ML20127N641

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Suppl 1 to SE in Matter of NSP Monticello Nuclear Generating Plant Unit 1
ML20127N641
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 03/30/1970
From:
US ATOMIC ENERGY COMMISSION (AEC)
To:
References
NUDOCS 9212010339
Download: ML20127N641 (26)


Text

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AEC EPCU1 ATORY ST/.FF SATTTY EVAL.l%TIO:; i. IN Tilt MATTER OF f 011TliERI STATP.S POWER COMPANY

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liDI:TICT1LO MUCLEA1; CT2;EllATIl:C Pl. ANT 1%.!.).T_1 I>0Cl3;T NO. 50-263 t I i-t i e Prepared By The , Division of. Compliance . U..S. Atomic Energy Commission s,- 4 - g. N s-9.4 -- y + -ww < ., ae ,%, y- ,g- ,,,; ,.s, -,y , , .g , . , ,.g,,,q, , .. , , _ _ _ _ ,., ,. __ , ' ' , , _.' *

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1. II; TIM. ' flO';
                                                                    ') h i t tuppite ntt the Safety Evoluution dated March lti, 1970,_

picpc'tc ..f the bi=.'i t ion of L ac tor Lic t uring of t he Ato.aic Energy Con.d t : _ wu (Cimi t L lor or AT.0 ) In connection eith its r e / i( '. of the l applice. tion of the Porthein States Power Compnny (applicant or I;5p) for n provisionnl operating licente for Unit 1 of the Monticello

                                                        !?ue lv a t Cencrating Plent (Monticello or Unit 1) . located in L'rirbt -                                              ,

County, :linnesot a. The DJ.vir ion of Compliant e, as en integral part of the Cen.mi s sion ' t. -  ; reguletory stcff, is rcrponsible for condncting the fic!d inrpcetions - . of AEC licentcer to, assure that licensed activitiet are in con <pliance , with the provit. ions of AEC licenses; the Atomic Energy Act of 1954, as araende d ; and the ruler and regulatient of the Commission. Divicion.of enmp 14 nnc.. <neporein,.= nr nncin.w pnent r ene r n n u n a r. r con n e rnr H on pursucnt to an AEC construction permit provide the basis for.findingt  :

                                                                                                                                          ~

'- as to the statue of completina of facility construction ~cnd'the conformity of thtt construction to the requirements.noted above. ' l- The Division of Compliance inspection prograra is conducted f r om five regional offices with each office having responsibility for the I inspection of all-AEC licensed activitics within an assigned geograph.- - ical-area. The inspection program at Monticello is the responsibility-of'the Division of Compliance, Pegion III office located in Glen. Ellyn, Illinois. A senior reactor inspector, who-reports to'the Regional Director, is responsible for supervising the: inspection

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_ program carried out by th_c various reactor inspectors. Technical. , l direction of'the inspection program is provided by the Division of-d b

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( m.plicnco . :W u .o r t r s <taff .hich r. ivc: dirttt,<nt, t or r(gion

                                                                                                                                                  ' i t h n r p ': t t .:       *s toi @ t         s   t' spetLit     ;5i a: itc     ,    },i'   > technicti supp      -t    te (;4 rt i c-                7    cer<><d, i' o e i : " t! ! 1   in:        'f"rn ed on insp(ction               . rit n t r in othtr i<rionr, and riintrini liriron eith other divit.t.r.              of t!a /.% r e g u l t t u r." t tof f en m: t ter t ihich affect t hr itir         i i 5 e n p r e;*,ri The prorrc- for the impec t ton of the constructir,n of Poiticello hc- Leon t rir h d out te r Ir.n r i l y                 1rgion ll? inspectei> hut, in c.d d i t i r n , technial rs r j r u tre he- bc en prov2Jc 6 by other r t g i o u.1 officet, by 111vi s ion o f Lor.pli anc e liecdquar t er e s ta f f , by ot.her divicions
                                 -                                                                                                                 of the AFC 2 egula t ory : t af f , and                L'. consultants to the ALC.                Tbc principal a<tivity of th.                   intpcetorc har involced per iodir: i n s pc. c t i e n t at the con::truction rite.                     'Ihot. rite inopcetic . c i >> r e conducted 90 nonrtgulci intervalt trith the f urpec tion f rec;uency dependent-                                en the activitier which vere in progreet at the site.                                 In addition to rite int:pec tiotu , there cere inspections at the thops of major equipment                                       i tupplitrs (vendors).                  '1hcre v.ere also inopcctions at the offices of NSP and at itr contractort for the purpos e of inspecting construction recordt and proccdures and enginecting reports telated to construction raa t t e r s .

