Text

Proposed Tech Specs,Modifying Operation of RHR Sys to Allow for More Flexibility But Retaining Min Required RHR Flow Rate of 1,000 Gpm
	ML19327B786
Person / Time
Site:	Salem
Issue date:	11/06/1989
From:	; Public Service Enterprise Group
To:	;
Shared Package
ML19327B784	List: ML19327B783; ML19327B786;
References
	NUDOCS 8911130301
	Download: ML19327B786 (14)
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THt5 PA M M WN TiwA L L Y 6 LAW 3.1. !. L c n rue flou r, ' O N REACT!VITY CONTROL SYSTEM 5_

1040N Q11gT1.0N LIMITING CONDITION FOR OPERATION s

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j 3.1 1.3 The flow rate of reactor coolant through the reactor coolant' systeh shall be 1 000 gym whenever a reduction in Reactor Coolant /

3 Systenbron concentration is being made.

APPLICA8!

All MODES.

ACTION:

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With the flow rate of reactor coolant through the reactor coolant system 3000 spm, immedlately suspend all operations invol(ing a reduction in boron concentration the Reactor Coolant System.

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SURVE!LLANCE REQUIREMENTS I

The flow rate of reactor \\ [

4:1.1.3 costant through the reactor coolant system shall. be determined to be p3000 gpm within one nour prior to the i

start of and at least once per hour durl a reduction in the Reactor i

Coolant System boron concentratMn by eit 4.

Verifying at less ne reactor cool' t pump is in operation, or

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Verifying that at least one RNR pump is n operation and supplying 3000 gpm through the reactor co Iant system.

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I ttFUELING CPERATIONS COOLANT CIRCULATION L N! TING CONDITION FOR OPERATION 3

[D 3.9.4.l A$/least one residual heat removal loop shall be in operation.

l APPLICABILITY: MODE 6.

ACTION:

With less than one residual heat rooval loop in operation, a.

except as provided in b. below, suspend a41 Gperations iwolving an increase in the reactor decay heat load or a 1

reduction in boron concentration of the Reactor Coolant t

System.

Close all containment penetrations providinp direct access from the containment atmosphere to the outside i

atmosphere within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

b.

The residual heat removal loop may be removed from operation for up to I hour per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period durino'the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs.

The provisions of $pecification 3.0.3 are not applicable.

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i SURVE!LLANCE REOUIRtutNTS t

I 4.9.8.l A-Peeldv64-heet-Penevel-16ep-sh411-be-determined-to-be-in-operet4en i

end-44eevleti= r;;et r ;^ 1ent-et-e-flow +ete-of-4000-epm-44-leett-4 eneo-per-12-houps.

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G, tt A722 T+sAu of 6 Q VAL TO 4000 G PM,

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$vffe t. s EM1~ TD osem HTA*N YM RLS 7 wpm arvtf A r-L&L5 Tw et Gq us L To /4'o *f.

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$AltM-UNIT 1 3/4 9 8 Amendment No. 34

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, o REFUELING OPERATION $

' 3/4.9.8 RE5100AL HEAT RDOVAL COOLANT CIRCULATION ALL WATER LEVEL $

LIN! TING COM01T10N.FOR OPERATION,

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3. 9. 8.1 At least one re;idual heat removal loop shall be in operation, j

APPLTCAS E : MCDE 6, ETJg:

With less than one residual heat removal loop in operation, except a.

as provided in b, below, suspend all operations involving an increase j

in the reactor decay beat load or a reduction ithoron concentration t

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of De Reactor Coolant System. Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

b.

The residual heat removal loop may be removed from operation for up l

to I hour per t hour period during the performance of CORE ALTERATIONS in the vicir.ity of the reactor pressure vessel het legs.

The provisions of Specification 3.0.3 are not applicable.

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$URVEILLANCE REQUIREMENTS l

4.9.8.l~ 4-residual-heat-removel-loop-shell-be-determined-to-be-in-operation-

-end-e iceulat i ng-eeac ter-cool ant-et-e-flow-rate -o f-greater-than-ee-e gva l-to-

-3000-gpe-et least-enee-pee-12-hours.

