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Summary of Status Rept by Util on Concrete Separation in Reactor Bldg Dome. Delaminated Area Diagrams Encl
	ML19329D727
Person / Time
Site:	Crystal River
Issue date:	08/09/1976
From:	Engle L; Office of Nuclear Reactor Regulation
To:	;
References
	NUDOCS 8003170517
	Download: ML19329D727 (26)
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3 1-Applicant:- Florida Pc'.mr Grporation Facility: Crystal Psiver, " nit 3 -

St@ARY.0F STATUS REPORT 'BY FLORIM PCHER CORDORATION O'l T!!E -

' C0 CRETE SEDARATIOL U! TE CRYSTAL. RIVER, U!MT _3 P.EACTM PJIILDING n0ME;

G The Florida Power Corporatica (FPC) and their censultar,ts.(Gilbert Asscciat5s, Incorporated;'MPPs, Incorporated; and Ccnstruction Engineer Consultants, Incornorated) cresented a status report-tn Se 5!C staff on "ay 12, l'76, re cr4ine concr* sonareinn',.in tM Crystal Giver Unit 3 (CP-3) reacter tuildine dcre.

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dout one inch belou the surface F the con:r?te dcr.e.

inc.tica tions-on April E.. 197n invohW the cuttira and movf of a o"e-by t5cce foot cencreto I N area s cre the void vas first o W W.

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.u vein mcrease- + "enth 1.1 the d r~d en of the donc apex.. Wr+Mr core drillinc en bril 17 nad M determined

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Nrsuant to 10 CFR '5n.W, t5 FPC ratified the airectorate of Mulaterr

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- ' Th'c CR-3 reactor; building is'a ' concrete' structure with'a 3.1/2 foot: ~

J t cylindrical wall and a:3 foot thick torispherical done.

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. to the inner surface'of the concrete is.a 3/2 inch carbon steel.

liner plate. -The dome desian is identical to the 19G7 Ecchtel desinn.

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.,, 6 The.domeDis', pre. stressed by means of tendons forming.a three layer systen "

' ~ ~ (See attactnent:3). There are~.123 done tendens~ arranged in ~41 tendons J.xper. layer.aThe conduit ~ sheathing for each tendon is a 5 ' inch diameter f schedule 40 calvanized pipe." Each tendon has an ultimate strength

-of 2.355 millica pounds:and was made of 163 seven millicater low-relaxation wires. The tendons are corrosion erotected by bulk filling the ccnduit with crease.

-The done:cor. crete was poured in concentric rings fron February to

...luly, '1074. The icwcr rinas wre peured in secticos and tSe upper rincs in ecmpletc cours. Fcr this facility. the cone.retc cce follcred ACI-318-63 and fCi 301-M with todifications (as specifiM in the FSAR). Aggregate used in the concrete mix was native to tSc stato of Florida.

TM Class i :tructure was designed "r an intern:1 msrure Of 55 Ssig and accid" ' tenerature conditio*.s of 2310F. Accide t nressiire conditic:; :.11 for 4'.1.6 psic.

Desica mereters ! eluda 7ed ! cad,. live load, and t-mraturn c.Ni.nts.

The str:n ture um be r,re-Mnr:tionally testrd at a' pressus - of C3.3 p*,1 q

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'The FrC stated that their core seroling procram to date irdicetes the concrete separation is clear of debris and L' c cicavar e zcne

. is sr.coth. There are no visible.sinns of surface crackiro. Core isamples continue to be drilled and FPC stated that extremo care is

'!>eing observed not to dansge rebar.,or tendons..

FPCffk presen.

,Jconducting,ir'a concrete analysis which includes:

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was first noticed..There are cresently rio core sanples and core drilling coaM nues such that sanoles will be availabic with 1/2 of the core sarple in adjacent pours.,The FPC is corino three samples to a set.

Plans call for testing

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one set and the saving of eno set for any additional tests.

-For any srt beinn testad, 2 samlas will Sc tested for conpressicn, and one sarple will be tested for. tension.

(3).The FPC is presently tabulating data availabic from their-4 documented nicro-fiche GA records..

