ML20062F957

Forwards Evaluation of Indication in Joseph Farley Unit 2 Steam Generator C Upper Shell to Transition Cone Girth Weld. Nonproprietary WCAP-12447,WCAP-12213 & Proprietary WCAP-12211 Also Encl

ML20062F957
Person / Time
Site:	Farley
Issue date:	11/20/1990
From:	Hairston W ALABAMA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19310C929	List: ML20062F957 ML20062F967 ML20062F968 ML20062F976 ML20062F978
References
IEIN-90-004, IEIN-90-4, NUDOCS 9011280285
Download: ML20062F957 (3)

Text

-

i Alabsima Power Company '

40 inverness Center Parkway Post Office Box 1295 Dirmingnam. Alabame 35201 Telephone 20$ 808 $$81 W. O. Hairston, til SonKw Vee President Nueear overanons Alabama b'er November 20, 1990 '****#M"'"'

10CFR50.55a(g)

Docket No. 50-364 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Vashington, D. C. 20555 Gentlemen:

l l Joseph H. Farley Nuclear Plant - Unit 2' l Evaluation of Steam Generator 2C Upper Transition Cone-to-Shell Girth Veld Indication During the Unit 2 seventh refueling outage, an augmented ultrasonic examination was performed on a portion of the 2C steam generator upper transition cone-to-shell girth veld. Examination results concluded that one indication exceeded the Section XI acceptance criteria.

-Evaluation determined that the indication has a through vall dimension of' O.35 inches, a length of 4.0 inches and is classified as subsurface. The indicat!on is located r. ear the backside of the veld and has been characterized as r. ser.er of small veld inclusions and/or voids resulting.from fabrication.

The ir. side nrface of the girth veld area vas visually examined and found to be accep t able.e. There were no indications of pitting or cracking of the type-typically found at other plants which have experienced cracking in the girth veld regior.. '

Examination personnel, procedures and techniques utilized met or exceeded the requirements of the 1983 Edition through the Summer 1983 Addenda of the ASME Code,Section XI and Information Notice 90-04. Persohnel performing.the visual examination had previously performed similar girth veld examinations at several other plants where cracking had been detected.

Iy, 1 1

A. .

] i I

1 U. S. Nuclear Regulatory Commission Page 2 ]

Enclosure 1 provides an ultrasonic exainination data summary, visual r.xamination results, preservice and inservice extmination results, results of reviews of the fabrication radiographs, discussians of indication characterization and l

determination of acceptability based os fracture mechanics analysis, i Enclosure 2 includes the following docun.tnts which make up the flaw evaluation  ;

handbook for Farley Nuclear Plant

1. I copy of WCAP-12211 " Background and Technical Basis Handbook on Flav Evaluation for the Farley Units 1 & 2 Main Coolant System and Components"

( (Proprietary).

2. I copy of WCAP-12447, " Background and Technical Basis Handbook on Flav  ;

Evaluation for the Farley Units 1 & 2 Main Coolant System and Components" (Non-Proprietaty).

P

3. 1 copy of VCAP-12213, Revision 1, " Handbook on Flav Evaluation for Joseph ,

Farley Units 1 and 2 Steam Generators and Pressurisers" (Non-Proprietary).

Also enclosed are a Vestinghouse authorization letter (CAV-90-092),

accompanying affidavit, Proprietary Information Notice, and Copyright Notice.

l As Item 1 contains information proprietary to'Vestinghouse Electric Corporation, it is-supported by an affidavit signed by Vestinghouse, the owner j of the information. The afildavit sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations l!sted in paragraph (b)(4) of Section 2.790 of the Commission's regulations.

Accordingly, it is respectfully requested that the information which is i proprietary to Vestinghouse be withheld from public disclosure in accordance with 10 CFR Section 2.790 of the Commission's regulations.

Correspondence with respect to the copyright or proprietary aspects of the items listed above or the supporting Vestinghouse affidavit should reference CAV-90-092 and should be addressed to R. A. Viesemann, Manager of Regulatory i Legislative Affairs, Vestinghouse Electric Corporation, P.O. Box 355, l l P.ttsburgh, Pennsylvania 15230-0355. I VCAP-12213, Appendix A-6 provides the fracture mechanics analysis.results applicable to the upper transition cone-to-shell girth veld. VCAP-12211 contains the supporting bases including material fracture mechanics properties, stress intensity factors, operating transients in the design bases,.fatigus evaluation and crack growth analysis which vere prepared in'accordance with the ASME Code,Section XI, 1983 Edition through the Summer 1983 Addenda.

A fracture mechanics analysis was performed as summarized in Enclosures 1 and 2 which concludeo that the indication-is acceptable based on the criteria of i l Section XI, IVB-3600. Pursuant to the requiremants of Section XI, IVB-3125(b), l Alabama Power company herewith submits the evaluation analyses documenting the l l

i I

I t U. S. Nuclear Regulatory Commission Page 3 acceptability of this indication. Alabama Power Company furthermore requests that the NRC approve the acceptable disposition of this indication based on -

this evaluation analysis as required by Section XI, IVB-3610(b). ,

Pursuant to Technical Specification 3.4.11(b), it is respectfully requested that this approval be granted no later than December 19, 1990, as this is the  ;

date tenta ively scheduled for the reactor coolant system temperature to be  :

raised abovt 200' F for Mode 4 operation. Approval by this date vill prevent i extension of the outage beyond the current schedule.

Respectfully submitted.

ALABAMA POWER COMPANY ft). . 5 V. G. Hairston, III VGH/DEH/STBicht-nre.8.40 l Enclosures cc Mr. S. D. Ebneter Mr. S. T. Hoffman Mr. G. F. Maxwell f

v