Regulatory Guide 3.53

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Applicability of Existing Regulatory Guides to the Design and Operation of an Independent Spent Fuel Storage Installation
ML031990381
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Site: WM-00011
Issue date: 07/31/1982
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Office of Nuclear Regulatory Research
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CE 037-4 NUDOCS 8804290116, RG-3.053
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U.S. NUCL; REGULATORY COMMISSION`'July 1982!) REGULATORY GUIDEOFFICE OF NUCLEAR REGULATORY RESEARCHREGULATORY GUIDE 3.63(Task CE 0374)APPLICABILITY OF EXISTING REGULATORY GUIDES TO THE DESIGN AND OPERATIONOF AN INDEPENDENT SPENT FUEL STORAGE INSTALLATIONA. INTRODUCTIONThe storage of spent fuel in an independent spent fuelstorage installation (ISFSI) pending its ultimate disposalIs a new step in the nuclear fuel cycle that is licensedpursuant to 10 CFR Part 72, "Licensing Requirements forthe Storage of Spent Fuel in an Independent Spent FuelStorage Installation." The conventional method for suchstorage is in water basins embedded in the ground withtheir water surface approximately at grade level. Othermethods using dry storage are also being considered. Thesemethods may include air-cooled canyons or vaults, under-ground caissons or dry wells, or surface-storage casks orsilos. Applicants may determine that other regulatoryguides contain useful information for particular situations.Potential use of other guides may be discussed with theNRC staff.This regulatory guide identifies existing regulatoryguides that may be applicable in whole or in part to thedesign and operation of an ISFSI. Since the differentmodes of storage vary widely in design, the guides cited willobviously not all be applicable to all design technologies.Also, as a general rule, the technologies and operatingconditions involved in the receipt and storage of aged spentfuel (i.e., spent fuel that has undergone at least 1 year ofdecay since removal from a reactor core) are not only muchless complex and dynamic than those of production andutilization facilities (i.e., reactor and reprocessing facilities),but they are also less complex and dynamic than the tech-nologies and conditions involved in the receipt and storageof spent fuel in reactor basins designed to receive spent fueldirectly from a reactor core after a decay of a few days orless. The referenced guides are useful not only because themethods of design and operation cited have been examinedby the NRC staff and found to be appropriate as a means ofmeeting the requirements of NRC regulations, but alsobecause these guides are familiar to licensees and applicants.Thus, while the guides inay exceed the requirements of Part72 in some cases (in particular, those guides written withreference to power reactors), they can be of benefit toapplicants and licensees who already have experience withthe solutions endorsed in them and who may wish to applyfamiliar solutions rather than develop alternative solutionsless certain of being acceptable to the NRC staff.B. DISCUSSIONExisting regulatory guides were examined for theirpotential applicability to the design and operation of anISFSI that may use either a wet or dry mode of storage.The specific revision of each guide that may be appli-cable, in whole or In part, is listed In the tables of thisguide. This guide will be updated as referenced guidesare revised.The user and staff must exercise discretion in using all ofthe