ML12275A498
| ML12275A498 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| 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: ML12275A498 (12) | |
Text
NYS000441 Submitted: October 1, 2012 Clark, Theresa From: Ader, Charles (-
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 Activities for Fiscal Year 2013" Attachments: ADAMS Document.APK Importance: High Mike.
I recommend concurring on the subject paper with the foliowing omrnents:
- 1) Memorandum page 4 under "Assessinci Climate Variability Contribution to Risk at Nuclear Facilities" -
Need to clarify or delete commen't (Drn. ORCA under the 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,
- 2) 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."
Enclosure
- 3. 2 page 5 under , .. R' latorv Issues o:' -,e Thorium Cycle" - The last sentence refers to fuel rmnarufacturig i s .. . ', 1hou
.... n t th.ms refer to fuel m anufacturinn issues with Th-232 as the fertile fuel is made with z Tn--32 not U-232. L...2312 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 requ,,rmnents).
From: Correa, Yessie Sent: Monday, January 10, 2011 11:31 AM To: Penny, Melissa Cc: Clark, Theresa; Lombard, Mark; Coates, Anissa; Berry, Lee
Subject:
ACTION: YT-2011-0003: Request Parallel concurrence on document: "Agency Long-Term Research ActiVities for Fiscal Year 2013" Importance: High ACTION:
YT-2011-0003: Request Parallei concurre-erce on document: "Agency Long-Term PResearch Activities for Fiscal Year 2013" Assiqned To: C. Ader, bD5,A bue bate: 01/20/2011 by noon Inst.: Requesting review and commrnerconcut rence.
SeeM, Johnson's e-mail below; Per his concur'rnce
- Thanks,
.z.1. Correspondence Team NRC .............. . .. ..... .......... ............
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" Ple.ase licket. DSRA lead. My concurrence From: Bano, Mahmooda Sent: Monday, January 10, 2011 11:16 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: Request Parallel concurrence on document: "Agency Long-Term Research Activities for Fiscal Year 2013"
- All, Please review and comment / concurrence requested by January 20t' , 2011 by noon:
"Agency Long-Term Research Activities for Fiscal Year 2013" Thank you ADAMS Package: ML110100020 Policy Issues: MLl10100018 : ML110100029 : ML110100032
Clark, Theresa From: Ader, Charles Sent: Thursday, January 20, 2011 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 "Agency 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 the 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 Guidance (more info at the RES SharePoint site);
Q The LT Research Projects Review Committee will prioritize allsubmissions that are within the scope of the RES mission and will report to the RES Office Director who will determine whether each will befunded, based on priority and availability of funds. This process-will' be completed by Defcember 2010, starting with the submittal of NRO's consolidated suggestions by.October 30.
Fill out each row, with as much information as. possible to support the committee's review. Use the last five rows to indicate-how-the follbwing.prioritizatio.nfactors apply to the topic:
o Leverages resources while maintaining NRC's independence and supporting the needed schedule for issue resolution (weight.10%)
o Advances the state-of-the-art in a:subject.area with.significant incertainties and significant: risk or safety implications (weight 30%)
o Provides anindependent tool. or information that is needed.for future regulatory decisionmaking (weight 10%)° c) 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 employed by licensees or applicants (weight 30.%)
ITitle Licensing Support for Liquid Metal Fast Reactor Brief Summaryof Need Contact-Name William Reckley-I SCost.Estimate $.30,000 FTE Estimate 1.0 Description of Work " To fully assess NRC capabilities and gaps in our ability to evaluate and license liquid metal fast reactors. Although some !ow-level work has been undertaken in "recent years (eg., knowledge managernent, metal fuel oualification assessment),
.a more detailed study is needed to assess previous activities (Clinch River, PRISM, SAFR) and begin research activities to address significant gaps in technical and regulatory areas. This activity would ssJpport initial efforts that would then form the basis for a longer term program to support the licensing of fast reactors.
Prioritization Leveraging iNational laboratories currently involved in research and licensing support for new Factors., . Resources nuclear plants, integrated pressurized water reactors, high-temperature gas-
-cooled reactors and other activities. These recent and ongoing efforts provide a
!logical basis for the addition of activities for fast reactor technologies.
Advancing State Some of these, activities would logically advance the state of the art as revision of of the Art !existing tools and development of new tools are needed for a different
-.technology.
