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| {{#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) | | {{#Wiki_filter:Enclosure 1 to this Letter Contains Proprietary Information Withhold Enclosure 1 from Public Disclosure in Accordance with 10 CFR 2.390 NEXTera( |
| | ENERGY ~ |
| | SEABROOK October 03, 2017 10 CFR 50 *>f'." |
| | Docket No. 50-443 SBK-L-17156 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Seabrook Station Response to Request for Additional Information Regarding License Amendment Request 16-03 Related to Alkali-Silica Reaction (CAC No. MF8260) |
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| ==References:== | | ==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). | | : 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). | | : 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. | | 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). |
| 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. | | 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'." | | NextEra Energy Seabrook, LLC P.O. Box 300, Lafayette Road, Seabrook, NH 03874 |
| 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.
| | 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). | | 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. |
| 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 | | If there are any questions or additional information is needed, please contact Mr. |
| -License Renewal, at (603) 773-7957. | | 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. | | 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 | | I declare under penalty of perjury that the foregoing is true and correct. |
| -Regional Vice Presid e nt -
| | Executed on October 3, 2017. |
| Region U.S. Nuclear Regulatory Commission SBK-L-17156 I Page 3 | | Sincerely, NextEra Energy Seabrook, LLC |
| | ~~,v.At |
| | ~ ccae; Regional Vice President - |
| | - |
| | N~thern Region |
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| | U.S. Nuclear Regulatory Commission SBK-L-17156 I Page 3 |
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| ==Enclosures:== | | ==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 NRC Region I Administrator J.C. Poole NRC Project Manager P. C. Cataldo NRC Senior Resident Inspector L. M. James NRC Project Manager, License Renewal Mr. Perry Plummer 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 |
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| | U.S. Nuclear Regulatory Commission SBK-L-17156 I Enclosure 2 I Page 2 SE BROOK D1.l>1C*~ c11 |
| | * 11<uc n 11<L'>. Co:-.tf't)'\l |
| | * 1~. 1:1.)t 'IPMD-: 1 A *t1 Rel'i ion 16 STA'fl O~ Svsrr t~ Section 3.8 UF. A H D sign of Category I Stru tul'\.'S Pai.ie 147 3.8..t.7 Te~tin g and fn~')ervic Snn*eilla nce 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 co nducted 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 . *1he total exrxinsion of t\SR-afli:ckd nrc.L~ is limited l o 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. |
| | *1he 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'T UIU :: i\ 1 01\ I TOHl ~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 93-0 1 " f111fit11t:1 G11idt'li111* .fi*r Mo11itor-i11g i h<' £Jecriw11,*1. o Mai11M1m1c,* at N1w/e11r l'r111w f'lnnt" '. nod '' ith guidan e rrnm /\C' I 3.J9.3R, "l.nihmtion 0f fx i\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 gui dan~.: of thl">C thn:,* <locum *111. . *1h |
| | * Prvgr.im j, irnplememed to monitor the i:on<lition or st ructures 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 rroR INC |
| | *1he 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 T he , tnicturc l\fonit ring Program rtrf rrns 1 isual in ~p..'Ct i ns of the c0ncretc slrncture' ut . c:1bmol.. for i ndi *~thm\ of the prc,cnct* of alkali*silica r-::uct ion (A~R) . ASR inl'oh*c, tht form tion or 11 nll,ali-silicn gel 11hich e.\pa11ds \\ht:n it. hoorbs \l <ll ~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 mdd ng \\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) |
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| | U.S. Nuclear Regulatory Commission SBK-L-17156 I Enclosure 2 I Page 3 Sf.AUROOK D r IGN OF ST UC'l llllt:S. CoMI'O\JL1' J~. EQLlll'Mf:'\f );IJ Revision 16 |
| | , T TI O'! YSTl:MS ection . |
| | UJ-'AR U |
| | * ign <>f Categ r) I , lruttures Po:c 148 har<1clc ri1cd h) u nct11t1rJ.. or .. r;1t tern" of cmcJ..s. 1icm *rad.ing luc to ASR j, gene rated thr ugh forces applied by the c:-p:mdinu ;iggregate part icle m1d lor S\\elling nf the alkn li-il i 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 |
| | * posi t> m the con r le urfuce. The ge l 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> |
| | idcm ified, an ernlunti n will be perfonned to determine furthe r actions. |
| | Moni toring of crncl-.. grol\ th i ~ u,t.-d to ill.st.">~ the in-plan |
| | * ex pansion 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 th i 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 efll oresccJJ<:e. A. R ma~ also I:>" dctcctl'd or con fi nned b} r elll(I\ al of concrete c res and subsequent p.:t rogrnphic nnal) *i'. |
| | /1 Combined Crucl.ing lndc:\ ((' ' I) is c tablishcd at t hrc~hold:. at 11hi 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 CC I 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 fo r e1 id n c of further degradation. The chang |
| | * from 4ualital i1 |
| | * 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 mm lm in the 1crtical and horiLOntul dire tion>. 'onrn:tt* era *J.. I\ idihi. I > than 0.05 rnm cun nt*t b |
| | * uernrald) measured and relio bly n:peuted \\ ith standt1rd. 1i ual inspecli n CtJUipm.:-111. A CCI of 1.0 mm 1m or greater require' structura l C\ nf11 *. tion (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 frequ cnc>> and added to the through-thickness \pans i m monitoring 1*in cxtcn om*tcrs. All I ation meeting the *1ier 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* ahili l) to vi ,ua ll~ detect crae!.iog in c .\ po~~d |
| | * urface~ ntr.1.l.ing it an cffccti1e initinl d tect ion par.imc tcr. |
| | ~ l rur t urn l Jl commtndation for lndMdu*I Tltr lllo11horing rlltrln C'on ttlt Com1>0nu111 Proi:rnm <'nttgol'} |
| | St:uclurJI I ' ah.raliun l 1n.1c,*..-rtJ~!i: l mpkmcnl nh~lk<J Al>R 1.0 mm:m or l".r att:r c*n mhitl~J (ri:q u i r-:~ fu1* 1!1~r llli~ ll;h *rin~- s.u1. h a*1 thfo.1,g.h .. |
| | C' \J hr.1t l{'O} \\all" p.Hh1on n10nitt 1cin~ |
| | l'r*cl.i nr to.I.:' f( '< IJ 1..Lin ' C"tcn un 't~rs |
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| | U.S. Nuclear Regulatory Commission SBK-L-17156 I Enclosure 2 I Page 4 SEABROOK 01..,1 iN OI* 11n ' ttrR i:s. Co~ ll'O\L 1 , EQl lf'lll[r\1 M m Re\ i ion 16 STATIO:-i . e tion 3.1! |
| | UFS n Pngc 149 I O.S mm **m ,,r gtt=.lk't ( 1 4 IJL1JJlli1.11ivc \lM it.oring aod *1or greater 1h:m 0.5 mmlm in Il 1\c *crtahlc \\ilh rr.~nJin~ th<'. 1mkal anJ horit0n1al Jif\..~1iO U.:!t. |
| | I r>dk L...ncic"i I' ll~ arc;> will\ *i IJJI f'l'C~CllCC of t\SR(. dcfill('d in l l l\\',\ |
| | * ll ll |
| | * 12* |
| | n221 ;u;*cornr>.mi.'<l b) "l"I "ti ' |
| | tlnn I).* mm-'m in th.: ' crtk,11anJ I h*>rit 11t.il dirc.:1ion,,,_ |
| | 1\ rea ha\ th* inJ ic.llion .. (lfpatti:m knuti n~ in'i'cdi\>n as pn:~crit'l\.*<l b~ |
| | ra..:h1n' M \\OI er inpn:, |
| | * No \ ;,uJI th.: l\1ructur.il 1'.t.mhorinr. Pre cldm S) mrtom ~ ol A:]{ |
| | *1he Alkali-Silica lk1.-:t i n Monitoring Program \\ a initial!) b:i cd 0n publi !P1i studi s dcsrribi1)g s re *ning ll1t:lhods to let nninc \\"h *n . trllctural t*1*alulll ion 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 uppr 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. |
