ML19332B253

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Small Break Operating Guidelines. Related Correspondence
ML19332B253
Person / Time
Site: Oconee, Crystal River, Rancho Seco, Crane  Duke Energy icon.png
Issue date: 11/30/1979
From:
BABCOCK & WILCOX CO.
To:
Shared Package
ML19332B231 List:
References
69-1106001, 69-1106001-00, ISSUANCES-SP, NUDOCS 8009260366
Download: ML19332B253 (48)
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Text

{{#Wiki_filter:RE!ATED CORRBSPONDENCB Docket No. 50-289 (Restart) Licensee's Exhibit No. O E 00ck m 3 0) M DSNRO t 19195, 3 g // 4 'b B&W Document 69-1106001-00, "Small Break Operating Guidelines," November, 1979 g009260 THIS DOCUMENT CONTAINS FOOR QUALITY PAGES f

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Sni-20004 (6-76) BA8COCX & WILCOX , NUCIA4 PCWtt CENetAf1CN DivfSCN TECHNICAL DOCUMENT t'eff"' A " P ts IRE lhh"f!!pii['S!iY Pi EMERGD'CY OPERATING SPECIFICATION 69 1106.001 - 00 Doc. ID - Serial No., Revision No. for OPERATING GUIDELINES FOR SMALL 3REAKS FOR CCONEE 1, 2 AND 3, THREE MILE ISLAND 1, 2, CRYSTAL RIVER 3, AND RANC-lO SECO 1 PAGE 1 l

3WP-ZC005 (6-76) ~ BABCOCX & WILCOX wc1Aa PCwft GENetATICN 3rv@CM OIII RECORD OF REVISION 69-11o6o01-oo REY. NO. CHANGE SECT / PARA. DESCRIPTION / CHANGE AUTHORIZATION 00 Original Issue - D. A. Beckner Cust:mer Services / ~ Y,,n u. ] < m,'i n DATE // / k 9 ?REPARED SY L $./ //l->m 1 Q gei tu-1.> APPROVED SY ( M_

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69-1106001 9 PART 1 - OPERAT!?0 CUIDEL!NES FOR S'.*l.L 3RIAKS 1.0 SWFTC5!S M:D INDICATIC::S ( ;0!EDIATI !!' DICA *IO':S) 1.1 IICISSIVI RIAC""CR COOLA C SYSTE! (RCS) MARIU?* ~ 1. 2 DICR:".ASI::C RCS PRESSU"I 1.3 RIACOR ~RI? l 1.4 DICEASDiC PRESSURIZIR LT.'IL* 1.5 ISTAS ACTUATION

  • 1.6 LOW MAKIUP TMiR LI"IIL*

1.7 ADDITIONAL CRHIRIA DURDiG EF.AIUP AND CCOLDOWN

  • 1.7.1 RCS TDf? INCEASDiG, MDIDC;M LITDCici AND PRESSURIIIR LI7IL DICEASEIG 1.7.2 WITE A C00LDOL? 0F < 100*F/ER AND CMINCT MADCADi LIVIL Di MAKIUP TANK
  • MAY N0* OCC!R ON ALL SMALL 3RIAKS 2.0 DCTDIATE ACIO::S o

2.1 IF THE F.5FAS HAS EEIN INITIATID AU'"CMATICALLY 32CAUSI C7 LCU RC PRESSURI. Et>EDIA I'Y SICURI ALL RC ?m!?S. 2.2 VIRITY CONTROL ROCM DOICATIONS SUP?OR- *EI AI. ARMS RICIITID, VIRITf AUTOMATIC ACTIONS, AC CARRY OCT STXCARD POST-TRI? ACIONS. 2.3 3ALANCE HICH-?RISSURI DiJICTION (EP!) FLCW 3ET*ITi M.L INJICION LDTIS WHO HPI IS DiITIA'"ID. o 2.4 VIRITt THAT AP?ROPRIATI CNCI-TERCUGE STIMI CEERATOR (OTSG) LIVIL IS MAINTAINID SY FIEWATER C0!iTROL (LOW LITIL LDi!! WCF. RC ? CTS 0? IRATE:0, DERCEICY 'zr/IL WCECUT RC 7t2GS 0?IRAriG). .0 2.5 MONCCR SYL. :t PRESSURI mfd TIMPIRikTURI. !? SATURA ID CODI IONS ~ OCCUR, DII I.A I H?!. l l 2.6 IF ISTAS EAS 3m 3Y?ASSC DCI 20 ETC? OR COOLDCk'N, DCC"I l SAIT"! DiJIC ION. CAUTION: IF 50*F ST3C00 LING CRA.4 S 1.7, IIROTTLI H?! FLCW TO KII? SYSTEM PRISSURI WITEDI NOD!A' ICriICAL SPI C-FICAT 0N ?-T CTRVI I.D!CS. 17 RCS IS NOT 50*F SUICCOLD, C0h'"riUI FUIJ., SAFI T IL*FCION CC:*., 50*F SU2CCOLDiG IS ATTA3D CR *EI P-! LDi!!S OF ?!CURI L ARI RIACED........ ~-

69-1106C01 3.0 PRECAUT!CNS e 3.1 IF T!E ISTAS IIAS BID: INITIATID On LCW o.C PRISSrzI. IP2.tr ATICU OF RC PCf? OPERATIO:s TAKIS,? RECEDE"CI 0"IR ALL 01CR OIEDIATI ACC0!!S. NOTI: IF ISFAS HAI BIIN AC UATD ON HIGH R3 PP2SSURI, C."* !!CN!!CR RC PRESSUP.I NiD TRIF RC PCGS CNCI ?RESSURI DICRIASES E'~~.C'; THE ISFAS LOW PRISSURI su. OtiT. 3.2 IF ESFAS !!AS BE!:I INITIATED, Tilz RC ITMP'S TR!??D, 273 CE RCS DETIPJIINID TO 3I AT '.IAST 50 F SUSCOOLD. !!E CPE2ATOR SMOL O ESTA3LISl! AS OUICELY /.S POSS!3LI IF THE CAUSE FOR ~~4I '"**UR::A-TION IS DUE TC EITf!ER A LOCA OR NON-LOCA (OVIRCOOLI"C) E7ENT. PROCIID TO STEP !. 4 FOR NON-LOCA IVI.'iTS. 3.3 I7 THE HPI SYSTD! '!!AS ACTUATC EICAUSI 0F LCW PRISSURI CONDI IONS, IT MUST REMADI IN OFERATION UNTIL ONI 0F THE FOLI.0*C'G CRITIRIA IS SAT!SFID : 1. TEI L?I STS El IS Di CPIRATION MiD IT.CWEIG AT A RATI Of EXCISS OF 1000 GPM IN IACH Lniz AND Tnz SITUATICN EAS SIIN STA3LI FOR 20 MDiUTIS. OR l 2. ALL ECT AND COLD LIG TDfPIRATC32S ARI AT LIAST SOF 3ILOW THE SATURATION T2f?IRATURI TCR TEI EXIST 2TG RCS PRISSURI - AND - ) IEI ACTION IS NICISSART TO FRZ7ENT III DTDICATD PRISSURIIIR LI7EL FROM GODIG 0??-SCALI EIGH. NOTE: II SOF SU3C00L2iG CANNOT 3I NA2CAriD, TEI EPI SEALL BI RIACTIVATE. NOTI: THE DEGRII 0F SU3 COOL 2iG 3ETOND SOF AND THE LEIGTE OF T2fI EPI IS IN OPERA!!ON SEALL 3I LS.:_; 37 Idz PRIESCRI/ } NERATURI CCNSDERATIONS FOR THI 7ESSIL Oi""IGRI ! (SII SICTION 3.4). g -

~ 1 69-1106001 1 3.4 WHIN TdI REACTOR C00 LUC IS > 50 F SU3C00LD, "E RIAC CR VISSIL o. DOWNCOMIR ?RISSL*RI/C!?I?An'RE (?-T) CO:GriATICN SE.C BI *~I? 3ILOW AND TO TdI RICC OF TE LO!!! CTRVI SEC*41 Ci F*GJRI 1. 7dI DCI.'.;C"MIR TDGI?a:URI SEAL' 3I DCID!!ND AS FOLLOWS: 3.4.1 WITE O!!I OR MORI RC ?t}25 0?IRAT*NG USI ANY COLD LIG R""O AS AN DiDICAT!ON OF RIAC OR VISSr.* OCUNCO:!IR TD2ERATJRI. ~ 3.4.2 WI H NO RC PC!?S 0?IRATINO Td! RV DCliNCOMIR TD2I?a2*RI SH.C 3I Dr*"."."?_R.".*...D-m'"?_."A v*. *.* '.u..?..?'.'/?

