ML20170A383
Text
Page 1 of 16 DSAR-1.2 Introduction and Summary Summary Plant Description Rev 5 Safety Classification:
Usage Level:
Safety Information Change No.:
EC 70009 Reason for Change:
Changes due to Partial Site Release - Phase 2.
Changes on page 5.
Preparer:
R.L. Church/Ryan Layman Fort Calhoun Station
DSAR-1.2 Information Use Page 2 of 16 Summary Plant Description Rev. 5 Table of Contents 1.2 Summary Plant Description.......................................................................................... 5 1.2.1 Plant Site........................................................................................................ 5 1.2.2 Plant Arrangement......................................................................................... 6 1.2.3 Reactor and Reactor Coolant System............................................................ 8 1.2.4 Containment................................................................................................... 8 1.2.5 Engineered Safeguards Systems................................................................... 8 1.2.6 Instrumentation and Control........................................................................... 9 1.2.6.1 Deleted............................................................................................ 9 1.2.6.2 Instrumentation................................................................................ 9 1.2.6.3 Plant Computer................................................................................ 9 1.2.7 Electrical Systems........................................................................................ 10 1.2.8 Auxiliary Systems......................................................................................... 10 1.2.8.1 Chemical and Volume Control System.......................................... 10 1.2.8.2 Shutdown Cooling System............................................................ 10 1.2.8.3 Component Cooling and Raw Water Systems.............................. 11 1.2.8.4 Fuel Handling and Storage............................................................ 11 1.2.8.5 Sampling Systems......................................................................... 13 1.2.8.6 Circulating and Turbine Plant Cooling Water Systems.................. 13 1.2.8.7 Plant Ventilation Systems.............................................................. 13 1.2.8.8 Plant Fire Protection...................................................................... 14 1.2.8.9 Auxiliary Steam System................................................................. 14 1.2.8.10 Compressed Air System................................................................ 14 1.2.9 Deleted......................................................................................................... 14 1.2.10 Radioactive Waste Disposal System............................................................ 14 1.2.11 Plant Design Characteristics........................................................................ 15
DSAR-1.2 Information Use Page 3 of 16 Summary Plant Description Rev. 5 List of Tables Table 1.2 Deleted............................................................................................................. 16
DSAR-1.2 Information Use Page 4 of 16 Summary Plant Description Rev. 5 List of Figures 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 1.2-3 Primary Plant South Elevation............................................................... 12167 1.2-4 Primary Plant West Elevation................................................................. 12168 1.2-5 Primary Plant North Elevation................................................................ 12169 1.2-7 Turbine and Office Building Cross Sections........................................... 12195 1.2-8 Intake Structure Floor Plans................................................................... 12206 1.2-9 Intake Structure Building Sections and Panel Details............................ 12209 1.2-10 Intake Structure and Tunnels Foundation Plan and Details................... 16531 1.2-11 Intake Structure and Tunnels Plan at Elevation 985'-0 and 993'0" and Details............................................................................................. 16532 1.2-12 Intake Structure and Tunnels Plan at Elevation 1007'-6" and Details.... 16533 1.2-13 Intake Structure and Tunnels Sections and Details................................ 16535 1.2-14 Intake Structure and Tunnels Trash Rack and Stop Log Details............ 16538 1.2-15 Intake Structure and Tunnels Miscellaneous Details I............................ 16539 1.2-16 Intake Structure and Tunnels Miscellaneous Details II........................... 16540
DSAR-1.2 Information Use Page 5 of 16 Summary Plant Description Rev. 5 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 plant 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 at the north end of the plant protected area in the extended protected area designated for dry storage of spent fuel. The ISFSI is licensed under Subpart K of 10 CFR Part 72.
The area adjoining the site is farmland and sparsely populated. The minimum exclusion distance is 1525 feet. The nearest 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 1.2-2.
The exclusion zone, as defined in Section 100.3(a) of 10 CFR 100 consists of approximately 540 acres owned by Omaha Public Power District, and approximately 117 acres directly across the Missouri River, The restricted area as defined in Section 20.3(a)(14) of 10 CFR Part 20 is shown on Figure 1.2-1.