The Division of Compliance inspection activitics were directed toward verifying, on a sampling basis, that the cottpleted f acility would conform to AEC regulatory requirements. Systems and components of the facility were selected for inspection on the basis of the AEC

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3 rtgulatory rinff'r detern.ination as to their importance to the E.? f e (Teration of the facility. *lhere inspection ac tivities included the f ol h, ring - ,

1. Review of the applicant'r overall quality esrurance and '

l qunlity control programe end their implenentation.

2. Inspection of quality control recorde such so concrete strength tett dato, matt: rial Lect reports for plate and  ;

piping, tupplier certifications for piping, valves and fittings, and' nondertructive test records for_velding.

3. Obcervation of construction work in progress, e.g.,

concreto placeawnt, uciding issociated with vessel construction or piping installation, equipment alignment and inr,tallntion, and nondestruct-ive testing, i

4. Review of construction procedurer, e.g., velding; procedures and nondestructive testing procejures.
5. Witnessing the performance of major consuoction tests such as hydrostatic-testo of. piping and pressure test of primary centainment'.

6.- Review of program for functional testing of systems.and equipment including the tests planned, the test procedures,- and the test results.

                                                                                                  ~
7. Review of preparationr. for ? f acility operations including such areas as organization and staffing plans and.imple.--

mentation, program and procedures for fuel loading and. , power tes' ting, development of routine operating. procedures, [. . =. ..  : . .- .- . . - . . . - -. . - --. -

4 r;jr'e" T e p ' d e a: re . , ic0'atier plottttion placedurer, i and rergenry procedures, f' lu s pt t t i t n r,c t h J L ie r cere carticd out. at the vcudorr' shopt with the tr< objectiver. Inere inspection r. c t i v i t i e t vore sirri l a to thett notcJ nbo'.e inc luding obrervation of verk in progress, um O' l in;ptttion o! quality control recordt,, and reviou of procedures.

    .,                       IT D'l.T             0 ' ._3_1:f.iTrT! O:: or c0MSTFT10': UORK g                                                                                     .

Since the itcrance of Provisionel Construct-lon Perrait Da, R- 3 4 to UEP authoriziN, th construction of Unit 1, inspections by . Division of Cc:m,11ance h.,ve bet u conducted at the construction site, , at the vendor:i' thopc, :nd at the IR officce, A chronology of these in r p e r ' i or'r ' <; a t tic h e d n i Appen The rcrultc of the inspection of Unit i, con ucted ihrough March 13, 1970, are discucsed by system in the same (rder s prescnted in the safety Evaluation dated March 18, 1970, pr(pared by the Divi cion .>f Reactor Licenring.

                                      ,,                       l'r i e n t v Cool at Svstere
1. Primarv Pa r eu.e Poundarv Pinire The primary pressure boundary piping includes the two primary recirculating loops, the main steam piping.

downstream from the reactor vessel to and including the main < ream isolation valve outside the primary contain-ment, and those pertions of all piping systems connected to ,the recir('ilating system and the reactor pressure vessel out to the second isolation valve in each system.

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De r i n r p e c t i o n p r o p,r ert ; : d i i t.: t c d t t - 1d cudit ir tiu I J rac: Lin , o r u t lon, e.r.d O m n 3tractiv: l e !- t i.U), of 'l p s I ; . rv v 10 : suit Im ai;h i s t o- .e u t 5 and pipi n[;. Thir- effort inc luded int pec t iom et t the t.ite aral venJ : inrpections ut ill::i n;. oor rteff opteialirt: )n thir iepard, the lydronta*it test of the primary preocure boundary at 12.'i7, o f de r i e,n piersurc at n quired by the AN c o. ' r rac m ta sted

      ,                                                       by o Divit ion c.f Complir.nc e incpect or.                          In cNition

'3M 2 W. to the norr..a l quc li ty cont ro l int pec t ions , , rpecial s 0' , quality conttel intpectica vars pt: forr,ed ducirm the ucch of Noverier 17, 1969, by a t ean of i t .:f f speciali sts and a rpecialirt f rorn the Divitien of IP.:r.ctor Ftandetdr under the leaderehip of the assipwd inrpecto. A sample war selected for quality control cudit which included five piping rynene that are a part of the - primary precture boendary or connect to it. Datite quality control records of these five pipirm syn tenu; ucre examined. Equipncut and material re wrds of~these five piping, systens were selectively excmined in the offices of the General Electric Conpany (CE) cnd the Bechtel Corporation (Ecchtel), the construction contractor, as a part of the quality control inspection, A follow-up inspection was made at the shops of one of the pipe fabricators on February 24 thru 27, 1970.

