Text

Proposed Tech Specs,Revising Core Operating Limits Rept License Amend Submittal
	ML19327A955
Person / Time
Site:	Summer
Issue date:	10/19/1989
From:	; SOUTH CAROLINA ELECTRIC & GAS CO.
To:	;
Shared Package
ML19327A954	List: ML19327A953; ML19327A955;
References
	NUDOCS 8910240039
	Download: ML19327A955 (12)
	v • d • e

,_ _

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k htACTiv1TY CONTROL $YSTEMS it 400t4ATOR TEMPf u TUtf COEFFICltWT

],0 et A r

LIN! TING CONDITION FOR OP[ RATION

=

erster to.p.reture co.ericient <me> shaii beir A 4 M.

3.1.1. 3 The skd IM the Codi 0$lte ftah I,tattr5 (Aptf(cold), 'fhs.

i menma m lef64A.3.I*A I

.a m

=z-APPLitAl!LITY:

Lo 20t$ 1 and 2* enlyf i

- M00E5 1. 2 and 3 only#

ACTION:

(I b

ODb4 sos With the WTC more positive than the9ieltg

~

a.

operation in MODES 1 and 2 may proceed prov'

above, Control roc withdrawa) 11mits are established and maintain6ot 1.

hcoLA

> ifficient to ra wa the MTC to less positive than the at/

^"

._ __within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in NOT STAN08Y l

w snth the ned H hours. These withdrawal limits shall be in

~

addition to the insertion limits of $pecification 3.1.3.6.

2.

The control rods are natatained within the withdrawat limits established above until a subsequent calculation veriffes that

}

the MTC has been rtstored to within its liett for the all rods i

withdrawn condition.

I 3.

In iteu of any other report reevired by Specification 6.9.1, a I

Special Report is prepared and submitted to the Commission i

i pursuant to Specification 4.9.2 within 10 days, describing the j

value of the measured NTC, the interie centrol red withdrawai limits and the pmdicted everage core burnup necessary for restering the positive NTC to within its iteit for the all rods withdrawn condition.

b.

With the NTC aere tive than the eit h l be in HOT $NLITDOW within hours.

, gg with K,gg greater than or equal to 1.0

$ee special Test taception 3.10.3 i

i

$UlttER UNIT 1 3/4 1 4 Anonement No.

l l

t Jgo2gggy $$,

P i

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t

.EActiv!TY CONT 40L $YSTEMS 1

l SVtVtitLANCf.f00!#EMfWT5 i

. 1. 2. 3 th cy ie.. <.e m.h.n

.ete,,ined t..e.itnin it, u.it. oring e.ca roei i

n e..,

g 4^l 4.

The WTC s e and compared to the SOL liett a

Prior to initial operation above 1

e i

or each fuel leading.

The WTC thall be seasured at any THEW 4 POWER.and c j

b.

C "..-

arod to

_. _ _~ J-'7(411 red, witherewn RATED Th IMAL POWtt l

/comenTen; wnnfn r srre afur teething a i

5 tretion of 300 ppe. !

n h

i is more negative than on indicates the WTC 10.eeae

, and c ed to the 4

e-

"f" SPI-*.

r

.t is nee

,14 u,0 orin,th. r g

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$1494tR

UNIT 1 1/4 bl Amendment No.

6 y----.w.,

~ _... _

l

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_ y, --

~

w ag y2 % d,. eees i

3/4.2 P M A Ollititut10w (!MITs CPER47} r, umit s REPcf T AXIALFlurO!Fr[Rtwethar0} $

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3/4.2.1 t!MITING C0W ITION FOR OPtM TION

)

l 3.2.1 The indicated AX1AL FLUX DIFFitthCE (MO) shall be sh!BEWPi:rJertfMmPleampferttre, difre,e-o do,rn.. san. s, ined in we dehe.t,,e ta,,et n.

i

. m in = te, t ase io e,e,. u on.

a,,ue= Im Ha 1.e.e a efu m m.L

i i

gng:

I rer u0e e,e.uen.mgin.i..ted 0 e tside of = a,,ucaie a.

v n o us s,- in ed in we n or,este,e we indi.ated Ar0 to. min weggs,ecine. !

