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Page 1: t |4 ' r . , . . . . Substitution and Deletion-of Proposed ... · g ' t - ' f A t 4 |4 ' r . , .. . . ' Substitution and Deletion-of Proposed Pages PROPOSED PAGE-REPLACEWITHNEWPAGE(ATTACHED).454

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4 . Fort St. Vrain #1' > '

'^f :.) Technical' Specifications ,

7 Amendment No. '

N. ' / Page 4.7-6 i

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l' SPECIFICATION LCO 4.7.3 FUEL STORAGE WELLS

.

|-LIMITING CONDITION FOR OPERATION i

i

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

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

| b. 'Both cooling water coils OPERABLE with at least one coil in.| operation, and.the outlet cooling water temperature of each coil| operating shall be 150 degrees F or .less, or j

| c. One cool.ing water coil operating with the outlet cooling water' t

| temperature ISO degrees F or less, and the fuel storage well ;

| emergency booster fan OPERABLE and capable of moving a minimum>

n | total air flow of 9000 cfm -through the fuel storage vaults. '{,

.| d.--No- IRRADIATED PJEL located in the central column of a fuel 9'

| storage well. .[

.| 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| required - conditions within 24 hours, or perform one of the| following within'the next 24 hours:

I a. Transfer IRRADIATED FUEL to a. storage well or wells for1 'which the required conditions are met, or

| b. Establish backup cooling to the affected fuel storage-wells,|~. or

| c. Perform an engineering evaluation to confirm that theI hottest fuel element surface temperature will.not exceed 750| degrees F.

|:-ASSOCIATED SURVEILLANCE REQUIREMENT: SR 5.7.2

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'f Fort St. Vrain #1-',

.' Technical Specificati nsj; .

W Amendment No.'

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Y :. Page 4.7-7.,

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J| BASIS FOR SPECIFICATION LCO 4.7.3'

. -

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;-| The storage well cooling water system is designed.with two 100%*

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

-

|-The~ accident conditions described in the FSAR postulate the totaln | 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 :| the normal, ventilation air flow to cool the well by convection on the t

| external surface. The increase in air flow is supplied by the fuel '

.

' -|. storage well emergency booster fan. This specification _is _ based on-| thet analysis in FSAR Section.14.6.3.2 which uses the conservative !

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

,

| wells, thus adequately protecting the affected storage well and fuel 4r

l within it from damaging temperatures. (There are three fuel storage-| wells in each of the three fuel storage. vaults). |

4| IRRADIATED FilEL elements are not stored in the central column of a| 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| 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 ;

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

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

-| temperature from reaching 750 degrees _F, thus obviating any-l significant oxidation in the unlikely combined events of air| inleakage and loss of normal cooling.

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l' J - m Technical Specifications _3

U )t3 * [" Amendment No.'

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p ST /.- Page 4.7-9 i

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|LSPECIFICATION LCO 4.7.5 INSTRUMENTATION ~l

- . .;: X -| LIMITING CONDITION FOR OPERATION __ !

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W> -| The reactivity .of the core shall.be continuously monitored by at'', ,

.| least,two startup channel neutron flux monitors in accordance with: 3F -|-LCO.4.4.1;(Tables 4.4-1 and 4.4-4).'

-

~| APPLICABILITY:- REFUELING !-

,

| 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: _.

, ,. |- resulting in positive reactivity changes, or movement of- |

v3 :L| IRRADIATED FUEL in the PCRV. 1

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

.| ir, operable cr not-operatirg: '

39 .

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| _, 1. Immediately suspend all ' operations- involving CORE. l

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

|L - reactivivy changes, or movetnent of IRRADIATED Fl!EL,- ,-~*

1

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

.|: remetely operated mechanism from the PCRV, ;

|~ 3. Close the ' reactor .isulation valve or opening through;| ths;PCRV as soon as practicable,--and '

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il 4. Within 12 hours evaluate the SHUTDOWN MARGIN per ';.

|- SR:4.1.4.

| ASSOCIATED SURVEILLANCE REQUIREMENT: SR 5.7.5- 4

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p.; - -k Fort St. Vrain"#1 .

Technical Specifications- i,

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a6- Amendment No.e .1 Page 4.7-10;-

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| BASIS FOR SPECIFICATION LCO;4.7.5| ts- - ;

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

.|Lthat; redundant' monitoring capability is available to detect changes .i,.

b | sin the . reactivity condition of the core. This-specification also '

L | applies to reactor internal maintenance that does not' involve a CORE. 1

.| ALTERATION, such as a helium circulator'changeout or modifications or- ;jP

L | repair of L the . primary . coolant purification systems. For this .),

7

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

; l. flux monitors, provided the other. ACTION requirements are met'. j

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n, l.The.JACTION statement ' ensures that activities that could affectLthe-| reactivity condition ofithe core are. suspended whenever neutron. flux' '

| monitoring capabilities are degraded. [L.u s ,

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m ''n - :|: SPECIFICATION SR 5.7.5 INSTRUMENTATION [.1- !,

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l'a.. Once per 24 hours, 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 ,, |- by: performance of a CHANNEL TEST,-and i,

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'' f. li-Thefsurveillance;requirementsensurethatthe'neutronfluxmonitors- i77 f LL_areccapable of-oetecting-. changes in_ reactor conditions in time to Mr?;: .lipermit- corrective actions if reouired. TheseLare in addition to the- 1', :| calibration requirements ef.IR 5.4.1. ;,

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