ML20040F625

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Requests Technical Assistance in Review of Util 700226 Application for Authorization to Construct & Operate Two Identical BWRs on Schuykill River.Extract from Review Plan Encl
ML20040F625
Person / Time
Site: 05000000, Limerick
Issue date: 04/22/1970
From: Morris P
US ATOMIC ENERGY COMMISSION (AEC)
To: Case E
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20040F238 List:
References
FOIA-81-385 NUDOCS 8202090427
Download: ML20040F625 (10)
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E. GLCase Director, Division of' Reactor Standards. .. s > e-f., . y;.,,' -u-y iy .,a , - vr.. 5 , : r. y @y.[ TECHNICAL ASSISTANCE,~ REQUEST NO. .1-4,LIMERICKCENERATING;j'g. 50-353= V c,. .,,e,

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STATION. (ISS), DOCKEI liOS. 250-352 5;.~.!. 3. '..- ,.e, : ? t._-. ..,. m. p ^:.T :... c-;:.: .n... Tc ; w . ~ ~. . g -; ; cc ~ y ).[. ,} ~[ I j Wd ' a. Memo to Director,.DRS;' March'11',~1970; subject:. " Status Sn-ary c.. . i-p . 4'.L. of BWR Project As'signmentsf";-. ' -. *,' .M - . 's. .' 5 ~.

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A - v. X. .z,. 'W ,7 unctions. and Assignmen.ts."....~t ~ '" Transfer of $ J L T.2. - ~ b. Hemo to Director l DRS,4tarch'25,1970; ' subject: ~ D..' .. a. -0 '..c g. ' T. ' + - ,+. -~ w ,,-,..(,.3.... , Philadelphia Electric Company $ filed...,an application dated 7ebruary!26,.,.. . ~.. 1970, for authorization to construct and operate two identical boiling y) water reactors on the Schuylkill River about 1.7 miles southeast of Q. Pottstown, Pennsylvania, and 21 miles northwest of Philadelphia, ? Pennsylvania. George E. Lear, BWR B anch No. 1, has been assigned 7 as the project leader for the review of Limerick Generating Station.(LGS). y We request DRS technical assistance in order to coc:plete the review of f this facility. A proposed review schedule and a prel hinary.. review plan, ~ k ~ for.IES have been. prepared._.A< copy.of the proposed review schedule; i. 7,. u. ?-- is appended as Attachment 11.d An stract from.the review plan islappended ~# y ~~ as Attachment 2..The extract lists tasks for which we are requesting specialized review froct DRS. It is requested that DRS personne1' 7,' initiate their review of the outlined items and be guided by thelattached _p schedule. We also request that a stenary evaluation be prepared by,. July 1,1970 for inclusion in a preliminary report to the ACRS.', ",70. - - [ 4 u -W Please advise me if the proposed review schedule, the listing of tasks t., to be performed,-and the concept for this initial review are acceptable i 5 ....,] c....-. _. end eatisfactory. -p , a. , ~.. j .. x; :., d

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y x... . ',~ '.' 2.*,f_. {&. , m..,,.,5R',,. Y s,* A : . w.m, I j ' .s.."'*ye- 's. [ - -.. Q .,.. 3... 3, e .a ,,...e ..<.,:.~.. . ; ;;;w. + ~ p...* s m.,.,..,;,.. y.. y. -.u.. os, y.~_. p $$y,y.q - .n.g ; . y.p;[.y y, _ 3.,-.y,, c.. g.-g nf, s. fy :g.. c.a.. 4 w. y y:: a, -L ~ (ME) 4.4. Review and evaluate ' ability lfor einservice inspection of the freactor 9 'A f U p coolant system and conformanceSwith Section II, ASME Boilei'and Pressure ?' ~1 G g.',.. 1,Q q -/M[7. ] Tl ' "VesselCode,' January 1970.,v,~jQ,,e.;.] - :. e g - N.S a._ k. a:~~ ~. -.... y x. J... r. .,......c.. x,:c - u.;-.. :- '.'.(MSM) 4.5 Evaluate extent, adequacy,: and,, appropriateness: of neutron irradiation 2. ..1.; f;!.. '. ~ damage testing and also.non-destrpetive testing of -components of.the - u : -f. 9 X ; 'y. .-Q. ' '- '. : '..v'[:. :.. : ll.l. Q~ ~ Q.. [ b.h _ ' i reactor coolant system. :., Y 4.'3 n. 4: .r. 4..<>.. .. W '?o:i.'. ~::,;.n O ., +. ;. ' ':.'-'.. s. S.- 1..: ~,.. ". -~ (SE) 4.6 ' Evaluate seismic design (Clas's 'I and Class II seismic) of equipment ~ ~ ' ' [4 and piping, to include restraints against seismic forces. Evaluate potential for generation of missiles or pipe whip. Determine adequacy 3 of restraint or protection against missiles and pipe whip. (USC&GS y and Newmark & Hall to act as consultants in review of seismic design.)

