Text

Feb-March 2004 Exam 50-400/2004-301 Final Scenarios & Outlines
	ML041130433
Person / Time
Site:	Harris
Issue date:	10/30/2003
From:	Ernstes M; Operator Licensing and Human Performance Branch
To:	Scarola J; Carolina Power & Light Co
References
	50-400/04-301, ES-D-1 50-400/04-301
	Download: ML041130433 (70)
	v • d • e

HARRIS EXAM

50-40012004-301

FEBRUARY 23 - 27,2004

& MARCH 4,2004 (WR1TTEN)

Annendix L)

Simulator Scenario Outline

FOKM ES-D-I

Facility:

~

HARRIS

Scenario Kumber:

1

Op-Test Number:

K

Exuminers

Operators

Initial Conditions: Reset to saved IC-164 (based on IC-32): 26% power MOL;

Run CAEP ile2004scenariuI; CAEP includes the following intial setup items:

AFW Pump A-SA 0 0 s (CFWO26 RACK-OUT; CFWL 13 CP_OFF)

E.VI?. 7 -Reactor Trip failure (RPSOIB 3 3)

EVENT H - AI:% Pump 6 hip (CFWIB)

EVENT 9 - ICs-292 (LCV-I 158) RWSTto CSIR failed shut ABD ICs-291

(LCV-I i 5D) RWSl to CSiPe fail to auto open on SI or lo40 VCT level (CW2 I A

0; ZRPK70lB FAII,..ASIS; ZRPK602B FAIL-ASISI

Ensure the foilowing:

0

DEI1 HOLD button is illuminated

DEFI Demand window @ 195

Both Demand Connters on Bank L) @ IO8 steps

ICE-2791 ICE-284 in OFF

Hoth Condensate Pumps in setvice

One Condensate Booster Pump in service

Reactivity Plan is provided

Marked up copy of GP-005 to Step I18 with Step 93 noted to indicate maintenance

in progress un Condensate Booster Pump B and nll other steps marked off, inchding

Step 14metal temps of 350F7, Step 15 load rate 3 DEH Ihits, and Step 60 time of 1

how ago

Red Bar placed on ALB-01-6-5, ESF SIS TRN A BYPASSED OR INOPERABLE

e

rumover:

The unit is at 2h0/npower at hlOl., R hours following a reactor staitup. The plant tripped

approximately 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months ago (I 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months before startup).

Boron concenhation is 1166ppm. Bank D rods iire at IOllstrps

AFW Pump Awns @&en out of service 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago for oil replacement due to

contaminants and is expected to he rehlmed to aenricr within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . Technical

Specification 3.7.1.2 has been entered. Risk level is YliLLOW.

The Hot Start pushbutton on the MSRs Wac depressed I hour ago.

PMs were performed on Condensate Booster Pump R and have been completed. The pun

isready to be placed in service. An Auxiliary Operator is standing by to stat the

Condensate Booster Pump. All prestarl checks to s t a ~ I the pump are complete.

Shift orders are to plax Condrnsatc Rooster Rimp B in serrice and cantinue the power

ramp to 9Phpower and restore AFW Pump Ato service when it becomes awiilnbk

GP-005 is heing pformed per Step 5.0. I IR.

OSI-PI is not a\\,ailable.

SCENARIOftl

NUREG-1021. Rcririon 9 , h

doXiinction

Number

N A

-j-

!OR LT4T

(none 0 0)

IWO

COK LT48h

none 0 0) 0 0

M F KCS06A

b5O 0 Ask

____

IMf'CND03

18 0 Ash

_-

MF MSSOlC

Asls

xeos znm

mnm 3 3

--

I

-

s

CiWlB

CVC21.40

ZRPK701B

FAII.,-ASIS

%WK6OZB

FAIL ASIS

Evcnt

'hype'

N (BOP)

N (SRO)

1 (W

___.I

___ -.

I (SRV)

I (BOP)

I (SRO)

I (KO)

I (SRO)

c (BOP)

c (SRO)

.~

R (RO)

_-

M (ALL)

__

M (ALL)

_I_

C (BOP)

c (§KO)

_I

C (RO)

C (SRO)

-

Pressurizer Level high failure

SG Level Lou, Failure

Partial Iass of Condenser Vacuum -----

NOTE: INITIATE THISEVENTDLIRIMG PERFORMANCE

OF EVENT 4 A S NOTED IN BODY OFSCENARIO DUE TO

TIME UNTIL THISEVENTIS NOTED BYAVAILABLE CUES.

T H E E VENT WILL ALSOREQUIRESl&iUU TOR

OPEM TOR TO ADJL'STSEVERIn.

Steam Break loaide Containment

Reactor Trip failure

NOTE: INSERT MALIWVCTrON DMUNG INITIAL SETWP

OFSIMULATOR.

AFW Pump 'B trip

4

VOTE; .MI 'I. TIPLE E 1'E.YT.S REQl 'IRt'D. IXSERT

MA1.FLiYCJIO.Y.S DL'RJNG IClTjAL SET1 'P Ot .Yl.Ul'L~j~~lR.

I

Page 2 "f 25

SCENARIOtlI

NUREG-1021, Revision 9,Dnil

Appendix 3

Required Operator Actions

FORM E§-D-2

SCEKAKIONUMBER: 1

EVENTNUMBER: I

FAC:Il.l'lY:

Harris

EVKNT DESCRIPTION:

Place Second Condensate Baoerter Pump in servtDe

I . Om Condcnsatc Booster Pump is in service per Section 5.5 ofOP-134

2. Condensate Booster Pump 3 Iak-Out Relay reset

Reviews CALITION: 'To prevent damagilig the CBP t'ecirc valves. do not operate

the second Condcnsate Booster Piimp for more than 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months with MPP suction

flow lass than 4500 kpph.

3. Total Fcedwater flow is greater than 4500 kpph

4, CPV Operator andChemishg have been notified ofpotential flow and pressiue

anges in the Condensate S

~..~.

TEBOOSI1<X P[MP 13 RECIR6>cE-261

in MOlXj

wsCAUTIQN: There

s UOTE: (:omputer points listed in Section 6.0cf this

monitored for infonnation,

' E: When die Condensate fiourter Pump control switch is placed to

sition, the A m Lube Oil Pump will start and supply the VSF

ater than or equal to 20 psi& at which

Page 5 of15

SI'ENARIOi'l

NUREG-IMI. Reviaion 9,Drafi

Appendix LI

Ryulred Operator Aclions

FORM ES-D-2

SCENARIOXUMRER: 1

PVENTNUMBEK:

1

FACILITY:

Harris

E m N r DESCRIPlTf~N:

Place Seoood Loodensate Traln in

vice (CONTmUED)

Pump running

k-+ BOP

1 Place the control switch CONDFNSATE BOOS%

PllMP R

SCEYARIC P I

h U R K - 1021, Revrsion 9, Drae

Page 4 of 25

Aptundia L1

Required Orrerator Actions

FORM ES-D-2

S(?ENi\\IAX?O NlJl\\.IREX: 1

EVENT NIJMBEk

2

FACILITY:

plsrais

EVENT DESCRIPTION:

PressurizeaLevel high failure

(IKG E:) ICOR L1459 (none0 0) IO0 0

APPLICANT'S AFI'IOZIS OR BEEIAVIOR

SXO

KO

....

-.

Diagnose high failure of controlling PRZ level control channel, 1.T.459

1.1-459 indicating IO(!%

D

Pi(z barkup heaters alJ energize3

e

C h q i n g flowdomcasingon F1-122A.l

PK% CONT HKiB 1,BYEL DEVIATION AEiD HEATERS OX (ALB-009-2-

._I__

increases flow to maintain YRZ lcVci

Enters and directs the performance of OWF-RP

Seizcts chnnneln 460146 1 011 PRZ.

Level Control Selcctar (may select per ALB-

309-4-I 01 -.1-2)

Directs tripping appiopriatc. histables

Kestores chweine iCS-231.1:K-l22.1

CSIAXGIKG FLOW) and aSaces in

.

