ML060660132
| ML060660132 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 04/05/2006 |
| From: | Richard Laufer Plant Licensing Branch III-2 |
| To: | Kansler M Entergy Nuclear Operations |
| Bsingal NRR/DORL 415-3016 | |
| References | |
| TAC MC8300 | |
| Download: ML060660132 (7) | |
Text
April 5, 2006 Mr. Michael R. Kansler, President Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
PILGRIM NUCLEAR POWER STATION - RELIEF REQUEST NO.
PIL-05-R-002 (TAC NO. MC8300)
Dear Mr. Kansler:
By letter dated June 29, 2005, Entergy Nuclear Operations, Inc. (the licensee), proposed an alternative to use the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, 2001 Edition through the 2003 Addendum, in lieu of the 1998 Edition through the 2000 Addendum in regard to Subparagraph IWA-2210, Visual Examinations, including subsections IWA-2211 through IWA-2216.
The Nuclear Regulatory Commission staff has concluded that authorizing the visual examination requirements in Subparagraph IWA-2210 and subsections IWA-2211 through IWA-2216 of the 2001 Edition through the 2003 Addendum, in lieu of the requirements in the 1998 Edition through the 2000 Addendum, will provide an acceptable level of quality and safety.
The staffs analysis is provided in the enclosed safety evaluation. Pursuant to 10 CFR 50.55a(a)(3)(I), the proposed alternative is authorized for the Pilgrim Nuclear Power Stations fourth 10-year inservice inspection interval, which ends on June 30, 2015.
If you have any questions regarding this approval, please contact the Pilgrim Project Manager, James Shea, at 301-415-1388.
Sincerely,
/RA/
Richard J. Laufer, Chief Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-293
Enclosure:
As stated cc w/encl: See next page
ML060660132 *See SE dated 12/14/05 OFFICE LPL1-1/PM LPL1-1/PM LPL1-1/LA CPNB OGC LPL1-1/BC NAME BSingal JShea SLittle JTsao*
PMoulding RLaufer DATE 03/13/06 03/13/06 03/23/06 12/14/05 04/04/06 04/05/06
Pilgrim Nuclear Power Station cc:
Regional Administrator, Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Senior 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 Nuclear Matters Committee Town Hall 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 Director, Radiation Control Program Commonwealth of Massachusetts Executive Offices of Health and Human Services 174 Portland Street Boston, MA 02114 Secretary of Public Safety Executive Office of Public Safety One Ashburton Place Boston, MA 02108 Director, Massachusetts Emergency Management Agency Attn: James Muckerheide 400 Worcester Road Framingham, MA 01702-5399 Mr. William D. Meinert Nuclear Engineer Massachusetts Municipal Wholesale Electric Company P.O. Box 426 Ludlow, MA 01056-0426 Mr. Michael A. Balduzzi Site Vice President Entergy Nuclear Operations, Inc.
Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360-5508 Mr. Stephen J. Bethay Director, Nuclear Safety Assurance 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 Ms. Charlene D. Faison Manager, Licensing Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
Pilgrim Nuclear Power Station cc:
Mr. Gary J. Taylor Chief Executive Officer Entergy Operations 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. Oscar Limpias Vice President, Engineering Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Christopher Schwarz 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 Mr. Michael J. Colomb Director of Oversight Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Travis C. McCullough Assistant General Counsel Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Ms. Stacey Lousteau Treasury Department Entergy Services, Inc.
639 Loyola Avenue New Orleans, LA 70113 Mr. James Sniezek 5486 Nithsdale Drive Salisbury, MD 21801-2490 Mr. Michael D. Lyster 5931 Barclay Lane Naples, FL 34110-7306
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST NO. PIL-05-R-002 PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293
1.0 INTRODUCTION
By letter dated June 29, 2005, Agencywide Documents Access and Management System (accession number ML051920157), Entergy Nuclear Operations, Inc, (the licensee) submitted Relief Request No. PIL-05-R-002, related to the fourth 10-year interval inservice inspection (ISI)
Program for the Pilgrim Nuclear Power Station (Pilgrim). The licensee proposed an alternative to use the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, 2001 Edition through the 2003 Addendum, in lieu of the 1998 Edition through the 2000 Addendum in regard to Subparagraph IWA-2210, Visual Examinations, including subsections IWA-2211 through IWA-2216. The licensees proposed use of portions of subsequent edition and addenda to the ASME Code,Section XI, which is incorporated by reference in 10 CFR 50.55a(b)(2), is in accordance with 10 CFR 50.55a(g)(4)(iv). Therefore, the Nuclear Regulatory Commission (NRC) staffs review has focused on whether the related requirements of the respective Codes and addenda are being met. The licensees request would be applicable during Pilgrims fourth 10-year ISI interval, which ends on June 30, 2015.
