ML20236F236

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Amends 113 & 140 to Licenses DPR-71 & DPR-62,respectively, Changing Tech Specs to Add GE Fuel Type GE8 to List of Fuels in Core & Remove Limitations on Max Fuel Enrichments in Tech Spec Sections 5.3.1 & 5.6.1.2
ML20236F236
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 10/27/1987
From: Adensam E
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20236F238 List:
References
NUDOCS 8711020059
Download: ML20236F236 (12)
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Text

{{#Wiki_filter:_ 'q p. ~ s q op ' UNITED STATES 1 =8 NUCLEAR REGULATORY COMMISSION - o (~ tf WASHINGTON, D. C. 20665 - \\...a / CAROLINA' POWER & LIGHT COMPANY; et al'. DOCKET NO. 50a325 BRUNSWICK-STEAM ELECTRIC PLANT, UNIT <1-AMENDMENT TO FACILITY! OPERATING LICENSE 1 y Amendment!No.i 113 "

License?No.;DPR-714 s.

~1. The. Nuclear. Regulatory Comissionl (the'.Commissio'n) has fouhd'thatf:- A. TheapplicationforamendmentfiledbylCarolinaPower-& Light:Com'pany (the. licensee),datedJune 12, 1987, as supplemented.on' September:10.- and 11,1987, complies ;with the: standards and: requirements'of' the< Atomic. Energy Act of.1954, as amended (the-Act),L and:the Comission's rules andL regulations set forth in:10 CFR. Chapter I;: ~ j B. The facility will operate in: conformity with:theLapplication sthe. provisions of the Act, and.the rules and. regulations of: the' 1 Comission; C. Thereisreasonable. assurance:l(1)Lthatthe' activities' authorized and safety of the public,:and (ii):without endangeringithechealth by this amendment can be conducted .that.such' activities will.be-conducted in compliance with the:Comission's Regulations;. D. The issuance of this amendment willnottbe(inimical to'the! q comon defense and; security or. to'the health and safety of2the' j public; and' E. The issuance of this amendment-islin:accordance-'with 10 CFR Part.51' of;the Comission!s regulations and all applicable. requirements have been-satisfied. i 2. Accordingly, the license is amended-by changes:to the Technical ~ .. t SpecificationsJas indicated in the attachment to thisilicense amendment;L fj and paragraph 2.C.(2) of Facility Operating License.No.'DPR-7,1~is hereby amended to read as follows: 8711D2OO'59 871'd27 ~1 PDR ADOCK 05000324

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I' C. j .}) .1 6:, > ;n l" 3; j;g n 4 p l re L, ATTACHMENT TO LICENSE < AMENDMENT.N0.J113: . n,s 02' FACILITY;0PERATING LICENSE N0'.LDPR-71 V N '4-: b w, : DOCKET.N0.450-325: 4_ a ')

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. =.. o !... ? ' Replace: the following pages of the Appendix.' A Technical: Specifications withL b

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r /(SSEP-1-105)- + 4 ' 5'. 0 DESIGN FEATURES . 5.1 " SITE ' EXCLUSION AREA-l q 5.1.1.The exc1'usion area shallbe as'shown in Figure.5.1.1-l'. . LOW: POPULATION 20Nr'- .[ -f '.l ' 5[1.2l The' low population. zone shall be as shown in1FigureJS.t'.2-1, based: en; O the information:given:in Section 2.2.of the FSAR.- l 4 SITE BOUNDARY 5.1.3 The-SITE BOUNDARY shall.be as-- 1shown in Figure 5.1.3-1. ForTche purpose ofLeffluent' release _ calculations,.the boundary for atmospheric releas'es is,the. SITE BOUNDARY and the boundary for liquid releases is the-SITE BOUNDARY prior to.' dilution in the Atlantic' Ocean. H - 5.2 CONTAINMENT' t CONFIGURATION l 5.2.1 The PRIMARY CONTAINMENT'is a steel-lined reinfov'/'. concrete structure-composed of a series of vertical right cylinders 'and;trutt ated-cones which form a drywell. This drywell is attached to a suppression chamber;through a series of. vents. The suppression chamber is s' concrete steel-lined pressure 4 l vessel in the shape.of a torus. The' primary containment has a minimum free ~ air volume of (288,000) cubic feet. DESIGN TEMPERATURE AND PRESSURE f 5.2.2.The primary containment is designed and shall be maintained for: Maximum internal pressure 62 psig. a. ,i b. Maximum internal temperature: drywell 300 F. l 0 suppression chamber 200 F. .{ c. Maximum external pressure 2 psig. 5.3 REACTOR' CORE l FUEL ASSEMBLIES ~ l 5.3.1 The reactor core shall contain 560 fuel assemblies limited to the-following fuel' types: 8x8R, P8x8R, BP8x8R, and CE8. l l h h

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. CONTROL RODi ASSEMBLIES.

