ML20024B001
| ML20024B001 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 05/31/1971 |
| From: | BABCOCK & WILCOX CO., GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| References | |
| TASK-*, TASK-GB GPU-0212, GPU-212, NUDOCS 8307010291 | |
| Download: ML20024B001 (177) | |
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-CONTRACT FOR EUCLE.;R FUEL For Tae Tnree Mile Island I:uclear Station Unit 1
.1 3ettleen
- etropolitan Edison Compan:-
and Th.: ?!ai ece:: & Hilec:: Ccmoan-GPU BoR. Exh. For ID- dIk N'. LtMy Charles Shapiro CSR Doyle Reporting Inc. E \ rI EI ~ O s A
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IUDEX Faae No. 1 ocope cI. Sn.: ply
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_1 A. Ec'CriCation i 3. I:cu;ren Sources and Burnable Fci.;on 2 Red Assecclies 2 C. Fuel Services 2 1 Uranium Supply 3
. 2 Loading Services 4-3 Evaluation Services 5 4 Drawings and' Data $
5 Reload Batch Design Effor; 13 4 II. S upcl.t of Special Nuclear Material 13 A. Initici Core E. Eelcad Butches; Replacement Fuel Assemblies; 1.s 5
.... 2
.n. c a_4 .*s 17 Fabrica:icn Scrap and Manufacturing Overage C.
18 l III. Titic. Eelivery and Schedules . _1.Q
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- 3. I' liv e r.'z 19 I'.: livery Sci:edulas
- v C. 19' f i') Initial Ccre 19
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IX. Consecuential Damages . 52 X. Bnck Charges, Assignment and Subcontracting 53 A. Back Charges . 53
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tica (hereinafter referred to as "E n?"), is effect!.ve as of I;cvember 15, 1966. Meted and BEN have entered into a contract f r tha purchase and suppl". J. respectively of a nuclear stea tuppic :: ton, effective as of November 15,19c6, and hereinafter rsf 3 rr .: .: +c a: "ths plant contract".
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L'.Y.. -:ill fab; icate , for use in Mated's Three Mile Island
- !ac' ear St.atica Unit 1 (hereinafter referred to as "the plant"', ,
' . . _ 'M.tial ccre and two relsad batches in ace:rcance with
.he .!esign 60acribed in Appendi:: A to this contract. An used
..c r c iti the term."fabricato" includes withdrawal of~ enriched uran 1*.:a hc;;afluoride fcc:a an AEC -isoto.ne se.oaration .niant>
':t n";rsicn of th:: traniu:a he;<afluoride to uranium dio.':ide, ricatir.'n of the uraniu:a dic;cid 2 into cumnla'2d fuci ns st-L'.- :n, and 21.!. trancycr'.ation of fuel catorial: incid.nt'to.
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(i) 267 chall furnich with the firs t core .w"icient neutrcn s o " .- a .' ., a. .r.n. .a.a s '.tl
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(2) BFri shall furnish with the.first core a suf"icient number of burnable poisen rod ascemplies, as described in' Appendix A , . to satisf.v applicable AEC licensing requirements and'EueT's warranties herein. C. 7'el 5errices EII.. chall provide :*etEd with fuel services based on the desi n y Joacriced in A.n.:endi:: A and Appendix E, as the." may i:e modified
.e c.. ;2.n to .4rcicle I C(5) and/or . article VI.
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(a) m.:cs cla.,,> a,or ueul. n en.ances proposed b _ u. a t. r:,.u, our-cuant c Article VI A, specify the enrichmenta and cuantitics of uranium required for cach batch of fusi s,..,..w,.... (i. ) P'i;! chall provide hetEd with predici.ict:c Of it; fu:.ure uranium rcquiremonta in termc cf uranium enrichment:
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[ in purchasin; :/cllow cal:e and in arr:'nging fcr its conversien and toll enrichment. (-)
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.'or all fuel assemblies supplied by _EST under this ccncract ESid on a timely basis shall:
(2) _ prepare and furnish recuirements for receiving, inspec-f tion, and scora.ge of fuel. assemblies and procedures. ,, and re=cval 4 for in-core fuel loading, repositioning, of fuel asseI'clies ' cased upon the previously established final design fer the initial core or the reload batch, i O as apptcpriate, giving recognition to I:etId's energy requirst:nts as furnished to Efid in writing not less J l than two (2) ;caths prior to scheduled shutdown for t
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., b ) preparc and 1;rnichiinc,tructions for pcciticning and
, ropcciticning reactivity control elementc; (c) prepare and furnich specificatient and procedures for ccre te.:t. int; during and following initial fueling and refueling, and during plant heat-up anc until attain- 1 mant. of the- niiltional cutput leve' " ""'nted in the plant ccncract; i (ti) unalyce recultc cf 1,he core cects and propcce r ? rating
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(C) cupply the techniques car, and prue lures tc. Le useu in, th.! preparation or fuel exposura calculaticn: .,
- necessary to establich core po::er di.s ri' uti:n during plant operation; and (h) provide all programs and numerical cens. ants for the on-site computer and procedures for nuclear steam .
supply system operatien when the cc puter is una tail-able and for ccmputer operation '. hen it is put back into sertice and for making appropria e data ad,justments. (,.i
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. *?ith respect to data obtained during the time the core o.." the p;an- is ccaposed enclucivel"J of fuel as cmHias supplied .L".?
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(S) analyze data to catablich baces for ineconacc in tnc AE' licensed power level; (c) adzico Mated en operaticn of the plant.'. nuclear ctcat
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Snc propo:ca refuelin.; ccherlule including identi-
.* Le7': ion of s ceamblier tha t compric 0.cecifl0 lot On: b. ches; .
1 ( .' ) esti:t.::e fro:n compu:er data the neutron fl.r: e:-:po s .:re 1 and - the effec:e thereof on reactivity control ele:.en:2, and on in-core ine:rumenta tion; and (g) supply es'timates of the radioactivity levels of dis-charged fuel assemblies and discharged in-co/e equip-ment such as control clusteh ass'emblies, crifice plu[ escemblias, fixed chics, etc. (h) Or r.e '.n.~0 end Dat3 (a) 2 74.1 shall furnich to IletEd, on a timely basis,- fer .:ce in
^ 0nnec'-ion wi:h LietEd's rev$ew of thh design of th? f us '-
- emblis and other appr.ra tu ' to' be supplied hereunder, as r.c n.',' e cp ie ~ - Lis tEd may rea sonably require, of menrh'.;r ler: 2
- e n a c :a':.:e repo c: ,anc parioiic nonsu.ry repor , pre-litiinary ana final drawinge, design da ta, and rpecifica . ions fo.c the uccpu of supply hoccunder. Within 30 calenuar ds;/2 af ter raccipt, idetEd chall review, comment upon, an.1 return one co c' cf uuch repor:0, drawin;;;, da ca and Opee'.flec t!.cna to L'd!. Such review by li.<::Ed chall not relievo U2.: of any of it: ob11;;.tlona unuer t. hic Can'w:ct. E's: chal? :l.:rnich e .::tr:n Sna contr. rue tton drnuincn!nud Opm: 1 flea tlone: o,f- :he fuel n: o:r.hil?: oc neon a.; practi.:atic upun act;'letion cf
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octained and shall furnish suitable offich facilities for such employees. In this cennection, E E shall make a"cilable to Meted for use during such c'esercation and
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, end-ce.ps. grida, etc.) must meet.
(2) The requircir: cat: '.:hich 1'inished fuel red and con:rc'- clement mast meet. (?) The requiremants whicl comp'.eted f uel :.s s ct!'li e s ?.nd
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- cceponents, clements and ccmpleted acaemblic:, an thcce l i
1 ! r2 cord: shall be a tailable for raview by Mu tZti and/or it: a on,s. EET shall cico maintain records on the disp :iticn of all deviatien notices and these record: shall be made available for review by Meted and/or its agents. l BMT.shall arrange for Meted and/or its a en to have sini-1 J 1ar access to the plants and records of BSf subcentracters i i performing work or supplying materials related to this i Contract. However, the ph.'/sical facilit.ies made a railabla at such plants to Meted chall be limited to those which are available to SEf. . 3 Inspections and audits conducted by NetEd and/or its aGan:s 1 prior to delivery of fuel accetablics to the plant sits chall 4 not con titute acceptance (except as providad in Ar;i'.la IV C i hercor) nor shall they in any way r:lieve E%i cr its cubcen- , tractorc of their contractual obli;;ntion or raspencibility i to furnish fuel assemblies and control rod accemblics whi::h meet all contractual requirement:. i
*Any propri etary infor=2tica concernin:l, tuo nroduc c or manu-facturing procccues of E3.i, its supplie rs and cubcentractor:
which are decicnatec au prcpriot ary information b:. 22: in 4 uriting and diuclo::ed to the enployecc of Ec:Ed er-100 , . acont inciden: '
.c the performan c of ti. in cont rac r'.. ;'l-i rescin tha property of Ei:'.1. and chall bc. diccic cd in c.:: -
j ffidoncef.ar.:!.r.3 i 1Jh -
- .are cear.:.cd.to MctEd or.1.: a.;cn 3
- cr of.hcr ?c:rplcyc :c 0 pecduce er h: ec preduced an" cu::h r
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I i '. {;; (:; products or to practice or cause to be practiced nr.y cuch manufacturin s prococccc. The employees of NetEd or of its agen.s chall remain sapl:;'ees
' of Meted or its agente, as the case may b3, for all pur;:ses durinS the design, fabrication and testing of the fuel assemblies to be supplied hereunder, and their salaries, travel, commanications and living expences shall be paid b.'/ Meted or its agents, as the case may be.
The agents employed by Meted for purposes of this Article : C (4) (b) may be disapproved by EE.1 if such agents have a ocn-flict of interest. Except as provided in. Article XII B(2), SLh shall have n: obligition to provide Workmen's Ccapensation or Occupaticnal Disease Act coverage for any type of employee. S &'.i w i l l b e liable for perscnal injur; cr prcperty damage arising on: of cuch employce'0 activities at ELW facilities only to t'.e r e:: tent that such liability is covered by its exietin . incuranco policies or progre.mu, encluc.lyc of Workmon's Compencation or Occupational Diccacc insurance. Any lin-bility for da:tage in exccan of E.~t.. c applicabic oxisti:..:. incurance coverare or prc.y.c.:aa and liability to such employecc under Worh'n':n's Compencatien and occupaticnal Dic <r.-. :
..c t: :: hall ce !.he recpor.cibility cf yetEl.
,, (c) E':W chull provi.'le fu:1 dru....n;n and data na X2tEd may I ' ? T 4 g
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IC (fe) (c)
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Acasor. ably rewire to contract for spent fuel shic,en:s cr.d renre:ersing 'ervices witn corac:c.t s u.np l i e r s . (r;) :u t e t 'J r. t . , 7.a . i.-- E # f :r t
, E..: 1:s , :na.s :. tete: 7 ..tns prior t :, t h .: Scheduled Shipicr.: N t. c for ti.: first rcic. ' ba:ch cr.d act 1.:s s ti:an te n :: ,.-rh 3 prio: tc t i ..: 5:heduled Sh'i. ont.Dete for the secoid reload bc:ch, estchlish*:d pursim t to Article.Ill C (2), ita:. Ed shs i l adv i t.c U,'.f .in
<.r i : i r ::
of i t s prcjected e.rcegy re ;ui re .cnt . for the rarn,'iir:.*ar of the t he.- curre. c/cic, the taext relecd c/ cia, cnd the four s.ycles succec. fit:g th: r.-:.s t rc!oad cy.ic. If such t.dvice s:cil indica:e an ener;y reca::c: :.: d i f ft:rt s; f a cn t he ercr , / r. . duc t ic.n c c:-t i l i ty dc. :.: W.c d
- n 4:1 : . :: .. A for :: c cext reic .d bctch to be w,;:,l .' cd - he reur.i r by E ' '. . . .T ! ili pic... iy.c2.ferr.1':: ;;c e t i t . of :,h. Iced E.:. . 9. L' ., i g n E 'ar: r.T. r a st.ry 1 fetar'.in:. Octh::r or not t he t*:.: C d r et,i: : : ::s c r. t s c ct-
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e, ,, I C (5) (r.) and the quantitics of uranium required for, and the number of acccablies to be contained in the next reicad batch, and of the estimated enrich =cnts and quantity of uranium required ;
- for, and the number of asccmblies to be ccntained in the follcuing two reioad batches based on the Meted projected energy requirements and two months thereafter SFd shall l l
advise Meted of the revised projected uranium and plutoniu: discharge values for the initial core and for the first and second reload batch. This contract shall then be promptly c ended by the parties in the manner prescribed in Article XVIII to substitute the new B&W design for the design specifie6 l in Appendi:: A, to equitably atend the warranties under Article 1 ~- - cf_the plant contract and under Article V of this centract 4 consistent with the new design to the extent necessary and i tce.scnaile (it being agreed that no cuch amendment shall increat the warranty obligationa vi B&W), to designate the new design 3 as the supply obligations of E&W under this contract, and te
, amend the applicable porticns of-Appendix B to this contract including the time schedulec in Appendi:: B if the number Of accemblies is to be increased by 255 or n. ore. .
( 4. ) If the Meted cncrgy requirements cannot be natisfied without changen other than the e::empt changes, but come lecuer change in the energy production capability for.the reload ? . ! batch can be accc==cdated with chan ea limited to the i exe::.p t chan:;en, , EEJ chall promptly (wi'hin one (1) conth e I O m_ _
't.:! . I TP.
IC ( 5 ) ('t-) l w- ) followinG the Meted advice) advice Meted in writin; of the energy objectives which can be thus catisfied and of the , reascns why Meted's energy requirem.ents car.not be satisfied'
. without changes other than the exempt changes. Unlesc Meted shall object within 10 calendar days after receipt by Meted of the EsW advice, the. B&.f identified energy cbjec-tives shall be Meted's energy requirements and. advice,.as of that date, . and the parties shall. thereafter proceed as specified in (a) above e- - - - -
!' . .=- In the event that the reasons stated by B&W are inadequate to support the EEf advice, E&W's railure to have ti=21y _- proceeded under paragraph (a) above shall'not constitute a p breach of this contract, and, further, if Mete'd chall :b.ere-fore direct EEN to proceed under paragraph (a), ELW shall thereupon proceed as ;ct cut in paragraph (a), provided that Meted shall Grant ELU an equitable adjustment in "the' affected delivery schedule. (c) If the Meted requirements cannet.be satisfied in any degree without changes other than the exempt chan5es, (E&W shall nbtify Mated in writing of such conclusiona and the rea ons-therefor within enc (1) month'following the Meted advice), or if Meted chall reject'the encrcy objectives identified l by EL)! under (b) above, or if Meted chall reqtient a design l change after havinc notice that B&W llc proceeding with
~'
the design ef' fort under either (a) or (b) above, cr if
~
Meted chall fail to give ::ritten notice ac tc i s require-cent: au cpecifiod in the firnt centence of thic -
. ... . , t .. n_
iC (b) (c) Article I C (5) BE! shall be relieved from further perfcrmanet under this Reload Batch Design Effort provision with respect to the particular reload batch. Such relief shall not e::cuse EU;l from supplying the reload batch or batches 'as described in Appendix A. In the. event that the reasons' stated by B&W that3EC cannot satisfy Meted's energy requirements in any degree, 'without changes other than exempt changes, are inadequate to support the E&ii advice, B&if's failure to have timely proceeded under paragraph (a) or (b) above shall not constitute a breach 1
. cf this contract, and, further, if Meted shall therefore dj rect E&W to proceed under paragraph (a) or (b), Sat! shall ehereupon proceed as set out in paragraph (a) or (b), pro-vided that Meted shall grant ES'1 an equitable adjustment in the affected delivery schedule.
Ilothin; in the foregoing shall,' at any time, be deemed to preven: MatEu frcm exercising its rights under Article VI of this contract. ~ e e W i -= V t..
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' t '. 21 3 II - Supel; of Scecial Muele:r Ma terial
- a. In'-ial Core (1) .NetEd will lesce from the AEC, or otherwice provide,
- pecial nuclear material for the initial core and will authorice Ef 3 or its subconcrac cor to wir.ndraw such
.T.aterial frca the AEC isotope separacion plant in conformance
~
~
with the quantity, enrichment,.and delivery schedule set out in Appandix B. , (a) To the e:: tent tha t the special nuclear material is ro ter131 leased from the AEC, Meted will pay all AEC charges including but not limited to withdrawal ena packaging charges, AEC use charges, and AEC charges for locres prior to celivery of the fabrica ted fuel accembliec to the Three Mile Island Nuclear Station site (herair.af ter referreo to as "the plan; cite"). The cerap and any manu'factaring usarages on special nuclear material will be returned to the AEC by EUd a t Lts expence and with rearonable promptneca in the " Standard Form" of cpecial nuclear material ao defined in Meted's Gpecial Nuclear Material Leace Agreement with the AEC or in auch other form which La acceptacle to the AEC. The cont of conversion to such "Stancard Form" or to such other form and the AEC's cervice charge, 11 any, for accepting cuch other form, chall be to the account of Euc . EhW ulll pay all AEC container charcas if any, and all chippinc costn.
.~ ,. . , n_ -
!! A (1) - 13a -
(b) To t.b. 9x ten t 1.hte t the special nucione mo torial is other than material loaced f rom the AEC, Meted elli pay all AEC charge in connection with the enrichtent, withdraual, and pac!: aging of the specisi nuclear ta eri) from the AEC, and bed will pay all AEC container cher'Ese if any, and all chipping. cocts associa ted with the withdrawal, conversion to uranium dioxide, and fabrica-
~
tion.. Except as otnerwise provided in thic Contract, Meted shall be responsible for all carrying charges on such special nuclear material during the fabrica:lon. (2) In the event of delays in the ' plant construction sche le thich are attributable to B&W, Meted may recuest E2W to
~
adjust the Schedulec Shipment Dates in Appendi:: E for t'.c-initial core, such adjustment tobenotgreaterthanapAricd ocual to the portion of the delay in the planc echedule
.;;;ricutable to E5h. ,2fd.f in recponse to such MecE5 reques:,
chall so adjust tho. Scheduled Shipment Da tes, and further,
.: hell either adjust the portion of - the rela ted schedule for delivery of enriched UF6,to B&W for which withdrasal-of cpecial nuclear material has not been made, or refuse to ad,iuct such schedule in whole'or in part. Tc the e::tont that' ESW chall refuce to ad,iuct any portion of-the schedule for delivery of'enrichch UF6 to Efid for.which uithdrawal of apecial nuclear material nas noc been =ada a t ; the time of the Meted requoct, ES'i shall, with i'e'30ec c .to ,
s, Special nuclear :ns terial leaced from the. AEC, rei:E5urseMet3d] o l 1
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- l'cr the eucace,. use ci'.r:ec i.ncurred by MatEn u i Special Nuclear !%tcrial Leace Anreement with and. wi th racpect to cpecial nuclear mate'ia r (
?.aterial leased from the AEC, pay to Meted the
. interest charres on the cost to Meted of the d,5 nuclear material calculated at the then curreni rate of interest, an a direct result df such E!
with respect to such portiion. If delays in th@ c.3 set out in Appendix B are requested by Meted i
~
reason othar than those within the control o~f 3 will use its best efforts to adjust the schedul out in Appendi:: 3, subject to an equitable adju of the Initial Core Contract Price. to reflect a2 thereby incurrad by EUU. s BON will use<its best; to minitlice cuch costs. /- O (3) In the event shipment of fabricated fuel assemb1 delayed beyond the, Ocheduled , Shipment .Date3'est& J Appendi:c B at the requect'of MobEd or fo,r any'rs 1
/ / )
referenced in Article'VIII,TtietEd, orlBd.1,'at Me t r - request, chall arrange fo'c ntoraGe of the ~ fuel a and chall protect tham ccainct damaceifrom tha wi
.a or other causcu. MetEdshall'accumef'and'indemn aGainct, the rick of locc or damage, and chall b i
ible for ctoral;3 and other renconable chargea, a
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of cuch ctorata, cubccquent to cuch Scheduled Oh$ 1 and until .dal'.'/ery to the piar.t 2 (te _. . EW! will y i effort: to .hinimico cuch' ::octc. Jf the delay 'in-r- f
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- Tr m :t to special nuclear ma ter!.nl Iceced from t AEC, pay co s'tE5 the AEC use: char.;ec for the pe.d of the delay for'the special nuclear material in
.iclayed fuel acsemblies and, with recpect to cpec nuclear material other than ::carini leaced from. '
AEC, pay to Meted the interest charges for the pe2 of delay' on the cost' to Meted of the special nucle material contained in the delayed fuel. assemblies calculated at the then current prime rate oI'-inter 3 Rolos5 220ches; Reclacement Feel Assemblies; and Repadr (1) :'202d will provide special nuclear material for ea the firch two reload batches to be used in the pla
.c required, for repairs and for replacemen assen i.e.,
aaccmblics to replace accembliec-rejected pu
.. Oc Article IV C and to replace failed fuel ascemb1:
- ~etEa will authorice ELh' to withdraw cuch material the AEC in the quantity, enrichment, and delivery :
cet out . in Appendi:t 3 for reload batchec as modifie p'.'.rcuant to Article I 'C (5) and/or Article III C (1 Meted will pay all AEC charges in connection with t i 4
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t s and pachacin,, oi' the speciat nuclear ::terial frca the AIO.,
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a:. 4:1.C .,ill pay all AEC container chirges, if c.ny, and all
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- 6 in this Centract, .'.IetId shall be respenci'le c per all carrying charges on the special nuclear m:sterial during the fabri-cation.
(S) In the event the Scheduled Shipmend Dates for the initial s core are adjusted pursuarit :to t,he first sentence in Article , I II A ~ (2), the ufo wit'.ddr). gal' schedules ,and the Scheduled 13 . Shipment Dates in Appendi:n3 for the reload batches shall ce correspondingly adjust _ed, \ '
'4 4N- s
- f. ! ;g I.: the event chipment of faiticated fuel assemblies is t
delayed s ueyond-the Schedulec Shipment Date, establishcd in s, . , -pp J ndi:: B as mcdified purcuant to the provisions-h: rein at the recucct of MotEd, or Ja any reason referenced in Article s VIII, Meted, or EtB,at Meted's'rcquest,shall arrange for v storaGo of the fuel assemblies ari.d c, hall .orotect them c:2 inst - i i dama;;c from.the weather er other b'ausgs. I-:e tEd shall . ac c r.e ,
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.; hall be responsible for ptor? h,.s and other reccc:r.cle charges.l 20 a result cf. such storagej ekosequent te'cuch Schedul.rd
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until ueliTery;to tho plant site. B"5 l
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- ill u e its bact :cfferts to minimine cu'ch costa. . IT. the
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.- .mc to an.y other r e::::ote, iWM ahali bone auch ricP. of loca or damage and cuch charges, if any, on. If the Sched.iled Shipment Date is as ectabliched in- Article III C (2} (a) or as adjustad pursuant. to Article III C (2) (b), and if Meted authorized 30W co withdrcw cpecial nuclear e.s terial in accordance trith the schedule ce t cu t in Appendi:: 3 as modified pursuant to Article I C (5) and/cr Article III C (2) (b), E&W shall pay to Meted the interes; charges for-the period of the delay on the cost to Meted of the special nuclear material contained in the delayed fuel assemblies calculated ac the then currenc prime ra:e of interent.
C. Fcbrication Scrau and Manufacturing Overate f.on-irradiated ccbap resulting from the fabricacion of :he
-pcrtion of the initial core containing special nuclear nacerial c .her than material leased from the AEC, from the f2b.'icacion of the relcad batchoc, alic rrom any repairc to, or replacements of any fuel accemblier supplied by IMdl hereunde,r v:111 be promptl; proce cod by E&N, a t no coct to Meted, to the form of uranyl
- itrate colution and delivered to Meted f.o.b. place of proce: Gins. Any manufacturing overaco of cpecial nuclear
- dcorial (othcr than cpeciol nuclear materini leauhd rrc= che AEC), at the option of MabEd, will be either promptly proce5 sed b/ E&M, at no cost to MdtEd, to the form of uranyl nitrate solution. and delivered to Meted f.o.b. place of pr0cecsin.;, or ~ .
~
dell .'ered to Mat 5' 5t t'he pl2nc citi in the form in : higi
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eniats *.::en it 10 . determined to be. manufacturing overage. 15radfatca dicidy 62c5IE ~dy"frc= ' the repair of fuel assenb1'.e: tril-2g un.e u:a .--
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": * , J . : !!T - T'tle. 'bliverv anti 'jchedulo c A. T'tle ind Rick of Loco Title to all fuel accemblico and to all cat' rial cupplied by Eel under thic Contract (other-than the special nuclear macarial laased from the AEC and the special nuclear material) shall pass to Meted when the fuel assemblies arrive at the plant site. Except as provided in Articlec II A (3) and II E (3), risk of loss of, or damage to, the materials supplied hereunder (including the special nuclear material).shall pass to Meted when the fuel" assemblies arFive at the plant site. -
Encapt as provided'in Articles II A (3) and II B (3), BE+!"shall
~
dear che risk of loss of, or damage to, the fuel assemblies and catorialc supplied under this contract including the special nuclear material leaced from the AEC or otherwise provided by ."etEd prior to' arrival of the fuel assemblies at the~ plant 4 c_:0 in the case of fuel ascemblies, and prior to delivery te
%tEd (or the AEC) in the case of fabrication scrap and e
T.anufacturing overage of cpecial nuclear material, all subjec:j ho.:e ve r, to the other provisions of this concract ~respecting p.ilowable procencing losses.
! E. Delivery Fuel accembliec shall be delivered f.o.b. plant cito. Tlha typo 'of transportation and the routing chall ce determined 4 ; cy L b';! . Trancportation-chargea shall be paid by SW!. Shipping-containers chall he returned to BY! f.o.b.-plant cite ac coon ac 'prEcticable following delivery of the fuel acsom.blies but not later than -30 dayc following delivery, in as cocd a cond* tion ac received allowing lfor normal usar and'
+ tear.
. - . . . - ~. . . .
J^ 7 197'. 4 IiI e l 0 C. D 714 zerr Schedules ( .'. ) Initial Core T'.e initial core fuel assemblies will be chipped to the site at an appro::imately uniform rate between June 15, 1971, and Decenber 15, 1971, or such other dates as may te mu ually agreed upon. (2) Reload Batches (a) The Scheduled Shipment Dates to the plant site of the last fuel assembly in each reload batch are set forth in Appendix 3. (b.) Meted may adjust the Scheduled Shipment Dates for the
,, relcad batches, upon written notice to ESW twelve.('_2) months prior to the then Scheduled Shipment Ette for the first reload batch, and ten (10) months prior c the then Scheduled Shiument -
Date for the secend r61 cad batch. Such adjustments may reschedule the Scheduled i Shipment Date as much as six (6) months beyond'the then t l Scheduled Shipment Date and as much as two (2) months l prior to the then Scheduled Shipment Date. (Any adjust-
^
l ment in the Scheduled Shipment Date for.tlue first reload batch will result in a corresponding adjustment cf the Scheduled Shipment Date for the cecend relcad batch and will not prejudlec MotEd's right hereunder to subsequent) read.Juu t the Schedub:d ' Shipment Date for the ceccnd e o _ . _ . _ .
