2CAN109902, Submits Withdrawal of Code Case N-593 for ANO-2 Replacement SGs
| ML20217G450 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/15/1999 |
| From: | Vandergrift J ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2CAN109902, NUDOCS 9910210290 | |
| Download: ML20217G450 (2) | |
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Entergy operations,Inc.
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Tel501858 5000 October 15,1999 2CAN109902 U. S. Nuclear Regulatory Commission Document ControlDesk Mail Station OPI-17 Washington, DC 20555
Subject:
Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 Withdrawal of Code Case N-593 for ANO-2 Replacement Steam Generators Gentlemen:
On October 30,1998 (2CAN109803), Entergy Operations requested NRC approval for the use of ASME Code Case N-593, Mternatin Examination Requirementsfor Steam Generator Nozzle to Vessel Welds, for the inservice inspection (ISI) of the steam generator nozzle-to-vessel welds on the Arkansas Nuclear One, Unit 2 (ANO-2) replacement steam generators. The ANO-2 replacement steam generators are being fabricated with cylindrical section primary nozzles welded to integrally forged contours on the primary head. ASME Section XI, IWB-2500 for the Examination Category B-D does not provide for the volumetric examination of this type of steam generator nozzle-to-vessel welds. In lieu of a two-sided examination, this code case provides for a single-sided examination as an alternative for ISI weld inspection coverage.
Subsequent to the submittal, Entergy Operations has engaged in discussion with the NRC Staff for determining the acceptability of the code case. As a result of these discussions, NRC approval was dependent on Entergy Operations' commitment to pursue a Performance Demonstration Initiative (PDI) qualification process for the subject nozzles.
A revision of 10CFR50.55a was noticed in the Federal Register on September 22,1999 l
which required, among other changes, the application of Appendix VIII of the 1995 O
Edition /1996 Addenda of ASME Section XI for the PDI process over a staggered schedule. Currently, there are no provisions for inspection of steam generator weld configurations in Appendix VIII. Entergy Operations believes that committing to a PDI qualification process for these welds is premature in that guidance and test standards have 9
not been developed within the ASME Code at this time. Entergy Operations will not need o
to perform these ISI nozzle examinations until the upcoming interval, which will end in March of 2010. Depending on the future status of the ASME PDI requirements for steam 9910210290 991015 DR ADOCK 0500 8
Y U. S. NRC d
October 15,1999 2CAN109902 Page 2 tenerato,rs, Entergy Operations will evaluate the need to seek an alternative inspection process. Therefore, at this time we are withdrawing Code Case N-593 for NRC approval.
Very truly yours, r
Ji D. Vander Director, Nuclear Safety JDV/sab cc:
Mr. Ellis W. Merschoff Regional Administrator U. S. Nuclear Regulatory Commission RegionIV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 Mr. Chris Nolan NRR Project Manager RegionIV/ANO-2 U. S. Nuclear Regulatory Commission NRR Mail Stop 04-D-03 One White Flint North 11555 Rockville Pike -
Rockville, MD 20852