ML041740184
| ML041740184 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim, FitzPatrick |
| Issue date: | 07/06/2004 |
| From: | Richard Laufer NRC/NRR/DLPM/LPD1 |
| To: | Kansler M Entergy Nuclear Operations |
| References | |
| TAC MC1999, TAC MC2006 | |
| Download: ML041740184 (9) | |
Text
July 6, 2004 Mr. Michael R. Kansler, President Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT AND PILGRIM NUCLEAR POWER STATION - RELIEF REQUEST NOS. RR-34 AND PRR-32 FOR THE THIRD 10-YEAR INSERVICE INSPECTION (ISI) INTERVAL (TAC NOS.
Dear Mr. Kansler:
By letter dated February 11, 2004, you submitted a request for relief from certain American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI requirements for inservice inspection (ISI) at James A. FitzPatrick Nuclear Power Plant (JAFNPP) and Pilgrim Nuclear Power Station (PNPS). The ASME Code,Section XI, 1995 Edition with 1996 Addenda, Appendix VIII, Supplement 4, requires that performance demonstration results for ultrasonic testing satisfy the statistical parameters specified in Subparagraph 3.2(c). In lieu of Subparagraph 3.2(c), you proposed using a depth sizing error not to exceed 0.15 inch root mean square.
Based on the enclosed safety evaluation, the Nuclear Regulatory Commission staff finds that the proposed alternative provides an acceptable level of quality and safety. Accordingly, the alternative is authorized for use at JAFNPP and PNPS, pursuant to 10 CFR 50.55a(a)(3)(i), for the remainder of the third 10-year ISI interval.
Sincerely,
/RA/
Richard J. Laufer, Chief, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-333 and 50-293
Enclosure:
As stated cc w/encl: See next page
July 6, 2004 Mr. Michael R. Kansler, President Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT AND PILGRIM NUCLEAR POWER STATION - RELIEF REQUEST NOS. RR-34 AND PRR-32 FOR THE THIRD 10-YEAR INSERVICE INSPECTION (ISI) INTERVAL (TAC NOS.
Dear Mr. Kansler:
By letter dated February 11, 2004, you submitted a request for relief from certain American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI requirements for inservice inspection (ISI) at James A. FitzPatrick Nuclear Power Plant (JAFNPP) and Pilgrim Nuclear Power Station (PNPS). The ASME Code,Section XI, 1995 Edition with 1996 Addenda, Appendix VIII, Supplement 4, requires that performance demonstration results for ultrasonic testing satisfy the statistical parameters specified in Subparagraph 3.2(c). In lieu of Subparagraph 3.2(c), you proposed using a depth sizing error not to exceed 0.15 inch root mean square.
Based on the enclosed safety evaluation, the Nuclear Regulatory Commission staff finds that the proposed alternative provides an acceptable level of quality and safety. Accordingly, the alternative is authorized for use at JAFNPP and PNPS, pursuant to 10 CFR 50.55a(a)(3)(i), for the remainder of the third 10-year ISI interval.
Sincerely,
/RA/
Richard J. Laufer, Chief, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-333 and 50-293
Enclosure:
As stated cc w/encl: See next page DISTRIBUTION:
PUBLIC PDI-1 RF C. Holden R. Laufer J. Clifford T. Chan P. Milano T. Tate D. Votolato S. Little C. Bixler, R-I G. Hill (2)
J. Jolicoeur, OEDO OGC ACRS Accession No.: ML041740184 Safety Evaluation provided - no changes made.
OFFICE PDI-1/PM PDI-1/LA PDI-2 EMCB OGC PDI-1/SC NAME PMilano SLittle TTate TChan*
RLaufer DATE 06/30/04 06/30/04 07/01/04 03/09/2004 07/02/04 07/06/04 OFFICIAL RECORD COPY
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
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 19406-1415 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. 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. 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 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 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 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 Senior Resident Inspector U.S. Nuclear Regulatory Commission Pilgrim Nuclear Power Station 600 Rocky Hill Road Mail Stop 66 Plymouth, MA 02360-5508 Ms. Stacey Lousteau Treasury Department Entergy Services, Inc.