Independent. The initial efforts would ultrnately lead To the adoption or development of Decisionmaking independent decision-m,,aking tools for applications related to fast reactors Tool Multi-Program T1he fast reactor technologies are likely to be- part of multi-program activities Improvement related to both reactor licensing and changes to the nuclear fuel cycle. These activities will need to be coordinated with NMSS activities related to waste, ryin Irecycling, and fuel cycleý facilities.
Addressing Gapsi*Ti-, natlre ot this .-ctivit/ is to irdenilfy cand begin resolution of gaps in technical
," ,g,,u to,.ry a re- lated ,to h0,, licensing and oversight of fast reactors.
iTitle New Improved MELCOR Accident Consequence Code System (MACCS)
Brief Summary of Need hr e nian'd to r-view, and udWte or apg .dt, as nece ssar',, certain iniut O wes .... r o -ri, th, MACCS? for off-,ie radielorlcai a ond --crio mic consequunc* ,' ovwe a-cdervLs, ya as epor"d iin Se-wver Acclad't
,Mana510 er1 Alt oA:t natIv- (-AN,) ; Sever e Accident Managerent Design
. rAIrer atiw2 (SAMOA) anaiyses submitted as part of combined operatng hcense apprications and standard reactor design certifIcation applications. For instance,
,applicants oftfre begin wrth input values that are found in "Sample Problem A" ahatis distributed with the MACCS2 code (NUREGiCR-6613). The values in Sample Prob"lem A were taken from a calculation for Surry done for NUREG-1t50, which was published in 1990. The pedigree of some of those input valueS is not known.
Conitact NMie, Jay Lee (NRO/DSFR)
Estimate tCost "- .. OK FTE Estimate i-Description of Work nRevnew and- updase or upgrade as necessary, certain input values often used i ' the MACCS tu'r off-site ra'l*logicai and economirc onsequences or severe IN Non o;ite-serific parameters ,bevrad. by a rnOuLof experts f-om the US and th.e con-.rmnsron of European Comrrunities NCEC), to be important to or uninifnt Or dri no-st Oing consequences were subjected to an expert emit on -iuning the late 1995.s Sandia National Laboratories (SNL) prepared ranges on and degrees of belief and associated correlation coefficients ov'aLis for all M the non site"-pecaiit parnmeters. This information shoud be 1 incorporated intote impe opved new code (Ref. 3).
i hianticipation of the Commission approval in near future for use of the
)i-i ncroved maut paiameters used in the development of Stae-of-the Art
- Reactor Consequence Analyses MSOARCA), incoirporate these new parameters rint the irproved new code
- 14)r umornpete and incorporate new improved economic model being developed by SNL as an alternative to the current model in MACCS2 (See SRMs dated Septemher in,2,t10. aridJune 2, 2009). The new model will be based on an
. xi rrng code, 1regional Economic Accountng (REAcct)" which uses an l input/output model to calculate loss of gross dornesticproduct (GDP) due to economic clisruptions caused by natural and/or manmade disasters. The main i ssue i ernarinig to ne resolved is extending the iodelei to longer-teriii impacts on Me ecoriomy that could potentially result from a reactor accident (See COCO 2 rnodel), if approprate.
SR!e*rcne.o- NE. Bixer. a i., "Evaluation of Distribution Representing importanIt Non*Site-.pecifoc Parameters in Off-Site Consequence Analyses," Draft NUREG/CR-1 S IXXXX, SAND20T0XXXX.
lProritization Leverging Factors Resources Advancihg State of the Art Independent Multi-Program i Improvement jAddressing Gaps!I
NRO Suggestions for FY13 Long-Term Research Plan Background and Guidance (more infoat the RES SharePoint site);
The LT Research. Projects Review Committee will prioritize all submissions that are within the scope 0fthe RES mission and will'report to the RES'.Office Director who will determine whether each will be funded, based on priorityandlavailability-offunds, This process will be completed by December 2010, starting with the submiittal of NRO's consolidated suggestions by October 30.
o Fill outýeach,,roW~with.as:,much-inform ation as possible-to support the commrittee's.review..use the last five!': -
rows.to indicate how the following prioritization factors apply.to the topic:"
c Leverages Iresourceswhilemaintaiiiing NRC's independence and Isupportingthe needed schedule for issue.
resoluti6n (w*ight0%),. ""
o Advances the:state-of-tbe-art in a subject area with significant uincertainties and significant risk or safety implications (weight 30%)
o Providesan, independent tool or information that is needed for future regulatory decisionmaking (weight 10%)
0 Improves more than one program area or the integration between multiple program areas (weight 20%)
0 Addresses gaps created by technology advancements that may be employed by licensees or applicants (weight 30%).'
Title. Hyperion Power Module Brief Summaryof Need.
