View source for SBK-L-17156, Response to Request for Additional Information Regarding License Amendment Request 16-03 Related to Alkali-Silica Reaction

{{Adams
| number = ML17277A337
| issue date = 10/03/2017
| title = Response to Request for Additional Information Regarding License Amendment Request 16-03 Related to Alkali-Silica Reaction
| author name = McCartney E
| author affiliation = NextEra Energy Seabrook, LLC
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000443
| license number = 
| contact person = 
| case reference number = CAC MF8260, SBK-L-17156
| package number = ML17277A336
| document type = Letter type:SBK, Response to Request for Additional Information (RAI)
| page count = 12
| project = CAC:MF8260
| stage = Response to RAI
}}

=Text=
{{#Wiki_filter:Enclosure 1 to this Letter Contains Proprietary Information Withhold Enclosure 1 from Public Disclosure in Accordance with 10 CFR 2.390 October 03, 2017 10 CFR 50 Docket No. 50-443 SBK-L-17156 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Seabrook Station NEXT era ( SEABROOK Response to Request for Additional Information Regarding License Amendment Request 16-03 Related to Alkali-Silica Reaction (CAC No. MF8260) 

==References:==
: 1. NextEra Energy Seabrook, LLC letter SBK-L-16071, "License Amendment Request 16-03, Revise Current Licensing Basis to Adopt a Methodology for the Analysis of Seismic Category I Structures with Concrete Affected by Alkali-Silica Reaction," August 1, 2016(ML16216A240).
: 2. NRC, "Request for Additional Information Regarding License Amendment Request Related to Alkali-Silica Reaction (CAC No. MF8260)," August 4, 2017 (Accession Number ML 17214A085).
In Reference 1, NextEra Energy Seabrook, LLC (NextEra Energy Seabrook) submitted letter SBK-L-16701, requesting an amendment to the license for NextEra Energy Seabrook.
Specifically, the proposed change revises the NextEra Energy Seabrook Updated Final Safety Analysis Report (UFSAR) to include methods for analyzing seismic Category I structures with concrete affected by an Alkali-Silica Reaction (ASR). In Reference 2, the NRC requested additional information to complete the review of the NextEra Energy Seabrook License Amendment Request 16-03. Enclosure 1 provides NextEra Energy Seabrook's response to the NRC's Request for Additional Information (RAI) concerning the License Amendment Request related to Alkali-Silica Reaction.
NextEra Energy Seabrook, LLC P.O. Box 300, Lafayette Road, Seabrook, NH 03874 *>f'."
U.S. Nuclear Regulatory Commission SBK-L-17156 I Page 2 Enclosure 2 provides the revised NextEra Energy Seabrook Updated Final Safety Analysis Report (UFSAR) Section 3.8 markup as referenced in the RAI responses within Enclosure
: 1. Enclosure 1 to this letter contains information proprietary to NextEra Energy Seabrook.
This letter is supported by an affidavit (Enclosure 3), setting forth the basis on which the information in Enclosure 1 may be withheld from public disclosure by the Commission and addressing the considerations listed in 10 CFR 2.390(b)(4).
Accordingly, it is respectfully requested that the information which is proprietary be withheld from public disclosure in accordance with 10 CFR 2.390. A non-proprietary version of this letter will be submitted under separate cover by November 3, 2017. If there are any questions or additional information is needed, please contact Mr. Edward J. Carley, Engineering Supervisor 
-License Renewal, at (603) 773-7957.
If you have any questions regarding this correspondence, please contact Mr. Kenneth Browne, Licensing Manager, at (603) 773-7932.
