from

Tagging AUO reports to Control Room with two Hold Order Tags for tagging out ?A-A MB AFW pump. Reports to Unit Supervisor that Operations Superintendent has requested an immediate clearance to be placed on ? A 4 MD AFW pump to prevent damage to pump.


None

Objectives:

Evaluate the crew's response to report of inoperability of 1A-A MDAFW pump.

0 Determines the correct conditions to enter for the appropriate Tech Spec LCO.

Success Path:

Takes actions to remove 1A-A MDAFW pump from service.


Rev. 8 Page 7 of 39

Evaluate and enter appropriate Technical Specification.

EVENT 3 - Respond to Chem Lab report of small 10 gpd tube leak on #1 SG.

Small Steam Generator Tube Leak on #1 Steam generator.


thlOa, Steam Generator Tube Leak Loop 1 Steam Generator. (IO gpdj

Objectives:

Evaluate the candidates ability in their use of Abnormal Operating Instructions AOI-33 in response to the onset of a small SGTL Evaluates the candidate’s ability to implement Appendix A of AOI-33 to provide enhanced leak rate monitoring.

Success Path:

Candidates implement AOI-33 to respond to chemistry report of 10 gpd tube leak on # I SG.

* Candidates utilize available control room indications to monitor RCS. (ICs display CHEM7, ICs net charging flow. Determines leakage is within Tech Spec limits.

Scenario 1 Appendix D WBN NRC Simulator Exam Rev. 8

Page 8 of 39

EVENT 4 - Main Steam Header Pressure Transmitter I-BT-1-33 fails HIGH

Main steam header pressure transmitter, I-PT-1-33 fails HIGH which causes Main FW pump speed to raise which requires the operator to take manual control. This failure will cause elevated feedwater flow and SG levels will begin to RiSE until the operator takes manual control and lowers flow.


e rx20, Main Steam Header Pressure Transmitter 1-PT-1-33 failure to position.

0 bjectives:

* Evaluate the candidates ability to implement AOl-16 when main steam pressure transmitter fails HIGH. Evaluates candidates ability to manually control Main FW pump speed.

Success Path:

* Crew implements 808-16, section 3.7, to respond to the Main Feedwater Pump control circuit failure, takes manual control of the pumps and stabilizes the plant.

EVENT 5 - 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-62- 93A, is required. Failed channel must be defeated and charging and letdown restored. Operators should respond using AOI-28.


e rx05a , Pzr bevel Transmitter I-bT-68-339 fails to 8%.

0 bjectives:

* Evaluates the candidates use of AOE-20 for failure of 1-LT-68-339 LOW.

Appendix 8) Scenario 1

Rev. 0 Page 9 of 39

WBN NWC Simulator Exam

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


Rev. 0 Page 18 of 39

Success Path:

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

* Manual control of PZR Bevel established. Stabilizes the plant and restore PZR heaters, charging and letdown to service. Returns charging flow control valve to auto position.

0 Determines the correct conditions to enter for the appropriate LCOs.

EVENT 6 - Steam Generator #I Tube Rupture


0 tho% 30, Steam Generator #I tube failure

Objectives:

0 Evaluate the candidate’s ability to diagnose a steam generator tube rupture. Evaluate the candidates ability to implement AOI-33 Steam Generator Tube Leak with leak that will require manual trip and safety injection initiation.

Success Path:

Crew responds to tube rupture on # I SG by AOI-33 and then EOP network procedures (E-0, E-3).

EVENT 7 - AUTQ SI Fails to Actuate


rp02b, Auto SI initiation Failure

Objectives:

e Evaluate the candidate’s ability to monitor SI initiation parameters and manually initiate SI when required.



Success Path:

Crew diagnoses need for Safety Injection and initiates a Manual SI. Crew determines that they cannot keep up with the Steam Generatmtor Tube beak with charging maximized and manually initiates reactor trip and SI. Crew implements E-0 to respond to a Steam Generator Tube Rupture.

EVENT 8- VCT Outlet Valves Fail tQ Close


si09e, failure of individual SI signal to 1-LCV-62-132 e si09f, failure of individual SI signal to 4-LCV-62-133

Objectives:

Evaluate the Crew's ability to monitor proper operation of ECCS equipment following response to manual actuation.

