ML20213G996

Requests one-time Relief to Utilize ASME Code 1983 Edition Through Summer 1983 Addenda of Section XI Evaluation Stds for Inservice Insp Program as Alternative for Inappropriate 1974 Edition Through Summer 1975 Addenda

ML20213G996
Person / Time
Site:	Farley
Issue date:	11/10/1986
From:	Mcdonald R ALABAMA POWER CO.
To:	Rubenstein L Office of Nuclear Reactor Regulation
References
TAC-63521, NUDOCS 8611190013
Download: ML20213G996 (3)

Text

4 orth 18 h S reet Post Office Box 2641 Birmingham, Alabama 35291-0400 Telephone 205 250-1835 AlabamaPower

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sWW Mmsp nio V ce r sident November 10, 1986 Docket No. 50-348 Director, Nuclear Reactor Regulation U. S. Nuclear Regulatory Commisstor Washington, D. C. 20555 Attention: Mr. L. S. Rubenstein Gentlemen:

Joseph M. Farley Nuclear Plant - Unit 1 Inservice Inspection Program for ASME Code Class 1, 2 and 3 Components Alabama Power Company is presently completing ten year inservice inspection activities which were scheduled for performance during the Unit i seventh refueling outage. During performance of the required surface examination of one reactor coolant pipe-to-safe end weld on the C loop cold leg (inlet) pipe, a linear indication was found. Subsequent evaluation of this indication in accordance with the ASME Code,Section XI,1974 Edition through the Summer 1975 Addenda resulted in a determination that the evaluation criteria provided therein is inappropriate for use in dispositioning this indication. Therefore, one-time relief is requested to utilize the evaluation standards of the 1983 Edition through the Summer 1983 Addenda of Section XI as an acceptable alternative.

The linear indication is 0.25 inches in length and is located in the piping base material 21/2 inches from the edge of the pipe-to-safe end weld joint. During the preservice inspection numerous linear indications were discovered in this same location and were subsequently removed or reduced to an acceptable size by buffing. The remaining indications were then evaluated and dispositioned as being acceptable.

04) 8611190013 861110 I\

PDR ADOCK 05000348 O PDR i

a Director, Nuclear Reactor Regulation November 10, 1986 U. S. Nuclear Regulatory Comission Page 2 After detection of the indication during the current outage, an evaluation was made as required by paragraph IWB-3120 and Table IWB-3410 which reference the evaluation standards of paragraph IWB-3514 of the Sumer 1974 Addenda. This standard requires that surface indications not exceed five percent of the wall thickness. The indication depth is impossible to quantify utilizing surface examination methods.

Volumetric examinations of the affected area performed during preservice and inservice inspection did not detect any relevant indications. Thus the evaluation standards of the 1974 Edition through the Sumer 1975 Addenda are inappropriate for dispositioning this indication. Based on this consideration, Alabama Power Company requests one-time relief from these requirements pursuant to 10CFR50.55 a(g)(6)(i).

As an alternative, Alabama Power Company proposes to utilize the acceptance standards of the ASME Code,Section XI,1983 Edition through the Summer 1983 Addenda for the disposition of this indication.

Paragraph IWB-3514.3 and Table IWB-3514-2 provide sufficient guidance for evaluation of indications detected by surface methods. This criteria permits a linear indication found inservice of 0.51 inches for the pipe thickness in question, which is well in excess of the measured length of the existing indication.

The requested relief is summarized on the attached page and is needed to permit proper disposition of this indication prior to returning Unit 1 to service. The current critical path outage schedule indicates that return to service will begin by 6:00 P.M. on Thursday, November 13, 1986. The NRC is therefore requested to grant this relief prior to this time in order to prevent the extension of the outage.

Enclosed is the required application fee of $150.00. If there are any questions or if additional information is needed, please advise.

Respectfully submitted,

_U R. P. Mcdonald RPM / STB /cs1:0391 Attachment cc: Mr. L. B. Long Dr. J. N. Grace Mr. E. A. Reeves ifr. W. H. Bradford

e ATTACHMENT RELIEF REQUEST: Relief is requested from the evaluation criteria of IWB-3514.1 of the A5ME Code,Section XI,1974 Edition through the Summer 1975 Addenda for evaluating one indication found in the reactor coolant pipe-to-safe end weld (Item B4.1, Category B-F).

Evaluation Requirements:

The ASME Code,Section XI,1974 Edition through the Summer 1975 Addenda, Paragraph IWB-3120 and Table IWB-3410 require that evaluation of indications found during nondestructive examination be performed in accordance with paragraph IWB-3514.1.

Relief Request:

Relief is requested from evaluating the linear indication detected by surface examination methods performed on one reactor coolant pipe-to-safe end weld (Item B4.1, Category B-F) in accordance with the ASME Code,Section XI,1974 Edition through the Summer 1975 Addenda, paragraph IWB-3514.1.

Basis for Relief:

The existing evaluation requirements are inappropriate for the evaluation of linear indications detected by surface methods, particularly where the depth of the indication cannot be quantified. Volumetric examination does not detect the presence of the indication.

Proposed Alternate Evaluation:

The indication found during performance of the surface examination of the reactor coolant pipe-to-safe end weld (Item 84.1, Category B-F) will be evaluated in accordance with the ASME Code,Section XI, paragraph IWB-3514.3, 1983 Edition through the Summer 1983 Addenda.