ML20214A577

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Board Exhibit B-8,consisting of Partial Reg Guide 1.61, Damping Values for Seismic Design of Nuclear Power Plants, Dtd Oct 1973
ML20214A577
Person / Time
Site: Braidwood  Constellation icon.png
Issue date: 11/05/1986
From:
US ATOMIC ENERGY COMMISSION (AEC)
To:
References
RTR-REGGD-01.061, RTR-REGGD-1.061 OL-B-008, OL-B-8, NUDOCS 8705190504
Download: ML20214A577 (2)


Text

{{#Wiki_filter:. e s w/s/rs y-g %g n O,,e,,,,,,n /e 0.s. Avoasse sessney coasassessom j REGULATORY G.UIDE k,,j: eenscrionaTu or noeuunomy sTamoanos ~87 APR 24 P4 :43 REQULATOnY GUIDE 1.81 DAMPlNG VALUES FOR SElSMIC DESIGN OF NUCt.Eh[@VER. PLANTS f ~ iens - A. INTRODUCTION dissipation in the analytical model equivalent to that i expected to occur as a result of material and structural Criterion 2. " Design Bases for Protection Against damping in the real structure. Natural Phenomena," of Appendix A. " General Damien Crttena for Nuclear Power Plants " to 10 CFR Part 50, After reviewing a number of applications for j "uoansing of Production and Utilisation Facilities," mastruction pernuts and operating licennes and after requires, in part, that nuclear power plant structures, reviewing portinent literstum including Reference 1. the l i systems, and components important to safety be AEC Repdatory staff has determhud as acceptable, for desipied to withstand the effects of 4 '- Interim use, the modal damping values shown in Table 1 / Proposed Appendix A. " Seismic and Geologic Sting of this pdde. Thsee modal damping values should be Criteria," to 10CFR Part 100," Reactor Ste Criteria," used for aR modes considsad la elastic spectral or would roquare, in part, that suitable seisniic dynamac time. history dynande analyses. Values are tabulated for analysis, such as a time history or spectral response the two earthquakes, the Safe Shutdown Earthquake analysis, be performed to demonstrate that the and the Operating Basis Earthquake (or M the Safe structures, systems, and componssta important to safety Shutdown Earthquake), far which nuclear power plants will remmia functionalin the event of a Safe Shutdown are required to be desissed as specified in propowd Earthquake (SSE). This pdde delinestes damping values Appendix A to 10 CFR Part 100,"Seismac and Geologic acceptable to the AEC Regulatory staN to be used in the Sting Criteria." elastic model dynernic seismic analysis of Sciende Category I' structures, systerns, and components. The . EGMATOnY POOmON Advisory Co.nmittee on Reactor Safeguards has been

l. The modal damping values expressed as a percentage t

pod of critical damping shown la Table 1 of this guide should be used for viscous modal damping for all modes B. DISCUSS 8CN considend in an elastic spectral or time history dynamic minnic of the Seismic Categuy I uructuus m The energy dissipation within a structure due to components specined in the table. The modal damping l material and structural dampwg while it is responding to m specined la Table I am for m in the dynamic an earthqe depends on a number of factcs such as aan ym anciated with two Mmnt rnaputudn of i . types of joints or connectforts wfCJn the structme, the eenhquakes, tle Safe Steadown Earthquake and the structural matenal, and the magmtude of defor astions Operating Basis Earthquake (or M the Safe Shutdown i experienced. In a dynamic elastic s.aelysts, tnt energy Earthquake). Thsee analyus would be required by r I deipation usually is accounted for ty s,n.t<ying an amount of viscous damping that would result in energy pr p sed Appendix A to,10 CFR Part 100,"Setsmic and Geologic Siting Criteria. 'Structurse, systems, and compensees of a mucieur powet 2. Demping values higher than the ones dehneated in j pieni that ase aadr==aad as Seemine Category I are dedened to Table I of this guide may be used in a dynanuc scarrue unthesand the erfects of the Safe Shuedoes Earthquake (SSE) and renwa functional (see Regulatory Guide 1.29. "Sakunic analysis if documented test data are provided to support i i pes.yi Ctsannetton"), higher values. f usasc neouLAtosty euess c w ma w , n. ia ,.= = r ".' ' r.n.:

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r~ l .l. If the m.aumum combmed stresses due to static. dampng values lower than those speciAnd in Table I of msmie, and other dynamic loading are sgm8cently tids gWde should be used for that structure or - hwer llun the yield stres and % yield strees for SSE and P to suoid underestispedag the emplitude of % SSI'. respectively, in any structure or <==ramant. voirations or W sassess, c l i 1 TASt.E 1 1 DAartNG VALUES' i (Peroent of Critient Damping) ossruine emis sees samassius sonnessne er n seg sirustwo or ceassamas anunemma senseems Een8* 'ho 8 Equipment and large.dlameter piping sysseau. 3 pipe diameter yester then 12 in............ 2 Small-diameter piping systems. diesmatar aquel 1 2 to or less then 12 in. 4 Welded steel structures................... 2 Iloited steel structures................... 4 7 Prestressed concrete structures............. 2 5 4 7 Reinforced concrete structures........,.... ' Taber i is destead freen the ressemandmeines does in Refesamme 1. 'le' the dyesmic anstre6e of active e es duftmed in llegutneury Guide 1.4 temme vatens absmid she to and Aur SM. elecludes both materni sad aristurel damping. If the pipdag ersteun ammaises es est ens er tsue ageIn wie telle sausammi as.iping, use vennes for senaHinnement ydphus. l f u g M b 4 4 i ( REFERENCE yN-v . l

1. 'Newmark N. M., John A. Blume, and Kanwar K. Kapur, h.Ih g o} o' M

" Design bsponse Spectre for Nuclear Power Fleets, ASCE i j j, 8 3z gjg Structural Basiseenas Meeting. San Francuso, Apnl 1973. s s se n== a i

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