L-75-209, Response to AEC Questions Re Fplgs Proposed Changes to Technical Specifications

Response to AEC Questions Re Fplgs Proposed Changes to Technical Specifications

ML18227B027
Person / Time
Site:	Turkey Point
Issue date:	04/30/1975
From:	Robert E. Uhrig Florida Power & Light Co
To:	Rusche B Office of Nuclear Reactor Regulation
References
L-75-209
Download: ML18227B027 (15)

Text

NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL

~

(TEMPORARY FORiYI)

CONTROL NO:

FILE'ROM Florida Powex 8 Light Co, Miami, Fla.

Robert E

Uh i DATE OF DOC 4-30-75 DATE R EC'D 5-5-75 LTR TWX RPT TO:

Benard C, Rusche ORIG 1 Signed CC OTHER SENT AEC PDR SE NT'.OCAL P D R CLASS UNCLASS PROPINFO INPUT NO CYS REC'D 1

DOCKET NO:

50>>250 25 DESC R I P T ION:

Ltr, refer. their ltr of 3-11-75, also xefer, our ltr of 4-15-75, concerning ECCS trans the following....

ENCLOSURES Proposed Changes to Tech, Spec,, relative to the ECCS Analysis and fuel design.....

~

(

1 cy. Encl.,~.xecid)

~ PLANT NAME:

Turkey Point 3 6 4

'i FOR ACTION/INFORMATION

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~1 NSIC (BUCHANAN) 1 W. PENNINGTON, Rm E 201 GT 1 ASLB 1

CONSULTANTS

.1 Newton Anderson NEWiMARK/BLUME/AGBABIAN

~/ ~ i OJ 1 PD R.SAN/LA/NY 1 BROOKHAVEN NAT LAB 1 G. ULRIKSON, ORiVL 1 AGMED (RUTH GUSS~)IAiU)

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April 30, 1975 L-75-209 lair. Benard C.

Rusche, Director Office of Nuclear Reactor Regulation

. U.

S. nuclear Regulatory Commission Mashin gton, D.

C.

20555

Dear,

Mr. Rusche:

.TURKEY POXT PLAHT DOCKET NOS.

50-250 and 50-251 PROPOSED CHA'.AGES TO ECH"'ICAL SPECIFICATIONS In the review of our Proposed Changes in Technical Specifi-cations submitted March ll, 1975, your staff submitted several ouestions to us on Ap il 15, 1975, relative to the HCCS analysis and fuel design.

>te are enclosing with this letter th ans~rcrs to those quests.o>>s.

Very truly yours,

./

g'> 'g% rP <<C/

I

~

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Robert E. Uhrig Vice President REII:L"EL:tg I'.nclo..ures

QUES)i'S ID M'!S<".P!'S BPLWZ!: ilG ~ I TU!?!iEY POXNNT UNXT 4

)?L'LOAD Ai' HCCS:? EEK~hLUSTXON On the soconQ anQ third pages of t:he Appendi.x to your proposod amendment t:o your. Oporati>>g lice>>so datod February l0, 1975, you indi.cat:e

-our factors which werc oonsiQered i.n establishi>>g contxol zod insertion limits for Cycle 2 of Unit: 4.

Ploaso furn,ish det:ails on which of those factors were controlling and why.

A.The co>>t:rol rod insertion limits for Cyclo 2 of Unit 4

are conservative based o!3 all four factoxs in establishing theso limits.

At tho ond of cycle,

)naintai))3.ng adequate shut:down n)argin is typically t:ho'ost: limiting factor.

2.

Q - No understand t:hat there appeared to bo substantial Qiffer-ences between predict:od and measureQ control bank worth for Cycle 2 in Unit 3.

Plea..e furnish det.ails as to whet:hoz this is a probl m and it:s potential effect on start.up test:..

and operation of Unit 4.

Nest:i.nghouse has recalculatod BOL control. bank. worth for Unit 3, Cyc3.e 2 based on actual EOL Cyc3.o

l. boron measure-ment:s.

The resu3.t:s of: these calculat.ions indica).~

tha<-

)noasured rod wort!3 i.s within 0

of t:he x evised pzedi.ctions

'and this analysis sho:,. that adecuat:e shutdown margin i available at the end of Cycle 2 for Unit:s 3 and 4.

Xn-depondent calculations, perforn)ed by FPL, aze in ovcellont:

agreement:

with t:he revised Ne t:inghouse results.

Since the same procedure ~;ill be used'y Nestinghou.e fox Unit BOL predictions, we foresee no problem in this area.

3.

Ne have received information for ot:hoz nuclear.

power faci.litios that the partial flux map option in the proposed ECCS Technical Specifications may allow operating conditions for which the DHD analys3s 3s

) ot co1Ap3e1 e Xs th3$ the case for. Tur);oy Point?

Ne have been advised of this situation by Nestinghouse

and, at thoir x'ocomn:endation, we do not int:ond to utilize tho partial flux map option unt:il such tin)e as t:he Dido analysis 3.s con)piete.