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Ar Lta rr oues l'rt si Houts ooc AHA L.cof' Sxnc de VitorarD in Ofs t Artcw A wO Col cav e n re 4 &

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REM 7ELING OPERATIONS l

COOLANT CIRCU1ATION LIMITING CONDITION FOR OPERATION 3.9.8.1 At least one residual heat removal loop shall be in operation.

l APPLICARILITY:-

MODE 6.

k ACTION:

a.

With less than one residual heat removal loop in operation except lr as provided in b. below, suspend all operations involving an L

increase in the reactor decay heat load or a reduction in boron concentration of_the Reactor Coolant System.

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

The residual heat removal loop may be removed from operation for up to I hour per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period during the performance of CORE t

ALTERATIONS in the vicinity of the reactor pressure vessel hot i

legs.

c.

The provisions of Specification 3.0.3 are not applicable.

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o SURVEILIANCE REQUIREMETS 4.9.8.1 At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months one RHR loop shall be verified in operation and circulating coolant at a flow rate of:

a.

greater than or equal to 1000 gpm, and b.

sufficient to maintain the RCS temperature at less than or equal to 140 F.

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SALEM UNIT 1 3/4 98 Amendment No.

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3/4.9.8 RESIDUAL MEAT REMOVAL COOLANT CIRCULATION l

ALL WATER LEVELS LIMITING CONDITION IVR OPERATION 1

3.9.8.1 At least one residual heat removal loop shall be in operation.

l-APPLICABILITY:

MODE 6.

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i ACTION:

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a.

With less than one residual heat removal loop in operation, except as provided in b. below, suspend all operations involving an increase in the reactor decay heat load or a

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reduction in boron concentration of the Reactor Coolant L

System.

Close all containment penetrations providing direct j

access from the containment atmosphere to the outside i

atmosphere within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

.b.

The residual heat removal loop may be removed from operation i

for up to I hour per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period during the performance of j

l CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs.

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c.

The provisions of Specification 3.0.3 are not applicable, j

SURVEILLANCE REQUIREMENTS

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y 4.9.8.1 At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months one RHR loop shall be verified in operation and circulating coolant at a flow rate of:

a.

greater than or equal to 1000 gpm, and i

b, sufficient to maintain the RCS temperature at less than or equal to 140 F.

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SALEM.- UNIT 2 3/4 98 1

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ATTACHMENT 4 I

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v; 3/4.1 REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1 BORATION CONTROL 3/4.1.1.1 and 3/4.1.1.2 SHUTDOWN MARGIN A sufficient SHUT 00h'N MARGIN ensures that 1) the reactor can be.

made sub:ritical from all operating conditions, 2) the reactivity trsnsients associated with postulated accident c nditions are centro 11able within acceptable limits, and 3) the rea:::r will be maintained sufficiently suberitical to preclude inadvertent criti:ality in the shutdown condition.

SHUTDOWN HARGIN requirements vary throughout core life as a function of fuel depletien, RCS bcron concentration, and RCS T The most restricti.ve concition occurs a: ECL, witn T atno!E!: ope'ra ting temperature, and is associated witn a pestu}$,ted :ttaam line break a::ide'nt and resulting un:0ntrolled RCS 00:1down.

In tne ar.alysis of this Lccicert, a minimum SHUTCOWN MARGIN of 1.5", ak/k is initially recuired to c ntrol +

the reactivity transient.

A::erdingly, tne SHUTDCWN MAR 31N recuirerent is based upon this limiting condition and is consistent with FSAR safety analysis assumptiens. With Tav; 1 200'F, the reactivity transients resulting from a postulated steam line break cooldevn are minimal and a 1* ak/k shutdown margin provides adequate protecti:n.

