ML20031F140

Summary of 810918 Meeting W/Westinghouse Owners Group Re Pressurized Thermal Shock to Reactor Pressure Vessels. Attendance List & Handouts Encl

ML20031F140
Person / Time
Site:	Beaver Valley, Millstone, Calvert Cliffs, Davis Besse, Browns Ferry, Salem, Oconee, Palisades, Indian Point, Kewaunee, Saint Lucie, Point Beach, Sequoyah, Arkansas Nuclear, Prairie Island, Surry, North Anna, Turkey Point, Crystal River, Haddam Neck, Ginna, Farley, Robinson, San Onofre, Cook, Yankee Rowe, Maine Yankee, Rancho Seco, Zion, Fort Calhoun, McGuire, Trojan, Crane
Issue date:	10/01/1981
From:	Vissing G Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
TASK-2.K.2.13, TASK-TM TAC-46890, TAC-46909, TAC-47549, TAC-59974, NUDOCS 8110190243
Download: ML20031F140 (22)

Text

{{#Wiki_filter:', pMn W oq*j%; UNITED STATES \\, f g NUCLEAR REGULATORY COMMISSION g, -t

y WASHINGTON, D. C. 20556

/ October 1,1981 6 ' OCT' 619sts 3 T s,s, s. v Docket No. (All operating plants with Westinghouse NSSS) y j Licensees: All licensees representatives by Westinghouse Owners Group

SUBJECT:

SUff4ARY OF MEETING WITH THE WESTINGHOUSE OWNERS' GROUP 0F SEPTEMBER 18, 1981, CONCERNING PRESSURIZED THERMAL SH0CK TO REACTOR PRESSURE VESSELS (RPV) Introduction This meeting was a followup meeting to the meeting of July 29, 1981, to review progress and to discuss the technical issues concerning the system analyses, operator responses, and materials and fracture mechanics aspects of the pressurized thermal shock issue. The meeting was a continuation of the technical discussions of the meeting of July 29, 1981. The attendees for this meeting are identified in Enclosure 1. Visual aids for the owners groups' presentations are included in Enclosure 2. Summary and Conclusion The Westinghouse program, due at the end of the year, will include the following elements: 1. Generic thermal-hydraulic analyses of transients including the small break LOCA and the steam line break. 2. Fracture mechanics calculations for each plant. 3. A date and a RTNDT consistant with the date for each plant when acceptable conditions will not be met. 4. Consideration of benchmarking the Rancho Seco event using pressure / temperature factors for all classes of Westinghouse plants. 5. Evaluation of remedial action including: l a) Heating the RWST b) Reduction of Fluence i c) Vessel annealing d) Automatic pressure reduction e) Limiting auxiliary feedwater. l f) Automatic termir.ation of safety injection. l Likely remedial actions will not be the same for all transients or all plants. '0110190243 811001 DR ADOCK 0500

l i l } l The aspect of removing fuel and loading the core to reduce the fluence at the vessel welds was discussed in greater detail. By selectively I removing or replacing fuel closest to the thermal shield with spent fuel j assemblies the flux could be reduced at the belt line in some areas I by : factor of 2 to 3. However, this could also increase the flux at l other areas by factor of 2-3 also. There would be other penalties, l such as power and cost depending upon the core management scheme. There also could be a fluence reduction by factor of 10 if 1/3 of the i f core was removed. The report, which is due at the end of the year, ( would provide evaluation of different core management schemes from which each plant could chose to suit its purpose. l I Preliminary analyses using the pressure / temperature history of the Rancho Seco event indicates that there is at least 3 EFPY remaining for I any plant before there is a concern. I The Westinghouse small steam line break (SSI.B) is similar to the Rancho Seco event but is more limiting. Preliminary analysis indicates that any plant has at least 3 EFPY left before there is a concern. This is based upon a conservative analysis. The report due at the end of the year will provide the EFPY remaining for each plant on the basis of the analysis of the Rancho Seco event, the SSLB, and the small break LOCAs. Westinghouse is concentrating on the accident areas and not the operational transients. i It was concluded that the staff needed to arrange a separate meeting I to discuss the fracture mechanics and materials areas. l ./ l p S. Vissing, Pro ect Manager perating Reacto Branch #4 Division of Licensing l l i l

