ML063060595

2006/09/07-E-mail: Final RAI on Section 4.3.2.1 on Pilgrim LRA

ML063060595
Person / Time
Site:	Pilgrim
Issue date:	09/07/2006
From:	Subbaratnam R Office of New Reactors
To:	Ellis D, Ford B, Mogolesko F Entergy Corp
References
%dam200612, TAC MD2296
Download: ML063060595 (10)

Text

ItKe-ht How-ard - Final RAI on S ection- 4.3.2.1 on Pilgrim LRA Page 1 Kent Howard Final RAI on Section 4.3.2.1 on Pilgrim LRA

-

P~6TI From: Ram Subbaratnam To: bford@entergy.com; Dellisl @entergy.com; fmogole@entergy.com Date: 9/7/2006 10:34:33 AM

Subject:

Final RAI on Section 4.3.2.1 on Pilgrim LRA Folks:

Please find attached one set of formal RAis on section 4.3.2.1 from the NRC staff on the Pilgrim LRA. 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 P.S I owe you two more set of RAIs that will conclude the milestone on issuing Final RAIs (Schedule September 10, 2006). I am planning to send them by COB today.

CC: Anissa Coates; Twana Ellis

11C.\tem D\GW 10000 1.TM P Pacie 111I em,\.. TM P..a . . .. .. . .... "e 1 Mail Envelope Properties (45002DF9.903: 19: 10294)

Subject:

Final RAI on Section 4.3.2.1 on Pilgrim LRA Creation Date 9/7/2006 10:34:33 AM From: Ram Subbaratnam Created By: RXS2@nrc.gov Recipients Action Date & Time entergy.com bford (bford@entergy.com) dellisl (Dellisl @entergy.com) fmogole (fmogole @entergy.com) nrc.gov OWGWPOO2.HQGWDO01 TYE CC (Twana Ellis) nrc.gov OWGWPOO3.HQGWDO01 ARC3 CC (Anissa Coates)

Post Office Delivered Route Pending entergy.com OWGWPOO2.HQGWDO01 Pending nrc.gov OWGWPOO3.HQGWDO01 Pending nrc.gov Files Size Date & Time MESSAGE 1132 9/7/2006 10:34:33 AM EFGBectio4.3.2.1RAIsFinal.wpd 34630 9/7/2006 10:28:30 AM 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

I!c:\temp\GW}O0001 .TMP Pane 211 1

Status Tracking: Delivered & Opened

August 25, 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 License Renewal Section: 4.3.1.2 Reactor Vessel Internals.

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.q-ov.

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

ML062490501 C:\temp\EFG Bectio4.3.2.1 RAIsFinal.wpd OFFICE PM:RLRA:DLR PM:CFEB:DCI LA:RLRA:DLR BC:REBB:DLR NAME RSubbaratnam Chia-Fu Sheng YEdmonds Llund R. Auluck for DATE 8/25/06 8/24/06 8/24/06 8/25/06

Letter to Michael Kansler from Ram Subbaratnam dated: August 25, 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 RidsNrrDIrRlrb RidsNrrDe RidsNrrDci RidsNrreEemb RidsNrrDeEeeb RidsNrrDeEqva RidsNrrDss RidsNrrDnrl RidsOgcMailCenter RidsNrrAdes DLR Staff RSubbaratnam Shoffman SUttal JShea AWilliamson Chia-Fu Sheng KGruss 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-Director, Radiation Control Program Plymouth, MA 02360-5508 Commonwealth of Massachusetts Executive Offices of Health and Mr. Gary J. Taylor Human Services Chief Executive -Officer 174 Portland Street Entergy Operations Boston, MA 02114 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 02332

REQUESTS FOR ADDITIONAL INFORMATION PILGRIM LICENSE RENEWAL APPLICATION (LRA)

