ML12334A734
| ML12334A734 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 12/31/2010 |
| From: | Office of Nuclear Reactor Regulation |
| To: | Atomic Safety and Licensing Board Panel |
| SECY RAS | |
| References | |
| RAS 21569, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01 NUREG-1437, S38, V3 | |
| Download: ML12334A734 (255) | |
Text
{{#Wiki_filter:United States Nuclear Regulatory Commission Official Hearing Exhibit NYS00133I Entergy Nuclear Operations, Inc. Submitted: December 16, 2011 In the Matter of: (Indian Point Nuclear Generating Units 2 and 3) V\..~P.R REG(J<.q)<o ASLBP #: 07-858-03-LR-BD01 l~\ Docket #: 05000247 l 05000286
" 0'!:
Exhibit #: NYS00133I-00-BD01 Identified: 10/15/2012
>-
'" ~ Admitted: 10/15/2012 Withdrawn: Appendix A
~
'1"'....1-: 0' i Rejected: Stricken:
" .*** .. " Other:
December 2010 A-1257 NUREG-1437, Supplement 38 OAGI0001367E_00244
Appendix A
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1 NUREG-1437, Supplement 38 A-1258 December 2010 OAGI0001367E 00245
Appendix A
Dear Pat fa1ciano,
.
Thzmk you v-ery much for the educational tour of Indian Point. Honestly, 1 was always afraid of the dnngers of IlUclear power plants, all.d easHy gave into the fearful media coverage. After learning about the mechanics of the plant, the beneficial etJectsindusirially and the friendly impacts envirommmtally, 1 have det'ill:itdy become a nuclear power supporter. }'be containment of the radioactive material and the minute amount that could ever afiect stUTotmdillg people is comforting as I hve
\>;iithin a I() mile radius ofthe planu;, The lecture v{as both infonnative and interesting and 1 thoroughly enjoyed the presentation, Confident in my ahility to detbnd nuclear energy, J have already found myself enhgluening others with the knowl.edge you have besl()wed me with. Thank you tOr HIe tour as \"cU, it \va.<; a great experience and I know the Information J received f ",ill rernemher for life.
Just as. the generous items received in my "goodie bag" say, Indian Point IS sUfe, >liiecure and vita! and with my ue\"ly gained knowledge, 1 have evidential Slipport l Thank yotl, Chelsea Wendhnger (Hackley Sello(Jl Student) 1 December 2010 A-1259 NUREG-1437, Supplement 38 OAGI0001367E 00246
Appendix A
! just wanted to take lhi~ opponunity to thllJik y(m fl)! allowing our $Chool to visit IndiMl Point Power Plant. r Via$ pers,mally fa!lCin,HCd by the predsioll and intracity of Inc te<:l1n()lo;§!y u;;e'll at Iudiml Point. V(Hl gave a v<.:~ry wd.l doue preSCIHathm\ln !he power plant Lh:u wa,.. entirely factuaHy bas~d, whidl 1 \'cry !lh!(~h apprecined ((> deltr 1.11) so(Ue rum(lr$_ Through the media I devch)pt~d ~! bia~ed vi~\v l!)wnnl the plallt I thought if eV<2!"
the sliglnest ,hing were to go wmng, or jf it was aU!lcked the df('(~ts would bt: Ciltastmphk. f now Know that is )1:(l1 tnlC:. I wa~ vt:ry impressed with the fll!..~ilities and thcwann lltmosph{~~: from ,he tedlnicians at (he -pIanl.. I. ",Iw appreciated t1'K~ high level ~)f ~~Ilrity, and while they were not as warm ilS the t(~chl)idan" I !Inacrs\mlcl !he i.rnp(Htance of maintainitlg a vcry !ugh. level of security. lll()w think thai !1udcm' energy is viabltLahernative to fossil fllek Nuclear energy cre-ittcs absolu!dy no pollution cmis~ iom, hu! there llrc draw-back'>. We have to think aO(llJt thermal poHution and s("mgc. of letha.! nl.dioa(:(iv{: waste. But, fossil Cuds arc n1(lrt (If a pmhlem fur ~)Uf atmosphere at ttl!: ptcscnt moment. so 1 think if we cn:oatcd ,m !;;Ji.U'ol storage tank i'm*t.he mdi.oac-tivc waste, or simply find ways of making the waste inert ;l!Jd n(~tl--lcthHl, h;l.rn.es~i.ng md.i()adive energy woule! be jll.st as Entcrgy .'>ays., "Safe, Securc and Vit~~I." I wmf( gn (m a1mut what. should be done, btl!. 10 simply thank you for giving me the educational OppOrllltllty to Sere 'what hamcssing JIIlclear cm~rgy is really lih~ firs, hand. With g!'elli: appreci.ation,
#:h~
" Ty Smith 1
NUREG-1437, Supplement 38 A-1260 December 2010 OAGI0001367E 00247
Appendix A 1 2 De.at Mr. r-~A\c lO.V)(/ I Thank you S'lI much for giving Il~ a very inicmnativc (uur and presentation of Indian Point I !carned s{) much about the intricate working.$ of a nuclear power plant,espcehll.!y in regam to the fue.! rods and urllnium pellets, I had no idea of how small they were, lind how tll*c)1 cOlllllinment buildings are, how .Iittle of .an eft'eel eertain amounts of radiation can have on the miles aWII)' from its origill. In :<ddition to the infomlntion ! learned during the presentation, :I tl\{)f(mghJy enjoyed Ulkinga tour of the power plant. It gave me a;Jl idc:fI. dhow many components are induded in the pro(e~s of crellting energy t!J.fI)ugh the lise <)f uranium. Tlte aml)IUlts of water pumped into the plant ellcn hour stll!wed me, lU, did Sile (If the c(1mplex. The size (If the room that (<:Iuwlled UJe r~;JIctor UIUlH~ wus iIS!o!1iBhing! One of the m(~st impressive things I encountered at Ihe plant, though, wa~ the secllrily. The (,let that :students were obliged to pm,s through II metal detector, a oomb detect()J and two sets of radioactive dctect!lr8 was very reassurillg. aHd sll{!wed Ihe lImHUHI Agllil1, I would I.ike to thlmk yon s() much for (lUI tollr lind pmsentalioll, Hnd ! know each one of us had. all eled:rifying time: lit Indl.al1 P~)i.nt. 3 December 2010 A-1261 NUREG-1437, Supplement 38 OAGI0001367E 00248
Appendix A 1 February 2Siil Z006 DCllI Mr. FilJciallo. I. wanted io thank you for the informative lecture and lour you gave !Jaeklcy School last \Ved.n,,\~day. From rhe Iccture,l found thJ<t Iluckm: plants, especially those as
$<;:cure a:; Indian P,>int, ,m: much ~afer than the: publk tcud.~ to think. N1.IckClJ" pow<..~ is dean bW:tling, safe, and seciirt::. I believe that nudcar IXlwer wii! be vcry itnp(lrtt.mt in OIlY futures (a$ Yi$ing adult:;) as the puhlic h::arn,;; hnw sHfe it really is. I e.f~i{lycd the lour immensely, and I Joved how we had access to many scdiOB$ ofthe Illilllt. Thank ym3 ag<lin for hdping me \iHdct:;tmIGS the tHiih about H\,lckm: plan!:; and the many p~)sitiyc eil'ccls tbey h,.n'e (HI soddy, Thank you!
Sincerely. _ 1{;[Qf3.£t:. K.:"lte Bihi 2 3 NUREG-1437, Supplement 38 A-1262 December 2010 OAGI0001367E 00249
Appendix A 1 2 December 2010 A-1263 NUREG-1437, Supplement 38 OAGI0001367E 00250
Appendix A
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Appendix A De2.f )'",!r. Vakimw., I ,un gmtelhl to YOll and w your (:(H"Scorts tor edU(:i~ting me ilnd my d;l,~S about l1w::k:ar p(j'i\iC~< and atml.ll th,,~ Pl"(;!:;;;;~" occull:ing llt indian P,)im, W(; all k~,rnd ,\ gre,lt d;;;nl, ,m.e! y<)tl
~et\"ed ;3$,1 gl'.;,at C(1l3nt<:l'baJ,mce til til", <werwhdmin~! sk\,,' of had ptc~ss Ih<1t Indi;m Point !ta, <\
te£l!k~!H':Y to ge!lerak~ Fr,mkly" giv,;;n all the ncgatiH~hyp.;: ;l.b()l,l! nuclear power, I half.cxjJccttd tt, sec btmdl ,I of n1tlJ \;citntisb trud.:i.l1g around \.....eap()H&'g,rad(~ pluk,nlum on 'Iittk hnncic:1,t, C\,tTywbel'c, I think <; fair number ol'my dassmatc w'()r~ afn1id tim! at ilny mlnut~ a 767 might ,i:ml ,U!!O mw ill the containment building,s amI nllkx: \VC$tdl;;;"~!CL CklUly, you can su: how bildly we: nc~;ded edm:HtiolJ, I think Ihat what we learned hlS\ week goes fhnhu than j1l5111<)w l1uclear power w~"};k", and ~dlY li)dil;ltl Poitil is iJ()i the Ihl'(:,,\ w(: thin],. it is, W,~ nise> S~l'\( tlw p,~<)pk, ~i~ICh as you.rself, working iit thepl21lL AS;l (wdlll: gm(\ef vyi.ng ii)f ;ldmlssion to college, I'n, btnm on a lot of tours latdy. I ,vi.si1 tnm the students giving tb,)&(~ C()liejl;l~ hHlrs .had ot:en half ;3$ (,l1lhw;lllStic and p;:t.'isi<:m<lt\."; nb-cnn their colleges ;;r.s YWtllUld yom: wJkagl.lcs wew liOnll! nm::kitf pnwel"' I think th<lt
'WI!: mi~i()i {)H~rsigh!. that the public ha::; in '.""rili.ng nf llt<d()flfp')W"r tiS "'iii i::; tht~ qmliity of tho;;"
wmkmg at your facility, I saw ll01hillg but sirlcerity ::lnd integrity, and lhe d"dic*ati.on to K(:(:p lmliall Point it) tnp vMrking ordCL."I fed ;~afe krtOwing lha! t!w IllId<::;:u PllW(;TJ1i~nt Ul my c(mnty is in such gOl)(1 !lunds Tlmnk yo).! (lgain, for you !H:\VC shown u:'> 11 ~idt' (If un lsslIIe ihlll. ",..ill <)nly gmw in imrX)ftance, lhalIWb~)d.y d~;: c<)uld s!mw U$. 1 December 2010 A-1265 NUREG-1437, Supplement 38 OAGI0001367E 00252
Appendix A Thank you f\H iaking tilU~ Qui of Y~AIf busy ocheduklB educate us on the benefits ofnurbu pOWCf phmt.s. I did not know hC}w safe they, in fact, were and hr.,-w liuk r.idiatio!l even a ,\'orh~r is eXJXlsed to there, The !no"t itUcf'lS!ing part I)ftlm cn!irc trip for me w;~s the video that denmnstratedhnw' virtw:dly indestructihle the transportation talik~ w<::re. OvcwlL the trip was very ;nfornmtiy.:: and gave me II new per~pcctivc 011 rWdCtll energy. Thanks aga.in for Y(lUf i\me, 1 NUREG-1437, Supplement 38 A-1266 December 2010 OAGI0001367E 00253
Appendix A 1kallh . ';0 tI\.,,~~ t -h.b j '\.1l-. M."tl ~i .... t-U!!..1k /:.,)., ~j (. ~..e..cL l,-i<w. rk-:J <d!{" U~
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1 December 2010 A-1267 NUREG-1437, Supplement 38 OAGI0001367E_00254
Appendix A Jonas iVls.lrlllss AI' EnvironIllental Science CI,,:;~ Fdml3fY 27, ZO(){i
Dear lI.{r. FakLlno,
fhank yut> so mudl :fi)r ymlT lour of !.mliafl Point.. The tom and letlllU wa~ very concerning nuckar energy, r !earned many things while on the tour. MId I 11ll1l1aW in Th;mk you very muc.h for giving lIS ym!f lime:, and touring us around Indian FOlnt Sincerely, 1 NUREG-1437, Supplement 38 A-1268 December 2010 OAGI0001367E 00255
Appendix A
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Appendix A
Dear Mr. Falciano,
Thank you very much for allowing my class to visit Indian Point. I won't lie; I had a lot of reservations about nuclear power from what I had studied previously. You a.nd ,Jim., my tour guide, put aU of my concerns to rest. You were very informative throughout your presentation and as was Jim during the tour. The passion that both of you had for your job was incredible! It was really very impressive and I thank you for doing your job to power my house and therefore my computer so I could write this note! Thanks a.gain, 1 2 NUREG-1437, Supplement 38 A-1272 December 2010 OAGI0001367E 00259
Appendix A 1 i'" l'he Masters School --------- ~ r'
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_ .. _. I)~ar Mr. fil!ciano, On b0half of the: e!1tire fj'" grade class, ! would like to ~hilnk vou for taking tin'!'!; out of ynut schedule to give Q presental"'H) 011 Indiim Poim "nd !living an informal discussion talk to ~<lrs Geofile's.
>tll<Jeflts. Th~ ~d0as pres~!1ted in y01Jf f'owerPoint haye gil/en student~; the took. to obj~t:!h.eiy evaluate the u,e of nudCilr power in tile U,S, \Ve hope to continue uSing vou a~ a rf.'Source to help enridl OlJr ClJrriwlutn.
SwttCom 2 3 December 2010 A-1273 NUREG-1437, Supplement 38 OAGI0001367E 00260
Appendix A NE\\.' R1KHH.LJ<: \1u;u SCIIOnL
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Pat Faciano Indian Point Station Broadway & BleakIey Buchanan. NY 105'1 i New York, NY 10032 May 29. 2008
Dear Mr. Fadano,
Dr" Archibold and her students join me in thanking you for your informative talks on nuclear el1ergy We are truly facing an energy crisis and your lecture made U$ all aware of tl1eimportance *of cOl1sideril'1,g alternative sources of poweL It is beneficial 10 involve the community in the education of our youth. Your lecture seNed to make the students more aW<:l.re of the problems the nmd generation will be facing. Urging them to find solutions enabloo students 10 think about thelf effect en our frag:ile planet. I look: forward to seeing you again soon and hope to invite YOu back to speak to (JUt students next yeaL co: J.Archibold J. Pollock 1 NUREG-1437, Supplement 38 A-1274 December 2010 OAGI0001367E 00261
Appendix A The L,egisiature of Rockland County JOHN A. MVRPHY l.{.'R~shh:;:r Tm.i!,I'fl (If(~~.ngt.:*t{Hq:;~. ~ Pi~*rf:1f;t l6 Bdli~!' &: l'in."oe ("mUlino" G:)\.'¢:ff1n-wi11 (~pl:.r;{<<-i<.nt!{. C'i'.mlUUJJ<:'.e' Angus! 21, 2ntl6 l\.'1r. Tilol]:}.3.S Fitl.p'll:l:ick Vice Pr~s<ident Oiuhuni !":JIll1W;, l1;C STime, Sqmltt' New York NY 10036-6;i3() Ms.. Kathleen Mc!\4llUin Communic<lt.iof!.sl\*lal1ager Ente.rgy Nllckl:r Ope.r(ltkm, lnc [~dhlfl POlat Energy Center 205 Bf!)Hthvay, Sui.!!! 1 IlIl.chl!!lal1, NY 105n,0149 JMr. Patrick F;J.kitmo OlliTeBch Cil(IHlin.3tor Indian Point Energy CommUflsc,ltiom; 205 B!<)u~lwaJ' Suitel Bu.chanan. NY W511-()249
.De.Hf Kathiee:), Patrick '11'1(\ Th0JJ111S:
I was so i.mprcs$(ld by your prokSSW!)cllism. th:1I1. am mOYe4 1(1 sugge~1 a similar '<'!sit by my COHmy L!;.'>g!sl;;liVt' CC>lICllgtlCS who m,~y nol have el'ljoyoda.n (lPP(lItun.ity 10 v.lsi! th~; C{,llter to d.alc. 1 would 'llso l!k<~ In !m:J!H.J::,*ljh' Town n~)flJd <:If th~~ T(')w.11 ;)f Or.311geWwll, New York, in which lies my C,)L1l1i.y Leghlative Dharicl aml, where! have r.esidc.d fix
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December 2010 A-1275 NUREG-1437, Supplement 38 OAGI0001367E 00262
Appendix A August 21, 2:00() Likewise, 1 \voukl Jove the Publi,.heriEdjl:or 01' our higbly rC$jX',eH-:J ,Ycck}y newspaper, the "Ollr. Town" to bl': inviiccl, l:l is mailed free Ill, ~~vety home irl the Town <)1' Orangeti}Wll every week, Very fnli y yom:~, (\, -l"*)\..L!,;'j~*LJ
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JOlIN A. MURPHY County Legl slatnr 1 NUREG-1437, Supplement 38 A-1276 December 2010 OAGI0001367E 00263
Appendix A Page 1 of I Faleiano, Patrick From: GRAVES, ALLISON LESLEY 8eot: Friday, December 08,2006 2:00 PM To; Tlloobalcls, Kenneth: Fay, Deborah; McMullin, Kattlle~m M; Carj:Rno, ROllald J: FafCiano. Palri.ck Cc; Kanslef. Michael R; HEBERT, CURllS L: Ha.lvorsen. Jerald V
Subject:
HOlJse Committee slaff ***Indian Point tourfollow*up Oeoo, Ka!hy" Pat and Ron. Thank you all for conducling and armngi~ tha tour of Indian Point last: Sunday. It was a very thomugh and educaliom'11 lour. <HId I appreciate you 8CCQmmodatlng the House Committee s1affs schootlle and giving US so mLlch of your lime on Sunday. The knowledge P!!ct and Ron oifur&d M tntl four W!!lS fan.t9£Dc. As 'Iou know, theM rout stalfi'!rn repmsE'..nloo tmth the Oemocranc and Republican st.aff cf 1ha Hou.,>~ Homeland Se,curitY Commltte& - a comm~ that could potentially heip or hurt (l~lr nuclear fleet. In fa!;t, ! saw Colleen O'Keefe last ni@hl. Colleen was the staffllJlhat am3inged the lour. She complimented the lUlu and said how impressed they all Wefe wm'!the facility, lhe se<:Urity measures, our emp.loyeas ~jti$t overall imp:ress.ed. She sald, "in met, we wIIre talking about it this weel<: -flOW safe we WQlJId all fOOc! Ii.Vl!l9 flak! to a nuclear poWer plant." ShE! went on wsay l10w mUch they appreCiated Us oondlkltl:ng the toUt an Sunday and that we werQ muoh roore accmnroodating than the folks all tJwlr lour of Plum Island th~ flext day. Job ~I! dene! Thank you for showing some of I~selcey Hill staffers what a well-.rufl facilUy Indiall Pm:nt is. Have a good wookend, Jlllison A.lIison Graves Director. F~eral E'm:lIgY Poficy ENTERGY CORPORATION 101 ConstlMiotl Ave" NW, Suite 200 East Washjngron, DC 20001 202-530-7300 (office) 202-530*7350 (fal() 202..!l574022 {cell}
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December 2010 A-1277 NUREG-1437, Supplement 38 OAGI0001367E 00264
Appendix A No\)crnbcr '7. 2007 Mr. I'atrick Fall~ia(1o, Outreach C(!oriliuak1r {PEe C<)nmlll.nication~ l:mha!! I'oilll Energy Ct:tJt~r 45j) nrot.t,h':ay PO, Box 249 Bl.d"man, NY 10511-{)149 11 \\'as a pleasure to have you speak with our Green Team on W,xlllcsd,(V, October 14, 2()07. Your presen!:~ti<)X1 was illvaiuahle and <1 l.earning ~xp~ri~l1ee [<)t all those ill attend<luce. Thank YOl1 i~-'r d,ulfying (he misconceptions regard.ing the function :)nd safe op~l'aliofl ofltldian POint. I '<viI! b0 in touch shortly w anange tor a lour of/hi:) Il"ldiilU Point Po,ver PJantlor OHf GTe;;;Jl Team. Seymour R<)senfeld ProFcss<)I Engineer'ing Tedmology (irecB T oam Mentor pc: Dr. Hmikin. Dean Wang 1 NUREG-1437, Supplement 38 A-1278 December 2010 OAGI0001367E 00265
Appendix A U5*S(,t:rli Smnr. MmllJ.MBw:...., '",,!:\,\, \:,m'KIW40 (l\.;I5) ~44*llnl O~~ W,,~.BP<<H(':< O,'rUH. NtWliWIIG!!, "'t'w ~'I)IlJi: 12550 I:!j.;l:~) S!i.2**l~S..t . Ms. KMhy McMu.llin El'rtel'gy Nuclear Nol'th~ast fudian Point Energy Center 45Q Broru!way P.O. Ilox 429 Bm;hamm,.NY lOS 11-02<)4
Dear Ms. McMullin:
On. a scale of] to 10 the ~cent visit oftbc Orange: Country Community College Engillcering {)cpattitlellt. to Y<:Iur hldian Point I~ility wa... a 10+. Mr< Charles Kocsi$ and Mr. PatrickFukiano CQuid Mt have been mDtc wel<:<ttning and tlWrc professional. Our s.ludt:nu. have alrelldy been exposed to n. filir IlIDI)uni of physics, chemistry. m.atnemlltic..o; alld engin<:'Cfing and Misll:lrs Koesis lind htlciano instinctively [bun.d the correct level on which l<.) iid.dres$ tht;:m. During the visit there \wre a few othi:f gentlemen who a:ssisled with basting IlS hut I did not get theit names. ] asstri:e yeu tl'lat they toit were first t'llli.t oopl-esemal:ives of :!,'OUf <,';ompany. Om stut!.:.mtsllioroughly e~joyed thcvillit
- a visit which re*illfofCe<..i both their theoretical .
physics/engineering courses us well as 'their desire to fin<:i .. career ill tlB e~cit1ng engineering field. The motivational fltctOf that results from thiN quiilily of exposure cllnnot!xl overemphasized, The impressive expertise oiMr, Koesis and the obviQUS experience of Mr, Falciooo served to motivate the students as ""'ell as inform them. Thank: you for making this opportunity possible. Co!'di~lny, f(Y:~ f,.i. John r. C(unmins. Pit!). Chair, Stience &. Enginetiring 1 December 2010 A-1279 NUREG-1437, Supplement 38 OAGI0001367E 00266
Appendix A Page 1 of 1 Falciano, Patrick from: Shu-Ping Chang Isp;chang@us.illm . coml Sent; Monday, Oc!oberaO, 20009:50 .AM TOo: Falciam3, Patrick Cc: PEllEGRINOR@oon<<l.com Subjeu: FaQdback frr.Irn attendees ollfEE TZ, ASME, SME Oct. 17 Energy C~ntar m&Qting Oaar Friend: We hal/e recewed posffive feedbacks from oUr attendees for the visit to your l'Hcifity. Attochetl!8 ooa of1h-am. We wauld flke 10 thank. you for your assistanCfJ ro make our Octobar rnetltlrtg successful. We surely will plan futura ac!lvi:ty 10 YOllr center to educate more of our memoors Chesrs! SP ChaHg, Ph. O. 16M T,J, Watson Research Cemer 19 Skytine Dt. Hawthorne, NY 10532 Phorl&:. +1 914784-.114$ (111863-7746) spch.<lntl@lI$.ibm.com
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/,<,1y fatr'l(tf ana I attem:l-e-d the I.EEE I ASME I SME meeting anti toUf of Indian Point 80th or us- haU a wonderful lime and learned a great d~al aoout the Entergy EnefllY center, My fat!1"r actually IJraw up In Croton Oil Hudson an<! although not an engineer '118'.> quite irnpreswd with the visit Visiting an actual nuclear powet plant with a k~Jr lead by one of tts control room operators is ao experience that !SiteI)' uniQue a:no lruly lmpressl\'e and we vel¥ much appreciate lhe effort that went into planning !he event Reflecting back 011 thE! 'lisit:1 c~me away wilt. a m(ln~ comfortable feEding aOOut the opera~on and safely of nuclear plants than beronl ! arrived.
Hopefull;y tntlre wUI 00 mote Qf such a>lenl$ in the futute, opportunities. to 'iistt Bj!lique fa:Cift!i'es !Ilthe New Vork: area. Please share my COfH!rn}1'I1:s with !.hose at Enmrg'{. Thank you again, Daniel 101'30/2006 1 NUREG-1437, Supplement 38 A-1280 December 2010 OAGI0001367E 00267
Appendix A Thank you
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Mr. Falciano! From New Rochelle High School Chemistry Students 1 December 2010 A-1281 NUREG-1437, Supplement 38 OAGI0001367E 00268
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Appendix A 1 December 2010 A-1283 NUREG-1437, Supplement 38 OAGI0001367E 00270
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Appendix A 1 NUREG-1437, Supplement 38 A-1288 December 2010 OAGI0001367E 00275
Appendix A 1 2 MR. VITALE: Good afternoon, my name is Paul Vitale. 3 I'm vice president of the government relations for the Business 4 Council of Westchester. Business Council of Westchester is 5 Westchester's largest business organization, representing over 6 1200 members ranging in size from large multinational 7 corporations and mid-size businesses to professional firms not 8 for profit organizations and small-business owners in every 9 sector of the county's diverse economy. The economic 10 situation in Westchester is increasingly distressing. As 11 such, the closure of Indian Point, which is the backbone of 12 Westchester County and the lower Hudson Valley's electricity 13 network, would be economically devastating. It should be 14 emphasized that Indian Point provides more than 75% of the 169-a-ALI 15 electricity consumed within the lower Hudson Valley. Indian EC/SO 16 Point contributes over $50 million paid in local taxes, 17 including sales taxes, payroll taxes, property taxes and 18 state and local income taxes. Losing Indian Point could 19 potentially cause major power disruptions, the loss of up to 20 11,000 jobs and $2.1 billion in cumulative lost wages, while 21 Westchester's unemployment rate continues to increase. 22 The closure of Indian Point could result in the 23 doubling of the electricity rates of the second highest rates 169-b-ALI AQ/EC 24 that New York homeowners and businesses currently pay. Many 25 December 2010 A-1289 NUREG-1437, Supplement 38 OAGI0001367E 00276
Appendix A 1 businesses in Westchester County already having trouble 2 managing their increasing costs, including the cost of 3 reliable electricity. The alternatives laid out to 4 replace Indian Point do not make sense economically or 5 environmentally for this region. Replacing Indian Point 6 with any fossil fuel equivalent would greatly increase the 169-b-ALI AQ/EC contd. 7 carbon emissions of the region at a time when we can ill 8 afford to do so. Indian Point has been very important to 9 this region and our communities. The renewal of the 10 operating license for Indian Point is crucial more than 11 ever before. Thank you for the chance to address this 12 audience. 13 14 NUREG-1437, Supplement 38 A-1290 December 2010 OAGI0001367E 00277
Appendix A 1 IPR01l<::walCEmails 2 from: M.fJn:'}:") \('\};~~s.h f:~~ar:G.r,'ho.:S:t*':':~J?:Jpt:)r')::;I;j, :n{;.~; Sent; f":~:"~~~SG,~~*. Mar,::~ ri,:=- 2ZK191:.?-G:3 Ar<<1 To: i 'i:~;.':.~:-,tPC.' nr 2~::; Ht:.~t>:jrcl:':: 1 on~:-~- d~::: t~?~~k~},,,":j1J;: C~_:Ji;:;'~';~:1~;'; U." ~h~: tEt:.i!1 ~"j£w.t~:;p...:';,.*ifk :-:.uppj;;:[H';'!:t ~G t~l~; Ci(;I1tT~(: r.1p.*~~-(:':1:)*K~nt~d lmp.tK-:: Siak~mcnt ~br L~r.i;.-"n:;{; Rl'Jl(:'~\::':~J. c*;' NUt*).l~a;* f'b3nt) {(i*E1S)~ NURE(i~ t':P:?, r<'~>~~-d::1g dH: fi.:'ni.:**\'~*id of l.*.'~~1t:t'~;'~~~~f; h~~:.:';(')(::; D~:\H-2{~ ~~r!d npR~6~ fi,'jf ;;~n ;~ddh~<<ll\~t 10 y:::~"x:,~ (~f <)p~n~tk'f1 k~t' ),hi:' lnd~:::i-: fJG:;~~ ~~~w~'k~::' (,(:m::*;:I:.~n~~ Urd~ Nr-,*~~, 2 .(:md -~ dP-.~ and :P')). ~i~; a (onc\.~r:~{*d ~j~:z.cn; ~1 p'l~r(;:~:~ ::r1d:: !"c:~~d(r:; ,~>((:t)r'~;~;~;d~ 1\:hmGr ~l~KG lq*C)S.
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December 2010 A-1291 NUREG-1437, Supplement 38
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jf'~ , S/'\l\lA :!O *******P.r{)\!idc ~1 t)(~ni:lJ;:~~ dk):IJ-.-r.ki:1,,":::r~ b-i~Ht'fY {,h;;\:"~t.~r H.l hnpl'*y.:e de r~j'S{':" ~-di;"lbijit). Sdk~)' .. r~:'i~:h;:*d: r..s.i;; ..:om:e{.:~ n:otdd h-t~ t:~c;~d ~.\) :,,'h~mg::: a sckdtd baH~ry, Thb n.'lGdEH:.::;~Hon \\'Pl-~;d <.~n}1:HK~i;: ,th(~ km~"u:nn opcr'<~~~':(E ;,)"f ~h\:' ~U! bifa>dr:""'cn :\r:\~/ ;J:.::n;p' on h.nHL~:)' dep!eli;.~n. S ..-\1\.*t:\ S2 < -Pr~*J{;(:d::f;;S.:izi:' opi:'n~~~¢ thl~ ~'ity \,,*:th:'( .'~t:';:JP~;: v;~h:~' ~~'~r ;~J~cn1~l~t ..*~ AFV~/ :;y~t:;,m. p~m"!p ~;Hd1fjn l(> enlmm:t lhe: availahH.il) ()( AfW 'y';ltm. NUREG-1437, Supplement 38 A-1292 December 2010 OAGI0001367E 00279
Appendix A 1 2 SA ;'. . v\ ~ 3** .. rrr~T;:i:: ~a: c:,~;'.:.::::;,!-: n{~'~\: \.: .ilv.;:* ~~) r~:dt,~~x~ ~:1(! d;~k ~::':::ic:,;j~:~::;d ~\, i!h hydr~)g{:n ,.::~p!,:)s; .. m ~ i,n\; kk' r.~:,~' n'::.'ht[1:;.~ h::'li:din~:, (~r pd~~l~lry ~U:\.n:;11)* h;.~~ki:ng ~;"'{Y}: l;\.:!n(;'.j~;;~;~i til r<:~"::3(c:;j ;;In.;:d . . . ~;1:s, )s::'h 'lJW~~-::-t.,: ;l.1:~~t~*:-). S:'\.\i.:\ j j .... FtS"ovld:;.~ ~h:(~ ~:;~p;Jb~H~.\: ,~r( p("~"'*i;r:n.; \m~~ ;-.:;d~~:" int':*,:t~f:lr: pHmp ~1r Jun~. P1}WP :x:;'i::r ~h~~ Appt~rl'-~;:\ R d~:;:::$<:l {~'K (: 3 ~ 2/\) t~) ::;nh'11h~ ...~ rf;{~,,'~..:~r ';:(I{,ding S;".'~k~~f'j i~~jcGt:(>~~ 170-d-PA/SM
- , 2 1:,'::p~lbt:jl).: d:.n'iH'(!; ~:\'(nh th:!*; ":dlt~~:':: k)$S of pow\~r ;~l;l[n th,\:, .:n:o* V :H..' \, ltd bus'i::S. contd.
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f:'o:n ~ht~ ::'81)* V ;j.: \ ..h'il b~l:;"':'~~.
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,I,h:1,.? t'frp(.~s<: (~/L:'(;.(:* . .o!fl;;-~ C:*-;;np;"":H":~**';~ '::l';~h .i (.i f,f ( } N P,:~,-f 50, I r:.:.~,i(Ah.'t:' ~',:) ~!r.(' /(q;rrid i~/}lw.-*;.~i aq:tonc If.::.~)d ~?XI'K),~'::wl! F"."l.ihH:l;Y ;:v (.'!!fT{-:h'f.~~~:. ,')n,j Nf~O.'\()(:'(f(~!.i' .:kh"':1'vb:. .: (ft ('*a(A) .'" }:?!id{'/iu(:s ,~).r "~P!h!i*iI.h.... f (;j'1'~~/'! ,j~; {3 m.r.r.:}~-;.>r (~;. 03 ;mS'v:.>;*i"; :,)f.('d h1H~~'
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T11i~; I:; j)(}~:.'~ :::(:nai)~ ';l::k:':',,:nl b(:,.:dlk1~ ~h:t: C;-"8<..~~ Cf~i:Ui, (.Ifd~;:~ :~dlH~':l~:::-uf G\V into ~l1t (::.~V'ir.;)t~m(;:): ;~fl,:: C !!lll'lu ~hll1 (:~;:\.;':;~rj~:}ly. ~j)~: .:\.,fRC' *:;t;3il~i-.;:,:'; H(lt 3,J.~~H{i~kJ .;.my nt':';; ~jffd s;gH;r:c~mt :::"3f'brmJ;~\)n dUflng d~ irf(kp:::rdi;'fj~ ft'vk"~~ nf lhe ~ F~l ~md 1P3 E1(. th::; ~,;i,~ ;;~~dit, :h~ ~ . .:;,"'pll1~; pf:':K:(:':,~~~ or .;: \*;..d:J:.\ll.::n (}f f):,ho:.'t' ;:'v;~i !~1bh:: in l"(1rn'ui ion, Thcn.:f(.~.::{.~. fh(; -N f{C sl';~,i:' ~,~~K h~,dt~~ ~l::3.t: ~hi:'f(~ a ["i.:': :in {) n~;il.\::' r ~\:.~i(!'bgj*;y:;~d im.paCl$ {: n~~j\:idna] ,~*n~'*c~t,) r.~f tbe
~)';*~1nlllm h~::;l.:.:y:::~:.:.: du:'h~g Hx: rt:"l:::"v'~':l kr~H bt~}":.'}nd !h',:\:i~ di~~c:':$:;ri;d i~~ tho:: (,r:~~. f~.':r::.;;.,*;~ti(~Hy. the NRC j:~
c<:"~~~\.~!Hd;n:g :th:J~. h..:'(*;~1J:*,-:'~ ~~ 'fi~r:; n(~~ ~d(':-Hlfkj jmpa~'F; if! th;:~ p~~~:t. rH.~at? e>;i';1 f~':r ~he HHW'(:. Thi~; i~; W1S\)t~[!.d ~;.H* 170-f-HH/PAI S(:'\'('fa} :'(:a'$~)n): UF
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;~,d.. nG\ykdg.(: ~h:m: tilt p*[aU! d'::II.:::~ P'):)(~ a r:~k leI ~*:t: in(*re;~St~~t nU:11.t~(.l" i}f p~f"pk~ 3f ::l s':'Vi:'r:.;.~ ;;:~:cjdG$~t OC<;ltt~~.
~lk~rco\'c..:r.., r;:'(:' ~'~ldh:ttt':m fi,Jl:';j:*,.:.~d (rom th~: ph~r:~ P{~~;($ ~~ ~'!.s-~ ~j) a. w'~'at.:.:'r* rturj:"jr::-:?j:' c~{p,:;opt¢.
Tbe NRC :,taif ,.;~t~~hldc":~ ~h~~t th~~ *:;(}-.:i.~~:;*G'.~nomi:; il11p(:p.:b ofpb~~t ::.hn1d{)\\'n ~I,',;)uld hkdy' h;.:: :~~r\tln ~!.nd h.:lv~' m~~.:.h~L":l(: t~'H~"'e,;~s f(w ~h,.: H~1Idt*id:. :-bd:S':Hl C::"ff,tnlt S\j,f)")~ D~51.rkL \.'iHag.c of BH;::h::~nan: 'T'r.1". .'.,n nf Cor~lmHtL,
~tnd ~ht \'c~:<t;;,~,;;k r~n; D:_strkr. l :l~:/'~:":= I,vf1.h ~h~) ;~!;:;.e:,;~;n~.:::n~ wv.,! i:',d:.<\*;,: ;}~t\~ th(: ifK,!"{:::::-;:,:'*d ':;;"d~~'f):' ~'l,nd "v'ftttnty tf}
170-g-AL our ~;.t",~:,\ ~f 1n.r.lhm P\'.lim. ';~~tH:; d(iVd~ '\y*;)utd fnpr . .~ ~h~Hl (:':')lnp[:r:~.::l~.t t~*~t" ~he k~$l. r~~\'l:::aW;$, : H.~~jp(:ctHJHy J (>P"P~Xs(~ r:::li"::(:~,}~1ng ~,!{J::3n. Fl."),3::? be*c:m~~.:':: i }1~l;:;;:'\:r; ~h;.[t :~h(": ~;,nlt'!f:w::( (J§H;::f;ni~~l1 df;3j~ ;3g;n,R: Hwdt'[:t- p.. n.~\:T pbnt 3n :-;:.\;.:h ~:{:::v~;y P('!pUhth:d ~~f('~ <::r~W~.~ an :!nt-";::;l:;(}:nahl{~ ri{:~.. (Ifh~:nl: t*:) ....~iriz~r!s,. m.;"!,~;. ,:d~:::H ~o tlh~ n10~1 (;! 170-h-HH/OR
;.u1ncrnl-:-:k* indi\:*i::h;~~;~*. (~lj:," ('~l;:l.:i~'(~n_ }~1 ~h.t~ \"~~ry ;,;;a~;t~ ~h~ >~RC <:\"'~~~:;S tk{~~, 1*0 lhOSr.; lh,..jng ~~1 ~i1:..:.~ ~;i1<~<kl\."" or 11>
2 ~md lPJ to *C(J~li~>.X:t ;j mo:.~ lh~:~o~(th. s.c.:.~r¢hing <in~dy;s!:;, pmtj.;.,;ubd> r:tfrh::: i~l1r~a:i:b ()r,j :,-,I,.~Y ...~r(; "lr;:.;:~d~~nt ~1-:: December 2010 A-1293 NUREG-1437, Supplement 38 OAGI0001367E_00280
Appendix A 1 170-h-HH/OR
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2
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Cc>rtl;ll'lh 1\:I;mm. ':";Y jn~6.7 {~~ ~ :i)7:;(~-~)*~g*i NUREG-1437, Supplement 38 A-1294 December 2010 OAGI0001367E 002
Appendix A 1 MS. WALTZER: Hi. In considering whether Indian Point 2 should remain open or not, I'd like us to look to the past 3 and to the future. From sitting here tonight, I realize 4 how very important job issue is to so many people. And 5 it's a valid issue. But I want to remind you that when we 171-a-SO 6 had sailboats and we went into steam boats, those sailors 7 didn't lose their jobs. When we had horses and went to 8 cars, people still kept their jobs. They might have 9 changed to something more for the future. But we still 10 keep our jobs. They just change. The other thing I would 11 like to remind you is that this is a human issue. These 12 are human beings that are running Indian Point as any 13 nuclear power plant. I'd like you to think of any realm of 14 human endeavor. Whether it's business, government, 15 financial institutions, religious organizations, sports, 16 politics, the arts, the space program, even in families. 171-b-PAI ST 17 We're human beings. And we are subject to making mistakes. 18 To corruption. To sabotage. To blackmail. We're 19 vulnerable to terrorism. We make errors and so on. So I'd 20 like to ask you, what makes you think that this aging, 21 leaking power plant would be immune to all of these human 22 frailties? Thank you. 23 December 2010 A-1295 NUREG-1437, Supplement 38 OAGI0001367E 00282
Appendix A 1 2 3 Frum: ..~*:?~f ~/',k~;1;:~1'~: ~:~I.I.~(::;,:1~:)::~5f:H~t!:~:f~t.. ne;tJ S""t; To:
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!-:*ar;fJ~n;;,::-d ~:~k(:;;i:dV C.atlE~(~ iJ "~::9httr:a:~" tV:8 P;:1'5.~ ::-'H*N.~, ~-.:l~(n:;Y:~~>~s:orH3r ~f18 -sinnq :~~fH"l(;!~~} plan;}>.:n tb~ tl~:(~:~;S ,:~fth¢ ~*~:"\s.1:t<~~t Go:')cefftr.:~iif:l1 (">f. hiJ:n~lr!t~V of :~r:'{ ()P0:!\::t!!~'!J f~~ci~ltV. ,':.:.kj~~.~j t..) t~h~~
tQf~$(~-:$ A~ is the f**;;t;.~r~. V",/~: df*cl~..(t ~.:n*~}vv_ rjU:-(~:V k~lC"~V~ rnl";st \Ii~a~ (:i~Y' .*:~':::~:H~(:,(n:c::::~':.". ~;~ ~m:; ::.G~tnti*Y. :::1 an cH"'::L/3 ~hz:t (.*annct b0 f:"ia[~,ia1B(f in timely r3f;*hKjH,. if '::~f, <~~:. :s 3,:1 Otitt'8g0 p'}trn::Hed fjnly ~j'>~ tJ~i~ w::Hf~}; *~~lttt;:f;?:t0 1::d:~h'!.:P.~~$$ C~ thE..~ si~~~!~g Can~rni.8si:"Jn t'\-;:r"(aps H10~:~? :,vt..1 i.>ri.g:n<~n\, SikK~ i1 !"~Bfr:} ;n~gh~ nl)Vl ;~i5:~/. ',:',1'2 (:DU:U:'n n-...e :::";.:tt;'~Q ~~:':-JfqP:~~t1'.<:~f: !*:~~S~> ;11; ~;;!;c:'~ ;f<<(::.~se te*: n~i:; Cf):r.~rn,i~s;cn. ::Hi \~~ OI)(:1Cl<:1 (;If.I!3~at~\i'*$ H;;lUy st;Slt~jj ~nl,.i~~t~ PO;::1:~ ..,~..*as th~ t:'h~ir1i3l 8; 1 i
} 172-b-DE/EP
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Appendix A 1 2 3
!PReIl0waICEmai!s 4
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FI'lf!;>~ V/~,~ni~l~ief White Plains, New Yor'k 10606 NUREG-1437, Supplement 38 A-1298 December 2010
Appendix A IPRenewalCEmalis 1 From: ;s;:,(1:::*:t~::;..';S:fiJr:p~: rn I.:m. :~(:t 2 Sent' \*~(:?ijr:(:;r~,j~*~* ?!~(Cl;"1*~. 2{H)~ ~,~ ."!~: ~.M To; lr:*:J:.t~nF'('I~i1tS~~i ~~f~s{~;::rc.;::~ SlJbj(l(;t D~j ~1~;'~ :"0::-:*80'.1'.1 t~:~)I' :t::.*;~~::~,(; "{\"! lWe ~:~*~;i3:S F-"(:~(:1
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~ .. nif: C(;'l1 tklll:~lg. li:,d*,: -::-f ~..c:c~$(:;~,,;: tive ~'t';~k~r frot:-t df'i:' h~<;;*1:~:t1 P<~~~H .: :,p~:~~ fuel p<>(}i !f~:,<< th(: :~Sf:d.H:\..h\~;~~T m~~J 176-d-LE 1 :u,:J::e()'f!, Rive:,; ~u~d 1h~; ~\:*-;idu.i~I';:~\:I~t::;ql~t~t.:.ttU:l 'Co::b~-'d by th~: ~Iurn(;s. ,:~f con.-\:;:Hd:~::a.~*d y.ru~wdv'i*J~'~r ~ha~ 'Sh}'\\'~_\'
k~b:h [,J..... k: ~~r:m~;,mn3~O and C(::~hHn,,~}7 iH1.(~ ['he: j*h~d.son Rj\,*.;:C.
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(.::.~n\..~~n!y hof.(;.:r::~~d i~: :);Xjr1~; m::::;(~;;~~nt::d $p:.::ru fn"J p<:{"}!:; an.d "'dry 1;~o6.:~S'* ~;-l;~t ,~(C v~:tn~:'"~~bk' l.:~~':*'P~ :=,f ;,.ttL".:..':*:. [.,,'1 SF/ST
\Vr:; (k;p~;t:d {HI ~.;.':~~Hl~11l.t(y bodtc$ lib: y::~')r:; ;",) ~1":~:k:;; ,(~(~!. ;-"i,;~,r '\'{~t"k ',-:,~*'n~Hn(:::~~il.:'~; $.~~1{~r ~r:1d f:H';.~r.';,~
'~rF,:;c:jnd)k:. i!:d3i~l'! Poh~~ i:; rpCt *.11-:.1 \\'itb ;, ..~ ..: In(;t":,~' jnsU(m"-"HlHL4hk~ probh:'1If.:-Z t~; I.:~;,sn~nw;,~ Y~'i~l":
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NUREG-1437, Supplement 38 A-1300 December 2010 OAGI0001367E 002
Appendix A 1 MR. WILSON: Thank you. Good evening. My name is Craig Wilson. 2 I am the Executive Director of SHARE. SHARE is a non-profit 3 coalition of organizations that are committed to ensuring the 4 continued supply of reliable clean and affordable electricity 5 for all New Yorkers. We're especially pleased today that we 6 have members of SHARE that made the trip from various parts of 7 the city: Brooklyn, many of our folks are from. May you all 8 have a round. And some great signs too that you can show. For 9 too long high electricity prices have placed an undue economic 177-a-AQI 10 burden on New York's families and businesses. While poor air EC/SO 11 quality has led to high asthma rates which place our most 12 vulnerable at risk. Right now, as we all are too well aware, we 13 are in the midst of a most severe economic crisis since the 14 Great Depression. Community residents, small businesses and 15 working men and women from communities across the region are 16 struggling. And yet there is a light at the end of the tunnel 17 that we can see right now. Recognizing the turmoil within our 18 economy, now is not the time to shut our source of clean, safe 19 and affordable power for the region. 20 As much as 40% of our power, used for everything from 21 our schools, hospitals and businesses comes from the Indian 177-b-EC 22 .Energy Center. If it were to be closed, it is estimated that 23 electricity costs for small, excuse me, electricity costs for 24 small businesses could rise as much as $10,000 annually, while December 2010 A-1301 NUREG-1437, Supplement 38 OAGI0001367E 00288
Appendix A 1 individual residences would pay an additional $1500 a year. 177-b-EC 2 members simply are not able to pay these dramatically higher contd. 3 electricity bills particularly in these economic times. Beyond 4 the financial benefits, the Indian Point Energy Center greatly 5 reduces the amount of pollution emitted into our air. Unlike 6 all other power plants within the region, Indian Point does not 7 release asthma causing pollutants or greenhouse gases into the 177-c-AQ 8 atmosphere. This is of great benefit to our air quality as 9 nearly all the counties served by Indian Point consistently have 10 their air-quality rated an 'F' by the American Lung Association. 11 Clearly, we need more clean energy facilities like Indian Point, 12 not fewer. Moreover, many of the members of our members live In 13 low-income communities where asthma rates are four times the 14 national average. And one in four children suffer from this 15 serious life altering disease. Nearly one third of New York 16 City children with asthma reside in the Bronx with neighborhoods 17 like Hunts Point and Mont Haven having among the highest asthma 18 rates in the country. For these reasons, SHARE and its member 177-d-AQI EJ/SR 19 organizations, firmly support the continued operation of the 20 clean, safe and secure Indian Point Energy Center. 21 Additionally, we are committed to working with local 22 stakeholders in the New York metropolitan area to provide to 23 provide all New Yorkers with the clean and affordable power they 24 deserve. Thank you. NUREG-1437, Supplement 38 A-1302 December 2010 OAGI0001367E 00289
Appendix A S *HAR**..E~~ SAfE tlEALl11Y AFfOROA8lE RUlABLE ENERGY
'.<
<1 M,. IInd,."w SlUYV<"flbt:rg t)l\drDmY:~~nt<!i PrcjE'c-t rvt,~n:age*f Olvision of tj(::{;(I~~e Rf:"nt~w<~~, Otffn-~ tjf Nt;,.j{~,;:H' H1~;Jf:tf):- get~ut;3Uon U.S. Nt;de~~f Fh~t~~t:ljat()rv f()rr~n'~~:;sioi!
!v1",1 %jP 0*111'1 1,;'ViJ$hn"lgton.. DC 20S~1,eOO l GONl o:"ening. 111,/ rwrn,' i,; er"lg Wil"un ~lwll ,'!m Tho: f.~ef:"tiv" OiHlnor ofStlAHf:. SHARf:' is il non*profit (Odltti:()q I.)f o~'g;'ln'l?ati'ons ~:otn,mjtt.ed tq <!:~:n~urlHg t.ht: G:~ntirH.lf:(j :;upp~y l1r r~H;;)b~e, d~a:11 ~nd ~lfford3ble e;N:tridty for aU N<!,'\.' 'i'<)ti<l'rs. rl)f t()t) long, high d,,,,\rieity pri( 0, h.J1.W pl,j<<~[j ,'In t)ndu<~ eUltlOml('
bur de!! ~on N~.:::~\>v '(ork':'), f~((t~li{'$ LH1d blj:;ine:;~'~"j~ wh~k~ POQf r,~r .qu(l:hty h~~>;; ~Hd to h~gh :lst.hrntl r3~~S; Whlth pl(1te' Of~n mo";t. vul:ner,:Jb~E" at d~k. 177 -a-AQ/ECI Hight n(.H.~"!i a!~ Wt~ ~f'e <JB tDO v.I(:H (J:*oIJG~'e. Wf1 Bre in the m~dst j')rHH.:~ nH)s.t ~ev~r(~ !?'to(lOfH!,r .(rj~** $ ~inc~ the SO Gr~a~ D~pr~:~$.i'on. COrl1n1Un:tv H?~tjd~qt$.. snM~t hU~l~ne$:;e!! .(u~c1 'w,..)rl<~f\'fj rnen ..:It"}(~ w<}rnafl frorn com!lH;~!il.i~;; ~uo,<; Ihe f"glon ,m~ ,trugg!;c'fl And~, of right ;l()W, tt'~fe ;:;n't )/'" ~igh! <11 the allj of tile t!!nnd. lkCl';,:!1i,ing nit: turmoil witl1in OUt e<:lJnNT<\i. "ow i, not th(' time to ,;hUltl'r a S(lurer: of Cleill'\, $i!fe anci affoH!tlblc' po,>,""'* f(H* tit", r;;gion A> rn,'[ll a, 40% of ,1W rower. w,e<i for ~v",ythin!l from our sth{lf.<i:. . h()"rit3Is ~nd t"J;,in,,~w~', f:f)""" fl"" Hv, Indian Point Energy CN;IN . And if it Wilt!: to b;~ dtlw,n. il :"
} 177-b-EC
",ti(fl,,(.-,d !.flM (:!.,cfrlC:ity (:Osts fm ~m~lIlm"in,~,~{?~ would r1$0 $lO.lXK} anmJil!ly wllile il1dividuill r!:;iil(;'tl,,'' w,'mkl pi.y an additional $1,500, Our r'H~mber$ 'H!.' ,implv '1<'1' i>bl<~ to r""{ thes<3 drilmHti<:aliy higtwt <~tt'~(.tdr,i~y bW5, ~,MrtkuL3dy in the~e t?('f)nnrflic tirn:E~~,
Bqoncl the fin;mci,,1 bndib, the Inilian Point [nf!rgy Cent",r gn'iltly H?duCIlS the< ammml of pollutIon
,'milted intO our ~ir. Unlike all othf.>r [lower PI,mt$ witr!on th,~ f(,'~i(}n, ImJiil(l Point <lo;;;s 110t Hd'~3"~
",thr:m coll,i"g poilut(lrlb 01 W'~f~"h"'~'J;;'-' gases into the ;1trnosplmH'. 'fhis b of ereal. ben.f!fil to ""f ;,ir } 177-c-AQ qU;lli,y ,'S tl<ldy ail of th<! counties seried Il,. Indi,m Pf.,;nt consistentl,!, have their air qUi3lity [ated arl F hy the fo.mer;{:3fl Lung A%ooa*lion. CIt:;tt!V. we need Hltlf'e (le,m e!1Nf.:Y- fi,dlitie, like inlHan POint, and nOl~~wH.
Mon:<)vet, m~ny ,1'f members livi? in !ow-i>1c('m~ {.mnrmmlti;:s lllihN0 $st!u;.c< t"alr!s am fnu( times t!>(' nahmal aVNilf, and (me in four (.hildr<lrl sufffH fmlYllhis serious, lif~*a!!erlllg liis",;;,>!. N"~rly one*third
<1f New Ymk City chiklren with t1Slrlffla r~,id!! Itl the Bronx, wilh: ne,ghllorl1<lodslik" liw,t,*f>,,*int <1I">d M(.,tt Hall,,,:) having amo!1§ ttl!:! hil;!"!,t rille, of 3stl1rn'1 in HIt' wuntry 177 -d-AQ/EJI For UJ,o~<, [('<"SIXI;', SW\Rf:, ilnn its ml!'mh!?t' (J'l~.jt)jl<,ti(j!15. firmly SUilll<Jn the wntinueo or>t,ration uf the SR dean, saf(, <iflU .~cure Indian f'oint Energy Cerlter. A"ditlon<lll\', we are c(Jrmnitte<l ttl w,lrkin(; with lo(;~1 stakeholder;; in the New York m~tfOpolit"n ,lrf;i! 1.0 provid~ <ill NeW' '1orkers with the clean <lnd 3fft)rd~blll P(>W!!f thf.'I' d,,~;'nJoc. 'fh<:iok VOLI.
445 H;~.~Al:.T()N AVF.r*4lJt 3(jL~ ~,R'()/*X)V-/l. .'r* sum; 110/.' :: ,*Hf*: F-:.CK)R ViHt1E FlA[N~~, NY 106;'): NEw !Of<K. NY i(KKj;' f'W')r',;f: (91,q -422*8G,l:!. PHONE: ;2~?~ g9? -S~~j~~~ FAX: ('Yl*ll 'In-O:<82 F/\X; -r212,J 3':17-,,5.82/ 1 December 2010 A-1303 NUREG-1437, Supplement 38 OAG
Appendix A IPR!;f1!;waICE::maiis 1 Fr(t~n: L(~:'-:l !~~ {/:!:~i'::~D':::: ~: '~~%:h~J'" ?~~ (.::-~.~~ r'r1 ~~~J ~:G m j 2 S{HIt: ~r:d3>', r-::-br')arv 2"{, 2(:,(:SI ;;":,':' Af.:~ T'J.: fn.i;a.r.F(,~;;r:,~l: ~S R~~~.t1::F{;i;:~ Subjf)ct: Df; ff'!'".i :"::::i:.:.'!i;:-'::;'(; Ind:;;;::: Poir;~.
'rh~ (,"[mtiHltifl~ l-t~al... (,f ra~Hn:H~'tj\'t' rater {!"(:in ~h,:; jnd~;3n P~:im ~: ')P('::~ fu:::l rp~,;: l:nH,l ~h\;' ~;:'(~ur:..J~',:,:*~:*:" :~nd.
Hu.j-~~:,:~ H~"";;';'. ,1:'ld ~f~\: )e'~!du;~ I (:*;Jrll arr;~~wt i*:.n '-',:H.f~;:::d by th: p*::.~mt~*::' \,)f .;.:;.~ntn:Y: in:H0d ~;:r::'*~':~~h\*;~~k:~ ~'h::::: ~;io ..,\t~ 178-a-LE/ORI k;:lCh l:U. j,,: ~,~f*,m~it~m,,~).O :lnd ~>:,~*.;i~Jf:1~l:3( :;:~C~ th(; !1:H-::-::.'n f{i~*>..:!', RW l"ht' I<Hl~ krill sionlgc t>f ihi>!j.~'HJth !'.ft(JlI~ ofbighly I!)~il" lHlduw Wil,1f '.Hl 1he b,)n:" ;)-(111<: Hud:X!!1 Ri\'n,
*.::HH{:'~n ::~. h~t:~.~*d 111 p~,ud~. m;:1~~-~~:!Jn(:~j: :lr'(;:n~ fi.:c:l youl ~T ~~t-:(!: -::l'} ;,:;~;cJ.~~: :.h~n ;;=l~Y: \:' 1..: L:-"':ERA BLJ:,
NUREG-1437, Supplement 38 A-1304 December 2010 OAGI0001367E 00291
Appendix A 1 2 MR. WOLF: Good afternoon. While I am certainly 3 sympathetic to the comments that have been made about the 4 environment, I believe this meeting is about the environment 5 and specifically the environmental statement. Rather than 6 going through the thousand of pages of material, I'd like to 7 get back to basics. Because sometimes we're so inundated by 8 the information that is contained In these documents that we 9 lose sight of what we really need to consider and what the 10 NRC needs to consider. The NRC's 2008 citizen's report 11 states that the NRC's vision is quote excellence In 12 regulating the safe and secure use and management of 13 radioactive materials for public good unquote. They also say 14 that their number one strategic goal is safety, as evidenced 179-a-SAI SF/RW 15 by the first strategic outcome, which is to quote prevent the 16 occurrence of any releases of any radioactive materials that 17 would result in significant radiation exposures unquote 18 and/or quote adverse environmental impacts unquote. Which is 19 on page 8. Their factors, which singley or certainly in 20 combination, create an untenable environmental risk regarding 21 the releases of radioactive material regarding Indian Point. 22 Including but not limited to number one: the type of above 23 ground storage of spent fuel. 24 December 2010 A-1305 NUREG-1437, Supplement 38 OAGI0001367E 00292
Appendix A 1 Again this report on page 7 says, typically the spent fuel 2 from nuclear power plants is stored either in water filled 3 pools at each reactor site or as a storage facility In 4 Illinois unquote. And that quote several nuclear power 5 plants have also begun not using dry-cask to store spent 6 fuel and that the heavy metal In concrete casks rests on 179-a-SAI SF/RW 7 concrete pads adjacent to the reactor facility. My contd. 8 understanding is that this type of storage is not as safe as 9 underground in water. Now, we know that a lot of this has 10 come because Yucca Mountain cannot accept the nuclear waste 11 that was envisioned when the plant was created. But 12 nonetheless, we have to deal with the reality of what this 13 means in storing these casks above ground. 14 Two: the unusual high number of leaks or shutdowns 15 and other indications of mismanagement of the facility has 16 compromised the safety for the community around it and the 179-b-LEI OP/SA 17 apparent continuation of its radioactive leaks is indicated 18 that Indian Point is not responsibly dealing with the 19 environmental and safety aspect of this plant. 20 Three: the plant falls on a fault-line creating an 21 earthquake risk, which means that if there is an earthquake 179-c-PA 22 and storage facilities are not adequate that radiation will 23 go throughout the community. 24 NUREG-1437, Supplement 38 A-1306 December 2010 OAGI0001367E 00293
Appendix A 1 Four: again, it's not Indian Point's initial
=I 79-d-DE 2 problem because they didn't build the plant, but the fact is 3 that it is perilously close to high population areas.
4 Five: there is the possibility of the continuation J 79-e-LE/ 5 of radioactive leaks and further contamination into the WA 6 Hudson River. 7 Six: even though we're now in the year 2009, the 8 threats that were created in 2001, still exist and are still =I 79-f-RW/ SF/ST 9 a problem, especially when you're talking about aboveground 10 storage of spent nuclear waste. 11 And seven: we don't know and I don't think from 12 what I've seen that the report adequately deals with the fact 13 that you're now going to have a plant that's 40 to 60 years 179-g-AM 14 old. And we don't have a very good safety record dealing 15 with the first 40 years, and I think that the NRC needs to 16 look at this as well. 17 We all take risks every day. Even driving here to 18 make this statement involved risk. But we must evaluate the 19 risk/reward ratio and make a determination. The NRC also 20 must make a determination as to the continued safety and 179-h-OR/ SA 21 viability of having Indian Point operate for another 20 22 years. Based on the risks outlined above as well as other 23 risks that have been discussed in these reports, it would December 2010 A-1307 NUREG-1437, Supplement 38 OAGI0001367E 00294
Appendix A 1 seem incumbent upon the Nuclear Regulatory Commission in its 2 primary goal of excellence in regulating safe and secure 179-h-ORI 3 management of radioactive materials for the public good to SA contd. 4 turn down the application for the re-licensing of Indian 5 Point. Thank you. 6 7 NUREG-1437, Supplement 38 A-1308 December 2010 OAGI0001367E 00295
Appendix A 1 2
~~5 ~""h;,:,q Srfl:~l ... Sll~k B l~;;~')~fngs-<ltl-~-I:J.J';,Ot:, N\,' 11'.1706 1'>-l:lr~h P, ">::;')
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1n.rJi::.m P ...(jIll. u:~it~*, December 2010 A-1309 NUREG-1437, Supplement 38 OAGI0001367E 00296
Appendix A 1 IpRel1()W(lICEmai!s 2 From: f.J;~n,~ V~**~,:xl [P*J"*~';Q!.g::-~;,'"~~~l..~ut~~i::ifl,:).':(rg~ S-ent: nX~~:$j<;y> ~'~H;:r;:~ ie. 2DQ9' 4:G2 ~)~./l T<): ~tKti":;jnPfJ;:~tF.~ S ~>.;.~.l)!):,:;e S,jtJjflC!; ~no:~,n f-:'Qi:~'~
~ Wf:te win1 H~~ 9f~~te~t ('{,1f~:'.~(;:':'l O~}0f ~~le ep9~~~.iV:~ !"""':f tl~lt3 EN1[F~G'{ fHJd~2f p-{:*'.;\.'0f J;:1~2m~ at :ndi:8f1 r.:-~o:::*H. f-**1y I:,f.~>'::; \4:rJrk mvc~h;es Ulf: nrot0:::ti:(>:! C';- h~l~r~~:~:;~ ~ronl E:l:',.dr0n~Y:0Ht;~i ~:a7.;:jfd~~ Gn~~ ~ !se¢ too n:any :r.r~Dct::11t p<3cp*!e
~-n.~ 'v'~C~~j'"n,..-;; {;f :f~rB';!: c{)rp:)fB~k.'m~ H~<~{~ j~n(:~t: ~h~~ 1(ef}!f.:-r.. tk~u~ imp-3c:t 1hi!lY ~?:*e f 1iJ,',/ipg Ort k"l.r:a~ Pt"PB!~~; ...m'S bV
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NUREG-1437, Supplement 38 A-1310 December 2010
Appendix A 1 2
*fh~~ Dr:.~i~ [:~~ is def~*~*(;~::~~*; it"', :-:IG~l0C~!rt~ t~) :::\.I:8~H3t~ ~hf; dnV:f{H1(rH.~.'nt~: n~~ks: ::flhe:~nt n-: :~H~ feam:~'$ tf~a~ ~he (ip~~r0{(;r ;;ll:d ~h~~ NRC ~wr*if.:- a.:..~%nc'tv:"':~j1':~~f;:~"i ~ha: ;t i~; noi f.e;:Js:ble to ~~J::~y tnSp-t-~[;! UH~ fl)~} pooi.?.. , thi:!: t'n:fied :!3r.d i:rrd)0dd0.:i r:Hr.i!1!*~~t cri~k~~; et~cn"i:"~(1~ wiring .. Of 1h{~ domf:. '.;,,r~H~,:e ~*~*~:$l h;~s a~~~-::2dy b<8;~n dett.:{.~~f:;d.
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Appendix A 1 2 MR. YANOFSKY: Boy, that's a tough act to follow and 3 I'm in the performing arts. I'm violating the cardinal rule 4 which is never follow a great act. But my name is John Yanofsky 5 and I'm here under three auspices. 6 The first is I'm the executive director of the 7 Paramount Center for the Arts, which is a non-profit 8 organization housed in an historic theater built in 1930 located 9 in downtown Peekskill. I'm also a board member of the 10 Westchester Arts Council, which now goes by the name of Arts 11 Westchester, which is a countywide organization that not only 12 re-grants to non-profits throughout the county, but also does an 13 extensive amount of direct services and programs out of their 14 headquarters in downtown White Plains. And thirdly, I'm a 15 homeowner and resident here in Peekskill. 16 I am here to strongly urge the renewal of the 17 Indian Point license. The parent company of Indian Point, 18 Entergy has been a model corporate citizen to the Paramount, 19 to Arts Westchester, to dozens of arts organizations through 20 out the region as well as non-profits. There are few 181-a-SEI SR 21 corporations in the county who do more for the non-profit 22 sector than Entergy. Their commitment to the quality-of-life 23 issues that we all face is reflected in their demonstrative 24 commitment to supporting essential programs and services that NUREG-1437, Supplement 38 A-1312 December 2010 OAGI0001367E 00299
Appendix A 1 non-profits like the Paramount provide and serve in the 2 community and to our residents. Specifically with respect to 3 the Paramount, Entergy was there for our organization during 4 a very critical period when we began our revitalization and 5 restoration of our historic theater and they were the lead 6 supporter of our ability to renovate a historic theater, 7 which now draws tens of thousands of people to downtown 8 Peekskill to support local businesses and restaurants and 9 have become, our theater has become a major anchor to the 10 downtown revitalization in Peekskill. We could not have 11 accomplished that without the support of Entergy. 12 I've also had the personal honor and privilege to 13 serve with several Entergy employees in my role as a board 181-a-SEI SR 14 member of Arts Westchester, as well as on the Board of contd. 15 Trustees at the Paramount Center. In addition to volunteers 16 and colleagues that I've come into contact with, not only 17 through my work at the Paramount, but in other organizations 18 who donate their time and services to the quality-of-life and 19 improving the quality of life in our county. Entergy's 20 support is also instrumental to the vitality of other arts 21 organizations, as I alluded to. And certainly, given our 22 current financial situations becomes even more desperate and 23 dire situation. For some organization's, Entergy's support December 2010 A-1313 NUREG-1437, Suppleme 38 OAGI0001367E 00300
Appendix A 1 really means and make the difference between staying open and 2 closing its doors. As a business professional, as a 3 resident of this county, someone who lives and works here 4 and has dedicated his professional life to the ongoing 181-a-SEI 5 improvement through culture and artistic expression, I SR contd. 6 strongly urge the NRC to re-license Indian Point for another 7 20 years and to keep Entergy a vital force In our communities 8 and in the lives of our county. Thank you. 9 10 NUREG-1437, Supplement 38 A-1314 December 2010 OAGI0001367E 00301
Appendix A IPRellowaJCEmails 1 Fn;"u; JUDI rH 'Y }'... ~~ME IY~H*fflf}(A:,,"@a0:.tX)m~ 2 S<;nt-. r~uns,:.i*:~y. ~~~::~:'(;h ~::'... ?:)O~l 6:HS PM T<); !(~di[j):I~j.:iln~E~:;; Rf~Sr~t:rc,<:: St.tbjecl: rf:***;k:i;::n:;:'I:t:g rc- VV:h(HTI ~t ,m~:y C::';fKE;;,~~1. I ;"-1~~'ndtHj Q1: ne.~rifjr~ o~ ~h~ Nne r,::' t:t:I';~: (0*~~c0ns:ng o{thf? ::ndi.::1r1 ~J.,~ln~ p::.:tnt for iO t~:*()n:l y\n"l:f~;. : \.v<1~
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- ow I*~v~: t}1,H::'0~H ~'Vf~S~t8' c~n ~~t4:'! r~rr:8::n~~ I;n ".-~ddrf:$S0d. f1:a;t!! *:"JJ!~(:"'~rn$ 0; -cHilt?ns r~rn3:~n~ ~H*: .. ,;3d{jn:::;se~t r/IGH:.~ ~:rf:1htr~ning ~~il; b* ~h(~ S0r~ol.~S fi::;;k c.f t.;.3r:"r:.ris.:::~ ~~~J:"1in;jt th~$ p{)wer pl:~n~ U $*fl~-d~:I~; ;-~ \"t/onderitJl {,zFSlB't to RW/SF those v::ho \:**}01;.~W do B:; l"~;3rtn. It ~~;:'3~.I:;j h:rn ~..Jf.:\i"..1 Yer:ot Ct~y, :::1~Hi (,f *:-;rWf$0" (:1 hU1~~ ~~Hj~t;~~ .::i;':,;u:1d the eft*t. into ~J n~\V Ch::::rr:c,oyl. Ct~mtYI th~p?;~ nn '.I"':.'By ~_~) l)":':'~:(:-; t.h~r> (:::t(;, ...*.*'tth Js stC*ft:tf nuck?;Jr '1\/~1S:~H, g:~fe h{":t~) ,:'w aU~~d<.
