ML22081A041
| ML22081A041 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun, 07100256  |
| Issue date: | 03/10/2022 |
| From: | Omaha Public Power District |
| To: | Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML22081A039 | List: |
| References | |
| LIC-22-0002 | |
| Download: ML22081A041 (81) | |
Text
DSAR-Table of Contents Page 1 of 3 FCSI Rev. 0 Information Use Introduction
Table of Contents
1.0 INTRODUCTION
AND
SUMMARY
1.1 Introduction 1.2 Summary Plant Description 1.2.1 Plant Site 1.2.2 Station Arrangement 1.2.3 Reactor and Reactor Coolant System 1.2.4 Deleted 1.2.5 Engineered Safeguards Systems 1.2.6 Instrumentation and Control 1.2.7 Electrical Systems 1.2.8 Auxiliary Systems 1.2.9 Deleted 1.2.10 Radioactive Waste Disposal 1.2.11 Plant Design Characteristics 1.11 Specific References
2.0 SITE AND ENVIRONS
2.1 Introduction 2.2 General Description of Site and Environs 2.3 ARCHIVED TEXT*
Topography 2.4 Seismology 2.4.1 Seismic Geology and History 2.4.2 Seismicity 2.4.3 Seismic Design Criteria 2.4.4 Conclusions 2.4.5 References 2.5 Meteorology 2.5.1 General Climate 2.5.2 Local Meteorology 2.6 Geology 2.6.1 Physiography 2.6.2 Regional Geology 2.6.3 Regional Structure 2.6.4 Areal Structure 2.6.5 Geologic History 2.6.6 Glacial History of the Missouri Valley 2.6.7 Site Geology 2.6.8 Conclusions 2.7 Hydrology 2.7.1 Surface Drainage DSAR-Table of Contents Page 2 of 3 FCSI Rev. 0 Information Use Introduction
2.7.2 Ground Water 2.8 Demography 2.9 Land Use 2.9.1 General 2.9.2 Agronomy 2.9.3 Industry 2.9.4 Wildlife 2.10 Environmental Radiation Monitoring 2.10.1 General 2.10.2 Preoperational Survey Program 2.10.3 Preoperation Survey Results 2.10.4 Radiological Environmental Monitoring Program (REMP) 2.11 Section 2 References
- 5. STRUCTURES
5.8 External Missiles
- 12. CONDUCT OF OPERATIONS
12.1 Organization and Responsibility 12.2 Training 12.3 Written Procedures 12.4 Records 12.6 Site Emergency Plan 12.7 Plant Security
APPENDIX A
APPENDIX G
DSAR-Table of Contents Page 3 of 3 FCSI Rev. 0 Information Use Introduction
List of Figures
The following figures are contro lled drawings and can be viewed and printed from the listed aperture card.
Figure No. Title Aperture Card
1.2-1 Site Plan................................................................................................. 36030 1.2-2 Site Vicinity Plan 36031
2.2-1 Aerial Photograph of Site and Environs................................................. 36042 2.2-2 Geographical Features W ithin 60 Miles of Site...................................... 36043 2.2-3 Geographical Features W ithin 30 Miles of Site...................................... 36044 2.2-4 Metes and Bounds................................................................................. 36045
2.3-1 Site Topography..................................................................................... 36046
2.4-1 Response Spectra Maximu m Hypothetical Earthquake......................... 85358
2.7-1 Upper Missouri River Basin.................................................................... 36047 2.7-2 Stage Duration Curve............................................................................. 36048 2.7-3 Flow Duration Curve.............................................................................. 36049 2.7-4 Missouri River Rating Curve.................................................................. 36050
DSAR-1.1 Page 1 of 2 FCSI Rev. 3 Information Use Introduction
- 1. INTRODUCTION AND
SUMMARY
1.1 Introduction
By letters dated June 24 and Augu st 25, 2016, OPPD notified the NRC of its intention to permanently cease power operat ions at Fort Calhoun Station ( FCS) pursuant to 10 CFR 50.82(a)(1)(i). On Oct ober 24, 2016, OPPD permanently c eased power operations at FCS (References 1-13, 1-14).
Pursuant to 10 CFR 50.82(a)(1)( ii), OPPD certified to the NRC that as of November 13, 2016, all fuel had been permanently removed from t he FCS reactor vessel and had been placed into the spent fuel pool. The lette r acknowledged that upon docketing the certifications for permanent cessation of op erations and permanent removal of fuel from the reactor vessel, the 10 CFR Part 50 license no longer authorized operation of the reactor or emplacement or retention of fuel in the reactor vessel (Reference 1-15).
By letter from NRC (J. Kim) to O PPD (M. Fisher) Fort Calhoun Station, Unit 1 -
Issuance of Amendment Re: Revised Technical Specifications to Align to Those Requirements for Decommissioning Dated March 6, 2018 (NRC-18-011), OPPD was granted Permanently Defueled Techni cal Specifications (PDTS). PDTS removed all sections of operating plant TS that no longer apply during the decommissioning process.
Based on the above, the DSAR was updated as the Defueled Safety Analysis Report, or DSAR. Prior to permanent rem oval of fuel, the revised Final Safety Analysis Report, referred to as USAR, was submitted as required under 10 CFR Part 50.71(e),
effective July 22, 1980. The orig inal Final Safety Analysis Report was submitted in support of the application by the Omaha Public Power District, (OPPD), for a license pursuant to Section 104b of the Atomic Energy Act, 1954, to ope rate the Fort Calhoun Station Unit No. 1, (AEC Docket 50 285, Construction Permit CPP R 41).
By letter from NRC (J. Parrott) to OPPD (M. Fisher) Fort Calho un Station, Unit 1 -
Issuance of Amendment Re: Revised Fort Calhoun Station Permanen tly Defueled Technical Specifications to Align to Those Requirements for Permanent Removal of Spent Fuel from Spent Fuel Pool., Dated December 11, 2019 (NRC-19-026), OPPD was granted the amendment to the Permanently Defueled Technical Specifications (PDTS). This amendment removed all sections associated with the storage of fuel and relocated administrative require ments to appropriate documents. Based on the above, the DSAR has been revised to ref lect the new license conditions and requirements.
DSAR-1.1 Page 2 of 2 FCSI Rev. 3 Information Use Introduction
This report provided pertinent tec hnical information in accordance with the requirements set forth under Tit le 10 of the Code of Federal Re gulations, Part 50, (10 CFR Part 50) and informat ion and analyses submitted to the NRC or prepared as a result of NRC requirements. T he plant began commercial opera tion on September 26, 1973. Prior to decommissioning, the nuclear steam supply system (NSSS) was of the pressurized wa ter type. It was similar in design to several facilities which began operation or were under review by the U.S. Atomic E nergy Commission at the time the plant was pursuin g its original operating license. A license was requested to operate the facility at power levels up to and including 1420 core thermal megawatts (MWt) which corres ponded to a turbine-generator outpu t of 481 MWe. The license was then amended to allow operation at power levels up to and including 1500 core thermal megawatts (MWt) which corresponded to a turbi ne-generator output of nominal 533.7 MWe at 0.90 power factor.
DSAR-1.2 Page 1 of 8 FCSI Rev. 8 Information Use Summary Plant Description
1.0 INTRODUCTION
AND
SUMMARY
1.2 Summary Plant Description
1.2.1 Plant Site
The site for the Fort Calhoun St ation contains approximately 540 acres on the west bank of the Missouri Rive r, approximately 19.4 miles n orth of Omaha, Nebraska. OPPD has a per petual easement on approximatel y 117 acres of land on the east bank of the river directly opposi te the plant buildings. On the Western part of the site the ground rises sh arply about 60 feet to a higher level area which is bounded on the west by U.S.
Highway 75, formerly U.S. Highway 73.
The U.S. Corps of Engineers' river improvement program has led to the development of a stable, well def ined river bank in the vicinit y of the site. A partially filled-in area, about 450 feet wide, runs parallel to the bank.
The legacy station buildings are supported by a system of pipe piles which were driven to bedrock approximat ely 60 feet below the surface. Ground water level is close to existing grade and structures below gra de are suitably water-proofed.
An Independent Spent Fuel Storage In stallation (ISFSI) is locat ed in the protected area designated for dry storage of spent fuel and gre ater than class C waste (GTCC). The ISFS I is licensed under Subpart K of 10 CFR Part 72.
The area adjoining the site is farmland and sparsely populated. The minimum exclusion distance is 1525 feet. The nearest populatio n center area of more than 25,000 is formed by adjacent cities of Omaha, Nebraska and Council Bluffs, Iowa. The site v icinity plan is shown in Figure 1.2-2.
The exclusion zone consists of approximately 540 acres owned by Omaha Public Power District. The rest ricted area as defined in Section 20.3(a)(14) of 10 CFR Part 20 is shown on Figure 1.2-1.
A rail spur from the Chicago and Northwestern (CNW) Railway was constructed to serve the construction of the Fort Calhoun Stati on (FCS). The original CNW tracks and rail s pur have since been removed. In 1994, a permanent easement was granted to allow the construction of a n ew rail spur in the approximate location of t he old CNW railway to allow tra ins to serve the Cargill industrial facility located north of FCS. Road acc ess to FCS is from U.S. Highway No. 75.
DSAR-1.2 Page 2 of 8 FCSI Rev. 8 Information Use Summary Plant Description
1.2.2 Station Arrangement
Station status is continually changing during decommissioning. Current information on systems, radiologi cal conditions and demolition progress is maintained by the Radiation Protection and Decommissioning orga nizations respectively.
The principal station structures are the ISFSI Operating Facility (IOF) and ISFSI.
The sites legacy buildings include the turbine building, intak e structure, technical support center, service building, maintenance shop, and the chemistry and radiation protection/locker facility including th e office/cafeteria addition, and hazardous material storage building. All are located outside of the Protected Area.
Some specific system descriptions have been removed from the DS AR as all spent fuel has been removed from the Spent Fuel Pool to the ISF SI pad and these SSC no longer have a design function.
The reactor, steam generators, r eactor coolant pumps and pressurizer are located in the containment, toget her with other nuclear steam s upply system (NSSS) components which no longer have a design function.
A polar bridge crane is installed above the Containment operati ng floor, but no longer has a design function.
The reactor auxiliaries include, engineered safeguards componen ts, the control room, radiation controlled area (RCA) protective clothi ng issue and dress area and laboratories, and fuel handling and storage facilities are located in the auxiliary building, but no longer have a design function.
Reactor auxiliaries that retain a function include the waste tr eatment facilities.
A traveling bridge crane is located over the fuel handling and storage area in the auxiliary building. The tr aveling bridge crane no longer h as a design function.
