ML19276E695

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Summary of 790206-07 Meetings W/Detroit Edison to Discuss Calculated Asymmetric Loads on Reactor Vessel Support Caused by Break of Primary Sys Pipe Near Reactor Vessel Nozzle, & Hydrodynamic Loads on Torus & Components
ML19276E695
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 02/28/1979
From: Kintner L
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 7903200278
Download: ML19276E695 (5)


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NUCLEAR REGULATORY COMMisslON

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FEB 2 81973 Docket No:

50-341 APPLICANT: Detroit Edison Company FACILITY:

Enrico Fermi Atomic Power Plant Unit 2

SUBJECT:

SUMMARY

OF MEETINGS WITH NRC ON FEBRUARY 6 AND FEBRUARY 7,1979 The meeting on February 6,1979 was held to discuss the calculated asymmetric loads on the reactor vessel support and other primary system components and supports caused by a postulated break of a primary system pipe near the reactor vessel nozzle. Enclosure 1 is a list of attendees.

The applicant and its contractors (Nuclear Utility Services, Sargent

& Lundy, and General Electric) presented sumaries of their calculations.

Reports by Detroit Edison, Nuclear Utility Services and Sargent & Lundy have been filled; the General Electric report of loads on the reactor vessel support and reactor vessel internals is scheduled for submittal during April 1979. The applicant provided responses to the staff's questions on:

the method of computing loads from the annulus pressure distribution; effect of annulus gas temperature increase on results; effect of a break at the weld joining the stainless steel piping to the carbon steel nozzle; desion of reactor vessel to support skirt transition; fuel assembly hudraulic ioading; buckling forces acting on reactor vessel skirt; lifting forces acting on the fuel assembly; and the comparison of sacrificial shield structural design to criteria in the NRC Structural Engineering Branch Document B.

The meeting on February 7,1979 was held to discuss the calculated hydro-dynamic loads on the modified containment torus, torus supports, piping systems, and components caused by a postulated loss of coolant accident and safety / relief valve actuation. is a list of attendees.

A description of the calculations and modifications has been filed in Amendment 12.

In response to the staff's questions the applicant stated that the effect of torus motion during the postulated accident on emergency core cooling system piping and components external to the torus has been accounted for by using a design vertical motion of 0.25 inches at the connecticn to the torus.

(Reported in FSAR Section 3.8' The applicant also briefly described the basis for the reactor i cernals vibration assurance program (NEDE 2dO57-P) and the feedwater sparger design and analysis (NEDE-21821).

The applicant responded to questions raised by the Quality Assurance Branch regarding the piping preoperational vibration program.

7003200 M N FEB 2 8 ;g, g The staff described its need for additional information regarding the capability of seismic Category I equipment to withstand the combined loading due to carthquakes and hydrodynamic vibratory loads associated with the response of pressure suppression pools to safety / relief dis-charge loads. The staff said it expected to send a request for this additional information shortly.

The applicant has agreed to provide a letter surmiarizing significant information transmitted in the meeting including a copy of significant slides.

)'l tRew L. L. Kintner, Project Manager Light Water Reactors Branch No. 1 Division of Project Management Enclosures :

1.

Attendance List for February 6,1979 meeting 2.

Attendance List for February 7, 1979 meeting CC" See next page

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r..37,e 4. Jens FEB 2 81979 4.

'..' ay n e ". J e n s Mr. Jeffrey A. Alson J.ssistan: Vice President 772 Green Street, Building 4 Engineering & Construction

.Ypsilanti, Michigan 48197 Detroit Edison Company 2300 Second Avenue Mr. David Hiller Detroit, Michigan 48226 University of MichigrA Law School cc:

Eugune B. Thomas, Jr., Esq.

Hutchins Hall LeBoeuf, Lamb, Leiby & MacRae Ann Arbor, Michigan 48109 1757 N. Street, N.W.'

Washington, D. C.

20036 Mrs. Martha Drake 230 Fairview Peter A. Marquardt, Esq.

Petoskey, Michiaan 49770 Co-Counsel The Detroit Edison Company 2000 Second Avenue Detroit, Michigan 48226 Mr. William J. Fahrner Project Manager - Fermi 2 The Detroit Edison' Company 2000 Second Avenue Detroit, Michigan 48226 Larry E. Schuerman Licensing Engineer - Fermi 2 Detroit Edison Company 2000 Second Avenue Detroit Michigan 48226 Charles Bechhoefer, Esq., Chairman Atomic Safety & Licensing Board Panel V. S. Nuclear Regulatory Commission Washington, D. C.

20555 Dr. David R. Schnik Department of Oceanography Texas A & M University College Station, Texas 77840 Mr. Frederick J. Shon Atomic Safety & Licensing Board

?anel U. S. Nuclear Regulatory Ccmmission Washington, D. C.

20555

ENCLOSURE 1 ATTENDANCE LIST FOR FERfil 2 MEETING FEBRUARY 6, 1979 NRC Detroit Edison General Electric A. Bates (ACRS)

M. Batch R. L. Smith E. D. Throm D. Lehnert R. Villa J. Guttmann L. Schuerman R. A. Hill T. Huang E. Lusis C. P. Tan J. Casiglia P. Y. Chen F. C. Cherny K. Desai R. Bosnak L. Kintner J. Kudrick S. B. Kim D. Houston Saraent & Lundr Nuclear Utility Services R. Cheboub T. R. Hencey E. R. Schmidt

ENCLOSURF 2 ATTENDANCE LIST FOR FERMI 2 MEETING FEBRUARY 7, 1979 NRC Detroit Edison Comoany L. L. Kintner E. Lusis C. I. Grimes F. E. Gregor C. P. Tan L. Schuerman S. Hou D. Lehnert B. Clayton P. Y. Chen F. C. Cherny K. D. Desai NUTECH T. Huang R. Bosnak A. Higginbothan