ML18191A093
| ML18191A093 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 05/01/1978 |
| From: | Sobon L General Electric Co |
| To: | Knight J Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18191A093 (4) | |
Text
uS f4/ep REGULATORY INFORMATION DISTRIBUTIGtI SY TEM (RIDS )
DISTRIBUTION FOR INCOMING IIATERIAL TOPRFP PFC:
KNIGHT J P
NRC ORG:
SQBGhl L J GEN ELEC DGCDATE: 05/01/78 DATE RCVD: 05/1 1/78 DGCTYPE:
LETTER NOTARIZED:
NO COPIES RECEIVED
SUBJECT:
LTR 1
El'lCL 70 FORWARDING G. E.
E XECTIVE SUi IMARY REPT AND SUPPLEI'IENT ENTITLED:
"TECH IN I CAL BASIS FGR THE SRSS METHOD OF COMBINING DYNAtIIC RESPONSE" r
DTD APRIL(
1: 78r IN SUPPORT OF THE MARK II SUBJECT REPT AND FGR GENERIC CQNSIDERATIGN.
REVIEWER INITIAL: XJt'I DISTRIBUTOR IN1TIAL:~
DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS TOPICAL RPTS
- 8. CORRESPONDENCE RE MARK Il CONTAINMENT
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E I. E C QglJgg(Y gft ENERGY GENERAL'ELECTRIC COMPANY, 175 CURTNER AVE., SAN JOSE, CALIFORNIA95125 MC 681, (408) 925-3495 PROJECTS DIVISION MFN-180- 78 Nay 1, 1978 U. S. Nuclear Regulatory Commission Division of Systems Safety Office of Nuclear Reactor Regulation Washington, D.
C.
20555 Attention:
Nr. J.
P. Knight Assistant Director For Engineering
~~ ~J
~P.l f1'entlemen:
SUBJECT:
Reference:
EXECUTIVE
SUMMARY
REPORT AND SUPPLEMENT ENTITLED, "TECHNICAL BASIS FOR THE SRSS METHOD OF COMBINING DYNAMIC RESPONSE",
DATED APRIL 1978
- Letter, LJ Sobon to Olan Parr, dated 8/1/77 transmitting GE Report NEDE-24010-P, "Technical Basis For The Use Of The Square-Root Of The Sum Of Squares (SRSS)
Method For Combining Dynamic Loads On Mark II Plants-July 1977" Seventy copies of the subject Summary Report are being provided by General Electric in support of the above referenced Nark II report and for generic consideration.
The purpose of this Executive Summary Report is to highlight the signi-ficant results and conclusions of the Mark II SRSS study and to present important information from subsequent technical studies.
A key result that quantitatively demonstrates the dynamic design margin inherent in nuclear plant structures designed to meet ASNE Code (or equivalent) stress limits is shown to be related to the energy absorption capability of the component.
For structures exhibiting even moderately ductile behavior, this margin is significantly greater than the ratio of static failure stress to code allowable, and therefore assures sufficient addi-tional margin to protect against structural failure even in the unlikely event that peak combined dynamic response exceeds the SRSS value.
Based on the material presented in this Summary Report, it is concluded that the use of SRSS method is technically justifiable and represents a
prudent and practical engineering approach for the combination of dynamic responses originating from earthquake, LOCA transient and SRV discharge loadings.
78 1 310029
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4
GENERAL O'LECTRIC U. S. Nuclear Regulatory Commission Mr. J.
P. Knight May 1, 1978 Page 2
Any questions regarding this Summary Report should be directed to K.
G. Hazifotis, Containment Licensing Engineer, (408) 925-2209.
Sincerely, L. J.
- Sobon, Manager BWR Containment Licensing Containment Improvement Programs LJS;gmm/901-902
Enclosures:
Seventy cc:
R. J. Mattson (NRC)
R. L. Tedesco (NRC C. Anderson (NRC)
T.
M.
Su (NRC)
I. Sihweil (NRC)
R. J.
Bosnak (NRC)
J.
C. Guibert (NRC)
R.
S.
Boyd (NRC)
R.
C.
DeYoung (NRC)
L. S. Gifford (GE-BETH)
File 2.10