ML18019A787

Rev 0 to Emergency Operating & End Path Procedure EOP-EPP-004, Reactor Trip Response. W/One Oversize Drawing

ML18019A787
Person / Time
Site:	Harris
Issue date:	12/04/1984
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18003B224	List: ML18003B223 ML18019A787
References
EOP-EPP-004, EOP-EPP-4, NUDOCS 8605010207
Download: ML18019A787 (29)

Text

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 A

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LIST OF EFFECTIVE PAGES

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Revision No.

1 through 13.

0 EOP-EPP-4 Rev; 0

Page 2 of 13

EOPHP3 REACTOR TRIP RESPONSE i31.0 PURPOSE

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.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 Rev.. 0 Page 3 of l3

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EOPHP3 REACTOP, 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, greater than. 400 GPM or 192 KPPH until level greater than 10K in at'east.

one S/G.

c:

IF'ooldown: continues, THEN close MSIVs 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

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IC EOPHP3 REACTOR TRIP RESPONSE Verify At Least One RCP - RUNNING Perform the following:

o Place steam dump in pressure control mode.

o Dump steam to establish natural circulation.

3.

Check Feed System Status:

a; Check. RCS'emperature:

LESS'HAN, 564'F a-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~ to S:/Gs c.

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

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Page 5 of 13

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EOPHP3 REACTOR TRIP

RESPONSE

4.

Verify All Control Rods Fully Inserted.

IF two or more control rods NOT fully

inserted, 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 to Blender) and..open FCV-113B 0

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(Blender Outlet to CSIP suction)

OR Open. FCV-113K (Bpric Acid to Blender) 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

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~ 'OPHP3 REACTOR 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 restore PZR level greater than-17K.

b Ver'ify charging and. letdown.

IK SERVICE.

c..

Level STABLE AT OR; TRENDING c.,

Control'harging and letdown to TO 25K maintain PZR level at 257.'.

6:

Check PZR Pressure.

ControT a

Pressure GREATER THAN'881.

PSIG:

a Verify SI actuation.

AND go to PATE-1:, entry-point A.

EOP-EPP Rev 0

Page 7 of 13

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EOPHP3 REACTOR TRIP RESPONSE

'b.,

Pressure STABLE AT'R TRENDING 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 block valve.

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Ver'ify PZR spray valves closed~/

IF valve(s) can NOT be

closed, THEN stop RCP(s) supplying failed spray valve(s).

3)

Verify'ZR heaters energized.,

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, in service,,

THEN use. auxiliary spray IF'OT, THEN use one PZR; PORV; EOP-EPP-4 Rev.

0 Page 8 of 13

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Check S/G Levels:

REACTOR TRIP

RESPONSE

a.

Narrow. range level GREATER THAN 10X a.

Maintain total feed flow greater than 400 GPM or 192 KPPH until narrow 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

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~ EOPHP3 REACTOR TRIP RESPONSE 0,

8.

Verify All AC Busses ENERGIZED Perform the fol3owing as necessary:

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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 loss of offsite power., If due to a failure-of the: startup transformer,.

request; assistance from. maintenance crews to restore 4

power from: either the main or spare startup transformer.. If the loss'f power is the result of a loss, of; grid, obtain assi'stance-.from.

the Load Dispatcher..

9..

Transfer C'ondenser steam, Dump to Pressure Control Mode.

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IF condense<

NO+" available,.

THEN use

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le S/G-'ORVs'.

EOP-EPP-4 Rev.

0 Page 10 of. 13

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gOPHP3 i'EACTOR TRIP

RESPONSE

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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 running RCP(s) using OP-100, "REACTOR COOLANT SYSTEM," while. continuing with. this, procedure..

b 'tart'CP(s)

IF at. least one-RCP can NOT be stamped.,

THEN verify natural c&culation from; trended values:

o RCS'ubcooling GREATER THAN 25 F o

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.

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IF natur~ circulation NOT'erified, THEN increase.

dumping steam.

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

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EOPHP3 REACTOR TRIP RESPONSE I

11.

Check If Source Range Detector Should Be Energized:

a.

Check intermediate range flux

- LESS'HAN 10 AMPS a.

Continue with step 12.

WHEN flux

-10 less than 10

AMPS, THEN do steps 10b and c.

b.

Verify source range detector's ENERGIZED c..

Transfer nuclear recorder'o source. 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 Isolate BTRSerify 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

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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 to power operation..

c Check RCP'tatus A'Z LEAST'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"NORMAL PLANT'OOLDOWN n 0-FINAL PAGE Pane 13 of 13

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EOPHP3 FOLDCUTS

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FOLDOUT D a.

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

1)

RCS Subcoollng 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 'f emergency busses 1A-SA and 1B-SB are deenergzied.

EOP-FOLDOUT Rev.

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RCP TRIP CRITEIIIA TRIP ALL RCP IP OOTN CO>>IITIIMS LISTED OELolt AIM IRT I

CSIP AT LEAST ua HlatilMI

2. Rcs pREsslAM - LEss THAN 1500 psla c lsoo psliD 0

Sl TuailNAT ION CR! TERIA I

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fl 4 M ao ro Epp-0 si vsRI owvNM lr ALL cctofrfcfa LISTED SZLI>> occur IIM - 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 RPPH 5.

RC5 PRE55UHE - STASLE CR INCREASII43 4, I'ZR LEVEL MKIITEN THAH lait I4010 C

COLO LEO RECIRCILATIIM SIIITCHOVPZI DUTEIIION

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

SECotOARY INTESRITY CRITEIIIOH 00 To EPP 14, PISLTEO 5TEAII 0ENEIIATOR ISOLATICN, STEP I It'NY 5/0 PRESMIM wia 'of OEEH 150uiTES OECIIEASES 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 Il ENEROTNCY 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 AN UNCONTIIOLLEO IIAtosa OR ANY 0/0 HAS A!MOMIALIIAOIATICNLEVELS nt I~

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