ML070850605
| ML070850605 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 04/02/2007 |
| From: | Tuan Le NRC/NRR/ADRO/DLR/RLRB |
| To: | Peter Dietrich Entergy Nuclear Operations |
| Le N. B., NRR/DLR/RLRB, 415-1458 | |
| References | |
| Download: ML070850605 (7) | |
Text
April 2, 2007 Mr. Peter T. Dietrich Site Vice President Entergy Nuclear Operations, Inc.
P.O. Box 110 Lycoming, NY 13093
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE JAMES A. FITZPATRICK NUCLEAR POWER PLANT, LICENSE RENEWAL APPLICATION
Dear Mr. Dietrich:
By letter dated July 31, 2006, Entergy Nuclear Operations, Inc., submitted an application pursuant to 10 CFR Part 54, to renew the operating license for James A. FitzPatrick Nuclear Power Plant, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review.
These requests for additional information were discussed with Rick Plasse, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-1458 or e-mail NBL@nrc.gov.
Sincerely,
/RA/
Tommy Le, Sr. Project Manager License Renewal Branch B Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-333
Enclosure:
Request for Additional Information cc w/encl: See next page
ML070850605 OFFICE LA:DLR PM:RLRB:DLR BC:RLRB:DLR NAME SFigueroa TLe RAuluck DATE 03/27/07 03/27/07 04/2/07
Enclosure JAMES A. FITZPATRICK NUCLEAR POWER PLANT (JAFNPP)
LICENSE RENEWAL APPLICATION (LRA)
REQUESTS FOR ADDITIONAL INFORMATION (RAI)
Table 3.1.2-1 RAI 3.1.2-1. In Table 3.1.2-1, the applicant applied time-limited aging analysis (TLAA)-metal fatigue as an aging management program to manage fatigue cracking for many Class 1 components such as reactor vessel internal attachments and welds, the incore monitor housing bolting, control rod drive (CRD) housings, CRD stub tubes, the CRD return line, the reactor vessel (the shell, upper and bottom head and the closure flange), and the reactor vessel nozzles (including safe ends and thermal sleeves) for various piping and instrumentation connections.
Chapter 4.3 of NUREG-1800 provides guidance on the metal fatigue analysis which is focused on the fatigue analysis based on the American Society of Mechanical Engineers (ASME) Code,Section III, of using cumulative usage factor concept. The ASME Code,Section III analysis assumes that no crack exists in the components. Chapter 4.3 of the Fitzpatrick license renewal application has addressed the requirements of the ASME Code,Section III fatigue calculations.
However, a metal fatigue analysis based on a known initial flaw should also be performed for those components that contain flaw(s). The calculation is performed to assess the stability of the final crack size of the affected component at the end of the license. This analysis will demonstrate that the component has sufficient fracture toughness to resist rapid crack propagation and thus arrest the crack. The method for this calculation would follow the ASME Code,Section XI. Chapter 4.3 of the FitzPatrick license renewal application discussed this analysis without providing much details.
Based on the above review, the staff requests the following additional information:
(a) Identify all the Class 1 components in Table 3.1.2-1 that contain indications or flaws remained in service at the FitzPatrick nuclear plant based on the acceptance criteria of the ASME Code,Section XI, (b) Discuss the flaw evaluations (such as procedures and assumptions) performed for the affected components in accordance with the ASME Code,Section XI, (c) Discuss the number of years assumed in the associated fatigue crack growth analysis, and (d) Discuss whether the affected components are demonstrated to be acceptable for the extended period of operation.
Letter to P. Dietrich from N. Le dated April 2, 2007 DISTRIBUTION:
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE JAMES A. FITZPATRICK NUCLEAR POWER PLANT, LICENSE RENEWAL APPLICATION
SUBJECT:
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FitzPatrick Nuclear Power Plant cc:
Mr. Gary J. Taylor Chief Executive Officer Entergy Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Mr. John T. Herron Sr. VP and Chief Operating Officer Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Peter T. Dietrich Site Vice President Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093 Mr. Kevin J. Mulligan General Manager, Plant Operations Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093 Mr. Oscar Limpias Vice President Engineering Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Christopher Schwartz Vice President, Operations Support Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. John F. McCann Director, Licensing Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Resident Inspector's Office James A. FitzPatrick Nuclear Power Plant U. S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, NY 13093 Ms. Charlene D. Faison Manager, Licensing Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Michael J. Colomb Director of Oversight Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. David Wallace Director, Nuclear Safety Assurance Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093 Mr. James Costedio Manager, Regulatory Compliance Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093 Assistant General Counsel Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271
FitzPatrick Nuclear Power Plant cc: Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Steven Lyman Oswego County Administrator 46 East Bridge Street Oswego, NY 13126 Mr. Peter R. Smith, President New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Mr. Paul Eddy New York State Dept. of Public Service 3 Empire State Plaza Albany, NY 12223-1350 Supervisor Town of Scriba Route 8, Box 382 Oswego, NY 13126 Mr. James H. Sniezek BWR SRC Consultant 5486 Nithsdale Drive Salisbury, MD 21801-2490 Mr. Michael D. Lyster BWR SRC Consultant 5931 Barclay Lane Naples, FL 34110-7306 Mr. Garrett D. Edwards 814 Waverly Road Kennett Square, PA 19348 Mr. Rick Plasse Project Manager, License Renewal Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093 Mr. James Ross Nuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-37