ML051680452

Summary of Telecon Held on March 28, 2005, Between the U.S. NRC and Nuclear Management Company, LLC Concerning Draft Requests for Additional Information Pertaining to Point Beach Nuclear Plant, Units 1 and 2, License Renewal Application

ML051680452
Person / Time
Site:	Point Beach
Issue date:	06/16/2005
From:	Veronica Rodriguez NRC/NRR/DRIP/RLEP
To:	Nuclear Management Co
Rodriguez V, RLEP/DRIP/NRR, 415-2232
References
TAC MC2099, TAC MC2100
Download: ML051680452 (7)

Text

June 16, 2005 LICENSEE:

Nuclear Management Company, LLC FACILITY:

Point Beach Nuclear Plant, Units 1 and 2

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON MARCH 28, 2005, 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 (TAC NOS. MC2099 AND MC2100)

The U.S. Nuclear Regulatory Commission staff (the staff) and representatives of Nuclear Management Company, LLC (NMC) held a telephone conference call on March 28, 2005, 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/

Veronica M. Rodriguez, 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

DOCUMENT NAME: E:\\Filenet\\ML051680452.wpd OFFICE PM:RLEP PM:RLEP LA:RLEP SC:RLEP NAME GSuber VRodriguez YEdmonds SLee DATE 04/28/05 04/13/05 04/13/05 06/16/05

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

DISTRIBUTION: Note to Nuclear Management Company, Re: Summary of telecon held on March 28, 2005, Dated: June 16, 2005 Adams Accession No.: ML051680452 HARD COPY RLEP RF 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 K. Winsberg (RidsOgcMailCenter)

R. Weisman M. Mayfield A. Murphy S. Smith (srs3)

S. Duraiswamy Y. L. (Renee) Li RLEP Staff P. Lougheed, RIII J. Strasma, RIII A. Stone, RIII H. Chernoff W. Ruland L. Raghavan T. Mensah OPA LIST OF PARTICIPANTS FOR TELEPHONE CONFERENCE CALL TO DISCUSS THE POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION MARCH 28, 2005 Participant Affiliation Brad Fromm Nuclear Management Company, LLC (NMC)

Jim Knorr NMC John Thorgersen NMC Mark Ortmayer NMC Todd Mielke NMC Johnny Eads U.S. Nuclear Regulatory Commission (NRC)

Ken Chang NRC Kurt Cozens NRC Michael Morgan NRC Muhammad Razzaque NRC Robert Hsu NRC Samuel Miranda NRC Veronica Rodriguez NRC DRAFT REQUESTS FOR ADDITIONAL INFORMATION (D-RAI)

POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION March 28, 2005 The U.S. Nuclear Regulatory Commission staff (the staff) and representatives of Nuclear Management Company, LLC (NMC) held a telephone conference call on March 28, 2005, 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.

D-RAI 3.1.1-2 The staff believes that the steam generator (SG) feedrings and associated J-tubes should be included in the scope of license renewal. Since this component is completely enclosed by safety-related pressure-boundary components, it is important to show that failures of this component would not impede its designed safety-related functions, as required by 10 CFR 54.4(a)(2).

Industry experience indicates that certain aging effects will degrade these components, and if permitted to continue, could result in loose parts and could interfere with its intended function.

Examples of the operating experience information compiled by both the Institute of Nuclear Power Operations (INPO) and World Association of Nuclear Operators (WANO) are presented as follows:

On April 25, 1989, a Westinghouse Model 51 steam generator was undergoing periodic testing and J-nozzles were found to be eroded/corroded.

On January 14, 1995, a Westinghouse Model 51 steam generator was undergoing a special leak test of the feedring and water appeared to be flowing from a fault in either the piping or plug located at the support bracket, 180 degrees from the feedwater inlet.

Two J-nozzles were removed from the top of the feedring, the area was cleaned, and the damaged weld in the bottom of the feedring was weld repaired. Although there was no failure on the J-nozzles, two existing J-nozzles were replaced with new style Inconel J-nozzles as a preventive measure.

The staff requests the applicant to justify why the SG feedrings and associated J-tubes should not be scoped into the license renewal. If such justification is not available, the staff requests the applicant to provide the aging management program that PBNP will be committing to manage these aging effects.

Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI 3.5-13 (1) In LRA Section 3.5.2.2.1.1, the applicant stated that concrete degradation in air due to aggressive rainwater is insignificant and the below-grade/lake water environment is non-aggressive. The staff requests the applicant to provide sufficient data to support this statement.

(2) During its AMR review, the staff was unable to identify how the LRA addresses the items described in the Interim Staff Guidance (ISG)-03. The staff requests the applicant to identify how its AMRs address all the items described ISG-03.

Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

D-RAI 2.3.1.2-2 The staff believes that the reactor vessel flange leakoff lines should be included in the scope of license renewal. The staff has taken the position (B&W Owners Group, ML993130195) that the reactor vessel flange pressure boundary is at the outboard flange seal. Therefore, the reactor vessel flange leakoff lines are part of the reactor vessel pressure boundary and should be treated as part of the reactor coolant system pressure boundary. As a result, the reactor vessel flange leakoff lines are within the scope of 10 CFR 54.4.

The staff requests the applicant to justify why the reactor vessel flange leakoff lines are not within the scope of 10 CFR 54.4 or to provide the aging management program that will be used to manage the lines during the period of extended operation.

Discussion: The applicant indicated that at Point Beach the reactor vessel flange leakoff lines are nonsafety-related components and therefore if it was to be considered within the scope of license renewal it will be screened under the 10 CFR 54.4(a)(2) criteria. Because the staff is not aware of any credible aging effect mechanism, there is no basis to conclude that this component will degrade and prevent any safety-related component from performing its intended function. Therefore, this question is WITHDRAWN and will not be sent as a formal RAI.