detailed information ssociated with each regulatoryposition cited, e.g., not all appendices and examples con-tained in the cited guides are applicable to an ISFSI. Ifthe guidance in a guide written specifically for an ISFSIdiffers from that in a guide developed for another facility,(e.g., a Division I guide), the guidance in the guide specificto an ISFSI should be followed.C. REGULATORY POSITIONTables 1, 2, and 3 list existing regulatory guides thatmay be applicable to an ISFSI. Table I identifies guidesapplicable to ISFSI design and Table 2 identifies guidesapplicable to ISFSI operation. Table 3 identifies guides thatare specific to an ISFSI. The guides are listed in the tablesby number, title, and revision under general subjects thatare arranged alphabetically. Relevant regulatory positions ineach guide are identified and briefly described. In Tables 1and 2, the portions of the NRC regulations addressed bythe regulatory positions are also identified and otherpertinent information is provided.USNRC REGULATORY GUIDESRegulatory Guides are issued to describe and make available to thepublic methods acceptable to the NRC taff of Implementingspecific parts f the Commission's regulations, to delineate tech-niques used by the staff In evaluating specific problems or postu-lated ccloents or to provide guidance to applicants Regulatory~ Guides are nof substitutes for regulations, and compliance with-; them Is not required. Methods and solutions different from those setout In the guides will be acceptable I they Povide basis for thefindings requisite to the issuance or continuance of a permit orlicense by the Commission.This guide was Issued after consideration of comments received fromthe Public. Comments and suggestions for Improvements in theseguides are encouraged at all times, and guides will be revised, asappropriate, to accommodate comments and to reflect new Informa-tion or experience.8804290116 80411N- ISS SUBJ .--- ~102 DCD.Comments should be ent to the Secretary of the Commission.U.S. Nuclear Regulatory Commission Washington D.C. 20555.Attentiong Dockting and Service ranch.The guides are ssued In the following ten broad divisions:1. Power Reactors 6. Products2. Research and Test Reactors 7. Transportation3. Fuels and MaterIals Fcilities 8. Occupational Health4. Environmental and Siting 9. Antitrust and Financial Review5. Materials and Plant Protection 10. GeneralCopies of Issued guides may be purchased at the current GovernmentPrinting Office price. A subscription service for future guides In spe-cific divisions Is available through the Government Printing Office.information on the subscription service and current OPO prices maybe obtained by writing the U.S. Nuclear Regulatory Commission.Washington, D.C. 20555. Attention: Publications Sales Manage V , .Table IDESIGNSubjectRegulatory GuideRegulatory PositionPortions of 10 CFR AddressedAccident Analysis1.25, Assumptions Used for Evaluating thePotential Radiological Consequences of aFuel Handling Accident in the Fuel Handl-ing and Storage Facility for Boiling andPressurized Water Reactors (Safety Guide 25).23.b-Atmospheric diffusionassumptions-External whole-bodyapproximations assumptions72.65(a), 72.74(d)72.65(a), 72.74(d)1.91, Revision , Evaluations of ExplosionsPostulated To Occur on TransportationRoutes Near Nuclear Power Plants223-Explosive transport-Explosive transport-Explosive transport7x.63, 72.7f(c)72.63, 72.72(c)72.63, 72.72(c)(1.145, Atmosphen'S Dispersion Models forPotential Accidenytonsequence Assess-ments at Nucleaf Power Plants1.21.31.4234Control