ML25290A087

Susquehanna, Units 1 and 2 - Updated Final Safety Analysis Report, Rev. 72, Chapter 12, Section 12.2, Radiation Sources

ML25290A087
Person / Time
Site:	Susquehanna
Issue date:	10/13/2025
From:	Talen Energy, Susquehanna
To:	Office of Nuclear Reactor Regulation
Shared Package
ML25290A004	List: ML25290A005 ML25290A006 ML25290A008 ML25290A009 ML25290A010 ML25290A012 ML25290A013 ML25290A015 ML25290A017 ML25290A019 ML25290A020 ML25290A022 ML25290A023 ML25290A024 ML25290A025 ML25290A026 ML25290A028 ML25290A029 ML25290A030 ML25290A031 ML25290A032 ML25290A033 ML25290A034 ML25290A035 ML25290A036 ML25290A037 ML25290A038 ML25290A039 ML25290A040 ML25290A041 ML25290A042 ML25290A043 ML25290A044 ML25290A045 ML25290A047 ML25290A048 ML25290A049 ML25290A050 ML25290A051 ML25290A052 ML25290A053 ML25290A054 ML25290A055 ML25290A056 ML25290A057 ML25290A058 ML25290A059 ML25290A060 ML25290A062 ML25290A063 ... further results
References
PLA-8177
Download: ML25290A087 (1)

Text

SSES-FSAR Text Rev. 61 FSAR Rev. 71 12.2-1 12.2 RADIATION SOURCES In this section the sources of radiation that form the basis for shield design calculations and the sources of airborne radioactivity required for the design of personnel protective measures and for dose assessment are discussed and identified.

12.2.1 CONTAINED SOURCES The shielding design source terms are based on a noble gas fission product release rate of 0.1 i/sec (after 30 minutes decay) and the corresponding fission, activation, and corrosion product concentrations in the primary coolant. The sources in the primary coolant are discussed in Section 11.1 and listed in Tables 11.1-1 through 11.1-5. Throughout most of the primary coolant system, activation products, principally nitrogen-16, are the primary radiation sources for shielding design. For all systems transporting radioactive materials, conservative allowance is made for transit decay, while at the same time providing for daughter product formation.

Basic reactor data and core region description used for this section are listed in Tables 12.2-1 through 12.2-5.

The data contained in these Tables is the original design basis for the plant and have not been revised for power uprate. Although doses from the reactor core will increase due to power uprate, these increases have no effect on normal operating doses to plant personnel or on equipment qualification. The increased doses from the core resulting from power uprate meet radiation shielding and zoning requirements inside containment.

In this subsection the design sources are presented by building location and system. General locations of the equipment discussed in this section are shown on the shielding and zoning drawings, Dwgs. A-511, Sh. 1, A-512, Sh. 1, A-513, Sh. 1, A-514, Sh. 1, A-515, Sh. 1, A-516, Sh. 1, A-517, Sh. 1, A-518, Sh. 1, A-519, Sh. 1, A-520, Sh. 1, A-521, Sh. 1, A-522, Sh. 1, A-523, Sh. 1, A-524, Sh. 1, A-525, Sh. 1, A-526, Sh. 1, A-527, Sh. 1, A-528, Sh. 1, A-529, Sh. 1, and A-530, Sh. 1. The layout of equipment in Unit 2 is not significantly different from the layout in Unit 1, therefore the shielding and zoning requirements shown on these drawings are applicable to both units. Detailed data on source descriptions for each shielded plant area are presented in Tables 12.2-38 through 12.2-40.

Shielding source terms presented in this section and associated tables are based on conservative assumptions regarding system and equipment operations and characteristics to provide reasonably conservative radioactivity concentrations for shielding design. Therefore, the shielding source terms are not intended to approximate the actual system design radioactivity concentrations.

12.2.1.1 Drywell 12.2.1.1.1 Reactor Core The primary radiations within the drywell during full power operation are neutron and gamma radiation resulting from the fission process in the core. Tables 12.2-4 and 12.2-5 list the multigroup neutron and gamma ray fluxes at the outside surfaces of the reactor pressure vessel

SSES-FSAR Text Rev. 61 FSAR Rev. 71 12.2-2 and the primary shield at the core midplane. The gamma fluxes include those resulting from capture or inelastic scattering of neutrons within the reactor pressure vessel and core shroud and the gamma radiation resulting from prompt fission and fission product decay.

The data contained in Tables 12.2-4 and 12.2-5 is the original design basis for the plant and have not been revised for power uprate. Although doses from the reactor core will increase due to power uprate, these increases have no effect on normal operating doses to plant personnel or on equipment qualification. The increased doses from the core resulting from power uprate meet radiation shielding and zoning requirements inside containment.

The largest radiation sources after reactor shutdown are the decaying fission products in the fuel. Tables 12.2-9A1 and 12.2-9A2 list the core gamma sources as a function of shutdown time. Secondary sources are the structural material activation of the RPV, its internals, and the piping and equipment located in the primary containment and also the activated corrosion products accumulated or deposited in the internals of the RPV, the primary coolant piping, and other process system piping in the primary containment.

12.2.1.1.2 Reactor Coolant System Sources of radiation in the reactor coolant system are fission products estimated to be released from fuel and activation and corrosion products that are circulated in the reactor coolant. These sources are listed in Tables 11.1-1 through 11.1-5 and their bases are discussed in Section 11.1. The nitrogen-16 concentration in the reactor coolant is assumed to be 50 Ci/gm of coolant at the reactor recirculation outlet nozzle.

12.2.1.1.3 Primary Steam System Radiation sources in the primary steam system piping include activation gases, principally nitrogen-16, and the corrosion and fission products carried over to the steam system.

The nitrogen-16 concentration in the main steam is assumed to be 250 Ci/gm of steam leaving the reactor vessel at the main steam outlet nozzle. Fission product activity corresponds to an offgas release rate of 100,000 Ci/sec at 30 minutes delay from the reactor steam nozzle.

Partition fractions for activity into the steam system are 100 percent for gases, 8 percent by weight for halogens, and 0.1 percent by weight for particulates. These partition factors are applied to the reactor water concentrations as given in Table 11.1-2 through 11.1-5.

12.2.1.2 Reactor Building 12.2.1.2.1 Reactor Water Cleanup System Radiation sources in the RWCU system consist of those radioisotopes carried in the reactor water. Nitrogen-16 is the predominant radiation source in the regenerative and nonregenerative heat exchangers and RWCU pumps and piping. The inventory of N-16 is based upon component transit times, as shown in Table 12.2-6. The main sources for the RWCU filter demineralizers, holding pumps, and the RWCU backwash receiving tank are the accumulated corrosion and fission products, based on the inlet reactor water concentrations given in Section 11.1. Table 12.2-7 provides the inventory of the accumulated isotopes in the filter demineralizer, and Table 12.2-8 provides the inventory of isotopes in the RWCU backwash receiving tank.

SSES-FSAR Text Rev. 61 FSAR Rev. 71 12.2-3 12.2.1.2.2 Spent Fuel Handling and Transfer The spent fuel assemblies are the predominant source of radiation in the containment after plant shutdown for refueling. A reactor operating time necessary to establish near fission product buildup equilibrium for the reactor at rated power is used in determining the source strength.

Shielding requirements for spent fuel transfer are based on the fission product activity present 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after shutdown. Source terms for spent fuel are discussed in Subsection 12.2.1.3.1 and are listed in Tables 12.2-9A1 and 12.2-9A2.

12.2.1.2.3 Residual Heat Removal System The pumps, heat exchangers, and associated piping of the Residual Heat Removal (RHR)

System are potential carriers of radioactive materials. For plant shutdown, the RHR pumps and heat exchanger sources result from the radioactive isotopes carried in the reactor coolant, discussed in Subsection 12.2.1.1.2, after 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of decay following shutdown. The radioactive isotopic concentrations are listed in Table 12.2-10.

12.2.1.2.4 Reactor Core Isolation Cooling System Components of the Reactor Core Isolation Cooling (RCIC) System that are potential radiation sources are the RCIC turbine and steam inlet and exhaust piping. Radioactivity in the turbine and piping is that present in the driving steam that has been extracted from the main steam system. The steam activity as discussed in Subsection 12.2.1.1.3, decayed for the appropriate transit time to the RCIC turbine, is used for the shielding calculations for this system, and is listed in Table 12.2-11.

12.2.1.2.5 High Pressure Coolant Injection System The radiation sources for the High Pressure Coolant Injection System are the HPCI turbine and the steam inlet and exhaust piping. The steam activity, as discussed in Subsections 12.2.1.1.3, decayed for the appropriate transit times is used for the shielding of this system as shown in Table 12.2-11.

12.2.1.2.6 Core Spray Systems Because the core spray, when testing, uses condensate from the condensate storage tank with very low radioactivity concentrations, no shielding is required.

12.2.1.3 Refueling Facilities 12.2.1.3.1 Spent Fuel Storage and Transfer The predominant radiation sources in the spent fuel storage and transfer areas are the spent fuel assemblies. Spent fuel assembly sources are discussed in Subsection 12.2.1.2.2. For shielding design, the spent fuel pool is assumed to contain the design maximum of 2840 fuel assemblies (Section 9.1) with 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> decay. The activity of fission product radionuclides which serve as the basis for the spent fuel source term are shown in Tables 12.2-9A1 and 12.2-9A2.

SSES-FSAR Text Rev. 61 FSAR Rev. 71 12.2-4 Spent fuel assemblies are also a radiation source at the Independent Spent Fuel Storage Installation (ISFSI). For shielding design and dose rate determinations the Dry Shielded Canisters (DSCs) located on the original ISFSI (A, B, C, D, and E Rows) are modeled representative of actual DSC loading conditions, with exception to seven DSCs within Horizontal Storage Modules (HSMs) E15 through E21. For these seven DSCs and all of the DSCs located on the expanded ISFSI (F and G Rows), each DSC is assumed to contain 61 fuel assemblies with a minimum 3 year decay cooling in the spent fuel pool. Dose rates as a function of distance are calculated including the addition of 26 HI-STORM FW casks which will be placed on the existing ISFSI Basemats 4 and 5. For the HI-STORM FW cask shielding analysis, all 26 casks are assumed to be loaded with a bounding, regionalized loading pattern with a minimum 3 year decay cooling in the spent fuel pool. Refer to Section 11.7.3 for ISFSI Source Terms.

12.2.1.3.2 Fuel Pool Cooling and Cleanup System Sources in the Fuel Pool Cooling and Cleanup (FPCC) System are primarily a result of transfer of radioactive isotopes from the reactor coolant into the spent fuel pool during refueling operations. The total gross activity in the Fuel Pool water is assumed to be reactor coolant activities for fission, corrosion, and activation products (Tables 11.1-1 through 11.1-5),

normalized to 1.0E-2 Ci/cc for shutdown conditions and 1.00E-04 µCi/cc for normal operations.

This activity then undergoes subsequent decay and accumulation on the FPCC filter demineralizers (see Table 12.2-13). The FPCC filter demineralizer resins are back washed periodically into a backwash receiving tank. Shielding source terms for the backwash receiving tank are shown in Table 12.2-14.

12.2.1.4 Turbine Building 12.2.1.4.1 Primary Steam and Power Conversion Systems Radiation sources for piping and equipment which contain primary steam are based on the radioactivity carried over into the steam from the reactor coolant and include fission product gases and halogens, corrosion and fission products, and gaseous activation products as discussed in Subsection 12.2.1.1.3. Steam density variations and the steam transit times through equipment and pipes are factored into the source term evaluation to account for volumetric dilution effects, radiological decay, and daughter product generation.

12.2.1.4.2 Condensate System The sources in the condensate system are based on decayed main steam activities (Subsection 12.2.1.1.3). Eighty percent of the N-16 and 100 percent of the noble gases are assumed to be removed from the condensate system by the main condenser evacuation system. The gaseous activities are minor in the hotwell and negligible in the remainder of the condensate system.

The hotwell has a minimum of three minutes holdup of condensate and therefore N-16 activity at the condenser outlet is negligible. Fission products, activated corrosion products, and the daughter products from the decay of fission product gases in transit through the turbine are the inlet sources to the condensate system.

These sources, as shown in Table 12.2-15, are present in the condensate pumps and piping and accumulate on the condensate filters and demineralizer resins. When spent, the condensate filters and demineralizer resins are discharged to the solid waste management system for packaging and offsite disposal. Table 12.2-16 provides the isotopic inventory

SSES-FSAR Text Rev. 61 FSAR Rev. 71 12.2-5 utilized as the shielding source terms for the condensate demineralizers. Tables 12.2.46, 12.2.47, and 12.2.48 provide the shielding source terms for the condensate filter vessel, condensate backwash solution, and the condensate filter backwash receiving tank, respectively.

12.2.1.4.3 Offgas System Recombiner Radioactive sources in the gas treatment system originate with the noble gases and non-condensible gases removed from the main condenser, and the activity entering with the extraction driving steam to the main condenser evacuation system. The activity removed from the main condenser is based on the primary steam activity as described in Subsection 12.2.1.1.3, decayed for the total transit time to the steam jet air ejector. Eighty percent of the N-16 and 100 percent of the noble gases are assumed to be removed by the air ejector.

Activity in the extraction driving steam to the air ejector is the primary steam activity as described in Subsection 12.2.1.1.3, decayed by the transit time to the air ejector. The total quantity of activity in the offgas pipe and recombiner and source term assumptions are shown in Tables 12.2-17 and 12.2-18.

12.2.1.5 Radwaste Building 12.2.1.5.1 Liquid Waste Management System The liquid waste management system (LWMS) sources are radioisotopes, including fission and activation products, present in the reactor coolant. The components of the LWMS contain varying degrees of radioactivity depending on the detailed system and equipment design.

The concentrations of radionuclides present in the process fluids at various locations in the system such as pipes, tanks, filters, and demineralizers are discussed in Section 11.2 and are listed in Tables 11.2-5 through 11.2-7. Shielding and associated radiation zoning for components of the LWMS are based on the design basis radioactivity concentrations given in Sections 11.1 and 11.2.

12.2.1.5.2 Solid Waste Management System Wet and dry radioactive wastes are collected, treated, and stored in the solid radwaste facilities as discussed in Section 11.4. The radioactive wastes are processed by filtration, decanting, and ion-exchange treatment. The resultant volume reduced products (e.g., filter cakes, depleted resins) are dewatered for storage and offsite shipment. Processed liquids may be analyzed for reuse as condensate make-up, processed as radioactive waste, or diluted and discharged.

Radioactive waste may be solidified in containers specified in the Solid Radioactive Waste Process Control Program, then washed to minimize external surface contaminants, and shipped or stored in concrete shielded compartments. The aforementioned operations may be accomplished utilizing remote container loading, transfer, capping facilities, and an overhead crane. Shielding and radiation zone designations of the solid radioactive waste areas are based on the maximum activity sources at zero decay presented in Tables 11.2-6 and 11.4-6, without any consideration of external container shielding credit.

SSES-FSAR Text Rev. 61 FSAR Rev. 71 12.2-6 12.2.1.5.3 Ambient Charcoal Offgas Treatment System The charcoal offgas system as described in Section 11.3 is located in the radwaste building and primarily adsorbs the noble gases and daughter products remaining in the noncondensible gases removed from the main condenser after treatment in the recombiner offgas system.

The shielding of the components is based on the transit times for formation and accumulation of noble gas daughter products and the remaining xenon and krypton gases on the carbon beds.

The gases, after charcoal treatment, pass through a post HEPA filter where remaining particulates are trapped prior to exhausting. The concentration of the activity on the piping, equipment, and particulate and charcoal filters for shield design is shown in Tables 12.2-19 through 12.2-24.

12.2.1.6 Sources Resulting from Design Basis Accidents Radiation sources and shielding requirements resulting from design basis accidents are presented and evaluated in Section 18.1.20 Plant Shielding (II.B.2).

12.2.1.7 Site Boundary N-16 Shine Dose The N-16 present in the reactor steam in the primary steam lines, turbines, and moisture separator can contribute to the site boundary dose as a result of high energy gamma emission.

The turbine shielding was designed to minimize shine dose. The N-16 shine dose rate at the site boundary was calculated based on the final turbine shielding design. The turbine operating floor component N-16 inventories are listed in Table 12.2-11.

12.2.1.8 Stored Radioactivity Normally the only sources of activity not stored inside the plant structures are the refueling water storage tank (RWST) and the condensate storage tank (CST). A berm is provided around these tanks to retain leakage and provide for Zone 1 (<0.5 mrem/hr) access. Provisions have been made to recycle the water from both the condensate and refueling water storage tanks to the condensate demineralizer.

Under normal conditions the condensate storage tank contains concentrations of radionuclides that yield a surface exposure rate of less than 1. 5 mr/hr. The condensate storage tank isotopic inventory is shown in Table 12.2-29.

The refueling water storage tank is also expected to have a maximum contact exposure rate of less than1.5 mr/hr.

All spent fuel is stored in the spent fuel pool until it is placed in the spent fuel shipping cask for offsite transport or transferred to the Independent Spent Fuel Storage Installation (ISFSI) described in Section 11.7. Storage space is provided in the radwaste enclosure for interim storage of packaged solid waste materials. Radioactive wastes stored inside the plant structures are shielded in place such that there is normally Zone I access outside the structure.

A separate Steam Dryer Storage Facility (SDSF) is provided within the plant protected area for the storage shielding and radioactive decay of replaced Reactor steam dryers. The steam dryers are cut in half and packaged into steel containers for storage in the SDSF. They are not considered as radioactive waste but are treated as irradiated plant equipment. The SDSF is a

SSES-FSAR Text Rev. 61 FSAR Rev. 71 12.2-7 reinforced concrete vault with removable roof slab access only, meeting 10 CFR 20 dose limits.

Low Level Radwaste is stored in the Low Level Radwaste Holding Facility (LLRWHF) and is described in Section 11.6.

12.2.1.9 Special Sources Special materials used in the radiochemistry laboratory and sealed sources used for calibration purposes are of the low activity level and are handled in accordance with station health physics procedures. Unsealed sources and radiochemistry samples are handled in hoods that exhaust to the ventilation system.

The radiation source for the Transverse Incore Probe System (TIP) is provided in Tables 12.2-41, 12.2-42, 12.2-43, and 12.2-44. The radiation source is based upon location within the core and residence time. As indicated in the tables, the TIP system consists of three components for shielding calculations, the fissionable material, non-fissionable material, and the cable. Sources are provided for each component as a function of irradiation and decay times.

The reactor startup source is shipped to the site in a special cask designed for shielding. The source is transferred under water while in the cask and loaded into beryllium containers. This is then loaded into the reactor while remaining under water. The source is stored in the Spent Fuel Pool. Thus, no unique shielding requirements after reactor operation are required.

12.2.2 AIRBORNE RADIOACTIVE MATERIAL SOURCES 12.2.2.1 Sources of Airborne Radioactivity The sources of airborne radioactivity are found in the various confined areas of the plant facility and are primarily from the process leakage of the systems carrying radioactive gases, steam, and liquids. Depending on the type of the system and its physical condition, such as system pressures and temperatures, the leakage will be as a gas, steam, liquid, or a mixture of these.

12.2.2.2 Production of Airborne Materials Radioactive materials become airborne through a number of mechanisms. The primary production mechanisms are spraying, splashing, flashing, evaporation, and diffusion.

12.2.2.3 Locations of Sources of Airborne Radioactivity The primary sources of airborne radioactivity are found in the reactor, turbine, and radwaste buildings. Within these structures, the radioactivity may be released in equipment cubicles, system compartments, valve and piping galleries, sampling stations, radwaste handling areas, cleaning and decontamination areas and repair shops.

12.2.2.4 Control of Airborne Radioactivity Ventilation is an effective means of controlling airborne radioactive materials. Ventilation flow paths are designed such that air from low potential airborne areas flows toward the higher potential airborne areas. This flow pattern will ensure that activity released in the above mentioned source locations, which usually have low personnel access requirements, will have

SSES-FSAR Text Rev. 61 FSAR Rev. 71 12.2-8 little chance to escape to areas with a high personnel occupancy such as corridors, working aisles and operating floors.

12.2.2.5 Methodology for Estimating the Concentration of Airborne Radioactive Material Within the Plant In order to estimate the airborne radioactive material concentrations at locations within the plant, the following methodology was used:

(1)

Estimate the total airborne releases (in Curies per year) for each of the buildings of the plant; (2)

Estimate a distribution for these releases among the various equipment areas of each building based on operating data and engineering judgment; (3)

Determine the annual exhaust flow from each equipment area, (4)

Calculate the resultant airborne radionuclide concentration (Ci/cc) in each equipment area based on the release distribution (Ci/yr) and exhaust flow rate (cc/yr).

The following subsections discuss each step in the above procedure in more detail.

12.2.2.6 Estimation of Total Airborne Releases Within the Plant The estimated quantities of untreated airborne radioactive material produced in the buildings of the plant are given in Table 12.2-30. These releases were based upon NUREG-0016 Revision 1, "Calculation of Radioactive Materials in Gaseous and Liquid Effluents from Boiling Water Reactors." The quantities in Table 12.2-30 were generated as follows:

All turbine building releases were originally reduced by a factor of five to take credit for the leakage collection system installed for valves in lines 2 1/2" and larger.

Valves in the turbine building were originally provided with valve stem packing leakoff connections. Research and testing has shown that improved packing provides an effective seal to prevent leakage into the Turbine Building. As a result, these leakoff connections are in the process of being removed and packing configurations changed, as appropriate, to conform with the new requirements. As part of this effort, leakoff isolation valves and piping will be removed (or abandoned in place) and the leakoff collection header piping will be removed or abandoned in place.

(NOTE: Releases assigned to the turbine building are assumed to include any control structure releases.)

The reactor building releases were taken to be the sum of releases listed in NUREG-0016 Revision 1 for the auxiliary building and containment building.

The radwaste building releases are "per reactor" and consequently were doubled for Susquehanna SES.

SSES-FSAR Text Rev. 61 FSAR Rev. 71 12.2-9 12.2.2.7 Distribution of Airborne Releases Within the Plant The approach taken to determine the anticipated distribution of gaseous effluents assumed that all untreated airborne radioactive material originates only within the equipment areas of the plant. It was further assumed that a major percentage of the release is generated within a few specific areas of each building. These areas are identified as per NUREG-0016 Revision 1, Section 2.2.4, "Gaseous Releases From Building Ventilation Systems", as follows:

For the Reactor Building, 90% of the normal power operation releases are due to the reactor water cleanup (RWCU) pumps and filter/demineralizers (F/Ds), and the emergency core cooling systems (ECCS) and 10% of the releases are due to the fuel handling and drywell areas.

During shutdown, 10% of the releases are from the RWCU and ECCS Systems and 90% of the releases are from the fuel handling and drywell areas.

For the Turbine Building, 85% of the normal power operation releases are from the main condenser area and 15% of the releases are from miscellaneous areas such as the steam jet air ejector (SJAE) room, the turbine operating floor, the feedwater pump room, and the mechanical vacuum pump room. During shutdown, 50% of the releases are from the main condenser area and 50% of the releases are from miscellaneous areas.

For the Radwaste Building, during normal power operation and shutdown, 10% of the releases are from the solid waste handling areas and 90% of the releases are from the liquid waste handling areas.

Releases were assumed to be generated continuously throughout the year.

The selection and relative contributions of the major areas was determined from NUREG-0016 Revision 1, based on EPRI NP-495 and NRC studies. These studies provide data on the important sources of Iodine-131 at operating BWR's and determined the relative release rate from each source. The relative release rates for all airborne radionuclides were then assumed to be directly proportional to the Iodine-131 release rates.

Table 12.2-31 lists the major airborne contributors in each building and the percentage of the total building release assigned to each. Tables 12.2-32 through 12.2-34 provide the specific equipment areas of the plant associated with the major contributors and the applicable exhaust air flow rates. Note that only those equipment areas which have a significant potential for airborne radioactive material releases were included in the "other equipment areas" category.

12.2.2.8 Estimated Airborne Radioactive Material Concentrations Within the Plant The airborne radionuclide concentrations for each equipment area were calculated using the following methodology. For a specific area, the appropriate building release (Table 12.2-30) was multiplied by the applicable release percentage for the area (Table 12.2-31) and divided by the area annual exhaust flow (Table 12.2-32, 12.2-33, or 12.2-34). The resultant concentrations are presented in Tables 12.2-35 through 12.2-37 and are compared to 10 CFR 20 Appendix B requirements.

SSES-FSAR Text Rev. 61 FSAR Rev. 71 12.2-10 12.2.2.9 Changes to Source Data Since PSAR Source data has been updated to reflect changes in contained sources due to the implementation of power uprate, 24-month fuel cycle, design and operational changes, hydrogen water chemistry, condensate filtration, and NUREG-0016, Revision 1.

SSES-FSAR TABLE 12.2-1 BASIC REACTOR DATA (1) (2l Page 1 of 1

1.

Reactor Rated Thermal Power 3323 megawatts

2.

Overall Average Core Power Density

50. 7 watts/cc

3.

Core Power Peaking Factors:

a.

At Core Center Pmax (Axial) 1.5 Pevez 1.4 Pmax (Axial)

Paver

b.

