ML20058G823

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Proposed Tech Specs Re Operations of RCS & Shutdown Cooling Sys During Reduced Inventory Conditions
ML20058G823
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 11/05/1990
From:
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20058G821 List:
References
NUDOCS 9011140014
Download: ML20058G823 (8)
v • d • e


Text

1 A1TACHMENT I UNIT I REVISED -

TECHNICAL SPECIFICATION

-AND BASES PAGES 3/49 B - 3/4 9-2 i 9011140014 901105 PDR ADOCK 05000317 p PDC i

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11 i Rs~UELING CpERATIONS -

L -s p, 5HUTDOWN COOLING AND COCLANT C' ACULATION

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3.9.B.1 At leas: :ne shutd:wn :: ling ':00 shall be in :cera:icn.-

APPLICABILITY: MODE 5 et all reactor water levels. ,

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. a. Wi:n less tnan :ne snu:d:wn ::aling 100; in : pert:icn', sus:end _i all operations ir volving an increase in the reac :r deca.v".ea: l load or a reductien in coron concen:ratien of the Reacter' j Coolant system anc, specifically .

tne cnarging pumps snall be ,

de-energ' ec and :he charging fl:w paths shall be cl; sed. Close  !

all containment ;ene:ra:icns pr:viding direct ac:ess fr:m :ne c.ontainment atmospnere to the outside atmosphere within 4' hours.

The shutdown coolir.g pumps may .be. de-er,ergi:ed. during the. time.

intervals required for local leak rate testing of c:ntainment l'

.j penetration number 41 pursuant to the requirements of specifica-tion 4.6.1.2.d and/or to permit maintenance en valves located  !

in the con, mon shutdown cooling suction line, pr:vided -(l) no -

I coera-ions are :ermitted which could cause dilution of the reactor coolant system.coron concentration and , specifically, i

ne charging pum:s snall be de-energi:ed and the charging ficw paths shall be closec, (2) all CORE ALTERATIONS-are suspended, l (3) ai'. centainment :ene:ra: ions :roviding direc: ac:sss fr:m the :entainmen; a:m0s;nere to the outside atmosphere are main-  ;

tained closed , and (4) :he bater level abcve the top of :ne irradiated fuel is greater than 23 feet, r

j  :. The pr:visi:ns of 5:Scification 3.0.3 are no: a;ciicable.

lSURVEILLANCEREC91REMENT5

-l 4.9.8.1 A sne:down cooling loco shall be -determined to be in coera:1cn anc circulating reactor coolantut a flow ra te of > 3000 gpm -Ja; leas: once per li a hours. A g 1

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  • The sh'utdown cooling loop may be removed from operation for.up to 'l hour 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 vicinity of the reactor pressure vessel hot legs.

_ i f**> 1500 gpm when the Reactor Coolant System is dra~ined 'to'a level below thi]F Lmidplane of the hot leg.; w . -

G CALVERT CLIFFS - UNIT 1 3/4 9-8 Amendm an: No. 33, 55, 59 i

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REFUEL.'ING Op! RATIONS BASE 3 "

>3/4.9.6 REFUELING MACHINE OPERABILITY The OPERAS!LITY requirements for the refueling machine ensure that:

(1) the refueling machine will be ueed for movement of CEAs and fuel assemolies, (2) the refueling machine has sufficient load capacity to itft a CEA or fuel assembly, and (3) the core internals and pressure vessel are protected from excessive lifting for:e in the event they are inadvertently engaged. curing lifting operations.

3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILOING The restriction on movement of loads in excess of the nominal weight of a fuel assembly and CEA 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 assemoly, and (2) any possible distertion, 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 anal/ses.

3/a.9.8 COOLANT CIRCULATION The requirement that at least one shutdown cooling loop be in operation ensures that (1) sufficient cooling capacity is availacle 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 boren stratification.

The requiremen to have two sr.utcown coolieg loops OPERABLE when there is less than 23 feet of water above the core ensures that a single failure of I the operating shutcown cooling loop will not result in a c:mplete loss of decay 1 heat removal capability. With the reactor-vessel head removec ?.nd 23 feet of .'

l water acove the core, a large heat sink is available for core cocling, thus i in the event of a failure of the operating shutdown ecoling loup, adequate time is orovided to initiate emergency procedures to ceci the core.

ENsfRT' PneM Nur PAGE ~f-3/4.9.9 CONTAINMENT PURGE VALVE ISOLAtt0N SYSTEM The OPERA 3!LITY of this system ensures that the
entainment purge valves will se autcmati:all / isolated upon detection :f hign radis: ion levels within the con air. ment. *he OPERABILITY of this system is required' to restrict One

. release of radioective . material from the containment atmosphere to the environment.

1 l CALVERT CLIFFS - UNIT 1 Amendment No. ::: -

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i INSERT for E ASES 3/4.9.8, " COOLANT CIRCULATION" In MODE 6, shutdown cooling flow must provide sufficient heat removal to match core (

decay heat generation rates and maintain the core exit temperature within the MODE-limit. Thus, as decay heat production is reduced with time, shutdown cooling flow may be proportionally reduced. Pursuant to NRC Generic Letter 88-17, flow reduction - is

i necessary for operations near the mid-point'. of the hot . leg! piping to prevent, vortex i formation at the shutdown cooling suction nozzle. Prevention of vortex formation i reduces the potential for a loss .of shutdown cooling ' due to, air binding of the low -

pressure safety injection (LPSI) pump (s) operating- to provide : shutdown'. cooling flow.E 'r In accordance with the recommendations of NRC Generic' Letter _ 88-04, " Safety Related Pump Loss," a minimum flowrate requirement of 1500 gpm is administratively imposed.