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JlJdW1 Y;')Hllz. G\?n:Hnsf" N8~"I; 'Yor~; December 2010 A-1315 NUREG-1437, Supplement 38 OAGI0001367E 00302
Appendix A 1 2 Front' ysr()r.l'!tt ;@~;~l~:.C;:'1*tf 3 S~,,!; ~I,'~or.:,d~;-( K,'l~H:J:, H\ 2(i:)::) 1/.'-5'4 pr. .1 r,,; 4 Cc; l:~*f.~:l~~;'.t,:*;*!*~~.It;:;:p:::-r )xg SubjC(;I: 1.::c.f:i~S";~ R:;:*r::e*~,,*~! 5
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If!"d,;h')\\::' l*a:::.~if'hh: New 'Y{xk NUREG-1437, Supplement 38 A-1316 December 2010 OAGI0001367E 003
Appendix B Contributors to the Supplement OAGI0001367E 00304
1 Appendix B 2 Contributors to the Supplement 3 The Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, had overall 4 responsibility for the preparation of this supplement assisted by staff from other NRC 5 organizations, AECOM, and Pacific Northwest National Laboratory. Name Function or Expertise U.S. Nuclear Regulatory Commission Andrew Stuyvenberg Environmental Project Manager/Alternatives Rani Franovich Branch Chief David Wrona Branch Chief Bo Pham Branch Chief Andy Imboden Branch Chief Dennis Beissel Hydrology/Water Use Elizabeth Wexler Ecology Dennis Logan Ecology Briana Balsam Ecology Jeffrey Rikhoff Socioeconomics/Land Use/Env. Justice Jennifer Davis Historical/Archeological Resources Steve Klementowicz Radiation Protection/Human Health Andrew Carrera Radiation Protection/Human Health Ekaterina Lenning Air Quality Robert Palla Severe Accident Mitigation Alternatives Tina Ghosh Severe Accident Mitigation Alternatives Paula Cooper Comment Resolution April Bebault Comment Resolution AECOM Roberta Hurley Project Manager Kevin Taylor Alternatives Stephen Duda Ecology Stephen Dillard Terrestrial Ecology December 2010 B-1 NUREG-1437, Supplement 38 OAGI0001367E 00305
Appendix B Name Function or Expertise Ed Kaczmarczyk Air Quality Matthew Goodwin Historical!Archeological Resources Robert Dover Alternatives/Nuclear Fuel Cycle Nicole Spangler Project Coordinator Katie Broom Project Support Bonnie Freeman Administrative Support Pacific Northwest National Laboratory Jeffrey A. Ward Aquatic Ecology Valerie Cullinan Aquatic Ecology Lance W. Vail Hydrology/Water Use Sandia National Laboratory Joseph Jones Severe Accident Mitigation Alternatives Nathan Bixler Severe Accident Mitigation Alternatives Fotini Watson Severe Accident Mitigation Alternatives 1 I NUREG-1437, Supplement 38 B-2 December 2010 OAGI0001367E 00306
Appendix C Chronology of NRC Staff Environmental Review Correspondence Related to the Entergy Nuclear Operations, Inc. Application for License Renewal of Indian Point Nuclear Generating Unit Nos. 2 and 3 OAGI0001367E 00307
1 Appendix C 2 Chronology of NRC Staff Environmental Review Correspondence 3 Related to the Entergy Nuclear Operations, Inc., 4 Application for License Renewal of Indian Point Nuclear Generating 5 Unit Nos. 2 and 3 6 This appendix contains a chronological listing of correspondence between the U.S. Nuclear 7 Regulatory Commission (NRC) and Entergy Nuclear Operations, Inc. (Entergy). and other 8 correspondence related to the NRC staff's environmental review under Title 10, Part 51, 9 "Environmental Protection Regulations for Domestic Licensing and Related Regulatory 10 Functions" of the Code of Federal Regulations (10 CFR Part 51). of Entergy's application for 11 renewal of the operating licenses for Indian Point Nuclear Generating Unit Nos. 2 and 3. All 12 documents, with the exception of those containing proprietary information, have been placed in 13 the NRC's Public Document Room at One White Flint North, 11555 Rockville Pike (first floor). 14 Rockville, Maryland. These documents are also available electronically from the Public 15 Electronic Reading Room found on the Internet at http://www.nrc.gov/reading-rm.html. From 16 this site, the public can gain access to the NRC's Agencywide Documents Access and 17 Management System (ADAMS). which provides text and image files of NRC's public documents 18 in the Publicly Available Records component of ADAMS. The ADAMS accession numbers for 19 each document are included below. 20 April 23, 2007 Letter to NRC from Entergy forwarding the application for renewal of 21 operating licenses for Indian Point Nuclear Generating Units 2 and 3, 22 requesting extension of operating licenses for an additional 20 years. 23 (Accession No. ML071207512) 24 April 23, 2007 Letter to NRC from Entergy forwarding a copy of reference documents 25 used in preparing the Environmental Report (Appendix E) for the 26 Indian Point Nuclear Generating Units 2 and 3 license renewal 27 application. (Accession No. ML071210108) 28 May 7, 2007 Letter to Entergy from NRC, "Receipt and Availability of the License 29 Renewal Application for Indian Point Nuclear Generating Unit Nos. 2 30 and 3." (Accession No. ML071080133) 31 May7,2007 Letter to Ms. Patricia Thorsen, White Plains Public Library, from NRC, 32 "Maintenance of Reference Materials at the White Plains Public 33 Library Related to the Review of the Entergy Nuclear Operations, Inc., 34 License Renewal Application." (Accession No. ML071070518) 35 May 7, 2007 Letter to Ms. Resa Getman, Hendrick Hudson Free Library, from 36 NRC, "Maintenance of Reference Materials at the Hendrick Hudson December 2010 C-1 NUREG-1437, Supplement 38 OAGI0001367E 00308
Appendix C 1 Free Library Related to the Review of the Entergy Nuclear 2 Operations, Inc., License Renewal Application." (Accession 3 No. ML071080080) 4 May 7,2007 Letter to Ms. Susan Thaler, The Field Library, from NRC, 5 "Maintenance of Reference Materials at The Field Library Related to 6 the Review of the Entergy Nuclear Operations, Inc., License Renewal 7 Application." (Accession No. ML071080122) 8 July 25, 2007 Letter to Entergy from NRC transmitting "Determination of 9 Acceptability and Sufficiency for Docketing, Proposed Review 10 Schedule, and Opportunity for a Hearing Regarding the Application 11 from Entergy Nuclear Operations, Inc. for Renewal of Operating 12 Licenses for Indian Point Nuclear Generating Unit Nos. 2 and 3." 13 (Accession No. ML071900365) 14 August 6, 2007 Letter to Entergy from NRC, "Notice of Intent to Prepare an 15 Environmental Impact Statement and Conduct Scoping Process for 16 License Renewal for Indian Pont Nuclear Generating Unit Nos. 2 and 17 3," and forwarding Federal Register notice. (Accession 18 No. ML071840939) 19 August 9, 2007 Memorandum on "Forthcoming Meeting to Discuss Environmental 20 Scoping Process for Indian Point Nuclear Generating Unit Nos. 2 and 21 3 License Renewal Application." (Accession No. ML072180296) 22 August 9, 2007 Letter to New York State Office of Parks, Recreation, and Historic 23 Preservation from NRC, "Indian Point Nuclear Generating Unit Nos. 2 24 and 3 (Indian Point) License Renewal Application Review (SHPO 25 No.06PR06720)." (Accession No. ML072130333) 26 August 9, 2007 Letter to Advisory Council on Historic Preservation from NRC, "Indian 27 Point Nuclear Generating Unit Nos. 2 and 3 License Renewal 28 Application Review." (Accession No. ML072130367) 29 August 16, 2007 Letter to Mr. David Stillwell, U.S. Fish and Wildlife Service (USFWSL 30 "Request for List of Protected Species Within the Area Under 31 Evaluation for the Indian Point Nuclear Generating Unit Nos. 2 and 3 32 License Renewal Application Review." (Accession 33 No. ML072130211) 34 August 16, 2007 Letter to Mr. Peter Colosi, National Marine Fisheries Service (NMFSL 35 "Request for List of Protected Species and Essential Fish Habitat 36 Within the Area Under Evaluation for the Indian Point Nuclear 37 Generating Unit Nos. 2 and 3 License Renewal Application Review." 38 (Accession No. ML072130388) 39 August 24, 2007 Letter to Mr. Andy Warrior, Absentee Shawnee Tribe of Oklahoma, NUREG-1437, Supplement 38 C-2 December 2010 OAGI0001367E 00309
Appendix C 1 "Request for Comments Concerning the Indian Point Nuclear 2 Generating Unit Nos. 2 and 3 License Renewal Application Review." 3 (Accession No. ML072250103) 4 August 24, 2007 Letter to The Honorable Maurice John, Cattaraugus Reservation, 5 Seneca Nation, "Request for Comments Concerning the Indian Point 6 Nuclear Generating Unit Nos. 2 and 3 License Renewal Application 7 Review." (Accession No. ML072250171) 8 August 24, 2007 Letter to Mr. Clint Halftown, Cayuga Nation, "Request for Comments 9 Concerning the Indian Point Nuclear Generating Unit Nos. 2 and 3 10 License Renewal Application Review." (Accession 11 No. ML072250394) 12 August 24, 2007 Letter to Ms. Nikki Owings-Crumm, Delaware Nation, "Request for 13 Comments Concerning the Indian Point Nuclear Generating Unit 14 Nos. 2 and 3 License Renewal Application Review." (Accession 15 No. ML072250459) 16 August 24, 2007 Letter to The Honorable Jerry Douglas, Delaware Tribe of Indians, 17 "Request for Comments Concerning the Indian Point Nuclear 18 Generating Unit Nos. 2 and 3 License Renewal Application Review." 19 (Accession No. ML072250488) 20 August 24, 2007 Letter to The Honorable C.W. Longlow, Echota Chickamauga 21 Cherokee Tribe of New Jersey, "Request for Comments Concerning 22 the Indian Point Nuclear Generating Unit Nos. 2 and 3 License 23 Renewal Application Review." (Accession No. ML072250534) 24 August 24, 2007 Letter to The Honorable Michael Thomas, Mashantucket Pequot 25 Tribe, "Request for Comments Concerning the Indian Point Nuclear 26 Generating Unit Nos. 2 and 3 License Renewal Application Review." 27 (Accession No. ML072260033) 28 August 24, 2007 Letter to Ms. Jeanne Schbotte, Mohegan Tribe, "Request for 29 Comments Concerning the Indian Point Nuclear Generating Unit 30 Nos. 2 and 3 License Renewal Application Review." (Accession 31 No. ML072260047) 32 August 24, 2007 Letter to Mr. Ray Halbritter, Oneida Indian Nation of New York, 33 "Request for Comments Concerning the Indian Point Nuclear 34 Generating Unit Nos. 2 and 3 License Renewal Application Review." 35 (Accession No. ML072260201) 36 August 24, 2007 Letter to Council of Chiefs, Onondaga Nation, "Request for Comments 37 Concerning the Indian Point Nuclear Generating Unit Nos. 2 and 3 38 License Renewal Application Review." (Accession 39 No. ML072260245) December 2010 C-3 NUREG-1437, Supplement 38 I OAGI0001367E 00310
Appendix C 1 August 24, 2007 Letter to The Honorable Dwaine Perry, Ramapough Lenape, "Request 2 for Comments Concerning the Indian Point Nuclear Generating Unit 3 Nos. 2 and 3 License Renewal Application Review." (Accession 4 No. ML072260491) 5 August 24, 2007 Letter to Mr. Mike John, Seneca Nation of Indians, "Request for 6 Comments Concerning the Indian Point Nuclear Generating Unit 7 Nos. 2 and 3 License Renewal Application Review." (Accession 8 No. ML072260519) 9 August 24, 2007 Letter to Mr. Randy Kind, Shinnecock Tribe, "Request for Comments 10 Concerning the Indian Point Nuclear Generating Unit Nos. 2 and 3 11 License Renewal Application Review." (Accession 12 No. ML072270070) 13 August 24, 2007 Letter to The Honorable Harry B. Wallace, Unkechaug Nation, 14 "Request for Comments Concerning the Indian Point Nuclear 15 Generating Unit Nos. 2 and 3 License Renewal Application Review." 16 (Accession No. ML072270113) 17 August 24, 2007 Letter to The Honorable Leo Henry, Tuscarora Nation, "Request for 18 Comments Concerning the Indian Point Nuclear Generating Unit 19 Nos. 2 and 3 License Renewal Application Review." (Accession 20 No. ML072270548) 21 August 24, 2007 Letter to The Honorable Roger Hill, Tonawanda Band of Senecas, 22 "Request for Comments Concerning the Indian Point Nuclear 23 Generating Unit Nos. 2 and 3 License Renewal Application Review." 24 (Accession No. ML072270590) 25 August 24, 2007 Letter to Ms. Sherry White, Stockbridge-Munsee Community Band of 26 Mohican Indians, "Request for Comments Concerning the Indian Point 27 Nuclear Generating Unit Nos. 2 and 3 License Renewal Application 28 Review" (Accession No. ML072270615) 29 August 24, 2007 Letter to Mr. Ken Jock, St. Regis Mohawk Tribal Council, "Request for 30 Comments Concerning the Indian Point Nuclear Generating Unit 31 Nos. 2 and 3 License Renewal Application Review." (Accession 32 No. ML072280045) 33 August 29, 2007 Letter to NRC from USFWS, "Indian Point Nuclear Generating Unit 34 Nos. 2 and 3 Protected Species Response." (Accession 35 No. ML0732307840) 36 October 4, 2007 Letter to NRC from NMFS regarding endangered species near Indian 37 Point Nuclear Generating Unit Nos. 2 and 3. (Accession No. 38 ML073340068) I NUREG-1437, Supplement 38 C-4 December 2010 OAGI0001367E 00311
Appendix C 1 October 5, 2007 Letter to NRC from New York State Department of Environmental 2 Conservation (NYSDECL "Indian Point Units 2 and 3 Relicensing 3 Extension Request for Scoping Comments on SEIS." (Accession 4 No. ML072820746) 5 October 10, 2007 Letter to NRC from NYSDEC, "Indian Point Units 2 and 3 Relicensing 6 Extension Request for Scoping Comments on SEIS." (Accession 7 No. ML072900470) 8 October 11, 2007 Letter to NYSDEC from NRC regarding extension request for scoping 9 comments. (Accession No. ML072840275) 10 October24,2007 "Meeting Summary of Public Environmental Scoping Meetings 11 Related to the Review of the Indian Point Nuclear Generating Unit 12 Nos. 2 and 3, License Renewal Application (TAC nos. MD5411 and 13 MD5412)." (Accession No. ML072851079) 14 November 8, 2007 Summary of Site Audit Related to the Review of the License Renewal 15 Application for Indian Point Nuclear Generating Unit Nos. 2 and 3. 16 (Accession No. ML073050267) 17 November 14, 2007 Letter to NRC from Entergy, "Supplement to License Renewal 18 Application (LRA) Environmental Report References." (Accession 19 No. ML073330590) 20 November27,2007 Letter to NYSDEC from NRC, "Request for List of State Protected 21 Species Within the Area Under Evaluation for the Indian Point Nuclear 22 Generating Unit Nos. 2 and 3 License Renewal Application Review." 23 (Accession No. ML073190161) 24 December 5, 2007 Letter to Entergy from NRC, "Request for Additional Information 25 Regarding Environmental Review for Indian Point Nuclear Generating 26 Unit Nos. 2 and 3 License Renewal (TAC nos. MD5411 and 27 MD5412)." (Accession No. ML073330931) 28 December 7, 2007 Letter to Entergy from NRC, "Request for Additional Information 29 Regarding Severe Accident Mitigation Alternatives for Indian Point 30 Nuclear Generating Unit Nos. 2 and 3 License Renewal (TAC 31 nos. MD5411 and MD5412)." (Accession No. ML073110447) 32 December 20, 2007 Letter to NRC from Entergy, "Supplement to License Renewal 33 Application (LRA)-Environmental Report References." (Accession 34 No. ML080080205) 35 December 28, 2007 Letter to NRC from NYSDEC regarding rare or State-listed animals 36 and plants, significant natural communities, and other habitats on or in 37 the vicinity of the Indian Point site. (Accession No. ML080070085, 38 withheld from public disclosure per request by NYSDEC) December 2010 C-5 NUREG-1437, Supplement 38 OAGI0001367E 00312
Appendix C 1 January 4, 2008 Letter to NRC from Entergy, "Reply to Request for Additional 2 Information Regarding Environmental Review for License Renewal 3 Application." (Accession No. ML080110372) 4 January 10, 2008 Letter to NRC from Entergy, "Supplemental Response to Request for 5 Additional Information Regarding Environmental Review for License 6 Renewal Application." (Accession No. ML080220165) 7 January 30, 2008 Letter to NRC from Entergy, "Supplemental Response to Request for 8 Additional Information Regarding Environmental Review for License 9 Renewal Application." (Accession No. ML080380096) 10 February 20,2008 Letter to NRC from Entergy, "Document Request for Additional 11 Information Regarding Environmental Review for License Renewal 12 Application-Electronic Copy of Impingement Data-Tables 4-1 and 13 4-2 of the 1990 Annual Report (EA 1991)." (Accession 14 No. ML080580408) 15 February 28, 2008 Letter to NRC from NMFS, "Essential Fish Habitat Information 16 Request for Docket Nos. 50-247 and 50-286; Indian Point Nuclear 17 Generating Unit Nos. 2 and 3 License Renewal; at the Village of 18 Buchanan, Town of Cortlandt Westchester County, NY." (Accession 19 No. ML080990403) 20 March 7, 2008 Letter to NRC from Entergy, "Document Request for Additional 21 Information Regarding Environmental Review for License Renewal 22 Application-Hudson River Fisheries Program Data (Year Class 23 Report)." (Accession No. ML080n0457) 24 April 9, 2008 Letter to Entergy from NRC, "Request for Additional Information 25 Regarding the Review of the License Renewal Application for Indian 26 Point Nuclear Generating Unit Nos. 2 and 3 (TAC nos. MD5411 and 27 MD5412)." (Accession No. ML080880104) 28 April 14, 2008 Letter to Entergy from NRC, "Request for Additional Information 29 Regarding the Review of the License Renewal Application for Indian 30 Point Nuclear Generating Unit Nos. 2 and 3 (TAC nos. MD5411 and 31 MD5412)." (Accession No. ML080940408) 32 April 23, 2008 Letter to Entergy from NRC, "Revision of Schedule for the Review of 33 the Indian Point Nuclear Generating Unit Nos. 2 and 3 License 34 Renewal Application (TAC nos. MD5411 and MD5412)." (Accession 35 No. ML081000441) 36 April 23, 2008 Letter to NRC from Entergy, "Reply to Document Request for 37 Additional Information Regarding Site Audit Review of License 38 Renewal Application for Indian Point Nuclear Generating Unit Nos. 2 39 and 3." (Accession No. ML081230243) NUREG-1437, Supplement 38 C-6 December 2010 OAGI0001367E 00313
Appendix C 1 May 14, 2008 Letter to NRC from Entergy, "Reply to Request for Additional 2 Information Regarding License Renewal Application-Refurbishment." 3 (Accession No. ML081440052) 4 May 22, 2008 Letter to NRC from Entergy, "Supplemental Reply to Request for 5 Additional Information Regarding License Renewal Application-6 Severe Accident Mitigation Alternatives Analysis." (Accession 7 No. ML081490336) 8 December 19, 2008 Letter to Entergy from NRC, "Issuance of Environmental Scoping 9 Summary Report Associated with the Staffs Review of the Application 10 for Renewal of the Operating Licenses for Indian Point Nuclear 11 Generating Unit Nos. 2 and 3 (TAC Nos. MD5411 and MD5412)." 12 (Accession No. ML083360062) 13 December 22, 2008 Letter to Entergy from NRC, "Notice of Availability of the Draft Plant-14 Specific Supplement 38 to the Generic Environmental Impact 15 Statement for License Renewal of Nuclear Plants Regarding Indian 16 Point Nuclear Generating Unit Nos. 2 and 3 (TAC Nos. MD5411 and 17 MD5412)." (Accession No. ML083390523) 18 December 22, 2008 Letter to U.S. Environmental Protection Agency from NRC, "Notice of 19 Availability of the Draft Plant-Specific Supplement 38 to the Generic 20 Environmental Impact Statement for License Renewal of Nuclear 21 Plants Regarding Indian Point Nuclear Generating Unit Nos. 2 and 3." 22 (Accession No. ML083400180) 23 December 22, 2008 Letter to New York State Historic Preservation Officer (Ms. Carol Ash) 24 from NRC, "Indian Point Nuclear Generating Unit Nos. 2 and 3 25 License Renewal Application Review." (Accession No. 26 ML083400192) 27 December 22, 2008 Letter to National Marine Fisheries Service (Ms. Mary Colligan) from 28 NRC, "Biological Assessment for License Renewal of the Indian Point 29 Nuclear Generating Unit Nos. 2 and 3." (Accession No. 30 ML083450723) 31 January 12, 2009 Letter to Delaware Nation of Oklahoma (Ms. Danieala Nieto) from 32 NRC, "Request for Comments Concerning the Indian Point Nuclear 33 Generating Unit Nos. 2 and 3, Draft Supplemental Environmental 34 Impact Statement." (Accession No. ML083500409) 35 February 24, 2009 Letter from National Marine Fisheries Service (Ms. Mary Colligan) to 36 NRC, "RE: Biological Assessment for License Renewal of Indian Point 37 Nuclear Generating Unit Nos. 2 and 3." (Accession No. 38 ML090820316) 39 March 11, 2009 Letter to NRC from U.S. Environmental Protection Agency (John December 2010 C-7 NUREG-1437, Supplement 38 OAGI0001367E 00314
Appendix C 1 Filippelli). (Accession No. ML090860878) 2 April 30, 2009 Letter to National Marine Fisheries Service (Mr. Peter Colosi) from 3 NRC, "Essential Fish Habitat Assessment for License Renewal of 4 Indian Point Nuclear Generating Unit Nos. 2 and 3 (TAC Nos. 5 MD5411 and MD5412)". (Accession No. ML090790176) 6 July 1, 2009 Letter to NRC from Entergy, "Transmission of Additional Requested 7 Information Regarding Sturgeon Impingement Data." (Accession No. 8 ML091950345) 9 November 24, 1009 Letter from Entergy to NRC, "Request for Additional Information 10 Related to License Renewal Indian Point Nuclear Application 11 Environmental Report - Impingement Data." (Accession No. 12 ML093420528) 13 December 11, 2009 Letter from Entergy to NRC, "License Renewal Application - SAMA 14 Reanalysis Using Alternate Meteorological Tower Data." (Accession 15 No. ML093580089.) 16 December 17, 2009 Letter from Entergy to NRC, "Documents Related to License Renewal 17 Application - Environmental Report." (Accession No ML100290495) 18 January 14, 2010 Letter to NRC from Entergy, "License Renewal Application - 19 Supplement to SAMA Reanalysis Using Alternate Meteorological 20 Tower Data." (Accession No. ML100260750) 21 February2,2010 Letter to Entergy from NRC, "Revision of Schedule for Review of the 22 Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal 23 Application." (Accession No. M L100110063) 24 May 25, 2010 Letter to Entergy from NRC, "Revision of Schedule for Review of the 25 Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal 26 Application." (Accession No. M L101260536) 27 May 27,2010 Letter to NRC from Entergy, "Correction to License Renewal 28 Application (TAC Nos. MD5407 and MD5408) Indian Point Unit 29 Numbers 2 and 3." (Accession No. ML101590515) 30 August 31, 2010 Letter to Entergy from NRC, "Revision of Schedule for Review of the 31 Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal 32 Application." (Accession No. M L101260536) 33 September 21, 2010 Letter to National Marine Fisheries Service (Mr. Peter D. Colosi) from 34 NRC, "Essential Fish Habitat Consultation for License Renewal of 35 Indian Point Nuclear Generating Unit Nos. 2 and 3 (TAC Nos. 36 MD5411 and MD5412)." (Accession No. ML092860253) 37 September 27,2010 Letter to New York State Office of Parks, Recreation and Historic NUREG-1437, Supplement 38 C-8 December 2010 OAGI0001367E 00315
Appendix C 1 Preservation (Ms. Ruth L. Pierpont) from NRC, "Indian Point Nuclear 2 Generating Unit Nos. 2 and 3 License Renewal Application Review 3 (SHPO No. 06PR06720)." (Accession No. ML092860228) 4 October12,2010 Letter to NRC from National Marine Fisheries Service (Mr. Peter D. 5 Colosi). "Re: Indian Point Nuclear Generating Unit Nos. 2 and 3 6 License Renewal; Docket Nos. 50-247 and 50-268 [sic]; Essential 7 Fish Habitat Consultation." (Accession No. ML102930012) 8 October26,2010 Letter to NRC from New York State Office of Parks, Recreation and 9 Historic Preservation (Mr. Thomas B. Lyons). "Re: NRC, Indian Point 10 License Renewal, Buchanan, Westchester County." (Accession No. 11 ML103060210) 12 13 14 I December 2010 C-9 NUREG-1437, Supplement 38 OAGI0001367E 00316
Appendix D Organizations Contacted OAGI0001367E 00317
1 Appendix D 2 Organizations Contacted 3 The U.S. Nuclear Regulatory Commission contacted the following Federal, State, regional, and 4 local agencies, and Native American Tribes, during its independent review of the environmental 5 impacts related to the application by Entergy Nuclear Operations, Inc., for renewal of the 6 operating licenses for Indian Point Nuclear Generating Units Nos. 2 and 3: 7 Absentee Shawnee Tribe of Oklahoma 8 Cattaraugus Reservation, Seneca Nation 9 Cayuga Nation 10 Delaware Nation 11 Delaware Tribe of Indians 12 Echota Chickamauga Cherokee Tribe of New Jersey 13 National Marine Fisheries Service 14 New York State Department of Environmental Conservation 15 New York State Office of Parks, Recreation and Historic Preservation, Historic Preservation 16 Field Services Bureau 17 Oneida Indian Nation of New York 18 Onondaga Nation 19 Ramapough Lenape, Ramapough Tribal Office 20 Seneca Nation of Indians 21 Seneca Nation Tribal Historic Preservation 22 Shinnecock Tribe 23 St. Regis Mohawk Tribal Council 24 Stockbridge-Munsee Community Band of Mohican Indians, Tribal Historic Preservation Office 25 The Mashantucket Pequot Tribe (CT) 26 The Mohegan Tribe (CT) 27 Tonawanda Band of Senecas 28 Tuscarora Nation 29 Unkechaug Nation 30 U.S. Environmental Protection Agency, Region 2 31 U.S. Fish and Wildlife Service December 2010 D-1 NUREG-1437, Supplement 38 I OAGI0001367E 00318
Appendix E Compliance Status and Consultation Correspondence 1 OAGI0001367E 00319
Appendix E Indian Point Nuclear Generating Unit Nos. 2 and 3 Compliance Status and Consultation Correspondence Consultation correspondence related to the evaluation of the application for renewal of the operating licenses for Indian Point Nuclear Generating Units 2 and 3 (lP2 and IP3, respectively) is identified in Table E-1. Copies of the correspondence are included in this appendix. The licenses, permits, consultations, and other approvals obtained from Federal, State, regional, and local authorities for SSES are listed in Table E-2. Table E-1. Consultation Correspondence Source Recipient Date of letter U.S. Nuclear Regulatory State Historical Preservation Office August 9, 2007 Commission (R. Franovich) (Office of Parks, Recreation, and Historic Preservation, R. L. Pierpont) U.S. Nuclear Regulatory Advisory Council on Historic Preservation August 9, 2007 Commission (R. Franovich) (D. Klima) U.S. Nuclear Regulatory U.S. Fish and Wildlife Service (D. August 16, 2007 Commission (R. Franovich) Stillwell) U.S. Nuclear Regulatory National Marine Fisheries Service (P. August 16,2007 Commission (R. Franovich) Colosi) U.S. Nuclear Regulatory Absentee Shawnee Tribe of Oklahoma August 24, 2007 Commission (R. Franovich) (A. Warrior) U.S. Nuclear Regulatory Cattaraugus Reservation, Seneca Nation August 24, 2007 Commission (R. Franovich) (The Hon. M. John) U.S. Nuclear Regulatory Cayuga Nation August 24, 2007 Commission (R. Franovich) (C. Halftown) U.S. Nuclear Regulatory Delaware Nation (N. Owings-Crumm) August 24, 2007 Commission (R. Franovich) December 2010 E-1 NUREG-1437, Supplement 38 I OAGI0001367E 00320
Appendix E U.S. Nuclear Regulatory Delaware Tribe of Indians (The Hon. J. August 24, 2007 Commission (R. Franovich) Douglas) U.S. Nuclear Regulatory Echota Chickamauga Cherokee Tribe of August 24, 2007 Commission (R. Franovich) New Jersey (The Hon. C.W. Longlow) U.S. Nuclear Regulatory Mashantucket Pequot Tribe (The Hon. M. August 24, 2007 Commission (R. Franovich) Thomas) U.S. Nuclear Regulatory Mohegan Tribe (J. Schbotte) August 24, 2007 Commission (R. Franovich) U.S. Nuclear Regulatory Oneida Indian Nation of New York (R. August 24, 2007 Commission (R. Franovich) Halbritter) U.S. Nuclear Regulatory Onondaga Nation (Council of Chiefs) August 24, 2007 Commission (R. Franovich) U.S. Nuclear Regulatory Ramapough Lenape (The Hon. D. Perry) August 24, 2007 Commission (R. Franovich) U.S. Nuclear Regulatory Seneca Nation of Indians (M. John) August 24, 2007 Commission (R. Franovich) U.S. Nuclear Regulatory Shinnecock Tribe (R. Kind) August 24, 2007 Commission (R. Franovich) U.S. Nuclear Regulatory Unkechaug Nation (The Hon. H. B. August 24, 2007 Commission (R. Franovich) Wallace) U.S. Nuclear Regulatory Tuscarora Nation (The Hon. L. Henry) August 24, 2007 Commission (R. Franovich) U.S. Nuclear Regulatory Tonawanda Band of Senecas (The Hon. August 24, 2007 Commission (R. Franovich) R. Hill) U.S. Nuclear Regulatory Stockbridge-Munsee Community Band of August 24, 2007 Commission (R. Franovich) Mohican Indians (S. White) U.S. Nuclear Regulatory S1. Regis Mohawk Tribal Council (K. August 24, 2007 Commission (R. Franovich) Jock) U.S. Fish and Wildlife Service (M. U.S. Nuclear Regulatory Commission (R. August 29, 2007 VanDonsell and R. Niver) Franovich) Delaware Nation (D. Nieto) U.S. Nuclear Regulatory Commission September 5, 2007 National Marine Fisheries Service U.S. Nuclear Regulatory Commission (R. October 4, 2007 (M. A. Colligan) Franovich) I NUREG-1437, Supplement 38 E-2 December 2010 OAGI0001367E 00321
Appendix E U.S. Nuclear Regulatory New York State Dept. of Environmental November 11, 2007 Commission (R. Franovich) Conservation (J. Pietrusiak) New York State Department of U.S. Nuclear Regulatory Commission (R. December 28, 2007 Environmental Conservation (T. Franovich) Seoane) National Marine Fisheries Service U.S. Nuclear Regulatory Commission (R. February 28, 2008 (P. Colosi) Franovich) U.S. Nuclear Regulatory New York State Historic Preservation December 22, 2008 Commission (D. Wrona) Office (Carol Ash) U.S. Nuclear Regulatory National Marine Fisheries Service (MA December 22, 2008 Commission (D. Wrona) Colligan) U.S. Nuclear Regulatory Delaware Nation (D. Nieto) January 12, 2009 Commission (D. Wrona) National Marine Fisheries Service U.S. Nuclear Regulatory Commission (D. February 24,2009 (M.A. Colligan) Wrona) U.S. Nuclear Regulatory National Marine Fisheries Service (P. April 30, 2009 Commission (D. Wrona) Colosi) U.S. Nuclear Regulatory National Marine Fisheries Service (P. September 21,2010 Commission (D. Wrona) Colosi) U.S. Nuclear Regulatory New York State Office of Parks, September 27,2010 Commission (D. Wrona) Recreation and Historic Preservation (R. Pierpont) National Marine Fisheries Service U.S. Nuclear Regulatory Commission (D. October 12, 2010 (P. Colosi) Wrona) New York State Office of Parks, U.S. Nuclear Regulatory Commission (D. October 26, 2010 Recreation and Historic Wrona) Preservation (T. Lyons) December 2010 E-3 NUREG-1437, Supplement 38 I OAGI0001367E 00322
Appendix E Table E-2. Federal, State, Local, and Regional Licenses, Permits, Consultations, and Other Approvals for the Indian Point site Expiration Agency Authority Description Number Date Remarks NRC 10 CFR Part 50 Possession License, DPR-5 09/28/13 Authorizes Indian Point Unit 1 SAFSTOR for Unit 1 NRC 10 CFR Part 50 Operating license, IP2 DPR-26 09/28/13 Authorizes operation of IP2 NRC 10 CFR Part 50 Operating license, IP3 DPR-64 12/10/15 Authorizes operation of IP3 DOT 49 CFR Part 107 IP2 Hazardous Materials 051909552037 06/30/12 Radioactive Certificate of RT and hazardous Registration materials shipments DOT 49 CFR Part 107 IP3 Hazardous Materials 05919552032 R 06/30/12 Radioactive Certificate of T and hazardous Registration materials shipments EPA 40 CFR Part 264 IP2 Hazardous Solid NYD991304411 10/14/02 Accumulation Waste Amendment and temporary Permit (1) on site storage of mixed waste for >90 days EPA 40 CFR Part 264 IP3 Hazardous Solid NYD085503 746 10/17/01 Accumulation Waste Amendment and temporary Permit (2) on site storage of mixed waste for >90 days NYSDEC 6 NYCRR Part 325 IP2 Pesticide Application 12696 04/30/12 Pesticide Business Registration application NYSDEC 6 NYCRR Part 325 IP3 Pesticide Application 13163 04/30/12 Pesticide Business Registration application NYSDEC 6 NYCRR Parts 704 IP1, 2, and 3 SPDES NY 000 4472 10101/92 3 Discharge of and 750 Permit (3) wastewaters and storm waters to waters of the State NYSDEC 6 NYCRR Part 704 Simulator Transformer NY 025 0414 02/28/13 Discharge of Vault SPDES Permit wastewaters to waters of the State I NUREG-1437, Supplement 38 E-4 December 2010 OAGI0001367E 00323
Appendix E Expiration Agency Authority Description Number Date Remarks NYSDEC 6 NYCRR Part 704 Buchanan Gas Turbine NY 0224826 02/28/13 Discharge of SPDES Permit wastewaters to waters of the State NYSDEC 6 NYCRR Part 750 ISFSI Project SPDES NYR OOE 125 NA Stormwater Multi-Sector General discharge Permit during construction of dry cask spent fuel storage NYSDEC 6 NYCRR Parts 200 IP2 Air Permit 3-5522- NA Operation of and 201 00011/00026 air emission sources (boilers, turbines and generators) NYSDEC 6 NYCRR Parts 200 IP3 Air Permit 3-5522- NA Operation of and 201 00105/00009 air emission sources (boilers, turbines and generators) NYSDEC 6 NYCRR Part 596 IP2 Hazardous 3-000107 09/04/11 Onsite bulk Substance Bulk Storage storage of Registration Certificate hazardous substances NYSDEC 6 NYCRR Part 596 IP3 Hazardous 3-000071 08/16/12 Onsite bulk Substance Bulk Storage storage of Registration Certificate hazardous substances NYSDEC 6 NYCRR Part 610 IP2 Major Oil Storage 3-2140 Onsite bulk Facility (4) storage of
>400,000 gallons of petroleum products NYSDEC 6 NYCRR Part 372 IP2 Hazardous Waste NYD991304411 NA Hazardous Generator Identification waste generation NYSDEC 6 NYCRR Part 372 IP3 Hazardous Waste NYD085503 746 NA Hazardous Generator Identification waste generation NYSDEC 6 NYCRR Part 373 IP2 Hazardous Waste NYD991304411 02/28/07 Accumulation Part 373 Permit (5) and temporary on site storage of mixed waste for >90 days December 2010 E-5 NUREG-1437, Supplement 38 I OAGI0001367E 00324
Appendix E Expiration Agency Authority Description Number Date Remarks WCDOH Chapter 873, Article IP2 Gas Turbine 1 Air #00021 12/31/12 Operation of XIII, Section Permit an air 873.1306.1 of the contam ination Laws of Westchester source County WCDOH Chapter 873, Article IP2 Gas Turbine 2 Air #00022 12/31/12 Operation of XIII, Section Permit an air 873.1306.1 of the contam ination Laws of Westchester source County WCDOH Chapter 873, Article IP2 Gas Turbine 3 Air #00023 12/31/12 Operation of XIII, Section Permit an air 873.1306.1 of the contam ination Laws of Westchester source County WCDOH Chapter 873, Article IP2 Boiler Permit 52-4493 NA Operation of XIII, Section an air 873.1306.1 of the contam ination Laws of Westchester source County WCDOH Chapter 873, Article IP2 Vapor Extractor Air VEOO01 12/31/12 Operation of XIII, Section Permit an air 873.1306.1 of the contam ination Laws of Westchester source County WCDOH Chapter 873, Article IP3 VaRor Extractor Air NA NA Operation of XIII, Section Permit (6) an air 873.1306.1 of the contam ination Laws of Westchester source County WCDOH Chapter 873, Article IP3 Boiler Permit 52-6497 NA Operation of XIII, Section an air 873.1306.1 of the contam ination Laws of Westchester source County WCDOH Chapter 873, Article IP3 Training Center 52-6498 NA Operation of XIII, Section Boiler Permit an air 873.1306.1 of the contam ination Laws of Westchester source County WCDOH Chapter 873, Article IP3 Vapor Extractor Air Operation of XIII, Section Permit an air 873.1306.1 of the contam ination Laws of Westchester source County WCDOH Westchester County IP3 Petroleum Bulk 3-166367 09/07/10 Onsite Bulk Sanitary Code, Article Storage Registration Storage of XXV Certificate Petroleum Products I NUREG-1437, Supplement 38 E-6 December 2010 OAGI0001367E 00325
Appendix E Expiration Agency Authority Description Number Date Remarks TDEC Tennessee IP2 Tennessee T-NY-010-L09 12/31/10 Shipment of Department of Radioactive Waste- radioactive Environment and License-for-Delivery material into Conservation Tennessee to Regulations a disposall processing facility. TDEC Tennessee IP3 Tennessee T-NY-005-L09 12/31/10 Shipment of Department of Radioactive Waste- radioactive Environment and License-for-Delivery material into Conservation Tennessee to Regulations a disposall processing facility. Notes: (1) IP2 Hazardous Solid Waste Amendment Permit = Permit has been administratively continued based on conditional mixed waste exemption. (2) IP3 Hazardous Solid Waste Amendment Permit = Permit has been administratively continued based on conditional mixed waste exemption. (3) IP1, 2, and 3 SPDES Permit = Timely Renewal application was submitted; therefore, permit is administratively continued under New York Administrative Procedures Act. (4) IP2 Major Oil Storage Facility = Timely renewal application was submitted; therefore, permit is administratively continued under New York Administrative Procedures Act. (5) IPs Hazardous Waste Part 373 Permit = Timely renewal application was submitted; therefore, permit is administratively continued under New York Administrative Procedures Act. (6) IP3 Vapor Extractor Air Permit = Application has been submitted to WCDOH, but permit has not yet been issued. CFR = Code of Federal Regulations DOT = U.S. Department of Transportation EPA = U.S. Environmental Protection Agency IP 2 = Indian Point, Unit 2 IP 3 = Indian Point, Unit 3 NRC = U.S. Nuclear Regulatory Commission NYCRR = New York Codes, Rules, and Regulations NYSDEC = New York State Department of Environmental Conservation SAFSTOR = Safe Storage SPDES = State Pollutant Discharge Elimination System TDEC = Tennessee Department of Environment and Conservation WCDOH = Westchester County Department of Health December 2010 E-7 NUREG-1437, Supplement 38 I OAGI0001367E 00326
Appendix E August 9, 20(>7 Ms, Runl L. Pierpont. Director Ne'/Oi Vork Slale Office Df PZili"o" Recreation ()nd Hlstor:c Pre.3er\ta~10n Historic Preservation Fie:d Services BUf26U Peeble'3 Is:aw:, P,O, Box '12;9
~'\I:a!Brford. NY ':2'1.38-0'169 iNDl.A,N POINT NUCLE,4,R GENERA TiNe; UNIT NOS 2 &1 i,lNDIAN POINTi LICENSE FtENElNAL f\,PPLlCATION REVIEV'l (SHPO NO, %PR0( 7 20)
Dear ~';ls. PierponL ThE' U,S, Nuclear Re9ulatory Commi:;sioll iNRC) ,;I,d IS [.w:ewir'iJ ,m appiioJtioll to reI1",,,*\1 the opemtin~1 license for Indl[,n Point, whicl: :'0' loc[;te::i ,n B:JcilaPJn, NY, 8pprox i l'161ely 24 m,:es north of Ille Ne'N Ycwk City bOllndm'/ ::ne, Illdian Point :5 operated b'y' E!:lel-gy Nudear-Opemtiolh, Inc, (Enter~lY) The clppiicat,on for rene\,<;'al \>vm, submitted by Entergy by letter duted Apr:H 2:3, 2007) and supplerner:ted by :ett~~ws (jated r'*. '::av 3: and ,June 2":, 2007: pu!'sunnt to TI;.Ie '10 of trle (:o(le of FellerB.! RGQu./olion:,: Par! 5.:1 ('I CI CFR P,-..i'! 54), Hie NRC I:as est;;:t,llstlecl !t-laL as pa:'! of 11:12 slal,'s reVle'>/\' of any !luc:e"I' power pl<tn! iicense rene\'\;l:Il <lction, £< site-specific Supplemented Environmenlallrnpact Statero;em f!3EiS} to :ts "Generic EnvlrDnmen;al Irnp<:ct State::)8nj for licenSE: RenG'Na: of Nuclei):" PI'Jnts, NUREG-14,37 ,viii be prpmecl under the pfDvisi,:)n" cf 'W CFR Pa:'t ') ':, the NRC's I'e,,?,ulrltion thot!mp:ements trl8 Ne,lianal Env!wfII';ent(d Pollc>, Art of h!:;,9 (NEPA) tn acco!'rjance WIt!'! 36 CFR BODS(e), the SEiS v.(,iI in<::ll;de anaIY,,:8:; of pot81:lial in',pacts to I"storie and culluml rE:SDur(:e~;. til the corr;ext of !I-,e N;;:,liGI181 Histone PI-eservation Aet ,)1 1966, as amencierJ, tile NRC staff t:as d81ermifle{1 lhcol the area of potentia! efled I.i\PE) for a iicellsB reflewal acticn is the area at the pO\o'ver plent '3.:16 and j~s irml'18£liate envlror::s that rr:8'y' be i:mpscted by post-License r6ne\,'/a~ lanci-disturt;in',1 {,peralions or projected refw'bistlll:ent activitif% associated with ti:8 preposed clctioll. 11-le ,APE flkl'y exten,j i}eyom! tlleim,:lediatB environs in ti'lose Illstances wl',ere po:,t-iic.ense l-el:ewallar,d-clislul'!:!in9 operat:ons Dr projected retJrbisrlment ,-,ch:iti8s specifically relBte;j to license rel1eV,/:::!1 may potenti<:llY :l;::,V8 ,,1'1 effed 011 kr,mvn m pn:>po,3ec: ni',;loric ,oite:;. This determ:natiofl :s 1118:..'1e irrespective 0' ownership or cOr!;wi of the larKls of interest On Septembel- '19. 2007, Ihe NRC wilt C(JrJ.:lllct t'vV'J publie NEP,A, ';COpi'lg meetil19s at tile C::,;onial TelTflce, 'oc61e(1 at: 'I :,! Oregon RDad ii, Cor;i<"-I(ll r,1allor. NY YO'-l and your sl<::ff me invi!ed te attend, VOl:: (,ffice will rec2i';e a CDPY of Ille malt SEIS alol1,; \'vith a request fot' comments, Tile sIaff expecls to p,lbl:sl; Hie (!mft SEtS ill ,.lui:,. 2008. NUREG-1437, Supplement 38 E-8 December 2010 OAGI0001367E 00327
Appendix E R Pierpor:1 If you IlflV8 any questiolh or require adeiiliona!infar:Tlation, P:8,""8 'X>l:t~lct 1':15. Jii, Caverly, Envircmnlnlal P!"Ojed ~',,1ana~18r, by pt'lone at 30'1-415-6099 or by eillflil at i,i';cLXt:}[:<;',ii'XL S:rlGerely)
!RAl Rani Frano',/icil,. Brand'i Chief EnVifOI C 'll81:tal Braner, B Dlvis:or: of License R8newCj:!
Office of NI.:ciear Re8ctor Regulation Docket No',;. 50-247 i3nd 50-2(',6 cc See next par,le December 2010 E-9 NUREG-1437, Supplement 38 I OAGI0001367E 00328
Appendix E Ivlr. Don L Kli:llCl, Director Advi:;{>rl' Council on Histor!c Prec;ervatiDn Office of Federal Ape:1Gj f"ITli;IIT,ITIS
':'100 Pennsylvania Ave. NIN Su,le SCI]
\'V,,shiI19ton, DC 20004 SUBJECT INDIAN POINT GENERAT1W" UNIT NOS. 2 .& 3 LICENSE RENEI'V!",-
APPLICATION RE\'lEW
Dear [,
j[ Klirna: The U S. Nuclear Re9t:iatof'j' COnlmis:siol1 {NRC [,nd the sta;f) is i"8'lie"Ning an ap~;licacion to rene'N !lie Opertlti:1~! Ilcer:ses for 1!),Jian F'Gm! Genemtl!'eJ til'lt Nos. 2 1>. ::; <Jlldian F'olntl \N:1Iell is leGa!ed in 8U<:::'lmwr" Nev.,' York. approximateiy 24 miles no:'lh of t:'le r,Jew York C:ty tJoUlK:ary lille Il'Iclian Point is operated !Jy Entergy Nt;cle'Jr O:::eratiolls, IIlC, (Entsr(lVJ TIlE'r:ppiic::'lliGn fDI' rene'wa: was submitted by EIl1er']y bV letter elated Aoril 22,. 2007, and supplemen1ed ,::y leIters (lmee! ?,It!y 3, ;md .Jm:e 21,20(17, PW:'::lJf:nt to Title '10 of tr,e Coc!e of Fel/em! Re::juiatiom; Part St llO CFR Part 54), The NRC hdS e"t",blished ,hst. as ,-,,,,ri of the sta"'s review of "'I'll' Ilude,,:r pO'Nel' plcmtiicense renewal action, a ::;.ite-::;.peGific Supplemental EnViPJI'IT18nt:"llnlpact Sl81ement (SEIS, to ib "Gen<Hic Environmental Im;:;act Statement lor Licen:;e R81'ewal of Nuclear P:ants," NURE(3-14J7, 'Niil be pn;pared under me pr;:,YiS:OIlS 01:0 C*FR Part 51 ;(Ie NRC's regui::'lt:Gn 1h:;-,I inlp!elnents the National Environmental Policy .Ad of '196~; (~~EPA) In accorciance with 36 CFR BG08{c) ttle SEIS 'Ni'! inGlucie alk:iyse;:; 'Jf potentialif'lpac\'; to I:i:;tolic all(i cuitural resources The NRC ",tail plans 10 hold ,'.':'0 public ~JEPA scoping meetiWl", 011 Sep!embe:- 19, 2007, ," Co:onial TelTace, IOG<<,e;:! at : '19 Cn'e,loll Road ii' Cortlandt !VlanG:, New York. Tlw ::rst meetil'eJ wi;; CO:-fV8Ji at 'J: 3D p.rn. and \*vi:1 continue un~~J 4::}O p.n-L. r3S flCGSSBt-y. 1h-e S8G':)fld rneetin'J v\tW GO~~fVerle Elt 7:00 p.rn.: ~'if:t~l <.: repeat o~ H-le O'*i8IV:8'iN portions of the ~fr~,t nle6ttr~g, tln[1 ~iiW C0!,tinlle l!ntill 000 pm" r:s nece",',my. In additioll, ',18ff wi!! condl:cl <l sitel:ilxlit September 10-14. 20:J7. ilt 11l(!:an F'o:nl. You and your staff me ilwilecllo altelK! trot!'1 tlie putrlic meelillr;IS and 11:8 si~e DUdl!. Your office wi!! recei','e n GOpy 0; the dmfl SEIS aiong witl: a reque~it fm comments. Tne <lnticip<lle::i put)!:mti::>ll <:Ir:!e for me dm!! SEIS is lat8 ,JUly 200S. NUREG-1437, Supplement 38 E-10 December 2010 OAGI0001367E 00329
Appendix E D. Kiima If VOU In'le anv ql:eslions or ["'quirE' i.Xl[jil:ollal infonnalion. pi"'8se cOl:tac.t trl8 Erwil"onIY:ent8: Project Manag8f Ms. ,lill C<:Neriy at 3:)1-4E')-<36'~9 Of vin 8-mail at h.:;:~&C!2~,s1?*!~
/RAl Ralli Franovic'"i. Ekilr1ch Cllie:'
Elw:ronmentai Eq'anch B Div:sion of License Rsne,vai Office of Nuclear- Reildor Re9Uldio!l Dod,e! No", 50-247 al:d 50-268 December 2010 E-11 NUREG-1437, Supplement 38 I OAGI0001367E 00330
Appendix E 1I'Ir Devk: S!,!!weli Field Su perv:sor U.S Fls~1 and VVildlife Service New York Field Office 38: 7 Luke: Romj C:)rUar:d, NY 'l31J45
SUBJECT:
REQUEST FOR UST OF PROTECTED SPECIES WITHIN THE ,D,REA UNDER EV,A,lUATION FOR THE IN[)I.lIN POINT NUCLEAR GENER!UING UNIT NOS. 2 &.~; LICENSE RENEVVAL APPLICATION REV!EVV Dem r'. :lf. David Stil:well: The U S Nuclear Regulatory Commission (NRC) is re'lielNing an application sclbmitled by Entergy Nl:cieaf O;:,emiions. Inc.. for the re!le'Nal of the opel'tltin.:; lie:":)5e:, ;'0:' Indian Poim Nuc:em C3ene r atil'g Unit Nos :2 & 3 (ir:ciic:n Poil~t} Ir:cii[:n Point Is 10N:ted :n BuchalvJn, New Yorl':, approxim",'teiy 24 n::les no';!'! of II-Ie New Yorl" Citv bOUlK':ary' lil'e. ft,:> pmt of the re,rlew of the liGell';e renewal application (LR,<q, ;he NRC is prep,:rin;;; fI Supp:amental Environmental Impact Slate',,-,e:)l {SEIS) 1I1'dB:' lhe provi'S:on'S :)f T:tle '10 of lhe C::;,)", of Federal Requiatief)s Pmi 51 {II} CFR Pm! 51} tha NRCs regulmion that implen12n!s the Natiorwl En\!,ml'ITkmt,,; Policy Act (NEPA} of *:'~168. The SEIS :nc!:,K;e5 Uri iJna:ys:s of pertinem enviwnmen1al issues,
'llcilld'"~1 8nd51lQ81'sd or tilreaiel:ecl species ar~d irnl)acl'S to fish and \'1I,ldl,le, This letter is bBIWI subnlitted lJndel' the provisiDns of t~ie Endangered Speciec; Act of 1-97:3. i3S an12:KI2cl, "nel tDe Fisil and VVilcllife Co(x::ii'lt!tioll AGt Df HH4, ;JS <Hle'ldecL Trl8 ,:Im;:l05.<1 aGticiIl i:> to renev,,' tile faGiirty Cii}emtir:(! license',; for Indian F'*)int for an adclitioIK:!
20 ye[~fS beyond the eX;J~r[:tjon 0~ ti:,s cun"8n~ '.)perDt~ng ;;censes. The proposed Dctiofl \,vC'ukl
'nclude H'le use Cll'c1 G')llt:!lued rnail'tal'lallce of eXIsting plant faeilltie'S ana tml'sIT::SS:OIl I'nes.
The Indian Point ,;ita Govers appro}:i'T!~;tel~, 2:39 anE'S. In>.:~iar: POint is bordered ')n t'1a Ilorth, Sout~1 and east by p;:,rtially wooded privately ownecl I<:nd cmd all 11'18 west by the Huds*oll RIval'. Enclosure's I and :2 provide a general o ...*8rview* 0' th8 sits 1:)Gation 2mel 'Site ia:vout. lnciisn Poim i,3 equ:ppecj 'Nitl~ a '),'iCe-lhrour~!'1 opell-c:ycle (;ooi:ng ,",:s;em iI'lut witl'l(lravVs Gooling water fro tTl <.-:nd diSCf""large-s ~")fH.:.~k ~r:to the Hud'son RiVEd' The intake s:lsteY'(J indl:des seven b8:ys fewead,: Uilit 10GBte*j at Fie 51*\0:a. S'x 96-'1"Icr: ,::ipe~; (!i"dlarqe water IJefieaHl tflB water':" sUlisce witflin a cO-'oot wide discharge canal. Trl8 transmi:3,3ion !illes in trle :>Gope of NRC's elWiWlllnel'tal rw.;iew for Iker::;e fenewal me those that "vere migimlily GO:1structed fo:' ,he soecific purpose :)f con~wGling the plan! to tile tmnsmi:>,;ion c,y,;tel)'. Th'3 tmn',m'$,;,on !ine corr!,jor to tDe BUGDanall Sub:3tatic:n {ap~A0Xim;Jlelv 2 lOG feet southeast fro-I the mill::!",r'> ..,llst 'clGmss 6road lNay frorn the 'acility's nlZlill efllrZlllce) is IOGr:!",:1 in 11':8 in(lustriai portl:)!) of the site. 9XGapt for w~iere the lines cr:)ss Bwachv{IY. Ths tmnsrnissi')n line corridor :s beif19 evall:ated 83 part Of the e:wironITI8l'lzll re-V:!BV',/ proce:~;s. NUREG-1437, Supplement 38 E-12 December 2010 OAGI0001367E 00331
Appendix E D. SiilhNel: The enclosed translTlis:3ion line map shows the transll~is~,:OIl s;ystem lhet is beil'9 eveluated in the SEIS. T,'1o 345-kilovoit (k\illines connect Indian Point to tr:s Buch8mm Sub5tetion. TI-lis c0rricjo:- also includes '13.'3-k\i m:lI'~;rnission lines th~Jt suppiy offsite pmNf.H from tile sut;statwn mto Iwjian Po:n!. To support tile SEIS prepe:mtiDn process ancl to ensul'8 compile:nce w:th Sect:oJ: 7 of nl8 Endan,;ered S;:;8(;:es iXcl. trle NRC requests :n':xmal:on on FederDiij. . -:isted, proposed. ;:md cm'ciicate speci8s enci critical hat:d1at tr:at m~ly i::'8 in tl':8 'oficimty of Indien POint Bne: :Is associate;:; Irall:311l':3c;:on ::n8 rigr:I:3-of-wa'i. In addition. ,::le,,,,e pwvicle eny illf:::.rmat:Gn you cOp:,.icler appw;xiate Ullder the P!'ov:sions 0: the Fisil and VViidlife Cocrclin",!iofl Act The NRC s!a:f plans tel hole two putilic NEP.A scoping n~eetings on September '1 [) 2007. at COionial Terrace. loceled at 1'1 ~~'I Oregon Road iJ: COl"ll<.,ndt l",ilenof. NelN York. The 1lr",t rneetinQ wi!! convene at '130 ~u-n and -wiil continue LJr.Iil4:30 Pf:'. 21'3 necessani- The second meet:ng wiii convene at YO;j p.rn., ,v:m e I'e peat 0; the overView portions 0: ;t-Ie ::r'3t n,eetil'<J. awl ,viii cor:tinue until! 0:;)0 p.m .* as necessary In e,;:!::litior: *. ttle NRC '3!a;: pl8n'3 to conduct a site audit at II,dian Point during the ,;vee;,: :)f September .! 0, 2007. You and your staf, are in\'ited to attend botil the pU!Jlic meetings end tile site audi!. Your o:fice 'Nill rece:ve a copy of the draft SEIS alon£) 'N:tl1 a request for comments. The anliGipated put:licotion dat8 for ti,e clra'; SEIS is I;J!e
.July 2008.
!f you rlave any qL;estions GOnCelTlil'9 trle NRC :3t8ff'~, I'ev:ew of tt,is L.F:A, pie8se contact 1,'ls. ,Ii" Cflverly Project r"tmr:qer at :30'!-415-8450 Of via !?-ma:: at i:~::;J@mLL::~:(
IRA! Rmil Fri-"I"tovicfl. B,-ancll Chief Envir:J\'lTIefitai Brflrlch B DIVisiD'-1 of License F:ellelial Office of ~~l:t~lear Reactor R8Quietioil Docket Nos. 50-247 ar:d 50-286 Encioslires:
- i. S:te Loc;J!ion
- 2. S:te Layout December 2010 E-13 NUREG-1437, Supplement 38 OAGI0001367E 00332
Appendix E
,I\UQusti 13 _20D7 f,-Ir_ Peter Colosi Ha:t;:tat COflSer\tattUr: Co.ofcHnstor Ni'Wonal f','larme Fishelle" Selvice Olle BldCkb:_11'n Drive (3IouSt91-, l'/l,A (;-1930 SUBJECT REQUEST FOR LIST OF PROTEC TED SF'ECiES p,ND ESSENTIAL FISH H,l\8ITiH INITHIN THE P,REA UNDER E'VALUP,TION FOR THE INDIAN POINT NU':LEt.,R GENERATIN(:' UNIT NOS,:2 AND:) LICENSE RENEV/'L APPLICATION REVIE'N T:w U_S N!.:cieOlr Re'~"I"'tory CO:TIIO;I%ion {NRCI i-3 reviewin9 an llppllcOition submitted by Enlergv Nuclear Operatiof):" Inc, for H-Ie rel:ewal of H-,e operatinq I:censes ~or Indian Poinl Nuclea Genemtit:.;! Unit NIY, ::: and :3 (lm!:an Point)_ Ir1d:an POint is laeated in 5,-,ch;3nan, t'.!y, 2lppr0x:mDtely 24 miiw'i north of tiw New York City boundar,,' iine, /'-:; part of tfte revie,-\! 0' (I"e
'icense mnewlli appiicati:)ll (LRiI.l, the NRC is pr"'Gar:ng a Supp:ell1",ntal Envlr:)Il::,enlai Impact Statemellt (SEISI !':nejer the ,::rovis:ons Df Title 1;] 0:' H-Ie Cocle of FerJelill Regulation::: Part 5"1
,-10 CFR F'drt 5i), thB NR'=-s rB9uiotion that i,-nplements ihe NDtiol1dl EI'!'-Jiroll::]eni::1i F'o:icy,D,ct (NEF'A) of :96J" Th", SEIS :nd,Jd"':3 an 3:1<:>I)lsi5 of perlinelll elwiron!l:ental issue:,,_ :!lclu::lillt;J endangered or trlreatene'j spedes and imp",;:.;:; to t'flarinG resour;;es "me! tvabitat Thi" !elter I',
bej~~fg s:lbn::Herj ur~der the pro\*'is:o[1s af tl::6' Endsn~~5refj Specfs3 Act .of 19 7.3; 5~ 'Dn:ensleo) :;hs FIS'l alld "v\iildli:'e Coordination Ad of IP34, as <<!118nc!8d: 30ld the Sust<llll;3ble Fistleri85 Ad of f E}~l!). T~le pf'Jposed adionis to reflew ttle f8Gi!Hy opera;:!l:g licenses for ir:c!i,3n Point fOI- an acditicm,,:i LG ',:ef:I'S beyond the exp:rat:or, of tl:8 c.c:tTent :jperat!n~~ I:cen:;es_ The pl'Oposed fIction \l,folJld
'neil/de :t-Ie lise ""xl cDntinued !l'ailltenanc", of existit19 plan: f<:cilit:es <IIY; !ral:sll"":s:OI'l I:nes_
T:18 Indian Point site covers f:PP!F(:matelv 23G "cres_ Indian Poim IS bDt-cl8red 011 t'-18 north. 50IJih and e,,51 by pC1rlial'y v,':)oded pr:vately awned land <m(j 01-, tile ,:ve:sl by tile Hudson River_ Enc:osureSo ,t and 2 prov:de 8 ge!ler3~ overvie'"v oj trig ';jtf:' ~oc8tion 8nd Sit8 :8YDUL Indian P*oht is 8qu:pped with", ollce-thmll9h op",n-eyc:e GOolm9 sys;elT: tl1[,1 'Nithdrm\'s cooli:lg wa!er from and clI5c:-rt'fge:. !Jack 11110 the Hudsc:I-1 Ri'.;er, The mtak8 "YS1"),:1 illdl.:d",s "even bEl)':; fot- each unit bC'Jted CIt tile ,i-,ore_ Six ';iG-:nch pipes disl.:barge -wfltet- beneath the 'N81e(s surface I,vit!-f~n 8 4!J-foot ~v:de discharge Gsna:. NUREG-1437, Supplement 38 E-14 December 2010 OAGI0001367E 00333
Appendix E The tr8I'"lsF::ssioFl jjnes in lrl8 SCOp8 of NRC':; 8r!vi:-onrpent81I"eVie\~V fDr HC81:se r.e:nev)lal :are t110"e tI<<lt 'were ol"lt;JinQ:ly <;oflstructec1 for tl18 specific purpose of conneclin9 H'le pian; t:) tile trar:smis'3ion ,;ystem, The ;rar:smssioniine ;;orridor to the BUC::-I8I:an SlJb*,tGtror: (<lPPI'oximnte!y 2iDO feet 'Southeast from the reactors, .1:J'3.t acw:3S Broadwt--'Y from the file-iii!y's i1l<:,i!l I?mm!lGI?) is IOCil\e::11r1 tl18 ir:[jl.ls!riB' ",mion of tf:e site, except fOl' wnere tr,e lines eros:, Brnadv,lay. Th~s t:an~,~-ms;:.i{}n liDe corridor h beirH] 8valu8~ed 135 Pj):-t of the SElS pr:)[:8~,S. The enclosed tralIS-ITllSSIOn line nmp SllO>'/S tl,e tr.:msrnlss:on system n',at IS bell:Q I?v"lt;atecl II: IIle SEIS, Two 345*kil*:)"/olt {k\!) li!ll?~, conried India!l Point to tl:I? Buchanan Substzoticn, This (;or:-:(!o:- al"o illdl:cles I3E-k\--' ,nmslTlission I:ne'; til at slmply off;::rle ':;O'I,ver froll': tile ;::ullSta!ion into !1l<1ifln POint. To support nJe SEIS prepsr"tion process arK~ to ensure COI"plisllce with Sediol1 7 of thE> EIlClan~18re.;:l Spew"s ,I)\c! !lle NRC requests infor!1l<ltiGll on Ff.'Gem::y ::sted. p:'oposecl, ami c[lnc!idate species; aile! cnticall:abitat tI:at may be :n the vicinity of the Indi211: Po:nt site. III mldi1iofl, 1)le,"'E> prCi"/idB 2ny in;'ommt:on yO!~ GO!v,ider appre3pr:ote uncleI' ln8 DPJv:sion;:, G~ Ille Fish and \NildlifE> Coordination Act Also, in support of t:w SEiS pI'ep8mtioil 8nd to E>r*sure compliallce with Sect':ol: 3:J5 of the rv'l<1gnUSGIl-St9vell:3 Fi5bery' COlls9r ',a]ion 211:t! r"'lw'a~19ITlenl Act the NRC reques;I~; ;J lis;; cf 8sserl!lal fisfl habil,,;s Iha! ha\l8 been ;jes,iIJna!8C:i if! the vicinity of the Indiw: POint site, 011 SBpt81T'ber : 9. lOG?, the NRC :ste,ff plans to hoid twa PUblic NEPA sc-op:n~i meetir:gs at trle Co:ol'llal Terrace, loc<:ted at ., H'I Oregon Rd,in (*oI1Iancl; 1"1,,nor, NY, The first sess:or< Wili CQI:\i8ne 3t 't"30 p.rn. and ',fill: ccmtil:u until 4:30 p.:11., as nec.es~;ary. The second ses~;jofl ;;vH; convene c:t 70(1 prn, INith a repeat Df It,e ovel"-/ie'N port:on:, of 1l'Ie rneetin~i, alK! w:1I continue unti: W:DO p.m., as n8CS,,-,I'V TI:e NR.C staff plal:s to conduct [, "lite audit at trle Indian Poil:: site during the v"'eek of Septe,,:ber .: 0, 2007. You !3nd your 5til~f are invited to !3Uencl batIJ the yub:,c meeting;:: DI'clll,e s:te audit. In iJcldiiion. 'lour oiflce will receive a COIN of tile drai , SEIS along wi\!: a f9qU9"t for comments The <lnticip<lt9d publicution date for the d~'aft SEIS is July lODt:. If you have al'ly questions. conceming the NRC $~Zlif r9vie,v of thiS LRA, ple;:)"e contact t~. ls, ,W: Ca"Iel'ly, PrOiecl i'.*lanafIH at :};J1*4IS-G6~j8 or j.:j.'LU;':W-'-':'.::.t.<" Sincerely, iRA! Rut': Fmno'v'ich, Bmllcil Chis; Em'ironment,;i Branerl B Division of LiGem,6 RenewiJi Office Qf NutiE:aI' Reactor Rel;Julalion Encio'S:ul'I?S:
.A.~; ';tated December 2010 E-15 NUREG-1437, Supplement 38 OAGI0001367E 00334
Appendix E
,A,ugust 24, 2007 rvl:', Andy \Narl:ol' Di!'ect'Ji", Cultuml P:'sc;ervatioll Absentee Shm'lnee Tribe of Oklerlol::a 2025 S GOI'don Cooper Drive Sha',Nnee, OK 748(1:
SUBJECT:
REOUEST FOR COM!',,1ENTS CONCERNING THE INDIAN POINT NUCLEi'\R C~ENERP,TH-.jG UNIT ems 2 AND 3 LICENSE RENEVVA.L ,4.PPLlC,t.,TION RE\./::EVV
Dear HI' W<:
rrior The US Nuclear Re~l\JlatDr'iCDITlrni';c.lon {NRC) :s :,ee",ing input for :ts envll'Dnmen!81 review 0: an application from Eniergv Nuclear iJpemtions (Entel'gy) for- Ille rene,..,.,,1 of Ihe open:,::ng licen:3e:, fcr the Indiun Point Nuclear Generatmg I)nit Nos, 2 aml:=J ,:Indian Poinn, loci3ted :n Buchanan, NY, approx:rrmtely 24 m:les nortl: of the Ne'N Yor'k Cily boundary line, Indian Point
- s In close proximity to lands lilal ma, be of il'!8:est !o trle Absentee Shmvl,ee Tribe of C!klaholTl8, As cle:"cribed biow, tl'e NRC'~, pnJC8:s'; includes all opporlullity for ;:.ublic onei
- nter-9Dvemment81 participation :n me environmental review, VVe wont to el:sure that you 81'8 aV';8r-e cf Dt:r effDr-::~; ancL pursl:ant to TiHe '10 ofth:e COffe of Fedelr~'1 ReQuh:iti!JnE (10 CFR)
Pm; 5'1, Sectiol, 512B{t>>), the NRC if1vi1e~' tile Ac!sentee Sfl8vinee Tribe of ()ki;}fID'Tla to orov:de:nput to tbe SGopil:g process re:aUng to the NRC's el:v;rol',I1'entall'eview of the appl:C[ltiof:, In a<::clition, as outlir:e.;:! in 36 CFR BijO,8(0, (r1f3 NRC plans to coordh,ate cocnpliallCe with Section 'iOe of the Not:O£E:I HistDric PresBrv,,:tic!Il i\d oi I!~::f, t!:rOlJgll the
- 'equ:rements of me National Env:ronrnenta: Policy A,d of 18139, Uncler NRC re;~ulations, tile or!~linal ;)peralin~~ licem,e for a nuciear pDwe:' pinntis issue,l fOl' up to 40 ye;:ws Thelicerrse may t'e renewed for up to f,rr additional 20 year's if NRC reqlJ:I'el,-,ellh are Ine; The current olHratinp i:cer:se:, 'nrilldian Point wil: expire :n September, 2013, zond Deeember', 2G I 5, Entergy '3ut,m:tted :t~; 13ppiim1iorr for mnewa! of tile Incli:C:1l Point opemtillg licenses in a leller datecl ,"'pril 13, 2007, a::; supple::lentec! by letters; (iated Hr:y ::, Dnd
,June 21, 2ij07 n"3 NRC is gatllering information for arr Inrjian Poim site-specific supp:e'11em to its "(3eflHic Environmelltallmpact Stmefllel'lt for L:c:ell:,e Renew8: of NuGieat F'lmlt:3' (GElS),
NUf:;!EG-'1437, The sL:pplement ,,!,,':II contain tfle results of the r8'.;i8\1,,' of the erlVimnmentzll
- ITIDacls on lile area SlIITO!;ndinr,l ,tw Indi81l Poin, site relmed 10 terre:,tr:alewlo:;ry, a(Ew!ic ecology, hy::lr'ology, cullural resou!'ees, 3n,j ',<oc:oecono;:',;c:ss'-les (emonr,l olher",<), and w:11 contail' <: recomr::endat:on reg8rding ti'le environment'JI ileceptat;ility of the license rene'l'-';'JI ad':]I'I, NUREG-1437, Supplement 38 E-16 December 2010 OAGI0001367E 00335
Appendix E A." VVcHTior To 8ccoll1moda;e in;e:'e,ted I"nembers; of the rub:ic, tile NRC will ",old two put;lic <;coping
- lleHtil',,:;;,> for the Indinn Pointiicer:se re!'ewal supoleme:lt 10 t~le GElS 0:1 \Nednesdny, September '18. 2D07, at The Colonial Terrclce. 10Gsted all'19 Ore~ion H'j in Cortlandt
[*,-1"no:; NY. The first SSS'SiOll wili convene at 1:30 p.IY:. rind w:1I continue until 4::30 ~;.m .. 8S nece:3sary, The seGO!v:: se:3'3ior: v<ill GOnV81'e at 7:0;) pm" with ,j repeat of the oV8rvie 'lv
- )or;ions ;)f the meeting, ",rid wil i c:ontint,8 umi! 10:00 pm., as neces'3flf'\,', Ad::l!li;)I",aliy. the NRC stoff \.vW f:Gst lnfonr:::l~ ~jiscussions one hotlr before H}9 sta~i of e;)cl: ses::::.ion.
The iie8!:se rel,ewal flppliefltiOrl (LRA)is publicly fI'*mii",ble ;Jt tile NRC Public Ooctily;ent Room (POR) iocate(1 8t One WI::t:? Flint NOlill,!'; ':>55 Rockville Pike, RJckvilie, Maryl61ld 20352. or from tne NRC's ,.I'\.~ler:cV\Nide DoclJmen!s A.cce% £!I:d :vlamlgemEcm System ~ADA.MS). The
,ADAMS Public Electronic Eeadil:9 Room is access:ble ;at i,t,o .:;Jd~::n*,.w~:I;s'",:::c~*:.i""'{,,';c:*,j.:d()i::"lip 1::1":';;' TIlE' ::icGe'3:sion number fo:' tile lRA is
!-.,.lL0712105G7 FeEsor;s 'Nho >::0 no! hiwe aCC8S~3 to i\.D,~MS. or 'vvno encountel' pl':Jtjlem~31ll accessill9 me clocumel',;s iowlec! In A.DAMS, "Mulel contact the NRC's POR Reference staff by telepnone,lt !-800-:3fl7-420H or 3:]'1-4'15-4737, :J!' t,y e-mail at '::'],':",1;W::;"l.r2',:,
The Indic:rI Poil:t LRf\ is also c:vailable 011 the Inlernet ot
- "tt: p /::*::'..:ww"r::" ,:~ ..:; ::;"; ::*::*;.~~G":{*~ s.: c~r>:~:" c3i in(: ':Jl,:~"~n:~i~ V::"f *:~n~?:I'.:':~ :/;:~~::~)i :(:;:~:ti:i:I:":::,.f:i~ :~ji;:~:"i" )::~i rf:: ~I:t:r~:. In aeldit:c)n. the Hen.;:!r:cl, HUGs,xI r-I'ee LibIT:ry, locate;j ir: fvlonll'OS8, NY., H'le riel::! lic>wlY 10C,":l<o>(1
- n Peeks;,il:. NY, an.;:! Ine ':iVllite Plam:3 Pubiic Lib:'m'i ioeated in VVnite Pia,rlS, N'{. nave a~II'eed to make the lR.A available for pUDllG inspection The (;EIS, whiG'" clocumenl<; the NRC's a,>,ess,.,18nt of tile :,COP8 ;:m':i impact of ery...*imnmentfll effects. th8~ v.fou;d !)e assodi::1ed \"1:th iicense rene\.v::l; at 8ny nude::!!" pov.ler plant ~;:te. can a:~;G
;:;*8 fOLH:d Gil tI:8 NRCs 'Nebsite or at the NF~Cs F'DR Plea'3e subrmt any GOnllYlents lila! the .A.thentee Slli3wr:e8 Tl'itie of Oki::;n;)rna fiB'\, rlave ;0 OilBf on the scope of I",e 8nvimnmBntai :'eview by October '12, 20G7 Written Gomments s~louici be suDmitted by 'T,ail to the CnieL Rules and Oireclves Branch . Division 01 .~drninist:ative Sen-'ice~" r""laii Stop T-,;,059, U.s, Nuciear Re~wlalorv Commis:3iol1, VVa:sl::ll£)loD, DC 205!:-5-0001 Eiectronic CDmrnent5. n'D'{ t;8 :;ubm:tted :0 the NRC bYEHTlaii at
- r:(liii,.:~***)::':,~!S/T::ln: .* X;'*1 At the GOl1ciu::;ioll of the :3(;opiIl9 proce%, tile NRC: ;3tt:,ff viill prepae a summalY of H18 si;Wl'fictlllt issue:, :::i6l:tifi8;:: and tn8 cDnckrs!ons re::;cI:8(1. and fllijil a CDI}Y to you.
December 2010 E-17 NUREG-1437, Supplement 38 OAGI0001367E 00336
Appendix E
.,
-,)-
The st::;ff expects to publ:Sf: the cirail supplement loU)e (jEIS in JU!y 2008. Tf:e NRC w:iI hoid another se! of ;::t:biic 1T":estings in !he :,,:te vicinity b sol:eit COIllIT":ents on the c!I'gf! sup pie mental envII"onmDtal :mpm:l stBl.eIl:ent (SEIS). A. copy of tr:e clraft SEIS '-N!H be S8r:! to you for'iour review and mrmnent After Gonc:lde!'8t:oll (if public (:omnHnts received on the dmft. t~r8 NRC will prepare a final SEIS. Tile i:o.sut1nee 0; a fir:al SEIS for Indian Point is planned for April 2009. If you need 3ddilionai: informi3\ion fQElfi:ling U:8 eflv::ronrnemai reV!8vc! proCSs, plea:"e cOI:iact [vis .Jill erNe!"ly. Environmental Pr")ject MD.fmger, at 3[)'1-41 :,-i3Cfl9 or ilt Sin{:erely.
/RA Christjan .Jacobs fori Rar:i L Franovi:ch. Bn'lnUl Chief EIl"iiron,:rentcll Brand'i B Dw:sion of Licellse Renev.;a:
Office of Nucleflr ReaetOl' Re~l'l.Iimion Docl,et Nos. 50-247 fmd 50-236 cc See !:ext page I NUREG-1437, Supplement 38 E-18 December 2010 OAGI0001367E 00337
Appendix E AlJgust 2~. 2007 The H:)llorable Maur:ce John, Preside:l, CaU<lraugu5 Rw:;e!vat:O!', Se!lt>ci.:1 Nation
!4D Rt 438 Irving NY14DI,\"I
SUBJECT:
REOUEST FOR COMHE~JTS CON!~ERNING THE INDLAN P()INT NUCLEAR. C3ENERiHING UNIT NOS, 2 AND::; LICENSE RE~~E\;"i.A.L APPLICATION REVIEW Fie US, Nudem Re"ulatolj Commission {NRC} IS; seekil'g input for it'> epvironmental review of 81' [Ipplicaci:)n 'rom Entergy Nuc:em Operatio£l-3 (Emer~lY) for ;he rellVifal of Ihe operating license:; fo:' ,he Indian Point Nuclear (Oene><"I:n9 Un:! Nos, ::: and :5 (Indi'Jn Point}, locateci :11 Bucha:K.I', N'{, apPl'Oxill'ate!y 24 1n,le3 north of the ~~e,v Yuri<. CityiJoUl,dary line. Indian F'oi:lt
- s II: dose IJI'OXlllll!Y to 1;l')(i:3 ,i"e'! :;-,ay bE' of Imemst to the Calta:-augus Reselv;:mon, SenE'ca Nat:on. As descri!:!8::i r'eIO'w, the NRCs proC8% i:lc1l1des an oppurtllnity for public and mter-90vt>rnrnenl<li p2!!t,c:i;xl/iori i!l the 81wircmrnEI'tai nwiew, INc 'Nan! to ensure Inat yo~! are
~J~,\"'are of ota' erfclfts ::-Hlli, !XSf:;U::Hlt to Title 'tD nf the (\)(:e {l FedB(fJ/ RQuJ~~t.iGns C~O CFFn Paf1 5*1:. S8ctio0 ::1 : .28{b}, the NRC in*'.l~te::::. t~e CaUan:HJgu"S Re5er**~Jatlon, Seneca Netio!':: to
;:;r<wltle IIIput tD ttle :,COPlng proce% fE¥E'llg !G IIle NRC:, ell'-{irDl,rne:'lt[li rev'e"", e)f FI8 appl,cation In addition, a:s. ouilineci:n 36 CFR 80:J8(c), ;hG ~JRC p16ns to coordinate compliance with Sediol: I :J!3- of the Nationi31 H::,~o::c Preservatioll .Ad of 1966 tl",OlJ'J!l 11:8 reqt:irelllEd:, of Um NZltiol'!:'",! Envirc.mT181,tal Policy Act 0' l,i69 Under NRC requl<llIOI:S, tI:E or:ginal ,)p8!"atllll~ llcense fo:' a t:ucleal' po'",e:' plafttis ",sue.;:! for up to 40 ),*earc;. The licer:se may be reneWEd fOl' up 10 em addik:n81 20 year-; if NRC 1'8ciu,remenh me met. Ti,e current c:peralinp licenses fur Inclian Poio, \ltd I 6xp:n" in September. 2013, and December, 2015. Ent61IIY submitted its ,3pp!;calion for ren8W[I; 0; the indi[l!l Po,nt opep:lting
!!cense" in aleler CifltE'd A!)ri i 23. 2007, 8:, C.,lpplemenleti e,y letters :jam," M;JY 2- nm!
.Jtlne 2'" 20Cl7 T:',6 NHCi's gather:n[Jinformation for ,.r. Indial" F'oim s:le-s;=,eeific supple'H8m to i,s "G8ne,-ic Environmentallmpad. Stillen:ent for License R8ne'Nu; of Nuciem Plants" {GElS),
NUREG-'1437 Th8 ~;I~ppiement wi!; cnntZiI!l the results Df tile reviev,,' of thO) environmedal impacts ot: lhe mea surPJunding the il:dl[:n PoiJ:t 5ite reinte:j to tHrs'3inai ecology, aquatic ec~)~og'~'l- hydrOlogy, L~JltUL31 reSO~lrGeS_ and ::;.:)dDeCtH"!ornic is:;uE:<:3 (fl(i{Ci!l(J others}, B:nd v~fiH cDI:tain a recornmendatiofl regaf~jing 1he en~l!rOfWnen~ft: fiGceptab:::iy of the lic&r1':.e rene'vvt:! action. December 2010 E-19 NUREG-1437, Supplement 38 OAGI0001367E 00338
Appendix E ld ..John To ~cco'Tlmo(jaieinterestec! members of the publiC, tl:8 NRC ,viI' I"-,okl t'II.',) pU!Jlic :'.(:O:}in~1 fIleetin*'is 'or the Indian POIr,; licen5-e 1'81'18".\'31 supplement to ;ile GElS on \/ifednescl8'y'. Sepiel1'ber '19.2007, <it TI18 Colonial TerPJce. 1(lcated at '119 Oreg(ln R<:i If! COl'tiancit fv1::mo,', NY. The first s9:osiol'; will convene at ., :30 p m. Zind Will continue lB,t:! 4<,0 1).1"1; , as nece:;C;;}f).'. The second ,;e:;:;ior, wi!! convene OJt 7:00 Dm., w,th 13 [e;:le3t of (toe oV8rvie:II" p'Jrtlons of the meetmg. and 'iN:11 continue ur:ti'IO:OO p.In., as necBssnry. Addi;Io:'lall'y', thE' NRC
',18ff >'IIIII1OSi Infornl~1 :jISGU5SIOns one noul'l:;8fore a'ie start of eacf: :;e*,siol1.
Pie license ren8wal application (LRA} is ::HJb:icly available <It ;"e ~~RC Public DOG'.II,:"mt Room (PDR). iGCat8d alOne 'NlHe Fli!,t Nor~h.I*155S R'Jckvllle Pike, Rockville, t*,'lal).'i8l,d 20352, ,)1' from ti,8 NRCs A.genc,!w:[)e DOc'JIT:8nts f\,cces:; snd rv'I"rlll~;emenl System (,11..0,6&. . 15 i Tile AD,-"IMS Public Elec!iofl!c Rem!i!'g Room is acc:e%:ble at http /:2:;:ia:'-;l~.V:... ~:::;.~:e~~f;:)':.r;:'(;.{:(:\l"':jo~:)q~n i-:H~:i. ThE aG{;8s~:=:.ion rv..J(qber fo;" ihe LRA is ldL07*12*W5G7. Pel'sons; 'Nha do 1"'01 hwe accss:; to ADf\t*,lS. or 'who 8IK-OI;:1(8)" proDle:lls:n aCJ~e:3s:n~1 nle c:loGul1'ents locate::! in .ADM*.:IS. srIDul::l cOl'incl tt,e NRC':3 "'DR Reference :,taff by telephone nt '1-800-'3f~7 -4209 or 30'~ -4 '15-4 737, or by e-!TI<.:1~! ,3t ~:{tC~i'nG~"g~:t~. T~le Indian Point LRA is ::<lso dvailable on the Int8met 'J,
- !LU~E"i:,\.'vi',J'3:;,D;;:~*,*;I:~"t'~\:JJSq.'(":,,~li'j~:il['-"';::],"JJ.['i!J.';::J";:'i',0.U,i),mii<~:,].t.:,\iE~'J3,:"Jl~"!,'J~:::jJ.,L!Lll: 111 f]ck,itio'l, tile Hendriel, Hudson Free library, located in ~':Ionlrc;se. NY, the Fiel::! L:bmry locmed
- n Peei.',skill, NY, tind the V'ihile F'IClillS Publ,,, Library iocated In *vVr.:;e Plmns. NV' ~Iave <,greed to make ti,e LRA "",.'allable for ;)lIl):IC Inspedioll T~le GElS, Wllid, documents me NRC's ass8ssr:lent of tll8 scope and :mpact of el:*...*irQnment211 effects th8t would be assudated v-jith ::cenSe renevv;:l! at 8n~...' nuclear pO\i\ler ~dant site car: also t:e found on ;ile NRCs ..,."ebsite or f111he NF~C'3 F'DR Plea:,e slhmil any COITII118nls ella: the Ci3!,amugus Reserva:ion. Senec[l Nat:on may h3ve to offer on tile scope of the 8IlV:I"OI::'fl81l!al revieW.. by Odober :2.2007. 1;\lntlell comments sllClul<:!
be submitted b},' mail 10 the C!'lief Ruies and Directives 8ranch, Divis;i0:, of A.dmlni'Slrati*,m Service:" r-.;la:1 StqJ T-6D5~;, U.S. NuGiedr Re"iul<J!Of).' Cor,.,mi::,icm, \N83hinplon. DC 20555-0001. Electronic GOIT;:,lenis may t'e submitted I') the NRC by ",mail at lL;~,~'!!::?2tllf~;~*;@!:.:E,,';<;>*,.. At 11:8 conciu,ion Of the scoping proce35, ,rle NRC staff will pl'8pme a Sl:mmm-y cf tile significzmt :s~,ue',; Identified ,:l1d tile cGnclus!on:, l'eacheC!. ar,d mail a cop,,' to yOu. NUREG-1437, Supplement 38 E-20 December 2010 OAGI0001367E 00339
Appendix E M_ ,John TrlB staff expects to i)u[)iis!< ,riB dmft :,_tmplemBnt te; H-le <:5t:IS in ,Illiy 2008. Tlw NRC w:1I1101d arV)trl8r s81 0' public 11'8",'iIl9:' ill the sile '1icinity to c;olicit COITIIl18nis Oil trl8 draft :;upple:TI8nt8i E:llv:ronl1:entlJi ir'lpacl stmel1'ent ~SEI-S). A cOP'I' of tile elm;; SEI-S wil' b8 sent to you for your re'lie'h' an(1 cornmellt. After cOrls:d",ratlo!) of DubilC cornme!)t., rece:ved on H-Ie ::Irall tr,e NRC
',.viii prepare <1 fined SEIS. T:-18 i%uElnce of El fifl[ll SEIS for InGian PO::lt is planr,ed fOI-Apr:12[)08. If you r,eed a(jditiol1<Ji infOl':'l[:lion r",~:ar(liWl the erlvironrnental re','iew p:-ocess, plea",,,, contact ~,'ls;_ Jiii Cn'lel-Iy, EllVironmelllnl Project Mann,i8r, at 3D'I-~', 5-6f_/19 or f~ t f.:~*~~_;_£g!H~.LS}:2}~.