At Core Boundary Pmax (Axial) 0.5 Pave Pmax (Radial) 0.7 Pave

4.

Core Volume Fractions:

Density Volume Material gm/cc Fraction U02 10.4 0.254 Zr 6.4 0.140 H20 1.0 0.274 Void 0

0.332

5.

Average Water Density Between Core and Vessel and 0.74 gm/cc Below the Core

6.

Average Water-steam Density above Core:

a.

In the Plenum Region 0.23 gm/cc

b.

Above the Plenum {Homogenized) 0.6 gm/cc

7.

Average Steam Density 0.036 gm/cc (1 l This table represents the physical data required to form the reactor vessel model, which includes volume fractions, reactor power, and power distribution.

121 Original plant design basis not revised for power uprate.

Rev. 49, 04/96

SSES-FSAR TABLE 12.2-2 Core Region Description Used in Calculations to Determine Radial Flux Distribution at Reactor Core Midplane '21 Page 1 of 1 Region Cumulative Region Description Thickness Thickness Ma~nrial (cm)

(cm)

[

1.

Active Fuel Zone 237.7 237.7 c4re

2.

Water 20.2 257.9 Water

3.

Core Shroud 5.08 262.98 Carbor. Steel

4.

Water 55.88 318.86 Water

5.

Pressure Vessel and Liner 17.12 335.98 Carbon Steel

6.

Air Gap 44.5 380.48 Ar

7.

Steel Liner (Primary Shield) 1.27 381.75 Carbot1 Steel

8.

Concrete (Primary Shield <11 48.2 429.95 Mag netite-i I men ite

9.

Steel Liner (Primary Shield) 3.81 433.76 Carbor! Steel

10. Air Gap 457.2 890.96 Ar

11. Primary Containment 182.88 1074.5 Ordinary; :oncrete I

(1)

Magnetite, Ilmenite Aggregate Mixture (21 Original Plant Design Basis Not Revised for Power Uprate Rev. 49, 04/96

SSES-FSAR TABLE 12.2-3 MATERIAL COMPOSITION TO DETERMINE RADIAL FLUX DISTRIBUTIONS AT REACTOR CORE MIDPLANE 131 Page 1 of 1 MA TE RIAL I 102 4 atoms/eel ELEMENT Core Water SS-304 Carbon Steel Concrate111 Air Ordinary Concrete H

1.836-2121 4.888-2 3.66-3 7.84-3 0

2.257-2 2.444-2 4.51-2 1.12-5 4.41-3 Mo 5.93-4 U235 1.24-4 U238 5.46-3 Mg 9.685-4 1.43-4 Al 1.32-3 2.39-3 Si 1.69-3 4.19-4 5.49-3 1.57-2 Ca 4.00-3 2.91-3 Ti 2.17-3 Mn 1.73-3 8.59-4 4.86-4 Fe 5.76-2 8.4-2 1.16-2 3.09-4 C

3.18-4 1.00-3 Cr 1.73-2 Ni 8.06-3 N

4.17-6 Na 1.05-3 K

6.91 -4 s

5.30-5

11)

Mixture Magnetite-Ilmenite (21 1.836-2 = 1.836 X 10"2 (31 Original Plant Design Basis Not Revised for Power Uprate Rev. 49, 04/96

SSES-FSAR TABLE 12.2-4 CALCULATED GAMMA RAY AND NEUTRON FLUXES AT OUTSIDE SURFACE OF RPV l4>

Outside Vessel At Core Midplane l1 l l2>

Page 1 of 1 Gamma Energy Gamma Flux Neutron Energy Neutron Flux (Upper mev)

(y/cm2-sec)

(Upper evJ (q/cm2*sec) 10.0 1.64+ 7<31 15.0+6 3.80+5 8.0 1.89+8 12.2+6 1.34+ 6 6.5 1.77+8 10.0+6 3.04+6 5.0 2.33+8 8.18+6 5.84+6 -

4.0 4.46+8 6.36+6 8.36+6 3.0 3.51 +8 4.96+6 6.20+6 2.5 6.15+8 4.06+6 9.95 +6 2.0 5.15+8 3.01 +6 1.13+7 1.66 6.16+8 2.46+6 3.67 +6 1.33 7.83+8 2.35+6 2.16+7 1.0 5.95+8 1.83+6 7.18+7 0.8 7.57+8 1.11+6 2.11 + 8 0.6 1.43+9 0.55+6 6.14+8 0.4 9.06+8 0.11 + 6 4.59+8 0.3 1.44+9 3.35+3 1.14+8 0.2 1.41 +9 5.83 + 2 9.44+7 0.1 6.83+7 1.01 + 2 6.47 + 7 0.05 1.32+5 2.9+1 4.09+7 1.07 + 1 4.05+7 3.06 2.52+7 1.12 1.72+ 7 0.414 1.19+6 m

At 100 percer:it power t2)

Geometry, Table 12.2*2 f3) 1.64+ 7 = 1.64x107 (4)

Original Plant Design Basis Not Revised for Power Uprate Rev. 49, 04/96

SSES-FSAR TABLE 12.2--5 CALCULATED GAMMA RAY AND NEUTRON FLUXES AT OUTSIDE SURFACE OF PRIMARY SHIELD <4>

Outside Surface of Primary Shield At Core Midplane ' 11 f2J Page 1 of 1 Gamma Energy.

Gamma Flux Neutron Energy Neutron Flux (Upper mev)

(y/cm2-sec)

(Upper ev)

(q/cm2-sec) 10.0 9.81+4<3>

15.0+6 9.81 + 2 8.0 1.21 +6 12.2+6 3.38+3 6.5 1.03+6 10.0+6 8.05+3 5.0 9.78+5 8.18+6 1.77+4 4.0 1.39+6 6.36+6 2.65 +4 3.0 8.81 +5 4.96+6 1.97 +4 2.5 1.13+6 4.06+6 2.56 +4 2.0 9.31 +5 3.01 +6 4.54+4 1.66 1.10+6 2.46+6 2.51 +4 1.33 1.36+6 2.35 +6 7.78+4 1.0 1.03+6 1.83+6 2.01 +5 0.8 1.30+6 1.11 +6 4.49+5 0.6 2.82+6 0.55+6 1.13+6 0.4 1.52+6 0.11 +6 1.31 + 6 0.3 2.27+6 3.35+3 4.89+5 0.2 2.77 +6 5.83+2 4.95+5 0.1 4.89+5 1.01 + 2 4.70+5 0.05 3.79+3 2.9+1 3.40+5 1.07 + 1 4.10+ 5 3.06 3.09+5 1.12 2.58+5 0.414 4.59+5 (1)

At 100 percent power (2)

Geometry, Table 12.2-2 (3) 9.81 +4 = 9.81x104 (4)

Original Plant Design Basis Not Revised for Power Uprate Rev. 49, 04/96

SSES-FSAR Table Rev. 54 FSAR Rev. 64 Page 1 of 1 TABLE 12.2-6 REACTOR WATER CLEANUP SYSTEM N-16 SHIELDING SOURCE TERMS(1)(2)

Equipment Decay Times (seconds)

N-16 (Ci/gm)

Recirculation Pumps 0

5.00E+01(3)

Regenerative Heat Exchangers 32.6 2.10E+00 Non-Regenerative Heat Exchangers 96.6 4.18E-03 Inlet Lines to Filter Demineralizer 157 1.18E-05 NOTES:

(1)

Activation and Fission Products in Reactor Water are included in shielding design. However, N-16 dominates for all equipment except the Reactor Water Cleanup Filter/Demineralizer.

(2)

Decay times are at the inlet of each equipment piece.

(3) 5.00E+01 = 5.00x101

SSES-FSAR TABLE 12.2-7 REACTOR WATER CLEANUP FILTER DEMINERALIZER SHIELDING SOURCE TERMs<1)<2>{3>(4><5U5>

Activity Activity Activity Isotope (Curies)

Isotope (Curies)

Isotope (Curies)

Na-24

_1.46E+oou 1 Sr-92 1.44E+01 Nd-147 1.52E-01 P-32 2.q6E-01 y.. 92 1.45E+01 W-187 3.47E+00 Cr-51 8.53E+00 Ru-103 3.58E-01 Np-239 6.59E+02 Mn-54 9.40E-01 Rh-103m 3.58E-01 Sr-91 3.17E+01 Mn-56 6.20E+00 Ag-110m 1.40E+00 Y-91m 1.83E+01 Fe-59 1.55E+00 Te-129m 7.24E-01 Yk91 9.36E+00 Co-58 1.05E+02 Te-129 4.55E-01 Zr-95 8.30E-01 Co-60 1.21 E+01 Te-132 1.86E+02 Nb-95 9.82E-01 Ni-65 3.63E-02 1-132 2.00E+02 Mo-99 7.05E+01 Sr-90 5.58E+00 1-131 1.13E+02 Tc-99m 1.44E+02 Tc-101 1.42E+00 Cs-137 5.82E+00 1-133 8.99E+01 1-134 9.87E+00 Ba-137m 5.51E+00 1-135 4.17E+01 Cs-134 3.83E+00 Ba-140 1.08E+02 Ba-141 2.28E+00 Cs-136 1.34E+00 La-140 1.04E+02 La-141 2."52E+OO Cs-138 4.69E+00 Ba-142 1.24E+00 Ce-141 1.88E+00 Ba-139 1.06E+01 La-142

. 1.47E+00 Ce-144 8.20E-01 Br-83 1.72E+00 Pr-143 5.14E-01 Pr-144 8.19E-01 Sr-89 6.17E+01 Notes:

(1)

(2)

(3)

(4)

(5)

(6)

Based on 30 day accumulation of reactor water activation, halogen, and fission products (Tables 11. 1 *2 through 11.1-5).

(7)

DF = 10,000 (99.99 percent removal).

Flow rate through demineralizer is 148.5 gpm.

Initial decay of reactor water (flow from RPV to F/D inlet) of 157 seconds.

Not shown are isotopes with an accumulated inventory below 1E-01 curies.

Noble gases, tritium, and coolant activation products were not included as design source terms because they will not be present in the component under consideration due to decay (coolant activation products), removal as offgas (noble gases), or non-retention,* OF = 1, (tritium).

1.46E+00 = 1.46 X 10+0.

Rev. 53, 04/99 Page 1 of 1

SSES-FSAR TABLE 12.2-8 REACTOR WATER CLEANUP BACKWASH RECEIVING TANK SHIELDING SOURCE TERMsc1l(2>13l14)

• Activity Activity Activity Isotope (Curies)

Isotope (Curies)

Isotope (Curies)

Na-24 1.46E+QQ\"I Sr-92 1.44E+01 Nd-147 1.52E-01 P-32 2.56E-01 Y-92 1.45E+01 W-187 3.47E+00 Cr-51 8.53E+00 Ru-103 3.58E-01 Np-239 6.59E+02 Mn-54 9.40E-01 Rh-103m 3.58E-01 Sr-91 3.17E+01 Mn-56 6.20E+OO Ag-110m 1.40E+00 Y-91m 1.83E+01 Fe-59 1.55E+OO Te-129m 7.24E-01 Y-91 9.36E+00 Co-58 1.05E+02 Te-129 4.55E-01 Zr-95 8.30E-01 Co-60 1.21E+01 Te-132 1.86E+02 Nb-95 9.82E-01 Ni-65 3.63E-02 1-132 2.00E+02 Mo-99 7.05E+01 Sr-90 5.58E+00 1-131 1.13E+02 Tc-99m 1.44E+02 Tc-101 1.42E+00 Cs-137 5.82E+00 1-133 8.99E+o1 *.

1-134 9.87E+00 Ba-137m 5.51E+00 1-135 4.17E+01 Cs-134 3.83E+00 Ba-140 1.08E+02 Ba-141 2.28E+00 Cs-136 1.34E+00 La-140 1.04E+02 La-141 2.52E+00 Cs-138 4.69E+00 Ba-142 1.24E+O0 Ce-141 1.88E+00 Ba-139 1.06E+01 La-142 1.47E+O0 Ce-144 8.20E-01 Br-83 1.72E+00 Pr-143 5.14E-01 Pr-144 8.19E-01 Sr-89 6.17E+01 Notes:

(1)

Based on one RWCU filter demineralizer backwash at a 30 day interval.

(2)

Initial backwash activity as given in Table 12.2-7.

(3)

Backwash requires 1,470 gallons.

(4)

Isotopes with an activity less than 1 E-01 curies not shown.

(5) 1.46E+00 = 1.46 X 10+0*

Rev. 53, 04/99 Page 1 of 1 I

SSES-FSAR Table Rev. 1 FSAR Rev. 70 Page 1 of 7 Table 12.2-9A1 Activity (Curies) per Full Core of ATRIUM-11 Fuel Sum of Actinides, Fission Products and Light Elements Decay time Following Burnup to 41 GWd/MTU Nuclide T = 0 1 sec 30 min 1 hr 8 hr 1.0 d 4.0 d 30.0 d 90.0 d 180.0 d 1 yr 3 yr H 3 8.30E+04 8.30E+04 8.30E+04 8.30E+04 8.30E+04 8.30E+04 8.29E+04 8.26E+04 8.19E+04 8.07E+04 7.85E+04 7.01E+04 Na 24 1.92E+02 1.92E+02 1.88E+02 1.83E+02 1.33E+02 6.33E+01 2.27E+00 6.77E-13 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr 51 2.08E+06 2.08E+06 2.08E+06 2.08E+06 2.06E+06 2.03E+06 1.88E+06 9.82E+05 2.19E+05 2.30E+04 2.25E+02 2.62E-06 Mn 54 2.52E+04 2.52E+04 2.52E+04 2.52E+04 2.51E+04 2.51E+04 2.49E+04 2.35E+04 2.06E+04 1.69E+04 1.12E+04 2.21E+03 Fe 55 2.14E+05 2.14E+05 2.14E+05 2.14E+05 2.14E+05 2.14E+05 2.14E+05 2.10E+05 2.01E+05 1.89E+05 1.66E+05 1.00E+05 Mn 56 4.39E+05 4.39E+05 3.84E+05 3.35E+05 5.11E+04 6.93E+02 2.73E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co 58 4.33E+05 4.33E+05 4.33E+05 4.33E+05 4.32E+05 4.30E+05 4.18E+05 3.24E+05 1.80E+05 7.47E+04 1.22E+04 9.69E+00 Fe 59 1.51E+04 1.51E+04 1.51E+04 1.51E+04 1.50E+04 1.48E+04 1.42E+04 9.44E+03 3.71E+03 9.12E+02 5.11E+01 5.88E-04 Ni 59 2.52E+02 2.52E+02 2.52E+02 2.52E+02 2.52E+02 2.52E+02 2.52E+02 2.52E+02 2.52E+02 2.52E+02 2.52E+02 2.52E+02 Co 60 1.77E+04 1.77E+04 1.77E+04 1.77E+04 1.77E+04 1.77E+04 1.77E+04 1.75E+04 1.71E+04 1.66E+04 1.55E+04 1.19E+04 Ni 63 3.94E+04 3.94E+04 3.94E+04 3.94E+04 3.94E+04 3.94E+04 3.94E+04 3.94E+04 3.94E+04 3.93E+04 3.92E+04 3.86E+04 Cu 64 8.05E+04 8.05E+04 7.84E+04 7.63E+04 5.20E+04 2.17E+04 4.27E+02 6.94E-13 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ni 65 5.44E+04 5.44E+04 4.74E+04 4.13E+04 6.01E+03 7.34E+01 1.80E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ga 73 6.84E+03 6.84E+03 6.38E+03 5.94E+03 2.19E+03 2.23E+02 7.75E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ge 73m 6.74E+03 6.74E+03 6.28E+03 5.85E+03 2.16E+03 2.20E+02 9.44E-03 1.44E-03 8.56E-04 3.94E-04 7.98E-05 1.46E-07 As 76 3.03E+03 3.03E+03 2.99E+03 2.95E+03 2.46E+03 1.61E+03 2.40E+02 1.67E-05 5.02E-22 0.00E+00 0.00E+00 0.00E+00 Ge 77 2.20E+05 2.20E+05 2.14E+05 2.07E+05 1.35E+05 5.05E+04 6.10E+02 1.45E-14 0.00E+00 0.00E+00 0.00E+00 0.00E+00 As 77 2.27E+05 2.27E+05 2.27E+05 2.26E+05 2.20E+05 1.86E+05 5.69E+04 8.30E-01 5.69E-12 1.02E-28 0.00E+00 0.00E+00 Ge 78 5.94E+05 5.94E+05 4.69E+05 3.70E+05 1.36E+04 7.05E+00 1.18E-14 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 As 78 6.10E+05 6.10E+05 5.93E+05 5.57E+05 6.82E+04 1.02E+02 1.14E-12 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br 82 3.89E+05 3.89E+05 3.87E+05 3.83E+05 3.34E+05 2.44E+05 5.92E+04 2.81E-01 1.45E-13 5.41E-32 0.00E+00 0.00E+00 Br 83 1.27E+07 1.27E+07 1.20E+07 1.07E+07 1.46E+06 1.44E+04 1.34E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr 83m 1.27E+07 1.27E+07 1.27E+07 1.24E+07 3.75E+06 5.50E+04 4.46E-01 3.62E-01 2.23E-01 1.08E-01 2.45E-02 6.91E-05 Kr 85 1.67E+06 1.67E+06 1.67E+06 1.67E+06 1.67E+06 1.67E+06 1.67E+06 1.67E+06 1.65E+06 1.62E+06 1.57E+06 1.38E+06 Kr 85m 2.80E+07 2.80E+07 2.62E+07 2.43E+07 8.22E+06 6.91E+05 1.00E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb 86 2.47E+05 2.47E+05 2.47E+05 2.46E+05 2.44E+05 2.38E+05 2.13E+05 8.09E+04 8.68E+03 3.05E+02 3.13E-01 5.01E-13 Kr 87 5.33E+07 5.33E+07 4.10E+07 3.12E+07 6.88E+05 1.12E+02 1.02E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr 88 7.18E+07 7.18E+07 6.36E+07 5.63E+07 1.02E+07 2.05E+05 4.79E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb 88 7.31E+07 7.31E+07 6.88E+07 6.21E+07 1.14E+07 2.29E+05 5.35E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

SSES-FSAR Table Rev. 1 FSAR Rev. 70 Page 2 of 7 Table 12.2-9A1 Activity (Curies) per Full Core of ATRIUM-11 Fuel Sum of Actinides, Fission Products and Light Elements Decay time Following Burnup to 41 GWd/MTU Nuclide T = 0 1 sec 30 min 1 hr 8 hr 1.0 d 4.0 d 30.0 d 90.0 d 180.0 d 1 yr 3 yr Zr 89 2.86E+04 2.86E+04 2.84E+04 2.83E+04 2.66E+04 2.31E+04 1.22E+04 4.92E+01 1.46E-04 7.42E-13 6.68E-30 0.00E+00 Sr 89 9.99E+07 9.99E+07 9.99E+07 9.98E+07 9.94E+07 9.85E+07 9.46E+07 6.62E+07 2.91E+07 8.46E+06 6.68E+05 2.99E+01 Y 89m 3.99E+04 3.99E+04 3.80E+04 3.79E+04 3.62E+04 3.26E+04 2.13E+04 6.43E+03 2.80E+03 8.15E+02 6.44E+01 2.89E-03 Sr 90 1.33E+07 1.33E+07 1.33E+07 1.33E+07 1.33E+07 1.33E+07 1.33E+07 1.33E+07 1.32E+07 1.32E+07 1.30E+07 1.24E+07 Y 90 1.41E+07 1.41E+07 1.41E+07 1.41E+07 1.40E+07 1.39E+07 1.36E+07 1.33E+07 1.33E+07 1.32E+07 1.30E+07 1.24E+07 Sr 91 1.26E+08 1.26E+08 1.21E+08 1.17E+08 7.08E+07 2.24E+07 1.26E+05 3.92E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y 91 1.30E+08 1.30E+08 1.30E+08 1.30E+08 1.30E+08 1.29E+08 1.25E+08 9.19E+07 4.51E+07 1.55E+07 1.74E+06 3.05E+02 Y 91m 7.40E+07 7.40E+07 7.36E+07 7.24E+07 4.56E+07 1.44E+07 8.09E+04 2.52E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr 92 1.36E+08 1.36E+08 1.20E+08 1.05E+08 1.76E+07 2.93E+05 2.95E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y 92 1.37E+08 1.37E+08 1.37E+08 1.34E+08 6.40E+07 4.33E+06 3.98E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr 93 3.53E+02 3.53E+02 3.53E+02 3.53E+02 3.53E+02 3.53E+02 3.53E+02 3.53E+02 3.53E+02 3.53E+02 3.53E+02 3.53E+02 Y 93 1.56E+08 1.56E+08 1.53E+08 1.48E+08 9.16E+07 3.08E+07 2.29E+05 8.09E-14 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr 95 1.89E+08 1.89E+08 1.88E+08 1.88E+08 1.88E+08 1.87E+08 1.81E+08 1.36E+08 7.12E+07 2.69E+07 3.63E+06 1.34E+03 Nb 95 1.89E+08 1.89E+08 1.89E+08 1.89E+08 1.89E+08 1.89E+08 1.89E+08 1.75E+08 1.19E+08 5.28E+07 7.83E+06 2.96E+03 Nb 95m 2.12E+06 2.12E+06 2.12E+06 2.12E+06 2.11E+06 2.10E+06 2.05E+06 1.56E+06 8.15E+05 3.08E+05 4.15E+04 1.54E+01 Nb 96 4.88E+05 4.88E+05 4.81E+05 4.74E+05 3.85E+05 2.39E+05 2.82E+04 2.55E-04 6.94E-23 0.00E+00 0.00E+00 0.00E+00 Zr 97 1.91E+08 1.91E+08 1.88E+08 1.84E+08 1.37E+08 7.09E+07 3.60E+06 2.20E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb 97 1.93E+08 1.93E+08 1.92E+08 1.90E+08 1.47E+08 7.13E+07 3.62E+06 2.37E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb 97m 1.82E+08 1.82E+08 1.78E+08 1.75E+08 1.31E+08 6.75E+07 3.43E+06 2.09E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mo 99 2.01E+08 2.01E+08 2.00E+08 1.99E+08 1.85E+08 1.56E+08 7.32E+07 1.04E+05 2.80E-02 3.90E-12 2.15E-32 0.00E+00 Tc 99 2.36E+03 2.36E+03 2.36E+03 2.36E+03 2.36E+03 2.37E+03 2.37E+03 2.37E+03 2.37E+03 2.37E+03 2.37E+03 2.37E+03 Tc 99m 1.76E+08 1.76E+08 1.76E+08 1.76E+08 1.71E+08 1.50E+08 7.08E+07 1.01E+05 2.71E-02 3.78E-12 2.08E-32 0.00E+00 Ru103 1.74E+08 1.74E+08 1.73E+08 1.73E+08 1.73E+08 1.70E+08 1.62E+08 1.02E+08 3.54E+07 7.22E+06 2.75E+05 6.93E-01 Rh103m 1.72E+08 1.72E+08 1.72E+08 1.71E+08 1.71E+08 1.69E+08 1.60E+08 1.01E+08 3.50E+07 7.15E+06 2.72E+05 6.85E-01 Ru105 1.21E+08 1.21E+08 1.15E+08 1.06E+08 3.57E+07 2.93E+06 3.85E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rh105 1.12E+08 1.12E+08 1.12E+08 1.12E+08 1.06E+08 8.06E+07 1.98E+07 9.63E+01 5.30E-11 2.16E-29 0.00E+00 0.00E+00 Rh105m 3.42E+07 3.42E+07 3.26E+07 3.02E+07 1.01E+07 8.34E+05 1.10E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ru106 6.72E+07 6.72E+07 6.72E+07 6.72E+07 6.71E+07 6.70E+07 6.67E+07 6.35E+07 5.68E+07 4.80E+07 3.40E+07 8.72E+06 Rh106 7.51E+07 7.49E+07 6.72E+07 6.72E+07 6.71E+07 6.70E+07 6.67E+07 6.35E+07 5.68E+07 4.80E+07 3.40E+07 8.72E+06

