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

Response to Request for Additional Information Regarding License Amendment Request 16-03 Related to Alkali-Silica Reaction

ML17277A337
Person / Time
Site:	Seabrook
Issue date:	10/03/2017
From:	Mccartney E NextEra Energy Seabrook
To:	Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML17277A336	List: SBK-L-17156, Response to Request for Additional Information Regarding License Amendment Request 16-03 Related to Alkali-Silica Reaction
References
CAC MF8260, SBK-L-17156
Download: ML17277A337 (12)

Text

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 NEXTera(

ENERGY ~

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 ML17214A085).

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. 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 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. 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

~~,v.At

~ ccae; Regional Vice President - N~thern Region

U.S. Nuclear Regulatory Commission SBK-L-17156 I Page 3

Enclosures:

- Response to Request for Additional Information Regarding License Amendment Request 16-03 Related to Alkali-Silica Reaction (CAC No.

MF8260) (Proprietary) - 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 - 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 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 Page 2 SE BROOK STA'flO~

UF. AH D1.l>1C*~ c11

• 11<uc n 11<L'>. Co:-.tf't)'\\l

• 1~. 1:1.)t 'IPMD-: 1 A *t1 Svsrr t~

D sign of Category I Stru tul'\\.'S Rel'i ion 16 Section 3.8 Pai.ie 147 3.8..t.7 Te~tin g and fn~')ervic Snn*eillance Rec1uirement<;

Normal quality cantrul testing is di cu s*d in ubsection 3.8.3.6. A gencr:il visual inspe tion of the exposed acc.:ssihlc inlt!rinr and cxtc:rior surfaces of the Containment Fnclosurc Building will be periodically conducted as di: ' LIS * *d in Su~cctio n 6.2.6.1.

ll1c S1ructural foniioring Pwgrum include~ requ i rement~ for in:.p.:cting :m1cturi:s aOc.:tcd by A.'R. *1 he total exrxinsion of t\\SR-afli:ckd nrc.L~ is limited lo le than the amounts spcdfied in l"abl 3.8-18. 1'1:riodi *ally, cfifying that ASR xpansion k Is an: he! th..: limits i nc\\.OCssary to cnsur' struclllrJI pr,1JX!rti s f ASR-al1i:ctcd 1rea' :u\\' similat to an:as with no cvidcn c nf

'R.

• 1 he Structural I\\ f,,11iu1ri11g. Program al. has limits n SUlJCture d fom1ati\\)1t from. R on r te expansion.

1ruc1u1e~ \\\\ ith incr asing le\\' I ~ of d fo1matio11. as de1cm1in *d hy ;111 analysi-; of the self*stminin" loads, nre cla silied M Stag.e l. 2. or ~. t..loni1.1ring criicrin for ca h structure :w*

included in IJlC Stmc1uml Monitoring Pro *ram and in,pcclion rcquircmcnL~ arc ddin *d liascd on the analysis and la *sitic.ition of each slru lure.

3.8..J.7.I STIUJC'TUIU:: i\\ 1 01\\ ITOHl ~G Pl<OGRAl\\I The. 1ructurcs \\1onit0rin£ Progrnm ;, i111plem ntcd through 1h~ plant il.laintcnancc Ruic Pr,1gr m. \\\\hi h i> ha~cd on the guidance prm idl*d in NRC R gulatof') Guide 1.160

• • .tto11ilori11g tlw J:' erti1*meJ".1 of Mai111em111ce.11 1\\'11' lct1r power l'lann.. :md 'UM RC 93-01 " f111fit11t:1 G11idt'li111*.fi*r Mo11itor-i11g ih<' £Jecriw11,*1. o Mai11M1m1c,* at N1w/e11r l'r111w f'lnnt" '. nod ith guidan e rrnm /\\C'I 3.J9.3R, "l.nihmtion 0f fxi\\ting Nu*lcar Sald)-Rcl:itcJ Con r<'h: Structure~". 1 he* Stru-::Lun:s l\\lonitoring l'rogrurn 11a.... d.:1d pl.'d u>ing the gu i dan~.: of thl">C thn:,* <locum *111.. *1 h

• Prvgr.im j, irnplememed to monitor the i:on<lition or structures and stn.11.:tural utnponents \\\\ ilhin lhi:: scope of the Maintenance Huie-. such thfll th r.: i ~ n I ss o stri1cturc or strucmrnl compom:nt intended functi n.