| | CC l°S limitation fo r ht:<I\ ii} reirlfo r.: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 e calc test program~ to plntcm1 ut u rdativcl} 1 it l.:H:I 1 |
| | ( I f 1n::u111ulated ~t rain (uppn '\imatd~ I rnm 1m). 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-. use ful rnr the d te,*t i n nnd monitoring of SH at the initia l s1age.. ;m addit ional nwnitorin' p;irameter in the Ill* f-pl ane 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 na l 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 i on~ '' here the potential for deformation b likely 1\ill be mon itored for displac.:mcnl \'ia/ o,*atil*n*spcdfic 1 r:c h11 i4 uc~. |
| | 3.8.4.7.3 Ull lLUING lll:FOH IATION 10.:'\ffOHli G PJWGl< M The Building Dt'fo m1:n ion Monit<1rin~ Pl gram i a pl.mt pccifk pmg r.tm i1111,l *1n *nt.::<l undrr the rx isting 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. |
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| | 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: 1 ofl TABLE3.8-18 TABLE3.8-18 ASR EXPANSION LIMITS FOR STRUCTURAL LIMIT STATES Structural Limit State ASR Expansion Limit Shear Through-th ickness: See FP# LOI 020 Section 2.1 (Ref7) (2) |
| | Flexure Volu metri c: See FP# IO IOSO Appendi x 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. |
| | (2) The through-thickness expansion limit for shear, fl exure 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, fl exure and re inforcement anchorage identified in FP# I 01050, Appendix B, Section 5 are di fferent. The most limiting value is applied as the acceptance criterion for volumetric expansion monitoring among these strnctural limit states. |
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| | U.S. Nuclear Regulatory Commission SBK-L-17156 I Enclosure 2 I Page 6 SEABROOK DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT AND Revision 16 STATION SYSTEMS Section 3.8 UFSAR Design of Category I Structures Page 653 3.8.6 References |
| | : 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 |
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| | 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 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. |
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| Enclosure 1 -Response to Request for Additional Information Regarding License Amendment Request 16-03 Related to Alkali-Silica Reaction (CAC No. MF8260) (Proprietary)
| | 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. |
| 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
| | (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. |
| * 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.
| | (7) The information is of a sort customarily held in confidence by NextEra Energy Seabrook, and is in fact so held. |
| \\ ith i ncr asing l e\' of d fo1matio11. as d e 1cm1 i n *d hy ;111 analysi-;
| | (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. |
| 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
| | 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. |
| :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£ 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:
| | ~ccaney Regional Vice ~ orthern Region NextEra Energy Seabrook, LLC 626 Lafayette Road Seabrook, New Hampshire 03874 Subscribed and sworn to before me this 31W dayofOctober, 2017. |
| 1 G11idt'li111
| | QfwiA:N~ |
| * .fi*r Mo11itor-i11g i h<' £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
| | Notary Public L My commission expires 3 fl /22}} |
| * 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
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| \\ 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
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| !>l rength om l andwrng
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| * 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)
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| 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:'\
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| f );IJ YSTl:MS R ev i sion 1 6 ection . U
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| * ign <>f Categ r) I , lruttur e s P o:c 148 har<1clc r i1cd h) u nct11t1rJ..
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| 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
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| ;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
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| * 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
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| (S<'I.' table bckt\1 ). The Crack in i,? lnd e:1. (C'l) i
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| * th e s w mnn ti on oftlJ
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| * 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
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| * 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
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| \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
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| * fr om 4u ali t al i1
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| * m on it ori ng t o 4uantiw1 i vc n wnilmin
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| * 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
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| * 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
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| \'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 "
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| s.u1.h a*1 t hfo.1,g.h
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| .. \\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
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| \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:,
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| * 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,..'.
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| 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
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| * 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°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
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| * 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
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| *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.
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| Hen ce , structural tmplicat io n s will not change significantly i n a short t i me period of six month s.
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| U.S. Nuclear Regulatory Commission SBK-L-17156 I Enclosure 2 I Page 5 SEABROOK DESIGN OF STRUCTURES, COMPONENTS EQUIPMENT Revision:
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| 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.
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| 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.
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| : 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
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| /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:
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| (1) I am the Regional Vice President
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| -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.
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| (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.
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| 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.