IMMEDIATE DISTRIBUTION - THERMAL SH0CK OWNERS GROUP RESPONSE H. D' oton/E. Case (1) D. Eisenhut (1) G. Lainas (2) T. Novak (2) T. Murley (3) R. Vollmer (1) R. Klecker (1) W. Hazelton (1) R. Mattson (1) T. Speis (1) i S. Hanauer (1) D. Basdekas (1) l L. Shao (1) R. Bernero (1) AE0D(1) l I. Igne (1) T. Marsh (1) J. Austin (1) R. Crouse (1) B. D. Liaw (1) M. Vagins (1) D. Ziemann (1) G. Vissing (1) R. Johnson R. Woods J. Clifford Lambros Lois E. Abbott

MEETING SUPNARY DISTRIBUTION 1 l Docket File NRC PDR L PDR ORB #4 Rdg TNovak JStolz Licensing Assistant OELD IE-3 SShowe (PWR) Meeting Sunnary File-0RB#4 RFraley, ACRS-10 Program Support Branch J01shinski BGrimes, DEP. l SSchwartz, DEP SRamos, EPDB FPagano, EPLB i

ATTENDANCE TO MEETING WITH WESTINGHOUSE OWNERS GROUP CONCERNING PRESSURIZED THERMAL SH0CK ISSUE SEPTEMBER 18, 1981 1:00 PM, P-ll8 Name Organization / Position Guy S. Vissing Project Manager DL/NRR Bruce King Westinghouse. R. W. Klecker NRC/DE Daniel M. Speyer Westinghouse T. A. Meyer Westinghouse D. L. Basoakas NRC/RES Herman F. Petsch TYA-EN-DES-NEB Knoxville George J. Schnabel Public Service Electric & Gas Co. (NJ) D. L. Dill Wisconsin Electric Power Co. S. K. Mathavan Florida Power & Light Roger Wyrick Institute of Nuclear Power Operations Edward D. Thrcm NRC-DSI-RSB Richard E. Johnson NRC/ DST /GIB Roy Woods NRC/ DST /GIB B. D. Liaw NRC/0CM Vernon T. Chilson Florida Power & Light Pryor Randall NRC/NRR J. N. Cnirigos Westinghouse P.A. Cozinel Electronucleaire-Brussels (Belgium) Arthur F. Billy EPRI/NSAC R. L. Kinsaul Southern Company Services J. V. Brunetti Power Authority of NY Tom Murley NRR/ DST

~ . Name Organization / Position B. S. Monty Westingh'ouse. Milton Vagins NRC/RES/DET? Jack Strosnieder NRC/RES/DET' Lambros Lois NRC/NRR/DSI Grant Chappell Carolina Power & Light Stan Anderson Westinghouse James Kay Yankee Atomic Electric Co. D. G. Maire Westinghouse Terry Kishraugh NUTECH J. J. Sheppart Carolina Power & Light Tvia loroi Westinghouse Mike Ahern Northeast Utilities Brent Clayton NRC/DHFS Neuton Anderson NRC/ DST Walton Jamson NRC/DSI Tad Marsh NRC/0CM Paulette Tramblay NUS for NSAC/EPRI l j Eugene S. Grecheck VEPC0 r D. L. Lippart VEPC0 John Tounsend Pacific Gas & Electric Co. Robert Borsum Babcock & Wilcox-J. D. Sieber Duquesne Light Co. L. D. Butterfield Commonwealth Edison F. G. Lentine Commonwealth Edison Joseph P. DeRoy Power Authority of the State of.NY Robert L. Goyette ' Power AuthorityLof the State of.NY Tom Novak NRR/D0L m

