ML20078F417

Proposed Tech Specs 3.9.8.1, SDC & Coolant Circulation -- High Water Level, 3.9.8.2, SDC & Coolant Circulation -- Low Water Level & Refueling Outage Bases 3/4.9.8, SDC & Coolant Circulation

ML20078F417
Person / Time
Site:	San Onofre
Issue date:	01/30/1995
From:	SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML20078F389	List: ML20078F387 ML20078F402 ML20078F417
References
NUDOCS 9502020099
Download: ML20078F417 (54)

Text

,...

NPF-10/15-40235UPPLDIENT!!

M A55A k',-:CWo;V4WN>hWSA9kNW.-?

.i 1

1 l

ATTACHMENT "A" 2

EXISTING SPECIFICATIONS UNIT 2 4

?

l J

i t

i d

d 9502020099 950130 PDR ADOCK 05000361 P

PDR

u 89 j

1 REFUELING OPERATIONS 3/4.g.g SHUTDOWN COOLING AND COOLANT CIRCULATION

~

HIGH VATER LEVEL LIMITING CONDITION FOR OPERATION At least one shutdown cooling train shall be OPERABLE and in l

3.9.8.1 operation.#*

H00E 6 when the water level above the top of the reactor Appl 1CABILITY:

pressure vessel flange is greater than or equal to 23 feet.

ACTION:

With no shutdown cooling train OPERABLE and in operation, suspend all opera-tions involving an increase in the reactor decay heat load or a reduction in boron concantration of the Reactor Coolant System and imediately initiate cor-rective action to return the required shutdown cooling train to OPERABLE and Close all containment penetrations pro-operating status as soon as possible.

viding direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVElllANCE RE00fREMENTS At least one shutdown cooling train shall be verified to be in 4.9.8.1 a.

operation and circulating reactor coolant at a flow rate of greater than or equal to 2200 gpm at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

1. The shutdown cooling train may be removed from operation for up to I hour per 8-hour. period.during the performance of CORE ALTERATIONS in the vicinity ofi the reactor pressure vessel hot legs.

• A containment spray pump may be used in place of a low pressure safety injet-tion pump in either or both shutdown cooling trains to provide shutdown cooling flow.

(Subsequent to implementation of DCP 2-6863)

AMENDMENT NO. % 106 SAN ONOFRE - UNIT 2 3/4 9-8

n.

REFUft1NG OPERATIONS LOW WATER LEVEL 4

LIMITING CONDITION FOR OPERATION Two independent shutdown cooling trains shall be OPERABLE and at l

3.9.8.2 i

least one shutdown cooling train shall be in oper ation.*

APPttcABitITY: MODE 6 when the water level above the top of the reactor pressure vessel flange is less than 23 feet.

gHgi:

With less than tb quired shutdown cooling trains OPERABLE, imme-

rrective action to return the required shutdown a.

diately init! ate cooling trains i< OPERABLE status, or to establish greater than or equal to 23 feet of watar above the reactor pressure vessel flange as suon as possible.

With no shutdown cooling train in operation, suspend all operations b.

involving a reduction in boron concentration of the Reactor Coolant i

1 System and immediately initiate corrective action to return the Close all containment.

required shutdown cooling train to operation.

penetrations providing direct access from the centainment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

i SURVElttANCE REOUIREMENTS At least one shutdown cooling train shall be verified to be in 4.9.8.2 operation and circulating reactor coolant at a flow rate of greater than or equal to 2200 gpm at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

l

• A containment spray pump may be used in place of a low pressure safety injec-tion pump in either or both shutdown cooling trains to provide shutdown cooling flow.

(subsequent to implementation of DCP 2-6863)

AMENDMENT NO. 46; 10f SAN ON0fRE - UNIT 2 3/4 9-9

I j

o REFU LING OPERATICNS

1

^

BASES SHUTDOWN COOLING AND COOLANT CIRCULATION 3/4.9.8 The requirement that at least one shutdown cooling train be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140*F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification.

In MODE 6 a containment spray (CS) pump may be used in place of the low pressure safety injection (LPSI) pump in either or both shutdown cooling train to provide shutdown cooling (SOC) flow.

The requirement to have two shutdown cooling trains OPERABLE when there is le than ?3 feet of water above the reactor pressure vessel flange, ensures that a single failure of the operating shutdown cooling loop will not result in aWith th complete loss of decay heat removal capacity.

removed and 23 feet of water above the reactor pressur operating shutdown cooling train, adequate time is provided to initiate emer-gency procedures to cool the core.

i

)

\\

l f

W AMENDMENT NO. 4 SAN ONOFRE - UNIT 2 B 3/4 9-Za 1C6

NPF-10/15-402jfSUPPLEMENT51 i

ATTACHMENT "B" EXISTING SPECIFICATIONS UNIT 3

84 8

O REFUEt1NG' OPERATIONS 3/4,9,8 SHUTDOWN COOLING AND COOLANT CIRCULATION HIGH VATER LEVEL i

LIMITING CONDITION FOR ODERATION l

I 3.9.8.1 At least one shutdown cooling train shall be OPERABLE and in l

operation.#*

APPLICABILITY: MODE 6 when the water level above the top of the reactor pressure vessel flange is greater than or equal to 23 feet.

ACTION:

With no shutdown cooling train OPERABLE and in operation, suspend all opera-tions involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System and immediately initiate cor-rective action to return the required shutdown cooling train to OPERABLE and 1

Close all containment penetrations pro-operating status as soon as possible.

viding direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCE RE00fREMENTS At least one shutdown cooling train shall be verified to be in 4.9.8.1 a.

operation and circulating reactor coolant at a flow rate of greater than or equal to 2200 gpm at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

1. The shutdown cooling train may be removed from operation for up to I hour per 8-hour period during the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs.

• A containment spray pump may be used in place of a low pressure safety injec-tion pump in either or both shutdown cooling trains to provide shutdown

~

cooling flow.

(Subsequent to implementation of MMP 3-6863)

AMEN 0 MENT NO. 94 9 SAN ONOFRE - UNIT 3 3/4 9-8

~PEFUELING OPERATIONS Lew WATER LEVEL i

t1MITING CONOTTION FO'R OPERATION Two independent shutdown cooling trains shall be OPERABLE and at l

l 3.9.8.2 least one. shutdown cooling train shall be in operation.f*

MODE 6 when the water level above the top of the reactor APPLICABILITY:

pressure vessel flange is less than 23 feet.

ACTION:

f With less than the required shutdown cooling trains OPERABLE, imme-distely initiate corrective action to return the required shutdown a.

cooling trains to OPERABLE status, or to establish greater than or equal to 23 feet of water above the reactor pressure vessel flange as soon as possible.

With no shutdown cooling train in oper,"fon, suspend all operations involving a reduction in boron concentration of the Reactor Coolant b.

System and immediately initiate corrective action to return the Close all containment required shutdown cooling train to operation.

penetrations providing direct access from the containn,ent atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, SURVEILLANCE REOUIREHENTS At least one shutdown cooling train shall be verified to be in 4.9.8.2 operation and circulating reactor coolant at a flow rate of greater than or equal to 2200 gpm at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

1

1. Both shutdown cooling trains may be removed from operation for up to I hour per 8-hour period during the performance of (ORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs provided all operations involving a reduction in boron concentration of the RCS are suspended.

• A containment spray pump may be used in place of a low pressure safety injec-tion pump in either or both shutdown cooling trains to provide shutdown cooling flow.

(Subsequent to implementation of MMP 3-6863)

AMENDMENT NO. 44, 95 SAN ONOFRE - UNIT 3 3/4 9-9 1

o 3,

REFUELING OPERATIONS

[

BASES 3/4.9 8 S'dUTDOWN COOLING AND COOLANT CIRCULATION The requirement that at least one shutdown cooling train be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140*F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a baron dilution incident and prevent boron stratification.

In MODE 6 a containment spray (CS) pump may be used in place of the low pressure safety injection (LPSI) pump in either or both shutdown cooling trains to provide shutdown cooling (SDC) flow.

The requirement to have two shutdown cooling trains OPERABLE when there is less than 23 feet of water above the reactor pressure vessel flange, ensures that a single failure of the operating shutdown cooling icop will not result in a ecm-plate loss of decay heat removal capacity. With the reactor vessel head re-moved and 23 feet of water above the reactor pressure vessel flange, a large i

heat sink is available for core cooling, thus in the event of a failure of the i

operating shutdown cooling train, adequate time is provided to initiate emer-gency procedures to cool the core.

G M

e

's SAN ONOFRE - UNIT 3 B 3/4 9-2a AMEN 0 MENT NO. =

1.

NPF-10/15-402yfSUPPLEMENT91 ATTACHMENT "C" REVISED SPECIFICATIONS UNIT 2

o REFUELING OPERATIONS 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION HIGH WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8.1 At least one shutdown cooling train shall be OPERABLE and in operation.#*

APPLICABILITY: MODE 6 when the water level above the top of the reactor pressure vessel flange is greater than or equal to B3 20 feet.

l AClION:

With no shutdown cooling train OPERABLE and in operation, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required shutdown cooling train to OPERABLE and operating status as soon as possible.

Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.9.8.1 a.

At least one shutdown cooling train shall be verified to be in N

operation and circulating reactor coolant at a flow rate of 1

greater than or equal to 2200 gpm at least onco per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, h

4 i

With1the upper guide ~ structure removed from1the::? reactor?

h shutdown cooling train"may be~ removed ' fro'm" operation'for' pressure > vessel,jthe hour period during the performance of 1) CORE ALTERATIONS in the"vicinit9 of the l

reactor pressure vessel hot legs or 2)/ testing of/LPSIJsjsteinicomponents required by the inservice inspection program providedF ~

.a..:The maximum RCS temperatur.e'isimaintained t 140*F; b.

No operations; are permitted thats would:causeta:reductionTf1the RCS boron 1 concentration; c.1The capability: to clo'se' th'e: contai~nmentipe'netrations with direct access to'the<outside atmosphere within the: calculated: time to boil is maintained.

