ML20127M847

Forwards Final Version of App a, Division of Reactor Licensing Staff Rept on Field Erection of Reactor Vessel, Northern States Power Co Monticello Nuclear Generating Plant,Unit One, for Review & Concurrence

ML20127M847
Person / Time
Site:	Monticello
Issue date:	04/28/1967
From:	Boyd R US ATOMIC ENERGY COMMISSION (AEC)
To:	Lofy R PARAMETER, INC.
References
NUDOCS 9211300489
Download: ML20127M847 (18)

Text

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1 April 28, 1967 Seeket Be. 50-263 -

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Mr. Richard A. Lofy, President Parameter, Inc.

13545 Watertown Plank Rd.

Elm Crewe, Wiseensia 53122 I

Dear Mr. Lefy:

As disenesed in your telephase conversaties with D. R. Neller en April 28, 1967, a copy of our final vereien of Appendix A'

" Division of Roseter Licensing Staff Report om Field Erection of the teactor Vessel, Northern States Power Cagamy.--Neaties11e-Nuclear Gamerating Plant, Dmit 1" is enciceed for your review and eencurremes.

Thank yes again for year kind assistanes in this matter.

Siseerely yours, Regar 5. Boyd, Assistaat Director for Reacter Projects Divisies of teacter Licensing Eaclosure Appendix A Distribution:

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• APPENDIX B ITIVISION OF REACTOR 1.1CENSINC STArF PEPORT nN -

FIELD ERECTION _ 0F THE DEACTOP ' VERSEL NORTHERN STATES PO' E" C0"PANY-unNT1 CELLO Nt! CLEAR CENERATINC P! ANT.JJ1T_1, Mo'IET No. 50-163

'l.0 IST ROD 11CTION

.The Chicar,o Bridge and lion Conpany- (CEI) under cont ract with the Gene t al Electric Company -will ficic crect at the preposed site tbc reacter vessel' or the.-

propc 8cd Monticel lo -Nuclear Generat ine. Plant l'n i t 1.

The *roposed 1,325-acre site is located on the we,t bank of the' Misatssinni L "!ver in Wright County, Minnchota, approximately 3.niles northwest o f Mon tice llo, innesot a.

Field cruction of the reactor vessel, the first tire for a nuclear mwer plant in the l'nited States, is a practical necessity in. this case because the site-is inaccess-ible to a barre of the capacity necessary to transport a conpletely fabricated react or vessel.. The site is also not accessible to ready overland transport.

The reactor vessel will be crected at'the site from pre-assembled senments small enourh'to be. shipped by railroad.

The design of the Monticello reactor vessel will be in accordance with the ASME Code, Section IIIr plusLadditional and more strinnent,requironents imposed' i

by General Electric Company APED Specifications.-- These~are identical;to-the' requirements imposed.on other reactor'sessels currently being shop fabricated for q

Gene ral.: Elect ric.

Dur evaluation of the technical' feasibility of erecting this-

'l reactor vessel in the field has' focused on those design features or fabrication procedures associated with-field erection which dif fer - f rom presently accepted q.

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r. hop practices.

Because of this, our review and evaluation has been influenced by the procedures cutlined by CIMI for the field fabrication as well as expected i

I terformance by C36f pe nonnel. Thus, our evaluatien does not encompass field

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fhrication of n ;v.t c r vessels in eineral; rather, it is directed solely to field

'A rientinn o: tue "Atl a !!o r e t. t o r. t e m e l b : v361.

A p t t e. s e n ti 1,ultant, i'a rar.e t e r, Inc., of I;l n <. v o t e, h'isconsin.

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,a ant There ase ten, rete al

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l at ive expe rivnce of.ror oxirtatelu 200 years, in addition t o the review by Pavineter, Inc., scrsennel, l'a n n:.et e r, Inc., ha, at olle d itself of the services of ceveral in6ependent consultan

+ho are hirhi* rualitivd in r eefalty areas such as weldinn t'tocc ues, vn-Ce n t m t i c te t in, and AS"F Code cunaiderations.

