ML042020609

RAI, Regarding Relief Request Nos. RR-62 and 3-32 Concerning Embedded Flaw Repair Methods, Indian Point Nuclear Generating Unit Nos. 2 and 3

ML042020609
Person / Time
Site:	Indian Point
Issue date:	07/20/2004
From:	Milano P NRC/NRR/DLPM/LPD1
To:	Kansler M Entergy Nuclear Operations
Milano P, NRR/DLPM 415-1457
References
TAC MC3281, TAC MC3282
Download: ML042020609 (5)

Text

July 20, 2004 Mr. Michael R. Kansler, President Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST NOS. RR-62 AND 3-32 CONCERNING EMBEDDED FLAW REPAIR METHODS, INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 (TAC NOS. MC3281 AND MC3282)

Dear Mr. Kansler:

By letter dated May 25, 2004, Entergy Nuclear Operations, Inc. (Entergy) submitted relief requests (RRs) 62, Revision 1, and 3-32, Revision 1, regarding proposed alternative repair methods and examination techniques for Indian Point Nuclear Generating Unit Nos. 2 and 3.

Specifically, Entergy has proposed an alternative to the requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code to use the embedded flaw process for the repair of reactor vessel head penetrations, if necessary.

The Nuclear Regulatory Commission staff is reviewing your request and has determined that additional information is necessary in order to complete its evaluation. The specific question is in the enclosed request for additional information (RAI). During a telephone call on July 12, 2004, the Entergy staff indicated that a response to the RAI would be provided within 60 days.

Sincerely,

/RA/

Patrick D. Milano, Sr. Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286

Enclosure:

As stated cc w/encl: See next page

ML042020609 OFFICE PDI-1/PM PDI-1/LA EMCB/SC PDI-1/SC NAME PMilano SLittle TChan RLaufer DATE 07/14/04 07/14/04 07/15/04 07/20/04 Indian Point Nuclear Generating Unit No. 2 and 3 cc:

Mr. Gary Taylor Ms. Charlene Faison Chief Executive Officer Manager, Licensing Entergy Operations, Inc. Entergy Nuclear Operations, Inc.

1340 Echelon Parkway 440 Hamilton Avenue Jackson, MS 39213 White Plains, NY 10601 Mr. John Herron Director of Oversight Senior Vice President and Entergy Nuclear Operations, Inc.

Chief Operating Officer 440 Hamilton Avenue Entergy Nuclear Operations, Inc. White Plains, NY 10601 440 Hamilton Avenue White Plains, NY 10601 Mr. James Comiotes Director, Nuclear Safety Assurance Mr. Fred Dacimo Entergy Nuclear Operations, Inc.

Vice President, Operations Indian Point Energy Center Entergy Nuclear Operations, Inc. 295 Broadway, Suite 2 Indian Point Energy Center P.O. Box 249 295 Broadway, Suite 2 Buchanan, NY 10511-0249 P.O. Box 249 Buchanan, NY 10511-0249 Mr. Patric Conroy Manager, Licensing Mr. Christopher Schwarz Entergy Nuclear Operations, Inc.

General Manager, Plant Operations Indian Point Energy Center Entergy Nuclear Operations, Inc. 295 Broadway, Suite 2 Indian Point Energy Center P. O. Box 249 295 Broadway, Suite 2 Buchanan, NY 10511-0249 P.O. Box 249 Buchanan, NY 10511-0249 Mr. John M. Fulton Assistant General Counsel Mr. Dan Pace Entergy Nuclear Operations, Inc.

Vice President Engineering 440 Hamilton Avenue Entergy Nuclear Operations, Inc. White Plains, NY 10601 440 Hamilton Avenue White Plains, NY 10601 Regional Administrator, Region I U.S. Nuclear Regulatory Commission Mr. Randall Edington 475 Allendale Road Vice President Operations Support King of Prussia, PA 19406 Entergy Nuclear Operations, Inc.

440 Hamilton Avenue Senior Resident Inspector, Indian Point 3 White Plains, NY 10601 U. S. Nuclear Regulatory Commission 295 Broadway, Suite 1 Mr. John McCann P.O. Box 337 Director, Nuclear Safety Assurance Buchanan, NY 10511-0337 Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601

Indian Point Nuclear Generating Unit No. 2 and 3 cc:

Mr. Peter R. Smith, President Mr. Dan C. Poole New York State Energy, Research, and PWR SRC Consultant Development Authority 20 Captains Cove Road Corporate Plaza West Inglis, FL 34449 286 Washington Avenue Extension Albany, NY 12203-6399 Mr. William T. Russell PWR SRC Consultant Mr. Paul Eddy 400 Plantation Lane Electric Division Stevensville, MD 21666-3232 New York State Department of Public Service Mr. Alex Matthiessen 3 Empire State Plaza, 10th Floor Executive Director Albany, NY 12223 Riverkeeper, Inc.

25 Wing & Wing Mr. Charles Donaldson, Esquire Garrison, NY 10524 Assistant Attorney General New York Department of Law Mr. Paul Leventhal 120 Broadway The Nuclear Control Institute New York, NY 10271 1000 Connecticut Avenue NW Suite 410 Mayor, Village of Buchanan Washington, DC, 20036 236 Tate Avenue Buchanan, NY 10511 Mr. Karl Coplan Pace Environmental Litigation Clinic Mr. Ray Albanese 78 No. Broadway Executive Chair White Plains, NY 10603 Four County Nuclear Safety Committee Westchester County Fire Training Center Mr. Jim Riccio 4 Dana Road Greenpeace Valhalla, NY 10592 702 H Street, NW Suite 300 Ms. Stacey Lousteau Washington, DC 20001 Treasury Department Entergy Services, Inc. Mr. Robert D. Snook 639 Loyola Avenue Assistant Attorney General Mail Stop: L-ENT-15E State of Connecticut New Orleans, LA 70113 55 Elm Street P.O. Box 120 Mr. William DiProfio Hartford, CT 06141-0120 PWR SRC ConsultaNT 139 Depot Road East Kingston, NH 03827

Indian Point Nuclear Generating Unit No. 2 and 3 cc:

Mr. David Lochbaum Nuclear Safety Engineer Union of Concerned Scientists 1707 H Street NW, Suite 600 Washington, DC 20006

REQUEST FOR ADDITIONAL INFORMATION (RAI)

REGARDING RELIEF REQUESTS 62, REVISION 1, AND 3-32, REVISION 1 ON ALTERNATE REPAIR AND EXAMINATION METHODS INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 (IP2 AND 3)

DOCKET NOS. 50-247 AND 50-286 Relief Request (RR) 3-32, Revision 1, states in Proposed Alternative that: The embedded flaw repair overlay welds on the inside diameter (ID) and the outside diameter (OD) of the penetration tube material will consist of a minimum of 2 deposited layers of weld, consistent with References 3, 4, and 5 to minimize welding induced residual stresses and material distortion. Reference 4 is the NRC safety evaluation for Palo Verde Nuclear Generating Station, and Reference 5 is not identified. As stated in your May 25, 2004, letter to the NRC, RR 3-32, Revision 1, is similar to RR 62, Revision 1, for IP2. RR 62 makes reference, in part, to the Westinghouse Topical Report, WCAP-15987-P-A, Revision 2. It is not clear how References 4 and 5 apply to RR 3-32. Provide the specific aspects of References 4 and 5 that apply to this RR.

Enclosure