ML18191A087

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Provide 70 Copies of 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
ML18191A087
Person / Time
Site: Nine Mile Point, Columbia, Limerick, LaSalle, Zimmer, Shoreham, Bailly  File:Long Island Lighting Company icon.png
Issue date: 07/28/1978
From: Sobon L
General Electric Co
To: Stolz J
Office of Nuclear Reactor Regulation
References
MFN-315-78, NEDO-23834
Download: ML18191A087 (5)


Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS )

DISTRIBUTION FGR INCOMING MATERIAL TOPREP REC:

STOLZ J F

NRC ORG:

SOBON L J GEN ELEC DOCDATE: 07/28/78 DATE RCVD: 08/02/78 DOCTYPE:

LETTER NOTARIZED:

NQ COPIES RECEIVED

SUBJECT:

LTR i ENCL 70 FORWARDING GE MARK II CONTAINMENT PROGRAM REPT ENTITLED: "FLUID STRUCTURE INTERACTION ANALYSI OF RAMSl.lEAD SAFETY RELIEF VALVE DISCl-IARGE IN MARK I STEEL CONTAINMENT TORUS> "

Na DO 23834)

JUNE i978.

REVIEWER INITIAL: XJM DISTRIBUTOR INITIAL:~

DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS TOPICAL RPTS

& CORRESPONDENCE RE MARK II CONTAINMENT

<DISTRIBUTION CODE T002)

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782 00 7 THE END

'I IlHgi%i GENERAL

ELECTRIC GENERAL ELECTRIC COMPANY, 175 CURTNER AVE., SAN JOSE, CALIFORNIA95125 MC 681, (408) 925-3495 NUCLEAR ENERGY PROJECTS DIVISION MFN-315-78 July 28, 1978 Attention:

U.

S. Nuclear Regulatory Commission Division of Project Management Office of Nuclear Reactor Regulation Washington, D.C.

20555 Mr. John F. Stolz (Chief)

Light Water Reactors Branch No.

1 Gentlemen:

SUBJECT:

Reference:

MARK II CONTAINMENT PROGRAM REPORT, "FLUID STRUCTURE INTERACTION ANALYSIS OF RAMSHEAD SAFETY RELIEF VALVE DISCHARGE IN MARK I-STEEL'ONTAINMENT 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.

752150077

/o>

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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 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)

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REVIEWER Iihl1TIAL:

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