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| 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}} | |
Letter Sequence Response to RAI |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance
Results
Other: ML17199T383, ML17283A040, ML18135A046, ML18204A242, ML18353A954, ML19044A768, ML19058A216, NRC-2019-0075, Federal Register Notice - License Amendment; Issuance (CAC No. MF8260; EPID L-2016-LLA-0007), SBK-L-16013, License Renewal Application Relating to the Alkali-Silica Reaction Monitoring Program, SBK-L-16181, License Renewal Application Relating to the Alkali-Silica Reaction Monitoring Program, SBK-L-17101, Update to Reply to a Notice of Violation; EA-16-101 Corrective Action Plan
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MONTHYEARSBK-L-16013, License Renewal Application Relating to the Alkali-Silica Reaction Monitoring Program2016-08-0909 August 2016 License Renewal Application Relating to the Alkali-Silica Reaction Monitoring Program Project stage: Other ML16258A0222016-09-19019 September 2016 Supplemental Information Needed for Acceptance of Requested Licensing Action Alkali-Silica Reaction Project stage: Acceptance Review ML16265A4402016-10-12012 October 2016 Acceptance of Requested Licensing Action Alkali-Silica Reaction Project stage: Acceptance Review SBK-L-16181, License Renewal Application Relating to the Alkali-Silica Reaction Monitoring Program2016-12-23023 December 2016 License Renewal Application Relating to the Alkali-Silica Reaction Monitoring Program Project stage: Other SBK-L-17101, Update to Reply to a Notice of Violation; EA-16-101 Corrective Action Plan2017-06-16016 June 2017 Update to Reply to a Notice of Violation; EA-16-101 Corrective Action Plan Project stage: Other ML17199T3832017-07-26026 July 2017 Site Visit Report Regarding Regulatory Audit for Alkali Silica Reaction License Amendment Request Project stage: Other ML17214A0852017-08-0404 August 2017 Request for Additional Information Regarding License Amendment Request Related to Alkali-Silica Reaction Project stage: RAI ML17283A0412017-08-24024 August 2017 Enclosure 3 - Licensee'S Presentation-Seabrook Station, License Amendment Request 16-03 ASR Structural Evaluation Methodology Project stage: Request SBK-L-17156, Response to Request for Additional Information Regarding License Amendment Request 16-03 Related to Alkali-Silica Reaction2017-10-0303 October 2017 Response to Request for Additional Information Regarding License Amendment Request 16-03 Related to Alkali-Silica Reaction Project stage: Response to RAI SBK-L-17155, Supplement 58 - Response to Request for Additional Information for the Review of the License Renewal Application - Building Deformation Analyses Related to Concrete Alkali-Silica Reaction2017-10-0303 October 2017 Supplement 58 - Response to Request for Additional Information for the Review of the License Renewal Application - Building Deformation Analyses Related to Concrete Alkali-Silica Reaction Project stage: Response to RAI ML17283A0402017-10-10010 October 2017 Enclosure 2 - Nrc'S Presentation Slides-Seabrook Station, License Amendment Request, Stage 3 Methodology Project stage: Other ML17261B2172017-10-11011 October 2017 Request for Additional Information Regarding License Amendment Request Related to Alkali-Silica Reaction (CAC No. MF8260; EPID L-2016-LLA-0007) Project stage: RAI ML17278A7482017-10-13013 October 2017 Summary of August 24, 2017, Meeting with NextEra Energy Regarding License Amendment Request on Alkali Silica Reaction (CAC No. MF8260; EPID L-2016-LLA-0007) Project stage: Meeting ML17310A1142017-10-17017 October 2017 La - (External_Sender) Name Correction: Summary of August 24, 2017, Meeting with NextEra Energy Regarding License Amendment Request on Alkali Silica Reaction (CAC No. MF8260; EPID L-2016-LLA-0007) Project stage: Meeting ML17310B5402017-11-0303 November 2017 La - (External_Sender) SBK-L-17180 Supplement 58 - Revised Alkali-Silica Reaction Aging Management Program Project stage: Request SBK-L-17180, Supplement 58, Revised Alkali-Silica Reaction Aging Management Program2017-11-0303 November 2017 Supplement 58, Revised Alkali-Silica Reaction Aging Management Program Project stage: Request ML17341A0622017-11-17017 November 2017 NextEra Energy Seabrook Presentation Slides - Seabrook Station ASR Methodology LAR: Structural Deformation - LAR 16-03, Methodology and Responses to Rais D2-D8 - for November 17, 2017, Public Meeting Project stage: Response to RAI SBK-L-17204, Response to Request for Additional Information Regarding License Amendment Request Related to Alkali-Silica Reaction (CAC No. MF8260; EPID L-2016-LLA-0007)2017-12-11011 December 2017 Response to Request for Additional Information Regarding License Amendment Request Related to Alkali-Silica Reaction (CAC No. MF8260; EPID L-2016-LLA-0007) Project stage: Response to RAI ML17340A1862017-12-14014 December 2017 Summary of November 17, 2017, Meeting with NextEra Energy Regarding License Amendment Request on Alkali Silica Reaction - Requests for Additional Information (CAC No. MF8260; EPID L-2016-LLA-0007) Project stage: RAI ML18102A0972018-04-12012 April 2018 Commission Memorandum and Order CLI-18-04 Project stage: Request SBK-L-18072, Revised Structures Monitoring Aging Management Program2018-05-18018 May 2018 Revised Structures Monitoring Aging Management Program Project stage: Request ML18135A0462018-05-21021 May 2018 Site Visit Report Regarding Regulatory Audit for License Amendment Request Alkali Silica Reaction License Amendment Request and License Renewal Alkali-Silica Reaction Aging Management Program Review (CAC No. MF8260; EPID L-2016-LLA-007) Project stage: Other SBK-L-18074, Response to Request for Additional Information Regarding License Amendment Request 16-032018-06-0707 June 2018 Response to Request for Additional Information Regarding License Amendment Request 16-03 Project stage: Response to RAI ML17088A6742018-08-17017 August 2018 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML18226A2052018-09-28028 September 2018 Redacted, Submission of Alkali-Silica Reaction License Amendment Request Draft Safety Evaluation to Support Advisory Committee on Reactor Safeguards Review of Seabrook License Renewal (CAC No. MF8260; EPID L-2016-LLA-0007) Project stage: Draft Approval ML18271A0692018-09-28028 September 2018 Attachment 2 NRC Staff Draft Safety Evaluation (Non-Proprietary) Project stage: Request ML18348A9512018-12-14014 December 2018 License Renewal Application: Review of Licensee Program Addressing Alkali-Silica Reaction Project stage: Approval ML18353A9542018-12-19019 December 2018 Report on the Safety Aspects of the License Renewal Application for the Seabrook Station, Unit 1 Project stage: Other ML19011A3562019-01-11011 January 2019 Board Notification Project stage: Request ML19022A4002019-01-22022 January 2019 NRC Staff Board Notification Project stage: Request ML19044A7682019-02-13013 February 2019 Emergency