The turbine building houses the turbine generator, condenser, a nd other turbine heat cycle components. T hese components no longer have a design function. The 150-ton traveli ng bridge crane no longer has a d esign function.
The service building houses the auxiliary boiler which no longer has a design function.
The condenser cooling circulatin g water and raw water pumps are located in the intake structure. They no longer have a design function.
DSAR-1.2 Page 3 of 8 FCSI Rev. 8 Information Use Summary Plant Description
Station Structures can contain pr ovisions for dry active waste (DAW) processing, liquid radwaste filt ration and ion exchange (FIX) e quipment and radwaste solidification equipment.
1.2.3 Reactor and Reactor Coolant System
The reactor and reactor coolant system are located in containme nt but no longer have a design function.
1.2.4 Deleted
1.2.5 Engineered Safeguards Systems
The components which made up t he engineered safeguards systems are located in the Auxiliary Building and Containment, but no longe r have a design function.
1.2.6 Instrumentation and Control
A. Deleted.
B. Instrumentation
Local control of the remaining in strumentation monitoring syste m function to support the remaini ng functional portions of the wa ste disposal, radiation monitors, and HVAC systems. All other proce ss instrumentation and monitoring syst ems remain installed, but no longer have a design function.
C. Plant Computer
The plant computer remains insta lled, but no longer has a desi gn function.
1.2.7 Electrical Systems
The source of energy for the ISFSI loads are the 13.8 kV circui t from the OPPD Substation, and a diesel-generator set located in the IOF.
Power systems provide power to m eet required remaining decommis sioning support functions. Other legacy electrical systems remain inst alled, but no longer have a design function.
DSAR-1.2 Page 4 of 8 FCSI Rev. 8 Information Use Summary Plant Description
1.2.8 Auxiliary Systems
The following systems remain i nstalled but no longer have a des ign function:
Chemical Volume and Control System Shutdown Cooling System Component Cooling Water and Raw Water Systems Sampling Systems Circulating and Turbine Plant Cooling Water Systems Compressed Air System Spent Fuel Pool Cooling Auxiliary Boiler System Radioactive Waste Disposal System
A. Fuel Handling and Storage
Irradiated fuel bundles are not a llowed to be stored in the SFP. The system remains installed, but no longer has a design function. The ISFSI contains all fuel for stor age prior to off-site shipment.
OPPD has constructed an ISFSI, located in the Protected Area designated for dry storage of s pent fuel. The ISFSI consists o f the concrete basemat that was buil t on an elevated pad of compacted,
engineered fill for flood protecti on, concrete horizontal storage modules, concrete shield walls, concrete approach slabs adjacent to the basemat, the ISFSI electrical equipment building, and the IOF. The ISFS I is designed for 42 horizontal stor age modules arranged in a 2 x 21 back-to-back configuration. Eac h horizontal storage module hol ds one dry shielded canister for fuel s torage or a canister containing greater than class C waste (GTCC) for storage. The HSM protects the canister(s) from natural phenome na such as tornado missiles, an d is designed to provide for passive c ooling of the canister by mean s of natural air circulation. The IS FSI basemat is 42 ft. wide by 211 ft. long, with its long dimension orient ed in the east-west direction. T he elevation of the top of the basemat is at 1009 ft-10 inches, above the le vel of the probable maximum flood. This DSAR for the Fort Calhoun Station does not assess the safety of the dr y spent fuel storage system, which is licensed under Subpart K of 10 CFR Part 72 for general ISFSI li censes.
DSAR-1.2 Page 5 of 8 FCSI Rev. 8 Information Use Summary Plant Description
Transnuclear, Inc., the storage system vendor, maintains the Fi nal Safety Analysis Report for the NUHOMS Horizontal Modular Storage System (Reference 1-6). Certi ficate of Compliance No. 1004 (Reference 1-7) was issued by the NRC for the NUHOMS -system, with the 32PT DSC used at the Fort Cal houn Station ISFSI. The Technical Specifications for the NUHOMS storage system are included as Attachment A to Certificate of Compliance No. 1004.
B. Plant Ventilation Systems
Station Ventilation systems (s erving the containment and part of the auxiliary building) handle air borne contaminants so that offsit e concentrations and in plant doses (which are controlled by the ODCM and administrative procedures) are within 10 CFR Part 20 limits.
The remaining plant ventilation systems remains installed but n o longer have a design function.
C. Plant Fire Protection
In November 2016, OPPD certified to the NRC per 10 CFR 50.82(a) (1) that fuel had been permanently rem oved from the reactor vessel. With this certification, 10 CFR 50.48(f) became applicable to the fi re protection program. Subsequently, Amendment No. 290 to the Renewed Facili ty License DPR-40 deleted the fire protection program as a License Condition. The fire protection program is now maintained in ac cordance with 10 CFR 50.48(f). These prog rams address both the site and the ISFSI (CC-FC-211 and FCSI-FP-100).
1.2.9 Deleted
DSAR-1.2 Page 6 of 8 FCSI Rev. 8 Information Use Summary Plant Description
1.2.10 Radioactive Waste Disposal
Radioactive waste is managed du ring decommissioning through the use of permanent and temporary liquid, g aseous and solid treatment sys tems.
These systems collect, process, m onitor and regulate the discharge of potentially radioactive wastes from the site.
The waste equipment used for radioactive waste processing and d isposal are designed to protect plant personnel and the public from exposur e to radioactive wastes in accordance with 10 CFR Part 20; 10 CFR 50, Appendix I; 40 CFR Part 190; 10 CFR 50 Appen dix A General Design Criterion 60, and Draft GDC Criteria 17 and 18.
This equipment along with approv ed procedures will provide the administrative controls to ensur e that the radioactive releases are completed within the allowable concentrati ons and dose limitations defined in the Quality Assurance Topical Repor t (QATR), Appendix E and the Off site Dose Calculation Manual (ODCM)
A. Liquid
Effluents shall be limited to le ss than ten times 10 CFR Part 20, Appendix B, Table 2, Column 2 concentrations at discharge as de scribed within the ODCM.
B. Gaseous
The Five year average dispersion factor (/Q) for gaseous releases used to determine exposures in the unrestricted area is specified in the ODCM. The ODCM ensures that all releases are within applicable criteria.
C. Solid
The general types of radioactive sol id wastes produced at the s tation are processed in accordance with radi ological requirements in the O DCM and the Process Control Program (PC).
D. Shielding
Radiation shielding is designed to provide radiation protection for personnel inside and outside the plant, and for the general pub lic.
DSAR-1.2 Page 7 of 8 FCSI Rev. 8 Information Use Summary Plant Description
Containment Building
The containment has one major sh ielding function: It shields adjacent auxiliary plant and yard areas fr om radiation originating from inside the containment.
Auxiliary Building
Adequate shielding is provided around equipment that carries ra dioactive liquid, slurry or gas.
Radioactive Waste Processing Building and CARP Building
Adequate shielding is provided fo r each room in the Radioactive Waste Processing and CARP buildings to permit continuous occupancy in general access areas.
E. Radiation Monitoring
Radiation monitors are provided for radiological controls and O DCM requirements
F. Miscellaneous Radioact ive Material Sources
Miscellaneous radioactive material sources are controlled by Ra diation Protection procedures.
G. Radiological Effluent Requirements
The QATR, Process Control Program (PCP), and the ODCM contain all the radiological effluent requirements.
H. Event Analysis
The PSDAR and FC08566, Dose Cons equences of a High Integrity Container (HIC) Drop Event (Re ference 1.4.1), provide quantity and design incidents for radiologica l solid (postulated gas) releases. This calculation supports the ISFSI O nly Emergency Plan (IOEP) license, which assumes onsite deconstructi on activities are administratively controlled.
The radioactive waste handling events have been postulated to b e the limiting events for decommissioni ng activities and does not rel y on any equipment for mitigation.
DSAR-1.2 Page 8 of 8 FCSI Rev. 8 Information Use Summary Plant Description
Therefore, there is no SSC required to meet 10 CFR 20 limits for these events.
1.2.11 Plant Design Characteristics
Amendment No. 283 to Renew ed Facility Operating License No. DPR-40 allows the design and/or analysis of piping to be performed in accordance with ASME Section III, 1980 Edition (no Addenda) as an alternat ive to USAS B31.7, 1968 (DRAFT) Edition.
There is no longer any safety cl ass components at the station.
DSAR-1.11 Page 1 of 2 FCSI Rev. 5 Information Use Specific References
1.0 INTRODUCTION
AND
SUMMARY
1.11 Specific References
1-1 Deleted
1-2 Deleted
1-3 Deleted
1-4 Deleted
1-5 Deleted
1-6 Final Safety Analysis Report for the Standardized NUHOMS Horizontal Modular Storage System for Ir radiated Nuclear Fuel (NUH-003),
Transnuclear Inc., Revisions 9, 10, and 18.
1-7 Renewed Certificate of Com pliance No. 1004, Amendments No. 8, 9, and 15, issued to Transnuclear, Inc. for Standardized NUHOMS-24P, -52B, -61BT, -
24PHB and -32PT, including Attachment A, Technical Specificatio ns, and NRC Safety Evaluation Report (SER).
1-8 Deleted
1-9 Deleted
1-10 Deleted
1-11 Deleted
1-12 Deleted
1-13 Letter from OPPD (T. Burke) to USNRC (Document Control Des k),
"Certification of Permanent Cessation of Power Operations," dated June 24, 2016 (LIC-16-0043) (ML16176A213).
1-14 Letter from OPPD (T. Burke) to USNRC (Document Control Des k),
"Certification of Permanent Cessation of Power Operations," dated August 25, 2016 (LIC-16-0067) (ML16242A127).
1-15 Letter from OPPD (T. Burke) to USNRC (Document Control Des k),
"Certification of Permanent Rem oval of Fuel from the Reactor Ve ssel," dated November 13, 2016 (LIC-16-0074).
DSAR-1.11 Page 2 of 2 FCSI Rev. 5 Information Use Specific References
1-16 Letter from NRC (J. Kim) to O PPD (M. Fisher) Fort Calhoun Station, Unit 1 -
Issuance of Amendment Re: Revised Technical Specifications to Align to Those Requirements for Decommissioning Dated March 6, 2018 (NRC-18-011).
1-17 Letter from NRC (J. Parrot) to OPPD (M. Fisher) Fort Calhoun Station, Unit 1 - Issuance of Amendment t o Revise Fort Calhoun Station Permanently Defueled Technical Specifications to Align to the R equirements for Permanent Removal of Spent F uel from Spent Fuel Pool Dated December 11, 2019 (NRC-19-026)
DSAR-2.1 Page 1 of 1 FCSI Rev. 3 Information Use Introduction
- 2. SITE AND ENVIRONS
ARCHIVED TEXT*
2.1 Introduction
This section outlines the bases fo r the remaining selection of design criteria for Fort Calhoun Station and provides the background data required to su bstantiate the proposed methods for controlling and assessing routine and acci dental releases of radioactive liquids and gases to the environment. Field progra ms to investigate site geology, seismology, and subterr anean hydrology have been compl eted.
