ML20040F642

From kanterella
Jump to navigation Jump to search
Forwards Request for Addl Info to Complete Application Review.Questions Relate to PSAR Matl Re Containment & Other Class 1 Structures
ML20040F642
Person / Time
Site: 05000000, Limerick
Issue date: 07/02/1970
From: Case E
US ATOMIC ENERGY COMMISSION (AEC)
To: Morris P
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20040F238 List:
References
FOIA-81-385 NUDOCS 8202100007
Download: ML20040F642 (5)
v • d • e


Text

{{#Wiki_filter:... m y. Q p

g..

p:- 7,- .G

  • -e

~ v-

-z, a-

_!E -1: .JUL. ~y' n,- c) ,;y.. n..- -?. if .* ~ f-s- _4 -w. - *w.- s.. g ... n. 'fl. ..y

4. Q.

y.;5? fr.. - f.; y,. _n -~

4.. y.

3..g.~..a., o.s... " ^~ 9 Peter A. Morriss. Director ~ '. Ea '") Division of Reactor Licensing 5 9 .: po r , PHILADELPHIA ELELTRIC COMPANY, LTMERICK GENERATING STATION }%- c IEITS 1 AND.2 - DOCKET NOS. 50-352/353 1-4? t ; v. Adequate resigmses to the " enclosed' list 'of questions will be ;; g,.. s s 4 - * .9:;. fj' required before we can complete our review of the subject appli-c.~. a Tnese questions relate to the material presented in x. cation. o h.5,; Sections 5.0,12.0, and Appendix C of the PSAR concerning the .?:- coo minnent and other Class I structures. (.- The seismic consultants' 1; r .w l questions have' not.been received and incorpor=tal -E. ,\\ '. h. a$ .s 3 v. a x_.- ps C ~ Original signed by g -g; E.. G. Case Edson G. Case, Director 'it Division of Reactor Standards 4 h Inclosure: y List of Questions: ~ y. ~ cc w/ encl: G Distribution: R. Boyd, DEL E. Maccary, DRS Suppl :: -I l D. Enuth, DEL DR RP D --- 4 - p A. Droserick, DRS DRS RF 7 G. Lear, DEL SEB RF T A. Gluchmann, DRS - bec: E. G. Case -4 C. Arndt DRS -a e F. Schauer, DRS 4 R. Shevnaker, DES T .j N. Davison, DES... 4 4 - - DRS :S B DRS:SEB. DRS. /E ....DR5 inOt f f ?4 omer> $ ) p. . b.......... 'M*

c., -

e er RM r 1 ~y gap *: v sunNAur >...s,... f- ] - 0 _{ 6-30-70 ], _ 7 { -70 7- ) -70 k oart > "'g'{0[1h00Ok 811019 E $SYz!Esi-ass pDa

m -c.,- t. ~ , ~ ~, ~.,, _ r(. z J m 3 s. ADDITIONAL INTDRMATION REQUEST ]; ' ..g- + ~~ .v. .'.t...,.,...- LIMERICK GENERATING STATION . UNITS 1 AND 2, y ..: ~ M .. DOCKET NOS. 50-352/353 .'t.;; l S ' ~$. t. 'h . ~ -a i - 'U, s 3 ; '( _ 4 :+.;.y,;:. k L'-.'..,1j;. Justify the use of the load hetors specifiad -in Appendix C, which~ are ./ Al

s.. _,.. ~

t. m. i' -Y;# 2'. less than ACI 318-63 values,nin the light %f the ' fact that the' rest .s S , v ~ - 4l p~ - :.,. ,,,.L'-

  • n.' y d ~ ~.,' of,' the ultimate strength design' approach ifollows..the ACI 318-63 tode.

