ML12340A748

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Official Exhibit - NYS000441-00-BD01 - E-mail String; Subject; Action: Request Parallel Concurrence on Document: Agency Long-Term Research Activities for Fiscal Year 2013.
ML12340A748
Person / Time
Site: Indian Point  Entergy icon.png
Issue date: 01/19/2011
From: Ader C
Office of New Reactors
To: Mary Johnson
NRC/EDO
SECY RAS
References
RAS 23554, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01
Download: ML12340A748 (12)
v • d • e


Text

United States Nuclear Regulatory Commission Official Hearing Exhibit Entergy Nuclear Operations, Inc.

In the Matter of:

(Indian Point Nuclear Generating Units 2 and 3) c,.\..t.P-R REGU'-tr ASLBP #: 07-858-03-LR-BD01 NYS000441 l~"

Docket #: 05000247 l 05000286 Submitted: October 1, 2012 Exhibit #: NYS000441-00-BD01 Identified: 10/15/2012

~

0

~

~ Admitted: 10/15/2012 Withdrawn:

~ ~ ~

....~.., ~& Rejected: Stricken:

        • '" Other:

Clark, Theresa From: Ader, Charles ./ ~ 0 Sent: Wednesday, January 19, 2011 8:42 AM To: Johnson, Michael Cc: Dube, Donald; Chokshi, Nilesh; Flanders, Scott; Holahan, Gary; Clark, Theresa; Lombard, Mark; Bergman, Thomas

Subject:

FW: ACTION: YT-2011-0003: Request Parallel concurrence on document: "Agency Long-Term Research P.,ctivities for Fiscal Year 2013" Attachments: ADAMS DocumentAPK Importance: High Mike, i n::commend concurring on trie subject paper with the following COITlrnen[s:

1) Memorandum page 4 under "Assessing Climate Variability Contribution to Risk at Nuciear Facilities" -

Need to clarify or delete .comment on SO.ARCA under the ciiniate variability proJect. While it is true that SOA,RCA. found external events risk to perhaps dominate total risk. this was mainly from seismic. This is unrelated to climate variability

2) Same section - to clarify that the se',tenc::e is intended to refer to events such as flooding and not all external events (eg., seismic) modify the sentence that reads "The treatment of external events in PRA and risk-informed decisions is currently much less mature than the treatment of internal events although the risk from external events may dominate total facility risk."

to read as "The treatment of these external events in PRA and risk-informed decisions is currently much less mature than the treatment of internal events although the risk from external events may dominate total facility risk."

'2,,) E.nclosure 2 pagE: .5 uf':der Issues of Lr~ie 'Thoriun'"'t C*ycie'! -- Th~:: last sentence refers to fuel rnanufacturinQ is:sues WilhSrlouicin t th:s refer to fuel manufacturing issues with Th-232 as the fertiie fuel IS made with T:l**232 not 1j**232. U"232 is a byproduct of the nuclear I"eactions. but is in-situ (unless this sentence is intendeci to discuss processing the spent fuel, which contalils U-233 and U-232. the iatter gi\jin~l way to decay producis that are hard gamma emitters, complicating the shielding requirements).

From: Correa, Yessie Sent: Monday, January 10, 2011 11:31 N~

To: Penny, f\1elissa Cc: Clark, Theresa; Lombard, Mark; Coates, Anissa; Berry, Lee

Subject:

AmON: YT-20U**0003: Request Parallel concurrence on document: "Agency Long-Term Research Activities for Fiscal Year 2013" Importance: High ACTIOI'J:

YT-2011-0003: Request Paralle! concurrencs on document: If Agency LOr1g- Term Research Activities for Fiscal Year 2013" Assigned To: C. Ader, DSRA Due Date: 01/20/2011 by noon Ins'!.: Requesting review and comrnent/concUJ'l'ence.

SeeM. Johnson's e-mail below : P'2r his C'Jf)C:UfTence

Thanks,

~R~ _~~~.~~_~P'~,~9_~~<:~,I:~?1i1 .....

From: Johnson, Michael Sent: Monday, January 10, 2011 11:20 AM To: Correa, Yessie; Berry, Lee Cc: Holahan, Gary; Williams, Donna

Subject:

FW: Action: Request Parallel concurrence on document: "Agency Long-Term Research Activities for Fiscal Year 2013" Please ticket. DSRA lead. My concurrence .

From: Bano, Mahmooda Sent: Monday, January 10, 201111:16 AM To: Lui, Christiana; Case, Michael; RidsOgcMailCenter Resource; RidsNrrOd Resource; RidsNmssOd Resource; RidsFsmeOd Resource; RidsNroOd Resource; RidsOcfoMailCenter Resource; RidsNsirOd Resource; Turk, Sherwin; Leeds, Eric; Miller, Charles; Johnson, Michael; Mitchell, Reggie ; Wiggins, Jim Cc: Ghosh, Tina;' Santiago, Patricia; Bano, Mahmooda; Wach, Lisa; Greenwood, Carol

Subject:

Action: Req'uest Parallel concurrence on document: "Agency Long-Term Research Activities for Fiscal Year 2013"

All, th Please review and comment / concurrence requested by January 20 , 2011 by noon:

"Agency Long-Term Research Activities for Fiscal Year 2013" Thank you ADAMS Package: ML110100020 Policy Issues: ML110100018 : MLll0100029 : MLll0100032

2

Clark, Theresa From: Ader, Charles Sent: Thursday, January 20, 20-11 10:00 AM To: Bano, Mahmooda Cc: Ghosh, Tina: Santiago Patricia; Clark, Theresa; RidsNroMailCenter Resource; Johnson, Michael Chokshi, Nilesh: Bergman, Thomas Flanders, Scott: Gibson, Kathy; Dube, Donald

Subject:

RE NRO concurrence on FY13 long-term res SECY (YT-2011-0003)

Mahmooda, Mike Johnson concurs on the SECY "A.gency Long-Term Research Activities for Fiscal Year 2013" (ML110100020, YT-2011-0003), subject to the following comments:
1) Memorandum page 3 under "Evaluating Service Life of Nuclear Power Plant Concrete Structures" -

Consider discussing the relationship with the FY11 long-term research topic (Enclosure 2, page 4) on nondestructive evaluation and surveillance of civil structures,

2) Memorandum page 4 under "Assessing Climate Variability Contribution to Risk at Nuclear Facilities" -

Need to clarify or delete comment on SOARCA under t~e climate variability project. While it is true that SOARCA found external events risk to perhaps dominate total risk, this was mainly from seismic, This is unrelated to climate variability,

3) Same section - to clarify that the sentence is intended to refer to events such as flooding and not all external events (e,g" seismic) modify the sentence that reads:

"The treatment of external events in PRA and risk-informed decisions is currently much less mature than the treatment of internal events although the risk from external events may dominate total facility risk,"

to read as:

"The treatment of these external events in PRA and risk-informed decisions is currently much less mature than the treatment of internal events although the risk from external events may dominate total facility risk,"

4) Enclosure 2 page 5 under "Safety and Regulatory Issues of the Thorium Cycle" - The last sentence refers to fuel manufacturing issues with U-232 Shouldn't thiS refer to fuel manufacturing issues with Th-232 as the fertile fuel is made with Th-232, not U-232? U-232 is a byproduct of the nuclear reactions, but is in-situ (unless this sentence is intended to discuss processing the spent fuel, which contains U-233 and U-232, the latter giving way to decay products that are hard gamma emitters, complicating the shielding requirements),

This completes action on NRO YT-2011-0003

NRO Suggestions for FY13 Long-Term Research Plan Background and GuJdance .(moreinfo atthe RES SharePoint site);

.. The LT Research Projects Review Comrni ttee will prioritize all submissions that are within the scope oftheRES mission and will report to the RES Office Director who will determine whether each will be funded, based on

.. priority and availability of funds. This process.wiH be completed by December 2010, startingwith the submittal ofNRO's consolidated suggestions by October 30.

r. Fill out eachrowwith as much information as possible to support the committee's review. Use thelasUive rows to indicatehowthefollbwing prioritization factors apply to the. topic: ' . .... i .' . .;

<) .. LeveragesresourceswhilemaintainingNRCs independence and suppoJ;tinglhe neededschedLilefor iss~e resolutibn.(weightl0%) . . .

o .A.dvancesthestat'e~of-the-artin asubjectarea with significant Llilcertainties and significanUisk or safety implications (weight 30%) . ' ' . .'

o Provides an independent tooLorinformation that is neededJor fUture regulatory decisionmaking(weight

~~ . .

<] Improves more than one program area or the integration between multiple program areas (weight 20%)

o Addresses gaps created by technology advancements that may be ell1ploYi?d by licensees or applicants (weight30%)

!Title jLicensing Support for Liq~id Metal Fast Reactor - i

'-IB-r-ie~f-s-u-m-m-a-rY-':-of-N--'e-e-d-' --[.--.-.- _ .. -......-.-.---..-.-.--..--.. _.-.. --.-.-.. -....._-.-.----****-.-.------.-.-....---*.-.-.--.-..---.-----..-1 IContact'Name f-I---.---~-------+.

Iwill.~~~.~~~ckl~x_... _.__... _. _____.._______ . ___ ._:==-_=----------1 ...-.... - ..-.-... ---._--.- ... _--.-j ICostEstimate IS7S0,OOO FTE Estimate' 11.0 f----::-'---~-'-------+---------------

Description of Work ITofuliY assess NI\C capabiiities and g<lpS in our ability to ev,lluate <lnd liCf"nse iiqUid metal fast reactors. /\Ithough some !ow-Ieve! work has been undert<Jken in l recent yeclrs (e,g., knowledge rnanag(-'Illl'nt, ml1tal fuel qualification assessment),

la more det;iled study is needed to assess previoLJs activities (Clinch River, PRISM, SAFR) c1l1d b.'gin I'esearch activities to addrf:ss Significant gaps in If::chnical and  ;

i regulatoryal*eas. This activity would SlJpport initial efforts th"t would then form I Ithe basis fOI* a lonw:r term program to support the licensing or f(lst reactors. I f-P-r-i o-r-it-iz-a-t-io-n-.-:-L-e-v-e-r-a-gi-n-g~--+-IN-a--ti ~~~I'~'b-~~<l~'~;~i; 5 C 1;-1:~~'ti~-r~;~-~i'~~~li~~'~';s ea ;~h;;~dli~;~*;~i*I~*i;~*~; 0 ;;f~;;-~';~1 Factors. Resources 'Inuclear piants, integrated pressul-ized water reactors, high*temperature gas- I

'cooled reactol's and other activities. These recent and ongoing efforts provide a I I

,logical basis for the addirion of activities for f;,st f'eactor technologies. J f-A-d-v-a-n-c-jn-g-S-t-a-t-e-1I-s'o-m-e-o-ft-h-;~f' <1~~~it*ies ~~~'ldl~'i~;;~-ad~ance-th~:~<;tat~"~fth';art ~-;-;visiol;;;f I oftheArt' lexistin g tools and development ot new tools are needed for a ditferent I

. . !technology. .

