ML20071K897

Proposed Tech Specs 3.9.8.1 & 3.9.8.2 Re Shutdown Cooling & Coolant Recirculation

ML20071K897
Person / Time
Site:	San Onofre
Issue date:	07/28/1994
From:	SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML20071K869	List: ML20071K865 ML20071K877 ML20071K897
References
NUDOCS 9408020075
Download: ML20071K897 (53)

Text

NPf-10/15-402 ATTACHMENT "A" EXISTING SPECIFICATIONS UNIT 2 9408020075 940728 PDR ADOCK 05000361 p PDR

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REFUELING OPERATIONS 3142 9.8 SHUTDOWN C00t1NG AND COOLANT CIRCULATION 1

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_H_1GH VATER LEVEL (1MITING CONDITION FOR OPERATION 3.9.8.1 At least one shutdown cooling train shall be OPERABLE and in 3 l

operation.l*

t APPLICABillTY:

H0DE 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-l tions involving an increase in the reactor decay heat load or a reduction in T boron concentration of the Reactor Coolant System and immediately initiate cor-rective action to return the required shutdown cooling train to OPERABLE and operating status as soon as possible. Close all containment penetrations pro-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 />.

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SVRVEILLANCE REOUTREMENTS 4.9.8.1 a. At least one shutdown cooling train shall be verified to be in  ;

operation and circulating reactor coolant at a flow rate of i 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 />.  !

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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 DCP 2-6863)

AMENDMENT NO. 457 106 SAN DNOFRE - UNIT 2 3/4 9-8

t REFUEt1NG OPERATIONS

- LOW WATER LEVEL L1MITING CONDITION FOR OPERATION 3.9.8.2 Two independent shutdown cooling trains shall be OPERABLE and at l l least one shutdown cooling train shall be in operation.*

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

pressure vessel flange is less than 23 feet.  !

ACTION:  !

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a. With less than the required shutdown cooling trains OPERABLE, imme-diately initiate corrective action to return the required shutdown cooling trains to OPERABLE status, or to establish greater than or aqual to 23 feet of water above the reactor pressure vessel flange as soon as possible.

b. With no shutdown cooling train in operation, suspend all operations involving a reduction in baron 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 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

i SURVElttANCE RE0UTREMENTS 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

• 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. 44; 106 SAN ONOFRE - UNIT 2 3/4 9-9

I REFUEllNG OPERATIONS A

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BASES 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION The requircment 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 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 loop will not result in aWith the r complete loss of decay heat removal capacity. removed and 23 feet of w 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 emer-gency procedures to cool the core.

AMENDMENT N0.-87, M4 SAN ONOFRE - UNIT 2 B 3/4 9-2a 106

NPF-10/15-402 ATTACHMENT "B" EXISTING SPECIFICATIONS UNIT 3 I

_ . _ . = _ . _ _ _ _ _ _ _. . _ .

s 4

I D REFUELING OPERATIONS 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION  :

HIGH WATER LEVEL l LIMITING CONDITION FOR OPERATION 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: i

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

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 />.

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SURVEILLANCE REOUIREMENTS J a.9.8.1 a. 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. l, i

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 flaw. (Subsequent to implementation of MMP 3-6863)

SAN ONOFRE - UNIT 3 3/4 9-8 AMENOMENT NO. SA 95 I

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gjFUELING OPERATIONS r,

. LOW WATER LEVEL LIMITING CONDITION FdR OPERATION 3.9.8.2 Two independent shutdown cooling trains shall be OPEPABLE and at l least one shutdown cooling train shall be in operation.f*

APPLICABILITY:

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

ACTION:

a. With less than the required shutdown cooling trains OPERABLE, inne-diately initiate corrective action to return the required shutdown 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,

b. 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 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEllLAtlCJ 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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 HMP 3-6863)

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

,4 REFUEL!NG OPERATIONS g

j BASES 3/4.9.8 SHUTOOWN 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 boron dilution incident and prevent boron stratification.

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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 f to provide shutdown cooling (SDC) flow.

The requirement to have two shutdown cooling trains OPERABLE when there is less i

than 23 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 com-plete 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 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 emer-gency procedures to cool the core. ,

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' AMENDMENT NO. W . W.

SAN DE UNIT 3 B 3/4 9-2a 95 x

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NPF-10/15-402 e

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ATTACHMENT "C"  ;

REVISED SPECIFICATIONS UNIT 2 i

REFUELING OPERATIONS 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION W GH 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 j 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 />.  !

