ML062990446

Email: (NPA-PD-LR) Fwd: Final RAI on Section 3.2.1 and 4.2.1 on the Pilgrim LRA

ML062990446
Person / Time
Site:	Pilgrim
Issue date:	09/08/2006
From:	Subbaratnam R Office of New Reactors
To:	Perry Buckberg Office of Nuclear Reactor Regulation
References
%dam200612, TAC MD2296
Download: ML062990446 (16)

Text

I1Kent Howard - Fwd: Final RAI on Sections 3.2.1 and 4.2.1 on the Pilgrim LRA Page 111 From: Ram Subbaratnam To: phbl Date: 9/8/2006 3:11:39 PM

Subject:

Fwd: Final RAI on Sections 3.2.1 and 4.2.1 on the Pilgrim LRA Here it is!

Ram

>>> Ram Subbaratnam 09/08/2006 3:06 PM >>>

Folks:

Please find attached one set of formal RAIs on section 3.2.1 and 4.2.1 from the NRC staff on the Pilgrim LRA. These are the last set of RAIs on this LRA and hopefully concludes the staff requests. I am sending you an advance copy so that Entergy can work on the lead in responding to the RAIs. As previously agreed upon, you formal response on docket will be due 30 days from the date of receipt of the RAIs in mail.

Thanking you.

Sincerely yours Ram Subbaratnam PM Pilgrim LRA US NRC, (301) 415 1478

I 0001.TMP Paae 111I c:\temDViWlOOQQl .TMP Paoe 1 II Mail Envelope Properties (4501C06B.320: 19: 10294)

Subject:

Fwd: Final RAI on Sections 3.2.1 and 4.2.1 on the Pilgrim LRA Creation Date 9/8/2006 3:11:39 PM From: Ram Subbaratnam Created By: RXS2@nrc.gov Recipients Action Date & Time nrc.gov OWGWPO01.HQGWDO01 PHB 1 (Perry Buckberg)

Post Office Delivered Route OWGWPO01 .HQGWDO01 Pending nrc.gov Files Size Date & Time MESSAGE 1186 9/8/2006 3:11:39 PN RLRCSection3.2.1AdditionalQsFinal.wpd 28831 9/8/2006 2:58:33 PM CVIBectio4.2.lRAIsFinal.rev 1.wpd 38446 9/8/2006 2:58:59 PM Options Auto Delete: No Expiration Date: None Notify Recipients: Yes Priority: Standard ReplyRequested: No Return Notification: None Concealed

Subject:

No Security: Standard To Be Delivered: Immediate Status Tracking: Delivered & Opened

September 8, 2006 Mr. Michael Kansler President Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601-1839

SUBJECT:

REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE PILGRIM NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION (TAC NO. MC9669)

Dear Mr. Kansler:

By letter dated January 25, 2006, Entergy Nuclear Operations, Inc., submitted an application pursuant to Title 10 of the Code of FederalRegulations 10 CFR Part 54, to renew the operating license for Pilgrim Nuclear Power Station for review by the U.S. Nuclear Regulatory Commission (NRC). The NRC 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 address Sections 3.2 Engineered Safety Features.

These questions were discussed with a member of your staff, Bryan Ford, and a mutually agreeable date for this response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-1478 or e-mail RXS2@nrc.gov.

Sincerely, IRN Ram Subbaratnam, Project Manager License Renewal Branch A Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-293

Enclosure:

As Stated cc w/encl: See next page

ML062500431 C:\temp\RLRCSection3.2.1 AdditionalQsFinal.wpd OFFICE PM:RLRA:DLR LA:DLR BC:REBB:DLR NAME RSubbaratnam YEdmonds LLund DATE 9/6/06 19/7/06 09/8 /06

Letter to Michael Kansler from Ram Subbaratnam dated: September 8, 2006

SUBJECT:

REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE PILGRIM NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION (TAC MC9669)

HARD COPY DLR R/F E-MAIL:

JFair RWeisman AMurphy RPettis GGalletti DShum GBagchi SSmith (srs3)