II2y ; I'JN 1 I l I L.! C (..!) ( b ) -Po-reload batch.) With ranpect to any ad.jua.mont pursuant to this Article III C (2) (b) vshich defers the Scheduled' Shipment Dates, Meted may defer such dates on a ten:h
. to month basis provided the total deferral for each reload batch does not exceed six (6) months, and provided that any adjustment notice by NetEd precedes the then Scheduled Shipment Date by tvielve (12) mcnths for the first reload batch and by ten (10) months fcr tha second reload batch. In the event of any adjustmen; of the Scheduled Shipment Dates hereunder, there shall be a correspcnding adjustment of the schedules, in Appendix B, for delivery of Enriched UF6 to B&E. Excepc for price adjustments in accordance tiith Article 17 D of this Contract, there shall be no change in the Contra.e prices in the event of any adjustment hereunder of the 1 Scheduled Ship =cnt Dates.
I (c) If Meted requests a change in the Scheduled Shipment Date for the fir t reload batch after tv:elve (12) mcnthc, and for the cocond reload batch after ten (10) months, prior to the then Scheduled Shipment Date or if Meted requests l- an advance of more than tvlo (2) months or a delay Of =cre than clx months in the then Scheduled Shipment Eate and' such chango is requented for any reason other than thesc Sithin the control of E&W, B&'.i will uce it ter,t efforts v to m2Ne such requested changcu in the schedulis subject :- an equitable adjust =cnt' of the reload batch price (s) . _1L_._.____.___ . _ . _ .__.-__.___._-_____.m._.___.___._____._.-______m _-. ____ -. . _ _ . _ _
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E3M will al o use its beat efforts to minimize ' the amo= of any necessary price increaseu under cuch circu:r. stance a
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A. Centreet P-i c s (I) Initici Core ' tic t Ed sha l l pay to ili/.t . for the f ab r i ca t ion o f t h<: initial core consis tinc c.f 177 fuel c:sembiias at:d fer the related 4
. =-
services descrihed 'in :hi; enntr4fc: the t ur. of Five till ien , j- Seven I undre:' 5ev::: :y- T1.ouswod Dol lar: (15,770,000) (herein a referred to as th:: "Initiei Core Cor. tree r Price") .
- (2) Reload Satches 1
11:t Ed shall pay to Sr.! for the fsbrir.acion of the fir;t ar,d scct.:G relo?d hi e.ch:s and for the reinted
. services de: crit, d ir, this contract ti.e sum of Thi r ty- T. o 78 ce.ar.d Dol li.rs (,132,000) icr each
+$
. . f or,r i ri: t ed f u : 1 a s s er.b i / (iie ctr i ti refected to as tiie "Fi rs t P.c ! cad Dstch Cor.t ra:.t Pr ict" c: the "lucorid Re l end !!c t ch For.t r c:t P r i re" as 4.ppr:::: i:.i te) .
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P. a..:.: ::. t . T: e I r. i '. i t. ! Core Cont ract Pr ice , t!:; F i r .! l : load l'a: ch L:ao t r..: t , Pricc, t.s ci the Sucot:( A: lecd S.:tch Contraci P r i ce , c s t n.:.y ::a r be adjusted rursuan.. to the r,ro > i s to:ir. :.f t h ~ s con t rhet , 1,hcIl be 1,a i d 10^,' n.:t cuti
. o.. sh i p:: re ts prora te.! c a. s'.i p.-.c:its go forwa rc8
, 1:c*..uver . . in Ll.c uven t shi pir.:nt of f t:bri ca ter f u.:1 ast.; .sh l ies is ' x, delc/cd I ,nad t'v: Oth::.It,le:1 !bi;.: mat ( 1tes a t the refqt: "
. t of
- Ite t Ed i u r' t
- a n t to Articles 11 A (3).or-Il b (3) , for r. .n.cns t h tr th: sri cle I.vf:. a t t r i tv al ! . t o G!'.!, ..r.tl i f D 9 i . ret.d y t a -
a... l. : , hip-
- w. o t pr ior to t he l'.:t T.J- recu i s t e.! ,liips nt ilt.t.s, of .ni; porti:n ,
.- of tini fue1 ,.ipply un.fes t :i a. Con: ract it'.tl. en .t hu J.in isi- r.ot !. - p. + y _ , ._ s . _ ~
-e--- ~ *
, _. = -
6 .. . . - - 1 sn.,, 1.:.) F1 2, i readinecc, chall be entitled to bill 95% of the amount it would hace been entitled to bill if chipment had actually been made, a' nd further, to bil1 the remaining 55 of cuch ap. aunt on the da:e of actual shipment. In the event that the Scheculed Shipment Date fcr the initial core is adjusted at the recuest of Me:Ed pursuan: to Article II A (2) to reflect delays in plant construction which are a'ttributable to E?dT, and . withdrawal of special nuclear ma:erial h2d pre ticusly taken place and if E&IT completes the fabricatica of, and is ready to ship, assemblies using such previously withdrawn i special nuclear material, B&IT, on the date of such readiness, shall J be entitled to bill 70%.of the amount it would have been entitled ~ r 4 to bill if such shipment had actually been made, and, further, to bill the remaining 30% of such amount on the date of actual chipuent. 1 All payments shall be due and payable 10 business days f su:.cequent to the date that invoices from B&IT are received by
....=,:.. ,
1
- C. I.cnoction (1,
. Meted, at any time within thirty (30) calendar days after delivery Of each chipment 'or fuel ascemb'ics (including.
repaired and replacement acaembliec), supplied hereunder to the plan cite, but not later than ten (10) calendar days after delivery of the last shipment of fuel accemblies for the initial core, for the first reload batch, and for i l t
. :a ; . .:r-IV C-(l) v the second relead batch respectively, (and proiided b
that Meted has not previously assumed the risk of loss of, or of damage to, such fuel assemblies under other ' provisions of this contract),-may inspect the fuel assemblies, and reject by notice in writing for cause
~
stated, any assemblies which are so damaged as to be, - or are otherwise mutually agreed to be, unsditable for uce in the reactor core due to even'ts occurring prior to such delivery to the plant site. (Meted, at any time it may be required under this contract to assume - ' the risk' of loss of, or of damage to,: fuel assemblies ' cu,0 plied hereunder at a place other than f.o.b. plan site, chall be entitled to conduct a prompt inspection and to reject in the same manner as is specified above ) . Meted shall further st$te, in such written notice of rejection, the date on which, in its best ,iudgment taking all available facts into careful account , Meted requires a repaired or replacement fuel assembly in hand at the reactor for incertion thercin without being rcquired to delay its planned ctart-up to . power which ' would have utiliced cuch rejected concmbly. W
~
___n . _ . s i Ha:/ > LVli IV ': ( :) ; ~- (2) If E?eW responds to such rejection to the effect that in S&W's best judgment, taking all available facts into careful account, B&W can have repaired or replacement fuel assembly (ies) in good order in hand at the reactor for insertion therein on or before the date specified by Met 5d, B&W shall'either repair or replace, at its clection, such rejected assembly (ies) and may elect the place'of repair if that remedy is chosen. Otherwise, MotEd may elect either to accept'a prompt refund by E&W of that portion of the fabrication price theretofore paid by Meted for any such rejected a'ssembly or to permit E&W to elect. to repair or replace any such rejected assembly (including election of the place of repair if that remedy is chosen). If Meted, when i.t is entitled to so cicat, shall choose to have a refand of the applicable portion of the fabrication price, it shall accept such refund as full satisfaction and final settlement of any and all claims and demands available to MotEd with respect to sucn rejected assembl; for which auch refund is made with the exceptlon or any claims MotEd may have under Article V A. Titic to and risk of-
- loss of, or damage to such rejected assneblies fcr which refund *is made shall remain in Meted. .
7 (3) . 1: hen EFd shall have made its clection to either repair l i,_ l or replace rejected fuel. asse=blies pursuant to Article IV C (: l l. i l
ai
, s f,. : ..
, . .ay , , n. . . a, a ni.: (2), MetEJ Chall promptly mace auch accombliec atallable to E&W, in the case of election to repair, at either f.o.b. plant alte or at a loca tion on cite ac
- pecified by E&W. ESW chall promptly make such repair or replacement. The cost of such repair or replace.T.ent including the related transportation, and except such costs as are assigned to or assumed by HetEd under other provisions of'this contract, shall be ho the account of ESW. Except'for assemblies damaged by evsnts be' yond the reaconable control of E&W, iftherejectedassemblies contain special nuclear material leased from the AEC,' EEW shall be responsible for the payment of,'or reiEbursement tc Meted for, all AEC use charges applicable to the special nuclear material c~ontained in' the rejected assemblies s covering th'e period subsequent to the Scheduled Shipment rate and unti'. the rejected assemblies are repaired or replaced.
Zx': 2pt for ' assemblies da,maged by event; bayond the reasonable centrol of ELN, if the rejected ascomblice contain other than Special nuclear material leased from the AEC, E&W shall be re:pencible for reimbursement of charges on the cost to Meted or the special nuclear material contained in the rejected accembliec, calculated at- the then current primo rate of intereut, for the period of time cubceouent to the Scheduled Chip:.~.cnt Dato and until the rejected fuel acecablica nra repairet or replaced. Except as to title to the AEC owned cpecial nucle 2) O d' e
. ~ - - -
- n
T11-1 IV C ( .1 ) . r.,.,.tc r i a l s , t i t l e to and r i s k or l os . o f o r da .:a ic t c the 1 1 reje:ted asse blics shall re.*a in v5s t e:d in Pet Es l 1 (1-) ner i:J 's fa i lur e to inst:c..t and/or failure to ti cly s.a o l . cons t i t u t e a wa i ve r o, .':e t -d r.ig,is, reject a . if ..ay. under this /. tic.le i t.' C , no t.si t hs ta- d it..i the p-$e:s!ons of Article X.d , a.d P.ct id's sole ru..: Jy anc i '. ' - s r. ole cb ir:ction th:r :r.f ter.s':clI be in c.ccordance . :in !v ticle V cf this r.cntract. D. __ P r i ce. l.c. iu.e, . . t. men
- Tt.e C..n t ra:t i:ri es for furnishing fuel asscwbli c ':,i s es d u r : n.: a 'e i s ,.: fat;icatica -^-(;r:, in
. .:n ce , c c: :,..nc i ng i. i t,i. . : r c..:.
/ (:Oc: ti.e .initio: :.c L u ;. a.. .. I N t/ - - i ;:. J UF., t / ';7.! and (.: . : r." w i G t . e S c r e.'.. i ' ;. t .: Of
,o.r; .' t es t.
tua .icst of tn.e r e c. . c scr. u : n :t. in t r.c
- * ; -i l co. t or * ; .. . lon tcl.. I'r> r pu r ; .o . . o f d e'. v . . i c. i rg & . mi.i: !Ob-i-r..;c.-' :.'ri..
p.-- - t o t it i a; s.:c t i ct: , 15: "ci tcda l .:. ,. ' . ( t ci !
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.: u.51 ,:. ::er'.i . l .ic 3 :n ttu 2- 1.3 , . '. .. .,, :. ,
. r. c an St.hedole:: C c t r. o.' S h ; p.un t o f t i- '
et f., . l 1 . ;'..- i 2r - a t c iie s lin<, . li i.1d f. r.l.r.l l be Oc to*ie r 1, 193 : 1 .'c ir 'ic- ! *i, 1974 c.c. i t % l .'s o n . e f ..,.: r .e t . . t e ar. ; c i a c .i
- r. . :. . sv.ey. 1.i- .
i s ,;
- c. . . . - .
t i.e i:.i t i.:1 corn, 'I t..il end:s c s. ,:: ttis l e.r l'a t ci. 7 'i (-
- l i r r.
- rel.:e: ..
5 c.41 :ada r r:.on t ti . fear l'a t c.. ,< S ( tiic *,: r c . i r e i c.ad ) .
.i he . r iu.s 1 ,.a,1: . i c.. ! .c.n ge< .r ,i r.% , .v: i.e.:.cel oa t hc ..c ;,
..m ,. c :, Mi
. ..,. r. '.
I'a i>. ; .:e c i'i i cd i r i.;,;.endix b <;r , at. L t.- r a .c u.e/
. .i s b.. a .: .. , .
w .
.- es.- -
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i is:I-l l 'i D -2C-f. ( delay (cr c.v. ten sicn.) a s tc c i ther cc: .acncemen t of the f abr icat ion pcrit.d, or cc.?pIction of the 105 fuel assc:::bly r. cdy for shipment, or Leth, in ccm: arisen to the Applicctle base fi.br i cc. t i o n p-ricd, at t..e ru: nest of Met Ed p.u.: cant to Art icle !!! C (i) or (71 (S),
- is designatcJ a+ the adjusted fri:ticatien p e r i c. ' . Upan ::. i6:nti-f ic t.: icn of such adjusted f abricetlori period th! s Pr ice Ad,: :s en:2nt pro /isiOn : ti.li beco.c cifactive and the Contract Price (s) s' et i !
be r! justed upwa-d in accc.-dar.cc with the follo..io";: (I) ( t.) .Mc te: r i r.1 : For thI c u. sc. .t cf t!iis ; rice Edjustr.:k previsiv:. caly, the nic.:u ,t re,p rc.. cat i r..; s ter i al' i s f i s.c d a t 45 re c:nt of t' 'ontr ct -!:e. I n ai i tias t i r. ' . .: : q. a :
. the
~
. I ndev.c s of . hol e.t.,1 c ; r i cc: for "I ron wJ S tec t" c :dar
- '.citc ! s and fi:tc i . r eda::: r. : publ i si-cd c:.:..iil y oy tna harce.o ,f '.ste r .tc t i s t ic: of t he ti . 5. Ccpartn.at of L .a b . . . i r. th: !:cn .S l y t. :b:.- f. . i c.. tri l i * < c c ,~. '. c e fo. the e
r:a c ." . b - i t.r. t i r.n c .c les :. The p c .- en t :.- < b y t : i c u .h
.:ver.. <
it 10.. : .- thtn Lin. . . ure.:;c of U... i t,4 .::. 7 0.- t :e ner7. .? f : e.n di:. i n the adj u t ed fo!,r ie , t i ct- peri,' will b e dc t r. i r.e d ..in-! c,.p i i .: t t o t h 2 re c :n t c::; et cut ::9 r.in t c r .i a l c r :. . xco ciove to obta.in th inc..o,iu i t. :i2 a::cua l repre erit.e :.e s.:L l a : ..ri. . . . The Con t re.c . r r ice- :. l . i l .i he i nc r. :. .r J 1./ nn c. .:aun: e. cu i ca l en t. to th. inerc...e in t iec .
- neu :t reprue.cn t i r.r. r.ia t e r i a l s. de t . ru i n ;d .
e 9 f* t
,n
'>>t:) (:.)
. . .. 1 d ( i, ) - , . .
w o o.n L.w... . . .
>~ - Poi t:'.e
. 'arpece cf thic on.1 *,,* 3
.. H. g .s.. . 3 . ., & pri':c ad,justment pro'it 1.n.. ,o .e,. .
- e. .- -
. .. ., ..3.6. i r.u.,r 5
- h. 2 .ne.,.c ,n u - ."v,.4, o A .o. .a. n w. * ,
v .e ....
~ .,.
.e.4 ,-ec
+. s c t o +...m ,. > c +v average .u. . ,., ,.,
.... .a.. a , .4 s
of the inde::na .
<..u.
t . > for " Primary I.'etal Indu of avera;;e hourly e . s by the Eureau stries";as published ?on t . of Labor Statictics j mont of Labor in the. ;ionthly of L the U. S. _ De cor.puted for the abor Review will be. cantage by which such avecase fabric The pes average of rage 10 1 4-the adjusted fabricatio the indexes for uraber the n louer th of months in and c.pplied to the a:noi:ntn period ' dill be de as fi::ed e.bova to reprecenting shcp lc.bor capreaanzinc, thcp inborobtain thee increa . aucunt ire.:r.d.:ced by an arao. The Contract Prica . 1 the un', equivalent chall b t ament r-1 (c) L s The indexen ..prementing chap labor to the incre u j .
.,for any :.>,1v. r. :..ca!.h ,
a) and shall 1L(b.)-b
- for that montn.
in Paradreph . .; If for~ any reason the ione fi ndonen o crecifi 1 publi::hed for any , or ir perLod1. . _ compiled (n)-P.ad or 1 indexeu la emi;'.ed any - co:::penen t- o r she 1-6 indo.,.:r ind:Me.: rrca tise publ'.* ched indexes , tna 1 (~ bu Uu .:ato ne. t;. :.t 1 ufor thar.e accu:.cd periodto-chal 1 i . ,to .r ci. :mi.:st;n. . :-. cor.: piled or publich.'d . . prio
- ".:culd cuci
*.1
,.e. . , . , . ..
,,......,i,..gv.,.,,.,,. . . . . .ca: inn ien cent.inus -
i -
. .%.,_-t...
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- 4 ,'.q
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~c d amM M' '
... a 1,
- 1. :.:-
s 1.' D ,( t ) -( c ) .- then upon notificatica by either party to the other 4 of cuch opinion E.MI and I*etEd chall negotiate the Selecticn of a suitchle substituta index to replace ! th'a indan or indexes ir. Paragraphs 1(a) and 1(b) , above. . (2) The percenta;;es in Paragraphs 1(a) and 1(b) above shall be ., computed tg the nearest third decimal place and the i.. crease cr docreacc for caterial and shop labor costc. shall be cal-cul?.tod to the nearect dollar. 1
- (3) 2.; h e e-vent that Contract Price Revisions are negotiated I f.ar chan.cc in tne Contract, such Revisions shall~be priced as of the applicabic Scheduled Shipment Dates and shall be
..ied to, or subtracted from, the Contract Price to cbtain
. . : viand Contract Prica ?;hicF shall be used as a bas $3 for 4
, r. .: forc/;oing material ~ and shop labor price ad;iustment clauses.
I
~
~
( '! ) idynentu of all prico adjustmento ch:.11.be due and pal table.
..; nn receipt of intcicon. Invoices chall be rendered ': hen
,i
- .au-final pay =cnt on f.he Contract Price ic dub or '. hen hev r
- yuired indcac.: Cer complete adjustment ar: a eailabl::,
.:1cheve'r' la later.
e i d
. %~
. . _~ ._ _. ._
i I _ n, _ ..,.
- ; . ,. 'l .
...,, .,r- ...,. ..... L..
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. . . . . ... .... ..,1,,,.,.,.,..
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. t s.,
2"id tiarrants th.t the initial core and the tuo reload catcr.cc cone'..: ting cf a total of 294 fuel a semblica: (2) chall 'ce capabl? cf prcducing a total of not less
- i. .c- ,a. o%c o_ . 9 * ,.,,_ .,
J. ,w 3. w,. o .e _n ,4. e4. . w.. n
.m u...... e.. ts s.,.4
. v ., (=tu)'
ui:hout necassity for operation of the rasc cr beyor.d depletion of reactivity. of any reacter loading containing any of'such fuel acaemblies, uithout necessity for operation o,f the reactor at condf.tions
' ~
more restrictive than tho operating'limitationn ctated in Table 18 of ' Appendix A and :tithout ns cessity i for restrictin;; the plant:'a maneuverability c.u. o.... c. .,4. .,. . , t i u.. :
.t . s,, nc; .t..,
. .n. ,.
(b) uill con;ain, .,then discharged from the reacter (upon the cuccessive events of depletion of reactitity) n wv, e. _ ..., , <-
...,,n
... .,r_ ,ija-i.4 1.s,3
. . . . _ 23 oi .n. ., ..
.. . ,, u m , u . . . ., ,, u a v:eight ed average accay .of not loss than 0.93f' of l
iiranium-235 and not lecc than 859 kilcarams of Plutonium-239 and Plutonium-241; ( .: ) ' t-till require that Meted provide. not more than: l'i l o c r c:r.c o r Ea ric:r.en t . enriched U as C U-233 !^ , U W. , ( '.m. _i , * ~.2 ' '. "a... " i . ..: For the initisl' core e u. ..u_..,.,
.. . . < , ; ,, ,. c . , .,--o _
fuel ascenblia; 8h,~dQO 2.02 For tbc first rolcac-
. u..... s.,,h c c... .,.u_.., i., . o c:p, fuel a.:ar::blic.; '26, 'T65~ 5 22 Fcr t:.c .:occ::d relcac
.,..g'. ,,.*f*
. ( . . . . .4. . . e ...
- ,1:ci ac ucc.7,,,..t. . ,. , , .
. c_ c.;, a;;c , , , . . ,
m a as a m .A___ -+
V'A(1)(d). (dj 7:ill cc:, nin, upcn delivery; r.ot more than L quantiti?3 of IictEd cupplied urani'.un and hav cach case, e.n acaay in cuch IictEd cupplied u not less thr_n the neighted average ass.ay cup IIctEd as UF6-
.re. 1c.. , ... . ..
For the initial core consisting . .. of 177 fuel assemblies, _
- ,62,4 1
For the first reload batch- " E ,- consisting of 56 fuel assemblies .
- For the second reload batch 76,~
censisting of 61 fuel acsemblies
?till result in the return of manufacturing s
. (c)
- - for.r. set out in Articles II A(1) (a) and II priate, c.nd/or overage quantitled of not last
.r s Kilegrc:ns assay not i
weiahted a sunclied B 7cr f.he init2.a.:. core ecnsisting .
.m.
c , .. .i uc,
.it t L.cse:nblie.3 1 i. x.
For the-first rulcad batch conciuting of $6 fuel assemblies ~3CW For the seconc relcac bar.ec 39T ' conciating of 51 fuel accomblien. 4 l a e'
- here J, K, and L are the c::tenta to which the te of i4ctEd supplied uraniten v:arranted in (d) above sta.i of the actual qrtantit.en of IIctEd supplied u.
In t::e 'rucpca'.ive cerc and b .:tchc0 cc mancured a:
' b.y iWei ac th . ',1=c of pre .ranlon for chipcent.-
i - f I- . 9 h
+ +-
s.- -r--- er - . , , , = , =wvr -"- ,- i-
-t ,-
t
. 1, 1. m
. a s. . . .; n-(M) P. c: ."r:nnn: o 5:ar: : n f.- Ad.hi:: 1.: m . t. c
'O
\ / If anJ" . of the fuel assemblica supplied horcunder arc do:r. aged by . reacons not uttributable to EE:W due to an -
etent occurring during transit to the plant site or cccurring after delivery to the plant site and t:.erefere are not inserted in the recctor core, and are not reple.c e d with replacement assemblies the performance warranties in Articles V A(1) (a) and (b) shall be appropriately adjusted to exclude therefrom the energy and discharge quantity and assay of uranium and quantita" of plutenium anticipated t frcm such fuel sssemblies to the extant such exclusien _is consistent wit.: core characteristics considering the omissicn of such fuel assemblies. 4 4 (b) If the actuc1 production of Etu's exceeas the quantity warranted in Article V A(1) (a), the warranty in Article ~ ,
, V A(1) (b) of total quantities at discharge of hilegrans m' uranium, Uranium-235 accay, and kilegrams of pluteniu::
inotopes 239 and 241 shall be appropriately revised. (c) In tce event Meted elects to remove fuel assemblies for-reanonc cther than mechanical failure of fuci prior to or to cperate the plant after, depletion of reactivity,. the warrant.:.<:a in Articles V A(1) (a) anc (b) shall be a.n.cro.criatal" s re ficed , provided however, that tnc wsrrante P,tu's in /.rtielos V A(1)(a) shall not thereby be increased. (ti) In the event :..eehanically failed fu.-d assemblic: cec 3
- r. :acved and re.cluced purcuant to Articic V D's4)(c). a ceparate r.cs cutput :arranty chall .cc agreed upon te: Ween p - ',. - - - . , -
, ,e . - , - - , - ~ -
.v.
, V A(:.-)( ;) the parti 0 with rea;;cct to cact. Cuch replacement a:cembly, if, and to the e.xtent that its design charac-teristics and. designated in-core residence positicn are intended to rasult in reacter residence (for auch 4 replacement assembly during reactor cparating cycles subsequent to the cna at .thich the replaced assembly wculd normally have been removed. In addition, tha parties shall agree upon a separate warranty for such replacement.
~
fuel assembl", J censistent with its design charactaristics and designat'ed in-cord residence position ~s, under which
~
its content, at the time of dischcr:;e Crca the rea'ct'or, in terms of quantities of uranium and plutenium and in. terms of assc.y of uranium-235 in.the contained uranium will be identified. Furthar, tha parties chall agree, upon EEf's election to replace, upcn ad.justments in the wacranties in lirticler V i
- (1)(a) and (b), if, and solely to the e::: ant that. the decign characteri.; tics and designated in-core residence positiens for the replacement acsemtly incrcace or decrer.se j
the ability of the romainin.; originally-supplied fuc1
- accomblics to attaih t.hcir initially unrranted capabilitieci (e) In the event'that mocimnicall;/ failea fuel asse:: lieu sre rcnoyed und so ttica.ent thcrofor .10 cade purcunnt to Articla V B(4)(d), and/c,r .in ' the o'/ent that itael a00ctblie.$ .
r .
- 1 i ' arc re,1cc
- cd - and Octtlement. thcrofor ic made pur ;:ent' to l Article -It! C(2) and DE! 1: nct entitled to an cd;ustment therefor pur: nant to. Artic12 V A(2)(a),
4 I e
i l 1 1
. .I s 1 t,r ' n. ,r. ; T, f, . ..;g_) - ;..-
(1) *!here IletEd electc to innert a fuel acsc:.bly nct cupplied by IMdl into the reactor in place or une failed, or rej ect.cd , 2?i.1 fuel accec.bly, adjuc ments _4 n ,t.is..,, ... ., r.,. _., n *., _a
- _i 1 .?s.> '. 4 c 1 ' ',' ,'. /.-1 , 6s ,i = . * .
b' '- ) o- i .c._' _' h. s-a .~.. d a (o."'o*..*.a..',, a 1 a :, 'u .". --..^^^^ .'< -. '= J-
"=
~~)'
4"
-. . a a--w----
a - -" a " "E. with the principlea e:: pressed in Ar;icle '/II of this contract. (2) Where Meted elects to operate the reactor with scae device other than a fueled fuel assembly in place of-the failed or re.jected E!:N assembly, ad.justments in 4 .,,. , r. _u _m.,1.,
- a 1 n,'
u.%....,_,,,4.,,..,
. . _ . m.. _
4 :ir n -
..h.:
1..
- ., ,_1 _,
be zado to the entent necassary to tal:e account cf the effect en everall reactor operating chcracter , istics of such I.;etEd decision. -The adlJustments shall be-limited to the effects of the device
"' e _.'.."' . 'c -
-. .,v a.d h.v .'. +u....-
. s..-.~ .9. ... _1 1 ..o "<. 4.'1". 1. " d- a.
. , .', u - o -
nents for the failed or rejected E!!.1 assembly which i: not insertad in -tne reac tor. (3) It ir., agreed that tath of the fore $.oing J warrranty ad.):ts tmen t provisicnc ma.",.be a.n.nlicable witn res.nect , to .ir:y given :*ciled , or reject 6d. I'?d!-cupplied fuci accc.mbly carit:r the pericdc of re :idence of :c:y-l S.s!_::upplied fuel a::.;e:d: lies in tha reactar. (f). It 10 ogreed that, wit:.in Lnc variaLica.: por::itt.ad by the .
..,..-.v-v .m . . 1.
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performance by ;.ie cE.i he. ounder. The -:orrantie: in Articles Y A(1)(a) and (b) r.i;;.11 be ac.p a tc.. . cit <:r the final . tith-- u r , ..to, l v. ,- ,,,,.. r.e c i.. .. e.
