ML20064K075

Request for Amend to License DPF-2,granting Relief from Requirements of 1974 Edition Through Summer 1974 Addenda to ASME Code,Section Xi,Table IWB-2600 Re Inservice Insp Program for ASME Code Class 1,2 & 3 Components

ML20064K075
Person / Time
Site:	Farley
Issue date:	01/10/1983
From:	Clayton F ALABAMA POWER CO.
To:	Varga S Office of Nuclear Reactor Regulation
References
TAC-48559, TAC-49373, NUDOCS 8301180292
Download: ML20064K075 (2)

Text

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Malling Address Alabama Power Company 600 North 18th Street Post Office Box 2641 Birmingham. Alabama 35291 Telephone 205 783-6081 F. L Clayton, Jr.

Senior Vice President Flintridge Building pghgg3 gg Docket No. 50-348 netmectm system January 10, 1983 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. S. A. Varga Joseph M. Farley Nuclear Plant - Unit 1 Inservice Inspection Program for ASME Code Class 1, 2 and 3 Components Gentlemen:

In accordance with the requirements of 10CFR50.55a(g)(6)(1), Alabama Power Company hereby requests that relief be granted from the requirements of the 1974 Edition through the Summer 1975 Addenda of the ASME Code,Section XI, Table IWB-2600 Item Numbers B1.14, B2.9 and B3.8. A complete description of the affected components, existing examination requirements, bases of request for relief and proposed alternative examinations are contained in Attachment I.

This request for relief supplements the request for relief submitted for Unit i by our letter of April 17, 1981. In addition, Alabama Power Company inadvertently omitted the required fee from this request.

This request is designated as Class III in accordance with 10CFR170.22 requirements. Enclosed is a check for $4,000.00 to cover the total amount of fees required.

Yours truly,

'kF. L. Claytor t.

, Jr.

STB:bs Enclosures cc: Mr. R. A. Thomas Mr. G. F. Trowbridge Mr. J. P. O'Reilly Mr. E. A. Reeves Mr. W. H. Bradford f W pot 8301100292 830110 PDR ADOCK 05000348 P PDR

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. l Note 17 to the Class 1 Table COMP 0NENT: CODE CLASS: 1 Reactor Vessel Cladding, Pressurizer Cladding and Steam Gererator Cladding (Item M>mbers B1.14, B2.9, and B3.8, Examination Categories B-I-1 and B-I-2).

EXAMINATION REQUIREMENT:

Visual examination of the reactor vessel cladding shall include at least six patches (each 36 sq. in.) evenly distributed in accessible sections of the vessel shell. The examinations performed during each inspection interval shall cover 100% of the patch areas. Visual examination of the pressurizer and steam generator vessel cladding shall include at least one patch (36 sq. in.) near each manway in the primary side of the vessel. The examinations performed during each inspection interval shall cover 100% of the patch areas. The examination of the patch areas in the pressurizer and steam generator may be performed at or near the end of the inspection interval.

BASIS FOR RELIEF:

Pressurizer and steam generator cladding examinations which must be performed by manual inspections inside the vessels are impractical because of the high radiation levels in the areas required to be examined. The reactor vessel cladding visual examination is impractical to perform because of the critical outage time required to remove the access plugs or fuel and core barrel that enable the use of cameras to assist in the l examination.

ALTERNATIVE EXAMINATION:

! The reactor vessel longitudinal and circumferential shell welds are volumetrically examined per Table IWB-2600, Item Bl.1 Category B-A and Item BI.2 Category B-B. The pressurizer longitudinal and circumferential welds are volumetrically examined per Table IWB-2600, Item B2.1 Category B-B.

The tube sheet-to-head weld on the steam generators are volumetrically examined per Table IWB-2600, Item B3.1 Category B-B. These weld d' examinations include the cladding on the weld and the adjacent base metal for a distance of one wall thickness on each side of the weld. ,

l CONCLUSION:

l l Volumetric examinations'8which are required for the longitudinal and l circumferential welds in vessels provide sufficient evidence of component structural i ntegri ty. Additional support for not requi ring the present

, inspections is that later NRC approved editions of Section XI no longer l require cladding inspections but allow for volumetric examinations. Based on this guidance, no additional examinations will be performed for categories B-I-1 and B-I-2 for the cladded areas included in this request and, in the cladded areas described in the original April 17, 1981 relief request.

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