DSAR-1.2 Information Use Page 6 of 16 Summary Plant Description Rev. 5 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. As shown on Figure 1.2-1, the original steam generator storage facility (OSGSF) is located west of the rail spur near the access road. See DSAR Section 11.2.4 for radioactive material storage details.
A building to house equipment for diverse, flexible, coping strategies (FLEX) is located in between the OSGSF and U.S. Highway No. 75.
1.2.2 Plant Arrangement Plant status is continually changing during decommissioning. Current information on operating systems, radiological conditions and demolition progress is maintained by the Operations, Radiation Protection and Decommissioning organizations respectively.
The principal plant structures are the containment building, the auxiliary building, the turbine building, the service building, the technical support center, the maintenance shop, the radioactive waste processing building and the chemistry and radiation protection/locker facility including the office/cafeteria addition. A hazardous material storage building is located to the west of the main buildings, outside of the Protected Area.
Elevations of the primary plant are shown in Figures 1.2-3 to 1.2-5 inclusive.
The intake structure is a separate building located at the river bank to the east of the service building.
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.
An airlock sized for personnel access and passage of small components connects to the auxiliary building. An equipment access hatch is located at the 1013 foot level and connects to a handling area within the auxiliary building. A polar bridge crane is installed above the operating floor to handle the reactor vessel head and reactor internals for maintenance operations within the reactor containment. Additional items handled by the polar crane include the missile shield and cable trays.
DSAR-1.2 Information Use Page 7 of 16 Summary Plant Description Rev. 5 The reactor auxiliaries including waste treatment facilities, certain engineered safeguards components, the control room, radiation controlled area (RCA) protective clothing issue and dress area and laboratories, emergency diesel generators and fuel handling and storage facilities are located in the auxiliary building. A traveling bridge crane is located over the fuel handling and storage area in the auxiliary building.
The layout of the containment and auxiliary buildings is shown in P&ID 11405-A-5 thru 11405-A-8, P&ID 11405-A-13 and 11405-A-14.
The turbine building houses the turbine generator, condenser, condensate and feedwater pumps, feedwater heaters, other turbine heat cycle components. The service building houses the auxiliary boiler. A 150-ton traveling bridge crane is installed and serves the entire high bay portion of the building. The layout of the turbine building and the adjacent office building is shown in P&ID 11405-A-257 thru 11405-A-261, 11405-A-263, and Figure 1.2-7.
The condenser cooling circulating water and raw water pumps are located in the intake structure as shown in Figures 1.2-8, 1.2-9 and P&ID 11405-A-279.
Floor plans, building section details and structural features of the intake structure are shown in Figures 1.2-8 through 1.2-16 and P&ID 11405-A-279.
The radioactive waste processing building contains provisions for dry active waste (DAW) processing, liquid radwaste filtration and ion exchange (FIX) equipment and radwaste solidification equipment.
An Independent Spent Fuel Storage Installation (ISFSI) is located at the north end of the plant protected area in the extended protected area designated for dry storage of spent fuel. The ISFSI is licensed under Subpart K of 10 CFR Part 72. The ISFSI consists of a 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 and the ISFSI Electrical Equipment Building. The transfer cask carries dry shielded canisters containing spent fuel from the Auxiliary Building to the ISFSI by means of the haul route that runs west of the plant.
DSAR-1.2 Information Use Page 8 of 16 Summary Plant Description Rev. 5 1.2.3 Reactor and Reactor Coolant System The reactor and reactor coolant system remain installed but no longer have a design function and are not in use. The system consisted of a pressurized water reactor and its associated coolant system, arranged as two closed loops each containing two reactor coolant pumps and a steam generator connected in parallel to the reactor. A pressurizer is connected to one of the loops.
The reactor vessel and its closure head are fabricated from low alloy manganese-molybdenum steel internally clad with stainless steel.
The internal structures include the core support barrel, the core support plate, the core shroud, the thermal shield, the upper guide structure assembly, and the incore instrument thimble assembly.
