ML20024B421

Forwards B&W Input to Rept to NRC Concerning 770924 Depressurization Event at Davis Besse.Input Includes Description of Event,Evaluation of Reactor Coolant Components & Evalution of Fuel

ML20024B421
Person / Time
Site:	Crane, Davis Besse
Issue date:	11/01/1977
From:	Lauer J, Lazar A BABCOCK & WILCOX CO.
To:	Doreck C TOLEDO EDISON CO.
References
TASK-03, TASK-07, TASK-3, TASK-7, TASK-GB GPU-2507, NUDOCS 8307080694
Download: ML20024B421 (31)

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November 1, 1977 ww w s u sut J. P. Jones BWT-1SE3 9

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q E. I ane File: T1.2/123 f

D. L. Rice

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J. D. Lenara:en w/a J. C. Leeds

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!!r. C. R. Demet D. J. Oc!.c C. ol r.

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!;uclear Projtet Engineer-E. C..pMc

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Pc-er Engirering & C:nst-ction

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Toledo, Ohio 43552 J

330 f*adisen Avenue q

Subject:

Toledo Edison Cormany '

d REFORT ON DEPRESSURIZATIO:: EVEhT

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Davis-Besse Unit 1

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B&W Reference USS,14

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Dear fir. Doreck:

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By telecen of October 10, you have requested 85:1 input for a rescrt to NRC regarding the deoressurization event of Septecter 24 The NRC exit interview notes dated Octeter 7 su=arized the necessary content of the re: ort. B&ti is providing write-u:s J

'in t*:e-follcuing areas in order to subs.antiate the cenclusions of CUT-1573 and B;.7-1579 dated Octcber 5 and 7:

7.ad

.i A.

Description of the event

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B.

Evaluation of the react 6r coolant c:rponents

"...T C.

Evaluation, of RC pu=ps,

.~]

2 D.

Evaluation of the fuel 0

In order to ex;edite submittal of ycur report, we are sending Sections A, C and D at this tire, as agreed in our teleccri of Octeter 24 We ex;cet to foniarc Section 3 by

!!avec:er 7, and,we will try to in:pr. e on this date.

Section A describes the to:uen:e of events as recenstructed from cercuter alar:n print-out, reactir.atar ::c :. and :entrol room recorders (Attach =ent A.1).

We have attacned pertirent rec:rcer c arts of T RC pressu e, pressuri:er level (Attaca.ecnts A2, A3 and A4) and reacti.ater alc:s of Ein,let ten::erature, RCS f1cu in each loca, RC pressure, presstri:er tevel, anc ustar level and outlet pressure of each steam generator (Attach-cents A5 througn A12).

s Section 3 will include evaluatiens of stresses in the pressure boundary, the depressuri:a.

tion transient, boiling the SG dry, jet impingement or the SG, and,effect upon fatigue life-q S:

CONFIDENT!A!-

COUN m ONi.Y

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Noventer 1,1977 BisT-1589 E

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Section C explains the evaluation which was perfomed to vertfy that there was no-I significant datage to RC pu a bearings, seals, or it:::ellers (attachaent C1).

transient as it affected the pts::ps is su iarized in Atcach ent C2.

The

-]

Attachtrent C3 defines the instrLantation and operational checks acolied to the pu:ps.

The results of the operational checks are tabulated in At.tachment C4.

i Sectici D evaluates the effect upon the core to detemine (1) whether ' steam was 4

produced in the core (2) the raximura tr.ternal fuel rod pressure, and (3) whether t

maxlem lift force exceeded the limit (Attachment D.1).

attached fer reference Attach:ents D.2 through D.6.

Reactimeter plots are l

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Very truly your's,

.v A. H. Lazar f

.,n Senior Proje Manager

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A. Lauer

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4 The event' started at time 21:34:20 on Septerber 24, 1977. The plant was The turbi'e had been shutdown earlier in the

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in Mode 1 with Power (WT) = 263.

c evening to repair a leak in the main steam line ae.an instrument connection At this time between the turbine.stop valves and the high pressu're turbine.

a half trip of the Steam and Feedvater Rupture Control Systen (STROS) was initiated Wis trip shut the startup feedwater valve to #2 stea= generator f

by an unknown cause.

and stopped all feedvater to this generacor (because of the low power level the r.sta feedwater block valve was already shut, isolatir.g tne main feedu. iter e ntrol valve).

