ML20041E375

Forwards Request for Addl Info Re Matls Engineering.Response Should Be Submitted in 60 Days

ML20041E375
Person / Time
Site:	Clinch River
Issue date:	02/26/1982
From:	Check P Office of Nuclear Reactor Regulation
To:	Langenecker J ENERGY, DEPT. OF
References
NUDOCS 8203100442
Download: ML20041E375 (4)

Text

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Distribution

/DocketFile February 26, 1982 NRG PDR Local PDR NSIC CRBR Reading docket 110.: 50-537 R.

a P. Check

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{ %J.'I h Cg% h Mr. Jonn R. Longenecker F. Litton f

Licensing and Environmental Coordination W. Foster j

Clinch River Breeder Reactor Plant P. Shuttlewo v

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U. S. Departuent of Energy, HE-561 Washington, D.C.

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SUBJECT:

CLINCH RIVER BREEDER REACTOR PLANT, REQUEST FOR ADDITI0I4AL INFORIMTION As a result of our review of your application for a construction permit for the Clinch River Breeder Reactor Plant, we find that we need addi-tional information in the area of Materials Engineering. 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, OMP clearance is not required under P.L.96-511.

If you desire any discussion or clarification of the information requested, please contact R. M. Stark, Project Manager (301) 492-9732.

Sincerely, Original Signed by p na s twek Paul S. Check, Director CRBR Program Office Office of Nuclear Reactor Regulation

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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 Gei..ral 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 Stsphens, Chief Docketing and Service Section Office of the Secretary U. S. Nuclear Regulatory Commission Washington, D.C.

20555 Raymond L. Copeland i

Project Management Corp.

P. O. Box U Oak Ridge, Tennessee 37830

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w CLINCH RIVER BREEDER REACTOR PLANT DOCKET NUMBER 50-537 MATERIALS ENGINEERING BRANCH COMPONENT INTEGRITY SECTION CS250.3 Identify the components and supports in the reactor coolant system and connecting systems (including tha steam generator) which have been constructed, stating the purchase date and the Code, Standards, and criteria to which they were fabricated.

Describe the procedures used for their storage.

Indicate the difference in the purchase requirements and the Codes, Standards and criteria in effect at the present time.

The use of the components should be justified on the basis that they will provide an equivalent degree of system integrity and safety as if fabricated to the requirements of the current Codes, Star.dards, and criteria.

CS250.4 Provide the method for structural evaluation of weldments and associated materials for service at elevated temperature.

The following should be addressed:

(i) room temperature and elevated temperature material acceptance criteria; (ii) creep rupture damage resulting from residual forming and welding stresses; (iii) mass transfer effects; (iv) metallurgical notch effects; i

. (v) fracture toughness criteria; (vi) thermal aging effects; and (vii) irradiation effects.

CS250.5 Provide the method and data base for the structural evaluation and acceptance of bi-metallic and tri-metallic transition welds for service in the primary and intermediate heat transport systems.

CS250.6 Provide justification for the use of the simplified creep ratcheting bounding methods in Code Case 1592 at structural discontinuities.

CS250.7 How do you account for the elastic follow-up in elevated temperature component and piping (elbows) system analyses?

CS250:8 Provide the design criteria fan the elevated temperature core support

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structuce, including the welds in the forging and the reactor vessel.

CS250.9 Provide the elevated temperature data base for the mechanical properties of the following materials:

(i)

Type 304 stainless steel; (ii)

Type 316 stainless steel; (iii) 2 1/4 Cr - 1 Mo alloy; (iv)

Alloy 718.

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