EOPHP3'

CAROLINA.POWER & LIGHT COMPANY

SHEARON HARRIS NUCLEAR POWER PLANT

PLANT OPERATING MANUAL

VOLUME 3

PART'.

PROCEDURE'YPE':. EMERGENCY OPERATING PROCEDURE'EOP)

END PATH PROCEDURE (EPP)

NUMBER:, EOP-EPP- ~TITLE',

..e.'EACTOR, TRIP'ESPONSE

REVISION 0

APPROVED

SIGNATURE DATE

TITLE

POR A8~0SO~oi0~ 8~0„F OOC~ 0~000+00

428PDR

Page 1 of 13I

PATH-1 44r 4

A.C IArl IUI ~

~ ILi~tAs

vo oto ~IAL'lot autLLl~LL

44 L

rtLDOII A

IVWQV~o ~ IIVWWW IWI

W WVI OW WWO ~ W IBIJOU w vw'Io ~

~ WO W U U~ U iAO UO OVVOOVNO WV ~ V OOI IOh,~ V IW I ~ IIU

~ IVO V WWOI WOO

W 'U ~ U V U WW ~ QCWU It~ I ~

IILIKI/t~I

~ ~ IU IW N 'h WLOWWOVw AIL oo&~ w Iv Uw

TgrorttL

1tt. 'L4j

m%ÃLL

K-'IK

ALL~

47Ã

EN~M

o'LA+PA

ILSAL a

LO4

IO,or'ro

PT'K~:Qr

~ WWIIOWWIO OWO W IVO I I OVOIW OVO IWo~OWVU WO IW MI W IOW I I UO lt IUU IUO

~ ~

gOPHP3 0LIST OF EFFECTIVE PAGES

~Pa e Revision No.

1 through 13. 0

EOP-EPP-4 Rev; 0 Page 2 of 13

EOPHP3REACTOR TRIP RESPONSE

i31.0 PURPOSE~

~

~"

.This procedure provides the necessary instructions to stabilize and control the

plant folloving a reactor trip vithout k safety injection..

2.0 OPERATOR ACTIONS'.

CAUTION

If SI actuation.. occurs't= any. time, immediately go to PATH»l,, entry point A.

NOTE" Fo1dout= D should: be. open

EOP-EPP-4- Rev.. 0 Page 3 of l3

1

1 4

I

p -r

EOPHP3REACTOP, TRIP RESPONSE

- Instructions Res onse Not Obtained

1. Check RCS Temperature — STABLE

AT OR TRENDING TO 557F'F temperature less t

S

decreasing, THEN:

hen 557'F and

a. Stop- dumping-steam.

b IF'ooldown continues, THEN

contro3 total feed flow.Maintain total feed flow, greaterthan. 400 GPM or 192 KPPH untillevel greater than 10K in

at'east.

one S/G.

c: IF'ooldown: continues, THEN closeMSIVs and bypass valves.

IF: temperature. greater than 557'F and

increasing;, THEN:II

o 'ump steam to condenser.OR'

Dump steam. using S/0 PORVs.

EOP.-EPP-4 Rev.. 0. Page 4 of 13

~ ~

~ '

IC

EOPHP3REACTOR TRIP RESPONSE

Verify At Least One RCP - RUNNING Perform the following:

o Place steam dump in pressure

control mode.

o Dump steam to establish naturalcirculation.

3. Check Feed System Status:

a; Check. RCS'emperature: —LESS'HAN,

564'Fa- Continue. with step 4. WHEN RCS

temperature less than 564'F, THEN

do steps.3b and c.'

Verif'y. feed regul'ator va1ves:—CLOSED,

c.. EstabTfsh, FR'ypass EXo~ toS:/Gs

c. Establish; AFV'low to S'/Gs..

~P ~ e

EOP-EPP-4'ev, 0 Page 5 of 13

%I i+ t% ItR lt' l

~ 'U

EOPHP3REACTOR TRIP RESPONSE

4. Verify All Control Rods FullyInserted.

IF two or more control rods NOT fullyinserted, THEN emergency borate as

follows:

a. Start a boric acid pump.

b. Align boric acid to CSIP suction(listed in order of preference).

o Open 8104(Emergency'oration)

OR

o Open FCV-113A (Boric Acid toBlender) and..open FCV-113B

0 ~

(Blender Outlet to CSIP

suction)OR

Open. FCV-113K (Bpric Acid toBlender) and open FCV-1.14A

(Blender, Outlet to, VCT)

c;. Verify boric. acid. flow to CSIP~ suction;.

Verify CSIP flow to RCS.

EOP-EPP-4 Rev. 0 Page 6 of 13

~ ~

@type ~t aPk

.

'

~ 'OPHP3REACTOR TRIP RESPONSE

5. Check PZR Level Control: ,'

a., Level — GREATER THAN 17K a.. Perform „.. following:

1) Verify letdown isolation.

2) Verify PZR heaters secured.

3) Control charging to restorePZR level greater than- 17K.

b Ver'ify charging and. letdown.—IK SERVICE.

c.. Level —STABLE AT OR; TRENDING c., Control'harging and letdown toTO 25K maintain PZR level at 257.'.