4 .f i - Enclosure 2 4 u. +. 4 = I 5 ? y I N.N ^ FUEL ASSEMBLY. REMOVAL ~; e,. ;. .4 . ; c,..,..e;p%p:_ 7: i ..u. e .s i ~ r* ,, _'? ' ~ kf1 J' tg - ce: -- 3.. .., ' V 3 5.i,.t=s k 7 - , ' h r',s [.-o j. - $( ~ ^ 4' e s a. i-, r,. 41.0 j > + .' A r.".- ?. p. - REDUCTION OF FLUENCE THROUGH REMOVAL OF PERIPHERAL ASSEMBLIES j t 1 s LOOP 12 ASSEMBLIES ) {. J 12 ASSEMBLIES LOOP i 1 'P. .,.,g. it LOOP 16 ASSEMBLIES

l 1

l i i J l' 1 L I i + + 2 i t r A. s 'T t t I m. ~.. _. _. _ _,_.._

y \\l M ) FI GU R.E ) l l L 9-L.dCF 91.9 'iT R, e G. E c t. ET R.'! o 0 I s' I i; *. o,, + I R 4c7 i1 1. 09 +R If t l lll } }' ! l Y-l / T);g HO ///'/ 9 ~e

• l!<

Nag / j, ' 'Yp ~ l' /j s / j l Y / ///lill!/ / ///// / / 'j, l /, ).0fo ! 1.09 1.01 D -[J [ / //// / ///{/ oj .s ). a, ) )o. ! ).00 1.05 ! ).15 l C.15d>s #$ l ST7 ).c5 0.i1';0.81 1.07 1.0 0 ' l 0 5 / i ).03 ' ).cro ! 0.55 )'O 1.04 I. j 0:'lo ! ).09 l1'. ).12. 0.'Y5. i I i

o. a 7.' O. w p i

).:c7!).e5 0 34 a;, AUTHOR OATE CHK'O. 6 Y OATE CH K*D. B Y.. DATE REV RE Y. NO DATE WE STINGHOUSE F O RM 5S2130 ~ - O ( I a

l ^ .h 7 4 ~'3r

1. ^

...,,s

m..,... ;

n.. . ',_ < \\,, [ ^ f; ' _' ,,. ;; -. 2 %,.4, +,.

4g e

.', -} .f, - r' ~ <r ~ 1 . :.,,.g;. 7, u.f

• REMOVAL OF A

P E R I P H E R A L " F,U E L W ' S P., 6. '..' ..~,- .n n, 9;. 1,7 ASSEMBLY MAY RESULT IN A F A,C T O Rc, 1 J r .q, o... x. : 0F 2-3 REDUCTION IN FAST ~,.N E U T R 0 N' ',.. F L'U X IN AREAS OF THE PRESSUREr r VESSEL WHICH ARE ADJACENT T 0-THE- ~ ' C0RE VACANCY-e s,, :r ;. .m 14 %

c...

• FAST NEUTRON FLUX IN AREAS OF THE VESSEL AWAY FROM THE CORE ~

PERTURBATION M Y INCREASE SLIGHTLY. ~ IF CONSTANT-REACTOR POWER IS t. MA'NTAINED .x, r. x x.. 'y, "1 .,_s' c,' 1 . - s

• w. ~s. % d~. ~,

p. ?, ...

• 4"-

.. ; (g,', a. , _ ' }.,;Ll l $.N'-ll'(-g?',**[L'=L N.1.t ; % ? Wf s'".QfLt R ', ' "> j' ' 1'. d' ,,L ';; ? ':, $,f' I s ? 4.' l' {;* * 't.., 2 ^ Git;/s 7.; m.* T. ;(n, t 4 G 3,, r.ry

• r,. ;g,.y<*. e i 4 p:q,31 (

e.", fQ j gi,. ?? 3 l'. a, _/, pL. T. .,N". a i+ c.i s. ! '. g+ d' %S V* t 4 3 ~y:,'.,; : r , =, ;, 93. r.- G (_ i.l., ;- 4 / N ,_m

..c.- ..: c._.3 9 _ O. O,;

[ 7 m.~

- = ---.. - _.; :--- ;; -- --- 3------y---------- i _y. sr. ~ - ,,].,_=. ,~ .= il_ -i -:--i

• i ~ _.q =; :i : :i..=.~~ j _+2 _._- 5 :. :.- -.