'7,,' c : e s-J- , g;.c q '. ..c, - y., .'a y. C.. q:% 2. .i - -Q: OT.[j[.f ' [ Mere the ult-immte strength; design _ lonii; factor on tornado in 1.0 as noted gv ~.,, - -i;% - - m9 ~ 1 ~~ - D ".. c . y.- - %@n .,... in Appendix C.-A design 11mitof.0.85 f'ci which is the ACI-318-63 Code ^',g,. y.O definition of concrete ultimate compressive.atrength for concrete, would 6 s S.; e 3; not be considered to be adequately conservative. Specify the concrete ' s. r2.. compressive strength limit which will be used to provide an adequate OX1 design margin for the specified tornado loading. v. -b 3 In order to permit evaluation of secondary containment, clarify the Y. c,c C ' ", U location and Llayout of the pipe tunnel referred to on page.5.2-27, since -j ~ >. _.m _ no description has'been furnished. - m. A N- -A 4'(..4 N... Y ~.. Describe _ the criteria to which the joints between the primary and secondary I T.- -f.c. - m -containment will be designed., and how these criteria will be met, especially i. Mr vhere the joint forms the barrier between the interior and exterior of the n. j'] mecondary contaiment. 'h .~ ~ 5. For the alternate liner anchorage systems given in Figure 5.2.4 and on 3 page 5.2.2, discuss the design approach to preclude undue buckling, j including a description of the anchors, their spacing and the attaching .~; welds,

..l --

hk ~~ -J ' '6. Indicate whether diagonal reinforcing will be used to carry earthquake G.7-y%, tangential. shears '.in the primary containment,.as is currently being s.. %;r :. ,,c: s :. 3 .m ? ,,,.g,4*,- I-s b "5', @f?s',{'. - l-1, , p'7,.y. ~ ~ .;;.. :.~ 'E r - ,p 4 1

) p 4- -2. ={ f r ' y - provided on similar containments for. structural integ,rity. such as' the. i) ~ -+ ...u.. ) Q Shoreham Plant. t 9 r

7.. State the design differential pressure across the ' floor at elev. 236' -O"

~ .y y ~ under losa-of-coolant accide'nt conditions. Also indicate what initial .-C i and subsequent testing of the. floor with r.egard to strength and laakage ., - ~ T. . '*..^ ' ^ -

  • 3 s

. = - - 3

will be performed, and how it.will be carried,out. 'Specify the mart =um s-...

4 allowable leakage without resulting in overpressure of either upper,and .e -- " ~ lower compartments and design leakage through the flooi,~ including the bases upon which these leakage values are deternined. 1 4? 8. Indicate the canner by which the joint detail for the floor at elev. f n 236'-0" (Figure 5.2.2) is considered' to be adequate as a leakage y, V barrier and how it will handle differen'tial pressure under loss-of-coolant',. ( ..s.? '.. ~ .n

  • .- ;.,.. ~.

~. accident conditions,' and the thermally-induced ' differential motione be' ween 4 ~- t p ( 4 the floor and the vall under normal opedation., Also furnish the principal 4 . -, s., -. e ~- p . dimensions of the contafn=ent and the liner. 9. Indicate the =mnner by which the vertical shears will be carried at 't (f ' the support ledge for' the ' floor in Figure 5.2.2, and.at the support. ledge.' i ~ w for the dryvell head in Tigure 5.2.3.- to assure structural integrity. h Uith the rigid connection between the drywel[ floor (elev. 236'-0") 10. and the vall shown in Figure S.2.2, describe the handling of the s following resultant intaractions: a. Increesed shears and bending moments in the dryvell wall above. ~ and below the floor and at the base;y ~ ' {. ;..j - 4t* .f g e,. d..,., 6 .. {,. ,p.,.,., g, ... g. ~: g a.. y e -a. y,4 Fi 6 g ~

1 r - .J '. a j ..;j.. p -. m,. : 3 r, _~

- ~.

J -S. ;f; f 2.- .,.~: *. ,s .,-5<..,,. ..:. ~.

u..

.. ~ 5,~. '.. g w-b. Increased shears, tension ' and banrHng moments in the floor;,and,. l . q. ,,,..,_.g- .~ . w :.r r. .v.:..,. ,,.7 ,..n ar. y Uplift at the floorM dge due to downcomer jet. reactions and.', s c. ..:.c__ Q.. y,. ' l ~ . :.- y vertical thermal growth of. the. reactor ' support vedestal.,.m ;4 -y,4.g.. ? l i v.f. 1

  • 6.lf ~ e

., j.,... ,.~: ~<. .m. ' ll. For the reactor support structure: (a}. discuss bow.the.horizontalishaars),.' { o 3 . y.. . v. s .a. .s

