ML070960030

03/21/2007 Summary of Telephone Conference Call Between the U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Concerning Information Pertaining to the James A. FitzPatrick Nuclear Power Plant License Renewal..

ML070960030
Person / Time
Site:	FitzPatrick
Issue date:	05/24/2007
From:	Tuan Le NRC/NRR/ADRO/DLR/RLRB
To:	Entergy Nuclear Operations
Le N. B., NRR/DLR/RLRB, 415-1458
References
Download: ML070960030 (10)

Text

May 24, 2007LICENSEE: Entergy Nuclear Operations, Inc.FACILITY: James A. FitzPatrick Nuclear Power Plant

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON MARCH 21, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC., CONCERNING INFORMATION PERTAINING TO THE JAMES A. FITZPATRICK NUCLEAR POWER PLANT, LICENSE RENEWAL APPLICATIONThe U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of EntergyNuclear Operations, Inc., held a telephone conference call on March 21, 2007, to discuss and clarify the staff's requests for additional information concerning the James A. FitzPatrick Nuclear Power Plant, license renewal application. The telephone conference call was useful in clarifying the intent of the staff's questions.Enclosure 1 provides a listing of the participants and Enclosure 2 contains a discussion of theissues discussed with the applicant.The applicant had an opportunity to comment on this summary./RA/Tommy Le, Sr. Project Manager License Renewal Branch B Division of License Renewal Office of Nuclear Reactor RegulationDocket No. 50-333

Enclosures:

1. List of Participants

2. List of Requests for Additional Informationcc w/encls: See next page

ML070960030 OFFICEPM:RLRB:DLRLA:DLRBC:RLRB:DLRNAMENBLeIKingRAuluck DATE05/24/0704/09/0705/24/07 TELEPHONE CONFERENCE CALLJAMES A. FITZPATRICK NUCLEAR POWER PLANTLICENSE RENEWAL APPLICATIONLIST OF PARTICIPANTSMARCH 21, 2007PARTICIPANTSAFFILIATIONSKent HowardU.S. Nuclear Regulatory Commission (NRC)Ngoc LeNRC James MedoffNRC Roy MathewNRC Allison BlackNRC Matthew MitchellNRC Qi Gan ChiNRC Rick PlasseEntergy Nuclear Operations (ENO)Alan CoxENOJoe PahacheckENO Doug HarrisonENO Chris PimmENO Steve GloverENO Tom MoskalykENO Mike StroudENO REQUESTS FOR ADDITIONAL INFORMATION JAMES A. FITZPATRICK NUCLEAR POWER PLANTLICENSE RENEWAL APPLICATIONMARCH 21, 2007The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of EntergyNuclear Operations, Inc., (Entergy) held a telephone conference call on March 21, 2007, to discuss and clarify the following questions concerning the James A. FitzPatrick Nuclear Power Plant (JAFNPP), license renewal application (LRA). Discussion #1

A.Commitment #20 on metal fatigue: The NRC requested that Entergy performan additional review of Commitment #20 on metal fatigue analyses to determine whether the actions of the commitment cover activities on performing new cumulative usage factors (CUF) calculations for Class 1 piping in the residual heat removal (RHR) and feedwater (FW) systems and on applying the appropriate F en factors to the CUF values in order to establish the environmentalCUF values for these NUREG/CR-6260 piping locations.Additional Requested Actions to Address this Issue

1.The NRC requested that Entergy perform an additional review of theexisting wording of Commitment #20 to see if the existing wording in the commitment already addresses this issue. If the current commitment does address this issue, Entergy will clarify how the existing commitment addresses actions to perform new enviromental CUF calculations for the Class 1 RHR and FW piping. If not, Entergy stated it will revise the commitment to propose additional actions to address this issue.B.Commitments #21 and #23 on management of cracking and loss of preload incore plate rim hold-down bolts: The NRC informed the applicant, that upon apeer review applicant's basis for managing cracking and loss of preload in the core plate rim hold-down bolts, Option 3 in Commitment #23 is not acceptable as a basis for managing these aging effects in the bolts for the period of extended operation (PEO).Additional Requested Actions to Address this Issue

1.Delete Commitment #21 on the LRA and use Commitment #23 as thebasis for managing cracking and loss of preload in the core plate rim hold-down bolts. The basis is that the staff does not require two separate commitments on the core plate rim hold-down bolts.2.Amend Commitment #23 as follows:(A)Amend Option 2 of the Commitment to state: "Complete a plant-specific analysis to determine acceptance criteria for continued inspection of core plate rim hold down bolting in 2accordance with boiling water reactor (BWR) VIP-25 and submitthe inspection plan, along with the acceptance criteria and justification for the inspection plan, to the NRC two years prior to the period of extended operation for NRC review and approval."(B) Delete Option 3 of the Commitment.