SSES-FSAR Table Rev. 1 FSAR Rev. 70 Page 3 of 7 Table 12.2-9A1 Activity (Curies) per Full Core of ATRIUM-11 Fuel Sum of Actinides, Fission Products and Light Elements Decay time Following Burnup to 41 GWd/MTU Nuclide T = 0 1 sec 30 min 1 hr 8 hr 1.0 d 4.0 d 30.0 d 90.0 d 180.0 d 1 yr 3 yr Rh106m 8.43E+05 8.43E+05 7.19E+05 6.14E+05 6.65E+04 4.14E+02 4.89E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ag109m 3.63E+07 3.63E+07 3.55E+07 3.46E+07 2.43E+07 1.08E+07 2.83E+05 2.13E+01 1.95E+01 1.70E+01 1.29E+01 4.31E+00 Ag110 1.56E+07 1.52E+07 4.63E+03 4.63E+03 4.62E+03 4.61E+03 4.58E+03 4.26E+03 3.60E+03 2.81E+03 1.68E+03 2.22E+02 Ag110m 3.40E+05 3.40E+05 3.40E+05 3.40E+05 3.40E+05 3.39E+05 3.36E+05 3.13E+05 2.65E+05 2.06E+05 1.24E+05 1.63E+04 Pd111 6.84E+06 6.84E+06 2.84E+06 1.17E+06 2.16E+03 2.86E+02 3.28E-02 2.31E-36 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Pd111m 7.51E+03 7.51E+03 7.05E+03 6.62E+03 2.74E+03 3.65E+02 4.18E-02 2.94E-36 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ag111 7.00E+06 7.00E+06 7.00E+06 6.99E+06 6.81E+06 6.40E+06 4.84E+06 4.31E+05 1.62E+03 3.74E-01 1.25E-08 0.00E+00 Ag111m 6.91E+06 6.91E+06 2.96E+06 1.22E+06 2.67E+03 3.54E+02 4.07E-02 2.86E-36 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Pd112 3.11E+06 3.11E+06 3.06E+06 3.01E+06 2.39E+06 1.41E+06 1.31E+05 1.53E-04 3.75E-25 0.00E+00 0.00E+00 0.00E+00 Ag112 3.11E+06 3.11E+06 3.11E+06 3.10E+06 2.71E+06 1.65E+06 1.54E+05 1.80E-04 4.40E-25 0.00E+00 0.00E+00 0.00E+00 In113m 2.89E+05 2.89E+05 2.89E+05 2.89E+05 2.89E+05 2.88E+05 2.83E+05 2.42E+05 1.68E+05 9.79E+04 3.21E+04 3.96E+02 Sn113 2.89E+05 2.89E+05 2.89E+05 2.89E+05 2.89E+05 2.88E+05 2.82E+05 2.41E+05 1.68E+05 9.78E+04 3.21E+04 3.96E+02 Ag113 1.43E+06 1.43E+06 1.35E+06 1.27E+06 5.15E+05 6.52E+04 6.00E+00 6.29E-35 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cd113m 3.58E+01 3.58E+01 3.59E+01 3.60E+01 3.65E+01 3.69E+01 3.69E+01 3.68E+01 3.65E+01 3.61E+01 3.52E+01 3.19E+01 In114 6.06E+04 6.03E+04 3.23E+04 3.23E+04 3.22E+04 3.19E+04 3.05E+04 2.12E+04 9.16E+03 2.60E+03 1.95E+02 7.10E-03 In114m 3.34E+04 3.34E+04 3.34E+04 3.34E+04 3.32E+04 3.29E+04 3.16E+04 2.19E+04 9.47E+03 2.69E+03 2.02E+02 7.34E-03 Cd115 1.15E+06 1.15E+06 1.14E+06 1.14E+06 1.04E+06 8.45E+05 3.32E+05 1.02E+02 7.92E-07 5.44E-19 0.00E+00 0.00E+00 Cd115m 7.00E+04 7.00E+04 7.00E+04 7.00E+04 6.97E+04 6.90E+04 6.58E+04 4.39E+04 1.73E+04 4.26E+03 2.40E+02 2.80E-03 In115m 1.15E+06 1.15E+06 1.15E+06 1.15E+06 1.10E+06 9.19E+05 3.63E+05 1.16E+02 1.83E+00 4.52E-01 2.55E-02 2.98E-07 Cd117 8.82E+05 8.82E+05 7.73E+05 6.72E+05 9.58E+04 1.11E+03 2.20E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cd117m 2.00E+05 2.00E+05 1.81E+05 1.64E+05 3.86E+04 1.42E+03 5.04E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 In117 6.54E+05 6.54E+05 6.47E+05 6.30E+05 2.00E+05 4.07E+03 6.49E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 In117m 8.10E+05 8.10E+05 8.02E+05 7.79E+05 2.33E+05 4.10E+03 2.09E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sn117m 7.86E+04 7.86E+04 7.86E+04 7.85E+04 7.73E+04 7.48E+04 6.42E+04 1.71E+04 8.01E+02 8.16E+00 6.56E-04 4.55E-20 Sn119m 5.13E+04 5.13E+04 5.13E+04 5.13E+04 5.12E+04 5.12E+04 5.08E+04 4.78E+04 4.14E+04 3.35E+04 2.16E+04 3.85E+03 Sn121 1.60E+06 1.60E+06 1.58E+06 1.56E+06 1.31E+06 8.69E+05 1.40E+05 3.27E+03 3.27E+03 3.25E+03 3.23E+03 3.13E+03 Sn121m 4.22E+03 4.22E+03 4.22E+03 4.22E+03 4.22E+03 4.22E+03 4.22E+03 4.22E+03 4.21E+03 4.19E+03 4.16E+03 4.03E+03 Sb122 2.18E+05 2.18E+05 2.17E+05 2.16E+05 2.00E+05 1.69E+05 7.87E+04 1.05E+02 2.46E-05 2.78E-15 9.97E-36 0.00E+00 Te123m 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.25E+03 1.07E+03 7.55E+02 4.48E+02 1.53E+02 2.19E+00

SSES-FSAR Table Rev. 1 FSAR Rev. 70 Page 4 of 7 Table 12.2-9A1 Activity (Curies) per Full Core of ATRIUM-11 Fuel Sum of Actinides, Fission Products and Light Elements Decay time Following Burnup to 41 GWd/MTU Nuclide T = 0 1 sec 30 min 1 hr 8 hr 1.0 d 4.0 d 30.0 d 90.0 d 180.0 d 1 yr 3 yr Sn123 1.67E+05 1.67E+05 1.67E+05 1.67E+05 1.67E+05 1.66E+05 1.63E+05 1.42E+05 1.03E+05 6.36E+04 2.36E+04 4.69E+02 Sn123m 1.10E+06 1.10E+06 6.59E+05 3.92E+05 2.74E+02 1.68E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sb124 9.71E+04 9.71E+04 9.70E+04 9.70E+04 9.67E+04 9.59E+04 9.27E+04 6.87E+04 3.44E+04 1.22E+04 1.45E+03 3.25E-01 Sn125 1.14E+06 1.14E+06 1.14E+06 1.13E+06 1.11E+06 1.06E+06 8.53E+05 1.32E+05 1.76E+03 2.72E+00 4.55E-06 0.00E+00 Sn125m 1.86E+06 1.86E+06 2.11E+05 2.37E+04 1.24E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sb125 1.60E+06 1.60E+06 1.60E+06 1.60E+06 1.60E+06 1.60E+06 1.60E+06 1.57E+06 1.51E+06 1.42E+06 1.25E+06 7.57E+05 Te125m 3.49E+05 3.49E+05 3.49E+05 3.49E+05 3.49E+05 3.49E+05 3.50E+05 3.54E+05 3.55E+05 3.43E+05 3.06E+05 1.85E+05 Sb126 4.76E+04 4.76E+04 4.76E+04 4.75E+04 4.67E+04 4.50E+04 3.80E+04 8.85E+03 3.10E+02 7.57E+00 5.62E+00 5.62E+00 Sb126m 5.72E+04 5.72E+04 1.93E+04 6.55E+03 4.02E+01 4.01E+01 4.01E+01 4.01E+01 4.01E+01 4.01E+01 4.01E+01 4.01E+01 Sn127 6.11E+06 6.11E+06 5.18E+06 4.39E+06 4.36E+05 2.22E+03 1.06E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sb127 1.03E+07 1.03E+07 1.03E+07 1.03E+07 9.83E+06 8.73E+06 5.09E+06 4.72E+04 9.60E-01 8.81E-08 3.02E-22 0.00E+00 Te127 9.28E+06 9.28E+06 9.28E+06 9.28E+06 9.21E+06 8.63E+06 5.45E+06 6.85E+05 4.38E+05 2.47E+05 7.62E+04 7.34E+02 Te127m 7.29E+05 7.29E+05 7.30E+05 7.30E+05 7.31E+05 7.35E+05 7.42E+05 6.55E+05 4.47E+05 2.52E+05 7.78E+04 7.50E+02 Sb128 1.60E+06 1.60E+06 1.56E+06 1.51E+06 9.04E+05 2.64E+05 1.04E+03 1.47E-18 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sb129 3.08E+07 3.08E+07 2.87E+07 2.66E+07 8.82E+06 7.10E+05 8.42E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Te129 2.93E+07 2.93E+07 2.91E+07 2.85E+07 1.33E+07 3.96E+06 2.95E+06 1.73E+06 5.00E+05 7.82E+04 1.72E+03 4.96E-04 Te129m 5.05E+06 5.05E+06 5.05E+06 5.05E+06 5.04E+06 4.97E+06 4.68E+06 2.73E+06 7.93E+05 1.24E+05 2.73E+03 7.86E-04 Xe129m 1.30E+03 1.30E+03 1.30E+03 1.30E+03 1.27E+03 1.20E+03 9.53E+02 1.25E+02 1.16E+00 1.03E-03 5.51E-10 0.00E+00 I130 2.53E+06 2.53E+06 2.47E+06 2.41E+06 1.62E+06 6.62E+05 1.17E+04 7.41E-12 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Te131 9.29E+07 9.28E+07 7.19E+07 4.58E+07 4.69E+06 3.36E+06 7.49E+05 1.68E+00 1.54E-13 4.28E-33 0.00E+00 0.00E+00 Te131m 2.11E+07 2.11E+07 2.09E+07 2.07E+07 1.79E+07 1.28E+07 2.86E+06 6.40E+00 5.87E-13 1.63E-32 0.00E+00 0.00E+00 I131 1.08E+08 1.08E+08 1.08E+08 1.08E+08 1.06E+08 1.01E+08 7.95E+07 8.48E+06 4.76E+04 2.00E+01 2.30E-06 0.00E+00 Xe131m 1.18E+06 1.18E+06 1.18E+06 1.18E+06 1.18E+06 1.17E+06 1.14E+06 4.55E+05 1.82E+04 9.91E+01 1.97E-03 5.42E-22 Te132 1.54E+08 1.54E+08 1.53E+08 1.53E+08 1.43E+08 1.24E+08 6.49E+07 2.34E+05 5.40E-01 1.89E-09 7.84E-27 0.00E+00 I132 1.58E+08 1.58E+08 1.58E+08 1.57E+08 1.48E+08 1.28E+08 6.69E+07 2.41E+05 5.56E-01 1.95E-09 8.08E-27 0.00E+00 Cs132 2.45E+03 2.45E+03 2.44E+03 2.44E+03 2.36E+03 2.20E+03 1.60E+03 9.90E+01 1.62E-01 1.06E-05 2.71E-14 0.00E+00 Te133m 1.10E+08 1.10E+08 7.63E+07 5.24E+07 2.74E+05 1.66E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I133 2.21E+08 2.21E+08 2.20E+08 2.18E+08 1.74E+08 1.02E+08 9.29E+06 8.65E-03 1.25E-23 0.00E+00 0.00E+00 0.00E+00 Xe133 2.17E+08 2.17E+08 2.17E+08 2.17E+08 2.16E+08 2.09E+08 1.54E+08 5.07E+06 1.82E+03 1.24E-02 2.96E-13 0.00E+00

SSES-FSAR Table Rev. 1 FSAR Rev. 70 Page 5 of 7 Table 12.2-9A1 Activity (Curies) per Full Core of ATRIUM-11 Fuel Sum of Actinides, Fission Products and Light Elements Decay time Following Burnup to 41 GWd/MTU Nuclide T = 0 1 sec 30 min 1 hr 8 hr 1.0 d 4.0 d 30.0 d 90.0 d 180.0 d 1 yr 3 yr Xe133m 6.85E+06 6.85E+06 6.84E+06 6.84E+06 6.73E+06 6.17E+06 2.95E+06 8.34E+02 4.72E-06 2.01E-18 0.00E+00 0.00E+00 I134 2.48E+08 2.48E+08 2.17E+08 1.76E+08 1.53E+06 5.58E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs134 2.36E+07 2.36E+07 2.36E+07 2.36E+07 2.36E+07 2.35E+07 2.35E+07 2.29E+07 2.17E+07 2.00E+07 1.69E+07 8.62E+06 Cs134m 5.99E+06 5.99E+06 5.32E+06 4.72E+06 8.92E+05 1.98E+04 7.14E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I135 2.11E+08 2.11E+08 2.01E+08 1.90E+08 9.10E+07 1.68E+07 8.45E+03 2.17E-25 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe135 5.85E+07 5.85E+07 6.42E+07 6.92E+07 9.47E+07 5.43E+07 3.93E+05 1.17E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe135m 4.74E+07 4.74E+07 3.73E+07 3.34E+07 1.56E+07 2.89E+06 1.45E+03 3.72E-26 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba135m 1.83E+04 1.83E+04 1.80E+04 1.78E+04 1.50E+04 1.02E+04 1.80E+03 5.12E-04 4.02E-19 0.00E+00 0.00E+00 0.00E+00 Cs136 5.95E+06 5.95E+06 5.95E+06 5.94E+06 5.85E+06 5.65E+06 4.82E+06 1.23E+06 5.20E+04 4.54E+02 2.66E-02 5.33E-19 Ba136m 6.63E+05 6.60E+05 6.59E+05 6.58E+05 6.48E+05 6.26E+05 5.34E+05 1.36E+05 5.76E+03 5.03E+01 2.95E-03 5.91E-20 Cs137 1.80E+07 1.80E+07 1.80E+07 1.80E+07 1.80E+07 1.80E+07 1.80E+07 1.80E+07 1.79E+07 1.78E+07 1.76E+07 1.68E+07 Ba137m 1.72E+07 1.72E+07 1.71E+07 1.71E+07 1.71E+07 1.71E+07 1.71E+07 1.71E+07 1.70E+07 1.69E+07 1.67E+07 1.60E+07 Cs138 2.05E+08 2.05E+08 1.53E+08 9.17E+07 1.62E+04 3.64E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba139 1.96E+08 1.96E+08 1.69E+08 1.34E+08 4.02E+06 1.33E+03 2.94E-13 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba140 1.89E+08 1.89E+08 1.89E+08 1.89E+08 1.86E+08 1.79E+08 1.52E+08 3.70E+07 1.42E+06 1.07E+04 4.58E-01 2.69E-18 La140 1.98E+08 1.98E+08 1.98E+08 1.98E+08 1.97E+08 1.93E+08 1.71E+08 4.26E+07 1.63E+06 1.23E+04 5.27E-01 3.09E-18 La141 1.77E+08 1.77E+08 1.71E+08 1.59E+08 4.67E+07 2.76E+06 8.15E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce141 1.78E+08 1.78E+08 1.78E+08 1.78E+08 1.78E+08 1.76E+08 1.65E+08 9.46E+07 2.63E+07 3.86E+06 7.48E+04 1.30E-02 La142 1.70E+08 1.70E+08 1.50E+08 1.21E+08 4.98E+06 3.35E+03 1.78E-11 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Pr142 8.29E+06 8.29E+06 8.17E+06 8.03E+06 6.23E+06 3.49E+06 2.56E+05 3.84E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce143 1.65E+08 1.65E+08 1.65E+08 1.63E+08 1.41E+08 1.01E+08 2.22E+07 4.59E+01 3.47E-12 7.24E-32 0.00E+00 0.00E+00 Pr143 1.61E+08 1.61E+08 1.61E+08 1.61E+08 1.61E+08 1.60E+08 1.44E+08 3.89E+07 1.82E+06 1.83E+04 1.44E+00 9.22E-17 Ce144 1.48E+08 1.48E+08 1.48E+08 1.48E+08 1.48E+08 1.48E+08 1.47E+08 1.38E+08 1.19E+08 9.56E+07 6.10E+07 1.03E+07 Pr144 1.49E+08 1.49E+08 1.49E+08 1.48E+08 1.48E+08 1.48E+08 1.47E+08 1.38E+08 1.19E+08 9.56E+07 6.10E+07 1.03E+07 Pr144m 1.95E+06 1.95E+06 1.44E+06 1.42E+06 1.41E+06 1.41E+06 1.40E+06 1.32E+06 1.14E+06 9.13E+05 5.82E+05 9.86E+04 Pr145 1.12E+08 1.12E+08 1.07E+08 1.01E+08 4.49E+07 7.04E+06 1.68E+03 6.84E-29 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nd147 7.07E+07 7.07E+07 7.06E+07 7.06E+07 6.93E+07 6.64E+07 5.50E+07 1.06E+07 2.41E+05 8.22E+02 6.96E-03 6.74E-23 Pm147 2.76E+07 2.76E+07 2.76E+07 2.76E+07 2.76E+07 2.77E+07 2.77E+07 2.77E+07 2.67E+07 2.50E+07 2.18E+07 1.29E+07 Pm148 2.13E+07 2.13E+07 2.12E+07 2.12E+07 2.04E+07 1.87E+07 1.28E+07 5.37E+05 3.62E+04 7.93E+03 3.55E+02 1.69E-03

SSES-FSAR Table Rev. 1 FSAR Rev. 70 Page 6 of 7 Table 12.2-9A1 Activity (Curies) per Full Core of ATRIUM-11 Fuel Sum of Actinides, Fission Products and Light Elements Decay time Following Burnup to 41 GWd/MTU Nuclide T = 0 1 sec 30 min 1 hr 8 hr 1.0 d 4.0 d 30.0 d 90.0 d 180.0 d 1 yr 3 yr Pm148m 3.37E+06 3.37E+06 3.37E+06 3.37E+06 3.35E+06 3.32E+06 3.15E+06 2.04E+06 7.44E+05 1.64E+05 7.36E+03 3.50E-02 Nd149 4.10E+07 4.10E+07 3.43E+07 2.80E+07 1.69E+06 2.76E+03 7.91E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Pm149 5.72E+07 5.72E+07 5.70E+07 5.69E+07 5.27E+07 4.28E+07 1.67E+07 4.84E+03 3.30E-05 1.85E-17 0.00E+00 0.00E+00 Pm150 6.34E+05 6.34E+05 5.57E+05 4.90E+05 8.01E+04 1.28E+03 1.05E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Pm151 2.11E+07 2.11E+07 2.10E+07 2.08E+07 1.75E+07 1.18E+07 2.04E+06 4.97E-01 2.70E-16 0.00E+00 0.00E+00 0.00E+00 Sm151 4.27E+04 4.27E+04 4.27E+04 4.27E+04 4.28E+04 4.30E+04 4.34E+04 4.34E+04 4.34E+04 4.33E+04 4.31E+04 4.25E+04 Eu152m 1.40E+04 1.40E+04 1.35E+04 1.30E+04 7.73E+03 2.35E+03 1.10E+01 7.42E-20 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sm153 5.21E+07 5.21E+07 5.18E+07 5.14E+07 4.63E+07 3.65E+07 1.25E+07 1.14E+03 5.42E-07 5.63E-21 0.00E+00 0.00E+00 Gd153 8.30E+04 8.30E+04 8.30E+04 8.30E+04 8.29E+04 8.27E+04 8.20E+04 7.61E+04 6.40E+04 4.94E+04 2.90E+04 3.53E+03 Eu154 9.98E+05 9.98E+05 9.98E+05 9.98E+05 9.98E+05 9.98E+05 9.97E+05 9.92E+05 9.79E+05 9.59E+05 9.21E+05 7.84E+05 Eu155 6.40E+05 6.40E+05 6.40E+05 6.40E+05 6.40E+05 6.40E+05 6.39E+05 6.33E+05 6.18E+05 5.96E+05 5.53E+05 4.13E+05 Sm156 2.67E+06 2.67E+06 2.58E+06 2.48E+06 1.48E+06 4.56E+05 2.25E+03 2.34E-17 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Eu156 3.05E+07 3.05E+07 3.04E+07 3.04E+07 3.00E+07 2.92E+07 2.54E+07 7.77E+06 5.02E+05 8.27E+03 1.78E+00 6.08E-15 Gd159 2.23E+07 2.23E+07 2.19E+07 2.15E+07 1.65E+07 9.05E+06 6.08E+05 4.16E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tb160 4.83E+06 4.83E+06 4.83E+06 4.83E+06 4.82E+06 4.79E+06 4.65E+06 3.63E+06 2.04E+06 8.61E+05 1.46E+05 1.33E+02 Tb161 4.30E+06 4.30E+06 4.29E+06 4.28E+06 4.16E+06 3.89E+06 2.88E+06 2.12E+05 5.14E+02 6.13E-02 5.29E-10 0.00E+00 Dy165 7.32E+05 7.32E+05 6.34E+05 5.47E+05 6.84E+04 5.91E+02 3.06E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Dy166 3.41E+03 3.41E+03 3.40E+03 3.38E+03 3.19E+03 2.78E+03 1.51E+03 7.53E+00 3.67E-05 3.94E-13 1.65E-29 0.00E+00 Ho166 1.26E+05 1.26E+05 1.25E+05 1.23E+05 1.03E+05 6.93E+04 1.24E+04 1.12E+01 5.46E-05 5.87E-13 2.45E-29 0.00E+00 Hf175 3.15E+03 3.15E+03 3.15E+03 3.15E+03 3.14E+03 3.12E+03 3.03E+03 2.34E+03 1.29E+03 5.31E+02 8.50E+01 6.16E-02 Lu176m 1.71E+03 1.71E+03 1.55E+03 1.41E+03 3.71E+02 1.76E+01 1.91E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Lu177 7.84E+02 7.84E+02 7.82E+02 7.80E+02 7.57E+02 7.06E+02 5.17E+02 3.45E+01 1.75E-01 7.43E-02 3.34E-02 1.43E-03 Hf180m 8.54E+03 8.54E+03 8.02E+03 7.53E+03 3.12E+03 4.15E+02 4.76E-02 3.34E-36 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Hf181 1.52E+05 1.52E+05 1.52E+05 1.52E+05 1.51E+05 1.49E+05 1.42E+05 9.30E+04 3.49E+04 8.00E+03 3.89E+02 2.54E-03 W181 9.96E-02 9.96E-02 9.96E-02 9.95E-02 9.94E-02 9.90E-02 9.73E-02 8.39E-02 5.95E-02 3.56E-02 1.23E-02 1.90E-04 Ta182 4.64E+03 4.64E+03 4.64E+03 4.64E+03 4.63E+03 4.62E+03 4.53E+03 3.87E+03 2.70E+03 1.57E+03 5.12E+02 6.22E+00 Ta183 4.93E+04 4.93E+04 4.92E+04 4.90E+04 4.71E+04 4.30E+04 2.86E+04 8.36E+02 2.40E-01 1.17E-06 1.41E-17 0.00E+00 W183m 2.64E+03 2.63E+03 2.51E+03 2.50E+03 2.40E+03 2.19E+03 1.46E+03 4.26E+01 1.22E-02 5.97E-08 7.18E-19 0.00E+00 W185 3.26E+01 3.26E+01 3.25E+01 3.25E+01 3.25E+01 3.23E+01 3.14E+01 2.47E+01 1.42E+01 6.18E+00 1.12E+00 1.33E-03