I declare under penalty of perjury that the foregoing is true and correct. Executed on October 3, 2017. Sincerely, NextEra Energy Seabrook, LLC 
-Regional Vice Presid e nt -
Region U.S. Nuclear Regulatory Commission SBK-L-17156 I Page 3 

==Enclosures:==

Enclosure 1 -Response to Request for Additional Information Regarding License Amendment Request 16-03 Related to Alkali-Silica Reaction (CAC No. MF8260) (Proprietary)
Enclosure 2 -NextEra Energy Seabrook Updated Final Safety Analyses Report Markup of Section 3.8 -Design of Structures, Components, Equipment and Systems -Design of Category I Structures Enclosure 3 -NextEra Energy Seabrook, Application for Withholding Proprietary Information from Public Disclosure and Affidavit cc: D. H. Dorman J.C. Poole P. C. Cataldo L. M. James Mr. Perry Plummer NRC Region I Administrator NRC Project Manager NRC Senior Resident Inspector NRC Project Manager, License Renewal Director Homeland Security and Emergency Management New Hampshire Department of Safety Division of Homeland Security and Emergency Management Bureau of Emergency Management 33 Hazen Drive Concord, NH 03305 perry.plummer@dos.nh.gov Mr. John Giarrusso, Jr., Nuclear Preparedness Manager The Commonwealth of Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 01702-5399 John.Giarrusso@massmail.state.ma.us Enclosure 2 to SBK-L-17156 NextEra Energy Seabrook Updated Final Safety Analyses Report Markup of Section 3.8 -Design of Structures, Components, Equipment and Systems -Design of Category I Structures U.S. Nuclear Regulatory Commission SBK-L-17156 I Enclosure 2 I P age 2 S E BROOK UF. A H c 11
* 11<u c n 1 1<L'>. Co:-.t f't)'\l 1:1.)t 'IPMD-: 1 A *t 1 Svsrr D sign o f C a t e go r y I S t ru tul'\.'S Rel'i i on 1 6 Sec t ion 3.8 P ai.ie 1 47 3.8..t.7 and Snn*e ill a n ce Rec 1 uireme n t<; Nor ma l qualit y cantrul t es t ing i s d i cu s*d i n ubsection 3.8.3.6. A gencr:il visual i nspe ti on o f th e expose d acc.:ss ih lc inlt!rinr a nd c xtc:ri o r su rfa ces o f th e Containment Fncl os urc B u i l din g will be peri o di cally c o ndu cte d as d i: 'L IS* *d i n 6.2.6.1. ll1c S1ructural foniioring Pwgrum for i n:.p.:ct i n g :m1cturi:s aOc.:tcd b y A.'R. *1 h e t ota l exrxinsion of t\SR-afli:ckd i s l imited l o l e t ha n the amo u nts spcdfied i n l"abl 3.8-18. 1'1:riodi *a lly , cfif y ing t hat A SR xpan s ion k Is an: he! ''t h..: limits i nc\.OCssary t o cnsur' struclllrJI p r , 1JX!rti s f ASR-al1i:ctcd 1rea' :u\' similat t o a n: as with n o c v i d cn c n f 'R. *1 he Str u c tural I\ f ,, 11iu1 ri 11g. P rogram al. has limits n SUlJCture d fom1ati\)1t fr o m . R on r t e expans i on. 
\\ ith i ncr asing l e\' of d fo1matio11. as d e 1cm1 i n *d hy ;111 analysi-;