Nill the proposed ECCS Technical. Specific.tions result in restricti.on to power level. at any time in the future?

Xf power lovel restrict:ions will result:,

Qescribo t:he magnit:ude anQ Qu).at:ion of uch restrictio)ls.

Ne Qo not: an'cipate any power 3.evol rostriction for now cox'os i)3 tho futuro'

~ ~

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~ I QU):ST10!)S MID MCS)'l)."!)S (Continual) g ilillthe proposed ECCS Technical Specifications affect fuel utili7cation by chang3ng fuel thxough-put?

Xf fuel utili7ation ls affected descl lbe the magnitude of this change.

A Fuel utilization (through-put) is continuou ly bei.ng evaluated from an economi.c fuel management standpoint but v~e do not expect any a feet duo to the px'oposed ECCH Techn3.cc\\1 Speclflcatlons.

6.

Q

.i'3.11 any change ill effluent x'QleasQs 3.osult from the px'0 posed ECCS Technical Specifications?

Xf effluent release are changed, describe the magnitude and composi.tion of the ness relea es.

A None.

DOC1'I;T ".OS, 50-250

~: 50-251

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S>.!7alytica(3.1y justify t!7e IIPX f3.ow <'pl.i.ts across t:ho

<:!;!a3 l.to-int:e.modiato b7 Qak poctru il ~

Describe thc sc; cal.cu3.ations and s):ow t:hat: suf ficiont )IP3: flow is i.njc.ct:od to t:ho rc!actor vossol for: a brcak in an IIVX l ine (i. Q.,

show t hat <ill. IIP i watox is not pumpocl to t:ho brea): ).

Hach of the 'hreo cold leg hi<<)7 pres uze.,afety.injection lin.s connects to one of the t:hzec:

10 i.>>ch accumulator jection lines just upstream of ti!o 10 inch choc): va3ve.

(See PSEiR Figure 6.2-1).

Therefore, a brea);

i.n one of the high pressure safety injection lines would not rosu3.t in a bl.ow-down of the reactor:

coo3.<".nt sy tom and there is no concozn for the zesu3.t:ing prcssure imbalance at t:he dischargo points for tho bro)'en lines versus the intact lines.

ln t:he event thaL a "small brea);" occurs downstream of tho 10 inch check valvo in the low pressure injoction connection to T:he RCS a blowciown of the RCS will. occur.

I!owover, tho pressure in the broken li.ne aT: the point of high pressuxe safety injection will be thc; arne as t:ho zest of thc-. reactor coola>>t; system except fox a mino - adju:tment for pze suzo losses caused by the brc.ak flow through the react;or coolan'.

systom.

Thus for "small breaks" whc.re t:he f3.ow from tho hic,h pressu!.e 1n)ect~ on syst ol(l 1$ 3P(lportant thore xs no 87.g>>3.f 1ca:1 pressuro imbalance at t)1o injection points int:o the BCS

<a!7c'.

th>>s there is no proponc"'c.rance of safoty injc!OLion floe. through Lhe broken line on Lo th(

coAtain.!Qnt f1007:

Xt shou3.cl <<iso bl I!ll"Iltiolled'Lh(1L>>0 cx(7dit is i" cake".A 7.0z uny saZULy i'1jo(" iGA f3.0w il'1to the

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it only for flow t)7rough tho two linos with the highest li.ne rosistance ancl T:he line wiLh the lowest zesi,stance is a<;s(!mad t:o be pumping to the broken line and spil3.ing to the conta.in-mcnt.

The safety injection, line resist:a!7ces for the Turkey Point units we7".e voxifiecl by pze-opera Lional tes'Li!!g 'Lo be i)7 satisfactory agzecmen'ith the analysis.

They demonstrated that ti.e safety injection system woul.d deliver a flo.; to the core greater t:han the flow assumed for the analysis

<<ssum(ing a broken RCS cold lcg and tho worst sing3.e active failuro (i. e. with mini.mum safeguards)

Foz a break whe7:e the 10 i.nch line becomes separated from the RCS and the safoty in lection l.ine is exposed to contai.nmont backp7. essuro a pl Qs ure ililbalance will exist betwee!'1 the discharge.

point!s of tho intact a>>el broken S.X. li.ne duzir-g the RCS blowdow!1.

Such a pressure im)7a3.ance i cor.sidezed in the an<!lysis.

Thc. ar!al.gsis account for thi.s diffc.zcnco in prcssure at the injection points an:l calcu3.aLes t;he corzesponcling S.3:. flow throug). each 3.inc'..

Ilowcver, such a

brea!; is a "large brcak" and blowclown of t:ho reactor cool<!nt sy s i.o!1! is compl et:Qcl in a shox t t:i.me and the z Qactoz c:001 a 1'1t system and tho containmo!!t arc. then at t:).e samo p!:ossuro, t:hus t:Qrmi>>ating the flow ir(ba3.ance that zosu3.tocl from the di,fferont. bac);pro -sure -.