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h_w- t r As a retult of our'inrpection progrca of the

                                                        . privary pleanto baandary piping ,, twa di _ ihi.m,;c1_c el 5

vere cbserved N ee deficiencirr, whicL-h':ve.ijeep-rubse:piently corru ted by the app 11 rent and bl: ' cont ree t oi r , ve re as,. fol!cwc: -

a. h documentation of rent'u tructive tu tr and their reruits w:re incomplete. Ue have.

confirmed, by cubecquent irtpcetian, that thin ritutttion has been correctml.

b. The quality of certain carbon steel vstves ,
                ,                                                       vac qucstioned on the' basin of defectr found in other velves fabricated by the ex            vendot'.          .

Tbc applicout resolved.thic natter-by cepoiring the defective valves cod by icvieving;tisc quality recordt for the other. valves to demonstrate that ' the quality- of till valves : ract - the applicabic codes. An inspection at.- the vendor's' shop by Division of1 Compliance

                                                                      '. inspectors confirmed that the reppired valves                           M met the applicable: codes.

The applicant-and his contractors performed an audit-- of the p aiity records'for all of the. equipment and material'in the. primary pressure boundary during t.he period July through .0ctober -1969, -:- A number of ' deviations.- 4 d a v k.

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4 frou procurement r pe ci f i t t, t ient werc identified os c retult of thett audit efforts dnd were eatisfctiotily rotolved b;, the appiscrat. Deviat i ons f rc:n t he epplicchic coder which may require tecclutior, rete identified er follows

a. Severr.1 short etctient of pNe ve re oppcrently not hydrc.t:tatien t ly t es t ed in t he vendor 'c thop as required by the applicable ASTM ,

cpec i f f u.t f ont , b: Radiop,raphic inrpections of the recireulating system vnives and the recticulating pomp castingr vere not perforwed by thc vender to achieve 100% covercge volumetrically, at required by the cpplicable code. The applicent has established that radiography was performed to the extent possibic at the time of manu-- facture by the vendor.

c. The acceptance criteria used for the radiography of the safety valves did not meet applicable requirements, These deviations must'be reso'1ved to the-catisfaction of the AEC regulatory staf f prior- to a finding by the Division of Compliance that the facility has been completed.

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E >t C + 3 .. . gegpictirn Stcrur; Conn roctior of tht pr13 try preicure ' j, bundary piping han been completsd. i  ; t 2. Moctm Prrrrure Verre!- 3 -- '1he retie tor pret sure s ve rsel 1:aF fabricated in ths ~ ficId by the Chicago tridge and Iron-Cotspeny '(C3hl)c-i Sectient of the pres-wre versel wre icbriented et - the'- [ a CD61 shcrt in Eirn.ircham, Alabnre, and UcrF tront phrted-q L to the site chort at-rtmbly of thc ve srcl ucr. completed 4 f by veldiny_the rec t i ons toge t.be r. 'l F s

                                                                           ' Division of Cor:pliance pressure vertel specialists ~                                  [

i rod consultants have revicued mat.crial qudlity and  ; 1 } nonde e tnic t ive test data, observcd chop fabriention-i-- ] practicer, obccrved field fabrication and erection prccticer, observed ficid 'strers 'relie f ope.rationc,- observed nondcstructive testing, and obeerved 'the field '  : _l -

                                                                                                                                                              ': p hydrostatic testing of the vescel. ,Uc hcvc verified,;by; incpection, that the-pressure-vercelibes' received the-required - ASME Section_ III code stc:ap. We have-Inspected-                                  ',

a the instc11ation of core internels.. including storage - B 1:. procedures, fabrication and velding procedures,.fitup,- , and nondestructive tecting. -No deficiencies vere detected. , Comoletion Status: - Construction of :the reactor pressure ,

                                                                   --vessel and core interncis has been completed,                                                 *

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3. P rt: cr ore 1klie r end r,f ay vc!ytr Ue have vet ified by- inspection 'tlkat[ tho pre';s ure relief and catety valver have been installed end are-set to relieve at the dchignattd pretnures. >

Comp _letion Status: Construction and instalIntion of , t these valves'have been completed. , 4, heretor Core Isolation Cooline Syneem'(!:CIC) Uc, hr.ve veri fied by inspection ' thet the ECIC systen A han been satisfactorily installed and that preegerttional!

               ,                                             . testing has beer. completed.

Completion Str.tus: ' Insulation remains:to be placed on; j. 7; several scetion of piping'in thir, ry.: tem. Thic work is scheduled to be cornpleted by. April- 17, 1970. Conclur-fons: The Divisioni of Compliance findirig'of final; plant completion'and ccnformity with-AEC regulatory require---- .

