RS-10-007, 375636, Revision 0, Dewatered Resin Flammable Gas Generation Assessment, Appendix B

375636, Revision 0, Dewatered Resin Flammable Gas Generation Assessment, Appendix B

ML100070303
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Site:	LaSalle
Issue date:	09/28/2009
From:	URS Corp
To:	Office of Nuclear Reactor Regulation
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ML100070297	List: ML100070301 RS-10-007, 375636, Revision 0, Dewatered Resin Flammable Gas Generation Assessment, Appendix B RS-10-007, LaSalle County Station, Units 1 and 2 - Request for License Amendment to Allow Receipt and Storage of Low-Level Radioactive Waste RS-10-007, LaSalle Station, Units 1 and 2 - Irsf LAR Support Technical Report Supporting Engineering Change (EC) No. 375636 Type: Document Change Request (DCR) Subtype: Dsgn
References
29487-NCS0097, FOIA/PA-2010-0209, RS-10-007 375636, Rev 0
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Text

APPENDIX B LASALLE DEWATERED RESIN FLAMMABLE GAS GENERATION ASSESSMENT Appendix B - Page 1 of 16

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 1 DEWATERED RESIN FLAMMABLE GAS GENERATING ASSESSMENT This appendix provides an evaluation of potential flammable gas generation under the worst-case assumed full Class B/C radwaste loading conditions considering extended storage, i.e. greater than 5 years.

1.1. Combustible Gas Evolution Gases, including some potentially flammable gases, are generated in radioactive ion-exchange resins from a radiolytic reaction due to radiation. Most of the flammable gas is hydrogen, but there is a small percentage of methane, and carbon monoxide. These gases are potentially explosive in high concentrations. Gas generated is in direct proportion to the Curie loading.

1.1.1. High Integrity Containers (HICs)

In this assessment, 8-120 standard HDPE containers supplied by Energy Solutions are assumed to be used for storing radioactive waste in the LaSalle IRSF storage bay: See Table 1 for detailed information on this container.

Table 1 HDPE High Integrity Container (HIC) 8-120 Parameter Value Value Internal Volume 107.6 ft3 3.05E+03 L Diameter 61.5 in 156.2 cm Height 73.5 in 186.7 cm Port opening 22.5 in 57.2 cm Disposal Volume 120.3 ft3 3.41E+03 L Gross weight 10,000.0 lb 4,536 kg For extended storage in the past, waste package deformation was observed due to an increase in internal pressure. For this reason, a passive vent (HEPA) device was installed on the container to automatically vent gases, designed to resist plugging by resins.

Appendix B - Page 2 of 16

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 1.1.2. LaSalle Existing IRSF Capacity Table 2, indicates LaSalle IRSF storage area dimensions. For more details see Attachment C- LaSalle IRSF Dimensions.

Table 2- LaSalle Existing IRSF Capacity by Volume Parameter Volume Up to Rail Total IRSF Volume Height 34 ft 49 ft Length 95 ft 95 ft Width 60 ft 60 ft 2

IRSF Storage Area 3,230 ft 4,655 ft2 IRSF Storage Volume 193,800 ft3 279,300 ft3 IRSF Storage Volume 5,486,478 L 7,906,983 L Maximum HIC Capacity 270 containers 1.1.3. Flammable Gas Generation Volumes A major study was performed and published via ASTM ( post- TMI accident) relative to combustible gas evolution from resins generated during water cleanup operations using EPICOR 2 System prefilters coated with organic resins (see reference 4, page 1240). The hydrogen gas generation in each vessel is concluded to be directly proportional to the curie content present. The study documents that flammable gas generation in bead resin Radwaste is found to be 6 x 10-6 L/h-Ci at standard temperature and pressure. Assuming waste isotopes are primarily Co-60 (conservative assumption, see Reference 4, page A1-2), a 100 R/hr HIC will have a curie content of approximately 300 Ci and a hydrogen gas generation rate of about 1.8 x 10-3 L/hr. See Attachment D-Hydrogen Gas Generation Calculation Excel Spreadsheet, Rev A..

Exelon is expecting to have an average container contact dose rate of 50 R/hr on a regular basis. Some containers are expected to have higher dose rates depending on the site,;

Appendix B - Page 3 of 16

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 therefore, a linear evaluation is performed for hot containers cases using 100 R/hr, 300 R/hr, and 500 R/hr. See a summary of inputs below.

Input Summary List Flammable Gas Generation 6.00E-06 L/(hr-Ci) See Reference 4, page 1240 Assuming Co-60 isotope content only See Reference 4, (conservative assumption) page A1-2 Dose Rate per HIC 100 R/hr Curie Content 300 Ci Hydrogen Gas generated 1.8E-03 L/hr HIC Volume 107.6 ft3 3046.156 L Maximum HIC Capacity Stored 270 Containers (double stacked)

Table 3- Flammable Gas Generation Flammable Gas Flammable Gas Generation in the Generation in the Hydrogen Gas Storage Area at Storage Area at Generation Rate Maximum Maximum Dose Rates per container Capacity (270 Capacity (270 Cases HICs) per Hour HICs) per Year Expected Case 50 R/hr 9.0E-04 L/hr 0.24 L/hr] 2,129 L/yr Hot Container 100 R/hr 1.8E-03 L/hr 0.49 L/hr 4,257 L/yr Hot Container 300 R/hr 5.4E-03 L/hr 1.46 L/hr 12,772 L/yr Hot Container 500 R/hr 9.0E-03 L/hr 2.43 L/hr 21,287 L/yr As indicated in Table 3, the hydrogen gas volumes generated at LaSalle Station for 50 R/hr, 100 R/hr, 300 R/hr, and 500 R/hr containers are 0.24 L/hr, 0.49 L/hr, 1.46 L/hr, and Appendix B - Page 4 of 16

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 2.43 L/hr respectively. At maximum capacity, the total amount of gas generated is 2,129 L/yr, 4,257 L/yr, 12,772 L/yr, and 21,287 L/yr for the respective cases. See Figure 1.

Hydrogen Gas Generation Rate vs. Dose Rates 1.0E-02 Hydrogen Gas Generation Rate (L/hr) 9.0E-03 500, 9.0E-03 8.0E-03 7.0E-03 6.0E-03 300, 5.4E-03 5.0E-03 4.0E-03 3.0E-03 100, 1.8E-03 2.0E-03 1.0E-03 50, 9.0E-04 0.0E+00 0 100 200 300 400 500 600 Dose Rate (R/hr)

Figure 1 For the case where it is postulated that the ventilation system fails over a period of 6 weeks (42 days) during which operational maintenance is expected to be able to return the ventilation system back to normal, the hydrogen gas generation is evaluated to determine the flammable gas generation volumes in the entire storage bay. See Table 4 for detail.

Table 4- Flammable Gas Generation per 42 Days without Ventilation Hydrogen Gas Time Period Generation without Operational Hydrogen Gas at Maximum Ventilation Generation per HIC Capacity (270 Cases Dose Rates System in 42 days HICs)

Expected Case 50 R/hr 42 day 0.91 L/container 245 L Hot Container 100 R/hr 42 day 1.81 L/container 490 L Hot Container 300 R/hr 42 day 5.44 L/container 1,470 L Hot Container 500 R/hr 42 day 9.07 L/container 2,449 L Appendix B - Page 5 of 16

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Assuming the HICs are stored without proper ventilation for a period of 42 days, the expected hydrogen generation volume per HIC would be about 0.91 liters, 1.81 liters, 5.44 liters, and 9.07 liters according to the containers dose rates. If 270 HICs are stored for 42 days, the amount of gas generation volume is 245 liters, 490 liters, 1,470 liters and 2,449 liters, respectively.

For the maximum hot container case (500 R/hr), at maximum capacity (270 containers),

the hydrogen concentration would be well below the hydrogen flammability limits at about 0.03% of the storage bay volume (see Section 1.2.5). It is not expected that the ventilation system would be out of service for as long as 42 days.

1.1.4. Flammability Risk Analysis Due to flammable gas generated internal to the container and vented into the IRSF storage bay area, an evaluation of the potential buildup of combustible gases needs to be considered. NRC Information Notice. 84-72 stipulates that the hydrogen generated must be limited to a molar quantity no more than 5% by volume in the container gas void (or equivalent limits for other flammable gases). However, the NFPA hydrogen flammability rating is 4 (red), with an autoignition temperature of 1060oF (571oF). The Lower Flammability Limit (LFL) is 4.0% in air by volume; for administrative purposes, 2% will be considered the limit of hydrogen gas accumulated by total volume. In this case, FLF values in Table 5- Hydrogen Gas Explosivity Values are limits for the storage bay cell.

Table 5- Hydrogen Gas Explosivity Values Lower Flammability Limit (LFL) for Hydrogen 4  % 316,279 L Hydrogen Administrative Limit 2  % 109,730 L The building ventilation system should be in continuous operation to offset flammable gas concentration buildup. In case of a ventilation failure, the maximum period of time without venting before reaching the maximum flammability limits is determined below.

Table 6 evaluates the percentage hydrogen gas generation at maximum storage capacity per year, 270 double stacked containers, without any building ventilation credit. (Note, that even buildings without forced ventilation will experience air exchange rates on the order of 1 per day through doors, cracks, exhaust paths, etc.) In addition, the calculated time periods for storing the maximum capacity containers in the storage bay per dose rate case are given in this table.

Appendix B - Page 6 of 16

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Table 6- IRSF Hydrogen Gas Evaluation Duration of IRSF Hydrogen Gas Generation % Saturation w/

Volume per Hydrogen Gas (2%

Cases Dose Rates Year Admin Limit )

Expected Case 50 [R/hr] 0.0269  % 74 yr Hot Container 100 [R/hr] 0.0538  % 37 yr Hot Container 300 [R/hr] 0.1615  % 12 yr Hot Container 500 [R/hr] 0.2692  % 7 yr Based on the extended period of time (years) required to reach the administrative limit, and reasonable expectations on natural ventilation, it is not credible that flammable concentrations could accumulate in the LaSalle IRSF atmosphere due to hydrogen gas generation in and ventilation from stored radioactive material. Vents in storage containers (or shield bells) are required to alleviate in-container gas build-up.

Figure 2 depicts the gas generation % volume per year relationship to container dose rate graphically.

Hydrogen Gas Accumulation per Year 0.30 Hydrogen Gas Accumulated in 500, 0.2692 0.25 0.20 300, 0.1615 0.15 the Storage Area per year (%)

0.10 0.05 100, 0.0538 50, 0.0269 0.00 0 100 200 300 400 500 600 Dose Rates (R/hr)

Figure 2 Appendix B - Page 7 of 16

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 1.1.5. Hydrogen Gas Pocket Assessment The analysis of flammable gas generation indicates that projected hydrogen gas releases will NOT reach the administrative 2% concentration limit even for extended periods without ventilation system operation. Hydrogen gas pockets could only be generated if large quantities of hydrogen are rapidly released and if the hydrogen is not evenly mixed.

This is not considered credible.

In the expected case, 9.0 x10-3 L/hr per HIC (for the maximum dose rate container case) is slowly released. The hydrogen gas is expected to diffuse and be evenly mixed in the open storage bay air, so no segregation into pockets of the hydrogen is expected to occur.

Additionally, the LaSalle ventilation system has ten (10) air vent vertical discharges of 1,662 cfm each. With adequate air circulation, hydrogen will be well mixed in the present medium, so no hydrogen concentrations will be further diluted.

1.1.6. Gas Generation Rates from Biodegradation and Chemical Reaction Regarding the special case of methane evolution due to organic material experiencing bacterial activity, NRC Information Notice 90-50 recommends that the stations control methane generation at the source and minimize microbiological-contaminated compounds in the Radwaste system, followed by prevention of microbiological recontamination. Exelon Chemistry Department has endorsed these recommendations and has a Procedure in effect to minimize biological contamination in the waste streams.

Radwaste containing reactive components will not be authorized for IRSF storage until their relative components are removed or neutralized in accordance with the Exelon approved Process Control Program, as per reference [2].

1.2. Conclusion Flammable gas generation in the LaSalle IRSF storage bay for the proposed waste forms even at maximum theoretical container quantities and dose rate is not of concern as long as the containers (and shield bells, if used) are adequately vented. This conclusion holds even without storage bay forced air ventilation in operation for extended periods.

Appendix B - Page 8 of 16

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 1.3.

References:

1. Exelon IRSF Extended Storage Issues Report Report-Draft, email from Don Gardner, to Howard James, CC. Paul Reichert, Ed Taylor, Robert Murr, and Irving Tsang on Friday 9/12/2008.

2. Transmittal of LaSalle On-Site Review, Independent Review Director, D.J.Ray, Station Manager, 7/20/94

3. Waste Containers for Extended Storage of Class A, Class B and C, Rev1, EPRI, Dec 6, 2006.

4. Effects of Radiation on Materials: Twelfth International Symposium, Radiation Effects on Resins and Zeolites at Three Mile Island Unit II, J.K. Reilly, P.J. Grant, G.J. Quinn, T.C. Runion, K.J. Hofstetter, ASTM, 1985

5. Hydrogen Material Safety Data Sheet, Airgas, document #001026 Appendix B - Page 9 of 16

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Attachment A - HIC Drawing Appendix B - Page 10 of 16

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Attachment B - Radwaste Summary of Waste Sample Appendix B - Page 11 of 16

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Attachment C - LaSalle IRSF Dimensions Appendix B - Page 12 of 16

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Attachment D - Hydrogen Gas Generation Calculation Excel Spreadsheet, Rev 0 Note:

The values determined in this analysis were calculated using a MicrosoftTM ExcelTM spreadsheet, and are calculated to a greater number of significant figures than presented in this document.

Appendix B - Page 13 of 16

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Appendix B - Page 14 of 16

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Attachment E - Hydrogen Gas Generation Calculation Excel Spreadsheet Formulas, Rev 0 Appendix B - Page 15 of 16

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Appendix B - Page 16 of 16

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 APPENDIX C HDPE (POLY) HIGH INTEGRITY CONTAINERS (HIC)

CONTAINER INTEGRITY ASSESSMENT Appendix C - Page 1 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Historical Background On March 1989 the United States Nuclear Regulatory Commission (NRC) issued Information Notice (IN) 89-27, Limitations on the use of Waste Forms and High Integrity Containers for the Disposal of Low-Level Radioactive Waste following the review of various vendors Topical Reports (TRs) on HICs. The NRC staff concluded that High Density Polyethylene (HDPE) did not satisfy the requirements for waste form stability in accordance with 10 CFR Part 61, Licensing Requirements for Land Disposal of Radioactive Waste and the subsequent Branch Technical Position Paper on waste form, unless special provisions are made at the disposal site. As a result the NRC did not approve HDPE containers as HICs for the disposal of Low-Level Radioactive Waste (LLRW). The special provision cited here involves placement of the HDPE containers in concrete overpacks for burial. In this burial configuration the concrete overpack is the HIC not the HDPE container. The NRC did not approve HDPE containers as HICs due to concerns relating to container integrity for a period of 10 half lives of the longest lived significant isotope which equates to 300 years for resin waste. In resin waste, the predominant isotope is Cs-137 with a half life of 30 years. This concern was substantiated by several studies conducted in the 1980s by Brookhaven National Laboratory (BNL) for the NRC (see Section 2.0 of this report). In essence multiple BNL studies concluded that HDPE materials displayed a susceptibility to crack formation due to exposure to oxygen, and increased cross-linking leading to embrittlement after prolonged exposure to gamma radiation.

Since the closure of the Barnwell, SC commercial low-level radioactive waste disposal site to non-compact members in July 1, 2008; thirty six (36) states, the District of Columbia, the Commonwealth of Puerto Rico and the U.S. Territories are unable to ship Class B and Class C wastes to a disposal site. Class A waste can still be disposed of at the Envirocare, Clive Utah site. Extended storage of LLRW at onsite Radwaste storage facilities is now the only available option for non-compact LLRW generators. The NRC position on HDPE as HICs is problematic for extended storage of HICs in air before ultimate disposal. The use of concrete overpacks for each HIC in an on-site storage facility is not a feasible option due to cost and space constraints. Therefore the service life for HDPE containers for storage in air must be estimated to determine how long the container will maintain its physical integrity under site specific storage conditions before the onset of material degradation effects.

Appendix C - Page 2 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 1.0 Introduction Exelon Corporation (Exelon) has full or majority ownership of eleven (11) nuclear power plants, all of which (except for Oyster Creek located in New Jersey) are affected by the closure of the Barnwell disposal site. New Jersey, Connecticut and South Carolina are members of the Atlantic Interstate Low-Level Radioactive Waste Management Compact. Exelon has an immediate need to utilize its existing interim Radwaste storage facility (IRSF) at LaSalle (Illinois) for extended storage of Class B and C LLRW generated at its Byron, Braidwood, and Clinton Stations. Exelon plans to use Energy Solutions (ES) stackable-grapple compatible HDPE 8-120B containers for storage of Class B/C LLRW.

Exelon has requested that URS Washington Division conduct an assessment of the service life of HDPE containers when used as HICs for extended storage in air.

The ultimate objective of this assessment is to determine whether HDPE containers exposed to air, gamma radiation and stacking stresses under storage conditions will maintain their physical integrity for the duration of the extended storage period and will not rupture when subjected to handling for transportation to a future disposal site. The NRC does not give a time frame for extended storage. Exelon has defined extended storage as life of plant plus 40 years which is established as 80 years.

Appendix C - Page 3 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 2.0 Summary of Concerns Brookhaven National Laboratory HDPE Study Results The NRC commissioned BNL to perform a series of tests to investigate the effects of chemical environments on the mechanical properties of HDPE. BNL produced several publications on this subject all of which had essentially the same conclusion. For brevity this assessment will focus on BNL-NUREG-52196 (Reference 1) because the testing conducted in this study represents typical site specific conditions to which HDPE containers will be exposed during extended storage at LaSalle IRSF. BNL contends that an oxidized layer (about 5 microns) is introduced to the internal surface of HDPE material during the high temperature (300oC) rotational molding process making it prone to crack initiation under relatively low stresses. U-bend samples from as-received HDPE container material exhibited this phenomenon. BNL conducted U-bend tests on as-received container materials to observe the effects of chemical environments on polymer material properties. The U-bend samples were segregated into three groups as follows:

x Type I - as-received HDPE material with oxidized surface intact, which had natural cracks present due to bending into U-bend configuration.

x Type II - same as Type I material but with 0.010 inch of the oxidized surface removed with fine abrasive paper prior to bending. No cracks were seen after bending.

x Type III - as-received, non-oxidized HDPE material (that is the surface in contact with the mold during the manufacturing process which does not get oxidized). No cracks were seen after bending.

This study concluded based on the test results, that exposure to atmospheric oxygen occurring simultaneously with gamma radiation exacerbates the propagation and nucleation of natural cracks present in oxidized HDPE material resulting in an eventual loss of ductility. This study also concluded that the onset of failure/rupture of HDPE containers will be increased by the rate of creep due to application of high stresses in these environments.

BNL U-bend Test Results for exposure to atmospheric oxygen Since oxygen is known to be detrimental to HDPE properties, BNL performed U-bend tests in air, deionized water (DIW), Nitrogen (N2) and vacuum (oxygen-free) environments at 20oC (68 oF) using 1/8 inch thick samples cut from the walls of as-received HDPE rotationally-molded drums. The test was conducted in two cycles, the first lasting a period of 227 days and the second cycle for an additional 210 days, for a total of 437 days. Neither the width nor the depth of cracks was quantified in this study. Large cracks were classified as cracks with lengths measuring greater than 1/4 inch and small cracks were classified as cracks with lengths less than 1/4 inch. Table 1 and Table 2 from the study provide a summary Appendix C - Page 4 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 of the test results. BNL concluded from these results that specimens tested in air, water and nitrogen give larger crack growth rates than those for the vacuum. The abundance of oxygen was identified as the most likely reason for this enhanced cracking.

Table 1: Cracking in Type I HDPE U-bend specimens exposed for 227 d to various test environments at room temperature.(1).

(Table 1 extracted from BNL HDPE study Reference 1)

Environment Cracks Before Exposure Cracks After Exposure Percent Change in Number of Cracks Large Small Total Large Small Total Large Small Total Air 48 58 106 70 63 133 45.8 8.6 25.5 DIW 41 48 89 69 50 119 68.3 4.2 33.7 N2 44 34 78 63 36 99 43.2 5.9 26.9 (2)

Vacuum 58 52 110 80 46 126 37.9 -11.5 14.6 Notes:

1. The numbers of cracks are the totals counted for each batch of 8 replicate specimens.

2. Vacuum not maintained throughout test period.

Table 2: Cracking in Type I HDPE U-bend specimens exposed for 437 d to various test environments at room temperature.(1)

(Table 2 extracted from BNL HDPE study Reference 1)

Environment Cracks Before Exposure Cracks After Exposure Percent Change in Number of Cracks Large Small Total Large Small Total Large Small Total Air 48 58 106 85 51 136 77.1 -12.1 28.3 DIW 41 48 89 79 45 124 68.3 -6.3 39.3 N2 44 34 78 67 36 103 52.3 +5.9 32.1 Vacuum(2) 58 52 110 87 42 129 50.0 -19.2 17.3 Notes:

1. The numbers of cracks are the totals counted for each batch of 8 replicate specimens.

2. Vacuum maintained throughout the second test period of 210 d.

BNL U-bend Test Results for exposure to gamma radiation BNL conducted two different sets of U-bend tests for gamma irradiation utilizing Co-60. Eight 1/8 inch thick large specimens (10L x 1W) were prepared for scoping tests on irradiation embrittlement. Table 3 summarizes observations made on the large U-bend specimens. A second 1/8 thick U-bend sample (4L x 0.5W) was prepared and separated into Type I, Type II and Type III samples as Appendix C - Page 5 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 described above. These samples were subjected to gamma radiation environments for a duration of 350 days for the first cycle and for an additional 180 days for the second cycle for a total of 530 days, at a temperature of 10oC (50oF) to determine crack propagation effects for three gamma dose rates of 1.4 x 103 rad/hr, 8.4 x 104 rad/hr and 4.4 x 105 rad/hr in air. A set of unirradiated control samples were stored in a refrigerator at 10oC (50 oF). Type I test results are summarized in Table 4 (first cycle) and Table 5 (second cycle). For the first irradiation cycle all irradiated specimens showed a larger increase in the numbers of cracks compared to unirradiated specimens. After the second irradiation cycle the largest numbers of new cracks were found in unirradiated material; the irradiated samples showed no new crack initiations. Type II and Type III sample results were not summarized in a table for this study, but these samples generally displayed less numerous and fine cracks compared to Type I samples. This was attributed to the fact that the oxidized layer introduced into the samples from the manufacturing process, was removed in the Type II samples, and was not present in the Type III samples.

BNL concluded from these findings that, overall, gamma irradiation in air led to rapid growth in both small and large crack densities (Table 3). Low and intermediate dose rates give the larger cracking effects (due to the number of full penetration cracks at these rates, (see Table 4 and Table 5), and the lack of new crack initiations at low and intermediate doses may be a result of stress relaxation in the irradiated U-bend samples caused by polymer chain scission mechanisms.

Table 3: Observations on Marlex CL-100 HDPE U-bend specimens exposed to gamma radiation (Table 3 extracted from BNL HDPE study Reference 1)

Dose (rad) Dose Rate (rad/h) 3 3.4 x 10 5.6 x 104 2.1 x 106 4.9 x 106 Cracks appear to grow. Specimen color is light brown -

1.6 x 107 Cracks definitely growing. - -

Specimen color is tan.

2.0 x 107 One crack propagated through - -

specimen 2.9 x 107 Little additional crack - -

propagation. Specimen still flexible.

3.6 x 107 Large crack at apex still - -

propagating. Another crack also growing rapidly. Both cracks almost full penetration.

Specimens have slight odor.

9.9 x 107 (a) - Specimen color dark brown Appendix C - Page 6 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 1.6 x 108 (a) Specimen color medium -

brown. One crack growing.

3.2 x 108 (a) Several cracks growing in -

size 5.9 x 108 (a) Noticeable crack growth in -

both specimens. Cracks about 50% through thickness of specimen.

1.2 x 109 (a) (a) Specimen becoming sticky.

Small shiny areas developing.

2.9 x 109 (a) (a) Specimen very sticky, brown/black color. Strong aroma noticed.

5.8 x 109 (a) (a) Small surface bubbles form on original shiny areas.

8.8 x 109 (a) (a) Many bubbles now seen on surface. Specimen black.

1.7 x 1010 (a) (a) Tests terminated. Specimens completely brittle, no longer sticky.

(a) Dose not yet reached.

Table 4: Crack initiation and propagation in Type I HDPE U-bend specimens after the first gamma irradiation cycle(1)

(Table 4 extracted from BNL HDPE study Reference 1)

Irradiation Cracks Before Cracks After Percent Change in Numbers Full Near Irradiation Irradiation of Cracks Penet. Full Cracks Penet.

Dose Large Small Total Large Small Total Large Small Total Cracks 0 84 11 95 90 13 103 7 18 8 0 0 6

7.5 x 10 (at 1.4 x 81 3 84 97 3 100 20 0 19 2 1 103 R/h) 6.0 x 107 (at 8.4 x 78 2 80 95 4 99 22 100 24 2 4 104 R/h) 1.3 x 109 (at 4.4 x 69 3 72 82 4 86 19 33 19 0 1 105 R/h)

Note: (1) The numbers of cracks are the totals counted for each batch of eight replicate samples.

Appendix C - Page 7 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Table 5: Crack initiation and propagation in Type I HDPE U-bend specimens after the second gamma irradiation cycle(1)

(Table 5 extracted from BNL HDPE study Reference 1)

Irradiation Cracks Before Cracks After Irradiation Percent Change in Full Near Full Dose Irradiation Numbers of Cracks Penet. Penet.

Large Small Total Large Small Total Large Small Total Cracks Cracks Unirradiated 84 11 95 95 15 110 13 36 16 0 0 Controls 1.3 x 107 81 3 84 97 3 100 20 0 19 7 1 (at 1.4 x 103 R/h) 9.5 x 107 78 2 80 94 8 102 21 300 28 7 1 (at 8.4 x 104 R/h) 3.1 x 109 69 3 72 83 3 86 21 0 19 1 0 (at 4.4 x 105 R/h)

Note: (1) The numbers of cracks are the totals counted for each batch of eight replicate samples.

BNL Test for Creep effects BNL conducted creep tests on 1/8 inch thick samples at 20oC (68oF) using a simple constant load system. Strains were measured using Linearly Variable Differential Transducers (LVDTs). Figure 1 is a plot of test results for the different test environments. The graph depicts a linear relationship between applied stress and time. BNL concluded that if the stress levels in a waste container are kept significantly below 6.89 MPa (1,000 psi) then HDPE should be immune to a creep-type failure mode. Figure 2 from the creep test, shows the relationship between applied stress and ductility. BNL found that for samples which can be readily examined during the test, such as those exposed to air, fine cracks in the oxidized surface formed after about 20% (>8 MPa or 1,160 psi) elongation.

Irradiation during creep tests were also conducted in air at gamma dose rates of 5 x 103 rad/hr and 2 x 104 rad/hr. This BNL study concluded that irradiation causes increased cross-linking in HDPE and reduced creep rate at low dose during creep.

Appendix C - Page 8 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Figure 1: Stress-rupture results for Marlex CL-100 HDPE tested at 20oC in various environments (Figure 1 extracted from BNL HDPE study Reference 1)

Appendix C - Page 9 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Figure 2: Elongations at failure for Marlex CL-100 HDPE tested at 20oC in various environments (Figure 2 extracted from BNL HDPE study Reference 1)

Appendix C - Page 10 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 3.0 Discussion 3.1 Oxidation Effects on ES HDPE 8-120B Container The BNL-NUREG-52196 study shows that chemical aging takes place in the HDPE material eventually leading to a reduction in engineering properties, and that creep due to high stresses is a phenomenon that will lead to deformation in HDPE materials. The containers to be stored in LaSalles IRSF will be exposed to an environment of air and gamma radiation (beta radiation will accompany the gamma radiation, but the short range of betas effectively removes them from consideration here). The proposed IRSF storage configuration is to stack the containers atop each other two high. For this application, the chemical aging of the containers in storage is of primary concern and will be assessed in detail in this report. The effect of creep is considered as a secondary concern due to the intended arrangement of the proposed HDPE containers, as ES, the vendor of the stackable-grapple compatible HDPE 8-120B containers, attests that the design of the stackable lifting baskets in which the HDPE container is emplaced transfers the stresses due to stacking and lifting from the HDPE container to the steel basket, and then to the floor. This will be discussed in greater detail in Section 3.3 of this assessment.

Changes in HDPE material properties due to exposure to air and gamma radiation are inevitable. The challenge is to determine how these changes may be mitigated under IRSF-specific conditions and the resulting expected service life of the container in this facility. This assessment will consider mitigating factors such as (a) the addition of anti-oxidants in the polyethylene (PE) resin which retards the degradation effects of oxygen until the anti-oxidants are depleted, (b) the calculated actual total integrated dose (TID) expected in the IRSF over the maximum established 80 year storage period compared to the relatively high TID used in the BNL study which resulted in crack initiation, propagation and nucleation and (c) the thickness of the proposed HDPE container compared to the 1/8 inch sample specimen used in the BNL study.

Addition of anti-oxidants in PE resin The 8-120B HDPE container proposed for extended storage is manufactured from SCHULINK XL-350S-01G HDPE resin (see Attachment A for technical and material safety data sheets). This resin is a thermosetting plastic, meaning it can be cured, set or hardened into a permanent shape. The curing (rotational molding) process is an irreversible chemical reaction known as cross linking (see Figure 3, (d and e)). The finished cross linked product is a crystalline structure with increased density, tensile strength, and stiffness capable of withstanding higher temperatures.

Appendix C - Page 11 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Figure 3: Schematic of Cross-linked Polyethylene (Figure 3 extracted from Plastics Technology Handbook, Reference 12)

HDPE reacts with atmospheric oxygen resulting in oxidation, the effect of which is the breaking of bonds or chain scission in the polymer structure, eventually causing material degradation and failure. Polymers are formulated with anti-oxidants (AO) to prevent oxidation reactions from occurring. The XL-350S PE resin used to manufacture the 8-120B container, is formulated with an AO package (see Attachment B, for manufacturer confirmation of an AO package).

The AO package prevents oxidation by deactivating emerging free radicals and unstable intermediate products. In this deactivating process, the AO are consumed to the point where polymer oxidation can no longer be avoided. (M.C Cramez et al, Reference 13). The time to reach complete consumption of the AO package is the oxidation induction time (OIT). Thus, the effects of atmospheric oxygen on polymer material degradation are not a factor until the AO in the polymer structure are depleted.

Appendix C - Page 12 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 According to the Geo-synthetic Institute (GSI) which has performed numerous experimental and field studies on the service life of HDPE geo-membranes, the oxidation process involves three distinct stages (see Figure 4):

x Depletion time of antioxidants where no property changes occur x Induction time for oxidation to begin with minor property changes x Time to reach a specified reduction in the value of a significant engineering property, e.g. elongation, tensile strength, etc.

Figure 4: The Three conceptual stages of chemical aging of HDPE Geo-membranes (GMs)

(Figure 4 extracted from EPA geo-membrane study Reference 2)

Stage A - Anti-oxidants depletion time The length of time for anti-oxidants to deplete in a polymeric material is greatly dependent on its formulation which varies from manufacturer to manufacturer.

As a minimum the anti-oxidant package should contain primary category chemicals such as hindered phenols and hindered amine light stabilizers (HALS) and secondary category chemicals such as phosphites, sulfur compounds, HALS and thiosynergists; to ensure that the product is protected at both the high temperature rotational molding process and the lower temperature during its lifetime. To ensure long term service life, a manufacturer will use two or more types of anti-oxidants; typically one from a primary category and another from the secondary category. Figure 5 is a depiction of the effective temperature ranges of the different types of AO packages.

Appendix C - Page 13 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Figure 5: Effective temperature ranges of the four anti-oxidant types (Figure 5 extracted from EPA geo-membrane study Reference 2)

The chemical type, chemical name and percentage of AO in the XL-350S PE resin are proprietary information, but an indication of AO formulation can be determined from ASTM testing methods such as OIT. Two options are available to evaluate the AO depletion time they are the standard OIT test (STD-OIT) per ASTM D3895 and high pressure OIT test (HP-OIT) per ASTM D5885. Both tests are conducted using a differential scanning calorimeter (DSC). For the STD-OIT test the polymer sample is melted at room temperature to 200o C under a nitrogen atmosphere. When the 200o C is achieved the sample is maintained in an isothermal condition for 5 minutes, then the gas is switched from nitrogen to oxygen. The test is terminated when an exothermal peak is detected. The HP-OIT differs from the STD-OIT in temperature and pressure range only. For the HP-OIT test the polymer melt temperature is 150o C at a pressure of 5500 kPa as opposed to 35 kPa for the STD-OIT. The purpose of the difference in test temperatures is to compensate for the effective temperature ranges for HALS type AO formulation (see Figure 5), which will rapidly volatilize in a STD-OIT test, thereby giving a low OIT value which may not be indicative of the actual service life of the AO package. The purpose of the higher pressure is to compensate for the lower temperature at which the HP-OIT test is conducted which results in a long test duration at the standard 35 kPa pressure, therefore a higher pressure is applied for a practical test duration. Figure 6 is a typical thermal curve for both STD-OIT and HP-OIT.

Appendix C - Page 14 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Figure 6: Thermal Curve of OIT test (Figure 6 extracted from EPA geo-membrane study Reference 2)

From figure 6, the first (very large) downward peak is the melting of the HDPE sample (under nitrogen gas) due to the temperature going from room temperature up to 200°C or 150°C for STD-OIT and HP-OIT respectively. The second small peak is the replacement of nitrogen gas environment with oxygen gas. From this second peak onward the antioxidants (AOs) are protecting the resin from being consumed (i.e., oxidized) by the oxygen gas. Thus, the time frame from this second peak to where the curve begins to rise is the OIT-value, i.e., the time duration for the oxygen gas to consume the AOs and start degrading the resin.

The OIT time in minutes obtained from either test can be used to determine the AO depletion time in years in the resin formulation. GSI under the sponsorship of the United States Environmental Protection Agency (USEPA) conducted years of research on HDPE geo-membranes to determine the longevity of the material in in-situ applications, and a summary of their testing is presented in Reference 14.

Essentially GSI performed incubation testing of HDPE geo-membranes under various temperatures and pressures over a period of 24 months and the OIT test was performed on these incubated samples at specified intervals. The OIT depletion rate (min/month) was determined from this testing by plotting the natural log of OIT against the incubation time. Next, the OIT depletion rate is extrapolated to a site-specific temperature (from the experimental temperature) by using the Arrhenius equation. The Arrhenius equation is based on a time-temperature superposition principle. It uses high temperature incubation of the polymer material in question, followed by lab testing (in this case OIT), to extrapolate the incubation experimental behavior to a site-specific, and lower temperature. The assumption is that the materials behavior at the high incubation temperature (indicated by the materials activation energy) is constant within this range and can be extrapolated to the lower temperature behavior of interest.

Using this methodology, GSI calculated the AO depletion time on the geo-Appendix C - Page 15 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 membranes tested to be 200 years. GSI established, based on their studies, that 200 years of service life of geo-membranes equates to 100 minutes STD-OIT or 400 minutes HP-OIT.

A 6 inch square sample from a newly rotational molded 8-120B HDPE container was provided by Assmann Corporation (manufacturer of Energy Solutions 8-120B container) was tested for both STD-OIT and HP-OIT. Table 6 is a summary of the test results (Attachment H is the summary and computer output of ASTM D3895 and ASTM D5885 lab testing by TRI/Environmental Inc - a GSI certified laboratory).

Table 6: OIT test result for 8-120B HDPE Sample Parameter Test Replicate OIT Number (minutes)

STD-OIT (ASTM D3895) 1 17 HP-OIT (ASTM D5885) 1 303 The results give an indication that the AO formulation of the 8-120B HDPE container is of the HALS variety, since it produces a much shorter STD-OIT time.

The HP-OIT results will thus be used to determine the service life of the 8-120B HDPE container. Before establishing the AO depletion time in years based on above test results, it is important to understand that there are factors that may accelerate the otherwise slow process of AO depletion.

The depletion of anti-oxidants is a slow process and can be caused by two mechanisms, chemical reactions of the anti-oxidants and physical loss of anti-oxidants from the polymers by leaching (Koerner et al, Reference 2). The depletion of anti-oxidants due to chemical reactions is dependent on the chemical formulation of the product (the OIT results will give an indication of the package formulation). The depletion of anti-oxidants due to physical loss is a function of the anti-oxidants volatility and extractability. The volatility of anti-oxidants is a thermally activated process; wherein temperature changes affect the evaporation of the stabilizers from the polymer surface as well as its diffusion from the interior to the surface layer. For the proposed HDPE container the low temperature condition in the IRSF is expected to be nominally 75oF therefore volatility of anti-oxidants will not be a factor. Extractability of anti-oxidants becomes a factor if the proposed HDPE container comes into contact with liquids such as water. This is not a concern because the proposed HDPE container will contain dewatered resin beads. Dewatering removes all free standing water in the container to less than 1% by volume in accordance with NRC regulatory guidance (Generic Letter 81-38). All remaining water is absorbed, i.e., adsorbed in the resin beads or entrapped in the interstitial space between resin beads. Another Appendix C - Page 16 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 BNL study, BNL-NUREG-51841 (Reference 3), states that ion-exchange resins lose their ability to retain water and release free liquid at increased radiation dose.

For anion resin this phenomenon was seen at 3 x 108 Rads and for cation resin at 5 x 108 Rads. Dewatered ion-exchange resins to be stored in the LaSalle IRSF are not expected to ever see an accumulated dose greater than 108 Rads (see Section 3.2 for detailed gamma radiation discussion) for the maximum storage period of 80 years. Therefore the ion-exchange resins are not expected to lose their ability to retain water and release free liquid. Furthermore, Table 7 extracted from the Plastics Technology Handbook shows that the water absorption of polyethylene is less than 0.01% for a 1/8 inch (3.2 mm) sample tested. This indicates that polyethylene is fairly resistant to water absorption. In addition, the LaSalle IRSF is not equipped with a fire suppression system (i.e. sprinklers), so the containers will not be exposed to standing water resulting from a sprinkler system activation or malfunction. Based on the foregoing conditions, it can be concluded that the proposed HDPE container is not expected to be exposed to significant leaching effects of bulk free standing water, so extractability of anti-oxidants from the HDPE container is not expected to be significant.

Table 7: Assessment of Plastics and Rubbers Resistance (Extracted from Plastics Technology Handbook, Reference 12)

Appendix C - Page 17 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Based on GSIs GRI-GM 13 specification, Test Methods, Test Properties and Testing Frequency for High Density Polyethylene (HDPE) Smooth and Textured Geomembranes(Reference 15) it is established that 100 minutes STD-OIT equates to 200 years AO depletion time and 400 minutes HP-OIT equates to 200 years AO depletion time. As indicated from OIT test results of 8-120B HDPE sample, the AO formulation is of the HALS variety due to the higher OIT time for this test, therefore, the HP-OIT time will be used to calculate the AO depletion time in years. Assuming that the AO package for the 8-120B container responds similarly to the experimental samples used to create GRI-GM 13 specification, a linear scaling will suggest the following:

HP-OIT Results 303 min utes AO( years) (200 years) 152 years 400 min utes For conservatism the AO depletion time for the purpose of this study is established as 100 years per the recommendation of Dr. Koerner, Director GSI; to compensate for standard deviation in the test and site specific extended storage conditions. Dr. Koerner recommends additional testing such as UV and oven aging of the proposed 8-120B container sample to augment the OIT test results.

The only purpose of these additional tests will be to serve as additional indicators that the 8-120B AO package continues to behave in a manner similar to the AO packages of the experimental samples from which the GRI-GM13 specification was formulated (see Attachment D for correspondences with Dr. Koerner, establishing 100 years AO depletion time for 8-120B HDPE sample).

Stage B - Induction Time Once the AO is completely depleted, oxygen will begin to attack the polymer, leading to the induction time. PE resins manufactured without an AO package do not immediately begin to degrade or show signs of degradation. Instead studies have shown that an appreciable amount of time elapses before degradation of material properties due to oxidation effects is observed. It is impossible to determine the length of time after AO depletion that degradation due to oxidation occurs. Therefore, to be conservative, no credit is taken for stage B induction time.

Stage C - 50% Property Degradation This stage, by definition, represents the half-life or length of time for a HDPE material to reach 50% degradation in its engineering properties. The rate at which this stage occurs is dependent on factors such as temperature, chemical environments and stresses on the HDPE material. The proposed HDPE container Appendix C - Page 18 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 in the LaSalle IRSF will be exposed to atmospheric oxygen, gamma radiations, ambient temperature conditions, and low stacking stresses which are discussed in Sections 3.2 and 3.3.

3.2 Site Specific Gamma Irradiation Effects To quote Dr. Peter Soo the author of BNL-NUREG-52196, without atmospheric oxygen, gamma radiation is far less damaging to plastics (see Attachment C for email correspondence with Dr. Soo). This is in agreement with Parkinson and Sismans work (Reference 4), wherein they stated that the net result on the effect of oxygen on the rate of radiation damage appears to be predominantly an increase in scission rate when oxygen is present. It can be concluded then that the effects of gamma radiation on the proposed HDPE containers will not be a factor until after the anti-oxidants in the container material have been depleted and oxidation due to atmospheric oxygen begins to diffuse within the material. To assess how damaging gamma radiation will affect the proposed container properties, the TID over a period of 80 years must be calculated. To obtain this, a sample isotopic mix of waste generated at Exelons Peach Bottom Generating Station was used and is considered conservative. The isotopic mix comprised of more than typical short lived and long lived isotopes such as Ag-110m, Co-58, Co-60, Cs-134, Cs137/Ba137m, Mn-54, Nb-95, Sr-92 and Zn-65. Co-60 was the most important isotope in the mix but not completely dominant. The TID at 5 years is calculated to be 5 x 106 Rads and at 80 years to be 1.2 x 107 Rads at a dose rate of 241 rad/hr of which 109 rad/hr is from Co-60 (see Attachment E for calculation spreadsheet). Figure 7, is a graphical representation of calculated TID versus number of storage years.

From BNL gamma radiation testing (Table 3) it was observed that at 4.9 x 106 Rads cracks appear to grow and at 1.6 x 107 Rads cracks were definitely growing.

These two doses closely represent Exelon site expected actual dose at 5 years and 80 years respectively (Figure 7). It can be concluded based on Table 3 results that the proposed HDPE container in LaSalle IRSF will display growth in surface cracks within 5 years and will show signs of definite crack growth around 80 years. These cracks are not expected to propagate to failure since maximum IRSF TID at 80 years is 1.2 x 107 Rads, which is less than 5.9 x 108 Rads at which sample specimen in Table 3 displayed cracks propagating through 50% of the specimen thickness. Also the proposed HDPE container in the LaSalle IRSF will maintain its ductility throughout the 80 years storage period since the TID at 80 years is significantly less than the 1.2 x 109 Rads at which the 1/8 inch sample specimen from Table 3 starts to show signs of embrittlement.

The Polymer Volume 36 (Reference 13) documents a study on structural changes due to irradiation in the presence of air using infra-red spectroscopy on HDPE samples. The samples were irradiated by a Co-60 gamma ray source at room temperature in air. Doses up to 1.0 x 108 Rads at a dose rate of 4.72 x 105 Rads/hr Appendix C - Page 19 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 were used. The findings were as follows (a) at doses less than or equal to 1.0 x 107 Rads no formation of carboxylic groups (byproduct of oxidation) was detected and cross linking of the HDPE sample was the predominant effect of irradiation at this dose (b) at doses between 1.0 x 107 Rads to 2.0 x 107 Rads cross linking and degradation are the predominant phenomena and (c) for doses greater than 2.0 x 107 Rads oxidative degradation predominates which was evidenced by the increase in carboxylic groups. Applying the results from the infra-red spectroscopy results to LaSalle IRSF TID conditions it can be concluded that from 5 - 30 years (dose  1.0 x 107 Rads) the proposed HDPE container will primarily undergo low density cross linking as a result of gamma radiation. There will likely be some increase in tensile strength, density and stiffness, although the HDPE material is expected to maintain its ductility. The thickness of the container minimizes the rate of cross linking (this will be discussed further in material thickness section). Between 40 - 80 years no degradation of the material is expected to occur because the maximum TID at 80 years never equals or exceeds 2.0 x 107 Rads at which degradation predominates.

Effect of Radiation on Material Thickness Table 4 and Table 5 of BNL study also shows near full and full penetration cracks at low and intermediate doses. It is important to note that the specimen tested were 1/8 inch thick and bent into the U-bend configuration prior to gamma irradiation in air. It is assumed that the oxygen rich testing environment, together with the gamma dose and applied stress on the small, thin specimen may have been the cause of the full penetration cracks. In Parkinson and Sismans work (Reference 4) it is stated that the diffusion of oxygen into the polymer material will be limited to the surface for thicker specimen and may not affect the bulk properties of the material. Table 8 is extracted from Parkinson and Sismans work. It summarizes the effect of radiation on mechanical properties of plastics.

It shows that for the thicker HDPE material (Super Dylan) which is 0.12 inch (1/8) 80% - 100% of material strength and elongation properties are retained even at greater than 109 Rads exposure. For the 0.002 inch thick HDPE material (Marlex-50), only 50 -80% of strength and elongation properties are retained after 107 Rads exposure. This indicates a definite relationship with thickness and material degradation properties as a function of gamma dose. In addition the proposed HDPE containers are 1/2 inch thick cross-linked HDPE material which is denser than the linear HDPE material in this study, so it can be concluded that the rate of diffusion in this material will be significantly less aggressive to material bulk properties, thereby limiting crack propagation and penetration.

Parkinson and Sismans work is in agreement with the study documented in the Polymer Volume 36 (reference 13) in which the mechanical behavior of HDPE samples of various thicknesses (0.2 mm, 0.3 mm and 0.4 mm) were studied. The effects of gamma radiation on the samples were investigated using a modified dynamic resonance technique. It was found that the polymer chain cross linking Appendix C - Page 20 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 rate, as a result of irradiation by gamma ray doses up to 2.0 x 107 Rads depends on the sample thickness. The internal friction and stiffness of the HDPE samples were investigated under irradiation. It was found that at doses up to 2.0 x 107 the internal friction (the force resisting motion between the elements making up a solid material while it undergoes deformation) is lower. This was attributed to oxygen diffusing into the samples, with the thinner the samples, the greater the effect of oxygen, causing a greater number of chain scissions. The same phenomenon was discovered in the stiffness of the HDPE samples at the same dose. Oxygen diffusion was credited for the decrease in stiffness in the thinner samples, with a higher diffusion of oxygen into the thinner samples causing greater oxidative degradation, and reduction in samples stiffness. These results indicate that the thickness of HDPE material controls the oxygen diffusion process at low to intermediate doses.

Thus, based on the foregoing assessment, it can be concluded that following AO depletion in the HDPE container and the onset of atmospheric oxygen and gamma radiation degradation effects, the thickness of the proposed container will limit the diffusion of oxygen within the material at the calculated TID doses expected throughout the extended storage period. The material is expected to maintain greater than 80% of its mechanical properties over an extended period of time as indicated by Table 8.

Figure 7: Peach Bottom Accumulated Dose to Container during storage duration Accum ulated Dose to Container 11.78 12.01 12.2 13 11.48 11.09 12 10.53 Total Integrated Dose (Mrads) 11 9.56 10 9 7.38 8

7 6 5.01 5 Total Integrated Dose 4 Mrads 3

2 1

0 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 85 Storage Duration (yrs)

Appendix C - Page 21 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Table 8: Effects of Radiation on Mechanical Properties of Plastics (Irradiated in air at 25oC unless otherwise noted)

Appendix C - Page 22 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 3.3 Creep effects due to applied stresses Stresses due to Stacking The ES HDPE 8-120B container is enclosed in a steel basket configuration (see Attachment F), for stacking and lifting purposes. The steel basket is comprised of four 1 inch thick straps for wall support, four 1/4 inch thick straps for bracing at mid height of the container, four 1/4 inch thick straps for securing the base of the container, and one 1/4 inch thick rolled angle iron ring at the top for securing components into the basket configuration. The stacking arrangement of the basket is comprised of 3/8 inch thick rolled angle iron ring welded all around the top head of the basket and a 1/2 inch thick stacking plate with a 1/4 inch grapple ring welded to the plate for lifting of the stacking plate. The 3/8 inch angle ring doubles as a lifting arrangement when a grapple is used, otherwise lifting slings designed in accordance with ANSI B30.9 can be provided.

Prior to stacking the HDPE container, a stacking plate is placed between the bottom and top HDPE container assembly. All materials are constructed of ASTM A-36 carbon steel and all load bearing welds are full penetration welds.

All steel components are coated with zinc chromate primer and painted with a coat of industrial enamel. Any long term corrosion effects will also be picked up by the periodic video surveillance program. The HDPE container assemblies receive a polyurethane foamed flat top in the void space at the top of the dome head of the HDPE container and the top of the basket for stacking purposes (Reference 5).

ES attests that the design of the lifting basket isolates the HDPE container from service loads due to stacking, which are transferred to the steel basket uprights then to the floor. ES Calculation ST-098 Structural Evaluation of the Stackable-Grapple compatible HIC baskets (Reference 11) analyzes the stresses imposed on the basket as a result of stacking two (2) high. The maximum top load for stacking of the 8-120B is set at 13,500 lbs. Table 9 below summarizes the results of the analysis.

Appendix C - Page 23 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Table 9: Stress Evaluation Results for 8-120B Stackable-Grapple Basket (Extracted from Energy Solutions Structural Analysis ST-098)

Description Calculated Allowable Check Value Tensile Stress at weld 4,333 psi 11,610 psi 4,333 psi < 11,610 psi Bolt shear stress 10,105 psi 14,400 psi 10,105 psi < 14,400 psi Shear out of angle 6,368 psi 6,960 psi 6,368 psi < 6,960 psi Bending Stress of stacking plate 21,271 psi 36,000 psi 21,271 psi < 36,000 psi Deflection of Stacking plate 0.743 in 1.625 in 0.743 in < 1.625 in Critical buckling load under bolt 393,519 lb Critical buckling load in four (4) uprights 14,724 lb Buckling safety factor 4.4 3 4.4 > 3 Based on these results it can be concluded that the stacking plate and basket can withstand the maximum gross weight of a loaded 8-120B HDPE container stacked atop without failure while isolating the enclosed HDPE container from stacking loads.

Stresses due to container contents Since the ES HDPE container assembly design isolates the HDPE container from stresses due to stacking (see Table 9), it can be deduced that the only stresses imposed on the HDPE container will be internal stresses from the dewatered ion-exchange resin (hoop and meroidional stresses). Attachment G is a spread sheet computation of the hoop and meriodional stresses on the HDPE container as a result of the internal pressure of container contents. BNL concluded that if the stress levels in a waste container are kept significantly below 6.89 MPa (1,000 psi) then HDPE should be immune to a creep-type failure mode (Reference 1).

From Attachment G the Combined Principal Stress (hoop and meriodional) on the HDPE container resulting from internal pressure of contents is calculated to be 282 psi which is less than 1,000 psi. Therefore it can be concluded that the HDPE container should be immune to a creep type failure.

Appendix C - Page 24 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 4.0 Conclusions and Recommendations 4.1 General The NRC has not approved HDPE container as HICs for burial of LLRW due to concerns relating to container integrity for a 300 years period. This is due in part to studies performed by BNL under the auspices of the NRC. BNL-NUREG 52196 concluded that HDPE material is oxidized during the high temperature rotational molding process and that the oxidized layer formed from this process is susceptible to crack formation and propagation at relatively low stresses and that exposure of HDPE to chemical environments such as air and gamma radiation exacerbates cracking which may lead to failure. This assessment takes into consideration mitigating factors such as the addition of anti-oxidants in the polyethylene formulation, the thickness of the proposed HDPE container, and the calculated low total accumulated dose rate expected over the extended storage period.

4.2 Anti-oxidants Effects Studies have shown that anti-oxidants added to polyethylene formulation retard the effect of oxidation in the polymer structure until the anti-oxidants are depleted, thereby increasing the service life of the container. The HP-OIT test results for the proposed 8-120B HDPE container is 303 minutes which is equivalent to 152 years AO depletion time. To allow for standard deviation in testing and the effects of site-specific conditions on the 8-120B HDPE container, the AO depletion time is established as at least 100 years.

With the effects of oxidative environment subverted by anti-oxidants, oxygen atoms are unable to interact with free radicals generated by the radiation field (Reference 1). Therefore gamma radiation effects are minimized without oxygen as a catalyst. This is shown in Table 4 and 5 of this assessment where the largest number of new cracks initiation were found in the second cycle of unirradiated controls exposed to air. No new crack initiations were found in the irradiated samples during the second cycle. This is evidence that gamma radiation alone does not exhibit accelerated crack initiation rate.

Table 5 also show cracks propagating to failure at intermediate doses which are similar to accumulated dose calculated at the end of the extended storage period (see Figure 7). It is concluded based on Table 8 extracted from Parkinson and Sismans work (Reference 4) that thicker HDPE material is fairly resistant to gamma radiation and will maintain 80% - 100% of its material properties at >109 Rads. This is in agreement with the dynamic resonance technique testing of HDPE materials documented in Reference 13. It was concluded in this study that at low to intermediate doses polymer chain degradation depends on the sample Appendix C - Page 25 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 thickness, with thinner samples exhibiting a higher oxygen diffusion rate causing a greater number of chain scission and reduction in material stiffness.

4.3 Creep Effects Creep effect is not a concern for HDPE container storage in air. The design of the HDPE container assembly isolates the HDPE container from service loads due to stacking and lifting. Table 9 of this assessment is a result summary from ES structural analysis ST-098. The stresses due to stacking and lifting are transferred to the basket assembly. The calculated stresses are less than the allowable stresses for tensile, shear, bending, deflection and buckling. The hoop and meriodional stresses on the HDPE container from internal pressure of container contents is calculated to be 282 psi (see Attachment G) which is less than 1,000 psi (6.89 MPa) making the HDPE container material immune to creep type failure.

4.4 Expected Service Lifetime of ES 8-120B HDPE HIC The life cycle of HDPE material includes three stages (a) AO depletion time, (b) induction and (c) half-life or material properties degradation. The AO depletion time can be derived from either STD-OIT or HP-OIT test results. For this assessment the HP-OIT test result is used to obtain an AO depletion time of at least 100 years for the ES 8-120B HDPE container sample tested. The induction stage is the period immediately following the complete consumption of the AO package. This period lasts an appreciable amount of time dependending on several factors. It is difficult to assign a time frame for this period due to lack of field experimentation in this area. Any amount of years assigned to this period will be based on intuitive engineering judgment; therefore URS Washington Division has not included an induction stage lifetime for this assessment. The material degradation is the final life cycle stage for HDPE material. Again this stage lasts an appreciable amount of time based on chemical makeup of the material and the physical conditions affecting the materials mechanical properties. URS Washington Division believes that the thickness of the ES 8-120B HDPE container, coupled with the low TID expected in LaSalles IRSF, will minimize the rate of oxygen diffusion into the HDPE material. This belief is supported by recent dynamic resonance technique studies which show that HDPE material thickness controls oxygen diffusion, with thinner material displaying a higher susceptibility to oxygen diffusion within the material structure. Thus, URS Washington Division, with the support of Dr. Koerners assessment of HP-OIT test results, has determined that the estimated overall lifetime for ES 8-120B HDPE containers in air for extended storage inside an ambient temperature storage bay is at least 100 years. This lifetime is based only on AO depletion time since no credit is taken for induction and material degradation life cycle stages.

Appendix C - Page 26 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 4.5 Recommendations It is recommended per Dr. Koerner that additional testing such as oven aging and UV resistance testing be conducted on ES 8-120B HDPE container coupons to augment initial HP-OIT test results. Oven aging and UV resistance testing will give an indication of the percentage of OIT remaining after material exposure to this test environment. In accordance with GSIs GRI-GM13 specification, for HP-OIT following oven aging and UV exposure, the amount of OIT remaining in the HDPE sample tested shall be in the range of 80% and 50% for oven aging and UV, respectively. That is, if after oven aging the HP-OIT value is 242 minutes (80% of initial HP-OIT of 303 minutes), and 152 minutes (50% of initial HP-OIT) after UV exposure, then it can be stated with a greater degree of certainty that the AO depletion time of ES 8-120B HDPE container equates to 152 years (see HP-OIT calculation).

Appendix C - Page 27 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 5.0 References

1. Soo, P. et al., A Study of the Use of Crosslinked High-Density Polyethylene for Low-Level Radioactive Waste Containers. BNL-NUREG-52196 (June 1989).

2. Koerner, Robert et al., Assessment and Recommendations for Improving the Performance of Waste Containment Systems. EPA/600/R-02/099 (December 2002).

3. Siskind, B et al., Extended Storage of Low-Level Radioactive Waste:

Potential Problem Areas. BNL-NUREG-51841 (December 1985).

4. Parkinson, W., and O. Sisman, The Use of Plastics and Elastomers in Nuclear Radiation. October 19, 1970.

5. Chem-Nuclear Systems, Inc., Topical Report: Polyethylene High Integrity Containers. CNSI-HIC-14571-01-NP. December 23, 1983.

6. Soo, P. et al., The Effects of Environment and Gamma Irradiation on the Mechanical Properties of High Density Polyethylene. Topical Report BNL-NUREG-51991. March 1986.

7. Dougherty, D. R., J.W. Adams, Radiation Resistance Testing of High-Density Polyethylene. BNL-NUREG-33641.

8. Soo, P, Effects of Chemical and Gamma Irradiation Environments on the Mechanical Properties of High-Density Polyethylene (HDPE). BNL-NUREG-40842.

9. International Atomic Energy Agency (IAEA), Development of Specifications for Radioactive Waste Packages. IAEA-TECDOC-1515. October 2006.

10. Nuclear Regulatory Commission (NRC), Information Notice No. 89-27:

Limitations on the use of Waste Forms and High Integrity Containers for the Disposal of Low-Level Radioactive Waste. March 8, 1989.

11. ST-098, Structural Evaluation of Stackable, Grapple Compatible HIC Baskets Revision 1. January 7, 1993.

12. Manas Chanda, Salil K. Roy, Plastics Technology Handbook (Plastics Engineering , Vol 47).

13. A.M Shaban, N. Kinawy, Polymer Vol.36 No. 25, pp 4767 - 4770, 1995, Crosslinking rate dependence on the thickness of high-density polyethylene sheets after gamma-ray irradiation in the presence of air.

14. Y. G. Hsuan and R. M. Koerner, Journal of Geotechnical and Geoenvironmental Engineering / JUNE 1998: Antioxidant Depletion Lifetime in High Density Polyethylene Geomembranes.

Appendix C - Page 28 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09

15. GRI Test Method GM13:Test Methods, Test Properties and Testing Frequency for High Density Polyethylene (HDPE) Smooth and Textured Geomembranes Revision 9, June 2009.

Appendix C - Page 29 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Attachment A Appendix C - Page 30 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Attachment A (Contd)

Appendix C - Page 31 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Attachment A (Contd)

Appendix C - Page 32 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Attachment A (Contd)

Appendix C - Page 33 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Attachment A (Contd)

Appendix C - Page 34 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Attachment B- Schulman Email Correspondence Appendix C - Page 35 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Attachment C -Dr. Peter Soo Expert Opinion Correspondences Appendix C - Page 36 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Attachment C (Contd)

Appendix C - Page 37 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Attachment C (Contd)

Appendix C - Page 38 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Attachment D - Dr. Robert Koerner Geo-membrane Expert Opinion Email Correspondence Appendix C - Page 39 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Attachment D (Contd)

Appendix C - Page 40 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Attachment E-Peach Bottom Generating Station Isotopic Mix TID Calculation Input Values:

A B C D E F G H I J K 1 Test of accumulated dose to container, using a PBAPS isotopic mix 2 ignores beta because of short range 3 80 storage duration (years) 4 5 Ag110m Co58 Co60 Cs134 Cs137/Ba137m Mn-54 Nb-95 Sr-92 Zn-65 Isotope Total 6 3.671 3.273 109.2 27.86 11.76 1.816 0.575 38.89 43.96 initial contact dose rate (rads/hr) 241.0 7 6.842E-01 1.938E-01 5.271E+00 2.062E+00 3.000E+01 8.556E-01 9.624E-02 3.091E-04 6.678E-01 half-life (years) 8 1.156E-04 4.079E-04 1.500E-05 3.835E-05 2.636E-06 9.242E-05 8.217E-04 2.558E-01 1.184E-04 decay constant (1/hours) 9 3.18E-02 8.02E-03 7.28E+00 7.27E-01 3.76E+00 1.96E-02 7.00E-04 1.52E-04 3.71E-01 accumulated dose (Mrads) 12.20 10 0.3% 0.1% 59.7% 6.0% 30.8% 0.2% 0.0% 0.0% 3.0% percent of accumulated dose 11 12 13 MicroShield Results (mR/hr), isotopic effects 1092 14 241 All 15 131.8 Less Co-60 109.2 16 87.84 Less Zn-65 43.96 17 48.95 Less Sr-92 38.89 18 21.09 Less Cs-134 27.86 19 9.335 Less Cs-137 11.755 20 6.062 Less Co-58 3.273 21 2.391 Less Ag-110m 3.671 22 0.5747 Less Mn-54 1.8163 23 Nb-95 only Appendix C - Page 41 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Attachment F - Typical HDPE Container Lifting Basket Appendix C - Page 42 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Attachment G - Effect of Internal Stresses on ES 8-120B HDPE Container 1 Objective and Introduction The main objective of this spreadsheet computation is to perform analysis of unconstrained stress on the walls and bottom of the 8-120B HDPE HIC container due to the internal pressure of dewatered resin beads. The results will determine whether the container could be susceptible to a creep type failure over an extended period of time.