Petition by C-10 Research and Education Foundation for Exercise of Commission'S Supervisory Authority to Reverse No Significant Hazards Determination and Immediately Suspend License Amendment and License Renewal Decisions Project stage: Other ML19042A1102019-02-13013 February 2019 Presentation Slides - 2019 Seabrook Public Meeting Project stage: Request ML19056A4772019-02-13013 February 2019 Transcript of Public Meeting on the Seabrook Alkali Silica Reaction (ASR) License Amendment Request and License Renewal Application, February 13, 2019, Pages 1-158 Project stage: Meeting ML19050A3202019-02-13013 February 2019 Package from Stephen B. Comley, Sr. at February 13, 2019 Seabrook Station, Unit 1, Public Meeting Project stage: Request ML19056A5882019-02-25025 February 2019 NRC Staff Answer to C-10's Emergency Petition Project stage: Request ML19056A5862019-02-25025 February 2019 Nextera'S Answer Opposing C-10 Emergency Petition Project stage: Request ML19046A3832019-02-26026 February 2019 Meeting Summary of February 13, 2019, Public Meeting in Hampton, New Hampshire Alkali-Silica Reaction License Amendment Request and License Renewal Application Project stage: Meeting ML19057A3832019-03-0404 March 2019 Renewal of Full-Power Operating License for Seabrook Station, Unit No. 1 Project stage: Request ML19058A2162019-03-0404 March 2019 Update to Proposed Issuance of a Final No Significant Hazards Consideration Determination and License Amendment Regarding Which a Hearing Has Been Requested (CAC No. MF8260; EPID L-2016-LLA-0007) Project stage: Other ML19015A1832019-03-11011 March 2019 Notice of Issuance of License Amendment to Facility Operating License No. NPF-86 (CAC No. MF8260; EPID L-2016-LLA-0007) Project stage: Approval ML18204A2422019-03-12012 March 2019 Federal Register Notice - License Amendment; Issuance (CAC No. MF8260; EPID L-2016-LLA-0007) Project stage: Other NRC-2019-0075, Federal Register Notice - License Amendment; Issuance (CAC No. MF8260; EPID L-2016-LLA-0007)2019-03-12012 March 2019 Federal Register Notice - License Amendment; Issuance (CAC No. MF8260; EPID L-2016-LLA-0007) Project stage: Other ML19205A3942019-07-24024 July 2019 NRC046 - Summary of August 24, 2017, Meeting with NextEra Energy Regarding License Amendment Request on Alkali Silica Reaction (CAC No. MF8260; EPID l-2016-lla-0007) (Oct. 13, 2017) Project stage: Meeting 2017-08-04
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Category:Letter type:SBK
MONTHYEARSBK-L-23053, Radiological Emergency Plan (Ssrep), Revision 802023-06-22022 June 2023 Radiological Emergency Plan (Ssrep), Revision 80 SBK-L-23031, 2022 Annual Radioactive Effluent Release Report2023-04-28028 April 2023 2022 Annual Radioactive Effluent Release Report SBK-L-23044, 2022 Annual Radiological Environmental Operating Report2023-04-28028 April 2023 2022 Annual Radiological Environmental Operating Report SBK-L-23033, 2022 Annual Environmental Operating Report2023-04-11011 April 2023 2022 Annual Environmental Operating Report SBK-L-22093, 75 Day and 150 Day Submittal Letters2022-12-0101 December 2022 75 Day and 150 Day Submittal Letters SBK-L-22113, Radiological Emergency Plan (Ssrep), Revision 792022-11-16016 November 2022 Radiological Emergency Plan (Ssrep), Revision 79 SBK-L-22114, Independent Spent Fuel Storage Installation (Isfsi), Cask Registration2022-11-0909 November 2022 Independent Spent Fuel Storage Installation (Isfsi), Cask Registration SBK-L-22112, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2022-11-0303 November 2022 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration SBK-L-22094, Relief Request 4RA-22-001, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2)2022-10-26026 October 2022 Relief Request 4RA-22-001, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) SBK-L-22105, Supplement to 2021 Annual Radioactive Effluent Release Report2022-10-24024 October 2022 Supplement to 2021 Annual Radioactive Effluent Release Report SBK-L-22103, 5 to the Physical Security Plan, Training and Qualification Plan and Safeguards Contingency Plan2022-10-12012 October 2022 5 to the Physical Security Plan, Training and Qualification Plan and Safeguards Contingency Plan SBK-L-22102, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2022-10-0606 October 2022 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration SBK-L-22080, Submittal of 10 CFR 72.48 Report of Changes, Tests and Experiments for August 2020 to July 20222022-08-12012 August 2022 Submittal of 10 CFR 72.48 Report of Changes, Tests and Experiments for August 2020 to July 2022 SBK-L-22054, SBK-L-22054 - License Amendment Request 22-01, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-06-0909 June 2022 SBK-L-22054 - License Amendment Request 22-01, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections SBK-L-22044, 2021 Annual Radioactive Effluent Release Report2022-04-29029 April 2022 2021 Annual Radioactive Effluent Release Report SBK-L-22036, Steam Generator Tube Inspection Report2022-04-25025 April 2022 Steam Generator Tube Inspection Report SBK-L-22040, Radiological Emergency Plan (Ssrep), Revision 7822022-04-20020 April 2022 Radiological Emergency Plan (Ssrep), Revision 782 SBK-L-22024, Response to Request for Additional Information (Raj) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements2022-03-0707 March 2022 Response to Request for Additional Information (Raj) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements SBK-L-22003, Inservice Inspection Examination Report2022-01-24024 January 2022 Inservice Inspection Examination Report SBK-L-21126, Fourth 10 Year Interval - Inservice Inspection (ISI) Program Plan2022-01-0404 January 2022 Fourth 10 Year Interval - Inservice Inspection (ISI) Program Plan SBK-L-21135, Submittal of Changes to the Seabrook Station Technical Specification Bases2021-12-29029 December 2021 Submittal of Changes to the Seabrook Station Technical Specification Bases SBK-L-21108, Core Operating Limits Report for Cycle 222021-11-0404 November 2021 Core Operating Limits Report for Cycle 22 SBK-L-21106, Transmittal of WCAP-18607-NP, Analysis of Capsule X from the NextEra Energy Seabrook Unit 1 Reactor Vessel Radiation Surveillance Program2021-09-30030 September 2021 Transmittal of WCAP-18607-NP, Analysis of Capsule X from the NextEra Energy Seabrook Unit 1 Reactor Vessel Radiation Surveillance Program SBK-L-21105, Withdrawal of Emergency License Amendment Request 21-02, Service Water System I Ultimate Heat Sink One-Time Allowed Outage Time (AOT) Extension2021-09-27027 September 2021 Withdrawal of Emergency License Amendment Request 21-02, Service Water System I Ultimate Heat Sink One-Time Allowed Outage Time (AOT) Extension SBK-L-21103, Request for Exercise of Enforcement Discretion2021-09-25025 September 2021 Request for Exercise of Enforcement Discretion SBK-L-21104, Emergency License Amendment Request 21-02, Service Water System I Ultimate Heat Sink Onetime Allowed Outage