.a. =_. 4. a_._ _.;...:_., a 3, ~ c ry =-3.= _ u ; 3 _ =. ti_i-p =_nj-p - _x-_ _ $URWRTEM---CA P$Uly.,$ :=:1 g-1 ..... -. _.. _..=_.

=_ __.__ - _: : t -__

_ - ___ _- -; _;=-- _. -. ~ =_ } _ y gg =, .= a

=..: _ =.-i_...-._.._]..-.___.._._.______

_ ~.. __ :_.- : =_-4 = :-. = += 4 : q_ _ - = 5 y.._ 7 =a.:. _ q. _p,

_. __ _ _ ; 3 g

---i = :l : - i_.i

2. _: - = -[ - -j=: :=_.i -~. : g:gy;j--; g-.i-_ 3= -g y: __q. _[ _f:__y 3 /Q

.--L i ' 3: 5 _i ~f ~ ~ __ ti. [= i-5 ~. -$1r_Si:52 EE- ~~ - ~ ~ i E-i-d M&cd E-~"=_'=i! =: = i-Ei=.i . L: - c h=_:= ::u. = r_,.: _= _1:===:- -

-t- = _. _ __ _j ----- _ _=_q =

-m==.__-_-- t_._==---

---

=:

=:=.ir : r _ -

_] = _ 3 j --- r._ nr: _ __.__.___g--__4_.__ -- q y

7. __ _,_

_.._._.7._ = __ _ _.y___...-- _ :1_= _.=_ = :. _...:- -,. _ _ =- - -W _ :. _ i.. _ _. - _ _._ L. _ ___p_. _...__ ___g _ _ ___ _____. - - _.._._4__.___ A ______y.___._ L. L_____ _ _ _ _ ___,L_ _.._. __ _ ! - %_.i T_-L_O_C AT.__i_o_W l.. _ _ _ _ _ o _ _ _ _______.._y____ 10 _1 90 l_- -_ _ j L_ __ m* i j i T - i a. p-((

g 4 =e

.i... j -i

g2_ { -. :

. - ;+_ { j.... _. 9 = . a y 3

?. -5

g= 4- -.-i -

. -i t+; g===i4 y-= -g -y- =- g _.2: 7 ; ;_ :. - d -l _: I i Nii M ~ ~ --~ . i I I M I 5N-i : 4555}i ~EM : 5.5~2id.)i _Id ~~4: 528 -I hi v} ~~-~}= =.c... ... z 3 = : =.:= = :.t :. : = :. =- : 1 =. := =_: --

y- =. := : = g= ; : 2-5223

-~'i I ' =a'2 ' 7-2 ' = = = =.== =... L: _' t ' = z i =-- - - 2 + --~ ' ' C' - - s 6 e4 =: : : :.:' = t= =.:. =__ . = = - :.:.= = { :. = : : : g 5 - 2 ~ ! I ~ - I- - - - - - -~ ^ T7 ZZ I ~7 221 T----*-----~ 0

1 i-i. 4 } :--3 = - 1, E I =. = 12 ij -i-+ 91

• Rili i ---f r +- : 23 :i 4

E : - - l ~' i M lj M :1_=.. .2.-t1iii1 f5 i -ti ilh -i~i-i fi -7 _6 - d.E -i - E % ~~ 1 i v . _; - ~ j. __ E iri.1-ii" i3:5 i_i1. ; h_E-is j -ii_y ;Mpjii" Lip l ; i-i_ g :ig q 'i 1gia --r _:(

::: a r : r:2 a i := ;- --- - :

_:n-.=,= =.-- =:: = -=_-. c : = - _: t.

2 :- =

. = =. : z === 1 = : : := = =~ t.==:: ===..===-==:== ::: _. Y ~ t

: z_ :.