Independent. 1,'The initial efforts would ultimately lead TO the adoption or development of Decisionmaklng linde pendE'llt dL~cision-lllaking tools for applications related to fast reactors Tool  !

Multi-Program iThe fCist l'eCicto:' tl'chnologies ~i'r:: likl-:iy to be part of rfluiti-progralll activities Improvement !reiated to both reactor licensing and cllilflges to tht..; nuclear fuel cycle. These iactlvltlfCS will need to be COOI'drn,lted with NMSS activltl.c5 rl~latedlo wJste, I(Pcycling, ;iIld fuel cycle facilities.

I Addressing GapsITh!~ ~latU(t.- of this ,~cUvllV is to Idpntrh/ and begin resoiution of grJps in tE1chnicai

' -_ _ _ _.....L_ _ _ _ _ _ _ l~!*id n*;gU!':itorv drea::: ~*P!d~~~_~_~~_~~~_~~~!ng [~'ld oVt:~r~Jjght (Jf ~~:_st rf::a(t()r'~

[Title __~_.______~____~__l~'IJ!:,,\f\I__~~l£,r?ved ~~EL~{]~A-ccident Consequen ce Code System (MACeS) iBrief Summary ofl\!eed i and econo('nic Iicon~)eClucnc(:-:'

.. .  :~ C); -:':, !'.~VL'rc  :';Llcll d'~ Sev(::f"e /\ccicient

! r\t1anat~enlE'r;t ,u,lt7~rndtivf: (SAiVl,Aj or- Sever-e i'.:...ccident rvlan2genlent Design iAlterniltlve (SAM[)I\) anaiyses submitted as part of corn b!ll ed operating license j;jpplications and stand;:3rd (eactor design certjfication applications. For instance, lappiicarits often begin with input values that are found in "Sanlple Problem A" Itllat IS distributed with the MACCS2 code (~JUREG/CH-6613). The valur~s. in Sam pie IProblem A were taken from a calculation for Surry done for ~~UREG-1150, which was published in 199(), The pedigree of some of those input values is not known,

!contact Name

! . . -c-r---. Lee (NRO/DSFR)

Jay--.-.. -..--... .. ._. .________.-,..__. _____ n . _ _ ** _ *

  • _ . _ . _ _ _ ._~ _ _ *
  • _ * ** _ _ _ _ _ _ _
  • _ _ _ _ _ _ _ _ *1i

!CostEstimate .... . . ... .... II-S_l_5_0_K_ _ _ _ _ _ _ _ _~_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _"""""[

IFTHsti;,-;te------------: ?~~_~C_~[.. _. __ . ._ ._..... _____ ._._.____._._______ n_. _ _ _ _ _ _ _ _._ _ _ .. __ . _ _ ._._.. _ .** _ .* _

iDescription of Work il) KeV:t<vV dry! Upcl,lk or upg!*Clc!E; CiS nect<ss;JI*Y, certain input vCliues often u,;(C,d in the !ViJ\CCS;~ for off-site radiojogicai and econornicconsequences of severe i:iccidents.

)) ~Jon;lte-sppcifIC par*<Jmeters believed, by a group of experts from the US and trw CcnHrW,SllHl or I:uropean Communities ieEC), to be Important to or i: fer dptt0 r rn i ning off-site consequences 'Nere subjected to an expert i I

eliCitation I,:luring the late 19905, Sandia j\latronal Laboratories (SNL) prepared I I

j' 0 1 valCiC~ ,.md dt:grces of beiief and <;ssociateci correlation coefficients for all of Ule non sitf:-specjfic parJr'fH?ters. This info(filation should be incOI'pOl'c.ltcd into tlw improved new code (Hef. 3).

in anticipation of tile Comrnission ;;!PPI*ova! in near* futul*e fo, use of the irnproved input pal*ameters used If1 the development of State*of-the Art Reactor* Consequence Anaivses (SOAf\CA), incorporate these new par*an1eter*s i into the in)proveci new code

14) Compiete and incorporilte new improved economic mode! being developed i by Si\JL as dn alternative to the c~rrent rnode! in MACCS2 (See SRMs dated Septf::nlber 10: 200S and June 23} 2009). The n(~\jI} rr-:odel \,vill b!~ b21sed on an f'xi,;trng coeie, "Rcogionai Economic Accounting (REAcet)" which uses an input/output model to calculilte loss of gross dornesticproduct (C;IJP) due to economic disruptions caused by natural and/or manrnade disasters. The main

! Issue rc'rnair1l!ig to be resoived is extending the rTwdei to longer-term Impacts I

I, i 011 the economy HElt could potentially rc';u!t from a I*eactor- aCCident (See i : COCO-) model), If appropriate.

