ML041740184

Relief Request, Nos. RR-34 and PRR for the Third 10-Year Inservice Inspection (ISI) Interval, MC1999 and MC2006

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.

MC1999 AND MC2006)

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.

MC1999 AND MC2006)

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 R. Laufer P. Milano S. Little G. Hill (2) OGC PDI-1 RF J. Clifford T. Tate C. Bixler, R-I J. Jolicoeur, ACRS C. Holden T. Chan D. Votolato OEDO 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 Resident Inspector's Office Chief Executive Officer James A. FitzPatrick Nuclear Power Plant Entergy Operations, Inc. U. S. Nuclear Regulatory Commission 1340 Echelon Parkway P.O. Box 136 Jackson, MS 39213 Lycoming, NY 13093 Mr. John T. Herron Ms. Charlene D. Faison Sr. VP and Chief Operating Officer Manager, Licensing Entergy Nuclear Operations, Inc. Entergy Nuclear Operations, Inc.

440 Hamilton Avenue 440 Hamilton Avenue White Plains, NY 10601 White Plains, NY 10601 Mr. Theodore A. Sullivan Mr. Michael J. Colomb Site Vice President Director of Oversight Entergy Nuclear Operations, Inc. Entergy Nuclear Operations, Inc.

James A. FitzPatrick Nuclear Power Plant 440 Hamilton Avenue P.O. Box 110 White Plains, NY 10601 Lycoming, NY 13093 Mr. William Maquire Mr. Kevin J. Mulligan Director, Nuclear Safety Assurance General Manager, Plant Operations Entergy Nuclear Operations, Inc.

Entergy Nuclear Operations, Inc. James A. FitzPatrick Nuclear Power Plant James A. FitzPatrick Nuclear Power Plant P.O. Box 110 P.O. Box 110 Lycoming, NY 13093 Lycoming, NY 13093 Mr. Andrew Halliday Mr. Danny L. Pace Manager, Regulatory Compliance Vice President, Engineering Entergy Nuclear Operations, Inc.

Entergy Nuclear Operations, Inc. James A. FitzPatrick Nuclear Power Plant 440 Hamilton Avenue P.O. Box 110 White Plains, NY 10601 Lycoming, NY 13093 Mr. Brian OGrady Supervisor Vice President, Operations Support Town of Scriba Entergy Nuclear Operations, Inc. Route 8, Box 382 440 Hamilton Avenue Oswego, NY 13126 White Plains, NY 10601 Mr. Charles Donaldson, Esquire Mr. John F. McCann Assistant Attorney General Director, Nuclear Safety Assurance New York Department of Law Entergy Nuclear Operations, Inc. 120 Broadway 440 Hamilton Avenue New York, NY 10271 White Plains, NY 10601

FitzPatrick Nuclear Power Plant cc:

Regional Administrator, Region I Ms. Stacey Lousteau U.S. Nuclear Regulatory Commission Treasury Department 475 Allendale Road Entergy Services, Inc.

King of Prussia, PA 19406 639 Loyola Avenue Mail Stop L-ENT-15E Oswego County Administrator New Orleans, LA 70113 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

Pilgrim Nuclear Power Station cc:

Resident Inspector Mr. Steve Brennion U. S. Nuclear Regulatory Commission Supt., Regulatory & Industry Affairs Pilgrim Nuclear Power Station Entergy Nuclear Operations, Inc.

Post Office Box 867 Pilgrim Nuclear Power Station Plymouth, MA 02360 600 Rocky Hill Road, M/S 1 Plymouth, MA 02360-5508 Chairman, Board of Selectmen 11 Lincoln Street Mr. Jack Alexander Plymouth, MA 02360 Manager, Reg. Relations and Quality Assurance Chairman, Duxbury Board of Selectmen Pilgrim Nuclear Power Station Town Hall 600 Rocky Hill Road 878 Tremont Street Plymouth, MA 02360-5599 Duxbury, MA 02332 Mr. David F. Tarantino Office of the Commissioner Nuclear Information Manager Massachusetts Department of Pilgrim Nuclear Power Station Environmental Protection 600 Rocky Hill Road One Winter Street Plymouth, MA 02360-5599 Boston, MA 02108 Ms. Jane Perlov Office of the Attorney General Secretary of Public Safety One Ashburton Place Executive Office of Public Safety 20th Floor One Ashburton Place Boston, MA 02108 Boston, MA 02108 Dr. Robert M. Hallisey, Director Mr. Stephen J. McGrail, Director Radiation Control Program Attn: James Muckerheide Commonwealth of Massachusetts Massachusetts Emergency Management Executive Offices of Health and Agency Human Services 400 Worcester Road 174 Portland Street Framingham, MA 01702-5399 Boston, MA 02114 Chairman Regional Administrator, Region I Nuclear Matters Committee U. S. Nuclear Regulatory Commission Town Hall 475 Allendale Road 11 Lincoln Street King of Prussia, PA 19406-1415 Plymouth, MA 02360 Mr. John M. Fulton Mr. William D. Meinert Assistant General Counsel Nuclear Engineer Entergy Nuclear Operations, Inc. Massachusetts Municipal Wholesale 440 Hamilton Avenue Electric Company White Plains, NY 10601 P.O. Box 426 Ludlow, MA 01056-0426

Pilgrim Nuclear Power Station cc:

Mr. Gary J. Taylor Mr. John F. McCann Chief Executive Officer Director, Nuclear Safety Assurance Entergy Operations Entergy Nuclear Operations, Inc.

1340 Echelon Parkway 440 Hamilton Avenue Jackson, MS 39213 White Plains, NY 10601 Mr. John T. Herron Ms. Charlene D. Faison Sr. VP and Chief Operating Officer Manager, Licensing Entergy Nuclear Operations, Inc. Entergy Nuclear Operations, Inc.

440 Hamilton Avenue 440 Hamilton Avenue White Plains, NY 10601 White Plains, NY 10601 Mr. Michael A. Balduzzi Mr. Michael J. Colomb Site Vice President Director of Oversight Entergy Nuclear Operations, Inc. Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station 440 Hamilton Avenue 600 Rocky Hill Road White Plains, NY 10601 Plymouth, MA 02360-5508 Senior Resident Inspector Mr. Stephen J. Bethay U.S. Nuclear Regulatory Commission Director, Nuclear Assessment Pilgrim Nuclear Power Station Entergy Nuclear Operations, Inc. 600 Rocky Hill Road Pilgrim Nuclear Power Station Mail Stop 66 600 Rocky Hill Road Plymouth, MA 02360-5508 Plymouth, MA 02360-5508 Ms. Stacey Lousteau Mr. Bryan S. Ford Treasury Department Manager, Licensing Entergy Services, Inc.

Entergy Nuclear Operations, Inc. 639 Loyola Avenue Pilgrim Nuclear Power Station New Orleans, LA 70113 600 Rocky Hill Road Plymouth, MA 02360-5508 Jim Sniezek 5486 Nithsdale Drive Mr. Danny L. Pace Salisbury, MD 21801 Vice President, Engineering Entergy Nuclear Operations, Inc. Mr. Kennety L. Graesser 440 Hamilton Avenue 38832 N. Ashley Drive White Plains, NY 10601 Lake Villa, IL 60046 Mr. Brian OGrady Mr. Ronald Toole Vice President, Operations Support 1282 Valley of Lakes Entergy Nuclear Operations, Inc. Box R-10 440 Hamilton Avenue Hazelton, PA 18202 White Plains, NY 10601

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.

Enclosure

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