ML20041G300
| ML20041G300 | |
| Person / Time | |
|---|---|
| Site: | Clinch River |
| Issue date: | 03/11/1982 |
| From: | Check P Office of Nuclear Reactor Regulation |
| To: | Longenecker J ENERGY, DEPT. OF, CLINCH RIVER BREEDER REACTOR PLANT |
| References | |
| NUDOCS 8203220025 | |
| Download: ML20041G300 (4) | |
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Distribution March 11, 1982
. Docket File. 3 NRC PDR Local POR NSIC fBR Docket flo.: 50-537 sta C. Thomas P. Check Mr. John R. Longenecker R. Wright Licensing and Environmental Coordination W. Foster Clinch River Breeder Reactor Plant P. Shuttleworth U. S. Department of Energy, llE-561 Washington, D.C.
20545
Dear fir. Longenecker:
SUBJECT:
CLINCil RIVER BREEDER REACTOR PLANT, REQUEST FOR ADDITIONAL INFORIMTION As a result of our review of your application for a construction pennit for the Clinch River Breeder Reactor Plant, we find that we need addi-tional information in the area of Equipment Qualification.
Please provide your final responses within sixty days of the receipt of this request.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore Ole clearance is not required under P.L.96-511.
If you desire any discussion or clarification of the information requested, please contact R. H. Stark, Project Manager (301) 492-9732.
Sincerely, Original Signed by I'aul S. check Paul S. Check, Director CRBR Program Office Office of fluclear Reactor Regulation
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I, ENCLOSURE CS270.10 The equipment qualification program at CRBR invovles several parties, the Department of Energy, Project Management Corporation, and various vendors.
When the plant is fully licensed and operational, it will be turned over to the plant operator.
It is essential for the operator of the plant to maintain all relevant documentation on equipment quali-fication in an auditable manner at a central location.
Regarding equip-ment qualification the details of the interactions of the organizations and location of the central file should be provided by amending appropriate sections of the PSAR.
CS270.11 Recognizing that margins to be used in developing the required seismic and dynamic loadings are to be in accordance with the requirements of IEEE Standard 344-1975, provide an amendment that addresses (a) how the input loading specified in the purchasa specification will be verified against the final design values,, id (b) what method will be used to establish the total margin consisting of an input envelope over a number of similar equipment, differences between the initial input and final design input, and the test input versus the required
- input, CS270.12 Provide an admendment that discusses the procedure that will be used to combine the equipment loading from earthquake, generally in the 0 to 33 Hz range, and from the dynamic shock wave loading resulting from Na-H2O reaction with a frequency range of 20 to 100 Hz.
Equipment to be qualified by tests should be specially addressed.
CS270.13 Some equipment experiences high temperatures.
Material behavior under the effects of high temperature during normal oceration can go from the linear to the non-linear regime.
Thus, normal operating loads superimposed with seismic and dynamic loads are likely to produce non-linear responses in equipment.
Discuss in detail in the amendment the non-linear analysis procedures to be used for equipment qualification.
In the case of seismic analysis to account for the non-linear effects indicate how the non uniqueness of seismic time history will be considered.
Indicate what method or criteria will be used, including reduction of allowable stresses beyond those that are established for pressure boundary integrity, to account for the effects of material non-linearity at high temperatures and creep to ensure equipment operability.
CS270.14 The Nuclear Regulatory Commission is proposing to amend its regulations applicable to nuclear power plants to achieve consistency, reliability, and reproducibility of test results, and to provide adequate control of equipment qualification testing.
To achieve these ends, the proposed rule requires that all qualification testing of equipment important to safety shall be performed by testing organizations accredited by the Institute of Electrical and Electronic Engineers, Inc. (IEEE) to perform such tests.
This requirement conforms to an agreement between the NRC and the IEEE, effective September 30, 1981, regarding the accreditation
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How does the applicant plan to achieve consistency, reliability, and reproducibility of test results, and provide adequate control of equipment qualification?
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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 Chase Stephens, Chief Docketing and Service Section Office of the Secretary V. S. Nuclear Regulatory Commission Washington, D.C.
20555 Raymond L. Copeland Project Management Corp.
P. O. Box U Oak Ridge, Tennessee 37830