1.

neits,m in ti sinotes, or i

t.

med.e M o t > = = to

. min 30 eintes and,0.iess mn,s=.e,e, ume.m L,==

7,i, sei,e m s to sess on,e meer e uai m'erum =n n.

1f t"

tro = P=

within the nest 4 heure.

I b.

For late Lead retten above A,LP with the indicated AFD evtside of the appi, cat ta,get band about the target flu iffgrencest-i 1.

Either,estere the indicated AFD to within the target band within 15 minutes, or S,ecified I

i 2.

Reduce MML POWEA te less than A,L8

[

and discontinue lase Lead operetten within 30 einstes.

of MTED THt.L PMR THEWL POWER shall not be increased aseve 55 of 4ATED M i

c.

unless the indicated AFD is withi. the applicable AAge limits.

i l

t

5ee Special Test faception 3.10.2 O

- A,L is the einism al' o.able power lev be feev4 set in the1__ _

^-- . el far base lead ope,etion and wd1 W

N

___ Oper Specification 6.9.1.11.

z coac oerm* urnas aerear) sumta unti i v4 t-1 Amendment No.

I

9

0Wft OllisitL/ffen (!ngts i '

599Vt1LLM! sgoultDqtwf5

4. 2. 2.1 The pr, visions of Specification 4.0.4 are not applicaele.

4.4.2.2 For 4AOC eneration. F (a) shall be evaluated is within its Itait ty:

0 Q

Using the oevable incere setectors to attain a sewer tittribution a.

esp at av THt4PEL POWER greater than M of 4ATO THEApML POWER.

!= reasing m. esu,.e r m co.,en.nt of = - r.istri.ution esp by W te account for m,anufacturing tolerances and furth i

Yority the requirements of Specification 3.2.2 are s i

s.tisfring = fene.15 rei.ii.nai, c.

i r"d)

C

a m,e,,,...

r a v (a)

[

m a. L A'_-(4 pgg,)

p ;,

g f

e4u, F(s)i for P i 0.

-- O where (3)fsthesensuredF(a)i ed by the allowances g

4g,P(t) if for annufacturing)taledr l

K uncertainty is i[>

the F limit t(s is Pisthere} stye A g(g) og,

.andqeatewinstranstaatae i

s4 s

cyc function that I

ace i t

per apes m sezien v.~w.L.

m d.

Y Measuring Fj(I) escording to the following schedule oNRenk.B l

Limin88MT) 1.

Upon echterine equilibria censittens after onceasing by 15 t

or este of RATB THESEL POWER, the THESEL POWER st which t

F (t) wee lost estermined

er g

3.

At 1oest enee per 31 fffective Full Power Days, whichever escurs ffret.

l During power escalation at the beginning of each cycle, power level acy be increased until a power level for extenced operetten has been achievee and power distributten esp ettaines, a

_t h.e-2 t

t

_,..,-. - - -, _. - -.--...-~ _,,-. _.--__ _..,.,_..

_.. ~. - _. _., ~ _ _ _ _.., ~. - - -

,,---,-w--

, -. ~..

E llfeltyfl0N LIMITS

$URVitttANct ttoulatMtwTs (continued)

(2) One of the following actions shall be taken I

i (4) Within 15 minutes, control the M O to within new AF0 limits which are determined by reducing the aeolicable WO Ifetts by 15 AFD for each percent F (4) oceeds its Iteils as reset the AFD alare setpointa to t#ese modified tisits, or q

detemined in $pecification 4.t.2.3f.1). Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

l (b)

Cos F (ely with the requirements of $pecification 3.2.l or j

(c) Verify that the reeutrements of specification 4.2.2.3 for lose Lead o 3

operation. peration are satisfied and enter Sase Lead

)

The 11mits specified in Specifications 4.2.2.tc.

4 4

i g.

4.2.2.2f. above are not appilcable in the followIng.2.2.2e.. and regions:

core plano j

i 1.

tower core region free e to 15 i Upper core region free el to lob,nclusive.

2.

inclusive.

4.2.2.3 lase lead operetten is permitted at powers above APLE if the following conditions are satisfied:

t 1

Prior to entering lase Land operetten, osintain THEM4L POER above f

a.