6"M.y ,o . 5.~3.2: TheLreactor. core shall'containL137,contreifrod. assemblies,-..each?- W > [, ' consistingfof c al cruci form iarray, of ; s t'ainless t.s tee 11: tubes : containing s.. TMw ~ /- approximately143inchesor.boroncarbide,fBjC,powderLor'hafniumiabhorberd 4[ L i "rodsfsurrounded by a. cruciform-shaped. stainless: steel. sheath.. ~ m; a ,7 ,{S s -5.4E/ REACTOR COOLANT SYSTEM-i s y

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b , ;DESIGNTPRESSURE-AND TEMPERATURE: 1 -y .e .r. . I. [ -.. c5.4.lg The' nuclear boiler'and> reactor. recirculation system isidesigned?and W,

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I. N In accordance:wi$h thh code' requirementsispecifidd lin[Seci: ion [4% of ?

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the FSAR, with allowance forfncemalidegradationi:pursuantito;the .( g ~ 4 N% . applicable Surveillance Requirements.'- x - b.- For a pressure-of 1250:psig,.and? ~ , q e, c. For a temperature of 575 FL '%l m e VOLUME-p l' 5.'4. 2 The total water and. steam' volume of theireactor: vessel.and-recirculation syst'em-ts-approximately'18;670; cubic' feet., . 9 m 5.5 METEOROLOGICAL-TOWER LOCATION: ? r 2. L 5.5.1 The' meteorological tower shall.be located as-shownsin Figuref5.1.1-1.:. I y ( I k a.= Ame'ndmentiNo.,- 75i1133 BRUNSWICK'- UNIT 1-5-41 ^ s s i.[] ,Q, r h;g h. g,g-r ~ r gJ ,...r. t .c 1 r c ..i

c 4., sj h ;,, s '9. 3 xv 2. '?(BSEP-14105)? C 1 w q 'c. J-DESIGN FEATURES 43 t ,a i j 5 5.6' LFUEL STORACE e > CRITICALITY , 3.. 5.6.1.1 The new fuel storage racks. are.' designed -and shall be:maintainediwith : sufficient' center-to-center. distance,between fuel assemblies'placed in'the'. 49 storage racks to: ensure a k gg equivalent:to.lessfthan 0.90 whenLdry;and less ,: than 0.95 when flooded with,unborated: water.. tin order to. meet these limits, new. fuel assemblies shall"have an infinite' core geometry lattice r multiplication factor l'ess than or equalito'1.31'at.20*C.; M f 3 4 5.6.1.2 Thesp'ent. fuel:storagerack'staredesig'nedandLAhal'1lbemaintained/ ~ n. with sufficient' center-to-center' distance between fuel-aesemblies' pla'ced;in.D ~ r' o l the storage racks to ensure a'k,gg equivalent to.less than'.-0.95:with the'- d p storage pool-' filled with unborated. water'withF + PWR-fue1Lassemblies with almaximum infinite core g'ometry lattic~e e s. multiplication.factortless'thanLor'equall to l'.411at: 20*C.- d BWR fuel assemblies with a maximum infinite core geometry;. lattice l b. multiplication' factor less than or equal to.1.33 at:20'C.L j ~ 5.6.1.3The k,gg for the unpoisoned racks; includes s' conservative; allowance' d of 0.5% ak/k for uncertainties., The k,gg calculated.for thefpoisoned racks' includes the sum of all appropriate' biases and the root-mean-square-(RMS);of the uncertainties. j 4 DRAINACE 5.6.2 The spent fuel storage pool is designed and.shall be maintained.to prevent inadvertent draining of the pool below elevation 116'4".: CAPACITY 5.6.3 The fuel storage pool is. designed and shal1~belmaintainedLwith a; ~ h storage capacity limited to no more than;160 PWR fue1 assemblies-and 1803 BWR' fuel assemblies. g i L5.7 COMPONENT CYCLIC:0R TRANSIENT LIMIT. 4 5.7.1. The components identified in' Table 5.7.-1-1 are designed'and shall be - maintained within the cycle or-transient limits of. Table;5.7.1-1. o q 1 l. s ! l'j BRUNSWICK --UNIT 1 L5-5' Amhndment No. p,113 : .1 r; 1 +