.- .

-

~~~~

..

~~~~

~

---..___~I

~

I,

.

automatic> if desired

ReferstnTS 3.3.1(6lu),3.1.3.S.ahday)and3.3.3.h( 7day)forPRZlevel

channel failure

Initiates repairs

_..-_I

..

I__I__.

COMMENIS:

Page i

Of2?

SCENARIOUI

NVKEO-IQ21, Kevisim 9.D&

~~

~~~~~

~

Appendix 1)

Required Operdtor .Actions

FORM ESD-2

SCENARIONUMBER

1

EVENTNUMBER:

3

FACIIJTY:

Harris

EVENT DESCRIPTION:

SC: Level Low Failure

'El (AI.B-14-5-IA) alanning

SG 'B' feed ree wlvc meninx

~~~

~

(IMMEDIATE ACTION) Cheek any Main FeMtwater Pump hipped

(IMMEDIATE ACTION) Chcck initial Reactor power Less than 90'h.

BOP

power less than 80%.

.

-

-**6ntrolti"g

__l-l____

Turbine Valves properly

~-1

-

BOP

Mdntain all oftke following:

. . ALL Steam Ge~ne~~~~reaterthan 3Ooh-_.

Check Feedwater Regulator Vnlvrs NOT operating properly in A U l 0 and perfom

.At least one Main Feedwater Pomp running

Main Feedwater flow to all Stem Generators

ter Regulator Valve (PK-488) m MANUAL

s between 52 and 62%(EDUCEFW

.

Paer 6 of25

SCENARlOQl

NUREG-1021. Rension 9, DnR

..

Appendix I)

Required Operator Actions

FORM ES-D-2

)NlJMBEl

.SCRIPTIC

WSITIOK

SRO

SKO

IIOP

BOP

SRO

CUMMENIS:

1

EVEKI'NCMEIER:

3

FACILITY:

Harris

SG Level b w Failure (CONTIWJFB)

APPLICANTS ACTIONS OR BEHAVIOR

Check the following Pump status:

0

If any Fzcdwafcr Train hmps tripped, go to §tap I 1

.........

.......

...

..

...

.-

.VOTE: ON* Y 4 FW PI .tip .E OPRR.J TING A T riiis rwF.

Gc IC [!I<

sedluablc \\C'I:r)":

..

o

All i'nndenat+ieiPeedwatcr flow malfunctrona (other than pump trips) Scctlon

3.1 .-

.

Check the following Kesirc and Dump Valves operating properly in MODU:

Main Fcedaater Punips

0

Condenrate Booser Primps

e

Condensate Pumps

e

ICE-293, Condensate Kecirc

<;heck the Condensate and Feedwater System mtact

Reviews NOTE: Pump8 sliould br stopped in the order ofhigher to lower

oressure. (To s t m a Condensate Pumo. stou a Main Feedwater PYMD fidlowed hv e

e

ICl..-142, Condensate Dumq'Ib __

CST Isolation Valve

-

_I

Check Reactor thermal power changed hy less than 15% in any onc hour pcriud

Exit AOP-010

Xefm toi)WP-RP for SG 'B'level fnili:re ( X i 'B' Level)

ReferstoTSi.?.l (Items 13and 14). ~io,rrrerluirementfotri?,hislablw

lnitiatc repairs

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

~~.

. ~ ~ .

-

.-I__

.-

Pafie 7 of 25

SCENABUONUMBER 4

EVENTNUMBER:

4

FACILITY

Harris

EVEKT UCSCRII'TION:

Median Tsvg high Cnllure

(TRG E3) IMF R W 6 A 6% 0 ASIS

alarming

Charging flow FI-122A.1 increasing

YK-122 output increasing

Enter and direct the actions of BOP-00 1. Malfunction d Rod Control and

SRO

-

lndicatioti System

(IMMEDIATE ACTION1 Chcck that < 2 control rods are dropped

-

(IMMEDIATE ACTION) Position Rod Bank Selector Switch to MAN --

-

--

ACTl0K;Chcck Control Rank motion stopped

SRO

Goto the appropriate section:

Section 3.2, Continuous SpuiiousControl Bank Motion

.~

.~ -

-4 no I Manuallu merate affected control hank to restore the fnllowinz:

. .

-

. Equilibrium power and temperature conditions

! e

Rods above the insertion limits of Tech Saec 3.1 3.6 and PLP-I 06. Technical

COMMENTS:

Page8of25

SCENARIO#i

NUREG-IU21. Revision 9, Drdlt

Agpcndm I1

Kqarred Opemtoi Actions

FORM ES-D-2

D

KCSTavg

e

RCS Tref

a

Power RangeNl channels

~

Reactor Makeup Control System

~.

Check that this section was not entered t l x

_.I_

cnntrol banks moving out and go tn

c following occurred:

.~

ed RCS dilution

n automatic Rod Control malfunction occiirred

COMMENTS:

I'age 9 of 25

SCENARIO%I

NUREO.1021, Rcvisiotl9, Dnfl

FORM ES-D-2

Ameridix r)

Required Ooerator Actions

SCENARIO NUMBER: 1

EVENTNUMBER:

5

FACILITY:

Harris

EVEXI I)ESCRIP1'60N:

PirIX Loss of Condenser Vacuum

(TRO M)IMFCNW3 18 Oasis

in both %ones ess t

5.5 inches Hg-absolute and Turbine first stage pressure is @eater thnn Wh

g absolute and Turbine fint stage pressure is less than 60%

Y~CCUUIII loss identifiedwd corrected

stable or incredsing

1-

'H OPERATOR

COMMEhTS:

Appendix D

Rcqwcd Operator ~4ctionr

FORM ES-13-2

SCENARIONIIMDER: 1

EVEN1 NLIMBER:

5

FACILITY:

Harris

EVEN? DESCRIPTION

Partial LOSS of Condenser Vacuum (CONTINUED)

Ilowing valves shut

e

ICE-449. Condenser Vac Breaker

expansion joint is indicated and 80 to Step 14

i

SRO

i%k

NO lsolahle IC&

between Con&crWaterbox

isolation valves exists and I

go to Step20

Check Circulating Water tcmpcraturce using the following EWIS

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

~ ~ ~ ~ . ~ ~ . . .

Points stable or decreasing:

e

TCW 1939, Cooling Tower Basin Temp

TCW1940A. Con&nser A Circ Water-Inlet Temp

TCWI94OB, Condenser U Circ Waterlnlet Temp

plant shutdown initiated

Load Disvatcher of reduced load capability

__

..

. -

--

itor lurhiae vibsatinn levelfi normal

COMMENTS:

FJW 11 of 25

SCENARlOill

Appendix D

Required O m t o r Actions

10RM ES-D-2

SCENAKIO NIIMHER: 1

EVENTNUMBER:

S

FACILITY:

Harris

EVEhV DESCRIPlION:

Partial Loss of CondenserVaculurm (CONTWUEII)

Page 12of25

SCENARlOill

NUREG-1021, Revision% Drafl

.Appendix D

Required Operator Actions

FORM ES-D-2

SCPNARilONIiMBER: ?

EVENTNIJMBER:

6 / 7

FACILITY:

Harris

EVEN'?' IIIISCKIPTIOK:

Steam Urea& Inside Containment with FaikW of Rea&or to Trip

IIRG ESI IMF MSSOIC 8eMX ZO%JAssIs

L

neartar power increasing

-

Steam ilow increasing

Feed flow increasing

s

SG Ieve1s decreasing after iiiitial swell

Steam pressure decreasing

KCS temperature decreasing

0

Containment pressure increasig

Containment sadiation levels unciiange

Orders a reactor trip and safety injection and enten PATH-I

__

Reactor trip bieakcrr closed

Kod bottom lights off

a

Neii:ron flux NOT dccrcasing

Altcmpts manual trip ofreactor

Dstenninesmanml trip NOT successful

a

Raactnr trip breakers dosed

a

Rod bottom lights off

e

Neutron flux NOT decreasing

Infsm~ SRO of failure of reactor to trip autumntically or nmually

Transitions to and directs the actions ofFW-S.:, RcsponsttoNuclear Power

(jmcration / A'rw

(MMEDBATK ACTION) Verifies rods inserting a~~tornatically

or manually inserts

contrul rods

..-..._____I

-~

.~

~~

~

.