SDuraiswamy YL (Renee) Li RidsNrrDIr RidsNrrDIrRlra RidsNrrDIrRIrb RidsNrrDe RidsNrrDci RidsNrreEemb RidsNrrDeEeeb RidsNrrDeEqva RidsNrrDss RidsNrrDnrl RidsOgcMailCenter RidsNrrAdes DLR Staff RSubbaratnam SHoffman SUttal JShea AWilliamson JDavis KChang GWilson CAnderson, Region 1 WRaymond, Region 1 NSheehan, Region 1

Pilgrim Nuclear Power Station cc:

Regional Administrator, Region I Secretary of Public Safety U. S. Nuclear Regulatory Commission Executive Office of Public Safety 475 Allendale Road One Ashburton Place King of Prussia, PA 19406-1415 Boston, MA 02108 Senior Resident Inspector Director, Massachusetts Emergency U. S. Nuclear Regulatory Commission Management Agency Pilgrim Nuclear Power Station Attn: James Muckerheide Post Office Box 867 400 Worcester Road Plymouth, MA 02360 Framingham, MA 01702-5399 Chairman, Board of Selectmen Mr. William D. Meinert 11 Lincoln Street Nuclear Engineer Plymouth, MA 02360 Massachusetts Municipal Wholesale Electric Company Chairman P.O. Box 426 Nuclear Matters Committee Ludlow, MA 01056-0426 Town Hall 11 Lincoln Street Mr. Michael A. Balduzzi Plymouth, MA 02360 Site Vice President Entergy Nuclear Operations, Inc.

Chairman, Duxbury Board of Selectmen Pilgrim Nuclear Power Station Town Hall 600 Rocky Hill Road 878 Tremont Street Plymouth, MA 02360-5508 Duxbury, MA 02332 Mr. Stephen J. Bethay Office of the Commissioner Director, Nuclear Safety Assurance Massachusetts Department of Entergy Nuclear Operations, Inc.

Environmental Protection Pilgrim Nuclear Power Station One Winter Street 600 Rocky Hill Road Boston, MA 02108 Plymouth, MA 02360-5508 Office of the Attorney General Mr. Bryan S. Ford One Ashburton Place Manager, Licensing 20th Floor Entergy Nuclear Operations, Inc.

Boston, MA 02108 Pilgrim Nuclear Power Station 600 Rocky Hill Road MA Department of Public Health Plymouth, MA 02360-5508 Radiation Control Program Schrafft Center, Suite 1M2A Mr. Gary J. Taylor 529 Main Street Chief Executive Officer Charlestown, MA 02129 Entergy Operations 1340 Echelon Parkway Jackson, MS 39213

Pilgrim Nuclear Power Station cc:

Mr. John T. Herron Ms. Stacey Lousteau Sr. VP and Chief Operating Officer Treasury Department Entergy Nuclear Operations, Inc. Entergy Services, Inc.

440 Hamilton Avenue 639 Loyola Avenue White Plains, NY 10601 New Orleans, LA 70113 Mr. Oscar Limpias Mr. James Sniezek Vice President, Engineering 5486 Nithsdale Drive Entergy Nuclear Operations, Inc. Salisbury, MD 21801 440 Hamilton Avenue White Plains, NY 10601 Mr. Travis C. McCullough Assistant General Counsel Mr. Christopher Schwarz Entergy Nuclear Operations, Inc.

Vice President, Operations Support 440 Hamilton Avenue Entergy Nuclear Operations, Inc. White Plains, NY 10601 440 Hamilton Avenue White Plains, NY 10601 Mr. James Ross Nuclear Energy Institute Mr. John F. McCann 1776 I Street, NW, Suite 400 Director, Nuclear Safety Assurance Washington, DC 20006-3708 Entergy Nuclear Operations, Inc.