                         ,                             ments will depend o.n correction or resolution of all:                                  ,

, - outstanding code deviations. -'The' deviations which vereL reported in connection with the primary pressure boundary are under evaluation by = the AEC regulatory staf f. Based-on,the' results of- our inspections to date,:we conclude that . there is reasonable: assurance that'the-primary coolant-. systems will be completed in accordance with AEC' regulatory Icquirements. l

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P. , Cont r inrtnt Syrirre 1, . hiu ry Contafnmnnt

                                          %e prire.ry contninctnt.):hich 1ncludn the-dryvell
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and the toru.c was field cesembled fion chop. fabricated secticas by CLET. C%r inspcction program included selective exminati.e.a of material quality records, telective examination of field fchricctica procedurec, obrervation of field f abrication vol'h, obsetve tion of nonde s truc t ive te r t itig , telective examination of onsite quality control records, and observation of overpressure-test. Ue have verified by field inspecti6n that an ASTE-

                                  . t etion llI code otamp has been af fixed ~ to - the contairment.
                                -vecsel.

, The rollowing two problems rere identified by the. applicant during the construction of the primary. containment:

a. Underbead cracking in the shell course velds- ,

of the containment 'was found prior to :the . overpressure test, b Defects were found in the' attachment selds et the piping penetration 'for.the control'. rod drive. hydraulic system.- The applicant and his contractors investigated;and.. resolved to' our- satis f action both of. the- above problems . by inspecting the containment to identify the~ extent1of-

t the prohlm, identi f ying the (aore of tim problen, a r.d r< pc iring all c'ef ect s. Division of Coupliance inspec-tort follored the pierrett of the above invertirntinc.c t>y in.s pe c t i eris a t the rite. Cn: plo t inn Statur: This syrton vil) be templete then the integrated lenh rate test has been perforned. Thir test is ochedul(d for 1: arch 2G and 20, 1970,

2. Cont:irmoet inert in" Sertcr Th e c on t a i tur.m t inertint; tystem het not been installed. Installation of the systen vill be verified when conplettd.

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ne cent 91n- ent f rer t in:; cyr t e- ir scheduled to be conpleted by June 1, 1970.

3. Secondary containment The secondary containment system concistr cf the secondary containment structure and the ventiletion and standby gas treatment systens, k'e have inspected the construction of the secondary containnent structure from the standpoint of construction procedurec and concrete quality and test data. 1;o problems were identified in these areas.
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                                                       .rian etien' N rur: Conetwetion on th6 e.ec.ordNry l

2 4 cont +1nsent is schedu hd for ccmplction by /pri1115,. 1970. The t e cundary -cotitsimnent systcr.,le d. rate

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t e r: t vill be per formed follouing the ' ccepiction of cons truc tion of the r econdary conttimtent,- t he

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completion of oth'er constructicm activitico _ incide the containesut, and the icaoval of.consti.uction cquipment. Tbc tcat 4 5 t;chedu led to be perftrurd on April 18 and 19, 1970. Testing'of the chArcoaf 1 and halogen filtere.is sch6duled cc a part of the

                                                       -preoperational test program for the st.andby gas
                                                                                                                                 ,y treatment system. We will review the recultsTcf.

there tests when they become svailabicl awi prior  ! + to making a finding that the system istcomplete. 4, Primarv Co o l an t T.c ah Tie t ec t i on Sy n t en - l We have verified by' inspection that_the Isrimary -j coolant-leak detection system has~ been' installed; a t Completion-Status: -Construction of the-primary-coolant-leak detection system.has beenscompleted.

Conclusions:

Based on the;results of-our inspectionsetoi ~ date, we conclude that there'is reasonable 1ascurance=that

                 +
                                                 .the fabrication end testing of the containmentLsystems                          '

will'be completed'in.accordance with AEC regulatory.

                                                                                                      ~

requircinent s .

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                                                                                                       . 13 C. _!revi_gnev Core Cooline Sveth _(FCCfQ Die ECCS consists of the,high prert.ure coolant injection ryetca (HPCI), .eu tomtie prescuro - relicf' rysten -(nuto-rclief), .                                  .

core spray, and low prorsute-coolant injection (LPCI)':tystems.- We have inspected the construction of and'have examined-sciccted quclity control records-for'the ECCS. As~a result? 4 of quality cont rol inspections of the primary proccure boundcry pf ping disc ust ed above'which included- a portion of i the piping in the ECCS, tlic applicant'and his contractore .! extended'their audit of quality records beyond the primary pressure'houndcry piping to-include the remaining portions _ of the ECCS. No deviations from-applicable coder have been identified. The applicant has developed a program for testing the performance of these systcmc prior .to fuel loading and _ during the power testing phar.cs follouing startup. We have.' _ reviewed this program and have. concluded'that the test = '