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..v .n TIMPERATJRI RIN)CiGS M*D SU3' RAC rig 150 F FRCM THI AVI?aGI INCORI THID!OCOU?LI TEGIRATURI VALUI. 5 Free - 150 F T DWN WHERE T = AVIRACI RV DOWNCOMER TD2I?ATURI, F DWN l IT = SUM OF THE 5 LOWIST INCORI THIRMCCOU?LI TEGIRATURI tc RIADINGS. NOTI: FIGURI 1 IS A??LICA3LI ONLT miDIR LOCA CONDITIONS. TEI P/T CURVI IN TEI TICENICAL SPICIFICATION IS VA'.D FOR ALL OTHIR OPIRATOTG CONDITICNS. NOTI: WEIN TdI RIAC~OR COCLuiT IS LISS TRAN 50 F SUBC00 LID, "'HI RIACTOR VISSEL DCWNCOMIR PRISSi"2I "'DGIRATJRI CO W.*.:ATION WILL ETHIRE!TLY 3I 3ELOW AND TO TdI RIGE"' 0F TdZ LE!!! CURVI. TEFORI, NO OFIRA OR ACTION U2L SI RIQU RD TO PRIVDC IXCIIDE;G TEI RIAC OR VISS.*. OCIGRI*T LO.T;S UNTIL As 4.a A > 50 F SU3C00LD MARGri IES S. I Reced ~3-l 1

59-1.106001 NOTE: WIN THE RIAC"07. C00LMC 23 ?. 50*7 SU200CLC, RC PESSURI CAN BI ?,0CCD SY RCCCniG T.iI H?! TLOW RATI TO AVOID INCIDOG D!I RV ECIORI'~f L21!!S. ~ 3;$ PRISSURCn LI7IL MAY EI 2:CRIAS3G DUI TO RCS REACH 3:: SA~UMT~.3 CONDITICNS CR A 3RIAK QN TOP OF TE PESSU?.IIIR. 36 IF HICn AC'"IVITY IS DI IC c IN A S Int GINIMTOR, IS0;.ATI r/.I LIAK=G GENERATCR. IT Is RICC:0! ECD TMT 20TH S IE! GINI2AT025 NOT 32 ISCLATIO. 3.7 OTHE C;DICATIONS WHICH C#l CONT *R:1 TE D**STDiCI C7 A LOCA:

3. 7.1 RC DRAU; TANK (QUINCH TANK) PRISSURI (RUP UE DISK 14AY BI ELOWM).
3. 7. 2 INCRIAS DC RIACTCE BUID OC SUMP trVIL.
3. 7.3 DCEASING RFACTCR EUILDING TD2 ERA ~URI.
3. 7.4 INCRIASING RIACTOR BUD.3 3G PRISSU?.I.
3. 7. 5 INCRIAsn:G RADIATICN McNHCR READINGS D S!DI t*JNIAUT.E!C
3. 7. 6 RIACTOR COOLANT SYSTDI D2IMTURI BIC0id.IliG SaTURATD RIIATIVE TO THE RCS PRISSURI.
3. 7. 7 HOT LIG TD2ERATLRI IQUALS CR IXCICS ??2SSURIZIF. TD2IMTUT.I.

3.7.8 INCRIASE IN THE IICORI NIU RCN DI~ICTCR DIDICACONS. 210TI: IN CCN!! UNCTION WCH *EI INDICATIONS IN 3.10.1. THIS COULD BI AN INDICATION OF DIADIQUAT' CCRI C00L3G. I al 3.8 E?I C00L2iG RIQU""fENTS COCIIDI?LITI *EI 3CRA*ID WA3 STCRAGI *JNK, AND INIMAUCN OF LPI FLCW IRC1". ~3I RIACTCR EUD35G 57.9 TC. ~E E?I PUGS WCUL3 3I EQUIRE. 3.9 ALTIRNATI DISTRCiDT CHALTS S20013 3I CHICKD AS AVAD.A3LI TO CONFIRM KIT PARAMETIR RIADDIGS (*I, STS Di TDTSRATL72S, ?RISSURIS AD PRISSURIZIR L. P. ). 3.10 MADrd" 3 A *D2ERATURI VIRSUS *D2 ? LOT AND A CCRRIS?CDOG *Df?IRATU?2 PESSURI PLCT CN A SATURA~ICN D!AGRMI. USD:G ECT LIG R'"3'S AND EIGEIST DICORI THIRMCCCUPLZ RIADING, "EISI ? LOTS **ILL MAKI IT POSS 3LI TO "' RACK I TEI PLAIC'S CCNDCION TERCUGE ?tXiT C00CCWN. 3.10.1 I7 C'"ER OF TIE 70LLOWUG ECICAUCNS OF 3ADIQUA"'I CORI C00L3G IIIST, GO TO SECOON 4.5. 1. HOT LIG R*3'S RIA3 SU? IRE 7 AID ICR *EI EISnNG RCS ?RISSURI. 2. INCORI THIRMOCOU/LI ~I~G RIADS SU?mTCC 70R T!.I J IIISTING RCS ??2SSURI. g) 3.10.2 II ?RD!ARY TD2 ERA ~i.~E A2C ? ESSURE IS DEC. EASING ALONG rdI SATURA!!CN CL'RVI *RDi SU3COCLD CCCICONS WI'~. 3I ISTA3LIS'.lD. THIS WILL 3I 2CICA D IY PRO!ARY SYSTDI ?RISSI RI NO LCNCIR FCLLOW3G TE SATURA!!CM GVI, AS PROfARY STS D! TDT. DICV. ASIS. 'GIIN Td!S OCCURS, PRDfARY SYSTDi ?RISSURI. SECULD SI CONTRCT'"

69-1106001 3Y ADJUS OIG 17! FLOW, TO MAnCAC* 50*7 SU2C00LO*G. ZI DICRIZ OF SU3C00LE:G 3 CON 3 50*7 SHALL 3Z C0!GOLLC WI IIN THE LDf!TS DErric ni SIC !ON 3.4. J.11 COMPONE;I CCOL2:G WA IR (CCW) A'O SEAL n'JIC !CN SECULD 3I MAIN ~AE*U TO TRI RC ?ces TO INSURI CON nit ID SIRVICI CR WI A3*LI~T TO ?ISTG~ UE ?Df?S AT A LA*IR TO'I. 0 3.11.1 IT CCW 'S LOS~ MD Til! RC PC!?S ARE 0?IRAT*VI. CCI.* 'CET 3I RISTORO WIT!!I : 30 MI::U ES OR "'III RC P'**?S FI*ST 3C !'AN*' ALLY TRI??CD. o 3.11.2 17 Tl!E RC PUMPS ARE TRI?? D 70R A d RIASON, ST.AL INJI*~ ION SHOULD BE MAINTAI!:D TO INSURI LONO I-J! SEAL 2:~IO*lITY. l 4.0 70LLoti'? AC*!CNS 4.1 IDE TITICATICN A'iD IARLY CC!."rROL 4.1.1 U E?I HAS INITIATED 3ECAUSI 0F LOW PRISSURI, CONTROL EFI DI ACCORDANCI WI H STI? 3.3. 4.1.2 IF BOTH EP! TRADIS HAVI NOT ACTUATD CN IS7AS SIGNAI., START SICOND UPI TRAIN I7 POSSI3LI. PALCCI HPI TLCWS. 4.1.3 U RC PRISSUP2 DIC".IASIS CONTINUOUSLT, VIR UT THAT CORI FLOOD TANKS (CCs) AND LCW PRISSL*RI D:J.CTION (L?!) HAVE ACTUATE AS IwC, AND 3ALANCE L?!. o 4.1.4 U CAUSE FOR COOLDOWN/DZ?PISSURIZATICN IS DCIRMIND TO 3I DUI TO A NCN-LOG OVERC00LO C IVEC MC TEI RCS IS AT I.IAST 50 7 SU3CCOLE DICi PROCIID 0 SICTIO:t 4.4 4.1.5 AT! ret TO LOCATI MID ISCLATI LIAK U PCSSI3LI. LI DOUN WAS ISOLCID Di S I? 2.2. OTHER ISCLATALLI LIAKS AFI ?CRV (CLOSI 3 LOCK VALVI) AND 3CWICI VALVIS Uf S? RAY LDI (CLOSI S? RAT A!Q 3LCCI VALVI). ~ 4.1.6 DCISICII AVAILCIL*U C7 ?2AC OR COOLANT ? UMPS (RC?s) A:O MAIN AND ACI2.IARY ::.:,WA~IR SYS* DIS. U FIIDWATIR IS NCT l AVAILt3LI GO TO 4.2. U FICWAm IS AVAILA3LI GO TO 4.3. 4.2 AC"!ONS *T FIC WATIR IS NOT AVAII.A3LI 4.2.1 THROUCHCUT THE 70LLCW2:C STI?S MACCAri MAIO!C24 EPI TLOW A:D RISTORI FIEWATIR AS SCON AS POSSIILI. 0 4.2.2 U RC?s ARE OPIRATING, GO TO CNE ?22 PIR LCOP. II RC?s ARI NOT CPIRATOIC, CO TO STI? 4.2.6 3'. 0*J. 4.2.3 U RCS ??2SSURI n:CEASIS, OPEI PCRV AND LIAVI CPU. NOTE: U THE PORY CM:N0! 3Z ACA.w, THE SA :...IS W~s*el RILIIVI PRESSL"AI.

69-1106001 o 4.2,4 WHI:t TIDWATIR S RI:0 VIED, RISTORI CTSG LT.T S 27 A CON-TROLLD EU::iIR. CLOSI ?CRV CR 3LCCR VAL 7I, 17 POSS 3LI, AND PROCID TO S I? 4.3.2. 4.?.3 17 NO RC?s.CI C?IRATEIG, 0?Ci PCRV M!D MAI:CADI H?! FLOW. NOTI: !? HI ?CR7 CA::::0T 3Z AC'A D

      1. .I SAFI IIS UT*.L RELII/I PRESSURI.

