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{{#Wiki_filter:}} | {{#Wiki_filter:Fort St Vrain 11 Technical Specifications Arend=en: | ||
l Page 3.1-1 3.1 Rea::c Co re - Safe:v Limit | |||
====3.1.1 Apoli==== | |||
bili:v Applies to the li=iting cc Sinations of core ther al power and core heliu= flew rate. | |||
3.1.2 Obiective To maintain the in:eg 1:7 of the fuel particle coa:ings. | |||
3.1.3 Specifica:1on SL 3.1 - Rese:Or Core Saferv Li d: | |||
i The combina:icn of :he reac:cr core power-:0-ficw ratio and the 00:21 | |||
,i integrated operating tire a: the power-::-flew ratio during :he life: ire of e | |||
i any seg=en: shall no: exceed :he following 11=its. | |||
4 i | |||
3.1.3.1 Power-:c-? lev Ratio 3e:veen 1.17 and 2.3 The co=bina: ion of the reactor core pcwer-to-flew ra:ia and the :otal I | |||
integrated operating ti=e at this power-to-flow ratio during the lifetime of | |||
.I . | |||
I 8 | |||
any seg=en: shall no: exceed the 11:1: given in Figure 3.1-1. This safe:y 11=1: is exceeded when the cc binatica of operating parameters (;cuer, flew, and :i=e) lies above or :o the right of the line given in Figure 3.1-1. | |||
i 1 | |||
For :he purpose of obtaining the :otal eff ective in:egra:ed opera in:. | |||
:i=e for Figure 3.1-1, only ::ansients resulting in a power-:c-flow ratio abcVe the curve of Figure 3.1-2, at the appropriate core power level shall be used. | |||
8302100 570 | |||
Fort St. Vrain til | |||
, Technical Specifications A=end=en t Page 3.1-2 Fc pcwer-:c-flev ratics between 1.17 and 2.5, the opera:or shall | |||
, i==ediately reduce pcwer to 1cuer the power-:c-flow ratio :o less :han 1.17. !! | |||
i l | |||
this correc:1ve actica is no: successful within two =inu:es, an i==edia:e 1 | |||
shu:down shall be ini:iated. | |||
? | |||
3.1.3.2 ?cwer-:c-?lcw Ratio Greater than 2.5 and Less Than or Ecual to 15 fi The :1=e interval (t) from :he start of the ; ansient in pcVer-to-flew l ra:1o abeve Figure 3.1-2 :o the ti=e at which the power-to-flew ratio goes below f a talue of 2.5 shr.11 be reduced by 1C0 se: ends and the remaining ti=e shall be li=1:ed to a otal allevable :i=e of 2 minutes. The allowable :i=e for power-te-flow ra:ios less than 2.5 at :i=es larger :han (:) are given in 3.1.3.1. | |||
t i | |||
3.1.3.3 Pewer-to-Flow Ratio Greater than 15 i | |||
The ti=e interval (:) frc= che start of the transient in power-to-flow i | |||
l ra:1o above Figure 3.1-2 to che time at which the power-to-ficw ratio gces belev | |||
! ! a value of 2.5 shall be reduced by 60 seconds and the re=aining :ine shall be I | |||
l | |||
! li=ited to a total allowable ti=e of 2 minutes. The allevable ti=e f or pcwer-to-I i | |||
j flow ra:ios less :han 2.5 at :1=es larger than (c) are given in 3.1.3.1. | |||
f i | |||
! ! 3.1.3.4 Power-to-Flew Ratio Less Than 1.17 l | |||
For power-to-flew ratics exceeding values of Figure 3.1-2 but less than - | |||
! ! 1.17, an cperating ti=e 11=1: of 100 hours shall be used. If the cc=bination | |||
! cf power-to-flev ratio and percentage of design core ther=al power I | |||
r I | |||
i L | |||
I L | |||
Fort St. Vrain #1 | |||
. Technical Specifications A=endment a | |||
Page 3.1-3 i | |||
exceeds :he curve of Figure 3.1-2, the Operator vill take action c bring 4 | |||
:he cenbina:ica of pcwer-t:-flew and percen: age of desi;n core ther:21 pcver i | |||
under :he curve of Figure 3.1-2. If this cannot be acec:plished in four 4 | |||
hours, an erderly shutdevn shall be initia:ed. | |||
4 i | |||
! 3.1.4 3 asis for Specific g:1 n SL 3.1 i | |||
a In O rder :o assure in:egrity c f the fuel particles as a fissien ;rr-due: barrier, i: is necessary :o prevent :he f ailure of significant quanti:ies a | |||