' d.- lThe reactor cavity water.levelEis' maintained a '20 feettabove thel: top of the: reactor / pressure vessel flange, ;'or, :for Core Alterations,.

2 23 feet above the top of Lthe reactor l pressure vessel: flange.

• A containment spray pump may be used in place of a low pressure safety injection pump in either or both shutdown cooling trains to provide shutdown cooling flow. (Subsequent-t+-implementation of DCP 2 5853}

SAN ONOFRE-UNIT 2 3/4 9-8 AMENDMENT No.

REFUELING OPERATIONS LOW WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8.2 Two independent shutdown cooling trains shall be OPERABLE and at least one shutdown cooling train shall be in operation.*

~o'r OnF tira i nMf ss hutdownTEodl i ng"ishal l i bsTOPERABL Erand ? op"erati ngiunde rit he

^^

~ ^ " ' " "

~ ~ " ~ '"'^

fo110wingsc6nditionsf 1 The f reictor:!ha s(beenis hutd6wn](;fogatRs.a s ti61dayp 2)lThe watssleV61JabovsitheWeact@pe~ss#131angy!isWeaterithanij g 12xfeetz g)j0n{traiC ofl Sal tlWateEl Co611 ngll;[L($WC)}iR0PERABLEfagpperati ng] 4 )f 0neTirai n#of[ CompOnenti Cool i 6g? Wa ter7(CCW) Jand ;thelCCW [swi ngipump] iare10PERABLE;iand:the(CCWftrainiisioperating'withleitheriof4thef" , J E_RABLE;CCW Jumpsj ^ "" ~~ ~" '~ 5 )ioneit pa i.nl o f;3 Shu tdowni co61 t ngli M.0PERABL E 5wi thMEont ainmentF'f ^ ispraylpdepioperatingfonishutdowniccolingNthethighspres'ure; s x ' - s afetif i nj ecti on tpump':: and ithe ll oW! pre s su re? s a fety? inj ecti 6ni pump s:t , fofsthe 'same1trainsare;0PERA9LEtand availableiforninj~ection:)fromafo~ [thelRWST. ~ ' ~ ~ ~ ~ ~ ~ " ~ ~ ~ ' ~ " " ~ Thel RWST"contai ns1 theWol ume EofrwateW rsdi rsd itoirii se1ths b 6)l51evelfto:20lfeet;iabove thel reactor)vesseljflan f ~ i 7)jThe.:; associated [EmergencyfDiesel1Genehtorsis?OPERABLED L 8)?The waterstemperatureiof:thelSDC7systemMsimaintainedslessR i han.s120*F2 ^ ~ ^ ^ ^ ~ ~ ~' t APPLICABILITY: MODE 6 when the water level above the top of the reactor pressure vessel flange is less than M 201 feet. ACTION: a. With less than the required shutdown cocling trains OPERABLE, immediately initiate corrective action to return the required shut-down cooling trains to OPERABLE status, or to establish greater than or equal to 23 20 feet of water above the reactor pressure vessel flange as soon as possible. ' bpIfioperatingT one; t rain 7of; thelshutdownicooling !:: system. with71essithan '20;fe'et1ofiwater above:theLreactoripressdre vesselt f1ange!and!any of the'requ' ired conditions 1(1 through!8)!are;not?n;atSimmediEtelittaks" action /to ? establishfgreater than; orl equsif to(20 f feet; of; wa;terfabove thel reactor pressure vessel flange. SAN ON0FRE-UNIT 2 3/4 9-9 AMENDMENT NO.

.s b c. With no shutdown cooling train in operation, suspend all operations "^ involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required shutdown cooling train to operation. Close all containment penetrations providing direct access from the containment atmosphere to the ov'. side atmosphere within 4 hours. $URVEILLANCE RE0VIREMENTS 4.9.8.2 At least one shutdown cooling train shall be verified to be in operation and circulating reactor coolant at a flow rate of greater than or equal to 2200 gpm at least once per 12 hours. i

• A containment spray pump may be used in place of a low pressure safety injection pump in either or both shutdown cooling trains to provide shutdown cooling flow.

(Sub:cquent to implementation of DCP 2 5853) SAN ON0FRE-UNIT 2 3/4 9-9a AMENDMENT NO.

~ l I r r REFUELING OPERATIONS BASES 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION The requirement that at least one shutdown cooling train be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140aF as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and i prevent boron stratification. In MODE 6 a containment spray (CS) pump may be used in place of the low pressure safety injection (LPSI) pump in either or both shutdown cooling trains to provide shutdown cooling (SDC) flow. The requirement to have two shutdown cooling trains OPERABLE when there is less than 23 20 feet of water above the reactor pressure vessel flange, ensures that a single' failure of the operating shutdown cooling loop will not result in a complete loss of decay heat removal capacity. With the reactor vessel head removed and B3 20 feet of water above the reactor pressure vessel flange, a large heat sink"is available for core cooling, thus in the event of a failure of the operating shutdown cooling train, adequate time is provided to initiate emergency procedures to cool the core. Withith6EreactorNessellhead removedi::and?l2Tfeet7of'wateRabovsithe~ reactor pressure Tvesssisflangel and iald: a' method!isjav;fequirsmentsFeetpa%eatisin lithetsp~ecifled available for: core; cooling: an ailableito,restoreithelrsactop caC ty? level to. 20 L feet 4aboveTthelreactorivessel f fl angehaTherefore n in ithe event of;.alfailure:ofsthefoperating' shutdown?-cool;ingstrainhadequateltimelis provided;tosinitjatelemergencyjproceduresito[ cool.4the[ corse " ~ ' ~' ~ ~ ' ] i l 1 SAN ONOFRE-UNIT 2 B 3/4 9-2a AMENDMENT No.

o NPF-10/15-402[ SUPPL.EMENT!;)1 1 ATTACHMENT "D" ) REVISED SPECIFICATIONS i UNIT 3

REFUELING OPERATIONS 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION HIGH WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8.1 At least one shutdown cooling train shall be OPERABLE and in operation.#* APPLICABILITY: MODE 6 when the water level above the top of the reactor pressure vessel flange is greater than or equal to M 20 feet. ACTION: With no shutdown cooling train OPERABLE and in operation, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required shutdown cooling train to OPERABLE and operating status as soon as possible. Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours. SURVEILLANCE RE0VIREMENTS 4.9.8.1 a. At least one shutdown cooling train shall be verified to be in s operation and circulating reactor coolant at a flow rate of g greater than or equal to 2200 gpm at least once per 12 hours. } cd 'Wi t hi t he ~ uppe rT gu ide Tstruc tu ret removedX fromi the^!re~ acto 6 pre s'su rsive s s el M't h e w) shutdo'wn~coolinb tFain~may^bs"remolled' ffdin^6iisFition~f6Fuft6W2f hours per 8-hour period during the performance of 1) CORE ALTERATIONS in the'vicinit9 of the .reactorpressurevesselhotlegsoff2);testingsof:{LPSpfstemfc6mponents requirediby"the" ins _ ice inspectlon; program:provided: erv ' ::a. 4' Thejmaximut.tRCS?te.mperaturesislmaintainedfs[1409.'

{bL yNo1operationsfarespermit.tedithatiwould cau'se(ajredustionlopthe~ RCS boron concentratione

c MThs/c apabi.l i ty / t o icl o seit hei c ont ai nmentipenet rat i onsNi thidi feet acces s sto i the [ outjs ideiatmosphere Tsi thi n [ths;fc al cul atep time (to! boil is maintaineds

~ Tdi ?TheJeactoricavitfwaterilevelfi'sima14tainsdLii.i20TfeetVab6Vef theitop 'ofL.the' reactor pressure vessel?flangehorgfor[CopeJAlterations;W23 feettab,0ve;the? top}ofith6reactorf pressure @esselfflange) ' ~

• A containment spray pump may be used in place of a low r essure safety injection pump in either or both shutdown cooling trains to provide shutdown cooling flow.

(Subsequent 10 implementat& cf MMP 3 5853) SAN ON0FRE - UNIT 3 3/4 9-8 AMENDMENT N0. i - ~

r REFUELING OPERATIONS LQiLWATER LEVEL LIMITING CONDITION FOR OPERATION t 3.9.8.2 Two Independent shutdown cooling trains shall be OPERABLE and at least one shutdown cooling train shall be in operation.#* 5 t Onh2 t'ra i nTofs shntdswn Rool;i ngishall ?bdi OPERABLEsandiop~dPati hyTusderIths f d owta9 M aditi a5f ~ ~ ~ ' ' ~ ~ ~ ~ ~ ~ ~ ~ ~ ? 1)JJh6TjayctoghRhieg{st[std6W(ifdgit%1jiastigdai,s] O)lThsTsatersleVelEab6Vi!thdTreictoFy~sise#yflinge!K' ~y"peatFr{ l 2 ^ ^ * ' ~ " " ' ^ "" ~~ " ~' l,2ffge,t{ ~~~ ^ ~ 3 ) ? 0.nei t r. a i n t o.f!.S a,l t? WateM~Co,o,l i ng ?~(SWC)a.~t s70PERABL_EE ahd io.pe r.ati n, g?, l i w~ c -~ n .a I 4)i one$ t rai n2 o f( Compon#n t s Cool i ngiWaterit.(CCW)iand j thelCCW[swi ng?psspy l E Fare: 0PERABLEkandithelCCWstra101sioperating'isithyeither?ofethhP1.1