Room-Chemical Release1.78, Assumptions for Evaluating theHabitability of a Nuclear Power PlantControl Room During a PostulatedHazardous Chemical ReleaseI2345.a61112-Distances for X/Q-X/Q at the controlled area-X/Q at EPZ-Maximum sector X/Q values-5% overall site XJ1 value-Selection of X/Q-Stored chemicals-Transported chemicals-Onsite chemicals-Toxicity limits-Accident concentration-Dilution factor* Removal systems-Natural phenomenaand chemical release-Emergency proceduresIn applying this guide to anISFSI, substitute the terms"controlled area" as definedin § 72.3(h) and "ISFSI-emergency planning zone(ISFSI-EPZ)" as defined in§ 72.3(n) respectively forthe terms "exclusion area"and "low population zone(LPZ)" wherever they appear.72.65(a), 72.74(d)72.65(a), 72.74(d)72.65(a), 72.74(d)72.65(a), 72.74(d)72.65(a), 72.74(d)72.65(a), 72.74(d)72.61(b), 72.72(j)72.61 (b), 72.72(j)72.6 1(b), 72.72(j)-72.72(j)72.61(b), 72.72(j)72.61(b), 72.72(j)72.72(j)72.61(b), 72.720)As72.1 (a)(1 l)

Table 1 (Continued)DESIGNSubjectCriticality SafetyRegulatory Guide3.41, RevisioA 1, Validation of CalculationalMethods for Nuclear Criticality SafetyRegulatory PositionPortions of 10 CFR Addressed72.73(a)All-Endorsement of ANSIN16.9-1975Floods1.59, Revision 2, Design Basis Floods forNuclear Power PlantsI2.a2.c34-Flood conditions-Hardened protectionalternative-warning time-Hardened protectionalternative-less severeflood conditions-Unanticipated changes-Data utilization72.33(cX4), 72.61(c), 72.62,72.72(bX2), 72.72(b)(4)72.33(cX4). 72.61(c), 72.62,72.72(bX2), 72.72(bX4)72.33(cX4), 72.61(c), 72.62,72.72(bX2), 72.72(bX4)72.33(cX4), 72.61(c), 72.62,72.72(bX2), 72.72(b)(4)72.33(c)(4), 72.61(c), 72.62,72.72(bX2), 72.72(bX4)(wwFlood Protection1.102, Revision 1, Flood Protection forNuclear Power Plants223-Types of protection-Shutdown specifications-Vulnerability of safety-relatedequipment72.72(b)X2)72.72(b)(2)72.72(b)X2)Physical Hydraulic Models1.125, Revision 1, Physical Models forDesign and Operation of Hydraulic Struc-tures and Systems for Nuclear PowerPlants223-Model preconstructionsubmittals-Early staff discussions-Documentation-Comparison of data andmodel-Design changes72.15(aX3), 72.33(cX4),72.61(c), 72.6272.1 5(aX3), 72.33(cX4),72.61(c), 72.6272.15(a)(3), 72.33(cX4),72.61(c), 72.6272.15(aX3), 72.33(cX4),72.61(c), 72.62, 72.72(bX3)72.1 S(aX3), 72.33(cX4),72.61(c), 72.62, 72.72(bX3)72.15(aX3), 72.33(cX4),72.61(c), 72.62, 72.72(bX3)456 -Report contents r .ITable I (Continued)DESIGNSubjectRegulatory GuideRegulatory PositionPortons of 10 CFR AddressedQuality Assutance-Designand Constructon1.28, Revision 2, Quality AssuranceProgram Requirements (Design andConstruction)General-Endorsement of ANSIN45.2-19774472.15(a)(14), 72.72(a), 72.8072.15(aX14), 7.72(a), 72.80Quality Auurance-Terms1.7, Quality Assurance Terms andDetinitionsSecond Paragraph -Procurement documents72.80(Radiological Protection-ALARA8.8, Revision 3, Information Relevant toi!nsuring that Occupational Radiation Expo-sures at Nuclear Power Stations Wm Be AsLow As h Reasonably AchievableWLab1Ld2.a2.b( 1)2.b(2)2.b(4)2.b(5)2.b(6)2.b(7)2.b(8)2.b(9)2.b(I0)2.c2.d(l)2.d(2)* Review of designs andequipment-Access control of radiationareas-Shielding for senice personnel* Temporary shieldft anddistance-Streaming and scattering-Streaming-Reduction of exposurefrom pipes-Expeditious design features-Laydown space-Removal of equipment-Drains* Process instrumentation andcontrols-Control of airborne con-taminants (air flow)-Ventilation systemsIn applying this guide to anISFSI, substitute the term"ISFSI" for the tenns "LWR"and "nuclear power station"wherever they appear. Dis-regard references to the nuclearsteam supply vendor.20.1(c), 72.15(a)(5), 72.74(a)20.1(c), 72.15(aXS), 72.74(a)20.1(c), 72.IS(a)(S), 72.74(a)20.1(c), 72.15(a)(5), 72.74(a)20. 