ML20083Q452

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Rev Oa to Nuclear Guide 1.61, Damping Values for Seismic Design of Nuclear Power Plants
ML20083Q452
Person / Time
Site: Oconee, Mcguire, Catawba, McGuire, 05000000, Cherokee
Issue date: 01/06/1983
From:
DUKE POWER CO.
To:
Shared Package
ML20083Q427 List:
References
1.61, NUDOCS 8302250400
Download: ML20083Q452 (7)
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Nuclear Guide 1.61

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NUCLEAR GUIDE Effective Date 1/6/83 Revision OA 2

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Title:

Damping' Values for Seismic Design of Nuclear Power Plants Reference NRC Regulatory Guide Number 1.61 Revision 0

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DUKE POWER NUCLEAR GUIDE 1.61 The following requirements shall apply for damping values used in seismic analysis of all Seismic Category I structures or components at Duke Power Company's McGuire and Catawba Nuclear stations. These requirements are in lieu of those specified in USAEC Regulatory Guide 1.61.

1.

The modal damping values expressed as a percentage of critical damping shown in Tables A & B of this guide should be used for viscous modal damping for all modes considered in t.n elastic 1

spectral or time-history dynamic seismic analysis of the Seismic Category I structures or components specified in the tables. The modal damping values specified in Tables A & B are for use in the dynamic analyses associated with two different magnitudes of earthquakes, the Safe Shutdown Earthquake and the Operating Basis Earthquake.

2.

Damping values higher than the ones delineated in Tables A & B i

of this guide may be used in a dynamic seismic analysis if documented test data are provided to support higher values.

3.

If the maximum combined stresses due to static, seismic, and other dynamic loading are significantly lower than the yield stress and 1/2 yield stress for SSE and OBE, respectively, in any structure

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or component, damping values lower than those specified in Tables A & B of this guide should be used for that structure or component to avoid underestimating the amplitude of vibrations or dynamic stresses.

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TABLE A MCGUIRE NUCLEAR STATION DAMPING VALUES (Percent of Critical Damping)

Operating Basis Safe Shutdown Structure or Component Earthquake Earthquake Equipment and large-diameter piping systems, pipe diameter greater than 2

2 12 in.

Small-diameter piping systems, diameter equal to or less than 1

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12 in.

Containment vessel 1

1 Welded steel structures......

2 2

Bolted steel structures......

4 7

Reinforced concrete structures 5

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4 TABLE B CATAWBA NUCLEAR STATION DAMPING VALUES (Percent of Critical Damping)

Operating Basis Safe Shutdown Structure or Component Earthquake Earthquake Equipment, components and large-diameter piping systems, pipe 2

2 diameter greater than 12-in.....

Primary coolant loop........

0.5 1

i Small-diameter piping systems, diameter equal to or less than 1

1 12 in.

Containment vessel.........

1 2

Welded steel structures 2

2 Bolted steel structures 5

5 Reinforced concrete structures...

5 5

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.r Omober M U.S. ATOMIC ENERGY COMMISSION t

a r REGULATORY GUIDE o,4res o,! _

DIRECTORATE OF REGULATORY STANDARDS n

REGULATORY GUIDE 1.61 DAMPING VALUES FOR SEISMIC DESIGN OF NUCLEAR POWER PLANTS A. INTRODUCTION dissipation in the analytical model equivalent to that 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 Design Criteria for Nuclear Power Plants." to 10 CFR Part 50 After reviewing a number of applications for

" Licensing of Production and Utilization Facilities,"

construction permits and operating licenses and after requires, in part, that nuclear power plant structures, reviewing pertinent literature including Reference I,the systems, and components important to safety be AEC Regulatory staff has determined as acceptable, for designed to withstand the effects of earthquakes.

Interim use, the modal damping values shown in Table 1 Proposed Appendix A, " Seismic and Geologic Siting of this guide. These modal damping values should be Criteria," to 10 CFR Part 100," Reactor Site Criteria,"

used for all modes considered in clastic spectral or would require, in part, that suitab*e seismic dynamic time history dynamic 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 Opera'.ing Basis Earthquake (or % the Safe structures, systems, and componer.ts important to safety Shutdown Earthquake), for which nuclear power plants will remain functionalin the event of a Safe Shutdown are required to be designed as specified in proposed Earthquake (SSE). This guide delineates damping values Appendix A to 10 CFR Part 100," Seismic and Geologic acceptable to the AEC Regulatory staff to be used in the Siting Criteria."

elastic modal dynamic seismic analysis of Seismic Category I' structures, systems, and components. The C. REGULATORY POSITION Advisory Committee on Reactor Safeguards has been consulted conceming this guide and has concurred in the 1.

The modal damping values expressed as a percentage regulatory position.

of cr tical damping shownin Table 1 of this guide should be used for viscous modal damping for all modes 8

considered in an clastic spectral or time history dynamic se sm analys f tk Seismk Category I stmetmo or The energy dissipation within a structure due to l

material and structural damping while it is responding to e mp nents specified in the table. The modal damping an earthquake depends on a number of factors such as valuu 8PecWied b TaWe I are br un in de @namk types of joints or connections within the structure, the analysn au cisted wu two dWennt magnMn of can a n,the a utdown Ean%uah aM the structural material, and the magnitude of deformatiuns

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  • dissipation usually is accounted for by sPecify1'nE an proposed Appendix A to 10 CFR Part 100,.". Seismi amount of viscous damping that would result in energy Geologic Siting Criteria."

' Structures..ystems, and components of a nuclear power 2.

Damping values higher than the ones delineated in plant that are designated as Seismic Category I are designed to Table I of this Iuide may be used in a dynamic seismic withstand the effects of the Safe Shutdown Earthquake rSSE) analys...f documented test data are provided to support ts i and remain functional (see Regulatory Guide 1.29, Scismk Design Clauifiestion").

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11 the maximum combined stresses due to static, damping values lower than those specified in Table I of seismie, and other dynamic loading are significantly this guide should be used for that structure or lowei.1 in the yield st:.ss and % yield stress for SSE and component to avoid underestimating the amplitude of

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% SSE, respectively, in any structure or component, vibrations or dynamic stresses.

TABLE 1 DAMPlNG VALUES' (Percent of Critical Damping)

Operating Basis Earthquake or % Sete Safe Shutdown 8

Structure or Component Shutdown Earthquake Earthquake 8

Equipment and large diameter piping systems,

pipe diameter greater than 12 in............

2 3

Small diameter piping systems, diameter equal to or less than 12 in.

I 2

Welded st eel structures...................

2 4

f 7

Bol ted st eel structures...................

4 Prestressed concrete structures.............

2 5

Reinforced concrete structures 4

7

' Table I is derived from the recommendations given in Reference 1.

81n the dynamic analysis of active components as defined in Regulatory Guide 1.4f1.these values should also be used for SSE.

sindudes both materbt and structural damping. If the piping system consists of only one or two spans with little structurat iLampuig, use salues tor small db;.icter piping.

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l REFERENCE I.

Newmark, N. M., John A. Blume, and Kanwar K. Kapur.

    • Design Response Spectra for Nuclear Power Plants." ASCE l

l Structural Engineering Meeting, San Franeiwo April 1973.

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