4.2.6 WHEN 7IDWATIR TLOW IS RISTORD, RAISI OTSG LI I:.S TO 952 ON THI 0?IRATI RMiGI, CLOSI PORV CR 3LCCR VALVI, !? ?CSSI2LI. NOTE: OTSG LIVIL SHOULD SI MONI 0?ID ?IRICOICALLY DURD:G HI FILL PROCISS. LIVILS > 95% ON *EI CPI?JTO:C ?_CGI MUST 3I AVCDC TO PRICLDI FIDt A IR CAPSYCVIR TO T.-2 STEMILINIS. 4.2.7 VERITI NATURAL CIRCi!LA* ION Di t.v., RCS 3Y 03SIRVDiG: o 4.2.7.1 COLD LIG TreIRA U?2 IS SATU?aTICN *IMPIRATUF2 07 SECONDARY SIOZ PRESSURI IC*ECT A??RCID'.ATILY 5 MINUTIS. 4.2.7.2 ?RD'.ARY f.T (O!OT - TCOLD) 3ECO 'IS CONSTMC 4.2.8 GO TO ST 4.3 ACTIONS WITH fig.#.3 p '.ILA3LI TO ONI OR 30'"H GINI?aTCR$ 4.3.1 MAINTAIN CNI RC? RUNN2iG ?IR L00? (SOP CTI:IR RC?s). !? NO RC?s OPERA t:G (CUI '"O A LOSS OF 0775 I ?CUIR CR ::UI TO MANUAI. SECUR.N_C PIR SICTION 2.0), CC TO S I? 4.3.4 EILOW. 4.3.2 ALLOW RCS PRESSURI TO STA32.,I::Z. 4.3.3 ISTA3LISH AND MAINTAti OTSC COOLDiG 3Y ADJUSTO:G STIAM ?RISSU?2 VIA TUR3DiI 3Y? ASS AND/CR AO'CS?EIRIC DOCS. COCLOCW:7 AT 100 ? PER HCUR TO Au.a.vt Mi RC PRISSI'RI 07 230 ?SIG. R.::s TO ?RI-CAUTICN 3.10 TOR DIVILOPMI:T OF TIMPIRAT RI AND PRISSURI ?LO'"S. ISCLATI CORI 37.CCD TM;RS WHIN 50 7 ST 3C: 0L2iG IS A'":*AO;ID M:3 RC ?RISSi;RI !S LISS T/.Mi 700 PSIG. GC CCO L?! C00LCIO ?IR AP?rIDIZ A. O 4.3.4 II RC?s ARI NOT CPIRA!!NG: ~ 4.3.4.1 IS*"A3LISH AND CO:CROL CTSG LI I: TO 95: CN ~EI CFIRATI RANGI. VIRITY TI!I CONDIT!CNS Ci S I? 4.2.7 NC I: OTSG L 7ILS Ct*,TIR O!Mi 95* CN ""*-!I C?IRAT2:0 RANCE MUST 3E AVO! 20 TO PR CLDI FIIOt?ATIR l CARRYOVER I C0 -*-!I 5 IM'L2;?S. oRevised .f. a

69-1106001 4.3.4.2 IF RC ?RISSL72 IS D::CRIASO:G, L'AC U:CIL C STA3I~.CIS OR SIGD S E!CRTASI::G. I? IT 3IGO;5 UTCRIASC:G, CO O STI? 4.3.4.4 4.3.4.3 FROCID L'! 2 A CC CRCLLD CCCCCW:t A 100 7/IR SY CONTRCLLOIG ST~.M! GI';IRATCR SECO:OARY SOE PESSU?.I. ?!ONCOR RC PRISSL?IS kid TE2 IRA L*?25 DURING CCCCCI.7l MiD PROCID AS DOICA D 3ILCU: 4.3.4.3.1 IF RC PRISSL7.I CO:CC;UIS TO DICRI.MI, 70LLCWING SICO:CARY SCI PESSURI DICRIASIS AND WITH ??J.ARY STS D! TD22.M~L*RIS EiDICATD;G SATURAID CONDI!!ONS, CO::'"CCI C00LDOWN UN IL AN RC PRISSUE 07150 ?SI IS RIACHID, R;D ?Ro m To STI? A.4 0F APPINDIZ A. 4.3.4.3.2 17 RC ??JSSURI STOPS DICRI.ASC:G Di RIS?CNSI TO SICO:QARY SDI PRISSURI DICRIASI MC RIACTOR STS"'Di 32CC'ES SL*ECCCLD, CHICR TQ SII TE.C THE TOLLCWING CC:CCIONS A?2 20~$ SATIS 7CD: A) AII. ICT AIC COLD LIG TD2 IRA"'L*RIS AE BILOW !"dI SA~.UR.CION TD2 ERA ~U'd: POR TEI ECSTE!G RCS ?RISSURI. AND IQ TEI ICT AND COLD LIG TD2 ERA!;RIS ARI DICRIASING Di RESPONSI TO $!IAM GENERAICR SICONDARY TIMPIRACRI DICRIASI. IT THISI CONDCIONS ARI SATIS?!D A:D R.Ei',2 SATISFID, CO CO;UI CCCCCW:t TO AC'-CIVI Ei RCS TDGI. U.C (COLD LIG) 07 ISO 7, A D u PROCID To sar.e A.1 CF APPECEC A. NOTI: I? TEI CC!D CIONS AIOVI ARI 1.C 3 ILC*,' 700 PSIC, "".-2 COE 7:.00D Tx:XS 520L" D BI ISCLATD. NOTI: I? TEI PR20.RY SYSTE". IS 50 7 SC3CCCLC Di 30TE ECT X!D COLD CCS A:D PRD:A?.T -7_

69-1106001 SYSTD1 ?RISSI:2I IS A30VI 230 PS'.C, STAR'"O G A RIAC*CR CCCLA::T ?i::0 IS ?I?.- )fISSI3LI.

  • 7 STS~r! DOES NC* KI"*J?l; 70 AT LIAST SO ? SL*3CCCLO:0 IN -'.0 >CN*.7IS, TRIP PL7IPS.

.~7 ?CRCIO CI2CLU TION IS ACHII7ED, ?RCve.u 70 S T 4.3. 1 i e e l e I e 4 -g_ e

69-1106001 4.3.4.3.3 17 RC ??l.;SURI STO. S DICRIASO C AIC ~3I CCNDITIC:IS OT 4.3.4.3.2 ARI l'OT MI" CR CIASI TO SI }S"' CP. I? RC ?RISST?2 3ECO*S TO OIC?iASI, T*Ci PRCCID TO S !? 4.3.4.4 SILOW. 4.3.4.4 ES ORI RC? ECW (CNI ?IR LCCP) WH?l! FOSSII*I ?IR TE DISTRUCTICNS 31~.C7. 17 RC ?OGS CMCICT 3I OPIRATED M;D PRISSi;RI IS CICRIASING, CD TO !!I? 4.3.4.6. 4.3.4.4.1 IT PRESSUM IS OICRIASDIG, S~ ART 0;G A ?O2 IS PIRMISSISLI AT RC ?RISSURI CRIA~IR ~3AN 1600 PSIG. 4.3.4.4.2 II RIACTOR CCCLA:C SYSTIM ?RISSURI IICICS STIAM Gr(I?a:CR SICCNDARY ?RISSU?2 37 6C0 PSIC CR MCRI "302" ONI RIAC~CR CCOLMC PUMP 7CR A PIRICD OF'A??ROI.*.a:ILY 10 SECONDS (?RITI?.A3LT Di 0? IRA 3LI STIAM GINIRATCR LCOP). ALLOW RIAC CR CCOLMC SYSTIM PRISSURI TOSTA3 LIII. CC:CINUI CCCLDCWN. II RIACTCR CCCIRC SYS~IM PRISSi!RI AGAIN IICIC S SICCNDARY PRESSURI BY SCO ?SI, WAIT AT LIAST 15 mew.c.S A D RI?IAT ~2I PQT "IUMP". 302 ALTI?2iATI ?U12S 50 ~3AT NO PUMP IS 302D MCRI THAN CNCI Ci Mi 20UR. THIS MAY' 3I RI?IATID, W!~2 Mi D..:.tTAL OF 15 MINU"'IS, UP TO 5 ~223. A7"'IR 23I ?!E E " BUMP," ALLOW TEI RIACTCR CCCLA C ?D2 TC CONTDnN D' C:'O IIC i. 4.3.4.4.3 II PRISSURI ?>.S STA31LICID 70R G"AIA'"IR T?.AN CNE HOUR, SICC:CARY PRISSURI IS LISS ~2AN 100 PSIG AND PR2 Lay,! pgIssTgg :s onIA;23 gan 250 PSIO, 3C2 A PTM?, WAI"' 30 MDw.-S, MD STAR

  • AN AL'"I?2iA I 702..

m 69-1106001 4.344.5 IT TCRCD TLC;.' IS STA3L:SHD, CO TC S:"J2 4.3.3. 4.3.4.6 !? A P2ACTCR CCCLA:C ?'#.0 CA::::CT 3I C?IRATC A:O RIACTOR CCOLA::: SYS D! PRISSUE ?2ACHIS 2300 PS G, OPIN ??2SSUR:IIR ?CRV TO RD UCI RIACTCR CCCIA C SYSTIM ??ISSU?2. RICLCSI ?CRV '4EIN RCS PRISSU?2 FALLS TO 100 PS: A30VI TEI SICC::::A?.Y ?RISSURI. RI?IAT I? NICISSARY. I? POR'I IS NOT CPIRA3;I, PRISSUR;;IR Skr.x? VALVIS 4:LL RIL IVI CVI?JRISS'.7.I. 4.3.4.7 MAO.'TADI RC ?RISSURI AS DiDICA!D Ui 4.3.4.6 I7 PRISSURI C;CRIASIS. MAni A N TE S CCOLE;3 MCDI UNTIL AN RC PUMP IS STARTD CR S IAM GE;I?aTCR CCOLC;G IS ISTA3LISED AS nc:CA D 3Y ISTA2LISEO;G CONDITIONS DISCM3 D Di 4.3.4.3.1 CR 4.3.4.3.2. WHEN TEIS OCCURS, PROCID AS DIRICTID IN *ECSI STI?S. CO TO STI? 4.3.2 I? 70 RCD TLOW IS 7.STA3LIS?ID. 4 e i -loe l

69-1106001 4.4 FO!-LCCA OVIEC00LINC ""tA :Sirc WI ;! 7IntJa IR AVAILASLI 'i 4.4.1 nc!CIATILY ?.ZSTART A RC ?OT IN IACH 100? II THZ RCS IS I 50 7 $U3C00LD. i i 4.4.2 C0!CROL STTO! ?RISSURI VIA TUP 3!!!I 3Y? ASS OR A"'!OSPERIC OCO VALVIS TO STA3ILII: OR CO: RCL ?LA:C EA'"UP. i NOTI: CONSDIRA3LI 'TI MAY I!AVI ZIri ADOD 70 TRI RCS. TERITOE, TO PEvr:0 RCS FRCM GOI:'c SCLD, THE ) A307I ACTICN MAY 3I NICISSART. 4.4.3 AS LCNG AS *E RCS IS MAECADiD 50 7 SU3C00LD, *3RO TI.I EPI /MU AND L"s."IDOW FLOW TO MAUCAri ??2SSURIZIR LIVIL AT % 100 CCF.~eS. 4.4.4 USUG TUR31NI 3Y? ASS VALVIS AND TECWA"'IR SYSTDf, CO CROL S IAM GCIIRATORS AS NIEC *O LO!IT PLA C EIA.i.,e U:C*L RC PRISSURI CONTROL CAN 3I RI-ISTA3LISHID WITH TEI ??2SSU?.I;IR. NOTI: COLD RCS WATER MAY HAVI.3Irl ADDD TO *HZ ??2SSUR!:IR; TERITORI, A PERIOD OF TDII MAY " APSI 3ITORI NCM1AL RC PRESSURI CONTROL CAN BI ISTA3LISHID WI"'"3 TEI PRISSURIZIR 'i HEATIRS. 4.4.5 ONCE ?RISSURI CONTROL IS RI-ISTAILISHID, USI NCE :AL EATi,l?/ C00LDCWN ?ROCDURI TO ISTA3LISH DIS! RID PLA:C COEITIONS. e .n.