Success path;

Manually closes valve upon discovery of failure to close.

EVENT 9 -#I SIG main steam line break inside containment

Main Stearn line break on SG #'l inside containment when crew transitions to E- 3.

Malfunctions required - 1

msOZa, #I SIG Steam bine Break inside containment (ramped)

0 bjectives:

Evaluates the candidate's ability to identify faulted SG inside containment. Evaluate the candidate's response to a Ruptured Steam Generator that is now faulted inside containment.

Scenario I

Page ? 2 of 39 Appendix D WBN NRC Simulator Exam Rev. 0

* Evaluate the candidate’s response to High High Containment pressure per implementation of FR-Z.1.

Appendix D

Success Path:

WBN NRC Simulator Exam Scenario 1


Recognize Main Steam line break. Ensure that Faulted Steam Generator has been isolated. Crew does not feed a ruptured and faulted steam generator. Crew transitions from E-3 to ECA-3.2 for appropriate guidance. Recognize entry conditions and implement FR-Z.1. Crew monitors containment pressure and when containment pressure less than 2 psig, resets containment spray signal, stops containment spray pumps and placed then in F-Auto. These steps conserve RWST for ECCS injection to RCS.

Appendix B

ELAPSED TIME ..... .. . . . . . . . .

Sim Setup

0

n v

J

3

3

3

3

WBN NRC Simulator Exam

CONSOLE OPERATORS INSTRUCTIONS

IClMFlRFlOW

rst 144, switch check, select RUN

NOTE: Bf unavailable then continue with setup with IC 51.

Turn audible simulator fault alarm to “off’ (down position)

irnf rd09

imf siO9e

imf si09f

imf thlOa (el) 4

imf 1x20 (e4) 100

imf rx05a (e5) 0

irnf msOla (e6) 1 5:

irnf th05a (e7) 30

imf rp02b

Scenario 1 Rev. 0

Page 14 of 39

DESCRIPTIOH _. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

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

Control rods fail to move in AUTO.

VCT outlet valves 1 -LCV-62-132 & 233 fail to close.

Small SGTL on #I SG at -10 gpd.

Main steam I-PT-1-33 fails high and causes MFPT speed to rise.

1-LT-68-339, Pnr Level fails low.

Main Steam Break inside containment on SG 1 at 1 % over 5 minutes.

#I SG Tube Rupture a -690 gpm

Auto SI Initiation Failure

Appendix D

When directed by the evaluator.

Enter Control Room with two hold order tags for clearance on 1A-A MD AFW

Request permission to hang HO tags for 1A-A MDAFW pump on the MCR panel.

WBN NWC Simulator Exam


After crew has placed HO tags for

pump, wait approximately 2 minutes then enter override.

IA-A MD AFW

imf itrigger

Have crew Place Z HS-3-118A in BTL and then tag 1-HS-3-118A and 1-HS-3-355.

ior zlohs3355[1] off

ior zlohs3118a[~] off

ior zlohs3118a[2] off

Scenario 1 Rev. 0

Page 15 of 39

DESCRIPTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

Inserts small SGBL on # I SG at -10 gpd. This will cause condenser vacuum exhaust monitors lo start slowly rising with no perceptible change in charging. Event 3 will provide a chem lab report of small -10 aod tube leak on SG # 1.

Role Play: Tagging AUO enters Control Room with two Hold Order Tags for tagging out 1 A-A MB AFW pump. Reports to Unit Supervisor that Operations Superintendent has requested an immediate clearance to be placed on 1A-A MD AFW pump to prevent damage to pump. The data taken pump during Surveillance run last shift, on review by Engineering, indicates action required due to high vibrations.

Role Play: If called confirm that you have directed that an immediate clearance be placed on 7A-A MD AFW pump.

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

Simulates 1A-A MDAFWP handswitch lights out.

Scenario I

Page I 6 of 39 Appendix D WEN NRC Simulator Exam Rev. 0

CONSOLE OPERATORS INSTKUCTIONS

If/when called by MCR.


When requested by the crew to initiate: CM-5.01.

When requested



(Continued;

imf itrigger4

imf itrigger5

DESCRIPTION . . . . . . . . . . . . . . . . . . . . . .

Role Play: As the Work Week Manager and respond to the MCW request to take immediate actions to restore an AFW pump to operable status. Also, we will perform a risk assessment for the situation per TI- 124.