S~flcere:y_. iRA Christian Jacobs for.! Ran: L_ Franov!ch, Branch Chief Elw:ron,:1entai Bral1c!l B DII':510n of License Renewal Office of NcJciB£Ir Rei3do: Re>;lul::H!On Docket Nn::.. 50-247 and 50-286 (;c See next p'JQe December 2010 E-21 NUREG-1437, Supplement 38 OAGI0001367E 00340
Appendix E AlJgust 2~. 2007 1'/11'. Clmt H'ilftoWIl Repre':;elltativ8 Cayu~~~a Na~j;)n PO Box:
\!ers;ai::es, NY 14'168 SIJBJECT: REQUEST FOR Cm.,IMENTS CmJCERNING THE INDIAN POINT NUCLEAR
- ENERATING UNIT NOS 2 .AND" LICENSE RE~*lE\NA.L AF'PL.lCATIO~J R.EVIE'll FIB U S, Nlldear Re~luiatol-Y Cornmi'3
- ,inrl {NRC) 13 :,eekil:9 input for it::. elwironmentsi re',iew of 31: application from Entergy NUClear Open"t:oll'S (Entergy) for the renewal of lile open"t:rl(l iicew;,.." i,x :he Indian Point N~!deilr Ger:en:t:ng Un:! Nos, 2 and :3 ;lndi8n Poin!). IO';;3ted in BucilDnm:, NY, Dppro)(lfH;te!\, 24 mdes Ilorth of trl8 Ne\l,I York Citv ilom:cla!v 11fI8. Ind:an Pomt is jp close pro:<ttYll1Y to f9:1ds t.hnt ~'(19y be :)f jntB:8st t.o the Cayuga N~ltjOn. lAs ,described bekx(,o\o',
the NRC's pmce:;s h:clt,I[le':; an opportunity;or public alld inter~JClve:'!llTlellt2!; i}mticmatiGI1 WI the environr;-H~ntd: revteVi/ ~r.,.ie V.JfHit to ensure th~1t you sn~ 0:vWJre of our efforts r:u-;d, pursu8rd 10 Ttle 'I:) of the Gods of FBde(EJ.I ReQuhlticns i'; 0 CFR) Part 51, Sediol', S'I,28(b}, the NRC invites tile Cavu~la NEllio!) to prDvi(je II1PUt to Iiie ~,COPIIl~~ p!oce:,s reic:tlrl':) to tI':8 NRC':, enVII'Ofl'TI8!)tal fev:ew of the spp!icaliOl: In addi!ion, a'S ou!:inedin :30 CFR 8008(c), ;he NRC pial1:s, to Gomdir:ate compliance w:t!: Seciio:l '106 of t!18 National H:sto!ic Pieservatioll /',ct of ; '~6f.i thmugh !rle :eql;irements of the Natiorni Envircnmer::al Po!:cy Act of FH39, Under NRC requlallol:s, tI:e or:ginal :)p8!'atllll~ llcense io:- a I:ucleal' po'",e:' plBfltis i',sue.;:! for up to 40 yearc*. The licer:se may be I'8l'ewed fOl' up to em Bddit!onal 20 year'; if NRC r'eciuireme'lh are met. Tl,e current operating licenses for Inclian Point \ltd I expire in September. 2013, and December, 20 '15. EntelIIY submitted its o3pplicalion for renew[,: 0; the Ii:di[,!l Point opel":iting
!!C8I'1Se:s in aletl8r [jelted A!)ri i 23, 2007, a:s ~.'Ipplmented t,y letters :jam," M;JY 2- nm!
.Jtlne 2';, 2007 T'-le NHCi's Qalher:n[JinforlTlation for ,.r. Indial'l F'aim s:le-s;=.8eific supple'nem ta i;s "Gen8ric Environmentallmpil(,t Stillen:ent for License Rene'Na; of Nuclem Plants" {GElS),
NUREG-'1437 The ~;I~ppielTIent will cDntZiI!l the results Df tile fevim'-i of thO) e'lvironlnedal impacts 01: lh8 wei'! surPJunding the il:dl[ln PoiJ:t ,,,its relnt8'j to tHrss!nai ecology, aquatic ec~)~og'~'l- hydrology, L~JltUL31 reSO~lrGeS_ and ::;.:)dDeCtH"!ornic is:;uE:<:3 (fl(i{Ci!l(J others}, B:nd v~fiH cDI:tain a recornmendatiofl regaf~jing 1he en~l!rOfWnen~ft: fiGceptab:::iy of the lic&r1':.e rene'vvt:! action, NUREG-1437, Supplement 38 E-22 December 2010 OAGI0001367E 00341
Appendix E C Halftow!l To f:ccon-,moda~BirltBrested membel-s (If ti:e publi.;;. tl18 NRC w:!II};)id two publiG scopil:~! meetill',;s 'or the Indi8n Poin iicense rene,:,'ai supplement to ,he GElS on ',Vednesda¥, SepiBI1':}er Hi, 2007, at Hie Coion:al fer-rucs. located flt*, 19 Oregol' Rd. ill Cortlwc,jt fv1::<no:-, NY. The first se%ion will (;01We1l8 at ; :30 p.Il'. and Witl continue unli14:30 p.m , as nece;3c;ary. The ;3econd 5e',,,,;01: ',vi!! convene at 7 OD p.m., Witt] a repee:! cf tile overview p'.:.rt:0f"3 of the meetll"9. amj ',<;:11 continue ul'lll W:OD p.m., as neC'essary Additionally, the NRC staff 'N111110S\ infornlGi di",cl.iSSIOns one nour t)eiOI-e ,1"18 st3:*, of 8m:i, session. n,s !iGense renewa: app!i(:ation (lRil,) is publiCly avaiiBble et ,"18 NRC F-!bliC Document R:)on1 (PDR). IGca!ed at One Wine Flir,\ NOlth .. '1 '1555 RockVille Pike, Rod'lille, r',.iaryiancl 2G352. or from t:1e NRC s Agencyw!cje Documents .AG,;e,,,s ilnd Ivlsf1Dgemel1t System !.AOAJilS I. Tf:8 ADi,\MS Pubiic Ei&CTOfl:G R&mjir:g Room "~; ::H:.Ge,;sible at htt[r/:*[:;=:ar;l*~.\'\o'%:').3eaf{:}-:.r:;'C.(K:**I:'**c:'=d~)G~n_i~::tn':i. The accession nUPioer for the LRA is t\'ILOTI2', Cl5G7. Person,:; 'Nit:::. do pot hwe access to fo.D.4f,.iS .. or who enu;unte:' problems ::1 aCGe:os;ng tile clocuments io(:atecl ill AD,Il,J."IS. ",rloulcl contBel tile NRC~: PDR Reference staff i~y tele:Jhone <1t1-l',OO-397-4209 or 30 ;-415-473 7 ,or by e-mml at ;;l-,).r!~,!:NL9,Qx. The Ind:an Point LRA. is siso cwailClble on the Internet '3t iJ.~U~L~i:""'~LI'3~'L9;):,';'r:~_;l':';:~:L:~::~:;1(;"_0.;::J-'.dl<:C("3_:_,"JJ.:g;_:_("3_:-,j:~':~:;:~_~ll~"::::'_'-~i_'~::':~:jJ.::);']J.:_:::!::)_:L:;_L~I'!j In add;tiCin, tile Hendr:ck Huci:;.)fI Free Libmry. located if' !',;Iontro:;e, NY. the Fie![j Library ;owteci
- n Pee:'.skill. NV, clnd thE> V'ihite PIl::ins Publ:c Ubrsry IOGatee: in V.,rhite Plains. NY hd'ie agrE>ed to I:~ake tl"te LRA ",;.,.'allable iOI- pUi):ic '"Specti()I' Tile ;3EIS, whicb dOC:JI11HI;S Irle NRC's 2lssessmem of tile 'scope and i:'lpac:t of ell\'ironment'JI effects th8t v~~ou;d be a~)sodat8d ~N:tr: ~:c9nse rene'J~iaJ at Gny n~Jc:e8r pO\4Jef plant site, eril1 also be found or, ,he NHC"s 'website or st the NRC"s PDR Plei3"e :;u:)I"nit ':iIT\' comments ;il"" the CaY-Wi:'! Nation may It",,,e to off9:' Gil tne scope of ,he en'lironrnem;::i review try October 12. 2007. \Vrit!err commellts ~:ho'II::1 be submitted bv mail to the Chif:f, Rule" [,nd Directives Bmnch Dp..-ision of Ad','lin,c;trg\ive Services, r',;'icll; Stop T-eD59 US. Nlxlem- Regu;at*.xy COIl1!Tli%ion. \N8snin9tol1. DC 20555-;]001 Electrc::nic COITllner:!s 1l1ay tie sulxnitted tl) the NRC I)y e-m::;!! at J.i.1:,:i:;:!!.J>'Ar:j::,;,~:::'h.:F:.~;::.::". A,I Ii-Ie conc!uslor, of the scopill';; process, mE' NRC staff wili prep:::re " sUHlr":"ry of the ::;i~1niiic<lnt '3-SlieS 'den~ifi8d <,nd the cor:clusior:s reoche'j, and [::all <1 <;opy to YDU.
December 2010 E-23 NUREG-1437, Supplement 38 OAGI0001367E 00342
Appendix E C Halftovo'n -:5-Th8 s;t1:df expects to pub,isf: the clr<:ft supplNrl8!lt to the GElS ii' ,JLJ'Y 2008. Tbe NRC will bold a.noH-jer :,et 0: public n-:eetinr,ls ::1 the ',<ite vicillity to solici! COIYlmenls on "-Ie dmft :3.upplemental HI\/ironmentai impact stelement (SEIS) A copy of tl:6 draft SEIS w::1 be sent to you for your reV!fw,.' aJ:d c{Jmm81't. Aftel' con~;:[jerati')n of pubHc Gomrnents reG8i:/eci on tt18 drnH. the NRC INil,: prepme ;:> f:nni SEIS. Tile iss,![JllCe of a firm I SEIS ior {IKHan Point is plm-tIled fOI* Apr:; 2009. If you neeCl aClditionnl infor:T!8tioll re~lardll'1~1 ttle en:;ilollrnenral 18VieV{ process . plense co:-I,act :\-ls_ Jill Cavel*ty Environmental Project r. ']ana;ier, at 301-4 *15-6(;9:~ Of it! i'?:~~_L:~~l~i~:_:~:~~~l:E{ .
- ,ncerely,
/RA Christian Jacobs fori Rar:1 L. Franovic!:, Brandl C'-lief Envimnmentnl Br,men B Division of license Rene\fv;.:-H Office a~ NUGIE:ar Reactor Rer,juliJ,i0!l
[locket Nos. SD-247 and ':,0-286 CG See next pa~le I NUREG-1437, Supplement 38 E-24 December 2010 OAGI0001367E 00343
Appendix E AUgU'3! 24.20;]7 1:!'S. N:kki OV:iinflS-Crlimm EITvironp,ent2i Dino>clor Deiaware Natiol' P,O. 50x 825 AndarkD, OK 730:j5 SUBJECT REQUEST FOR Cm.*i1"IENTS CmJCERNING THE INDlAN POINT NUCLEAR (;ENERiHING UN!T NOS 2 .AND " LlCEt..JSE RENEVV.AL APPLICATION RE\iIE',~! Dem r**/ls. Owin~ls-Crumm: Th", U,S, NI"dear Regui"toIY Cornrni';:;iorl {NRC) is :;eekil:g input for its elwlronment81 review of ,m ap:Jlication from Entergy Nuc:ear Open"liOIl'S (Efltergy} fm the rel<ewal of the operating lic:en';",,,, fQ:'lhe Indian Point Nuclear Ger:en,ling Unit Nos, 2 and ;3 :;Indian Poi:1l:, IOGGled in Buclln:-I3l:, NY, appro)(lmately 24 m:!es north of trle Nev.,' York City t}oUl:c:lmv II:-Ie. Ind:an F'olnl j:; in clo:3e proxtn1ji":l to lands ~hat ~'n9y :bs :)f intBrest t.o ti1e DeJawarB' N<ltjon. As described below,. ,riB NRC",; proces', inclLides i3n opportuility for pu::>li(: am, iIlter-~IDVefflIT!Bnta, p::Ht:cipf"itlon in th8 er;Vin)rHr:~nta: revie.j.J_ V'Je \~.'8nt to en~;ure that VOl: [ire 8\;'1. . 8(8 of o:Jr effolis. and, purst;::tnt to TjUe -jO of the C:c;de c;,f Federfrf Re~}{f;fJtio,'?D (iD CFR) Pf~rt 51 > Secl:on :::. i22:it,:, lI:e NRC ,rwites ;Iie Delawme Nation ;0 provlcle lqJut te: tl18 <,(Op:n::1 pro(;es~; rel"ling to tloe NRCS e'lVwnrnentaI O"e'>,i8\'\o' of the application In 'Jdcii,ion. t,,; 0utiilwd in36 CFR 8QD, io,\C) , the NRC pialls to coord:m:M' CO:',p:lm'e8 with Section '106 oj tl-Ie N"l:o:l<'ll Historic PreservatiDn Act of FH3>:; ti'lroWlh the reqll!nement3 of the NatiollC:: Environmer:tal Poliey' Act of
':96:,r, Under NF::C; r8<,;uICltior:s. the (>fii~inal ')ps'atil1g license for i3 r:udear pm,ver plant i3 i%ued for up to 4(: years, TI"" license may iJe :'e!:ewe:j for-up 10 'In ad(iitiQllal 20 yem'S if NR'=* rW-iuil'emellis i]re :'net The Gun'ent c,peratill'~lliceflses for Indian F'oin! Will expire in S&pteITlbel-, 2013, and Dec8ms*er, 2015. EntelIIY sut"T,itted ils 3pplic,ol:on for I'enewa! (of It:<O; Inc:lian F'o:nt operating I:censes in a leHer (k,ted Ar}ri: 23, 2007, a:;sc)pplemented bV letters date::! l'lhly ~) <'nel
,JlB:e :2 : . 2D07 TI-I9 NRC is gat!leri!lginformation for ai' Ind:aI" F'oint Si:8-specillc s'-lppI9mefl~ to i~:s "Gener:c Erwiromnent:c,llmpad St8tement for LiGen,;e Rene'NEl! of Nudem Plants' (C::;EIS::*,
NUREC-i-1':)37 The 5upp ielT;ent \lvil: contain the results of the revielf.;' of the emiiwllIne!:tai i;-npm:ls or: the area surwunding the ir:ckm Poir:t site 1'I"lmeG 10 telTe",lrial ecobgy, aqualic: ec*:)!ogy, hydrohJ{fY'1 G\.dtLHBl :esourCE:s. an~j s:JG~Crec:Jl:onl;c ,issues (a~;no!1g o!hers}. t:nd V'-Jlll cD!:tail< " reCO'llmenrjfltion reg "Wing t!18 environment.:,: aGCeptabiiity Ol the licen'Se rene,;:,,,,1
!]c:hon.
December 2010 E-25 NUREG-1437, Supplement 38 OAGI0001367E 00344
Appendix E N.Owings-Crlln1H: To f:ccon-,moda~BintBrested membel-s (If ti:e publ:.;;. tl18 NRC wi!II};)ld two publiG scopil:~! meetill',;s 'or the Indi8n Poin license rene'Nal supplement to ,he GElS orr ',Vednesda¥, SepiBl1'i}er Hi, 2007, at Hie Colon:al Terruce. located flt*, 19 Oregol' Rd. ill Cortlwc,jt fv1::<no:-, NY. The first se%ion will (;01We1l8 at : :30 p.Il'. and Will continue unli14:30 p.m , as nece;3c;ary. The ;3econd 5e',:>,ol: ',vi!! convene at 7 OD p.m., Witt] a repeel! cf tile overview p'.:.rt:0f"3 of the meetll"9, amj ',<;:11 continue udll W:OD p.m., as neC'essary Additionally, the NRC staff 'N111110S\ infornlGI di:>cl.iSSIOns one nour t)eiOI-e ,1"18 st3:*, of 8m:I, session. n,e !iGense renewai app!i(:ation (lRil,) is publiCly availBble et ,i'le NRC F'ubliC Document R:)on1 (PDR). IGca!ed at One Wil:;e Flir,\ NOlth .. '1 '1555 RockVille Pike, Rod'lill, r',.iarY:;3nci 2G352. or from t:1e NRC s Agencyw!cje Documents .AG*;e,,,s ilnd Ivlsf1Dgemel1t Sysiem !,AOAJilS I, Tf:8 ADi,\MS Public EI&c!l"OfliG R&mjir:g Room ", aCG'osible at htt[r/:*[:;=:ar;l*~.\'\o'%:').3eaf{:}-:.r:;'C.(K:**I:'**c:'=d~)G~n_i~::tn':i. The accession nUPioer for the LRA is t\'ILOT12'i Cl5G7. Person,:; 'Nh:::. do pot hwe acc.ess to AD.4f,.iS .. or who enu;unte:' problems ::1 aCGe:os;ng tile clocuments :o(:atecl ill AD,Il,J."IS. ",rloulcl contBel tile NRC~: PDR Heference staff i~y tele:Jhone <1t1-l',OO-397-4209 or 30 :-415-473 7 ,or by e-mml at ;;l-,).r!~,!:NL9.Qx. The Ind:an Point LRA. is s:so cwailClble on the Internet di iJ.~U~L~i:""'~Ll'3~'L9;):,';'r:~_;l':';:~:L:~::~:;1(":_0.;i:Adl<:C("3_:_,"JJ.:g;_:_("3_:-,j:~':~:;:~_~ll~::::::'_'-~i_'~::':~:jJ.::);']J.:_:::!::)_:L:;_L~l'!j In add;tiCin, tile Hendrick Huci:;.)fI Free Libmry. located if' ]',;lol1tro:;e, NY, ;he Fie![j Library lowt&ci
- n Pee".skill. NV, clnd thE> V'ihite F'IDins Publ:c librsry IOGatee: in Vvi1it& Plains. NY hd'/e agrE>ed to I:~ake tfte LRA ",'.,.'allable iOI- pUi)iic ':1Spectiol' Tile ;3EIS, whicb dOC:JI11HI;S Irle NRC's 2lssessmem of tile 'scope and i:'lpac:t of ell\'ironment'JI effects th8t v~~ou;d be a~)sodat8d ~N:tr: ~:c9nse rene'J~iaJ at Gny n~Jc:e8r pO\4Jef plant site, eril1 also be found or, ,he NHC"s 'website or st the NRC's PDR Plei3"e :;u')I'nit ':iIT\' comments ;Il"" the D&I"o'Nare Ni3lio!l niay :-Ia ... ", t,) o:'fer 011 the scope of the err'liro:-J£llem;::i review t)'y October 12. 2007. \Vrit!&rt commellts ~:ho'II::1 be subrnitted bv mail to the Chif:f, Rules [,nd Directives Bmnch Dpiision of Adl:'linic;trg\ive Services, r',/bl: Stop T-eD59 US. Nlxl&m- Regulator'y COll1iTli:>:>ion. iN8snin9t0:1. DC 20555-;]001 ElectfGnic CDIT1lller:ts nia)'
tie sulxnitted tl) the NRC I)y 8-mail at JJ.1:,:i:::!!.J>'Ar:j::.:,~:;C!!.:F"~;:"::" A,I II-Ie conc!uslor, of the scopin*;; process. mE> NRC staff wil! prep:::I'E> " sUHlr":"ry of the :si~1niiic<lnt '::;,slies 'den~ifi8d <,nd the cor:clusior:s reoche'j, and [::wl <1 <;opy to YDU. NUREG-1437, Supplement 38 E-26 December 2010 OAGI0001367E 00345
Appendix E The sI,afi expect:, to putllish the drflft sliDplemem to me ;:;EIS in ,.lui:.,. 2008, Tll8 NRC will I:Dld anotrle:' :3el of pw::lic ll1eetings in tl:e site vldr:ity to '::o:icil COITlments or: ,rle (fIT:ft supplementai environn,enli::i ir:;pud slmemenl (SEIS). A ccmv cf the draft SEIS wHII}e sent to you fOf your
!'eVieW unci comment. foJtH conside!'atiofl of pubiic. comments received on II-,e ::tmft, tile NRC Ivi!! prepa:'e '" final SEIS, Tne issuar:ce of <1 final SEIS for Inr;::::m POint is plfmr:ed for Apnl 2!JO~~'I, If you r:sed [,(jdilionai infor-mi3lion r'egard;n~l tile environmental reViS';\, p!'oce::.s, please COlll<lct tA:s:, Jiii C8vsrly" Er:vi:-onmer:lal F'roJect Manager', ;,.,130'1-4'15-6<599 or at S:ncer8Iy, lRA Christian Jacobs for!
Rani L, Fn:.novicl:, Bmnc:'1 Chief Env:ronment8i Bmnch B Divi"ioll of license Rene""",! Offi<:e G! Nuc.IHir Reactor Regula::on 00ckst No'S. 50-247 ar:d 50-286 cc: Se8 nexll)2we December 2010 E-27 NUREG-1437, Supplement 38 I OAGI0001367E 00346
Appendix E August 2"', 2007 The H)!lorable Je:TY D:)LJglas, Chief De:aw<:lre TrilJf3 of Indians De:awme Tribal Headql",,}fte:s
'; 70 North Ea.st 8arba~'fl BarHesvWe, OK 74001:'i
SUBJECT:
REi)UE.3T FOR Cor"lr':lENTS CONCERNING THE INDIAN ~'OINT NUCLEAR GENERATINC-; UNIT NOS 2 ,<\ND 3 LICENSE REr'JE\",1Al APPLlC.A TiO~"j RE\ilEVV Dem Chief Dou!~Ii'r" Hie U S, NI"dear Regu:<:,t!JIY Cornmis:,ion (NRC) 1'3 :oe8kin9 input fOl' it::: environmental review' of 31: applicatio!l ;1'O'n Enlergy Nuclear Operations (EntePJY) for trl8 rer~e'Nal of the opernlin\l "Gense", fo:' ,he Indian Poin; Nuclear Ger:emting Unit Nos, 2 and ~j ilndiiln Point:>, IDGated in 6uellflnm:, NY, approXllTltltely 24 m:le~: non 1'1 of lh8 New YorK Cij'y I)oundarv line. Indian POI:!' is in cio:;e proximity to lands that l'(lay be ;'If interest to the Dslav'i[:!'e T:'ibe of India:1s, As cie:;cribed ::ielow, ille NRC:; ,Jmce",,:; indl.:c!es aI: 0piJortunity for puiJiic <lEl;j int'3I~-90',el!lmellta: part:eipf"ition in trl8 en',;in:Hln-;ent:-d re'~{feW_ Vve \>\,'Bnt to en~;ure that you ~1re ~J~*vare ot our effolis and, purst;ftnt to TiUe -10 of the (;ccle of Federal ll:;:egujatioos ( 10 CFR) Pad 5 J, Sec!!on::::. !22i(tl:, tne NRC: :nvites ;1'18 D8iaw:c:!e Tr!tJe of In'jlar:s 10 proVIGB Ir:ijut ,0 tllB SCGP:rlr.i pro(,8"'", relatil'g to the NRC" environmentsl re.vie::,,' of the apr;licatiofl, Ir, tld(ji;ion, r:s outline,,! if! 3~;, CFR eOO,BiG), tlle NRC plan:3 to comdinllte cOPlpiillllce with Section :[160; Hie Natiolllli Histone Preserv[,t:on Act of '196,3 trIlT)Ui]h Ihe Ho,c:uir8!Tlellt:; of trle N"t:onal Envirc.l1rne'lt,,1 POlicy Ad of -I ::l<3:,1 UncleI' NFK; re',!UICltiof's, the (Jfi'~inzll operatin9 license fo: a r,ucie8r po',ve: plan; i" :ssoed 'or up to 40 years Tlce lice.I'se may t:e re!:ewEKI for up tQ an edditlor.ai 20 YBars if ~JRC l'equireITle!:l:3 are "let The CUfP2nt (,pefatin'~lli<;ens% fe,r Indian Poin, Will expire ill September, 20': 3, [,!lei Decernber, 2015. EntelIIY sutl>T,itted as ;::,:;,pll<.;ot:O£1 for r8ne:,'iEll of ;1:8 IndiClIl POint opemlin9 "Ge!lse" in a I",Her ci<:,led ,t\pri: 23, 2007, as suppiemented by !sHe:s. dated "lay:3 and
,.lUl:e 2 : , 2D07 The NRC is gat!leri!l9informatiDn for ai' Indian Poi:1t Site-speCific 5upole:l1ent cO its °Generic Ellvironment:c,llmpad StCltemBnt for Licen:;e Ren8l.i81 of Nuc:!em Pi,,!);:, . . {GElS},
NURE(i-1437 The sl:ppiement will contai:l the re'wltc: :)f he review of th", environmental inlpm:ts or: the area sllrTOlJnding Ihe Indian Poi!:! :;ite I'8b!ec: to telTe':;triai ecclogy aquatic eo)!ogy. hydrohJ{fY'1 Gidtural :-esources, arvj s:Jcii)ec~:rJ:on,:,:~~ j~.sues U:l~"flong ~)trI8r3), and \'Vt:: cOI:tain " reco'lll1'enr,i<ttion re'Jarding me ",n:;ironmental acc8p!8b!:ity of th8 license r8newCl: action. NUREG-1437, Supplement 38 E-28 December 2010 OAGI0001367E 00347
Appendix E To ~cco'Tlmo(jaieinterestec! members of the publiC, tl:s NRC ,viI' I"-,okl t'II.',) pU!Jlic :,,(:O:}in~1 fIleetin',is 'or the Indian POIr,; license 1'81'18".\'31 supplement to ;ile GElS on \/ifednescl8'y'. Sepiel1'ber '19,2007, <it TllS Colonial TerPJce, 1(lcated at '119 Oreg(ln R<:i in Co!'Vancit fv1zmo,', NY, The first s9:osiol'; will convene at '! :30 P In, Zind Will continue lB,t:! 4<,0 i),n; , as nece:;c;arv, The second ,;e:;:;ior, wi!! convene OJt 7:00 Dm" w,th 13 re;:le3t of (toe ovsrvie:II" p'Jrtlons of the meetmg, and 'iN:11 continue ur:ti'IO:OO p,m" as necBssnry, A(j(;ii:o:',all'y', thO' NRC
',18ff >'IIIII1OSi Infornl~1 :jISGU5SIOns one nOlll'!:;sfore H'le start of eaGf: :;e',siol1, Pie license ren8wa: application (LRA} is ::Jub:icly available <It ;:,e ~~RC Public DOGul',:"mt Room (PDR). iGcated alOne 'NlHe Fli!,t Nor~h,I'155S R':>ckvllie Pike, Rockville, t','lal).'i8l,ej 20352. ,)1' from ti18 NRCs A,genc,!w:[)8 DOc'JIT:8nts J\cces,; snd rv'I"rlll~;emenl System (,11..0,6&",15 i Tile AD.-"lMS Public Elec!iofl!c Rem!i!'g Room is acc:e:;c;:ble at http /:2:;:ia:'-;l~.V:.-\~::).~:e~~f;:)':.r;:'(;.{:(:\l"':jo~:)q~n i-:~r~:i. Tt-lG (1(;ce.3sion nt:~TlbE:r for t~18 LRA ~:3
!dL07'12'W5GT F'el'sons; 'Nha do 1"01 hwe accss:; to ADf\t';lS, or 'who SIK.o!;:1ter proDle:lls:n aCJ~e'3s:n~1 nle c:loGul1'ents locate::! in ,ADA,r...:IS. srIDul::l cOI,!ncl H,e NRC:3 "'DR Reference ,,,taff by telephone nt '1-800-'3f~7 -4209 or 30'~ -4 '15-4 737, or by e-!TI<.:1~! ,3t ~:{tC~i'nG~"gQ>~.
T~le Indian Point LRA is ,,:so dvailable on the Int8met 'J, i!LU~E"i:,\.'vY,J'3:;,D;;:~',';I:~"t'~\:JLS:q.'(":,,~li'j~:il[;;c';::],"JJ.['i!J.';::J";:'Y,0,U,i)jJ~::<~:*].t.:,\iE~'J!,:"Jl~"!:J~:::jJ.,Li!Llli 111 f]ckiitio'l, tile Hendriel, Hudson Free library. located in ~':Ionlrc;se, NY, the Fiel::! L:bmry locmed
- n Peei.',skill,. NY, tind the V'il'iile P'lClillS Publ:c Library iocat8d :n 'v'llhite Plmns. NV' ~laV8 <,greed to make ti,e LRA z,vallable for ;)lIl):IC inspedioll T~le GElS, Wllid, documents me NRC's ass8ssr:lent of tile scope and :mpClGl of el:'.,.'irQnmenl211 effects th8t would be assudated v-jith ::cenSe renevv;:l! at 8n~...' nuclear pO\i\ler ~dant site car: also t:e found on ;ile NRCs viebsite or fllthe NF~C's F'DR Plea"e SlJ!)IYlil any commsnts chat the Deia'Nme Tri!Je oflndiaf':s rnay ha,.'s to of!'er Dn 1!1El scope of the enviwrII':entc,1 revie'.", ty~ Oct<Ji:Jer L:', 2[107, ~\irilten comment:> ,;hO,II::1 be stlbnlitted by mail to the Chief Rules and Directives Branch, Di\lisioll 01 Adn':nistrat:ve Service". rVlail StqJ T-6D5~;. I),S, NuGiedr Re',iulr:lofy' Cornm::,-:,icm, \N8shnp!of!, DC 205::'5-0DOI, El8c!ronic G(:mmenls may tie >.ubmilted to the NRC by 8-mail Dt lL;~,~'!!::?2tllf~;~*;@!::E,,';<;>',., At II:s conciu,ion Of the sGoping proce35, ,rle NRC staff will pl'spme a Sl:mmm-y c:f tile significzmt :s~,ue',; Identified ,:l1d tile cGncius!on:, l'eaehecL ar,;j mail a cop,,' to yOu.
December 2010 E-29 NUREG-1437, Supplement 38 OAGI0001367E 00348
Appendix E F)
-.j-Fie staff expects to publ:sh the draft :o,up;:demem to Ule (3EISin .}l:iy 2008. n',13 NRC v>'i:111(lI(j allotile:' set Df put:lic meetill9s III the site ',':cil"ty to solie:; comments on !I'le dl'aft sl,lpple:qenta:
ell'/il'Onmentai ilY:paci stDten'lent {SE!S) ,4 copy of the (!:8ft SEIS \,Viii be sent to you fo:' your
- 8\1:e'.'.' and comlTl8l'1. AftH conslc!emtion of publ:c CDlY:ments received on the draft, the NRC wiH pre,::me ,,1 final SE!S. The issumlce of a final SEIS foe Irrc:1]11 Foint i~; pianr:ed for Apl::12009. If you peen aGditiona: infonrlallor: r'e9m(jin,r tl'":e enviror:!Tlen!al revie';v process please contad 1110., J:ii Cavert'!, Ellvironmeptal Pl'Oject tdanager', at 30: *4 ',5-6i399 r::r at Sincerely.
iRA Christian Jacobs fori Rani L. Franov:c:il, Bmrlch Cl'rief Envimn::lenta: Bmndl B Di'li:,ion of License. Renev,al Office. of Nuclear Reedo: Regulation Docket No:,; 50-247 and 50*286 I NUREG-1437, Supplement 38 E-30 December 2010 OAGI0001367E 00349
Appendix E AlJgust 2~. 2007 The H"norable C.VV Long,ol:v, Chi"f Echoto Chickornmlq3 Che£oke8 Trit,e 0' New Jer:;ey
.: 164 Stuyvesant .'WBflUB Irvington, f~,J 07 j., ')
SUBJECT REQUEST FOR Cm.'i1"IENTS CmJCERNING THE INDIAN POINT NUCLEAR (;ENERiHING UNIT NOS 2 ,AND" L1CEt..JSE RENEVV.AL APPLICATION RE\iIE',~! Dem Chief LOWJlow: Th", U,S, N,"dear Regul"toIY Cornrni'3:,ion {NRC) is :,eekil:g illput for its elwlronment81 review of ,m ap:Jlicatio!l from Eillergy Nuciear OP"P"liOIl'S (Efltergy} fm the rel,ewai of tile operating l:cel1',8", fQ:'lhe Indian Point Nuclear Ger:en:ting Unit Nos, 2 and ;3 :;Indian Poi:1l:, IOGBled :n BIXiln:'I3l:, NY, appro)(lmately 24 m:les north of trle Ne1o/ York City t}(JuJ:,:lmv 11:'le. Ind:an F'olnl j:; in clo:3e proxtn1ji":l to lands ~hat ~'n9y :bs :)f intBrest t.o ti1e Ecbota C:--liGkarr;8ug8 C!~f8r:)kee Tribe Df Ne"IV Jersey, ,A.s ,:::esL:£ibeej I:>elow. tite NRCs PIOC8"" includes an DPPDrtunity fcr pub::c and tnt8r-governrnBnk:! p3rtfc:ipBt:or: m the en\/:t'ol:!"f1ental rev:e'.i'.:', ':"./8 Wf~nt to ensure t!1.at you are 2rware :)f our efforts ftn(j, pt;:"suant to Tttle 10 of the CGlde of FedBU.l{ F..'egu/atiO(iD nO CFR} Pm1 51, Sect:of: 5 1,28d)), ;:I,e r'JRe :Iw:tes trle E<:Jlc)ta Cr:£ckalll<lU::j<l CI,:erokee Tnt,e 0' N"v" .Jers:ElY to pn:w:de input 10 the scopir.g process relat:ng to tho NRC's environrne.I',[d reView of the iJppiica!iC>I: II, aclditio:L a" GI;tinedin ::'.6 CFR. 800,o(c\ ~he NFlC p!illH to Gomdif:ate cornpliance """I;h Sec!ion Hjt; Df the NEltional Hi,;torIG Pl'8servation A,ct ofHli:;I~, t!"fi)Uqh the recl';il'ement'S of til" N<ltioll<::1 EnvifOl'lment<ll Pol:Gy Act of!'~G!~I. Uncl"f NF::C; r8,,;uIClliof:S. thEl (>f:i~inal i)pe r atil1g lieens" for a r:uoiear pm-vel' plant is i%ued for up 10 4(: years, Tlc 8 license 11'<1)' iJe I'e!:ewe:j fOl' up 10 'In a*(j(Iil':)nal 20 yem'S if NR'=, rWiuirements i3re :'net The Gun'ent c,periltin,i licenses for Indian F'oint Will expire :n Septel"l:>el', 2013, and Oecems*er, 2015. EntelIIY sut"]',itted ils i:lpplic-01:on for I'enewa! (:f II:" 1I:c:lian F'o:nt operating l'c,ens8:>' in a I"tter (k,ted Ar}fi! 23, 2007, a:,silpplemented bV I",ters dated l\lhly ~) <lnd
,JlB:e :2 : . 2D07 Th9 NRC is gat!leri!lginformation for aI' Indii'm F'oint si1e-sp<?cilIC sClppl9mefl~ to i~:s "Gen8!':c Erwiromnent:,,:1 Impact St81ement for LiGen,;e Rene'NElI of Nudem Plants' ([;EIS::"
!'lURE:::.;-!.:)3? The suppienwnt \lvi!i contain th8 re'Sults of the revi",,;, of the emiiwllIneJ:tai i;-npm:ts or: the area surTOunding the il:ckm Poir:! sit8 !'IolmeG 10 telTe..,lrial 8cobgy, aqualic ec*:)!ogy, hydrohJ{fY'1 G\.dtLHBl :esourCE:s. an~j s:JG~Crec:Jl:onl;c ,issues (a~;no!1g o!hers}. t:nd V'-Jlll c0!:tain " reCO'lll1'enrjfltion l'eg"Wlng t!le environment':,i ac.ceptaIJil:ty Dl the licen'Se fene\hal
!3chon.
December 2010 E-31 NUREG-1437, Supplement 38 OAGI0001367E 00350
Appendix E c .vv Lon~]:o\;\.r -L-Te; aCC,)nlITlo::late i!ltere:,Jed tT:em!)ers of the public, the NR.C ,viii fn)ld IINO pU!Jlic :,.coplng m8e1~fjgs fl:lr the Indian Poir':t !icen58 reneVo/ftl :3,upp:lern8nt to the GElS ')1"1 VVednesdfty. Sep1ell1l)el' '19, 2007. at nil" Colonia! Termce, I:)cated atl1 ',r Oreg:)11 Rd. In Cxtiand!
~ibrior, NY. The first ~;e%ion wil! <;oflvene at '13(> pm and wlil continue 1II,tll 4<10 I),il; , as
- lCeSSat'i. The seGo!ld ~,eSSlor: Will CDl'!vene el! 7:0;] Dm .. w,nl a repei"! of tf:e :}vervie'iI" portiol>::: of tfT", m",et1n9, 'Jrld will continue untii1000 pm, ;:'S nec83sa:"i. !'\dditionally, the NRC s!",ff INil1 flost Informal cHS:<;USSICJnS one 110m [Hi:fore It-,e :,tart of eael, session.
Ti,e license reflel',*al aps-licacion (LRA) is pulJlicly avaiialJ!e at ti,e NRC Public DO('JJI:lent Room (PDR 1, IOC;3\86 at One \.Vfrite Flint North. j 1555 Rockville Pike, Rock",:!le, r-Jarylm,d 20852, ,)1' fro£': the NRC's Agencyv4!(le Documents Acee'os a'1,i Mc:rlEl',;e£':ent System ("'.ClAf',.,1S) Tile
,t.,DA~i!S Public Eledronic Reading Room is acc:es,,,ble ot
~tt::: :':ad~-::T:3~~~'ebs0~::"(',h nr{. (J'J*I... ,;dD:(:.J:::~: ;":~:'-;l:i. The 8GCeS310!l rll. .Jrni)8f fo:- i~le LRA (s ML07"210507. Persons who do 110t have access to ADM',*lS. or 'Nho enCOI~:1ter proDi:11S in acces"ing 1!'le o::!ocul:lent:3 locatec! in ADAMS, '0 I'IOU lei cOI:taGl !tIe NRC's PDR Referem:e :"ta'f try tslephon,e 8t J-800<:97-4209 or 30'l-4'15-47?i7, or by e-rn¥.:1::: ilt ~::::~:_~1~~r::.::~~"{t~:>~.
The Indiorl Point LRA is ,,:Iso ;JVailsble on the Imemet "t
')t~:,:i'~'~'i~,,'!,.L::>.',..;:::j'!;~:~('j,':.'2t(:j),;~S:':j)::;:;"fl!'g::I,::;.'j;']:~J)Xj~J.'j;'],;;','uk:']):.::::li<~~!JJ!J,r:~!j3::"Jl:l:Ll:>:::1J"1,i!Ll'i. 111 a::lr:ition. the Hewil'ick HudsDn Free Library', 1::)Gated in 'Vlontmse, NY the Fiel::! L,bfi3ry locmed
- n Peebkil!, NY, and the 'oN'hile Piai!:" Public Lit:rmyloGmed 111 White Plr,jns, N'r' ~Ia';ie (,greed to mak.e tile LRA avajjai)le for pulJIIG mspediQll Tfle GElS, wtlici, (joCU::lents 11'18 NRC's assessment IJf tile 5ccqe [m::i :mp>JGt of el,"lironment211 effe-Gts th:-:-H "'.!"./ou;d be Bss:.8G:ated \*'.~~th ~!cen'~e re!l8v'J81 at any flUG::Bflr ;,10\A-'9:- r.dB:nt SHEL car: also 1)8 found on tile NRC's 'websile Of c,I lhe NHC's F'DR Please sub;'nit anY' cO!mnents that the Ec;nola ChicKmmlugn ChewKee TI'ibe of NBW Jen2V may he,ve to Dffe£' ::;li1 trl8 scope of the 8:1virol1lnedal review b'f Octobel' 12, 2007. VVritt81' romn18ni-o; SflOlild be c"lbrnitteci by mail !o tbe C!lief Rules and Difecti"les Branch, Di,':s;ion of Adillini3tmlive Servic;e:,. 1,,1>:lil St,)P T-CD5rl, US Nudem HegLJli3t:J!~{ Ccm'1l1ission.
'/Vssil:ngton, DC 2(1':,55-0(1:)'1 Eiectronlc GOlmner:t:s may ;:;'13 submitted to me NRC bye-mail al At tI:s cOI',Giu<;ion of the sGoping process, \rle NRC: slaf:' ""ill pl'epme si~lllifiGant ,:,,,,uee; Identified and Ine cQl:clus!on::; reac:neG. Hf:[j mail" cop,,' to NUREG-1437, Supplement 38 E-32 December 2010 OAGI0001367E 00351
Appendix E Trle s;h:,ff expects to pul)i;si: tile cil-aft supp!e::'lenl to tile CiEIS in ,JUly 2008. Tr:e NRC w::lllol::1 anoH-ler :3el 0: public nleetingsin the site vicin:!\, to solicit comments Oil !ile draft :3upplernentai environmental impact sl::]tement {SEIS). A copy Df tI:e (i:-a:t SEIS "'!iii be sent to you for your re,'iBw ar:d comment After consi(j8PJtion of public CQI:;'1lents received :):-1 the draft, the NRC INiH prepme ;:> final SEIS. TI"" issuanc8 0' <OJ final SEIS for Indian Point j~; plalliled Inr Apr:! 20(1'1 If ),0,1 need ack!itionai inf:)I"maiion I"8gsr::ling the 8!WlrOf'!T18!l!al reV:8 ,V proces,~,
'
please contact ::vls, Jill C'3',;erly. Environmental F'rojec; [Vlanagel', at 3(>, -4i 5-\36P~1 or at 1'*,,::::-c1),'::,::'(uv. Sincereiy. lRA Christian Jacobs for.' Ral'; L. Ffanov:ch. Smncll Cflief EnVironment",: Branch B Di\,'ision of License RenelNal Office of Nuclear Reactor Regul;J!ion Doeket No";' 50-247 and 'SG-28G cc See Ilext par,l8 December 2010 E-33 NUREG-1437, Supplement 38 I OAGI0001367E 00352
Appendix E A.l.Igusl 24.2007 The H:J!lOf6ble !**,1ichw3: Thomas. Chairman MsslltJrltl:Gket ~'eqllot Tribe
': 10 PeqmJt TI'aii p.o. Box 318D
!'/k:shantGcket, CT 06~<39
SUBJECT:
REQUEST FOR cm*!r,*lENTS CONCERNING THE INDt~N POINT NUCLEAR CoENERfHING UNIT NOS 2 AND J LICENSE RENE*WAL. APPL!C!'-XION REVIEW The U S Nuclear Re9uiatolY Cornrni'ssion {NRC) is seekil:g input for its e!:'iiwnlnE'ntal reviE'w c" al: appllGatio!l from Ellt!?rgy N,IG!ear Open:l!iOI1'S (Enter9'1) for the rs!:e'Nal of lIle c:perat:ng i:cense" for lhe In::km Point Nc!cieBr Ger:E'rat:n9 Uilit Nos. 2 Bnc:! :3 ::indial1 Point.:, io;:.atedin Bucl1<:lnal:, NY, approxinmteiy 24 m:18s north of the Nell York City bO:Jl1da:y lin!? Ind:all Poill; i:; in dD:;!? pi'oKimity tD lands t~iaj ,.nay be of inte!'est to the r*. .ia"llan!uciwl Peqcio! Tribe. As
'::!e";criL1ed !:;*elow, !he NRC':,; proc8ssincli"des ai' QIl~;Qrtunity 'or public. Oriel intel'-guve:nrnerltill part:cipatlon in :~Ie ,&nvironrr:ente! re~~*'iev,;(. V',J& v..:ant to ensure th8t *;l0U ar,8 8:V\*'::'"lre of Clur e:'fm!s c:mc!, pursl.:an! te, Title i 0 *Jf the Code or Fe,!erai Re9u!alions {'I;) CFR:, Pm! ;:,1, Section :',:28{b;, the NRC illvites the r**;,lashantuckel PeqG')t Tribe to pmvide input t*J the 5cQpin*c! proC8::;3 relating to the NF:C'::; environn'ent<tl review of the <Ipplicatioll. III 'l(!cliliOIl. as out::ned ill 36 CFR ,30Cr:O.ici. the NRC plans to L:O<xdil:ate compliance with SectiDI: '106 Df the Natiol10: HistQr:c F'reservation Act of I!~"313 tl:n:>l;gh t!-IE' requir81:;ents of the NiJ;ionai Elwiroilinental Policy Act of '!fi6{1 Under NRC rer;lulations. tbe original olJe:'atin9 licellse 1m a nuclear power plant is Iss,ued ior up to 40 yeilr:,. The licel:se may tie !'er:e,,-'e:) for up ;0 <In additiolli31 20 vea,", if NRC 1'8':<,lir8:11enis dre :TIet Th8 GUfI'el1t opmt:ng licenses for Ind:an Poin; lNili expire :1'> Sept&mber 2013, "nd Decem!:!!?L 20'15. Entel-gy subnlitt!?d ,;::; application for rene'wil: of thE: Indian POint operating i:(:8!V,eS ill a letter dBteci .A.prj! 22., 2007. ih :;uppiemenleej b::i le;ter:, clateCl j';lay 3 and
.JUl:E: 2'i, 2007 Th", NRC is qatheringinformation for ill: Ind:C!n Point si,e-:;pec:fic sUllplernent to :to "Generic Elwll'oIlIT:entallmpact Statement for license Renewal oi Nuclear Plants"' (C~EISl NURE(~* 1437. The "cipp:ement wil! *,;ontain the results of the review of the envirDIlH:ental Impacts Of' ihe clr8;J SllITOI.:ncJiI1Q tile 1!:cliZtI1 Point site I'elated lO telT8stria ecol()g,/, ;XllkltiG GOtogy, hydro~o~ry') (".:..dtuf::.ll resources. and sodoeconorn:c :issus .(atTIOn~l o~hers}, i:nd y./i::
cOf:,oin [l rec<):'nn:en;jatiDn fe9Bn:lin';l the elwir::l!1ITlenta! c](;Geptat,!iity o~ tbe lic:en:"e renewal nctiol1. NUREG-1437, Supplement 38 E-34 December 2010 OAGI0001367E 00353
Appendix E ld. Thomas To ~cco'Tlmo(jaieinterestec! members of the publiC, tl:8 NRC ,viI' r-,okl t'II.',) pU!Jlic :'.(:O:}in~1 fIleetin*'is 'or the Indian POIr,; licen5-e r8n8'*.\'3I supplement to ;ile GElS on \/ifednescl8'y'. Sepiel1'ber '19,2007, <it TI18 Colonial TerPJce. 1(lcated at '119 Oreg(ln R<:i in Co!"Vancit fv1::mo,", NY. The first s9:osiOl"; will convene at ., :30 p m. Zind Will continue lB,t:! 4<,0 1).1"1; , as nece:;c;arv. The seGond ,;e:;:;ior, wi!! convene OJt 7:00 Dm., w,th 13 re;:le3t of (t:e oV8rvie:II" p'Jrtlons of the meetmg. and 'iN:11 continue ur:ti'IO:OO p.In., 81S necBssnr'y'. A(j(;iilo:",all'y', thO' NRC
',18ff >'IIIII1O",i Infornl~1 :jISGU5SIOns one nOlll"!:;8fore a"le start of eaGf: :;e*,siol1.
Pie license ren8wa, application (LRA} is ::HJb:icly available <It ;"e ~~RC Public DOGI.II,:"mt Room (PDR). iGcated alOne 'NlHe Fli!,t Nor~h.I*155S R*:>ckvllie Pike, Rockville, t','lary'i8l,d 20352, ,)1' from ti18 NRCs A.genc,!wl[)e DOc'JIT:8nts !\,cces:; snd rv'I"rlll~;emenl System (,11..0,6&. . 15 i Tile AD.t.,MS Public Elec!iofl!c Rem!i!'g Room is acc:e%:ble at http /:2:;:ia:'-;l~.V:... ~:::;.~:e~~f;:)':.r;:'(;.{:(:\l"':jo~:)q~n i-:H~:i. ThE aG{;8s~:=:.ion rv..J(qber fo;" ihe LRA is ldL07*12*W5G7. Pel"sons; 'Nh:] do 1"'01 hwe aeGSs:; to ADf\t*,jS. or 'who 8IK-OI;:1te)" proDle:lls;n aCJ~e:3s:n~1 nle c:loGul1'ents locate::! in .ADM*.:IS. srIDul::l cOI,!ncl H,e NRC:3 "'DR Reference :,taff by telephone nt '1-800-'3f~7 -4209 or 30'~ -4 '15-4 737, or by e-!TI<.:1~! ,3t ~:{tC~i'nG~"gQ>~. T~le Indian Point LRA is ,,:so dvailable on the Int8met 'J, i!LU~E"i:,\.'vY"J'3:;"D;;:~*,*;I:~",t'~\:JJSq.'("'",~li'j~:il['-"';::]""JJ.['i!J.';::J";:'Y"0.U"i)jJ~::<~:'].t.:"\iE~'J3":",Jl~"!"'J~:::jJ.,Li!Llli In f]ckiitio'l, tile Hendriel, Hudson F,-ee library, located in ~':Ionlrc;se. NY, the Fiel::! L:bmry locmed
- n Peei.',skill, NY. tind the V'il"ii!e P'lClillS Publ:c Library iocat8d In 'v'llhite Plmns, NV' ~Iave <,greed to make ti,e LRA m.'allable for ;)lIl):IC inspedioll T~le GElS, Wllid, documents me NRC's ass8ssr:lent of tile scope and :iTlPClG! of el:*...*irQnmen!211 effects th8t would be assudated v-jith ::cenSe renevv;:l! at 8n~...' nuclear pO\i\ler ~dant site car: also t:e found on ;ile NRCs viebsite or fllthe NF~C's F'DR Plea:,e slhmil any COITII118nts ;llm the j:.*l':is!1a!:tuGkel Pequo! TriDe lTlay have to off:?l* 011 the scope of the enviwrII':entc,1 revie ty~ Oct<Ji:Jer '12, 2[107. ~\iritten comment:; ,;ilO,II::1 be stlbnlitted by mail to the Chief Rules and Directives Branch, Di\lisioll 01 Adn"nistrat:ve Service:" rVlail StqJ T-6D5~;, 1).5. Nude,,[ Re',iul<Jlofy' Co,.,.,m;::;-:,icm, \Nnshinpiofl. DC 205::'5-0DOI. Elec!ronic Gcmmenls may t'e >-ubmilted to the NRC by 8-mail Dt lL;~'~"!!::?2tllf~;~*;@!:.:E,,';<;>',.. At 11:8 conciu,ion Of the sGoping proce35, ,rle NRC staff will pl'8pme a Sl:mmm-y c:f tile significzmt ::,~,ue',; Identified ,:l1d tile cGncius!on:; l"eaeheC!. ar,;j mail a cop,,' to yOu.
December 2010 E-35 NUREG-1437, Supplement 38 OAGI0001367E 00354
Appendix E Pv!_ Thomas T~le smfi expects ;0 pubii:>I, the clraf1 supple,:,.,;nt tl) !l,e (;EIS ill .July- 2008. Tile NRC will I:old al"lotl"le:" 5et <)~ I)ublic meetings in the ,;ite vlcini:ty to ~;()iic:t comments 0l: the draft sup;:delTi8ntal el"lvironl"!:8ntid iro:pod :;I,Hement (SEtS)_ A CDPY of Ir:8 Gmft SEIS wiil t)e "ent to you for YDur
!-eVi8W om! comrnellt p,ftel- consic!ermioll of public cOIl':l18nls I-eceived Oil tile drat, tlw r~RC will prepare <l final SEIS_ The bSUilllC8 0; a final SEIS for InGiall Point is ptarmecl for April 2!JO!J. If 'IoU I:ee(; a(jditionai informailon regardinq the 8Iwironrnenj,-,1 ,,,,,'iew process.
pletlS8 contact !:.*ls_ Jlii Caverly. EI:viromnental Project 1,. . lanager. at 30'1-4 -l5-6i:"~i~! or at
- ,t
- '~ .:~~~; nrr=. {~(r~' .
S:r;cefely_ iRA Christian Jacobs fori Rani L Fr,-wQvlch. Bn:mcll CIl:ef Environmentai Branch E'i Division of Lic8nse Renew;:>! Office of NLJdear F:e:c:dar Regulation Docl~et Nos. 50-247 8nc! 50-28.6 cc: See next p'Jge I NUREG-1437, Supplement 38 E-36 December 2010 OAGI0001367E 00355
Appendix E A,l.Igusl 24,2007 Ms, Je<lnJ'e Schbotte MOi1egol'l Tl'ibe
- f. Crow Hi!i Road Unca',;viHe, CT 01',]2.2
SUBJECT:
REQUEST FOR Cm'!r,'lENTS CONCERNING THE INDt~N POINT NUCLEAR CoENERfHING UN!T NOS 2 AND J LICENSE RENE'WAL. AF'PL!C}\TION REVIEW De<tr r"..ls, Schbutle: The U S Nuclear Re9u!atolY Cornrni'ssion {NRC) is seekil:g input for its el:'iiwl1tnE'ntal reviE'w c." al: appllGatio!l from Elltergy N,IGiear Open:l!iOI1'S (Enter9'1) for the rSI'e'Nal of lile c:perat:ng i:cellse', lor lhe In::km Point Nc!dear Ger,E'rat:119 Uilit Nos, 2 811c:! :3 ::indiar] Point.:, iO;:,3tedin Bucl1<:lnal:, NY, approxinmtety 24 m:les north of trre Nell York City bo,Jl1da:y line. Ind:all Pain; i:; in dD:;e pi'oKimity tD lands t~ia1 rnay be of inle!'est to the r'",iof:e9a!1 Tribe, As de5cribed Delo),;,;, t:'18 NRC;'" process il:Glude" an opportunity for pubiic ail(~ inter-90vermr:ent;:'t p;::n:cipat!oJ1 in !l:e en~,,*ir0~~fn'8nt;:.:: reVt8~v. ~'V8 '>ND,nt to ,en';lJre th8:t you are BW8:re of our effol1's flnd. pursu('H::t ~'] Title F) c,:' the Gocle of Federal RegulfltilfiJS (: 0 CFR) Pilli 5 j, Section 51,281b), the r'JRCiIT'fite5 the !\/!ohe~wn Tribe to pl",)l,Iide :nput to the scoplng proce:;s '"&1:3;:119 to the NRC's env:l'Cll:menta! reView of the ilppilcatiol: in addllion, as ol;tiined in 36 CFR, 800,8(;\ the NF:C pim::> to
;;omdir,ate cornpl:anc8 :.,,':;1: Seclion Hjt; Df the N8liona: Hi:;tor:c PmSel'\fmiorr ,An nf 1<:);36 t:w),lqh the requirement'S uf the Nation",1 Environmental Pol:cy Act of 1:)13!~1 Under NF:C re',iulatior,5, the of!'~inal ()pe:ating licer1'3e i<J:' a nucl8ar pO'I'.'er plant is Is,.ued lor liP to 40 years The nCBnse rntry be r8t~8'.:VHd for up ![1 ,:lrl add:t:or::al 20 yerl:s if NRC r8qu~re:rl'8fl~s i3re :llet The Gurn211t (,periltng li*;;enses fDr Indian Point will expire in Septe!T;ber, 2013, and Decell1~;.er, 20 I=', Entel'fJY submitted :;S iJpplicllt:<)fI for renewa: of the In,jian POint opel'ating k.ense:o, ill a lelter dated !;,pri: 23, 2007,0.:0' :,clppie!l'ented bv letters dnled M"y~:l fmd
.June :2 : . 2007 TtEl NRC is gat!1erillginforll1<ttion for ai' Indian Point s::8-:,!)ecific supplement to il:o. "GellHic Elwil'Ollrnentai Impact Statement for LiGense Renewai of Nuciear- Plants' !'(iEIS:>,
NURE(~- 1437 Th8 su!)p:ement \lvili contain the re'Sults of the review of the environmental irnpm:ts Of! the are13 SllrTC'I.:ncjing tile il'ciir,n Poil:t site ['elated ;0 telTestria: ecohJgy, aquatic: ecologv, hydroi;yJ'{, cultuml reS(J,lrces, onc sociOeCClIlOniicissues iamon'J 0;'-,8[$). [:nd wiii GOI:tain " reCO:llIT:end<tti(Jn re9ar<1lng U,e envirunl'ltm\-li ilGceptab:ilty of the licen,e renewflt i3CtiCm. December 2010 E-37 NUREG-1437, Supplement 38 OAGI0001367E 00356
Appendix E
,J, Schbotte To ilccormnoda!e interested I11el';!:;,8rs of the publ:c, the NRC w::1 hoid hvo public Sc.ol)ir.g
- ll8eiings for IDe l!ldi<lll F'oint :icens8 rerr""','!",, :3!;pplement to !I-,e (3EIS on W8(;1l8S;clav, Septembe,-19, 2007, m The CDioni81 Terrace, locat".::! 8tl'!;~i Ore~lon Ret in Cortlm:dt r\.'lanor, NY Tle8 firsi session I/I"I!, C0!1V8ne at '130 y,n: and \,,.:11 continue unlil 4 31) run, as nces:;ary. The ~~eGond sess:on ",!"tin con'.:ene [It 7:00 p.tn.: '~,v~th 8 re.peat of the ove-rviey.;
Dortic:ns Df the meetill~l, ane: will continue iJnU '10:(>0 ,un __ as IV3GeSsalY Adc:lItiOlwlly, the NRC steff \~..'ill host :nfGrrfl8: disC'l;ssions one hour be"fore ~h6 S~[:f~ of each s6:3sion. The licem'6 mne'Nai applic::!ti');'J (LRA) Is publ:cly avai:alJ,e at the NRC Pubic Document R:J')ITI iF'DR),iocale(j at One \;V'lite Flinl NOlili, ',155~, Rock\,',II"" Pike" Rockville, r',;laf',.,lflIX! 20:352. or from tl18 NRCs A~lenGy,vicie Ooculn(o'nts .Acces;s <<nd Mi3llf',]6ment SY5!em (,,,OAk1S), The ADA,~ilS F\IIJi:c Eledw:1le ReaejlllQ Room ,5 acc(o's511::le at Lltt~_~_::~~~::Hj_~lrE~.L~i-,_~t:!*~L:..?~rflL.r.:E~~~:j~X!':~~:1~_~L~.:~'~:!!!-j_-_ht[]_~t T be a(;ees siD n nu ~TI b r for H"18 LRA fS r'ilLO7', 210507 Persons \1\;'110 do not 1,3\,'e a,:cess to ,'\OA.r-.;lS. or wrlo enCOUflCef proNems in aecessing the .;:ioc:un,(o'nt$ tDeated in ,il,DAr-,'lS, :3hould CD!:tac;t the NRCs PDR Reierellc(o' ';t<l:'f by telephon'8 at 1-800-:3';0 -4200;! or 30 j -4 f ;:.-4 7 ~t7 ~ or by e-l"nan ot t'_;_~G~}?L!LT_._~~'~:L:{.
- 1~tC::: . \",' . . .':,',~\\. :-1 r{: Q;_~\... t"'~.?;~::'; ~,:(~.:~;:;,:(::::: S*f ;~:tif:q i: :(;:;'n;:~-:G/;"t;'n;':~\'\\'a~:~:x: ()l):,..:::.~\k:n:~:/: :~:{:: sn- c:,",:::~*:t. :1tr;::. In adc:itioll, \I:e Henc:rick Hudson Free Libr<tl\', i:Jcateu il: f,:lontrose, NY, Hie Fieid Library iOGated in Pe8~,:;kiH, NY cl!:ci the ",Vhite Piains Public Libmry IGca;ed in 'A'hite Pains, NY. have W)l'eed to make the LRA 3'.1{,ilable for publ:c ins.pect:O!;
The GElS, which documents the NFK;'s asse%rnent of the scope and impact of ellvironmental effects Hl~lt 'Nould be as-s:]c:ated ,;vith Hcense renevvsl at any nuclear PQ~Vei plant si1e. can also be found 01: the NRCs ';,eb',ite or i3t !"Ie NRC's F'DR Please sutl.-,It any c-o"nn'ent'S trial tile Mol'leQlH: Tribe may 'mve to off",,:' on the scope of tile 8f1v:ronrr:'3ntal re-\"':B\4J by ()GbJ!JBr ': 2. 2007. VVr!tten GQrnrner':!s shnukJ be- SUbtT:1tted by rna:! to the Cilief, Rules mxl 0:,'e(:;1,8:O BmnGl'1. Division of Admill::otr;Jtive Selvices, [\lDil Slop T -(:iO:':{' US Nl:clear R8~1[;lalori Con",',ission VVashinglon, DC 20555-DOOi Electronic GOITIIl1el:ls n:'lY be submitted to the NRC by e-IYIi'lil <,t i"'.I',nP:::'f,',I:,;/i:T::,;,c~i, At tne C-GllciusIOl: (d tr,e scopil:g process, t!'ie NRC staff wHI prepme u summmy of !lle slhl!lificallt ::;sue:, Icleniified and thE!' cDnduston:s reacl'l8d;. and rr:ail a copy to you. NUREG-1437, Supplement 38 E-38 December 2010 OAGI0001367E 00357
Appendix E cL Schbmte T~"Ie sInff expects to put'!isl: the dElft supplelTIent to i~le (;Elf:; in ell::);' 2008. The NRC w!il hold anotrl8r :381 of pu!::lic: meeting:, i!l tile site vidllily to sotiC!t C:O!Tlmenb or: 11-,8 draft sllpplernema! environment,,:: impuct slaten:ent (SEIS:, ,A, CODY of the cifaft SEIS '8W t:<e sent to you for your
!ev!ew unci cOll1ment ,I\.Itel' CDns!deration of public ccmmen!s re<;e!'led on tr1e ::iraft, the NRC
\'I-'i:i prepa:'e ::: fina' SEIS, Tt'le issuance of <I final SEIS for Iw::ian POi!lti~, p\<lnl:ed for
,1\pnI2009, If you l!e8d a*jditionel infow18lioll re9(mHnp the enviror:men!al revie"N process, ple0se contact ~,'1s:, Jill CElv&rly, Environmental Pr-oject M8nil<]ET at 30', -4', ':>-61399 or at iRA Christian Jacobs for/
Rml: L, Fl"ilnovlc'-I. Branerl Chief Enviromnentc:, Brallch B DivisiDn of License Renewal Off:c:e of Nuclem Reactor Regulatio!l Docket Nos. 5~")-247 m:d Sfj-286 cc: See next page December 2010 E-39 NUREG-1437, Supplement 38 I OAGI0001367E 00358
Appendix E AlJgust 2~. 2007 Ivlr. Ray Halbntte:', Nati0f1 Represenh:ltive Clneidfl Ineiii'm NatiO!' (i: New YOlk.
~;er=e~;se-8 Street;, AGle:; Plaza C!nei::le, NY 13421
SUBJECT:
REOUEST FOR COMHE~JTS CON!~ERNING THE INDLAN P()INT NUCLEAR C3ENERiHING UNIT NOS, 2 AND::; LICENSE RE~~E\;"iAL APPUCATION REVIEW Deal' r'"lr Hal britler: Fie US, NlJdem Re"ulatolj Commission {NRC} IS; seekil'g input for it'> epvironmental review of 81' [lpplicaci;)1"l 'rom Entergy Nuc:em Operatio£l'3 (Emer~lY) for ;he rellVifal of the operating iicense::; fo:' ,he Indian Point Nuclear Genef<"ting Un:! Nos, ::: and :5 (Indiml Poin!}, locateci in Bucha"a!', N'{, appwxincateiy 24 mile3 north of the ~~e,v Y0ri<. Cit'liJolB,dary line. Indian F'oi:1!
- s II: dose I)I"OXIlll:!Y 10 l;m(i:3 IIK,I ';-,ay be ;Jf Imemst to the Clnelc!a 11,(llan Nmlon ;Jf New York.
As *:!esuibed below. the NRC';; proces:,. ind!;deS ,om opportl;l1Ity for ,xlblic and mter-90vernrnenlal p2!ltic:ip3tiOri ill the elwircmrnEntal reviEI-~, ~"ie '<'"ant to enswe Inat you are
;J~*'"*,,re 0' uta' effurts anti, pursuant to Tille 'lD of the C.)(ie ,A Fed.,([)) RBQul'lticms ('10 CFR)
Pm1 5'1 *. S8cti0!l ,:, : 28{b;, the NRC invite:o, the Oneida Indian Nation of N8W York to l)r(Nide input to U"IE' ~'coDlng pro';e,,"s rel8tmg to tile NRC's environmental review 0: tr:8 applrcatloll In acbli()'l, as ol;iiil1ed in :3f CFR. 8008(e>, the NRC plew*s to coordinate compiim:ce ':v'ith Section 106 of ,he Natiollal r.is~orie P:eservatioll Act of I Gti6 :~IIO'-J'Jll tile le,:;uire:mm~s of til8 ~l3tion[!1 Erwiwnmentai Poiicy ,"'.ct of : !~i3g Under NRC requl8110r:s, tI:E original ,)p8!"atlll'~ llcense fo:' a I:ucleal' po'",e:' plBfltis i',sue.;:! for up to 40 yearc;. The lieEw:se may be renewed fOl' up to em Bddi!iOIXII 20 year's if NRC I'eciuiremenh me met. TI18 current c:peralinp licenses f0r Incli<111 Poin1 'will expir-e in September, 2013, and December, 2015. EntelIry submitted i~s ,3pplicalion for renew[,: 0; the Indi[,!l Point opep:lting iic8nses in sletler [jelted AI)fi i 23, 2007, a:; c.,lpplementeti e,y letters :jam," M;JY 2- nm!
.Jtlne 2'" 20Cl7 T",8 NRC i', galher:n[JinforlTlation for ,.r. India I', F'aim s:le-s;=.eeific supple:nem ta i,s "Generic Environmentallmpad. Stillen:ent for License Rene'N<:l: of Nuclem Plants" {GElS),
NUREG-'1437 The ~;I;ppielTlent wi!! contzilll the results Df the reV-iff\'.,' of thO) environmedal impacts 01: lhe mea surPJunding the il:dl[:n PoiJ:t ",ite relnte;j to tHrsstnai ecology. aquatic ec~)~og'~'l- hydrOlogy, L~JltUL31 reSO~lrGeS_ and ::;.:)dDeCtH"!ornic is:;uE:<:3 (fl(i{Ci!l(J others}, B:nd v~fiH cDI:tain a recornmendatiofl regaf~jing 1he en~l!rOfWnen~ft: fiGceptab:::iy of the lic&r1':.e rene'vvt:! action, NUREG-1437, Supplement 38 E-40 December 2010 OAGI0001367E 00359
Appendix E R. Hllibritler To 8cco:nmodi3leinterested members of Ihe put)iic. tr:e NRC ,>,viii hoi<j 11'-.'0 pUDlic scopil:g meet!Il~~;S ;;)1' the Indian POIr*: licen",,,, r8newal supplement to the GElS on \/-!I;Klmr,.c!3y. Sep!en:ber 19, 2007. at nie COlonial Termce, I:Jeated atl W Oreg:)11 Rd. in C:)ftlar:dt r,1an*x. NY_ The firs! sessioll will conV">!'1e at -1 :3[> p.m. and 'Ni:l contirllH until 4::30 p.I'n .. as nt:!i.::e'S's,*a~rI. TI::G secDnd .3e'Ssiof~ \tv;;; corr'*ierH3 at 7:0:] p.111. 'w:!h;'J rep'Ztt o~ the OV8fVifHN portio!:S Df the meetin*;;, and ,viii continue udil '1000 p_m., 83 neceSS<l!y Ad,.jitionillly, II"" NRC
;::taff 'Nill host !f1forn-,ai :jisGussions one 110ur tiefore the star! of eacle 58s~oion.
The license rene'Nal apDlication (LRA,i IS Dut!!ICly llvailat)ie at the NF:C Puti:IC Document Room (PDR). located at One 'I/-,i!l:;e Flil:t NOlth,155f. Rocb'iile Pik8, Rockv:118, Mm-v1ar:d 2G8~,:r or from the NRCs Agencywic1e Docull,enls .A(ocess i3:t(j M8m'~lel":ent Sy~,t81": (P,DAf,'ISj Tile ADAHS PubliC El8ctmn:G Rei3dil:~l RODn' is accessible ,-,t Li_tt:!;::~",:jj}Ll5J:"~5]_;;,::,,:;_i}1,::L1~,-L_-;;,:j'lL~d,:jjJlrdi_,t'~lL Tt18 m:ce ':;siC:;!l nu ill bel' fDr me L.I::;~A IS {i. .'l10712': 0507. Person'S \o\'ho do I~ot have in:.:ce3~S to A.DAf"'::S, or v/ho encounter problerns ;n accessing the documents lo<:ale(! in ADA.P,,*lS, siloui(j GOI:IBcl Ine NRC's FOR F:eference st3~f t:V tetEJ)honea~ *1-f:OO-397-4209 Of 30-1-4-15-47:37; orby -nlf~:: 8t ~~::_L~§~E~~~:!",~":"*~~'~.~. The Indian Point LRA i:, abo a'l3ilst,je on the Interne! "1; LttQ_:L~~'5_*(l{~**LnH~-_'~~;x~~,~r~;JJ~t~=~:L~~.~~=~lh~fJJtLn~~~tt~~;~~(J~:jLh;{L;~~(J~_~_~~~~;lL~~:~rl~i~~~*~:~ljt~~_~~::~~*~[_~!Jt~~[t-J~QHJt~~J1H~i. Ifi add:,i():1. the Hendr:e-k Hud30n F!"ee Ubrary loc,-"ed III :\lontrose, t'4Y, the Fie:d librmy, 1:)Gated III Pee!\sklll, NY, mod lI:e '-/\l1111e Plalll:3 Put)liC LB::r<llyioci3te,j in \lV!::!e PI81!1:3, NY, nave i3greec! to I':ake the LRA aV8il'Jble for public :nspediol1 The GElS, which dOCL.IITI8nts the NRC's 'J%eSSme'lt of the scope 811d impact of environnwflt'JI
",;feet'S trla.t wouid tiellsSoCl8ted with :!cense renewal ;Jt any nuclea:- pm:;e!" I=dent site. c<,n also be found a,: the NRC's website or al the NRC's PDR Please :w!:!nlil any conmlel-,Ic: that the On8i:1" h:dis:1 Nation of NelN York may 11<,ve to offer GIl tne scope Df me environr.:ent8! revieW:N (Jdo!:\er 12, 20D7. VVritten COIl::-flents s'lou:d :)13 s:lJbmitted by ff'ail to the Chief, Ruies dnd Directives Bfmlerl, Div:sion of Administmti,'e Services. fl'lail SlOp T-tiD~,P_ US Nuclear Regulstol'i ConlllHSSIGn_ Wa':;[:I1-,,:;ton, DC 20E,'55-0001. Eleclmnic COIl::TI8I'i1S may \::e submitted 10 the NRC bY' e-mail at 1:i(_i_i~lr:::'(!I:t.t:_i::;;,(k:~:r';_.:~(;,_:;. At tr.e cOllciusiGIl of (I-,e scopi'1~! process l:v" NRC st;:,ff w::1 prepare
<l <;u:T,m(1l-,' of the ,;igriificant issues idem:ifiecl i3nd th8 cOf:Giusions reaehe;j. mod I::ail f: <;opy to you.
December 2010 E-41 NUREG-1437, Supplement 38 OAGI0001367E 00360
Appendix E R Halbrit!er Hie st<lff expects 10 pubiisl: lile dl-",f! :wppie;-nent to tile (3EIS in ,JulY 20[1.'3. Tr:e NRC wiil hol::1 anoiher set of public meetings in the site \,'icin:ty to 'Solici; comments on H-Ie dmft supplement;:li environmental impact st",lement {SEIS). A copy Df lI:s (i:-aft SEIS "'!iii be sent to you for your r8'.Jiew aJ:d cornene!'! After con:,;icier;Jtion of public COlY;ments received on ;rle draft, the NRC INiH prepme ;:> final SEIS. TI"" issuance 0' a final SEIS for Indian Point j~; plal1lled Inr Apr:1 ::!009. If you neec: ackHtion:c:; infomK:lIon l'egar::lin~1 tr:8 en',:iror:!Tlental :"8',/:e'lv jJroc8:,:" please conine1 :Ivls, Jill C'J',:erly. Environmental Projee; rVlanagel', at 30! -4: 5-\3e.P~l or at Sincerely, IRA Christian Jacobs for.! Rani L. Fran0Vic!1, Branch Cnief En,;ironlY;entr:1 BPJnch B Division of LicETlse Rene'Nal 0'f:c8 of Nuclear Reactor Regulation DOGket No~,. 50-247 om! '50-~86 GC See next page I NUREG-1437, Supplement 38 E-42 December 2010 OAGI0001367E 00361
Appendix E
.A.ugust 24, 2007
(:;)Uflc!l of Chi8fs ()rK~;ltiagi) Nat10n 25~! C Route 1'8 Onontiag8 Natiol: Nedrow, NY 13', 20 SUBJECT REQUEST FOR ,:;mArvIENTS CONCERNING THE INDIAN POINT NUCLE.AR GENERATING UNIT NOS, 2 AND 3 LICENSE RENEV'iAL APPLlCI\T!ON RE\/lE\/V Ttw U,S, NU(:lear Rei;lulalory Co;:mliosion :NRC) :s seeking :np!;t f,x ::s 8nllil-onmentai rev:e,v 0' f,n appiicat:ofl from Eme'QY Nuclear Operations (Entergy) fO!' lil8 1'8 1'1 e'.'.:3 I of ti,e opel'ilting
- icen:9,'s for the Indian Point Nudem (-ienerating Unit Nos, 2 and] (Indian Point), locnted :n BUGkHBn, NY. apPl'Clximately 24 m;le:3 no It!": of the Ne\'v York City bDumjary line. InCli,jn Point
;s in cllose prox:m;;y to lands tflElt may tle of Int8!est to tne f)ncilldagi3 Nation, A:3 ciescricled
- )e,ow, til' NRC's pmGe',', includes an opportl;nily for pulJlic and i:lter-q:)'i8rr:n:enckl' pm~icir,at:on:n !lle envlronmenl81 review. We want to ensure Ih:::;: you are mvare ,)~ ou:'
6~~arts and" purSUtlnt to TfHe "10 of the Code c~f Feder}]l eeguhjlfCnS CiO CFR) Part 5"1; Section 512i3{b), lile NRC inVites 1",03 Ol'londag8 Nation io provide input to the scopin<;l pf:)cess relating ,0 the NRC's 8lwifcnmental :'eview 0' the appli<;alion h: mklitiOl\ as ou,lined il: :31~~ CFR 800,8(8), tlw NRC plafls to coorr~lnate com;:;lim:Ge 'Ivith Sedo!'! 'Wi) of!tw National Hi'otoric Preservalion Act of, PDt: throuGh che requ:ren181:ts of !I-Ie N",;ional E!lvironn18Pia, POliCY Act 0: 19'~;;l UI:cler NRC I'egulaliol:s, til' original operating licell~,e fOl' a nuc,ear Do',ve, P,fl!ltiS IssueCl fOf up to 40 year.,. TI-Iel:c.en"e Inay !:Ie rene,,ved for up to an :::idd:(ional 20 "ears if NRC :'e'::jUif8;:-,ents
<1l'e me; The current Clpemtill9 licenses forlnd:afl Point lNili expire :1'1 September .. 20 1:3, "nei DeCel'llJer, 20'15. Entergy submitted itS app i icallon for renewai of the Indian Point operating
,icen:3e'3 In a ietl8r dmecl A.pr" 23, 2007, as 5upple'TI81:tec! b" letters G81aG fv'I,W 3 <:II:(!