69-H06001 [ 4.5 ACTIONS FOR INADE0CATE CORE COOLING 4.5.1 IMMEDIATE STEPS 70R INADEQUATE CORI COOLING ~ NOTE: !? RC ? UMPS ARE RUNNING, DO NCT TR:? ? UMPS. THIS SUPERCEDES INSTRUCTIONS IN SECTION 2.1. 4.5.1.1 VERITT HP!/LPI SYSTEMS ARE PUNCT 0NING PROPERLY WITH MAIIMUM FLOW. START MAKIU? PUMP (S), I? I POSSIBLE, TO INCREASE INJICTION FLOW. J' 4.5.1.2 VERI 7T STIAM GENERATOR LEVEL IS 3E NG CONTROLLED j AT 95I ON OPERATE RANGE. NOTE: FOR TECO STIAM GENERATOR LEVIL SHOULD 3E AT 96 INCHES INDICATED ON THE STARTUP RANGE s CAUTION: REFERENCE LEG 30! LING COULD GIVE d ,K e FALSE LEVEL INDICATION et 4.5.1.3 DEPRESSURIZE OPERATIVE STEAM GENERATOR (S) TO Ehrr ESTABLISH A 10007/HR DECREASE IN SECONDARY 7' SATURATION TEMPERATURE. f:?! 4.5,.1.4 ENSURE CORE FLOOD TANK ISOLATION VALVES ARE OPEN. ig '4.5.1.5 IT REACTOR COOLANT SYSTEM PRESSURE INCREASES TO 2300 PSIG (1500 PSIG FOR D3-1) OPEN PRESSURIZER (hj PORY TO REDUCI REACTOR COOLANT SYSTEM PRESSURE. ,'.h .m! RECLOSE PORV WHEM RCS TALLS TO 100 PSIG A30VI 1; fi THE SECONDART PRESSURI. REPEAT I? NECESSARY. g{j IT PORY IS NOT OPERA 3LE, PRESSUR ZER SAFETT 15 VALVES WILL RELIEVE PRESSURI. ,p 4.5.1.6 PROCEED IMMEDIATELY TO 4.5.2. 5I' 4.5.2 WHEN THE INDICATED INCORE THERMOCOUPLE TEMPERATURES OR p HOT LEG RTD TEM?IRATURES ARE SUPERHEATED FOR THE EIISTING OPERATORACTIONSEALLBI3A RCS PRESSURE, -{ DETERMINED FROM FIGURE 3, BY A SAMPLE OF THI HIGHEST d4 INCORE THERMOCOUPLE TEMPERATURE READINGS TO DETERMINE THE {k CORE EZIT THERM 0COUPLZ TEMPERATURI. ([ NOTE: MORI THAN ONE THERMOCOUPLE TEM?IRATURE READING fi SEC ULD 3E USED (70R IIAMPLE USE THE AVERAGE OF 5). 1% 93

a 69-1106001 4.5.3 WHEN THE INCORE THERMOCOU?LI TIM?IRATURI HAS 3EIN DITERMINID ?IR SICTION 4.5.2, GO TO THI SICTION IND:CATID 3ILOW. INCORI THIRMOCOU?LI TIM?IRATURI SECTION w. INCORI Tc i SATURA!!ON 4.1.6 h CURVE 1 A.INCORI Tc < CURVI 2 ?!GURI 3 4.5.4 )q INCORI T: 1 CURVI I ?!GURI 3 4.5.5 $U NOTI: TII INCORI THIRMOCOU?LI IIMPIRATTRI RIADINGS

e.,

SRALL 3I CONTINU0CSLT MONITORID UNTIL THE INDICATID l INCORI THIRMOCCU?LI TIMPIRATURIS RITURN TO SATURATION TIM??RATURI 70R THI IIISTING RCS .$.4' }E PRESSURI. 4.5.4 ACTIONS FOR CURVI 1 1 INCORI Tc < CURVI 2 FIGURI 3 4.5.4.1 I? RC PUM?S ARI NOT OPERATING, START ONI PUM? PIR LOO? (I? ?OSSI3LI). THI3 INSTRUCTION ap f%.. SUPIRSIDES PRIVIOUS INSTRUCTIONS TO TRI? t RC ? UMPS. jp: NOTE: DO NOT 3!? ASS NORhAL INTERLOCKS. ?!; I 4.5.4.2 DI?RISSURIII OPERATIVE STIAM GINIRATOR(S) AS 4;

  • a RAPIDLT AS POSSI3LE TO 400 PSIG OR AS FAR AS t

.21 NICISSART TO ACHIIVE A 10007 DICRIASE IN ]} 2 SECONDART SATURA!!ON TEMPERATURI. I! D' 4.5.4.3 0?IN THE PORV, AS NICESSARY, TO MAINTAIN RCS 7,; i PRESSURI WITHIN 50 ?SI 07 STIAM GINIRATOR h SECONDARY SIDI PRESSURI. Y i T NOTI: I? STIAM GENERATOR DI?RISSURI7ATION WAS NOT POSSI3LI, 0?IN PORY AND LIAVI .$7 OPIN. 4.5.4.4 IMMIDIATILY CONTINUE PLANT C00LDOWN 3Y MAIN-IN TAINING 100?/HR. DECRIASI IN SECONDARY F" c S ATURATION TIMPIRATURI TC ACd!IVI 150 ?SIG 2 RCS ?RISSURI.

]

CAUTION: !? AUI!LIARY FIID PUM? IS SU??L;ID 3! MAIN STIAM, 30 NOT DICRIASI d ' t ?RISSURI 3ELOW THAT PRESSURI NICISSART -j FOR AUIILIARY FIID PUM? 0?IRAT:0N. 'd met, -- t

69-1106001 4.5.4.5 !? THE AVERAGE INCORE THERMOCCUPLE TEMPERATURE INCREASIS TO CURVE 2 FIGURE 3 PROCEED IMMEDIA~ELT %h ' TO SECTION 4.5.5. Y! 4.5.4.6 WHEN RCS PRESSURE REACHES 150 PSIG, GO TO APPENDIX "A". -( .4.5.5 ACTIONS FOR INCORE Tc 1 CURVE 2 FIGURE 3 .c p.< 4.5.5.1 IF POSSI3LE, START ALL RC PUM?S. "S NOTE: STARTING INTERLOCKS SHOULD 3E DEFEATED E -r-IF NECESSART. m'

  • 1.

4.5.5.2 DEPRESSURIZE THE OPERA *IVE STIAM GENERA *0R(S) ) AS QUICKLT AS POSSI3LE TO ATMOSPHERIC PRESSURE. P CAUTION: IF AUXILIARY FIED PUM? IS SU?? LIED 1: BT MAIN STEAM, DO NOT DECREASE

  • i PRESSURE 3ELOW TEAT PRESSURE I

NECESSART FOR AUI!LIART ?IED PUMP OPERATION. 4.5.5.3 OPEN THE PRESSTRI;ER PORY AND LEAVE OPEN. 2 ,N0

  • E :

THE RCS WILL DIPRESSURIZE AND THE h, LPI STSTEM SHOULD RISTORE CORE COOLING 4.5.5.4 WHEN INCORE THERMOCOU?LE *EMPERATURES RETURN TO THE SATURATION TEMPERATURE FOR THE ZZISTISG I,'_ s RCS PRESSURE - AND - THE LPI SYSTEM IS g DELIVERING FLOW, PROCEED AS FOLLOWS: 4.5.5.4.1 CLOSE THE PRESSURIZER PORV; RIOPEN b IF RCS PRESSURE INCREASES A30VI 150 PSIG. ibt. 4.5.5.4.! DECREASE To TWO (2) RC PUMP OPERATION f (ONE PER LOOP). F 4.5.5.4.3 ISOLATE THE CORE TLOOD TANKS. 4.5.5.4.4 MAINTAIN STEAM GENERATOR PRESSURE AT ? ~ ATMOSPHERIC OR AS LOW AS 70SS!3LE IF MAINTAINING AUZ LIART FEED PUMP !N 'k e OPERATION OFF 07 MAIN STIAN. [' 4.5.5.4.5 CONTROL HPI PIR 3.3.

== b i l _... r

69-1106001 4.5.5.4.6 MON!!OR 3WST LI7IL AS LO-LO LI7IL La LIMITS ARI AP?ROACIID, ALIGN L'* [~ SYSTIM 70R SUCTION TROM K3 SUMP. CLOSI THE L?I 3WST SUCTION VAL 7ES. Ij NOTE: I? I?! IS RIQUIRID PIR 3.3, ALIGN LPI AND H?! IN ?! GGT 3ACK

  • l MODI.

