ML24079A257

Attachment 1 - Dsar/Ifha/L Tp Change Form Rev 9

ML24079A257
Person / Time
Site:	Fort Calhoun, 07100256
Issue date:	02/01/2022
From:	Church R Omaha Public Power District
To:	Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
LIC-24-0004
Download: ML24079A257 (1)

Text

{{#Wiki_filter:FCSI Information Use FCSI-RA-102 Page 1 of 4 Rev. 2 Control of Licensing Document Changes DSAR-1.2 - DSAR/IFHA/L TP Change Form Change No.: EC 70840 I Unit(s): FCS Type of change: ~ Technical ~ Editorial Affected DSAR/IFHAILTP Section(s), Table(s), Figure(s), Page(s): DSAR-1.2, Summary Plant Description; DSAR-1.11 Specific

References:

DSAR-2.2, General Description of Site and Environs; DSAR-2.7, Hydrology; DSAR-2.8, Demography; DSAR-2.11, Section 2 Specific References; DSAR figure 1.2-1; DSAR figure 1.2-3; DSAR figure 2.2-4; DSAR figure 12.1-1. Description of Change (Provide summary here and attach affected pages marked to show the changes): This OCR EC will revise sections and figures of the DSAR that are no longer relevant to the facility and will update chapters and sections that continue to be relevant as per R.G. 1. 184 guidance, The existing site Design and Licensing Basis is unchanged by this EC. In addition to other adrrinistrative changes this OCR is corrective action for CR-2021-

00073, DSAR Sections 1.2, 2.2, 2.11 and DSAR figure 2.2-4 (file 36045) will be revised to address Exclusion Area Boundary (EAB) wording and to rerrove the previous Chapter 14 design basis event bounding calculation, FC08790, "Atrrospheric Dispersion Factors (X/Qs) at the Decormissioning Exclusion Area Boundary (EAB) for Radiological Releases from Fort Calhoun Station." FC08790 was previously used to bound 8nergency Plan and Design basis events (previous DSAR chapter 14 events), The above DSAR sections and figures will be revised to reflect previously approved changes which were il'Tl)lemented by EC 70269 and EC 70558. This portion of the change is a correction of errors in incorporating previously approved changes, Changes of this type are not subject to 10 CFR 50.59 per the 50.59 Resource IVanual, Section 4.2.3. DSAR reference to FC08790 will be deleted, FC08790 will remain an Active calculation for reference purposes, The Exclusion Area term as described in the DSAR will be changed to Controlled Area and Site Boundary Area were appropriate. The boundaries themselves and descriptions of the areas are unchanged. Ref. CR-2021-00073.

The following are editorial changes: Formal reference to FC08566 (HIC Drop) will be added to DSAR-1. 11, Specific References. DSAR-1.2, Summary Plant Description, will be edited to rerrove unnecessary detail regarding site buildings and equipment that no longer exist on the Decormissioning Site. DSAR figure 1.2-1 (file 36030) is revised to reflect rerroval of buildings and structures that no longer exist on site. DSAR figure 1.2-3 (file 12167) to be made historical and rerroved from the DSAR 1.2 figures. DSAR-2, 7, Hydrology, will be edited to rerrove unnecessary detail regarding the Groundwater M:mitoring Program, Reference to the quality documents where relevant program details can be found will be added to this section (PBD-37, Groundwater Protection Program Basis Document; SO-G-118, Site Groundwater Protection Program), DSAR-2.8, Derrography, contains U.S. Census data for areas surrounding the site, The latest data currently in the DSAR is from 2010 U.S. Census, This section is being updated to reflect the 2020 U.S. Census, DSAR figure 12.1-1 (file 36586) Station Organization Chart, to be made historical and rerroved from the DSAR figures. Supporting Documentation: Attach all supporting documents such as design change packages, calculations, drawings, letters, etc., and include attachments where appropriate: All supporting forms for 50.82, 50.59 and Environmental Review requirements are attached to EC 70840 in Asset Suite in the Topic Notes. (Req Re"1ews: QA) R9 03-15-22

FCSI Information Use FCSI-RA-102 Page 2 of 4 Rev. 2 Control of Licensing Document Changes Attach 10 CFR 50.59 Evaluation or Safety Evaluation Report, if required (Ref. 6.1.4): N/A Date and Schedule for Implementing Activities: Estimated date of issue for this DSAR change is prior to 2/28/2022 pending approvals. Required Technical Reviewers: Prepared by (Please Print): R.L. Church (Req Reviews: QA) ufiaiefqy:Regulatory Assurance f\\,,t 2/2/2022 3:01 PM CST E391699A3s23.J..-ocation / De part me nt: FCS/Eng. 2/2/2022 3:06 PM CST Extension: Date:2-1-2022 6073

FCSI Information Use Control of Licensing Document Changes - DSAR/IFHA'LTP Change Technical Review Form To: R. L. Church From: Don Pier, Regulatory Assurance FCSI-RA-102 Page 3 of 4 Rev. 2

Reference:

DSAR I DSAR/IFHAILTP Change Number: EC 70840 Please review the attached DSAR/IFHA/L TP change and return by: lte m to Che ck Reviewer r: 01nitial/Date 01 The changes are clear and accurate. VrVLr 02 The 50.59 Evaluation/Safety Evaluation Report supports all of the u" µ)~p changes. 03 The supporting attached technical documents support the change. r; tilt(' 04 The changes do not conflict with other DSAR/IFHA/L TP sections. /IV\\, 05 The DSAR/IFHA/L TP change log has been reviewed to see if the same pages are affected by other changes. If so, impact of other changes i.,--- os h~p must be considered. 06 The changes do not conflict with other design basis documents. i-tftlll.,r 07 The changes do not invalidate licensing commitments. t PA.,r n 08 The integrity of the design basis is maintained. JtVLr 09 Additional reviewers are identified for changes that may affect other departments, if applicable. OfltP Comments:

== Conclusion:== (check one) Change is technically acceptable. No Comments. Change is technically acceptable. Editorial Comments attached. ~ Change is technically acceptable pending incorporation of comments. (Attach comments or describe above.) Change is technically acceptable pending the following activity and estimated completion date. Change is technically unacceptable. Provide reason in comment section and notify the preparer. Reviewed by (Print): ,.----DocuS,gned Signature: 2/7/20gptf:6:57 AM CST Don Pier D1J1*,1/ J flt Pi, v-Return this form to the Char~:Pre~r. Comment Resolution: The reviewer concurs with the comment resolution (signatr vr.cuSignedby: 0tJIA-OLJ flt. Piur '---- E30678D54A3E430... (Req Reviews: QA)

FCSI Information Use Control of Licensing Document Changes - DSAR/IFHA/L TP Change Approval Form To: Regulatory Assurance and Emergency Planning Manager, Andrea Barker From: Responsible Engineer, R.L. Church DSAR/IFHA/L TP Change Number: EC 70840 Technical Review Summary FCSI-RA-102 Page 4 of 4 Rev. 2 The following have reviewed and concur with the technical adequacy of this DSAR/IFHA/L TP change. (Attach a copy of the review form ( - DSAR/IFHA/L TP Change Technical Review Form) for each reviewer.) Name Title Department Approval by Regulatory Assurance and Emergency Planning Manager

== Conclusion:== (check one) Change is approved and may be used. Change is approved after editorial comments are incorporated. (Attach comments) Change is approved pending the following activity and estimated completion date. Change is unacceptable. Provide reason and notify the Preparer: Technical review is not sufficient. The following is required: The approval authority ensures that the technical reviewers above are sufficient to technically review the scope of the change. The approval authority ensures that the change is technically and administratively sound. Approved by (Print): Andrea Barker (7 Docu5igned by: Signature: () It j2_ ~ 2/7/Ja~er 8:09 AM CST Regulatory Assurar1~1::vxv_' J1 1(ency Planning Manager (signature): Andrea Barker n 11 g,__n1 Regulatory AssurarteeEam~mergency Planning Manager License Document final editorial review complete (signature): Andrea Barker (Req Reviews: QA) l /)oc 1 u:igj£: ~ 1 I V - - '--<1----- ~ '--..:.. E391699A3B234B3...

Information Use Summary Plant Description

1.0 INTRODUCTION

AND

SUMMARY

1.2 Summary Plant Description 1.2.1 Plant Site DSAR-1.2 Page 1 of 9 Rev. 8 The site for the Fort Calhoun Station contains approximately 540 acres on the west bank of the Missouri River, approximately 19.4 miles north of Omaha, Nebraska. OPPD has a perpetual easement on approximately 117 acres of land on the east bank of the river directly opposite the plant buildings. On the Western part of the site the ground rises sharply 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 defined river bank in the vicinity 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 approximately 60 feet below the surface. Ground water level is close to existing grade and structures below grade are suitably water-proofed. An Independent Spent Fuel Storage Installation (ISFSI) is located in the protected area designated for dry storage of spent fuel and greater than class C waste (GTCC). The ISFSI is licensed under Subpart K of 10 CFR Part 72. The area adjoining the site is farmland and sparsely populated. The minimum exolusion controlled arearestrioted distance is 1525 feet. The nearest population center area of more than 25,000 is formed by adjacent cities of Omaha, Nebraska and Council Bluffs, Iowa. The site vicinity plan is shown in Figure 1.2-12'. The exolusion zonerestrioted zoneSite Area boundary consists of approximately 540 acres owned by Omaha Public Power District. The restricted area as defined in Section 20.J1003~of 10 CFR Part 20 is shown on Figure 1.2-1.

DSAR-1.2 Page 2 of 9 Rev. 8 Information Use Summary Plant Description A rail spur from the Chicago and Northwestern (CNW) Railway was constructed to serve the construction of the Fort Calhoun Station (FCS). The original CNW tracks and rail spur have since been removed. In 1994, a permanent easement was granted to allow the construction of a new rail spur in the approximate location of the old CNW railway to allow trains to serve the Cargill industrial facility located north of FCS. Road access to FCS is from U.S. Highway No. 75. 1.2.2 Station Arrangement Station status is continually changing during decommissioning. Current information on systems, radiological conditions and demolition progress is maintained by the Radiation Protection and Decommissioning organizations respectively. The principal station structures are the ISFSI Operating Facility (IOF) and ISFSI. The site's legacy buildings include the turbine building, intake structure, technical support center, service building, maintenance shop, and the chemistry and radiation protection/locker facility including the offise/safteria addition, and hazardous material storage building. All are located outside of the Protected Area. Some specific system descriptions have been removed from the DSAR as all spent fuel has been removed from the Spent Fuel Pool to the ISFSI pad and these SSC no longer have a design function. The reactor, steam generators, reactor coolant pumps and pressurizer are located in the containment, together with other nuclear steam supply system (NSSS) components which no longer have a design function. A polar bridge crane is installed above the Containment operating floor, but no longer has a design function. The reactor auxiliaries include, engineered safeguards components, the control room, radiation controlled area (RCA) protective clothing 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 treatment facilities. A traveling bridge crane is located over the fuel handling and storage area in the auxiliary building. The traveling bridge crane no longer has a design function.

DSAR-1.2 Page 3 of 9 Rev. 8 Information Use Summary Plant Description The turbine building houses the turbine generator, condenser, and other turbine heat cycle components. These components no longer have a design function. The 150-ton traveling bridge crane no longer has a design function. The servioe building houses the auxiliary boiler whioh no longer has a design funotion. The condenser cooling circulating water and raw water pumps are located in the intake structure. They no longer have a design function. Station Structures can contain provisions for dry active waste (DAW) processing, liquid radwaste filtration and ion exchange (FIX) equipment and radwaste solidification equipment. 1.2.3 Reactor and Reactor Coolant System The reactor and reactor coolant system are located in containment but no longer have a design function. 1.2.4 Deleted 1.2.5 Engineered Safeguards Systems The components which made up the engineered safeguards systems are located in the Auxiliary Building and Containment, but no longer have a design function. 1.2.6 Instrumentation and Control A. Deleted. B. Instrumentation Local control of the remaining instrumentation monitoring system function to support the remaining functional portions of the waste disposal, radiation monitors, and HVAC systems. All other process instrumentation and monitoring systems remain installed, but no longer have a design function. C. Deleted. Plant Computer The plant oomputer remains installed, but no longer has a design funotion.

DSAR-1.2 Page 4 of 9 Rev. 8 Information Use Summary Plant Description 1.2.7 Electrical Systems The source of energy for the ISFSI loads are the 13.8 kV circuit from the OPPD Substation, and a diesel-generator set located in the IOF. Power systems provide power to meet required remaining decommissioning support functions. Other legacy electrical systems remain installed, but no longer have a design function. 1.2.8 Auxiliary Systems The following systems remain installed but no longer have a design 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 allowed to be stored in the SFP. The SFP system remains installed, but no longer has a design function. The ISFSI contains all fuel for storage prior to off-site shipment.

DSAR-1.2 Page 5 of 9 Rev. 8 Information Use Summary Plant Description OPPD has constructed an ISFSI, located in the Protected Area designated for dry storage of spent fuel. The ISFSI consists of the concrete basemat that was built on an elevated pad of compacted, engineered fill for flood protection, concrete horizontal storage modules, concrete shield walls, concrete approach slabs adjacent to the basemat, the ISFSI electrical equipment building, and the IOF. The ISFSI is designed for 42 horizontal storage modules arranged in a 2 x 21 back-to-back configuration. Each horizontal storage module holds one dry shielded canister for fuel storage or a canister containing greater than class C waste (GTCC) for storage. The HSM protects the canister(s) from natural phenomena such as tornado missiles, and is designed to provide for passive cooling of the canister by means of natural air circulation. The ISFSI basemat is 42 ft. wide by 211 ft. long, with its long dimension oriented in the east-west direction. The elevation of the top of the basemat is at 1009 ft-10 inches, above the level of the probable maximum flood. This DSAR for the Fort Calhoun Station does not assess the safety of the dry spent fuel storage system, which is licensed under Subpart K of 10 CFR Part 72 for general ISFSI licenses. Transnuclear, Inc., the storage system vendor, maintains the Final Safety Analysis Report for the NU HOMS Horizontal Modular Storage System (Reference 1-6). Certificate of Compliance No. 1004 (Reference 1-7) was issued by the NRC for the NUHOMs-system, with the 32PT DSC used at the Fort Calhoun Station ISFSI. The Technical Specifications for the NU HOMS storage system are included as Attachment A to Certificate of Compliance No. 1004. B. Plant Ventilation Systems Station Ventilation systems (serving the containment and part of the auxiliary building) handle airborne contaminants so that offsite concentrations and in plant doses (which are controlled by the ODCM and administrative procedures) are within 10 CFR Part 20 limits. +l:lePortions of +the remaining plant ventilation systems remains installed but no longer have a design function. C. Plant Fire Protection

Information Use Summary Plant Description Containment Building DSAR-1.2 Page 8 of 9 Rev. 8 The containment has one major shielding function: It shields adjacent auxiliary plant and yard areas from radiation originating from inside the containment. Auxiliary Building Adequate shielding is provided around equipment that carries radioactive liquid, slurry or gas. Radioactive Waste Processing Building and CARP Building Adequate shielding is provided for 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 ODCM requirements F. Miscellaneous Radioactive Material Sources Miscellaneous radioactive material sources are controlled by Radiation 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 Consequences of a High Integrity Container (HIC) Drop Event (Reference 1-184--44), provide quantity and design incidents for radiological solid (postulated gas) releases. This calculation supports the ISFSI Only Emergency Plan (IOEP) license, which assumes onsite deconstruction activities are administratively controlled. The radioactive waste handling events have been postulated to be the limiting events for decommissioning activities and does not rely on any equipment for mitigation.