The site of the power station is located at 96 degrees, 4 minut es and 39 seconds west longitude and 41 degrees, 31 minutes and 14 seconds north latit ude in Washington County, Nebraska, on the southwes t bank of the Missouri River a t river mile 646.0, approximately 2.4 miles south-southeast of the Chicago and Nort hwestern Railway bridge at Blair, Nebraska. The si te is 19.4 miles north-northwest of the intersection of 16th Street and Dodge Street in the city of Omaha. Meteorologi cally, hydrologically, geologically, and seismologically, this site is favorable for a nuclear power station.
The plant is designed, neverthele ss, so that there will be no u ncontrolled release of radioactive material during decommissioning operations. Radioactive effluents, both gases and liquids, will be released in a controlled manner to e nsure that they are below allowable limits.
Dames and Moore, consulting en gineers in the applied earth sciences, conducted investigations in site geology, seismology, subterranean hydrol ogy and meteorology.
- DSAR pages labeled as "ARCHIVED TEXT" are pages with text which is not revised or updated. Information on "ARCHIVED TEXT" pages is: A) of historical significant to the original licensing basis of the plant OR B) not meaningful to update.
DSAR-2.2 Page 1 of 4 FCSI Rev. 6 Information Use General Description of Site and Environs
- 2. SITE AND ENVIRONS
2.2 General Description of Site and Environs
The post permanent shutdown site extent is approximately 540 acres; approximately 445 acres of this area is on t he alluvial flood plain of the Missouri River, and the remainder is part of the bluff syst em on the southwest side of the river. An additional exclusion area of approximately 117 acres is included on the no rtheast bank of the river directly opposite the industrial area.
This additional exclusion area is provided by means of perpetua l easements which allows OPPD to restrict or prohi bit access should evacuation be necessary. More specifically on October 28, 1969, the owners of property locate d across the Missouri River from OPPD's Fort Calhoun fa cility executed easements in p erpetuity to the OPPD which consists of the following:
In consideration of the sum of One Dollar and other valuable consideration and of further agreements herein stat ed, the undersigned owners of rea l estate hereinafter described, their heirs, executors, administrators, successors and assigns, hereinafter called "Grantor" hereby grant and convey to the Omaha Public Power District, its successors and assigns, hereinaf ter called "District", a perpetual easement over, along and upon the following described a ccretion land owned by the Grantor and sometimes described as:
October 28, 1969 Agreement:
From the South 1/4 corner of Sec tion 17, Township 18 North, Ran ge 12 East of the 6th P.M., Washington County, Nebraska; thence North 00° 10'15" Wes t along the 1/4 line a distance of 2,088.27 feet to the point of beginning, s aid point being on the right bank of the designed channel of the Missouri River, thenc e continuing North 00° 10' 15" West a distance of 574. 52 feet to intersect the 1943 Nebraska-Iowa compact line; thence along the compact line as follows:
South 42°52' East a distance of 277.91 feet; South 47°12' East a distance of 476.86 feet; South 51°42' East a distance of 477.30 feet; South 55°42' East a distance of 479.83 feet; South 59°24' East a distance of 478.09 feet; South 64°14' East a distance of 481.84 feet; South 68°56'20" East a distance of 1,031.14 feet; South 62°14' East a distance of 468.62 feet; South 56°54' East a distance of 566.97 feet; South 51°30' East a distance of 366.47 feet; South 46°48' East a distance of 468.26 feet; South 41°07' East a distance of 282.40 feet;
DSAR-2.2 Page 2 of 4 FCSI Rev. 6 Information Use General Description of Site and Environs
To intersect the projected cent erline of Broadway Street in Old DeSoto Townsite; thence South 32° 35' West along sa id center line a distance of 925.90 feet to intersect the right bank of the designed channel of the Missouri River, t hence along said right bank as follows:
North 61°18' West a distance of 299.23 feet; North 59°40' West a distance of 500.00 feet; North 57°48' West a distance of 500.00 feet; North 56°20' West a distance of 500.00 feet; North 54°16' West a distance of 500.00 feet; North 52°30' West a distance of 500.00 feet; North 50°50' West a distance of 500.00 feet; North 49°00' West a distance of 500.00 feet; North 47°26' West a distance of 500.00 feet; North 44°50' West a distance of 500.00 feet; North 43°32' West a distance of 500.00 feet; North 41°30' West a distance of 234.74 feet;
To the point of beginning, lying in Sections 16, 17, 20 and 21, Township 18 North, Range 12 East of the 6th P.M., Washington County, Nebraska, and containing 109.26 acres, more or less.
"1. District shall have the right of ingress and egress along t he Grantor's property for any purpose necessary in maintaining the described property as an exclusion area, as later described."
"2. That part of the above descr ibed property is part of an exclusion area, now defined in the rules and regulat ions published by the United States Atomic Energy Commission, and more parti cularly by Title 10 - Atomic Energy, Part 100, 100.3 Definitions, (a) thereof, whi ch exclusion area is an inte gral part of the District's nuclear power plant site, the balance of which lies on the Nebraska side of the Missouri River opposite sa id property and in said County.
"3. The Grantor may make any u se of the above described propert y for their own benefit, except that the Grantor sha ll not make or permit any use or occupancy of said property, which shall be inconsistent with the maintenance of said property by District as such an exclusion area, or which shall be prohibited by any law or regulation now or hereafter enact ed by proper public authority, either governing or applicable to the use and main tenance of said property as an exclusion area as now or hereafter defined, or otherwise.
"4. Grantor specifically covenant s that no structure shall be b uilt and that any structure now existing upon said land shall not be occupied at any time by any person or persons."
DSAR-2.2 Page 3 of 4 FCSI Rev. 6 Information Use General Description of Site and Environs
"5. The District shall have the right to post said land for the purpose of securing the area as a minimum exclusion as defined and required by the Atomic Energy Commission.
"6. In the event that an emergen cy should occur in connection with the operation of District's power plant, which in District's opinion would requi re such action in the interest of public health and safety, District may, without not ice, take all necessary steps to exclude persons and property from within the posted area and to continue to exclude said persons and property until such tim e as said emergency has passed.
"7. The District shall reimburs e the Grantor for any crop damage that might occur as a result of the District's personnel or any of its representati ves entering upon the exclusion area property during an emergency.
"8. As further consideration for said easement, District shall, subject to the rights of the District created by this easement, quit-claim all right, ti tle and interest of ownership of the above described p roperty to Grantor herein.
"9. It is further agreed that Gr antor has lawful possession of said real estate, good, right and lawful authority to m ake said conveyance and that the ir heirs, executors, administrators, successors and assigns shall warrant and defend same and will indemnify and hold harmless to th e District forever against cla ims of all persons whomsoever in any way asserting any right, title or interest pr ior to or contrary to this conveyance.
In the opinion of counsel, paragr aphs 3 and 6 of these agreemen ts give OPPD ample legal authority to vacate said p roperty in the event that an em ergency should occur.
Figure 2.2-1 is an aerial photograph of the site and immediately surrounding area. A majority of the site is being farmed at the present time and it is planned that farming will continue. On-site farming consists primarily of grain. A pproximately 354 acres of the total approximately 540 acre s are under cultivation. The environmental monitoring program is performed in accordan ce with the ODCM. The area adj acent to the site is farm land and is sparsely popu lated. The nearest population ar ea is the town of Blair, Nebraska, approximately 3.4 mile s west northwest of the plant.
Figures 2.2-2 and 2.2-3 show the geographical features within 60 and 30 miles, respectively, of the site center; Figure 2.2-4 defines the mete s and bounds of the site.
DSAR-2.2 Page 2 of 4 FCSI Rev. 6 Information Use General Description of Site and Environs
Both private and commercial traf fic make use of U. S. Highway N o. 75 which forms the southwest boundary of the site and of the Missouri River which forms the northeast boundary. The highway is located at least 3,200 feet away, the refore, it is unlikely that an accident on this route would affect the station. The river traffic handles few hazardous materials. The danger to the station from air traffi c is considered minimal since the site is not located near landing patterns or runways of any large commercial or military airport facility.
DSAR-2.3 Page 1 of 1 FCSI Rev. 1 Information Use Topography
- 2. SITE AND ENVIRONS
ARCHIVED TEXT*
2.3 Topography
Figure 2.3-1 shows the topography within the site boundaries. The surface of the land, starting from the Missouri River at about elevation 997 feet ab ove mean sea level, falls to an old channel of the river before rising again to approximately 1,004 feet. Beyond this point, the land then gradua lly falls off to about 1,000 feet, rises again to approximately 1,020 feet, and then rises approximately 60 feet to a higher plateau at elevation 1,080 feet.
The Missouri River, which flows generally north to south, forms the northeast to southeast site boundary. This part of the river is referred to by the Corps of Engineers as the Blair Bend. The river lim its are under control of the Corps who have established a structure azimuth line which acts as another site boundary.
The site drainage development pr ogram provides proper drainage of the plant site and upstream properties. This system controls runoff of local precipitation; drainage empties into the Missouri River above the plant.
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2.4 Seismology
2.4.1 Seismic Geology and History
The site is underlain by 65 to 75 feet of unconsolidated alluvial and glacial deposits, largely loose to moder ately compact silty sand and deeper sands and gravels resting on sediment ary bedrock. The bedrock is gen erally flat with a westward dip.
A study of the possible existence of faults was made during the geologic investigation of the area. No faulting is apparent in the unconsolidated Pleistocene and recent sediment s of the Missouri River lowlands.
The closest known regional structures in the vicinity of the site are the Nehawka-Richfield Arch and t he La Platte Fault. The Nehawka-Richfield Arch extends from near Omaha-C ouncil Bluffs south and southwest for about 20 to 30 miles. There is no reco rd of movement of the fault in historic times, or any indication of activity in recent geologic time.
One of the major structural feat ures of the Nebraska-Iowa regio n is the Thurman-Wilson Fault which ext ends from south of Lincoln, Nebra ska, northeast for about 150 miles, almost to Des Moines, Iowa. The re is no record of movement of this fault in historic times.
2.4.2 Seismicity
The epicenters of several sho cks in the region with a Modified Mercalli Intensity greater than V are located in a zone south of Omaha p arallel to the Nemaha Uplift and the Abilene Ar ch. The epicenters fall betwee n the Salina Basin on the west and the Fore st City Basin on the east. Other activity is centered south and west of the Sioux Uplift, northwest of the s ite. Epicentral locations of all known earthquakes in the vicinity of the site with Modified Mercalli Intensity V were tabul ated in the Dames and Moore stud y referenced in Appendix B.