. . .i ..,,..._;...
. . . . _ . t.. 1. c , ,. ., s. .. ,. ,,- . ,
.-, .. -. .. . . .%. .. , o. .2 c .. a_ v- -- a batc, ., i. c wu1.u. , c, ,. ..t. ., ... . . .. . . .., .. .. ., . . -. . . .
. 1 .. . .. c.. ~.,,c.,..,, .- --
c.e 't .i. .L u .' > '. . .*. . . . . ' '.. k . d. '. a . .".'. ,.:.....'....
...e.<.t+,.
.. .e e d uv e l .> ..,. .5 .e......'.. . , . ..
. l,. e
- i. L. e a -,,,ont.., ,,,ric.:
.. ..,,,_ . . . .....,. . .~. .
(c,) The warrantics in Articlas V A(1)(0.) cnd (b) chall be appropriately adjusted to the extent that the uranium quantiti.es actually leaded 1,nto thalfirst core and first. and second relcad bate:.es vary not more tner. j- 0.5% frc= the ncminal leadin - of Kilo srams of U s.cecified belc:: . Nominal Kile;;; rams
. of U as UUo
~ For the initial co:e consisting _ . . . . .
of 177 fuel asse:cblies 82,063 For tha first reload bn:ch consistin.3 ..25, ce , of .56 fuel an:<-m'a lies For the second reic ':! M i ch _. consistin;; of ol fuci -.;;emulies O$. .,2:32 (h) The warranted quantitie.1 in Article V A(1)'(e) chall be adjunted to the exten; nececcary-to reflect the differences between the r;unntitius withdrawn by P.9;: hereunder and the
'luentitlen rc rp;en .cd :ro;. i.he 0S/.70 .
(3) m.:gis tion.: o f P ;r f r = u .c o .::2 rrnn t. e
- .:W' c performance : n t ran'.ic.:. are s ubfoc t to the follo.-1::;;
cona'tionc: (a) The equip:.icnt en! .:.' . rialu a1~.'.11 be opera !.cd . ted:ed,
. ._4.,,...,.e................,..e.,c.,...
. . . i , . , . ,. ,., . .. .;. .. , ,. c;, 4. .
. . . . . ...,...o..=...
. . 4....
- . o , : , .....,. n . . 4. . . , , ,
. . . ,.,...,si..,.;.,..,.....,,i 1 ;. . , .
- .,,. , , 4. ,.,. e
. . .:.... .; y.. . . ,,--
s..,,
.y ,'i il VI a(2) (a) ~
~
reasonaole maintenance, operating and refueling instructions which may be specified by ELN and uhich are concurred in by NetEd, which concurrence shall not be unreasonably withheld. The opera' ting
, instructions shall not impose upon the plant cperation limitations more restrictive than the operating licitations set forth in Table 18 of Appendix A and shall permit operation at a core power level of 2535 MNt. Nor shall..such operating instructions restrict'or preclude plant maneuverability as -
described in Appendix A. .In the event the plant is . operated outside such operatins instructions as a . described above, and beyond any operating limitation -- set forth in Table 16 of Appendix A and if such operation could reasonably be-expected to have adversely affected the fuel performance, the warranties in Section V A and V B shall be appropriately adjusted to reflect the effect of such operation. -The operating instruction chall. include provisions
- - relating to the extent to'uhich instrumentation and-control equipment 10 to be available to monitor fuel performance.
l_ (Cont'd, on page 37a) I .
7- ,
% ll p ] ??'l5
-3 71-(b)
H&BI shcli have the right to participate in the exemination I of any core components, including partially-irracisted ccmpenents, and.to examine and reproduce records of the and, to the extent
- operation and maintenance of the plant available to Meted, the fuel reprocessing procedures.
for B&t! exa ninction, Meted a6rees to secure and preserve, appropriate records of . operation and maintenance of the the fuel plant and, to the extent available to Meted, , reprocessin;;; procedures adequate to enable the parties to prope,rly. ascertain their rights and duties-under this performance uarranty. (c) 3&57 shall be given written notice of any deficiency in performance cnd any ccndition which might indicate a deficiency in performance with sufficient prcmptness o to enabla 359I to make a timely investigation of such condi-tiens or deficiency. (Continuad on case 33) l f 1 l i 6 4 L __l_ 'm e - -,s L'..m .e . w__
.l l
Ma,*/,'l#)71 l V A(3)(d) l 1 (d) All fuel assemblies used in the plant during the term ' of this warranty shall be supplied by E&W or' as prescribed by B&W in accordance with the provisions of Article VII. (u) Remedies (a) In the event that, during their successive-periods cf residence in the reactor, the fuel assemblies shall have been incapable of producing the total quantity of Stu warranted in Article'V A (1)(a)," as adjusted pursuant to any' and all'of the ' adjustment prdvisions ir$ this contract,
~
B&W shall pay to Meted the sum of $35,600 for each one
~
(1) trillion Btu (or part thereof prorated to the nearest billion Btu) of deficiency between the actual total quantity of Btu produced and tlie warranted total quan-ity of~ Btu. (b) In the ev.ent that the actual total quantities when discharged from the reactor of Plutonium-239 and Plutenium-241, or of uranium, or the. actual assay of Uranium-235 in such uranium in the fuel assemblics, as' determined by measurements and determinations made during_ reprocessing cf the fuel assemblies, as adjusted for reprocessin; lasses under arrangements effected by Meted for its account, chall be lesc than the warranted total quantities of Plutonium-239 and Plutonium-241, or of uranium or-the warranted assay of Uranium-235 in such uranium warranted in Article V A(1)(b) as adjusted pursuant to any and all L of the adjuctment ' provisions- in this centract, E&W will promptly precurg and delivery t'o Meted at no cost to M- m e oSA -
V ,' (.*;} (! ' :.:e t.Ed anan m:.on:.:,c cf en riene<! uranitmi anc . cucc. ocour. ,: cf plutoniu:a 23') and 241 as will on-ble t:et.Sd to accure r..... m .c ..
.. . r. -...g. n,.. . g g w,.... ..a. g ( .4 *. _:..a.. O.,t, w.._. u .,.s. ) . .
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,,pm..a en. g .4 g. g .....
. . I g,,.,.
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. *u*
. m .c _o _ _1e fuel assemblies purcuant to Article V3.(3), Meted may obte.in larger quantities of uranium from the renoved failed fuel assemblius th'.n would otherwise be une case if such assamblies retained in the core until their scheduled discharge. '. Ti t '. .-
out Y:crogation of any of Mated 's rights under Article V5(4), nn'i in the event cf such removal of failed fuel assemblies
.:.u c.c a d :ficiency in the actual to:a1 quantities of
. . 4. . , . . . . ; ,. r. .3A.. . . . . ..U_;
..i A
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.
- O., and P_~ u*.. . o.=._4 i..m . O.,h_1.
. n' ' t. "., _* : . . i_ .'a. .' .
credit 2'iI with not mere than 50 percent of the er. cess
. ,. ... .. es.
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. . c.'. .' u c h. .
'1: removal er fciled' fuel andemMies,. which credit shall
- . .: applied .(cn a kilogram for kilogrcm exchr.nce b:::is) unly assinat the deficiency-in the discharged quantity cf ci.ut.onism. 239 acd Plutonitun 241 when compared with the
- n . a::t.cd dineha n',e gur.ntity of Plutonium 239 and ?lutonium "cl. The t.cicht fraction. of the plutonium 239 and 241tcc;cper ec.c.t;.:.qu in tno total plutoniur. delis arod by El:4 shall be c:.u:entially identit:al to the weight fractica of such 1:.:ota.nt 0 in the cucotaced .clutonium and in any e*/ent r. hall .
h .: '.:1 th' n L nn r u:ge c,i'
~
O.70 to 0.0 0. De'tive rit>J '. y E:d! c, .. < ., ...,. 4.... , . s. . . . i. .t. r ... c. .. .-.. .:..o- ,, , 3 . . c.n._4 . . ....is.,- c,n. .t. ., w ,. p - . .. .. ., ____n - - - -
3 1 qs . . . , . . .. . , . 7 c:r it:ri:la 1 <:onmy'me , r. .; ';aan ; L: : '- en / he :e '..;no ed b"_iietEd :encirtent ulch Meted'c licence for po:sessi.cn of,
. . . . -e .l.
. .. . ,. . . 4 ._.,.
i.) t - .. .'1 ti .$ .$ ". m. . '., . . .. . , '^t..- i, .~. .~. , u e. l_ .q"~* n 'v .t
- t = ". c .
, , - . t. .w. . . _' "m... n . . .,:/o .
;..,,.., ... o
. . ./ oi* U. ~..,'."-.a 2 .7s i.. e .- a. 5 6... . . . .. t. . , e,.g vc.4 a... . u ,
. m,. ,. c,.
uranium required for tr.e fabrica:lon of :he initisl core (or che first or seconr. roload batch) e:: eed ti e cuantity anc/or weighted average assay warranted in Article V A(1) (c ), EM1 will procure, or be financially responsible for, . the additional quantitles and/or assay of private-owner-chip uraniu:. in the amount of such excess _ in sach case.
' ith regard to the initial core, to the extent that the
-:pecia. z. nuclear material therefor la leased from the AEC, 3E1 Chall give written notice to 14etEd of the prospect of Cuch an event in a cicaly manner aufficient tc permit 7.etEd to cecure the written :!;reement of the AEC, if necessary, is
;6vance of cuch mi::ing er blend 1nt; by Ed:b of priv n:ely-cune'; uranium with the enriche~d dranium obtained under i4c tEd '; f.pecial Ih:clene ita terial Lea re Agreement teith the AEC. Filethermore FC&!, on a timely ba a10, Zhall e::ecuco e,uch aigreements (other'than any agreement unich
'an./ r-aquiro p&l to purchase AEC-leased cpecial nuclear ec.terial or to pay.use enarges theraca) as may ce necessary to preclude automatic cale, to Meted c,f Che cpocial* nuclear unterial 10ccad from t;m AEC ac a result of cuen mi::ing or blendi;L- by v trtue o!.' any provi:: tons in Meted 't. Special
-a
.-. ,st c _3..s. .,. , c.. .. u .s. .,_i ,. L .-. .. . ., .3. .,.,,, ., .t. .un o 1 ,. i.. + , o . n. A .
.1
L- .if h
.; , 1 .
Ma./ , ..;/ .
.el-r, .).(i)
( .i) In the event that the. init LS1 cor<: a:1<i/or e ithe r or both of the reload batcher, upon delivery by Ea?ti, contain a weighted everage accay of ur.anium ls~ r.: than the weighted averace assay cupplied by 1 Meted as UFg pursuant to Article II, EEic chsld, pay to Meted within (30) days after delivery of the initial core and each such reload batchec, the differenca,between the value of the quantity and assay con'cained in the initial core and in the reload batch ('es) and the- value of such quantity at the assay of the UF6 celivered for such initial core and such relosd batch (es) by Meted 'essed upon the actual cost to Meted of supplying such" UFf . including associated transportation costc. (e) To satisfy the warranty set out in' Article V A(1)-(e), Y E:le! chall procure and deliver to Mated such amounts of enriched uranium as will enable Meted to have the requisite quantities of such scrtp or overage' mate fal, in the form as prescribed in Article II A(1) for initial core scrap and overage and in Article II' , for reload batch cerap and overace, or, with the concurrence of Meted, rei:aburce Meted for ( L) the coreccpondin.-j locces coct: payable,by Meted to the AEC unJor MetEJ'c Opocial Huelcar flaterial Loa ;c-Acreoment for the initial core or the .valua of th s ccenp and overace deficioney as acacured by MotEc'c1 coct of procurin:; the cupply of enriched UFg (ce y the in' uial core if not leased frota heAE.:jand
' (00n:'d. on pass-412)-
6
- a <e. . s yowN. e; , ._ f _ v
.s.. . . .,. , , .1,- :
I 4 4* i A l n, - l 1 1 _ (11) tne value of the cercp anu cverc;c defic _w.cy a :nascured by [40tEd's cocta of procuring the l aupply of enriched Urg rce the fir 0t onc ::econd reload batchec respectively. (3) Lafinitien of Decletion of Recctiviti Dipiction of reactivity shall be deemed to c. ave occurred when the reactivity of the reactor is insufficient to permit steady-(Cont'd. on page 42) e 4
*eauB e
I 4 9 enma e r a g n e e e
_. ,. _ - - - - . - -.. .. .. - _. _ - . - . _~ - - . - . y
~
.;, i:
,.. 1 ,i
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w ,, i
,e.
n ( c.). .
.,2
,, .2 +
.itate opor tion at the applicablo. power cutput. warranted in f
the .clunt centract and in accordanca!, . 'tith ~ ~
':he USAEC c.neratin=-
\;.
licence c:::iiticas i(in effect' at 'any' time r;hile the core -is
, s
\sn "E . .
.cc=pocod exclusively o.{. Es.el asse.mblies supplied hereunder)
. ' other than those t:hich' I!!d! demonstrate: 'are conditions direct 1;- t . > s , and primarily related to an increase in the stect cutput <cf p s g ; s . the plant 'from "\the additional 'Jarranted outpus".En the olant-can' tract!to 2535.,M;1t core ocwer. ' (6). ne'-4rminatien or ueat outettt ) (a). The actual total quantity of Btu produced by the initial
' ,* ,e core and the two relcas;, batches ~shalls be" determined by:
i 3 1 i 4
)
(#1)- The poner distributio.7 in the relacier, as determined s s' , by .M ytith> the concurrence of 14etEd,- (based en + l
. calculations y and ::icEstre.hents made during startup), .
g - g
~ and adju3ted peric61'cally durir;g plant operatic'n: and i;
~
r ,
\
; (11) The%., accunulatedrheat output of tne reacter during
> s
.g. *
- s the pecioptthan the initial core and the two reldad '<-
s s.- s 'r, fs a t. L s hatchen nnie in the reactor.. The heat outout'of :he
<g s 1 reactor will be w tbancd y unon~ calc'ulatied stean: production
- . s
'4 '
m y, and system hc6.t talances. IdetEd'shall =cintain s s , , ,
.7. .
. ., propor calibration ofi pertinent' instrumentation and' s . r n
. 1, \*
j ( s shol1 $ahe peripdic inspectiona and ..djustments.
'"1.
- b . ..
vp for thQ' purpose. ', 22S -shall bc ;iven -acccan to the-
~,
s i : s s records relatind.,to the.de instrwnents a::d may pre ride - c . '\\ , te,Epera.ry crocial teht inntrur.v'nts' to vsrify c,uen
~
+
,. 3 s ; ,a.
s- s calibiationa.C , f 'g.
, .\
-- g
,. e- i
-(g)iIf'.etEd"cycre.tys the plant after depleti n of re :titity, l s.
.' 7 [ tanyucutput'so,obtained chall be' included in-the accumulated y
e 3 ,_ 7
)
Li .
. [ - '
.G. , ._
3
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i i
~ V A s' O, ( : ; .
IG - heat output unicac depletien of reactivity occura prior to a scheduled refueling ("ccheduled" cn the basis of units of energ'j) in uhich event only the cutput obtained frc the fuel assemblies whicn will remain in the reactor > during subsequent cycles shall be included in the accumulated heat output. B. Warrcnc' Mainst Fuel Mechanical Failure (1) Warranty 3F.I uarrants that Fuel Mechanical Failure of the assem'clies supplied hereunder, including replacement fuel assemblies > cupplied pursuant to Article V B 4 c and Article IV c 3, , during Operation of the plant ac core power levels up to 2535 :.~dt will not occur before the initial core and the cut-
- .r; ent first and second reload batches have satisfied the
;*errorma'nce warrt_ncy in Article V A(1)(a).
( ~ ,' inition cf Ftml :iechanical Failure
- /uci Mechanical Failure shall ce deemea to have cccurred when (i) alth the purification system in operation, the continucus netivity.of Iodine-131 in the reactor primary coolant exceed:'
3 0 microcuries per milliliter (ii) detected and identified by failed fuel element detection proceduro; to be agreed upon by 374 cnd MotHd, or (iii) normal operation of the nuclear rencLor la prevented by any obaervable or measurcable change in the physical dicencions of any fuel assembly. ( ~2 ) P.>=ctal o!' Failed Fuel
.In the ovent of Fuel :::chanical Fcilure, specific fuel assc=blics J
=
supplic'l hereunder chall be deemed to have mechanically failed,
,<r -
.a .:1. -.6 V B(3) -4h-and MetEJ may remove them if the assemblien:
(1) show vicible penetration through the cladding, (ii) shou observable or measureable change. In phy:;ical dimensions, , (iii) have been identified by the fciled fuel element detection precedures, or (iv) should be removed to provide reasonable assurance against the occurence of Fuel IIechanical Failure prior to the next scheduled fuel refueling date by mutual cgreemen (h) ?.emadv (a) 3LW, as it may elect, shall repair or replace each mechanically failed fuel assembly, or BiU may make a financial adjuJtment therefor as provided hereinaf ter; provided, hc;1ever, that any such election to make a s financial adjustment, for a failed initial core assembly, cr for a iciled first relcad batch acceably during its
.ir:t cycle residence,' !n11 be subject to the prior ccncurrence of Meted. Ert! shall give reasonably prompt notice to Meted of its election. If ESW cannot make repairs on the plant citc or deliver repaired or replacemen; asce:r.blien (allowin'g a renconabic interval for IletEd to cupply additicnal Special I!uclear liaterial which may be required) to the plant cite in time for insertion in the reactor ::ithout delayinn :lotEd's planned Otart-up and return .i;o po;;er, Meted i.;ny elect to require E".:W tc make l c financial no: ;1c= tnt na hereinaf cr prcvided.
O w
/ e-
--_ .-~-- -. - . . - . . - - - - - -. ; l l
th/, l' 71 l V B(t. ) /1-)
-4 5-(b) If H.tW clects tr> repair railed tuul annemblicc, Meted will make !.he annemblian availabic for repair and, with-cut cost to B&W, will place its site facilities including
- its fuel storage pool and its site personnel, to the exteni
- available and not inconsistent with percennel Jcb classi-4 4
fications, at B&W's dispccal to assist in the performance of repair work under B&W's direction. ' If such site fac'111ti[ sand /orpersonnelarenotavailable,ELW,at
~
its expense, sha11'prov'iSe personnel and,'if necessary",
~
alternate facilities to perform the repair work. B&W challbearallccstsofn(ce'ssarymaterials(excluding , supplementary special' nuclear materials) and of trans-
. portation in connection with the repair work. Upon
- s reinsertion in the reactor, the performance and fuel mechanical failure warranties on such repaired fuel 4 assemblies shall run a.s if no rcpair had been parformed.
1 ]; (c) If EYd elects to replace failed fuel assemblies, Meted I shall, as promptly as practicable, make availabic to EaW, at Mot 2d8s expense, all speci~al nuclear material required by BSW, based on core residence cycles to be'specified by Meted, for all of the replacement fuel accemblies 11 conformance'with Articles II B(1) and (2). .S&W shall, j nc promptly as practicabic following its receipt < cf
' Meted - supplied special nuclear material,- deliver the
~
.replacceent fuel accomblics f.o.b. MotEd's plant site.
Promptly upon auch delivery, EF4 shall be entitled to l I bill,-and be paid en acccunt, for each such replace:sent i i
i.
.a. , - :
, 7 l!(h)(c) 46-fuel acccmbly .:n amount determined by multiplyin.3 .
$34,200 by A.
II , Whore: A = actual equivalent full pcwer dayc'of residence in
. the reactor core of the replaced fuel assembly, and B = the equivalent full power days of residence in the reactor core of the replaced fuel assembly specified in Appendix A as modified pursuant to the provisions of this Contract.
The heat output performance obtained from such reclacement fuel assc=bly, during the reactor operating cycles during
- hich the replaced assembly would have been in the cere, Shall be treated as the heat output performance cbtained frca the replaced fuel assembly for-the purpose of and ac described'in Article V A(1)(a).
( <i) If ELW makes a financial adjuctment for any mechanically failed fuel casembly pursuant to Article V B(4)(a), E&W chall make prcr.!pt pay;.1ont to Me'tEd of an amount for each ' such mechanically failed fuel acccably determined by raultiplying the figure of $34,290 by tne fraction 1 - A E which payment. when made chall constitute full satisfaction
.of EMi's obilgationc under thefudL aechanical failure warranty.
in Article V L, and where A and B cro defined in.(c) above.. (5) Conili::lan:: of .~:el iMchanical-Fn11ure Weirrantv El-W'c warranty. acclnct Fuel Meenanical Failure is cubjecc to
~
t.he ccnditicns cet forth in Article V A(3)(a),-(b) and (c)
. 1, T n*i1 V ll(b) . and to the following conditic,: .
Uo claim under the warranty against mechanical' failure of Tucl shall be made with respect to any fuel o ncerr.bly subsequent to nine (9) years following the.date of ship-cent of the first fuel assembly supplied under this centr;c:: 3 O e % e m 9 t O e I l O O 1 l -s l %.
- - - . - , . . . -. .e..e., . . _ . . _. . ._ ._._
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in ** th~N AUel. 5 o*' ,, ~ is: C a ~eO . u tcqui cd au' - d w., ,L "orn G n d / o r' g ,. - a UU"* w, " ' ' to ~. cura "00 - it:igin ".. 2 ply
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' ton pay
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i12y , 195 l VI C ! fuel design and supply, provided that the time of p( . shall be appropriately adjusted. If, subsequent to acceptance but prior to final acceptance, as definco C of the plant contract, modificaticns in the fuel 6 supply are required as a result or USAEC requirement primarily related to an increase in the steam output from the initial warranted output to the additional put, as respectively defined in Articles..V A(1) and .( - plant centract, B&W shall make such modifications at previded that the tima of performance shall be appros adjusted. If, as a result of any such USAEC requirem to preliminary acceptance, or subsequent to prelimine but prior to final acceptance, a modification in fue3 supply is necessary to assure fuel performance in ace
. the warranties in Articles V A (1)(a) and (c) and V B make such modifications at its expense. B&W shall gi' uritten notice of such modification to Meted, but Met) written approval shall not be required. The limit of hereunder shall be equal to the sum of the Contract P1 under.
d
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- 3rorr:er:ra"n t of W:01 F om Of.norr U;;c:: r<; quest of Met.Ed, RE! chall furnich to MotEd cucn informaticn and apecifications ac would be required by qualified manufacturers o aubmi; meaningful bids for, and to supply, two (2) cubsequen't
_uci tatchos. Such infor:.ation will include, amohg other things,
-he information set cut in Appendix C to this Contract. In the even
- 40:
Zd procures subsequent fuel batches in conformance with the E?s supplied information and specificatiens to the extent relevant, EMTis warranties with respect to fuel performance and mechanical in ;2 rity shall continue in effect with respect to_ EST supplied fuel remaining in the plant. f In the event Meted elects to precure
..:_ equent fuel batches not in conformance with the relevant i .m.:i_'ications and information supplied by EMI, and if the fuel - per_'ermanac warranties are to remain effective, Meted shall n u.n.o l.v.
adeo.unte information to BS! to .oermit it to evaluate > at I:ct:2.a e:: pence, the design and construction of the subsequen-w.'l c.atches and shall make a new agreement with Emi, if necessary 2: .. . . - . Meted co desires, with regard to the centinued applicability o t'
.a fuel performance warranties. (Analysis and inspection au cicua by 3?ci ith respect to such cubscquent fuel batches chall L.
.2.id for by Meted based on quotations from EE! at the time suci.
ceniceu are required.) In any event, the mechanical integrity
.::a/..nt.y chall remin effective with recpect to the US! cupplied fue:
remainin:; in the plant, provided that the non-BST cupplied fuel,
- .e .
uned to.gether with the ES! cupplied ' fuel remaining in the plant c::all .ot c:.uco the EMI fuel accomblies to encecc the design' limits es ah.:.nhed in the _Cinal Safety Analysis Report as modified by E!51 approved a.12ndments thereto and AEC cperating licence canditiens.
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1 Delt:;er MetEJ nor 224 shall be liable to the other for any loss or damage re:ulting frc= any delay in performance or from any in!.lu.c tc perfora it.: respective contractual obligaticus, within the time pecified herein, due to fires, floods, strikes, labor
- dispu:cs, labor shortages, inability to secure c.ateriala, ricts, I
. :n . . ul.. . .
l theftc, accidents, acts or failure to act of government, or any other cause whatsoever, whether similar or dissimilar to those
; enumerated above, beyond the reasonable control of the party '
conce:ned which may delay or preventTperformance bereunder. The
; time of performance shall be extended for a period equal to the f tima lest by reason of cny such delay. 'Ectn parties shall make f every effort to keep delays in~ performance at a minicu..
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EYel st:all not be liable in any event for locs of cnticipated trafit.2, 1:0: by reacon of plant s hutd o.In , ncnoperation or anernsad c:: pense of cperation of otner equip:.. ant , or any special or ccncequential loss or damsga of any nature aricing cut of the construction or operation of the plant. m O 4lmmus* s I l I L l I l l 3
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. *i . 1 GL Ar* :1. I - ihek Charnen . Annis nme:nt .nd Cubcon t rac tin:r. .- A. Each Char:.es Eyci naall not be called upon to make any allo.;ancea for caterial, laber repairs, or alteratienc made fcr its account unless authorint by i- in writing.
- 3. A:sicncent Any c:sigar.ent by either B&W or Meted of this centract or any rights thereunder, without the prior written approval of the other, shall be void and not merely voidable.
C. Subcentracting (1) E&W shall advise Meted of the equipment proposed to be cubcontracted and tb.e namcc and locations of the ca.jor subcontractors. . (2) Before ESW places any subcontract for the equipment referenced-s- in paragraph (1) of this Section, Meted shall have the right to designate an alternate vendor or subcontractor. which tuat be acceptable to ESW lith re pact to the technical, delivery and contractual aspects of the cont.ract, provided Meted psyc B&W the amount, if any, by which the cost of the acquired equipment exceedc the cost of the equipment proposed to be selected by E&W. (3) 22H chall acaume as full responsibility to Meted for the acts or omi: Cions of its subcontractors as for the acts or c.c.iscien) of persons directly cmployed by B&W. e 9%
'a/, 1971
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The partiec recognize that certain construction permits, licenses
~
and other government authorizaticns will have-to be obtained from the AEC and other federal, state and loc al agencies. ELW shall cbtain all author'inatiens which are required to carry on work wnich will be performed in its own facilities. Meted shall be responsible for obtaining all authorizations for work at the
; plant site.