• ~ ~ ' " " ^ ~

"~' ""'" ' g {0PERABLE{CCW jumpsf ^ 5 6linjectionTp6mpliandithelloWprsssurehssfetain C i F Vsamet_trainiarel0_PE_RAB.z E. r ~.nd_s av_ ail ab_l e.sfo_rJinject_ ion _ifrom;th. e. ? RWST.,). i L a s x~ ~~~ m. m ^ 6)fThe? RWSTi conta insV theTVol ume?of!waterNequi feditoTrai s#5the3 ".%^' ll evel,tt6 !,20 !feethb6ve s thei rsa,eto. rive ss_el s f.l anse f ^ m. j w c c a)?TheTis soci ated ? Em.ergenci;Di esel ? Ge,nsf,atdMs"0.PERABLE!, l 7 .- a- ~n +u ~ 8);ThelwateQemperitbrs[ ggt.h[SDp{ sis {enilis^ main {iihedgeis] (, ? ,;than!120!Fg APPLICABILITY: MODE 6 when the water level above the top of the reactor pressure vessel flange is less than H 20ffeet. ACTION: a. With less than the required shutdown cooling trains OPERABLE, immediately initiate corrective action to return the required shut-down cooling trains to OPERABLE status, or to establish greater than or equal to M 20 feet of water above the reactor pressure vessel flange as soon ai possible. N bOIffopefatingToneitPaihioflthe? shutdown?coolihgisystsmLwith11essithad ^ 20! fee tio fJwaterfaboVes the7 re actoripfe s sure 3 ves sel ? fl ange land lanf o f thsfrequirsd? con'ditions4(11throughj8)dsalstoi!20(feet offwatersab actionitoiestablishigreaterdthan orle " ^ " " the reactorjpressurek~ vesselfflangeF" ' "~ ' ~ '3/4"919~ AMENDMENT N0. SAN ON0FRE P UNIT'3 1

>w v b d. With no shutdown cooling train in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required shutdown cooling train to operation. Close all containment penetrations providing direct access from the. containment atmosphere to the outside atmosphere within 4 hours. SURVEILLANCE REQUIREMENTS 4.9.8.2 At least one shutdown cooling train shall be verified to be in operation and circulating reactor coolant at a flow rate of greater than or equal to 2200 gpm at least once per 12 hours. l l 1 1 i

• Beth shutdcwn cccling train; ::y be rc=cved frc: Operatica for up tc 1 hcur per S hour pericd during the performance of CORE ALTERATIONS in the eicini+y of 2

the rc::tcr prc :urc vc :cl het leg: :rovided all cperation; involving c reductica in bcron ccncentration of t:c RCS are uspended. j

• A cor.tainment spray pump may be used in place of a low pressure safety injection pump in either or both shutdown cooling trains to provide shutdown cooling flow. (Subsequent to impicmentatica of MMP 3 SSS&t i

SAN ONOFRE - UNIT 3 3/4 9-9a AMENDMENT N0.

o s REFUELING OPERATIONS BASES m 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION The requirement that at least one shutdown cooling train be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below I40of as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a baron dilution incident and prevent boron stratification. In MODE 6 a containment spray (CS) pump may be used in place of the low pressure safety injection (LPSI) pump in either or both shutdown cooling trains to provide shutdown cooling (SDC) flow. The requirement to have two shutdown cooling trains OPERABLE when there is less than G3 20 feet of water above the reactor pressure vessel flange, ensures that a single" failure of the operating shutdown cooling loop will not result in a complete loss of decay heat removal capacity. With the reactor vessel head removed and 24 20 feet of water above the reactor pressure vessel flange, a large heat sink ~is available for core cooling, thus in the event of a failure of the operating shutdown cooling train, adequate time is provided to initiate emergency procedures to cool the core. Wi thithe ? reactopive s seliiheadl remoVsd f arid ?l 2E feetX6fNater faboVe~ the Treactor pres s ureive s s ellfl ange Tand i all hthei s pec t fl ed f requ l Fsment s}methy hsit} si nkSi s availablelforicore coolingyandf atmethodfisfavailablehtoirestoreithegeactor . cavity (1epel{to!20ifeetsabove the;reattor; vessel 1f1angeOThereforeMinithe event r ofialfail urelo ff the foperati ng ishu.td6wn; cool ing ;trai n,j adpguateJ time [i s .provided;tolinitiate; emergency;proceduresjto;coolitheycore.: 1 1 i SAN ON0FRE-UNIT 3 B 3/4 9-2a AMENDMENT No.

i-REVISED TECHNICAL SPECIFICATION IMPROVEMENT PRGGRAM (PCN 299) TECHNICAL SPECIFICATIONS UNIT 2

SDC and Coolant Circulation-High Water Level w-3.9.4-3.9 REFUELING OPERATIONS 3.9.4 Shutdown Cooling (SDC) and Coolant Circulation-High Water Level N LCO 3.9,4 One SDC loop shall be OPERABLE and in operation. __...............__......__.N0TE---------------------------- Wi th}theXupperguidej structpreTrem6vef from1thejreictos pressureivesseldthe sh6tdown cooling t?ain may lie removed froni~opeFation~f6r 5 + 21 hours per 8-hour period during the performance of ]) CORE ALTERATIONS in the vicinity of the bys tein ^componentsTriqdi red; bgt he]j,n se(tes ti ng?of s.LP reactor pressure vessel hot legs br#2) program;provided:

alpThe j aaxj eumlRCS[t'empetithtiif s {mit ritii riedM140*f) i

bM'NofoperationstarefpermittedEthatswouldXcause/a?redsct~ ion ofdtheiRCS boron / concentration

^ ^'~ EcMTheicapabilitpitsicloseltheh' ontainmen0 enetrations c "'"With1 direct #accessiteithssoutsideintmos'ereiwithintthe calsn1hteditimestO boll?ff maintained?"~ ~ ~ " ' id M The i reacto M6avi ty#e s s h% sienfl h 'Wiodifd'Cm ! waterl1 svel ? i s iai ntiined W 20 ?fset " abo ket k h t & Alteration s O 23!feetlaboselthe#topjg ithedreactor" ~ Priputejessel? flange ( " ~ ~ ^ " ~ " ^ ~ ............._____......----N0TE---------------------------- A containment spray pump may be used in place of a low pressure safety injection pump to provide shutdown cooling fl ow. APPLICABILITY: MODE 6 with the water level 7-M 20tft above the top of reactor vessel flange. ACTIONS REQUIRED ACTION COMPLETION TIME A. SDC loop requirements A.1 Suspend operations Immediately not met. invol sing a reduction in reactor coolant boron concentration. MQ (continued) SAN ON0FRE--UNIT 2 3.9-6 AMENDMENT NO.

i

4 9~

SDC and Coolant Circulation-High Water Level 3.9.4 ACTIONS CONDITION REQUIRED ACTION Ct IPLETIM TIME A. (continued) A.2 Suspend loading Immediately. irradiated fuel assemblies in the Core. E A.3 Initiate action to Immediately satisfy SDC loop requirements. l f AND A.4 Close all containment 4 hours t penetrations j providing direct access from containment i atmosphere to outside i atmosphere. i F , SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY [ SR 3.9.4.1 Verify one SDC loop is in operation and 12 hours circulating reactor coolant at a flow rate of a 2200.gpm. SAN ON0FRE--UNIT 2 3.9-7 AMENDMENT N0.

SDC and Coolant Circulation-Low Water Level 3.9.5 3.9 REFUELING OPERATIONS 3.9.5 Shutdown Cooling (SDC) and Coolant Circulation-Low Water Level LC0 3.9.5 Two SDC loops shall be OPERABLE, and one SDC loop shall be in operation. br x - One triinTof? shutdown 7coolingishallibeIOPERABLErand. ppgratingjunlderttheijfWowingiconditionsf ,1),2Th47re.ac.topih,a,s7 beenM_hutdo,snifo_pf,it_%1esst. !67,da.ys 2)iThe14tbr21evel?hboveithe?reictorWeiseEflangilist^ ~ ' s ,k T t,e~aterith,an t.l2._if.eeti ^ ' ~ " " ~ " ' ' ^~ 9 m 3 );ionel t ra i n [o f(S al t? WateFICool i ng(SWC)psiOPERABLEi ang (; ope [ating3 4)(Eswingipumplare:On6? t f a i n?~4f!Compinent^ Cool i hgl Wste 0PERABLE Whndcthe CCWitrainilisto ' r, (with: eithe.kofithe':G. PERA. BLE. i_CCW? pump,sP~" ~~~ " -~ 5)Toneitti.in[ofShutdown?Codli.ngsiU 0PERABLE?with 4 U ' Tcontainmentispray(pumpf.operatingYont:: shutdown coolingdthes e Jigh';; pressure lsafetykinjection.ipump?hndsthellowLpressure; liafety! injection! pump? of; thelsamestrain Laret 0PERABLE{and)

.,Tav ai,l _i.11_el for ji njec.ti..on s.. fromj th.e_3 RWS_T h. " ' "

m. ~- 1 6)?ThetRWSTidentsinCthe^Nolumsibf@itspiFsquirsdftoirais#7 ' 4 theyl evelf.to (20,feetTaboveJhef reactorf ve s sel j fl ange r~ 7)} The ia s s oci ated [ Eme rgencyl Di e sellGeneratodj sT OPERABLE 0 8)(The water ~ temperatur'e:?of the!SDC; systemji s{mainta iried ? (1sssithaM120*Fl . ^ ............................N0TE---------------------------- A containment spray ; ump may be used in place of a low pressure safety injection pump to provide shutdown cooling flow. j APPLICABILITY: MODE 6 with the water level < M 20 ft above the top of reactor vessel flange. ACTIONS SAN ON0FRE--UNIT 2 3.9-8 AMENDMENT N0. j l

v SDC and Coolant Circulation-Low Water Level i 3.9.5 CONDITION REQUIRED ACTION COMPLETION TIME A. One SDC loop A.1 Initiate action to Immediately inoperable. restore SDC loop to-OPERABLE status. (Applic'ableltCi.nitial. conditionssof#twoishutdo._wn OR

c. oo, ling.itra,inROPERABLE..). ^ '

establish a 33 20 ft i of water above the l top of reactor vessel flange. I BM.0nb" SOC?ToopidpeFabls? .B[1.1 sInitiatsisdti6nMtd .Immsdiktsly~ ~^^1essi:than;.20; feett of' "establishit020sfeet ~~~ ^ ivater.Tabove:)the~'~ ofsated reactWJpressure " ~ ~ ^

• yesselsflange Land ?all 8[requirementsin'atime,t,

( Applicable 7tdfinitial. conditionstbfionefshutdown cooling; train (OPERABLE 4and operating lwith~ ' ' ' ~ Requirements [1-8) BC. No SDC loop OPERABLE BC.1 Suspend operations Immediately or in operation. involving a reduction in reactor coolant boron concentration. AND (continued) SAN ON0FRE--UNIT 2 3.9-9 AMENDMENT NO.

