ML041600012
| ML041600012 | |
| Person / Time | |
|---|---|
| Site: | Monticello, Duane Arnold  |
| Issue date: | 06/15/2004 |
| From: | David Beaulieu NRC/NRR/DLPM/LPD3 |
| To: | Weinkam E Nuclear Management Co |
| Beaulieu, David, NRR/DLPM, 415-3243 | |
| References | |
| TAC MC2374, TAC MC2375 | |
| Download: ML041600012 (5) | |
Text
June 15, 2004 Mr. Edward J. Weinkam Director of Regulatory Services Nuclear Management Company, LLC 700 First Street Hudson, WI 54016
SUBJECT:
DUANE ARNOLD ENERGY CENTER AND MONTICELLO NUCLEAR GENERATING PLANT RE: REQUEST FOR ADDITIONAL INFORMATION RELATED TO REQUEST FOR AUTHORIZATION TO UTILIZE CODE CASE N-613-1 (TAC NOS. MC2374 AND MC2375)
Dear Mr. Weinkam:
The Nuclear Management Company, LLCs letter of February 27, 2004, requested U.S. Nuclear Regulatory Commission (NRC) approval for the Duane Arnold Energy Center and Monticello Nuclear Generating Plant to use the alternative examination volume requirements of Code Case N-613-11 in lieu of certain American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, requirements. The NRC staff is reviewing your request and finds that additional information is needed as shown in the enclosed request for additional information (RAI).
I discussed the enclosed RAI with Ms. Clara Rushworth of your organization on June 2, 2004, and she agreed to respond within 30 days of receipt of the RAI. Please contact me at (301) 415-3243 if you have questions.
Sincerely,
/RA/
David P. Beaulieu, Project Manager, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-331 and 50-263
Enclosure:
Request for Additional Information cc w/encl: See next page
ML041600012 OFFICE PDIII-1/PM PDIII-1/PM PDIII-1/LA PDIII-1/SC NAME DBeaulieu LPadovan THarris LRaghavan DATE 06/10/04 06/10/04 06/10/04 06/10/04
Duane Arnold Energy Center cc:
Mr. John Paul Cowan Executive Vice President &
Chief Nuclear Officer Nuclear Management Company, LLC 700 First Street Hudson, MI 54016 John Bjorseth Plant Manager Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324 Steven R. Catron Manager, Regulatory Affairs Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324 U.S. Nuclear Regulatory Commission Resident Inspectors Office Rural Route #1 Palo, IA 52324 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 2443 Warrenville Road, Suite 210 Lisle, IL 60532-4352 Jonathan Rogoff Vice President, Counsel & Secretary Nuclear Management Company, LLC 700 First Street Hudson, WI 54016 Bruce Lacy Nuclear Asset Manager Alliant Energy/Interstate Power and Light Company 3277 DAEC Road Palo, IA 52324 Daniel McGhee Utilities Division Iowa Department of Commerce Lucas Office Buildings, 5th floor Des Moines, IA 50319 Chairman, Linn County Board of Supervisors 930 1st Street SW Cedar Rapids, IA 52404 Craig G. Anderson Senior Vice President, Group Operations 700 First Street Hudson, WI 54016 Mark A. Peifer Site Vice President Duane Arnold Energy Center Nuclear Management Company, LLC 3277 DAEC Road Palo, IA 52324-0351
Monticello Nuclear Generating Plant cc:
Jonathan Rogoff, Esquire Vice President, Counsel & Secretary Nuclear Management Company, LLC 700 First Street Hudson, WI 54016 U.S. Nuclear Regulatory Commission Resident Inspectors Office 2807 W. County Road 75 Monticello, MN 55362 Manager, Regulatory Affairs Monticello Nuclear Generating Plant Nuclear Management Company, LLC 2807 West County Road 75 Monticello, MN 55362-9637 Robert Nelson, President Minnesota Environmental Control Citizens Association (MECCA) 1051 South McKnight Road St. Paul, MN 55119 Commissioner Minnesota Pollution Control Agency 520 Lafayette Road St. Paul, MN 55155-4194 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 2443 Warrenville Road, Suite 210 Lisle, IL 60532-4352 Commissioner Minnesota Department of Health 717 Delaware Street, S. E.
Minneapolis, MN 55440 Douglas M. Gruber, Auditor/Treasurer Wright County Government Center 10 NW Second Street Buffalo, MN 55313 Commissioner Minnesota Department of Commerce 121 Seventh Place East Suite 200 St. Paul, MN 55101-2145 Manager - Environmental Protection Division Minnesota Attorney Generals Office 445 Minnesota St., Suite 900 St. Paul, MN 55101-2127 John Paul Cowan Executive Vice President & Chief Nuclear Officer Nuclear Management Company, LLC 700 First Street Hudson, WI 54016 Nuclear Asset Manager Xcel Energy, Inc.
414 Nicollet Mall, R.S. 8 Minneapolis, MN 55401 Mr. Thomas J. Palmisano Site Vice President Monticello Nuclear Generating Plant Nuclear Management Company, LLC 2807 West County Road 75 Monticello, MN 55362-9637
Enclosure REQUEST FOR ADDITIONAL INFORMATION REQUEST FOR AUTHORIZATION TO UTILIZE CODE CASE N-613-1 NUCLEAR MANAGEMENT COMPANY, LLC DUANE ARNOLD ENERGY CENTER MONTICELLO NUCLEAR GENERATING PLANT DOCKET NOS. 50-331 AND 50-263 The Nuclear Regulatory Commission staff is reviewing the Nuclear Management Companys (NMCs) request for authorization to utilize Code Case N-613-1 and has determined that the following additional information is needed in order to complete the review:
1.
In Item 5,Proposed Alternatives and Basis for Use, of NMCs letter of February 27, 2004, states that the required examination volume for the RPV [reactor pressure vessel] nozzle-to-vessel welds extends far beyond the weld into the base metal, and is unnecessarily large. This proposed alternative would redefine the examination volume boundary to one-half inch of base metal on each side of the widest portion of the weld.
a.
Please provide a supplemental sketch showing the specific configuration nozzle-to-vessel weld and revised examination volume (including dimensions).
b.
Identify the type of ultrasonic technique (manual or automated), nominal pipe diameters, and weldment material (ferritic, austenitic, Inconel) that NMC is proposing to inspect.
c.
It is not clear how NMC personnel will be able to locate the widest portion of the nozzle-to-vessel weld precisely. It is unclear how repaired areas extending beyond the ideal weld cross-sectional area are identified and how these areas will be examined. If personnel are to identify the widest sections of the nozzle-to-vessel welds, please specify what positive means of examination will be used to identify the weld extremities. Will the extremities be identified on both the inside and outside diameters of the nozzle to ensure complete coverage of the welds?
2.
In Item 5 of NMCs letter of February 27, 2004, it also states that the creation of flaws during plant service in the volume excluded from the proposed reduced examination is unlikely because of the low stress in the base metal away from the weld. Please provide your technical basis and analyses in order to support this statement.