Text

Proposed Tech Specs,Revising Core Operating Limits Rept License Amend Submittal Dtd 890919
	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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', V. . .

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

et A ],0 r

LIN! TING CONDITION FOR OP[ RATION =

3.1.1. 3 The

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

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

i menma I m lef64A.3.I*A

=z- .a m Lo APPLitAl!LITY: .

20t$ 1 and 2* enlyf i

- M00E5 1. 2 and 3 only#

ACTION: (I *

b ODb4 a.

sos _

With the WTC more positive than the9ieltg

~

above,

operation in MODES 1 and 2 may proceed prov'

1. 6ot

- Control roc ifficient towithdrawa) ra wa 11mits are established and maintain ,

^" the MTC to less positive than the hcoLA at/

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

l -- ~

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 i

! the MTC has withdrawn been rtstored to within its liett for the all rods condition.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withdrawn condition.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 '

HOT $NLITDOW within hours. eit h l be in

, 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 l Anonement No. l t

Jgo2gggy $$ ,

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.EActiv!TY CONT 40L $YSTEMS l

SVtVtitLANCf .f00!#EMfWT5 '

i

. 1. 2. 3 th !

cy ie .. <.e m, .h.n n e.. .ete,,ined t. .e .itnin it, u.it. oring e.ca roei i

4. The WTC s a e and compared to the SOL liett g 4^l ;

Prior to initial operation above 1 or each fuel leading. e i ,

b. j C The" . .- WTC thall be seasured at any THEW 4 POWER.and

__ arod cto

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

i 5

tretion of 300 ppe. !

10.eeaer

/comenTen; is more negative than

, and c wnnfn r srre afur teething a ed to the n h on indicates the WTC 4 ,

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.t is nee e-

,14 u ,0 orin,th. r "f" SPI-*. -

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$1494tR

UNIT 1 1/4 bl ;

Amendment No.

6 y----.w., , , , - - . - . . . . , , , . _ - . , _ , , , , , - , , . - .

- ~ _ . . . _

l

. _ y, -- ~

.l w ag y2 % d,. eees

' i 3/4.2 P M A Ollititut10w (!MITs CPER47} r, umit s REPcf T 3/4.2.1 AXIALFlurO!Fr[Rtwethar0} $ _

~

l t!MITING C0W ITION FOR OPtM TION )

l 3.2.1 '-

The indicated AX1AL FLUX DIFFitthCE (MO) shall be sh!BEWPi:rJertfMmPleampferttre, !

.. . m in = te, t ined in we dehe.t ,,e ta,,et n.

difre,e-o do,rn. . san. ase io s, e,e,. u on. i a,,ue= Im Ha 1.e.e a efu m m .L ;i gng: i I

a. v n o us s ,- in ed in we 0 e tside of = a,,ucaie rer u0e e,e .uen .mgin.i..ted ;

1.

n or ,este,e neits ,m in ti sinotes, we indi.ated or Ar0 to . min weggs,ecine. ! -

i

t. med.e M o t > = = to L ,== ;

. min 30 eintes and ,0.iess . mn,s=.e,e,t" ume.m tro 7,i, sei,e m s to sess on,e meer e uai m'erum =n = n.P=#1f within the nest 4 heure.

I

b. For late Lead retten above A,LP of the appi, cat with the indicated AFD evtside !

ta,get band about the target flu iffgrencest- i

1. Either ,estere the indicated AFD to within the S,ecified I i

target band within 15 minutes, or ;

2. Reduce MML POWEA te less than A,L8

[ of MTED THt.L PMR and discontinue lase Lead operetten within 30 einstes.

i c.

THEWL unless thePOWER indicated AFD shallisnot withi.bethe increased applicableaseve 55 of 4ATED MN AAge limits. ;

i l t

5ee Special Test faception 3.10.2

- A,LO is the einism al' o.able power lev !

be feev4 set in the1__ _ ^-- . el far___

baseOperlead ope,etion6.9.1.11.

Specification and wd1 !

W N -

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 is within itsFor Itait 4AOC ty: eneration. F (a) shall be evaluated 0

Q t

a. ,

Using the oevable incere setectors to attain a sewer tittribution !