_

Appendix D

Required Operator Actions

FORM ES-D-2

SCEIL'ARIONI!MRER 1

EVEN1' NUMBER: 6 / 7 !

8

FAC.IL1I'Y: Harris

EVENT DESCRIPTION:

Steam Break inside Contninmentwith Failure of Reactor to Trip

fCONTINUED)-FallureofMAPW Pumn to Start

I

Ai! turbine throttle valves shut

I

tripped and directs operato

I

I NEGATIVE REACTIVITY TO CQRE.

I

Directs operatorto locallytrip the reactor hy (order of preference):

-

Loally opening the reactor trip kreakers

i.ocal!v @in both rud drive M(i set eenerator oulput breakers.

Page 140f25

SCENARIO PI

~

Appendix D

Required Operator Actions

FORM ES-D-2

(CONTINUED)

-FailureofR'rVST toCSW Suctions to Qpen

CSlP Suction Valve Failm initiated in CAEP

0

Start a boric scid pump

Open !C:S-Z7R, Emergency Boric Acid Addition valve

Verify :.- 30 gptn emergeiicy boration flow

Verify > 30 gppn: CSlP llowtn KCS

Verify RCS pressure -: 2335 p i

Krcect.; RO to initiate manual §I

due:"

oiily one train actuating

Attempts to nrsnually actuate Train B SI

NOTE: 5 I A C m F E D m 1

_l_l

..~

I

kernpis to open IC§-491 and ~ ~ p o r t s

failureto SRU

1 CS-291 red light off. green w o n

COMMEKTS:

Page 15 uf25

SCENAK1OBI

NI!KE(i-I021,

Revision !), DraR

Appendix I)

Required Operator Actions

FORM ES-t-2

SCENARIONUMBER: 1

EVENT NUIMBER:

6 / 7

FACILI1'Y:

Harris

EVENT DESCRIPTION:

Steam Break Inside CQUtUinEEICUt with Failure of Reactor to Trip

(CONTINUED)

R T I C C ~ R L Y I F M S I S O L A T l ~ ~ n A S

OCXURRED, AND

TQISOLATEAFWTOSG 'C!

, II Dilution Paths Isolated

Reactor Makeup Water pumps OFF

I'C.V-I 14B. Reactor Makeup Water valve SHUT

ICSOR, BTRS Bypass valvc OPEN

Direct A 0 to locally verifv ICs-S IO. Boric Acid Ratch Tank Outlet valve

@

Checks for positive reac.tivity addition due to cooldown

Keactar timed

COMMEWS:

Page 16 of 25

SCENARIOUI

hVREF;-IOZL, ReririonY, Drafl

Appendix 1)

Kequirrd Opsmtor Actions

FORM ES-D-2

SCENARIOMJMIIEK: I

EVENTNIMBER:

6 / 7

FACILITY:

Harris

EVENT DFXR1PTION:

S t e m Break Inside Containment wlth Failum of Reactor to Trio

(CONTINCED)

APPI.ICAUI"S ACIIONS OR BEHAVIOR

I>etermines S t i 'W'and SO '8' NOT faulted

RO

SRO

.

. -

ISOlatZS sc 'C'

e

Verifics PORV closed

Verifies FW Isolation closed

Verifies AFW iuohted to Si3

e

Closeu Steam supply to TDAFW Pwnp

0

Verifies beforz Beat draiii isoiation ctwcd

Verifies SCi blowdoown isolation closed

Verifies stcam analyzer isolation closed

0

Vcrify reactor subcritical

e

Power ranges< 24

Intermediate startup ratc negative

Implcmcnts I W 3 . as required and transitions IO PATH- I due fn NO Red or

Orange Path conditions ~-

Page iIof'2S

SCBNAKlOXl

NIREG-IO21, Reriiion 9. Draft

FORM ES-D-2

Appendix I)

Required Operator Actions

I

~~~~

Verifics p r o p operation of emergcnc.). safeguards equipment

CSIP and RllR pumps running

Main steam line isolation

SI flnw > 200 gpm

c

Containment pressure above 10 psig, with action3 takcn

AFW flow at least 210 KPPL; available

I

-

COMMEhTS

SCENARIO ff 1

NUREG-1021, RevisioaQ. h a R

i w m d i x 1)

Required Operator Actions

FORM ES-D-2

SCENARIO NLMBER: 1

EVENI"UR1HER:

6 i 7

FACIIII'Y

Harris

EVENT DESCRIPT1C)h:

Steam 5rmk Inside Containment with Pailore oPReador to Trio

(CONTINUED)

APPLICANT'S ACTIONS OK REIIAVIOR

ESFAS proper aligninem using Attachment 6

0

2 CSIPs iunning

e

2 KHR Primps running

2 CCW Pumps running

All ESW and t S W Booseer Pumps mnning

s

SI Valves properly aligned

NOTE: RWSTWC'TlON TOCSIP ICS-fYi FAil

ACTliA TIOX MAYII.4 VE REENRECOG~VIZEL

ALREADYATTEMPTED TQ OPEA!

e

Phase A proper alignment

e

Main steam lines isolatd

Rlowdowi: and SCi sample YBIY~S

shut

Containment Spray opcmtion

RCPs stopped

Both PW Pumps tripped

1:W Isolation valves closed

NEITHER MDAFW Pump operating

'I'DAFW Pilmp operating

AFW alignment (FLOW ISOIATED TO SG 'C')

Containment Fan Cuolcrs - I per unit operating in slow speed

Contrul Room Ventilation in Emergency Xecirc

AC Buses 1.41 and ID! encrgizd

Air compressors 1A and lil in Local Control Mode

a

80th EL)Gs iunning

8

s

a

e

SCENARIWI

Reauired Oaerntor Actions

FORlrl IS-D-2

Anncndix I)

SCENARIONIJMBER: 1

EVENTNUMBER:

6 ! 7

FACILII'Y:

Harris

EVENT UESCRiPllON:

Steam Break Inside Containment with Failure of Reactor to Trip

CONTINUED)

SG 'C' was previously isolated

SI NUL'terminated by SI flow being > 200 gpni

RCS Pnsrurc (stable/ incnasine)

-.

~~~~

~~

RCS OVERFILL AND PRESSURIZATION RESULTiNG IN

COMMENTS

SCENARIOPI

Appendix I1

Required Opermr Actions

FORM ES-11-2

SCENARIONIIMBER 1

EVENTNUMBER:

61 7

FACILITY: Harris

EVENT DOSCRIPTIOW.

Steam Break 1nsideContdinmentwith Failure aftleastor to Trip

ow isolation valves

. ICs-196

I . ICs-210

I

VALVES(ICS-I82. ICs-196, AND ICs-210) STROKE

0PEA'A.W TMENIMMEDIA TELY CLOSE. TRAINA VALVE (ICs-214)

COMMENTS,

NVREG.1021, Rcvrsron 9, Draft

Page 21 of 2s

SCEhARIO1 I

Appendix D

Required Operator Actions

FORM ES-a2

SCENARIONUMBER: I

E\\'E.NI"UMBER:

6/ 4

FACLITY

Hnrris

EVENT UESCRIPTIOK:

Steam 5reak Imide Contsinmenfwith Failnreaf Readorto Trip

DIRECT BREAKER

BOOTH OPERATOR

t east 60 gpm through CSlP

Ne 23 of25

SCENARIO#l

NUXEG-IUZI, Revision9, kfl

Appendix 1)

Required Opmtor Actions

FOKM ES-D-2

SCENARIO NIJMWER

I

CRITICAL TASKS

FACILITY:

Harris

CRITICAL TASKS INSCENARIO 1

the following:

CRITKALSTEP TOPREVENTPLANT TRIPASA RESULT OFKIGH-

HIGH SG LE VEL.

contact orreport to Control Room

Place applicable Fcedwatcr Rcgulmor Valve (I'K-4R8) hi MANIlAl.