6: Check PZR Pressure. ControT

a Pressure —GREATER THAN'881.

PSIG:

a Verify SI actuation. AND go toPATE-1:, entry- point A.

EOP-EPP-4- Rev 0 Page 7 of 13

t,

u H A ~ l',. ~~ a «'< g emP

'

EOPHP3REACTOR TRIP RESPONSE

'b., Pressure —STABLE AT'RTRENDING TO 2235 PSIG

b. IF pressure LESS THAN 2235 PSIG

and decreasing, THEN:

1) Verify PZR PORVs closed.

2)

IF. any PZR PORV can NOT be

closed, THEN close its blockvalve. ~

Ver'ify PZR spray valves

closed~

/IF valve(s) can NOT be

closed, THEN stop RCP(s)

supplying failed sprayvalve(s).

3) Verify'ZR heatersenergized.,

IF- pressure greater. than 2235

PSIG and. increasing;. THEN:

1) Verify PZR heaters off.

2) Control pressure using-

normal'ZR. spray IF NOT

available: AND letdown, inservice,, THEN use. auxiliaryspray IF'OT, THEN use one

PZR; PORV;

EOP-EPP-4 Rev. 0 Page 8 of 13

4

~ ~ $ ~

p ~

4

I

EOPHP3C

Ig

7.. Check S/G Levels:

REACTOR TRIP RESPONSE

a. Narrow. range level — GREATER

THAN 10X

a. Maintain total feed flow greaterthan 400 GPM or 192 KPPH untilnarrow range level greater than

10X'n at least one S/G.

b.- Control. feed flow to maintain.narrow: range; level'etween..10X'nd, 50X;

b. IF narrow range. level in any S/G

continues to increase, THEN stop

feed flow. to that S/G.

EOP-EPP-4 Rev; 0 Page 9 of 13

'D, hh

Pgt ~ 1&CWL~ "uh

'e ~ t5

~ EOPHP3REACTOR TRIP RESPONSE

0,

8. Verify All AC Busses — ENERGIZED Perform the fol3owing as necessary:%~

BY OFFSITE POWER

a. Verify EDGs have started.

b. Verify EDGs have assumed the

proper loads.

c., Verify turbine DC lube oil pump

and air'ide seal oil backup pump

are: running.

'.. Verify adequate EDG capacity and

load the following equipment on

the. EDGs:.

1) One instrument air.compressor

2') Battery chargers

3) PZR. heaters,. as needed.,

e., Determine the cause of the lossof offsite power., If due to a

failure- of the: startuptransformer,. request; assistancefrom. maintenance crews to restore

4

power from: either the main orspare startup transformer.. Ifthe loss'f power is the resultof a loss, of; grid, obtainassi'stance-.from. the Load

Dispatcher..

9.. Transfer C'ondenser steam, Dump toPressure Control Mode.

$ )IF condense< NO+" available,. THEN use ~

le

S/G-'ORVs'.

EOP-EPP-4 Rev. 0 Page 10 of. 13

Ap 4 ~+<a ~ ~ M

II

gOPHP3i'EACTOR TRIP RESPONSE

e,~C~'

CAUTTON

On natural circulation, RTD bypass temperatures and associated interrocts will be

inaccurate..

NOTE: RCPs shoul'd be run in order of priority to provide normal PZR spray.

10.. Check. RCP Status —AT LEAST ONE

RUNNING

Try to start one RCP:

a Establish conditions for runningRCP(s) using OP-100, "REACTOR

COOLANT SYSTEM," while. continuingwith. this, procedure..

b 'tart'CP(s)

IF at. least one- RCP can NOT be

stamped., THEN verify naturalc&culation from; trended values:

o RCS'ubcooling —GREATER

THAN 25 Fo Steam; pressure. - STABLE OR

DECREASING ..

o RCS: hot, leg temperature—STABL'E OR DECREASING;

o. Core exit T/Cs —STABLE OR

DECREASING

o RCS.cold: leg- temperatures—TRENDING'O OR. AT SATURATION

TEMPERATURE FOR'TEAM

PRESSURE.~ 4w.

IF natur~ circulationNOT'erified,

THEN increase. dumping

steam.

EOP-EPP-4- Rev.. 0 Page. Ll of 13

C II7ICE4

. ~ EOPHP3REACTOR TRIP RESPONSE

I11. Check If Source Range Detector

Should Be Energized:

a. Check intermediate range flux- LESS'HAN 10 AMPS

a. Continue with step 12. WHEN flux-10less than 10 AMPS, THEN do

steps 10b and c.

b. Verify source range detector's—ENERGIZED

c.. Transfer nuclear recorder'osource. range scale.

12. Shutdown. U

Equipment=

0:

o.