Time (AOT) Extension2021-09-25025 September 2021 Emergency License Amendment Request 21-02, Service Water System I Ultimate Heat Sink Onetime Allowed Outage Time (AOT) Extension SBK-L-21098, Supplement to License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements2021-09-22022 September 2021 Supplement to License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements SBK-L-21083, NextEra Energy Seabrook, LLC - Relief Request 3IR-18 and 3IR-19 for End of Third 10-Year ISI Interval for Examinations with Limited Coverage2021-08-18018 August 2021 NextEra Energy Seabrook, LLC - Relief Request 3IR-18 and 3IR-19 for End of Third 10-Year ISI Interval for Examinations with Limited Coverage SBK-L-21067, License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements2021-07-21021 July 2021 License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements SBK-L-21049, Revision to Updated Final Response to NRC Generic Letter 2004-022021-06-24024 June 2021 Revision to Updated Final Response to NRC Generic Letter 2004-02 SBK-L-21056, Response to Request for Additional Information Regarding Seabrook Steam Generator Tube Inspection Report Review References:2021-05-20020 May 2021 Response to Request for Additional Information Regarding Seabrook Steam Generator Tube Inspection Report Review References: SBK-L-21045, Submittal of 2020 Annual Radioactive Effluent Release Report2021-04-30030 April 2021 Submittal of 2020 Annual Radioactive Effluent Release Report SBK-L-21044, 2020 Annual Radiological Environmental Operating Report2021-04-30030 April 2021 2020 Annual Radiological Environmental Operating Report SBK-L-21042, Response to RIS 2021-01 Preparation and Scheduling of Operator Licensing Examinations2021-04-22022 April 2021 Response to RIS 2021-01 Preparation and Scheduling of Operator Licensing Examinations SBK-L-21033, Response to Request for Additional Information (RAI) Regarding License Amendment Request (LAR) 20-02, Resolve Non-Conservative Heat Flux Hot Channel Factor (Fo(Z)) Requirements2021-03-24024 March 2021 Response to Request for Additional Information (RAI) Regarding License Amendment Request (LAR) 20-02, Resolve Non-Conservative Heat Flux Hot Channel Factor (Fo(Z)) Requirements SBK-L-21023, Radiological Emergency Plan (Ssrep), Revision 772021-03-0404 March 2021 Radiological Emergency Plan (Ssrep), Revision 77 SBK-L-20154, Submittal of Changes to the Seabrook Station Technical Specification Bases2020-12-22022 December 2020 Submittal of Changes to the Seabrook Station Technical Specification Bases SBK-L-20149, Response to Request for Additional Information in Respect to One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-12-0808 December 2020 Response to Request for Additional Information in Respect to One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic SBK-L-20146, One-Time Exemption Request for the Biennial Emergency Preparedness Exercise Requirements of 10 CFR 50, Appendix E. IV.F.2.b and IV.F.2.c2020-12-0303 December 2020 One-Time Exemption Request for the Biennial Emergency Preparedness Exercise Requirements of 10 CFR 50, Appendix E. IV.F.2.b and IV.F.2.c SBK-L-20144, Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-11-23023 November 2020 Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic SBK-L-20143, Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 004-022020-11-19019 November 2020 Withdrawal of Exemption Request Supporting Updated Final Response to NRC Generic Letter 004-02 SBK-L-20132, Fourth Interval Inservice Testing (IST) Program2020-10-21021 October 2020 Fourth Interval Inservice Testing (IST) Program SBK-L-20127, Generator Tube Inspection Report2020-10-20020 October 2020 Generator Tube Inspection Report SBK-L-20117, Response to Request for Additional Information Regarding Technical Specification 3/4.8.1 for a One-Time Extension of Allowed Outage Time License Amendment Request2020-09-23023 September 2020 Response to Request for Additional Information Regarding Technical Specification 3/4.8.1 for a One-Time Extension of Allowed Outage Time License Amendment Request SBK-L-20103, Inservice Inspection Examination Report2020-07-27027 July 2020 Inservice Inspection Examination Report SBK-L-20092, Response to Request for Additional Information Regarding License Amendment Requests to Adopt TSTF-411 and TSTF-4182020-07-13013 July 2020 Response to Request for Additional Information Regarding License Amendment Requests to Adopt TSTF-411 and TSTF-418 SBK-L-20068, License Amendment Request 20-01, One-Time Change to the Seabrook Technical Specifications A.C. Sources - Operating2020-07-13013 July 2020 License Amendment Request 20-01, One-Time Change to the Seabrook Technical Specifications A.C. Sources - Operating SBK-L-20085, Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic2020-06-16016 June 2020 Supplement to Exemption Request for Access Authorization and Fitness for Duty Requirements Due to COVID-19 Pandemic SBK-L-20077, Core Operating Limits Report for Cycle 212020-06-0101 June 2020 Core Operating Limits Report for Cycle 21 SBK-L-20057, Response to Request for Additional Information Regarding Degraded Voltage Time Delay Setpoint License Amendment Request2020-05-20020 May 2020 Response to Request for Additional Information Regarding Degraded Voltage Time Delay Setpoint License Amendment Request 2023-06-22
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARL-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2023-005, Response to Request for Additional Information for Seabrook Relief Request 4RA-22-0012023-01-26026 January 2023 Response to Request for Additional Information for Seabrook Relief Request 4RA-22-001 ML22307A1682022-11-0303 November 2022 Cover Memo and Response to C-10 Questions Regarding 2Q2022 Inspection Report - Corrected L-2022-157, Response to Request for Additional Information Regarding Seabrook Steam Generator Tube Inspection Report2022-09-28028 September 2022 Response to Request for Additional Information Regarding Seabrook Steam Generator Tube Inspection Report L-2022-106, Revised Response to Request for Additional Information (RAI) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements2022-06-27027 June 2022 Revised Response to Request for Additional Information (RAI) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements ML22109A0342022-04-19019 April 2022 Cover Memo and Response to C-10 Questions Regarding 4Q2021 Inspection Report SBK-L-22024, Response to Request for Additional Information (Raj) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements2022-03-0707 March 2022 Response to Request for Additional Information (Raj) Regarding License Amendment Request 21-01, Revise 120-Volt AC Vital Instrument Panel Requirements ML21280A2622021-10-0707 October 2021 Response Letter to N. Treat (C-10 Research and Education Foundation) Regarding 2Q 2021 Integrated Inspection Report Questions SBK-L-21049, Revision to Updated Final Response to NRC Generic Letter 