A. 3 AEC Licensing (1) XetEdandB&Wshallprovidesuchreasonableassistanceas
~
may be requested by either of the other parties in obtaining the necessa'ry AEC authorizations. , (2) ELW shall perform und provide the nuclear safety analyses , for its scope,of supply for the plant as required for Meted l to obtain and maintain ,an AEC construction permit and operating licence authorizing operation oI' the plant at the initial and additional ou,tput . levelc warranted in the plant centract and at 2535 MNt core power level; provided however i uhat this provision shall not obligate E&W to undertake any additional research and development'to justify the issuance or maintenanca of a license. insofar as cuch research and novelopment in' applicable colely for obtaining authorization to operate the plant above the additional output level warrantet in the plant contract. (3) ESW chgli preparc, for MotEd's review and approval, or assist in'the preparation of: ' (a) those cocticr.c of the . Safety Analysis Reports '.to be sub-mitted to-the AEC :hich relate to the EkW cecpe of supply
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NY! , 1. ':71 XI (A)(3)(b) (b) other reports, data deceriptions, drawincn and calculation: which relate to D&W-supplied equipment systems and services
,as may be reasonably requested by. Meted to obtain the 4
neccanary permits, licenses and approvals,for'the con-struction and operation of the plant at the initial and additional cutput levels warranted in the plant centract, and at 2535 MUt core power level; and (c) any reports which Meted is required to make to the AEC ! under the plant construction permit and operating license,
.:. . r -
to the extent that such report's req'uire information which is developed by B&W and relates to B&W scope of supply hereunder, and is not otherwise available to Meted s. vithout additional cost. Such report s shall be furnished by ESW without additional costs to Meted, if required prior to final acceptance as defined in Article VI (C) of the plant contract, and if required thercafter with respect to the cores, so long'as they are composed exclusively of fuel assemblies supplied hereunder. If required thereafter, the reports shall be furnished at -a charge which provides ELW with reasona' ole compensation for the services rendered.
-(4) EdW shall.furnich the services of sucn technical personnel' an ELW cnd Meted consider nccccsary-to make procentations +
at meetings anc hearings with the AEC.
-(5) _W ith the exception of the responsibilities accepted by E5U ,
under thic centract all coats incurred in obtainin(; AEC-Lauthorinations,. including'the reproduction of th'e preliminary I
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. a:u. rinh1 cafety analycic reports chall be the re:ponnibili .y of Meted.
- 3. :? ul1*.; r / Anprovaln h / Ot.hnr Gavarrr. ant A.ar.cies (1) OtEd and ELW nhall provide cuch rensc:.able acnistance c3 r.::./ be requested by either of the other parties in obtainir.G aut.norizations or approval from goverr=cr.tal agencies other than the AEC.
(2) All costs incurred in obtaining such authorizations shall be paid by the party responsible for obtaining the particular authorization. I e 1 l
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'J-
} ut,<.l.- e.c gn n t 1 *s i re:* s.1 7 <> r i to t i re <: t.1y by tnuclear renc t Lon, u nue.it:ttr radial.lon , or ' radioac tive cont.nmination, reculting. from i tic ialeril :; a l. t.lic p l a n t. cit.c, wiiether cont rol. led or uncontrolled. (2) For its own protection and for the protecticr. cf Meted, with respect to Article XII B(1) above, E&W at its sole expen:e, will secure and maintain in force (and shall cause its sub-contractors to secure and maintal.n in force), during the time f employees of B&W or its supplier.- or subcontracters are present at the plant site for or in connection with the perfor-
- mance of site work or. operations, policies of insurance of the'following types
- -
(a) Workmen's Compensation Insurance witin limits of liability
,, at leact as high as the statutory limits of liabilit:t in any state in which ESW may be required to pay ccmpen-cation; (b) Employers Liability *Incurance '.sith limits not 1csc than
$500,000 for each occurrence or diseace; (c) Comprehensive Automobile Liability Insurance including owned and non-owned automobiles operated by employees of U&W or its suppliers or subcontractors with bodily
, inijury limits of not lecc thr.n $100,000 ~ for each percen and not loca than $300,000 for each accident and with property damage limits.of not less than $100,000 per accid: A certa.ficate of cuch incurance must be filed: with and c.pproved , 4 by MetEci prior t.o eccmencement of said wort: or operation at qy the plant cite. i 9 y D* "*O .9'*_9,- ., . , , - . . . . . _ _ _ , _ . _ . ,.y,
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u s: : . : !* t'. :r : n. I n u osu s'u:~ .:e tinu .: L t.h h 2C r*::w );.t,;oc..;, nn. " ' ' * ' - ] o:cep:a:.i u tility prac tico, .:o long 0 3 the me",orlulu, c' ,it. Or.0, c'n i ae rvieu., to be l'or :i::hou he re unoc e .:hu l l b e >.t co u . (2) .ietEd in:lemnifiec unr1 hol<ic harmleccW. I:, Lt. cupplier; cnd 1
- c::bi:ont.rac teru 1:,;ainnt all touccc, <:la inc, . , mages or clia'ilitis' 1 :'i n i nt . out or or baned upon bodily in.Jt.r.v (including den th a t, ahy time reculting therei'rcm) and- lous of or damage to cny proper.ty located on or off th'e site whenever or wherever c:curri
'shon stue to the ne611gence of Meted, (includin.; ithor: 11:17 : '-
Iict E l' n .venta '.'nd employees) in the performance o; ch': uontra _ or in the opera tion of- the plant, or, regardless of negligence,
- nen reculting in v: hole or part uirec cly or indirec tly frc n.;elear reaction, nuclear radiation, or radioactive concamina tic
.'c':lt inc from incidento a t the cite, whether controlled cr no:ontrolled.
r.
.w (J) E: ept to the extent Meted in or uould be compenca ted by incor inec cocured uncler Articic XII A or L'y Mete.i'c other .
t.-;.icting i.ncurance coverage, ES:W indemnifiec and holds harm-1er:c MotEd ar 9 inct. all locucc, claims, ci.a ma c 2 3 or liabilities
- ri: in!. occ o!' or ba:te<l upon bodily in.lu ry (ir.cluding cen th 3 3 finy time recul ting I.he rcreom) and loca of or 'amare to properr" l
occurrin; prior 1.0 final act cptance, as de!'ine.i in Section VI C ct' l.hc pinnt contract, nnd due to the negli,ence of K :, inc
- .':ppl icPc or aut contrac t.orn, provided nuch bodi.ly in,i r.ry
(~nl ' :t- *eitti at any t i:t:e renult in:: theref rom) and locc of
~ ' c :- :amarc to croperty does not result fron: ce la r;ot 20.;ced in
ib.:. I'*i' A n l. i " t - Xfi - i t:<l. :ritt i tr., rul i n::n t imt e - A. :: t r. t (1) It is contemplated that MotEd, prior to the date of delivery cr fuel accomblicc to the plant sif.e ui.1L zcure c nd c.:ir.;c ir. so len;h as I?b! ha0 any respons'ibility under this contract, nuclear energy property incurance in an amount eq .:11 to the completed value of the project or equal to the maximum a cunt which can be secured through the insurance pools (!;EPIA and/cr MAERP,),...whicile.ver amount is lesser. Such insurance shall provide that Meted and thq insurance carrier, or carriers, univoanyandallrightsofrecoveryand['orsubrogationwhich they or any of them might have or acquire against ES:W, its suppliers and subcontractors. (2) Mated agrees that the material, equipment and/or services to be furnished hereunder shall not be used or operated in connection with a nuclear or atomic energy activity or f acilit; unle:n and until (a) Meted shall have entered into an agreement, of indemnific$. tion with the AEC, as provided under Section 170 of the Atomic Energy Act of 1994, an amended, and
~
(b) Meted chall'have obtained such policy or policios of incurance, or chall have provided financial protection of such type and in such amountc, as the AEC citall require as a coruillion of itu cntering into the indctnnity agreement referre+ to in (a) above. Meted.agrecc that BS:W, its supplier: and subcontractore, chall be included among the persons indemnifie-under '(a) above, and among the perconc protected under (b) above. Meted ncrocc to maintain auch inde:ctification agreemen and insurance or other financial protection, in full fcrce i
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t J,0 - t The price:; provided for hcroin arc exclusive of any prc ent or futtirc Federal. State, Municipal or other cale: or une tax :iti c .:.:p o e t to t::c material or equipment or services covered hereby,
. or arly other pretetit or future excice tax upon or concured by the crcan receipts fren thic transaction or any' allocated portion tnereof or by the grocc value of the materal or equipment ccvered hereby, and of any precent or future property tax or similar chargo with re0pcct to the matcrial or equipment covered hereby.
If Hit.! 10 required by applicable law or regulation to pay or collec; w:o auch tax cr taxes on account of this transaction or the caterisi er equipment or services covered hereby, then such amount of tax shall be paid by Meted in addition to the prices herein provided
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'A. h P..* c mil de ferid at its own er.perice an;/ cuit or action brought a".niti.;L i*etEd based on a clajm t. hat any individual piece of erpil .::e l r n:. or tu::; .:y::t.cm Tu rni::hed by IU?d he re un.hr r, conn t.ituter, in:*rl:.r,ement of an tq, para tun or ay::Lem claim or any pat,ent of the ;. - Unit.cd Staten, and B&W shall also pay all cocts and dan: ages awarded therein against MotEd. In case any cuch B&W furnished ec.:ipment or system, or any part thereof, is held to constitute infringemen ,l i and its use is enjoined, B&W promptly shall, at its own expense, 4
either procure for Meted the right to continue using the equipment
.or systems, or replace the same with non-infringing equipmen't ci" ' ~
3:/ tem;, or modify it so it becomes non-infringing. Where MetId has Gi ven written instructions to B&W which direct (1) a specified
. manner of performance of the contract or (2) a specific design or 4
4
, arrc:: cement of the equipment or a part or parts thereof to be 4 fur:;iuned hereunder, other than a manner of performance, design
- cr arrangement, propoced by B&W, Meted shall defend at its own i
e.: pence any uuit or action banc:: on a claim thac the. equipment or a part thereof furniched hereunder conctitutes infringement of a [ United Sta(es patent, where such infringement results from such written inntructions, and Meted shall also pay all costs and car::w;os aunrded Li.orcin against B&W. . B. i;enher I:ctEd nor 1%W nhall have the right to claim indemnity under Lnia . para;;rapu unlacs prompt notice of the ascertion of any claim. l-for which i:ide::nity is cout;ht la given in writing and' unless the
- p a r t,. ucci.izi, incer
- .nity~cauen available to the other party all other nor:di information,. a:sistan c, and authority it poscesccc
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- E U J' L!80 fl*Jl*tJf t.7(r ol* 3f37 :Ull OT prOCCOding in Which OUCH C1a.4... 4ao OO!'OTLOd, a
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-oj-A:- :.: :: / - A ri i t.rtt . I fc.n J1i . ; <:en t.: ave ray o r eini m ( er.c op t, any claim for <1arar;rf.ca t.ccav::o of im .
- l 1::.j u rluu , inclutlinfj; deat.!t at any time recultine, i.riorefrc:n,
.;i- ::i:teri b.y a: . percon or Persons > and c;. cept anJ- claim for dam:n S3 -
Lee: u:;o of irijurie:.5 to or dectruction of property) cricing cut of cr rol::,t.ing, t.o t, hic contrac t or the breach t!creof. ci:all be ue; t. led by arbitration in accordance with the Arbitration Rules of the American Arbitration Association. I 4 e 4 e we - ..e. e
.41/, I?'71
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- 4ctEu :;i:all notify B&t! irmediately, by Registered Mail addressed to EhW at 161 East 42nd Strcot, New York, of all claims brought against Meted for uhich S&W may be liable, and E&W shall notify
- etEd 1.T.T.ediately by P.egistered Mail addressed to Meted at Readin.5, Pennsylvania, of all claims brought against E&W for which Meted may be liable.
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(, r, .. \ fittitle ::*/ l 1 - C. n cl: ! I a t ir.n v it.' t Ed . In th; event !%'; Ed can:c!: the plant contrcet,' l'et Ed mc/ c mcci this c n:.ac: e<ecn writ:c, actict. and upon pa/:::2. t to 80.1 of re w. eb t e . :.1 ;:ce; sis- cancallotica chtrees. S:;ch charges ha!I i nc ! .J.: direc- labor and :.'a tcr ial c::n,enscs ; vendar conct i l --ion charpes ; rec;u it.i t ion en.;it:ccring cnd cref ting c>,>cnse , ba s.n' on the
~
.).n.catsiic of com.,1 stlen ci the engineering sad draf t ing t c.rk:
(icseln..ent .wir cerire s:ac!cliy it.cus red for the . ccricel l.d order
'inci.nting speci..i tcois, dics, fixtures and pctterns; and >!1 cQer eire:t .;;.J :a:I u-:; cc: 1+ ; rorer ly a l incti,l .: or opreartiomiie to
- ..e ..ib uni .c W"c s1.:. .derd accr.u .;Ita; pract !ce, and prcii t en the r;. p ricer.ced.
. lie: Ed sr'Jil 5:: .:n:l t !c3 to cl l ' t..ger ia l
.. i .-l iy r..
( cr :lct'ed for tne orJcr a:'d in:lt::!ed in the n'x..e c:earscs ;
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*.. ;n:n s e , v , ct i t s opi i ,n . t he ;;il v;.g o va l:.:e the ec' '
s!all
. di :. . t . ' f rec :..: cen:clictic.$ thrrSes. t!c t Ed n:", et !:s
< ; i -, vs . . .. u . t.e . e ; f i r:.. o f i nt.: t,cn:!:r. t : :..:..an taa t s c ..- da c :
im i... r:nd.:n er - - ic: ?;s .
.6 ce rLii'y !.h t t ?. . : :. : q,: > c ee !~
- c : v. wi th :aanda rd 12.1 pr<a c t i c.: .
Such fin: h.!! bc Lise it : . nj e: 1 ,. r.c r. t er n r - iW/ a: t.hc i.i::n een 1::.+ riit t Ed s b.. I ! i n e r . i f a i t.1: .:nri for re .w.b i c c cti v ot',i.:t.t te r.t ch occ .i.u.' .a t s . in =h i ..' c..c e s us.i. I ndei*e:. den t ::ccodo' .n t s sha ll he a f i rr i, . .L i l / ~ ~ c.c. nT 1 . I C 10 C? and !!v. L'- . It: : hl , b. 1 I h.'. v e the -lgi.6 , tri t la r t:Sp.tc t. Le ciih(r t u e :.*:c e n i i .. , . 6 ba t ch , c.r 1.1,th th. f i r . i cand 3,.:c.ind rc i n:ri b::t ches , to to: i te thi eratre.ct 2: r.ir t f or cause- ( . . : . , s ite ce s.o r r cou-r,f ~ . c h. . ir :1 - f:,i irre ..: t.. t h .r. :'!" ici t h.. f u.e ! 0.. < c:..b 1 1 : - in t ., .. , :.1 c 4.i. ..i c r .a: lor . t a p: eu.. . s .-
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( desica :..crgy set forth in .4.et.cndix A or failure to r.ec: delivery schedu!cs , due to cace:s not ercuir.ble unde:r this en , t ..c t , hf a r i: ; 4. per ie.d o f r cre r;un fe,ur . .:h s.) . Such partiei.t m..:notica for caus sh al I
- r. qui re uri t c, not ice f n i P.c: E :t ::s ?stl. 3 cc no:i;e :Sai1 obl ip i.e !!c: Ed te pay' recs.'nable and pro cr c.nc.:!l.'.ica char,;.:e. f c.q such p, ret ial ter.:!na: ion rec.9nct ing such relca:i ha ts. c.- bat e:i.cs in the s / t manner tri th respect' to the terctincted pa t t.s ott linc 4 a!cv6 4
fo r cc p l e t c r..v:c u l i c t i on ; p. c. ri d ed , !.c,ue ve r , that :.c ;: char": . fo - pc.-tiil :cr:nin;:le , for ccuse shall not include cny indirect costs et t h:.n it :f i rc :t c :n . 2 t.h i cin , in cc.brc:ce.cu t:i :h i: \.'s :.v.! s c ind ::ct:vi.t i)
- .ys ici.:, c::n s i , t a.i c i, cpp l i .5:i, .,.e assicr.cd i.s a r.e. : uf itsk r sir..p c et r.n J s n .t I nr.t ine : vde ai.y T.. :.: i t . Upon such tr -; ; ; en, :; .. p . : ! u sha1i r.. t.. ::,; i ,' ..,ved this co..:.cet, r,s se.; ; I as :h;; ;i.:.s ct.n ri.c t . :c ref :. . . l.e ..r t ... :. of su:h : .rriino icn t.gr,.i t he r i:.
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* - i - te 'TIII - Contrac t. Ch:'nec:, nmi E:'ce, Wo r1:
The tur::tu of I hi:: contrac t .: ball not br: c har agod , cuport.c<;rr, eor at:ppix.cnted c::copt by written contrac t change orde <;uly
;. : 0 .' ,a.i by on officer or an:/ doctrinated recrecent:ative of I:.at2.. nnd by an officer or any decl3nated reprecent:1tive of 2.':h. !!o ultim for extra cou tpment, system: or servico: Chall k
b0 V111d unic;;a attthorir.cel' by a written concrae t c. ance order duly executed by an officer or any decignate i recrecentati of I.ietEd and by an authorized officer or any designatec reprocentative of E&U. 4 4 G
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E3Y 127i t59
. A r t a c h /:TX - A.!=inin t. ration of Con t rac t i4ctSd chall desicnate, in writing, a Three i:lle Icland praject mana.,;er, and EMI shall decignate, in writinC, a project mar.scer tc administer this contract. Any aesignation.2 no n.ade may be char.ged by written notice and individuals may be designat2d t.c ac t ir tne absence of cither of the desi 6nces. Subject to the pro /isions of Art.iclo XVIII, the individuals so designated shall have respcasi-bility and authority on behalf of their respective' principals to administer operations under this contract, to formalize ar.d agree upcn contract procedure, to handle disputes,'to receive notices, and to do all things necessary to' carry out the contract work.'
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L.:w Thl:: eun t,r:2c t clia l l ch:tl1 bc be slee:aets t.o be conctrued in a Fenr.cylvania and cc:=on law of accordance c or. t he com r.onwealthwi th, and go y of Pennsylv atic . o 9 9 0 b
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is vs .. t . 7.:'.X - Uni vo r:; Tine riti. lure of McLErl t.o enforce at. any time any of the pro /isicr.3 c: thin contrac t, or 1.o regilire at any time performance by Eid a; :u;y t. the proviciati:1 h e r r; o r g ::holl in no '.tay be construed to be a waiver of cuch provicion, nor in any way to affect the v:lidity of thic contract or:2ny part thereof, or the rig.tr. c:_
/.e tEd Lc th3reafter enforce cach and every e.uch provicicn.
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/s r: icl e- VXII - Tutmtration With respec t to the cub ject ma tter hereof, thic contract cuper-sedes all previous ieproceritationc, unders tandings and netotiatic.;
cit.ber written or oral, between the parties here'to or their reprocentativen, and constitutcu the entire contract between the particc. IN HITI!ESS WiiEREOF, Meted and B&W have caused this' contract to be execute'd in duplicate by their duly authoriced representatives tc be effective as of the day and year hereinabove first mentioned. METROPOLITAN EDISON 00MPAIG By /s/ J. G. Miller . Vice President and
-- Title chief Encineer (SEAL) s.
Date June 2, 1971 A t to c i, : /s/ U. D. Eollin cer *
. THE BABCOCK tc WILCOX coy?AXY Dy * /s/ Danald A. Minner Title R;r. Plan. & ca=. (SEAL)
Date May 21. 1971 is; tc: 1. : /:/ ihvid P.. Broun l l s' .. i 1 1
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CC:: Tit'.CT TOIL ::UCITAR FI'::L A!!D I:0U::"* .':T
. A::C: 0:- O T ::0. 1 This A=cnd cnt No.' 1 amends the Contract for ::ucicar Feel (Cont:act) cntered into between Metropolitan Edison Cc=pany ( :ct-Ed) cnd The Scbcoch a Uiley: Cc:pany (31%) dated effective November 15,19%, to reficct the effect:, of a ch nge in the origin of supply of the prinary coolant pumps for Threc Mile Island Nuclecr Station Unit ?!o . 1.
The Ccatract, Article V-A(3)(a) second and third sentences are herchy a:cnded to rend as follevs:
".. .E:: cept for li=itations which cust be 1:f:poced incident t'o the use of Ucstinghouse primary coolant pumps (because the said pumps do not
' provide the flow and head pc'r formance equivalent to 88,000 gpa and 371 f cet), the operating instructions shall not impose .upon the plant operation li itations core restrici-ive than"the operati:ig
~
, licitations set forth in Table 1S of Appendix A and shall not pre-vent operatica at a core-power level of 2535 E!t. Simi]arly, c:ccept f or liuitations which cust be imposed incident to the use 'of I.'estint; house pricary coolant pu=ps (because the said pumps do not provide the ficw and head performance equivalent to 30,000 gpa and 371 f ect), such operating instructions shall not restrict or preclude
, plant naneuvarr.bility as described in Appendix A. . ." .--
- i. .
. !!E,TROPOLITAN EDISONcbOMPANY i
Y='.h f *' 7 ; j, . BY
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nATc JUN 2 19../t
- THE-DABCOCl* & UILCOX COMPANY J
B\'A._%.sn*:*1f.t/..-,;:
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w.. y u I ATTET: 'Ji/Y(vM TITLE thr. , Cc= r. :: cin! & P1,nn1: ,-
- DATE April 30, 19*,'l i
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['. g .i:; i (v. . . - i :,. i .- .s.. TIIREF. ::II.E ISU. :9 NO. 1 (. . CONTDACT FOP. NUCT. EAR Fl'EL AND EO'{IP}!-':T IlIE::D:IC::T : 0. 2 This Amendment No. 2 a:cnds the Contract f~cr Nuc1 car FEcl *(Con +.rcet) cntered into between !!stropoliten Edison Cenpany (Mat-Ed) cnd The Ecbcock 1 tilce:' Ccapany (0.'.*O dated ef f ective No.* caber 15, 1906, to reflect the effc..ts of a chan;;e in tha' origin of supply of the princry coolant },u Ps i for Three Mile Is1:nd Nuclear Station Unit No. 1.
- The Contract, Ar
- ic1c.XVIII las't sentence, is hereby ar.cnded to read ,
as fo11cus:
"!!cuover, ET*.J clai=s for c :tra equip:.cnt syste:as and services shall ,
be valid when authori:cd by a uritten purchase docu=ent .
- c:::cuted by an officer or any designated. represcatat'ive of MENEd
-(including an cuthorized Purchasing Agent) ." .
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METROPOLITAN EDISON CO):PA'.T
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c 6dl.IC , TITLE Yice Pratiden' a.- t c'i:g e n -in .- DATE Jbiii82 .o 4 mL! i .. Ti1Ed:ABCOCI; & UILCQX.-CCliP5:G' ' V j .q y '
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. DATE Auril 30, 1971 t
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TFiiEE ITILE ISLAllD I!O. 1 l i CO!! TRACT FOR ::UCLEAR .%~EL AI!D EDUIEi'E !? 7 a- - , ru.- :m_,4.gu.m
- .. . .t.io . .a TJ.is Amend:ent Ho. 3 amends the Contract for liuclear Fuel (Con ract) entered into bettleen Metropolitan Edison Compan; i
(I:et Ed) and The Sabcock & Wilcox Company '(EFel) dated effective Novem~ce r 15, 1966, to add pre-pressurization to the fuel red deceription and to reflect the effects of-a change in fuel enrich-ment and dancity on:
- 1. Fuel Burn-up Data.
- 2. Eatch and Cycle Energy Outpue.
~.; Quantities of Enriched Uranium T:et Ed must provide
, 3i:! as U?f.
Quantities of Uranium as UOo contained in the fuel assea'clies supplied to Met Ed by ESi. l Qucntities'of Uranium and Plutonium Remaining in
- the Spent Fuel at the End of' Life.
- T::e Contract is herei>y amendod ac follouc: ,
i Pages Dated
- Pacc - t-!ay , 1971
- M1.e:ted Sul ct' tutad
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I P a,$es Dar.e'l ! Pa :::2 D:ay , 1971' g-21; r.:.d Sub s ti tute<1 I::3 NO 47 47 Ap;:andi:: 3 AppeneIlx E ETROPOLITAN EDIC0H CO??A If 4 By /s/ J. G. Millee Vice President and . Title Chief Encineer (SEAL) Date June 2. 1971
.. a. .
i /,/ ". 3. Mollinger THE BAECOCK 2: WILCOX CO:GANY By /s/ Donalti A. Minner Title M r. Plan. & Cem . (SEAL) Date May 21. lo71 Att.at:
/a/ T:2vid R. 3rown I
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. A r . i l _ \* ruel '.hrrantie:
A. Pcrf reance 'iarrant (1) 1hrrant'> i 3.'i.i warrants that the initial core and the t':o reload i batches consisting of a total of 294 fuel ascemblies: 1 I.
, . (a) shall be capable of .croducing a total of not less than 292.9 trillions of Eritish Thermal Units (Etu) .' without necessity for operation of.the reactor beyond depletion of-reactivity of any reactor loading.-
]' .. . __ ._.__.. _____ . containing any of such fuel assemblies, withou; ]' necessity for operation of the reactor at conditions j more restrictive than the operating limitations 4-stated in Table 18 of Appendi:c A and without necessity for restricting the plant's. maneuverability . i described in Appendix A; (b) will contain, when discharged from.the reactor-(upon the succes0ive events of depletion of reactivity) [ not lacs than 131,534 kilograms of uranium, hav'ir.s l a weighted average ascay of not loss than 0.93% of
! Uranium-235 and not less than 659 kilograms of a
4 l Plutonium-239 and Plutenium-241; (c) will recuire that Meted provide not more than: 1 l Kilogrcr.s or Enrici_te::: i enricned U as 9 U-235-l UFA (wed .'h t ori nters-e' ror the initial core ccncintin.3 of 177 l fdel ac::d:..tlies 34,600 2.6,2 , For the fir t reload i bater. conciatin:; of 56 . fuel assemblies ,26,706 3.22 For ti:c seccnd rcicad baten fnel a::cm'.: con:1stin. lie::, of 61
- 29.,153. , 7 2. EO.
V A(1)(d)- May, 1971* (d) will contain, upon delivery, not more than the follmiin;; quantitics of Meted supplied uranitun and having, in 4 i each case, an assay in such Meted cupplied uranium cf not less than the weighted average ascay supplied by Meted as UF6 Kilograms of U as UC2 For the initial core consistin5
, of 177 fuel assemblies _
82,473. For the first reload batch' consisting of 56 fuel assemblies , 26,093 For the second reload batch con isting of 61 fuel assembli.es 20,423 (e) will result in the return of manufacturing scrap in the form set out in Articles II A(1) (a) and II C, as apprc-priate, and/or overage quantities of not less than: Kilograms of U at an assay not less than the weighted average asca; supnlied by MccEd For the initial core concluLino of 177 fuel assemblies 1152 + J For the first relcad batch consisting
-of.56 fuel assemblies 364'+ K For the cocond reload batch con 13 ting of 61 fuel assemblies 39T'+ L' unero si,- K, and L are tile extents to which the maximum con ,cnt of MetEti supplied uranium warrantea in (d) above exceed-the
.:c;n of the actual cuantitics of~ Meted sup,611cd uranium con: ined.'
in tne rocpcetive core and batches as measured and certifice by Eid.i at the ti=o cf preparation for chipment. l 1 l s -1 l L _. _ _ _ _ __ j
V A(0)(f) May, 1971* performance by Meted hereunder. The warranties in Articles V'A(1)(a) and (b) shall be adjusted, after the final with-
.drawal of enriched uranium. hereunder for the second reload
. batch, to the extent necessary to reflect the actual weighted average assay of the uranium withdraun.by 2F4 from the USAEC-enrichment. plant.