                                                        - program vill meet-the intended purpose of' demonstrating:the" functional: performance of the'ECCS. JPre- fuel [ loading" func-
                                                        - tional testing of the ECCS is complete andithe results are:

under review by NSP. These-test results willLbc reviewed by the-D_ivision of Compliance to assure that theLECCS is capable of- performing its intended ! function. - l

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                                                                                                                                                                                   .t Ct a h < .ce- f t r t u.y :                Ccr.u ruction of the ECCf; is ettentin11y      .

conplets, Involction tenait..c to be pibeed on'several s t e t Hu , of piping i:bich_iz.' scheduled to be coupleted by L T ri' 17, 1970. ' Cnplu s iom En ed on t.he results of cur intrections to date, ce conclude that there is reasonable crsurancethat the ECCS will be completed in accordance with AEC regulutoty' toquirements.

1) 7 n strur entar ion. Contcol _nd Auxilit v Flectrit Power Systers-
  • These systems include the reactor protective, centro),

scfety, and nuclear instrumentation systems; the_ normal power: 9

upf.ly sys t e n.s ; _ ad L;.v eseguccy pown - cupply .sys tems,- -

Ke have inspectc" the cuality of electrical _ ond instrsmentation installation, the adequacy of, selected'componsnts, clectrical' separation of key circuits, and the electrical ' loading of n l -- _ cable tray:.. We have also reviered installation criteria. - have' determined that acceptable insta11ation practices were uced and'that the constructfon and insta11ation of-systems meet opplicable criteria. Completion Status: Installation of'the_ instrumentation,- j- , f 1- control and auxiliary cicctric power systems is complete'

                       ~

with the exception of the auto-relief system and the-electric power systems. Installation:of the auto-relief sys tem is scheduled for comple tion by June 1, '1970. ~0ne

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of tuc 345 IV pover transmission'11nts, specified in.the applicat lon, has not _ yt t b;:en ivi U.lled, .Ibu cppliennt

                                                                           ~

plcac to complctc thiri line by Jura ' 15',; 1970. In s t a l l a t ion -- of onsite emergency pouer supply circuitry is-complete. ' Testing ic scheduled for cotoplction by April 15, 1970. Conc lu r f e n: : 1:ated-on the retulte of our inspections-to date, ce conclude th c. t there--is reasonable assurcnce-that the inettumentation, cont rol,- and au>:lliary pose r sys t cmc will-be completed in accordance dith'AT,C-regulatory requirements. E. Rndinactivc Warre Dirrocal Svrteme *

1. Linuf d Radiat ion Unsto Dit prent racili ty The liquid radiation vaste disposcl. f acility includes storcac tanks, pumps,--deep bed deionizers, filtcts, interconnecting piping, process instru -

v mentdtion, radiation monitoring instrumentation, and drum filling and. handling facilities--for the , deioni::er resins. We have inspected installation. 2 of the major system components. .four inspections; indicate that there are no unmonitored release - -u. paths. As a result of our inspections, thc liquid effluent monitor will be relocated to an'arca:of-

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                                             ' lower-radiation background.
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cr 4 Co:v k t ion S r n ton , Inntc))ation of the rojor equipment piccer and piping ~is complete exceptefor the drun _; 1 " ham 1ing fccilit y , uhichiis rSheduled; for compict im. !by:  !

                                                                                                                                                                         .)

June 1, 1970. Electrical and instrumentction iustclla - < tion it complete, with the exception of severr.1 ins trt,gnts with late delivery dates, Installation..end celloration of liquid effluent monitoring cquipt.cnt 18.

                                                             . scheduled for completion by May.1, 1970. .Prcoperational; testing is tcheduled to be completed by Junc-1, 1970,
2. Gascous Radiation k'aste Svetem
                                                                       *The principc1 componentc of the r,aseous 'rrdistion varte facility are the 30-ninute. holdup line,_the high-effleicncy p u ticulate filters, dilution tcns, the i

plant raain stack, air ejectorc, automatic valvec, and 1

the radiation monitoring system.- Uc havefinspected the installation of-the gaseous radiation vasto systen, Our inspection program identified one _ potential. path ~

1--- for gaseous release via'the reacror. building ventilation ^ stack which was not properly'manitored. . D r- spplicant ' is in. the process of modifying :the monitori system f^r

                                                             .thereactorbuildingl ventilation ~stacktoprovide.a system which will be' adequate.     -

3 Corpletion Status: Insta11ction.of theimajor equipment-and the' instrumentation including'the modification;is l l. p 4 J l ~ .

