Text

July 2004 Exam 50-390/2004-301 Final Simulator Scenarios
	ML042450328
Person / Time
Site:	Watts Bar
Issue date:	04/05/2004
From:	Ernstes M; Operator Licensing and Human Performance Branch
To:	Scalice J; Tennessee Valley Authority
References
	50-390/04-301, ES-D-1 50-390/04-301
	Download: ML042450328 (146)
	v • d • e

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)

Scenario 3

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CONCURRED:

I

(Operations Superintendent)

(Date)

Scenario 3

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Nuclear Training

RevisionlUsage Log

Scenario 3

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'age 4 of 33

0

initial Issue

07/26/04

ALL

Scenario 3

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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 3

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Page 6 of 33

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.

Scenario 3

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Page 7 of 33

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 candidates ability to perform dilution for AI correction.

Evaluates the candidates 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 candidates ability to recognize loss of dilution flow

e

Evaluate the candidates 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.

Scenario 3

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Page 8 of 33

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 candidates ability to implement 801-18 when Pzr Pressure

Transmitter fails low.

Evaluates candidates 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.

Malfunctions required: 1

rxlla 0, Turbine Impulse Pressure Transmitter, 1-PT-2-73, fails LOW.

Objectives:

Evaluate the candidates ability to implement AOI-2 when Turbine Impulse

Pressure Transmitter fails low.

Scenario 3

Revision 0

Page 9 of 33

Evaluates candidates ability to access control board indications to determine

event in progress.

Success Path:

Scenario 3

Revision 0

Page 10 of 33

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.

Malfunctions required: 4

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

Objectives:

Evaluate the candidates ability to diagnose that a loss of the A

Train CCS

cooling control board indicators and annunciators.

Evaluate the candidates 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.

Scenario 3

Revision 0

Page 11 of 33

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 candidates 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

Malfunctions required: 1

sp02b, Auto SI Initiation Failure

Objectives:

Evaluate the candidates 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

Scenario 3

Revision 0

Page 13 of 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 candidates 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.

Scenario 3

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Page 24 of 33

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

if 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

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.

Scenario 3

Revision 0

Page 16 of 33

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.

Scenario 3

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Page 17 of 33

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-

Scenario 3

Revision 0

Page 18 of 33

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

Scenario 3

Revision 0

Page 19 of 33

APPENDIX A

INFORMATION TO EVALUATORS

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

personnel.

US

~ Unit Supervisor

OAC - Operator at Controls

CRO - Control Room Operator

2. Review the Shift Briefing Information with the operating crew. Provide the US with a

copy of Appendix 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 GO4 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.

Scenario 3

Revision 0

Page 20 of 33

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

KID [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.

Scenario 3

Revision 0

Page 21 of 33

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

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.

Scenario 3

Revision 0

Page 22 of 33

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.

Scenario 3

Revision 0

Page 23 of 33

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 3

Revision 0

Page 24 of 33

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

Scenario 3

Revision 0

Scenario 3

Revision 0

Page 26 of 33

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

0

Scenario 3

Revision 0

Page 27 of 33

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

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.

Scenario 3

Revision 0

Page 29 of 33

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

3eiayed as 5 0

fakes

wiority.

Scenario 3

Revision 0

Page 30 of 33

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.

Scenario 3

Revision 0

Page 31 of 33

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

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.

Scenario 3

Revision 0

Page 32 of 33

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.

Scenario 3

Revision 0

Page 33 of 33

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.

Scenario 3

Revision 0

Scenario 3

Revision 0

Page 35 of 33

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

us

OAC

QAC

CRO

US

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.

Scenario 3

Revision 0

Page 36 of 33

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

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

Scenario 3

Revision 0

Page 37 of 33

OP Test No:

Scenario No.:

3

Event No.:

6, 7, 8

Page -

6

of

~

7

Event

Description:

Main Steam Line Break, Auto SI failure to actuate, BIT outlet

valves fail to Open on SI.

CRQ

CRO

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.

Scenario 3

Revision 0

Page 38 of 33

OQ Test No:

Scenario No.:

3

Event No.:

6, 7, 8

Page -

7

of

7 -

Event

Description:

~

OAC

Main Steam Line Break, Auto SI failure to actuate, BIT outlet

valves fail to Open on SI.