]

r -----

_. : = :._:: =

=== = -~. ; : ===

tr.===:===. : : = =

d:.=:+ = - f: = =3: /d_LO_C97 ION - :-

r - x --.

r. !.... ___

___d___,

. a l. = -. :. -. tz _.==_ =. _ h =- :...

==- _ : =w : : = : = - t 1-~: L. : _ _- nc:

r;:rr;;

n. : T. -

3

---

+--i_

...__w ---v.__. ...__.4.__.- 2_ - - - + - - - p_ - ___- v_- - -. ._-_-_--t,__-.- _ - - _.--t.-.__. t- _. - g..__. _. ._y-... ,. s . p t_.. . _ _ t... _.. _ _ {.... .l_.... ._ _ _j. W _i. - - -. 7,. -- .--._.o._.___ __._.j_.. ~2" )0gj. i i y 9 / = q., -- 4.

-- - 4 --

- i - =. U--

--=A---- g g - :; i .3. - -i= _:ri _ qi l-4.=4 4.. p ] -l HJ lu l. ju-cul j - {. l : i.j 2 :.__: _ _ _~ J. :.. j

=

...i .. :. l

. ; : rl_i-l 1-id i_-i j-l i _-{i {: :.2_3 l.3-- i, }f,.; h 3 j [.; j -

d i i - i EJ :' ~ i M I iM-! M i :- : TNM M5'l.:4~? #i.- U "J : <~ '.jJ l l l_ i .p i.; ; ;..

m-1

2

[..~

.! :, g i l i.'l - -

• - - l q 4

' i- _;l Tc-l ..; i- _[~ c ;_pj i : ! O i;. I; .: FE ! i rz.T E: t -1 1_.._.: :. _.......u::=. + t . _ _: :._: _ F._.._ 1, __ _ _..... _..

: c. L:=. :-

3 l 1 FmVRE - 3 . ; g :: : ;- 7:.:2 r-g [~fiTj JRj [,5 ' i L 4 x-.i 1 ::.::n:=-. r:. h r_.- l== :v : x t L C9LCVL9TEDi AlMUTHBL iDiSTRiBUTiou __0F3MtM0M_:595T K1EUTR04 1 1. l.. 1. _4... 1 - :.'_;: !:r:.: ;_...~_:_...: c:7 FLUM (E M.o MeV): WITHIO. THE ' PRESSURE - WMEL' - - - - c _.. .l .. _ _I 6 i ....i.,. 4 ....t.._. j SU RN E)LL9MC.E CGPSOLE GEOMETR9 - - ' -3545 M OU-- _ = _. * -. -...

• • • --e-'

=. * *. _ ~

• _ * = = = +. _ = = -

+_..*.e-. o >o ao so i no so Ah MUTH 91_ bM E-bI 1

4 s-6- a ~ x - : + -. : :.

. ~,.2

z.. :

-..e =.. - -.. 4 d> \\ CORE MARGIN PENALTY ,m

3,_ ce - 1,.,,

m -.a - p ::

:. n.,. 3.,. v c u

c - ..~ Y f d J CORE AVERAGE KW/FT INCREASES ~. i i .: 4 l 't j I' LOOP 10% i t ~ 8% - 3;t00P i 1 7 i LOOP. 8% ? ~ a y - enc, a m + 4 - LOCA LIMIT DECREASES ' LOOP 10% i . LOOP 8% ~ : - LOOP 8% ~ ~ } ~ ?.. N... t,[:.-, f - f0H NTIAL RADIAL PEAKI'NG PENALTY- -s ,e y>,8 -l% j y."0 % s ^, '.~, 1 'y l - *y ;a tf+3; I +. %. - x); ,, y y,,,,. - ^,s ~L.. , +, p.: .., > ~. ,,o g .s y,,'_ se -. =, -. l gt. S ~ .5'-s ..,g j,' ej P, 8 ;, ;J- -T- 'b + Y f A ^ L ~g L % .'.$ fg. $l ~ * *. ' ' g,T , %-;r. Q.g.7',_,;]*,,'t[..' ^' l g # 'k, a - p. z %. ~. - t o, y g > qr s,7.,(.!, ce p.; yg; - r, _, 4 --a m n s, T,;. ; ',.+.e , ' 4..- +- ,y s 4 4. 1,. ' g 1 ' p-m e g