440 Hamilton Avenue Plymouth Public Library White Plains, NY 10601 Attn: Dinah O'Brien 132 South Street Ms. Charlene D. Faison Plymouth, MA 02360 Manager, Licensing Entergy Nuclear Operations, Inc. Duxbury Free Library 440 Hamilton Avenue ATTN: Ms. Elaine Winquist White Plains, NY 10601 77 Alden Street Duxbury, MA 02332 Mr. Michael D. Lyster 5931 Barclay Lane Kingston Public Library Naples, FL 34110-7306 ATTN: Reference Librarian 6 Green Street Mr. Michael J. Colomb Kingston, MA 02364 Director of Oversight Entergy Nuclear Operations, Inc. Ms. Mary Lampert 440 Hamilton Avenue Duxbury Nuclear Advisory, Chair White Plains, NY 10601 Pilgrim Watch, Director 148 Washington Street Mr. Kevin H. Bronson Duxbury, MA 02332 General Manager, Plant Operations Entergy Nuclear Operations, Inc. Mr. Garrett D. Edwards Pilgrim Nuclear Power Station 814 Waverly Road 600 Rocky Hill Road Kennett Square, PA 19348 Plymouth, MA 02360-5508

REQUESTS FOR ADDITIONAL INFORMATION (RAIs)

PILGRIM NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SECTIONS 3.2 ENGINEERED SAFETY FEATURES SYSTEMS 3.2 Engineered Safety Features Systems RAI 3.2.1 Piping of the Reactor Core isolation Cooling System is subject to flow accelerated corrosion.

The applicant in LRA Table 3.2.1 engineered safety feature (ESF) and Table 3.2.1 credit the plant-specific Periodic Surveillance and Preventive Maintenance Program for the management of loss of materials (wall thinning). The GALL report recommends using the Flow-Accelerated Corrosion Program, XI.M17, to manage wall thinning. The Periodic Surveillance and Preventive Maintenance Program provides for inspection for material loss (wall thinning) every 5 years but no Monitoring and Trending activities to predict areas of high wall thinning rates or for trending of thinning as does XI.M17. Please provide justification for not providing for monitoring and trending of wall thinning for reactor core isolation cooling (RCIC) piping.

RAI 3.2.2 The applicant in Table 3.2.1 Item 18 of the PNPS LRA stated that none of the ESF system components are within the scope of the BWR Stress Corrosion Cracking Program. Please provide the details that justify this statement.

ENCLOSURE

September 8, 2006 Mr. Michael Kansler President Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601-1839

SUBJECT:

REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE PILGRIM NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION (TAC NO. MC9669)

Dear Mr. Kansler:

By letter dated January 25, 2006, Entergy Nuclear Operations, Inc., submitted an application pursuant to Title 10 9f the Code of FederalRegulations 10 CFR Part 54, to renew the operating license for Pilgrim Nuclear Power Station, for review by the U.S. Nuclear Regulatory Commission (NRC). The NRC 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 on Time Limited Aging Analysis of Reactor Vessel Internals in License Renewal Section: 4.2.1.

These questions were discussed with a member of your staff, Bryan Ford, and a mutually agreeable date for this response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-1478 or by e-mail at RXS2@nrc.aov.

Sincerely, IRN Ram Subbaratnam, Project Manager License Renewal Branch A Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-293

Enclosure:

Requests for Additional Information cc w/encl: See next page

September 8, 2006 Mr. Michael Kansler President Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601-1839

SUBJECT:

REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE PILGRIM NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION (TAC MC9669)

Dear Mr. Kansler:

By letter dated January 25, 2006, Entergy Nuclear Operations, Inc., submitted an application pursuant to Title 10 of the Code of FederalRegulations 10 CFR Part 54, to renew the operating license for Pilgrim Nuclear Power Station, for review by the U.S. Nuclear Regulatory Commission (NRC). The NRC 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 on Time Limited Aging Analysis of Reactor Vessel Internals in License Renewal Section: 4.2.1.

These questions were discussed with a member of your staff, Bryan Ford, and a mutually agreeable date for this response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-1,478 or by e-mail at RXS2@nrc.aov.