2004-022021-06-24024 June 2021 Revision to Updated Final Response to NRC Generic Letter 2004-02 SBK-L-21056, Response to Request for Additional Information Regarding Seabrook Steam Generator Tube Inspection Report Review References:2021-05-20020 May 2021 Response to Request for Additional Information Regarding Seabrook Steam Generator Tube Inspection Report Review References: SBK-L-21033, Response to Request for Additional Information (RAI) Regarding License Amendment Request (LAR) 20-02, Resolve Non-Conservative Heat Flux Hot Channel Factor (Fo(Z)) Requirements2021-03-24024 March 2021 Response to Request for Additional Information (RAI) Regarding License Amendment Request (LAR) 20-02, Resolve Non-Conservative Heat Flux Hot Channel Factor (Fo(Z)) Requirements SBK-L-20149, Response to Request for Additional Information in Respect to One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-12-0808 December 2020 Response to Request for Additional Information in Respect to One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic SBK-L-20117, Response to Request for Additional Information Regarding Technical Specification 3/4.8.1 for a One-Time Extension of Allowed Outage Time License Amendment Request2020-09-23023 September 2020 Response to Request for Additional Information Regarding Technical Specification 3/4.8.1 for a One-Time Extension of Allowed Outage Time License Amendment Request SBK-L-20092, Response to Request for Additional Information Regarding License Amendment Requests to Adopt TSTF-411 and TSTF-4182020-07-13013 July 2020 Response to Request for Additional Information Regarding License Amendment Requests to Adopt TSTF-411 and TSTF-418 SBK-L-20057, Response to Request for Additional Information Regarding Degraded Voltage Time Delay Setpoint License Amendment Request2020-05-20020 May 2020 Response to Request for Additional Information Regarding Degraded Voltage Time Delay Setpoint License Amendment Request SBK-L-19120, Response to Request for Additional Information Related to Seabrook Inverter Amendment2019-10-30030 October 2019 Response to Request for Additional Information Related to Seabrook Inverter Amendment SBK-L-18106, Response to Requests for Additional Information Related to License Renewal Application Environmental Review2018-06-14014 June 2018 Response to Requests for Additional Information Related to License Renewal Application Environmental Review SBK-L-18074, Response to Request for Additional Information Regarding License Amendment Request 16-032018-06-0707 June 2018 Response to Request for Additional Information Regarding License Amendment Request 16-03 L-2018-068, Florida Power and Light Co. - Response to Request for Additional Information Re Decommissioning Funding Plan Updates for Independent Spent Fuel Storage Installations2018-04-0303 April 2018 Florida Power and Light Co. - Response to Request for Additional Information Re Decommissioning Funding Plan Updates for Independent Spent Fuel Storage Installations SBK-L-18027, Supplement 59 - Response to Final Requests for Additional Information for the Safety Review of the Seabrook Station License Renewal Application - 10 CFR 50 Appendix J Program2018-02-28028 February 2018 Supplement 59 - Response to Final Requests for Additional Information for the Safety Review of the Seabrook Station License Renewal Application - 10 CFR 50 Appendix J Program SBK-L-18028, 0 - Response to Final Requests for Additional Information for the Safety Review of the Seabrook Station License Renewal Application - ASME Section XI, Subsection Iwl Program2018-02-28028 February 2018 0 - Response to Final Requests for Additional Information for the Safety Review of the Seabrook Station License Renewal Application - ASME Section XI, Subsection Iwl Program SBK-L-17202, Response to Seabrook Station, Unit No. 1 - Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment to Delete Operator Action and Request for Exemption2017-12-14014 December 2017 Response to Seabrook Station, Unit No. 1 - Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment to Delete Operator Action and Request for Exemption SBK-L-17204, Response to Request for Additional Information Regarding License Amendment Request Related to Alkali-Silica Reaction (CAC No. MF8260; EPID L-2016-LLA-0007)2017-12-11011 December 2017 Response to Request for Additional Information Regarding License Amendment Request Related to Alkali-Silica Reaction (CAC No. MF8260; EPID L-2016-LLA-0007) SBK-L-17180, Supplement 58, Revised Alkali-Silica Reaction Aging Management Program2017-11-0303 November 2017 Supplement 58, Revised Alkali-Silica Reaction Aging Management Program SBK-L-17169, Supplement 58 - Non-Proprietary Enclosure 1 to SBK-L-171552017-10-17017 October 2017 Supplement 58 - Non-Proprietary Enclosure 1 to SBK-L-17155 SBK-L-17170, Non-Proprietary Enclosure 1 to SBK-L-171562017-10-17017 October 2017 Non-Proprietary Enclosure 1 to SBK-L-17156 SBK-L-17155, Supplement 58 - Response to Request for Additional Information for the Review of the License Renewal Application - Building Deformation Analyses Related to Concrete Alkali-Silica Reaction2017-10-0303 October 2017 Supplement 58 - Response to Request for Additional Information for the Review of the License Renewal Application - Building Deformation Analyses Related to Concrete Alkali-Silica Reaction SBK-L-17156, Response to Request for Additional Information Regarding License Amendment Request 16-03 Related to Alkali-Silica Reaction2017-10-0303 October 2017 Response to Request for Additional Information Regarding License Amendment Request 16-03 Related to Alkali-Silica Reaction SBK-L-17133, Clarification to Supplement 55 - Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application - Bolting Integrity Program2017-08-11011 August 2017 Clarification to Supplement 55 - Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application - Bolting Integrity Program SBK-L-17103, Supplement 55 - Response to Request for Additional Information for the Review of the License Renewal Application - Bolting Integrity Program2017-06-20020 June 2017 Supplement 55 - Response to Request for Additional Information for the Review of the License Renewal Application - Bolting Integrity Program SBK-L-17087, Supplement 53 - Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application - LR-ISG-2016-01 - Changes to Aging Management Guidance for Various Steam Generator Components2017-05-25025 May 2017 Supplement 53 - Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application - LR-ISG-2016-01 - Changes to Aging Management Guidance for Various Steam Generator Components SBK-L-17082, Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application - LR-ISG-2016-01 -Changes to Aging Management Guidance for Various Steam Generator Components2017-05-19019 May 2017 Response to Request for Additional Information for the Review of the Seabrook Station License Renewal Application - LR-ISG-2016-01 -Changes to Aging Management Guidance