There,e rs ons, n r' na r d i-in rettrentat and c mi, ult in - indewndent iv, have aaent 1;tetines in tht,,.-

wecialty Helds, are nationally kne.-cn,.ini have cont ributed l

hinni ficantly in advancing the " state of the art" in those areas, i

l Parameter. Inc., has been u.ied durinn this review to advise us in specific l

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subject areas and also to confirn that our cencral conclusions regardinr. field

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l fabrication are well founded.

Parareter, Inc., has reviewed and concurs in the i

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The reactor vessel which is proposed to be field erected will be a vertical cylindrical pressure vessel with an inside height of approxfinately 63 feet and an inside diameter of 17 feet 1 inch. The cylindrical wall thickness will be 5-1/16-inches cint un slus 1/8-inch mininum stainicss steel internal cladding..

The bott ar: head Jollst

.! u th :.rh.hich centrol rods and instrunent lines pass f

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- d n b.u, thin nera plus 1/8-inch nininu',,tninless steel

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,e 2 -1/lb-inche n nininum plus 1/8-inch nininun stainlest t.t et 1 e l. ns : r. r 4

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.f tbs prinary slaat will be centrolled durine norrnal nseration nt a r *,2 a w 1 -.

wu -i c.

The desi cn : rc uure for the reactor vessel

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<.lu. 57 in accordance with AS11E r. ode).

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.nroud ar.d the vessel will sicnificantly

at e r n t :.s am a, bc tw n th. tore W,. <

....t neatica v4 osure of the tessel at the re wtor belt line, Exnoaure 1

tor the li f et ime ei the sc-4n1 will be-an'rox'. rat ely 8.2 x 10 ovt for neut ron ene r ;;t es P.reat < r than 1 Fev.

Th t:. exposure corres und4 to a naximum NDI temnera-turc shift of 80*F.

Steam will c dt throurn t our Ibatnch nonles in the reactor vessel body, he lie f valves.

romt ed en vn)(a in the r.ain steam li-In addf tion.to the s

faut steam linen, the reactor te w l -ill have twe 3b" x 2E" re.cf reulation outlet penetrations. ten 12" rec i rculat tan inict nenctrations, four-10" feedwater penetrations, f our 8" pene trat icas fci tore s,rav, f icodin n. or in,t rueentation,,

plus a nu. lie r. o f s f a lle r

• er.ct r at i on +. - Ihc lower head will be nenetrated by the '

121 6-inch ceat rol rad drise nou lss.

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1 : n. reacter vessel will be supmorted bi a steci skirt, the top of which will

[.00 be welded t o the hottom head of the vensel. The base of the skirt will be w to a sunport in' steel cylinder ri siny from the secendar" containeent vessel vhich the support for the ve n c! dur'n < rect!on.

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.hich must br ac::; ned t o a c re,t the e f rh t t ' the n +1 ic: t ever 93 9 4 e!) t u, t t..et i cn." d r e, t s d:, t he eve r-ol!. c :Im et ti r

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r c + 7 0 c t :- fro ~ t i.e da ;i m

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I d9 to noted coevleusly, tic rest - :

es W ill be h ieres! In nccordam e

' he requi rer en u of the W T G.!c -ir. the a Mit icnal.md ore < t rinec nt &

. a requirceents irmosed W Cencral Elect ric.

ccordinale, all reactor ver el dc > inn draaints and stress analysis calculot tens et t be suhritted hv Chicano Bridre I ron t

onpany to Gene ral Elect ric for indenendent review and 1" proval.

Since the At omic Power 1:quiprent Department of Ceneral Elect ric Compan" will provide a calculational service to Chicano Bridge & Iron Company in the steady-state and transient thernal stress analysis of the reactor vessel, another company will review and approvo calculations in the area of steady state and transient thermal sticss analysis so that a completely independent review is conducted.

The company which will perform this review has not yet been identified.

1 We have no -reservations regarding the desinn of the Monticello pressure vessel.

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The materials selected for the Monticello reactor vessel are the same 0

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5 materials used in shop-fabricated veasels for boiling water cactors; narnely, lov alloy steel plate made in accordance with AS!'E-SA 533, Grade B, class 1, per ASME Code Case 1339-2 We have no reservations regarding' the use of these rrat e ria1s.