Sincerely, IRA/

Ram Subbaratnam, Project Manager License Renewal Branch A Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-293

Enclosure:

Requests for Additional Information cc w/encl: See next page ADAMS Accession No.: ML062500401 OFFICE PM:RLRA:DLR LA:RLRA:DLR BC:REBB:DLR NAME RSubbaratnam YEdmonds LLund DATE 09/08/06 09/08/06 09/08/06 OFFICIAL RECbRD COPY

Letter to Michael Kansler from Ram Subbaratnam dated: September 8. 2006

SUBJECT:

REQUESTS FOR ADDITIONAL INFORMATION.FOR THE REVIEW OF THE PILGRIM NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION (TAC MC9669)

HARD COPY DLR R/F E-MAIL:

JFair RWeisman AMurphy RPettis GGalletti DShum GBagchi SSmith (srs3)

SDuraiswamy YL (Renee) Li RidsNrrDIr RidsNrrDIrRIra RidsNrrDIrRlrb RidsNrrDe RidsNrrDci RidsNrreEemb RidsNrrDeEeeb RidsNrrDeEqva RidsNrrDss RidsNrrDnrl RidsOgcMailCenter RidsNrrAdes DLR Staff RSubbaratnam Shoffman SUttal JShea AWilliamson CSydnor MMtichel GWilson CAnderson, Region 1 WRaymond, Region 1 NSheehan, Region 1

Pilgrim Nuclear Power Station cc:

Regional Administrator, Region I Secretary of Public Safety U. S. Nuclear Regulatory Commission Executive Office of Public Safety 475 Allendale Road One Ashburton Place King of Prussia, PA 19406-1415 Boston, MA 02108 Senior Resident Inspector Director, Massachusetts Emergency U. S. Nuclear Regulatory Commission Management Agency Pilgrim Nuclear Power Station Attn: James Muckerheide Post Office Box 867 400 Worcester Road Plymouth, MA 02360 Framingham, MA 01702-5399 Chairman, Board of Selectmen Mr. William D. Meinert 11 Lincoln Street Nuclear Engineer Plymouth, MA 02360 Massachusetts Municipal Wholesale Electric Company Chairman P.O. Box 426 Nuclear Matters Committee Ludlow, MA 01056-0426 Town Hall 11 Lincoln Street Mr. Michael A. Balduzzi Plymouth, MA 02360 Site Vice President Entergy Nuclear Operations, Inc.

Chairman, Duxbury Board of Selectmen Pilgrim Nuclear Power Station Town Hall 600 Rocky Hill Road 878 Tremont Street Plymouth, MA 02360-5508 Duxbury, MA 02332 Mr. Stephen J. Bethay Office of the Commissioner Director, Nuclear Safety Assurance Massachusetts Department of Entergy Nuclear Operations, Inc.

Environmental Protection Pilgrim Nuclear Power Station One Winter Street 600 Rocky Hill Road Boston, MA 02108 Plymouth, MA 02360-5508 Office of the Attorney General Mr. Bryan S. Ford One Ashburton Place Manager, Licensing 20th Floor Entergy Nuclear Operations, Inc.

Boston, MA 02108 Pilgrim Nuclear Power Station 600 Rocky Hill Road MA Department of Public Health Plymouth, MA 02360-5508 Radiation Control Program Schrafft Center, Suite 1 M2A Mr. Gary J. Taylor 529 Main Street ' Chief Executive Officer Charlestown, MA 02129 Entergy Operations 1340 Echelon Parkway Jackson, MS 39213

Pilgrim Nuclear Power Station cc:

Mr. John T. Herron Ms. Stacey Lousteau Sr. VP and Chief Operating Officer Treasury Department Entergy Nuclear Operations, Inc. Entergy Services, Inc.

440 Hamilton Avenue 639 Loyola Avenue White Plains, NY 10601 New Orleans, LA 70113 Mr. Oscar Limpias Mr. James Sniezek Vice President, Engineering 5486 Nithsdale Drive Entergy Nuclear Operations, Inc. Salisbury, MD 21801 440 Hamilton Avenue White Plains, NY 10601 Mr. Travis C. McCullough Assistant General Counsel Mr. Christopher Schwarz Entergy Nuclear Operations, Inc.