(g) The warranties in Articles V A(1)(a) and (b) shall-be appropriately'adjustedi.to~the extent that'the uranium quantities actually loaded into the first core and first and second reload batches vary not more than + 0.5% frc= the nominal loading of Kilograms of U specified belo..':
' Nominal Kilograms
. of U as UUp For the initial core consisting of 177~ fuel assemblies 82,063 For the first reload batch consisting of 56 fuel assemblies. 25,963 For the second reload batch cond'isting of 61 fuel assemblies 28,282 (h) The warranted quantities in Article V A(1)(e) shall be adjusted to the extent necessary to reflect.the differences between the quantities withdrawn by E&W hereunder:and the quantities requested from the U0AEC .
(3) Ccnditions of Performance Warranty LYd's performance warranties are subject to'the following ccncitions: (a) The equipmsnt and materials shall be operated, tested, maintaineo und prctected frca damaging agents by "etEd in
- accordsnce with generally approved practices and with all
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.!!! CORE DETECTOR - LOC ATI ONS
T l $ 3 l' ELCCTRIC AL 2*.00 SEAL PSI.\ / CCiviECTOA i ,/
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APPEN0lX_0 Fuc t Del ivery Schet' . l e Scheduled Saip. rant Da:c ( ',5 i :-e:. c.i
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1 2.06 26,766 . C< c.'.= 1 2 !- 3 till shi,. Trem 2 ?.72 29,156 licrch li,. 1971 June 15, 1 72 to I:t c e.! a r I ', , i .;7 : 3 3.c, 23,673 4 3.2? 26,766 Five vtn:hs prior Arril 1, 1:75 to Sche 0.:ed Shi;'- ir.cr. t 0 0 . _ , as cd-J t::t::d ptirt.ucnt to Sectica Iii C (2). 5 7 . 'i l 2'), I f 6 Five n. :in priur Apri1 , 1 : .' '-
. to Sc4 d I n c4 f.h;p-
- e n t D.9, as cd-j t!.4 '. Ct! ; i t i r ! i t. -
- Sc.ct i r n ::i C (2).
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- r nf .... .elivery i: i idicLit . Cel c i l e ' 9 ~ ve ry r.. '. le '- ,
; c> is . .: r ^c e o e.r Ed ::ot I c. t e r t he r. E r.;on t hs. p; i c e to Sct.c.'. led ': . -tit if 0 ; e .
O e e 8 G s 9
..cb rir.: ry 3,).,
r .L ,j,e 5 TO: :/r E. H. Chcrry j i sui'J1'n - I*oti:1 cation l'.'.te for Chirnent of Fabricated Pue: .
/- For T::1-1, ".':;t-2 und Forhc.J River- 1
( . , . REFE".7:22 : : .o frem J. D. It:c=a to B. !! Che: y - Dated A;:ril 17, Igrl3, on sa:.e sub.r,-t, Th2 foll:..:ini; schedules super:cdc tiaore niven in the re: renedd me:?.a.
-A i.:entienu.1, these i.atcc Ocfine pa: ment scheadea to be uct : to ttinf:- the vari:.:c: era frbric'. tion contract they ray n ;t nececce rD y c . re. poad to t.he ac tt:a1 chip..:nt period:
'DiB " current thinking" de.tas are ba:ed en GFU Te rcer t . . - !hten in effect today. '!.:e dcadline date corresponds to that cay be.',;_ e .;hicit Clii met conta::'; the vendor if it is desired to change 2.c Final Eni;r:ent Contract .hte.
Each contract pecifies the r.ay.i:m::: period of tiac c Ccatract Date c.ay be shifted. Reactor Care: Final Ship ent Final Ship- .en , Current i!atifi-( S t .r t-o ; - ~ l e )_ Centract Date Carrent 'Thir.':in~ cation Nadline T_; 7 . Rdcaa 1 (11j'1/76) 14 / 1 / 7 5 '.0/i ' ! f 9/1/76 h/1/74 M . J v- 3 (~.1/1/77) h/1/ 6 .* 9/1/77 'E6/1/75
. .,..-a.
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k Iur,.1:o core (10/1/76) 3/1/75 - 9/1/75 *//1/75 - 1/!/76 No rore dater: fre.i Contract Date t:ithcut a penul'.; nelc21 1 (!:/1/7S) 10/1/77 2/1/73 10/1/76 - n:a eno 3 (:/1/79) 10/1/78 2/1/79 10/1/77 I Forhed " r<r-2: 1:....r1 Core (1/1/79), I!cne 10/1/77 - J./J /70 7/1/76 B ! v*e) 1.(U/1/80) !!one 2/1/80- h/1/79 i' . 2
'?(4/1/31) 1:an2 2/1/81 5/1./80
' 'l na 3 (!>/1/82) I:ene 2/1/62 5/1/31 t
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's ,,, {'Vf1 APPEi!D F:: C INFORMATION FOR PRC':UREMENT OF FUEL The following information will be made availah te to Meted if it
.has not already been made availabte to Meted in the course of fulfillment of the plant and fuel contract obligations:
A. Plant & Nuclear Data L. Reactor nuclear, hydraulic , and thermal data at license conditions, including basic assumptionn used in design. 1
- 2. Original isotopic composition of fuel on loaded into J
\
present core and anticipated reloads prior to loading ( , of batch #6. J Initial total mass of uranium per assemoly. ' l
- 4. Fuc1 clad materials, volu:neu, and masse ~,.
- 5. Coolant volumes.
o. Control rod location, materials and structure. 7 Burnable poison location, composition, Ind masses. , i C. ifature of side and end reflec. tors. I 9 Fuel pelict diaceter, densLt,y, and shape .
'1 0 .
Coolant chemictry with operating limite of pH, O,H) g 2 k, - Cl, and total solids required.
..}
A/, l'N1
.. e m.:1:. C I:.r e .acica roc Procuremenn of Fuc1 s
- 11. Fu'l dcccriptions of mater i alc expo:.cd o p riniar;/ coolant (preocurc veccel, core cuppcrts, control rodo, pip ing, primary coolant pumps, val ves including coa t materials ) .
- 12. In-core instrumentation and lead locations.
13 Location of in-vessel instruments, including thermacouples. B. Puel Accemb1v Materials 1 Faterials list of all materials required and pertinent 4.3T?! specifications, as app ropriate.
- 2. Specifications for fuel pellets and assembly ccmponents s
including claddin,g and grid spacers. Pequirements for curface preparation and/or heat treatment
.:ncro they are escen Llal'n .ael assembly performance.
- 4. Utandards appropriate to acceptable cleanliness.
C. !>c. ; . ., . 2: Cuecification l ' l Fuel rod, end fittingc, grid, guide and instrument tubc l i and ac;;encly; and completed acccmbly including fuel envelope d2=cncions and tolerancoc; also, chock loading and vibratien
'!acign i,cadc for acccmblies and trancaics ion of loads, and
- ther lcnds cuch ac decalera .lon forces and' torques frba s
drivc0 and control roda.
? Scurce red and fittin;,0.
..-. ... - - - - - -- --' ~ ' ~ '
.1 e.y , l') /1 2
l
.. .. : : s *:
.~
; <. : ,,,wa r,i on ro, Pr ocurem<:nt. o r Fuc t gs 3 Equipment used in fuel han 11ing which mater, with the fuel acccmbly (including specification for wade and deflections i.
- l. which result frcm their us,-).
e.
- 4. Reactor internals ' which af rect the pas i t icoing and support
$ of fuel assemblies; i.~e., grid plates, core barrel, e tc .' 5;. Control rod assembly includ ing dimensionn and t. ole rances . 3
- 6. Orifice plug assemblies including matching dimensions and tolerances.
D. Core Thermal Hydraulics Information i J j -
., 1. Pressure drop characteristics _(flow rate vs P) of the fuel *
[ assemblies remaining in the core, i
~
- 2. Flow areas within re: raining Pucl acceablies. Total coolant
; flow area in the core as weli as coolant. Ilou arean.through
- thermal shields, ' entrance anit exit plenumn.
E. Accident Analysis i. Coolant pumps flow coact-down characteristics ac cupplied
- by pump manufacturer.
2. Delay time between initiation of scram and control rod motion.- 3 Control' rod' drop velocity. ' t
- ., l.
! Xaximum rod *aithdrawal:cpeed.
- j. 3: Heactor setpoints and instrucent errors.
t i *
$-*< v v w D,wg-iy -?==-'y F '*W w 41 A- % gr +W -
(g W ' w i *
.- :27 , t (1-1 2.1.1 Fuel Rod A fuel rod consists of fuel pelletc, the clad, fuel cupport componente, and end caps. The fuel pellets.are in the form of sintered and ground pellets of low enriched uranium dioxide. Pellet ends are dished to minimice differential thermal expansion between the fuel and the cladding. The nominal density of .the fuel is 92'.55 of the . theoretical density.
The pellets are clad in Zircaloy 4 tubing and sealed by Zircaloy-4 end caps. The fuel rods are then pre-pressuriced. Design average burnup of the fuel is 31,,700 mwd /MTU with a peak design burnup of 55,000 mwd /MTU. At the design peak burnup, the fuel growth is calculated to be 9-1/2 volume percent. Radial grcuth of the fuel during burnup is accommodated by s pallec porosity, radial clearance between the pellets and the cladding , and by a small amount of permanent strain in the cl2dding. Calculated peak turnup of the fuel ic 42,000 mud /MTU. Below each fuel column is a thin-wall stainlecs steel spacer which axially locates the bottom of the fuel column and separates the fuel from the lower fuel rod end cap. This pedestal is designed to collapse at a predetermined column load i to prevent oncecsive axial atrain in the cladding. Abov,e the fuel column ic a thin-wall stainlecs steel upacer tube that separates the fuel from the fuel rod upper end l l cap. This spacer maintains the fuel' column in place during-l 7 chippin,g and handling. In operation, _ the~cpacer permits axia]
, . differential drowth and thermal expansion between the fuel and x .
I i
+
-2
= * * , * = , .A g
- pc=o g a 9 , 6 y +t-
.%y, l' :'l 1 -
Table 3 Nuclear Desian Data F al Assembly llolume Fractions
- v. .-..u, o.u90 2
- ::cdcrator 0.580 Zircaloy 0.102 Stainless Steel - 0.003 -
Void 0.012 1.000
' ~
Tc al UOg (30L, First Core)'
- n ric Tons 93 1 cc e Sin nciens, in.
. 2lui'falent Diameter 128.9
..ati/e F.eight 144.0 Ur.i t C;11 He0 to U Atomic Ratio g;'ul1 ACC0mely)
Gcid , 2.85 Hot - 2.04 F 211-F o mr Lifetime , Days. First Cycle (at 2335-relt core oower) 506 Each Succeeding Cycle (at 2452 core power) 325 7 >:1 Irrceildtion, '? 'D/tITU Firct C:/,cle Average (at 2335 tc!t core noter) 14,400 Cucceeding Cycle Averago '(at 24 22 I.T.It core 9,700 p o'.!c P ) Fuel Loadir. , .7:t5 U-235 2;r.e 1/ Zone 2/Zene 3 2.06/2.72/3.03 L (Core A/erage First Cycle) (2.62)
~ - - ._ . _
~ .. .-- . . .
i.:a y , 71 i ' TV&' a' 3* (Cont'd) 5, 0,?ntrol Mea e Control Ecd Material
- As-In-Cd
-
- ur.ber cf Full Length CRA's
. ~ 61 ~
'icrth of 61 Full Length CRA's n , i.. v
\D t./ 1% )}2 10.6
, Control Rod Cladding Material Ty.oe.304 SS,
. cold-worked 3
- f.v-=ra. a
- :r? ron Flu:- Levels at 2568 Mit (n/en2-s --
Therr.al (O to 1.855 ev) ! - , , . 0.5 x 1014 I 'I 2.5 x 1014 - 0 N
- 4 4
1 1-i k - i i
- i 4
I . t t
.g.
l 4 t 1 1 1
+
r
- _ ,---.m^
1 l l i h 'i s 1:IT l
- m. .r n. r.. . =. h m ,. r . ..m
.. .: r. v. c. o r.n.'0 ". r... .: 1
. . . in. .m.r.o.
s .T. ..ar .", , .A I.T D II..'?. .".", TO '." 4 . t I 4
- T" ". i.ATERIAL DIt1ENSIO!!S (inehec )
Fuel N110t UO (Sintered, 2 0.370 0.D'.
~
. Ground & Diched) .
92.55; Theoretical Dencity 1.7% dish volume. 1 l Fue1 Clad *~ ,- Zircaloy-4 0.430 0 D. 1 Cold-Worked 0.377 I.D. . 153 125 Fue1 Rcd T1tch_ .__.........- ....--ai '% $6 8 - Fuel Accambly Pitch 8.587 Actitc Fuel Length 144 -- - 1 0 Ier .11 Fue.1 /..:c ombly Length 165.625 Contral Ec;. Guide Tube Circalcy-4 0 530 0.D. . i i s. 0.498 I.D.
.Inc t ru:. .+ r.' .U:.'.cn Tub e Zircaloy-4 0.493 0.D. -
1 0.441 I.D. j Cpacer Griu: (3) Inconel-718 Strips ' 0.016 thich 6 Intermediate Grids 1.440 high - i 2 End Grids 2.880 high 15 5-lb/accembly [ End Fittin.7 Stainlecc Steel,304 l l Fi::e i cn G'.:: Plenum " Top t
- Bottom 5.$-
i Yi.; Tuc1 claddin~ 10 to be frve standing at.. design prescur . on a 'shor*; t '.::7.- :. a u ', 0 ac'approxicatel:t 7"5cF. i:ot spot temperature av. raged l- ti;r n y che clad-. tall.- This is the octimated hot cootf tennerature' l a t'. 2 l '. 4. p c :o r c o nd i t ion . s-l l .: _ t .'; -
. ,c. ,..- < ._,_. -- ~, - a-- ,-. .- .-~- .-.- - --~~~--- ~~- -.
4 i
'h:/
. , 1971* l I
J l I TABLE 14' Fuel Cycle Length Reactor Full, Power Capacity Calendar CIcle - Power Days Factor Davs-1 '2335. 506* o.88 544 2 - 2452 325 0.85 382 3 2452 325 0.85 382 a 2452 325 0.85 382 5 2h52 325 0.85- 382 $ 6 2452 .325 0.85 382 i
'27 ./PD are consumed . in startup period; 479 days-@ o.85 C.F.
"folicuir.; commercial' operation Eives calendar days.
1 9 e t t ht-
, , - , , ,, 5' [ -- r v -
n T y - -- "- f f -
4 TABLE 15 Fuel Mass and Enrichment Data
' ~~ "-"
Installed Removed'hs Scent Fuel' Weight of Pu Estch Weight Enrichment Weight Enrichment Kg of Pu-239
?:u:rb2r Ke of U d U-2?5 Kg of U 5 U-235 and Pu-2h1 1 25,964 2.06 25,297 .'910 133 2 . ) 2 23,292 2.72 27,304 0.911 179.5 3 97,813 3 05 26,768 o.945 186.8 14 25 464 3 22 ,,
24,968 0.905 175.2 5 25,282 2.91 '<t ,197 0.978 184.3 4 h5- .
..y.-- ... ._........ .. .. .
i+r/, l'f/1 -
~
TABLE 16 Fuel Burnuo Data No. of Batch Average Average Eurnu.o htch As se.e.blies Burnuo (ICID/MTU) - (iG?D/hiTU) . 1 56 15,848 I 2 61 25,900 2 60 30,093 ) 26,257 i 56 31,668 5 61 27,428 i . s G G
. :;f
i;;1:: , L
- 7 '.
*e TABLE 17 Eatch and Cycle Energy Output (Trillions of Btu -'1012). ,
Cycles Batch 1 2 3 4 5 Total 1 33.70 33 7 s. 2 38.99 20.99 59.9 23.91 23.23 21.41 6S.5 20.75 25.64, 20.96. '67.3 5 17.93 24.71 20.88 63.5 Tonal 'h: . 60 64.97 6'4.98 45.67 20.88 292.9 a s e 8'*
. k'
i%y , 1*.* ? !. 1 APPE! DIX E Fuel Delivery Schedule Chicment Of
- 30. t i: . Enrichmen: P.2q'd. Delivery of Asse'blies m by El I.M . G U-235 Kg U as UF6 E".riched UF6 to B&d, On or Eefere a
1 2.06" 26,766 B2tches 1,2, - 2: 3 will ship frce' 2 2.72 29,156 March 15, 1971* June 15, 1971 to December 15, i 3 '. 3. 05 . 58,678' _ 1971
- 4 3 22 . . ' 24,.766 Hay 1, 1973*L october 1, 1973
~
5 2.91 .: 2's,7136 May 15, 1974* October 15; 197-The quantity, enrichment and delivery schedules for j , r3 placement fuel assemblies will be specified by Eid!.
.* 02te of first delivery is shown. Detailed delivery-schedules will be forwarded not later than 8' months 1 '
- prior to the dates shown.
?
h
. m i
9 b
^l
'\
4 T
%.m I *g / '
r h i 4
.l .
l > i c, c -
~ *
, f.
-r . , s , , , . .-,,,w.a ,
i _T!!?FC f!!LC l ~l /it!!! t!? I '
. Cot:VnA'.i V')r, :: !CL E!.it F*JCL t.*:0 01'JI Er'T O*:
1 A!2t!D:'i::T 1:0. !< This A nondswnt flo. 4 amends the Co'n tree t entered into hetuccn l'.et ro;c.litan Edi On Corp for n tiuclear Fuct (Centrect) t!i l cria C;;m::any (..t*,1)
. .: y ((!c - - t Cd) .an-J T:)e- Bchcoch t.
dat ed r.f fcct ive fiosem ce 15, 1966, to rc.:e ,: . reic1dtsarchet, price of i to climinate cancelictio.i for convenicnce ,
. p r e.-!:, ion fer reload batch 's as defic.::d in Article XVil and to .
for relci,3 bttches. p rov i de fo r ::c<e fuel s h i p.. .a n t da:cs The C.,n:roct is F<:rcLy cmcr der; . as fol lo.,:,:
. . s.
~
P8 0 - . . . .Papes 04:cd YL.'.5'i.'-9. Aprl! Ic72 r-o . Sub< t_i t.c t cQ
- 22 C
(' 27 2h 2 f., . 27 e*)- . 2g C5 . 6$ Ap:er.d ir 1: c5 . Appe..dir. 0 IitTilC,PO:. I L .:: i.t t ; -:. (U :;';Yf . .. T I (;
,/
/ ' . /.
A17EST.
/ il. .: .2 ! CY :.g *,.,,=.,/ I * -) '
i
' --...:.~
- c s u t.sr, T I Tt. E, '
-..V . .
I ..' ..P.r .r.._'i
. ' : Ii;
- ;L)
DATC
-.l'r-. ~-e..-d. x . . .. *: . :: , -
DAltr0Ct:.4 !!!! Co.$: rc '.'A:r'
- a. . *<
., s . s s .
, . . DY /,..'.' , . ..../ <
' # l *.,="*. - \.
../. . _. , /,.4 ,'..";' .:.'. . '
*3 g . .. y # . . . . ',. *[
' ( *n?..i'.'..*___.__.... T 111. C,,;,. ,
, , ,;;;g g g.c. , .g. g,., _p .u,i,, ( . .g.,3 )
tim.
-..) ..v. .... . t. o. , , , .
e o
,..e-* .,..e - '
., m 9- ,s -
. .;> r i . , i ; . .'
Till - 1 t 9 i C (4) (c) Reasonably require to contract for scent fuel shipments and l reprccessing services with ccmpetent suppliers. (5) P.d cad Sat c5 Oca.i .- Effert
- ilo t less than twelve tcnths prior to the Scheduled Shipt.icnt Oc to for the first rela:d catch ar.d not less than ten tr.onths prior to j i
the Scheduled Sh*p.cnt Date for the second reload batch, establishG pursusnt to Article t il C (2), Pet Ed shall advise !2sti in w'riting of its projected energy requirements for the remainder of the : hen current cycle, the next reload c/cle, and the four cycles succeedirt the next relcad cycle, if such advice shall indicate an energy requirc.:ent di ?ferent f rcra the energ*/ production capability desc-T
- in Ap1:ndix A for the r. ext relcad batch t,o be su;, plied hereuntier b)
~
BC'.!, '.!LU ui l ! p rcr. ; t l y per f orn that portica of the Relcad Eat:h 1::t Effort necessary ta determine whether or not the itet Ed requi rer..cn0 bc satisfied. , (a) If the P.ct Cd enert.y recuirc:ents can he satisfied witho'.it che in the desigr, other than a change i n en r i chr.'en t , and/or in t hc quantity of crar.iuai, and/or in the r.uc'ber of itbricated assc a! 3 Wo'- in the progra iin;. of then enis ting or then plocck.i cu eq u i ;). .:n L , .nd/or i r. the r.o s i t i cn i :.t; Af fuct a . .c mbi ics t e:;uil a result of a cdsncie hereunder in h.dch si;e, (h..rcint.f ter ca .
,' "c urent chan ps") , Mt! sh.'.I i cer. i:m : the det,irr ef forL te sui
*O- . cc.r;*l e t icn and , ui ti in twa (2) r. oa t h s ic i l ow i n.; thi ile t Ed a.' -
.h
'( * ,
s.. vat h idl icr.;it.a sfer the fira.: relo..d is..tch . n! wi tid a onc (1) 4 ,> liet Ed advice fer t he 'seco.id re l o,J ' b.i t ch , s ha l l ~.nt'. i de tie r '. l' the enric! :ents
. - - - - - ., _ . . - . . . . . . . . , , , , 4. , _
.s rii, i.n &
T.u.1 - 1 Artici. . l'.'
- Centr.1ct P r._i_c_e_. T.. r n . c f P avraen : t. n .1 Insecctinn A. Contrnet Price (1) Initi..I Cnec tie t Ed shtl1 ;:ay to D&'.! for the fabrication of the initial core consistinr2 of 177 fuel cesemblics and for the related services described in this centract th+ sum of Five itillion, Seven I:undred icventy Thce:;end Dollars ($3,770,000) (herein referred to as th:: "In i t ial Core Contract Price") .
(2) Relcad Ertc6es - l'et Ed shall pay to 00t/ for the fabrication of the f i r , t ar.:: se ::..d reload !:a iches and for the related services de:crih:J in tnis contrac: the sum of Thirt/-T::o Thou.and Collt.r
, (032.000) for each fabricated fuci esse,bl/ (herein referred to as tl'e "Tirst Pa load Ihtch Cont re.:.t Pricc" cr the "Eccend i'..:lo.vl I.a t ch Con tr ac t P r i e :" a s t.p; ropr ia te) .
D. --Ter:- r.f- ...P... ..e a t The initial Core Coatract Price, t h F i r:. : P..: lead Datch Contreet Pricc, are: t he Luco:t.4 . ^nleed Da;ch Contract P ice, as trey may be ad ius ted rurt,ui.nc to ti:0 prctisitas,raf ti.is contract, :, hall be paid I C.YJ ne t ca r.h c. :.h i prat :ri t. c. prort,ted c: sl.i p:cen t s go f orwa rd .
!!n. ever. in ll.c event sh i pe.:n t r t" f t bri catesi fuel a !,:,:i:'h l i c s i s delayc:1 I?" yond the C 1.: lu t ed !b i;. . <.n t lt c5 .$ t the r.c:: ,L of l'a t Li res rat:ent to Articles ll A (.1) or 11 L (3), for reascnn other t h.tri i!e l r, e. at t r i b :: al !
- to CL,
.. :! i f . '".J i. ready t :. r.. A. .: s h i;)-
ment paior tri t he l'e t !.J ret;ues t e f ,h i p'.. ri t dates, of any portion o! thc Iur1 .upply i:.: h r this C w ire.:.t, t' '. ' l , on Ihe date of such
. _ ._ . ._ . - _ . ._ m._. . _ _ . _ - - . ._ . _ . _ _ _ _. .__ ____ . ._
*0teria;5, tiela. to -
and rcjc teg ussen,blIcs sy y 0 5h or'ja~. ' of or d e,:r.a y . (to) . 1:nr gg a 5 g , rerr,y ;n Ve s ted - o the , faigUIC to j
- n fic t ~r,.,
rcjccc m sy,;, Constitut, M and/or (ay,Ure to t;
~
'****r
~ci# ~
o *' sW. undcr Chi' Article gy ( G right,' j
*I Articic xxg "Y'
- twi ths tand in*
'
- e M cs.;5 Ions i
ay;,noClon thcreafteand he t and
~
o gg cr..:' ,, ,o I' 'C'ucd'.
**I' V cf thi3 ~
l be in ##'***d<;nce s.;;'t.
- cntract. . .
D. pri .
. "'ticle Mcst.u c te N en .
- The Ccntrn:t p,,Cesorf y
^
I" Article gy A. ishine lion fue ; 0 5 F c-'$ l ;,5 dThese fI'M
*' ated 1
cuch ut'ina " base gayI
- c based o" 'Ch'ic*C*. out
'":o lance
- Cct.~,gpC . ggn
'"9 '* Ith t h., IOU, in Of cnr;',Ed U.r* '**
5,, .
- Le e. l gg ) '.ule
'* 'o e .s
- E' I h nt z,( th2 I::.1: an;", C'adir. j w; gy ,ho f '. . t *Wrc..;4 ;
la Of r cec '*d the fuci asscts!;g. . ~% t e M o r re g. *-~ . .. ., is,, g g,,
.' PUrposas o( *n the ;,.,g, ,
purst,
- Scotion e the e ' S t % n
8Cej *.
- 00% ) j n, . ~ "CNCdUlyg n,te pof:;+,cos.-aSc'" 'r.,gf5Cc
~.
*n th., - .Initic',
- n. '.
s 1:,.. - ~~
,. heat,;,,; ,. c si,y; ;
M'- c, the Ip ,g Oc: 0:.' ' ' * ' (r Ts.'lchc Itas cOlc Of rl'I '!~'ntt n.o ~ 15, l oi'- t- ,
- S e e y
i y'1 t
'*:'V"c: 1.ig. ;, and S shal; bc Ccto,c,. l '"'# *b l 10::
'H S s. 1973 ;,,,,~ -
gg,. ,,C I(ib c.- .,2
- _ 88. base (".5ficotion pag ..
11laf cora , J r,7;;
- e S e,, g ,:s stla r ,.4n u lend;> t h *, ,*,,,.r l'a
,.. n th s yt>r :ta ,
e ru :t t.ga . for9 ,'s. ,. g
, ' ' '- ( tl n g t c.s ;,-
'l u.11 f ay,. ; "" "#U I 'u d
- Isc r ic,s*.
**=and re lc.Q
> 1:a c g. .
. ' faccifjeg * 3 I" A:<;. nd;,y g , h;or.e,g "" lI*c . , ,,Sc! cg , y , . ,,~l, M
.i *
. (I"' ca s e ,,,, , ., .
I
- t d_ og f
L 4 4 g *4-4M G ' .Gwe MN$ we e _ _D-_* b M g.W i . k 6. <4h n eha rha. -..-a . ** = -"'w-- =
s. U2 materials, title to and risk rejc:ted asse:nblics shr.l! or loss of or da:nage to the (4) 1 ct (d's failure to insccetrcera in vcs ted in tiet reject and/or failure to ticaly - shall constitute a v.aiverof .'et under this Article IV C, notwithst Ed rights, if any,
- of Article XXI, and tiet Ed's sole randir.9 the pec.vis icas
. cbligation thereaf ter shall be in a craedy and W 's sole .