of fuel particle coatings. Failure of fuel particle coatings can resul: fro: | |||
:he =igration of the fuel kernels through their coatings. The fependence of i | |||
the ra:e of n13:a:1on of the par:1cle kernel upon te pera:ure and :e:perature difference across the par:icle kernel using 93% confidence levels en :he ex-perimen:21 da:a was used. Ouring power opera:icn, there is a :e:pera:ura gradient across each fuel rod, tae hi;her ter;erature being a: :he center of the fuel : d and the lever te=perature at the ou:er edge of :he fuel. In i an over:e=pera:ure condi:1ca, fuel kernels can =ove thrcugh : heir coatings in this :e=pera:ure gradient, in the direction of the higher temperature. | |||
I | |||
,i l | |||
p The Core Safety Li:10 has been constructed to assure that a fuel ker-l l | |||
nel migrating at the highest rate in the core vill penetra:e a distance less l | |||
i than the cc:bined thickness of the buffer centing plus the inner isotropic I | |||
I coating on :he particle. | |||
I l The quantity of f ailed particle coatings in the core a: all :i=es i | |||
l is deter inable by =easure=ent of gaseous fission produe: activi:7 in the pri-l l Cary 100p. | |||
i l | |||
l | |||
For: St. Vrain 91 Technical Specifications A=end=en: | |||
i Page.3.1-4 In Figure 3.1-1, the quanti:y ? is :he fraction o f design core ther- | |||
=al pcwer, i.e. , core :her=al pcuer O'O divided by 542. D e quanti:y ? is 3 the frac:fon of desip. core coolant ficws a: the circula: Ors, i.e., :he total l | |||
~ | |||
I coolant flew a t the circulators in (lb/hr) divided by 3.5 x 106 lb/hr. ' | |||
The li=1:ing co=binations of core :her=al power and core coolan: flew rate are established using a series of short ti=e conservative assu=pticas. | |||
All hot channel fae: ors discussed in Section 3.6 and all pewer peaking f ac- | |||
: ors discussed in See:1on 3.3.4 of the FSA?. were applied in determining this li=iting curve. The range of regica radial power peaking factors (average pcwer densi:7 in any refueling regica, I g, divided by average power density in :he core, Fcore) was assu=ed :o be less than or equal to 1.33 and grea:er | |||
:han or equal o 0.4 ~h e =a " '= in:ra-region pcwer peaking f ac:or (average , | |||
pcwer densi:7 in a fuel colu::n, ?_co.,, divided by :he average pcwer densi:v in a fuel region, Ireg) used was 1.46 | |||
* 0.2 for regions with con:rol rods inser:ed and 1.34 i 0.2 for all unredded regions. A conserva:ive es:1= ate of the = cst unfavorable axial pcwer dis:ributien was also used. Tha: is, the ratio of pcwer density in the bot::= layer of fuel ele =ents of a core region, ts | |||
?,cwer layer, | |||
_ the c~trage pcwer density of :he region, ? reg, is less :han or equal to 0.90 1 0.09 for regions with control rods fully inserted or with-drawn, and 1.2310.12 for regions with cen:rol reds inser:ed = ore than :wo feet. ~he =easured regien coolant outle: ta=cerature for the nine regions w1:h : heir orifice valves =os: fully closed and all regions with control reds inserted =cre than two fee:, was assu=ed to be nc: =cre than 50*F 3: eater | |||
: nan the cere average cu:le: te=pera:ure. The =easu: ad regica coolan: cut-le: :e=:erature for the re=aind ng core regions was assu=ed to be no: =cre than | |||
i For: St. Vrsin dl j . Technical Specifica:icns 4 | |||
4 A=endment Page 3.1-3 i | |||
i q l 200*? greater than the core average ou:le: tempe ra:ure . During nor:21 full I i | |||
pcVer cperation, a condition with any reasured region outlet tenperature =cre | |||
) | |||
E than f 0* F abcve average shculd not persist for lenger :han a few hours. A | |||