Specific items to be calculated and/or derived include:

Pressure at base of container Meriodional stress Hoop stress 2 Inputs The 8-120B container input data is taken from Reference 1 and is shown on Table 1.

Table 1 120B Container Dimensions Liner Diameter Radius Height Thickness (inches) (inches) (inches) (inches) 8-120B 61.5 30.75 73.5 0.5 3 Assumptions The density of the dewatered resin 72.0 lb/ft3 The density of water 62.4 lb/ft3 Pressure at which HDPE should be immune to a creep-type failure  1,000 psi This is based on creep tests on 1/8 inch thick HDPE samples using a simple constant load system. Strains were measured using Linearly Variable Differential Transducers (LVDTs).

This testing was performed by Brookhaven National Laboratory (BNL) for the Nuclear Regulatory Commission (NRC) (Reference 2).

Application of the BNL creep test results for 1/8 inch sample coupons to 1/2 inch 8-120B HDPE HIC is conservative.

The pressure at the base of the container is assumed to be the most limiting case.

Unless otherwise noted the formulas used in this calculation are derived from Roark's Formulas for Stress and Strain, Seventh Edition.

4 Methodology This calculation was performed using a MicrosoftTM ExcelTM spreadsheet. The equations are simple stress and pressure calculations as described below and are used to calculate the meriodional stress and hoop stress on the 8-120B container.

Appendix C - Page 43 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 5 Calculation Pressure The pressure at the bottom of the 8-120B container is considered to be the most limiting case. Using the density of water = 62.4 lb/ft3 (0.036 lb/in3) the pressure is calculated as:

Pbottom = U water u H Where:

P= Pressure, (psi)

U = Density, lb/ft3 H = Height, (in)

Pbottom = U water u H = 0.036lb / ft 3 u 73.5in 2.65 psi U re sin 72lb / ft 3 Correction factor = = 1.15 U water 62.4lb / ft 3 Pbottom = 1.15 u 2.65 psi 3.05 psi Meriodional Stress The equation for calculating the meriodional stress on the 8-120B container is:

Pbottom R V1 2t Where:

V 1 = Meroidional Stress (psi)

R= Radius, (in) t= Thickness, (in) 3.05lb / in 2 u 30.75in V1 94 psi 2 u 0.5in Appendix C - Page 44 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Hoop Stress The equation for calculating the hoop stress on the 8-120B container is:

Pbottom R V2 t

Where:

V 2 = Hoop Stress (psi) 3.05lb / in 2 u 30.75in V2 188 psi 0.5in Combined Principal Stress The Combined Principal Stress V T is the sum of V 1 and V 2 :

VT 94 psi  188 psi 282 psi 6 Summary of Results The results are summarized in Table 2. The combined stresses (hoop and meriodional) acting on the 8-120B container as a result of internal pressure is 282 psi. It can be concluded based on this result that since the combined stresses 282 psi is less than 1000 psi, the 8-120B container will be immune to a creep type failure.

Table 2 Result Summary Calculation Value Allowable (psi) (psi)

Pressure (P) 3.05 Meriodional Stress ( V 1 ) 94 Hoop Stress ( V 2 ) 188 Combined Principal Stress 282 < 1,000 psi OK (V T )

Appendix C - Page 45 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 7 References

[1] EPRI Report 1007863, Waste Containers for Extended Storage of Class A, B and C Wastes, Revision 1, August 2003.

[2] P Soo, et al, NUREG/CR-5363 (BNL-NUREG-52196), A Study of the Use of Crosslinked High-Density Polyethylene for Low-Level Radioactive Waste Containers, June 1989.

Appendix C - Page 46 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 - Excel Spreadsheet Input Values:

A B 1 Pressure Calculation 3

2 Density of Water (lb/in ) 0.03611 3

3 Density of Resin (lb/in ) 0.04167 4 Height (in) 73.5 5 Correction Factor (resin/water) 1.15385 6 Pressure (psi) 3.06 7

8 Meriodional Stress Calculation 9 Pressure 3.06 10 Radius (in) 30.75 11 Thickness (in) 0.5 12 Meriodional Stress 1, (psi) 94.17 13 14 Hoop Stress Calculation 15 Pressure 3.06 16 Radius (in) 30.75 17 Thickness (in) 0.5 18 Hoop Stress 2, (psi) 188.34 19 20 Combined Principal Stress Calculation 21 Meriodional Stress 1, (psi) 94.17 22 Hoop Stress 2, (psi) 188.34 23 Combined Principal Stress (psi) 283 Appendix C - Page 47 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Formulas:

A B 1 Pressure Calculation 3

2 Density of Water (lb/in ) =62.4*(1/12)^3 3

3 Density of Resin (lb/in ) =72*(1/12)^3 4 Height (in) 73.5 5 Correction Factor (resin/water) =B3/B2 6 Pressure (psi) =B5*(B2*B4) 7 8 Meriodional Stress Calculation 9 Pressure =B6 10 Radius (in) 30.75 11 Thickness (in) 0.5 12 Meriodional Stress 1, (psi) =(B9*B10)/(2*B11) 13 14 Hoop Stress Calculation 15 Pressure =B6 16 Radius (in) 30.75 17 Thickness (in) 0.5 18 Hoop Stress 2, (psi) =(B15*B16)/B17 19 20 Combined Principal Stress Calculation 21 Meriodional Stress 1, (psi) =B12 22 Hoop Stress 2, (psi) =B18 23 Combined Principal Stress (psi) =B21+B22 Appendix C - Page 48 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Attachment H: TRI/Environmental Labs Standard OIT (ASTM D3895) and HP OIT (ASTM D5885) Test Results Appendix C - Page 49 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Attachment H (Contd)

Appendix C - Page 50 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Appendix C - Page 51 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Attachment H (Contd)

Appendix C - Page 52 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Attachment H (Contd)

Appendix C - Page 53 of 53

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 APPENDIX D WASTE ACCEPTANCE CRITERIA (WAC)

FOR INTERIM RADWASTE STORAGE FACILITY LASALLE COUNTY NUCLEAR STATION Appendix D - Page 1 of 13

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09

1.0 INTRODUCTION

Class B/C radioactive waste is expected to be transported from Braidwood, Byron, and Clinton Stations in Illinois to LaSalle County Station Interim Radwaste Storage Facility (IRSF). To make sure that the waste radioactive waste form and packaging received by LaSalle County IRSF are acceptable for long-term (greater than five years) storage and eventual shipment for disposal, specific criteria identifying conditions of acceptance is needed. The waste acceptance criteria provided herein is based on the Barnwell Waste Management Facility (Barnwell, South Carolina) License Amendment No. 49 (Attachment 1).

The Barnwell WAC text was used in its entirety for the IRSF WAC except for where:

a) Specific text did not apply b) Specific text was modified or replaced.

Applicable Barnwell WAC text was not transferred to the IRSF WAC and therefore, its attachment to this document is necessary for completeness.

1.1 PURPOSE The purpose of LaSalle County Station IRSF Waste Acceptance Criteria (WAC) is to provide the authorized radioactive material, form, and packaging for emplacement in the facility for long-term storage and eventual transshipment to a disposal facility.

1.2 WASTE ACCEPTANCE CONDITIONS The following conditions constitute the requirements necessary for radioactive waste packages to be received at the IRSF for long-term storage and shipped to a disposal facility when one is identified. These conditions numbers and text are identical to those found in the Reference 1 document, accept as indicated.

Conditions 1 - 4 Does not Apply Condition 5 - Is replaced with the following:

Authorized Material - Any radioactive material, excluding source and special nuclear material, except as authorized by this WAC.

Condition 6 - Is replaced with the following:

Chemical and/or Physical Form - Dry packaged radioactive waste except as authorized or excluded by this WAC.

Condition 7 - Does not Apply Appendix D - Page 2 of 13

Condition 8 - Is replaced with the following:

Authorized Radioactive Materials - Class B and C quantities of radioactive waste materials packaged in accordance with this WAC.

General Conditions Starts at Condition Condition 9 - Does Not Apply Condition 10 - Does Not Apply Condition 11 - Is replaced with the following:

LaSalle County IRSF will remain in compliance with all Station policies, practices, and procedures. If a conflict arises between Station directives and the facilitys ability to receive waste, receiving operations will be suspended until compliance can be assured.

Condition 12 - Is replaced with the following:

Operations authorized in the LaSalle County IRSF are performed in accordance with the following Station and Exelon Corporate Procedures:

a. Station procedures x Abnormal IRSF Operation Procedure x IRSF General Use Procedure (LOP-WX-32)

b. Exelon Corporate Procedures x Radwaste Storage Facility/Waste Container Inspections (RW-AA-104) x Guidelines for Operating an Interim On Site Low Level Radioactive Waste Storage Facility (RW-AA-105)

Condition 13 - All station soliciting waste to LaSalle County IRSF including LaSalle Facility shall comply with Exelons training procedures as stated in Condition 12.

Condition 14 - Is replaced with the following:

Operations of the LaSalle County IRSF will be conducted by the Stations Radwaste Supervisor or his designee in accordance with the Condition 12 procedures.

Condition 15 - Does Not Apply Condition 16 - Is replaced with the following:

Appendix D - Page 3 of 13

Documented inspections of facility operations and storage bay surveillances are conducted in accordance with the applicable Condition 12 procedure.

Condition 17 - Is replaced with the following:

a. All waste received for long term-storage must be in compliance with applicable US Department of Transportation (DOT), US Nuclear Regulatory Commission (NRC), and the requirements of this WAC.

b. Exception, on-site generated waste destined for long-term storage may exceed transportation radiation dose limits, as long as handling and placement of those waste packages are conducted in accordance with applicable Condition 12 procedures and RegGuide 8.8 Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations will be As Low As is Reasonably Achievable (Reference 1).

Condition 18 - Is replaced with the following:

All records and shipment manifest pertinent to the transportation, receipt, package decontamination, repackaging, and transshipment of long-termed stored waste packages must be maintained according to the applicable Condition 12 procedure.

Condition 19 - Is replaced with the following:

All records of shipments and transshipments must be maintained according to the requirements of the applicable Condition 12 procedures in accordance with 10 CFR 61.80 (c) Maintenance of Records, Reports, and Transfers requirements (Reference 2).

Condition 20 - Is replaced with the following:

Semi-annual reports identifying facility operations (including, waste receiving, surveillances, transshipments, and unusual occurrences) must be submitted to the Exelon Corporate Radioactive Waste Manager.

Condition 21 - Does Not Apply Appendix D - Page 4 of 13

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Receipt, Acceptance and Inspection Conditions Condition 22 - Is replaced with the following:

The facility shall not accept radioactive waste for long-term storage unless 1) its from an authorized shipper and 2) the shipper has provided the following:

a. Annual waste forecast identifying the quantity and types of waste expected to be shipped to the facility for long term storage. This criterion includes shipments from on-site sources.

b. US NRC Uniform Low-Level Radioactive Waste Manifest Forms 540 (Shipping Paper), 541 (Container and Waste Description), and 542 (Manifest Index and Regional Compact Tabulation) as needed according to the applicable Conditions 12 procedure.

Condition 23 - Does Not Apply Condition 24 - Does Not Apply (see Condition 22)

Condition 25 - Is replaced with the following:

No waste will be shipped to the IRSF for long-term storage until it has been certified as passing the applicable Condition 12 inspection procedure.

Received waste not passing inspection may 1) be return to the sending Station as long as all DOT and NRC transportation requirements are met or 2) reprocessed and other issues causing the package to be rejected resolved. Any case of unusual occurrence reported per the station Corrective Action Process.

Condition 26 - Is replaced with the following:

The facility will not accept radioactive waste shipments containing unusual hazards or potential hazards including but not limited to, physical, gaseous, chemical, pyrophoric, or unexpected high radiation levels at the container surfaces.

Additionally, the facility will not accept any waste package containing radioactive mixed waste as described in Information Appendix D - Page 5 of 13

Notice 90-09 Extended Interim Storage of Low-Level Radioactive Waste by Fuel Cycle and Material Licensees (Reference 3).

Condition 27 - Does Not Apply Condition 28 - Does Not Apply Condition 29 - Is replaced with the following:

a. The facility operator shall notify the shipping Station when it has been determined that a radioactive waste shipment or part of a shipment cannot be accepted for long-term storage and selected Condition 25 resolution.

b. The facility operator shall notify the shipping Station before the end of the next business day if a shipment has failed to arrive at the disposal facility within the 24-hour time frame indicated in the advance notification or manifest.

Condition 30 - Is replaced with the following:

a. The facility operator shall acknowledge receipt of the waste within 7 days of its acceptance for long-term storage by returning a signed copy of the shipment manifest or shipping papers to the shipping Station.

b. The facility operator shall indicate on the returned copy of the shipment manifest or shipping papers any discrepancy between the waste description listed on the manifest or papers and the waste materials received in the shipment and discrepancy resolution.

Waste Characteristics and Waste Form Conditions Condition 31 - Is replaced with the following:

The facility operator shall not accept any radioactive waste for long-term storage unless the shipping Station has marked each disposal container, as specified by the applicable Condition 12 procedure, to identify its classification as either Class B, or Class C waste, and certifies that the waste materials have been classified and prepared in accordance with the following waste classification table, as appropriate. Additionally, the wastes stability classification will also be marked on the container.

Appendix D - Page 6 of 13

Class B/C Columns of the Table are included in their entirety.

A. Is utilized in its entirety.

B. Does Not Apply C. Is utilized in its entirety.

D. Is utilized in its entirety.

E. Is utilized in its entirety.

F. Is utilized in its entirety.

G. Is replaced with the following:

If the concentration of any single radionuclide exceeds Class C values in the table, the waste is not acceptable for long-term storage H. Is utilized in its entirety.

I. Does Not Apply Condition 32 - Is replaced with the following:

a. Liquid wastes are not authorized for receipt in the IRSF regardless of the chemical or physical form.

b. Solidified or dewatered radioactive waste shall have no detectable free standing liquids in excess of one-half percent (0.5%) by waste volume of non-corrosive liquids per container.

c. In lieu of the requirements of paragraph b. above, solidified or dewatered waste containing noncorrosive liquids in excess of one-half percent (0.5%) by waste volume, and less than on percent (1%) non-corrosive liquids by waste volume, may be received and disposed of in high integrity containers (HICs) approved by the Exelon Corporate Radwaste Manager Appendix D - Page 7 of 13

Condition 33 - Is replaced with the following:

a. The facility shall only receive aqueous liquids and other applicable waste forms which have been solidified or otherwise stabilized with one of the following solidification media:

1. Vinyl Ester Styrene

2. Cement

3. Bitumen (see Subparagraph d. below)

4. Vinyl Chloride

5. TBD

b. Solidification media and processes used to stabilize Class B and C waste, shall meet and have been evaluated in accordance with the "Stability Guidance" requirements of the US NRC Waste Management Division, Technical Position on Waste Form, Revision 1, dated January 1991 (Reference 4) and Exelon/Station procedure specifically prepared to address its requirements.

c. Other solidification media and processes shall be acceptable for which a topical report has been prepared and received approval from the US NRC and approved by the Exelon Corporate Radwaste Manager.

d. The facility shall only receive for disposal, full formula, oxidized bitumen (asphalt) solidified waste, which is a free standing monolith as received for disposal, and certified as such by the shipping Station.

Condition 34 - Does Not Apply Condition 35 - Is replaced with the following:

The facility shall not receive evaporator bottoms or concentrates, residues, sludges, or other waste which may contain free standing liquids, unless they are solidified in accordance with Condition 33, and meet the requirements as specified in Condition 32.

Evaporator bottoms or concentrates which contain no free standing water and are not free flowing are acceptable for disposal when processed by a method specifically approved by the Exelon Corporate Radwaste Manager.

Condition 36 - Is utilized in its entirety, accept licensee is replaced with facility.

Appendix D - Page 8 of 13

Condition 37 - Is utilized in its entirety, accept licensee is replaced with facility.

Condition 38 - Is replaced with the following:

Regardless of the waste classification of Condition 31, ion exchange resins and filter media containing isotopes with greater than five (5) year half-lives having a specific activity of all these isotopes of 1 microcurie/cubic centimeter or greater must be stabilized by solidification in accordance with Condition 33 and meet the free standing liquid requirements of Condition 32.a.

However, in lieu of solidification, these waste forms meeting the free standing liquid requirements of Condition 32.C. can receive long-term storage in approved high integrity containers or other methods of stabilization are acceptable for long-term storage approved by the Exelon Corporate Radwaste Manager.

Condition 39 - Does Not Apply Condition 40 - Is replaced with the following:

Radioactive waste containing transuranic radionuclides or other special nuclear materials within the limits specified in Condition 31 are acceptable provided that the transuranic radionuclides or other special nuclear materials are evenly distributed within a homogeneous waste form and are incidental to the total radioactivity. Incidental in this condition is defined as not more than one percent (1%) of the total activity.

Condition 41 - Does Not Apply Condition 42 - Does Not Apply Condition 43 - Does Not Apply Condition 44 - Does Not Apply Condition 45 - Is replaced with the following:

The facility shall not receive radioactive waste in the forms of incinerator ash or powder which may be dispersible unless solidified with a media specified in Condition 33.

Condition 46 - Is utilized in its entirety, accept Department is replaced with Exelon Corporate Radwaste Manager.

Condition 47 - Is replaced with the following:

Gaseous radioactive wastes are not acceptable for IRSF storage.

Appendix D - Page 9 of 13

Condition 48 - Does Not Apply Condition 49 - Is utilized in its entirety, accept licensee is replaced with facility.

Condition 50 - Is replaced with the following:

The facility shall not receive radioactive waste which contains or is capable of generating quantities of toxic gases, vapors, or fumes harmful to persons transporting, handling, or disposing of the waste.

Condition 51 - Is utilized in its entirety, accept licensee is replaced with facility and or disposed is deleted.

Condition 52 - Is replaced with the following:

The facility shall not receive for long-term storage petroleum based materials in any physical form. However, this does not prohibit the receipt of waste containing incidental or trace amounts of oil or petroleum based materials which have been absorbed, provided that the amount of absorbed oil and petroleum based materials does not exceed one percent (1%) by waste volume in a container.

Condition 53 - Is replaced with the following:

The facility shall not receive radioactive waste containing hazardous biological, pathogenic, or infectious material.

Condition 54 - Does Not Apply Contamination Limit Conditions Condition 55 - Is utilized in its entirety, accept Barnwell Suite is replaced with at the facility Condition 56 - Is utilized in its entirety.

Condition 57 - Is utilized in its entirety.

Condition 58 - Is utilized in its entirety, accept licensee is replaced with facility.

Condition 59 - Is replaced with the following:

The IRSF decontamination facility will remain in inoperative. All decontamination efforts will be provided in the Radwaste Building or a facility as identified by the Radwaste Supervisor.

Appendix D - Page 10 of 13

General Packaging Conditions Condition 60 - Is replaced with the following:

All radioactive waste shall be packaged and loaded in accordance with applicable US DOT Regulations, US NRC Regulations 10 CFR Part 71, and the requirements of this WAC.

Condition 61 - Does Not Apply Condition 62 - Does Not Apply Condition 63 - Is replaced with the following:

The facility shall, to the extent practicable, repair or repackage any damaged package accepted for storage.

Condition 64 - Is replaced with the following:

Prior to transshipment for disposal, the facility shall, to the extent practicable, remove all liquids from waste packages found in excess of allowable limits. Container dewatering or reprocessing is not authorized in the facility and therefore most be performed in another Station area.

Condition 65 - Is utilized in its entirety, accept Barnwell Suite is replaced with at the facility Condition 66 - Is utilized in its entirety, accept Barnwell Suite is replaced with at the facility Condition 67 - 100 - Do Not Apply

( Environmental Surveillance Conditions are handed in another document which is not part of the WAC)

Appendix D - Page 11 of 13

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 1.3 References

1. RegGuide 8.8 Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations will be As Low As is Reasonably Achievable, Revision 3

2. 10 CFR 61.80 (c) Maintenance of Records, Reports, and Transfers requirements

3. Information Notice 90-09 Extended Interim Storage of Low-Level Radioactive Waste by Fuel Cycle and Material Licensees

4. US NRC Waste Management Division, Technical Position on Waste Form, Revision 1, dated January 1991

5. Environmental Surveillance Conditions to be determined Appendix D - Page 12 of 13

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 ATTACHMENT A- South Carolina Department of Health and Environmental Control Radioactive Material License Appendix D - Page 13 of 13

SOUTH CAROLINA DEPARTMENT OF HEALTH AND ENVIRONMENTAL CONTROL RADIOACTIVE MATERIAL LICENSE Pursuant to the Atomic Energy and Radiation Control Act, Section 13-7-40 et. seq. of S.C. Code of Laws of 1976 as amended and Supplements thereto, and the South Carolina Department of Health and Environmental Control Regulation 61-63 Radioactive Material (Title A), and in reliance on statements and representations heretofore made by the applicant, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer radioactive material listed below; and to use such radioactive material for the purpose(s) and at the place(s) designated below. The license is subject to all applicable rules of the South Carolina Department ofHealth and Environmental Control now or hereafter in effect and to any conditions specified below.

Amendment No. 49 amends LICENSEE 3. License Number I. Name Chern-Nuclear Systems, LLC. 097 in its entirety Barnwell Waste Management Facility

2. Address ~. Expiration Date 740 Osborn Road Barnwell, S.c. 29812 Five year term to be determined

5. Radioactive Material 6. Chemical and/or Physical Form 7. Maximum Radioactivity and/or quantity of material which licensee may (Element and Mass Number) possess at anyone time.

A Any Radioactive material A Dry packaged radioactive A 50,000 curies excluding source material and waste except as authorized in special nuclear material. this license.

B. Source material B. Dry packaged radioactive B. 60,000 pounds waste except as authorized in this license.

C. Special Nuclear Material C. Dry packaged radioactive C. 350 grams total of 235U or 200 waste except as authorized in grams 233U or 200 grams of this license. plutonium or any combination of these provided the sum of the ratios of the quantities does not exceed unity.

8. Authorized Use:

A, B. and C.

Radioactive material as low-level radioactive waste may be received, stored, and disposed of by enhanced shallow land burial in approved engineering barriers (vaults) unless otherwise specifically authorized by the Department . The licensee shall not receive an annual volume of more than the authorized limits of South Carolina Code of Laws of 1976, as amended.

Unless otherwise authorized by the Department, only radioactive waste consigned for burial shall be received at the location specified in Condition No. 9 of this license. The maximum radioactivity and/or quantity of radioactive material indicated in Item 7. A, B, and C applies to the above-ground activities.

Appendix D C, Page _1_ of _17_

Project No. 29487-NCS0097.N.LAS EC DCR # 375636

Page 2 of11 Pages SOUTH CAROLINA DEPARTMENT OF HEALTH AND ENVIRONMENTAL CONTROL Radioactive Material License Supplementary Sheet License Nwnber 097 Amendment Nwnber 49 General Conditions

9. Unless otherwise specified, the authorized place of use is a site located approximately five miles northwest of Barnwell, South Carolina, in the Seven Pines School District, Red Oak Township, Barnwell County, South Carolina within the boundary of the land area described in Lease agreement dated April 6, 1976, as amended.

10. The licensee shall comply with the provisions of the South Carolina Department of Health and Environmental Control (SC DHEC) Regulation 61-63, Radioactive Material, (Title A), Part 1 - General Provisions; Part II -

Licensing of Radioactive Materials; Part III - Standards for Protection Against Radiation; Part VI - Notices, Instructions, and Reports to Workers; Inspections, and Part VII - Licensing Requirements for Land Disposal of Radioactive Waste; Department Regulation 61-83, Transportation of Radioactive Waste Into or Within South Carolina.

I 1. Unless otherwise specified in this license, the licensee shall make no changes in the internal safety audits, Safety Review Board, ALARA Review Committee, Site Criteria, or procedures governing these specific activities without approval from the Department.

12. Operations authorized by this license shall be conducted in accordance with Chern-Nuclear Systems (CNS) procedures and subsequent revisions and additions approved by the Department. However, the licensee may upon notification to the Department but without Department approval, make minor changes to these procedures provided that:

A. The change does not affect requirements of any other license condition in this license; B. The change does not increase the potential for personnel exposure; C. The change does not diminish operational safety; D. The change does not increase the potential for release of radioactive material to unrestricted areas; and E. The change does not reduce the licensee's record keeping and reporting system.

The licensee shall maintain records of these changes including evaluations which provide the basis for the change.

U. The licensee shall ensure that all site personnel have satisfactorily completed the trammg program requirements as specified in the CNS Barnwell Site Training Prograrn. Changes and additions to the program shall be submitted to the Department for review. Time intervals for personnel indoctrination, training, examinations, certification, retraining specified in CNS Procedure S20-AD-004, "Barnwell Radioactive Waste Burial Site Personnel Training", shall not be changed without Department approval.

14. Operations shall be conducted by or under the supervision of: William A. Veronee, (RSO), James W. Latham, Joseph 1. Still, William B. House, Michael 1. Benjamin, Wayne Inabinett, Edward F. Boyles, Jr. or other individuals designated by the licensee's Radiation Safety Officer upon successful completion of the licensee's training program and approval by the licensee's Safety Review Board.

15. The licensee shall to the extent necessary, continue the employment of all personnel involved in the operation of the Barnwell Waste Management Facility in accordance with all requirements in the license and applicable regulations and, in the event replacement of employees becomes necessary, only individuals of comparable qualifications and experience will be hired.

Appendix DC, Page _2_ of _17_

Project No. 29487-NCS0097.N.LAS EC DCR # 375636

Page 3 of 11 Pages SOUTHCAROLmADEPARTMENTOFHEALTHANDE~ONMENTALCONTROL Radioactive Material License Supplementary Sheet License Nwnber 097 Amendment Nwnber 49

16. A documented weekly inspection of site operations and the restricted area of the site for compliance with applicable conditions of this license shall be conducted by a named authorized user in Condition 14 or other individual approved by the Department.

11. The transportation of radioactive materials and radioactive waste within the State of South Carolina shall be in accordance with applicable regulations of the United States Department of Transportation (US DOT), the United States Nuclear Regulatory Commission (US NRC), Section RHA 2.22, Department Regulation 61-63, Radioactive Material (Title A), and Department Regulation 61-83, "Transportation of Radioactive Waste Into or Within South Carolina".

18. The licensee shall maintain all records and shipment manifest pertinent to the transportation, receipt, and disposal of radioactive material at the location specified in Condition 9 of this license until authorization is given by the Department for transfer or disposal of such records.

19. The licensee shall maintain records for each shipment of waste disposed of at the site. The records shall conform with the requirements of RHA 7.32, Department Regulation 61-63, Radioactive Material (Title A).

The licensee shall maintain all records required in the Department Regulations 61-63 and 61-83, and 10 CFR Part 61 at the disposal facility in readable form to include electronic and microfilm, and stored in an environmentally-controlled facility to prevent damage.

20. A monthly site receipt and burial activities report shall be submitted no later than the lOth day following the month to the Assistant Director, Division of Waste Management, Bureau of Land & Waste Management, SC DHEC, 2600 Bull Street, Columbia, SC 29201.

I1. Except as specifically provided otherwise by this license, the licensee shall possess and use radioactive material described in Items 5, 6, and 7 of this license and conduct site operations in accordance with statements, representations, operating procedures, and disposal criteria, heretofore made by the licensee or his authorized representative in application for and subsequent to issuance of SC Radioactive Material License No. 097, and amendments thereto.

Receipt, Acceptance and Inspection Conditions

22. The licensee shall not accept radioactive waste for storage or disposal unless the shipper has completed the required information for the waste shipment on the US NRC Uniform Low-Level Radioactive Waste Manifest Forms 540 (Shipping Paper), 541 (Container and Waste Description), and 542 (Manifest Index and Regional Compact Tabulation) as applicable, or approved equivalent forms.

23. The licensee shall not accept radioactive waste for storage or disposal unless the generator of such waste has a valid, unsuspended Radioactive Waste Transport Permit issued by the SC DHEC.

24. The licensee shall not accept radioactive waste for storage or disposal unless the shipper has provided a properly executed Department Form, DHEC-803, Radioactive Waste Shipment Certification Form, Part I and II. Shipments consisting of more than 75 cubic feet or containing more than one (1) curie shall also be accompanied by a properly completed and executed Department Form, DHEC-802, Radioactive Waste Prior Notification and Manifest Form. Changes to the shipment identification number on the forms may be made by the licensee, provided that the Department is notified of the change no later than the last day of the month for which the shipment was originally scheduled. Forms shall not be carried over more than one month.

Appendix D C, Page _3_ of_17_

Project No. 29487-NCS0097.N.LAS EC DCR # 375636

Page 4 of 11 Pages SOUTH CAROLINA DEPARTMENT OF HEALTH AND ENVIRONMENTAL CONTROL Radioactive Material License Supplementary Sheet License Nwnber 097 Amendment Nwnber 49

25. The licensee shall only accept radioactive waste shipments for storage or disposal which have been inspected by a representative of the Department. The licensee shall assist the Department in inspection, sampling and analysis of the waste as deemed necessary by the Department to ensure compliance with the requirements of this license. The licensee shall perform radiological analysis of liquids found in waste packages and interstitial spaces of shipping casks as deemed necessary by the Department.

26. Notwithstanding other conditions of this license, the licensee shall not accept radioactive waste for storage or disposal unless he has received advanced written notification of any waste shipment containing unusual hazards or potential hazards including but not limited to, physical, gaseous, chemical, pyrophoric, or excessive removable contamination on the disposal containers shipped inside casks or excessive internally contaminated casks, and unexpected high radiation levels at the disposal container surfaces.

27. The licensee shall immediately notify the Department or the Department's on-site representative of any waste shipments where a violation of applicable regulations or license conditions has been found.

28. The licensee shall notify the shipper and the Department when any shipment of radioactive waste or part of a shipment has not arrived within 60 days after the advance copy of the shipment manifest or shipping papers was received by the licensee.

29. The licensee shall notify the shipper when it has been determined that a radioactive waste shipment or part of a shipment cannot be accepted for disposal by the licensee. The licensee shall notify the waste generator/shipper before the end of the next business day if a shipment has failed to arrive at the disposal facility within the 24-hour time frame indicated in the advance notification or manifest

30. The licensee shall acknowledge receipt of the waste within 7 days of its acceptance for disposal by returning a signed copy of the shipment manifest or shipping papers to the shipper. The licensee shall indicate on the returned copy of the shipment manifest or shipping papers any discrepancy between the waste description listed on the manifest or papers and the waste materials received in the shipment.

Waste Characteristics and Waste Form Conditions

31. The licensee shall not accept any radioactive waste for storage or disposal unless the shipper has marked each disposal container, as specified by the licensee, to identify its classification as either Class A, stable or unstable (S or U), Class B, or Class C waste, and certifies that the waste materials have been classified and prepared in accordance with the following waste classification table:

Waste Classification Table AppendixDC, Page _4_ of _17_

Project No. 29487-NCS0097.N.LAS EC DCR # 375636

Page 5 of 11 Pages SOUTH CAROLINA DEPARTMENT OF HEALTH AND ENVIRONMENTAL CONTROL Radioactive Material License Supplementary Sheet License Nwnber 097 Amendment Nwnber 49 RADIONUCLIDES CONCENTRAnON LIMITS IN CURIES/CUBIC METER' Table I (long-lived) Class A Class B Class C C-14 ~ 0.8 ~ 8 C-14 in activated metal < 8 < 80 Ni-59 in activated metal ~ 22 ~ 220 Nb-94 in activated metal ~ 0.02 < 0.2 Tc-99 < 0.3 ~ 3 1-129 < 0.008 < 0.08 CONCENTRATION LIMITS IN NANOCURIES/GRAM Alpha emitting transuranics with ~ 10 ~ 100 half-life greater than 5 years Ra-226 ~ 10 ~ 100 Pu-241 < 350 ~ 3500 Cm-242 ~ 2000 < 20000 CONCENTRATION LIMITS IN CURIES/CUBIC METER' Table II (short-lived) Class A Class B Class C Total of all with half-life less < 700 > 700 than 5 years H-3 < 40 > 40 Co-60 ~ 700 > 700 Ni-63 < 3.5 < 70 ~ 700 Ni-63 in activated metal ~ 35 ~ 700 ~ 7000 Sr-90 ~ 0.04 ~ 150 ~ 7000 Cs-137 < I < 44 < 4600

.curies/cubic meter is equivalent to microcuries/cubic centimeter A. The concentration of a radionuclide or radionuclide mixture may be averaged over the volume of the waste and, if used, the solidification agent or matrix if the waste form is a homogenous mixture. The concentration of radionuclides in filters/sealed sources encapsulated with a solidification agent or matrix shall be averaged over the volume of the filter/sealed source not the solidification agent. The volume of packaging, containers, liners, or overpacks shall not be included in this calculation, nor shall the volume of the waste mixture be artificially increased with the addition of non-dispersible solids or objects even if considered as waste.

If expressed in units of nanocuries per gram, concentration may be averaged over the weight of the waste and, if used, the solidification agent if homogenous, except in the case of encapsulation of filters which shall be over the weight of the filter. The weight of packaging, containers, liners, or overpacks shall not be included in this calculation, nor shall the weight of the waste mixture be artificially increased by the addition of heavy, non-dispersible solids or objects even if considered as waste.

B. The waste is Class A if none of the listed radionuclides are present.

c. There are no upper limits in Class B waste for the first three radionuclides listed in Table II.

Page 6 of 11 Pages SOUTH CAROLINA DEPARTMENT OF HEALTH AND ENVIRONMENTAL CONTROL Radioactive Material License Supplementary Sheet License Number 097 AJnendrnent Number 49 D. There are no Class B values for the first nine (9) radionuclides listed; their presence classifies the waste as either Class A or Class C according to their concentrations.

E. The waste class for mixtures of radionuclides is determined by deriving for each radionuclide the ratio between its concentration in the mixture and its concentration limit in the table and adding the resulting ratio values for each radionuclide group. All limits used in the calculation must be for the same waste class. The sum of the ratios for each group must be less than or equal to 1.0 or the waste is of a higher classification than that used for the calculation.

F. If Class C limits are used in the calculation and the sum of the ratios for either group is equal to or exceeds 1.0, the waste is not acceptable for disposal without prior written approval from the Department.

G. If the concentration of any single radionuclide exceeds Class C values in the table, the waste is not acceptable for disposal without prior written approval from the Department.

H. Concentrations for C-14, Ni-59, Ni-63, and Nb-94 in activated metal must be evaluated for any irradiated metal component, filters and filter material associated with spent fuel pools.

I. Waste containing radium may be accepted only if the requirements of condition 44 of this license are met.

32. A. Unless otherwise specified in this license, the licensee shall not receive any liquid radioactive waste regardless of the chemical or physical form. Absorbent materials may be placed in packages of dry, solid waste to absorb unintentional and incidental amounts of liquids. Further, liquids in the interstitial spaces oftransport casks and containers shall be removed to the extent practical.

B. Solidified or dewatered radioactive waste shall have no detectable free standing liquids in excess of one-half percent (0.5%) by waste volume ofnon-corrosive liquids per container.

C. In lieu of the requirements of paragraph B. above, solidified or dewatered waste containing non-corrosive liquids in excess of one-half percent (0.5%) by waste volume, and less than on percent (1%) non-corrosive liquids by waste volume, may be received and disposed of in high integrity containers approved by the Department.

A. Unless otherwise specified, the licensee shall only receive aqueous liquids and other applicable waste forms which have been solidified or otherwise stabilized with one of the following solidification media:

a. Vinyl Ester Styrene

b. Cement

c. Bitumen (see Subparagraph E. below) Appendix D, Page _6_ of_17_

d. Vinyl Chloride Project No. 29487-NCS0097.N.LAS EC # 375636 B. Solidification media and processes used to stabilize Class A aqueous liquids and other Class A wastes containing isotopes with greater than five (5) year half-lives having a total specific activity if all these isotopes of I microcurie/cubic centimeter or greater, and all applicable Class Band C waste, shall meet and have been evaluated in accordance with the "Stability Guidance" requirements of the

Page 7 of 11 Pages SOUTH CAROLINA DEPARTMENT OF HEALTH AND ENVIRONMENTAL CONTROL Radioactive Material License Supplementary Sheet License Number 097 Amendment Number 49 US NRC Waste Management Division, Technical Position on Waste Fonn, (Revision I), dated January 1991, or other evaluation criteria or methods specifically approved by the NRC or the Department.

C. Solidified Class A aqueous liquids and other applicable waste forms with a specific activity of less than 1 microcurie/cubic centimeter, shall meet the requirements of the "Solidified Class A Waste Products" of the NRC Technical Position on Waste Fonn, (Revision 1) dated January 1991.

D. Other solidification media and processes shall be acceptable for which a topical report has been prepared and received approval from the US NRC with concurrence from the Department or approval by the Department.

E. The licensee shall only receive for disposal, full fonnula, oxidized bitumen (asphalt) solidified waste, which is a free standing monolith as received for disposal, and certified as such by the waste generator.

34. Except as specifically provided in this license, the licensee shall not accept liquid radioactive waste packaged in absorbent materials, or where absorbent materials have been used to absorb liquids rather than properly solidified with an approved media.

35. Regardless of the waste classification of Condition 31, and unless otherwise authorized by the Department, the licensee shall not receive evaporator bottoms or concentrates, residues, sludges, or other waste which may contain free standing liquids, unless they are solidified in accordance with Condition 33, and meet the requirements as specified in Condition 32. Evaporator bottoms or concentrates which contain no free standing water and are not free flowing are acceptable for disposal when processed by a method specifically approved by the Department.

36. The licensee may receive resins and filter media in a dewatered fonn provided that the free standing liquid requirements of Condition 32 and the requirements of Condition 38 are met.

37. The licensee shall not receive containers of ion exchange resins or filter media (dewatered or solidified) unless records of complete radiological analyses (quantitative and qualitative) are provided. The records must specify the specific activity of each radionuclide expressed in microcuries/cubic centimeter and transuranic radionuclides in nanocuries/gram.

38. Regardless of the waste classification of Condition 31, ion exchange resins and filter media containing isotopes with greater than five (5) year half-lives having a specific activity of all these isotopes of I microcurie/cubic centimeter or greater must be stabilized by solidification in accordance with Condition 33 and meet the free standing liquid requirements of Condition 32.B. However, in lieu of solidification, the Department will authorize disposal of these waste fonns meeting the free standing liquid requirements of Condition 32.C. in approved high integrity containers or other approved methods of stabilization.

39. Unless specifically provided otherwise, the licensee shall dispose of all classes of wastes in concrete overpacks or vaults which are approved by the Department and provided by the site operator. Void spaces within the waste and between the waste and its packaging shall be reduced to the extent practicable, but in no case shall less than eighty-five percent (85%) of the capacity of the containers be filled for all waste classes unless placed in a High Integrity Container. The licensee may allow a variance from this condition in certain instances, but only after receiving a written justification from the waste generator prior to receiving the waste shipment. Variance justifications and approvals shall be maintained for review by the Department.

40. Radioactive waste containing transuranic radionuclides within the limits specified in Condition 31 are acceptable provided that the transuranic radionuclides are evenly distributed within a homogeneous waste fonn and are incidental to the total radioactivity. Incidental in this condition is defined as not more than one

Page 8 of 11 Pages SOUTH CAROLINA DEPARTMENT OF HEALTH AND ENVIRONMENTAL CONTROL Radioactive Material License Supplementary Sheet License Nwnber 097 Amendment Nwnber 49 percent (1 %) of the total activity. This license does not authorize the receipt of disposal of components or equipment primarily contaminated with transuranic radionuclides on vehicles, equipment, or components, with contamination limits in excess of those specified in Condition 55.

41. Household or industrial smoke or gas detectors containing Americium-241 foils which may exceed the transuranic radionuclide limit specified in Condition 31 of this license may be accepted for disposal provided the entire detector is received for disposal.

42. The licensee shall not receive or dispose of sealed sources or special form radioactive materials containing more than 5 curies of radioactive material with half-lives greater than 5 years except in a container which provides long term containment. Such containers are subject to approval by the Department. Irradiated metal components which have similar characteristics of special form radioactive materials are subject to Department review for disposal container requirements.

The licensee may accept the following sealed sources and maximum total activities provided that the sources are encapsulated with a minimum of four (4) inches of cement on all sides having a minimum compressive strength of 2,500 pounds per square inch.

Radionuclide Maximum Total Activity (microcuries)

C-14 100 Ni-59 100 Nb-94 0.01 Tc-99 10 1-129 0.01 Radionuclides in Condition 31. 107 Table II

43. The licensee shall not receive toluene, xylene, dioxane, scintillation liquids which exhibit hazardous properties or other organic liquids or solids with similar chemical properties except as specified below:

A. Containers which have contained any of the liquids mentioned above are acceptable for disposal after treatment as specifically authorized by the Department.

B. The ash and/or residue from the incineration of these wastes are acceptable in accordance with Condition 45 of this license.

CI) r-~

I~ 44. Unless otherwise authorized by the Department the licensee shall not receive any radioactive waste containing Radium except for:

...... r-10\

..... 0 o 0 A. Radium contained in solid homogeneous waste forms in which the Radium activity is incidental CI)

IU (incidental is defined as not more that one percent of the total activity) and the concentration of OOz I I Radium has not been technologically enhanced or, Q) r-0000 tIS '<t P-c0\ B. Radium contained in the following devices: self-luminous dials, hands of dials, timepieces,

~ N compasses, and electron tubes provided that the entire device is received and buried, or C. Radium contained in biological research waste, or

Page 9 of 11 Pages SOUTH CAROLINA DEPARTMENT OF HEALTH AND ENVIRONMENTAL CONTROL Radioactive Material License Supplementary Sheet License Number 097 Amendment Number 49 D. Radium sources specifically approved by the Department.

45. The licensee shaH not receive radioactive waste in the forms of incinerator ash or powder which may be dispersible unless solidified with a media specified in Condition 33 of this license, or packaged to prevent dispersion as specifically approved by the Department. In lieu of solidification, these waste forms may be received in high integrity containers approved by the Department, provided the waste is rendered nondispersible with a binding matrix.

46. Radioactive waste containing chelating agents between 0.1 percent and 8 percent by weight in the waste as received for disposal shall be in High Integrity Containers or shaH be stabilized by solidification with a media specified in Condition 33 of this license or an alternative method specificaHy approved by the Department.

47. The licensee may only receive gaseous radioactive materials of Krypton 85, Xenon 133, and Tritium for burial provided they meet the foHowing criteria:

A. For Krypton 85 and Xenon 133:

a. Burial containers must be US DOT specification cylinders or U.S. Nuclear Regulatory Commission approved sealed sources.

b. Internal pressure of containers may not exceed 1.5 atmospheres.

c. Total activity of containers shall not exceed 100 curies each.

B. For Tritium:

a. Only sources approved by the US NRC or an Agreement State may be received for disposal.

b. The source/device must be received intact.

c. The internal pressure of the source/device shall not exceed 1.5 atmospheres.

d. Sources/devices must be packaged to prevent breakage.

e. The maximum activity per disposal container shall not exceed 1000 curies.

f. Devices requiring stabilization based on waste classification (using the volume of the source/device only) must be placed in a high integrity container or encapsulated with an appropriate stabilization media.

48. A. Unless otherwise authorized, the licensee shaH not receive for storage nor disposal any mixed low-level radioactive waste defined as waste that satisfies the definition of low-level radioactive waste specified in the Low-Level Radioactive Waste Policy Amendments Act of 1985 (P.L.99-240), and contains waste that either (I) is listed as hazardous waste in Subpart D, 40 CFR 261, or (2) causes the waste to exhibit any of the hazardous waste characteristics identified in Subpart C, 40 CFR Part 261.

B. The licensee may however receive waste that has been treated by acceptable methods to render it nonhazardous and therefore not subject to the jurisdiction of the Resource Conservation and Recovery Act (RCRA). Waste which may contain discrete quantities of hazardous or toxic materials may be evaluated for disposal by the licensee and such evaluations provided to the Department for consideration of approval.

Page 10 ofl7 Pages SOUTH CAROLINA DEPARTMENT OF HEALTH AND ENVIRONMENTAL CONTROL Radioactive Material License Supplementary Sheet License Number 097 Amendment Number 49

49. The licensee shall not receive mdioactive waste that is readily capable of detonation or of explosive decomposition or reaction at normal pressures and temperature, or of explosive or exothermic reaction with water.

50. The licensee shall not receive mdioactive waste which contains or is capable of genemting quantities of toxic gases, vapors, or fumes harmful to persons tmnsporting, handling or disposing of the waste. This does not apply to radioactive gaseous waste packaged in accordance with Condition 47 ofthis license.

51. The license shall not receive or dispose of any pyrophoric material or flammable solids. These materials contained in waste shall be treated, prepared and packaged to be nonflammable and the final waste form rendered nonpyrophoric and nonflammable prior to tmnsportation and receipt.

52. The licensee shall not receive or bury oil or petroleum based materials in any physical form. However, this does not prohibit the receipt and disposal of waste containing incidental or trace amounts of oil or petroleum based materials which have been absorbed, provided that the amount of absorbed oil and petroleum based materials does not exceed one percent (1 %) by waste volume in a container.

53. The licensee shall not receive radioactive waste containing hazardous biological, pathogenic, or infectious material unless treated to reduce to maximum extent pmcticable the potential hazard from the materials. In addition, radioactive waste containing biological, pathogenic, or infectious material shall be doubly packaged in new or properly recertified containers which meet the general packaging requirements of DOT as follows:

A. First, the inner container having a capacity of 55-gallon or less shall have a water tight liner at least 4 mils thick hermetically sealed after filling.

B. The biological material shall be thoroughly layered in the inner container in a ratio of thirty (30) parts biological material to at least one (1) part slaked lime and ten (10) parts absorbent, which shall be agricultural grade 4 vermiculite or medium grade diatomaceous earth, or other adsorbents that have received approval from the Department by volume. The addition of formaldehyde is strictly prohibited.

c. The closure on the inner container shall be a standard lid with securely attached ring and bolt. Lever locks are not acceptable.

D. Unless otherwise authorized by the Department, the outer container, which shall have a volume of at least 1.5 times the inner container shall be filled initially with at least 4 inches of absorbent material, specified in B., the inner container in an upright position, and the remaining volume filled with the absorbent material, then securely closed and properly sealed.

54. Unless otherwise authorized by the Department, the licensee shall receive Special Nuclear Material (SNM) as authorized in Conditions 5, 6, 7, and 8 of this license in 55 gallon or larger containers only. Any SNM shipment in which there is evidence that SNM is missing or that the waste packages have been tampered with in transport shall be received by the licensee and safely stored pending notification to the Department. The licensee shall not dispose of such packages unless authorized by the Department.

Contamination Limit Conditions

55. For receipt at the Barnwell Site, all shipments shall comply with contamination control limits as prescribed in US DOT Regulations, 49 CFR 173.443.

Page 11 of 17 Pages SOUTH CAROLINA DEPARTMENT OF HEALTH AND ENVIRONMENTAL CONTROL Radioactive Material License Supplementary Sheet License Nwnber 097 Amendment Nwnber 49 Enclosed radioactive material transport vehicles used solely for transporting radioactive materials and marked "For Radioactive Material Use Only" and accessible surface of transport casks and trailer shall not be released from the site if contamination limits exceed the following:

A. Fixed contamination of 10 mR/hr on contact with the interior surface or 2 mR/hr at I meter from the interior surface.

B. Removable contamination of 2200 dpm/IOO sq. cm. Beta-gamma or 220 dpm/IOO sq. cm. Alpha.

This applied to interior and exterior surfaces.

C. Fixed contamination of 0.5 mR/hr on contact with any exterior surface.

Internally contaminated (fIxed or removable) shipping casks released from the site are subject to applicable shipping regulations of the US DOT. The licensee shall inform the recipient of such casks of the contaminated nature ofthe cask. Shipping documentation for the casks must be maintained by the licensee for review by the Department.

56. Vehicles used solely for transporting radioactive material and are not marked "For Radioactive Material Use Only" shall not be released from the site if the contamination limits exceed the following:

A. Fixed contamination of 0.5 mR/hr at any accessible surface.

B. Removable contamination of2200 dpm/IOO sq. cm. Beta-gamma, or 220 dpm/IOO sq. cm. Alpha.

57. Vehicles or items for unrestricted use shall not be released from the site if the contamination limits exceed the following unless specifically authorized by the Department:

A. Fixed contamination of 0.1 mR/hr at any accessible surface.

B. Removable contamination of220 dpm/lOO sq. cm. Beta-gamma, or 22 dpm/IOO sq. cm. Alpha.

58. The licensee shall perform decontamination on vehicles, equipment, or components, with contamination limits in excess of those specifIed in Condition 56 in a controlled environment.

59. The licensee shall not use its vehicle wash-down facility for any vehicles or equipment with removable contamination limits in excess of those specified in Condition 56 unless specifIcally approved by the Department.

General Packaging Conditions

60. All radioactive waste shall be packaged and loaded in accordance with applicable US DOT Regulations, US NRC Regulations 10 CFR Part 71, the requirements of this license, and the disposal site criteria.

Ql. Unless otherwise authorized, all radioactive waste shall be received and buried in closed containers.

Containers which have been altered, and solidification or encapsulation media intended to serve as containers or container closures, are not acceptable unless approved by the Department. Loose radioactive waste and solidifIcation residuals within shipping casks or other reusable containers are prohibited.

62. The licensee shall not receive any package to be used as the final burial container that is corroded to the point of degradation or damage. Any package used as the final burial container shall be of such material

Page 12 of 17 Pages SOUTH CAROLINA DEPARTMENT OF HEALTH AND ENVIRONMENTAL CONTROL Radioactive Material License Supplementary Sheet License Number 097 Amendment Number 49 construction that there will be no significant chemical, galvanic, or other reaction among the packaging components, or between the packaging components and the package contents.

63. The licensee shall, to the extent practicable, repair or repackage any damaged package used as the final burial container if such packages are approved for acceptance by the Department.

64. Prior to burial, the licensee shall, to the extent practicable, remove all liquids from waste packages found in excess of allowable limits if such packages are approved for acceptance by the Department.

65. The licensee shall not receive shipments of radioactive materials unless appropriate lifting devices of sufficient length has been provided and securely attached to containers and palletized shipments within a cask.

66. The licensee is not authorized to open any packages at its facility, except for the following:

A. For purposes of repairing or repackaging damaged containers.

B. For purposes of inspecting to insure compliance with this license.

C. For purposes of returning outer shipping containers.

D. For purposes of confirming package contents.

Site Design, Construction and Maintenance Conditions

67. Construction of waste burial trenches shall be in accordance with CNS Procedure S20-AD-008, "Trench Construction" and Department approved drawings and specifications. Any changes to these drawings, specifications, or procedures must have approval from the Department before implementation.

68. The licensee shall not begin construction of any trench prior to approval of the Department as to location, trench bottom elevation and intended use.

69. The licensee shall not initiate burial operations in newly excavated trenches until the Department has inspected and approved the trenches. Trench construction inspections shall be performed in accordance with CNS Procedure S20-AD-008, "Trench Construction" and any additional inspections deemed necessary by the Department.

70. Trench backfill and completion shall be performed in accordance with CNS Procedure S20-AD-008, "Trench Construction".

n* A. Completed trenches shall at no time be used for stockpiling large volumes of earth not withstanding provisions for a final grading plan.

B. The licensee shall design trench covers to minimize to the extent practicable water infiltration, to direct percolating or surface water away from the disposed waste, and to resist degradation by surface geologic processes and biotic activity.

72. Open trenches to include trenches under construction and partially filled trenches shall be protected to prevent runoff water from entering trenches. Radioactive waste shall not be placed into trench areas where water has

Page 13 of 17 Pages SOUTH CAROLINA DEPARTMENT OF HEALTH AND ENVIRONMENTAL CONTROL Radioactive Material License Supplementary Sheet License Number 097 AJnendrnent Number 49 accumulated. Burial of radioactive waste into trenches with unusual amounts of water shall immediately cease until the origin of water has been determined and corrective action taken.

73. The licensee shall use proper surface water management techniques on the site to insure that:

A. Erosion is minimized.

B. Surface runoff is directed away from the trenches.

C. Accumulation of standing water is minimized.

D. Standing water in the immediate disposal area is prevented.

74. All monitoring wells, sumps, shall be sufficiently capped or covered to prevent the introduction of extraneous material or infiltration ofwater. All well and sump pipes shall be protected from damage.

75. The licensee shall perform inspections of completed trenches and capped areas in accordance with CNS Procedure S20-0P-007, "Completed Trench Inspection Procedure", to ascertain any erosion, settling, cracking, subsidence, or loss of ground cover grasses and make corrections immediately. Documentation of the inspection findings and all repairs even if the repairs were performed as a routine maintenance function shall be made and incorporated into a permanent record and submitted with the stabilization plan for final site closure.

76. The licensee shall initiate closure and stabilization measures as each trench is filled and covered. Interim or final grades shall be established at no more than one year following final trench burial operations. Completed trenches shall be continuously and properly maintained to control erosion. Active waste disposal operations must not have an adverse effect on completed closure and stabilization measures.

77. The licensee shall use any reasonable means, including but not limited to fencing and security personnel, to prevent unauthorized entry into the restricted area of the site.

78. The boundaries and locations of each disposal trench shall be accurately located and mapped by means of a land survey. Temporary trench boundary markers and trench identification markers shall be erected upon completion ofbackfill operations until permanent markers are installed.

79. A series of markers, one at the end of each completed trench and on each corner, shall be installed upon completion of the seeding of trench covers. End monuments shall be constructed of granite. Trench corner markers shall be constructed in accordance with CNS Drawing No. B-2 I5-C-OOI O. The following information shall be reported to the Assistant Director, Division of Waste Management, Bureau of Land &

Waste Management, SC DHEC, 2600 Bull Street, Columbia, SC 29201:

A. Total activity of radioactive material in curies total amount of source material in pounds, and total amount of special nuclear material in grams in the trench.

Appendix D C, Page _13_ of_17_

Project No. 29487-NCS0097.N.LAS B. Date of completion of the burial operations; and EC nCR # 375636 C. Volume ofwaste in the trench.

Page 14 of 11 Pages SOUTH CAROLINA DEPARTMENT OF HEALTH AND ENVIRONMENTAL CONTROL Radioactive Material License Supplementary Sheet License Nwnber 097 Amendment Nwnber 49 Burial Operation Conditions

80. Unless specifically authorized by the Department, the licensee shall not exhume previously buried waste.

81. All waste shall be placed in vaults which will provide additional structural stability. Structural evaluations for large components may be submitted to the Department for review and with concurrence from the Department will not require disposal in a vault. The licensee shall construct the vaults in accordance with procedures, drawings, standards, and a quality assurance plan that have received approval from the Department.

82. The disposal trenches and vaults shall be designed and constructed to meet the following objectives:

A. to minimize the migration of water onto the disposal trench.

B. to minimize the migration of waste or waste contaminated water out of the disposal units.

C. to detect water or other liquids in the trenches for assessment and potential remedial measures.

D. to facilitate remedial methods without disturbing other disposal trenches.

E. to provide reasonable assurance that the waste will be isolated for at least the institutional control period.

F. to prevent contact between the waste and the surrounding earth, except for earthen materials used for backfilling within the disposal unit.

83. Wastes designated as Class C pursuant to Condition 31 of this license, shall be disposed of so that the top of the waste is a minimum of 5 meters below the top surface of the cover or shall be disposed of with intruder barriers that are designed to protect against an inadvertent intrusion for at least 500 years. Such intruder barrier designs must be specifically approved by the Department.

84. The licensee shall handle and emplace packages of radioactive waste in disposal trenches in such a manner that maintains packaging integrity during handling, emplacing, and subsequent backfilling. Waste packages deposited in trenches shall be protected from any adverse operations which may cause damage to them.

85. The licensee shall emplace disposal vaults in such a manner to minimize voids between vaults and permit voids between vaults to be filled with earth to reduce future trench subsidence.

86. The licensee shall be a "Registered User" of all licensed casks delivered to the site containing radioactive waste for disposal.

87. At least one health physics technician shall be present during all waste handling, offloading, and disposal operations.

88. The licensee shall maintain radiation levels at the edge of the open trenches at or below 100 mR/hr.

89. Licensee personnel shall wear appropriate protective clothing, apparatus, and gloves at all times while handling or disposing of radioactive waste.

90. Vaults shall be covered within six (6) months of being filled with waste unless otherwise approved by the Department.

Appendix DC, Page _14_ of_17_

Project No. 29487-NCS0097.N.LAS EC DCR # 375636

Page 15 of11 Pages SOUTH CAROLINA DEPARTMENT OF HEALTH AND ENVIRONMENTAL CONTROL Radioactive Material License Supplementary Sheet License Number 097 Amendment Number 49

91. The licensee shall bury containers of Krypton 85 and Xenon 133 gaseous radioactive materials in upright positions within concrete overpacks or vaults. Each gas container shall be disposed in different overpacks or vaults unless otherwise authorized by the Department.

92. Unless specifically authorized, the licensee shal1 not store any package containing radioactive waste for a period greater than six months from the date of receipt of the package prior to burial. Radioactive waste shall not be stored in the trench area or an open environment for a period greater than ten (10) days from receipt, and shall be protected from damage and inclement weather conditions.

Environmental Surveillance Conditions

93. The licensee shall conduct an on-site monitoring and environmental monitoring program capable of detecting the potential contribution of radioactive material and hazardous constituents from the site to the environment.

The monitoring program shall be performed in accordance with CNS Procedures

94. Should any samples taken from the monitoring wells, or air samples reveal increases in the concentration of radioactive material which were determined prior to commencement of the burial operations, the licensee shall perform further surveys to determine whether or not the increase is due to the land burial operations. The licensee shal1 notify the Assistant Director, Division of Waste Management, Bureau of Land & Waste Management, SC DHEC, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of any such increases.

95. The licensee shal1 submit results of al1 scheduled environmental sampling and analysis to the Department quarterly.

96. Monitoring wel1s shall be placed outside the trenches but in the trench area. Specific locations shall be determined through consultation. All wells shal1 be grouted, sealed and capped.

97. As radioactive material buried may not be transferred by abandonment or otherwise, unless specifically authorized by the Department, the expiration date of this license applies only to the above ground activities and to authority to bury radioactive material wastes at the site specified in Condition 9. The license continues in effect and the responsibility and authority for possession of buried radioactive material waste continues until the Department finds that the plan established for preparation of the Bamwel1 Site for transfer to another person has been satisfactorily implemented in a manner to reasonably assure protection of the public health and safety and the Department takes action to terminate the licensee's responsibility and authority under this license. AI1 requirements for environmental monitoring, site inspection, maintenance and site security continue whether wastes are being buried or not.

98. The licensee shal1 develop a site closure and stabilization plan that addresses, as a minimum, the following performance objectives:

A. Bury all waste in accordance with the requirements of the license.

B. Dismantle, decontaminate, as required, and dispose of all structures, equipment, and materials that are not to be transferred to the site custodian.

C. Document the arrangements and the status of the arrangements for orderly transfer of site control and for long term care by the government custodian. Also document the agreement, if any, of state or federal governments to participate in, or accomplish, any performance objective. Specific funding arrangements to assure the availability of funds to complete the site closure and stabilization plan must be made.

Page 16 of 11 Pages SOUTH CAROLINA DEPARTMENT OF HEALTH AND ENVIRONMENTAL CONTROL Radioactive Material License Supplementary Sheet License Number 097 Amendment Number 49 D. Direct gamma radiation from buried wastes should be essentially background.

E. Demonstrate by measurement and/or model during operations and after site closure that concentrations of radioactive material which may be released to the general environment in ground water, surface water, air, soil, plants, or animals will not result in an annual dose exceeding an equivalent of 25 millirems to the whole body, 75 millirems to the thyroid, and 25 millirems to any other organ of any member of the public.

F. Render the site suitable for surface activities during custodial care. Planned custodial care may be limited to activities such as vegetation control, minor maintenance, and environmental monitoring.

However, use of the site surface for activities such as parking lots may be planned. Final conditions at the site must be acceptable to the government custodian and compatible with its plan for the site.

G. Demonstrate that all trench elevations are above water table levels taking into account the complete history of seasonable fluctuations.

H. Eliminate the potential for loss of site or trench integrity due to factors such as erosion, surface water, wind, subsidence, and frost action. For example, an overall site surface water management system must be established for humid sites to drain rainwater and snowmelt away from the burial trenches. All slopes must be sufficiently gentle to prevent slumping or gullying. The surface must be stabilized with established short rooted grass, rock, riprap, or other measures. Trench caps must be stabilized to minimize erosion, settling, or slumping of caps.

I. Demonstrate that trench markers are in place, stable, and keyed to benchmarks. Identifying information must be clearly and permanently marked.

1. Compile and transfer to the Department complete records of site maintenance and stabilization activities, trench elevation and locations, trench inventories, and monitoring data for use during custodial care for unexpected corrective measures and date interpretation.

K. Establish a buffer zone surrounding the site sufficient to provide space to stabilize slopes, incorporate surface water management features, assure that future excavation on adjoining areas would not compromise trench or site integrity, and provide working space for unexpected mitigating measures in the future. The buffer zone must also be transferred to the custodial agency. The buffer zone may generally be less than 300 feet but not less than 100 feet.

• C/)

1'lj L. Provide a secure passive site security system (e.g., a fence) that requires minimum maintenance.

-':i I .

,,-,'1' o 0\ M. Stabilize the site in a manner to minimize environmental monitoring requirements for the long-term o custodial phase and develop a monitoring program based on the stabilization plan.