  • /L5 5.0 containment O

x. -~. h b' {; 5.1' lteview all significant differences from previously approved. facilities J '." 'I F[,' '(Shoreham Nuclear Power Station may. serve as a. guide foracontainment. . review.) Specifically, identify,and ' evaluate.significant differences in: S z. .O j; (SE) 5.1.1 Primary and secondary containment structural design. Note that the h primary containment design pr'ssure has been reduced to 48 psig. { e Special interest should'be afforded the drywell floor to containwnt s wall structural design. Check capability of the. floor to accept p thermc1 stresses and differential pressures of the 10CA. 2 a 5$ .(SE) 5.1.2. Naterials testing for installed equipment and building materials using j appropriate code techniques. Consider reinforcing steel, steel liner, / ~ 4 concrete, cadweld splices,~ sealants, insulation, vessels, valves, and 1 pumps. c.,. l (SEV & 5.2 Review and evaluate calculation of peak pressure in drywell and i.. SAN) suppression chamber following a LOCA. Note that peak pressure indicated -I( l 1s 38 psig which is lower than earlier approved values for this -2 containment concept. This value is lower than independent DRL ~{ calculation of 48 psig using Miller paper Ro. 68-WA/NE-1 " Pressure y y . Suppression Containment Design-Current State of the Art,".ASME f f Transaction, 1968. A CONTEMPT-PS Code run by SAN Branch using 1GS T inpus caca is. requested for evaluacion of w.-oechtei. casa.. M l~ W...

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^ -a n.'wr..--tZU.c.li'; ;forth in Appendix:C,' tor.the K.SAR t. @ f

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Jc(ES) 7.1.4 Nuclear system stability analysis; include potential for xenon oscillations.- . :p 's,.. ,~ o s ~ T,;(ES) 7.1!5 Process computer system. "',.. ;,. J..., ,L, e.. .. a- - , '.,, e.-..,.n. u u. ..+ :. t. 7~ . :, e., ..w...< .~.. Evaluate conformance with'IEEE;279:for a11' systems performing m safety... R (ES) 7.2 6.'... ; or protection function. -Evaluate; freedom from loss of protective or',. ~ l safety,functiods-by co-an mode failures and systematic failures. ' ' l 2 '(ES) 7.3 Evaluate the ability of the protection and safety criented instrumentation and control systems to withstand the effects and environment of the 7. - 4 postulated design basis events as well as the pos'sible natural phenomena ' V.., ' ' ' described -in IEEE 279. ' '.1 J4...I. 3 s.,.. g-.., + +-*.* ,........g. 4 ...a ..w. . ~.. v. .... a. p ',. :.:,;- ~,. s :.

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.. - r .,5 v vn 'F f4'1 8.0 ... ?'e 'J%k.W.3-Nhh hfh[Wfd.flGN k {ES). 8.1 Identify. and zvaluate allisignificant.differenge's.from'previouslyb.. G;,'Cd Y% ^4 ' g:(:.:.@ 'i ' particular-attention 7to;th;e';adequae'y-ofTsupplying ~ power-t i -. -y.. approved.. facilities.forPoffsitei'onsite. landde powe'r(systems lvith".FE) criented-idstrumedhMansitsd'equipaeut.oif,giy".'$, w.jnf4$7.,M, J-f q'.P.'~^.,',;cd.$ and eafety7 .,.. y mw + c< t.:em,%.:.w.- rf, mmc.n,t-'.- 3;Qw,;t.cm:,., b4;l ^3.,, Z (ES)f SJ2,' Evaluate operational <capabilityQo'fsthe 4mergency; diesel ~genera w_u.e.-,..y,. ..g.. e, -.ww. 3 j 7 :..,... .. v w. - '.... e. W s w e.:. '..: ,,, '@M.'W Q. ' ; *.W' Check sizing and'redundaicy!fo6s6pF1 ping power.toMfe'ty.'),oadsifn" p D*[. t -J.Q.Y-conformity vithicurrent<criteriii.for rating"a'n'd"opirating:eme s ~ d .e.o(ES). 811. Evaluate t. conformity.aof Class ;.E electr. .genciatdrs.M;- w k. M / ". dieself ?_ .u-;y ~,.%. G.. WW

