ML20005D723

Amend 40 to Applications for Ols,Responding to Listed Concerns as Discussed W/Reviewers on 720809

ML20005D723
Person / Time
Site:	Browns Ferry
Issue date:	08/22/1972
From:	Gilleland J TENNESSEE VALLEY AUTHORITY
To:	Oleary J US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20005D724	List: ML20005D723 ML20005D755
References
AOOL-720822, NUDOCS 8912140358
Download: ML20005D723 (7)

Text

TENNESSEE V LEY AUTHORITY g yd CHATTANOOGA. TC :ArsstE n 4os

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August 22, 1972

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L AUG o.',19725 2 t.s,,yyfo g w ww a

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966., get Je Mr. John F. O' Leary, Director A

Directorate of Licensing g n 7 ge) gy..(,3 United States Atoni: Energy Co: mission

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Dear Mr. O' Leary:

In the Matter of the Applications of )

Docket Nos. 50-259 Tennessee Valley Authority

)

50-260 50-296 Submitted herewith is A=endment h0 to the TVA applications for units 1, 2, aqd 3 of the Browns Ferry Euclear Plant.

Amendment h0 censists of resp:nses to the folleving concerns

~

as discussed with AIC reviewers on Angust 9,1972.

1.

De seisric qualification of the spent fuel pool cooling and cleanup system.

2.

he standby a.c. power syster for multiunit operation.

(This A end:ent 50 raterie.1 cens:itutes cur ret;cuse

.o the multinnit portion of Mr. Roger S. Boyd's June 27, 1972, letter. )

3.

Se syste: :: pressuri::

a -u centrcl root -ith filtered air in it.e e ce:.t of an s.ccident.

h.

The flood pnte::icn plan.

5.

The possibili y or failures in ncn-Class I equipment flooding out Class I equiptent.

('"his Arendment h0 raterial con-stitutec cur resp : se to ".r.

?ccer S. Boyd's letter of Au6ust l',1:-72, x.02rni:.6 a circulating water line failu e at Quad Ci.i:-s u.it 1. '

6.

ne rust in the Ir:. Ferry :.uclere Plant unit 1 torus.

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8912140358 720022 PDR ADOCK 05000296 w

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l Mr. John F. q'I,eary August 22, 1972 s

7.

Unit 1 preoperational reactor vessel vihre'..on mocitoring.

8.

Fuel design. !

Instructions for incorporating the revised material into the FSAR are included with the amendment. -

Very truly yours,

~

m J. E. Gilleland Assistant to the Manager of PNer i

s C

Subscribed me this h,and sworn to befcre day of

',e.,-1972

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Notary Pidlic W Cocnission Expires 2 ' - 7 2-Enclesure e

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BFNP-h0 f

00!!TF.flTG OF AM)3DMENT 40 i

Amendment h0 to the TVA applications for Browns Ferry Juclear Plant unite 1, 2,.and' 3 is submitted to provide additional information as requested by the regulatory staff in the' August 9,1972, meeting.

\\

Instructions for Inserting Amendment h0

)

l-The_ following instructional information and check list is furnished to help L

. you insert Amendment Kumber 40 into the Browns Ferry fiuclear Plknt FSAR.

i Rince in most cases the original PSAR contains infonnation printed on both l

i niden of a sheet of loose lear paner, a new sheet is furnished to replace I

. sheets:containing cuperseded material. As a result, the front or back of

-s'.nheet may contain inforination that is merely reprinted rather than changed.

H J0nly parcs which contain amended (i.e., added, deleted, or revised) infor-mation' are identified with the cipher 'EFNP-h0" at the top of the page.

l Further, where amended information is new or revised, a vertical bar with y _the number "h0" has been inscribed adjacent to the information in the' out-l side margin of the page.

i

. Discard the old sheets and insert the new sheets, as listed below. Keep these instructions in the front of Volume I to serve as a record of changen, l' _ Appendix B.5A is to be inserted.at the end of Section B.S.

I Discard Insert l

Old. Theet Scw Gheet I

(Front /Pach )

(Front /Back )

3

3. f,-7/ 3./.-U 3.f -T/1.(>-3

3. f>-9/ 3.4-10 3.6-9/3.6-1o L

Appendix 8.5A l

Fig. 10.12-P Fig. 10.12-2 l

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I e-iodine pveining it<tterenuat eiwauoni. Ibe esisnaied tempesature. Nornial plant operetw a condm ted at ates et. curacy in determming thrt.nold floaes weliition dewi wis es of these pe anu* ten suth "et reactor transients t

r petiWl ent+ comp..lg a ntia) o et thetu h!!fil W,

' ef e e tl AW'n (l'# e J'Cr J+l PP" t r #

j.tastit prisOnt el

' Int. h4psV ta 6 f.ed:'let*4 b lerJ 10 0 0 L."1 sollislety Iht 'eJttDI p' i'itd ' n"t s)?