(C)Amend the Commitment to add a paragraph after the options thatstates: "If Option 2 is selected, the analysis to determine acceptance criteria will address the information requested in request for additional information (RAI) 3.1.2-2A and 4.7.3.2-1." (D)Amend the "Related LRA Section No. / Comments" entry forCommitment #23 to reflect the following references: A.2.2.7, A.2.1.7, B.17, 4.7.3.2, Audit Item 483, Audit Item 252, and RAI 4.7.3.2-1.3.Amend the response to parts b and c of RAI 4.7.3.2-1 as follows: (A)Amend Option 2 of the response to the RAI to state: "Complete aplant-specific analysis to determine acceptance criteria for continued inspection of core plate rim hold down bolting in accordance with BWRVIP-25 and submit the inspection plan, along with the acceptance criteria and justification for the inspection plan, to the NRC two years prior to the period of extended operation for NRC review and approval."(B) Delete Option 3 of the response to the RAI.C.Clarification on aging management of top guide grid beam locations: The NRCinformed the applicant, that upon further discussion with NRC management in the Division of Component Integrity, NRR, the position on inspections of top guide grid beam locations for the PEO is that the position in generic aging lessons learned (GALL) aging managing program (AMP) XI.M9, BWR Internals, is (i.e. five percent of the locations within six years of entering the PEO and an additional five percent of the locations within 12 years of entering the PEO) a sufficient basis for managing the effects of aging during the PEO if cracking has yet to be detected in the top guide grid beam locations. If prior examinations have been conducted and cracking has been detected in the grid beam locations, the staff position is that the cracking would put the top guide outside of the bounds of the recommendations in BWRVIP-26-A, and that the applicant would need to address the impact of cracking on the intended function of the top guide, as assessed within the scope of corrective action provisions in Renewal Applicant Action Item (1) in Section 4.1 of the staff's safety evaluation on BWRVIP-26-A, dated December 7, 2000 (ADAMS Accession No.

ML003776110).

3Additional Requested Actions to Address this Issue

1.The NRC informed the applicant that no additional commitments on topguide grid beam inspections are necessary at this time. No evidence of cracking has yet to be detected in the top guide grid beam locations to date. Entergy has therefore proposed to inspection the grid beam locations in the JAFNPP top guide in conformance with the position established for top guides on page XI M-4 of GALL AMP XI.M9, "BWR Internals." This is in conformance with GALL AMP XI.M9. However, the staff requested the Entergy Nuclear North's (ENN's) responsible BWRVIP-Engineer perform an additional review of ENN BWRVIP program and to clarify what ENN's administrative BWRVIP program process would require (this is an Entergy-established requirement not an NRC requirement) if cracking is detected in any of the top guide grid beam locations.Discussion #2

The discussion centered around information the applicant had previously submitted inresponse to our February,13 2007, conference call. In their response they proposed deleting section 4.7.2 "Leak Before Break."4 NRC staff wondered how the issue of fatigue in the calculations in the updated final safety analysis report had been dispositioned such that a time-limited aging analysis (TLAA) no longer existed. The applicant believed the calculation should never have been called a TLAA because there is no mention of 40 years, only a number of cycles, which still bounds the period of license extension. NRC was concerned about how the NRC Office of General Counsel (OGC) would define a TLAA. The NRC action item was to talk with OGC and determine their characterization of the situation. If the calculation should be a TLAA, the applicant will not delete the section, but will provide information to close a review of the TLAA.

Note to Entergy Nuclear Operations, from N. Le, date May 24, 2007DISTRIBUTION:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON MARCH 21, 2007, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND ENTERGY NUCLEAR OPERATIONS, INC.,,

CONCERNING INFORMATION PERTAINING TO THE JAMES A.

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ECobey RLaufer JBoska FitzPatrick Nuclear Power Plant cc:Mr. Gary J. TaylorChief Executive Officer Entergy Operations, Inc.

1340 Echelon Parkway Jackson, MS 39213Mr. John T. HerronSr. VP and Chief Operating Officer Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601Mr. Peter T. DietrichSite Vice President Entergy Nuclear Operations, Inc.

James A. FitzPatrick Nuclear Power PlantP.O. Box 110 Lycoming, NY 13093Mr. Kevin J. MulliganGeneral Manager, Plant Operations Entergy Nuclear Operations, Inc.

James A. FitzPatrick Nuclear Power PlantP.O. Box 110 Lycoming, NY 13093Mr. Oscar LimpiasVice President Engineering Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601Mr. Christopher SchwartzVice President, Operations Support Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601Mr. John F. McCannDirector, Licensing Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601Resident Inspector's OfficeJames A. FitzPatrick Nuclear Power Plant U. S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, NY 13093Ms. Charlene D. FaisonManager, Licensing Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601Mr. Michael J. ColombDirector of Oversight Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601Mr. David WallaceDirector, Nuclear Safety Assurance Entergy Nuclear Operations, Inc.

James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093Mr. James CostedioManager, Regulatory Compliance Entergy Nuclear Operations, Inc.

James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093Assistant General CounselEntergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601Mr. Charles Donaldson, EsquireAssistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 FitzPatrick Nuclear Power Plant cc:-2-Regional Administrator, Region IU.S. Nuclear Regulatory Commission

475 Allendale Road King of Prussia, PA 19406Mr. Steven LymanOswego County Administrator 46 East Bridge Street Oswego, NY 13126Mr. Peter R. Smith, PresidentNew York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399Mr. Paul EddyNew York State Dept. of Public Service 3 Empire State Plaza Albany, NY 12223-1350SupervisorTown of Scriba Route 8, Box 382 Oswego, NY 13126Mr. James H. SniezekBWR SRC Consultant 5486 Nithsdale Drive Salisbury, MD 21801-2490Mr. Michael D. LysterBWR SRC Consultant 5931 Barclay Lane Naples, FL 34110-7306Mr. Garrett D. Edwards814 Waverly Road Kennett Square, PA 19348Mr. Rick PlasseProject Manager, License Renewal Entergy Nuclear Operations, Inc.

James A. FitzPatrick Nuclear Power PlantP.O. Box 110 Lycoming, NY 13093 Mr. James RossNuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708