2.0 REGULATORY EVALUATION
Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(g), requires that the ISI of ASME Code Class 1, 2, and 3 components be performed in accordance with Section XI of the ASME Code and applicable addenda, except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(I). According to 10 CFR 50.55a(a)(3),
alternatives to the requirements of paragraph (g) may be used, when authorized by the NRC, if an applicant demonstrates that the proposed alternatives would provide an acceptable level of quality and safety or if the specified requirement 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 (ISI) of Nuclear Power Plant Components, to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulations require that the ISI 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) 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. The ISI Code of record for the fourth 10-year inspection interval for Pilgrim Station is the 1998 Edition through the 2000 Addendum of the ASME Code,Section XI.
Pursuant to 10 CFR 50.55a(g)(4)(iv), inservice examination of components and system pressure tests may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in paragraph (b) of this section, subject to the limitations and modifications listed in paragraph (b) of this section, and subject to NRC approval. Portions of editions and addenda may be used, provided that all related requirements of the respective editions or addenda are met.
Regulatory Issue Summary 2004-16, Use of Later Editions and Addenda to ASME Code Section XI for Repair/Replacement Activities, provides additional information regarding the use of editions and addenda of the ASME Code subsequent to the Code of Record.
2.1 Code Requirements for which Relief is Requested Pursuant to 10 CFR 50.55a(g)(4)(iv), the licensee has proposed an alternative to use the visual examination requirements of Subparagraph IWA-2210, including subsections IWA-2211 through IWA-2216 of the ASME Code,Section XI, 2001 Edition through the 2003 Addendum.
The request is applicable to all components subject to VT-1, VT-2, or VT-3 visual examinations of the ASME Code,Section XI.
2.2 ASME Code Requirements The Code requirements that would otherwise apply are as stated in IWA-2210, IWA-2211 through IWA-2216 of the ASME Code,Section XI, 1998 Edition through the 2000 Addendum.
2.3 Licensees Basis for Requesting Relief The changes to ASME Code,Section XI, Paragraph IWA-2200, including Subparagraph IWA-2210 and subsections IWA-2211 through IWA-2216 on visual examinations for Class 1, 2, and 3 items, do not affect other parts of the Code. The 2001 Edition through the 2003 Addendum of the ASME Code,Section XI, provides clarifications as to the requirements of visual examinations to be performed on Class 1, 2, and 3 components during inservice examinations. This requirement would also be followed under the Pilgrim Repair/Replacement Program.
3.0 TECHNICAL EVALUATION
The licensees proposed use of portions of subsequent edition and addenda to the ASME Code,Section XI, which is incorporated by reference in 10 CFR 50.55a(b)(2), is in accordance with 10 CFR 50.55a(g)(4)(iv). Therefore, the NRC staffs review has focused on whether the related requirements of the respective Codes and addenda are being met. The staff has reviewed Subparagraph IWA-2210 and subsections IWA-2211 through IWA-2216 pertaining to visual examinations in both versions of the ASME Code,Section XI; the 1998 Edition through the 2000 Addendum and the 2001 Edition through the 2003 Addendum. The staff believes that the later Code, including the Addendum, has the same requirement as that of the previous version except that it provides clarification concerning illumination during visual examinations.
There is thus no new requirement in regard to visual examinations in either version of the Code that has to be met as a result of the Code upgrade in this area. The NRC staff, therefore, has determined that the use of the ASME Code,Section XI, 2001 Edition through the 2003 Addendum in lieu of the 1998 Edition through the 2000 Addendum, will provide an acceptable level of quality and safety.
4.0 CONCLUSION
Based on the NRC staffs review and comparison of the ASME Codes,Section XI (1998 and 2001 Editions), the staff finds that use of the visual examination requirements in Subparagraph IWA-2210 and subsections IWA-2211 through IWA-2216 of the 2001 Edition through the 2003 Addendum, in lieu of the requirements in the 1998 Edition through the 2000 Addendum, will provide an acceptable level of quality and safety. The staff authorizes the alternative proposed in Relief Request No. PIL-05-R-002 pursuant to 10 CFR 50.55a(a)(3)(I), for the fourth 10-year ISI interval for Pilgrim. All other ASME Code,Section XI, requirements for which relief was not specifically requested and approved in this relief request remain applicable, including third party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor: P. Patnaik Date: April 5, 2006