10

\OC/)

-u Iz I , N. Investigate the causes of any statistical increases in environmental samples which have occurred o r--.

1:>/)00 during operation and stabilization. In particular, any evidence of unusual or unexpected rates or C<l "<t A., 0\ levels of radionuclide or hazardous constituent migration in or with the groundwater must be N

analyzed and corrective measures implemented.

o. Eliminate the need for active water management measures, such as sump or trench pumping and treatment of the water to assure that wastes are not leached by standing water in the trenches.

P. Evaluate present and zoned activities on adjoining areas to determine their impact on the long-term performance of the site and take reasonable action to minimize the effects.

Page 17 of 11 Pages SOUTH CAROLINA DEPARTMENT OF HEALTH AND ENVIRONMENTAL CONTROL Radioactive Material License Supplementary Sheet License Number 097 Amendment Number 49

99. An interim site closure and stabilization plan, assessment of current operating practices, and the long term care plan for the site shall be submitted for review one year prior to the expiration date listed in Condition 4 of this license. The plan shall be consistent with Condition 98 of this license and shall include demonstration that funds are being set aside or other measures being taken are adequate to finance site closure and long term care.

The plan shall also include preliminary estimates of costs, environmental impacts, data needs, personnel needs, material and equipment needs, planned documentation and quality assurance, and detailed plan for trench locations and elevations, expected capacities, planned surface contours, and buffer zones.

100. The licensee shall periodically assess the adequacy of the Decommissioning Trust accounts and any other financial mechanisms to assure that sufficient funds are available to complete the remaining activities required to close and stabilize the site in accordance with the latest revision of the site closure fund. The licensee shall provide an annual report of this assessment in accordance with RHA 7.30.3 to the Department by June 30.

For the South Carolina Department of Health and Environmental Control Date of Issuance By:

Henry J. Porter, Assistant Director Division of Waste Management Bureau of Land and Waste Management Appendix C, D Page _17_ of _17_

Project No. 29487-NCS0097.N.LAS EC DCR # 375636

APPENDIX E FIRE HAZARD ANALYSIS REPORT FOR INTERIM RADWASTE STORAGE FACILITY LASALLE COUNTY NUCLEAR STATION Appendix E - Page 1 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09

1.0 INTRODUCTION

1.1 Scope This section consists of a review of fire protection and life safety related to the Interim Radwaste Storage Facility Project for LaSalle County Nuclear Station. Information gathered for the analysis includes drawings and specifications as referenced documents herein.

1.2 Limitations This analysis was performed as part of the LaSalle County Station IRSF 10 CFR 50.59 LAR Support Technical Report, and presumes no significant changes to the Interim Radwaste Storage Facility were made since 1994.

1.3 Criteria for Evaluation Combustible fire loadings used in developing the results of this Fire Hazard Analysis are as follows:

Combustible Fire Loading Electrical insulation 10,500 btu/lb Class A (wood, paper, etc.) 8,000 btu/lb Vehicle tires 14,000 btu/lb Oil (any type, 2, one pint each) 150,000 btu/gal High-density polyethylene 20,000 btu/lb Diesel fuel 150,000 btu/gal Resins (when dried) 18,800 btu/lb Transient combustibles and their use in the project's facilities are considered to be limited. Materials used during maintenance activities and paper supplies are considered transient.

Electric power, control, and instrumentation cable construction meet the smoke and flame test requirements of IEEE 383/UL 1277. The contribution of cable within conduit to the fire loading in an area is dependent on the severity of the postulated design basis fire.

Due to the non-propagating properties of the cable and the fact that the cable is enclosed in non-combustible metal conduit, cable will not be considered to pyrolyze inside the conduit unless the temperature shown on the standard time-temperature curve corresponding to the calculated equivalent severity is above 1100 oF (Reference NFPA Appendix E - Page 2 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Fire Protection Handbook, pages 7-109 through 7-111, Fire Severity" and "Standard Time-Temperature Curve, Attachment C.).

Occupancy for this facility is considered to be Special Purpose Industrial with regard to NFPA 101, Life Safety Code, 1988, Group B, Div. 2 with regard to the Uniform Building Code (UBC) and Ordinary Hazard, Group 2 with regard to NFPA 13, Standard for the Installation of Sprinkler Systems, 1991.

The Interim Radwaste Storage Facility serves for interim and long term (extended) storage of containerized Radwaste. This facility is not reactor safe-shutdown related (safety-related).

1.4 Evaluation Assumptions For the purposes of this report, outside walls are not considered requiring a fire rating unless an exterior combustible (i.e., oil filled transformer, etc.) exists, which creates an exposure hazard.

Small quantities of grease (< one pound) or oil (< one quart) used as a lubricant in valves, motors, pans, damper operators and pumps will not be considered as contributing to a fire when contained within packing glands, bearings, or reservoirs.

Electric power and electric equipment such as motor control centers will not contribute significantly to the fire loading due to their metal enclosures. Similarly, totally enclosed electric motors are not considered to contribute significantly to fire loading.

It is assumed that a postulated fire is unlikely to exist if only electrical cables are involved. The construction of the specified electrical power, control, and instrumentation cable meets IEEE 383/UL 1277 which certify the cables non-propagational and fire resistance capabilities.

Electrical faults will be mitigated by selective tripping of breakers or blowing of fuses.

All cables, except festoon cables servicing the bridge crane, are in conduit.

Appendix E - Page 3 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 1.5 Definitions FIRE AREA- An area of a facility that is separated from other areas by complete fire barriers with at least a two hour rating. This includes walls, floors, and ceilings, with any openings therein protected with seals or closures having a fire resistance rating equal to that of the barriers.

FIRE ZONE- the subdivisions of fire areas (as defined above) which are subdivided by fire rated partitions or special separation.

HIGHLY PROTECTED RISK - The term involves the use and application of judgment and thus does not lend itself to a precise, fixed definition applicable, in all locations and situations. It has the same meaning and intent as is commonly understood when this or the term, improved risk, is used in the insurance industry. Generally, a Highly Protected Risk property is one that would qualify for complete insurance coverage by the Factory Mutual System, the Industrial Risk Insurers, and other industrial insurance companies that limit their insurance underwriting to the best protected class of industrial risk. The most evident characteristic of such a property is the existence of reliable, automatic fire extinguishing systems throughout all buildings of combustible construction or content where the building is vital to operational, continuity or may experience a large property loss from fire in the absence of an automatic extinguishing system.

DESIGN BASIS FIRE - A fire that is the most severe accident of this type. In postulating such a fire, failure of automatic and manual fire suppression provisions is assumed except for those safety class items/systems that are specifically designed to remain available (structurally or functionally) through the event.

FIRE HAZARD ANALYSIS - An analysis, documented in report form, which establishes a systematic approach to fire protection design which will ensure that all fire protection requirements are met and will facilitate a fire protection review. The analysis is documented in report form in the facility project files and referenced by the Safety Analysis Report.

MAXIMUM CREDIBLE FIRE LOSS - The maximum loss that could occur from a combination of events resulting from a single fire. Any installed fire protection systems are assumed to function as designed. Due to the uncertainties of predicting human action, the effect of emergency response is generally omitted except for post-fire actions such as salvage work, shutting down water systems, and restoring production.

Appendix E - Page 4 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 MAXIMUM POSSIBLE FIRE LOSS - The maximum possible loss that could occur in a single fire area assuming the failure of both automatic and manual fire extinguishing actions.

2.0 PURPOSE AND OBJECTIVES Fire Protection Design Analysis The purpose and objectives of this analysis are to:

x Demonstrate that the hazards to on-site personnel and off-site population as a result of a fire are maintained as low as reasonably achievable, in accordance with NRC regulations and LaSalle County Nuclear Station policy.

x To insure facility compliance with the applicable NFPA requirements in the areas of fire protection and life safety.

x Determine and recommend those special fire prevention and protection features and controls necessary to achieve a level of "Highly Protected Risk fire protection.

3.0 REFERENCE CODES, STANDARDS, AND DRAWINGS The following codes, standards, and reference documents have been utilized in the development of this report And, except for NFPA 801, were current when the IRSF was originally assessed via a 50.59 evaluation (1992).

Codes and Standards (and other references)

National Fire Protection Association (NFPA) Standards and

References:

NFPA 10 Portable Extinguishers, 1988 NFPA 13 Installation of Sprinkler Systems, 1989 Appendix E - Page 5 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 NFPA 14 Standpipe and Hose Systems, 1990 NFPA 15 Water Spray Fixed Systems, 1990 NFPA 24 Installation of Private Fire Service Mains, 1987 NFPA 26 Supervision of Valves Controlling Water Supplies, 1988 NFPA 70 National Electric Code, 1990 NFPA 72 Installation, Maintenance, and Use of Local protective signaling Systems, 1990 NFPA 72E Automatic fire Detectors, 1990 NFPA 72H Testing Procedures for Local, Auxiliary, Remote Station and Proprietary Protective Signaling Systems, 1988 NFPA 80 Fire Doors and Windows, 1990 NFPA 80A Exterior Fire Exposures, 1987 NFPA 90A Installation of Air Conditioning and NFPA 101, Ventilating Systems, 1989 NFPA 101 Life Safety Code, 1991 NFPA 203M Roof Coverings and Roof Deck Construct ions, 1987 NFPA 241 Safeguarding Construction, Alteration, and Demolition Operations, 1989 NFPA Fire Protection Handbook, 16th Edition, 1986 Appendix E - Page 6 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 NFPA 801 Standard for Fire Protections for Facilities Handling Radioactive Material, 2008 Uniform Building Code, 1988 Edison Electric Institute, Suggested Guidelines for Completing a Fire Hazards Analysis for Electric Utility Facilities," April 1981 U.S. Government-Occupational Safety and Health Administration (OSHA) Part 1910, Title 29 of Federal Regulation", 1984 10CFR50.59- Domestic Licensing of Production and Utilization Facilities, Changes, Tests, and Experimentsm,1991 Underwriters Laboratory (UL), Fire Resistance Directory, 1989 Drawings As listed on the Fire Hazard Analysis Detail Sheets Specifications None 4.0 FACILITY OVERVIEW 4.1 Description, Location, Construction This facility provides long-term storage of Class B/C radioactive wastes resulting from normal operations. In July 2008, Barnwell Burial Facility stopped receiving generated Radwaste material from out of compact nuclear facilities. Class B/C radioactive wastes generated by the LaSalle Station and potentially Byron, Braidwood and Clinton stations will be accepted at this facility.

This facility is located on the site of LaSalle County Nuclear Station.

The exterior of the storage and truck bays of the structure is reinforced concrete, including the roof. Control room and mechanical equipment exterior walls are cement Appendix E - Page 7 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 masonry units. Floors are slab-on-grade. The storage area is surrounded by walls of minimum 30 inches thick reinforced concrete up to a height of 34 feet and is 12-15 inches thick in the roof. The storage area is separated from the truck bay by a 30 inch reinforced concrete wall up to a height of 34 feet. There is no separating wall above the 34 feet elevation. There is an opening notch 7 feet by 7 feet at the top of this wall. The truck bay is surrounded by minimum 15 inches thick concrete exterior walls for passing containers through/from the storage bay. A truck entrance is located at one end of the truck bay while personnel doors are located at each end of the truck bay. In addition, a forklift entrance is located in the truck bay near the truck entrance.

4.2 Important Processes, Equipment, and Cabling Quantities of Radwaste that will be moved into the storage area are limited to the size of one transportation vehicle at any given time (normally a single HIC). Waste is expected to be either processed waste in the form of dewatered bead resins (e.g., DOWEX) or powdered resins (e.g., Powdex). Dewatered resin waste will be contained in HICs made of molded high-density polyethylene or poly HICs in metal shells. The HICs feature filtered vents and are corrosion resistant. The new container size limitation is no larger than a standard size 195 cu. ft. due to the wall opening limitation of 7 feet by 7 feet. The standard HIC will be 8-120 , having an internal volume of 107.6 ft3, 61.5 in diameter, and 73.5 in height, but others container sizes have been generated and are currently waiting for a long-term storage.

Corrosive, reactive, and other radioactive mixed wastes are not authorized for IRSF storage.

The following paragraph describes the IRSF waste loading process.

A tractor-trailer is moved into the truck bay area. The tractor is disengaged and the truck removed from the facility. The truck bay doors are then closed. The ventilation system is shut down. The trailer's contents are removed by a remote-operated crane and hoisted into the storage area. The IRSF crane is equipped with a winch system which permits it to be manually retracted over the truck bay without electrical power or functioning drive motors. The design of container lifting equipment is such that dropping a container is highly unlikely. Additionally, containers are constructed in accordance with DOT standards and are, therefore, highly resistant to impact damage. Consequently, the probability that a container drop will occur and the contents be released within the truck bay is low, and in any case will not credibly spread beyond the Truck Bay zone.

With the truck cab removed, significant sources of potential ignition are not available in the truck bay. Additionally, Manual Fire Suppression and smoke detectors are provided Appendix E - Page 8 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 for the truck bay. Consequently, the probability that any combustible contents will be released or exposed to any source of ignition within the truck bay is low.

4.3 Epoxy Coating The LaSalle County Station IRSF Specification No. 70160-2000-14 for Field Painting specifies epoxy coating applied to the storage bay floor and from the floor up to 10 on the four side walls of the storage bay as follows: interior concrete floors with sprayed on one coat of Keeler & Long No. 3500 Kolor-Poxy self-priming surfacing enamel primer/finish, with a dry film thickness (DFT) of 10 to 30 mils; interior concrete walls with a seal coat of Keeler & Long No. 4129 Epoxy Clear Curing Compound, 0.5 to 1.5 DFT, + strike flush coat of Keeler & Long No. 3500 Kolor-Poxy self-priming surfacing enamel, 1.0 to 5.0 DFT, + body coat of Keeler & Long No. 3500 Kolor-Poxy self-priming surfacing enamel) thickness, 20 to 40 mils DFT.

NRC Industry Notice 2007-26 on Combustibility of Epoxy Floor Coatings at Commercial Nuclear Power Plants defines a non-combustible material as:

a. A material which in the form in which it is used and under the conditions anticipated, will not ignite, burn, support combustion, or release flammable vapors when subjected to fire or heat; and

b. Material having a structural base of noncombustible material, as defined in a., above, with a surfacing not over 1/8-inch thick that has a flame spread rating not higher than 50 when measured using the test protocol of American Society for Testing and Materials (ASTM) E 84, Standard Test Method for Surface Burning Characteristics of Building Materials.

On July 22, 2009, URS - Washington Division personnel met with Mr. John De Barba, Field Technical Service Manager for PPG Protective & Marine Coatings, the current owner of Keeler & Long, to discuss the flame spread rating of the Keeler & Long epoxy surface finish 4500. Mr. De Barba initially provided test results performed in accordance with ASTM Standard E-84, indicating tested values of 45 for all thicknesses tested up to 25 mils dry film thickness. Mr. De Barba indicated that thicknesses above this level would not be applicable despite the Field Painting Specification, as cracking of the coating takes place above these thicknesses which would render them as unacceptable upon inspection. However, in response to a URS - Washington Division request for additional information regarding flame spread ratings of thicker Keeler & Long epoxy No. 3500, Mr. De Barba provided additional ASTM Standard E-84 test results of a flame spread index of 53.059 for coatings up to 30 mils in dry mil thickness.

Appendix E - Page 9 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Industry Notice 2007-26 indicates that epoxy floor coverings at the Donald C. Cook Nuclear Power Plant with thickness between 0.115 inches (115 mils) and 0.230 inches (230 mils) with flame spread ratings of 140 to 150, and at the Duane Arnold Energy Center with a flame spread rating of 110, were acceptable with respect to not causing fires to propagate. As Exelon IRSF epoxy floor coating thicknesses and flame spread ratings are both less than one-half those considered acceptable with respect to combustibility at other plants, the Exelon IRSF epoxy floor coating is considered acceptable with respect to not causing fires to propagate.

In conclusion, although testing for up to 30 mils dry film thickness of KL3500 resulted in Flame Spread Rating slightly above 50, the LaSalle IRSF epoxy coating is considered non-combustible based on:

x Epoxy dry film thicknesses sufficient to result in flame spread ratings above 50 would be subject to unacceptable cracking upon application, and therefore actual thicknesses would have flame spread ratings below 50.

x Industry Notice 2007-26 actual plant data indicates non-combustibility of epoxies at much greater thicknesses and higher flame spread ratings.

4.4 Fire Detection Systems The fire alarm systems in the IRSF are Class A supervised, designed and installed in accordance with NFPA 72, 1990 and NFPA 72E, 1990 and UBC, 1990. The local panel alarms locally and remotely in the reactor control room (manned 24/7) and in the IRSF control room. The fire detection system causes closure of duct-mounted fire dampers by melting a fusible link when high temperatures are obtained in cases of a fire.

There are no fire detection systems in the storage area. However, a single fire detector is located directly over the storage bay/truck bay interface wall, and three (3) duct smoke detectors are located in the ventilation recirculation return ducts from the storage bay.

Additionally, likelihood of fire in the storage bay area is considered extremely remote.

The truck bay is protected by smoke detectors which transmit an alarm to the local alarm panel.

The mechanical equipment room is protected by ionization type smoke detectors which transmit an alarm to the local alarm panel. Supply air ducts are equipped with duct-mounted smoke detectors which cause interruption of fan operation in addition to transmitting an alarm signal.

Appendix E - Page 10 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 The IRSF control room is protected by ionization type detectors which transmit an alarm to the local alarm panel.

4.5 Fire Suppression Systems Exterior:

A looped fire main is provided at the site. Hydrants are spaced so that the distance to all portions of buildings and structures is not more than 300 ft. At least two hydrants are within 500 feet of the structure.

Mobile fire units are available on a 24-hour-per-day basis from the Marseilles, IL Fire Department. These units are available to respond to an emergency.

Interior:

Dry chemical fire extinguishers are provided per NFPA 10 in the truck bay.

4.6 Ventilation Description The Interim Radwaste Storage Facility HVAC system is comprised of three subsystems.

This non-safety-related system is designed to maintain temperature within the facility for storage of Radwaste, control and mechanical equipment ventilation; and limits the minimum IRSF temperature to 50oF.

The system is designed to maintain the control room at 75oF nominal; the equipment room at 70-120oF; and the storage area/truck bay at 50-120oF.

The IRSF system is designed to function with variable quantities of outside air intake, from maximum recycle to 100% outside air intake. This ventilation system is adequate to prevent the buildup of potential combustible gases vented from containers of dewatered waste and to maintain an inside thermal environment without excessive temperature extremes.

Heating and ventilation in the truck bay and storage bay are provided by a 19,500 cfm fan with an electric coil. During cooling season the system operates on 100% outside air.

During heating season outside air dampers move to the minimum position, allowing 3,450 cfm of outside air into the building. The remaining 16,050 cfm of ventilation air is recirculated. Auxiliary heating in the truck bay is provided by a duct-mounted electric coil and electric unit heaters. Truck bay and storage bay exhaust is via a louvered vent located on the mezzanine level in the truck bay.

Appendix E - Page 11 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Ventilation in the mechanical equipment room is provided by a 4000 cfm rooftop exhaust fan and motor operated wall louvers. Heating is provided by unit heaters.

Heating, ventilation and air conditioning is provided in the control room by a ducted split system air conditioning unit located in the mechanical equipment room. Heat is provided by duct-mounted electric coils. Outside air is taken in via a louver with motor operated damper connected to the return air duct in the mechanical equipment room. Air is exhausted via a rooftop exhaust fan.

Appendix E - Page 12 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 5.0 DESIGN BASIS FIRE ANALYSES Design Basis Fire Analysis Data Sheets The sheets in Section 6.0 (Attachments) provide detailed information for each fire zone and/or area.

5.2 Ignition Sources Ignition sources in the IRSF storage bay are relatively limited. NFPA reported that 29%

of fires initiates by an electrical ignition source and 34% by open flames. See Figure 1 for detail . In the IRSF, there is no human accessibility in the storage bay; therefore the only credible ignition source is failure of the crane cable and direct contact with the combustible material. As calculated in IRSF Storage Bay Fire HIC Spacing Assessment L-003429, Rev 000, such direct contact would be required for a period of 1,386 seconds to result in ignition.

Ignition Sources in Industrial Fire in Storage Facilities Electrical Equipment Open Flame 29%

34%

Cigarette 6%

Hot Object 6% Spontaneous Ignition 7%

Cutting/Welding Fuled Fired equipment 9%

9%

Figure 1- Ignition Sources in Industrial Fire in Storage Facilities Extracted from Industrial Fire Protection Engineering pg 18 based on NFPA large data excluding fires with unknown ignition sources In addition, LaSalle created procedures to minimize the risk of fire in the IRSF building such as loading/unloading containers (see Section 4.2), periodic surveillance, and detectors.

Appendix E - Page 13 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 6.0 ATTACHMENTS Design Basis Fire Analysis Data Sheets:

6.1 DESIGN BASIS FIRE ANALYSIS TRUCK BAY AREA 6.2 DESIGN BASIS FIRE ANALYSIS CONTROL ROOM 6.3 DESIGN BASIS FIRE ANALYSIS EQUIPMENT ROOM 6.4 DESIGN BASIS FIRE ANALYSIS STORAGE AREA 6.4.1 CASE 1-HDPE HICS 6.4.2 CASE 2-6 HDPE HICS ARRAYED WITH ADEQUATE SEPARATION DISTANCE TO OTHER HICS TO ELIMINATE FIRE SPREAD 6.4.3 CASE 3-STEEL SHELL HICS Appendix E - Page 14 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 6.1 DESIGN BASIS FIRE ANALYSIS TRUCK BAY AREA

1.0 BUILDING

Interim Radwaste Storage Facility (IRSF) 2.0 FIRE AREA OR ZONE: IRSF-F1-Z1 2.1 ROOM: Truck Bay Area

2.2 LOCATION

N/A 2.3 REFERENCE DRAWING NOS. A-961, A-962, A-965, A-966, A-970, S-1473, S-1474, S-1476, S-1477, M-737; shts. 1-7, 1E-0-3341, 1E-0-334, 1E-0-3755, 1E-0-4673AA 3.0 CONSTRUCTION OF FIRE AREA OR ZONE BOUNDARIES BOUNDARIES MATERIAL MIN. FIRE RATING 3.1 WALL NORTH 30 & 15 concrete N/A ext. wall EAST 30 & 15 concrete N/A ext. wall SOUTH 30 conc. (part.) None WEST 30 & 15 concrete N/A ext. wall 3.2 FLOOR 30 concrete N/A slab on grade 3.3 CEILING N/A N/A 3.4 DOORS 1000 17x14 stl. Rollup N/A ext.

1001 7-2x3 HM N/A ext.

1002 8x10 stl. rollup N/A ext.

1003 68 x 3 HM 90 min. -B label 3.5 ROOF 15 conc. N/A ext.

Appendix E - Page 15 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 4.0 FLOOR AREA: 1920 SQ.FT.

LENGTH: 60 0 WIDTH: 32 0 HEIGHT: 49 0

5.0 VOLUME

94,080 CU.FT 6.0 FLOOR DRAINS YES X NO (drains to Truck Bay Sump) 7.0 VENTILATION SYSTEM DESCRIPTION 2,880 cfm of ventilation air is provided to the truck bay and 16,620 cfm to the storage area by a common supply fan. Outside intake is variable between 19,500 and 3,450 cfm. The balance of supply air is ducted return. Ratio of return to outside air is controlled by operable louvers. Intake air is preheated in HV unit in the mechanical room upstream of the main supply fan by an electric duct heater.

There is a thermostatically controlled heater in the duct branch leading to the truck bay for additional tempering. Duct passing through the control room is provided with fire dampers at points of penetration through fire rated walls. The truck bay is provided with an independent exhaust fan with 2880 cfm capacity, intended to remove diesel exhaust fumes during truck start-up. The truck bay is equipped with electric unit heaters.

8.0 FIRE PROTECTION TYPE 8.1 SUPPRESSION None 8.2 DETECTION Smoke detectors in truck bay 8.3 MANUAL Hydrant within 300 8.4 EXTINGUISHERS 20 lb class ABC or BC per NFPA 10 8.5 OTHER None 9.0 FIRE LOADING IN AREA 9.1 FLAMMABLES/COMBUSTIBLES FIRE LOADING IN AREA/ZONE Appendix E - Page 16 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 HEAT OF TOTAL HEAT HEAT COMBUSTIBLE AMOUNT COMBUSTION POTENTIAL POTENTIAL Electrical Insulation 500 lbs 10,500 Btu/lb 5,250,000 Btu 2,875 Btu/sq.ft 15,625 Diesel fuel 200 gal 150,000 Btu/gal 30,000,000 Btu Btu/sq.ft 13,125 Vehicle tires 800 lbs 14,000 Btu/lb 25,200,000 Btu Btu/sq.ft 8,855 HIC 850 lbs 20,000 Btu/lb 17,000,000 Btu Btu/sq.ft.

Class A: 150 lbs 8,000 Btu/lb 1,200,000 Btu 625 Btu/sq.ft.

Transients: 0 lbs 9.2 TOTAL FIRE LOADING IN AREA: 41,105 BTU/sq.ft.

9.3 TOTAL HEAT POTENTIAL: 78,921,609 BTU 9.4 Equivalent Severity: approximately 35 minutes O

9.5 TEMPERATURE

1575 F 10.0 PROCESS HAZARDS None.

11.0 DESIGN BASIS FIRE DESCRIPTION A fire starting in the truck bay is not considered credible because the three elements of fire (combustible material, ignition source, and unlimited oxygen supply) are not present at the same time. Exelon loading and unloading procedures are followed to minimize fire potential risks. See Section 4.2 for loading/unloading procedure description. In case of an incredible fire in the truck bay, manual and fire brigade are available for immediate remediation.

Only during this transient loading/unloading event there is a possible fire risk, which would be controlled.

12.0 CONSEQUENCES OF DESIGN BASIS FIRE No consequences are postulated.

Appendix E - Page 17 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 13.0 LIFE SAFETY CONSIDERATIONS 13.1 OCCUPANCY: NFPA 101: SPECIAL PURPOSES UBC: GROUP B.DIV 2 INDUSTRIAL 13.2 PROCESS HAZARDS: None 13.3 EMERGENCY LIGHTING: Meets all requirements 13.4 EXIT LIGHTING/SIGNS: Meets all requirements 13.5 CORRIDOR WIDTH: N/ A 13.6 EXITS AND EGRESS: Meets all requirements 13.7 TRAVEL DISTANCE TO EXIT: Meets all requirements 13.8 STAIRS: N/A 13.9 DOOR HARDWARE: Meets all requirements Appendix E - Page 18 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 6.2 DESIGN BASIS FIRE ANALYSIS CONTROL ROOM

1.0 BUILDING

Interim Radwaste Storage Facility (IRSF) 2.0 FIRE AREA OR ZONE: IRSF-F2 2.1 ROOM: Control Room

2.2 LOCATION

N/A 2.3 REFERENCE DRAWING NOS. A-962, A-962, A-966, A-965, A-970, M-737; shts. 1-7, 1E-0-3341, 1E-0-3341, 1E-0-3344, 1E-0-3755, 1E-0-4673AA 3.0 CONSTRUCTION OF FIRE AREA OR ZONE BOUNDARIES BOUNDARIES MATERIAL MIN. FIRE RATING 3.1 WALL NORTH 12 CMU N/A ext. wall EAST 6 CMU N/A ext. wall SOUTH 6 CMU 2-hr (lower)

WEST 30 conc. 3-hr (lower) 3.2 FLOOR 6 conc. N/A slab on grade 3.3 CEILING N/A 3.4 DOORS 1003 6 8 X 3 HM 90 min. B-label 1004 7 -2 X 3 HM N/A ext.

1005 (2) 7 2 X 3 HM 90 min. B-label 3.5 ROOF 12 concrete. N/A ext.

Appendix E - Page 19 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 4.0 FLOOR AREA: 266 SQ.FT.

LENGTH: 19 0 WIDTH: 14 0 HEIGHT: 16 4

5.0 VOLUME

4,344 CU.FT 6.0 FLOOR DRAINS YES NO X (drains to Truck Bay Sump) 7.0 VENTILATION SYSTEM DESCRIPTION Heating and cooling for the control room are provided by a split system air conditioning unit with heating coil. The unit supplies 1600 CFM of conditioned air. Return air volume is variable between 0 and 1440 CFM. Control room design conditions are 70oF minimum, 78oF maximum. Fire dampers are provided at points of penetration through fire-rated walls.

8.0 FIRE PROTECTION TYPE

8.1 SUPPRESSION

None

8.2 DETECTION

Smoke detectors in control room

8.3 MANUAL

Hydrant within 300

8.4 EXTINGUISHERS

20 lb class ABC or BC per NFPA 10

8.5 OTHER

None 9.0 FIRE LOADING IN AREA 9.1 FLAMMABLES/COMBUSTIBLES FIRE LOADING IN AREA/ZONE Appendix E - Page 20 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 HEAT OF TOTAL HEAT HEAT COMBUSTIBLE AMOUNT COMBUSTION POTENTIAL POTENTIAL Electrical insulation (see 15,800 11.0) 400 lbs 10,500 Btu/lb 4,200,000 Btu Btu/sq.ft Class A: 150 lbs 8,000 Btu/lb 1,200,000 Btu 4,525 Btu/sq.ft 8,000 Btu/lb (computer paper 9,025 Transients: 300 lbs stocks) 2,400,000 Btu Btu/sq.ft.

Others none 9.2 TOTAL FIRE LOADING IN AREA: 29,350 BTU/sq.ft.

9.3 TOTAL HEAT POTENTIAL: 7,807,000 BTU 9.4 Equivalent Severity: less than 30 minutes 10.0 PROCESS HAZARDS None.

11.0 DESIGN BASIS FIRE DESCRIPTION During maintenance operations, welding spark ignites pile computer paper stock.

Fire spreads to consume 150 lbs of class A combustibles. Cable within conduit pyrolyzes due to intensity of fire, adding additional heat of combustion.

12.0 CONSEQUENCES OF DESIGN BASIS FIRE Loss of ordinary combustible In control room ( i.e. , paper, wood products, cloth, etc.). Loss of electrical cable in conduit. Heat damage to cable and electronic components of control equipment. Loss of use of facility during repair period.

13.0 LIFE SAFETY CONSIDERATIONS 13.1 OCCUPANCY: NFPA 101: Special Purposes UBC:

Group B.Div 2 Industrial 13.2 PROCESS HAZARDS: None Appendix E - Page 21 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 13.3 EMERGENCY LIGHTING: Meets all requirements 13.4 EXIT LIGHTING/SIGNS: Meets all requirements 13.5 CORRIDOR WIDTH: N/ A 13.6 EXITS AND EGRESS: Meets all requirements 13.7 TRAVEL DISTANCE TO EXIT: Meets all requirements 13.8 STAIRS: N/A 13.9 DOOR HARDWARE: Meets all requirements Appendix E - Page 22 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 6.3 DESIGN BASIS FIRE ANALYSIS EQUIPMENT ROOM

1.0 BUILDING

Interim Radwaste Storage Facility (IRSF) 2.0 FIRE AREA OR ZONE: IRSF-F3 2.1 ROOM: Mechanical Equipment Room

2.2 LOCATION

N/A 2.3 REFERENCE DRAWING NOS. A-961, A-962, A-966, A-965, A-970, M-737; shts. 1-7, 1E-0-3341, 1E-0-3341, 1E-0-3344, 1E-0-3755, 1E-0-4673AA 3.0 CONSTRUCTION OF FIRE AREA OR ZONE BOUNDARIES BOUNDARIES MATERIAL MIN. FIRE RATING 3.1 WALL NORTH 6 CMU 2 - HR EAST 12 CMU N/A ext. wall SOUTH 12 CMU N/A ext. wall WEST 30 conc. 3 - HR 3.2 FLOOR 6 conc. N/A slab on grade 3.3 CEILING N/A 3.4 DOORS 1005 (2) 7 2 X 3 HM 90 min. B-label 1006 (2) 7 2 X 3 HM N/A ext.

3.5 ROOF 12 concrete. N/A ext.

Appendix E - Page 23 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 4.0 FLOOR AREA: 826.5 SQ.FT.

LENGTH: 43 6 WIDTH: 19 0 HEIGHT: 16 4

5.0 VOLUME

13,500 CU.FT 6.0 FLOOR DRAINS YES X NO (drains to Sump in mech.

Equip. room) 7.0 VENTILATION SYSTEM DESCRIPTION Ventilation is provided to the mechanical room by exhaust fans and motorized louvers. Heat is provided by electric unit heaters.

8.0 FIRE PROTECTION TYPE

8.1 SUPPRESSION

None

8.2 DETECTION

Ionization smoke detectors

8.3 MANUAL

Hydrant within 300

8.4 EXTINGUISHERS

20 lb class ABC or BC extinguishers

8.5 OTHER

None 9.0 FIRE LOADING IN AREA 9.1 FLAMMABLES/COMBUSTIBLES FIRE LOADING IN AREA/ZONE HEAT OF TOTAL HEAT HEAT COMBUSTIBLE AMOUNT COMBUSTION POTENTIAL POTENTIAL Electrical insulation (see 12,700 11.0) 1,000 lbs 10,500 Btu/lb 10,500,000 Btu Btu/sq.ft Class A: 300 lbs 8,000 Btu/lb 2,400,000 Btu 2,900 Btu/sq.ft 8,000 Btu/lb (computer paper 2,900 Transients: 300 lbs stocks) 2,400,000 Btu Btu/sq.ft.

Others none Appendix E - Page 24 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 9.2 TOTAL FIRE LOADING IN AREA: 18,500 BTU/sq.ft.

9.3 TOTAL HEAT POTENTIAL: 15,290,250 BTU 9.4 Equivalent Severity: less than 30 minutes 10.0 PROCESS HAZARDS None.

11.0 DESIGN BASIS FIRE DESCRIPTION During maintenance activities, welding spark ignites 300 pounds of transient combustibles brought in for use in maintenance. Fire spreads to consume 300 pounds of class A combustibles ordinarily used and/or stored in area. Intensity of fire causes pyrolization of cable in conduit, adding to heat of combustion released in area.

12.0 CONSEQUENCES OF DESIGN BASIS FIRE Loss of all combustibles in area (i.e., filters in HVAC equipment, and items stored in tool crib). Loss of all electrical equipment in area. Loss of electric cables in area. Loss of use of facility during repair period.

13.0 LIFE SAFETY CONSIDERATIONS 13.1 OCCUPANCY: NFPA 101: Special Purposes UBC:

Group B.Div 2 Industrial 13.2 PROCESS HAZARDS: None 13.3 EMERGENCY LIGHTING: Meets all requirements 13.4 EXIT LIGHTING/SIGNS: Meets all requirements 13.5 CORRIDOR WIDTH: N/ A 13.6 EXITS AND EGRESS: Meets all requirements 13.7 TRAVEL DISTANCE TO EXIT: Meets all requirements Appendix E - Page 25 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 13.8 STAIRS: N/A 13.9 DOOR HARDWARE: Meets all requirements Appendix E - Page 26 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 6.4 DESIGN BASIS FIRE ANALYSIS STORAGE AREA -

6.4.1 CASE 1-HDPE HICS

1.0 BUILDING

Interim Radwaste Storage Facility (IRSF) 2.0 FIRE AREA OR ZONE: IRSF-F1-Z2 2.1 ROOM: Storage Area

2.2 SCENARIO

270 units of 8-120 High Density Polyethylene (HDPE) (Non-steel shelled) High Integrity Containers (HIC), Double Stacked.

2.3 LOCATION

N/A 2.4 REFERENCE DRAWING NOS. A-961, A-962, A-966, A-965, A-970, M-737; shts. 1-7, 1E-0-3341, 1E-0-3341, 1E-0-3344, 1E-0-3755, 1E-0-4673AA 3.0 CONSTRUCTION OF FIRE AREA OR ZONE BOUNDARIES BOUNDARIES MATERIAL MIN. FIRE RATING 3.1 WALL NORTH 30 & 15 concrete EAST 30 & 15 concrete None SOUTH 30 & 15 concrete 3-hr (lower)

WEST 30 & 15 (part.) N/A ext. wall 3.2 FLOOR 30 concrete N/A ext. wall 3.3 CEILING N/A N/A slab on grade 3.4 DOORS None 3.5 ROOF 15 concrete.

N/A ext.

Appendix E - Page 27 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 4.0 FLOOR AREA: 5,700 SQ.FT.

LENGTH: 95 0 WIDTH: 60 0 HEIGHT: 49 0

5.0 VOLUME

279,300 CU.FT 6.0 FLOOR DRAINS YES X NO (drains to Truck Bay Sump) 7.0 VENTILATION SYSTEM DESCRIPTION 16,620 cfm of ventilation air is provided to the storage area and 2,880 cfm to the truck bay by a common supply fan. Outside air intake is variable between 19,500 and 3,450 cfm. The balance of supply air is ducted return. Ratio of return to outside air is controlled by operable louvers. Intake air is preheated in the HV unit in the mechanical room upstream of the main supply fan by an electric duct heater.

8.0 FIRE PROTECTION

8.1 SUPPRESSION

None

8.2 DETECTION

Duct detectors in the ventilation system and detectors in the truck bay area

8.3 MANUAL

None

8.4 EXTINGUISHERS

None

8.5 OTHER

None 9.0 FIRE LOADING IN AREA 9.1 FLAMMABLES/COMBUSTIBLES FIRE LOADING IN AREA/ZONE Appendix E - Page 28 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Heat of Total Heat Heat Combustible Amount Units Combustion Units Potential Units Potential Units HDPE 270 HICs HICs 256,500* lbs 20,000 Btu/lb 5.13E+09 Btu 900,000 Btu/sq.ft Electrical insulation (see 11.0) 400 lbs 10,500 Btu/lb 4.20E+06 Btu 737 Btu/sq.ft Transients: lbs

• Weight is based on Energy Solutions Information. See L-003429 Rev 000, Attachment B 9.2 TOTAL FIRE LOADING IN AREA: 900,737 BTU/sq.ft.

9.3 TOTAL HEAT POTENTIAL: 5.13x109 BTU 9.4 Equivalent Severity: over 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> 10.0 PROCESS HAZARDS None.

11.0 DESIGN BASIS FIRE DESCRIPTION Fire initiation of one HIC is postulated by a non-mechanistic source. The probability of source ignition in the storage area is extremely low. If HICs are sufficiently exposed to a heat source and the ignition temperature is reached, the fire could spread to other containers and could potentially consume all combustibles in the storage bay area. Cable in conduit is pyrolyzed. Heat from fire damages or destroys all electrical cabling and equipment in storage area. The crane structural steel will be damaged due to prolonged exposure to high temperatures from the fire. Potential resin dry out may occur and could ignite and contribute to the fire load.

12.0 CONSEQUENCES OF DESIGN BASIS FIRE Loss of all HICs in the storage area. Structural damage to building from heat resulting in roof collapse and structure debilitation. Loss of all electrical cable in area. Complete loss and use of the facility. Possible unspecified radiological releases if resins are dried out in a conflagration and ignite.

Appendix E - Page 29 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 13.0 LIFE SAFETY CONSIDERATIONS 13.1 OCCUPANCY: NFPA 101: Special Purposes UBC:

Group B.Div 2 Industrial 13.2 PROCESS HAZARDS: None 13.3 EMERGENCY LIGHTING: None required 13.4 EXIT LIGHTING/SIGNS: None required 13.5 CORRIDOR WIDTH: N/ A 13.6 EXITS AND EGRESS: None required 13.7 TRAVEL DISTANCE TO EXIT: N/A 13.8 STAIRS: N/A 13.9 DOOR HARDWARE: N/A 14.0 RECOMMENDATION In the case where 270 polyethylene (poly) HICs are stored in the IRSF, addition of an automatic fire suppression system is highly recommended and required based on NFPA 801 and NFPA 804 considering the potential risk involved in burning all the containers. Results indicate sufficient heat load may be available to dry out portions of the dewatered resin, potentially resulting in resin ignition.

The IRSF would likely be destroyed by the fire.

Appendix E - Page 30 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 6.4.2 CASE 2-HDPE HICS ARRAYED WITH ADEQUATE SEPARATION DISTANCE TO OTHER HICS TO ELIMINATE FIRE SPREAD

1.0 BUILDING

Interim Radwaste Storage Facility (IRSF) 2.0 FIRE AREA OR ZONE: IRSF-F1-Z2 2.1 ROOM: Storage Area

2.2 SCENARIO

100 units of double stacked non-steel shelled 8-120 HDPE HICs (Balance of 170 are steel shelled)

2.3 LOCATION

N/A 2.4 REFERENCE DRAWING NOS. A-961, A-962, A-966, A-965, A-970, M-737; shts. 1-7, 1E-0-3341, 1E-0-3341, 1E-0-3344, 1E-0-3755, 1E-0-4673AA 3.0 CONSTRUCTION OF FIRE AREA OR ZONE BOUNDARIES BOUNDARIES MATERIAL MIN. FIRE RATING 3.1 WALL NORTH 30 & 15 concrete None EAST 30 & 15 concrete 2-hr (lower)

SOUTH 30 & 15 concrete N/A ext. wall WEST 30 & 15 (part.) N/A ext. wall 3.2 FLOOR 30 concrete N/A slab on grade 3.3 CEILING N/A 3.4 DOORS None 3.5 ROOF 15 concrete. N/A ext.

4.0 FLOOR AREA: 5,700 SQ.FT.

Appendix E - Page 31 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 LENGTH: 95 0 WIDTH: 60 0 HEIGHT: 49 0

5.0 VOLUME

279,300 CU.FT 6.0 FLOOR DRAINS YES X NO (drains to Truck Bay Sump) 7.0 VENTILATION SYSTEM DESCRIPTION 16,620 cfm of ventilation air is provided t o the storage area and 2,880 cfm t o the truck bay by a common supply fan. Outside air intake is variable between 19,500 and 3,450 cfm . The balance of supply air is ducted return. Ratio of return t o outside air is controlled by operable louvers. Intake air is preheated in the HV unit in the mechanical room upstream of the main supply fan by an electric duct heater.

8.0 FIRE PROTECTION

8.1 SUPPRESSION

None

8.2 DETECTION

Duct detectors in the ventilation system and detectors in the truck bay area

8.3 MANUAL

None

8.4 EXTINGUISHERS

None

8.5 OTHER

None 9.0 FIRE LOADING IN AREA 9.1 FLAMMABLES/COMBUSTIBLES FIRE LOADING IN AREA/ZONE Heat of Total Heat Heat Combustible Amount Units Combustion Units Potential Units Potential Units HDPE 6 HICs HICs 5,700* lbs 20,000 Btu/lb 1.14 x108 Btu 20,000 Btu/sq.ft Electrical insulation (see 11.0) 400 lbs 10,500 Btu/lb 42x105 Btu 737 Btu/sq.ft Transients: 0 lbs

• Weight is based on Energy Solutions Information. See L-003429 Rev 000, Attachment B Appendix E - Page 32 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 9.2 TOTAL FIRE LOADING IN AREA: 20,737 BTU/sq.ft.

9.3 TOTAL HEAT POTENTIAL: 1.18 x108 BTU 9.4 Equivalent Severity: 16 minutes 10.0 PROCESS HAZARDS None.

11.0 DESIGN BASIS FIRE DESCRIPTION The fire initiation of (6) non-steel shelled poly HIC is postulated based on a non-mechanistic source. The probability of fire ignition in the storage area is extremely low and is considered incredible. In the event of an incredible non-mechanistic fire, the (6) HICs configuration will have sufficient separation distance of 6.6 feet from the adjacent HICs that the group is expected to self extinguish and not initiate an adjacent poly HIC fire. In case of an incredible fire in the storage bay area during loading/unloading operations, the smoke detector located directly over the 34x60 storage bay/truck bay shield wall will detect and alert the operators of smoke in the IRSF. Therefore, it is required that Exelon procedures instruct operators to open the main truck bay door (17x14) so the heat and smoke can be vented from the facility through the open door. See calculation L-003429 IRSF Storage Bay HIC Spacing to Prevent Spread of a Postulated HIC Fire, Rev 000 for details.

12.0 CONSEQUENCES OF DESIGN BASIS FIRE Loss of (6) poly HICs in the storage area. Generated heat from fire is not sufficient to damage or destroy the IRSF. The fire will not spread to other HICs since the minimum distance of 6.6 feet is maintained. A postulated radiological release from such an event results in doses within the regulatory limit of 10% of 10CFR100, as demonstrated in calculation L-003430 IRSF Design Basis Event Dose Assessment.

13.0 LIFE SAFETY CONSIDERATIONS 13.1 OCCUPANCY: NFPA 101: Special Purposes UBC:

Group B.Div 2 Industrial 13.2 PROCESS HAZARDS: None 13.3 EMERGENCY LIGHTING: None required Appendix E - Page 33 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 13.4 EXIT LIGHTING/SIGNS: None required 13.5 CORRIDOR WIDTH: N/ A 13.6 EXITS AND EGRESS: None required 13.7 TRAVEL DISTANCE TO EXIT: N/A 13.8 STAIRS: N/A 13.9 DOOR HARDWARE: N/A 14.0 RECOMMENDATION The (6) non-steel shelled poly HIC configuration arrayed with adequate separation distance to other non-steel shelled poly HICs to eliminate fire spread

,has been shown to be acceptable.. Using the LaSalle current crane indexing system to determine the container arrangement, 100 non-steel shelled poly HICs can be stored per Sketch 15.0 (100 HICs Configuration Arrangement Sketch) without implementing additional fire detection and suppression systems.

The balance of storage bay capacity (270 HICs) can be achieved by loading steel-shelled poly HICs in the open spaces, stacked 2 high if needed.

Additional fire detection or suppression systems are not required for this case.

URS Washington Division recommends this case (Case 2).

Appendix E - Page 34 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 15.0 100 HICS CONFIGURATION ARRANGEMENT SKETCH (CURRENT LASALLE CRANE INDEX SYSTEM)

Appendix E - Page 35 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Appendix E - Page 36 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 6.4.3 CASE 3-STEEL SHELL HICS

1.0 BUILDING

Interim Radwaste Storage Facility (IRSF) 2.0 FIRE AREA OR ZONE: IRSF-F1-Z2 2.1 ROOM: Storage Area

2.2 SCENARIO

270 units of Steel Shell HDPE HICs. The HIC is completely covered by steel with no large exposed areas of the HIC.

2.3 LOCATION

N/A 2.4 REFERENCE DRAWING NOS. A-961, A-962, A-966, A-965, A-970, M-737; shts. 1-7, 1E-0-3341, 1E-0-3341, 1E-0-3344, 1E-0-3755, 1E-0-4673AA 3.0 CONSTRUCTION OF FIRE AREA OR ZONE BOUNDARIES BOUNDARIES MATERIAL MIN. FIRE RATING 3.1 WALL NORTH 30 & 15 concrete None EAST 30 & 15 concrete 2-hr (lower)

SOUTH 30 & 15 concrete N/A ext. wall WEST 30 & 15 (part.) N/A ext. wall 3.2 FLOOR 30 concrete N/A slab on grade 3.3 CEILING N/A 3.4 DOORS None 3.5 ROOF 15 concrete. N/A ext.

Appendix E - Page 37 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 4.0 FLOOR AREA: 5,700 SQ.FT.

LENGTH: 95 0 WIDTH: 60 0 HEIGHT: 49 0

5.0 VOLUME

279,300 CU.FT 6.0 FLOOR DRAINS YES X NO (drains to Truck Bay Sump) 7.0 VENTILATION SYSTEM DESCRIPTION 16,620 cfm of ventilation air is provided t o the storage area and 2,880 cfm t o the truck bay by a common supply fan. Outside air intake is variable between 19,500 and 3,450 cfm. The balance of supply air is ducted return. Ratio of return t o outside air is controlled by operable louvers. Intake air is preheated in the HV unit in the mechanical room upstream of the main supply fan by an electric duct heater.

8.0 FIRE PROTECTION

8.1 SUPPRESSION

None

8.2 DETECTION

Duct detectors in the ventilation system and detectors in the truck bay area

8.3 MANUAL

None

8.4 EXTINGUISHERS

None

8.5 OTHER

None 9.0 FIRE LOADING IN AREA 9.1 FLAMMABLES/COMBUSTIBLES FIRE LOADING IN AREA/ZONE Appendix E - Page 38 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 Heat of Total Heat Heat Combustible Amount Units CombustionUnits Potential Units Potential Units Steel Shell 1 HICs HICs 2,150* lbs 20,000 Btu/lb 4.3E+07 Btu 7,544 Btu/sq.ft Electrical insulation (see 11.0) 400 lbs 10,500 Btu/lb 4.20E+06 Btu 737 Btu/sq.ft Transients: 0 lbs

• Weight is based on Energy Solutions Information. See L-003429 Rev 000, Attachment B 9.2 TOTAL FIRE LOADING IN AREA: 8,574 BTU/sq.ft.

9.3 TOTAL HEAT POTENTIAL: 4.72x107 BTU 9.4 Equivalent Severity: 19 minutes 10.0 PROCESS HAZARDS None.

11.0 DESIGN BASIS FIRE DESCRIPTION In case of an unspecified ignition source in the storage bay area, it is not considered credible for the poly HIC inside the steel shell to ignite. Assuming that a poly HIC container is somehow ignited by a non-mechanistic source, no significant impact would occur in the steel shell container case since the steel shell acts as a fire retardant material for a limited period of time and will contain the burning HIC. The poly HIC is not expected to sustain significant combustion because of a lack of oxygen. Never-the-less, the poly material for one HIC is assumed in this fire scenario to continue to smolder until exhausted. No propagation to other steel shelled HICs occurs.

Appendix E - Page 39 of 40

TECHINICAL REPORT Project No. 29487-NCS0097 SUPPORTING EC No. 375636 ENGINEERING CHANGE Rev. 0 Date: 9/28/09 12.0 CONSEQUENCES OF DESIGN BASIS FIRE The steel shell (casing) does not prevent the enclosed polyethylene HIC from melting or drying resin out in the case of an extreme fire scenario which is considered incredible. In any case, even in an isolated case where one poly HIC is assumed to ignite non-mechanistically and burn, the fire will not be propagated to the other steel lined poly HIC containers, if they are fully enclosed.

14.0 LIFE SAFETY CONSIDERATIONS 14.1 OCCUPANCY: NFPA 101: Special Purposes UBC:

Group B.Div 2 Industrial 14.2 PROCESS HAZARDS: None 14.3 EMERGENCY LIGHTING: None required 14.4 EXIT LIGHTING/SIGNS: None required 14.5 CORRIDOR WIDTH: N/ A 14.6 EXITS AND EGRESS: None required 14.7 TRAVEL DISTANCE TO EXIT: N/A 14.8 STAIRS: N/A 14.9 DOOR HARDWARE: N/A 15.0 RECOMMENDATION In the case where 270 Steel shell covered poly HICs are stored in the IRSF, no automatic fire suppression is required. These containers are normally supplied with stacking plates, but should have metal lids covering the open fill port. Steel shell poly HICs are normally considered a fire resistant container when fully enclosed, even allowing for small holes in the top for venting.

Appendix E - Page 40 of 40

ATTACHMENT 4 Calculation L-003430 LaSalle IRSF Design Basis Event Dose Assessment

ee ~,4 - 3 Q~ --I 00 I

~:rt;:"'" S-

?~ J-71 utP A7T/tLtltH t AJ { I

?~J" '1 !J / 1/1 Design AnalysIs Major Revision Cover Sheet ~

Design Analysis (Major Revision) I Last Page No.

• 11 f Att D-2 Analysis No.: ' L-003430 Revision: ' 000

Title:

' IRSF Design Basis Event Dose Assessment EC/ECR No.:

• 375636 Revision: ' 0 Statlon(s): 1 LaSalle County Station Component(s): ..

Unit No.:' 00 IV/h-Discipline: * #tth Descrlp. Code/Keyword: '0

/fIJI / 'ffl-S f Safety/QA Class: " Non-Safety System Code: I> NII1-Structure: " N/"-

CONTROLLED DOCUMENT REFERENCES "

Document No.: FromlTo Document No.: FromlTo

~ ~

I+-e- ~

~ ~

~ ~

If yes, see SY-AA-Is this Design Analysis Safeguards Information? ** Yes 0 No I8J 101-106 If yes, Does this Design Analysis contain Unverified Assumptions? " Yes 0 No [gI ATI/AR#:

This Design Analysis SUPERCEDES: " None ...,;., ,I< ".J-;rdw Description of Revision (list affected pages for partials): " Initial Issue Preparer: " VhH~M. Go~1\ ~A~ .. cr/l&ft7' Prtnt Name Sign Name Oa'-

Testing Method of Review:" Detailed Review I2J Alternate Calculations (attached) 0 Reviewer:

n H. lSofhIf~/~ I",7*IlJ.."ftL H.I{. IN o ~(jDr Print Name SlgnN"",. Oate Review Notes:" Independent review [gI Peer review 0 All inputs. assumptions, approaches, numerical analyses. and results were independently reviewed and checked.

(For Ext.",al Analys.. Only)

External Approver:" Donald Gardner Print Name ~~::'~o:/"fh~

Exelon Reviewer: " )(5Si tR Of<t...l.o.:r,/

PnntName

~'"Q.llt"\... 1J!I!:,'N1./~ O~l~/ (Iof/I Independent 3rd Party Review Reqd? ,. Yes 0* No {81 Exelon Approver: " .PtlN $clf~/r Print NatT'18 *~p iCJ1Name

/Ihtk 1 ba'- I

CC-AA-309 Revision 9 Page 17 of 17 ATTACHMENT 1 Owners Acceptance Review Checklist for External Design Analysis Page 1 of 1 DESIGN ANALYSIS NO. L-003430 REV: 0 Yes No N/A

1. Do assumptions have sufficient rationale? I8I' 0 0 2.

Are assumptions compatible with the way the plant is operated and with the licensing basis?

g 0 0

3. Do the design inputs have sufficient rationale? ri( 0 0 4.

Are design inputs correct and reasonable with critical parameters Identified, if appropriate? m 0 0 Are design inputs compatible with the way the plant is operated and with the 5.

licensing basis? ~ 0 0

6. Are Engineering Judgments clearly documented and justified? ~ 0 0 Are Engineering JUdgments compatible with the way the plant is operated 7.

and with the licensing basis?

f.i(' 0 0 8.

Do the results and conclusions satisfy the purpose and objective of the Design Analysis? ~ 0 0 Are the results and conclusions compatible with the way the plant is operated 9.

and with the licensing basis? ~ 0 0 Does the Design Analysis include the applicable design basis 10.

documentation? b<r' 0 0 Have any limitations on the use of the results been identified and transmitted 11.

to the appropriate organizations? ~ 0 0 t"ftlt'?J"7

12. Are there any unverified assumptions? 0 l8" 0 Do all unverified assumptions have a tracking and closure mechanism in 13.

place? 0 0 ~

Have all affected design analyses been documented on the Affected 14.

Documents List (ADL) for the associated Configuration Change? fl2] 0 0 Do the sources of inputs and analysis methodology used meet current technical requirements and regulatory commitments? (If the input sources or

15. analysis methodology are based on an out-of-date methodology or code, additional reconciliation may be required if the site has since committed to a

~ 0 0 more recent code)

Have vendor supporting technical documents and references (including GE 16.

DRFs) been reviewed when necessary? 8 0 0 Have margin impacts been identified and documented appropriately for any

17. negative impacts (Reference ER-M-2007)? 0 0 ~

EXELON REVIEWER:

CALCULATION No L-003430 REV. 000 PAGE iii TABLE OF CONTENTS OWNERS ACCEPTANCE REVIEW CHECKLIST FOR EXTERNAL DESIGN ANALYSIS ..................................................................................... 2

1. Introduction & Purpose............................................................................ 4

2. Inputs........................................................................................................ 4

3. Assumptions............................................................................................. 5 3.1 Technically Justified Assumptions ..................................................................... 5 3.2 Assumptions that Require Verification............................................................... 5

4. References................................................................................................ 5

5. Method of Analysis.................................................................................. 6 5.1 Design Basis Container Activity......................................................................... 7 5.2 Internal Events .................................................................................................... 7

6. Numeric Analysis..................................................................................... 8 6.1 Bounding Design Basis Container Contents....................................................... 8 6.2 Container Drop.................................................................................................... 9

7. Results ...................................................................................................... 9

8. Conclusion ............................................................................................. 10 ATTACHMENT A: LaSalle: MicroShield Runs and Excel Spreadsheets ............................. A-1 ATTACHMENT B: Clinton: MicroShield Runs and Excel Spreadsheets.............................. B-1 ATTACHMENT C: Byron and Braidwood: MicroShield Runs and Excel Spreadsheets ...... C-1 ATTACHMENT D: Computer Disclosure Sheets.................................................................. D-1

CALCULATION No L-003430 REV. 000 PAGE 4

1. Introduction & Purpose The purpose of this calculation is to select and analyze design basis events (e.g., fire, and container drop) for the LSCS Interim Radwaste Storage Facility (IRSF). These analyses must demonstrate that dose consequences of bounding events do not exceed a small fraction (10 percent) of 10 CFR Part 100 dose limits, as per Reference (9), the General Information section of Generic Letter 81-38 entitled Storage of Low-Level Radioactive Wastes at Power Reactor Sites, and as suggested in EPRI Guidelines for Operation IRSF (Reference (3)).

Waste stored in the IRSF will be from LSCS, but may also include waste transported for interim storage from the Byron, Braidwood, or Clinton Stations.

Bounding design basis events considered are a waste handling accident, involving a container drop, and a postulated fire in the storage bay.

2. Inputs Parameter Value Basis i Byron, Braidwood, or 200 rem/hr Assumption 3.1.1 Clinton Stations Container Contact Dose Rate for Nominal Analysis i LSCS Container Contact 380 rem/hr Assumption 3.1.1 Dose Rate for Bounding Analysis i Container Isotopic Mix: Table 11.1-10 Reference (12)

Byron and Braidwood NSSS Demineralizer i Container Isotopic Mix: Table 12.2-13 Reference (13)

Byron and Braidwood Mixed Bed Demineralize i Container Isotopic Mix: Table 12.2-12 Reference (14)

Clinton Power Station i Container Isotopic Mix: Table 11.2-5 Reference (15)

LaSalle County Station i Resin Density 0.9 g/cc Nominal Value i Number of Containers 1 Assumption 3.1.2 Dropped i Container Drop Height 28 ft (853.44 cm) Reference (5)

CALCULATION No L-003430 REV. 000 PAGE 5 i Number of Containers 6 Reference (11)

Burned i Mixing Credit 100%, well mixed It is expected that the nature of the accident event will cause significant mixing i Calculated 2-hour X/Q at 5.40E-04 Reference (8) the Exclusion Area Boundary (EAB) for ground level release (sec/m3) i Fraction Released: 0.809% Section 6.2.1 Container Drop i Fraction Released: 0.78% Reference (7)

Container Fire i Breathing Rate at EAB 3.5E-04 Reference (17) i Decay 60 Days Assumption 3.1.3

3. Assumptions 3.1 Technically Justified Assumptions 3.1.1 Analyses used to compare isotopic mixes from LaSalle, Clinton, Byron and Braidwood are based on a nominal 200 R/hr container. Accident analyses are based on a bounding 380 R/hr container dose limit for LaSalle containers.

Activities released and resulting doses are proportional to container contact dose rates, isotopic mixes being equal.

3.1.2 The crane in the IRSF can only carry one container at a time and therefore one container will be assumed to drop into an area (the truck bay) permitting a relatively ready release for the drop accident.

3.1.3 Based on typical practice, resins are not packaged until at least 60 days after discharge, so 60 days is conservatively used.

3.2 Assumptions that Require Verification There are no assumptions that require verification in this calculation.

4. References (1) NUREG-1320, Nuclear Fuel Cycle Facility Accident Analysis Handbook, May 1988.

CALCULATION No L-003430 REV. 000 PAGE 6 (2) 10 CFR 100, Reactor Site Criteria.

(3) EPRI, Guidelines for Operating an Interim On Site Low Level Radioactive Waste Storage Facility - Revision 1, February 2009.

(4) LaSalle UFSAR, Chapter 11, Table 11.2-5, current as of this calculation.

(5) LaSalle Drawing No. A-965, General Arrangements - Sections IRSF- LaSalle Station, Section 1-1, August 1984.

(6) U.S. Department of Energy, External Dose-Rate Conversion Factors for Calculation of Dose to the Public, July 1988. (FGR-11, per section 6.1-4 )

(7) U.S. Department of Energy, Airborne Release Fractions/Rates and Respirable Fractions for Nonreactor Nuclear Facilities, December 1994.

(8) LSCS Design Analysis L-003063, Alternative Source Term Onsite and Offsite X/Q Values, October 2008.

(9) URS: Washington Division, Design Change Package, Stn:LAS Unit:00, Interim Radwaste Storage Facility LAR Support.

(10) USNRC-Standard Review Plan, Section 11.4-A, Design Guidance for Temporary Storage of Low-Level Radioactive Waste, Revision 3, March 2007.

(11) LaSalle Calculation, L-003429, IRSF Storage Bay Fire HIC Spacing Assessment.

(12) Byron and Braidwood UFSAR, Chapter 11, Table 11.1-10, Realistic Source Terms for NSSS Demineralizers, current as of this calculation.

(13) Byron and Braidwood UFSAR, Chapter 12, Table 12.2-13, Mixed Bed Demineralizer, current as of this calculation.

(14) Clinton UFSAR, Chapter 12, Table 12.2-12, Design-Basis Inventories of Radioactive Nuclides in Major Wet Solid Waste Subsystem Components -

Phase Separator Tank Column, current as of this calculation.

(15) LaSalle UFSAR, Chapter 11, Table 11.2-5, Inventory Summary RWCU Phase Separator Column, current as of this calculation.