3a 3 ["I'.I"1 All plat t na'.e r i a l cill be detailed to the naxinn lenct h and vidth dir n-st:n. that c,m "e N !: ct re.1 f rc-the nil 1 and handled at t 17.1 f enrica !r saer in Birminchar, AlabaN.

';hc I l lat es. "urchased in m m ad and tene r ed condit ion, are fJ are-cut t n e,roxinate af ze. and are cold-forNO h a 5000-;

n hydraulic press recentl" le s talled J n the 1;i rrinchan sho,.

'It! ouch cold-n rt : sine o f t eactor ves sel nl a'.e, to th desi red -ha m i s ne'e l-react or eevel fabrica-tien, the AS!'E Code mo rnit s formine in an; anner. nree'ded spc i fied materi.tli n ronett ier, can be obtained in the final condition. Tht-retiod of fabricatie i has been used f ar non-nuclear vessels.

The sthod of nlate for-inn is deter fned larnely by the shop f acilities and preferences of the f ab ricato r and is not a requirement inposed by field crectien.

Cold-formine, because it is new, will be followed closely as the test results become available.

In other respects, our review of the proposed forninn procedures indicates no problems unicue to a f!cid f abricated reactor vessel.

3.4 Fab ri cat i on The shop-forrred componen ts. shell halves. bot tom and top heads, skirts, ilanges, etc.. will be shipped bv rail to the ?tonticello site where they will be assembled into lareer components suitable for final field erection.

The ascenb13 yard at tho' site will be equipped. as needed, with weather nrotcetion enclomr<,

level work tables, testinn equipment, and heat treatment fur,aco.

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6-The assembly yard f abrication process will proceed as fo11cus t (a) join shell halves into rings, bottom head to skirt extension, and top head to flance

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on. level work tables; (b)-preheat and weld sections tonether; _(c) mannetic particle check the welds periodica11" durinn deposition of metal as preliminarv inspec_ tion step; (d). hot ultrasc,nic test the velds; (c) postweld heat treat at 1130'F; (f) cool and radionraph welds; (n) cold ultrasonic test the welds; v0 wnual overthy acida; (1) postucid heat treat; (j) cooi

d u lt ra4 oni s overlae; and (k) dye check overlay.

The vessel closure flance. af ter being welded to the No. 4 shell rinc. in the assembly yard.will be drilled and tapacd in place to' receive the bushind and hold-down bolts.

The holes and sIceves for the 1216-inch dia seter control rod drive th!nhins and the 40 2-inch diameter holes-for the in-core flux sensors will'be bored, utilizing precision cuide temnlates, opticall/ alicned in a tem,erature con-trolled housinn to guide a vertical borinn bar and cutter head.

The field erection o'f the reactor vessel will proceed in the following manne r: -

.The bottom head and stub' support skirt asserb1' will be set in place on a 17-foot diameter cylindrical support. skirt in. the drywell base of. the containment,

structure.- The bottom head skirt assenbly will be' leveled usinn the devicen on the stub skirt and intermediate skirt extension provided..

The levelinn-and plumbing procedure will.be repeated af ter each of the' four-shell'rinns is placed. The No. L shell ring, complete with-the 36 by 28-inch '

diameter recirculation and other nozzles will be placed inl position atop the -

bottom head. The nirth seam will be; fit - preheated, and the hand welding will-'

be ~ started. - The No.,2 rinn will then be niaced, fit, nnd welded be fore an0 y

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estucid treate.ent is donc in place on either rine. Temporary weather protec-tion will be provided by the nultipurpose pontweld heat treatment furnace st ruc

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ture. The preheat will be maintained on the bottom head to No. I rinc cirth scam until the No. I to No. 2 cirth seam is ready for postweld treatrent. The shroud support skirt will be in talled.

At this time, the two rinc4 uill be stress relieved simaltaruously in this ten,orar f u rna ce.

Af ter the ';., 1 and 'o.

