ML20067C665

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Advises That ACRS Considers Many Stds,Codes & Guides in Formulating Recommendations Re Nuclear Generating Facility Const to Aec.Forwards List of Relevant Examples.Info Re Specific Facilities Available at Listed PDRs
ML20067C665
Person / Time
Site: Point Beach, Kewaunee  NextEra Energy icon.png
Issue date: 07/19/1973
From: Fraley R
Advisory Committee on Reactor Safeguards
To: Marcus P
WISCONSIN, UNIV. OF, MADISON, WI
Shared Package
ML20067C396 List:
References
FOIA-90-173 ACRS-GENERAL, NUDOCS 9102120153
Download: ML20067C665 (7)
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July 19, 1973

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Mr. P. Marcus, Research Assistant Environ. ental Awareness Center University of Wisconsin 1201 West Dayton street Madison, Wisconsin 53706

Dear Mr. Marcus:

This is in answer to your request for infor: nation on the nuelsar safety criteria applied by the Advisory Comnittee on Reactor Safoguards to nuclear generating facility construction. In its review of proposed facilities, there are :nany standards, codes, and guidas which are normally considered by the Cconittee in formulating its recoteendations to the AgC.

N ee include:

published, and scos proposed, Cecraission Regulations, Wich are the basic requirements established for licensing: AEC Esgulatory Outdas, g

which describe acceptable nethods of meeting the general requirasnents; and Industry Codes and StaMards. It should be noted that these standards are -

not all irclusive or universally appitcable since reaictor type, sise, loca-tion, etc., are variables that cust be considered. The Cocntttee frequently reconnends additions to or variations of these requirements on a case-by-case basis. Nse recetmandations are included in the Cocnittee's reports to the Atomic Energy Comission on the cases that are reviewed by the ACRS.

The ertsened itst includes many of the relevent examples of each. In addition, I understand that you can find specific examplas of the eriteria used in specific cases in the library of the Department of hbelaar Engi-nearing at the University. Dr. Max Carbon Head of the Departant of Nuctsar j

Engineering, Las indiccted that he wuld be willing to make this information j

availad e to you. Additional information reg,arding specific projects, the Kevaunee Nuclear Plant and the Point Beach Nuclear Plant, is available at the Pubite Document Rooms located att Kawaunee Public Library Manitowoc Public Library Atta Mrs. O. H. Holls, Librarian 808 Hamilton Street 314 Milwaukae Street Manitowoc, Wisconsta 54336 '

Kantaunes, Wisconsin 54216

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9102120153 901219 PDR FDIA DEKOK90-173 PDR

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Mr. P. Marcus

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In addition, I have attached an article describing the metivities afg.yo'a#

1 the ACRS which may be of further use to you, p}.,,",

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Orig nal Signed by i

R. F. Fraley

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-1 R. F. Fraley Emeutive' Secretary

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1) List of AEC Regulations
2) AEC Regulatory Guides
3) Industry Codes and Standards
4) Article re Activities of ACRS I

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I Atomic Enerev Commission Renulations 10 CFR 20* - Standards-for Protection Against Radiation 10 CFR 50 - Licensing of Production and Utilitation racilities Appendix A - General Design Criteria for Nucicar Power Plants i

Appendix B - Quality Assurance Criteria for Nucicar Power Plants and Fuel Reprocessing Plants Appendix E - Emergency Plans for Production and Utilization Facilities Appendix F - Policy Relating to the Siting of Fuel Reprocessing Plants and Related Waste Management Facilities Appendix G - Fracture Toughness Requirements (Proposed)

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Appendix 11 - Reactor Vessel Material Surveillance Program

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Requirements (Proposed) 4 Appendix I - Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion "as Low as Practicable" for 4

Radioactive Material in Light-Water-Cooled

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Nuclear-Power Reactor Effluents (Proposed) 10 CFR 55 - Operators' Licenses

  • Part 20 of the Title 10 of the Code of Federal Regulations 1

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Packaging of 1.adioactive !!aterial for Transport and l