3.8..t.7.2 ;\\LK Ll-SllJ(' HEACTION (,\\ I<) 10 rroRINC

• 1 he ASH lonih,ring Program manage~ crncking due to cxpan,ion and reaction "ith tiggn~gatc' of c1111..:rctc !Mucturc> The potential imp.1ct,,f A \\ I{ on the tru.:1unil !>lrength oml andwrng

• rnpacit) of con~n:k i,, a.onscqu.:11.:c ol strains rc,uhing fr,1m the c\\p n~iH~

gel The, tnicturc l\\fonit ring Program rtrf rrns 1 isual in ~p..'C t i ns of the c0ncretc slrncture' ut. c:1bmol.. for i ndi *~thm\\ of the prc,cnct* of alkali*silica r-::uction (A~R). ASR inl'oh*c, tht form tion or 11 nll,ali-silicn gel 11hich e.\\pa11ds \\\\ht:n it. hoorbs \\l <l l ~r.., hb e.1.p:m.. ion i;,

\\ olumetrk in nature but i~ mo. t read ii; detected I'>) ' i<.ual on>cn :iti.m of' racking on the

~urfn c of 1hc cum::rctc. Thi~ 111cki11g is the rnuh e>f C).p, n. i n thal is oe urring in th in*

plane dirccti n.. I 'pansion is ul occurring prrpcndicular (through lhe 1hicl.11c'>s of the l\\Oll) lo the 'urlilcc nf thc \\\\all, hul mddng \\\\ill rmt he' isible in 1hi> dire ti n from the

1~ce,sibk ~urfo,c. < '1acl.i11g *Ht the sut f; c.:: of the on rctc i\\ t)pically :iccp111pa11k-J b) the prcs..:nct: of m0i,1urc and ctllor.:>lt:rr "

'onnd<: uffectcd b~ npwi'il r A. k is tniicall)

U.S. Nuclear Regulatory Commission SBK-L-17156 I Enclosure 2 I Page 3 Sf.AUROOK

, T TIO'!

UJ-'AR Dr IGN OF ST UC'l llllt:S. CoMI'O\\JL1' J ~. EQLlll'Mf:'\\f

);IJ YSTl:MS Revision 16 ection.

U

• ign <>f Categ r) I, lruttures Po:c 148 har<1clcri1cd h) u nct11t1rJ.. or.. r;1ttern" of cmcJ..s. 1icm *rad.ing luc to ASR j, generated thr ugh forces applied by the c:-p:mdinu ;iggregate particle m1dlor S\\\\elling nf the alknli-ili a gel \\\\ ithin and around the boundaries of reacting aggregate parti I *. The

. R g *I ma, exude from the cracJ.. forming "hi1e sn:mdar) d* posit> m the con r le urfuce. The gel also oft *n cau *s a darl, di <'Oloralion of the c m nt paste surrounding the crnck ut th' onrn:te.urfacc.

lf "pml rn.. or "mnp.. nicJ..ing I) picul of ~ on *rete uflc tcJ b) A 'R i>

idcmified, an ernlunti n will be perfonned to determine further actions.

Monitoring of crncl-.. grol\\ th i ~ u,t.-d to ill.st.">~ the in-plan

• expansion u<>sociatcd " ith A ' R aml to ~pedty monitoring inter\\ ol.

In "lc,*ted location. core \\\\ill rt'llll.l\\'ed for modu l u ~ testing to csrohli h 1he k1 cl flf through-thicl.n<'s e"pnnsion to date. h1strumt>11ts (e ten met rs) 1-ill be pl:i ed in the resultin!: bore hole t monitor e:1.paiv*io11 in thi din*,*1ion gnin

• fomar<l.

ASll is primari I) detect *J by non-imrush.: \\ i ual obscn mion of crJcJ..ing on th

• surfl1t*c l*f the t*on rete The crad.ing is t~pi c.1 11 ) acn,mp.1.nit'<l b~ the pr'. l*ncc of mui,tun: and eflloresccJJ<:e. A. R ma~ also I:>" dctcctl'd or con finned b} relll(I\\ al of concrete c res and subsequent p.:trogrnphic nnal) *i'.

/1 Combined Crucl.ing lndc:\\ ((' 'I) is c tablishcd at t hrc~hold:. at 11 hi ch stru *tur 11 C\\ aluatit111 i nc..:c~ar~ (S<'I.' table bckt\\1 ). The Crackini,? lnde:1. (C'l) i

• the swmnntion oftlJ

• crn *k \\\\ idth> on 1hc hori10111al or \\*enical side:; of 20*in *h hy. O*inch grid on the ;\\ SR-afl"c'tl'd on *rc1c surflt *c. The horitcmtal and 'crti ul CrncJ..ing lndi

~

• re ti\\ *r:iged to obtain a Combined CrarJ..ing Ind.::-. {CCI) for ca h an:a of int rc>l. A CCI orb

.., thun the 1.0 mm 1m can be d med acccptnbk \\I ilh defkicncics {I icr 2). Delkkn ie Jctermincd tu be ac cptnhl ith further r.:\\'i ar... tr ndro for e1 id n c of further degradation. The chang

• from 4ualitali1

• monitoring to 4uantiw1ivc nwnilmin

• 1 cur> wh *n th* Cra l..ing lnde:-. (C l),l f th pntt *rn crai:J..i ng equab or is greater than 0.5 mmlm in the 1crtical and horiLOntul dire tion>.