' % 1.1.3 3CRON DILUTION

. A minimum ate of at least 3000 3FM ;r:vides a:aq,uata mtPTTi[~

prevents stratificat ensures that reactivit Jvbarget will :e d

gradual during boron concent it?:n reductia -4n'the Reacter C:clant System. A flow rate of at least 3 P will circulate an' equivalent Reactor Coolant System volume-of'12,612 cu ic-Leet in approximately 30 minutes.

The rjactivify change rate associated D t Qoron reductions will therefor,e be within the capability for operator recogn tion and

<ontrol.

3/4.1.1.4 MODERATOR TEMPERATURE COEFFICIENT (MTC)

The limitations on MTC are provided to ensure that the value of this coefficient remains within the limiting condition assumed in the i

accident and transient analyses.

SALEM - UNIT 1 B 3/4 1-1 Amendment No.16

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REMELING OPERM BASES' l

3/4.9.6 MANIPUIATOR CRANE l

The OPERABILITY requirements for the manipulator cranes ensure that

1) manipulator cranas will be used for movement of control rods and fuel assemblies, 2) each crane has sufficient load capacity to lift a control rod or fuel assembly, and 3) the core internals and pressure vessel are protected from excessive lif ting force in the event t'aey are inadvertently engaged during lifting operations, ij

?/4.9.7 CRANE TRAVEL - SPENT WEL STORAGE BUILDING j

t The restriction on movement of loads in excess of the nominal wei ht 5

of a fuel and control rod assembly and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release will be limited to that contained in a i

sfngle fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the accident analyses, j

J/4.9.8 RESIDUAL HEAT REMOVAL AND COOIANT CT.RCU1ATION The requirements that at least one residual he.at removal loop be in operation ensures that (1) sufficient cooling capacity is available to l

remove decay heat and maintain the water in the reactor pressure vessel below 140'F as required during the REFUELING MODE, and (2) sufficient I

coolant circulation is maintained through the reactor core to minimize the l

effects of a boron dilution incident and prevent boron stratification.l A j

minimum flow rate of 1000 gpm is requ Eelil. AddItiona171ow limitations are specified in plant procedures, with the design basis documented in the Sales UfSAR. These flow limitations address the concerns related to vortexing and

.DO air entrapment in the Residual Heat Removal system, and provide operational l

8 flexibility by adjusting _the flow limitations based on time after shutdown.

The requirement to have two RHR loops OPERABLE when there is less than 23 feet of water above the reactor vessel flange ensures that a single failure of the operating RHR loop will not result in a complete loss of residual heat removal i

capability. The provisions of Sections 3.4.1.4 and 3.9.8.2 [ paragraph (b) of footnote (*)) which permit one service water header to be out of service, are

. based on the following:

1.

The period of time during which plant operations rely upon the l

provisions of this footnote shall be limited to a cumulative 45 days for any single outage, and

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2.

The Gas Turbine shall be operable, as a backup to the dieral I

generators, in the event of a loss of offsite power, to supply the applicable loads. The basis for OPERABILITY is one successful startup of the Gas Turbine no more than 14 days prior to the beginning of the Unit outage.

With the reactor vessel head removed and 23 feet of water above the l

reactor pressure vessel flange, a large heat sink is available for core cooling. Thus, in the event of a failure of the operating RHR Icop, adequate time is provided to initiate emergency procedures to cool the core.

SALEM. UNIT 1 B 3/4 9-2 Amendment No, i

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i REFUELING OPERATIONS

' BASES 3/4.93 MANIPU1ATOR CPANE j

The OPERABILITY requirements for the manipulator cranas ensure that: 1)

)

manipulator cranes will be used for movement of control rods and fuel i

assemblies, 2) each crane has sufficient load capacity to lift a control rod i

or fuel assembly, and 3) the core internals and pressure vessel are protected i

from excessive. lifting force in the event they are inadvertently engaged during lifting operations.

