ML040760945
| ML040760945 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 03/12/2004 |
| From: | Wang A NRC/NRR/DLPM/LPD4 |
| To: | Ridenoure R Omaha Public Power District |
| Wang A, NRR/DLPM, 415-1445 | |
| References | |
| TAC MC1115 | |
| Download: ML040760945 (5) | |
Text
March 12, 2004 Mr. R. T. Ridenoure Division Manager - Nuclear Operations Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
Post Office Box 550 Fort Calhoun, NE 68023-0550
SUBJECT:
FORT CALHOUN STATION, UNIT NO. 1 - REQUEST FOR ADDITIONAL INFORMATION ON REQUEST FOR RELIEF RELATED TO REACTOR PRESSURE VESSEL NOZZLE INSPECTIONS (TAC NO. MC1115)
Dear Mr. Ridenoure:
By letter dated October 24, 2003, Omaha Public Power District (OPPD) submitted Request for Relief (RR) 9 for the third 10-year interval. The request proposed to use Code Case N-615, "Ultrasonic Examination as a Surface Examination Method for Category B-F and B-J Piping Welds." OPPD proposed to perform an alternative examination from the inside surface of the reactor pressure vessel nozzle-to-safe end weld.
The staff has completed its preliminary review of this submittal and has determined it needs additional information to complete the review. Our request for additional information is enclosed. This request was discussed with Richard Jaworski of your staff and it was agreed that a response would be provided within 30 days of receipt of this letter.
Sincerely,
/RA/
Alan B. Wang, Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-285
Enclosure:
Request for Additional Information cc w/encl: See next page
March 12, 2004 Mr. R. T. Ridenoure Division Manager - Nuclear Operations Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
Post Office Box 550 Fort Calhoun, NE 68023-0550
SUBJECT:
FORT CALHOUN STATION, UNIT NO. 1 - REQUEST FOR ADDITIONAL INFORMATION ON REQUEST FOR RELIEF RELATED TO REACTOR PRESSURE VESSEL NOZZLE INSPECTIONS (TAC NO. MC1115)
Dear Mr. Ridenoure:
By letter dated October 24, 2003, Omaha Public Power District (OPPD) submitted Request for Relief (RR) 9 for the third 10-year interval. The request proposed to use Code Case N-615, "Ultrasonic Examination as a Surface Examination Method for Category B-F and B-J Piping Welds." OPPD proposed to perform an alternative examination from the inside surface of the reactor pressure vessel nozzle-to-safe end weld.
The staff has completed its preliminary review of this submittal and has determined it needs additional information to complete the review. Our request for additional information is enclosed. This request was discussed with Richard Jaworski of your staff and it was agreed that a response would be provided within 30 days of receipt of this letter.
Sincerely,
/RA/
Alan B. Wang, Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-285
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
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SSheng ADAMS ACCESSION NO.: ML040760945 OFFICE PDIV-2/PM PDIV-2/LA PDIV-2/SC NAME AWang EPeyton JNDonohew for SDembek DATE 3/11/04 3/10/04 3/11/04 DOCUMENT NAME: C:\\ORPCheckout\\FileNET\\ML040760945.wpd OFFICIAL RECORD COPY
Ft. Calhoun Station, Unit 1 cc:
Winston & Strawn ATTN: James R. Curtiss, Esq.
1400 L Street, N.W.
Washington, DC 20005-3502 Chairman Washington County Board of Supervisors P.O. Box 466 Blair, NE 68008 Mr. John Kramer, Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 310 Fort Calhoun, NE 68023 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Ms. Sue Semerera, Section Administrator Nebraska Health and Human Services Systems Division of Public Health Assurance Consumer Services Section 301 Cententiall Mall, South P.O. Box 95007 Lincoln, NE 68509-5007 Mr. David J. Bannister, Manager Fort Calhoun Station Omaha Public Power District Fort Calhoun Station FC-1-1 Plant P.O. Box 550 Fort Calhoun, NE 68023-0550 Mr. John B. Herman Manager - Nuclear Licensing Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
P.O. Box 550 Fort Calhoun, NE 68023-0550 Mr. Daniel K. McGhee Bureau of Radiological Health Iowa Department of Public Health 401 SW 7th Street, Suite D Des Moines, IA 50309 Mr. Richard P. Clemens Division Manager - Nuclear Assessments Omaha Public Power District Fort Calhoun Station P.O. Box 550 Fort Calhoun, NE 68023-0550
REQUEST FOR ADDITIONAL INFORMATION REQUEST FOR RELIEF PERTAINING TO REACTOR VESSEL NOZZLE INSPECTIONS OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT NO. 1 DOCKET NO. 50-285 By letter dated October 24, 2003, Omaha Public Power District (OPPD/the licensee) submitted Request for Relief (RR) 9 for the third 10-year interval. The request proposed to use the ASME Code Case N-615, "Ultrasonic Examination as a Surface Examination Method for Category B-F and B-J Piping Welds," (N-615). OPPD proposed to perform an alternative examination from the inside surface of the reactor pressure vessel nozzle-to-safe end weld. The staff has completed its preliminary review of this relief request and has determined that the following additional information is needed to complete the review.
1.
Regulatory Guide 1.147, Revision 13, ""Inservice Inspection Code Case Acceptability-ASME Section XI, Division 1," disapproves the use of N-615 because it does not require a performance demonstration according to Appendix VIII. Therefore, N-615 is not applicable for use as an alternative to the Code unless accompanied with an Appendix VIII qualification.
The calibration block indicated that the subject welds are corrosion resistance cladded (CRC). The Code has recognized the difficulty in satisfying the performance demonstration criteria for CRC welds according to Appendix VIII. Therefore, in lieu of an Appendix VIII qualification, the Code imposed a Section V qualification and examination requirement. Because of the inability to reliably demonstrate through-wall examinations of CRC welds, this type of request for relief may be proposed as a hardship.
2.
The submittal states that the relief is for six reactor pressure vessel nozzle-to-safe end dissimilar metal welds. Provide the unique identification for these welds.
3.
On pages 3 and 4 of the submittal, the tables use the abbreviation "NDD". What is the definition of NDD?
4.
The submittal describes the calibration block used for setting up equipment and demonstrating ultrasonic testing procedure. Provide a sketch of the site-specific welds in question showing the cladding (are both surfaces cladded on all six welds),
weld/butter/base material (carbon steel, stainless steel, Inconel) restrictions (if any),
inside surface irregularities, nominal wall thickness, and surface inspection volume.