10 CFR 71 Transportation of Radioactive Material Under Certain Conditions 10 CFR 100 - Reactor Site Criteria t-

- Interim Acceptance Criteria for Emergency-core Cooling Systems for Light-

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Water-Cooled Nuclear Power 7eactors i

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AEC REGULATORY CUID.ES--

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1.1 Net Pimtne Suetion llent for I!metrency Cure ronling and Containment Heat Removal System Pumps (formeily Natety Guide 1) 1.2

'lhelmal Simck in Reater lhuute Venels(fortnetly Safety Guide 2) i.3 Assum; nora U3:d for iblaatmg tlw Potenti.d Radiolepeal Comequences of a 1 oss of Coolant j

Acenlent foi lui.nr Ntei Reacton (Remnvi 1,6;7.4,of fonner Safely Guide 3) j Anumptions Uvd for 1.wluating II e Potennai Radnougical Consequences of a Loss of Coolant i

1.4 Accid <nt for Prescrired Water Rcactora (Rnisi= !.0/72 of forrnes Safety Guide 4) 1.5 Awumptmus lised for !Wting the l'ortnual Radadopeal Consequences of a Ste;on Line Dreak j

Auident for Dedm;, her Rerator-(fo:n.criy S.;iety Cmde 5) 1.6 indepenAnce Detween Red.a.Jant Standby tons.te) Power Scurces and Between Their Dhtribution Systems (former! Sde'y Guid: 6) 1.7 Contrul of Comt.estd.le Gn concentrahons in Cents;nmsnt Following a 12,5s of Coolant Ace > dent (fca moly Safety GG il 1.M Personn:15eketLm aaJ Tn.: rang (formedy SM ty GmJe R) l."

Seketioa of the<:1 U nei br S:t C.ipaeity lor Standby Pov.u Supplies (formerly Safety Guide 4) 1.10 Meclnnical (Caje.elJi S;1 ices in Reinfoiony liars of Cater.ny 1 Concate Suu:tures (Roiuon I, r

I 1/.'/73, of forrar Stfety Guok 10) 1.11 Instrm.rzut Lines Pentit::iiar hinany lbsto: Centamment (furmerly Safety Guid: 11) 1.12 Instronentation for L:all pLn(foiractly Sahts Guide 121 1.13 Fuel Staiap: Facihty Dm;n Dais (formctly Of[t> GuiJ: 13) i e-(

l.14 Rearlot Coot nt f ump i 1.ui.21 latepny (fonneth Sdei) Gmde 11) 1.15 Tertig or nein terein7 9m for rene,eg. 3,n g,7,, g;nism,1.12/28D2, of f ormer Safety Guide 15) 1.16 Repstttr.;;of Operatmg Ir.ferrration (fonnn;y Sde!y C

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1.17 Prouction of Neckar Pi..nts Apinsi Indutr.;d Sabuta;;c (llevismn

1. 6/73, of former Safe t) 3 Guid: 17) 7 1.18 Structural Acceptance Test for Concrete Prirum' Resetor Containments (Revision 1,12/28/72, of I

fornier Safety Gu% lb) l.19 Nondunuetive Examinatmn of Piimary Cont inment t mer Welds (Revision 1, R/II/72, of fonnet Safety Guid: 19) 1.20 Vibratian Measurements on Reactoi Intern.h(formeily Safety Guide 20) 1.21 Measuiing and Reponing of 11f0uents fwm Swica: Pmver 1%nts(formerly Safety Guide 21) 1.22 Pesiodie Testing of Pietcet;on System Actuatian Fonttions(formerly SdctyGmJe 22) 1.23 Oasite Metcomlopcal Pmtrams(fonnalv F;.fety Guid 23) l.24 Assumptions Ured for laaluating the Poie.rual Radiolor.ieal Consequences of a Pressurised Wales j

Rcaetor Gas Storar: Tank Failute (fonnerly Safet> Guide 24) i.25 Assumptions Used ici Evaluatlng the Potennal Hadelot cal Consequences of a Fuel Handling i

Accident in th: Fu:1 llandling and Storate Faedity for Boihng and Pressurized Water Reactors j