Ecfore the The lov level alarn was reached in f 2 steam generator ac 21:34:4&.

j operator could identify and co+ rect the problem. the lov level in #2 steam severator

. produced a full trip of the 57%3. This trip sixt the r.ain stcan isclation valver a

STI CS and feedvater isolation valvas On both stean unsettors (cir.e 21:??:13).

j The nuteer cne pc ; v *fe med as in-

x. lao startel both auxCisry. feedwater pumps.

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tended, however, numbe: no auxiliary feedvater punp n-Iy u:.e up u 2600 KP.M. in -

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srfffclent to feed its stein geccator (f2).

'the loss of feedvater, first co cue and then both ster Seacr2 tors, caused an j

e:aur.e. which r esulted in an incress.: in pensuri:ce bererse in primary water te=r At 2215 PSIG the pressardser e1cetro-3 1

le7el acJ thus reactor cochr.t systaa 3.ressure.

AC seconJs. 'it ta:elved y

During the v.at mat.f c relief valve received u opu sinal.After one of those rignals the valse erv @

t mine dif ferene open and c.1vse signals, This providae a c'.stitiuous 24*-nert path frcs the pressurizarr t* the 4xash g

open.

W.n pressurizer levd got to 290", tne operator aanually tri; pac' che r43ctot (t m 11:36:#). Er ergy escardt*g from the electrocatic relief valve aus. t.hree wain

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sceta relief ualves.:sused a rapid cooldow:s od depressurinatida of the seaa:ar colant 21:37:37) ialtiating i

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Enctor coclant systa:n prasaure dripsed to 16P3 PSIG (ti.e I

2his starteo high pressure icjection and NT*w- - 1

.J th< h!hy 7entures Actus :ica Syste:s WAS).

cluer; nusuc.us coatainment isolation valves: ir.<!udieg t:.e quench tuk croAlt.g liess, h

TI th e the 41 ectr'omatic reitef v+1ve still open and coolirC vater isolated t4 vj'

40) relieving waterhtraa n t:

quench tank, t% quench tank tupture disc ruttured (ti=e 21:This diacharfe damaged a ne 4

to.the contairment buildicg.

The secam tcre off deflected of f this duct and directed' onto #2 steam generator.

approximately a 10' high x 20' cirenaferential section of insulation from A2 see.us The paint from the then exposed area of the steam Scncestor was blasted i

generator.

M-at also resulted in two fire alar: s (one near RCP ?-2 away. The steam in the cont l

and one naar the pressurizer) ad a single channel RPS trip on hit! reactor buildins 3

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pressure (4 PSIC).

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When the main steam relief valves ressated the decrease in ' reactor coolant system f

j temperature stopped and the high pressure injection pumps statted to raise pressurizer (The level. At time 21:40:34 the operator stopped the high pressur e injection pu=ps. -

opetators had been heavily involved before this time in regnir tsg seal injection flov This flow had been stopped by the SFAS scruation. By to the reactor coolant pumps.

40 the appropriate SFAS signals had been overriden and r.ormal flows restored to Reactor coolant system pressure cortinued to decrease until

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21:39:

the seals of the ptmps).

saturation pressure was reached and steam began to form in the RCS (approximate time the pressurizer and pressurizer level a

21:42). This caused an insurge of water into During this level increase the operstor, seeing went off sesle high at 320 inches.

stopped

. average resctor coolant system temperature and pressurizer level increasing 1

one reactor coolant pump in each loop (time 21:43:11).

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"Due to decreasing presmure in f2 ste.m generator, the SFp.CS s 48:33. This slerted the opeator to H

low pressure block permit signal at time 21:

He blocked the low pressure L

the lov level and f eed condition of #2 steam generator.