ROLE PLAY: As Chern Lab, Inform the MCR that #I SIG sample is indicating approximately 10 gpd leak rate on the initial count.

ROLE PLAY: As Chemistry acknowledge the request.

ROLE PLAY: As Chemistry, acknowledge request to adjust radiation monitor setpoints for I-RM- 90-119, -120, -121 to provide prompt indication of leakage rise.

Main steam PT 1-33 fails high

ROLE PLAY: As Work Control, when contacted, inform the MCR that the failed 1-PT-1-33 will be added to the work list for the IMs.

1-CT-68-339, Pzr Level Transmitter fails LOW.

ROLE PLAY: As Work Control, when contacted, inform the crew a work package will be initiated for repairs.

Appendix D WBN NRC Simulator Exam


...................


- 8 minutes after

- 10 minutes after

chemistry samples.

1) When Crew enters E-3.

When requested, wait 2 minutes then insert over ride.

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

imf itrigger6

imf itrigger7

mrf sir14 on

-

Scenario 1 Rev. 0

Page 17 of 39

SG tube leak propagates into a rupture on#1 SG.

ROLE PLAY: As Radcon, report that there are higher levels of radiation indicated on #? SG blowdown and steam lines.

ROLE PLAY: As Chemistry, report that there are higher levels of radiation indicated on #I SG blowdown. Currently running analysis to determine leak rate.

Main steam break inside containment at 1 % on SG #I. Ramps in over 5 minutes.


ROLE PLAY: As AUO, acknowledge request; then report power has been *stored to 1 -FCV-63-I ~

Appendix D WBN NWC Simulator Exam Scenario 1



1. Assign Crew Positions: (Assign positions based on evaluation requirements for personnel.) Log the positions on Appendix C.

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 E, Shift Briefing Information.


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

5. Ensure ICs computer active and updating.

6. If not previousby done, review any major differences between plant and simulator.

7. Review CONSOLE OPERATORS INSTRUCTON for INITIATING CUES.

8. Provide copy of GO4 “Normal Power Operation” Section 5.1 completed through step 34 for use by the Unit Supervisor.

Provide copy of E-O ”Reactor Trip or Safety Injection’ Appendices “ A and “5” to the CRO Evaluator.

9.

Appendix D Operator Actions Scenario 1


The crew continues plant startup from 75% power in accordance with General Operating Instruction, GO-4. Description:

............. ................ ................ ................ ................ ................ ................ ................ ................

~ :...... ................ . . .y$&f~

CREW

................

CRO

OAC

Walks control boards down in preparation for raising power and initiates load escalation to 100%

Initiates load escalation to 100% power

0 Determines and sets in load rate, Uses reference control button to set desired load.

0 Depresses go to begin raising load.

Compares Tavg, AT and NIS to verify indications are consistent with expected values. Adjust control rods as necessary to maintain Tave-Tref mismatch.

Appendix B Operator Actions Scenario Z


OF' Test No: Scenario Ne.: 1 Event No.: 2 Page 1 of __ 1 - -

Event Description:

Removal of 1A-A MDAFW pump from service.

.................... .................... $#..$ -

-

- ................ ................ ................ ................ ................ ................ ................ ................ p6$qt&Jfi

LIS

................

US

US

US

-..

Tagging A l l 0 enters Control Room with two Hold Order Tags for tagging out 1A-A MB AFW pump. Reports to Unit Supervisor that Operations Superintendent has requested an immediate clearance to be placed on 1A-A MD AFW pump to prevent damage to pump. The data taken pump during Surveillance run last shift, ~ f l review by Engineering, indicates action required due to high vibrations.

Refers to Tech Specs, declares the ?A-A pump inoperable, and enters TS 3.9.5 Condition B "Restore Operable Status within 72 hours AND 10 days from discovery to meet the LCO."

3irects the CRO to place IA-A MDAFW pump in stop and pull to lock for placing hold order tags.