1 SDC and Coolant Circulation-Low Water Level 3.9.5 i ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME BC,. (continued) BC.2 Initiate action to Immediately J restore one SDC loop to OPERABLE status and to operation. AND BC.3 Close all containment 4 hours penetrations providing direct access from containment atmosphere to outside atmosphere. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 Verify required SDC loops are OPERABLE 12 hours and one SDC loop is in operation and circulating reactor coolant at a flow rate of a 2200 gpm. SAN ONOFRE--UNIT 2 3.9-10 AMENDMENT NO.

SDC and Coolant Circulation-High Water Level B 3.9.4 8 3.9 REFUELING OPERATIONS B 3.9.4 Shutdown Cooling (SDC) and Coolant Circulation-High Water Level BASES BACKGROUND The purposes of the SDC System in MODE 6 are to remove decar heat and sensible heat from the Reactor Coolant System (RCS), as required by GDC 34, to provide mixing of borated coolant, to provide sufficient coolant circulation to minimize the effects of a boron dilution accident, and to prevent boron stratification (Ref. 1). Heat is removed from the RCS by circulating reactor coolant through the SDC heat exchangers, where the heat is transferred to the Component Cooling Water System via the SDC heat exchangers. The coolant is then returned to the RCS via the RCS cold leg (s). Operation of the SDC System for normal cooldown or decay heat renm tl is manually accomplished from the control room. The heat maal rate is adjusted by controlling the flow of reactor cc ?t through the SDC heat exchangers and bypassing tu Nat exchangers. Mixing of the reactor coolant is maintained by this continuous circulation of reactor coolant through the SDC System. The shutdown cooling system is a safety related, seismically qualified system which is powered by a class lE electrical system. The cooling capacity of 1 train of the shutdown cooling system is sufficient to maintain the spent fuel pool temperature lower than can be maintained by the spent fuel pool cooling system. When components of the shutdown cooling system are not required to be OPEPABLE by technical specifications, then one train of the shutdown cooling system (consisting of at least 1 LPSI pump or 1 containment spray pump, I heat exchanger, flow path to and from the SFP, and the associated Diesel Generator) may be aligned to cool the spent fuel pool. Additionally, during MODE 6 with the reactor refueling canal water level greater than or equal to M 20 feet above the reactor flange, the SDC system (consisting of at least 2 pumps (either 1 LPSI pump and 1 CS pump or 2 CS pumps),1 SDC heat exchanger, flow paths to and from the RCS and SFP, and the associated Diesel Generator) may be aligned to cool both the SFP and the reactor core. (continued) SAN ON0FRE--UNIT 2 8 3.9-16 AMENDMENT NO.

SDC and Coolant Circulation-High Water Level B 3.9.4 BASES APPLICABLE If the reactor coolant temperature is not maintained below SAFETY ANALYSES 200*F, boiling of the reactor coolant could result. This could lead to inadequate cooling of the reactor fuel due to a resulting loss of coolant in the reactor vessel. Additionally, boiling of the reactor coolant could lead to a reduction in boron concentration in the coolant due to the boron plating out on components near the areas of the boiling activity, and because of the possible addition of water to the reactor vessel with a lower boron concentration than is required to keep the reactor subcritical. The loss of reactor coolant and the reduction of boron concentration in the reactor coolant would eventually challenge the integrity of the fuel cladding, which is a fission product barrier. One train of the SDC System is required to be operational in MODE 6, with the water level a M 20 ft above the top of the reactor vessel flange, to prevent this challenge. The LC0 does permit de-energizing of the SDC pump for short durations under the condition that the boron concentration is not diluted. This conditional de-energizing of the SDC pump does not result in a challenge to the fission proiuct barrier. SDC and Coolant Circulation-High Water Level satisfies Criterion 2 of the NRC Policy Statement. LCO Only one SDC loop is required for decay heat removal in MODE 6, with water level a M 20 ft above the top of the reactor vessel flange. Only one SDC loop is required because the volume of water above the reactor vessel flange provides backup decay heat removal capability. At least one SDC loop must be in operation to provide: a. Removal of decay heat; b. Mixing of borated coolant to minimize the possibility of a criticality; and c. Indication of reactor coolant temperature. An OPERABLE SDC loop includes an SDC pump, a heat exchanger, valves, piping, instruments, and controls to ensure an OPERABLE flow path and to determine the low end temperature. (continued) SAN ONOFRE--UNIT 2 B 3.9-17 AMENDMENT NO.

e SDC and Coolant Circulation-High Water Level B 3.9.4 j BASES k \\ LC0 The flow path starts in one of. the RCS hot legs and is J( (continued) returned to the RCS cold legs. The LCO is modified by a Note that Nithithelupper:I structsre7emoVidifrom"thsWeactbrpressure3vesse&suide-c a116ws K t he" req u i rud *o p e Fa t i hg

• SDC'16bp't~6' be"FemoVed"f r6m ~se rv i c e 5

for up to 42 hour.i in each 8 hour period, provided thati no Operation: Erc pcF=ltted that weald cau:c dilutica $f"the Re:cter Ccc1cnt Syste: Scrca concentratica. 419The"Mhimum' RCSitempetitureili7mii ntai ned @l40? F! b W No3peratio'nsEares permitteditha.tf would?cau' _e Da" ' ~ " s 7p g g .cym?The i cipabil i ti.stoicl o sei theYcont ai nmentsbiih trat i on s y g g the"caldulated1timelto!boiliis maintaineds:" ~ ~ dy TThe; reacto8cavityjater&1.ev'eMis? maintained @iforl Core T20? feet ~~bovejthe[ reactor {pressurejvesse15flangeNor, a Al terati ons @ls.33 feetpbovej theltop;ofitheireactor 2 pressurejvepse flangei This permits operations such as core mapping or alterations in the vicinity of the reactor vessel hot leg nozzles, and RCS to SDC isolation valve testing WindlinserVids? testing'?of LPSIlsystemTcomp6nents. Du ri ng th i s" 2 "ho u r '^p6Fiod, "ded'ay hest'is removed bi~ natural convection to the large mass of water in the refueling canal. ] Also, this LC0 is modified by the Note that allows Operations to use a containment spray pump in place of a low pressure safety injection pump to provide shutdown cooling flow. d APPLICABILITY One SDC loop must be in operation in MODE 6, with the water level E M20 ft above the top of the reactor vessel flange, to provide ~ decay heat removal. The 23 ft icvel w;; selected j because it corrc pend; tc the 23 ft requirc ent c tablished for fucl =cvc= cat in LCC 3.9.5, " Refueling hier Level." Requirements for the SDC System in other MODES are covered by LCOs in Section 3.4, Reactor Coolant System (RCS), and Section 3.5, Emergency Core Cooling Systems (ECCS). SDC loop requirements in MODE 6, with the water level < M 20 ft above the top of the reactor vessel flange, are located 'in LC0 3.9.5, " Shutdown Cooling (SDC) and Coolant Circulation-Low Water Level." (continued) SAN ON0FRE--UNIT 2 B 3.9-18 AMENDMENT NO.

SDC and Coolant Circulation-High Water Level B 3.9.4 BASES i ACTIONS SDC loop requirements are met by having one SDC loop OPERABLE and in operation, except as permitted in the Note to the LCO. Am1 If SDC loop requirements are not met, there will be no forced circulation to provide mixing to establish uniform boron concentrations. Redeced boron concentrations can occur through the addition of water with a lower boron concentration than that contained in the RCS. Therefore, actions that reduce boron concentration shall be suspended immediately. 612 If SDC loop requirements are not met, actions shall be taken immediately to suspend loading irradiated fuel assemblies in the core. With no forced circulation cooling, decay heat removal from the core occurs by natural convection to the heat sink provided by the water above the core. A minimum refueling water level of 2320 ft above the reactor vessel flange provides an adequate ~ivailable heat sink. Suspending any operation that would increase the decay heat load, such as loading a fuel assembly, is a prudent action under this condition. bal If SDC loop requirements are not met, actions shall be s initiated and continued in order to satisfy SDC loop requirements. A.4 If SDC loop requirements are not met, all containment penetrations to the outside atmosphere must be closed to prevent fission products, if released by a loss of decay heat event, from escaping the containment building. The 4 hour Completion Time allows fixing most SDC problems without incurring the additional action of violating the containment atmosphere. (continued) SAN ON0FRE--UNIT 2 8 3.9-19 AMENDMENT N0. t

SDC and Coolant Circulation-High Water Level B 3.9.4 BASES SURVEILLANCE SR 3.9.4.1 REQUIREMENTS This Surveillance demonstrates that the SDC loop is in operation and circulating reactor coolant. The flow rate is determined by the flow rate necessary to provide sufficient decay heat removal capability and to prevent thermal and boron stratification in the core. The Frequency of 12 hours is sufficient, considering the flow, temperature, pump control, and alarm indications available to the operator in the control room for monitoring the SDC System. REFERENCE 1. UFSAR, Section 7.4. I SAN ON0FRE--UNIT 2 B 3.9-20 AMENDMENT N0.

