ML063040463

Email: (NPA-PD-LR) RAI on Chapter 4.0 TLAAs (from Ram Subbaratnam)

ML063040463
Person / Time
Site:	Pilgrim
Issue date:	08/16/2006
From:	Subbaratnam R Office of Nuclear Reactor Regulation
To:	Ganesh Cheruvenki, Christopher Sydnor Office of Nuclear Reactor Regulation
References
%dam200612, TAC MD2296
Download: ML063040463 (11)

Text

l[Kenýt pward_-RAI on Chapter 4.0 TLAAs ................ . .. .. . . .... _ _Page 1 From: Ram Subt *aratnam To: ChristophEer Sydnor; Ganesh Cheruvenki Date: 8/16/2006 10:36:35 AM

Subject:

RAI on Ch apter 4.0 TLAAs Ganesh/Chris:

These are the only RAIs so far on chapter 4.0 (from Simon). As I am wrapping up my RAIs for Pilgrim (I thank you all for the very prompt and pro-active coperation in providing me insight related to your assignment), I will very much appreciate it if you can let me know if you have any furhter Qs on Chapter 4.0.

Thanking you.

Ram Subbaratnam PM Pilgrim LRA (301) 415 1478 CC: Kimberly Gruss; Matthew Mitchell

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Subject:

RAI on Chapter 4.0 TLAAs Creation Date 8/16/2006 10:36:35 AM From: Ram Subbaratnam Created By: RXS2@ nrc. gov Recipients Action Date & Time nrc.gov OWGWPOO2.HQGWDO01 KAG1 CC (Kimberly Gruss) nrc.gov OWGWPOO3.HQGWDO01 GSC (Ganesh Cheruvenki) nrc.gov TWGWPOO1.HQGWDO01 MAM4 CC (Matthew Mitchell) nrc.gov TWGWPO02.HQGWDO01 CRS (Christopher Sydnor)

Post Office Delivered Route OWGWPO02.HQGWDO01 Pending nrc.gov OWGWPOO3.HQGWDOO1 Pending nrc.gov TWGWPOO1.HQGWDO01 Pending nrc.gov TWGWPO02.HQGWDOO1 Pending nrc.gov Files Size Date & Time MESSAGE 846 8/16/2006 10:36:35 AM CVlBSection4.2.1 RAIsFinal.wpd 37286 7/31/2006 6:12:40 PM Options Auto Delete: No Expiration Date: None Notify Recipients: Yes Priority: Standard ReplyRequested: No Return Notification: None

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

Kent Howard - CVIBSection4.2.1 RAIsFinal.wpd Page 1 11 Kent Howard CVIBSection4.2.1 RAIsFinaI.wpd Page 1 II July 31, 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 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 B.1.3 Control Rod Drive Return Nozzle, B.1.26 Reactor Vessel Surveillance Program and time-limited aging analysis aspects for Reactor Vessel Fluence (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 e-mail RXS2@nrc.qov.

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

ML062120752 CVIBSection4.2.1 RAIsFinal.wpd OFFICE PM:RLRA:DLR LA:DLR BC:REBB:DLR NAME RSubbaratnam IKing LLund DATE 7/26 /06 7/21 /06 7/26 /06 Kent Howard - CVIBSection4.2.1 RAIsFinal.wpd Page 3 11 J~

Kent Howard - CVIBSection4.2.1 RAIsFinal.wpd Page 311 3

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 RidsNrrDIrRIrb RidsNrrDe RidsNrrDci RidsNrreEemb RidsNrrDeEeeb RidsNrrDeEqva RidsNrrDss RidsNrrDnrI RidsOgcMailCenter RidsNrrAdes DLR Staff RSubbaratnam SHoffman SUttal JShea AWilliamson MMitchell Llambrose GCheruvenki GWilson CAnderson, Region 1 WRaymond, Region 1 NSheehan, Region 1 Pilgrim Nuclear Power Station cc:

i Kent HQward - CVlBSection4.2.1 RAIsFinal.wpjd ... ... ........ . .. . . . . . .... . .. .. Pag e 4 1 4

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

Nuclear Matters Committee Pilgrim Nuclear Power Station Town Hall 600 Rocky Hill Road 11 Lincoln Street Plymouth, MA 02360-5508 Plymouth, MA 02360 Mr. Stephen J. Bethay

'Chairman, Duxbury Board of Selectmen Director, Nuclear Safety Assurance Town Hall Entergy Nuclear Operations, Inc.

878 Tremont Street Pilgrim Nuclear Power Station Duxbury, MA 02332 600 Rocky Hill Road Plymouth, MA 02360-5508 Office of the Commissioner Massachusetts Department of Mr. Bryan S. Ford Environmental Protection Manager, Licensing One Winter Street Entergy Nuclear Operations, Inc.

Boston, MA 02108 Pilgrim Nuclear Power Station 600 Rocky Hill Road Office of the Attorney General Plymouth, MA 02360-5508 One Ashburton Place 20th Floor Mr. Gary J. Taylor Boston, MA 02108 Chief Executive Officer Entergy Operations Director, Radiation Control Program 1340 Echelon Parkway Commonwealth of Massachusetts Jackson, MS 39213 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

It-Kent Howard - CVIBSection4.2.1 RAIsFinal.wpd . . . ._ .. .. . . . . . . . .......... . . ... Pa g e 511 5

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 Naples, FL 34110-7306 Kingston Public Library ATTN: Reference Librarian Mr. Michael J. Colomb 6 Green Street Director of Oversight Kingston, MA 02364 Entergy Nuclear Operations, Inc.