1.2.4 Containment Most of the content of this section has been deleted to reflect the permanent cessation of operations of the Fort Calhoun Station. The reactor containment building is a concrete structure in the form of a vertical cylinder with domed roof and a flat base. The cylinder and dome are of post-tensioned concrete and the base is of reinforced concrete construction. The containment structure provides radiation shielding and control of radioactive materials.
A few systems continue to provide limited functions inside Containment to support the defueled condition as described in further detail throughout the DSAR (Fire Protection, Radiation Monitoring, Waste Disposal, Containment Ventilation, etc.).
1.2.5 Engineered Safeguards Systems The requirements related to engineered safeguards and safe shutdown of the reactor are no longer applicable because the station is permanently defueled. As such, the content of this section has been deleted in its entirety to reflect the permanent cessation of operations of the Fort Calhoun Station.
The components which made up the engineered safeguards systems including components of the safety injection system, containment spray system, containment air cooling and filtering system, auxiliary feedwater system, and containment isolation system remain physically installed in the plant, but are not in use and will not be returned to service.
DSAR-1.2 Information Use Page 9 of 16 Summary Plant Description Rev. 5 1.2.6 Instrumentation and Control 1.2.6.1 Deleted 1.2.6.2 Instrumentation The process instrumentation monitoring system includes those critical channels which are used for protective action. Additional temperature, pressure, flow and liquid level monitoring is provided, as required, to keep the operating personnel informed of plant conditions, and to provide information from which plant processes can be evaluated and/or regulated.
The plant gaseous and liquid effluents are monitored for radioactivity. Activity levels are displayed and off-normal values are annunciated. Area monitoring stations are provided to measure radioactivity at selected locations in the plant.
High radiation conditions within the containment or Auxiliary Building stack are monitored in the control room and in the plant.
1.2.6.3 Plant Computer The plant computer is a real time digital processing system, the basic functions of which are the assimilation of plant data and the surveillance of plant parameters. The computer also provides supplementary information to aid in plant operation and provide positive indication of off-normal conditions.
DSAR-1.2 Information Use Page 10 of 16 Summary Plant Description Rev. 5 1.2.7 Electrical Systems Plant status is continually changing during decommissioning. Current sources of energy for plant loads are 161 kV circuits from several OPPD Substations, and two 2500 kW, diesel-generator sets located in the plant.
Normal supply for the plant power is from two house service transformers fed from 161 kV that can supply maximum plant demand continuously. One transformer is associated with buses 1A1 and 1A3 and one transformer is associated with buses 1A2 and 1A4. A 345kV supply is available should the 161kV supply experience an outage.
A 4.16-kV system is provided and consists of four main buses with flexible supply transfer schemes. The 480-Volt loads are supplied through 4160 -
480-Volt transformers connected to double-ended 480-Volt load centers.
Each load center is arranged with three bus sections; the center (mid-tie) bus section can be connected to either adjacent bus section.
A 125-Volt, d-c control energy system is provided, comprised of lead-calcium control batteries, battery chargers, main buses, and distribution apparatus.
120-Volt a-c, main instrument buses are provided for instrumentation and control systems.
A 13.8 kV circuit derived from the 161 kV circuit serves as alternate power source of 480 V power to plant distribution.
1.2.8 Auxiliary Systems 1.2.8.1 Chemical and Volume Control System The chemical and volume control system no longer has a design function and is not in use. All piping, pumps, tanks, heat exchangers, and support components remain installed in the plant but are not in operation.
1.2.8.2 Shutdown Cooling System The shutdown cooling system provides an emergency backup for the spent fuel pool cooling system in the event of failure of that system. (Reference DSAR Section 9.6.2).
The shutdown cooling system utilizes the low pressure safety injection pumps to provide an alternate method for Spent Fuel Pool Cooling.
DSAR-1.2 Information Use Page 11 of 16 Summary Plant Description Rev. 5 The component cooling system supplies cooling water for the shutdown cooling heat exchangers.