2

'rth se e4 hree been noitu id haat t re at.1, t i t( n.perary furnacc wi ll be conve rted int s an a't cenditiened and ventilated wv:1 r oom around the bot t om head and ';o. 1 shell - in r.

A temporar: cover vill be installed above t h i, w o t '.< area e that the ha'.ance of the vessel can be creete, in the m.tnne r deset lhed a'.o se wt P.eut interfering ith the bot t om head work.

Four rirth scam weld'. w:li the complete the tr-nl. ice field erection of the Monticello teactor vessel.

Concurrent with erection of the vessel shell, the veuel top head will be positioned f or drillinn the 5-1/4-inch diameter hold-down bolt holes.

With the cover in the same position, the grooves f or the two 1/2-inch diameter stainles s.

"0" ring gaskets will be nachined with portable Cii61 equipment.

We have reviewed the f abrication procedures outlined b CB61 for auembly yard fabrication and crection and are satis fied that field erection and machining can be a:complished without compromising rea:. tor vewel interrity and that fit-up within the tolerances described can he achieved.

3.5 Mdh Preheating for welding will be accomplished using electric. strip heaters, insulation, and met:11 foil to provide a uniform temperature within the nrcheat ran ge. This preheat will be applied bef ore any weldinn beeins and will continue until the parts beinn welded have been niven a postweld heat t reatmen t,

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'!he main joints to be welded in the field are doubic-beveled and utiliec a 4

square bar as a spacer and temporary backup bar for weldinn. Wcld edge prepara-tion will be accomplished in the shop by flame-cuttinn the desired bevels and land upon the plate cdres followed by prinding and nannetic particle inspection in the field prior t o weldine. Approxinatelv 1-1/2 inches of weld netal will be deposi ted by t he nult it.le nass technique on the inside be fore removin t tne spater hat cmmlett ly by are couninc from the outaide surt -n.:

.f *he ve sc*.

The att nouned nroo*.e, as ecil as the wold surface intIde, ill be raen<tto i

patticle inspected before veldinn f rom both sides pro reu simultanceusi..

ine nanual multiple naas shielded netal are proce.se will be u,ed for all of the field weld'nn of the maior joint <. in the piessure veul.

This technique ptoducen sound welds without re daci n q any of t he physica!,ropertica of th( ba.s nctrl below the standards required bv Section lit, AS"E CaJc.

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steel coated elect rode develored to nat ch citsely the phv.ic.1 and caenical l

preperties of the base retal will be utilized int the weldiac. The los hydrecer.

i and the temposition of the elect rode result in a deposited wcid retal that has notch toughness advantare from added nickel and an NDT ter crature _ lower than that of the base retal. A review of the typical results indicates a close ratch-inn of the base t etal tensile properties and 1mer NDT. temneratutes.

Welding will he continuous as dictated b: job site cc:.htions.

Centinuous visual inspection of the weldinc will be accomlished by assinning one weldinn supervisor for every 6 to 8 welders. The weldinn supervisor will have the responsibility to assure that all welding procedures are carefully followed-and i

that any irregularity that occurs in 'a veld head denosit i t, removed. There vill i

,be onc project veldian supervisor who is responsible for all of tt. weldine ner-l formed under the direction of the weldine supervisors.

The weldinn supervisors

_j will be under the direct cont rol of the nreject weldin" su ervisor.

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Field overlay welding of the stainless steel claddine will be p erfor cd i;

usinn the strinner bead technique with a rininun of two layers to accor911 h 1

s the full ucid overlay thickncas.

Close visual inspection wilk be performed by the welding supervisors to assure quality, and ultrasonic and dyc penetr ant examina-tiens will be perforNJ.

The uverlay bui'du% for the cont rol red drive o"enin

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othe r Inconti we r i rr s that n.v be ; c:ui red as the des! n

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pe r formeci wi t h c lihe r t he

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anc, tctal inert ~ac are or eo'ece cd I

are prorcsses or a ccrbinat; 4

n: t !.e s c.i ca s e..

Inten I uill be derosited directly to the base ne t il.in ! n m < n t e r i a s t ain lev. stce! overla".