4 SURVElltANCE REQUIREMENTS j i

4.9.8.1 a. 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. '

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'The shutdown cooling train may be removed from operation for up to FF. hours r per 8-hour period during the performance of 1) CORE ALTERATIONS in the licinity i of the reactor pressure vessel hot legs orL2) testingiofrLPSI system components required by:the in'servicelinspection prog' ram provided: .

a. The maximum RCS: temperature-is: maintained T 140aF; .

b. Nooperationstaretpermittedthatwouldicauselafredu~ctionoftheiRCS (

baron concentration;

c. The!capabilityJto close;thelcontainmentlienetrations:with' i direct

' access toithe outside atmosphere!withint:the' calculated:Ltime;to boil

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is. maintained;

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Td. L The reactor: cavity waterJ1.evellis:maintainedX20'.: feet aboveltheTtop  ;

of the reactor: pressure vessel; flange,/or',1for CoreiAlterations a: 23 ' feet above'the' top of. the reactor pressure vesself flange.l ,

• 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. fSubsequent-to-4mplementet4en-of DCP 2 5853)

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

REFUELING OPERATIONS LCW WATER LEVEL IIMITING 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.*

or One train'of shutdown ' cooling shall- be; OPERABLELand operating lunderf the following' conditions:

1)1The. reactor has been shutdown for'_attleast _6Tdays.

2) The ' water level' above the reactorf vessel flange is' greater than 12 feet.

3)'One train of Salt? Water Cooling .(SWC)'is OPERABLE a'nd operating:

4) 'One train 'of Component - Cooling' Water -(CCW)1and the ' CCW swing pump'.-

are OPERABLE, and.the.CCW train-is operatingLwith either of' thel OPERABLE CCW. pumps.

5) One train"of Shutdown Cooling ~1sLOPERABLE'with' a7contairimenta spray pump operating on :hutdown cooling, the high. pressure:

safety injection pump and the low pressure 'safetyJinjection pump of the'same train are OPERABLE and 'available for injection from:

the RWST.

6) The' RWST contains the ' volume of water required to' raise the level: to 20' feet above the reactor vessel flange.

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7) ;The ' associated EmergencyLDiesel . Generator is .0PERABLE.  :

1 8)~The' water temperature of'the SDC4 system is' maintained 11essi l

-than 120*F l l

6PPLICABILITY: MODE 6 when the water level above the top of the reactor {

pressure vessel flange is less than M 20' feet.

ACTIO.!]:

a. With less than the required shutdown cooling trains OPERABLE, immediately initiate corrective action to return the required shut- I down cooling trains to OPERABLE status, or to establish greater than or equal to N 20 feet of water above the reactor pressure vessel flange as soon as possible.

b. If operating one-train ~ of the shutdown" cooling system with less than 20 feet of water above the' reactor. pressure vessel flange and any of the required conditions ~(1 through 8) are not met, immediately take action-to' establ.ish greater than or-equal .to 20 feet'of ' water above the reactor pressure. vessel flange. '

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

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b c. With no shutdown cooling train in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant l 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 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCE REQUIREMENTS  :

i 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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• 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 to implementation--cf DCP 2 5853)

SAN ON0FRE-UNIT 2 3/4 9-9a AMENDMENT NO.

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REFUELING OPERATIONS BASES I

l 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION )

The requirement that at least one shutdown cooling train be in operation ensures l that (1) sufficient cooling capacity is available to remove decay heat and j 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 ,

1 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 l provide shutdown cooling (SDC) flow.

The requirement to have two shutdown cooling trains OPERABLE when there is less than e3 20 feet of water above the reactor pressure vessel flange, ensures that 1 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 M 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.

With' the reactor vessel head' removed and 12 feet' 'of- water above the reactor pressure vessel flange and all the specified requirements' met', a boat . sink is available for core cooling and a method is available to:restare.Jae reactor cavity level to 20 feet above the reactor vessel flange. p;nerefore, in the event of a failure of the operating shutdown ~ cooling. train,f adequate: timeli.s 1 provided to initiate emergency procedures-to cool thefcore; i

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l SAN ON0FRE-UNIT 2 B 3/4 9-2a AMENDMENT No. l l

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NPF-10/15-402 l

ATTACHMENT "D" REVISED SPECIFICATIONS UNIT 3 l

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REFUELING OPERATIONS 3/4.9.8 SHUTDOWN C00_ LING AND COOLANT CIRCULATION HIGH WATER LEVEL '

LIMITING CONDITION FOR OPERATION ,

i 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 I 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 />.

SURVEliLANCE RE0VIREMENTS s 4.9.8.1 a. 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

'The shutdown cooling train may be removed from operation for up to E 2? hours per 8-hour period during the performance of 1) CORE ALTERATIONS in ths 91cinity of the reactor pressure vessel hot legs ors 2)ctestingtof LPSItsystem? components

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required by the ,inservicesinsphctionTprogram provided:.

- a.. The maximum;RCSLtemperatureDis: maintained s!140*Fi s

b. 'No:operationsvare; permitted;~thatiwoulicauselaf reductioniofEthe1RCS boron ~ concentration c.lThecapabili.tyftocloselth'eTcontainmentjpenetrat;ionswithidiPect  :

access to the:outsideratmosphere within theicalculated timeito: boil is maintainedi

'd. The reactor. cavity water levelfis?maintainedit120ifeettabove. thet top of the- reactor: pressure vessel flange,y or, for Core Alterationstar23 feet above the : top;of the7 reactor pressure vessellflange.  !

• 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. tSubsequent to implementaticn of MMP 3 SSGt L

F SAN ONOFRE - UNIT 3 3/4 9-8 AMENDMENT N0.  !