Maintain Steam Generator levels between 52 and 62% (REDUCE FW

FLOW)

- f l M M E D l ~ 4

TE ACTION) Deteimines ,actor

is not tripped and directs operator to

. ~ ~ _ ~ ~ ~ .

TO DIRE'CTA I.OC.4L REACTQR TRIP TOADD

NEGATIVE REACTIVITY TO CORE.

___

Isolates SG ' C

a

Verifies PORV closed

e

Verifies FW Isolation closed

e

Verifies AFW imlated to SG

e

Closes r h m supplgto TDAFW Pump

-

Verifies before scat drain isolation closed

-

Verifies SG blowdown isolation closed

-

Vcrifies steam analvzer isolation dosed

, - ~

~

~~~

~

Verifies chemical addition isolations closed

I'OISOLATESG 'C'PRIOR TOEXITING FRP-SI Til

I MI!VlMlZE PRE.SSLIRE RISE INSIDE CONTAIh'MENT,

...~

....

~

-_

R O

Determines SI'I'ern:inathn Criteria arc met

s

Subcooling (Z 40°F)

Hent Sink(SG level > 40%)

-

KCS Pressure (stable I increasing)

Page t5 of25

SCENARIO Jil

WREG-1021, Revision9,Dnft

Ths unit is zt 16% power at MUI,, 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months following a reactor startup. 'h

plant nipped

approximately 20 liotirs ago (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months before startup).

Boron concentration is 1 866 ppm. Rank D rods are at j OS steps.

Ai:W Punip 'A' was takdii ntif of senice 2 hwrs ago for oii replacement duc to contaminant8 and

is cxpccted IO be rerliined tQ sewice within the x x t 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . Technical Specification 3.9.1.2 has

been entered. Ri& level is YlII.I.C)W

The Hot Slanpushhutton on the MSRs was depressed I hour ago

PMs WCIO perforniod on Condensate Booxter Pump B and have been completed, The pump is

ready to bc placcd in service. An Auxiliary Operator is standing by to start the Condensate

Rooster Pump. All prestart checks to daltthe pump arc complete.

Shift orders are to place Condensate Booster Pump LI in service and continue the power ramp I o

909; powrr and restore AFW Pump 'A' to service when it bcconiss available.

W - O O S is king performed per Step 5.0.1 IS.

0%-PI is not available

4 010102

5 010102

6 0lO102

7 010102

R 0101@2

xi 010102

I1 010102

I3 010102

I4 OlOi02

15 010i02

16 010:02

17 010102

18 0lOI02

I.?

0lDiC2

20 nioxcli

21 010i@2

22 nieinz

13 nicnc;1

Y nioim

12 nioinz

M 010102

25 010102

26 OXliOZ

27 u1011'2

P 1111)102

30 OL0102

31 010102

2 om102

1s.n

21.0

18.0

24.0

27.0

30.0

33.0

s.0

39.0

45.0

51.0

54.0

57.0

64.0

63.0

66. fl

R . O

78.0

81.0

84.0

R4.0

90.0

93.0

96. a

100.0

Xa.2

100.0

42.0

48.0

69.0

35.11

0

n

0

ZB

33

31

3L

2s

27

P

42

27

2u

m

Iti

P

19

6

I I

6

3

0

25

I ?

1

n

171

II

Q1

60

19

G

0

(I

0

U

0

a

n

0

52

49

n

0

285

952

n

1:5

m

121

124

I27

122

137

141

145

I48

5.2

5.8

6.3

6.6

6.9

7.2

7.5

S.8

8.1

8.4

8.1

9.0

9.4

9.7

io.0

10.1

10.3

10.5

10.4

10.5

10.2

lU.0

ln.7

11.5

eZ.0

11.6

9.3

6.8

-3.1

-3.2

-3.3

-3.4

-2.5

-3.6

-3.9

-3.7'

-3.7

-3.6

-3.5

-3.4

-3.2

-2.1

-2.9

-2.7

-2.4

-2.2

8 9

-1.5

-1.2

-0.9

-0.5

2.1

5.3

-0.2

0.99491

0.93498

0.9949i

0.YY49i

O.Og4Y 1

n.wz

0.99491

0.941%

n.wm

n.mgi

0,994'11

0.934%

0.99491

0. W491

0.Y9401

0. 59491

1;. 9749 I

0.9949'1

0.594991

n.93ps

0.99490

U.'IY49O

0.99491

0.88491

0.99491

Q.99492

0.99490

n.wm

~4ppendix 9

Simulator Scenario Outline

FORM BS-i-I

Facility:

HANRBS

Scenario Number:

2

Qp-Tcst Number:

1

-.

Examiners

Operators

Psge I Of 19

SCENARIO U?

NURF.(i-IO?I. ReVisiun 9, Draft

A'CTKON DGRIVG INITIAL

(N)nrmnl, (R)eactiviIy, (I)nshurnent, (C)nmponent, (Wnjor

SCENARIO#I

Appendix D

Keqlured Operator Actions

FORM ES-D3

SCENARIONUMHER 2

EVENT NUMBER:

2

FACILITY:

l a d s

EVIWr DESCRIPTlOK:

LT-IlZ,VCT Level, High Failure

(TRG EZ)lCORI.T:11? ( m w O Q ) 1000

ailable

.tennines LK-I I2 output lm failed

r VCT leyel using either:

.

. ~.

~I

TINI!OUS ACTION) Maintain VCT level above 5% autos

COMMENTS:

Page 4 of 10

SCENAKIONIIMBER 2

EVENTNLIMBER:

2

FRCIIJTY:

Harris

EVENT DESCRIPTION:

LT-II2,VCT !&vel, High Failure (CONTINUED)

-

Appendix I)

Required Operator Artiona

FORh4 FS-D-2

.....

FACILITY

llorrir

--..-_.

SCFN\\RIO Ut. ! d l k K .

i

EVtN'I NI:MBEK:

?

C \\'LS I' UESCRI PT!lji:

_..-

I h p p e d Control Rod F2

alarming

AI Fl-013-4-5. POWER RANGE CHANNU. DEVIATION, alarmink?

a

ALB-013-5-3; POWER RANGE IJPPEK DETECTOR HIGH FLUX-UEV OR

AlJ1O I:)EFE.AS, alarming

AI,B-013-5-4. POWER RANGE LOWER DETECTORHIGH FLIJX DEV

OR AtJTO DEFEAT, ahming

A1.B-013-1.4, ONE ROD AT BOlTOM. alarming

ALB-013-8.1. RANK D F7lLL ROD WITHDRAWAL, alsrming

AL.13-0(3-8-5, COMPUTER ALARM ROD DEViSEy t 4 S PWR RANGE

'TILTS, alarming

Contml rods semina out until C-l 1 interlock

e

D

w . RCS temperature decreasing

.. -

9

Enters and directs the actions of AOP-00 I, Malfunction of Rod Cuntrd and

DRPl indicates Rod F2 drop&

___

Go To Section 3.1. Dronncd Cuntrol Rod

Record the time at whic.h the rod dropped

Adjust m e of the fullowing to equalize Tavy with Tret

-

Turbine load mine OP-131.0I.A0!'-038.

orGI'-'-006

nommal operation, as fi)llows

NO Blowtl fuses

Power and Loeic Cabinets

COMMEY I'S

SCENARIO b2

NIIRW-lO?l, Revwon 9, Lhfl

Page 6 of 19

Amrndix D

Remind Operator Actions

FORM ES-D-2

SRO

0

e

3 2 ! , Axial Flux Difference

0

Notify thc following:

Manager -0pcrations

3.1.1.1, Hriraiiun Control -Shutdown Margin -Modes :C 2

3.1.3.1. Movable Control Assemblies -Group Height

3.1.3.5, Shutdown Kod Insmion Limit

1. I .3.6, Control Rod lnreltion : h i t s

3.2.4, Quadrant Power Tilt Ratio

I

i Dop I Reset any negative rate trip alarm attht NIS cabiosts

COMMENI'S:

P U * ~ ? 7 f I Y

SCENARIO c2

NIJREG-1021,

Kevisiun 9.1haR

--

Awcndix I1

Required Operator Actions

FORM ES-D-2

Direct the actions of AOP-038, "Rqid Downpower" after

IO onnwfor dropped rad recovev

_I

Criteria using A t l a c m , !

.

. .

Notify Load Dispatrltrr that the Unit is Educing load

Dcteminc reouired boric acid addition for desired ooww rrductbn usim

.

requirenients due to bratian-

Check that a planned load duction will NOT take thc Unit to Turbine shutdown

__I-

~~

netennine react(n power change will NOT exc&

15% in il one hour p i a l

Dirccts Tavg-lkf maintilined within f 2-F

Check Kod Ccnbol in NOT in AITIY) and maintains Tavg-Trefwithin t 2'F

~~

_.__I..__.

-__

~ Ene.min dl svailahle PRZ Backup hentors

. .~

Direct A 0 to go to letmination Cabinet Room to check VIDAM

Depress the Load Kate M W M N pushbutton

Enter desired rate in DEMAND display

Depress EXIER pushbutton

e

Deprcss KEF pushbutton

e

Ikprcss EKTOR pushhutton

Enter desired load in DEMAND display

Check 1101.D pushbutton 1.1 P

COMMENTS :

Page 8 of 15'

SCENARlOf2

NCREG-1024, Revision 9, DruIi

Appendix D

Kequized Operator Actions

FORM ES-D-2

SCENARIO NUMBEK: 2

WENT NUMBEK:

4 / 5

FACILITY

Harrir

EVENT DESCRIPTION:

Puwer Reduction (Continued) I Bode Acid Pump Tdp

TRG E4 IMT CVC23A

Harrir

on (Continued) I Bode Acid Pumo T ~ D

. .

TRG E4 IMT CVC%A-

Insertion Litnil_,

AI,i3-006-8-4, BONC ACID FLOW I>EVIATION, alarming

Boric Acid Pump A-SA tripped

RCS tcmpemturo NOT responding

~ - -

A'OTE: ALB-1106-84 WILL QNLYEE INANAL4RMSODDITION~F THE

BQRATION IS PERFORMED USlh'G NORMAL BQRATlOn: RAPID

EQRAT~~NWPLLNOTRESULTIN

THISALARM WHENTHE PUMP

I I

SRO

I

I Drrcts RO to start standby boric acid pump to allow continuing boration

--

s W

R

~

guidelines

ch ail operator tn open 3A and

,el at the target value

COMMbNTS

rage 9 of 19

SCENARIO #2

NURFfi-IMI, RevislonY,htl

I_

___

-

Amendix O

Required Operator Actions

FORM ES-D-2

SCEN.4RIO NUMRER 2

EVENTNUMBER:

6

FACILITY:

Harris

EVENT DESCRIPTION:

Losa of Power to an ESP Bus with Failureof ED(: to toad

(TRti E5) IMF EPSOSA

IMF nuitri .I

.....

__.

.

APPIJCANTS ACTIONS OR WHAVIOK

, I m s of One Emergency AC Bus

3.6.5 V

m

Relief System

.

3.8.1.1 AC SourcesOpcrating

3.8.3.1 Onsite Power Distribution -Operating

Page IO of 19

SCENARIO U2

NUREG-1021, Xcvision 9, DraR

Appclldlx D

Requircd Operator Actions

FORM ES-D-2

XENARIONUMBEX: 2

EVENS NI!MREK:

6

FACILITY:

Harris

EVENT DF.SC.RlPTIOK:

LQW ofPowerto an ESF 5s with Fsilurc ofEDG to Loa&

(CONTIWED)

I

y Charging and Lctdown flow per OP-107

Directs sccuring or azknowledgenreourine TDAFW Pump hy

lI>hF\\V Pump by closing IMS-40

COMMENTS:

Page I I of 19

SCENARIO nz

Appendix D

Required Operator Actions

FORM ES-DZ

SCENARIO 3UMRE.K: 2

EVENT NUMBER:

7

FACILITY: Nards

EVENI DESCRIPlION:

Second Dropped Contml Rod K14/ Reactor Tnp

TUG E6 IMF CRFOjB 2 23

ALB-0 13-7-3. TWO OR MORE RODS AT BOTTOM, alanniny

OR WHEN SECOND DROPPED