I 49:25), took =snual centrol of the speed of !2 r.uxiliary feedvater trip (tize 21:

The operator saw the rapid addition of pu=p and fed f2 generator (ti=e 21:50).

system temperature and stopped the

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cold feedwater dropping the reactor coolant g

a f eedvater addition to this generator.

Y the block valve for the electromatic At approxic.stely 21:55 the operstor shut

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relief valve en the pressurizer and stopped the venting of the reactor coolant systen to the quench tar.a.

Aa. 22:05 pressurizer level case back on scale..At 22:13 the q

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eperator start'ed a second cakeup pu=p to try and stop the pressurizer level decrease.

.1 71.is additional cold water started the rea: tor coolant syste= o s a slow dects:as.!ng Le lov level interlock f

temperature transient. At 22:17 pressuriser IcVel reached E

At 22:23 the operstar seseted s high pressure l

med cut off the' press c'tter he ers.the decreising pressurizer Icvci.

injection ;ucp to try had stop J

j Tw lesel and pressure sa #2 steam &ca.erster sgain decressed te the refst tere

-d The operator again bloc %ed the r

the *JIILS gave a la.w pressure block pamit sirsal. speed costrol of its auxiliary feed.*

l trip ar.d, c: rough e=mmt l

lewel an( prenure is #2 steam senerator bine 22:2.D.

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Mith pressutiser level vell en its vsy to recovering.the operster stepped the 44).

At time 22:31 he restcred KC makeup hi,,h pressure hjection p.=p (tis.e 22:27:This strep;s t the slow decreasing RC te.perature cra rstent ilow tc norual.

centrol m1 the plant was ar time 12.15.

All piant yara=ccars were now fully unde.

j hrought to a steady stats enndition and a nor=al plant coo *doctr started.

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RC ;wps j

As a result of the Septecter 24 abnormal syste, transient', the reactor coolant i

pures experienced the conditions outlined in Attachrent C.2.

In order to deconstrate that there was no serious darnage to the pu as, a series of ocerational checks were perfomed as outlined in Attach.ent C.3.

The results of'the

{

operationa' enecks are described in Attad.c:ent C.4 i

Ba'J has reviewed the results of the ocerational cFecks a6 d concivded that no l

detectable damage has occurred to tne puro cor.ponents. E finds t.' 2 pu c! ts be serviceasle f'ar sustained full operatiorial conditions with ro it.raciate requirement for caintenance.

1 It should be noted ths?. a step iacrease in vertical vibration of 2 2 pe-o was observed curing the initial low pressure checkout r.ms.

This indtcation wes later assessed to be sourious instrurent roise as a res it of a loose conrectar on

+

J an instr. rent lire. Af ter the connector w'as tightened, vertical vibration 5 remainwd i

tess tnar. one quarter til peak-to-peak an:plitrda.

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.L ATTAC!ctC;T C.2

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h I

l RC Pl#75 i.'

d, SEPTEP.3ER 24 TRANSIENT S DB-1 L:]

• ._':-3

y. s

-r;

j. 2 All four RC pumps were subjected to the fo11 ming:

p-j v5 y-0:00 Reactor trip W

t.

1:10 SFAS trip d

1:12 Seal return valves shut for 1:16 i

1:13 Seal injection valves shut for li32 i

al.1 four pte:as o;:erated for 1:15 with no seal 9

tajection and no sect return flow during an RCS M...

de-pressurization.

2:28 Sea 7 retum velves open kj 5 6:00 Steam formation P.]

.i

,J 3:05 Seal injecticn valves open.

M' pressure oscillating near P for 9.30 to 45 minutes p,.4,

.9 J

25:G7 Total seal injection flow icw 41argAT

,t g?

I' pg -3.t r

- 3 7:45 Shaft stcpped (b

1 7:04 Fume tripped' i

36:07 Atcut one r.inute of lw ceal injection flow (neai 2 gpm)

J hh flow icbalant.e s'tarved seal injection

't p'i

'9-f j,'

-J 36:30 Seal retura valve shut s

r' rd.

