ML19332F356
| ML19332F356 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 12/04/1989 |
| From: | PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| Shared Package | |
| ML19332F352 | List: |
| References | |
| NUDOCS 8912140311 | |
| Download: ML19332F356 (6) | |
Text
g t - ' f A
+
l4 '
t 4
r.,.
Substitution and Deletion-of Proposed Pages PROPOSED PAGE-REPLACEWITHNEWPAGE(ATTACHED).
454 - 7b Use Existing Technical Specification Page 4.4 -.9 Use Existing Technical Specification Page
[!:
- 4.4~- 13~
Use Existing Technical Specification-Page
-4.7:- 6 4.7 - 6
- 4.7 - 7 4.7 - 7
[.
4.7 - 9 4.7 - 9
~4.7 - 10 4.7 - 10 5.7 - 8 5.7 - 8 i;
11,
i u
Q;;jl, g-n.#. <
e 6
f l
i
.i i
3 i
i 4
h'.
L L-8912140311 891204
?
.PDR ADOCK 05000267 4
. P.
PDC a--
., t "#
xa.
,_+-..R........._,_....-,.....,
4 Fort St. Vrain #1' >
'^
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
y
'f Fort St. Vrain #1-Technical Specificati ns j;
W Amendment No.
Y Page 4.7-7.
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 l wells, thus adequately protecting the affected storage well and fuel 4
r l within it from damaging temperatures.
(There are three fuel storage
-l wells in each of the three fuel storage. vaults).
l 4
l IRRADIATED FilEL elements are not stored in the central column of a 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.
h o
i
l:B l' J m
Technical Specifications _
3 U )t3
["
Amendment No.
p ST
/.-
Page 4.7-9 i
D lLSPECIFICATION LCO 4.7.5 INSTRUMENTATION ~
l
- X
-l LIMITING CONDITION FOR OPERATION __
[:(
W>
-l The reactivity.of the core shall.be continuously monitored by at'
.l least,two startup channel neutron flux monitors in accordance with:
3 F
-l-LCO.4.4.1;(Tables 4.4-1 and 4.4-4).
~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.
.l ir, operable cr not-operatirg:
39
- Ti' :1 l _,
1.
Immediately suspend all ' operations-involving CORE.
l l.
ALTERATIONS, any evolution-resu'iting in positive' y
lL
- reactivivy changes, or movetnent of IRRADIATED Fl!EL,-
~*
1
+
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
_1 n
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
t:
l l
4 b
i h
7 9
!U q
~~ it i jj
"")
~-
^
p.; - -
k Fort St. Vrain"#1 Technical Specifications-i "o
a6-Amendment No.
e.1 Page 4.7-10; I
l n
r 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
.l ALTERATION, such as a helium circulator'changeout or modifications or-
- j P
L l repair of L the. primary. coolant purification systems.
For this
.)
7 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.
[
L.u s
i I
k t
t a
o
-gj E
'h
.t-
.i
.5 I
J
?
b t
"I l
r
)
t 2.-
u.
OE !,
O'
' Fort St.'.Vrain'#1
?!,qc.
Technical' Specifications J>
sr Amendment No.
m j F:n oj 3 :
Page 5.7-8 t
e l'I lt -
-}
- i i
m n -
- l: SPECIFICATION SR 5.7.5 INSTRUMENTATION
[
.1-t
- .t
-l-Each startup channel' neutron flux; monitor; shall be demonstrated l OPERABLE whenever LCO 4.7.5 is applicable:
i
-x s
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
l E
' l / b..
Within-24~ hours prior to the initial start of, CORE. ALTERATIONS, I,,
l-by: performance of a CHANNEL TEST,-and i
k
' l ' ci..Once per 7 days ~, by performance of a CHANNEL TEST;
[
w k
g
<l: ASSOCIATED LC0i LCO 4.7.5 b
j g
e1
[c; l EA_S_IS FOR g _5;7J _ -
_gm __ _._
RF ll- %.
f.
li-Thefsurveillance;requirementsensurethatthe'neutronfluxmonitors-i 77 f LL_areccapable of-oetecting-. changes in_ reactor conditions in time to Mr
?;:
.lipermit-corrective actions if reouired. TheseLare in addition to the-1
- l calibration requirements ef.IR 5.4.1.
k D?
~$
h t
F P
. I t'<
1 r
4
- 7 h*l f
-r a
II i o
?
<4 )
t
.k :.h. :p i
'(
b.
.-