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 MDMW 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 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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

APPENDIX B

SHIFT TURNOVER CHECKLIST

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

&

- -

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

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- RO

C - BOP

C-RO

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

PROGRAM:

WBN Operator Training

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 lQ.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 IO), 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

SCENARIO OBJECTIVES:

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 candidates ability to manually control Main Feedwater Pump

speed and establish proper delta P for S/G level control.

Success Path:

Crew implements the appropriate procedures to place 1 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 candidates 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 CRWs use of AQi-4 during load escalation while on main

reg valves.

Evaluates candidates 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.

Malfunctions required: 1

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

Malfunctions required: 1

rdOl , Continuous Rod Withdrawal

Objectives

Evaluate the candidates 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

Malfunctions required: 1

thQ2b

LOCA Cold Leg Loop 2

Objectives:

Evaluate the candidates 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 candidates 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 candidates 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

Malfunctions required: 1

e siQ9t Failure Phase A Train A Gntmt Isolation Signal

0 bjectives:

e Evaluate the candidates 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

Malfunctions required: 1

0

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

0 bjectives:

e

Evaluate the candidates 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

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

Yhen requested

CONSOLE OPERATORS INSTRUCTIONS

(Continued)

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

Restores power to 1 -FCV-63-22

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

APPENDIX A

INFORMATION TO EVALUATORS

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.

3. Allow the crew to familiarize themselves with current control panel condition

(up to 10 minutes).

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

Note any deficiencies during shift briefing.

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

simulator.

6. Review CONSOLE OPERATORS INSTRUCTON for INITIATING CUES.

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

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

__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

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

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

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

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

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 154 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

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

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.1High 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

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

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

_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

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

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?jr

. .

(00s 1 h ! i E x 4 . h y j l

. .

.

. . ._

__.. IC0 3 . ~ , 5 . A ~ . ~ j q ~ a s l . ~ ~ u r

71 hours8.217593e-4 days 0.0197 hours 1.173942e-4 weeks 2.70155e-5 months : 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

Review the following programs for changes since last shifl turnover:

g]

immediate required reading

0

TACF (N/A for AUOs

A walkdown of the MCR control boards (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

KO@) 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]

APPENDIX B

SHIFT TURNOVER CHECKLIST

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

Appendix D

WBN NRC Simulator Exam

Scenario 1

Rev. 0

Page 4 of 39

PROGRAM: WBN Operator Training

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

SCENARIO OBJECTIVES:

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.

Appendix B

WBN NRC Simulator Exam

Scenario 1

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.

Malfunctions required: 0

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.

Appendix D

WBN NRC Simulator Exam

Scenario 1

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.

Malfunctions required: 1

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 candidates 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.

Malfunctions required: 1

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.

Malfunctions required: 1

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.

Appendix B

WBN NRC Simulator Exam

Scenario 1

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

Malfunctions required: 1

0

tho% 30, Steam Generator #I

tube failure

Objectives:

0

Evaluate the candidates 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

Malfunctions required: 1

rp02b, Auto SI initiation Failure

Objectives:

e

Evaluate the candidates ability to monitor SI initiation parameters and

manually initiate SI when required.

Appendix D

WBN NRC Simulator Exam

Scenario 1

Rev. 0

Page 11 of 39

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

Malfunctions required: 2

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 candidates response to High High Containment pressure

per implementation of FR-Z.1.

Appendix D

Success Path:

WBN NRC Simulator Exam

Scenario 1

Rev. 0

Page 13 of 39

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

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

CONSOLE OPERATORS INSTRUCTIONS

(Continued)

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 directed by

the evaluator.

When requested by

the crew to initiate:

CM-5.01.

When requested

When directed by

the evaluator.

When directed by

the evaluator.

(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

CONSOLE OPERATORS INSTRUCTIONS

(Continued)

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

When directed by

the evaluator.

- 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.

Restores power to 1 -FCV-63-1

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

Rev. 0

Page 18 of 39

APPENDIX A

INFORMATION TO EVALUATORS

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.

3. Allow the crew to familiarize themselves with current control panel condition

(up to 10 minutes).

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

Rev. 0

Page 19 of 39

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 D

Operator Actions

Scenario 1

Rev. 0

Page 20 of 39

Appendix B

Operator Actions

Scenario Z

Rev. 0

Page 21 of 39

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

-..