SSES-FSAR Table Rev. 1 FSAR Rev. 70 Page 7 of 7 Table 12.2-9A1 Activity (Curies) per Full Core of ATRIUM-11 Fuel Sum of Actinides, Fission Products and Light Elements Decay time Following Burnup to 41 GWd/MTU Nuclide T = 0 1 sec 30 min 1 hr 8 hr 1.0 d 4.0 d 30.0 d 90.0 d 180.0 d 1 yr 3 yr Re186 9.12E+00 9.12E+00 9.09E+00 9.05E+00 8.57E+00 7.57E+00 4.33E+00 3.40E-02 4.97E-07 2.52E-08 2.52E-08 2.52E-08 W187 9.23E-02 9.23E-02 9.10E-02 8.97E-02 7.33E-02 4.62E-02 5.77E-03 8.60E-11 7.46E-29 0.00E+00 0.00E+00 0.00E+00 W188 1.03E-04 1.03E-04 1.03E-04 1.03E-04 1.03E-04 1.02E-04 9.93E-05 7.67E-05 4.22E-05 1.73E-05 2.75E-06 1.95E-09 Re188 1.01E-02 1.01E-02 9.91E-03 9.71E-03 7.33E-03 3.87E-03 3.00E-04 7.74E-05 4.27E-05 1.75E-05 2.78E-06 1.97E-09 Os191 1.00E-06 1.00E-06 1.00E-06 1.00E-06 1.00E-06 9.82E-07 8.65E-07 2.69E-07 1.80E-08 3.14E-10 7.60E-14 4.08E-28 Os191m 8.50E-07 8.50E-07 8.28E-07 8.06E-07 5.56E-07 2.39E-07 5.29E-09 2.42E-23 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ir192 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.04E-07 1.04E-07 1.01E-07 7.91E-08 4.50E-08 1.93E-08 3.40E-09 3.59E-12 Np236m 8.51E+02 8.51E+02 8.38E+02 8.25E+02 6.65E+02 4.06E+02 4.42E+01 1.98E-07 1.07E-26 0.00E+00 0.00E+00 0.00E+00 U237 8.86E+07 8.86E+07 8.85E+07 8.83E+07 8.57E+07 8.00E+07 5.88E+07 4.07E+06 9.01E+03 4.20E+02 4.09E+02 3.72E+02 Pu237 6.93E+01 6.93E+01 6.93E+01 6.93E+01 6.90E+01 6.83E+01 6.53E+01 4.40E+01 1.77E+01 4.52E+00 2.72E-01 4.17E-06 Np238 4.14E+07 4.14E+07 4.11E+07 4.08E+07 3.71E+07 2.98E+07 1.12E+07 2.25E+03 4.45E+00 4.44E+00 4.43E+00 4.39E+00 Pu238 4.38E+05 4.38E+05 4.38E+05 4.38E+05 4.38E+05 4.38E+05 4.40E+05 4.45E+05 4.52E+05 4.60E+05 4.68E+05 4.68E+05 Np239 2.04E+09 2.04E+09 2.03E+09 2.03E+09 1.86E+09 1.53E+09 6.33E+08 3.04E+05 2.77E+03 2.77E+03 2.77E+03 2.76E+03 Pu239 4.13E+04 4.13E+04 4.13E+04 4.13E+04 4.13E+04 4.14E+04 4.17E+04 4.18E+04 4.18E+04 4.18E+04 4.18E+04 4.18E+04 Np240 1.15E+06 1.15E+06 8.25E+05 5.90E+05 5.35E+03 1.15E-01 3.92E-08 3.92E-08 3.92E-08 3.92E-08 3.92E-08 3.92E-08 Pu240 7.36E+04 7.36E+04 7.36E+04 7.36E+04 7.36E+04 7.36E+04 7.36E+04 7.36E+04 7.36E+04 7.36E+04 7.36E+04 7.37E+04 Pu241 1.75E+07 1.75E+07 1.75E+07 1.75E+07 1.75E+07 1.75E+07 1.75E+07 1.74E+07 1.73E+07 1.71E+07 1.67E+07 1.51E+07 Am241 2.16E+04 2.16E+04 2.16E+04 2.16E+04 2.16E+04 2.17E+04 2.19E+04 2.39E+04 2.85E+04 3.53E+04 4.89E+04 9.96E+04 Am242m 9.70E+02 9.70E+02 9.70E+02 9.70E+02 9.70E+02 9.70E+02 9.70E+02 9.70E+02 9.69E+02 9.68E+02 9.65E+02 9.56E+02 Am242 1.25E+07 1.25E+07 1.22E+07 1.20E+07 8.84E+06 4.43E+06 1.97E+05 9.65E+02 9.64E+02 9.63E+02 9.61E+02 9.51E+02 Cm242 7.68E+06 7.68E+06 7.68E+06 7.68E+06 7.68E+06 7.67E+06 7.59E+06 6.79E+06 5.26E+06 3.59E+06 1.63E+06 7.40E+04 Pu243 3.93E+07 3.93E+07 3.67E+07 3.42E+07 1.28E+07 1.37E+06 5.80E+01 3.26E-05 3.26E-05 3.26E-05 3.26E-05 3.26E-05 Am243 2.76E+03 2.76E+03 2.76E+03 2.76E+03 2.76E+03 2.77E+03 2.77E+03 2.77E+03 2.77E+03 2.77E+03 2.77E+03 2.76E+03 Cm243 3.08E+03 3.08E+03 3.08E+03 3.08E+03 3.08E+03 3.08E+03 3.08E+03 3.07E+03 3.06E+03 3.04E+03 3.01E+03 2.87E+03 Am244 8.92E+05 8.92E+05 8.62E+05 8.33E+05 5.15E+05 1.72E+05 1.23E+03 3.76E-07 3.71E-07 3.64E-07 3.50E-07 3.00E-07 Cm244 3.91E+05 3.91E+05 3.91E+05 3.91E+05 3.91E+05 3.91E+05 3.91E+05 3.90E+05 3.87E+05 3.84E+05 3.76E+05 3.49E+05

SSES-FSAR Table Rev. 1 FSAR Rev. 70 Page 1 of 8 Table 12.2-9A2 Activity (Curies) per Single Assembly of ATRIUM-11 Fuel Sum of Actinides, Fission Products and Light Elements Decay time Following Burnup to 58 GWd/MTU Nuclide T = 0 1 sec 30 min 1 hr 8 hr 1.0 d 4.0 d 30.0 d 90.0 d 180.0 d 1 yr 3 yr H 3 1.58E+02 1.58E+02 1.58E+02 1.58E+02 1.58E+02 1.58E+02 1.58E+02 1.57E+02 1.56E+02 1.54E+02 1.49E+02 1.34E+02 Na 24 3.03E-01 3.03E-01 2.96E-01 2.89E-01 2.09E-01 9.98E-02 3.58E-03 1.07E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr 51 3.49E+03 3.49E+03 3.48E+03 3.48E+03 3.46E+03 3.40E+03 3.15E+03 1.65E+03 3.67E+02 3.86E+01 3.77E-01 4.39E-09 Mn 54 3.94E+01 3.94E+01 3.94E+01 3.94E+01 3.94E+01 3.93E+01 3.90E+01 3.69E+01 3.23E+01 2.64E+01 1.75E+01 3.46E+00 Fe 55 3.92E+02 3.92E+02 3.92E+02 3.92E+02 3.91E+02 3.91E+02 3.90E+02 3.84E+02 3.68E+02 3.46E+02 3.04E+02 1.84E+02 Mn 56 7.26E+02 7.26E+02 6.34E+02 5.55E+02 8.45E+01 1.15E+00 4.52E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co 58 5.86E+02 5.86E+02 5.86E+02 5.86E+02 5.85E+02 5.82E+02 5.66E+02 4.39E+02 2.44E+02 1.01E+02 1.66E+01 1.31E-02 Fe 59 2.89E+01 2.89E+01 2.89E+01 2.89E+01 2.87E+01 2.84E+01 2.71E+01 1.81E+01 7.10E+00 1.75E+00 9.80E-02 1.13E-06 Ni 59 4.91E-01 4.91E-01 4.91E-01 4.91E-01 4.91E-01 4.91E-01 4.91E-01 4.91E-01 4.91E-01 4.91E-01 4.91E-01 4.91E-01 Co 60 3.80E+01 3.80E+01 3.80E+01 3.80E+01 3.80E+01 3.80E+01 3.80E+01 3.76E+01 3.68E+01 3.56E+01 3.33E+01 2.56E+01 Ni 63 8.16E+01 8.16E+01 8.16E+01 8.16E+01 8.16E+01 8.16E+01 8.16E+01 8.15E+01 8.14E+01 8.13E+01 8.10E+01 7.99E+01 Cu 64 1.33E+02 1.33E+02 1.30E+02 1.26E+02 8.61E+01 3.60E+01 7.07E-01 1.15E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ni 65 9.33E+01 9.33E+01 8.13E+01 7.09E+01 1.03E+01 1.26E-01 3.09E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ga 73 9.69E+00 9.69E+00 9.03E+00 8.41E+00 3.10E+00 3.16E-01 1.10E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ge 73m 9.56E+00 9.55E+00 8.90E+00 8.29E+00 3.05E+00 3.12E-01 1.37E-05 2.34E-06 1.39E-06 6.41E-07 1.30E-07 2.38E-10 As 76 6.48E+00 6.48E+00 6.39E+00 6.31E+00 5.24E+00 3.44E+00 5.13E-01 3.56E-08 1.07E-24 0.00E+00 0.00E+00 0.00E+00 Ge 77 2.61E+02 2.61E+02 2.53E+02 2.46E+02 1.60E+02 5.99E+01 7.23E-01 1.72E-17 0.00E+00 0.00E+00 0.00E+00 0.00E+00 As 77 2.71E+02 2.71E+02 2.71E+02 2.70E+02 2.62E+02 2.22E+02 6.78E+01 9.90E-04 6.79E-15 1.22E-31 0.00E+00 0.00E+00 Ge 78 7.19E+02 7.19E+02 5.68E+02 4.49E+02 1.64E+01 8.54E-03 1.43E-17 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 As 78 7.44E+02 7.44E+02 7.23E+02 6.78E+02 8.27E+01 1.24E-01 1.39E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br 82 8.02E+02 8.02E+02 7.96E+02 7.89E+02 6.87E+02 5.02E+02 1.22E+02 5.78E-04 2.99E-16 1.11E-34 0.00E+00 0.00E+00 Br 83 1.44E+04 1.44E+04 1.35E+04 1.21E+04 1.65E+03 1.62E+01 1.51E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr 83m 1.44E+04 1.44E+04 1.43E+04 1.41E+04 4.23E+03 6.20E+01 7.19E-04 5.84E-04 3.60E-04 1.75E-04 3.95E-05 1.11E-07 Kr 85 2.71E+03 2.71E+03 2.71E+03 2.71E+03 2.71E+03 2.71E+03 2.71E+03 2.70E+03 2.67E+03 2.63E+03 2.54E+03 2.24E+03 Kr 85m 3.02E+04 3.02E+04 2.83E+04 2.62E+04 8.86E+03 7.45E+02 1.08E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb 86 5.11E+02 5.11E+02 5.11E+02 5.10E+02 5.05E+02 4.92E+02 4.40E+02 1.67E+02 1.80E+01 6.31E-01 6.47E-04 1.04E-15 Kr 87 5.64E+04 5.64E+04 4.34E+04 3.30E+04 7.28E+02 1.19E-01 1.07E-18 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kr 88 7.47E+04 7.47E+04 6.62E+04 5.86E+04 1.06E+04 2.14E+02 4.99E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

SSES-FSAR Table Rev. 1 FSAR Rev. 70 Page 2 of 8 Table 12.2-9A2 Activity (Curies) per Single Assembly of ATRIUM-11 Fuel Sum of Actinides, Fission Products and Light Elements Decay time Following Burnup to 58 GWd/MTU Nuclide T = 0 1 sec 30 min 1 hr 8 hr 1.0 d 4.0 d 30.0 d 90.0 d 180.0 d 1 yr 3 yr Rb 88 7.66E+04 7.66E+04 7.18E+04 6.48E+04 1.19E+04 2.39E+02 5.57E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr 89 5.08E+01 5.08E+01 5.06E+01 5.03E+01 4.73E+01 4.11E+01 2.17E+01 8.74E-02 2.59E-07 1.32E-15 1.19E-32 0.00E+00 Sr 89 1.04E+05 1.04E+05 1.04E+05 1.04E+05 1.04E+05 1.03E+05 9.89E+04 6.92E+04 3.04E+04 8.84E+03 6.99E+02 3.13E-02 Y 89m 6.39E+01 6.37E+01 6.06E+01 6.03E+01 5.73E+01 5.10E+01 3.12E+01 6.76E+00 2.93E+00 8.52E-01 6.74E-02 3.02E-06 Sr 90 2.21E+04 2.21E+04 2.21E+04 2.21E+04 2.21E+04 2.21E+04 2.21E+04 2.20E+04 2.19E+04 2.18E+04 2.15E+04 2.05E+04 Y 90 2.36E+04 2.36E+04 2.36E+04 2.36E+04 2.35E+04 2.33E+04 2.26E+04 2.20E+04 2.19E+04 2.18E+04 2.15E+04 2.05E+04 Sr 91 1.36E+05 1.36E+05 1.31E+05 1.26E+05 7.64E+04 2.41E+04 1.36E+02 4.23E-18 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y 91 1.41E+05 1.41E+05 1.41E+05 1.41E+05 1.41E+05 1.40E+05 1.35E+05 9.95E+04 4.89E+04 1.68E+04 1.88E+03 3.30E-01 Y 91m 7.98E+04 7.98E+04 7.93E+04 7.81E+04 4.91E+04 1.55E+04 8.72E+01 2.72E-18 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr 92 1.51E+05 1.51E+05 1.33E+05 1.17E+05 1.95E+04 3.26E+02 3.28E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Y 92 1.53E+05 1.53E+05 1.52E+05 1.49E+05 7.12E+04 4.82E+03 4.42E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr 93 6.27E-01 6.27E-01 6.27E-01 6.27E-01 6.27E-01 6.27E-01 6.27E-01 6.27E-01 6.27E-01 6.27E-01 6.27E-01 6.27E-01 Y 93 1.80E+05 1.80E+05 1.76E+05 1.70E+05 1.05E+05 3.55E+04 2.64E+02 9.31E-17 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zr 95 2.30E+05 2.30E+05 2.30E+05 2.30E+05 2.29E+05 2.27E+05 2.20E+05 1.66E+05 8.68E+04 3.28E+04 4.42E+03 1.64E+00 Nb 95 2.31E+05 2.31E+05 2.31E+05 2.31E+05 2.31E+05 2.31E+05 2.31E+05 2.14E+05 1.45E+05 6.44E+04 9.54E+03 3.61E+00 Nb 95m 2.57E+03 2.57E+03 2.57E+03 2.57E+03 2.56E+03 2.55E+03 2.49E+03 1.90E+03 9.93E+02 3.75E+02 5.06E+01 1.87E-02 Nb 96 7.50E+02 7.50E+02 7.39E+02 7.28E+02 5.91E+02 3.68E+02 4.34E+01 3.91E-07 1.07E-25 0.00E+00 0.00E+00 0.00E+00 Zr 97 2.43E+05 2.43E+05 2.38E+05 2.33E+05 1.74E+05 8.98E+04 4.57E+03 2.78E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb 97 2.44E+05 2.44E+05 2.43E+05 2.41E+05 1.87E+05 9.03E+04 4.59E+03 3.00E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb 97m 2.31E+05 2.31E+05 2.26E+05 2.21E+05 1.66E+05 8.55E+04 4.34E+03 2.65E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Mo 99 2.59E+05 2.59E+05 2.57E+05 2.56E+05 2.38E+05 2.01E+05 9.44E+04 1.34E+02 3.61E-05 5.03E-15 2.77E-35 0.00E+00 Tc 99 4.12E+00 4.12E+00 4.12E+00 4.12E+00 4.12E+00 4.12E+00 4.12E+00 4.13E+00 4.13E+00 4.13E+00 4.13E+00 4.13E+00 Tc 99m 2.27E+05 2.27E+05 2.27E+05 2.27E+05 2.21E+05 1.93E+05 9.13E+04 1.30E+02 3.49E-05 4.87E-15 2.68E-35 0.00E+00 Ru103 2.53E+05 2.53E+05 2.53E+05 2.53E+05 2.52E+05 2.49E+05 2.36E+05 1.49E+05 5.17E+04 1.05E+04 4.02E+02 1.01E-03 Rh103m 2.51E+05 2.51E+05 2.50E+05 2.50E+05 2.49E+05 2.46E+05 2.34E+05 1.48E+05 5.11E+04 1.04E+04 3.98E+02 1.00E-03 Ru105 1.91E+05 1.91E+05 1.82E+05 1.68E+05 5.64E+04 4.64E+03 6.10E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rh105 1.73E+05 1.73E+05 1.73E+05 1.73E+05 1.64E+05 1.25E+05 3.07E+04 1.49E-01 8.22E-14 3.36E-32 0.00E+00 0.00E+00 Rh105m 5.41E+04 5.41E+04 5.16E+04 4.78E+04 1.60E+04 1.32E+03 1.73E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

SSES-FSAR Table Rev. 1 FSAR Rev. 70 Page 3 of 8 Table 12.2-9A2 Activity (Curies) per Single Assembly of ATRIUM-11 Fuel Sum of Actinides, Fission Products and Light Elements Decay time Following Burnup to 58 GWd/MTU Nuclide T = 0 1 sec 30 min 1 hr 8 hr 1.0 d 4.0 d 30.0 d 90.0 d 180.0 d 1 yr 3 yr Ru106 1.22E+05 1.22E+05 1.22E+05 1.22E+05 1.22E+05 1.21E+05 1.21E+05 1.15E+05 1.03E+05 8.70E+04 6.16E+04 1.58E+04 Rh106 1.38E+05 1.37E+05 1.22E+05 1.22E+05 1.22E+05 1.21E+05 1.21E+05 1.15E+05 1.03E+05 8.70E+04 6.16E+04 1.58E+04 Rh106m 1.70E+03 1.70E+03 1.45E+03 1.24E+03 1.34E+02 8.34E-01 9.86E-11 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ag109m 6.83E+04 6.83E+04 6.68E+04 6.51E+04 4.57E+04 2.03E+04 5.33E+02 8.04E-02 7.34E-02 6.42E-02 4.86E-02 1.62E-02 Ag110 3.93E+04 3.82E+04 1.19E+01 1.19E+01 1.19E+01 1.18E+01 1.17E+01 1.09E+01 9.25E+00 7.21E+00 4.31E+00 5.69E-01 Ag110m 8.73E+02 8.73E+02 8.73E+02 8.73E+02 8.73E+02 8.71E+02 8.64E+02 8.04E+02 6.80E+02 5.30E+02 3.17E+02 4.18E+01 Pd111 1.18E+04 1.18E+04 4.92E+03 2.04E+03 8.46E+00 1.12E+00 1.29E-04 9.06E-39 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Pd111m 2.95E+01 2.95E+01 2.77E+01 2.60E+01 1.07E+01 1.43E+00 1.64E-04 1.15E-38 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ag111 1.25E+04 1.25E+04 1.25E+04 1.24E+04 1.21E+04 1.14E+04 8.61E+03 7.66E+02 2.88E+00 6.66E-04 2.23E-11 0.00E+00 Ag111m 1.21E+04 1.21E+04 5.13E+03 2.12E+03 1.05E+01 1.39E+00 1.60E-04 1.12E-38 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Pd112 5.28E+03 5.28E+03 5.19E+03 5.11E+03 4.06E+03 2.39E+03 2.23E+02 2.61E-07 6.37E-28 0.00E+00 0.00E+00 0.00E+00 Ag112 5.30E+03 5.30E+03 5.29E+03 5.28E+03 4.61E+03 2.81E+03 2.62E+02 3.06E-07 7.48E-28 0.00E+00 0.00E+00 0.00E+00 In113m 4.46E+02 4.46E+02 4.46E+02 4.46E+02 4.46E+02 4.44E+02 4.36E+02 3.73E+02 2.60E+02 1.51E+02 4.96E+01 6.11E-01 Sn113 4.46E+02 4.46E+02 4.46E+02 4.46E+02 4.45E+02 4.44E+02 4.36E+02 3.72E+02 2.60E+02 1.51E+02 4.95E+01 6.10E-01 Ag113 2.39E+03 2.39E+03 2.26E+03 2.12E+03 8.58E+02 1.09E+02 1.00E-02 1.05E-37 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cd113m 5.30E-02 5.30E-02 5.31E-02 5.32E-02 5.42E-02 5.47E-02 5.48E-02 5.46E-02 5.42E-02 5.35E-02 5.22E-02 4.73E-02 In114 1.36E+02 1.36E+02 7.29E+01 7.29E+01 7.26E+01 7.19E+01 6.89E+01 4.79E+01 2.07E+01 5.87E+00 4.40E-01 1.60E-05 In114m 7.54E+01 7.54E+01 7.53E+01 7.53E+01 7.50E+01 7.43E+01 7.13E+01 4.95E+01 2.14E+01 6.06E+00 4.55E-01 1.66E-05 Cd115 1.80E+03 1.80E+03 1.79E+03 1.78E+03 1.63E+03 1.32E+03 5.21E+02 1.60E-01 1.24E-09 8.54E-22 0.00E+00 0.00E+00 Cd115m 1.13E+02 1.13E+02 1.13E+02 1.13E+02 1.13E+02 1.12E+02 1.07E+02 7.11E+01 2.80E+01 6.90E+00 3.88E-01 4.54E-06 In-115m 1.80E+03 1.80E+03 1.80E+03 1.80E+03 1.73E+03 1.44E+03 5.68E+02 1.82E-01 2.97E-03 7.33E-04 4.12E-05 4.82E-10 Cd117 1.31E+03 1.31E+03 1.15E+03 1.00E+03 1.43E+02 1.66E+00 3.28E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cd117m 2.95E+02 2.95E+02 2.67E+02 2.41E+02 5.68E+01 2.09E+00 7.42E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 In117 9.70E+02 9.70E+02 9.61E+02 9.36E+02 2.97E+02 6.03E+00 9.55E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 In117m 1.21E+03 1.21E+03 1.20E+03 1.16E+03 3.47E+02 6.11E+00 3.09E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sn117m 1.20E+02 1.20E+02 1.20E+02 1.20E+02 1.18E+02 1.15E+02 9.83E+01 2.61E+01 1.23E+00 1.25E-02 1.00E-06 6.97E-23 Sn119m 7.96E+01 7.96E+01 7.96E+01 7.96E+01 7.96E+01 7.94E+01 7.89E+01 7.42E+01 6.44E+01 5.20E+01 3.36E+01 5.97E+00 Sn121 2.42E+03 2.42E+03 2.40E+03 2.36E+03 1.98E+03 1.31E+03 2.13E+02 6.38E+00 6.36E+00 6.33E+00 6.28E+00 6.09E+00

SSES-FSAR Table Rev. 1 FSAR Rev. 70 Page 4 of 8 Table 12.2-9A2 Activity (Curies) per Single Assembly of ATRIUM-11 Fuel Sum of Actinides, Fission Products and Light Elements Decay time Following Burnup to 58 GWd/MTU Nuclide T = 0 1 sec 30 min 1 hr 8 hr 1.0 d 4.0 d 30.0 d 90.0 d 180.0 d 1 yr 3 yr Sn121m 8.23E+00 8.23E+00 8.23E+00 8.22E+00 8.22E+00 8.22E+00 8.22E+00 8.21E+00 8.19E+00 8.16E+00 8.10E+00 7.84E+00 Sb122 4.98E+02 4.98E+02 4.95E+02 4.93E+02 4.57E+02 3.86E+02 1.80E+02 2.41E-01 5.63E-08 6.36E-18 2.28E-38 0.00E+00 Te123m 4.38E+00 4.38E+00 4.38E+00 4.38E+00 4.38E+00 4.36E+00 4.28E+00 3.68E+00 2.60E+00 1.54E+00 5.25E-01 7.53E-03 Sn123 2.65E+02 2.65E+02 2.65E+02 2.65E+02 2.65E+02 2.64E+02 2.60E+02 2.26E+02 1.64E+02 1.01E+02 3.74E+01 7.46E-01 Sn123m 1.60E+03 1.60E+03 9.61E+02 5.72E+02 3.99E-01 2.44E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sb124 2.30E+02 2.30E+02 2.30E+02 2.30E+02 2.30E+02 2.28E+02 2.20E+02 1.63E+02 8.18E+01 2.90E+01 3.45E+00 7.71E-04 Sn125 1.70E+03 1.70E+03 1.70E+03 1.69E+03 1.66E+03 1.58E+03 1.27E+03 1.96E+02 2.63E+00 4.06E-03 6.79E-09 0.00E+00 Sn125m 2.72E+03 2.72E+03 3.08E+02 3.47E+01 1.82E-12 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sb125 2.78E+03 2.78E+03 2.78E+03 2.78E+03 2.78E+03 2.78E+03 2.78E+03 2.74E+03 2.63E+03 2.47E+03 2.17E+03 1.32E+03 Te125m 6.18E+02 6.18E+02 6.18E+02 6.18E+02 6.18E+02 6.19E+02 6.19E+02 6.24E+02 6.21E+02 5.97E+02 5.32E+02 3.22E+02 Sb126 7.12E+01 7.12E+01 7.11E+01 7.10E+01 6.99E+01 6.73E+01 5.69E+01 1.32E+01 4.67E-01 1.42E-02 1.13E-02 1.13E-02 Sb126m 7.30E+01 7.30E+01 2.47E+01 8.39E+00 8.08E-02 8.08E-02 8.08E-02 8.08E-02 8.08E-02 8.08E-02 8.08E-02 8.08E-02 Sn127 8.84E+03 8.84E+03 7.50E+03 6.36E+03 6.31E+02 3.21E+00 1.53E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sb127 1.50E+04 1.50E+04 1.49E+04 1.49E+04 1.43E+04 1.27E+04 7.38E+03 6.84E+01 1.39E-03 1.28E-10 4.38E-25 0.00E+00 Te127 1.33E+04 1.33E+04 1.33E+04 1.33E+04 1.32E+04 1.24E+04 7.76E+03 8.73E+02 5.53E+02 3.12E+02 9.62E+01 9.27E-01 Te127m 9.09E+02 9.09E+02 9.09E+02 9.10E+02 9.12E+02 9.18E+02 9.31E+02 8.26E+02 5.65E+02 3.19E+02 9.82E+01 9.46E-01 Sb128 2.31E+03 2.31E+03 2.25E+03 2.19E+03 1.31E+03 3.82E+02 1.50E+00 2.13E-21 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sb129 4.40E+04 4.40E+04 4.11E+04 3.80E+04 1.26E+04 1.01E+03 1.20E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Te129 4.20E+04 4.20E+04 4.16E+04 4.07E+04 1.89E+04 5.65E+03 4.21E+03 2.46E+03 7.14E+02 1.12E+02 2.46E+00 7.08E-07 Te129m 7.21E+03 7.21E+03 7.21E+03 7.21E+03 7.19E+03 7.10E+03 6.67E+03 3.90E+03 1.13E+03 1.77E+02 3.89E+00 1.12E-06 Xe129m 5.06E+00 5.06E+00 5.06E+00 5.05E+00 4.93E+00 4.68E+00 3.71E+00 4.87E-01 4.50E-03 4.00E-06 2.14E-12 0.00E+00 I130 6.24E+03 6.24E+03 6.10E+03 5.94E+03 4.01E+03 1.64E+03 2.88E+01 1.83E-14 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Te131 1.22E+05 1.22E+05 9.43E+04 6.02E+04 6.54E+03 4.68E+03 1.04E+03 2.34E-03 2.15E-16 5.97E-36 0.00E+00 0.00E+00 Te131m 2.94E+04 2.94E+04 2.91E+04 2.88E+04 2.49E+04 1.79E+04 3.98E+03 8.92E-03 8.18E-16 2.28E-35 0.00E+00 0.00E+00 I131 1.44E+05 1.44E+05 1.44E+05 1.44E+05 1.41E+05 1.35E+05 1.06E+05 1.13E+04 6.35E+01 2.67E-02 3.07E-09 0.00E+00 Xe131m 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.56E+03 1.52E+03 6.06E+02 2.43E+01 1.32E-01 2.62E-06 7.22E-25 Te132 2.02E+05 2.02E+05 2.02E+05 2.01E+05 1.88E+05 1.63E+05 8.52E+04 3.07E+02 7.09E-04 2.48E-12 1.03E-29 0.00E+00 I132 2.08E+05 2.08E+05 2.08E+05 2.07E+05 1.94E+05 1.68E+05 8.78E+04 3.17E+02 7.30E-04 2.56E-12 1.06E-29 0.00E+00