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A number of smaller earthquakes have been experienced in the Nebraska-Iowa region. The epicent ers of some of these shocks w ere along the Missouri, Platte and Solomon Rivers. Studies in Illinois indicate a possible relationship between river load and earthquake occurre nce, but no similar studies have been perfo rmed for this area. In general, because of poor records and lack of damage a ssociated with these smaller shocks, they are of little significance.
The significant shocks, i.e., thos e within 200 miles of the site, were tabulated.
On the basis of this history, i t is evident that the site lies in a region of infrequent seismic activity. Since the middle of the 19th centu ry, from the first historical record of earthquake occurrence in the area, only 12 shocks with epicentral Modified Mercalli Intensities of V or greater have o ccurred within 200 miles of the plant site. Thes e shocks were all of light to moderate intensity, with few of sufficient intensity to cause structural damage.
The largest earthquakes reported in the area had epicentral int ensities of Modified Mercalli VII. Three sho cks of this intensity originated within 200 miles of the site. Of these, the closest occurred in Novem ber 1877 near Lincoln, Nebraska, about 60 mile s from the site. Two shocks we re felt; the larger was felt over an elliptical area of approximately 140,000 square miles and was reported to have lasted 40 seconds. It is estimated that this shock had a magnitude of about 5 or sli ghtly higher on the Richter Sc ale.
A shock of Modified Mercalli Intensity VII occurred in April 18 67, near Manhattan, Kansas, about 170 miles from the site, and was felt over an area of 300,000 square miles. It is es timated that this shock had an intensity of about 5-1/2 on the Richter Scal e. Another shock of Modified Mer calli Intensity VII occurred in the same area in January 1906, and was percepti ble over an area of 10,000 square miles. The magnitude of this shock was p robably not more than 5 on the Richter Scale.
Only one earthquake of Modified Me rcalli Intensity VI has been reported within 200 miles of the site. It occurred in March 1935, near Tecumseh, Nebraska, and was felt in an ar ea over 50,000 square miles.
Eight earthquakes of Modified Mercalli Intensity V have been re ported within 200 miles of the site. The eart hquake with its epicenter nearest the site occurred in February 1910, near C olumbus, Nebraska, about 65 mi les from the site. No significant str uctural damage occurred.
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No damaging earthquakes have been r eported within 50 miles of the site.
While some of the regional shoc ks were undoubtedly felt in the locality of the site, no significant damage woul d be expected in even moderately well-built structures from a recurrence of these disturbances. It is prob able that the earthquake of November 1877, was fe lt at the site with an intensity of about Modified Mercalli V.
No major earthquake has occurred near the site. The closest ma jor shock was about 500 miles to the sout heast. In 1811 and 1812 a serie s of large shocks were experienced near New Madrid, Missouri, but these sh ocks bore no relation to the structural geology surrounding the site.
Therefore, on a historical basis, it would appear that the site will not experience damaging earthquake motion.
2.4.3 Seismic Design Criteria
Although on the basis of the hist ory of the region no significant earthquake ground motion is expected at t he site, occasional shocks along the Missouri River and a continuation of sho cks in the belt extending northward from the Abilene Arch to the Sioux Uplift could be postulated. For cons ervatism in the determination of appropriate seism ic criteria the proximity of a fault to the site is considered. On this basis, and in accordance with the recom mendations of the U.S. Coast and Geodetic Sur vey (USC&GS), site seismic criteria has been established.
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2.4.4 Design and Maximum Hypothetical Earthquakes
The following criteria was appl ied to components, structures an d equipment for the design earthquake and maxi mum hypothetical earthquake.
Design Earthquake (Operating Basis Earthquake)
All Class I components, systems and structures were designed so that the seismic stresses resulting from the response to a ground acceleration of 0.08g acting in the horizontal direction and two-thirds of 0.08 g acting in the vertical direction simultaneously, in combination with the prim ary steady state stresses, are maintained within th e allowable working stress limits accepted as good practice and, where applic able, set forth in the appropriate design standards; e.g., the ASME Boiler and Pressure Vessel Code, B31. 1 (1967) and B31.7 (1968) Codes for Pressu re Piping, ACI 318 Building Co de Requirements for Reinforced Conc rete, and AISC Specifications for the Design and Erection of Str uctural Steel for Buildings.
Maximum Hypothetical Earthquake (Design Basis Earthquake)
All Class I components, systems, structures (historic) and the ISFSI basemat (current) are designed so that sei smic stresses resulting from the response to a ground acceleration of 0.17g acting in the horizontal direction and two-thirds of 0.17g acting in t he vertical direction simultaneously, in combination with the primary stea dy state stresses, are limited so that the function of the component, system o r structure is not impaired in such a manner that function is prevented.
Structures no longer have any des ign features that are credited in any event analysis.
2.4.5 Conclusions
The site is subject to infrequen t slight ground motion from reg ional shocks.
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2.4.6 References
2.4.6.1 Dames and Moore letter, Report, Site Environmental Studies, Fort Calhoun Station - Unit No. 1, Near Fort Calhoun, Nebraska, Omaha Public Power District, dated March 30, 1967 (WIP8403)
2.4.6.2 Dames and Moore letter, Recommendation for Response Spectra to be Used with Ground Acceleration of 8 Percent and 17 Percent of Gravity, dated November 28, 1967 (WIP3618)
2.4.6.3 FCS-203087-USAR-2.4, Revision 1, USAR 2.4 Verification Summary Report (EC 67224)
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2.5 Meteorology
2.5.1 General Climate
The general climate is classified as continental, i.e., hotter in summer and colder in winter than in lands near the oc ean. Nebraska is located midwa y between two distinctive climatic zones, the humid east and the dry west (4). Thus, cyclic weather conditions representative of eit her zone, or combinations of bo th occur. Changes in weather result from the invasion of large masses of air with di ssimilar properties.
These air masses tend to get thei r characteristics from either the warm and humid south-southeast, the warm and dry southwest, the cool and dry north-northwest, or the cold continental polar air of the north (6). The region is also affected by many storms or cyclones (areas of low p ressure) which travel across the country, generally from west to east. Thus, peri odic and rapid changes in the weather are normal, especially in the winter(3).
2.5.2 Local Meteorology
Data from proximal long-term Nat ional Weather Service (NWS) Stations have been used to supplement the existing Fort Calhoun Station data in fo rmulating the description of the local meteorology.
2.5.2.1 Wind Direction and Speeds
A comparison of the climatological normals for the North Omaha NWS and five years of data from the For t Calhoun Station has been archi ved in Table 2.5-1. The elevation of t he North Omaha NWS wind sensor was 20 feet above ground during the fi ve-year period, while the elevation of the Fort Calhoun wind sensor was 10 meters above ground. Further discussion on the on-site data fo r wind direction and speed is presented below in Section 2.5.2.6.
The mean and maximum wind speeds recorded at Eppley Airfield and the North Omaha NWS for each month of the year are archived in Table 2.5-2.
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2.5.2.2 Precipitation
Monthly and annual normal and extreme precipitation amounts for Eppley Airfield and the North Omaha NWS are archived in Table 2.5-3. Average monthly precipitation follows a seasonal trend, reaching a maxi mum in May and a minimum in January. The mean number of days with measurable precipitation varies between a 12-day maximum in May to a 5-day minimum in November. The normals and extremes for amount s of snow and ice pellets (including sleet) for Eppley Airfield and the North Omaha NWS are archived in Table 2.5-4.
2.5.2.3 Temperatures
The monthly temperatures at Eppl ey Airfield and the North Omaha NWS for the period 1961 through 1990 ar e archived in Table 2.5-5. This table also shows the record high and re cord low temperatures recorded at both locations through 1990. Annual ext remes have been received at other locations in the Omaha vicinity a s follows: a record high of 1 14°F in July, 1936, and a record low of -32°F in January, 1885 (4).
Monthly and annual temper ature normals for Eppley Airfield, North Omaha NWS and Blair are archived in Table 2.5-6(4). These show close agreement.
2.5.2.4 Relative Humidity
The average relative humidity va lues for Eppley Airfield, the N orth Omaha NWS, and the Fort Calhoun Station for four times of the day are archived in Table 2.5-7. The mean number o f days with heavy fog (visibility 3 mile or less) at Eppley Airfield and the North Omaha NWS are archive d in Table 2.5-8.
2.5.2.5 Thunderstorms
The mean number of days with thunder storms at Eppley Airfield and the North Omaha NWS are archived in Table 2.5-9. A maximum frequen cy of approximately 9.5 thunderstorms o ccur during the month of June. This decreases to a minimum of approx imately 0.1 thunderstorms durin g the month of January.
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2.5.2.6 Atmospheric Stability
Wind direction and speed data ar e presented in relative frequen cy distribution (in percent) by stability classes.
2.5.2.7 Topographical Descrip tion and Its Influence on Site Met eorology
The terrain in the vicinity of Fort Calhoun Station is generall y flat from the north, northeast, east and southeas t sectors, with an elevation of approximately 1000 feet above mean sea level (msl), for a radius of at least 10 miles. This terrain i s generally the flood plain of t he Missouri River. Terrain in the remaining sectors, south-southeast throu gh west-northwest, show much greater relief from the low lying bluffs, cut by numerous ravines, with elevations of about 1300 feet above msl. These bluffs extend along the wester n bank of the Missouri River, whi ch runs generally from the northwest to th e southeast, and come within about one mile of the Fort Calhoun Stati on in the south through west-sout hwest sectors.
Two unusual effects in the site meteorology are: 1) under very light westerly wind flow there is a possibility of weak drainage flow off the bluffs to the west toward the river, and 2) there will possibly be a s lowing down of weak winds as air flows acro ss the river from east to west a nd meets the rising terrain to the west. H owever, neither of these effe cts are regarded as significant in their influence on site meteorology and should not, under most synoptic weather ty pes, severely skew the stron g measures of covariation (+0.75 to +1.00) which exist between th e site and other meteorological stations.
2.5.2.8 Tornadoes
Amendment 272(37) revised the DBT and associated tornado missiles for Fort Calhoun Station (FCS) to t hat defined in Regulatory Guide (RG) 1.76, Revision 1(38). This ensures that designated SSCs are adequately protected from the DBT and a ssociated tornado missiles.
The physical properties and ve locities of tornado generated mis siles are described in Regulatory Gu ide 1.76, Revision 1.