'onrn:tt* era *J.. I\\ idihi. I > than 0.05 rnm cunnt*t b

• uernrald) measured and reliobly n:peuted \\\\ ith standt1rd. 1 i ual inspecli n CtJUipm.:-111. A CCI of 1.0 mm 1m or greater require' structural C\\ nf11 *. ti on (Tier 3). All locati ns meeting Tier 3 critcrifi 11 ill be monil\\lr~d \\'ia CCI on a Vi ar (6-monthl inspect ion frequcnc>> and added to the through-thickness \\pansi m monitoring 1*in cxtcn om*tcrs. All I ation meeting the *1 ier 2 struc111rcs monitorini; riti:ria \\\\ill be monitor*d nn a 2.5 )Ca r <.'O*month) lr *quenc; ~. CCI

Jtrclntc 11cll iih sir.tin in the in-rl*lllt dircl:tit>n' and th* ahilil) to vi,ua ll~ detect crae!.iog in c.\\ po~~d

• urface~ ntr.1.l.ing it an cffccti1e initinl d tection par.imctcr.

~ l rur t urn l Tltr lllo11horing Proi:rnm < 'nttgol'}

l 1n.1c,*.. -rtJ~!i:

(ri:qu i r-:~ fu1* 1!1~r C'\\Jhr.1tl{'O}

Jl commtndation for lndMdu*I C'on ttlt Com1>0nu111 St:uclurJI I ' ah.raliun lmpkmcnl nh~lk<J Al>R lll i~ ll;h *rin~- s.u1. h a*1 thfo.1,g.h..

\\\\all" p.Hh1on n10nitt 1cin~

1..Lin ' C"tcn un ' t~rs rlltrln 1.0 mm:m or l".r att:r c

• nmhitl~J l'r*cl.inr to.I.:' f ( '< IJ

U.S. Nuclear Regulatory Commission SBK-L-17156 I Enclosure 2 I Page 4 SEABROOK STATIO:-i UFS n 01..,1 iN OI*

11n ' ttrR i:s. Co~ ll'O\\L 1, EQllf'lll[r\\1 Mm Re\\ i ion 16

. e tion 3.1!

Pngc 149 I

I l 1\\c*crtahlc \\\\ilh I r>dk L... ncic"i I

IJL1JJlli1.11ivc \\lM it.oring aod rr.~nJin~

knut i n~ in'i'cdi\\>n as pn:~crit'l\\.*<l b~

th.: l\\1ructur.il 1'.t.mhorinr. Pre cldm O.S mm**m,,r gtt=.lk't (

4 1

• 1 or greater 1h:m 0.5 mmlm in th<'. 1mkal anJ horit0n1al Jif\\..~1iOU.:!t.

I' ll~ arc;> will\\ *i IJJI f'l'C~CllCC of t\\SR(. dcfill('d in l ll\\\\',\\ *llll *12*

n221 ;u;*cornr>.mi.'<l b) "l"I "ti '

tlnn I).* mm-'m in th.: ' crtk,11 anJ h*>rit 11t.il dirc.:1ion,,,_

1\\ rea ha\\ th* inJic.llion.. (lfpatti:m ra..:h1n' M \\\\OI er inpn:,

• No \\ ;,uJI S) mrtom ~ ol A:]{

• 1 he Alkali-Silica lk1.-:ti n Monitoring Program \\\\ a initial!) b:i cd 0n publi !P1istudi s dcsrribi1)g s re *ning ll1t:lhods to let nninc \\\\"h *n. trllctural t*1*alulllion or /\\. r~ ;iffc..:t *d r.:1llH."rete lit.: nppr prime. I !Ir!!* scale I *stmcli\\l' tc.;tin,..'. of oncretc hcam: "ilh utc.:IL*mtcd ASR has co111irrnc l that pumm' er.; hcing monitored arc up pr 1prim

• tu manag.: th** t.>ffc 1, of 1\\ SR and that uc cp!un c rritcrii*n of I mm/in u u ~t'<l pro\\ ii.Jes ~11ffiden t margin.