SSES-FSAR Table Rev. 1 FSAR Rev. 70 Page 5 of 8 Table 12.2-9A2 Activity (Curies) per Single Assembly of ATRIUM-11 Fuel Sum of Actinides, Fission Products and Light Elements Decay time Following Burnup to 58 GWd/MTU Nuclide T = 0 1 sec 30 min 1 hr 8 hr 1.0 d 4.0 d 30.0 d 90.0 d 180.0 d 1 yr 3 yr Cs132 5.26E+00 5.26E+00 5.24E+00 5.23E+00 5.07E+00 4.72E+00 3.43E+00 2.12E-01 3.46E-04 2.28E-08 5.81E-17 0.00E+00 Te133m 1.38E+05 1.38E+05 9.50E+04 6.52E+04 3.41E+02 2.07E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I133 2.85E+05 2.85E+05 2.83E+05 2.80E+05 2.25E+05 1.32E+05 1.20E+04 1.11E-05 1.61E-26 0.00E+00 0.00E+00 0.00E+00 Xe133 2.87E+05 2.87E+05 2.87E+05 2.87E+05 2.85E+05 2.76E+05 2.02E+05 6.67E+03 2.40E+00 1.63E-05 3.89E-16 0.00E+00 Xe133m 9.03E+03 9.03E+03 9.02E+03 9.02E+03 8.85E+03 8.10E+03 3.86E+03 1.09E+00 6.16E-09 2.62E-21 0.00E+00 0.00E+00 I134 3.16E+05 3.16E+05 2.75E+05 2.22E+05 1.90E+03 6.92E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs134 5.50E+04 5.50E+04 5.50E+04 5.50E+04 5.50E+04 5.50E+04 5.48E+04 5.35E+04 5.06E+04 4.66E+04 3.93E+04 2.01E+04 CS134m 1.21E+04 1.21E+04 1.08E+04 9.56E+03 1.81E+03 4.01E+01 1.44E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I135 2.74E+05 2.74E+05 2.60E+05 2.47E+05 1.18E+05 2.18E+04 1.10E+01 2.81E-28 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe135 6.08E+04 6.08E+04 6.89E+04 7.59E+04 1.15E+05 6.81E+04 5.00E+02 1.48E-18 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Xe135m 6.38E+04 6.38E+04 4.90E+04 4.35E+04 2.03E+04 3.75E+03 1.88E+00 4.83E-29 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba135m 7.29E+01 7.29E+01 7.20E+01 7.11E+01 6.01E+01 4.08E+01 7.17E+00 2.04E-06 1.61E-21 0.00E+00 0.00E+00 0.00E+00 Cs136 1.21E+04 1.21E+04 1.20E+04 1.20E+04 1.19E+04 1.14E+04 9.77E+03 2.48E+03 1.05E+02 9.20E-01 5.40E-05 1.08E-21 Ba136m 1.34E+03 1.34E+03 1.33E+03 1.33E+03 1.31E+03 1.27E+03 1.08E+03 2.75E+02 1.17E+01 1.02E-01 5.98E-06 1.20E-22 Cs137 3.28E+04 3.28E+04 3.28E+04 3.28E+04 3.28E+04 3.28E+04 3.28E+04 3.27E+04 3.26E+04 3.24E+04 3.20E+04 3.06E+04 Ba137m 3.11E+04 3.11E+04 3.10E+04 3.10E+04 3.10E+04 3.10E+04 3.10E+04 3.10E+04 3.09E+04 3.07E+04 3.03E+04 2.90E+04 Cs138 2.59E+05 2.59E+05 1.93E+05 1.16E+05 2.05E+01 4.59E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba139 2.47E+05 2.47E+05 2.14E+05 1.69E+05 5.08E+03 1.68E+00 3.71E-16 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ba140 2.37E+05 2.37E+05 2.37E+05 2.37E+05 2.33E+05 2.25E+05 1.91E+05 4.65E+04 1.78E+03 1.34E+01 5.75E-04 3.37E-21 La140 2.54E+05 2.54E+05 2.54E+05 2.54E+05 2.52E+05 2.46E+05 2.16E+05 5.35E+04 2.05E+03 1.54E+01 6.62E-04 3.88E-21 La141 2.22E+05 2.22E+05 2.14E+05 2.00E+05 5.85E+04 3.45E+03 1.02E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce141 2.24E+05 2.24E+05 2.24E+05 2.24E+05 2.23E+05 2.20E+05 2.07E+05 1.19E+05 3.30E+04 4.84E+03 9.38E+01 1.63E-05 La142 2.11E+05 2.11E+05 1.86E+05 1.50E+05 6.17E+03 4.15E+00 2.20E-14 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Pr142 1.91E+04 1.91E+04 1.88E+04 1.85E+04 1.44E+04 8.04E+03 5.91E+02 8.86E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ce143 2.02E+05 2.02E+05 2.01E+05 1.99E+05 1.72E+05 1.23E+05 2.71E+04 5.60E-02 4.24E-15 8.84E-35 0.00E+00 0.00E+00 Pr143 1.98E+05 1.98E+05 1.98E+05 1.98E+05 1.98E+05 1.96E+05 1.77E+05 4.77E+04 2.23E+03 2.24E+01 1.77E-03 1.13E-19 Ce144 1.86E+05 1.86E+05 1.86E+05 1.86E+05 1.86E+05 1.86E+05 1.84E+05 1.73E+05 1.50E+05 1.20E+05 7.67E+04 1.30E+04 Pr144 1.88E+05 1.88E+05 1.87E+05 1.86E+05 1.86E+05 1.86E+05 1.84E+05 1.73E+05 1.50E+05 1.20E+05 7.67E+04 1.30E+04

SSES-FSAR Table Rev. 1 FSAR Rev. 70 Page 6 of 8 Table 12.2-9A2 Activity (Curies) per Single Assembly of ATRIUM-11 Fuel Sum of Actinides, Fission Products and Light Elements Decay time Following Burnup to 58 GWd/MTU Nuclide T = 0 1 sec 30 min 1 hr 8 hr 1.0 d 4.0 d 30.0 d 90.0 d 180.0 d 1 yr 3 yr Pr144m 2.62E+03 2.62E+03 1.83E+03 1.78E+03 1.78E+03 1.77E+03 1.76E+03 1.65E+03 1.43E+03 1.15E+03 7.32E+02 1.24E+02 Pr145 1.38E+05 1.38E+05 1.32E+05 1.24E+05 5.53E+04 8.67E+03 2.07E+00 8.42E-32 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nd147 9.04E+04 9.04E+04 9.03E+04 9.02E+04 8.86E+04 8.49E+04 7.03E+04 1.36E+04 3.08E+02 1.05E+00 8.90E-06 8.62E-26 Pm147 3.52E+04 3.52E+04 3.52E+04 3.52E+04 3.52E+04 3.52E+04 3.53E+04 3.53E+04 3.39E+04 3.18E+04 2.78E+04 1.64E+04 Pm148 3.20E+04 3.20E+04 3.19E+04 3.19E+04 3.07E+04 2.82E+04 1.92E+04 7.83E+02 4.46E+01 9.77E+00 4.38E-01 2.08E-06 Pm148m 4.15E+03 4.15E+03 4.15E+03 4.15E+03 4.13E+03 4.09E+03 3.89E+03 2.51E+03 9.17E+02 2.02E+02 9.07E+00 4.32E-05 Nd149 5.58E+04 5.58E+04 4.66E+04 3.82E+04 2.30E+03 3.76E+00 1.08E-12 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Pm149 8.14E+04 8.14E+04 8.12E+04 8.09E+04 7.50E+04 6.09E+04 2.38E+04 6.88E+00 4.69E-08 2.64E-20 0.00E+00 0.00E+00 Pm150 1.17E+03 1.17E+03 1.03E+03 9.03E+02 1.48E+02 2.36E+00 1.93E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Pm151 3.05E+04 3.05E+04 3.04E+04 3.00E+04 2.53E+04 1.71E+04 2.96E+03 7.18E-04 3.91E-19 0.00E+00 0.00E+00 0.00E+00 Sm151 5.77E+01 5.77E+01 5.77E+01 5.77E+01 5.79E+01 5.82E+01 5.87E+01 5.87E+01 5.87E+01 5.86E+01 5.83E+01 5.74E+01 Eu152m 1.85E+01 1.85E+01 1.78E+01 1.72E+01 1.02E+01 3.10E+00 1.46E-02 9.79E-23 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sm153 9.59E+04 9.59E+04 9.52E+04 9.45E+04 8.52E+04 6.71E+04 2.29E+04 2.09E+00 9.97E-10 1.04E-23 0.00E+00 0.00E+00 Gd153 4.66E+01 4.66E+01 4.66E+01 4.66E+01 4.66E+01 4.65E+01 4.61E+01 4.28E+01 3.60E+01 2.78E+01 1.63E+01 1.98E+00 Eu154 1.99E+03 1.99E+03 1.99E+03 1.99E+03 1.99E+03 1.98E+03 1.98E+03 1.97E+03 1.95E+03 1.91E+03 1.83E+03 1.56E+03 Eu155 1.32E+03 1.32E+03 1.32E+03 1.32E+03 1.32E+03 1.32E+03 1.32E+03 1.30E+03 1.27E+03 1.23E+03 1.14E+03 8.52E+02 Sm156 4.36E+03 4.36E+03 4.21E+03 4.06E+03 2.42E+03 7.44E+02 3.68E+00 3.82E-20 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Eu156 7.50E+04 7.50E+04 7.49E+04 7.49E+04 7.39E+04 7.18E+04 6.26E+04 1.91E+04 1.24E+03 2.03E+01 4.39E-03 1.50E-17 Gd159 3.54E+04 3.54E+04 3.47E+04 3.41E+04 2.62E+04 1.44E+04 9.66E+02 6.60E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tb160 1.07E+04 1.07E+04 1.07E+04 1.07E+04 1.07E+04 1.06E+04 1.03E+04 8.04E+03 4.52E+03 1.91E+03 3.24E+02 2.96E-01 Tb161 8.17E+03 8.17E+03 8.16E+03 8.14E+03 7.91E+03 7.40E+03 5.47E+03 4.03E+02 9.76E-01 1.17E-04 1.01E-12 0.00E+00 Dy165 3.37E+03 3.37E+03 2.92E+03 2.52E+03 3.15E+02 2.72E+00 1.41E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Dy166 1.43E+01 1.43E+01 1.42E+01 1.41E+01 1.33E+01 1.16E+01 6.31E+00 3.15E-02 1.53E-07 1.65E-15 6.88E-32 0.00E+00 Ho166 8.83E+02 8.83E+02 8.72E+02 8.61E+02 7.20E+02 4.81E+02 8.14E+01 4.70E-02 2.28E-07 2.46E-15 1.02E-31 0.00E+00 Hf175 2.02E+00 2.02E+00 2.02E+00 2.02E+00 2.01E+00 2.00E+00 1.94E+00 1.50E+00 8.27E-01 3.39E-01 5.43E-02 3.94E-05 Lu176m 2.50E+00 2.50E+00 2.27E+00 2.07E+00 5.44E-01 2.57E-02 2.80E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Lu177 1.22E+00 1.22E+00 1.22E+00 1.21E+00 1.18E+00 1.10E+00 8.03E-01 5.36E-02 2.84E-04 1.23E-04 5.53E-05 2.36E-06 Hf180m 1.26E+01 1.26E+01 1.18E+01 1.11E+01 4.60E+00 6.12E-01 7.02E-05 4.93E-39 0.00E+00 0.00E+00 0.00E+00 0.00E+00

SSES-FSAR Table Rev. 1 FSAR Rev. 70 Page 7 of 8 Table 12.2-9A2 Activity (Curies) per Single Assembly of ATRIUM-11 Fuel Sum of Actinides, Fission Products and Light Elements Decay time Following Burnup to 58 GWd/MTU Nuclide T = 0 1 sec 30 min 1 hr 8 hr 1.0 d 4.0 d 30.0 d 90.0 d 180.0 d 1 yr 3 yr Hf181 2.86E+02 2.86E+02 2.86E+02 2.86E+02 2.84E+02 2.81E+02 2.68E+02 1.75E+02 6.56E+01 1.51E+01 7.31E-01 4.79E-06 W181 3.43E-04 3.43E-04 3.43E-04 3.43E-04 3.43E-04 3.41E-04 3.35E-04 2.89E-04 2.05E-04 1.23E-04 4.26E-05 6.54E-07 Ta182 8.84E+00 8.84E+00 8.83E+00 8.83E+00 8.82E+00 8.78E+00 8.62E+00 7.37E+00 5.13E+00 2.98E+00 9.74E-01 1.18E-02 Ta183 1.23E+02 1.23E+02 1.23E+02 1.23E+02 1.18E+02 1.08E+02 7.17E+01 2.09E+00 6.02E-04 2.93E-09 3.52E-20 0.00E+00 W183m 6.66E+00 6.62E+00 6.28E+00 6.26E+00 6.02E+00 5.50E+00 3.66E+00 1.07E-01 3.07E-05 1.49E-10 1.80E-21 0.00E+00 W185 2.24E-01 2.24E-01 2.24E-01 2.24E-01 2.23E-01 2.22E-01 2.16E-01 1.70E-01 9.75E-02 4.25E-02 7.70E-03 9.13E-06 Re186 8.73E-02 8.73E-02 8.70E-02 8.66E-02 8.20E-02 7.25E-02 4.14E-02 3.25E-04 4.81E-09 2.97E-10 2.97E-10 2.97E-10 W187 1.31E-03 1.31E-03 1.29E-03 1.27E-03 1.04E-03 6.56E-04 8.20E-05 1.22E-12 1.06E-30 0.00E+00 0.00E+00 0.00E+00 W188 1.93E-06 1.93E-06 1.93E-06 1.93E-06 1.92E-06 1.91E-06 1.85E-06 1.43E-06 7.89E-07 3.23E-07 5.14E-08 3.64E-11 Re188 2.15E-04 2.15E-04 2.11E-04 2.07E-04 1.56E-04 8.22E-05 6.14E-06 1.45E-06 7.97E-07 3.26E-07 5.19E-08 3.68E-11 Os191 1.10E-07 1.10E-07 1.10E-07 1.10E-07 1.09E-07 1.07E-07 9.46E-08 2.94E-08 1.97E-09 3.43E-11 8.30E-15 4.46E-29 Os191m 8.96E-08 8.96E-08 8.73E-08 8.50E-08 5.87E-08 2.52E-08 5.58E-10 2.55E-24 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ir192 1.53E-08 1.53E-08 1.53E-08 1.53E-08 1.53E-08 1.52E-08 1.48E-08 1.16E-08 6.58E-09 2.83E-09 4.98E-10 5.25E-13 Np236m 1.93E+00 1.93E+00 1.90E+00 1.87E+00 1.51E+00 9.22E-01 1.00E-01 4.50E-10 2.44E-29 0.00E+00 0.00E+00 0.00E+00 U237 1.45E+05 1.45E+05 1.44E+05 1.44E+05 1.40E+05 1.31E+05 9.60E+04 6.65E+03 1.47E+01 6.49E-01 6.32E-01 5.74E-01 Pu237 2.10E-01 2.10E-01 2.10E-01 2.10E-01 2.09E-01 2.07E-01 1.97E-01 1.33E-01 5.35E-02 1.37E-02 8.23E-04 1.26E-08 Np238 9.48E+04 9.48E+04 9.41E+04 9.35E+04 8.50E+04 6.83E+04 2.56E+04 5.14E+00 6.72E-03 6.71E-03 6.70E-03 6.63E-03 Pu238 1.24E+03 1.24E+03 1.24E+03 1.24E+03 1.24E+03 1.24E+03 1.25E+03 1.26E+03 1.27E+03 1.29E+03 1.31E+03 1.30E+03 Np239 3.20E+06 3.20E+06 3.19E+06 3.18E+06 2.92E+06 2.40E+06 9.93E+05 4.83E+02 1.01E+01 1.01E+01 1.01E+01 1.01E+01 Pu239 5.07E+01 5.07E+01 5.07E+01 5.07E+01 5.08E+01 5.09E+01 5.13E+01 5.16E+01 5.16E+01 5.16E+01 5.16E+01 5.16E+01 Np240 2.22E+03 2.22E+03 1.59E+03 1.13E+03 1.03E+01 2.21E-04 2.44E-10 2.44E-10 2.44E-10 2.44E-10 2.44E-10 2.44E-10 Pu240 1.20E+02 1.20E+02 1.20E+02 1.20E+02 1.20E+02 1.20E+02 1.20E+02 1.20E+02 1.20E+02 1.20E+02 1.20E+02 1.21E+02 Pu241 2.71E+04 2.71E+04 2.71E+04 2.71E+04 2.71E+04 2.71E+04 2.70E+04 2.69E+04 2.67E+04 2.64E+04 2.58E+04 2.34E+04 Am241 3.32E+01 3.32E+01 3.32E+01 3.32E+01 3.33E+01 3.33E+01 3.37E+01 3.68E+01 4.38E+01 5.43E+01 7.54E+01 1.54E+02 Am242m 1.47E+00 1.47E+00 1.47E+00 1.47E+00 1.47E+00 1.47E+00 1.47E+00 1.47E+00 1.46E+00 1.46E+00 1.46E+00 1.44E+00 Am242 2.34E+04 2.34E+04 2.29E+04 2.24E+04 1.65E+04 8.28E+03 3.69E+02 1.46E+00 1.46E+00 1.46E+00 1.45E+00 1.44E+00 Cm242 1.68E+04 1.68E+04 1.68E+04 1.68E+04 1.68E+04 1.68E+04 1.66E+04 1.49E+04 1.15E+04 7.87E+03 3.58E+03 1.62E+02 Pu243 1.16E+05 1.16E+05 1.08E+05 1.00E+05 3.78E+04 4.03E+03 1.71E-01 6.67E-07 6.67E-07 6.67E-07 6.67E-07 6.67E-07

SSES-FSAR Table Rev. 1 FSAR Rev. 70 Page 8 of 8 Table 12.2-9A2 Activity (Curies) per Single Assembly of ATRIUM-11 Fuel Sum of Actinides, Fission Products and Light Elements Decay time Following Burnup to 58 GWd/MTU Nuclide T = 0 1 sec 30 min 1 hr 8 hr 1.0 d 4.0 d 30.0 d 90.0 d 180.0 d 1 yr 3 yr Am243 1.01E+01 1.01E+01 1.01E+01 1.01E+01 1.01E+01 1.01E+01 1.01E+01 1.01E+01 1.01E+01 1.01E+01 1.01E+01 1.01E+01 Cm243 9.47E+00 9.47E+00 9.47E+00 9.47E+00 9.47E+00 9.47E+00 9.47E+00 9.45E+00 9.42E+00 9.36E+00 9.25E+00 8.82E+00 Am244 3.74E+03 3.74E+03 3.61E+03 3.49E+03 2.16E+03 7.20E+02 5.15E+00 2.19E-08 2.17E-08 2.13E-08 2.05E-08 1.75E-08 Cm244 2.29E+03 2.29E+03 2.29E+03 2.29E+03 2.29E+03 2.29E+03 2.29E+03 2.28E+03 2.27E+03 2.25E+03 2.20E+03 2.04E+03

SSES-FSAR PF.SIDUAJ. HEAT REPIIOVAL SYSTf.11 SHIELDING SOURCE 'IERNS<& ><z ><~)

1sotope< 3 >

Activity Ci/cc Isotope Activity Ci/cc F-18 B.B-10<*>

Tc-99s 1, 8-7 Na-24 1.7-9 Te-132 lf.7-8 cr-51

5. 0-10 Cs-134

,.6-10 f'ln-56 1.7-8 Cs-136 1.1-10 Co-58

5. 0-9 cs-137

2. 4-10 co-60 5.0-10 Cs-13A

,.,-9 f"lo-99 2.1-8 Ba-139

2. 2-8 W-181 2.7-9 Ba-140

8. q-9 Br-83 4.?-9 Np-239

2. 3-7 Bt-P~

,.4-10 La-142

3. 7-9 J-1.Ji

1. 3-8 La-1'11

., *,_ 9 I-132 fi.q-A La-140 6.0-10 I-133 7.8-8 y-q2 3.5-R 1-134 1.0-8 Y-91m 3.1-8

!-135 A.6-8 Xe-135 2.1-8 sr-Rq

• 3.1-9 xe-135111 1.4-8 Sr-90

2. 3-10 Xe-133

1. 8-9 Sr-q1 5.2-8 Xe-133RJ.

1. 2-10 Sr-92 q.0-8 ir-AJm

6. 0-9 Ba-137m

2. 3-10

< 1)

Based on RHR systPm st art of cool in Q 4 hr a ft er sh n+.d own

<z>

Isotopes with concentrations below 10-10 Ci/cc are not listed

< 3 > IsotopP sources ar~ the coo]ant fissicr prcducts and coolan* and noncool~nt ~ctivation products fro1

'r a bl (' 1 1

• 1-1 th r o u q h 11. 1 - S d e ca ye d q hr

• A.8-10 = 8.8x1Q-t0

<5 >

No cr~dit is taken for vessel depressurization Rev. 35, 07/84

SSES-FSAR Table Rev. 55 FSAR Rev. 64 Page 1 of 1 TABLE 12.2-11 STEAM N-16 SHIELDING SOURCE TERMS FOR TURBINE AND REACTOR BUILDING EQUIPMENT(1)(2)

Equipment Decay Time(2)

(Seconds)

N-16(1)

Ci/gm Steam Density gm/cc Reactor Pressure Vessel Nozzle 0

250 3.51E-02(3) 24 Main Steam Line 0

250 3.51E-02 Main Steam Stop Valves 1.87 227.3 3.51E-02 High Pressure Turbine Inlet 2.30 218.0 3.51E-02 High Pressure Turbine Outlet 2.41 215.6 8.67E-03 Moisture Separator Inlet 2.41 215.6 8.67E-03 Moisture Separator Outlet 3.11 201.4 7.22E-03 Cross Around Piping 3.11 201.4 7.22E-03 Combined Intermediate Valve 3.11 201.4 7.22E-03 Low Pressure Turbine Inlet 3.11 201.4 7.22E-03 Low Pressure Turbine Outlet 3.36 196.6 9.28E-05 Steam to Reactor Feedwater Turbine 4 Turbine 10 0.37 5.24 250 163.7 3.51E-02 7.30E-03 Reactor Feedwater Turbine Exhaust 5.24 163.7 1.07E-04 Feedwater Heaters E-103 E-104 E-105 3.04 3.15 2.42 202.9 200.6 215.4 2.75E-03 4.71E-03 1.11E-02 Steam Seal Evaporator (Inlet Steam) 5.51 159.5 2.58E-03 RCIC Turbine (Inlet Steam) 1.0 247.2 3.51E-02 HPCI Turbine (Inlet Steam) 1.0 247.2 3.51E-02 Notes:

1.

Values presented are based on plant operation with hydrogen water chemistry.

2.

Decay time is based on a conservative estimate of the transit time at a Main Steam flow rate of 1.65E+07 lbs/hr.

3.

