ML20042B252
| ML20042B252 | |
| Person / Time | |
|---|---|
| Site: | Clinch River |
| Issue date: | 03/17/1982 |
| From: | Stark R Office of Nuclear Reactor Regulation |
| To: | Check P Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8203250145 | |
| Download: ML20042B252 (5) | |
Text
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4 IIECE!VED March 17, 1982 j
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14 Docket flo.: 50-537 r,
NEMORA:iDUM FOR: Paul S. Check, Director, CRBR Program Office, Office of fluclear Reactor Regulation FR0i:
Richard M. Stark, Project flanager, CRBR Program Office, Office of liuclear Reactor Regulation
SUBJECT:
CLIllCil RIVER BREEDER REACTOR !!ATERIALS AllD MECilAfiICAL EllGIllEERI!!G REVIEll IIEETIliG DATE &
April 6 & 7, 1932, Air Rights Building, Room 2242, LOCATI0il:
Bethesda, !kl., at 8:30 a.m.
PURPOSE:
Continue the CRBR !!aterials and !!echanical Engineering review. See Agenda.
PARTICIPAiTS:
Departraent of Energy J. Longenecker, D. Goeser, et. al.
14RC
- 11. llolz, S. Ilou, F. Litton, R. Stark, et. al.
ORIGINAL SIG ED BY Richard M. Stark, Project !!anager CRBR Program Office Office of tiuclear Reactor Regulation
Enclosure:
As stated cc:
Service List i
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CRBRP/NRC MEETING ON MATERIALS AND STRUCTURES PROPOSED AGENDA TOPIC I.
Intraduction (Description of data on material behavior and failure that are needed for elevated temperature design).
II.
Materials Da.ta Base - 304, 316, 718 (Presents data substantiating values used for design at elevated temperature for long term and cyclic loading).
III.
Design Feature Tests (Describes analyses and tests verifying the materials data for representative conditions).
IV.
CRBRP Environmental Effects a.
Sodium Effects b.
Radiation Effects V.
Special Materials Cor.siderations.
a.
Fracture Mechanics b.
Hot leg c.
Transition VI.
Special flaterials Considerations a.
Metallurgical notch b.
Elevated temperature acceptance tests c.
Biaxial effects'in creep rupture VIII.
Special Stress Considerations a.
Simplified Ratchetting Rule b.
Elastic Follow-up c.
Weld residual stresses VIII.
Special Criteria Considerations a.
Component Effective Date Evaluation b.
Core Support Structure IX.
Transition Joint Experience and Technology I
l X.
Reactor Vessel Transition Joint (Description of geometry, materials, loadings, conditions, design basis, stress analysis, surveillance and inspection).
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2-XI.
IHTS Transition Joints (Description of geometry, materials, loadings, conditions, design basis, stress analysis, surveillance and inspection.
In addition, the applicant will discuss the following Mechanical Engineering topics:
1.
Many components for the CRBR plant were manufactured several years ago and have been.in storage since then.
Have the components been stored in such a fashion so that the stress analysis and fatigue analysis have not been compromised?
2.
What provisions currently exist to control sodium spray? Discuss the design of the vessel support including the concrete supporting ledge and the transfer of loads into concrete, for the SSE and with normal temperature gradients.
3.
The SRP states that Loading Combination Methodology shall be consistent with NUREG-0484.
Section 3.9.3 of the PSAR does not reference the transients of Appendix B of the PSAR, nor does it explicitly address the m thods dsed to form loading c6mbinations such as DBA & SSE.
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. cc:
Dr. Cadet H. Hand, Jr., Director Barbara A. Finamore Bodega Marine Laboratory S. Jacob Scherr University of California Ellyn R. Weiss P. O. Box 247 Dr. Thomas B. Cochran Bodega Bay, California 94923 Natural Resources Defense Council, Inc.
Daniel Swanson 1725 I Street, N.W.
Office of the Executive Suite 600 Legal Director Washington, D.C.
20006 U. S. Nuclear Regulatory Commission Eldon V. C. Greenberg Washington, D.C.
20555 Tuttle & Taylor 1901 L Street, N.W.
William B. Hubbard, Esq.
Suite 805 Assistant Attorney General Washington, D.C.
20036 State of Tennessee Office of the Attorney General L. Ribb 450 James Robertson Parkway LNR Associates Nashville, TN 37219 Nuclear Power Safety Consultants 8605 Grimsby Court William E. Lantrip, Esq.
Potomac, MD 20854 City Attorney Municipal Building P. O. Box 1 Oak Ridge, TN 37830 George L. Edgar, Esq.
Morgan, Lewis & Bockius 1800 M Street, N.W.
Washington, D.C.
20036 Herbert S. Sanger, Jr., Esq.
General Counsel Tennessee Valley Authority Knoxville, TN 37902 i
Chase Stephens, Chief Docketing and Service Section Office of the Secretary U. S. Nuclear Regulatory Commission Washington, D.C.
20555 l
Raymond L. Copeland l
Project Management Corp.
P. O. Box U Oak Ridge, Tennessee 37830
1 Distribution Docket File' bec: Applicant Service List NRC PDR Local PDR NSIC CRBRPO File H. Denton D. Eisenhut R. Vollmer R. Mattson S. Hanauer H. Thompson J. P. Knight W. Johnston D. Muller P. Check R. W. Houston L. Rubenstein F. Schroeder M. Ernst ACRS (16)
OI&E (3)
S. Treby (0 ELD)
V. Moore B. Grimes R. Woodruff Region II Administrator m
EDO (4)
L. S. Tong NRC Participants J. A. Olshinski, Reg. II R. E. Ireland, NRC-Idaho J. Austin B. D. Liaw J. Glynn P. Wood Receptionist - Phillips Bldg.
CR8R Staff J. Long R. Jackson Charlie Thayer, Reactor Training Center, Chattanooga