,Iune 21, 7007, HI8 NRC i-:, Q",tfleling informatioll fer 8n 1£1;;i:::1£1 PDint site-specific 5iJpp,e:fl8nt to its "Generic En"iironmentalln-,pflct S;aiement lor license Renewai of Nuclear Plenb." (GElS),
NUREG-1437 TI:e .,upplement\i\;fill Gontain t~le r":.Ilts of the review of tile enviwnmental
- ITI1)f,cls on lhE' meo sllrml:ndin9 the Indian Poir:t c.lte related l<) !errestriDI ecology. ¥lUf,lic ecology, hy::inJiogy, cullumi reSOcl"ees, and %c!oecono,:1ic:ssues (mr,on9 oli-Iel',,). f,nd w:11 cont01il: :co recolnl::emjation regarding !l18 ellvimmnental acceptability of ;j:8 iicense r81:8wal O1dall.
December 2010 E-43 NUREG-1437, Supplement 38 OAGI0001367E 00362
Appendix E Council of Chiefs To ClcCOlmllGdz,!e :n!e:-e:3ted Plembers ,)f tile pub:ic. tile NRC wi!! nole! two put;lic :3coping
'11setlngs for the Indien Pointiicer~se re!'ewal supplement to me GElS on \'Vednesdey, Septell1berW. 2:J07, at The Colonial Terrace, located at '1'19 O:e~lo:l Rd in C.olilandt f'"lano:, NY_ The flrsl sessioll wil: cOlwene at I :?,O pJY:. (:nd V'-/:II contin,le lint!! 4::}O p.m. a" n8.:...-~e:3Sary. The second s8ssiol: \rViH GOnVer~8 at 7:0:J p.tr: ... \~t';~h a repeat.of ~hG OY8fV:if:vV D<x;iof1s of tilE' [:;eetinQ. ;;:nd wil! continue until 10:00 plTi __ as lleces:3flrji_ A.d::li!ionai!y. tr:8 NRC s;(lff ",vi!i he,s! informal diSCl)'3Sions one hour before the '3tart d e~ich ses'3ion.
TIlE' iicep:,.e rellwal appiiGli'ofi (LRA) is: pU!JI:dy avmiable at trl8 NRC Public Docurn8nt Roo'll (PDRi :ocate(1 8t Ol1e WI:ite Flint NOlill.l*i ':>55 ROGkville Pike, R)ckvi1:e, Msrylend 20352. or from t!le NRCs AQ6ncywide Documents Acces:, 'Jnd :',,1anegement System {i\D,A.!,:lS)_ TI:8
,l'1.DAh*1S Public Electronic F~eadi"9 Room is accec.s:ble (,t
!-,tt';_):i,,'i:,;i'lUX,;:?(d:;~_"l"'~_',~_',IjL,~_~j~~,~s:,1~i,,~,:jjEJl;ElL TI,e accession number for the LRA i~:
ML07'12HJ5G7 Perso!:s 'who r;Q !lot hwe aCGBSS t:) .A.D,~.r;lS_ or vvno 8nCOW1Iel' pml;lems in acces',.inp trl6 dOClJ:Tlents iDeate.::! in .A'ol'J'::IS_ ".rlould cDntuct the NRCs PDR Referer:ce stuff t,y teleprlor,e ;Jtl-800-397-4209 or JiJ'I-415-4737, :)!" by e-mail at::'*,i:_':~i:W:~,g:?{ The Ifldic:n Poi"t LRA is t!iso c:vailable on the Inten:t at
- 1ttp: ,; ":'.';:.'.~';:.'.~';:'.:n rc: ::: ;::V/;'";2. at t;_,:~-s/,:~ ~)£:: 'c{t in;:: /J) f;::T::::.: n~~:: rs: t10\',:S :,:' ~~: ~)[~! !(:~~:t: {);: ';/:ir: d inn -- L'i;:~: n t_~:t:"n: . In aejdit:C)D. the Her}::!r;cl, HUGs,xI r-I-ee LibIT:IY, locatec: ir: fvlon!mse, NY., II-Ie !-iel::1 LibwlY 10c,':1e(1
- 1'1 Peei<-"kili, NY. ancl he VYhlte Plains Pl;I):IC Library iOC81e(1 ill "/'!rne !='i1]ins, NY, i-18ve 8greecl to make the LR.A available for pUDllG inspection Hie C;EIS. wl'1iO'1 clocument<; the NRC's sssessP18nt of tile :,COP8 ;:m':i impact 0: erY';'imllmentai effects tha~ \'VOUl0 be as'SDc~a~ed with iiGtH1'SB fBne\tV8: at any nUGI98r fJO\;V9T plant site; Gflr:: a;so i)8 fOLH'cI en the NRC's website or at the NF~C's F'DR PleaS,8 sutHYlit any comments 11-lal the Onopciaga Nation Play l1a.,.'e to offer Gr1 t!1e scope of the environmental :-e\iiew t.y October 12_ 2DClT \.'1lritlen CO:TI!11ent'3 srlGulG be submittecl by [::aii to tl18 Chid, Rules fmd DireGHves Branch, Division of Ac!mini:3tmtiv8 Sel'vices, Mail Stop T-I3D59, US Nudem Re,ltllatof'l COP11Tli::osion. Washington, DC 2G555-0001 Electronic CO(:':,'le!::s pmy s,e s,lbm:tled to the NRC t,y e-mail alj!_...i ..:.f_:E.gt_lt;:T;;t:.;:::jL<~g) *.. At the Gcm:lusion of ti,e scopin~1 process. the NF~C :;taff ,,<,1:11 prepare a S.LI'Tlnldl"\i of tbe slgn:ficant issue:; identlf;ed anci 1I-le com:!u:3ions re8Ghed . and fili3ii Zi GOpy to you.
NUREG-1437, Supplement 38 E-44 December 2010 OAGI0001367E 00363
Appendix E (;Ol.ln<::l, of Chief:; The sCB:ff expect:, to put)li:3h the draft :'.tlppIBIT:ent to trlB GElS i:'1 Ju!y 2008, TI':8 NRC wlll flold anonlel' ~:et of public meetifl';lS in the :;ite vicinity to :,oIU! CDmments on trle cllTlft siJpple!llentai env:r'omnental il:,paGl stfltement (SEIS), A. copy,J! the draft SEIS w:!! be sell! to yO:J for YOU!'
!'evievv and c:)mment After cGfls:deratiof: of public GO:ll!T:ellts: :'eceive::ion the drf,ft, t:1e NRC Wii! prepare '3 final SEIS, Tile issuaI:ce of [, finai SEIS for India!' F'0:nt is planned for April 2i}0~1. If you need <:ddit:on81 inform8~ion r'er,lw-d:ng the environmental review proC8:,S .
please contact Ms, ,JiiI Caverly', EIl\fiml:n-:el:l": Project !**,lan"ger', at .3lJl-4'15-(;6:~j9 or at
~:::Ll~g}DJL._~=3:=X~~ .
S:ncerely, IRA Christian Jacobs fori Rani L. Fmno'/id-" Bmncrl Chief Environmel:l8i Brunell B Divl~3iO" of Uc&ns& Ren8,*vai OffiCB Df r~UGlei:1r Reactol' Re~II_:iti!iorr Docket No.". 50-247 and :50-286 December 2010 E-45 NUREG-1437, Supplement 38 I OAGI0001367E 00364
Appendix E A.ugusl 2c, 2007 Tne Honorable DWi3:l1e Perry. Chiei Ramapough Lelm;:;8 RanKlpOtlgh Triba: Offic Hii~ Stag Hill Roarl r'ilr,rlwah, N,J 07430 SUBJECT REClUEST FOR (:or*.:U**.:lENTS CO~lCERNIN(3 THE INDL,;,N POINT NUCLEi,R 13ENERATING UNIT NOS,:2 AND 3 LlCEt,jSE RENE\:VAL APPLICATION REI/lEV',! Deal' Cflief Perri,!: Tile US Nl:clear Rf39Uiatorl' C:)llll'1ission (NRC) i's seekil:~1 input fOI its el:virOlllTlental revie'", of <:iIl ap:Jlic:"tion fUYfI E:lter,:,)/ Nuclear Opemticn" {Entergy) for ttle r8newal of lhe Gper"til'I;~ iicenses for 11'18 Indian F'oim NuGie;:,r (;el'8I'5t:n9 Unit No::;, 2 and:, :lml:5Il POi:lt!. localed:n Buchanan, NY, Z'PIX,)xima!eiy 24 miles north of lhe Ne'N York City bounda:'y li!le, In::lmn Poinl is ip el')se proxil'::ty to Imide. thilt me:)' tie of illte;est to llw Ral:'12;JOugl'l LBnape /',3 de:;cr:be,j below, ,he NRC's proc8ss includes; al) opooituility forpubiic ano illter-go/efllIT:ents: pi)rticjpa~ion ir: ;:he 8r::vk~)nn18nta~ reVi8\!v. V1/8 '~"~~ant to e:~tSL::r-e that ')(Ot~ ore a'livare of our efforts and, purSu3nt to TiUeiCI of the Code of Federal Rellulations II:J CFR) Part 5'1 SedieJlc ':d 28(b), U:e ~JR.c invites the RmTlapou~lh lel'ape to pmvide :I'IIXI1 to ,he scoping proGE;c;S re:8;in9 ;0 the NRCc, el)vimnrnentCli review 01 the I1pp:iGl1tion, 111 acidition, ,'s Dutline;~ in 2.0 CFR 80:J8!c). ;he NRC plam, to coord,nate GOI-:"piiar:ce with Section! 06 of the National HI~.tmic PrC),;e:vatiol" Act oi '19E'6 ,,.,rDugl] the 1'8'.~Uif8:1l81,jS ,)f the NBticlI3: E!lvimll:llentz,1 POiiCY Aet ,.)f 19t3!;J. UncleI' NRC regulatiOl':3, th8 or:~lill111 (,peratiIl9 licellse fo!' a l'uGieilr power pkmt is is~,lIed ;,or up to 40 yeElr" The lire!:se may be rer-e\,vecl for up to an sdd:t:ol1al 2[1 ',em:; il NRC m'~uir8ITI81:'S me rnet. The C!;:Ter~t op6mt:nc,liice:J3es ior Indian F':)inl will expir8 :n Sept6r'lber, 2[1', ~:l, nnd December 20', 5, EntEr~IY sub,nit1e::1 its ::lDpl:catiDI1 IDI' refle'wai of the Indian POint op8rB!in~1 iicenses il: a lette: dated A,pri! 23. 2007, as 3upplemented "yle;ter", dale:; ~\'Iay] and
.JIJIle 2'1. 2:J07, The NRC is galileri:)p information for i'lI: Indian F':)int site-speCific suppl8rnent 10 ;cs:'Gener:c Env!wnn'enltli IrniX,Gl Sta!8lnent lor Li,:;e:1se Renev;,'a! oi Nuclear Pla!lh" (GElS!.
NUREG-1437, Tile Sl<pp!el'18nt wi!! ,;ontain the reselits of tl"iE rEview of thE 81wi:onmelltai iP1PSc.tS Of' ti'le mea sUIT)unding tile IndiE'd1 Poil,t site I-elateo ~:) telTestria: eGoI09Y *. <lqu<ltic ee01(}~~y. hydro:o~iY, Ctlltuf81 re5Durce~3: Bno 5.oc:oeCDl""!:orr::e :i~,sues .(J3rnDn~1 otrlerS), :]nd \}/t:: (",;ontain <l recommelKi3tion regardin9 the 81wironmentai acceptability of the IlcE'l'Ise renewoi action, NUREG-1437, Supplement 38 E-46 December 2010 OAGI0001367E 00365
Appendix E D. PeITy' To f)cco:T,n'odi3.~einterested members of the public, t\:e NR.C ',vlii hold two ptl!:!lic 3Gopil'9 meetil1';;~' for Hw Indian POIf:; license renel'*ml :,upple:l1-3nl to tile GElS on VVe*::lnesdav.
!3epierr'ber HI. 2007, at The Coionial TerPJce. i;jcated aiiE; Oreg;jll Rd. in C;jrtlm:dt Mailor. NY. The first se:,slon will convene at '130 pm :::II-I(! wiil continue until 4:30run. as ne-c:es3cH)'. Th'e second s8ss~or= w;n COrt'V8J1e [)t 7:0:) p.IT!_ v~. . ith a repeDt of the O'\./er'{jel,.~~r portions of tile meeting. cmd ,viii continue until 1000 p.m. ;:6 Ileces:,,-yy ..A.d(jijionally. 11>6 NR.C staff 'Nill h.Jst il1for:01<,1 discussions one how before the slart of eaGi-: ses:,ion.
The iicense re:1e'Nai application (LRA.j is ::;ub;icly avaiiab;e at the NRC Pub;ic DOGulYlent ROOITI {PDR). Ic:ct!;ecl ill One "NIHe Flil't North. 1'!555 Roekviile Pike. Rockv:!le, r',lm-Y!;:H,d 20852, Dr f:'om th8 NRC's Aqencyw i d8 Document" i'll;CeSS and r*.,klrm:~;el':8Flt Sy'O.tel': (J'>,DAfvlSr Ths ADi'\.MS PubiiC Ei8Ctl'0f1!C R.8mlil:£l Room is acces~,:IJ!e at t:HQ~J:~B..:~:_c)LJ~:~:::;_:~:2~:J_(::f:~i'::A::~t~_-_g~~:~"-,:iE23~:jgit~j=:_~~:JJ.. The f..l1:,cBS3tOn nurnbef for 1:'-le LRA ~:3
~,. lL07'!2*i 0507 Fel-',;(HiS wh:] do r~<)t I:a**;e [ICG8S:, to AD.AJvlS. or '.'.,.110 encounter pmblerns in access:ng the documents iocated in ADA.MS. should cO!:;aci ;~Ie NRC's F'DR RBf8fencB sta'f rJV teteDho!le {It 'l-eOO-3'S~7 -420'~~ Of 30 "1-4 '15-4 737, 01- t!:l 9-rnB::: [It :~:=_:_:);1:t:_:~~~_~:_:/:.:*.
The Indian Point LRA I::; abo >J\railable on the Intern8! <1; LH.[~_:_:~~>~~<~)'~*,~~,'~"_n r_~~::."_ g::_,~~~*:r::_::.}~~t:~:J_ ~~*:*:~:P~~:-:.}tl ~-: ~:J_h~'} D_~_~_U_~'~: :'f.'} D~_:_*l(:}l.: ::H.:}) l~(~~J:;}{: ~~h:-)!J.k~ :1:.P~~*K~t .11trr: 1. fn adcl:tiCi'l, tile Henclr:CK Huclson F:-e8lilJrary located III :vlontrose, NY, the Fi8;d UbWl-y. iocat8d In Pee*.skill. NY. <wd tbe 'White Plains F'ubliC Lit:r<>ri;OCi3~e(j ill Wbite PI<:,ins. NY, !lave sgreed to I::ake trle LR.A :::;v[Jrli3t)le for plIiJilC ::'lspedioll HIe (JEIS. wiliel-! dOCUl'ltmts Ine NRC's i3S5ess:01e!lt of tfle sc:)!)e en::l :lTIpact of enVironmental effects that \*vouk! be assodated vvith i~c8nse ren8\.'Val at un). . fluc::-eaf Pl:I~.~'-3:- plant ~.~te. car': of~.o t'e found (In ihe NRCs website or at 11-,8 NRC'S POR Ple;Yoe :suc*mll any CCiflHnent"' ,f,st trl8 Rflmc:;xR:gh Lelvape :ml'y rlav8 10 offer on tt18 scope 01 tit£! en',,"irDnnientfl: r8YtBV~" by October l2, 2D07 V'irftten GOITirner-:ts ShOl:td be subn1:ttBd by Pl<.:d tD tr:e C;'lief, Rule~3 an;:: Oi:-edives Bri3ncll, Oi*.[isioll of .t\cjminis;rat:'*;e Sef'iice";' r'::Ii3i1 SteIp T-;:;059. U.S. Nudem Re~lulatory Commission, Vh.:s.l::n91on. DC 20555-COOI. Eie8lrolliG COIF118!lb mav be ',liDlnIHe<:l to ~t")8 NR.C by e-n~ail aUIUi:'1r:::'Q;:1iJ~_;_,:,t!i':ii<::_'::1:)"* . .At ,ne
<;of:clu',ion of the <:::cop:rI:g proce<:::s. the NRC Slllff 'NiH prep.:;re " sUIT,marv of the s:,]nif:c<lnt i::;sues identified ami t!w concil.lsio!", 1'8a(;I18:J and ma; a copy to 'lOLL December 2010 E-47 NUREG-1437, Supplement 38 OAGI0001367E 00366
Appendix E D. Perry Tne staff expec.ts t:) pubii',<r: t~ie c!mft SUppl81YI8nt t:) Hw ,3EIS in ,Juy 2008. Tr,e NRC w::lllol::1 anotrl8r :,.131 of put:lic 1-:':eetinr,15 :n the site vicillity to ,.o'i(::\ cO;;'lments :)1' !I-'8 draft :3uppier'lenta' env:romY;entrd impact stdell'ent (SEIS) A. copy of tl:e ;j,f,ft SEIS wil, be sent to yo<. 1 lor your
- -8',::ew and commentA.ftel' c.ons:deration :)1 put,Hc commellts received :)n the dral(. the NRC "Ni'i prepi:l:"e a f:rli:l; SEIS. The :%~mIlC8 of a finol SEIS fo, Im~:al1 FO:'lti~; plal1l'ed for
,A.prH 2009. II you need addition81 infoPTl8i1oll regardin£1 the 8Iw!ror:rn8Ilial ,8Vle;,'v Pf(JC8SS.
Dle,o" GOfilaCt 1\'15. Jill Caver*ly. Environmental Project Mana~ler'_ ",t 3D, -4',5-\3699 or at Sincereh/. iRA Christian Jacobs for.! Ran: L. FI-anovic!1, Brancil Chief Erw:r:)lllllenta; Brandl B Di'*/ision of License Ren6'Ni:l1 Olf:ce of Nuclear Reactor Reguli:ltion Docket Nos. 50-247 or-=d 50-28(:( cc SeE next page I NUREG-1437, Supplement 38 E-48 December 2010 OAGI0001367E 00367
Appendix E AlJgust 2~. 2007 f'*,'lr Mike .John CO:-158rv(':tIOl':i5t SenE'ca Na,iDn of Indians P_O. 50x 23! Sal<lmanC;3, NY i4479 SUBJECT REQUEST FOR Cm.*i1"IENTS CmJCERNING THE INOlAN POINT NUCLEAR (;ENERiHING UN!T NOS 2 .AND " L1CEt..JSE RENEVV.A.'-- APPLICATION RE\iIE',~! Dem f'*:ll' ,John: Th", U,S, NI"dear RE'gul"toIY Cornrni'3:,iorl {NRC) is :,eekil:g input for its 8lwlronment<l1 review of ,m ap:Jlication from En!ergy Nuc!ear Open"lion'S (Efltergy} fm the rel,ewai of tile operating I:cen',es fo:-1he Ind;an Point Nuclear Ger:en:t;ng Unit Nos, 2 and ;3 :;Indian Poi:":, IOGsied :It Blxiln:-I3l:. NY, appro)(lmately 24 m:les north of trle Ne1o/ York City t}(JuJ;,:lmv II:-Ie. Ind:an F'olnl I:; in close proximity to 13nds that "nsy be :)f interest to the Senec:" Nation of Indians. ft,:; de:,crii:>Ed ;:ielow, tile NRC':, iJroGe,>::;i!ldl~d8S af: GPPGrtunity ~or pul;,!ic i311,j inter-goV8! nmen131 p::Ht:cipf"ition in trl8 enVin)rHr:~ntf~: revie.j.J_ V'Je \~.'8nt to en~;Ufe that Vau Dra ~1\;'I. . ar8 Q~ O~H" effolis. and, purst;::tnt to TjUe -jO of the C:c;de c;,f Federfrf Re~}{f;fJtio,'?D (iD CFR) Pf~rt 51 > Sec,:on :::. i22;it,:, lI:e NRC invites ;Iie Senem Nation of Inclc1ns;o provle!e IrIput to the scop:ng pr(.c8s*". 1'8iatir.g to the NRCsenvirontr:sntal r.. vie'.'; of Ih .. application In lKldiliol\ a'S outlinsd In Je CFR eOD_BiG), !lIe NRC plall:> to coordinate co!'1pilm'c8 with Section '106 oj H-Ie N,:,io:1al Historic ~'re5el-v,:kJn p,ct of '196>3 trllT)ugh :he recwire'1l ..m:; (if the ~~at!onal En'l;rof:'1lental POlicy A.c.t of 'I :j6'c! Uncler NF::C; rg*,;uICltiof:s. th8 (>f;i~inal ')pe r atil1g liCEnse fo,- II r:uclear pm'ver plant is i%ued for up to 4(: years, TI"" license may iJe !-e!:ewe:j for-up tD 'In ad(iitional 20 yem'S if NR'=* rWiuirements i3re :-net The GUrI'ent c,peratill'~lliceflses for Indian F'oin! Will exp:re :It SepteITIi:>el-, 2013, and Oecems*er, 2015. EntelIIY sut"-]',itt8d ils i:lppl;c-01:on for I'enewa! (:f II:e In,:lian F'n:nt operating licenses in a I",Her (k,ted .A.r}ri; 23, 2007, i3."sc)pplemented bV letters dOlt<?:.:! fllhly ~) <'nel
,JlB:e :2 : . 2D07 The NRC is gat!ler;nginformatiort fOf ai' Indiml F'oint si,e-sp<?cilIC s'-Ipplemeflt to it:s "Generic Envirolll'nent(':llmpad St8tement for LiGen:;e Rene'NElI of Nuclem Plants' (CjEIS::*,
NUREC-i-!.:)37 The supp;eIT:ent \lvi!! contain the r<?sults of the revi",,,;, of the emiiwllInst:tai i,-npm:ts or: the area sUiTOunding the il:ckm Poir:t site t'lolmeG 10 telTe",lrial eco!,)gy_ aqualic: ec*:)!ogy, hydrohJ{fY'1 G\.dtLHBl :esourCE:s. an~j s:JG~Crec:Jl:onl;c ,issues (a~;no!1g o!hers}. t:nd V'-Jlll cD!:tain " reCD'11menrjfltion reg "Wing t!le environment':l! aGceplability Dl the licen'Se renel;:,al i3chon. December 2010 E-49 NUREG-1437, Supplement 38 OAGI0001367E 00368
Appendix E 1\'1. ,John To [:ccommodaleinterested members of the public, tl:e NRC wll: hold two put'lic scooil1 rJ
- lleet:n,:;;', :01' the Indian Poir:l license ren8l,'iaI sl.lpple;:',ellt 10 llw GElS 011 \Nednesdey, Seplember IP, 2007, Dt The Colonial Terwce, located 8t -:-19 Orepof. R;j if! Co,-t:anclt 1\.:1 ",no:' NY. T~e first se,sion Will convene at 130 p 1:1. Dn,j Will continue lIf';:1 430 ::UT: , DS nec8s~;ary_ Tb:e secD!ld '::)8SS~Of': win conve.ne at 7:0(1 p.tl:_; v'!/ith ~3 fe.P83t of t:t:6 Q'y'8rV!2 IA" Dorliof.s of tile meeting, i3n,j w:11 continue 11r.ti: 10:00 Pin .. ,,6IleC9:3:3Etfy', Adc::::o:'18lly, 11".8 NRC stc~ff \-viU l10S~ tnforri}<:":! di:::cu'SsioFl3 one rlour before the start of each :3S'SSlOTf.
T"16 license re:lewal ap;:;lication iLRA) is publicl'y available Dt ,Ile NRC Public DOCUITlent Room
;PDRJ, lOGfited at One VVll:!e Flip; NCiI"",t'I,11555 Rockville Pike, R.ock',/ille, r',,:larylll!'d 20852. or from til> ~lRC's .4~l9nc'yw;cje DDciJments iI,Gces:; 2nd ~ilaria~;~ment Syst~m (ADl"~..!S I Th~
,l\[),I\.J.:1S Pu!)lic E18cHoflic RealH!'9 Room k3 accessible at
.tlttJX.:~{!:L*_i£::~[JJ-_::~:i5.:~::!tL~_:-'_~~::K*~~~Lf~~_;_~~_::j:_~~~.~!-3L:&:~!litLJ!~E*£L. The acc8s~3jon nurnbar for th8 LRA is tdL07'12'i05G7. F'~l"sQns whcr do not ICflve access to AD.'\I',,:18, or 'NllO encounter pfODle:llsin aCGe%:!li;i (fIe dOGun:ent~, 'ocated in .AD.4r',,:!s. should wntad the NRC's PDR Refere!lGe "taff by tel8pfl'X!e ;3(1-800-307,4200 01" 301 -4 15-4737, or by e-milil at .t~li.@lJi.s~,:Q;:}"':'
Fie In(jian PDint LRA is ,li::;o i3\fail,:Dle on tile Internet at httt~.,.* .':.,,1,/"';;:,1'.:. nrc. C~(!I,:';'f ".::ac t;,:,:r~:/;::p£.!';'a~! n*:..: :~i:c:£.:~':::.:n(.::r£.::':"":;:'/*:a !. . ~:Pf"~: :~_' ,~xt :(:*f: '3,/ir:d!~:;}-p,:~: nJ ht:"I'l;. l n wk::~io!l, ~il8 Hendnc!" HI.IC!SO:l F:ee Library, located il: l".:1onlrose, NY, tile Fiel:.:! UblaJY, locateej in Peekskill, NV, and the 1iVhite Plains Pulll;,; Library located :n \,-'\11".:,8 Plains. N'( have 8gr8ecl to make the LRA tivailable for pub:ic :'1speGtioll T~le GEl,S, wllid! ClGCclf1lElritS t~le NRC',; aSS8s;:,r,wnt of the scope and i:Tip<:lct of 81:virDnmental effects thui \Nould bE; as'SvciatecJ v*..'fth ::CS!lSE: rene\~iDl at [~n'! nU~::8ar povver plant 5f~e: car: also t;8 found on lhe NRC's website or at the NHC's: PDR Please SUi)!"fll! 'JITV comments lilac lile Seneca N8tlOn of In(j:mls may 1"18Ve ~o offer on tlce scope 0' the 9l'vironmentai review ::,y Octo!:oer 12. 20U7 I/iritten WIT"H:wnts should be subnlitted by mail ,0 the <::rlief, Rule" aI:d D:recti',;e:s Brandl, Division of ,q<:lmil:istrati',e Services, r"lal: St'Jp T-13D59. U S Nuclear R89ulalory Cornnlission, V,jashilll!ton DC 20555-000'1 Eledrol~ic can"Tlents !1lZ1'i be s!;i)mitte,j to the f'JRC by e-Il'!3il (\l "'*:~;;";:-:Fo:;f::f,',n:i.-t:,,::,:;,,:;::-\.. , /It the cOI:dl.l;::io'1 of me c,eop:ll~l pI"oce"s, the NRC ';tafi will ,)repare D summary of the ;::igl::f:csnt
;ssue:, Identified ,,:1;:1 the c(lrIC1U5iol~S re"ched, and mail a copy to you.
NUREG-1437, Supplement 38 E-50 December 2010 OAGI0001367E 00369
Appendix E Trle ;::(off eXpect'; 10 ;:;utliist: Hie dl"ilft :supplement k> the GElS il: Jllly 2008. Tile NRC wHlllold
,mother set of publiG meelin~):3 In the site vicil::t'! to solicit commellt:, on the dmft supplelTlen(o:
enVlfOfllTlenlill impact s\i::lement (SEtS) ,1'\ copy of ttw ,jmft SEIS 'NIII be sent to you for your [evie\'", m:d COI1::Tler:t. AJtBI c:on;:,ide:;3tion of put:,i:c comments re;;8ived on the dwfI, ttw NRC "NiH prepm-e a fillel SEIS. Tile ISSU"H:ce 0: a final SEIS for illCll2in Point is plam:ed f:)I" Apr:: 2009. If you need addition:::: infmmaIiof: 1'89ar::lirl r;1 tile e!lViWn!lle!lt,,1 review p"ocess, pie;Jse contact ~'ls. Jill Cav'Hlv, EI:\.'ironl1'el:tai Project r',;,ian a<;;H, at 30'1-415.-6E")9 or 'J! SinGerel'!. iRA Christian Jacobs fori Ram L. Franovicll. Brallerl eldef Enviwnmentill BCanC!l B Div:sion of license F:elle\l:iaI OffiCE of Nuc!ear Reactm Heputmiofl Docket Nos. 50-247 and 50-28.6 cc: See next paqe December 2010 E-51 NUREG-1437, Supplement 38 I OAGI0001367E 00370
Appendix E
,'\ugust 2-", 2007 Mr Rmldy Kind, Chairman Sh:innec[1c;<. Tlibe Rte 27-A, MOIl;auk Hwy SDI.:nli:amDt:Jll, NY '119G8 SUBJECT RECiUEST FOR COI\/I~,!ENTS CONCERNING THE INDIAN POINT NUCLEAR GENERi\"TNG UNIT NOS. :2 N~D 3 lICE~~SE RENEWAL AF'PUC,<\TIC>N RE\!IE\:\I The US. Nuclear Re~~tiI8torl' COflm::ssion (NRC) is seekill!,! il:~;.ut fOI' its e!:vironn'eritiJi re',1iew O! a!: ",ppliG<ltion from Enter,,',' Nucie:::,! Opsr;]tions (Enler"y) for the rene'Nal of the opemtmq licenses for ,rV3 Indian Point NlId>3af Geller<Jiing Un:t No:;. 2 and 3 !In::liBI1 F'oim;, lon:ted :n Bud,a:l<:,n, NY, [~pproximatelv 24 miles north of ,l1e New 1'01" City boul:dary line. Iml:2!n P::Jinl
- ',i" d0'3e moximity to la!lds thi:lt ,Tlay be of interest to the S!linr:ecock Tribe. ,A.s de',cm::ed t'el,:}'{,', tile NRC',: proce:"sinclL:d85 HI' opportunity 'or lJut'iic. cll-~C; inteH;tO'iEnnments i pmti-dp8tion lr: the 'I:~iironIT;enta: revrevLf. VVe v\.'::'lnt to enS!;r',8 that you are ~*p;v.:!re of our e!fort" and. PlW;Ci3nt to Til'e 'W of the (~;o(le of Federai PeguiatiCms ('I [i CFR) P<:1!i 51, Seet,,".r' 5 : 18!b), the NRC il'>'!:tes the S!:inr*ecock TriL", io prov:,]e input to the scoring process relBting to the NRC's ellv;ror::nental review of tile <:ppliC::.lt;O!'. In addition, ,:.:0 ol;:Hned in :315 CFR 8CI[i8(c}, the NRC pimv; tD coordinate compliance with Section 'lOc; of the Niltional HI:;loriG FI'eservCltioll A.ct of 'I ::l66 throlP;lh the r"qu:1'I31l16nts oi the National El'vironmel'tal Policy Act of 1%9 Under NRC regul[:;:ons. the onpi!:al ooeraiil:Q licerlSe fm a I'ucl"ar yowe!' plflf)tis issued ror up tD 40 years. The license may be rellB"",ed for up to an <Jdditim:al 20 yeilrs if NRC require:w,mt5 mernet The CLirrent opemtin:J ::censes !:)f' Indiol1 Foin: ",,:11 expire :n September 20 13, and Deeember, 21}15. Enter,w submitted ih npplic<>tlGI1 fOI' renewal or tl:6 Indian POint {merilti:1~1 licenses in B letter datecl h::riI13, 1007 as supp:elT!ented i:;y lette!s elatecj i'.*lay :I nne!
..lune 21, 2007.
ThE' NRC is gathellng inf0rmmion to: an Ind:an Point site-speci':c '3llpple:Tlent co its "{38neric En'./ifonmentalll11pad St>>;emellt for LiGense R.enew::)i of Nuclear Plants" (GEISL NUREG-1437. The sLJ[:piement ',<Jill contain the resul!s of the review oi the e:wirollmer:tal impncL 01: me area '>l:ITolind:ng me Incliul'! Point site mlateci to tem~s,ri[:1 e8olo~!y. aqu;Jiic eCO~O~TY: hydro!DQY, cunural ;-6S0Ut"C8S. and SOd:)6Cor:Grn:ic issues (8xnOn{~ others), end 'wi:!:! c:Jl:tail: ,j rec:J!llIT1enclmiNI regar,jrng tile enwon,nental acceptaiJi!;;y 0' the license rene'N:c:i aGtiori. NUREG-1437, Supplement 38 E-52 December 2010 OAGI0001367E 00371
Appendix E R Killcl -L-Te; aCC,)nlITlo::late i!ltere:,Jed tT:em!)ers of the public, the NR.C ,viii fn)ld tlNO pU!Jlic :,.coplng m8e1~fjgs fl:lr the Indian Poir':t !icen58 reneVo/ftl :3,upp:lern8nt to the GElS ')1"1 VVednesdfty. Sep1ell1l)el' '19, 2007. at nil" Colonia! Termce, I:)cated atll ',r Oreg:)11 Rd. In Cxtiand!
~ibrior, NY. The first ~;e%ion wil! <;oflvene at '13(> pm and wl:1 continue 1II,til 4<10 I),il; , as
- lCeSSat'i. The seGo!ld ~,eSSlor: Will CDl'!vene el! 7:0;] Dm .. winl a repei"! of tf:e :}vervie'iI" portiol"" of tfTB mBetin9, 'Jrld wi:: continue untii1000 pm, ;:'S nec83sa:"i. !'\dditionally, the NRC s!",ff INil1 flost Informal (Hs:<;usslcJns one 110m [H::fore It-,e :,tart of eael, session.
Ti,e license reflel',*al aps-licacion (LRA) IS pulJlicly avaiialJ!e at ti,e NRC Pub:ic DO('JJI:lent Room (PDR 1, ;oc;3\e6 at One \.Vfrite Flint North. j 1555 Rockville Pike, Rock",:!le, r-Jarylm,d 20852, ,)1' fro£': the NRC's Agencyv4!(le Documents Acee';s a'1,i Mc:rlEl',;e£':ent System ("'.ClAf',.,1S) Tile
,t.,DA~i!S Public Eledronic Reading Room is acc:es,,,ble ot
~tt::: :':ad~-::T:3~~~'ebs0~::"(',h nr{. (J'J*I... ,;dD:(:.J:::~: ;":~:'-;l:i. The 8GCeS310!l rll. .Jrni)8f fo:- i~le LRA (s ML07"210507. Persons who do 110\ ilave access to ADM',*lS. or 'Nho enCOI~:1ter proDi:11S in acces"ing 1:-le o::!ocul:lent:3 locatec! in ADAMS, '; I'IOU lei cOI:taGl !tIe NRC's PDR Referem:e :"ta'f try tslephon,e 8t J-800<:97-4209 or 30'l-4'15-47?i7, or by e-rn¥.:1::: ilt ~::::~:_~1~~r::.::~~"{t~:>~.
The Indiorl Point LRA is ,,:Iso ;JVailsble on the Imemet "t
')t~:,:i'~'~'i~,,'!,.L::>.',..;:::j'!:~:~j,':.'2t(:j),:~S:':j)::;:"'fl!'g::;,:.';.'j;']:~J)Xj~J.'j;'],;;','uk:']):,;:::II<~~!JJ!J,r:~!j3::"Jl:l:Ll:>:::1J"1,i!Ll'i. 111 a::lr:ition. the Hew:I'ick HudsDn Free Library', 1::)Gated in 'Vlontmse, NY the Fiel::! L,bfi3ry locmed
- n Peebkil:, NY, and the 'oN'hile Piai!::3 Public Lit:rmyloGmed 111 White Plr,jns, N'r' ~Ia';ie (,greed to mak.e tile LRA avajjai)le for pulJliG II1spediQll Tfle GElS, wtlici, (joCU::lents 11'18 NRC's assessment IJf tile 5ccqe [m::i :mp>JGt of el,"lirQnment21i effe-Gts th:-:-H "'.!"./ou;d be Bss:.8G:ated \*'.~~th ~!cen'~e re!l8v'J81 at any flUG::Bflr ;,10\A-'9:- r.dB:nt SHEL car: also
;)8 found on tile NRC's 'website Of c,t lhe NHC's F'DR Please subn-,it anY' cO!mnents that the Silinr:ecock Tnt:e mav h;3v2 to offer Oil the ',cope of Ir:e env:lollmentilll'8v:ew by Octobr : 2,20:]7 VVritten COITlnlr,;:; "flouid be ",ubmlltecl by £ml:! tD he Chief, Rules: anc! Dlredl',,Ies Brallch, Division of Admlnistmti',"-8 Ser,..-ices r"kl:; Stop T-fiDSi:l, U .s. Nu':;~eaf Re~Jt;b:ltOt),. CQ:~nr::1:i3s:ion_ v\lt")shington, DC 20555-[100"; _ E;8ci:-on:c; CD:;1rner,::ts n"'luy
- )8 ';ub'llitterj tD the ~lRC by 8-m;:>i1 at ;:.'.":;"~:):\iU.1.';.~:T;"d::,1r<~.,:~m'~. At tile cOrlfiuSIOIl of tile swpil:g process, lile NR.C staff wi;1 prE:r.:i:"l1'8::: su:,lm:::r\' of the significant issues identified and tile GGnClllSlons l-e~lc!lecL ane! mail a GOpy to you December 2010 E-53 NUREG-1437, Supplement 38 OAGI0001367E 00372
Appendix E R Kind Tne staff expec.ts t:) pubii',<r: t~ie c!mft SUppl81YI8nt t:) Hw ,3EIS in ,Juy 2008. Tr,e NRC w::lllol::1 anotrl8r :,.131 of put:lic 1":eetinr,15 in the site vicillity to ,.oiiGij cO;;'lments :)1 11-,8 draft :3uppier'lenta:
'
enviromY;entrd impact stdell1ent (SEIS) A. copy of tl:e ;j,f,ft SEIS w;l: be sent to yO'. 1 lor your
- -e',:iew and comm-entA.ftel- c.onsideration :)1 put,Hc commellts received :)n the dral(. the NRC "NiI, prepi:l:e a f:rli:l; SEIS. The :%~mIlC8 of a finol SEI-S fo, Im~:al1 FO:'lti~; plal1l'ed for
,A.prH 2009. II you need addition81 infol"'Tl8i1oll regardin£1 the 8lwiror:rn8llial ,8Vle;,'v Pf(JC8SS.
Dle,o" GOfilaCt 1\'15. J,II Caver'ly. Environmental Project Mana~ler'_ ",t 3D, -4',5-\3699 or at Sincereh/. iRA Christian Jacobs for.! Ran: L. FI-anovic!1, Brancil Chief Erwir:)llnJenta; Brandl B Di'*/ision of License Ren6'Ni:l1 OlflC8 of Nuclear Reactor Reguli:ltion Docket Nos. 50-247 or-=d 50-28(:( cc SeE next page I NUREG-1437, Supplement 38 E-54 December 2010 OAGI0001367E 00373
Appendix E A,l.Igusl 24,2007 The HO!lOrable HalTY S V\i2!18GB" Cnief Unkect:wJ~~ Nst!cn PO BoxtH3
~,'13StiC, New Yor!', I'! 'j5D
SUBJECT:
REQUEST FOR Cm'!r,'lENTS CONCERNING THE INDt~N POINT NUCLEAR CoENERfHING UNIT NOS 2 AND J LICENSE RENE'WAL. APPL!C}\TION REVIEW The U S Nueiear Re9uialolY Cornrnission {NRC) is seeking input fOf its el:\riwntnE'l:tal revie\>v c,: al: appllGatio!l from Ellt<?rgy N,IG!ear Open:I!,OI1'S (Enter9'1) for the rs!:e'Nal of lile c:perat:ng I:cense" for !he In::km Point Nc!cie8r Ger,E'mt:1l9 Uilit Nos. 2 81ld :3 ::Indiall Point.:, lo,:,ated:n Bucl1<:lnal:, NY, approxinmteiy 24 m:les north of the Nell York City bo,Jl1da:y lin<? Ind:all Poill; i:, in dD:,<? proKimity tD lands t~ia1 :nay be of inle!'est to the IJllli<?d1aufl NBtioll ..A:, de',cr,bed below, trle NRC'" qroce:o:s incllides Ell: opportunity for plJblic <Inc) !l1tef-gove:llI'f:enta! part,cipatkm in :he *e!'vironmellta: fe'iiew. \f.Je want to e:1sure that yOlO are aw,-,re 01 !)'If effor!s c:mc!, pursl.:an! tc, Title i 0 'Jf the Code or Fe,!erai Re9u!alions {'I;) CFR:, Pm! ;:,1, Section :','28{b;, the NRC illvites the Unkeclmu9 Nation to I)ro'tide iq}ut to the SCOpin9 proce'Ss reiatir.9 to the NRCs environment,,: fe,'iew of the appHG3tioll, in addition, a:s outliner; in 3'3 CFR B008~G), the NRC plans to CO)*ord:n8te Gl'np'im:Ge :,,,,,ith Section ',Go of the Nr,;'ortc:11 Historic F're'3er,ali::rn Act of '1960 trlrollgh the requiremer-ts of th<? NationCl: E:T,liropmen\::.,1 Fol:cy Ad of 'l:j6P Under NRC re';lulations, tb", original oIJe:'atin9 licellse 1m a nuclear power plan! is ISSou<?d ior up to 40 yeilr:" The licel:se may toe !'er,e,,,'e:) for up ;0 <Ill add,t,olli31 20 vea,", if NRC 1'8'=<~life"lenls dl'e :TIet The GUfI'ent opemt:ng licenses for Ind:an Poin! lNili expire :n Sept&mber 2013. "nd Dec6m!:!<?L 20'15, Entel-gy subnlitt<?d :;3 applicat,ol'l for I'ene',va: 0: the Indian Paint operatin9 1:(:8!V,eS ill a letter d8teci .A.prj; 22" 2007, ih :;upplemeI11e(j b::i le;ter:, clateCl j'.'iay 3 and
,Jut:& 2-i , 2007 Th", NRC is qati1&r'nginforll1ation fDr ill: Ind:an Point s';6-:'pec:fic supplernent to :to "Generic Elwll'olllT:entallmpact Statement for license Renewal oi Nuclear Flan!s"' (C~EISl NURE(~, 1437. The "cipp:ement wil! *,;ontain the results of the review of the enVifDIlH:ental Impacts Of' ihe c1l'e;J SllITOI.:ncJiI1Q tile 1!:cliZtI1 Point site I'elated !o telTestria ecoll)g,/. ;Xllk1tiG GOtogy, hydro~o~ry') (".:..dtUf::.ll resources. and sodoeconorn:c :issus .(atTIOn~l o~hers}, i:nd y./i::
cor,;oin [l rec<):,!HJ:EHl'jatiDn fe98n:lin';l the ellvinl!lITlenta! c]cGeptat"lity o~ tbe lic:en:"e renewal nctiol1, December 2010 E-55 NUREG-1437, Supplement 38 OAGI0001367E 00374
Appendix E H ViJl:ace To acconillodale interested members, of the pulJlic the NRC \i\;'1ii hold two public scoring rneet~nQs fDr tne tndian F'"clr::t Hcense renev'Jel supplE:-:ncnt to the GElS on \t\lecmesday. Sertembe:-19,2007 at Tile Co:oll:al Terrac8, located at '119 Ore/Joll Rd. ill Cortiar:dt rV1£:tlOf, NY The fir:::t "S8:3s:ion vvill convene at "1 :30 p.rn. atl{! "'\'./:::1 GontmUe untd 4:.30 run., t~5 nC8~~SOt-y. The se~~oflcj '~;E:SS~Dr: tVm convene (~t 7:0;) p.I'l1.. '...v~t~"'l a repeat o~ tj:e D\lef\iI8\-V portiens of the rT'eetin9, and will GontirTue ul:ti: 1000 I). In .. as necessmy Ad(H'<)flEllly, the NR(:
,:,\z,fl will i,osl :nf,)ITna: ::ilsc!;s:,ions one :lour iJefor2 tlw :3tarl of eael' :'25510n.
T:le Ilcen",,, renewal appllcatlQn (lR£:.) is plIbiiclv avarial)le at 11'le NRC PutlilC Dowment RClom (PDRL located at One I,Vhite Flir:i Noreh, '11555 Rockvile Pil,e. ROGkville. f';:al-ylam! 20<352. or from the NRC:" A::j8rrc'{\,</:cle Documents ,'~(:Ges.:3 (,mi 1""lsI1a~ieIT:ent Sv~:telT: U',DAJl"lS) Tl-,e ADA~...lS Publ'c E:ectr,Jn:G R88dir'9 Room is aGcessible [It tll1;;:~:,-'t:l~'JIl.;;'.;\at;5_",m:~tJ::L:~_i'.K';::'~i-':>12QJn_t'!)*Gl. Tile accession numt1er for j'18 L.RA, 1<; ML07': 210507. Pef3cns wno de r:ot hf:n.re flCGeSS to A DAr. .:::S , or ~Ii{ho encounter r-:roblern~~ in accessing tl-,e documenL located In ADAf,:lS" sllGulei Gomaet 11-,e NRCs. F'DR F~eference staff by tslephon8 at 1*800.:3')7-420') or 301*415*4737 orbye'I1K!11 at'Z:::@[:;::':;_5:~_'" nle Indian Poin, lRA is aiso aV;J,i.::,t:leoll Ii-,e Internet at t1!:t~;:_~i::"':.*~~*~*~::!'~j~~rt~_~).2>~:I~~~Jr_~'2~_~jc'~'2;~'B_::~Jt_:}~:"JJ~~f;L::~~~n;:;~E~;j~~~:~~~:Idi~:}Q;:_:jf~_~t:~~:?:-~:_~j:~t:_:~:3J~t:J:l;!-;.t~~~~_:}t~:_:_:.. In aci:jitiofl. the H",rjl31'ick Hudson Free L:bfCiry. locmed in ".,lol1t['.):;e. ~N, the Fie:d library, located in PeeKskill. NY 31:d tl:6 '.fnlit6 Piains Putdic l!!)rmy iDOJie(i in NI",e Plains. NY, h{r'le agre,,(! to make the LRfo. aV':l118ble :'<:or l)ut;iic: i!hpeGt:on. n,e GElS. which documents the NRC" 85S<3<;<;I':',9'1! of the scope alld iPlpac:t of elwir:.:mm"ntni effects tim! '<'<(:l.Ilcl be a ',;:"ociateci '.',m!' licell:,,,, ren8',,*'al at any nuc!ea:' DO'he! pl,:llt ~,i!8> C[1Il al~,o be found Ol: the NRC'svvelislte or;::t ,he NRC's PDR. Please submit any conm:ellts !tnt the Ullkecl'i81.l9 ~JHti:J:1 lTIay have to of'er on the ~:cc:pe of the envlrCtnn'ental r-8Vle'lN by Oc!ot:er12, 2007 \r\fritten GOI":me!:iS silouid !Je 5ublmtted by mail to trle Chie:'. Rules: ar:cl Dil'ec1ives Bra:,cr,. Divi:,ion of Administ!a:ive SerVi{:e:3, Idail Stop T*E!D59. U.S. Nt:cl8Hr F~Bgu!atcHY C:)n1rnls3i')~\, \r\/8:;h:ingtorl: DC 2G5~*5-0GO-: _ ElBctronic COff1ll1er;ts may
!Je sub'nitted to the NRC by e*':l<,::1 at Ir,(Li_~-'tI:'~)!r!t_ti_:;ifjtl[~_gs!'{ A.t tile conclUSion oi U:6 scoplr'Ll pr,xess. (fIe NRC "mff 1 :111 prep31'8 'l surmm,ry of Ii18 si>;jnilicant i:,sLle:, icien!lfie(i and the (':or!dus~m:,s reached. ~tnd tY;3~1 f: cOPY' to 'Y'Ou.
NUREG-1437, Supplement 38 E-56 December 2010 OAGI0001367E 00375
Appendix E H. V".!tl::ae8 -
"
.~!-
The staff eXp8Gt; t:) publish t~ie dmft sUiJple1:lent to 1I'le (3EIS in .Jl:iy 20[1-'3. Tf:8 NRC wiil f:old
'Jnotrle:' s*et of public meetings :n the site vicinity to soiiGii cO:,'lments on ti'I8 dmft supplerneflt;:~1 en,;ironlY:entrd il":pacl :,tdement (SEIS) A copy of tl:e dmft SEIS wiii be sent to you for your revi8w 8nd comment, .Alter considefati')n of DubHc comments reeeh;ed on the drafi, the NRC
'Nii! prepijr8 a finij: SEtS, The :%UDIlCe of a finDI SEIS for Im~:tm F(J!nti~: plal1lled Inr April 2;)08. !f you r,8e,j ac:ditiDl'lal infor,TI8tioll re~lar;:jin£1 tf:8 erl',;iror:!Tlent81 rev:e',',' proc:e":,,
Dlea:,e Gontact Ms. Jiii Cav8l'ly. Environmental Project Mana~18I', ",t 3(>, ,4: 5-\36P~1 or at Sir:cen:dy iRA Christian Jacobs for! Rani L. FI'an0Vic!1, Brancil C,'lief Env:rollmente: Bmnch B Di',/ision of License Ren8'Nfll Olf:c8 of Nuclear Reactor Regulstio'l cc See next pi3~le December 2010 E-57 NUREG-1437, Supplement 38 I OAGI0001367E 00376
Appendix E AUQLlst2"'_20D7 Hie HOilOrab!e Leo HenlY Chief TuscaI"<JrB Nation 5f.d6 VValnl0r& Ro::.")d L8\:v~51on_. Nev*,.. York -~4D92
SUBJECT:
REOUEST FOR Cm.*lr,,!ENTS CONCEF:NING THE !NDIAN POINT NUCLE.,5,R CiENER;HING UNIT NOS. 2 .AND3 LICENSE RENE\'VAL APPLICATION REv'IEIN Dei'lr Cilief Henry' HI8 U S_ Nudear Reguial')I\! C:ornf':I%IOn {NRC) I'; 'oeeklll~lll:Pllt for IT;:: elW!fiXlmental reVl8'.\f of al: applicatio!l ;I"O,-n Enler':;;y Nuclear Opefc,tlons (Entergy) for the l-er~8wal of the opefc,lin;l iic:efvoes fo,- 1I-le In::lian FOlIE Nuclear Ger:8IT:tlng Un:h No_ 2 ancl :) (lrdian FOIIlt::-. IDGatecj in 6uc!lclnm:, NY, approxilTKltei'! 24 m:les: nor;h of lhe New Yorl< City boundary line_ Indian Poifl: is in clo:,e proKilnity tD IBflcls UBt mBy tie of intere~it to ,.118 TliSCBH3rf: NatiOl'. As deSGlt;ecl below_ trl8 NRC',; "roc8';:; includes (m opportunity 'or public anc; intel"-gnvernmental part:cipation in t;-18 environn-;6nt:)~ re'~**f5'.fiJ. \r\16 V\*'flnt to enSL1re that you are ~J\*vare ot our efforts ::inc! purs!;ant to Title 10 of the Code of Federa! F:::eguifJtiOrlS ("]0 CFR) Part 51, Sec,!on S i2~;(t>:, the NRC invites ;he T1I3Gc:Wrs Ne,ti:]I' to prcvide inpcJ; to the 3Gopillg pre-c.",s" relelill,] tD tlce NRC:-s e:wiwnrnenlill rEI'iiew of tile appiicatiol'_ In 8ddi1ion,ils ouWr.e,1 in 3:3 CFR SOD_SiC)' the NRC pian:3 to .;;oord:n8te COI',p!ianCe with SectionW6 0; the National Hdoric: Preselvation Act 'Jf Eit36 t!-Irou~lh the requirement*; oi the Nation;:,: Er:vi'onmerltal Policy Act of
'19139_
Unc!..r NF:C re',;cllatior:s, the o[i').illal operating license for 8 r:uel",ar po-we: plml; i" :s'3uecl 'or up to 40 years. The l:jc.8r:se n~ay ~)e :er:6~ved for u:p to an f~ddit~op.a~ 20 years i'f ~JR.C r~equ:re:mE>r:!:; afe :ne! HI8 Gement opBrat:n~lli';e!l5-3::. fDr Indian Poin, Will expire irl Septemtler, 20-! ~1, a:1<:1 DeCernr)8r, 2015_ Entel-qy Sub'T,ittedi,s c::;.plicot:ofl for reI18;,',:[11 of ;he IndiClIl Point ope:atil1g iiGe!lse:o_ ill a Idtel dateci i\pri! 23, 2007, <1,,_ supplemented i)y lette!:, :.:lated ~"lay:3 "nd JUI'e 2:, 2007. The NRC is gat!l8ri!19information f,Jr ill: Ind:m-; Point sile-speci:'ic sup!Jlen18r11 ,Oils "Ge:,eriG Environmental Impact Ststement for License Rene'lvi:l1 of Nuc:!ei:lr F:lam,," {GElS}, NURE(~- 1437 The supplement will contain tile results; :)f ti1B rBview of tiw environmental inlpm:ts or: 1he i3rei3 slmounding the Indian F'oillt site I-elated to telTestriBI eGC::logy_ aquatic eC')!o9V, rlydro!0~JY', 8ultuf81 resources. arv::~ :;:JcioeCDJ:on~H~ j~.sues (an'K)llQ 'JtrI8rS}, Bind Vi/t:: cOI:!ain f~ reconlrr~en(j8tion regardtng t!~fB en'v':rafwnentDj aecept::'lbjHty of the ~jGense r6ne\.vnl actloll. NUREG-1437, Supplement 38 E-58 December 2010 OAGI0001367E 00377
Appendix E L HenlY To 8ccornmoda~8int8res!ed members of the publiC, tl:s NRC ,vii' r,old IIII'D plI!Jlic "coping fIlee!il1',!" 'or the Indi811 Poir.! licen'>8 rene'Nul supplement to !he GElS ')!"\ VVednesclil'y, Sepl8mber Hi. 2007, a: TI"18 COionial TerPJce. I"cated ati19 Or"g:)n Road in CortlWKH M21l0r, NY. The first 5£>"sion will GOllvsne a: .: :30 p.m. >:irKl will continue lB,td 4:30 Ic.IT*. , as nece:3*,;ary. The :3ec.o!1d 5e:3sior. Wi!! convene OJt 7:0;) D.I1:., wIth 13 repe",t of tl-.s CiV8!vie'N port:o!":; of ths I11S8tll"9. and w:11 continu8 ur:ti'IO:OO p.ln. "" nec83sa,*y'. Additionally. the Np.e staff ,,,,'IIII,os\ wlfornl2i dlSGl.iS~ilOns one !'"IOlll" i:;sfor£> a"l£> start of ead: sessioll. TI",e iicense renewai <lpp:ic<ltion {LRA} is oub:icly avaii<lble at li,e NRC Ptlb:ic [10('.I.11:18nl Room (PDR). Icc<l!ed at On 'W!l"<?- Fli!,t Nmth .. I*IS5S RockVille Pike, Rockville, t-Jarylmxl 20852, en from ti,e NRCs Agencyw:[je Documents J\cces:; s!1(1 rv%rlll~;emenl System (p..DAf*.**1S) Tile
.ADi'I.HS Public Ei&C!l"OfI!c R<?-mlil'g Room is acce:;c;:ble 8t l~:ttt::r,;:*[:;=:a(:l*~.\,\o'&:,).3e[~f0::-:.r::'c.{K:**/"':jQt:)q~n i-:H~:. T~fe accBss~0n nunlber ::Jr the LR.A fS
!\'llOT!2W5G7. Persons; \:'./110 do pot hwe accs;;:; te, ADf\t*,'IS. or ',','1-10 enCDI~:lter proDI:lls in acce:,,:3:ng tile cloeuments iO(::::Ile(! in .A.DAJ.:1S. srlDuld con!ae! H,e NRC's PDR Reference :3ta:'f tly t.e~eph\.lne ;at {?,OO-'397 -4209 or 30'~ -415-4737, or by e-!Tla~: ,tlt ~:::{:_~J~~f::.~~~"{t~:>~
The Ind:all Point LRA. is 81so d'failsble on the In18m8t 'Jt L~tl~"'::'i:""*~';J]3~'~'D;)"',*;:l:~",t'::\:~1S:~t.'(":",~li'j.\.:il['-"f::]""JH'i:t';::J-';"*'Y"0.~::'"i)jJ'ii'~:']t:JJJ':~j3":,.Jl*l:Ll2:::1HLi!Lt'i in add:!io". tile Hendrick Hucl:;on Free Library, located in ~vlontrc;s"l. NY the Fiel::! Library locat"ld in Pee"""kil'. NV. [,I'd the \,-Vhite F'i<lillS Pub I", Library ,oeal,;:} in i/llhit: Plrlins. NY !"Iave agreed to ,,'ake tfle LP.A ",'iallable for ,"Ullilc i:lSP8dlOll The ;3EIS. whicb doctimems me NRC's a.ssessr:,ent of tile SCO~;8 arid :lTIpuct of BI:vironmenta.i
~ffect~; thot v~~ou;d be assDciated v-fiH: ::cense renevvil! a~ 8ny nuc:eilr ;,10\';\"9:- ):dB:nt .s~tEL car: also be foune! or. ;he NHC's 'wbsite or "llthe NF~C'3 F'DR Please :3ui:>ITlit <liT)' comments thm the TllSCafCra NatiQ!' rnay have !C offer on ;he :;Gope of the env~rOnE1erl~i:d rEnt~e~'i/ by October fl . 2D07 V'./ritter! GCIT!men~s shouid be subrn~!te(l by EVJ:I tD t!18 Chief, R:118S [,nd Dil"ecllv"s Braner.. Di'iis:ol1 of Jl.dn-,inist:'ali*. . 8 Ser';ices. P. .h"l:' Stop T"605':1 US. NI~GI£><lI" Regula!")!"Y Commi%ion, vV[lShil'gton DC 2;)555"0;)01 Eledrc,niG c.O!llI-r.enl:, rnay t:e sclbrnitted t') the NRC: by e"'1"!ail at JJ}-'),,:,;,e~.:'inr::j::;;,'l::J!.(~.::!r.~~*:. At tile CCrleiU3 iOIl of tile 5copin';; proce";3. me NRC staff wil! preparE' a summary' of ~he ',i91lliiGant issues identified and the {~or:clus~or:s reache*j; ;:!n{! £:1fl:l Z: copy to YDU.
December 2010 E-59 NUREG-1437, Supplement 38 OAGI0001367E 00378
Appendix E L Henry TrIB staff expect:3 10 pui)!!s!: It1+" draft :3upple!Tlent to the GElS incli;:y 20GB. Tile NRC wiil hoi;j anOlher set cf put}lic meetinr,J',!n Hle site 'IiGin:ty to soliei; comments on the draft sllpplernem.al envlwflmenl<ll impact sta!mnent (SEIS) . .A. copy of lI:e ;j:'aft SEIS '8::: t,e sent to you for your reViB'N (lI:d com:118r:t. ,A.ftef Gon'3i(j8fation of Dublic carnmBnts rec:eived 0:, !.he <:il'aft, the NR.C
'"iiii prepme a finei SEIS. Tile is:3Um<ee 0: (, fi:,al SEiS fo,- In*jian Pamt j~, ,-,ian ned for A.pr:' 2009. If you nE:8d aclclitiom::i infofnl<:;ion regardlri'J !I:e envimwl1&nllli :'8\,':ew process pI8;J:3e contact i~*ls, Jill Caverl,,!'; En"iironm&ntal Pl'Oject f'.:lanag&r, at 30i -4: 5-6i39;~' ar ai Silleerely .
.iRA Christian Jacobs for/
Ran: l. Fr8novic!'I. Bmnch Crlief Environn,enli:1i Bfi3r1ch B Division Df Licen,=,e Renewal Office of Nuc!em Reactor Regulatio!l Docket Nos. 50-247 and 50-286 ec: See next page DISTRIBUTION See l:exl page I NUREG-1437, Supplement 38 E-60 December 2010 OAGI0001367E 00379
Appendix E AlJgust 2~, 2007 The HonQrable R098!' Hi::' C!l:ef TOI:aw::m::!a Band of Sellecf:5 7027 rVleadvi!le Road Bason, Ne\'v York ':"'0'13
SUBJECT:
REOUEST FOR COMHE~JTS CON!~ERNING THE INDLAN P()INT NUCLEAR C3ENERiHING UNiT NOS, 2 AND::; LICENSE RE~~E\;"iAL APPLICATION REVIEW Deal' C'lief Hill Fie US, NlJdem Re"ulatolj Commission {NRC} IS; seekil'g input for it'> epvironmentai review of 81: [Ipplicaci')n 'rom Entergy Nuc:em Operatio£l'3 (Emr~lY) for ;he rellVifal of Ihe operating license::; fo:' ,he indian Point Nuclear Genen,:t:ng Units No, ::: and :5 (Indi'Jn Point}, locatecl in Buchanm:, N'{, appwxin'ate!y 24 mile3 north of the ~~e,v Yuri<. CityiJolB,dary line, Indian F'oi:lt
- s II: dose proxwnlly to 1;l')(i:3 ,i',;:,l '",av bE' of Ime:est to !tIe T')na'ivancia oc:nel of Senecas, p,s described b8Im" the NRCs proces:"inc!t;d8S a!~ c:pporUnity for Gut;:ic and inter-govemmenta:
partiGipatlDrt in tr12 er:\(,lronn:enta: feviE'V_ \Ne \l'vant ro e!l~~ure that ~lOt: fIre EH:var8 of n:'lf e:'fOliE: anci, PlllSI,;;lnt to Titl", '10 ofn,e Cc(ie cfFedrc!',,,!Rrc,}u.iai1ofls (ID CFR) Pod 51, Sectton :5: .26{b}, the NRC m"',lites the TonaviI'anda B~Hld of SeneCftS to provide input to t!~fe Elccmll'~i pm<;ess rel8tmg to tile NRC's elwironmer:tal reVIE"~", 0;' tr:e application In mjdltioll, [IS out::ned ill 36 eFR 800,3(c), t:'18 NRC plans 10 coordiPJle complidflce with S8c{ior* '1 D,~ of the Natiow3: Hi:,.\oriG Preser','atioll Ad of 19fji} lhol;gll tile requirement" cof lbe NaliQrlill Erwiwnmentai Po:icy ,A,ct of : !~i3g Under NRC requlellol:s, tI:8 or:ginal ,)p8!"atllll~ llcense fo:' il r:ucleal' pU'Ne:' plant is i',sueo::! for up to 40 yearc:, The licer:se may be renewed fOl' up Iu em addi!!on81 20 year-; if NRC I'eciuiremenh are met. Ti,e current operatinp licenses for Incli<111 Poio1 \ltd I exp:I'e :n September, 2013, and December, 2015, Entel{IY submitted its ,3pp!;cal:on for renew[,; 0; the Indif,!) Po:nl opep:lting iicenses in a letter CifltE'd A!)ri: 23, 2007, 8:S c.,lpplemented e,y letters :jam," M;JY 2- nml
.Jtlne 2':, 20Cl7 T",e NHCi's galher:n[JinforlTlation for ,.r. In::l:al" F'oin; s:le-s;=,eeific supple:nem t(1 ::s "Generic Environmentallmpad. Stillen:ent for Ucense Rene'Nu: of Nuclem Plants" {GElS),
NUREG-'1437 The ~;I~pp:elTlent wi!! cnntzil!l the re5ults Df tile reviev*/ of thO) environmedal impacts 01: lhe ar8a surPJunding the il:dl[:n PoiJ:t ",ite relnl8'j ,0 tHreslnai ecology, aquatic ec~)~og'~'l- hydrology, L~JltUL31 reSO~lrGeS_ and ::;.:)dDeCtH"!ornic is:;uE:<:3 (fl(i{Ci!l(J others}, B:nd v~fiH cDI:tain a recornmendatiofl regaf~jing 1he en~l!rOfWnen~ft: fiGceptab:::iy of the lic&r1':.e rene'vvt:! action. December 2010 E-61 NUREG-1437, Supplement 38 OAGI0001367E 00380
Appendix E RHil1 To ~cco'Tlmo(jaieinterestec! members of the publiC, tl:8 NRC ,viI' I"-,okl t'II.',) pU!Jlic :,,(:O:}in~1 fIleetin',is 'or the Indian POIr,; license 1'81'18".\'31 supplement to ;he GElS on \/ifednescl8'y'. Sepiel1'ber '19,2007, <it TI18 Colonial TerPJce, 1(lcated at '119 Oreg(ln Rna"1 inl=ortlandt fv1zmo,', NY, The first s9:osiol'; will convene at '! :30 P In, and wlil continue lB,td 4<,0 lo,Il;" as nece:;C;;}f).', The second ,;e:;:;ior, wi!! convene OJt 7:00 Dm" w,th 13 [e;:le3t of (toe oV8rvie:II" p'Jrtlons of the meetmg, and 'iN:11 continue ur:ti'IO:OO p,m" as necBssnr'y', A(j(iiilo:',all'y', thE' NRC
',18ff >'IIIII1OSi Infornl~1 :j1SGtl5SIOns one !"Iolll'l:;8fore a'ie start of eaGf: :;e',siol1, Pie license ren8wa, application (LRA} is ::Jub:icly available <it ;"e ~~RC Public DOGul',:"mt Room (PDR), iGcated alOne 'NlHe Fli!,t Nor~h,I'155S R':>ckvllie Pike, Rockville, t','lal).'i8l,ej 20352, ,)1' from ti18 NRCs A,genc,!w l [)8 DOc'JIT:8nts J\CC8S:; 2nd rv'I"rlll~;emenl System (,11..0,6&",15 i Tile AD.t.,MS Public Elec!iofl!c Rem!i!'g Room is acc:e%:ble at http /:2:;:ia:'-;l~.V:... ~:::;.~:e~~f;:)':.r;:'(;.{:(:\l"':jo~:)q~n i-:H~:. T~fe accession nunlbsT :01' the LR.A is
!dL07'12'W5GT P8l'sons; 'Nha do 1"01 hwe accss:; to ADf\t';lS, or 'who 8IK.o!;:1ter proDle:lls;n aCJ~e'3s:n~1 nle c:loGul1'ents locate::! in ,ADA,r...:IS. srIDul::1 cOI,lncl lile NRC:3 "'DR Reference ,,,taff by telephone nt '1-800-'3f~7 -4209 or 30'~ -4 '15-4 737, or by e-!TI<.:1~! ,3t ~:{tC~i'nG~"gQ>~
T~le Indian Point LRA is ,,:so dvailable on the Int8met 'J, i!LU~E"i:'\'vY,J'3::;,D;;:~',';I:~"t'~\:JLS::J))H:,,~li'j~:il[;;c';::],"JJ.['i!J-';::J-';:'Y,0.U,i)jJ~::'~:'].t.:,\iE~'J3,:,:Jl~"!:J~:::jJ.,Li!,~mi In f]ck,itio'l, tile Hendriel, Hudson Free library, located in ~':Ionlrc;se, NY, the Fiel::! L:bmry locmed
- n Peei',skill,. NY, tind the V'il'iile P'lClillS Publ:c Library iocat8d In 'v'llhite Plmns. NV' ~laV8 <,greed to make ti,e LRA z,vallable for ;)lIl):IC Inspedioll T~le GElS, Wllid, documents me NRC's ass8ssr:lent of tile scope and :mpact of el:'.,.'irQnment211 effects th8t would be assudated v-jith ::cenSe renevv;:l! at 8n~...' nuclear pO\i\ler ~dant site car: also t:e found on ;he NRCs ""iebsite or flllhe NF~C'3 F'DR Plea"e SlJ!)IYlil any comments Ihm the T L,nm'if:!,d8 Band of Se!'eC<I'; may h8ve to offer on the 3C{>pe of the en'v'ir{mE;entf~: f8'lie'l,t;/ try C~ct.)ber ": 2,2[107. \\1rittBri con~!T~ent~3 sho:Jk:J be stlbnlitted by mail to the Chief Rules and Directives Branch, D'\IISiol1 01 Adn"nistrat:v8 Service", rvla:1 StqJ T-6D5~;, US, NuGiedr Re"iuI8!0f).' Co,-,-,mi:,-:,icm, \N83hinplon DC 2055::'-
OClOI, Electronic GOIT::llenis may t'e submitted t') the NRC bye-mail at lL;~,~'!!::?2tllf~;~<;@!::E,,';I;>*,., At 11:8 conciu,ion Of the sGoping proce35, ,rle NRC staff will pl'8pme a Sl:mmm-y c:f tile significzmt :s~,ue',; Identified ,:l1d tile cGnclus!on:; l'eaei1eC!, ar,;j mail a cop,,' to yOu. NUREG-1437, Supplement 38 E-62 December 2010 OAGI0001367E 00381
Appendix E R. Hilt T~H SIflfi exPEct:, to putliis!: thE dmft sUDplelTIent to i~le (3EIS in JI.::Y 2008. The NRC wiil hold anolrler :3et of pu!::lie [::Eetings i!1 tile site vid!':I!Y to c;c;iiciI C:O:TI£nEnls or: 1I-le clraft sllppler:lem.,'! environment,,:: imp8ct staten:ent (SEIS). ,A, copV of the cifflft SEIS '8W t:<e sent to you for your
!'eVieW 8ncl comment After' con~,idefati,):1 of pul):ic cGmments received on tile ::trail, the NR,C
\'I.'j;i prepa:'e ::: fina: SEIS, Tt-,e issuance of f, final SEIS fOf Iw::ian POi!lti~, pt<lrIl:ed for April 200~~'1 If you r~eed additionel infolT:)elioll l-e'FmHn~, tile eflviw!:mefll.al review process ple0se contact ~,-Js;, Jill CElv&rl\( Environmental Pr-oject Mi'lnil<]er, at 30': -4', ':>-61399 or ai Sil:c:erE!Y, iRA Christian Jacobs for/
Rml: L, Fr'ilnovlc:',. Broncrl Chief Envirc:;mnentfl: Bmnch B DivisiDn of License Renewal Off:G8 of ~Jucle(,r Reactor Regulatio!l Docket Nos, 50-247 ar:d :50-286 cc: See next page December 2010 E-63 NUREG-1437, Supplement 38 I OAGI0001367E 00382
Appendix E AlJgust 2~. 2007 Ivls. Sherry White Tribal HistDriG Pre",ervaticlfl Officer StoGkblidg8-Mun,:ee Comml:nity Bano of
,'vlol",ican Indi"mc:
~~V't34.:t7 Call1p '~4 Road Bowler, V\I'I 544 ! i3 SUBJECT REOUEST FOR Cm.,H,,'lENTS CO~lCERNING THE INDIAN PDINT NUCLEAR (3ENEF!.fHING UNIT NOS, 2 AND '3 LICENSE RE~JE'NAL iWPLlC,l\TION REVIEV/
Trle U S Nuclear Rer;luialory Cornmission {NRC} is seBkil:Q input for its 81:vironmental review oi ar: application ~r,):11 Emer'Tl Nucle.ar Opemt!cns {Entergyl fm the re.newal of lhe opemtmg
;,censes for Ilw Incllan FOlfit NJclear Gel'erst:ng Un:! Nos, 2 and 3 dndl8n FOlflI), loc[,te:j ,n BUGh<,nm:, NY, aporo:,xin,<,tely 24 n:de~: north rA ,he New '1'01'1" City bOUl:da:"y' lin8, Indian P:)i~lt is if: ck)s pro;<~f11ity tD ~B:-~tj:3 trlat i:E1~l t~e af wlte:Bst to tf:6 StDcl\:=:'ri~jge-~o!lunse9 Corr-::Tlur::ty Bm:cI of rvlorlican Inti:an'; A:o de:;crib",c; below, the NRC':; prOC")?SS :ncludes iJn opportun:ty for pub::G nnd inter-gcp..;'e:Twnenta! pB:rtk;:ipf~tj0r~ In the env:~-ol:(n8ntal rS',.,':ev*(. VVe 'wnnt to en:3UfS tllat vou me lrware of our ellon:, alE:, pl.:rs.u8nt to Tltle Ie of tile Co(ll'! ,)[ FB{iemi FieQuiar.roi?:,
no CFR) Pmt :°,'1, Secl:on 5I,2S(b). ;he ~JRC :IW:t8'; the SloGkbr:dge-r'..'lur:see Community Band 0; fvlohiccmlnd:all:3 to ,}rovi(;e illput to the SGOpilig process rela~ir:g ~:) the NRC's eIWif'On:ne!ltal
!'el/ie'"," of tl-Ie appiic<,iiof": In Hcj,jilion, as Gl.:tlinedin 36 CFR 8008iC), the NRC p ii3IlS to coordinate [ornpl:"l'Ic6 '1'1:;1: S6Gii;)~-1 '1013 of the Nallon,,1 H:sto;-ic FIFser:,ration A,c; of ': 96fl tllrougrl H'le req!;iI'<2menh of tile Natioll:::i Envirolml81'tal POliCY Ad oi IPfJf',
Und",r NRC rergulaiions, tlce or:glnal (1)8:'alil<l;1 license fo!' a nuclear power pl[:ntis issue,! for up t,;) 4(J year~)" The t:icr!se n18Y t:e rer:e"'.!\id f,;x up to an r:c1dit:Qnal 20 years if NRC re(::'Hfeflle:1ts al'8 1T18t Trle current opemting licenses for Indian F'oinl will exp:re :1'1 SeptemtlH, 20 D, anlj Decem!:!e!',20'15, Enlel-gy SUb'T,itt8d I;S a:Jplicatiol1 for I'enel;\lal oi tl:e h:dia:l POint opel'ating I'(:el]:,e::; in a letter datecl ,A,prll 23, 2007,13:> 5upplemente;:j by letter:3 ::iatec: 1:,1ay 3 and clune 21, 2087. T~le NRCi" gather:n9infofll1ation for Ell' Ind:an F'oint S!;8-s:)ecific supple:TIent to its "Generic Efwiwnrnentsilmpact Sta.ien'ent for L:ce:)se Renewa: of Nuclear Flcmts" {(3EIS), NUREG-1437 The ',Lipplement will contain the 1'8',ults: of Ihe revie',,,, of the e:wimnm8r:tal impacts or: Ihe Or8'J 3llITC<1.:mjing the ll,cll<lrl Foi!'t site I'elme::! 10 telT8stmli ecology, 'Jqu',dic ecology, 1-lydroio'JY, 8ultuml resources, and sOG:oecof:omic issues (a:':-,onp oth8:'s\, endwiii cQI:tt3ir:: a reC~):11IT:endatiol1 re-gan::1n~] t!1 E:-nV~rnnnlent<j; t3cCeptabiHty of the license rene"Nr:~ action. NUREG-1437, Supplement 38 E-64 December 2010 OAGI0001367E 00383
Appendix E To f:ccDmmo(lmBlmereste(! mrr:t=er:,; of tile pU!)!:G, t!: NRC w!!i Iwcl tW{) plJ')IIC SCOp!n~1 meetin.;;> for the Indian Poil:: license renewf:i supple:Tlent to the c;EIS on V\:'erines:day, Sepien:!jer j~~. 2007, at TilE: Colonial Terrace. 'ocated all E; Ol'egon RO'3d inCor!li3nd!
!,':!anm. f>lY TI'e fir,t session 'Nill convene [l" :30 p.IY' and '.'",iil continuE' IJlltil 4 30 pm. as necessary', The scDnd :)*85sior~ '~Vj:t convene l"lt 7:00 p.rt:., "\Nith a repeat of ti:8 0v8rviel;'v port:of:s of tile meeting. !3n,j wil: coritmue uf:t!i 'IOClfj p.m, a~, neces5.ar",. Adc:li!iO!wlly, U:e NRC
'stafi willlw,,! inform",1 dic:cussion" one hour before :he ,tor! ,,:.I each se3sion.