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P 17 - T E complete, Inr t rimen t ~c t.1Rration ir not y6t" complete,- Co l d t r n t i e ,1 is reb (duled to be complete by April 15; 1970, Cr>nc l tp i n ur . Imsed on the tcsults of our inspectionc to date,'we conclude th :t there h renstmabic assurcuce - that .1

                                           ,                           the radioactive waste dieposal'eystens will'he. completed in accordance.virh /.EC reguir. tory requirements, l'.      Sneur ruel Stptrpe The t: pent fuel storage cyctem consists of fuell.itorage rackr,'thef'ucl' storage poo), and'the fuel storage--pool 1                                                                      cleanep systen.

Cu vitiiun S i. c i u ,. . W L., v t vetirled by luopettivn i.h u t. lhe i L major structure r have bcci irected and the associated equip-l ment has been' installed. Preoperationol-testing-is in ' t progress, . It is. expected "o be completed by April 17, 1970.- L l. conclusions: Lared on the results of our. inspections, to ll date, we conclude that there is renconabic assurance'that l-l- -the spent fuel. storage system will'be' completed in accordance with AEC regulatory requirements. l C. Administrative Syst h  ? The administrative system,---as'used here, includes the organizatio.n and staf fing,- the. preparation = and review' of. -

                                                                  . procedures, and - the administrative directives which NSP has-9 I_' )              L                                                                "

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t devs icpt o . 4;o conduct- the funt tional tst: propre and- __ 5 suhrequcm cpe rations at tiw lionticello- f acility. In cdditinn to-cur ineptctione el fccility conatruction, i re bave itu pe cted certain arpcets of this edalnistrctivc-sys t er. . ice have obterved that the ap}.11cimt her , establi:hed operational-revico and cudit carruit tee s ~ vhich - t are actively crgcced in al1 pbcecs of preparations for plant rtcrtup. 1:e Lcyc verified'that the appilcaat..has , develc. ped a pregi m for functional testing of syste.M end equip;nont, nu ! _ ra have emained ,- on a celect ive , baris, the func tional tert procedurec. Ue have aleo

  • ic1cetively c xmined l.he 'rcsolts oil those testsiiohich have been completed and Ec plan to oxmine other Lett results ihen they become available. We have_ initiated our rcvicu of the -progratu: and procedurco for_ fuel
                                        . loading and startup cesting, an:1 the procedures for     _

plant operation, Uc plan to examine ~these procedures on a selective basis,when their preparation-has been -

                                        -completcd.

Completion Status: The functional ' test program, including 7 k review of test results, andiall administrative preparations ~. for fuel loading, . startup tecting, and power operation are

. - scheduled to be completed by April.25,-1970.'-

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n y <=' J Conc l u r i on: haced on the results of our in< pectionr' tT l r

                                                                      ' dh e ve conclude- that; there is reasonable arturance thet            .

l i the admitait,trative EyEttm will bc cogletcd in cccorpence. 'i i eith /1C regalntory requiremente, 111. CD::CLUr.] D: . -i

                                                               -Eased on the results of our inspections of the Menticc1}n fccili ty ,                               .
                                                                                                                                                                  -I we have concluded that:                                                                                 o
                                                                                                                                                                   -4 5

A. The re ic reasonabic acsurance that Unit I rill be completed ~ in conforuance with Provisional Construction Fermit l'o. . cpl'R- 31, the application, . as cmended , the provicions - of the . ' Actiand. the rules and regulation of the Corniscion;-lcnd [ sj There is reasonabic assurance that Unit'l will be vendy for. D.  ! initial loading with nuclear fuel within ninety daye from ' April 28, 1970, the date on which the public hearing in j

                                                                          .              .                                                                              1 this procceding.is-scheduled to-begin,                                                            i ll I

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a 4 g m .< - . . q Cm t ' U . OF COV . !, 7 DIV 1 W: IL 3 pf C 1 ' rm s' . V ,. 1:n- I r. i . . . . t... . .. > .!L... IM T. _1._, Nt 1,.., i:, a: . Sco, of i n: n.:3 c t i en 11/3/.C Shsp int get ic , - 1:a per t ed op f ac ilicio sud discussed proposed Chic.go EriJ.y a prccedurcs for field m e .M y of reactor Iron Corusr.:, rrt e wi e ve atl . . Eivn.inpO

                                                                                          /.i n b a n.a 3/D-9/6/                                                    Shop Inspectie. _                                    h cimd f abricc-t ion nrugren; of recetor Chicago bri4 2 6                                     pressure vesset.               Observ;s cork in ptor,ress, Irtn Co.rpcm                                         1: pu ted rm , n            r  :,f m )ainc,,       f1ter , and P, i r:.. i n gh am ,                               ult: aonic 1: cpections Alabama f'/2c/67                                                    Site Inspection                  -

Initial site ineptction to observe stotus of

                                                                                           !% n a ger .:n t tReting                            c or .i t t uc t ion .      Tui t ial met ing wi th I'SP manage-rte n t t o d i's c u Y S D iv is i~en o f Cor-pi^it.nce inspecti.on progran during reactcr construccion.