SECTION: 4.3.1.2 REACTOR VESSEL INTERNALS 4.3.1.2 Reactor Vessel Internals RAI 4.3.1.2-1 Control rod drive (CRD) return line nozzle-to-end cap weld: Regarding the CRD return line nozzle-to-end cap weld repair, your Project Report LRPD-06, "Pilgrim NPS License Renewal Project - Time-Limited Aging Analyses, Mechanical Fatigue," Response 2.4 refers to Relief Request PRR-36 and concludes, "This relief did not involve any analyses based on time-limited assumptions and therefore is not a TLAA." PRR-36 was submitted by letters dated October 1, 3, and 8, 2004, and July 12, 2004, for relief from certain American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) requirements pertaining to the repair of the nozzle-to-end cap weld with a detected flaw and the associated non-destructive examinations. Alternatively, PRR-36 proposed to use ASME Code Case N-504-2, "Alternative Rules for Repair of Class 1, 2, and 3 Austenitic Stainless Steel Piping," with modifications to perform the repair. The request was approved in a safety evaluation (SE) dated February 25, 2005. ASME Code Case N-504-2 (g)(2) requires a flaw evaluation be performed on the repaired component such that "The evaluation should demonstrate that the requirements of IWB-3640... are satisfied for the design life of the repair, considering potential flaw growth due to fatigue and the mechanism believed to have caused the flaw. The flaw growth evaluation shall be performed in accordance with Appendix C." Explain how Entergy meets the ASME Code Case N-504-2 requirement on performing a flaw evaluation that considers fatigue and the mechanism believed to have caused the flaw. If applicable, you may provide a document showing that the weld overlay region adjacent to the interface is in the compressive stress zone.

RAI 4.3.1.2-2 Reactor recirculation nozzle thermal sleeves regarding the flaws on reactor recirculation nozzle thermal sleeves, LRPD-06 Response 2.4 refers to a flaw growth analysis in NEDC-30730 and concludes, "The NRC reviewed and accepted the analysis as documented in an SER (Ref.

4.2.21). As this analysis is only based on 18 months, it is not a TLAA." The cited SE was issued on December 4, 1984. As you stated, the crack growth analysis is for 18 months. One of the six criteria specified in 10 CFR 54.3(a) for classifying an analysis as a TLAA is the analysis "[i]nvolve time-limited assumptions defined by the current operating term, for example, 40 years." The meaning of a crack growth analysis based on 18 months is that the structural integrity of reactor recirculation nozzle thermal sleeves is not only a concern for the extended period of operation but also a concern for the remaining period of operation under the current 40-year license. Therefore, Entergy needs to consider this as a TLAA and address the following:

For the License Renewal Application:

(1) Confirm whether Report PMA86-07, "Pilgrim Nuclear Power Station Recirculation Inlet Thermal Sleeve Mock Up Fabrication and Evaluation," dated October 1986 had been reviewed by NRC staff.

ENCLOSURE

(2) Identify the SE which accepts use of hydrogen water chemistry as the mitigating method and as the basis for Entergy to operate with the flaws on the thermal sleeves beyond 1987.

(3) Provide an analysis of the inspection results on these thermal sleeves obtained from 1987 to date.

(4) Provide the end-of-extended-period-of-operation (60 years) flaw length of the circumferential through-wall flaw which was 32 percent circumference in 1987 (per the December 4,1984, SE for the worst flaw among the detected recirculation nozzle thermal sleeve cracks) and perform a stability analysis for this flaw.

(5) If the stability analysis of effort (4) shows that the predicted end-of-extended-period-of-operation through-wall flaw length does not meet the ASME Code Section XI margin, provide an impact evaluation on operation and structural integrity of other components due to a broken thermal sleeve piece of a reasonable size.

(6) Provide an inspection plan for these detected thermal sleeve flaws in the extended period of operation.

For current operation till the end of the 40-year operation:

(7) Discuss the adequacy of the inspection plan for recirculation nozzle thermal sleeves for the remaining period of 40-year operation.

(8) Provide the end of the 40-year operation flaw length of the circumferential through-wall flaw which was 32 percent circumference in 1987 and perform a stability analysis for this flaw.