1:12:55 Stand::ipe level high

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1:17:07 Standpipe level nomal F.4

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Pung 2 2:

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4:20 High vibratico '~

~

1 7:04 Purm ?. ripped gf y _d 35:07 Lost seal injection for about one minute t2 t

36:22 Teil return valve shut for about 40 seconds E

t a

t.a e

s E.

q 4

?

4 1

4

.j F

i f

E..

I a

r l

-,; - x.. -

~

I,j 3 pj l

j

-> 5O5

(

k =

.a..-.__.--

,m..

ev

--g

.-e-

--n--e.- -, _

m w

-e'

=

. - -.. ~ - - -.. "

~. _.. _.

_y

^ ~- +--

1_

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

cuen ar w.=u c=.m=

.y-Il g

r.

Ptl.'f0CZ:

i T:

-)

A :c :; whether maintencace is required of RO pu=ps as a resul* of ab: cmd E-

)

i.rcacient of 9/2h/7T. Opere..icn21 chech: vill be required to de:.rr.:trate f_-

6ft sad that no cicnifices'. d:.ncre has oc: 2rred.o the pu: p Licri :::, ch:

f vill be perfor=ed in !bde $ due to c;.craticasl i

j seals. Tir:t series of te t:

I::

restrictions by ;*~'O.

Lv.er on operatio.c2. check: vill be perfor=al in !%de i

g T. ch pt_..p vill be operated individ22117 for :. ders.tio:: not *o c cced 3,

rc: sin within ll=it:

.g Q'

~{

ten (10) =1: rates, p-o ridir: all defined paraneter:

established in tt.is preced:: e.

~

j Operation:1 seque sce vill 'ce as 'fc11cv::

4 e

T:r ite valaes

[

(1. lin pumps vill be ctarted and p.=.y :h200 ret =ted by 1::d.

"l

.#ElI; an r.st to cz:eed IOC *t-lbs.

A steth ::cepe '-111 to p.-orid:d to detert k,;ig l

f.*.* sic he: bee = sati:-

a:7 u:: u:1 :nen:.mical noises is sa:1 houni ; cres.

i fa co.-ily sc ;.leted as ic/3/T7).

b.]

)

2. Mode 5 tettir.c 225.;.sfg.

t

,i O.;$

Instrsr::estation Required see a.ttacheri (14) 9 2.1 i

2.2 ce=72* r Data -

..j P:ints:t *.s sp-cizl s -- y trend fer ::ninc ECP eve:/

k: ::1 17 scec.it.

t

.,. ;, A-55 N<

g

~,A 2.2 Follovi.:c 11-its shall act be exceeded:

Yi d

g}j T".

A.

shaft vibrrtion - 15 tills Peah t.2 peab

v.,.

Tot:1 sta=tpipe le:Asce (ep :er seal lezi.:ce) plu: seal rh urs should t'

7. :

L

"].

not exceedC.6 cg.

If, A ing the te:t this li=it ': c=: ceded, t".e In no case v111 te 21 seti j

.]

pos:ibility exists of r.n open se21.

If this li=it it. er.:ecded.

1; d

leakace be allcwed to exceed 1.$ g;=.

't maintenznce vill.be required bef=re fur:ter, ; o;cratics.

-]

g.;..

i C.

All other ner=si plc.at li:it: sad 3.sr.:*icss prevail.

f,

.-a i

.[

2. 16 Sequence cf Operation:

t.

S

/

A.

Secure standpipe flush.

u

,c.

m

.Estchlish sesl is,lec* ion is accordance with plant operating procedure.

3.

E y

Measure end recerd =tandpipe 1e:k:ge==d return flow, ceufirm that C.

.1 total leakage li=1ts are not excucted.

~

j i

'A Vcatien betscen constr-1 recs cmd pcreonnel ststioned

/

D.

As:ure c L

at ECP standpipe leskece drain 1124.

s C

1:

..1 E.

countacn.n frem lo to 0

{

Ctart = trip c! srt recorders at Lidt.oced; 3Lart Ecactor Coci:utt P :=s 0-2 !" -t

. rd:usec with pl: t op. proceJuria.

