ML040760084
| ML040760084 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 03/15/2004 |
| From: | Milano P NRC/NRR/DLPM/LPD1 |
| To: | Kansler M Entergy Nuclear Operations |
| Milano P, NRR/DLPM , 415-1457 | |
| References | |
| TAC MC1698, TAC MC1699 | |
| Download: ML040760084 (7) | |
Text
March 15, 2004 Mr. Michael R. Kansler, President Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUESTS TO USE CODE CASE N-613-1 FOR REACTOR VESSEL NOZZLE TO VESSEL WELD INSPECTIONS, INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 (TAC NOS. MC1698 AND MC1699)
Dear Mr. Kansler:
In a letter dated December 30, 2003, Entergy Nuclear Operations, Inc. (ENO) submitted Relief Request Nos. RR-67 and RR 3-36 for Indian Point Nuclear Generating Unit Nos. 2 and 3 (IP3),
respectively. In the relief requests, ENO proposed to perform the inspection of Class 1, Category B-D, reactor pressure vessel nozzle to vessel welds, using the alternative examination requirements in American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-613-1.
The Nuclear Regulatory Commission staff is reviewing the information provided in the December 30 submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). During a telephone call on March 10, 2004, the ENO staff indicated that a response to the RAI would be provided within 30 days.
If you should have any questions, please do not hesitate to call me.
Sincerely,
/RA/
Patrick D. Milano, Sr. Project Manager, Section 1 Project Directorate 1 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286
Enclosure:
RAI cc w/encl: See next page
March 15, 2004 Mr. Michael R. Kansler, President Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUESTS TO USE CODE CASE N-613-1 FOR REACTOR VESSEL NOZZLE TO VESSEL WELD INSPECTIONS, INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 (TAC NOS. MC1698 AND MC1699)
Dear Mr. Kansler:
In a letter dated December 30, 2003, Entergy Nuclear Operations, Inc. (ENO) submitted Relief Request Nos. RR-67 and RR 3-36 for Indian Point Nuclear Generating Unit Nos. 2 and 3 (IP3),
respectively. In the relief requests, ENO proposed to perform the inspection of Class 1, Category B-D, reactor pressure vessel nozzle to vessel welds, using the alternative examination requirements in American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-613-1.
The Nuclear Regulatory Commission staff is reviewing the information provided in the December 30 submittal and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). During a telephone call on March 10, 2004, the ENO staff indicated that a response to the RAI would be provided within 30 days.
If you should have any questions, please do not hesitate to call me.
Sincerely,
/RA/
Patrick D. Milano, Sr. Project Manager, Section 1 Project Directorate 1 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-224 and 50-286
Enclosure:
RAI cc w/encl: See next page DISTRIBUTION PUBLIC PDI-1 Reading A. Howe R. Laufer P. Milano T. Chan S. Little B. McDermott, R-I E. Andruszkiewicz OGC G. Hill (2)
ACRS C. Bixler, R-I Document Name: ML040760084.wpd Accession Number: ML040760084
- See previous concurrence OFFICE PDI-1:PM PDI-1:LA EMCB:SC*
PDI-1:SC NAME PMilano SLittle TChan RLaufer DATE 03/10/04 03/10/04 03/08/04 03/11/04 OFFICIAL RECORD COPY
Indian Point Nuclear Generating Unit Nos. 2 & 3 cc:
Mr. Gary Taylor Chief Executive Officer Entergy Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Mr. John Herron Senior Vice President and Chief Operating Officer Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Fred Dacimo Vice President, Operations Entergy Nuclear Operations, Inc.
Indian Point Energy Center 295 Broadway, Suite 2 P.O. Box 249 Buchanan, NY 10511-0249 Mr. Christopher Schwarz General Manager, Plant Operations Entergy Nuclear Operations, Inc.
Indian Point Energy Center 295 Broadway, Suite 2 P.O. Box 249 Buchanan, NY 10511-0249 Mr. Dan Pace Vice President Engineering Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Randall Edington Vice President Operations Support Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. John McCann Director, Nuclear Safety Assurance Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Ms. Charlene Faison Manager, Licensing Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Director of Oversight Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. James Comiotes Director, Nuclear Safety Assurance Entergy Nuclear Operations, Inc.
Indian Point Energy Center 295 Broadway, Suite 2 P.O. Box 249 Buchanan, NY 10511-0249 Mr. Patric Conroy Manager, Licensing Entergy Nuclear Operations, Inc.