DSAR-1.11 Page 2 of 2 Rev.5 Information Use Specific References 1-16 Letter from NRG (J. Kim) to OPPD (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 NRG (J. Parrot) to OPPD (M. Fisher) "Fort Calhoun Station, Unit 1 - Issuance of Amendment to Revise Fort Calhoun Station Permanently Defueled Technical Specifications to Align to the Requirements for Permanent Removal of Spent Fuel from Spent Fuel Pool" Dated December 11, 2019 (NRC-19-026) 1.:.1§_ 4--4-8-----Calculation FC08566, Dose Consequences of High Integrity Container (HIC) Drop Event. Formatted: Outline numbered+ Level: 2 + Numbering Style: 1, 2, 3,... + Start at: 5 + Alignment: Left+ Aligned at: 0.5 + Tab after: 0.75" + Indent at: 0.75"

DSAR-2.7 Page 4 of 6 Rev. 4 Information Use Hydrology Thirteen groundwatergGroundwater monitoring wells (both shallow and deep) areweFe installed at FCS from August 15 through August 27, 2007. Hydro geologioal information was oolleoted and evaluated by Terraoon Consultants lnoorporated. A seoond review and evaluation was performed by Radiation Safety and Control Servioes inoorporated. Soils observed during the advancement of the well borings consisted primarily of unconsolidated lean clay, silt, and sand. These materials appear to be representative of Missouri River alluvium, although some 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 silt approximately 20 to 50 feet thick, and an underlying fine to coarse sand with some gravel. This lower unit extends to the relatively flat-lying carbonate bedrock surface at a depth of approximately 70 to 75 feet below grade. Both unconsolidated units are water bearing, but the deeper unit 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 hydraulic gradient, combined with moderate hydraulic conductivity of the fine grained alluvial material, results in relatively slow ground water velocity beneath the site. Water table and potentiometric surface contour maps constructed based upon water levels measured in the new wells indicate groundwater flow directions different from the directions presumed prior to construction of the wells. Initially two conditions at FCS produced groundwater flow gradients opposite to those originally presumed. The first condition that affected groundwater flow was the pumping of the ground water supply well located at the Northwest corner of the old warehouse pad however, this well no longer exists.

DSAR-2.7 Page 5 of 6 Rev. 4 Information Use Hydrology 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 generally from April through September when precipitation is greatest, river water recharges the nearby alluvial aquifer and induces groundwater flow gradients outward from the river channel. These gradients reverse seasonally, during periods of lower river 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 the plant appears to be within a dynamic groundwater environment influenced by pumping of the ground water supply well, (this groundwater supply well no longer exists), river level, and seasonal amounts of precipitation. Consequently, the Site Groundwater Protection Program (ODCM~ Formatted: Font: (Default) Arial SO-G-118, PBD-37) accounts for potential variations in flow directions present within the industrial area. 2.7.2.3 Well Water Analyses Samples were taken from the test 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 temperature 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.

2.

SITE AND ENVIRONS 2.8 Demography Information Use Demography DSAR-2.8 Page 1 of 5 Rev. 2 The plant site is located on the alluvial plain of the Missouri River in a predominantly agricultural region roughly ten miles north of the Omaha metropolitan area. There are no residences within one-half mile of the reactor location. 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 property. Industries include a large corn processing facility, agricultural fertilizer storage facilities and various other light industrial plants. The DeSoto National Wildlife Refuge occupies approximately 7,821 acres east of the plant site. This area is open to the public for day use year round. Visitors to the refuge generally use areas from two 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. The expected maximum daily usage of the facility has been placed at 2500 visitors for 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 plant site. Visitors to the recreation area generally use areas 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 the Fort Atkinson State Historic Park 5.5 miles southeast of the plant site. This day use facility is mostly seasonal 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 Refuge and four miles southeast of the plant site. The estimates for usage of this facility range from 500 on winter weekday to 1000 on a summer weekend. Two private facilities lie to the north of the plant along the Missouri River. The Cottonwood Cove Marina & RV Resort 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 campground lying directly to the south of Cottonwood Marina and ranging from 4 to 4.5 miles 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 +-;9007,799 per the ~2020 census. Fort Calhoun is about five miles southeast of the facility. The ~2020 census reported a population of 900-1100 in Fort Calhoun and 4e-7-381 in Kennard Village, about seven miles from the plant site. The 2024Q20-W population of Washington County is 20,3612a4.

DSAR-2.8 Page 2 of 5 Rev. 2 Information Use Demography Missouri Valley, Iowa, about 11 miles east, has a 20-W-2020 population of ~2.678 as compared to the '2010 population of ~2.838. In St. Johns Township, of which the city is a part, population has steadily decreased. The Omaha metropolitan area includes the cities of Omaha and Council Bluffs, Iowa, and the adjoining areas of Douglas, Washington, and Sarpy Counties, Nebraska, and Pottawattamie County, Iowa. The area lies 10 to 25 miles southeast of the site, with the main concentration of population beyond the 15-mile radius. Population studies have been undertaken by the Metropolitan Area Planning Agency. Population information is as follows: 1960 U.S. Census 1970 U.S. Census 1980 U.S. Census 1990 U.S. Census 2000 U.S. Census 2010 U.S. Census 2020 U.S. Census Omaha City 301,598 346,929 313,911 335,795 390,007 408,958 472,914 Metropolitan Area 457,873 542,646 569,614 618,262 707,211 789,342 789,342855,603

I Fest I Sector Direction 0-1 A N 0 B NNE 0 C NE 0 D ENE 0 E E 0 F ESE 0 G SE G~ H SSE 4-+-Q J s ~Q K SSW

!-87 L

SW

!.Gll M

WSW 0 N w 4-GQ DSAR-2.8 Page 3 of 5 Rev. 2 Information Use Demography Table 2.8 Population Distribution as of 20-1--02020 Distance From Reactor In Miles/Square Miles of Sector Segment 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 0 0 4.Ll. G14 aJ43 ~257 ~633 ~3.51 1 ~~ 0 gz 4Q Mi336 489798 l--U726 9W1,133 0 0 eQ

1416 448164 ~2.46 ~2.425 4;-7741,78 6

3 0 0 0 44§ 900813 4;-8+e3,53 1,00-7-066 4,-4@3,96 § ll 0 0 0 Gll 4;;1411.1 907986 2,4-e-4498 3.~06 0 814 0 4-8Q 8226 1.419204-2 2,900e2e ~.22 G § ~21 44I eQ ~306 799622 3,7+e407 41,5989W ~2.30 § 4-+-48 4-923 ~261 200327 1,526We HlJ,9e1.1.§ Hl1,GeG156 19,37289 5,007 ,686 44-a72 e+-87 84-143 17§4.e +ed650 1 aa,arn.Ll. 14e,ea7155 ~.39 8,275 ,175 8 4-;;!.2.1 4447 4;;!-45 ~281 4-,eedZJ. 48;-e4-4~ ~90,8 &,-00a6,67 08 625 45 5 49Q 84172 ~3 @126

!-49333 2,316~ 4,9W6,089 6,748448 W80 4-eQ

~296 87173 5574ee4 4-;-WQ2,05 JG.;47e31. 6 ~2.73 e § 91 1 142~ 10744-04 514~ 10678 304;;!.4e 608~ 4-,ee42,074 1,0199M 7-40-50 TOTALS r---{ Formatted Table l ~2..,§ 1,-89+7,29 16 Q ~.M ~6.05 44 § ~2.Jl. ~9.76 15 9 e;-04+4_Jl_ ~H.., §1 340 1.~603 8,447616 1,213004 ~9.79 I ~u ~§j_,_ 49 024 e;-24-4§,§ aaa,GnJ 76 38,826 3,e;;!4554 ~9J,J9JJ 06,371 ~§2 rn4,a4~2 35 07,969 ~_d 4-7,-7002.Q,_ 00 136 1,777eag ~~ 366 1,30394-9 &,-92-G6. 17 I

I Fest I p WNW 023 iQ

w)202 3,782~

4 Q NW 0 0 2204-a24 1,017M a Q R NNW 0 0 4180 19~ TOTALS 128+a 39644a 920W9a a,-789§_,_ g 140

• Based on 20-W--2020 U.S. Census Data Information Use Demography 1,974~ 26~

483 Q ~~ 1329449 4 11~ 55W 3,375e 8,046+-;--7 ~ 4+ Sectors are assigned for 22.5 degree segments starting from 11.25 degrees East of North. DSAR-2.8 Page 4 of 5 Rev. 2 45584484 7844-,+98 7014-a74-a 1,9994894-8 1,803~ 441aa4aa Je9,rn141 44J,Ga4497 3,716 ,630 5,145~ 1,501878 7969d8 72,723/J+. ~ 2,268007 14,89604 e-;Qa8 1,179M 6,758~ -74 2,919M- ~6.08 ~ § 50.40249 9aG,1971.,_ ~ 053,476

DSAR-2.11 Page 4 of 4 Rev.5 Information Use Section 2 References 50._Calculation FC08790, Atmospheric Dispersion Factors (X/Qs) at the Decommissionin§ Exclusion Area Boundary (EAB) for Radiolo9ical Releases from Fort Calhoun Station.DELETED Project 2444, Partial Site Release.

---

( Formatted: Indent: Left: 0.5", Hanging: 0.38"

IEC 70840 I TO WEATHER TOWERS FIRING RANGE / Remove highlighted buildings and structures -i /' IOF H (J)

u.

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• -----J **

J 1l $:CjlQN A J C Drawing to be statused as historical and removed as a DSAR 1.2 figure. L~ c : * - r*...,._* D c.. c.11~*_)

,.1,7 ,ry,o '/969 £ast1msnt, Change note 1 as follows: Circle depicts the Controlled Area that is 1525 ft from the Auxiliary Building Stack. Ref. FC08566, Dose Consequences of a High Integrity Container (HIC) Drop Event, This Controlled Area depiction is not to scale. THE CENTERLINE OF THE AUXILLARY BUILDING STACK. REF. FC08790-ATMOSPHERIC DISPERSION FACTORS IX/OSI AT THE DECOMMISSIONING EXCLUSION AREA BOUNDARY IEABl FOR RADIOLOGICAL RELEASES FROM FORT CALHOUN STATION. THIS EAB DEPICTION IS NOT OMAHA PUBLIC POWER DISTRICT FOAT CALHOUN STATION UNIT NO. I N

t i/I Ill

,a HARRSON COUNTY, IOWA R-45-W IEC 70840 I WASHINGTON COUNTY, NEBRASKA REV.SH. 25674 FILE 36045 METES ANO BOUNDS FORT CALHOUN STATION APVD REV L. Church Figure

2. 2 -4 5

IEC 70840 I Manager - Operations* (Assistant Plant Manager) Shift Managers* Unit Supervisors* Shift Technical Advisors Licensed/Non-Licensed Operators* Fire Brigade* Manager - Operations Services Fire Marshall* Lead WCC Supervisor Licensed Operators* Service and Support Team Director - Plant Management* {Plant Manager) Manager - Radiation Protection* Manager - Chemistry*

• Supervisor -

RP (Operations)

• Supervisor - RP (ALARA/Shipping)
• Supervisor - RP (Chem/Environ)
• Radiological Engineer
• Supervisor -

Chemical Operations l I Manager-Maintenance* Program Manager - Project Controls Drawing to be statused as historical and removed as a DSAR 12 figure. I i ~ ~ I FORT CALHOUN STATION

• POSITIONS AND/OR GROUPS POSSESSING FIRE PROTECTION RESPONSIBILITIES STATION ORGANIZATION CHART owe. FIG. 12.1-1 REV.SH. 23624 APVD I REV FILE 36586 J.Re1mers 24

Information Use Summary Plant Description

1.0 INTRODUCTION

AND

SUMMARY

1.2 Summary Plant Description 1.2.1 Plant Site DSAR-1.2 Page 1 of 9 Rev. 8 The site for the Fort Calhoun Station contains approximately 540 acres on the west bank of the Missouri River, approximately 19.4 miles north of Omaha, Nebraska. OPPD has a perpetual easement on approximately 117 acres of land on the east bank of the river directly opposite the plant buildings. On the Western part of the site the ground rises sharply 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 defined river bank in the vicinity 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 approximately 60 feet below the surface. Ground water level is close to existing grade and structures below grade are suitably water-proofed. An Independent Spent Fuel Storage Installation (ISFSI) is located in the protected area designated for dry storage of spent fuel and greater than class C waste (GTCC). The ISFSI is licensed under Subpart K of 10 CFR Part 72. The area adjoining the site is farmland and sparsely populated. The minimum exch,rnion controlled arearestricted distance is 1525 feet. The nearest population center area of more than 25,000 is formed by adjacent cities of Omaha, Nebraska and Council Bluffs, Iowa. The site vicinity plan is shown in Figure 1.2-12'. The exclusion zonerestricted zoneSite Area boundary consists of approximately 540 acres owned by Omaha Public Power District. The restricted area as defined in Section 20.J1003fatf44t-of 10 CFR Part 20 is shown on Figure 1.2-1.

DSAR-1.2 Page 2 of 9 Rev. 8 Information Use Summary Plant Description A rail spur from the Chicago and Northwestern (CNW) Railway was constructed to serve the construction of the Fort Calhoun Station (FCS). The original CNW tracks and rail spur have since been removed. In 1994, a permanent easement was granted to allow the construction of a new rail spur in the approximate location of the old CNW railway to allow trains to serve the Cargill industrial facility located north of FCS. Road access to FCS is from U.S. Highway No. 75. 1.2.2 Station Arrangement Station status is continually changing during decommissioning. Current information on systems, radiological conditions and demolition progress is maintained by the Radiation Protection and Decommissioning organizations respectively. The principal station structures are the ISFSI Operating Facility (IOF) and ISFSI. The site's legacy buildings include the turbine building, intake structure, technical support center, service building, maintenance shop, and the chemistry and radiation protection/locker facility including the 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 DSAR as all spent fuel has been removed from the Spent Fuel Pool to the ISFSI pad and these SSC no longer have a design function. The reactor, steam generators, reactor coolant pumps and pressurizer are located in the containment, together with other nuclear steam supply system (NSSS) components which no longer have a design function. A polar bridge crane is installed above the Containment operating floor, but no longer has a design function. The reactor auxiliaries include, engineered safeguards components, the control room, radiation controlled area (RCA) protective clothing 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 treatment facilities. A traveling bridge crane is located over the fuel handling and storage area in the auxiliary building. The traveling bridge crane no longer has a design function.

DSAR-1.2 Page 3 of 9 Rev. 8 Information Use Summary Plant Description The turbine building houses the turbine generator, condenser, and other turbine heat cycle components. These components no longer have a design function. The 150-ton traveling bridge crane no longer has a design function. The service building houses the auxiliary boiler which no longer has a design function. The condenser cooling circulating water and raw water pumps are located in the intake structure. They no longer have a design function. Station Structures can contain provisions for dry active waste (DAW) processing, liquid radwaste filtration and ion exchange (FIX) equipment and radwaste solidification equipment. 1.2.3 Reactor and Reactor Coolant System The reactor and reactor coolant system are located in containment but no longer have a design function. 1.2.4 Deleted 1.2.5 Engineered Safeguards Systems The components which made up the engineered safeguards systems are located in the Auxiliary Building and Containment, but no longer have a design function. 1.2.6 Instrumentation and Control A. Deleted. B. Instrumentation Local control of the remaining instrumentation monitoring system function to support the remaining functional portions of the waste disposal, radiation monitors, and HVAC systems. All other process instrumentation and monitoring systems remain installed, but no longer have a design function. C. Deleted. Plant Computer The plant computer remains installed, but no longer has a design function.