The iicense re'lewal ap;:;licmiofi (LRA) '3 publicly avai:abie ilt the NRC Public Document RO')IT, {PDR). ,oGflled at One ~'Vilite Flin; Nortl':.11S55 Rockvi:le Pike, Rockv:!le, r',;larvl;",lxi 20852, or from tDe NRC's ,I\~le:[cywic! DociJments Acce% 2!ld P"li31l8';!emrit System \i~DM-,lS). The AD,IlJAS Pubiic EI8CtrofliC Radll:g Room is accessible at htlI~,,~{~L*_~£:~!JJ_:~~i~~~tL~_~.'}~~:;t*~~~L:'~~..;..~~ .. ~:J:X~~.~~:3~~.:~L::!:~Jt~. J~iJJJ. T he a cee 53 ~ 0 I;: !ll: :Tl be r fo r trl8 LRA fS MlD712'i05G7. F'el"sol',s 'Nil:) do not have access to ,,,-DAr',,,lS or who encounter problems in aCGw,sinQ the dDGUlT:enl~, ioGt"lted in ,AD,AtdS. should cm:tfiG! t~ie NRC's PDR Reierellce staff by teI8;Jh'x! ;Jt 'l-oOO-?,97 -421]9 or ~<OI-4 15-4737, 01" iN e-lTIs:i fit DQcil"-:'*L~.!;:::i-". The IElij:an POint LRJI, is flt;:J i3vwl:C:Dle on 11'113 Imemet at hHp: /:.~\I,/,,,...:\~.:. nr:;. Ck"':\/;*:r .;.?aDu::rs.:'::p£~ :';)~! i~(l d: :'";S' !,:":?j~'::J;re n".?*'(\:aL. . ~~,::::::) :f.:[~\::(:,:..;.::~/: :~:d:Sq--C:iJ::~':t. :1~t..;:: In add:iio!l, n,e Hendnc!\ Huels,):) F:-ee lil;ml"y', located in "./Iontrose, NY, !I-Ie Fie:(j Lil)rary 10(oflte(! in Peekskill, NV, and the \,Vhite Plain:'; Public Lit'mryloca;ed in '/ihite Plains. NY, have 2!preed 10 I:'flke tile LRA ;"wailable for public inspectioll. The GElS, INhid! ClCC,mWri!S t~le NRC,. asswosrnenl of the sc.ope c:nej impact of ellviromnsntai effects lilal ,vouid bE: a<;soclated witl: licen<;e renewal at [Iny :luciear power plant slle. ean also be found 'In ihe NRC's \uebs.ite Of at ihe NRC's PDR Plea'3e SllblTllI any cmTllllents tim! Ihe Stockbridge-!',.:llJl:se Community B"nd of !dohic,ln Indians mtlY Ili3ve;0 offer 011 tilE: scope oi tl:8 en'li!'Of':!118111al rev:8w by OctGber' 12, 2U07. V',/riUen cornmenls srIGul(:l b8 sui)ITlltt8(1 i)V enall to II:e Cillef, Rl:ie~: one! Dlrecl!'/8:; Beimerl. Div:sion of Admit:istm:ive Service3, t',;lail Stop T-6D5(;, US. Nuclear Reguifltory Commi,,:siol'l, VV[J:,llin,!!on D. C. 20555-000',. Elec!rof:ic cemment" may t,e :"ulvT,ilted to \rIB NRC t,y e-Il:ail [J! I.n.'~:"'-;.;)~li:.ltr::.:'~~,~::.:r.{;g',*:*,:- At the conclusion of the scoping VOCElSS, the NRC sta;f ';'1:lI prepare i3 summary COT tile significfillt :";"'lIes :::ientifiE:d wld Ine co!'cil.lslow;' r8f1c!le<:l. and Inail i3 copy to you. December 2010 E-65 NUREG-1437, Supplement 38 OAGI0001367E 00384
Appendix E S VVhite Trle s;h:,ff expects to pul)i;si: tile cil-aft supp!e::'lenl to tile CiEIS in ,JUly 2008. Tr:e NRC w::lllol::1 anoH-!er :3el 0: public nleeti!lgsin the site vicin:!\, to solicit comments Oil !ile draft :3upplernental environmental impact sl::]temenl {SEIS). A copy Df tI:e (i:-a:t SEIS "'!iii be sent to you for your re,'iBw ilI:d comment After consi(jePJtion of public CQI:;'1lents received :)n the draft, the NRC INiH prepme ;:> final SEIS. TI"" issuance 0' <OJ final SEIS for Indian Point j~; plalliled fnr Apr:: 20(1'1 If ),0,1 need ack!itionai inf:xmaiiol1 I"8gsr::ling the 8!Wlror:me!l!al rev:s',\-' proces,~, please con1net ;:vls, Jill C'3',;erly. Environmental F'rojec; [Vlanagel', at 3(>; -4i 5-\36P~1 or at 1'*,,::::-c1),'::,::.(uv. Sincerely, iRA Christian Jacobs for! Rani L. Fran0Vic!1, Branch Cnief Enviromnenl2! Bmnct-! B Division of Lieel'lss Rene'Nal Office of Nuclear Reador Regulation Docket No~" 50-2~7 lmd '5Q-~8e GC See n8X1 page I NUREG-1437, Supplement 38 E-66 December 2010 OAGI0001367E 00385
Appendix E AlJgust 2~. 2007 f'*,'lr Ke:) Jock Councl: r,,'lemt,er SL Re~li'; r,,'lohawk Tribal Council 4 12 SWle Route :37 A.k\.ves3~;ne, NY 13f.i55 SUBJECT REQUEST FOR Cm.*ir"IENTS CmJCERNING THE INDIAN POINT NUCLEAR (;ENERiHING UN!T NOS 2 .AND " LlCEt..JSE RENEVV.AL APPLICATION RE\iIE',~! Deal' f',:ll' ,JocK: Th", U,S, NI"dear Regul"toIY Cornrni'3,;iorl {NRC) is ,;eekil:g input for its elwlronment81 review of ,m ap:Jlication from Entergy Nuc:ear Open"liOIl'S (Efltergy} fm the rel,ewal of tile operating liGen';",,,, fQ:'lhe Indian Point Nuclear Ger:en:ting Unit Nos, 2 and ;3 :;Indian POi:)l:, IOGGled in Blxiln"I3l:. NY, appro)(lmately 24 mdes north of trle Ne1o/ York City t}(JuJ;<:lmv 11,'le. Ind:an F'olnl I:; in close proximity to 13nds: that I1:sy be of intere;;t to the St. Regi", f,;1ohswk Tribsl Counc.ii. A'S de:icrii:>Ed i:ielow, tile NRC':, iJroGe,>':;i!ldl~d8S af: GPPGrtunity ~or pul;':ic iHI,j inter'goV8! nmerl131 p::Ht:cipf"ition in trl8 enVin)rHr:~ntf~: revie.j.J_ V'Je \~.'8nt to en~;Ufe that Vau Dra ~1\;'I. . ar8 Q~ O~H" effolis. and, purst;::tnt to TjUe -jO of the C:c;de c;,f Federfrf Re~}{f;fJtio,'?D (iD CFR) Pf~rt 51 > Secr:on :::. 122;ic,:, Ine NRC Ilwiles ;l:e 31. Re(l's MotliW:k Tl'!t)J: CouncIl tD 11(o'.;:(!8 Input to !I'l8 s:Gopill~j proces:s l'!'iial:ng to tile NRC's: elwironment,]1 rev:iew 0' the "pplication. In sdditioll, as outiined ill 36 CFR aoo.e.(C), t!18 NRC plans to cao:dip:tte complinnce 'NIH'I SedlO!' '106 of tile Natiolla: HistDne Preservatioll Ad of '196i3 t!:i'ol.:gil ti'I8 requirementci Gf the Na;innClI Envtronly~ent5; Po:icy .A,ct of '!E1-!J9. Under NF::C; rg*,jUICltiof:S. the (>fii~inal ')pe r atil1g licEllse for a r:uclear pm'ver plant is i%ued for up to 4(: year",. Tlce license 11'8)' iJe !'e!:ewe:j for'up 10 'In ad(!itional 20 '113m'S if NR'=* rW-iuirements i3re :'net The GUfI'ent c,peratill'~llicE>nses for Indian F'oin! w,ll expire in S&pteITIi:>el', 2013, and [lec8ms*er, 2015. EntelIIY sut"]',itted ils i:lpplic-01:on for I'enewa! (of II:e in<:lian F'o:nt operating licenses in a I",Her (k,ted .A.r}rii 23, 2007, a:,silpplemented bV letters dated f1lhly ~) <'nel
,JlB:e :2 : . 2D07 Th9 NRC is gat!leringinform8tion for ai' In(jim, F'oint Si:8-Sp<?cilIC s'-lppI9mefl~ to i~:s "Generic Erwirolll'nent:,,:llmpad St8tement for Lic.en:;", Rene'NElI of NuciBm Plants' (CjEIS::*,
NUREC-i-!.:)37 The suppielT:ent \lvi!: contsin the results of the revi",,,;, of the emiiwllInsl:tai irnpm:ts or: the area sUiTOunding the il:ckm Poir:! site t'I"lmeG lo telTe",lrial 8cobgy. aqualic: ec*:)!ogy, hydrohJ{fY'1 G\.dtLHBl :esourCE:s. an~j s:JG~Crec:Jl:onl;c ,issues (a~;no!1g o!hers}. t:nd V'-Jlll cD!:tain " reCO'llmenrjfltion reg "Wing t!18 environment.:,: aGcept8bil,ty Ol the licen'Se rene,;:,,,,1
!3Ghon.
December 2010 E-67 NUREG-1437, Supplement 38 OAGI0001367E 00386
Appendix E K. ,Jock To accommcda!e interesteci mE'mber,; of the publ:c, tile NRC wi!: h,)ld tw') public ',cc'pln9
- 118e;inQs for t!-Ie Indian Point !icen'Se renew';;:: I SlJppl"f',ent to the (,EIS on Wednesday Sep!8rnbe:-19. 20G7, f:; Hie Co,oniz,1 T81T8C8, located at,I9 Ore gO!' R.oad in Cortlanat r',bnor, NY. Th8 firs: :;essiol1 'Nill com*'ene at: ::30 p.m. Bnd w:11 continue lB:t:l 4:.30 p.m., as n8cessary. Th8 sE:-cond sess:on ).\'1:: C()rlvene t"lt 7:00 p'.rn.; 'N:tll 0 rep8<.:t of t:r.e oven."~ew l)orticns of tlw nleetill9, ana Wi!: continue until '1O:0iJ p.m., JS ne(:e~,s8:y ,A.dc::t:Qnally, the NRC stuff \i'.*'ill h0:3~ inforrnai dtSCU3sions one hour t~efore nie stDr~ of Bact': session.
Tne licel1',",( refl8\'vai (lpp,icatiDn (LRo,) is DutiiiCly JV(,il(IIJie ,:t trle NRC PutiiiC DoclH::enl RooiTI
'PDR,L loc9ied at On.::. Whit.::. Flint NOlih,1 *1555 Rockv:lle Pike, Rockville, Ml1I"ylm:d 208:°,2,..J!"
frm" tile NRC., A,gencywide Dowment" Acces:3 and tdarmgement Sys;em (ADP.fv*IS) Tile
,A.DM,;,lS P,lbic E,edwnic ReEding ROGm is 3ccessltde at
.'_("J.J:':H-'-'}'-'.'_:_":i!}':)~!;]_'}:*i.J,--:-:,,-;._~p';i((:_,_,)",:",_..':r:,-,.'.. Tne accessiOl: rlLJrntJer- ;01' lI-le LR.A i:,
P,'lL07'i 2*1(1507. Persons '"<;'~IO do I:Gt have w::cess to A.DAt,,"1S, or 'who eneol:nter problems. in acc6s5in~: the documents located in ,A.DA.MS_ s,lould c:Jlltact lhe NRC's PDR F:eferen(:e staif ,::v telephone at cl-800-:3:?'? -420:?, (if" 3D"; -..:lIS-47 3.7; or by e-n-Ia~~ ~t ~_~JJr£~1}H~~_.:j;.:1:~~:{, The IndlJn Point LRA IS also available on the Internet m
.'.ltt;,';:L)(5):*'1:_'-JH:,_>j'X,,~:r':,*;,(J,}c:':!'}U':j::£;i,-j'Ji[l~"'!jj_:~;:n!j_!~j,X'h,i:<jr'l~i~<lJj'~£!~:':JL'J;il*',~j:J!,:_~jJ:UjJj.r,i _ in a(i(jitioll, tl,,, Hen(jrick Hudson Free Libmry. located if' tJontl'Ose, NY, niB Field l:brm'y', located
- n Peekskill, NY, m,d the \Vhite Piall'3 P,lbl:c L:bfi3r-y iecale'; :n VVh:t8 P!8in:;, NY. !lave i39reecl to make the lRi'\ available for ;:;ubiic :nspec!io!:
The GElS, w!-lieh GocwTI'3nl5 the NHC's as:,e,;c;n',tmt of tile sume and impact of er,viwnlnen!a, effects that 'NolJlc! be assoc:ated witlllicense renewal ;Jt any nuclear powe, pl;:m; ,,:te. car, ol"G be fOllnd Of" the NRC'S 'N8b::;:;e or st n,e NRCs PDR. Please sub:]",t any CO'T,f]"ents thai the St Re',lis f',Aohm'ik Tribai COllne,1 mav have 10 offer on the scope of ~:'-Ie 8nV1rOrtrrlEwlta~ r8v~e\"v by* ()cto!:;;er "12: 2007 VVrittefl GOrnnlsnts Sh:)d~d be subrnit1ec! by mail to 11":8 Chief. Rule~3 <trl'3 Directives 6wncll. 0:\/:,,1011 of i'\::!m:nistrat"'i8 Services. Mail Slop T -f;O ':,9 , U.S_ NucleCi'- Reg:Jla1ory Cor:,mission, vV8sh:n9ton DC 2{1::,5:5-OOij j E!ectron:c commet:ts may be s:lJi:;rrlitted to the NHC by e-mi3:1 at
!f!'J}_'H!f:>!!:.I[:;J~_QT:'L';!';;!.- At the cOl1ciw"iol1 0; the :3COpin9 proces,;, ,he NRC 3laf; *",<,*ill prepare a sUITlmarv of tl,e s:';lmflei'll:t issues identified and tile conclus:olls reaCilEfG. al"d 11'<111 a copy to you.
NUREG-1437, Supplement 38 E-68 December 2010 OAGI0001367E 00387
Appendix E K. Jock Hie st8ff e:<:pecb 10 ;:!ubHst: Itle draft ;;upple:Tlent 10 ,he GElS in ,Iuiy 2008.. The NR.c wi!! hol!:j 8no,hef set co' put;lic meeti:1Qsill (:I',e site vicinity to solie;; comments on the dl-aft sllpple:T,emai environmental imp<,,~t statement tSEIS). ,ti,. copy of tl'e ,:;:-8'( SEIS wiil be sent to you for your rev ie,\, twd COI'::ller~t. ,"',fter cOfl<;ideration of public cGI'-::T18rJi<; received on the dl-flf!, the NRC "NiH prepere a fined SEIS. TI-Ie i5Sum<ee of " fin*al SEIS for Indifln Pomt is plflnned for-
,A,pril 200!~'. If you nee'j aclclitio[1[:i inform[:tion regardm:J U:G eflVil"Ol:mefllal review process, plecls8 GCl'ltact ;:Vls. J:II Caverly, Environmenlal Pn)jeet Fdanager, aI301-4:5-f,69fl or til IRA Christian Jacobs for/
R;:;ni L. Fmnovlci-L Brandl Crlief Env:I-omnental Branch B Division ,)f License Flenewal ()ffice of N~.lci6m R8f1ctcw Regulation Docket NuS. ::'0-247 and ':,0-286 cc: See next pa~le December 2010 E-69 NUREG-1437, Supplement 38 I OAGI0001367E 00388
Appendix E Delaware Nation Rllvu-onmental programs PO Box HZ5 JJ - An;Hhrko, OK 73005 ~ C~~i
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- ,.....) --s September S, 200'1 OS. Nuclea~ Reglllatotl' Commission Chief QJ Rule. a~d Directives Brandl Divisioll of Admil1il;!rntivc &n:i=
M3il Stoll T --6D5<) W;i~hingt01', D,C. 21)S55-l)()() I Dcar Sir: 1 :utI writing ill regard 10 yOUf.*kll<f mitt!<! August 24, LOIn reque,ling oomJl,ents cOJ'~rning the 11ldian P<lint NlIdaar GlllJemting tJliiI N()S, 2 ;ind 1 Hcens-e rell~wal appliciltion 'review. As mcntjOIl~d ill the
~nvimnlllefJtal rept>t1. (lle DClaw-are peopk were orrc of ,he aborigillalClllities IQCalcd i1l Lhc Hoooou-Mohawk Ba'l<n III fm: e.1rly 17"' ccntul)' aud should have heeJ' om~ (If the initi:.1 <.....,R'>l'ltinl" p,tI\ies, As om; of the aoorigillal enliti"" we :Ire yery jnter<$!cd ;n being.<1 part of llre revlew pnx:es5 nm onh for cull<<ra!
ptcser.... ~li<)n bnltl)f ~n,,;m!u\leJHill protcctilJ!l a, welL ' '
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In rn-der fur Delaware Niltioll personneL to* be j.hOrougllJy informed abmrt this. prqi<<! ami 10- pruviffi;: COUlJllGllts we would like 10 Je!j"c~1 ,talli~i" ;i consulting pari}'. With this 5latUS, we are collfidcnl !ha, YDU wOldd bt: able to furwam a:wpy nf aJJ formal documcllls senl to all CGR,l,lting parties print fO the August 24, 2007 letter we received. n is, impt,rI;11l1 to Ihe, Ddawam NlIli<}fI lhal aU ,cull!!!al sit<.'S arc pmpcrJy mainlai;,oo ;Uld rhe ellvir,,,uv>:ntil!, impacts be reviewed bd<lre furll.er actir,n is ti!l\,~u, Thanl<. you for COJ1\flctinr. It'<l D<1l~warc Nal.iol! IfJ be inducted in III~ f~l(jC\\' (J(lhi~ application renewal. W~ look t'mwaru to yOllf quick f<SPQllJiC., Md ro:eipt of the docmnellt<; leqacsred to continue a Vrotluc1i<.,<,: relationship ""ill! ~OUt <lrganu;ation: {{you lmve any q"<SLior.\.~ Of t<;"I"'r<; ~ddlhollal !n{ormalitlll, yuu mll.y 1.'QH!:"-1 Mrs, Oimit~Ja Nie'o, "<;ljJlg.:UitC<:IQt or E,wirolllnCn(aI Pro!lral1l~ !!lldJor Ms. T31l\ilt<\ francis. Culrur.1l Prescr;"lioll Di=lor bylekpll.ollil'at(4tl5) 247*2448 Of by fa:. at (.t05) H 7 *9393.
,-;;:: Tamanl Fr<InC,s",CuUl1rni Preservatioll Director _ ,'., '"
, OrlCl Gibson, Tribal Adminiirator
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NUREG-1437, Supplement 38 E-70 December 2010 OAGI0001367E 00389
Appendix E Page I of J Ji1I C ..,vcrly - Indian Point Nucl~al' Gj;ncniing Uuit Nos. 2 and 3 Protected Speejr.s Rcspol1sr. 46:; : From: <MaryEJ!en.YanDonsel@"fws.gov> To: '\i~d @,'m*c.goy~' Dati!: 01li29;'20{!7 ! J :06 AM
Subject:
Indian Point Nuclear Generating Unit }'Io~. 2 und 3 Prokcted Species Response Please see the attached me fer our respof'!:;(; :rom the US. Fish ar.d Wildlife Se:-vice. Ma:yEllen VanD():\sill U.S, Fi&rl and Wildlife Service 3317 Luker Road Cortland. NY 13045 PI-lOnE': 607*753-9334
"'ax: 607*753*0099 file:iiC:\.(cmp\UW}OOOOl.HTM 1Oi01!2007 December 2010 E-71 NUREG-1437, Supplement 38 I OAGI0001367E 00390
Appendix E Vnited States Department of the Intel'io!' FISH AND WIIllLlH'. SERVICE x>~ ..v y{~!,~ l:~e:~i {);:t';;:¢
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~~~tt"i>.:~:\' .,\).: {l..l'::: ~t;O'/,' ~;,'-' r:.;!!:~:::~ t- :1Y f~ I I\lV~ k:vl.; n:~;;cj'.,Ii.'d yC'~U' r;;qUCst f<)3' inform;.ni0'n r\;':!..anhr.:g. (}c(m'n.:nc(:;-, ()f r~d~raHy*Esl<;d !hrc;;H*(.n~d :w'.1
..:-ndnnf;~n;*J ::pt:':..:k'*; . . ,*,:t~h:n :h~' \'~':*.II:~jf)* o!"~h~ ~~h~*:'\/..;:*n..;r:;;rj;:-t';>t."j r'rrnj,~,,*J':p?"op<..~dy. De..:t! in im::{C:bing \"Drk1o<:"': {l~jd l'(~tiW.:~~;"'1n '.~f ~1ljtr~ ~i,or :~rC' fH) l(mg(~;' ~~bit'" 10 fC'p!y to c~1.dang*'::f"I.,;~.J :;pC(;k's. :lSl f:.":qee_'ib ~n. a t~::I:iC!Y m8.0n~'J'. In an eHz't~""t !~-) ~~rt':al'ahn.t' pI njc,-"t n:~\. 11,.'\\ '~_ v.-'~~ t:.rc ~h i.H~ng tIle l~~<::lfOl'!t~* .:;f ~pl'c:e~t l::~t r(:qUl*.~}t;'., tn ~n:!' wd.. ~i'tc.:": ,1l hHp::t~.'\i*~*'*'!\*:' g()~.'<nC)IH';~'i.:yi:n:,.'t~~:{;':::"'~jJ,.,t,;tio:l*l :a:H, ?~I...';;~\."l gll it .. i',ur \H:b::;,i~~ il!H! p: :In the app:rl)pli(J~t'= j"(lHt~.)l~:-:;' u~
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;ig ...:t~fit~:~, :!l..::<..m~';iJ~!;~tint1 ~.... idl dH. ~ 1...: S. Fi,~:l; ,=-m,d \Vl:db;.~: ~[:;f':11;1..:~ (:;';.1.::-\ ~~:-.:.f~ hi' :..*:~~!V~: ~:~;il ar~_".il(:tl . .m ii ~~Ulh:.H'f:t.:.;::.
- ~'Hld:c.;.' ~~r c.:J.n-*i(:',~ ('}ut is :--lO:."i :ikd;..- 10 j'::'llp;sr,,Jl:ru ~h-:.:. (.~-tn~:n~~r:d t:.:..:j'~i::*1~.:.::t: of listed ~pl::'ci~.-I:, t""!r fe:'~:lJlt j!,~ !h~ de~:trllcti';JH
(.f ;.I_"k',-,p,l,,~ m~~di!1~-.l:H.!(\f! (If ,;,;.:111J.'C1: 1~;jb~~;J\ )\.5.1 :I~S::-*~:'-:lr:'r.":l~t ;"'1:: ~h"::, j"H"1"t::nlld 1 dir-r.;l.:t. :f1di{I;;:~(,.t .*:~1d <;;1J;nul:..;ti\'~ imp:.t~'t= i~ n,>.-l,uB'cd I"O( k:B ""~dc!"~d . .:t~ucrr~; ;JHE nti.!Y (~i"k . . . ). it'::ih:d :;pt'{',i(:$ FrJr rrojf:.d~ ;~(:t ~*tUlj:fJl'!J.t'(..L fnnd{'d~ fJ; r:.r.!"Ti<.'d Gut by ~I r t:'dcra! :w~nt;y'~. c{":'-n~u~~~n,ll.'l~ wtth the:- ~,~:n k,~ p~lr~U;Hlt Hi Sr.:,:,:.!kH1 7{t:l};:~) of ~hf;.' ESA i .q nc:{ n::'1uIn:d,
- ..kn.\'I".~v:c~*, un p'ef~(~n i~ autlJ';:;'I*t/...:G. 1.0 *"~ak:;:.*'~ -ur,y U:::ted ::;p~'.:.i~~ 'i\,l1.hi..HJ;. appr~)p('jfl.ic .:.mth.("ni7.:H~i-(,:m~ from.tho!;,,';
'S(':!""vic';;', rh,:!**;:ft~r~l \'r'(' pH.1\:id1.; ic,:hH{G~t .a&;i~t"lH. ") ~~) Hldi\:rdl.L~h ~1J~rJ ~lg~,n(:k':.,; ~(J ~$*.,:jst \vHh p:-~\jl~t;1 pLmniHg: :. :)
3v(d(~ -::J~(' p'.. . t.:~~ti;l~ (.:'(1" *'}. ~tk~:>" e-n' \~:'lir.:'H ~~ppn*,pri~n.:: . t;.~ pt*cY*;-ido:.' 'lx~i~t:nK'.tl \'.~hlJ thtttr h~'tplicati."'*It! t~x an int~1d,ttH!a: 1.lk~ i,}I;'~H~~ pl,H":-JmnH lO S(;~t :on ; O( '-1)( ~ }(B) .(tf the tS:\. fln~j(,;.;.':t ,::~)r1-~tn~(,'bno Of' imrk'1~l(q1Hti,c!H t;hf)~~d 1)(.\1 ;J)1}H1H;ncl,.<* UtLin all r{.'quh("mcnt~ ('Iftbe I':;A tWNC ht':-C:l
~~\J :fii:cd: rf:> 1m :l:l nan:..: l.J1 p,.:;-.~ :rms. ~'l( (~q~liJ '.: (~~H-r:lCt ::t~:~; :!;~r_~m-:L"~ {l:~,,~[r-o;i:tl~ t:ll\:~!len ..:d ,1~ cnd~~Jg"'r':'~ spe,;j~):~,
IJk':~s.i,: um:::t'"~~ th(~ LndaH!3.~r:.'i.f ~;p{.~,. . ~r;B P:*fJ:f.n:.m ~I {f:tr?'i --;5J~9.ljLl Plc:r:~\.'. rl',;~~~ h)t;"':c nb~~"¥\.* dLIi:*UfHcr~l':;'.~f1[r("!! fwrnn. cr ji} ;'t't~J' (i!iHfv (D:"le~-:{~nr!L;("th'(:~ j)~:~~'I:"': .. ~l".l!~~. ::::b"~,.t, "F'~;;,;!~1 1-.,.;: :' . ":,, ;'::~:~.I,.,:: '-'r '.,~ ,1;\~:l:;::l :t:," ,(';. :~1:::(1;: -r):' P:j":'l-:( :;f::P 1:: iHlti*:".:;5:(. "I:' t"'r\:i.,:::~
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';J:";':I~:":; :~1;..1 ::;,;:.,:< ::I~( '~,I;:I~~! :-t'::" "~I'-: :',:-:d'*.1:_ '-;:'l' ;:,,:~, .:: i', ."~:...:.~ :t!,;~.~<l :'1 :>1.':[. d~.::*:(!,.." "':<:';'r:;-, 'I*'::':.:p('~t i't- sb};: .::a~:~l 'x~F'::~::t, l:li!l
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NUREG-1437, Supplement 38 E-72 December 2010 OAGI0001367E 00391
Appendix E New York State Oepartment of Environmental Conservation Office of General Counsel, 1411. Floor 625 Broad\'>'aY, Albany, New York ~ 2233~1500 FAX; (5:8l402~9018 or {5~8) 402,9019 Web$ite: www.dec.ny.gov Alexar-de'"' B. Grar..n;s GamtT'j~z*j.:\'Her ()~.:~~ t) ber 5~ 200 '] Mt. 1:10 Ph.am SmiiJr PfOj~;:( M31\3gcr* bdi;m Poin, Rdit'erlsing Apphcatwn DlVisirlfJ or Li~cJ~se Rcncw~!
;vlaj.~ S10i) l)-iBI l}l1l!cd S:a[~s Nuclc'Jf Rcg~l"tory COHlII;i,;,iofJ On~ W'l1i;(; Flint N,)rtb I )S55 R,)ckvill~ Pike Ro""dl.k MD Zn352-2TJ3 Re: Indian Point IJllib 2 lilld 3 Rcli~emjug Extension Rl'qU~st for ScupjU); Comu1I.'rits on SOS Dcar ~'l;, Ph,'.)l':,
Th~ Slntc nf ","ew Yo~k 'e.,pi;l~,jU!ly rcql.1cst~ <>14 e,y.\'-'1.,itI H ul)tii October 31, 2007, in v,bich tn tile wrill,,!) Scnpins Comments em lhe dmfl g'Jpplcmcntal Envir11l1mcnLtllJllpac: Stlltemem (SFlS) lhal the N1J{;k;,r Regulmory Cnffimis;;I<)Jl (NRC) i, pr .... ~"lrillg in l',(ll"Juncti(lll wilh the f~li<;"'fl;;ing ~pplicHHo!l like! by Emcrgy Nuclea~ Op<:mtions, liK , j<)r the [ndi;m Pmnt nuclear power plants tlacian P,~int 2 and lndi~n Point 3) it": Bu~l11\nan, New Yt'rk, The St;;Ic;' h~, b<:,<:n working Jiiig"nt!y 10 prCiYlrc its C',TIl!11trl[" As you KJ\ow, th~ [)"partn~en\ o( EIlI'irorlHlcl;1ai Conscr,"atlOl1 hilS 8S,IH)lcd thc rule of {;oordinating with Olher Stale EXl"i:titiH; Ag"'ildt:~ l)11 tbe rclkcnsing a"plk~tim;, The Exc;:<,;uliw Ap;cncies arc 31 S,) working closely w,tll the;, SLHc AUVIl';CY Gc"cr~I's CXli,'", '.",j (he ~'di<:CIiSi;lg applicali.:m. Th,,' ,Hlch!mmJ! time wi;; allow fl>l' mfJr" <lfl'icienl (;o{Jrr.lin,115~.la vn t:le scop~ng \.~omn1.ents. MOI<'ov<'1. ,he NRC b;" ,-,xtcmicd the (lcndJine until ","ovcrnbtr 30, 2007, in whi~h :0 tile J Ril:'SI ,~", a j 1c,-,ri.!:gfPeliriun f(,[ l.eavc to h;lcl'\'~n, on 'h..: rdiccnsing "pplic3:.inn, Tht: St;H(: i,s lhus j:1 ihe :11(1'-'\:5S (If i<lemifying Cll\i:<)aal~nEil! i,if\lCS 10 r~iot as cOlll~ntjQm. Withml! ';<.Ic"lio:'1, thuE proccs, is l'(;:r,tcd 10 Ihe dmfling of comments on the, SEIS. Pxt.emling tbe deadline \() fil~ S~O))illg Cmmncnl, wi:.1 mc,rc;: ck,sdy coorciillflte wi~h Ilw S::"te'" ell"rts on th" R~qu"'~t t()r;;- He:!dl1g.'l'eiition je,f Le:wC! to lntcr\'cnt'. December 2010 E-73 NUREG-1437, Supplement 38 OAGI0001367E 00392
Appendix E HnuEy, J()~ll1 ~'hHhew" the kBd counsel k', the St;,!e EX<:culIV<l Ag<lu..;ies, hus had a s;gdt~c"nt falnl)Y me(1H~al wlergcncy sil)<:e Labor Day, whidl ,mly this week appe3rs to b~ rc:;(>jving, allowing heT W ('!Ice ljf~;jill ,kvn!c her lull i:!teminn lO lhi, l1mlter. RCS!l'-"Cll',J]ly ,ljbllnlt~J,
//A" /,rJ;cti~) G2,L. J;J~ !~~
/ ' JO'AN LE/JY~\I!\TJHEWS /JZlI-lN SIPOS /)
S~m':<r A~h,mcy fc)t Spe':iai I'roj.x';s A"j',:,aat Atiomey Genera! New Yor" Stale DCpa~I1lKnt of New Y,)rk Stale Dcpnrt1'lt:t1I oft;)w ff)virOlHll';IHa: C()lls<:;va,j(J;; l'nviron!Y:c'ntirl Pmle,'lion l'l\!,eiJU 5JS-~(},::9:YO ThtcCapitol iIT'wl\h~~(!)r,' _d':;::,$t3tt~, ny.us Albany, NY 12224 518,402~2251 jorm ~Jjpos((.?~O~1v.s~ate.nv.ll~ NUREG-1437, Supplement 38 E-74 December 2010 OAGI0001367E 00393
Appendix E New York. State Department of Environmental Conservation Office of General Counsel, 14'" Floor 625 6rc0dwClY, Albany, New York 12233~1500 FAX: (518) 402,9018 or (518) 402-9019 Web~ite~ I..~J/w*w.dec.ny.90\'" A,i eX3(1fjer E'l. (;-rar*m5 (:,:.m m1~:;.;k"j.1*l}r October 10, 2007 ML Bu I'haJil S.:nior Project 1\:1anagcr . indian POlnt Rt::liccn~ing App!k,Hion Dh-ision of Lh:ense R~ncwal Mail Stop O*7B i Cnittd Slates Nuclear Regulatory Commission One White Flin\ North
! I :'iSs R\)ckviHe Pike Rock \'illt', lI.;JD 20852-27:'l5 Rc: Indian Point Units 2 lind J [{dic\!llsiIlg Extension RNluest for SCOI)illg Comments on S-ElS
Dear 1'dr,
Pham: Thilnk you lb, }Clllr tdcphollC call yesterdilY ill n;,pollse to (hc State orNe' York'~ nx!u*~st to submit scoj)ing ~omment~ by O<;wbc( 3 J, 20(j7, on the aoove llMtter. This kIter is to coni1ml lhat the Stat,' W!.U :;ubmit its sc,)ping CDmments by Oetob~r 31, 2{}07, and thaI the NRC
'will c<)u;ciuer I.h<:sc c()mlTH~nK These l,vrittcn comment,; will be in additioll to tht' oral commcn(s that th,' New York Dcpmimcnt f*f Environm~tlt31 Conservation and the New Y(Jrk Department of Law provided nl th" :;cDping session on September 19, 20()7 \Iie very rnuch flppmd:lt~~ this
~~':-t~>Jmn~odat ~on.
Resp('ct,iJ!ly submiHed, jct-~ Q ~;i 0-~AN Lb\R'r MA! II-IEW:-; ~lJ>OS ,fjJ.J-~ Senior Attorney fOE Special I'fOjccts A:lsiSllln\ Attomes G(:Ileml New YMk State Depurtmcm or New York Stale Dl-1)artmenl of Law Environmentill Con"elTalion Enviromnt:nl:ll Protection Bureau 5! 8- c102--919D The Capitol i Illliltt'-K~~o_~k~,i!m-'~cllYJJ:'i Albany, NY : 2124 51 8-402-2251
,h~hJ)_,~.i_P.i!;!@~);_tg,~\l!t.r;nxJ!Jj December 2010 E-75 NUREG-1437, Supplement 38 I OAGI0001367E 00394
Appendix E
,JOf~f1 Leary ~'r1att!-f8v'/S Sepi:]f ,4.1tomey for Special Fmiects New Y,)I'k Stille Deparlment 01 Elwironlnel,tal COflser!ation Offiee of General Counsel, 14th Floor i3~5 Broud\,v,:1Y AII)ml\,', NY '12233-1500 I a:ll respon{ling to yOl:r letter of Octo['er 5, 2007, in \lvl-,'Ch you requested an extension until Octobel' 31,2007, to f!le,\-Tittel' ',eeming COIl1ITlents; fOf the env!l'Omnental impact statement til"t the US, Nuclear R8':;iul[jlory CDl1l!11ission (NF:C) Will b8 p[epming as pmi Df it:s le"lie", of tl:8 Inclial) Point Nuclear Generati!l9, UI'!t No';, :2 "r,d 3, I:cen',e fe!lew,,18pplicati l )n, Hie ~mc staff hilS cor,-;idered 'imll' request, but he,s deten"-lined tl1at iln exte!)si:]:) Df ;he GO:tTm1ent per::)d is nG! 'warran!ed. As Y*)IJ :'~nov!,o', <] NOUC8 ',:vas ~lub:ishe(; tf': the Fedsra! RfJ9r.':.::ter on A-'Jr~lust 10, 2007, Imlijin~l members of he put-He io attend tl:8 8lYVirDlllT:ental 'Scopin'] meeting schedljeG ;'0:' Seplel:':ber 'Ill, 2007, and providing an (mportull:;Y for inlel'ested p9r~,()nS to submit wl'itte!: scopin~1 GC:ITlI118nt-; dunn~1 u tWCl-ITIOl1th period fc4wiinQ iJubliciliiofi of the Notice (72 FH 45(75). ,6.$ stated jn th'8 Fr3dGn~d Regi,'3ter, \!vr:tten :;cGPir!{t CGrr!rnefl!S :;h:DlJld be submilled no IGter ,h,m October! 2. 2[107, to t'e conSidered 'n me scoplng process Numerous CGm!1'lents have been SublT,;!ted to \fIe NRC, c!uriflQ tl:e c:Gop,n9 meet!1l9 ",nd in ;Nritill~!, i:ln,j we anticipate furliwf written comn-,ent~, tJefore me enCi of U-,e GOITlrnel't period NoneH-,ele'3s, H'l8 NRC v-:iH consider C{)rrHnen~~. r9{~eived after such dGte, to the extent that ~; i'; Pf2l(;t:c8b~e to do s').
W'3 en':;ou[,,:ge you to ~'uIJrnit '{Gu: v,I'iitell 'ocoping CDmments ,,:1 yow' earlies! opportt:nlly, T!lBnk you for your :nterest <lnd P3Iii(;:pB~ion in t!16 iicense lenewal prGces:" Sincerely, iRA by Jill Caverly for/ 60 :Vi. PhaTl, ,Sen 0:' Pmject :vlafliJge r Enviwmnel,t,,; Bmndl 8 Dlvi'Sion of License Rene-Nfll Olli,:;e of Nudeai' ReBc!o!" ReQt:iatiOl' NUREG-1437, Supplement 38 E-76 December 2010 OAGI0001367E 00395
Appendix E UNITED STATES DEPARTMENT OF COMMEflCE National OeIllElI'lk: and Almllllphltrlc Admlnls,lraUQn N"TlONAl MAAfNf FlSHER;~$ 5ERVfCE NORTHEAST REGIOr-! 01:'YJ tUil.vkbttm D~~ G!OI",**l6f W. ,)l9:1O-;>.;!Sl! OCI' -4 am? Chief. Rliles and Directives Branch Division of Administmtivc St:rvi<;<.'~ D~ SO-'~4-i-Oftlce of Adlllini~tration Mailstop T*6D59 50- 28b US Nuclear RcguhltOI'Y C<Jmmi,,,io)"l
\Vi\shingtofl, DCW555-fJOOl Rc: 72 FR45(}7S*6 (August 10, 200Ij To Whom It ilklY Concern:
The5t' COTYImCIll, arc submitted by ljle Protected Re:ioun;t:s Divisi(H1 (PRD) of NOAA's National Marine Fi~berie, Servi(:(; (NMFS) r;;;gmling the appli~ation for n:ncwal of Facility Opemting Lic~n~c, DP[{*26 and DPR*64 f(w an additional 20 year"S of operation at Indian Poini Nuclear Generating (Jnit No" 2 and 3. A w(,PJCst tiJ'[ ,'\)mlJlcnt~ rcliltcu to the Nuclear Rcgujat(11)' ' Commission's (NRC) inwllt 10 prepi:re an Environmental Impact 'Statc'1nent (FrS) and condllci the scopil',g pmccss purslJant to the National Eflvironmentall'oliey Act (NEI'A) Wi;l~ published ill the Federal Regisier on August 10,2007. A populati01l of iCdemHy endangcr,"d shortnGse stllrgeOll (Ad{NnSer bl'e1.'lroslnan) uccur, ill the Hudson RIver, AdditiOl)u!ly, Atlantic glllrgeon (Aciptll.w;r oxyrillchll,j' (),'0'YtncilUs) ,we also present ir; lIle Hudson River. Atlamlc stu,geotl are considered. a Cundidate Species as NMFS has initialed a status review for this specics !o determine iflistillg as t1u'catened or endangered tmdr:r the ESA i~ wammted. A status review report was complc!cd by the ,l,,!Us review team in h;:bruury 2007. ]\IMPS is ,:uHcntly reviewing the report fino Nh,'f fH"ailahie inl'onnatinn In detenninc if listing under the ESA is ',v arramed. A listing d~tcrrnination, lind, if listing l~ wan-anted, any acc.ompanyillg proposed !<lk($). is exp<~{;tcd io be published by NI\1FS in 2008, [f il is dt:t<::rminru thalli~tjng j~ wtmantru, << li;;li:1g detcnuilllltioll 2Sld Jl11a! r\lll: listing the spedes CDu\d be publ1shcd w"ithin 3 year from the date of pub lica:i on ofthe listing determination or proposed ruk. The Statu< Review report i~ "v"il"bk ilt; hIIP:/;"vww Iwr"o,/l{)(i{Jgovii.,I'Ol"res..'Cmdidme:-peclesl'rogramiAtfSlurgeOllS!(Ju-lsRevi(!wReporl, {HI/' N:\lFS has several concems roigarding the potentia! for'the :~onti!lued opcration of the Indian Point facility to atI~l:t sturgeon, >~ tv[FS' prim"fY concern is ille Iikdih('()d of impingement of
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,
December 2010 E-77 NUREG-1437, Supplement 38 OAGI0001367E 00396
Appendix E r .'"i. 4.
!
~turgeon on screcm or racks OIl pliillt inlakes. In!Onnation provided in the application by Dym:gy fur un Endangered Spe<:les Act (ESA) Section 1O(a)("!)(B) permit for their Ro,eton and Dan~k;jm!tler pJams indicated that rrm::! 1972-1998, 3 7 shmtno~e :;!mgcon wer\: impinged at Indiml Point Unit 2 and tram 1976*199~, 26 shortnas~ sturgtO,lll were impinged at Indian Poim Unit 3, It is NMFS undcr~mndillg tlH! no IT!(lllllOri3Jg of tfle inmkes has OCCUl"ft~d since ;:creening Jnd a fish return ,yswm wert install*"d in 1998. \Vhik the scre~ning ,md !ish return system wero de-sigJ),cd III minimi!..., t;ntminment and !educethe levels ol"injury and mortc,li(y u5so(;iateU with impillgel11Cnt, no studies hav.: been conduded to dcmo1\~t:atc the cfl'ectiveness of these systems for stllrgeon. \Vhilt: NMfiS 11ll~ tiD ir:forTnlltion on like!)' Impingerner;! rates since 19Q5, we also have lW inilJlTl1atiem that :>uggL'St~it no longer 'Jccurs. Short nose sturgtOOrl i.mpinged on int"ke screens (K racb; experience high levels of inJ,ny andiorm()naJi!.y, StlJrgeo:) yplk sac hlrv,Lr;; (YSL) and post yolk sac larvae (P")'SLj have been do"um~:lltcd in the vicinity oflndian Point. Given that two distinct dl~tributions of YSt and FYSL have beer.
idcnti1}~u in tb: rivi::r (<tbovc RM J2!J <md RM 48 to 110), it i~ assumed !lmt Ihe lnn-ne in the lower river grouping arc }\tlm;ti~, sturgeon, As such, entrainlll¢nt is a ;;ignificant CO!l(.:cm tor AtlaJltic sturgeon iillhis area of t!lt river. The he~t available m!om1alion suggegt~ that umuthorilcd take (as deHned in Section '10fthi:' ESA) h~s ()<.!CUlTed in [he past at the Indilln f'tJint facility and may C()nlim;~, to OC<;Uf, Additionally, At!anlic sturgt~n egg;; and.ltJr lan'ae ;m; likdy to be present in this ri::gion of the riv[)[ and mily he subject to entrainment in the fllcilil"\"S intilke~, Botl1 shortnose and Atlantic
$!urgcvlI lIlay alsQ bt: affe..;tod l'y tllt, discharge of healed effluent. "hlorim\ und t)lher pu]lutallts or antifOUling agents.
Section 7(8)(2) ofthe ESA stmes Ihat t:llch Federal agency sha!!, in J.:{m~llltatlOt1 with tnt: SI:'Cl'ctmy, imme (11(1; allY action they authorize, fund, (>r carry' out is not hkely In JCilpardiz<~ th,,' contirwlOd existellce or a listed spedes HI" result in the destrlll::tion or ild\!erse modit!(;<:I!ion of de~ignate{\ <;riticill habitat. A11Y di5C1"etionilry federal action that may dfcct a listed species mllst undergo section 7 consultation, The rclicensmg or lmhan Point by till" NRC is a ICdcraJ acti{)n that wi!! require section 7 cOl1wltalicn. If it is dctendned through ~()nsultiil.ion between (he NRC aDd NivlFS that the action is likely to adversely affect any ltsted species (i.e" irany 3dvetse effect to hsted species may ()I.;cm a~ u di.rect or indirect n:sult of (he prop(!s~d imllon (If its intcrrclal\.,'\l 01" inlcnicpcmlent <lcliom;, and ,be clTect>: are not: diswuntabJc, itlsignif!canl, or be!leficia:) thelill ftc'l1naI cOJ)sultJ!iol1. re&ulling in the iSSUlli]C() of J BiokJgicnl Opmion and
,\..;companying In(:idenlal T!lkc Statclllent would be rcqu.ired, Any NEPA. documentation prepared by NRC relating t(l thc rel!cen~illg of this f(!cilit}' should contain an assc~SlJ)cnt of thi:: Llcility's. impact on shortnw;c alld Atlantic sturgeon. Additionally, Nl\*tFS expects the NRC to initiate section 7 consultation WWl NMfS Oll the effects of the pmposcd achon Of! listed 5pt~..;ics. In order to wnduct a cou:;a[taliotl, NMFS will need a compkttl project descrlphon and :l comp!cte E!~SC3smcnt of the facility's i:npads on listed speck's, NMfS expects thm this a,~c~sm(mt will include an estimate ofthc mlmbcf of short nose sturgeon likely to b" impinged aml!or entraim,d at the !hcility'~ intake., ()Ver the life of the proposed 20 year license, This infuralaliol1 should be submillcd to ",1\*1FS along with a rcqllcsc for ~OJ1eurreIlCt~ with NRC's dct<'rmiJ~ation of eltht5 and JUSTification for th.at determination.
- 2 NUREG-1437, Supplement 38 E-78 December 2010 OAGI0001367E 00397
Appendix E
.:, ,"" i. ) "
My slnff looks fanl/ani to working l;ooperatlvdy \-'lith the NRC during tbe n:licen>~jng pmc;eo5. Should you hi.lv~ <lny questions reg,mling sho!tnose stul'gt'on Of Ih~ section 7 p!'o~,esH in genera!, plcast conwct Pi;l Selda, Endangered Species Coordinator (978)281-9208 or
!:,";!;;lFlHlc,~cid;li:;i'Il(lll'U~O\')' For qucst:ion~ ~pccifJ~ to A:lan1ic sturgeon, please cont3d Kim Damon-Rnoda! L Pro <lcl.i lie Conservation Progrnrn Coordinntor (97 8-28 1-93 DO ](6535),
Sincerely,
\...... (\.
~~(---
Mm-)'~ Colhgan Assisi!ll1t Regional Administrator fi)r Protected Resourws Cc: Nash, NRC Crader, Damon-Randal! . F/NER4 Ru~anow~ky, Colosi .. , FiNER3 Lindow, r Fik Code: Sec !M1K It.dian Point Rdiccn,;IlJ; pefS: T,1\T.R.i2006:,07 !O~) December 2010 E-79 NUREG-1437, Supplement 38 I OAGI0001367E 00398
Appendix E N<':IVetnbe:" 27 2007 r,'ls. ,Jean Pietn.fs~nk Nevi York SWle Departrnent of nle cnvirDnfllent NYDEC-DFI.".,IMR NY Natural Herita~le Fro~~rilITI - ir:fcrmatioll Sef'/ice',; 625 8 roadway , 5th Floor Alban\" NY '12233-47':',7 SUBJECT REQUEST FOR LIST OF STp,TE PROTECTED SPECIES li'iiTHIN THE ARE/I. UNDER c\/,A.LUATION FOR THE INDIAN POINT NUCLEAR (iENERATING UNIT NOS. :1 AND 3 LICENSE RENEWAL AF'PLlC,,,TION REVIEVV Deal' [',k,. Fiet!llsialc Fie US, Nuclear Re91JIcltDl)' <::ommls:sion (~JF:C} is revi8wil~g on applicat;cl'l submitted by Ent"r~T)f Nuclear Operations, Ille (EI~tergy) fo:' ,he renewai of the opemting iicenses fOI" Indian Point NlJeiear Generating Unit Nos. 2 alld 3 {ll:ditln P'Jil,t), Indian Point i:, IDcated il': Buchanan, NeoN York. appr-0xirnHte i 'y' 24 m:l,,;:; nord~ oi tfle New York City llo;lI1darV I:ne ,iJ.", par, of the reV:BW of the ilcense renewal application (LRA\ the NRC i:" preparing ("; SUpplBI1'ental EnviwllmentailinpClct Statement (SEIS: un;jer ti"le pmvie;:Of:S of Titie '1001 niB C'C1c/e of Fef,'erB;' ReQuiaticns Part 51 ;: Hi CFR Part 5:). the NPCs re:Jl!lation that :m~;lement". the Nst:onal Environmenli31 F'olic:y Act (NEFA) of! 969. Tile SEIS Includes an 3n8Iys::3 of perti!'en! erwiw'lmenta: :ssues.il,cludi'lg encl,mgered or threatened ,;pee:es ;::H,d impacts to I:';" m,d wildlife, Th:s letter is ~;ein~! submit:e:; ',lIlder the PW\li 3ions of the Endangered Species ,i\ct of
'! 973,8:3 tlfller"I(le(l, ane! tl,e Fish ;JrId vVll,jllfe CcoF:!ln,m:):"I Aft of!934, a~; ElIT181xled Tne propose;j ac,;on i:; ;0 renew 11"18 facility GperatlW; ;jeenss fGf Indian Point for a:'1 clci::lit!Gnal 20 ysgrs beyOlv:; the e::<pirmion of Ihe CUrT81~t opsPJtin~) licensee, T~le prop:]secl aet:on V1/,;)uld mc.:ude the u~)e and c:)nt:nued tYH3::ntenf:ffc.8 af eXisting p:an{ 'facilities an[;: trnflsn::ssion hr:6'3.
T~le !n'jlar: PDmt site Govers Clpprox:lfnately 239 aGree;. !i0(11811 Pornt IS ixnderec: on ,ne Il(>,,!\ sOlJih and 6G1St D':l partia~ly vvooded; privately ovvned :~ln(j and on ~h6 i.'VEt;:.! D':-'" the Htldson R~"/8r. Enclosures I allel 2 ;:;rovi::1e to gBI:emi overview of tile site iocation ':111(; site I<<vout Ind:an Pcin, is equipped ,vim f' ollcB-tllI"OUgl, open-cycle COOiil',g system m"t \'I"ithdraws cooling
- 'velter fn:>In, flm! d:schorqes wate:- back into. ;1'11" H:,ldson Ri'ier. The it:take system :ncludes seven bavs for eacl: :Jnit located a, he shore, Six ~H3-inch pipes di'ScI":ar:;le water beneatl: the
- ~ve(s surface \.vdh,in f"~ 40-fo:]t ;~\j,:de di~;ch8r!:.1:e GanGI T~le trai1SI11issiof': line,'~ Wi the sco:pe o~ NRC/s envirOnrr"l81'"!tal rev:el.t'V jor ~jG.gn~).e r8ne'l}i:'=:: are those th[)t vvere Dr:g:i~laljy constructed fOf the ~3pednc pur;:;'8se of corll:e(:tjn9 the qlnnt to the transl":;ission syo:;iem, Tile tram,mlSSlon !ine corrielor to tl18 Bucllanf,n Substation (approximately 2"1[iO ieet 50tEneus! from the !"K.clors, just 3CroS:> Broad"M:)" ~ronl tlle facility':> main elltrance~ is ioeated in tI,e mGustrol portio!: of the :site, except for wllere the :ines cross Bro;:,cI;,'iay. This IrtWSI"::S5:0n 1:l1e c:)ITi::ioris be:n9 evalLJated tb pmi of the SEIS process.
T~-H? er::dDsed !ran:3ni::s':,~D!l lir::f2 n::np :3hovvs th8 tranSfn~SS~Oft s'ysten:1 thai ::~ bin~l ev::duated in the SEIS. T><vo 345-K:I'wolt {kV') lillee, connect In(jiorl PO:'lt tD trl8 BUGll8n:::m Sut,;:;to1ior:, Tilic, NUREG-1437, Supplement 38 E-80 December 2010 OAGI0001367E 00399
Appendix E corridor als:) includes n8-1~\/ transmiss:on lines tnat suppty dfs;l!e pO\'I'o3:' from ti,e sllbst0tiol' into In,jian POint. To support the SEIS prepElrat:on yrocess, tile NRC requests information on s;ate-li*,,;ed,. proposed, ;;)l1d cElndidale "peG:es ;;)nD cr:;iGall:ab:tat thnt !TWY be ii' the vlcin:ty of IndiElIl POint 111 addition, ,)18;;),,,13 provide nny information you consicier cl;:::pmprinte undel' tI:e pnwisions of tile Fish and 1/1/:I(;::;e C:)ordin:::tioll Act If you Ilnve any questions conceming ;I-Ie NRC 'i.taffs* review of this license reneV:ie: appHcation, please contact r";'ls, Jill Caverly, Env:mn,:lental Project r**;hmager, al 30 1-4'1~)-'3C:99 'x by 8-ma:1 nt Sincerely, IRA Bo Pham fori R:c:ni Fmnovid'1. Brancll U'lief Project:3 6mnell 2 Div~sion of Licel:se Rellewal Office of NIJ(:iear Reador Regulat:or: O:)d\et N:Js. 50-247 and 50-2*3E:
Enclosures:
Site :oG;Jlion map
- 2. Site layout map cc \!Vi8llcls See next page December 2010 E-81 NUREG-1437, Supplement 38 I OAGI0001367E 00400
Appendix E New York State Department of Environmental Conservation Division of Fish, Wildlife & Marine Resources New York Natura! Heritage Program 625 8roadiay, Alb:')(\>>', New York 12233-4757 Phone: (518) 402-8935 . fAX: (e*18) 402*8925 Website: v\~vN"{Jec.sl~,~.e . ny,us A:~xand~f S. G:fa~ni$ Rnni .Fnmovich U. S. Nuc.lear ReguiatoryCommission Projects Br,H1ch 2, Division LicCllS" Renewal
\Vllshington, DC 2tlS55,OOOl
Dear Ms. FnmOYlc:
h: In response to your recent requcst, we have feyi~wed the XC\I' York Nctmrid Heritage Program databasocs INith rc:sp!:;!:;l to an Envinmmt"Dtal Assessment for the propo~<::d Lin~fl~e RC!1t;;"'aJ Applicalion - Indj~Jl Point Nuclear Generating Units 2 ilnd _\ <lNiI as indicated on the map you pwvided, loctlted in Town of Buchun:m. End,;scd iii a report ofl'are or stlltc-lis1Cd i!llimaIs amI plants, signilkant natural cOmmunities, and other sigl;ificl1nt habitats, which om databases i:.ldicate occur, or rnay occur, on your site VI' in the immccii,ltc vicinity of your site. Tile ir:fl,rmmh'l1 contamed in this repeJJ1 is con,iM.red sensitive and should not DC re!em;c,l to the pnblic witbout pcnni~si()n li-tlln the NeVi York Natuntl H,,6t.<igc PrognlllJ. Thi, project location is adjau.'11t to ll. designated Sigllilicant Coastal Fish and \Vil(!lifc HaL-itat. This hd.jtat is part of New York State's Cu,!st<l1 Mafwgemenl Program (CMP), which is adminis!en;d i'Y th" NYS Department of State (DOS), Projects which may impact the habit"t arc reviewed by DOS for consistency with the eMf'. For more information regru:dh1g this dilsigrmtcd habitat and applicllble mnsistency revicw requirements, please conlild: JeiTZappieri (>r Vance Bllrr - (518) 474~60.o0 NYS Dl,'pal1m(~nt of Slate Divi~ion HfColl~wl ResOllrces ami Waterfront Rcvitalizat::.otJ 41 State Slr~ct, Albany, NY 12231 111C presence of rare speeie8 may result in.yom project rcquiri:lg additional pennits. permit conditiOn>, or review .. For further guidallce, and for inii:.'mmtioll n::gm'ding ()th~r pi;:rruits th:!: m;;y he rt'~ltrifed under shlte law flw rcguhlted are,lS or iwliv:lies {e.g:, regll!at<;d wetbnd,,), please C{J11!act the appropriate NYS DEC Regional Oftice, DhisiDn of Environmental Permits, at the enclo~ed address. NUREG-1437, Supplement 38 E-82 December 2010 OAGI0001367E 00401
Appendix E For most sites:, comprehensive ficld.surveys: have not been conducted; the enclosed report only indud;;;~ fc(;()nh fwm our databases, We cannot provide a definitive smtement on the presence or ahsem:t~ of all rare or stato-listed species or siS'Ilific.mlt natural communities_ Thi s int-brmation should NOT b(~ ,ubstituted for on-sill': surv<:ys that may be requlret1 for cnviwnmeiltal impac.! :lSf'CSsmenL Our dalabascs are continually growing as records are added [lnd updated. Iflhis proposed project is still under development one year hom now, \-ve recommend that you mntuct U~ agaill so that we Hlay update this l'Csponse \>.'ith the most ClInellt information. 1?:~~ r~ra Scoane Information Services NY Natural Heritage Program c-,,: Reg. :\, Fis.ileri<,g IvIgr. Peter Nyc, Endangered Specks Uuit, A!ballY Shmm Keeler, Bureau Df Fisherie~. Albany Chri$ Hogau, Lt1virmnYlema!Penlljt~, ,~"i f1(l(1t, AlbiiJl;i Enclosure (report containing a list of rare or State-listed plants and animals) withheld by NRC as sensitive information per New York Natural Heritage Program request. December 2010 E-83 NUREG-1437, Supplement 38 I OAGI0001367E 00402
Appendix E UNITED STATES O£PARTMENT OF COMMERCE NatlooalOr:a:n11: and Almo$pherlc Admlnlstrntlon NATIONAl !1MlNE flSHEWES SERVICE N~FlTHEAS1 R!;GION Ooolll",'_ Dnve G:Q"""""", 1M 01 __~ FEB 28 2008 M,;.lhmi Ffaaovich Branch Chief,.En;;imnmefl!<>! B"'!1c:b B Dillj,a(J11 of Licl:'uoe Rl~newlll Office of Nuclear Re3ctor Reguhtic'l1 Ullited Stal ..'S Nuclear Re-gu];,tury Commi%i(!fj
\"ia;,hington, D.C. ::!0555*00()1 Re: E~selJtial }'ish Uabit:d In[ormalion RCqUl~~1 fOt* Docket Nos. $O~247 and..
50-286; Indian Poi lit Nud~flr (,cnerutillg linit Nos. 2 and 3 Lk~mc Renewal; at tht' Village of lllll'illHllm" Town of Cortlandt, "Ve~"'llt'st.N' COUllty,. NY RdereIK.t' is m3lk to your inf<)I1Tmlion rtXltl(~*,t mgmdi<lg es,cntnl fish h~bitat (EFl-1) designated
- n the vicinity e,(th.e Indian Point Nuclear Geocnlling Station (Imiian Point}, YOUI lettef indlcat.:s that the NU(;e~f ReglllBtnry Commi"i.(J11 i8 i" til" pmet'>' of prepanng a ,'urpJemental envlfllnmC11t,,] impact Sl.al.ement (SUS) uuder ,he pJO"i,ioll~ of'l ide 10 of the Cod" of Federal Re-gulftli<)Jls Part 51 (10 CFR Part 51), the NRC's reglllatimJ ;h,)1 implements lIle N;n'(>[I:'lj Endjc)nm""t~J Polky Ad (NEI'!\') 0(" 1969 The SFlS i. b<::;ag pr"p"rd ;nCO,l1jurKt;OJJ will', a requt§: b)' 'fultei'gy Nuclear Opeiiltj'~D,i,- hie, for ih~rcn2,\"al ()flhe (>refilling liccnSl;5t;Jr the two opct'aling unils' at Indian*Point. Thi, pmpo~cd r6Icwa!\HJIJ 1J. 6:!cndthc current .<lpcraling
!i(;(;!l;;",;20 yt"~;'~ (><'yond tI,,,is' "lllTW1. expiralion dates: Jnd would c.-i;/~r the usc and c(lm;uued
- l'l;lintemnce {)fUnils Tw(} and Thr~t: and apputlcnad!!ailsmi>~!on lille> that (J)illle,'[ Indi~n P()i~Jt t'l the o~mhy BuciJau;'fl Sub~wt.ion. .
Tht' f~"i litie~ jie on :Jl<~ <~~s1."'m ,kll'e <)(I.he H.mj">n R.~H~r in \V'e,t<::hestel COllnty, approximalely
~,! miles U(>llh ofthc N"w York City limits Th" industrial portion> ofthc' site' oceilp),'
appoox;miH.dy 239 ,:cr~s b-l)unded to the nOI',\1, cost, ilm;! south by private property and by the Hud~'m Ri"er Oil I.h", ',\Ie!;!. l;!ltergy N(ldca:: Northeast OWIL~ all three unit;; at the ~;ite. At this lime, ol.l.ly Units T .;vo and Thrce: afC ()perati::mal. and Vlli! One i, intact bLl; has been d.~CO!nrlli$si(>n",d Tht' ','pen1Iiuf,l unib fi:,lluft' \V"tiHghom<: jJll~S~t1ri.zed \\'H.\(:'1 reat,lms fila! HIe cooled hy ellei- . drawn Ii-om (~l<l Hu,l:;on River da a ofl(;,>~hwugh, Dpc~*<,;ycJe <,;oo!.\ng system. The intake system lndndc::" ,,,~'c::n bays for each nmt. Thcrm"J\y~enrit'h",d watt',' sllh,efj I;e" I.ly is r"IIJn1t'd had. into lheri',er thwug,h six, 96" pipe:i ll-,.-:! emply in!u the plaat'~ 40' w;dc dtscha,g~ ",anal. Th", B<'l"h:1111m J(;<I,,1; of the Hlld~oJ1 Rjve! i~ iid~lly-d(")mii131,cd31ld tends loexhibjt mcsohaline or oligohalifl(c :;alinity ,.al!g~s that valY >",.asonally. Salmi!y illihem;es the distribution and limclion (~f ~"tquntk: cO.Hlluuni:Jefl, \¥,bich cOil. .pd~c(~ a ""vide . . '1l.yjety \)f tlj;~d.ron:ntl:'l <<nd re~*iden! ':i.shes i; 1 di vent' forage spec:ics inc Imjing 3 wide army ,)f ilb~cts, crustaceans, ami ('lher itlvep,chmtts. WhiJ~.n<.>t iO!f;oded to hoc. an ""I,l<lu,!lve li~t. 'it ~hO;jJd b" ;"..,(,,,1 Ib,11 Ill" fish c<.ltnmunjlv wduilc:; Ameri.ca..1 eel (A"gmtia "'!.\Irma), slrip(d ba5s'(Mm'olU' ;'axillin.\-rlYhit~ p'erch (Mi)i'(i~(;. . amirf!2,;jn'jJ)~ b(u~ ~.rat~*<<}a;riincj:.'i~!x,$j)rndt'.~), bay .;H;~hf.lvy (AJ1 ..*.Jl{)j2 nlilc!!(ili), .Ad~nt~c '~(h'~;l'~{dcs {A}e~li{"~ia ,)'ru~nidioi. h6gchcik¢r (TrjN,?:cl?_!i mi10~daje.()~ }\irieriCan shad.f:llo,~a 'snp:d/'i.~i;n{1.j, '.. r
!oa;[0u. (?vJicriigJdt"'/':';'lc:,:>d), bl<l~~h,d 1:t'JTirig Uf[o ;'iJo;eS{;\;iili,i alH:i ,;:ewiJ~:l .41,)>"£1 ,".
NUREG-1437, Supplement 38 E-84 December 2010 OAGI0001367E 00403
Appendix E [J.\Twdo/J,mmgu.,) ".... /iicil use the gcae:'al proje<:;j rc;,,"ch iiJ, a variety oi'hzbitiH jhncti(Jt~~, notably spawning and nur'icry hllbllat, w"ing and se:~s,"n(\l C{l[IC"nt~alioll areas. Atlomtic sturgcoll (Ai."fpi'IiSer a.wrfm:hw"j, a ('amJidalt' >pedes for listing umkr the EJ\<.l;mg"'r~d Spcci", Act (ESA.) itS am\ounc~d ill the f~derill Reglste;- 011 October 16, 2006 {71 FRN 61002.).
,,)so occ~r in the Hll<is(m River. The term "caodidilt~ spocic," refers to \,1) sp<eci,', tfwt ar,\ thc su.hject of a petilion to lisl a3 thrcatclR,d or endanger",d; (b) "PCC!CS for wl11<:h NMFS IUl';
determined tbat Jisting pumwnt to s0ction 4 (h )(3)(!1,.) of the ESA may he warranl;i;d; atH.! (c) 111M!! species are not the: su!)ject of" ~ petiHon btl! [()f whicb Nl\,-lFS h~..'i aru!0ulir:~d lit!;' i.llitiatiul! of a status review in the Fedeml. Register. The ;,mice of ava!lab,li,)" of tile status rt,vit:w for the Atlanlk "lurgeon wa, published in the rederal Regi,t;:; on Apri! 3,2\1(>7 (72 fRN 15865) A copy of the report can hedowllloaucd Ii'om tl:c {oJJowing w.::b;;itc: www.nerO.noaa. Ql'virrot. 1*e:;;candidr:test1t9-"W.mIT~J:l.li<<~r)mJ). The ;>,t!:mtic Sturgeon Simus Rcvi.::wTe3lJl (SRT) has dctcrmir..cd (hat the H'-IJ50n River and T.ld"w,m~ Rlvcr Athmti::: slurgeO!; stuck cUHSt.i1.utc a di,linct populat.ion ,egmcnt (DPSl c311ed the N~w York l3i.ght UPS, Th~ SRT hi!:< also concluded Eh~[ Inc )\;C\V York Bight Df'S Wd, likdy (0-50 %, ch:mcc) to noxOlll<.\ ~r;dallg<:l"cd witiJin the ncxt 20 years, ~':MFS is ~Ul;:~rrlly c(>n~idcriflg the information in th" ,:Iltus rq)(lr! to detemlinc if action und~r the ESA is wlll'atll~d. Th~ SRT als*:) identiiic:; ,cveral diffC:'fcnt strCS,Ol"S lhlll may :mpact lll,,' ;I,.!l,m!ic s\c:rg""", pnpubiiom Hldu.ding dmns for fl,xld nmlrol <lud hydrop"''' ~,"1."rutioa, water q\.l;;)i\y dcgrildalion, dr¢i;,;ing, and bill.'tmg. Ft:derillly endangerc(l shortn<)s<: :1t1.!rgc<lD (Acipeflsa {;1'evin;sm,fN) may be found ill the Hudson River ill the vicinity of Indian Pllint. Any f...xkral m:tiorJ, ;r:.u;:h as the approvaJ, funciing, or impkn;cnt<1tion of a proj(OCI. by a tc,1"T~1 agency that ma~* atT(X;t 3 listed species mUii! undergo c:onsulwion pUE~imt to Stctim 7 of th" Endangc:rl"il Specie>; Act (ESA) 01" 1973, as ;im<~lllkd. Once fipC~ifk pmj;;;(:!;; arc identified 1md pmJ"~: plmls are de"daped, the NRC: ,lmuld ;;u!;m.it ib dctcrmiJta1io[l [)f cff,,'!:!s, ilil1[jg v,ithjustitk;lc:.ion E))' the dcwrm.inatiHtl and 1\ rcqw,t fOf eonc,lrn:nec, 10 tile ~neHfi1111 <)i" the tJJdalJgernl SpC~!"S Coo,dlnrtto!", ",(TvlFS, ""o,1hcast Regional Offic.~, f'n'!(cled Rcs,)\)rcc~ Division, One Blackburtl Drive, Ghm~~stcr. MA 01930. In addil.ion. EFH ba~ been dcsigna,ed III thil Hlld;:(l!) R1VClr miXing z*.]ne lor a v3rietyof ledcmHy managed !l.shny n:sour~~s. Th<",c includ<: I;crmin lif~. ,tagcs IJf th~ red hake (Uropi!.I'cis cimss), wintr.:';t tk~under (P5:etJ.dop!euJ"onect<?,s on1;;ricanu.'i,:)) \\lindt)'),,'p~lnc (S'cnpthalmfb" aquosusJ hlucfi'~h (Pot1utft)mus _w{/ralr;'x). !'.. thBHic buU~r fish {Pepriius !!'lacanrktfSh sumrner f1f1under {P{;.ralichth.:*,/s dClHatu.)*\ .r\.tbnti::: ~t"a h,=,rr~ng (Cfupea htwt.?n;"-"l:ts)l 2:)(1 the black SC~{ b~i~S (Cei'!tyopYis~*t.(s"\'Jri{t!a). Info;:mil:iOll 1"<gll,*di.ng th",e desigr:.illions :11ay be f()"<.Jnd at out regional w,b,it~ (llt!.. :i/www.ne!\l.no~ ... £oviiKdiind(;x.html#cfh).This il1fofmar.ion is intendr:d~, ~ g<:)lCl1C gui,k that lists the EFH Specl<:S withil1 3113r::3 and is not intended for U:'ie (m ,\5 OWll. Th~ ~ctual EfH d"c,c.ript:OH:S, til" sp""ies h".bi~m prd",n;l1l\eC;, I:fld J;.1'" h:~tmy pa;."l1meten, are provided jJ.l Gu.ide tn EFH Dcs~ripti.:)ll.i, Tbc Councils" Fishery Management Plam (F!>iPs) ,"'so should be refem~J to for :J.lQ;e extemiv<, bfol1m:tioll regarding EfH Section 305(b)(2) lllt!!" MSA "Xluifl;"s all ib.l{;'ral ag<:ll~ie., 10 COtl$uh with Ni\U:S on any nc.ti!irl authorized, fi.m(kd, or ur:dert:,ken by that ~g~ncy ,hut JJ::.ay 3dverseJy aff<;.~t EFH. Included j:) this consultation proces;; is !b~ prep:l!1ltitl tl of an EFH a$~e$~mo:!ill!) provil1c J)CCc~scny in!<JnIl.at!c)J: o:! w~!jcl; to t'on~ult. O:Jf EFH r08""bli<.>n <<t SO CFR 6nO.905 mand,~("s the pr"l"mJ"2tion of E}*H
<l,Se~smell:S and ge~enlty -:Jull:nt'S ",:,cll agency's obligiHions in this consultation procc<kt~. Tbe kvd of ':dai.l in the EFH 'i",(;%tllcnt ,hould Ije (o()fJlJ.n~a'!Jjate with the potenti'1l imp"c" of r.he December 2010 E-85 NUREG-1437, Supplement 38 OAGI0001367E 00404
Appendix E pf<ljXi$cd proje<:t. It should also evaiuale all ofihc din:.:t, Indi.re,t, illd.ividual, amI cumnlative impacts on EfH. The rt-'quir~d ~()m¢m, of lm EFH ll,sc,smem h~dl:dc: 1) a ([,,'SCription ~)l'thc lIclkn; 2) all anaiysi5 of the potential ?dversc cfie:'~T3 oft!:c ac;,.,n Oil EFH End the amnagcd ::p",,,,ie,; 3J (he NRC', condusio11S ,~gatdjng (hr.; effects of :h~ acti')D l<n EFH; 4)'propoSGd mi~igatlOn, if applicable. O!h{;T mlprmatioll fhat sh()uld be contained in (he UTI 'lss,~~>mcllt. if appfc'priJ!e, im:iutk:,., 1) Ihe result:; of on~O;l!e inspecti<ms to evaluate the habitat and ,;il~-;;p~dfiG effects;. 2) the yiews !);' mcognized e.xperts on the habit2t or Ihe Spt;d~;, tlwt may be affcct()d, 3) a review of pe]~ille!ll 1:t<lfatur() and reLa.led infonnali(JD; 3.,,([ 5) an ~n'lly;;is of ~lt<lmativcs to Ihc action t.hat cO>.:.ld avmd or minilllize Ihe "dyers.: .:f!(,C(S on EFH. Tn oHler ~() allow us to cYa!\'3lc fully the prujel'(s If!lP~('T; on EFH ami fc<leI!:!!Y I1HI.m'gt;d ~pccjC$, addilioJlaJ infmmatifJIl on the impacts of comil1':1emmendati()ns io fwihCl' minimize impacts on bFH and fe<l,::n.Jly mam:ged specie,. Dq,~nding upon ~ht: e)<;p~ckd impil-:l, and the CUIlSlllldion f;chedul~, ackJilional best management pH!.ctiee3 or seasonal work resln<;tiom lllay be appr<lpriat~ E1'H comc.r\*lItion rccomm.::1:datJ0lls Thank yC.IIJ k~r yQw: inquiry fegardlng h;ih~lar. uses hy re~():ur::.:c;q tlf CfJl.lCern ~n the Indirtn fJoint arc~. We appreciate the opportunity 10 pmvide you wit!J ,his preliminary coordinatIOn in,fOlmatiotl. Sho[Jld y:..,u wi,h t" dj,j.(!u~~ I.h",~" ,"",mnCH!, fUltlmf, pk,l';c c(m!a<!t DiaJt'" RllS;illlJ\vliky at {2\l.') SS2-6:"(J4. Sinct':rc:iy,
/)L /1'-/ f d HJ2f l.{)t*lt I A-Pete, D. Colosi. Jr.
Assistam R,gional Admi:lj~t,3tor for Habitat COOSo:rv;ltioti
~,: fiNER'! - ~'lilibrd liNER3 .. PrNL't:kd Res<)w'(,es USACE .. NAX USF\\'S C!)Jtbnd NUREG-1437, Supplement 38 E-86 December 2010 OAGI0001367E 00405
Appendix E December 22, 2008 Ms. Carol Ash State Historic Preservation Officer Parks, Recreation & Historic Preservation Agency Building #1 Empire State Plaza Albany, NY 12238
SUBJECT:
INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 LICENSE RENEWAL APPLICATION REVIEW
Dear Ms. Ash:
The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing an application to renew the operating licenses for Indian Point Nuclear Generating Unit Nos. 2 and 3 (IP2 and IP3), which are located in Westchester County in the village of Buchanan, New York, approximately 24 miles north of New York City. IP2 and IP3 are operated by Entergy Nuclear Operations, Inc. (the licensee). As part of its review of the proposed action, the NRC staff has prepared a site-specific Supplemental Environmental Impact Statement (SEIS) to its "Generic Environmental Impact Statement for License Renewal of Nuclear Plants," NUREG-1437. The SElS includes analyses of relevant environmental issues. including potential impacts to historic and archaeological resources from extended operation and refurbishment activities associated with license renewal. In accordance with our letter to you dated August 9, 2007, a copy of the draft SEIS is enclosed. Pursuant to Title 36 of the Code of Federal Regulations, Chapter 800.8(c). we are requesting your comments on the draft SEIS and on our preliminary conclusions regarding historic properties. As stated in our letter dated August 9, 2007, the NRC staff has determined that the area of potential effect (APE) for a license renewal action is the area at the power plant site and its immediate environs that may be impacted by post-license renewal land disturbing operation or projected refurbishment activities associated vvith the proposed action. The staff views the APE for the IP2 and IP3 license renewal as including the IP2 and IP3 site and the immediate environs. The NRC staff has conducted an environmental audit at the site and has revievved historic and archaeological records. The NRC staff also contacted 15 Native American Tribes identified as having potential interest in the proposed undertaking. The NRC staff is transmitting a copy of the draft SEIS to the Delaware Nation for their review and comment In the context of the National Environmental Policy Act of 1969, under which the draft SEIS ,vas prepared, the NRC staff's preliminary determination is that the impact of license renev/al on historical and archaeological resources is small. Under the provisions of the National Historic Preservation Act of 1966, the NRC staff's preliminary determination is that no historic properties
\vill be affected by the proposed action.