Zontacts SM and informs the SM of condition of the unit and may request Licensing group assistance in Tech Spec directed actions and may request evaluating risk using TI-124 "Equipment q

Appendix 5 Operator Actions Scenario 1



Rev. Q Page 23 of 39

OP Test No: Scenario NO.: 1 Event No.: 3 Page 1 of 2 __ ~ -

Event Description: SG #I ~

Chem Lab report of small steam generator tube leak (1 0 gpd) on

- . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ?Jm& - -

. . . . . . . . . . . . . . . . . . . . P

us

OAC

US

CRO

CR€W

CREW

OAC

implements AQI-33 “Steam Generator Tube beak.

Checks Pzr level and charging flow determines that Pzr level is STABLE and charging Row 1s STABLE

GO PO Appendix A, Enhanced Leak Rate Monitoring for a 10 gallday leak on #I S/G.

Monitors 1 -RE-90-119 operable and determines that count rate is rising.

E Monitors leak rate USING Chem 7 screen for I -RE-90- 1 19 Response/ Leak Rate Conversion.

e Checks Vacuum pump exhaust and SG Elowdown monitors.

3etermines leakage rate-of-change at least once per 30 min using the difference in leak rate divided by the change in time.

Uonitors PZF level STABLE.

-a-

. . . . . . . . . . . _. . . . . . .



QP Test No: - Scenario No.: I Event No.: 3 Page - 2 of ~ 2

Event Description: SG #I.

Chem Lab report of small steam generator tube leak ( I O gpd) on

- . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .iw . . . . . . . . . . :: . . . :. . . . . .M . . . -

- -

____e

US

US

US

US

US

CREW

Evaluates leakage using Appendix E3 & C, SG Tube Leak Shutdown Criteria, and determines that increased monitoring is required (greater than or equal to 5 gpd but less than 30 gpd).

Directs CWO to monitor radiation monitor readings hourly until stable per Appendix A.

Contacts Chemistry to adjust radiation monitors 1-WM-113, -120,- 121 setpoints to provide prompt indication of leakage rise.

Notifies RADCQN to survey

Notifies Shift Manager concerning SG tube leakage on #I SG.

Makes PA announcement to plant concerning SG tube leak.



OP Test No: Scenario No.: 1 Event No.: 4 Page I of 2 - - -

Main steam header pressure transmitter, 1-PT-1-33 fails HIGH which causes Main FW pump speed to raise which requires the operator to take manual control.

Phis failure will cause elevated feedwater flow and SG levels will begin to rise until the operator takes manual control and Bowers flow.

Event Description:

- CRQ

US

CRO

OAC

QAC

. . . . . . . . .

Respond to annunciators and recognize Failure of PT 1-33. Informs crew of Failure. May lower pump speed.

Indications: * Feedwater flow rising

SIG levels rising

Alarms: * #I HEATERS FW SUPPLY

Computer alarms: FW pump suction pressure low; MFP l A & I B discharge pressure high

PRESS HI (57-8)

Implements AOI-16, section 3.7 and jirects action of the CRO.

'laces main feed pump speed :ontroller (master) in MANUAL. (May ower pump speed to lower discharge xessure).

Zhecks rod control in MANUAL. I - Znsure Tavg-Tref are within 3°F.

Appendix B Operator Actions Scenario 1



Main steam header pressure transmitter, 1 -PT-1-33 fails HIGH which causes Main FW pump speed to raise which requires the operator to take manual control.

This failure will cause elevated feedwater flow and SG levels will begin to rise until the operator takes manual control and lowers flow.

Event Description:

C RQ

CRO

us

OAC

Adjusts speed control to maintain Feed Pump discharge pressure on PROGRAM and return S16 levels to PROGRAM.

Checks Steam Dump mode in Tavg Dosition.

Notifies Work Control to initiate repairs.

If desired to place control rods in auto, Then ensure Tavg and Tref within I" and place control rods to auto. (Leaves rod control in manual)

B Auto Control of Steam Dumps in Pressure Mode not available (will work in manual).

B Feed pump speed requires manuai control.

VOTE: Auto rod control 3ut of service due to iNork in logic cabinet.



Page 1 of 4 - - - OQ Test No: Scenario No.: 1 Event No.: 5

Event Description:

Controlling PZR level transmitter 1-LT-68-339 fails LOW. - ................ ................ ................ ................ ................ ................ ................ ................ F&$lfl6Ki

OAC

................ __I

OAC

us

Recognize PZR level channel I failure and informs crew.

PZW level alarms: Channel I level indication fails Low.