CCl°S limitation for ht:<I\\ ii} reirlfor.:ei.J ~ l ru Cttirt*~ is that in-plane e. *p:llh kin. and thcn.:fon:*

CCJ. h<1s lx*en ob>encJ in the lor 1e calc test program~ to plntcm1 ut u rdativcl} 1 it l.:H:I (If 1n::u111ulated ~t rain (uppn '\\imatd~ I rnm1m). Nu Mru('luml impact" from A "R ha1e h cn seen ut th *~ plJk:iu I*, *Is in till.: large ~.:ale 1.:sting program at the ni\\er ity of Tt.\\.tL~ at /\\u:-tin. h.:rgu:.on Stru wral t:ngincaing t nboratory. \\\\'hilc

'I remain-. useful rnr the d te,*ti n nnd monitoring of SH at the initial s1age.. ;m additional nwnitorin' p;irameter in the Ill* f-plane direction i ~ required 1(1 monitor mo * !li.h'uneed A 'R pr gre ~ i n n. AS !~ e\\ pan itm in the uut-of*plan din: tion \\1 ill be mouitorcJ by bor.::hol

• C\\lCn~OfllClcrs in,talkd in drilled ore rnm: Ito! '>.

Ahhough the b *r,*ed strain due 10 A *R urr: i* H'ry small mnl!.nitudc 1111d adcquntcl}

11H111itun.><l Ii} CCI anJ exten meters. over Jar* di lances imd " ith the right building i,:comdr~. l he~ rnn re~u h in disc-emuble dimen ion clrnnges in n stru tun;-.

ddili nal 11l\\lnitl*ri11g of this 1--elali\\c dis~1lo 'ement potel \\al m11.l its impa.:t to plant s~st.:nh and t*omponem~ is includeJ in the

. R !'vi nitoring 'Mgram. Spcc i l icall~. monitoring includes idcntif} ing signs 11f rclati\\'c displaccm *nt

~ r building dcformnlio (c.. g.. lire selll di placement. sebmi I!UP " idth changt-;;, pir/:tcom.luit mi;alignmcnts at pcnctrnlion; r hct\\\\CCl1 1djaccn1 "tructurcs. bent ur di P:l,~ed pipelconJuit and suppom. d ma) m i~ l ign 111e111s). Critical building g~omet r} l0y at ion~ here the potential for deformation b likely 1\\ill be monitored for displac.:mcnl \\'ia/ o,*atil*n*spcdfic 1 r:ch11 i4 uc~.

3.8.4.7.3 UlllLUING lll:FOH IATION 10.:'\\ffOHli G PJWGl< M The Building Dt'fom1:nion Monit<1rin~ Pl gram i a pl.mt pccifk pmgr.tm i1111,l *1n *nt.::<l undrr the rxisting Muintcnam:c l{u'r

~IHI *ttm:s Monitoring Program. Building Through-thickness expansion will be monitored every six months, consistent with the monitoring interval for CCI of Tier 3 locations This interval is appropriate because ASR is a relatively slow moving process and the concrete at Seabrook St<ition has been in existence for decades.

There is no reason to expect a sudden acceleration of ASR development. Hence, structural tmplications will not change significantly in a short time period of six months.

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 Through-thickness: See FP# LO I 020 Section 2.1 (Ref7) (2)

Volumetric: See FP# IO IOSO Appendix B (Ref8) (3)

Reinforcement Anchorage Anchors See FP# I 0 I 020 Section 2.1 (Ref 7)

Compression (I)

(I)

Compressive load from ASR in the direction ofreinforcement is combined and evaluated with other applied compressive loads.

1 ofl (2)

The through-thickness expansion limit for shear, flexure and reinforcement anchorage presented in FP# 10 I 020 are different. The most limiting value is applied as the acceptance criterion for through-thickness expansion monitoring among these structural limit states.

(3)

TI1e maximum observed maximum volumetric expansion for shear, flexure and reinforcement anchorage identified in FP# I 01050, Appendix B, Section 5 are different. The most limiting value is applied as the acceptance criterion for volumetric expansion monitoring among these strnctural limit states.

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 Evaluations," 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 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 NEXTera EN~~~~

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 programs would have to be performed 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 likely to cause substantial harm to NextEra Energy Seabrook's competitive position and NextEra Energy Seabrook has a rational basis for considering this information to be confidential commercial 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 confidentiality agreements that provide for maintaining the information in confidence.

I declare that the foregoing affidavit and the matters stated therein are true and correct to the best of my knowledge, information, and belief. Further, the affiant sayeth not.

Subscribed and sworn to before me this 31W dayofOctober, 2017.

QfwiA:N~

Notary Public L

My commission expires 3 fl /2 2

~ccaney Regional Vice~

orthern Region NextEra Energy Seabrook, LLC 626 Lafayette Road Seabrook, New Hampshire 03874