• e 1

3 i A k 4 1 I J e, e ....-_.~s-~.:--' ....--.-.=na n- - -:--------~~--------- ' ~ ~ ~ - ' ~ ' * - -~~ ~ ~ ~ ~ ~ ~ ^ ~ ' ~ ~ ' ~ ~ M V 1 u,.--- --,., ~. - - -,,,,,,, - -. ~,---r. r,,- r-n -. ~, -,, - ,,.n.,w-m-. ,~.--.-we--., -n*, 1e 'd

>x ?. - ~, . u* r,. -.. z , ~ w +. - - - ~ ~ ~ - - - - -

---

m

--o- .. - c 2 4 - 5 _g' a w ,i "' *.j% s,. g

4...

s u v. . u ,s - n 4 e% y ,t y-.*": - ~ q-n ' &, _ *y; : g 4 vQ t, _. 3mi

• \\

l f.4 0%% '1' ,a % f - tj s.4 ...,.~:%. ~.., p. _.1.. ~. - n.~ 7 ..y . v:., a3n_ m.,..: .r e 1,3 V..n, , n.m y . m a .e MnM1.g P.&,N, ECONOMIC.S PENALT.IES 'z m' n , ~. 7 ,w. -m.pw.- a a..t. a - a ~.n.., u x... w ... p,,;, ~.. s w. 1.. s. %I $700 MWD /MTU LOSS IN CYCLE LIFETIME N-d e . a s 2 f. .e ' t 5 3 +... $2.5% INCREASE IN FUEL CYCLE COST; s + ~ ^Y 4 _s. d-1 3g WD-FA-A 0 l w - 4 s , i ei-j vS d [ '" " i g 4p8 m b jA [A -g,i g,, s d$., -. - M k 'i,& pp,. ',,- f. Y 4_.,. gI e 5 g s e e G 4 4 + 4 .e' s; +

• J, y.

^ * * ~ + a e p 'a s -'A *. o g y^ *#7 'U_'

• v'.

9 3.~.,,, Jf

• 'y i,N/ d

.h h, ' e ,9 + ,,,g,f,.

• ., = a

_w: ... s: - " g& ,g* 'A,, ( - 'd E- .[ . M - ; n.s u. (* 6h.M.., . 4..-%,:y+%,s" % . T. x. m,, &,- s - n'?- ,p % "ar fd ' s 'f % *Ql?' f. M / y& 'gn h 5 $,s.,a,. _ * 'g. + v., h.qE f' u, s 'y a;:. J. g q n f 5 e 4..t u ~....,,*y*'" J ' /

gjF, y'

f f f /y m.,)h',4(ee', ' M'

4. A.

%'* 4_.) e%9 . _ g( + :%' , a,.. C t'fp% g.yiff $ M 'v$$,/ g:,: e s 7 3,.. 4 _ 44-g Ae w p ,..% 4 v f.v.

,;p y

-- ; gryC;p?~ j, *.yj p..y4 p, P .o 3 j-

v.,

,;~,.p

: q ~ s,% ; t; j f %- ),s.

? . w.. s.er,'. m m..- a s v k.,e x ,[ E., \\ ! , - M e *," N.,) <... i Y l [ 4 ."\\ f y pt.o - .c J r( g "X',S}., s! s. .,, 4,. , t. - ~ 4 i .j. -.+- ',,jp .v x. ' o-a o-e ' ^; p 3.- .= e ' '* L. s w "i -. ?.' [, i g,*,..,, ' Y r. 7... -- n u .l ~ e. s 6 y. i + +g t l_k'. 'l' s , e { y 0 I i j. g I g u,.. -.h .t f. -~.. .~, ~ e. ni .p' i M ___..m.._ d

~ } x i t k, n, s B E' LIE F'I T S . TO BE DERIVED ~ F R O M ' : Q,, gy;, ' ' ,.7. FUEL REMOVAL DEPEND ON .i

1. T H E TIME IN PLANT LIFE WHEN THE CORE CHANGE IS MADE

~ 2. THE LOCATION OF THE' MOST ~ CRITICAL MATERIAL IN THE REACTOR VESSEL BELTLIN.E

~. -

i.1 - e ,./ ' t m L p:::.," ; m.

