ML042740664
| ML042740664 | |
| Person / Time | |
|---|---|
| Site: | Indian Point, Pilgrim, FitzPatrick  |
| Issue date: | 10/14/2004 |
| From: | Richard Laufer NRC/NRR/DLPM/LPD1 |
| To: | Kansler M Entergy Nuclear Operations |
| Milano P, NRR/DLPM , 415-1457 | |
| References | |
| TAC MC2637, TAC MC2638, TAC MC2639, TAC MC2640 | |
| Download: ML042740664 (12) | |
Text
October 14, 2004 Mr. Michael R. Kansler, President Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
RELIEF REQUEST NOS. R-33, R-71, R 3-40(A) AND R-41, JAMES A.
FITZPATRICK NUCLEAR POWER PLANT, INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND NO. 3 AND PILGRIM NUCLEAR POWER STATION (TAC NOS. MC2637, MC2639, MC2640, AND MC2638)
Dear Mr. Kansler:
By letter dated April 14, 2004, Entergy Nuclear Operations, Inc. (the licensee), requested relief from the inservice inspection (ISI) requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, 1989 Edition, for the James A. Fitzpatrick Nuclear Power Plant (JAF), Indian Point Nuclear Generating Unit Nos. 2 and 3 (IP2 and 3), and the Pilgrim Nuclear Power Station (Pilgrim). Specifically, the licensee proposed to use the requirements in the 1998 Edition, 2000 Addenda of the ASME Code Section XI, Table IWB-2500-1, Category B-G-1, Item B6.30, for the examination of reactor vessel head pressure closure studs (when removed).
The Nuclear Regulatory Commission (NRC) has reviewed the proposed use of the later ASME Code edition in the subject relief requests. The results are provided in the enclosed safety evaluation. In a letter dated July 15, 2004, the NRC staff issued a request for additional information regarding the relief requests. However, on July 28, 2004, the NRC issued Regulatory Issue Summary 2004-12, Clarification on Use of Later Editions and Addenda to the ASME OM Code and Section XI, which precluded the need for this additional information.
Therefore, in a conference call with the licensee staff on August 30, 2004, the NRC staff informed the licensee that a response to the RAI was not required.
In accordance with 10 CFR 50.55a(g)(4)(iv), the NRC staff approves the use of the 1998 Edition, 2000 Addenda of the ASME Code,Section XI, Table IWB-2500-1, Category B-G-1, Item B6.30, for the ISI of reactor vessel head pressure closure studs (when removed). The use of this Code edition is authorized for the remainder of the third 10-year ISI interval, which is until September 27, 2006, for JAF, until April 3, 2006, for IP2, until July 20, 2009, for IP3, and until June 30, 2005, for Pilgrim. All other requirements of the ASME Code,Section III and XI, remain applicable, including third party review by the Authorized Nuclear Inservice Inspector.
M. Kansler If you have any questions regarding this approval, please contact the JAF, IP2 and IP3 Project Manager, Patrick Milano, at 301-415-1457 or the Pilgrim Project Manager, Lee Licata, at 301-415-4090.
Sincerely,
/RA/
Richard J. Laufer, Chief, Section 1 Project Directorate I Division of Licensing Project Management Office of Reactor Regulation Docket Nos. 50-333, 50-247, 50-286, and 50-293
Enclosure:
Safety Evaluation cc w/encl: See next page
- No substantive changes made OFFICE PDI-1/PM PDI-2/PM PDI-1/LA EMCB*
OGC PDI-1/SC NAME PMilano LLicata SLittle SCoffin HMcGurren RLaufer DATE 09/30/04 09/27/04 09/30/04 09/27/04 10/8/04 10/13/04
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. Theodore A. Sullivan 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. Danny L. Pace Vice President, Engineering Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Brian OGrady Vice President, Operations Support Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. John F. McCann Director, Nuclear Safety Assurance 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. William Maquire Director, Nuclear Safety Assurance Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093 Mr. Andrew Halliday Manager, Regulatory Compliance Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093 Supervisor Town of Scriba Route 8, Box 382 Oswego, NY 13126 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 Oswego County Administrator Mr. Steven Lyman 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 Mr. John M. Fulton Assistant General Counsel Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Ken L. Graesser BWR SRC Consultant 38832 N. Ashley Drive Lake Villa, IL 60046 Mr. Jim Sniezek Nuclear Management Consultant 5486 Nithsdale Drive Salisbury, MD 21801 Mr. Ron Toole BWR SRC Consultant 1282 Valley of Lakes Box R-10 Hazelton, PA 18202 Ms. Stacey Lousteau Treasury Department Entergy Services, Inc.
