ML20170A447
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Page 1 of 3 DSAR-APPENDIX B Site Environmental Studies Rev 0 Safety Classification:
Usage Level:
Safety Information Change No.:
EC 69283 Reason for Change:
LIC-16-0074 certifies permanent removal of fuel from the FCS reactor core. This information Supports USAR 5.7 Piling. Since this information will no longer change, this appendix is being archived.
Preparer:
J. Carlson Fort Calhoun Station ARCHIVED TEXT*
- USAR pages labeled as "ARCHIVED TEXT" are pages with text which is not revised or updated. Information on "ARCHIVED TEXT" pages is A) of historical nature significant to the original licensing basis of the plant OR B) not meaningful to update.
DSAR-Appendix B Information Use Page 2 of 3 Site Environmental Studies Rev. 0 ARCHIVED TEXT*
An initial comprehensive investigation of the plant site was carried out by Dames and Moore.
This investigation covered field explorations, laboratory tests, geologic and hydrologic studies, engineering seismology, and recommendations for foundation design and installation criteria. The results of these studies were included in a report by Dames and Moore which was submitted as Appendix A to the Preliminary Facility Description and Safety Analysis Report.
Subsequent to the submittal of this report, some of the information has been superseded due to changes in design criteria and additional information acquired during engineering studies and further site investigations. The principal changes since the compilation of the report, and the pertinent references, are as follows:
- a.
Solution cavities were encountered in the limestone bedrock; therefore, a more extensive investigation of the bedrock was performed and a special technique for pile installation was devised.
References Preliminary Facility Description and Safety Analysis Report, Supplement No. 4 (Exhibit F-4)
Final Safety Analysis Report, Section 5.7 Final Safety Analysis Report, Appendix C
- b.
The values of the design earthquake and maximum hypothetical earthquake factors given as 5 and 15 percent of gravity respectively were subsequently increased to 8 and 17 percent of gravity respectively in accordance with the U.S. Coast and Geodetic Survey recommendations.
References Preliminary Facility Description and Safety Analysis Report, Supplement No. 11 (Exhibit F-11)
Final Safety Analysis Report, Appendix F
- c.
The earthquake response spectra have been revised on two occasions. The first change was due to a change in the governing basis. The second modification was made in response to the increased earthquake factors.
References Preliminary Facility Description and Safety Analysis Report, Supplements No. 1, 2 and 11 (Exhibits F-1, F-2 and F-11)
Final Safety Analysis Report, Appendix F
DSAR-Appendix B Information Use Page 3 of 3 Site Environmental Studies Rev. 0 ARCHIVED TEXT*
- d.
Potential liquefaction of the soil was found to require consideration.
References Preliminary Facility Description and Safety Analysis Report, Supplements No. 2, 8, 11 and 12 (Exhibits F-2, F-8, F-11 and F-12)
Final Safety Analysis Report, Appendix C
- e.
The discussion of the Missouri River 100 year high water level of 1008.8 feet at the plant site was clarified and revised.
References Preliminary Facility Description and Safety Analysis Report, Supplements No. 2 and 12 (Exhibits F-2 and F-12)
Final Safety Analysis Report, Section 2.7.1