639 Loyola Avenue New Orleans, LA 70113 Jim Sniezek 5486 Nithsdale Drive Salisbury, MD 21801 Mr. Kennety L. Graesser 38832 N. Ashley Drive Lake Villa, IL 60046 Mr. Ronald Toole 1282 Valley of Lakes Box R-10 Hazelton, PA 18202
Enclosure SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION FOR THE THIRD INSERVICE INSPECTION (ISI) INTERVAL RELIEF REQUEST NOS. RR-34 AND PRR-32 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AND PILGRIM NUCLEAR POWER STATION ENTERGY NUCLEAR OPERATIONS, INC.
DOCKET NOS. 50-333 AND 50-293
1.0 INTRODUCTION
By letter dated February 11, 2004 (ADAMS No. ML040440157), Entergy Nuclear Operations, Inc. (Entergy or the licensee) submitted a request for relief from certain American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI requirements for inservice inspection (ISI) at James A. FitzPatrick Nuclear Power Plant (JAFNPP) and Pilgrim Nuclear Power Station (PNPS). Specifically, the 1995 Edition with 1996 Addenda of the ASME Code,Section XI, Appendix VIII, Supplement 4, Qualification Requirements for the Clad/Base Metal Interface of Reactor Vessel, requires that performance demonstration results satisfy the statistical parameters specified in Subparagraph 3.2(c). In lieu of Subparagraph 3.2(c), the licensee proposed using a depth sizing error not to exceed 0.15 inch root mean square (RMS).
1.1 Components for Which Relief Is Requested ASME Code,Section XI, IWB-2500-1,Class 1, Examination Category B-A, Item No. B1.10, Circumferential and Longitudinal Shell Welds and B1.20, Head Welds.
1.2 ASME Code Requirements Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(b)(2) was amended to reference Section XI of the ASME Code through the 1995 Edition with the 1996 Addenda (64 FR 51370).
The 1995 Edition with 1996 Addenda of the ASME Code,Section XI, Appendix VIII, Supplement 4, requires that performance demonstration results satisfy the statistical parameters specified in Subparagraph 3.2(c), which states that performance demonstration results reported by the candidate, when plotted on a two-dimensional plot with the depth estimated by ultrasonics plotted along the ordinate and the true depth plotted along the abscissa, satisfy the following statistical parameters: (1) slope of the linear regression line is not less that 0.7; (2) the mean deviation of flaw depth is less than 0.25 inch; and (3) correlation coefficient is not less than 0.70.
1.3 Proposed Alternative Pursuant to 10 CFR 50.55a(a)(3)(i), relief is requested to use the RMS value from the proposed rule of 10 CFR 50.55a(b)(2)(xv)(C)(1) (69 FR 892), which modifies the depth sizing criteria of the 1995 Edition with 1996 Addenda of the ASME Code,Section XI, Appendix VIII, Supplement 4, Subparagraph 3.2(a), in lieu of Subparagraph 3.2(c).
