ML20170A398

Independent Spent Fuel Storage Installation Updated Decommissioning Safety Analysis Report, DSAR 3.10, Rev. 0, General References

ML20170A398
Person / Time
Site:	Fort Calhoun, 07100256
Issue date:	04/30/2020
From:	Schulte T Omaha Public Power District
To:	Office of Nuclear Reactor Regulation, Office of Nuclear Material Safety and Safeguards
Shared Package
ML20170A380	List: LIC-20-0005, Independent Spent Fuel Storage Installation, Technical Specification Basis ML20170A382 ML20170A383 ML20170A384 ML20170A385 ML20170A387 ML20170A388 ML20170A389 ML20170A390 ML20170A391 ML20170A392 ML20170A393 ML20170A394 ML20170A395 ML20170A396 ML20170A397 ML20170A398 ML20170A399 ML20170A400 ML20170A401 ML20170A402 ML20170A403 ML20170A404 ML20170A405 ML20170A406 ML20170A408 ML20170A409 ML20170A410 ML20170A411 ML20170A412 ML20170A414 ML20170A415 ML20170A416 ML20170A417 ML20170A418 ML20170A419 ML20170A420 ML20170A421 ML20170A422 ML20170A423 ML20170A424 ML20170A425 ML20170A426 ML20170A427 ML20170A428 ML20170A429 ML20170A430 ML20170A431 ML20170A432 ML20170A433 ... further results
References
LIC-20-0005
Download: ML20170A398 (3)

Text

Page 1 of 3 DSAR-3.10 Reactor General References Rev 0 Safety Classification:

Usage Level:

Safety Information Change No.:

EC 69283 Reason for Change:

This section is being updated to reflect the permanent cessation of operations of Fort Calhoun Station. The contents of this section have been changed to remove any information which is not applicable during decommissioning.

Preparer:

Tim Schulte Fort Calhoun Station

DSAR-3.10 Information Use Page 2 of 3 General References Rev. 0 Table of Contents 3.10 General References................................................................................................. 3

DSAR-3.10 Information Use Page 3 of 3 General References Rev. 0 3.10 General References 3.10.1 Deleted 3.10.2 Deleted 3.10.3 Deleted 3.10.4 Deleted 3.10.5 Deleted 3.10.6 An Evaluation of Some Uncertainties in the Comparison Between Theory and Experiments for Regular Light Water Lattices, Fayer, F. J., et al, Brit. Nuc.

En. Soc. J., 6 (April 1967) 3.10.7 XTG - A Two-Group Three Dimensional Reactor Simulator Utilizing Coarse Mesh Spacing, Stout, R. B., XN-CC-28, Revision 3 (January 1965) 3.10.8 Deleted 3.10.9 Not Used 3.10.10 Zircaloy-Clad UO2 Rod Evaluation Program, Quarterly Progress Report No. 1, Megerth, F. H., November 1967-January 1968, GEAP-5598, March 1968 3.10.11 Deleted 3.10.12 Deleted 3.10.13 Not Used 3.10.14 Deleted 3.10.15 Deleted