ML20082C536
| ML20082C536 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/10/1983 |
| From: | Clayton F ALABAMA POWER CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20082C540 | List: |
| References | |
| TAC-53266, TAC-54234, NUDOCS 8311220112 | |
| Download: ML20082C536 (2) | |
Text
_.
Memog Address Alabama Power Company 600 North 18th Street Post Office Box 2641 Birmingham, Alabama 35291 Telephone 205 783-6081 F. L Clayton, Jr.
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AlabamaPower the southern electnc system November 10, 1983 Docket No. 50-364 Director, Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Attention: Mr. S. A. Varga Joseph M. Farley Nuclear Plant - Unit 2 Reactor Vessel Surveillance Capsule Report Gentlemen:
Pursuant to the requirements of 10CFR50 Appendix H and Technical Specification 3/4.4.10, A!4aama Power Company herewith submits the Westinghouse WCAP-10A?S Report entitled " Analysis of Capsule U from the Alabama Power Company Joseph M. Farley Unit 2 Reactor Vessel Radiation Surveillance Program." This report presents the reactor vessel surveillance capsule test results which were used to evalisate the reactor vessel material properties following 1.1 EFPY. This report concludes that the actual shift in material mechanical properties was less than that predicted utilizing the methodology of NRC Regulatory Guide 1.99, Rev.1.
Based on the attached surveillance capsule test results, pressure-temperature curves shown on Pages A-8 and A-9 of the subject report remain the same as those in Technical specification Figures 3.4-2 and 3.4-3.
Therefore, no technical change to the existing Technical Specification curves is required and no changes to the operating
-procedures are required. However, as a result of our review, some minor administrative changes to the notations of Technical Specification Figures 3.4-2 and 3.4-3 are planned.
In addition, modifications to Technical _ Specification Table 4.4-5 are needed due to recent changes in 10CFR50 Appendix H and improvements in neutron flux prediction methodology. An administrative Technical Specification change addressing these revisions will be submitted within ninety days for NRC
-a review and approval.
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Mr. S. A. Varga November 10, 1983 U. S. Nuclear Regulatory Commission Page 2 If there are any' questions, please advise.
Yours very truly, F.
. Clayton, J.
FLCJ r/GGY:ddr-D4 Attachment cc: Mr. R. A. Thomas Mr.'G. F. Trowbridge Mr. J. P. O'P.eilly Mr. E. A. Reeves Mr. W. H. Bradford 0
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