EfF_UR ING OPERATIONS LOW WATER LEVEL llMITING CONDITION FOR OPERATION 3.9.8.2 Two Independent shutdown cooling trair s shall be OPERABLE and at least one shutdown cooling train shall be in operatici .K*

or One train of shutdown cooling shall_ be'0PERABLE and operating under;the following~ conditions:

1) The reactor has been shutdown for atileast 6 days.

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2) The water level above the reactor vessel flange'is' greater than -

12' feet.

3) Onel train of.~ Salt Water: Cooling;(SWC).' is OPERABLE';and operating.

4) One ' train ~'of Component' Cooling' Water (CCW) and the CCW swing pump 1-are OPERABLE, and-the;CCW train is operating with eitherlof-the-OPERABLE CCW pumps.

5) 0n'Etrain'of e Shutdown Cooling.'is10PERABLE with a containment 1 spray 1 pump: operating. on. shutdown cooling, the high pressureisafety;

' injection ' pump and the low pressure safety injection' pump of the; same train are OPERABLE and 'available for. injection L from the RWST)

6) The' RWST contains ?the volume 'of water required toi. raise ~ the

-level to 20 feet above'the reactor vessel. flange.

7)'The' assoc'iated Emergency Diesel?Generatorfis'0PERABLE; p

8)-The water' temperature of the?SDC ^ system is maintairied less than 120$F.

APPLICABILITY: MODE 6 when the water level above the top of the reactor pressure vessel flange is less than M 20ifeet.

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 N 20 feet of water above the reactor pressure vessel flange as soon as' possible.

'b. If' operating one: train. of the shutdown cooling system.with less;than l 20 feet .of water above'the' reactor pressure vessel- f1ange and any ~of the. required conditions-(1 through-8) a.re not' met,Timmediately;take action to. establish greater than or' equal. to 20 feet of water above  ;

the reactor-pressure vessel flar,:;e.

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SAN ON0FRE - UNIT 3 3/4 9-9 AMENDMENT N0.

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b c. With no shutdown cooling train in operation, suspend all operations i involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the l required shutdown cooling train to operation. Close all containment j penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 HOURS.

J SURVEllLANCE RE0VIREMENTS i i

4.9.8.2 At least one shutdown cooling train shall be verified to be in  !

operation and circulating reactor ccolant 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 />.

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l fi--Beth-shut 4cwn cccling train; may be removed frc= cperation for up to I hcur per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during the performance of CORE ALTERATIONS in the Jicinity of the-reaet-er pressure vc;;cl het leg: revided all cperation; involving a reduction in bcron concentratica cf t;c RGS arc suspended.

• 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, fSubsequent-to impic=entat4cn of MMP 3 5853}

SAN ONOFRE - UNIT 3 3/4 9-9a AMENDMENT NO.

1 REFUELING OPERATIONS i i

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

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complete loss of decay heat removal capacity. With the reactor vessel head removed and M 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.

With"the' reactor" vessel head? removed 3and L12~ feet ~of water ~above':the reactor pressure vessel flange fandf all:the specified -'requirementsfmet, .a. heat l sink:is available:for core coolingiandra.. method.is :available to~ restore thel reactor cavity. level to 20 feetn above; the reactor vessel: flange.- Therefore,:;i_n the event'of a' failure of the operating shutdown, cooling' train,. adequate; time;is provided to? initiate emergency procedures to cool the: core; I

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

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i Enclosure 2 )

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l REVISED TECHNICAL SPECIFICATION IMPROVEMENT PROGRAM (PCN 299) TECHNICAL SPECIFICATIONS UNIT 2 n

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1 SDC and Coolant Circulation-High Water Level l 3.9.4 3.9 REFUELING OPERAT70NS 3.9.4 Shutdown Cooling (SDC) and Coolant Circulation-High Water Level LC0 3.9.4 One SDC loop shall be OPERABLE and in operation.

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NOTE----------------------------

The shutdown cooling train may be removed from operation for 512Jhours per 8-hour period during the performance of 1) t CORE ALTERATIONS in the vicinity of the reactor pressure ~ ' r vessel hot legs ort 2)ttestingloffLPSITsjsteml components  !

required;byfthecinservice? inspect'onLprogramTprovided:  !

a. !The maximum.RCSL:temperaturedis maintained s 1400F;

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b. Nofoperations~are:permittedithat(wouldLeauseia reduction t

'ofathe::RCS<boronLconcentration)

The; capability 1to close ntheTcontain.mentEienetrations i Ec.~ withldirects ac' cess toithe .out'sideiatmospiere Within1the

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i calculated timeLto: boil 11s maintainedF ~ ~

idMThe reactor. cavityfwater[levelijsimaintainedW 20? feet

'above :the reactor pressure vesseli f1ange,<or,fforl Core

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t Alterations,? r 23 :feetLabove the(top"of;thelreactor ~ '

pressure vessel):: flange..-

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...-N0TE----------------------------

A containment spray pump may be used in place of a low ,

pressure safety injection pump to provide shutdown cooling i flow. 'l i

i APPLICABILITY: MODE 6 with the water level m 33 20fft above the top of reactor vessel flange.

ACTIONS I 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 2 3.9-6 AMENDMENT NO.