I . 'l.f3gf~~!.E'DC:?_: N,E. Bixlcr,et ai.., "E.v'Jluatlon of Distribution Representing Import,mt i INoilnSite-Specific Parameters in Off-Site Consequence Analyses," Dr*aft NURECjjC:R*j

~ ' i x x x x , S,I\ND2010XXXX, i

. - - - _ .-.-.---.-----_n*_*'-**r------*** n . -*** - ***** - - - . -****** - *** _ _ ** _ .*

  • _ - - - - ----_._-_._---_._---_._---_._-----------_._---

IPrioritization ILeveraging i I iFa eto rs In~_:':.'? u ~_~..____ J _. _______ . . ._ ._.___._._._.______._ . _n_______ .___________.. ____ .__.___.__:

IAdvancihgState! .

lof the Art i r;:=1------===~==------=~=~-=~------..-J IMulti"Program I

i I

II Ilmprovement I.

, - .-.-----.----...-..--.,-.-._.-.. - .. -,.------_. -. ...- ..-... -.- .-.. -..-.----. -..-'----..-.-..---..----_o._------

I

[Addressing Gapsl .

1i

NRO Suggestions for FY13 Long-Term Research Plan Background and Guidance (more info.a.ttheRES Share Point site):

o Th~ LTResearchProjects Review Committee will prioritize all submissions that are within the scqpe btthe RES' mission and wilrreport to the RES Office Director who will determine whether each will be funded, based on prioritYcandavaiiabilityofJunds. This process will be completed by December 2010, startingwith the submittal

. of NRO's consolidated kuggestions by.O(tober30.. ' . '. .. ..' - .' .' .

o Fill ouf:eacli"row;witn:as:muchiiiformatioRas possibletosupportthe committee's review . .Usethe.lastfive -'

rows:toindicat~h'owt~eTol,-00ingprioritizationfactorsappIyto the topic: . .'. . .....

<9 .. Lever.ages resourcesv,Jhile:maihtaiiiingNRC'S independenceandsupportihgthe neededs'chedl:Jlefor issue

. resoIUticin;(w@ighflO%). "

o Advancesth:e'state-of-thecartih asubject area with significant lrncertaihties and significantriskor safety implications (weight 30%) .

o Provides an independenttool or information that is needed fO!" futureregu latory decisionmaking(weight 10%)

o Improves more than one program area or the integration between multiple program areas (weight 20%)

o Addresses gaps created by technologyadvantements that Illay be employed by licensees or appliCants

. (weight 30%)

iTitle- . !Hvperion Power Module BriefSuminarv. of Need I

.--------------------------~----1 Contact Name. Neil Ray (NRO/OE) I i

Cost Estimate $100000 i

..------------ -*--.. ---*--------*--------*----**---------*-1 IFTE. Estimate . . 10 I .J.- i

. I -

Description*of-Work IFoliow developments in neutronics and materiel Is behcwior. Materials proposed for power module and its intel-action with thc' coolant le"d-bismuth (-'u:ectlc. (L8E) i Also, proposed fuel IS Uranium NItride may require further- collection aT cJelIa while I I

Istudving fuel cracking. i I-'------,--'-r----'-~--'-'---'___'_l-~-.....::=--------.---..:.:--------------------.--------. _____________________J Priodtizati on . Lev~raging - A compact, low-power reactor concept is being studies at Los Alamos National FactorS Reso'urces', laboratory. HVPNlon corporation is formed and thel-e is private investment I

"through ventUie capital and strategic pal-tnerships formed AdvancingStat,e I of the'Artl 1 - - - - - - - + '---------------.----------------- -----

Independent i Decisionmaking I f-T_o_ol_ _ _--i_____ ._____._______________.-------------.--._____________ .__________________~!

Multi-Program I I Improvement I Addr.esSing-Gaps----*---------------------------*-------------1 I

ITitle . ~Accident Source Terms for Sodium-cooled Fast Reactors (SFRs) I iBrief Summary of Need ITh2 De-~~"~r~~*~:~it-~f~-;;r~y c-;;~tinu~~-*to press for- ciosing the nuci;;r~~;;Clf,.-l i iThe strateg,( they have devised for this includes sodium-cooled fast reactors for I

! Iremovint; ",Cliniac'; from Spf:!lt fuel from water 1*f.'Clctors. It is anticip,lled in the 1

, lcoming years that DOE INllt begin seriously detailed design studies of a sodium-  !

