ML20214P384

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Forwards Rev 0 to FNP-1-M-043, Second 10-Yr Inservice Insp Program for Class 1,2 & 3 Components, Per 10CFR50.55a(g)(4) & (5).Requests That Relief Be Granted by 871201 for Preparation of Eighth Refueling Outage.Fee Paid
ML20214P384
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 05/27/1987
From: Mcdonald R
ALABAMA POWER CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20214P385 List:
References
NUDOCS 8706030351
Download: ML20214P384 (2)


Text

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A11bsma Power Company #

'I 600 North 18th Street Post Office Box 2641 Birmingham, Afabama 35291-0400 e

Telephone 205 250-1835

- IenioYv' ce"P sident Docket No. 50-348

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10CFR50.55a(g)

May 27, 1987 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C.

20555 Gentlemen:

Joseph M. Farley Nuclear Plant - Unit 1 Second Ten Year Interval Inservice Inspection Program for ASME Code Class 1, 2 and 3 Components Pursuant to the requirements of 10CFR50.55a(g)(4) and (5), enclosed is the Joseph M. Farley Nuclear Plant Unit'l Inservice Inspection Program for the Second Ten Year Interval of plant operation. To the extent practical within the limitations of design, geometry and materials of construction of the components, this updated program meets the requirements of the latest NRC approved Code edition and addenda as of December 1,1986 which is the ASHE Code,Section XI,1983 Edition through the Sumer 1983 Addenda. Exceptions to this are permitted by 10CFR50.55a(b)(2)(fi) and (iv). Under these exceptions, the extent of examinations for ASME Code Class 1 and 2 piping welds is determined in accordance with the 1974 Edition through the Summer 1975 Addenda of Section XI.

The enclosed program includes a set of tables for each of the three ASME Code component classifications and for component supports. These tables describe how the appropriate ASME Code requirements are applied and met for the design of Farley Nuclear Plant Unit 1.

In addition, Inservice Inspection Boundary Diagrams which have been developed to show the required examinations and their respective boundaries, are included and reflect these requirements.

Where certain ASME Code requirements have been determined to be impractical, relief requests have been prepared which summarize the component or relief area, the ASME Code requirement, the basis for relief and, where appropriate, the proposed alternative examination. These reliefs are included in the program along with references in the tables and diagrams where appropriate for specific components.

In addition, certain of the reliefs requested have previously been granted by the NRC for Farley Nuclear Plant.

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l U. S. Nuclear Regulatory Comission May 27, 1987 Page 2 Pursuant to the requirements of 10CFR50.55a(g)(6)(1), Alabama Power Company requests that the NRC grant relief from the ASME Code requirements as defined in the forty-three (43). relief requests ' submitted with the enclosed program.

It is requested that these reliefs be granted by December 1,1987 so that the planning and preparation for the Unit i eighth refueling outage,. tentatively scheduled to commence in March 1988, can be completed on a timely basis. The inservice inspection activities planned for this outage will require utilization of a number of these relief requests.

1 Pursuant to 10CFR170.21, the required application fee of $150.00 is enclosed.

If there are any questions, please advise.

Respectfully submitted, ALABAMA P0 COMPANY GB #

o R. P. Mcdonald RPM / STB:csi-1 Enclosures cc: Mr. L. B. Long, w/o enclosure Dr. J. N. Grace, w/1 enclosure Mr. E. A. Reeves, w/1 enclosure Mr. W. H. Bradford, w/o enclosure l

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