ML20153D647
| ML20153D647 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 05/05/1988 |
| From: | Mcdonald R ALABAMA POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20153D649 | List: |
| References | |
| NUDOCS 8805090231 | |
| Download: ML20153D647 (2) | |
Text
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-s Al:bam: Power Compa ny 600 North 18th Strzt Post OfSce Box 2641 Birmingham. Alabama 35291-0400 Telephone 205 250-1835 L
Mahama POWCf R. P. McDonaki Senior Vice Pres + dent the scantwn eWtrc sprem Docket No. 50-348 10CFR50.55a(g)
May 5, 1988 U. S. Nuclear Regulato'.y Commission At tentic,n: Document Control Desk washington, D. C.
20555 Gentlemen:
Joseph M. Farley Nuclear Plant - Unit 1 Final Reports on the Evaluation of Indications from the Reactor Vessel Inservice Inspection (TAC 67690)
By letter dated April 28, 1988, Alabama Power Company submitted initial reports which provided information on the evaluation and disposition of five indications found during the inservice examination of the Unit i reactor vessel. h is letter also requested the NRC's approval of the acceptable disposition of two of these indications based on the fracture mechanics evaluations permitted by the ASME Code,Section XI.
'Ihe remaining indications were determined to be either within the Code acceptance criteria or outside the Code required examination volume.
'Ihe final reports, which were prepared by Westinghouse, are included herein as Enclosures 1, 2 and 3. provides an ovaluation of the two indications which exceed the allowable standards of the ASME Code,Section XI, IWB-3500. Enclosure 2 provides an evaluation of the three remaining indications. is the "Background and Technical Basis for the Handbook on Flaw Evaluation of the Joseph M. Farley Nuclear Plante Units 1 and 2 Reactor Vessel Beltline and Nozzle-to-Shell Welds," WCAP-11763, which provides the fracture mechanics analysis methodology used to determine that the indications discussed in Enclosure 1 are acceptable based on the criteria of Section XI, IkW 3600. Together, the reports in Enclosures 1 and 3 provide the information requested by the NRC Staff for use in approving the acceptable disposition of the two indications in accordance with section XI, Iww 3610(b). Wis information includes a detailed probabilistic risk assessment of the low temperature overpressurization transient, including its relevance to the flaw evaluation analysis, and a discussion of the assumptions made concerning the fracture properties of Op q the nozzle forging and weld materials.
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8805090231 880505 PDR ADOCK 05000348
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U. S. Nuclear Regulatory Comission May 5, 1988 Page 2 As discussed in the April 28, 1988 letter, this approval is respectfully requested no later than May 12, 1988 as this is the date tentatively scheduled for initial criticality during startup following the current refueling outage. The required application fee was enclosed with the initial reports.
It should be noted that the information provided in Enclosure 3 is nonproprietary. Distribution of this enclosure by the NRC is herewith authorized by Alabama Power Company.
If there are any questions, please advise.
Respectfully submitted, ANY
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R. P. Mcdonald RPfySTB:csl Enclosures cc:
Mr. L. B. Long Dr. J. N. Grace Mr. E. A. Reeves Mr. W. H. Bradford Dr. C. E. Fox l
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