Icooied actinide burner wiHl the intention of submitting the design for certification I bY ,~JR(*' ...... IR,=Jpr*,"r-ce

\. ". I ", c-:-, I I !p -'Old'l+ion

~ ~i J' "I W " l,  :, "'e'e II I . . d -rp,. .se'Jer-ol'

~ ~.. S':Rc

~ r. ,J - g pLII*sued

'01"'111- . ~... by I 1

Idifferent reactor vendors (e.g., Toshiba 4S, GEH PRISM) and NRC is expecting i IdeSign certification .:lpplicc;tton submittals in 2G13.(R.eference 2) I

.I I

'-t~-.o-n-ta-c-t"'-N-a-m-*""e-~-----lI-Jc-1Y' Lee (r~-RC;/DSER)-*---------* I

[Cost Estimate 1$2801< I c--~_-T-E~_E~s-t_i-m~~-_t-e~-_~~~~-~--:-_-. __---+I-;oFrE--.-.-------..-.---.-----. . - I

!Description of Work 1.1\ part of this cerliriGH!on effort wili require that NRO have an understanding of I I the posslb!e re!cils25 of rcldionuclides from the sodium in the event of accident I i

either within or be,!orld the design basis. NRC) will need independent capabilitie c. iI to <155(,';', the CD:l5equenccs of cicciderltal rciedses of 1'C1dionuciides to the I I

cOtlt;lill!llE~nt Of CDtlfillcmf;'tlt :illd le;Jkage ot radioiluclides into the enviroilment.  !

ThiS capability will be very much different tilan that now available for light water reactors. There is an opportunity to lever*age resources on the investigation of the source term for SFRs. OECD and IRSN in France have augmented their efforts in this particular ell*ea. Sp(:'dfic activities that should be undertaken:

A.ssemble data base on known information concerning the release of radionuc!ides from liauid sodiull1 Assemble data IJ(3se of ';odium aerosol behavior Develc!) d thcrrnuc;,etT'icdl model of radiol1L1c!lde release from sodium to s,(stenFHi1e tnf above data base. ;jllov" extrapolation of the data base, anej idp.fltJfv dr2r3S of crucial iilissjng data OUcintitzi,!vciy ,'Vd!U,J[C til£' ImpOl"ti1nce of these phenomena and the need for ~1clditJorJdl experin"ientaJ research identify <idditiona! phenomc"na that are high importance andhave a high II need tor additional experimental research Reference 1.; D. A. Powers, et JI., "Advanced Sodium Fast Reactor Accident Source L--.-:

. Terms: Research Neecis," Sand Repon, SAND2010-5506, September 2010.

Reference ): (Sensitive NRC Internal Information) "Advanced Reactor Program Plan," Hevision 1. ,\ugust 2010, Advanced Reactor Program/NRO/NRC

!Prioritization ILeveraging.

!Factors . lResources i I *IAdva~~h,~. stat;l---------------------------1!11 i of the Art .! .

' j-***-*-**--*-*. *_-*--*-*-*'c--i- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ' - - - - 1 Iindependent i

'I' Decisionmaking !

,Tool i I . ~--.-----------------.--

!Multj.*Program I

' Improvement ,

i. ........ -. ..... .. -. .1-----.---..--------- . I I ____... ___________

L._._. . Addr.essing ._..._ .... _..*.__Gapsi

. "'. :  !. "~. ' I .

New Improved MELCOR Accident Consequence Code System (MACCS)

IBriefSummary of Need .: IThere is a need to review, and upda tE or upgrade as necessa ry , certain input I Iva luE-'s often us('d in thl" MACCS2 for off-site I'o,diolo gical and econO llllC

' Iconsequences of severe (jccidfnt~, . such as rfport ed in Severe Accident iManag ernent 1~ltE:rn ativl' (S/\M/\\ 01' Severe I\ccid ent MiJI:,vgem('nt Design IA lterna tive (SAMDA) i'lni:1lyse s subnlltled as piHt of combined operating license i

!appl1cations ,,3nd .standelrd reactor deSign certificcltion afjpi:.~.,)lions. For in ')lan~,E', i apP llcants o rten oeg ln With InpUl values t h at are foun d In ':)ampie Problem A  :

l

. that is distributed with the MACCS? cod e (NLJ REG /CH-661.3). The va lues in Samp le I IIPrObiem A wel'e taken from a calculation for Su r ry done for NUREG-1150, which I

' ' ~

" . , <, was published Ir1 1990, The pedigree of some of those In put values IS not known .

[contactJ\Jame'dIJay Lee ( N R O / D S E R ) ' I CostEstimate '. 1$1501<

1------'-"'--------' - -- - - - -- - - - - - - ----------.---------- ---.- - - - - . - - i FTE Estimate . . 0.5 FTE Description of Work 1.) Review, and update or lIPgrClde as necessal'Y. certain input values often used in the MI\CCS2 for off-site radiological Clnd l'conomic consequences of severe accidents.

2) Non site.-specific par(lfl"1;:>tE:I') bl?lil?ved, by a group of (~xperts from the US and the Comm iss ion oj Europ ean CGlTlmunities (CEC)' to bt: important to or sig nific ant for dete!"l11 ining off*s;te consequences W(e l'P subjected to an expert elicit ation dU l'ing tl1(' late 1990s, Somdia National Labol'3torlE'S (SNL) prepared ranges of valu es and degrees of belief and associated corr'elat ion coeffic ients for all of the non sit~~ - sp(~cific piHarnet,?rs, Th is info l'm,ltio n should be incorporated int o the improved Ilew code (Rei. 3j.