(16) LaSalle Procedure LOP-WX-33, Revision 1, Abnormal IRSF Operation Procedure, March 2008.

(17) NRC Regulatory Guide 1.183, Rev. 0, Alternative Radiological Source Terms for Evaluating Design Basis Accidents At Nuclear Power Reactors.

5. Method of Analysis In general, these analyses determine or utilize:

(1) a bounding design basis container content; (2) number of containers affected by the event; (3) fraction of contained activity released for airborne dispersion (4) appropriate dispersion factors; (5) resulting doses at the Exclusion Area Boundary (the bounding location for the assumed instantaneous ground level release)

CALCULATION No L-003430 REV. 000 PAGE 7 5.1 Design Basis Container Activity The Chem-Nuclear system polyethylene HIC has a inner diameter of 60 inches and a fill line height of 72 inches. The HIC will have the worst isotopic mixture from one of the three plants shipping to LaSalle. The HIC contents will have decayed for a period of 60 days and are at a contact dose rate of 200 rem/hr for non-LaSalle waste and 380 rem/hr for bounding LaSalle waste.

5.2 Internal Events 5.2.1 Container Drop In this accident, one container will be moved from the storage module, through a notch that is 27 feet from the floor, and into the truck bay, which can be seen in Figure 5.2-1.

This is where the container is assumed to be released from a height of 28 feet. The container will free fall and rupture upon impact, causing a release.

Figure 5.2-1 5.2.2 Container Fire As stated in L-003429, the HICs are isolated from humans and equipment failure and most associated ignition sources. Only transient electrical equipment associated with the crane is brought over the storage area. Only HDPE HICs are considered to provide a credible combustible source that could lead to a fire that might involve resin drying and burning. Therefore, placement of HDPE HICs is limited to 6, which must then be separated from adjacent HDPE groups so that the heat flux from the fire will not be great enough for another fire to occur, as seen in Figure 5.2-2.

CALCULATION No L-003430 REV. 000 PAGE 8 Therefore the postulated worst event would be a group fire of six HICs. In this event, the HICs are stacked in twos and are grouped together.

Figure 5.2-2

6. Numeric Analysis 6.1 Bounding Design Basis Container Contents Bounding HICs generated at LaSalle are assumed to have a contact dose rate of 380 R/hr.

A container with this contact dose rate may require a hold in storage for a decay period.

Containers shipped from Byron, Braidwood, or Clinton are assumed to have a maximum contact dose rate 200 R/hr, because of limitations on dose rates exterior to a transport package.

Shielding analyses have been performed on an all Co-60 basis to simulate worst case conditions. However, design basis events involving postulated airborne releases and inhalation doses must consider relative inhalation dose conversion factors. For this reason, isotopic mixes from station UFSARs for the bounding resin sources were evaluated using the following process.

1. For Byron and Braidwood two mixes were collected, one from UFSAR Table 11.1-10 Realistic Source Terms for NSSS Demineralizers and one from Table 12.2-13 Mixed Bed Demineralizer. For Clinton, phase separator characteristics from UFSAR Table 12.2-12 Design-Basis Inventories of Radioactive Nuclides in Major Wet Solid Waste Subsystem Components - Phase Separator Tank Column were used. For LaSalle, UFSAR Table 11.2-5 Inventory Summary RWCU Phase Separator Column was used.

2. These 4 mixes were place in a nominal HIC to determine a contact dose rate, using MicroShield. A decay before container loading period of 60 days was

CALCULATION No L-003430 REV. 000 PAGE 9 assumed, and the resulting mix of isotopes adjusted using MicroShield to result in the 200 R/hr container contact dose.

3. These isotopic mix concentrations were then multiplied by effective inhalation dose conversion factors from FGR-11 and then summed to determine which mix would yield the maximum inhalation dose. The result of this step was that LaSalle RWCU Phase Separator had the bounding isotopic mix.

4. With the bounding isotopic mix in a container, the contents are adjusted proportionally to yield the design basis 380 R/hr LaSalle Container, which based on both isotopics and contact dose rate limits, is bounding.

5. Accidents are evaluated based on multiplying the following factors: (1) Container Contents; (2) the number of containers affected; (3) the release fraction applicable to the event; (4) the LaSalle EAB X/Q for ground level releases; (5) a Breathing Rate of 3.5E-4 m3/s; and (6) Dose Conversion Factors from Reference (6).

6.2 Container Drop 6.2.1 Airborne Release Fraction NUREG-1320 (Ref. (1)) provides an equation for calculating the airborne release from powder spills which are a function of spill height and spill density.

Fraction airborne = 1 x 10-8 x H2/ p (Ref.(1))

Where H = Spill height, cm

p= Powder density g/cm3 H = 28' = 853.44 cm Where 28 is the elevation of the bottom of the container in relation to the floor.

The density for a dry Powdex comparable resin:

p = 0.9 g/cc Therefore, fraction airborne = 1 x 10-8 x (853.44)2 / (9 x 10-1) = 8.09 x 10-3

7. Results This calculation was performed to evaluate LSCS IRSF internal design basis events (fire and container drop) as bounding events. The methodology is conservative as discussed below. The calculated doses are:

Event Calculated Dose Limit Container Drop 0.389 rem 2.5 rem Container Fire 2.334 rem 2.5 rem Some of the conservatisms applied in this calculation are listed below.

CALCULATION No L-003430 REV. 000 PAGE 10 i All affected containers are assumed to have a contact dose rate of 380 R/hr, which is the maximum allowed in the IRSFs based on ODCM requirements.

i In the Fire Event, 6 containers are assumed to be involved(two high stacking in three positions) with a contact dose rate of 380 R/hr. Typical stacking practices would have upper containers with a significantly lower contact dose rate for skyshine minimization.

i Release Fractions for container drop use a conservative NUREG-1320 based dry powder spill scenario to determine an airborne fraction. The worst case Powdex-like resin is expected to be wet and to be less easily made airborne. Larger bead resin would be even less likely to become airborne. The assumed drop is from the maximum release height with a resulting calculated airborne release fraction of 0.00809, which is rounded to 0.01.

i Release Fractions for the Fire Event use a conservative DOE Handbook approach for resin fires and similarly round a 0.0078 value to 0.01.

i All airborne activity is assumed to be instantly released to the environment from the IRSF. No particle settling is assumed either in the IRSF or in transit to the EAB.

The IRSF ventilation system is isolated during container handling to maximize the potential for such settling. For the Fire Event, procedure LOP-WX-33 (Ref (16))

directs that the ventilation system be secured.

i Selected worst case UFSAR isotopic mix which is richer in fission products than would be normally expected. For instance, 69% of above calculated doses result from Sr-89 and Sr-90.

8. Conclusion By performing this evaluation, it has been concluded that a container fire of six containers is a bounding event. The level of conservatism includes significant safety factors for calculating an effective dose release to the EAB through a container drop or container fire analysis.

Doses from the bounding internal events in the IRSF are within 10% of 10 CFR 100 limits.

Attachment A: LaSalle MicroShield......................................................................................................................... 2 Run #1: Based on UFSAR Table Data from 11.2-5 ....................................................... 2 Run #2: Based on UFSAR Table Data from 11.2-5 w/ 60 Day Decay .......................... 5 Run #3: Based on UFSAR Table Data from 11.2-5 w/ 60 Day Decay and Normalized Contact Dose................................................................................................................... 8 Excel Sheets ...................................................................................................................... 11 Drop Accident............................................................................................................... 11 Captures the isotopic mix from Run #3 in column D, and then calculates a final dose in column F.

Fire Accident................................................................................................................. 13 Captures the isotopic mix from Run #3 in column D, and then calculates a final dose in column F.

Drop Accident: Formula Version.................................................................................. 15 Fire Accident: Formula Version ................................................................................... 17 Calc. No. L-003430, Rev. 0, Attachment A, A-1 of A-18

A B C D E F G H I 1 MicroShield 8.01 2 Washington Group International (8.00-0000) 3 Date By Checked 4

5 Filename Run Date Run Time Duration 6 Lasalle.msd 11-Aug-09 8:54:48 AM 0:00:07 7 Project Info 8 Case Title Lasalle 11.2-5 9 Description before decay and resizing 10 Geometry 7 - Cylinder Volume - Side Shields 11 Source Dimensions 12 Height 182.88 cm (6 ft) 13 Radius 76.2 cm (2 ft 6.0 in) 14 Dose Points 15 A X Y Z 16 #1 78.74 cm (2 ft 7.0 in) 91.44 cm (3 ft) 0.0 cm (0 in) 17 Shields 18 Shield N Dimension Material Density 19 Source 3.34e+06 cm³ Water 0.9 20 Transition Air 0.00122 21 Air Gap Air 0.00122 22 Source Input: Grouping Method - Linear Energy 23 Number of Groups: 25 24 Lower Energy Cutoff: 0.015 25 Photons < 0.015: Included 26 Library: Grove 27 Nuclide Ci Bq µCi/cm³ Bq/cm³ 28 Ag-110 1.47E-01 5.44E+09 4.41E-02 1.63E+03 29 Ag-110m 1.13E+01 4.18E+11 3.39E+00 1.25E+05 30 Ba-137m 2.96E+01 1.10E+12 8.87E+00 3.28E+05 31 Ba-139 1.74E+01 6.44E+11 5.22E+00 1.93E+05 32 Ba-140 2.20E+02 8.14E+12 6.59E+01 2.44E+06 33 Ba-141 3.84E+00 1.42E+11 1.15E+00 4.26E+04 34 Ba-142 2.26E+00 8.36E+10 6.77E-01 2.51E+04 35 Br-83 2.86E+00 1.06E+11 8.57E-01 3.17E+04 36 Br-84 1.11E+00 4.11E+10 3.33E-01 1.23E+04 37 Br-85 4.80E-02 1.78E+09 1.44E-02 5.32E+02 38 Ce-141 6.38E+00 2.36E+11 1.91E+00 7.08E+04 39 Ce-143 9.21E-02 3.41E+09 2.76E-02 1.02E+03 40 Ce-144 6.76E+00 2.50E+11 2.03E+00 7.50E+04 41 Co-58 5.62E+02 2.08E+13 1.68E+02 6.23E+06 42 Co-60 1.16E+02 4.29E+12 3.48E+01 1.29E+06 43 Cr-51 2.63E+01 9.73E+11 7.88E+00 2.92E+05 44 Cs-134 1.95E+01 7.22E+11 5.85E+00 2.16E+05 45 Cs-135 46 Cs-136 1.52E+00 5.62E+10 4.56E-01 1.69E+04 47 Cs-137 3.16E+01 1.17E+12 9.47E+00 3.50E+05 48 Cs-138 4.37E+00 1.62E+11 1.31E+00 4.85E+04 49 F-18 50 Fe-59 6.45E+00 2.39E+11 1.93E+00 7.15E+04 51 I-129 3.83E-08 1.42E+03 1.15E-08 4.25E-04 52 I-131 2.00E+02 7.40E+12 6.00E+01 2.22E+06 53 I-132 3.27E+02 1.21E+13 9.80E+01 3.63E+06 54 I-133 1.49E+02 5.51E+12 4.47E+01 1.65E+06 55 I-134 1.63E+01 6.03E+11 4.89E+00 1.81E+05 56 I-135 6.93E+01 2.56E+12 2.08E+01 7.69E+05 57 Kr-83m 58 Kr-85 59 Kr-85m 60 La-140 2.20E+02 8.14E+12 6.59E+01 2.44E+06 61 La-141 4.06E+00 1.50E+11 1.22E+00 4.50E+04 62 La-142 2.48E+00 9.18E+10 7.43E-01 2.75E+04 63 Mn-54 7.82E+00 2.89E+11 2.34E+00 8.67E+04 64 Mn-56 1.02E+01 3.77E+11 3.06E+00 1.13E+05 65 Mo-99 1.17E+02 4.33E+12 3.51E+01 1.30E+06 66 N-16 Calc. No. L-003430, Rev. 0, Attachment A, A-2 of A-18

A B C D E F G H I 67 Na-24 2.40E+00 8.88E+10 7.19E-01 2.66E+04 68 Nb-95 6.29E+00 2.33E+11 1.89E+00 6.98E+04 69 Nb-95m 8.39E-02 3.10E+09 2.52E-02 9.31E+02 70 Nb-97 4.35E-02 1.61E+09 1.30E-02 4.82E+02 71 Nb-97m 4.33E-02 1.60E+09 1.30E-02 4.80E+02 72 Nd-147 2.98E-01 1.10E+10 8.93E-02 3.31E+03 73 Ni-65 6.08E-02 2.25E+09 1.82E-02 6.74E+02 74 Np-239 1.08E+03 4.00E+13 3.24E+02 1.20E+07 75 P-32 5.47E-01 2.02E+10 1.64E-01 6.07E+03 76 Pm-147 3.33E-02 1.23E+09 9.98E-03 3.69E+02 77 Pr-143 1.08E+00 4.00E+10 3.24E-01 1.20E+04 78 Pr-144 6.76E+00 2.50E+11 2.03E+00 7.50E+04 79 Rh-103m 1.38E+00 5.11E+10 4.14E-01 1.53E+04 80 Rh-106 5.26E-01 1.95E+10 1.58E-01 5.83E+03 81 Ru-103 1.38E+00 5.11E+10 4.14E-01 1.53E+04 82 Ru-106 5.26E-01 1.95E+10 1.58E-01 5.83E+03 83 Sr-89 2.80E+02 1.04E+13 8.39E+01 3.11E+06 84 Sr-90 5.46E+01 2.02E+12 1.64E+01 6.06E+05 85 Sr-91 5.31E+01 1.96E+12 1.59E+01 5.89E+05 86 Sr-92 2.36E+01 8.73E+11 7.07E+00 2.62E+05 87 Tc-99 4.01E-04 1.48E+07 1.20E-04 4.45E+00 88 Tc-99m 2.36E+02 8.73E+12 7.07E+01 2.62E+06 89 Tc-101 2.42E+00 8.95E+10 7.25E-01 2.68E+04 90 Te-129 1.62E+00 5.99E+10 4.86E-01 1.80E+04 91 Te-129m 2.53E+00 9.36E+10 7.58E-01 2.81E+04 92 Te-132 3.05E+02 1.13E+13 9.14E+01 3.38E+06 93 W-187 5.71E+00 2.11E+11 1.71E+00 6.33E+04 94 Xe-131m 95 Xe-133 96 Xe-133m 97 Xe-135 98 Xe-135m 99 Y-90 5.34E+01 1.98E+12 1.60E+01 5.92E+05 100 Y-90m 101 Y-91 4.68E+01 1.73E+12 1.40E+01 5.19E+05 102 Y-91m 3.12E+01 1.15E+12 9.35E+00 3.46E+05 103 Y-92 2.38E+01 8.81E+11 7.13E+00 2.64E+05 104 Zn-65 3.74E-01 1.38E+10 1.12E-01 4.15E+03 105 Zn-69 3.29E-02 1.22E+09 9.86E-03 3.65E+02 106 Zn-69m 3.28E-02 1.21E+09 9.83E-03 3.64E+02 107 Zr-95 4.24E+00 1.57E+11 1.27E+00 4.70E+04 108 Zr-97 4.34E-02 1.61E+09 1.30E-02 4.81E+02 109 Buildup: The material reference is Source 110 Integration Parameters 111 Radial 30 112 Circumferential 30 113 Y Direction (axial) 60 114 Results 115 Fluence Rate Fluence Rate Exposure Rate Exposure Rate 116 Energy (MeV) Activity (Photons/sec) MeV/cm²/sec MeV/cm²/sec mR/hr mR/hr 117 No Buildup With Buildup No Buildup With Buildup 118 0.0621 8.36E+13 3.70E+06 2.33E+07 7.05E+03 4.44E+04 119 0.2445 2.46E+13 6.53E+06 2.72E+07 1.20E+04 5.00E+04 120 0.3986 1.39E+13 7.20E+06 2.30E+07 1.40E+04 4.48E+04 121 0.5441 2.17E+13 1.74E+07 4.84E+07 3.41E+04 9.48E+04 122 0.7586 5.19E+13 6.71E+07 1.63E+08 1.28E+05 3.12E+05 123 0.9037 7.17E+12 1.20E+07 2.73E+07 2.24E+04 5.11E+04 124 1.0755 3.15E+12 6.78E+06 1.46E+07 1.23E+04 2.66E+04 125 1.1998 6.19E+12 1.57E+07 3.27E+07 2.79E+04 5.81E+04 126 1.3588 7.12E+12 2.17E+07 4.35E+07 3.75E+04 7.51E+04 127 1.5948 7.97E+12 3.09E+07 5.91E+07 5.11E+04 9.77E+04 128 1.7185 7.44E+11 3.22E+06 6.04E+06 5.22E+03 9.78E+03 129 1.8681 3.24E+11 1.59E+06 2.91E+06 2.51E+03 4.60E+03 130 2.0421 2.48E+11 1.39E+06 2.49E+06 2.14E+03 3.83E+03 131 2.2086 8.98E+10 5.66E+05 9.95E+05 8.48E+02 1.49E+03 132 2.3715 1.32E+11 9.26E+05 1.60E+06 1.36E+03 2.34E+03 Calc. No. L-003430, Rev. 0, Attachment A, A-3 of A-18

A B C D E F G H I 133 2.5226 3.10E+11 2.38E+06 4.05E+06 3.42E+03 5.81E+03 134 2.7363 1.07E+11 9.25E+05 1.54E+06 1.29E+03 2.16E+03 135 2.8117 2.35E+09 2.12E+04 3.51E+04 2.94E+01 4.86E+01 136 2.9944 8.63E+09 8.55E+04 1.40E+05 1.16E+02 1.89E+02 137 3.2183 1.90E+09 2.09E+04 3.36E+04 2.78E+01 4.46E+01 138 3.3487 4.13E+09 4.82E+04 7.67E+04 6.32E+01 1.01E+02 139 3.4593 3.37E+08 4.13E+03 6.52E+03 5.36E+00 8.46E+00 140 3.6364 2.17E+09 2.86E+04 4.46E+04 3.65E+01 5.69E+01 141 3.8453 2.98E+08 4.26E+03 6.56E+03 5.34E+00 8.22E+00 142 3.9336 2.94E+09 4.34E+04 6.65E+04 5.41E+01 8.28E+01 143 Totals 2.29E+14 2.00E+08 4.82E+08 3.64E+05 8.85E+05 Calc. No. L-003430, Rev. 0, Attachment A, A-4 of A-18

A B C D E F G H I 1 MicroShield 8.01 2 Washington Group International (8.00-0000) 3 Date By Checked 4

5 Filename Run Date Run Time Duration 6 Lasalledecay4.msd 11-Aug-09 8:56:39 AM 0:00:07 7 Project Info 8 Case Title Lasalle 11.2-5 9 Description before resizing 10 Geometry 7 - Cylinder Volume - Side Shields 11 Source Dimensions 12 Height 182.88 cm (6 ft) 13 Radius 76.2 cm (2 ft 6.0 in) 14 Dose Points 15 A X Y Z 16 #1 78.74 cm (2 ft 7.0 in) 91.44 cm (3 ft) 0.0 cm (0 in) 17 Shields 18 Shield N Dimension Material Density 19 Source 3.34e+06 cm³ Water 0.9 20 Transition Air 0.00122 21 Air Gap Air 0.00122 22 Source Input: Grouping Method - Linear Energy 23 Number of Groups: 25 24 Lower Energy Cutoff: 0.015 25 Photons < 0.015: Included 26 Library: Grove 27 Nuclide Ci Bq µCi/cm³ Bq/cm³ 28 Ac-227 1.10E-22 4.05E-12 3.28E-23 1.21E-18 29 Ag-110 1.27E-01 4.71E+09 3.81E-02 1.41E+03 30 Ag-110m 9.57E+00 3.54E+11 2.87E+00 1.06E+05 31 Ba-137m 2.98E+01 1.10E+12 8.93E+00 3.30E+05 32 Ba-139 1.8042e-312 6.68E-302 5.4084e-313 0.00E-01 33 Ba-140 8.51E+00 3.15E+11 2.55E+00 9.44E+04 34 Ba-141 35 Ba-142 36 Bi-211 2.46E-23 9.09E-13 7.37E-24 2.73E-19 37 Br-83 1.21E-181 4.48E-171 3.63E-182 1.34E-177 38 Br-84 39 Br-85 40 Ce-141 1.78E+00 6.59E+10 5.34E-01 1.97E+04 41 Ce-143 6.74E-15 2.49E-04 2.02E-15 7.47E-11 42 Ce-144 5.84E+00 2.16E+11 1.75E+00 6.48E+04 43 Co-58 3.12E+02 1.16E+13 9.36E+01 3.46E+06 44 Co-60 1.14E+02 4.20E+12 3.40E+01 1.26E+06 45 Cr-51 5.86E+00 2.17E+11 1.76E+00 6.50E+04 46 Cs-134 1.85E+01 6.83E+11 5.53E+00 2.05E+05 47 Cs-135 2.27E-08 8.41E+02 6.81E-09 2.52E-04 48 Cs-136 6.45E-02 2.39E+09 1.93E-02 7.15E+02 49 Cs-137 3.15E+01 1.16E+12 9.44E+00 3.49E+05 50 Cs-138 51 F-18 52 Fe-59 2.54E+00 9.40E+10 7.61E-01 2.82E+04 53 Fr-223 1.58E-24 5.85E-14 4.74E-25 1.75E-20 54 I-129 4.88E-08 1.81E+03 1.46E-08 5.42E-04 55 I-131 1.13E+00 4.20E+10 3.40E-01 1.26E+04 56 I-132 9.00E-04 3.33E+07 2.70E-04 9.98E+00 57 I-133 2.15E-19 7.96E-09 6.45E-20 2.39E-15 58 I-134 59 I-135 1.82E-64 6.75E-54 5.47E-65 2.02E-60 60 Kr-83m 5.16E-181 1.91E-170 1.55E-181 5.72E-177 61 Kr-85 5.13E-09 1.90E+02 1.54E-09 5.69E-05 62 Kr-85m 8.98E-101 3.32E-90 2.69E-101 9.96E-97 63 La-140 9.80E+00 3.63E+11 2.94E+00 1.09E+05 64 La-141 4.17E-110 1.54E-99 1.25E-110 4.63E-106 65 La-142 6.47E-273 2.39E-262 1.94E-273 7.17E-269 66 Mn-54 6.85E+00 2.53E+11 2.05E+00 7.59E+04 Calc. No. L-003430, Rev. 0, Attachment A, A-5 of A-18

A B C D E F G H I 67 Mn-56 7.84E-168 2.90E-157 2.35E-168 8.69E-164 68 Mo-99 3.18E-05 1.18E+06 9.53E-06 3.53E-01 69 N-16 70 Na-24 3.03E-29 1.12E-18 9.08E-30 3.36E-25 71 Nb-95 3.96E+00 1.46E+11 1.19E+00 4.39E+04 72 Nb-95m 1.88E-02 6.95E+08 5.63E-03 2.08E+02 73 Nb-97 1.05E-27 3.87E-17 3.14E-28 1.16E-23 74 Nb-97m 9.21E-28 3.41E-17 2.76E-28 1.02E-23 75 Nd-147 6.75E-03 2.50E+08 2.02E-03 7.49E+01 76 Ni-65 5.84E-174 2.16E-163 1.75E-174 6.48E-170 77 Np-239 2.31E-05 8.55E+05 6.93E-06 2.56E-01 78 P-32 2.98E-02 1.10E+09 8.93E-03 3.30E+02 79 Pa-231 6.87E-20 2.54E-09 2.06E-20 7.61E-16 80 Pb-211 2.03E-23 7.53E-13 6.10E-24 2.26E-19 81 Pm-147 3.51E-02 1.30E+09 1.05E-02 3.89E+02 82 Po-211 5.49E-26 2.03E-15 1.65E-26 6.09E-22 83 Po-215 1.93E-23 7.16E-13 5.80E-24 2.15E-19 84 Pr-143 5.08E-02 1.88E+09 1.52E-02 5.63E+02 85 Pr-144 5.84E+00 2.16E+11 1.75E+00 6.48E+04 86 Pr-144m 8.35E-02 3.09E+09 2.50E-02 9.26E+02 87 Pu-239 2.89E-04 1.07E+07 8.65E-05 3.20E+00 88 Ra-223 1.80E-23 6.66E-13 5.40E-24 2.00E-19 89 Re-187 3.30E-13 1.22E-02 9.90E-14 3.66E-09 90 Rh-103m 4.79E-01 1.77E+10 1.44E-01 5.31E+03 91 Rh-106 4.70E-01 1.74E+10 1.41E-01 5.21E+03 92 Rn-219 2.54E-23 9.39E-13 7.61E-24 2.81E-19 93 Ru-103 4.80E-01 1.77E+10 1.44E-01 5.32E+03 94 Ru-106 4.70E-01 1.74E+10 1.41E-01 5.21E+03 95 Sm-147 3.77E-14 1.39E-03 1.13E-14 4.18E-10 96 Sr-89 1.23E+02 4.55E+12 3.69E+01 1.36E+06 97 Sr-90 5.44E+01 2.01E+12 1.63E+01 6.03E+05 98 Sr-91 1.25E-44 4.61E-34 3.73E-45 1.38E-40 99 Sr-92 2.61E-159 9.64E-149 7.81E-160 2.89E-155 100 Tc-99 4.06E-04 1.50E+07 1.22E-04 4.50E+00 101 Tc-99m 3.10E-05 1.15E+06 9.29E-06 3.44E-01 102 Tc-101 103 Te-129 4.62E-01 1.71E+10 1.39E-01 5.13E+03 104 Te-129m 7.34E-01 2.72E+10 2.20E-01 8.14E+03 105 Te-132 8.73E-04 3.23E+07 2.62E-04 9.68E+00 106 Th-227 4.12E-23 1.52E-12 1.24E-23 4.57E-19 107 Th-231 4.28E-14 1.59E-03 1.28E-14 4.75E-10 108 Tl-207 2.38E-23 8.80E-13 7.13E-24 2.64E-19 109 U-235 4.40E-14 1.63E-03 1.32E-14 4.88E-10 110 W-187 3.68E-18 1.36E-07 1.10E-18 4.08E-14 111 Xe-131m 1.11E-01 4.11E+09 3.33E-02 1.23E+03 112 Xe-133 1.08E-02 4.01E+08 3.25E-03 1.20E+02 113 Xe-133m 1.59E-08 5.88E+02 4.77E-09 1.76E-04 114 Xe-135 4.81E-46 1.78E-35 1.44E-46 5.33E-42 115 Xe-135m 3.13E-65 1.16E-54 9.38E-66 3.47E-61 116 Y-90 5.44E+01 2.01E+12 1.63E+01 6.03E+05 117 Y-90m 118 Y-91 2.32E+01 8.58E+11 6.95E+00 2.57E+05 119 Y-91m 7.83E-45 2.90E-34 2.35E-45 8.69E-41 120 Y-92 3.55E-121 1.32E-110 1.07E-121 3.94E-117 121 Zn-65 3.15E-01 1.17E+10 9.46E-02 3.50E+03 122 Zn-69 1.10E-33 4.08E-23 3.31E-34 1.22E-29 123 Zn-69m 1.03E-33 3.81E-23 3.09E-34 1.14E-29 124 Zr-95 2.21E+00 8.19E+10 6.64E-01 2.46E+04 125 Zr-97 9.72E-28 3.60E-17 2.91E-28 1.08E-23 126 Buildup: The material reference is Source 127 Integration Parameters 128 Radial 30 129 Circumferential 30 130 Y Direction (axial) 60 131 Results 132 Fluence Rate Fluence Rate Exposure Rate Exposure Rate Calc. No. L-003430, Rev. 0, Attachment A, A-6 of A-18

A B C D E F G H I 133 Energy (MeV) Activity (Photons/sec) MeV/cm²/sec MeV/cm²/sec mR/hr mR/hr 134 No Buildup With Buildup No Buildup With Buildup 135 0.0102 3.52E+12 3.03E+03 3.53E+03 8.86E+02 1.03E+03 136 0.2239 4.63E+10 1.09E+04 4.82E+04 1.98E+01 8.71E+01 137 0.3606 1.73E+11 7.81E+04 2.62E+05 1.51E+02 5.07E+02 138 0.5262 4.56E+12 3.49E+06 9.83E+06 6.85E+03 1.93E+04 139 0.681 1.81E+12 2.00E+06 5.08E+06 3.87E+03 9.82E+03 140 0.8126 1.29E+13 1.84E+07 4.36E+07 3.49E+04 8.27E+04 141 0.9418 1.58E+11 2.80E+05 6.31E+05 5.21E+02 1.18E+03 142 1.1722 4.28E+12 1.05E+07 2.20E+07 1.87E+04 3.92E+04 143 1.3333 4.35E+12 1.29E+07 2.60E+07 2.23E+04 4.50E+04 144 1.4981 6.11E+10 2.15E+05 4.19E+05 3.62E+02 7.05E+02 145 1.6079 4.12E+11 1.62E+06 3.09E+06 2.67E+03 5.09E+03 146 1.7575 9.86E+04 4.41E-01 8.23E-01 7.10E-04 1.32E-03 147 1.9599 7.56E+05 3.98E+00 7.22E+00 6.20E-03 1.12E-02 148 2.0868 7.88E+04 4.56E-01 8.14E-01 6.96E-04 1.24E-03 149 2.1857 1.67E+09 1.04E+04 1.83E+04 1.56E+01 2.75E+01 150 2.3488 3.08E+09 2.13E+04 3.69E+04 3.13E+01 5.42E+01 151 2.5224 1.29E+10 9.92E+04 1.69E+05 1.42E+02 2.42E+02 152 2.7541 1.12E-18 9.80E-24 1.63E-23 1.37E-26 2.28E-26 153 2.8086 4.90E-264 4.42E-269 7.32E-269 6.12E-272 1.01E-271 154 2.9598 8.89E-160 8.66E-165 1.42E-164 1.18E-167 1.93E-167 155 3.1706 1.26E-264 1.36E-269 2.18E-269 1.81E-272 2.91E-272 156 3.3696 4.87E-160 5.75E-165 9.12E-165 7.52E-168 1.19E-167 157 3.4328 1.63E-264 1.98E-269 3.13E-269 2.57E-272 4.07E-272 158 3.6237 4.90E-264 6.43E-269 1.00E-268 8.22E-272 1.28E-271 159 3.8236 7.18E-22 1.02E-26 1.57E-26 1.28E-29 1.97E-29 160 Totals 3.23E+13 4.96E+07 1.11E+08 9.15E+04 2.05E+05 Calc. No. L-003430, Rev. 0, Attachment A, A-7 of A-18

A B C D E F G H I 1 MicroShield 8.01 2 Washington Group International (8.00-0000) 3 Date By Checked 4

5 Filename Run Date Run Time Duration 6 Lasalledecay2.msd 3-Aug-09 1:38:55 PM 0:00:07 7 Project Info 8 Case Title Lasalle 11.2-5 9 Description After Resizing 10 Geometry 7 - Cylinder Volume - Side Shields 11 Source Dimensions 12 Height 182.88 cm (6 ft) 13 Radius 76.2 cm (2 ft 6.0 in) 14 Dose Points 15 A X Y Z 16 #1 78.74 cm (2 ft 7.0 in) 91.44 cm (3 ft) 0.0 cm (0 in) 17 Shields 18 Shield N Dimension Material Density 19 Source 2.04e+05 in³ Water 0.9 20 Transition Air 0.00122 21 Air Gap Air 0.00122 22 Source Input: Grouping Method - Linear Energy 23 Number of Groups: 25 24 Lower Energy Cutoff: 0.015 25 Photons < 0.015: Included 26 Library: Grove 27 Nuclide Ci Bq µCi/cm³ Bq/cm³ 28 Ac-227 1.07E-22 3.95E-12 3.20E-23 1.18E-18 29 Ag-110 1.24E-01 4.59E+09 3.72E-02 1.38E+03 30 Ag-110m 9.33E+00 3.45E+11 2.80E+00 1.04E+05 31 Ba-137m 2.91E+01 1.08E+12 8.71E+00 3.22E+05 32 Ba-139 1.7602e-312 6.51E-302 5.2765e-313 0.00E-01 33 Ba-140 8.31E+00 3.07E+11 2.49E+00 9.21E+04 34 Ba-141 35 Ba-142 36 Bi-211 2.40E-23 8.87E-13 7.19E-24 2.66E-19 37 Br-83 1.18E-181 4.37E-171 3.54E-182 1.31E-177 38 Br-84 39 Br-85 40 Ce-141 1.74E+00 6.43E+10 5.21E-01 1.93E+04 41 Ce-143 6.57E-15 2.43E-04 1.97E-15 7.29E-11 42 Ce-144 5.70E+00 2.11E+11 1.71E+00 6.32E+04 43 Co-58 3.05E+02 1.13E+13 9.13E+01 3.38E+06 44 Co-60 1.11E+02 4.10E+12 3.32E+01 1.23E+06 45 Cr-51 5.72E+00 2.12E+11 1.71E+00 6.34E+04 46 Cs-134 1.80E+01 6.66E+11 5.40E+00 2.00E+05 47 Cs-135 2.22E-08 8.20E+02 6.64E-09 2.46E-04 48 Cs-136 6.29E-02 2.33E+09 1.89E-02 6.98E+02 49 Cs-137 3.07E+01 1.14E+12 9.21E+00 3.41E+05 50 Cs-138 51 F-18 52 Fe-59 2.48E+00 9.17E+10 7.43E-01 2.75E+04 53 Fr-223 1.54E-24 5.71E-14 4.63E-25 1.71E-20 54 I-129 4.76E-08 1.76E+03 1.43E-08 5.28E-04 Calc. No. L-003430, Rev. 0, Attachment A, A-8 of A-18

A B C D E F G H I 55 I-131 1.11E+00 4.09E+10 3.32E-01 1.23E+04 56 I-132 8.78E-04 3.25E+07 2.63E-04 9.73E+00 57 I-133 2.10E-19 7.76E-09 6.29E-20 2.33E-15 58 I-134 59 I-135 1.78E-64 6.58E-54 5.33E-65 1.97E-60 60 Kr-83m 5.04E-181 1.86E-170 1.51E-181 5.58E-177 61 Kr-85 5.00E-09 1.85E+02 1.50E-09 5.55E-05 62 Kr-85m 8.77E-101 3.24E-90 2.63E-101 9.72E-97 63 La-140 9.56E+00 3.54E+11 2.87E+00 1.06E+05 64 La-141 4.07E-110 1.51E-99 1.22E-110 4.52E-106 65 La-142 6.31E-273 2.34E-262 1.89E-273 7.00E-269 66 Mn-54 6.68E+00 2.47E+11 2.00E+00 7.41E+04 67 Mn-56 7.65E-168 2.83E-157 2.29E-168 8.48E-164 68 Mo-99 3.10E-05 1.15E+06 9.30E-06 3.44E-01 69 N-16 70 Na-24 2.96E-29 1.09E-18 8.86E-30 3.28E-25 71 Nb-95 3.86E+00 1.43E+11 1.16E+00 4.28E+04 72 Nb-95m 1.83E-02 6.78E+08 5.49E-03 2.03E+02 73 Nb-97 1.02E-27 3.78E-17 3.06E-28 1.13E-23 74 Nb-97m 8.99E-28 3.33E-17 2.69E-28 9.97E-24 75 Nd-147 6.58E-03 2.44E+08 1.97E-03 7.30E+01 76 Ni-65 5.70E-174 2.11E-163 1.71E-174 6.32E-170 77 Np-239 2.26E-05 8.34E+05 6.76E-06 2.50E-01 78 P-32 2.91E-02 1.08E+09 8.71E-03 3.22E+02 79 Pa-231 6.70E-20 2.48E-09 2.01E-20 7.43E-16 80 Pb-211 1.98E-23 7.34E-13 5.95E-24 2.20E-19 81 Pm-147 3.43E-02 1.27E+09 1.03E-02 3.80E+02 82 Po-211 5.36E-26 1.98E-15 1.61E-26 5.94E-22 83 Po-215 1.89E-23 6.98E-13 5.66E-24 2.09E-19 84 Pr-143 4.95E-02 1.83E+09 1.48E-02 5.49E+02 85 Pr-144 5.70E+00 2.11E+11 1.71E+00 6.32E+04 86 Pr-144m 8.15E-02 3.01E+09 2.44E-02 9.04E+02 87 Pu-239 2.82E-04 1.04E+07 8.44E-05 3.12E+00 88 Ra-223 1.76E-23 6.50E-13 5.27E-24 1.95E-19 89 Re-187 3.22E-13 1.19E-02 9.66E-14 3.57E-09 90 Rh-103m 4.67E-01 1.73E+10 1.40E-01 5.18E+03 91 Rh-106 4.58E-01 1.70E+10 1.37E-01 5.08E+03 92 Rn-219 2.48E-23 9.16E-13 7.42E-24 2.75E-19 93 Ru-103 4.68E-01 1.73E+10 1.40E-01 5.19E+03 94 Ru-106 4.58E-01 1.70E+10 1.37E-01 5.08E+03 95 Sm-147 3.68E-14 1.36E-03 1.10E-14 4.08E-10 96 Sr-89 1.20E+02 4.44E+12 3.60E+01 1.33E+06 97 Sr-90 5.31E+01 1.96E+12 1.59E+01 5.88E+05 98 Sr-91 1.22E-44 4.50E-34 3.64E-45 1.35E-40 99 Sr-92 2.54E-159 9.41E-149 7.62E-160 2.82E-155 100 Tc-99 3.96E-04 1.47E+07 1.19E-04 4.39E+00 101 Tc-99m 3.02E-05 1.12E+06 9.06E-06 3.35E-01 102 Tc-101 103 Te-129 4.51E-01 1.67E+10 1.35E-01 5.00E+03 104 Te-129m 7.16E-01 2.65E+10 2.15E-01 7.94E+03 105 Te-132 8.52E-04 3.15E+07 2.55E-04 9.45E+00 106 Th-227 4.02E-23 1.49E-12 1.21E-23 4.46E-19 107 Th-231 4.18E-14 1.55E-03 1.25E-14 4.64E-10 Calc. No. L-003430, Rev. 0, Attachment A, A-9 of A-18

A B C D E F G H I 108 Tl-207 2.32E-23 8.58E-13 6.95E-24 2.57E-19 109 U-235 4.30E-14 1.59E-03 1.29E-14 4.77E-10 110 W-187 3.59E-18 1.33E-07 1.08E-18 3.98E-14 111 Xe-131m 1.08E-01 4.01E+09 3.25E-02 1.20E+03 112 Xe-133 1.06E-02 3.91E+08 3.17E-03 1.17E+02 113 Xe-133m 1.55E-08 5.74E+02 4.65E-09 1.72E-04 114 Xe-135 4.69E-46 1.74E-35 1.41E-46 5.20E-42 115 Xe-135m 3.05E-65 1.13E-54 9.15E-66 3.39E-61 116 Y-90 5.31E+01 1.96E+12 1.59E+01 5.89E+05 117 Y-90m 118 Y-91 2.26E+01 8.37E+11 6.78E+00 2.51E+05 119 Y-91m 7.64E-45 2.83E-34 2.29E-45 8.47E-41 120 Y-92 3.47E-121 1.28E-110 1.04E-121 3.85E-117 121 Zn-65 3.08E-01 1.14E+10 9.23E-02 3.41E+03 122 Zn-69 1.08E-33 3.98E-23 3.23E-34 1.19E-29 123 Zn-69m 1.00E-33 3.72E-23 3.01E-34 1.11E-29 124 Zr-95 2.16E+00 7.99E+10 6.48E-01 2.40E+04 125 Zr-97 9.48E-28 3.51E-17 2.84E-28 1.05E-23 126 Buildup: The material reference is Source 127 Integration Parameters 128 Radial 30 129 Circumferential 30 130 Y Direction (axial) 60 131 Results 132 Fluence Rate Fluence Rate Exposure Rate Exposure Rate 133 Energy (MeV) Activity (Photons/sec) MeV/cm²/sec MeV/cm²/sec mR/hr mR/hr 134 No Buildup With Buildup No Buildup With Buildup 135 0.0102 3.44E+12 2.96E+03 3.44E+03 8.64E+02 1.01E+03 136 0.2239 4.52E+10 1.07E+04 4.70E+04 1.93E+01 8.49E+01 137 0.3606 1.69E+11 7.62E+04 2.56E+05 1.47E+02 4.94E+02 138 0.5262 4.45E+12 3.40E+06 9.59E+06 6.68E+03 1.88E+04 139 0.681 1.77E+12 1.95E+06 4.95E+06 3.78E+03 9.58E+03 140 0.8126 1.26E+13 1.79E+07 4.25E+07 3.40E+04 8.07E+04 141 0.9418 1.54E+11 2.73E+05 6.16E+05 5.09E+02 1.15E+03 142 1.1722 4.17E+12 1.02E+07 2.14E+07 1.82E+04 3.83E+04 143 1.3333 4.24E+12 1.26E+07 2.53E+07 2.18E+04 4.39E+04 144 1.4981 5.96E+10 2.10E+05 4.09E+05 3.53E+02 6.88E+02 145 1.6079 4.02E+11 1.58E+06 3.01E+06 2.60E+03 4.97E+03 146 1.7575 9.61E+04 4.30E-01 8.02E-01 6.92E-04 1.29E-03 147 1.9599 7.37E+05 3.89E+00 7.04E+00 6.05E-03 1.10E-02 148 2.0868 7.69E+04 4.45E-01 7.94E-01 6.79E-04 1.21E-03 149 2.1857 1.63E+09 1.01E+04 1.79E+04 1.52E+01 2.68E+01 150 2.3488 3.01E+09 2.08E+04 3.60E+04 3.05E+01 5.29E+01 151 2.5224 1.26E+10 9.68E+04 1.65E+05 1.39E+02 2.36E+02 152 2.7541 1.09E-18 9.56E-24 1.59E-23 1.33E-26 2.22E-26 153 2.8086 4.78E-264 4.31E-269 7.14E-269 5.97E-272 9.89E-272 154 2.9598 8.67E-160 8.45E-165 1.38E-164 1.15E-167 1.88E-167 155 3.1706 1.23E-264 1.32E-269 2.13E-269 1.76E-272 2.84E-272 156 3.3696 4.76E-160 5.61E-165 8.90E-165 7.33E-168 1.16E-167 157 3.4328 1.59E-264 1.93E-269 3.05E-269 2.51E-272 3.97E-272 158 3.6237 4.78E-264 6.27E-269 9.79E-269 8.01E-272 1.25E-271 159 3.8236 7.01E-22 9.94E-27 1.53E-26 1.25E-29 1.92E-29 160 Totals 3.15E+13 4.83E+07 1.08E+08 8.92E+04 2.00E+05 Calc. No. L-003430, Rev. 0, Attachment A, A-10 of A-18

A B C D E F 1 Container Drop Event: LaSalle Isotopic: Table 11.2-5 2 5.400E-04 X/Q (sec/m^3) 3 3.500E-04 Breathing Rate (m^3/sec) 4 1.000E-02 Release Fraction 5 3.70E+12 Conversion Factor (rem/Ci per Sv/Bq) 6 1.00E+00 Containers/Accident 7 2.00E+02 Container Contact - Nominal Baseline Analysis (R/hr) 8 3.80E+02 Container Contact - Bounding Accident Value (R/hr) 9 10 3.889E-01 Total Inhalation Dose 11 60 day Decay 12 Isotope Ci in container InhaleDCF Dose (rem) 13 Ac-227 1.068E-22 1.810E-03 2.57E-21 14 Ag-110 1.241E-01 0.00E+00 0.00E+00 15 Ag-110m 9.334E+00 2.170E-08 2.69E-03 16 Ba-137m 2.906E+01 0.00E+00 0.00E+00 17 Ba-139 1.7602e-312 4.640E-11 0.00E+00 18 Ba-140 8.306E+00 1.010E-09 1.11E-04 19 Ba-141 0.000E+00 2.180E-11 0.00E+00 20 Ba-142 0.000E+00 1.110E-11 0.00E+00 21 Bi-211 2.398E-23 0.00E+00 0.00E+00 22 Br-83 1.180E-181 2.410E-11 3.78E-188 23 Br-84 0.000E+00 2.610E-11 0.00E+00 24 Br-85 0.000E+00 0.00E+00 0.00E+00 25 Ce-141 1.737E+00 2.420E-09 5.59E-05 26 Ce-143 6.572E-15 9.160E-10 8.00E-20 27 Ce-144 5.698E+00 1.010E-07 7.65E-03 28 Co-58 3.047E+02 2.940E-09 1.19E-02 29 Co-60 1.108E+02 5.910E-08 8.70E-02 30 Cr-51 5.718E+00 9.030E-11 6.86E-06 31 Cs-134 1.800E+01 1.250E-08 2.99E-03 32 Cs-135 2.217E-08 1.230E-09 3.62E-13 33 Cs-136 6.290E-02 1.980E-09 1.65E-06 34 Cs-137 3.071E+01 8.630E-09 3.52E-03 35 Cs-138 0.000E+00 2.740E-11 0.00E+00 36 F-18 0.000E+00 2.260E-11 0.00E+00 37 Fe-59 2.478E+00 4.000E-09 1.32E-04 38 Fr-223 1.543E-24 1.680E-09 3.45E-29 39 I-129 4.764E-08 4.690E-08 2.97E-11 40 I-131 1.106E+00 8.890E-09 1.31E-04 41 I-132 8.776E-04 1.030E-10 1.20E-09 42 I-133 2.099E-19 1.580E-09 4.41E-24 43 I-134 0.000E+00 3.550E-11 0.00E+00 44 I-135 1.779E-64 3.320E-10 7.85E-70 45 Kr-83m 5.035E-181 0.00E+00 0.00E+00 46 Kr-85 5.001E-09 0.00E+00 0.00E+00 47 Kr-85m 8.765E-101 0.00E+00 0.00E+00 48 La-140 9.559E+00 1.310E-09 1.66E-04 49 La-141 4.072E-110 1.570E-10 8.49E-116 50 La-142 6.311E-273 6.840E-11 5.74E-279 51 Mn-54 6.679E+00 1.810E-09 1.61E-04 52 Mn-56 7.645E-168 1.020E-10 1.04E-173 53 Mo-99 3.101E-05 1.070E-09 4.41E-10 54 N-16 0.000E+00 0.00E+00 0.00E+00 55 Na-24 2.955E-29 3.270E-10 1.28E-34 56 Nb-95 3.859E+00 1.570E-09 8.05E-05 57 Nb-95m 1.832E-02 6.590E-10 1.60E-07 Calc. No. L-003430, Rev. 0, Attachment A, A-11 of A-18

A B C D E F 58 Nb-97 1.022E-27 2.240E-11 3.04E-34 59 Nb-97m 8.988E-28 0.00E+00 0.00E+00 60 Nd-147 6.585E-03 1.850E-09 1.62E-07 61 Ni-65 5.702E-174 9.320E-11 7.06E-180 62 Np-239 2.255E-05 6.780E-10 2.03E-10 63 P-32 2.906E-02 4.190E-09 1.62E-06 64 Pa-231 6.698E-20 3.470E-04 3.09E-19 65 Pb-211 1.984E-23 2.350E-09 6.20E-28 66 Pm-147 3.426E-02 1.060E-08 4.83E-06 67 Po-211 5.359E-26 0.00E+00 0.00E+00 68 Po-215 1.888E-23 0.00E+00 0.00E+00 69 Pr-143 4.953E-02 2.190E-09 1.44E-06 70 Pr-144 5.698E+00 1.170E-11 8.86E-07 71 Pr-144m 8.148E-02 0.00E+00 0.00E+00 72 Pu-239 2.815E-04 1.160E-04 4.34E-04 73 Ra-223 1.757E-23 2.120E-06 4.95E-25 74 Re-187 3.222E-13 1.470E-11 6.29E-20 75 Rh-103m 4.671E-01 1.380E-12 8.57E-09 76 Rh-106 4.584E-01 0.00E+00 0.00E+00 77 Rn-219 2.476E-23 0.00E+00 0.00E+00 78 Ru-103 4.679E-01 2.420E-09 1.50E-05 79 Ru-106 4.584E-01 1.290E-07 7.86E-04 80 Sm-147 3.676E-14 2.020E-05 9.87E-15 81 Sr-89 1.200E+02 1.120E-08 1.79E-02 82 Sr-90 5.306E+01 3.510E-07 2.47E-01 83 Sr-91 1.215E-44 4.490E-10 7.25E-50 84 Sr-92 2.543E-159 2.180E-10 7.36E-165 85 Tc-99 3.960E-04 2.250E-09 1.18E-08 86 Tc-99m 3.023E-05 8.800E-12 3.53E-12 87 Tc-101 0.000E+00 4.840E-12 0.00E+00 88 Te-129 4.509E-01 2.420E-11 1.45E-07 89 Te-129m 7.159E-01 6.470E-09 6.15E-05 90 Te-132 8.518E-04 2.550E-09 2.89E-08 91 Th-227 4.020E-23 4.370E-06 2.33E-24 92 Th-231 4.180E-14 2.370E-10 1.32E-19 93 Tl-207 2.320E-23 0.00E+00 0.00E+00 94 U-235 4.297E-14 3.320E-05 1.90E-14 95 W-187 3.591E-18 1.670E-10 7.97E-24 96 Xe-131m 1.083E-01 0.00E+00 0.00E+00 97 Xe-133 1.057E-02 0.00E+00 0.00E+00 98 Xe-133m 1.551E-08 0.00E+00 0.00E+00 99 Xe-135 4.689E-46 0.00E+00 0.00E+00 100 Xe-135m 3.053E-65 0.00E+00 0.00E+00 101 Y-90 5.307E+01 2.280E-09 1.61E-03 102 Y-90m 0.000E+00 1.270E-10 0.00E+00 103 Y-91 2.261E+01 1.320E-08 3.97E-03 104 Y-91m 7.640E-45 9.820E-12 9.97E-52 105 Y-92 3.468E-121 2.110E-10 9.72E-127 106 Zn-65 3.078E-01 5.510E-09 2.25E-05 107 Zn-69 1.077E-33 1.060E-11 1.52E-40 108 Zn-69m 1.005E-33 2.200E-10 2.94E-39 109 Zr-95 2.160E+00 6.390E-09 1.83E-04 110 Zr-97 9.481E-28 1.170E-09 1.47E-32 111 112 113 114 Dose Total (rem) 3.889E-01 Calc. No. L-003430, Rev. 0, Attachment A, A-12 of A-18

A B C D E F 1 Container Fire Event: LaSalle Isotopic: Table 11.2-5 2 5.400E-04 X/Q (sec/m^3) 3 3.500E-04 Breathing Rate (m^3/sec) 4 1.000E-02 Release Fraction 5 3.70E+12 Conversion Factor (rem/Ci per Sv/Bq) 6 6.00E+00 Containers/Accident 7 2.00E+02 Container Contact - Nominal Baseline Analysis (R/hr) 8 3.80E+02 Container Contact - Bounding Accident Value (R/hr) 9 10 2.334E+00 Total Inhalation Dose 11 60 day Decay 12 Isotope Ci in Container Inhaled DCF Dose (rem) 13 Ac-227 1.068E-22 1.810E-03 1.541E-20 14 Ag-110 1.241E-01 0.00E+00 0.000E+00 15 Ag-110m 9.334E+00 2.170E-08 1.615E-02 16 Ba-137m 2.906E+01 0.00E+00 0.000E+00 17 Ba-139 1.7602e-312 4.640E-11 0.000E+00 18 Ba-140 8.306E+00 1.010E-09 6.688E-04 19 Ba-141 0.000E+00 2.180E-11 0.000E+00 20 Ba-142 0.000E+00 1.110E-11 0.000E+00 21 Bi-211 2.398E-23 0.00E+00 0.000E+00 22 Br-83 1.180E-181 2.410E-11 2.267E-187 23 Br-84 0.000E+00 2.610E-11 0.000E+00 24 Br-85 0.000E+00 0.00E+00 0.000E+00 25 Ce-141 1.737E+00 2.420E-09 3.351E-04 26 Ce-143 6.572E-15 9.160E-10 4.799E-19 27 Ce-144 5.698E+00 1.010E-07 4.588E-02 28 Co-58 3.047E+02 2.940E-09 7.142E-02 29 Co-60 1.108E+02 5.910E-08 5.218E-01 30 Cr-51 5.718E+00 9.030E-11 4.117E-05 31 Cs-134 1.800E+01 1.250E-08 1.794E-02 32 Cs-135 2.217E-08 1.230E-09 2.174E-12 33 Cs-136 6.290E-02 1.980E-09 9.928E-06 34 Cs-137 3.071E+01 8.630E-09 2.113E-02 35 Cs-138 0.000E+00 2.740E-11 0.000E+00 36 F-18 0.000E+00 2.260E-11 0.000E+00 37 Fe-59 2.478E+00 4.000E-09 7.903E-04 38 Fr-223 1.543E-24 1.680E-09 2.067E-28 39 I-129 4.764E-08 4.690E-08 1.781E-10 40 I-131 1.106E+00 8.890E-09 7.839E-04 41 I-132 8.776E-04 1.030E-10 7.206E-09 42 I-133 2.099E-19 1.580E-09 2.643E-23 43 I-134 0.000E+00 3.550E-11 0.000E+00 44 I-135 1.779E-64 3.320E-10 4.708E-69 45 Kr-83m 5.035E-181 0.00E+00 0.000E+00 46 Kr-85 5.001E-09 0.00E+00 0.000E+00 47 Kr-85m 8.765E-101 0.00E+00 0.000E+00 48 La-140 9.559E+00 1.310E-09 9.983E-04 49 La-141 4.072E-110 1.570E-10 5.096E-115 50 La-142 6.311E-273 6.840E-11 3.441E-278 51 Mn-54 6.679E+00 1.810E-09 9.638E-04 52 Mn-56 7.645E-168 1.020E-10 6.217E-173 53 Mo-99 3.101E-05 1.070E-09 2.645E-09 54 N-16 0.000E+00 0.00E+00 0.000E+00 55 Na-24 2.955E-29 3.270E-10 7.704E-34 56 Nb-95 3.859E+00 1.570E-09 4.830E-04 57 Nb-95m 1.832E-02 6.590E-10 9.622E-07 58 Nb-97 1.022E-27 2.240E-11 1.824E-33 Calc. No. L-003430, Rev. 0, Attachment A, A-13 of A-18

A B C D E F 59 Nb-97m 8.988E-28 0.00E+00 0.000E+00 60 Nd-147 6.585E-03 1.850E-09 9.711E-07 61 Ni-65 5.702E-174 9.320E-11 4.237E-179 62 Np-239 2.255E-05 6.780E-10 1.219E-09 63 P-32 2.906E-02 4.190E-09 9.707E-06 64 Pa-231 6.698E-20 3.470E-04 1.853E-18 65 Pb-211 1.984E-23 2.350E-09 3.717E-27 66 Pm-147 3.426E-02 1.060E-08 2.895E-05 67 Po-211 5.359E-26 0.00E+00 0.000E+00 68 Po-215 1.888E-23 0.00E+00 0.000E+00 69 Pr-143 4.953E-02 2.190E-09 8.647E-06 70 Pr-144 5.698E+00 1.170E-11 5.314E-06 71 Pr-144m 8.148E-02 0.00E+00 0.000E+00 72 Pu-239 2.815E-04 1.160E-04 2.603E-03 73 Ra-223 1.757E-23 2.120E-06 2.969E-24 74 Re-187 3.222E-13 1.470E-11 3.776E-19 75 Rh-103m 4.671E-01 1.380E-12 5.139E-08 76 Rh-106 4.584E-01 0.00E+00 0.000E+00 77 Rn-219 2.476E-23 0.00E+00 0.000E+00 78 Ru-103 4.679E-01 2.420E-09 9.027E-05 79 Ru-106 4.584E-01 1.290E-07 4.714E-03 80 Sm-147 3.676E-14 2.020E-05 5.920E-14 81 Sr-89 1.200E+02 1.120E-08 1.071E-01 82 Sr-90 5.306E+01 3.510E-07 1.485E+00 83 Sr-91 1.215E-44 4.490E-10 4.349E-49 84 Sr-92 2.543E-159 2.180E-10 4.419E-164 85 Tc-99 3.960E-04 2.250E-09 7.103E-08 86 Tc-99m 3.023E-05 8.800E-12 2.121E-11 87 Tc-101 0.000E+00 4.840E-12 0.000E+00 88 Te-129 4.509E-01 2.420E-11 8.700E-07 89 Te-129m 7.159E-01 6.470E-09 3.692E-04 90 Te-132 8.518E-04 2.550E-09 1.731E-07 91 Th-227 4.020E-23 4.370E-06 1.400E-23 92 Th-231 4.180E-14 2.370E-10 7.898E-19 93 Tl-207 2.320E-23 0.00E+00 0.000E+00 94 U-235 4.297E-14 3.320E-05 1.137E-13 95 W-187 3.591E-18 1.670E-10 4.781E-23 96 Xe-131m 1.083E-01 0.00E+00 0.000E+00 97 Xe-133 1.057E-02 0.00E+00 0.000E+00 98 Xe-133m 1.551E-08 0.00E+00 0.000E+00 99 Xe-135 4.689E-46 0.00E+00 0.000E+00 100 Xe-135m 3.053E-65 0.00E+00 0.000E+00 101 Y-90 5.307E+01 2.280E-09 9.646E-03 102 Y-90m 0.000E+00 1.270E-10 0.000E+00 103 Y-91 2.261E+01 1.320E-08 2.379E-02 104 Y-91m 7.640E-45 9.820E-12 5.981E-51 105 Y-92 3.468E-121 2.110E-10 5.834E-126 106 Zn-65 3.078E-01 5.510E-09 1.352E-04 107 Zn-69 1.077E-33 1.060E-11 9.099E-40 108 Zn-69m 1.005E-33 2.200E-10 1.762E-38 109 Zr-95 2.160E+00 6.390E-09 1.100E-03 110 Zr-97 9.481E-28 1.170E-09 8.844E-32 111 112 113 114 Dose Total (rem) 2.334E+00 Calc. No. L-003430, Rev. 0, Attachment A, A-14 of A-18

A B C D E F 1 Container Drop Event: LaSalle Isotopic: Table 11.2-5 2 0.00054 X/Q (sec/m^3) 3 0.00035 Breathing Rate (m^3/sec) 4 0.01 Release Fraction 5 3700000000000 Conversion Factor (rem/Ci per Sv/Bq) 6 1 Containers/Accident 7 200 Container Contact - Nominal Baseline Analysis (R/hr) 8 380 Container Contact - Bounding Accident Value (R/hr) 9 10 =F114 Total Inhalation Dose 11 60 day Decay 12 Isotope Ci in container InhaleDCF Dose (rem) 13 =LSFinal!A28 =LSFinal!E28 0.00181 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D13*E13 14 =LSFinal!A29 =LSFinal!E29 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D14*E14 15 =LSFinal!A30 =LSFinal!E30 0.0000000217 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D15*E15 16 =LSFinal!A31 =LSFinal!E31 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D16*E16 17 =LSFinal!A32 =LSFinal!E32 0.0000000000464 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D17*E17 18 =LSFinal!A33 =LSFinal!E33 0.00000000101 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D18*E18 19 =LSFinal!A34 =LSFinal!E34 0.0000000000218 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D19*E19 20 =LSFinal!A35 =LSFinal!E35 0.0000000000111 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D20*E20 21 =LSFinal!A36 =LSFinal!E36 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D21*E21 22 =LSFinal!A37 =LSFinal!E37 0.0000000000241 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D22*E22 23 =LSFinal!A38 =LSFinal!E38 0.0000000000261 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D23*E23 24 =LSFinal!A39 =LSFinal!E39 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D24*E24 25 =LSFinal!A40 =LSFinal!E40 0.00000000242 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D25*E25 26 =LSFinal!A41 =LSFinal!E41 0.000000000916 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D26*E26 27 =LSFinal!A42 =LSFinal!E42 0.000000101 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D27*E27 28 =LSFinal!A43 =LSFinal!E43 0.00000000294 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D28*E28 29 =LSFinal!A44 =LSFinal!E44 0.0000000591 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D29*E29 30 =LSFinal!A45 =LSFinal!E45 0.0000000000903 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D30*E30 31 =LSFinal!A46 =LSFinal!E46 0.0000000125 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D31*E31 32 =LSFinal!A47 =LSFinal!E47 0.00000000123 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D32*E32 33 =LSFinal!A48 =LSFinal!E48 0.00000000198 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D33*E33 34 =LSFinal!A49 =LSFinal!E49 0.00000000863 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D34*E34 35 =LSFinal!A50 =LSFinal!E50 0.0000000000274 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D35*E35 36 =LSFinal!A51 =LSFinal!E51 0.0000000000226 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D36*E36 37 =LSFinal!A52 =LSFinal!E52 0.000000004 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D37*E37 38 =LSFinal!A53 =LSFinal!E53 0.00000000168 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D38*E38 39 =LSFinal!A54 =LSFinal!E54 0.0000000469 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D39*E39 40 =LSFinal!A55 =LSFinal!E55 0.00000000889 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D40*E40 41 =LSFinal!A56 =LSFinal!E56 0.000000000103 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D41*E41 42 =LSFinal!A57 =LSFinal!E57 0.00000000158 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D42*E42 43 =LSFinal!A58 =LSFinal!E58 0.0000000000355 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D43*E43 44 =LSFinal!A59 =LSFinal!E59 0.000000000332 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D44*E44 45 =LSFinal!A60 =LSFinal!E60 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D45*E45 46 =LSFinal!A61 =LSFinal!E61 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D46*E46 47 =LSFinal!A62 =LSFinal!E62 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D47*E47 48 =LSFinal!A63 =LSFinal!E63 0.00000000131 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D48*E48 49 =LSFinal!A64 =LSFinal!E64 0.000000000157 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D49*E49 50 =LSFinal!A65 =LSFinal!E65 0.0000000000684 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D50*E50 51 =LSFinal!A66 =LSFinal!E66 0.00000000181 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D51*E51 52 =LSFinal!A67 =LSFinal!E67 0.000000000102 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D52*E52 53 =LSFinal!A68 =LSFinal!E68 0.00000000107 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D53*E53 54 =LSFinal!A69 =LSFinal!E69 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D54*E54 55 =LSFinal!A70 =LSFinal!E70 0.000000000327 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D55*E55 56 =LSFinal!A71 =LSFinal!E71 0.00000000157 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D56*E56 57 =LSFinal!A72 =LSFinal!E72 0.000000000659 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D57*E57 58 =LSFinal!A73 =LSFinal!E73 0.0000000000224 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D58*E58 59 =LSFinal!A74 =LSFinal!E74 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D59*E59 60 =LSFinal!A75 =LSFinal!E75 0.00000000185 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D60*E60 61 =LSFinal!A76 =LSFinal!E76 0.0000000000932 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D61*E61 62 =LSFinal!A77 =LSFinal!E77 0.000000000678 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D62*E62 63 =LSFinal!A78 =LSFinal!E78 0.00000000419 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D63*E63 64 =LSFinal!A79 =LSFinal!E79 0.000347 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D64*E64 65 =LSFinal!A80 =LSFinal!E80 0.00000000235 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D65*E65 66 =LSFinal!A81 =LSFinal!E81 0.0000000106 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D66*E66 67 =LSFinal!A82 =LSFinal!E82 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D67*E67 68 =LSFinal!A83 =LSFinal!E83 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D68*E68 69 =LSFinal!A84 =LSFinal!E84 0.00000000219 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D69*E69 70 =LSFinal!A85 =LSFinal!E85 0.0000000000117 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D70*E70 71 =LSFinal!A86 =LSFinal!E86 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D71*E71 72 =LSFinal!A87 =LSFinal!E87 0.000116 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D72*E72 73 =LSFinal!A88 =LSFinal!E88 0.00000212 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D73*E73 74 =LSFinal!A89 =LSFinal!E89 0.0000000000147 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D74*E74 75 =LSFinal!A90 =LSFinal!E90 0.00000000000138 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D75*E75 76 =LSFinal!A91 =LSFinal!E91 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D76*E76 77 =LSFinal!A92 =LSFinal!E92 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D77*E77 78 =LSFinal!A93 =LSFinal!E93 0.00000000242 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D78*E78 79 =LSFinal!A94 =LSFinal!E94 0.000000129 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D79*E79 80 =LSFinal!A95 =LSFinal!E95 0.0000202 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D80*E80 81 =LSFinal!A96 =LSFinal!E96 0.0000000112 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D81*E81 82 =LSFinal!A97 =LSFinal!E97 0.000000351 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D82*E82 83 =LSFinal!A98 =LSFinal!E98 0.000000000449 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D83*E83 84 =LSFinal!A99 =LSFinal!E99 0.000000000218 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D84*E84 85 =LSFinal!A100 =LSFinal!E100 0.00000000225 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D85*E85 86 =LSFinal!A101 =LSFinal!E101 0.0000000000088 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D86*E86 87 =LSFinal!A102 =LSFinal!E102 0.00000000000484 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D87*E87 88 =LSFinal!A103 =LSFinal!E103 0.0000000000242 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D88*E88 89 =LSFinal!A104 =LSFinal!E104 0.00000000647 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D89*E89 90 =LSFinal!A105 =LSFinal!E105 0.00000000255 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D90*E90 91 =LSFinal!A106 =LSFinal!E106 0.00000437 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D91*E91 Calc. No. L-003430, Rev. 0, Attachment A, A-15 of A-18