[

.i 8

After cpprox. 11 rec., reduce : -8:

Sart. = peed.

.."b

.x *,.. m..

.= c.

e E

• b.oq3][351C t

i i

r r

L i--_,----,

p

--.-p p

y.

1

_n.

= ' 'A Q'

x-y, w p ep fpr two (2) uisuti= unic:: cy above ll=3ts are excecced.

Duts tg.ca vill be a::e::cd by Etl.t n$d D-J reprencntatives.

C.

L.

~

n. Toller.tinc u:ces:r.ent of dsts, pte.p r:y be run for 2n additiond fi re (5)

L' i

minutes to allow fcr venti c proc: dure requirerwn*.

[.

i. - J I.

Follow aboa.e zee.uence on 2-1,1-2 and 1-1.

k j A::ese: ent of this dats vill deterr_ise whether c:r/ ceinten=nce is yg J.

kile.ed.

required before hiche: pressure c; crc ica 10

[...

.:p/N44X.

.. -* 1;e - e -<*-u hm-

- i nw test vill be r:peated with syste:s prc. Tire ht i--ette

.s..

g; j 4

3 l

is c.::P att

-].

before final deterr.i.utics on condition of t.5e p:::p:

g..

s }j p.

1

- 9 4

E.

.i 1

I

'['.*

w 4

'Y M.I1'

.{

LC/5)Yi

.)

f.I.'. 1, p

a 4'

e

,. 1 a

n..

b b',~ i 9

.i 4..j d

g.

aa C

.l

.2..

e

.I

'y W,

3 p-e i

r

,.r

.e

4 l

• -).

h

f. A 1

1.-

n s s

- i..

'g y

L d

=

L 1

.q r

E b

q r

=

P E

• q i.

T 6

e ss 6

1 e

. 1 k

o

[

/.

,r Y.

,-g-.g.,

<g-'

"'a

~ ~ '

.' ' _

• Y.

e

'T-_

_m L.

mmm

$. }1D I,,

1 l

t

.. _ J o )

1 3

I

?

• - ~ - - - - - - ~ ~ - -

f

,. _ _ y.

..:.=_

-L -

1 -

g-;

~: -?

, --a

~

U" j l 2

7 ny 19.., W E GC<G N #.., "' t'**

W*'

d d

I n

r 4

n12. four Pu=ps.

[

1.

ppper ed lever caw F...,2 l

ll fC M'*

,e

.'P ra*.ic-Pmbec - a e

2.

Both horizon.L..

1 1,

.4.

3. kT Oyr,tt Prc xre er =:tica. presc e.

7

'5 1

Vertie:d J.r:be c. 7 2 m.

s

?

1

.~,

Standpipe less ; VM i. :C1 ::cd.:4 ::- u-ed t.: ring tae test,

.A, o

I I'

5.

.s I

trrA rsecrder ~1ccated

-3 All or above saculd be ree:rdt.d on su O chac.c::

1 f."CL' l

ila th: cester.1 rce:.

,a h

J

.1

'=

f.;

v.-..

e-(

' J..

3 m

r v

Jr 3n y c

.4-d g4*

4u 1

I 3"

7 s

n.,

.J 1,

')

4 l

4 i

I i

d

.I y

e N

Jd 84

'1 1

e%

i 4

1ej 9

• t

.g L*

[! ncLOCS

~,

5 1

.C I

P b

- -n. -

..C.

.... w.

m..

- a

~

W nhh r h_corL3[3I j

,_, or a c7 w.::::a catj=.paeS gi feu-peseter Coolant $=;s were run on 10/5/77, per the attaded Proc'ir'.

vish the folie.-ing results- -

j RC> 2-2 10 /'/7 .: t (2 ~10 1 1

'rd Seal leaksre 7 0:

<

• r. *' -

Sysr.es pn ssure 225 ; sis

,,a ye,,f, 2nd Seal cavity pressure 165 psig 3rd S,el cavity ;nss=re 123.9 psic Kari:ostal V.truics 5 + 7.5 til15 Vertiez1 ribratica.25 si.1Ls e f" r.ic"+ '

'Sr spte= vent.1:.