1(c), 72. I5(aX5), 72.74(a)20.1(c), 72.1S(a)(5), 72.74(a)20.1(c), 72.15(aXS), 72.74(a)20.1(c), 72.15(aXS), 72.74(a)20.1(c), 72.15(a)(5), 72.74(a)20.1(c), 72.15(aXS), 72.74(a)20.1(c), 72.15(aX5), 72.74(a)20.1(c), 72.1S(a)(S), 72.74(a)20.1(c), 72.15(a)(S), 72.74(a),72.74(c), 72.74(d)20.1(c), 72.1 5(aXS),72.1 5(aXI 2), 72.74(a)72.74(d)II Table (Continued)DESIGNSubjectRegulatory GuideRegulatory PositionPortions of 10 dFR Addresed2.d(3)2.f2.g2.h(1)2.h(2)2.h(3)2h(4)2.h(5)2Jh(6)2.h(7)2i(l)w%A2i(2)2Ji(3)2i(4)2i(5)2i(7)2.i(8)2i(9)2(10)2.i(11)2i(12)2.i(3)21(14)2i.(15)3.a3.b(1)3.b(3)3.c4.-Auxiliary ventilationsystems-Isolation and decontamination-Radiation monitoring systems* Reduction of accumulation-Need for maintenance-Pipe bends* Pipe surfaces-Pipe tees* Slurry piping-Sparging* Radiation-damage-resistantmaterials-Stainless steel piping .* Pipe routing* Filters-Servicing valves-Valve selection-Pumps-Sedimentation-Spare pipe connections-Station design,.-Component removal-Working environment-Lamp replacement-Emergency lighting-Radiation protection programpreparation and planning-Health physics technicians-Communications* Postoperations-Radiation protection facil-ities Instrumentation andequipment20.1(c), 72$ 5(ax)()72.1 5(a)( 2), 72.74(a)72.74(c), 72.74(d).20.1(c), 72.1S(a)(S),72.74(a), 72.74(b)20.1(c), 72.16(aXS),72.74(b), 72.74(c)20.1(c), 72.15(aXS), 72.74(a)20.1(c), 72.1S(a)(S), 72.74(a)20.1(c), 72.15(aX5), 72.74(a)20.1(c), 72.lS(aXS), 72.74(a)20.1(c), 72.15(aXS), 72.74(a)20.1(c), 72.1S(aXS), 72.74(a)20.1(c), 72.15(aXS), 72.74(a)20.1(c), 72.15(a)(5), 72.74(a)20.1(c), 72.15(aX5), 72.74(a)20.1(c), 72.15(a)(5), 72.74(a)20.1(c), 72.1S(aX5), 72.74(a)20.1(c), 72.1S(aXS), 72.74(a)20.1(c), 72.1S(aX5), 72.74(a)20.1(c), 72.15(aX5), 72.74(a)20.1(c), 72.15(aXS), 72.74(a)20.1(c), 72.15(aXS), 72.74(a)20.1(c), 72.IS(aXS), 72.74(a)'20.1(c), 72.lS(aXS), 72.74(a) -20.1(c), 72.15(aXS), 72.74(a) (20.1(c), 72.15(aXS), 72.74(a)20.1(c), 72.1S(aXS), 72.74(a)20.1(c), 72.33(c)(5)20.1(c), 72.33(c)(S)20.1(c), 72.33(cX5)20.1(c), 72.33(cXS)20.1(c), 72.33(c)(S), 72.74 Table I (Continued)DESIGNSubjectRegulator GuideRegulatory PositionSeismic1.29, Revision 3, Seismic Design ClassificationPortions of 10 CFR AddressedIn applying this guide to anISFSI, substitute the term"ISFSI Design Earthquake(ISFSI-DE)" (or the "SafeShutdown Earthquake (SSE)"wherever it appears.72.72(b)(2)I .d1.6I.iI.jL.k111.nL.p1.q23-All sections listed for posi-tion I describe applicableactivities to be included72.72(bl(2) -72.72(b)X2)72.72(b)X2)72.72(b)X2), 72.72(i)72.72(b)X2)72.720)72.75(a)72.72(b)X2)72.72(b)X2)W'AW-Non-safety-relatedcomponents-Defined boundaries72.72(bX2)1.6o, Revision 1, Design Response Spectra forSeismic Design of Nuclear Power PlantsIn applying this guide to anISFSI, substitute the term"ISFSI Design Earthquake(ISFSI-DE)" for the term"Safe Shutdown Earthquake(SSE)" wherever it appears.The term "Operating BasisEarthquake (OBE)" is notapplicable to an SFSI.72.66(a)(2), 72.66(a)(6),72.66(b)72.66(aX2), 72.66(a)(6),72.66(b)In applying this guide to anISFSI, substitute the term"ISFSI Design Earthquake(ISFSI-DE)" for the term22-Horizontal component* Vertical component1.61, Damping Values for Seismic Design ofNuclear Power PlantsTo C .7Table I (Continued)DESIGNSubfeetRegulatory GuideRegulatory PositionPortiots