DSAR-1.2 Page 4 of9 Rev. 8 Information Use Summary Plant Description 1.2.7 Electrical Systems The source of energy for the ISFSI loads are the 13.8 kV circuit from the OPPD Substation, and a diesel-generator set located in the IOF. Power systems provide power to meet required remaining decommissioning support functions. Other legacy electrical systems remain installed, but no longer have a design function. 1.2.8 Auxiliary Systems The following systems remain installed but no longer have a design 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 Aul<iliary Boiler System Radioactive Waste Disposal System A. Fuel Handling and Storage Irradiated fuel bundles are not allowed to be stored in the SFP. The SFP system remains installed, but no longer has a design function. The ISFSI contains all fuel for storage prior to off-site shipment.

DSAR-1.2 Page 5 of 9 Rev. 8 Information Use Summary Plant Description OPPD has constructed an ISFSI, located in the Protected Area designated for dry storage of spent fuel. The ISFSI consists of the concrete basemat that was built on an elevated pad of compacted, engineered fill for flood protection, concrete horizontal storage modules, concrete shield walls, concrete approach slabs adjacent to the basemat, the ISFSI electrical equipment building, and the IOF. The ISFSI is designed for 42 horizontal storage modules arranged in a 2 x 21 back-to-back configuration. Each horizontal storage module holds one dry shielded canister for fuel storage or a canister containing greater than class C waste (GTCC) for storage. The HSM protects the canister(s) from natural phenomena such as tornado missiles, and is designed to provide for passive cooling of the canister by means of natural air circulation. The ISFSI basemat is 42 ft. wide by 211 ft. long, with its long dimension oriented in the east-west direction. The elevation of the top of the basemat is at 1009 ft-10 inches, above the level of the probable maximum flood. This DSAR for the Fort Calhoun Station does not assess the safety of the dry spent fuel storage system, which is licensed under Subpart K of 10 CFR Part 72 for general ISFSI licenses. Transnuclear, Inc., the storage system vendor, maintains the Final Safety Analysis Report for the NU HOMS Horizontal Modular Storage System (Reference 1-6). Certificate of Compliance No. 1004 (Reference 1-7) was issued by the NRC for the NUHOMS-system, with the 32PT DSC used at the Fort Calhoun Station ISFSI. The Technical Specifications for the NU HOMS storage system are included as Attachment A to Certificate of Compliance No. 1004. B. Plant Ventilation Systems Station Ventilation systems (serving the containment and part of the auxiliary building) handle airborne contaminants so that offsite concentrations and in plant doses (which are controlled by the ODCM and administrative procedures) are within 10 CFR Part 20 limits. +J::iePortions of +the remaining plant ventilation systems remains installed but no longer have a design function. C. Plant Fire Protection

Information Use Summary Plant Description Containment Building DSAR-1.2 Page 8 of 9 Rev. 8 The containment has one major shielding function: It shields adjacent auxiliary plant and yard areas from radiation originating from inside the containment. Auxiliary Building Adequate shielding is provided around equipment that carries radioactive liquid, slurry or gas. Radioactive Waste Processing Building and CARP Building Adequate shielding is provided for 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 ODCM requirements F. Miscellaneous Radioactive Material Sources Miscellaneous radioactive material sources are controlled by Radiation 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 Consequences of a High Integrity Container (HIC) Drop Event (Reference 1-184--4-4), provide quantity and design incidents for radiological solid (postulated gas) releases. This calculation supports the ISFSI Only Emergency Plan (IOEP) license, which assumes onsite deconstruction activities are administratively controlled. The radioactive waste handling events have been postulated to be the limiting events for decommissioning activities and does not rely on any equipment for mitigation.

DSAR-1.11 Page 2 of 2 Rev.5 Information Use Specific References 1-16 Letter from NRC (J. Kim) to OPPD (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 to Revise Fort Calhoun Station Permanently Defueled Technical Specifications to Align to the Requirements for Permanent Removal of Spent Fuel from Spent Fuel Pool" Dated December 11, 2019 (NRC-19-026) .1.:.1.L 4-4-&---Calculation FC08566, Dose Consequences of High Integrity Container (HIC) Drop Event. Formatted: Outline numbered+ Level: 2 + Numbering Style: 1, 2, 3,... + Start at: 5 + Alignment: Left+ Aligned at: 0.5 + Tab after: 0.75" + Indent at: 0.75"

DSAR-2.7 Page 4 of 6 Rev. 4 Information Use Hydrology Thirteen grmmdwatergGroundwater monitoring wells (both shallow and deep) arewe-re installed at FCS from /\\1,1g1,1st 15 thro1,1gh /\\1,1g1,1st 27, 2QQ7. Hydro geologisal information was sollested and eval1,1ated by Terrason Cons1,1ltants lnsorporated. A sesond review and eval1,1ation was performed by Radiation Safety and Control Servises insorporated. Soils observed during the advancement of the well borings consisted primarily of unconsolidated lean clay, silt, and sand. These materials appear to be representative of Missouri River alluvium, although some 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 silt approximately 20 to 50 feet thick, and an underlying fine to coarse sand with some gravel. This lower unit extends to the relatively flat-lying carbonate bedrock surface at a depth of approximately 70 to 75 feet below grade. Both unconsolidated units are water bearing, but the deeper unit 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 hydraulic gradient, combined with moderate hydraulic conductivity of the fine grained alluvial material, results in relatively slow ground water velocity beneath the site. Water table and potentiometric surface contour maps constructed based upon water levels measured in the new wells indicate groundwater flow directions different from the directions presumed prior to construction of the wells. Initially two conditions at FCS produced groundwater flow gradients opposite to those originally presumed. The first condition that affected groundwater flow was the pumping of the ground water supply well located at the Northwest corner of the old warehouse pad however, this well no longer exists.

2.7.2.3 DSAR-2.7 Page 5 of 6 Rev. 4 Information Use Hydrology 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 generally from April through September when precipitation is greatest, river water recharges the nearby alluvial aquifer and induces groundwater flow gradients outward from the river channel. These gradients reverse seasonally, during periods of lower river 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 the plant appears to be within a dynamic groundwater environment influenced by pumping of the ground water supply well, (this groundwater supply well no longer exists), river level, and seasonal amounts of precipitation. Consequently, the Site Groundwater Protection Program (ODCM~ Formatted: Font: (Default) Arial SO-G-118 PBD-37) accounts for potential variations in flow directions present within the industrial area. Well Water Analyses Samples were taken from the test 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 temperature 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.

2.

SITE AND ENVIRONS 2.8 Demography Information Use Demography DSAR-2.8 Page 1 of 5 Rev. 2 The plant site is located on the alluvial plain of the Missouri River in a predominantly agricultural region roughly ten miles north of the Omaha metropolitan area. There are no residences within one-half mile of the reactor location. 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 property. Industries include a large corn processing facility, agricultural fertilizer storage facilities and various other light industrial plants. The DeSoto National Wildlife Refuge occupies approximately 7,821 acres east of the plant site. This area is open to the public for day use year round. Visitors to the refuge generally use areas from two 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. The expected maximum daily usage of the facility has been placed at 2500 visitors for 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 plant site. Visitors to the recreation area generally use areas 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 the Fort Atkinson State Historic Park 5.5 miles southeast of the plant site. This day use facility is mostly seasonal 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 Refuge and four miles southeast of the plant site. The estimates for usage of this facility range from 500 on winter weekday to 1000 on a summer weekend. Two private facilities lie to the north of the plant along the Missouri River. The Cottonwood Cove Marina & RV Resort 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 campground lying directly to the south of Cottonwood Marina and ranging from 4 to 4.5 miles 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 +,WO? 799 per the ~2020 census. Fort Calhoun is about five miles southeast of the facility. The ~2020 census reported a population of 90&-1100 in Fort Calhoun and 4-e+--381 in Kennard Village, about seven miles from the plant site. The 2024-Q:WW population of Washington County is 20,361~.

DSAR-2.8 Page 2 of 5 Rev. 2 Information Use Demography Missouri Valley, Iowa, about 11 miles east, has a ~2020 population of 2,8332,678 as compared to the ~2010 population of ~2.838. In St. Johns Township, of which the city is a part, population has steadily decreased. The Omaha metropolitan area includes the cities of Omaha and Council Bluffs, Iowa, and the adjoining areas of Douglas, Washington, and Sarpy Counties, Nebraska, and Pottawattamie County, Iowa. The area lies 10 to 25 miles southeast of the site, with the main concentration of population 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 2020 U.S. Census 472 914 789 342855 603

Sector Direction 0-1 A N 0 B NNE 0 C NE 0 D ENE 0 E E 0 F ESE 0 G SE 0~ H SSE 4+Q j s ~Q K SSW 2§1 L SW 20~ M WSW 0 N w 4-0Q DSAR-2.8 Page 3 of 5 Rev. 2 Information Use Demography Table 2.8 Population Distribution as of 2Q..W2020 Distance From Reactor In Miles/Square Miles of Sector Segment 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 0 0 4.Ll_ OH_ ~_]_ ~257 ~633 ~Ml 1 ~ll 0 SI 4Q ~336 4S9798 l-M-726 9W1133 0 0 aQ ~.1§ 44-8164 ~2.A§ ~2425 4-,-7-741-2§ § .1 0 0 0 44§ 900813 4,-S+a~ 1,00-7-066 4;-W2.1Jl.§ Q ~ 0 0 0 0~ 4-24-ill W-7-986 2,4e4-498 3,~06 0 SH_ 0 4-SQ a2~ 1,419~ 2,900~ ~_,ll 0 Q ~2.1 4-4-Z eQ ~306 +-99622 3,+-+a407 41,5989W ~2..J..Q Q 4+4__§_ 492]_ ~261 ~327 1,526~ ~1.Q 4e4-;-0eO 1 56 19,372~ 5 007 ~ 2 ~ll a-7-fil S-t 143 .1la4-a ~650 ~.Ll. 44-e;-eal-1 55 e,-722~ 8 275 175 8 4-22.1 44-4__.I 424__§_ Jro281 ~bl 4-S,M4~ ~~ ~§..,§1 Q§ 625 ~ Q 49Q 64-172 ~_]_ S0126 249333 2,3164-S2 4-;%S6 089 6,74844-S ae§Q 4-eQ ~296 S-7173 55746M ~~ ~.11....§ ~U.1 e § ~ 1 142~ 10744-04 514~ 106+S 304246 608~ 4-,ea42 074 1,0199a-i + TOTALS c--{ Formatted Table I 40-50 ~b§ +;-W+~ 1.§ Q ~l,Q ~§_,QQ 11 § ~~ ~~ 1.Q ~ a,04-74__1! ~H.., _gj_ 340 1,~603 8,44-7-616 1,213004 ~~ I ~u ~.51., ~ 024 ~-52 ~.1 I§ 38 826 3,~554 ~.1 06 371 e,2+a§..2 -W4,M2~ ~ 07 969 ~_..,.1 4+,-7002.Q_, QQ 136 1,777~ ~.N, 366 1 30394-9 ~§.J.l I

p WNW Q2]_ JQ d4-G202 Q NW 0 0 220~ ~ R NNW 0 0 +/-1_W TOTALS 1281a 396~ 920M9a g

• Based on 2G-W-2020 U.S. Census Data 3,782de 4

1,017~ Q ~~ ~§_, 140 Information Use Demography 1 974&, 263~ ~ Q ~~ 13294-4--9 4 11M ~w 3,375e 8 046+-,+ ~ 4+ Sectors are assigned for 22.5 degree segments starting from 11.25 degrees East of North. DSAR-2.8 Page 4 of 5 Rev. 2 455~ 7844-;-+W 701~ 1,999~ 1,8039-72 441~ ~_j_ ~97 3 716 .filQ 5,145~ 2,26800-7 14 89684 ~ 1,501e+S 1179~ 6,758~ +4 796~ 2919~ ~§_,_Q§ ~ 5 72 723fJ+ 50 40249 9W,4-9+1., ~ ~ 053 476

5+.-50. Information Use Section 2 References DSAR-2.11 Page 4 of 4 Rev. 5 5Q._Calculation FCQ879Q, Atmospheric Dispersion Factors (X/Qs) at the Decommissioning Exclusion Area Boundary (EAB) for Radiological Releases from Fort Calhoun atation.DELETED Project 2444, Partial Site Release. .---( Formatted: Indent: Left: 0.5, Hanging: 0.38"

FCSI 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 1 of 3 Rev. 0

FCSI 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 Information Use Introduction 2.10 Environmental Radiation Monitoring 2.10.1 General 2.10.2 Preoperational Survey Program 2.10.3 Preoperation Survey Results DSAR-Table of Contents Page 2 of 3 Rev. 0 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

FCSI Information Use Introduction List of Figures DSAR-Table of Contents Page 3 of 3 Rev. 0 The following figures are controlled 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 Within 60 Miles of Site...................................... 36043 2.2-3 Geographical Features Within 30 Miles of Site...................................... 36044 2.2-4 Metes and Bounds................................................................................. 36045 2.3-1 Site Topography..................................................................................... 36046 2.4-1 Response Spectra Maximum 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

FCSI Information Use Introduction

1.

INTRODUCTION AND

SUMMARY

1.1 Introduction DSAR-1.1 Page 1 of 2 Rev. 3 By letters dated June 24 and August 25, 2016, OPPD notified the NRC of its intention to permanently cease power operations at Fort Calhoun Station (FCS) pursuant to 10 CFR 50.82(a)(1 )(i). On October 24, 2016, OPPD permanently ceased 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 the FCS reactor vessel and had been placed into the spent fuel pool. The letter acknowledged that upon docketing the certifications for permanent cessation of operations 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 OPPD (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 Technical Specifications (POTS). POTS 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 removal 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 original 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 operate the Fort Calhoun Station Unit No. 1, (AEC Docket 50 285, Construction Permit CPPR 41 ). By letter from NRC (J. Parrott) to OPPD (M. Fisher) "Fort Calhoun Station, Unit 1 - Issuance of Amendment Re: Revised Fort Calhoun Station Permanently 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 (POTS). This amendment removed all sections associated with the storage of fuel and relocated administrative requirements to appropriate documents. Based on the above, the DSAR has been revised to reflect the new license conditions and requirements.

FCSI Information Use Introduction DSAR-1.1 Page 2 of 2 Rev. 3 This report provided pertinent technical information in accordance with the requirements set forth under Title 10 of the Code of Federal Regulations, Part 50, (10 CFR Part 50) and information and analyses submitted to the NRC or prepared as a result of NRC requirements. The plant began commercial operation on September 26, 1973. Prior to decommissioning, the nuclear steam supply system (NSSS) was of the pressurized water type. It was similar in design to several facilities which began operation or were under review by the U.S. Atomic Energy Commission at the time the plant was pursuing 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 corresponded to a turbine-generator output 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 turbine-generator output of nominal 533.7 MWe at 0.90 power factor.