~~~

. Trip breaken KTA and BYA - Ope11

Trip breakers RTB and BYR .- open

I

I, Rod hottorn lights - no( available due to loss of power

D

Check bus voltages

Check 6.9 KV bus IA-SA breakers -wen

COMMWTS:

Page 12 of I 9

SCENARiO #2

NIIREG-IC21, Revision 9, DmA

FORM ES-D-2

Appendix 5

Required Operator Actions

SC:ENARIO NIJMUEK: 2

EVENTILIJMBEK:

4

FACILITY:

Harris

EVENT DESCKIPTION:

Second Dropped Control Rod K14 /Reactor Trip (CONlINUED)

. A m - I 1-2-2

ALR-11-5-1

. ALN-I 1-5-3

SI Actuated bpass permissive iighl

Page 13 or I9

SCENARIO P2

NUREGI021, Revision 9, Draft

Appendix D

Required Opcratur Adianr

FORM ES-0-2

--

Page 14 of19

SCENARIO #Z

NUREG-IO21. Revirion 9. Drafl

Required Operator Actions

FORM PS-D-2

Appeiidix D

EVENr NGMBER:

R

FACILITY.

liarpis

SCENARIONUMBER 2

EVEN1 DESCRIPTION:

Pressurizer Steam SpeceBreakl Single Train SI (CONT!NUF:D)

COMMENTS:

Pase IS of 19

SCEAARlCdZ

NIIREG- 1021, Revision 9, Drafl

Awendrx L)

Rwoired Overator Actions

FORM ESD-2

SCENARIO NIJMBEK: 2

EVENT NUMBER

8 / 9

FACYLITY:

Harris

EVEN! DESCRIPTION:

Pressurizer Steam Space Break I Single Train SI (CONTINUEIEP))

MS IntermediateRange Compensating Voltage Low, Failore

KlS COMP VOLT FAILURF. blitiated in CAEP

COMMENTS:

Paga 16 of 19

SCENARIO#

NUREGI02:. KennonY, Dnfl

Appcndix D

Required Operator Actions

FORM PS-D3

SCENAKIONUMBER: 2

EVENTNYMRER

S

FACILITY:

Harris

EVENY UESCKIPYION:

Presssriz@r Steam Space Breek/ Singlelrain $1 (CONTlNWO)

rifv Auriliarv and Radwastc hoocessinc Liuildinr Radiution iinrmal

COMMENTS:

Page 1:

of 19

SCENARIO n2

NlJREG- 1021, Re~ision9, haft

Appendix D

Required Operator Actions

FORM FS-D-2

SCEiXAKIO NUMBER: 2

EVENT NJMRER

I O

FACILITY:

Harris

EVENT DESCRIPTION:

Ckwsifies the Event

'ITME I POSITION 1

APPLICANT'S ACI'IONS OR BEHAVIOR

SCENARIO#2

NIJREG-102I.

Revision 9, I h R

Appendix D

Required Operator Actions

FOXM E§-D-2

SCENARIONCMUER: 2

CKITICAI. 'TASKS

FACILITY:

Harris

CRITICAL TASKS IN SCENARIO2

..

,STEP TO TMP REACTOR WHEN SECOND DROPPED ROD

Trips RCPs when RCS-pirssure decreases below 1400 psig afrer verifying SI tlow

C) TRIP RCPs WMFA 'TRIP CRBlERIA MET.