3/4.9.7 CRANE TRAVEL - SPENT ITEL STORACE BUILDING i

The restriction on movement of loads in excess of the nominal weight of a f

fuel e d control rod assembly and associated handling tool over other fuel

. assemblies in the storage pool easures that in the event this load is dropped (1) the activity release will be limited to that contained in a single fuel assembly.,and (2) any possible distortion of fuel in the storage racks will not result in a critical array This assumption is consistent with the i

activity release assumed in the accident analysee.

3/4.9.8 REEIDUAL HEAT REMOVAL AND COOLANT CIRCU1ATION f

The requirements that ac least one residual heat removal loop 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 l

as required during the REFUELING MODE, and (2) sufficient ecolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and prevent boron __ stratification _.J A minimum flow rate of 1000 gpm is required. Additional flow limitations are specified in plant procedures, with the design basis documen:ed in the Salem UFSAR. These flow j

limitations address the concerns related to vortexing and air entrapment in l

gg the Residual Heat Removal system, and provide operational flexibility by adjusting the flow limitations _ based on time after shutdown. l The requirement to have two RHR loops OPERABLE when there is less than 23 fee't of water above the reactor vessel flange ensures that a single failure of the operating RHR loop will not result in a ccapleto loss of residual heat removal capability, y

The provisions of Sections 3.4.1.4 and 3.9.8.2 [ paragraph (b) of footnote (*))

I which permit one service water header to be out of service, are based on the following:

l 1.

The period of time during which plant operations rely upon the I

provisions of this footnote shall be limited to a cumulative 45 i

days for any single outage, and i

2.

The Gas Turbine shall be operable, as a backup to the diesel generators, in the event of a loss of offsite power, to supply the applicable loads. The basis for OPERABILITY is one l-successful startup of the Gas Turbine no more than 14 days prior I

to the beginning of the Unit outage.

With the reactor vessel head removed and 23 feet of water above the reactor pressure vessel flange, a Isrge heat sink is available for core

(

cooling. Thus, in the event of a failure of the operating RHR loop, adequate time is provided to initiate emergency procedures to cool the core.

SALEM UNIT 2 B 3/4 9-2 Amendment No.

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3/4.1 REACTIVITY CONTROL SYSTEMS 1

BASES l

3/4.1.1 RORATION CONTRC),

j 3/4.1.1.1 and 3/4.1.1. 2 SHUTDOWN MARGIN j

A sufficient SHUTDOWN KARGIN ensures that 1) the reactor can be made L

suberitical from all operating conditions, 2) the reactivity transients associated with postulated accident conditions are controllable within acceptable limits, and 3) the reactor will be saintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition.

SHUTDOVN KARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS Tavg.

The most restrictive condition occurs at EOL, with Tavg at no load operating temperature, and is associated with a postulated steam line break accident and resulting uncontrolled RCS cooldown.

In the analysis of this accident.

a minimum SKUTDOWN MARGIN of 1.6% _k/k is initially required to control the reactivity transient. Accordingly, the SHUTDOVN KARGIN requirement is

' based upon this limiting condition and is consistent with FSAR safety

]

analysis assumptions. With Tavg_ 200'F, the reactivity transients resulting from a postulated steam line break cooldown are minimal and a 16 ik/k shutdown margin provides adequate protection, j

'3/4.1.1.4 MODERATOR TEMPERATURE COEFFICIENT (MTC) i The limitations on MTC are provided to ensure that the value of this i

coefficient remains within the limiting condition assumed in the accident and transient analyses.

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l SALEN UNIT 1 B 3/4 1 1 Amendesnt No. 16

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REWELING OPERIf,U)Li

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SASES s

f 3/4.9'6 MANIPUIATOR CRANE The OPERABILITY requirements for the manipulator cranes ensure that:

1) manipulator cranes will be used for movement of control rods and fuel t

assemblies 2) each crane has sufficient load capacity to lift a control l

l rod or fuel assembly, and 3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently l

engaged during lifting oporations.

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3/4.9.7 CRANE TRAVEL - SPENT PUEL STORAGE BUILDING l

l p

The restriction on movement of loads in excess of the nominal weight of a fuel and control rod assembly and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is j

dropped (1) the activity release will be limited to that contained in a j

single fuel assembly, and (2) any possible distortion of fuel in the j

storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the accident analyses.