0 PZR LEVEL HllLO [92-A] PZR LEVEL LO-HTRS OFF & LETDOWN CLOSED [92-C]

Recognizes letdown isolation and should isolate charging. (1-HS-62-9QA & I-HS- 62-91A).

Implement 801-20 “Malfunction of Pressurizer Level Control System” and directs the actions of the crew.

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

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



Page 2 of 4 - - - OP Test No: Scenario No.: 1 Event Ne.: 5

Event Description:

m .......... .......... .......... .......... .......... .......... .......... gfsg ...

-

........... .....- ................ ................ ................ ................

................ ................ ................ i5glrt6g ................

. . . . ................

QAC

QAC

OAC

QAC

OAC

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

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

failure is LOW.

Piaces charging valve controller 1-HIC- 62-93A in Manual, and cioses l-FCV-62- 89.

Maintains RCP seal flow between 8 and 13 gpm with charging valve controller 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-68-3395. (Channel 339 not selected.)

68-335 8320).

I

Appendix B Operator Actions Scenario


- OP Test No: ~ Scenario No.: 1 Event No.: 5 Page 3 of 4 - -

Event Description:

Controlling PZR level transmitter 1 -bT-68-339 fails LOW. - ................ ................ ................ ................ ................ ................ ................ r663tTggi ................ . . . . . . . . . . . . . ................

QAC Establishes normal charging and letdown per attachment 1 of AOI-20

Closes I -FCV-62-89. Ensures Charging Pump running. Openskheck 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 gprn seal flow. Ensure letdown isolation valves oper 1 -FCV-62-69, 1 -FCV-62-70 and 1 -

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 40-50% open. Establish charging flow 75 gpm or greater & 8-13 gpm seal injection flow to each RCP. Open letdown orifices as needed. 4-FCV-62-73 or 74, or 72 or 76. Adjust letdown pressure (1-HIC-62- 81A) to -32Opsig and place in AUTO. Place I-HIC-62-78A, letdown hx outlet temp TCVJO-192 cntl, in AUTO. Returns Pzr level to program Return l-HlC-62-93A, charging Row pzr level control, to AUTO.

FCV-62-77.

!0-30% open if 45 gpm xifice used.



--

Page 4 of 4 - ~

OP Pest No: Scenario No.: 1 Event No.: 5

Event Description:

Controlling PfR level transmitter 1 -LT-68-339 fails LOW.

OAC Restores Pzr level control to normal: MAINTAIN regen hx letdown temp <380 "F. Controls charging and letdown to return Pzr level to program.

8 Ensures Pzr control heater bank D red light lit. Momentarily places 1-HS-68-941 H Pnr 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.

us Notifies work control to remove failed channel from service.

US 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.



- QP Test No: Scenario No.: - 1 Event No.: 6, 7, 8 Page - 1 of - 6

Event Description: valves to auto close.

SG #I Tube Rupture. Failure of Auto SI. Failure of VCT Outlet

CREW Recognize SG tube leak by indications and alarms:

Indications: Rising vacuum pump exhaust and SG blowdown radiation Dropping PZR level, rising charging.

* Dropping PZR pressure Reduced feedwater flow to #I SG

Alarms:

PZRPRESSLOBACKLJPHTRS

PZR LEVEL HllbO

* VAC PMP EXH 1-RM-119 HI RAD

ON

LIS

QAC

Returns to section 3.0 of AOI-33 and directs crew actions.

Establishes maximum charging flow. Opens 1-FCV-62-33 and - 89.

Monitors PZR level and determines that pressurizer level is still dropping even with maximum charging.

Way take several ninutes for this determination.



Scenario No.: - 1 Event No.: 6, 7, 8 Page 2 of 6 OP Test No: - -

Event SG #I Tube Rupture. Failure of Auto SI. Failure of VCT Outlet Description: valves to auto ciose. - . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . rrmg; . . . . . . . . . . -

-

.......... CRQ

CRO

US

US

OAC

OAC

US

Places dumpback to CST in MANUAL. and closes 1-LCV-2-3 using 1-[SIC-2-3.

Monitors condenser level 1 -bR-2-12 on scale.

Notifies Radcon and Chemistry to survey secondary plant and sample SGs for high activity.

* Makes plant announcement to warn personnel.