'l

~

.. i-

.3 - w b 1M. tt? Pit:0 V3 S FC Aner the tvc cinute :

De In '.? vaa r,un eg,,1= c!. 0 c. -.-

.2.. -"~C.. L (-

ust 33 ece:e.s tefere see m vu shtaa. '"

• 2' i

.._,e

.d. -

,.8 a n. ic:. u sn.,,.

4 5 a b, L,y- --

t bratics to 2.5 r.O.1E.

7,,;1cy.

c-a -3 y-. e 1* 1:.r-e e.se d,, <.r. _m,.

cheche.t this @ene==nen.

i

.)

-s vere sua cre. a....,--_-...utes*. e: 2-2 1

e# cut 5.s ec.2..ae.ex.

n 4

..~.

1enger -c3.tm,4.g axe p p.,

c e

,,,,,,,.s s. ed M,.25 =i m f'r

-- ve,,,,,,E, 7.is 5i1' CC ~ ih

• M h ,, ",-

3 vu m.alo:- for 13

!. :r.es.

the tnttre run.

heut up.

=

A 5

pi-r p-1 '

t

. ]'

^'.. -

i P L1 i 3-I !.esi leala68 j <A " -

Cyst h 7 ms e 2 PSis 3,,gy 2 ;;eg

=d Scal'cevit7 Iress=n 132 psit y

e 3ri 3eal cavity presens T3 pri p

Ecrizontal vibratica 5 7.] m2h,C '

I 8

s

+

d BC' I '

P 3rd Se u leata

• PLS

<*h @

Systea pressure 225 psis,,

gun giey.

,,s,..,

,a 3

2=d Seal cavit7 Tress== ~ "

3rd Seal cavit7 press =e E3 Psig Ecrimestal vibratics 5 - T.5 =i'.ls r.

2 RCS 1-1 3rd Seal leaksge plus

< A gy:a Systes pressure 205 M ',*_...i i--.

ntur: fiev 2nd Seal cavity press =re 3rd Sesi cavit*/ 7;ess=:e w9.u~~. s< =-

a Ecri ectal vibrati: 5 - 7.5 111s

.c e.

, el}- -

. t e

J.

0 e"

___,e.g.r--7.-

N pQ

..u-F

\\

g a.-"

.M,%

. l 1.0 D

-l ' 5 I }

P I

b k

I w

1

~~

l

~.

.=

~ _

r-f 18 Q.~l D'

}

I f

d a

he apparent discrepancy on seal cavity pressures en 1-1 and 1-2 was checked

':he cn 10/6/77 by installing pressure gauges at the pressure trans=itters.

gauges read as fo11cus:

1-1:

a;

[

Isle 2nd cavity 4

i j

111-3rd cavity a

)

]

1-2:

1Bk-2nd cavity

~

.i 112 3rd cavity 7.=

Se rea.iings indicate tha seale are stagn; ;-: erW Fased on the a3cve perfer=r.nce. 3&*J sees ;v., ce=ce-. ehJ th vocid just10/ ainten-s:g:e at this !!:ne.

s I

Pcther Testir.g ta be Cons:

l l

1..During hestep,.ccatset 3FJ vhowver TECO plats to start a>RCP, so ad4tional i

data can he tak.en at E4W s diseveticzt.

~~

2.

At rystes prasu~e > 1300 psis. 3 pu=;s :-- *ng, cats. vi;.1 de taken m i

e all fou. pu=ps.,

T a

& e g

4 j

w

.c

'd a

J

..5 3i C:"E:=1f a

l 1D/7/77 1

b 4

J i

4

-4 J

i 5

)

4:

/.

_Me

' 5If d Eq3 L

r I

6 J

L 4

r e

L

~

w

-.-----a

.w-

---o m

.. ya o z.

, _- n_

j g ;Q

u.,,. -

r j

e J'

m S;/cs 07 C:-2 KC';:* cT.ET.A0 TOR CCCL*:"' PfH?S: 10/13/T7 a

. p.I u

I.-

~

All fs=r.90 P..=;: have beer. run at syste pressure greater *.har.1300 psi.