[

3 /4. 9. 8 RESIDUAL HEAT REMOVAL AND COO 1 ANT CIRCUI ATION l

The requirementa that at least one residual heat removal loop be in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor prassure 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. A l

l minimum flow rate of 1000 gpm is required.

Additional flow limitations are specified in plant procedures, with the design basis documented in the Salem e

UFSAR. These flow limitations address the concerns related to vortexing and

.a r entrapment in t e Residual Heat Removal system, and provide operational i

i h

r flexibility by adjusting the flow limitations based on time after shutdown.

l f

The requirement to have two RHR loops OPERABLE when there is less than 23 feet i

of water above the reactor vessel flange ensures that a single failure of the j

operating RHR loop will not result in a complete loss of residual heat removal capability. The provisions of Sections 3.4.1.4 and 3.9.8.2 [ paragraph (b) of

{

footnote (*)) which permit one service water header to be out of service, are i

)

based on the following:

1.

The period of time during which plant operations rely upon the i

provisions of this footnote shall be limited to a cumulative 45 days L

for any single outage, and I

2.

The Gas Turbine shall be operable, as a backup to the diesel generators, in the event of a loss of offsite power, to supply the t

applicable loads. The basis for OPERABILITY is one successful startup i

of the Cas Turbine no more than 14 days prior to the beginning of the Unit outage.

i With the reactor vessel head removed and 23 feet of water above the i

reactor pressure vessel flange, a large heat sink is available for core cooling. Thus, in the event of a failure of the operating RHR loop, adequate time is provided to initiate emergency procedures to cool the

)

core.

l SALEM - UNIT 1 B 3/4 9 2 Amendment No, l

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REFUELING OPERATIONS RASES' 3 /4. 9. 6 MANIPUIATOR CRANE' The OPERABILITY requirements for the manipulator cranes ensure that: 1)

F manipuistor cranes will be used for movement of control rods and fuel assemblies, 2) each crane has sufficient load capacity to lift a control rod or fuel assembly,'and 3) the core internals and pressure vessel are protected from excessive lifting. force'in the event they are inadvertently engaged during lifting operations.

+

3/4.9.7 CRANE TRAVEL - SPENT PUEL STORAGE BUILDING The restriction on movement of loads in excess of the nominal weight of a fuel and control rod assembly and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage reeks will not result in a critical array. This assumption is consistent with the activity release assumed in the accident analyses.

3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirements that at least one residual heat removal loop 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 usintained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification. A minimum flow rate of 1000 gpm is required. Additional flow limitations are specified in plant procedures, with the design basis documented in the Salem UFSAR. These flow limitations address the concerns related to vortexing and air entrapment in the Residual Heat Removal system, and provide operational flexibility by adjusting the flow limitations based on time af ter shutdown.

The requirement to have two RHR loops OPERABLE when there is less than 23 feet of water above the reactor vessel flange ensures that a single failure of the operating RHR loep will not result in a complete loss of residual heat removal capability.

The provisions.of Sections 3.4.1.4 and 3.9.8.2 [ paragraph (b) of footnote (*))

which permit one service water header to be out of service, are based on the following:

1.

The period of time during which plant operations rely upon the provisions of this footnote shall be limited to a cumulative 45 days for any single outage, and 2.

The Gas Turbine shall be operable, as a backup to the diesel generators, in the event of a loss of offsite power, to supply the applicable loads.

The basis for OPERABILITY is one successful startup of the Gas Turbine no more than 14 days prior to the begintaing of the Unit outage.

With the reactor vessel head removed and 23 feet of water above the reactor pressure vessel flange, a large heat sink is available for core caoling. Thus, in the event of a failure of the operating RHR loop, adequate time is provided to initiate emergency procedures to cool the core.

SALEM - UNIT 2 B 3/4 9 2 Amendment No.

-.

ML19327B786

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