SDC and Coolant Circulation-Low Water Level B 3.9.5 B 3.9 REFUELING OPERATIONS B 3.9.5 Shutdown Cooling (SDC) and Coolant Circulation-Low Water Level BASES BACKGROUND The purposes of the SDC System in MODE 6 are to remove decay heat and sensible heat from the Reactor Coolant System (RCS), as required by GDC 34, to provida mixing of borated coolant, to provide sufficient coolant circulation to minimize the effects of a boron dilution accident, and to prevent boron styatification (Ref. 1). Heat is removed from the RCS by circulating reactor coolant through the SDC heat exchangers, where the heat is transferred to the Component Cooling Water System via the SDC heat exchangers. The coolant is then returned to the RCS via the RCS cold legs. Operation of the SDC System for normal cooldown or decay heat removal is manually accomplished from the control room. The heat removal rate is adjusted by controlling the flow of reactor coolant through the SDC heat exchangers and bypassing the heat exchangers. Mixing of the reactor coolant is maintained by this continuous circulation of reactor coolant through the SDC System. The shutdown cooling system is a safety related, seismically qualified system which is powered by a class 1E electrical system. The cooling capacity of 1 train of the shutdown cooling system is sufficient to maintain the spent fuel pool temperature lower than can be maintained by the spent fuel pool cooling system. When components of the shutdown cooling system are not required to be OPERABLE by technical specifications, then one train of the shutdown cooling system (consisting of at least 1 LPSI pump or 1 containment spray pump, I heat exchanger, flow path to and from the SFP, and the associated Diesel Generator) may be aligned to cool the spent fuel pool. Additionally, during MODE 6 with the reactor refueling cavity water level less than M 20 feet above the reactor flange, the SDC system (consisting of at least 2 pumps (either 1 LPSI pump and 1 CS pump or 2 CS pumps),1 SDC heat exchanger, flow paths to and from the RCS and SFP, and the associated Diesel Generator) may be aligned to cool both the SFP and the reactor core. (continued) SAN ON0FRE--UNIT 2 8 3.9-21 AMENDMENT N0.

4 o-s. SDC and Coolant Circu^ ation-Low Water Level B 3.9.5 BASES APPLICABLE If the reactor coolant temperature is not maintained below SAFETY ANALYSES 200aF, boiling of the reactor coolant could result. This could lead to inadequate cooling of the reactor fuel due to the resulting loss of coolant in the reactor vessel. Additionally, boiling of the reactor coolant could lead to a reduction in boron concentration in the coolant due to the boron plating out on components near the areas of the boiling activity, and because of the possible addition of water to the reactor vessel with a lower boron concentration i than is required to keep the reactor subcritical. The loss of reactor coolant and the reduction of boron concentration in the reactor coolant would eventually challenge the integrity of the fuel cladding, which is a fission product barrier. Two trains of the 500 System are required to be OPERABLE, and one train is required to be in operation in MODE 6, with the water level < M20 ft above the top of the reactor vessel flange, to prevent ^"this challenge. Wi thi(theme;ai:toMVeWilJ hiad Wbm6 ped [ahd 32sfeitF6fjy~atet .above 3 t hei reactorEpre s s ure?Ve s selsfl angelandla1 Rthe ~~ speci fjedirequi rement simetya i heatis i nkgi slava 11 a.bl ej foMc6re cool i ng?and ia3 method si s tavai.l abl eitoirestoreithesreactor cavi tytl evellt o]20) feetlaboveltheWeactorWes seMfl angel, Thereforelin' thefeventloff sjfailurefof#thejoperating" ' ~ J shutdown [co6lingstrainnad. equate;timefisfprovidedjjp .i n i ti a.t e Lemergency g pyocedu.re sp o; cool dt.heicge; One train of shutdown cooling shall be OPERABLE and operating under the following conditions: SDC and Coolant Circulation-Low Water Level satisfies Criterion 3 of the NRC Policy Statement. LC0 In MODE 6, with the water level < 2320 ft above the top of the reactor vessel flange, both SDC 160ps must be OPERABLE. Additionally, one loop of the SDC System must be in operation in order to provide: a. Removal of decay heat; b. Mixing of borated coolant to minimize the possibility i of a criticality; and i c. Indication of reactor coolant temperature. (continued) SAN ON0FRE--UNIT 2 B 3.9-22 AMENDMENT NO.

SDC and Coolant Circulation-Low Water Level 0: B 3.9.5 1 ' BASES LCO An GPERABLE SDC loop consists-of an SDC pump, a heat (continued) exchanger, valves, piping, instruments, and controls to ensure an OPERABLE flow path and to determine the low end temperature. The flow path starts in one of the RCS hot legs and is returned to the RCS cold legs. This LC0 is modified by the Note that allows Operations to use a containment spray pump in place of a low pressure safety injection pump to provide shutdown cooling flow. s$ i i mea _T9 hs?fek_t6_rNss_5bseWil.h_ut.d6wh[fdgatMmiasti6Tdays? I m

2) NThe?Wate61sVe1RaboisithgrdRtbEViiisisfl aWgelii 9rejtsdyan@ifegt7"

"""~~'" 3)M0neltrai%iipSal,t'!WajgC%g]fSWC)j[iQgERABLEfsnd EP'EdlMi ")" 70nFt ra1 Foff Componint? Cool.i ngi_ Wats 6(CCW)!?ind!the!CCW 4L iwing L pumpiaret OPERABLE #andithel CCWitra i n:ii s"^~~~ ~^ 'P8Tatippi t{ei theQff the@gRA8LECC,W1umpy ") g' contiinment@ phayTpumpTopepatin @on?shutdownideol.ing 5 0neltrai n2 b f! Shutdown? Cool ing i?i s10PERABL Eiwith?i ths;3highlpressuressafetyQnjecttonipumplandttheslos~ press'uressafetysinjestiontpumplofsthessameltrainfafs - OPERA _8tE._ta_nd,tavillab. m if_orii_nje_ctioni_ fro._mit_helRWSTT le m._ ms m 6)MTh's RWSTfcontaini5thenslumsibf7Watepe4ulfedlto "'"hi the M_61stuf 2,0lfi_et?atidvsi_the_7 r_eactor.g_ves sel 7-m m f .4 ..M 5- ' o 4 [)f3ThQsspc }aled (EmeFgenyQe@KG6phytor;j[igogiprabl e] 8)*' 7TheTwaterltssperatureiof#the*SDCTiisteiniis?siaintiihid hanfl 20gI" " '"""" " ^~^~~~~'~~ ~' " ff?i.iCADILITY Two SDC loops are required to be OPERABLE, and one SDC loop i must be in operation in MODE 6, with the water level l < M20 ft above the top of the reactor vessel flange, to provide decay heat removal. Requirements for the SDC System ) in other MODES are covered by LCOs in Section 3.4, Reactor Coolant System. MODE 6 requirements, with a water level a M20, ft above the reactor vessel flange, are covered in (continued) SAN ONOFRE--UNIT 2 8 3.9-23 AMENDMENT N0. I i

SDC and Coolant Circulation--Low Water Level B 3.9.5 BASES APPLICABILITY LC0 3.9.4, " Shutdown Cooling and Coolant Circulation-High (continued). Water Level." ACTIONS A.] and A.2 WherRteoTSDCitFains7aFeT6psrablesandpif one SDC loop +s 155liEFsb1hbecomesiinop'eiable;*seti6ns shall be immediately initiated shd'iont'inhed'U~ntil the SDC loop is restored to OPERABLE status and to operation, or until a M20 ft f water level is established above the reactor vessel flange. When the water level is established at a M20 ft above the reactor vessel flange, the Applicability will change to that of LC0 3.9.4, " Shutdown Cooling and Coolant Circulation-High Water Level," and only one SDC loop is required to be OPERABLE and in operation. An immediate i Completion Time is necessary for an operator to initiate corrective actions. IL1 WheWon'TtrainTof?SDCfisFoperablelithirequifements7178 e 6 s ati s fl ed l arid i thel SDC sl oop1 bscome ni sherabl e f orfal l E 8 * 'requ i rement s fa reinot:f aiet ty scti en sisha115 be siiusedi at ely ,i ni ti atedito l est abl i shk ai wateryl evel jN 20ifeet(above jthe .reactorpressurejflangedWhenithe.; water 4eveljis. 1 establishedfat m 20efeetfabovelthe:re. actor; pressure;v.. _l esse T Shutdown [ Cool i ng Tand >.i ty! wil i t chang ~ef to s t h ati of flangeRthe?applicabil Cool anti Ci rcul ati on - Hi gtC Water ~" ^ t.evel i "):and ionly) one) SDC} l oop 4;i si:;requi red lto f be10PERABLE ?and anoperatortolinitiate;correctivelectjons;disipecessaryffop inloperation:4Ansimmediate[CompletionRime 2 10.1 If no SDC loop is in operation or no SDC loops are OPERABLE, there will be no forced circulation to provide mixing to establish uniform boron concentrations. Reduced boron J concentrations can occur by the addition of water with lower boron concentration than that contained in the RCS. Therefore, actions that reduce boron concentration shall be suspended immediately. (continued) SAN ON0FRE--UNIT 2 B 3.9-24 AMENDMENT NO.

SDC and Coolant Circulation -Low Water Level B 3.9.5 BASES ACTIONS fL2 (continued) If no SDC loop is in operation or no SDC loops are OPERABLE, actions shall be initiated immediately and continued without interruption to restore one SDC loop to OPERABLE status and operation. Since the unit is in Conditions A and B concurrently, the restoration of two OPERABLF SDC loops and one operating SDC loop should be accomplished expeditiously. 1L3 If SDC loops requirements are not met, all containment penetrations to the outside atmosphere must be closed to prevent fission products, if released by a loss of decay heat event, from escaping the containment building. The 4 hour Completion Time allows fixing most SDC problems without incurring the additional action of violating the containment atmosphere. SURVEILLANCE SR 3.9.5.1 REQUIREMENTS This Surveillance demonstrates that one SDC loop is operating and circulating reactor coolant. The flow rate is determined by the flow rate necessary to provide sufficient decay heat removal capability and to prevent thermal and boron stratification in the core. In addition, this Surveillance demonstrates that the other SDC loop is OPERABLE. In addition, during operation of the SDC loop with the water level in the vicinity of the reactor vessel nozzles, the SDC loop flow rate determination must also consider the SDC pump suction requirements. The Frequency of 12 hours is sefficient, considering the flow, temperature, pump control, and alarm indications available to the c.mrator to monitor the SDC System in the control room. Verification that the required loops are OPERABLE and in operation ensures that loops can be placed in operation as needed, to maintain decay heat and retain forced circulation. The Frequency of 12 hours is considered reasonable, since other administrative controls are available and have proven to be acceptable by operating experience. (continued) SAN ON0FRE--UNIT 2 8 3.9-25 AMENDMENT NO.