3.51E-02 = 3.51 X 10-2

SSES-FSAR TABLE 12.2-12 FUEL POOL SYSTEM SHIELDING SOURCE TERMS<1>(2' Activity Activity Activity Isotope

(µCi(cc)

Isotope

(µCi/cc)

Isotope

(µCi/cc)

Na-24 8.60E-Q6l,)J Ba-139 6.88E-04 Nd-147 6.02E-08 P-32 8.60E-08 Zn-69m 1.29E-07 W-187 1.29E-05 Cr-51 2.15E-06 Br-83 6.45E-05 Np-239 1.03E-03 Mn-54 1.72E-07 Sr-89 1.33E-05 Br-85 7.31 E-05 Mn-56 2.15E-04 Sr-92 4.73E-04 Sr-91 2.97E-04 Fe-59 3.44E-07 Ru-103 8.17E--08 Zr-95 1.72E-07 Co-58 2.15E-05 Ru-106 1.12E-08 Nb-95 1.81E-07 Co-60 2.15E-06 Ag-110m 2.58E-07 Zr-97 1.38E-07 Ni-65 1 :29E-06 Te-129m 1.72E-07 Mo-99 9.46E-05 Zn-65 8.60E-09 Te-132 2.11 E-04 Tc-99m 1.20E-03 Br-84 1.16E-04 1-132 5.16E-04 1-133 3.83E-04 Sr-90 9.89E-07 1-131 5.59E-05 1-135 5.59E-04 Tc-101 6.02E-04 Cs-137 1.03E-06 Ba-141 7.31E-04 1-134 1.03E-03 Ba-140 3.87E-05 Ce-141 1.68E-07 Cs-134 6.BBE-07 Ba-142 7.31 E-04 Ce-144

• 1.S0E-07 Cs-136 4.73E-07 Ce-143 1.50E-07 Cs-138 8.17E-04 Pr-143 1.63E-07 Notes:

(1)

Initial isotopic sources are the coolant halogen, fission product, and non-coolant activation products (Tables 11.1-2, 11.2-3, and 11.2-5). normalized to a total coolant activity of 1.00E-02 µCi/cc.

(2)

No credit is taken for RWCU System operation after shutdown prior to head removal.

(3) 8.60E-06 = 8.60 X 1 o-s Rev. 53, 04/99 Page 1 of 1

SSES-FSAR TABLE 12.2-13 FUEL POOL FILTER DEMINERALIZER SHIELDING SOURCE TERMs<1>(2)(3H4>

Activity Activity Activity Isotope (Curies)

Isotope (Curies)

Isotope (Curies)

Na-24 2.57E-02l::>J Sr-92 2.55E-01*

w.1a7 6.10E-02 Cr-51 2.38E-01 Y-92 2.55E-01 Np-239 1.15E+01 Mn-54 3.91E-02 Ru-103 1.11 E-02 Sr-91 5.59E-01 Mn-56 1.10E-01 Rh-103m 1.11 E-02 Y-91m 3.21 E-01 Fe-59 4.98E-02 Ag-110m 5.74E-02 Y-91 3.24E-01 Co-58 3.74E+00 Te-129m 2.15E-02 Zr-95 2.89E-02 Co-60 5.26E-01 Te-129 1.35E-02 Nb-95 3.83E-02 Br-84 1.22E-02 Te-132.

3.28E+00 Mo.99 1.24E+00 Sr-90 2.45E-01 1-132 3.51E+00 Tc-99m 2.53E+00 Tc-101 2.83E-02 1-131 2.14E+00 t-133 1.58E+00 1-134 1.79E-01 Cs-137 2.55E-01 1-135 7.34E-01 Cs-134 1.65E-01 Ba-137m 2.41E-01 Ba-141 4.42E-02 Cs-136 2.90E-02 Ba-140 2.31E+00 La-141 4.42E-02 Cs-138 8.7DE-02 La-140 2.3.1E+00 Ce-141 5.55E-02 Ba-139 1.89E-01 Ba-142 2.59E-02 Ce-144 3.38E-02 Br-83 3.06E-02 La-142 2.59E-02 Pr-144 3.38E-02 Sr-89 2.04E+00 Pr-143 1.12E-02 SSES-FSAR TABLE 12.2 continued Notes:

(1)

Based on processing reactor water diluted to a total isotopic inventory of 1.00E-02

µCi/cc for 73 days (as given in Table 12.2-12) and processing of reactor water diluted to a total isotopic inventory of 1. 00E-04 µCi/cc for 292 days.

(2)

Average flow rate = 600 gpm.

(3)

DF = 10,000 (99.99 percent removal) for buildup on filter demineralizer.

(4)

Isotopes with activity concentrations less than 10*2 µCi/cc are not shown.

(5) 2.57E-02 = 2.57 X 10-2.

Rev. 53, 04/99 Page 1 of 1

SSES-FSAR TABLE 12.2-14 FUEL POOL WATER CLEANUP BACKWASH RECEIVING TANK SHIELDING SOURCE TERMs<1i<2H3l<4H5>

• Activity Activity Activity Isotope (Curies)

Isotope (Curies)

Isotope (Curies)

Na-24 2.57E-02101 Sr-92 2.55E-01 W-187 6.10E-02 Cr-51 2.38E-01 Y-92 2.55E-01 Np-239 1.15E+01 Mn-54 3.91E-02 Ru-103 1.11 E-02 Sr-91 5.59E-01 Mn-56 1.10E-01 Rh-103m 1.11E-02 Y-91m 3.21E-01 Fe-59 4.98E-02 Ag-110m 5.74E-02 Y-91 3.24E-01 Co-58 3.74E+OO Te-129m

• 2.15E-02 Zr-95 2.89E-02 Co-60 5.26E".01 Te-129 1.35E-02 Nb-95 3.83E-02 Br-84 1.22E-02 Te-132 3.28E+00 Mo-99 1.24E+00 Sr-90 2.45E-01 1-132 3.51E+00 Tc-99m 2.53E+00 Tc-101 2.83E-02 1-131 2.14E+00 1-133 1.58E+00 1-134 1.79E-01 Cs-137 2.55E-01 1-135 7.34E-01 Cs-134 1.65E-01 Ba-137m 2.41E-01 Ba-141 4.42E-02 Cs-136 2.90E-02 Ba-140 2.31E+00 La-141 4.42E-02 Cs-138 8.70E-02 La-140 2.31E+00 Ce-141 5.55E-02 Ba-139 1.89E-01 Ba-142 2.59E-02 Ce-144 3.38E-02 Br-83 3.0SE-02 La-142 2.59E-02 Pr-144 3.38E-02.

Sr-89 2.04E+00 Pr-143 1.12E-02 Notes:

(1)

Based on one fuel pool demineralizer backwash (common or outage filter, not non-outage).

(2)

Backwash volume is 1450 gallons.

(3)

A transit time of zero seconds between the filter and tank is assumed.

(4)

Initial backwash activity as given in Table 12.2-13.

(5)

Isotopes with activity concentrations less than 10-2 µCi/cc are not shown.

(6) 2.57E-02 = 2.57 X 10-2.

Rev. 53, 04/99 Page 1 of 1

SSES-FSAR Table 55 FSAR Rev. 64 Page 1 of 1 TABLE 12.2-15 CONDENSATE SHIELDING SOURCE TERMS(1)(2)(4)

Isotope Ci/cc Isotope Ci/cc Isotope Ci/cc Br-83 4.75E-04(3)

Ba-139 1.72E-04 Kr-83m 3.74E-06 Br-84 1.14E-03 Ba-140 9.34E-06 La-144 1.44E-06 Br-85 7.35E-04 Ba-141 3.32E-04 Cs-141 2.72E-04 I-131 3.38E-04 Ba-142 2.14E-04 Cs-140 2.17E-03 I-132 3.81E-03 Np-289 2.40E-04 Cs-139 8.01E-04 I-133 2.34E-03 Na-24 2.00E-06 Rb-90m 1.76E-04 I-134 9.34E-03 Cr-51 5.00E-07 Rb-88 3.30E-05 I-135 3.63E-03 Mn-56 4.96E-05 Sr-94 9.91E-06 Sr-89 3.10E-06 Co-58 5.00E-06 Y-94 1.31E-06 Sr-90 2.30E-07 Co-60 5.00E-07 Sr-95 1.05E-06 Sr-91 8.10E-05 Ni-65 2.97E-07 Y-95 1.20E-06 Sr-92 1.39E-04 W-187 3.00E-06 Sr-93 1.23E-04 Mo-99 2.20E-05 La-142 3.41E-06 Y-93 2.88E-07 Tc-99m 2.79E-04 La-141 1.77E-06 Y-93m 4.80E-05 Tc-101 1.27E-04 Y-92 9.04E-07 Rb-91 2.17E-03 Te-132 4.90E-05 Y-91m 1.20E-06 Rb-90 1.74E-03 Cs-134 1.60E-07 Xe-135 5.60E-06 Rb-89 2.51E-04 Cs-136 1.10E-07 Xe-135m 3.41E-05 N-13 6.09E-03 Cs-137 2.40E-07 Xe-133 3.20E-07 N-16 4.29E-04 Cs-138 2.68E-04 Kr-85m 1.38E-06 Notes:

(1)

Basis for condensate isotopic sources:

a.

Daughter products formed from decay of noble gases in transit through the turbine and main condenser.

b.

Coolant and noncoolant particulate activation and fission product carryover fraction of 1X10-3 per unit weight into steam.

c.

Reaction water fission product halogen carryover fraction of 8X10-2 per unit weight into steam.

(2)

Isotopes with activity concentrations less than 10-7 Ci/cc are not shown.

(3) 4.75E-04 = 4.75 X 10-4 (4)

Values shown are conservatively based on 2 minutes holdup. Minimum retention time in the Hotwell is estimated at 3 minutes.

SSES-FSAR TABLE 12.2-16 CONDENSATE DEMINERALIZER SHIELDING SOURCE TERMS(1H2l Isotope Curies Isotope Curies Isotope Curies Co-58 1.34E+oo<3)

Sr-92 5.93E-01 Ba-137m 7.94E+00 Co-60 1.49E+OO Y-92 5.99E-01 Cs-138 2.24E-01 Br-83 1.78E+00 Nb-95 1.52E-01 Cs-139 1.91 E-01 Br-84 9.41 E-01 Mo-99 2.28E+00 Ba-139 5.70E-01 Rb-89 1.00E-01 Tc-99m 4.66E+00 Ba-140 4.58E+00 Sr-89 6.01E+00 1-131 1.03E+02 La-140 4.58E+00 Rb-90 1.09E-01 Te-132 6.03E+00 Ba-141 3.44E+00 Sr-90 8.04E+00 f-132 2.34E+01 La-141 3.77E+00 Sr-91

,1.34E+02 1-133 7.56E+01 Ce-141 3.82E+00 Y~91rn 7.72E+01 1-134 1.28E+01 Ce-144 3.63E-01 Y-91 1.35E+02 Cs-134 3.28E+00 Pr-144 3.63E-01

• Cs-137 8.39E+00 1-135 3.77E+01 Np-239 2.13E+01 Notes:

(1)

Basis for condensate demineralizer isotopic sources (See Table 12.2-15).

a.

Daughter products formed from 5 second decay of noble gases in transit through the turbine and main condenser.

b.

Coolant and noncoolant particulate activation and fission product carryover fraction of 1X10-3 per unit weight into steam.

C.

Reactor water fission product halogen carryover fraction of sx10*2 per unit weight into steam.

d.

Accumulation period 4 years 1 removal efficiency = 99.99%.

e.

Flow rate 4,800 gpm for each demineralizer.

f.

CFS removal efficiency= 90% {noncoolant activation products only).

(2)

Isotopes with activity less than 1 ff 1 Ci are not shown.

(3) 1.34E+oo = 1.34 x 1 o... 0 Rev. 54, 10/99 Page 1 of 1

SSES-FSAR Table Rev. 55 FSAR Rev. 64 Page 1 of 1 TABLE 12.2-17 OFFGAS LINE FROM SJAE TO RECOMBINER SHIELDING SOURCE TERMS (1)(3)

Isotope Curies Isotope Curies Isotope Curies Xe-133 3.49E-03(2)

Ba-139 1.14E-02 Sr-91 1.00E-02 Xe-135m 1.13E-02 Cs-138 3.91E-03 Y-91 1.00E-02 Xe-135 9.10E-03 Cs-137 3.90E-03 Y-91m 5.93E-03 Xe-137 6.26E-02 Kr-83m 1.44E-03 Rb-90 1.12E-02 Xe-138 3.78E-02 Kr-85m 2.58E-03 Sr-90 7.01E-03 Xe-139 1.10E-01 Kr-87 8.33E-03 Y-90 7.01E-03 Xe-140 1.00E-01 Kr-88 8.34E-03 Rb-89 5.62E-03 Xe-141 1.94E-02 Kr-89 5.41E-02 Sr-89 5.60E-03 Xe-142 4.82E-03 Kr-90 1.07E-01 N-13 2.11E-02 Cs-142 1.00E-03 Kr-91 9.70E-02 N-16 7.79E+01 Cs-141 2.23E-03 Kr-92 4.79E-02 N-17 2.85E-02 Ba-141 2.02E-03 Kr-93 9.39E-03 O-19 5.27E-01 La-141 2.01E-03 Kr-94 1.39E-03 F-18 3.03E-03 Ce-141 2.01E-03 Rb-93 1.41E-03 Cs-140 1.08E-02 Rb-92 7.30E-03 Ba-140 1.04E-02 Sr-92 4.98E-03 La-140 1.04E-02 Y-92 4.98E-03 Cs-139 1.14E-02 Rb-91 1.04E-02 Notes:

(1)

Bases:

a.

100,000 Ci/sec noble gases (after 30 min. decay).

b.

Decay time from Reactor Nozzle to Preheater Inlet, 5.23 seconds.

c.

Main Steam flow 1.65E+07 lbs/ hr.

d.

All particulates generated plateout on pipe surfaces.

e.

Normal water chemistry source terms for N-13, N-16, and N-17 are increased by a factor of five due to hydrogen water chemistry operation.

(2) 3.49E-03 = 3.49 X 10-3 (3)

Isotopes with activity less than 10-3 Ci are not shown.

SSES-FSAR Table Rev. 55 FSAR Rev. 64 Page 1 of 1 TABLE 12.2-18 OFF-GAS RECOMBINER SHIELDING SOURCE TERMS(1)(2)

Isotope Curies Isotope Curies Isotope Curies Xe-133 3.44E-03(3)

Cs-139 2.30E-01 Rb-92 8.28E-02 Xe-135m 1.12E-02 Ba-139 2.30E-01 Sr-92 8.59E-02 Xe-135 8.97E-03 Cs-138 7.98E-02 Y-92 8.59E-02 Xe-137 6.15E-02 Cs-137 7.96E-02 Rb-91 1.94E-01 Xe-138 3.72E-02 Kr-83m 1.42E-03 Sr-91 1.95E-01 Xe-139 1.07E-01 Kr-85m 2.54E-03 Y-91 1.95E-01 Xe-140 9.48E-02 Kr-87 8.21E-03 Y-91m 1.15E-01 Xe-141 1.32E-02 Kr-88 8.22E-03 Rb-90 2.22E-01 Xe-142 3.14E-03 Kr-89 5.32E-02 Sr-90 1.41E-01 Cs-142 6.85E-03 Kr-90 1.03E-01 Y-90 1.41E-01 Ba-142 7.46E-03 Kr-91 8.93E-02 Rb-89 1.14E-01 La-142 7.46E-03 Kr-92 3.81E-02 Sr-89 1.14E-01 Cs-141 3.07E-02 Kr-93 6.74E-03 Rb-88 1.76E-02 Ba-141

3. 09E-02 Rb-94 1.97E-03 N-13 2.08E-02 La-141 3.09E-02 Sr-94 2.11E-03 N-16 7.03E+01 Ce-141 3.09E-02 Y-94 2.11E-03 N-17 2.39E-02 Ba-140 2.05E-01 Rb-93 1.51E-02 O-19 5.07E-01 Cs-140 2.05E-01 Sr-93 1.56E-02 F-18 2.99E-03 La-140 2.05E-01 Y-93 1.56E-02 NOTES:

(1)

Bases a) 100,000 Ci/sec noble gases (after 30 minute decay).

b)

Decay time from Reactor Nozzle to entrance of recombiner, 6.22 seconds.

c)

Particulate daughter products accumulate for 40 years in Recombiner.

d)

Nitrogen partition factors: 80 percent noncondensible gases, 20 percent to main condenser hotwell.

e)

Main steam flow 1.65E+07 lbs/hr.

f)

Normal water chemistry source terms for N-13, N-16, and N-17 are increased by a factor of five due to hydrogen water chemistry operation.

(2)

Isotopes with activity less then 10-3 Ci are not shown.

(3) 3.44E-03 = 3.44 X 10-3

SSES-FSAR Table Rev. 55 FSAR Rev. 64 Page 1 of 1 TABLE 12.2-19 OFF-GAS LINE FROM RECOMBINER TO CHARCOAL SYSTEM SHIELDING SOURCE TERMS(1),(2)

Isotope Curies Isotope Curies Isotope Curies Xe-133m 1.32E-02(3)

Cs-138 4.48E-01 Y-91 4.45E-02 Xe-133 3.79E-01 Cs-137 3.24E-01 Y-91m 2.65E-02 Xe-135m 1.16E+00 Kr-83m 1.55E-01 Rb-90 7.20E-01 Xe-135 9.90E-01 Kr-85m 2.79E-01 Sr-90 1.90E-01 Xe-137 5.34E+00 Kr-87 8.95E-01 Y-90 1.90E-01 Xe-138 3.88E+00 Kr-88 9.01E-01 Rb-89 5.75E-01 Xe-139 3.96E+00 Kr-89 4.39E+00 Sr-89 4.42E-01 Xe-140 1.07E+00 Kr-90 2.9 E+00 Rb-88 1.15E-01 Cs-140 4.27E-01 Kr-91 4.31E-01 N-13 2.08E+00 Ba-140 1.09E-01 Kr-92 1.20E-02 N-16 1.80E+02 La-140 1.09E-01 Rb-92 1.07E-02 N-17 1.76E-02 Cs-139 5.93E-01 Rb-91 1.67E-01 F-18 3.27E-01 Ba-139 4.02E-01 Sr-91 4.46E-02 NOTES:

(1)

Bases a) 100,000 Ci/sec noble gases (after 30 minute decay).

b)

Main steam flow 1.65E+07 lbs/hr.

c)

Decay time from Reactor Nozzle to offgas line entrance, 45.5 seconds.

d)

Normal water chemistry source terms for N-13, N-16, and N-17 are increased by a factor of five due to hydrogen water chemistry operation.

e)

Nitrogen partition factors: 80 percent for non-condensible gases; 20 percent to main condenser hotwell.

(2)

Isotopes with activity less then 10-2 Ci are not shown.

(3) 1.32E-02 = 1.32 X 10-2

SSES-FSAR Table Rev. 55 FSAR Rev. 64 Page 1 of 1 TABLE 12.2-21 OFFGAS AMBIENT CHARCOAL FREON CHILLER SHIELDING SOURCE TERMS (1) (3)

Isotope Curies Isotope Curies Kr-87 1.62E-01(2)

Rb-89 3.81E-01 Kr-88 1.66E-01 Sr-89 3.81E-01 Kr-89 4.07E-01 Rb-88 1.54E-01 Xe-135m 1.87E-01 N-13 3.11E-01 Xe-135 1.84E-01 Xe-137 5.64E-01 Xe-138 6.37E-01 Cs-138 5.94E-01 Cs-137 3.18E-01 NOTES:

(1)

Bases:

a.

100,000 Ci/sec noble gas release rate after 30 min. decay.

b.

Decay time from Reactor Nozzle to inlet of Freon Chiller, 472 seconds.

c.

Particulate daughter products accumulate for 40 years in equipment.

d.

Nitrogen partition factors: 80 percent noncondensible gases, 20 percent to main condenser hotwell.

e.

Main Steam flow 1.65E+07 lbs /hr.

f.

Normal water chemistry source terms for N-13, N-16, and N-17 are increased by a factor of five due to hydrogen water chemistry operation.

(2) 1.62E-01 = 1.62 X 10-1 (3)

Isotopes with activities less than10-1 Ci are not shown.

SSES-FSAR Table Rev. 55 FSAR Rev. 64 Page 1 of 1 TABLE 12.2-22 OFFGAS CHARCOAL GUARD BED SHIELDING SOURCE TERMS (1) (3)

Isotope Curies Isotope Curies Kr-87 1.13E-01(2)

Rb-89 3.64E-01 Kr-88 1.15E-01 Sr-89 3.64E-01 Kr-89 2.77E-01 Rb-88 1.51E-01 Xe-135m 1.30E-01 N-13 2.15E-01 Xe-135 1.28E-01 Xe-137 3.85E-01 Xe-138 4.42E-01 Cs-138 5.78E-01 Cs-137 3.05E-01 NOTES:

(1)

Bases:

a.

100,000 Ci/sec noble gas release rate after 30 min. decay.

b.

Decay time from Reactor Nozzle to Charcoal Guard Bed, 486 seconds.

c.

Particulate daughter products accumulate for 40 years in equipment.

d.

Nitrogen partition factors: 80 percent noncondensible gases, 20 percent to main condenser hotwell.

e.

Main Steam flow 1.65E+07 lbs/hr.

f.

Normal water chemistry source terms for N-13, N-16, and N-17 are increased by a factor of five due to hydrogen water chemistry operation.

(2) 1.13E-01 = 1.13 X 10-1.

(3)

Isotopes with activity less than 10-1 Ci are not shown.

SSES-FSAR Table Rev. 55 FSAR Rev. 64 Page 1 of 1 TABLE 12.2-23 OFFGAS CHARCOAL BEDS SHIELDING SOURCE TERMS (1)(3)(4)(5)

Isotope Curies Isotope Curies F-18dd 3.87E+00 Kr-83m 3.10E+01 Xe-131m 4.79E+00 Kr-85m 1.29E+02 Xe-133m 4.75E+01(2)

Kr-85 8.05E+00 Xe-133 2.08E+03 Kr-87 1.21E+02 Xe-135m 2.89E+01 Kr-88 2.70E+02 Xe-135 9.36E+02 Kr-89 1.24E+01 Xe-137 2.13E+01 Rb-89 1.26E+01 Xe-138 1.11E+02 Sr-89 1.25E+01 Xe-139 1.82E-01 Rb-88 2.70E+02 Cs-139 1.97E-01 N-13 1.25E+01 Ba-139 1.97E-01 Cs-137 1.29E+01 Cs-138 1.11E+02 NOTES:

(1)

Bases:

a.

100,000 Ci/sec noble gas release rate after 30 min. decay.

b.

Decay time from Reactor Nozzle to inlet of Main Charcoal Beds (1st bed), 503 seconds.

c.

Particulate daughter products accumulate for 40 years in equipment.

d.

Main Steam flow 1.65E+07 lbs/hr.

e.

Normal water chemistry source terms for N-13, N-16, and N-17 are increased by a factor of five due to hydrogen water chemistry operation.

(2) 4.75E+01 = 4.75 X 10+1.

(3)

Activity per charcoal bed (1 only).

(4)

Representative of each of the five charcoal beds.

(5)

Isotopes with activity less than 10-1 Ci are not shown.

SSES-FSAR Table Rev. 55 FSAR Rev. 64 Page 1 of 1 TABLE 12.2-24 OFFGAS POST HEPA FILTER SHIELDING SOURCE TERMS (1)(3)

Isotope Curies Xe-131m 1.25E-05(2)

Xe-133 2.12E-03 Kr-83m 2.08E-05 Kr-85m 5.21E-04 Kr-85 5.62E-05 Kr-87 2.82E-05 Kr-88 4.72E-04 Rb-88 3.06E-03 N-13 3.01E-03 F-18 1.29E-02 NOTES:

(1)

Bases:

a.

100,000 Ci/sec noble gas release rate after 30 min. decay.

b.

Decay time from Reactor Nozzle to outlet of ambient Charcoal Absorbers:

Kryptons - 1.16E+05 seconds Xenons - 2.05E+06 seconds

c.

Particulate daughter products accumulate for 40 years in equipment.

d.

Main Steam flow 1.65E+07 lbs /hr.

e.

Normal water chemistry source terms for N-13, N-16, and N-17 are increased by a factor of five due to hydrogen water chemistry operation.

(2) 1.25E-05 = 1.25 X 10-5.

(3)

Isotopes with activity less than 10-5 Ci are not shown.

SSES-FSAR Table 12.2-29 CONDENSATE STORAGE TANK SOURCE TERMS11 K 3l Isotope I

Curies i

Isotope Curies i

I Br-83 I

2. 75E-02l*I I

Sr-93 7.89E-04 Br-84 I

2.42E-02 i

Y-93 1.71E-04 1-131 3.80E-02 I

La-141 1.89E-03 1-132 2.18E-01 Br-85 1.77E-03 1-133 2'.39E-01 Tc-101 1.32E-03 1-134 2.90E-01 Cs-134 I

9.0BE-05 1-135 3.0?E-01 Cs-136 I

6.20E-05 Cr-51 5.66E-05 Cs-137 1.36E-04 Mn-56 2.97E-03 Na-24 1.97E-04 I

Co-58 5.67E-04 Ni-65 1.77E-05 Co-60 5.68E-05 W-187 i

3.11 E-04 Sr-89 r

3.78E-04 Cs-141 t

4.44E-04 Sr-91 I

9.45E-03 Sr-94 I

1.09E-05 I

Sr-92 I

8.54E-03 Y-94 I

2.85E-05 Mo-99 I

2.41 E-03 Y-95 I

1.06E-05 Tc-99m I

2.35E-02 Rb-91 I

1.0SE-02

\

Te-132 5.40E-03 Rb-90 l

2.03E-02 I

Cs-138 2.87E-02 Rb-89 1.42E-02 Ba-139 I

2.56E-02 Rb-88 2.13E-03 Ba-140 1.12E-03 La-142 1.23E-03 Ba-141 I

4.72E-03 I

Y-91m i

5.11 E-03 Ba-142 1.78E-03 I

Y -91 I

1.46E-05 Np-239 2.62E-02 I

Sr-90 I

2.61 E-05 Cs-140 9.75E-03 La-140 I

6.12E-05 I

Y *92 i

3.44E-03 I

I Cs-139 i

2.91 E-02 j

I T_o_t_al ___

1_._39_E_+_0_0 ___

'. I

{1)

Basis:

(2)

. {3)

a.