440 Hamilton Avenue Ms. Mary Lampert White Plains, NY 10601 Duxbury Nuclear Advisory, Chair Pilgrim watch, Director 148 Washington Street Duxbury 02332

Kent Howard - CVIBSection4.2.1 RAIsFinaI.wpd Page 6 6

11Kent Howard - CVIBSection4.2.1 RAIsFinal.wDd Paqe 7 11 BKent Howard CVlBSection4.2.1 RAlsFinal.wDd Pacie 711 7

REQUESTS FOR ADDITIONAL INFORMATION (RAIs)

PILGRIM NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION SECTIONS B.1.3, B.1.26 and 4.2.1 B.1.26 Reactor Vessel Surveillance Program RAI-B.11.26-1 The applicant in the updated final safety analysis report (UFSAR) supplement A.2.1.28, "Reactor Vessel Surveillance Program," and in the aging management program (AMP) B.1.26, "Reactor Vessel Surveillance," states that it will implement the Boiling Water Reactor Vessel and Internals Project (BWRVIP) integrated surveillance program (ISP) at the Pilgrim Nuclear Power Station (PNPS) as specified in BWRVIP-1 16, "BWR Vessel Internals Project Integrated Surveillance Program Implementation for License Renewal." - By letter dated March 1, 2006, the staff has issued the final safety evaluation (SE) for the BWRVIP-1 16 report and therefore, the staff requests that the applicant include the following statement in UFSAR supplement Section A.2.1.28 and in AMP B.1.26 of the license renewal application (LRA).

"The BWRVIP-1 16 report which was approved by the staff will be implemented at PNPS with the conditions documented in Sections 3 and 4 of the staff's final SE dated March 1,2006, for the BWRVIP-116 report."

RAI-B.1.26-2 Title 10 of the Code Federal Regulations Part 50 (10 CFR Part 50), Appendix H requires that an ISP used as a basis for a licensee implemented reactor vessel surveillance program be reviewed and approved by the NRC staff. The ISP to be used by the applicant is a program that was developed by the BWRVIP. The applicant will apply the BWRVIP ISP as the method by which the PNPS unit will comply with the requirements of 10 CFR Part 50, Appendix H. The BWRVIP ISP identifies capsules that must be tested to monitor neutron radiation embrittlement for all licensees participating in the ISP and identifies capsules that need not to be tested (standby capsules). Table 3-3 of the BWRVIP-1 16 report indicates that the standby capsule from PNPS unit is not to be tested. This untested capsule was originally part of the applicant's plant-specific surveillance program and has received significant amounts of neutron radiation.

The staff requests that the applicant include the following statement in the UFSAR supplement Section A.2.1.28 of the LRA.

"If the PNPS standby capsule is removed from the reactor vessel without the intent to test it, the capsule will be stored in a manner which maintains it in a condition which would permit its future use, including during the period of extended operation, if necessary."

Enclosure

11Kent Howard - CVIBSection4.2.1 RAIsFinal.wi)d Page 8 11 Kent Howard - CVlBSection4.2.1 RAlsFinal.wpd Page 8D B.1.3-1 Control Rod Drive (CRD) Return Nozzle RAI-B.11.3-1 Provide information regarding the type of inspection and the inspection frequency of the capped CRD return line nozzle weld overlay during the extended period of operation.

RAI-B.11.3-2 The applicant states that it will take the following exception to the inspection requirements for the CRD return line nozzle weld as mandated by the American Society of Mechanical Engineers (ASME) Code, Section Xl.

PNPS proposes to examine 12" of the volume on either side of the widest part of the N10 nozzle-to-vessel weld in lieu of 1/2 the vessel wall thickness as required by the ASME Code, Section Xl, 1998 Edition, 2000 Addenda, Figure IAB-2500-7(b).

The staff requests that the applicant provide information regarding the state of stress that is present in the volume of the subject weld that will not be included in the future examinations.

Clarify whether the highly stressed volume of the weld, where cracks can initiate, will be examined effectively with the proposed alternative. The staff believes that the applicant should obtain prior approval from the staff for implementing the proposed alternative examination under the provisions of 10 CFR 50.55a before entering into the extended period of operation.

Provide information whether the proposed alternative examination of the CRD return line nozzle weld has previously been submitted to the staff for review and approval for the current ISI interval.

4.2.1 Reactor Vessel Fluence RAI 4.2.1-1 Section 4.2.1 of the submittal indicates that PNPS used the radiation analysis modeling application code for the calculation of the 54 effective full-power year (EFPY) vessel fluence values. Section 4.2.2 states that recent calculations done per Regulatory Guide 1.190 confirm that the fluence for 54 EFPY is less than the fluence used to calculate the pressure and temperature limits in Reference 4.2-5, "Pilgrim Nuclear Power Station - Issuance of Amendment Re: Pressure-Temperature Limit Curves (TAC NO.MB0561)," letter dated April 13, 2001, Wang, A., to M. Bellamy.

Please provide information to substantiate this statement, preferably in the form of a contractor's report that documented these fluence calculations.

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