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SDC and Coolant Circulation--High Water Level 3.9.4 ACTIONS j I

CONDITION REQUIRED ACTION COMPLETION TIME l

A. (continued) A.2 Suspend loading Immediately irradiated fuel assemblies in the Core.

b]LD A.3 Initiate action to Immediately satisfy SDC loop requirements.

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.4.1 Verify one SDC loop is in operation and 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> circulating reactor coolant at a flow rate of a 2200 gpm.

SAN ONOFRE--UNIT 2 3.9-7 AMENDMENT ND.

SDC and Coolant Circulation-Lou dater 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.

or One train;of shutdown cooling shall be OPERABLE:and operating under'the following.conditi.ons':

1) The ' reactor'hasbeen shutdownLfor7at.least 6 days;

2) The water level above the reactorlessel flange is:

greater than 12 feet.

3)'One train'of Sa.itl Water Coolingf(SWC)Lis' OPERABLE'and operating.-

4).0ne' train o.f Comp'onent Cooling Water'(CCW):andithe'CCWL:

swing pump are OPERABLE,-and:the CCW train is' operating.

with either of the OPERABLE CCW pumps.

~

5) 0ne' train'of ShutdowiCoolinglis 0PERABLE with a .

containment spray pump operatington shutdown cooling, the!

high. pressure safety. inje'ction pump and the-low pressure

! safety injection pump.of the same-train are.-OPERABLE-and_

available for injection.from the' RWST.

6) The RWST contains'the volume'of water required to' raise

' the level to 20 feet above the: reactor.Lvessel flange.

7)"The associated' Emergency Die'selEGeneratorLis;OPERABLY.

8) The' water temperature;of:the~SDC-system i'~ '

s maintained

~less'than'120*F.

---

NOTE----------------------------

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

APPLICABILITY: MODE 6 with the water level < M 20 ft above the top of reactor vessel flange.

1 ACTIONS l

l SAN ON0FRE--UNIT 2 3.9-8 AMENDMENT NO.  !

SDC and Coolant Circulation-Low dater Level 3.9.5 CONDITION REQUIRED ACTION COMPLETION TIME A. One SDC loop A.I Initiate action to Immediately inoperable. restore SDC loop to OPERABLE status.

(ApplicablejtoLinitial conditions of two shutdown OB cooling; trains.0PERABLE)~ '

A.2 Initiate actions to Immediately establish a 33 20 ft of water above the top of reactor vessel flange.

B. :One'SDCL1o'opioperablel B?!? !InitiateTactionsDto Immediately less'than>20 feet of ~ establish al201 feet water above ~the' of! water.

reactor; pressure vessel flangelandra ll 8: requirements lnot met (Applicable': tolinitial conditions. of. one shutdowet cool ing; train'.' OPERABLE. and operating with requirementsM1-8)

BC. No SDC loop OPERABLE BC.I Suspend operations Immediately or in operation. involving a reduction in reactor coolant boron concentration.

AND (continued)

SAN ONOFRE--UNIT 2 3.9-9 AMENDMENT N0.

SDC and Coolant Circulation-Low Water Level 3.9.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME BC. (continued) BC.2 Initiate action to Immediately restore one SDC loop to OPERABLE status and to operation.

AND BC.3 Close all containment 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and one SDC loop is in operation and circulating reactor coolant at a flow rate of a 2200 gpm.

SAN ON0FRE--UNIT 2 3.9-10 AMENDMENT NO.

SDC and Coolant Circulation-High Water Level B 3.9.4 B 3.9 REFUELING OPERATIONS B 3.9.4 Shutdown Cooling (SDC) and Coolant Circulation-High Water Level BASES l

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 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 l 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 r 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 i system (consisting of at least 1 LPSI pump or 1 containment ,

spray pump,1 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 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 to cool both the SFP and the reactor core.

1 (continued)

SAN ONOFRE--UNIT 2 B 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 resrlt. This could lead to inadequate cooling of the reactor fuel due to a resulting loss of coolant in the reactor vessel.

Additionally, toiling 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 l of reactor coolant and the reduction of boron concentration l 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 e N 20 ft above the top of the reactor vessel flange, to prevent this challenge. The LCO 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 product barrier.

SDC and Coolant Circulation-High Water Level satisfies Criterion 2 of the NRC Policy Statement. l l

l LC0 Only one SDC loop is required for decay heat removal in MODE 6, with water level e N 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 backu) decay heat removal capability. At least one SDC loop must )e 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. I 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.

f I

t (Continued)

SAN ON0FRE--UNIT 2 B 3.9-17 AMENDMENT N0.

SDC and Coolant Circulation-High Water Level  !

B 3.9.4 BASES LCO The flow path starts in one of the RCS hot legs and is (continued) returned to the RCS cold legs.

The LCO is modified by a Note that allows the required operating SDC loop to be removed from service for up to 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br /> in each 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period, provided that: no operations are-permitted -that aculd cause di4* tion c'f' the "cactor Ceslant-Sy tem beren-ecncentratien.

a '. 'The Maximum RCS temperature is~ maintained $ 140aF.

b. .No operations are . permitted that. would cause a reduction of.the RCS boron concentration.

c. The capability to close the containment pen.etrations with direct access to.the outside atmosphere within

~

the calculated time-to boil is maintained.-

d. The reactor cavity waterJ1evel is maintained a 20 feet

~

above the reactor pressure vessel flange, or, for Core Alterations,~a:23' feet above'theLtop of the reactor'

~

pressure vessel flange.