I.,)

I;) In antiCipJtlon of the Commission approv<J1 fn near futu r e fOI- use of the II improved input parameters Lis? d in the development of State-of-the Art i Reactor Consequ(?nce Analyses (SOARC;\), incorporate these new parameters i in to the im proved n ew code It1) Comp lete and incorporate new improved economic model being developed by SNL as om alternative to the cCJr r (~n t model in MACCS2 (See SRMs dated

" Septembel' 1.0, 2008 and June 2.3, :!009), The new model will be based on an existing code, "Regio nal Economic Accountin g (REAcct)" which uses an input/output m ode! to ca lculate loss of gros s domestic product (GDP) due to economic disruptions G1L1sed by natural and/O!" m<Jnll1ade disasters, The main issue remaining to be resoived is extending the moael to longer-term impacts ,

on the economy t ha t couid potentiaily lesliit from a reacter accident (See I COCO*2 model), if appropriatE' r Referencp.: N .t . 8ixlH , f *T .11 ., "['i,iICiritiC!1 ()f Oi strib ution Rep resPllting important II

!Non.Site -Specific f'ar,Jrrll;\ er ';, ii' Off Site Consequence (,/1,JIYSCS, " !)r,ift NUREG/CR-I jxxxx, SAND201OXXXX. I Prioritization Leveraging  !

I Factors Resources I I

Advancing State.

I of the Art i

IndepelJdent DeCision Tool Multi ~Program.

Improvement

'--_ _ _ _-'-A_d_d_r_e_s_si_n_g_G _ a_p_s....:I__ .. _..________ _ _.__ ._.. ___._._.____ ._ __ ._.____ .___ . __ _ .. _._____ .____.:... _____ J

iTitle I General Site Suitability Criteria for Small Modular Reactors (SMRs)

I .----------.. - - - - - - - - -.. -----.---.-----------.--------.--.--------.--.-----.. -

I -

IBrief Summary of Need jThe cUr'rent gUide, Hegu!alorv Guide .:1,)', IIC:eneral Site Suitability Criteria for Nuclear

!Powel Stat.iotls/' discusses tnt: !llajDt site C[l3racteristics rel3ted to public health and safety I land environrnental issues that tt~!e  !\J!~C staff considers In deterrnininB the suitabilitv of sites II op L'VI'c

!'t IC"'I la- rD'- V >.J. n'e 3,-1'\'--,."*,,,,-,

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':1 rflod'Jlor l (..1 :n'"or-I II L'-t:l (1 P"'R-I/V \3, hloh'

  • tJ I !ternperallire Bas-cooled reactors, soc:iurn-cooled fast reactors, and 311 othe' designs 01 itechnoiogies f:,l;xcept for' iarge 1.\JVRs (gr(:2te:" th8n 700 MvVe), The SfV1R designs are and reactor configuration. Tileretore, there is a II 'rer.llarkabIY. tJlffer'!:,nt in size (power!evels)

. Ileed to develop new regulatory gUidance for the NRC staff to cOllsider in determining the I l

!suitabilitv of :)jtes fc: the StvIR::.,

I------'- . -,.---------....-----.---------------------------.------~

I ICO nta c tNa

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l"'ll i ICo-;E~~----- +1-s-~-~_-~_-K-_-__-_- __-_-_-_-__-_-_- __-_-_-~~------------------------1 IHE Estimate. :10 FIt' -

1 I'D~~~ip~*i~~-~fW~;k '1 Develop new regulat.ol,Y POSltiOilS (1;l,'he population ciensity; e.~clusion boundary 2r1d low i pOIJul"tlon ;:one: POiJuldtlon celiter olstdnce; use of the site environs Hlclucilng proximity to I Iman-marle tla::arOs, and OlWclC21 Cil21,-Ct,~rISt,CS of the Site, Inclucilng seismology, 11... _ _ ... __ ~

!!11etco;"ljlo;sY, geology, ~nc :ly!-jrnlc,y

~ "_.~ __ ~~~. _~

Irl_detp t n11tllllg the dcceptalJlilty of a SITe fcy tl ~1v'1R

_ _ ._. _ _ _ _ _ _ _ _ ~____ _ ** _ _ _ _ _ ~_J I

!rrioritization.\Leveraging I iI Factors Resources 'I I~__ ---_-----'-'--f--- .. __. ____ ... _ ....._. __.____ .. __.. _.,

  • ___ . __ . _____ __ ... ____..______ ..._____... _______________ ....._ .__________ ....1 IIAdVancingStatel i t of l~e Ar_~_ _l_.. _______. ___.. __ ..._________. .____________.___._____________ .____._.___________.__~

"llndependerit i I I loecisionmakin g I I 1;~I~i~;-~~;;~'--1 1 Ilmprovement I I' IAdd~;ssjngG~~~~1----------------------------------------------~

'-----~ . '------..-_._._----_._-_._---------------------------~~--------'

,.-------------------..------------------------- --------------- ----.---------------.------ ----------- --I r--T_it_l_e___________+-io_p_e_ra_t_io_n_a_1C_o_n_si_d_e_r_a_ti__o_n_s_o__f Liquid Metal Reactor Designs i I

Brief Summary of Need_ The I_MR designs preSent;3 numlJer operational considerations not currently evaluated by thc' current Sf,Ps, such c:': opcrc;tioll with crlrlchrnenl percentages .

much greater than 59{" which impacts fuel storage requir-ernerns, radiation -.  !

monitoring requirements and ADO i.Jnd aCCident clilalysis source terms_ Some LMR I

[ reactors have experienced coolant contamination thathas resulted ill fuel damagel I(e_g. Fermi 1, Santa Susana Sodium Reactor Experiment), coolant purification (cold; Itr-aps) and other methods of monitoring and ensuring coolant purity are not well I

!documented for use by NRC personnel. Methods for pel'forming In Service I Iinspections <mel related f~CS compon("nts inspections is not available to the staff_ I Contact Name . IRon l.aVera (NRO/DC!PjCHPf3) I Cost Estimate I ----------------------------------------------------------1 HE.Estimate I 1 Description of Work Collect tht' requir-ed indumy, DOt, Del) cHld intei'niltional oper-Jtillg l'xpClwnce  !

