ML20170A429

Independent Spent Fuel Storage Installation Updated Decommissioning Safety Analysis Report, DSAR-11.4, Rev. 0, Radioactive Waste and Radiation Protection and Monitoring, Specific References

ML20170A429
Person / Time
Site:	Fort Calhoun, 07100256
Issue date:	04/30/2020
From:	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: ML20170A429 (4)

Text

Page 1 of 4 DSAR-11.4 Radioactive Waste and Radiation Protection and Monitoring Specific 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 at Fort Calhoun Station. The contents of this section have been changed to remove any information which is not applicable during decommissioning.

Preparer: T. Schulte Fort Calhoun Station

DSAR-11.4 Information Use Page 2 of 4 Specific References Rev. 0 Table of Contents 11.4 Specific References ...................................................................................................... 3

DSAR-11.4 Information Use Page 3 of 4 Specific References Rev. 0 11.4 Specific References 11.4.1 Deleted 11.4.2 Engineering Analysis (EA-FC-90-111), Shielding Calculation Revision Phase I - Comparison Study.

11.4.3 Deleted 11.4.4 Deleted 11.4.5 Nuclear Applications and Technology, Volume 9, August 1970, pages 268-273 and October 1970, pages 508-515, respectively.

11.4.6 Amendment No. 91 to Facility Operating License DPR-40 for Fort Calhoun Station Unit No. 1, issued August 22, 1985.

11.4.7 NUREG-0472, Revision 3, Draft 7, Standard Radiological Effluent Technical Specifications for Pressurized Water Reactors, United States Nuclear Regulatory Commission.

11.4.8 Amendment No. 86 to Facility Operating License DPR-40 for Fort Calhoun Station Unit No. 1, issued April 3, 1985.

11.4.9 Amendment No. 93 to Facility Operating License DPR-40 for Fort Calhoun Station Unit No. 1, issued December 6, 1985.

11.4.10 Amendment No. 102 to Facility Operating License DPR-40 for Fort Calhoun Station Unit No. 1, issued January 20, 1987.

11.4.11 Amendment No. 106 to Facility Operating License DPR-40 for Fort Calhoun Station Unit No. 1, issued March 26, 1987.

11.4.12 NUREG-0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, U.S. Nuclear Regulatory Commission, October, 1978.

11.4.13 Amendment No. 113 to Facility Operating License DPR-40 for Fort Calhoun Station Unit No. 1, issued May 4, 1988.

11.4.14 Amendment No. 164 to Facility Operating License DPR-40 for Fort Calhoun Station Unit No. 1, issued August 24, 1994.

11.4.15 Safety Evaluation by the Office of Nuclear Reactor Regulation, Revised Response to Regulatory Guide 1.97, dated May 10, 1996.

11.4.16 OPPD Calculation FC-06864, Revision 0, Implementation and Comparison of Alternate Source Term Inventory to USAR Section 11 Failed Fuel Inventory, December 2001.

DSAR-11.4 Information Use Page 4 of 4 Specific References Rev. 0 11.4.17 OPPD Calculation FC-06873, Rev. 1, "USAR Section 11 Update Due to Revised Core Inventory", November 2006.

11.4.18 Safety Evaluation for Amendment No. 165 to Facility Operating License DPR-40 for the Fort Calhoun Station Unit No. 1, dated August 25, 1994.

11.4.19 OPPD Calculation FC-08073, Rev. 0, 11.2, "Update - Design Basis Curie Content of the Radwaste Building," December 2012.

11.4.20 OPPD Calculation FC-07082, Rev. 1, Original Steam Generator Storage Facility Shielding Assessment, November 29, 2006.