FCSI Information Use Summary Plant Description DSAR-1.2 Page 1 of 9 Rev. 8

1.0 INTRODUCTION

AND

SUMMARY

1.2 Summary Plant Description 1.2.1 Plant Site The site for the Fort Calhoun Station contains approximately 540 acres on the west bank of the Missouri River, approximately 19.4 miles north of Omaha, Nebraska. OPPD has a perpetual easement on approximately 117 acres of land on the east bank of the river directly opposite the plant buildings. On the Western part of the site the ground rises sharply 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 defined river bank in the vicinity 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 approximately 60 feet below the surface. Ground water level is close to existing grade and structures below grade are suitably water-proofed. An Independent Spent Fuel Storage Installation (ISFSI) is located in the protected area designated for dry storage of spent fuel and greater than class C waste (GTCC). The ISFSI is licensed under Subpart K of 10 CFR Part 72. The area adjoining the site is farmland and sparsely populated. The minimum controlled area distance is 1525 feet. The nearest population center area of more than 25,000 is formed by adjacent cities of Omaha, Nebraska and Council Bluffs, Iowa. The site vicinity plan is shown in Figure 1.2-1. The Site Area boundary consists of approximately 540 acres owned by Omaha Public Power District. The restricted area as defined in Section 20.1003of 10 CFR Part 20 is shown on Figure 1.2-1.

FCSI DSAR-1.2 Page 2 of 9 Rev. 8 Information Use Summary Plant Description A rail spur from the Chicago and Northwestern (CNW) Railway was constructed to serve the construction of the Fort Calhoun Station (FCS). The original CNW tracks and rail spur have since been removed. In 1994, a permanent easement was granted to allow the construction of a new rail spur in the approximate location of the old CNW railway to allow trains to serve the Cargill industrial facility located north of FCS. Road access to FCS is from U.S. Highway No. 75. 1.2.2 Station Arrangement Station status is continually changing during decommissioning. Current information on systems, radiological conditions and demolition progress is maintained by the Radiation Protection and Decommissioning organizations respectively. The principal station structures are the ISFSI Operating Facility (IOF) and ISFSI. The site's legacy buildings include the turbine building, intake structure, service building and hazardous material storage building. All are located outside of the Protected Area. Some specific system descriptions have been removed from the DSAR as all spent fuel has been removed from the Spent Fuel Pool to the ISFSI pad and these SSC no longer have a design function. The reactor, steam generators, reactor coolant pumps and pressurizer are located in the containment, together with other nuclear steam supply system (NSSS) components which no longer have a design function. A polar bridge crane is installed above the Containment operating floor, but no longer has a design function. The reactor auxiliaries include, engineered safeguards components, the control room, radiation controlled area (RCA) protective clothing 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 treatment facilities. A traveling bridge crane is located over the fuel handling and storage area in the auxiliary building. The traveling bridge crane no longer has a design function. The turbine building houses the turbine generator, condenser, and other turbine heat cycle components. These components no longer have a design function. The 150-ton traveling bridge crane no longer has a design function.

FCSI Information Use Summary Plant Description DSAR-1.2 Page 3 of 9 Rev. 8 The condenser cooling circulating water and raw water pumps are located in the intake structure. They no longer have a design function. Station Structures can contain provisions for dry active waste (DAW) processing, liquid radwaste filtration and ion exchange (FIX) equipment and radwaste solidification equipment. 1.2.3 Reactor and Reactor Coolant System The reactor and reactor coolant system are located in containment but no longer have a design function. 1.2.4 Deleted 1.2.5 Engineered Safeguards Systems The components which made up the engineered safeguards systems are located in the Auxiliary Building and Containment, but no longer have a design function. 1.2.6 Instrumentation and Control A. Deleted. B. Instrumentation Local control of the remaining instrumentation monitoring system function to support the remaining functional portions of the waste disposal, radiation monitors, and HVAC systems. All other process instrumentation and monitoring systems remain installed, but no longer have a design function. C. Deleted.

FCSI Information Use Summary Plant Description DSAR-1.2 Page 4 of 9 Rev. 8 1.2.7 Electrical Systems The source of energy for the ISFSI loads are the 13.8 kV circuit from the OPPD Substation, and a diesel-generator set located in the IOF. Power systems provide power to meet required remaining decommissioning support functions. Other legacy electrical systems remain installed, but no longer have a design function. 1.2.8 Auxiliary Systems The following systems remain installed but no longer have a design 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 Radioactive Waste Disposal System A. Fuel Storage Irradiated fuel bundles are not allowed to be stored in the SFP. The SFP system remains installed, but no longer has a design function. The ISFSI contains all fuel for storage prior to off-site shipment.

FCSI DSAR-1.2 Page 5 of 9 Rev. 8 Information Use Summary Plant Description OPPD has constructed an ISFSI, located in the Protected Area designated for dry storage of spent fuel. The ISFSI consists of the concrete basemat that was built on an elevated pad of compacted, engineered fill for flood protection, concrete horizontal storage modules, concrete shield walls, concrete approach slabs adjacent to the basemat, the ISFSI electrical equipment building, and the IOF. The ISFSI is designed for 42 horizontal storage modules arranged in a 2 x 21 back-to-back configuration. Each horizontal storage module holds one dry shielded canister for fuel storage or a canister containing greater than class C waste (GTCC) for storage. The HSM protects the canister(s) from natural phenomena such as tornado missiles, and is designed to provide for passive cooling of the canister by means of natural air circulation. The ISFSI basemat is 42 ft. wide by 211 ft. long, with its long dimension oriented in the east-west direction. The elevation of the top of the basemat is at 1009 ft-10 inches, above the level of the probable maximum flood. This DSAR for the Fort Calhoun Station does not assess the safety of the dry spent fuel storage system, which is licensed under Subpart K of 10 CFR Part 72 for general ISFSI licenses. Transnuclear, Inc., the storage system vendor, maintains the Final Safety Analysis Report for the NUHOMS Horizontal Modular Storage System (Reference 1-6). Certificate of Compliance No. 1004 (Reference 1-7) was issued by the NRC for the NUHOMS-system, with the 32PT DSC used at the Fort Calhoun Station ISFSI. The Technical Specifications for the NU HOMS storage system are included as Attachment A to Certificate of Compliance No. 1004. B. Plant Ventilation Systems Station Ventilation systems (serving the containment and part of the auxiliary building) handle airborne contaminants so that offsite concentrations and in plant doses (which are controlled by the ODCM and administrative procedures) are within 10 CFR Part 20 limits. Portions of the remaining plant ventilation systems remains installed but no longer have a design function. C. Plant Fire Protection

FCSI DSAR-1.2 Page 6 of 9 Rev. 8 Information Use Summary Plant Description In November 2016, OPPD certified to the NRC per 10 CFR 50.82(a)(1) that fuel had been permanently removed from the reactor vessel. With this certification, 10 CFR 50.48(f) became applicable to the fire protection program. Subsequently, Amendment No. 290 to the Renewed Facility License DPR-40 deleted the fire protection program as a License Condition. The fire protection program is now maintained in accordance with 10 CFR 50.48(f). These programs address both the site and the ISFSI (CC-FC-211 and FCSI-FP-100). 1.2.9 Deleted

FCSI Information Use Summary Plant Description DSAR-1.2 Page 7 of 9 Rev. 8 1.2.10 Radioactive Waste Disposal Radioactive waste is managed during decommissioning through the use of permanent and temporary liquid, gaseous and solid treatment systems. These systems collect, process, monitor and regulate the discharge of potentially radioactive wastes from the site. The waste equipment used for radioactive waste processing and disposal are designed to protect plant personnel and the public from exposure to radioactive wastes in accordance with 10 CFR Part 20; 10 CFR 50, Appendix I; 40 CFR Part 190; 10 CFR 50 Appendix A General Design Criterion 60, and Draft GDC Criteria 17 and 18. This equipment along with approved procedures will provide the administrative controls to ensure that the radioactive releases are completed within the allowable concentrations and dose limitations defined in the Quality Assurance Topical Report (QATR), Appendix E and the Offsite Dose Calculation Manual (ODCM) A. Liquid Effluents shall be limited to less than ten times 10 CFR Part 20, Appendix B, Table 2, Column 2 concentrations at discharge as described within the ODCM. B. Gaseous The Five year average dispersion factor (x/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 solid wastes produced at the station are processed in accordance with radiological requirements in the ODCM 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 public.

FCSI Information Use Summary Plant Description Containment Building DSAR-1.2 Page 8 of 9 Rev. 8 The containment has one major shielding function: It shields adjacent auxiliary plant and yard areas from radiation originating from inside the containment. Auxiliary Building Adequate shielding is provided around equipment that carries radioactive liquid, slurry or gas. Radioactive Waste Processing Building Adequate shielding is provided for each room in the Radioactive Waste Processing to permit continuous occupancy in general access areas. E. Radiation Monitoring Radiation monitors are provided for radiological controls and ODCM requirements F. Miscellaneous Radioactive Material Sources Miscellaneous radioactive material sources are controlled by Radiation 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 Consequences of a High Integrity Container (HIC) Drop Event (Reference 1-18), provide quantity and design incidents for radiological solid (postulated gas) releases. This calculation supports the ISFSI Only Emergency Plan (IOEP) license, which assumes onsite deconstruction activities are administratively controlled. The radioactive waste handling events have been postulated to be the limiting events for decommissioning activities and does not rely on any equipment for mitigation.

FCSI DSAR-1.2 Page 9 of 9 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 Renewed Facility Operating License No. DPR-40 allows the design and/or analysis of piping to be performed in accordance with ASME Section Ill, 1980 Edition (no Addenda) as an alternative to USAS B31.7, 1968 (DRAFT) Edition. There is no longer any safety class components at the station.

FCSI 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 DSAR-1.11 Page 1 of 2 Rev. 5 1-6 Final Safety Analysis Report for the Standardized NU HOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel (NUH-003), Transnuclear Inc., Revisions 9, 10, and 18. 1-7 Renewed Certificate of Compliance No. 1004, Amendments No. 8, 9, and 15, issued to Transnuclear, Inc. for Standardized NUHOMS-24P, -52B, -61 BT, - 24PHB and -32PT, including Attachment A, Technical Specifications, 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 Desk), "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 Desk), "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 Desk), "Certification of Permanent Removal of Fuel from the Reactor Vessel," dated November 13, 2016 (LIC-16-0074).

FCSI Information Use Specific References DSAR-1.11 Page 2 of 2 Rev. 5 1-16 Letter from NRC (J. Kim) to OPPD (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 to Revise Fort Calhoun Station Permanently Defueled Technical Specifications to Align to the Requirements for Permanent Removal of Spent Fuel from Spent Fuel Pool" Dated December 11, 2019 (NRC-19-026) 1-18 Calculation FC08566, Dose Consequences of High Integrity Container (HIC) Drop Event.

FCSI

2.

SITE AND ENVIRONS ARCHIVED TEXT* 2.1 Introduction Information Use Introduction DSAR-2.1 Page 1 of 1 Rev. 3 This section outlines the bases for the remaining selection of design criteria for Fort Calhoun Station and provides the background data required to substantiate the proposed methods for controlling and assessing routine and accidental releases of radioactive liquids and gases to the environment. Field programs to investigate site geology, seismology, and subterranean hydrology have been completed. The site of the power station is located at 96 degrees, 4 minutes and 39 seconds west longitude and 41 degrees, 31 minutes and 14 seconds north latitude in Washington County, Nebraska, on the southwest bank of the Missouri River at river mile 646.0, approximately 2.4 miles south-southeast of the Chicago and Northwestern Railway bridge at Blair, Nebraska. The site is 19.4 miles north-northwest of the intersection of 16th Street and Dodge Street in the city of Omaha. Meteorologically, hydrologically, geologically, and seismologically, this site is favorable for a nuclear power station. The plant is designed, nevertheless, so that there will be no uncontrolled release of radioactive material during decommissioning operations. Radioactive effluents, both gases and liquids, will be released in a controlled manner to ensure that they are below allowable limits. Dames and Moore, consulting engineers in the applied earth sciences, conducted investigations in site geology, seismology, subterranean hydrology 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 ORB) not meaningful to update.

FCSI Information Use General Description of Site and Environs

2.

SITE AND ENVIRONS 2.2 General Description of Site and Environs DSAR-2.2 Page 1 of 4 Rev. 6 The post permanent shutdown site extent is approximately 540 acres; approximately 445 acres of this area is on the alluvial flood plain of the Missouri River, and the remainder is part of the bluff system on the southwest side of the river. -An additional exclusion area of approximately 117 acres is included on the northeast bank of the river directly opposite the industrial area. This additional exclusion area is provided by means of perpetual easements which allows OPPD to restrict or prohibit access should evacuation be necessary. More specifically on October 28, 1969, the owners of property located across the Missouri River from OPPD's Fort Calhoun facility executed easements in perpetuity 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 stated, the undersigned owners of real estate hereinafter described, their heirs, executors, administrators, successors and assigns, hereinafter called "Granter" hereby grant and convey to the Omaha Public Power District, its successors and assigns, hereinafter called "District", a perpetual easement over, along and upon the following described accretion land owned by the Granter and sometimes described as: October 28, 1969 Agreement: From the South 1/4 corner of Section 17, Township 18 North, Range 12 East of the 6th P.M., Washington County, Nebraska; thence North 00° 10'15" West along the 1/4 line a distance of 2,088.27 feet to the point of beginning, said point being on the right bank of the designed channel of the Missouri River, thence 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 4 77.30 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 366.4 7 feet; South 46°48' East a distance of 468.26 feet; South 41 °07' East a distance of 282.40 feet;

FCSI Information Use General Description of Site and Environs DSAR-2.2 Page 2 of 4 Rev. 6 To intersect the projected centerline of Broadway Street in Old DeSoto Townsite; thence South 32° 35' West along said center line a distance of 925.90 feet to intersect the right bank of the designed channel of the Missouri River, thence 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 4 7°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. 7 4 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 the 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 described property is part of an exclusion area, now defined in the rules and regulations published by the United States Atomic Energy Commission, and more particularly by Title 10 - Atomic Energy, Part 100, 100.3 Definitions, (a) thereof, which exclusion area is an integral part of the District's nuclear power plant site, the balance of which lies on the Nebraska side of the Missouri River opposite said property and in said County. "3. The Grantor may make any use of the above described property for their own benefit, except that the Grantor shall 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 a exclusion area, or which shall be prohibited by any law or regulation now or hereafter enacted by proper public authority, either governing or applicable to the use and maintenance of said property as a exclusion area as now or hereafter defined, or otherwise. "4. Grantor specifically covenants that no structure shall be built and that any structure now existing upon said land shall not be occupied at any time by any person or persons."

FCSI Information Use General Description of Site and Environs DSAR-2.2 Page 3 of 4 Rev. 6 "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 emergency should occur in connection with the operation of District's power plant, which in District's opinion would require such action in the interest of public health and safety, District may, without notice, 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 time as said emergency has passed. "7. The District shall reimburse the Grantor for any crop damage that might occur as a result of the District's personnel or any of its representatives 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, title and interest of ownership of the above described property to Grantor herein. "9. It is further agreed that Grantor has lawful possession of said real estate, good, right and lawful authority to make said conveyance and that their heirs, executors, administrators, successors and assigns shall warrant and defend same and will indemnify and hold harmless to the District forever against claims of all persons whomsoever in any way asserting any right, title or interest prior to or contrary to this conveyance. In the opinion of counsel, paragraphs 3 and 6 of these agreements give OPPD ample legal authority to vacate said property in the event that an emergency 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. Approximately 354 acres of the total approximately 540 acres are under cultivation. The environmental monitoring program is performed in accordance with the ODCM. The area adjacent to the site is farm land and is sparsely populated. The nearest population area is the town of Blair, Nebraska, approximately 3.4 miles 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 metes and bounds of the site.