1.4 Licensee Basis for Use ASME Code,Section XI, Appendix VIII, supplement 4, Subparagraph 3.2(c) imposes three statistical parameters for depth sizing. The first parameter, 3.2(c)(1), pertains to the scope of a linear regression line. The linear regression line is the difference between actual versus true value plotted along a through-wall thickness. For Supplement 4 performance demonstrations, a linear regression line of the data is not applicable because the performance demonstrations are performed on test specimens with flaws located in the inner 15 percent through-wall. The differences between the measured versus true value produce a tight grouping of results, which resemble a shotgun pattern. The slope of a regression line from such data is extremely sensitive to small variations, thus making the parameter of 3.2(c)(1), an inappropriate criterion. The second parameter, 3.2(c)(2), pertains to the mean deviation of flaw depth. The value used in the Code is too lax with respect to evaluating flaw depths within the inner 15 percent of wall thickness. Therefore, Entergy Nuclear Operations, Inc. (Entergy) proposes to use the more appropriate criterion of 0.15 inch RMS of 10CFR50.55a(b)(2)(xv)(C)(1), which modifies Subparagraph 3.2(a), as the acceptance criterion. The third parameter, 3.2(c)(3), pertains to a correction coefficient. The value of the correction coefficient in Subparagraph 3.2(c)(3) is inappropriate for this application since it is based on the linear regression from Subparagraph 3.2(c)(1).
Entergy believes the proposed alternative to use the RMS value of 10CFR50.55a(b)(2)(xv)(C)(1), which modifies the criterion of ASME Code, Appendix VIII, Supplement 4, Subparagraph 3.2(a), in lieu of Subparagraph 3.2(c), will provide an acceptable level of quality and safety.
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 50.55(a)(3)(i), 10 CFR 50.55a(a)(3)(ii), or 10 CFR 50.55a(g)(6)(i). In 10 CFR 50.55a(a)(3), it states that alternatives to the requirements of paragraph (g) may be used, when authorized by the Nuclear Regulatory Commission (NRC), if the licensee 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 materials of construction 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) 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. For JAFNPP and PNPS, the applicable edition of Section XI of the ASME Code for the third 10-year ISI interval is the 1989 Edition, no addenda.
3.0 TECHNICAL EVALUATION
Supplement 4, Subparagraph 3.2(c) of Appendix VIII, requires that the ultrasonic performance demonstration results be plotted on a two-dimensional plot, with the measured depth plotted along the ordinate axis and the true depth plotted along the abscissa axis. For qualification, the plot must satisfy the following statistical parameters: (1) slope of the linear regression line is not less than 0.7; (2) the mean deviation of flaw depth is less than 0.25 inch; and (3) correlation coefficient is not less than 0.70.
On January 7, 2004 (69 FR 879), the NRC staff proposed to revise 10 CFR 50.55a(b)(2)(xv)(C)(1) to specify that the flaw depth size provision in Subparagraph 3.2(c) of Supplement 4 to Appendix VIII is not applicable when Appendix VIII is implemented in accordance with 10 CFR 50.55a(b)(2)(xv). This revision was necessary to correct an oversight when NRC mandated accelerated implementation of Appendix VIII in a September 22, 1999, rulemaking (64 FR 51370).
The staff recognized that implementation of Subparagraph 3.2(c) was not compatible when implementing 10 CFR 50.55a(b)(2)(xv), but did not notice that Subparagraph 3.2(c) was not addressed in the rulemaking until after it was published.
The licensees proposed alternative is consistent with the NRC staffs revision in the proposed rulemaking. Therefore, the staff has determined that the use of Subparagraph 3.2(c) requirements is inappropriate as a screening parameter for determining the acceptability of Supplement 4 performance demonstration results. The proposed alternative to use the RMS value of 10 CFR 50.55a(b)(2)(xv)(C)(1), which modifies the criterion of Appendix VIII, Supplement 4, Subparagraph 3.2(a), and applies the same criterion to Subparagraph 3.2(c),
specifically 0.15 inch RMS, will provide an acceptable level of quality and safety.
4.0 CONCLUSION
Based on the discussion above, the NRC staff concludes that the proposed alternative to use the depth sizing criterion of Appendix VIII, Supplement 4, Subparagraph 3.2(a) as modified by 10 CFR 50.55a(b)(2)(xv)(C)(1), in lieu of Subparagraph 3.2(c), will provide an acceptable level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the proposed alternative is authorized for the third 10-year ISI interval for JAFNPP and PNPS. 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: D. Vototato Date: July 6, 2004