9/5 0/f ' Shep Incpreti - - E~cie. :d f alci :. tier pr:grer r f rec.:ter pr::: urc Chicago Bridm & venel, Observed work in prcgress and inspected Iron Company, recordt of radiograph;, , fitup , and plate materia: Birmingham, properties.

                                                                                           /] abs .                                                                                                                       Y 11/13-14/6'/                                            Site Inspection -                                    Inspected vessel assembly and heat treatment area; reviewed vessel cstembly and welding pro-cedures and quality assurance program.                        Inspected data reports of concrete strength tests and radiographs of primary containment welding.

2/5-7/68 Shop Inspection - Incpected certified mill test reports for Technical mecting material used in-primary containment, Reviewed Chicago Bridge 6 field welding procedures used in crection of Iron Company containment. Discussed metallurgical analyses 1305 k'. 105th St. of cracks found in penetration plates near Chicago, Illinois welds and crack repair procedures, and Oak Brook, Illinois APPENDIX A f

              . - - - - _ . . .                        .     .-                   - -.-. . . . . . -                        . ~ . .. .                    .          . . . . - - ~ . . - - .

i . s: P 21 - Du< Tune inrpection- Scope of Inspectfon  ; 2/b-!O/08 Sitc Inspection Keviewed infort:ation on 'c>: tent of crcckr in en talument repairs made,.and nondsstructive test. ' results.-(UT nnd RT). Reviewed. status of reat tor pressure vessel- nner mbly and procedures for radiographic and ultresonic t.t.sts,. control of ' heat treatments, and quality centrol reccrds.-. -' Revicued test procedure and obt.crved i>crf ornance - of pressure test on primary containment - (2/10/68';' 3/4 4/68 Site Inspection Obnerved . ali;;nment of bottom head assembly of resctor vessel and fitup of first shell ring to hottom head. Inspected quality-control-data on concrete strength.

                 '/13-19/66                              Site Inspection                                   Obnerved pir ement and alignment of third shelli ring to second shell ring.                                Inspected quality corn trol dat.a on concrete and reviewed procedure fori construction of concrete' chic 1d around;drywell; 5/2-3/08                                 Site Inspection                                   Revicued heat treatment procedure.for.rcactor.

vunel av,wmbly . Inspected records of heat treatment, fit-up, and nondestructiv'e tests. l- - 6 / 2 7- 28/fs S Site Inspection Inspected concrete test data. Reviewedrinspec-tion results and repair procedures'for cuatrol' rod-drive hydraulic line containment-penetrations' Reviewed NSP quality assurance program. Reviewed NSP env.tronmental monitoring' plan. Observed j welding and machining operations .onireactor

                                                                                                           ' vessel control. rod drive stub tubes.

0/27-28/68 Site Inspection - Observed status of reactor pressure vessel anddit Management Meeting cussed ~ procedures for insth11ation:of vesoci inter nals. -- Discussed status of Division .of' Compliancei u

                                                                                                        . intpection program and plans for future intpectior
                                                                                                                                                                                             ~

[ 9/11-13/68 Vendor Inspection inspected quality control- records and- reviewed : h - Willamette. Iron needures for installation of reactorivessel and Stcc1 Compe i- wnals including jet pumps; q Willamette, Or w n i. l. APPENDIX A-h l

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Tyne Inn e tion Scope : o f - in snec t ion . M in 9/1 M 0/ tit Sh'p inre ction _ Revicwid proc (. dure: t.n d inepc et ed equnlity5 con . . Chicott Rridge 6 tral records for the f abricat io; of control , Iron Comyce" red drive hyJruplic line penetration-intert i 1305 W. 105th St. plates. Chicane, 7111nois 10/3 //h8 4 Sit e Inspect:or. Inspected rccerds of control fod Arive . hydraulic line penetration repairs. Reviewed NSP quality assurence progran . Revieuce prepcrations-for ~! operntion including orgt.niention, staffiugi snd , training plans. _ Observed electrical uork in progress. Inspected records ~of pressure; vessd ns-built di;.encions and recocds of tccts on stub tube welds. , 12/11-13/60 Site Inspection -Revicued specifications for welding,-inspection and cleaning of piping systeras. Reviewed weld ,- , ing procedurcs. Reviewed preparr.tfens inr' preoperat16nal. testing ~ including the participo-tion of NSP in the review and approval. of test-proce6u2da. 1/17,19- Site Inspection Uitnessed hydrostatic Lest of the reactor 20/69 pressure vessel. Reviewed preparations tor test,,- test procedurcs, and test records. Reviewed primo contractors quality assuriince procedures Observed piping installation in . progress. 4 Inspected program for welder qualifications. 2/17-18/69 Site Inspection Witnessed pos t-hydro nondestructive tests: of - reactor vessel.