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c, sBRUNSWICK: STEAM' ELECTRIC) PLANT,oVNIT.2: m ',/ YOFACILITIOPERhTIN'GULICENSE] 5 ' MENDMENT: 1AmendmentTNod40( l ' i X, M ?LicenseiNo'.7 DPR;62 ? 4 g, :.; y a b; >> ^ e s ~ -1 ~ -1. TheNuclearRegulatoryCommission!(the:;Commissi.on)jhasifoundsthat:: A. TheapplicationSforamendmentCfiledbyrCarolinaioNrfailighMCompany-. P .(the licensee).Ldated' June 12,L1987, a's; supplement'ed;o'nl September l10,' 7 11,'1987, complies with the standards andfrequirements;ofs the Atomic. p'h Energy Act of 1954, as-amended'(the~Act), Land the; Commissions rules) and regulations set;forth in:10LCFR Chapter I'; f n ] -B. The facility will operate. in c0nformity:with the lpplicsti'o'nk' thec provisions-of:the Act, and the rules:and regulations of-the? .1 W <' X Comission; .p A m.. [ ..... Y C. Thereisreasonable. assurance:j(iht$tt'.thetactivities; authorized f bythisamendment3can'beconducted.withoutl endangering;thehealthW f andsafetyofthe1public,and(ii)thatjsuchactivities;willibe,LL' conducted in compliance with;the? Comission's: regulations;4 p n D.*Theissuance~o'fithisamendmentwillnotlbein'imicalt'ojthei ~ common defense and security or to the healthlandfsafety of;the; a O public; and E. The issuance-of this? amendment islinLacco'rdance with 10LCFR Part?51l .j of the Commission's / regulations and:all 'applicableirequirementsi 9 have been satisfied.- ~~ o j 2. Accordingly, the license isiamen'ded b'/ changes to the Technica1L 4 y L Specifications-as indicated in the attachment' to thisL license amendment;e ' A Jandparagraph'2.C;(2)of-Facility-0perating: License.NotDPR-62Ds-hereby. amended to read a's follows: i~ s e ~ L gq q 1 g ,6 } T m m

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. v j 3- { f 1 .] (2) Technical Specifications - j .( The Technical Specifications contained inLAppendices A'and B,.as.- ~ revised through-Amendment No.;140, are hereby incorporated in the-y license. The licensee.shall. operate theffacility in.'accordance; .j 1 with the' Technical Specifications. ,\\'. 3. This license amendment is effective as of Lthe date of its-issuance and - shall be: implemented within 60 days of issuance. .q .'FOR THE NUCLEAR' REGULATORY! COMMISSION .l ^ ?? l . Ili or G'. Adensa ',' Director. Project Directorate II-1:. j Division of Reactor. Projects I/II q

Attachment:

1 ' Changes to the Technical' + Specifications j Date of' Issuance: October 27,1987.l W t 4 t N 8 .tOf11:DRPR PM:PD21:DRPR -B D:P A

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I. PeplaceLthe following. pages':of the'. Appendix : A LTechnica10 Sp'ecifications with. L the~ enclosed pages. The; revised areas.are indicated byimarginal<linesi J. Remove Pacjes . Ins'ert:Pages [,',c j 5-1 5-11 ^5-4. 5-4' 525 5-5. -t -w I ( F 45 0 9 I ) l1]. ,1 f 6 4 .N i s , k _:- I, i ' 4 > g,- i 4 [.f!,' <3... b :: l: '- "g y __ __ __11: .___.______1.___ J_-_ nil _' D

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+ ~ ( 4 EXCLUSION AREA 3p 5.1.1iThe'exclusionareashall'.b$as=shownLin' Figure 51.1$1.'- %s s r 3.v < .o. iY 1 LOW POPULATION ZONE' b ~ W .5.1.2-The low' population zone shall.be as'shown.:in Fisurei5s1';2-11 i 4 9: W, b, SITE BOUNDARY: s..., e,sms o.4 ^ 5.1 ~. 3 TheSITEBOUNDARYshallibe-asLsh'owniin'. Figure'5.li3hl.ujFor:the, purpose (, of ef fluent ' release calculations, the :boundaryf for) atmospheric: releasesLis;.thec o m -SITE BOUNDARY'and,the boundary forfliquid releases is the/ SITE', BOUNDARY pri'or( q to diluti'on in thelAtlantic" Ocean.- s y., 15.2 CONTAINMEN'T-g j. m w CONFIGURATION ,.[.- 5.2.1 The, PRIMARY CONTAINMENT is'a-steel-lined; reinforcid c'oncretesst'ructure' truncate'lconeswhichi composed of a series-of vertical right'.cylindersJandi a form a drywell. This.drywell 'i~s. attached.to la ;suppressiori t chamber (throughTa; 1 series of vents. The-suppression' chamber is a concrete,Eskeel-lined pressure > '] vessel in the shape of a torus. 'The primary containmentLhas.;aimini. mum free air. volume.of 288,000 cubic feet.- .m DESIGN TEMPERATURE AND PRESSURE