• ACTUAL BENEFITS MUST BE e

B,Y Uv.sj:- u..,~ M ESTABLISHED 0N A CASE y .,4.~ . w.

•  ?? 3 ? !! h Jl. 9..,i CASE E' A S I S

, - - g ::n c c -Y';;1h.;; ' Th?' .9 ;., r ;lt *,:-s L. ;'.a?. 3. 3 p yy -y -r (s_.. s S I 3 / .---e v-w_,, .y--, - ,---.-._.a v -t."

LOWLEAKAGEPATTERNOPT[0N 4 lb e - No CHAT!GE Iti. CORE AVERAGE KW/FT - No LOCA LIMIT MARGIN REDUCTION WITH THE USE OF BURf!ABLE.FOISONS - FUEL CYCLE COSTS UNCHAt4GED OR POTENTI AL BENEFIT N , l' . t '. N O i -y t-a'" .., c ' [ g b Y - e g t ~ w 4 e t .I I )

UFECT OF BST WPEMTUPE Oil FRACTURE IE0WIICS ATLYSIS OF A HIGli CU 'ESSEL N6IIEMP (CF) iiltalua E PY FOR h111C!!10 PROELEM IS NiflCIPATED fio 10EFPY 10 E W B EW 10) 25 EP( .120 32 EPY (Et0 0F LIFE) / i

t. s-TI@ficl EIEOH A ETfcA1:1 0 5^0 1531 E0 f.G3 U10 12C0 18 2 1830 1E00 3E5 2020 200 313 211 0 3000 225 2130 3500 2&2 2100 1000 233 2uA LEO 2EA 2000 9fD 299 LA5O E00 320 1900 i i i I i 'k l' i i 4

\\Ilf 1 l { <) iij c a M TS 2 2 2 1 2 2 A 3 3 3 3 3 3 9 9 1 2 2 2 2 6 G. 3 3 3 3 2 2 R 14 / ~ H 2 2 2 2 2 8 3 3 3 3 3 2 STNE I ~ S 1 N R A S R A 2 2 1 3 T 3 3 2 1 O CES -0 1 9 0 9 N 1 ~ 1 R R G. 2 6 3 1 0 R 2 1 1 3 [ 21 S 3 TL USE H R 2 2 2 6 'x 3 2 2 3-YRM t IM i U B E S R A 2 2 2 4 6 3 3 3 1 1 P 99 1 7 G. 2 2 2 3 1 3 3 1 1 7 R J, H 2 2 2 2 8 3 3 3 3 2 n uE DE tV nP ER PT 1 2 3 4 5

• 6 e.

tY R c SA C \\' l lj i 1

-~e-- l-l 1 l l l i O '/" ICC p __ _ _._ l, 1 / g -200 j / g -400 g -350 a. -600 100 o 2 0 e2mN~ T MO, w TCOLD R -200 ). kJ -230 r i I I I I I I -no -300 0 500 1000 1500 2000 2500 3000 3500 4000 TlHE(SECONDS) Su stent lmE FREAK - EEACTOR C00UV6 IhCSSURE NO TDPERAREE VERSUS I!ME I s'

I l PELIMIMRY ESlJLTS FOR Sml.L STEAM LINE BREAK TRNSIBIT PuwrTYPE 2 LOOP 3 LOOP 4 LOOP TRENDCURVES W ' R.G. ASTM W R.G. ASTM W R. G.' ASTM 1 32 29 32 32 20 ~ 52 -32 i32 32 ~ 2 32 21 32 32 17 32 32 .32 32 ~ 3 32 11 31 32 24 32 23 32 4 31 3 32 5 28 13 16 23 ' 10-13 32 22 29 e I I

