NRC Generic Letter 1979-04

NRC Generic Letter 1979-004: Modification to Review & Acceptance of Spent Fuel Storage & Handling Applications

ML031290521
Person / Time
Site:	Beaver Valley, Hatch, Monticello, Dresden, Peach Bottom, Browns Ferry, Salem, Nine Mile Point, Indian Point, Kewaunee, Point Beach, Cooper, Pilgrim, Prairie Island, Brunswick, Surry, Turkey Point, Vermont Yankee, Duane Arnold, Farley, Robinson, Cook, Quad Cities, Humboldt Bay, Zion, FitzPatrick, 05000000, Trojan
Issue date:	01/18/1979
From:	Grimes B K Office of Nuclear Reactor Regulation
To:
References
NUDOCS 7903080173, GL-79-004
Download: ML031290521 (4)

06-S4 S16-3(o .UNITED STATESAt NUCLEAR REGULATORY COMMISSIONj 1J 0 WASHINGTON, D. C. 20555January 18, 1979To All Power Reactor LicenseesGentlemen:Our letter of April 14, 1978, provided NRC Guidance entitled,"Review and Acceptance of Spent Fuel Storage and HandlingApplications." Enclosed are modifications to this documentfor your information and use. These involve pages IV-5 andIV-6 of the document and comprise modified rationale andcorrections.oe~--z- 79- V

Sincerely,_ 2-7Brian K. Grimes, Assistant Directorfor Engineering and ProjectsDivision of Operating Reactors

Enclosure:

Pages IV-5 and IV-6cc w/enclosure:Service List92903080173 In order to determine the flexibility of the pool wall it isacceptable for the licensee to use equivalent mass and stiffnessproperties obtained from calculations similar to those described in"Introduction to Structural Dynamics" by J. M. Biggs published byMcGraw Hill Book Company. Should the fundamental frequency ofthe pool wall model be higher than or equal to 33 Hertz, it maybe assumed that the response of the pool wall and the corres-ponding lateral support to the new rack system are identical tothose of the base slab, for which appropriate floor responsespectra or ground response spectra may already exist.(6) Structural Acceptance CriteriaWhen AISC Code procedures are adopted, the structural acceptancecriteria are those given in Section 3.8.4.I.5 of the StandardReview Plan for steel and concrete structures. For stainlesssteel the acceptance criteria expressed as a percentage of yieldstress should satisfy Section 3.8.4.Il.5 of the Standard ReviewPlan. When subsection NF,Section III, of the ASME B&PV Code isused for the racks, the structural acceptance criteria are thosegiven in the Table below. When buckling loads are considered in thedesign, the structural acceptance criteria shall be limited by therequirements of Appendix XVII-2110(b) of the ASME Boiler and PressureVessel Code.For impact loading the ductility ratios utilized to absorb kineticenergy in the tensile, flexural, compressive, and shearing modesshould be quantified. When considering the effects of seismicloads, factors of safety against gross sliding and overturning ofracks and rack modules under all probable service conditions shallbe in accordance with the Section 3.8.5.II-5 of the Standard ReviewPlan. This position on factors of safety against sliding and tiltingneed not be met provided any one of the following conditions is met:(a) it can be shown by detailed nonlinear dynamic analyses thatthe amplitudes of sliding motion are minimal, and impactbetween adjacent rack modules or between a rack module andthe pool walls is prevented provided that the factors ofsafety against tilting are within the values permitted bySection 3.8.5.Il.5 of the Standard Review Plan.(b) it can be shown that any sliding and tilting motion will becontained within suitable geometric constraints such asthermal clearances, and that any impact due to the clear-ances is incorporated.(7) Materials, Quality Control, and Special Construction Techniques:The materials, quality control procedures, and any special con-struction techniques should be described. The sequence of in-stallation of the new fuel racks, and a description of the pre-cautions to be taken to prevent damage to the stored fuel duringIV-5 TABLELoad CombinationElastic AnalysisAcceptance LimitNormal limits of NF 3231 .aD + LD + L + ENormal limits of NF 3231 .1aD + L + ToLesser of 2Sy or Su stress rangeD + L + To + ED + L + Ta + ED + L + Ta + ELesser of 2Sy or Su stress rangeLesser of 2Sy or Su stress rangeFaulted condition limits ofNF 3231.1cLimit Analysis1.7 (D + L)1.7 (D + L + E)Limits of XVII-4000 of Appendix XVIIof ASME Code Section III1 .3 (D + L + To)1.3 (D + L + E + To)1.1 (D + L + Ta + E)Notes: 1. The abbreviations in the table above are those used inSection 3.8.4 of the Standard Review Plan where each termis defined except for Ta which is defined as the highesttemperature associated with the postulated abnormal designconditions.2. Deformation limits specified by the Design Specificationlimits shall be satisfied, and such deformation limitsshould preclude damage to the fuel assemblies.3. The provisions of NF 3231.1 shall be amended by therequirements of the paragraphs c.2, 3, and 4 of theRegulatory Guide 1.124 entitled "Design Limits and LoadCombinations for Class 1 Linear-Type Component Supports."IV-6 JConsolidated Edison Company --of New York, Inc.cc: White Plains Public Library100 Martine AvenueWhite Plains, New York 10601Joseph D. Block, Esq.Executive Vice President -AdministrationConsolidated Edison Companyof New York, Inc.4 Irving PlaceNew York, New York 10003Edward J. Sack, Esq.Law DepartmentConsolidated Edison Companyof New York, Inc.4 Irving PlaceNew York, Hew York 10003Anthony Z. RoismanNatural Resources Defense Council917 -15th Street, NWWashington, D.C. 20005Paul S. Shemin, EsquireAssistant Attorney GeneralState of Hew YorkDepartment of LawTwo World Trade CenterNew York, New York 10047Sarah Chasis, Esquire-Natural Resources Defense Council122 East 42nd StreetNew York, New York 10017Theodore A. RebelwoskiUSNRCP. 0. Box 38Buchanan, New York 10511