Vice President, Operations Support 440 Hamilton Avenue Entergy Nuclear Operations, Inc. White Plains, NY 10601 440 Hamilton Avenue White Plains, NY 10601 Mr. James Ross Nuclear Energy Institute Mr. John F. McCann 1776 I Street, NW, Suite 400 Director, Nuclear Safety Assurance Washington, DC 20006-3708 Entergy Nuclear Operations, Inc.

440 Hamilton Avenue Plymouth Public Library White Plains, NY 10601 Attn: Dinah O'Brien 132 South Street Ms. Charlene D. Faison Plymouth, MA 02360 Manager, Licensing Entergy Nuclear Operations, Inc. Duxbury Free Library 440 Hamilton Avenue ATTN: Ms. Elaine Winquist White Plains, NY 10601 77 Alden Street Duxbury, MA 02332 Mr. Michael D. Lyster 5931 Barclay Lane Kingston Public Library Naples, FL 34110-7306 ATTN: Reference Librarian 6 Green Street Mr. Michael J. Colomb Kingston, MA 02364 Director of Oversight Entergy Nuclear Operations, Inc. Ms. Mary Lampert 440 Hamilton Avenue Duxbury Nuclear Advisory, Chair White Plains, NY 10601 Pilgrim Watch, Director 148 Washington Street Duxbury, MA 02332

I ý REQUESTS FOR ADDITIONAL INFORMATION PILGRIM LICENSE RENEWAL APPLICATION (LRA)

TIME-LIMITED AGING ANALYSIS (TLAA) OF REACTOR VESSEL (RV) INTERNALS SECTION: 4.2.1 NEUTRON FLUENCE RAI 4.2.2-1 Section 4.2.2 of the Pilgrim Nuclear Power Station (PNPS) License Renewal Application (LRA),

"Pressure-Temperature [P-T] Limits," states that in a license amendment request dated December 4, 2002, PNPS requested to use the present P-T limit curves through the end of operating cycle 16, which corresponds to approximately 23 effective full power years (EFPY) of facility operation. The end of operating cycle 16 is expected to occur in 2007. Section 4.2.2 also states that, in this December 4, 2002 submittal, PNPS committed to develop and submit updated P-T limit curves and revised fluence calculations based on an NRC-approved calculation method that adheres to Regulatory Guide (RG) 1.190, "Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence," prior to the end of operating cycle

16. License Amendment 197 granted this request in 2003. Section 4.2.2 then states that recent fluence calculations that were done per RG 1.190 confirm that the fluence for 54 EFPY is less than the fluence used to calculate the P-T limits that were approved for use only through the end of operating cycle 14. Based on the above statements, you conclude that the current Technical Specification (TS) P-T limit curves remain valid for the period of extended operation.

(a) Please confirm whether the P-T limit curves currently established in the PNPS TSs expire at the end of operating cycle 16 (23 EFPY).

(b) Please explain why the recent fluence calculations that were done per RG 1.190 confirm that the fluence for 54 EFPY is less than the fluence used to calculate the P-T limits that were approved for use through the end of cycle 14. Explain how this information was used to determine that the existing P-T limits remain valid for the period of extended operation.

(c) The staff does not require the P-T limit curves for the extended period of operation to be submitted as part of the applicant's LRA for this time-limited aging analysis (TLAA).

However, the staff does require NRC approval of the P-T limit curves for the extended period of operation prior to the expiration of the P-T limit curves for 32 EFPY. Please state when you intend to submit P-T limit curves for NRC approval for the extended licensed period of operation (54 EFPY).