Stop; bottr. heater drain. pumps

Stop.. condensate pump,

condensate. booster pump„ and:

EW'ump='as; required.

o IsolateBTRS''erify

turbine generator goes.,

on-. the turning: gear; one-

minute after zero, speed. alarm.

is: received-:

o, Secure. the. MSRs

o Stop DEK pumps

EOP-EPP-4 Rev.. 0 Page 12 of 13

'

~ g'~ r~ ~ ~'r 't >Kw l 3

Cigar

P 4

EOPQP3\

REACTOR TRIP RESPONSE

13. Maintain Stable, Plant Conditions:

a. PZR pressure - AT OR TRENDING

TO 2235 PSIG

b.. PZR level —AT OR TRENDING TO

25X'

S/G'arrow.range levels—BETWEEN 10X: AND

50X'.

RCS average temperature- —AT'R

TRENDING'O 557'F

14- Go: To Appropriate Pl'ant Procedure:I

As; Determined'. Below."

a Perform:OMM-004-„"POSZ'RIP'/SAZEGUARDS-

REVIEW"

b 'heck plant. status —RCS

COOLDOWN: REQUIRED

b.,'o to GP-'04, "RECOVERY FROM'

REACTOR'RIP," and return topower operation..

c Check RCP'tatus —A'ZLEAST'NE

RCP AVAIMKE.c.. Go to EPP-5, "NATURAL CIRCgLATION

COOLDOWN," step 1..

d'tart= RCP(s)'sing, OP-100'.

"REACTOR COOLANT: SYSTEM ."'

Go to. GP'OT„"NORMALPLANT'OOLDOWN"

n 0- FINAL PAGEPane 13„ of 13

' ~ ~

'I

V

AI

u'II

C

I' ~

~ i II

EOPHP3FOLDCUTS

'c(

FOLDOUT D

a. SI ACTUATION CRITERIA

detente SI end go to PATH-1, entry point A f ElTHER co"..d-.'or. lie."'cbelov occurs:

1) RCS Subcool|ng — LESS THAN 25'F [30'F]2) PZR Level — CANNOT BE MAINTAINED GREATER THAN 10'~ [45X]

b. LOSS OF EMERGENCY'OWER

Go to EPP».1, "LOSS OF AC POWER TO lA-SA AND 1B-SB BUSSES," step 1 'femergency busses 1A-SA and 1B-SB are deenergzied.

EOP-FOLDOUT Rev. 0 Page 7 of 13

0

' F

t

A.

~F4K

e

r

'

4p

.a 0

L

D G

PATH —1

4 I I

WIV

~MARCH HA»II~ MICLSAR MSGR PLANT

IGVZSICN

stfauruaI I ~

~ M 1

A.C. I

O/I I M IGLC

Njavtgg

a.c..0/

TrTLE t Tf DII

la

TI wM I ~ I

~ I I M

0 I

FOLDOUT R

4 RCP TRIP CRITEIIIA

TRIP ALL RCP IP OOTN CO»IITIIMS LISTED OELolt AIM IRTI CSIP AT LEAST ua HlatilMI2. Rcs pREsslAM - LEss THAN 1500 psla c lsoo psliD

0 Sl TuailNAT ION CR! TERIA

I I Ifl 4 M

ao ro Epp-0 si vsRI owvNM lr ALL cctofrfcfa LISTED SZLI» occurIIM - fatrATER ftfAN a P cso rr

2 NARRON RAMM LEVEL IN Ar LEAST Ofa IHTACT S/0 " SIMATER IWI loa C40Xl

t»

TOT». PEEO PLOU To INTACT 0/0 . OREI TEli TWIN 400 OPtl OR 102 RPPH5. RC5 PRE55UHE - STASLE CR INCREASII434, I'ZR LEVEL MKIITEN THAH lait I4010C COLO LEO RECIRCILATIIM SIIITCHOVPZI DUTEIIION

~ I

00 To ZPP I 0 TRANSI'ER To COLO LES IMCIRCIEATICN ~ STEP I IP RitST LEVELOECREIISES To LESS THAH LATER

0 SECotOARY INTESRITY CRITEIIIOH

00 To EPP 14, PISLTEO 5TEAII 0ENEIIATOR ISOLATICN, STEP I It'NY 5/0 PRESMIMwia 'of OEEH 150uiTESOECIIEASES IN AN LliCONTIEELEO IIAMMR Oi HAS COHPLETELY OEPIMSSLRIZEO ZZZZ

E LOSS CP EtERSENCY POIIBI

00 To EPP 1 LOSS CP AC POIIER To IA.SA A141 IS 50 SUSSES STEP I IlENEROTNCY SIMSES iA.SA»D ia-sa»M CEENERarzso

Hvlrl/0 SSTR ISOLATlaa

00 To EPP-10 SOTR ISOLATION, STEP I H ANY S/0 LEVEL INCREASES IH ANUNCONTIIOLLEO IIAtosa OR ANY 0/0 HAS A!MOMIALIIAOIATICNLEVELS

nt

I~ I

Hi

E14

N

Gw \BI ~ Yl

H. I

4

IMEP12

10

II IM I IHI

~ 4 THIS PROCEDURE CLRRENTLY DOES NOT CONTAIN ALL NECESSARY INPOIOIATTON,REOUIRED IHPOISMTION MIST OE TILLED IN PRIOR TO PLANT TUEL LOAD

G