~

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 and inservice' testing'of LPSI system components. During this 2~ hour period, decay heat is removed by 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.

APPLICABILITY One SDC loop must be in operation in MODE 6, with the water level a M 20 ft above the top of the reactor vessel flange, to provide decay heat removal. The 23 ft !cvel was selected beseuse it- corresponds-4+-the 23 f t requkement established -

for-fue4-mevement-in-LCO 3.9.5, "acfueling Ster 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 < N 20 ft above the top of the reactor vessel flange, are located in LCO 3.9.5, " Shutdown Cooling (SDC) and Coolant Circulation- ,

Low Water Level." l l

l (continued)

SAN ON0FRE--UNIT 2 8 3.9-18 AMENDMENT NO.

I

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.

A.1 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.

A.2 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 2-320 ft above the reactor vessel flange provides an adequate'available 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.

r A.3 If SDC loop requirements are not met, actions shall be initiated and continued in order to satisfy SDC loop requirements.

i 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 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time allows fixing most SDC problems without incurring the additional action of violating the containment atmosphere.

l (continued)

SAN ON0FRE--UNIT 2 B 3.9-19 AMENDMENT NO.

l l

SDC and Coolant Circulation--High Water Level B 3.9.4 l

BASES SURVEILLANCE SR 3.9.4.1 l HEQUIREMENTS  !

This Surveillance demonstrater 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  ;

baron stratification in the core. The Frequency of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is sufficient, considering the flow, temperature, pump t control, and alarm indications available to the operator in the control room for monitoring the SDC System. j REFERENCE 1. UFSAR F.e.-tion 7.4. ,

I i

i I

i i

l I

SAN ON0FRE--UNIT 2 8 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 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 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. i 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 i 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 j 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 i and SFP, and the associated Diesel Generator) may be aligned to cool both the SFP and the reactor core.

(continued)

SAN ONOFRE--UNIT 2 B 3.9-21 AMENDMENT NO.

SDC and Coolant Circulation-Low Water Level B 3.9.5 BASES APPLICABLE If the reactor coolant temperature is not maintained below SAFETY ANALYSES 200oF, bailing 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 barrier. 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.

Withfthe' reactor vessel head' removed and'127 feet'of water

~

above- the; reactor pressure vessel flangeland all. the specified. requirements met a heat sink is available-for' core cooling and a method-is available:ta restore the reactor cavity level to 20 feet above the' reactor vessel flange.

Therefore in the event of at failure of the operating shutdown cooling train, adequate time is provided to initiate emergency procedures to cool the core.

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 < M20 ft above the top of the reactor vessel flange, both SDC loops must be OPERABLE.

Additionally, one loop of the SDC System must be in operation in order to provide: i a Removal of decay heat;

c. Mixing of borated coolant to minimize the possibility of a criticality; and

c. Indication of reactor coolant temperature.

(continued) l SAN ON0FRE--UNIT 2 8 3.9-22 AMENDMENT NO.

l

SDC and Coolant Circulation-Lou 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 one of the RCS hot legs and is returned to the RCS cold legs.

This LCO 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, or 1)? The reactor has been shutdown for at.least 6' days'.

2) The water-' level above. the' reactor vessel flan'ge' is greater than .12 feet.

3) One train of Salt Water Cooling l(SWC) is'.0PERABLE and operating.

4)' One train of Component Cooling' Water (CCW)? and' thel CCW swing pump are OPERABLE,.and the'CCW train'is operating with.either of...the OPERABLE CCW pumps.

~

5)~ ' One tr'ain of LShutdown ' Cooling Tis OPERABLE with'a containment spray pump operating'on shutdown'coolings the high pressure safety injection pump'and the_ low pressure safety' injection pump of: the same train /are OPERABLE and available'for injection from the RWST.

6)' The' RWSTJcontains.the volumeof water. required to raise the level to 20 feet above :the reactor vessel fl ange.-

7)' The associated Emergency Diesel. Generator ~is . Operable.

8) The water temperatureTof the' SDC system is ' maintained less than 120aF.

APPLICABILITY Two SDC loops are required to be OPERABLE, and one SDC loop must be in operation in MODE 6, with the water level

< e320 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 e320 ft above the reactor vessel flange, are covered in (continued)

SAN ONOFRE--UNIT 2 B 3.9-23 AMENDMENT NO. l

SDC and Coolant Circulation-Low Mater Level l B 3.9.5 l l

i l

BASES APPLICABILITY LC0 3.9.4, " Shutdown Cooling and Coolant Circulation-High I (continued) Water Level."

ACTIONS A.1 and A.2 When two SDC trains are ' operable and31f one SDC loop -is 4nopecablebecomes-inoperable, ~~a'ction's s ' hall be immediately initiated and continued until the SDC loop is restored to OPERABLE status and to operation, or until a M20 ft of water level is established above the reactor ves'sel flange.