A B C D E F 92 =LSFinal!A107 =LSFinal!E107 0.000000000237 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D92*E92 93 =LSFinal!A108 =LSFinal!E108 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D93*E93 94 =LSFinal!A109 =LSFinal!E109 0.0000332 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D94*E94 95 =LSFinal!A110 =LSFinal!E110 0.000000000167 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D95*E95 96 =LSFinal!A111 =LSFinal!E111 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D96*E96 97 =LSFinal!A112 =LSFinal!E112 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D97*E97 98 =LSFinal!A113 =LSFinal!E113 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D98*E98 99 =LSFinal!A114 =LSFinal!E114 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D99*E99 100 =LSFinal!A115 =LSFinal!E115 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D100*E100 101 =LSFinal!A116 =LSFinal!E116 0.00000000228 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D101*E101 102 =LSFinal!A117 =LSFinal!E117 0.000000000127 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D102*E102 103 =LSFinal!A118 =LSFinal!E118 0.0000000132 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D103*E103 104 =LSFinal!A119 =LSFinal!E119 0.00000000000982 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D104*E104 105 =LSFinal!A120 =LSFinal!E120 0.000000000211 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D105*E105 106 =LSFinal!A121 =LSFinal!E121 0.00000000551 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D106*E106 107 =LSFinal!A122 =LSFinal!E122 0.0000000000106 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D107*E107 108 =LSFinal!A123 =LSFinal!E123 0.00000000022 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D108*E108 109 =LSFinal!A124 =LSFinal!E124 0.00000000639 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D109*E109 110 =LSFinal!A125 =LSFinal!E125 0.00000000117 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D110*E110 111 112 113 114 Dose Total (rem) =SUM(F13:F110)

Calc. No. L-003430, Rev. 0, Attachment A, A-16 of A-18

A B C D E F 1 Container Fire Event: LaSalle Isotopic: Table 11.2-5 2 0.00054 X/Q (sec/m^3) 3 0.00035 Breathing Rate (m^3/sec) 4 0.01 Release Fraction 5 3700000000000 Conversion Factor (rem/Ci per Sv/Bq) 6 6 Containers/Accident 7 200 Container Contact - Nominal Baseline Analysis (R/hr) 8 380 Container Contact - Bounding Accident Value (R/hr) 9 10 =F114 Total Inhalation Dose 11 60 day Decay 12 Isotope Ci in Container Inhaled DCF Dose (rem) 13 =LSFinal!A28 =LSFinal!E28 0.00181 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D13*E13 14 =LSFinal!A29 =LSFinal!E29 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D14*E14 15 =LSFinal!A30 =LSFinal!E30 0.0000000217 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D15*E15 16 =LSFinal!A31 =LSFinal!E31 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D16*E16 17 =LSFinal!A32 =LSFinal!E32 0.0000000000464 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D17*E17 18 =LSFinal!A33 =LSFinal!E33 0.00000000101 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D18*E18 19 =LSFinal!A34 =LSFinal!E34 0.0000000000218 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D19*E19 20 =LSFinal!A35 =LSFinal!E35 0.0000000000111 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D20*E20 21 =LSFinal!A36 =LSFinal!E36 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D21*E21 22 =LSFinal!A37 =LSFinal!E37 0.0000000000241 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D22*E22 23 =LSFinal!A38 =LSFinal!E38 0.0000000000261 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D23*E23 24 =LSFinal!A39 =LSFinal!E39 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D24*E24 25 =LSFinal!A40 =LSFinal!E40 0.00000000242 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D25*E25 26 =LSFinal!A41 =LSFinal!E41 0.000000000916 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D26*E26 27 =LSFinal!A42 =LSFinal!E42 0.000000101 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D27*E27 28 =LSFinal!A43 =LSFinal!E43 0.00000000294 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D28*E28 29 =LSFinal!A44 =LSFinal!E44 0.0000000591 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D29*E29 30 =LSFinal!A45 =LSFinal!E45 0.0000000000903 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D30*E30 31 =LSFinal!A46 =LSFinal!E46 0.0000000125 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D31*E31 32 =LSFinal!A47 =LSFinal!E47 0.00000000123 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D32*E32 33 =LSFinal!A48 =LSFinal!E48 0.00000000198 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D33*E33 34 =LSFinal!A49 =LSFinal!E49 0.00000000863 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D34*E34 35 =LSFinal!A50 =LSFinal!E50 0.0000000000274 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D35*E35 36 =LSFinal!A51 =LSFinal!E51 0.0000000000226 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D36*E36 37 =LSFinal!A52 =LSFinal!E52 0.000000004 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D37*E37 38 =LSFinal!A53 =LSFinal!E53 0.00000000168 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D38*E38 39 =LSFinal!A54 =LSFinal!E54 0.0000000469 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D39*E39 40 =LSFinal!A55 =LSFinal!E55 0.00000000889 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D40*E40 41 =LSFinal!A56 =LSFinal!E56 0.000000000103 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D41*E41 42 =LSFinal!A57 =LSFinal!E57 0.00000000158 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D42*E42 43 =LSFinal!A58 =LSFinal!E58 0.0000000000355 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D43*E43 44 =LSFinal!A59 =LSFinal!E59 0.000000000332 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D44*E44 45 =LSFinal!A60 =LSFinal!E60 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D45*E45 46 =LSFinal!A61 =LSFinal!E61 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D46*E46 47 =LSFinal!A62 =LSFinal!E62 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D47*E47 48 =LSFinal!A63 =LSFinal!E63 0.00000000131 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D48*E48 49 =LSFinal!A64 =LSFinal!E64 0.000000000157 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D49*E49 50 =LSFinal!A65 =LSFinal!E65 0.0000000000684 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D50*E50 51 =LSFinal!A66 =LSFinal!E66 0.00000000181 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D51*E51 52 =LSFinal!A67 =LSFinal!E67 0.000000000102 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D52*E52 53 =LSFinal!A68 =LSFinal!E68 0.00000000107 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D53*E53 54 =LSFinal!A69 =LSFinal!E69 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D54*E54 55 =LSFinal!A70 =LSFinal!E70 0.000000000327 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D55*E55 56 =LSFinal!A71 =LSFinal!E71 0.00000000157 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D56*E56 57 =LSFinal!A72 =LSFinal!E72 0.000000000659 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D57*E57 58 =LSFinal!A73 =LSFinal!E73 0.0000000000224 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D58*E58 59 =LSFinal!A74 =LSFinal!E74 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D59*E59 60 =LSFinal!A75 =LSFinal!E75 0.00000000185 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D60*E60 61 =LSFinal!A76 =LSFinal!E76 0.0000000000932 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D61*E61 62 =LSFinal!A77 =LSFinal!E77 0.000000000678 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D62*E62 63 =LSFinal!A78 =LSFinal!E78 0.00000000419 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D63*E63 64 =LSFinal!A79 =LSFinal!E79 0.000347 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D64*E64 65 =LSFinal!A80 =LSFinal!E80 0.00000000235 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D65*E65 66 =LSFinal!A81 =LSFinal!E81 0.0000000106 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D66*E66 67 =LSFinal!A82 =LSFinal!E82 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D67*E67 68 =LSFinal!A83 =LSFinal!E83 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D68*E68 69 =LSFinal!A84 =LSFinal!E84 0.00000000219 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D69*E69 70 =LSFinal!A85 =LSFinal!E85 0.0000000000117 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D70*E70 71 =LSFinal!A86 =LSFinal!E86 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D71*E71 72 =LSFinal!A87 =LSFinal!E87 0.000116 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D72*E72 73 =LSFinal!A88 =LSFinal!E88 0.00000212 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D73*E73 74 =LSFinal!A89 =LSFinal!E89 0.0000000000147 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D74*E74 75 =LSFinal!A90 =LSFinal!E90 0.00000000000138 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D75*E75 76 =LSFinal!A91 =LSFinal!E91 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D76*E76 77 =LSFinal!A92 =LSFinal!E92 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D77*E77 78 =LSFinal!A93 =LSFinal!E93 0.00000000242 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D78*E78 79 =LSFinal!A94 =LSFinal!E94 0.000000129 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D79*E79 80 =LSFinal!A95 =LSFinal!E95 0.0000202 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D80*E80 81 =LSFinal!A96 =LSFinal!E96 0.0000000112 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D81*E81 82 =LSFinal!A97 =LSFinal!E97 0.000000351 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D82*E82 83 =LSFinal!A98 =LSFinal!E98 0.000000000449 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D83*E83 84 =LSFinal!A99 =LSFinal!E99 0.000000000218 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D84*E84 85 =LSFinal!A100 =LSFinal!E100 0.00000000225 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D85*E85 86 =LSFinal!A101 =LSFinal!E101 0.0000000000088 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D86*E86 87 =LSFinal!A102 =LSFinal!E102 0.00000000000484 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D87*E87 88 =LSFinal!A103 =LSFinal!E103 0.0000000000242 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D88*E88 89 =LSFinal!A104 =LSFinal!E104 0.00000000647 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D89*E89 90 =LSFinal!A105 =LSFinal!E105 0.00000000255 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D90*E90 Calc. No. L-003430, Rev. 0, Attachment A, A-17 of A-18

A B C D E F 91 =LSFinal!A106 =LSFinal!E106 0.00000437 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D91*E91 92 =LSFinal!A107 =LSFinal!E107 0.000000000237 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D92*E92 93 =LSFinal!A108 =LSFinal!E108 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D93*E93 94 =LSFinal!A109 =LSFinal!E109 0.0000332 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D94*E94 95 =LSFinal!A110 =LSFinal!E110 0.000000000167 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D95*E95 96 =LSFinal!A111 =LSFinal!E111 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D96*E96 97 =LSFinal!A112 =LSFinal!E112 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D97*E97 98 =LSFinal!A113 =LSFinal!E113 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D98*E98 99 =LSFinal!A114 =LSFinal!E114 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D99*E99 100 =LSFinal!A115 =LSFinal!E115 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D100*E100 101 =LSFinal!A116 =LSFinal!E116 0.00000000228 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D101*E101 102 =LSFinal!A117 =LSFinal!E117 0.000000000127 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D102*E102 103 =LSFinal!A118 =LSFinal!E118 0.0000000132 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D103*E103 104 =LSFinal!A119 =LSFinal!E119 0.00000000000982 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D104*E104 105 =LSFinal!A120 =LSFinal!E120 0.000000000211 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D105*E105 106 =LSFinal!A121 =LSFinal!E121 0.00000000551 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D106*E106 107 =LSFinal!A122 =LSFinal!E122 0.0000000000106 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D107*E107 108 =LSFinal!A123 =LSFinal!E123 0.00000000022 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D108*E108 109 =LSFinal!A124 =LSFinal!E124 0.00000000639 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D109*E109 110 =LSFinal!A125 =LSFinal!E125 0.00000000117 =$A$2*$A$3*$A$4*$A$5*$A$6*$A$8/$A$7*D110*E110 111 112 113 114 Dose Total (rem) =SUM(F13:F110)

Calc. No. L-003430, Rev. 0, Attachment A, A-18 of A-18

Attachment B: Clinton MicroShield......................................................................................................................... 2 Run #1: Based on UFSAR Table Data from 12.2-12 ..................................................... 2 Run #2: Based on UFSAR Table Data from 12.2-12 with 60 Day Decay ..................... 4 Run #3: Based on UFSAR Table Data from 12.2-12 with 60 Day Decay and Normalized Contact Dose ............................................................................................... 6 Excel Sheets ........................................................................................................................ 8 Drop Accident................................................................................................................. 8 Captures the isotopic mix from Run #3 in column D, and calculates a final dose in column F.

Fire Accdent.................................................................................................................. 11 Captures the isotopic mix from Run #3 in column D, and calculates a final dose in column F.

Drop Accident: Formula Version.................................................................................. 14 Fire Accident: Formula Version ................................................................................... 16 Calc. No. L-003430, Rev. 0, Attachment B, B-1 of B-17

A B C D E F G H I 1 MicroShield 8.01 2 Washington Group International (8.00-0000) 3 Date By Checked 4

5 Filename Run Date Run Time Duration 6 clinton1.msd 11-Aug-09 9:09:42 AM 0:00:07 7 Project Info 8 Case Title Clinton 12.2-12 9 Description before decay and resizing 10 Geometry 7 - Cylinder Volume - Side Shields 11 Source Dimensions 12 Height 182.88 cm (6 ft) 13 Radius 76.2 cm (2 ft 6.0 in) 14 Dose Points 15 A X Y Z 16 #1 78.74 cm (2 ft 7.0 in) 91.44 cm (3 ft) 0.0 cm (0 in) 17 Shields 18 Shield N Dimension Material Density 19 Source 2.04e+05 in³ Water 0.9 20 Transition Air 0.00122 21 Air Gap Air 0.00122 22 Source Input: Grouping Method - Linear Energy 23 Number of Groups: 25 24 Lower Energy Cutoff: 0.015 25 Photons < 0.015: Included 26 Library: Grove 27 Nuclide Ci Bq µCi/cm³ Bq/cm³ 28 Ag-110 3.90E-01 1.44E+10 1.17E-01 4.33E+03 29 Ag-110m 9.40E+01 3.48E+12 2.82E+01 1.04E+06 30 Am-241 6.00E-02 2.22E+09 1.80E-02 6.65E+02 31 Ba-137m 8.50E+01 3.15E+12 2.55E+01 9.43E+05 32 Ba-139 8.70E-10 3.22E+01 2.61E-10 9.65E-06 33 Ba-140 7.20E+02 2.66E+13 2.16E+02 7.99E+06 34 Br-83 1.70E-06 6.29E+04 5.10E-07 1.89E-02 35 Ce-141 2.50E+01 9.25E+11 7.49E+00 2.77E+05 36 Ce-143 5.00E-02 1.85E+09 1.50E-02 5.55E+02 37 Ce-144 1.20E+01 4.44E+11 3.60E+00 1.33E+05 38 Cm-242 2.00E-03 7.40E+07 6.00E-04 2.22E+01 39 Co-57 2.90E+01 1.07E+12 8.69E+00 3.22E+05 40 Co-58 3.50E+03 1.30E+14 1.05E+03 3.88E+07 41 Co-60 3.00E+04 1.11E+15 8.99E+03 3.33E+08 42 Cr-51 1.10E+04 4.07E+14 3.30E+03 1.22E+08 43 Cs-134 5.90E+01 2.18E+12 1.77E+01 6.54E+05 44 Cs-136 8.80E+00 3.26E+11 2.64E+00 9.76E+04 45 Cs-137 9.30E+01 3.44E+12 2.79E+01 1.03E+06 46 F-18 5.00E-09 1.85E+02 1.50E-09 5.55E-05 47 Fe-55 2.00E+04 7.40E+14 6.00E+03 2.22E+08 48 Fe-59 2.80E+02 1.04E+13 8.39E+01 3.11E+06 49 I-131 6.50E+02 2.41E+13 1.95E+02 7.21E+06 50 I-132 5.30E+02 1.96E+13 1.59E+02 5.88E+06 51 I-133 3.30E+01 1.22E+12 9.89E+00 3.66E+05 52 I-135 2.60E-01 9.62E+09 7.79E-02 2.88E+03 53 La-140 8.40E+02 3.11E+13 2.52E+02 9.32E+06 54 La-141 5.40E-04 2.00E+07 1.62E-04 5.99E+00 55 La-142 2.00E-10 7.40E+00 6.00E-11 2.22E-06 56 Mn-54 1.50E+04 5.55E+14 4.50E+03 1.66E+08 57 Mn-56 1.30E-05 4.81E+05 3.90E-06 1.44E-01 58 Mo-99 1.70E+02 6.29E+12 5.10E+01 1.89E+06 59 Na-24 1.90E-01 7.03E+09 5.70E-02 2.11E+03 60 Nb-95 1.40E+01 5.18E+11 4.20E+00 1.55E+05 61 Nb-95m 2.10E-01 7.77E+09 6.30E-02 2.33E+03 62 Nb-97 6.10E-03 2.26E+08 1.83E-03 6.77E+01 63 Nb-97m 5.10E-03 1.89E+08 1.53E-03 5.66E+01 64 Nd-147 9.90E-01 3.66E+10 2.97E-01 1.10E+04 65 Ni-63 3.30E+02 1.22E+13 9.89E+01 3.66E+06 66 Ni-65 6.40E-08 2.37E+03 1.92E-08 7.10E-04 Calc. No. L-003430, Rev. 0, Attachment B, B-2 of B-17

A B C D E F G H I 67 Np-239 1.30E+03 4.81E+13 3.90E+02 1.44E+07 68 P-32 1.80E+00 6.66E+10 5.40E-01 2.00E+04 69 Pm-147 4.80E-02 1.78E+09 1.44E-02 5.32E+02 70 Pr-143 3.80E+00 1.41E+11 1.14E+00 4.21E+04 71 Pr-144 1.20E+01 4.44E+11 3.60E+00 1.33E+05 72 Rh-103m 4.20E+00 1.55E+11 1.26E+00 4.66E+04 73 Rh-106 9.30E-01 3.44E+10 2.79E-01 1.03E+04 74 Ru-103 4.20E+00 1.55E+11 1.26E+00 4.66E+04 75 Ru-106 9.30E-01 3.44E+10 2.79E-01 1.03E+04 76 Sr-89 7.40E+02 2.74E+13 2.22E+02 8.21E+06 77 Sr-90 8.90E+01 3.29E+12 2.67E+01 9.87E+05 78 Sr-91 1.10E+00 4.07E+10 3.30E-01 1.22E+04 79 Sr-92 6.40E-05 2.37E+06 1.92E-05 7.10E-01 80 Tc-99 3.80E-01 1.41E+10 1.14E-01 4.21E+03 81 Tc-99m 1.70E+02 6.29E+12 5.10E+01 1.89E+06 82 Te-129 7.60E+00 2.81E+11 2.28E+00 8.43E+04 83 Te-129m 7.60E+00 2.81E+11 2.28E+00 8.43E+04 84 Te-132 5.20E+02 1.92E+13 1.56E+02 5.77E+06 85 W-187 1.50E+00 5.55E+10 4.50E-01 1.66E+04 86 Y-90 8.70E+01 3.22E+12 2.61E+01 9.65E+05 87 Y-91 1.30E+02 4.81E+12 3.90E+01 1.44E+06 88 Y-91m 7.30E-01 2.70E+10 2.19E-01 8.10E+03 89 Y-92 4.30E-03 1.59E+08 1.29E-03 4.77E+01 90 Zn-65 8.60E+02 3.18E+13 2.58E+02 9.54E+06 91 Zn-69 2.20E-03 8.14E+07 6.59E-04 2.44E+01 92 Zn-69m 2.00E-03 7.40E+07 6.00E-04 2.22E+01 93 Zr-95 1.10E+01 4.07E+11 3.30E+00 1.22E+05 94 Zr-97 5.60E-03 2.07E+08 1.68E-03 6.21E+01 95 Buildup: The material reference is Source 96 Integration Parameters 97 Radial 30 98 Circumferential 30 99 Y Direction (axial) 60 100 Results 101 Fluence Rate Fluence Rate Exposure Rate Exposure Rate 102 Energy (MeV) Activity (Photons/sec) MeV/cm²/sec MeV/cm²/sec mR/hr mR/hr 103 No Buildup With Buildup No Buildup With Buildup 104 0.015 5.93E+14 7.55E+05 8.79E+05 6.46E+04 7.52E+04 105 0.2381 3.72E+13 9.55E+06 4.05E+07 1.75E+04 7.40E+04 106 0.3378 7.10E+13 2.93E+07 1.01E+08 5.63E+04 1.95E+05 107 0.5128 6.93E+13 5.12E+07 1.46E+08 1.00E+05 2.86E+05 108 0.674 4.04E+13 4.40E+07 1.12E+08 8.51E+04 2.17E+05 109 0.8292 7.18E+14 1.06E+09 2.48E+09 2.00E+06 4.70E+06 110 0.9532 8.32E+12 1.50E+07 3.37E+07 2.79E+04 6.26E+04 111 1.172 1.13E+15 2.77E+09 5.82E+09 4.95E+06 1.04E+07 112 1.3324 1.12E+15 3.31E+09 6.66E+09 5.73E+06 1.16E+07 113 1.4307 2.30E+12 7.55E+06 1.49E+07 1.29E+04 2.54E+04 114 1.5982 3.04E+13 1.18E+08 2.26E+08 1.95E+05 3.73E+05 115 1.7576 5.93E+10 2.66E+05 4.95E+05 4.27E+02 7.96E+02 116 1.9599 4.45E+11 2.35E+06 4.25E+06 3.65E+03 6.62E+03 117 2.0867 4.65E+10 2.69E+05 4.81E+05 4.11E+02 7.33E+02 118 2.1914 6.54E+10 4.08E+05 7.18E+05 6.12E+02 1.08E+03 119 2.3534 2.97E+11 2.06E+06 3.57E+06 3.03E+03 5.24E+03 120 2.5224 1.11E+12 8.50E+06 1.45E+07 1.22E+04 2.08E+04 121 2.7541 7.02E+09 6.15E+04 1.02E+05 8.57E+01 1.43E+02 122 2.8086 1.52E-01 1.37E-06 2.26E-06 1.89E-09 3.14E-09 123 2.9598 1.48E+03 1.44E-02 2.35E-02 1.96E-05 3.20E-05 124 3.1706 3.89E-02 4.19E-07 6.75E-07 5.58E-10 8.99E-10 125 3.3696 8.09E+02 9.54E-03 1.51E-02 1.25E-05 1.98E-05 126 3.4328 5.05E-02 6.12E-07 9.68E-07 7.96E-10 1.26E-09 127 3.6237 1.52E-01 1.99E-06 3.10E-06 2.54E-09 3.97E-09 128 3.8236 4.51E+06 6.39E+01 9.85E+01 8.03E-02 1.24E-01 129 Totals 3.82E+15 7.42E+09 1.57E+10 1.33E+07 2.80E+07 Calc. No. L-003430, Rev. 0, Attachment B, B-3 of B-17

A B C D E F G H I 1 MicroShield 8.01 2 Washington Group International (8.00-0000) 3 Date By Checked 4

5 Filename Run Date Run Time Duration 6 clinton1decay.msd 11-Aug-09 9:14:37 AM 0:00:07 7 Project Info 8 Case Title Clinton 12.2-12 9 Description before resizing 10 Geometry 7 - Cylinder Volume - Side Shields 11 Source Dimensions 12 Height 182.88 cm (6 ft) 13 Radius 76.2 cm (2 ft 6.0 in) 14 Dose Points 15 A X Y Z 16 #1 78.74 cm (2 ft 7.0 in) 91.44 cm (3 ft) 0.0 cm (0 in) 17 Shields 18 Shield N Dimension Material Density 19 Source 2.04e+05 in³ Water 0.9 20 Transition Air 0.00122 21 Air Gap Air 0.00122 22 Source Input: Grouping Method - Linear Energy 23 Number of Groups: 25 24 Lower Energy Cutoff: 0.015 25 Photons < 0.015: Included 26 Library: Grove 27 Nuclide Ci Bq µCi/cm³ Bq/cm³ 28 Ac-225 1.86E-21 6.87E-11 5.57E-22 2.06E-17 29 Ac-227 1.32E-22 4.88E-12 3.95E-23 1.46E-18 30 Ag-110 1.06E+00 3.92E+10 3.17E-01 1.17E+04 31 Ag-110m 7.96E+01 2.94E+12 2.39E+01 8.83E+05 32 Am-241 6.00E-02 2.22E+09 1.80E-02 6.65E+02 33 At-217 34 Ba-137m 8.76E+01 3.24E+12 2.63E+01 9.72E+05 35 Ba-139 8.8932e-323 3.2905e-312 2.4703e-323 9.8635e-319 36 Ba-140 2.79E+01 1.03E+12 8.35E+00 3.09E+05 37 Bi-210 2.34E-24 8.66E-14 7.01E-25 2.60E-20 38 Bi-211 2.96E-23 1.09E-12 8.87E-24 3.28E-19 39 Bi-213 40 Bi-214 5.49E-24 2.03E-13 1.65E-24 6.09E-20 41 Br-83 7.19E-188 2.66E-177 2.16E-188 7.97E-184 42 Ce-141 6.95E+00 2.57E+11 2.08E+00 7.71E+04 43 Ce-143 3.66E-15 1.35E-04 1.10E-15 4.06E-11 44 Ce-144 1.04E+01 3.84E+11 3.11E+00 1.15E+05 45 Cm-242 1.55E-03 5.74E+07 4.65E-04 1.72E+01 46 Co-57 2.49E+01 9.20E+11 7.46E+00 2.76E+05 47 Co-58 1.95E+03 7.20E+13 5.83E+02 2.16E+07 48 Co-60 2.94E+04 1.09E+15 8.80E+03 3.26E+08 49 Cr-51 2.45E+03 9.07E+13 7.35E+02 2.72E+07 50 Cs-134 5.58E+01 2.07E+12 1.67E+01 6.19E+05 51 Cs-135 8.52E-11 3.15E+00 2.56E-11 9.45E-07 52 Cs-136 3.73E-01 1.38E+10 1.12E-01 4.14E+03 53 Cs-137 9.27E+01 3.43E+12 2.78E+01 1.03E+06 54 F-18 4.94E-246 1.83E-235 1.48E-246 5.47E-242 55 Fe-55 1.92E+04 7.09E+14 5.75E+03 2.13E+08 56 Fe-59 1.10E+02 4.08E+12 3.31E+01 1.22E+06 57 Fr-221 3.56E-22 1.32E-11 1.07E-22 3.95E-18 58 Fr-223 1.90E-24 7.05E-14 5.71E-25 2.11E-20 59 I-129 3.17E-08 1.17E+03 9.49E-09 3.51E-04 60 I-131 3.68E+00 1.36E+11 1.10E+00 4.09E+04 61 I-132 1.53E-03 5.67E+07 4.60E-04 1.70E+01 62 I-133 4.76E-20 1.76E-09 1.43E-20 5.28E-16 63 I-135 6.84E-67 2.53E-56 2.05E-67 7.59E-63 64 Kr-83m 3.07E-187 1.14E-176 9.20E-188 3.40E-183 65 La-140 3.21E+01 1.19E+12 9.61E+00 3.56E+05 66 La-141 5.14E-114 1.90E-103 1.54E-114 5.71E-110 67 La-142 4.68E-283 1.73E-272 1.40E-283 5.19E-279 68 Mn-54 1.31E+04 4.86E+14 3.94E+03 1.46E+08 69 Mn-56 9.99E-174 3.70E-163 2.99E-174 1.11E-169 70 Mo-99 4.62E-05 1.71E+06 1.38E-05 5.12E-01 71 Na-24 2.40E-30 8.87E-20 7.19E-31 2.66E-26 72 Nb-95 9.55E+00 3.53E+11 2.86E+00 1.06E+05 73 Nb-95m 4.87E-02 1.80E+09 1.46E-02 5.40E+02 74 Nb-97 1.35E-28 5.00E-18 4.05E-29 1.50E-24 75 Nb-97m 1.19E-28 4.40E-18 3.56E-29 1.32E-24 76 Nd-147 2.24E-02 8.30E+08 6.72E-03 2.49E+02 77 Ni-63 3.30E+02 1.22E+13 9.88E+01 3.66E+06 78 Ni-65 6.15E-180 2.28E-169 1.84E-180 6.82E-176 79 Np-237 3.19E-09 1.18E+02 9.57E-10 3.54E-05 80 Np-239 2.78E-05 1.03E+06 8.34E-06 3.09E-01 81 P-32 9.80E-02 3.63E+09 2.94E-02 1.09E+03 82 Pa-231 8.26E-20 3.06E-09 2.48E-20 9.17E-16 83 Pa-233 1.56E-09 5.79E+01 4.69E-10 1.73E-05 84 Pb-209 85 Pb-210 2.29E-24 8.47E-14 6.87E-25 2.54E-20 86 Pb-211 2.45E-23 9.06E-13 7.34E-24 2.72E-19 87 Pb-214 4.60E-24 1.70E-13 1.38E-24 5.10E-20 88 Pm-147 5.67E-02 2.10E+09 1.70E-02 6.29E+02 89 Po-210 1.57E-24 5.79E-14 4.69E-25 1.74E-20 90 Po-211 6.61E-26 2.45E-15 1.98E-26 7.33E-22 91 Po-213 92 Po-214 5.76E-24 2.13E-13 1.73E-24 6.38E-20 Calc. No. L-003430, Rev. 0, Attachment B, B-4 of B-17

A B C D E F G H I 93 Po-215 2.33E-23 8.62E-13 6.98E-24 2.58E-19 94 Po-218 4.55E-24 1.68E-13 1.36E-24 5.05E-20 95 Pr-143 1.77E-01 6.56E+09 5.31E-02 1.97E+03 96 Pr-144 1.04E+01 3.84E+11 3.11E+00 1.15E+05 97 Pr-144m 1.48E-01 5.49E+09 4.44E-02 1.64E+03 98 Pu-238 2.29E-06 8.47E+04 6.86E-07 2.54E-02 99 Pu-239 3.47E-04 1.29E+07 1.04E-04 3.85E+00 100 Ra-223 2.17E-23 8.02E-13 6.50E-24 2.40E-19 101 Ra-225 1.03E-21 3.82E-11 3.09E-22 1.14E-17 102 Ra-226 6.12E-24 2.27E-13 1.84E-24 6.79E-20 103 Re-187 8.68E-14 3.21E-03 2.60E-14 9.62E-10 104 Rh-103m 1.46E+00 5.39E+10 4.37E-01 1.62E+04 105 Rh-106 8.31E-01 3.07E+10 2.49E-01 9.21E+03 106 Rn-219 3.05E-23 1.13E-12 9.16E-24 3.39E-19 107 Rn-222 4.50E-24 1.67E-13 1.35E-24 5.00E-20 108 Ru-103 1.46E+00 5.40E+10 4.38E-01 1.62E+04 109 Ru-106 8.31E-01 3.07E+10 2.49E-01 9.21E+03 110 Sm-147 5.93E-14 2.20E-03 1.78E-14 6.58E-10 111 Sr-89 3.25E+02 1.20E+13 9.74E+01 3.61E+06 112 Sr-90 8.86E+01 3.28E+12 2.66E+01 9.83E+05 113 Sr-91 2.58E-46 9.55E-36 7.73E-47 2.86E-42 114 Sr-92 7.07E-165 2.62E-154 2.12E-165 7.84E-161 115 Tc-99 3.80E-01 1.41E+10 1.14E-01 4.21E+03 116 Tc-99m 4.50E-05 1.67E+06 1.35E-05 4.99E-01 117 Te-129 1.39E+00 5.14E+10 4.16E-01 1.54E+04 118 Te-129m 2.20E+00 8.16E+10 6.61E-01 2.44E+04 119 Te-132 1.49E-03 5.51E+07 4.46E-04 1.65E+01 120 Th-227 4.96E-23 1.84E-12 1.49E-23 5.50E-19 121 Th-229 2.30E-21 8.50E-11 6.88E-22 2.55E-17 122 Th-230 2.80E-19 1.04E-08 8.39E-20 3.10E-15 123 Th-231 5.16E-14 1.91E-03 1.55E-14 5.72E-10 124 Tl-207 2.86E-23 1.06E-12 8.58E-24 3.17E-19 125 Tl-209 4.58E-23 1.70E-12 1.37E-23 5.08E-19 126 U-233 4.15E-16 1.54E-05 1.25E-16 4.61E-12 127 U-234 5.56E-13 2.06E-02 1.67E-13 6.16E-09 128 U-235 5.30E-14 1.96E-03 1.59E-14 5.88E-10 129 W-187 9.67E-19 3.58E-08 2.90E-19 1.07E-14 130 Xe-131m 3.61E-01 1.33E+10 1.08E-01 4.00E+03 131 Xe-133 2.40E-03 8.88E+07 7.20E-04 2.66E+01 132 Xe-133m 3.52E-09 1.30E+02 1.06E-09 3.91E-05 133 Xe-135 1.80E-48 6.67E-38 5.41E-49 2.00E-44 134 Xe-135m 1.17E-67 4.34E-57 3.52E-68 1.30E-63 135 Y-90 8.87E+01 3.28E+12 2.66E+01 9.83E+05 136 Y-91 6.39E+01 2.36E+12 1.91E+01 7.08E+05 137 Y-91m 1.62E-46 6.00E-36 4.86E-47 1.80E-42 138 Y-92 1.59E-125 5.88E-115 4.76E-126 1.76E-121 139 Zn-65 7.25E+02 2.68E+13 2.17E+02 8.05E+06 140 Zn-69 6.73E-35 2.49E-24 2.02E-35 7.46E-31 141 Zn-69m 6.28E-35 2.32E-24 1.88E-35 6.96E-31 142 Zr-95 5.74E+00 2.13E+11 1.72E+00 6.37E+04 143 Zr-97 1.25E-28 4.64E-18 3.76E-29 1.39E-24 144 Buildup: The material reference is Source 145 Integration Parameters 146 Radial 30 147 Circumferential 30 148 Y Direction (axial) 60 149 Results 150 Fluence Rate Fluence Rate Exposure Rate Exposure Rate 151 Energy (MeV) Activity (Photons/sec) MeV/cm²/sec MeV/cm²/sec mR/hr mR/hr 152 No Buildup With Buildup No Buildup With Buildup 153 0.0062 3.77E+14 1.97E+05 2.29E+05 9.77E+04 1.14E+05 154 0.2101 2.70E+11 5.87E+04 2.69E+05 1.05E+02 4.80E+02 155 0.3234 9.49E+12 3.69E+06 1.30E+07 7.05E+03 2.49E+04 156 0.5192 2.57E+13 1.93E+07 5.46E+07 3.78E+04 1.07E+05 157 0.6809 8.44E+12 9.33E+06 2.37E+07 1.80E+04 4.57E+04 158 0.8318 5.63E+14 8.31E+08 1.95E+09 1.57E+06 3.70E+06 159 0.9398 1.13E+12 2.00E+06 4.51E+06 3.72E+03 8.40E+03 160 1.1723 1.10E+15 2.70E+09 5.66E+09 4.82E+06 1.01E+07 161 1.3325 1.09E+15 3.22E+09 6.50E+09 5.59E+06 1.13E+07 162 1.4981 5.04E+11 1.78E+06 3.46E+06 2.99E+03 5.82E+03 163 1.6152 1.55E+12 6.13E+06 1.17E+07 1.01E+04 1.93E+04 164 1.7575 1.68E+05 7.52E-01 1.40E+00 1.21E-03 2.26E-03 165 1.9599 1.29E+06 6.79E+00 1.23E+01 1.06E-02 1.92E-02 166 2.0868 1.34E+05 7.78E-01 1.39E+00 1.19E-03 2.12E-03 167 2.1857 2.97E+09 1.84E+04 3.25E+04 2.77E+01 4.88E+01 168 2.3488 1.01E+10 6.97E+04 1.21E+05 1.02E+02 1.77E+02 169 2.5224 4.23E+10 3.25E+05 5.52E+05 4.66E+02 7.92E+02 170 2.7541 8.86E-20 7.76E-25 1.29E-24 1.08E-27 1.80E-27 171 2.8086 3.54E-274 3.19E-279 5.29E-279 4.43E-282 7.33E-282 172 2.9598 1.13E-165 1.10E-170 1.81E-170 1.50E-173 2.46E-173 173 3.1706 9.09E-275 9.80E-280 1.58E-279 1.31E-282 2.10E-282 174 3.3696 6.21E-166 7.32E-171 1.16E-170 9.58E-174 1.52E-173 175 3.4328 1.18E-274 1.43E-279 2.26E-279 1.86E-282 2.94E-282 176 3.6237 3.54E-274 4.65E-279 7.26E-279 5.94E-282 9.27E-282 177 3.8236 5.69E-23 8.07E-28 1.24E-27 1.01E-30 1.56E-30 178 Totals 3.18E+15 6.79E+09 1.42E+10 1.22E+07 2.54E+07 Calc. No. L-003430, Rev. 0, Attachment B, B-5 of B-17

A B C D E F G H I 1 MicroShield 8.01 2 Washington Group International (8.00-0000) 3 Date By Checked 4

5 Filename Run Date Run Time Duration 6 Clintondecay2..msd 3-Aug-09 1:47:47 PM 0:00:08 7 Project Info 8 Case Title Clinton 12.2-12 9 Description Final 10 Geometry 7 - Cylinder Volume - Side Shields 11 Source Dimensions 12 Height 182.88 cm (6 ft) 13 Radius 76.2 cm (2 ft 6.0 in) 14 Dose Points 15 A X Y Z 16 #1 78.74 cm (2 ft 7.0 in) 91.44 cm (3 ft) 0.0 cm (0 in) 17 Shields 18 Shield N Dimension Material Density 19 Source 2.04e+05 in³ Water 0.9 20 Transition Air 0.00122 21 Air Gap Air 0.00122 22 Source Input: Grouping Method - Linear Energy 23 Number of Groups: 25 24 Lower Energy Cutoff: 0.015 25 Photons < 0.015: Included 26 Library: Grove 27 Nuclide Ci Bq µCi/cm³ Bq/cm³ 28 Ac-225 1.46E-23 5.41E-13 4.38E-24 1.62E-19 29 Ac-227 1.04E-24 3.84E-14 3.11E-25 1.15E-20 30 Ag-110 8.33E-03 3.08E+08 2.50E-03 9.24E+01 31 Ag-110m 6.26E-01 2.32E+10 1.88E-01 6.95E+03 32 Am-241 4.72E-04 1.75E+07 1.41E-04 5.24E+00 33 At-217 34 Ba-137m 6.90E-01 2.55E+10 2.07E-01 7.65E+03 35 Ba-139 36 Ba-140 2.19E-01 8.11E+09 6.57E-02 2.43E+03 37 Bi-210 1.84E-26 6.81E-16 5.52E-27 2.04E-22 38 Bi-211 2.33E-25 8.61E-15 6.98E-26 2.58E-21 39 Bi-213 40 Bi-214 4.32E-26 1.60E-15 1.29E-26 4.79E-22 41 Br-83 5.66E-190 2.09E-179 1.70E-190 6.28E-186 42 Ce-141 5.47E-02 2.02E+09 1.64E-02 6.07E+02 43 Ce-143 2.88E-17 1.06E-06 8.63E-18 3.19E-13 44 Ce-144 8.16E-02 3.02E+09 2.45E-02 9.05E+02 45 Cm-242 1.22E-05 4.51E+05 3.66E-06 1.35E-01 46 Co-57 1.96E-01 7.24E+09 5.87E-02 2.17E+03 47 Co-58 1.53E+01 5.66E+11 4.59E+00 1.70E+05 48 Co-60 2.31E+02 8.55E+12 6.93E+01 2.56E+06 49 Cr-51 1.93E+01 7.14E+11 5.78E+00 2.14E+05 50 Cs-134 4.39E-01 1.63E+10 1.32E-01 4.87E+03 51 Cs-135 6.71E-13 2.48E-02 2.01E-13 7.44E-09 52 Cs-136 2.94E-03 1.09E+08 8.80E-04 3.26E+01 53 Cs-137 7.29E-01 2.70E+10 2.19E-01 8.09E+03 54 F-18 3.88E-248 1.44E-237 1.16E-248 4.31E-244 55 Fe-55 1.51E+02 5.58E+12 4.52E+01 1.67E+06 56 Fe-59 8.68E-01 3.21E+10 2.60E-01 9.62E+03 57 Fr-221 2.80E-24 1.04E-13 8.40E-25 3.11E-20 58 Fr-223 1.50E-26 5.54E-16 4.49E-27 1.66E-22 59 I-129 2.49E-10 9.22E+00 7.47E-11 2.76E-06 60 I-131 2.90E-02 1.07E+09 8.69E-03 3.22E+02 61 I-132 1.21E-05 4.47E+05 3.62E-06 1.34E-01 62 I-133 3.75E-22 1.39E-11 1.12E-22 4.16E-18 63 I-135 5.38E-69 1.99E-58 1.61E-69 5.97E-65 64 Kr-83m 2.41E-189 8.93E-179 7.24E-190 2.68E-185 65 La-140 2.52E-01 9.34E+09 7.56E-02 2.80E+03 66 La-141 4.05E-116 1.50E-105 1.21E-116 4.49E-112 67 La-142 3.68E-285 1.36E-274 1.10E-285 4.08E-281 68 Mn-54 1.03E+02 3.82E+12 3.10E+01 1.15E+06 69 Mn-56 7.86E-176 2.91E-165 2.36E-176 8.72E-172 70 Mo-99 3.63E-07 1.34E+04 1.09E-07 4.03E-03 71 Na-24 1.89E-32 6.98E-22 5.66E-33 2.09E-28 72 Nb-95 7.52E-02 2.78E+09 2.25E-02 8.34E+02 73 Nb-95m 3.83E-04 1.42E+07 1.15E-04 4.25E+00 74 Nb-97 1.06E-30 3.93E-20 3.19E-31 1.18E-26 75 Nb-97m 9.35E-31 3.46E-20 2.80E-31 1.04E-26 76 Nd-147 1.76E-04 6.53E+06 5.29E-05 1.96E+00 77 Ni-63 2.59E+00 9.60E+10 7.78E-01 2.88E+04 78 Ni-65 4.84E-182 1.79E-171 1.45E-182 5.37E-178 79 Np-237 2.51E-11 9.29E-01 7.53E-12 2.79E-07 80 Np-239 2.19E-07 8.10E+03 6.56E-08 2.43E-03 81 P-32 7.71E-04 2.85E+07 2.31E-04 8.55E+00 82 Pa-231 6.50E-22 2.41E-11 1.95E-22 7.21E-18 83 Pa-233 1.23E-11 4.55E-01 3.69E-12 1.36E-07 84 Pb-209 85 Pb-210 1.80E-26 6.67E-16 5.40E-27 2.00E-22 86 Pb-211 1.93E-25 7.13E-15 5.77E-26 2.14E-21 87 Pb-214 3.62E-26 1.34E-15 1.09E-26 4.01E-22 88 Pm-147 4.46E-04 1.65E+07 1.34E-04 4.95E+00 89 Po-210 1.23E-26 4.56E-16 3.69E-27 1.37E-22 90 Po-211 5.20E-28 1.93E-17 1.56E-28 5.77E-24 91 Po-213 92 Po-214 4.53E-26 1.68E-15 1.36E-26 5.02E-22 Calc. No. L-003430, Rev. 0, Attachment B, B-6 of B-17

A B C D E F G H I 93 Po-215 1.83E-25 6.78E-15 5.49E-26 2.03E-21 94 Po-218 3.58E-26 1.33E-15 1.07E-26 3.97E-22 95 Pr-143 1.39E-03 5.16E+07 4.18E-04 1.55E+01 96 Pr-144 8.16E-02 3.02E+09 2.45E-02 9.05E+02 97 Pr-144m 1.17E-03 4.32E+07 3.50E-04 1.29E+01 98 Pu-238 1.80E-08 6.67E+02 5.40E-09 2.00E-04 99 Pu-239 2.73E-06 1.01E+05 8.19E-07 3.03E-02 100 Ra-223 1.71E-25 6.31E-15 5.11E-26 1.89E-21 101 Ra-225 8.12E-24 3.00E-13 2.43E-24 9.00E-20 102 Ra-226 4.82E-26 1.78E-15 1.44E-26 5.34E-22 103 Re-187 6.83E-16 2.53E-05 2.05E-16 7.57E-12 104 Rh-103m 1.15E-02 4.24E+08 3.44E-03 1.27E+02 105 Rh-106 6.54E-03 2.42E+08 1.96E-03 7.25E+01 106 Rn-219 2.40E-25 8.89E-15 7.20E-26 2.67E-21 107 Rn-222 3.54E-26 1.31E-15 1.06E-26 3.93E-22 108 Ru-103 1.15E-02 4.25E+08 3.44E-03 1.27E+02 109 Ru-106 6.54E-03 2.42E+08 1.96E-03 7.25E+01 110 Sm-147 4.67E-16 1.73E-05 1.40E-16 5.18E-12 111 Sr-89 2.56E+00 9.46E+10 7.67E-01 2.84E+04 112 Sr-90 6.98E-01 2.58E+10 2.09E-01 7.74E+03 113 Sr-91 2.03E-48 7.51E-38 6.09E-49 2.25E-44 114 Sr-92 5.56E-167 2.06E-156 1.67E-167 6.17E-163 115 Tc-99 2.99E-03 1.11E+08 8.96E-04 3.32E+01 116 Tc-99m 3.54E-07 1.31E+04 1.06E-07 3.93E-03 117 Te-129 1.09E-02 4.04E+08 3.28E-03 1.21E+02 118 Te-129m 1.73E-02 6.42E+08 5.20E-03 1.92E+02 119 Te-132 1.17E-05 4.33E+05 3.51E-06 1.30E-01 120 Th-227 3.90E-25 1.44E-14 1.17E-25 4.33E-21 121 Th-229 1.81E-23 6.68E-13 5.42E-24 2.00E-19 122 Th-230 2.20E-21 8.14E-11 6.60E-22 2.44E-17 123 Th-231 4.06E-16 1.50E-05 1.22E-16 4.50E-12 124 Tl-207 2.25E-25 8.33E-15 6.75E-26 2.50E-21 125 Tl-209 3.61E-25 1.33E-14 1.08E-25 4.00E-21 126 U-233 3.27E-18 1.21E-07 9.80E-19 3.63E-14 127 U-234 4.37E-15 1.62E-04 1.31E-15 4.85E-11 128 U-235 4.17E-16 1.54E-05 1.25E-16 4.63E-12 129 W-187 7.61E-21 2.82E-10 2.28E-21 8.44E-17 130 Xe-131m 2.84E-03 1.05E+08 8.51E-04 3.15E+01 131 Xe-133 1.89E-05 6.99E+05 5.66E-06 2.10E-01 132 Xe-133m 2.77E-11 1.03E+00 8.31E-12 3.07E-07 133 Xe-135 1.42E-50 5.25E-40 4.25E-51 1.57E-46 134 Xe-135m 9.24E-70 3.42E-59 2.77E-70 1.02E-65 135 Y-90 6.98E-01 2.58E+10 2.09E-01 7.74E+03 136 Y-91 5.03E-01 1.86E+10 1.51E-01 5.57E+03 137 Y-91m 1.28E-48 4.72E-38 3.83E-49 1.42E-44 138 Y-92 1.25E-127 4.63E-117 3.75E-128 1.39E-123 139 Zn-65 5.71E+00 2.11E+11 1.71E+00 6.33E+04 140 Zn-69 5.30E-37 1.96E-26 1.59E-37 5.87E-33 141 Zn-69m 4.94E-37 1.83E-26 1.48E-37 5.48E-33 142 Zr-95 4.52E-02 1.67E+09 1.36E-02 5.01E+02 143 Zr-97 9.87E-31 3.65E-20 2.96E-31 1.09E-26 144 Buildup: The material reference is Source 145 Integration Parameters 146 Radial 30 147 Circumferential 30 148 Y Direction (axial) 60 149 Results 150 Fluence Rate Fluence Rate Exposure Rate Exposure Rate 151 Energy (MeV) Activity (Photons/sec) MeV/cm²/sec MeV/cm²/sec mR/hr mR/hr 152 No Buildup With Buildup No Buildup With Buildup 153 0.0062 2.96E+12 1.55E+03 1.80E+03 7.69E+02 8.95E+02 154 0.2101 2.13E+09 4.62E+02 2.12E+03 8.24E-01 3.77E+00 155 0.3234 7.47E+10 2.90E+04 1.03E+05 5.55E+01 1.96E+02 156 0.5192 2.02E+11 1.52E+05 4.30E+05 2.98E+02 8.43E+02 157 0.6809 6.64E+10 7.34E+04 1.86E+05 1.42E+02 3.60E+02 158 0.8318 4.43E+12 6.54E+06 1.54E+07 1.24E+04 2.91E+04 159 0.9398 8.92E+09 1.57E+04 3.55E+04 2.93E+01 6.61E+01 160 1.1723 8.67E+12 2.12E+07 4.45E+07 3.79E+04 7.96E+04 161 1.3325 8.57E+12 2.54E+07 5.11E+07 4.40E+04 8.87E+04 162 1.4981 3.96E+09 1.40E+04 2.72E+04 2.35E+01 4.58E+01 163 1.6152 1.22E+10 4.82E+04 9.20E+04 7.95E+01 1.52E+02 164 1.7575 1.32E+03 5.92E-03 1.10E-02 9.52E-06 1.78E-05 165 1.9599 1.01E+04 5.34E-02 9.68E-02 8.31E-05 1.51E-04 166 2.0868 1.06E+03 6.12E-03 1.09E-02 9.34E-06 1.67E-05 167 2.1857 2.34E+07 1.45E+02 2.56E+02 2.18E-01 3.84E-01 168 2.3488 7.94E+07 5.49E+02 9.50E+02 8.06E-01 1.40E+00 169 2.5224 3.32E+08 2.55E+03 4.34E+03 3.67E+00 6.23E+00 170 2.7541 6.97E-22 6.10E-27 1.02E-26 8.51E-30 1.42E-29 171 2.8086 2.79E-276 2.51E-281 4.17E-281 3.48E-284 5.77E-284 172 2.9598 8.91E-168 8.68E-173 1.42E-172 1.18E-175 1.94E-175 173 3.1706 7.15E-277 7.71E-282 1.24E-281 1.03E-284 1.66E-284 174 3.3696 4.89E-168 5.76E-173 9.15E-173 7.54E-176 1.20E-175 175 3.4328 9.30E-277 1.13E-281 1.78E-281 1.47E-284 2.32E-284 176 3.6237 2.79E-276 3.66E-281 5.71E-281 4.68E-284 7.30E-284 177 3.8236 4.48E-25 6.35E-30 9.78E-30 7.97E-33 1.23E-32 178 Totals 2.50E+13 5.35E+07 1.12E+08 9.57E+04 2.00E+05 Calc. No. L-003430, Rev. 0, Attachment B, B-7 of B-17

A B C D E F 1 Container Drop Event: Clinton Isotopic: Table 12.2-12 2 5.400E-04 X/Q (sec/m^3) 3 3.500E-04 Breathing Rate (m^3/sec) 4 1.000E-02 Release Fraction 5 3.70E+12 Conversion Factor (rem/Ci per Sv/Bq) 6 1.00E+00 Containers/Accident 7 2.00E+02 Container Contact - Nominal Baseline Analysis (R/hr) 8 9 1.008E-01 Total Inhalation Dose 10 11 60 day decay 12 Isotope Ci in container InhaleDCF Dose (rem) 13 Ac-225 1.462E-23 2.920E-06 2.985E-25 14 Ac-227 1.037E-24 1.810E-03 1.313E-23 15 Ag-110 8.329E-03 0.00E+00 0.000E+00 16 Ag-110m 6.263E-01 2.170E-08 9.503E-05 17 Am-241 4.720E-04 1.200E-04 3.961E-04 18 At-217 0.000E+00 0.00E+00 0.000E+00 19 Ba-137m 6.897E-01 0.00E+00 0.000E+00 20 Ba-139 0.000E+00 4.640E-11 0.000E+00 21 Ba-140 2.193E-01 1.010E-09 1.549E-06 22 Bi-210 1.841E-26 5.290E-08 6.812E-30 23 Bi-211 2.328E-25 0.00E+00 0.000E+00 24 Bi-213 0.000E+00 4.630E-09 0.000E+00 25 Bi-214 4.319E-26 1.780E-09 5.376E-31 26 Br-83 5.658E-190 2.410E-11 9.535E-197 27 Ce-141 5.472E-02 2.420E-09 9.259E-07 28 Ce-143 2.878E-17 9.160E-10 1.843E-22 29 Ce-144 8.158E-02 1.010E-07 5.762E-05 30 Cm-242 1.220E-05 4.670E-06 3.983E-07 31 Co-57 1.957E-01 2.450E-09 3.353E-06 32 Co-58 1.531E+01 2.940E-09 3.147E-04 33 Co-60 2.310E+02 5.910E-08 9.548E-02 34 Cr-51 1.929E+01 9.030E-11 1.218E-05 35 Cs-134 4.393E-01 1.250E-08 3.840E-05 36 Cs-135 6.707E-13 1.230E-09 5.769E-18 37 Cs-136 2.937E-03 1.980E-09 4.067E-08 38 Cs-137 7.291E-01 8.630E-09 4.400E-05 39 F-18 3.884E-248 2.260E-11 6.139E-255 40 Fe-55 1.509E+02 7.260E-10 7.660E-04 41 Fe-59 8.677E-01 4.000E-09 2.427E-05 42 Fr-221 2.804E-24 0.00E+00 0.000E+00 43 Fr-223 1.498E-26 1.680E-09 1.760E-31 44 I-129 2.492E-10 4.690E-08 8.173E-14 45 I-131 2.900E-02 8.890E-09 1.803E-06 46 I-132 1.207E-05 1.030E-10 8.692E-12 47 I-133 3.749E-22 1.580E-09 4.142E-27 48 I-135 5.382E-69 3.320E-10 1.250E-74 49 Kr-83m 2.414E-189 0.00E+00 0.000E+00 50 La-140 2.523E-01 1.310E-09 2.311E-06 51 La-141 4.048E-116 1.570E-10 4.444E-122 52 La-142 3.681E-285 6.840E-11 1.761E-291 53 Mn-54 1.033E+02 1.810E-09 1.308E-03 54 Mn-56 7.859E-176 1.020E-10 5.606E-182 55 Mo-99 3.634E-07 1.070E-09 2.719E-12 56 Na-24 1.887E-32 3.270E-10 4.315E-38 57 Nb-95 7.517E-02 1.570E-09 8.253E-07 58 Nb-95m 3.832E-04 6.590E-10 1.766E-09 59 Nb-97 1.063E-30 2.240E-11 1.666E-37 60 Nb-97m 9.354E-31 0.00E+00 0.000E+00 61 Nd-147 1.764E-04 1.850E-09 2.282E-09 62 Ni-63 2.594E+00 1.700E-09 3.084E-05 63 Ni-65 4.841E-182 9.320E-11 3.155E-188 64 Np-237 2.512E-11 1.460E-04 2.564E-11 65 Np-239 2.189E-07 6.780E-10 1.038E-12 Calc. No. L-003430, Rev. 0, Attachment B, B-8 of B-17

A B C D E F 66 P-32 7.713E-04 4.190E-09 2.260E-08 67 Pa-231 6.503E-22 3.470E-04 1.578E-21 68 Pa-233 1.231E-11 2.580E-09 2.220E-16 69 Pb-209 0.000E+00 2.560E-11 0.000E+00 70 Pb-210 1.802E-26 3.670E-06 4.625E-28 71 Pb-211 1.927E-25 2.350E-09 3.166E-30 72 Pb-214 3.620E-26 2.110E-09 5.341E-31 73 Pm-147 4.461E-04 1.060E-08 3.307E-08 74 Po-210 1.232E-26 2.540E-06 2.188E-28 75 Po-211 5.203E-28 0.00E+00 0.000E+00 76 Po-213 0.000E+00 0.00E+00 0.000E+00 77 Po-214 4.529E-26 0.00E+00 0.000E+00 78 Po-215 1.833E-25 0.00E+00 0.000E+00 79 Po-218 3.582E-26 0.00E+00 0.000E+00 80 Pr-143 1.394E-03 2.190E-09 2.135E-08 81 Pr-144 8.158E-02 1.170E-11 6.675E-09 82 Pr-144m 1.167E-03 0.00E+00 0.000E+00 83 Pu-238 1.802E-08 1.060E-04 1.335E-08 84 Pu-239 2.733E-06 1.160E-04 2.217E-06 85 Ra-223 1.706E-25 2.120E-06 2.529E-27 86 Ra-225 8.116E-24 2.100E-06 1.192E-25 87 Ra-226 4.818E-26 2.320E-06 7.816E-28 88 Re-187 6.827E-16 1.470E-11 7.018E-23 89 Rh-103m 1.147E-02 1.380E-12 1.107E-10 90 Rh-106 6.536E-03 0.00E+00 0.000E+00 91 Rn-219 2.403E-25 0.00E+00 0.000E+00 92 Rn-222 3.544E-26 0.00E+00 0.000E+00 93 Ru-103 1.149E-02 2.420E-09 1.944E-07 94 Ru-106 6.536E-03 1.290E-07 5.896E-06 95 Sm-147 4.669E-16 2.020E-05 6.596E-17 96 Sr-89 2.558E+00 1.120E-08 2.003E-04 97 Sr-90 6.976E-01 3.510E-07 1.712E-03 98 Sr-91 2.030E-48 4.490E-10 6.374E-54 99 Sr-92 5.562E-167 2.180E-10 8.478E-173 100 Tc-99 2.990E-03 2.250E-09 4.705E-08 101 Tc-99m 3.543E-07 8.800E-12 2.180E-14 102 Te-129 1.093E-02 2.420E-11 1.849E-09 103 Te-129m 1.735E-02 6.470E-09 7.848E-07 104 Te-132 1.171E-05 2.550E-09 2.089E-10 105 Th-227 3.903E-25 4.370E-06 1.193E-26 106 Th-229 1.807E-23 5.800E-04 7.328E-23 107 Th-230 2.201E-21 8.800E-05 1.355E-21 108 Th-231 4.059E-16 2.370E-10 6.726E-22 109 Tl-207 2.252E-25 0.00E+00 0.000E+00 110 Tl-209 3.606E-25 0.00E+00 0.000E+00 111 U-233 3.269E-18 3.660E-05 8.366E-19 112 U-234 4.374E-15 3.580E-05 1.095E-15 113 U-235 4.172E-16 3.320E-05 9.685E-17 114 W-187 7.609E-21 1.670E-10 8.886E-27 115 Xe-131m 2.838E-03 0.00E+00 0.000E+00 116 Xe-133 1.889E-05 0.00E+00 0.000E+00 117 Xe-133m 2.771E-11 0.00E+00 0.000E+00 118 Xe-135 1.419E-50 0.00E+00 0.000E+00 119 Xe-135m 9.239E-70 0.00E+00 0.000E+00 120 Y-90 6.977E-01 2.280E-09 1.112E-05 121 Y-91 5.026E-01 1.320E-08 4.639E-05 122 Y-91m 1.277E-48 9.820E-12 8.766E-56 123 Y-92 1.251E-127 2.110E-10 1.845E-133 124 Zn-65 5.708E+00 5.510E-09 2.199E-04 125 Zn-69 5.296E-37 1.060E-11 3.926E-44 126 Zn-69m 4.941E-37 2.200E-10 7.601E-43 127 Zr-95 4.520E-02 6.390E-09 2.020E-06 128 Zr-97 9.868E-31 1.170E-09 8.073E-36 129 130 Calc. No. L-003430, Rev. 0, Attachment B, B-9 of B-17