V cf this ccatract. . ccordence v:ith Article D. Pr i ce ,* ct iu,s tr en i The Centr.ict Prices sfor furni hi in-Articic IV A. ng fuel assemblics are stated
. of These fiern pe ices arc boscJ or, it.,* c ice tion
- ti.n fuel essemblies riuring a t ase fabs ica t ion perio.2 in cach inu tzunce, car..wncing v.i ,
th t t.e of c.ric!.ad UF initial date of ..ithdre al . Shipn : t c,f 0 the Icst !./.ofICJ 'and cndic 1 v.ir.dth.htet!.c of Sci cdui or rcit.;d la,tch. the feci asser.blics in the For purpose.5 tir.iiri core pursu::n t to this s::ct ion, of ddtcrrainirs the caseonfribricrti . peried
. fuel the !;chedried Cote of Shir -
455cmblics in tne initici ar. t o f th le s t
- t:. 1: co e shsil de oc:. m;;e -
1u tshredele:; Late of Sh ip ont of 15, ir/i. ' t h::
- for isMehe . Ilos, la cnd 5 shall Ia:.L fuel c.ce.blio;-
re:.;: O l ively. be cctrAcc I, 1975 cr.1 ccccher 15, 1974, This, bat.c fabrict. tion operi d i the is.it ial core, s9 c.. ls n ::;r con t h s for
*! c a l e.ndar
,:' t h s f or Ca t 5 c..it.: edar cont h*,
ch J4 (ti.c f irst ruload) and for Pa tc.i J5 (t h e ., :corul reic.ad) .
\
The .ictual fabr' cation peri te d
, .ss beit.ert Da t e s
- e. :cc i f i ed ten the Sc!.c.i. sled Shi in I.;,;wndix 8 or, a , lic:- n.ent .
c M e raay !.
. m bs.,ed on a 4
m s e . _ _ - - - " ~
Aoril, 1972 THi-I ly 0 - delay (ce extension) as to cither ccma:encement of the f abr ica t ion peticd, or ccmpletion of the last fuel assembly recdy for shipment, or both, i.9 cemporison to the applicable base f abrication period,
, at the request of t'cc Ed pu. suant to Article ll1 C (1) or (2) (b), ,
is designated 65 the adjusted fcbricaticn peric.J. Upon the identi-fication of such adjusted fabrication period' this Price Adjustment prnvision shall beccmc. effective and the Contract Price (s) shall bu adjusted u; ward in accordance with the follu. ting: (1) (a) .ta te r i ci : for tht pu r po.s.: cf this price cdjustr.cnt provision en.ly, the ni.: cunt rep ect.cn t i r.g ra ter i c t is fixed at 25 percent . of t!.a Contrcct l*-!ce. .a.n n ri t[imet i cci cvercc.e of ' hc indexes of wholesale prices for " Iron and Steci" under l'etals and itetcl Products at publish 3 reenthly by the Curecu of Leber' Statistics cf t he U. S. Departrutit of Lebor in the t:enthly Labc.,r Rsvi.:. will be ccm,,utre; for the ba:.<- fabr ica t ir.n per iod. The percentage by which such average is le,v.a than the ceer..go of tiet indexe, for the neeber of rmt.th:. in the adjutted fa!,riention peric,d will be det urr.i r.ed a:! c,,p l i c d I o t h- cr:cen t c;;r.M. u:s t i re: n'a tcr i a l af, fixed above to obtain th. increase it; th-nt:ou.i t represen t inc, r.v.terict , The Contract Price shall bc incrc .st J L.y an .wount . qu ivalent to the increase in th.: a:* ct:rit repr es en t i nri r:?:s t e r i a l s o d u t t'ru i n ed .
- q .
O
- .. T'il - 1 Article T/fl - r..ncellation bv t% t Ed in the event tiet Ed canccis the plcnt contrcct, lie t Ed ra," c.incel this ::ntract upon written noticc cnd upon paye. cat to BE'./ o f rer.soncble .r.d preper canes i la t ica chcrees. Such charges shill include direct labor and t.'a terial cy.penses ; vendor cance ll a t ion charges; rec;uisitica engineering cnd decf ting exaense, based on the p:.rcentage of ccealetlen ci the engincering snd draf ting work; develop?.cnt cr:'ineering specict ly incurred for the cancelleJ crder
' including speci.;l tools, dics, fixtures and patterns; and all other direct . nd indirect costs properly allocable or apportione.ble to the order undar 0:;i,"s sta*.dard acccun: ing pract ice, and prof i t on t he vor i. ; c r ie r: ...d.
l'e t Ed sh a l l b e en t i t l ed to c i l r..a t e r ia l
!.recially n:c.:r victed for the order and included in the abcva charges; shi;.r.cd at its c.spense, or, et its cotion, the salvage value the.cof shal l be de:2u:ttd f ron the cen:cIlation chare:cs. fic t Ed raa y , a t its opt imi ad e.m,i:nso, have a fir:a of ine:ccendar.t c:.countants conduct sin i r.d epenc'en t e. .vn i n.' t i na .nd certify thet tire cha. ges are in accorh.".e wi t h r.tendarrj C :l ;) rect ice. Such fire sh.ll be t;ie iri:: . cadent acciaun tantr. of 1411 a t Lbc i.i:.u un i c:.5 tet Ed shall in garri f a i th ..riti for rec 3..n.tbic cause ot.J.:c t t e r.u ch c.c c ,i,in te.n t s ,
i n ".h i c !- case suc.h indepe..d ; tit accoun t.sn e s s hL l l be a f i rr, . o bra l ly i.c c.cp t .W ! c to I,!.'..' t.nd Mi. t Ed, ite t i il ,ha. I l havs: the rlgi.t. stith rea.p2ct to cithcr *ne Sr:cend r e l ead la a t ch , or ho 's h t h. i i r..L sud :.ccond rc l o .d ba t che:; , t o , t r t oin:.t c t hi i co:it re. '. in e.ar t for cr.use (...g., th0 crcurrence h of
'haiir.al fe iiert: ..: i .,.r e t han 2.'.*.'. o f t h e f ee ! a s s emb l i r*. in t h<: i n : t i:.1 . .re or f.il l ore t c. prc d..s . - 7.: ': C f t !.e initi.il ceru L ,4 ,u, u- O - --^'
' .sprii, i .';, 4 int-l X',' l l design energy set forth in Appendix A or failure to r:ect delivery schedules, due to causes not excusabic under this conter.ct, by a ti.Tc l
peri ~cd of rore than fcur c:::n:hs) . Such portial terre. inst icn for, cause
- hali require uritten notice f cm ttat Ed to St,W. Such notice shall obligotc !!ct Ed to pay reasonable and pec cr cance!!: tion chargas for such partial termination respecting such reload t;atch or batches in the scne manner with respect to the termincted part as outlined abcvc for cc..plete car:ccllation; provided, ho. ever , that such chargas for pcrticl tcrminaeica for,ccuse ch:11 not include any indircet costs other t h..n ir tiirec t ros o which, in 4.ccordence ui th Est.s exi s t ing accour t ing Sys t :,, censit contly appli-ed , crc ass igr.ed as a part of L'5W's sinop cos :
and a Il r.at include arey pro: i t. L'pon such te. -ir::.t ica , the i.arties shali r . v.::,9 t i v r. . end th i s co;e t. ac t , as well as the plant con t ri.c t , to re f ... . br-eil c<;t of su:h terraina tien upc.i the right s and c.bl i;.c t iens of tha s,..rtI40. t e 9 e s e e r$ . e
. . 4. -mer. 6-a ===ww. * ** =
. .p ; i > , . ., / .'
Tnt-1
.s APPENDIX D Fuel Delivery Sch-dule
,' Schedulo.d Siii;::.unt Date (Shirmont of
- atch En r i cl.::.en t Req'd. Delivery of A .sc:-b 1 le s by F.P.i
.f.M. _. .. 'I U .235
= F'.o ll a s U.T S, Enrich::d UFr. to !:M.!A __
On er I.sforci I 2.06 26,766 . Datches I, 2 !. 3 will ship from 2 2 72 29.156 flarch 15, 1971 June 15, 1971 to December 15, 1371 3 3.05 28,673 4 3.22 26,766 Five renths prior April 1, 1975 to Scheduled Ohip-ment D c, as ad- , just::d pursuant to Snction iII C (2). 5 7 . 'i l 2') ,156 Five er.9: ties. p r i o r April 1, 19.'5 s, to Sch..d.: lad f;tip-ment D te, as cd-Justed ; a 'Uent f. u Sectieri !!I C (2). a G '.c of i;s.i dali. cry it. 1 id i c t.t r. i . Ce tai led de l ive ry r.. ':: Jo ! r, s : 11 be fo .ar h t.. '- . G: tot 10te. then E months p'rici to Sche;..'u t ed Sh i pt..ees t Dete.
. O I
h 7 .
/*
i. d pl. 3PP-
\
I'Uf N:nn.T- A ' . . . 2 M'1* $ 4 M _ Ml., CII??[,'f , h e.~h.,* ,
- er ee .
h' 4 9 e %
.se-* . . . . - -.- t~ ^' .@ . ?
c'a:/ .
- i. - -
1.;
~'
C:w n1 COi:TM ITC
'. C,: .
_ PAG!
'2 .1 1
- Fu.1 Assectly ,
2.1.1 Fuel Roc 2 2.1.2 2 2.1 3 Control Rad Guide e Tub 2.1.4 Instrumentation Tube 3 Spacer Sleeve 3 2.1 5 Spacer Orid J 2.1.6 2.2 Ec.d Pittin:s U 23 Control nod Assemb:y 4 2.h Axial Power Shapir;; o R d 3 Assembly 25 Eurnable Po,ison Rod A 0 ssembly
~?..c
- Orifica
.. Roc Accemb'ly 7
?. .: utron Source p E0.;1~r. Eace: *
. c R.uctiv~ity Centrol
- E.1 10 E::ces:, Deac ticity
- a. *? 10 P.2activi;y Control D 11 4.2.1 1 :i.ribu tion 4.2.2 Cor. trol by Moval:leA CR 11 Control by Goluble P 11 4.2 3 olcon h.? Con *, col i>y Eurnable P 12 Reactivity Coefficie t olcon
!.3.1 no l?
h.3.2 D,)ppl ar Coerricien t 13 Fiorierator Vold 13 h.?.? Coefficient h.?.3 ::o:1.rn tor Proccure C 14
- .4 Iiodern ter T::.npora tu oeffle ten t 2h Xenon S:
2 bial'.y and Ccacr o:. re Co< efficient U O a d en 4 .._.m .. .._ ... _ _ _ _ _ _ _ _ _ _ . . . _ . _ _ _ _ _ _ . _ _ . _ _
O
. /....
.. . . ,)
i' ' ' '. ( C., i .. i. nu iet )
.. I: 9: e f: .: 1. s s tru. r e t.:t l. * .;;i ,". ,' : I . . r ?
).l .3,j::1,e:n 01:.b :t tvr -
5.' .c t :t wn A: r + : <.::.n : 5 . *: Drc-ictor an't Letect.r A::.wmbly Daceription 31 Applicaticr. of 25tector .Cl;nal
- 6. ?lant Ihneuverability and Load Following Capa'cility 6.1 Power and Transient Operation 6.2 Transient Caoability
- 7. Fuel C::cle Data ,
N m. I e f w ( em G ap --
1
- 1. . .
s J 3 1- Corn' ' h 318n Dat3 PA
--- G== ,
o Thermal a"d Hydrau11c D 29 I.'u 1. gar es1En Da ta
~n* *GA n Da ta 3e
' A D :~en tonz- U**CG CD s M%g 3 ' ~
3 ' CCDCrol Roc gg,"D1 Su 6- 7 Da ta Axial o
~ 7- ouer Sha91
'( Burnany 6 Rod Aasembly vagg O- son Rod A**'=mbly gg gg C.~1:1c, y . 3' =
I
- 9. ::. '
- 8 8A'017 Dato 37
- . ceca pgg 1C. y ConcIClons 30 11- p.,. ,. , ,ri c ,. Con trol "rI
- t a
Colu ;3,u ,. Plbttion
\ '9
- 12. 'A
[.To
. g g,,, '
1
-'2cPcera tu4. and florgy (First Cycle;- q, E'* "Cor:;.an ,,
OGE[icient l . y9,,,3 **DD in ScrVica 1r2. ~0ncth Fu g 3 '. . 43
'lacu und s.'
36 p
^ ucy gurnup pagg hat Da ta N' 17- -
4 ti~ . 4:atch and Cycle 10 Operatin*~* "r a "tPUt
'ML ta tiong
-g7 s.
47a 1 1il l 4
. . .. . . .- . n. . - ..
. . - =- ---
1 1 1 n 1.,, y a....o e-LIST OF FIGURES 1 / tt;:.
- 1. Core Cr:ss Section 46
- 2. Frclir.: int:.T Cora Lond'.n:; Zons Bottndaries (Cora I) D e . . .... . . _, .3s.
- n..b '_.s,r 50
. Cc.in;;'ol Rod Accembl ,- 51
. 5 isnial Po.ler Shaping Rod Assembly -
52 s
~
c- r C mi:.0.r.v Location of A<1.9.1 Po W P Shapin .Roda
,. 2 * :rn . c i.: Po :. con r.o d I.acembly. :-
. L;c'.::cn of Fuel Asse:mblies cantaining
.:' ;;" .0 .;1v 20100n r.oG.'
i
- g. c . _i .i. .
.o.e a '.c.u. . .,, ,..
... 36
- 10. ,Jaifor:- 1/cid Coefficient for 3 77 Ausen bly Care 57
- 1) S:- etor and Otean: Temocrature va Lo,0 53
;.'. Mr '.c Acid Co::cante.m.t lon vn Cara Life 59
5
non T: in: 1-int Clarac tcrintte 00 l . Tr:1:ralent Xcnon Control 61 1 ;; . . . ; ' v. 2 .C2c.c,co2 Loco;.cna . O ..
- 1. f, . ; .,
. . . G .n, . :,
.J n ;. 1, v<. p- i...,. - 4 t.....l.,
. . . . 3.f . .... .
sj ."', G I 9 3.
.y. - -
I APPW!Di ~.' A I!UCLI?ATI FU11 SUPPLY *
- 1. Gm v're.1 The dimentienn, drawings. 111uc tration , data , 'weightc, material:-
and enact details of construction included herein, represent the bett in.ormation a';ailab1'c at this time, and are .3ubject to change during development of the final design in accordance
.uith the provisions of Article VI.
- 2. Core e
The core is made up of 177' fuel assembliec that are arranged in a equare lattice to appronimate the shape of a cylinder. The core croco acction la shown in Figure 1. The enrichment distributien in the first ccre is shown in Figure 2. Core disig:1 cala are summarized in Table 1, thermal and hydraulic design dItc. .in Table 2, and nuclear decign data in Table 3 R._ Fue:1 A.cembl" .
.A fuel ascembly concinto of 208 fuel roda, 16 control rad-c.u ld.: tub,3, one inctrumentation. tube. 7 segmented spacer s1ceves, M cpetcor grida, and 2 ond rittings. The guide tubec, spacer grids m'. ! er.:t fittinr0 form c.ctructural cage to arrange.the rode and i.ubon in a 15 n 3 5 array. The center pa:I tlon in :.h. . cuu -mily i.-"
ru: or tod for the instru:;:ent,ation tube. All fuel ccacmblic; are.' _derstical 5.u - mech inical een:st.ruc tion, and mechanically inter-chanceable in any core location.. A fuel aancmbly 13 cnown in F1:,ure ' 3. F".dl 3:.nemb.ly. ec:::::enents . caterialt: . and di:r.dnulen;
. . .. ,, t........-..%
,t .,
4.. :..... t .,. a .
. . . %. ..., ......,,,, .: ,_...,...a..n._.--.....o.,,,,,_
- 3. .s . . . :. . . ..
. -. ,.._._.,a u...,.. ,,,,,.,..n....,,
.o....,..__..,.._._s-.
,.,,, .. . . , ., . ,, a. , _.._ , ,; .........,.:
_.....A..
.n.. .....
. . . * . . .-,,e,.~.
s.:
....,.,'m.
se
... .~ . . . . . . _ . . . . . . , , . . ,...
m _ _1.-- -- -
.v.
l
- .3.A .r:,. .,. .,1. .n. a.
A fuel reul conciata of fuel nel Mt , the clad. fuel
. ,t.'part .ccaponente, and end citp0. The fuel pullets e.re in the 20= cf cintered and pound p.:lletc of Ic'.: ecriched urtnium dic::ide . Fellet ends era disned to minimita differential
- hermal expansion between the fuel and the claddi.g. The n =inal density of the fuel is CE.55> of the theoretics1 density.
The pellets are clad in Zircaloy-4 tubing and sealed ty Zirce.loy-4 end caps. The fuel rods are then ore-orest:urinad. Design average burnup of the fuel is 31,7C0 M!1d/ICU with a pe2k design burnup of 55,000 Weld/ TfU. At the design .ceak turnup, the fuel gro'e:th is calculated to be 9-1/2 volu:ne percent. E7dici growth of the fuel during burnup is accor: nodated by"
~5111:t, por0 ity, radini clearance between the pellets and the cir.dding , and by a small amount of pa =anent strain'in the
; ?.dding . Ccleulctad pard:. turnap of the fuel ic ! 2,000 Mh*d/!8U. !
t - Solcw each fu 1 column it a thin-wall scainless stoel
.: pacer which anin11y locates the bottom of tha fu'el colump and
- iparates tha fuel from the lower fuel red end cap. This n . iectal is de::1gned to collapse at 'a predet.nr.:ined column 1 cad to provenn c: c :.:niv.: nxh1.:tra in in ' the cladding.
Aco tv th: fue.i coluna la a thia-wall Otainlesu steel
. : cer tube that ceperaco:: thr: fuel:frca the fuel rod upper.end cap. _ Thia :: pacer u.tintaina the fuel column in place; during r:hippins cnd handling. In oporntion. , the Op1 car permits n.xial
.difforentin'. growth ind 'th2=21 oxpanal n be :.;en the fuel and m u.
I - l- =ii' i- i _ _ _ . . _ _ _ _ .m___. _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ - . - - - _ - . _ _ . _
]
th elad. Thic spacer alco provides radial fuel rod cladding
.;ttppo rt .
Ceramic .tpacer; are located be tween the fuel pellets and th: tub? spacers, to thercally insulate and separate fuel
- pc11ets from tube spacers.
Fission gas release from the fuel in ven;ed to voids within the fuel, the radial cap betueen the pellets and the claddir.*g, and to the void spaces.at top and bottom ends of the fuel rods. 2.1.2 Control Rod Guide Tube , The Zircaloy guide. tuces provide concinuous guidance for-the control rod assemblies when inserted in the fuel assembly.
.nd provide the structural continuity for the fuel assembly.
' Gilded to each end of. a guide tube are flanged and threaded
/
, cleeves, which secure the guide tubes to,e ach end fitting by locked-welded nuts. Transveroe location of the guide tubes is orovi' led by taa spacer grida.
2.1 3 Inntm,cntati on Tuhd This Zircaloy tube servec as a channel to.gulde, position,
~
and contain the in-core inctrumentation within the fuel assembly. The inutrumentation probe 10 guided up through the lower end t'ittin:; to the d 2 1r->d core elevation. It in retaincd axially a t t hr. Iower end fittin*; by a n'etainer sleeve.
'2.1.4 Soncer Cleeve The ' upacer tube ' cog::ent:: fit around the inctrument-tube bettern Opacer r; rid and provant axiol movecent 'of the pacer-grid; durin.; psitary coo 3 nnt . O cu through the fuel assembly..
\-
- 3.-
~ _ .. .. __
. . .i
( _ 2.1.9 Sa'c~" Grid - Spacer gri<ia are conucructed Cron strics whic nad f it tr.d to>; ether in "c3~, c ra te" rac h i.on . Each er a t ri a:: , l# p.'rpenriicular to lo, whlen forms th.' 15 x 2 Ti:^ : 3quare walls formed by the interlaced strips pros th' fcel reda in two perpendicular directions. Cont 8 on the walls of each square opening are integrally pu the strips. On each of the two end spacer grids, the strip 10 extended and rigidly attached to the respect fitting. . 2.1.o End Fittinn:s The lower end fitting positions the ass,embly ir core grid plate. The lower ende of the f,uel rods resi s 3 rid of the louer end fitting. Penetrations in the lo fitting are provided for attaching the control rod gui an.1 for access to the incurmcentation tube. Tha upper end fitting.ponitionc the upper end of n;aembly in the upper core grid plate structure and pre meana for coupling the handling equipment. An identif;- on each upper end fitting provide; pocit1*ve identifical An internal hollow poet in the center of the end f providcc mcEna for retention of either an orifice rod a a burnuble polaon rod a::cambly. Integral with each upper end fitting 13 a holddown
\
and upider to provide a poultiv:-holddown cargin to opp
' hydraulle forcec.
?_nctration 1::
. . \
the upper and f'.: tin; grid are pro-the guid2 tub 20. M 9
. - - - - ^ - -'
. .- . - - _ _ . . - -. _- .- . .~. . . -
19'/1 P . :. ( * , r . ', r A il vi A; ::<ci1] / (CT?A ) s .c 5..ch control rod acaembly (Figure 4) has 16 control rods, a stalalass teel spider, and a female coucling. The 16 control rods are a:tcched to the spider by meanc of a nut threaded to the upper chank of each rod. Af ter assembly, all nuts are lock teldad. The control rod drive is coupled to the CRA by a bayonet type connection. Full length guidance 'for the CRA is provided by the. control rod guide tube of the upper plenum assembly and by the fuel assembly guide tubes. The CRA's and guide tubes are 4 designed with adequate flexibility and clearances to permit freedom c'f t, notion y_ithin the fuel assembly guide tubes throughout the Otroke.
' Each control rod has a sectidn of ne,utron absorber h.aterial.
4 The abacrber material is an alloy of silver-indium-cadmium. It 14 clad in coldworked type 304 stainless steel tubing. stainless { . st:-l end pieces are welded to the tubing to form a water-and i orcecure-tight container fqr tha absorber material. The stainless. ctcel tubing provides the structural strength of the control rode und prevenca corroclon or the absorber material. A tube
.: pacer similar to that in the fuel assembly is used to prevenc nL orber . motion uithin the cladding during the shipping and handling, and.co permit differential expansion in service.
i. Pripcinal data percaining to the CRA are sho.,vn in Table .5. j These control rods are deuigned to withstand all' operating-load.: -including thocin resulting from hydraulic 1forch, thermal gradiente,'und reacter' trip deceleration.
' The abilit:/ o.f the control red clad to roulut collapce has been established in a
_aar 6%MD MNI -
p,y, L ': (J \ q -
- c. .:t pro,;rart.
- ta on cold-wort:cd .:tainl~na ateel tubing.
Ac-In-Cd alloy poicon doen noteyi ld Escau 4
'rttd h Llon, intt?rnal pronaure a gaceous product u and aw 131ng ol' the absorber
- ?.torial will not cause excessive cl2d. stre asing or ctretching of-23 Axial Power Shaoinz Rod Assembly (APSRA)
Each axial power shaping rod accembl power shaping rods, a stainless steel y (Figure 5) has 16 e coupling. spider, and a female The 16 rods are attached to the hpid er by means of nut threaded to the upper shank of each rod. nuts are' lock welded. After assembly a4 coupled to the APSRA by a bayonet cThe e is ax
. onnection.
cc,uplin,3s of the APSRA and CRA have sli The female , to ensure that each type of ght dimensional differens type of drive mechanism . rod can only be coupled to the cor When the APSRA is inserted into th by the cuide tubes to the fuel a e fuel assembly it is guik ssembly. of tha APSRA in provided by the cont Full length guidance spur plenum accembly. rol rod guide tube of the rod drive stroke, the lower end of thAt the control full fuel acuembly guide tube to mai e APSRA remains within the throucnout the rod travel lentain the ccntinuity of guidance ngth. permit mar.imum codformity with thThe APSRA's are dealgned to tnrou3nout travel. e fuel assembly E;uide tube Each oxial power chapin's rod has a
- .al.corber material. acction of neucron cilver-indium-<:admium and is clad i. Th10 ' a tubing . tith utainless steel u n cold-wor::sd, stainless steel pper and lower end pieces.
The end
-E-
iin i . ' 71 piec-u are welded to tha tubin ; to form a war.<.m und precoure-tighj contain.:r for the abcorbe r ma terial . The tubing providea the Otructural strength of the axial power shaping rods and pre /ents
.rerrosion of th.: absorber mat.c rial . Above t,he section containing
- 5. hr abcorber materlal is a tubular follower mace of cold-worked 21rcaloy h tubing. This follower is attached to the absorber stction by welding to the end piece and is vented to permit the ccolant-moderator to fill the void. Percinent data on the APSRA is shown in Table 6.
These axial power shaping rods are designed to withstand all operating leads including those resulting from hydraulic forces and thermal gradients. The ability of the axial power shaping rod clad to resist collapse due to the system pressure has been dr..onstrated by an extensive collapse test program on stainless i -
- ct2e1 tubing. Eccause the Ag-In-Cd alloy does not yield gaseous croducts under irradiation, internal pressure is not generated
.ithir. tP.e clad. Swelling of the absorber material is negligible.
and will not caunc unacceptatic clad train. Locatio'ns of fuel ac =n:alles containing a::J al power shaping rods a'ra shown in Figure 6. 2.4 Eurnable Poinon Rod Assembly (PPRA) Each LPRA (Flgure 7) hau up to 16 burnable poison rods, c Otainleau nteel spider, and a coupling mechanism. The coupling mechanibm and burnable poison rods are attached to tha epider. The EPRA is inserted into the fuel assembly guide tutes throuch the upper end fitting. The coupling mechanien provides a means for positive'ecuollng 1. tween the EPRA and the fue) assembly holddoun latch. _7_ .
.401 T;tpleal 1cantlona
([2.. or fuo] ro.h: are ahown in Plgure U t...:,:mi 71.u con
;; bus t,a Each burnable polcon
.cc11ats which serve as- burnable son.
poir
- clad in cold-worked Zircaloy 4 t lower end, pieces. -
The burnab: The ubing and Zircaloy-4 form a ma terial,. water and precsure-tight a cont i The Zircaloy-4 ner for the abs of the burnable poison rodstubing provides the c tui In addition,to.their nuclea to minimize guide tube b r function,.the SPR.o. a . the SPRA are shown in Tablypass coolant flow. Pertine.nu e 7. The burnsble poison rods ar operating. loads. including tho e designed to withstand
'I ~
and thermal gradientc. se resulting from hydrauliE clad to resist collapse due tThe ability.of the e pois o the preocuro has been demonstra sys' tem pressure and cold-worked Zircaloy-4 tubin'ted g. by an extensive prot;: te 05 Orifice Rod Accemoly (ORA) Each orifice stainlecs steel spider,a androd assembly orifice(Fig & mechaniam provides a coupling mechancim. The cou ORA and the fuel accen bly hmeans i coupling for positiv between-t are incerted into theembly. fuel assolddoun orificelat ? bypaca flow through empty guide tubes. The ORA serves'to is ch own 'in Table 8. Pertinent data'on t..
. (-
. -e-
,^2_ j { e..ma a 4 - - h. -.
1 . s
- . en .7<,u r.ceg
( i l l' .ut: on courcoc encauculaccil in etain1ccc cteel
!;ocition i>/ crainlecc ctcc1 cpacers are used in celc) accciablion for *he initial ctartun of the reactor, at incerted ir.:c vacant control rod guide tu'ces.
The ca i:e cr.e of the followir.g typec: Tentative T'.'oe of Source _
?!o. of Primary Scurces Strencth o
_of Shinoina GE-ABC Po ~Be 2 !