When the water level is established at a M20 ft above the reactor vessel flange, the Applicability will change to that of LCO 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 necessary for an operator to initiate corrective actions.

L.1 When one train of SDC is operable'.with req'uirements'la8 satisfied and the SDC loop becomes inoperable or-all 8 requirements are'not met, actions shall be immediately initiated to establish a water level > 20 feet'above the reactor pressure flange. When the water. level is established at'> 20 feet above.the' reactor. pressure-vessel flange, -the applicability will' change to;thatof' LCO 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 necessary for an operator to~ initiate. corrective actions.

BC.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 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) i SAN ON0FRE--UNIT 2 B 3.9-24 AMENDMENT NO.

SDC and Coolant Circulation-Low Water Level B 3.9.5 BASES ,

l ACTIONS LZ (continued) l If no SDC loop is in operation or no SDC loops are OPERABLE, actions shall be initiated immediately and continued without interruptian to restore one SDC loop to OPERABLE status and operation. Since the unit is in Conditions A and B concurrentiy, the restoration of two OPERABLE SDC loops and one operat,ng SDC loop should be accomplished expeditiously.

BC.3 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 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time allows fixing most SDC problems without incurring the additional action of violating the containment atmcsphere.

1 SURVEILLANCE SR 3.9.5.1 REQUIREMENTS This Surveillance demonstrates that one SDC loop is I 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is considered  ;

reasonable, since other administrative controls are available and have proven to be acceptable by operating experience.

(continued)

SAN ONOFRE--UNIT 2 B 3.9-25 AMENDMENT NO.

SDC and Coolant Circulation-Low Mater Level B 3.9.5 -

BASES REFERENCE 1. UFSAR, Section 7.4.

l SAN ON0FRE--UNIT 2 B 3.9-26 AMENDMENT N0. l 1

i

Enclosure 2 l

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

l l

1 1

1 l

l

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 LC0 3.9.4 One SDC loop shall be OPERABLE and in operation.

---

NOTE----------------------------

The shutdown cooling train may be removed from operation for 5 1 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8-hour period to support 1) CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs or

2) testing ~ofjLPSI. system components required by3the inservice. inspection program provided:

a. .The maximum.RCS temperature is maintainedLs 140'F.

b; No 0)erations:are: permitted that would;cause.a' reduction of tae:RCS boron concentrationi Tc.~ .The capability to close the' containment")enetrations with direct: access.to1the outside' atmospiere within:the calculated time'to' boil.is~ maintained.'

L d. The reactor. cavity. water levelLis maintainedia:20' feet

'aboveitheLreactor pressure . vessel: flange, or, for: Core Alterations, t 23 feet aboveLtheltop of the reactor 1 pressure Evessel. flange.

_______________________.----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 B3 20 ft above the top of reactor vessel flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDC loop requirements A.1 Suspend operations Immedia+ely not met. involving a reduction in reactor ccolant boron concentration.

AND (continued)

SAN ON0FRE--UNIT 3 3.9-6 AMENDMENT NO.

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.

ARQ A.3 Initiate action to Immediately satisfy SDC loop requirements.

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

SURVEILLANCEREgiRFMENTS SURVEILLANCE FREQUENCY SR 3.9.4.1 Verify one SDC loop is in operation and 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> circulating reactor coolant at a flow rate of a 2200 gpm.

i SAN ONOFRE--UNIT 3 3.9-7 AliENDMENT 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 LCO 3.9.5 Two SDC loops shall be OPERABLE, and one SDC loop shall be in operation.

or One train' of ? shutdown cooling'~ shall b'e OPERABLE and operating under the following conditions: '

1) The' reactor.~ha's been~ shutdown for'at'least 5 days.

2) The' water level above"the . reactor ' vessel flange' is greater'than 12 feet.

3) One' train.off Salt. Water Cooling:;.;(SWC) Lis~ OPERABLE:and operating.

~~

4)'One' train'of Component Cooling Water'(CCW)~and~the CCW swing pump are OPERABLE, and the CCW train ~is operating with either'.of the OPERABLE CCW pumps.

~

5)~ 0ne train of Shutdown' Cooling is 0PERABLE with a containment spray pump operating.on shutdown cooling, the'- '

-high pressure safety injection. pump and:the. low pressure safety injection pump of the same train are 0PERABLE and-available for injection from the RWST.

6)The RWST contains.the volume'of water required 16 raise the level 'to 20 feet' above the . reactor vessel' f1ange.

7). The_ associated Emergency! Diesel Generator is:0PERABLE.

8)~ The water' temperature of.the SDC system'is' maintained less than~120*F.

---

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 le 'el < 23 20 ft tbove the top of reactor vessel flan 7e.

ACTIONS SAN ON0'RE--UNIT 3 3,9-8 AMENDMENT NO.

SDC and Coolant Circulation-Low Water Level 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.

(Applicable to initial conditions of two shutdown OR cooling trains:0PERABLE)

A.2 Initiate actions to Immediately establish a B3 20 ft of water above the top of reactor vessel fl ange.