A B C D E F 131 Total Rem 1.008E-01 Calc. No. L-003430, Rev. 0, Attachment B, B-10 of B-17

A B C D E F 1 Container Fire Event: Clinton Isotopic: Table 12.2-12 2 5.400E-04 X/Q (sec/m^3) 3 3.500E-04 Breathing Rate (m^3/sec) 4 1.000E-02 Release Fraction 5 3.70E+12 Conversion Factor (rem/Ci per Sv/Bq) 6 6.00E+00 Containers/Accident 7 2.00E+02 Container Contact - Nominal Baseline Analysis (R/hr) 8 9 6.047E-01 Total Inhalation Dose 10 11 60 day decay 12 Isotope Ci in container InhaleDCF Dose (rem) 13 Ac-225 1.462E-23 2.920E-06 1.791E-24 14 Ac-227 1.037E-24 1.810E-03 7.877E-23 15 Ag-110 8.329E-03 0.00E+00 0.000E+00 16 Ag-110m 6.263E-01 2.170E-08 5.702E-04 17 Am-241 4.720E-04 1.200E-04 2.377E-03 18 At-217 0.000E+00 0.00E+00 0.000E+00 19 Ba-137m 6.897E-01 0.00E+00 0.000E+00 20 Ba-139 0.000E+00 4.640E-11 0.000E+00 21 Ba-140 2.193E-01 1.010E-09 9.292E-06 22 Bi-210 1.841E-26 5.290E-08 4.087E-29 23 Bi-211 2.328E-25 0.00E+00 0.000E+00 24 Bi-213 0.000E+00 4.630E-09 0.000E+00 25 Bi-214 4.319E-26 1.780E-09 3.226E-30 26 Br-83 5.658E-190 2.410E-11 5.721E-196 27 Ce-141 5.472E-02 2.420E-09 5.556E-06 28 Ce-143 2.878E-17 9.160E-10 1.106E-21 29 Ce-144 8.158E-02 1.010E-07 3.457E-04 30 Cm-242 1.220E-05 4.670E-06 2.390E-06 31 Co-57 1.957E-01 2.450E-09 2.012E-05 32 Co-58 1.531E+01 2.940E-09 1.888E-03 33 Co-60 2.310E+02 5.910E-08 5.729E-01 34 Cr-51 1.929E+01 9.030E-11 7.309E-05 35 Cs-134 4.393E-01 1.250E-08 2.304E-04 36 Cs-135 6.707E-13 1.230E-09 3.462E-17 37 Cs-136 2.937E-03 1.980E-09 2.440E-07 38 Cs-137 7.291E-01 8.630E-09 2.640E-04 39 F-18 3.884E-248 2.260E-11 3.683E-254 40 Fe-55 1.509E+02 7.260E-10 4.596E-03 41 Fe-59 8.677E-01 4.000E-09 1.456E-04 42 Fr-221 2.804E-24 0.00E+00 0.000E+00 43 Fr-223 1.498E-26 1.680E-09 1.056E-30 44 I-129 2.492E-10 4.690E-08 4.904E-13 45 I-131 2.900E-02 8.890E-09 1.082E-05 46 I-132 1.207E-05 1.030E-10 5.215E-11 47 I-133 3.749E-22 1.580E-09 2.485E-26 48 I-135 5.382E-69 3.320E-10 7.498E-74 49 Kr-83m 2.414E-189 0.00E+00 0.000E+00 50 La-140 2.523E-01 1.310E-09 1.387E-05 51 La-141 4.048E-116 1.570E-10 2.666E-121 52 La-142 3.681E-285 6.840E-11 1.057E-290 53 Mn-54 1.033E+02 1.810E-09 7.847E-03 54 Mn-56 7.859E-176 1.020E-10 3.363E-181 55 Mo-99 3.634E-07 1.070E-09 1.632E-11 56 Na-24 1.887E-32 3.270E-10 2.589E-37 57 Nb-95 7.517E-02 1.570E-09 4.952E-06 58 Nb-95m 3.832E-04 6.590E-10 1.060E-08 59 Nb-97 1.063E-30 2.240E-11 9.994E-37 60 Nb-97m 9.354E-31 0.00E+00 0.000E+00 61 Nd-147 1.764E-04 1.850E-09 1.369E-08 62 Ni-63 2.594E+00 1.700E-09 1.850E-04 63 Ni-65 4.841E-182 9.320E-11 1.893E-187 64 Np-237 2.512E-11 1.460E-04 1.539E-10 65 Np-239 2.189E-07 6.780E-10 6.228E-12 Calc. No. L-003430, Rev. 0, Attachment B, B-11 of B-17

A B C D E F 66 P-32 7.713E-04 4.190E-09 1.356E-07 67 Pa-231 6.503E-22 3.470E-04 9.468E-21 68 Pa-233 1.231E-11 2.580E-09 1.332E-15 69 Pb-209 0.000E+00 2.560E-11 0.000E+00 70 Pb-210 1.802E-26 3.670E-06 2.775E-27 71 Pb-211 1.927E-25 2.350E-09 1.900E-29 72 Pb-214 3.620E-26 2.110E-09 3.205E-30 73 Pm-147 4.461E-04 1.060E-08 1.984E-07 74 Po-210 1.232E-26 2.540E-06 1.313E-27 75 Po-211 5.203E-28 0.00E+00 0.000E+00 76 Po-213 0.000E+00 0.00E+00 0.000E+00 77 Po-214 4.529E-26 0.00E+00 0.000E+00 78 Po-215 1.833E-25 0.00E+00 0.000E+00 79 Po-218 3.582E-26 0.00E+00 0.000E+00 80 Pr-143 1.394E-03 2.190E-09 1.281E-07 81 Pr-144 8.158E-02 1.170E-11 4.005E-08 82 Pr-144m 1.167E-03 0.00E+00 0.000E+00 83 Pu-238 1.802E-08 1.060E-04 8.012E-08 84 Pu-239 2.733E-06 1.160E-04 1.330E-05 85 Ra-223 1.706E-25 2.120E-06 1.517E-26 86 Ra-225 8.116E-24 2.100E-06 7.151E-25 87 Ra-226 4.818E-26 2.320E-06 4.690E-27 88 Re-187 6.827E-16 1.470E-11 4.211E-22 89 Rh-103m 1.147E-02 1.380E-12 6.640E-10 90 Rh-106 6.536E-03 0.00E+00 0.000E+00 91 Rn-219 2.403E-25 0.00E+00 0.000E+00 92 Rn-222 3.544E-26 0.00E+00 0.000E+00 93 Ru-103 1.149E-02 2.420E-09 1.166E-06 94 Ru-106 6.536E-03 1.290E-07 3.538E-05 95 Sm-147 4.669E-16 2.020E-05 3.958E-16 96 Sr-89 2.558E+00 1.120E-08 1.202E-03 97 Sr-90 6.976E-01 3.510E-07 1.027E-02 98 Sr-91 2.030E-48 4.490E-10 3.824E-53 99 Sr-92 5.562E-167 2.180E-10 5.087E-172 100 Tc-99 2.990E-03 2.250E-09 2.823E-07 101 Tc-99m 3.543E-07 8.800E-12 1.308E-13 102 Te-129 1.093E-02 2.420E-11 1.109E-08 103 Te-129m 1.735E-02 6.470E-09 4.709E-06 104 Te-132 1.171E-05 2.550E-09 1.253E-09 105 Th-227 3.903E-25 4.370E-06 7.156E-26 106 Th-229 1.807E-23 5.800E-04 4.397E-22 107 Th-230 2.201E-21 8.800E-05 8.127E-21 108 Th-231 4.059E-16 2.370E-10 4.036E-21 109 Tl-207 2.252E-25 0.00E+00 0.000E+00 110 Tl-209 3.606E-25 0.00E+00 0.000E+00 111 U-233 3.269E-18 3.660E-05 5.020E-18 112 U-234 4.374E-15 3.580E-05 6.570E-15 113 U-235 4.172E-16 3.320E-05 5.811E-16 114 W-187 7.609E-21 1.670E-10 5.332E-26 115 Xe-131m 2.838E-03 0.00E+00 0.000E+00 116 Xe-133 1.889E-05 0.00E+00 0.000E+00 117 Xe-133m 2.771E-11 0.00E+00 0.000E+00 118 Xe-135 1.419E-50 0.00E+00 0.000E+00 119 Xe-135m 9.239E-70 0.00E+00 0.000E+00 120 Y-90 6.977E-01 2.280E-09 6.675E-05 121 Y-91 5.026E-01 1.320E-08 2.783E-04 122 Y-91m 1.277E-48 9.820E-12 5.260E-55 123 Y-92 1.251E-127 2.110E-10 1.107E-132 124 Zn-65 5.708E+00 5.510E-09 1.320E-03 125 Zn-69 5.296E-37 1.060E-11 2.355E-43 126 Zn-69m 4.941E-37 2.200E-10 4.561E-42 127 Zr-95 4.520E-02 6.390E-09 1.212E-05 128 Zr-97 9.868E-31 1.170E-09 4.844E-35 129 130 Calc. No. L-003430, Rev. 0, Attachment B, B-12 of B-17

A B C D E F 131 Total Rem 6.047E-01 Calc. No. L-003430, Rev. 0, Attachment B, B-13 of B-17

A B C D E F 1 Container Drop Event: Clinton Isotopic: Table 12.2-12 2 0.00054 X/Q (sec/m^3) 3 0.00035 Breathing Rate (m^3/sec) 4 0.01 Release Fraction 5 3700000000000 Conversion Factor (rem/Ci per Sv/Bq) 6 1 Containers/Accident 7 200 Container Contact - Nominal Baseline Analysis (R/hr) 8 9 =F131 Total Inhalation Dose 10 11 60 day decay 12 Isotope Ci in container InhaleDCF Dose (rem) 13 =CPS!A28 =CPS!E28 0.00000292 =$A$2*$A$3*$A$4*$A$5*$A$6*D13*E13 14 =CPS!A29 =CPS!E29 0.00181 =$A$2*$A$3*$A$4*$A$5*$A$6*D14*E14 15 =CPS!A30 =CPS!E30 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D15*E15 16 =CPS!A31 =CPS!E31 0.0000000217 =$A$2*$A$3*$A$4*$A$5*$A$6*D16*E16 17 =CPS!A32 =CPS!E32 0.00012 =$A$2*$A$3*$A$4*$A$5*$A$6*D17*E17 18 =CPS!A33 =CPS!E33 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D18*E18 19 =CPS!A34 =CPS!E34 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D19*E19 20 =CPS!A35 =CPS!E35 0.0000000000464 =$A$2*$A$3*$A$4*$A$5*$A$6*D20*E20 21 =CPS!A36 =CPS!E36 0.00000000101 =$A$2*$A$3*$A$4*$A$5*$A$6*D21*E21 22 =CPS!A37 =CPS!E37 0.0000000529 =$A$2*$A$3*$A$4*$A$5*$A$6*D22*E22 23 =CPS!A38 =CPS!E38 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D23*E23 24 =CPS!A39 =CPS!E39 0.00000000463 =$A$2*$A$3*$A$4*$A$5*$A$6*D24*E24 25 =CPS!A40 =CPS!E40 0.00000000178 =$A$2*$A$3*$A$4*$A$5*$A$6*D25*E25 26 =CPS!A41 =CPS!E41 0.0000000000241 =$A$2*$A$3*$A$4*$A$5*$A$6*D26*E26 27 =CPS!A42 =CPS!E42 0.00000000242 =$A$2*$A$3*$A$4*$A$5*$A$6*D27*E27 28 =CPS!A43 =CPS!E43 0.000000000916 =$A$2*$A$3*$A$4*$A$5*$A$6*D28*E28 29 =CPS!A44 =CPS!E44 0.000000101 =$A$2*$A$3*$A$4*$A$5*$A$6*D29*E29 30 =CPS!A45 =CPS!E45 0.00000467 =$A$2*$A$3*$A$4*$A$5*$A$6*D30*E30 31 =CPS!A46 =CPS!E46 0.00000000245 =$A$2*$A$3*$A$4*$A$5*$A$6*D31*E31 32 =CPS!A47 =CPS!E47 0.00000000294 =$A$2*$A$3*$A$4*$A$5*$A$6*D32*E32 33 =CPS!A48 =CPS!E48 0.0000000591 =$A$2*$A$3*$A$4*$A$5*$A$6*D33*E33 34 =CPS!A49 =CPS!E49 0.0000000000903 =$A$2*$A$3*$A$4*$A$5*$A$6*D34*E34 35 =CPS!A50 =CPS!E50 0.0000000125 =$A$2*$A$3*$A$4*$A$5*$A$6*D35*E35 36 =CPS!A51 =CPS!E51 0.00000000123 =$A$2*$A$3*$A$4*$A$5*$A$6*D36*E36 37 =CPS!A52 =CPS!E52 0.00000000198 =$A$2*$A$3*$A$4*$A$5*$A$6*D37*E37 38 =CPS!A53 =CPS!E53 0.00000000863 =$A$2*$A$3*$A$4*$A$5*$A$6*D38*E38 39 =CPS!A54 =CPS!E54 0.0000000000226 =$A$2*$A$3*$A$4*$A$5*$A$6*D39*E39 40 =CPS!A55 =CPS!E55 0.000000000726 =$A$2*$A$3*$A$4*$A$5*$A$6*D40*E40 41 =CPS!A56 =CPS!E56 0.000000004 =$A$2*$A$3*$A$4*$A$5*$A$6*D41*E41 42 =CPS!A57 =CPS!E57 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D42*E42 43 =CPS!A58 =CPS!E58 0.00000000168 =$A$2*$A$3*$A$4*$A$5*$A$6*D43*E43 44 =CPS!A59 =CPS!E59 0.0000000469 =$A$2*$A$3*$A$4*$A$5*$A$6*D44*E44 45 =CPS!A60 =CPS!E60 0.00000000889 =$A$2*$A$3*$A$4*$A$5*$A$6*D45*E45 46 =CPS!A61 =CPS!E61 0.000000000103 =$A$2*$A$3*$A$4*$A$5*$A$6*D46*E46 47 =CPS!A62 =CPS!E62 0.00000000158 =$A$2*$A$3*$A$4*$A$5*$A$6*D47*E47 48 =CPS!A63 =CPS!E63 0.000000000332 =$A$2*$A$3*$A$4*$A$5*$A$6*D48*E48 49 =CPS!A64 =CPS!E64 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D49*E49 50 =CPS!A65 =CPS!E65 0.00000000131 =$A$2*$A$3*$A$4*$A$5*$A$6*D50*E50 51 =CPS!A66 =CPS!E66 0.000000000157 =$A$2*$A$3*$A$4*$A$5*$A$6*D51*E51 52 =CPS!A67 =CPS!E67 0.0000000000684 =$A$2*$A$3*$A$4*$A$5*$A$6*D52*E52 53 =CPS!A68 =CPS!E68 0.00000000181 =$A$2*$A$3*$A$4*$A$5*$A$6*D53*E53 54 =CPS!A69 =CPS!E69 0.000000000102 =$A$2*$A$3*$A$4*$A$5*$A$6*D54*E54 55 =CPS!A70 =CPS!E70 0.00000000107 =$A$2*$A$3*$A$4*$A$5*$A$6*D55*E55 56 =CPS!A71 =CPS!E71 0.000000000327 =$A$2*$A$3*$A$4*$A$5*$A$6*D56*E56 57 =CPS!A72 =CPS!E72 0.00000000157 =$A$2*$A$3*$A$4*$A$5*$A$6*D57*E57 58 =CPS!A73 =CPS!E73 0.000000000659 =$A$2*$A$3*$A$4*$A$5*$A$6*D58*E58 59 =CPS!A74 =CPS!E74 0.0000000000224 =$A$2*$A$3*$A$4*$A$5*$A$6*D59*E59 60 =CPS!A75 =CPS!E75 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D60*E60 61 =CPS!A76 =CPS!E76 0.00000000185 =$A$2*$A$3*$A$4*$A$5*$A$6*D61*E61 62 =CPS!A77 =CPS!E77 0.0000000017 =$A$2*$A$3*$A$4*$A$5*$A$6*D62*E62 63 =CPS!A78 =CPS!E78 0.0000000000932 =$A$2*$A$3*$A$4*$A$5*$A$6*D63*E63 64 =CPS!A79 =CPS!E79 0.000146 =$A$2*$A$3*$A$4*$A$5*$A$6*D64*E64 65 =CPS!A80 =CPS!E80 0.000000000678 =$A$2*$A$3*$A$4*$A$5*$A$6*D65*E65 66 =CPS!A81 =CPS!E81 0.00000000419 =$A$2*$A$3*$A$4*$A$5*$A$6*D66*E66 67 =CPS!A82 =CPS!E82 0.000347 =$A$2*$A$3*$A$4*$A$5*$A$6*D67*E67 68 =CPS!A83 =CPS!E83 0.00000000258 =$A$2*$A$3*$A$4*$A$5*$A$6*D68*E68 69 =CPS!A84 =CPS!E84 0.0000000000256 =$A$2*$A$3*$A$4*$A$5*$A$6*D69*E69 70 =CPS!A85 =CPS!E85 0.00000367 =$A$2*$A$3*$A$4*$A$5*$A$6*D70*E70 71 =CPS!A86 =CPS!E86 0.00000000235 =$A$2*$A$3*$A$4*$A$5*$A$6*D71*E71 72 =CPS!A87 =CPS!E87 0.00000000211 =$A$2*$A$3*$A$4*$A$5*$A$6*D72*E72 73 =CPS!A88 =CPS!E88 0.0000000106 =$A$2*$A$3*$A$4*$A$5*$A$6*D73*E73 74 =CPS!A89 =CPS!E89 0.00000254 =$A$2*$A$3*$A$4*$A$5*$A$6*D74*E74 75 =CPS!A90 =CPS!E90 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D75*E75 76 =CPS!A91 =CPS!E91 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D76*E76 77 =CPS!A92 =CPS!E92 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D77*E77 78 =CPS!A93 =CPS!E93 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D78*E78 79 =CPS!A94 =CPS!E94 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D79*E79 80 =CPS!A95 =CPS!E95 0.00000000219 =$A$2*$A$3*$A$4*$A$5*$A$6*D80*E80 81 =CPS!A96 =CPS!E96 0.0000000000117 =$A$2*$A$3*$A$4*$A$5*$A$6*D81*E81 82 =CPS!A97 =CPS!E97 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D82*E82 83 =CPS!A98 =CPS!E98 0.000106 =$A$2*$A$3*$A$4*$A$5*$A$6*D83*E83 84 =CPS!A99 =CPS!E99 0.000116 =$A$2*$A$3*$A$4*$A$5*$A$6*D84*E84 85 =CPS!A100 =CPS!E100 0.00000212 =$A$2*$A$3*$A$4*$A$5*$A$6*D85*E85 Calc. No. L-003430, Rev. 0, Attachment B, B-14 of B-17

A B C D E F 86 =CPS!A101 =CPS!E101 0.0000021 =$A$2*$A$3*$A$4*$A$5*$A$6*D86*E86 87 =CPS!A102 =CPS!E102 0.00000232 =$A$2*$A$3*$A$4*$A$5*$A$6*D87*E87 88 =CPS!A103 =CPS!E103 0.0000000000147 =$A$2*$A$3*$A$4*$A$5*$A$6*D88*E88 89 =CPS!A104 =CPS!E104 0.00000000000138 =$A$2*$A$3*$A$4*$A$5*$A$6*D89*E89 90 =CPS!A105 =CPS!E105 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D90*E90 91 =CPS!A106 =CPS!E106 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D91*E91 92 =CPS!A107 =CPS!E107 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D92*E92 93 =CPS!A108 =CPS!E108 0.00000000242 =$A$2*$A$3*$A$4*$A$5*$A$6*D93*E93 94 =CPS!A109 =CPS!E109 0.000000129 =$A$2*$A$3*$A$4*$A$5*$A$6*D94*E94 95 =CPS!A110 =CPS!E110 0.0000202 =$A$2*$A$3*$A$4*$A$5*$A$6*D95*E95 96 =CPS!A111 =CPS!E111 0.0000000112 =$A$2*$A$3*$A$4*$A$5*$A$6*D96*E96 97 =CPS!A112 =CPS!E112 0.000000351 =$A$2*$A$3*$A$4*$A$5*$A$6*D97*E97 98 =CPS!A113 =CPS!E113 0.000000000449 =$A$2*$A$3*$A$4*$A$5*$A$6*D98*E98 99 =CPS!A114 =CPS!E114 0.000000000218 =$A$2*$A$3*$A$4*$A$5*$A$6*D99*E99 100 =CPS!A115 =CPS!E115 0.00000000225 =$A$2*$A$3*$A$4*$A$5*$A$6*D100*E100 101 =CPS!A116 =CPS!E116 0.0000000000088 =$A$2*$A$3*$A$4*$A$5*$A$6*D101*E101 102 =CPS!A117 =CPS!E117 0.0000000000242 =$A$2*$A$3*$A$4*$A$5*$A$6*D102*E102 103 =CPS!A118 =CPS!E118 0.00000000647 =$A$2*$A$3*$A$4*$A$5*$A$6*D103*E103 104 =CPS!A119 =CPS!E119 0.00000000255 =$A$2*$A$3*$A$4*$A$5*$A$6*D104*E104 105 =CPS!A120 =CPS!E120 0.00000437 =$A$2*$A$3*$A$4*$A$5*$A$6*D105*E105 106 =CPS!A121 =CPS!E121 0.00058 =$A$2*$A$3*$A$4*$A$5*$A$6*D106*E106 107 =CPS!A122 =CPS!E122 0.000088 =$A$2*$A$3*$A$4*$A$5*$A$6*D107*E107 108 =CPS!A123 =CPS!E123 0.000000000237 =$A$2*$A$3*$A$4*$A$5*$A$6*D108*E108 109 =CPS!A124 =CPS!E124 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D109*E109 110 =CPS!A125 =CPS!E125 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D110*E110 111 =CPS!A126 =CPS!E126 0.0000366 =$A$2*$A$3*$A$4*$A$5*$A$6*D111*E111 112 =CPS!A127 =CPS!E127 0.0000358 =$A$2*$A$3*$A$4*$A$5*$A$6*D112*E112 113 =CPS!A128 =CPS!E128 0.0000332 =$A$2*$A$3*$A$4*$A$5*$A$6*D113*E113 114 =CPS!A129 =CPS!E129 0.000000000167 =$A$2*$A$3*$A$4*$A$5*$A$6*D114*E114 115 =CPS!A130 =CPS!E130 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D115*E115 116 =CPS!A131 =CPS!E131 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D116*E116 117 =CPS!A132 =CPS!E132 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D117*E117 118 =CPS!A133 =CPS!E133 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D118*E118 119 =CPS!A134 =CPS!E134 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D119*E119 120 =CPS!A135 =CPS!E135 0.00000000228 =$A$2*$A$3*$A$4*$A$5*$A$6*D120*E120 121 =CPS!A136 =CPS!E136 0.0000000132 =$A$2*$A$3*$A$4*$A$5*$A$6*D121*E121 122 =CPS!A137 =CPS!E137 0.00000000000982 =$A$2*$A$3*$A$4*$A$5*$A$6*D122*E122 123 =CPS!A138 =CPS!E138 0.000000000211 =$A$2*$A$3*$A$4*$A$5*$A$6*D123*E123 124 =CPS!A139 =CPS!E139 0.00000000551 =$A$2*$A$3*$A$4*$A$5*$A$6*D124*E124 125 =CPS!A140 =CPS!E140 0.0000000000106 =$A$2*$A$3*$A$4*$A$5*$A$6*D125*E125 126 =CPS!A141 =CPS!E141 0.00000000022 =$A$2*$A$3*$A$4*$A$5*$A$6*D126*E126 127 =CPS!A142 =CPS!E142 0.00000000639 =$A$2*$A$3*$A$4*$A$5*$A$6*D127*E127 128 =CPS!A143 =CPS!E143 0.00000000117 =$A$2*$A$3*$A$4*$A$5*$A$6*D128*E128 129 130 131 Total Rem =SUM(F13:F128)

Calc. No. L-003430, Rev. 0, Attachment B, B-15 of B-17

A B C D E F 1 Container Fire Event: Clinton Isotopic: Table 12.2-12 2 0.00054 X/Q (sec/m^3) 3 0.00035 Breathing Rate (m^3/sec) 4 0.01 Release Fraction 5 3700000000000 Conversion Factor (rem/Ci per Sv/Bq) 6 6 Containers/Accident 7 200 Container Contact - Nominal Baseline Analysis (R/hr) 8 9 =F131 Total Inhalation Dose 10 11 60 day decay 12 Isotope Ci in container InhaleDCF Dose (rem) 13 =CPS!A28 =CPS!E28 0.00000292 =$A$2*$A$3*$A$4*$A$5*$A$6*D13*E13 14 =CPS!A29 =CPS!E29 0.00181 =$A$2*$A$3*$A$4*$A$5*$A$6*D14*E14 15 =CPS!A30 =CPS!E30 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D15*E15 16 =CPS!A31 =CPS!E31 0.0000000217 =$A$2*$A$3*$A$4*$A$5*$A$6*D16*E16 17 =CPS!A32 =CPS!E32 0.00012 =$A$2*$A$3*$A$4*$A$5*$A$6*D17*E17 18 =CPS!A33 =CPS!E33 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D18*E18 19 =CPS!A34 =CPS!E34 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D19*E19 20 =CPS!A35 =CPS!E35 0.0000000000464 =$A$2*$A$3*$A$4*$A$5*$A$6*D20*E20 21 =CPS!A36 =CPS!E36 0.00000000101 =$A$2*$A$3*$A$4*$A$5*$A$6*D21*E21 22 =CPS!A37 =CPS!E37 0.0000000529 =$A$2*$A$3*$A$4*$A$5*$A$6*D22*E22 23 =CPS!A38 =CPS!E38 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D23*E23 24 =CPS!A39 =CPS!E39 0.00000000463 =$A$2*$A$3*$A$4*$A$5*$A$6*D24*E24 25 =CPS!A40 =CPS!E40 0.00000000178 =$A$2*$A$3*$A$4*$A$5*$A$6*D25*E25 26 =CPS!A41 =CPS!E41 0.0000000000241 =$A$2*$A$3*$A$4*$A$5*$A$6*D26*E26 27 =CPS!A42 =CPS!E42 0.00000000242 =$A$2*$A$3*$A$4*$A$5*$A$6*D27*E27 28 =CPS!A43 =CPS!E43 0.000000000916 =$A$2*$A$3*$A$4*$A$5*$A$6*D28*E28 29 =CPS!A44 =CPS!E44 0.000000101 =$A$2*$A$3*$A$4*$A$5*$A$6*D29*E29 30 =CPS!A45 =CPS!E45 0.00000467 =$A$2*$A$3*$A$4*$A$5*$A$6*D30*E30 31 =CPS!A46 =CPS!E46 0.00000000245 =$A$2*$A$3*$A$4*$A$5*$A$6*D31*E31 32 =CPS!A47 =CPS!E47 0.00000000294 =$A$2*$A$3*$A$4*$A$5*$A$6*D32*E32 33 =CPS!A48 =CPS!E48 0.0000000591 =$A$2*$A$3*$A$4*$A$5*$A$6*D33*E33 34 =CPS!A49 =CPS!E49 0.0000000000903 =$A$2*$A$3*$A$4*$A$5*$A$6*D34*E34 35 =CPS!A50 =CPS!E50 0.0000000125 =$A$2*$A$3*$A$4*$A$5*$A$6*D35*E35 36 =CPS!A51 =CPS!E51 0.00000000123 =$A$2*$A$3*$A$4*$A$5*$A$6*D36*E36 37 =CPS!A52 =CPS!E52 0.00000000198 =$A$2*$A$3*$A$4*$A$5*$A$6*D37*E37 38 =CPS!A53 =CPS!E53 0.00000000863 =$A$2*$A$3*$A$4*$A$5*$A$6*D38*E38 39 =CPS!A54 =CPS!E54 0.0000000000226 =$A$2*$A$3*$A$4*$A$5*$A$6*D39*E39 40 =CPS!A55 =CPS!E55 0.000000000726 =$A$2*$A$3*$A$4*$A$5*$A$6*D40*E40 41 =CPS!A56 =CPS!E56 0.000000004 =$A$2*$A$3*$A$4*$A$5*$A$6*D41*E41 42 =CPS!A57 =CPS!E57 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D42*E42 43 =CPS!A58 =CPS!E58 0.00000000168 =$A$2*$A$3*$A$4*$A$5*$A$6*D43*E43 44 =CPS!A59 =CPS!E59 0.0000000469 =$A$2*$A$3*$A$4*$A$5*$A$6*D44*E44 45 =CPS!A60 =CPS!E60 0.00000000889 =$A$2*$A$3*$A$4*$A$5*$A$6*D45*E45 46 =CPS!A61 =CPS!E61 0.000000000103 =$A$2*$A$3*$A$4*$A$5*$A$6*D46*E46 47 =CPS!A62 =CPS!E62 0.00000000158 =$A$2*$A$3*$A$4*$A$5*$A$6*D47*E47 48 =CPS!A63 =CPS!E63 0.000000000332 =$A$2*$A$3*$A$4*$A$5*$A$6*D48*E48 49 =CPS!A64 =CPS!E64 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D49*E49 50 =CPS!A65 =CPS!E65 0.00000000131 =$A$2*$A$3*$A$4*$A$5*$A$6*D50*E50 51 =CPS!A66 =CPS!E66 0.000000000157 =$A$2*$A$3*$A$4*$A$5*$A$6*D51*E51 52 =CPS!A67 =CPS!E67 0.0000000000684 =$A$2*$A$3*$A$4*$A$5*$A$6*D52*E52 53 =CPS!A68 =CPS!E68 0.00000000181 =$A$2*$A$3*$A$4*$A$5*$A$6*D53*E53 54 =CPS!A69 =CPS!E69 0.000000000102 =$A$2*$A$3*$A$4*$A$5*$A$6*D54*E54 55 =CPS!A70 =CPS!E70 0.00000000107 =$A$2*$A$3*$A$4*$A$5*$A$6*D55*E55 56 =CPS!A71 =CPS!E71 0.000000000327 =$A$2*$A$3*$A$4*$A$5*$A$6*D56*E56 57 =CPS!A72 =CPS!E72 0.00000000157 =$A$2*$A$3*$A$4*$A$5*$A$6*D57*E57 58 =CPS!A73 =CPS!E73 0.000000000659 =$A$2*$A$3*$A$4*$A$5*$A$6*D58*E58 59 =CPS!A74 =CPS!E74 0.0000000000224 =$A$2*$A$3*$A$4*$A$5*$A$6*D59*E59 60 =CPS!A75 =CPS!E75 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D60*E60 61 =CPS!A76 =CPS!E76 0.00000000185 =$A$2*$A$3*$A$4*$A$5*$A$6*D61*E61 62 =CPS!A77 =CPS!E77 0.0000000017 =$A$2*$A$3*$A$4*$A$5*$A$6*D62*E62 63 =CPS!A78 =CPS!E78 0.0000000000932 =$A$2*$A$3*$A$4*$A$5*$A$6*D63*E63 64 =CPS!A79 =CPS!E79 0.000146 =$A$2*$A$3*$A$4*$A$5*$A$6*D64*E64 65 =CPS!A80 =CPS!E80 0.000000000678 =$A$2*$A$3*$A$4*$A$5*$A$6*D65*E65 66 =CPS!A81 =CPS!E81 0.00000000419 =$A$2*$A$3*$A$4*$A$5*$A$6*D66*E66 67 =CPS!A82 =CPS!E82 0.000347 =$A$2*$A$3*$A$4*$A$5*$A$6*D67*E67 68 =CPS!A83 =CPS!E83 0.00000000258 =$A$2*$A$3*$A$4*$A$5*$A$6*D68*E68 69 =CPS!A84 =CPS!E84 0.0000000000256 =$A$2*$A$3*$A$4*$A$5*$A$6*D69*E69 70 =CPS!A85 =CPS!E85 0.00000367 =$A$2*$A$3*$A$4*$A$5*$A$6*D70*E70 71 =CPS!A86 =CPS!E86 0.00000000235 =$A$2*$A$3*$A$4*$A$5*$A$6*D71*E71 72 =CPS!A87 =CPS!E87 0.00000000211 =$A$2*$A$3*$A$4*$A$5*$A$6*D72*E72 73 =CPS!A88 =CPS!E88 0.0000000106 =$A$2*$A$3*$A$4*$A$5*$A$6*D73*E73 74 =CPS!A89 =CPS!E89 0.00000254 =$A$2*$A$3*$A$4*$A$5*$A$6*D74*E74 75 =CPS!A90 =CPS!E90 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D75*E75 76 =CPS!A91 =CPS!E91 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D76*E76 77 =CPS!A92 =CPS!E92 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D77*E77 78 =CPS!A93 =CPS!E93 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D78*E78 79 =CPS!A94 =CPS!E94 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D79*E79 80 =CPS!A95 =CPS!E95 0.00000000219 =$A$2*$A$3*$A$4*$A$5*$A$6*D80*E80 81 =CPS!A96 =CPS!E96 0.0000000000117 =$A$2*$A$3*$A$4*$A$5*$A$6*D81*E81 82 =CPS!A97 =CPS!E97 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D82*E82 83 =CPS!A98 =CPS!E98 0.000106 =$A$2*$A$3*$A$4*$A$5*$A$6*D83*E83 84 =CPS!A99 =CPS!E99 0.000116 =$A$2*$A$3*$A$4*$A$5*$A$6*D84*E84 85 =CPS!A100 =CPS!E100 0.00000212 =$A$2*$A$3*$A$4*$A$5*$A$6*D85*E85 Calc. No. L-003430, Rev. 0, Attachment B, B-16 of B-17

A B C D E F 86 =CPS!A101 =CPS!E101 0.0000021 =$A$2*$A$3*$A$4*$A$5*$A$6*D86*E86 87 =CPS!A102 =CPS!E102 0.00000232 =$A$2*$A$3*$A$4*$A$5*$A$6*D87*E87 88 =CPS!A103 =CPS!E103 0.0000000000147 =$A$2*$A$3*$A$4*$A$5*$A$6*D88*E88 89 =CPS!A104 =CPS!E104 0.00000000000138 =$A$2*$A$3*$A$4*$A$5*$A$6*D89*E89 90 =CPS!A105 =CPS!E105 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D90*E90 91 =CPS!A106 =CPS!E106 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D91*E91 92 =CPS!A107 =CPS!E107 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D92*E92 93 =CPS!A108 =CPS!E108 0.00000000242 =$A$2*$A$3*$A$4*$A$5*$A$6*D93*E93 94 =CPS!A109 =CPS!E109 0.000000129 =$A$2*$A$3*$A$4*$A$5*$A$6*D94*E94 95 =CPS!A110 =CPS!E110 0.0000202 =$A$2*$A$3*$A$4*$A$5*$A$6*D95*E95 96 =CPS!A111 =CPS!E111 0.0000000112 =$A$2*$A$3*$A$4*$A$5*$A$6*D96*E96 97 =CPS!A112 =CPS!E112 0.000000351 =$A$2*$A$3*$A$4*$A$5*$A$6*D97*E97 98 =CPS!A113 =CPS!E113 0.000000000449 =$A$2*$A$3*$A$4*$A$5*$A$6*D98*E98 99 =CPS!A114 =CPS!E114 0.000000000218 =$A$2*$A$3*$A$4*$A$5*$A$6*D99*E99 100 =CPS!A115 =CPS!E115 0.00000000225 =$A$2*$A$3*$A$4*$A$5*$A$6*D100*E100 101 =CPS!A116 =CPS!E116 0.0000000000088 =$A$2*$A$3*$A$4*$A$5*$A$6*D101*E101 102 =CPS!A117 =CPS!E117 0.0000000000242 =$A$2*$A$3*$A$4*$A$5*$A$6*D102*E102 103 =CPS!A118 =CPS!E118 0.00000000647 =$A$2*$A$3*$A$4*$A$5*$A$6*D103*E103 104 =CPS!A119 =CPS!E119 0.00000000255 =$A$2*$A$3*$A$4*$A$5*$A$6*D104*E104 105 =CPS!A120 =CPS!E120 0.00000437 =$A$2*$A$3*$A$4*$A$5*$A$6*D105*E105 106 =CPS!A121 =CPS!E121 0.00058 =$A$2*$A$3*$A$4*$A$5*$A$6*D106*E106 107 =CPS!A122 =CPS!E122 0.000088 =$A$2*$A$3*$A$4*$A$5*$A$6*D107*E107 108 =CPS!A123 =CPS!E123 0.000000000237 =$A$2*$A$3*$A$4*$A$5*$A$6*D108*E108 109 =CPS!A124 =CPS!E124 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D109*E109 110 =CPS!A125 =CPS!E125 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D110*E110 111 =CPS!A126 =CPS!E126 0.0000366 =$A$2*$A$3*$A$4*$A$5*$A$6*D111*E111 112 =CPS!A127 =CPS!E127 0.0000358 =$A$2*$A$3*$A$4*$A$5*$A$6*D112*E112 113 =CPS!A128 =CPS!E128 0.0000332 =$A$2*$A$3*$A$4*$A$5*$A$6*D113*E113 114 =CPS!A129 =CPS!E129 0.000000000167 =$A$2*$A$3*$A$4*$A$5*$A$6*D114*E114 115 =CPS!A130 =CPS!E130 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D115*E115 116 =CPS!A131 =CPS!E131 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D116*E116 117 =CPS!A132 =CPS!E132 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D117*E117 118 =CPS!A133 =CPS!E133 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D118*E118 119 =CPS!A134 =CPS!E134 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D119*E119 120 =CPS!A135 =CPS!E135 0.00000000228 =$A$2*$A$3*$A$4*$A$5*$A$6*D120*E120 121 =CPS!A136 =CPS!E136 0.0000000132 =$A$2*$A$3*$A$4*$A$5*$A$6*D121*E121 122 =CPS!A137 =CPS!E137 0.00000000000982 =$A$2*$A$3*$A$4*$A$5*$A$6*D122*E122 123 =CPS!A138 =CPS!E138 0.000000000211 =$A$2*$A$3*$A$4*$A$5*$A$6*D123*E123 124 =CPS!A139 =CPS!E139 0.00000000551 =$A$2*$A$3*$A$4*$A$5*$A$6*D124*E124 125 =CPS!A140 =CPS!E140 0.0000000000106 =$A$2*$A$3*$A$4*$A$5*$A$6*D125*E125 126 =CPS!A141 =CPS!E141 0.00000000022 =$A$2*$A$3*$A$4*$A$5*$A$6*D126*E126 127 =CPS!A142 =CPS!E142 0.00000000639 =$A$2*$A$3*$A$4*$A$5*$A$6*D127*E127 128 =CPS!A143 =CPS!E143 0.00000000117 =$A$2*$A$3*$A$4*$A$5*$A$6*D128*E128 129 130 131 Total Rem =SUM(F13:F128)

Calc. No. L-003430, Rev. 0, Attachment B, B-17 of B-17

Attachment C: Byron and Braidwood MicroShield......................................................................................................................... 2 Run #1: Based on UFSAR Table Data from 11.1-10 ..................................................... 2 Run #2: Based on UFSAR Table Data from 11.1-10 with 60 Day Decay ..................... 4 Run #3: Based on UFSAR Table Data from 11.1-10 with 60 Day Decay and Normalized Contact Dose ............................................................................................... 6 Run #4: Based on UFSAR Table Data from 12.2-13 ..................................................... 8 Run #5: Based on UFSAR Table Data from 12.2-13 with 60 Day Decay ................... 10 Run #6: Based on UFSAR Table Data from 12.2-13 with 60 Day Decay and Normalized Contact Dose ............................................................................................. 12 Excel Sheets ...................................................................................................................... 14 Drop Accident: Based on UFSAR Table 11.1-10......................................................... 14 Captures the isotopic mix from Run #3 in column D, and calculates a final dose in column F.

Fire Accdent: Based on UFSAR Table 11.1-10............................................................ 15 Captures the isotopic mix from Run #3 in column D, and calculates a final dose in column F.

Drop Accident: Based on UFSAR Table 12.2-13......................................................... 16 Captures the isotopic mix from Run #6 in column D, and calculates a final dose in column F.

Fire Accdent: Based on UFSAR Table 12.2-13............................................................ 17 Captures the isotopic mix from Run #6 in column D, and calculates a final dose in column F.

Drop Accident: Formula Version: Based on UFSAR Table 11.1-10 ........................... 18 Fire Accident: Formula Version: Based on UFSAR Table 11.1-10 ............................. 19 Drop Accident: Formula Version: Based on UFSAR Table 12.2-13 ........................... 20 Fire Accident: Formula Version: Based on UFSAR Table 12.2-13 ............................. 21 Calc. No. L-003430, Rev. 0, Attachment C, C-1 of C-21

A B C D E F G H I 1 MicroShield 8.01 2 Washington Group International (8.00-0000) 3 Date By Checked 4

5 Filename Run Date Run Time Duration 6 BB111.msd 11-Aug-09 9:20:26 AM 0:00:05 7 Project Info 8 Case Title B&B 11.1-10 9 Description before decay and resizing 10 Geometry 7 - Cylinder Volume - Side Shields 11 Source Dimensions 12 Height 182.88 cm (6 ft) 13 Radius 76.2 cm (2 ft 6.0 in) 14 Dose Points 15 A X Y Z 16 #1 78.74 cm (2 ft 7.0 in) 91.44 cm (3 ft) 0.0 cm (0 in) 17 Shields 18 Shield N Dimension Material Density 19 Source 2.04e+05 in³ Water 0.9 20 Transition Air 0.00122 21 Air Gap Air 0.00122 22 Source Input: Grouping Method - Linear Energy 23 Number of Groups: 25 24 Lower Energy Cutoff: 0.015 25 Photons < 0.015: Included 26 Library: Grove 27 Nuclide Ci Bq µCi/cm³ Bq/cm³ 28 Ba-137m 6.58E+02 2.43E+13 1.97E+02 7.29E+06 29 Ba-140 1.70E+00 6.29E+10 5.09E-01 1.88E+04 30 Co-58 5.10E+02 1.89E+13 1.53E+02 5.65E+06 31 Co-60 1.32E+02 4.87E+12 3.95E+01 1.46E+06 32 Cr-51 2.80E+01 1.04E+12 8.40E+00 3.11E+05 33 Cs-134 8.92E+02 3.30E+13 2.67E+02 9.89E+06 34 Cs-136 5.18E+01 1.92E+12 1.55E+01 5.75E+05 35 Cs-137 6.95E+02 2.57E+13 2.08E+02 7.71E+06 36 Fe-55 1.02E+02 3.77E+12 3.06E+01 1.13E+06 37 Fe-59 2.29E+01 8.49E+11 6.88E+00 2.54E+05 38 I-133 1.85E+02 6.85E+12 5.55E+01 2.05E+06 39 La-140 1.70E+00 6.29E+10 5.09E-01 1.88E+04 40 Mn-54 1.70E+01 6.29E+11 5.09E+00 1.88E+05 41 Mo-99 42 Nb-95 43 Rb-86 5.10E-01 1.89E+10 1.53E-01 5.65E+03 44 Rh-103m 45 Rh-106 46 Ru-103 47 Ru-106 48 Sr-89 8.50E+00 3.14E+11 2.55E+00 9.42E+04 49 Sr-90 6.80E-01 2.51E+10 2.04E-01 7.54E+03 50 Y-90 51 Y-91 52 Zr-95 53 Buildup: The material reference is Source 54 Integration Parameters 55 Radial 30 56 Circumferential 30 57 Y Direction (axial) 60 58 Results 59 Fluence Rate Fluence Rate Exposure Rate Exposure Rate 60 Energy (MeV) Activity (Photons/sec) MeV/cm²/sec MeV/cm²/sec mR/hr mR/hr 61 No Buildup With Buildup No Buildup With Buildup 62 0.0154 9.59E+12 1.33E+04 1.57E+04 1.06E+03 1.25E+03 63 0.1678 5.63E+11 9.08E+04 4.71E+05 1.54E+02 7.97E+02 64 0.2729 2.90E+11 8.95E+04 3.48E+05 1.68E+02 6.51E+02 65 0.3384 1.07E+12 4.43E+05 1.53E+06 8.52E+02 2.95E+03 66 0.4736 5.66E+11 3.74E+05 1.10E+06 7.33E+02 2.16E+03 Calc. No. L-003430, Rev. 0, Attachment C, C-2 of C-21

A B C D E F G H I 67 0.58 5.18E+13 4.55E+07 1.23E+08 8.90E+04 2.41E+05 68 0.6618 2.21E+13 2.34E+07 6.01E+07 4.54E+04 1.17E+05 69 0.8018 4.99E+13 6.98E+07 1.66E+08 1.33E+05 3.16E+05 70 0.8309 3.11E+12 4.59E+06 1.08E+07 8.69E+03 2.05E+04 71 0.925 6.60E+09 1.14E+04 2.58E+04 2.13E+01 4.82E+01 72 1.0572 2.38E+12 5.00E+06 1.09E+07 9.13E+03 1.98E+04 73 1.1726 5.47E+12 1.34E+07 2.81E+07 2.39E+04 5.02E+04 74 1.2659 1.01E+12 2.76E+06 5.66E+06 4.85E+03 9.94E+03 75 1.3381 5.89E+12 1.75E+07 3.53E+07 3.04E+04 6.12E+04 76 1.5965 6.00E+10 2.33E+05 4.45E+05 3.85E+02 7.36E+02 77 1.6747 1.01E+11 4.22E+05 7.96E+05 6.88E+02 1.30E+03 78 2.3488 5.35E+08 3.70E+03 6.40E+03 5.43E+00 9.40E+00 79 2.5224 2.24E+09 1.72E+04 2.93E+04 2.47E+01 4.20E+01 80 Totals 1.54E+14 1.84E+08 4.45E+08 3.48E+05 8.45E+05 Calc. No. L-003430, Rev. 0, Attachment C, C-3 of C-21

A B C D E F G H I 1 MicroShield 8.01 2 Washington Group International (8.00-0000) 3 Date By Checked 4

5 Filename Run Date Run Time Duration 6 BB111decay.msd 11-Aug-09 9:21:29 AM 0:00:05 7 Project Info 8 Case Title B&B 11.1-10 9 Description before resizing 10 Geometry 7 - Cylinder Volume - Side Shields 11 Source Dimensions 12 Height 182.88 cm (6 ft) 13 Radius 76.2 cm (2 ft 6.0 in) 14 Dose Points 15 A X Y Z 16 #1 78.74 cm (2 ft 7.0 in) 91.44 cm (3 ft) 0.0 cm (0 in) 17 Shields 18 Shield N Dimension Material Density 19 Source 2.04e+05 in³ Water 0.9 20 Transition Air 0.00122 21 Air Gap Air 0.00122 22 Source Input: Grouping Method - Linear Energy 23 Number of Groups: 25 24 Lower Energy Cutoff: 0.015 25 Photons < 0.015: Included 26 Library: Grove 27 Nuclide Ci Bq µCi/cm³ Bq/cm³ 28 Ba-137m 6.55E+02 2.42E+13 1.96E+02 7.26E+06 29 Ba-140 6.58E-02 2.43E+09 1.97E-02 7.29E+02 30 Co-58 2.83E+02 1.05E+13 8.49E+01 3.14E+06 31 Co-60 1.29E+02 4.77E+12 3.86E+01 1.43E+06 32 Cr-51 6.25E+00 2.31E+11 1.87E+00 6.93E+04 33 Cs-134 8.44E+02 3.12E+13 2.53E+02 9.36E+06 34 Cs-136 2.20E+00 8.13E+10 6.59E-01 2.44E+04 35 Cs-137 6.92E+02 2.56E+13 2.08E+02 7.68E+06 36 Fe-55 9.77E+01 3.62E+12 2.93E+01 1.08E+06 37 Fe-59 9.03E+00 3.34E+11 2.71E+00 1.00E+05 38 I-133 2.67E-19 9.89E-09 8.01E-20 2.97E-15 39 La-140 7.57E-02 2.80E+09 2.27E-02 8.39E+02 40 Mn-54 1.49E+01 5.50E+11 4.46E+00 1.65E+05 41 Mo-99 42 Nb-95 43 Rb-86 5.49E-02 2.03E+09 1.64E-02 6.09E+02 44 Rh-103m 45 Rh-106 46 Ru-103 47 Ru-106 48 Sr-89 3.73E+00 1.38E+11 1.12E+00 4.14E+04 49 Sr-90 6.77E-01 2.50E+10 2.03E-01 7.51E+03 50 Xe-133 1.35E-02 4.98E+08 4.04E-03 1.49E+02 51 Xe-133m 1.98E-08 7.31E+02 5.92E-09 2.19E-04 52 Y-90 6.77E-01 2.51E+10 2.03E-01 7.51E+03 53 Y-91 54 Zr-95 55 Buildup: The material reference is Source 56 Integration Parameters 57 Radial 30 58 Circumferential 30 59 Y Direction (axial) 60 60 Results 61 Fluence Rate Fluence Rate Exposure Rate Exposure Rate 62 Energy (MeV) Activity (Photons/sec) MeV/cm²/sec MeV/cm²/sec mR/hr mR/hr 63 No Buildup With Buildup No Buildup With Buildup 64 0.0148 6.31E+12 7.92E+03 9.21E+03 7.07E+02 8.22E+02 65 0.1719 3.62E+10 6.03E+03 3.09E+04 1.03E+01 5.26E+01 66 0.2754 2.15E+10 6.71E+03 2.59E+04 1.26E+01 4.86E+01 Calc. No. L-003430, Rev. 0, Attachment C, C-4 of C-21

A B C D E F G H I 67 0.333 6.41E+10 2.59E+04 9.02E+04 4.97E+01 1.73E+02 68 0.4754 4.58E+11 3.04E+05 8.96E+05 5.97E+02 1.76E+03 69 0.5908 4.11E+13 3.70E+07 9.95E+07 7.24E+04 1.94E+05 70 0.6617 2.18E+13 2.31E+07 5.93E+07 4.49E+04 1.15E+05 71 0.8002 3.98E+13 5.56E+07 1.33E+08 1.06E+05 2.52E+05 72 0.8361 7.09E+11 1.06E+06 2.48E+06 2.00E+03 4.69E+03 73 0.925 2.94E+08 5.07E+02 1.15E+03 9.47E-01 2.15E+00 74 1.0599 5.66E+11 1.19E+06 2.59E+06 2.18E+03 4.72E+03 75 1.1726 5.33E+12 1.30E+07 2.74E+07 2.33E+04 4.89E+04 76 1.2859 1.61E+11 4.51E+05 9.20E+05 7.90E+02 1.61E+03 77 1.3379 5.72E+12 1.70E+07 3.43E+07 2.95E+04 5.94E+04 78 1.5965 2.67E+09 1.04E+04 1.98E+04 1.71E+01 3.28E+01 79 1.6747 5.63E+10 2.34E+05 4.43E+05 3.82E+02 7.22E+02 80 2.3488 2.38E+07 1.65E+02 2.85E+02 2.42E-01 4.19E-01 81 2.5224 9.97E+07 7.66E+02 1.30E+03 1.10E+00 1.87E+00 82 Totals 1.22E+14 1.49E+08 3.61E+08 2.83E+05 6.84E+05 Calc. No. L-003430, Rev. 0, Attachment C, C-5 of C-21

A B C D E F G H I 1 MicroShield 8.01 2 Washington Group International (8.00-0000) 3 Date By Checked 4

5 Filename Run Date Run Time Duration 6 BB11decay2.msd 3-Aug-09 2:05:01 PM 0:00:05 7 Project Info 8 Case Title BB 11.1-10 9 Description before resizing 10 Geometry 7 - Cylinder Volume - Side Shields 11 Source Dimensions 12 Height 182.88 cm (6 ft) 13 Radius 76.2 cm (2 ft 6.0 in) 14 Dose Points 15 A X Y Z 16 #1 78.74 cm (2 ft 7.0 in) 91.44 cm (3 ft) 0.0 cm (0 in) 17 Shields 18 Shield N Dimension Material Density 19 Source 2.04e+05 in³ Water 0.9 20 Transition Air 0.00122 21 Air Gap Air 0.00122 22 Source Input: Grouping Method - Linear Energy 23 Number of Groups: 25 24 Lower Energy Cutoff: 0.015 25 Photons < 0.015: Included 26 Library: Grove 27 Nuclide Ci Bq µCi/cm³ Bq/cm³ 28 Ba-137m 1.91E+02 7.08E+12 5.74E+01 2.12E+06 29 Ba-140 1.92E-02 7.11E+08 5.76E-03 2.13E+02 30 Co-58 8.28E+01 3.06E+12 2.48E+01 9.18E+05 31 Co-60 3.77E+01 1.39E+12 1.13E+01 4.18E+05 32 Cr-51 1.83E+00 6.76E+10 5.47E-01 2.03E+04 33 Cs-134 2.47E+02 9.13E+12 7.39E+01 2.74E+06 34 Cs-136 6.42E-01 2.38E+10 1.93E-01 7.12E+03 35 Cs-137 2.02E+02 7.49E+12 6.07E+01 2.24E+06 36 Fe-55 2.86E+01 1.06E+12 8.56E+00 3.17E+05 37 Fe-59 2.64E+00 9.77E+10 7.91E-01 2.93E+04 38 I-133 7.81E-20 2.89E-09 2.34E-20 8.67E-16 39 La-140 2.21E-02 8.18E+08 6.63E-03 2.45E+02 40 Mn-54 4.35E+00 1.61E+11 1.30E+00 4.82E+04 41 Mo-99 42 Nb-95 43 Rb-86 1.60E-02 5.93E+08 4.81E-03 1.78E+02 44 Rh-103m 45 Rh-106 46 Ru-103 47 Ru-106 48 Sr-89 1.09E+00 4.04E+10 3.27E-01 1.21E+04 49 Sr-90 1.98E-01 7.32E+09 5.93E-02 2.19E+03 50 Xe-133 3.94E-03 1.46E+08 1.18E-03 4.37E+01 51 Xe-133m 5.78E-09 2.14E+02 1.73E-09 6.41E-05 52 Y-90 1.98E-01 7.32E+09 5.93E-02 2.19E+03 53 Y-91 54 Zr-95 55 Buildup: The material reference is Source 56 Integration Parameters 57 Radial 30 58 Circumferential 30 59 Y Direction (axial) 60 60 Results 61 Fluence Rate Fluence Rate Exposure Rate Exposure Rate 62 Energy (MeV) Activity (Photons/sec) MeV/cm²/sec MeV/cm²/sec mR/hr mR/hr 63 No Buildup With Buildup No Buildup With Buildup 64 0.0148 1.85E+12 2.31E+03 2.69E+03 2.07E+02 2.40E+02 65 0.1719 1.06E+10 1.76E+03 9.02E+03 3.00E+00 1.54E+01 66 0.2754 6.28E+09 1.96E+03 7.58E+03 3.67E+00 1.42E+01 Calc. No. L-003430, Rev. 0, Attachment C, C-6 of C-21

A B C D E F G H I 67 0.333 1.87E+10 7.57E+03 2.64E+04 1.45E+01 5.06E+01 68 0.4754 1.34E+11 8.89E+04 2.62E+05 1.74E+02 5.14E+02 69 0.5908 1.20E+13 1.08E+07 2.91E+07 2.12E+04 5.68E+04 70 0.6617 6.37E+12 6.76E+06 1.73E+07 1.31E+04 3.36E+04 71 0.8002 1.16E+13 1.63E+07 3.87E+07 3.09E+04 7.37E+04 72 0.8361 2.07E+11 3.09E+05 7.24E+05 5.84E+02 1.37E+03 73 0.925 8.60E+07 1.48E+02 3.36E+02 2.77E-01 6.27E-01 74 1.0599 1.65E+11 3.49E+05 7.56E+05 6.36E+02 1.38E+03 75 1.1726 1.56E+12 3.81E+06 8.00E+06 6.81E+03 1.43E+04 76 1.2859 4.70E+10 1.32E+05 2.69E+05 2.31E+02 4.70E+02 77 1.3379 1.67E+12 4.98E+06 1.00E+07 8.62E+03 1.74E+04 78 1.5965 7.81E+08 3.03E+03 5.80E+03 5.01E+00 9.58E+00 79 1.6747 1.65E+10 6.85E+04 1.29E+05 1.12E+02 2.11E+02 80 2.3488 6.96E+06 4.81E+01 8.33E+01 7.06E-02 1.22E-01 81 2.5224 2.91E+07 2.24E+02 3.81E+02 3.21E-01 5.46E-01 82 Totals 3.57E+13 4.36E+07 1.05E+08 8.26E+04 2.00E+05 Calc. No. L-003430, Rev. 0, Attachment C, C-7 of C-21

A B C D E F G H I 1 MicroShield 8.01 2 Washington Group International (8.00-0000) 3 Date By Checked 4

5 Filename Run Date Run Time Duration 6 BB222.msd 11-Aug-09 9:27:01 AM 0:00:05 7 Project Info 8 Case Title B&B 12.2-13 9 Description before decay and resizing 10 Geometry 7 - Cylinder Volume - Side Shields 11 Source Dimensions 12 Height 182.88 cm (6 ft) 13 Radius 76.2 cm (2 ft 6.0 in) 14 Dose Points 15 A X Y Z 16 #1 78.74 cm (2 ft 7.0 in) 91.44 cm (3 ft) 0.0 cm (0 in) 17 Shields 18 Shield N Dimension Material Density 19 Source 2.04e+05 in³ Water 0.9 20 Transition Air 0.00122 21 Air Gap Air 0.00122 22 Source Input: Grouping Method - Linear Energy 23 Number of Groups: 25 24 Lower Energy Cutoff: 0.015 25 Photons < 0.015: Included 26 Library: Grove 27 Nuclide Ci Bq µCi/cm³ Bq/cm³ 28 Ba-137m 5.27E+03 1.95E+14 1.58E+03 5.84E+07 29 Ba-140 2.91E+01 1.08E+12 8.73E+00 3.23E+05 30 Ce-144 1.85E+01 6.85E+11 5.55E+00 2.05E+05 31 Co-58 5.52E+02 2.04E+13 1.66E+02 6.12E+06 32 Co-60 7.22E+01 2.67E+12 2.16E+01 8.01E+05 33 Cs-134 8.58E+03 3.17E+14 2.57E+03 9.52E+07 34 Cs-136 6.29E+02 2.33E+13 1.88E+02 6.97E+06 35 Cs-137 5.61E+03 2.07E+14 1.68E+03 6.22E+07 36 Cs-138 1.10E+01 4.05E+11 3.29E+00 1.22E+05 37 Fe-59 1.53E+01 5.66E+11 4.58E+00 1.70E+05 38 I-131 1.06E+04 3.93E+14 3.18E+03 1.18E+08 39 I-132 1.56E+03 5.78E+13 4.69E+02 1.73E+07 40 I-133 1.85E+03 6.85E+13 5.55E+02 2.05E+07 41 I-134 1.14E+01 4.21E+11 3.41E+00 1.26E+05 42 I-135 3.20E+02 1.19E+13 9.60E+01 3.55E+06 43 La-140 3.04E+01 1.13E+12 9.12E+00 3.37E+05 44 Mn-54 4.08E+01 1.51E+12 1.22E+01 4.52E+05 45 Mn-56 1.02E+00 3.77E+10 3.06E-01 1.13E+04 46 Mo-99 1.11E+03 4.12E+13 3.34E+02 1.23E+07 47 Nb-95 3.37E+01 1.25E+12 1.01E+01 3.74E+05 48 Pr-144 1.85E+01 6.85E+11 5.55E+00 2.05E+05 49 Rb-88 2.46E+01 9.08E+11 7.36E+00 2.72E+05 50 Rb-89 1.10E+00 4.07E+10 3.30E-01 1.22E+04 51 Sr-89 8.83E+01 3.27E+12 2.65E+01 9.80E+05 52 Sr-90 1.29E+01 4.78E+11 3.87E+00 1.43E+05 53 Sr-91 4.25E-01 1.57E+10 1.27E-01 4.71E+03 54 Sr-92 4.42E-02 1.63E+09 1.32E-02 4.90E+02 55 Te-132 4.59E+02 1.70E+13 1.38E+02 5.09E+06 56 Te-134 4.59E-01 1.70E+10 1.38E-01 5.09E+03 57 Y-90 6.37E+00 2.36E+11 1.91E+00 7.07E+04 58 Y-91 9.17E+00 3.39E+11 2.75E+00 1.02E+05 59 Y-92 1.02E-01 3.77E+09 3.06E-02 1.13E+03 60 Zr-95 2.27E+01 8.39E+11 6.80E+00 2.52E+05 61 Buildup: The material reference is Source 62 Integration Parameters 63 Radial 30 64 Circumferential 30 65 Y Direction (axial) 60 66 Results Calc. No. L-003430, Rev. 0, Attachment C, C-8 of C-21