;,3

-ara carried by,the bolted support. system at the -reactoriskirt bas'a'." r,.. - s.' .. g '.:x,['d ;d 3 r- -.,..... *.... y.. g:.*. x ..,.....'...a, >*y.- g 4 .,w- .2, (steel ring girder)., '.(The upper and lover' halves of L h'e' aupporti: detail'.7... \\ 7 t 1 '." s K f:: ;:n.T f ' .i - i.g: . ; :;e. w'. - are clamped together with bolta, cmd friction appeard to-be the means of - r.

w...~. -

c y,..- , a. ~ resisting horizontal shears). Also, indicate how the shears are to i i be transferred to the coucrete support, and (b) list. the allowable ] I stresses which have been applied to the critical elements of the support- [ l ing structure, including the reactor skirt, steel ring girdor, bolts, [ and the concrete. pedestal','inider the -ccabination of design" loads 1rhich y..~ .....m,.,,y..s. N ; :.x y..._;-f;. .v. ..,.a.. ~,.: .3 results in the east highly. stressed co,ndition.,; Discuss. thermal gradients ~ . ~ l . State l used in the design, including startup and shutdown transients. .j. T to which code' the reactor support skirt will be designed. ~

12. - Explaf n the bases for only. electrical penetrations having, design provisions 1

, s'; for testing and not the -mechanical penetrations indicated on page 5.2-28 3 I I \\ i and Figures 5.2.5 ; 5.2.6, and 5.2.7. j 3 ( f' I

13. With regard to quality control of reinforcing bars:

Indicate whether the user tests -on reinforcing bars (p. 5.2-17,.18) l a. l l vill use only full size samples, and what procedure will be followed } for determining the acceptability of a ship.aent if full size user [ s tests and mill tests (which to date have'been most19. ton reduced'. , j;. f> ~ y ' 9. ;. - l , J. g'. 4 < 7 -3 ~~ a +- '. L.: ...1-size samples) do not_ agree.~ 4,g,*..'.f...., l' . x,n,..~.. . w t ) ' '~ ~~ 9 i g

~% n;;-. . ; *~... .u s

4..

x 7 ~..:,,;. .. ; s... \\.' ' 45, a y . e Clarify'whether are welding of rainforcing bars' (p. 5.2-19),will b. .-' T,e - ' ~ , n;. ' ;. '.e .,. - ~ -

pt, a
-^
m.

be permittad,,and if so, what ecetrolled"chMatry will be used ,,,. '? ' - ' *h;*- n*, , 3 ; + ,q ~s- ?*;* - a* _

  • 4

'. ~ .s -c; M 9. s. * ;, * '. m'!.. ~ np = f p g, 1. ~1.' Q' , _ [~.. for these reinforcing bars. '^ 1 -..z. :. n.,,.. c. 7.. .c...,a

14.. Describe whether test ch= mal = will be used on, all. liner seams; or. just:

.c.

  • 9 :, y * '*

~ y.;,,.. .e '?*- .:. ~... s- ..-v,s.~.< . p%. +..: those which will later be.inacceasible, such as' at the base,. mat;'Do s 4 ..,,:.~. ...e_~..-. -v ~. v state what percentage of the liner seams 'will be radiographed (p.'$.2221). e- . %,G.:. ' . '.h;. ;r*~;-{ >. A.~~ 15. State whether the containment can be tested to full desig.2 pressure at -. any time during plant life in order to perform integrated ' leakage rate e tests, as required by the proposed /2C General Design Criteria for liuclear Power Plant Construction Permit. -f 15. i Indicate whether base elab -vertical deflection measurements will be made 6 n k 9 at the ' edge and contar of the slab during the prooftast in 4rder to ) J measure slab bending to verify structuial. design. ,g. I w r concrete pedestal is anchored to the foundetion g. ,s

17. Describe how the reacto' b(

mat against seismic and blowdown loads, and how liner integrity,is y maintained at this point with regard to containment leaktightness and h s... t [ r, t penetration of water seepage between ' liner and backup concrete. x. l. t' sgw l ~ k. l t l .-e. ,.. i. e O ..p g s c-p e v g E +h-a e '.I

  • g **
  • i 8

t. I4 ..*7 i.--i--i.-- - - - - - - - - -}}

Retrieved from "https://kanterella.com/w/index.php?title=ML20040F642&oldid=4553206"