639 Loyola Avenue Mail Stop L-ENT-15E New Orleans, LA 70113 Ms. Deb Katz, Executive Director Nuclear Security Coalition c/o Citizens Awareness Network P.O. Box 83 Shelburne Falls, MA 01370
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 Mr. Alex Matthiessen Executive Director Riverkeeper, Inc.
25 Wing & Wing Garrison, NY 10524 Mr. Paul Leventhal The Nuclear Control Institute 1000 Connecticut Avenue NW Suite 410 Washington, DC, 20036 Mr. Karl Coplan Pace Environmental Litigation Clinic 78 No. Broadway White Plains, NY 10603 Mr. 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
Pilgrim Nuclear Power Station cc:
Resident Inspector U. S. Nuclear Regulatory Commission Pilgrim Nuclear Power Station Post Office Box 867 Plymouth, MA 02360 Chairman, Board of Selectmen 11 Lincoln Street Plymouth, MA 02360 Chairman, Duxbury Board of Selectmen Town Hall 878 Tremont Street Duxbury, MA 02332 Office of the Commissioner Massachusetts Department of Environmental Protection One Winter Street Boston, MA 02108 Office of the Attorney General One Ashburton Place 20th Floor Boston, MA 02108 Dr. Robert M. Hallisey, Director Radiation Control Program Commonwealth of Massachusetts Executive Offices of Health and Human Services 174 Portland Street Boston, MA 02114 Regional Administrator, Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. John M. Fulton Assistant General Counsel Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Steve Brennion Supt., Regulatory & Industry Affairs Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill Road, M/S 1 Plymouth, MA 02360-5508 Mr. Jack Alexander Manager, Reg. Relations and Quality Assurance Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5599 Mr. David F. Tarantino Nuclear Information Manager Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5599 Ms. Jane Perlov Secretary of Public Safety Executive Office of Public Safety One Ashburton Place Boston, MA 02108 Mr. Stephen J. McGrail, Director Attn: James Muckerheide Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 01702-5399 Chairman Nuclear Matters Committee Town Hall 11 Lincoln Street Plymouth, MA 02360 Mr. William D. Meinert Nuclear Engineer Massachusetts Municipal Wholesale Electric Company P.O. Box 426 Ludlow, MA 01056-0426
Pilgrim Nuclear Power Station cc:
Mr. Michael A. Balduzzi Site Vice President Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5508 Mr. William J. Riggs Director, Nuclear Assessment Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5508 Mr. Bryan S. Ford Manager, Licensing Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5508 Senior Resident Inspector U.S. Nuclear Regulatory Commission Pilgrim Nuclear Power Station 600 Rocky Hill Road Mail Stop 66 Plymouth, MA 02360-5508 Mr. James Sniezek BWR SRC Consultant 5486 Nithsdale Drive Salisbury, MD 21801
Enclosure SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUESTS FROM IWC-2500 REQUIREMENTS AND THE USE OF CODE CASE N-663 JAMES A. FITZPATRICK NUCLEAR POWER PLANT INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 PILGRIM NUCLEAR POWER STATION DOCKET NOS. 50-333, 50-247, 50-286, AND 50-293
1.0 INTRODUCTION
By letter dated April 14, 2004, Entergy Nuclear Operations, Inc. (the licensee), submitted a relief request from certain inspection requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, for James A. FitzPatrick Nuclear Power Plant (JAF), Indian Point Nuclear Generating Unit Nos. 2 and 3 (IP2 and 3), and Pilgrim Nuclear Power Station (Pilgrim). Specifically, the licensee proposed using the requirements in a later edition of the ASME Code for the examination of reactor vessel head pressure closure studs (when removed). The licensee requested approval to use the requirements in the 1998 Edition, 2000 Addenda of the ASME Code Section XI, Table IWB-2500-1, Category B-G-1, Item B6.30. The request is for the remainder of the third 10-year inservice inspection (ISI) interval.