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. '.. "IEEE-ANS Standa' ds'ProgramOleportid9*Mrith < enclosure deitledit M1).Y-$QJ/; 'e r " Obtaining Power from the Transmission Jietvork for Nuclear Puele'd}. j ;. ~ ' ~ ( .4 W ' ' '. Generating Stations. " Qn.U: ' ef..;'.. I,p.-,.' .. m... x

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f';(sZ)210.2 ? Evaluate.de,signiand-inten3ed aise..cGthe kspent' fuel istorage2fa'cilityyrg-g-Q

~ .~. .'..:.f to prevent; inadequate? fuel :cddling in:the ' event of 'midropped'caskR *T.!i,C~ i =: '

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8 .. w t7 (SE) 10l3, Evaluate struc'tural protectionhof. the'stpent;;fuelnatorage3facilityjsad 9.6%',:.:. 7 -refueling canal against utssiles or dropped iobjects of large mass'.;_g'%. '. xL

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...:~ ; g. :.g. (SE) -12.1 ~ In conjunction with the ' review and evaluation of the. structural'tlesign ". - 1 of the containment, accomplish similar review and evaluation of structures

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~ listed in paragraph 12;1,;J.CS PSAR. Consider also the structural' design G of the circulation water intake structure from the alternate source (when designated) and 'the protection' of the.Schuylkill River intake. ' y O.5 structure against' river ice dnote. that little information;is now j;..,. .5.. !f ' ;' available in this area)..? Consider structural design of-turbine building ~ , +.. and consequences.o..y.; failures:siue to seismic disturbances or. tornadoes. f l Q.

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.<v ' ', a-Philadelphia Electric onpany filed ,(1 :; 1970, for authorization o constru and operate two identical boiling water reactors co the Schoylkill iver about 1.7 miles.acutheast of ~ 9 S Pottstown, Pennsylvania, 21 iles northwest of Philadelphia, p., f' ,Penn=ylvania.. George E.,14ar 'R 3 ranch No..1, has been assigned:' a.. . ' Y-as the project leader for? revieir of limerick Generating Stati.on-(LGS).1-I." f . w te. y. ..' J D,;,.: r r..'y. - ~w m...., a...-. .\\. v.cr.,- .n: ;kM% a;.:&,, +..~..-@.r - .a n v:,: w,e.7..;m:s )c.w .3 ..,m 3

ord.er.sto coWple.t'e,<t. hiere. view 4f443;.

u, w. p ~z~ < - y of.the proposed.. review].yi..{.4~ ~E.. Y . sis ta.ne.".Iin..dule.and r.aj.. yW. p.y u... e 4 request' DES.te.chsd...ea.D .C.C-." ^' w w e n e ,Q,. 4 review.s e 7 this facility.g'A propos gy .j ., J-q 3 e.. plan for LGS:have'been. eparedp-Ac v.:.... g . schedule.is appended a. Attachment 1.. extract. front the jreview'gh4Fyj :';(. gr. 1 Fact 11sta d. a. s.k. s for-whic.h.:V.-E.,N/;~- ~ N,... W M c 9. y*m. plan is appended -as. A tachment '2. J The... n . 9 n s .. It.istreguestedFthatr. 4 jg ' alized" review;from- -eq.' N ve are requesting a i 73 ~ DRS personnel init to their review-of Jehe ' outlined -items.and be~ N.K.s. j h 1, j r,. ?, J rW M.. (~- f.. s VM..,y%.. v.,a z.& ', , guided by,the at ched. schedule'. W Y M.p;n. e.; - . y,, .n ... s. >. y _. - ;n g. m..:

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