for Various Steam Generator Components SBK-L-17063, Response to Request for Additional Information Regarding License Amendment Request 17-01 One-Time Exigent Change to the Seabrook Licensing Basis Regarding Service Water Cooling Tower Functionality2017-04-0808 April 2017 Response to Request for Additional Information Regarding License Amendment Request 17-01 One-Time Exigent Change to the Seabrook Licensing Basis Regarding Service Water Cooling Tower Functionality SBK-L-16205, Response to Request for Supplemental Information Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency and EMCB-RAI-22016-12-30030 December 2016 Response to Request for Supplemental Information Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency and EMCB-RAI-2 SBK-L-16196, Response to Request for Supplemental Information Regarding License Amendment Request 15-02, Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive...2016-12-15015 December 2016 Response to Request for Supplemental Information Regarding License Amendment Request 15-02, Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive... SBK-L-16186, Supplement 50, Response to Request for Additional Information for the Review of License Renewal Application Providing Changes to Buried and Underground Piping and Tank Recommendations2016-11-23023 November 2016 Supplement 50, Response to Request for Additional Information for the Review of License Renewal Application Providing Changes to Buried and Underground Piping and Tank Recommendations SBK-L-16190, Response to Request for Supplemental Information Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency2016-11-17017 November 2016 Response to Request for Supplemental Information Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency ML16314D4272016-11-0707 November 2016 Response to NRC 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.1, Flooding - Submittal of Flooding Hazards Reevaluation Report, Revision 1 L-2016-188, Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools, Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f)2016-11-0303 November 2016 Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools, Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) SBK-L-16170, Response to Request for Additional Information for the 04/22/2016 Steam Generator Tube Inspection Report2016-10-27027 October 2016 Response to Request for Additional Information for the 04/22/2016 Steam Generator Tube Inspection Report SBK-L-16165, Response to RAI Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency2016-10-27027 October 2016 Response to RAI Regarding License Amendment Request 16-01, Request to Extend Containment Leakage Test Frequency SBK-L-16162, Response to Request for Additional Information Regarding License Amendment Request 15-02, Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors2016-10-27027 October 2016 Response to Request for Additional Information Regarding License Amendment Request 15-02, Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors SBK-L-16156, Response to Issuance of LR-ISG-2015-01 Changes to Buried and Underground Piping and Tank Recommendations2016-10-0707 October 2016 Response to Issuance of LR-ISG-2015-01 Changes to Buried and Underground Piping and Tank Recommendations SBK-L-16134, Response to RAI Related to Severe Accident Mitigation Alternatives License Renewal Application2016-09-0606 September 2016 Response to RAI Related to Severe Accident Mitigation Alternatives License Renewal Application SBK-L-16121, Response to RIS-16-09, Preparation and Scheduling of Operator Licensing Examinations2016-07-20020 July 2016 Response to RIS-16-09, Preparation and Scheduling of Operator Licensing Examinations SBK-L-16044, Response to Request for Information Regarding the Flooding Hazards Reevaluation Report2016-03-28028 March 2016 Response to Request for Information Regarding the Flooding Hazards Reevaluation Report ML16067A1642016-02-26026 February 2016 NextEra Response to NRC 12/23/2015 Request for Additional Information for ASR Ceb and RHR Vault SBK-L-16022, Response to Request for Voluntary Response to 2.206 Petition Regarding Methods for Identification of Concrete Affected by Alkali-Silica Reaction2016-02-23023 February 2016 Response to Request for Voluntary Response to 2.206 Petition Regarding Methods for Identification of Concrete Affected by Alkali-Silica Reaction SBK-L-15202, Transmittal of Response to Requests for Additional Information for the Review of the License Renewal Application - Set 25, Relating to the Alkali-Silica Reaction2015-12-0303 December 2015 Transmittal of Response to Requests for Additional Information for the Review of the License Renewal Application - Set 25, Relating to the Alkali-Silica Reaction 2023-08-07
[Table view] |
Text
Enclosure 1 to this Letter Contains Proprietary Information Withhold Enclosure 1 from Public Disclosure in Accordance with 10 CFR 2.390 NEXTera(
ENERGY ~
SEABROOK October 03, 2017 10 CFR 50 *>f'."
Docket No. 50-443 SBK-L-17156 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Seabrook Station 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
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 NRC Region I Administrator J.C. Poole NRC Project Manager P. C. Cataldo NRC Senior Resident Inspector L. M. James NRC Project Manager, License Renewal Mr. Perry Plummer 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 Page 2 SE BROOK D1.l>1C*~ c11
- 11<uc n 11<L'>. Co:-.tf't)'\l
- 1~. 1:1.)t 'IPMD-: 1 A *t1 Rel'i ion 16 STA'fl O~ Svsrr t~ Section 3.8 UF. A H D sign of Category I Stru tul'\.'S Pai.ie 147 3.8..t.7 Te~tin g and fn~')ervic Snn*eilla nce 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 co nducted 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 . *1he total exrxinsion of t\SR-afli:ckd nrc.L~ is limited l o 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.
- 1he 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'T UIU :: i\ 1 01\ I TOHl ~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 93-0 1 " f111fit11t:1 G11idt'li111* .fi*r Mo11itor-i11g i h<' £Jecriw11,*1. o Mai11M1m1c,* at N1w/e11r l'r111w f'lnnt" '. nod ith guidan e rrnm /\C' I 3.J9.3R, "l.nihmtion 0f fx i\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 gui dan~.: of thl">C thn:,* <locum *111. . *1h
- Prvgr.im j, irnplememed to monitor the i:on<lition or st ructures 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 rroR INC
- 1he 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 T he , tnicturc l\fonit ring Program rtrf rrns 1 isual in ~p..'Ct i ns of the c0ncretc slrncture' ut . c:1bmol.. for i ndi *~thm\ of the prc,cnct* of alkali*silica r-::uct ion (A~R) . ASR inl'oh*c, tht form tion or 11 nll,ali-silicn gel 11hich e.\pa11ds \\ht:n it. hoorbs \l <ll ~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 mdd ng \\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 D r IGN OF ST UC'l llllt:S. CoMI'O\JL1' J~. EQLlll'Mf:'\f );IJ Revision 16
, T TI O'! YSTl:MS ection .
