ML20040F197
| ML20040F197 | |
| Person / Time | |
|---|---|
| Site: | Clinch River |
| Issue date: | 02/02/1982 |
| From: | Stark R Office of Nuclear Reactor Regulation |
| To: | Check P Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8202080463 | |
| Download: ML20040F197 (5) | |
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UNITED STATES
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Docket No. 50-537 S
MEMORANDUM FOR: Paul S. Check, Director, CRBR Program Office, Office of Nuclear Reactor Regulation FROM:
Richard M. Stark, Project Manager, CRBR Program Office, Office of Nuclear Reactor Regulation
SUBJECT:
CLINCH RIVER BREEDER REACTOR STRUCTURAL REVIEW MEETING Il DATE &
LOCATION February M 1982, Air Rights Building, Room 2242, Bethesda, MD at 8:30 a.m.
PURPOSE:
To review the CRBR Structural Design.
See Agenda.
PARTICIPANTS:
Department of Energy J. Longenecker, D. Goeser, et. al.
NRC C.P. Tan, R. Stark, et. al.
At H1 chard M. Stark, Project Manager CRBR Program Office Office of Nuclear Reactor Regulation i
cc:
Enclosure:
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AGENDA STRUCTURAL ENGINEERING BRANCH 1.
Codes, Standards, Rules and Regulations to be used in the CRBR applications a.
New Code and SRP revisions b.
Edition of ASME Section III Codes 2.
Missile Protection Requirements (3.5.3) a.
Concrete thicknesses for wall and slab 3
Seismic Design (3.7)
Analysis of soil structure interaction a.
- 1) Modeling ii)
Damping 111) Application of input motion iv) Validation of computer program v)
Non-linear time history analysis b.
Effect of drainage rock layer under foundation c.
Reactor system computer model 4.
Category I Structures (3.8)
I.
Containment a.
Buckling stress criteria ASME code case N-284 (1980)
Factors of safety b.
Buckling calculations Buckling for dynamic loads Buckling for thermal loads Temperature distributions (including TMBDB)
, I II. Reactor cavity thermal stress analysis a.
Use of ANSYS for concrete b.
Temperature distributions c.
Interaction between components (for example, effect of RC on
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pipeway cell floor)
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5.
Cell Liners (3.8) a I.
Use of ultimate strain for liner failure.
Is this applicable-to high shear areas near studs?
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II. Analysis of cell liner system a.
Possible buckling modes b.
Creep effects c.
Nonuniform temperature distribution d.
Corrosion and flaws
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Penetrations and other discontinuities and studs near these e.
areas.
6.
TMBDB effects on Structural Design s
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Dr. Cadet H. Hand, Jr., Director Barbara A. Finamore cc:~ Bodega Marine Laboratory S. Jacob Scherr University of California Ellyn R. Weiss P. O. Box 247' Dr. Thomas B. Cochran Natural Resources Defense Council, Inc.
Bodega Bay, California 94923 1725 I Street, N.W.
Daniel Swanson Suite 600
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Office of-the Executive Washington, D.C.
20006 Legal Director U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Wi.lliam B. Hubbard, Esq.
Assistant Attorney General State of Tennessee
' Office of the Attorney General
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4P2 Supreme Court Building Nashville, TN 37219 Luther M. Reed, Esq.
Attorney.for the City of Oa.k Ridge 253 Main St.reet, East Oak Ridge, TN 37830
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'r, George L. Edgar, Esq.
~1800'M Street, N.W.
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Washjngton, D.C.
7.0036 Herbert S. Sanger,.Jr., Esq.
i Ganeral Counsel l
Tennessee Valley Authority Knoxviille, TN 37902 Chase Stephens, Chief Docketing and Service Section Office of the Secretary U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Raymond L. Copeland Project Management Corp.
P. O. Box 0 Oak Ridge, Tennessee '37830 L. Ribb LNR Associates Nuclear Power Safety Consultants 8605 Grimsby Court Potemac, MD 20854
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Docket File?-
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Applicant Service List NRC POR Local PDR CRBRPG File NSIC H. Denton D. Eisenhut-R. Vollmer R. Mattson S. Hanauar H. Thompson J. P. Knight W. Johnston O. Muller P. Check W. Kreger L. Rubenstein F. Schroeder M. Ernst ACRS (16) 01&E (3)
- 5. Treby (0 ELD)
J. Le0cux, I&E V. Moore B. Grimes
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Thomas P. Leech P. Stark W. H. Foster I
R. Woodruff S. Morris I&E Region II ECO (a)
L. S. Tong Licensing Assistant - P. Shuttlewor n NRC Participants J. A. Olsninski, IE: Reg. II R. E. Ireland, NRC-Idano J. Austin B. D. Liaw I
J. Glynn P. Wood