ML19347D876
| ML19347D876 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/09/1981 |
| From: | Baynard P FLORIDA POWER CORP. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| 3-041-11, 3-41-11, NUDOCS 8104140372 | |
| Download: ML19347D876 (2) | |
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April 9,1981 4Ajp2 lc
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.m Mr. Darrell G. Eisenhut Di rector
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Division of Licensing U.S. Nuclear Regulatory Comission Washington, D.C.
20555
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. OPR-72 COMPLIANCE WITH 10 CFR 50, APPENDIX G
Reference:
Letter, J.H. Taylor (B&W), to J. S. Berggren (NRC) dated March 12,1981, transmittal of B&W Report BAW-1511P,
" Irradiation - Induced Reduction in Charpy Upper - Shelf Energy of Reactor Vessel Welds", dated October,1980.
Dear Mr. Eisenhut:
The Ccde of Federal Regulations (Appendix G to 10 CFR 50) requires the licensee to demonstrate to the Commission the adequacy of fracture tough-ness of Reactor Vessel materials when significant radiation-induced degradation of material fracture toughness properties occurs.
To demonstrate compliance with the requirements of 10 CFR 50, Appendix G, the B&W Owners Group has developed a multiphase program.
Phase I has the objective of determining the period of time for which the requirements of Appendix G to 10 CFR 50 are satisfied for each Owners Group reactor vessel, i.e., the service life to the C OSE 50 ft-lb y
threshold.
Phases II-VII have the objective of developing the data and methodology to demonstrate that each plant possesses adequate margin of safety against non-ductile failure for the full 40-year plant design life.
810.414o 3VA
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Page Two April 9,1981 The Phase I results are summarized in the B&W report BAW-1511P,
" Irradiation-Induced Reduction in Charpy Upper-Shelf Energy of Reactor Vessel Welds".
This report was transmitted to your Mr. J. S. Berggren generically for B&W 177FA plants by the above referenced letter.
We have reviewed the generic report and determined that CR-3 Reactor Vessel Welds are predicted to exhibit' a CyVSE of more than 50 ft-lb for 16 or more years.
Completion of work in the other. phases of the B&W Owners Group Program on Reactor Vessel Materials will provide the justification for plant operation for the 40-year design life.
Should you have any questions regarding the above subject, please contact this office.
Very truly yours, FLORIDA POWER CORPORATION
.da(,T} X <t)metd P. Y. B'aynard Manager Nuclear Support Services Lobo (T03)D1-3 r
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