=easureren: uncertain:y for :he core regica outlet tempera:ure of i f0*F was assumed. A f' uncertainty in ficv reasurenent and a ."' uncertainty in reac cr i thernal pcwer =easurerent was assu=ed in establishing the 11=10. r i | |||
For :he to:a1 fuel lifetite in he core, based on calcula:iens inter-porating plant parameters and uncertain:1es approp riate for longer tires , 21-i gra:100 of the fuel parcicle kernel through i:s coating would be less than | |||
* a 20 =1crens for the fuel with the =cs: da= aging te=perature his tory and with the core opera:ed constantly at any of the pcwer-to-flow ratics and power ccm-bina:1 cts shows en the curve of Figure 3.1-2. Cu of a total inner coa:ing : | |||
i thickness of 70 microns, only f0 sierons have been used for tae deter =ination I | |||
of fuel particle f ailure in set:ing the lini: curre in Figure 3.1-1. | |||
As can been seen fro: Figure 3.1-1, sufficien: :ime (at least nine | |||
=inu:es) is available for :he operator :o :ske corrective action to prevent i | |||
the core safety limit from being exceeded for pcwer-to-flow ratios less than i | |||
; or equal to 2.0. In order :n. reach a power-to-flow ratio of this =agnitude | |||
; ! through an increase in cora pcwer, significan: equip =en =alfunc tion, o r failure, and/or one or more significant deviaticas fro: cpera:ing precedures vculd have to occur. | |||
1 1 | |||
i However, high core pcwer-to-flew ratics can also Le obtai..ed as a result of a reduction or loss of pri=ar/ c clant circulation. The core nega-4 :ive coefficien: of reactivity provides an intrinsic reans to reduce :he core Y | |||
l 4 | |||
t 5 | |||
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a c:nsecuent decrease in reac:or pcver or an abnar .a1 rapid pcwer increase. | |||
I i | |||
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.t t | |||
t | |||
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. . '.~.,v ~ h. e C.9. . =. .~ a .' =. ~. f ' . . ' * . ~ . . C"..*e. ".'.~.e.=..'.~.e, i | |||
Fort St. Vrain al Technical Specifications A=endemn: | |||
Page 3.1-7 this delay period can be alleved without ec prenising the integri::. of the f ue l. As a resui: cf many transient analyses, :he delay pericd has been cen-servatively set a: 100 see:nds for ::ansients rasui:ing in a ;cver-:c-flow ra:ia above 2.5 but less than or equal to 15 and 60 seconds if the pcuer-:c- | |||
; fira ra:10 is grea:er than 15. | |||
The allevable tire, af ter the delay time, for all transients which lead : a pcuer-: -flow rati: in e: cess o f 2.5 is s et 2: 2 minutes which is also the allreable ti e fe r a pcver-::-flev rati: of 2.5 given by Figure 3.1-The lici:a:icn of alicwable opera:ing tire to a value of 100 hours 1 | |||
for all operations with a pcVer-to-flew ra:ic above the curve of Figure 3.1- | |||
+ | |||
t 2 and below a value o f 1.17 provides a conservative li it since this is the I | |||
{ alicwable :1:e for a power-to-f1: V ra:ic of 1.17 given by Figure 3.1-1. | |||
I li=10ing the cen:inuous operating ti=e in this range o f pcver-to-flev ratics i to a value of 4 hours is addi:ionally cc servative. The 4 hours continueus s | |||
e opera:ing :1:e limit :ust be included as a frac: ion of the 100 hours alluvable t | |||
, Ci e. | |||
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Latest revision as of 00:19, 18 February 2020
ML20003B267 | |
Person / Time | |
---|---|
Site: | Fort Saint Vrain ![]() |
Issue date: | 01/30/1981 |
From: | PUBLIC SERVICE CO. OF COLORADO |
To: | |
Shared Package | |
ML20003B261 | List: |
References | |
NUDOCS 8102100570 | |
Download: ML20003B267 (9) | |
Text
Fort St Vrain 11 Technical Specifications Arend=en:
l Page 3.1-1 3.1 Rea::c Co re - Safe:v Limit
3.1.1 Apoli
bili:v Applies to the li=iting cc Sinations of core ther al power and core heliu= flew rate.