Contact:
Name 1Neil Ray (NRO/DE) _
Cost'Estimate $ý10000 FTE Estimate 10.5 DescriptionofWork.. Follow developments in neutronics and materials behavior, Materials proposed for powei module and its interaction with the coolant lead-bismuth eutectic (L1E).
Also, proposed fuei is Uranium Nitride may require further collection of data while Istudying fuel crackinF.
A compact, low-power reactor concept is being studies at Los Alamnos National Priodritization; Leveraging&
Factors Resources.* laboratory. Hyperion corporation is formed and there is private investment through venture capital and strategic oartnerships fortmed.
Advancing State of theArt " 1."__
Independent Decisionmaking Tool Multi-Program Improvement. _
Addressing-Gaps
'Title Accident Source Terms for Sodium-cooled Fast Reactors (SFRs)
Brief Summary of Need !The Departrnernt of Energy continues to press for closing the nuclear fuel cycle.
The strategy they have devised for this includes sodiurn-cooled fast reactors for iremoving actinides from _spent fue! from water reactors. It is anticipated in the looming years that DOE wvii begin seriously detailed design studies of a sodium-cooled actinide burner with he"intention of submitting the design for certificaton by NRC (Rer;erence ])I hn addition, there are several SFRs being pursued by different reactor vendors e.g., -oshiba 4S, C ElH PRISM) and NRC is expecting design certificatiorn appicition s'ubmittais in 2013.(Reference 2)
Contact Name Jay Lee (NRO/DSER)
- Cost Estimate S280K iFTE Estimate 1.0 FTE L
iDescription of Work A part of this certification effort wil requite that NRO have an understanding of the possible releases of radionuclrde- 'rom the sodium in the event of accident either withiin or beyond the design basis, NRO will need independent capabilities to assess the consequ *n'ces or arccidental releases of radionuclides to the containment or aontonement and lea-'kage of radionuclides into the environment.
This capability will be verv much differ ent than that now available for light water reactors. There is an opportunity to leverage resources on the investigation of the source term for SFRs. OECD and IRSN in France have augmented their efforts in this particular area. Specific activities that should be undertaken:
Assemble data base on known information concerning the release of radionuc~ides from liquid sodiufm 0 Assemble data oase of sodium aerosol behavior
- Develop a therrruc,heirical model of radionuclide release from sodium to s/sternatire roe above data base, allow extrapolation of the data base, and id-nf' v :rias of Lrlciai missing data
" Q uantitat ivei y va'i.aLe the inmportance of these phenomena and the efor addc'toona! eixpeanrnmentaj research o Identify additional phuhnonmena that are high importance and have a high need for additionai extp erimental research Reference i: D, A. Powers, et ai., "Advanced Sodium Fast Reactor Accident Source Terms: Research Needs," Sand Report, SAND2010-5506, September 2010.
Reference 2: (Sensitive NRC Internal Information) "Advanced Reactor Program Plan," Revision 1. August 2010, Advanced Reactor Program/NRO/NRC lPrioriftization .1Leveraging.
Factors Resources Advancing State of the Art Independent
'Decisionmaking Tool
!Multi-Program Improvement Addressing Gaps.
Tte. ,. New Improved MELCOR Accident Consequence Code System (MACCS)
Brief Su mmaryofNeed, There is a need to review, and update or upgrade as necessary, certain input values often used in the MACCS2 for off-site radiological and economic consequences of severe scients. such as reported in Severe Accident Management Alternative (,S/\NMA*.' or Severe Accident Ma.agemnent Design Alternative (SAMDA) anayvses submitted as part of combined operatinp licen* e apptications and standard reactor design certification arpiications. For instance, applicants often begin with input values that are found in "Sample Problem A"
- that is distributed with the MACCS2 code (NUREG/CR-661,3). The values in Sample Problem A were taken from a calcuiation for Surry done for NUREG-itSO, which was published in 1990. The pedigree of some of those input values is not known.
Contact-,Name. ay Lee (NRO/DSER)
Cost Estimate: . . . i(
FTEcEstimate f W " FTE Description of Work 0) Review, and update or qograce as necessary, certain input values often used in the MACCS2 for off-sire radiologicai and economic consequences of severe accidents.