Tho att:ac

'; c!gros dopict tho rc.su3 of

!o analysis for ca.le cons3.uerin~ a sp3.11:l>>g

.3.3.l'le Curve.

l.

Pl.ow deli.vcroc) through

(.he t:wo hi,gh hcacl S.:t.

w3.t)1 t)le hi.qhor flow rosista>>ce.

Plow for wllich crodit coo3.3.>>c3 3.s t,a)co>>.

1 1.1'lc.s xor co'o Curve

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Total flow deli.vercd throug)l all three high hoad safety injoction.l.ines.

Tho difference between the two curv,.

represent."

the flow to tho linc connectocl to tho bro):o>>

IK:S loop (i.e.

tho spilli>>g li.ne flow for. whi.c'.h no credit i.. t:a::Gn) 2.

0 A spuriou.

oponing of JJOVS 860'nQ 86lh (or NOV.. 860B a>>cl 861<:)

at t)1o containment sump would permit contai>>mc.nt pre., uro durinq the injection J)hase of a LOCh to bo exerted on t)1G..water i>> the line from t:he RhST (thereby pr>=.venting flob from iho RNST)

Verify the completo el.ectr ica3 separation (separate cable t:rays, etc. ) is achieved up to the powor supply which i.s common to each of these set

. of valves.

A The power suppli:c.s for t:he blOVs 8605 and B,

and 861k and B

comply with olectri.ca3. train soparation crit:eria.

Val.vos designated to function as part of the "I~" train have their control. cabling and power cabling routed in cable trays, duct.,

co>>Qu3.ts o c. separai:oly 3,0caf OQ from tho. e fol.

B i:rain on suring that any physi.cal c'.amac)e, affecting oi1G circuit will no" affect i.ts du;>>licate.

Thore is no rec)uireme>>t to have further, sepal. at io>> 0f cab 1 3.>>cj t.o ind 1.v3.clua 1 corn poneilt of a givol'l rain anc) thus zhe powol. caDLi>>g lor vcllvt s 860>x a>>Q 8vlZx ar>;: r'l!1

~ the amo caJ)3o t ray and tho power ca)31e fol. Valves 860B and l>6." '-

al e al. 0 run in t he same cable tray.

The cont-.rol cable for these valves is similarly route:Q (i.e. soparation by train only).

3.

0 For a

CD. of 0.4, t:he genori.c 3-loop analysi.s showed a pos'tive core f3.ow bet>>

en 1.0-13 seco>>cl compared to 1"inure 1~i. 3. 2-35 which shows a nogat:ivo core fl.ow during this period...

Re-xun this >>orst:-case >>ith react:or coolanc pumps runninq to confirm thai the expect:ed decrease i>> coro flow afior.

10 seconds (with pumps running) would not clause an i.ncxease in PCT.

A Figure 1.

sho>>>s plots of the core floe~ during blowdown for t):G Doub3.G I".ndod Cold Log BreaJ: with CD = 0.4 for t.wo condit:ions:

1)

The "desi.gn" as umptio>> that t:ho RCS pumps trip at the time of the pipe brea):.

2) Assuming t:hat.thc.

RCS pumps run at 100"..

Speed during blowdo;.'n.

All othor. input as umpti.o>>s wore identical for t:heso case.,

and the resul.ts are that t:he desiqn case (pumps trip) h;ld a'pea.c cl.acl tomporature

?6 I'i.g? or than tho pump'un case.

This confirm..- the re..;ults a>>cl co>>clu..iohs re.!chocl in the go>>c ri" 3 loop so>>sitivity study )xresontcd in PCliP 8336.

"'Applies for. 'J.'ur);ey Point Uni.ts 3

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)i~o) 1'Aa3 ly closed IJOV 86GA and VGG)3 - Xt: Should be confirinc'";

t;)1at the stalin>> Tech Specs require the poorer supply t.o t:hase val.ves t:o bc loc)'cd out.

The circuit: brealccrs for mnt:or operat)cd valves 8GGA and OGG!3 axe loci:ed open at t:heir respect ve 111ot'01". cont'rol centers.

Th>>

valves are administ:ratively conirollcd by p3.ant operat)in<

procedures.

There is no rcquircmcnt: in the Tcc)1nical S)ieci=ica-t)-ons Lhat: spec).f ).ca lly add).ess 3 oc)i3.n<3 chcsc valves c 3 osec

~

9

)iorrnally open NOU 862K and

?lOV 8G28 Xt shou3.d he conf ir.",:.d t:hat:

t:he station Tech Specs require t:he poli'cr supply t:o t:);use va3.ves be 3.ockcd out:.

A The e valves are cont:rolled a. discu sed above and have no specific Tech Spec requirement.

DOCKET NOS.

50-250 (<:.50-?5l

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