ML051050312

From kanterella
Jump to navigation Jump to search

Summary of Telephone Conference Call Held on March 31, 2005 Between NRC and Nuclear Management Company, LLC, Concerning Draft RAIs Pertaining to Point Beach, Units 1 and 2, License Renewal Application
ML051050312
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 04/15/2005
From: Veronica Rodriguez
NRC/NRR/DRIP/RLEP
To:
Nuclear Management Co
Rodriguez V, RLEP/DRIP/NRR, 415-2232
References
TAC MC2099, TAC MC2100
Download: ML051050312 (7)


Text

April 15, 2005 LICENSEE:

Nuclear Management Company, LLC FACILITY:

Point Beach Nuclear Plant, Units 1 and 2

SUBJECT:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON MARCH 31, 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 31, 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

ML051050312 DOCUMENT NAME: E:\\Filenet\\ML051050312.wpd OFFICE PM:RLEP PM:RLEP LA:RLEP SC:RLEP NAME GSuber VRodriguez YEdmonds SLee DATE 04/15/05 04/13/05 04/13/05 04/15/05

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 Co., LLC, Re: Telecon held on March 31, 2005 concerning draft RAIs pertaining to Pt. Beach (1 and 2), Dated: April 15, 2005 Adams Accession No.: ML051050312 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 31, 2005 Participants Affiliations Brad Fromm Nuclear Management Company, LLC (NMC)

Jim Knorr NMC John Thorgersen NMC Mark Ortmayer NMC Kurt Cozens Nuclear Regulatory Commission (NRC)

Robert Hsu NRC Veronica Rodriguez NRC DRAFT REQUESTS FOR ADDITIONAL INFORMATION (D-RAI)

POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION March 31, 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 31, 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.

Aging Management of Auxiliary Systems D-RAI 3.3-7 In LRA Table 3.3.2-2 (Page 3-221), the applicant proposed to manage cracking due to IGA/IGSCC of stainless steel in heat exchanges exposed to primary treated water with T>480oF (internal) using the Water Chemistry Control Program. This line item cites Note 35, which states Component/material/environment is not addressed in the corresponding NUREG-1801 Chapter, but the component/material/environment is addressed in another NUREG-1801 Chapter. The AMR line item references AMR line item 3.1.1-36 which provides the following discussion:

Crack initiation and growth due to SCC and flaw growth are identified as aging effects requiring management for the reactor vessel nozzle safe ends, CRD housing, and RCS components. Aging management programs credited for managing these effects are the Water Chemistry Control Program and ASME Section XI, Subsections IWB, IWC, and IWD Inservice Inspection Program.

The Note implies that ASME Section XI, Subsections IWB, IWC, and IWD Inservice Inspection Program should have also been applied to LRA Table 3.3.2-2. The staff requests the applicant to explain this discrepancy or make a commitment to revise the line item in LRA Table 3.3.2-2 to include the Inservice Inspection Program.

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

Aging Management of Containments, Structures and Component Supports D-RAI 3.5-14 (1) In LRA Table 3.5.1, Item 3.5.1-33, the applicant stated that the Bolting Integrity Program includes the use of Inservice Inspections to evaluate and monitor crack initiation and growth due to SSC, if present, in high strength low-alloy steel bolts used in NSSS component support.

In LRA Tables 3.5.2-1 through 3.5.2-14, the applicant does not address Group B1.1, high strength low-alloy bolts.

In LRA Section B2.1.4, the applicant indicated that high strength component support bolting is used in pinned connections associated with steam, reactor coolant pumps and reactor vessel supports and is loaded only in shear with no preload stress.

No preload stress indicates that PBNP NSSS components bolting were installed with snug-tight only, without using any torque or turn-of nuts method during installation. The staff requests the applicant to provide justification for the statement of no preload stress for NSSS components bolting. The applicant is requested to clarify if there are any Group B1.1, high strength low-alloy bolts, not used for pinned connection only.

Additionally, the applicants Bolting Integrity Program does not support the discussion in LRA Table 3.5.1, Item 3.5.1-33. The staff requests the applicant to identify the aging management for the Group B1.1, high strength low-alloy bolts.

(2) In LRA Tables 3.5.2-1 through 3.5.2-14, the applicant stated that concrete and grout components do not have any aging effect requiring management (AERM). The staff does not agree with this statement. The staff requests the applicant to provide the aging effects for these components.

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