_lj 7

q BC P =;s 2-1 4...

2-2 hate cc..tir.ued to run fres the isitial cold pu=p starts.

Belcre is a :fpical lime of data frc= esch pu:p.

t,;

2 e

y.

r. j 4

RCP 2-1

.)

b ICC psig y

~

syste.s Pressure 2nd Sea'. Cavity Pressee - IC3h psig F

a 4

3ril 3esi Cavity Pn-ssu.m - 500 psig,,

I i

Toriaccts.1 Tibntica - 3 mils 4

[lp:

4 J

3 mu Systes Presarn 1650 psig

.J 2=6 34at (***dty Press.,:1. - 1G75 - ic g

.j

,rd "eni Cx.r.t;- Pnssc:-t - Sf.3 p'. y fj Ka.tt:c.stal ViW i*ic= - 3." si'.a fj

.d

.,f Ci

't hb j

RCP 1-1 M

q Syre.:s y m su e -

1CSC rsia C-j l

Nd Se 1 CArit7 ?resst:n - 1006 Psig

[j J

3rc neal C.sn 7 ? v.ss. s -

5*+0 ;sig t

3 Ecrirnstai Vitra !.a le nils,

b-e q:

..g t

• e l

g

.Ff..;? I-f..

)

Cl,"$.c.t. Pr2ssue = 18$6 ;5dC h'f '

i 2nd Sesi Cav'.::* Fr.sw fs - 920 psig fj

)

3rr Seal Ca?ity Press :. s - 523 ;.d5

+

,h P.orize..tal Vib-stien

':.12.s

.-c

. c_

1:

Based on the above data. 3W feels that all four pu=os are in good operating J

i:

ennattien and require ::tning more at this ti:ne chas periodic monitorir.g.

c.

?

J.

t 1

m d

e h

EIN 10/13/77 r

I y

a 1

~

p a

1

+

/,

i

/

=

w-L*

b me

~l

]O h

.C

~

I i

m m..___.,-

V

.: sand CS.1 CORE A'lALYSIS OF SEPTEiGER 24 DEPRESSt'RIZATI0ft EVEffT A more detailed analysis was done to assess core therr.31 cenditions during the Se 1

Core conditions were analyzed to (1)

-h, 24 depressurizaticn event at Davis-Besse 1.

determine if steam was produced in the core, (2) cetemine the r.axi: um inte-nal.

rod pressure during the transient, and (3) detemine if maxir:um lif t force exceeded

]L the limit.

.d" C' ORE C00LAtlT CDflDITIO!!S Attachment D.2 st.o.es transient thermal conditions as monitored by the reactir:eter.

Ti.e t,vstec pressure is r:eesured at the pressure tap, which is accruxicately 65 fe Th'e RC pressure at the. top of the cort is ancruximately

-q above tne top of' tne dore.'

50 psi t."gh.n than the nesscrea pressure because of unrecover:ble and clevatien prt.sture Icsses. As shewn in Attactt ert D.3., tne predicted core coolar,t tecneratur is slightly hicher tt.ar. tne er.nimm saturation te'rocrat.e e (based ugen Nasured

}

pressre), however, there is scme encartainty in octh the re

-T.;

An eran:inatier, of the react 1reter y

ir. water) cwic' have ccqtrer! within the ccre.

data (at*tchttet D.4) indicatt.e tnat the RCS pressure lev time pericd durinc which the I

,j 50 p;i. Therefore, tne caxir rt Acoroxirsately witn a varieticn c# +

curv truld ha>. teifsubjected ts bubbly flow was less ttan ene heer.

j estituted saturatf ea tercerature, therefore, the bubbly flen, e

JJ If bubble:s were fcreed curing this xriod, j.

i or.:.rivd for.o core it.r.n *en trir'utes,,

the fonation would t'e it. *he liquid as w:ll a) en the surf..ce, as o;oosed to format on With the tefreer.stures, ttree duratico, and type of formance. no frem a hat surhce.

signif t:,nt effect on the car.4.onents muld be predicted.