Condensate isotopic specific activities (Table 12.2-15) reduced by the demineralizer, are used as feed into the storage tank.

b.

The condensate demineralizer is assumed to provide a OF of 2 for isotopes of cesium and rubidium, and 1 0 for all other isotopes.

c.

A continuous flow rate of 1500 GPM of cleaned condensate is assumed through the 300,000 gallon storage tank.

d.

Instantaneous homogeneous mixing is assumed to occur for a period of one year, by which time a steady state activity should be reached.

2.75E-02 = 2.75 X 10*

2 Reactor water fission product halogen carryover fraction of sx10-2 per unit weight into steam.

Rev. 54, 10/99 Page 1 of 1

SSES-FSAR Table Rev. 55 FSAR Rev. 64 Page 1 of 2 TABLE 12.2-30 ESTIMATED AIRBORNE RADIOACTIVE RELEASES PRIOR TO TREATMENT (CURIES /YEAR)(1)

Nuclide Reactor(3) Building Releases (Ci/Unit)

Turbine(2) Building Releases (Ci/Unit)

Radwaste Building Release (Ci/Site)

Kr-83m Kr-85m 4.00E+00(4) 5.00E+00 Kr-85 Kr-87 2.00E+00 1.22E+01 Kr-88 4.00E+00 1.82E+01 Kr-89 2.00E+00 1.16E+02 5.80E+01 Xe-131m Xe-133m Xe-133 1.10E+02 3.00E+01 4.40E+02 Xe-135m 6.00E+01 8.00E+01 1.06E+03 Xe-135 1.27E+02 6.60E+01 5.60E+02 Xe-137 1.80E+02 2.00E+02 1.66E+02 Xe-138 8.00E+00 2.00E+02 4.00E+00 Cr-51 1.10E-03 1.80E-04 1.40E-03 Mn-54 1.40E-03 1.20E-04 8.00E-03 Fe-59 3.90E-04 2.00E-05 6.00E-04 Co-58 3.00E-04 2.00E-04 4.00E-04 Co-60 5.00E-03 2.00E-04 1.40E-02 Zn-65 5.00E-03 1.20E-03 6.00E-04 Sr-89 5.00E-05 1.20E-03 Sr-90 1.00E-05 4.00E-06 Zr-95 1.00E-03 8.00E-06 1.60E-03 Nb-95 1.00E-02 1.20E-06 8.00E-06 Mo-99 6.60E-02 4.00E-04 6.00E-06 Ru-103 4.20E-03 1.00E-05 2.00E-06 Ag-110m 2.40E-06 Sb-124 5.00E-05 2.00E-05 1.40E-04 Cs-134 4.70E-03 4.00E-05 4.80E-03 Cs-136 5.00E-04 2.00E-05 Cs-137 6.00E-03 2.00E-04 8.00E-03 Ba-140 2.20E-02 2.00E-03 8.00E-06 Ce-141 9.00E-04 2.00E-03 1.40E-05 I-131 2.51E-02 6.60E+02 1.83E-02 I-132 5.62E-01 1.47E+00 4.09E-01 I-133 3.56E-01 9.34E+01 2.59E-01 I-134 1.16E+00 3.05E+00 8.47E+00 I-135 3.91E-01 1.03E+00 2.85E-01

SSES-FSAR Table Rev. 55 FSAR Rev. 64 Page 2 of 2 TABLE 12.2-30 ESTIMATED AIRBORNE RADIOACTIVE RELEASES PRIOR TO TREATMENT (CURIES /YEAR)(1)

Notes:

1.

Based on NUREG-0016, Revision 1, Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Boiling Water Reactors, (BWR - GALE Code), Section 2.2.4.

2.

Turbine Building releases reduced by a factor of 5 due to installation of the Process Valve Stem Leakoff Collection System.

3.

Reactor Building is the sum of the Containment & Auxiliary Building.

4.

4.00E+00 = 4.00 X 100.

SSES-FSAR TABLE 12.2-31 ESTIMATED DISTRIBUTION OF AIRBORNE RADIOACTIVE RELEASES(1>

Airborne Release Fraction (Percent)

TURBINE BUILDING RELEASES Condenser Area 0.78 Miscellaneous Areas 0.22 REACTOR BUILDING RELEASES Containment Building 0.26 Auxiliary Building 0.74 RADWASTE BUILDING RELEASES Solid Handling Areas 0.10 Liquid Waste Handing Areas 0.90 Notes:

1.

Based on NUREG-0016, Revision 1, "Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Boiling Water React~rs"I (BWR - GALE Code), Section 2.2.4.

Rev. 53, 04/99 Page 1 of 1

SSES-FSAR Table Rev. 55 FSAR Rev. 64 Page 1 of 1 TABLE 12.2-32 TURBINE BUILDING AIRBORNE SOURCE DESCRIPTIONS AREA DESIGNATION ROOM NUMBERS AND AREAS INCLUDED TOTAL EXHAUST FLOW (CFM)

TOTAL ANNUAL(1)

EXHAUST (cc/yr)

Condenser 30, 31, 32, 34, 37, 38, 39, 113, 211 23,100 3.44E+14(2)

Miscellaneous Areas C-10, C-12, C-130, C212 C220, C301, C-400, C-900, C-912, 33, 35, 42, 43, 45, 53, 59, 111, 112, 114,115, 116, 117, 118, 119, 120, 121, 122, 123, 124, 125, 126, 128, 130, 210, 212, 214, 215, 216, 217, 300, 415, 416, 417, 419, 421 183,900 2.74E+15 Notes:

1.

Based on continuous release of 365 days per year.

2.

3.44E+14 = 3.44 x 1014

SSES-FSAR Table Rev. 54 FSAR Rev. 64 Page 1 of 1 TABLE 12.2-33 REACTOR BUILDING AIRBORNE SOURCE DESCRIPTIONS AREA DESIGNATION ROOM NUMBERS AND AREAS INCLUDED TOTAL EXHAUST FLOW (CFM)

TOTAL ANNUAL(1)

EXHAUST (cc/yr)

Containment Building 206, 207, 400, 516, 607, 804, 806, 808, 810 37,202 5.54E+14(2)

Auxiliary Building C-601, C-800, C-801,C-802, 10, 12, 15, 17, 102, 103, 104, 105, 106, 107, 200, 201, 202, 203, 204, 205, 401, 403, 404, 405, 410, 411, 412, 500, 501, 506, 508, 509, 511, 513, 514, 515, 608, 610, 616, 619, 620, 621, 704, 800, 801, 802, 811 110,020 1.64E+15 Notes:

1.

Based on continuous release of 365 days per year.

2.

5.54E+14 = 5.54 x 1014

SSES-FSAR Table Rev. 54 FSAR Rev. 64 Page 1 of 1 TABLE 12.2-34 RADWASTE BUILDING AIRBORNE SOURCE DESCRIPTIONS AREA DESIGNATION ROOM NUMBERS AND AREAS INCLUDED TOTAL EXHAUST FLOW (CFM)

TOTAL ANNUAL(1)

EXHAUST (cc/yr)

Solid Radwaste Handling 26, 28, 31, 32, 35, 106, 107, 203, 205, 206, 208, 209, 211, 212, 213, 214, 216, 218, 219, 220, 222, 228, 232, 233, 239, 240, 241, 242, 300, 301, 302, 304, 305,306,307,308, 309,311,312 44,295 6.59E+14(2)

Liquid Radwaste Handling 3, 7, 8, 11, 15, 16, 17, 18, 19, 36, 101, 108, 110, 207, 225, 227, 229, 230, 234, 235, 236, 237, 243, 244 22,650 3.37E+14 Notes:

1.

Based on continuous release of 365 days per year.

2.

6.59E+14 = 6.59 x 1014

SSES-FSAR Table Rev. 55 FSAR Rev. 64 Page 1 of 1 TABLE 12.2-35 ESTIMATED AIRBORNE CONCENTRATIONS IN THE TURBINE BUILDING AND FRACTION OF DACs 10CFR20 Condenser Areas Misc. Areas Nuclide DAC Limit (Ci/cc)

Concen.

(Ci/cc)

Fraction of DAC Concen.

(Ci/cc)

Fraction of DAC Kr-83m 1.00E-02(1)

Kr-85m 2.00E-05 1.13E-08(1) 5.67E-04 4.02E-10 2.01E-05 Kr-85 1.00E-04 Kr-87 5.00E-06 2.77E-08 5.54E-03 9.81E-10 1.96E-04 Kr-88 2.00E-06 4.13E-08 2.06E-02 1.46E-09 7.31E-04 Kr-89 1.00E-07 2.63E-07 2.63E+00 9.32E-09 9.32E-02 Xe-131m 4.00E-04 Xe-133m 1.00E-04 Xe-133 1.00E-04 6.81E-08 6.81E-04 2.41E-09 2.41E-05 Xe-135m 9.00E-06 1.81E-07 2.02E-02 6.43E-09 7.14E-04 Xe-135 1.00E-05 1.50E-07 1.50E-02 5.30E-09 5.30E-04 Xe-137 1.00E-07 4.54E-07 4.54E+00 1.61E-08 1.61E-01 Xe-138 4.00E-06 4.54E-07 1.13E-01 1.61E-08 4.02E-03 Cr-51 8.00E-06 4.08E-13 5.10E-08 1.45E-14 1.81E-09 Mn-54 3.00E-07 2.72E-13 9.07E-07 9.65E-15 3.22E-08 Fe-59 1.00E-07 4.54E-14 4.54E-07 1.61E-15 1.61E-08 Co-58 3.00E-07 4.54E-13 1.51E-06 1.61E-14 5.36E-08 Co-60 1.00E-08 4.54E-13 4.54E-05 1.61E-14 1.61E-06 Zn-65 1.00E-07 2.72E-12 2.72E-05 9.65E-14 9.65E-06 Sr-89 6.00E-08 2.72E-12 4.54E-05 9.65E-14 1.61E-06 Sr-90 2.00E-09 9.07E-15 4.54E-06 3.22E-16 1.61E-07 Zr-95 5.00E-08 1.81E-14 3.63E-07 6.43E-16 1.29E-08 Nb-95 5.00E-07 2.72E-15 5.44E-09 9.65E-17 1.93E-10 Mo-99 6.00E-07 9.07E-13 1.51E-06 3.22E-14 5.36E-08 Ru-103 3.00E-07 2.27E-14 7.56E-08 8.04E-16 2.68E-09 Ag-110m 4.00E-08 Sb-124 1.00E-07 4.54E-14 4.54E-07 1.61E-15 1.61E-08 Cs-134 4.00E-08 9.07E-14 2.27E-06 3.22E-15 8.04E-08 Cs-136 3.00E-07 4.54E-14 1.51E-07 1.61E-15 5.36E-09 Cs-137 6.00E-08 4.54E-13 7.56E-05 1.61E-14 2.68E-07 Ba-140 6.00E-07 4.54E-12 7.56E-05 1.61E-13 2.68E-07 Ce-141 2.00E-07 4.54E-12 2.27E-05 1.61E-13 8.04E-07 I-131 2.00E-08 1.50E-10 7.49E-03 5.30E-12 2.65E-04 I-132 3.00E-06 3.34E-09 1.11E-03 1.19E-10 3.95E-05 I-133 1.00E-07 2.12E-09 2.12E-02 7.51E-11 7.51E-04 I-134 2.00E-05 6.93E-09 3.46E-04 2.45E-10 1.23E-05 I-135 7.00E-07 2.33E-09 3.33E-03 8.25E-11 1.18E-04 (1) 1.00E-02 = 1.00 X 10-2 r--------+-------+------+-------+------+---------, I

SSES-FSAR Table Rev. 55 FSAR Rev. 64 Page 1 of 1 TABLE 12.2-36 ESTIMATED AIRBORNE CONCENTRATIONS IN THE REACTOR BUILDING AND FRACTION OF DACs 10CFR20 Containment Areas Aux. Bldg. Area Nuclide DAC Limit (Ci/cc)

Concen.

(Ci/cc)

Fraction of DAC Concen.

(Ci/cc)

Fraction of DAC Kr-83m 1.00E-02(1)

Kr-85m 2.00E-05 1.88E-09 9.39E-05 1.81E-09 9.04E-05 Kr-85 1.00E-04 Kr-87 5.00E-06 9.39E-10 1.88E 9.04E-10 1.81E-04 Kr-88 2.00E-06 1.88E-09 9.39E-04 1.81E-09 9.04E-04 Kr-89 1.00E-07 9.39E-10 9.39E-03 9.04E-10 9.04E-03 Xe-131m 4.00E-04 Xe-133m 1.00E-04 Xe-133 1.00E-04 5.17E-08 5.17E-04 4.97E-08 4.97E-04 Xe-135m 9.00E-06 2.82E-08 3.13E-03 2.71E-08 3.01E-03 Xe-135 1.00E-05 5.96E-08 5.96E-03 5.74E-08 5.74E-03 Xe-137 1.00E-07 8.45E-08 8.45E-01 8.13E-08 8.13E+01 Xe-138 4.00E-06 3.76E-09 9.39E-04 3.62E-09 9.04E-04 Cr-51 8.00E-06 5.17E-13 6.46E-08 4.97E-13 6.21E-08 Mn-54 3.00E-07 6.57E-13 2.19E-06 6.33E-13 2.11E-06 Fe-59 1.00E-07 1.83E-13 1.83E-06 1.76E-13 1.76E-06 Co-58 3.00E-07 1.41E-13 4.70E-07 1.36E-13 4.52E-07 Co-60 1.00E-08 2.35E-12 2.35E-04 2.26E-12 2.26E-04 Zn-65 1.00E-07 2.35E-12 2.35E-05 2.26E-12 2.26E-05 Sr-89 6.00E-08 2.35E-14 3.91E-07 2.26E-14 3.77E-07 Sr-90 2.00E-09 4.70E-15 2.35E-06 4.52E-15 2.26E-06 Zr-95 5.00E-08 4.70E-13 9.39E-06 4.52E-13 9.04E-06 Nb-95 5.00E-07 4.70E-12 9.39E-06 4.52E-12 9.04E-06 Mo-99 6.00E-07 3.10E-11 5.17E-05 2.98E-11 4.97E-05 Ru-103 3.00E-07 1.97E-12 6.57E-06 1.90E-12 6.333E-06 Ag-110m 4.00E-08 1.13E-15 2.82E-08 1.08E-15 2.71E-08 Sb-124 1.00E-07 2.35E-14 2.35E-07 2.26E-14 2.26E-07 Cs-134 4.00E-08 2.21E-12 5.52E-05 2.12E-12 5.31E-05 Cs-136 3.00E-07 2.35E-13 7.83E-07 2.26E-13 7.53E-07 Cs-137 6.00E-08 2.82E-12 4.70E-05 2.71E-12 4.52E-05 Ba-140 6.00E-07 1.03E-11 1.72E-05 9.94E-12 1.66E-05 Ce-141 2.00E-07 4.23E-13 2.11E-06 4.07E-13 2.03E-06 I-131 2.00E-08 1.18E-11 5.90E-04 1.14E-11 5.68E-04 I-132 3.00E-06 2.64E-10 8.79E-05 2.54E-10 8.46E-05 I-133 1.00E-07 1.67E-10 1.67E-03 1.61E-10 1.61E-03 I-134 2.00E-05 5.46E-10 2.73E-05 5.26E-10 2.63E-05 I-135 7.00E-07 1.84E-10 2.62E-04 1.77E-10 2.52E-04 (1) 1.00E-02 = 1.00 X 10-2 t-------+-----+-----+-----+------+----------11

SSES-FSAR Table Rev. 55 FSAR Rev. 64 Page 1 of 1 TABLE 12.2-37 ESTIMATED AIRBORNE CONCENTRATIONS IN THE RADWASTE BUILDING AND FRACTION OF DACs 10CFR20 Solid Radwaste Handling Area Liquid Radwaste Handling Area Nuclide DAC Limit (Ci/cc)

Concen.

(Ci/cc)

Fraction of DAC Concen.

(Ci/cc)

Fraction of DAC Kr-83m 1.00E-02(1)

Kr-85m 2.00E-05 Kr-85 1.00E-04 Kr-87 5.00E-06 Kr-88 2.00E-06 Kr-89 1.00E-07 8.80E-09 8.80E-02 1.55E-07 1.55E+00 Xe-131m 4.00E-04 Xe-133m 1.00E-04 Xe-133 1.00E-04 6.67E-08 6.67E-04 1.17E-06 1.17E-02 Xe-135m 9.00E-06 1.61E-07 1.79E-02 2.83E-06 3.14E-01 Xe-135 1.00E-05 8.49E-08 8.49E-03 1.50E-06 1.50E-01 Xe-137 1.00E-07 2.52E-08 2.52E-01 4.43E-07 4.43E+00 Xe-138 4.00E-06 6.07E-10 1.52E-04 1.07E-08 2.67E-03 Cr-51 8.00E-06 2.12E-13 2.65E-08 3.74E-12 4.67E-07 Mn-54 3.00E-07 1.21E-12 4.04E-06 2.14E-11 7.12E-05 Fe-59 1.00E-07 9.10E-14 9.10E-07 1.60E-12 1.60E-05 Co-58 3.00E-07 6.07E-14 2.02E-07 1.07E-12 3.56E-06 Co-60 1.00E-08 2.12E-12 2.12E-04 3.74E-11 3.74E-03 Zn-65 1.00E-07 9.10E-14 9.10E-07 1.60E-12 1.60E-05 Sr-89 6.00E-08 Sr-90 2.00E-09 Zr-95 5.00E-08 2.43E-13 4.85E-06 4.27E-12 8.54E-05 Nb-95 5.00E-07 1.21E-15 2.43E-09 2.14E-14 4.27E-08 Mo-99 6.00E-07 9.10E-16 1.52E-09 1.60E-14 2.67E-08 Ru-103 3.00E-07 3.03E-16 1.01E-09 5.34E-15 1.78E-08 Ag-110m 4.00E-08 Sb-124 1.00E-07 2.12E-14 2.12E-07 3.74E-13 3.74E-06 Cs-134 4.00E-08 7.28E-13 1.82E-05 1.28E-11 3.20E-04 Cs-136 3.00E-07 Cs-137 6.00E-08 1.21E-12 2.02E-05 2.14E-11 3.56E-04 Ba-140 6.00E-07 1.21E-15 2.02E-09 2.14E-14 3.56E-08 Ce-141 2.00E-07 2.21E-15 1.06E-08 3.74E-14 1.87E-07 I-131 2.00E-08 2.78E-12 1.39E-04 4.89E-11 2.44E-03 I-132 3.00E-06 6.20E-11 2.07E-05 1.09E-09 3.64E-04 I-133 1.00E-07 3.93E-11 3.93E-04 6.91E-10 6.91E-03 I-134 2.00E-05 1.28E-10 6.42E-06 2.26E-09 1.13E-04 I-135 7.00E-07 4.32E-11 6.17E-05 7.60E-10 1.09E-03 (1) 1.00E-02 = 1.00 X 10-2

SSES-FSAR NIMS Rev. 60 FSAR Rev. 65 Page 1 of 4 TABLE 12.2-38 TURBINE BUILDING SHIELDING DESIGN RADIATION SOURCE DESCRIPTION Room No.

E1 Dominant Radiation Source Source Location or Identification Geometry Effective Source Density gm/cc Equipment Self Shielding (Steel)

Thickness in.)

FSAR Source Table 1

646 Offgas lines from recombiner to radwaste 8 GBC-106 8 diam. cyl.

1.17x10-3 0.322 12.2-19 30 31 656 656 Condensate pumps and lines 1P-102A,B,C,D 48, 30 and 18 diam. cyl.

1.0 0.375 12.2-15 32 34 656 656 Recombiner Recombiner 1S-125 5 diam. x 6-2 ht. cyl.

1.21x10-3 0.75 12.2-18 33 656 Steam Packing exhauster 1E-110 36 diam. cyl.

30 diam. cyl.

1.0 0.375 11.1-1,-2,-3,-4 55 656 Vacuum pump 1P-105 12 diam. cyl.

1.4x10-3 0.406 11.1-1,-2,-3,-4 56 656 Recombiner pipe valve manifold from SJAE 8 diam. and 10 diam. cyl.

1.21x10-3 0.322 12.2-17 C-11 656 Chem drain tank and pumps OT-114 OP-132A,B 3-6 diam.

6-4 ht. cyl.

1.0 0.187 11.2-6 42 656 Condensate demineralizer pipeway Various resin lines 30,24,14,3 diam. cyl.

1.0 0.216 12.2-16 12.2-15 152 656 Regeneration waste surge tanks 1T-106A,B 7 diam.

13 high cyl.

1.0 0.5 12.2-16 151 656 Neutralizing pumps 1P130A,B 2 diam. cyl.

1.0 0.154 12.2-16 43 656 Chemical waste 1T130A,B 12 diam.

1.0 0.197 12.2-16 Neutralizing tanks 20 length 37 656 RFP turbine 27x75 RFT 3 diam. cyl.

2.04x10-4 0.25 12.2-11 38 656 exhaust duct duct 11.1-1,-2,-3,-4 39 656

SSES-FSAR NIMS Rev. 60 FSAR Rev. 65 Page 2 of 4 TABLE 12.2-38 TURBINE BUILDING SHIELDING DESIGN RADIATION SOURCE DESCRIPTION Room No.

E1 Dominant Radiation Source Source Location or Identification Geometry Effective Source Density gm/cc Equipment Self Shielding (Steel)

Thickness in.)

FSAR Source Table 36 656 Main condenser and steam piping IE-108A,B,C, RFW duct condensate lines 3 diam.

36 diam. cyl.

2.04x10-4 1.0 0.25 11.1-1,-2,-3,-4 12.2-11 12.2-15 59 656 Condensate Filtration Backwash Receiving Tank 1T-187 9 diam.x24 1 cyl 1.0 0.25 12.2-48 117 676 Deep bed 1F-106G 11 diam. cyl.

1.0 1.5 12.2-6 118 676 Condensate demin.

1F-106F 3 deep 1.0 1.5 12.2-16 119 676 1F-106E 1.0 1.5 12.2-16 120 676 1F-106D 1.0 1.5 12.2-16 121 676 1F-106C 1.0 1.5 12.2-16 123 676 1F-106B 1.0 1.5 12.2-16 124 676 1F-106A 1.0 1.5 12.2-16 125 676 1F-106H 1.0 1.5 12.2-16 114 676 RFP turbine 105C 4 diam. cyl.

0.033 0.337 12.2-11 115 676 RFP turbine 105B 10 diam. cyl.

0.0061 0.365 11.1-1,-2,-3,-4 116 676 RFP turbine 105A 111 676 SJAE 1E-109 8 diam. cyl.

1.21x10-3 0.322 12.2-17 112 676 Future SJAE 3-6 diam. x 12 h cyl.

1.21x10-3 1.08 113 676 Main condenser steam piping 1E-108A,B,C 42,28,26,16 diam. cycl.

.00623,.036

.00216, 0.625 0.375 11.1-1,-2,-3,-4, 12.2-11

.00786 125 676 Anion and cation 1T-157 46øx14h cyl.

1.0 0.25 12.2-16 regeneration 1T-158,159 66x14h cyl.

SSES-FSAR NIMS Rev. 60 FSAR Rev. 65 Page 3 of 4 TABLE 12.2-38 TURBINE BUILDING SHIELDING DESIGN RADIATION SOURCE DESCRIPTION Room No.

E1 Dominant Radiation Source Source Location or Identification Geometry Effective Source Density gm/cc Equipment Self Shielding (Steel)

Thickness in.)

FSAR Source Table 110 676 Turbine bldg.

1C-132A,B 3/8 SS tubing Varies 11.1-1,-2,-3,-4 sample station 130 676 Condensate Filter Bundles 1F135A,B,C,D,E,F 6 diam.x4-2 h cyl.

0.975 1.584 12.2-46 133(1) 676 Condensate Filter Bundles 2F125G 6 diam.x4-2 h cyl.

0.975 1.584 12.2-46

130, 133(1),

C-100 676 Backwash Piping 12 HCD-107(130) 12 HCD-207(133, C-100) 12 diam. cyl.

1.0 0.25 12.2-47 211 699 Main condenser and steam piping 1E108A,B,C, 24 DBB-101 102, 203, 104 24 diam. cyl.

28 diam. cyl.

42 diam. cyl.

.036

.0328 0.00674 0.94 0.375 0.625 11.1-1,-2,-3,-4 12.2-11 212 699 Feedwater heaters 1E103 6øx45 cyl.

0.714 9/16 11.1-1,-2,-3,-4 214 699 Feedwater heaters 1E104 6øx40 cyl.