- 2) onsite,-specific par amters b._ieved', b y a group of experts from the US and the Commission oi European Con]mu nities (CEC), to be important to or significant for determining off-site consequences were subjected to an e pert elicitation during the late 1990s. Sandia National Laboratories (SNL) prepared ranges of values and degrees of belief and associated correlation coefficients for all of the non site-specific p.rarneters. This information should be incorporated into the improved new code (Ref. 3).
In anticipation of the Commission approval in near future for use of the improved input parameters used in the development of State-of-the Art Reactor Consequence Analyses (SOARCA), incorporate these new parameters into the improved new code
- 4) Complete and incorporate new improved economic model being developed by SNL as an alternative to the current model in MACCS2 (See SRMs dated September 1.0, 2008 and June 23, 2009). The new model will be based on an existing code, "Regional Economic Accounting (REAcct)" which uses an input/output model to calculate loss of gross domestic product (GDP) due to econornic disruptions caused by natural and/or manmade disasters. The main issue remaining to be resolved is extending the model to longer-term impacts on the economy that couid potentially result from a reactor accident (See COCO-2 model), if' appropria.te.
Reference:
N.E. Rixier, 1 , atin of Distribution Representing important Non-Site-Specific Parmrn F.*,er-:, in Off Sitenequence Analyses," Draft*NUREG/C.1-
.XXXX, SAND21OOXXXX Prioritization Leveraging Factors Resources Advancing State of the Art Independent Decision Tool Multi-Program.
Improvement.
Addressing Gapsj
jTitle General Site Suitability Criteria fo malMoua Reactors (SMRs)
Brief Summary of Need i he cur rent 2Uide, 'KegluY~or'y Cuidiý 4.7, "(--neral Site SUitahility Critpria for Nuclear lPowet StatIions," discusses meP nlaio site -_,haraczleristics related to public health dfId saftLy jai ernvironwr~ital Y~ tha tie"VC staff considers in determining the SUitability of sites ifor Iar e LWP~s, !'e advamceci ie' mr5, ilClUde small~ rnodula r Intecrai PW~s, hi-h
~ a~-o Pmper3W ~ctors, ýoc~ur-cooled fast reactors, and all other designs or rea Itechnoi Jgres (rxcptTor Icige 1,VVRs (g~eater than 700 MV~e). The SfvR dpsjgns are rcmrnarkbly different in si.c. (po vi levels) and reactor configuration.. Thereforp, there is a need to develop new regulatory guinance -or the NRC staff to consider in determining the su~itability of siees f(,: tho S iR,1
'Contact Name Jay Lee NRO/DSIR)
Cost Estimate S280K FTE Estimate 1. 0 FFTE Description of Work Develop riew regulatory piosroic i' -' l I-e 0PoUlazior densityv; excluison bounrdary and low populrition ;:(cre: focouiation l~ne ldistalce; use of the site environs indcluing proximrity to rran-mc1-e had;adpyil a,,i-c~ef stics of the site, inlcdicing seismnology.
IMetearmlogy, ýcolcgy, and hydroio-y irndteý-nimng the accepta bility o- a. site for a SMR.
Prioritization Leveraging Ft a r .R s_ou rc s . .....
R'ore ---- -- _.... . . ..... .. .....
!Factors "Advancing State*
... of theArt* .
.. ndependent DecisiorimakiIng
'Tool I.jilmprovement I
IMulti-Program
_ jAddressing
' GapsI
Title !Operational Considerations of Liquid Metal Reactor Designs BriefSurnmary of Need. The LMR designs present a numcer operational considerations not Currently evaluated by the current SRPs, sucn as oroertion with enrichment percenMtags i much greater than 5%,vwhich impacts fuel storage requirments, radiation monitoring requirements and AOO and accident analysis source terms. Some LMR reactors have exoerienced coolant contamination that has resulted in fuel damag*l I(e.g. Fermi 1, Santa Susana Sodium Reactor Experiment), coolant purification (cold Itraps) cnd other methods of monitoring and ensuring coolant purity are not well Idocumented for use by NRC personnel. Methods for performing In Service Inspections and related RCS components inspections is not available to the staff.
Contact Narfle Ron i aVera (NRO/DCIP/CIAPB)
- I Cost Estimate FTE Estimate Description of Work Collect the required industry, DOE, DOD and international operating experionce information, to support development o f the appropriate evaluation crciea and methods* Fhen develop the ruidlince.
Prioritization Leveraging, The current NRC guidance does not appear t-o address these types of arpas Factors Resources Advancing State Based on participation in some [,MR ARP concept presentation meetings, of the Art. i experience in these areas are poorly understood and not well corrmunicated.
