ML20027D635
| ML20027D635 | |
| Person / Time | |
|---|---|
| Site: | Clinch River |
| Issue date: | 11/03/1982 |
| From: | Longenecker J ENERGY, DEPT. OF, CLINCH RIVER BREEDER REACTOR PLANT |
| To: | Check P Office of Nuclear Reactor Regulation |
| References | |
| HQ:S:82:121, NUDOCS 8211080182 | |
| Download: ML20027D635 (2) | |
Text
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Department of Energy Washington, D.C. 20545 Docket No. 50-537 HQ:S:82:121 g
!!r. Paul S. Check, Director CRBR Program Office Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Check:
MEETING
SUMMARY
FROM THE PIPING INTEGRITY MEETING 0F OCTOBER 28, 29, 1982
Reference:
HQ:S:82:093, J. R. Longenecker to P. S. Check,
Subject:
Meeting Summary for MEB/CRBRP September 8 and 9,1982, Meeting, dated September 21, 1982 The Clinch River Breeder Reactor Plant (CRBRP) Project presented a detailed discussion of the materials data base end basic analyses and evaluations supporting the Project's position on piping integrity of the Primary Heat Transport System to the Nuclear Regulatory Commission (NRC) staff on October 28 and E9. The presentations included detailed discussions of high temperature design related questions documented in the reference letter. At the conclusion of the meeting, the NRC staff concluded that the Leak-Before-Break concept is acceptable for the primary cold leg. NRC further stated that the concept of Leak-Before-Break would be acceptable in the primary hot leg subject to satisfactory demonstration by the applicant that creep and creep / fatigue interactions have been appropriately accounted for in the analysis. Alternatively, a satisfactory confirmatory program of analysis and/or experiment to show that such effects can be accommodated within the design envelope would also be acceptable by NRC. The Project agreed to address these concerns by the scheduled November 22 meeting.
Additionally, the status of low temperature design related questions were discussed. A majority of these questions were stated to be resolved, with a few under review or awaiting additional information as previously described in the reference letter.
goN 8211080182 821103 PDR ADOCK 05000537 A
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Questions regarding this meeting sumary can be addressed to D. Robinson (FTS 626-6098) or F. Niziolek (FTS 626-6190) of the Project Office Oak Ridge staff.
Sincerely, b~
N' v V
Jo '
R. Longen c er Acting Director, Office of the Clinch River Breeder Reactor Plant Project Office of Nuclear Energy cc: Service List Standard Distribution Licensing Distribution