0.815 9/16 12.2-11 215 699 Feedwater heaters 1E105 6øx36 cyl.

0.853 9/16 300 714 Main steam tunnel 24-DBB-101, 24 diam. cyl.

.036 0.97 11.1-1,-2,-3,-4 102, 103, 104 12.2-11 411 729 Main steam tunnel 24-DBB-101, 24 diam. cyl.

.036 0.97 11.1-1,-2,-3,-4 102, 103, 104 12.2-11 416 729 Steam seal 1E-128 51/2øx34 cyl.

0.447 5/8 11.1-1,-2,-3,-4 evaporator 12-EBB-113 12 diam. cyl.

2.25-3 0.687 12.2-11 419 729 Moisture separator 1T-104A,B 10-8x67.3 cyl.

0.768 0.75 11.1-1,-2,-3,-4 421 729 and 42 cross-over steam lines 42-GE Supplied 42 diam. cyl.

0.0063 0.625 12.2-11

SSES-FSAR NIMS Rev. 60 FSAR Rev. 65 Page 4 of 4 TABLE 12.2-38 TURBINE BUILDING SHIELDING DESIGN RADIATION SOURCE DESCRIPTION Room No.

E1 Dominant Radiation Source Source Location or Identification Geometry Effective Source Density gm/cc Equipment Self Shielding (Steel)

Thickness in.)

FSAR Source Table 420 729 HP & LP turbines 1G-101 28 diam. cyl.

.0328 1.4 11.1-1,-2,-3,-4 28, 42 GE Supplied 42 diam. cyl.

.00623 0.625 12.2-11 531 762 H&V System 1F-156, 157 2x2x1 (63 units) 0.49 0.25 N/A 532 762 (HEPA & charcoal) 1F-158 315 ft3 (carbon)

Note: 1. Room 133 only applies to Unit 2.

SSES-FSAR Table Rev. 55 TABLE 12.2-39 REACTOR BUILDING SHIELDING DESIGN RADIATION SOURCE DESCRIPTION FSAR Rev. 64 Page 1 of 5 Room No.

El.

Dominant Radiation Source Source Location or Identification Geometry Effective Source Density gm/cc Equipment Self Shielding (Steel)

Thickness in.)

FSAR Source Table 11 645 HPCI turbine 1S-211 10 diam. cyl.

20 diam. cyl.

.036 0.375 11.-1,-2,-3,-4 12.2-11 12 645 RCIC turbine 1S-212 4 diam. cyl.

10 diam. cyl.

.036 0.365 11.1-1-2,-3,-4 12.2-11 13 645 RHR heat exchanger suction, discharge lines 1E-205B 30-GBB-110 5 diam. x 21 long (HT. EXCH) and 1.24 1.0 12.2-10 14 645 RHR heat exchanger suction, discharge lines 1E-205A 30-GBB-110 24 & 20 diam. cyl.

(lines) 0.76 0.375 12.2-10 202 204 205 683 683 683 RHR, core spray, and HPCI Line with associated drywell penetrations (GBB lines) 24, 18, 16, 12 10, 4 diam. cyl.

0.76 0.375 12.2-10 11.1-2,-3,-4,-5 206 683 Reactor Recirculating water pump and lines 1P-401 28, 26, 22, 12 diam. cylinders 0.73 1.076, 1.009 1.013 0.586 11.1-2,-3,-4,-5 400 719 Reactor Recirculating water lines in drywell 1P-401 28, 26, 22, 12 diam. cylinders 0.73 1.076 1.009 1.013, 0.586 11.1-2,-3,-4,-5 402 719 Reactor Recirculating water lines in drywell 1P-401 28, 26, 22, 12 diam. cylinders 0.73 1.076 1.009 1.013, 0.586 11.1-2,-3,-4,-5

SSES-FSAR Table Rev. 55 TABLE 12.2-39 REACTOR BUILDING SHIELDING DESIGN RADIATION SOURCE DESCRIPTION FSAR Rev. 64 Page 2 of 5 Room No.

El.

Dominant Radiation Source Source Location or Identification Geometry Effective Source Density gm/cc Equipment Self Shielding (Steel)

Thickness in.)

FSAR Source Table 412 719 Reactor Recirculating water lines in drywell 1P-401 28, 26, 22, 12 diam. cylinders 0.73 1.076 1.009 1.013, 0.586 11.1-2,-3,-4,-5 411 719 Main steamlines 24 DBB-101, 102, 103, 104 24 diam. cyl.

0.036 0.941 11.1-1,-2,-3,-4 12.2-11 501 749-1 Drywell penetrations Reactor core and water recirc lines Annual streaming Not applicable Not applicable 11.1-1-2,-3,-4-5 12.2-4,-5 502 503 749-1 R/W cleanup pumps 1P-221A 1P-221B 3, 4 diam. cyl.

1.0 0.30 0.44 12.2-6 11.1-2,-3,-4,-5 504 505 749-1 749-1 Regenerative ht exch.

Nonregenerative heat exch.

1E-207 1E-208 1-6øx21-4 Long cyl.

1-6øx28-2 Long cyl.

2.64 2.71 0.5 0.5 12.2-6 11.1-2,-2,-3,-4,-5 506 749-1 Drywell penetrations Reactor core and water recirc lines Annular streaming Not applicable Not applicable 11.1-1,-2,-3,-4,-5 12.2-4,-5 509 761-10 R/W F/D backwash receiving tank 1T-225 7øx2 h cyl.

1.0 0.197 12.2-8 511 762-10 Fuel pool F/D backwash receiving tank OT-203 6øx8 h cyl.

1.0 0.475 12.2-14 514 749-1 Fuel pool heat exchangers 1E-202A,B,C 20øx21.4 Long cyl.

1.264 0.5 12.2-12

SSES-FSAR Table Rev. 55 TABLE 12.2-39 REACTOR BUILDING SHIELDING DESIGN RADIATION SOURCE DESCRIPTION FSAR Rev. 64 Page 3 of 5 Room No.

El.

Dominant Radiation Source Source Location or Identification Geometry Effective Source Density gm/cc Equipment Self Shielding (Steel)

Thickness in.)

FSAR Source Table 515 761-10 Main steam lines out drywell 24 DBB-101 102, 103, 104 24ø cyl.

.036 0.941 12.2-11 11.1-1,-2,-3,-4 516 749-1 Core, recirc pumps and lines Reactor core and recirc water lines 28, 26, 22, 12 diam. cyl.

0.73 1.076 1.009 1.009 0.586 11.1-1,-2,-3,-4,-5 12.2-4,-5 607 779-1 Core, recirc lines, steamlines Reactor core and steamlines 26 diam. cyl.

0.036 1.009 11.1-1,-2,-3,-4,-5 12.2-4,-5 601 779-1 Skimmer surge tank 1T-208 7 1/2 øx26 h cyl.

1.0 0.25 Crud from fuel pool 602 779-1 Spent fuel cask Spent fuel elements 7 diam.

20 long 1.0 6 lead 12.2-9A1, 12.2-9A2, 603 779-1 Spent fuel pool Spent fuel elements 150 active fuel 4.50 12.2-9 619 779-1 R/W cleanup demin.

Holding pumps 1P-223A,B 4 diam. cyl.

3 diam. cyl.

1.0 1.0 0.237 0.300 12.2-6 12.2-7 620 779-1 Sample station 1C-210 3/8 lines Varies 12.2-6,-10,-11,-12 621 779-1 Fuel pool demin holding pumps 1P-205 0P-205 6 diam. cyl.

1.0 0.280 12.2-13 C-801 802 799-1 Fuel pool filter demineralizers 1F-202 0F-202 3øx4.5 h cyl.

1.0 0.25 12.2-13

SSES-FSAR Table Rev. 55 TABLE 12.2-39 REACTOR BUILDING SHIELDING DESIGN RADIATION SOURCE DESCRIPTION FSAR Rev. 64 Page 4 of 5 Room No.

El.

Dominant Radiation Source Source Location or Identification Geometry Effective Source Density gm/cc Equipment Self Shielding (Steel)

Thickness in.)

FSAR Source Table 403 719 TIP cable from drywell Stainless steel cables 1S-217A, B,C,D,E 1/2 OD, tw-0.083 SS-304 tube Not applicable Not applicable Activation of SS-304 804 799-1 Steam separator and dryer in storage B-11-33-2 B-11-37-2 22-6x196 22-6x183 cyl.

Not applicable Not applicable Crud and activation of SS-304 607 779-1 Steam lines in drywell 24 DBB-101 102, 103, 104 24 diam. cyl.

0.36 0.941 11.1-1,-2,-3,-4, 12.2-11 603 779-1 Spent fuel assemblies 150 active fuel 4.50 None 12.2-9A1, 12.2-9A2 700 799-1 HEPA & charcoal filters 1F-254, 255, 258 1E-257 (A&B) 2 x 2x1 (48 units) 22 ft3 (carbon) 0.48 0.25 12.2-30,31,33 800 801 799-1 799-1 Reactor water filter/demin.

1F-203A 1F-203B 2.5 diam. x 8 h cyl.

1.0 0.5 12.2-7 C-801 802 799-1 799-1 Fuel pool filter/demin.

0F-202 1F-202 3 diam. x 4.5 h cyl.

1.0 0.25 12.2-13 710 799-1 Main steam lines 24 DBB-101 102, 103, 104 3.75 diam x 4 0.36 0.941 11.1-1,-2,-3,-4 12.2-11 701 100 799-1 670-0 Spent fuel cask (transfer)

Spent fuel elements 7 diam.

20 long cyl.

1.0 6 load 12.2-9A1, 12.2-9A2

SSES-FSAR Table Rev. 55 TABLE 12.2-39 REACTOR BUILDING SHIELDING DESIGN RADIATION SOURCE DESCRIPTION FSAR Rev. 64 Page 5 of 5 Room No.

El.

Dominant Radiation Source Source Location or Identification Geometry Effective Source Density gm/cc Equipment Self Shielding (Steel)

Thickness in.)

FSAR Source Table 702 799-1 H&V filters (HEPA and carbon) 1F-215, 216, 217, 218 2x2x1 (12 units) 63 ft3 - carbon 0.49 0.25 N/A 807 818-1 Spent fuel elements (pool)

Spent fuel assemblies (138% core loading) 5.438øx150 (7x7 array) 4.50 N/A 12.2-9A1 12.2-9A2

SSES-FSAR TABLE 12.2-40 RADWASTE BUILDING SHIELDING DESIGN RADIATION SOURCE TERMS Equipment Effective Self Shielding Dominant Source Location or Source Density (Steel)

FSAR Room No.

E1 Radiation Source Identification Geometry gm/cc Thickness in.)

Source Table R-1 646'-0" 8"0 offgas lines and.

a* GBC-106 8" diam. cyl.

1.21x10*3 0.322 12.2-19 other radwaste lines R-38 646'-0" Liquid radwaste valve 8" GBC-106 8" and 3" diam.

1.21x10"3 0.322 12.2-19 gallery 3" HCD-49 cyl.

11.4-6 11.2-6 R-2 646'-0" Laundry drain tank and OT-311A,B 5'0x8' h cyl.

1.0 3/16 11.2-6 pumps OP-318A,8 R-3 646'-0" Chemical waste tank OT-314 11.5'0x20 h cyl.

1.0 3/16 11.2-6 R-4 646'-0" Chemical waste tank OP-326A,8 2" diam. cyl.

1.0 0.154 11.2-6 pumps and lines R-5 646'-0" Radwaste evaporator OE-302A 6'0x17' long cyl.

1.0 3/16 R-9 646'-0" OE-3028 R-6 646'-0" Radwaste evaporator OP-327A&B 2" diam. cyl.

1.0 0.145 11.2-6 distillate and OP-328 concentrates pumps 2"-HCD-78 R-7 646'-0" Evaporator distillate tank OT-321 9'0x17' h cyl.

1.0 3/16 11.2-6 R-8 646'-0" Evaporator concentrates OT-322 8'0x14.5' h cyl.

1.0 3/16 tank R-11 646' Liquid radwaste sample OT-303A,B,C,D,E. F 11.5'0x20' h cyl.

1.0 3/16 11.2-6 tanks R-12 646' Liquid radwaste sample OP-305A,B,C 4" diam. cyl.

1.0 0.120 11.2-6 tank pumps Rev. 54, 10/99 Page 1 of 4

SSES-FSAR TABLE 12.2-40 RADWASTE BUILDING SHIELDING DESIGN RADIATION SOURCE TERMS Equipment Effective Self Shielding Dominant Source Location or Source Density (Steel)

FSAR Room No.

E1 Radiation Source Identification Geometry gm/cc Thickness i.n.)

Source Table R-13 646' Radwaste demin. valve 4" HCD-46 4" diam. cyl.

1.0 0.120 11.2-6 manifold 11.4-6 R-14 646' LRW sump pump 0P-338A,B 3" diam. cyl.

1.0 0.216 11.2-6 0P-337A,B 11.4-6 R-15 646' Liquid radwaste surge OT-304A,B,C,D 11.5'0x20' h cyl.

1.0 3/16 11.2-6 R-16 646' tank R-17 "646' Liquid radwaste 0T-302A,B,C,D,E,F 11.5'0x20' h cyl.

1.0 3/16 11.2-6 R-18 646' collection tanks R-19 646' R-20 646' Liquid radwaste surge OP-301A,B,C 5* diam. cyl.

1.0 0.28 11.2-6 and collection pumps 0P-302 6" HBD-34 R-34 646' Tank vent filter unit 0F-357,358,359 3 carbon trays, 0.49 0:25 12.2-30,-31 180 lb total R-30 646' Waste sludge phase OT-331 11'6"0x14.5' h cyl.

1.0 3/16 11.4-6 separator R-31 646' Reactor water phase 0T-318A,B 11'6"x10' h cyl.

1.0 3/16 11.4-6 R-32 646' separator R-29 646' Waste sludge mixing OP-331,332 4" diam. cyl.

1.0 0.120 11.2-6 pumps OP-334,336 11.4-6 Rev. 54, 10/99 Page2 of 4

SSES-FSAR TABLE 12.2-40 RADWASTE BUILDING SHIELDING DESIGN RADIATION SOURCE TERMS Equipment Effective Self Shielding Dominant Source Location or Source Density (Steel)

FSAR Room No.

E1 Radiation Source Identification Geometry gm/cc Thickness in.)

Source Table R-24 646' Solid radwaste container 55-gal drums and 6" diam. x 6' cyl.

2.3 0.25 11.4-9 R-25 646' radwaste shipping 11.4-10 R-26 646' containers R-27 646' R-37 646' R-28 646' Spent resin tank OT-324 9.5'0x17 h cyl.

1.0 3/16 11.4-6 R-110 664'-3~

Valve gallery liquid 8" GBC-106 8" diam. cyl.

1.17x10-3 0.322 12.2-19 radwaste 4" HBD-131,-231 4" diam. cyl.

1.0 0.237 11.4-6 R-105 660'-0" LRW piping to LRW filter 4"-HCD-48 4" diam. cyl.

1.0 0.120 11.4-6 R-106 660' Waste mixing tank OT-307A,B 6'0x8' h cycl.

1.0 3/16 11.4-6 R-107 660' 14" diam. chute 14" diam. cycl.

0.25 R-102 658'-3' Radwaste demineralizer OF-301

• 6'6"0x10 h cyl.

1.0 1/2 11.4-6 R-101 661'-9" Various LRW and offgas 8"-GBC-106 8",3",1.5" diam.

1.2-1x10--3 0.322 12.2-19 lines 3" HCD-49 cyl.

1.0 0.120 11.4-6 1.5" HCD-79 1.0 0.145 11.2-6 R-222 676' Solid radwaste 6'cubes 6' diam. x 6' cyl.

2.3 0.25 11.4-9 R-223 676' container(s) 11.4-10 R-224 676' R-225 678'-6" Liquid radwaste filters OF-302A,B 5' diam. x 5' h 1.0 0.25 11.4-6 R-227 678-6" cylinder R-311 691'-6" H&V HEPA filters OF-335A,B 2'x2'x1'

.00129 0.25 NIA R-312 691'-6" (30 units)

Rev. 54. 10/99 Page 3 of 4

SSES-FSAR TABLE 12.2-40 RADWASTE BUILDING SHIELDING DESIGN RADIATION SOURCE TERMS Equipment Effective Self Shielding Dominant Source location or Source Density

{Steel)

FSAR Room No.

E1 Radiation Source Identification Geometry gm/cc Thickness in.)

Source Table R-240 676'-0" Main H-306, 307, 8' diam. x 0.50 1.19 12.2-23 R-242 Charcoal 308,309,310 18' high cylinder Bed R-243 676'-0" Guard 1T-305 2'-6" diam. x 0.50 0.75 12.2-22 Bed 8' h cylinder R-244 676'-0" Water 2E-302 (precooler) 9"0x6' h cyl.

1.34 0.321 12.2-21 R-245 Removal 2E-303 ( chiller) 16"rz,x6' h cyl.

0.422 0.374 Skid R-212 676'-0" Post HEPA 1F-302 10.75" diam. x 1.21x10*3 0.365 12.2-24 R-213 Filter 2'-3" h cylinder R-215 676'-0" Off-Gas 6" GBD-158 6" diam. cylinder 1.21x10"3 0.43" 12.2-19 lines 3" GBD-158 3" diam. cylinder 0.3" Rev. 54, 10/99 Page 4 of 4

SSES-FSAR TABLE 12.2-41 MATERIAL COMPOSITION OF THE TIP SYSTEM COMPONENTS AS USED IN ACTIVATION CALCULATIONS MATERIAL DETECTOR REGION AISI 304 Stainless Steel

• Commercially Pure Titanium Fosterite Ceramic Nichrome Uranium 235 (U-235)

CABLE REGION AISI 3041 Stainless Steel

• AISI C1070 Carbon Steel

. Magnesium Oxide Rev. 53, 04/99 WEIGHT 4 grams 3 grams 0.5 grams 0.02 grams 0.001 grams 0.12 grams per inch 2.1 grams per inch 0.12 grams per inch Page 1 of 1

SSES-FSAR TABLE 12.2-42 TRAVERSING INCORE PRO.BE (TIP) DETECTOR URANIUM-235 GAMMA DECAY ACTIVITIEs<1)<2>(3>

GAMMA ENERGY RANGE (MeV)

GAMMA EMISSION (MeV/sec) 0.1 to 0.4 0.4 to 0.9 0.9 to 1.35 1.35 to 1.8

-1.8 to 2.2 2.2 to 2.6 2.6. to 3.0 3.0 to 3.5 3.5 to 4.0 4.0 to 4.5 4.5 to 5.0 5.0 to* 5.5 NOTES:

(1) Activity due to 0.001 grams U-235 present.

(2)

Decay time= 1 second (3)

Activation time:;; 100 seconds (4) 3.4E+09 = 3.4 X 109 Rev. 53, 04/99 3.4E+o9(4>

1.5E+10 1.2E+10 1.1E+10 8.0E+09 6.4E+09 5.6E+09 5.1E+09 4.3E+09 2.5E+09 1.5E+09 7.9E+08 Page 1 of 1

SSES-FSAR TABLE 12.2-43 TRAVERSING INCORE PROBE (TIP) DETECTOR GAMMA DECAY ACTIV.ITIES OF MATERIALS IN IRRADIATED DETECTORc1H2l<3l ACTIVATED ISOTOPES Fe-59 Mn-56 Cr-51 Mn-54 Co-58m Co-58 Ni-57 Co-57 Ni-65 Co-60m Co-60 Co-61 Si-31 NOTES:

(1) Above activity excludes U-235.

(2)

Decay time = 1 second (3)

Activation time= 100 seconds (4) 1.1E+01 = 1.1 X 101 Rev. 53, 04/99 ACTIVITY (µCi) 1.1 E+01'4l 1.7E+05 7.0E+01 2.1E+00 3.5E+03 2.2E-02 1.1 E-01 6.0E-07 4.0E+02 7.6E+03 1.8E-03 9.6E+00 2.9E+01 Page 1 of 1

SSES-FSAR TABLE 12.2-44 GAMMA DECAY ACTIVITIES OF MATERIALS IN THE IRRADIATED TIP CABLE(1H2l ACTIVATED ISOTOPES Fe-59 Mn-56 Cr-51 Mn-54 Co-58m Co-58 Ni-57 Co-57 Ni-65 Co-60m Co-60 Co-61 Si-31 NOTES:

(1)

Decay time = 1 'second (2)

Activation time = 100 seconds (3) 8.2E+00 = 8.2 X 10° Rev. 53, 04/99 ACTIVITY (µCi/inch) 8.2E+0Q(3) 7.4E+04 3.7E+00 1.6E+OO 1.0E+02 6.SE-04 3.3E-03' 1.BE-08 1.2E+01 2.2E+02 5.1 E-05 2.BE-01 8.7E-01 I

I I I I I I

I f

I I

[

I I

~

I Page 1 of 1

SSES-FSAR TABLE 12.2-46 CONDENSATE FILTER VESSEL SHIELDING SOURCE TERMS (1)

Isotope Activity(Curies)

Ag-110m 3.902E-021.~J Ba-139 4.517E-01 Ba-140 5.416E+00 Ba-141 1.922E-01 Ba-142 7.221E-02 Co-58 5.711E-02 Co-60 4.734E-01 Cr-51 2.515E-01 Fe-59 9.995E-01 La-141 1.312E-02 La-142 9.994E-03 Mn-54 2.897E+00 Mn-56 2.430E-01 Mo-99 2.761E+00 Ni-65 1.423E-03 Np-239 2.569E+01 Sb-124 2.070E-02 Sr-89 5.179E+00 Sr-90 6.814E-01 Sr-91 1.240E+00 Sr-92 7.159E-01 Sr-93 2.896E-02 Tc-101 5.754E-02 Tc-99m 3.186E+00 Te-132 6.297E+01 W-187 1.360E-01 Y-91m 1.890E-03

.Y-92 6.083E-03 Y-93 5.612E-03 Zn-65 1.307E-01 (1)

Source term based on buildup of condensate activity for 94 days. Th1s buildup time corresponds to the accumulation of 280 lbs of solids on the filter which is the maximum filter loading for structural*integrity.

(2) 3.902E-02 = 3.902 X 10*

2 Rev. 54, 10/99 Page 1 of 1

SSES-FSAR TABLE 12.2-47 CONDENSATE FILTER VESSEL BACKWASH SHIELDING SOURCE TERMS <

1l

• fsotope Activity Concentration In Backwash(µCi/cc)

Ag-110m 5.998E-031L)

Ba-139 6.943E-02 Ba-140 8.325E-01 Ba-141 2.954E-02 Ba-142 1.110E-02 Co-58 8.779E-03 Co*60 7.276E-02 Cr-51 3.866E-02 Fe-59 1.536E-01 La-141 2.017E-03 La-142 1.536E-03 Mn-54 4.453E-01 Mn-56 3.735E-02 Mo-99 4.244E-01 Ni-65 2.187E-04 Np-239 3.948E+00 Sb-124 3.181 E-03 Sr-89 7.959E-01 Sr-90 1.047E-01 Sr-91 1.906E-01 Sr-92 1.1 00E-01 Sr-93 4.450E-03 Tc-101 8.844E-03 Tc-99m 4.897E-01 Te-132 9.678E+00 W-187 2.091E-02 Y-91m 2.905E-04 Y-92 9.350E-04 Y-93 8.625E-04 Zn-65 2.00BE-02 (1}

Source term for condensate filter backwash is based on 80% of the maximum filter activity contained in one backwash surge volume. A minimum of two surges is required for filter backwash.

(2) 5.998E-03 = 5.998 X 10-3 Rev. 54, 10/99 Page 1 of 1

SSES-FSAR TABLE 12.2-48 CONDENSATE FILTER VESSEL BACKWASH RECEIVING TANK SHIELDING SOURCE TERMS Pl Isotope Activity(Curies)

Ag-110m 1.171E-01(L!

Ba-139 1.355E+00 Ba-140 1.625E+01 Ba-141 5.766E-01 Ba-142 2.166E*01 Co-58 1_.713E-01 Co-60 1.420E+00 Cr-51 7.547E-01 Fe-59 2.998E+00 La-141 3.937E-02 La-142 2.998E-02 Mn-54 8.691E+00 Mn-56 7.291E-01 Mo-99 8.283E+00 Ni-65 4.268E-03 Np-239 7.706E+01 Sb-124 6.210E-02 Sr-89 1.554E+01 Sr-90 2.044E+00 Sr-91 3.719E+00 Sr-92 2.148E+00 Sr-93 8.687E-02 Tc-101 1.726E-01 Tc-99m 9.558E+O0 Te-132 1.889E+02 W-187 4.081E-01 Y-91m 5.670E-03 Y-92 1.825E-02 Y-93 1.684E-02 Zn-65 3.920E-01 NOTES:

(1)

Source term for Backwash Receiving Tank is based on three fitter backwashes with each backwash requiring only two backwash surges. A minimum of two surges is required for filter backwash. Each backwash removes 100% of the maximum filter activity. The Backwash receiving Tank is designed to hold two triple backwashes with 20% freeboard.

(2) 1.171E-01 = 1.171 X 10*1 Rev. 54, 10/99 Page 1 of 1