of 10 CF1 Addressed223-Modal damping values* High damping values-Combined stress"Safe Shutdown Earthquake(SSE)' wherever t appears.The term "Operating BasisEarthquake (OBD)" is notapplicable to an ISFSI.72.66(aX2), 72.66(aX6),72.66(b)72.66(aX2), 72.66(a)(6),72.66(b)72.66(aX2), 72.66(aX6),72.66(b)wAf-J1*1.92, Revision 1. Combining Modal Responsesand Spatial Components In Seismic ResponseAnalysis1.122, Revision 1, Development of Floor DesignResponse Spectra for Seismic Design of Floor-Supported Equipment or ComponentsI2-Combination of effects-Combining of modal responsesl-Directional analysis72.66(aX2), 72.66(sX6),72.66(b)72.66(aX2), 72.66(a)(6),72.66(b)72.66(aX2), 72.66(a)(6),72.66(b)72.66(aX2), 72.66(aX6),72.66(b)72.66(aX2), 72.66(a)(6),72.66(b)2-Uncertainties3-Response spectrumSite Investigations-Foundstions1.132, Revision 1, Site Investigations forFoundations of Nuclear Power PlantsThis guide applies to all typesof ISFSI designs (§ 72.66).If massive structures orfoundations are required bythe specific design (i.e., waterbasin, vault, canyon, supporthot cell), this guide wouldprovide applicable guidance forthe site investigation.I223-General site investigation-Boring logs-Ground-water investigations72.61(a), 72.66(a)(4)72.61(a), 72.66(aX4)72.61(a), 72.66(a)(4)r Table 1 (Continued)DZESIGNSuetRegulator GuideRegulatory Position4S67-Procedures-Spacing and depth-Sampling-Retention of records andsamplesSite Investlgations-soils1.138, Laboratory Inwestigations of Soils forEngineering Analysis and Design of NuclearPower PlantsI2-Requirements for testingprogram-Handling and storage ofsamples-Selection and preparationof specimens-Criteria for testing procedures-Documentation34SwthYPortlon of 10 CFR Addressed72.61(a), 72.66(aX4)72.61(a), 72.66(a)(4)72.61(a), 72.66(a)(4)72.61(a), 72.66(aX4)72.61(a), 72.66(aX4)72.61(a), 72.66(a(4)72.61(a), 72.66(aX4)72.61(a), 72.66(aX4)72.61(a), 72.66(aX4)72.1 S(aX3), 72.33(c)(4),72.74(a)72.8072.8072.1 5(aX3), 72.33(cX4),72.74(a)72.1 5(a)(3), 72.33(c)(4),72.74(a)72.1 S(aX3), 72.33(c)(4),72.74(a)72.1 S(aX3), 72.3 3(cX4),72.74(a)72.1 5(aX3), 72.33(cX4),72.74(a)72.1 S(aX3), 72.33(cX4),72.74(a)(Structures.-ConcreteShields1.69, Concrete Radiation Shields for NuclearPower PlantsGeneral12345678-Endorsement ofANSI-N101.6-1972Testing-Diesel Generator1.108, Revision 1, Periodic TestingofDiesel Generator Units Used as OnsiteElectric Power Systems at Nuclear PowerPlants323-General design* Testing-Records and reports72.72(f, 72.72(k)72.72(k)Reports are not submittedpursuant to RegulatoryGuide 1.16. 72.72(k)

40 toTable 1 ContInued)DESIGNSubjectRegulatory GuideRegulator PositionTesting-Protective1.22, Periodic Testing of Protection SystemActuation Functions (Safety Guide 22)Porton of 10 CFR AddresedIn applying this guide to anISFSI, substitute the expres-sion "lSFSI receiving and stor-age operations" for the expres-sion "reactor operation" wher-ever it appears.72.72(f)72.72(f)72.72(f)72.61(c), 72.6272.61(c), 72.62224-Testing requirements-Testing methods-Untested equipment-Design basis tornadob Len conseis tive designbasis tornado(Tornado1.76, Design Basis Tornado for Nuclear PowerPlants12Wbt41Waste ManagementSystems1.143, Revision 1, Design Guidance forRadioactive Waste Management Systems,.Structures, and Components Installed inLight-Water-Cooled Nuclear Power PlantsThis guide does not refer tothe spent fuel storage systemssuch as the basin, cask, vault,etc., but only applies to thesystems that ae used to collect,store, control, or process wastethat is generated during theISFSI operation.Liquid Waste System1.1.1