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 i

esp by W te account for m,anufacturing tolerances and furthl i Yority the requirements of Specification 3.2.2 are s' c.

s.tisfring = fene.15 rei.ii.nai, i r"d) *r*aC a v (a) m ,e, , ,... ,

p ;,

g

[ m a. L A'_-(4e4u, f pgg,) !

F(s)i for P i 0. - -

O where ;

(3)fsthesensuredF(a)i g ed by the allowances if ;

l 4g,P(t)K for annufacturing)taledr uncertainty is A g(g) og, the F limit t(s is Pisthere} stye ,

i[> ace i s4

.andqeatewinstranstaatae s cyc function that i

I t

per apes m sezien v.~w.L.

m

. d. oNRenk.B Y Measuring Fj(I) escording to the following schedule Limin88MT) l 1.

Upon echterine equilibria censittens after onceasing by 15 t t

or este of RATB THESEL POWER, the THESEL POWER st which Fg (t) wee lost estermined

er !

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- l 2 !

t t

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

,, E llfeltyfl0N LIMITS

$URVitttANct ttoulatMtwTs (continued) ,_

i (2) One of the following actions shall be taken 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 percentq F (4) oceeds its Iteils as 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 .

reset the AFD alare setpointa to t#ese modified tisits, or (b) Cos l 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 :

4

)

i

g. The 11mits specified in Specifications 4.2.2.tc. 4 ;

j 4.2.2.2f. above are not appilcable in the followIng.2.2.2e.. core planoand regions: .

i

1. tower core region free e to 15 i '

2. Upper core region free el to lob,nclusive. inclusive.

4.2.2.3 lase lead operetten is permitted at powers above APLE if the following conditions are satisfied: t 1

a.

Prior to entering lase Land operetten, osintain THEM4L POER above f I Apt" and less than er equal to that allowed by Specification 4.2.2.2 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 i anda,tegttedprovidi rL er between AP POER is osintained between APLE I 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 Fq (a) in.reas , t e .n _ ,or annu t.ie en - and - :

esasurement uncertainty. The gF 11eit i C: 1- J i

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

{

w(a) an

$l80ER

UNIT 1 3/4 2 la Amendment Me ,

I :

.w . . -.---e.-.,.~.,,,-.w.-.. . ._ - . ,. . - -.... - ..

.n,~,....-,,,,,....m.., . . . ___---..--..-,--.-_-.-,.w

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

, ,.. E 013ft!PUT20N TIM!T$

IVevt!LLANCE Rt0UIREMtwts (conting. )

b. _

During lase Loss operation, if the THERMAL PO ApL creased below then the concittens of 4.2.2.3.4 re entering test Lead operation. shall be s ed before 4.2.2.4

' Fg (t) is within its Iteit ty:During g Base Leade Operettenaratne if F

a.

Using the movable incere detectors stor bution obtain a p

b. map at any THERMAL POWER above ND, Apl

, Increasing the measured g F (t) component u on of the 1

c.

sap by 35 to account for manufacturin Verify the requirements of Specification .. 3 2 n2es.

are sat J tad.

Satisfying the fellowine relationship:

$(a)i for P> APL"'

E

[

where:

O (3)isth'sasasuredF(s).

g The qF limit is f en he ts 1 a pec 4.

Measuring %(3) in conjunetten with target erence flus diff

.~. determinetten according to the fe11 swing schedule:

A n*fA 1.

"I Prior to entering SA$t LOAD operettenec-after satis previous 31 EFPS witgthe relative th esintained aheve APL e

2. for the 24 heure prior to aapping, and e.

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

- d(s)

E(a) of over the core height (t) increasing since the previous dot

,- (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)

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

l 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 allowabletotal f1 op)eration i g

Where:

M H p L RATED THLRMAL PUWER

c. Fh = Measured values of Fh obtained by using the movable intore 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 --

APPLICA61LITY: MODE 1. fle.)(,5 W ) N Y8W ACTION:

~ >

i With the combination of RCS total flow rate and R outsjde the region of accept-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 toovethe combination limits, or of RC$ total flow rate and R to within i 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. i 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 !

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

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

c. Identify and correct the cause of the out-of limit condition prior 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 of acceptable and RCS total flow rate cosparison, to be within the region operation:^ -'

following THERMAL POWER 'evels:

_1 - iprior to exceeding the l i

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

- - . . ~ . . . - . . , r , ,.-..,_r_,. _...,,.....,..,,._,,..v~.._,.m.,, _m.....,_.. -_ .. , .