3.1.2 Obiective To maintain the in:eg 1:7 of the fuel particle coa:ings.
3.1.3 Specifica:1on SL 3.1 - Rese:Or Core Saferv Li d:
i The combina:icn of :he reac:cr core power-:0-ficw ratio and the 00:21
,i integrated operating tire a: the power-::-flew ratio during :he life: ire of e
i any seg=en: shall no: exceed :he following 11=its.
4 i
3.1.3.1 Power-:c-? lev Ratio 3e:veen 1.17 and 2.3 The co=bina: ion of the reactor core pcwer-to-flew ra:ia and the :otal I
integrated operating ti=e at this power-to-flow ratio during the lifetime of
.I .
I 8
any seg=en: shall no: exceed the 11:1: given in Figure 3.1-1. This safe:y 11=1: is exceeded when the cc binatica of operating parameters (;cuer, flew, and :i=e) lies above or :o the right of the line given in Figure 3.1-1.
i 1
For :he purpose of obtaining the :otal eff ective in:egra:ed opera in:.
- i=e for Figure 3.1-1, only ::ansients resulting in a power-:c-flow ratio abcVe the curve of Figure 3.1-2, at the appropriate core power level shall be used.
8302100 570
Fort St. Vrain til
, Technical Specifications A=end=en t Page 3.1-2 Fc pcwer-:c-flev ratics between 1.17 and 2.5, the opera:or shall
, i==ediately reduce pcwer to 1cuer the power-:c-flow ratio :o less :han 1.17. !!
i l
this correc:1ve actica is no: successful within two =inu:es, an i==edia:e 1
shu:down shall be ini:iated.
?
3.1.3.2 ?cwer-:c-?lcw Ratio Greater than 2.5 and Less Than or Ecual to 15 fi The :1=e interval (t) from :he start of the ; ansient in pcVer-to-flew l ra:1o abeve Figure 3.1-2 :o the ti=e at which the power-to-flew ratio goes below f a talue of 2.5 shr.11 be reduced by 1C0 se: ends and the remaining ti=e shall be li=1:ed to a otal allevable :i=e of 2 minutes. The allowable :i=e for power-te-flow ra:ios less than 2.5 at :i=es larger :han (:) are given in 3.1.3.1.
t i
3.1.3.3 Pewer-to-Flow Ratio Greater than 15 i
The ti=e interval (:) frc= che start of the transient in power-to-flow i
l ra:1o above Figure 3.1-2 to che time at which the power-to-ficw ratio gces belev
! ! a value of 2.5 shall be reduced by 60 seconds and the re=aining :ine shall be I
l
! li=ited to a total allowable ti=e of 2 minutes. The allevable ti=e f or pcwer-to-I i
j flow ra:ios less :han 2.5 at :1=es larger than (c) are given in 3.1.3.1.