  • Design and test requrements1.1.3 -Seismic criteria1.1.4
  • Seismic criteria1.2 -Tank design72.72(a)72.72(b)(1), 72.72(bX2)72.72(b)(1), 72.72(bX2)72.75I ITable I (Continued)DESIGNSubjectRegulatory GuideRegulatory PositionPorthr of 10 CFR AddressedSolid Waste System3.1.1 e Design and test requirements3.1.3 -Seismic criteria3.1.4 v Seismic criteria4.1 -ALARA4.4 -Hydrostatic testing4.5 -Testing5.2 -Buildings housing radwastesystems5.3 -Optional shielding7i.72(a)72.72(b)(1). 72.72(b)(2)72.72(b)(1), 72.72(bX2)72.7572.7572.7572.72(b)(1), 72.72(b)(2)72.72(b)(1), 72.72(b)(2)(%wfwfCDIICt)

ITable 2OPERATIONSSubjectRegulatory GuideRegulatory PositionPortions of 10 CFR AddressedAtmospheric Releases4.16,Measuring, Evaluating, and ReportingRadioactivity in Releases of RadioactiveMaterials in Liquid and Airborne Effluentsfrom Nuclear Fuel Processing and Fabrica-tion PlantsExamples in this guide are notapplicable to an ISFSI.Environmental reports for anISFSI should be submitted onan annual basis rather thansemiannually as stated In posi-tion 5.1.72.74(c)72.74(c)72.74(c)72.74(c)1234S* Methods of sampling analysis-Sampling program-Analysis of samples-Precision and accuracy ofresults-Reporting of results72.33(dX3).tAAtmospheric Transport1.11"1) Revision 1, Methods for EstimatingAtmospheric Transport and Dispersion ofGaseous Effluents in Routine Releases fromLight.Water-Cooled ReactorsI* Atmospheric transportand diffusion models-Source configuration23-Removal mechanisms4Meteorological data formodels72.33(dX3), 72.61(e).72.65(a), 72.74(d)72.33(d)(3), 72.61(e),72.65(a), 72.74(d)72.33(dX3), 72.61(e),72.65(a), 72.74(d)72.33(dX3), 72.61(e),72.65(a), 72.74(d)72.15(a)(13), 72.33(dX3),72.61(e), 72.65(a), 72.74(d)72.15(aX13), 72.33(dX3),72.61(e), 72.65(a), 72.74(d)Aqnati Dispersion1.113, Revision 1, Estimating Aquatic Disper-sion of Effluents from Accidental and RoutineReactor Releases for the

Purpose

of Imple.menting Appendix II-Transport and water-usemodels-Selection of models2Dose Assessment1.1 IUY, Revision 1, Calculation of AnnualDoses to Man from Routine Releases ofReactor Effluents for the

Purpose

ofEvaluating Compliance with 10 CFRPart 50, Appendix I.134-Doses from liquideffluent pathways-Doses from airborneparticulates-Integrated doses topopulation72.33(d)(3), 72.61(e),72.65(a), 72.74(d)72.33(dX3), 72.61(e),72.6S(a), 72.74(d)72.33(dX3), 72.61(e),72.65(a), 72.74(d)f Table 2 (Continued)OPERATIONSSubjectEffluent MonitoringTleguhar GuideRegulatory Position1.21, Revision l, Measuring, Evaluating,and Reporting Radioactivity in SolidWastes and Releases of Radioactive Mate-dals in Liquid and Gaseous Effluents fromLight-Water-Cooled Nudear Power Plants'.ftle)234S6789l .aI I.bI .c12.b12.cLocation of monitoring* Type of monitoring-Gross radioactivitymeasurements-Measurements of specificradionuclides-Representative samples-Composite samples* Time between collectionand analysis-Corrections for decay-Errors in measurement-Quality controls-Calibrations-Significant figures-Numerical valuesPortion of 10 CFR AddressedFor an ISPSI that is co-locatedat a reactor site, as opposed toan ISFSI at a separate site, themonitoring requirements maybe reduced. Monitoring may beneeded at the fuel receiving andstorage areas on a continuousbasis only when spent fuel isbeing handled. Otherwise,periodic measurements maysuffice, particularly for possiblesealed storage modes.72.74(c)(1), 72.74(d)72.33(d), 72.74(c)(1), 72.74(d)72.33(d), 72.74(cX 1),72.74(d)72.33(d), 72.74(c)(1),72.74(d)72.33(d), 12.74(c)(1)72.33(d), 