Directs reactor trip and safety injection initiation based on inability of charging to maintain pressurizer level.

Initiates manual reactor trip. Verifies Reactor trip.

Initiates manual Safety Injection.

May determine that Auto SI did not actuate as required. Manually initiates safety injection or places in service at ieast one full train of ESF equipment before transition from E-0.

Implements E-0 “Reactor Trip end Safety Injection” and directs crew actions.

EVENT 7

Appendix €I Operator Actions Scenario 1


Scenario No.: ~ 1 Event No.: 6, 7, 8 Page 3 of 6 OP Test No: __ -

Event SG #I Tube Rupture. Failure of Auto SI. Failure of VCT Outlet Description: valves lo auto close.

?????E? .... ii rf*&;

............ .................... .................... .............. i&A&&Li P

GREW

OAC

CRO

CRO

CRO

Performs immediate actions of E-0.

Ensures reactor trip and safety injection.

* Manually closes VCT Outlet Valves 1 -LCV-62-132 & 4 33.

Ensures turbine trip.

energized. 0 Ensures shutdown boards

Ensures AFW pump operation: I B-B AFW pump & TD AFW pump running AFW LCVs in AUTO

Znsures MFW isolation: MFW isolation valves closed MFW bypass isolations closed MFW reg and bypass reg vaives closed MFWPT A and B tripped

a Standby MFWP stopped * Cond demin pumps tripped

Cond booster pumps tripped

EVENT 8

Appendix 5 Scenario 1

Operator Actions Rev. 0 Page 34 of 39

Scenario No.: 1 Event no^: 6, 7, 8 Page 4 of 6 - __ OP Test No: __

Event Description: valves to auto close.

SG #? Tube Rupture. Failure of Auto SI. Failure of VCT Outlet

P

CRO

US

OAC

CRQ

Evaluates support systems:

0 SI support systems using €3, Appendix A.

Phase B Pipe Break Contingencies using E-0, Appendix B.

~~

Announces reactor trip and SI.

0 Monitors ECCS actuation by checking pumps running and alignments. Manually CLOSE VCT outlet valves 1-LCV-62-132 8 133.

checking Phase A. and CVl on status panels.

0 Checks cntmt pressure 2.8 psig

Ensures cntmt isolations by

Ensures secondary heat sink by checking AFW flow > 410 gpm or SG levels 9 10% NR.

See Attachment for copy of Appendix A & B 3f E-0 in back of this guide.

K T outlet valves may 7ave been closed sarlier.

3 e w may take prudent 3perator action (after step I 2 of E-O), swap steam supply for TD 1DW pump to #4 SG, md isoiate FW to #I



Scenario No.: - 1 Event No.: 6, 7, 8 Page 5 of 6 - - OP Test No:

Event Description: valves to auto ckose.


??=v??- ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . .............. . . . . . . . . . . . . . . Positiorr.''

OAC

CRO

US

CREW

US

QAC

e Monitors Tavg stable or trending 557°F. Checks excess letdown valves closed.

e Checks Pmr PORVs closed Checks Pzr safety valves closed by tailpipe temp or acoustic monitor. Checks Pzr sprays closed. Determines that RCPs should be on

e Checks SG pressures controlled or rising

e Determines that secondary radiation is NOT normal.

Transitions to E-3 "Steam Generator Tube Rupture" and directs crew actions.

Note: Console Operator insert #I SG Steam Line break at this point.

Commences monitoring of Status Trees

Refers to EPBP-1 or notifies the SM to refer to REP.

Determines that RCPs should remain in service. If RCS oressure I 1500

Appendix 5 Operator Actions Scenario 1


n I psig, then RCPs are stopped.




CREW

CRO

eription: valves to auto close.

CRO

CRO

CRO

CRO

CREW

Identifies #I SG as ruptured.

Ensure #I SG PORV set at 90% and in P-AUTO

Ensure #I SG PORV set at 90% and in P-AUTO (may have been performed previously)

Ensures SG #I blowdown isolated.

Isolates ruptured #I SG:

Isolates AFW to #1 (may have been done previously)

* Ensures MFW isolated to #I SG Close #I SG Main Steam Isolation Valve (MSRV).

0 Controls #1 SG > 10% NR.

Determines that containment pressure is rising and the ruptured SG is now faulted to containment.