Pagt I 9 of 19

SCENARIO 112

The unit is at 100%powcr at ROL, with equilibriumxenon conditions

Buron concentration is 1238 ppm. Bank D rods are at 2 I5 steps

APW Pump 'A'war taken out ofsc-cc

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago for oil rcplscenient due lo contaminants and

is expcctedtn be returned to sewiccwithin the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . Technical Specification 1.7.1.2 has

been entered. Risk level isYEiLOW,

IIDP 'A' was tagged out of service 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ago for bearing replacenlent and is not expected back

forthe next several days.

Shift orders are to maintain power at 100% and restore AFW Pump 'A' to selvice when it

becomes available. GP-005 was completed prim to removing HDP 'A' h i n service. The plmt

has been stuble for 3 weeks.

C)SI-PI is oot available

SCPNARIO #2

Appmdix D

Simulator Scenario Outline

FORM ES-D-I

Facility:

HARRIS

Scenario Number:

3

Op-lest Nllrnbrr:

1

Examiners

OQ'

rrdtnrs

'

Initial Conditions: Reset to saved IC-Io0 (bnsed on IC-] X): 1000iooower BOL:

Power lowered hy 25 MWe and increased boron eoacentmtion by 2 ppm: Allowed

plant to stabilize.

EVENT 7 - Failure ofMSlV on Ruptured Si; to close - can he clnsed locally

(MSS-5C 2)

E V X W 8 - Partial failurr of Automatic Phase A isolation signal (Train II Phase A

Slave Relay for select CNMT Phase A valves fails to energize when required). ISH-

287, ICs-l I 8 !SW-242

(ZWXc62213 Deenergire)

e

The unit is at appmxiinatcly 99". power at Il3L. with equilibrium xenon conditions.

Boron cuncajtration is 12iBppin. Bank 1) rods are at 215 steps

AFW Pump 'A'was taken nut of service 2 honrs ago for oil replacement due to

contaminants and is exprcted to be returned In service within the ncxt 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . Technica

Sprc,ification 3.7.1.2 has been entered. Risk level is YEI.LOW.

IlDP 'A' was tagged out of sesviee 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ago for bearing replaccrnent and is not

expectedbnck for the mxt seueral days.

Shift orders are tn maintain current powcr level and restore AFW Pump

wwice

when it hecomes available. GP-005 was compietedpriur to removing HDP 'A'from

servicc. The plant llad been ntahlr for 3 reeks prior tu removing the Heater Drain Pump

from service

0 3 - P I is not available

Page 1 of22

NiJREG-1021, Revision 0

0

I l e O 6 . 4 *

[COR FT477

(TRG E4)

---+--

IMFCRF 148

(TRG E4)

C (BOP

C (SRO

C: (RO)

c m a

-

I (BOP)

I (SRO)

C (BOP

c (SRO

R (KO)

--

Main Generator Oscillations

___-

Heater Drain Pump Tripwitb Fail

Automatically Runhack

Auto Rod Failure - Rods Fail To Mow

NOTE: MULTIPLEE VENTS Oh' TRIGGER 4.

iVOTE: INSER TMALFUNCTIO.h'DL?RLVGlNlT~.4L

@)mal, (Rpactivity, Ojnstrument, (C)omponent, (u)ajor

Page 2 of 22

SCENARIC#3

NUREG-1021, Revision9

Appendix 1)

Kequircd Operator Actions

FORM ES-D-2

SCENhMIONUMBER: 3

EVEiWNCMBER:

I

FACILITY:

Harris

EVEN i DESCRIPTION.

Mdn Generator Oscillations

clears, then a l m s again and clears as Generator Voltage exceeds high aid 1

alarm fietpoiat s-hile oa4lntii:g

I._..._..__

_.

~-ALB-lIZ2-9-4

__.___

is JlidI56XA in Group 2 :sing one of the following:

..-__lll

ator voltage mid Mvar indications

SH ERFIS Group Display GENRION. GENMON!. or

~~.__.....-._~I__._

568A GEN GKDSS REACTWE POWER,

may indicate an impending or achlal gcneralor voltage regulator failure

.-

__

-

mprvogage ~-

Places piirrator voltage replalor in nliiniial and adjusts for pmwr voltage

Place the regulator in TEST

Operate CiENBKATOR UASE ADIliSTEX switch to r e s t ~ c Genoraator voltage

-P-T

tu 22KV

Appendix D

Required Overator Actions

FORM ES-D-2

SCENARIO NUMBER: 3

EVEKT N 6 k 3 k R :

2

FACILITY:

Harris

EVENT DESCRIPTION:

Operating CCW Pump Trip with failure or standby pump kti

asltornstifsIly start

( ~ ~ t i m i ~ ~ t ' ~ c w o 4 i o n

IMI: CCWMl A

automatic start

0

Ntimrmr alarms on ALB-005 due to no CCW flor

Breaker indication on CCW Pumo IA-SA

I

R O

1 Check CCW header oressure male1 than 52 D R I ~

I

COMMENTS,

Page 4 of22

SCEN.ARIOU2

KIJREO IOZI. Revision 9

Appendix D

Requircd Operator Actions

FORM ES-I)-?

SCENARIO NUMBER: 3

EVENT N1 IMBER

3

FACILITY:

Harris

HOI'

APPl II'ANT'S ACTIOVS OR BEHAVIOR

Diagnosr low failurc of controlling SG 'A'fcod flow channcl

o

D

FI-477 indicating 5

e

Xi 'A' Icwl decreasing

Enter and alircct the actions of AOP-01 0, ?c.edwxer Malfunctions

(IMMELXATE ACTION) Check NO Main Feedwater Yliinp tripped

rake8 MANUAL control of FK-478 prior to direction in AOP-010 tu f e d per

K-Ol)linsUuctions

Chcck DEH controlling Turbinc Valvcs properly

Maintain all of the following:

B

At lcast one Main Feedwater Pump sunning

a

Main Feedwater flow to all Steam Generattors

B

ALL Stem Cicnemt:Llovclr

rreaterthan 319b

Check Feedwater Kcgulatoi Valves NO1 operating properly in AUTO and perl'vrm

the following:

D

1

CRITICAL STEP TO PWEVEYF PLAXT TWY AS A RESULT OF

lheck W i n Control Room annunciators avnilablc

Check the following Punip mbs:

SG A STM > FW FLOW MISMATCH (A1.B-0144-1 B) alarming

SG 'A'feed rcg ~ d v e

cinaing

a

SG ' K a e feed flow=

!ow... -

..

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

. .-

___II_.

__

___.

~.

._.._.^_____._I___-

......

..

~'IIICE appljuuhls Feedwater Kepulator Valve ( F K - U X ) in MANIIAI.

Maintain Stearnncnerator levekbetween 52 and 625 Wl>LXX FW FLOW)

LQWSG I.EVEI..

......... -

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

N C Feedwater Train Pumps tripped

a

only m e l.ll>P operating

COMMENTS:

Page 5 of 22

SCtUARIOA3

NUREti-lli21. Revision9

FOKM ES-D-2

Aooeudh n

ResnimJ Ooerator Actions

3

EVENT NI!MBER

3

FACILITY:

Harris

i:

Feed Water Flow Low FaiIure(CQNT1NUED)

NOTE: E VEX THOUGH DNLY ONE HDP IS OPEMTrNG, THE CREW

,siiOuw GO TO SECTION 3.1 IroR THE FAILURE OF THE FEED FLOW

TRANSMITTER.

Go to the applicahlc soction

e

Ckck the following Kscirc and Dump Valves operating proprly in MODU:

Main Feedwater Pumps

Candensate Pumps

ICE-293. Condensate Kecirc

-.

a

ICli-142. Condensate Dump ToCST b&tion Valve

Check the Condensate nnd Feedwater System intact

All Con&nsate/Fe.edwater flow ri?alftrnclions (other lhan pump trips! Section

3. I

..

I

--

Condensate BmSter PUInpS

__I_._

~.___

_.

-.

.I_

Check pumps for noms1 operation

Notify Load Dispatcher of any Ihad limitiilions

Check Reactor thermal power changed hy less than 1.5% in any one I~our period

--

-.