. o Core sample f30 has showed three cracks at the depths'of 1l 3/8 inches, o 1/2 inches, and 11_1/16 inches..The core drilling progran requires the use of water and it has been observed that water rust be vacuted out of the core sarple holes indicatica cracks are not execssive.

Inbient internal and external terparature eeasurerents are being nade and strair gace neasurer.ents have t'oen ccepleted. The dere is now instrur.ented to cback for the possible racurrence of additional caccre.te scoaration.

Man attach"ent 4).

'.n.sti.atic: of Caum for Cer r+ Ecoaratim The rPC is presently avaluating factors which may have centri'mted to the concrete separatica. They are:

(1) Properties of Concrete (2)

F'.flure be to Padial Ter.sion (3)' Cccpression-Tension Interactions (4) Then al Effects (5)ITendenAltgrnent,

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Iten 4 above no~v be' a significant contributing factor to the pmbler.

' The tenerature of the anti-corrosion creasa who.n introduced in tPc tendon ccnduit was 130-150 F.

A expansion study of 40 schedule 0

pina indicates a 10 rise'in grease temeratur: prcduccs a pressure of 10 psi on concrete surrmmding the pipe conduit.

~lnad Beari_no Anal _yses

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The FPC stated that.corputer. analyses are r.ow being rade to detemine if the delaninated structure in its' currently observed conditiors can neet the load combinations as specified in the CR-3 FSAE criteria (i.e., dead load, pre-stress, normal,. LOCA. Accident, a r. ' OM).

Aralytical studies are beine conducted on teth 2 an.' 3 foot do.ms to datermine if the ?. foot dorc'c(tSc ccncrete thicPness below the ecccrete separation) can adequately perforn t% intended functions of the throc foot h C-rrectim rf x Reters 4fc5 tM rPC are nresentiv cycluating in orAr to detertine tbs corri-cMye Mn are:

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(2) Po preMbility for additiml M.we to the dem cao if detensioning Seco os cart of the corre:tive fix.

(3) Otter-instit n of a detensioning and re-tensioning sencence to ninimize cmnressinn-tension forces in tSe :tructure.

(4) ' Additional survey'of cor.creta crackir.g belcu the corerete separation gand the possible. effect on expoxy..greutinc of the Void.

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7 (7) Udditio'r.al-analyses;to detemine coc:fression-tension interactions

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The FPC stated:that"examinaiion of their co$struction records. revealed

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N"i thet"on' December 4. +1974 at'7:20 f.!6' a ledd noisior tocn occurred.

~en' site.. Tho' moise-reportedly appeared to ecse frort the Reactor F

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Building and was: heard by certain construction workers. One ucrFer was in the Reactor Fuilding personnel-Inck at the tirCand felt vibrations

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of ccontainment revealed "nothing. ;It was. assumed the disturbance right

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have l en a "s.oniciboom",,N The eventias not reoorted~to.the NP.C.

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The !!RC staff expressed.'theid. concerns ~regarding these.eatters as follows:-

(1) The establishnent of the causes of the corcrate swaration is important in order to provide the ulti.rnte " corrective fM.

(2). The u':e of r: dial anchors will' enhance the capability of the repaired dem to resist radial tension.

(3) Pecause of the te merature effect of tSc crecsa in the t W m conduit. the effect of pres:ure in the conduit on concrM.: mauld be considered in the stress analysis of tb dow cencreto.

(d) Sinc"' tha drManc Of IcN07 'Corticrs of *;be derm ca,-e.ra'.e is restraf.ed by the sttel lineri an1 the +on certion Sr no ne restraint. co". sider ttien should 6 ciwn to the ef fect c:-

concrete differcr.tial shrir.b er.

(3) The cresence of the 5-inch schc-Jule 40 Dipe as tenden sheathing in the dore give rise to:

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.(b)- Stress concentration,jin the"do e.

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~.'Therefore', the: Use 'ofLa'.24" thick concrete doce section for tha l'. *t2 foot'analyticalJmedel'doesi not represent the actual conditions.

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. auaregate in the direct tensile.strangth.cf concrete. This

- factor should. be investiga. ted.

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m.

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y :.e n., n w :m.. x y-a, p n, _ w. n.,.,,AUgg.g, y. m,_..._.._,.

s.