Indications: Lowering SG levels Lowering SG #I Steam Flow

Alarms KCS LOOSE PARTS DETECTED

CNTMT MOISTURE HI ICE CONB INLET DOOR OPEN

Criticai Task



OP Best No: Scenario No.: - 1 Event No.: 9 Page - 1 of - 6

Event Description:

SG #I Ruptured and Faulted inside containment

CRQ

us

QAC

CREW

us

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

Transitions to E 9 “Faulted Steam Generator isolation” if any SG pressure Bow or dropping uncontrolled AND has not been isolated. Direct crew actions.

Reports that CNTMT pressure > 2.8 psig. Phase B has initiated. Verifies containment spray fiow, stops RCPs.

Identifies ORANGE path FR-Z.1 “High Containment Pressure”.

Transition to FR-2.2 based on Status Trees Response to High High Containment Pressure.



Page 2 of 6 __ __ OP Best No: Scenario No.: 1 Event No.: 9

Event Description:


. . . . . . . . . . . . . . .

CROIOAC

CRO

US

Implement actions of FR-Z.l "High Containment Pressure" as directed

Determines both Cntmt Spray pumps running. There is Cntmt Spray Flow both trains Ensures @A, DB, and CVI isolations. Ensures MSlVs and Bypasses CLOSED. Placeslchecks steam dump controls in OFF Ensures all four WCPs STOPPED. Ensures EGTS and ABGTS RUNNING. Monitors air return fan start 10 minutes adter Phase B initiation.

-

Checks SIG Pressures. Isolates #I SIG:

Ensures AFW to # I SI6 isolated Ensures MFW isolated to # I SI6

Transitions back to E-3 and directs crew actions.

- ~



P P

Page 3 of 6 - __ OP Test No: Scenario No.: I Event No.: 9

Event Description:


us

CRQ

US

OAC

CRO

CRQ

P

.I....... ...............................

Determines that SG #I should not be supplied feedwater (SG #I also faulted inside containment).

* Places dumpback to CST in manual and closed (may have been performed previously) Maintains condenser Bevel on scale

e Checks Cond Dl Bypass valve 1- FCV-14-3 OPEN.

e Ensure Radcon dispatched to survey secondary plant

* Notifies Chemistry to sample SGs

Notifies plant personnel of potential releases

Monitors Pzr PORVs and safeties closed.

Check SG #2, #3, and #4 pressure controlled or rising.

Verifies at least 1 intact SIG available. #2, #3, and #4 SlGs are intact.



SG # I Ruptured and Faulted inside containment

OAC Resets SI, Phase A, Phase B and stops RHR Pumps.

I I !

Establishes Cntmt air by opening 1- FCV-32-80 and 1 -FCV-32-102.

CRO Monitors all AC buses energized by offsite power. !

I I CRo Ensures #I SG isolated from intact SGs and SG #I pressure 680 psig.

1 Transitions to ECA-3.1 ir- I us us

---+--- QAC

Implements ECA-3.1 “SGTR and LOCA - Subcooled Recovery” and directs crew actions.

Dispatches personnel to restore power to RHR suction valve from RWST. (Appendix A of ECA9.1)

/I I OAC Resets SI, Phase A, and Phase 5. (should have been performed earlier)

Ensures cntmt ais in service. (should



8_ __ - OP Test No: Scenario No.: 1 Event No.: 9 Page 5 of 6 - - __

Event Description:


- - . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ......... ... :.Em:@ aiiiijij.

-

OAC

OAC

CREW

us

us

Monitors all AC buses energized by Dffsite power.

Checks RHR pumps not required and shutdown in A-AUTO

Determines that Cntmt Spray not required.

Resets CS signal, stops and places in A-AUTO both CS pumps.

GfO§e§ their respective Cntmt Spray Discharge Valves 1- FCV-72-2 and 1-FCV-72-39. (May have been performed earlier)

Maintain feedwater isolated to SG #I. (Ruptured & Faulted)

Notifies Chemistry of event status and plant conditions.

May direct STNSM to evaluate plant equipment evaluation Appendix D of ECA3.1.



- P


Event Description:


~ - .......... .......... .......... .......... .......... .......... .......... if$@ ...

-

....._._.._._.___ ....................... .................................... ........................................ .........................

....................

.................... ...............