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^ 5.2.2 Theprimarycontainmentis-designedand'shall[b'eima'ihtainedfor:! Haximum internal l pressure 62 psig. En ' O s. - b. Maximum internal temperature: dryvell 30d'F1.. L

Suppression chamb'er1200*F, Maximum external pressure 2 psig.
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U2 -5.3 REACTOR CORE ~ I L

FUEL' ASSEMBLIES'

[ 3 -5.3.1 The reactor-core shall contain 560 fuel. assemblies liniitedi oi t hei- ~ t J .following fuelTtypes: 8x8R,. P8x8R', BP8x8R,.: andiCE8.: y - r.l }: ' Amendment!No.Q91h10,d40e BRUNSWICK - UNIT., 5-1 1 \\Y' } f E-- -.i L

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=1, 7 'f f t.. '): y s' 4 1.-. ' ,.a(BSEP-2-106); j + m j ) b i O . DESIGN FEATURES 34:! s .f t- .5.3' REACTOR CORE ] - CONTROL' ROD ASSEMBLIES -c 5.3.2' The reactor core shall.contain(137 controllrod assemblies,.;eachj , h, ~ . consistingLof a cruciformfarray of' stainless' steel tubes containing1 l - approximately 143 inches of boron! carbide,;B C,ipowderfor? hafnium absorber 4 - rods' surrounded'by'a cruciform-shaped stainles's; steel sheathi N 5.4 ' REACTOR COOLANT SYSTEM, 9 ,1 DESIGN PRESSURE AND TEMPERATURE. j

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) 5.4.1 The nuclear' boiler and reactor: recirculation; system is': designed?and -e ~ ajf shall be maintained: m 'a. In accordance with the.codeLrequirement'2s specified i~n SectionL.4~.2 of: the FSAR, with allowance for': normal'degradationrpursuant.to thel applicable Surveillance. Requirements 6 Tis b. For a pressure of 1250.psig, and. -d 0 c. For a temperature of 575 F.' VOLUME 5.4.2' The total water and-steam. volume of the reactor vessel'and-d recirculation system is approximately 18,670 cubic feet.- i . METEOROLOGICAL TOWER LOCATION l-5.5 5.5.1 The meteorological-tower shall'be located as;shown in Figure:5.1.1-1. Liq .r. l-l' ,1 f !j;> h

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5.6.1.1 The new fuel storage racks'are designe~d'and'shall be' maintained with~ sufficientfcenter-to-center distance between.fue11 assemblies ~placedrin the; l . storage. racks-to ensure ai,gg equivalent to less;than10.90'when' dry.Eand,i.ess k than 0.95 when flobded with unborated water.1 Iniorder to meet these limits,

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.1 M new fuel. assembli'es :shall" have an infinite-core geometry lattice . multiplication factor less than'or. equal;to 1.31"at 20'CO y W d 5.6.1.2 The' spent fuel' storage racks are designed and shall be' maintained' with sufficient: center-to-centar distance!between fus1 assemblies placed;in; the storage racks to ensure alkggg equivalent'to less than 0.95 with thes storage. pool. filled :with unborated water: withs ' t -q PWR fuel assemblies.with a maximum infinite core geometry la'ttice: j a.

  • 4 multiplication factor _less than'orfequal'to'1.4,1 at.20*C' b.

BWR fuel assemblies with a maximumiinfinite core' geometry latticeL multiplication factor less than'or equal to 1'.33 at'20'C-J 5.6.1.3 The k for the unpoisoned racks' includes aJconservative allowance'

i of 0.5% ak/k f,ggor uncertainties. The k gg. calculated-for the poisoned racks-q includes.the sum of all appropriate bi,ases and the
root-mean-square (RMS)'.of' J

the uncertainties. f DRAINACE j 5.6.2 The spent: fuel storage pool is designed and shall.be maintained to-prevent inadvertent draining of the pool below elevation.116'4". 2. CAPACITY 4 5.6.3 The fuel storage pool is designed and shall be maintained with a' a ~ storage: capacity limited to no more than 144 PWR!fdel' assemblies;and.1839_BWR- [ fuel assembiles. d 5.7 COMPONENT' CYCLIC OR TRANSIENT LIMIT' 5.7.1 The. components identified'in Table 5.7.1-1 are designed and shall~be i maintained within the-cycle:or transient limits of Table 5.7.1-1. g .1 xj O BRUNSWICK:- UNIT.2 5-5 ' Amen'dment-No($7[140; a. o .}}

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