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7 3.:

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=

j. m e.m 17)7Any analysis for:de.c.nodels using -less.tnan the oriciial"thse- ~

1' I

.O foot design thicknessicf tbe-do o should consida the followIrh

, ~

.. effects

w M. ~7

^

~

', ~

~ '

o

..~ 7..

(a) increase. in.conedte etnpressive stress

~

(b)' increase in creep as a consequence of (a)-

(c) increase.in rin'g girder compressive stress.

~

r 4

s e

i

-.. m.. a

. r w.u

< G (d)iincrease,.in.the-Poisson's1 ratio' for concretes t.'. ',

?

. z. w. m.,

ac..,

w

-n

./

~

s.

r a

'(8); ;The effedts resultingifrom construction rdth'ods'should include:

.s

- + q.

.. (a) vibratio'n of. concrete (b) adecuacy of Lconstruction joints between successive ring scurs.

thn prestres ik wwce c::o..ni d 9..o. val. ua..t,M o i th. =tM "s e

.. ~.. w

.a

. ~.. ~.

- tc) s of a finite M.a. t. -cces: uter. prograd with input paranctors fo: r -

oom all prmn essing comoncnt; acting on the dore.

(9) The staff advidd the FPC of referenes.r.nlic:51e to cemenion-tension stress analysis.- For tha torisien-e.cwrcssion interfction, refer to p. MS, ite: 6 of 'i!andhcok of Fxrerirental Stress Sr.alysW hy ". HetenyL Ahn Wiley A Nns, Inc., TOM. The athar referorce renticW ir the metiac is-

" " r" ef Plai-Concreta ".9 Sinxial Stress" ty Isrwi ?ctentha! %d hseph Glue.ikiich,

' p. N3, EI JGUM., Pov.1971 ino staff concluded with the statemnt to the FPC that "the repaired reactor buildfag dom must meet the applicable cafety codes an f critoria seccified in the' CR-3 FSAR, and the re;: aired structure will he recaf red to reet the requirc~nts of the preccerational contain=ent integrity and leakpmor tests."

i-y m,

%,f '

~ y.,,

original sisned tg '

Leon 3.Icgle e.

3.6. a

'.t.

n

-p *

-a m

.e s.

.~......

f..y.,., Leon:ErOTe,;P.ro.1ect Yanagcr n.

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3 igc.

j o, e. C,%. j ' 1l$$.. (t.ight4!ater Reectors Branch Mo;il.

. s.f. 1 c.

.;cw.n-m e

DivisionJof Projectfanagement

~-

. nn

....n Attackents:

. c 1.

l.; Attendance Listi I

.h {b 2.

Oclaminated Area on' CR ^

D MD

'T D 7

~ Reactor Duilding DeceT o

" @ =J.'

d J\\ b$

~

L 3.

Reactor Huildinn Dece. C.

.m w.. con ve m L -

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Iz q

u.

.rm _

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typ

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.: y w '. :-_. 08pg Fj76-087,5Q76 _ ^

V w;

acu u,sas..

7- '".7ers AEtM13 Geo. bH) Aarw pHg g

.'.m ?.Y.t us as sevemmasser namvine crim:ss Befa.eee tas ?

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n.. '

b b _1 N ReiI S 3$M d.. N *.5 M h *-

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=

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. J...,.,,,0dGars...

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Assistant:Vice Frcsident'and '

~'.% ^

i !!uclear Project Manager

[>

6~

~

f 1

P. 0.HBox 14042'

~

St.' Peter 1 burg,. Florida] 33733 Mr. S. A.' Erandinore -

. ;Vice Pres! dent and Gueral Ccunsel-e

~

.-iT P. O. Box 14042 0 %m. '

n. ;,/ E St. Petersburg.', Florida ? 33733, < >

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form AtC 314 (Rev. 9 95) ABCM G24 m

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4

ATTACHMENT 1 Attendance List Florida Power Corporation Crystal River. Unit 3 Florida Power Corporation Stiefel Associates L. Alberdi J. Stiefel D. Black W. Nisula R. Raymond NRC Staff J. Rodgers E. Arndt R. Lewis H. Ashar R. Shewmaker Gilbert Associates, Incorporated L. Beratan J. Shapaker W. Butler W. Swan C. Bitling S. Chan D. Croneburger L. Engle E. Hottenstein M. Fields J. Herr T. Greene R. Pages A. Gluckman F. Moreadith C. Hofmayer P. Zia

