ML18018A895
| ML18018A895 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 07/28/1978 |
| From: | Sobon L General Electric Co |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| MFN-315-78 | |
| Download: ML18018A895 (6) | |
Text
li p, c r/~ jzso REGULATORY INFORMATION DISTRIBUTION SYSTEM (AIDS)
DISTRIBUTION FGR INCOMING MATERIAL TOPREP REC: STOLZ J F ORG: SGBON L J DOCDATE: 07/28/ 78 NRC GEN ELEC DATE RCVD: 08/02/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR 1 ENCL 70 FORWARDING GE MARK lI CONTAINMENT PROGRAM REPT ENTITLED: "FLUID STRUCTURE INTERACTION ANALYol OF RAMSI.IEAD SAFETY RELIEF VALVE DISCI.IARGE IN MARK I STEEL
- CONTAINMENT TORUS( " NEDO-23334'UNE 197$ .
REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:~
DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS TOPICAL RPTS 8c CORR-SPGNDENCE RL= MARK II CONTAINMENT
<DISTRIBUTION CODE T002)
INTERNAL: REG FILE4+W/0 ENCL CENTRAL FILE++W/2 ENCL 50-322 FILE++LTR ONLY 50-352 FILE+4LTR ONLY 50-353 FILE+4LTR ONLY 50-358 FILE4+LTR ONLY 50-367 FILE++LTR ONLY 50-373 FILE+4LTR ONLY FILE44LTR ONLY 50-397 FILE44LTR Oh!LY 0-410 ILE++LTR ONLY NRC PDR++Wf ENCL RU RAL ENG BR++W/2 ENCL CONTAINMENT SYSTEMS+<W/7 ENCL AD FOR ENG++W/2 ENCL C ANDERSQN~~W/ENCL I PELT IER+4 W/ENCL M D LYNCH++W/ENCL J SNELL++W/ENCL A BGURNIA~~W/ENCL W KANE+4 WfENCL S MINER4+W/ENCL D TIBBETTS++W/ENCL DEPUTY DIR DPM++LTR ONLY D VASSALLO4+LTR ONLY LWR52 CHIEF+4LTR ONLY LWR53 CHIEF++LTR ONLY LWR01 CHIEF+MTR ONLY AD FOR PLANT SYSTEMS+4LTR ONLY M RUSIIBROGK+4LTR ONLY W PIKE++LTR ONLY LWR04 CHIEF++LTR ONLY EXTERNAL: LPQ& 8 3 PORT JEFFERSON-.PDR++W/ENCL POT<TSTQWNi PA-PDR++WfENCL BATAVIAiOH-PDR+4W/ENCL CHESTERTON'N-PDR++W/ENCL GGLESBYi IL-PDR4+WfENCL RICHLANDt WA-PDR++WfENCL OSWEGO'Y-PDR+4W/ENCL TERA++WfENCL NSIC+4W/ENCL ACRS CAT ++Wf 16 ENCL DISTRIBUTION: LTR 65 ENCL 47 CONTROL NBR: 782150077 SIZE: 2P+36P THE END
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6 EN ERAL I ELECTRIC N'U'CL'E'AR ENERGY PROJECTS DIVISION GENERAL ELECTRIC COMPANY, 175 CURTNER AVE., SAN JOSE, CALIFORNIA 95125 MC 681, (408) 925-3495 MFN-315-78 July 28, 1978 U. S. Nuclear Regulatory Commission Division of Project Management Office of Nuclear Reactor Regulation Mashington, D.C. 20555
.Attention: Mr. John F. Stolz (Chief)
Light Mater Reactors Branch No. 1 Gentl emen:
SUBJECT:
MARK II CONTAINMENT PROGRAM REPORT, "FLUID STRUCTURE INTERACTION ANALYSIS OF RAMSHEAD SAFETY RELIEF VALVE DISCHARGE IN MARK I STEEL CONTAINMENT TORUS," NEDO"23834, JUNE 1978
Reference:
Letter with report, "Mark II Containment Program Report,
'Fluid Structure Interaction Analysis of Ramshead Safety Relief Valve Discharge in Mark I Steel Containment Torus,'ED0-23834, June 1978," to J. F. Stolz (NRC) from L. H. Sobon (GE), dated July 7, 1978 Seventy (70) copies of the subject report (NEDO-23834) are being provided by General Electric Company on behalf of the Mark II Owners Group for your review, as part of the Mark II Containment Supporting Program, Task B. 10. This report presents the results of an analysis of the fluid-structure interaction (FSI) effects on the major wall pressure data from safety relief valve (SRV) discharge. The studies conclude that FSI effects in the Mark I SRV tests were not significant and that this data can be used as a benchmark for the Mark II ramshead load prediction methodology.
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GENERAL@ELECTRIC U.S. Nuclear Regulatory Commission Page 2 July 28, 1978 The enclosed copies of NEDO-23834 are the printed versions of the ten (10) advance copies sent to you on July 7, 1978 (reference). Please discard or return the advance copies.
Since ely, L. J. Sobon, Manage BMR Containment Licensing Containment Improvement Programs 4
LJs:bp/1290 Enclosures (70) cc: C. J. Anderson (NRC)
H. C. Brinkmann (Mark II Owners Group)
H. Chau (Mark II Owners Group)
L. S. Gifford (GE, Bethesda)
I. A. Peltier (NRC)
R. L. Tedesco (NRC)
File: 3.2.7. c