ML19332F356

Proposed Tech Specs Re Limiting Condition for Operations 4.7.3, Fuel Storage Wells & 4.7.5, Instrumentation.

ML19332F356
Person / Time
Site:	Fort Saint Vrain
Issue date:	12/04/1989
From:	PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML19332F352	List: ML19332F351 ML19332F353 ML19332F356
References
NUDOCS 8912140311
Download: ML19332F356 (6)

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f  :.) Technical' Specifications ,

7 Amendment No.

N. ' / Page 4.7-6 i

l' SPECIFICATION LCO 4.7.3 FUEL STORAGE WELLS l-LIMITING CONDITION FOR OPERATION i i

-l Each fuel storage well containing IRRADIATED FUEL shall have:  ;

. l a. A _ helium ' atmosphere maintained at approximately atmospheric l pressure (< I psig) or slightly below, and  :

l b. 'Both cooling water coils OPERABLE with at least one coil in.

l operation, and.the outlet cooling water temperature of each coil l operating shall be 150 degrees F or .less, or j l c. One cool.ing water coil operating with the outlet cooling water' t l temperature ISO degrees F or less, and the fuel storage well  ;

l emergency booster fan OPERABLE and capable of moving a minimum n l total air flow of 9000 cfm -through the fuel storage vaults. '{

.l d.--No- IRRADIATED PJEL located in the central column of a fuel 9 l storage well. .[

, .l APPLICABILITY:- When IRRADIATED-FUEL is stored in the fuel- storage d

l' well.

,1 ACTION: With less than the above required conditions satisfied, I within I hour initiate corrective action to re-establish the l required - conditions within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or perform one of the l following within'the next 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:

I a. Transfer IRRADIATED FUEL to a. storage well or wells for 1 'which the required conditions are met, or l b. Establish backup cooling to the affected fuel storage-wells, l~. or l c. Perform an engineering evaluation to confirm that the I hottest fuel element surface temperature will.not exceed 750 l degrees F.

l:-ASSOCIATED SURVEILLANCE REQUIREMENT: SR 5.7.2 h

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Technical Specificati ns .

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Jl BASIS FOR SPECIFICATION LCO 4.7.3 P

-l The storage well cooling water system is designed.with two 100%

l capability cooling coils supplied from independent. water sources' l:(FSAR'Section 9.1.2).-

l l-The~ accident conditions described in the FSAR postulate the total n l loss of cooling water to one of the nine fuel storage wells. If .thi s'. ,

l were to occur, adequate cooling could be achieved by an increase in  :

l the normal, ventilation air flow to cool the well by convection on the t l external surface. The increase in air flow is supplied by the fuel

-l. storage well emergency booster fan. This specification _is _ based on

-l thet analysis in FSAR Section.14.6.3.2 which uses the conservative  !

l assumption that a' total flow of 9000 cfm would be drawn (equally 1 l divided)~'through all three vault compartments'of the fuel storage ,

r l wells, thus adequately protecting the affected storage well and fuel 4 l within it from damaging temperatures. (There are three fuel storage

-l wells in each of the three fuel storage. vaults). l l IRRADIATED FilEL elements are not stored in the central column of a 4 l fuel stcrage well _because they cuinot br edeat.ately cooled in that  ;

, l' location (FSAR "Section 9.1.2.2.2).  ;

1 To pr m nt significant oxidation sf the 3RRADIATED FUEL, the fuel l str, rage wells are designed to mair;tair the IRRADIATED FUEL cool' and [

l'under a nu.irially dry atmosphere of heliam. An outlet tempwature of  ;

l;150 degrees or less from a single cooling coil ensures the hottest 1 j IRRADIATED FUtX element surface temperatures will be maintained below l 750 degrees F, proventing any sigr.ificant. graphite oxidation in; the l event of air inleakaga into the storage well. The helium storage j system provides purified helium for this~ service, giving sufficient l-protection against.a moist atmosphere.

l The ACTION statements provide for corrective actions wi_ thin'an l adequate time to prevent-the hottest stored fuel element surface

-l temperature from reaching 750 degrees _F, thus obviating any

-l significant oxidation in the unlikely combined events of air l inleakage and loss of normal cooling.

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U )t3 Amendment No. ,

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lLSPECIFICATION LCO 4.7.5 INSTRUMENTATION ~

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. :X -l LIMITING CONDITION FOR OPERATION __  !

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, -l The reactivity .of the core shall.be continuously monitored by at'

.l least,two startup channel neutron flux monitors in accordance with: 3

-l-LCO.4.4.1;(Tables 4.4-1 and 4.4-4).

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~l APPLICABILITY:- REFUELING  !

l ACTION:-  !

a. With :one, of the _above required neutron flux- monitors'

[' inoperable,.,or- not operating,. immediately. Suspend all:

operations- i nvol vi ng .- CORE ALTERATIONS, any; evolution: _.

. l- resulting in positive reactivity changes, or movement of- l v3 :L l IRRADIATED FUEL in the PCRV. 1 ns .

.l b. 'Vith. both of -the above required neutron flux monitors.  ;

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.l ir, operable cr not-operatirg: '

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l _, 1. Immediately suspend all ' operations- involving CORE. l y~*

, l. ALTERATIONS, any evolution- resu'iting in positive'  ;

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- reactivivy changes, or movetnent of IRRADIATED Fl!EL,- ,-

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Lj ' =2. Retract the: fuel: handling- mechanism or any- other .

.l: remetely operated mechanism from the PCRV,  ;

l~ 3. Close the ' reactor .isulation valve or opening through -

l ths;PCRV as soon as practicable,--and g!

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n _1 il 4. Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> evaluate the SHUTDOWN MARGIN per ';

l- SR:4.1.4.

- l ASSOCIATED SURVEILLANCE REQUIREMENT: SR 5.7.5 4

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1 l BASIS FOR SPECIFICATION LCO;4.7.5l t s-  ;

'l The OPERABILITY of'the'startup channel neutron flux monitors ensures:  ;

,. .lLthat; redundant' monitoring capability is available to detect changes .i' b l sin the . reactivity condition of the core. This-specification also L l applies to reactor internal maintenance that does not' involve a CORE. 1 P

.l ALTERATION, such as a helium circulator'changeout or modifications or- ;j L , l repair of L the . primary . coolant purification systems.

7 For this .)

l l maintenance. where: no changes are lbeing. made to core' reactivity, i l activities are parmitted in the event of inoperable startup channel 1

l. flux monitors, provided the other. ACTION requirements are met'. j V T n, l.The.JACTION statement ' ensures that activities that could affectLthe-l reactivity condition ofithe core are. suspended whenever neutron. flux '

l monitoring capabilities are degraded. [

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-l-Each startup channel' neutron flux; monitor; shall be demonstrated s

-x l OPERABLE whenever LCO 4.7.5 is applicable: i l'a.. Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, by performance of aLCHANNEL CHECK, 4

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E ' l / b. . Within- 24~ hours prior to the initial start of, CORE. ALTERATIONS, I ,, .

l- by: performance of a CHANNEL TEST,-and i

' l ' ci. .Once per 7 days ~, by performance of a CHANNEL TEST; ,

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f. li-Thefsurveillance;requirementsensurethatthe'neutronfluxmonitors-LL_areccapable of-oetecting-. changes in_ reactor conditions in time to i

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?;: .lipermit- corrective actions if reouired. TheseLare in addition to the- 1

', , :l calibration requirements ef.IR 5.4.1.  ;

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