of the se lf*s t minin" l oa d s, nre cla silied M Sta g.e l. 2. or t..l on i1.1ring criicrin for ca h structure
:w* i ncluded i n IJlC Stmc 1 um l M o nitorin g P r o *ram and i n,pcclion arc ddin *d l iascd on t he ana l ysis and l a *s itic.ition of each slru l ure. 3.8 . .J.7.I ST I UJ C'T U I U:: Pl<OGR A l\I T he . 1ru c turcs \1 on i t 0ri n&#xa3; Pr o g rnm ;, i111plem ntcd t h ro u g h p l ant il.l a i ntcn ancc R uic Pr ,1g r m. \\hi h i> on t he guidance p rm i dl*d in NR C R gu l atof') G u i d e 1.160 **.tto11ilor i 11g t lw J: ' erti 1*me J".1 o f Mai111 em 111 ce .11 1\'11' lc t1r pow e r l'lann .. :md 'UM R C 93-0 1 " f 111fit11t:
1 G11idt'li111
* .fi*r Mo11itor-i11g i h<' &#xa3;Jecriw11,*1. o Mai11M 1m1 c ,* at N1w/e11r l'r111w f'lnnt"'. nod '' ith guidan e r rnm /\C'I 3.J 9.3R, " l.nihmti o n 0f fx i\t i n g Nu*lc ar Sald)-Rcl:i tcJ C o n r<'h: 1 h e* Stru-:: L un: s l\l oni toring l'rogrurn 1 1a.. .. d.: 1 d pl.'d u>ing t he o f t hl">C t hn:,* <locum *111. . *1 h
* P rvgr.im j, i rnplememed to m o ni t or the i:on<l i tion or st r u c t ures and stn.11.:tural utnponents 
\\ ilhin l hi:: sco pe o f the Mainten a n c e H uie-. s u c h t hfll t h r.: n I ss o s tri1c t ur c or strucmrn l compom:nt intend ed functi n. 3.8..t.7.2 ;\L K Ll-S ll J(' H EAC TIO N (,\ I<) 10 rroR I N C *1 h e AS H l onih,ring Program c rn c k i ng due t o cxpan,ion and re ac ti on "ith of c1111..: rctc !Mucturc> T h e p otential imp.1 c t , ,f A \I{ on t he tru.:1unil 
!>l rength om l andwrng
* rnpacit) of i,, a .onscqu.:11.:c ol strains rc,uhin g fr , 1 m th e c\p ge l T h e , tnic t urc l\fon i t r ing Pr ogram rtrf rrns 1 i sua l ns of th e c0ncre t c s l rn ct ure' ut . c: 1 bmol.. for o f t he prc,cn c t* of a l kali*s i l ica r-::uct i o n ASR i nl'oh*c, t ht form t i on o r 11 nll, a l i-si licn gel 1 1hich e.\pa 11 d s \\ht:n i t. hoorbs ., hb e.1.p:m .. ion i;, \ o l um e t rk i n n at ure bu t mo. t read ii; detect ed I'>) 'i<.u a l o n>c n :iti.m o f' rac k i ng on the c of 1hc cum::rctc. 111ck i 11g i s t he r nuh e>f C).p , n. i n t h al i s oe u r ring i n t h in* pl ane dir c c t i n .. I 'pa nsio n is u l occurr i ng p rrpcndic u l ar (throu g h lh e 1h icl.11 c'>s of t he l\O ll) l o th e 'urlil c c n f thc \\a ll , hul md d n g \\ill rmt he' isible i n 1 hi> d ire t i n from t he < '1 ac l.i11 g *H t the s ut f; c.:: o f t he on rctc i\ t)pical l y :i c cp111 p a11k-J b) t he prcs..:n ct: o f m0i,1urc and ctll or.:>l t: rr " 'onnd<: uffectc d npwi'il r A. k i s t niic a ll)
U.S. Nuclear Regulatory Commission SBK-L-17156 I Enclosure 2 I Page 3 Sf.AUROOK , T TI O'! UJ-'A R D r I GN OF S T UC'l llllt:S. CoMI'O\JL1' J EQLlll'Mf:'\
f );IJ YSTl:MS R ev i sion 1 6 ection . U
* ign <>f Categ r) I , lruttur e s P o:c 148 har<1clc r i1cd h) u nct11t1rJ..