December 2010 E-87 NUREG-1437, Supplement 38 OAGI0001367E 00406
Appendix E C, Ash Please note that the period for public comment expires on March 18, 2009, If your office requires additional time, or if there are any other questions regarding this correspondence, please have your representative contact the Environmental Project Manager. Mr. Andrew Stuyvenberg, at 301-415-4006 or Andre"v,Stuvv{,'H'1betg(qnrc,90v, Sincerely. IRAJ David J. Wrona, Branch Chief Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-247 and 50-286 cc wio encl.: See next page I NUREG-1437, Supplement 38 E-88 December 2010 OAGI0001367E 00407
Appendix E Decenlber22,2008 Ms. Mary A. Colligan Assistant Regional Administrator for Protected Resources U.S. Department of Commerce National Oceanic and Atmospheric Administration National Marine Fisheries Service Northeast Region One Blackburn Drive Gloucester, MA 01930-2298
SUBJECT:
BIOLOGICAL ASSESSMENT FOR LICENSE RENEWAL OF THE INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3
Dear Ms. Colligan:
The Nuclear Regulatory Commission (NRC) staff has prepared a biological assessment (SA). which is included in Appendix E of the enclosed draft Supplemental Environmental Impact Statement (SEIS). The SEIS is the site-specific supplement to the "Generic Environmental Impact Statement for License Renewal of Nuclear Plants." NUREG-1437. This report evaluates v'Ihether the proposed renewal of the Indian Point Nuclear Generating Unit Nos. 2 and 3 (Indian Point) operating licenses for a period of an additional 20 years would have adverse effects on listed species. The proposed action (license renewal) is not a major construction activity. In a letter dated August 16. 2007, the NRC requested that the National Marine Fisheries Service (NMFS) provide lists of Federally listed endangered or threatened species and information on protected, proposed, and candidate species, as well as any designated critical habitat, that may be in the vicinity of Indian Point and its associated transmission line right of vvays. The NMFS responded to the NRC request in a letter dated October 4,2007. and indicated that the Federally listed endangered shortnose sturgeon (Acipenser brevirostrum) and the candidate species Atlantic sturgeon (Acipenser oXYfinchus oxyrinchus) should be considered for potential impacts of license renevval and operation. The NRC staff found that renewal of the operating license of Indian Point to include another 20 years of operation could adversely affect the population of shortnose sturgeons in the Hudson River through impingement and thermal impacts. At this time, the NRC staff cannot quantify the extent to which the population could be affected. The NRC staff is preparing an essential fish habitat (EFH) assessment to evaluate vvhether the proposed renewal of the Indian Point operating licenses for a period of an additional 20 years would have adverse effects on habitats. This assessment is performed in accordance with the 1996 amendments to the Magnuson-Stevens Fishery Conservation and Management Act (MSA, 16 U.S.C. 1801 et seq.) to identify the importance of habitat protection to healthy fisheries. The NRC staff will transmit the EFH assessment under a separate cover letter. December 2010 E-89 NUREG-1437, Supplement 38 OAGI0001367E 00408
Appendix E M. Colligan We are requesting your concurrence with our determination. In reaching our conclusion, the NRC staff relied on information provided by the applicant, on research performed by NRC staff, and on information from NMFS (including a current listing of species provided by the NMFS). If you have any questions regarding this BA or the staff's request, please contact Mr. Andrew Stuyvenberg, Environmental Project Manager, at 301-415-4006 or bye-mail at
;:\:-~d:**::~'/I!, Stl) '~rven b~~ rG(cz)r:n), qn '.,/,
Sincerely, IRAJ David J. Wrona, Branch Chief Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos.: 50-247 and 50-286 cc wlo enc!.: See next page NUREG-1437, Supplement 38 E-90 December 2010 OAGI0001367E 00409
Appendix E Ms. Danieala Nieto Air Program Coordinator and Acting Director Dela':'lare Nation of Oklahoma Environmental Programs P.O. Box 825 Anadarko, OK 73005
SUBJECT:
REQUEST FOR COMMENTS CONCERNING THE INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3. DRAFT SUPPLEMENTAL ENVIRONMENTAL IMPACT STATEMENT
Dear Ms. Nieto:
The U.S. Nuclear Regulatory Commission (NRC) staff is seeking input for its environmental review of an application to renew the operating licenses for Indian Point Nuclear Generating Unit Nos. 2 and 3 (lP2 and IP3), which are located in Westchester County in the village of Buchanan, NY, approximately 24 miles north of New York City. IP2 and IP3 are operated by Entergy Nuclear Operations, Inc. As part of its revievv of the proposed action, the NRC staff has prepared a draft site-specific Supplemental Environmental Impact Statement (SEIS) to its "Generic Environmental Impact Statement for License Renewal of Nuclear Plants," NUREG-1437. This draft document includes analyses of relevant environmental issues, including potential impacts to historic and archaeological resources from extended operation and refurbishment activities associated with license renewal. By letter dated December 22, 2008, NRC staff transmitted the draft SEIS to interested parties, including your organization. In your letter to us dated September 5, 2007, you requested that all formal consultation documents be sent to you as a consulting party. Appendix C of the draft SEIS contains a chronology of formal correspondence associated with the license renewal environmental review for IP2 and IP3, and Appendix E contains copies of consultation correspondence. In accordance with Title 10 of the Code of Federal Regulations Part 51, Section 73, v"e request your comments on the draft SEIS and on our preliminary conclusions contained therein. Please submit any comments that you may have on the draft SEIS by March 18,2009. Written comments should be submitted by mail to the Chief, Rules and Directives Branch, Division of Administrative Services, Mail Stop T-6D59, U.S. Nuclear Regulatory Commission, Washington. DC 20555-0001. Electronic comments may be submilted to the NRC bye-mail at I:ldianPoi:lt.EIS~a~*.r:n::.qO". All relevant comments will be addressed in the final SEIS. The NRC will hold two public meetings to receive oral comments on the IP2 and IP3 license renewal draft SEIS on February 12, 2009: both will be at the Colonial Terrace, 119 Oregon Road, Cortlandt Manor, New York 10567. The first meeting will convene at 1 :30 p.m. and will continue until 4:30 p.m., as necessary. The second meeting will convene al 7:00 p.m. and will continue until 10:00 p.m., as necessary. Additionally, the NRC staff will host informal discussions one hour before the start of each session. Both meeting sessions vliill be December 2010 E-91 NUREG-1437, Supplement 38 OAGI0001367E 00410
Appendix E D. Nieto transcribed and any comments received at the meetings will be handled using the same process as written comments provided by mail or e-mail. The IP2 and IP3 license renewal application. the draft SEIS, and other relevant documents are available on the internet at h~:'P:!!\'i'i/'8.1 )~G,qov/ f r,:,,'1ctOf :',/Ol)t'f clt;i )(1/1 icr,m,-~,nqjf '::ne'/','2: I/a~)pli(:atii)nsii I~d im:-poitlt, h,rn I. The staff expects to publish the final SEIS - which will include responses to relevant comments received on the draft SEIS - in February 2010. Please note that the period for public comment expires on March 18, 2009. If you and your organization have any questions regarding this correspondence, please contact the Environmental Project Manager, Mr. Andrew Stuyvenberg, at 301-415-4006 or Andrevl.,l.Stuvvsnb8~~q@)r::T;;,goV. Sincerely, IRA! David J. Wrona, Branch Chief Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos.: 50-247 and 50-286 cc wlo encl: See next page NUREG-1437, Supplement 38 E-92 December 2010 OAGI0001367E 00411
Appendix E UNITED STATES DEPARTMENT OF COMMERCE National Oc:eanlc: and Atmospheric: Administration NATIONAL MARINE FISHERIES SEF\VICE NORTHEAST REGION 55 Great Republic Drive Gloucester, MA 0193()-2276 FEB 24 2009 David J. Wrona, Branch Chief Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Program US Nuclear Regulatory Commission Washington, DC 20555-0001 RE: Biological Assessment for License Renewal of the Indian Point Nuclear Generating Unit Nos. 2 and 3
.:. '-,
De,ir Mr'. Wrona: .,' ' Thi*~.~~esp~)nde.n~~' ~e~p:Q~d~fto*.a-;<I~t*ter"-dated: D¢c~.rP~~r* ~i',,~20b8 {re;ceived Janu,3.iY 2'; 2'o09}' ... regarding the initiatiori"of' fOrimil c<insllltation for the pfopt)'sEid fene\\/itfby the US Nuclear' Regulatory C(nmnission (NRC) ofthe' rriciiah P6irit Nu~ l'ea'f tknerating Unit Nbs:'2 and 3 (IP2*" and IP3) opcratmgliccnses for il p'yriod of an additional 20 years pursuant to Section 7 of the Endangered SpeCies'Act (ESA) 'of 1973, as amt:nded'. "The current openiiing licenses for these ", units expire on S~tel1\ber 28, ;2013 (IP2) and December 12, 20 15(IP3 ),Corisultationwith NoAA's Natior'l1ilMarinc FisheriesServ'ice (NMFS) teg~rditJg'the proj:lOsedlicenserenewal is' appropriat'e ~s th~' action m,ay adverselv affeCt the federally endangeredsportnose sturgeon " (A~ipe~ser brevir-ostrum). Accompanying your lett~ ~as a'Bio16gical Assessment (BA) " evaluating rhe impact of the proposed renewaion federally t;ndangt::reu ~horlnose sturgeon (Acipenser bri:viroslrum), as well as a copy of the (J<;ner;:c Environmentallmpact Statement f~r Lice~;~e Renewal QfNuclear Plants. Supplement)9 R~g~rdi'fzglli'dia~Point Nuclear Generating Yi.!it Nos. 2 and 3 Dralt Report. NMFS has cQ~pleted. an)niti'al're:vie'Yof the BA anddraftEIS and has detenninedthat we have not received all of the infonnati()TI' necessary to i'nitiate ,".' Consultation, To complete the initiation package, w.e ~iiJ req'uire'the informatio:n outlined below.
,. " .. "'" ." "
Sectio;14 qft~e, ~Ac{;ntains life history and status itilotInation forshorlnose' stii'rgeon. Several cOf1"ec~lons ,~e neces'saJ:'); in this section. ,In the Hudson River; shOltnose sturgeon 'spawn'when
'"vater i:~mpcr<i'tLI~es are between 8 and 15°C, which tyP{c~lly occursin ApriL Recen't l~forii1ation suggests, that the population estimate calculated by Bain, and included in the BA, likely
'o'>erestimates the number of shortnose srurgeon in the Hudson River. Dr. Katherine Hattala, a December 2010 E-93 NUREG-1437, Supplement 38 OAGI0001367E 00412
Appendix E biologist with the State of New York, has examined tlie data used by Bain and determined that a more appropriate estimate is approximately 30,000 adult shortnosc sturgeon. Section 4,3.2 of the BA assesses the impact of impingement on shortnose sturgeon, The BA* contains a Sl.UTImary of the available infonnation on impingement of shortnose sturgeon (Table 2). NMFS requests that NRC staff provide the following infomiation in regards to Table 2: (a) for each year, indicate the level of monitoring effort (e.g. weekly for six months, etc.); (b) for each year when then~ is no number recorded, indicate whether that was due to alack of mOliitoring, or due to a lack of capture; (c) indicate the date of impingement; and, (d) indicate the size and condition (i.e., alive, injured or dead) of the impinged fish. It is our understanding that no impingement monitOling has been conducted ,since traveling Ristroph~type screens were installed at the facility in 1991. As noted in the BA, the lack of information makes it difficult to predict the etIects of relicensing and an additional 20 years of operation on shortnose sturgeon. Ifthe NRC is 110t able to require the applicant to conduct monitoring in support ofrcliccnsing, NMFS requests that the NRC provide an estimate, based on the best available scientific infonllation, of the likely number of shortnosc sturgeon impinged at the facility with the traveling Ristroph-type screens in use, NMFS expects that the NRC could use the existing impingement data in conj unction with data on the effectiveness of Ristroph~type screens to calculate this estimate. As noted in the BA, another important factor is the mortality rate of impinged sturgeons. NMFS requests that NRC provide an estimate of the mortality rate far impinged shortnosc sturgeon. NMFS expects this rate could be calculated based on available mortality rate data for other similar species and/or other facilities where similar screen types have been installed. Section 4.3.3 of the BA discusses thermal impacts. As noted in the BA; without a model of the . thermal plume it is extremely difficult to predict what the level of exposure to elevated water temperatures is for shortnose sturgeon'. If NRC is unablc,to require that the applicant conduct modeling of the .thermal plume in support of relic ensing, NMFS requests that the NRC use the best available scientific information to estimate me likely temporal and spatial extent to which shOltn08e sturgeon will be exposed to water temperarures where adverse effects are likely (i,e., greater than 28°C). It is NM'FS understanding that the proposed action is the relicensing of the facility with no modification to the existing intakes. However, in the DEIS, the NRC discusses alternatives including cooling towers. NMFS seeks clarification as to the process by which the NRC will detennine whether the installation of cooling towei's, or other measures, will be required of the applicant. NMFS also seeks clarification regarding the current requirements of the National Pollutant Discharge Elimination System (NPDES) Permit issued by the State of New York and the potential ontcomeofthe adjudication process currently ongoing regarding this pemlit, as well as the potential far the State NPDES permit to require cooling towers. . The fomlai consultation process for the proposed action will not begill until we receive all of the requested information or a statement explaining why that information cannot be made available. We will notify you when we receive this additional information; our notification letter will also outline the dates within which fonnal consultation should be complete and the. biological opinion 2 NUREG-1437, Supplement 38 E-94 December 2010 OAGI0001367E 00413
Appendix E delivered. My staff is available to discuss these infonnation needs with NRC staff. I look forward to continuing to work with you and your staff during the consultation process. If you have any questions or concerns about 'this letter or about the consultation process in general, please contact Julie Crock(.,'!' at (978) 282-8480. Sincerely,
~M 'A'C~ 11' , -
ary . 0 19an Assistant Regional Administrator for Protected Resources cc: Crocker, FlNER3 (hardcopy) Damon-Randall, Hartley ~ FiNER3 (pdf) Rusanowsky~ FINER4 (pdt) Logan ~ NRC (pdf) File Code Sec 7 NRC Indian Point Nuclear PhllH Rcliccnsing PCTS, ffNER/2009!00619 3 December 2010 E-95 NUREG-1437, Supplement 38 OAGI0001367E 00414
Appendix E April 30. 2009 Mr. Peter D. Colosi Assistant Regional Administrator for Habitat Conservation National Marine Fisheries Service Northeast Regional Office One Blackburn Drive Gloucester, MA 01930-2237
SUBJECT:
ESSENTIAL FISH HABITAT ASSESSMENT FOR LICENSE RENEWAL OF INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 (TAC NOS. MD5411 AND MD5412)
Dear Mr. Colosi:
In accordance with the Magnuson-Stevens Fishery Conservation and Management Act, the U.S. Nuclear Regulatory Commission (NRC) is requesting initiation of an Essential Fish Habitat (EFH) consultation regarding the proposed action of license renewal for the Indian Point Nuclear Generating Unit Nos. 2 and 3 (IP2 and IP3) for a period of an additional 20 years. Enclosed is the NRC staff's EFH assessment, as well as a copy of the draft site-specific Supplement 38 to NUREG-1437, "Generic Environmental Impact Statementfor License Renewal of Nuclear Plants" (GElS). IP2 and IP3 are located on the eastern bank of the Hudson River at river mile 43 (river kilometer 69), in the Village of Buchanan, in upper Westchester County, New York. IP2 and IP3 are equipped with a once-through heat dissipation system that \tvithdra\tvs cooling vl/ater from and discharges it to the Hudson River. Water for cooling and service water is withdra'vvn from the Hudson River via tviO separate intake structures. After circulating through the condensers, cooling water is returned to the Hudson River via a discharge channel to the south of the intakes. As described in the EFH Assessment. the NRC staff identified 8 species that have EFH designated in the vicinity of IP2 and IP3. The NRC staff has determined that there may be adverse individual or cumulative effects on EFH in the project area for one or more life stages of 5 of these species from the proposed license renewal. The NRC staff has determined that continued operation of the IP2 and IP3 cooling system, with its existing mitigation measures, is expected to have an overall minimal adverse effect on EFH within the Hudson River ecosystem. I NUREG-1437, Supplement 38 E-96 December 2010 OAGI0001367E 00415
Appendix E P. Colosi In reaching these conclusions, the NRC staff relied on information provided by the applicant, on research and statistical analysis performed by NRC staff, on information from the Fish and Wildlife Service. and on information from National Marine Fisheries Service. If you have any questions regarding the enclosed draft supplement to the GElS, the EFH Assessment, or the staff's request, please contact Mr. Andrevv Stuyvenberg, Project Manager, at 301-415-4006 or by e-mail atQ.[::.gJf~.!.:S.tH:t:Y.~.[J?©j:c.t@n[~9:;;l:Q:{. Sincerely, IRAI Brian E. Holian, Director Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286
Enclosure:
As stated cc w/enel: See next page December 2010 E-97 NUREG-1437, Supplement 38 I OAGI0001367E 00416
Appendix E UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, DC. 20555-0001 September 21,2010 Mr p.eter O. Colosi Assistant Regional Administrator for Habitat Conservation National Marine Fisheries Service Northeast Regional Office One Blackburn Drive Gloucester) MA 01930*2237 SUBJECT ESSENTIAL FISH HABITAT CONSULTATION FOR LICENSE RENEWAL OF INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 (TAC NOS, MD5411 AND MD5412)
Dear Mr Colosi:
By letter dated April 30, 2009. the staff of the U.S. Nuclear Regulatory Commission (NRC) requested initiation of an Essential Fish Habitat (EFH) consultation regarding the proposed action of license renewal for the Indian Point Nuclear Generating Unit Nos. 2 and NO.3 (lP2 and IP3). in accordance with Sections 305(b)(2) and (b}(4) of the Magnuson-Stevens Fishery Conservation and Management Act (Magnuson-Stevens Act), 16 USC. Section 1855{b) With its letter of Apnl 30. the NRC staff fo!Warded a copy of the NRC staffs EFH assessment and the NRC staff's draft site-specific Supplement 38 to NUREG-1437, "Generic Enwonmentallmpact Statement for License Renewal of Nuclear Plants" (Draft SEIS) conceming IP2JIP3 license renewaL The NRC staff also sent copies of the letter, I.he EFH assessment, and the Draft 8EI$ to the Milford Laboratory on May 13, .2009, as requested by Ms, Diane Rusanowsky. Fishery Biologist in the NOAAiNMFS Habitat Conservation Division, Milford Field Office. in her e-mail message of March 18, 2009. NRC staff subsequently attempted to contact her on several occasions to obtain her comment, without success. As described in the EFH assessment, the NRC staff identified eight species for which NMFS has cesignated EFH in the vicinity of IP2 and IP3. The NRC staff has determined tMat there may be adverse individual or cumulative effects on EFH in the project area for one or more life stages of five of these species resulting from the proposed license renewal. The NRC staff further determined that continued operation of the IP2 and IP3 cooling system, with its existing mitigation measures, is expected to have an overall minima! adverse effect on EFH within the Hudson River ecosystem. In reaching these conclusions, the NRC staff relied on information provided by the applicant. research and statistical analysis performed by NRC staff, and information from the U.S. Fish and Wildlife Service and NMFS. The NRC staff also considered additional mitigation measures in its EFH assessment and in the body of the Draft SEIS. More than 20 months have passed Since the NRC staff issued the Draft SEIS for IP2JIP31icense renewal. and more than one year has elapsed since NRC staff issued the EFH assessment. Comments on the Draft SEIS were due within 75 days, while NMFS comments on the NRC staff's EFH assessment were due within 30 days after notification of the EFH assessment, in accordance with 50 Code of Federal Regulafjons Section 600.920{h){4); further, this period exceeds the SO-day time period which would have been aUoited for expanded consultation on the EFH assessment, under 50 CFR. § 600 920{h){4)(i)(4) , The NRC staff requested NUREG-1437, Supplement 38 E-98 December 2010 OAGI0001367E 00417
Appendix E p, Colosi comments on its EFH assessment from NMFS and the Milford laboratory staff, but has received no comments to date from either NMFS or the Milford Laboratory staff on either the NRC staff's EFH assessment or the Draft SEIS for IP211P3 license renewal. In view of the time that has passed since the NRC staff initiated consultation with NMFS under Section 305(b) of the Magnuson-Stevens Act, and in the absence of any comments by NMFS on the EFH assessment, the NRC staff considers that it has fulfilled its responsibilities for consultation under the Magnuson-Stevens Act. Nonetheless, the NRC slaff requests that any comments from NMFS on the EFH assessment be submitted within 15 days of the date of this fetter so that the NRC staff may consider those comments. If you have any questions, please contact Mr. Andrew Stuyvenberg, EnVironmental Project Manager, at 301-415-4006 or bye-mail at Andrew.Stuy:venbl'lrg@nrc,gov. Sincerely. David J, Wrona, Chief Projects Branch 2 Division of License Renewa! Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286 cc Distribution via Listserv December 2010 E-99 NUREG-1437, Supplement 38 I OAGI0001367E 00418
Appendix E UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555..{)001 September 27,2010 Ms. Ruth L Pierpont, Director Field Services Bureau New York State Parks, Recreation & Historic Preservation Peebles Island P,O. 189 Waterford, NY 12188-0189
SUBJECT:
INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 LICENSE RENEWAL APPLICATION REVIEW (SHPO NO, 06PR06720)
Dear Ms. Pierpont:
As you know, the staff of the U.S. Nuclear Regulatory Commission (NRC} is reviewing an application to renew the operating licenses for Indian Point Nuclear Generating Units No, 2 (IP2) and No, 3 (IP3), which are located in Westchester County, in the Village of Buchanan, New York, approximately 24 miles north of New York City. IP2 and IPS are operated by Entergy Nuclear Operations, Inc. {Entergy), On August 9, 2007, the NRC staff wrote to you, informing you of the application, the staffs determination of the area of potentia! effect (APE), the environmental scoping process that would be conducted and the schedule for review. On December 22, 2008, the NRC staff transmitted to Msc Carol Ash, the New York State Historic Preservation Officer (SHPO). a copy of the draft Supplemental Environmental Impact Statement (Draft SEIS) for license renewal of IP2 and IP3. In that letter, the NRC staff informed the SHPO that it had made a preliminary determination that the impact of IP211P3 license renewal on historical and archaeological resources is "Small," and that no historic properties will be affected by the proposed action. Further. the NRC staff requested the SHPO's comments on the Draft SEtS and the Staff's preliminary conclusions regarding historic properties, and noted that the period for public comment would expire on March 18, 200R The NRC staff subsequently communicated with Mr. Kenneth Markunas of your office regarding this matter, by telephone and in a-mail messages transmitted on June 30 and September 10. 2009. To date, the NRC staff has received no comments from your agency regarding the conclusions in the Draft SEIS; the letter of December 22.2008, to Ms. Carol Ash; or the follow-up e-mails and telephone communications between NRC staff and Mr. Kenneth Markunas of your office, While the formal comment period for the IP2 and IP3 Draft SEIS closed on March 18, 2009. the NRC staff forwarded copies of consultation letters and a hard copy of the Draft SEIS to Mr, Markunas in July 2009, in order to be sure that your agency was aware of the proposed action as well as the NRC staff's conclusions, and to be sure that the letter and Draft SEIS reached the appropriate review staff" As stated in NRC's letter of December 22,2008, in the context of the National EnVironmental Policy Act of 1969 (under which the Draft SEIS was prepared), the NRC staff's preliminary determination is that the impact of license renewal on historical and archaeological resources is small. As further stated in that letter, under the provisions of the National Historic Preservation Act of 1966 (NHPA), the NRC staff's preliminary determination is that no historic properties will be affected by the proposed action. The NRC staff also sought comments from the Delaware NUREG-1437, Supplement 38 E-100 December 2010 OAGI0001367E 00419
Appendix E R. Pierpont Nation of Oklahoma - which had requested consulting party status - in a letter dated January 12,2009, The Delaware Nation of Oklahoma submitted no comments on the Draft SEIS. The NRC staff is aware of your letter dated December 14, 2006, to James A Thomas of Enercon Services (Entergy's contractor) indicating that the proposed renewal project "will have No Adverse Effect upon cultural resources in or eligible for incfusion in the National Registers of Historic Places." That letter also indicated that your agency had reviewed the project in accordance with Section 106 of the NHPA While that letter did not address the Draft SEIS for IP2/1P3, its conclusions appear to be consistent with the NRC staff's preliminary determination, recited above, that the impact of IP2/1P3 license renewal on historical and archaeological resources is small, and that no historrc properties will be affected by the proposed action. Pursuant to 36 Code of Federal Regulations {CFR) Section 800.4(d)( 1)(i), your agency was required to object to the NRC staffs findings within 30 days. Inasmuch as the comment period for the Draft SEIS closed long ago, and no comments have been received from your office regarding the Draft SEIS or the potential impacts of IP2/1P3 license renewal on historical and archaeological resources, the NRC staff considers that it has fulfilled its consultation responsibilities under Section 106 of the NHPA. as stated in 36 CFR § 800.4(d)(1)(i), Nonetheless, if your agency has any comments on the staffs conclusions under NHPA, the NRC staff requests that your agency respond within 15 days of the date of this letter so the comments may be considered by NRC staff. If you or your staff have any other questions regarding this correspondence, please have your representative contact the Environmental Project Manager, Mr. Andrew Stuyvenberg, at 301-415-4006 or Andrew.Stuyvenberg@nrc.gov. Thank you for your time and attention. Sincerely, OJ 9 1/~ David J. Wrona, Chief Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286 cc: Distribution via Ustserv December 2010 E-101 NUREG-1437, Supplement 38 OAGI0001367E 00420
Appendix E 11.... .....,.,.;., IO!lg UNITED STATES DEPARTMENT OF COMMERCE National Oceanic and Atmospheric Administration NATIONAl. MARINE FISHERIES SERVICE NORTHEAST REGION 55 Great Republic Drive Gloucester. MA 0193G-2276 Mr. Brian E. Holian, Director Division of License Renewal Office of Nuclear Regulation OCT 12 2010 U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Mr. David J. Wrona, Chief Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Re: Indian Point Generating Unit Nos. 2 & 3 License Renewal; Docket Nos. 50-247 and 50-268; Essential Fish Habitat Consultation
Dear Messrs. Holian and Wrona:
The National Marine Fisheries Service [NMFS] has reviewed the essential fish habitat [EFHJ assessment and supplemental information provided within the United States Nuclear Regulatory Commission's [NRC)
'Generic Environmental Impacts Statement for License Renewal of Nuclear Plants, Supplement 38, Regarding Indian Point Nuclear Generating Unit Nos. 2 and 3' [dGEISj, and its attendant appendices.
These documents evaluate the proposed renewal of the operating licenses for Indian Point Energy Center's Units 2 [IP2] and 3 [IP3] for a period of twenty years. The documents include a brief description and analysis of adverse effects to a variety of diadromous and estuary~dependent fishes, crustaceans and other invertebrates, as well as EFH that is designated in the immediate project vicinity. We will
. elaborate on the affected resources and our concerns regarding continued operations at IP2 and IP3 under present conditions in subsequent sections of this letter. However, upon our review of the available information, NMFS does not reach all of the same conclusions as the NRC with respect to adverse effects that relicensing IP2 and IP3 would have on fishery resources and their habitats. We appreciate the opportunity to provide comments at this time in accordance with Mr. Wrona's letter of 21 September 2010.
The current licenses for Ihe two Indian Point nuclear generation facilities are due to expire in 2013 and 2015, respectively. Because IP2 and IP3 withdraw and discharge water Into the Hudson River, a navigable surface water body, their operations are subject to Clean Water Act oversight. In New York, this oversight is administered by the New York State Department of Environmental Conservation, which issues Clean Water Act §401 Water Quality Certificate [WaC] deciSions under its State Pollutant Discharge and Elimination System [SPDES] program. The New York State Department of State also has a bearing on these proceedings in that it is responsible for any decisions relating to the conSistency of the proposed action with the state's Coastal Management Program. Entergy Corporation [Entergy], the current owner-operator of the Indian Point Energy Center [Indian Point] generating units, has made application for the necessary state and federal authorizations and has requested that they are issued to run concurrently. Since these state actions may effect EFH, the NMFS is invoking its option to share our comments and recommendations to the involved state agencies on their activities as provided by the EFH implementing regulations. We do so here by including them in the service list for this correspondence. The dGEIS and EFH assessment prepared by the NRC evaluate the proposed action of the license renewal for IP2 and IP3 and form the base documentation for consultation between NRC and the National Manne Fisheries Service [NMFS]. The authorities under which we engage in consultation include the ..~"'" 1 l"~.1i
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§ NUREG-1437, Supplement 38 E-102 December 2010 OAGI0001367E 00421
Appendix E NRC's environmental protection regulations in Title 10, Part 51, "Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions", of the Code of Federal Regulations (10 CFR Part 51), which implement the National Environmental Policy Act of 1969, as amended (NEPA}; the Fish and Wildlife Coordination Act (FWCA) . the Endangered Species Act (ESA), and the requirements of our EFH regulation at 50 CFR 600.905 of the Magnuson-Stevens Fishery Conservation and Management Act (MSFCMA), which mandates the preparation of EFH assessments and generally outlines each agency's obligations in this consultation procedure. The comments provided in this letter pertain to the FWCA and 1 MSFCMA coordination issues that are part of your NEPA and relicensing processes. To summarize briefly, these documents acknowledge Ihat operating once-through cooling systems at Indian Point has resulted in adverse environmental impacts, yet both documents nonetheless conclude with NRC's preliminary determination that the adverse effects aSSOCiated with license renewal would have only minimal impacts on both living aquatic resources themselves and on EFH designated for federally managed species in the immediate Indian Point area. NRC's analysis or impacts relies upon comparing near field impacts thai would occur in the immediate project viciOl1y versus all EFH designated for a particular species. We frame the issue differently, and instead consider both the aqverse effects to the local fishery stocks emanating from the Hudson and the unusually high potential capacity of the mid-Hudson for recruitment of estuary-dependent fishes and production of forage species as important defining issues that lead us to a different conclusion. Project
Background:
The Indian Point Energy Center [Indian Point} is a three-unit power station located on the east shore of the Hudson River in the Village of Buchannan, Town of Cortlandt, Westchester County, New York. Only two of the generating units are operating. Indian Point Unit 1 was 'permanently shut down in 1974 because the emergency core cooling system did not meet regulatory requirements and therefore posed an unacceptable public risk; IP2 and IP3 continue to operate and are the subjects of upcoming license renewals requested by Entergy. Indian POint has a long presence in the Hudson and is one of the facilities included in the 'Hudson River Settlement Agreement' [HRSA] agreed among the U.S. Environmental Protection Agency and five New York electric utility companies in a controversy regarding coastal habitat and water uses, fish kills and ecological damage in the Mid-Hudson region. Under the HRSA, the power plant owners and operators made several concessions to stakeholders representing various environmental interests in exchange for them' agreeing to withhold imminent pursuit of forced installation of closed-cycle cooling at Indian Point and several other once-through cooled power plants in the mid-Hudson region. In particular, Consolidated Edison abandoned its plans for developing a major pumped storage [hydroelectric] facility at Storm King Mountain, and the various plant operators agreed to collect data and analyze impacts their facilities were having on living aquatic resources for a period of ten years. Subsequent modifications to the HRSA extended the study period by another decade and have allowed these plants to continue withdrawing about a trillion gallons of river water or more per year. Total river water consumption is dependent upon how many days each plant is operating annually and at what output level. Scheduled outages at Indian Point and more sporadic operation of the fossil fueled plants are all determining factors in terms of the actual water consumption levels at any given time. The biological and ecological effects of Ihese withdrawals are somewhat seasonal in that they reflect the biomass and species assemblage present at the time that the water withdrawals are taking place. The extended study period included impl~menting a variety of measures that partially mitigated for impingement and entrainment impacts, but these individually and cumulatively did nat achieve the leve! af impact reduction that would .result from installing closed cycle cooling at Indian Point. The Indian Poin! generating units alone consume about 2.5 billion gallons of water per day for their pressurized-water reactors. To meet this need, Indian Point relies upon the Hudson River as a cooling water source and heat sink. Water is withdrawn directly from the'river through batteries of seven intake 1 ESA issues have been coordinated in consultation with our counterparts in the Northeast Regional Office's Protected Resources Division and we do not address them here. 2 December 2010 E-103 NUREG-1437, Supplement 38 OAGI0001367E 00422
Appendix E bays into each generating unit and distributed to once-through condensers and auxiliary cooling systems, Cooling water is drawn into the plants by variable- or dual-speed pumps, As it first enters, the withdrawn water is skimmed of floating debris and subsequently passed over modified, vertical Ristroph traveling screens designed to protect aquatic life by retaining water and minimizing vortex stress. These modified screens attempt to reduce, but do not eliminate, impingement mortality. A high pressure spray-wash system removes debris from the front of the traveling screen mechanism and a low pressure spray-wash system flushes impinged fishes off the screen and into a sluice system that returns them to the Hudson River. Under the HRSA, the former owners of Indian Point conducted impingement monitoring between 1975 and 1990 using a variety of techniques; however, neither the previous nor the current owner-operators have performed validation studies to evaluate the actual performance of the modified traveling screens. The EFH assessment Table 6 contains impingement data for IP2 and IP3 collected between 1981 and 1990. Revised data populating this table were provided to the NRC in December, 2009. Upon NMFS' request, these data were provided for our use on October 01,2010 and were used in our review. Entrained organisms are not removed from the cooling water stream and instead are carried into and through the plants' cooling systems, as they are first collected by the circulating pumps, and subsequently passed through the plant intakes into the condenser tubes used to cool the turbine exhaust steam. Within the condensers, the organisms are subjected to mechanical damage and shear stress, thermal shock, and exposure to chlorine, industrial chemicals and biocide residues, Both the entrained organisms and heated effluent streams then exit the generating plant and are returned to the Hudson River through a shared discharge channel. According to the dGEIS, the prior Indian Point owner-operators periodically conducted entrainment loss studies for IP2 and IP3 since the early 1970s. The most recent data of this nature reported in the dGEIS are from 1990. Environmental Setting: The Hudson River Estuary supports an unusually large and diverse assemblage of fish and shellfish, and has long been recognized as a valuable national and regional resource. That is in part because the Hudson makes large contributions not only to local aquatiC resource communities, but also to coastal and
" offshore fisheries that are supported by prey and other nutrients emanating from the estuary. Some of .
these fishery resources are managed by on an inter-state basis by the Atlantic States Marine Fisheries Commission [ASMFC) and others are managed federally pursuant to the Magnuson-Stevens Fishery Conservation and Management Act [MSFCMA] or the Endangered Species Act [ESA). All of these aquatic organisms as well as non-managed species such as forage speCies and other lower trophic level organisms receive consideration under the federal Fish and Wildlife Coordination Act [FWCAj as NOAA trust resoun::es. More than 200 fish species have been recorded from within the entire Hudson watershed, and approximately two thirds of these occur in the estuary itself for all or part of their life cycles. More specifically, the Buchanan reach of the Hudson River IS a tidally-dominated habitat that serves as a migratory corridor, spawning habitat, and nursery area for an unusually diverse species assemblage of resident or diadromous fishes, crustaceans, shellfish, and many lower trophic level prey items (Smith and Lake 1990): Ambient salinity conditions vary seasonally, and generally tend to lie in the mesohaline or oligohaline ranges. The immediate project reach is within the EFH designations for the Hudson-Raritan estuary and is significant with respect to the resources under the stewardship of the agencies mentioned above. As is true of other estuarine habitats, local temperature and salinity regimes, water depth, bottom type, sediment load and current velocities all influence the distribution and function of aquatic com'T1unities. Evidence suggests that northeast coast estuaries have lost much of their rich former fishery productivity because of habitat degradation or loss, but lack of absolute speCies abundance data for early historical periods prior to:significant human disturbances makes this conclusion somewhat inferential. Yet the linkage is supported by strong evidence, particularly that stock sizes for most estuarine dependent fishery resources under the jurisdiction of the Atlantic States Marine Fisheries Gommission, New England or Mid-3 NUREG-1437, Supplement 38 E-104 December 2010 OAGI0001367E 00423
Appendix E Atlantic Management Councils, or the states of New York and New Jersey fishery management agencies, are not currently over fished, but fall below historic levels (NEFMC 1998; ASMFC 2005). This observation suggests that the Hudson River's ability to support and produce living aquatic organisms has been compromised over the years by lost habitat quality and quantity as humans have dredged, filled, and withdrawn river waler for a myriad of uses, resulting in confliCts of use with fishery resources! As described above in the Project Background section of this letter, water withdrawals for once-through cooling systems that serve the mid-Hudson power plants has been a major conflict of use that has gone unresolved for decades. A total of five units remain in operation in the mid-Hudson: IP2, IP3, Bowline Point, Danskammer, and Roseton Generating Stations. All of these plants use one-through cooling* systems. In the interim since the most recent rellcensing was completed for the Indian Point plants, most fish species have experienced declines, and essential fish habitat [EFH) has been deSignated in order to better manage adverse anthropogenic effects on fisheries. For the immediate Indian Point area, deSignated EFH includes acreage that produces organisms that are under direct federal stewardship as well as prey items for species further downriver and offshore. The Hudson River is an important regional source for both harvested stocks and prey, so reductions in its productivity are of great significance to fishery ecology and fishery management. Given the immense natural productive potential of the Hudson River Estuary, and taking into consideration the staggering numbers of organisms that are lost directly, indirectly and cumulatively through continued operation of electric generating stations that continue to use once-through cooling technology in the Mid-Hudson reach,3 the National Marine Fisheries Service [NMFS] suggests that the current Indian Point relicensing process is an appropriate and opportune time to apply the Clean Water Act § 316(a} and 316 (b) provisions regarding large power generation facilities. We note that the Indian Point generating units comfortably fit under the criteria for being required to ensure that the location, deSign, construction, and capacity for cooling water intake structures reflect the best technology available [BAT) to protect aquatic.organisms from being killed or injured by impingement cr entrainment. We provide further rationale for this conclusion in the following sections of this letter. General Comments on NRCs Exposition of Environmental Impacts of Operation in the dGEIS: Nuclear power plant system operation may create a number of habitat disturbances that range from minor to major risk to aquatic resources. The evaluation of these impacts would have been enhanced by a more expanded discussion rather than being distilled to a series of summaries on pp. 4-3 to 4-6. These bullets address topics related to a variety of predominantly phySical impacts that the NRC dismisses based upon prior experience at other nuclear plants or on the basis of information presented elsewhere in the EIS. We suggest that the NRC reconsider their evaluation before the GElS and supplement is finalized, Several of these bullets mention subjects which have a potential bearing on EFH and other aquatic resources of concern, and some modifications would demonstrate adequate support for its conclusions. For instance, on page 4-3, the NRC considers altered currents at intake and discharge structures and finds:
"Altered current patterns have not been found to be a problem at operating nuclear power plants and are not expected to be a problem during the license renewal term".
2 We note that the U.S. EPA generally tias delermined that operation of industrial scale cooling water intakes results in a wide spectrum of*undesirable and unacceptable adverse effects on aquatic resources including entrainment and impingement; disrupting the food chain; and losses to aquatic populations that may result in reductions in biological diversity or other undesirable effects on ecosystem structure or function. See 66 Federal Register 65,256, 65,292 (December 18,2001),69 Federal Register 41,576, 41,586 (July 9,2004). In addition, 3 Described in NYSDEC's April 2,2010 denial of Entergy's water quality certificate and also in the NRC's Supplement 38 to the generic Environmental Impact Statement for the proposed re-licenseing of IP2 and IP3 4 December 2010 E-105 NUREG-1437, Supplement 38 OAGI0001367E 00424
Appendix E Given the large volumes of water consumed at Indian Point each day and the relatively narrow configuration of the Hudson River at the project reach, it seems plausible that under full operation, the plant could induce noticeable changes in the current regime or perhaps induce changes in the local erosion and accretion rates that have unintended adverse effects such as losses of submerged aquatic vegetation, chronic disturbances that discourage settlement of tiny prey items, and similar effects. Although NRC regulations do not compel the project proponents to provide plume modeling or field studies, our EFH regulations compel us to assume the worst case scenario that the effluent is creating a barrier to migrating fishes and other unacceptable environmental.conditions that would adversely affect the amount and quality of available EFH. We understand that the plant operators have been using various measures to partially mitigate for these effects, put the lack of a detailed study that 1) evaluates the impacts of once-through cooling at Indian Point and the three other generating units and 2) clearly demonstrates that the measures they have been implementing are functionally equivalent to the installation of closed-cycle cooling leaves their position on the Clean Water Act § 316(a) and 316 (b) provisions as unsupported assertions. After several extensions of the HRSA. the situation remains fundamentally unchanged with regard to fish stocks and the plants are potential triggers for lost EFH in the form of direct habitat loss compounded by lost productivity in designated EFH. There is similar concern in the statements for many of the other bullets in this section of the dGEIS, notably as regards the potential release of chemical or thermal pollution [and attendant adverse impacts to fishery resource movements, etc.}; entrainment of phytoplankton and zooplankton; inductIon of low dissolved oxygen; and other line items that would reduce the quality and quantity of deSignated EFH as described in the implementing regulations for the MSFCMA. As such, it is difficult for us to dismiss these topics so easily as problems that .could be thoroughly assessed in our overall FWCA andEFH coordination. Along these same lines, existing entrainment study results from IP2 and IP3 collected from 1981-1987 do not seem to include hard data or discussion of the entrainment implications for fish eggs and larvae, copepods and other invertebrate prey items that are described clearly as prey in the EFH vignettes included for red hake, winter flound~r, windowpane, bluefish and Atlantic butterfish. While Section H.1.2 of the dGEIS and its corresponding subsections do provide a short discussion of entrainment, and even casually observe that a wide variety of phytoplankton, zooplankton, and early life stages of fish and shellfish are vulnerable to becoming drawn into the generating plants via the cooling
.. water stream, the review documents do not provide a thorough analysis of impacts to EFH with respect to their operations. Losses of this nature would have at least indirect and cumulative adverse effects on EFH .,' not just in the mid-Hudson region, but extending into the marine portions of the coastai zone.
Coincidentally, the discussion noted in the foregoing paragraph touches upon the controversial nature of how different stakeholders view entrainment survival, which has a bearing on how a disagreement like the Hudson River power plant example can take deep root, intensify and perpetuate. For entrainment, the NRC documents note a; wide range of perceptions on how different stakeholders view the potential for entrainment survival. As these documents suggest, the most conservative estimates consider entrainment 100% fatal, while some of the power companies su£gest that some species or life stages could fare considerably better based upon 96-hour survival studies. The NRC correctly acknowledges in the dGEIS that the latter studies do not take into account indirect losses that arise to organisms becoming injured, disoriented or less able to forage in the event that they are fortunate enough to survive entrainment initially, and conclude for the purposes of their assessment that such losses are unknown. Consequently, NMFS does not see justification in the gDEIS to support a conclusion that impingement effects are not Significant, or that any mitigation attempted to date has been as effective as the BAT for industria! scale operations, namely, closed-cycle cooling. This cails into question any progress claimed to have been made in implementing the HRSA in part because it gives the appearance that the various indian Point operators did not follow through completely on their commitments under the HRSA. Moreover, it appears the operators are content to continue under the status quo without demonstrating that their mitigation to date has been functionally equivalent to best available technology as required under CWA §316{b). 5 I NUREG-1437, Supplement 38 E-106 December 2010 OAGI0001367E 00425
Appendix E NRCs Evaluation of Impacts on Aquatic Resources from Operation of the Cooling Water Intake: The intake impacts for once-through cooling systems largely surround physical habitat loss associated with construction of the intakes themselves as well as the inability of aquatic species from being successfully able to use habitat within the volumes of water withdrawn from the source supply. These impacts may include changing particular ecological features such as local hydrological patterns as suggested in the foregoing section, but the preponderance of the impacts usually are associated with organism impingement and entrainment. Impingement impacts tend to accrue to larger species and life stages that cannot pass through the impingement screens nor avoid the intake current, but become trapped on cooling water screens and sometimes cannot escape before suffering exhaustion, injury or. even mortality. For the subject re-licensing proposal, we note that the most recent study results reported in the dGEIS and EFH assessment are decades old, with the most recent information collected in 1990, This fact concerns us on two counts: 1) the data may not accurately depict contemporary habitat usage of the mid-Hudson region by fishes, invertebrates, and other aquatic fife, and 2) the project proponents have not evaluated the effectiveness of adaptive measures that have been implemented since the original HRSA was put into place. For instance, installation of the modified Ristroph traveling screens as a means of addressing some of the impacts associated with impingement injury and mortality was predicated on assumptions made in a limited pilot study. The review materials suggest that the actual performance of this gear has not been demonstrated in situ. This is an important consideration because gear does not always perform the same in the field as it does in a laboratory setting and its effectiveness can vary based upon the living aquatic resource assemblages it encounters in different geographic settings. Thus, w~ are left without empirical data to estimate the effectiveness of installing the modified screens and other mitigation measures against closed-cycle cooling. While the new gear mayor may not have improved a less than ideal situation, neither NRC nor Entergy can definitively state how effectively the miw screen designs are performing as a means of justifying an additional license renewal that permits continued use of once-through cooling in a potential license renewal. Unlike impingement impacts, which tend to exhibit some selective characteristics in that they largely .-.. accrue to larger taxa or more mature life stages, entrainment of organisms into the COOling water source .~ stream are relative:y indiscriminate and may adversely affect any organism that fits through the screens ". and cannot counter the suction force of the intake. While the review material indicate that the IP2 and IP3 cooling systems have been retrofitted with dual-speed and variable-flow pumps in order that intake flows can be regulated to some degree to provide some level of mitigation or protection, we note that the dGEIS also indicates that using planned seasonal outages or maximum pump speeds does not eliminate
. the losses of fishes and other organisms to entrainment.
Regarding these collective intake impact matters, NMFS disagrees with the NRCs approach to presenting and analyzing the impingement and entrainment data. We particularly dispute the NRCs decision to attempt correlating overall population level trends with operation of the Indian Point nuclear generating facilities. First of all, analyzing the data over the entire range of a species instead of a more meaningful population segment does not follow the spirit of the National Environmental Policy Act nor the implementing regulations for EFH in the MSA because it ignores real and obvious impacts that could adversely affect a local stoCK. It is rare for the preponderance of a particular species be extirpated unless it already is endangered or threatened, but it certainly is quite plausible that a more local segment of an otherwise healthy population could be effectively decimated in an acute event or after years of suffering chronic or cumulative impacts" Thus, when considering the impacts of cooling water withdrawal on more local stock contributions emanating from the Hudson River and potentially recruiting to a greatly dispersed coastal fishery, the effects of cooling withdrawal even from a limited portion of the total available habitat' (as it is construed in the dGEIS) could be quite profound. Finally, we are critical of this type of data transformation because it also has great potential for.creating undesirable artifacts because it assumes all fishery habitats, regardless of their geographic location, size, and ecological condition, are equally valuable to the living resources that they support. The scientific literature is replete with studies that organisms do not use habitats uniformly over their ranges, and this observation is borne out in our 6 December 2010 E-107 NUREG-1437, Supplement 38 OAGI0001367E 00426
Appendix E own status and trends dala that have been used to select closed areas or to make similar resource management decisions for certain federally managed fishery resources. In concluding Section 4.1.5 of the dGEIS, upon which the NRC relies to support its overall EFH conclusions, the NRC posits that "impingement and entrainment from the operation of IP2 and IP3 are likely to have an adverse effect on aquatic ecosystems in the lower Hudson River during the period of extended operation", and goes so far as to name several potential mitigation options, but neither arrives at the specific conclusions that the units should be retrofitted with closed-cycle cooling systems, nor selects particular alternatives that they would recommend in lieu of closed-cycle cooling. NRCs Evaluation of Impacts on Aquatic Resources from Operation of the Cooling Water Discharge: As disClosed in the dGEIS, the discharge of heated water into the Hudson River Can manifest a variety of lethal and sublethal effects on aquatic life, influence local ecological conditions, and create barriers to fish migrations. Direct effects tend to be thought of as mortalities that occur when an indiVidual is exposed to conditions beyond their upper thermal tolerance limits. Indirect effects can result in changes to reproductive behaviors, changes in growth rate or survival of young, blocking migratory movements, altered predator-prey relationships. and similar community level disruptions. Oversight of these matters is regulated under a SPDES permit, which imposes effluent limitations, monitoring requirements, and other conditions to ensure that all discharges are in compliance wilh New York state code and the CWA. The most recent SPDES permit sets a maximum discharge temperature of 110°F, and limits daily average discharge temperatures nol to exceed 93.2°F for a set number of days from mid-April through June. These terms have changed over a series of four consent orders since the original SPDES was let. The NRC bases its evaluation of thermal effects on the status of the SPDES permits for Indian Point. According to the applicant's assessment, IP2 and IP3 are in compliance with terms of a SPDES permit issued by the Slate of New York as well as further mitigation required under the fourth HRSA consent order. The New York State Department of EnVironmental Conservation (NYSDEC), which maintains regulatory oversight over this arrangement, concludes that under certain circumstances, modeling demonstrates that discharges from the operating units at Indian Point allow greater than the four degree (F.) over ambient temperature limit, or a maximum of 83°F, whichever is less, in certain estuary cross sections specified under New York State regulations. These matters have been, and remain, in dispute among the plant operators and the NYSDEC, culminating in the state denying a water quality certificate in April, 2010. An ongoing proceeding with the DEC has not resolved the problem, and the NRC notes in Ihe dGEIS that the matter may not be concluded before the NRC issues its final SEIS: The lack of a thermal study proposed by the NYSDEC or an alternative proposed by the applicant leaves the NRC in the position of having to use existing information to determine the appropriate thermal impact. This resulted in their finding that continued operations with once-through cooling and vanous mitigation measures would have a small to moderate effect, depending on the ex~ent or magnitude of the plume, the sensitivity of aquatic life stages that were present, and related criteria. In addition to th-ermal discharges, the NRC considered the potential for plant operations resulting'in other impacts to aquatic resources, and concluded that impingement and entrainment are likely to have adverse effects. The significance and extent of these impaCts remain in dispute among the involved parties. The project proponents hold that existing operations adequately mitigate impingement and entrainment effects because dual- and variable-speed pumps as well as modified Rislroph were installed at IP2 and IP3, but the efficacy of these and related measures has not been verified by studies. The NYSDEC disagrees with their position, and has concluded that closed cycle cooling is the BAT to address the Hudson. River utilities' impacts to aquatic resources. The NRC considered several additional mitigation oplionsand determined thatwedgewire screening systems are not feasible; and marine life exclusion systems andior behaviorai deterrents potentially would require further study. 7 I NUREG-1437, Supplement 38 E-108 December 2010 OAGI0001367E 00427
Appendix E We realize that the ongoing dispute between the plant operator and the State have hampered the NRC's ability to present a full analysis of additional mitigation options available for the existing cooling system, and its potential utility for conserving or protecting EFH functions and values. Nevertheless, we maintain that our analysis of the severity of the project Impacts on NOAA trust resources is compelling, and that our conservation recommendations are necessary and appropriate to address the project impacts. Essential Fish Habitat Comments; Eight federally managed species with EFH designations within the mixing zone of the Hudson River estuary were identified in the NRCs EFH assessment. Of these, according to NRCs assessment, "there may be adverse individual or cumulative impacts on EFH in the project area for red hake larvae, winter flounder larvae, windowpane juveniles and adults, bluefish juveniles, and Atlantic butterfish juveniles and adults". However, the NRC went on to say in its preliminary EFH determination that they were of the opinion that none of these Impacts would rise to a level of concern because "the proportion of EFH affected by IP2 and IP3 is small compared to EFH for the total managed stock'. The NRC also proposed that continued operations of the open-cycle cooling systems for. these units could continue in a renewed license scenario provided that appropriate mitigation measures were implemented to reduce thermal effluent as well as entrainment and impingement effects. While the review materials include examples of measures that have been (or could be) implemented to reduce mortalities, it neither advocates a particular approach nor evaluates the effectiveness of those measures for protecting and conserving designated EFH or other fishery resource uses. We also note that because the EFH evaluation relies on comparing the immediate project waterfront against the total EFH designated coastally for selected species ar.d life stages, it does not give adequate conSideration to the. fact that occupation and use of EFH is no/. uniform. The EFH designations are made on the basis of habitat that is supporting particular species and generic life stages, but does not currently discriminate
-.. more finely as to how that habitat is used within a designation, As an example, early juvenile life stages tend to focus on occupation of inshore nurseries and later [but still juvenile] fishes may be using coastal and offshore EFH that better meet their needs. Thus, we do not consider it appropriate to suggest that - EFH for a one or two year old juvenile fish is equally suitable for supporting current young of the year juveniles.
Constraining the analysis of impacts to the immediate Indian Point reach and comparing that information against the habitat available to support the entire population and not the stocks originating from the Hudson River, erroneously creates the setting for not being able to find any impacts to EFH. A more appropriate analysis extends the view of entrainment, impingement and thermal discharge impacts to include the mortalities and reduced productivity of forage species, diadromous species, and resident fishes; to assess their impacts on coastal fisheries including species for which EFH is designated downstream; and to discuss how the lost productivity out of the mid-Hudson represents a net reduction in forage opportunities for offshore and downstream resources. This latter class of impacts is quite relevant in this situation and is not analyzed by the NRCs review materials. Nonetheless, the NRCs EFH assessment concluded that there may be adverse individual or cumulative effects of the proposed action or red hake larvae, winter flounder larvae, windowpane juveniles and adults, bluefish juveniles, and Atlantic bulterfish juveniles and adults. However, in making this judgment, the NRC did not specif~' particular impacts of concern in the EFH assessment itself. Extrapolating from the dGEIS, NMFS notes that the primary impacts of concern regarding fishery resources and their habitat generally, and for EFH in particular, that would be associated with continued operations using an open-ended cooling system would be organism loss and habitat degradation. We could not enumerate these impacts based upon the materials provided for our review, but note that at over 2 billion gallons of water consumed per day, the amount of prey available to fishes in particular would be significantly diminished through entrainment alone. 8 December 2010 E-109 NUREG-1437, Supplement 38 I OAGI0001367E 00428
Appendix E While we recognize the impediments associated with lack of newer studies and related information, NMFS does not agree with some of the methods that the NRC used or assumptions that it made in performing its fish impact evaluations. According to the review materials provided, operating lP2 and IP3 as they currently are leads to direct impacts to EFH species and their prey in the mid-Hudson region. We also note thai the EFH assessment and associated analyses were configured too narrowly to capture the breadth and implications that continued operations would have on living aquatic resources and their habitats both in the mid-Hudson and to coastal fisheries. As noted above, we are particularly concerned with the potential for Indian Point operations leading to reduced production or availability of prey, which constitutes an indirect or cumulative adverse effect that diminishes the quality of designated EFH as defined in the MSFCMA. Similarly, it is our opinion that a proper cumulative effects analYSis for this situation should have included the adverse effects associated with operations at all of the mid-Hudson power plants that rely on Hudson River water to feed once-through cooling systems. We are not alone in this conviction. According to the NYDECs Final Draft Fact Sheet NY-OQ04472, dated November, 2003, . regarding Indian Point's Surface Water Renewal Permit Action, "Pursuant to Section 316(b) of the CWA, and 6 NYCRR Section 704.5, the Department has determined that the site-specific best technology available (BTA) to minimize adverse environmental impact of the Indian Point Units 1, 2 and 3 cooling water intake structures is closed-cycle cooling." NMFS agrees with New York that a closed-cycle cooling system would significantly limit the amount of intake f!ow and thereby reduce impacts associated with especially impingement and entrainment. It is our opinion that implementing this measure is in the best Interest of fishery resources and also IS the most appropriate option for meeting our mutual EFH mandates while allowing continued electric generation at lP2 and IP3 in an otherwise sensitive ecological area. Essential Fish Habitat Recommendations: To minimize the .impacts on EFH, pursuant to Section 305(b)(4)(A) of the MDFCMA, NMFS recommends that the follOWing conservation recommendations be adopled in conjunction with the proposed federal action: .
- Implement thebesl available practicable technology to mitigate impingement, entrainment, and thermal impacts. The BAT for Indian Point would be reconfiguring the faCilities by replacing the once-through cooling system with a state-of-the-art, closed-cycle design. A closed cycle cooling system would minimize water intaKe rates and return little to no heated water back into the Hudson River. The reduced water withdrawals and greatly diminished, perhaps even non-existent, plume associated with a closed-cycle cooling system would avoid and minimize what NMFS considers to be highly significant mortalities of billions of aquatic organisms and their attendant impacts to coastal fisheries.
Please note that Seeton 305(b)(4)(8) of the MSFCMA requires that the NRC provide NMFS with a detailed written response to the EFH conservation recommendation, including a description of the measures adopted by the NRC for avoiding, mitigating, or offsetting the impact of the project on EFH. In the case of a response that is inconsistent with NMFS' recommendation(s}, Section 305(b)(4)(6) a the MSFCMA also indicates that the NRC must explain its reasons for not following the recommendation(s). Included in such reasoning would be the scientific justification for any disagreements with NMFS over the anticipated effect of the proposed action and the measures needed to avoid, minimize,mitigate,.or offset such effects pursuant to 50 CFR 600.920(k). Please note that a distinct and further EFH consultation must be re*initiated pursuant to 50 CFR 600.920(1), if new information becomes available or the project is revised in such a manner that it affects the basis for the above EFH conservation recommendation. Endangered Species Act: The federally listed, endangered SNS and the candidate species for listing Atlantic sturgeon may be present in the project area. The NRC is currently in consultation with NMFS NEROs Protected Resources Division pursuant to Section 7 of the ESA and the NRC will conclude the ESA consultation with our 9 NUREG-1437, Supplement 38 E-110 December 2010 OAGI0001367E 00429
Appendix E colleagues in this Division of NMFS. The contents of the above EFH and FWCA coordination does not . replace or supersede any negotiations that you may have conducted or will conduct with our PR division. and only pertains to our mutual obligations unde~ the FWCA and MSFCMA. Should you have any question regarding these comments or need additional information, please contact Diane Rusanowsky at diane.rusanowsky@noaa.gov; 203-882-6504 Sincerely, Peter D. Colosi, Jr. Assistant Regional Administrator For Habitat Conservation December 2010 E-111 NUREG-1437, Supplement 38 I OAGI0001367E 00430
Appendix E David A. Paterson Governor New York State Office of Parks t Carol Ash c vft)rtWSS~O;1 e I~ Recreation and Historic Preservation The Goverl1or Noison A. Rockefeller Empire Stale Plaza' {'geney 8li!lding 1, Albany, New York 12238 www.nysparks.com October 26,2010 David l Wrona Chief, Projects Brunch 2 Division of License Renewal Office of Nuclear Reactor Regulation US Nuclear Regulatory Conunissiotl Washingt0l1; [).c. 20555*()OOI . Re: NRC Indian Point License Renewal Buchanan, \\?estchest.er County
Dear Mr. Wrona:
Thank you for your letter dated September 27,2010 to.Ruth Pierpont regarding the Jjccnsercne\vul of the Indian Point Nuclear Power Generating Units 2: and 3. The New York State Historic Preservation Office (SHPO) previously commented on this matter'.l.lI1defo,~e~}ipl1:~I06 of the National Historic Preservation Act by le.tterdated March 24, 2,OO~ {CORY attach(4). A.s noted, lILthat.l,etter,SppO ~svOn:llnelltf) ~~donpt* includ~e pot~ntial.e~v;i~nm'ent'~1:iO:tp;Ct:~:t9'N~....::.York S!,iteJJarkl~!!(1Yhi{m~y'b~inyoi~e~in'or Ilear your proj ect. .Such impacts ,n~ust be CQnsidered as part of the env ii-onmental review . pf the proJec.t P)!.rSlJ~riU9 ,the N~t~onal En';'ironJ!l:ent~l Policy Act .. "," :111e. New York State*Offir.,e ofParks, Recr.eation ,ar)d Historic Preservalionthereforc appre~iates:this to opportlmity -.c:9rnnl~nt, UP('l~ a specific.'i[~pact upOll one of ourineplaceable facilities that,docs not appcartoiiavc beenaddrcsscd in the draftSupp1emental EnvlrQnmental IDl~act Stat~}ll{mt(bSEiS), '. . .... .' '. '. '. . . As noted in section 2.2.9 ofthc DSEIS, Stony Poini BaHlefield State Historic Site is i()catedjustsou1l1(jfallQ directly across the Huds;n River from the Indian Point faCility.. .Tbisllls(oric ~jJe is directly as~ociuted with. th~ July 16, ..1779 b~ttle of Stony
~oiill""l;here .General A-#thpny Waym~mlda sm.an elite for~e of the COfltincntal,Anny
. captured the "Sritisb garris?n stationed at the. PQinL This event jJlarked the l~st ulf'.ior.
conflict bfthpRcvblutionary Warinthenorthem theater. , The.45-acre park is. '. cl;1aracteriz.ed'by surylvingJ $11.: CimUJry \:.arthworks and an early 19~il centu\Y. 'navigational light.hQuse .. Th<~iie~'~f1S;gesi~ii~tcd aNati,?,nai )-listoric' L'll.1dins!h: hy the. y,~itedSiut~d Qepar,tlIle!1t'4if,lh.eJnt~ri6r ()n Jann[.iry2j},.19531. ,This is the Nati()n~s highes~historical
$I;q f!i?¥n, il~or~~~~~I~;' ,~:" ". ". ;':';,';,;:,;' ....'.:~,:. ;.'" '. c;: .'. ,: ;'/" :,,::'.c:;* ',' ,..:;:
NUREG-1437, Supplement 38 E-112 December 2010 OAGI0001367E 00431
Appendix E According to the Department of the Interior "National Historic Landmarks are nationally significant historic places designated by the Secretary of the Interior because they possess exceptional value or quality in illustrating Of interpreting theherilage of the United States. Today, fewer than 2,500 historie places bear thisnatiortaldistinction.," The DOl goes en te state: "National Historic Landmarks are exceptional places, They fOJ;l11 ~:, common bond between all Americans. W11ite there are many historic places across the nation, only a smal! number have meaning to all Americalls--lhese we call our National Historic Landmarks." As such, the Stony Point 'Battlefield is an ineplaccablc asset to the people of New York State and the Nation. The DSEIS in Chapter 5.2 purports to assess the impacts of a Severe Accident and the feasibility of Mitigation Alternatives, but ignores the impact of such an accident upon Stony Point Battlefield and fails to consider the impicmentation of alternatives to mitigate such impacts. Any loss, temporary or otherwise, of the public's access to this place wQu!d£ignifkatlt!y diminish the Nation's lexicon of ta£lgible historic resources associated with the American Revolutionary WaLStony Point Battle Field Histmic Site is a significant historic and cultural asset 10 the people of New York State and the Nation and we request that any potential impacts to this site be fully assessed in the enviromnental analysis or the relicensing ofIndian Point. ' If YOIl should have any questions regarding these comments 1 can be reached at (513) 474-0409. ff~8
. '. Thomas B.Lyons
. Director ofResource M cc: Tom Alworth Enclosure
... i December 2010 E-113 NUREG-1437, Supplement 38 I OAGI0001367E 00432
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thc:f<t l:'; ~h;~ iMtentbl forb::Jrid deposit."'. Te,mng rm~y be m~~c",~ary to "ktcrrMl;; fm dq:lti'l a:f:(ji{lt di:.:tr.J~;li:.W~':: ()f ,!:rig:tld :;.{1iL F'inuHy: th~ 'I(i;:u~; ;.;frl2~;::,t :;,'\,'s~~ h:a(~~ t-~} he a~;~12;gsed l~~ r~~~ *ufth~ nrl)J(~:d. if~h*~ coo:hng: U'w\~<*.~ '-hH k 8)':.~iH. NUREG-1437, Supplement 38 E-114 December 2010 OAGI0001367E 00433
Appendix E P.;!;.f~i~ 2 ()6PR~)6720 h)1 f;J~';h,:::( *S(l~w.~-;p')*lld~~)(;c :'"<.~g<lr:dll"<g dm. ))l{.j ~'l~t, pk,@.: hl~ ",n: t1J lTkr to ~h~ OPH.HP f'WJ,,'(;l Rt'-';l'~W (1' R} l1i~mt;r:r nr.~t,;:d l,i;{}v.;~ L( you have Mly qIJl%ti*:)%, pi e::t$e: c.al! me aI (5 ~ 8}
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Appendix F GElS Environmental Issues Not Applicable to Indian Point Nuclear Generating Station Unit Nos. 2 and 3 OAGI0001367E 00435
Appendix F GElS Environmental Issues Not Applicable to Indian Point Nuclear Generating Unit Nos. 2 and 3 Table F-1 lists those environmental issues identified in NUREG-1437, Volumes 1 and 2, "Generic Environmental Impact Statement for License Renewal of Nuclear Plants" (hereafter referred to as the GElS), issued 1996 and 1999,(1) and in Table B-1 of Appendix B to Subpart A of Title 10, Part 51, "Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions," of the Code of Federal Regulations (10 CFR Part 51), that are not applicable to Indian Point Nuclear Generating Unit Nos. 2 and 3 (lP2 and IP3) because of plant or site characteristics. Table F-1. GElS Environmental Issues Not Applicable to IP2 and IP3 ISSUE-10 CFR Part 51, Subpart A, Category GElS Appendix B, Table B-1 Sections Comment SURFACE WATER QUALITY, HYDROLOGY, AND USE (FOR ALL PLANTS) Altered thermal stratification of lakes 1 4.2.1.2.3, IP2 and IP3 do not 4.4.2.2 discharge into a lake. Water use conflicts (plants with 1 4.3.2.1, IP2 and IP3 have a once-cooling pond or cooling towers using 4.4.2.1 through cooling system. makeup water from a small river with low flow) Water use conflicts (plants with 2 4.3.2.1 This issue is related to cooling towers and cooling ponds 4.4.2.1 heat-dissipation systems using make-up water from a small that are not installed at IP2 river with low flow) and IP3. (1) The GElS was originally issued in 1996. Addendum 1 to the GElS was issued in 1999. Hereafter, all references to the GElS include both the GElS and its Addendum 1. December 2010 F-1 NUREG-1437, Supplement 38 I OAGI0001367E 00436
Appendix F AQUATIC ECOLOGY (FOR ALL PLANTS) AQUATIC ECOLOGY (FOR PLANTS WITH COOLING TOWER-BASED HEAT DISSIPATION SYSTEMS) Entrainment of fish and shellfish in 1 4.2.2.1.2, This issue is related to early life stages 4.4.3 heat-dissipation systems that are not installed at IP2 and IP3. Impingement of fish and shellfish 1 4.2.2.1.3, This issue is related to 4.4.3 heat-dissipation systems that are not installed at IP2 and IP3. Heat shock 1 4.2.2.1.4, This issue is related to 4.4.4 heat-dissipation systems that are not installed at IP2 and IP3. GROUND WATER USE AND QUALITY Ground water use conflicts (potable 1 4.8.1.1, IP2 and IP3 do not use and service water, and dewatering; 4.8.1.2 ground water for any plants that use <100 gpm) purpose. Ground water use conflicts (potable 2 4.8.1.1, IP2 and IP3 do not use and service water, and dewatering; 4.8.1.2 ground water for any plants that use> 100 gpm) purpose. Ground water use conflicts (plants 2 4.8.1.3 This issue is related to using cooling towers withdrawing heat-dissipation systems makeup water from a small river) that are not installed at IP2 and IP3. Ground water use conflicts (Ranney 2 4.8.1.4 I P2 and I P3 do not have or wells) use Ranney wells. Ground water quality degradation 1 4.8.2.2 I P2 and I P3 do not have or (Ranney wells) use Ranney wells. Ground water quality degradation 1 4.8.2.1 IP2 and IP3 do not use (saltwater intrusion) groundwater for any purpose. I NUREG-1437, Supplement 38 F-2 December 2010 OAGI0001367E 00437
Appendix F Ground water quality degradation 1 4.8.3 IP2 and IP3 do not use (cooling ponds in salt marshes) cooling ponds. Ground water quality degradation 2 4.8.3 IP2 and IP3 do not use (cooling ponds at inland sites) cooling ponds. HUMAN HEALTH Microbial organisms (occupational 1 4.3.6 This issue is related to a health) heat-dissipation system that is not installed at IP2 and IP3. Microbiological organisms (public 2 4.3.6 This issue is related to a health; plants lakes or canals, cooling heat-dissipation system towers, or cooling ponds that that is not installed at IP2 discharge to a small river) and IP3. TERRESTRIAL RESOURCES Cooling tower impacts on crops and 1 4.3.4 This issue is related to a ornamental vegetation heat-dissipation system that is not installed at IP2 and IP3. Cooling tower impacts on native 1 4.3.5.1 This issue is related to a plants heat-dissipation system that is not installed at IP2 and IP3. Bird collisions with cooling towers 1 4.3.5.2 This issue is related to a heat-dissipation system that is not installed at IP2 and IP3. Cooling pond impacts on terrestrial 1 4.4.4 This issue is related to a resources heat-dissipation system that is not installed at IP2 and IP3. December 2010 F-3 NUREG-1437, Supplement 38 I OAGI0001367E 00438
Appendix F References Code of Federal Regulations, Title 10, "Energy," Part 51, "Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions." U.S. Nuclear Regulatory Commission, NUREG-1437, "Generic Environmental Impact Statement for License Renewal of Nuclear Plants," Volumes 1 and 2, May 1996. U.S. Nuclear Regulatory Commission, NUREG-1437, "Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Main Report" Section 6.3, "Transportation," Table 9.1, "Summary of Findings on NEPA Issues for License Renewal of Nuclear Power Plants," Final Report Volume 1, Addendum 1, August 1999. I NUREG-1437, Supplement 38 F-4 December 2010 OAGI0001367E 00439
Appendix G u.s. Nuclear Regulatory Commission Staff Evaluation of Severe Accident Mitigation Alternatives for Indian Point Nuclear Generating Unit Nos. 2 and 3 in Support of License Renewal Application Review OAGI0001367E 00440
1 Appendix G 2 U.S. Nuclear Regulatory Commission Staff Evaluation of 3 Severe Accident Mitigation Alternatives for 4 Indian Point Nuclear Generating Unit Nos. 2 and 3 in 5 Support of License Renewal Application Review 6 G.1 Introduction 7 Entergy Nuclear Operations, Inc. (Entergy) submitted an assessment of severe accident 8 mitigation alternatives (SAMAs) for Indian Point Nuclear Generating Unit Nos. 2 and 3 (lP2 and 9 IP3) as part of the environmental report (ER) (Entergy 2007). Entergy based its assessment on 10 the most recent probabilistic safety assessment (PSA) for IP2 and IP3 (a site-specific offsite 11 consequence analysis performed using the MELCOR Accident Consequence Code System 2 12 (MACCS2) computer code), and on insights from the Individual Plant Examination (lPE) (Con 13 Ed 1992 and NYPA 1994) and the Individual Plant Examination of External Events (lPEEE) 14 (Con Ed 1995 and NYPA 1997) for each unit. In identifying and evaluating potential SAMAs, 15 Entergy considered SAMAs that addressed the major contributors to core damage frequency 16 (CDF) and large early release frequency (LERF) at IP2 and IP3, as well as SAMA candidates 17 for other operating plants that have submitted license renewal applications. Entergy identified 18 231 candidate SAMAs for IP2 and 237 SAMAs for IP3. This list was reduced to 68 (lP2) and 62 19 (lP3) unique SAMAs by eliminating SAMAs that are not applicable at IP2 and IP3 because they 20 have design differences, they have already been implemented at IP2 and IP3, or they are 21 similar in nature and could be combined with another SAMA candidate. Entergy assessed the 22 costs and benefits associated with each of the potential SAMAs and concluded in the ER that 23 several of these were potentially cost beneficial. 24 Based on a review of the SAMA assessment the U.S. Nuclear Regulatory Commission (NRC) 25 issued requests for additional information (RAls) to Entergy in letters dated December 7, 2007 26 (NRC 2007), and April 9, 2008 (NRC 2008). Key questions concerned major changes to the 27 internal flood model in each of the PSA updates; PSA peer review comments and their 28 resolution; MACCS2 input data and assumptions (including core inventory, evacuation 29 modeling, and offsite economic costs); assumptions used to quantify the benefits for certain 30 SAMAs; reasons for unit-to-unit differences for certain risk contributors and estimated SAMA 31 benefits; and further information on several specific candidate SAMAs and low-cost alternatives, 32 including SAM As related to steam generator tube rupture (SGTR) events. Entergy submitted 33 additional information by letters dated February 5, 2008 (Entergy 2008a), and May 22, 2008 34 (Entergy 2008b). In response to the RAls, Entergy provided clarification of the internal flooding 35 analysis changes in each PSA model version; additional information regarding the peer review 36 process and comment resolution; details regarding the MACCS2 input data, including results of 37 a sensitivity analysis addressing loss of tourism and business; additional explanation and 38 justification for the assumptions in each analysis case; descriptions of plant-specific features 39 that account for differences in risk and SAMA benefits between units; and additional information 40 regarding several specific SAMAs, including SGTR-related SAMAs. Entergy's responses 41 addressed the NRC staff's concerns and resulted in the identification of several additional December 2010 G-1 NUREG-1437, Supplement 38 OAGI0001367E 00441
Appendix G 1 potentially cost-beneficial SAMAs and the elimination of one previously identified cost-beneficial 2 SAMA. Subsequent to issuance of the Draft Supplemental Environmental Impact Statement 3 (DSEIS), Entergy identified an error in the Indian Point site meteorology file used to calculate 4 offsite consequences of severe accidents, and submitted a SAMA re-analysis based on the 5 corrected meteorological data (Entergy 2009). The SAMA re-analysis resulted in the 6 identification of several additional potentially cost-beneficial SAM As beyond those identified in 7 the ER and the DSEIS. 8 An assessment of SAMAs for IP2 and IP3 is presented below. 9 G.2 Estimate of Risk for IP2 and IP3 10 Entergy's estimates of offsite risk at IP2 and IP3 are summarized in Section G.2.1. The 11 summary is followed by the NRC staff's review of Entergy's risk estimates in Section G.2.2. 12 G.2.1. Entergy's Risk Estimates 13 The two distinct analyses that are combined to form the basis for the risk estimates used in the 14 SAMA analysis are (1) the IP2 and IP3 Level 1 and Level 2 PSA models, which are updated 15 versions of the IPE (Con Ed 1992 and NYPA 1994) and IPEEE (Con Ed 1995 and NYPA 1997) 16 for each unit, and (2) supplemental analyses of offsite consequences and economic impacts 17 (essentially a Level 3 PSA model) developed specifically for the SAMA analysis. The SAMA 18 analysis is based on the most recent IP2 and IP3 Level 1 and Level 2 PSA models available at 19 the time of the E R, referred to as the IP2 Revision 1 PSA model (April 2007) for IP2 and the IP3 20 Revision 2 PSA model (April 2007) for IP3. The scope of the PSA models does not include 21 external events. 22 The baseline CDF for the purpose of the SAMA evaluation is approximately 1. 79x1 0- 5 per year 23 for IP2 and 1.15x1 0- 5 per year for IP3. The CDF is based on the risk assessment for internally 24 initiated events, including internal flooding. Entergy did not include the contributions from 25 external events within the IP2 and IP3 risk estimates; however, it did perform separate 26 assessments of the CDF from external events and did account for the potential risk reduction 27 benefits associated with external events by multiplying the estimated benefits for internal events 28 by a factor of approximately 3.8 for IP2 and 5.5 for IP3. This is discussed further in Sections 29 G.2.2 and G.6.2. 30 The breakdown of CDF by initiating event is provided in Table G-1 for IP2 and IP3. For IP2, 31 loss of offsite power sequences, including station blackout (SBO) events and internal flooding 32 initiators are the dominant contributors to CDF. For IP3, internal flooding initiators, loss-of-33 coolant accidents (LOCAs), SGTR events, and anticipated transient without scram (ATWS) 34 events are the dominant contributors to CDF. 35 There are several significant differences between the two Indian Point units that account for 36 differences in the risk contributions shown in Table G-1. These differences include: 37 The pressurizer PORV block valves are normally closed in Unit 2, and normally open in Unit 3. 38 Thus, the ability to use the PORVs for feed and bleed cooling in LOOP and partial power loss 39 events is greater at Unit 3, resulting in a lower CDF for LOOP events in Unit 3. I NUREG-1437, Supplement 38 G-2 December 2010 OAGI0001367E 00442
Appendix G 1 There are differences in the internal flooding sources and building configurations (e.g., ingress 2 and egress paths). These physical differences together with differences in the method for 3 calculating failure frequencies result in higher flood CDF frequencies in Unit 2. 4 In Unit 2, DC control power for EDGs and other loads on emergency 480 VAC busses is 5 supplied from either normal or emergency backup supplies, with automatic switching between 6 supplies. Unit 3 does not have this backup capability. This results in a lower CDF contribution 7 from loss of DC power events in Unit 2. 8 Table G-1. IP2 and IP3 Core Damage Frequency (Entergy, 2007) Initiating Event IP2 IP3
% %
CDF Contribution CDF Contribution (Per Year) to CDF (Per Year) to CDF Loss of offsite power 1 6.7x10- 6 38 1.2x10- 7 1 Internal flooding 4.7x10- 6 26 2.2x10- 6 20 LOCA 1.5x10-6 8 2.2x10- 6 19 6 Transients 1 1.2x10- 7 8.5x10- 7 7 7 6 ATWS 9.9x10- 6 1.5x10- 13 SBO 8.5x10- 7 5 7.2x10- 7 6 SGTR 7.2x10- 7 4 1.6x10-6 14 Loss of component cooling water 5.8x10- 7 3 1.lx10- 7 <1 (CCW) Loss of nonessential service water 3.0x10- 7 2 2.8x10- 7 2 Interfacing systems LOCA (ISLOCA) 1.5x10- 7 <1 1.5x10- 7 1 7 7 Reactor vessel rupture 1.0x10- <1 1.0x10- <1 Loss of 125 volts (V) direct current 5.8x10- 8 <1 1.0x10-6 9 (dc) power Total loss of service water system 4.4x10- 8 <1 5.4x10- 7 5 Loss of essential service water 1.9x10- 1O
<1 1.8x10-8 <1 Total CDF (internal events) 1.79x10-5 100 1.15x10-5 100 1 Contributions from SBO and ATWS events are noted separately and are not included in the reported values for loss of offsite power or transients.
