ML20003B267

Proposed Tech Specs for Facility

ML20003B267
Person / Time
Site:	Fort Saint Vrain
Issue date:	01/30/1981
From:	PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20003B261	List: ML20003B260 ML20003B267
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:

The combina:icn of :he reac:cr core power-:0-ficw ratio and the 00:21 i

,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 3.1.3.1 Power-:c-? lev Ratio 3e:veen 1.17 and 2.3 i

The co=bina: ion of the reactor core pcwer-to-flew ra:ia and the :otal integrated operating ti=e at this power-to-flow ratio during the lifetime of

.I I

I any seg=en: shall no: exceed the 11:1: given in Figure 3.1-1.

This safe:y 8

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 f

The :1=e interval (t) from :he start of the ; ansient in pcVer-to-flew i

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 3.1.3.3 Pewer-to-Flow Ratio Greater than 15 ii The ti=e interval (:) frc= che start of the transient in power-to-flow l

ra:1o above Figure 3.1-2 to che time at which the power-to-ficw ratio gces belev i

! 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

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Fort St. Vrain #1 Technical Specifications A=endment Page 3.1-3 a

i exceeds :he curve of Figure 3.1-2, the Operator vill take action c bring

he cenbina:ica of pcwer-t:-flew and percen: age of desi;n core ther:21 pcver 4

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

In O rder :o assure in:egrity c f the fuel particles as a fissien ;rr-a due: barrier, i: is necessary :o prevent :he f ailure of significant quanti:ies of fuel particle coatings. Failure of fuel particle coatings can resul: fro:

a

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

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The Core Safety Li:10 has been constructed to assure that a fuel ker-p l

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nel migrating at the highest rate in the core vill penetra:e a distance less i

than the cc:bined thickness of the buffer centing plus the inner isotropic I

I coating on :he particle.

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The quantity of f ailed particle coatings in the core a: all :i=es i

is deter inable by =easure=ent of gaseous fission produe: activi:7 in the pri-l 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

~

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,

?,cwer layer, the c~trage pcwer density of :he region, ? reg, is less :han ts 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 A=endment 4

4 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

)

than f 0* F abcve average shculd not persist for lenger :han a few hours. A E

=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 thernal pcwer =easurerent was assu=ed in establishing the 11=10.

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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-

ive coefficien: of reactivity provides an intrinsic reans to reduce :he core 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 3.1-2 and below a value o f 1.17 provides a conservative li it since this is the

+

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alicwable :1:e for a power-to-f1:

ra:ic of 1.17 given by Figure 3.1-1.

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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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