1.2.8.3 Component Cooling and Raw Water Systems The component cooling water (CCW) system consists of a number of parallel closed loops which remove heat from the various auxiliary systems, some of which are potentially contaminated.
The system provides cooling to various heat exchangers. Heat removed by the component cooling water system is transferred to the raw water system by the component cooling heat exchangers.
The raw water system is a once-through system operating with screened river water. River water passes through traveling screens before reaching the Raw Water pumps. Pumped raw water passes through a debris strainer before delivery to the tube side of the component cooling heat exchangers. Redundancy has been provided in the component cooling and raw water systems to provide for both normal and emergency operation with portions of the systems out of service. Further, the system arrangement permits the raw water to be circulated through portions of the component cooling system piping to provide direct cooling of components in the unlikely event of all of the component cooling pumps and heat exchangers being unavailable.
1.2.8.4 Fuel Handling and Storage Irradiated fuel bundles will be stored in the spent fuel pool or the Independent Spent Fuel Installation (ISFSI) prior to off-site shipment. The spent fuel pool is normally filled with borated water.
DSAR-1.2 Information Use Page 12 of 16 Summary Plant Description Rev. 5 Normally the spent fuel pool cooling system will maintain the bulk water temperature of the pool below 120°F. The spent fuel pool is a reinforced concrete structure lined with stainless steel which provides storage capacity for 1083 fuel assemblies. The spent fuel racks are designed and will be maintained such that the calculated effective multiplication factor under normal conditions is no greater than 0.95 (including all known uncertainties) assuming the pool is flooded with unborated water. Under accident conditions involving misplacement of a low burnup assembly, the Technical Specification requirement of 500 ppm boron will ensure criticality requirements are met. The racks are divided into 2 regions. Storage in Region 1 and Region 2 of the spent fuel racks shall be restricted to fuel assemblies having initial enrichment less than or equal to 4.5 weight percent of U-235.
Region 1 and 2 cells are surrounded by Boral. Cooling and purification equipment is provided for the fuel pool.
The fuel handling systems provide for the safe handling of fuel assemblies and include the spent fuel handling machine and the associated controls and communication equipment.
OPPD has constructed an Independent Spent Fuel Storage Installation (ISFSI), located at the north end of the plant protected area in the extended 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 and the ISFSI electrical equipment building. The ISFSI is designed for 40 horizontal storage modules arranged in a 2 x 20 back-to-back configuration. Each horizontal storage module holds one dry shielded canister, protects the canister 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.
DSAR-1.2 Information Use Page 13 of 16 Summary Plant Description Rev. 5 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 NUHOMS storage system are included as Attachment A to Certificate of Compliance No. 1004.
Per Nuclear Regulatory Commission (NRC) Inspection Report 05000285/2015004 and 07200054/2015001 and as documented in Condition Report 2016-00250 which contains restrictions for this cask. DFS-DSC-04 is acceptable for storage under the Fort Calhoun Stations general Part 72 license but does not meet all applicable Part 71 requirements to be acceptable for transportation. This issue is to be resolved by Fort Calhoun Station prior to transportation of DFS-DSC-04.
1.2.8.5 Sampling Systems Various sampling systems are provided to monitor both chemical and radiological conditions of various process fluids used in the plant. Grab sampling stations are provided throughout the plant for laboratory analyses to monitor the quality of the fluid used in the plant.
1.2.8.6 Circulating and Turbine Plant Cooling Water Systems The circulating water system remains installed but is no longer operated to provide cooling water. The turbine plant cooling water (TPCW) system remains installed as a backup cooling method for the station air compressors. Cooling to the air compressors is provided by the Potable Water system.
1.2.8.7 Plant Ventilation Systems The plant ventilation systems maintain a suitable environment for equipment and personnel. The ventilation equipment incorporates steam coils to provide heating where necessary. The control room and office areas are air-conditioned. Those systems serving areas subject to possible radioactive airborne contamination contain filtration equipment to restrict the release of radioactivity to the environment.
