LIC-04-0010, Revision of Fort Calhoun Station Core Reload Methodology Topical Reports

Revision of Fort Calhoun Station Core Reload Methodology Topical Reports

ML040340228
Person / Time
Site:	Fort Calhoun
Issue date:	01/23/2004
From:	Ridenoure R Omaha Public Power District
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GL-83-011, LIC-04-0010
Download: ML040340228 (3)

Text

rn- mp Omaha Public Power District 444 South 16th Street Afall Omaha NE 68102-2247 January 23, 2004 LIC-04-00 10 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

References:

1. Docket No. 50-285

2. OPPD-NA-8301-P, "Reload Core Analysis Methodology Overview"

3. OPPD-NA-8302-P, "Reload Core Analysis Methodology, Neutronics Design Methods and Verification"

4. OPPD-NA-8303-P, "Reload Core Analysis Methodology, Transient and Accident Analysis Methods and Verification"

5. NRC Generic Letter 83-11, Supplement 1, "Licensee Qualification for Performing Safety Analyses," June 24, 1999

SUBJECT:

Revision of Fort Calhoun Station Core Reload Methodology Topical Reports In accordance with Reference 5, Omaha Public Power District (OPPD) hereby provides notification of updates to the reload methodology documents referenced in the Fort Calhoun Station (FCS) Technical Specifications Section 5.9.5.

OPPD has updated References 2, 3, and 4 in accordance with the guidance furnished in Reference 5. Detailed topical reports are not being submitted since the prescribed guidelines are met and approved codes and methods are used. The FCS Core Operating Limits Report will be updated to reflect these document changes and sent to the NRC following completion of the next core reload design. No FCS Technical Specification changes are necessary for this update.

-40o Employment lit,: Equal Opportunity

U. S. Nuclear Regulatory Commission LIC-04-001 0 Page 2 Commitments made to the NRC in this letter are listed in the Attachment.

If you have any questions or require additional information, please contact Dr. R. L.

Jaworski at (402) 533-6833.

SicePresient/

Attach nt: Commitment Summary c: B. S. Mallett, NRC Regional Administrator, Region IV A. B. Wang, NRC Project Manager J. G. Kramer, NRC Senior Resident Inspector

LIC-04-001 0 Attachment Page 1 Commitment Summary Update the FCS Core Operating Limits Report (COLR), TDB-VI, to reflect OPPD reload methodology topical report changes and distribute the COLR to the NRC following completion of the next core design. (AR26159)

Text

rn- mp Omaha Public Power District 444 South 16th Street Afall Omaha NE 68102-2247 January 23, 2004 LIC-04-00 10 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

References:

1. Docket No. 50-285

2. OPPD-NA-8301-P, "Reload Core Analysis Methodology Overview"

3. OPPD-NA-8302-P, "Reload Core Analysis Methodology, Neutronics Design Methods and Verification"

4. OPPD-NA-8303-P, "Reload Core Analysis Methodology, Transient and Accident Analysis Methods and Verification"

5. NRC Generic Letter 83-11, Supplement 1, "Licensee Qualification for Performing Safety Analyses," June 24, 1999

SUBJECT:

Revision of Fort Calhoun Station Core Reload Methodology Topical Reports In accordance with Reference 5, Omaha Public Power District (OPPD) hereby provides notification of updates to the reload methodology documents referenced in the Fort Calhoun Station (FCS) Technical Specifications Section 5.9.5.

OPPD has updated References 2, 3, and 4 in accordance with the guidance furnished in Reference 5. Detailed topical reports are not being submitted since the prescribed guidelines are met and approved codes and methods are used. The FCS Core Operating Limits Report will be updated to reflect these document changes and sent to the NRC following completion of the next core reload design. No FCS Technical Specification changes are necessary for this update.

-40o Employment lit,: Equal Opportunity

U. S. Nuclear Regulatory Commission LIC-04-001 0 Page 2 Commitments made to the NRC in this letter are listed in the Attachment.

If you have any questions or require additional information, please contact Dr. R. L.

Jaworski at (402) 533-6833.

SicePresient/

Attach nt: Commitment Summary c: B. S. Mallett, NRC Regional Administrator, Region IV A. B. Wang, NRC Project Manager J. G. Kramer, NRC Senior Resident Inspector

LIC-04-001 0 Attachment Page 1 Commitment Summary Update the FCS Core Operating Limits Report (COLR), TDB-VI, to reflect OPPD reload methodology topical report changes and distribute the COLR to the NRC following completion of the next core design. (AR26159)