'W. Laudan Construction Encineerina Consultants, Incorocrated J. Artuso P. Mast MPR, Incorporated N. Cole Ebasco, Incorporated H. Kuo E. O'Connor ACRS Staff R. Muller i

l

Page 1 ATTACfNENT 2 Delaminated Dome Area for Crystal River, Unit 3 (pages 1, 2, A 3)

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PAGE 3 bO'ntteie 3cbG N+1W

___....x-7_" GAP 14E' h

Ik" GAP kk" I "G APK 0 5" gii 5

g"G AP DESIGN B+

E" LINER S

1 2.5;...

t si-x36'

{

i O

I R = ?.O'-o" R - 4 o '- o" R:

=

30. o..

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Doua SacTiow-90 Atiuurs i

(sovERutNG As is comE TmcKNess')

ao

NTT CMENT h PAGE 1 Cr,ystal River, Unit 3 gr Reactor Building Dome g-T Tenoon Detail 7

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{

n ATTACHMENT 4 PAGE 1 Crvstal River, Unit 3 Core Samplino Procram D

e.,. e"

, 2.4 n -

4"* core DRILL l=

r ga& CORE DRILL I* ' ' 0 '

b t

Ed

_ (4-17-%

/.18 % -

'+;

l 2 to L

2tn I F tu o

-a c

,3 2>

=

(:w : '

a o

f L'

POUR Q Y

-g}

y.a.,<*

9 POOR L ":o -

a..

f POUR M A

m C O R.E ~" O POUR K t.4' 4 CORE e--O" DRI LLw~

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_.. y 2,

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s-d l~

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(4-IS %')

I

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DOME TENDON ex T O P L A Y E. R 6ECTION k-k POUR L

.b.i r-:. ':; -

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/

s --

4_CN.(TOP DOME TENDON-POUR K

-f y

g g g ;; e.yL; c= *z I

3ECTION 0-O

PAGE 2 5"

7[tDRILL%

4" C DRILL

)

t w

EDGE OF TOP DOME TENDON

\\

x" IFI A \\ () d-

=

a.

I I

'.E' d'5" y "4 POUR H

" POUR L

)

/

~

I J

POUR M (POUR J

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POUR K POUR G Coaa#A CORE ' S EIS"

' 22b

g. f,." 6 CORE DRILL 4

CORE %=

(v-20-m A h

(4. gc3.g)

\\\\,M

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. POUR L 5,4 Y

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PAGE 3 N

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CORE HOLES 23"30" DEEP EB-2B"YB Q A-do"A 19 EXCEPT FOR: I-27" III I60 DEEP EXPLORATORY CORE HotEs

@hhk hkOh

PAGE a

~

l" 4 C.V. ( O*- 7 7 O* )

( CORE ORtLL (4-14%')

~

-ki' VERT. CRACK IN POUR Q l

N.E. ( S.W. F ACE OF COREj TOP SHELL L

t,h h

NOTE"A"

,=, j

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_ia CR ACK DETECTED 4

7

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4.-CORE DRILL is n

Mgtt 11 i 16

( 4 -7.5 l G')

s is 7

1_2 l

i

=

(4.gg,q g)

LIMIT OF CRACK LIMIT OF BY SOUNDING Nl CRACK BY souwoiwe ~

tt$ CRACK TD i

p k=

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o

@b

_ 4"&

L tg=tpt M

n 2.

1 e

t

/M 6

m["c.

. POUR H "g

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4=

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4 I

s?.Tofd' WIDE CRACK POUR G Coaa# 11 Coaa # l2 y]@$ $$}bb

'3-Y P.