FCSI Information Use General Description of Site and Environs DSAR-2.2 Page 2 of 4 Rev. 6 Both private and commercial traffic make use of U. S. Highway No. 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, therefore, 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 traffic is considered minimal since the site is not located near landing patterns or runways of any large commercial or military airport facility.

FCSI

2.

SITE AND ENVIRONS ARCHIVED TEXT* 2.3 Topography Information Use Topography DSAR-2.3 Page 1 of 1 Rev. 1 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 above 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 gradually 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 limits are under control of the Corps who have established a structure azimuth line which acts as another site boundary. The site drainage development program 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.

• 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.

FCSI Information Use Seismology DSAR-2.4 Page 1 of 5 Rev. 3

2.

SITE AND ENVIRONS ARCHIVED TEXT 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 moderately compact silty sand and deeper sands and gravels resting on sedimentary bedrock. The bedrock is generally 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 sediments of the Missouri River lowlands. The closest known regional structures in the vicinity of the site are the Nehawka-Richfield Arch and the La Platte Fault. The Nehawka-Richfield Arch extends from near Omaha-Council Bluffs south and southwest for about 20 to 30 miles. There is no record of movement of the fault in historic times, or any indication of activity in recent geologic time. One of the major structural features of the Nebraska-Iowa region is the Thurman-Wilson Fault which extends from south of Lincoln, Nebraska, northeast for about 150 miles, almost to Des Moines, Iowa. There is no record of movement of this fault in historic times. 2.4.2 Seismicity The epicenters of several shocks in the region with a Modified Mercalli Intensity greater than V are located in a zone south of Omaha parallel to the Nemaha Uplift and the Abilene Arch. The epicenters fall between the Salina Basin on the west and the Forest City Basin on the east. Other activity is centered south and west of the Sioux Uplift, northwest of the site. Epicentral locations of all known earthquakes in the vicinity of the site with Modified Mercalli Intensity V were tabulated in the Dames and Moore study referenced in Appendix B.

• 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.

FCSI Information Use Seismology DSAR-2.4 Page 2 of 5 Rev. 3 ARCHIVED TEXT A number of smaller earthquakes have been experienced in the Nebraska-Iowa region. The epicenters of some of these shocks were along the Missouri, Platte and Solomon Rivers. Studies in Illinois indicate a possible relationship between river load and earthquake occurrence, but no similar studies have been performed for this area. In general, because of poor records and lack of damage associated with these smaller shocks, they are of little significance. The significant shocks, i.e., those within 200 miles of the site, were tabulated. On the basis of this history, it is evident that the site lies in a region of infrequent seismic activity. Since the middle of the 19th century, from the first historical record of earthquake occurrence in the area, only 12 shocks with epicentral Modified Mercalli Intensities of V or greater have occurred within 200 miles of the plant site. These 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 intensities of Modified Mercalli VII. Three shocks of this intensity originated within 200 miles of the site. Of these, the closest occurred in November 1877 near Lincoln, Nebraska, about 60 miles from the site. Two shocks were 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 slightly higher on the Richter Scale. A shock of Modified Mercalli Intensity VII occurred in April 1867, near Manhattan, Kansas, about 170 miles from the site, and was felt over an area of 300,000 square miles. It is estimated that this shock had an intensity of about 5-1/2 on the Richter Scale. Another shock of Modified Mercalli Intensity VII occurred in the same area in January 1906, and was perceptible over an area of 10,000 square miles. The magnitude of this shock was probably not more than 5 on the Richter Scale. Only one earthquake of Modified Mercalli Intensity VI has been reported within 200 miles of the site. It occurred in March 1935, near Tecumseh, Nebraska, and was felt in an area over 50,000 square miles. Eight earthquakes of Modified Mercalli Intensity V have been reported within 200 miles of the site. The earthquake with its epicenter nearest the site occurred in February 1910, near Columbus, Nebraska, about 65 miles from the site. No significant structural damage occurred.

• 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.

FCSI Information Use Seismology DSAR-2.4 Page 3 of 5 Rev. 3 ARCHIVED TEXT No damaging earthquakes have been reported within 50 miles of the site. While some of the regional shocks were undoubtedly felt in the locality of the site, no significant damage would be expected in even moderately well-built structures from a recurrence of these disturbances. It is probable that the earthquake of November 1877, was felt at the site with an intensity of about Modified Mercalli V. No major earthquake has occurred near the site. The closest major shock was about 500 miles to the southeast. In 1811 and 1812 a series of large shocks were experienced near New Madrid, Missouri, but these shocks 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 history of the region no significant earthquake ground motion is expected at the site, occasional shocks along the Missouri River and a continuation of shocks in the belt extending northward from the Abilene Arch to the Sioux Uplift could be postulated. For conservatism in the determination of appropriate seismic criteria the proximity of a fault to the site is considered. On this basis, and in accordance with the recommendations of the U.S. Coast and Geodetic Survey (USC&GS), site seismic criteria has been established.

• 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.

FCSI Information Use Seismology DSAR-2.4 Page 4 of 5 Rev. 3 2.4.4 Design and Maximum Hypothetical Earthquakes The following criteria was applied to components, structures and equipment for the design earthquake and maximum 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 0.08g acting in the vertical direction simultaneously, in combination with the primary steady state stresses, are maintained within the allowable working stress limits accepted as good practice and, where applicable, 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 Pressure Piping, ACI 318 Building Code Requirements for Reinforced Concrete, and AISC Specifications for the Design and Erection of Structural 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 seismic 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 the vertical direction simultaneously, in combination with the primary steady state stresses, are limited so that the function of the component, system or structure is not impaired in such a manner that function is prevented. Structures no longer have any design features that are credited in any event analysis. 2.4.5 Conclusions The site is subject to infrequent slight ground motion from regional shocks.

• 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.

FCSI ARCHIVED TEXT Information Use Seismology DSAR-2.4 Page 5 of 5 Rev. 3 2.4.6 References 2.4.6.1 2.4.6.2 2.4.6.3 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) 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) FCS-203087-USAR-2.4, Revision 1, USAR 2.4 Verification Summary Report (EC 67224)

• 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.

FCSI Information Use Meteorology DSAR-2.5 Page 1 of 11 Rev. 5

2.

SITE AND ENVIRONS 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 ocean. Nebraska is located midway between two distinctive climatic zones, the humid east and the dry west(4l. Thus, cyclic weather conditions representative of either zone, or combinations of both occur. Changes in weather result from the invasion of large masses of air with dissimilar properties. These air masses tend to get their 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(6l. The region is also affected by many storms or cyclones (areas of low pressure) which travel across the country, generally from west to east. Thus, periodic and rapid changes in the weather are normal, especially in the winter(3). 2.5.2 Local Meteorology Data from proximal long-term National Weather Service (NWS) Stations have been used to supplement the existing Fort Calhoun Station data in formulating 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 Fort Calhoun Station has been archived in Table 2.5-1. The elevation of the North Omaha NWS wind sensor was 20 feet above ground during the five-year period, while the elevation of the Fort Calhoun wind sensor was 10 meters above ground. Further discussion on the on-site data for 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.

FCSI 2.5.2.2 2.5.2.3 2.5.2.4 Precipitation DSAR-2.5 Page 2 of 11 Rev. 5 Information Use Meteorology 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 maximum 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 amounts of snow and ice pellets (including sleet) for Eppley Airfield and the North Omaha NWS are archived in Table 2.5-4. Temperatures The monthly temperatures at Eppley Airfield and the North Omaha NWS for the period 1961 through 1990 are archived in Table 2.5-5. This table also shows the record high and record low temperatures recorded at both locations through 1990. Annual extremes have been received at other locations in the Omaha vicinity as follows: a record high of 114 °F in July, 1936, and a record low of -32°F in January, 1885(4)_ Monthly and annual temperature normals for Eppley Airfield, North Omaha NWS and Blair are archived in Table 2.5-6(4)_ These show close agreement. Relative Humidity The average relative humidity values for Eppley Airfield, the North Omaha NWS, and the Fort Calhoun Station for four times of the day are archived in Table 2.5-7. The mean number of days with heavy fog (visibility 3 mile or less) at Eppley Airfield and the North Omaha NWS are archived in Table 2.5-8. 2.5.2.5 Thunderstorms The mean number of days with thunderstorms at Eppley Airfield and the North Omaha NWS are archived in Table 2.5-9. A maximum frequency of approximately 9.5 thunderstorms occur during the month of June. This decreases to a minimum of approximately 0.1 thunderstorms during the month of January.

FCSI Information Use Meteorology DSAR-2.5 Page 3 of 11 Rev.5 2.5.2.6 Atmospheric Stability Wind direction and speed data are presented in relative frequency distribution (in percent) by stability classes. 2.5.2.7 Topographical Description and Its Influence on Site Meteorology 2.5.2.8 The terrain in the vicinity of Fort Calhoun Station is generally flat from the north, northeast, east and southeast sectors, with an elevation of approximately 1000 feet above mean sea level (msl), for a radius of at least 10 miles. This terrain is generally the flood plain of the Missouri River. Terrain in the remaining sectors, south-southeast through 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 western bank of the Missouri River, which runs generally from the northwest to the southeast, and come within about one mile of the Fort Calhoun Station in the south through west-southwest 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 slowing down of weak winds as air flows across the river from east to west and meets the rising terrain to the west. However, neither of these effects are regarded as significant in their influence on site meteorology and should not, under most synoptic weather types, severely skew the strong measures of covariation (+0.75 to +1.00) which exist between the site and other meteorological stations. Tornadoes Amendment 272(37) revised the DBT and associated tornado missiles for Fort Calhoun Station (FCS) to that defined in Regulatory Guide (RG) 1.76, Revision 1 (33)_ This ensures that designated SSCs are adequately protected from the DBT and associated tornado missiles. Tornado Missiles The physical properties and velocities of tornado generated missiles are described in Regulatory Guide 1.76, Revision 1.

FCSI Information Use Meteorology DSAR-2.5 Page 4 of 11 Rev. 5 ARCHIVED TEXT* Wind Direction NNE NE ENE E ESE SE SSE s SSW SW WSW w WNW NW NNW N Missing Average Table 2.5 Climatological Normals, Comparison of North Omaha NWS with Fort Calhoun Station WIND DIRECTION (PERCENT) WIND SPEED (MPH) North Omaha NWS Fort Calhoun North Omaha NWS Fort Calhoun (1985-1989) (1985-1989) (1985-1989) (1985-1989) 3.8 2.6 8.2 4.9 3.3 2.4 6.9 4.6 3.2 2.4 6.5 4.5 3.1 3.1 6.7 5.0 5.4 5.7 6.8 5.4 7.1 9.0 7.8 6.8 10.0 10.2 9.9 8.9 10.8 10.1 10.4 9.5 9.1 7.2 9.5 9.3 4.3 3.7 8.5 7.5 2.4 3.0 7.2 5.5 3.9 4.5 7.7 4.4 5.3 7.6 10.1 4.6 8.6 10.7 12.9 6.6 6.8 9.4 12.8 6.5 13.0 5.5 8.0 5.9 2.9 2.9 8.7 6.3 NOTE: The wind speeds at the North Omaha NWS were recorded 20 feet above ground level, and the wind speeds at Fort Calhoun Station were recorded at 10 meters, above ground level. Data obtained from the Local Climatological Data; see References 4 and 5.

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ARCHIVED TEXT* Fastest Period Wind Speed (1949-1990) January 57 February 57 March 73 April 65 May 73 June 72 July 109 August 66 Septembe 47 r October 62 November 56 December 52 Year 109 Information Use Meteorology DSAR-2.5 Page 5 of 11 Rev. 5 Table 2.5 Maximum Recorded and Mean Wind Speeds (MPH) EPPLEY AIRFIELD NORTH OMAHA NWS Direction Mean Fastest Direction (Degrees) Year (1936-1990) Wind Speed (Degrees) Year (1979-1990) NW 1938 10.9 41 NW 1978 NW 1947 11.1 38 NW 1978 NW 1950 12.3 38 NW 1982 NW 1937 12.7 46 NW 1982 NW 1936 10.9 34 N 1983 N 1942 10.1 34 NW 1983 N 1936 8.9 46 NW 1980 N 1944 8.9 39 NW 1980 E 1948 9.5 35 NW 1980 NW 1966 9.8 34 NW 1979 NW 1951 10.9 38 NW 1982 NW 1938 10.7 37 NW 1981 N 1936 10.6 46 NW 1982 Mean (1985-1990) 10.4 9.6 10.9 10.6 8.9 8.4 7.5 7.7 8.4 8.9 9.9 9.9 9.3 NOTE: The wind speeds at Eppley Airfield were recorded at 70 feet above ground level (agl) until 1974; 20 feet agl since that time. The wind speeds at the North Omaha NWS were recorded at 20 feet agl. Data obtained from the Local Climatological Data; see References 4 and 5.

