ML060550294

Request for Additional Information Related to the Use of M5 Fuel Cladding

ML060550294
Person / Time
Site:	Fort Calhoun
Issue date:	03/02/2006
From:	Wang A NRC/NRR/ADRO/DORL/LPLG
To:	Ridenoure R Omaha Public Power District
Wang A, NRR/DLPM, 415-1445
References
TAC MC8096
Download: ML060550294 (5)

Text

March 02, 2006 Mr. R. T. Ridenoure Vice President - Chief Nuclear Officer 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 1 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE USE OF M5 FUEL CLADDING (TAC NO. MC8096)

Dear Mr. Ridenoure:

By letter dated August 11, 2005, Omaha Public Power District (OPPD/the licensee) submitted a license amendment request for the Fort Calhoun Station, Unit 1. The licensee requested a technical specification change that would permit the use of AREVA (Framatome ANP) M5 advanced alloy for fuel rod cladding and other structural components in the reactor core, beginning with Refueling Cycle 24.

The Nuclear Regulatory Commission (NRC) staff has completed a preliminary review of OPPDs submittal. The NRC staff has determined that additional information is needed to complete our review. A request for additional information (RAI) is enclosed. This request was discussed with Thomas Byrne of your staff on February 9, 2006, and it was agreed that a response would be provided within 30 days of receipt of this letter.

If you have any questions, please contact me at (301) 415-1445.

Sincerely,

/RA/

Alan B. Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285

Enclosure:

RAI cc w/encl: See next page

March 02, 2006 Mr. R. T. Ridenoure Vice President - Chief Nuclear Officer 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 1 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE USE OF M5 FUEL CLADDING (TAC NO. MC8096)

Dear Mr. Ridenoure:

By letter dated August 11, 2005, Omaha Public Power District (OPPD/the licensee) submitted a license amendment request for the Fort Calhoun Station, Unit 1. The licensee requested a technical specification change that would permit the use of AREVA (Framatome ANP) M5 advanced alloy for fuel rod cladding and other structural components in the reactor core, beginning with Refueling Cycle 24.

The Nuclear Regulatory Commission (NRC) staff has completed a preliminary review of OPPDs submittal. The NRC staff has determined that additional information is needed to complete our review. A request for additional information (RAI) is enclosed. This request was discussed with Thomas Byrne of your staff on February 9, 2006, and it was agreed that a response would be provided within 30 days of receipt of this letter.

If you have any questions, please contact me at (301) 415-1445.

Sincerely,

/RA/

Alan B. Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285

Enclosure:

RAI cc w/encl: See next page DISTRIBUTION:

PUBLIC RidsNrrPMAWang RidsNrrAcrsAcnwMailCenter LPLIV R/F RidsNrrLALFeizollahi RidsRgn4MailCenter (DGraves)

RidsNrrDorlLplg (DTerao) RidsOgcRp Tford RidsNrrDpr ACCESSION NO. ML060550294 OFFICE LPL4/PM LPL4/LA LPL4/BC NAME AWang LFeizollahi DTerao DATE OFFICIAL RECORD COPY

REQUEST FOR ADDITIONAL INFORMATION REGARDING THE USE OF M5 FUEL CLADDING OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION DOCKET NO. 50-285 By letter dated August 11, 2005, Omaha Public Power District (OPPD/the licensee) submitted a a license amendment request for the Fort Calhoun Station, Unit 1. The licensee requested a technical specification change that would permit the use of AREVA (Framatome ANP) M5 advanced alloy for fuel rod cladding and other structural components in the reactor core, beginning with Refueling Cycle 24. The Nuclear Regulatory Commission (NRC) staff has completed a preliminary review of OPPDs submittal. The NRC staff has determined that the following additional information is needed to complete our review.

1. Provide the calculated peak clad temperatures for both the M5 cladding (Mark-B-HTP fuel design) and the co-resident Zircaloy-4 cladding.

2. Does the loss-of-coolant accident (LOCA) Evaluation Model consider both the pre-LOCA and LOCA oxidation in demonstrating compliance with 10 CFR 50.46 requirements?

3. Is the non-M5 fuel cladding oxidation bounded by a number which is less than or equal to the 10 CFR 50.46 acceptance criteria of 17 percent?

Ft. Calhoun Station, Unit 1 cc:

Winston & Strawn ATTN: James R. Curtiss, Esq. Mr. Daniel K. McGhee 1400 L Street, N.W. Bureau of Radiological Health Washington, DC 20005-3502 Iowa Department of Public Health Lucas State Office Building, 5th Floor Chairman 321 East 12th Street Washington County Board of Supervisors Des Moines, IA 50319 P.O. Box 466 Blair, NE 68008 Mr. John Hanna, 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. Julia Schmitt, Manager Radiation Control Program Nebraska Health & Human Services R & L Public Health Assurance 301 Centennial 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. Joe L. McManis Manager - Nuclear Licensing Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.

P.O. Box 550 Fort Calhoun, NE 68023-0550 January 2006