Apt" and less than er equal to that allowed by Specification 4.2.2.2 I

I for at least the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Maintain sese Lead operation surveillance (APS within aspitcable target band about the target flum difference) during this ties peries. Sase Lead operation is then anda,tegttedprovidi POER is osintained between APLE I

i rL er between AP and 103 (whichever is sost liattine and F surveillance is esintained pursuant to Specification 4.1.)2.4.

APL is deFi as the einfeus value of:

}

Ee APLE=

a 105 qa)a W )g i

over the core neight (a) where: d(s) is the eneeured F (a) q in.reas

, t e.n _,or annu t.ie en - and esasurement uncertainty. The F 11eit i C: 1-J i

g

,f 4""__ _ - " O W )g s the cycle dependent function that accounts

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$l80ER

UNIT 1 3/4 2 la Amendment Me I

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E 013ft!PUT20N TIM!T$

IVevt!LLANCE Rt0UIREMtwts (conting. )

b.

During lase Loss operation, if the THERMAL PO ApL then the concittens of 4.2.2.3.4 shall be creased below re entering test Lead operation.

s ed before 4.2.2.4 F (t) is within its Iteit ty:During Base Lead Operetten F g

g e aratne if Using the movable incere detectors to obtain a p a.

map at any THERMAL POWER above Apl ND, s r bution b.

Increasing the measured F (t) component of the g

sap by 35 to account for manufacturin u on 1

Verify the requirements of Specification 3 2 2 are sat n es.

Satisfying the fellowine relationship:

c.

J tad.

$(a)i

[

E for P> APL"'

where:

O (3)isth'sasasuredF(s).

g The F limit is q

f en he ts 1

a pec 4.

Measuring %(3) in conjunetten with target flus diff determinetten according to the fe11 swing schedule:

erence

.~.

1.

Prior to entering SA$t LOAD operetten after satis A n*fA "I

previous 31 EFPS witgthe relative th ec-esintained aheve APL e

for the 24 heure prior to aapping, and 2.

At least once per 31 fffective Full Power Oeys, With the annia n value of e.

- d(s)

E(a) over the core height (t) increasing since the previous dot of (3) either of the following actione shell be taken SUptitA

UNIT 1 3/4 2*$b A8endbeet No-t l

Lf^*~! k 1Ar Cots o/>ceprisur 4/inr7's REP >t T (co tt)

RS TM y,a AA ym 2 jn, 7g, z,,, p,g,,

l M

p l

POWER 0l$TRIBUT10N LJNjf$

3/4.2.3 RC$ FLOW RATE AND NUCLEAR ENTHALPY RI$E HOT CHANNEL __

i LIMITING CONDITION FOR OPERATION l

l 3.2.3 The combination of indicated Reactor Coolant System (RC$

rate and R shall be maintained within the region of allowable op)eration total f1 i

g Where:

M H

L p

RATED THLRMAL PUWER Fh = Measured values of Fh obtained by using the movable intore c.

l l

detectors to obtain a power distribution map. The measured

[

values of Fh shall be used to calculate R sincef__' 1:

l

']

includes measurement uncertainties of 2.1% for flow and 4% for i

/

incore measurement of Fh, and fle.)(,5 W )

N Y8W APPLICA61LITY: MODE 1.

ACTION:

~

With the combination of RCS total flow rate and R outsjde the region of accept-i able operationM r;'Af k th, col & 5 l

t a.

Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months either; d

1.

Restore the combination of RC$ total flow rate and R to within i

the toove limits, or 2.

Reduce THERMAL POWER to less than 50K of RATED THERMAL POW and reduce the Power Range Neutron Flux High trip setpoint to less than or e next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . qual to $5x of RATED THERMAL POWER within the b.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of initially being outside the above lief ts, verify i

through incere flux napping and RC$ total flow rete comparison that the combination of R and RCS total flow rate are testored to within the above limits, or reduce THERMAL POWER to less than 5% of RATED l

THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Identify and correct the cause of the out-of limit condition prior c.

to increasing THERMAL POWER above the reduced THERMAL POWER limit reoutred by ACTION items a.2. and/or b. above; subsequent POWER 5

OPERATION may proceed provided that the combination of R and indicated RCS total flow rate are demonstrated, through incere flux mapping and RCS total flow rate cosparison, to be within the region of acceptable operation:^

_1 - iprior to exceeding the l

following THERMAL POWER 'evels:

i

$UmER - UNIT 1 3/4 2-3 AmendmentNo.f),pp gl. &g

- -.. ~... -..,

r

,.-..,_r_,.