2.0 REGULATORY EVALUATION
Inservice inspection of the ASME Code Class 1, 2, and 3 components is to be performed in accordance with Section XI of the ASME Code and applicable addenda as required by 10 CFR 50.55a(g), except where specific relief has been granted by the Commission pursuant to 10 CFR 50.55a(6)(g)(i). 10 CFR 50.55a(a)(3) states that alternatives to the requirements of paragraph (g) may be used, when authorized by the NRC, if the applicant demonstrates that:
(i) the proposed alternatives would provide an acceptable level of quality and safety or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, to the extent practical, within the limitations of design, geometry, and construction materials of the components. The regulations require that inservice examination of components and system pressure tests conducted during the first 10-year interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) twelve months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. The code of record for the FitzPatrick, IP2 and 3, and Pilgrim third 10-year ISI intervals is the 1989 Edition (no Addenda) of the ASME Code.
3.0 TECHNICAL EVALUATION
3.1 Code Requirement The 1989 Edition of the ASME Code,Section XI Table IWB-2500-1, Category B-G-1 for Item No. B6.30 requires that examinations of the reactor closure head studs include both a surface and volumetric method when removed.
3.2 System/Components ASME Class 1 Reactor Pressure Vessel Closure Head Studs when removed, Item No. B6.30.
3.3 Licensees Proposal The licensee requests to use the 1998 Edition, 2000 Addenda of the ASME Code,Section XI, Table IWB -2500-1 for Category B-G-1, Item B6.30, for the reactor vessel head pressure retaining bolting and all associated requirements, if any, as allowed by 10 CFR 50.55a(g)(4)(iv).
3.4 Licensees Basis The licensee states that the 1998 Edition, up to the 2000 Addenda of the ASME Code,Section XI, has been incorporated by reference into 10 CFR 50.55a(b). Thus, there are no related requirements in the 1998 Edition, 2000 Addenda of the Code for Category B-G-1, Item B6.30 that would need to be implemented.
3.5 Staff Evaluation The licensee proposes to use the 1998 Edition, 2000 Addenda, of the ASME Code,Section XI, Table IWB-2500-1 for Category B-G-1, Item B6.30, reactor vessel closure studs (when removed).
The 1989 Edition, Table IWB-2500-1, Category B-G-1, for Item No. B6.30 requires both surface and volumetric examinations of the closure studs when removed. The 1998 Edition, 2000 Addenda requires either a surface or a volumetric examination. This change to Table IWB-2500-1 examination criteria does not affect other parts of the Code. In addition, the 1998 Edition, 2000 Addenda has been reviewed and endorsed by the NRC staff, and has been incorporated by reference in 10 CFR 50.55a(b). Therefore, the licensees proposed alternative provides reasonable assurance of quality and safety.
4.0 CONCLUSION
Because the ASME Code 1998 Edition, 2000 Addenda has been incorporated by reference in 10 CFR 50.55a(b) and this edition does not affect related requirements, the NRC staff concludes that the licensees proposed alternative provides an acceptable level of quality and safety. Therefore, the licensees request to use ASME Code, 1998 Edition, 2000 Addenda,Section XI, Table IWB-2500-1, Category B-G-1, Item No. B6.30 is approved in accordance with 10 CFR 50.55a(g)(4)(iv). All other requirements of the ASME Code,Section III and XI, remain applicable, including third party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor: A. Black Date: October 14, 2004