CLOSI E?! SUCTION 7AL7ES je TO 3WST. 4.5.5.4.7 GO TO A??INDII "A". e e O e 4 O I -t3-

.s. 69-1106001 A?}'E;; DIX A LP I CO OT.I::C A.I Dr.64.4%....s....,

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L..,.,S. 20 ; St., rect, ..e C,., 6, s .ws o s. STI? A.3. I A.1.1 S ART L?I PU193. !? 30n! 2005 ARI OPIR.t;LI, CO ;0 STIP A.I. ?CR O'.II L'2'T. v'u C4."vs.2'Lt-v.n.'-.'t..-. C i e '.'.... L..'.' w,-s' /.S r....*S. ^ . c'..a' a v.- 6 c. v THI OPIR/OLI LPI TCT tcI.L 3I U$c ;0 l'AnCAI:: SYS;;; I;,T:.C?.Y. A.1.2 OBTAri ?Kr".A.RY SYSTDI CONDI"'ICNS CF 28C7 AND s 250 PSIG. A.1.3 ALICU THE disci!ARCI 0? THI OP.".*.M3LI LPI PU:2 TO nC SUCTIC: S 0~ O*I EPI PCTS AND TAKI SUCTION FRCM THE L';ST. IT T1C 3NST IS AT TII LCU LIVIL ALA?Ji, ALICU LPI SUCTION FICM T C R3 SU2 A!O SHUT SUCTION ?T.0% DWST. A.1.4 START TIC CPIRAILI LPI ?O2 S?ICITID A20VI. TEI IDI-L?! SYSTCIS VII.L NOW BI Di "?ICCY EACK" A'iD 11?! FLC*! IS }!AEChE*OiG SYS!C! PPISSURI. A.1.5 Co To S*.NCLI RC PC 2 OPIRATION. A.1.6 WHIN DE SICOND LPI PCT IS AVAILABLI, ALIGN IT 2: TIC DICAY ICAT MODI AND C012C:CI DECAY EIAT RCICVAL. (DECAY HEA SYSTCt TLQ*i CRIATIR THAN 1000 CP:!). SECURI RE!AE;U C RC ?C2 VIC; DICA'.' HI.'.T RD! OVAL IS ISTA3LISIIID. CAUTICN: VIRITY 3!AT AOIQUA*I N?SH I%IS S FOR TIC DICAY ET.'s? PDT IN THE DH RI: CVAL 1:0DI. !? E:ADIQUATI, TRA:;572K TO LPI IIODI. A.1.7 ROUCI R".\\C OR C00LAN"' ?RISSURI TO 130 ?S!.C 3Y 31RomC:C E?!.: Z. Coh. sw,u .r K. m.r,.~.w.!.,. L.S... DI. 3e v. u..- 6 - v..> e. a-. - Sv. s..... i Co e.--at.. e ...s m.w u$ s w s.!A3h. A.s Sv. S~.

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-g- ~ 69-1106001 A.1.8 SICURI n!I IIPI ?U:!? A!!D S11I?T TE LPI PC:? SU??!!/U:? iT TO nC L?! UlJECTIO;t l'0DE. A.1.9 RIDUCI RIACTOR C00UJ:T TCTERAC:R: TO 100 F 3Y CO:;-~!OLLI::0 OiI DECAY EAT SYSTri COOLIR BY? ASS. NOTI: IF 0::I 0F TE L?I/ DECAY HIAT ?C.'?S IS LOST, RI UTJ: 70 OTSG COOLI::C USIiG NATURAL CIROC.ATION OR C :I RIACTOR 000Ud:- ?Q2 (A1). A.2 COOLDCRi O!! TWO L?I PD2S A.2.1 l'.ADCADI RCS PRL3SURI AT s 250 PSIG AND RIDUCI RCS TD2I?r0RI TO 1 2807. A.2.2 ALIGN ONI L?I Pte UT DII DICAY E.C RE:0 VAL MODI. A.2.3 SICUP.I 0:E RC PC2 IF T'.?O ARI CPIRATC*C. A.2.4 START DC DICAY EAT PC2 DI !?.I DICAT EIAT R.CICVAL MOOI,.CD UEI'i DICAY li2AT SYS'"E! FLOW IS CRIAtIR THAN 1000 G?:!, SICURI 21I RC':*2:0 RC PC2. A.2.5 RIOUCI RC ??2SST.;RI TO 150 PSIC 3Y THRO m rig HPI FLOW. CO::510L RC TDGIRATURI To MAUCAri AT LEAST 50 PSI MARCIN TO SATURA!!O : ??lSSUT.I. A.2.6 START THI SICO::D LPI ?tT? IN TEI L?! D JECTION MODI. SICURI E?! PC2. A.2.7 SEI?T L?I SUC ION FROM O!I IWST TO OII RTAC OR BUILDEIG SC2 W.J.I: SUTTICIOC UTSE IS AVAU.A3LI. NOTE: UlIS IS DESIRA.'E.I O AVOID U:::ECISSARY QUA:CI!!IS CT *AT 2 IN CO:CAIN:2:C. A.2.8 EDUC RTAC OR C00IXC "'D2 Iran:RI TO 100 7 3Y CONTROLLD:0 HI DICAY HIAT SYSTD1 C00LIR 3Y? ASS. NOTI: IT CNI CF TIE L?!/DICAY EA ?C:?S IS LCST, RTJF2: 70 OTSC i COOLING USING MATURAI. CIRCUIXJION CR CNI RC ?C2 PER A.1. l -17

69-11C6001 ,. A.3 COOL DCt.*:: itC S*1:ITE! A" FATIIRATIC!: i A.3.1 l'.AOCA3 RC PRESSURE AT s 250 ? SIC. I 1 l l ALIGN 0::I LFI ?ti!P 50 SUCTICN OF lir.117I ?L ?S A D 11I Si.:CT C:: A.3.2 70 THE RIACTOR BUILDI::G Si;::?. (Si!UT 3*2S7 SUC~IC:l VAI.*.'I FOR ""HI l ?C!?. ) A. 3. 3' ,411m! d. ,.,S R...... .-.0.0. ... S, S _.n..,.. :..,. r . r .. u4

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  • ~1I:1 ?RE!ARY SYSTD! TDEIRATURI 3ECC:GS SUICCCI.ID IT AT LY.AST 50 7

= CD TO A.1.1. A.4 CCCLDCt.7i t. I!Ct.'T RIAC On C::CLANT ?U:2S A.4.1 RCS U!TL'J., CONDITIO::S A?2: PRISSL72150 PSI, TE2IRATURI AT SATURATICN. A.4.2 AI.ICN LCW PRISSLT2 EiJICTIC:t SYSTI:I FOR Si;CION FRCM RIACTCR 2UILO!:;0 SL*.f? AND PLACI I::TO SIRVICI. A.4.3 3ALANCE L?I INJICTIC:i AND CONTRCL RC TI:2I"lA-w7.I WI~H DECAY :-2C CCCLI'tS. A.4.4 ISCLATI Co?2 FLCCD TA::RS. A.4.5 CO TO S..e A.1.1 AND 70LLOW DII PROCIDURI C'V7N HI?2, IC::0RU G THE INSTRUCTIONS RI! ATI:;0 TO RC YL72 0?l2CICN. d ._m,,,__

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    • 1 4 0

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69-1106001 TIGURE 2 FOR TECO ONLT NOT NEDD FOR LOWERED LOOP PLANTS

69-uC6001 Figure 3 CORE EXIT THER*.:0 COUPLE TE'aPERATURE FOR INA0 EQUATE CDP.E COOLING 1200 1100 5 [1 CURVE *2 2 3 TCLAD LESS THAN 1500*F E' 1000 E E 900 E O M* 800 -/ CURVE #1 f 1 u TCLAD LESS THAN 1400*F 700 600 500 - 400 200 S00 1000 1400 1800 2200 Pressure asis { -n.

69-1106001 i Part II: Sccl1 Break phenomena - Descriction of Piant Eehavior ~ 1. Int oduction A loss-of-coolant accident is a condition in which liquid inventory is lost from the reactor coolant :ysten, Due to the loss of mass frem the reactor coolant system, the mest significant sher -tem symotem of a less-cf-coolant acefdent is an uncontrolled reduction in the reactor coolant systam pressure. The reactor protection system is designed to trip the reactor on icw pressure. This should occur before the reactor coolant system reaches saturation conditions. The existence of saturated conditiens within the reactor system is the principal longer-term indication of a LOCA and requires special consideration in the development of operating procecures. Following a reactor trip, it is necessary to remove decay heat frca the reac*.or core to prevent damage. However, so long as the reactor core is kept covered with cooling water, core damage will be avoided. The ECCS-systems are designed to respond automatically to low reactor coolant pressure conditiens and take the inital actions to protect the reactor core. They are si:ed to provide sufficient water to keep the reactor core covered even with a single failure in the ECCS systems. Subsequent operator actions are required ultimately to place the plant in a long-tem cooling mcde. The overall objective of the automatic emergency core cooling system and the followup operator actions is to keen the reactor core cool. A detailed discussion of the small break LOCA phenomenalogy is presented in this section. This discussion represents Part II of the operating procedure guidelines for the development of detailed operating procedures. Part I presents the more detailed step-by-step guidelines. -