\\

PAGE 5 l(

1 G" g

e4-CORE DRILL

/i

3) (RI 0

I.4 159 G) l{"9 CORE DRILL POUR M (4-2G-%)

T q'

's %t i

f L

%%gn % Ag

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_ EE NOTE T POUR G pegg g Cone *13 Coas. # 2Co 43" k",,

=

~

=_

d -4"@ CORE ORlLL

(

2G %)

4"9 CORE

(

'$ CORE POUR K ORlLLw D ILL T

(4 7 9-M) "

i

_g?;

.o l' (uvRox.t USVf=bj=m W

=

o y

_/.

u ww m

g-s.3 3

,g TOP Dot /.E ye iie-l' l

TENDON k 'g* ",4 CORE DRILL

(

POUR L g

= 0.01" CRACKS SEE NOT E " A" POUR a SECTiow l-l Cons +2c3 g gg$M, 3-y

PAGF 6

~

_ S 4" q.4"& ( g["9 CORE DRILLS

[pogg y (4 '2.5 7 G)w 5

\\

v' h

L 1 '

L

"-g

=0 g# $ U 0

A.Loj %!Mx ss y:.9 F/\\ \\ ff 9

- c. <,..'

r

=oogcaAcg h.

= o.o i c R A.C.s. -sEE uoTE "M' z o.oS CRAct, K P O U R K.

POUR J Cone #30 j.4 *qiga*

a

=

CORE DRILLS (4 2.G-7 G)

C b:

y

\\ POUR K POUR J

z O.01" CR ACK SEE NOTE "A" I

CRACK SMALLER N o E "A" CoRa*SB l

i

>y

/

TOP.OF CONCRETE (illi')

(f To TOP OF CONDulT (11.")

~ AS ButLT

<se e>

ys..,

(Gk")

{-DOME THICKNESS s

1 (33g" AS BUILT.

l.;-

2" GAP

['14E' (3N,,,

io i{" GAP 14

\\

N u

15 AP BE" 4(a 5"G AP DESIGN B+

(" LINER tst,.

m

+

, (31"

^

l j

, s3e-

/

R = 20'- O" R:

_ R:40'.o"

[

\\

So' o

4_ c.v. ~

l DOME SecTiosi-90 AaiMu rs i

(soVERNING AS \\S DOME THtCKNESS)

I NOTES

i a

e 1

t

)i l?

MEMO ROUTE SUP 1

5" * * * *"aa-

*r * *ac u" *** *-

Fa' *c*-

l form AECW (Rev. Me, 14,1944 AECM 0240 i

Note ena reeven.

Forsigasture.

For la8sematio*i.

ll To mm..aa...ii inne atuaans

[i J. Collins, Chief e-80 - 36A F

ETS3/DSE q-par d

/

l 3'-

T11RU:

F. Coagel V' I-10,~........,,

-um r

cc:

J. Boegli, ETSB

[

f D^ r*

i To usam..<.s u. n>

vano n u nans DATE l

CRYSTAL RIVER UNIT 3 APPENDIX I RADIOLOGICAL DOSES L

FROM (Name and unst) ngmanus i

i L A. Parsont /

Attached please find the appendix I Radiological RIS/RAB

//

P-214 dose evaluation for Crystal River Unit 3.

r.

PMomE feCL DAtt

1.

27955 8/17/76 f

7 USE OTHEA SipE FOR ADDITIO**AL R(MARKS CfC 3 ggig Q. 46 463

.[

j t-L1 t:1 M'

g.;

.! i pw

'):i 2

a '

o.I I

/,'

7'l e

r1

~

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I l

i Comparison of Calculated Doses from 1

Cqstal River Unit 3 i

+

,WithSectynsII.A,II.BandIl.C of Appe9 dix I,10 CFR 50 v

t Appendix I Calculated i.

Design Obiective Dosas Criterion--=-

Liquid Effluents j.

8 Dose to total body from j;

all pathways-3 mrem /yr 2.7x10-3 mrem /yr g

4 Dose to any organ from all pathways 10 mrem /yr 2.6 :10-3 mrem /yr

.l "

4 i-Noble Gas Effluents Gamma dose in air 10 mrad /yr 0.33 mrad /yr

{'

Leta dose in air 20 crad/yr 0.84 mrad /yr i

Dose to total body of an individual 5 mrem /yr 0.017 mrad /yr Dose to skin of an individual 15 mrem /yr 0.004 crem/yr e

Radioiodines and Particulates" h

l Dose to any organ from all

[

pathways 15 mrem /yr 0.069 mrem /yr

~

" Carbon-14 and tritium have been added to this category

~,

1 1

a

4IlI, h;

r3

[1 0

h

.

ML19329D727

Text

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