ML042320653
| ML042320653 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 08/19/2004 |
| From: | Morgan M NRC/NRR/DRIP/RLEP |
| To: | Nuclear Management Co |
| Morgan M, NRR/NRC/DRIP/RLEP, 415-2232 | |
| References | |
| Download: ML042320653 (7) | |
Text
August 19, 2004 LICENSEE:
Nuclear Management Company, LLC FACILITY:
Point Beach Nuclear Plant, Units 1 and 2
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE HELD ON JULY 15, 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 call on July 15, 2004, to discuss and clarify the staffs draft requests for additional information (D-RAIs) concerning the Point Beach Nuclear Plant License Renewal Application. The telephone conference was useful in clarifying the intent of the staffs D-RAIs. provides a list of the telephone conference 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 has had an opportunity to comment on this summary.
/RA/ Samson Lee for 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
ML042320653 DOCUMENT NAME: C:\\ORPCheckout\\FileNET\\ML042320653.wpd OFFICE PM:RLEP SE:RLEP LA:RLEP SC:RLEP NAME MMmorgan (SSLee for)
BMoy (SSLee for)
YEdmonds (Letter only)
SLee DATE 8/19/04 8/19/04 8/ /04 8/19/04
DISTRIBUTION: Dated: August 19, 2004 Accession No.: ML042320653 HARD COPY RLEP RF M. Morgan (PM)
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 J. Strasma, RIII A. Vegel, RIII H. Chernoff W. Ruland C. Marco L. Raghavan T. Mensah OPA
Point Beach Nuclear Plant, Units 1 and 2 cc:
Jonathan Rogoff, Esquire 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 Inspectors Office U.S. Nuclear Regulatory Commission 6612 Nuclear Road Two Rivers, WI 54241 Roger A. Newton 3623 Nagawicka Shores Drive Hartland, WI 53029 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 Dennis L. Koehl Site Vice President Point Beach Nuclear Plant Nuclear Management Company, LLC 6610 Nuclear Road Two Rivers, WI 54241 James E. Knorr License Renewal Project Nuclear Management Company, LLC 6610 Nuclear Road Point Beach Nuclear Plant Two Rivers, WI 54241 LIST OF PARTICIPANTS FOR TELEPHONE CONFERENCE TO DISCUSS THE POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION JULY 15, 2004 Participants Affiliation Michael J. Morgan U.S. Nuclear Regulatory Commission (NRC)
Arnold Lee NRC Brian Moy NRC Alvin Chiu NRC Douglas Johnson Nuclear Management Company, LLC (NMC)
Jim E. Knorr NMC Todd D. Mielke NMC DRAFT REQUESTS FOR ADDITIONAL INFORMATION (D-RAI)
POINT BEACH NUCLEAR PLANT, UNITS 1 & 2 LICENSE RENEWAL APPLICATION JULY 15, 2004 The U.S. Nuclear Regulatory Commission staff (the staff) and representatives of Nuclear Management Company, LLC (NMC) held a telephone conference call on July 15, 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 applications (LRA). The following D-RAIs were discussed during the telephone conference call.
Section 3.2 Engineered Safety Features RAI 3.2-1 In LRA Tables 3.2.2-1, 3.2.2-2, and 3.2.2-3, stainless steel heat exchangers, with heat transfer as the intended function, are identified with only internal environments and associated aging effects. The external environment is listed as N/A. The applicant is requested to explain why for these components the external environment and associated aging effects need not be identified. The applicant is also requested to address the similar question for the stainless steel heat exchangers in Tables 3.2.2-1 and 3.2.2-2, which have pressure boundary as their intended function.
Discussion:
The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
RAI 3.2-2 In LRA Tables 3.2.2-1 and 3.2.2-2, carbon/low alloy steel tank components are identified with only external environments and the associated aging effects. The internal environment is listed as N/A. On the other hand, stainless steel tank components are identified with internal environments with the associated aging effects. The applicant is requested to explain the material construction of the tank, and the environments to which it is exposed, to support the information provided in the tables.
Discussion:
The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
Section 3.4 Steam and Power Conversion System RAI 3.4-1 In LRA Table 3.4.2-3, stainless steel heat exchangers, with either heat transfer or pressure boundary as the intended function, are identified with only internal environments and associated aging effects. The external environment is listed as N/A. The applicant is requested to explain why for these components the external environment and associated aging effects need not be identified.
Discussion:
The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
RAI 3.4-2 In the first quarter of 2003, Point Beach Nuclear Plant entered the Multiple/Repetitive Degraded Cornerstone Column (Column IV) of the Action Matrix of NRC Inspection Manual Chapter 0305, Operating Reactor Assessment Program, as a result of a high significance (Red) inspection finding involving the potential for a common mode failure of the auxiliary feedwater system (AFW) following a loss of the instrument air system. A second Red inspection finding (Yellow for Unit 1 and Red for Unit 2) was subsequently identified which involved the potential common mode failure of the AFW pumps due to plugging of the recirculation line pressure reduction orifices. In view of the aforementioned inspection findings and the subsequent corrective actions for the two AFW issues, the applicant is requested to address the following questions in the context of the license renewal application:
(a)
Clarify whether the instrument air system and the recirculation line pressure reduction orifices are in scope for the LRA evaluation, and that appropriate AMPs have been identified to manage the components.
(b)
For aging management evaluation as summarized in LRA Table 3.4.2-3 for the auxiliary feedwater system, discuss any impact on the scoping of mechanical components in the auxiliary feedwater system, and the AMR performed for the affected components, as a result of the recent physical modifications made to resolve the auxiliary feedwater pump room Appendix R issues.
Discussion:
The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.