69-1106001 The response of the primary system to a small break will greatly depend on break si:e, its location in the system, operatien of tne reactor coolant pumps, the number of ECCS trains functioning, and the availability of seccndary side cooling. RCS pressure and pressuri:er level histories for vaMous combinations of parameters are cresented in order to indicate the wide range of system behavior which can occur for small LOCA's. 2. Jacact of RC pumo Oceration on a Small t.0CA With the RC pumps operating during a small break, the steam and water will remain mixed during the transient. This will result in 1tquid being discharged cut the break continuously. Thus, the fluid in the RCS can evolve to a high void fraction.as shewn in Figure 1. The maximum void fraction that the system evolves to, and the time ~ it occurs, is dependent on the break size and location. Continued RCpump operation, even at high systcm void fractions, will provide sufficient core flow to keep cladding temperatures within a few degrees of the saturated fluid temperature. Since the RC4 can evolve to a high void fraction for certain small breaks with the RC pumps on, a RC ptap trip by any means (i.e., less of offsite power, equipment failure, etc.) at a high void fracticn during the small break transient may leed to inadequate core cooling. That is, if the RC pumps trip at a time period when the system void fraction is greater than approximately 70%, a core heatup will occur because the amount of water ~ left in the RCS would not be sufficient to keep the core covered. The cladding temperature would increase until core cooling is re-established by the ECC systams. For certain break sizes and times of RC pump trip, acceptable peak cladding temperatures during the event could not be assured and the core cculd be damaged. Thus, promet operator action to trip the 1 RC pumps upcn receipt of a low pressure ESFAS signal is requi.ed in order 69-1106001 to ensure that adequate core cooling is provided. Following the RC puno trip, the small break transient will evolve as described in the. subsequent sections. 3. Small 3reaks with Auxiliary Feedwater There are four basic classes of break response for s=all breaks with auxiliary feedwater. These are: 1. LOCA large enough to depressuri:e the reac*ar coolant system 2. LOCA which stabili:es at approximately secondary side pressure 3. LOCA which may repressurize in a saturated condition 4. Small LCCA which stabilizes at a primary system greater than secondary system pressure The system transients for these breaks are depicted in Figure.2. 3.1 LOCA Larce Enouch to Deeressurize Reactor Coolant System: Cunes 1 and 2 of Figure 2 show the response of RCS pressure to breaks that are large enough in combination with the ECCS to depressuri:e the system to a stable low pressure. ECCS injection easily exceeds core boil-off and ensures core :oolicg. Curves 1 and 2 of Figure 3 show the pressuri:er level transient. Rapidly falling pressure causes the hot legs to saturate quickly. Cold leg temperature reaches saturation somewhat later as RC pumps coast down or the RCS depressurizes below the secondary side saturation pressure. Since these breaks are capable of depressurizing the RCS l without aid of the steam generators, they are essentially unaffected by the availability of auxiliary feedwater. Upon receipt of a lcw pressure ESFAS signal, the operator must trip all RC pmps and verify that all ESFAS l acticns have been completed. The operator must also balance HpI flows such l that ficw is available through all HPI injection no::les even if only one HPI is available. The operator should also ba. lance LoI flews, shouTd the system be actuated, to ensure flew through both lines. The operator needs to take no further acticns to bring the system to a safe shutdcwn 69-1106001 condition. Rapid depressuri:ation of the steam generators would only act to accelerate RCS depressuri:ation. It is, however, not necessary. Restarting of the RC pumps is not desirable for this class of break. Long-te:-n cooling will require the operator to shift the LPI pump suction to the reactor building sump. 3.2 LOCA Which Stabilizes at Accroximately Secondary Side Pressure. Curve 3 of Figure 2 stiows the pressure transient for a break which is too small in combination with the operating HPI to depressuri:e the RCS. The steam ' generators are, therefore, necessary to remove a portion of core decay heat. Although the system pressure will initially stabili:e near the secondary side pressure, RCS pressure may eventually begin falling as the decay fieat level decreases. Curve 3 of Figure 3 shows pressuri:er level behavior. The hot leg temperature quickly equali:es to the saturated ( temperature of the secondary side and controls pHmary system pressure at saturation. The cold leg temperature may remain slightly subecoled. If the HPI refills and repressuri:es the RCS, the hot legs can become subecoled. The imediate operator action is to tHp the RC pumps upon receipt of the law pressure ESFAS signal and then verify E5FAS functions. The. operator must then balance HPI in order to ensure flow through each high pressure injection line. Followup action by the operator is to raise the emergency feedwater level to 95% on the operating range and check for established natural circulation. This is done by gradually depressuri:ing the steam generators. If this test fails, intermittent bumping of a RC pump should be performed as soon as one is available. Continued depressuri:stion of the steam generators with natural circulation leads to cooling and depressuri:ation of the RCS. The operator's goal. is to depressuri:e the RCS to a pressure that enables the ECCS to exceed core boil-off, pessibly refill the RCS, and to ultimately establish long-ter.n cooling. --

69-1106001 ~ .j 3.3 LCCA Which May Recressurize in a Saturated Condition. Curve 4 t of Figure 2 shcws the behavior of a small break that is.po small, in c::mbination with the HPI, to depressuri:e the pMmary system. Althougn steam generator feedwater is available, the loss of primar/ system coolant and the resultant RC5 voiding will eventually lead to interruption of natural circulation. This is followed by gradual repressuM:ation of the primary systam. It is possible that the primary system could repressuri:e as high as the pressuri:er safety valve setpoint before the pressure stabili:es. This is shown by the dashed line in Curve 4. Once enough inventory has been lost from the primary system to allow direct steam condensatien in the regions of the steam generators contacting secondary side coolant, the primary system is forced to depressurf:e to the saturation pressure of the secondary side. .Since the cooling, capabilities of the secondary side are needed to continue to remove decay heat, RCS pressure will not fall below that on the secondary side. HPI flow' is sufficient to replace the inventory lost to boiling in the core, and condensation in the steam generators removes decay heat energy. The RCS is in a stable thermal condition and it will remain there until the operator takes further action. The pressuri:er level response is characteri:ed by Curve 3 of Figure 3 duMng the depressuri:aticn, and Curve 4 of Figure 3 during the temporary repressuM:ation phase. The dashed line indicatss the level behavior if pressure is forced up to the pressuri:er safety valva setpoint. During this transient, het leg temperature will rapidly appreach saturation with the initial system depressuM:ation, and it will remain saturated during the whole transient. Cold leg tamperature will approach saturation as circulaticn is Icst, but may remain slightly subcooled during the repressuri:ation phase of the transient. Later RC5 depressuri:ation could cause the cold les tamparatures to reach saturation. Subsequent refilling of the primary -ts-

69-1106 col I system by the HPI might cause temporary interruption of steam condensation in the steam generator as the primarygide level Mses above the seconcary side level. If the depressuM:ation capability of the break and the HPI is insufficient to offset decay heat, the primary system will ence mere repressuri:e. This decreases HPI flow and increases loss through the break until enougn RCS c olant is lest to once more allcw direct steam condensation in the steam generator. This cyclic behavior will stop once the HPI and break can bala'nce decay heat or the operator takes some action. The operator's imediate action is to trip the RC pumps upon receipt of the low pressure ESFAS signal and verify the completion of all ESFAS functions. The operator should then balance HPI flow. Following that, he should raise the~ steam generator level to 95% of the operating range and check for natural circulation. If it is positive, he should depressuri:e the steam generators, cool and depressuri:e the primary system, and attempt to refill it and establish long-term cooling. If the system fails to go into natural circulation, he should open the PORY long enough to bring and hold the RCS near the secondary side pressure. Once natural circulation is established or a RC pump can be bumped, he will be able to continue depressuri:ing the RCS with the steam generators and establish long-tem cooling. 3.4 Small t.0CA Which Stabili:es at Pa Psee. Curve 5 of Figure 2 shows the behavior'of the RCS pressure to a break for which high pressure injection is being supplied and exceeds the leak flow before the pressuri:er has emptied. The primary system remains subcooled and natural circulation to the steam generator removes core decay heat. The pressuri:er never emoties and continues to control primary system pressure. The operator needs to trip the RC pumps and ensure that ESTAS acticns have occured. Throttling of HPI ~ 0 is permitted only after RCS subcooling of 50 F has been established, the pressuri:er has refilled, and natural or forced circulation has been ~ ~ 1

69-1106001 ~ verified. A restart of the RC pumps under these conditions is desirable for plant centrol. 3.5 Small Breaks in pressurizer. The system pressure transiene for a small break in the pressuri:er will behave in a manner similar to that previously discussed. The initial decressuri:stien, however, will be more rapid as the initial inventory less is entirely steam. The pressuri:er level response for these accidents will initially behave like a very small break without auxiliary feedwater. The initial rise in pressurizer level shown in Figure 4 will occur due to the pressurs reduction in the pressuri:er and an insurge of coolant into the pressurizer from the RCS. Once the reactor trips, system contraction causes a decreasing level in the pressurizer. Flashing will ultimately occur in the hot leg piping and cause an insurge into the pressurizer. This ultimately fills the pressurizer. For the remainder of the transient, the pressuri:er will remain full..Toward the later stages of the transient, the pressurizer may contain a two-phase ihre and the indicated level will show that the pressurizer is only partially full. Except for. closing the p0RV block valve, operator actions ind system response are the same for these breaks as for similar breaks in the loops. 4. Small Breaks Without Auxiliary Feedwater There are three basic classes of break response for small breaks without auxiliary feedwater. These are: 1. Those breaks capable of relieving all decay heat via the break. 2. Breaks that relieve decay heat with both the HpI injection and via the break. 3. Breaks which do not automatically actuate the HpI and result in system reoressuri:ation. The system pressure transients for these breaks are depicted in Figure 5..

69-12.06001 ~-- I 4.1 LOCA's Laree Enouch to Deeressuri:e Reactor Coolant System. For Class 1 (curve 1 of Figure 5), RC system pressure decreases smoothly throughout the transient. For the larger breaks in this class, CFT actuation and LpI injection will probably occur. For the smaller breaks of this class only CFT actuation will occur. Auxiliary feedwater injection is not necessary for the short-tern stabili:ation of these breaks. The pressurizer level for this transient rapidly falls off scale. Operator action and plant response are similar to these described for this class of breaks with a feedwater supply. 4.2 LOCA's Which Reach a Semi-Stabili:ed State. For Class 2 (Curve 2 of Figure 5) breaks, the RC pressure will rapidly reach the low ;iressure ESFAS trip signal (about two to three minutes). With the HPI's on, a slow system depressurization will be established coincident with the decrease in core decay heat. No CFT actuation is expected. Auxiliary feedwater is not necessary for the short-tenn stabilization of. these breaks. The pressuri:er level for this transient rapidly falls off scale. The operator needs to trip the RC pumps upon the 1cw pressure ESFAS signal, verify completion of all ESFAS functions, and try to establish secondary side cooling. Balancing of the HPI must also be performed. If steam generator feedwater cannot be obtained and RCS pressure is increasing, the operator should open the PCRV and provide all the HPI and makeup capability possible. The goal is to depressurize and cool the core with the ECCS, the PCRY, and the break. If secondary s1de cooling is again established, the operator should verify natural circulation, and if unavailable, bump a RC pump to conglete RCS cooldown with the steam generators. At this point, the PORY can be closed, the systam refilled, and icng-tann cooling established.