1 information, to SUPPOI-t ciP'JPiopnlfnt nt.the appropriate i?Valllation emer!;] and i l m._p_th_o_o_', _--._l_h_t>_n_d_c_'V_t-_'1_o_Pth E:- i' cg u Iell () 'V eu ida n ct'.

I------,,----'---'---+-.

Prioritization IlleVeraging, Factors Resources

!The ClirrenT f

~JRC gUldanc~does ~~~ 'If)P-~;~-; ooere-55 these t'ipes of ,0 rPM ----1 '

i iAdvancing State 1G;;;d-on par~-~~patl;--~~~,-~~~~-~-I-MR- A-RP-C~~;;;Pt~;~~;e~~~~-~~e;.~~~g-;--------i of the Art. lexperlence In these areas are poorly understood and not well communicated. I I

.- .I.n.depende. nt ... [The CUI rent SRP and R(;-;~~an~e do;~- not encomp-;~5-;j~-pse types of opera tions-l DecisICmmaking in LMR. i Tool.. . I r Multi-Program ITiliS guidance will be 30pllcable to all of the LIVlR designs. ,I Improvement I I IAddressingGapS As noted above, tilis type of l~fOrrnatiC.H1 a. r.ld guidance does not appear to be 1 Ie currently available' in til(> COnl !TII"!-cia I C:'r1vironment.  :

I!---T_it-"le_*._ _ _ _ _ _-,-_ _ _-:I_E_Va.luation ofARP Specific Pressu!e Boundary Failu~:~~odes and Precursors ___~I IBrief Summary of Need i r~ nu m ber of the /\dvanc:e f-;eac:tOi- Pr-ojects lise design collfiglil-ations th;ll extend I I 'bl?yond thl? boundaries of current regularorv gUlciance. For instance, one design i envisions rnoving thr:' Clllll'C reactor v 0,,; s,:. I Illclud'rng spent ilO Dan Df the l

[ ,-:,)uti nE' 2.ctl\j!ri!~~. A droppecl bundle i1llaly:;is would possiblY c:xtend I Ii I beyond" single bundk, Clnd in"tedd would involve the entir'e core. Other design

!I

! nj"f'opT=i" , ! . t "_.t

"'~~-'_") I<'\loi'p 'ho........",.11::1..

  • .. ,I steilr]'

... lUI'" fpPH 'w,tpr pipe' ir"ie)'e

,,_ ,,_._J".~,~,_. ...J I,) the_ rc<.:

_~ .~'-csu*p

\.~~t--'le, J f..

I!

boundary, suer; the;[ a fJilUJe In one Of t.hose lines couid result in an ReS primary toi I

Isecondary leak that 1;:11' exceeds the flow ;ate of a single SG tube, utilized in the I i(un-ent anaiysis Other designs are proposing the use of inert gases at high. t pressui'e as. an f\CS cooling medium. How the current Leak Befor-e Break I i11ethodology (such as HCj 1.45) would be extended to these designs should be determined, as weil as how to analyze for non-tradltioni.ll core dcllTli.lge modes I lexperiencecl at similar plants (e.g, carbon moder'ated core fires at Windsca!e and i

. !ChernObYi)'

l~on.!~~!~afl1e:_** ~-.-~=----I;;;[~~V PI';~- (N-R-()jD(:!pi(:-f~!P8*i-----~---*-----------*--------*-*-----1 I

ICost Estimate

'--______________ I

.___L_._. _______.__ ._ ... _..... _..__. __"__.. _. _.._.____ ._ ...._.__ .____ ...._. ____ .__.. ___ .._. ___._________ . __.______ .._-'i IFTHstimate  ! i ID~~C~i-P~i~~Of W~rk [-Collect t~ req~ired !ndust~;-and operating experience information from national i I(DOE and DOD) and intemational sources, to SUppOI'! development of the I I lappropnate analytical methods. Then develop the regulatory guidance . I I

i Prioritization iLeveraging 1*;:;i;-~~d:::~~-;-:~!i-i;~~;;;;i~~l;le <;\;~)~~--cl~;:~b;r-*of~I;;; I\~;P' cie~ign concePts---------1 iFactors iResour~es....---.-:il'r~,c;ud:ngc*~oL[l~e

~----.- -- ... ... -

-~

of thE' ,lon I WR deSigns

_... _- .~, - ---- - ....__ .-.. .. ,.-..,--"...--,.."-..-."-,--~-.~-----.--.--~--------~~~i i iAdvancingState 18C1S0ci on pdrtic!oatioll In scveral/\r\P COriCE'Dt presentation meeting:>, expel'ipllu:, !

iof'the Art

.~-~-------+-

lin these ,Jreas ale: oooriv underc,tood and not well communicated,

....--..... ----~-" . ", ..-.--.. -.".- .. :.... -, .-.. ~-.-~ ... - _....--.. --"-........ -.-----.,-.. -..------------~-.. ------.**---*-~~~*--l

!lndependent ITI;(' current Sf'Y iind fIG [;uiciallce COloS not f:'nCOmpdSS these types ot failure I 1

I i

i Decision making modes.