Indian Point Energy Center 295 Broadway, Suite 2 P. O. Box 249 Buchanan, NY 10511-0249 Mr. John M. Fulton Assistant General Counsel Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspector, Indian Point 2 U. S. Nuclear Regulatory Commission 295 Broadway, Suite 1 P.O. Box 38 Buchanan, NY 10511-0038
Indian Point Nuclear Generating Unit Nos. 2 & 3 cc:
Senior Resident Inspector, Indian Point 3 U. S. Nuclear Regulatory Commission 295 Broadway, Suite 1 P.O. Box 337 Buchanan, NY 10511-0337 Mr. Peter R. Smith, President New York State Energy, Research, and Development Authority Corporate Plaza West 286 Washington Avenue Extension Albany, NY 12203-6399 Mr. Paul Eddy Electric Division New York State Department of Public Service 3 Empire State Plaza, 10th Floor Albany, NY 12223 Mr. Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Mayor, Village of Buchanan 236 Tate Avenue Buchanan, NY 10511 Mr. Ray Albanese Executive Chair Four County Nuclear Safety Committee Westchester County Fire Training Center 4 Dana Road Valhalla, NY 10592 Ms. Stacey Lousteau Treasury Department Entergy Services, Inc.
639 Loyola Avenue Mail Stop: L-ENT-15E New Orleans, LA 70113 Mr. William DiProfio PWR SRC Consultant 139 Depot Road East Kingston, NH 03827 Mr. Dan C. Poole PWR SRC Consultant 20 Captains Cove Road Inglis, FL 34449 Mr. William T. Russell PWR SRC Consultant 400 Plantation Lane Stevensville, MD 21666-3232 Alex Matthiessen Executive Director Riverkeeper, Inc.
25 Wing & Wing Garrison, NY 10524 Paul Leventhal The Nuclear Control Institute 1000 Connecticut Avenue NW Suite 410 Washington, DC, 20036 Karl Coplan Pace Environmental Litigation Clinic 78 No. Broadway White Plains, NY 10603 Jim Riccio Greenpeace 702 H Street, NW Suite 300 Washington, DC 20001
Indian Point Nuclear Generating Unit Nos. 2 & 3 cc:
Mr. Robert D. Snook Assistant Attorney General State of Connecticut 55 Elm Street P.O. Box 120 Hartford, CT 06141-0120 Mr. David Lochbaum Nuclear Safety Engineer Union of Concerned Scientists 1707 H Street NW, Suite 600 Washington, DC 20006
Enclosure REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST NOS. RR-67 AND RR 3-36 INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 (IP2 AND 3)
DOCKET NOS. 50-247 AND 50-286 In a letter dated December 30, 2003, Entergy Nuclear Operations, Inc. (Entergy, the licensee) submitted requests for relief to use alternative non-destructive examination (NDE) requirements for the reactor pressure vessel (RPV) nozzle to vessel weld examinations. Specifically, the licensee has requested authorization to use American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-613-1, Ultrasonic Examination of Full Penetration Nozzles in Vessels, Examination Category B-D, Item Nos. B3.10 and B3.90, Reactor Nozzle-To-Vessel Welds, Figs. IWB-2500-7(a), (b), and (c),Section XI, Division 1. The Nuclear Regulatory Commission staff has the following questions regarding the information provided in the relief requests:
- 1.
The licensee states that, The examination (exam) volumes for the reactor vessel nozzle to vessel welds are unnecessarily large. It further state that, Entergy shall ensure that the high stressed areas of the [IP2 and 3] reactor vessel nozzle to shell welds shall be included in the examination.
Provide a description of the analyses and results to indicate the extent and magnitude of stresses associated with RPV nozzle-to-vessel welds at IP2 and 3 in support of the contention that highly stressed areas of the reactor vessel nozzle to shell welds will be included in the examination.
- 2.
The weld sketches shown on the WesDyne sketches (Attachment 2 to the December 30 letter) are idealized drawings, which infer that the welds were square butt welds and welded perfectly. Since the welds to be examined are not ideal, perfect welds, it is unclear how the licensee will be able to precisely locate the extremities (widest sections) of the nozzle-to-vessel welds. It is unclear how repaired areas (fabrication or inservice) extending beyond the ideal weld cross-sectional area are identified, and how these areas will be examined.
a.
Discuss the documentation available of the actual cross-sectional dimensions and precise locations of repaired areas for all RPV nozzle-to-vessel welds at IP2 and 3. Discuss the process for defining new examination volumes that encompass these repair weld areas.
b.
If examination personnel are to identify the extremities (widest sections) of the nozzle-to-vessel welds, what positive means of examination (such as weld etching) will be used to identify the weld extremities? Will the weld extremities be identified on both the inside and outside diameters of the vessel to ensure complete coverage of the welds?
c.
Describe the process for accurately determining the location of ultrasonic reflectors with respect to the proposed new examination volumes.
- 3.
In various sections of the relief requests, the licensee has defined the proposed reduced examination volume as: (a)...examination of the base material volume extending 1/2 inch from each side of the weld.; (b)...1/2 inch of base metal on each side of the thickest portion of the weld, (c)... 1/2 inch from the weld, and (d) The weld and surrounding 1/2 inch volume... These definitions can possibly be interpreted in different ways, some of which do not capture the requirements shown in Code Case N-613-1.
Revise the relief requests to define the examination volume in terms that are unambiguous and conform with Code Case N-613-1. If not, provide the justification.