UJ-'AR U
- ign <>f Categ r) I , lruttures Po:c 148 har<1clc ri1cd h) u nct11t1rJ.. or .. r;1t tern" of cmcJ..s. 1icm *rad.ing luc to ASR j, gene rated thr ugh forces applied by the c:-p:mdinu ;iggregate part icle m1d lor S\\elling nf the alkn li-il i 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
- posi t> m the con r le urfuce. The ge l 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>
idcm ified, an ernlunti n will be perfonned to determine furthe r actions.
Moni toring of crncl-.. grol\ th i ~ u,t.-d to ill.st.">~ the in-plan
- ex pansion 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 th i din*,*1ion gnin
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 efll oresccJJ<:e. A. R ma~ also I:>" dctcctl'd or con fi nned b} r elll(I\ al of concrete c res and subsequent p.:t rogrnphic nnal) *i'.
/1 Combined Crucl.ing lndc:\ ((' ' I) is c tablishcd at t hrc~hold:. at 11hi ch stru *tur 11 C\ aluatit111 i nc..:c~ar~ ( S<'I.' table bckt\1 ). The Crackini,? lnde:1. (C' l) i
- 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 CC I 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 fo r e1 id n c of further degradation. The chang
- 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 mm lm in the 1crtical and horiLOntul dire tion>. 'onrn:tt* era *J.. I\ idihi. I > than 0.05 rnm cun nt*t b
- uernrald) measured and relio bly n:peuted \\ ith standt1rd. 1i ual inspecli n CtJUipm.:-111. A CCI of 1.0 mm 1m or greater require' structura l C\ nf11 *. tion (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 frequ cnc>> and added to the through-thickness \pans i m monitoring 1*in cxtcn om*tcrs. All I ation meeting the *1ier 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* ahili l) to vi ,ua ll~ detect crae!.iog in c .\ po~~d
- urface~ ntr.1.l.ing it an cffccti1e initinl d tect ion par.imc tcr.
~ l rur t urn l Jl commtndation for lndMdu*I Tltr lllo11horing rlltrln C'on ttlt Com1>0nu111 Proi:rnm <'nttgol'}
St:uclurJI I ' ah.raliun l 1n.1c,*..-rtJ~!i: l mpkmcnl nh~lk<J Al>R 1.0 mm:m or l".r att:r c*n mhitl~J (ri:q u i r-:~ fu1* 1!1~r llli~ ll;h *rin~- s.u1. h a*1 thfo.1,g.h ..
C' \J hr.1t l{'O} \\all" p.Hh1on n10nitt 1cin~
l'r*cl.i nr to.I.:' f( '< IJ 1..Lin ' C"tcn un 't~rs
U.S. Nuclear Regulatory Commission SBK-L-17156 I Enclosure 2 I Page 4 SEABROOK 01..,1 iN OI* 11n ' ttrR i:s. Co~ ll'O\L 1 , EQl lf'lll[r\1 M m Re\ i ion 16 STATIO:-i . e tion 3.1!
UFS n Pngc 149 I O.S mm **m ,,r gtt=.lk't ( 1 4 IJL1JJlli1.11ivc \lM it.oring aod *1or greater 1h:m 0.5 mmlm in Il 1\c *crtahlc \\ilh rr.~nJin~ th<'. 1mkal anJ horit0n1al Jif\..~1iO U.:!t.
I r>dk L...ncic"i I' ll~ arc;> will\ *i IJJI f'l'C~CllCC of t\SR(. dcfill('d in l l l\\',\
n221 ;u;*cornr>.mi.'<l b) "l"I "ti '
tlnn I).* mm-'m in th.: ' crtk,11anJ I h*>rit 11t.il dirc.:1ion,,,_
1\ rea ha\ th* inJ ic.llion .. (lfpatti:m knuti n~ in'i'cdi\>n as pn:~crit'l\.*<l b~
ra..:h1n' M \\OI er inpn:,
- No \ ;,uJI th.: l\1ructur.il 1'.t.mhorinr. Pre cldm S) mrtom ~ ol A:]{
- 1he Alkali-Silica lk1.-:t i 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*alulll ion 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 uppr 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.
CC l°S limitation fo r ht:<I\ ii} reirlfo r.: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 e calc test program~ to plntcm1 ut u rdativcl} 1 it l.:H:I 1
( I f 1n::u111ulated ~t rain (uppn '\imatd~ I rnm 1m). 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-. use ful rnr the d te,*t i n nnd monitoring of SH at the initia l s1age.. ;m addit ional nwnitorin' p;irameter in the Ill* f-pl ane 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 na l 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 i on~ here the potential for deformation b likely 1\ill be mon itored for displac.:mcnl \'ia/ o,*atil*n*spcdfic 1 r:c h11 i4 uc~.
3.8.4.7.3 Ull lLUING lll:FOH IATION 10.:'\ffOHli G PJWGl< M The Building Dt'fo m1:n ion Monit<1rin~ Pl gram i a pl.mt pccifk pmg r.tm i1111,l *1n *nt.::<l undrr the rx isting 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: 1 ofl TABLE3.8-18 TABLE3.8-18 ASR EXPANSION LIMITS FOR STRUCTURAL LIMIT STATES Structural Limit State ASR Expansion Limit Shear Through-th ickness: See FP# LOI 020 Section 2.1 (Ref7) (2)
Flexure Volu metri c: See FP# IO IOSO Appendi x 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.
(2) The through-thickness expansion limit for shear, fl exure 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, fl exure and re inforcement anchorage identified in FP# I 01050, Appendix B, Section 5 are di fferent. 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 Revision 16 STATION SYSTEMS Section 3.8 UFSAR Design of Category I Structures Page 653 3.8.6 References
- 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
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 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.
~ccaney Regional Vice ~ orthern Region NextEra Energy Seabrook, LLC 626 Lafayette Road Seabrook, New Hampshire 03874 Subscribed and sworn to before me this 31W dayofOctober, 2017.
QfwiA:N~
Notary Public L My commission expires 3 fl /22