ML050260699
| ML050260699 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 01/19/2005 |
| From: | Veronica Rodriguez NRC/NRR/DRIP/RLEP |
| To: | |
| Rodriguez VM, RLEP/DRIP/NRR, 415-3703 | |
| References | |
| Download: ML050260699 (6) | |
Text
January 19, 2005 LICENSEE: Nuclear Management Company, LLC FACILITY: Point Beach Nuclear Plant, Units 1 and 2
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE HELD ON JANUARY 10, 2005, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND NUCLEAR MANAGEMENT COMPANY, LLC, CONCERNING 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 January 10, 2005, to discuss and clarify the staffs requests for additional information (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 RAIs. provides a listing of the meeting participants. Enclosure 2 contains a listing of the RAIs discussed with the applicant, including a brief description on the status of the items. contains draft responses provided by the applicant.
The applicant had an opportunity to comment on this summary.
/RA/
Verónica M. Rodríguez, 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\ML050260699.wpd OFFICE PM:RLEP SC:RLEP NAME VRodríguez SLee DATE 01 / 14 / 05 01 / 19 / 05 Point Beach Nuclear Plant, Units 1 and 2 cc:
Jonathan Rogoff, Esq. Mr. Jeffrey Kitsembel Vice President, Counsel & Secretary Electric Division Nuclear Management Company, LLC Public Service Commission of Wisconsin 700 First Street P.O. Box 7854 Hudson, WI 54016 Madison, WI 53707-7854 Mr. Frederick D. Kuester David Weaver President and Chief Executive Officer Nuclear Asset Manager We Generation Wisconsin Electric Power Company 231 West Michigan Street 231 West Michigan Street Milwaukee, WI 53201 Milwaukee, WI 53201 James Connolly John Paul Cowan Manager, Regulatory Affairs Executive Vice President & Chief Nuclear Point Beach Nuclear Plant Officer Nuclear Management Company, LLC Nuclear Management Company, LLC 6610 Nuclear Road 700 First Street Two Rivers, WI 54241 Hudson, WI 54016 Mr. Ken Duveneck Douglas E. Cooper Town Chairman Senior Vice President - Group Operations Town of Two Creeks Palisades Nuclear Plant 13017 State Highway 42 Nuclear Management Company, LLC Mishicot, WI 54228 27780 Blue Star Memorial Highway Covert, MI 49043 Chairman Public Service Commission Fred Emerson of Wisconsin Nuclear Energy Institute P.O. Box 7854 1776 I Street, NW., Suite 400 Madison, WI 53707-7854 Washington, DC 20006-3708 Regional Administrator, Region III Roger A. Newton U.S. Nuclear Regulatory Commission 3623 Nagawicka Shores Drive 801 Warrenville Road Hartland, WI 53029 Lisle, IL 60532-4351 James E. Knorr Resident Inspector's Office License Renewal Project U.S. Nuclear Regulatory Commission Nuclear Management Company, LLC 6612 Nuclear Road 6610 Nuclear Road Two Rivers, WI 54241 Point Beach Nuclear Plant Two Rivers, WI 54241
DISTRIBUTION: Note to Licensee: Nuclear Management Company, LLC, Re: Summary of telephone conference held on January 10, 2005, Dated: January 19, 2005 Adams Accession No.: ML050260699 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 M. Itzkowitz (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 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 JANUARY 10, 2005 Participants Affiliations J. Knorr Nuclear Management Company, LLC M. Morgan Nuclear Regulatory Commission G. Suber Nuclear Regulatory Commission V. Rodriguez Nuclear Regulatory Commission Enclosure 1
DRAFT REQUESTS FOR ADDITIONAL INFORMATION (RAI)
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION January 10, 2005 The U.S. Nuclear Regulatory Commission staff (the staff) and representatives of Nuclear Management Company, LLC (NMC) held a telephone conference call on January 10, 2005, to discuss and clarify the staffs requests for additional information (RAIs) concerning the Point Beach Nuclear Plant, Units 1 and 2, license renewal application (LRA). The following RAIs were discussed during the telephone conference call.
Section 2.3.4 Steam and Power Conversion Systems 2.3.4.2 Feedwater and Condensate System Request for Additional Information (RAI)
RAI 2.3.4.2-4 In a letter dated November 16, 2004, the Nuclear Regulatory Commission'(NRC) requested additional information regarding the Auxiliary Systems (LRA Section 2.3.3) and Steam and other Balance of Plant (BOP) Systems in LRA Sections 2.3.3 and 2.3.4 respectively. PBNP response to this request was submitted to the NRC in Nuclear Management Company, LLC letter dated December 22, 2004. The NRC review of the PBNP response to RAI 2.3.4.2-1 identified two follow-up questions regarding the scoping for the small bore branch piping from the NSR portion of the 16" main feed water header (FW) between the feed regulating valve and the downstream steam generator FW inlet check valve:
- 1. Recognizing the NRC would not require a formal HELB evaluation be preformed on piping 1-inch and less, did PBNP perform any evaluation (i.e., walkdown, etc.) to confirm that a break in the branch piping would not impact any safety related equipment in the immediate vicinity of the possible break location?
- 2. Please discuss flooding associated with a failure in the branch piping and its impact on safety related equipment.
Discussion: The applicant clarified their draft response. The applicant will provide their formal response in writing.
Enclosure 2
ENCLOSURE RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION (LRA)
The following information is provided in response to the Nuclear Regulatory Commission (NRC) staff's request for additional information (RAI) regarding the Point Beach Nuclear Plant (PBNP)
The NRC staff's question is restated below, with the Nuclear Management Company (NMC) response following.
Section 2.3.4 Steam and Power Conversion Systems 2.3.4.2 Feedwater and Condensate System Request for Additional Information (RAI)
RAI 2.3.4.2-4 In a letter dated November 16, 2004, the Nuclear Regulatory Commission'(NRC) requested additional information regarding the Auxiliary Systems (LRA Section 2.3.3) and Steam and other Balance of Plant (BOP) Systems in LRA Sections 2.3.3 and 2.3.4 respectively. PBNP response to this request was submitted to the NRC in Nuclear Management Company, LLC letter dated December 22, 2004. The NRC review of the PBNP response to RAI 2.3.4.2-1 identified two follow-up questions regarding the scoping for the small bore branch piping from the NSR portion of the 16" main feed water header (FW) between the feed regulating valve and the downstream steam generator FW inlet check valve:
- 1. Recognizing the NRC would not require a formal HELB evaluation be preformed on piping 1-inch and less, did PBNP perform any evaluation (i.e., walkdown, etc.) to confirm that a break in the branch piping would not impact any safety related equipment in the immediate vicinity of the possible break location?
- 2. Please discuss flooding associated with a failure in the branch piping and its impact on safety related equipment.
NMC Response:
- 1) The section of main feedwater piping in question, was included in scope to protect the safety-related (but non-EQ) feedwater flow transmitters (1/2FT-466, -467, -476, -477).
Walkdowns were originally performed to verify that no high energy piping (including branch piping 1 and under) was in proximity to the SR transmitters where pipe whip or jet impingement could be a hazard. Additionally, the transmitters are in large open areas where the energy input from a failure of a small bore line off of this header would not be able to create a harsh environment for these transmitters.
Enclosure 3
- 2) The SR feedwater flow transmitters are located on the 26 elevation for U2 and the 39 elevation for U1, and mounted about 4 feet off of the floor. Any leakage from the main feedwater header branch connections at these elevations would cascade to lower elevations, and would not create any potential for flooding to impact the function of these transmitters nor any other safety-related equipment.
Enclosure 3