I i

ITool ______._!...: __ .__ ._____ . __.___ ._._.___ .*__.._._.___________________________

~. ~ ________________ J  !

. . llMulti-program lAS noted, Int.)rmatlon developed In support of the l WR ARP deSigns, may be I r Improvement iappilcdble to c[her deSign centers, sLich <:" HTGR. ]

'1IAddressi~;-Ga~<;l;s~t-;d ab~~;~~h~~-;~e ot~i~rmatlon anci gUidance does not appear to be I,_.__________.. _-- __1- _____________ ._.!Icurrentlv

________ '__ avaJldble ill the commercial envlronnle"lt.

ITitle ' . IEnvironmental Qu~lificat'i;~;' of Internal Reactor Vessel Electrical Components I

~B-r~ie-f.-s-u-m-m~a-ry-."':o":'f-N"':e-e-d~---'+IA-n-u-n-l-b-e-r-o-f-th-e-.-A-O-'v-a-n-c-p Reactor p(oJf?cts are planning on the Lise cf hi~h!

I " - (

!elcctrical cmrent compon cn t~, such as Reactor Coolan t Pum p motors, and COlltl'oi i IRor! Drive Mechanism ', M"gnets, t:1l;1t h;:;ve tradition ally he locateci outside of the I

'!Rrc<)cw r Coolant Sy~.i(Olr; or;: ss u((' boundary Electrlca! fail u re of traditionally

!Iocated components h ad lew (o nsequences, other' th an loss of f{CS flo\;v, or Idropping a conu'O! rod. !n t he !\RP deSigns, fCli!ure of internilily located elec trical components , due either to overheating, or electrica l short ci rcuits couid result in

  • ruptures of containmellt dEvices intended to separate electrical insu lati on and

... metals (coppe r, aluminum or lead) thd t couid bf~ inimica l to the fuel or the Res

' .? / .*

. .. .. ~ . ' pressure boundary. In addition, electrical faults in high current penetrations to

  • the ReS pressure boundary could change the accident frequency for Sma!1 Brea k LOCAs, at the point of th e penetration. Allowable limits and the associated models, methods and assumptions needed to assess and monitor the eKpected

'1' and actual condition :; for these ~:()mponents should be deve loped, and r-----------~__!~.~,~~~ 1

~ I~~~~~~. p~~ ef!r ~.~.IL~~~; . R ~.g~i~~~r~.. ~.u_i~~~~~r:r::~_......_. ____-. __.... ~ .. ______..__ .._ .. ~

Icontact Name IHon LaVer'a (NHO/DUPjCHPG)  :

Ic-c-o-s-t-E-s-ti-m- . a-t-e-----~'---+-  ! ___ .n .~ __ ~ _ _ _ _ _ _....* _u _ _ _ _ _ _ _ _ _:

-F-T-E- , E-6-ti-m~a-t-e- . - - - - - -....+1-* .... *..--*------........ *.. *--.. *--..* .. ............. -.... -..... --.-......... ~ ............... - ........ -.-...... -.......... ---.. -...... --.........-_ .......... ---.......-.;

~--~----------'--~----~+------------- . . . . ------- ~

DescriptionofWorl< rColiect the required indu st ry and operating experienc e in fo rmilt ion, both lNithi!', I

.' .'1the nuclear industry and other high temperature and high pressure industries, to I

  • support development of the ilppropriate analytical methods. Then develop the I

. regulatory guidance. i

~~-~~~~-~~--4-~----~--------

Prioritization Ite~eraging This guidance will be appli ca ble across a number of the ARP !.WR design concept s, i Factors* .... I"~esources . and possibly sOllle of th(' non -LWR designs. J

' -Advancing State IRased on parti~~;;~i;;-;~*i;,-~;~~~~-ARP~on~~t pr~~~nta ti o l;~;;eti~~, e~~;i~~ce I oftne 'Art . in these Jreas eire po'ol!y understood and not well communica ted. I I

Independent * . Hi ev;lua tion s are c~;';~'~~tI;~~~;~;-dby SRP s;ctio-I~ -31 1 ~Ti~~-~~id-;*!~*~~-;;~~~ded-j Decision making in thatSRP section and the re fe renced Industry StilndMd s are insufficient to Tool" support an adequate evaluation ot equipment qualificati on .

Multi~Progr.anr: . As noted, information deveioped in support of the LWR ARP designs, may be rll1prC)VerrH:!nt .> , applicable to other de sign cente rs, such as HTCjl~.

i, .~.

Addr:essingGaps As noted above, based all the ARP presentations, this typ.! of information and guidance does not app ear to be currently aVili!able.

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