Th.

niininat es the object f enable c:m uide rat :ont thct devo ' r f/ 1m Jnterlaver of sininless steci is beteevn the ba4c et al cn ' the :nt-1.

In considerat !an of t he weldin' c recedure,

the 't w etten and su crvir.!",

to be provided, the welde r quali t icat iun requi rennts, and we ld to e t f ne wh t h c

is outlined in Sections 1. 7 and 3.8 o f t hi;< re ort, we b al:c.ve that we ldina v quality equivalent to that availabic in a sh e will be achieved, t

3.6 Postweld Heat Trearrent Temporary furnaces will be utilized at the site to accomplish po,tueld heat t re at ment on the cround. The heat t reatnen t will be ronitored usinn therro-couples stratecically placed upon the assenhly and throurhout the entire f urnace.

Multipic point strip chart recording notentiometers will be used to record the actual heating progress of the assenbly durine the entire postweld heat treat-ing cycle.

Ficid orected assemblies will be enclosed and postweld heat t reated in a similar fashion to those on the ground.

Insulation, thermocouples, heatino, i

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The postweld heat treatrent of subasserrblies on the cround or cormleted asnemh11en in place in the field will be performed with the same limit ations and cont rols as tho te in the bhon.

The differenic betacon fictd and r. hon raturld heat t reat mt is that in t ht 'leid,the va r. ot t. part s are heat t rent ed as they are e itted; while in a

9. hop, the com,deted vessel i>. heat t reat ed.

T1.c eet hod e t heat t re at men t tu t i.e field a ptuposcu.

in our opinion, will in no way com9ror.ise the cuality of the Monticello sessel becau.5e the a cqui rerent s f or heat u-and t oeldown rat e. heat t i en+ nen t t erwe i at o re, and timine are the s a r e n i. tbnge which would be linpimed en a shon fabricated vessel.

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2 A latte nonber of the welders to 1.e used on this job will be exnesienced Cini veldetr.

Nevertheless, a welder t rainine scheol will be set un and con.

duct ed by exset-lent.ed and qualified CIB1 weldinc, suservisor s assir>ned t o the Monticello project.

Every welder, even thouch experienced, will be t rained in the job-<.ite schoal until a proficiency has been attained that will t,ernit the wclde: to qualify in accordnace with Section IX, AS"E Code and the General Electric 6pecitasations.

All material te be used for t raininn nurnose.. w 411 he identical, including thickness, to that of the reat. tor pressure vessel.

The t t'aininn programs will emphasize that weldnents can be made to a quality standard that will not require the correction of defectise work after radionraphic and 4

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e 1 4 3.8 'rentinc Several non-nuclear vcancis have been fabricated in teho fleid by C!M1 that were too larre to be shon-built. These vessels have been radiographed in the field, using Cobalt-60 wurcet..

The thicknes< of these vc $cis ranced f rom 2-3/4 inchei un t o 7 1/'. inchet, and we4 e 1.uf 1t to the recuirenenta of the M"r.

4 f h.0 Nu dif f icultaci ve rt enco ntered its ob t.tinina t he % t 1 1 '. - le ve l re du '. r e d b,

t.. i.4 rede.

With teapec t to rad!wra,5ic c,;;i iination of comit tt d field seld4 on the Ment icello reactor vet.cl. a radioc itive source auch a 4 r '. tit-60 or Ir idlun 192 e

1 will be ennlo;ed.

Iridtur 192 uill be u<.ed on steel t alck wnc* rancinn ' t oa 1/2 inch up to 3 int ae... uhe rea-cobalt-60 will be t, sed ca.tect thicknesnea ranginn f rom 1-1/2 inchen us t o 3 inchch.

The f11n t o be. etd ior radiogra,h will be fine grala etnllar t o I: 2, t man 1:od. A T,ipe AA, or e w al.

Weld surf aces vill be t.aenet ic par t icle inspected at e sich 1-!nt.h Imer of weld deposit.