B. One SDC Loop Operable, B.1 Initiate actions to Immediately less than 20 feet of ' establish t 20.ft of

~

water above the water reactor pressure vessel flange and'all 8 requirements not met (Applicable to initial conditions ~of one' shutdown cooling train OPERABLE and operating with 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 3 3.9-9 AMENDMENT N0.

l l

l

SDC and Coolant Circulation-Low Water Level 3.9.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME t

BC.2 Initiate action to Immediately restore one SDC loop ,

to OPERABLE status  :

and to operation.

AND BC.3 Close all containment 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and one SDC loop is in operation and circulating reactor coolant at a flow rate of a 2200 gpm.

l l

SAN ON0FRE--UNIT 3 3.9-10 AMENDMENT NO. l l

)

l SDC and Coolant Circulation-High Water Level l B 3.9.4 l

B 3.9 REFUELING OPERATIONS l

^

B 3.9.4 Shutdown Cooling (SDC) and Coolant Circulation-High Water Level BASES l 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 effects of a boron dilution accident, and to l prevent boron stratification (Ref.1). Heat is removed from i 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. l The heat removal rate is adjusted by controlling the flow of l reactor coolant through the SDC heat exchangers and bypassing the heat exchangers. Mixing of the reactor j 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 canal water level greater than or equal to 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 to cool both the SFP and the reactor core.

(continued)

SAh ONOFRE--UNIT 3 8 3.9-16 AMENDMENT NO.

1 z

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 i 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 LCO 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 product barrier.

SDC and Coolant Circulation-High Water Level satisfies Criterion 2 of the NRC Policy Statement.

LC0 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 i

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.

l (continued)

SAN ONOFRE--UNIT 3 8 3.9-17 AMENDMENT NO.

i

SDC and Coolant Circulation-High Water Level B 3.9.4 BASES LCO The flow path starts in one of the RCS hot legs and is (continued) returned to the RCS cold legs.

The LCO is modified by a Note that allows the required operating SDC loop to be removed from service for up to 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br /> in each 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period, provided that: no-eper+ Mons are-permitted that seculd c-ause dilution of the Reacter Goolant System baron concentraMont

a. The Maximum RCSl temperature is maintained E 140*F.

b. No operations'are permitted that would cause a' reduction:of the RCS' boron concentration,

~ The capability to close the containment jenetrations

~

c.

with; direct 'acce's s to the outside atmosp1ere' within the calculated time to boil'is maintained.

d. The reactor: cavity water levelL is maintained ef 20'~ feet above~ the reactor pressure: vesseli flange, :or,' for_ Core Alterations, t 23: feet above~thel top ofLthe. reactor pressure vessel; flange.

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,'~and inservice' testing"of LPSI system components. During this 2' hour period, decay heat is' removed by 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.

APPLICABILITY One SDC loop must be in operation in MODE 6, with the water level a 2420 ft above the top of the reactor vessel flange, to provide decay heat removal. The 23 ft level was selected beesuse4t--eorresponds-to-the 23 f t - requi rement c:tablehed for-fuel movement in LC0 3.9.5, " Refueling Water Level."

Requirements for the SDC System in other MODES are covered  ;

by LCOs in Section 3.4, Reactor Coolant System (RCS), and l Section 3.5, Emergency Core Cooling Systems (ECCS). SDC leap requirements in MODE 6, with the water level < 23 20 ft ubove the top of the reactor vessel flange, are located in LC0 3.9.5, " Shutdown Cooling (SDC) and Coolant Circulation-Low Water Level."

ll (continued)

SAN ONOFRE--UNIT 3 B 3.9-18 AMENDMENT NO.

i

i l

SDC and Coolant Circulation-High Water Level B 3.9.4 l i

BASES ACTIONS SDC loop requirements are met by having one SDC loop '

OPERABLE and in operation, except as permitted in the Note I to the LCO.

l A.1 ,

1 If SDC loop requirements are not met, there will be no forced circulation to provide mixing to establish uniform i 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 i immediately. .

A.2 i

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 i 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 N 20 ft above the reactor vessel flange provides an adequate'available 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 l

If SDC loop requirements are not met, actions shall be initiated and continued in order to satisfy SDC loop requi rements.

A.4 If SDC loop requirements are not met, all containment 4 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 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time allows fixing most SDC problems '

without incurring the additional action of violating the containment atmosphere.

1 l

l (continued) l SAN ON0FRE--UNIT 3 B 3.9-19 AMENDMENT NO.

1

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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ,

is sufficient, considering the flow, temperature, pump '

control, and alarm indications available to the operator in the control room for monitoring the SDC System. l l

l REFERENCE 1. UFSAR, Section 7.4.

1 SAN ONOFRE--UNIT 3 8 3.9-20 AMENDMENT N0.

i SDC and Coolant Circulation-Low Water Level i B 3.9.5 83.9 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 provide mixing of borated 6 coolant, to provide sufficient coolant circulation to minimize the effects of a boron dilution accident, and to prevent baron 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 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 B3 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.

I l

l l

(continued) l SAN ONOFRE--UNIT 3 B 3.9-21 AMENDMENT NO.