, . _ ~ _ _

s y,

POWER 0!$7t!Buffow LINtis--

i LIMITING CON 0lfl0N FOR OPfuf!0W I act!ON. x (Continued) f' i

1.

A nominal SOE of AATED THEWL POWER, 2.

A noetnal 72 of Raft 0 THERNAL POWER, and

3. j within =4 hoors 4ATED THERMAL of attainin. .reate, than e, et ai to m of 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 4.

~ - "3 t l

,,ier to, an.

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

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 assumed to receatly exist. obtataed value of R obtain65 per Spectfication . , is

[ 2et lei 4.2.3 !

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 1 i -

t 5

l .

I :

i l

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

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

" .f

!1 fever 0!$7R18UTION L! WIT i

\

p _

BASE $

y ,

4 g

_3/4.2.2 and 3/4.2 3 -

4 NucLEnx turMALn Ust Mor chammtL racicaNEAT AND FLUX Q

k' enthalpy the limits on heat flux hot channel factor t

i N4 local powerrise hot channel density and ninteus factor DNOR ensure are e

notthat exceed 1),thed design limi n peak i

LOCAlimit.

criteria the peak fuel clad temperatureand will not

2) in theexceed event of a the 2200 CC$ acceptance

)

I i

as specified in specifications 4.2.2 and 4Each of these is meas only be detersined periodically sufficient to insure that the Iteits are his ma.2.3.

intained periodic Surveillance is provided:

t

a. '

1 w i

Q Control rods inbyamore insertion Offferin single than group move together with rod no indivi D group t.seend posit on. 13 steps, indicated, from the

)

b.

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

%*g c. Q' .

3.1.3.6 are maintateed.The control' rod ...

insertion n

limits of sp h d. i O!FFERENCE, is maintainedPawee, within the limits.Th > ((

h will be maintained within its limits provided

d. above are maintained. :hrough conditio te " traded off" inst As noted on~)egesentetuT,) RC5 flow rate ands g acceptable i ther (i.e., a low measured RC$ flow rat may n ,

s ;

will not be below the design ON64 value.is aise low) to ensure that g the of insertion red THERMAL limits. POWER allows changes in theeradial h' pow N

I m R as calculated less than or equal to H .3 and used integesgsesesR) accounts for Fh '

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 .

,g ' desi nMar 1 mitin DN64. is maintained between the safety analysis liett e DNtt and th I pena ty and transition This coremargin penalty.is more than sufficient to offset any rod bow plant design flexibility. The remaining margin is available for When an F 8% and manufacturing tolerance must be saec.q sessurement is take '

y@ for a full core map taken with the intore detetAn allowance of 55 is appropriate 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. Fg (z) is met. V(t) accounts for the effects of normal opera-(' 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 * ^

') pe r

$pecification 6.9.1.11.

d Ne_cptRR7nqr o._ E f_ omt75

_ _ . . REMT(OLR) when RCS flow rate and are measured, no additional allowances are t

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

%Yl u, i

errors of 2.1% for RCS total f1 :

in detemining the ii.iti ofpEnrate ,nego and 4% for Fh have been allowed for l

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_ .

acceptable region of operation @ieiR)on~n ---' l l 3/4.2.4 OVA 0 RANT POWER TILT RATIO -

g. l l

The cuadrant power tilt ratio limit assures that the radial power distribu- '

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

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

! and linear heat generation rate protection with x y plane power, provites tiltt. DN6 A

I Itmiting F i tilt of 1.025 can be tolerated before the margin for uncertainty in 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 isgreinstated by reducing the maximum 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. #$.

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t.

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

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

, and Resident Inspector. .

P I

l :'

I:

f' I i i

S 1

L t r I

t V

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1 1.*

l l

1' l

~~

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

Core Operating Limits Report

. For V. C. Summor Cycle 5 '

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

u p

g- R= N FAHRTP e 1 (1 + PFAH ' (1-P))

THERMAL POWER where Ps RATED THERMAL POWER F

2.6.1 FAHRTP,.1.56

2. 6.' 2 PFAH = 0 3 I 2.6.3. The Acceptable Operation Region from the combinat. ion L of Reactor Coolant System total flow and R is provided in Figure 14. ;

[

l i-i f

Page 26 of 27

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ML19327A955

Text

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