or .. r;1t t ern" o f cmcJ..s. 1 icm *ra d.in g luc t o ASR j, gene r ated t hr ugh forces applied by th e c:-p:mdinu 
;iggregate p a rt ic le m1d l or S\\elling nf t he alkn l iil i a gel \\ ithin and around the b o undar i es of reac t in g agg r e ga te parti I *. T he . R g *I ma, exude from t he cracJ.. forming "hi 1 e sn: mdar) d* posi t> m the con r le urfu ce. T h e ge l a l so oft *n cau *s a darl, di <'O l oralio n of the c m nt paste sur r ound ing the crnck ut t h' o nrn:te .urfacc. lf "pm l rn .. or "m n p.. nicJ..ing I) picul of *r e t e uflc tc J b) A 'R i> i dcm ifi ed, an ern lunti n will be p erfonned t o determine furthe r actions. M o ni t oring of crncl-.. grol\t h u ,t.-d t o t he in-p lan* ex p ansion u<>sociatc d " i th A 'R am l to monitoring int er\ ol . In " l c,*t ed location . c ore \\ill rt'llll.l\'ed for t esting to c srohli h 1he k1 cl flf t hrough-thicl.n<'s e"pnn sion t o d a te. h 1s trum t>11ts (e t en met r s) 1-ill be pl:i ed in the re su lt in!: b ore h o l e t m on i tor e:1.paiv*io11 i n th i din*,*1ion gn in
* fomar<l. ASll i s p r imar i I) d etec t *J by n o n-im ru sh.: \ i ual ob sc n mion o f cr Jc J..i ng on th* surfl1t*c l*f t he t*on rete Th e crad.i ng is acn,m p.1.ni t'<l t he pr'. l*ncc o f mui,tun: and e fll o re sccJJ<:e. A. R also I:>" dctc ctl'd or con fi nne d b} r elll(I\ al o f concre t e c re s and subse quent p.:t rogrn ph ic nnal) *i'. /1 Combin e d Cru cl.ing l ndc:\ ((' 'I) i s c tablishcd at at 1 1 hi c h stru *tur 11 C\ aluatit111 i
(S<'I.' table bckt\1 ). The Crack in i,? lnd e:1. (C'l) i
* th e s w mnn ti on oftlJ
* crn *k \\ idth> on 1hc h o r i10111al or \*enical s ide:; of 20*i n *h h y . O*inch gr i d on the ;\SRa fl" c'tl'd on *rc1 c surflt *c. Th e horitcmtal and 'crti ul CrncJ..in g l ndi
* re ti\ *r:iged to obtain a C omb in ed C rarJ..i n g I nd.::-. {CCI) for ca h an: a of int r c>l. A CC I o rb .. , thun th e 1.0 mm 1 m can be d med acccptnbk 
\I i l h defkic n c ic s {I icr 2). Delkkn ie J ctermincd tu be ac cptnhl '' i th f urther r.:\'i '' ar ... tr ndro fo r e1 id n c of further de g rad a t ion. Th e chang
* fr om 4u ali t al i1
* m on it ori ng t o 4uantiw1 i vc n wnilmin
* 1 cur> wh *n th* Cra l..i n g l nde:-. (C l) , l f t h pntt *rn crai: J..i ng equab or is g reater t h an 0.5 mm l m in the 1 crtical and h o ri LOntul dir e t io n>. 'o nrn:tt* era *J.. I\ i dih i. I > th an 0.05 rnm c un n t*t b
* uernrald) m easured and r e l io bly n:p eute d \\ i t h s tandt1rd. 1 i ual i nspec l i n CtJUi pm.:-111. A CC I o f 1.0 mm 1 m or g re ater requi r e' s tru ctura l C\ nf11 *. t i o n (Tier 3). A l l l oca ti ns m eet in g T i er 3 critcrifi 1 1 ill b e 
\'i a CCI on a Vi ar (6-monthl i nspect i on frequ cnc>> and added t o t he t hrough-t h ickness \p ans i m m on it oring 1*i n cxtcn om*tc r s. A ll I ation m ee tin g the *1 i er 2 struc 111 rcs m o n itor in i; r i ti:ria \\ill be monitor*d nn a 2.5 )C a r <.'O*m on th) CCI ;Jt rc l ntc 11cll '' iih sir.t in in t he i n-rl*lllt dircl: t i t>n' and th* ah i li l) t o detect cr ae!.io g i n n tr.1.l.ing it an cffc cti 1e in i t i n l d te ct i on p ar.imc tcr. Tltr lllo11horing P roi:rnm < 'n t tgol'} l 1 n.1c ,* .. C'\J hr.1t l{'O} J l commt n dation for l ndM d u*I C'on ttlt Com1>0nu11 1 S t: u cl u r J I I 'ah.raliun l mpk mcn l Al>R  "