As a f urther check to assure a "no defect" conditlen af ter the base metal weldmenta are cortpleted and prior to postveld hr.at treatrent, these welds will be subjected to ultrasonic testine (het l'.T.) over and above the rec,uirements of the AST. Code or specifications that have Iten is.<ued by reneral Elcettic.

Irregularities disclosed by thin method can he correcttd before thu postucid heat t reatrcent and radiographic insMetf oa.

When the ba'.e retal weld-ments have been proven nativ. factory by the hot uit rasonic tosts, the joints will be niven an interstace postveld heat treatment at 1150'r for approxfinately one hour before allowing the veldments to cool to ambient ten erature.

Additional l

ultrasonic tests of the veld joints will be made, followed bv radiographic exami -

l nation as described above, prior to overlay weldinn the in.,ldc of the joints.

Ultrasonic and dye penetrant examinationr. will be perforr.ed on the overlay af ter i

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, completion. The welding and non-dest ructive testinn techniques have been employed on many non-nuclear thick walled-field-erected pressure veaso19 and there is ample evidence to support the conclusion that the quality of field welds will be at least comparable to shop ucid4 Upon completion of the in-place nachininn work on the ve Sel flance and control rod nieeves, the reactor cover will be attached and the vecel prenated for test.

A hydrat : st tvorload pre-sure test will be n.

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,d at 12 % deu.in (1$60 psig). Af ter the ove r-presnore tes t i s cortf le t e d

.t i l.old surfarc, ill be r ubjected to a marnetic 3 article examination or to a 13 uid penet rant exant-nation in accordance with r.he M"E code.

in addition, ult ra onic testine of bich stressed circumferential and longitudinal weld areas and ves:,el norzic, will be conducted to detect octential distress.

We have concluded that the b/dro test.md unb*ciuent in eection as deac:!bcd l

1s suf ficient and that this information vill be suitable base re(crence for similar tests which could be made at int e rvt <- throuchout reactor vessel lifetime.

3.9 Oualttv control Quality control for the Monticello reactor vessel util be directed by a C1161 quality control mananer ansisted by two quality ennt rc.1 coordinatura. The primary objective of this croup is to coordinate the many quality connected functions into a ryaten that will assure that the reactor sesuel nroduced aill meet the quality requitements and to document the fact that theno qualit'/ require-ments have been met.

Authority lines for project nanacceent and project quality cent rol are separated. - The nanarcrs of those activities report directly to the regional manager wlm,-in turn, reports to the Cll61 Vice President.

Each item or piece of material received at the shop or. site is to be covered by a work order and t raveler card which lists in sequence all of the

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1 13 o; r t at ion at.d inspectiens which that par ticular i t e*n ui6t underro.

h'ri t t en non-de s t r uc t i ve-t e t, t reports are to be prepared for cach radf orraphic, ult rasonic, tsarnetic par ticic, ana liquid penetrant in yection.

'. 'e l de r s ' t>c r forrance <;ual f-fic atiou cert ificates and t e'.t rce.ulti, will be available for revioi.

it the b.u. i n ot t,a.11t" centrol mea-ures dc4cribeJ b;. rt:M, n i c.,,ill c

u si d et. tl is 4roy.ct, m 'eet that the p rot i t'u r es in thi. : - =or t a t a re.i r.1 - t tet'e si - <<1

.!tt.. t e l e a s t.n b l e a 1 ) cell docu*. tcJ 3

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% 31 ni'ir.an'. 'ottfrn of the "on t # c e l l es t eact or $.es wel f.tb t. < :it i on wi l l 1 -

pertotaed in t he Cl:61 ho, ani. in thic rec'ect. vill se r:

araM r to i:ii l a r ve r., ~ a Sv otin r

.e l ' ah ri c at or s.

7he balase" o f t he f ah t i cat lon.eu a *c.e -O l, at t he t ito vill be "c t f or ed by C ' > '. ! ut!!izin* t"chni 1 ar.d equ' rK. n t which e be. l i e ve are eluivalent t o the e used in 4he, and in no annet will cor?ronise the.mii r quality er funct enal re u' nev"*s

t :,e. t el, t u r e va l u a t i en o f' the i n f o rt:a t i en P t escu t e? Ic.id i t o t he conclu.tr. t h at. the i

int e r,t i ty of t i e f ield-awenbled ritact or vc'..e] will be at lea.t r a ul v.11 en t to i

that of a shop-f ab ricat ed reactor ves sel.

