LR-N08-0206, Inspection and Mitigation of Alloy 82/182 Pressurizer Butt Welds

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Inspection and Mitigation of Alloy 82/182 Pressurizer Butt Welds
ML082610223
Person / Time
Site: Salem  PSEG icon.png
Issue date: 09/10/2008
From: Braun R
Public Service Enterprise Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N08-0206
Download: ML082610223 (3)


Text

PSEG Nuclear LLC P.O. Box 236,, Hancocks Bridge, NJ 08038-0236 LRN0 0 PSEG SEP 1 0 2008 Nuclear L.L. C.

United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 SALEM GENERATING STATION - UNIT 1 AND UNIT 2 FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 NRC DOCKET NOS. 50-272 AND 50-311

Subject:

Inspection and Mitigation of Alloy 82/182 Pressurizer Butt Welds

Reference:

Letter LR-N07-0020, Inspection and Mitigation of Alloy 82/182 Pressurizer Butt Welds, dated January 26, 2007 In the above referenced letter, PSEG indicated that a review of "original design, fabrication and audit documentation indicates that Alloy 82/182/600 was not used for penetrations, steam space piping or welds." PSEG would like to offer a clarification of what constituted the "original design, fabrication and audit documentation" that comprised that review.

The documentation reviewed in preparing the referenced letter included:

" The Westinghouse summary stress reports for Salem Units 1 and 2.

, The onsite available design and fabrication drawings (i.e., Westinghouse supplied outline drawings with details of nozzles).

Documentation from vendor audits that were conducted during the construction of the Salem pressurizers.

These documents substantiated that instrument penetrations, heater sleeves and nozzle safe ends were manufactured from Type 316 stainless steel, and that the dissimilar metal welds between the low alloy steel nozzles and safe ends were protected from the reactor coolant environment with stainless steel interior cladding.

The above documentation was used to confirm information provided in Westinghouse prepared documents which were in the form of a WCAP and a WOG issued report, both of which show that no Alloy 600 material or Inconel 82/182 welding material had been used in the construction of the Salem 1 or 2 pressurizers.

Autic)

Document Control Desk LR-N08-0206 As a result of questions posed during a review of TI-1 72, Reactor Coolant System Dissimilar Metal Butt Welds, a joint meeting of the NRC, PSEG Nuclear, and Westinghouse was held to review Westinghouse proprietary information regarding the shop fabrication welds on the pressurizer in order to review actual nozzle to safe end filler weld metal documents.

During that meeting additional information was reviewed (e.g., weld transfer process sheets) that was not in Salem's possession because of its proprietary nature. This meeting re-affirmed that Alloy 82/182 weld material had not been used to make the dissimilar metal welds.

Our staff is available to meet with the NRC to discuss any of the information in this letter. If there are any questions, please contact Mr. A. Thomas Roberts at 856-339-1177.

Sincerely, Robert Braun Site Vice President - Salem

Document Control Desk LR-N08-0206 CC Mr. S. Collins, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. R. Ennis, Licensing Project Manager - Salem U. S. Nuclear Regulatory Commission Mail Stop 08B1 Washington, DC 20555 USNRC Senior Resident Inspector - (Salem X24)

Mr. P. Mulligan, Manager IV Bureau of Nuclear Engineering P. O. Box 415 Trenton, NJ 08625