ML043280684
| ML043280684 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/22/2004 |
| From: | Morgan M NRC/NRR/DRIP/RLEP |
| To: | Division of Regulatory Improvement Programs |
| Morgan M, NRR/DRIP/RLEP, 415-2232 | |
| References | |
| Download: ML043280684 (7) | |
Text
November 22, 2004 LICENSEE:
Nuclear Management Company, LLC FACILITY:
Point Beach Nuclear Plant, Units 1 and 2
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE HELD ON OCTOBER 28, 2004, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND NUCLEAR MANAGEMENT COMPANY, LLC, CONCERNING DRAFT REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission staff (the staff) and representatives of Nuclear Management Company, LLC (NMC) held a telephone conference on October 28, 2004, to discuss and clarify the staffs draft requests for additional information (D-RAIs) concerning the Point Beach Nuclear Plant, Units 1 and 2, license renewal application. The conference call was useful in clarifying the intent of the staffs D-RAIs. provides a listing of the meeting participants. Enclosure 2 contains a listing of the D-RAIs discussed with the applicant, including a brief description on the status of the items.
The applicant had an opportunity to comment on this summary.
/RA/
Michael J. Morgan, Project Manager License Renewal Section A License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket Nos.: 50-266 and 50-301
Enclosures:
As stated cc w/encls: See next page
ML043280684 DOCUMENT NAME: E:\\Filenet\\ML043280684.wpd OFFICE PM:RLEP SC:RLEP NAME MMorgan SLee DATE 11/22/04 11/22/04
Point Beach Nuclear Plant, Units 1 and 2 cc:
Jonathan Rogoff, Esq.
Vice President, Counsel & Secretary Nuclear Management Company, LLC 700 First Street Hudson, WI 54016 Mr. Frederick D. Kuester President and Chief Executive Officer We Generation 231 West Michigan Street Milwaukee, WI 53201 James Connolly Manager, Regulatory Affairs Point Beach Nuclear Plant Nuclear Management Company, LLC 6610 Nuclear Road Two Rivers, WI 54241 Mr. Ken Duveneck Town Chairman Town of Two Creeks 13017 State Highway 42 Mishicot, WI 54228 Chairman Public Service Commission of Wisconsin P.O. Box 7854 Madison, WI 53707-7854 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Resident Inspector's Office U.S. Nuclear Regulatory Commission 6612 Nuclear Road Two Rivers, WI 54241 Mr. Jeffrey Kitsembel Electric Division Public Service Commission of Wisconsin P.O. Box 7854 Madison, WI 53707-7854 David Weaver Nuclear Asset Manager Wisconsin Electric Power Company 231 West Michigan Street Milwaukee, WI 53201 John Paul Cowan Executive Vice President & Chief Nuclear Officer Nuclear Management Company, LLC 700 First Street Hudson, WI 54016 Douglas E. Cooper Senior Vice President - Group Operations Palisades Nuclear Plant Nuclear Management Company, LLC 27780 Blue Star Memorial Highway Covert, MI 49043 Fred Emerson Nuclear Energy Institute 1776 I Street, NW., Suite 400 Washington, DC 20006-3708 Roger A. Newton 3623 Nagawicka Shores Drive Hartland, WI 53029 James E. Knorr License Renewal Project Nuclear Management Company, LLC 6610 Nuclear Road Point Beach Nuclear Plant Two Rivers, WI 54241 Dennis L. Koehl Site Vice President Point Beach Nuclear Plant Nuclear Management Company, LLC 6610 Nuclear Road Two Rivers, WI 54241
DISTRIBUTION: Note to Licensee: Nuclear Management Co., LCC, Re: Pt. Beach Nuclear Plant, Units 1 and 2. Dated: November 22, 2004 Adams accession no.: ML043280684 HARD COPY RLEP RF Project Manager E-MAIL:
RidsNrrDrip RidsNrrDe G. Bagchi K. Manoly W. Bateman J. Calvo R. Jenkins P. Shemanski J. Fair RidsNrrDssa RidsNrrDipm D. Thatcher R. Pettis G. Galletti C. Li M. Itzkowitz (RidsOgcMailCenter)
R. Weisman M. Mayfield A. Murphy S. Smith (srs3)
S. Duraiswamy Y. L. (Renee) Li RLEP Staff L. Kozak, RIII P. Lougheed, RIII J. Strasma, RIII A. Vegel, RIII H. Chernoff W. Ruland C. Marco L. Raghavan T. Mensah OPA LIST OF PARTICIPANTS FOR TELEPHONE CONFERENCE TO DISCUSS THE POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION OCTOBER 28, 2004 Participants Affiliations T. Mielke Nuclear Management Company, LLC J. Thorgersen Nuclear Management Company, LLC B. Fromm Nuclear Management Company, LLC J. Knorr Nuclear Management Company, LLC N. Ray Nuclear Regulatory Commission M. Heath Nuclear Regulatory Commission M. Morgan Nuclear Regulatory Commission DRAFT REQUESTS FOR ADDITIONAL INFORMATION (D-RAI)
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION October 28, 2004 The U.S. Nuclear Regulatory Commission staff (the staff) and representatives of Nuclear Management Company, LLC (NMC) held a telephone conference call on October 28, 2004, to discuss and clarify the staffs draft requests for additional information (D-RAIs) concerning the Point Beach Nuclear Plant, Units 1 and 2, license renewal application (LRA). The following D-RAIs were discussed during the telephone conference call.
