ML20073A803

Commits to Listed Actions to Close Out SER Open Item 1, Review of Rdt Stds F9-4T & F9-5T. Appropriate Info on Verification of Analysis Methods & Computer Programs Used in High Temp Design Will Be Provided at OL Review Stage

ML20073A803
Person / Time
Site:	Clinch River
Issue date:	04/07/1983
From:	Longenecker J ENERGY, DEPT. OF, CLINCH RIVER BREEDER REACTOR PLANT
To:	Grace J Office of Nuclear Reactor Regulation
References
HQ:S:83:240, NUDOCS 8304110870
Download: ML20073A803 (3)

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. Department of Energy Washington, D.C. 20545 Docket No. 50-537 HQ:S:83:240 APR 0 71983 Dr. J. Nelson Grace, Director CRBR Program Office Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.

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Dear Dr. Grace:

RESPONSE TO SAFETY EVALUATION REPORT (SER) OPEN ITEM NO.1 - REVIEW OF RDT STANDARDS F9-4T AND F9-5T As a result of the March 31, 1983, meeting with the Nuclear Regulatory Commission (NRC) staff, the Clinch River Breeder Reactor Plant (CRBRP) project commits to the following actions to close out SER Open Item No.1, " Review of 4

RDT Standards F9-4T and F9-5T," listed in Section 1.6 of the SER.

The CRBRP project commits to provide appropriate information on the verifica-tion of analysis methods and computer programs used in high temperature design at the operating license review stage. The requirement for verification of computer programs has been in place at the CRBRP project since the outset, in accord with the ASME Code requirements and requirements of Section 3.9.1 of the NRC Standard Review Plan. Preliminary information in accord with these requirements has been provided in Appendix A of the Preliminary Safety Analysis Report.

With regard to the use of the alternative temperature limits method of para-graph 6.2 of RDT Standard F9-ST; the project agrees that using this method, instead of the method of Code Case N-47, for the final design of Class -1 elevated temperature components, potentially ignores significant creep strain accumulation. Therefore, the project agrees that the alternative method will not be used in the final stress reports.

- Additionally, the NRC staff at the March 31, 1983, meeting stated its intention to impose a confirmatory program on material properties used for inelastic analyses that would be completed by the operating license review l

stage. The project commits to perform a program outlined in the enclosure to address this concern.

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2 Any questions regarding the above commitments may be' addressed to' Mr. D. Robinson (FTS 626-6098) or Mr. D. Edmonds (FTS 626-6157) of the -

Project Office Oak Ridge staff.

Sincerely, Jo n R.-Long cker Acting Director, Office of Breeder Demonstration Projects Office of Nuclear Energy cc: Service List Standard Distribution Licensing Distribution

ENCLOSURE AGREEMENTS'AND COMMITMENTS FROM CRBRP AND NRC MEETING ON ELEVATED TEMPERATURE DESIGN March 31, 1983 For those elevated temperature components containing radioactive sodium where inelastic design analyses are used, the staff required that the applicant evaluate the significance of material property variations.

This requires that minimum yield strength and minimum creep strength (80 percent of the average isochronous curves) properties be used to evaluate the fatigue damage, PZ (Na4 d4 j J.:

creep rupture damage, k

and the accumulated inelastic strains. These damage fractions for minimum and average material properties shall be presented using the method provided by the ASME Code Case for Class 1 Components in Elevated Temperature Service and reported.

The creep portion of the total accumulated inelastic strains (membrane, bending, peak) shall be presented using the method provided by the ASME Code Case for Class 1 Components in Elevated Temperature service and reported.

Demonstrate the structural adequacy of the components with the above values of damage and inelastic strain.

As a result of the staff review of materials properties variations, the applicant is required to consider minimum and average properties in performing the Confirmatory Programs associated with Findings 1, 5, and 9 in Para. 3.9.9 of the SER.