s.u1.h a*1 t hfo.1,g.h 
.. \\a ll" p.H h1on 1..Li n' C" t c n un rlltrln 1.0 m m:m or l".r at t: r c l'r*c l.i nr t o.I.:' f ( '< IJ U.S. Nuclear Regulatory Commission SBK-L-17156 I Enclosure 2 I Page 4 SEA B ROOK S T AT I O:-i UFS n 01.., 1 i N O I* 11 n 1 , EQ ll f'lll[r\1 M m R e\i i o n 1 6 . e t i on 3.1! P ng c 1 4 9 I I l 1\c*c rtahlc \\ilh I r>d k L ... ncic"i I IJL1JJlli1.11ivc 
\l M i t.oring aod in'i'cdi\>n as t h.: l\1 ructur.il 1'.t.mho rinr. Pr e cldm O.S mm**m ,,r gtt=.lk't ( 4 1 *1 or great e r 1 h:m 0.5 mm l m in t h<'. 1mkal anJ horit0n1al arc;> will\ *i IJJ I of t\SR(. dcfill('d i n l l l\\',\*ll ll*12* n221 ;u;*cornr>.mi.'<l b) "l"I "ti ' t lnn I).* mm-'m in th.: ' crtk,1 1 anJ h*>rit 11 t.i l dirc.:1 i on,,,_ 1\rea ha\ t h* i n J ic.llion .. (l fpatt i:m ra..: h 1n' M \\OI er inpn:,
* No \ ;,uJI S) ol A:]{ *1 h e A lkali-S i l ica l k1.-:t i n M on it oring P ro gram \\a in i tial!) b:i cd 0 n publi !P1 i s t u d i s dcsrribi 1)g s re *n ing ll1t:lhods t o l e t n ninc \\" h *n . trllctura l t*1*a l ulll i on or/\. ;i ff c..: t *d r.:1llH."r ete lit.: nppr prime. I !Ir!!* scale I *stmc l i\l' t c.;tin,..'.
o f onc r etc h cam: "i lh utc.:IL*m tc d AS R has co111irrnc l t hat p umm' er.; hcing monitore d arc u p p r 1 p rim
* t u m anag.: t h** t.>ffc 1 , of 1\SR an d t hat uc cp!un c rr itc r ii*n o f I mm/in u p ro\ ii.J es margin. CC l&deg;S li mitat i on fo r ht:<I\ i i} r eir l fo r.: ei.J i s th a t i n-p lane e. *p: ll h k i n. and th cn.:fon:* CC J. h<1s lx*en ob>encJ i n t he l or 1 e ca lc t es t t o p l ntcm1 ut u rda t i v c l} 1 it l.:H: I (I f 1n:: u 111ulate d (u p pn I rnm 1 m). N u M ru ('l u ml i mpac t" from A " R ha 1 e h cn seen ut t h p l Jk:iu I*, *I s in ti ll.: l a r ge 1.:s t i ng pr ogram a t t he ni\er i ty of a t /\u:-t i n. h.:rgu:.on S tru wra l t: ng i ncaing t nborat or y. \\'h i l c 'I remai n-. use ful r nr t he d te,*t i n nn d monitor i ng of SH a t t he i n i tia l s 1 age .. ;m a ddit i onal nw ni torin' p;iramete r in t h e Ill* f-pl ane d i rec ti on requi red 1(1 mon i to r m o * !li.h'unee d A 'R p r g r e e\p an itm i n t h e uu t-o f*p lan d i n: ti on \1 i ll b e m ou i to r c J b y bor.::ho l
* i n ,ta l kd in dri l led o re rnm: It o! '>. Ah ho u g h t h e b *r,*ed s t rain due 1 0 A *R urr: i* H'ry sm a ll m n l!.nitudc 1111 d adcqun t c l} 11 H111 i tun.><l Ii} CCI an J e xten me t ers. ove r J ar* di lances im d " ith t h e r ight b u il d i n g rn n i n disc-e m ub l e d i me n ion clrnnges i n n s t ru tun;-. ddi l i na l 11l\ln i tl*ri11g of t his 1--e l ali\c p ote l\al m11.l its impa.: t t o plant and i s include J in the . R !'vi n it o ri ng 'Mgram. monitoring i n c l u d es id c n tif} ing signs 11 f rc l a ti\'c dis p laccm *nt r building d cfor mnli o (c .. g.. l i r e selll di pla c ement. sebmi I!U P " i dt h changt-;;, p i r/: t com.l uit mi;alignmcnts at pc n ctrnl i on; r hct\\CCl1 1djaccn 1 " tructu r cs. be nt ur di p ipe l conJuit and su p pom. d ma) C ri tical bui l ding ''here the p otential fo r d eformation b li kely 1\ill be mon i tored fo r d is pl ac.:mc nl \'i a/o,*at i l*n*spcdfic 3.8.4.7.3 Ull l LUIN G ll l:FOH I AT I ON 10.:'\ffOHl i G P JWG l< M The Build ing D t'f o m1: n i o n P l gram i a p l.mt pcc i fk pm g r.tm i1111, l *1n *nt.::<l u ndrr t he rx i s t ing M uintc n a m: c l{u'r 