9 The current Level 2 PSA models are based on the IPE models, with updates to reflect changes 10 to the plant and modeling techniques, including a 3.3 percent and 4.8 percent power uprate for 11 IP2 and IP3, respectively; inclusion of additional plant damage states (PDSs) to improve the 12 Level 1-Level 2 PSA interface; and updated accident progression and source term analyses 13 using a later version of the Modular Accident Analysis Program (MAAP) computer code. The 14 Level 1 core damage sequences are placed into one of 57 PDS bins that provide the interface 15 between the Level 1 and Level 2 analyses. The Level 2 models use a single containment event 16 tree (CET) with functional nodes representing both systemic and phenomenological events. 17 CET nodes are evaluated using supporting fault trees and logic rules. 18 The result of the Level 2 PSA is a set of nine release categories with their respective frequency 19 and release characteristics. The results of this analysis for IP2 and IP3 are provided in Tables December 2010 G-3 NUREG-1437, Supplement 38 OAGI0001367E 00443
Appendix G 1 E.1-9 (lP2) and E.3-9 (lP3) of the ER. The frequency of each release category was obtained by 2 summing the frequency of the individual accident progression CET endpoints binned into the 3 release category. Source terms were developed for each of the nine release categories using 4 the results of MAAP 4.04 computer code calculations. The release characteristics for each 5 release category were obtained by frequency-weighting the release characteristics for each 6 CET endpoint contributing to the release category (Entergy 2007). 7 The offsite consequences and economic impact analyses use the MACCS2 code to determine 8 the offsite risk impacts on the surrounding environment and public. Inputs for these analyses 9 include plant-specific and site-specific input values for core radionuclide inventory, source term 10 and release characteristics, site meteorological data, projected population distribution (within an 11 80-kilometer [50-mile] radius) for the year 2035, emergency response evacuation modeling, and 12 economic data. The magnitude of the onsite impacts (in terms of cleanup and decontamination 13 costs and occupational dose) is based on information provided in NUREG/BR-0184 (NRC 14 1997a). 15 In its SAMA analysis, as revised, Entergy estimated the dose to the population within 80 16 kilometers (50 miles) of the IP2 and IP3 site to be approximately 0.87 person-sievert (Sv; 87 17 person-rem) per year for IP2, and 0.95 Sv (95 person-rem) per year for IP3. The breakdown of 18 the total population dose by containment failure mode is summarized in Table G-2, based on 19 information provided in Entergy's SAMA re-analysis submitted subsequent to issuance of the 20 DSEIS (Entergy 2009). SGTR events and late containment failures caused by gradual 21 overpressurization by steam and noncondensable gases dominate the population dose risk at 22 both units. 23 Table G-2. Breakdown of Population Dose by Containment Failure Mode (Entergy 2009) IP2 IP3 Population Population Containment Failure Dose (Person- Percent Dose (Person Percent Mode Rem 1 Per Year) Contribution Rem 1 Per Contribution Year) Intact containment <0.1 <1 <0.1 <1 Basemat meltthrough 4.1 5 2.4 3 Gradual overpressure 28.3 32 16.8 18 Late hydrogen burns 3.6 4 2.1 2 Early hydrogen burns 8.6 10 3.2 3 Invessel steam explosion 0.6 <1 0.2 <1 Reactor vessel rupture 4.1 5 1.5 2 ISLOCA 6.6 8 4.2 4 SGTR 31.5 36 64.4 68 Total 87.4 100 94.8 100 I A "rem" (Roentgen equivalent man) is a standard unit used to measure the dose equivalent (or effective dose) of radiation, which combines the amount of energy from ionizing radiation that is deposited in human tissue, along with the medical effects of the particular type of radiation (alpha, beta, gamma or neutron) involved. As defined in 10 CFR 20.1004, a rem is a dose-equivalent quantity of radiation equal to the absorbed dose in "rads" (radiation absorbed dose). A "person-rem" is the total dose (in rems) received by a population. One person-rem = 0.01 Sv. 24 25 G.2.2 Review of Entergy's Risk Estimates NUREG-1437, Supplement 38 G-4 December 2010 OAGI0001367E 00444
Appendix G 1 2 Entergy's determination of offsite risk at IP2 and IP3 is based on the following four major 3 elements of analysis: 4 (1) The Level 1 and Level 2 risk models that form the bases for the I PE submittals (Con Ed 5 1992, NYPA 1994) and the IPEEE submittals (Con Ed 1995,NYPA 1997); 6 (2) The major modifications to the IPE models that have been incorporated in the IP2 and 7 IP3 2007 PSA updates; 8 (3) Adjustments to the IPEEE seismic and fire risk results to represent recent plant changes, 9 updated failure probabilities, and more realistic assumptions; 10 (4) The MACCS2 analyses performed to translate fission product source terms and release 11 frequencies from the Level 2 PSA model into offsite consequence measures. 12 Each of these analyses was reviewed to determine the acceptability of Entergy's risk estimates 13 for the SAMA analysis, as summarized below. 14 The NRC staff's reviews of the IP2 and IP3 IPE submittals are described in the NRC reports 15 dated August 14,1996 (NRC 1996) and October 20,1995 (NRC 1995). for IP2 and IP3, 16 respectively. Based on its review of the IPE submittals and responses to RAls, the NRC staff 17 concluded that the IPE submittals met the intent of Generic Letter (GL) 88-20; that is, the 18 licensee's IPE process is capable of identifying the most likely severe accidents and severe 19 accident vulnerabilities. Although no vulnerabilities were identified in the IPE, several plant 20 improvements were identified. These improvements have either been implemented at the site 21 or addressed by a SAMA (Entergy 2007). These improvements are discussed in Section G.3.2. 22 There have been three revisions to the IP2 PSA model and two revisions to the IP3 PSA model 23 since the respective IPE submittals. A comparison of the internal events CDF between the IPE 24 submittals and the current PSA models indicates a decrease of approximately 45 and 75 percent for IP2 and IP3, respective~ (from 3.13x1 0- per year to 1. 79x1 0- per year for IP2 and 5 5 25 26 from 4.40x1 0- 5 per year to 1.15x1 0- per year for IP3). A description of those changes that 27 resulted in the greatest impact on the internal-event CDF is provided in Sections E.1.4 and 28 E.3.4 of the ER (Entergy 2007) and in response to a staff RAI (Entergy 2008a) and is 29 summarized in Tables G-3a and G-3b for IP2 and IP3, respectively. 30 December 2010 G-5 NUREG-1437, Supplement 38 I OAGI0001367E 00445
Appendix G 1 Table G-3a. IP2 PSA Historical Summary PSA Summary of Changes from Prior Model CDF Version (per year) 1992 IPE submittal (excluding internal flooding) (RISKMAN) 3.13x10- 5 2.19x10- 5 Update 5/2003 PSA Update (RISKMAN)
- credited recovery of feedwater and condensate
- added treatment of cross-header common-cause failure (CCF) for essential and nonessential service water headers
- updated equipment performance and unavailability data
- revised human error probabilities based on thermal-hydraulic calculations
- updated reactor coolant pump (RCP) seal LOCA model
- added treatment of internal flooding events Rev. 0 1.71x10- 5 3/2005 PSA update (Computer-Aided Fault-Tree Analysis code [CAFTA])
- updated initiating event. component failure, and unavailability databases
- updated offsite power recovery data per EPRI 1009889
- revised internal flooding analysis, including pipe-break frequencies and human error probabilities
- changed CCF model from multiple Greek letter to Alpha method
- updated human reliability analysis (HRA) method to the EPRI HRA method
- updated RCP seal LOCA model to WCAP-16141 (WOG2000)
- updated ISLOCA model to address ISLOCAs inside containment. to credit mitigation only for small LOCAs outside containment. and to remove credit for makeup to the refueling water storage tank (RWST)
I NUREG-1437, Supplement 38 G-6 December 2010 OAGI0001367E 00446
Appendix G PSA Summary of Changes from Prior Model CDF Version (~er ~ear) 1.79x10- 5 Rev. 1 2/2007 P5A update
- updated selected initiating event frequencies
- updated offsite power recovery model per NUREG/CR-6890
- included CCF for plugging service water pump strainers
- revised model to reflect that normal offsite power feeds to the 480-V ac safeguards buses do not trip on a safety injection (51) signal without a concurrent loss of offsite power
- added credit for Indian Point Unit 1 (lP1) station air compressors for scenarios that do not involve loss of offsite power
- revised auxiliary feedwater (AFW) success criterion to require flow to two (rather than one) steam generators for normal (non-ATW5) res~onse 1 Table G-3b. IP3 PSA Historical Summary PSA Summary of Changes from Prior Model CDF Version (~er ~ear) 1994 6
IPE submittal (including internal flooding CDF of 6.5x1 0- ) 4.40x10- 5 Rev. 1 1.35x10- 5 6/2001 P5A Update
- updated initiating event, component failure, and unavailability databases
- updated offsite power recovery model per NUREG/CR-5496
- revised and added CCF component groups consistent with the most recent probabilistic risk assessment (PRA) practices, and updated CCF data
- revised HRA to reflect EOP changes
- updated RCP seal LOCA model per Brookhaven model, including credit for qualified high-temperature RCP seals December 2010 G-7 NUREG-1437, Supplement 38 I OAGI0001367E 00447
Appendix G
- incorporated major plant design changes, including:
- replacement of power-operated relief valves (PORVs) to eliminate leakage and allow operation with the block valve open
- reassignment of power supplies to emergency diesel generator (EDG) room exhaust fans to eliminate dependencies
- modification of backup battery charger 35 to be able to be powered from 480-V MCC 36C, 36D, or 36E
- installation of a diesel-driven station air compressor
- installation of temperature detectors to provide control room alarm if high temperature on the 15 and 33 feet (ft) elevation of the control building
- installation of a waterproof door to the deluge valve station Rev. 2 1.15x10- 5 2/2007 PSA Update
- added a total loss of service water initiating event
- updated offsite power recovery model per NUREG/CR-6890
- changed CCF model from modified Beta method to Alpha method
- updated RCP seal LOCA model to WCAP-16141 (WOG2000)
- revised AFW success criterion to require flow to two (rather than one) steam generators for normal (non-A TWS) response
- modified success criteria for cooling of internal recirculation pumps to remove credit for cooling by redundant systems
- removed the credit for an offsite gas turbine (which is no longer maintained) 1 I NUREG-1437, Supplement 38 G-8 December 2010 OAGI0001367E 00448
Appendix G 1 The CDF values from the IP2 and IP3 IPE submittals (3.13x1 0- per year and 4.40x10- 5 per 5 2 year, respectively) are near the average of the CDF values reported in the IPEs for pressurized-3 water reactors (PWRs) with dry containments. Figure 11.2 of NUREG-1560 shows that the IPE-4 based total internal events for these plants range from 9x10- 8 to 8x1 0- 5 per year, with an 5 average CDF for the group of 2x1 0- 5 per year (N RC 1997b). The NRC staff recognizes that 6 other plants have updated the values for CDF subsequent to the IPE submittals to reflect 7 modeling and hardware changes. The current internal event CDF results for IP2 and IP3 8 (1. 79x1 0- 5 per year and 1.15x1 0- 5 per year, respectively) are comparable to those for other 9 plants of similar vintage and characteristics. 10 The NRC staff considered the peer reviews performed for the IP2 and IP3 PSAs and the 11 potential impact of the review findings on the SAMA evaluation in order to reach a conclusion 12 regarding adequacy of the PRA to support SAMA evaluation. In the ER Entergy described the 13 peer review by the (former) Westinghouse Owner's Group (WOG) of the IP2 PSA model, 14 conducted in May 2002, and of the IP3 PSA model, conducted in January 2001. The IP2 model 15 reviewed was an updated version of the IPE that predated the May 2003 version described in 16 Table G-3a. Similarly, the IP3 model reviewed was an updated version of the IPE that predated 17 the June 2001 version described in Table G-3b. 18 For both IP2 and IP3, the ER states that all of the technical elements were graded as sufficient 19 to support applications requiring the capabilities defined for grade 2 (e.g., risk-ranking 20 applications). In addition, most of the elements were further graded as sufficient to support 21 applications requiring the capabilities defined for grade 3 (e.g., risk-informed applications 22 supported by deterministic insights). 23 For IP2, the ER states that there were no Level A findings (for which immediate model changes 24 would have been appropriate) from the peer review. Although a number of minor model 25 corrections were made following the peer review, no significant changes were made to the 26 model structure or underlying assumptions in the May 2003 PSA update. The IP2 model was 27 subsequently converted from the support-state RISKMAN model to a linked-fault-tree CAFTA 28 model. Entergy indicates that the conversion effort included a number of modeling changes for 29 consistency with other Entergy models and addressed the remaining findings and observations 30 (F&Os) from the IP2 Peer Review (i.e., Level B, C, and D F&Os), where appropriate. In 31 addition, the issues raised during the peer review of the IP3 model were also examined for 32 applicability to IP2; all applicable issues were addressed consistent with the treatment used for 33 IP3. For IP3, the ER states that all Level A and B F&Os from the IP3 peer review were 34 addressed in the final version of the Revision 1 PSA model for IP3, which was issued in 35 June 2001, and that less significant (Level C & D) F&Os were addressed, where appropriate. 36 Entergy indicates that the model changes incorporated in the IP2 Revision 1 and the IP3 37 Revision 2 PSA models also underwent an internal independent review by Entergy PSA staff 38 and plant personnel and were subjected to a focused self-assessment to demonstrate technical 39 quality in preparation for the NRC Mitigating Systems Performance Indicator (MSPI) program in 40 2006. In addition, the IP2 model was also subjected to a weeklong review by a team of industry 41 peers from outside the Entergy staff in July 2005. Finally, the ER indicates that the model 42 changes in the IP2 Revision 1 and the IP3 Revision 2 PSA models were peer reviewed for 43 accuracy and consistency by members of the Entergy Nuclear Systems Analysis Group not 44 directly involved in their implementation (Entergy 2007). December 2010 G-9 NUREG-1437, Supplement 38 I OAGI0001367E 00449
Appendix G 1 Given that the IP2 and IP3 internal events PSA models have been peer reviewed and the peer 2 review findings were either addressed or judged to have no adverse impact on the SAMA 3 evaluation, and that Entergy has satisfactorily addressed the NRC questions regarding the PSA 4 (NRC 2007, NRC 2008, Entergy 2008a, Entergy 2008b). The NRC staff concludes that the 5 internal events Level 1 PSA model for the plants is of sufficient quality to support the SAMA 6 evaluation. 7 Section E.1.4 of the ER states that for IP2, internal flooding was examined as part of the 8 IPEEE, while Section E.3.4 indicates that internal flooding was included in the IP3 IPE. Internal 9 flooding was later incorporated into the IP2 May 2003 PSA update, resulting in the consistent 10 treatment of internal flooding for the two units. 11 The IP21PEEE analysis of internal flooding yielded a CDF of 6.6x10- 6 per year while the IP3 IPE 12 internal flooding analysis yielded a CDF of 6.5x1 0- 6 per year. For each plant three scenarios 13 accounted for more than 80 percent of the flood CDF. All these scenarios result in a reactor trip 14 and the nonrecoverable loss of safety-related switchgear from flooding sources located in or 15 adjacent to each unit's 480-V switchgear room. 16 The internal flooding analysis was included in the WOG peer review. In response to an RAI, 17 Entergy provided a detailed discussion on the incorporation of peer review comments for IP2 18 and IP3. For IP2, the licensee indicated that there were only two WOG peer review findings 19 associated with the internal flooding analysis. 20 The first finding related to use of a flooding event screening criterion of 1x1 0- 6 per year in the 21 analysis. That criterion, however, was only applied to a scenario involving the potential for 22 intercompartmental flooding from the EDG building to the electrical tunnel and involved leakage 23 that could be accommodated by existing plant drains rather than catastrophic failure. Therefore, 24 it was determined that screening of this scenario was appropriate and a model change was not 25 needed. 26 The second finding was a general concern that the flooding study had not been updated since 27 1993. The IP2 internal flooding analysis was subsequently updated in 2005 (Entergy 2008a). 28 For IP3, the licensee indicated that the IP3 WOG peer review concluded that the internal 29 flooding analysis demonstrated a superior combination of industry data and models to obtain 30 plant-specific piping rupture frequencies. The peer review identified four F&Os related to the 31 internal flooding analysis. One F&O was a strength that warranted no change to the model. 32 The other findings related to incorporation of historical data, assembly of walkdown records, and 33 consideration of applicable draft American Society of Mechanical Engineers (ASME) standards 34 to enhance the flooding analysis. The findings related to the incorporation of historical data and 35 to the assembly of walkdown records were resolved during preparation of the final version of 36 Revision 1 of the IP3 PSA model. The draft ASME standards identified by the review team were 37 reviewed, and no modeling changes were warranted. Therefore, all internal flooding review 38 comments that affect the model were addressed in the model used for the SAMA analysis 39 (Entergy 2008a). 40 As indicated above, the current IP2 and IP3 PSA models do not include external events. In the 41 absence of such an analysis, Entergy used the IP2 and IP3 IPEEEs, in conjunction with minor 42 adjustments in fire and seismic scenarios, to identify the highest risk accident sequences and 43 the potential means of reducing the risk posed by those sequences, as discussed below. I NUREG-1437, Supplement 38 G-10 December 2010 OAGI0001367E 00450
Appendix G 1 The IP2 and IP3 IPEEEs were submitted in December 1995 (Con Ed 1995) and September 2 1997 (NYPA 1997), in response to Supplement 4 of GL 88-20 (NRC 1991). These submittals 3 included a seismic PRA analysis, a fire PRA, a high-wind risk model, and a screening analysis 4 for other external events. While no fundamental weaknesses or vulnerabilities to severe 5 accident risk in regard to the external events were identified, several opportunities for risk 6 reduction were identified and implemented, as discussed below. In letters dated August 13, 7 1999, and February 15, 2001, the NRC staff concluded that the submittals for IP2 and IP3 8 generally met the intent of Supplement 4 to GL 88-20, and that the licensee's IPEEE process is 9 capable of identifying the most likely severe accidents and severe accident vulnerabilities (NRC 10 1999, NRC 2001). For IP3, the NRC staff identified an issue related to misdirection of manual 11 fire suppression, which can fail equipment but decided to resolve that issue separately from the 12 IPEEE. 13 The IPEEE seismic analyses employed a seismic PSA following the guidance of NUREG-1407. 14 The IPEEE estimated a seismic CDF of 1.46x10-5 and 4.4x10- 5 per year for IP2 and IP3, 15 respectively. Components related to decay heat removal were modeled in the seismic PSA for 16 both units. No unique decay-heat removal vulnerabilities were found for either unit based on the 17 quantitative risk results. Seismic-induced flooding and fires were examined as part of the 18 IPEEE process for both units. Specific seismic-fire interactions were identified by Entergy, as 19 listed in Table 2.12 of NUREG-1742 (NRC 2002). However, upon further consideration, the 20 NRC staff concluded that the contribution to the CDF is small because the conditional 21 probability of a fire, given an earthquake, is small (NRC 2001). For IP2 and IP3, the IPEEEs 22 also addressed the issue of relay chattering through a detailed examination of the relays used in 23 IP2 and IP3 against the low-capacity relay list found in Appendix D of Electric Power Research 24 Institute (EPRI) NP-7148-SL. A list of the dominant contributors to the seismic CDF for IP2 and 25 IP3 is provided in Tables G-4a and G-4b, based on the information provided in response to an 26 RAI (Entergy 2008a). 27 In Section 4.21.5.4 of the ER Entergy noted that conservative assumptions were used in the 28 seismic analyses, including the use of a single, conservative surrogate element to model the 29 most seismically rugged components, the assumption that redundant components are 30 completely correlated in determining the probability of seismic-induced failure, and the 31 assumption that seismic-induced ATWS events are not recoverable. For purposes of the SAMA 32 evaluation, Entergy performed a reevaluation of the seismic CDF, as discussed below. For IP2, 33 as a result of an IPEEE recommendation, the CCW surge tank hold-down bolts were upgraded. 34 This effectively eliminated the contribution from the failure of the CCW surge tank, reducing the 35 seismic CDF for IP2 from 1.46x1 0- 5 per year to approximately 1.06x1 0- 5 per year. For IP3, no 36 seismic improvements were recommended. However, Entergy reevaluated the seismic PSA to 37 reflect updated random component failure probabilities and to model recovery of onsite power 38 and local operation of the turbine-driven AFW pump. This reduced the seismic CDF for IP3 39 from 4.4x1 0- 5 per year to 2.65x1 0- 5 per year. These reduced CDF values were used in 40 developing the external events mUltipliers in the SAMA benefit analysis, as discussed later. December 2010 G-11 NUREG-1437, Supplement 38 I OAGI0001367E 00451
Appendix G 1 Table G-4a. IP2 Seismic Scenarios and Their Contribution to Seismic CDF CDF (per year) Seismic Scenario Description Percent Frequency Contribution Failure of CCW, primarily caused by failure of surge tank hold- 4.2x10- 6 29 down bolts Failure of the turbine building frame and consequential failure of 3.5x10- 6 24 control building Collapse of IP1 super heater stack onto control building 3.0x10- 6 21 6 Loss of 480 V emergency power 1.3x10- 9 Loss of service water (seismic failure of service water pumps) 1.3x10-6 9 7 Seismic-induced loss of offsite power 4.4x10- 3 7 Other 7 .4x1 0- 5 Total Seismic CDF from Dominant Scenarios 1.46x10-5 100 2 Table G-4b. IP3 Seismic Scenarios and Their Contribution to Seismic CDF CDF (per year) Seismic Scenario Description Percent Frequency Contribution Loss of 480-V ac electric power with consequential RCP seal 1.9x10- 5 43 LOCA Loss of CCW with consequential RCP seal LOCA 1.0x10- 5 23 Loss of offsite power with seismic failures of the RHR heat 9.2x10- 6 21 exchangers, the condensate stage tank, containment instrument racks, and AFW Surrogate element (represents screened out, rugged 3.5x10- 6 8 components and structures, where failure leads to core damage) Seismic-induced ATWS 2.2x10- 6 5 5 Total Seismic CDF from Dominant Scenarios 4.4x10- 100 3 I NUREG-1437, Supplement 38 G-12 December 2010 OAGI0001367E 00452
Appendix G 1 The IPEEE fire analyses employed a combination of PRA with the EPRl's fire-induced 2 vulnerability evaluation methodology. The evaluation was performed in four phases: 3 (1) Qualitative screening; 4 (2) Quantitative screening; 5 (3) Fire damage evaluation screening; 6 (4) Fire scenario evaluation and quantification. 7 Each phase focused on those fire areas that did not screen out in the prior phases. The final 8 phase involved using the IPE model for internal events to quantify the CDF resulting from a fire-9 initiating event. Each fire area that remained after screening was then treated as a separate 10 initiating event and was propagated through the model with the appropriate model modifications. 11 The CDF for each area was obtained by accounting for the frequency of a fire in a given fire 12 area; the conditional core damage probability associated with that fire scenario in the fire area, 13 including, where appropriate, the impact of fire suppression; and fire propagation. The potential 14 impact on containment performance and isolation was evaluated following the core damage 15 evaluation. The total fire CDF from the IPEEE was estimated to be 1.8x1 0-5 per year for IP2 16 (Con Ed 1995) and 5.6x10- 5 per year for IP3 (NYPA 1997). 17 In Section 4.21.5.4 of the ER Entergy noted that conservative assumptions were used in the 18 IPEEE fire analyses, including overestimation of the frequency and severity of fires; 19 conservative treatment of open, hot short and short -to-ground circuits; and assumption of a 20 plant trip for all fires. For purposes of the SAMA evaluation, Entergy performed a reevaluation 21 of the fire CDF, as discussed below. 22 For IP2, Section E.1.3.2 of the ER notes that the IP2 IPEEE fire model had the following known 23 conservatisms: 24 The main feedwater and condensate systems were assumed to be unavailable in all 25 scenarios, even when their power source was not affected by the fire scenario. 26 The pressurizer PORV block valves were assumed to be in the limiting position (open or 27 closed) to maximize the impact of the fire. 28 All sequences involving RCP seal LOCAs were assumed to lead to complete seal 29 failure. 30 For the purpose of the SAMA evaluation, Entergy reevaluated the dominant IPEEE fire 31 sequences (sequences with CDF contributions greater than 1x1 0- 7 per year) to reduce the 32 conservatisms associated with main feedwater and condensate unavailability and PORV block 33 valve assumptions and to reflect updated modeling associated with RCP-seal LOCAs. In 34 response to a RAI, Entergy explained that other portions of the fire analysis methodology and 35 modeling were not revised as part of the SAMA update. Entergy also noted that preliminary fire 36 analysis results were inadvertently included in the ER and provided a corrected, revised IP2 fire 37 CDF value of 8.4x10- 6 per reactor year (Entergy 2008a). These revised results are included in 38 Table G-5a and were used in developing the external events mUltiplier in the SAMA benefit 39 analysis. 40 Similarly, for IP3, Section E.3.3.2 of the ER notes that the IP3 IPEEE fire model had known 41 conservatisms in estimating the fire ignition frequency (e.g., an air compressor ignition December 2010 G-13 NUREG-1437, Supplement 38 OAGI0001367E 00453
Appendix G 1 frequency did not take into account that the compressor would operate only for a total of about 2 5 days per year). Also, at the time of IPEEE, the automatic suppression systems in some plant 3 areas were placed in "manual" mode because of concerns with seismic interactions. 4 Subsequently, some fire suppression systems were extensively modified so that the 5 suppression mode could have been returned to "automatic." As part of the update for the 6 purpose of SAMA evaluations, Entergy performed a reanalysis of the fire CDF and provided a 7 revised IP3 fire CD F value of 2. 55x1 0- 5 per year (Entergy 2007). These revised results are 8 included in Table G-5b and were used to develop the external events mUltiplier in the SAMA 9 benefit analysis. 10 Table G-5a. IP2 Fire Areas and Their Contribution to Fire CDF CDF (per year) Fire Area Area Description IPEEE Fire Reanalysis 1A Electrical tunnel/pipe penetration area 9.2x10- 7 6.6x10- 7 2A Primary water makeup area 1.lx10-6 5.1x10- 7 11 Cable spreading room 4.3x10- 6 2.0x10- 6 14 Switchgear room 3.8x10- 6 1.4x10-6 15 Control room 7.1x10- 6 3.0x10- 6 74A Electrical penetration area 1.lx10-6 7.3x10- 7 6A Drumming and storage station 1.5x10-9 1.5x10-9 32A Cable tunnel 9.6x10- 8 9.6x10- 8 1 CCW pump room 2.2x10- 9 2.2x10- 9 22/63A Service water intake 7.5x10- 9 7.5x10- 9 23 AFW pump room 6.2x10- 9 6.2x10- 9 Total Fire CDF from Major Fire Areas 1.8x10-5 8.4x10-6 11 Table G-5b. IP3 Fire Areas and Their Contribution to Fire CDF CDF (per year) Fire Area Area Description IPEEE Fire Reanalysis 14 480-V switchgear room 3.5x10- 5 1.3x10- 5 11 Cable spreading room 6.8x10- 6 5.3x10- 6 15 Control room 3. 7x1 0- 6 3. 7x1 0- 6 480-V switchgear room/south turbine 14/37A 4.5x10- 6 1.8x10- 7 building 10 Diesel generator 31 2.1x10- 6 2.0x10- 6 102A Diesel generator 33 1.9x10-6 4.7x10- 9 NUREG-1437, Supplement 38 G-14 December 2010 OAGI0001367E 00454
Appendix G CDF (per year) Fire Area Area Description IPEEE Fire Reanalysis 60A Upper electrical tunnel 7.lxl0- 7 7.lxl0- 7 lOlA Diesel generator 32 3.4xl0- 7 5.2xl0- 9 7A Lower electrical tunnel 2.8xl0- 7 2.8xl0- 7 1 December 2010 G-15 NUREG-1437, Supplement 38 I OAGI0001367E 00455
Appendix G 1 Table G-5b (continued) CDF (per year) Fire Area Area Description IPEEE Fire Reanalysis 23 AFW pump room 2.3x10- 7 2.3x10- 7 37A south turbine building elevation 15 ft 3.8x10- 8 3.8x10- 8 17A primary auxiliary building (PAB) corridor 3.2x10- 8 3.2x10- 8 Total Fire CDF from Major Fire Areas 5.6x10-5 2.6x10-5 2 For high-wind and tornado events, the ER noted that IP2 structures and systems predate the 3 1975 Standard Review Plan (SRP) criteria. Therefore, a detailed PRA was developed as part of 4 the IPEEE analysis to address the impact of high-wind events at IP2. The equipment of 5 concern includes that located within sheet metal clad structures (e.g., the gas turbine and EDG 6 components) and equipment in the yard, including the condensate storage tank (CST) and 7 service water pumps. The CDF for high-wind events was estimated in the IPEEE to be 8 3.03x10- 5 per year. In Section E.1.3.3.1 and E.1.4.3 of the ER Entergy noted that its planned 9 removal of the gas turbines from service would reduce the probability of recovering power from 10 the offsite gas turbine location (as modeled in the PRA), but as shown by a sensitivity analysis 11 this impact would be offset by the increased reliability and ruggedness of the new IP2 12 SBO/Appendix R diesel generator relative to that of the gas turbines. Accordingly, Entergy used 13 the IPEEE high-wind CDF of 3.03x1 0- 5 per year in determining the external event mUltiplier for 14 IP2, as discussed later. 15 The IP3 structures and systems also predate the SRP criteria, but the IPEEE found the 16 estimated CDF for high-wind events to be below the 1x1 0- 6 per year screening criterion (from 17 NUREG-1407). This conclusion is based in part on the assumption that high water levels are 18 maintained in the condensate storage and city water storage tank, thus preventing significant 19 wind load and pressure differential damage to the tanks that provide water to the AFW system 20 (NYPA 1997). Because of the low CDF value, the IP3 external-event mUltiplier does not 21 explicitly account for risks associated with high-wind and tornado events. 22 The IP2 and IP3 IPEEE submittals examined a number of other external hazards, including 23 external flooding, ice formation, and accidents involving hazardous chemicals, transportation 24 (e.g., accidental aircraft impacts), or nearby industrial facilities. These evaluations followed the 25 screening and evaluation approaches specified in Supplement 4 to GL 88-20 (NRC 1991). No 26 risks to the plant from external floods, ice formation, or accidents involving hazardous 27 chemicals, transportation, or nearby facilities, were identified that might lead to core damage 28 with a predicted frequency in excess of 1x1 0- 6 per year (Con Ed 1995, NYPA 1997). For IP3, 29 scenarios involving hydrogen explosions within the turbine building, the pipe trench between the 30 PAB and containment the hydrogen shed area in the containment access facility, and the pipe 31 chase on the 73-ft elevation of the northeast corner of the PAB were identified that in total, 32 could result in core damage with an estimated frequency slightly above 1x1 0- 6 per year. As a 33 result Phase II SAMA 53 was identified to evaluate the change in plant risk from plant 34 modifications to install an excess flow valve to reduce the risk associated with hydrogen 35 explosions inside the turbine building or PAB. Entergy noted that the risks from deliberate I NUREG-1437, Supplement 38 G-16 December 2010 OAGI0001367E 00456
Appendix G 1 aircraft impacts were explicitly excluded, since this was being considered in other forums, along 2 with other sources of sabotage. 3 Based on the aforementioned results, Entergy estimated that the external event CDF is 4 approximately 2.8 and 4.52 times that of the internal-event CDF for IP2 and IP3, respectively. 5 For IP2, this factor was based on an internal event CDF of 1. 79x1 0- 5 per year, a seismic CDF of 6 1.06x10-5 per year, a fire CDF of 8.4x1 0- 6 per year, and a high-wind CDF contribution of 7 3.03x10- 5 per year. For IP3, this factor was based on an internal-event CDF of 1.15x1 0- 5 per 8 year, a seismic CDF of 2.65x1 0- 5 per year, and a fire CDF of 2.55x1 0- 5 per year. Accordingly, 9 the total CDF from internal and external events would be approximately 3.8 times the internal-10 event CDF for IP2 and 5.5 times the internal event CDF for IP3. 11 In the SAMA analysis submitted in the ER Entergy increased the benefit that was derived from 12 the internal-event model by a factor 3.8 and 5.5 to account for the combined contribution from 13 internal and external events for IP2 and IP3, respectively. For SAMA candidates that address 14 only a specific external event and have no bearing on internal-event risk (e.g., IP2 SAMA 66-15 Harden EDG Building Against High Winds). Entergy derived the benefit directly from the 16 external-event risk model and then increased the benefit by the mUltipliers identified earlier. 17 This resulted in a bounding benefit for the SAMA candidates addressing a specific external 18 event. The NRC staff agrees with the licensee's overall conclusion concerning the impact of 19 external events and concludes that the licensee's use of a mUltiplier of 3.8 and 5.5 for IP2 and 20 IP3, respectively, to account for external events is reasonable for the purposes of the SAMA 21 evaluation. This is discussed further in Section G.6.2. 22 The NRC staff reviewed both the general process used by Entergy to translate the results of the 23 Level 1 PSA into containment releases and the results of the Level 2 analysis, as described in 24 the ER and in response to the NRC staff's RAls (Entergy 2007, Entergy 2008a). The 25 containment designs and the Level 2 analyses are similar for IP2 and IP3. The NRC staff notes 26 that after reviewing information provided by Entergy, the current Level 2 PSA models are based 27 on the IPE models, with updates to reflect changes to the plant and modeling techniques, 28 including a 3.3 percent and 4.8 percent power uprate for IP2 and IP3, respectively; inclusion of 29 additional PDSs to improve the Level 1-Level 2 PSA interface; and updated accident 30 progression and source term analyses using a later version of the MAAP computer code. 31 The Level 1 core damage sequences are placed into one of 57 PDS bins that provide the 32 interface between the Level 1 and Level 2 analyses. The PDSs are defined by a set of 33 functional characteristics for system operation that are important to accident progression, 34 containment failure, and source-term definition. The Level 2 models use a single CET with 35 functional nodes representing both systemic and phenomenological events. The CET is used to 36 determine the appropriate release category for each Level 2 sequence. CET nodes are 37 evaluated using supporting fault trees and logic rules. 38 Entergy characterized the releases for the spectrum of possible radionuclide release scenarios 39 using a set of nine release categories, defined based on the timing and magnitude of the 40 release and whether the containment remains intact fails, or is bypassed. The frequency of 41 each release category was obtained by summing the frequency of the individual accident 42 progression CET endpoints binned into the release category. The release characteristics for 43 each category were obtained by frequency weighting the release characteristics for each CET 44 endstate contributing to the release category. The source-term release fractions for the CET December 2010 G-17 NUREG-1437, Supplement 38 OAGI0001367E 00457
Appendix G 1 endstates were estimated based on the results of plant-specific analyses of the dominant CET 2 scenarios using the MAAP (Version 4.04) computer program. The release categories and their 3 frequencies and release characteristics are presented in Tables E.1-1 0 and E.3-10 of the ER. 4 During the review of the Level 2 analysis, the NRC staff could not determine the modeling 5 approach used to assess the likelihood of a thermally induced SGTR (TI-SGTR) following core 6 damage in the current IP2 and IP3 PSAs. Entergy explained that TI-SGTR events are 7 considered in the Level 2 analyses for two conditions: 8 (1) High reactor cooling system (RCS) pressure and steam generators dry (no secondary-9 side cooling); 10 (2) High RCS pressure and steam generators initially dry, with recovery of secondary-side 11 cooling before challenging the steam generator tubes. 12 The first condition applies to transient event sequences in which RCS pressure is at the 13 pressurizer PORV setpoint at the time of core damage. No credit is taken for recovery of 14 secondary-side cooling in these sequences. Entergy states that a TI-SGTR probability of 0.01 15 is used for this case, based on Table 2-1 of NUREG/CR-4551, Volume 2, Revision 1, Part 1, 16 which shows a distribution that ranges from 1x1 0- 5 to 0.1208 and a mean value of 0.018. The 17 second condition applies to SBO sequences in which RCS pressure is at the pressurizer PORV 18 setpoint at the time of core damage. Entergy states that a TI-SGTR probability of 5x1 0- 4 is used 19 for this SBO case, based on the expectation that the steam generators will not dry out until after 20 battery depletion and that secondary-side cooling and other mitigating system functions could 21 be recovered before that time. The value is stated as being derived from the transient case 22 value of 0.01 combined with the human error probability of 5.2x1 0- 2 for failure to align AFW 23 following ac power recovery. Entergy explained that a stuck-open main steam safety valve or 24 other secondary-side depressurization event is required to create the large differential pressure 25 needed for the conditional TI-SGTR probabilities assumed above and that the Level 2 analyses 26 conservatively did not account for the probability that these additional failures do not occur 27 (Entergy 2008b). A sensitivity analysis that increases the probability of the TI-SGTR was 28 developed at the staff's request and is described in Section G.6.2. 29 The NRC staff's reviews of the Level 2 IPEs for IP2 and IP3 concluded that the analyses 30 addressed the most important severe accident phenomena normally associated with large dry 31 containments and identified no significant problems or errors (N RC 1995, NRC 1996). It should 32 be noted, however, that the current Level 2 models are revisions to those of the IPE. The Level 33 2 PSA models were included in the WOG peer reviews mentioned previously. The changes to 34 the Level 2 models to update the methodology and to address the peer review 35 recommendations are described in Sections E.1.4 and E.3.4 of the ER (Entergy 2007) and in 36 response to an RAI concerning peer review findings related to the Level 2 PSA model (Entergy 37 2008a). 38 In the RAI response, Entergy provided a detailed discussion of all the changes that resulted 39 from the incorporation of the WOG peer review of the Level 2 PRA. For IP2, the licensee 40 indicated that there were two Level C F&Os related to the Level 2 analysis. One issue dealt 41 with treatment of containment failure from energetic events (e.g., direct containment heating, 42 hydrogen combustion, in-vessel steam explosions, and ex-vessel steam explosions). The other 43 issue related to treatment of a stuck-open main steam safety valve following an SGTR core I NUREG-1437, Supplement 38 G-18 December 2010 OAGI0001367E 00458
Appendix G 1 damage event. Entergy indicated that all peer review recommendations associated with the 2 WOG review were incorporated in Revision 0 of the IP2 PSA (3/2005). 3 For IP3, Entergy indicated that there were six F&Os from the WOG peer review team related to 4 the Level 2 analysis: 5
- One F&O was related to the containment strength that was considered for a plant-6 specific containment structural analysis.
7
- One Level A F&0 recommended that the LE RF definition include the release of iodine 8 as well as cesium and tellurium.
9
- Two Level B F&Os were related to justification for the value used for ex-vessel 10 explosions, and an overestimation of the "Alpha mode"-induced containment failure 11 probability.
12
- One Level C F&0 recommended crediting repair and recovery of systems that affect 13 containment performance.
14
- One Level D F&0 was related to documentation.
15 Entergy indicated that all Level A and B F&Os were resolved and that changes were 16 incorporated as necessary in Revision 1 of the IP3 PSA (6/2001). Entergy also stated that the 17 Level C and D F&Os were addressed, as appropriate, in the next revision of the model 18 (Revision 2, 2/2007). 19 Based on the NRC staff's review of the Level 2 methodology, the fact that the Level 2 model 20 was reviewed in more detail as part of the WOG peer review and updated to address peer 21 review findings, and Entergy's responses to the RAls, the NRC staff concludes that the Level 2 22 PSAs for IP2 and IP3 are technically sound and provide an acceptable basis for evaluating the 23 benefits associated with various SAMAs. 24 As indicated in the ER the estimated IP2 and IP3 reactor core radionuclide inventories used in 25 the MACCS2 input are based on the current core configuration and a power level of 3216 26 megawatt thermal (MWt). The information was derived from Westinghouse Electric Company, 27 Core Radiation Sources to Support IP2 Power Uprate Project CN-REA-03-4 (3/7/2005). and 28 Westinghouse Electric Company, Core Radiation Sources to Support IP3 Stretch Power Uprate 29 (SPU) Project CN-REA-03-40 (5/19/2005). In response to an RAt Entergy confirmed that the 30 current core design and operational practice are consistent with this analysis and that there are 31 no planned future changes to reactor power level or fuel management strategies that would 32 affect the reactor core radionuclide inventory used in the MACCS2 analysis (Entergy 2008a). 33 The NRC staff reviewed the process used by Entergy to extend the containment performance 34 (Level 2) portion of the PSA to an assessment of offsite consequences (essentially a Level 3 35 PSA). This included consideration of the source terms used to characterize fission product 36 releases for the applicable containment release categories and the major input assumptions 37 used in the offsite consequence analyses. The MACCS2 code was used to estimate offsite 38 consequences. Plant-specific input to the code includes the source terms for each release 39 category and the reactor core radionuclide inventory (both discussed above). site-specific 40 meteorological data, projected population distribution within an 80-kilometer (50-mile) radius for 41 the year 2035, emergency evacuation modeling, and economic data. This information is 42 provided in Sections E.1.5 and E.3.5 of the ER for IP2 and IP3, respectively (Entergy 2007). December 2010 G-19 NUREG-1437, Supplement 38 OAGI0001367E 00459
Appendix G 1 As described in Sections E.1.5.2.6 and E.3.5.2.6 of the ER meteorological data for a 5-year 2 period from January 2000 to December 2004 were obtained from the Indian Point onsite 3 meteorological monitoring system. The 5-year data included 43,848 consecutive hourly values 4 of wind speed, wind direction, precipitation, and temperature. Missing data were estimated 5 using data substitution methods. These methods include substitution of missing data with valid 6 data from the previous hour and with data collected from other elevations on the meteorological 7 tower. The data for the 5-year period were averaged to provide a data file consisting of one 8 year of hourly readings representative of site meteorology. This data file was used as input to 9 the MACCS2 code for the SAMA analysis reported in the E R. 10 Subsequent to issuance of the DSEIS, a problem with the process used to numerically average 11 the site-specific meteorological data was identified. Entergy determined that the method used 12 to average the wind direction data was faulty and resulted in a lower frequency of winds blowing 13 toward the south than actually observed. Since a majority of the population near Indian Point is 14 in the southern semicircle of the 50-mile radius, this error resulted in a smaller population dose 15 and a smaller offsite economic cost than would be expected using the corrected method. 16 Accordingly, the dose and economic impacts of a severe accident and the estimated benefits of 17 candidate SAM As would be larger than was reported in the ER (Entergy 2009). 18 To address the meteorological data error's impact on the SAMA evaluation, Entergy performed 19 a separate MACCS2 analysis for each of the five single years of meteorological data. Entergy 20 compared the results and selected the year that resulted in the largest population dose (year 21 2000) as the representative year for use in the SAMA analysis. This approach circumvents the 22 problem associated with averaging wind directions, and is consistent with the intent of the ER to 23 provide results for representative site meteorology. Entergy updated the population dose and 24 offsite economic cost values for each containment release mode, and the estimated benefits for 25 each SAMA based on the meteorological data for year 2000. The correction in meteorological 26 data resulted in approximately a factor of 4 increase in population dose and offsite economic 27 cost values, and resulted in several additional SAMAs becoming potentially cost-beneficial 28 (Entergy 2009). This is discussed further in Section G.6.1. The NRC staff concludes that the 29 updated approach taken for collecting and applying the meteorological data in the SAMA 30 analysis is reasonable and acceptable. This is discussed further in section G.2.3. 31 The population distribution which the licensee used as input to the MACCS2 analysis was 32 estimated for the year 2035 based on information from the New York Statistical Information 33 System from 2000 to 2030, the New Jersey Department of Labor and Workforce Development 34 from 2000 to 2025, the Connecticut State Data Center from 2000 to 2020, and the Pennsylvania 35 State Data Center from 2000 to 2020. These data were used to project county-level resident 36 populations to the year 2035 using regression analysis. The 2035 transient population was 37 assumed to be the 2004 transient-to-permanent population ratio multiplied by the extrapolated 38 permanent population. The 2004 transient data were obtained from State tourism agencies. 39 The NRC staff notes that Entergy's projected 2035 population within a 50-mile radius of IP2 and 40 IP3 reported in Tables E.1-12 and E.3-12 of the Entergy ER (19.2 million people) is 41 approximately 15 percent greater than the 50-mile population obtained from NRC SECPOP2000 42 code (16.8 million) for the year 2003 (N RC 2003). This represents an average annual growth 43 rate of 0.4 percent which comports with Entergy's estimated growth rates reported in Section 44 2.6.1 of the ER. The NRC staff considers the methods and assumptions for estimating 45 population reasonable and acceptable for the purposes of the SAMA evaluation. NUREG-1437, Supplement 38 G-20 December 2010 OAGI0001367E 00460
Appendix G 1 Entergy did not credit evacuation either as part of the base-case analysis or for estimating the 2 benefit from SAMA cases. Entergy assumed a "no evacuation scenario" to conservatively 3 estimate the population dose. In response to an NRC staff RAt Entergy clarified that the "no 4 evacuation scenario" assumes that individuals within the 1O-mile evacuation zone continue 5 normal activity following a postulated accident without taking emergency response actions such 6 as evacuation or sheltering. Relocation actions within a 50-mile radius of the plant are still 7 modeled in the "no evacuation scenario." As such, individuals within hot spots or high-radiation 8 areas anywhere within the 50-mile zone are assumed to be relocated outside the 50-mile zone 9 until long-term protective actions reduce radiation levels (Entergy 2008a). As used in the 10 MACCS2 code, "evacuation" refers to the prompt movement of the population out of an affected 11 region (e.g., certain sectors of the EPZ) during the emergency-phase time period immediately 12 following an accident in accordance with the emergency evacuation plan. "Relocation" refers to 13 the movement of the population out of an affected region (e.g., within hot spots or high radiation 14 areas) during the intermediate phase or long term phase based on longer-term dose 15 considerations. The NRC staff concludes that the evacuation and relocation assumptions and 16 analysis are generally conservative and acceptable for the purposes of the SAMA evaluation. 17 Much of the site-specific economic data was obtained from the 2002 Census of Agriculture 18 (USDA 2002). These include the value of farm and nonfarm wealth. Other data, such as 19 population relocation cost daily cost for a person who is relocated, and cost of farm and 20 nonfarm decontamination were obtained from the Code Manual for MACCS2 (NRC 1997c). 21 The data from the MACCS2 Code Manual were inflation-adjusted using the consumer price 22 index corresponding to the year 2005. Information on regional crops was obtained from the 23 2002 Census of Agriculture. Crops for each county were mapped into the seven MACCS2 crop 24 categories. 25 MACCS2 requires an average value of nonfarm wealth (identified as VALWNF in MACCS2). 26 The county-level nonfarm property value was used as a basis for deriving VAL WN F and 27 resulted in a value of $163,631 per person. This does not explicitly account for the economic 28 value associated with tourism and business. In the ER Entergy assessed the impact of 29 including tourism and business losses using a sensitivity case. This sensitivity case assumed a 30 loss of $208,838 per person in the affected region, as opposed to $163,631 per person in the 31 base case. The NRC staff questioned the basis for the modified VALWNF value ($208,838 per 32 person) and the rationale for treating the loss of tourism and business in a sensitivity case rather 33 than in the baseline analysis (NRC 2007). In response, Entergy described the basis for the 34 modified VAL WN F value and explained that the impact of lost tourism and business was not 35 modeled in the baseline analysis because the level of tourism and business activity can be re-36 established in time. Nevertheless, Entergy provided the results of a revised uncertainty analysis 37 using the modified VALWNF value (Entergy 2008a). As a result three additional potentially 38 cost-beneficial SAMAs were identified (SAMAs 9 and 53 for IP2 and SAMA 53 for IP3). In 39 response to an RAI, Entergy indicated that these SAMAs have been submitted for engineering 40 project cost-benefit analysis to obtain a more detailed examination of their viability and 41 implementation costs (Entergy 2008b). As described in Section G.6.2, the NRC staff has 42 adopted the case incorporating lost tourism and business as its base case, given that it may 43 take years to re-establish the level of tourism and business activity following a severe accident. 44 In the draft SEIS, the NRC staff reached a preliminary conclusion that the methodology used by 45 Entergy to estimate the offsite consequences for IP2 and IP3 provides an acceptable basis from December 2010 G-21 NUREG-1437, Supplement 38 OAGI0001367E 00461
Appendix G 1 which to proceed with an assessment of candidate SAMAs. A further assessment of the 2 methodology was subsequently performed by the NRC staff of issues raised in a petition by 3 New York State (NYS) to intervene in the license renewal proceeding. As described below in 4 Section G.2.3, the NRC staff reaffirms its original conclusion that the methodology used by 5 Entergy to estimate the offsite consequences for Indian Point as amended in Entergy's SAMA 6 re-analysis (Entergy 2009), provides an acceptable basis from which to proceed with an 7 assessment of candidate SAMAs. 8 G.2.3 Review of Issues Related to NYS Contentions 12 and 16 9 On November 30,2007, New York State (NYS) filed a petition to intervene in the Indian Point 10 license renewal proceeding, in which it filed various contentions, including two contentions 11 challenging Entergy's SAMA analysis, asserting that the analysis was flawed based, in part on 12 its use of certain input data for the MACCS2 code and the ATMOS air dispersion module. The 13 Atomic Safety Licensing Board (Board) admitted NYS Contentions 12 and 16 related to the 14 SAMA analysis on July 31, 2008. 15 On February 27,2009, NYS filed Amended Contentions 12A and 16A, challenging the NRC 16 staff's evaluation and preliminary conclusions regarding Entergy's SAMA analysis as set forth in 17 the DSEIS. On June 16, 2009, the Board admitted amended contentions NYS 12A and 16A, 18 and consolidated them with original contentions NYS 12 and 16. As admitted by the Board, 19 NYS Contention 12/12A challenges whether specific inputs and assumptions related to clean-up 20 and decontamination costs are correct for the area surrounding Indian Point and NYS 21 Contention 16/16A challenges: (1) whether the population projections used by Entergy are 22 underestimated, (2) whether the ATMOS module in MACCS2 is being used beyond its range of 23 validity (beyond thirty-one miles), and (3) whether use of MACCS2 with the ATMOS module 24 leads to non-conservative geographical distribution of radioactive dose within a fifty-mile radius 25 of Indian Point. 26 On March 11, 2010, NYS filed Amended Contentions 12B and 16B, challenging various aspects 27 of Entergy's December 2009 SAMA Reanalysis - which, using revised meteorological data, had 28 produced revised estimates of offsite population doses and economic costs, and revised SAMA 29 analysis results (including six additional potentially cost-beneficial SAMAs). On June 30,2010, 30 the Board admitted NYS Contentions 12B and 16B (in part), and consolidated them with NYS 31 Contentions 12/12A and 16/16A. Entergy Nuclear Operations, Inc. (Indian Point Nuclear 32 Generating Units 2 and 3), LBP-10-13, 71 NRC === (2010), slip op. at 10,14-15. 33 In reviewing the issues raised in these contentions, the NRC staff obtained the technical 34 assistance of Sandia National Laboratory (Sandia). The NRC staff and Sandia performed a 35 comprehensive review of relevant documents and references, including the ER the draft SEIS, 36 the MACCS2 input decks for Indian Point and associated documentation, the NYS contentions 37 and supporting documents and references, the Board's rulings on the contentions, and other 38 relevant filings in the adjudicatory proceeding. A summary of the staff's assessment of the 39 issues raised in the admitted contentions is provided below. 40 Clean-up and Decontamination Costs (NYS Contention 12/12A/12B) 41 NYS Contention 12/12A/12B argues that the size of the particles dispersed from a severe 42 reactor accident would be comparable to those released in nuclear weapons tests, smaller than 43 the particle size considered in MACCS2, and that it will be more expensive to decontaminate NUREG-1437, Supplement 38 G-22 December 2010 OAGI0001367E 00462
Appendix G 1 and clean-up a suburban/urban area in which small-sized radionuclide particles have been 2 dispersed. NYS defines large-sized particles as ranging in size from "tens to hundreds of 3 microns" and defines small particles as ranging in size from "a fraction of a micron to a few 4 microns". 5 The staff and Sandia reviewed the inputs and assumptions regarding particle size distribution 6 and decontamination costs used in the SAMA analysis, and determined that the particle size 7 utilized in the analysis was reasonable and acceptable. In this regard, in the MACCS2 input 8 files (atmbi2NS.inp and atmbi3NS.inp), Entergy used a dry deposition velocity value of 0.01 9 meters per second (m/s) for all aerosol particles. A deposition velocity of 0.01 m/s corresponds 10 to approximately a 5 to 10 micron radius particle, based on gravitational settling of small 11 spheres in dilute laminar flow fields. Thus, the MACCS2 dispersion does not assume that the 12 dispersion will consist of large-sized radionuclide particles as NYS contends. While smaller (or 13 larger) particle sizes could have been used in the analysis, the particle size utilized in the 14 analysis was relatively small, is consistent with the accepted SAMA analyses performed for 15 other nuclear power plants, and is acceptable. With respect to the estimated decontamination 16 costs used in Entergy's MACCS2 SAMA analysis, the staff found that Entergy's estimated 17 decontamination costs were reasonable and acceptable, as described below. 18 In the MACCS2 input files, Entergy used decontamination cost parameters that were typically 19 higher than the MACCS2 Sample Problem A values by a factor of 1.7. (Sample Problem A 20 values were primarily developed for the Surry plant analysis in NUREG-1150 and represent best 21 estimate information for that site and time.) As described in the ER the values were obtained 22 by adjusting the generic Sample Problem A economic data with the consumer price index of 23 195.3, which accounts for inflation between 1986 and 2005. Farm and nonfarm values for 24 Indian Point were based on site-specific data and were not extrapolated from Sample Problem 25 A. NYS suggests that in place of the "outdated" decontamination cost figures used by Entergy, 26 the methodology described in a Sandia document SAND96-0957, "Site Restoration: Estimation 27 of Attributable Costs from Plutonium-Dispersal Accident" should be used in establishing 28 decontamination values for input to MACCS2. The NRC staff does not consider the 29 methodology for clean-up of a nuclear weapons accident relevant to clean-up following a 30 nuclear power plant (NPP) accident. Nonetheless, at the staff's request Sandia performed a 31 comparison of the decontamination cost factors derived from the Site Restoration study to those 32 used in the SAMA analysis. The approach to the cost comparison included identifying basic 33 considerations of each type of accident (e.g., contaminants, half life of contaminants, and health 34 and safety considerations), identifying the decontamination methods required, and comparing 35 the Site Restoration study cost values (as applied to the urban area of New York City) to those 36 used in Entergy's analysis. 37 Sandia noted that the primary constituent in weapons grade plutonium, Pu239, is an alpha 38 emitter, whereas the primary contaminant from an NPP accident Cs137, is a gamma emitter. 39 As such, Pu239 is more difficult and expensive to characterize and verify in the field than 40 gamma emitters like Cs137. Furthermore, Pu239 is primarily an inhalation hazard with half-life 41 of 24,000 years, whereas Cs137 is primarily an external health hazard with half-life of about 30 42 years. The need for evacuating the public is much greater with plutonium because if inhaled, 43 the health consequences can be severe. 44 Both the Site Restoration study and the MACCS2 model consider the extent of decontamination 45 required in determining decontamination costs. This is typically expressed as a December 2010 G-23 NUREG-1437, Supplement 38 OAGI0001367E 00463
Appendix G 1 decontamination factor (OF) which represents the ratio of the contamination level before and 2 after clean-up. The Site Restoration study provides cost estimates for remediation of light 3 contamination (OF =2 to 5), moderate contamination (OF =5 to 10), and heavy contamination 4 (OF> 10). Appendix F of the Site Restoration study describes the decontamination methods for 5 light moderate, and heavy contamination by plutonium. For the Indian Point MACCS2 model, 6 Entergy provided decontamination cost input values for two levels of remediation, specifically, a 7 OF of 3 and a OF of 15. Sandia considered the decontamination activities described in the Site 8 Restoration study together with the differences in health hazards posed by Pu239 versus 9 Cs137, and concluded that the activities required to support clean-up of moderate plutonium 10 contamination align more closely with clean-up activities for heavy cesium contamination. 11 Sandia performed the comparison of decontamination cost values on this basis. 12 Sandia conservatively limited its cost comparison to urban areas (non-farmland) because urban 13 areas are more costly to decontaminate than farmland, and because farmland makes up a very 14 small percentage of land area within the Indian Point area, with most counties having less than 15 1 percent farmland. To further simplify the cost analysis and provide a comparison of the 16 highest cost areas, the cost comparison was performed only for New York City, which includes 17 five counties (the Bronx, Kings, New York, Queens, and Richmond). The population density of 18 New York City is about 12,000 persons/km 2. 19 As described above, the decontamination activities for moderate plutonium contamination are 20 most directly comparable to the decontamination activities for heavy cesium contamination. The 21 Site Restoration study (Table 6-2) provides an estimated cost of $178.4 million/km2 for clean-up 22 of moderate plutonium contamination in urban areas, or $14,900 per person when expressed on 23 a per capita basis for New York City. In contrast a cost of $13,824 per person was used in 24 Entergy's MACCS2 analysis for decontamination of heavy cesium contamination. Thus, the 25 decontamination cost from the Site Restoration study ($14,900 per person) is not significantly 26 different than the value used by Entergy in the SAMA analysis ($13,824 per person). If the Site 27 Restoration study values were escalated to 2005 dollars, as were the values used in the SAMA 28 analysis, the difference would be greater, but would still be within a factor of about 2, The 29 differential dollar cost attributable to this difference would vary depending upon the size of the 30 area (i.e., the number of people) that would need to be evacuated. Thus, using the Site 31 Restoration study values, decontamination could cost more than was estimated in Entergy's 32 analysis; however, it could also cost less than Entergy estimated, inasmuch as the SAMA 33 analysis assumed the dispersal of "heavy contamination." Considering the uncertainties 34 inherent in such predictions, Entergy's decontamination cost estimates appear reasonable and 35 acceptable. Further, Entergy's decontamination cost estimates are consistent with those used 36 in accepted SAMA analyses performed for other nuclear power plants. 37 Population Projections (NYS Contention 16/16A/16B) 38 NYS Contention 16/16A/16B argues that Entergy's projections of the 2035 population living 39 within the 50-mile radius of Indian Point underestimate the potential exposed population. The 40 staff and Sandia reviewed Entergy's baseline and projected population values and its population 41 projection methodology, and developed independent estimates of the baseline and projected 42 population. Entergy obtained population estimates directly from State agency reports for 43 periods ranging from 2000 to 2020 and 2000 to 2030, depending on the State data available. 44 Entergy projected total permanent populations to the year 2035 for 25 of the 28 counties that 45 are within or encroach upon the limit of 50 miles from Indian Point using linear extrapolation. NUREG-1437, Supplement 38 G-24 Oecember 2010 OAGI0001367E 00464
Appendix G 1 Entergy used areal weighting, which assumes a constant population distribution over the area 2 assessed (i.e., in each of the 160 cells within the 16 sectors and radial rings representing the 3 50-mile radius surrounding the IP site), to establish fractional population within 50 miles of 4 Indian Point. Entergy then adjusted this permanent population projection upward to account for 5 the presence of the transient (tourist) population as estimated from available tourist information. 6 For the remaining three counties, including New York (Manhattan), Rockland, and Westchester 7 counties, Entergy used polynomial regression for projecting the population. A polynomial 8 regression appears to have been used for these counties because State data shows a decrease 9 in the population of these counties. The population for these counties was projected by the 10 State to increase from 2000 to 2020 and then decrease from 2020 to 2030 resulting in a peak 11 population in 2020. Because there is a peak within the projection period, Sandia agreed that 12 use of a polynomial projection to the year 2035 is a more appropriate approach than a linear 13 projection for these counties. Entergy estimated the year 2000 permanent population within the 14 50-mile radius of Indian Point to be 16,914,178. Entergy projected the permanent population 15 out to 2035 to be 18,879,657, an increase of 12.43 percent. The population Entergy used in its 16 SAMA analysis was 19,228.114, which accounts for the transient population, as described 17 above. 18 Sandia performed an independent assessment of the population data within a 50-mile radius of 19 Indian Point using the SECPOP2000 computer program. The population data in SECPOP2000 20 is based on 2000 U.S. Census Bureau data. The population for the year 2000 estimated by 21 SECPOP2000 is 16,800,272; this compares very closely with Entergy's year 2000 estimate of 22 the permanent population within the 50-mile radius (16,914,178). 23 Sandia also performed two analyses of projected population growth to the year 2035, and 24 determined that Entergy's projected population growth was reasonable. The first evaluation 25 was based on the US Census Bureau's projected growth from 2000 to 2008 for the Northeast 26 region of the US. During these 8 years, the projected growth is 2.344 percent; based on this 27 number, the annualized growth rate for the Northeast region of the country is 0.2900 percent. 28 Assuming a constant growth rate between the years 2000 and 2035 results in an estimated 29 growth of 10.67 percent. This estimate is lower than the Entergy value of 12.43 percent. The 30 second evaluation used the same year 2000 population for the 28 counties surrounding Indian 31 Point as used by Entergy, but used a simpler method than Entergy for extrapolating out to 2035. 32 The annualized growth rate was calculated starting from the 2000 census values to the final 33 (latest) year projected by each of the states. Assuming this growth rate to continue through 34 2035, the estimated growth for the 28 counties is 15.98 percent. This value is larger than 35 Entergy's projected growth of 12.43 percent but the difference is small. Thus, the two 36 evaluations performed by Sandia bound the Entergy projection for population growth. 37 38 Finally, Sandia performed a separate population projection for the five counties comprising New 39 York City. For New York, Queens, and Richmond Counties, Sandia projected slightly higher 40 populations than Entergy. For Bronx and Kings Counties, Entergy projected higher populations. 41 The difference between the Sandia and Entergy population projections for all 5 counties is only 42 0.39 percent. The NRC staff concludes that Entergy's population data and projected population 43 growth analysis provide reasonable (and slightly conservative) population values for its SAMA 44 analysis. December 2010 G-25 NUREG-1437, Supplement 38 I OAGI0001367E 00465
Appendix G 1 Validity of ATMOS Model (NYS Contention 16/16A/16B) 2 NYS Contention 16/16A/16B argues that the ATMOS air dispersion module utilized in the 3 MACCS2 code is being used beyond its range of validity (beyond thirty-one miles). which could 4 affect the validity of decontamination cost estimates for areas beyond that range. The NRC 5 staff and Sandia National Laboratory addressed this issue in detail, in the NRC staff's October 6 13, 2009 response to a NYS motion for partial summary disposition. In brief, the NRC staff and 7 Sandia considered the State's concern, and concluded that ATMOS air dispersion module 8 provides an acceptable means for estimating potential plume travel and dispersion in a 9 probabilistic statistical analysis, and is acceptable for use with the MACCS2 code, in which a 10 probabilistic analysis is performed for a large number of meteorological trials, which are subject 11 to hourly variation. Further, this conclusion is supported by a comparison of the results 12 produced by MACCS2 analyses using the ATMOS module with the results of analyses 13 performed with other codes. 14 ATMOS is a Gaussian plume model within MACCS2 that treats plume segments under different 15 weather conditions based on hourly changes from the site meteorological data. The 16 meteorological data considered for each segment include wind speed, direction, stability class, 17 and precipitation. Once a plume is formed, the direction does not change; however, the wind 18 speed, stability class, and precipitation rate can change hour-by-hour based on the 19 meteorological data. 20 The MACCS2 code considers, among other things, phenomena related to atmospheric transport 21 and deposition under time-variant meteorology, short- and long-term mitigative actions, potential 22 exposure pathways, deterministic and stochastic health effects, and economic costs. The 23 MACCS2 code samples the meteorological data from an entire year and uses wind rose data to 24 account for the plume traveling through all 16 compass sectors to ensure that all the potential 25 plume paths are accounted for in the calculations. This ensures that likely impacts for the entire 26 area within a 50-mile radius have an accurate statistical model for likelihood of a plume reaching 27 that area and its expected concentration. The MACCS2 model generates average or expected 28 values of metrics of interest considering all of the relevant dose pathways, including the food 29 and water pathway, and covering essentially a lifetime of exposure to a contaminated 30 environment. 31 Questions regarding the adequacy of averaging metrics of interest over numerous weather 32 sequences have been studied in detail. This included a detailed code comparison completed in 33 2004 with the objective of determining if the average atmospheric transport and dispersion 34 results from codes such as MACCS2 are sufficiently accurate that more complex models are not 35 required. In that study, results from the MACCS2 code were directly compared to those from 36 the LODI (Lagrangian Operational Dispersion Integrator) code and the RASCAL 3.0 37 (Radiological Assessment System for Consequence Analysis, Version 3.0) code. 38 LODI is a state-of-the-art three-dimensional (3D) advection dispersion code that uses a 39 Lagrangian stochastic Monte Carlo method. LODI is coupled to ADAPT (Atmospheric Data 40 Assimilation and Parameterization Technique). which provides time-varying, 3D fields of mean 41 winds, turbulence, pressure, temperature, and precipitation based on observed meteorology. 42 LODI is an element of the National Atmospheric Release Advisory Center (NARAC) emergency 43 response modeling system at Lawrence Livermore National Laboratory (LLNL) which is a 44 national support and resource center for planning, real-time assessment emergency response, NUREG-1437, Supplement 38 G-26 December 2010 OAGI0001367E 00466
Appendix G 1 and detailed studies of incidents involving the spread of hazardous material accidentally or 2 intentionally released into the atmosphere. 3 RASCAL 3.0 is used by the NRC for emergency response applications where a rapid response 4 is required. The NRC evaluates accident conditions using RASCAL and compares results to 5 those produced by NARAC during an accident. RASCAL 3.0 contains atmospheric transport 6 and dispersion components that are intermediate in complexity between MACCS2 and ADAPT/ 7 LODI. RASCAL employs time-varying, two-dimensional meteorological fields of wind, stability, 8 and precipitation based on surface-level meteorological observations as input to a Lagrangian 9 trajectory transport model and a Gaussian puff dispersion model. While the dispersion portions 10 of RASCAL 3.0 are similar to those of MACCS2, the transport portions are significantly different. 11 The capabilities of RASCAL 3.0 are similar to those of the dispersion models CALPUFF and 12 AERMOD, which were recommended by NYS. 13 As documented in NUREG/CR-6853, "Comparison of Average Transport and Dispersion Among 14 a Gaussian, a Two-Dimensional, and a Three-Dimensional Model," this comparison shows that 15 MACCS2 provides results consistent with those from the more complex plume models at 16 distances up to 100 miles. This is well beyond the 50-mile radius considered in the SAMA 17 analysis. The MACCS2 predictions for average, time-integrated, ground-level air concentrations 18 (which directly relates to inhalation and cloudshine doses). and for average deposition (which 19 directly relates to ground shine and ingestion pathway doses) were very comparable to 20 predictions made by the state-of-the-art NARAC codes, ADAPT/LODI, at all distances. The 21 direct comparison to state-of-the-art codes demonstrates that MACCS2 is well within its range 22 of validity when used to perform SAMA analyses. 23 Geographical Distribution of Radioactive Contamination and Dose (NYS Contention 24 16/16A/16B) 25 NYS Contention 16/16A/16B also argues that use of MACCS2 with the ATMOS module leads to 26 a non-conservative geographical distribution of radioactive dose and radionuclide contamination 27 within a 50-mile radius of Indian Point which could affect the validity of dose and contamination 28 cost estimates within that area. The staff and Sandia considered the State's concerns regarding 29 ATMOS, and concluded that ATMOS provides an acceptable plume model for the calculation of 30 doses and radioactive contamination in a SAMA analysis. In response to this concern, Sandia 31 assessed the impact of using a Gaussian plume model on accident consequences, and 32 evaluated the population distribution and meteorological data used in Entergy's SAMA analysis. 33 The Gaussian plume model used in ATMOS assumes that the plume travels in a straight line. 34 For Indian Point this would minimize the distance the plume would travel in reaching the 35 highest population areas, which are near the periphery of the 50-mile radius. The Gaussian 36 plume model provides further conservatism under variable terrain conditions. Specifically, when 37 variable terrain features such as river embankments or mountains intervene between a source 38 and an observation point these features would tend to disperse and dilute the plume as it is 39 forced to move around obstacles. The plume model conservatively estimates that the plume 40 travels in a straight line over or through the obstacle, thereby resulting in larger accumulated 41 radiological doses and higher estimates of economic consequences in areas farther from the 42 plant. 43 Although there are large geographic variations of population density within 50 miles of Indian 44 Point the evaluation of population distribution shows that the largest populations are located at December 2010 G-27 NUREG-1437, Supplement 38 OAGI0001367E 00467
Appendix G 1 the furthest distances within the 50-mile radius surrounding the site (i.e., in the New York City 2 metropolitan area located about 30 to 50 miles south [SSE to SSW] of the Indian Point site). 3 The shorter path of travel associated with the Gaussian plume model, together with the 4 dominant wind direction being toward New York City (discussed below). ensures that a 5 conservatively large amount of contaminant reaches the areas with higher population density in 6 the MACCS2 analysis. Accordingly, use of the ATMOS module would result in a conservative 7 geographical distribution of radioactive dose within a 50-mile radius of Indian Point relative to 8 other atmospheric transport models. 9 Sandia reviewed the MACCS2 input files used in the Entergy baseline analysis to determine 10 whether input parameter selection might contribute to non-conservative geographical 11 distribution of radioactive dose within the 50-mile radius of Indian Point. Most of the input 12 parameters used by Entergy in the MACCS2 analyses were standard choices consistent with 13 Sample Problem A that is distributed with the MACCS2 code. The following input choices were 14 specifically reviewed by Sandia: 15
- Meteorology -In the SAMA analysis described in the ER Entergy averaged 16 meteorological data for a 5-year period to provide a data file consisting of one year of 17 hourly readings representative of site meteorology. After the staff raised questions 18 concerning the weather data used in the analysis, Entergy submitted an updated 19 MACCS2 input file which uses a single weather year with conservative data and corrects 20 the wind rose data. The use of a single year's data is consistent with regulatory 21 guidance; further, the wind direction in the updated file is predominantly to the south 22 (toward New York City). consistent with information reported elsewhere for Indian Point 23 (e.g., in annual effluent reports between 1999 through 2002). Thus, the staff's concern 24 regarding wind direction has been resolved in the updated analysis.
25
- Population - The population values in the MACCS2 input files are consistent with the 26 values reported in the ER. The population values were also found to be consistent with 27 the US Census data as discussed above. The 2035 projected population value of 28 19,228,712 used by Entergy was reviewed and found to be reasonable. Sandia 29 confirmed that Entergy's population projections for New York City, which is in the 30 dominant downwind plume direction, are reasonable. Further, Entergy's use of 31 populations accounting for tourists was found to be reasonable and to provide a slightly 32 higher estimated cost.
33
- Dry Deposition Velocity - The dry deposition velocity of 0.01 m/s corresponds to a 34 relatively small particle size. Within the plume model, small particle sizes will travel 35 greater distances than large particle sizes. Therefore, smaller particle sizes would favor 36 deposition at the higher population locations farther from the site, and would likely result 37 in greater population dose and greater decontamination costs because the areas farther 38 away from the plant are more densely populated urban areas which have higher 39 decontamination costs. While smaller or larger particle sizes could have been used in 40 the analysis, the particle size that Entergy used is reasonable and acceptable.
41
- Plume representation - Releases to the environment were modeled as a single 42 Gaussian plume in the SAMA analysis. While Entergy's analysis utilized a single plume, 43 MACCS2 has the ability to divide the plume into a number of plume segments. Use of 44 additional plume segments would likely result in some variation in wind direction, NUREG-1437, Supplement 38 G-28 December 2010 OAGI0001367E 00468
Appendix G 1 dispersing the radiation and resulting in lower peak doses to the public. For purposes of 2 a SAMA analysis, however, the results of a single isolated meteorological data trial is not 3 at issue; rather, the analysis should model the results of numerous meteorological trials 4 that provide a mean dispersion over the entire 50-mile radius. Such modeling 5 necessarily includes variations in wind direction. The end result of conducting multiple 6 meteorological trials is the calculation of a mean atmospheric transport which describes 7 the expected amount and timing of the contaminant release reaching any area within a 8 50-mile radius. This calculation allows for the determination of the mean effect on dose 9 and economic costs for each modeled event that could occur at some time in the future 10 under unknown weather conditions. The NRC staff notes that a SAMA analysis is not 11 meant to provide a prediction of the contamination for any specific weather event; rather, 12 it provides a mean result for a type of event under the mean potential circumstances. 13 The use of a single Gaussian plume in each trial in the SAMA analysis provides a 14 reasonable and acceptable approach for this purpose. 15
- Spatial grid - The MACCS2 analysis considered consequences with a 50-mile radius of 16 the Indian Point site. This is consistent with NRC guidance for regulatory analysis as 17 provided in NUREG/BR-0184.
18
- Decontamination costs - Decontamination costs were based on Sample Problem A and 19 adjusted for inflation using the consumer price index factor. A comparison of Entergy's 20 input values with those derived from the Site Restoration study shows the values are in 21 reasonable agreement.
22
- Emergency evacuation - The emergency phase evacuation was not modeled in the 23 Entergy analysis. Entergy claims that this is more conservative than using the radial 24 evacuation approach applied in Sample Problem A. The emergency evacuation 25 treatment is not expected to significantly affect the SAMA results (e.g., total population 26 dose and offsite economic cost risk) because these metrics are typically driven by 27 doses/deposition well beyond the 1O-mile emergency planning zone.
28 Based on the NRC staff's and Sandia's review, the ATMOS module and MACCS2 input 29 parameters used by Entergy are reasonable and acceptable, and do not result in a non-30 conservative geographical distribution of radioactive dose and contamination within a 50-mile 31 radius of Indian Point. 32 Summary 33 The NRC staff, with the assistance of Sandia National Laboratory, evaluated the concerns 34 raised in NYS Contentions 12/12A/12B and 16/16A/16B. Based on this review, the staff 35 concludes that the issues raised in these contentions do not alter the staff's conclusions, set 36 forth in the DSEIS, regarding the acceptability of Entergy's SAMA analysis. Accordingly, the 37 NRC concludes that Entergy's use of the MACCS2 code, including the inputs and ATMOS 38 module used to estimate offsite consequences for Indian Point as amended in Entergy's SAMA 39 re-analysis, provides an acceptable methodology for use in the assessment of candidate 40 SAMAs. 41 G.3 Potential Plant Improvements December 2010 G-29 NUREG-1437, Supplement 38 I OAGI0001367E 00469
Appendix G 1 This section discusses the process for identifying potential plant improvements, an evaluation of 2 that process, and the improvements evaluated in detail by Entergy. 3 G.3.1. Process for Identifying Potential Plant Improvements 4 Entergy's process for identifying potential plant improvements (SAMAs) consisted of the 5 following elements: 6
- The review of the most significant basic events from the current plant-specific PSA; 7
- The review of potential plant improvements identified in the IP2 and IP3 IPE and IPEEE; 8
- The review of Phase II SAMAs from license renewal applications for nine other 9 pressurized water reactors; 10
- The review of dominant contributors to seismic and fire events in the current seismic and 11 fire analyses; 12
- The review of other NRC and industry documentation discussing potential plant 13 improvements.
14 Based on this process, an initial set of 231 candidate SAMAs for IP2 and 237 candidate SAMAs 15 for IP3, referred to as Phase I SAMAs, was identified. In Phase I of the evaluation, Entergy 16 performed a qualitative screening of the initial list of SAMAs and eliminated SAMAs from further 17 consideration using one of the following criteria: 18
- The SAMA is not applicable at IP2 and IP3 because of design differences.
19
- The SAMA has already been implemented at IP2 and IP3.
20
- The SAMA is similar in nature and could be combined with another SAMA candidate.