72.74(c)(1)72.33(d), 72.74(c)(1)72.33(d), 72.74(c)( 1)72.33(d), 72.74(d)72.80(b)72.74(d)72.33(d), 72.74(d)72.33(d), 72.74(d)(Environmental MonitoringThe preoperational monitoringperiod as stated in regulatoryposition I should be reducedfrom 2 years to I year.72.33(d)(2), 72.6772.33(dX2), 72.6772.33(dX2), 72.674.1, Revision 1, Programs for MonitoringRadioactivity in the Environs of NuclearPower Plants12.a2.b-Preoperational program* Sample media-Sample frequency R4Table 2 (Continued)OPERATIONSRegui!Wry GuieRegatory PositionPortions of 10 CR Addressed2.d2.e3-Analysis-Quality control-Detection capabilities72.33(dX2)72.33(d)l2), 72.8072.33(dX2), 72.67Envi"omentalMonrtovins-TLD4.13, Revision 1, Performance, Testing,and Procedural Specifications forThermoluminescence Dosimetry:Environmental ApplicationsGeneralI2345-Endorsement ofANSI N545-1979Quality Asmnce-Environmental IMonitoring'4I..)4.15, Revision 1, Quality Assurance for Radio-logical Monitoring Programs (Normal Opera-tions)-Effluent Streams and the Environment124S6789-Organization andresponsibilities-Personnel qualifications* Records-Quality control In sampling-Quality control in analysis-Quality control for continuousmonitoring systems-Review and analysis of data-Audits72.33(d)(2), 72.74(c)(2)72.33(dX2), 72.74(cX2)72.33(d)(2), 72.74(c)(2)72.33(dX2), 72.74(cX2)72.33(dX2), 72.74(c)(2)72.1772.1772.33(cXS), 72.8072.33(c)(S), 72.8072.33(c)(5), 72.8072.33(cXS), 72.8072.33(c)(S), 72.8072.33(cXS), 72.80(RadiologicalProtection-ALARA8.8, Revision 3, Information Relevant toEnsuring that Occupational RadiationExposures at Nuclear Power Stations WillBe As Low As Is Reasonably AchievableIn applying this guide to anISFSI, substitute the term"ISFSI" for the terms "LWR"and "nuclear power station"wherever they appear. Dis-regard references to thenuclear steam supply vendor.20.1(c), 72.33(c)(S)20.1(c), 72.33(c)(S)20.1(c), 72.1720.1(c), 72.17, 72.92Il.bI.c-General-program goals* Establishment of program-Organization and personnelresponsibilities-Training and instructionr Table 2 (Continued)OPERATIONSSubjectRegulatory GuideRegulatory PositionPortlons of 10 CFR Addressed8.10, Revision -R, Operating Philosophy forMaintaining Occupational Radiation Expo-sumas As Low As Is Reasonably AchievableL.a-Management commitmentI .b-AuditsI c1.dl.el.f2-Responsibilities-Training-RSO authority-Procedure modifications-Staff vigilance-Calibration frequency-Err6r limit-Documentation20.1(c), 72.1 S(aX8), 72.17,72.33(c)(S)20.1(c), 72.1S(aX8),72.33(c)(S)20.1(c), 72.15saX8), 72.17,72.33(bX4), 72.33(cXS),72.9219.12, 72.17(d), 72.33(bX4),72.9220.1(e), 72.15(a)(8),72.33(c)(S)20.1(c), 72.1 S(aX8),72.33(c)(5)20.1(c), 72.15(aX8),72.33(c)3), 72.33(cXS)20.103(aX3), 72.74(b)20.103(aX3), 72.74(b)20.103(a)(3), 72.74(b)(wRadiological Protection-Ar Sampling Instru-ments8.25) Calibration and Error Limits of AirSampling Instruments for Total Volumeof Air Sampled123Radiological Protection-Boassay8.9, Acceptable Concepts, Models, Equa-tions, and Assumptions for a BioassayProgramAll-Assumption, models, concepts 20.108, 72.15(aI2)20.108, 72.1 S(aX8)8.26, Applications of Bioassay for Fissionand Activation ProductsAll* Endorsement ofANSI N343-1978Radiological Protection-Evacuation Signal8.5, Revision 1, Criticality and OtherInterior Evacuation SignalsAU* Endorsement ofANSI/ANS N2.3-197972.74(b)Radiological Protection-Pocket Dosimeters8.4, Direct-Reading and Indirect-ReadingP6cket DosimetersI-Testing2Rejection20.202(a), 20.401,72.15(aX5)20.202(a), 20.401,72.1 S(aXS)20.202(a), 20.401,72.1 S(a(5)3-Mixed radiation fieldsii ..