, (furmctly Saf,1y GuiJ: 25) l.25', Quality Group Clusifaations and Standards lfornverly Safety Guide 26) 1.27 Ulumate lhat Sink (formarly Safety Guit,e 27i 1.28 Quality Aismance Propam Requirement 2 (Dnirn and Construction)(formerly Safety Guide 2fy l.29 Seismic Dmp) ClassifLuon(formerly Cafetv Gu;de 291 1.30 Quality Assurance Itequirennnts for tM laitidlation. Insp:etmn and Testmg of Instrumentation ar.d I.itetrie Equipment (fmmnly Sdety CmJe M) 1.31 Control of Stainlos Suel Welding (Revnion 1, 6J3.of former Sdelv Guule 31) 1.32 Use of IIIE Sid 301; lt01, "Coresia for Clin !!' H:etne Systeun fm Nuclear Power Generating Statmns"(formerly Sdely Guid M)

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g L-b I.33 Quality Auurance Program RequirementGO vration)(fornicity Safety (;nide 33)'

t 1.34 Contml el FleeIrodag Weld Propealie.,(12j28/72) 1.M In<enice Sancillance of lingrouted Tendon > in Prestressed Conesete Containment Structutes

(.'/5/,74 1.36 Noinnetalhe t hernul Insulation for Austenitic Staim w Steelt 2/23/7 t1 17 Qn.dit) Amn i.cc llequiremenn for Cleaning ot Imd Syueim and Associated Components of Water Co.' led Nuclear Pow et Pianh (3/16l731 1.4 Qualit) As.ur.n.ce Rec;uirements for PacLagior. Shipping. Receiving.Storap,and llandUng of items for Wate:.Civled Nuclear Power Planb (3/16/73) l.N lion <el cep:ng P.equrements for Water. cooled Nnefear Power Plants (3/16/73)

I A0 Quahficativa 1sts of Continaans-Duty Mmon insialled in ide the Comainment of Wate:Cooied s

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.j Noclear P. v.cr Plants (3/16!73)

IAl Picogran. mal Testu :: o! Hedundant Oneite I:lectrie Power Systems to Verify Proper 1.oad (;roup

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1.:., ;a:n::t s (,1 'l S/73) r I A3 Contrul of Steii.S Steel Weld Cladding of I ow Alloy Steel Companenn f.V31 1.11 Control of il'e Cz e ef. Set.itized Stalidess Steel (5/731 lA% Peac'or Coo.' ant Prmare floondary Leak.y Detectiva Spienn15!73) i Ali Pioicetion Ap.c..t P;p. Wldp Inude Centai:naent (5/73r 1 A7 - hypmed and Irm, >*ab'c Statu. Indication f or Nn, lear I'lant Sdet) Systenn(5/73) i AS. Unca thnm. t! I -. olm. Com'. n inon: tw F nsone ( ateg n:.11 laid Sp'em Components (5/73) d j

l.50 Contra l ot P.elc.:: Teny cratam. for Low.Al lay.Wel Wejdmp (5/73) l.51 in eni c In rea cr.J /NdF CN: Obss 2 an.13 Nacica: P!.o.: cer usonmn (5!73) c l.53 Appuc.non iu o ; N-f f '.

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it...u, 3.f.tems ((.l73) 1.51 (Ja.41!ty Wi..a.cc Peqwcnws for hotcetisc Co Hap Ar; ned to Watet fooled Nutleur Power j

Planb ((3l73) l.55 Concrete PLeenm: in Catqary i Structure.i(6/731

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l.5r..f. Lint;n gc of Y..ae: Pmity in liaiFog Water Reacion ti.!73) l 1.37 ilesip Limia and Loadmg Cumhinations for Metal Prmury Reactor Containment System g

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e-Industry Coden and Standards 1.

Sections III and XI of the ASME Boiler and Pressure Vessel Code.

2, USA Standard Code for Pressure Piping (USASB 31.1) 3.

USA Standard Code for Pressure Piping (USASB 31.7)

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Institute of Electrical and Electronic Engineers Criteria for i

Nuclear Power Plant Protection SystemL(IEEE-279) e i

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