.................... - CROJUS

CRO

CRO

us

Crew

Evaluates plant equipment status using Appendix D of ECA-3.1.

Checks SG pressures controlled or rising

Monitors SG #2, #3, & #4 levels >25% but less than 50% and controlled.

Controls intact SG #2, #3, and #4 between 25% and 50%.

Contact SM/STA to refer to I-SI-0-10 for Shutdown margin.

nitiates RCS cooldown to cold ;hutdown maintaining T-cold cooldown ess than 100 O F in one hour. (or if :ooldown rate has been exceeded letermines when cooldown can be ;tasted.

Critical Task

TERMINATE THE EXERCISE WHEN CREW HAS INITIATED COOLDOWN OR DETERMINED WHEN THEY


Page 1 of 2

SHIFT TURNOVER CHECKLIST

US/MCR Unit - ' AUO Station - ' a uo Unit s_ Off-goinq- Natne

0 STAISTA Function) Qwomina - Name

>art 1 - Completed by off-going shiWReviewed by on-coming shift: RCS Cb _____ = 951

Abnormal noihment lineuo/conditions:

SI/Test in progresdpianned: (including need for new brief)

None in progress - see schsdule

Major ActivitiesIProcefJures in progresdplanned: 1) Cind Startup in p r o y r e s s ' o h o ~ shutdowr, for seconcrdry repet GO-4. Section 5 1 S:e@5 2) :tiirned;ately iebunie power esLJlwon lo 100% wnde mamain931 in target band

. -. . . =. . -. . . __ -. . -. . . . . -. .__ . . .- .- . . -. . . .

Radiological changes in plant during shift:

None

'art 2 - Performed bv on-comino shift ~ ~ ~ _ _ _

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

Review the foilowing programs for changes since last shift turnover:

Sanding Orders 67 LCO(s) in actions (N/A for ALIOS)

Immediate required reading 13 TACF (N/A for AUOs - I?

A rsview of the Rounds sheets/Abnwmal readings (AUOs only)

'aft 3 - Performed by both off-going and on-coming shift P -

A waikdown of the MCR control boards (N/A for AUOs)


TVA 40741 (03-20011 Page 1 of 1 BPBP-1-1 [03-?4-200ll

APPENDlX B SHIFT TURNOVER CHECKLIST

Page 2 of 2

SHIFT TURNOVER CHECKLIST Page of - -

_I

0 AUO Station - _I

SM 0 USiMCR Unit - €a uo Unit - Off-aoing - NKmB

STA (STA Function) - On-comino - Name

RCS Cb = 951 Part 1 - Completed by off-going shiftlReviewed by en-coming shift

Abnormal equipment lineuplconditins: 1) Maintenance is troubleshooting AUTO rod control circuit. Control rods in MANUAL.

SliTest in progresslplanned: (including need for new brief)

None in progress -see schedule

Major ActivitisslProcedures in pmgressiplanned: 1) Unit Startup in progress following shutdown for secondaly repairs. GO-4, Section 5.1 Step 35 2) Pie Conditioned power level is 100%. 3) Sol-62.02 Appendix E target boron for load escalation is 938 ppm 4) Sol-62.02 Appendix D states that 794 gallons of primary makeup needed to obtain 100% with

Control bank 'D' at 220 steps.

Radiological changes in plant during shift

- - - - 'art 2 - Performed by on-coming shift - - 8__ -

A review of the Operating Log since last held shift or 3 days, whichever is less (NIA for AUOs) A review of the Rounds sheetsIAbnorrnal readings (AUOs only)

Standing Orders LCO(s) in actions (NlA for AUOs)

Review the following programs for changes since last shift turnover:

0 Immediate required reading TACF (N/A for AUQs - - 'art 3 - Performed by both off-going and on-coming shift -

0 A walkdown of the MCR control boards (NlA for AUOs)


TVA 40741 [03-ZOOI] Page 1 of 1 OPW-1-1 [03-14-2001]

Watts Bar July 2004 Exam 50-390/2004-301 FINAL ...WATTS BAR JULY 2004 EXAM 50-39012004-301 JULY 23,...

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Transcript of Watts Bar July 2004 Exam 50-390/2004-301 FINAL ...WATTS BAR JULY 2004 EXAM 50-39012004-301 JULY 23,...