_...,,.....,..,,._,,..v~.._,.m.,,

_m.....,_..

_ ~ _ _

y, s

POWER 0!$7t!Buffow LINtis--

i LIMITING CON 0lfl0N FOR OPfuf!0W I

x act!ON.

(Continued) f i

1.

A nominal SOE of AATED THEWL POWER, 2.

A noetnal 72 of Raft 0 THERNAL POWER, and within =4 hoors of attainin..reate, than e, et ai to m of j

3.

4ATED THERMAL POWtt f

Sut 4!LLANCE REQUlttMENTS I

4.1.3.1 The previsions of Specification 4.0.4 are not appitcable.

4.2.3.2 detemined to be within the regten of acceptable operatte

~ - "3 t l

,,ier to e,e,atten a.e.e m of m:0==,0Wii after each f'eh 4.

ieadin, an.

b.

At least once per 31 Effective Full Power Days.

4. 2. 3. 3 The indicated RCS total flow rate sha reglen of acceptable operettenr

~__1_

M verified to be within the

{

the most receatly obtataed value of R obtain65 per Spectfication 4.2.3 2et le

[

assumed to exist.

., is i

t

4. 2. 3. 4 CALIBRATION at least once per 18 months.The RCS total flev rate ind i

i 4.2.3.5 l

ence per 18 months,The RCS total flew rate shall be determined by esasurement a

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1 i

t 5

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$ M R UNIT 1 3/4 2*l Amendment M. M e

- - - - - ^ ~ ~ ~ ~ ~ ' ~ _- - -

- - - '-'^~~ ~ ~_, _ _ _ - - - -

.f

!1 fever 0!$7R18UTION L! WIT

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i BASE $

py 4

_3/4.2.2 and 3/4.2 3 g

NucLEnx turMALn Ust Mor chammtL racicaNEAT FLUX AND Q

4 the limits on heat flux hot channel factor enthalpy rise hot channel factor ensure that 1),the design limi k'

N 4 local power density and ninteus DNOR are not exceed d i

LOCA the peak fuel clad temperature will not exceed the 2200 n peak t

i e

and 2) in the event of a criteria limit.

CC$ acceptance

)

as specified in specifications 4.2.2 and 4Each of these is meas I

i only be detersined periodically sufficient to insure that the Iteits are ma.2.3.

his periodic Surveillance is t

intained provided:

Control rods in a single group move together with no indiv a.

1 w

insertion Offferin i

Q by more than 13 steps, indicated, from the rod D

group t.seend posit on.

)

b.

Control rod groups are $49Venced with overlapping groups in $pecification 3.1.3.6.

scribed i

h Q'

%*g 3.1.3.6 are maintateed.The control' rod insertion limits of s c.

h n

i d.

O!FFERENCE, is maintained within the limits.Th

Pawee,

> ((

h will be maintained within its limits provided conditio

hrough

d. above are maintained.

As noted on~)egesentetuT,) RC5 flow rate ands te " traded off" inst may n

g acceptable i ther (i.e., a low measured RC$ flow rat will not be below the design ON64 value.is aise low) to ensure that the g

s of THERMAL POWER allows changes in the radial pow red insertion limits.

e h' R as calculated N

I

.3 and used integesgsesesR) accounts for Fh H

less than or equal to m

this value is uses in the various accident analyses where Th influefies parameters other than DNtt, e.g.. p temperature and thus is the staisua "as asesured" value allowed Mar in is maintained between the safety analysis liett DNtt and th

,g '

desi n 1 mit DN64.

This margin is more than sufficient to offset any rod bow e

pena ty and transition core penalty.

I The remaining margin is available for plant design flexibility.

