ML050060357
| ML050060357 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  (DPR-024) |
| Issue date: | 12/20/2004 |
| From: | Morgan M NRC/NRR/DRIP/RLEP |
| To: | Division of Regulatory Improvement Programs |
| Morgan M, NRR/DRIP/RLEP, 415-2232 | |
| References | |
| Download: ML050060357 (8) | |
Text
December 20, 2004 LICENSEE:
Nuclear Management Company, LLC FACILITY:
Point Beach Nuclear Plant, Units 1 and 2
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE HELD ON DECEMBER 17, 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 December 17, 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
ML050060357 DOCUMENT NAME: E:\\Filenet\\ML050060357.wpd OFFICE PM:RLEP SC:RLEP NAME MMorgan SLee DATE 12/22/04 12/22/04
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
DISTRIBUTION: Note to Licensee: Nuclear Management Co., LLC, Re: Point Beach Nuclear Plant, Units 1 and 2, Dated: December 20, 2004 Adams accession no.: ML050060357 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 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 DECEMBER 17, 2004 Participants Affiliations B. Fromm Nuclear Management Company, LLC (NMC)
J. Knorr NMC J. Thorgersen NMC T. Mielke NMC J. Rajan Nuclear Regulatory Commission (NRC)
M. Morgan NRC V. Rodriguez NRC 1
DRAFT REQUESTS FOR ADDITIONAL INFORMATION (D-RAI)
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION December 17, 2004 The U.S. Nuclear Regulatory Commission staff (the staff) and representatives of Nuclear Management Company, LLC (NMC) held a telephone conference call on December 17, 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.
3.3 Aging Management of Auxiliary Systems D-RAI 3.3-1 In LRA Tables 3.3.2-3, 3.3.2-7, and 3.3.2-9, heat exchangers and heater/coolers 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 the external environment and associated aging effects are not identified for these components. The applicant is also requested to address the similar question for the heat exchangers and heater/coolers in Tables 3.3.2-2, 3.3.2-3, 3.3.2-4, 3.3.2-5, 3.3.2-7, and 3.3.2-9 which have a 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.
D-RAI 3.3-2 LRA Table 3.3.2-7 identifies no aging effects for neoprene expansion joints with an internal environment of air and wetted gas less than 140EF. Also, LRA Table 3.3.2-13 identifies the aging effects change in material properties and cracking for neoprene expansion joints with an internal environment of indoor with no air condition but does not identify an aging management program for these aging effects. For similar neoprene components in a warm, moist environments, the GALL report identifies the aging effects hardening and loss of strength and recommends a plant specific AMP to manage these aging effects. The applicant is requested to provide justification why no aging effects were identified for the internals of the expansion joints in Table 3.3.2-7 and why no aging management program is identified to manage the aging effects for the expansion joints in Table 3.3.2-13.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-RAI 3.3-3 LRA Table 3.3.2-14 identifies the loss of material as an aging effect for carbon steel piping and fittings, and valve bodies in a raw water drainage environment. The applicant identifies the One-Time Inspection Program, LRA Section B2.1.13, to manage this aging effect. NUREG-2 1801, XI.M32 recommends one-time inspections as an appropriate aging management program where either an aging effect is not expected to occur but there is insufficient data to completely rule it out, or an aging effect is expected to progress very slowly. In cases where an aging effect is likely to occur, NUREG-1801 recommends periodic inspections. The staff does not consider a one-time inspection appropriate to manage the loss of material for carbon steel components in a raw water environment. The applicant is requested to justify use of a one-time inspection program to manage the loss of material for carbon steel components in a raw water environment.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-RAI 3.3-4 LRA Table 3.3.2-7 identifies no aging effects for carbon and low alloy steel tanks in a concrete environment. Staff notes that concrete has a high pH which is a natural inhibitor for steel; however, concrete contaminated with chlorides or concrete in contact with acidic water is subject to loss of material due to general, pitting, and crevice corrosion. The applicant is requested to describe the basis for concluding that no aging effects occur in this environment.
Also state the specific tanks, the location of the tanks including the external environment, describe how the concrete interfaces with the tanks, and discuss if chlorides or acidic water can be present in this environment.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-RAI 3.3-5 LRA Tables 3.3.2-7 and 3.3.2-9 identify the Periodic Surveillance and Preventive Maintenance (PSPM) program to manage the loss of heat transfer due to fouling for heat exchangers in oil, fuel oil, outdoor, and wetted air and gas environments. The monitoring and trending element in the applicants PSPM states that inspections, examination, testing, and component replacement activities are performed on a specified frequency based on operating experience or other requirements. The applicant stated that the results of these surveillance and preventive maintenance activities are documented, and subject to review and approval. NUREG-1800, Section A.1.2.3.5 recommends that monitoring and trending activities be described, and they should provide predictability of the extent of degradation and thus effect timely corrective actions. Plant specific and/or industry operating experience may be considered in evaluating the appropriateness of the technique and frequency. The applicant is requested to describe the inspection technique and frequency. The inspection frequency should be justified by plant operating experience and should be adequate to detect the aging effects such that the intended function will be maintained during the period of extended operation.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
3 D-RAI 3.3-6 Loss of preload is an aging effect for closure bolting in high temperature or high pressure systems. NUREG-1801, XI.M18, Bolting Integrity program provides aging management inspections for this aging effect. LRA section 3.3 for the auxiliary systems does not identify loss of preload as an aging effect for closure bolting. The applicant is requested to discuss why the loss of preload was not identified as an aging effects for auxiliary systems closure bolting and the inspections in NUREG-1801, XI.M18 were not credited for managing this aging effect. This RAI is also applicable for closure bolting in the ESF and SPCS.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI 4.3.13 Crane Load Cycle Limit D-RAI 4.3.13-1 LRA Section 4.3.13, Crane Load Cycle Limit, states that the load limit of the containment polar, auxiliary building, and turbine hall cranes are designed in accordance with CMAA-70 Class A service for 20,000 to 200,000 load cycles, and based on conservative usage assumptions, the cranes are expected to make 50,000 partial load lifts and less than 5.000 at or near rated load lift for the period of extended operation. The applicant is requested to provide the basis for concluding that 50,000 partial load lifts and less than 5,000 at or near rated load lift are in accordance with design of 20,000 to 200,000 load cycles.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.