f i
! ! 3.1.3.4 Power-to-Flew Ratio Less Than 1.17 l
For power-to-flew ratics exceeding values of Figure 3.1-2 but less than -
! ! 1.17, an cperating ti=e 11=1: of 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> shall be used. If the cc=bination
! cf power-to-flev ratio and percentage of design core ther=al power I
r I
i L
I L
Fort St. Vrain #1
. Technical Specifications A=endment a
Page 3.1-3 i
exceeds :he curve of Figure 3.1-2, the Operator vill take action c bring 4
- he cenbina:ica of pcwer-t:-flew and percen: age of desi;n core ther:21 pcver i
under :he curve of Figure 3.1-2. If this cannot be acec:plished in four 4
hours, an erderly shutdevn shall be initia:ed.
4 i
! 3.1.4 3 asis for Specific g:1 n SL 3.1 i
a In O rder :o assure in:egrity c f the fuel particles as a fissien ;rr-due: barrier, i: is necessary :o prevent :he f ailure of significant quanti:ies a
of fuel particle coatings. Failure of fuel particle coatings can resul: fro:
- he =igration of the fuel kernels through their coatings. The fependence of i
the ra:e of n13:a:1on of the par:1cle kernel upon te pera:ure and :e:perature difference across the par:icle kernel using 93% confidence levels en :he ex-perimen:21 da:a was used. Ouring power opera:icn, there is a :e:pera:ura gradient across each fuel rod, tae hi;her ter;erature being a: :he center of the fuel : d and the lever te=perature at the ou:er edge of :he fuel. In i an over:e=pera:ure condi:1ca, fuel kernels can =ove thrcugh : heir coatings in this :e=pera:ure gradient, in the direction of the higher temperature.
I
,i l
p The Core Safety Li:10 has been constructed to assure that a fuel ker-l l
nel migrating at the highest rate in the core vill penetra:e a distance less l
i than the cc:bined thickness of the buffer centing plus the inner isotropic I
I coating on :he particle.
I l The quantity of f ailed particle coatings in the core a: all :i=es i
l is deter inable by =easure=ent of gaseous fission produe: activi:7 in the pri-l l Cary 100p.
i l
l
For: St. Vrain 91 Technical Specifications A=end=en:
i Page.3.1-4 In Figure 3.1-1, the quanti:y ? is :he fraction o f design core ther-
=al pcwer, i.e. , core :her=al pcuer O'O divided by 542. D e quanti:y ? is 3 the frac:fon of desip. core coolant ficws a: the circula: Ors, i.e., :he total l
~
I coolant flew a t the circulators in (lb/hr) divided by 3.5 x 106 lb/hr. '
The li=1:ing co=binations of core :her=al power and core coolan: flew rate are established using a series of short ti=e conservative assu=pticas.
