ML18019A787
| ML18019A787 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 12/04/1984 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML18003B224 | List: |
| 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 8~0SO~oi0~
8~0F OOC~0~000+00 428 PDR Page 1 of 13 I PATH-1 44r 4 A.C I Arl IUI~~IL i~tAs vo oto~IAL'lot autLLl~LL 44 L rtLDOII A IVWQV~o~IIVWWW IWI W WVI OW WWO~W I BIJOU 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 WLOWWOV w AIL oo&~w Iv Uw TgrorttL 1tt.'L4j m%ÃLL K-'IK ALL~47ÃEN~M o'LA+PA IL SAL a LO4 IO,or'ro PT'K~:Qr~WWIIO WWIO OWO W IVO I I OVOIW OVO IWo~OWVU WO IW MI W IOW I I UO lt IUU IUO
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gOPHP3 0 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 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 Rev..0 Page 3 of l3 1 1 4 I p-r EOPHP3 REACTOP, TRIP RESPONSE-Instructions Res onse Not Obtained 1.Check RCS Temperature
-STABLE AT OR TRENDING TO 557 F'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..~P~e EOP-EPP-4'ev, 0 Page 5 of 13
%I i+t%It R lt'l~'U 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~(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
~~@type~t a P k.
'~'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 t, u H A~l',.~~a<<'<g em P' 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.~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 4~~$~p~4 I EOPHP3 C Ig 7..Check S/G Levels: REACTOR TRIP RESPONSE a.Narrow.range level-GREATER THAN 10X a.Maintain total feed flow greater than 400 GPM or 192 KPPH until narrow range level greater than 10X'n at least one S/G.b.-Control.feed flow to maintain.narrow: range;level'etween..
10X'nd, 50X;b.IF narrow range.level in any S/G continues to increase, THEN stop feed flow.to that S/G.EOP-EPP-4 Rev;0 Page 9 of 13
'D, hh Pgt~1&CWL~"u h'e~t 5
~EOPHP3 REACTOR TRIP RESPONSE 0, 8.Verify All AC Busses-ENERGIZED Perform the fol3owing as necessary:
%~BY OFFSITE POWER a.Verify EDGs have started.b.Verify EDGs have assumed the proper loads.c., Verify turbine DC lube oil pump and air'ide seal oil backup pump are: running.'..Verify adequate EDG capacity and load the following equipment on the.EDGs:.1)One instrument air.compressor 2')Battery chargers 3)PZR.heaters,.as needed., e., Determine the cause of the loss of offsite power., If due to a failure-of the: startup transformer,.
request;assistance from.maintenance crews to restore 4 power from: either the main or spare startup transformer..
If the loss'f power is the result of a loss, of;grid, obtain assi'stance-.from.
the Load Dispatcher..
9..Transfer C'ondenser steam, Dump to Pressure Control Mode.$)IF condense<NO+" available,.
THEN use~le S/G-'ORVs'.
EOP-EPP-4 Rev.0 Page 10 of.13 Ap 4~+<a~~M II gOPHP3 i'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 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.~4w.IF natur~circulation NOT'erified, THEN increase.dumping steam.EOP-EPP Rev..0 Page.Ll of 13 C II7ICE 4
.~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 pumpand: 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
'~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 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 13of 13
'~~'I V A I u'II C I'~~i II EOPHP3 FOLDCUTS'c(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.0 Page 7 of 13 0'F t A.~F4 K e r'4p.a 0 L D G PATH-1 4 I I W IV~MARCH HA>>II~MICLSAR MSGR PLANT IGVZSICN stfaurua I I~~M 1 A.C.I O/I I M I GLC Njavtgg a.c..0/T r TLE 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>>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 I I I 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~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!MOMIAL IIAOIATICN LEVELS nt I~I Hi E 14 N Gw\BI~Yl H.I 4 IM EP 12 10 I I 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