VE rE nnf ts.

1.

"De si en, Fab ri cat i on an d E re c t ion o f t he v nct or Vc a se l." Ancn dr.en t 2 e

Sovembe r 1966 2

" Answers to ACC ques tionn," Amendrent 6, " arch 7, 1967.

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f IMBERE No.

K-90 FOR IMMEDIATE RELEASE Tel.

973-3335 or (Friday, April 21, 1967) 973-3446

[(.h s1 $ S AEC SCHEDULES PUBLIC HEARING MAY 25 TO CONSIDER I

PERMIT FOR HUCLEAR POWER PLANT IN MINNESOTA The Atomic Energy Commission has scheduled a public hearing May 25 at Buffalo, Minnesota, to consider the appli-cation of Northern States Power Company for a permit to con-struct a nuclear power plant near Monticello, Minnesota.

The hearing will begin at 9 a.m. in the Wright County Courthouse at Buffalo.

It will be conducted by a three-member Atomic Safety and Licensing Board appointed by the Commission.

Members of the board are Dr. David B. Hall of the Los Alamos Scientific Laboratory, Los Alamos, New Mexico; Dr. Thomas H. Pigford, professor of nuclear engineering at the University of California, Berkeley; and Professor Arthur W. Murphy of the Columbia University School of Law, New York City.

Mr. Reuel C. Stratton, a consulting engineer of Hartford, Connecticut, will be alternate technical member of the board.

Professor Murphy will be the chairman.

A pre-hearing conference will be held May 12 in the Courthouse at Buffalo.

Northern States Power Company of Minneapolic has applied to the Commission for a permit to construct a boiling water reactor at the company's site about three miles northwest of Monticello.

The facility would have a net electrical output of about 471,700 kilowatts.

Northern States has contracted with the General Electric Company to design, engineer and construct the reactor and turbo-generator portions of the plant.

A copy of the Commission's notice of hearing is attached.

(NCrfE TO EDITORS AND CORRESPONDENTS:

Similar information also is being issued by the Commission's Operations Office in Argonne, Illinois.)

4/21/67

j I

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d UNITED STATES OF AMERICA ATOMIC ENERGY COMMISSION t

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In the Matter of i

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NORTHERN STATES POWER COMPANY)

Docket No. 50-263 (Monticello Nuclear j

I Generating Plant) 1 NOTICE OF HEARING ON APPLICATION 1

FOR PROVISIONAL CONSTRUCTION PERMIT Pursuant to the Atomic Energy Act of 1954, as amended, and the re sulations in Title 10, Code of Federal Regulations, i

Part 50, "LAcensing of Production and Utilization Facilities,"

and Part 2, " Rules of Practice, notice is hereby given that-a hearing will be held at-9:00 a.m., local time, on May 25, 1967, in the Wright County Courthouse, Buffalo,) Minnesota, to consider the application filed under a 104(b of the Act l

by the Northern States Power Company, Minneapolis, Minnesota, i

for a provisional construction permit for a boiling water nuclear reactor, designed to operate at 1469 megawatts (thermal), to be located at a site in Wright County, Minne-l sota, approximately 3 miles northwest of Monticello, Minne-sota.

i The hearing will be conducted by the Atomic Safety and Licensing Board-designated by the Atomic Energy Commission consisting of Dr. David B. Hall, Los Alamos, New Mexico; Dr. Thomas. H. Pigford, Berkeley, California; and Arthur W.

Murphy, Esc., Chairman, New York, New York.

Mr. Reuel C.

Stratton, Fartford, Connecticut, has been designated as a technically qualified alternate.

A prehearing conference will be held by the Board at 9:00 a.m., local time, on May 12, 1967, in the Wright County Courthouse, Buffalo, Minnesota, to consider the matters pro-i vided for consideration by a 2.752 of 10 CFR Part 2 and fection II of Appendix A to 10 CFR Part 2.