*ttm: s M onitor i n g P rogram. B ui l ding Through-th ick ness expa ns ion will be mon i tored every s i x months , cons i stent with the mon i t oring interval for CC I of Tier 3 locat ions This interva l is appropriate because ASR i s a re la tively slow mov i ng p r ocess and t he concrete at Seabrook S t<ition has been in existence for decades. There is n o r eason to expect a sudden acce l eration of ASR development.
Hen ce , structural tmplicat io n s will not change significantly i n a short t i me period of six month s.
U.S. Nuclear Regulatory Commission SBK-L-17156 I Enclosure 2 I Page 5 SEABROOK DESIGN OF STRUCTURES, COMPONENTS EQUIPMENT Revision:
8 STATION AND SYSTEMS UFSAR Sheet: TABLE3.8-18 TABLE3.8-18 ASR EXPANSION LIMITS FOR STRUCTURAL LIMIT STATES Structural Limit State ASR Expansion Limit Shear Flexure Throu g h-th i ckn ess: S ee FP# L O I 020 S e ct i on 2.1 (R e f7) (2) Vo lu m e tri c: See F P#IO I OSO App e ndi x B (R e f8) (3) Re infor ceme nt Anchorage Anchors See FP# I 0 I 020 Section 2.1 (Ref 7) Compression (I) (I) Compress i ve l oad from ASR in the dir ect i on ofreinfo r cement is combined and eva lu ated with ot h er a ppl ied compress i ve l oads. 1 ofl (2) T h e throu g h-thickn ess ex p a n s i o n l imit for s h ea r, fl ex ure a nd r e in fo rc e m e nt a nch orage pr ese nt e d i n FP# 1 0 I 0 2 0 a r e diff e r e nt. Th e mo s t l im i tin g va lu e i s app l i e d as th e acc e pt a nc e cr i t e r i on for throu g h-thi c kn ess ex pan s ion m o nito r in g amon g th es e s tructural l imit s t a t es. (3) TI1 e maximum ob se rved m ax imum v olum e tri c ex pan s ion for s h ea r , fl exu re a nd r e inforc e m e nt a n c h o ra g e id e ntifi e d i n FP# I 01050 , App e nd ix B , Sec ti o n 5 ar e di ffe r e n t. Th e m os t l imitin g va lu e is a pp l i ed a s t h e accep t a n ce crit e r i o n for vo lum e tric ex p a n s i on m on it o rin g a m o n g th ese s trn c tura l limit s t ates.
U.S. Nuclear Regulatory Commission SBK-L-17156 I Enclosure 2 I Page 6 SEABROOK DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT AND STATION SYSTEMS UFSAR Design of Category I Structures 

====3.8.6 References====

Revision 16 Section 3.8 Page 653 1. Wilson , E.L., "Structural Analysis of Axisymmetric Solids ," AIAAJ. Vol. 3 , No. 12 (1965) pp. 163-182. 2. Wilson, E.L., "A Digital Computer Program for the Finite Element Analysis of Axisymrnetric Solids with Orthotropic , Nonlinear Material Properties," November 1969. 3. Duchon, N.B., "Analysis of Reinforced Concrete Membrane Subject to Tension and Shear ," ACI Journal , September, 1972 , pp. 578-583. 4. Wilson, E.L. and Nicholl, R.E., "Application of the Finite Element Method to Heat Conduction Analysis ," Journal of Nuclear Engineering and Design, Vol. 4, 1966. 5. Alexandria , S. C., Effects of Irradiation of Concrete , Final Results , Research Reactor Division UKAEA, Harwell, AERE-R-4490 , December 1963. 6. Foreign Print 100716, Impact of ASR on Structures.
