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

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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- ~

e.'EACTOR, TRIP'ESPONSE TITLE',

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REVISION 0 APPROVED SIGNATURE DATE TITLE 8~0SO~oi0~ 8~0428 POR AOOC~

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LIST OF EFFECTIVE PAGES

~Pa e Revision No.

1 through 13. 0 EOP-EPP-4 Rev; 0 Page 2 of 13

EOPHP3 REACTOR TRIP RESPONSE

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~ 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 Rev.. 0 Page 3 of l3

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EOPHP3 REACTOP, TRIP RESPONSE

- Instructions Res onse Not Obtained

1. Check RCS AT OR TRENDING TO 557 F'F Temperature STABLE S temperature less decreasing, THEN:

t 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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EOPHP3 IC 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: a- Continue. with step 4. WHEN RCS LESS'HAN, 564'F temperature less than 564'F, THEN do steps.3b and c.'

Verif'y. feed regul'ator va1ves:

CLOSED, c.. EstabTfsh, FR'ypass EXo~ to c. Establish; AFV'low to S'/Gs..

S:/Gs

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EOPHP3 REACTOR TRIP RESPONSE

4. Verify All Control Rods Fully IF two or more control rods NOT fully Inserted. 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 (Blender Outlet to CSIP suction)

OR 0 ~

Open. FCV-113K (Bpric Acid to Blender) and open FCV-1.14A (Blender, Outlet to, VCT) c;. Verify boric. acid. flow to CSIP

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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. a Verify SI actuation. AND go to PSIG: 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 b. IF pressure LESS THAN 2235 PSIG TRENDING TO 2235 PSIG and decreasing, THEN:

1) Verify PZR PORVs closed.

IF. any PZR PORV can NOT be closed, THEN close its block valve. ~

2) Ver'ify PZR spray valves closed~

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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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REACTOR TRIP RESPONSE Ig 7.. Check S/G Levels:

a. Narrow. range level GREATER a. Maintain total feed flow greater THAN 10X 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. b. IF narrow range. level in any S/G narrow: range; level'etween.. continues to increase, THEN stop 10X'nd, 50X; 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..

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9.. Transfer C'ondenser steam, Dump to IF condense< NO+" available,. THEN use ~

le Pressure Control Mode. S/G-'ORVs'.

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

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i'EACTOR gOPHP3 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 Try to start one RCP:

RUNNING 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 THEN increase. dumping NOT'erified, 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 a. Continue with step 12. WHEN flux

- -10 LESS'HAN 10 AMPS 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: Stop; bottr. heater drain. pumps

o. 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 b.,'o to GP-'04, "RECOVERY FROM' COOLDOWN: REQUIRED REACTOR'RIP," and return to power operation..

c Check RCP'tatus A'Z LEAST'NE c.. Go to EPP-5, "NATURAL CIRCgLATION RCP AVAIMKE. 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 FOLDOUT D

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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. 0 Page 7 of 13

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~I I M 0 I FOLDOUT R 4 RCP TRIP CRITEIIIA TRIP ALL RCP IP OOTN CO>>II TIIMS 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 ao ro Epp-0 si vsRI owvNM lr ALL cctofrfcfa LISTED SZLI>> occur IIM - fatrATER ftfAN a P cso rr I I I 2 NARRON RAMM LEVEL IN Ar LEAST Ofa IHTACT S/0 " SIMATER IWI loa C40Xl fl 4 M TOT>>. PEEO PLOU To INTACT 0/0 . OREI TEli TWIN 400 OPtl 102 RPPH

5. RC5 PRE55UHE - STASLE CR INCREASII43 OR 4, I'ZR LEVEL MKIITEN THAH lait I4010 t>> C COLO LEO RECIRCILATIIM SIIITCHOVPZI DUTEIIION 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

~ I 00 To EPP 14, PISLTEO 5TEAII 0ENEIIATOR ISOLATICN, STEP I OECIIEASES IN AN LliCONTIEELEO IIAMMR Oi HAS COHPLETELY OEPIMSSLRIZEO It'NY 5/0 PRESMIM wia 'of OEEH 150uiTES 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!MOMIAL IIAOIATICN LEVELS nt Hi I~ I E 14 N

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