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ARCHIVED TEXT* Monthly Monthly Period Normal Maximum January 0.77 3.70 February 0.91 2.97 March 1.91 5.96 April 2.94 6.45 May 4.33 10.33 June 4.08 10.81 July 3.62 9.60 August 4.10 10.16 September 3.50 13.75 October 2.09 4.99 November 1.32 4.70 December 0.77 5.42 Year 30.34 13.75 Information Use Meteorology DSAR-2.5 Page 6 of 11 Rev. 5 Table 2.5 Normal and Extreme Precipitation Amounts (Inches) EPPLEY AIRFIELD (1936-1990) NORTH OMAHA (1954-1990) Monthly 24-Hour Monthly Monthly Monthly Year Year Maximum Year Year Year Minimum (1942-1990) Normal Maximum Minimum 1949 Trace 1986 1.52 1967 0.70 1.85 1975 Trace 1986 1965 0.09 1981 2.24 1954 0.95 2.86 1965 0.09 1968 1973 0.12 1956 1.45 1990 2.00 5.27 1983 0.06 1956 1951 0.23 1936 2.56 1938 2.74 7.12 1984 0.15 1962 1959 0.56 1948 4.16 1987 4.26 9.09 1959 0.55 1989 1947 1.03 1972 3.48 1942 4.21 8.16 1984 0.95 1972 1958 0.39 1983 3.37 1958 3.50 9.77 1958 0.29 1975 1982 0.61 1984 5.27 1987 4.19 11.77 1960 0.63 1971 1965 0.41 1953 6.47 1965 3.36 14.10 1965 0.96 1990 1961 Trace 1952 3.13 1968 2.11 5.34 1986 0.06 1958 1983 0.03 1976 2.53 1948 1.16 5.11 1983 0.03 1989 1984 Trace 1943 3.03 1984 0.76 4.45 1984 0.02 1958 1965 Trace 1986 6.47 1965 29.94 14.10 1965 Trace 1986 NOTE: Data obtained from the Local Climatological Data; see References 4 and 5. 24-Hour Maximum (1977-1990) 0.95 0.64 2.04 2.59 3.10 2.77 3.72 3.74 2.77 2.61 2.16 3.10 3.74

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Year 1982 1978 1982 1986 1987 1988 1977 1987 1989 1986 1983 1984 1987

ARCHIVED TEXT* Information Use Meteorology DSAR-2.5 Page 7 of 11 Rev. 5 Table 2.5 Normal and Extreme (Maximum) Snow and Ice Pellet Amounts (Inches) EPPLEY AIRFIELD (1936-1990) NORTH OMAHA (1954-1990) Monthly 24-Hour Monthly 24-Hour Period Normal Year Maximum Year Normal Year Maximum Maximum (1942-1990) Maximum (1976-1990) January 7.3 25.7 1936 13.1 1949 7.0 21.5 1975 6.0 February 6.8 25.4 1965 18.3 1965 6.7 23.2 1965 10.0 March 6.6 27.2 1948 13.0 1948 7.2 23.3 1960 13.3 April 0.8 8.6 1945 8.6 1945 1.2 10.3 1983 4.8 May 0.1 2.0 1945 2.0 1945 Trace 0.7 1967 0.0 June Trace Trace 1990 Trace 1990 0.0 0.0 0.0 July 0.0 0.0 0.0 0.0 0.0 0.0 August 0.0 0.0 0.0 0.0 0.0 0.0 September Trace Trace 1985 Trace 1985 Trace 0.3 1985 0.3 October 0.3 7.2 1941 7.2 1941 0.4 5.2 1980 5.2 November 2.5 12.0 1957 8.7 1957 3.2 13.9 1957 8.5 December 5.7 19.9 1969 10.2 1969 5.5 19.3 1969 7.5 Year 30.0 27.2 1948 18.3 1965 31.3 23.3 March 13.3 1960 NOTE: Data obtained from the Local Climatological Data: see References 4 and 5. Year 1979 1978 1987 1979 1985 1980 1983 1984 March 1987

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ARCHIVED TEXT* (1961-1990) Period Daily Daily Maximum Minimum January 31.1 12.7 February 35.8 17.1 March 47.5 27.8 April 62.4 41.1 May 73.0 52.2 June 82.5 61.9 July 87.7 67.1 August 85.2 64.9 September 76.9 55.6 October 65.5 43.7 November 48.6 29.6 December 35.6 18.4 Year 61.0 41.0 Information Use Meteorology DSAR-2.5 Page 8 of 11 Rev. 5 Table 2.5 Normal and Extreme Temperatures (EF) EPPLEY AIRFIELD NORTH OMAHA (1936-1990) (1961 -1990) Monthly Record Year Record Year Daily Daily Monthly Record Normal High Low Maximum Minimum Normal High 21.9 69.0 1944 -23.0 1982 29.3 11.1 20.2 66 26.5 78.0 1972 -21.0 1981 34.3 16.0 25.1 76 37.7 89.0 1986 -16.0 1948 46.4 26.9 36.7 88 51.8 97.0 1989 5.0 1975 60.2 38.6 49.4 96 62.6 99.0 1939 27.0 1980 70.6 50.0 60.3 100 72.2 105.0 1953 38.0 1983 81.6 60.9 71.3 104 77.4 114.0 1936 44.0 1972 85.9 66.0 76.0 107 75.1 110.0 1936 43.0 1967 83.8 63.8 73.8 106 66.3 104.0 1939 25.0 1984 74.9 54.3 64.6 103 54.6 96.0 1938 13.0 1972 64.0 42.7 53.4 93 39.1 80.0 1980 -9.0 1964 47.4 28.7 38.1 79 27.0 72.0 1939 -23.0 1989 33.8 16.4 25.1 66 51.0 114.0 1936 -23.0 1989 59.3 39.6 49.5 107 NOTES: 1. Data obtained from the Local Climatological Data; see References 4 and 5. (1954-1990) Year Record Year Low 1981 -22 1982 1972 -20 1981 1986 -16 1960 1989 7 1975 1967 25 1967 1988 41 1956 1974 44 1971 1983 44 1986 1955 28 1984 1975 16 1972 1980 -11 1964 1976 -25 1989 1974 -25 1989

2. At the time of containment design/construction the lowest recorded temperature at Eppley Airfield was -22.0°F (January 1974).

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ARCHIVED TEXT* Period January February March April May June July August September October November December Year Information Use Meteorology DSAR-2.5 Page 9 of 11 Rev. 5 Table 2.5 Monthly and Annual Temperature Normals (°F) Eppley Airfield (1936-1990) North Omaha NWS (1954-1990) 20.2 18.7 27.2 25.3 37.3 35.2 52.2 50.4 63.3 61.7 73.0 71.2 77.7 75.7 75.2 73.5 65.8 64.4 54.5 53.6 39.5 38.0 27.2 25.7 51.1 49.5 NOTE: Data obtained from references 4 and 5. Blair (1941-1970) 20.8 26.0 35.2 50.9 61.5 70.8 75.5 73.9 64.3 54.8 38.7 26.6 49.9

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ARCHIVED TEXT* DSAR-2.5 Page 10 of 11 Rev. 5 Information Use Meteorology Table 2.5 Comparative Relative Humidity Values for Eppley Airfield (1964-1990), North Omaha (N.O.) (1984-1990), and Fort Calhoun (1969-1975) 0000* 0600* 1200* 1800* 24 Hour Average Period Eppley N.O. Ft. Eppley N.O. Ft. Eppley N.O. Ft. Eppley N.O. Ft. Eppley N.O. Ft. Calhoun Calhoun Calhoun Calhoun Calhoun January 75 70 82 78 74 83 65 60 71 66 60 76 70 66 78 February 76 71 82 79 75 84 63 61 70 63 62 72 70 67 77 March 72 69 80 78 77 84 57 57 66 54 54 65 65 64 74 April 68 65 72 77 75 80 52 51 59 48 46 54 62 60 66 May 72 69 75 80 78 83 54 54 61 51 51 54 64 63 68 June 75 68 75 82 77 83 55 54 59 52 50 52 66 62 67 July 78 75 77 84 83 83 57 60 60 55 57 56 69 69 69 August 80 79 82 86 87 88 59 62 65 58 61 58 71 72 75 September 81 77 82 87 84 88 59 60 65 59 60 60 72 70 74 October 76 69 79 82 78 87 55 55 65 56 56 63 67 65 74 November 76 72 85 81 77 88 62 61 72 65 64 77 71 69 80 December 78 73 84 80 76 87 67 66 74 71 69 80 74 71 81 Year 76 71 80 81 78 85 59 58 66 58 58 64 69 66 74

• Local Standard Time NOTE: Data obtained from the Local Climatological Data; see References 4 and 5. Fort Calhoun data obtained from PSAR and archived meteorological data files.
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ARCHIVED TEXT* Table 2.5 Mean Number of Days with Heavy Fog (Visibility 1/4 Mile or Less) Period Eppley Airfield North Omaha NWS (1935-1990) (1975-1990) January 1.8 1.2 February 1.9 2.1 March 1.4 2.5 April 0.5 0.6 May 0.8 0.8 June 0.4 0.6 July 0.5 0.3 August 1.5 1.1 September 1.4 0.9 October 1.5 1.1 November 1.6 1.9 December 2.1 2.7 Year 15.4 15.8 Information Use Meteorology DSAR-2.5 Page 11 of 11 Rev. 5 Table 2.5 Mean Number of Days with Thunderstorms Period Eppley Airfield North Omaha NWS (1935-1990) (1975-1990) January 0.1 0.1 February 0.4 0.4 March 1.5 1.9 April 3.8 3.4 May 7.4 7.7 June 9.4 9.5 July 8.2 8.8 August 7.8 8.1 September 5.3 6.0 October 2.4 2.3 November 0.8 0.7 December 0.2 0.2 Year 47.2 49.0

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FCSI Information Use Geology DSAR-2.6 Page 1 of 4 Rev. 1

2.

SITE AND ENVIRONS ARCHIVED TEXT 2.6 Geology 2.6.1 Physiography Topographically, the site is part of the Missouri River bottom land, which is a nearly level plain about 15 miles wide at Blair, 8 miles wide at the site and narrowing to 3 miles wide in the vicinity of Omaha-Council Bluffs. The elevation of this plain averages about 1,000 feet above mean sea 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 consisting primarily of limestone, shale, and sandstone. There are no bedrock outcrops on the site, but there are exposures within 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 with 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 vicinity of the site. The dominant structural features of the Nebraska-Iowa region include the Thurman-Wilson Fault which extends from 12 miles southeast of Lincoln, Nebraska, northeast for approximately 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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FCSI Information Use Geology DSAR-2.6 Page 2 of 4 Rev. 1 ARCHIVED TEXT The Forest City Basin which is approximately 100 miles southeast of the Omaha area lies along the downthrown east flank of the Nemaha Ridge, 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 at the Nebraska-Kansas line, near the Missouri Border. The Salina Basin and its northern extension, the Central Nebraska Basin are approximately 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 indicate that a limb of this uplift may extend northward into the Omaha area and possibly farther. The closest known regional fault is the La Platte Fault which cuts across the Nehawka-Richfield Arch in the lower Platte River Valley. It apparently crosses the Thurman-Wilson Fault some 60 miles south of the site. This nearly vertical fault has a maximum 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 was marked by long periods of marine inundation which resulted in deposition of thick beds of limestone, dolomite, shale, and sandstone. In later Paleozoic time, shorter and more frequent periods of alternating marine and continental deposition occurred resulting in the production of thin coal beds and layers of shale, limestone, and some sandstones.

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FCSI Information Use Geology DSAR-2.6 Page 3 of 4 Rev. 1 ARCHIVED TEXT The major tectonic features of the mid-continent region began to develop late in the Paleozoic Era, and probably most of the important structural features of the Nebraska Iowa Missouri River Valley area had already developed 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 movements. The undisturbed beds of the Cretaceous Dakota formation indicate the lack of tectonic activity since that time. During the Pleistocene period, when the interior of the continent was covered by continental glaciers, Nebraska was occupied by only the first 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 deposition of additional till and outwash by subsequent glaciation. Ice damage to streams during this period resulted further in a deposition of lacustrine sands and gravels. Nebraska and western Iowa were not covered by later ice sheets, but during the retreat and advance of these ice sheets nearby, windblown deposits of fine sand and silt accumulated to thicknesses of as much as 100 feet. These deposits, known as loess, form the steep sided hills and bluffs of eastern Nebraska and western Iowa. Recent erosion and alluvial deposition have altered the landscape to its present form. 2.6.6 Glacial History of the Missouri Valley At the beginning of the Pleistocene period, the Missouri River Valley and its main tributaries were established in their approximate present positions. Subsequently under successive glacial movements, the valleys were filled and re-opened several times. During 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 actually of recent age and that deeper deposits are mostly of Pleistocene age.

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FCSI Information Use Geology DSAR-2.6 Page 4 of 4 Rev. 1 ARCHIVED TEXT 2.6.7 Site Geology Unconsolidated sediments at the plant site generally range from 65 to 75 feet in thickness. The soils are typically interstratified and cross-bedded. The beds change facies or grade laterally so rapidly that no bed lithologic correlation is possible from boring 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 in 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 thickness of seven feet. The bedrock consists of various types of limestone formations. 2.6.8 Conclusions The bedrock beneath the site provides suitable support for the plant structures. There is no geologic feature of the site or surrounding area which adversely affects the use of the site for a nuclear power plant.

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FCSI Information Use Hydrology DSAR-2.7 Page 1 of 5 Rev. 4

2.

SITE AND ENVIRONS 2.7 Hydrology 2.7.1 Surface Drainage 2.7.1.1 2.7.1.2 General The plant site is bounded on the northeast and southeast by a portion of Blair Bend of the Missouri River. The Corps maintains river structures to prevent further meandering of the channel within the alluvial flood plain; the 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, or 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 the reservoir system for 200 years or more. 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 the Fort Calhoun site. Rainfall sufficient to cause an appreciable flood would have to be heavy and occur over an extensive area.

FCSI Information Use Hydrology DSAR-2.7 Page 2 of 5 Rev. 4 2.7.2 Ground Water 2.7.2.1 2.7.2.2 General Ground water is from two sources. The first is the Missouri River Valley, where ample ground water is obtained from the Pleistocene Valley fill and alluvial sand and gravels. The water table ranges from 2 to 17 feet below the surface, and coincides with the elevation of the river in the bottom land adjacent to the river. The second source of ground water are the terraces and loess hill upland regions. In these areas, the majority of wells 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 along the base of the bluff confirms the movement of ground water from the hills to the river. The development and use of ground water adjacent to the Missouri River and downstream of the 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. Site Water Table and Transmissibility Water levels taken in a series of borings drilled during July and August, 1966, reveal that the ground water levels at the site varied from elevations 993.7 to 992.4 feet, while the river levels recorded 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 flow in the alluvial soils varies with the permeability. However, rate of flow is very low, because of the low gradients, and again, is toward the river. The coefficient of permeability varied from about one-half to three feet per day in the upper sandy silt and silty sand. In the lower fine-to-coarse sand and gravel, coefficients of permeability as high as 20 feet per day were measured.

FCSI DSAR-2.7 Page 3 of 5 Rev. 4 Information Use Hydrology A pumping test was conducted to evaluate the gross permeability and transmissibility characteristics 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 was between 1,300 and 1,800 feet. The gross permeability of the deep water 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. Such fluids would percolate slowly in the direction of the Missouri River. Thus, hydrological conditions are favorable for the location and operation of a nuclear facility. Groundwater monitoring wells (both shallow and deep) are installed at FCSSoils observed during the advancement of the well borings consisted primarily of unconsolidated lean clay, silt, and sand. These materials appear to be representative of Missouri River alluvium, although some 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 silt approximately 20 to 50 feet thick, and an underlying fine to coarse sand with some gravel. This lower unit extends to the relatively flat-lying carbonate bedrock surface at a depth of approximately 70 to 75 feet below grade. Both unconsolidated units are water bearing, but the deeper unit 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 hydraulic gradient, combined with moderate hydraulic conductivity of the fine grained alluvial material, results in relatively slow ground water velocity beneath the site. Water table and potentiometric surface contour maps constructed based upon water levels measured in the new wells indicate groundwater flow directions different from the directions presumed prior to construction of the wells. Initially two conditions at FCS produced groundwater flow gradients opposite to those originally presumed. The first condition that affected groundwater flow was the pumping of the ground water supply well located at the Northwest corner of the old warehouse pad however, this well no longer exists.

FCSI 2.7.2.3 DSAR-2.7 Page 4 of 5 Rev. 4 Information Use Hydrology 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 generally from April through September when precipitation is greatest, river water recharges the nearby alluvial aquifer and induces groundwater flow gradients outward from the river channel. These gradients reverse seasonally, during periods of lower river 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 the plant appears to be within a dynamic groundwater environment influenced by pumping of the ground water supply well, river level, and seasonal amounts of precipitation. Consequently, the Site Groundwater Protection Program (ODCM, SO-G-118) accounts for potential variations in flow directions present within the industrial area. Well Water Analyses Samples were taken from the test 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 temperature 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.