• lli rr.r muta n

REACTOR VESSEL INTEGRITY GENERIC ANALYSIS CONSERVATISMS OVER ESTIMATE OF CU FORAblVENGENERICCATEGORY NO ALLOWANCE FOR SPECIFIC MATERIAL FLUENCE ASSI)M) TION TH'AT AL.t, CRITICAL MATERI AL b!STS AS A _0NGITUDINAL WELD NO ALLOWANCES FOR RWST TEMPERATURE > 32 f 140 f NO ALLOWANCE FOR LOW HEAD SI PUMPS NO ALLOWANCE FOR ACTUAL SURVEILLANCE CAPSULE DATA USE OF GENERALLY CONSERVATIVE IRANSIENTS NO CONSIDERATION OF WARM PRESTRESSING BENEFITS ~ G G G g _, _

.t PRESSURIZED WATER REACTOR LICENS'EES Docket No. 50-348" Docket No. 50-334 ' Farley Unit 1 Beaver Valley Unit 1 Docket No. 50-313 Docket No. 50-302 Arkansas Unit 1 Crystal River 3 Docket No. 50-368 Docket No. 50-335 Arkansas Unit 2 St. Lucie 1 Docket No. 50-317 Docket No. 50-250 Calvert Cliffs Unit 1 Turkey Point Unit 3 Docket No. 50-318 Docket No. 50-251 Calvert Cliffs Unit 2 Turkey Point Unit 4 Docket-No. 50-261 Docket No. 50-315 H. B. Robinson Unit 2 D. C. Cook Unit 1 Docket No. 50-295~ - Docket N'o. 50-316 Zion Unit 1 D. C. Cook Unit 2 Docket No. 50-304 Docket No. 50-309 Zion Unit 2 Maine Yankee Docket No. 50-213' Docket No. 50-289 Connecticut Yankee (Haddam Neck) Three Mile Island Unit 1 4 m 4-M M 4 Docket No. 50-320 -tixdaeakoona4meesmis Three Mile Island Unit 2 Docket No. 50-247 Docket No. 50-336 Indian Point Unit 2 Millstone Unit 2 ~ Docket No. 50-296 Docket No. 50-282 Indian Point Unit 3 Prairie Island Unit 1 Docket No. E."-255 Docket No. 50-306 Palisades Prairie Island Unit 2 Docket No. 50-269 - Docket No. 50-285 Oconee Unit 1 Ft. Calhoun Docket No. 50-270 Docket No. 50-344 Oconee Unit 2 Trojan Docket No. 50-287 Docket No. 50-272 Oconee Unit 3 Salem Unit 1 f /

Docket No. 50-244 R. E. Ginna 1 Docket No. 50-312 Rancho Seco- ~DocketNoi'50-206 S.an Onofre Unit 1 Docket No. 50-346 , Davis-Besse 1... Docket No. 50-338 Worth Anna 1 Docket No. 50-280 Surry Unit 1 Docket No. 50-281 y Surry Unit.2 Docket No. 50-266 Point Beach Unit 1 t. Docket No. 50-301 Point Beach Unit 2 Docket No. 50-305 Kewaunee Docket No. 50-29 Yankee-Rowe Docket No. 50-339 North Anna 2 Docket No. 50-311 r ) . Salem.2 .y

v.,

, +

-

rf i /,p) Docket No. 50-327 , r, 'Sequoyah.1 ' - 4' I Docket No. 50-369 .McGuire 1 t Docket No. 50-364 Farley *2 m : :+

• 'W

~Mku y = e 7 4 d e ,~-y,e_gw-,.+ my.---.,,_,,,,,u,m y-- m.,,.9wr-y w-,,,wy ,s y y. p, y,,w-w r m .w- ,,3w-- 9 y v- =}}