When an F and manufacturing tolerance must be saec.q sessurement is tak 8%

for a full core map taken with the intore detetAn allowance of 55 is appropriate y@

3% allowance is appropriate for manufacturing to erance.r flux mapping systes

$UMMER UNIT 1 8 3/4 2 3 Amenement No.

, -. + - "

- - - - ~ ~ ~

~~

I t

p0WER Ol$TRIBUTION LIMIT BA$t$

3 HEAT FLUX HOT CHANNCL FACTOR and Rc$ FLOWRATE and NUCl[AR [NT HOT CHANN[L FACTOR LContinueo)

The hot channel factor F (z) is measured periodically and increased by a l

cycle and height dependent power factor appropriate to either RAOC or Base Load operation, W(1) or W(2)gt, to provide assurance that the limit on the hot channel f actor. F (z) is met. V(t) accounts for the effects of normal opera-g

(' k-tion transients and was detemined from expected power control maneuvers over the full range of burnup conditions in the core. W(s)gg accounts for the more restrictive operating limits allowed by 8ase Load operation which result in less severe transient val,ues. The W(z) and W(z)gt functions described above for normal operation tre t Z 3 in the *

$pecification 6.9.1.11.

Ne_c o._ E f_ _ _..

') pe r

^

d ptRR7nqr omt75 REMT(OLR) when RCS flow rate and t

are measured, no additional allowances are i

gj necessary prior to comparison With the limits of"'____1 D Measurement

%Yl errors of 2.1% for RCS total f1 in detemining the ii.iti ofpEnrate and 4% for Fh have been allowed for l

i u,

,nego The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months periodic surveillance of indicated RCS flow is sufficient to detect only flow degradation which could lead to operation outside the_

l l

acceptable region of operation @ieiR)on~n g.

l 3/4.2.4 OVA 0 RANT POWER TILT RATIO The cuadrant power tilt ratio limit assures that the radial power distribu-l O

tion satisfies the design values used in the power capability analysis. Radial power distribution measurements are maae during startup testing and periodically N.

j

{

during power operation, The limit of 1.02, at which corrective action is required y

and linear heat generation rate protection with x y plane power, provites DN6 tiltt. A Itmiting tilt of 1.025 can be tolerated before the margin for uncertainty in I

F i

g s depleted. The limit of 1.02 was selected to provide an allowance for the uncertainty associated with the indicated power tilt.

The two hour time allowance for operation with a tilt condition greater than 1.02 but less than 1.09 is provided to a11ow identification and correction of a cropped or misaligned contre) rod. in the event such action does not correct the tilt, the margin for uncertainty on F is reinstated by reducing the maximum g

allowed power by 3 percent for each percent of tilt in excess of 1.0, For purposes of monitoring QUADRANT POWER TILT RATIO when one encore detector is inoperable the movable incere detectors are used to confirs that the normalized symmetric power distribution is consistent with the QUADRANT POWER TILT RATIO.

The incore detector monitoring is done with a full incere flux map or two sets of 4 symmetric thinoles. These locations are C 8. E 5 E-11, H 3, H-13. L 5, L 11, N-8.

+

sum (R - UNIT 1 B 3/4 2 4 Amendment No. #$.

v,

[..

e v':

y t.

r I

l The CORE OPERATING LIMITS REPORT. including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle.

to the NRC Document Control Desk with copies to the Regional Administrator t,

and Resident Inspector.

P I

l :'

I:

f' I

i i

S 1

L t

r I

t V

l l

1 1.*

l l

1' l

~~

~

Core Operating Limits Report For V. C. Summor Cycle 5 i

2.6 BCS Flow Rate and Nuclear Enthalov Rise Hot Channel Factor (Specification 3.2 3) u p

g-R=

N FAHRTP e

(1 + PFAH ' (1-P))

1 THERMAL POWER where Ps RATED THERMAL POWER F

2.6.1 FAHRTP,.1.56

2. 6.' 2 PFAH = 0 3 2.6.3. The Acceptable Operation Region from the combinat. ion I

of Reactor Coolant System total flow and R is L

provided in Figure 14.

[

l i-i f

Page 26 of 27

-

ML19327A955

Text

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