Exit AOP-0 10

Refer to ORP-RFWX for SG Afced flow failure SF/W 1.

I___

OWP-KP-OR

Selects Channel 47.5 on FS-47XL for steam flow control in accordance with

OP-RPa*

. __

Referr to TS 3.3. I (Item 14)- 6 huur requirement lo trip histnhlur

Kestores Fced Reg Valve controller to AUTO when lcrel stable at program wit

nd steam flow mkhed

COMMENTS:

~

P ~ g e

6 cf 22

SCENARIO f 3

NL;RE<;-III21. Revision 9

Appendix D

Required Operator Actions

FORM ES-D-2

SC:ENARIONIJMBER: 3

EVENTNUMRER:

41 S

FACILI'I'Y:

Hsrsis

EVENT DESCRIPTION:

lkdter Drain Pump Trip with Failure of 'Turbine to Audumatknlly

Runbaek and Failweof Auto Rod Contrul

CUE

Diagnoses trip of Heater Drain Pump '3'

a

ALB-019-3-2A, HTR DXPi PlJRlP B O K TRIP-GND, alarming

ALB-U1944A, CND BSlK PVMP .4 SUCT LOW I'RESS. alarming

AI.B-019-5-4A. CND BS'TR PUMP B SIJCT i.OW PKESS, alarming

SG levels decnasinx

I

8QP

I fIMMkDIATE ACTII"

Check NO Main Feedwater Puim trinxd

.

, I

....

.-I

.__._I

1

T

F

-

F

Maintain all Q f the following:

Turbine Valves properly

At Iemt one Main FeedGater Pump running

Main Feedwater tlow to nil Steam Generators

... ALL Stcam ( i c n e r a t o r ! 4 8 f e ? ! e r t ~ a ~ O ~

Clreck Main Control Rwin annunciators available

Check the following Pump status:

NO Feedwater ?rain Pumps tripped

_f-E5?!!LEK!

hipped

....

Go tu the applicablc section:

0

Maintain 811 of the following:

0

9

0

I.oss ....

oi Rnnniw'urnps (incldi&fiO.IH Heater Drain Pumps~Se+jon 7

2

At least one Main Feedrater Pump running

Main kzdwater flow to :ill Stcam fitnerators

tLLSteamGenemtor levels grcatrr than 308

Appendix D

Required Operator Actions

1:ORM ES-D-2

SCtN.4RIO NL'MI3I.9 3

F.\\'FNl NUMBER

4 / 5

FAC'ILll'Y.

Harris

~~~~~~~~

~~

~~~

EVENT DESCRIPTION

Heater Drain &nip Trip with Failure- of Turbine to Ant~matis5lly

.....

Pump Kecirc Valves 'Tiippe,pe? Ump .

..

Check both Heater Drain I'umm trioord

~

I

BOP

I Commence load reduction to meet "bine one ofthe follouine

I

COMMENTS:

Page @of 22

NURL:Ci-1021 Revision !I

Appendix D

Krqiiircd Oporator Action,

FORM ES-D-2

..

SCENARIONlJ.MBER: 3

EVENT NIJMBER:

4 I 5

FACILITY:

Harris

EVEKT DESCRIPTION:

Heater Drain Pump Trip with Paililre of Turbbjne to Automabically

Runbark and Failure of AMfQ Rod Control (C0NTENIJF.D)

Notify Load Dispatcher thaf the Cnit is reducing load

Determine, required horic acid addition for desired power reduction using

~-

waste Control Room to he prepared for thz increased water processing

a piannsd load reduction wil! NOT take the ::nil

to Turbine shutdown

tsdwc.to.boration

~

__

..... ~-

-

y Chcmishy that Reactor power chxigc will e x c d 15%m a cine hour period

-

....

--

all available PW,

Backup heaters

_I___

~

h c k the DEH System in AUTO.

-

~

____

Perfonn the following at the DEE panel:

D

0

lkpreas EWER puahbunm

Depress REF pushhlrnon

Enter desired load in I)HMANl> display

e

Depress E:NTE:R pushhvttnn

Check HOLD pushbvnon lit

Direct A 0 w go IO

'Termination Cabinct Room IO check VIUAR

Deprcss thc Load Rate MWIMIN pushbutton

M e r desired rate (NOT to exceed 4.3 MWf!vllN) in DEMAND display

COMMENTS:

Page 9 of 22

SCENARIO #3

Appendix D

Required OpsrdtOr Actions

FORM ES-D-2

SCENARIONUMBER: 3

EVENTNCMBER:

4 I5

FACILITY:

Ilarsis

EVENT DESCRIPTIOIZ:

Heater Drain h m p Trip 6th Faillired Tlsrbine to Autnmaticdiy

Runback and Fsifure d

Auto Rod Controt (CONTINUKD)

mctive load (VAKs) within guiddincr

COMMENTS:

Page IO of 22

SCBNARIOX?

NUHRC-IIIZL.

Reviiicin 9

4ppendix I>

Required Operator Actions

FORMES-D-2

SCENARIONUMBER: 3

EVEhT NUMBER:

4 / 5

FACILITY.

Harris

EVENT DESCRIPTIOK.

Heater Drain Ponip Trip with Failureof Turbineto Automatkdly

Boratc or dilute as necessary to rnamwin AFD iCuwe F-X-21 as close to the m'sl -

value as possilrle while maintaining r d s above the Rod Insertion Limit (Corvel;

Notify the Lmd Dispatcher that power reduction iscomplete

Retuns to ADP-OIU

D

MSR Relief Valves

~..._...._._~-__.._I

~ _.__

__I

~-

I tu check the following seated, observing tailpips:

. ..

&endint: to bemeen 71% slld 96%.

"

Reset Loss of Load interlwks C7A and C7B

Xotify Load Dispatcher of any load limitations

Check Ractorlhermal ~ o w e ~

chanerd by less thm 15% in a n ~

one how oerind

_____

.

~

_

.

~ - ~..

SRO

.. -

~

.~

~~~ ........

~

tion, check control rods above inseltion limits

____

___

COMMENTS:

rage I I or22

SCENhRlOY3

NIIREG-IIEI. Rcrision 9

Apwndin I)

Required Operator Actions

L'OKM ES-D-?

. . . . . . . .

FACILITY:

Harris

_

. . . . . . . . . .

CC'CNT N'IJMIWR

4

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

SCENA.RIONll\\IFJEK. 3

~

~~~~

EVENT DESCRIPTION:

Pressurizer Pressure High Failure

(TKGES I C O R ~ I Y ~ ~

m n e n n)2500 iron

APPLICANT'S ACTIONS O R BEHAVIOR

Diagnoses high failure of Pressurizer Pressurc channel P

4

e PKESSURIZER HIGH PRESS DEVIATION CONTROL (ALB-0%-3-1).

- --

I?-

alarming

PRESSURIZER RELIEF DISCHARGE HIGH TEMP(ALB-M)9-8-2).

alarming

PRESSURIZER HIGH-LOU' PRESS (.4LB-00%.5-lj. alarming

PRF.SS:'RIJER

RELIEF TANK HIGH-LOU' LEVEL., PRESS OR TAMP

(ALB-009-8-I), akrniing

o

D

s PRZ heaters o t i

-

PWI sprnys open

B

PR' PORV 4448 rnomeiitarily open

D

PKL pressure lowerine. m o ~ ~ h ~ M . e l s

h t e m and directs the actions of BOP-01 7, Malfunction of KCS Ikssun Connoi

(IMMEDIATEACTION) Check that a kuhhie exists in the PRL

[IMMEDIATE ACTION) Venfics proper operation of PKZ PORVs AND

ysiated block valves by closing POKvJg&.--

'IMMEDIATE ACTION) 'lakes manual cmml CC pressurizer pressure by either:

b

iecs Rx Trip limits for high and low pressure

io TO Section 3.1, Pressure Control Malfunctions While Operating With a

donitor PKZ pressure by observing othcr reliable indication

_'heck plsnt in MODE I OR 2

heck PKZ prcsrure controlled

CONTINIJOUS ACTION) Check PK'

pressure 7335l'SIG OK I.ESS

.