1

SDC and Coolant Circulation-Low Water Level B 3.9.5 BASES APPLICABLE If the reactor coo' ant temperature is not maintained below j SAFETY ANALYSES 200*F, boiling of the reactor coolant could result. This l could lead to inadequate cooling of the reactor fuel due to the resulting loss of coolant in the reactor vessel.

i 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. 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.

With the~reactorfvessellhead removed;and 12 feet'~of8 water above -the reactor pressure vesseliflang'e' andL all the' specified requirements mets a heat sink is'available for" core cooling and.'a method .is available to: restore:the reactor cavity level 'to 20: feet above:the. reactor vessel flange.-

Therefore11n' the event.of a' failure)of the operating shutdown cooling train, adequatec time is provided to initiate emergency procedures to cool. the core.

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 < M20 ft above the top of the reactor vessel flange, both SDC loops must be OPERABLE.

Additionally, one loop of the SDC System must be in operation in order to provide:

a. Removal of Gecay heat;

b. hixing of borated coolant to minimize the possibility of a criticality; and

c. Indication of reactor coolant temperature.

(continued)

SAN ONOFRE--UNIT 3 8 3.9-22 AMENDMENT NO.

SDC and Coolant Circulation-Low Water Level B 3.9.5 BASES LCO 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 one of the RCS hot legs and is returned to the RCS cold legs.

This LCO 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.

of

1) . The. reactor; has been shutdown for atlleast 6' days.

2) The water levelabove:the reactor' vessel flange is greater than'12' feet.

3) L0ne train of Salt Water Cooling:(SWC) is' OPERABLE'and operating.

4) 'One train of Component Cooling' Water (CCW)Lant the CCW swing pump are OPERABLE,..and the CCW train is

~

operating with either.of the 0PERABLE.CCW pumps; 5)- One train of Shutdown Cooling .is '0PERABLEiwith a containment spray pump operating on shutdown cooling, the high pressure safety injection pump and the low pressure safety. injection. pump of the same train'are OPERABLE and available for tinjection from the' RWST..

6) :The1RWST contains the' volume of. water required to raise. the level to 20 feet abova the~ reactor vessel

~

fl ange.

7)~ The~ associated Emergency Dieser Generator is: Operable; The' water temperature of the SDC ' system is' maintained 8) less--than 120aF.

APPLICABILITY Two SDC loops are required to be OPERABLE, and one SDC loop must be in operation in MODE 6, with the water level

< 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 t M20 ft above the reactor vessel flange, are covered in (continued)

SAN ON0FRE--UNIT 3 B 3.9-23 AMENDMENT NO.

SDC and Coolant Circulation-Low Water Level B 3.9.5 BASES APPLICABILITY LCO 3.9.4, " Shutdown Cooling and Coolant Circulation-High (continued) Water Level ."

ACTIONS A.1 and A.2 When two' SDC ; trains are ~ operable'and 31f one SDC loop 4+

4nepenbhbecomes inoperable, ' actions shall be immediately initiated and ' continued until the SDC loop is restored to OPERABLE status and to operation, or until e M 20 ft of water level is established above the reactor vess'el flange.

When the water level is established at e M20 ft above the reactor vessel flange, the Applicability will change to that of LCO 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 necessary for in operator to initiate corrective actions.

IL1 When one train of 'SDC ~is ' operable' with requirements L1-8 satisfied and the SDC.. loop.becomes: inoperable or all 8' requirements are not met, actions shall be-immediately

~

initiated to establish a water: level > 20 ' feet above the reactor pressure flange. When the water level is established at > 20 feet above:.the reactor pressure vessel flange, the' applicability will change to .that of LCO 3.9.4,

" Shutdown Cooling and Coolant Circulation-High'. Water Level," and only: one SDC loop 'is required'.to be. 0PERABLE 'and in operation. An 'immediate Completion Time is, necessary'for an operator to' initiate corrective actions.

BC.1 l

If no SDC loop is in operation or no SDC loops are OPERABLE, there will be no forced circulation to provide mixing to l establish uniform boron concentrations. Reduced boron i concentrations can occur by the addition of water with lower  !

boron concentration than that contained in the RCS. l Therefore, actions that reduce boron concentration shall be suspended immediately.

(continued) l l l

l SAN ONOFRE--UNIT 3 8 3.9-24 AMENDMENT NO.

l

SDC and Coolant Circulation-Low Water Level i ACTIONS O i (continued) )

If no SDC loop is in operation or no SDC loops are OPERABLE, i actions shall be initiated immediately and continued without l 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 I one operating SDC loop should be accomplished expeditiously.

(

{ BC 3 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 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Completion Time allows fixing most SDC problems without incurring the additional action of violating the l containment atmosphere.

{

SURVEILLANCE SR 3.9.5.1 REQUIREMENTS T9is 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is considered reasonable, since other administrative controls are available and have proven to be acceptable by operating experience.

(continued) l l

SAN ON0FRE--UNIT 3 8 3.9-25 AMENDMENT NO.

l

SDC and Coolant Circulation-Low Water Level B 3.9.5 BASES REFERENCE 1. UFSAR, Section 7.4.

1 SAN ON0FRE--UNIT 3 B 3.9-26 AMENDMENT NO.

,