21 Based on this screening, 163 IP2 SAMAs and 175 IP3 SAMAs were eliminated, leaving 68 22 unique SAMAs for IP2 and 62 unique SAMAs for IP3. The remaining SAMAs, referred to as 23 Phase II SAMAs, are listed in Tables E.2-2 and E.4-2 of the ER (Entergy 2007). In Phase II, a 24 detailed evaluation was performed for each of the remaining SAMA candidates, as discussed in 25 Sections G.4 and G.6 below. To account for the potential impact of external events, the 26 estimated benefits based on internal events were multiplied by a factor of 3.8 for IP2 and 5.5 for 27 IP3, as previously discussed. 28 G.3.2. Review of Entergy's Process 29 Entergy's efforts to identify potential SAMAs focused primarily on areas associated with internal 30 initiating events but also included explicit consideration of potential SAMAs for seismic and fire. 31 The initial list of SAMAs generally addressed the accident sequences considered to be 32 important to CDF from functional, initiating event and risk-reduction worth (RRW) perspectives 33 at IP2 and IP3 and included selected SAMAs from prior SAMA analyses for other plants. 34 Entergy provided a tabular listing of the PSA basic events, sorted according to their RRW for 35 CDF (Entergy 2007). SAMAs affecting these basic events would have the greatest potential for 36 reducing risk. Entergy used an RRW cutoff of 1.005, which corresponds to about a 0.5-percent 37 change in CDF, given the 100 -percent reliability of the SAMA. This equates to a benefit of 38 approximately $7,000 for IP2 and IP3 (based on a total benefit of about $1.3 million for each unit NUREG-1437, Supplement 38 G-30 December 2010 OAGI0001367E 00470
Appendix G 1 for eliminating all severe accidents caused by internal events). Entergy also provided and 2 reviewed the LERF-based RRW events down to an RRW of 1.005. Entergy correlated the top 3 CDF and LERF events with the SAMAs evaluated in Phase I or Phase II and showed that with 4 a few exceptions, all of the significant basic events are addressed by one or more SAMAs 5 (Entergy 2007). Of the basic events of high-risk importance that are not addressed by SAMAs, 6 each is closely tied to other basic events that had been addressed by one or more SAMAs. 7 Entergy considered the potential plant improvements described in the IPE and IPEEE in the 8 identification of plant-specific candidate SAMAs for internal and external events. As a result of 9 the IPE, four major procedural/hardware improvements were identified for each unit. The IP2 10 enhancements are to (1) upgrade IP2 gas turbine black-start capability, (2) install an additional 11 EDG building fan, (3) monitor changes in the operating position of PORV block valves, and (4) 12 implement periodic testing of all the EDG building fans. The IP3 enhancements are to (1) revise 13 emergency operating procedures (EOPs) to instruct operators to align the backup city water 14 supply to the AFW pumps, should the CST outlet valve fail as indicated by a low-suction-flow 15 alarm, (2) revise the alarm response procedure for a high AFW pump room temperature, to 16 direct operators to open the rollup door to the AFW pump room for ventilation, (3) install a 17 switchgear room high-temperature alarm and implement an associated procedure to direct 18 operators to block open doors to the 480-V ac switchgear room, and (4) revise EOPs to 19 emphasize the need to align the safe-shutdown equipment to MCC 312A during events 20 involving the loss of all 480-V ac safeguard buses while offsite power is available, as well as 21 during fire-related events. These improvements have all been implemented and therefore were 22 not considered further in the SAMA analysis. 23 As a result of the IPEEEs, several improvements were identified for external events. The IP2 24 enhancements are to (1) replace the hold-down bolts for the CCW surge tank with higher tensile 25 strength bolts, (2) add surveillance of the control building drain flapper valve flow, (3) add 26 weather stripping to doors between the transformer area and the switchgear room, and (4) add 27 screens on the 480-V switchgear room equipment. The IP3 enhancements are to (1) restore 28 the carbon dioxide (C0 2) suppression system to automatic mode within the switchgear room, 29 (2) reroute the EDG exhaust fans and the auxiliary cables so that a fire in a single EDG cell 30 would not affect multiple EDGs, and (3) install an excess flow valve to reduce the risk 31 associated with hydrogen explosions inside the turbine building or PAB. With the exception of 32 the last item, all of these improvements have been implemented and therefore were not 33 considered further in the SAMA analysis. As noted in Section E.3.3.3 of the ER IP3 SAMA 53 34 (install an excess flow valve to reduce the risk associated with hydrogen explosions) was 35 proposed as a result of the IPEEE analysis and retained for the Phase II evaluation. 36 Several concerns were raised in the IPEEE regarding the seismic-induced failures offire 37 protection equipment (primarily for IP3). As mentioned above, these seismic-fire interactions 38 were judged to be of little risk significance (N RC 2001). One plant improvement identified in 39 Table 2.4 of NUREG-1742 (NRC 2002) addressed the potential spurious operation of the EDG 40 room's CO 2 system and subsequent shutdown of the EDG ventilation system during a seismic 41 event. Entergy subsequently installed a quality assurance Category I, seismic class I actuation 42 permission auxiliary control panel for CO 2 discharge into the EDG building. Since shutdown of 43 EDG ventilation caused by spurious operation of the CO 2 system during a seismic event is not 44 considered in the seismic PSA model, the seismic CDF was not affected by this modification. December 2010 G-31 NUREG-1437, Supplement 38 I OAGI0001367E 00471
Appendix G 1 As noted in Section E.1.3.3.1 of the ER the IP2 CDF for SBO events with gas turbines 2 unavailable could be reduced by (1) aligning the IP3 Appendix R diesel to IP2, (2) installing an 3 IP2 Appendix R diesel, (3) upgrading the EDG building for high winds, and (4) protecting the 4 alternate power source from tornadoes and high winds. However, with the exception of the third 5 item, these modifications were not evaluated as candidate SAM As because a modification to 6 replace the existing gas turbines with an IP2 SBO/Appendix R diesel generator capable of being 7 used to recover power to the vital buses following an SBO was planned for the near future. The 8 planned modification included provisions for aligning the IP3 Appendix R generator to IP2 and 9 for protecting the new alternate power source from tornadoes and high winds.' 10 For a number of the Phase II SAMAs listed in the ER the NRC staff found that information 11 provided did not sufficiently describe the proposed modifications or other considerations that 12 might have been taken into account in estimating the benefit and implementation cost. 13 Therefore, the NRC staff requested, and the licensee provided, more information on certain 14 proposed modifications listed for the Phase II SAMA candidates (NRC 2007, Entergy 2008a). 15 For several SAMA candidates, the NRC staff questioned if lower cost alternatives could have 16 been considered, including: 17
- The implementation of improved instrumentation and procedures to help cool down and 18 depressurize the RCS before RWST depletion.
19
- The implementation of a procedure for recovery of the steam dump to condenser from 20 the unaffected steam generator.
21
- The implementation of a procedure for recovery of the main feed water valve/condensate 22 post-SI actuation.
23
- The purchase or manufacture of a "gagging device" that could be used to close a stuck-24 open steam generator safety valve on an SGTR before core damage occurred.
25
- The reactivation of the IP3 postaccident containment venting system (a system that is 26 still active on IP2 but was deactivated on IP3).
27 In response, Entergy indicated that most of the low-cost alternatives to aid in the mitigation of an 28 SGTR (four out of the five alternatives dismissed above) have been already implemented and 29 provided specific reasons why the cost of these alternative SAMA candidates would be high 30 enough that the decision on the final SAMA selection would not have been affected. However, 31 the alternative associated with the gagging device was found to be potentially cost beneficial 32 (Entergy 2008a, Entergy 2008b). The evaluation of these SAMAs is discussed further in 33 Section G.6.2. 34 The NRC staff notes that the set of SAMAs submitted is not all inclusive, since additional, 35 possibly even less expensive, design alternatives can always be postulated. However, the NRC 36 staff concludes that the benefits of any additional modifications are unlikely to exceed the 37 benefits of the modifications evaluated and that the alternative improvements would not likely 38 cost less than the least expensive alternatives evaluated, when the subsidiary costs associated 39 with maintenance, procedures, and training are considered. 1 Installation of this diesel was made a condition of acceptance of the License Renewal Application (LRA) for review. The diesel was installed and operated prior to 4/30/2008. See Entergy letter NL-08-074, Indian Point, Units 2 and 3, Amendment 4 to LRA April 30, 2008 (ML081280491). NUREG-1437, Supplement 38 G-32 December 2010 OAGI0001367E 00472
Appendix G 1 The NRC staff concludes that Entergy used a systematic and comprehensive process for 2 identifying potential plant improvements for IP2 and IP3 and that the set of SAMAs evaluated in 3 the ER together with those identified in response to the NRC staff inquiries, is reasonably 4 comprehensive and therefore acceptable. The search included reviewing insights from the 5 plant-specific risk studies and reviewing plant improvements considered in previous SAMA 6 analyses. While explicit treatment of external events in the SAMA identification process was 7 limited, the NRC staff recognizes that the prior implementation of plant modifications for seismic 8 and fire events, and the absence of external-event vulnerabilities, reasonably justifies examining 9 primarily the internal-event risk results for this purpose. 10 G.4 Risk-Reduction Potential of Plant Improvements 11 Entergy evaluated the risk-reduction potential of the remaining 68 IP2 and 62 IP3 SAMAs. The 12 SAMA evaluations were performed using realistic assumptions with some conservatism. On 13 balance, such calculations overestimate the benefits and are conservative. 14 For all of the SAMAs, Entergy used model requantification to determine the potential benefits. 15 The CDF and population-dose reductions were estimated using the latest version of the IP2 and 16 IP3 PSA models. The changes made to the models to quantify the impact of the SAMAs are 17 detailed in Tables E.2-2 and E.4-2 of the ER (Entergy 2007). Table G-6 lists the assumptions 18 considered to estimate the risk reduction for each of the evaluated SAMAs, the estimated risk 19 reduction in terms of the percentage of reduction in CDF and population dose, and the 20 estimated total benefit (present value) of the averted risk. The estimated benefits reported in 21 Table G-6 reflect the combined benefit for both internal and external events and the correction 22 of the meteorological data error discussed previously. The determination of the benefits for the 23 various SAMAs is further discussed in Section G.6. 24 The NRC staff questioned the assumptions used in evaluating the benefits or risk-reduction 25 estimates of a number of SAMAs provided in the ER (NRC 2007). For example, the NRC staff 26 requested information regarding the plant features or modeling assumptions that result in the 27 CCW pumps having limited risk importance. In response, Entergy stated that both units are 28 unique in that the capability exists to initiate backup cooling to key components in the event the 29 primary CCW cooling function is lost. The use of backup city water cooling to the charging 30 pumps enables continued seal injection and therefore reduces the likelihood of an RCP seal 31 LOCA. In IP2, city water backup or primary water can be used to cool the safety injection and 32 residual heat removal (RHR) pumps. In IP3, city water backup is available to cool RHR 33 Pump 31. Also, CCW is not required in either plant during the injection phase of the response 34 to a LOCA. The NRC staff considers the explanation of the plant features, as clarified, to be 35 reasonable and therefore acceptable for the purposes of the SAMA evaluation. 36 For a number of the Phase II SAMAs listed in the ER the description of the improvement and 37 the associated analyses appeared either inconsistent between the two units or were unclear. 38 Therefore, the NRC staff asked the applicant to provide more detailed descriptions of the 39 modifications for several of the Phase II SAMA candidates (NRC 2007). In response, Entergy 40 provided additional information on those SAMA candidates that further explained the SAMA 41 modifications and the differences between units that account for the different analysis 42 assumptions for each unit (Entergy 2008a). Entergy also provided further clarifications and 43 discussion regarding the analysis assumptions and their bases. As an example, the licensee December 2010 G-33 NUREG-1437, Supplement 38 OAGI0001367E 00473
Appendix G 1 clarified a major difference in operation of a turbine-driven AFW pump between the two units 2 that affects the disposition of several SAMA candidates. In its response, Entergy indicated that 3 the units respond differently upon depletion of the station batteries. IP2 has pneumatic level 4 and pressure instruments that allow operators to monitor key parameters and effectively control 5 AFW flow after the batteries are depleted, whereas IP3 does not have this instrumentation. 6 Although it is still possible for the operators to manipulate AFW flow, the current IP3 model does 7 not credit this manual operation. 8 In the SAMA analysis submitted in the ER Entergy increased the benefit that was derived from 9 the internal-event model by factors of 3.8 and 5.5 to account for the combined contribution from 10 internal and external events for IP2 and IP3, respectively. The NRC staff agrees with the 11 licensee's overall conclusion concerning the impact of external events and concludes that the 12 licensee's use of a mUltiplier of 3.8 and 5.5 for IP2 and IP3, respectively, to account for external 13 events is reasonable for the purposes of the SAMA evaluation. This is discussed further in 14 Section G.6.2. 15 For SAMA candidates that only address a specific external event and have no bearing on 16 internal-event risk (e.g., IP2 SAMA 66-Harden EDG Building Against High Winds). Entergy 17 derived the benefit directly from the external-event risk model and then increased the benefit by 18 the mUltipliers identified earlier. The NRC staff notes that the use of mUltipliers for these 19 SAMAs (conceptually, to account for additional benefits in internal events) is unnecessary, since 20 these SAMAs have no bearing on internal events. However, use of the mUltipliers adds 21 conservatism to the benefit estimate for these SAMA candidates. 22 IP3 SAMA 53 (install an excess-flow valve to reduce the risk associated with hydrogen 23 explosions) was identified to reduce the risk associated with hydrogen explosions inside the 24 turbine building or PAB. The proposed plant modification involves the installation of a 25 nonelectric excess-flow valve. The benefit of this SAMA is also calculated in a bounding 26 manner. As discussed in Section G.6.2, this SAMA was found to be potentially cost beneficial, 27 based on revised analyses submitted in response to an NRC request. 28 The NRC staff has reviewed Entergy's bases for calculating the risk reduction for the various 29 plant improvements and concludes that the rationale and assumptions for estimating risk 30 reduction are reasonable and generally conservative (i.e., the estimated risk reduction is higher 31 than what would actually be realized). Accordingly, the NRC staff based its estimates of averted 32 risk for the various SAMAs on Entergy's risk reduction estimates. 33 G.S Cost Impacts of Candidate Plant Improvements 34 Entergy estimated the costs of implementing the candidate SAMAs through the application of 35 engineering judgment and use of other licensees' estimates for similar improvements. The ER 36 stated that the cost estimates conservatively did not include the cost of replacement power 37 during extended outages required to implement the modifications, nor did they include 38 contingency costs associated with unforeseen implementation obstacles. The cost estimates 39 provided in the ER also did not account for inflation, which is considered another conservatism. 40 The NRC staff reviewed the bases for the licensee's cost estimates. For certain improvements, 41 the NRC staff also compared the cost estimates to estimates developed elsewhere for similar 42 improvements, including estimates developed as part of other licensees' analyses of SAMAs for NUREG-1437, Supplement 38 G-34 December 2010 OAGI0001367E 00474
Appendix G 1 operating reactors and advanced light-water reactors. The NRC staff reviewed the costs and 2 found them to be reasonable and generally consistent with estimates provided in support of 3 other licensees' analyses. December 2010 G-35 NUREG-1437, Supplement 38 I OAGI0001367E 00475
z I C 1;;0 Table G-6. Final Potentially Cost-Beneficial SAM As for IP2 and IP3 1 rn C) Total Benefit
, % Risk
--'
.f::>. Reduction
($) Cost W SAMA Assumptions
-...J Population Baseline L. (lnt Baseline With
($) (f) CDF c Dose + Ext Events) Uncertainty
- gl ro IP2 SAMAs
~I
- J 9 - Create a reactor cavity flooding Eliminate containment failure 0 47 6.3M 13M 4.1M"
,...... system. caused by concrete-core W interaction.
<Xl 21 - Install additional pressure or leak Eliminate ISLOCA events. 0.8 11 2.1M 4.4M 3.2Mj monitoring instrumentation for ISLOCA.
22 - Add redundant and diverse limit Reduce ISLOCA frequency by 50 0.4 6 1.1M 2.3M 2.2M" switches to each containment percent. isolation valve. j 28 - Provide a portable diesel-driven Eliminate failure of local operation 5 9 1.4M 2.9M 938K
, battery charger. of the turbine-driven AFW pump w
(j) durinq SBO scenarios. 44 - Use fire water system as backup Eliminate failure of the turbine- 33 14 2.4M 4.9M 1.7M for steam generator inventory. driven AFW pump and local operation of AFW during SBO. 53 - Keep both pressurizer PORV Eliminate failure of PORV block 18 3 660K 1.4M 800K block valves open. valves to open. 54 - Install flood alarm in the 480-V ac Reduce control building flooding 20 39 5.6M 12M 200K switchgear room. initiator frequencies by a factor of 3. 56 - Keep RHR heat exchanger Eliminate failure of RHR heat 2 0.2 49K 100K 82K discharge MOVs normally open. exchanger discharge MOVs to open. 60 - Provide added protection against Eliminate flood initiated by a break 5 9 1.3M 2.7M 216K flood propagation from stairwell 4 in fire protection piping in 0 into the 480-V ac switchqear room. stairwell 4. (D ("") (D 61 - Provide added protection against Eliminate flood initiated by a break 10 19 2.8M 5.8M 192K
- 3 flood propagation from the deluge in the 1O-inch fire protection piping 0 cr
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..., % Risk Total Benefit N
Reduction ($) o Cost
--' Assumptions o Population Baseline L. (lnt Baseline With
($) SAMA CDF Dose + Ext Events) Uncertainty 62 - Provide a hard-wired connection Eliminate failure to align A555 3 6 850K 1.8M 1.5Mj to an 51 pump from A555 power power to 51 and charging pumps supply. following loss of power from 480V buses. 65 - Upgrade the A555 to allow timely Eliminate control building flooding 20 39 5.6M 12M 560K restoration of seal injection and initiators. coolin~. IP3 SAMAs4 I 7 - Create a reactor cavity flooding Eliminate containment failures due 0 24 5.0M 7.3M 4.1M"
, system. to core-concrete interactions w j
...... 18 - Route the discharge from the Reduce 5GTR accident source 0 11 4.8M" 15M" 12M M55Vs through a structure where terms by a factor of 2.
spray water would condense the stream and remove fission products. 19 - Install additional pressure or leak Eliminate 15LOCA events 1 7 2.1M 3.1M 2.8M" monitoring instrumentation for z 15LOCAs. c 52 - Open city water supply valve for Eliminate loss of the normal suction 1 1 250K 360K 50K I
;;0 rn alternative AFW pump suction. path to the AFW system.
C) 53 - Install an excess flow valve to Eliminate hydrogen ruptures inside 2 2 500K 720K 228K
,
--'
.f::>.
reduce the risk associated with the turbine building. W
-...J hydrogen explosions.
55 - Provide the capability of powering Eliminate operator failure to align 16 18 4.1M 5.9M 1.3M (f) C one 51 pump or RHR pump using MCC 312A.
"'0
"'0 the Appendix R bus (MCC 312A).
ro 61 - Upgrade the A555 to allow timely Eliminate control building flooding 17 20 4.4M 6.3M 560K 0 :3 restoration of seal injection and initiators.
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~ 62 - Install flood alarm in the 480-V ac Eliminate control building flooding 17 20 4.4M 6.3M 197K
"'0 switch~ear room. initiators.
1~ 2~::J 1 The information was reproduced by combining the information from ER Tables E.2-2 and E.4-2 and Entergy's SAMA re-analysis (Entergy 2009). 3~ 2 Reported benefit values account for risk reduction in both internal and external events and include the economic impact of lost tourism and business following a 4o::l severe accident. The values do not account for analysis uncertainties. 5 3 The cost estimate is based on a revised value provided in Entergy's SAMA re-analysis (Entergy 2009) 6 4 SAMA 30 was identified as cost beneficial in the ER. However, an error in the original benefit calculation was discovered subsequent to submittal of the ER, as 7 described in Entergy's response to RAI 5g (Entergy 2008a). Reported values in Table G-6 reflect correction of the calculational error. SAMA 30 is no longer cost 8 beneficial after corrections. 9 10C) I 5 The benefit estimate is based on revised TI-SGTR sensitivity study results provided in Entergy's SAMA re-analysis (Entergy 2009).
,
w 00 0 (D ("") (D
- 3 c-O ...,
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--'
0 0 w (j)
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00
Appendix G 1 The NRC staff questioned the high cost estimate ($800,000) for changing the pressurizer PORV 2 block valves from normally closed to normally open in conjunction with IP2 SAMA 53 (NRC 3 2008a). In response, Entergy clarified that a modification had been previously implemented 4 allowing closure of the block valves when operating pressure is less than 2235 pounds per 5 square inch gauge (psig). If the reactor coolant pressure increases to 2300 psig, the current 6 circuitry alarms and sends a signal to open the block valves. The SAMA would reverse this 7 operating approach and may require adding or changing the auto-open feature to a lower value. 8 Entergy provided a breakdown of the estimated cost which included a $236,000 contingency 9 cost. As Section 4.21 of the ER states that contingency costs are excluded, the staff requested 10 clarification of this apparent inconsistency. In response, Entergy stated that the site-specific 11 implementation cost estimates include some contingency costs to account for the high degree of 12 uncertainty associated with the preliminary cost estimates and that given the bounding nature 13 of the benefit analysis, it is reasonable to include contingency costs in these estimates. To 14 eliminate the confusion between Section 4.21 of the ER and the stated practice above, Entergy 15 revised Section 4.21, eliminating the contingency exclusion clause (Entergy 2008b). 16 Considering that this SAMA has been added to the list of potentially cost-beneficial SAM As (see 17 Section G.6L the staff finds the cost estimate for SAMA 53 to be acceptable. In addition, no 18 other improvement cost estimates were identified as outliers. Therefore, the impact of including 19 contingency costs does not appear to be consequential. 20 As part of Entergy's SAMA re-analysis (using corrected meteorological dataL Entergy subjected 21 a subset of the SAMAs to more comprehensive and precise cost estimating techniques - 22 specifically, those SAMAs that appeared to be cost-beneficial based on the new benefit 23 estimate and the original implementation cost estimate. For two IP2 SAMAs (lP SAMAs 17 and 24 40) and four IP3 SAMAs (lP3 SAMAs 17, 20,40, and 50L the updated (increased) cost estimate 25 resulted in the SAMA becoming non-cost-beneficial (i.e., the SAMA would be cost-beneficial 26 based on the cost estimate reported in the ER but not cost-beneficial based on the revised cost 27 estimate). For each of these SAMAs, the NRC Staff requested that Entergy provide the basis 28 for the revised cost estimate and a breakdown of the cost estimate in terms of the major cost 29 factors. Entergy provided this additional information by letter dated January 14, 2010 (Entergy 30 2010). As stated in the response, the revised cost estimates were developed using Entergy's 31 standard process for developing conceptual-level project cost estimates utilizing spreadsheets 32 containing 2009 rates for material, labor, insurance, fees, etc. Also, Entergy determined that 33 one SAMA that was previously identified as potentially cost beneficial was no longer cost 34 beneficial based on correction of an error in the ER (lP3 SAMA 30) (Entergy 2008b, Entergy 35 2009). 36 The NRC staff reviewed this additional cost information to determine the degree to which the 37 revised cost estimates and their constituent costs comport with the nature, magnitude and 38 complexity of each change. The NRC staff notes that the associated modifications all involve 39 either major plant modifications (e.g., erecting a barrier to protect the containment liner, 40 installing secondary side guard pipes) or changes to safety-related systems, structures, or 41 components (e.g., increasing secondary side pressure capacity, enhancing the RCS 42 depressurization capabilities). In addition to hardware costs, the modifications would require 43 extensive design work and safety analysis calculations, including seismic analyses, thermal 44 analyses, and analyses for piping or penetration interferences. The cost estimates reported in 45 previous SAMA analyses for similar modifications are typically on the order of $1 M or more. 46 Entergy's cost estimates are consistent with these values. The NRC staff also notes that for December 2010 G-39 NUREG-1437, Supplement 38 OAGI0001367E 00479
Appendix G 1 each of these SAMAs the revised cost estimates are at least 50 percent greater than the revised 2 benefit estimates even when the benefit estimates are increased to account for uncertainties. 3 Accordingly, Entergy's revised cost estimates appear reasonable, and result in an appropriate 4 determination that these candidate SAMAs are not cost-beneficial. 5 The NRC staff concludes that the cost estimates provided by Entergy are sufficient and 6 appropriate for use in the SAMA evaluation. 7 G.G Cost-Benefit Comparison 8 Entergy's cost-benefit analysis and the NRC staff's review are described in the following 9 sections. 10 G.G.1. Entergy's Evaluation 11 The methodology used by Entergy was based primarily on the NRC's guidance for performing a 12 cost-benefit analysis (i.e., NUREG/BR-0184, "Regulatory Analysis Technical Evaluation 13 Handbook" (NRC 1997a). The guidance involves determining the net present value for each 14 SAMA according to the following formula: 15 Net Value = (APE + AOC + AOE + AOSC) - COE, where 16 APE present value of averted public exposure ($) 17 AOC present value of averted offsite property damage costs ($) 18 AOE present value of averted occupational exposure costs ($) 19 AOSC = present value of averted onsite costs ($) 20 COE = cost of enhancement ($) 21 If the net value of a SAMA is negative, the cost of implementing the SAMA is larger than the 22 benefit associated with the SAMA, and it is not considered cost beneficial. Entergy's derivation 23 of each of the associated costs is summarized below. 24 NUREG/BR-0058 has recently been revised to reflect the agency's policy on discount rates. 25 Revision 4 of NUREG/BR-0058 states that two sets of estimates should be developed-one at 26 3 percent and one at 7 percent (NRC 2004). Entergy performed the SAMA analysis using 27 7 percent and provided a sensitivity analysis using the 3 percent discount rate in order to 28 capture SAMAs that may be cost-effective using the lower discount rate, as well as the higher, 29 baseline rate (Entergy 2007). This analysis is sufficient to satisfy NRC policy in Revision 4 of 30 NUREG/BR-0058. 31 Averted Public Exposure (APE) Costs 32 The APE costs were calculated using the following formula: 33 APE = Annual reduction in public exposure (b.person-rem/year) 34 x monetary equivalent of unit dose ($2000 per person-rem) 35 x present value conversion factor (10.76 based on a 20-year period with 36 a 7 percent discount rate) NUREG-1437, Supplement 38 G-40 December 2010 OAGI0001367E 00480
Appendix G 1 As stated in NUREG/BR-0184 (NRC 1997aL the monetary value of the public health risk after 2 discounting does not represent the expected reduction in public health risk caused by a single 3 accident. Rather, it is the present value of a stream of potential losses extending over the 4 remaining lifetime (in this case, the renewal period) of the facility. Thus, it reflects the expected 5 annual loss caused by a single accident the possibility that such an accident could occur at any 6 time over the renewal period, and the effect of discounting these potential future losses to 7 present value. For the purposes of initial screening, which assumes elimination of all severe 8 accidents caused by internal events, Entergy calculated an APE of approximately $474,000 for 9 IP2 and $527,000 for IP3 for the 20-year license renewal period. Based on Entergy's SAMA re-10 analysis (using corrected meteorological dataL these values increase to $1.88M for IP2 and 11 $2.04M for IP3. 12 Averted Offsite Property Damage Costs (AOC) 13 The AOCs were calculated using the following formula: 14 AOC = Annual CDF reduction 15 x offsite economic costs associated with a severe accident (on a per-16 event basis) 17 x present value conversion factor 18 For the purposes of initial screening, which assumes all severe accidents caused by internal 19 events are eliminated, Entergy calculated an annual offsite economic cost of about $45,000 for 20 IP2 and $53,000 for IP3 based on the Level 3 risk analysis. This results in a discounted value 21 of approximately $483,000 for IP2 and $568,000 for IP3 for the 20-year license renewal period. 22 Based on Entergy's SAMA re-analysis (using corrected meteorological dataL these values 23 increase to $2.28 million for IP2 and $2.81 million for IP3. 24 Averted Occupational Exposure (AOE) Costs 25 The AOE costs were calculated using the following formula: 26 AOE = Annual CDF reduction 27 x occupational exposure per core damage event 28 x monetary equivalent of unit dose 29 x present value conversion factor 30 Entergy derived the values for AOE from information provided in Section 5.7.3 of the regulatory 31 analysis handbook (N RC 1997 a). Best estimate values that provided for immediate 32 occupational dose (3300 person-rem) and long-term occupational dose (20,000 person-rem 33 over a 1O-year cleanup period) were used. The present value of these doses was calculated 34 using the equations provided in the handbook, in conjunction with a monetary equivalent of unit 35 dose of $2000 per person-rem, a real discount rate of 7 percent and a time period of 20 years 36 to represent the license renewal period. For the purposes of initial screening, which assumes 37 all severe accidents caused by internal events are eliminated, Entergy calculated an AOE of 38 approximately $7,000 for IP2 and $4,000 for IP3 for the 20-year license renewal period. December 2010 G-41 NUREG-1437, Supplement 38 I OAGI0001367E 00481
Appendix G 1 Averted Onsite Costs 2 Averted onsite costs (AOSC) include averted cleanup and decontamination costs and averted 3 power replacement costs. Repair and refurbishment costs are considered for recoverable 4 accidents only and not for severe accidents. Entergy derived the values for AOSC based on 5 information provided in Section 5.7.6 of NUREG/BR-0184, the regulatory analysis handbook 6 (NRC 1997a). 7 Entergy divided this cost element into two parts-the onsite cleanup and decontamination cost 8 also commonly referred to as averted cleanup and decontamination costs (ACCL and the 9 replacement power cost (RPC). 10 ACCs were calculated using the following formula: 11 ACC = Annual CDF reduction 12 x present value of cleanup costs per core damage event 13 x present value conversion factor 14 The total cost of cleanup and decontamination subsequent to a severe accident is estimated in 15 NUREG/BR-0184 to be $1.5x10 9 (undiscounted). This value was converted to present costs 16 over a 1O-year cleanup period and integrated over the term of the proposed license extension. 17 For the purposes of initial screening, which assumes all severe accidents caused by internal 18 events are eliminated, Entergy calculated an ACC of approximately $208,000 for IP2 and 19 $133,000 for IP3 for the 20-year license renewal period. 20 Long-term RPCs were calculated using the following formula: 21 RPC = Annual CDF reduction 22 x present value of replacement power for a single event 23 x factor to account for remaining service years for which replacement 24 power is required 25 x reactor power scaling factor 26 Entergy based its calculations on the value of 1071 megawatt electric (MWe) and scaled up 27 from the 910 MWe reference plant in NUREG/BR-0184 (NRC 1997b). Therefore, Entergy 28 applied a power-scaling factor of 1071/910 to determine the RPCs. For the purposes of initial 29 screening, which assumes all severe accidents caused by internal events are eliminated, 30 Entergy calculated an RPC of approximately $166,000 for IP2 and $107,000 for IP3, and an 31 AOSC of approximately $374,000 for IP2 and $240,000 for IP3 for the 20-year license renewal 32 period. 33 Using the above equations and corrected meteorological data, Entergy determined that the total 34 present dollar-value equivalent associated with completely eliminating severe accidents caused 35 by internal events is approximately $4.5 million at IP2 and $5.1 million at IP3. Use of a 36 mUltiplier of 3.8 for IP2 and 5.5 for IP3 to account for external events increases the present 37 dollar value to $17 million for IP2 and $28 million for IP3 and represents the present dollar value 38 associated with completely eliminating the risk of severe accidents caused by all internal and 39 external events at IP2 and IP3, respectively. 40 Entergy's Results NUREG-1437, Supplement 38 G-42 December 2010 OAGI0001367E 00482
Appendix G 1 If the implementation costs for a candidate SAMA exceeded the calculated benefit the SAMA 2 was considered by Entergy not to be cost beneficial. In the baseline analysis (using a 7 percent 3 discount rate) and the sensitivity analysis (using a 3 percent discount rate) contained in the ER 4 Entergy identified 10 potentially cost-beneficial SAMAs (five for IP2 and five for IP3). Based on 5 consideration of analysis uncertainties, Entergy identified two additional potentially cost-6 beneficial SAM As for IP2 in the ER (lP2 SAMAs 44 and 56). 7 In response to an NRC staff request Entergy provided the results of a revised uncertainty 8 analysis in which the impact of lost tourism and business was accounted for in the baseline 9 analysis (rather than as a separate sensitivity case). The revised uncertainty analysis resulted 10 in the identification of two additional potentially cost-beneficial SAMAs for IP2 (lP2 SAMAs 9 11 and 53) and one additional potentially cost-beneficial SAMA for IP3 (lP3 SAMA 53L as reported 12 in the DSEIS. 13 Based on the SAMA re-analysis (using corrected meteorological dataL Entergy identified three 14 additional potentially cost-beneficial SAMAs for IP2 (lP2 SAMAs 21,22, and 62) and three 15 additional potentially cost-beneficial SAMAs for IP3 (I P3 SAMAs 7, 18, and 19). 16 In sum, the potentially cost-beneficial SAMAs for IP2 are the following: 17
- SAMA 9 - Create a reactor cavity flooding system to reduce the impact of core-concrete 18 interaction from molten core debris following core damage and vessel failure.
19
- SAMA 21 - Install additional pressure or leak monitoring instrumentation to reduce the 20 frequency of interfacing system loss of coolant accidents.
21
- SAMA 22 - Add redundant and diverse limit switches to each containment isolation 22 valve. This modification would reduce the frequency of an interfacing system loss of 23 coolant accident.
24
- SAMA 28 - Provide a portable diesel-driven battery charger to improve dc power 25 reliability. A safety-related disconnect would be used to charge a selected battery. This 26 modification would enhance the long-term operation of the turbine-driven AFW pump on 27 battery depletion.
28
- SAMA 44 - Use fire water as a backup for steam generator inventory to increase the 29 availability of the steam generator water supply to ensure adequate inventory for the 30 operation of the turbine-driven AFW pump during SBO events.
31
- SAMA 53 - Keep both pressurizer PORV block valves open. This modification would 32 reduce the CDF contribution from loss of secondary heat sink by improving the 33 availability of feed and bleed.
34
- SAMA 54 - Install a flood alarm in the 480-V ac switchgear room to mitigate the 35 occurrence of internal floods inside the 480-V ac switchgear room.
36
- SAMA 56 - Keep RHR heat exchanger discharge valves, motor-operated valves 746 37 and 747, normally open. This procedure change would reduce the CDF contribution from 38 transients and LOCAs.
39
- SAMA 60 - Provide added protection against flood propagation from stairwell 4 into the 40 480-V ac switchgear room to reduce the CDF contribution from flood sources within 41 stairwell 4 adjacent to the 480-V ac switchgear room.
December 2010 G-43 NUREG-1437, Supplement 38 OAGI0001367E 00483
Appendix G 1
- SAMA 61 - Provide added protection against flood propagation from the deluge room 2 into the 480-V ac switchgear room to reduce the CDF contribution from flood sources 3 within the deluge room adjacent to the 480-V ac switchgear room.
4
- SAMA 62 - Provide a hard-wired connection to a safety injection (SI) pump from the 5 alternate safe shutdown system (ASSS) power supply. This modification would reduce 6 the CDF from events that involve loss of power from the 480V vital buses.
7
- SAMA 65 - Upgrade the alternate safe shutdown system (ASSS) to allow timely 8 restoration of RCP-seal injection and cooling from events that cause a loss of power 9 from the 480-V ac vital buses.
10 The potentially cost-beneficial SAMAs for IP3 are the following: 11
- SAMA 7 - Create a reactor cavity flooding system. This modification would enhance 12 core debris cooling and reduce the frequency of containment failure due to core-13 concrete interaction.
14
- SAMA 18 - Route the discharge from the main steam safety valves through a structure 15 where a water spray would condense the steam and remove fission products.
16
- SAMA 19 - Install additional pressure or leak monitoring instrumentation to reduce the 17 frequency of interfacing system loss of coolant accidents.
18
- SAMA 52 - Institute a procedure for opening the city water supply valve for alternative 19 AFW system pump suction to enhance the availability of the AFW system.
20
- SAMA 53 - Install an excess flow valve to reduce the risk associated with hydrogen 21 explosions inside the turbine building or PAB.
22
- SAMA 55 - Provide the capability of powering one safety injection pump or RHR pump 23 using the Appendix R diesel (MCC 312A) to enhance RCS injection capability during 24 events that cause a loss of power from the 480-V ac vital buses.
25
- SAMA 61 - Upgrade the ASSS to allow timely restoration of RCP-seal injection and 26 cooling from events that cause a loss of power from the 480-V ac vital buses.
27
- SAMA 62 - Install a flood alarm in the 480-V ac switchgear room to mitigate the 28 occurrence of internal floods inside the 480-V ac switchgear room.
29 In response to an NRC staff inquiry regarding estimated benefits for certain SAMAs and lower 30 cost alternatives, one additional potentially cost-beneficial SAMA was identified (regarding a 31 dedicated main stream safety valve gagging device for SGTR events in both units) (Entergy 32 2008b), and one SAMA that was previously identified as potentially cost beneficial was found no 33 longer cost beneficial based on correction of an error in the ER (lP3 SAMA 30) (Entergy 2008a, 34 Entergy 2009). The potentially cost-beneficial SAMAs and Entergy's plans for further evaluation 35 of these SAMAs are discussed in more detail in Section G.6.2. 36 G.1.2 Review of Entergy's Cost-Benefit Evaluation 37 The cost-benefit analysis performed by Entergy was based primarily on NUREG/BR-0184 (NRC 38 1997 a) and was implemented consistent with that guidance. NUREG-1437, Supplement 38 G-44 December 2010 OAGI0001367E 00484
Appendix G 1 SAMAs identified primarily on the basis of the internal events analysis could provide benefits in 2 certain external events, in addition to their benefits in internal events. To account for the 3 additional benefits in external events, Entergy multiplied the internal event benefits for each 4 internal event SAMA by an amount equal to the ratio of the sum of the internal and external 5 event CDF to the internal event CDF. This ratio is approximately 3.8 for IP2 and 5.5 for IP3. 6 Potential benefits in external events were estimated in this manner, since the external-event 7 models are generally less detailed than the internal-event models and do not lend themselves to 8 quantifying the benefits of the specific plant changes associated with internal-event SAMAs. 9 For example, the benefits of a procedural change associated with an important internal event 10 sequence cannot be readily assessed using the seismic-risk model if that operator action or 11 system is not represented in the seismic-risk model. The use of a mUltiplier on the benefits 12 obtained from the internal events PSA to incorporate the impact of external events implicitly 13 assumes that each SAMA would offer the same percentage reduction in external-event CDF 14 and population dose as it offers in internal events. While this provides only a rough 15 approximation of the potential benefits, such an adjustment was considered appropriate, given 16 the large risk contribution from external events relative to internal events and the lack of 17 information on which to base a more precise risk reduction estimate for external events. In view 18 of the remaining conservatism in the external events CDF, and the licensee's further evaluation 19 of the impacts of the use of a mUltiplier on the SAMA screening (as part of the uncertainty 20 assessment discussed below). the NRC staff agrees that the use of these mUltipliers for 21 external events is reasonable. 22 For SAMA candidates that only address a specific external event and have no bearing on 23 internal-event risk, Entergy derived the benefit directly from the external-event risk model and 24 then increased the benefit by the mUltipliers identified earlier. The NRC staff notes that the use 25 of mUltipliers for these SAMAs (conceptually, to account for additional benefits in internal 26 events) is unnecessary, since these SAMAs have no bearing on internal events. However, use 27 of the mUltipliers adds conservatism to the benefit estimate for these SAMA candidates. 28 Entergy considered the impact that possible increases in benefits from analysis uncertainties 29 would have on the results of the SAMA assessment. In the ER Entergy presents the results of 30 an uncertainty analysis of the internal-event CDF for IP2 and IP3, which indicates that the 95th 31 percentile value is a factor of 2.1 times the mean CDF for IP2 and 1.4 times the mean CDF for 32 IP3. Entergy assessed the impact on the SAMA screening if the estimated benefits for each 33 SAMA were further increased by these uncertainty factors. For purposes of this assessment 34 Entergy applied a mUltiplier of 8 to the internal-event benefits for each unit to account for both 35 internal and external events, with analysis uncertainty. The mUltiplier of 8 slightly exceeds the 36 product of the external-event mUltiplier and the uncertainty factor for each unit (i.e., 37 3.80x2.1 0= 7 .98 for IP2, and 5.53x1.40= 7 .73 for IP3) and adds a small amount of additional 38 conservatism. Although not cost beneficial in the baseline analysis, Entergy included any 39 additional SAMAs identified as potentially cost beneficial in the uncertainty analysis within the 40 set of potentially cost-beneficial SAMAs that it intends to examine further for implementation. 41 Entergy also provided the results of additional sensitivity analyses in the ER including use of a 42 3 percent discount rate, use of a longer plant life, and the consideration of economic losses by 43 tourism and business (which were not included in the baseline analysis). These analyses did 44 not identify any additional potentially cost-beneficial SAMAs beyond those already identified 45 through the uncertainty analysis. December 2010 G-45 NUREG-1437, Supplement 38 I OAGI0001367E 00485
Appendix G 1 The NRC staff questioned the rationale for treating the loss of tourism and business in a 2 sensitivity case rather than in the baseline analysis (NRC 2007). Incorporation of tourism and 3 business losses within the baseline analysis could result in identification of additional cost-4 beneficial SAMAs, particularly when the baseline benefits are multiplied to account for 5 uncertainties. In response, Entergy explained that the impact of lost tourism and business was 6 not modeled in the baseline analysis because the level of tourism and business activity can be 7 reestablished in time. Nevertheless, Entergy provided the results of an additional uncertainty 8 case showing the impact of lost tourism and business combined with analysis uncertainty. This 9 uncertainty case resulted in the identification of two additional potentially cost-beneficial SAMAs 10 for IP2 (lP2 SAMAs 9 and 53) and one additional potentially cost-beneficial SAMA for IP3 (lP3 11 SAMA 53). Given that it may take years to reestablish the level of tourism and business activity 12 following a severe accident the NRC staff has conservatively adopted the case incorporating 13 lost tourism and business as its base case and has reflected the results of that case in 14 Table G-6. 15 In responding to an NRC RAt Entergy identified and corrected an error in the benefit analysis 16 for IP3 SAMA 30 (provide a portable battery charger for monitoring instrumentation necessary to 17 allow manual operation of the turbine-driven AFW pump), which results in this SAMA no longer 18 being potentially cost beneficial. As indicated in ER Section E.4.3, the benefit of this SAMA was 19 estimated based on the assumption that the SAMA would increase the time available to recover 20 offsite power before local operation of AFW is required from 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> to 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />, and would also 21 reduce internal switchgear room floods by 5 percent (which bounds the benefit of using a 22 portable diesel-driven battery charger in switchgear flood events). According to Entergy, the 23 original analysis inadvertently reduced the contribution from internal switchgear room floods by 24 more than 5 percent (Entergy 2008a). Entergy's reevaluation of the benefits for this SAMA, 25 consistent with the intended bounding case, resulted in a reduction in the baseline benefit to 26 about $146,000, including the impacts of lost tourism and business and analysis uncertainties 27 (Entergy 2008a), and $309,000 using the same assumptions and corrected site meteorological 28 data (Entergy 2009). The revised benefit estimate using corrected site meteorology is reflected 29 in Table G-6. The NRC staff notes that the benefit associated with several other SAMA 30 candidates that could increase the time available to recover offsite power before local operation 31 of AFW is required from 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> to 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> (e.g., IP3 SAMA 24 (provide additional dc battery 32 capacity) was estimated at about $51,000, including the impacts of lost tourism and business 33 and analysis uncertainties. Therefore, a revised benefit estimate of $146,000 (before correcting 34 site meteorological data) for IP3 SAMA 30, which also includes the additional benefit from 35 reducing the contribution of internal switchgear room floods by 5 percent appears reasonable. 36 In the ER Entergy indicated that the implementation cost associated with IP3 SAMA 30 (i.e., 37 $494,000) was specifically estimated for IP3. The proposed plant modification involves 38 purchasing, installing, and maintaining a diesel-driven generator to charge the 125-V dc 39 batteries. Safety-related quick-disconnects would be used to charge the selected battery. The 40 diesel generator would be installed in a weather enclosure outside the turbine or control 41 building, requiring fire barrier penetration sealing. Calculation of cable size, as well as 42 procedure development and training, would be required (Entergy 2007). In view of the scope of 43 these modifications and the fact that the modifications involve a safety-related dc system, the 44 estimated costs appear reasonable. As part of Entergy's SAMA re-analysis (using corrected 45 meteorological data) Entergy provided an updated site-specific cost estimate of $938,000 for 46 SAMA 30 based on more comprehensive and precise cost estimating techniques (Entergy NUREG-1437, Supplement 38 G-46 December 2010 OAGI0001367E 00486
Appendix G 1 2009). However, the NRC staff notes that SAMA 30 would not be cost-beneficial regardless of 2 which cost estimate is used. Accordingly, the NRC staff agrees that this SAMA would not be 3 cost beneficial for IP3. 4 The NRC-sponsored severe accident analyses performed subsequent to the time of the IPE 5 suggest that the probability of a TI-SGTR given a core-damage event with high primary-side 6 pressure and a depressurized, dry secondary side, may be higher than the value used in the 7 IP2 and IP3 PSAs. In response to an NRC request Entergy provided the results of a sensitivity 8 study in which it increased the conditional TI-SGTR probability from 0.01 (used in the baseline 9 analysis) to 0.25, which is comparable to the values reported in NUREG-1570 (NRC 1998). 10 Entergy identified the candidate SAMAs potentially affected by the TI-SGTR assumption and 11 reassessed the benefits for these SAMAs, subject to the increased conditional failure probability 12 and the impact of analysis uncertainties. Entergy identified no additional cost-beneficial SAMAs 13 as a result of this reassessment. Entergy also noted that the IP2 and IP3 steam generators 14 have only 0.19 percent and 0.12 percent of the tubes plugged for IP2 and IP3, respectively, and 15 would be classified as "pristine," in accordance with the Westinghouse criteria for categorizing 16 steam generator tube integrity. With no observed corrosion, Entergy concludes-and the NRC 17 staff concurs-that this sensitivity study is conservative relative to the application of the 18 NUREG-1570 results for pristine generators (Entergy 2008b). 19 As part of Entergy's SAMA re-analysis, Entergy revisited this sensitivity study using corrected 20 site meteorological data. Due to the higher offsite consequences in the re-analysis, additional 21 SAMAs were identified as potentially impacted by the TI-SGTR assumption (relative to the 22 original study) and were re-evaluated. Based on the re-evaluation, one additional SAMA was 23 found to be potentially cost-beneficial for IP3 (lP3 SAMA 18) (Entergy 2009). 24 The NRC staff noted that for certain SAMAs considered in the ER there may be alternatives 25 that could achieve much of the risk reduction at a lower cost. The NRC staff asked the licensee 26 to evaluate several lower cost alternatives to the SAMAs considered in the ER including 27 SAMAs that had been found to be potentially cost beneficial at other PWR plants. These 28 alternatives were (1) implementation of improved instrumentation and/or procedures to aid in 29 the mitigation of a SGTR (2) implementation of a procedure for recovery of steam dump to 30 condenser from the unaffected steam generator to aid the mitigation of a SGTR, 31 (3) implementation of a procedure for recovery of the main feedwater/condensate after safety 32 injection actuation to aid in the mitigation of a SGTR (4) reactivation of the IP3 postaccident 33 containment venting system, and (5) purchase or manufacture of a "gagging device" that could 34 be used to close a stuck-open steam generator safety valve on a faulted steam generator 35 before core damage occurs (NRC 2007a, NRC 2007b). Entergy provided a further evaluation of 36 these alternatives, as summarized below. 37
- Improve SGTR instrumentation and/or valve procedures. Operator actions to cool and 38 depressurize the RCS to cold shutdown conditions following a SGTR before depleting 39 RWST inventory are already contained in EOPs. EOPs also direct plant personnel to 40 initiate RWST makeup, given a low RWST level without a corresponding increase in the 41 containment recirculation sump water level, or if the ruptured steam generator narrow-42 range level indication is high.
December 2010 G-47 NUREG-1437, Supplement 38 I OAGI0001367E 00487
Appendix G 1
- Institute a procedure for recovery of steam dump to condenser. Procedures for recovery 2 of steam dump to condenser from the unaffected steam generator are currently available 3 at both units.
4
- Recover main feedwater/condensate. For IP2, the operators are currently directed to 5 attempt to establish a secondary heat sink with AFW, main feedwater, or condensate, 6 should the AFW system initially not function or subsequently fail during implementation 7 of the EOPs. For IP3, procedural guidance currently exists for re-establishing 8 condensate flow, but there is no guidance to use main feed water following a loss of the 9 secondary heat sink. Thus, the development of guidance on aligning main feedwater for 10 secondary heat removal was evaluated as a potential SAMA for IP3.
11
- Reactivate the IP3 containment venting system. IP3 has three alternate methods of 12 containment depressurization and combustible gas control. These methods are 13 backflow to the steam ejector line, containment pressure relief line, and the containment 14 purge system. All of the venting functions require similar operator actions. Given these 15 various alternatives, failure to vent would be dominated by human error and would not 16 be substantially reduced by providing an additional means of venting.
17 With regard to the steam generator safety gagging device, which was found to be potentially 18 cost beneficial at another pressurized-water reactor seeking license renewal, Entergy provided 19 a separate assessment of the benefits and implementation costs. Entergy estimated the benefit 20 associated with successfully gagging a stuck-open main steam safety valve following an SGTR 21 by assuming all early steam generator isolation failures and all TI-SGTRs would be eliminated. 22 The total benefits were estimated to be about $2.9 million for IP2 and $4.4 million for IP3 23 (Entergy 2008b). Based on Entergy's SAMA re-analysis (using corrected meteorological dataL 24 these values would increase to about $13 million for IP2 and $19 million for IP3 (Entergy 2009). 25 The implementation cost including purchasing and storing a dedicated gagging devise, revising 26 procedures, and providing training, was estimated to be about $50,000 for each unit. As such, 27 the results indicate that this SAMA is potentially cost beneficial for both units. Entergy indicates 28 that this additional SAMA has been submitted for an engineering project cost-benefit analysis 29 for a more detailed examination of its viability and implementation cost (Entergy 2008b). The 30 NRC staff concurs with Entergy's findings regarding these alternative SAMAs because the NRC 31 staff finds the additional information provided by Entergy for the aforementioned alternative 32 SAMAs to be technically sound. 33 The NRC staff notes that all of the 12 potentially cost-beneficial SAMAs for IP2 (lP2 SAMAs 9, 34 21, 22, 28, 44, 53, 54, 56, 60, 61, 62 and 65) and eight potentially cost-beneficial SAM As for 35 IP3 (lP3 SAMAs 7,18,19,52,53,55,61, and 62L identified in either Entergy's baseline 36 analysis or supplemental analyses provided in response to the NRC requests, as well as the 37 additional SAMA regarding a dedicated gagging device for SGTR events (applicable to both 38 unitsL are included within the set of SAMAs that Entergy will consider further for 39 implementation. The NRC staff concludes that with the exception of the potentially cost-40 beneficial SAM As discussed above, the costs of the other SAMAs would be higher than the 41 associated benefits (i.e., no additional SAMAs appear to be cost-beneficial). 42 G.7 Conclusions I NUREG-1437, Supplement 38 G-48 December 2010 OAGI0001367E 00488
Appendix G 1 Entergy compiled a list of 231 candidate SAMAs for IP2 and 237 SAMAs for IP3, based on a 2 review of the most significant basic events from the current plant-specific PSA, insights from the 3 plant-specific IPE and IPEEE, and a review of other industry documentation. An initial 4 screening removed SAMA candidates that (1) were not applicable at IP2 and IP3, (2) were 5 already implemented or their intent had been met or (3) were similar in nature and could be 6 combined with another SAMA candidate. Based on this screening, 163 IP2 and 175 IP3 7 SAMAs were eliminated, leaving 68 IP2 and 62 IP3 candidate SAMAs for evaluation. 8 For the remaining SAMA candidates, more detailed evaluation was performed as shown in 9 Table G-6. The cost-benefit analyses in the ER showed that five IP2 and five IP3 SAMA 10 candidates were potentially cost beneficial in either the baseline analysis or sensitivity analysis 11 using a 3 percent discount rate. Entergy performed additional analyses to evaluate the impact 12 of parameter choices and uncertainties on the results of the SAMA assessment. As a result 13 four additionallP2 SAMAs and one additionallP3 SAMA were identified as potentially cost 14 beneficial. In addition, a SAMA regarding a dedicated gagging device for SGTR events was 15 identified as potentially cost beneficial for both units. Correction of an error in the benefit 16 analysis for IP2 SAMA 30 resulted in it no longer being considered cost beneficial. Subsequent 17 to issuance of the DSEIS, in response to NRC Staff questions, Entergy identified an error in the 18 Indian Point site meteorology file used to calculate offsite consequences of severe accidents, 19 and submitted a SAMA re-analysis based on corrected meteorological data (Entergy 2009). 20 The SAMA re-analysis resulted in identification of three additional potentially cost beneficial 21 SAMAs for IP2 (lP2 SAMAs 21,22, and 62) and three potentially cost beneficial SAMAs for IP3 22 (lP3 SAMAs 7, 18, and 19). Entergy has indicated that all 12 potentially cost-beneficial SAMAs 23 for IP2 (lP2 SAMAs 9, 21, 22, 28, 44, 53, 54, 56, 60, 61, 62, and 65) and eight potentially cost-24 beneficial SAM As for IP3 (lP3 SAMAs 7,18,19,52,53,55,61, and 62), as well as the 25 additional SAMA regarding a dedicated gagging device for SGTR events, will be considered 26 further for implementation at IP2 and IP3. 27 The NRC staff reviewed the Entergy analysis and concludes that the methods used and the 28 implementation of those methods were sound. The treatment of SAMA benefits and costs 29 support the general conclusion that the SAMA evaluations performed by Entergy are reasonable 30 and sufficient for the license renewal submittal. Although the treatment of SAMAs for external 31 events was somewhat limited, the likelihood of there being cost-beneficial enhancements in this 32 area was minimized by improvements that have been realized as a result of the IPEEE process 33 and inclusion of a mUltiplier to account for external events. 34 The NRC staff concurs with Entergy's identification of areas in which risk can be further reduced 35 in a cost-beneficial manner through the implementation of the identified, potentially cost-36 beneficial SAMAs. Given the potential for cost-beneficial risk reduction, the NRC staff agrees 37 that further evaluation of these SAMAs by Entergy is warranted. However, these SAMAs do not 38 relate to adequately managing the effects of aging during the period of extended operation. 39 Therefore, they need not be implemented as part of license renewal pursuant to Title 10 of the 40 Code of Federal Regulations, Part 54, "Requirements for Renewal of Operating Licenses for 41 Nuclear Power Plants" (10 CFR Part 54). 42 G.B References December 2010 G-49 NUREG-1437, Supplement 38 I OAGI0001367E 00489
Appendix G 1 Consolidated Edison (Con Ed). 1992. Letter from Stephen B. Bram to U.S. NRC,
Subject:
2 Generic Letter 88-20, Supplement 1: Individual Plant Examination (lPE) for Severe Accident 3 Vulnerabilities-10 CFR 50.54, IP2 and IP3 Unit No.2, August 12,1992. 4 Consolidated Edison (Con Ed). 1995. Letter from Stephen E. Quinn to U.S. NRC,
Subject:
5 Final Response to Generic Letter 88-20, Supplement 4: Submittal of Individual Plant 6 Examination of External Events (lPEEE) for Severe Accident Vulnerabilities, IP2 and IP3 Unit 7 No.2, December 6, 1995. 8 Entergy Nuclear Operations, Inc. (Entergy). 2007. Letter from Fred Dacimo to U.S. NRC, 9
Subject:
IP2 and IP3 Energy Center Licensee Renewal Application, NL-07-039, April 23, 2007. 10 ADAMS Accession No. ML071220512. 11 Entergy Nuclear Operations, Inc. (Entergy). 2008a. Letter from Fred R. Dacimo to U.S. NRC, 12
Subject:
Reply to Request for Additional Information Regarding License Renewal Application-13 Severe Accident Mitigation Alternatives Analysis, NL-08-028, February 5,2008. ADAMS 14 Accession No. ML080420264. 15 Entergy Nuclear Operations, Inc. (Entergy). 2008b. Letter from Fred R. Dacimo to U.S. NRC, 16
Subject:
Supplemental Reply to Request for Additional Information Regarding License Renewal 17 Application-Severe Accident Mitigation Alternatives Analysis, NL-08-086, May 22, 2008. 18 ADAMS Accession No. ML081490336. 19 Entergy Nuclear Operations, Inc. (Entergy). 2009. Letter from Fred Dacimo to U.S. NRC, 20
Subject:
License Renewal Application - SAMA Re-analysis Using Alternate Meteorological 21 Tower Data, NL-09-165, December 11,2009. ADAMS Accession No. ML093580089. 22 Entergy Nuclear Operations, Inc. (Entergy). 2010. Letter from Fred Dacimo to U.S. NRC, 23
Subject:
License Renewal Application - Supplement To SAMA Re-Analysis Using Alternate 24 Meteorological Tower Data, NL-10-013, January 14, 2010. ADAMS Accession No. 25 ML100260750. 26 New York Power Authority (NYPA). 1994. Letter from William A. Josiger to U. S. NRC,
Subject:
27 IP2 and IP3 3 Nuclear Power Plant Individual Plant Examination for Internal Events, June 30, 28 1994. 29 New York Power Authority (NYPA). 1997. Letter from James Knubel to U.S. NRC,
Subject:
30 IP2 and IP3 3 Nuclear Power Plant Individual Plant Examination of External Events (lPEEE), 31 September 26,1997. 32 Nuclear Regulatory Commission (NRC). 1990. "Severe Accident Risks: An Assessment for 33 Five U.S. Nuclear Power Plants." NUREG-1150, Washington, DC, December 1990. ADAMS 34 Accession No. ML040140729. 35 Nuclear Regulatory Commission (NRC). 1991. Generic Letter 88-20, Supplement 4, "Individual 36 Plant Examination of External Events (lPEEE) for Severe Accident Vulnerabilities," June 28, 37 1991. 38 Nuclear Regulatory Commission (NRC). 1995. Letter from Jefferey F. Harold to William J. 39 Cahill, Jr.,
Subject:
Staff Evaluation of IP2 and IP3 Nuclear Generating Unit NO.3-Individual 40 Plant Examination (TAC No. M74423), December 11, 1995. I NUREG-1437, Supplement 38 G-50 December 2010 OAGI0001367E 00490
Appendix G 1 Nuclear Regulatory Commission (NRC). 1996. Letter from Barry Westreich to Stephen E. 2 Quinn,
Subject:
Staff Evaluation of IP2 and IP3 Nuclear Generating Unit NO.2-Individual Plant 3 Examination (TAC No. M74422), August 14, 1996. 4 Nuclear Regulatory Commission (NRC). 1997a. "Regulatory Analysis Technical Evaluation 5 Handbook." NUREG/BR-0184, Washington, DC, January 1997. 6 Nuclear Regulatory Commission (NRC). 1997b. "Individual Plant Examination Program: 7 Perspectives on Reactor Safety and Plant Performance." NUREG-1560, Washington, DC, 8 December 1997. 9 Nuclear Regulatory Commission (NRC). 1997c. "Code Manual for MACCS2: Volume 1, User's 10 Guide." NUREG/CR-6613, Washington, DC, May 1998. 11 Nuclear Regulatory Commission (NRC). 1998. "Risk Assessment of Severe Accident-Induced 12 Steam Generator Tube Rupture." NUREG-1570, Washington, DC, March 1998. 13 Nuclear Regulatory Commission (NRC). 1999. Letter from Jefferey F. Harold to A. Alan Blind, 14
Subject:
Review of IP2 and IP3 Nuclear Generating Unit NO.2-Individual Plant Examination of 15 External Events (lPEEE) Submittal (TAC No. M83631), August 13,1999. 16 Nuclear Regulatory Commission (NRC). 2001. Letter from George F. Wunder to Michael 17 Kansler,
Subject:
Review of Individual Plant Examination of External Events-IP2 and IP3 18 Nuclear Generating Unit No.3 (TAC No. M83632), February 15, 2001. ADAMS Accession No. 19 ML010080273. 20 Nuclear Regulatory Commission (NRC). 2002. "Perspectives Gained From the Individual Plant 21 Examination of External Events (lPEEE) Program," Volume 1 & 2, Final Report. NUREG-1742, 22 Washington, DC, April 2002. 23 Nuclear Regulatory Commission (NRC). 2004. "Regulatory Analysis Guidelines of the U.S. 24 Nuclear Regulatory Commission." NUREG/BR-0058, Washington, DC, September 2004. 25 ADAMS Accession No. ML042820192. 26 Nuclear Regulatory Commission (NRC). 2007. Letter from Jill Caverly to Entergy,
Subject:
27 Request for Additional Information Regarding Severe Accident Mitigation Alternatives for IP2 28 and IP3 Nuclear Generating Unit Nos. 2 and 3 Licensee Renewal (TAC Nos. MD5411 and 29 MD5412), December 7,2007. ADAMS Accession No. ML073110447. 30 Nuclear Regulatory Commission (NRC). 2008. Letter from Bo M. Pham to Entergy,
Subject:
31 Request for Additional Information Regarding the Review of the License Renewal Application for 32 IP2 and IP3 Nuclear Generating Unit Nos. 2 and 3 (TAC Nos. MD5411 and MD5412), April 9, 33 2008. ADAMS Accession No. ML080880104. 34 Nuclear Regulatory Commission (NRC). 2010. Atomic Safety and Licensing Board. LBP 35 13. 71 NRC === (2010). slip op. at 10,14-15. 36 U.S. Department of Agriculture (USDA). 2002. "Census of Agriculture." Accessed at: 37 http://www.nass.usda.gov/census/onApril26.200S.us/on April 26,2009. December 2010 G-51 NUREG-1437, Supplement 38 I OAGI0001367E 00491
Appendix H u.s. Nuclear Regulatory Commission Staff Evaluation of Environmental Impacts of Cooling System OAGI0001367E 00492
1 Appendix H 2 U.S. Nuclear Regulatory Commission 3 Staff Evaluation of 4 Environmental Impacts of Cooling System 5 H.1 Environmental Impacts of Cooling System 6 Environmental issues associated with the operation of a nuclear power plant during the renewal 7 term are discussed in the U.S. Nuclear Regulatory Commission (NRC) document 8 NUREG-1437, Volumes 1 and 2, "Generic Environmental Impact Statement for License 9 Renewal of Nuclear Plants" (hereafter referred to as the GElS) (NRC 1996, 1999).(a) The GElS 10 includes a determination of whether the analysis of the environmental issues could be applied to 11 all plants and whether additional mitigation measures would be warranted. Issues are then 12 assigned a generic (Category 1) or site-specific (Category 2) designation. As set forth in the 13 GElS, generic issues are those that have the following characteristics: 14 (1) The environmental impacts associated with the issue have been determined to apply 15 either to all plants or, for some issues, to plants having a specific type of cooling system 16 or other specified plant or site characteristics. 17 (2) A single significance level (i.e., SMALL, MODERATE, OR LARGE) has been assigned to 18 the impacts (except for collective offsite radiological impacts from the fuel cycle and from 19 high-level waste and spent fuel disposal). 20 (3) Mitigation of adverse impacts associated with the issue has been considered in the 21 analysis, and it has been determined that additional plant-specific mitigation measures 22 are likely not to be sufficiently beneficial to warrant implementation. 23 No additional plant-specific analysis is required for generic issues unless new and significant 24 information is identified. Site-specific issues do not have all the above characteristics, and a 25 plant-specific review is required. 26 This appendix addresses the issues that are listed in Table B-1, Appendix B, Subpart A, of 27 Title 10 of the Code of Federal Regulations (CFR), Part 51, "Environmental Protection 28 Regulations for Domestic Licensing and Related Regulatory Functions," and that are related to 29 the operation of the cooling systems of Indian Point Nuclear Generating Unit Nos. 2 and 3 (lP2 30 and IP3) during their renewal term. Section H.1 addresses the impingement of fish and shellfish 31 applicable to the IP2 and IP3 cooling systems. Section H.2 addresses the entrainment of fish 32 and shellfish applicable to the IP2 and IP3 cooling systems. Section H.3 addresses the 33 combined effects of impingement and entrainment and Section H.4 discusses cumulative 34 impacts. Finally, Section H.5 lists the references for Appendix H. Category 1 and Category 2 35 issues that are not applicable to IP2 and IP3, because they are related to plant design features December 2010 H-1 NUREG-1437, Supplement 38 OAGI0001367E 00493
Appendix H 1 or site characteristics not found at IP2 and IP3, are listed in Appendix F. As stated in Section 2 4.1 of this SEIS, the applicant submitted corrected impingement and entrainment data following 3 publication of the draft SEIS. The NRC staff considered those data as well as comments NRC 4 received regarding the draft SEIS in preparing this appendix. 5 H.1.1. Impingement of Fish and Shellfish 6 Impingement occurs when organisms are trapped against cooling water intake screens or racks 7 by the force of moving water. Impingement can kill organisms immediately or gradually, by 8 exhaustion, suffocation, injury, or exposure to air when screens are rotated for cleaning. The 9 potential for injury or death is generally related to the amount of time an organism is impinged, 10 its susceptibility to injury, and the physical characteristics of the screenwash and fish return 11 system that is employed. Studies of impingement losses associated with the operation of IP2 12 and IP3 cooling systems were conducted annually from 1975 to 1990. Before the installation of 13 modified Ristroph screen systems in 1991, impingement mortality was assumed to be 14 100 percent. Beginning in 1985, studies were conducted to evaluate whether the addition of 15 Ristroph screens would decrease impingement mortality for representative species. The final 16 design (Version 2). as reported in Fletcher (1990). appeared to reduce impingement mortality, 17 based on a pilot study, in comparison to the existing (original) system in place at IP2 and IP3 18 (Table H-1). The impingement survival estimates reported in Fletcher (1990) were not 19 validated, however, after the new Ristroph screens were installed at IP2 and IP3 in 1991. 20 Table H-1 Assumed Cumulative Mortality and Injury of Selected Fish Species after 21 Impingement on Ristroph Screens Percent Species Dead and Injured Alewife 62 American Shad 35 Atlantic T omcod 17 Bay Anchovy 23 Blueback Herring 26 Hogchoker 13 Striped Bass 9 Weakfish 12 White Catfish 40 White Perch 14 Source: Fletcher 1990. 22 H.1.1.1. Summary of Impingement Monitoring Studies I NUREG-1437, Supplement 38 H-2 December 2010 OAGI0001367E 00494
Appendix H 1 The former owners of IP2 and IP3 conducted impingement monitoring between 1975 and 1990 2 using a variety of techniques. Between January 1975 and June 1981, fish were collected and 3 sorted during a daily intake screen washing between 0800 and 1200 hours50 days <br />7.143 weeks <br />1.644 months <br /> (hr). In July 1981 4 and continuing through October 1990, fish were collected during intake screen washings 5 between 0800 and 1200 hr on selected days determined from a stratified random design 6 intended to reduce the overall sampling effort without affecting data use and utility. Between 7 October and December 1990, IP2 was sampled every Tuesday, and IP3 was not sampled 8 because of a plant outage. During all collections, the wash water was circulated to draw a 9 portion of the fish and debris into the forebay, where it was drained through a sluice containing a 10 1-millimeter (mm) (0.375-inch [in.]) square mesh screen. Collection efficiency was estimated in 11 1974,1975, and 1977 at IP2. The results of these studies suggested that the collection 12 efficiency was highly variable (ranging from 2 percent to 45 percent based on the recovery of 13 dyed fish) and averaged 29 percent (Con Edison 1976, Con Edison 1979). Collection efficiency 14 at IP3 in 1976 and 1977 ranged from 58 percent to 86 percent recovery of dyed fish with an 15 average of 71 percent (Con Edison 1977, Con Edison 1979). The difference in the collection 16 efficiency at the two units was associated with the differences in the type of screens (fixed 17 versus traveling screens) and the method used for screen washing. To estimate the total 18 number of fish impinged, the total number of fish collected was multiplied by an adjustment 19 factor representing the inverse of the collection efficiency. From 1975 to 1978, adjustment 20 factors of 3.5 and 1.4 were used for IP2 and IP3, respectively (Con Edison 1980). 21 Analysis of variance and the correlation of environmental and IP2 and IP3 operation variables 22 were employed to explain the variation in collection efficiency. Early studies suggested that 23 collection efficiency increased during periods of low water temperature. In 1979, the adjustment 24 factor became a function of the time of year, based on the increase in collection efficiency when 25 water temperatures were less than 15°C (59°F). Thus, cool water adjustment factors of 2.1 and 26 1.2 were adopted to estimate the number of fish impinged at IP2 and IP3, respectively, during 27 January through April, November, and December. For May to October, the adjustment factor 28 was 3.8 for IP2 and 1.5 for IP3. In 1981, the collection efficiency was estimated with a 29 regression relationship with temperature: 30 IP2 efficiency= E2 = -0.00945 (Temperature 0c) + 0.54708 31 IP3 efficiency= E3 = -0.00792 (Temperature 0c) + 0.71640 (Con Edison 1984). 32 These regression relationships were updated in 1982, and screen-specific adjustments were 33 devised from studies conducted in 1985 and 1986 (Table H-2). 34 Impingement monitoring designs changed through time (Con Edison 1980, Con Edison 1984, 35 Con Edison and NYPA 1986, Con Edison and NYPA 1987, Con Edison and NYPA 1988, Con 36 Edison and NYPA 1991) as follows. In 1979, the daily variation in impingement counts was 37 analyzed to determine its effect on the precision and accuracy of reduced sampling plans. 38 Starting in July 1981, a sampling plan employing a seasonally stratified random sample 39 developed from these results was used for all further impingement studies except the last 40 quarter of 1990. Instead of sampling daily, IP2 and IP3 were sampled a total of 110 days per 41 year (a 30-percent sampling fraction with approximately 92-percent accuracy) (Con Edison 42 1984). Days were selected at random within four calendar strata defined by similar water 43 temperatures and variance in the number of fish impinged (January-March, April-June, July-44 September, and October-December). The number of days sampled per stratum was December 2010 H-3 NUREG-1437, Supplement 38 OAGI0001367E 00495
Appendix H 1 proportional to the number of days available and the variance in impingement for all taxa 2 combined (Table H-3) (Con Edison 1984). The number of days allocated to strata was updated 3 in 1985 to take advantage of current data trends and again in 1990 because of known plant 4 outages. Even though IP2 and IP3 had different numbers of samples allocated to each stratum, 5 sampling was conducted on the same day at both units to the extent possible. 6 During 1981, the New York State Department of Environmental Conservation (NYSDEC) 7 required daily sampling when total impingement counts were greater than 10,000 fish. Daily 8 sampling was required to continue until the total was below 10,000 fish. Because these 9 sampling dates were not part of the stratified design, they were used in place of random dates 10 that were associated with unplanned unit outages. Outages were defined as circulating pump 11 outages and were not necessarily associated with cessation of power generation. In 1981, 12 randomly selected days that fell on planned outages were not replaced. From 1982 to 13 October 1990, to minimize the effect of planned and unplanned outages on the selected days 14 for collection, a randomly selected replacement day within the given stratum was sampled. In 15 October 1990, a systematic sampling design was employed that required sampling at IP2 each 16 Tuesday. No sampling was conducted at IP3 from October 1990 to December 1990 because of 17 an extended outage. 18 Sampling for blue crabs began in April 1983 and continued though December 1990. Sampling 19 was conducted on all days of plant operation. The total number of impinged crab and their total 20 weight were obtained for each sampling. In addition, the carapace width, total weight and 21 observed condition were recorded for each collected individual. 22 Table H-2 Estimates of Collection Efficiency Based on Temporal Averages, Regressions 23 as a Function of Temperature, and Specific Screens Ristroph Screen Year IP2 Conventional Screen IP3 Conventional Screen Version 1 1975-1978 29 percent 71 to 73 percent None installed Jan.-April = 48 percent Jan.-April = 83 percent 1979-1980 May-Oct. = 26 percent May-Oct. = 66 percent None installed Nov.-Dec. = 48 percent Nov.-Dec. = 83 percent 1981 E2 = -0.00945 T + 0.54708 E3 = -0.00792 T + 0.71640 None installed 1982-1985 E2 = -0.00871 T + 0.51858 E3 = -0.00792 T + 0.71640 None installed 24 I NUREG-1437, Supplement 38 H-4 December 2010 OAGI0001367E 00496
Appendix H 1 Table H-2 (continued) IP2 Conventional Ristroph Screen Year IP3 Conventional Screen 1 Screen Version Jan.-Mar. = 70.8 percent Apr.-June = E2 or E3 E2 = -0.00871 T + 1986 E3 = -0.00792 T + 0.71640 July-Aug. = 18.7 percent 0.51858 Sept. = 29.6 percent Oct.-Dec. = E2 or E3 Jan.-Mar. = 74.4 percent Apr.-June = E2 or E3 E2 = -0.00871 T + 1987-1990 E3= -0.00792 T + 0.71640 July-Aug. = 18.7 percent 0.51858 Sept. = 29.6 percent Oct.-Dec. = E2 or E3 Number of Ristroph Screens at IP2. In 1986, a Ristroph Screen E2 - Collection Efficiency at IP2. was installed on Intake Bay 26. E3 = Collection Efficiency at IP3. T = Temperature in degrees C. Sources: Con Edison 1980, Con Edison 1984, Con Edison and NYPA 1986, Con Edison and NYPA 1987, Con Edison and NYPA 1988, Con Edison and NYPA 1991. 2 Table H-3 Number of Days Allocated to Each Quarter Based on the Stratified Random 3 Sampling Design Allocation to IP2 Allocation to IP3 Total Stratum Dates in 1981; 1982-84; in 1981; 1982-84; Days 1985-89; and 1990 1985-89; and 1990 Winter Jan. l-Mar. 31 90 N/Aa ; 30; 23; 23 N/A; 27; 35; 35 Spring Apr. l-June 30 91 N/A; 10; 8; 8 N/A; 18; 20; 20 Summer July l-Sept. 30 92 11; 11; 11; 11 31; 31; 31; 31 Fall Oct. l-Dec. 31 92 59; 59; 68; 13 34; 34; 24; 0 4 a N/A = Not Applicable, the reduced sampling began July 1, 1981 (Con Edison 1984). 5 Sources: Con Edison 1984, Con Edison and NYPA 1986, Con Edison and NYPA 1987, Con Edison and NYPA 1988, 6 Con Edison and NYPA 1991. 7 For all impingement studies, fish were sorted and counted completely if either the identified 8 species was white perch, striped bass, or tomcod, or the total number collected for a given 9 species was less than 100 individuals (with heads). All other sorted samples were enumerated 10 by subsampling and weighing to four general length classes. This information was used to 11 determine the total sample size. To estimate the number of fish impinged, the estimated daily 12 counts (taken before July 1981) were multiplied by the collection efficiency adjustment factor 13 (Con Edison 1984). During the period of stratified random sampling (July 1981-1990)' the December 2010 H-5 NUREG-1437, Supplement 38 I OAGI0001367E 00497
Appendix H 1 mean of the estimated number of fish counted within a stratum was multiplied by the collection 2 efficiency adjustment factor and the number of days of plant operation (Con Edison 1984). 3 H.1.1.2. Historic Assessment of Impingement Impacts 4 As discussed in the previous section, numerous studies have been conducted to evaluate the 5 effects of impingement associated with the Indian Point cooling systems. Studies have also 6 been conducted to evaluate the trends of fish populations in the Hudson River. Entergy Nuclear 7 Operations, Inc. (Entergy, or the applicant) and NYSDEC have used the results of these studies 8 to evaluate the potential for adverse effects associated with the operation of the Indian Point 9 cooling systems. The results of these assessments are described below. Nongovernmental 10 groups and members of the public have also evaluated publicly available information and data 11 associated with the Hudson River and have expressed the opinion that many species of fish in 12 the river are in decline and that the entrainment of juvenile and adult fish at Indian Point is 13 contributing to the decline, destabilization, and ultimate loss of these important aquatic 14 resources. 15 Applicant Assessment 16 In the draft environmental impact statement (DEIS) (CHGEC 1999) and environmental report 17 (ER) for license renewal (Entergy 2007), the applicant acknowledged that some impinged fish 18 survive and others die. Mortality can be immediate or occur at a later time (latent or long-term 19 mortality), and mortality rates depend on the species, the size of the fish, the water's 20 temperature and salinity, the design of the screens, the water velocity through the screen, the 21 length of time the fish was impinged, and the design and operation of the fish return system. 22 Impingement effects were examined by evaluating conditional mortality rates (CMRs) and 23 trends associated with population abundance for eight selected taxa representing 90 percent of 24 those fish species collected from screens at IP2 and IP3, including striped bass, white perch, 25 Atlantic tomcod, American shad, bay anchovy, alewife, blueback herring, and spottail shiner. 26 Estimates of the CMR, defined as the fractional reduction in the river population abundance of 27 the vulnerable age group caused by one source of mortality only, were assumed to be the same 28 as or lower than that which occurred in past years, caused by the installation of Ristroph 29 screens and fish return systems at IP2 and IP3. For species exhibiting low impingement 30 mortality (e.g., striped bass, white perch, and Atlantic tomcod), future impingement effects were 31 expected to be substantially lower than they were before the installation and use of the present 32 protective measures. 33 Central Hudson Gas and Electric Corporation (CHGEC) (1999) concluded that the maximum 34 expected total impingement CMR was 0.004 for white perch and less for all other taxa. The ER 35 (Entergy 2007) stated that the results of in-river population studies performed from 1974 to 1997 36 had not shown any negative trend in overall aquatic river species populations attributable to 37 plant operations: 38 I NUREG-1437, Supplement 38 H-6 December 2010 OAGI0001367E 00498}}