'l'@ his 10 sntPe e

evenist ' henOn nihr ut r 3ael ein W Or' e

0'c co o aihrint '5,i enn.at coal te.msnm t-yt.op a viam. The leve to lunwtv f t 1 i.atm 'u. <

.ow in." non..,

ee:.m v css t u w w..,

.r. t.b b e sotem P,nvt..b i etc.<r;<,'bw.H daos n en1twown.:n.ure ia qta m re+ ugh 19 in rve e t it +

it durin disturtiarne vi val ' trarn.io.-ution in auo; % : d u.o t he eriotive "Om i et W loa: 04maif i h. W - mtnaly curve used st21: sty, of 4ny-Qiven reactue uth s espc. t to tmwet in the it&ttivity escu slut o'..il m 5 shows) m Figuee distenaise ef fes ts de.iends oi. we irngth to o a.netel J b 11 fee strr). reas ttvos hi 'ounation of these -

(l!D: ti.t.fi Of H o. i c,. e Shuwei e < igaie 3 t'.11 is the atino. rn,

,,wational n oosm on n,

i in 6.spu e 3 ti Ib -

selab.e st.itithly U the esJial, sa w.,thal, and draal pnme-Almerme peiaum.ot uetwcv ts.re a.Ouated in Section clWiti:uncns os e funcien of Linutics Eo.ce 3 011 148. "Pla

• Saf ety Analy sa " No f.e >;enunge e rsalts froni di h.s that antal dad mmuth,H ovAaliots hwe a mt.ch any abnmal opeshonni trent :nt.

t h@N pict.abany of occurrence that radial oscillations f or l hta wecif.ed red uitnetimet v _t'Kes end the rod the reactor. Thu post only gives enformation rega' din 31 the wea th it:.miniter rna m ton n.d we a' eteeptdole low telsthe sieh8hty of the various po ur distt:tsuttors f or o values tr. %ninine the ron>>.quence c' e r e:tivity accident r

given core The cilect of the flux Je power level on the At any wiie<1 tractor < tote t% rnthalpies for tod stsbhv ol the as:e' power distobvenn es shtmo in figure removal a:cidents so'y thret.dy mth 'cd vvorths, it is the 3 6 I? 1 hoe d.ia which e.e e odop of tram tellotchef cen er,tt.eny c nich is the w.nessue of the inch.m 'he efiest ;l void D empiis t in the cua* du tclien.

• urw.14ve7ts of a redc u~it y ;.t r e e ' t ev enium dioude i

E ngure 3 612 shoos that the tNotts is we'l ddmped, anti

.apor presuf e dato of A(k erhu't0 s o tnt! in'espretation.lII that tsere n n i ntui of 4 hetweet. the threshold power

+ f all the s.a:lanic tests m the 1 W P S.uhty of Argunne COdll.( efit tfi whv ' ite%n ow.90n.t nb would I c trul i :ed

'id t :(, riel ' ab0ldto'y Md!C o le' inst wdden luel pin a

t end 6 t tabulent> rones corthc.e u Of the end of the artuse t%old a ab ni 48 As

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'obe t ; e r.,,- erne, ts f ry :n, piary en g int..?.1 l dJ (,il gr'

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weep -LC at t.a 'e c;':.'.rCO el f ee t. ~ hi f l'ECS 10 d i gt.t intet kr e in the retor.ance recutrcn Qlsetal tell temoval escursion analysis isom the

} ulstitn re; 3iive. t c t he therm ne'a-4 deem flum level endicates that peak fuel enthalpies of

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j n- } ul P *.

)tal/gm (fully molten uteruum deonicei ressts from too

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derefore, lisal) and removal rates of 5 f tssec 1 hew.novses atso t'.

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• r n r v i t h the e that for encorsions init ia rnt t'um ova sereis

temponding to 10% power, the ma a imum possib

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'deel tod worth. O CM ak. 6 inwiticient to c ause peak helpies St 28Qtagm The design bas.s rod crop t

f actor C f t en ident es evolvated es Sec tion 14, " Plant Safety

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g.. q j m;

a s-2 ' f fe N t.'

energief l

$ ysis l'III*U' iE 1i m trnEw T

. Preplanned tod patterns enforced by the rod worth

,, 2, ; r.*

simiter testrici roe worths to icis than 0 01.',k.

.iough larger values are acceptable within W ;5>0 caugm

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e-*

cient at tero m

h worth high enough to produce peak entoaiov of s

leal /gm of the rod were remo ed at 5 it sec Planned rod q, ure ir E i-m ;y.ett nega,ive

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terns and rod wortn eninim uer. therefore, are not

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,,g ;y ;7egented in ded to testrict control roo patterrst to limit the

r.. ir.;

:.ry data fcr a siL64e

. w mje wat sequences of ibe rod drop accioent v.nen thc reactor is atte i '

't?-

d Li e c re ut ing borer.-cteel ive 10% powei-cariai t..r..

at.pe:.t a t i e r..

The f olltv-ing are

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