SDC and Coolant Circulation-Low Water Level B 3.9.5 1 BASES REFERENCE 1. UFSAR, Section 7.4. 1 l I 1 SAN ON0FRE--UNIT 2 8 3.9-26 AMEIGNcNT NO.

o REVISED TECHNICAL SPECIFICATION IMPROVEMENT PROGRAM (PCN 299) TECHNICAL SPECIFICATIONS UNIT 3

) i q~, SDC and Coolant Circulation-High Water Level 3.9.4 3.9 REFUELING OPERATIONS-3.9.4 Shutdown Cooling (SDC) and Coolant Circulation-High Water Level A LCO 3.9.4 One SDC loop shall be OPERABLE and 'in. operation. _....._......_...---N0TE---------------------------- Withitheispped uiderstructsreTrsmoVWdifrosjtheWiistof .pressureWessel !;thb'sFUtddWH~E6"61'ind~tFifn hidy"be*Pem3ved h ffom'^ojeFitios"for :s 12 hour ~i per 8-hour period to support h 1} CORE ALTERATIONS in the viEinity of the reactor pressure Vessel hot legs 662)?testinfoffLPSIFsystem?Oomponents rdqui Eedliby;theFi rserv i celinspection#FogrsWiprovided i" saNMeeimaximum RC$ttemperaturesistmai'ntainediss140*P ["b M No fopirat ionsisreiperini ttsdithatj~liould[c aiset@'isducti od ~ 'o6theiRCS)bofonTconcentrition? ~^~" " " fcWThsi:ca~ abil i tisto2 cl osesth_elcontsi Nn6iitTpinktfationi ^ " ^withid rsstf accessitolthefiostside?itassphdeiwith'in?the i calcslatsdstimettoibollstimaihtsinedf"'~^" ~ "~ ' (d f~11 hefreacto@cav i ty$atedievsl di sima i ntiihed@ 20l fedt ~ "abossithedreactorspressuresvesselfflangeNorMfodlCors Al tiritiossnC23?fest?abossitheMbp;ofstheVrdict6F"" _ _ _ _ _ _ r.1....O.. !.. %t.% g et ~~~"_~~ ^ "_ _ _...~..~_ _ _.~~.~_ _ pressureWesssBflin .S.______ _________..----------NOTE---------------------------- A containment spray pump may be used in place of a low pressure safety injection pump to provide shutdown cooling fl ow. APPLICABILITY: MODE 6 with the water level a M '20 ft above the top of ~ reactor vessel flange. ACTIONS CONDITION REQUIRED ACTION COMPLETION-TIME A. SDC loop requirements A.I Suspend operations Immediately not met. involving a reduction in reactor coolant boron concentration. AND (continued) SAN ON0FRE--UNIT 3 3.9-6 AMENDMENT N0.

SDC and Coolant Circulation-High Water Level 3.9.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 Suspend loading Immediately irradiated fuel assemblies in the Core. AND A.3 Initiate action to Immediately satisfy SDC loop requirements. d!!D A.4 Close all containment 4 hours penetrations providing direct access from containment atmosphere to outside atmosphere. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY r SR 3.9.4.1 Verify one SDC loop is in operation and 12 hours circulating reactor coolant at a flow rate of a 2200 gpm. SAN ON0FRE--UNIT 3 3.9-7 AMENDMENT NO.

SDC and Coolant Circulation--Low Water Level -+ 3.9.5 3.9 REFUELING OPERATIONS 3.9.5 Shutdown Cooling (SDC) and Coolant Circulation-Low Water Level LC0 3.9.5 Two SDC loops shall be OPERABLE, and one SDC loop shall be in operation. o,f 2 Dhe?t rii hi^6fsshetdoWnitobl i ngishal litfel;0PERABLE?ahd i o,ps.ra.,timj+%nden.,t_helfo.i owingsspd,ifik~i? + w ~.s ~~ n ~ -.- h 1)au,iffe.a_stoEJ hisi beshi'shutdosnifo6PitRi ssit?6~7dsys? ETh a - _ - + -- n --- .n meg _reatme_than312. s fee.t_B~ ~~*'"~~"~' ' ~~"^"^~~ ^ 2)sThe?Wite616Viliab6Veithh?FisetbEiV~diseliflidgiEtir ""3 O ed m m $N)?Oniktf ai nT6f5 Sal t l Wsteff Cool ingfSWC p"~fs?0PERA 3 ~# NPNhtgg} ^~ "" ~~^^~ ' $F) 70nbittsihidf!CougichehtiCdblihilWatidi(CCW)lahdsth61CCW 4 issi.hgipumpsipe? OPERABLE F andithe!CCWilitfai_nM s E y g~ i~ ] Mop _ era _ ting eri_th 'e_ithe,nf_of ' __70PERA.B,L_EIC.C_W f pu_' mp,'s,u ii ~ um m m m

5) One train' of Shutdown' Cooling is~ OPERABLE ^ ith'a'J:i ^ l '

~ w containmentspraypumpoperatinsonshutdownco6fing,the! j hi h pressure safety injection pump and the low pressure ' sa ety injection pump of the same train are OPERABLE and ' ava.ilabl,e f.o.r..injecti.on: from, ~the RWST. J^ '~ ~ ~ ~ c 6 ?ThsIRWSTfcontilhiitheiv61smeTof(WhteFIFe'qd1E4 dst 6Tfatiil E)ltheR.. evelkto 20_1fei. tM,b_6Vdithe._@e_asto.~Mvbsielsf.. w ~ i 7)MhilasibciatedJEmergehjylDidselysnsfatbMig0PERABLE; tThs isater? tempe ratureT6fE thsi!SDC2 syst_em li i? mai ntai ned ? 8)11essit_hant120,*Fi y' ~' ~~~ ~ -- ~,. I ..........................--N0TE---------------------------- A containment spray pump may be used in place of a low l pressure s iety injection pump to provide shutdown cooling fl ow. 1 APPLICABILITY: MODE 6 with the water level < M 20 ft above the top of reactor vessel flange. l ACTIONS 1 SAN ON0FRE--UNIT 3 3.9-8 AMENDMENT N0. I

n SDC and Coolant Circulation-Low Water Level 3.9.5 ONM REQUIRED ACTION COMPLETION TIME f A. One SDC loop A.1 Initiate action to Immediately inoperable. restore SDC loop to OPERABLE status. (ApplicableitoNnitial conditions-ofitwoishutd6wn M coolingj~traists10PERABLE)' ~ ~' " ' ' A.2 Initiate actions to Immediately establish a M 20 ft of water above the top of reactor vessel flange. B;p':Onh1500?L6oR0pirablei Bilf.g"(Initiats?actiohsi,f6 Inimediateli 1,sfthan*20lfe'eti.of" establishi420Eftsf ~ " " " ' ~ " ~ ' s wateriabove:sthe~ ~ water"^'~ " "~ ~ reactor! pressure ve'ssel s flangef andTill' 8;reyuirementsllnotimet (Applicabic[to& initial. conditions:of+onefshutdown ' oolingj;t'rsinLOPERABLEland c '^ operating with requirements 11F8). BC No SDC loop OPERABLE 80.1 Suspend operations Immediately or in operation, involving a reduction in reactor coolant boron concentration. AND l (continued) I SAN ON0FRE--UNIT 3 3.9-9 AMENDMENT NO.

SDC and Coolant Circulation-Low Water Level 3.9.5 -ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME BC.2 Initiate action to Immediately restore one SDC loop to OPERABLE status and to operation. aM1 B0.3 Close all containment 4 hours penetrations providing direct access from containment atmosphere to outside atmosphere. SURVEILLANCE REQUIREMENTS SURVEILLANCE FRQUE SR 3.9.5.1 Verify required SDC loops are OPERABLE 12 hours and one SDC loop is in operation and circulating reactor coolant at a flow rate of a 2200 gpm. SAN ONOFRE--UNIT 3 3.9-10 AMENDMENT N0.

T SDC and Coolant Circulation-High Water Level 8 ?.9.4 8 3.9-REFUELING OPERATIONS B 3.9.4 Shutdown Cooling (SDC) and Coolant Circulation-High Water Level i BASES BACKGROUND The purposes of the SDC System in MODE 6 are to remove decay heat and sensible heat from the Reactor Coolant System (RCS), as required by GDC 34,-to provide mixing of borated coolant, to provide sufficient coolant circulation to minimize the offects of a boron dilution accident, and to prevent boron si.catification (Ref.1). Heat is removed from .the RCS by circulating reactor coolant through the SDC heat exchangers, where the heat is transferred to the Component Cooling Water System via the SDC heat exchangers. The coolant is then returned to the RCS via the RCS cold leg (s). Operation of the SDC System for normal cooldown or decay heat removal is manually accomplished from the control room. The heat removal rate is adjusted by controlling the flow of-reactor coolant through the SDC heat exchangers and bypassing the heat exchangers. Mixing of the reactor coolant is maintained by this continuous circulation of reactor coolant through the SDC System. The shutdown cooling ystem is a safety related, seismically qualified system which is powered by a class IE electrical system. The cooling capacity of 1 train of the shutdown cooling system is sufficient to maintain the spent fuel pool temperature lower than can be maintainad by the spent fuel pool cooling system. When components of the shutdown cooling system are not required to be OPERABLE by technical specifications, then one train of the shutdown cooling system (consisting of at least 1 LPSI pump or 1 containment spray pump, I heat exchanger, flow path to and from the SFP, and the associated Diesel Generator) may be aligned to cool the spent fuel pool. Addition:lly, during MODE 6 with the reactor rt Neling canal water level greater than or equal tc M 20 feet above the reactor flange, the SDC system (consisting of at least 2 pumps (either 1 LPSI pump and 1 CS pump or 2 CS pumps),1 SDC heat exchanger, flow paths to and from the RCS and SFP, and the associated Diesel Generator) may be aligned to cool both the SFP and the reactor core. (continued) SAN ONOFRE--UNIT 3 8 3.9-16 AMENDMENT N0. u a.- ,-r

SDC and Coolant Circulation-High Water Level B 3.9.4 BASES APPLICABLE If the reactor coolant temperature is not maintained below SAFETY ANALYSES 200aF, boiling of the reactor coolant could result. This could lead to inadequate cooling of the reactor fuel due to a resulting loss of coolant in the reactor vessel. Additionally, boiling of the reactor coolant could lead to a reduction in boron concentration in the coolant due to the boron piating out on components near the areas of the boiling activity, and because of the possible addition of water to the reactor vessel with a lower boron concentration than is required to keep the reactor subcritical. The loss of reactor coolant and thc reduction of boron concentration in the reactor coolant would eventually challenge the integrity of the fuel cladding, which is a fission product barrier. One train of the SDC System is required to be operational in MODE 6, with the water level a M 20 ft above the top of the reactor vessel flange, to prevent this challenge. The LC0 does permit de-energizing of the SDC pump for short durations under the condition that the boron concentration is not diluted. This conditional de-energizing of the DC pump does not result in a challenge to the fission product barrier. SDC and Coolant Circulation-High Water Level satisfies. Criterion 2 of the NRC Policy Statement. LCO Only one SDC loop is required for decay heat removal in MODE 6, with water level a M 20 ft above the top of the reactor vessel flange. Only one SDC loop is required because the volume of water above the reactor vessel flange provides backup decay heat removal capability. At least one SDC loop must be in operation to provide: a. Removal of decay heat; b. Mixing of borated coolant to minimize the possibility of a criticality; and c. Indication of reactor coolant temperature. An OPERABLE SDC loop includes an SDC pump, a heat exchanger, valves, piping, instruments, and controls to ensure an OPERABLE flow path and to determine the low end temperature. (continued) SAN ON0FRE--UNIT 3 B 3.9-17 AMENDMENT N0.