RAI 4.2.4-1 Table 4.2-2 of the PNPS LRA lists initial RTNDT values for the PNPS RV beltline materials. The initial RTNDT values for Lower Intermediate Shell Plate G-3108-1 (Heat No. C-2921-2) and Lower Intermediate Shell Plate G-3108-3 (Heat No. C-2945-2) are less conservative than the corresponding initial RTNDT values established in the NRC staff's reactor vessel integrity database (RVID) for these materials. Section 4.2.4 of the PNPS LRA states that, "initial RTNDT values are from report SIR-00-82, which was submitted in 2001 as part of the PNPS P-T limit change request (Reference 4.2-5)." Reference 4.2-5 points to the April 13, 2001, license amendment issued by the NRC authorizing revised P-T limit curves.

ENCLOSURE

Please provide additional information that points to where the NRC staff authorized the use of the specific initial RTNDT values listed in Table 4.2-4 for determining the adjusted reference temperature (ART) values for the PNPS reactor vessel (RV) beltline materials.

RAI 4.2.4-2 The %Cu and chemistry factor (CF) values for Lower Shell Axial Welds 2-338A, B, and C from LRA Table 4.2-2 are less conservative than the corresponding %Cu and CF values that were established in the staff's RVID for these welds. Please provide the following information:

(a) verification of whether the %Cu and CF values listed in Table 4.2-1 are valid for the above welds, (b) justification for the use of these chemistry data for the above welds, including the source of the data, and a specific reference for the documentation/analysis demonstrating that these chemistry data represent the best available estimate of the weld chemistries.

RAI 4.2.4-3 Lower Intermediate / Upper Shell Circumferential Weld 3-339B (Heat No. 13253) is listed in the NRC staff's RVID. However this weld is not represented in LRA Table 4.2-2 or (LRA Table 4.2-1). Please resolve this discrepancy.

RAI 4.2.5-1 Section 4.2.5 of the PNPS LRA addresses the TLAA for the RV Circumferential Weld Examination Relief. Table 4.2-3 of the LRA compares the limiting RV circumferential weld parameters for PNPS to those used in the NRC evaluation of the BWRVIP-05 report, "BWR Vessel and Internals Project, BWR Reactor Pressure Vessel Shell Weld Inspection Recommendations." The PNPS limiting RV circumferential weld parameters are based on Lower Intermediate / Lower Shell Circumferential Weld 1-334 (Heat No. 21935), which is the only circumferential weld represented in LRA Table 4.2-2. However, as discussed in RAI 4.2.4-3, the NRC staff's RVID also lists Lower Intermediate / Upper Shell Circumferential Weld 3-339B (Heat No. 13253) as one of the RV welds for PNPS. Furthermore, the chemistry and CF data for this weld are more limiting than for the Circumferential Weld 1-334. Please explain why this TLAA did not address Lower Intermediate / Upper Shell Circumferential Weld 3-339B (Heat No. 13253).

RAI 4.2.5-2 The NRC staff requires that a request for relief from the American Society of Mechanical Engineer Boiler and Pressure Vessel Code (ASME Code) RV circumferential shell weld examination requirements be submitted prior to the beginning of the extended period of operation. Please state whether you intend to apply for relief from the ASME Code RV circumferential weld examination requirements for the extended licensed period of operation.

State when you plan to submit this relief request.

RAI 4.2.5-3 In the July 28, 1998 SER on BWRVIP-05, the NRC staff concluded that examination of the RV circumferential shell welds would need to be performed if the corresponding volumetric examinations of the RV axial shell welds revealed the presence of an age-related degradation mechanism. Confirm whether or not previous volumetric examinations of the RV axial shell welds have shown any indication of cracking or other age-related degradation mechanisms in the welds.

RAI 4.2.6-1 The limiting axial weld failure probability calculated by the NRC staff in the BWRVIP-05 SER is based on the assumption that "essentially 100 percent" (i.e*, greater than 90 percent) examination coverage of all RV axial welds can be achieved in accordance with ASME Code, Section Xl requirements.

State whether your ISI examinations achieve "essentially 100 percent" (i.e., greater than 90.

percent) overall examination coverage for the RV axial welds for the duration of the current licensed operating period. If less than 90 percent overall examination coverage is achieved for the RV axial welds, revise this TLAA to account for the effects of the limited scope examination coverage.