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Table 2.5 Climatological Normals, Comparison of North Omaha NWS with Fort Calhoun Station
WIND DIRECTION (PERCENT) WIND SPEED (MPH)
Wind North Omaha NWS Fort Calhoun North Omaha NWS Fort Calhoun Direction (1985-1989) (1985-1989) (1985-1989) (1985-1989)
NNE 3.8 2.6 8.2 4.9 NE 3.3 2.4 6.9 4.6 ENE 3.2 2.4 6.5 4.5 E 3.1 3.1 6.7 5.0 ESE 5.4 5.7 6.8 5.4 SE 7.1 9.0 7.8 6.8 SSE 10.0 10.2 9.9 8.9 S 10.8 10.1 10.4 9.5 SSW 9.1 7.2 9.5 9.3 SW 4.3 3.7 8.5 7.5 WSW 2.4 3.0 7.2 5.5 W 3.9 4.5 7.7 4.4 WNW 5.3 7.6 10.1 4.6 NW 8.6 10.7 12.9 6.6 NNW 6.8 9.4 12.8 6.5 N 13.0 5.5 8.0 5.9 Missing --- 2.9 --- 2.9 Average --- --- 8.7 6.3
NOTE: The wind speeds at the North Oma ha NWS were recorded 20 feet above ground level, and the wind speeds at Fort Calhoun Stat ion were recorded at 10 met ers, above ground level. Data obtained from the Local Climatol ogical Data; see References 4 a nd 5.
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2.6 Geology
2.6.1 Physiography
Topographically, the site is part o f the Missouri River bottom land, which is a nearly level plain about 15 mile s wide at Blair, 8 miles wide at the site and narrowing to 3 miles wide in the vicinity of Omaha-Council Bluf fs. The elevation of this plain averages about 1,000 feet above mean se a level at the site.
2.6.2 Regional Geology
The principal geologic features of the region include a 100 to 200 foot thickness of soil deposited by a glacial action, streams, and wind, underlain by sedimentary bedrock of 500 to 2,500 feet in thickness consis ting primarily of limestone, shale, and sandstone. There are no bedrock outcr ops on the site, but there are exposures wi thin three and five miles from the site at two limestone quarries.
2.6.3 Regional Structure
With few exceptions, the bedrock formations of eastern Nebraska and western Iowa are nearly flat w ith a gradual westward dip. This regional attitude is modified by several well defined faults, basins, and arches.
However, none of these structural features occurs in the vicini ty of the site.
The dominant structural features of the Nebraska-Iowa region include the Thurman-Wilson Fault which ext ends from 12 miles southeast of L incoln, Nebraska, northeast for approxim ately 150 miles, almost to Des Moines, Iowa. It lies approximately 55 miles southeast of the site; the upthrown side is on the northwest.
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The Forest City Basin which is approximately 100 miles southeas t of the Omaha area lies along the downt hrown east flank of the Nemaha R idge, a very sharp buried uplift extending from near Lincoln, Nebraska, south southwest across Kansas and into northern Oklahoma. The depth to the Precambrian crystalline granite core is about 400 to 500 feet a t the Nebraska-Kansas line, near the Mi ssouri Border. The Salina Bas in and its northern extension, the Central N ebraska Basin are approximatel y 150 to 200 miles southwest of Omaha. In northern Kansas, the Abilene Arch lies between the Salina Basin and Nemaha Uplift. In southeast South Dakota, approximately 125 miles north of the site, is the Sioux Uplift, and southwest of the Sioux Uplift, in Western Nebraska, are the Siouxana Arch and the Cambridge Arch.
2.6.4 Areal Structure
The structures nearest the site are the Nehawka-Richfield Arch and the La Platte Fault. The arch extends from near Omaha south about 20 to 30 miles into Sarpy and Cass Counties, Nebraska. Deep well records indi cate that a limb of this uplift may extend nor thward into the Omaha area an d possibly farther.
The closest known regional fault is the La Platte Fault which c uts across the Nehawka-Richfield Arch in the lower Platte River Valley. It ap parently crosses the Thurman-Wilson Faul t some 60 miles south of the sit e. This nearly vertical fault has a maxim um upthrow of about 50 feet on the west.
There is no record of movement of the fault in historic times, nor any indication of activity in recent geologic time.
2.6.5 Geologic History
The early Paleozoic Era in western Iowa and eastern Nebraska wa s marked by long periods of marine inundati on which resulted in deposition of thick beds of limestone, dolomite, shal e, and sandstone. In later Pa leozoic time, shorter and more frequent periods of alternating marine and con tinental deposition occurred resulting in the production of thin coal be ds and layers of shale, limestone, and some sandstones.
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The major tectonic features o f the mid-continent region began t o develop late in the Paleozoic Era, and probably most of t he important structural features of the Nebraska Iowa Missouri River Valley area had already dev eloped or were developing by the end of the Permian period. From the end of the Permian to the beginning of the Cretaceous, there is no depositional record to correlate with structural m ovements. The undisturbed beds o f the Cretaceous Dakota formation indicate the lack of tectonic activ ity since that time.
During the Pleistocene period, w hen the interior of the continent was covered by continental glaciers, Nebraska was occupied by only the firs t two of four major ice sheets. The first of these resulted in a general leveling and deposition of till. This was followed by alluvial deposition during the inter-glacial stage, and depositi on of additional till and outwash by subsequent glaciation. Ice damage to streams during this perio d resulted further in a deposition of lacustr ine sands and gravels. Nebraska and western Iowa were not covered by later ice sheets, but during the retreat and advance of these ice sheets near by, windblown deposits of fine sand and silt accumulated to thicknesses o f as much as 100 feet. These depos its, known as loess, form the steep sided hi lls and bluffs of eastern Nebr aska and western Iowa. Recent erosion and alluvial deposition have alte red the landscape to its present form.
2.6.6 Glacial History of the Missouri Valley
At the beginning of the Pleistoce ne period, the Missouri River Valley and its main tributaries were establishe d in their approximate present positions.
Subsequently under successive glacial movements, the valleys we re filled and re-opened several times. Duri ng this period, the Peorian loess was deposited on the terraces and adjacent uplands. It is probable that only the upper part of the alluvium in the Missouri River Valley is actu ally of recent age and that deeper deposits are mo stly of Pleistocene age.
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2.6.7 Site Geology
Unconsolidated sediments at the plant site generally range from 65 to 75 feet in thickness. The soils are typi cally interstratified and cross-bedded. The beds change facies or grade latera lly so rapidly that no bed lithologic correlation is possible from bor ing to boring. The boring data indicate that the upper 20 to 50 feet of soil are predominately silty sands, and the lower beds consist of fine sands with occasional interbedded lenses of gravel.
The bedrock beneath the site lies between 65 and 75 feet below the surface.
The maximum relief of the bedrock surface in the site area is i n the order of 13 feet. Some borings indicate a thin layer of clay on top of bedrock, others a soft to hard shale up to a t hickness of seven feet. The bedr ock consists of various types of limestone formations.
2.6.8 Conclusions
The bedrock beneath the site provi des suitable support for the plant structures. There is no geologic feature of the site or surrou nding area which adversely affects the use of the site for a nuclear power plant.
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2.7 Hydrology
2.7.1 Surface Drainage
2.7.1.1 General
The plant site is bounded on t he northeast and southeast by a portion of Blair Bend of the Miss ouri River. The Corps maintains river structures to prevent further meandering of the channel within the alluvial flood plain; t he structures take the form of pile dikes and bank revetments.
There are six dams upstream of the plant site that control the river flow. There are no dams, locks, o r similar structures on the Missouri downstream of the plant site.
The Corps of Engineers has stated (Reference 12) that sedimentation will not affect the flood control capability of t he reservoir system for 200 years or more.
2.7.1.2 River Stage and Flow
The site has the following flood levels (Reference 21 and 22).
Flood Elevation (ft) Notes 1% (100 yr.) 1001.3 Below site grade 0.1% (1000 yr.) 1004.2 Site Grade 1950 Actual Flood 1007 Top of water tight foundations Maximum Probable 1009.3 Rainstorm below Gavins Point Dam Oahe or Fort Randall Dam 1014 Failure + 1009.3 flood
It is estimated that the large flows would take about two days to travel from Gavins Point to t he Fort Calhoun site. Rainfall sufficient to cause an appreciable flood would have to be heavy and occur over an extensive area.
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2.7.2 Ground Water
2.7.2.1 General
Ground water is from two sources. The first is the Missouri Ri ver Valley, where ample ground water is obtained from the Pleistocene Valley fill and alluvial sand and gravels. The wat er table ranges from 2 to 17 feet below the surface, and coincides with the elevation of the rive r in the bottom land adjacent to the river. The second source of grou nd water are the terraces and loess hill upland regions. In these areas, the majority of wel ls are drilled or dug and provide water mainly from the glacial sands and gravels.
The movement of ground water under the uplands is toward and into the Missouri River trench. The occurrence of springs alon g the base of the bluff confirms th e movement of ground water fro m the hills to the river.
The development and use of ground water adjacent to the Missouri River and downstream of t he plant will be monitored as a result of normal coordination with state and local authorities. The need for an evaluation of potential effects on these wells will be determined periodically.
2.7.2.2 Site Water Table and Transmissibility
Water levels taken in a series o f borings drilled during July a nd August, 1966, reveal that the ground water levels at the site v aried from elevations 993.7 to 992.4 feet, while the river levels rec orded during this same period ranged from elevations 993.2 to 992.4 feet. Ground water levels vary with changes in the river level. The rate of ground water fl ow in the alluvial soils varies with the permeability. However, rate of flow is very low, because of the low gradients, and again, is towa rd the river. The coefficient of permeability varied from about one-half to three feet per day i n the upper sandy silt and silty sand. In the lower fine-to-coarse s and and gravel, coefficients of permeability as high as 20 feet per day were measured.
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A pumping test was conducted to evaluate the gross permeability and transmissibility characteristi cs of the alluvial deposits. At a pumping rate of about 700 gallons per minute, the maximum drawdown in the well was 21 feet. The ultimate radius of influence of the test well wa s between 1,300 and 1,800 feet. T he gross permeability of the deep wa ter bearing sands and gravels amounts to 1,100 gallons per day per square foot. The soils are in direct hydrologic connection with the Missouri River.
The hydrologic characteristics of the site and surrounding area and the pattern of the ground water are such that accidental discharge of radioactive fluids into the ground would have no adverse effects on existing or potential ground water users. S uch fluids would percolate slowly in the direction of the Missouri River.
Thus, hydrological conditions are favorable for the location an d operation of a nuclear facility.
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Thirteen groundwater monitoring we lls (both shallow and deep) were installed at FCS from August 15 through August 27, 2007.