SDC and Coolant Circulation-High Water Level B 3.9.4 ~ BASES N L LCO The flow path starts in one of the RCS hot legs and is (continued). returned to the RCS cold. legs. TheLC0ismodifiedbyaNote.thatyNithithiispp6Figuide- \\ istfyctspeifemoyhdjfrom]thijaiptoFipNssureijassel ygil16ws f the requiFed operating SDC loop t'o be removed from service - for up to 42 hour's in each 8 hour period, provided th'ati ne Operati:n; Irc pehitted that.=uld ::::: dilution 5f"the Re: tcr C 01:nt Syster bcrca concentration. a.J" The' Maximum"RCS temperature is maintained 5 140*F: b. No operations are permitted that would cause a' ' "~ reduction of the RCS boron concentration: ^ c'i;]'The capability to close the containment ' penetrations With direct access to the outside atmosphere within" the calculated time to boil is maintainedT" ^"'"~'

d. ' The reactor cavity water level. is maintained =~20' feet

'" ' above,the reactor pressure vessel flange, or, for Core Alterations,'t 23 feet above the top of the reactor' pressure' vessel fl ange. "' ~" ' ~" " ~" ' ^ "" ~~ " ' This permits operations such as core mapping or alterations in the vicinity of the reactor vessel hot leg nozzles, and RCS to SDC isolation valve testing Nandiinservicelt6 sting *of LPS!Ny~stehTchapbnsnts. During th'is~2'^hobF^^peFiddT^dediy~ heat'is pem6Ved'by"nstural convection to the-large mass of water in the refueling canal. Also, this LC0 is modified by the Note that allows Operations to use a containment spray pump in place of a low pressure safety injection pump to provide shutdown cooling flow. APPLICABILITY One SDC loop must be in operation in MODE 6, with the water. level a M20 ft above the top of the reactor vessel flange, to provide ^ decay heat' removal. The 23 ft level =: ::100ted becau:: it ecrre:p nd; to the 23 ft requir =nt est:bli: Led for fuel =v= cat in LC0 3.0.5, "Refuelin;; nter Level." Requirements for the SDC System in other MODES are covered by LCOs in Section 3.4, Reactor Coolant. System (RCS), and Section 3.5, Emergency Core Cooling' Systems (ECCS). SDC loop requirements in MODE 6, with the water level < M 20 ft above the top of the reactor vessel-flange, are located *in LC0 3.9.5, " Shutdown Cooling (SDC) and Coolant Circulation-Low Water Level." (continued)' SAN ON0FRE--UNIT 3 8 3.9-18 AMENDMENT NO.

SDC and Coolant Circulation-High Water Level B 3.9.4 BASES ACTIONS SDC loop requirements are met by having one SDC loop OPERABLE and in operation, except as permitted in the Note to the LCO. M If SDC loop requirements are not met, there will be no forced circulation to provide mixing to establish uniform boron concentrations. Reduced boron concentrations can occur through the addition of water with a lower boron concentration than that contained in the RCS. Therefore, actions that reduce boron concentration shall be suspended immediately. U If SDC loop requirements are not met, actions shall be taken immediately to suspend loading ' irradiated fuel assemblies in the core. With no forced circulation cooiing, decay heat removal from the core occurs by natural convection to the heat sink provided by the water above the core. A minimum refueling water level of M 20 ft above the reactor vessel flange provides an adequate ~ivailable heat sink. Suspending any operation that would increase the decay heat load, such as loading a fuel assembly, is a prudent action under this condition. A.3 If SDL, loop requirements are not met, actions shall be initiated and continued in order to satisfy SDC loop requirements. A.4 If SDC loop requirements are not met, all containment penetrations to the outside atmosphere must be closed to prevent fission products, if released by a loss of decay heat event, from escaping the containment building. The 4 hour Completion Time allows fixing most SDC problems without incurring the additional action of violating the containment atmosphere. (continued) SAN ONOFRE--UNIT 3 8 3.9-19 AMENDMENT N0.

SDC and Coolant Circulation-High Water Level B 3.9.4 BASES SURVEILLANCE SR 3.9.4.1 REQUIREMENTS This Surveillance demonstrates that the SDC loop is in operation and circulating reactor coolant. The flow rate is determined by the flow rate necessary to provide sufficient decay heat removal capability and to prevent thermal and boron stratification in the core. The Frequency of 12 hours is sufficient, considering the flow, temperature, pump control, and alarm indications available to the operator in i the control room for monitoring the SDC System. 4 REFERENCE 1. UFSAR, Section 7.4. c A b i 1 1 t SAN ONOFRE--UNIT 3 B 3.9-20 AMENDMENT N0.

• 1 SDC and Coolant Circulation-Low Water Level B 3.9.5 B 3.9 REFUELING OPERATIONS B 3.9.5 Shutdown Cooling (SDC) and Coolant Circulation-Low Water Level BASES

,= BACKGROUND The purposes of the SDC System in MODE 6 are to remove decay heat Ahd sensible heat from the Reactor Coolant System (RCS), as required by GDC 34, to provide mixing of borated coolant, to provide sufficient coolant circulation to minimize the effects of a boron dilution accident, and to prevent boron stratification (Ref. 1). Heat is removed from the RCS by circulating reactor coolant through the SDC heat exchangers, where the heat is transferred to the Component Cooling Water System via the SDC heat exchangers. The 1 J coolant is then returned to the RCS via the RCS cold legs. Operation of the SDC System for normal cooldown or decay heat removal is manually accomplished from the control room. The heat removal rate is adjusted by controlling tha flow of reactor coolant through the SDC heat exchangers and bypassing the heat exchangers. Mixing of the reactor coolant is maintained by this continuous circulation of reactor coolant through the SDC System. The shutdown cooling system is a safety related, seismically qualified system which is powered by a class lE electrical system. The cooling capacity of 1 train of the shutdown cooling system is sufficient to maintain the spent fuel pool temperature lower than can be maintained by the spent fuel pool cooling system. When components of the shutdown cooling system are not required to be OPERABLE by technical specifications, then one train of the shutdown cooling system (consisting of at least 1 LPSI pump or 1 containment spray pump, I heat exchanger, flow path to and from the SFP, and the associated Diesel Generator) may be aligned to cool the spent fuel pool. Additionally, during MODE 6 with the reactor refueling cavity water level less than 23 20 feet above the reactor flange, the SDC system (consisting of at least 2 pumps (either 1 LPSI pump and 1 CS pump or 2 CS pumps),1 SDC heat exchanger, flow paths to and from the RCS and SFP, and the associated Diesel Generator) may be aligned 1 to cool both the SFP and the reactor core. (continued) SAN ON0FRE--UNIT 3 B 3.9-21 AMENDMENT NO.

SDC and Coolant Circulation-Low Water Level B 3.9.5 BASES ' APPLICABLE If the re'ctor coolant temperature is not maintained below SAFETY ANALYSES 200*F, boiling of the reactor coolant could result. This could lead to inadequate cooling of the reactor fuel due to the resulting loss of coolant in the reactor vessel. Additionally, boiling of the reactor coolant could lead to a reduction in boron concentration in the coolant due to the boron plating out on components near the areas of the boiling activity, and because of the possible addition of water to the reactor vessel with a lower boron concentration than is required to keep the reactor subcritical. The loss of reactor coolant and the reduction of boron concentration in the reactor coolant would eventually challenge the integrity of the fuel cladding, which is a fission product i b&rrier. Two trains of the SDC System are required to be OPERABLE, and one train is required to be in operation in MODE 6, with the water level < M20 ft above the top of the reactor vessel flange, to prevent'^this challenge. Wi thitheResctorlyessel [ head 2em6Vidfiddp2f feithffiatM aboventhageactorf pr.essurekvesselsflangetandssillthe ____. specifibdlrequirementsimetiatheatysinktislavailibleifor core cool;ingiandia methbdMslavailable3toirestoreithegeacto[r " cavity d evelstoj20s fietfabois ithe;reactorivessellfl angeh Thereforefirn the!eventiofiasfailweioff theioperating' ~ t s hutdown! c ool.i ng j t rain,fadequa test i meti s /provi ded3"0 initiatesemergencyjpr.octdureskto[coolkthpcoref One train of shutdown cooling shall be OPERABLE and operating under the following conditions: t SDC and Coolant Circulation-Low Water Level satisfies Criterion 3 of the NRC Policy Statement. LC0 In MODE 6, with the water level < M20 ft above the top of the reactor vessel flange, both SDC 160ps must be OPERABLE. Additionally, one loop of the SDC System must be in operation in order to provide: a. Removal of decay heat; b. Mixing of borated coolant to minimize the possibility of a criticality; and c. Indication of reactor coolant temperature. (continued) SAN ON0FRE--UNIT 3 B 3.9-22 AMENDMENT N0. l