Tagging All0 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 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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. 0

Page 22 of 39

Appendix D

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

CRW

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-

. . . . . . . . . . .

_. . . . . . .

Appendix D

Operator Actions

Scenario 1

Rev. 0

Page 24 of 39

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

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.

Appendix D

Operator Actions

Scenario 1

Rev. 0

Page 25 of 39

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

Rev. 0

Page 26 of 39

OP Test No:

Scenario No.:

1

Event No.:

4

Page

2

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.

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.

Appendix D

Operator Actions

Scenario 1

Rev. 0

Page 27 of 39

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.

Appendix D

Operator Actions

Scenario 1

Rev. 0

Page 28 of 39

Page

2

of

4

-

- -

OP Test No:

Scenario No.:

1

Event Ne.:

5

Event

Description:

m

..........

gfsg ...

-

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

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

i5glrt6g

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

. . . .

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

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

Rev. 0

Page 29 of 39

-

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.

Appendix D

Operator Actions

Scenario 1

Rev. 0

Page 30 of 39

-

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.

Appendix D

Operator Actions

Scenario 1

Rev. 0

Page 31 of 39

-

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.

Appendix D

Operator Actions

Scenario 1

Rev. 0

Page 32 of 39

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

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

Rev. 0

Page 33 of 39

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

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.

3ew 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

Appendix D

Operator Actions

Scenario 1

Rev. 0

Page 35 of 39

Appendix D

Operator Actions

Scenario 1

Rev. 0

Page 36 of 39

Scenario No.: -

1

Event No.:

6, 7, 8

Page 5 of

6

- -

OP Test No:

Event

Description:

valves to auto ckose.

SG #I

Tube Rupture. Failure of Auto SI. Failure of VCT Outlet

??=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

Rev. 0

Page 37 of 39

n

I

psig, then RCPs are stopped.

Appendix D

Operator Actions

Scenario 1

Rev. 0

Page 38 of 39

SG #I

Tube Rupture. Failure of Auto SI. Failure of VCT Outlet

CREW

CRO

eription:

valves to auto close.

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

Appendix D

Operator Actions

Scenario 1

Rev. 0

Page 39 of 39

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.

Appendix B

Operator Actions

Scenario 1

Rev. 0

Page 48 of 39

Appendix B

Operator Actions

Scenario 1

Rev. 0

Page 41 of 39

Page 2 of

6

__

OP Best No:

Scenario No.:

1

Event No.:

9

Event

Description:

SG #I

Ruptured and Faulted inside containment

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

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.

~

Appendix D

Operator Actions

Scenario 1

Rev. 0

Page 42 of 39

P

Page 3 of

6

-

__

OP Test No:

Scenario No.: I Event No.:

9

Event

Description:

SG #I

Ruptured and Faulted inside containment

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.

Appendix D

Operator Actions

Scenario 1

Rev. 0

Page 43 of 39

Appendix D

Operator Actions

Scenario 2

Rev. 0

Page 44 of 39

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

CRo

Ensures #I

SG isolated from intact

SGs and SG #I

pressure 680 psig.

1

Transitions to ECA-3.1

ir- I

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

Appendix B

Operator Actions

Scenario 1

Rev. 0

Page 45 of 39

8_

__

-

OP Test No:

Scenario No.:

1

Event No.:

9

Page

5

of

6

-

- __

Event

Description:

SG #I

Ruptured and Faulted inside containment

-

. . . . . . . . .

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

.Em:@

aiiiijij.

-

OAC

CREW

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.

Appendix D

Operator Actions

Scenario 1

Rev. 0

Page 46 of 39

-

P

OP Test No:

Scenario No.:

1

Event No.:

9

Page

6

of

6

-

- -

Event

Description:

SG #I

Ruptured and Faulted inside containment

~ -

..........

if$@

...

-

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

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

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

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

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

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

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

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

CROJUS

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

Appendix D

Operator Actions

Scenario 1

Rev. 0

Page 47 of 39

APPENDIX B

SHIFT TURNOVER CHECKLIST

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 proyress'oho~ 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)

Relief Time:

Relief Date:

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)

Relief Time:

Relief Date:

TVA 40741 [03-ZOOI]

Page 1 of 1

OPW-1-1 [03-14-2001]

ML042450328

Text

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