Hydro geological information wa s collected and evaluated by Terracon Consultants Incorporated. A second review and evaluation was performed by R adiation Safety and Control Services incorporated. Soils observed during the advancement o f the well borings consisted primarily of unconsolidated lean clay, silt, and sand. These material s appear to be representative of Missouri River alluvium, although so me relatively shallow soils may represent construction fill. The unconsolidated sediments that underlie the plant site can be grouped into two units: an upper fine grained sandy clay with sil t approximately 20 to 50 feet t hick, and an underlying fine to coarse sand with some gravel. This lower unit extends to the relati vely flat-lying carbonate bedro ck surface at a depth of approximat ely 70 to 75 feet below grade.
Both unconsolidated units are water bearing, but the deeper uni t has higher hydraulic conductivity. The depth to ground water ranges about 15 to 20 feet below ground surface. The resulting hydraulic gradient within the unconsolidated sediments is relatively flat. This low hy draulic gradient, combined with moderate hydraulic conductivity of the fine grained alluvial material, results in relatively slow ground water velocity bene ath the site. Water table and potent iometric surface contour maps constructed based upon water le vels measured in the new wells indicate groundwater flow directi ons different from the directions presumed prior to construction of the wells. Initially two conditions at FCS produced groundwater fl ow gradients opposite to those originally presumed. The first condition that affected groundwa ter flow was the pumping of the ground water supply well located at the Northwest corner of the old warehouse pad however, this wel l no longer exists.
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The second condition impacting groundwater flows, which remains applicable, is bank recharge. The Missouri River is in hydraulic connection with the groundwater in the alluvial aquifer.
During periods of relatively high river stage, which occur gene rally from April through September when precipitation is greatest, ri ver water recharges the nearby allu vial aquifer and induces groundwater flow gradients outward from the river channel.
These gradients reverse seasona lly, during periods of lower riv er stage. Groundwater flows at the landfill site were calculated at velocities of less than 0.8 ft day, toward or away from the river, based on river stage.
In summation, the setting of t he plant appears to be within a dynamic groundwater environmen t influenced by pumping of the ground water supply well, river level, and seasonal amounts of precipitation. Consequently, the Site Groundwater Protection Program (ODCM) accounts for pot ential variations in flow directions present within the industrial area.
2.7.2.3 Well Water Analyses
Samples were taken from the te st well on the plant site at eight-hour intervals during August, 1966. The chemical analyses of these samples are summarized in Table 2.7-4. Throughout the sampling period, the well-water t emperature was 54°F; no large seasonal temperature variations can be expected. Other samples were taken at bore holes and subsequently analyzed. However, the analyses reported in Table 2. 7-4 are typical and adequately describe the ground water.
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- 2. SITE AND ENVIRONS
2.8 Demography
The plant site is located on the alluvial plain of the Missouri River in a predominantly agricultural region roughly ten mi les north of the Omaha metrop olitan area.
There are no residences within one-half mile of the reactor loc ation. The seven nearest residences are from 3,000 to 4,000 feet distant. These are located generally along Highway 75, the western boundary of the site. There are no schools, hospitals, prisons, or motels/hotels in the immediate vicinity of the site. An industrial park is located north of the plant proper ty. Industries include a large corn processing facility, agricultural fertilizer storage fa cilities and various other light industrial plants.
The DeSoto National Wildlife Refuge occupies approximately 7,82 1 acres east of the plant site. This area is open to the public for day use year r ound. Visitors to the refuge generally use areas from t wo to five miles from the plant. Estimates by the U.S. Fish and Wildlife Service place annual usage of the facility at approximately 120,000 for the Visitors Center and 400,000 for the refuge. Th e expected maximum daily usage of the facility has been placed at 2500 visitors fo r a Winter weekday and 5000 on a Summer weekend. The Boyer Chute Federal Recreation Area is a day use facility occupying approximately 2000 acres southeast of the pl ant site. Visitors to the recreation area generally use are as seven to ten miles from the plant. The estimates for annual usage of this facility is approximately 50,000 visitors.
The State of Nebraska operates t he Fort Atkinson State Historic Park 5.5 miles southeast of the plant site. This day use facility is mostly s easonal and estimates place annual usage at 60,000. The State of Iowa maintains Wilson Island State Park with 275 camping spaces south of the DeSoto National Wildlife R efuge and four miles southeast of the plant site. The estimates for usage of this f acility range from 500 on winter weekday to 1000 on a summer weekend.
Two private facilities lie to t he north of the plant along the Missouri River. The Cottonwood Cove Marina & RV Res ort is located approximately 4.5 miles from the plant. Estimates place summer weekend usage at 200 people. River View Park Resort & Marina is a private c ampground lying directly to the s outh of Cottonwood Marina and ranging from 4 to 4.5 m iles from the plant. The campground has approximately 235 campsites and is open from April to October.
The nearest municipality is the city of Blair, about three miles northwest, with a population of 7,990 per the 2010 census.
Fort Calhoun is about five mil es southeast of the facility. Th e 2010 census reported a population of 908 in Fort Calhoun and 167 in Kennard Village, a bout seven miles from the plant site. The 2010 populatio n of Washington County is 20,234.
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Missouri Valley, Iowa, about 11 miles east, has a 2010 population of 2,838 as compared to the 2000 population of 2,982. In St. Johns Township, of which the city is a part, population has steadily decreased.
The Omaha metropolitan area incl udes the cities of Omaha and Co uncil Bluffs, Iowa, and the adjoining areas of Dougl as, Washington, and Sarpy Count ies, Nebraska, and Pottawattamie County, Iowa. The area lies 10 to 25 miles south east of the site, with the main concentration of populat ion beyond the 15-mile radius. Population studies have been undertaken by the Metropolitan Area Planning Agency. Population information is as follows:
Omaha City Metropolitan Area
1960 U.S. Census 301,598 457,873 1970 U.S. Census 346,929 542,646 1980 U.S. Census 313,911 569,614 1990 U.S. Census 335,795 618,262 2000 U.S. Census 390,007 707,211 2010 U.S. Census 408,958 789,342
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The U.S. Census data shows an increase in population in the Oma ha metropolitan area and in most of the nearby cit ies but a decrease in the rural and farm population.
While it is probable that the ar ea around the plant site outside of the Omaha metropolitan area will remain largely agricultural and that the population will increase slowly, a general decline of the rural population will continue, reflecting the movement of people into towns and cities. The expansion of the Omaha me tropolitan area has been generally south and westward, c oinciding with the intersta te highway. It is expected that future growth o f the metropolitan area will conti nue south and west and also northwestward. Thus it is probable that the area surround ing the plant site will continue to remain largely agricultural.
DSAR-2.9 Page 1 of 5 FCSI Rev. 1 Information Use Land Use
- 2. SITE AND ENVIRONS
2.9 Land Use
2.9.1 General
The land within 40 miles of the plant site is used primarily for farming with the exception of the heavily industr ialized cities of Omaha and Fremont, Nebraska, and Council Bluffs, Iowa.
2.9.2 Agronomy
Table 2.9-1 describes the use o f agricultural land in Nebraska of counties within 10 miles of the plant site. Table 2.9-2 summarizes simi lar information for Iowa. The data are present ed on a county basis for each of the two counties in Nebraska and the two counties in Iowa within 10 miles of the site. The data source for both t ables is the United States Census of Agriculture, (2002) and the U.S. Census Bureau "State and Count y QuickFacts" (assorted years).
2.9.3 Industry
The major industrial centers wi thin 40 miles of the plant site are Omaha and Fremont, Nebraska, and Council Bluffs, Iowa. The major industr ies within a 10 mile radius of the plant site ar e listed in Table 2.9-3 with firm name, product, number of employees, and direction and distance from t he plant site. The sources for information presented in this table are the Nebraska Department of Economic Development Web Site, www.neded.org (Nebraska Manufacturers Arranged by Comm unity, January 2004) and the Blai r Area Chamber of Commerce, Blair, Nebraska (2006).
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Table 2.9 Agricultural Land Use in Nebraska of Counties Within 10 miles of the Fort Calhoun Station
County Douglas Washington
Number of Farms 361 760 Land Area in county, acres 211,827 249,914 Land Area in Farms, acres 94,613 242,419 Land Area in Farms, % 44.7 97.0
Land Use
Total Cropland, acres 83,096 211,493 Total Harvested Cropland, acres 76,336 194,705
Principal Crops
Corn for grain, acres 36,520 87,038 Wheat for Grain, acres 121 379 Oats for Grain, acres 233 479 Soybeans for Beans, acres 32,242 87,154 Forage, All Hay and Haylage, acres 5,233 18,689
Livestock
Cattle and Calves Inventory, number 7,357 32,454 Hogs and Pigs Inventory, number 2,859 42,299
Value of Agricultural Products Sold
Market Value of Products Sold, $ 35,537,000 85,734,000 Crops, $ 21,957,000 39,512,000 Livestock, Poultry, and Their Products, $ 13,580,000 46,221,000
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Table 2.9 Agricultural Land Use In Iowa of Counties Within 10 Miles of the Fort Calhoun Station
County Harrison Pottawattamie
Number of Farms 828 1,255 Land Area in county, acres 445,901 610,726 Land Area in Farms, acres 428,235 540,288 Land Area in Farms, % 96.0 88.5
Land Use
Total Cropland, acres 367,561 487,579 Total Harvested Cropland, acres 337,240 442,923
Principal Crops
Corn for grain, acres 168,935 218,112 Wheat for Grain, acres 329 91 Oats for Grain, acres 328 1,220 Soybeans for Beans, acres 156,052 205,719 Forage, All Hay and Haylage, acres 10,269 16,632
Livestock
Cattle and Calves Inventory, number 33,874 63,358 Hogs and Pigs Inventory, number 42,545 55,626
Value of Agricultural Products Sold
Market Value of Products Sold, $ 111,191,000 163,267,000 Crops, $ 84,811,000 106,911,000 Livestock, Poultry, and Their Products, $ 26,380,000 56,356,0 00
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2.9.4 Wildlife
2.9.4.1 Fish
The Missouri River supports over fifty different species of fis h.
The more numerous fishes are m innows, carp, gizzard shad, goldeye and catfishes. There are approximately 160 licensed commercial fishermen who operat e in the Sioux City to Platte River area of the Missouri River and their primary catch is in carp and catfish. There is an increas ing number of sport fishermen on the river, their largest catch being in carp and catfish.
2.9.4.2 Animals and Birds
Deer, rabbits, squirrels, pheasant s and quail are hunted in the area of the plant site. The Desoto National Wildlife Refuge is in a migratory waterfowl flyway and has maximum populations of mallard ducks, snow and blue g eese, and Canada geese in the spring and fall. Fur-bearing animals such as the muskrat, beav er, and mink also inhabit the region of the site.