All hot channel fae: ors discussed in Section 3.6 and all pewer peaking f ac-
- ors discussed in See:1on 3.3.4 of the FSA?. were applied in determining this li=iting curve. The range of regica radial power peaking factors (average pcwer densi:7 in any refueling regica, I g, divided by average power density in :he core, Fcore) was assu=ed :o be less than or equal to 1.33 and grea:er
- han or equal o 0.4 ~h e =a " '= in:ra-region pcwer peaking f ac:or (average ,
pcwer densi:7 in a fuel colu::n, ?_co.,, divided by :he average pcwer densi:v in a fuel region, Ireg) used was 1.46
- 0.2 for regions with con:rol rods inser:ed and 1.34 i 0.2 for all unredded regions. A conserva:ive es:1= ate of the = cst unfavorable axial pcwer dis:ributien was also used. Tha: is, the ratio of pcwer density in the bot::= layer of fuel ele =ents of a core region, ts
?,cwer layer,
_ the c~trage pcwer density of :he region, ? reg, is less :han or equal to 0.90 1 0.09 for regions with control rods fully inserted or with-drawn, and 1.2310.12 for regions with cen:rol reds inser:ed = ore than :wo feet. ~he =easured regien coolant outle: ta=cerature for the nine regions w1:h : heir orifice valves =os: fully closed and all regions with control reds inserted =cre than two fee:, was assu=ed to be nc: =cre than 50*F 3: eater
- nan the cere average cu:le: te=pera:ure. The =easu: ad regica coolan: cut-le: :e=:erature for the re=aind ng core regions was assu=ed to be no: =cre than
i For: St. Vrsin dl j . Technical Specifica:icns 4
4 A=endment Page 3.1-3 i
i q l 200*? greater than the core average ou:le: tempe ra:ure . During nor:21 full I i
pcVer cperation, a condition with any reasured region outlet tenperature =cre
)
E than f 0* F abcve average shculd not persist for lenger :han a few hours. A
=easureren: uncertain:y for :he core regica outlet tempera:ure of i f0*F was assumed. A f' uncertainty in ficv reasurenent and a ."' uncertainty in reac cr i thernal pcwer =easurerent was assu=ed in establishing the 11=10. r i
For :he to:a1 fuel lifetite in he core, based on calcula:iens inter-porating plant parameters and uncertain:1es approp riate for longer tires , 21-i gra:100 of the fuel parcicle kernel through i:s coating would be less than
- a 20 =1crens for the fuel with the =cs: da= aging te=perature his tory and with the core opera:ed constantly at any of the pcwer-to-flow ratics and power ccm-bina:1 cts shows en the curve of Figure 3.1-2. Cu of a total inner coa:ing :
i thickness of 70 microns, only f0 sierons have been used for tae deter =ination I
of fuel particle f ailure in set:ing the lini: curre in Figure 3.1-1.
As can been seen fro: Figure 3.1-1, sufficien: :ime (at least nine
=inu:es) is available for :he operator :o :ske corrective action to prevent i
the core safety limit from being exceeded for pcwer-to-flow ratios less than i
- or equal to 2.0. In order
- n. reach a power-to-flow ratio of this =agnitude
- ! through an increase in cora pcwer, significan
- equip =en =alfunc tion, o r failure, and/or one or more significant deviaticas fro: cpera:ing precedures vculd have to occur.
1 1
i However, high core pcwer-to-flew ratics can also Le obtai..ed as a result of a reduction or loss of pri=ar/ c clant circulation. The core nega-4 :ive coefficien: of reactivity provides an intrinsic reans to reduce :he core Y
l 4
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Fort St. Vrain al Technical Specifications A=endemn:
Page 3.1-7 this delay period can be alleved without ec prenising the integri::. of the f ue l. As a resui: cf many transient analyses, :he delay pericd has been cen-servatively set a: 100 see:nds for ::ansients rasui:ing in a ;cver-:c-flow ra:ia above 2.5 but less than or equal to 15 and 60 seconds if the pcuer-:c-
- fira ra
- 10 is grea:er than 15.
The allevable tire, af ter the delay time, for all transients which lead : a pcuer-: -flow rati: in e: cess o f 2.5 is s et 2: 2 minutes which is also the allreable ti e fe r a pcver-::-flev rati: of 2.5 given by Figure 3.1-The lici:a:icn of alicwable opera:ing tire to a value of 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> 1
for all operations with a pcVer-to-flew ra:ic above the curve of Figure 3.1-
+
t 2 and below a value o f 1.17 provides a conservative li it since this is the I
{ alicwable :1:e for a power-to-f1: V ra:ic of 1.17 given by Figure 3.1-1.
I li=10ing the cen:inuous operating ti=e in this range o f pcver-to-flev ratics i to a value of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is addi:ionally cc servative. The 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> continueus s
e opera:ing :1:e limit :ust be included as a frac: ion of the 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> alluvable t
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