This protects the vendor-recommended minimum continuous duty flowrate of 1340 spm for-the LPSI pumps, 4

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4 ATTACHMENT 2 l

.t UNIT 2 REVISED TECHNICAL SPECIFICATION i AND BASES PAGES 1

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l REFUEL!NG0?CNS ERAT: I 1

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. LIMITING CON 0!?!ON 20P. OPEp.? TION - -

+2 3.9.3.1 At least :ne shutdewn :: cling 1:cp shall be in Operati:n;'

APPLICABILITY: MODE 5 a: all reacto'r water levels.

ACTION:

a. 4i:n '.ess : nan :ne snu:dewn :: cling 1:co- in :pera:'.:n', sus; enc all operati:ns inv61ving an increase in the reac :r decay-heat load or a reduction in boron concentration of the Reactor Coolant System and, specifically, the charging pumps shall be de-energized and the~ charging flew paths shall be closed. Close all containment penetrations providing direct ac:sss fr:m 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 />.

The shutdown cooling pumps may be de-energi:ed' during the time intervals required f:r local leak rate testing of containment. -

penetration number 41 pursuant to the requirements of Specifica-tion 4.6.1.2.d and/or to permit maintenance on valves located in the common shu;down cooling suction line, provided (1) no coeracions are cermitted which cculd cause dilution of the reactor coolant systan boron- concentration and, specifically, the charging pumps shall be de-energized and the charging flow paths shall be closed. (2) all CORE ALTERATIONS are suspended, (3) all centainment penetrations providing dire:: ac:ess f em the ::ntainment atmos:here to the outside atmosphere are main- .

ained closed , anc (2) the water level above :ne .:p o- the irradiated fuel is greater than 23 feet. .
b. The provisions of Specification 3.0.3 are not appli:able. ,

SURVEILLANCE REOUIREMENTS l

t d.9.8.1 A shutdown cooling loot shall be determined to be in operation and circulating reactor coolantrat a flow rate of > 3000 apm" J at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, p,q[ .

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  • The s'hutdown coolin.g l.oop may be rem'oved from operation for up to I hour per

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l j S hour period during the performance of CORE ALTERATIONS' in the vicinity of the l reactor pressure vessel hot legs.

f**,> 1500 gpm when the Reactor Coolant System is' drained to a level 'below the;} '.

I mi d pl a n e o f th e ' ho t l eg . [g EJ CALVERT CLIFFS - Uhii 2 3/4 9-8 knendment No. 37. 3B, 41 a -

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_, REFUEL:NG OPERATIONS

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3ASES f '

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!. 3/a.9.6 RE:'JELING 'dACHINE CPERABILITY "." ' '

The OPERAS:LITY requirements for the refueling machine ensure that:

(1) :he refueling machine will be used for movement of CEAs and fuel assemblies, (2) the refueling macntne nas sufficient Icao capacity :o lift a CEA or fuel assembly, and (3) the core internals and pressure vessel are protected from

,, excessive lifting for:e in the event they are inadvertently engaged during

' { lif ing c:erations.  !

i

'3/a.9.7  :?.ANE !;A'/E'. - SPENT FUEL STORAGE EU:LDING The restriction on movement of loads in excess of the nominal weight of a fuel assembly and CEA 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 :he storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the accident analyses. -

3/a.9.3 COOLANT CIRCULATION The recuirement :nat at least one shutdown cooling 1000 be in operation ,

ensures tha (1) sufficient cooling capacity is availaole :c-remove decay heat and maintain the water in the reactor pressure vessel below 1406 F as required

during the REFUELING MODE, and (2) sufficient
colant :irculation is maintained j and
nrougn the reactor ::re to minimi:e the effe:ts of a bcron dilution incident prevent boren stratification.

3 The recuirement :: have two shutdown cooling loo:s OPERABLE wnen there I is less than 23 feet of wa:er above the core ensures :na: a single failure of I the operating shutdown :coling loop will not result in. a complete loss of decay l6, heat removal ca; ability. Witn the reactor vessel head removed and 22 feet of ,

water a:ove :he core, a large heat sink is available for core cooling, thus in the event of a failure of the operating shutdcwn coolir; loop, adequate ll& time is proviced to initiate emercency rocedures to cool the core.

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l !3/a.9.9 CONTAINMENT PURGE '/AL'/E ISOLATION SYSTEM l ll Tne CPERASILITY :f :nis system ensures tha: :he :entainment purge valves l,' wi'1 oe au::mati: ally is:la:ed upon dete:: ion of hign radia:icn levels within l the :entainment. The OPERASILITY of this sys;em is recuired to restri:: tne release of radioactive ma:arial from the containment a:mos;nere to the envircnment.

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' CAL'/ERT CLIFF 5 - UN!T 3 3 3/4 9-2 Amendment No , jj

INSERT for BASES 3/4.9.8, " COOLANT CIRCULATION"  :

In MODE 6, shutdown cooling flow must provide sufficient heat removal to match core decay heat generation rates and maintain the core exit temperature within the MODE

~

limit. Thus, as decay heat production is reduced with time, shutdown cooling flow may be proportionally reduced. Pursuant to NRC Generic . Letter .88-17, flow reduction -. is

~

necessary for operations near the mid-point of the hot leg piping to prevent vortex formation at the shutdown' cooling suction nozzle. Prevention of vortex formation reduces the potential for a loss of shutdown cooling due to air ~ binding of the low-  ;

pressure safety injection -(LPSI) pump (s) operating - to provide shutdown - cooling : flow.

In accordance with the recommendations of NRC Generic Letter 88-04,'" Safety'.Related i Pump Loss," a minimum flowrate requirement of 1500 spm is administratively imposed..

This protects the vendor-recommended minimum continuous duty flowrate of 1340 spm for ,

the LPSI pumps.  ;-

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