The Director of Regulation proposes to make affirmative findings on Item Numbers 1-3 and a negative finding on Item-2 4 specified below as the basis for the issuance of a pro-visional construction permit to the applicant substantially in the form proposed in Appendix A hereto.

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In the event that this proceeding is not a contested proceeding, as defined by 5 2.4 of the Commission's " Rules

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of Practice," 10 CFR Part 2, the Board will, wdthout con-ducting a de novo evaluation of the-application, consider the issues of whether the application and the record of the proceeding contain sufficient information, and the review by the Commission's regulatory staff has been adequate, to support the findings proposed to be made and the orovisional construction permit proposed to be issued by the Jirector of Regulation.

In the event that this proceeding becomes a contested proceeding, the Board will consider and initially decide, as the issues in this proceeding, Item Numbers 1 through 4 above as the basis for determining whether a provisional construction permit should be issued to the applicant.

As they become available, the application, the report of the Commission's Advisory Committee on Reactor Safeguards

( ACRS) and the Safety Analysis by the Commission's regula-tory staff will be placed in the Commission's Public Docu-ment Room, 1717 H Street, N.W., Washington, D. C., where they will be available for inspection by members of the public.

Copies of the ACRS report and the regulatory staff's Safety Analysis may be obtained by request to the Director of the Division of Reactor Licensing, United States Atcmic Energy Commission, Washington, D. C. 20545.

Petitions for leave to intervene, ursuant to the pro-visions of a 2.714 of the Commission's ' Rules of Practice,"

must be received in the Offics of the Secretary, United States Atomic Energy Commission, Germantown, Maryland, or the Commission's Public Document Room, 1717 H Street, N.W.,

Washington, D. C., not later than May 12, 1967, or in the event of a postponement of the specific hearing date, at such time as the Board may specify.

Any person who kdshes to make an oral or written state-ment setting forth his position en the issues specified, but who does not wish to file a petition to intervene, may request permission to make a limited appearance pursuant to the provisions of 6 2 715 of the Commission's " Rules of Practice."

Limited appearances will be permitted at the time of the hearing in the discretion of the Board, udthin such limits and on such conditions as may be -fixed by the Board.

Persons desiring to make a limited appearance are requested to inform the Secretary, United States Atomic Energy Commission, Washington, D. C. 20545, by May 12, 1967.

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's APPENDIX A NORTHERN STATES POWER COMPANY (Monticello Nuclear Generating Plant)

DOCKET NO. 50-263 t

PROVISIONAL CONSTRUCTION PERMIT Construction Permit No.

1.

Pursuant to a 104 b, of the Atomic Energ Act of 1954, as amended, (the Act) and Title 10, Chapter 1, Code of Federal Regulations, Part 50, " Licensing of Production and Utilization Facilities," and pursuant to the order of the Atomic Safety and Licensing Board, the Atomic Energy Com-mission (the Commission) hereby 1scues a provisional con-struction permit to Northern States Power Com any (the appli-cant) for a-utilization facility-(the-facilit ), described in the application and amendments thereto fil d in this mat-ter by the applicant and as more fully described in the evi-dence received at the public hearing upon that application.

The facility, known as the Monticello Nuclear Generating Plant, will be located at the applicant's site in Wright County, Minnesota, about 3 miles northwest of Monticello, Minnesota.

2.

This permit shall be deemed to contain and be subject to the conditions specified in 88 50 54 and 50 55 of said regulations; is subject to all applicable provisions of the Act, and rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the conditions specified or incorporated below:

A.

The earliest date for the completion of the facility is October 1, 1969, and the latest date for comple-tion of the facility is February 1,1970.

B.

The facility shall be constructed and located at the site as described in the application, as amendec, in Wright County, Minnesota, about 3 miles northwest of Monticello, hEnnesota.

C.

This construction permit authorizes the applicant to construct the-facility described in the applica-tion and the hearing record in accordance with the-principal architectural and engineering criteria set forth therein.

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