4ho .,-Table 2 Continued)OPERATIONSSubjctRadiological Protection-Prenatal ExposureRegulary GuideRegulatory PositionPortions of 10 CFR Addressed19.1219.128.13j Revision, 1, Instruction Concerningi natal Radiation Exposure22-Instruction-ReasonsRadiological Protection-Respiratory Protection8.1 5)Acceptable Programs for RespiratoryPtotection12345678-Written policy-Equipment selection-Individual use of respirator-* Requirements of program* Equipment approval-Unapproved equipment-Protection factors-Technical requirements20.10320.10320.10320.10320.10320.10320.10320.103-tRadiological Protecton-SymbolSafeguards-AlannSystems8.1, Radiation Symbol5.44, Revision 2, Perimeter Intrusion AlarmSystemsGeneral20.20322-Qualification-Testing72.8172.81Safeguards-ContingeneyPlans5.55, Standard Format and Content of Safe-guards Contingency Plans for Fuel CycleFacilitiesAll-Contingency plans72.83Safeguards-Entry/ExitControl5.7, Revision 1, Entry/Exit Control forProtected Areas, Vital Areas, and MaterialAccess AreasI234-Protected Areas-Material Access Areas* Vital Areas-Emergency procedures72.8172.8172.8172.71(q), 72.81Safeguards-ocksS.12, General Use of Locks in the Protectionand Control of Facilities and Special NuclearMaterials1234* Combination locks-Combination padlocks-Key locks-Key padlocks72.8172.8172.8172.81 Table 2 (Continued)OPERATIONSSubjectReguiatoey GuldeRegulatory PositionPortlons of 10 CFR Addressed5678* Electric locks-Pushbutton mechanical locks-Mechanical locks-Combinations72.8172.8172.8172.81Safeguards-SecurityForce5.20, Training, Equipping, and Qualifyingof Guards and Watchmen1234-Preemployment screening-Training-Testing and requalification-Equipment72.8172.8172.8172.815.43, Plant Security Force Duties22-Oganization* Duties72.8172.81Safeguds-Trmngportatlon5.57, Revision 1, Shipping and ReceivingControl of Strategic Special NuclearMaterial1234-Preshipment controls on waste* Overchecks-Additional shipping controls-Receipts72.8172.8172.54, 72.8172.4, 72.81Safeguardo-ViualSurveillanceS 14, Revision 1, Use of Observation (VisualSurveillance) Techniques in Material AccessAreasI2-Operational measures-Aids to effective surveillance72.8172.81tqA A.-- X )

a IVALUE/IMPACT STATEMENT1. PROPOSED ACTION1.4 Decision on Proposed Action1.1 DescriptionThe storage of spent fuel in an independent spentfuel storage installation (ISFSI) is licensed under 10 CFRPart 72. For this type of installation, much of the materialin existing regulatory guides Is applicable. The proposedaction would be the ssuance of a regulatory guide thatwould identify the guides that are applicable to SFSls andthe extent of their applicability.-This guide is considered the most expeditious way toconvey to the public, the industry, and the staff the appli-cability of existing guidance to licensing actions pursuant toPart 72.2. TECHNICAL APPROACHThis guide addresses all technical subjects applicable toISFSls on which there is existing guidance.1.2 NeedApplications covering spent fuel storage in an ISFSI areexpected to be received in increasing quantity during thenext few years. The regulatory base applicable to SFSls isnot comparable to that for nuclear reactors, therefore, theissuance of this guide is a major step toward meeting thisdeficiency.1.3 Value/Impact Assessment1.3.1 NRCThe guidance provided by this guide is likely to expeditethe NRC staff's evaluation of the applications.1.3.2 Other Government Agencies3. PROCEDURAL APPROACHAmong the procedural alternatives considered formaking this guidance available, a regulatory guide wasdetermined to be the most appropriate.4. STATUTORY CONSIDERATIONS4.1 NRC AuthorityThe NRC derives its statutory authority from the AtomicEnergy Act of 1954, as amended, and the Energy Reorgani-zation Act of 1974, as amended, to provide guidance onacceptable means of meeting the requirements of itsregulations.None.4.2 Need for NEPA Assessment1.3.3 IndustryThis guide will be of particular value to industry sincethere are no precedents specifically applicable to a licenseapplication under 10 CFR Part 72.1.3.4 WorkersThe principle of maintaining occupational exposures aslow as is reasonably achievable (ALARA) Is covered in theproposed document.1.3.S PublicThis guide is designed primarily for the protection ofthe public and the environment.The issuance of this guide is not a major action asdefined in paragraph 15(a) of 10 CFR Part 5 1, hence, theaction does not require an environmental impact statement.S. RELATIONSHIP TO OTHER EXISTING ORPROPOSED REGULATIONS OR POLICIESThis guide is one of a series of guides on the storage ofspent fuel in an ISFSL6. SUMMARY AND CONCLUSIONSThis guide is the most expeditious way of establishingpart of the regulatory base required for the licensing of thestorage of spent fuel in an ISFSI3.53-18


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