ML052030025
| ML052030025 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 07/21/2005 |
| From: | Morgan J NRC/NRR/DRIP/RLEP |
| To: | Harden P Nuclear Management Co |
| morgan M NRR/NRC/DRIP/RLEP, 415-2232 | |
| References | |
| TAC MC6433 | |
| Download: ML052030025 (8) | |
Text
July 21, 2005 Paul A. Harden Site Vice President Nuclear Management Company, LLC 27780 Blue Star Memorial Highway Covert, MI 49043
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (RAI) FOR THE REVIEW OF THE PALISADES NUCLEAR PLANT, LICENSE RENEWAL APPLICATION (TAC NO. MC6433)
Dear Mr. Harden:
By letter dated March 22, 2005, Nuclear Management Company, LLC, (NMC or the applicant) submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 (10 CFR Part 54), to renew the operating license for Palisades Nuclear Plant (PNP), for review by the U.S. Nuclear Regulatory Commission (NRC). Subsequently, on May 5, 2005, the NRC received a supplement to the license renewal application. The NRC staff is reviewing the information contained in the license renewal application (LRA) and supplement and has identified, in the enclosure, areas where additional information is needed to complete the review.
These questions were discussed with your staff, Mr. Robert Vincent, and a mutually agreeable date for this response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-2232 or e-mail MJM2@nrc.gov.
Sincerely,
/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 No.: 50-255
Enclosure:
As stated cc w/encl: See next page
ML052030025 Document Name: E:\\Filenet\\ML052030025.wpd OFFICE PM:RLEP LA:RLEP SC:RLEP NAME MMorgan MJenkins SLee DATE 07/20/05 07/20/05 07/21/05
Palisades Nuclear Plant cc:
Robert A. Fenech, Senior Vice President Nuclear, Fossil, and Hydro Operations Consumers Energy Company 1945 Parnall Rd.
Jackson, MI 49201 Arunas T. Udrys, Esquire Consumers Energy Company 1 Energy Plaza Jackson, MI 49201 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Supervisor Covert Township P.O. Box 35 Covert, MI 49043 Office of the Governor P.O. Box 30013 Lansing, MI 48909 U.S. Nuclear Regulatory Commission Resident Inspectors Office Palisades Plant 27782 Blue Star Memorial Highway Covert, MI 49043 Michigan Department of Environmental Quality Waste and Hazardous Materials Division Hazardous Waste and Radiological Protection Section Nuclear Facilities Unit Constitution Hall, Lower-Level North 525 West Allegan Street P.O. Box 30241 Lansing, MI 48909-7741 Michigan Department of Attorney General Special Litigation Division 525 West Ottawa St.
Sixth Floor, G. Mennen Williams Building Lansing, MI 48913 Manager, Regulatory Affairs Nuclear Management Company, LLC 27780 Blue Star Memorial Highway Covert, MI 49043 Director of Nuclear Assets Consumers Energy Company Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043 John Paul Cowan Executive Vice President & Chief Nuclear Officer Nuclear Management Company, LLC 700 First Street Hudson, WI 54016 Jonathan Rogoff, Esquire Vice President, Counsel & Secretary 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 Robert A. Vincent Licensing Lead - License Renewal Project Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043
Palisades Nuclear Plant cc:
Darrel G. Turner License Renewal Project Manager Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043 Mr. James Ross Nuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708 Mr. Douglas F. Johnson Director, Plant Life Cycle Issues Nuclear Management Company, LLC 700 First Street Hudson, WI 54016 Secretary Federal Energy Regulatory Commission 888 First Street, NE, Room 1A Washington, DC 20426 Chairperson Michigan Public Service Commission PO Box 30221 Lansing, MI 48909-7721
DISTRIBUTION: Letter to P. Harden, Re: RAI for Palisades LRA, Dated: July 21, 2005 ADAMS Accession No.: ML052030025 HARD COPY RLEP RF M. Morgan (PM)
E-MAIL:
RidsNrrDrip RidsNrrDe G. Bagchi K. Manoly W. Bateman J. Calvo R. Jenkins 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. Ellegood, RIII M. Garza, RIII A. Stone, RIII L. Raghavan T. Mensah OPA
Enclosure PALISADES NUCLEAR PLANT LICENSE RENEWAL APPLICATION (LRA)
REQUEST FOR ADDITIONAL INFORMATION (RAI)
RAI 4.3-1 Provide an explanation for the difference in plant heat-ups (134) and plant cooldowns (119) in Table 4.3.1-1.