4.4 Fracture Mechanics Analysis D-RAI 4.4.2 (Reactor Coolant Pump Flywheel Analysis)
The staff needs explanation as to the number of reactor coolant pump (RCP) start/stop cycles that are assumed in the 60-year RCP flywheel fatigue crack growth assessment for the Point Beach Units.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
B 2.0 Aging Management Programs D-RAI B 2.1.6-1 (Boric Acid Corrosion Program)
The staff seeks additional clarification regarding the list of components that are within the scope of the Boric Acid Corrosion Program and the process the applicant uses to augment the list of components within the scope of the AMP based on pertinent industry experience. This is RAI B2.1.6-1. Specifically, the staff requested the following actions of the applicant:
C Submittal of a discussion on how NMCs responses to NRC Bulletin 2002-01, dated March 29, 2002, and May 16, 2002; responses to the NRCs RAIs on the bulletin, dated January 17, 2003; response to NRC Bulletin 2003-02, dated September 19, 2003; responses to NRC Order EA-03-009, dated March 3, 2003, April 11, 2003, and April 18, 2003; and response to NRC Bulletin 2004-01, dated May 28, 2004 have been used to update the list of component locations and types of visual inspections credited within the scope of the Boric Acid Corrosion Program or within the scope of other aging management programs (AMPs) that provide for implementation of similar or more conservative types of inspections.
C If the responses were used to supplement the scope of the Boric Acid Corrosion Program or other AMPs, identification of the component locations that have been added to the scope of the program and clarfication of the type of visual examinations (i.e.,
specification on whether VT-1, VT-2 or VT-3 will be used and whether the visual examinations will be enhanced, bare-surface, qualified, etc.) that will be implemented on those components within the current scope of the program.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-RAI B 2.1.18-1 (Reactor Vessel Surveillance Capsule Program)
GALL Program XI.M31 suggested that standby capsules are to be removed and placed in storage. Even though the capsules do not contain limiting material, these standby capsules provide general embrittlement trends and provide assurance that current embrittlement methodologies apply to Point Beach. Leaving the capsules in the vessel, further exposure would not provide any meaningful data. Please justify your decision of not removing the capsule and keep it in storage.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-RAI B 2.1.23-1 (Thimble Tube Inspection Program)
Section B2.1.23 indicates that eddy current examinations are performed on a periodicity consistent with the severity of wear damage for each thimble tube. The frequency of inspections is based on the maximum wall loss noted in a region of active wear and the projected wear which would occur based on a known wear rate.
1.
Identify the wear rate that is currently being used and how did you calculate the wear rate. Based on this wear rate, how were the inspection intervals determined to ensure that wear resulting from flow induced vibration does not result in the wall thickness below the minimum required thimble tube integrity?
2.
Specify the NDE uncertainty that is used in the calculations along with a justification for the NDE uncertainty value assumed in the calculation. Note that we would like the NDE uncertainty to be specified as a given percentage of the nominal wall thickness for the thimble tubes.
The applicants Operating Experience identified certain problems related to inspection deferrals, calculation methodology, and record retention.
Explain the problems in detail and how and when are you going to address the issues.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.