ML070960030
| 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, 2007 LICENSEE: Entergy Nuclear Operations, Inc.
FACILITY: James A. FitzPatrick Nuclear Power Plant
SUBJECT:
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 APPLICATION The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Nuclear Operations, Inc., held a telephone conference call on March 21, 2007, to discuss and clarify the staffs 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 staffs questions. provides a listing of the participants and Enclosure 2 contains a discussion of the issues 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 Regulation Docket No. 50-333
Enclosures:
- 1. List of Participants
- 2. List of Requests for Additional Information cc w/encls: See next page
ML070960030 OFFICE PM:RLRB:DLR LA:DLR BC:RLRB:DLR NAME NBLe IKing RAuluck DATE 05/24/07 04/09/07 05/24/07 TELEPHONE CONFERENCE CALL JAMES A. FITZPATRICK NUCLEAR POWER PLANT LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS MARCH 21, 2007 PARTICIPANTS AFFILIATIONS Kent Howard U.S. Nuclear Regulatory Commission (NRC)
Ngoc Le NRC James Medoff NRC Roy Mathew NRC Allison Black NRC Matthew Mitchell NRC Qi Gan Chi NRC Rick Plasse Entergy Nuclear Operations (ENO)
Alan Cox ENO Joe Pahacheck ENO Doug Harrison ENO Chris Pimm ENO Steve Glover ENO Tom Moskalyk ENO Mike Stroud ENO REQUESTS FOR ADDITIONAL INFORMATION JAMES A. FITZPATRICK NUCLEAR POWER PLANT LICENSE RENEWAL APPLICATION MARCH 21, 2007 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Entergy Nuclear 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 perform an 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 Fen factors to the CUF values in order to establish the environmental CUF 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 the existing 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 in core plate rim hold-down bolts: The NRC informed the applicant, that upon a peer review applicants 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 the basis 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
2 accordance with boiling water reactor (BWR) VIP-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 Commitment.
(C)
Amend the Commitment to add a paragraph after the options that states: 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 for Commitment #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 a plant-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 NRC informed 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 staffs safety evaluation on BWRVIP-26-A, dated December 7, 2000 (ADAMS Accession No. ML003776110).
3 Additional Requested Actions to Address this Issue:
1.
The NRC informed the applicant that no additional commitments on top guide 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 Norths (ENNs) responsible BWRVIP-Engineer perform an additional review of ENN BWRVIP program and to clarify what ENNs 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 in response 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, 2007 DISTRIBUTION:
SUBJECT:
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 APPLICATION HARD COPY:
DLR RF E-MAIL:
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FitzPatrick Nuclear Power Plant cc:
Mr. Gary J. Taylor Chief Executive Officer Entergy Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Mr. John T. Herron Sr. VP and Chief Operating Officer Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Peter T. Dietrich Site Vice President Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093 Mr. Kevin J. Mulligan General Manager, Plant Operations Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093 Mr. Oscar Limpias Vice President Engineering Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Christopher Schwartz Vice President, Operations Support Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. John F. McCann Director, Licensing Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Resident Inspector's Office James A. FitzPatrick Nuclear Power Plant U. S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, NY 13093 Ms. Charlene D. Faison Manager, Licensing Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Michael J. Colomb Director of Oversight Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. David Wallace Director, Nuclear Safety Assurance Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093 Mr. James Costedio Manager, Regulatory Compliance Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093 Assistant General Counsel Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271
FitzPatrick Nuclear Power Plant cc: Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Steven Lyman Oswego County Administrator 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 Supervisor Town of Scriba Route 8, Box 382 Oswego, NY 13126 Mr. James H. Sniezek BWR SRC Consultant 5486 Nithsdale Drive Salisbury, MD 21801-2490 Mr. Michael D. Lyster BWR SRC Consultant 5931 Barclay Lane Naples, FL 34110-7306 Mr. Garrett D. Edwards 814 Waverly Road Kennett Square, PA 19348 Mr. Rick Plasse Project Manager, License Renewal Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093 Mr. James Ross Nuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708