I

._

.._I_

Piacing martercontmllcr P K U A in manual, or

b ._ Placing heasztad-pmy valves in.&-

'ressunzcr

___

Bubble

.-

__

I_-.._.

~

__I..

._l_li__

. .~____...._.....I_.

__

COMMENTS:

NIlKlG.lOZI. Revmion4

Page I ? "f 22

SCENARIO X 3

Amendm B

Required Operator Act~oni

MRM ES-U-2

SCENARIO NIJMBER 3

EVENT NUMBER:

6

FACILITY:

Aarrjs

.......

EVENT DESCRPPTION

Pressurizer Pressore Isg Failure (COKTlNUEW)

fiutction of I T 4 4 4 has occurrcd

~

_

I

_

.

.....

pressure as follows:

0

D

Adjorr PK444A oulpol as necessary, to attempt to restore arid maintain PW.

Check both PRZ spray Y R ~ V C ~ ~ n t r ~ l l c n

in AIITC) and both spray valves

operating as desired

Check dl PKZ heaters operatingapdesid

.heck both of the following conditions prment:

e

PRZ nressum is controlled

..

...

. .

..

_

I

.

.-

.

....

..........

COMMENTS:

Required Operator Actions

FORM ES-D-2

Appendix D

SCEKARIO NUMHEK: 3

EVENT NUMBEK:

7

FACLITY:

Earris

~~

EVENT DESCRIPTION:

SG Tube Rupture

NOTE: MAYMAKEAl7XMPTS TO

EXCESSIVE PRIMARY PIANT LEA

THAT LEAKAGE IS lh EXCESS OF

Neutron flux decma:i&

[IMMEDIATE AC1ION)Verify Turbine Trip

0

(IMMHUIATE ACTIOY) Verify Ponser To AC Emergency Buses

Trip breakers RTA arid RYA -open

Trip breakem RTB and BYH -opeii

Rod b o r n Iights - lil

~

~~

~

~~ .~

All turbine throttle valves -,shut

All turbine governor valves T shut

..__

Check AC emergency buses IA-SA and 15-SB -energired by offsitr pvwer ur

COMMENTS:

Inpe 14 of22

SCENARlOWl

NIJRF.C-IO2I. Keviriun Y

Appendix D

Required Opsnror Actioiir

FORM ES-D-2

SCENAKIONUMHEII: 1

EVENT NIJHREK:

7 / 9

FACILITY:

Harris

EVENT U1;SCKIPTih)N:

SG 'Tube Rupture (CONTINUED)

PurUnI Failure nf Automatic Phase A Isolation Signal

__

....

___..,'..-~_._I__.

CS pressure > 230 psig

Steam Isolation NOT actuated, iiOR r

._ .. .

COMMENTS:

Auvendix Y

Required Owrator Actions

K)KRI E;S-D-2

SCEKARIO NIIMBER: 3

EVENT NUMBER:

7 I 8

FACI1,ITY:

llarpis

E V E N DESCRIPTION:

SG Tube Rupture (CONTINUED)

F~Nuw

or MSIV on Roptured SG to Close

I ISOLATE POTENTIAL RELEASE PATH.

COMMENTS:

eaEc i o 0 m

SCb.NAKIO#?

NLIKEG- I02 I, Kovlsion 9

Appendix D

Required Opemtur Actions

FORM m-n-2

SCENARIO NUMBER: 3

EVENT NUMBER.

7 I 9

FACILITY:

Harris

I 0

Shut all remaininr Main Steam Isoistim valves and hyn~sses

I

. .

SIVs AND PLACE

IN OFF/ RESET TO

~.

.

_ -

_I .-

...

.

condenserNOT available

.itnun rase using SG POI1Vs .

-n Cole Exit Temperatures are less than target temperature

Maintain CETs less than target temperature

h o e recovery actions during cooldawn

<

Slop thc RCS cooldmrn

--

......

~

ainmin KCPseal injection hetween 8 m'd 13 gpn

I_

~-

Control feed I~CW to maintain SG '.4'and

'R' levels hetween 25% and SO%

COMMENTS:

SCEXARIOH3

NlJRF~~~-Ili21,

Kerision 9

ripe 1 7 o f 2 2

w---t--

-1

Page 18 or 22

SCENARIO #3

NlIRliG-II121. Revision4

Appendix I)

Required Operator .4ctiions

FORM PS-n-2

SCENARIONUMBER: 3

EVENT NUMBER.

7

FACILITY:

Harris

EVEN1 DESCRIPTION:

SG Tube Ruptwre (CONTINUED)

. PKZ. level > 759%

e ANDPRZ level > In%

HAS BEEK COMPLETED.

COMMENTS.

Pape 19 "fa2

Appendix D

Required Operator Actions

FORM ES-D.2

SCENARIO NUMBER: 3

EVENT NUMBER:

9

FACIL.ITY: Hsrris

SCENARIO n3

Apwndix D

Required Owrator Actions

FURM BS-D-2

~~

~~~

SCENARIO NUMBER: 3

CRITICAL TASKS

FACIIJTY:

Harris

CRITICAL TASKS 1% SCEKARIQ 3

the following:

0

Place Gppk!ahk Feedwater Rogulator Valvc (FK-498) in MANUAL

Maintain StearnCencrator levels be!ween 52 and 62% (REDUCE FU' FLOW,

CRITICALSTEP TOPRI3WiNTPIANT TRIPAS A REW1.T OF HIGiI-

.?fIGJf SG @E.E.-p..~

__

Yctonnines the idlowins Phase A valves failed to close and wanudlv closes then

.

0

151-287, ACCLIMU'LATORS & PRZPOKV Ei2 SlJPPLY

ICs-I 1 , LTDN ISOL V1.V

0

e

Adjust ruptured SG 'c' I'OKV controller tn HXB and verify proper operation

Shut faulted SG 'c' steam supply valve, INS-72, to TDAFW puinp ( m y haw

been pzrformed earlier fur RCS trmpcrature control)

Verify SG hlowdown isnlation valves sliat

Verify SG 'c'

Main Steam Drain isolation valves shut

Verify s%TICAL

7QlSOLATESTEAM SUPPLY TO TDAFW' PUMP Til ISOLATE

eaTEN-Ei.EASEPdTY_.

-

Deterniines X i 'C' Main Stcam Isolation vabe failcd tn shut

3

9
Shut ail remaining Main Steam IsolatWn valves and bypasses
Place hoth Steam Dump interlock switches to OFF i RESET
Else intact SO W)RSa for all fimher steam dumping
Direct operator to locally isolate SG 'C' wing PAIH-? Guide, Attachment I
Page 2 1 of 22
NlJRl (ti. I O? 1 , Kcvision U
Required Oper3tar Actions
FORM ES-D-2
Appendix D
SCENARl0NUMBE.R 3
CRITICAL ACI'IONS
FACILITY:
Harris
CRITlC4L 'TASKS IN SCENARIO 3 (Continwd)
I
I
1 SECONUARY LEAKAGE.
PItgc 22 of 22
The unit is at appmiirnately 89% power at SOL. with equilibrium xenm conditions.
Boron concentration is 1238 ppm. Bank D sods nre at 215 steps.
AFW h m p Awns taken out of service 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago for oil replacement due to contaminants and i8
exlxctcd to k returned lo service within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . Technical Specification 3.7.1.2has been
altered. Risk level is YELLOW.
HD? .4ras tagged out of service3 hours ago for kanng rcpiwenxnl and is not expcctcd back for the
next several days.
Shift orders are to maintain current pawcr level and mtorc AIW Pump Atn Fewice when it becomes
availzhle, GP-005 was completed prior to removing HD? A from Service. lhc plant had k e n stable
for 3 wceks prior to removing the Ileater Drain Pump from service.
OSI-PI is not auailablc.

ML041130433

Text

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