Independent*, The current SRP and RG guidance does not encompass these types of operations Decision making in LMR.
Tool, Multi-Program This guidance will be applicable to all of the IMR designs.
Improvement Addressing Gaps As noted above,, this type of informration and guidance does not appear to be currently available in the commrtercial environment.
Title. *Evaluation of ARP Specific Pressure Boundary Failure Modes and Precursors Brief Summary of Need A number of the Advance Reactor Projects use design configurations that extend beyond the boundaries of current regulatory puidance. For instance, one design lenvisions mcviic threr entire reactor vessel inuclding spent fi, as sa" of the Irour~ne rfe ng ac . A dropped bundle analysis would possibiy extend es._
beyondas~euidie, and instea d wouid nvolve the entire core. Other design proposais invlve the use of steam o fee ,rter pipes inside the PCS pressure bou ndary, e - t L failure in orn of' hor.e ines could resiIt in an RCS primary toi secondary leak that far exceeds the. flow i aie of a single SG tube, utilized in the current analysis. Other designs are proposing the use of inert gases at high pressure as an RCS cooling medium. How the current Leak Before Break methodology (such as CG:1.45) would be extended to these designs should be determined, as well as how to analvze for non-traditional core damage modes experienced at similar plants (e.g. carbon moderated core fires at Windscale and Chernobyi)
Contact Name Ron LaVera (NRO/DC0P/CHPB)
[Cost Estimate%
IFTE Estimate Description of Work !Collect .he required industry and operating experience information from national j(DOE and DOD) and international sources, to support development of the pe'~,
the regoulatory guidance.
iapproriate analvticai methods. Then develo Prioritization [Leveraging I his ouidmc' will hbeapicable across a number of the ARP design concepts.
Factors !Resources iraclud'nrz some of ,the non-LWR des*gns, Advancing State Basedon par-ticipat on in several ArP concent presentation meetings, experience of the Art hrn these areas are poorly understood and nor well communicated.
independent fihe cui tent S'P and PC guKidance does not encompass these types of f.ailure Decision making Imoodes Tool,
[improvement:, applicable to other design centers, such as HTCR.
Addressing, Gaps As noted above, this type of information and gLidance does not appear to be
- " .crrntly avaiLboeinthecommercial environment.
Title Environmental Qualification of Internal Reactor Vessel Electrical Components Brief Summary of.Need IA number cf the Advance Reactor Projects are planning on the use of high electrical current comrnonoo ts, such as Reactor Coolant Pump motors, and Controi IRod Drive Mechari rs M,ýPnocs, that hove traditionally bo located o tride of the
!Reactor uoolant System ressuro bour(o ary. FI ctr i a;ilr rre of traditionally
!located components had few consequences, other than loss of RCS flow, or 1dropping a controi rod. !n the ARP desLns, faiure, of internally located electrical components, due either to overheating, or electrical short circuits could result in ruptures of containment devices intended to separate electrical insulation and metals (copper, aluminum or lead) that could be inimical to the fuel or the RCS Jpressure boundary, In addition, electrical faults in high current penetrations to the RCS pressure boundary could change the accident freouency for Small Break LOCAs, at the point of the penetration. Allowable limits and the associated models, methods and assumptions needed to assess and monitor the expected land actual conditions fot these :omponents should be developed, and lpromulgated, preferably in a Regulatory Guide format.
Contact Name Ron LaVera (NRO/DCI P./(CH1PiI)
Cost Estimate FTE. Estimate Description'of Work lCollect the required industry and operating experience information, both within, the nuclear indust ry and Iother high temperature and high pressure industries, to support development of the appropriate analytical methods. Then develop the
.. "regulatory guidance.
Prioritization Leveraging. This guidance will be applicable across a number of the ARP LVVR design conceptc, Factors,. !Resources and oossibly some of the non-LWR designs.
-Advancing State Based on participation in several ARP concept presentation meetings, experience of'the,Art .in these areas are poorly understood and not well commulnicated.
Independent EQ evaluations are currently required by SRP section 3.11. The guidance provided Decision making in thatSRP section and the referenced Industry Standards are insufficient to Tool . support an adequate evaluation of equipment qualification, MultiProgra.mni As noted, information developed in support of the LWR ARP designs, may be Improvement applicable to other tdesign centers, such as HTGR.
Addressing GapsSIAs noted above, based on the ARP presentations, this type of information and guidance does not appear to be:currently available.