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- 2. SITE AND ENVIRONS
2.10 Environmental Radiation Monitoring
2.10.1 General
The environmental monitoring pr ogram is designed to provide dat a concerning the types and amount of radioactivity present in the environment of the Fort Calhoun Station. The preoperational program was de signed to assess environmental conditions bef ore the arrival of fuel. Su bsequent analysis during the decommissioning program is being used to de monstrate that plant decommissioning effo rts do not have a significant ef fect on the environment. This program is des cribed and implemented in accordance with the ODCM.
ARCHIVED TEXT
2.10.2 Preoperational Survey Program
The purpose of the preoperational survey program was to determi ne the base level of existing radioactivity to which future analytical results can be compared; the program extended fo r four consecutive years. The monitoring program was developed in cooper ation with the regulatory agenci es of Nebraska and Iowa and the Fish and Wildlife Service of the United States Government Department o f the Interior.
Specific radionuclide and/or gro ss radioactivity analyses were performed on the selected samples. Table 2.10-1 summarizes the types of sam ples and analyses included in the pr eoperational program.
Table 2.10 Gross and Specific Radionuclide Analyses Gross Gross -Spec Sr-90 H-3 K-40 I-131 Cs-137 Surface Water X X X X X Well Water X X X X X Mud and Silt X X X Aquatic Biota X X X X Milk X X X X X X Vegetation X X X X X Air Particulate X X X Wildlife X X X X X
- DSAR 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.
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ARCHIVED TEXT
2.10.3 Preoperation Survey Results
2.10.3.1 Trial Monitoring Period
The first nine months of the pr ogram, starting in September 196 8, was a trial period designed to v erify the availability of adequate sample types and to select and te st analytical procedures.
Results obtained during the tria l period were preliminary. The trial period results are included in th is report because they describ e the background conditions and illustrated the preoperational surveillance program. No significant peaks were evident in any of the gamma scans performed on samples.
Water
Surface water samples were col lected at six stations: one at t he Desoto National Wildlife Refuge Lake area and five from the Mis souri River at sampling stations located above and below the plant si te, including the municipal water supplies at Omaha, Nebraska, and Council Bluffs, Iowa.
Well waters were sampled at elev en wells within a four-mile radius of the plant. Table 2.10-2 is a summa ry of the surface and well wa ter data.
Table 2.10 Average Radioactiv ity of Well and Surface Waters November 1968 - June 1969 Activity Concentration, pc/liter Well Water Surface Water (11 Samples) (6 Samples)
Alpha 0.0 0.7 Beta-Gamma 10.9 26.2 Strontium 90 0.1 1.3 Tritium 550 1000
- DSAR 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.
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ARCHIVED TEXT Mud and Silt
Mud and silt samples were ta ken from the Missouri River downstream of the plant. No alpha radiation was detectable; th e analysis for beta-gamma gross activity showed 18 picocuries per kilogram for the mud and silt.
Aquatic Biota
The basis for sampling aquatic biota was formulated from specif ic recommendations of the Nebraska Game, Forestation and Parks Commission. The fish species selected were chosen because their food habits include organi sms within many of the lower trophic levels and because they a re important from the standpoint of sport and commercial fishing.
The food habits and radioactivity o f the fish samples, which were taken from the Missouri River, are shown in Table 2.10-3.
Table 2.10 Food Habits and R adioactivity of Missouri River Fish October 1968 - June 1969 Specie Food Habits (-)-(K-40) K-40 Sr-90 nc/kg nc/kg pc/kg Flathead Catfish # Fish 3.2 2.6 0.0 Flathead Catfish
- Insects 7.8 10.6 0.0 Channel Catfish # Fish 3.2 6.7 100.00 Channel Catfish
- Insects 1.6 6.5 0.0 Carp Omnivorous 8.5 8.4 24.0 Paddlefish Plankton --- --- ---
Buffalo Algae and Insects 4.6 9.5 0.0 Shad Plankton --- --- ---
- Greater than 10 inches long
- Less than 10 inches long
- DSAR 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.
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ARCHIVED TEXT The paddlefish is difficult to c ollect but was included where possible because it feeds exclu sively on plankton; the shad and buffalo with food habits similar to the paddlefish are acceptable substitutes. During its lifetime, the flathead catfish remains within approximately one mile of its ori gin and is therefore, sampled downstream of the plant site. Catfish and carp are the most abundant of the commercial fish varieties.
The Missouri River has a sand bo ttom which moves with the water flow; therefore, benthos and other bottom organisms are extremely scarce. Joint effor ts with the Nebraska Game Commission to obtain sufficient s amples for analysis of periphyton have failed; a cooperative study c ontinues as a separate project.
Milk
Milk from large Grade A milk pr oducers in the local milk shed was sampled in cooperation with the Omaha Douglas County Health Department. The dairy herds of these Grade A milk producers ar e located downwind of the plant s ite. Radioactivity levels in the milk samples analyzed are shown in Table 2.10-4.
Table 2.10 Radioactivity in Milk January - March, 1969 Fresh Milk Preserved Milk I-131 Cs-137 (-)-(K-40) K-40 Sr-90 pc/1 pc/1 nc/1 nc/1 pc/gm Calcium Farm A 0 0 0.53 0.73 1.0 Farm B 0 0 0.81 0.74 1.0 Farm C 0 0 0.71 0.78 0.9
- DSAR 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.
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ARCHIVED TEXT Vegetation
Foods normally consumed by the general population constitute the vegetation samples. Six sta tions with a total of ten varieties of food were sampled during t he 1968 growing season. The variation in analytical results is shown in Table 2.10-5.
Table 2.10 Radioactivity in Vegetation October, 1968 Maximum Minimum nc/kg nc/kg Alpha 0.0 0.0 Beta-Gamma minus K-40 14.0 0.3 K-40 39.2 3.2 Sr-90 0.143 0.000 H-3 6 0
Air Particulate
Airborne particulate matter wa s collected at the plant site on 0.45 micron pore size filters; t he filter was removed from the sampler and counted after the ra dioactivity had decayed for at least seventy-two hours. The air volume passed through the fil ter was approximately 1,000 cubic feet. None of the 32 samples analyzed showed any indication o f alpha activity; the average beta-gamma concentration was 0.26 pc/m 3 with a maximum of 0.78 pc/m3 and a minimum of 0.08 pc/m 3.
Background radiation readings measured with a Geiger-Mueller survey meter at sixteen stations around the plant site were all in the 0.00-0.02 mr/hr range. Resul ts of the combination film badge-thermoluminescent dosimeter s, at eleven stations, were all less than 30 mrem per quarter.
Wildlife
A wild rabbit sample was included to represent wildlife normall y consumed in the area. These rabbits are free to wander, but th ey normally remain in the immediat e vicinity. The radioactive con tent was 20 picocuries of Strontium-90 per gram of calcium in the femur and no iodine-131 was det ectable in the thyroid.
- DSAR 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.
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ARCHIVED TEXT
2.10.3.2 Preoperational Monitoring Period
Following the trial period, the formal preoperational surveilla nce monitoring program was started in July, 1969, and continued for three years. This formal preoper ational survey was an intensif ied continuation of the trial period already discussed. The program included soil samples and vegetat ion which are stored for possible future analyses.
The preoperational program resul ts were documented for future reference and comparison; they defined the pre-operational background levels. Future backg round conditions may vary due to influences such as fallout fr om nuclear testing; however, th e continuing environmental survey programs will provide adequate data to document changes in the background conditions.
- DSAR 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.
2.10.4 Radiological Environmental Monitoring Program (REMP)
The purpose of the REMP (ODCM Sec tion 5.0) is to provide public assurance that the Fort Calhoun c ontribution to naturally existing radioactivity is negligible. The program veri fies the effectiveness of the w aste disposal systems and radiological safet y procedures incorporated in the plant.
The Offsite Dose Calculation Manual contains a list of the current types of samples being taken, their location, and sampling frequency.
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- 2. SITE AND ENVIRONS
2.11 Section 2 References
- 1. Letter from R. G. Burnett, U. S. Army Corps of Engineers to E. G. Drdla, OPPD; dated November 11, 1971
- 2. Nebraska, A Survey of Univers al Knowledge, Volume 16, Encycl opedia Britannica, Inc., Chicago, Illinois, 1959
- 3. Climatography of the United St ates No. 60-25, Climates of th e States, Nebraska, U. S. Department of Commerce, Weather Bureau, 1959
- 4. Local Climatological Data, Annual Summary with Comparative D ata for Omaha (North), Nebraska 1990, U. S. D epartment of Commerce, NOAA, NCD C, Asheville, NC
- 5. Local Climatological Data Annual Summary with Comparative Da ta for Omaha (Eppley Airfield) Nebraska, U.S. Department of Commerce, NCAA, NCDC, Asheville, NC
- 6. Krist, James G. Establishing Meteorological Correlations Bet ween the North Omaha National Weather Service S tation and the Fort Calhoun Nuclear Station, Master's Thesis, The University of Nebraska - Omaha, October 19 91
- 7. Lundlum, David M., Weather Rec ord Book, United States and Canada, Weatherwise, Inc., Princeton, New Jersey, 1971
- 8. Climatography of the United St ates, No. 81 (Nebraska), Month ly Normals of Temperature, Precipitation and H eating and Cooling Degrees Days 1941-70, U. S. Department of Commerce, NOAA, August, 1973
- 9. DELETED
- 10. Sagendorf, J. F., A Program for Evaluating Atmospheric Disp ersion from a Nuclear Power Station, NOAA Tech. Memo. ERL-ARL-42, 1974
- 11. Yanskey, G. R. et al., Climatography of National Reactor Te sting Station, Idaho Operations Office, USAEC, IDO-12048, 1966
- 12. Private Communication, Hipp, C. L., Department of the Army, Army Corps of Engineers, Omaha District, to De la Cruz, F., GHD&R, February 7,1967.
(WIP No. 2270).
- 13. DELETED
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- 14. Local Climatological Data, Annual Summary, Omaha (Eppley Ai rfield), Nebraska, 1985, NOAA, NCDC, Asheville, NC
- 15. Local Climatological Data, Monthly, Omaha (Eppley Airfield), Nebraska, 1982, 1983 and 1984, NOAA, NCDC, Asheville, NC
- 16. DELETED
- 17. DELETED
- 18. DELETED
- 19. Review of Ground Water Protec tion Program at the Fort Calhoun Nuclear Power Station, TSD#08-015, Revision 01, May 30, 2008
- 20. DELETED
- 21. Letter from Charles L. Hipp, U.S. Army Corps of Engineers, to T.E. Short, OPPD, December 12, 1967. (WIP No. 19888)
- 22. DELETED
- 23. Safety Evaluation of the Om aha Public Power District Fort C alhoun Station, Unit No. 1, Issue Date: August 9, 1973, Suppl. 1 - April 23, 1973
- 24. DELETED
- 25. Environmental Statement Relat ed to Operation of Fort Calhoun Station Unit 1, August 1972
- 26. Proposed Revision 1 to Regulatory Guide 1.23, Meteorologica l Programs in Support of Nuclear Power Plant, dated September 1980
- 27. DELETED
- 28. NUREG-0654, Rev 1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants, dated October 1980
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- 29. DELETED
- 30. DELETED
- 31. DELETED
- 32. DELETED
- 33. DELETED
- 34. DELETED
- 35. DELETED
- 36. DELETED
- 37. DELETED
- 38. DELETED
- 39. DELETED
- 40. DELETED
- 41. DELETED
- 42. DELETED
- 43. DELETED
- 44. DELETED
- 45. DELETED
- 46. DELETED
- 47. DELETED
- 48. DELETED
- 49. Memo, KLD Engineering, P.C., 50 Mile Population Calculatio n from 2010 and 2020 from Kevin Weinisch
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- 50. Calculation FC08790, Atmospher ic Dispersion Factors (X/Qs) at the Decommissioning Exclusion Area Boundary (EAB) for Radiological Releases from Fort Calhoun Station.