69-1106001 I 4.3 Small LCCA's Which do not Actuate the ESFAS. Automatic ESFAS actuation will not occur for Class 3 (Curve 3 of Figure 5) breaks. l Once the SG secondary side inventory is boiled off, system repressurizatien will occur as the break is not capable of removing all the decay heat being generated in the core. System repressurization to the p0RV or the pres-surizer safety valves will occur for smaller breaks in this class. For the "zero" break case, repressuri:ation to the p0RV will occur in the first five minutes. Operator action is required within the first 20 minutes to ensure core coverage throughout the transient. For the 177-FA lowered loop plants, this action can be either manual actuation of the auxiliary feedwater system or the HPI system. The establishment of auxiliary feedwater will rapidly depressurize the RCS to the E5FAS actuation pressure, and system pressure will stabili:e at either the seconuary side SG pressure or at a pressure where the HPI equals the leak rate. Upon receipt of the low pressure E5FAS signal, the operator must trip the RC pumps. i For the Class 3 breaks, pressuriter level response will be as shown in Figure 6. The minimum refill time for the pressuri:er is that for the. "zero" break and is shown in Figure S. After initially drawing inventory from the pressuri:er, the system repressurization will cause the pressuri:er level to increase, possibly to full pressuri:er level. Once the operator action to restore auxiliary feedwater has been taken, the system

~ ~ ~ ' 69-1106001 decressuri:ation will result and cause an outsurge fr:m the pressuri:er. Complete Icss of pressuri:er level may result. For the smaller breaks in Class 3 which result in a system repressuri:ation folicwing the actuation of the HPI system, pressuri:er level will increase and then stabili:e. Without auxiliary feedwater, both the hot and cold leg temperatures will saturate early in the transient and, for the Class 1 and 2 breaks, will remain saturated. Fcr the Class 3 breaks, once auxiliary feedwater is estelished, the cold leg temperatures will rapidly decrease to approximately the sautration temperature corresponding to the SG secondary side pressure and will remain there throughout the remainder of the transient. Hot leg temperatures will remain saturated thmughert the event. The operator needs to manually initiate all ESFAS actions, balaoce HpI flow, and attempt to restore secondary side cooling. In the meantime, he i should actuate the makeup pump and open the PORY in order to cool the enre and limit the RCS repressuri:ation. Once feedwatc-is available, he can close the PORY and continue the RCS cooldowr and depressurization with the steam generators. If natural circulation has not been established, he can bump a RC pump to cause forced circulation. The goal is to depressuri:e to where the ECCS can refill the RCS and guarantee long-tern cooling. 4.4 Small Breaks in pressuri:er. See the writeup for small breaks in pressuri:er with feedwater. Small breaks in the pressuri:er wtli differ frem those in the 1 cops in the same manner as those previcusly described in the section addressing small breaks in the pressuri:er with auxiliary feed. 5. Transients with Initial Resoonse similar to a small Break ~ Several transients give initial alarus similar to small breaks. These transients will be distinguished by additicnal alarms and indications or subsequent systen response. Overcooling transients such as steam ifne breaks, increased feedwater..

69-1106c01 ~ 1 i flow, and steane generator overfill can cause RC3 pressure decreases witn l'ow-pressure reactor tMp and ESFAS actuation. But steam line breaks . Actuate icw steam pressure alarns for the affected steam generator, and steam generator over# ills result in high steam generator level indications. The overcooling transients will repressuri:e the primary system because of HPI actuation, and will return to a subcooled conditien duMng repres-sum:ation. The immediate actions for both overcooling and s=all break transients are the same, including tripping of the RC pumps. The operator will recogni:e overcooling events during repressurization, if not sooner, and is instructed to throttle HPI and restart the RC pumps, j if subecoled conditions are established, by the small break operating instructions. A loss-of-feedwater transient wili result in a high reactor system pressure alarm but does not give an ESFAS actuation alarm. A loss of integrated control system power transient starts with a high RC pressure trip. After the reactor trip, this becomes an overcooling transient and will give low reactor system pressure and possibie ESFAS actuation. Steam generator levels remain high and the system becomes subcooled during repressuM:ation. Design features of the B&W NSS provide automatic protection during the early part of small break transients, thereby providing adequate time for small breaks to be identified and apprcpriate action taken to protect the system. The only prompt manual operator action required is to tM p the RC pumps once the low pressure ESFAS signal is reached. 6. Iransients that micht Initiate a LOCA There are no anticipated transients that might initiate a LOCA since the PCRV has been reset to a higher pressure and will not actuate during anticipated transients such as loss of main feedwater, turbine Mp, or loss of offsite power....

~ 69-1106001 ~ However, if the PORY should lift anc, fail to reset, there are a ~ number of indications which differentiate this transient.(rem the anticicated l I trensients identified above. These include: o ESFAS actuation o Quench tank pressure / temperature alarms o Saturated primary system o Rising pressuri:er level These additienal signals will identify to the operator that in addition to the anticipated transient, a LOCA has occurred. In the unlikely event that small breaks other than a 21 functioning PCR7 cccur after a transient, they can be identified by initially decreasing RCS pressure and convergence to saturation conditions in the reactor coolant. Small break repressuri:ation, if it occurs, will fo11cw saturatien conditiens. By remaining aware of whether the reactor ecof ant remains subecoled or becomes saturated after transients, the operator is able to reccgni:e when a small break has occurred. s. HPI Throttlim For small LOCA's, the HPI system is needed to provide makeup to the RCS and must rema,in operable unless specific criteria are satisfied. The basis for these criteria are described below. For certain small breaks, systen depressuri:ation will result in LPI actuation. Since the LPI is designed to provide injection at a greater capacity than the HPI, termination of t!.e HPI is allered. Mcwever, this ~ action should only be taker if the ficw rate through each line is at least 1000 gpm and the situation has been stamie for 20 minutes. The 20-minute time delay is included to ensure that t.ie systan will not repressuri:e and result in a loss of the LPI fluid. In the event of a core flooding line break, the LPI fluid entering the broken core flooding line will not reach the vessel. 111us, in crder to ensure tha: fluid is continually being injected to the RV for all breds, the L?! must be providing fluid through both lines. The 1000 spa is equivalent to the ficw frem 21 _

~ 69-1106001 two HPI pumps and ensures that upon termination of the HPI ptanos, adequate flow is being delivered to the RY. Throttling or termination of the HPI flow is also allowed if all the following criteria are met: 0 A'. Hot and cold leg tamperatures are at least 50 F below the saturation tamperatures for the existing RCS pressure. B. The action is necessary to prevent the indicated pressurizer level from going off-scale high. under these conditicas, the priman sy: tam is solid. Continued HPI flow at full capacity may result in a solid pressurizer and wculd result in a lifting of the PORY and/or the pressurizer code safety valves. This mayintiurnleadtoaLOCA. Thus, HPI flow should be throttled to 0 mais;tain a stable invento'ry in te RCS. However, if the 50 F subccoling cannot be maintained, the HPI shall be immediately reactivated. HPI flows shduid also be throttled to prevent violation of the nil ductility temperature (NOT) for the reactor vessel. This concern can only arise if the fluid tamperature 8 within the reactor vessel 4 at least 50 F subcooled. A curve of the allowable dcwncaner temperature for a given RCS pressure is provided within the operating guidelines. The downcomer tamperature is detannined by one of two' methods: 1. If one or more RC pumps are cperative, the cold leg RTD reading will be essentially the same as the reactor vessel downcomer tamperature. 2. Without the RC pumps operating, the cold leg RTD's may not provide -

6 F1106001 temperature readings indicative of the actual RV downc:zner temperature, as a stagnant pool of water may exist at these locations. The incere thermoccuples will provide the best indicator of the dcwncomer temperature and should be utilized if no RC pumps are available. In order to ac: cunt for heat 0 added to the fluid from the core,150 F must be subtracted from the incore thennecouple readings to reflect the downc:m'er temperature. This method will result in temperatures which will be icwer than the j expected downcemer temperature. Thus, use of this methodology assumes that NOT will not be a problem. 9 e 9 9 9 1 l l S 9 -

69-1106001 BREAK SPECTRUN AVERAGE SYSTEM V010 FRACTION WITH THE RC PUNPS OPERATIVE AND 2 HPI PUNPS 100 / ~25- ~ ~ g f

  1. --===

[ / , 80 hf /'s 5/ e ,ig] sfi' ~ &ia s i! / /,- // 1 W 40 j ,/ / o.Sfj.3 'p /'. 20 / / /*/ j 0 O 400 800 1200 1600 2000 2400 2800 Tian, sac Figure 1

69-1106001 ~ PRES 3URE VS TIME-SMALL BREAK 3 W!TH AUXILIARY FEE 0 H i!3 1 2500 - j--- 3 / \\ / 1 / \\ \\ 2000 / I s# I ~ E 1500 = 1 4 = E N-1000 2 500 1 0 O 500 1000 1500 2000 '2500 3000 1500 4000 Tlas, see Figure 2 l h

69-1106001 i PRESSURIZER LEVEL VS TillE-SMALL BREAKS 11TH AUXILIARY FEEDWATER 100 p-q I l l 80 / ~ = / I O / l 50 / 1 / I i ~ / / \\ / I E 40 I = 5 y 20 I I L s. g 'I l O O 500 1000 1500 2000 2500 3000 3500 Time, see Figura 3 4 e. _. "'h 4 .m-e og-

69-1106001 PRE 33URIZER LEVEL V3 TIME FGR SMALL BREAK IN PRESSURIZER 100 ~ = 1 0 75 1 E3 i l 2 E 50 E 25 f 8 1 0 200 400 600 800 1000 Tlas, sac Figure 4 i ~39-l

69-1106001 1 SYSTEM PRESSURE VS. TIME-SMALL BREAKS N/0 AUXILIARY FEEDWATER 2500 J "IERG" r f IIAll O 2000 I /,-

  • 1500

/ f W_ / V 1000 \\ UARGE (I) 500 j 0 e 0 500. 1000 1500 2000 2500 3000 3500 4000 Time, sac Figura 5 i m-