'2 ,,
300 Sb-Be ~ 400
. . . ~
. 16 . _ .
,,.loor 9 .
4 C Se
==
G G o. l l e e .. .. -
.::t:.* , L if f.
i - 3 P.: *. -P u m n 7'he r"acter is designed to conform to the following critoria: i
- 1. he decir;n maximum overpcwer is the highest c redible t
reactor power permitted by the safety system and is
. 114 percent cf 2568 N'!t core power.
- 2. !o contral melting of the fuel will occur at design maximum overpower.
3 The minimum allowable Dl!ER during normal operation and anticipated transiencs is 1.30 with the V!-3 correlation. 1
- 4. 0. 7 a 0 - 1 710 .- Control c --
R2act".vity control is maintained by movable. control rods, by rol a'..' noiron (boric acid) in the reactor coolant, and by lumped c urn 2 ' - poinen.
' ho T.cderator temperature coefficient (cold to hot critical),
v:': librium xencn, an well as lon.g-term reactivity changes caused by Puri burnnp and ficaion product poisoning, a."e cont rolled by add..;t!n: coluble poison concentration. i .'hnr:-term reactivity chances caused by poder change, transient x7ncu in).noninc and the moderator temperature change from aero to 1- r cant p'ower are contrclied by control rode anciated when-mecannr:/ by nolubic poison concentration. ! }
'o t - 4 %
I
4*. 1 "1
.., j -
en '.'v'tv \
.~ .c execca reactivity acaoulated with variouc core cenc't'ons is tabulated in Table 9.
4.0 lo2ctivity Control Di.ctribution T.;pical reactivity control distribution for the firct
. cycle *a cuown *n Table 10.
4.2.1 Control by Movable CRA i<Iovable CRA is used to control the following reactivity changes:
- a. Sufficient rod worth remains inserted in the core during normal operation for 90 percent of the fuel cycle to overcome the peak xenon transient following a power
. reduction of 70 percent of rated power. This override capability facilitates the return to normal operating conditions without extended delays. The presence of these rods In the core du.rinc operation does not produca cower pealts above the design value, and the shutdown margin of the core is not adversely af fce ted .
- b. Power lovel chances (Doppler) and regulation.
- c. Detween 0 an'd 15 percent of rated power, reactivity componcation by CRA will be required as a recult of the lir. car incroaca of reactor coolant toaucrature to the norr.al or, orating value.
s 11-a e aee a ngs . e se @.p go - qq g en . , 9, q p in , y e-~s
)
iM7 , l'.71 i I
- d. Additional reactivity is held by a group of partially incerted CRA (25 percent incertion ma::imum) to allow periedic rather than continuouc coluble boron dilution.
Automatic withdrawal of these CRA during operation is allowed to a 5 percent insertion limit where the dilution procedure is again initiated and this group of CRA is reinserted.
- e. A shutdcwn margin of k percento k/k below the hot critical condition also contributes to the reactivity controlled by CRA.
4.0.2 Control by Soluble Poison 2oren in colutien 13 used to control the follexing
, relativolv 01:w-coving reactivity changes:
- a. The r.oderator pericit in going frca ambient to operatinC tempe ratures.
- b. Equilibrium xenon and samarium.
- c. A part of excess reactivity required for fuel burnup and fission product buildup throughout cycle life.
Under conditioini where a cooldown to reactor l'u11 ding
- .: 5 3 ' n :=pora1,uren in required, concentrated coluble boren will be ad'!e! :o the reactor coclant to produce a chutdcen cargin of at leaJt 1 tore.ntiik/k. 2erinninc-of-life boron leveln for ceveral cort
- cendi; inns are licted in Table 11 alon.g with boron wort:. values.
L The conditier.: chewn .;1th nc CR/. illu:trate the hirheet recuirement3. m +*m
. . s, , , =
- 4:i / , 1 '/1 a . ; . .; Cn:1t ro l Br P,u rn % 1o Pol.non_
Gurnable poison rods are used to centrol the
1' ~'nr roactivity effceta:
- a. A part of excess reactivity required for fuel burnue and ficsion o. r: duct b uild uc.
during Cycle 1.
- b. Reduction of the moderator temperature coefficient at the beginning of Cycle 1 by being able to reduce the soluble boron concentra:ic.m
~
Such effects are reflected in Table 11. 4.3 Frteti*tity Ccefficients 7eactivity ccefficiento form the basis for studies involving normal and c5 normal reactor operating conditions. These coefficients ha te been investigated as part of the analysis of this core and are de.r cribed below as to function and tentative range of values . 2131 Ocnolor Coefficient: The Doppler coefficient reflects the change in reactivity as a function of fuel temperature. A rise in fuel te.rr or -ture results in an increase in the effective absorption crcss necL;.on cf the fuel (the Doppler broadening of the resonance peakc} r.n : . Carre:)ponding raduction in neutron prcductien. The range. for t h <t uurpler coefficient under operating conditionc is expected tc be -1.1 x 10 -3 to -1.7 x 10-5 (22 k/k)/F. 4
, .~--n. . . . . . .. s . .. .;
f
, vt / , !1 /!
4 3 . .' ?toderator 'Intd Coeffici3nt The moderator void co+:f ficient relatoc the chance in ua:ron multiplicatien to the pr^c ence of vcide in the moderator. The a:mected range for the void coefficient is anown in Figure 10. U.3 3 i!cderator Pressure Coe f ficient The moder.ator precsure coe f fi ci en t relates the change in moderator density, resulting from a reactor coolant prencure change, to the corresponding effect on ceutron production. . This coefficient is opposite in sign and considerably smaller when compared t: the noderator temperature coefficient. A typical range cf precauro coefficients over a life cycle would be -5 x 1C-7 to
~~ '
+3 x 10 5 (.3 g/x)/ psi. ,
4.3.h Moderator Temorrature Coefficient , The moderator temperature coefficient relates a change in niutr n multiplication to the change in reactor coolant temperature. R;2c_cra u in; soluble barca as a reucLivit/ control have a less nc;ative moderator temperature coefficient than do cores controlled colely ny movable or fi;:ed CRA. The major temperature effect on the c ool'_r : 10 a change in dencity. An increasing ecolant temperature nroducer a decreace in water density and an equal percentage reduction ir horon cor. centration. The concentration changa results in a positive r'.aut'.7.Ly component by reducing the absorption in the coolant. The man .i ad : of this cc:.;ponent is proportional to the total reactivity , 1 held by nolublu toron. euer m.; *.
- 1
.,v, l'?/' l M atritsuced polacnc (bornable poicen rod; c.-
in. >:'to't centrol reda) have a negative effect on the coderator ec frici.;nt fer, a ep'cified boren concentration. Tnat 10, the
=ciera:Or coe fficient fer a system uith 1200 ppm beren'in the ceclan: nnd 1.1 red worth incerted uill be core necative than fcr ,
a cyctom with 1200 ppm boron and no rods inserted. Oecendirg en the core size, core loading, and ' power density a plant may cr ' cay not require additional distributed poisons to yield the apprcpriate codera:cr tecperature coefficient as determined.by the safety analy.013 and the stability analysis of the core. This is illustrated in Tnble 12.
!; . a Zenon. Stability and Control
., Hodal and digital analysis of the core indicated that the
~
tendancy -towards xenon instability in the axial mode would e::ist tor a gicen cc=bination of events. Therefore, eight part-length Axial Pc:.;r Ch2pir.g Rod Assemblies (APSR,A'9) have been included.in't'he decign. They will be positioned during operation to maintain an acceptable distribution of power for any particular operating ccndition in the core, thereby reducing the tendency for axial oscu-It a .c:.0. ' w 3 r -
- .8 .
4 I e
- _- = -
. . - < m-
t- s .
$ t PA / , l71
( % , f. 6
, s t A
\ E
- i. s a% g
' N, - :.:. : .11. i i t i ::1.7. L 1 i 11,:/ o r 1.l c c6 te 't.: d* p e ntle n t on cor^
i t
- 3 . . G:. , p r.:
- i- . :n;;1 t,:/ , $nd I,he niocle ra l.or tempe ra ture coef ficienr .
In dr. ; - voz. t , na core will not be :succeptible to diversing
\
c c.u.. '.:t ': 1 o;;c illations .
. If the loadin!5 end .ccwer density are Icw
- er.d..g - tne core will be inherently stable. If not, then turnable
-i
- iacr. '.s added in thJ amount nececcary to ,crovide tha modrirator'-i 1
te:r.oc.-2ture coefficient that will result in azi:T:utr.a1 stability. 4 h.
"N I 4 g 4
* =g e 4
e f*'s- %. I g M e
,.m.
4 b
"a _
.g .g.
A _ mW
's
.s* T
, s b n f.
6
+
\ T s
a
- s 5
, .s %
-f
, 3, A.
s -\ Ag %. %
% 6 1 6
+
i s ;s
- y .,\.
k 8 g i t f f e g . -s
'i ;q . s s
* %, ; ' r
, ;, .y e
- 4. t, - +
i
-A a ,
i t < s i
< 1 1
),'
I1 l a, - . i c.
? > ,
; \ 'r
< I .
+ _,..- . .. . . . . . . . _ _ _ . . _ _ _ . . .
% . ,%, l
l k e , e.. . 4 op
. . , . . 7 . . , 3. . 7.. . i. r. 3,.n r pq ,, .. . ,,f r. t . n r c 3 C.! rent.n O!:.ia.;eivon 0 ' *
. i.n c u ro .netrumen.ation 7atem monitorn crre performance to f revt !c a .hintory of rcwer di.itribution. Data are i::cd to
{
'6,;20 r .ine the to:t ecencrical an.i safe core 'curnue pattern:: . "'he
.g -
- t.
o
- Ocnitor are not ured for direct reactor centrol or crotective -
4 action, but aid in optimizing centrcl settings and protective limitations necessary and provide information on disturbances' during -
- l. all =cie of pcwer operation. Data cbtained also aid in-meeting 1 '
- reactcr -licencing recuiretents to justify plant stretch capability .
P and tc perni; future core improvements.,
; 52 5" :tm- Arren e.:ent i
T'ie incore instru.entation arrangement is shown on Figure 1. Inc: ce; .:et ?ctor c:::aen' c liec cre located in the fuel assembly . instru-1 i em nion tui>e at C2 radial locations. Each detector assembly c:n _ctn e:' :even .ulf-powered detec: ors to measure- the local flux 7.' von diffarant elevatiena and one backt;rcund detec cr. le v' . ': ,[ 4
~n try cr -the detector acceablier is provided thro'uc'i the bottom 1
j cie*c.i c r tile reactor vennel. . c. d u I s t Y
)
r, ,' -t 4 i
~
- I t
L-b I. ' p -; ' L; < .
.ms. ....___.;-.......
! .-i.
t . ,+ ..w tno 1. t < c t or 4:.0 crc.L ' r Den e r ir,0 ' cn
'r w; nel P-ocwored 'dutect.or is manufacture'! b r No Mint:
.J.~._~. /^ 1 n of rhodiu . wir:+ to the tip of an Ir cne'. conductor
'?
0 - 0 .' - . .ch are surrounded by magne ium or.ide inculn-lon within an' : cenel theath. 'The br. sic detector is then draun cr nwaged tc th .:pecified dianoter. The backrround cetector in of sinilar manufacture, but has only an Inconel conductor which extends to the tip of the detector. The seven self-powered detectors and the ca0.- round detector are then Ercuped within an Inconel
- a. : r:l" . neath and the shaath is drec.in down to a ligh; fit around
. w.
.. 2 c%. . . u, %. . .. ..
- i. lInlication of Cetector Si: nal _
Decaune of the extremely slow burnup of the detector, the p 1 '. .: . . mpu er can integrate each detector's output current with re. e - 3: t '.n e , cc pute the total neutron flux seen by the detector n t- a burnuu fr.ctor to be applied to each detector cit nal. s
'": M v. tm ilin,q n.I . tem then comnutes an average flur value for
- n -
- .: ore , r..a rhe pc.icr distrib ution pattern of the cor.> .
+
k
-1:-
+
. , . , . , 1 .,*./ ;
s2 r, , .-..- " ., . . . . . cf . ~.! . i i t : .c . .nci Lo id Fr 11 owi n - C'n at: i 1 ! t r to full power
' n :: s.'
fol low i nt- dencription, all re ferencr
- .n:: ' fi . ' 8 ""d*, trire t.:Uc r.
, .1 f -war '.nd '"r in: 4*nt 0:eraticr '
Nerve 15.5 pcuer the reactor plant na/ be oce~;ted either en In autenatic contrc1, tne reacter manual cr automatic control. a narrow band coolant system average temperature in held within around the setpoint. The rtactor coolant system temperature, steam generator r ac.;uro , and the steam temperatures , are shown as a function of
- 'ady .' ste power level in Figure 11.
~
urin;; oower operation fuel depletion and accumulation This reduction in reactivity ci' Ti. ' '.c:' products reduces reactivity .
':'he coluble poison 1 : :'f r.u : t dilution of the soluble poison.
" 'c<mtration as a function of core operation is shor n in Figure 12.
"cn.rol and adjustment of the coluble poison concentration
. . . a ~.duc a: C011cun: ,
One Group of control rods which is on automatic control t the start of a cycle.
.i: indexed to be 75'; withd rawn a Heduction of available reactivity by fuel depletion and ficcion product buildup uill tend to decrease power laalin:- to a reducti:n in averai;c reacter coolant t emperat ure .
rod group The control e /cten automatically withdraws the When the rod ;;roup to restore tencerature conditions . reaci:c.: the 99,I withdra.:n pccition, the operator is alerbec b;' vi::ual and audible means and permissive circuit: cre ::: itch 0d to allow dilut'on. e
.. h "
t
**9 e*= * .
' --$__.___W
-tv
-,., -3 on.
- *:he operator initiates tne diluticn proce:c thich 1
j .centinues until the . rod grcup inserts (in response to amall reactor ecolant average temperature changes) to the 755 withdrawn positions. .An interlock stops
, Jilution at this point.
e Dilution 1: required about every 5 days at full. power cperation. For short-term part ~1oad operaticn, the automatic contrcl
- cc uili mcVe the centrol rods to maintain desired power and t ert;e rat ur? in response to transient renon reactivity changes. The-ccncrci cystem will then move the rods to maintain constant average to 7srature.
4 For extended operation at part load, control is similar. to (- that Scr chcrt ter= part' load, except that 'new equilibrium xenen ccnditi;nc are reached.. . A fuel burnup occurs, the control system withdrnw centrol rods'to maintain the pcuer. The average reacter c oe.1:.n :q=porature or coluble poi Or. concentration. may be changed to maintain relative rod positions. .Upon return to rul.1 power equilibrium conditiona , the operator adjusts. the soluble poison eincontration-an.neccccary to achieve the normal red pattern. Part load cporation in permissible within limits .with two
;-accer coolant pucpc out or nervice or one steam cenarator out of cervict. The maximum pour:r levels obtainable with various reactor
- ccolant pur.p cc=binaticna are shown in Table 13 i
L
- gg .
m
*e
-mg,=
y ~.s y-,, 7 e e
>. , 177t- ;
i U.2 Trancitint Cacability The Muclear Steam Supply .?tatem will follow step or ramp 10.m ei.ance:s under automa-tic control as follows: (1) Step load changes - increasing or decreasing load ste.cs of'10% of full power in the range 'cetween j 20% and 905 full power. (2) Ramp load changes - increasing or decreasing.lcad i F ramps of 10%/ minute in the range bet.-teen 20% and 905 full power. From 155 to 20% and from 905 to 100% full power increasing or decreasing ra:ro load changes of i 3%/ minute are accepted. g P I 4 J 9 J 9 (- A e
% A .n n,.wa iw u. .m mm. , , ,
May, - 19'/1 1
- The trannient capabilities listed aoove, particularly in l l
t.5e enne of a pcuer reduction followed by a later power increase, are d2renden; upon une xenon conditions in the core. These ' r c r.ditien. and their effecc upon the above listed trar.sient t
~
capacilities are di cussed below. Increasire Pouer Transients With an increase in power demand, the Integrated Centrol System initiates control rod motion', change"in feed flow and change in Ourbine throttle valve position. 'At the sam'e-time,'the-reacto$
^
I. coclbn? system average temperature tends to decrease due to the , increared heat transfer from the reactor coolant to the secondary
. s y t t .ri . Gn a decrease in reactor coolant temperature, the_ control J zycter = ves rods te return the system average tecperature to nor al- + .
i (etithir :h? deadb and limits ) . The-decrease in reactor coolant j avern: u tonpora:ure al o causes an outsurge in the pressuricer-r^"*.*.....:t in a decraase in prescure. Tnic, in turn, will energize i the pr. suriner heater to maintain cystem operating pressure. Cne extent of red motion, decrease in pressure,. and time to return to couilibrium loop' conditions , are . functions of ramp ~ rate and I time duraticn or t'he nize of the step increases. , h n ncint- Pounr Trannients . Locreacing power tranciento also 'concist of both stcp and ra'.1p decrer.cou in turbino Ienerator load. l For a decrca:In,7 power transient the reduction in steam 1ricw and ir.Oriace in^reacter ceclantitemperature call for rod insertion. A praecuriner. incurce ccourn which compresses the steam bubble and
. s.
inc re S:I c system proncuro. _The: pressure _increane actuate: the pro: dri er spray .'al/cc- dhich spray _ rcactor inlet water inte the
-. - r ,.. _ - ..-. - - , , _ m-
IUt'/ , 'l F*1 r
;_ .cc=. rnee t o - condensc steam and ma intain the -preccure at the
- d e c i re <1 value. During cevere load drops the turbine by-pasc
~
l .'.11 cpun to accict in stabilicing c t aam pressure . The most severe decreasing power trancient normally 8hecentered 10 that of turbine trip at full power. In this case, 4 the concrol syscem will run the reactor power back to 157, rull i power. Steam generated will flow through the turbine by-pass to the condenser. . i ! Z4nen Transients . .. , ,, ., ,
' Fellowing a change in reactor power, the reactivity :of the core ill change with time as a result of. variations 1n xenon ,
c:n ?ntra:ic...
.'sfcer a power reduction, the xenon concentration increases ,
~
to a .ma::imum value (peak xenon) in about five to eight hours and then _ b ecinc 00 ' decrease to a new equilibrium- value corresponding to- the A v e c., :: 1 ere1. Upon return to inicial pcuer cne xenon concentration firs: d2cr:2ses rapidly to a value 1csc than the initial power equilibrium 2 v ,10. and th an alculy return: to the initial power equilibriu value.
'!h e extent of the peah Xenon poisoning, the minimum xenon ccnc. n:ratica after return to initiel power, and the timc Jrequired L f o r t:. 7.cnon . concentration to recover to the initial power c<r:111brium value varico depending upon the initial, reduced, . and .
I final level and the cperating tice ac thece power levelc. Xenon
' trantients effecta arn chown on Fi.;urc 13 .,
e e
.. -- ~_ . -
i t
. .. ...^ ,. , , v-a i ,
-.. ':T. ct: , .ci. i
.. . - -e -..
ic- .
\
* , '.. t a, e ,.
, : . a. '-"
, "o" ,
;i ; . .. .. ; o llcNine- h .* .,v o ry ,
1
~
thd
'" ' Con trol
~
, , . .sd enan.c.c < n arme ,4.. t P
.; .'~h 2 -
a 0ferride :P
. c;ter pes :enon r:-cuctica of as
- o: centrat ion full pcNer tc 300 f l uch as $0 5 . created b u l pc: tor may be full ocwer within the
?.eturn to the ran coctrolled by xenon initiated at any timeoriginal poner .
tne level at red: a to cc pencate for Srall boron normal ramp rate ncy nonon a d.i t.a tren to e . . .i..e. .,,.4.
. ca. be rec uired
..p
.. . . s (v e .nec:'cencrations 1cuer th e
c ...,,, t 2 )
- . an the initial pc
'. h e
........,,o.,,,
. . . s capability of centrolli
.;,. . e 4 4 ,,. -
- cO.",
. ' ' O f e e.en .'ual cycl of each fuelng these xenon tranci .
ents 3
~
-: e this c/cle.
- 'm ;
During the last
. nd:.aun from the capability decrease s cera.
.4 t the slowly us the xer
. . .. s.. ....:
, ,, _ . oe c . .:. .,,,
2'
, .1d a .'. . . .
. eau of each fuel cyc le t, e n '. : , : .; .: .aric s,.cid dilution will be c n:,tr br.n 53.1czerride peak ,n cranede t recuired to s upploraent c: full power the we xenon created by cov within the er reduct eductions belcu0 2full power rance 100$ to 30j'
"'al l po.'tcr>
With full power u ' c r . -t u., later : ecurn to 'm.2r redn reductions cf up
. i ?. : . n ~ .:;uca cr alone, if return to cricinal powe !, can be c.u . t., original
- ,.: On t ::ay b e after 20 hourc. For thic power ic initiated 1
cecuired to care alco, bcron r
- hun the initial p compen:cate for cuer~equilibrjum va lue. xeno" conce::t racionc 1
h9 i no W ** e
H::t . ! ':Y1 31 The above method of contr l ling peak .m e a n c onc en t. ration e:. n ' rr.1 Ocncentration adjustment pe:.its return ' i criginni power at '. . ? ::crmal ramp rates . If boren cor. centration .uij un t, ment; are nc: cx_ red, the control rods designr.ted to cont: o : power Doppler r51c-ivity can be used tc supplement the xenon roda to override the pei: xencn reactivity. In this case only a oartial return to criginal power at normal ramp rate would be poss ib le , follcwed by a burocut of xenon and increase to original power over a period of one t. o fcur hours .
- 4) Tuc' xenon transient c as er, are illustrated in Fi gure 13 .
a) Supplemental Boron Shim Figure 14, Case 2 illustrates a typical lond transient over a pouer range which is beyond the capacity of xeno' override '.ith rods alone. In this case the loac is reduced from 1005 to 255 t at the normal ramp rate and held at 265 power for 6 hours, i.e. pe>a cransient zcncn condition. The boron concentrat ion 10 adj uc ,.m: during the six hour period to partially compensate for the xenon trancient reactivity. In the cane shown, the boron concentration ic reduced by 40 ppm to provide the reactivity difference E ttwen peak xenon reactivity and trancient zerien rod worth. The Coppler rods are available for a return to power at the normal ramp rate. M m.
,, . ,n_
w b) F. educed F.anp 9. ate Ficure 14, case 3 ille :trates a tv : cat exampi2 cr extended time to return to pcwer. 7ne Icad transient shown is a pcwer rer'.uc t ion from 1003 to 255, followed
-by operation at 255 fcr six hours. $1nce the xenon reactivity swing exceeds the worth of the Xenon transient rods , the Dcppler rods are partially withdrawn to maintain One reactor at the 25$ power level during buildup o f xenon. At the end of the cix hour period the Doppler rods have sufficient reactivity to increase power to anout 650 of the normal ramp rate. At the new pctier level, the
- xenon is burned out at a rate greater than uhi ch it is produced, hence tne xenon reactivity is gradually decreased. The gain in 'r"act ivi ty from burncut of xenen compcroated by an increase in power. Ab ou t one 1our is requi;ma !.o b urnout xenon and achieve orie t nal power for this load trancient.
'Cl o c t ric a] Lcnd Lons 7nc plant reopence to 1cna of external ete"trical load is an T . 1 /.. :. :
- 1. Electrical load upset cauces trip of breakers conne'eting main transformer to Grid. This action ,
may be automatic or i:y cperator a ct ion - ~ --
- 2. Upon trip cf the breakers , the turbine ir.:erecpt valles c1cce.
..+
il L l i 2 T.ie powe:r runb ack zi.;na '. is appliec i- the i nter; rat ed 1 control cyatem. Thin c :3ec cimuli :n : o tu: runneck of -reactor nower and feeduater fic. a ne 153 nower level. The turbine speod governce o 1:w
- the throttle valves to run closed.
- 4. The resulting increase to s e co:,d er;/ J i.e a m pressure is controlled by passing steam to the condenser th rough the turbine by-pass. I f' s t eu:a presaure continues to increase, pouer control or srtrety valves
'till coen to control the increaseo prorsure,
- 5. Turbine speed decreases to near nor:na] in approximately one minute and the intercept valves reopen. Throttle valves begin opening to maintain frecuency for tne
~
plant auxiliaries which nave remainea on tue generator. The four reactor coolant pumps remain in operation. J
'inen the react or and suc _." 5enerator n2'.*e ecualiced .
a'e 150 power, the reactc :' control ma.': oe placed on manual to reduce the pou ?r level to curreupond to the aun111ary load. Tito elapted time from losa of the electrical load to
'nteady ctate operation at 155 power letzel is approximately three r.inutes .
%W %
A, _g_.
1 t - f( L 7 'o1- c y c l ., Mta 1 At the beginning of cycle one , t':e fuel assern lias comerising
- ,aten. , 1, 2 and 3 (177 assemblien) "e loaded n: o the reactor.
Taer e a s amblies ccmprise Core 1.
. i t. the conclusion of cycle one, t; pro ximat e l y ano- th ird (1/3) of t he asse:.blies are removed from the core, the remaining assemblies may be repositioned, and the assemb1les comprisinc 6atch 4 a re. '
loaded into the empty positions. The reactor is : hen ready to I bef: C;cle 2.
'P e fc11oeiing tables provide the data for the eyeles and b a t cr.e: of fuel as::emblies used in each cy cle . Tr.c cate s!'o:in is for 2 ") Ut for the first cycle and 245? r*!t for subsequent cyctes.
T 2l ^ !O - Descriotion
.t~
INel Cycle Length 5 Fuel Mass and Enrichmenc Data
!U Fuel Burnun D.ta iI P'tch ard Cycle Encegy Cutput e
1 0 ( e W
.. 1 r/ ;
TABLE 1 Cc r e Des i r:n Dc _. e__ ( At 2566 i?dt Reccter l'ouer)
' vt r ' r t't;cel Occlant Inlet Temperature, a 554
" ; ;rel Coclan- Outlet Temperature, F 603.3 Core Outlet Temperature, F 009 3
~
2,18'3 Core Operating Pressure, psig 0 7 :' + 7 :^ 1 A n ne.mb lies T tol *N=b tr of Fuel Assemblies in Core 177 .
'r.6>r cf 7uel Rods per Fuel Asse.nty e POS tra f r cf C:ntrol P.od Guide Tubes per Assembly 26
- ~;2r of In-Core Instrumentation ?ositions As ceably 1 c 'r T .e
~
' : r' Cutside Diameter, In.
0.430
- u. '!!:i e;;n es s , in. 0.0265
- - '. 0 , 71:ca, in. ,
0 . 'J 6 3
~ue
- A: e.mbly Pitch Spacing, in. 8.587
'..: Cc11 Metal /'.'ater Fiatio (Volur.a Bas ir. ) - 0.82 ct o ris.1 Zircaloy e (Cold h'erked)
S
~%
O NO d
iv, ' W1 ) T/.it!.R ?