- 51. Project 2444, Partial Site Release.
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- 5. STRUCTURES
5.8 Missile Protection
5.8.1 External Missiles
5.8.1.1 Tornado Generated Missiles
The spectrum of hypothetical mi ssiles used for the ISFSI design basis analysis are described below in Table 5.8-1. The associated design-basis tornado (DBT) characteristics are described below in Table 5.8-3. The criteria shown in Tables 5.8-1 and 5.8-2 are taken from Regulatory Guide (RG) 1.76, Revision 1. Per RG 1.76, Revision 1, Fort Calhoun Station is located in Region I o f the United States where at the 10-7 per year probability level, the DBT is comprised of 230 mph winds with a concurrent pressure drop of 1.2 psi at a rate of 0.5 psi per second. The horizontal velocity component of torna do generated missiles is applied in all horizontal directions and where applicable, the vertical velocity component is equal to 67% of the horizontal velocity.
Table 5.8 DBT Missile Spectr um and Maximum Horizontal Speed s
Horizontal Item Weight (lbs) Velocity (fps)
Sched 40 Pipe (6.625" dia x 15' lg) 287 135 Automobile (16.4'x6.6'x4.3') 4000 135 Solid Steel Sphere (1" dia.) 0.147 26
(
Reference:
Table2ofRG1.76,Revision1)
Table 5.8 Design Basis Tornado Characteristics
Region Maximum Translational Maximum Radius of Pressure drop Rate of Wind Speed Speed (mph) Rotational Maximum (psi) Pressure (mph) Speed (mph) Rotational Drop (psi/s)
Speed (ft)
I 230 46 184 150 1.2 0.5
(
Reference:
Table 1 of RG 1.76 Revision 1)
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The Atomic Energy Commission ( AEC) approved Bechtel Topical Report BC-TOP-9A, "Design of Stru ctures for Missile Impacts,"
Revision 2, which was used to eva luate the spectrum of missiles described in Table 5.8-1 against t he SSCs to which they are bei ng applied. (Reference 5-16)
RG 1.76 Revision 1 and Bechte l Topical Report BC-TOP-9A, Revision 2, comprise the methodology used to assess structures, systems and components for t he DBT and associated missile impacts.
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- 12. CONDUCT OF OPERATIONS
12.1 Organization and Responsibility
Station organization is described in NO-FC-10, Quality Assuranc e Topical Report (QATR) and in site administrat ive procedures and organizational charts.
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- 12. CONDUCT OF OPERATIONS
12.2 Training
Station training requirements ar e located in NO-FC-10, Quality Assurance Topical Report (QATR) and in site adm inistrative procedures.
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- 12. CONDUCT OF OPERATIONS
12.3 Written Procedures
Station written procedures require ments are located in NO-FC-10, Quality Assurance Topical Report.
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- 12. CONDUCT OF OPERATIONS
12.4 Records
Station records requirements are located in NO-FC-10, Quality A ssurance Topical Report (QATR) and in site adm inistrative procedures.
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- 12. CONDUCT OF OPERATIONS
12.6 Site Emergency Plan
The ISFSI Only Emergency Plan (IO EP) requirements, as submitted to the NRC, are located in the IOEP.
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- 12. CONDUCT OF OPERATIONS
12.7 Plant Security
The ISFSI Security Plan requirem ents, as submitted to the NRC, are located in the Security Plan.
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APPENDIX A
1.0 INTRODUCTION
OPPD has ultimate responsibility for assuring that the Fort Calhoun Station is designed, maintained, tested, and operated in compliance with a pplicable regulations, codes, and standards and in a manner to protect the health and safety of the public.
In meeting this responsibility, a Quality Assurance program has been established and implemented which complies with the provisions of:
- a. Title 10, Code of Federal R egulations Part 50 Appendix B, "Q uality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants", and
- b. Applicable sections of the Am erican Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code.
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CRITERION 5 - RECORDS REQUIREMENT
Records of the design, fabricati on, and construction of essential components of the plant shall be maintained by the r eactor operator or under its contro l throughout the life of the reactor.
This criterion is met (2). The Omaha Public Power District (OPPD) is the owner and oper ator of Fort Calhoun Station, Unit N o. 1 (FCS). The Omaha Public Po wer District will maintain records of the design, fabrication, and construction of essential components of FCS.
Due to Decommissioning OPPD has sought and received an exemptio n to records retention as follows:
The Commission hereby grants OPPD 's partial exemptions from 10 CFR part 50, appendix B, Criterion XVII; 10 CFR 50.59(d)(3 ); and 10 CFR 50.71(c) to adva nce the schedule to remove records associated with Struc ture, System, or Components (SSC) that have been removed from the NRC's licensing basis documents by appropriate change mechanisms.
Records associated with residual radiological activity and with programmatic controls necessary to support decommissioning, such as security and qual ity assurance, are not affected by the exemption reques t because they will be retained as decommissioning records until the termination of the FCS license. Also, the licensee did not request an exemption associated with any other recor d keeping requirements for the s torage of spent fuel at its ISFSI under 10 CFR 50 or the gener al license requirements of 10 CFR 72. No exemption was requested from the decommissi oning records retention requirements of 10 CFR 50.75, or any other requirements of 10 CFR 50 applicable to decommissi oning and dismantlement.
(2) Exemptions are from NRC-17-063, dated October 4, 2017.
DSAR-Appendix G Page 2 of 6 FCSI Rev. 6 Information Use Responses to 70 Criteria
CRITERION 17 - MONITORING RADIOACTIVITY RELEASES
Means shall be provided for moni toring the containment atmosphere, the facility effluent discharge paths, and the facility environs for radioactivity th at could be released from normal operations, from anticipated transients and from accident condi tions.
This criterion is met.
Plant gaseous effluents are vent ed to the atmosphere. Particulate monitoring of gaseous effluent is accomplished by filter air samplers.
Plant liquid effluents are m onitored during release.
The above monitors are capable of detecting radioactivity relea sed from the site to ensure the ODCM requirements are met.
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CRITERION 18 - MONITORING FUEL AND WASTE STORAGE
Monitoring and alarm instrumentat ion shall be provided for fuel and waste storage and handling areas for conditions that might contribute to loss of continuity in decay heat removal and to radiation exposures.
This criterion is met. Area m onitoring of dose rates is supplied in the waste storage areas as required by the Radiation Protection Program which includes the use of local alarms and indicators.
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CRITERION 68 - FUEL AND WASTE STORAGE RADIATION SHIELDING
Shielding for radiation protec tion shall be provided in the design of spent fuel and waste storage facilities as required to meet the requirements of 10 C FR 20.
This criterion is met.
The liquid waste disposal equip ment is built to industry code s tandards.
Solid wastes are collected and ma y be stored in a shielded area if radioactivity levels are high. Spent resins are placed in a shipping container and stor ed in a shielded area.
All spent fuel is stored in the ISFSI. All storage requirement s are met as described in the 10 CFR 72.212 evaluation report. St ation Greater Than Class C (GTCC) waste can also be stored in the ISFSI.
The shielding for radiation prot ection meets the requirements of 10 CFR 20 for all waste storage areas.
DSAR-Appendix G Page 5 of 6 FCSI Rev. 6 Information Use Responses to 70 Criteria
CRITERION 69 - PROTECTION AGAINST RADIOACTIVITY RELEASE FROM SP ENT FUEL AND WASTE STORAGE
Containment of fuel and waste storage shall be provided if acci dents could lead to release of undue amounts of radioactivity to the public environs.
This criterion is met.
There are no accidents or events remaining that could exceed offsite limits.
Other areas where waste is sto red include the independent spent fuel storage installation (ISFSI), which is located at the north end of the site, in the ISFSI Protected Area.
All spent fuel is stored in the ISFSI. All storage requirement s are met as described in the 10 CFR 72.212 evaluation report. St ation GTCC waste can also be stored in the ISFSI.
Waste processing equipment is des igned for packaging, storage a nd transport of low-level radioactive wastes. This provi des control to maintain releases within ODCM and PCP requirements.
DSAR-Appendix G Page 6 of 6 FCSI Rev. 6 Information Use Responses to 70 Criteria
CRITERION 70 - CONTROL OF RELEASE OF RADIOACTIVITY TO THE ENVIR ONMENT
The facility design shall include those means necessary to main tain control over the plant radioactive effluents, whether gas eous, liquid, or solid. Appr opriate holdup capacity shall be provided for retention of gaseous, liquid, or solid effluents, particularly where unfavorable environmental conditions can be expected to require operational limitations upon the release of radioactive effluents to the env ironment. In all cases the design for radioactivity control shall be justified (a) on the basis of 10 CFR 20 requirements f or normal operations and for any transient situation that mi ght reasonably be anticipated to occur and (b) on the basis of 10 CFR 100 dosage level guidelines for potential reactor accidents of exceedingly low probability of occurrence except that reduction of the recommen ded dosage levels may be required where high population densities or very large cities can be affected by the radioactive effluents.
This criterion is met (3).
All release events are bounded within 10 CFR 20 limits with reliance on SSCs.
The liquid wastes are collected, treated (filtration or deminer alization) as appropriate, and analyzed prior to release. A radiation monitor, monitors all l iquid discharges of radioactive waste. The effluent discharge, w hen diluted, will not exceed r equirements of 10 CFR 20 as described in the ODCM.
Space for storage of the solid wa stes is provided so that packa ging, handling and shipping can be carried out under favo rable environmental conditions. All solid waste will be monitored, labeled, packaged an d handled according to applicable regulations.
Gaseous wastes are no longer stored. All waste gas is vented a nd monitored during release.
(3) Amendment No. 299 removed the requirements of 10 CFR 100 for reactor accident dose analysis at the decommissioning site.