A B C D E F G H I 67 Fluence Rate Fluence Rate Exposure Rate Exposure Rate 68 Energy (MeV) Activity (Photons/sec) MeV/cm²/sec MeV/cm²/sec mR/hr mR/hr 69 No Buildup With Buildup No Buildup With Buildup 70 0.053 9.48E+13 3.34E+06 1.81E+07 8.00E+03 4.33E+04 71 0.3517 3.78E+14 1.65E+08 5.59E+08 3.18E+05 1.08E+06 72 0.5419 1.67E+14 1.33E+08 3.70E+08 2.61E+05 7.25E+05 73 0.6335 6.08E+14 6.06E+08 1.58E+09 1.18E+06 3.08E+06 74 0.7974 4.06E+14 5.64E+08 1.35E+09 1.07E+06 2.56E+06 75 1.0318 4.21E+13 8.52E+07 1.86E+08 1.56E+05 3.42E+05 76 1.221 2.36E+13 6.12E+07 1.27E+08 1.08E+05 2.25E+05 77 1.3784 2.05E+13 6.37E+07 1.27E+08 1.10E+05 2.19E+05 78 1.6467 2.98E+12 1.21E+07 2.30E+07 1.99E+04 3.77E+04 79 1.7952 1.40E+12 6.47E+06 1.20E+07 1.04E+04 1.92E+04 80 1.9758 1.59E+12 8.49E+06 1.54E+07 1.32E+04 2.39E+04 81 2.2077 3.40E+11 2.14E+06 3.76E+06 3.21E+03 5.64E+03 82 2.3976 2.21E+11 1.57E+06 2.71E+06 2.29E+03 3.95E+03 83 2.5718 7.93E+10 6.27E+05 1.06E+06 8.94E+02 1.51E+03 84 2.6828 2.03E+10 1.71E+05 2.87E+05 2.41E+02 4.04E+02 85 3.0069 2.33E+09 2.33E+04 3.79E+04 3.15E+01 5.14E+01 86 3.2185 1.94E+09 2.14E+04 3.44E+04 2.84E+01 4.56E+01 87 3.3564 1.60E+09 1.87E+04 2.98E+04 2.45E+01 3.90E+01 88 3.4928 1.65E+09 2.06E+04 3.24E+04 2.66E+01 4.18E+01 89 4.7427 1.30E+09 2.52E+04 3.68E+04 2.94E+01 4.30E+01 90 Totals 1.75E+15 1.71E+09 4.37E+09 3.26E+06 8.36E+06 Calc. No. L-003430, Rev. 0, Attachment C, C-9 of C-21

A B C D E F G H I 1 MicroShield 8.01 2 Washington Group International (8.00-0000) 3 Date By Checked 4

5 Filename Run Date Run Time Duration 6 BB222decay.msd 11-Aug-09 9:28:06 AM 0:00:06 7 Project Info 8 Case Title B&B 12.2-13 9 Description before resizing 10 Geometry 7 - Cylinder Volume - Side Shields 11 Source Dimensions 12 Height 182.88 cm (6 ft) 13 Radius 76.2 cm (2 ft 6.0 in) 14 Dose Points 15 A X Y Z 16 #1 78.74 cm (2 ft 7.0 in) 91.44 cm (3 ft) 0.0 cm (0 in) 17 Shields 18 Shield N Dimension Material Density 19 Source 2.04e+05 in³ Water 0.9 20 Transition Air 0.00122 21 Air Gap Air 0.00122 22 Source Input: Grouping Method - Linear Energy 23 Number of Groups: 25 24 Lower Energy Cutoff: 0.015 25 Photons < 0.015: Included 26 Library: Grove 27 Nuclide Ci Bq µCi/cm³ Bq/cm³ 28 Ba-137m 5.28E+03 1.96E+14 1.58E+03 5.86E+07 29 Ba-140 1.13E+00 4.17E+10 3.38E-01 1.25E+04 30 Ce-144 1.60E+01 5.92E+11 4.80E+00 1.77E+05 31 Co-58 3.07E+02 1.14E+13 9.20E+01 3.40E+06 32 Co-60 7.07E+01 2.61E+12 2.12E+01 7.84E+05 33 Cs-134 8.12E+03 3.00E+14 2.43E+03 9.01E+07 34 Cs-135 1.05E-07 3.88E+03 3.15E-08 1.16E-03 35 Cs-136 2.67E+01 9.87E+11 7.99E+00 2.96E+05 36 Cs-137 5.59E+03 2.07E+14 1.67E+03 6.20E+07 37 Cs-138 38 Fe-59 6.02E+00 2.23E+11 1.81E+00 6.68E+04 39 I-131 6.02E+01 2.23E+12 1.80E+01 6.68E+05 40 I-132 1.35E-03 5.01E+07 4.06E-04 1.50E+01 41 I-133 2.67E-18 9.89E-08 8.01E-19 2.97E-14 42 I-134 43 I-135 8.43E-64 3.12E-53 2.53E-64 9.35E-60 44 La-140 1.30E+00 4.80E+10 3.89E-01 1.44E+04 45 Mn-54 3.57E+01 1.32E+12 1.07E+01 3.96E+05 46 Mn-56 7.83E-169 2.90E-158 2.35E-169 8.69E-165 47 Mo-99 3.02E-04 1.12E+07 9.06E-05 3.35E+00 48 Nb-95 2.12E+01 7.83E+11 6.35E+00 2.35E+05 49 Nb-95m 1.00E-01 3.72E+09 3.01E-02 1.11E+03 50 Pr-144 1.60E+01 5.92E+11 4.80E+00 1.77E+05 51 Pr-144m 2.29E-01 8.47E+09 6.86E-02 2.54E+03 52 Rb-88 53 Rb-89 54 Sr-89 3.88E+01 1.44E+12 1.16E+01 4.30E+05 55 Sr-90 1.29E+01 4.76E+11 3.86E+00 1.43E+05 56 Sr-91 9.96E-47 3.69E-36 2.99E-47 1.10E-42 57 Sr-92 4.88E-162 1.81E-151 1.46E-162 5.41E-158 58 Tc-99 3.93E-05 1.46E+06 1.18E-05 4.36E-01 59 Tc-99m 2.95E-04 1.09E+07 8.84E-05 3.27E+00 60 Te-132 1.31E-03 4.86E+07 3.94E-04 1.46E+01 61 Te-134 62 Xe-131m 5.89E+00 2.18E+11 1.77E+00 6.54E+04 63 Xe-133 1.35E-01 4.98E+09 4.04E-02 1.49E+03 64 Xe-133m 1.98E-07 7.31E+03 5.92E-08 2.19E-03 65 Xe-135 2.22E-45 8.22E-35 6.66E-46 2.46E-41 66 Xe-135m 1.45E-64 5.35E-54 4.34E-65 1.60E-60 Calc. No. L-003430, Rev. 0, Attachment C, C-10 of C-21

A B C D E F G H I 67 Y-90 1.29E+01 4.76E+11 3.86E+00 1.43E+05 68 Y-91 4.51E+00 1.67E+11 1.35E+00 5.00E+04 69 Y-91m 6.26E-47 2.32E-36 1.88E-47 6.95E-43 70 Y-92 8.68E-124 3.21E-113 2.60E-124 9.62E-120 71 Zr-95 1.18E+01 4.38E+11 3.55E+00 1.31E+05 72 Buildup: The material reference is Source 73 Integration Parameters 74 Radial 30 75 Circumferential 30 76 Y Direction (axial) 60 77 Results 78 Fluence Rate Fluence Rate Exposure Rate Exposure Rate 79 Energy (MeV) Activity (Photons/sec) MeV/cm²/sec MeV/cm²/sec mR/hr mR/hr 80 No Buildup With Buildup No Buildup With Buildup 81 0.0268 2.30E+13 2.08E+05 3.94E+05 2.88E+03 5.47E+03 82 0.1687 2.89E+11 4.69E+04 2.43E+05 7.96E+01 4.11E+02 83 0.3481 2.68E+12 1.15E+06 3.93E+06 2.22E+03 7.57E+03 84 0.491 7.83E+12 5.44E+06 1.58E+07 1.07E+04 3.10E+04 85 0.6183 5.41E+14 5.21E+08 1.37E+09 1.02E+06 2.67E+06 86 0.7962 2.84E+14 3.94E+08 9.40E+08 7.49E+05 1.79E+06 87 0.814 1.37E+13 1.96E+07 4.65E+07 3.72E+04 8.82E+04 88 1.0406 3.79E+12 7.77E+06 1.70E+07 1.42E+04 3.10E+04 89 1.1685 8.15E+12 1.98E+07 4.17E+07 3.55E+04 7.46E+04 90 1.3246 2.91E+12 8.52E+06 1.72E+07 1.48E+04 2.99E+04 91 1.3652 9.13E+12 2.80E+07 5.61E+07 4.83E+04 9.67E+04 92 1.5925 4.76E+10 1.84E+05 3.52E+05 3.04E+02 5.83E+02 93 1.6747 6.10E+10 2.54E+05 4.79E+05 4.14E+02 7.82E+02 94 1.7575 1.48E+05 6.64E-01 1.24E+00 1.07E-03 1.99E-03 95 1.9599 1.14E+06 5.99E+00 1.09E+01 9.32E-03 1.69E-02 96 2.0868 1.19E+05 6.86E-01 1.23E+00 1.05E-03 1.87E-03 97 2.1857 4.58E+09 2.84E+04 5.01E+04 4.27E+01 7.54E+01 98 2.3488 4.09E+08 2.82E+03 4.89E+03 4.15E+00 7.18E+00 99 2.5224 1.71E+09 1.31E+04 2.23E+04 1.89E+01 3.21E+01 100 2.6575 1.89E-160 1.57E-165 2.64E-165 2.22E-168 3.72E-168 101 2.9598 8.88E-161 8.65E-166 1.42E-165 1.18E-168 1.93E-168 102 3.3696 4.87E-161 5.74E-166 9.12E-166 7.51E-169 1.19E-168 103 Totals 8.97E+14 1.01E+09 2.51E+09 1.93E+06 4.83E+06 Calc. No. L-003430, Rev. 0, Attachment C, C-11 of C-21

A B C D E F G H I 1 MicroShield 8.01 2 Washington Group International (8.00-0000) 3 Date By Checked 4

5 Filename Run Date Run Time Duration 6 BB12decay2.msd 3-Aug-09 2:47:31 PM 0:00:06 7 Project Info 8 Case Title BB 12.2-13 9 Description after 10 Geometry 7 - Cylinder Volume - Side Shields 11 Source Dimensions 12 Height 182.88 cm (6 ft) 13 Radius 76.2 cm (2 ft 6.0 in) 14 Dose Points 15 A X Y Z 16 #1 78.74 cm (2 ft 7.0 in) 91.44 cm (3 ft) 0.0 cm (0 in) 17 Shields 18 Shield N Dimension Material Density 19 Source 2.04e+05 in³ Water 0.9 20 Transition Air 0.00122 21 Air Gap Air 0.00122 22 Source Input: Grouping Method - Linear Energy 23 Number of Groups: 25 24 Lower Energy Cutoff: 0.015 25 Photons < 0.015: Included 26 Library: Grove 27 Nuclide Ci Bq µCi/cm³ Bq/cm³ 28 Ba-137m 2.19E+02 8.10E+12 6.56E+01 2.43E+06 29 Ba-140 4.67E-02 1.73E+09 1.40E-02 5.18E+02 30 Ce-144 6.62E-01 2.45E+10 1.99E-01 7.35E+03 31 Co-58 1.27E+01 4.70E+11 3.81E+00 1.41E+05 32 Co-60 2.93E+00 1.08E+11 8.77E-01 3.25E+04 33 Cs-134 3.36E+02 1.24E+13 1.01E+02 3.73E+06 34 Cs-135 4.35E-09 1.61E+02 1.30E-09 4.82E-05 35 Cs-136 1.10E+00 4.09E+10 3.31E-01 1.22E+04 36 Cs-137 2.31E+02 8.56E+12 6.93E+01 2.57E+06 37 Cs-138 38 Fe-59 2.49E-01 9.23E+09 7.47E-02 2.77E+03 39 I-131 2.49E+00 9.22E+10 7.47E-01 2.76E+04 40 I-132 5.60E-05 2.07E+06 1.68E-05 6.21E-01 41 I-133 1.11E-19 4.10E-09 3.32E-20 1.23E-15 42 I-134 43 I-135 3.49E-65 1.29E-54 1.05E-65 3.87E-61 44 La-140 5.37E-02 1.99E+09 1.61E-02 5.96E+02 45 Mn-54 1.48E+00 5.47E+10 4.43E-01 1.64E+04 46 Mn-56 3.24E-170 1.20E-159 9.72E-171 3.60E-166 47 Mo-99 1.25E-05 4.63E+05 3.75E-06 1.39E-01 48 Nb-95 8.76E-01 3.24E+10 2.63E-01 9.72E+03 49 Nb-95m 4.16E-03 1.54E+08 1.25E-03 4.61E+01 50 Pr-144 6.63E-01 2.45E+10 1.99E-01 7.35E+03 51 Pr-144m 9.47E-03 3.51E+08 2.84E-03 1.05E+02 52 Rb-88 53 Rb-89 54 Sr-89 1.61E+00 5.95E+10 4.82E-01 1.78E+04 55 Sr-90 5.33E-01 1.97E+10 1.60E-01 5.91E+03 56 Sr-91 4.12E-48 1.53E-37 1.24E-48 4.58E-44 57 Sr-92 2.02E-163 7.47E-153 6.06E-164 2.24E-159 58 Tc-99 1.63E-06 6.03E+04 4.88E-07 1.81E-02 59 Tc-99m 1.22E-05 4.52E+05 3.66E-06 1.35E-01 60 Te-132 5.44E-05 2.01E+06 1.63E-05 6.03E-01 61 Te-134 62 Xe-131m 2.44E-01 9.03E+09 7.31E-02 2.71E+03 63 Xe-133 5.58E-03 2.06E+08 1.67E-03 6.19E+01 64 Xe-133m 8.18E-09 3.03E+02 2.45E-09 9.08E-05 65 Xe-135 9.20E-47 3.40E-36 2.76E-47 1.02E-42 66 Xe-135m 5.99E-66 2.22E-55 1.80E-66 6.64E-62 Calc. No. L-003430, Rev. 0, Attachment C, C-12 of C-21

A B C D E F G H I 67 Y-90 5.33E-01 1.97E+10 1.60E-01 5.91E+03 68 Y-91 1.87E-01 6.91E+09 5.60E-02 2.07E+03 69 Y-91m 2.59E-48 9.60E-38 7.78E-49 2.88E-44 70 Y-92 3.59E-125 1.33E-114 1.08E-125 3.98E-121 71 Zr-95 4.91E-01 1.81E+10 1.47E-01 5.44E+03 72 Buildup: The material reference is Source 73 Integration Parameters 74 Radial 30 75 Circumferential 30 76 Y Direction (axial) 60 77 Results 78 Fluence Rate Fluence Rate Exposure Rate Exposure Rate 79 Energy (MeV) Activity (Photons/sec) MeV/cm²/sec MeV/cm²/sec mR/hr mR/hr 80 No Buildup With Buildup No Buildup With Buildup 81 0.0268 9.53E+11 8.60E+03 1.63E+04 1.19E+02 2.26E+02 82 0.1687 1.20E+10 1.94E+03 1.00E+04 3.29E+00 1.70E+01 83 0.3481 1.11E+11 4.77E+04 1.63E+05 9.20E+01 3.14E+02 84 0.491 3.24E+11 2.25E+05 6.53E+05 4.42E+02 1.28E+03 85 0.6183 2.24E+13 2.16E+07 5.68E+07 4.20E+04 1.11E+05 86 0.7962 1.18E+13 1.63E+07 3.89E+07 3.10E+04 7.41E+04 87 0.814 5.67E+11 8.12E+05 1.92E+06 1.54E+03 3.65E+03 88 1.0406 1.57E+11 3.22E+05 7.02E+05 5.89E+02 1.29E+03 89 1.1685 3.37E+11 8.22E+05 1.73E+06 1.47E+03 3.09E+03 90 1.3246 1.20E+11 3.53E+05 7.13E+05 6.13E+02 1.24E+03 91 1.3652 3.78E+11 1.16E+06 2.32E+06 2.00E+03 4.00E+03 92 1.5925 1.97E+09 7.62E+03 1.46E+04 1.26E+01 2.41E+01 93 1.6747 2.52E+09 1.05E+04 1.99E+04 1.72E+01 3.24E+01 94 1.7575 6.14E+03 2.75E-02 5.12E-02 4.42E-05 8.24E-05 95 1.9599 4.71E+04 2.48E-01 4.50E-01 3.86E-04 7.00E-04 96 2.0868 4.91E+03 2.84E-02 5.07E-02 4.34E-05 7.74E-05 97 2.1857 1.90E+08 1.18E+03 2.08E+03 1.77E+00 3.12E+00 98 2.3488 1.69E+07 1.17E+02 2.02E+02 1.72E-01 2.97E-01 99 2.5224 7.08E+07 5.44E+02 9.25E+02 7.81E-01 1.33E+00 100 2.6575 7.83E-162 6.50E-167 1.09E-166 9.17E-170 1.54E-169 101 2.9598 3.68E-162 3.58E-167 5.86E-167 4.88E-170 7.99E-170 102 3.3696 2.02E-162 2.38E-167 3.78E-167 3.11E-170 4.94E-170 103 Totals 3.71E+13 4.16E+07 1.04E+08 8.00E+04 2.00E+05 Calc. No. L-003430, Rev. 0, Attachment C, C-13 of C-21

A B C D E F 1 Container Drop Event: Byron and Braidwood Isotopic: Table 11.1.10 2 5.400E-04 X/Q (sec/m^3) 3 3.500E-04 Breathing Rate (m^3/sec) 4 1.000E-02 Release Fraction 5 3.70E+12 Conversion Factor (rem/Ci per Sv/Bq) 6 1.00E+00 Containers/Accident 7 2.00E+02 Container Contact - Nominal Baseline Analysis (R/hr) 8 9 5.190E-02 Total Inhalation Dose (rem) 10 11 60 day Decay 12 Isotope Ci in container InhaleDCF Dose (rem) 13 Ba-137m 1.914E+02 0.00E+00 0.000E+00 14 Ba-140 1.922E-02 1.010E-09 1.357E-07 15 Co-58 8.279E+01 2.940E-09 1.702E-03 16 Co-60 3.766E+01 5.910E-08 1.557E-02 17 Cr-51 1.826E+00 9.030E-11 1.153E-06 18 Cs-134 2.467E+02 1.250E-08 2.156E-02 19 Cs-136 6.424E-01 1.980E-09 8.895E-06 20 Cs-137 2.023E+02 8.630E-09 1.221E-02 21 Fe-55 2.856E+01 7.260E-10 1.450E-04 22 Fe-59 2.640E+00 4.000E-09 7.385E-05 23 I-133 7.814E-20 1.580E-09 8.634E-25 24 La-140 2.212E-02 1.310E-09 2.026E-07 25 Mn-54 4.347E+00 1.810E-09 5.503E-05 26 Mo-99 0.000E+00 1.070E-09 0.000E+00 27 Nb-95 0.000E+00 1.570E-09 0.000E+00 28 Rb-86 1.604E-02 1.790E-09 2.008E-07 29 Rh-103m 0.000E+00 1.380E-12 0.000E+00 30 Rh-106 0.000E+00 0.00E+00 0.000E+00 31 Ru-103 0.000E+00 2.420E-09 0.000E+00 32 Ru-106 0.000E+00 1.290E-07 0.000E+00 33 Sr-89 1.091E+00 1.120E-08 8.541E-05 34 Sr-90 1.978E-01 3.510E-07 4.856E-04 35 Xe-133 3.937E-03 0.00E+00 0.000E+00 36 Xe-133m 5.775E-09 0.00E+00 0.000E+00 37 Y-90 1.979E-01 2.280E-09 3.155E-06 38 Y-91 0.000E+00 1.320E-08 0.000E+00 39 Zr-95 0.000E+00 6.390E-09 0.000E+00 40 41 42 Total Rem 5.190E-02 Calc. No. L-003430, Rev. 0, Attachment C, C-14 of C-21

A B C D E F 1 Container Drop Event: Byron and Braidwood Isotopic: Table 12.2.13 2 5.400E-04 X/Q (sec/m^3) 3 3.500E-04 Breathing Rate (m^3/sec) 4 1.000E-02 Release Fraction 5 3.70E+12 Conversion Factor (rem/Ci per Sv/Bq) 6 1.00E+00 Containers/Accident 7 2.00E+02 Container Contact - Nominal Baseline Analysis (R/hr) 8 9 4.697E-02 Total Inhalation Dose (rem) 10 11 60 day Decay 12 Isotope Ci in container InhaleDCF Dose (rem) 13 Ba-137m 2.188E+02 0.00E+00 0.000E+00 14 Ba-140 4.669E-02 1.010E-09 3.298E-07 15 Ce-144 6.625E-01 1.010E-07 4.679E-04 16 Co-58 1.271E+01 2.940E-09 2.612E-04 17 Co-60 2.926E+00 5.910E-08 1.209E-03 18 Cs-134 3.362E+02 1.250E-08 2.939E-02 19 Cs-135 4.348E-09 1.230E-09 3.740E-14 20 Cs-136 1.104E+00 1.980E-09 1.529E-05 21 Cs-137 2.313E+02 8.630E-09 1.396E-02 22 Cs-138 0.000E+00 2.740E-11 0.000E+00 23 Fe-59 2.494E-01 4.000E-09 6.975E-06 24 I-131 2.493E+00 8.890E-09 1.550E-04 25 I-132 5.602E-05 1.030E-10 4.035E-11 26 I-133 1.107E-19 1.580E-09 1.223E-24 27 I-134 0.000E+00 3.550E-11 0.000E+00 28 I-135 3.489E-65 3.320E-10 8.100E-71 29 La-140 5.373E-02 1.310E-09 4.922E-07 30 Mn-54 1.478E+00 1.810E-09 1.871E-05 31 Mn-56 3.243E-170 1.020E-10 2.313E-176 32 Mo-99 1.252E-05 1.070E-09 9.367E-11 33 Nb-95 8.765E-01 1.570E-09 9.623E-06 34 Nb-95m 4.158E-03 6.590E-10 1.916E-08 35 Pr-144 6.625E-01 1.170E-11 5.421E-08 36 Pr-144m 9.474E-03 0.00E+00 0.000E+00 37 Rb-88 0.000E+00 2.260E-11 0.000E+00 38 Rb-89 0.000E+00 1.160E-11 0.000E+00 39 Sr-89 1.607E+00 1.120E-08 1.259E-04 40 Sr-90 5.326E-01 3.510E-07 1.307E-03 41 Sr-91 4.125E-48 4.490E-10 1.295E-53 42 Sr-92 2.020E-163 2.180E-10 3.079E-169 43 Tc-99 1.629E-06 2.250E-09 2.564E-11 44 Tc-99m 1.221E-05 8.800E-12 7.511E-13 45 Te-132 5.437E-05 2.550E-09 9.696E-10 46 Te-134 0.000E+00 3.440E-11 0.000E+00 47 Xe-131m 2.440E-01 0.00E+00 0.000E+00 48 Xe-133 5.578E-03 0.00E+00 0.000E+00 49 Xe-133m 8.183E-09 0.00E+00 0.000E+00 50 Xe-135 9.198E-47 0.00E+00 0.000E+00 51 Xe-135m 5.989E-66 0.00E+00 0.000E+00 52 Y-90 5.327E-01 2.280E-09 8.493E-06 53 Y-91 1.867E-01 1.320E-08 1.723E-05 54 Y-91m 2.594E-48 9.820E-12 1.781E-55 55 Y-92 3.593E-125 2.110E-10 5.301E-131 56 Zr-95 4.905E-01 6.390E-09 2.192E-05 57 58 59 Total Rem 4.697E-02 Calc. No. L-003430, Rev. 0, Attachment C, C-15 of C-21

A B C D E F 1 Container Fire Event: Byron and Braidwood Isotopic: Table 11.1.10 2 5.400E-04 X/Q (sec/m^3) 3 3.500E-04 Breathing Rate (m^3/sec) 4 1.000E-02 Release Fraction 5 3.70E+12 Conversion Factor (rem/Ci per Sv/Bq) 6 6.00E+00 Containers/Accident 7 2.00E+02 Container Contact - Nominal Baseline Analysis (R/hr) 8 9 3.114E-01 Total Inhalation Dose (rem) 10 11 60 day Decay 12 Isotope Ci in container InhaleDCF Dose (rem) 13 Ba-137m 1.914E+02 0.00E+00 0.000E+00 14 Ba-140 1.922E-02 1.010E-09 8.144E-07 15 Co-58 8.279E+01 2.940E-09 1.021E-02 16 Co-60 3.766E+01 5.910E-08 9.339E-02 17 Cr-51 1.826E+00 9.030E-11 6.918E-06 18 Cs-134 2.467E+02 1.250E-08 1.294E-01 19 Cs-136 6.424E-01 1.980E-09 5.337E-05 20 Cs-137 2.023E+02 8.630E-09 7.326E-02 21 Fe-55 2.856E+01 7.260E-10 8.701E-04 22 Fe-59 2.640E+00 4.000E-09 4.431E-04 23 I-133 7.814E-20 1.580E-09 5.180E-24 24 La-140 2.212E-02 1.310E-09 1.216E-06 25 Mn-54 4.347E+00 1.810E-09 3.302E-04 26 Mo-99 0.000E+00 1.070E-09 0.000E+00 27 Nb-95 0.000E+00 1.570E-09 0.000E+00 28 Rb-86 1.604E-02 1.790E-09 1.205E-06 29 Rh-103m 0.000E+00 1.380E-12 0.000E+00 30 Rh-106 0.000E+00 0.00E+00 0.000E+00 31 Ru-103 0.000E+00 2.420E-09 0.000E+00 32 Ru-106 0.000E+00 1.290E-07 0.000E+00 33 Sr-89 1.091E+00 1.120E-08 5.125E-04 34 Sr-90 1.978E-01 3.510E-07 2.914E-03 35 Xe-133 3.937E-03 0.00E+00 0.000E+00 36 Xe-133m 5.775E-09 0.00E+00 0.000E+00 37 Y-90 1.979E-01 2.280E-09 1.893E-05 38 Y-91 0.000E+00 1.320E-08 0.000E+00 39 Zr-95 0.000E+00 6.390E-09 0.000E+00 40 41 42 Total Rem 3.114E-01 Calc. No. L-003430, Rev. 0, Attachment C, C-16 of C-21

A B C D E F 1 Container Fire Event: Byron and Braidwood Isotopic: Table 12.2.13 2 5.400E-04 X/Q (sec/m^3) 3 3.500E-04 Breathing Rate (m^3/sec) 4 1.000E-02 Release Fraction 5 3.70E+12 Conversion Factor (rem/Ci per Sv/Bq) 6 6.00E+00 Containers/Accident 7 2.00E+02 Container Contact - Nominal Baseline Analysis (R/hr) 8 9 2.818E-01 Total Inhalation Dose (rem) 10 11 60 day Decay 12 Isotope Ci in container InhaleDCF Dose (rem) 13 Ba-137m 2.188E+02 0.00E+00 0.000E+00 14 Ba-140 4.669E-02 1.010E-09 1.979E-06 15 Ce-144 6.625E-01 1.010E-07 2.807E-03 16 Co-58 1.271E+01 2.940E-09 1.567E-03 17 Co-60 2.926E+00 5.910E-08 7.256E-03 18 Cs-134 3.362E+02 1.250E-08 1.763E-01 19 Cs-135 4.348E-09 1.230E-09 2.244E-13 20 Cs-136 1.104E+00 1.980E-09 9.173E-05 21 Cs-137 2.313E+02 8.630E-09 8.375E-02 22 Cs-138 0.000E+00 2.740E-11 0.000E+00 23 Fe-59 2.494E-01 4.000E-09 4.185E-05 24 I-131 2.493E+00 8.890E-09 9.298E-04 25 I-132 5.602E-05 1.030E-10 2.421E-10 26 I-133 1.107E-19 1.580E-09 7.339E-24 27 I-134 0.000E+00 3.550E-11 0.000E+00 28 I-135 3.489E-65 3.320E-10 4.860E-70 29 La-140 5.373E-02 1.310E-09 2.953E-06 30 Mn-54 1.478E+00 1.810E-09 1.123E-04 31 Mn-56 3.243E-170 1.020E-10 1.388E-175 32 Mo-99 1.252E-05 1.070E-09 5.620E-10 33 Nb-95 8.765E-01 1.570E-09 5.774E-05 34 Nb-95m 4.158E-03 6.590E-10 1.150E-07 35 Pr-144 6.625E-01 1.170E-11 3.252E-07 36 Pr-144m 9.474E-03 0.00E+00 0.000E+00 37 Rb-88 0.000E+00 2.260E-11 0.000E+00 38 Rb-89 0.000E+00 1.160E-11 0.000E+00 39 Sr-89 1.607E+00 1.120E-08 7.551E-04 40 Sr-90 5.326E-01 3.510E-07 7.843E-03 41 Sr-91 4.125E-48 4.490E-10 7.771E-53 42 Sr-92 2.020E-163 2.180E-10 1.848E-168 43 Tc-99 1.629E-06 2.250E-09 1.538E-10 44 Tc-99m 1.221E-05 8.800E-12 4.506E-12 45 Te-132 5.437E-05 2.550E-09 5.818E-09 46 Te-134 0.000E+00 3.440E-11 0.000E+00 47 Xe-131m 2.440E-01 0.00E+00 0.000E+00 48 Xe-133 5.578E-03 0.00E+00 0.000E+00 49 Xe-133m 8.183E-09 0.00E+00 0.000E+00 50 Xe-135 9.198E-47 0.00E+00 0.000E+00 51 Xe-135m 5.989E-66 0.00E+00 0.000E+00 52 Y-90 5.327E-01 2.280E-09 5.096E-05 53 Y-91 1.867E-01 1.320E-08 1.034E-04 54 Y-91m 2.594E-48 9.820E-12 1.069E-54 55 Y-92 3.593E-125 2.110E-10 3.181E-130 56 Zr-95 4.905E-01 6.390E-09 1.315E-04 57 58 59 Total Rem 2.818E-01 Calc. No. L-003430, Rev. 0, Attachment C, C-17 of C-21

A B C D E F 1 Container Drop Event: Byron and Braidwood Isotopic: Table 11.1.10 2 0.00054 X/Q (sec/m^3) 3 0.00035 Breathing Rate (m^3/sec) 4 0.01 Release Fraction 5 3700000000000 Conversion Factor (rem/Ci per Sv/Bq) 6 1 Containers/Accident 7 200 Container Contact - Nominal Baseline Analysis (R/hr) 8 9 =F42 Total Inhalation Dose (rem) 10 11 60 day Decay 12 Isotope Ci in container InhaleDCF Dose (rem) 13 ='BB11'!A28 ='BB11'!E28 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D13*E13 14 ='BB11'!A29 ='BB11'!E29 0.00000000101 =$A$2*$A$3*$A$4*$A$5*$A$6*D14*E14 15 ='BB11'!A30 ='BB11'!E30 0.00000000294 =$A$2*$A$3*$A$4*$A$5*$A$6*D15*E15 16 ='BB11'!A31 ='BB11'!E31 0.0000000591 =$A$2*$A$3*$A$4*$A$5*$A$6*D16*E16 17 ='BB11'!A32 ='BB11'!E32 0.0000000000903 =$A$2*$A$3*$A$4*$A$5*$A$6*D17*E17 18 ='BB11'!A33 ='BB11'!E33 0.0000000125 =$A$2*$A$3*$A$4*$A$5*$A$6*D18*E18 19 ='BB11'!A34 ='BB11'!E34 0.00000000198 =$A$2*$A$3*$A$4*$A$5*$A$6*D19*E19 20 ='BB11'!A35 ='BB11'!E35 0.00000000863 =$A$2*$A$3*$A$4*$A$5*$A$6*D20*E20 21 ='BB11'!A36 ='BB11'!E36 0.000000000726 =$A$2*$A$3*$A$4*$A$5*$A$6*D21*E21 22 ='BB11'!A37 ='BB11'!E37 0.000000004 =$A$2*$A$3*$A$4*$A$5*$A$6*D22*E22 23 ='BB11'!A38 ='BB11'!E38 0.00000000158 =$A$2*$A$3*$A$4*$A$5*$A$6*D23*E23 24 ='BB11'!A39 ='BB11'!E39 0.00000000131 =$A$2*$A$3*$A$4*$A$5*$A$6*D24*E24 25 ='BB11'!A40 ='BB11'!E40 0.00000000181 =$A$2*$A$3*$A$4*$A$5*$A$6*D25*E25 26 ='BB11'!A41 ='BB11'!E41 0.00000000107 =$A$2*$A$3*$A$4*$A$5*$A$6*D26*E26 27 ='BB11'!A42 ='BB11'!E42 0.00000000157 =$A$2*$A$3*$A$4*$A$5*$A$6*D27*E27 28 ='BB11'!A43 ='BB11'!E43 0.00000000179 =$A$2*$A$3*$A$4*$A$5*$A$6*D28*E28 29 ='BB11'!A44 ='BB11'!E44 0.00000000000138 =$A$2*$A$3*$A$4*$A$5*$A$6*D29*E29 30 ='BB11'!A45 ='BB11'!E45 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D30*E30 31 ='BB11'!A46 ='BB11'!E46 0.00000000242 =$A$2*$A$3*$A$4*$A$5*$A$6*D31*E31 32 ='BB11'!A47 ='BB11'!E47 0.000000129 =$A$2*$A$3*$A$4*$A$5*$A$6*D32*E32 33 ='BB11'!A48 ='BB11'!E48 0.0000000112 =$A$2*$A$3*$A$4*$A$5*$A$6*D33*E33 34 ='BB11'!A49 ='BB11'!E49 0.000000351 =$A$2*$A$3*$A$4*$A$5*$A$6*D34*E34 35 ='BB11'!A50 ='BB11'!E50 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D35*E35 36 ='BB11'!A51 ='BB11'!E51 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D36*E36 37 ='BB11'!A52 ='BB11'!E52 0.00000000228 =$A$2*$A$3*$A$4*$A$5*$A$6*D37*E37 38 ='BB11'!A53 ='BB11'!E53 0.0000000132 =$A$2*$A$3*$A$4*$A$5*$A$6*D38*E38 39 ='BB11'!A54 ='BB11'!E54 0.00000000639 =$A$2*$A$3*$A$4*$A$5*$A$6*D39*E39 40 41 42 Total Rem =SUM(F13:F39)

Calc. No. L-003430, Rev. 0, Attachment C, C-18 of C-21

A B C D E F 1 Container Drop Event: Byron and Braidwood Isotopic: Table 12.2.13 2 0.00054 X/Q (sec/m^3) 3 0.00035 Breathing Rate (m^3/sec) 4 0.01 Release Fraction 5 3700000000000 Conversion Factor (rem/Ci per Sv/Bq) 6 1 Containers/Accident 7 200 Container Contact - Nominal Baseline Analysis (R/hr) 8 9 =F59 Total Inhalation Dose (rem) 10 11 60 day Decay 12 Isotope Ci in container InhaleDCF Dose (rem) 13 ='BB12'!A28 ='BB12'!E28 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D13*E13 14 ='BB12'!A29 ='BB12'!E29 0.00000000101 =$A$2*$A$3*$A$4*$A$5*$A$6*D14*E14 15 ='BB12'!A30 ='BB12'!E30 0.000000101 =$A$2*$A$3*$A$4*$A$5*$A$6*D15*E15 16 ='BB12'!A31 ='BB12'!E31 0.00000000294 =$A$2*$A$3*$A$4*$A$5*$A$6*D16*E16 17 ='BB12'!A32 ='BB12'!E32 0.0000000591 =$A$2*$A$3*$A$4*$A$5*$A$6*D17*E17 18 ='BB12'!A33 ='BB12'!E33 0.0000000125 =$A$2*$A$3*$A$4*$A$5*$A$6*D18*E18 19 ='BB12'!A34 ='BB12'!E34 0.00000000123 =$A$2*$A$3*$A$4*$A$5*$A$6*D19*E19 20 ='BB12'!A35 ='BB12'!E35 0.00000000198 =$A$2*$A$3*$A$4*$A$5*$A$6*D20*E20 21 ='BB12'!A36 ='BB12'!E36 0.00000000863 =$A$2*$A$3*$A$4*$A$5*$A$6*D21*E21 22 ='BB12'!A37 ='BB12'!E37 0.0000000000274 =$A$2*$A$3*$A$4*$A$5*$A$6*D22*E22 23 ='BB12'!A38 ='BB12'!E38 0.000000004 =$A$2*$A$3*$A$4*$A$5*$A$6*D23*E23 24 ='BB12'!A39 ='BB12'!E39 0.00000000889 =$A$2*$A$3*$A$4*$A$5*$A$6*D24*E24 25 ='BB12'!A40 ='BB12'!E40 0.000000000103 =$A$2*$A$3*$A$4*$A$5*$A$6*D25*E25 26 ='BB12'!A41 ='BB12'!E41 0.00000000158 =$A$2*$A$3*$A$4*$A$5*$A$6*D26*E26 27 ='BB12'!A42 ='BB12'!E42 0.0000000000355 =$A$2*$A$3*$A$4*$A$5*$A$6*D27*E27 28 ='BB12'!A43 ='BB12'!E43 0.000000000332 =$A$2*$A$3*$A$4*$A$5*$A$6*D28*E28 29 ='BB12'!A44 ='BB12'!E44 0.00000000131 =$A$2*$A$3*$A$4*$A$5*$A$6*D29*E29 30 ='BB12'!A45 ='BB12'!E45 0.00000000181 =$A$2*$A$3*$A$4*$A$5*$A$6*D30*E30 31 ='BB12'!A46 ='BB12'!E46 0.000000000102 =$A$2*$A$3*$A$4*$A$5*$A$6*D31*E31 32 ='BB12'!A47 ='BB12'!E47 0.00000000107 =$A$2*$A$3*$A$4*$A$5*$A$6*D32*E32 33 ='BB12'!A48 ='BB12'!E48 0.00000000157 =$A$2*$A$3*$A$4*$A$5*$A$6*D33*E33 34 ='BB12'!A49 ='BB12'!E49 0.000000000659 =$A$2*$A$3*$A$4*$A$5*$A$6*D34*E34 35 ='BB12'!A50 ='BB12'!E50 0.0000000000117 =$A$2*$A$3*$A$4*$A$5*$A$6*D35*E35 36 ='BB12'!A51 ='BB12'!E51 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D36*E36 37 ='BB12'!A52 ='BB12'!E52 0.0000000000226 =$A$2*$A$3*$A$4*$A$5*$A$6*D37*E37 38 ='BB12'!A53 ='BB12'!E53 0.0000000000116 =$A$2*$A$3*$A$4*$A$5*$A$6*D38*E38 39 ='BB12'!A54 ='BB12'!E54 0.0000000112 =$A$2*$A$3*$A$4*$A$5*$A$6*D39*E39 40 ='BB12'!A55 ='BB12'!E55 0.000000351 =$A$2*$A$3*$A$4*$A$5*$A$6*D40*E40 41 ='BB12'!A56 ='BB12'!E56 0.000000000449 =$A$2*$A$3*$A$4*$A$5*$A$6*D41*E41 42 ='BB12'!A57 ='BB12'!E57 0.000000000218 =$A$2*$A$3*$A$4*$A$5*$A$6*D42*E42 43 ='BB12'!A58 ='BB12'!E58 0.00000000225 =$A$2*$A$3*$A$4*$A$5*$A$6*D43*E43 44 ='BB12'!A59 ='BB12'!E59 0.0000000000088 =$A$2*$A$3*$A$4*$A$5*$A$6*D44*E44 45 ='BB12'!A60 ='BB12'!E60 0.00000000255 =$A$2*$A$3*$A$4*$A$5*$A$6*D45*E45 46 ='BB12'!A61 ='BB12'!E61 0.0000000000344 =$A$2*$A$3*$A$4*$A$5*$A$6*D46*E46 47 ='BB12'!A62 ='BB12'!E62 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D47*E47 48 ='BB12'!A63 ='BB12'!E63 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D48*E48 49 ='BB12'!A64 ='BB12'!E64 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D49*E49 50 ='BB12'!A65 ='BB12'!E65 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D50*E50 51 ='BB12'!A66 ='BB12'!E66 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D51*E51 52 ='BB12'!A67 ='BB12'!E67 0.00000000228 =$A$2*$A$3*$A$4*$A$5*$A$6*D52*E52 53 ='BB12'!A68 ='BB12'!E68 0.0000000132 =$A$2*$A$3*$A$4*$A$5*$A$6*D53*E53 54 ='BB12'!A69 ='BB12'!E69 0.00000000000982 =$A$2*$A$3*$A$4*$A$5*$A$6*D54*E54 55 ='BB12'!A70 ='BB12'!E70 0.000000000211 =$A$2*$A$3*$A$4*$A$5*$A$6*D55*E55 56 ='BB12'!A71 ='BB12'!E71 0.00000000639 =$A$2*$A$3*$A$4*$A$5*$A$6*D56*E56 57 58 59 Total Rem =SUM(F13:F56)

Calc. No. L-003430, Rev. 0, Attachment C, C-19 of C-21

A B C D E F 1 Container Fire Event: Byron and Braidwood Isotopic: Table 11.1.10 2 0.00054 X/Q (sec/m^3) 3 0.00035 Breathing Rate (m^3/sec) 4 0.01 Release Fraction 5 3700000000000 Conversion Factor (rem/Ci per Sv/Bq) 6 6 Containers/Accident 7 200 Container Contact - Nominal Baseline Analysis (R/hr) 8 9 =F42 Total Inhalation Dose (rem) 10 11 60 day Decay 12 Isotope Ci in container InhaleDCF Dose (rem) 13 ='BB11'!A28 ='BB11'!E28 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D13*E13 14 ='BB11'!A29 ='BB11'!E29 0.00000000101 =$A$2*$A$3*$A$4*$A$5*$A$6*D14*E14 15 ='BB11'!A30 ='BB11'!E30 0.00000000294 =$A$2*$A$3*$A$4*$A$5*$A$6*D15*E15 16 ='BB11'!A31 ='BB11'!E31 0.0000000591 =$A$2*$A$3*$A$4*$A$5*$A$6*D16*E16 17 ='BB11'!A32 ='BB11'!E32 0.0000000000903 =$A$2*$A$3*$A$4*$A$5*$A$6*D17*E17 18 ='BB11'!A33 ='BB11'!E33 0.0000000125 =$A$2*$A$3*$A$4*$A$5*$A$6*D18*E18 19 ='BB11'!A34 ='BB11'!E34 0.00000000198 =$A$2*$A$3*$A$4*$A$5*$A$6*D19*E19 20 ='BB11'!A35 ='BB11'!E35 0.00000000863 =$A$2*$A$3*$A$4*$A$5*$A$6*D20*E20 21 ='BB11'!A36 ='BB11'!E36 0.000000000726 =$A$2*$A$3*$A$4*$A$5*$A$6*D21*E21 22 ='BB11'!A37 ='BB11'!E37 0.000000004 =$A$2*$A$3*$A$4*$A$5*$A$6*D22*E22 23 ='BB11'!A38 ='BB11'!E38 0.00000000158 =$A$2*$A$3*$A$4*$A$5*$A$6*D23*E23 24 ='BB11'!A39 ='BB11'!E39 0.00000000131 =$A$2*$A$3*$A$4*$A$5*$A$6*D24*E24 25 ='BB11'!A40 ='BB11'!E40 0.00000000181 =$A$2*$A$3*$A$4*$A$5*$A$6*D25*E25 26 ='BB11'!A41 ='BB11'!E41 0.00000000107 =$A$2*$A$3*$A$4*$A$5*$A$6*D26*E26 27 ='BB11'!A42 ='BB11'!E42 0.00000000157 =$A$2*$A$3*$A$4*$A$5*$A$6*D27*E27 28 ='BB11'!A43 ='BB11'!E43 0.00000000179 =$A$2*$A$3*$A$4*$A$5*$A$6*D28*E28 29 ='BB11'!A44 ='BB11'!E44 0.00000000000138 =$A$2*$A$3*$A$4*$A$5*$A$6*D29*E29 30 ='BB11'!A45 ='BB11'!E45 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D30*E30 31 ='BB11'!A46 ='BB11'!E46 0.00000000242 =$A$2*$A$3*$A$4*$A$5*$A$6*D31*E31 32 ='BB11'!A47 ='BB11'!E47 0.000000129 =$A$2*$A$3*$A$4*$A$5*$A$6*D32*E32 33 ='BB11'!A48 ='BB11'!E48 0.0000000112 =$A$2*$A$3*$A$4*$A$5*$A$6*D33*E33 34 ='BB11'!A49 ='BB11'!E49 0.000000351 =$A$2*$A$3*$A$4*$A$5*$A$6*D34*E34 35 ='BB11'!A50 ='BB11'!E50 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D35*E35 36 ='BB11'!A51 ='BB11'!E51 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D36*E36 37 ='BB11'!A52 ='BB11'!E52 0.00000000228 =$A$2*$A$3*$A$4*$A$5*$A$6*D37*E37 38 ='BB11'!A53 ='BB11'!E53 0.0000000132 =$A$2*$A$3*$A$4*$A$5*$A$6*D38*E38 39 ='BB11'!A54 ='BB11'!E54 0.00000000639 =$A$2*$A$3*$A$4*$A$5*$A$6*D39*E39 40 41 42 Total Rem =SUM(F13:F39)

Calc. No. L-003430, Rev. 0, Attachment C, C-20 of C-21

A B C D E F 1 Container Fire Event: Byron and Braidwood Isotopic: Table 12.2.13 2 0.00054 X/Q (sec/m^3) 3 0.00035 Breathing Rate (m^3/sec) 4 0.01 Release Fraction 5 3700000000000 Conversion Factor (rem/Ci per Sv/Bq) 6 6 Containers/Accident 7 200 Container Contact - Nominal Baseline Analysis (R/hr) 8 9 =F59 Total Inhalation Dose (rem) 10 11 60 day Decay 12 Isotope Ci in container InhaleDCF Dose (rem) 13 ='BB12'!A28 ='BB12'!E28 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D13*E13 14 ='BB12'!A29 ='BB12'!E29 0.00000000101 =$A$2*$A$3*$A$4*$A$5*$A$6*D14*E14 15 ='BB12'!A30 ='BB12'!E30 0.000000101 =$A$2*$A$3*$A$4*$A$5*$A$6*D15*E15 16 ='BB12'!A31 ='BB12'!E31 0.00000000294 =$A$2*$A$3*$A$4*$A$5*$A$6*D16*E16 17 ='BB12'!A32 ='BB12'!E32 0.0000000591 =$A$2*$A$3*$A$4*$A$5*$A$6*D17*E17 18 ='BB12'!A33 ='BB12'!E33 0.0000000125 =$A$2*$A$3*$A$4*$A$5*$A$6*D18*E18 19 ='BB12'!A34 ='BB12'!E34 0.00000000123 =$A$2*$A$3*$A$4*$A$5*$A$6*D19*E19 20 ='BB12'!A35 ='BB12'!E35 0.00000000198 =$A$2*$A$3*$A$4*$A$5*$A$6*D20*E20 21 ='BB12'!A36 ='BB12'!E36 0.00000000863 =$A$2*$A$3*$A$4*$A$5*$A$6*D21*E21 22 ='BB12'!A37 ='BB12'!E37 0.0000000000274 =$A$2*$A$3*$A$4*$A$5*$A$6*D22*E22 23 ='BB12'!A38 ='BB12'!E38 0.000000004 =$A$2*$A$3*$A$4*$A$5*$A$6*D23*E23 24 ='BB12'!A39 ='BB12'!E39 0.00000000889 =$A$2*$A$3*$A$4*$A$5*$A$6*D24*E24 25 ='BB12'!A40 ='BB12'!E40 0.000000000103 =$A$2*$A$3*$A$4*$A$5*$A$6*D25*E25 26 ='BB12'!A41 ='BB12'!E41 0.00000000158 =$A$2*$A$3*$A$4*$A$5*$A$6*D26*E26 27 ='BB12'!A42 ='BB12'!E42 0.0000000000355 =$A$2*$A$3*$A$4*$A$5*$A$6*D27*E27 28 ='BB12'!A43 ='BB12'!E43 0.000000000332 =$A$2*$A$3*$A$4*$A$5*$A$6*D28*E28 29 ='BB12'!A44 ='BB12'!E44 0.00000000131 =$A$2*$A$3*$A$4*$A$5*$A$6*D29*E29 30 ='BB12'!A45 ='BB12'!E45 0.00000000181 =$A$2*$A$3*$A$4*$A$5*$A$6*D30*E30 31 ='BB12'!A46 ='BB12'!E46 0.000000000102 =$A$2*$A$3*$A$4*$A$5*$A$6*D31*E31 32 ='BB12'!A47 ='BB12'!E47 0.00000000107 =$A$2*$A$3*$A$4*$A$5*$A$6*D32*E32 33 ='BB12'!A48 ='BB12'!E48 0.00000000157 =$A$2*$A$3*$A$4*$A$5*$A$6*D33*E33 34 ='BB12'!A49 ='BB12'!E49 0.000000000659 =$A$2*$A$3*$A$4*$A$5*$A$6*D34*E34 35 ='BB12'!A50 ='BB12'!E50 0.0000000000117 =$A$2*$A$3*$A$4*$A$5*$A$6*D35*E35 36 ='BB12'!A51 ='BB12'!E51 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D36*E36 37 ='BB12'!A52 ='BB12'!E52 0.0000000000226 =$A$2*$A$3*$A$4*$A$5*$A$6*D37*E37 38 ='BB12'!A53 ='BB12'!E53 0.0000000000116 =$A$2*$A$3*$A$4*$A$5*$A$6*D38*E38 39 ='BB12'!A54 ='BB12'!E54 0.0000000112 =$A$2*$A$3*$A$4*$A$5*$A$6*D39*E39 40 ='BB12'!A55 ='BB12'!E55 0.000000351 =$A$2*$A$3*$A$4*$A$5*$A$6*D40*E40 41 ='BB12'!A56 ='BB12'!E56 0.000000000449 =$A$2*$A$3*$A$4*$A$5*$A$6*D41*E41 42 ='BB12'!A57 ='BB12'!E57 0.000000000218 =$A$2*$A$3*$A$4*$A$5*$A$6*D42*E42 43 ='BB12'!A58 ='BB12'!E58 0.00000000225 =$A$2*$A$3*$A$4*$A$5*$A$6*D43*E43 44 ='BB12'!A59 ='BB12'!E59 0.0000000000088 =$A$2*$A$3*$A$4*$A$5*$A$6*D44*E44 45 ='BB12'!A60 ='BB12'!E60 0.00000000255 =$A$2*$A$3*$A$4*$A$5*$A$6*D45*E45 46 ='BB12'!A61 ='BB12'!E61 0.0000000000344 =$A$2*$A$3*$A$4*$A$5*$A$6*D46*E46 47 ='BB12'!A62 ='BB12'!E62 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D47*E47 48 ='BB12'!A63 ='BB12'!E63 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D48*E48 49 ='BB12'!A64 ='BB12'!E64 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D49*E49 50 ='BB12'!A65 ='BB12'!E65 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D50*E50 51 ='BB12'!A66 ='BB12'!E66 0.00E+00 =$A$2*$A$3*$A$4*$A$5*$A$6*D51*E51 52 ='BB12'!A67 ='BB12'!E67 0.00000000228 =$A$2*$A$3*$A$4*$A$5*$A$6*D52*E52 53 ='BB12'!A68 ='BB12'!E68 0.0000000132 =$A$2*$A$3*$A$4*$A$5*$A$6*D53*E53 54 ='BB12'!A69 ='BB12'!E69 0.00000000000982 =$A$2*$A$3*$A$4*$A$5*$A$6*D54*E54 55 ='BB12'!A70 ='BB12'!E70 0.000000000211 =$A$2*$A$3*$A$4*$A$5*$A$6*D55*E55 56 ='BB12'!A71 ='BB12'!E71 0.00000000639 =$A$2*$A$3*$A$4*$A$5*$A$6*D56*E56 57 58 59 Total Rem =SUM(F13:F56)

Calc. No. L-003430, Rev. 0, Attachment C, C-21 of C-21

Computer Disclosure Sheet Discipline Nuclear Client: Exelon Corporation Date: August 2009 Project: LaSalle Generating Station Job No. NCS0097 IRSF DesiQn Basis Event Dose Assessment Program(s) used Rev No. Rev Date Calculation Set No.: L-003430, Rev. 0 Excel for Attachment Spreadsheets NI A NIA Status [ ] Prelim.

[X] Final

[ ] Void URS Prequalification [ ] Yes

[X] No Run No.

Description:

Analysis

Description:

Spreadsheets were used to execute arithmetic manipulations of numbers, for various applications within the attachments of this analysis. As a first step, it was verified that the spreadsheets duplicated the calculated values. All of the inputs were checked for consistency with their source and their use, and all results were checked for consistency with expected values. Spreadsheet formula pages are included with the calculations.

The attached computer output has been reviewed, the input data checked, And the results approved for release. Input criteria for this analysis were established.

By: On: 8/2009 Run by: W. Golden ~tJrt--

Checked by: H. Rothstein

-~

~ ....~ ---

-.......- ..I (

Approved by: D. Gardner Remarks:

These spreadsheets were applied in a straight-forward manner and were hand checked.

Calc. No. L-003430, Rev. 0, Attachment 0, Page 0-1 of 0-2

Computer Disclosure Sheet Discipline Nuclear Client: Exelon Corporation Date: August 2009 Project: LaSalle Generating Station Job No. NCS0097 IRSF Design Basis Event Dose Assessment Program(s) used Rev No. Rev Date Calculation Set No.: L-003430, Rev. 0 Microshield 8.01 (MC-201) 0 4/2009 Status [ ] Prelim.

[X] Final

[ ] Void URS Prequalification [ X] Yes

[ ] No Run No.

Description:

Analysis

Description:

MicroShield was used to develop HIC isotope mixes and adjust them for decay and to produce a 200 R/hr HIC contact dose rate, for use of the resulting Curie levels for each isotope in the Excel spreadsheet. All of the inputs were checked for consistency with their source and their use, and all results were checked for consistency with expected values.

The attached computer output has been reviewed, the input data checked, And the results approved for release. Input criteria for this analysis were established.

By: On: 8/2009 Run by: W. Golden ~~ {,f2----

Checked by: H. Rothstein fl-./J ~~

. ~.." __ J7

~\i Approved by: D. Gardner Remarks:

The program was applied in a straight-forward manner and was hand checked.

Calc. No. L-003430, Rev. 0, Attachment D, Page D-2 of 0-2

ATTACHMENT 5 Calculation No. L-003429 LaSalle IRSF Storage Bay HIC Spacing to Prevent Spread of a Postulated HIC Fire

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-r~ '2-7'j?t A7T'IUIJ""'/tflJ~ J 7~11s Deslan Analysis Malor Revision Cover Sheet p~ lIB Design Analysis (Major Revfslon) I Last Page No. '181 Att. J-1 Analysls No.: I l-O<>3429 Revision:

• 000

Title:

3 IRSF Storage Bay HIC Spacing to Prevent Spread of a Postulated HIC Fire ECIECR No.:

• 375636 Revision:

• 0 Statlon(a): t laSalle County Station Component(8): ....

Unit No.:' 00 IV/i-Dlscfptlne:

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Deecrip.C~eyw~: ~ fo'2./ rot> ~IZSf' j

S81ety/QA ClMs: " Non-Safety System Code: 11 IJ/A--

Structure: " AI/If CONTROLLED DOCUMENT REFERENCES .,

Document No.: FromITo DocwnentNo.: FromITo GC- 31!J7., ~ {q 1ifonTr; /"mm

~ I"-

~ f:tem.

F-- filo8m-If yes. see SY -M-18 this Design Analysis Safeguards Information? It YeaD No~

101-106 If yes.

Does this Dealgn Analysis contain Unvarlt1ed Assumptions? " VEHID No 181 ATVAA#:

This D8fIlgn Analysis SUPERCEDES: It ~

Description of Revision (list affected pages for partJals): I*'nltlallssue Preparer: .. Noanl Propst Jau,qU- 01119.. foq P""'Name Sign_ 001t Method of RevIew:" Detailed Review ~ AlternAte CItIt:t,"1'lt!.,.,~ (!!tt<!che~) n Testing 0

SamDawoud.

Reviewer: UceMedFJre

n protection Engineer PnntNome

..44L ~ Nama Ill.-- tUfZ C)'1,10.,Q DaItl Review Not..: :n Independent reI/lew ~ Peer review 0 All inputs, assumptlons.

approaches, numerical analyses, and results were independently reviewed and checked.

IFtv' ~vt~:>tI ~ ...!C __ ~hl\

,. External Approver:" Donald Gardner Print ,.,...

Exelon Reviewer: 15 bf'/t" ~([P~ PrInt_

Independent arc! Party Review Reqd?

• Yesl8l t No 0

/4IW St:wAt1 ¥ ~:~

t Exelon Approver: tt Pl1o'l Home SIgn Name

• Comblned Independent 3 party Review I Chief Engineer Design Review prOVided by Gaines Bruce, Licensed FIre Protection !nglneer \

~)jr NIxIE / 1h 1$ t4!Hf" S, ~ (.I f M#f k/"~ f f41 w. et -- All ~ 30 ~ -[ dtJ I ,.u;. '5" ..

(c~~ tJ( +Iu ~ ~~) 1£4

r ~~1/~ CC-AA-309 Revision 9 Page 17 of 17 ATTACHMENT 1 Owners Acceptance Review Checklist for External Design Analysis Page 1 of 1 DESIGN ANALYSIS NO. t. '~()$I.f:J-? REV: 0 Yes No N/A

1. Do assumptions have sufficient rationale? 62J 0 0 Are assumptions compatible with the way the plant is operated and with the 2.

licensing basis? ~ 0 0

3. Do the design inputs have sufficient rationale? ~ 0 0 Are design inputs correct and reasonable with critical parameters identified, if 4.

appropriate? IA 0 0 Are design inputs compatible with the way the plant is operated and with the 5.

licensing basis? &:J 0 0

6. Are Engineering Judgments clearly documented and justified? ~ 0 0 Are Engineering Judgments compatible with the way the plant is operated 7.

and with the licensing basis? l2 0 0 Do the results and conclusions satisfy the purpose and objective of the

8. Design Analysis? ~ 0 0 Are the results and conclusions compatible with the way the plant is operated

9. and with the licensing basis? ~ 0 0 Does the Design Analysis include the applicable design basis 10.

documentation? f>ZI 0 0 Have any limitations on the use of the results been identified and transmitted 11.

to the appropriate organizations? 1KI 0 0

12. Are there any unverified assumptions? 0 ~ 0 Do all unverified assumptions have a tracking and closure mechanism in 13.

place? 0 0 ~

Have all affected design analyses been documented on the Affected 14.

Documents List (ADL) for the associated Configuration Change? ~ 0 0 Do the sources of inputs and analysis methodology used meet current technical requirements and regulatory commitments? (If the input sources or

15. analysis methodology are based on an out-of-date methodology or code, ~ 0 0 additional reconciliation may be required if the site has since committed to a more recent code)

Have vendor supporting technical documents and references (including GE 16.

DRFs) been reviewed when necessary? ~ 0 0 Have margin impacts been identified and documented appropria ely for any 17.

negative impacts (Reference ER-AA-2007)? 0 0 I)a..

EXELON REVIEWER: e/lkt- 73~-lt- DATE: tI  !~Io<J r'

CALCULATION No L-003429 REV. 000 PAGE iv TABLE OF CONTENTS OWNERS ACCEPTANCE REVIEW CHECKLIST FOR EXTERNAL DESIGN ANALYSIS ......... 3

1. PURPOSE AND OBJECTIVE ................................................................................................ 5

2. METHODOLOGY AND ACCEPTANCE CRITERIA .............................................................. 5

3. ASSUMPTION ........................................................................................................................ 6

4. DESIGN INPUT ...................................................................................................................... 7 4.1 HIC Dimension ............................................................................................................... 7 4.2 Pool Fire Diameter ......................................................................................................... 7 4.3 HDPE Properties ............................................................................................................ 9 4.4 Resins Properties ......................................................................................................... 10

5. REFERENCES ..................................................................................................................... 11

6. CALCULATIONS.................................................................................................................. 12 6.1 HIC Surface Area ......................................................................................................... 12 6.2 HDPE HIC Material Volume ......................................................................................... 12 6.3 Pool Fire Diameter ....................................................................................................... 13 6.4 Surface Area of Pool Fire............................................................................................. 13 6.5 Heat Release Rate Calculation (HHR)......................................................................... 13 6.6 Heat Release Rate per Unit Length of Fire Calculation ............................................... 13 6.7 Flame Height Calculation ............................................................................................. 14 6.8 Emissive Power............................................................................................................ 15 6.9 Minimum Spacing Calculation...................................................................................... 15 6.9.1 View Factor .................................................................................................................. 15

7.

SUMMARY

OF RESULTS AND CONCLUSIONS ............................................................... 18 ATTACHMENT A- CALCULATION SPREADSHEETS ...........................................................................................A-1 ATTACHMENT B - EMPTY HIC WEIGHT BASIS (ENERGY SOLUTIONS MEMO)..............................................B-1 ATTACHMENT C - POLYPROPYLENE MATERIAL PROPERTIES ......................................................................C-1 ATTACHMENT D - COMPILATION OF EXPERIMENTAL DATA...........................................................................D-1 ATTACHMENT E - HDPE PHYSICAL AND CHEMICAL DATA - MSDS EXTRACT .............................................E-1 ATTACHMENT F - THERMAL PROPERTIES OF COMMON SOLID COMBUSTIBLE MATERIALS .................... F-1 ATTACHMENT G - RESULTS FOR SEVERAL DIFFERENT MATERIALS CORRELATING THE FLUX TIME PRODUCT .............................................................................................................................................................. G-1 ATTACHMENT H - COLLECTION OF DATA BY TEWARSON GIVING MINIMUM HEAT FLUX AND THERMAL RESPONSE PARAMETER VALUES ......................................................................................................................H-1 ATTACHMENT J - COMPUTER DISCLOSURE SHEET........................................................................................ J-1

CALCULATION No L-003429 REV. 000 PAGE 5

1. PURPOSE AND OBJECTIVE This calculation was prepared for the Exelon Interim Radwaste Storage Facility (IRSF) at the LaSalle County Station, but it also applies to similar Exelon IRSFs such as at the Dresden and Quad Cities Stations.