Sample No. 1 As As Analysis CaCO3 Ion Fe, ppm 26.0 14.5 Mn, ppm 1.2 0.6 Na, ppm 118.0 54.3 K, ppm 4.5 3.5 Ca, ppm 420.0 168.0 Mg, ppm 220.0 52.8 Total Cations,ppm 789.7 293.7 SO4, ppm 151.5 145.4 C1, ppm 183.9 130.6 HCO3, ppm 454.0 553.9 NQ3 ppm 0.3 0.4 Total Anions, ppm 789.7 830.3 SiO2 ppm 22.6 Total Dissolved Solids, 1,146.0 ppm Total Hardness, ppm, 640.0 CaCQ3 Alkalinity, ppm CaCO3 454.0 pH 7.0 Conductivity, mµmh 1,400 DSAR-2.7 Page 5 of 5 Rev.4 Information Use Hydrology Table 2.7-4 -Test Well Water Analysis Sample No. 2 Sample No. 3 Sample No. 4 Sample No. 5 As As As As As As As As CaCO3 Ion CaCO3 Ion CaCO3 Ion CaCO3 Ion 28.4 15.9 27.6 15.4 27.6 15.4 28.1 15.7 4.9 2.7 5.1 2.8 4.0 2.2 5.1 2.8 106.9 49.2 104.5 48.1 104.2 47.9 96.0 44.2 4.4 3.4 4.4 3.4 4.4 3.4 4.1 3.2 408.0 163.2 398.8 159.5 399.6 159.8 401.0 160.4 212.0 50.9 214.4 51.5 237.8 57.1 203.0 48.7 764.6 285.3 754.8 280.7 777.6 285.8 737.3 275.0 174.7 167.7 159.6 153.2 181.3 174.0 160.7 154.3 14.1 10.0 8.5 6.0 11.3 8.0 8.5 6.0 575.4 702.0 586.4 715.4 584.8 713.5 568.0 693.0 0.4 0.5 0.3 0.4 0.2 0.3 0.1 0.1 764.6 880.2 754.8 875.0 777.6 895.8 737.3 853.4 23.4 23.0 20.6 27.3 1,188.9 1,178.7 1,202.2 1,155.7 620.0 61 3.2 637.4 604.0 575.4 586.4 584.8 568.0 7.0 7.4 7.4 7.3 1,250 1,240 1,240 1,250 NOTES

1. Samples taken at 8-hour intervals, August 26 to 29, 1966.

2. Sample No. 7 was invalid.

Sample No. 6 Sample No. 8 As As As As CaCO3 Ion CaCO3 Ion 28.1 15.7 28.1 15.7 5.6 3.1 4.7 2.6 96.0 44.2 91.5 42.1 5.1 4.0 4.4 3.4 394.0 157.6 406.0 162.4 274.0 65.7 248.0 59.5 802.8 290.3 782.7 285.7 164.2 157.6 147.8 141.9 5.6 4.0 8.5 6.0 632.9 772.1 626.2 764.0 0.1 0.1 0.2 0.3 802.8 933.8 782.7 912.2 23.0 23.0 1,247.1 1,220.9 668.0 654.0 632.9 626.2 7.4 7.5 1,250 1,200

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SITE AND ENVIRONS 2.8 Demography Information Use Demography DSAR-2.8 Page 1 of 4 Rev. 2 The plant site is located on the alluvial plain of the Missouri River in a predominantly agricultural region roughly ten miles north of the Omaha metropolitan area. There are no residences within one-half mile of the reactor location. 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 property. Industries include a large corn processing facility, agricultural fertilizer storage facilities and various other light industrial plants. The DeSoto National Wildlife Refuge occupies approximately 7,821 acres east of the plant site. This area is open to the public for day use year round. Visitors to the refuge generally use areas from two 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. The expected maximum daily usage of the facility has been placed at 2500 visitors for 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 plant site. Visitors to the recreation area generally use areas 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 the Fort Atkinson State Historic Park 5.5 miles southeast of the plant site. This day use facility is mostly seasonal 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 Refuge and four miles southeast of the plant site. The estimates for usage of this facility range from 500 on winter weekday to 1000 on a summer weekend. Two private facilities lie to the north of the plant along the Missouri River. The Cottonwood Cove Marina & RV Resort 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 campground lying directly to the south of Cottonwood Marina and ranging from 4 to 4.5 miles 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 201 O census. Fort Calhoun is about five miles southeast of the facility. The 2010 census reported a population of 908 in Fort Calhoun and 167 in Kennard Village, about seven miles from the plant site. The 2010 population of Washington County is 20,234.

FCSI Information Use Demography DSAR-2.8 Page 2 of 4 Rev. 2 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 includes the cities of Omaha and Council Bluffs, Iowa, and the adjoining areas of Douglas, Washington, and Sarpy Counties, Nebraska, and Pottawattamie County, Iowa. The area lies 10 to 25 miles southeast of the site, with the main concentration of population beyond the 15-mile radius. Population studies have been undertaken by the Metropolitan Area Planning Agency. Population information is as follows: 1960 U.S. Census 1970 U.S. Census 1980 U.S. Census 1990 U.S. Census 2000 U.S. Census 2010 U.S. Census Omaha City 301,598 346,929 313,911 335,795 390,007 408,958 Metropolitan Area 457,873 542,646 569,614 618,262 707,211 789,342

Sector Direction 0-1 1-2 A N 0 0 B NNE 0 13 C NE 0 0 D ENE 0 0 E E 0 0 F ESE 0 0 G SE 0 26 H SSE 17 17 J s 26 143 K SSW 2 12 L SW 20 49 M WSW 0 56 N w 10 137 p WNW 0 2 Q NW 0 0 R NNW 0 0 TOTALS 75 445

• Based on 2010 U.S. Census Data DSAR-2.8 Page 3 of 4 Rev. 2 Information Use Demography Table 2.8 Population Distribution as of 2010 Distance From Reactor In Miles/Square Miles of Sector Segment 2-3 3-4 4-5 5-10 10-20 20-30 30-40 0

4 0 53 735 663 3,884 0 8 4 341 489 737 960 0 5 21 116 1,163 2,199 1,771 0 0 11 908 4,875 1,007 4,192 0 0 0 121 907 2,461 3,225 8 0 18 52 1,420 2,626 3,367 11 6 296 799 3,775 41,969 3,365 19 239 290 1,366 163,961 161,060 19,892 57 81 15 753 135,318 146,657 6,722 41 42 303 1,653 48,544 42,387 5,083 61 38 80 249 2,182 4,958 6,148 16 353 87 546 1,939 30,475 1,443 104 139 78 246 682 1,654 1,951 310 3,361 2,183 290 484 1,798 5,563 245 1,510 203 194 745 1,948 1,678 86 3 34 60 1,972 455 938 958 5,789 3,623 7,747 369,191 443,054 70,182 Sectors are assigned for 22.5 degree segments starting from 11.25 degrees East of North. TOTALS 40-50 2,558 7,897 3,135 5,687 2,350 7,625 5,017 16,010 1,733 8,447 1,064 8,555 3,111 53,358 6,211 353,072 3,621 293,393 6,275 104,342 3,915 17,700 1,538 36,453 919 5,920 2,067 16,058 2,174 6,983 3,435 8,697 49,123 950,197

FCSI Information Use Demography DSAR-2.8 Page 4 of 4 Rev. 2 The U.S. Census data shows an increase in population in the Omaha metropolitan area and in most of the nearby cities but a decrease in the rural and farm population. While it is probable that the area 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 metropolitan area has been generally south and westward, coinciding with the interstate highway. It is expected that future growth of the metropolitan area will continue south and west and also northwestward. Thus it is probable that the area surrounding the plant site will continue to remain largely agricultural.

FCSI Information Use Land Use DSAR-2.9 Page 1 of 5 Rev. 1

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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 industrialized cities of Omaha and Fremont, Nebraska, and Council Bluffs, Iowa. 2.9.2 Agronomy Table 2.9-1 describes the use of agricultural land in Nebraska of counties within 10 miles of the plant site. Table 2.9-2 summarizes similar information for Iowa. The data are presented 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 tables is the United States Census of Agriculture, (2002) and the U.S. Census Bureau "State and County QuickFacts" (assorted years). 2.9.3 Industry The major industrial centers within 40 miles of the plant site are Omaha and Fremont, Nebraska, and Council Bluffs, Iowa. The major industries within a 10 mile radius of the plant site are listed in Table 2.9-3 with firm name, product, number of employees, and direction and distance from the 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 Community, January 2004) and the Blair Area Chamber of Commerce, Blair, Nebraska (2006).

FCSI Information Use Land Use DSAR-2.9 Page 2 of 5 Rev. 1 Table 2.9 Agricultural Land Use in Nebraska of Counties Within 10 miles of the Fort Calhoun Station County Number of Farms Land Area in county, acres Land Area in Farms, acres Land Area in Farms, % Land Use Total Cropland, acres Total Harvested Cropland, acres Principal Crops Corn for grain, acres Wheat for Grain, acres Oats for Grain, acres Soybeans for Beans, acres Forage, All Hay and Haylage, acres Livestock Cattle and Calves Inventory, number Hogs and Pigs Inventory, number Value of Agricultural Products Sold Market Value of Products Sold, $ Crops, $ Livestock, Poultry, and Their Products, $ Douglas 361 211,827 94,613 44.7 83,096 76,336 36,520 121 233 32,242 5,233 7,357 2,859 35,537,000 21,957,000 13,580,000 Washington 760 249,914 242,419 97.0 211,493 194,705 87,038 379 479 87,154 18,689 32,454 42,299 85,734,000 39,512,000 46,221,000

FCSI Information Use Land Use DSAR-2.9 Page 3 of 5 Rev. 1 Table 2.9 Agricultural Land Use In Iowa of Counties Within 10 Miles of the Fort Calhoun Station County Number of Farms Land Area in county, acres Land Area in Farms, acres Land Area in Farms, % Land Use Total Cropland, acres Total Harvested Cropland, acres Principal Crops Corn for grain, acres Wheat for Grain, acres Oats for Grain, acres Soybeans for Beans, acres Forage, All Hay and Haylage, acres Livestock Cattle and Calves Inventory, number Hogs and Pigs Inventory, number Value of Agricultural Products Sold Market Value of Products Sold, $ Crops, $ Livestock, Poultry, and Their Products, $ Harrison 828 445,901 428,235 96.0 367,561 337,240 168,935 329 328 156,052 10,269 33,874 42,545 111,191,000 84,811,000 26,380,000 Pottawattamie 1,255 610,726 540,288 88.5 487,579 442,923 218,112 91 1,220 205,719 16,632 63,358 55,626 163,267,000 106,911,000 56,356,000

Firm Name Ag-Bag Corporation Blair Feed Mill, Inc. Blair Manufacturing Company Blair Readi-Mix Carlson's Meats and Lockers Cb Manufacturing, Inc. Collins Mill Concrete Equipment Company, Inc. Desoto Engineering Enterprise Company G & G Manufacturing Company Jebco P-K Manufacturing Corporation Terra Chemicals/Pro-Sil Division Tri-Matic Equipment Company Valley Ready Mix Company Wilkinson Manufacturing Company DSAR-2.9 Page 4 of 5 Rev. 1 Information Use Land Use Table 2.9 Industry Within 10 Miles of Fort Calhoun Station Product(s) Direction Plastic Bags for Agricultural Use WNW Livestock Feed WNW Feed Wagon, Manure Spreader, Elevator, Stalk WNW Chopper and Hay Rakes Ready-Mixed Concrete and Pre-cast Concrete WNW Products Custom Meat Processing WNW Feed Wagons, Spreaders, Livestock Trailers and WSW Rear Mounted Tractor Blades Commercial and Residential Oak Interior Mouldings WSW and Doors Concrete Plants, Bucket Elevators and Screw and WNW Ball Conveyors Precision Swiss Automatic Screw Parts and Custom WNW Centerless Grindina Commercial Printing and Weekly Newspaper WNW Threaded Products, Bolts, Nuts, Powdered Metal ENE Chain and Sprockets Truck Cranes, Personnel Lift Derricks, Aerial WNW Platforms and Elevator Belt Conveyors Lawn, Garden, Turf, Tree and Field Spraying and SSE Fertilizer Aoolication Eauioment Liquid Silage Actuator, Liquid Clay and Zinc WNW Complex for Fertilizers Paint Spray Equipment and Booths SSE Ready Mixed Concrete ENE Aluminum Foil Products and Swiss Screw Machine SSE Parts Distance No. of Employees 3-1/4 1 to 9 3-1/2 1 to 9 3 100 to 199 3-1/2 10 to 24 3-1/2 1 to 9 7-1/4 1 to 9 7-1/4 1 to 9 3-1/4 25 to 49 2-3/4 1 to 9 3-1/2 10 to 24 10 1 to 20 3-1/4 10 to 24 9 25 to 49 2-3/4 1 to 9 5-1/2 10 to 24 10 1 to 20 5-1/2 100 to 199

FCSI Information Use Land Use DSAR-2.9 Page 5 of 5 Rev. 1 2.9.4 Wildlife 2.9.4.1 Fish The Missouri River supports over fifty different species of fish. The more numerous fishes are minnows, carp, gizzard shad, goldeye and catfishes. There are approximately 160 licensed commercial fishermen who operate in the Sioux City to Platte River area of the Missouri River and their primary catch is in carp and catfish. There is an increasing 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, pheasants 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 geese, and Canada geese in the spring and fall. Fur-bearing animals such as the muskrat, beaver, and mink also inhabit the region of the site.

FCSI Information Use Environmental Radiation Monitoring DSAR-2.10 Page 1 of 6 Rev. 4

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SITE AND ENVIRONS 2.10 Environmental Radiation Monitoring 2.10.1 General The environmental monitoring program is designed to provide data concerning the types and amount of radioactivity present in the environment of the Fort Calhoun Station. The preoperational program was designed to assess environmental conditions before the arrival of fuel. Subsequent analysis during the decommissioning program is being used to demonstrate that plant decommissioning efforts do not have a significant effect on the environment. This program is described and implemented in accordance with the ODCM. ARCHIVED TEXT 2.10.2 Preoperational Survey Program Surface Water Well Water Mud and Silt Aquatic Biota Milk Vegetation Air Particulate Wildlife The purpose of the preoperational survey program was to determine the base level of existing radioactivity to which future analytical results can be compared; the program extended for four consecutive years. The monitoring program was developed in cooperation with the regulatory agencies of Nebraska and Iowa and the Fish and Wildlife Service of the United States Government Department of the Interior. Specific radionuclide and/or gross radioactivity analyses were performed on the selected samples. Table 2.10-1 summarizes the types of samples and analyses included in the preoperational program. Table 2.10 Gross and Specific Radionuclide Analyses Gross Gross y-Spec Sr-90 H-3 K-40 1-131 Cs-137 a J3-y X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X 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.

FCSI ARCHIVED TEXT Information Use Environmental Radiation Monitoring DSAR-2.10 Page 2 of 6 Rev. 4 2.10.3 Preoperation Survey Results 2.10.3.1 Trial Monitoring Period The first nine months of the program, starting in September 1968, was a trial period designed to verify the availability of adequate sample types and to select and test analytical procedures. Results obtained during the trial period were preliminary. The trial period results are included in this report because they describe 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 collected at six stations: one at the Desoto National Wildlife Refuge Lake area and five from the Missouri River at sampling stations located above and below the plant site, including the municipal water supplies at Omaha, Nebraska, and Council Bluffs, Iowa. Well waters were sampled at eleven wells within a four-mile radius of the plant. Table 2.10-2 is a summary of the surface and well water data. Table 2.10 Average Radioactivity 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 ORB) not meaningful to update.

