ML043380325
| ML043380325 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 12/03/2004 |
| From: | Michelle Honcharik NRC/NRR/DLPM/LPD4 |
| To: | Edington R Nebraska Public Power District (NPPD) |
| Honcharik M, NRR/DLPM, 301-415-1774 | |
| References | |
| TAC MC4954 | |
| Download: ML043380325 (4) | |
Text
December 3, 2004 Mr. Randall K. Edington Vice President-Nuclear and CNO Nebraska Public Power District P. O. Box 98 Brownville, NE 68321
SUBJECT:
COOPER NUCLEAR STATION - REQUEST FOR ADDITIONAL INFORMATION ON RELIEF REQUEST RI-35, REPAIR OF REACTOR PRESSURE VESSEL CONTROL ROD DRIVE NOZZLE-TO-CAP WELD (TAC NO. MC4954)
Dear Mr. Edington:
By letter dated October 25, 2004, Nebraska Public Power District (NPPD) requested the NRC staff to approve a request for relief as an alternative to the existing ASME Boiler and Pressure Vessel Code,Section XI requirements for the repair and examination of Class 1 welds.
The NRC staff has reviewed the information provided in the submittal and determined that the additional information identified in the enclosure is required in order for the NRC staff to complete its review. As agreed upon with Dave VanDerKamp on December 2, 2004, NPPD will respond to the NRC staff's request for additional information within 30 days from the date of this letter.
Sincerely,
/RA/
Michelle C. Honcharik, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-298
Enclosure:
Request for Additional Information cc w/encl: See next page
December 3, 2004 Mr. Randall K. Edington Vice President-Nuclear and CNO Nebraska Public Power District P. O. Box 98 Brownville, NE 68321
SUBJECT:
COOPER NUCLEAR STATION - REQUEST FOR ADDITIONAL INFORMATION ON RELIEF REQUEST RI-35, REPAIR OF REACTOR PRESSURE VESSEL CONTROL ROD DRIVE NOZZLE-TO-CAP WELD (TAC NO. MC4954)
Dear Mr. Edington:
By letter dated October 25, 2004, Nebraska Public Power District (NPPD) requested the NRC staff to approve a request for relief as an alternative to the existing ASME Boiler and Pressure Vessel Code,Section XI requirements for the repair and examination of Class 1 welds.
The NRC staff has reviewed the information provided in the submittal and determined that the additional information identified in the enclosure is required in order for the NRC staff to complete its review. As agreed upon with Dave VanDerKamp on December 2, 2004, NPPD will respond to the NRC staff's request for additional information within 30 days from the date of this letter.
Sincerely,
/RA/
Michelle C. Honcharik, Project Manager, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-298
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
PUBLIC PDIV-1 r/f RidsNrrDlpmLpdiv (HBerkow)
RidsNrrDlpmLpdiv1 (MWebb)
RidsNrrPMMHoncharik RidsNrrLADJohnson RidsAcrsAcnwMailCenter RidsOgcRp RidsRgn4MailCenter (KKennedy)
RidsNrrDlpmDpr (BPham)
RidsNrrDeDpr (SWall)
GGeorgiev MHartzman TChan KManoly ACCESSION NO: ML043380325
- No substantive changes OFFICE PDIV-1/PM PDIV-1/LA EMEB-B/SC EMCB-B/SC PDIV-1/SC NAME MHoncharik DJohnson KManoly TChan MWebb DATE 12/3/04 12/2/04 11/23/2004*
11/18/2004*
12/3/04 OFFICIAL RECORD COPY
Cooper Nuclear Station cc:
Mr. William J. Fehrman President and Chief Executive Officer Nebraska Public Power District 1414 15th Street Columbus, NE 68601 Mr. Clay C. Warren Vice President of Strategic Programs Nebraska Public Power District 1414 15th Street Columbus, NE 68601 Mr. John R. McPhail, General Counsel Nebraska Public Power District P. O. Box 499 Columbus, NE 68602-0499 Mr. Paul V. Fleming Licensing Manager Nebraska Public Power District P.O. Box 98 Brownville, NE 68321 Mr. Michael J. Linder, Director Nebraska Department of Environmental Quality P. O. Box 98922 Lincoln, NE 68509-8922 Chairman Nemaha County Board of Commissioners Nemaha County Courthouse 1824 N Street Auburn, NE 68305 Ms. Cheryl K. Rogers, Program Manager Nebraska Health & Human Services System Division of Public Health Assurance Consumer Services Section 301 Centennial Mall, South P. O. Box 95007 Lincoln, NE 68509-5007 Mr. Ronald A. Kucera, Director of Intergovernmental Cooperation Department of Natural Resources P.O. Box 176 Jefferson City, MO 65102 Senior Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 218 Brownville, NE 68321 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 Jerry Uhlmann, Director State Emergency Management Agency P. O. Box 116 Jefferson City, MO 65101 Chief, Radiation and Asbestos Control Section Kansas Department of Health and Environment Bureau of Air and Radiation 1000 SW Jackson Suite 310 Topeka, KS 66612-1366 Mr. Daniel K. McGhee Bureau of Radiological Health Iowa Department of Public Health 401 SW 7th Street Suite D Des Moines, IA 50309 Mr. Scott Clardy, Director Section for Environmental Public Health P.O. Box 570 Jefferson City, MO 65102-0570 Jerry C. Roberts, Director of Nuclear Safety Assurance Nebraska Public Power District P.O. Box 98 Brownville, NE 68321
REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST RI-35, REPAIR OF REACTOR PRESSURE VESSEL CONTROL ROD DRIVE NOZZLE-TO-CAP WELD NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION DOCKET NO. 50-298 1.
The October 25, 2004, submittal states that the welder and welding procedures will be qualified to use the shielded metal arc welding process. However, the deposition of the Alloy 52 requires the use of the gas tungsten arc welding (GTAW) process. Is the licensee planning to use welder and welding procedures qualified to use the GTAW process? If so, explain the difference.
2.
Provide a diagram/sketch showing the control rod drive return nozzle-to-cap weld and the proposed weld overlay configuration.
3.
Section (g)(2) of Code Case N-504-2 specifies that the evaluation of the repaired weld consider residual stresses produced by the weld overlay with the other applied loads on the system. The effects of water backing on the repair weld shall be considered.
Section (g)(3) of Code Case N-504-2 specifies that the welds and components meet the applicable stress limits of the construction code.
a.
What is the construction code that was used to satisfy the evaluation requirements in Sections (g)(2) and (g)(3) of the Code Case?
b.
Provide a description of the methodology used to determine residual stresses and shrinkage effects.
c.
Provide a list and a description of the calculations used for determining the length and thickness of the weld overlay.
d.
Provide a table comparing the current licensing basis primary and primary-plus-secondary stresses, and the primary and primary-plus-secondary stresses at the location of the highest stress regions resulting from the installation of the weld overlay. Show that the component and the weld meet the applicable stress limits of the Cooper construction code, as required by the Code Case.
e.
Provide the largest ASME Section III fatigue cumulative usage factor and its location in the region with and without the weld overlay, considering all applicable thermal and mechanical transients.