DSAR-1.2 Information Use Page 14 of 16 Summary Plant Description Rev. 5 1.2.8.8 Plant Fire Protection The fire protection system provides water to fire hydrants, spray systems and hose racks in the various areas of the plant. Fire detectors and alarms are installed throughout the plant.
Where possible, noncombustible and fire resistant materials are used throughout the facility. Portable fire extinguishers are placed at key locations for use in extinguishing limited fires.
1.2.8.9 Auxiliary Steam System The auxiliary steam system utilizes a package boiler to supply low pressure steam for plant ventilation heating coils.
1.2.8.10 Compressed Air System The compressed air system provides a supply of dry, oil-free air for instruments, controls and other equipment requiring service air. Cooling to the air compressors is provided by the Potable Water system.
1.2.9 Deleted 1.2.10 Radioactive Waste Disposal System The radioactive waste disposal system is used to collect, store, prepare for disposal, and dispose of radioactive wastes, including liquids, solids, and gases.
The system performs the following functions:
- a.
Collects all wastes from the containment and auxiliary buildings that are subject to radioactive contamination;
- b.
Collects the above wastes in three separate groups: liquid, solid, and gaseous;
- c.
Provides holding facilities to permit laboratory analysis of individual waste batches;
- d.
Provides treatment facilities for those waste batches that must be further prepared for disposal;
- e.
Provides for the temporary storage of liquid waste, monitoring, and controlled release of liquid and gaseous wastes;
DSAR-1.2 Information Use Page 15 of 16 Summary Plant Description Rev. 5
- f.
Provides for the concentration, temporary storage, and packaging of contaminated wastes in suitable form for off-site disposal by waste handling firms approved by the Nuclear Regulatory Commission.
1.2.11 Plant Design Characteristics The general mechanical contract for Fort Calhoun was let soon after the February 1968 Draft Edition of the Code for Nuclear Piping B31.7, was published; this draft was included in the contract requirements for nuclear piping. This draft differed from the adopted code only in details.
The Draft B31.7 1968 code provides for third party inspection by an authorized ASME organization where required by legal enforcement authorities. Since the local jurisdiction had no requirements for third party inspection, it was determined to proceed with OPPD QA performing the function of the examiner. All the required documentary evidence and traceability are provided. ASME form NP-1 "Partial Data Report" was not used because of the requirement of a signature by the ASME inspector, and the requirement that this form be utilized by an ASME stamp holder.
One deviation from B31.7 1968 was permitted in the marking of spool pieces used in piping fabrications. The code requires that each spool piece be marked with its heat number and that this mark be retained on the spool piece until it is erected, no matter how many pieces the original length of pipe is cut into. It has been found more practical to place an identification mark on each piping fabrication which includes a fabricator drawing number. The fabricator drawing identifies each spool piece and fitting in a given fabrication and states the heat number. This practice minimizes chances of making errors in transferring heat numbers and provides a more permanent record.
The same type of procedure is specified in Section III of the ASME Code.
The fabricator drawings were retained by Omaha Public Power District.
Instruments were not covered by Draft B31.7 1968. Connections between the body of instruments and connecting tubing were threaded because the instrument manufacturers do not provide for any other type of connections.
Such connections were not used elsewhere in nuclear piping systems.
A few piping fittings, e.g., orifice flanges, were let out for contract prior to publication of the Draft B31.7 1968. Such fittings were designed, fabricated, and inspected in accordance with Draft B31.7 1968 as much as practical. In some cases, this required a post-delivery inspection. Traceability of such fittings back to heat number is not always available.
DSAR-1.2 Information Use Page 16 of 16 Summary Plant Description Rev. 5 Class I systems and equipment including piping are designed to the criteria for load combinations and stresses in Table F-1. When Fort Calhoun Station was originally licensed, safety-related piping was designed and constructed to meet the requirements of USAS B31.7, 1968 (DRAFT) Edition (i.e., the Code of Record for this piping). 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 III, 1980 Edition (no Addenda) as an alternative to USAS B31.7, 1968 (DRAFT) Edition.