FCSI Information Use Environmental Radiation Monitoring DSAR-2.10 Page 3 of 6 Rev. 4 ARCHIVED TEXT Mud and Silt Mud and silt samples were taken from the Missouri River downstream of the plant. No alpha radiation was detectable; the 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 specific recommendations of the Nebraska Game, Forestation and Parks Commission. The fish species selected were chosen because their food habits include organisms within many of the lower trophic levels and because they are important from the standpoint of sport and commercial fishing. The food habits and radioactivity of the fish samples, which were taken from the Missouri River, are shown in Table 2.10-3. Table 2.10 Food Habits and Radioactivity of Missouri River Fish October 1968 - June 1969 Specie Food Habits ((3-y)-(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

1. 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.

FCSI ARCHIVED TEXT Information Use Environmental Radiation Monitoring DSAR-2.10 Page 4 of 6 Rev. 4 The paddlefish is difficult to collect but was included where possible because it feeds exclusively 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 origin 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 bottom which moves with the water flow; therefore, benthos and other bottom organisms are extremely scarce. Joint efforts with the Nebraska Game Commission to obtain sufficient samples for analysis of periphyton have failed; a cooperative study continues as a separate project. Milk Milk from large Grade A milk producers 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 are located downwind of the plant site. 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 1-131 Cs-137 (13-V)-(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.

FCSI ARCHIVED TEXT Information Use Environmental Radiation Monitoring Vegetation DSAR-2.10 Page 5 of 6 Rev. 4 Foods normally consumed by the general population constitute the vegetation samples. Six stations with a total of ten varieties of food were sampled during the 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 was collected at the plant site on 0.45 micron pore size filters; the filter was removed from the sampler and counted after the radioactivity had decayed for at least seventy-two hours. The air volume passed through the filter was approximately 1,000 cubic feet. None of the 32 samples analyzed showed any indication of alpha activity; the average beta-gamma concentration was 0.26 pc/m3 with a maximum of 0.78 pc/m3 and a minimum of 0.08 pc/m3. 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. Results of the combination film badge-thermoluminescent dosimeters, at eleven stations, were all less than 30 mrem per quarter. Wildlife A wild rabbit sample was included to represent wildlife normally consumed in the area. These rabbits are free to wander, but they normally remain in the immediate vicinity. The radioactive content was 20 picocuries of Strontium-90 per gram of calcium in the femur and no iodine-131 was detectable 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.

FCSI Information Use Environmental Radiation Monitoring DSAR-2.10 Page 6 of 6 Rev. 4 ARCHIVED TEXT 2.10.3.2 Preoperational Monitoring Period Following the trial period, the formal preoperational surveillance monitoring program was started in July, 1969, and continued for three years. This formal preoperational survey was an intensified continuation of the trial period already discussed. The program included soil samples and vegetation which are stored for possible future analyses. The preoperational program results were documented for future reference and comparison; they defined the pre-operational background levels. Future background conditions may vary due to influences such as fallout from nuclear testing; however, the 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 Section 5.0) is to provide public assurance that the Fort Calhoun contribution to naturally existing radioactivity is negligible. The program verifies the effectiveness of the waste disposal systems and radiological safety 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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SITE AND ENVIRONS 2.11 Section 2 References Information Use Section 2 References DSAR-2.11 Page 1 of 4 Rev. 5 1-18.1 Letter from R. G. Burnett, U.S. Army Corps of Engineers to E.G. Drdla, OPPD; dated November 11, 1971 1-18.2 Nebraska, A Survey of Universal Knowledge, Volume 16, Encyclopedia Britannica, Inc., Chicago, Illinois, 1959 1-18.3 Climatography of the United States No. 60-25, Climates of the States, Nebraska, U. S. Department of Commerce, Weather Bureau, 1959 1-18.4 Local Climatological Data, Annual Summary with Comparative Data for Omaha (North), Nebraska 1990, U.S. Department of Commerce, NOAA, NCDC, Asheville, NC 1-18.5 Local Climatological Data Annual Summary with Comparative Data for Omaha (Eppley Airfield) Nebraska, U.S. Department of Commerce, NCAA, NCDC, Asheville, NC 1-18.6 Krist, James G. Establishing Meteorological Correlations Between the North Omaha National Weather Service Station and the Fort Calhoun Nuclear Station, Master's Thesis, The University of Nebraska - Omaha, October 1991 1-18.7 Lundlum, David M., Weather Record Book, United States and Canada, Weatherwise, Inc., Princeton, New Jersey, 1971 1-18.8 Climatography of the United States, No. 81 (Nebraska), Monthly Normals of Temperature, Precipitation and Heating and Cooling Degrees Days 1941-70, U.S. Department of Commerce, NOAA, August, 1973 1-18.9 DELETED 1-18.10 Sagendorf, J. F., A Program for Evaluating Atmospheric Dispersion from a Nuclear Power Station, NOAA Tech. Memo. ERL-ARL-42, 1974 1-18.11 Yanskey, G. R. et al., Climatography of National Reactor Testing Station, Idaho Operations Office, USAEC, IDO-12048, 1966 1-18.12 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). 1-18.13 DELETED

FCSI Information Use Section 2 References DSAR-2.11 Page 2 of 4 Rev. 5 1-18.14 Local Climatological Data, Annual Summary, Omaha (Eppley Airfield), Nebraska, 1985, NOAA, NCDC, Asheville, NC 1-18.15 Local Climatological Data, Monthly, Omaha (Eppley Airfield), Nebraska, 1982, 1983 and 1984, NOAA, NCDC, Asheville, NC 1-18.16 1-18.17 1-18.18 DELETED DELETED DELETED 1-18.19 Review of Ground Water Protection Program at the Fort Calhoun Nuclear Power Station, TSD#08-015, Revision 01, May 30, 2008 1-18.20 DELETED 1-18.21 Letter from Charles L. Hipp, U.S. Army Corps of Engineers, to T.E. Short, OPPD, December 12, 1967. (WIP No. 19888) 1-18.22 DELETED 1-18.23 Safety Evaluation of the Omaha Public Power District Fort Calhoun Station, Unit No. 1, Issue Date: August 9, 1973, Suppl. 1 - April 23, 1973 1-18.24 DELETED 1-18.25 Environmental Statement Related to Operation of Fort Calhoun Station Unit 1, August 1972 1-18.26 Proposed Revision 1 to Regulatory Guide 1.23, Meteorological Programs in Support of Nuclear Power Plant, dated September 1980 1-18.27 DELETED 1-18.28 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

DSAR-2.11 FCSI Page 3 of 4 Rev. 5 Information Use Section 2 References 1-18.29 DELETED 1-18.30 DELETED 1-18.31 DELETED 1-18.32 DELETED 1-18.33 DELETED 1-18.34 DELETED 1-18.35 DELETED 1-18.36 DELETED 1-18.37 DELETED 1-18.38 DELETED 1-18.39 DELETED 1-18.40 DELETED 1-18.41 DELETED 1-18.42 DELETED 1-18.43 DELETED 1-18.44 DELETED 1-18.45 DELETED 1-18.46 DELETED 1-18.47 DELETED 1-18.48 DELETED 1-18.49 Memo, KLD Engineering, P.C., "50 Mile Population Calculation from 2010 and 2020" from Kevin Weinisch

FCSI Information Use Section 2 References DSAR-2.11 Page 4 of 4 Rev. 5 Calculation FC08790, Atmospheric Dispersion Factors (X/Qs) at the Decommissioning Exclusion Area Boundary (EAB) for Radiological Releases from Fort Calhoun Station. 1-18.50 Project 2444, Partial Site Release.

FCSI Information Use Missile Protection DSAR-5.8 Page 1 of 2 Rev. 2

5.

STRUCTURES 5.8 Missile Protection 5.8.1 External Missiles Region I 5.8.1.1 Tornado Generated Missiles The spectrum of hypothetical missiles 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 of 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 tornado 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 Spectrum and Maximum Horizontal Speeds Item Sched 40 Pipe (6.625" dia x 15' lg) Automobile (16.4'x6.6'x4.3') Solid Steel Sphere (1" dia.) Weight (lbs) 287 4000 0.147 (

Reference:

Table 2 of RG 1.76, Revision 1) Table 5.8 Design Basis Tornado Characteristics Maximum Translational Maximum Radius of Pressure drop Wind Speed Speed (mph) Rotational Maximum (psi) (mph) Speed (mph) Rotational Speed (ft) 230 46 184 150 1.2 (

Reference:

Table 1 of RG 1.76 Revision 1) Horizontal Velocity (fps) 135 135 26 Rate of Pressure Drop (psi/s) 0.5

FCSI DSAR-5.8 Page 2 of 2 Rev. 2 Information Use Missile Protection The Atomic Energy Commission (AEC) approved Bechtel Topical Report BC-TOP-9A, "Design of Structures for Missile Impacts," Revision 2, which was used to evaluate the spectrum of missiles described in Table 5.8-1 against the SSCs to which they are being applied. (Reference 5-16) RG 1.76 Revision 1 and Bechtel Topical Report BC-TOP-9A, Revision 2, comprise the methodology used to assess structures, systems and components for the DBT and associated missile impacts.

FCSI Information Use Organization and Responsibility

12.

CONDUCT OF OPERATIONS 12.1 Organization and Responsibility DSAR-12.1 Page 1 of 1 Rev. 3 Station organization is described in NO-FC-10, Quality Assurance Topical Report (QATR) and in site administrative procedures and organizational charts.

FCSI

12.

CONDUCT OF OPERATIONS 12.2 Training Information Use Training DSAR-12.2 Page 1 of 1 Rev. 3 Station training requirements are located in NO-FC-10, Quality Assurance Topical Report (QATR) and in site administrative procedures.

FCSI Information Use Written Procedures

12.

CONDUCT OF OPERATIONS 12.3 Written Procedures DSAR-12.3 Page 1 of 1 Rev. 3 Station written procedures requirements are located in NO-FC-10, Quality Assurance Topical Report.

FCSI

12.

CONDUCT OF OPERATIONS 12.4 Records Information Use Records DSAR-12.4 Page 1 of 1 Rev. 4 Station records requirements are located in NO-FC-10, Quality Assurance Topical Report (QATR) and in site administrative procedures.

FCSI Information Use Site Emergency Plan

12.

CONDUCT OF OPERATIONS 12.6 Site Emergency Plan DSAR-12.6 Page 1 of 1 Rev. 2 The ISFSI Only Emergency Plan (IOEP) requirements, as submitted to the NRC, are located in the IOEP.

FCSI

12.

CONDUCT OF OPERATIONS 12.7 Plant Security Information Use Plant Security DSAR-12.7 Page 1 of 1 Rev. 2 The ISFSI Security Plan requirements, as submitted to the NRC, are located in the Security Plan.

FCSI APPENDIX A

1.0 INTRODUCTION

Information Use Quality Assurance Program DSAR-Appendix A Page 1 of 1 Rev. 2 OPPD has ultimate responsibility for assuring that the Fort Calhoun Station is designed, maintained, tested, and operated in compliance with applicable 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 Regulations Part 50 Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants", and

b.

Applicable sections of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code.

FCSI Information Use Responses to 70 Criteria CRITERION 5 - RECORDS REQUIREMENT DSAR-Appendix G Page 1 of 6 Rev. 6 Records of the design, fabrication, and construction of essential components of the plant shall be maintained by the reactor operator or under its control throughout the life of the reactor. This criterion is met (2l. The Omaha Public Power District (OPPD) is the owner and operator of Fort Calhoun Station, Unit No. 1 (FCS). The Omaha Public Power District will maintain records of the design, fabrication, and construction of essential components of FCS. Due to Decommissioning OPPD has sought and received an exemption to records retention as follows: The Commission hereby grants OPP D'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 advance the schedule to remove records associated with Structure, 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 quality assurance, are not affected by the exemption request 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 record keeping requirements for the storage of spent fuel at its ISFSI under 10 CFR 50 or the general license requirements of 10 CFR 72. No exemption was requested from the decommissioning records retention requirements of 10 CFR 50.75, or any other requirements of 10 CFR 50 applicable to decommissioning and dismantlement. (2) Exemptions are from NRC-1 7-063, dated October 4, 2017.

FCSI Information Use Responses to 70 Criteria CRITERION 17 - MONITORING RADIOACTIVITY RELEASES DSAR-Appendix G Page 2 of 6 Rev. 6 Means shall be provided for monitoring the containment atmosphere, the facility effluent discharge paths, and the facility environs for radioactivity that could be released from normal operations, from anticipated transients and from accident conditions. This criterion is met. Plant gaseous effluents are vented to the atmosphere. Particulate monitoring of gaseous effluent is accomplished by filter air samplers. Plant liquid effluents are monitored during release. The above monitors are capable of detecting radioactivity released from the site to ensure the ODCM requirements are met.

FCSI Information Use Responses to 70 Criteria CRITERION 18 - MONITORING FUEL AND WASTE STORAGE DSAR-Appendix G Page 3 of 6 Rev. 6 Monitoring and alarm instrumentation 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 monitoring 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.

FCSI Information Use Responses to 70 Criteria CRITERION 68 - FUEL AND WASTE STORAGE RADIATION SHIELDING DSAR-Appendix G Page 4 of 6 Rev. 6 Shielding for radiation protection shall be provided in the design of spent fuel and waste storage facilities as required to meet the requirements of 10 CFR 20. This criterion is met. The liquid waste disposal equipment is built to industry code standards. Solid wastes are collected and may be stored in a shielded area if radioactivity levels are high. Spent resins are placed in a shipping container and stored in a shielded area. All spent fuel is stored in the ISFSI. All storage requirements are met as described in the 10 CFR 72.212 evaluation report. Station Greater Than Class "C" (GTCC) waste can also be stored in the ISFSI. The shielding for radiation protection meets the requirements of 10 CFR 20 for all waste storage areas.

FCSI Information Use Responses to 70 Criteria DSAR-Appendix G Page 5 of 6 Rev. 6 CRITERION 69 - PROTECTION AGAINST RADIOACTIVITY RELEASE FROM SPENT FUEL AND WASTE STORAGE Containment of fuel and waste storage shall be provided if accidents 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 stored 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 requirements are met as described in the 10 CFR 72.212 evaluation report. Station GTCC waste can also be stored in the ISFSI. Waste processing equipment is designed for packaging, storage and transport of low-level radioactive wastes. This provides control to maintain releases within ODCM and PCP requirements.

FCSI Information Use Responses to 70 Criteria DSAR-Appendix G Page 6 of 6 Rev. 6 CRITERION 70 - CONTROL OF RELEASE OF RADIOACTIVITY TO THE ENVIRONMENT The facility design shall include those means necessary to maintain control over the plant radioactive effluents, whether gaseous, liquid, or solid. Appropriate 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 environment. In all cases the design for radioactivity control shall be justified (a) on the basis of 10 CFR 20 requirements for normal operations and for any transient situation that might 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 recommended 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 demineralization) as appropriate, and analyzed prior to release. A radiation monitor, monitors all liquid discharges of radioactive waste. The effluent discharge, when diluted, will not exceed requirements of 10 CFR 20 as described in the ODCM. Space for storage of the solid wastes is provided so that packaging, handling and shipping can be carried out under favorable environmental conditions. All solid waste will be monitored, labeled, packaged and handled according to applicable regulations. Gaseous wastes are no longer stored. All waste gas is vented and monitored during release. (3) Amendment No. 299 removed the requirements of 10 CFR 100 for reactor accident dose analysis at the decommissioning site.}}