FUEL 100 PRESStVI PHor to the <hp e~ sri:stien event the resctor had been operating at i v

f aporox!r.nely cne week.The cort t,ur1uo was 1 EFPD, therefo*e *o sic.si ficant f rated power.

produc* ion had occurred amt none was released.the indicated RCS pressure

.i core the average coolant tecocrature was less than 540 F and no significant h generation ec' curred in the fuel.in the cladding nased unen a -aximum pressure d i

This evaluatien had been based uoan a GCL TAFY analysis with an aroitrary safety factor added to ensure that actual conditions would he bounded by the pred

%0 psi.

l A more recent analysis, again using TAFY, has resulted in a predicted fuel red pressure of 1000 psia.

On the o

3 hot, near zero power conditions at a ecolant average ter@crature of 540 F.

jj

(

l 1

1 d

1 i

J A

^

-e r _. r

-__ __ e h'gg" ].;516

- - ~ '

n' I,

.m.

gi igWe' p.c..,

~

-^

d to basis of this analysis it is c ncluded that the fuel red cladding was not subjecte any significant level of tensile stress during the subject depressurization even Since the cladding was not subjected to a 1arce, long tem tensile stress, no ine tensile stresses which could

• sve long ter:t effects en the cladding resulted.

d the occurred would have little effect on the claddirg due.to the smil stress levtl an short dttratien of the tensile stress.

s GM. LI.N Q

and if0 I 10 lb/r.tr. systes flow (per Ass.-=ing a c=21 ant tE3"a., s,;,y 3,7 r The m ic u lb. hhore.: will be less than MS 15.f.'al as fc c a

g fc is &

s t

.l t

. %p,

~

u

~ll

}

4 7

r.

J n

,f,

^e i

a 1

1

~

9 4

4 1

l I

J

- - c-6 4

AKm --

t.hu -

[

i

[!loq3 }

> 5 1_-

F l'i

^*

~ M W,.

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Q, F

r,. r.

. r.

-r.

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- :. -i+. s.L. en, n.u w,2!... ;

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J.. : ;. ;..:.; ;. ' i.

m.. ;..._ : ::--

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- r3,

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....... - i

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g.,,

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g....- i 4

.,...g..3:--...

..... q. -~. ty.,.

.O.

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is.

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., 3

..... r... : 3,,.-.-

t- --

. g

~..:..

g..

t e.b_

i

..... s. :

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s.

p A

-........i... '

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b,..i..j,._....-.

~:

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-.~.... i....-

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ff i.

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.... :.=

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a.

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a ;...:=. -.;a.:

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. es1 i.i!

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..: -::*.:. *:-:) D.. <.. >. - '.

.J.

• x e.

U.,, %..

.s s. :.- ::.:y.

e

]:

a 3 l-- b' e~ +-

..=.

- o

&;.' :-?~. L. i.u I...La.e..:... ~ F

.:a.

)

j a.

4:r s=c:;.a lG -

=- m c.

n...

• : ; 7.:... b.m

. :r.:

.:-? L"..:

j.,'. -

.w ca.a.e

.::=.~ e. : y- -r. : ~..\\

D T.-S.

r Y.1 G 1..

"W bi.s..u.4~N _

? W.-- 'hh?.ly 3

- u: -

L.....i i". 'a.s".:., =.

..uo i

e (f._. 'O'?*$_~2=~i 2..,u.-.?Y.5-Y?..h. Y e

• ..&. ~m.i=. :..

ec a: -~ u N. d.. m.:

-- - +

-4 a L.:n -

J.% :- -s

.:..-e s

.Y T.Q

- - - M...:=

7 ad.~- l, a. *.

.u

/,/..T ;;.QKma. : e.a.-.:-s.. R2i x.f,-

.e

..w a -

--r

' =.

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J *J.

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

"...:... ' k.

e...s. s..e..:.:.-:.-

V.

n a

. a-

-m f,

f _.::.? _.,.- c.~ +. a..

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T-,-

.. i.... w....e

,m.

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