SDC and Coolant Circulation-Low Water Level B 3.9.5 BASES LC0 An OPERABLE SDC loop consists of an SDC pump, a heat (continued) exchanger, valves, piping, instruments, and controls to ensure an OPERABLE flow path and to determine the low end temperature. The flow path starts in orie of the RCS hot legs and is returned to the RCS cold legs. This LC0 is modified by the Note that allows Operations to use a containment spray pump in place of a low pressure safety injection pump to provide shutdown cooling flow. 05 1)MThi?re.3,htsW his7 bs.eh.yjy.y. hut,,dosni.nm h,4.A,,+nwo:g, +,,mo:<.i?.x j;yfo ~itEliatt 67~5,1 i n + g.; 40M40~wa ' #; ,wfx y - 4;..' 4 -

1. f.;u,#.

eu .aq,w :- 9 4 g ,.,q

• )'~"gres. t_Lsri tm2 DTheTsater31evelysboWthsTFiacto@"'

ha6.m12_3 festi ~*"" ** *"" "^""~~^ ~~

• 3.-)s 40ne S,t ra i Wi_~o fi_S_al t3 Wa te.EI C6oa_1 hg3.(~S.W,C),%_i i[0,.~PER._ABL_E4nd 1

a_c an peraMn~gi 4 )p~0hfitPaih?6 ffC6mp6ndnt? Cosl ing1WstbQ(CCW)7ahdithij'CCW swingspumpVare:0PERABLEMandiths?;CCWitrainfis"" ~~ $,peratin.g-QC+y%?witMeitheriof4the(OPERABLE?fCCWipnapi! o '" - -* Gq _, -*2-

q.nz.g.:Q., -- ;&M.wxyg.y.:sqxr: - - x.y.g C);s.g@* v xgy;.,.pgqqn

, j.g 5 )UOnei tra t hio ff shutd6whiCool i ngII sIDPERABL EEWi thYi "~sontainment(sprayfpump$operatingfosi;uhutdswn?coolingy~ s thelhighipressuredsafetyfinjectionpmpland$the@los' t bressuretsafetysinjectioni OPERABLEs_andl.availabih? f6M. pumploff the.Bsames injecti6ntfaomEthelRWSU r a a _ w -a- - _ n.~ i 6)D'The s RWS1Tco#ta insitlidWol u' msisfssiteryisqu1 Fed htd ~~ rai sQ;hje g evelstoij 20Efest? abo 9eithshactor@es._se f1ange J)QThelaispi,atEdlEmsygespyJjyieXGeneQtogippiragg 8)'? 3Thiilwatsr'tempeFatspeisfEtheTSDC?iistem71iimaintainsd l ~ ~ *~ ~ ~ " ~ *^ " ~ ' ~ ~ ~ ^ 1essithanil20*FF. + a ~ APPLICABILITY Two SDC loops are required to be OPERABLE, and one SDC loop must be in operation in MODE 6, with the water level < M.20 ft above the top of the reactor vessel flange, to provide decay heat removal. Requirements for the SDC System 4 in other MODES are covered by LCOs in Section 3.4, Reactor 1 Coolant System. MODE 6 requirements, with a water level a M20 ft above the re:ctor vessel flange, are covered in g (continued) SAN ONOFRE--UNIT 3 8 3.9-23 AMENDMENT N0.

SDC and Coolant Circulation-Low Water Level B 1.9.5 BASES APPLICABILITY LC0 3.9.4, " Shutdown Cooling and Coolant Circulation-High (continued) Water Level." ACTIONS a.1 and A.2 WhesitwMSDC5trainMapelopePablefandMif one SDC loop 4s iEji3Fibibbecomestinoperable,'astiani shall be immediately initiated 'ind'Ednt"inued~until the SDC loop is restored to OPERABLE status and to operation, or until t 2320 ft of water level is established above the rmctor vessel flange. When the water level is established at t G420 ft above the reactor vessel flange, the Applicability will change to that of LC0 3.9.4, " Shutdown Cooling and Coolant Circulation-High Water Level," and only one SDC loop is required to be OPERABLE and in operation. An immediate Completion Time is nece sary for an operator to initiate corrective actions. LL1 WhenT6nettrainCof1SDCTis 5 rable %ithErequiremsnts? F 8 sat i s fied R and? the> SDCil oop; bbcomels}i noperabl e i requi remen ts$ a re s noti met u acti on sish al.1 :4 beliaml:oria ediately i ni ti ated ; toiest abl i sWlahvater21 evelM20 Lfeet?aboveit he reactor" pressure?flangeSWhenfthelwatetilevel!lis~ ' ~ i e stabl i shed ? atW 20ifeetlabovei thel re actort pre s s ure Ne s iel ] flangenthela~ ~plicabil'it swtll?chan eit6thatiofiLC093 1.e el, N andlonly sne l SDCil oopt i sEredvi i "ShutdowniCoo ingiand!Co lintECipuu atioh2 Hi ~~^ beIOPERABLEfand ) i n i bpe rs t i oh'. L ( Ah ?immedi.atelCompl eti _oh jTime21 s} nece'sls arylfoE an. operator ltoLijtiateicorrecttvegactionsf j ~~ El If no SDC loop is in operation or no SDC loops are OPERABLE, there will be no forced circulation to provide mixing to establish uniform coron concentrations. Reduced boron concentrations can occur by the addition of water with lower boron concentration than that conthined in the RCS. Therefore, actions that reduce boron concentration shall be suspended immediately. (continued) SAN ON0FRE--UNIT 3 8 3.9-24 AMENDMENT N0.

SDC and Coolant Circulation-Low Water Level B 3.9.5 BASES ACTIONS f!L2 (continued) If no SDC loop is in operation or no SDC loops are OPERABLE, actions shall be initiated immediately and continued without interruption to restore one SDC loop to OPERABLE status and operation. Since the unit is in Conditions A and B concurrently, the restoration of two OPERABLE SDC loops and one operating SDC loop should be accomplished expeditiously. 11L1 If SDC loops requirements are not met, all containment penetrations to the outside atmosphere must be closed to prevent fission products, if released by a loss of decay heat event, from escaping the containment building. The 4 hour Completion Time allows fixing most SDC problems without incurring the additional action of violating the containment atmosphere. SURVEILLANCE SR 3.9.5.1 REQUIREMENTS This Surveillance demonstrates that one SDC loop is operating and circulating reactor coolant. The flow rate is determined by the flow rate necessary to provide sufficient decay heat removal capability and to prevent thermal and boron stratification in the core. In addition, this Surveillance demonstrates that the other SDC loop is OPERABLE. In addition, during operation of the SDC loop with the water level in the vicinity of the reactor vessel nozzles, the SDC loop flow rate determination must also consider the SDC pump suction requirements. The Frequency of 12 hours is sufficient, considering the flow, temperature, pump control, and alarm indications available to the operator to monitor the SDC System in the control room. Verification that the required loops are OPERABLE and in operation ensures that loops can be placed in operation as ) needed, to maintain decay heat and retain forced circulation. The Frequency of 12 hours is considered i reasonable, since other administrative controls are available and have proven to be acceptable by operating experience. (continued) SAN ON0FRE--UNIT 3 8 3.9-25 AMENDMENT NO.

SDC and Coolant Circulation-Low Water Level B 3.9.5 BASES REFERENCE 1. UFSAR, Section 7.4. 1 SAN ONOFRE--UNIT 3 8 3.9-26 AMENDMENT NO.

7 =. .i e FIGURE 1 FROM CALCULATION NO. SUPPLEMENT A N-0220-029 RCS HEATUP RATE AS A FUNCTION OF TIME AFTER SHUTDOWN AND CAVITY LEVEL s F h- } ,h ' . 2 _ _ _ - _ _,. ~. -._.., _.. _ _ _ _. - -...

NES&L DEPARTMENT CALCULATION SHEET " ""o' PREUM. CCN NO. N 4 FAGE R OF M Propct or DCP/MMP SONGS 2/3 Calc. No.Suco A N-0220-029 CCN CONVERSION: CCN NO. CCN - SubjectRCS Homuo Followina l_m of Shutdown Coolina Sheet No. A-28 REV oR8GINATOR DATE IRE DATE REV ORIGINATop OATE IRE DATE R U E /s W. G. Floumoy 3/25/94 J, Boyajian 3/25/94 /\\ /\\ /\\ 3 z I v ! I .I l -i. l 't' 'l ! l l 3 I 5 5 5, ,g hhg, I,i. l~' l l 1 I ' I

l.. i i i

E [ '1 1 i i l' j i i i i i j i l if' i i !

l l

ij i l i i l l l 1 l.i I i l l ll l l l. I i il l l ll* ..:1-L -. _! -.==. L ...t. l L.. r--- ki,~ ^ -- .?-=N-N-- :- t - ~.YN--A-Y~ T ~ ~ l l l, I l l l l l l i l i .l_.-- b. 1 i-

7_. r-j

-f. 418 4 i i i I l f-i i i I vi j ; l~l'l l. I..! i i l l f A 7 i i e l.'...p::. .l - .s. l- ,o 8 1 I I-2lR '.! 'l 1l' l 2I I fi

• 1 5

I .r i i i g. 3 i l-t.l 6 0 2 .c - m 9 l! l..l : :l.. .... l. ) g g ...t. l. - j... ! l .. r..i -..-. 2.L 1 g l l i l l -.i l r.i '-lj j %i g l :g ! I I I i ii i I' !J i I j]. i I e i i i i .I i i.if

2J"

. j.. l. j i ,l.. .j j . If. i a i '- - l i . t'. I -':l - / l E' i i lf /r / ; $~ l I ! "[ /i // i I l i / I / ;/ I $l i ' i i i 11 .l- /..iri / //i E] I i l l ^! i ! if -l / // yl i i l,,~ . j.. ._. I / Ifi / / 1 3 1 i I I i l l i .1 i I.rj l l l ! I i i E E o g e ou/J.) stes dnieau 1}}