~
T!P'"*AL A**D HYDRAULIC L .CIGIi DATA (At 2 5 6 f'. i '. i t Re a c t o r_._ Pow e r )
- m. " - 3 :'a r n d Fluid Flow at Rated Power o
021 :Icat Transfer Surface in Core , ft'
- 49,734
- era;c He.st Flu:c, Btu /h-ft 171,470 2 534,4'80 hc t:i um Heat Flu::, Btu /h-ft Averar;e Power Density in Core, kW/1 83 39 Averace Thermal Output, kW/ft of Fwl Rod 5.66
- c. :i .. .:n Thermal Outp ut , kW/fc of Fuel Rod 17.61
65A 1 r Clad Surface Temperature, i'
<eruge Core Fuel Temperature, F 1,540
- 1. : Feel Central Temperature at. Hot Spot., F 11,250 6
Tota. 7.cacter Coolant Flo'.:, 1b/h 131 32 x 10 s u - Flou (Con:rol rod guide tubes) 2.232 x 10
*)
C c :, . a c*. Area (Iffective for Heat Transfer), f t '- ,49,19 r.lle Unrecoverable Pressure Less, pc1 14.1 Cor: Ccolant Averarfe Veloc'.ty, fpc 15 73 0 ne c .- Vcccel Unracoverable Prescure Drop, p:. . ST.2 Co n l:"W: Outlet Tctperature at Hot Channel, F 647.1 P o we r_ 21 : r. r.' ':u t i on
' '-:-/Avera;c Pcrer Ratio, Radla] x Local
'; W :uclear)
- 1. '/ 3
- m/Atardge Pouer Ratio, A::ial (F; Nuclear) 1 70 0
11 ?c.ecr Ratio (F q 1*uclear) 3.03
*c:or Generated 'n Fuel and Cladding, y, 97.3 - . . . . . . . . . . w"%______.
1 l
. t . >, l'7' l
TAPLE 2 - t r,2 nt in u > '! )
o- "
._r_ r S* 1 Ca c t o r .
i' ?cr Peakint- Factor (Fq ) - 1 011
'Le. Area Reduction Factor (F g)
. Ir..tarier Bundle Cells 0.98 "eripheral Bundle Cells 0 . 9 'i
' ~
Local Heat Flux Factor (Fq ") 1.014 ii o t f.' p o t flax 1'n um/ Average Heat Flu >: Ratio' (F g r.uc and mech)
- ^ -
3 li r ,. . a n _m , . .,
% 1;n O'ce rpower ( f, of 2568r@it Core Power) i ll'
- .3 '.atic at Design Overpower (U-3) 1.55 EC ir. tic at Rated Power (W-3) 2.0 et= m
- c ~ :n t '.ans ' -
' . :: , ccunds/hr (*at 2351 Mit NSS) 10,020,000
. .ccro, psia ') 2 5 3 meeraturc, F 570 4
%e.
- /, l ' ,'f t-
'! n ', . ' "'
ikcLaar D uirn Data l 'a:c m :5.1 1 Volume Practienc 4 4 4
. s. . , rJ . ,Jn,%
. ~.c'ic ra to r 0.530
~--., .c e. .,. o,", O .1 O ^c Stcir. lass Steel O.003 Vold 0.012 1.000
~o t:11 UD 1 (EOL., First Core)
'& cie Tonc 93.1 M ~' 1*.:nr.aio r.s , in.
E':u '.'ca12at Diaceter 128,9
..' ' b.
' . c.)
. . c . . t ,. .=.,~,1.'..,
' . '.1 2-0 to U Atomic F.?.tlo
- 1. ; *.: 2 i l'.O'3 e m J 1y )
- n . 2.85
%t 2.04
! ~t 'o.
.' U'o t '.:ne . Dn'rn First Cycle (at 2335 IF:It core couer) 506 2:2 :1 ."ucceeding Cycle (at 2452 core nower) 325 gl ".dlation. TTz?D/MTU
..rct C:!cle Average (at 2335 0.!t core onf..c) 2i,liOO L Succeeding Cycle Avern,30 (at 24~32 I?cic coro 9 700 pct: r)
;< 1 r.ondinr, wtf U-235
. . .si ,. n,. 1f1-.1.or. ,.. o../uc..
n
, s, -
o . n i2/ o_ .
. - m ,. . . c -sp
.(Cora Avertse Flrat Cycle) (2.62)
_,o_
=
h.m.i . . . . . . .
;%:, 1911' TAELE (Cont'd)
"antrol T.ta Cor. rol F.cd Material Ag-In-Cd
.':unter of Full Leng:n CRA's 61
'crth
- of 61 Full Length CRA'.;
(A K/K Jg 10.6 Control Rod Cladding Material Tyoe 304 SS, cold-worked fger.- e !!eutron Flux Levels at 2568 Ndt (n/cm2.nec) 0.5 x 10,' Thermal (0 to 1.855...ei) 7 .ct 2.5 x 1014 t 3 e A
- '3--
'l i , LO71*
'l*hl:f.V. 4
" ...I:. "H!.Y COMI 0 !F.:1Tl: . I! A 7!i.:: : A T.!: , At:D Ofi W!!P.f0NS
-!'~ IIATERIAL f> ff.! S.'!: I O:'!' (1ochen)
Fuel ?elict UO (Sintered, 0 370 0.D. 2 Ground & Dtched) _ _ .96.$$ Theoretical Density
. 1 7." dich volume.
0.430 0.D.
~
Fuel C1nd* Zircaloy-4 Cold-Worked 0 377 I.D. - 153 125 Puei fiod Pit ch - -- - 0 568 "uel Accembly Pitch 8.587 activo ~.el Length 144 O ve r'.l i uol Accombly Length 165.625 Centrol .'od Guide Tube Zircaloy-4 0 530 0.D.
. t 0.498 I.D.
Inst rie:" 't.ation Tube Zircaloy-4 0.493 0.D. 0.441 I.D. Upac u C. c.; (8) Inconel-71P Stripe 0.036 thick 6 Int e rme di .v. e Gri ds 1.440 h igh 2 End Crid; 2. 8S0 h igh 15.5 lb/acsembly I'n d C ; ti r.. c Stain 1cco Steel.304 71c:t 1 cr Ga:: Plenum Top 4 Butt.om 5.5 Tb. . .1 ':12ddint- ic to ba free standing at declen oressure on a short.
- 1 cc:o at anprc:Grnately 7050F, not apot tempe ra ture averaged tn rcu. :. the clad . tall. This is the estimated hot spot temperature at tia 114'3 , pouer ' condition. ,
4
'~
1 M*.n : , Tt3LE S Conti c1 Rod Au: enbly Data It ot1 Data 61 Ih::ber of CEA
!! umber of Control Rods per Assembly 16 Outside Dia.T.eter of Control Rod, in. 0.440 Cladding Thicicness, in. 0.021 Cladding I4aterial Type 304 SS 2 End Plug I'aterial Type 304 SS,.
Spider .'Ictorial SS Grade CF Poi.7en Material 80 ", A g , 155 Pciuon :: terial kleicht per Rod, Iba 5,.934 Fe='.lc cc :pling r!ateria! Type 304 Ss z 7 Lensth o;' Poison Section, in '. 134 Stro::e ol' Control Rod, in. 139 9 d s
~
~ a.7 , L ;1 TABLE 6 Axial Power T,hnning Rod fu r e mb ly DM i Iten Data Mu.~.uc c of Axial Power Chaping Rod Ac::cmblics 8 -
f Hu:yer of A::ial Pcwer Shaping Rods pec Asscebly 16 Ouca; de Diameter of Axial Pcwer Shaping Rod, In. 0.440 Cladding Thickness, in. C.021 Cladding Material Type 304 SS, Cold Worke 2n;! Plac Material Type 304 SS, Annealed Poicon Material 805 Ag, 15% In, -55 cd Spi ne - !!aterial SS, Grade CF3M Fen ?.l e Coupling Material Type 304 SS, Annealed ( Len,",th of Poison Section, in. 36 Stre' e of Control Rod, in. 139 e e s 4
't l
l
*IL r * ,' / , 1 ,
r TABL!: 7 Burnable Poicon Rod AL., mb ly Data j ': - - Data
' un:be' c:' P. urn ble Pcicon Rods Per Ac: 'nh ly Lo :.o 16 C utl_ c;e Dicteter of Burnable Poicon Pa d , in. 0 . h .iG Claddir.C Thi clcness , in. 0 . 0 P; Claddin;; Material Zircaloy-4, Cold Worked End can Material 7.t realoy-4, Annealed Poicon Material B q C in A1 0 23 lanGt" c. Poicon Section, in. 144 S. cider .aterial SS, Grade CF3M Couciit 4 ihensnisra Material 'R/ne 304 SS, Annealed
( Ei.C.. ;/a 1.25, 1.'. G.c3 ~ D e I
' 1 :,' , 197i TAl ti,1: fi Orifice Rod A:::,e m!,1 v Data l' n Data
':umbe:' o.' Orifice Rod Accemblies
- 120 l'u .Se :' o f Orifice Rods per Assembly L6 Outc!de Diameter of Orifice Red, in. 0.480 Orifice Rod Haterial Type 304 SS, Annealed Spide: Ilat.erial SS, Grade CF3M Cat.plinG Mechanism Material Type 304 S3, and 17-4 pH conditian H 1,100 Len g'.r, o !' Ori fi ce Ro d , in . 7
- (. 4 I e 4 kg i;;t y , l ' .*,7 T.13 LF. ^. E:: cess Reactivit / Crr.ditions (at 25Ga tTrit)
~
~
3rr ':'*;' "ultinlic2ticn(") e nre u, IC F, Clean 1.244 J. ". Clean, Zero Po.ter 1.170
?. ? :c , Clear., Full Poter i.15h 4 .et, Ft:11 Power, Equilibriu.r. 1. 109
, Xenon and Samarium Sintrle Fuel Assemb1v
.: o: 0.77 Cojd() '
O.87 (a) *i ra r c./cle at beginning of life (DOL), (b) 5cced en highest probable enrichtent of 3 5 wt. % U-23 5. (c) ' ar;?r-tc-center assembly pitch of 21 in. ic recuired - for :.C Keff in cold, tinborated water with no xenon or
.:: . ur. .
e f w. M
,O M s
- / . l' s t
i TAIM.E 10 *
~
Rettettvity Cont rol lit ::tribut ten (a) C AX / 7. _. - * ? 113 *: Pv Soluole Boren
~
a Medorator Tempe. ature Defic i t 3.4
. c. Equilibrium Xenon and Samarium 35
- c. '?uel Burnuo and Ficsion Product
~
Buildup 9.8
- 2. Controlled by Burnable Poison Rod ,
O n r.ano lie s (BPRA) c- Fuel Burnuo and Fission Product
~
Suildup 5.8 3 yg "rriled bu TJo rable Control Pod 2:ferc2ies (CRA) Transient Xenon 1.0
- n. Doppler deficit (0 to 1000 rated nower of 2452 MWt).
15
-- c. ifoderator Temperature Deficit (0 to 155 Rated Power of 2452 NWe) 0.8 Dilution Control 0.2 Chutdown ilargin 1.0 Tc: 21 Mcvable CRA Mequired 4.5
- 4. g. .11 Tele CR A orths a 7ctal CP.A Horth 10.6
. Stuck Rod Worth 25 e Minimum Available CRA Worth 8.1
'. Minimum Movable CRA Worth (b) 6.9
( ' ' 1 : c '; cy cle only at 256o IOlt. Eight APSRA worth 0.4-0.6l3 Ak/k not ocluced. (cibflects trancient xenon and dilution control. .
~-. .
I i m W
s m.
. ,ii.a
. n r .u. s .i ce i ..w , n n n .e ., r n,roi nnq i.!nnth I F i --- *. C > c l.? .
- g e t.: . * .' t
('c n Ccnditions EC L Scron Level:, e-- 1.. 'c i:: , R n,.c = 0 99
- c. ?!o CRA in 1 ,511 7 t) . All CRA in 992
- c. One stuck CRA 1,119 -
2 .. :: , Cero Power k ,, = 0 99 e.4
- a. :o CRA in 1,553 ill CRA in 493
- c. ^ne s t u c!: CRA 7133 3 : c '. .ted Power, k = 1.00 eff s.
- a. :: C??, in i , a...1 a
- t. .cnon Transient rods in 1,233
- 4. n ? asea Pcwer with Ec;uilibrium
. c r. :' , k -..
, g ,, = 1.00
- t . :o CEA in i,00 u 7.enon transient rods in. 933
~5 h c. ' 3ated Power with Equilibrium
. C= , k e .c .,, = 1.00
'o C:?A in 003 t, .9nen trancient rods in 883
- 6. dc cc:' '! orth ( Q k/k)/ ppm
.2 .- Het -
1/100 a rela 1/75 t '.-
- /, . .
- TIJ!LE 12 Moder 2. tor Temoerat ure Cce ffic ient
~
- enditions
- n!)'.31 critical conditions (hot full crtar, clean)
- a. 2oren concentration, ppm 1,233
- b. CRA inserted worth, %Ak/k 1.0' '
c Barnable poisort worth, %Ak/k 5.8
- a. 'oderator temperature coefficient , - 0 . 'l
! 10~ (3.k/k)/ F]
Val ue ci' =cderator temperature coefficient n ed in safety analysis, [10- (.%/k)/ F) - 0
- ac a r- :w; camperature coefficient at end -3,0 o l' ':auilibrium fuel cycle,
[ ~(i:/k)/ Oil ] t i-: ode rate r tetoerature coefficient at - '? . 6 t- . ci first cycle. [10 (L\k/k) /*F3 s e 1 1
%'"k
% \ k s M 6 -
/
- t b ;: , l' q1 TABLE 13 Performance vs Pumos In Service 2 Punpc* 2 Pumps Dur": '? r o- at in g is Punos 3_Punos (Sac.e Locc) (2 Lcces)
Max ma Pewer .1 100 75 46 h5 Reactor Flcw -5 100 74 46 38 Steam Pressure - psia 925 925 925 925 Stee Te perature - ? 570 570 570 570 "Oceraticn with two pucps in a' single loop is permissible only after p t :'r4 i:utdoun and bypassin;; of interlocks . Operation in this mode 13 t, / 'unual control. I G S I y = l %
, __ . .y . _ . . . _. . .
- - ~ ; 1 .
s . >
\ '
s N ,
, ,\.
.) \ r ~.
-- , i,
, , , ,.. 7. ,
n f 2 . e f 3, ,. . F x , s
,s -
i g
.. t
+
g .k t t
'\ t '
s . .,
' s s: ,
1
-t TABLE 14 , .
it .
. s
, $ s 2-Fuel Cvele Luncth ^
e s' ' ' L = i a
..s
- ?.::te r Full Pom>r CdpacLty Calendar - -
- c1 Ec :. er hys .-- Pa c ta r. .
Da rs t'
. s a
( g n. ,: 2,C6* O.8S 544 s w 2452 325 0.35 352 , t-0.85
~
- 2452 325 3S2 .
's \
~
2452 </ 325 0.C5 3S2
/
~
2 d52. $25 , o.85 , 382
. r
.a.co
/.c. ;,-, ],,._ , , n. r;)c ]
s O.e.; vp -- 4 t gW
.s
)
- . s .
Y J
~~' .Md, co'm.umed ir. atartiup pe riod'; 479 days 0 0.38 C.P.
i
;-. %:in;; ecmepi'cla,1" Ope ration -Given ca'&ndanf days .
* /
f 1, ) "
-^^' >
3 , Y s ' y t
> _' t
}.
a6* i E.. . s , T '" g ( 'g - # 1
' s %
G
< g M b
a fI k - i; , .
.t g- t ,. ...N- 7 j -
' 1
* . \ ' 's , b N
'.J 1-i r
.g
_. --- q '
, 'j ,
== - * , , '( .
, < v ,1
$ / .
'v ',') '
[
, - ', j .[ 'M r. f.~ ':, '
~.,. ' g.
.g' t .
. ', )
h*
.~
,;_ , ,E
\ L '~ ~' g- t'- .4. l
;-f 3 , . - xl.. . . ... 4. . . -
s
. : 1;/ , .1071.'
~
) 2, TABLE 355 Fuel Mass and Enrichment Data
. Installed Removed as Scent F'uel Weight of Pu Tu U h 'leight Enrichment Weight Enrichment Kg of Pu-239
' : :' ::: cf U G U-235 Ke of U G U-235 and Pu-24)
- .25,964 2.06- 25,297 0.o10 133 2
- 25,585 ~2.72 27,'304 ~0 911 179.5 27,8is "3 5 26fli8 O.9h5 136.8 '
L 25,9d4 3.22 , 24,968 0 905 ~175 2 27,i'97
~
5 28,281. 2.91 0.978 184.3 h e i 4 i .,. I
\g
, 1 i
ii: ci , ! '. s ,' 1
- 4 TABLE 16 Fuel Burnup Data No. of Batch Average Average Burnup z'a tcj] Assemblies Burnuo (IG1D/IITU) (W4D/L?TU) 1 56 -~15,81i8 '
I 2 61 25,900 t 1 3 60 ~35,093"' ) 26,257
~
h 56 ~3i~,668 5 61 ' l'7 J28 s e e t 4
\
' M ;. 1 r i'. '
TABLE 17 Batch and Cycle Enerev Outcut (Trillions of Btu .1012) Cveles 2 4 5 Tota- - n :. - - 1 3 1 32 70 33 7
~
a 33.99 20.99. 59.9
? 23 91 23 22, 21.41 65.5 1- 20.75 25.64 20.96. 67.3 5 17.93 U . 71 20.S4 53,3
~
' M a:1 96.60 "h11.97 611.98 d5.67 ro.88 292 9 t
l r _Tabl7 18 On e r.it l er ' . ' <.it '. ta t i onc 1. 2::0200 nlant 20 otharwisa specifienlly provided her<tn, t. n" chall ba cparaced v:ithi n the Tach.ni a::1 appandad
;o :'uel perfe to the r.ance. USAEC issued operating licencedoecir!. cation;
.inich apply The celott3:!ER 2.0 and during curing normal steady ntate operacian shall not be transient not be belcu 1 30 as determinec by the W- 3 heator abnormal t ransfer operation shall correlation assuming the "aa;:! mum design" mcensnical and '
r.uclear conditions set forth Final Safety Analysis Report. in Section 5 2.3.2. In the 3 During density nower normal steady occurring state in the operation the maximum linear
.w/ft. fuel snall not exceed 17.6 d
, .ransient I!ooperation.- central melting of the fuel shall occur during 4
.ba fuel assemblies
- ,caccur2 c shall not be subjecccc to an external Lien or above 2500 psig during transients.a'Hoove 2285 psis during cta ve r, n _ncients resulting in prescu.~es greater than 2500 psig, Juar.
La 2750 csig, can be tolerated not to e::ceed once per
' 2 Cual acc'emblies shall be ocarated cuch ull t:
c' urn-up of any fuel assambly doec notthat the peak
. cCM:izid/iitu . ~ exceed u
' ace tor water quality lilai cu shall be:
(a) :hzimum limit 0 tate opuration:at rated pracsure t'or uo: mal steady
- 1. Chloride, ppm ~~
O.15
- 2. Fluoride, ppm 0.10
!!ydrocen lon content, ph at 77F 4.8 - 8.5 4.
!P drogen ac2li ' std. ce/ liter I!;O
/
25 -W ( c. ) ihritum tnan normal Limits nteady of Ratedstate: Prancure for opecation at other
- 1. C'.:lorlde, ppa 15 Acc*utulated time acove 0.1 ppa - 2 ':cok/12 conth period-
- 2. Flucyld:, ppa 1.0 Time above 0.1 ppm rieek/lO conth neriod h 7a.
- 6. (b) (Cont'd) 3 Hydrog.r. ion content, pr' at 77F g .
u,te out. cide r.h oi,,4 m o ,.,, c-> - 0- - e, hourc - e occurr ce (c) '~ hen the r 22:or 15 not ;reccuricea, reactor 'lc te maintai.ad within tne Col to'. ling limitc :
- l. :'or.ai Conditions:
Hydracine, ppm Chloride, ppm Fluo ride , ppm Hydrogen ion content, pn at 77F
- 2. Other tuan Normal:
Chloride, ppm Fluoride, ppm Time above 0.1 ppm for c::lorida and fluoride 2 weeksfl2 months Time outcide hydracine range - 2 wee cs/12 mo (a) ::o te : c.ater Chemictry sampling and anclytical pract wrec anall be in accordance with ac Stand.i ed Methodc ( ASTB1 or Standard . tie thod.
'c.'aner .;nd Hacte Wa ter or BSM dater Chamic manual (BAW 1332 Rev. 1, dated Septemtcr or ac subsequently reviced). During peri.
when chloride and fluoride above e:cceed C Og muct alco be 1tmited to 0.1 pga.
- 7. Ti:o 1svel of reactor coolant chall keep the core cove:
du in' operation once the fuel hac been irradiatod. C. D.:lcw the coolant temperature range uncociated with nc nouer cp2 ration the rato of change of coolant tempera: cimall Le to ;reatur tnan 2: 1000 F/hr.
- 9. iturin:; r':ac cr ecoltioun, the cladding chall be maintai in compraccion unLil the clac temperature in below 42-2 Thic ma:t :.e acco mlici:cd by maintaininc; t.:e reactor cc p r 2 c cu r<3 abc7: tim locier ::rancurica lon limit. This 1 m
10 ea;abllai:ed Ly a lln connecting 1540 pela at 532 F
,.u
= . ,r, n 3.~- -a u, . ,. =. o .r .
-stt- ?.evised Apri
. -Q , 1 771
. r- FUEL ASSE;.mty l
?' *I h
- [/,[.. ,#'t. ,o ___o o' h,'>;%
f .'~- N,N A
/, A ,7., .. , - O4 : .;#r
+ , ;O/'%h
/;/
f O
' o ~ ' * ' ' ' ' 'o ' ' %y,%
tG* iO f i _13. Tie g l i rg i --l -- _ 7__o' \ ' (8. I@i lGI #GE 3GeeeGi i e \<
, O Q ,593 g o j gypT;gg , g,7,g.] g CONTROL RCD t,PP -- -- - * \' __
ASSEMBLY LOC ^* TION Of f@t* tot a
/I',j.s_@**'Or s
<Gk 49 e-?o \ \ s 1
' , , ' , , , , .' ' <0; k3) 1GilPQi3(33:;G).i '
7-yW- -6 i - e.34 ;c )- .3 - n ~. n ,' , )*I g i-
,, 60 !? # 61 #G8 161 i s N laccaE .'isTaurasaT
%m.i'I[!lSt*IQt r4.ci.uir.isi3,g,,g,,,g,&O.go
. ,* . 1 s
rst-@ 3.e, . te, own._e, sec.
\ .,. *ih-.
- s: :
.S!3 iqs- ---- ! (-)',_.
g
^g ;.___, __ l
/f/ / '
/
/ ,-
'oc = "
, -h,s ,so_i -
h0:*,G4 :
~~ s :.tvi . t e s s.4 e.// e i,
'v .,'
y,,./@.,c.[ g E tO; 'G,, lmo :i~jsa o A, # ', .
- REACTCR VISSEL f ~s
\ 's '-
%',0 t,,
s t.e
<]O o ,* p/ /
.f.-r f,d ,
'I '_ O -
% THERMAL SHlELD g
N// -[jj
\
I
- CORE BARREL SURVEILLANCE SPECIMEN HOLDER TU8E O
i r Figure i l , Core Cror,s Section r. 9 l l ( i. p i i- $ E.._
. . . - (1 l
1 9 l ' 1 i :
}e l l I
- j. '
i l _ _. I.
! # : i l l I e.Mt. --M.
- 4. . I ! .
- l. I 1
i i l-s .
' 4----', 1 j i .
S n" I C ., 'a '+- l> i DATC'iES 1 & 2
,1 1
i i i. i; P l; .'1 i . ,_ s
- 1. .
s t i, 4 . l-i e l i. A l l l L.--._. I 1
; i I _
1 . I 1 t f r:r ~. y.~ [ P.GLI:di4 FRY CO?.E LCADIf.'O ZO!TE EDUi?DAriTES (CORE I) [ t
^
t9-
- - . - , v-- y -. , _%
.. a ; ,
. J. G 8 4,CM.<ae :ra.we l
MG- h u m . v.o Fif f"sc
\{h. ?, [.-L 1
, t . . M, a
t I neu:n,,a se.zn 8 % g,~ ., .- . > . Llyn; ,o ,
, P -
m 1 U-3 urii W
?.:'r..w.=.s:i i ".,7,w: ~l:. i c:.3 sn:a c.2:a\ h,1;i'i ,
- j. ,. . .
'J h,.%. . .~:M. F.f.,.u,.ili s -, [q!.nf i f y
... iIiJ .
.%" l::'/ 0,:.-_ K:y1 :)- s.j-. 83, 'Tt , e, [ rd erre ?, -H 4 -
.m.e g so. na
- e. .n.,,s m.t..~u,,g . s' a< L.4 ; h< (a ip; w..; g. ; -
. c , p:
'g, .p
.,!;1 s d 'wSM.
.h!
. 2.Y.I fl.jit.:,
l i s rig hljg l 1/-' ---' -7_? j ,j y l i a~ j d( - ml Ka ,verw , . - --- - RP[rp[s:b1 t
'}
glI;$ft,
?
li < l
' ? l g 4 .:l llj
. .. .. .. witargeuir sextn susu iij
- i. l. r. k s{ t',(r8l I' ' g... ...ij;}
gi .: :r. 4 l:f!f cs k$l k ifd i jlhaN I hi i 1 43
- , i t f1.!.; l.
54, l. # e. it 2; - f g, a. if N Q..6.*?q!*k}!k{'djl4)! ac:st u ,rntafica : 63f tunt 4A. j ,g e ,h y l;.b 7' 8 "ld
- j 1 !g
. r 4.. ecos7 pot nos 4 ,i !, t 6 d; *
. -. 7 -..:.l..i.,:. M.,.. . M,. / cuset voac i.t r
.9 .u+
- - - - . m .. r s
; g,4 1 i, , :h:
- 3. . , y . ), )3, ,
, .-: .. -l..- .i t ;. . 4 .4+.s. q
. . - . , f p p, y I t a .s.
. !. g.3,l y
I --- " ! r- h *'.*.* ;-! h .t-i-5 !i:..4 s:t:.scte d [ sprL peo IT e84
.r...f.-
MlI$ll8*8 IL
- d-..'EI, . , , . . l.. .- u W l...,9 t
.. .f. .
l..w ...t
..s... .t .: 2 > i . . r I t .Lj '..s lJ.8. * !.;
l, [ \ 'l
' , Gl :.
lg ' ,i, , p ;j ,, f ,,s]* s y. 4. a.L. . . [.l..w
- r-b,,. e ti i I cr o:s sccison %.
, .3 n' ; *. k p3. 41 ) '+ ,.
., s fff$
- i. ' f *, .3i . ,-l :. a.0;'......i r [ ,.' , .'-
l
.l1 l 13e
.v.'i'!
ta
- I J.- la
- u.l 1
s I !) a1.':f]' . . :c -l - .:q , i_9 @... T _n , towragno... . . . _. 7 .. IlgUfC 7' C . :.,' eb
- I ,)
Fuel .sserbly s%%f 8'Vw('s taf ar/s TUEC CC*.44 ( r :C=
-5C-O
I a 1'.
,. = :::.r-(,. -i'
.. -. t I (/;
/ ..~; . , :." .
c:r;r L :iG s - ~;- r/. r/ - '. , .! 1
, ;/- sl t. ; i, ! if.
= e ,-
f, . n >/s t I #'
', ~'
~ .: , .
r I $
- 5. _ _.
4 I 4 g m:=, ,m. . :s ,=:, u:n l t
. .. .} .. .
.' s i a- .g
- Ir IGI..I "'
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