                 .4/14 16/69        Site Inspection           Reviewed quality assurance activikins related /to flitup , uciding, and nondestructive; testing of ~

piping and ~ to installation. andJ testing of

                                                            - electrical systems.                    Inspected quality control--

records for concrete. Reviewed program for con-struction. testing.. Observed instailation ofs reactor vessel --internais and inspected > welding procedurcs,. welder qualifications land non-0

                                                            - destructivi tests.

t

                                                                                                                         .APPENDIXTAT             .

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                 . / 2 0. ', /1/ f '                                                    V e nd u.        Inspcctiea       ]nspected cuoliti i     a m renct pi egi n:n   'n  go:tlity cont rol record s + vcnuor fur piping . p t c ms .

S/27-29/60 S it e Intpection Reviewed progr; for investi;:ntion of cracks in carLon steel valvcs and fw- utt.b11shing quality of a:1 vah:s. Inspc.cted specifications, inst nilat ion pacedures , an:1 qualit.y crenrance recordc- for containu nt electcical penetra .

                                ,                                                                                         tionG.

6/16-20/62 Site Incptetion Observed electrical cable installation in progress and reviev2d procedur( 3 for control of crble routing. Inspected licensec c;u c lity assurance propre.. Reviewed welding procedures and velder qualifications and revicued radio-1;raphs of weld s in recirculation system.

  • f,/13 - 15 / fe Site Inspection Reviewed status and results of contractor's t 'a n e ge -. ' n t, IIecting progrr.v for audit of material quality.

9/8-10/69 Site Inrpection Inspected quality control records for inctalla-tion of piping syntas and reactor venel internal 9/10-12/M Vendor Inspection Inspected procedures for electrical cabic Bechtc), San installation. Francisco, Calif, 9/22-24/69 Site Inspection Inspected specifications for containment penetra- ~ tion bellows. Inspected quality assurcnce records for electrical installction and observed work in progress. 9/23 .6/69 Vendor Inspection Inspected quality assurance program at valve-Ancher Equipment supplier and inspected quality control records Company for Monticello valves. Hayward, Calif. 10/30-31/69 Site Inspection Initiated preoperational inspection of radia-tion protection program. APPENDIX A

                                                     ~
                                                                           - 2!i -

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                                                                                         -.Senkn-erinst4etinn 11/1~. 2'/ / G      Ircem ive Qut,11ty           Tern insp(;tiv., te evchete quahty centrol of .                :

Control Im pu t ion a pre;ciect ed sampic of innt al,ledipiping '; at the site and'in Vistially incpec ted . piping ins tc1] ~c.t f on.

                                       -offices of thri              Inspected piping quality controlLrecordsfretained Cencral Electric             at the three locations.                                        '

Co m ny, S m Jc t c ', C r.1 i f or nic , rnd tbe ' recht.cl Corporction, , San I'rancis ce, Calif . 12/29-31/09 Site Inspection-- Initiated inspection of preoperctional test procrrm anJ _ obscried. hydrost at ic tent cf prinary pressure boundary.

                                                                                                                                ~

1/14-21/70- Site Inspection. Inspected electrical and instrumentction instal'-- lation and reviewed adequacy of selected-compcacatc. -

                  -2/2 4/70            Site-Inspectien               Continued incpection of-preoperational.; test                  ;

program and"of radiation protection pro!; ram. 2/5DO Minagenent leting I)iscusred resuits of intensive quality control inspection. g_ i 2/19-20/70 Site Inspection Reviewed deviation di spositions l prepared by - applicant and GE. 2/24-27/70 Vendor Inspection. Inspected quality control ~ records and docuuienta-- < National Valve and tion for ECCS and other piping. Manu f ac turing Company, Pittsburgh,- .

                                      .Pennsy1vania 3/2-3/70           Site Inspection               continued! inspection of preoperational test program. Initiated review of power test program and-operating procedures.

3/12-13/70 ' Site. Inspection- Continued; inspection 'of preoperational test D program and- revleu of power test program'end .- operating procedures. 1 _

                  =

3

                                                                                                                 - APPEIOTX hi
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