ML20064J484

Application for Amend to License NPF-8,requesting Relief from Inservice Insp Requirements of 1974 - Summer 1975 Addenda to ASME Code,Section Xi,Table IWB-2600,Item Numbers B1.13,B1.14,B2.9 & B3.8

ML20064J484
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 8301180091
Download: ML20064J484 (3)

Text

Milling Address Alabama Power Company

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

s='/Zgy"' WabamaPower Docket No. 50-364 rua meen rwcream January 10, 1983 Director of Nuclear Reactor Regulation q u @'/

U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. S. A. Varga Joseph M. Farley Nuclear Plant - Unit 2 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-/600 Item Numbers Bl.13, Bl.14, B2.9 and B3.8. A complete description of the affected components, existing examination requi rements , bases of request for relief and proposed alternative examinations are contained in Attachment I.

This request is designated as Class I in accordance with 10CFR170.22 requirements since the original technical review was done for Unit 1 in compliance with our April 17, 1981 letter and as supplemented by our Janua ry 10, 1983 letter. Enclosed is a check for $400.00 to cover the total amount of additional fees required. This amount is remitted since this is a duplicate unit review with $4,000.00 submitted with the Unit 1 supplement request dated January 10, 1983.

Yours truly,

. f9 [Claytonh'

. Jr. [

STB:bs Enclosures cc: Mr. R. A. Thomas Mr. G. F. Trowbridge Mr. J. P. O'Reilly Mr. E. A. Ree ns Mr. W. H. Bradtird /pl q

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9301180091 830110 PDR ADOCK 05000364 P PDR

d - - a ATTACHMENT I 2.13.13 RELIEF REQUEST COMP 0NENT: CODE CLASS: 1 Reactor Vesel Closure Head Cladding, Reactor Vessel Cladding, Pressurizer Cladding and Steam Generator Cladding (Item Numbers 81.13, Bl.14, B2.9, and B3.8, Examination Categories B-I-1 and B-I-2).

EXAMINATION REQUIREMENT:

Visual and surface or volumetric examination of the reactor vessel closure head cladding shall include at least six patches (each 36 sq. in.) evenly distributed in the closure head. 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 prima ry 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:

Reactor vessel closure head cladding patches and the pressurizer and steam generator cladding examinations, which must be performed by manual inspections under the head or 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 ba rrel that enable the use of cameras to assist in the examination.

ALTERNATIVE EXAMINATION:

The reactor vessel closure head welds are volumetrically examined per Table

. IWB-2600, Item Bl.2 Category B-B and Item 81.3 Category B-C. The closure head cladding adjacent to the welds is also examined volumetrically since Section XI requires that the base material for one wall thickness on each

! side of the weld also be examined. Although the clad areas adjacent to the welds are not " evenly distributed" as required in Category B-I-1, the total area of examinations as required by Categories B-B and B-C far exceed those of Category B-I-1.

Therefore, the weld examinations per items 81.2 and B1.3 will be used to satisfy the requirements of Item Bl.13.

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d Attachment I 2.13.13 Relief Request Page 2

The reactor vessel longitudinal and ci rcumferential shell welds are volumetrically examined per Table IWB-2600, Item Bl.1 Category B-A and Item Bl.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 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.

CONCLUSION:

4 Volumetric examinations which are required for the longitudinal and

circumferential welds in vessels and in the reactor vessel closure head provide sufficient evidence of component structural integrity. Additional support for not requi ring the present inspections is that later NRC s

approved editions of Section XI no longer require cladding inspections but allow for volumetric examinations. Based on this guidance, no additional cladding examinations will be performed for categories B-I-1 and B-I-2.

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