RAI 4.3-2 In Table 4.3.1-1, provide the basis for not counting the safety valve operation cycles and the assumption that the design value of 200 cycles will never be approached.
RAI 4.3-3 In Section 4.3.2, does the CUF value of 0.4516 represent the highest 60-year CUF for all structures and/or components in the reactor vessel, such as those listed in Table IV, A2 Reactor Vessel (PWR) of NUREG-1801, Volume 2, where cumulative fatigue damage/fatigue is the aging effect/mechanism, and which require further evaluation as TLAAs for the period of extended operation? If not, provide justification for not considering these components.
RAI 4.3-4 In Sections 4.3.2 and 4.3.3, provide the basis for the statement: The number of design basis transient events is not expected to approach the number assumed by the analysis during the extended licensed operating period.
RAI 4.3-5 Provide the highest 60-year CUFs and disposition for all structures and/or components in the reactor vessel internals, such as those listed in Table IV B3 Reactor Vessel Internals (PWR) -
Combustion Engineering, Items B3.2-f, B3.4-d and B3.5-g, of NUREG-1801, Volume 2, where cumulative fatigue damage/fatigue is the aging effect/mechanism, and which require further evaluation as TLAAs for the period of extended operation.
RAI 4.3-6 In Section 4.3.5, does the CUF value of 0.9158 represent the highest 60-year CUF for all structures and/or components in the steam generators, such as those listed in Table IV, D1 Steam Generators (Recirculating), Items D1.1 and D1.2 of NUREG-1801, Volume 2, where cumulative fatigue damage/fatigue is the aging effect/mechanism, and which require further evaluation as TLAAs for the period of extended operation? If not, provide justification for not considering these components.
RAI 4.3-7 In Section 4.3.5, provide the date of Plant Heat-up Number 106 and the date when Plant Heat-up Number 306 is projected to occur.
RAI 4.3-8 In Section 4.3.6, does the CUF value of 0.7572 represent the highest 60-year CUF for all structures and/or components in the pressurizer, such as those listed in Table IV, C2.5 Pressurizers of NUREG-1801, Volume 2, where cumulative fatigue damage/fatigue is the aging effect/mechanism, and which require further evaluation as TLAAs for the period of extended operation? If not, provide justification for not considering these components.
Enclosure RAI 4.3-9 Provide the highest 60-year CUFs and disposition for all structures and/or components in the reactor coolant system and connected lines, such as those listed in Table IV C2 Reactor Coolant System and Connected Lines (PWR), Items C2.2-a, C2.2-b and C2.2-c, Connected Systems Piping and Fittings, of NUREG-1801, Volume 2, where cumulative fatigue damage/fatigue is the aging effect/mechanism, and which require further evaluation as TLAAs for the period of extended operation.
RAI 4.3-10 In Section 4.3.8, provide the basis for the statement: The number of each of the design basis events that affect the hot and cold legs is not expected to approach its design basis limit during the extended licensed operating period...
RAI 4.3-11 In Section 4.3.9, provide clarification indicating whether Palisades has operated with continuous pressurizer spray operation since the start of plant operation. If not, indicate when continuous pressurizer spray operation was implemented. Indicate whether the CUFs for the surge line elbow, the Hot leg and Pressurizer Surge nozzles include cycling due to intermittent pressurizer spray operation.
RAI 4.3-12 In Section 4.3.9, provide the basis for the statement: The number of transient events which might be expected to initiate these thermal stratification events will not exceed their design basis limits for the extended licensed operating period.
RAI 4.3-13 In Section 4.3.10, provide the basis for the 60-year projected CUF of 0.517 for the pressurizer spray nozzle, when the first 20-year CUF is estimated as 0.353.
RAI 4.3-14 In Section 4.3.10, provide the basis for the statement: The projected number of cycles of the design basis events does not exceed the design basis limit during the extended licensed operating period.
RAI 4.3-15 Section 4.3.14 indicates that Palisades has no shutdown cooling line inlet transition, and that the safety injection and shutdown cooling functions share a common nozzle. As an alternate location to the shutdown cooling line inlet transition, provide the highest CUF at this location which includes the effect of the reactor coolant system environment, or select an alternative high CUF location equivalent to the shutdown cooling line inlet transition.