69-1106001 PRES 3URIZER LEVEL VS. TIME-CLASS 3 BREAKS 1/0 AUXILIARY FEEDWATER la - (--- "ZERG"I BREAK 1 i 80 - = I I 2 80 - E l ONLY FOR SMALL CLASS 3 BREAKS z l / 40 / I I 20 - I l O I O 500 1000 1500 2000 2500 3000 3500 4000 Time, see Figure 8 t 8 4 -- - -

  • u-@

,9 9 w-

~ 69-1105CC1 PART II - APPC?DIZ A l INADEQUATE CORE CCOL2iG - DESCRI? TION Cy ?LANT 3EEAVICR 1.0 INTRODUCICN Folloviog a loss-of-coolan: accident (LCCA) in which the reactor trips, 1: is necessary to remove the decay hea: from the reactor core to preven: damage. Core hea: removal is accomplished by supplying cooli=g vater to :Se core. The va:e which is available for core cooling is a portion of the initial reactor coolan: systes (RCS) vater i=ventory plus any va:er injected by the emergency core cooling system (ECCS). The heat added to the cooling water is removed a via the steam genera:or and/or the break. As long as :he reactor core is hept covered with a mixture of va:.e: add steam, core damage vill b,e avoided. If the supply of coc11=g j l vatar to the core is decreased or in:e::up:ed, a lover

  • ure level in the core vill result. If the upper porticus of the core becomes uncovered, cooling for those regions will be by forced convec: ion :o superheated steam which is a low hea: ::ansfer regi=e.

Continued operation in the steam cooling m de vill result is eleva:ed core ta=peratures and subsequent core da= age. 2.0 LCSS OF RCS INVE *0RT WI H REACOR CCOL4;T PCMPS OPERA-*NG Vith the RC pumps opera:ing during a s=all break, :he steam and wa:e vill remain mixed during the ::ansten:. This vill resul: in liquid being discharged ou: :he briak concinuously. Thus, the fluid in the RCS can evolve :o a high void frac:icn. The void frac:fon of the RCS. e N 6 we e

~ O e'-tioecot indiestes the ratio of the volume of steam in the RCS :o the :c:al volume of the RCS. Since the 2CS can evolve :o a high void frac:ics for :s::ais s:411 breaks vi:h the RC pumps on, a RC pump ::1p by any =ea:s (i.e., loss i - of offsi:e power, equipmen: failure, a:c.) a: a high void fractice during the small break ::ansies: =ay lead to 'i=adequa:e core cooling. That is, if the RC pumps trip at a time period when :he sys:e= void fraction is greater than app;c=isately 7C%, a core hea:up will occur because the amount of water left in the RCS would not be sufficient to keep the core covered. The claddi=g te=pera:::e would increase until core cooling is re-es:ablished by the ICC systa=s. For certain 1 of RC pump ::1, accep:able peak cladding break si:es and times 7 tempera:ures during the event could not be assured and :he core could be damaged. Thus, promo: operator action to trip :he RC pu=ps upon 1 receipt of a low pressure ESFAS signal is required is order to-ensure j that adequate core cooling is provided. Fo11ovi=g the RC pu=p ::1p, the small break ::ansien: concerns about inadequa:e core cooling vill be the same as describad in the previous see:1on. If the RC pumps can not be ::1pped by the opera:or, the cos:inued forced circulation of fluid :hroughout the RCS will keep the core cooled. However, if little or =c ICCS is being provided ec the RCS, the fluid in the RCS vill eventually beco=a pure s:aa= due to :he continued energy addition to the fluid p;cvided by the core decay hea:. Under these circum-stances, an inadequa:e core cooling si:ua:Lon vill e=is:. Since. pm# (

t 69-1106031 ~ tha but removal proceso under forced circulatica is b2::cr han.h3 steam cooling mode dese:1 bed below fo: :he pumps off si:uatio=, de operator actions and indica:1ons dese:1 bed in the subseque== see:1c= are suffician: for i= adequate cort coo 11=g vi:h de RC pu=ps opera==g. 3.0 LOSS OF RCS I'.TE; TORY *.'r 20CT ?J.AC OR C00' A'"? Pr.M?S 0?'".?.C:G Withou :he RC pu=ps opera:isg, :he cooling of.he core is acec=plished by keepi=g the core covered vi:h a steam va e: =12:=e. & de fluid in the core is hea:ed, some of it or all of it ay be tur:ed to s:ess. If insuffician: cooli=g ve:er is avsilable to a1=tain.he s:aa=-vatar mixture covert =g the core, the core exit fluid :empera:=es vill begin to deviate from the saturation tempera =re cc:respondi=g to the ;; essure of the RCS. One i= mediate indica:1on d a: inadequate core cooling =ay exis: in the core is that the ta=pera:u== of the core ext: :he=. occupies and ho: leg 3D 's are sune: heated..A: this co=di:1on isadequa:e core cooling is eviden as the core vill be partially uncovered. Eevever, the degree of uncovery is no: severe enough to cause core da= age. "his condizion is not expected to occur but is no, by itself, a cause for ex=ame action. If the ICCS systa=s are f=sc:1oning r.o=.elly, de ta=peratures should re:urs to satuation vidou any actices beyond those curlined for a s=all break. yor incore the =ccouple ta=pera:ure indica:ing superheated condi:1ons the opera or should (a) verify emergency coc11r4 water is bei=g i=jected throuSh all HPI no:=les in:o the RCS, (b) d d.ia:e any addi:icnal sources of ecoling va:ar available such as de sca=dby makeup pu=p, (c) verify :he stea= generator level is being =ain-bed at the e=ergency level (d) if steam generator level is not a: 95*. of operating range (96 inches indicated on the s:artup range for raisvi icop plants), raise level to the 95: level, y ,n.-.

n-w w. (a) if tho dosirod stoam genera:o: loval canno: ho achievod, ac:ua:e day additional available sourcos of foodwa:or such as s:artup auxiliary feedvater pump,.(f) es:ablish 100*?/hr. cooldown of RCS via s:aam generator pressure con :al, (3) open core flooding line isolation valves if previously isolated, and (h) if RC pressure increases :o 2300 psig (1500 psig for D3-1) open :he pressuri:er ?cR7 :o reduce l RC pressure and reclose ?ORV when RC pressure falls to 100 psi above the secondary pressure. These a:: ions are d *.r e e : e d t o'sard d ep re s - 1 suriza:Lon of :he RCS :o a pressure at which :he ICCS va:er input exceeds core s:eam genera: ion. The align =en: of c:her sources of cooling va:er is the recogni:Los :ha: the injec:1on of the E?I sys:e= j alone is not sufficient to exceed core boil o I l If the incore thermocouple indications reach curve #1 on Figure 3 i in Par: I, the peak fuel cladding tempera:ure has reached approxi=a:ely 1 140007. Above this temperature level there is a potencial for claddings rupture. Also, the :1rcaloy cladding water reac: ion vill begin to add a significant amount of hea to the fuel cladding hereby grea:17 increasing the possibility of core struct' ural damage unless adequate core cooling is res ored. Non-condensible gas forma:1er. vill increase rapidly from this leve1 of fuel clad temperature. Tor incore thermocouple temperature indica:icus at or exceeding curve

  1. 1 on Figure 3 in Part I, the operator should (a) star: one RC pump du each loop, (b) depressurize :he steam generator as rapidly as

~ possibla :o 400 psig or as far as necessary to achieve a 100 7 0 decrease in satura: ion :empera:ure, (c) i= mediately continue :he e plant cooldown by =aintaining a 100 7/hr. decrease in secondary satura:1on temperature to achieve 150 psig RC pressure, (d) open the pressunizar pilot opera:ed relief valve (?ORV), as necessary, to relieve RCS pressure and ven: non-cond ensib le gases. The opera:or action in star:ing the RC pumps will provide forced flow core cooling and vill reduce the fuel cladding tempera:ures. The rapid depres-suri:ation of the steam generators vill help to depressurt:e the primary system to :he point where che core flooding tanks vill actua:e. S:opping the depressuri: :1on a: 400 psig (or a: a.

69-L105001 - *:odue: ion in se:ura:Los :empora:uro of 100 y) vill =aintnin the i tube :o che?.1 :e:pera:ure difference within the 100 y design 11=1:. TWe' con:inued cooldown to 150 psig vill reduce :he pri=ary sys:e= pressere to :he point where the Lov ? essure Injec:Lon Sys:en can supply cocling. The opening cf the ?ORV will also help :o l depressuri:e :he primary sys:em.' The ?ORV should be closed when l 1 the primary pressure is vi:hin 30 psi of the secondary pressure and ? then should only be used as necessary :o main ain the primary sys:e= pressure at no grea:er than 50 psi above the secondary sys:e= pressure. This ce: hod of opera:1on vill minimize the loss of va:er from :he primary system through the PORV. If the incore thermocouple readings reach curve'#2 on yigure 3 in Part I, the peak cladding t,empera:ure is approximately a: the 1800*7 level. This is a very serious condizion. A: this level of clad :smperature, significant amoun:s of. non-condensible gas are being generated and core damage may be unavoidable. -Ixtre=e measures are required by the opera:o: :o prevent major core damage. The goal of :hese actions is :o depressurize the RCS to a level where the core flooding tanks vill fully discharge and the LPI system can be actua:ed thus providing promp: core recovery. The operato should (a) depressurize the steam generators as rapidly as possible down :o a:mospheric pressure, (b) s: art :he remaining RC pumps and (c) open the PORV and leave 1: epen. 4.0 INADEOUATE CORE COOLING RISULTING yROM LOSS 07 STTAM GENERATOR MEAT SINK For a very small or non-LOCA even:, che core decay hea: removal is accomplished via the steam generators. If :ha: hea: removal is de-creasec or lost, the na: ural circula: ion of fluid wi hin :he RCS may be reduced or st.pped. The loss of natural circula:Lon for core

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