: 7. MPR-4288, Revision 0, "Seabrook Station: Impact of Alkali-Silicia Reaction on the Structural Design E v aluations ," July 2016. FP#lO 1020 8. MPR-4273, Revision 0, "Seabrook Station -Implications of Large-Scale Test Program Results on Reinforced Concrete Affected by Alkali-Silica Reaction." FP#l01050 Enclosure 3 to SBK-L-17156 NextEra Energy Seabrook, Application for Withholding Proprietary Information from Public Disclosure and Affidavit U.S. Nuclear Regulatory Commission SBK-L-17156 
/Enclosure 3 I Page 2 NEXT era .. NextEra Energy Seabrook, LLC AFFIDAVIT IN SUPPORT OF APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE County of Rockingham ) ) State of New Hampshire ) I, Eric McCartney, being duly sworn according to law, depose and state the following:
(1) I am the Regional Vice President 
-Northern Region ofNextEra Energy Seabrook, LLC (NextEra Energy Seabrook), and have been delegated the function of reviewing the information described in paragraph (3) which is sought to be withheld, and have been authorized to apply for its withholding.
(2) I am making this Affidavit in conjunction with NextEra Energy Seabrook's "Application for Withholding Proprietary Information from Public Disclosure" accompanying this Affidavit and in conformance with the provisions of 10 CFR Section 2.390. (3) The information sought to be withheld is contained in Enclosure 1 ofNextEra Energy Seabrook's letter SBK-L-17156, Eric McCartney (NextEra Energy Seabrook) to U.S. Nuclear Regulatory Commission , entitled "Response to Request for Additional Information Regarding License Amendment Request 16-03 Related to Alkali-Silica Reaction (CAC No. MF8260)." (4) The information sought to be withheld is considered to be proprietary and confidential commercial information because alkali-silica reaction (ASR) is a newly-identified phenomenon at domestic nuclear plants. The information requested to be withheld is the result of several years of intensive NextEra Energy Seabrook effort and the expenditure of a considerable sum of money. This information may be marketable in the event nuclear facilities or other regulated facilities identify the presence of ASR. In order for potential customers to duplicate this information , similar technical pro g rams would hav e to be perform e d and a significant manpower effort, having the requisite talent and experience, would have to be expended. The extent to which this information is available to potential customers diminishes NextEra Energy Seabrook's ability to sell products and services involving the use of the information.
Thus, public disclosure of the information sought to be withheld is likel y to cause substantial harm to N ex tEra E n e r g y Seabrook's competitive position and NextEra E n e rgy Seabrook has a rational basis for considerin g this information to b e confid e ntial comm e rcial information.
U.S. Nuclear Regulatory Commission SBK-L-17156 I Enclosure 3 I Page 3 (5) The information sought to be withheld is being submitted to the NRC in confidence.
(6) The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by NextEra Energy Seabrook, has not been disclosed publicly, and not been made available in public sources. (7) The information is of a sort customarily held in confidence by NextEra Energy Seabrook , and is in fact so held. (8) All disclosures to third parties, including any required transmittals to the NRC, have been or will be pursuant to regulatory provisions and/or confiden t iality agreements that provide for maintaining the information in confidence.
I declare that the fore g oing affidavit and the matter s stated therein a r e true and correct to th e be s t of my knowledge , information , and belief. F urther , th e affiant sayeth not. Subscribed and sworn to before me this 31W dayofOctob e r , 2017.
Notary Public L My commission expires 3 fl /2 2 Regional orthern Region NextEra Energy Seabrook , LLC 626 Lafayette Road Seabrook , New Hampshire 03874}}