ML18018A895

Forwarding GE Mark II Containment Program Rept Entitled: Fluid - Structure Interaction Analysis of Ramshead Safety Relief Valve Discharge in Mark I Steel Containment Torus, NEDO-23834, June 1973

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

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r/~jzso REGULATORY INFORMATION DISTRIBUTION SYSTEM (AIDS)

DISTRIBUTION FGR INCOMING MATERIAL TOPREP REC:

STOLZ J F NRC ORG:

SGBON L J GEN ELEC DOCDATE: 07/28/ 78 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: XJM DISTRIBUTOR INITIAL:~

DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS TOPICAL RPTS 8c CORR-SPGNDENCE RL= MARK II CONTAINMENT

<DISTRIBUTION CODE T002)

INTERNAL:

EXTERNAL:

REG FILE4+W/0 ENCL 50-322 FILE++LTR ONLY 50-353 FILE+4LTR ONLY 50-367 FILE++LTR ONLY FILE44LTR ONLY 0-410 ILE++LTR ONLY RU RAL ENG BR++W/2 ENCL AD FOR ENG++W/2 ENCL I PELT IER+4 W/ENCL J SNELL++W/ENCL W KANE+4WfENCL D TIBBETTS++W/ENCL D VASSALLO4+LTR ONLY LWR53 CHIEF++LTR ONLY AD FOR PLANT SYSTEMS+4LTR ONLY W PIKE++LTR ONLY 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 RICHLANDtWA-PDR++WfENCL OSWEGO'Y-PDR+4W/ENCL TERA++WfENCL NSIC+4W/ENCL ACRS CAT

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782150077 THE END

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6 EN ERAL I

ELECTRIC N'U'CL'E'AR ENERGY GENERAL ELECTRIC COMPANY, 175 CURTNER AVE., SAN JOSE, CALIFORNIA95125 MC 681, (408) 925-3495 PROJECTS DIVISION 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:

Reference:

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 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.

782150077 Qo>

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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:

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