ML053200276
| ML053200276 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 11/21/2005 |
| From: | Brian Benney Plant Licensing Branch III-2 |
| To: | Eddington R Nebraska Public Power District (NPPD) |
| Benney B, NRR/DLPM, 415-3764 | |
| References | |
| TAC MC8512 | |
| Download: ML053200276 (5) | |
Text
November 21, 2005 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 RE: RELIEF REQUESTS RI-21, REVISION 2, AND RI-36 (TAC NO. MC8512)
Dear Mr. Edington:
Nebraska Public Power District (the licensee) requested the Nuclear Regulatory Commission (NRC) staffs approval for relief from certain inservice inspection requirements in Part 50 of Title 10 of the Code of Federal Regulations for the Cooper Nuclear Station.
The NRC staff has reviewed the information provided in the September 28, 2005, submittal and has determined that the additional information identified in this enclosure is required in order for the NRC staff to complete its review. The licensee requested NRC staff approval of the subject relief request by February 28, 2006. To meet that target date, the NRC staff requests that the licensee provide its response no later than December 9, 2005.
Sincerely,
/RA Brian Benney, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-298
Enclosure:
Request for Additional Information cc w/encl: See next page
November 21, 2005 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 RE: RELIEF REQUESTS RI-21, REVISION 2, AND RI-36 (TAC NO. MC8512)
Dear Mr. Edington:
Nebraska Public Power District (the licensee) requested the Nuclear Regulatory Commission (NRC) staffs approval for relief from certain inservice inspection requirements in Part 50 of Title 10 of the Code of Federal Regulations for the Cooper Nuclear Station.
The NRC staff has reviewed the information provided in the September 28, 2005, submittal and has determined that the additional information identified in this enclosure is required in order for the NRC staff to complete its review. The licensee requested NRC staff approval of the subject relief request by February 28, 2006. To meet that target date, the NRC staff requests that the licensee provide its response no later than December 9, 2005.
Sincerely,
/RA Brian Benney, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-298
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
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RidsAcrsAcnwMailCenter ADAMS ACCESSION NO: ML053200276 NRR-106 OFFICE LPLIV/PM LPLIV/LA CPNB/BC LPLIV/BC NAME BBenney LFeizollahi TChan DTerao DATE 11/18/05 11/18/05 11/18/05 11/21/05 OFFICIAL RECORD COPY
REQUEST FOR ADDITIONAL INFORMATION ISSUES RELATED TO INSERVICE INSPECTION RELIEF REQUESTS RI-21, REVISION 2, AND RI-36 COOPER NUCLEAR STATION DOCKET NO. 50-298 By letter dated September 28, 2005, Nebraska Public Power District requested relief from certain inservice inspection requirements in Part 50 of Title 10 of the Code of Federal Regulations for the Cooper Nuclear Station. To complete its review, the Nuclear Regulatory Commission (NRC) staff requests the following additional information:
Relief Request Number RI-21, Revision 2
- 1. Confirm that nozzles NVE-BD-N9 and NVE-BD-N4A&C are the only two components that are affected under Relief Request RI-21, Revision 2. There are 28 nozzles listed in this relief request; however, in the Basis for Relief section, the discussion focuses only on nozzles NVE-BD-N4A&C and NVE-BD-N9.
- 2. The licensee stated that the total volumetric examination coverage of nozzle NVE-BD-N9 was 40 percent. The figure in the attachment to the September 28, 2005, letter does not provide sufficient information regarding how the 40 percent coverage was achieved. Please demonstrate the 40 percent coverage by calculations and diagrams.
- 3. The submittal stated that the inner radius examination of nozzle NVE-BD-N9 in the third interval achieved 100 percent of the required examination volume. It also stated that the inner 15 percent of the nozzle received 100 percent coverage. Discuss why the volumetric examination can achieve 100 percent coverage in the inner radius region, but only 40 percent coverage was achieved.
- 4. (A)
The submittal stated that Based on EPRI [Electric Power Research Institute]
modeling of the examination volume... a higher quality of examination was achieved even though less overall coverage was achieved... Discuss how does the EPRI modeling of the examination volume lead to a higher quality of examination.
(B)
The submittal also stated that... the requirement to use only Performance Demonstration Initiative (PDI)-qualified transducers limited the examination to coverage and contributed to a reduction of coverage compared to previous examinations in the outer 85% volume. Discuss whether an approach based on less coverage with a higher quality examination (as opposed to more coverage with a lower quality examination) is appropriate in terms of detecting flaws in the nozzles in the Cooper Nuclear Station.
(C)
Discuss the results of previous examinations of nozzle NVE-BD-N9.
- 5. In a letter dated October 23, 1997, the NRC staff approved Relief Request RI-21, Revision 1. In the NRC staffs safety evaluation contained in that letter, the staff discussed a visual examination, VT-2, associated with inservice inspection of nozzle NVE-BD-N9.
Discuss whether the visual examination, VT-2, has been conducted and will be performed for nozzle NVE-BD-N9 in conjunction with the required volumetric examinations.
Relief Request Number RI-36
- 6. Provide a drawing of the subject welds RVD-BJ-17 and RVD-BJ-18, including the volume that were volumetrically examined, angle and trace of transmitting and receiving signals, and examination interferences.
- 7. Identify the piping system with which subject welds RVD-BJ-17 and RVD-BJ-18 are associated. Discuss results of the previous volumetric examination of RVD-BJ-17 and RVD-BJ-18.
- 8. The submittal stated that alternate angles were used; however, due to high signal-to-noise ratios additional coverage could not be achieved. Identify the original transducer angles and alternate angles used. Discuss whether the original angles used in the examination result in high signal-to-noise ratio and whether the examination results were not distorted by the signal-to-noise ratio.
- 9. The submittal stated that the affected welds in Relief Request RI-36 were selected to be included in risk-informed inservice inspection. Discuss how does Relief Request RI-36 satisfy the relief request guidelines in EPRI TR-112657, Revision B-A, Revised Risk-Informed Inservice Inspection Evaluation Procedure (PWRMRP-05), Final Report, December 1999.
October 2005 Cooper Nuclear Station cc:
Mr. William J. Fehrman President and Chief Executive Officer Nebraska Public Power District 1414 15th Street Columbus, NE 68601 Mr. Michael T. Boyce Nuclear Assett Manager Nebraska Public Power District P. O. Box 98 Brownville, NE 68321 Mr. John C. McClure Vice President and 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. Mike Wells, Deputy Director Missouri Department of Natural Resources P.O. Box 176 Jefferson City, MO 65101 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 Director, Missouri State Emergency Management Agency P. O. Box 116 Jefferson City, MO 65102-0116 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 Lucas State Office Building, 5th Floor 321 East 12th Street Des Moines, IA 50319 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 Mr. John F. McCann, Director Licensing, Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601-1813