These IRSFs serve as the interim storage facility for Low Level Radioactive Waste (LLRW). These facilities are not safety-related and have no safe-shutdown function for the nuclear plants they are associated with.

Currently, the IRSFs have several High-Density Polyethylene (HDPE) High-Integrity Containers (HICs) intended for long term storage. HDPE is considered a combustible material. Stored within these HDPE HICs are Class B and C radwaste resins, which contain approximately 40-50 percent water within the resin structure. The pure resin is also a combustible material.

A fire scenario in the IRSF storage area is not considered to be a realistic event, as there is no source for sustained ignition of the HDPE as would be required to initiate a fire in a HIC or group of stacked HICS. A stray spark landing on a HIC would be expected to self-extinguish rather than initiate a HIC fire. The HIC contents, with at least 40 percent water content, would be expected to smother the fire if it could reach them, rather than dry out and heat sufficiently from the energy release from a HDPE fire to reach the Auto-Ignition Temperature (AIT) and add to the fire loading. Sustainable ignition sources such as diesel fuel cannot be brought into the vicinity of the IRSF storage area; the adjacent truck bay is isolated from the storage area by thick concrete walls, with the only openings high above the floors of the truck bay and storage area. Any fire in the truck bay while manned for truck movement and unloading/loading due to the presence of transient combustibles would be extinguished by manual actions before the storage area could be affected. However, a fire is postulated to occur in the IRSF storage area for a group of HICS and their contents as a conservative measure. Currently, no automatic detection or suppression system is installed in the IRSF storage bay, and manual suppression systems are not credited because the postulated fire could be beyond the reach of human response due to storage area inaccessibility from the truck bay area. The purpose of this analysis is to determine a minimum horizontal separation distance between stored HICs to prevent spreading any postulated fire to another HIC or group of HICs in the IRSF storage area.

The postulated fire considered is conservatively of 3 bare (i.e., HDPE with no steel shell) double-stacked containers, for a total of 6 containers on fire. These containers are assumed to all be exposed to the fire simultaneously to form a pool fire diameter of 13.1 feet, according to the configuration layout as shown in Figures 1 and 2.

2. METHODOLOGY AND ACCEPTANCE CRITERIA This calculation is based on the methodology developed under Fire Dynamics Tools (FDT) Quantitative Fire Hazard Analysis Method for U.S. Nuclear Regulatory Commission Fire Inspection Program (NUREG -

1805, October 2004), Reference [1]. The NRC Section 5.3.2 method for Solid Flame Radiation Model equations for horizontal and vertical target orientations at ground level with no-wind conditions,,is the method that was applied, as the target HICs have exactly the same elevation as the HICs assumed to be on fire.

As mentioned above, no details of potential ignition sources are provided since the existing IRSFs have no possible fire exposure due to the isolation from humans or equipment failures, but the worst-case scenario is postulated with the assumption that a HIC group fire occurs. Radiative heat flux on a target HIC decreases with distance from burning HIC(s). The criteria for preventing ignition of the adjacent HIC is to specify the minimum distance that results in a maximum exposing radiative heat flux at a level below which ignition cannot occur. According to Janssens definition, the minimum heat flux for ignition, qmin(dot) is the heat flux below which the ignition under practical conditions (in bench scale test or a real fire) cannot occur (Reference [5] page 2).

The group of 6 HDPE HICs and their contained resin is assumed to be the combustible material involved in the fire.

CALCULATION No L-003429 REV. 000 PAGE 6

3. ASSUMPTION x The proposed HIC storage arrangement is shown in Figure 2.

x The area of fuel on fire is assumed to be a circular pool involving horizontal, upward facing, combustible fuel, which will form a dike or curing geometry. See Figures 1 and 2.

x The postulated fire is assumed to freely burn due to the configuration space available (there are no fire barriers to contain the fire). Oxygen depletion is not considered in this storage area. In addition, the HIC fire scenario is far from the storage area wall. Moisture effects on the fire are disregarded for conservatism.

x Although the IRFS is ventilated by a Heating, Ventilation, and Air Conditioning (HVAC) system to maintain a temperature range of approximately 45-120oF (see LaSalle IRSF LAR Support Technical Report Supporting EC DCR No. 375636, section 4.6 of Attachment E), the air flow rate in the vicinity of the HICs is low so the HVAC system is considered to not participate in the fire growth rate and a wind-free storage environment is assumed.

x A postulated piloted fire (i.e., with the presence of an ignition source) will start uniformly in one (1) bare HDPE HIC and then spread uniformly to five (5) other bare HICs, resulting in a fire configuration as shown on Figures 2 and 3 of three double-stacked HICs stored adjacent to each other. The pool fire diameter is assumed to form a circular area with all containers enclosed.

x There is conservatively no fire growth period; i.e., the maximum heat release rate (HRR) occurs instantaneously.

x The HICs are HDPE PL8-120B containers assumed to weight 950 lbs, per the manufacturer (although part of this weight includes internal dewatering legs that will be surrounded by resin, for conservatism, the calculation includes the dewatering legs participation in the fire analysis). See Attachment B- Empty HIC Weight Energy Solutions Memo.

x The HDPE empirical constant k is assumed to have a value of 100 m-1 as a conservative estimate since the exact values are not defined according to Reference [1]. The Attachment C-Polypropylene Material Property value is utilized, as the most similar to HDPE of those listed. This empirical constant is used to calculate the Heat Release Rate.

x The heat dissipated vertically (convection energy release rate) is conservatively assumed to be 40% of the total heat generated; the heat dissipated by radiation to the surrounding HICs is conservatively assumed to be 30% of the total heat generated; furthermore, 30% of the total heat generated is assumed to sustain the combustion reaction, Reference [2].

CALCULATION No L-003429 REV. 000 PAGE 7

4. DESIGN INPUT 4.1 HIC Dimension A standard HDPE PL8-120 container dimension is 61 inches (1.55 meter) diameter, 74.5 inches (1.90 meter) high, and 1/2 inch (12.7 mm) thick (see Attachment B). The HDPE HIC total weight is 950 lbs (430.91 kg). These containers are equipped with grapple-able lifting steel elements that support the weight when the container is lifted. A steel stacking plate is used for the two-high stackable basket support.

The container is determined to be a thermally thick inert solid, as per the following formula, Reference [5]:

Lo/ (tig)  4

 = thermal diffusivity, evaluated at the ignition tig = ignition temperature (oC)

Lo = thickness of the solid (m)

Where

 = k/Uc The thermal inertia, kUc, is 1.57 kW2s/m4K2 (see Attachment D - Compilation of Experimental Data).

4.2 Pool Fire Diameter It is assumed that HDPE will melt and burn forming a pool fire. See Figure 1, extracted from Reference [8].

POOL FIRE DIAMETER Figure 1 A combined pool fire diameter for three double-stacked adjacent HICs simultaneously burning is 13.1 ft.

See Figure 2.

CALCULATION No L-003429 REV. 000 PAGE 8 Figure 2 - HIC Configuration on IRSF Storage Bay Q(dot),Heat Release Rate (HRR)

Air Entrainment q(dot), Heat Flux to Surface Fuel m(dot)

Figure 3 -Features of a Pool Fire Reference [1], section 3-7

CALCULATION No L-003429 REV. 000 PAGE 9 4.3 HDPE Properties HDPE material properties are obtained from multiple references, and multiple values of the same material property can change the results of this calculation. For this reason, a safety factor is included in the calculations and for some material property values to provide a conservative value of the minimum safe distance required to prevent ignition by radiative heat in the adjacent uninsulated HIC.

x The specific gravity of HDPE is approximately 0.965, Reference [3]. See Attachment E- HDPE Physical and Chemical Data.

x The flash point temperature obtained experimentally is 608oF (320oC), Reference [5]. See Attachment D- Compilation of Experimental Data.

x The mass burning rate of fuel, m, is 0.018 kg/m2sec, Reference [1] , See Attachment C, Table 3-2 Large-Pool Fire Burning Rate Data. This value for HDPE is based on polypropylene similar properties.

x The complete heat of combustion of polyethylene is 46,500 kJ/kg, Reference [1], Table 8-1 Thermal Properties of Common Solid Combustible Material. See Attachment F- Thermal Properties of Common Solid Combustible Materials. This value is conservatively used as the effective heat of combustion of polyethylene. The difference between the complete heat of combustion and effective heat of combustion according to Reference [1], page 3-5, is that the complete heat of combustion leaves no residual fuel and releasing all of the chemical energy of the material ,instead of the effective heat of combustion, the measured of energy released when combustion is not necessarily complete and some residue remains.

x The empirical constant k is assumed to be 100 m-1 for conservatism based on polypropylene similar properties, Reference [1] Table 3-2 Large-Pool Burning Rate Data (Babrauskas, 2002, © SFPE). See Attachment C -Polypropylene Material Property.

x Material properties values are based on tests from a quiescent environment using a blackened material surface to maximize the surface absorptivity, thus minimizing the ignition temperature and the minimum heat flux for ignition, Reference [5]. Therefore, these values obtained by Reference [5]

are considered conservative. According to SFPE, Reference [5] pg 2, the values used in this calculation are considered conservative, and no additional safety factor is necessary for the minimum allowable radiation to prevent ignition x The lowest thermal load per unit area of initiating a combustion reaction on the HDPE is given by the critical heat flux, qcrit(dot), and this value is 6.2 kW/m2 , Reference [1] table 3. See Attachment D- Results from Several Different Materials Correlated Using the Flux Time Product.

x The minimum heat flux for ignition, qmin(dot), is 15 kW/m2, Reference [5] table 1. See Attachment H- Collection of Data by Tewarson Giving Minimum Heat Flux and Thermal Response Parameter Values.

x One-dimensional heat transfer through the solid with radiant heating on the surface.

x The radiative fraction, FUis 0.3, Reference [2].

x The thermal conductivity is 0.45 W/m K, and the specific heat is 1,900J/ K kg, reference [6].

x The thermal inertia is 1.57 (kW/m2 K)2, Reference [5]. See Attachment D.

CALCULATION No L-003429 REV. 000 PAGE 10 4.4 Resins Properties For conservatism, the resins material properties are assumed to be the same as HDPE material properties.

The maximum mass of resins stored in a HIC is approximately 6,500 lb.

CALCULATION No L-003429 REV. 000 PAGE 11

5. REFERENCES

[1] Fire Dynamics Tools (FDTs): Quantitative Fire Hazard Analysis Methods for the U.S. Nuclear Regulatory Commission Fire Protection Inspection Program, NUREG-1805, NRC, N. Iqbal, M.H.

Salley, October 2004.

[2] Introduction to Fire Dynamics 2nd edition, Dougal Drysdale 1999.

[3] High Density Polyethylene Material Safety Data Sheet, National Petochemical Company, Edit No.

01, ET/HSE/050.

[4] Fire Protection Handbook edition 19, A. Cote, C. Grant, J. Raymond Hall. NFPA, 2003.

[5] Engineering Guide: Piloted Ignition Solid Materials Under Radiant Exposure, SFPE, January 2002.

[6] Test on Flammability of Polyethylene, P.S. Flower, December 21, 2004.

[7] Powdex PCM Material Safety Data Sheet, Graver Technologies.

[8] Heat Release Rate Test of Plastic Trash Containers, D.W. Stroup and D. Madrzykowski, U.S.

Department of Commerce National Institute of Standards and Technology, April 24, 2003.

[9] Waste Containers for Extended Storage of Class A, B and C Wastes, EPRI, Rev 1.

CALCULATION No L-003429 REV. 000 PAGE 12

6. CALCULATIONS Note:

The values determined in this analysis were calculated using a MicrosoftTM ExcelTM spreadsheet, and are calculated to a greater number of significant figures than presented in this document. Full details of the equations and analysis can be seen by referring to the spreadsheet included as Attachment A.

Conversion Factors Table 7.1 To Convert from To Multiply by Feet Meter = 0.3048 Pounds Mass Kilogram = 0.45359 o o F C = 5/9oF - 32 BTU/lb kJ/kg = 2.325 kW BTU/sec = 0.94782 kW/m2 BTU/ft2 sec = 0.08805 Estimating Radiant Heat Flux from Fire to a Target Fuel at Ground Level under Wind-Free Condition Point Source Radiant Model (Reference [1], Spreadsheet 05.1 Heat Flux Calculation Wind Free, Solid Flame 1)

The following methods are carefully selected using professional judgment to ensure both conservatism in results and industry-expert and NRC acceptability.

6.1 HIC Surface Area Cylinder Surface Area AHIC = (2S r2 + 2S rhc)

Where, AHIC = surface area of pool fire of one HIC (m2) r = d/2 = radius of the container (m) hc = height of the container (m)

AHIC = (2S (1.55 m/ 2) 2 + 2S (1.55 m/2) * (1.89 m)) = 12.97 m2 6.2 HDPE HIC Material Volume Volume of an empty cylinder V = volume of sides + volume of top and bottom

= (S (r2 - ro2 )hc) + (2 S r2 T)

Where, V = volume of the container (m3) r = d/2 = radius of the container (m) ro = ( r - T)= empty radius of the container (m)

T = thickness of the container (m) hc = height of the container (m)

CALCULATION No L-003429 REV. 000 PAGE 13 V = S ((0.77 m)2- (0.77 m-0.0127 m)2) *(1.89 m) + 2 S(0.77 m)2 * (0.0127 m)

=0.16 m3 6.3 Pool Fire Diameter A pool fire diameter based on a circular shape is determined assuming that all 6 HICs burn together forming a large dike diameter on the floor. See Figure 2.

D = 3.99 m 6.4 Surface Area of Pool Fire HDPE material decomposes in a manner similar to liquids forming a horizontal, upward-facing pool fire. Since in this case six containers are simultaneously burning, it is predicted that an addition of all the containers will form a single combined cylinder area of pool fire.

Adike = 2S R2 Where, Adike = surface area of pool fire of combined HICs (m2)

R = D/2 = radius of circle formed by all the containers (m), see Figure [2].

Adike = (2S (3.99 m/ 2) 2 = 12.52 m2 6.5 Heat Release Rate Calculation (HHR)

The average burning rate of combustible materials has been experimentally determined in free-burning tests. The burning rate is reported as horizontal burning area in units of kg/m2-sec.

Q(dot) = m Hc,eff (1 - e-k D) Adike Where, Q(dot) = pool fire heat release rate (kW) m = mass burning rate of fuel per unit surface area (kg/m2-sec)

Hc,eff = effective heat of combustion of fuel (kJ/kg)

Adike = surface area of pool fire (area involved in vaporization) (m2) k = empirical constant (m-1)

D = diameter of pool fire (diameter involved in vaporization, circular pool is assumed) (m)

Q(dot) = (0.018 kg/m2sec) * (46,500 kJ/kg) *(1 - e-100 m-1

• 3.99 m) * (12.52 m2) =

10, 480.64 kW

• 0.94782 = 9,934 Btu/sec The HDPE container HHR is 10,480.64 kW ( ~10.5 MW).

6.6 Heat Release Rate per Unit Length of Fire Calculation The HHR per unit length can be calculated assuming the horizontal fire source length.

l x w = Adike = 12.52 m2

CALCULATION No L-003429 REV. 000 PAGE 14 l= (12.52 m2) = 3.54 m Q = Q(dot) /l Q = 10,480.64 kW / 3.54 m = 2,961.81 kW/m 6.7 Flame Height Calculation The flame height depends on whether the flame is laminar or turbulent. Laminar flames are shorter than turbulent flames. As a plume of hot gases rises above a flame, the temperature, velocity and width of the plume changes as the plume mixes with the surroundings. The height and temperature of the flame are important in estimating the ignition of adjacent combustibles. Flame height is defined as the flame observed at least 50 percent of the time. See Figure 3, extracted from Reference [8].

FLAME HEIGHT Figure 3 Several calculation methods are available for determining this flame height; the Heskestad method is used in this calculation as evaluation shows that it provides conservative results.

Heskestad Method (1995)

Hf = 0.235 Q(dot)2/5 - 1.02 D Where, Hf = flame height (m)

Q(dot) = heat release rate of the fire (kW)

D = Diameter of pool fire (m)

Hf = 0.235 (10,480.64 kW )2/5 - 1.02 (3.99 m) = 5.46 m

• 3.281 = 13.98 ft

CALCULATION No L-003429 REV. 000 PAGE 15 6.8 Emissive Power Emissive Power is the total radiative power leaving the surface of the fire per unit area per unit time based on Stefans law. Since the temperature is not well defined, Shokri and Beyler (1989) correlated experimental data of flame radiation to external targets in terms of an average power of the flame. For conservatism, the HDPE container is assumed to be a black body, having a cylindrical flame, acting as a homogeneous radiator with an average emissive power. Emissive power is inversely dependent on the pool diameter only, as follows:

E = 58 (10-0.00823D)

Where, E = Flame emissive power (kW/m2)

D= diameter of pool fire (m)

E = 58 (10-0.00823 x 3.99 m) = 53.77 kW/m2

• 0.08805 = 4.74 Btu/ft2sec The flame emissive power is calculated to be 4.74 Btu/ft2sec (53.77 kW/m2) and represents the average emissive power over the whole flame.

6.9 Minimum Spacing Calculation 6.9.1 View Factor The configuration factor is a geometrical value that provides the fraction of the radiation leaving one surface that strikes another surface directly. The value varies between 0 and 1 according to the target location, flame height, and pool fire diameter. When a target approaches the flame, the configuration factor approaches 1. The flame is based on a cylindrical shape (see Figure 4). The target containers are at the same ground level as the burning containers, therefore the following are considered:

CALCULATION No L-003429 REV. 000 PAGE 16 Source Flame Radiation Receiving Target E

Hf Flame Radiation q(dot)

L R

Figure 4 q(dot) = E*F12, Max (no wind) or F12, Max (no wind) = q(dot)/E Where, q(dot) = incident radiative heat flux or critical heat flux (kW/m2)

E = average emissive power at flame surface (kW/m2)

F12, Max (no wind) = configuration factor 2 2 F12, Max (no wind) = 15 kW/m / 53.77 kW/m = 0.279 Since the configuration factor is considered a 2-dimensional value, the following equations describe the horizontal and vertical behavior of the configuration fraction.

F12, Max (no wind) =  (F12, H2 + F12, V2 )

F12, H = (B-1/S) tan-1 (B+1)*(S-1) - (A -1/S) tan-1 (A+1)*(S-1)

S(B2-1) (B-1)* (S+1) S (A2-1) (A-1)* (S+1)

F12, V = 1 tan-1 h - h tan-1 (S-1) + Ah tan-1 (A+1)*(S-1)

SS (S2-1) SS (S+1) SS(A -1) 2 (A-1)* (S+1)

Where A, B, S, and h are mathematical constants and calculated as follows:

A = h2 + S2 +1 , B = 1 + S2 , S = 2R , h= 2Hf 2S 2S D D R = the distance between the center of the cylinder (flame) to the target (m)

CALCULATION No L-003429 REV. 000 PAGE 17 Hf = the height of the cylinder (flame) (m)

D = the cylinder (flame) diameter (m)

These values are determined when the distance between the center of the cylinder flame to the target, R, is known. The following describes the relation between R and L according to Figure 4.

R = L + D/2 Where, R= distance from center of the pool fire to edge of the target (m)

L = distance between pool fire and target (m)

D = pool fire diameter (m)

In this case, these values are unknown; therefore, due to the complexity of this mathematical equation, Excel goal seeking is used to calculate both vectors F12, H and F12, V, and the minimum distance R. The following are the results obtained (see Attachment A):

L= 2.022m / 0.3048 = 6.64 ft R = 2.022 m + 3.99m/2 = 4.019m /0.3048 = 13.19 ft h= (2*(5.46m))/3.99 m = 2.735 S= 2* (4.019 m) /3.99 m = 2.013 A = ( (2.013)2 +( 2.735)2 + 1)/ (2* 2.013) = 3.113 B= (1 + 2.0132 )/ (2

• 2.013) = 1.255 F12, H = (1.255-1/2.013) tan-1 (1.255+1)*( 2.013-1) - (3.113 -1/2.013) tan-1 (3.113+1)*( 1.255-1)

S(1.2552-1) (1.255-1)* (2.013+1) S (3.113 2-1) (3.113-1)* (1.255+1)

= 0.141 F12, V = 1 tan-1 2.735 - (2.735) tan-1 (2.013-1) + 3.113*(2.735) tan-1 (3.113+1)*( 2.013-1) 2 S*2.013 (2.013 -1) S*2.013 (2.013+1) S*2.013(3.1132-1) (3.113-1)* (2.013+1)

= 0.242 F12, Max (no wind) =  (0.1412 + 0.2422 ) = 0.280 The results indicate that the minimum safe distance from the edge of a container to the edge of the other container is 6.64 ft (2.022 m).

Following the spreadsheet and its formula version, Attachment A also contains this minimum spacing calculation and other calculated fire parameters of interest.

CALCULATION No L-003429 REV. 000 PAGE 18

7.

SUMMARY

OF RESULTS AND CONCLUSIONS This analysis determined a conservative spacing of bare HDPE HICs such that a postulated fire burning the containers for 3 HICs double-stacked would not spread to adjacent bare HDPE HICs. The methodology selected is based on the Fire Dynamics Tools (FDTs)-NUREG 1805, Reference [1], Spreadsheet 05.1 Heat Flux Calculation Wind Free, Solid Flame 1, based on the cylindrical configuration of the fire and same elevation level as the target. The level of conservatism includes significant safety factors for these geometrical configuration calculated values, since conservative material properties, design layout and method of approach are taken into account. The following list summarizes some of the conservative numbers in this calculation:

x The postulated fire consists of 6 HICs with all of their HDPE considered to be included as the fire source x The value of the minimum heat flux for ignition is obtained from the SFPE Engineering Guide for piloted ignition and based on a blackened surface to maximize the surface absorptivity, which, per the Guide, is conservative and therefore no additional safety factor is necessary for the minimum allowable radiation to prevent ignition.

x No fire growth period.

x Use of the 100 m-1 as the empirical constant.

x One dimensional heat transfer through the solid with radiant heating on the surface.

x Effective Heat of Combustion 46,500 kJ/kg.

x Diameter of pool fire is 13.1 feet.

The result is that maintaining a minimum distance of approximately 6.64 feet (2.0222 m) between adjacent bare HDPE HICs should ensure that even an incredible fire completely consuming a group of 3 HICs double-stacked would not spread to adjacent bare HDPE HICs in an IRSF.

CALCULATION No L-003429 REV. 000 PAGE A- 1 ATTACHMENT A- CALCULATION SPREADSHEETS Excel Spreadsheet Calculation (Separate File)

A B C D E F G H I J K L M N 1

2 Exelon IRSF August 6, 2009 3

4 5

6 7 ESTIMATING RADIANT HEAT FLUX FROM FIRE TO A TARGET FUEL AT GROUND LEVEL UNDER WIND-FREE CONDITION POINT SOURCE RADIATION MODEL 8 3 CONTAINERS ON FIRE - DOUBLE-STACKED 9 Entered by User 10 Fuel Properties 11 Calculated 12 13 INPUT PARAMETERS 14 15 16 HIC Diameter 5.08 ft 1.55 m 17 Pool of Fire Diameter (6 HICs) 13.1 ft 3.99 m 18 HIC Height 6.21 ft 1.89 m 19 Thickness of Container 0.0417 ft 0.013 m 20 Radiatice FractionFr 0.3 o

21 Initial Temperature (To) 77 oF 25 C 22 23 THERMAL PROPERTIES Minimum Heat Heat of Thermal Flux for Ignition Thermal TRP Flux Time Mass Burning Rate Combustion Empirical Critical Heat Density Conductivity Specific Heat Ignition q"min(dot) inertia (kW/m 2s1/2)( Product 2 -1 2 3 -1 o -1 o -1 -1 o 2 2 2 24 Fuel m"(kg/m -sec) Hc,eff (kJ/kg) Constant k (m ) Flux (kW/m ) (kg/m ) (Wm K ) (J K kg ) Temp ( C) (kW/m ) (kW/m K) flamm) Index (n) 25 High Density Polyethylene 0.018 46500 100 6.2 965 0.45 1900 320 15 1.57 321 1 26 Resins 0.018 46500 100 6.2 965 0.45 1900 320 15 1.57 321 1 27 28 29 Radius of the Container 2.5 ft 0.77 m 30 Radius of the Pool Fire 6.6 ft 2.00 m 31 HIC Surface Area(A HIC) 139.64 ft2 12.97 m2 32 Fuel Area or Dike Area (A dike) 134.78 ft2 12.52 m2 33 Volume of the Container 5.79 ft3 0.16 m3 34 35 Mass Burning Rate of Fuel (m") 0.018 kg/m2-sec 36 Effective Heat of Combustion of Fuel (H c,eff) 46,500 kJ/kg 37 Empirical Constant (k) 100 m-1 o

38 Air Density at 25 C 1.184 kg/m3 39 40 41 ESTIMATING RADIATIVE HEAT FLUX TO A TARGET FUEL 42 43 Pool Fire Diameter Calculation 44 45 46 D= 3.99 m 13.10 ft 47 48 Heat Release Rate Calculation

-kED 49 Q(dot) = m"'Hc,eff (1 - e ) Adike 50 Where Q(dot) = pool fire heat release rate (kW) 51 m" = mass burning rate of fuel per unit surface area (kg/m 2-sec) 52 'Hc = effective heat of combustion of fuel (kJ/kg) 2 53 Adike = surface area of pool fire (area involved in vaporization) (m )

-1 54 kE= empirical constant (m )

55 D = diameter of pool fire (diameter involved in vaporization, circular pool is assumed) (m) 56 HRR 57 Q(dot) = 10,480.64 kW 9,934 Btu/sec 58 59 Heat Release Rate Per Unit Length of Fire Calculation 60 Q'= Q/l 61 Where Q' = heat release rate per unit leght (KW/m) 62 Q(dot) = fire heat release rate of the fire (kW) 63 l = length of the fire source (m) 64 65 Fire Source Length Calculation 66 l x w = Adike 67 68 l= 3.54 m 69 70 Q' = 2,961.81 kW/m 71

A B C D E F G H I J K L M N 72 Flame Height Calculation 73 74 Heskestad Method (1995) 75 76 Hf = 0.235 Q (dot)2/5 - 1.02 D 77 78 Where, 79 Hf = flame height (m) 80 Q(dot) = heat release rate of the fire (kW) 81 D =Diameter of pool fire(m) 82 83 Hf 5.46 m 17.91 ft 84 85 86 Thomas Method (1962) 87 0.61 88 Hf = 42 x D[ m/ (Ua (g x D))]

89 90 Where, 91 Hf = flame height (m) 92 D = Diameter of pool fire (m) 93 g= gravitational acceleration (m/sec 2) 94 Ua = ambient air density (kg/m 3) 95 96 Hf 4.26 m 13.98 ft 97 98 Emissive Power

-0.00823D 99 E = 58 (10 )

2 100 Where, E = Flame emissive power (kW/m )

101 D= diameter of pool fire (m) 102 2 2 103 E= 53.77 kW/m 4.74 Btu/ft -sec 104 105 106 Distance from the Center of the Pool Fire to Edge of the Target Calculation 107 108 R = L + D/2 109 Where R = distance from center of the pool fire to edge of the target (m) 110 L = distance between pool fire and target (m) 111 D = pool fire diameter (m) 112 113 R= 4.019 m 13.19 ft Goal seek method 114 115 L= 2.022 m 6.64 ft R is obtained by manually inserting the view factor calculated value (C155 cell has to be 116 equal to C129 cell) in the "goal seek" under tools by varing the R (C133) 117 View Factor 118 119 q" = E*F1->2,Max 120 or 121 F1->2,H = q"/E 122 Where, 123 F1->2,H = configuration factor 124 q" = incident radiative heat flux or critical heat flux (kW/m 2) 125 E = emissive power 126 127 F1->2,Max 0.279 128 2 1/2 129 F1->2,H = (B-1/S)/S(B -1) tan ((B+1) (S-1)/(B-1)(S+1)) 1/2-(A-1/S)/(S(A2-1)1/2) tan-1 ((A+1)(S-1)/(A-1)(S+1)) 1/2

-1 130 F1->2,V = 1/(SS) tan-1(h/(S2-1)1/2)-(h/SS) tan-1 ((S-1)/(S+1)) 1/2 + Ah/SS(A2-1)1/2 tan-1 ((A+1)(S-1)/(A-1)(S+1)) 1/2 2 2 131 A= (h +S +1)/2S 132 B= (1+S2)/2S 133 S= 2R/D 134 h= 2Hf/D 135 F1->2,max = (F21->2,H + F21->2,V) 136 137 Where F1->2,H = horizontal view factor 138 F1->2,V = vertical view factor 139 F1->2,max = maximum view factor 140 R = distance from center of the pool fire to edge of the target (m) 141 Hf = height of the pool fire flame (m) 142 D = pool fire diameter (m) 143 144 145 146 S= 2.013 147 h= 2.735 148 A= 3.113 149 B= 1.255 150 151 F1->2,H = 0.141 152 F1->2,V = 0.242 153 F1->2,Max = 0.280 Check Value. Proceed if value is in the +/-5% error range 154

A B C D E F G H I J K L M N 155 Table of Distance vs Emissive Power Where the Pool Diameter Varies 156 Emmisive Power 2

157 Pool Fire Diameter (m) R L (kW/m ) View Factor S h A B F1->2,H F1->2,V F1->2,Max 158 12.50 8.16 1.91 45.77 0.328 1.306 0.874 1.328 1.036 0.231 0.371 0.437 159 12.00 7.92 1.92 46.20 0.325 1.319 0.910 1.352 1.039 0.228 0.367 0.432 160 11.50 7.67 1.92 46.64 0.322 1.333 0.950 1.380 1.042 0.225 0.364 0.428 161 11.00 7.41 1.91 47.09 0.319 1.347 0.993 1.411 1.045 0.223 0.360 0.424 162 10.50 7.15 1.90 47.53 0.316 1.362 1.040 1.445 1.048 0.220 0.356 0.419 163 10.00 6.90 1.90 47.99 0.313 1.379 1.092 1.484 1.052 0.217 0.352 0.414 164 9.50 6.64 1.89 48.44 0.310 1.397 1.149 1.529 1.057 0.214 0.348 0.409 165 9.00 6.38 1.88 48.91 0.307 1.417 1.213 1.581 1.061 0.211 0.343 0.403 166 8.50 6.11 1.86 49.37 0.304 1.438 1.285 1.641 1.067 0.208 0.339 0.397 167 8.00 5.84 1.84 49.84 0.301 1.461 1.365 1.710 1.073 0.205 0.334 0.392 168 7.50 5.57 1.82 50.32 0.298 1.486 1.456 1.793 1.079 0.202 0.329 0.385 169 7.00 5.29 1.79 50.79 0.295 1.513 1.560 1.891 1.087 0.198 0.323 0.379 170 6.50 5.00 1.75 51.28 0.293 1.540 1.680 2.011 1.095 0.196 0.318 0.373 171 6.00 4.72 1.72 51.77 0.290 1.573 1.820 2.157 1.104 0.192 0.312 0.366 172 5.50 4.42 1.67 52.26 0.287 1.609 1.985 2.340 1.115 0.188 0.305 0.359 173 5.00 4.12 1.62 52.76 0.284 1.648 2.184 2.575 1.127 0.185 0.298 0.351 174 4.50 3.81 1.56 53.26 0.282 1.693 2.427 2.881 1.142 0.181 0.291 0.343 175 4.00 3.49 1.49 53.77 0.279 1.744 2.730 3.296 1.159 0.176 0.283 0.334 176 3.50 3.15 1.40 54.28 0.276 1.801 3.120 3.880 1.178 0.172 0.275 0.324 177 3.00 2.79 1.29 54.79 0.274 1.863 3.640 4.756 1.200 0.168 0.266 0.315 178 2.50 2.42 1.17 55.32 0.271 1.937 4.368 6.151 1.227 0.163 0.257 0.304 179 2.00 2.02 1.02 55.84 0.269 2.015 5.460 8.652 1.256 0.158 0.247 0.293 180 1.50 1.58 0.83 56.37 0.266 2.107 7.280 13.870 1.291 0.153 0.237 0.282 181 1.00 1.10 0.60 56.91 0.264 2.193 10.920 28.511 1.325 0.148 0.228 0.272 182 183 Emmisive Power vs. Target Distance Varing Pool Fire Diameter 184 185 186 187 188 58.00 Emmisive Power (kW/m2) 189 190 55.00 191 192 193 52.00 194 195 49.00 196 y = -60.197x5 + 363.28x4 - 851.96x3 + 963.72x2 - 525.63x + 166.96 197 198 46.00 R2 = 0.99 199 200 43.00 201 202 40.00 203 204 0 1 1 2 2 3 205 L -Distance Between the Edge of the Cylinder (flame) to the Target (m) 206 207 208 209 Evaluation of the Distance Impact in Terms of Configuration Factor 210 Emmisive Power 2

211 Pool Fire Diameter (m) R L (kW/m ) S h A B F1->2,H F1->2,V F1->2,Max 212 9.63 20.50 15.69 48.33 4.258 1.134 2.397 2.246 0.007 0.046 0.047 213 9.63 20.00 15.19 48.33 4.154 1.134 2.352 2.197 0.008 0.049 0.049 214 9.63 19.50 14.69 48.33 4.050 1.134 2.307 2.148 0.009 0.051 0.052 215 9.63 19.00 14.19 48.33 3.946 1.134 2.263 2.100 0.010 0.054 0.055 216 9.63 18.50 13.69 48.33 3.842 1.134 2.219 2.051 0.010 0.057 0.058 217 9.63 18.00 13.19 48.33 3.738 1.134 2.175 2.003 0.011 0.061 0.062 218 9.63 17.50 12.69 48.33 3.634 1.134 2.132 1.955 0.013 0.064 0.065 219 9.63 17.00 12.19 48.33 3.531 1.134 2.089 1.907 0.014 0.068 0.070 220 9.63 16.50 11.69 48.33 3.427 1.134 2.047 1.859 0.015 0.073 0.074 221 9.63 16.00 11.19 48.33 3.323 1.134 2.005 1.812 0.017 0.077 0.079 222 9.63 15.50 10.69 48.33 3.219 1.134 1.965 1.765 0.019 0.083 0.085 223 9.63 15.00 10.19 48.33 3.115 1.134 1.925 1.718 0.021 0.088 0.091 224 9.63 14.50 9.69 48.33 3.011 1.134 1.885 1.672 0.023 0.095 0.097 225 9.63 14.00 9.19 48.33 2.908 1.134 1.847 1.626 0.026 0.101 0.105 226 9.63 13.50 8.69 48.33 2.804 1.134 1.810 1.580 0.029 0.109 0.113 227 9.63 13.00 8.19 48.33 2.700 1.134 1.773 1.535 0.033 0.118 0.122 228 9.63 12.50 7.69 48.33 2.596 1.134 1.738 1.491 0.038 0.127 0.132 229 9.63 12.00 7.19 48.33 2.492 1.134 1.705 1.447 0.043 0.137 0.144 230 9.63 11.50 6.69 48.33 2.388 1.134 1.673 1.404 0.049 0.149 0.157 231 9.63 11.00 6.19 48.33 2.285 1.134 1.643 1.361 0.056 0.162 0.171 232 9.63 10.50 5.69 48.33 2.181 1.134 1.614 1.320 0.065 0.176 0.188 233 9.63 10.00 5.19 48.33 2.077 1.134 1.589 1.279 0.075 0.192 0.206 234 9.63 9.50 4.69 48.33 1.973 1.134 1.566 1.240 0.087 0.210 0.227 235 9.63 9.00 4.19 48.33 1.869 1.134 1.546 1.202 0.102 0.230 0.251 236 237 Distance From Edge of The Source to Edge of Target vs 238 239 Configuration Factor 240 241 0.300 Configuration Factor 242 y = 1.8093x -1.3047 0.250 243 0.200 R2 = 0.9931 244 245 0.150 246 247 0.100 248 0.050 249 0.000 250 0.00 2.00 4.00 6.00 8.00 10.00 12.00 14.00 16.00 18.00 251 252 L -Distance from Edge of the Pool Fire to the Edge of the Target (m) 253 254

A B C D E F G H I J K L M N 255 256 257 258 ESTIMATING BURNING DURATION OF SOLID COMBUSTIBLES 259 260 The following calculations provides an approximation of the burning duration of solid combustibles based on free 261 burning rate with a given surface area.

262 Green boxes are inputs 263 264 INPUT PARAMETERS 265 266 Mass of Solid Fuel (m solid) 950 lb 430.91 kg 267 Mass of Resins(msolid) 6500 lb 2,948.3 kg 2

268 HIC exposed Floor Area of Fu 137.6 ft2 12.78 m 269 IRSF Storage Area 5700 ft2 529.55 m2 270 271 272 THERMAL PROPERTIES OF SOLID COMBUSTIBLE MATERIALS 273 274 HHR per Unit Floor Area Heat of Combustion Density Flash Pt Temp Auto Ignition Temp 275 Q" Hc ~ Tflash pt Tigniton 2 3 276 Polyethylene (PE) 1408 kW/m 46500 kJ/kg 930 kg/m 341 C 349 2 3 277 Resins 1408 kW/m 46500 kJ/kg 930 kg/m 341 C 349 278 279 BURNING DURATION OF SOLID COMBUSTIBLES 280 281

Reference:

Buchanan, A. H., "Structural Design for Fire Safety," 2001, Page 38.

282 The burning duration of a solid fuel can be calculated if the total energy contained in the fuel and HRR are known.

283 The burning duration is given by:

284 285 Q = E / t solid 286 or 287 tsolid = (E) / (Q" AFuel) 288 Where tsolid = burning duration of solid combustible (sec) 289 E = mFuel Hc = total energy contained in the fuel (kJ) 290 Q = heat releare rate of fire (kW) 2 291 Q" = heat release rate per unit floor area of fuel (kW/m )

2 292 AFuel = exposed floor area of fuel (m )

293 tsolid = (mFuel Hc) / (Q" AFuel) 294 Where mFuel = mass of solid fuel (kg) 295 Hc = fuel effective heat of combustion (kJ/kg) 296 tsolid = (msolid Hc) / (Q" Asolid) 297 298 tsolid = 8,730 sec 145.50 min 2.43 hr 299 300 Case I Method I Method II Total Numbers of 301 containers of PolyHICs 6 25,981.88 302 303 Mass of Solid Fuel (m solid) 5,700 lb 2.59E+03 kg 304 Mass of Resin (msolid) 39,000 lb 1.77E+04 kg 2 2 305 Exposed Floor Area of Fuel 140 ft 13.0 m 2

306 Heat Release Rate per Unit 1408 kW/m 307 Effective Heat of Combustio 46500 kJ/kg 308 tsolid = 51,615 sec 860.24 min 14.34 hr 309 310 Case II Method I Total Numbers of 311 containers of PolyHICs 270 312 313 Mass of Solid Fuel (m solid) 256,500 lb 1.16E+05 kg 314 Mass of Resin (msolid) 1,755,000 lb 7.96E+05 kg 2 2 315 Exposed Floor Area of Fuel 6,284 ft 583.8 m 2

316 Heat Release Rate per Unit 1408 kW/m 317 Effective Heat of Combustio 46500 kJ/kg 318 tsolid = 51,615 sec 860.24 min 14.34 hr 319

A B C D E F G H I J K L M N 320 321 322 323 Time of Ignition of HIC Exposed to a Constant Radiative Heat Flux 324 325 Method of Mikkola and Wichman (for thermally thick) 326 327 tig = S/4 kUc (Tig - Ta)2 / (qe" - qcritical")2 328 Where tig = material ignition time (sec) 2 2 329 kUc = material thermal inertia (kW/m -K) -sec 330 Tig = material ignition temperature (°C) 331 Ta = ambient air temperature (°C) 2 332 qe" = exposure or external radiative heat flux (kW/m )

2 333 q"critical = material critical heat flux for ignition (kW/m )

334 335 336 tig = 1385.70 sec 23.09 min

CALCULATION No L-003429 REV. 000 PAGE A- 2 Spreadsheet Formulas:

(Separate File)

A B C D E F G H I 1

2 Exelon IR 3

4 5

6 ESTIMA 3

CONTAI NERS ON FIRE DOUBLE-STACKE 7 D 8 3 9 Entered by User 10 Fuel Properties 11 Calculated 12 13 INPUT PARAMETERS 14 15 16 HIC Diameter 5.08 ft =D16*0.3048 m 17 Pool of Fire Diameter (6 HICs) =13.1 ft =D17*0.3048 m 18 HIC Height 6.21 ft =D18*0.3048 m 19 Thickness of Container 0.0417 ft =D19*0.3048 m 20 Radiatice FractionF r 0.3 o o 21 Initial Temperature (To) 77 F =(D21-32)/1.8 C 22 23 THERMAL PROPERTIES

-1 o Thermal Conductivity (Wm

-1 2 3 -1 o 1 24 Fuel Mass Burning Rate m"(kg/m2-sec) Heat of Combustion Hc,eff (kJ/kg) Empirical Constant k (m ) Critical Heat Flux (kW/m ) Density (kg/m ) K ) Specific Heat (J K kg )

25 High Density Polyethylene 0.018 46500 100 6.2 =0.965*1000 0.45 1900 26 Resins 0.018 46500 100 6.2 =0.965*1000 0.45 1900 27 28 29 Radius of the Container =D16/2 ft =D29*0.3048 m 30 Radius of the Pool Fire =D17/2 ft =D30*0.3048 m 31 HIC Surface Area(AHIC) =2*PI()*((D16/2)^2+(D16/2)*D18) ft2 =D31*(0.3048)^2 m2 32 Fuel Area or Dike Area (Adike) =PI()*D17^2/4 ft2 =D32*(0.3048)^2 m2 3

33 Volume of the Container =PI()*((D29)^2-(D29-D19)^2)*D18+2*PI()*(D29)^2*D19 ft3 =D33*(0.3048)^3 m 34 35 Mass Burning Rate of Fuel (m") =C25 kg/m2-sec 36 Effective Heat of Combustion of Fuel (Hc,eff) =D25 kJ/kg 37 Empirical Constant (k) =E25 m-1 38 Air Density at 25 oC 1.184 kg/m3 39 40 41 ESTIMATING RADIATIVE HEAT FLUX TO A TARGET 42 43 Pool Fire Diameter Calculation 44 45 46 D= =F17 m =C46*3.281 ft 47 48 Heat Release Rate Calculation 49 Q(dot) = m"'Hc,eff (1 - e-kED) Adike 50 Where Q(dot) = pool fire heat release rate (kW) 2 51 m" = mass burning rate of fuel per unit surface area (kg/m -sec) 52 'Hc = effective heat of combustion of fuel (kJ/kg) 53 Adike = surface area of pool fire (area involved in vaporization) (m2) 54 kE= empirical constant (m-1) 55 D = diameter of pool fire (diameter involved in vaporization, circular pool is assumed) (m) 56 HRR 57 Q(dot) = =D35*D36*F32*(1-EXP(-D37*C46)) kW =C57*0.94782 Btu/sec 58 59 Heat Release Rate Per Unit Length of Fire Calculation 60 Q'= Q/l 61 Where Q' = heat release rate per unit leght (KW/m) 62 Q(dot) = fire heat release rate of the fire (kW) 63 l = length of the fire source (m) 64 65 Fire Source Length Calculation 66 l x w = Adike 67 68 l= =(F32)^(1/2) m 69 70 Q' = =C57/C68 kW/m 71 72 Flame Height Calculation 73 74 Heskestad Method (1995) 75 2/5 76 Hf = 0.235 Q(dot) - 1.02 D 77 78 Where, 79 Hf = flame height (m) 80 Q(dot) = heat release rate of the fire (kW) 81 D =Diameter of pool fire(m) 82 83 Hf =0.235*C57^(2/5)-1.02*F17 m =C83*3.281 ft 84 85 86 Thomas Method (1962) 87 0.61 88 Hf = 42 x D[ m/ (Ua (g x D))]

89 90 Where, 91 Hf = flame height (m) 92 D = Diameter of pool fire (m) 93 g= gravitational acceleration (m/sec2) 3 94 U a = ambient air density (kg/m )

95 96 Hf =42*C46*(C25/(D38*(9.81*C46)^(1/2)))^(0.61) m =C96*3.281 ft 97

A B C D E F G H I 98 Emissive Power 99 E = 58 (10-0.00823D) 100 Where, E = Flame emissive power (kW/m2) 101 D= diameter of pool fire (m) 102 103 E= =58*(10^(-0.00823*C46)) kW/m2 =(C103*317)/(60*60) Btu/ft2-sec 104 105 106 Distance from the Center of the Pool Fire to Edge of t 107 108 R = L + D/2 109 Where R = distance from center of the pool fire to edge of the target (m) 110 L = distance between pool fire and target (m) 111 D = pool fire diameter (m) 112 113 R= 4.01871386592411 m =C113*3.281 ft Goal seek methody y g 114 view factor calculated value (C155 cell R is obtained by manually inserting the view factor calculated value (C155 cell has to be equal to C129 cell) i the "goal seek" under tools by varing the 115 L= =C113-C46/2 m =C115*3.281 ft R (C133) 116 117 View Factor 118 119 q" = E*F1->2,Max 120 or 121 F1->2,H = q"/E 122 Where, 123 F1->2,H = configuration factor 2

124 q" = incident radiative heat flux or critical heat flux (kW/m )

125 E = emissive power 126 127 F1->2,Max =K25/(C103) 128 2 1/2 -1 1/2 2 1/2 -1 1/2 129 F1->2,H = (B-1/S)/S(B -1) tan ((B+1) (S-1)/(B-1)(S+1)) -(A-1/S)/(S(A -1) ) tan ((A+1)(S-1)/(A-1)(S+1))

-1 2 1/2 -1 1/2 2 1/2 -1 1/2 130 F1->2,V = 1/(SS) tan (h/(S -1) )-(h/SS) tan ((S-1)/(S+1)) + Ah/SS(A -1) tan ((A+1)(S-1)/(A-1)(S+1))

2 2 131 A= (h +S +1)/2S 132 B= (1+S2)/2S 133 S= 2R/D 134 h= 2Hf/D 135 F1->2,max = (F21->2,H + F21->2,V) 136 137 Where F1->2,H = horizontal view factor 138 F1->2,V = vertical view factor 139 F1->2,max = maximum view factor 140 R = distance from center of the pool fire to edge of the target (m) 141 Hf = height of the pool fire flame (m) 142 D = pool fire diameter (m) 143 144 145 146 S= =2*C113/C46 147 h= =2*C83/C46 148 A= =(C147^2+C146^2+1)/(2*C146) 149 B= =(1+C146^2)/(2*C146) 150 151 F1->2,H = =((C149-1/C146)/(PI()*SQRT(C149^2-1))*ATAN(SQRT((C149+1)*(C146-1)/((C149-1)*(C146+1))))-(C148-1/C146)/(PI()*SQRT(C148^2-1))*ATAN(SQRT((C148+1)*(C146-1)/((C148-1)*(C146+1)))

152 F1->2,V = =1/(PI()*C146)*ATAN(C147/SQRT(C146^2-1))-C147/(PI()*C146)*ATAN(SQRT((C146-1)/(C146+1)))+C148*C147/(PI()*C146*SQRT(C148^2-1))*ATAN(SQRT((C148+1)*(C146-1)/((C148-1)*(C146+1))

153 F1->2,Max = =SQRT(C151^2+C152^2) =IF(C153=C127,"Results match, see cell C130","Check Value. Proceed if 154 155 Table of Distance vs Emissive Power Where the Pool 156 157 Pool Fire Diameter (m) R L Emmisive Power (kW/m2) View Factor S h A 158 12.5 8.16390530267151 =C158-B158/2 =58*10^(-0.00823*B158) =$K$25/E158 =2*C158/B158 =2*$C$83/B158 =(H158^2+G158^2+1)/(2*G158 159 12 7.91617302031288 =C159-B159/2 =58*10^(-0.00823*B159) =$K$25/E159 =2*C159/B159 =2*$C$83/B159 =(H159^2+G159^2+1)/(2*G159 160 11.5 7.66696105724212 =C160-B160/2 =58*10^(-0.00823*B160) =$K$25/E160 =2*C160/B160 =2*$C$83/B160 =(H160^2+G160^2+1)/(2*G160 161 11 7.40710272662139 =C161-B161/2 =58*10^(-0.00823*B161) =$K$25/E161 =2*C161/B161 =2*$C$83/B161 =(H161^2+G161^2+1)/(2*G161 162 10.5 7.15300493184372 =C162-B162/2 =58*10^(-0.00823*B162) =$K$25/E162 =2*C162/B162 =2*$C$83/B162 =(H162^2+G162^2+1)/(2*G162 163 10 6.89665304979002 =C163-B163/2 =58*10^(-0.00823*B163) =$K$25/E163 =2*C163/B163 =2*$C$83/B163 =(H163^2+G163^2+1)/(2*G163 164 9.5 6.63779080989267 =C164-B164/2 =58*10^(-0.00823*B164) =$K$25/E164 =2*C164/B164 =2*$C$83/B164 =(H164^2+G164^2+1)/(2*G164 165 9 6.37634881045982 =C165-B165/2 =58*10^(-0.00823*B165) =$K$25/E165 =2*C165/B165 =2*$C$83/B165 =(H165^2+G165^2+1)/(2*G165 166 8.5 6.11190372054874 =C166-B166/2 =58*10^(-0.00823*B166) =$K$25/E166 =2*C166/B166 =2*$C$83/B166 =(H166^2+G166^2+1)/(2*G166 167 8 5.84362315973297 =C167-B167/2 =58*10^(-0.00823*B167) =$K$25/E167 =2*C167/B167 =2*$C$83/B167 =(H167^2+G167^2+1)/(2*G167 168 7.5 5.57115994766075 =C168-B168/2 =58*10^(-0.00823*B168) =$K$25/E168 =2*C168/B168 =2*$C$83/B168 =(H168^2+G168^2+1)/(2*G168 169 7 5.29478869965268 =C169-B169/2 =58*10^(-0.00823*B169) =$K$25/E169 =2*C169/B169 =2*$C$83/B169 =(H169^2+G169^2+1)/(2*G169 170 6.5 5.00450446432636 =C170-B170/2 =58*10^(-0.00823*B170) =$K$25/E170 =2*C170/B170 =2*$C$83/B170 =(H170^2+G170^2+1)/(2*G170 171 6 4.71799650286776 =C171-B171/2 =58*10^(-0.00823*B171) =$K$25/E171 =2*C171/B171 =2*$C$83/B171 =(H171^2+G171^2+1)/(2*G171 172 5.5 4.42376617091138 =C172-B172/2 =58*10^(-0.00823*B172) =$K$25/E172 =2*C172/B172 =2*$C$83/B172 =(H172^2+G172^2+1)/(2*G172 173 5 4.12017778372421 =C173-B173/2 =58*10^(-0.00823*B173) =$K$25/E173 =2*C173/B173 =2*$C$83/B173 =(H173^2+G173^2+1)/(2*G173 174 4.5 3.80923844917601 =C174-B174/2 =58*10^(-0.00823*B174) =$K$25/E174 =2*C174/B174 =2*$C$83/B174 =(H174^2+G174^2+1)/(2*G174 175 4 3.48741080535168 =C175-B175/2 =58*10^(-0.00823*B175) =$K$25/E175 =2*C175/B175 =2*$C$83/B175 =(H175^2+G175^2+1)/(2*G175 176 3.5 3.15223517147927 =C176-B176/2 =58*10^(-0.00823*B176) =$K$25/E176 =2*C176/B176 =2*$C$83/B176 =(H176^2+G176^2+1)/(2*G176 177 3 2.79407447248193 =C177-B177/2 =58*10^(-0.00823*B177) =$K$25/E177 =2*C177/B177 =2*$C$83/B177 =(H177^2+G177^2+1)/(2*G177 178 2.5 2.42168176098249 =C178-B178/2 =58*10^(-0.00823*B178) =$K$25/E178 =2*C178/B178 =2*$C$83/B178 =(H178^2+G178^2+1)/(2*G178 179 2 2.01537535522333 =C179-B179/2 =58*10^(-0.00823*B179) =$K$25/E179 =2*C179/B179 =2*$C$83/B179 =(H179^2+G179^2+1)/(2*G179 180 1.5 1.58004047427233 =C180-B180/2 =58*10^(-0.00823*B180) =$K$25/E180 =2*C180/B180 =2*$C$83/B180 =(H180^2+G180^2+1)/(2*G180 181 1 1.09661692678027 =C181-B181/2 =58*10^(-0.00823*B181) =$K$25/E181 =2*C181/B181 =2*$C$83/B181 =(H181^2+G181^2+1)/(2*G181 182 183 184 185 186 187 188 189 190 191 192 193 194 195 196 197 198 199 200 201 202 203 204 205 206 207

A B C D E F G H I 208 209 Evaluation of the Distance Impact in Terms of Config 210 211 Pool Fire Diameter (m) R L Emmisive Power (kW/m2) S h A B 212 9.63 20.5 =C212-B212/2 =58*10^(-0.00823*B212) =2*C212/B212 =2*$C$83/B212 =(G212^2+F212^2+1)/(2*F21 =(1+F212^2)/(2*F212) 213 9.63 20 =C213-B213/2 =58*10^(-0.00823*B213) =2*C213/B213 =2*$C$83/B213 =(G213^2+F213^2+1)/(2*F21 =(1+F213^2)/(2*F213) 214 9.63 19.5 =C214-B214/2 =58*10^(-0.00823*B214) =2*C214/B214 =2*$C$83/B214 =(G214^2+F214^2+1)/(2*F21 =(1+F214^2)/(2*F214) 215 9.63 19 =C215-B215/2 =58*10^(-0.00823*B215) =2*C215/B215 =2*$C$83/B215 =(G215^2+F215^2+1)/(2*F21 =(1+F215^2)/(2*F215) 216 9.63 18.5 =C216-B216/2 =58*10^(-0.00823*B216) =2*C216/B216 =2*$C$83/B216 =(G216^2+F216^2+1)/(2*F21 =(1+F216^2)/(2*F216) 217 9.63 18 =C217-B217/2 =58*10^(-0.00823*B217) =2*C217/B217 =2*$C$83/B217 =(G217^2+F217^2+1)/(2*F21 =(1+F217^2)/(2*F217) 218 9.63 17.5 =C218-B218/2 =58*10^(-0.00823*B218) =2*C218/B218 =2*$C$83/B218 =(G218^2+F218^2+1)/(2*F21 =(1+F218^2)/(2*F218) 219 9.63 17 =C219-B219/2 =58*10^(-0.00823*B219) =2*C219/B219 =2*$C$83/B219 =(G219^2+F219^2+1)/(2*F21 =(1+F219^2)/(2*F219) 220 9.63 16.5 =C220-B220/2 =58*10^(-0.00823*B220) =2*C220/B220 =2*$C$83/B220 =(G220^2+F220^2+1)/(2*F22 =(1+F220^2)/(2*F220) 221 9.63 16 =C221-B221/2 =58*10^(-0.00823*B221) =2*C221/B221 =2*$C$83/B221 =(G221^2+F221^2+1)/(2*F22 =(1+F221^2)/(2*F221) 222 9.63 15.5 =C222-B222/2 =58*10^(-0.00823*B222) =2*C222/B222 =2*$C$83/B222 =(G222^2+F222^2+1)/(2*F22 =(1+F222^2)/(2*F222) 223 9.63 15 =C223-B223/2 =58*10^(-0.00823*B223) =2*C223/B223 =2*$C$83/B223 =(G223^2+F223^2+1)/(2*F22 =(1+F223^2)/(2*F223) 224 9.63 14.5 =C224-B224/2 =58*10^(-0.00823*B224) =2*C224/B224 =2*$C$83/B224 =(G224^2+F224^2+1)/(2*F22 =(1+F224^2)/(2*F224) 225 9.63 14 =C225-B225/2 =58*10^(-0.00823*B225) =2*C225/B225 =2*$C$83/B225 =(G225^2+F225^2+1)/(2*F22 =(1+F225^2)/(2*F225) 226 9.63 13.5 =C226-B226/2 =58*10^(-0.00823*B226) =2*C226/B226 =2*$C$83/B226 =(G226^2+F226^2+1)/(2*F22 =(1+F226^2)/(2*F226) 227 9.63 13 =C227-B227/2 =58*10^(-0.00823*B227) =2*C227/B227 =2*$C$83/B227 =(G227^2+F227^2+1)/(2*F22 =(1+F227^2)/(2*F227) 228 9.63 12.5 =C228-B228/2 =58*10^(-0.00823*B228) =2*C228/B228 =2*$C$83/B228 =(G228^2+F228^2+1)/(2*F22 =(1+F228^2)/(2*F228) 229 9.63 12 =C229-B229/2 =58*10^(-0.00823*B229) =2*C229/B229 =2*$C$83/B229 =(G229^2+F229^2+1)/(2*F22 =(1+F229^2)/(2*F229) 230 9.63 11.5 =C230-B230/2 =58*10^(-0.00823*B230) =2*C230/B230 =2*$C$83/B230 =(G230^2+F230^2+1)/(2*F23 =(1+F230^2)/(2*F230) 231 9.63 11 =C231-B231/2 =58*10^(-0.00823*B231) =2*C231/B231 =2*$C$83/B231 =(G231^2+F231^2+1)/(2*F23 =(1+F231^2)/(2*F231) 232 9.63 10.5 =C232-B232/2 =58*10^(-0.00823*B232) =2*C232/B232 =2*$C$83/B232 =(G232^2+F232^2+1)/(2*F23 =(1+F232^2)/(2*F232) 233 9.63 10 =C233-B233/2 =58*10^(-0.00823*B233) =2*C233/B233 =2*$C$83/B233 =(G233^2+F233^2+1)/(2*F23 =(1+F233^2)/(2*F233) 234 9.63 9.5 =C234-B234/2 =58*10^(-0.00823*B234) =2*C234/B234 =2*$C$83/B234 =(G234^2+F234^2+1)/(2*F23 =(1+F234^2)/(2*F234) 235 9.63 9 =C235-B235/2 =58*10^(-0.00823*B235) =2*C235/B235 =2*$C$83/B235 =(G235^2+F235^2+1)/(2*F23 =(1+F235^2)/(2*F235) 236 237 238 239 240 241 242 243 244 245 246 247 248 249 250 251 252 253 254 255 256 257 258 ESTIMATING BURNING DURATION OF SOLID COMB 259 260 The following calculations provides an approximation of t 261 burning rate with a given surface area.

262 Green boxes are inputs 263 264 INPUT PARAMETERS 265 266 Mass of Solid Fuel (msolid) 950 lb =C266*0.453592 kg 267 Mass of Resins(msolid) 6500 lb =C267*0.453592 kg 2

268 HIC exposed Floor Area of Fuel (Afuel) =2*PI()*(2.5)^2+2*PI()*(2.5)*(6.26) ft2 =C268*0.092903 m 2

269 IRSF Storage Area 5700 ft2 =C269*0.092903 m 270 271 272 THERMAL PROPERTIES OF 273 274 HHR per Unit Floor Area Heat of Combustion Density Flash Pt Temp 275 Q" Hc ~ T flash pt 2 3 276 Polyethylene (PE) 1408 kW/m 46500 kJ/kg 930 kg/m 341 3

277 Resins 1408 kW/m2 46500 kJ/kg 930 kg/m 341 278 279 BURNING DURATION OF SOLID COMBUSTIBLES 280 281

Reference:

Buchanan, A. H., "Structural Design for Fire S 282 The burning duration of a solid fuel can be calculated if th 283 The burning duration is given by:

284 285 Q = E / tsolid 286 or 287 tsolid = (E) / (Q" AFuel) 288 Where tsolid = burning duration of solid combustible (sec) 289 E = mFuel Hc = total energy contained in the fuel (kJ) 290 Q = heat releare rate of fire (kW) 2 291 Q" = heat release rate per unit floor area of fuel (kW/m) 292 AFuel = exposed floor area of fuel (m2) 293 tsolid = (mFuel Hc) / (Q" AFuel) 294 Where mFuel = mass of solid fuel (kg) 295 Hc = fuel effective heat of combustion (kJ/kg) 296 tsolid = (msolid Hc) / (Q" Asolid) 297 298 tsolid = =((E266+E267)*E276)/(C276*E268) sec =E298/60 min =G298/60 299 300 Case I Method I 301 Total Numbers of containers of PolyHICs 6 302 303 Mass of Solid Fuel (msolid) =E301*C266 lb =D303*0.453592 kg 304 Mass of Resin (msolid) =E301*C267 lb =D304*0.453592 kg 2 2 305 Exposed Floor Area of Fuel (Afuel) =D31 ft =D305*0.092903 m 2

306 Heat Release Rate per Unit Floor Area (Q") =C276 kW/m 307 Effective Heat of Combustion (H c,eff) =E276 kJ/kg 308 tsolid = =((F303+F304)*D307)/(D306*F305) sec =E308/60 min =G308/60 309 310 Case II Method I 311 Total Numbers of containers of PolyHICs 270 312 313 Mass of Solid Fuel (msolid) =E311*C266 lb =D313*0.453592 kg 314 Mass of Resin (msolid) =E311*C267 lb =D314*0.453592 kg 2 2 315 Exposed Floor Area of Fuel (Afuel) =D31*45 ft =D315*0.092903 m 2

316 Heat Release Rate per Unit Floor Area (Q") =C276 kW/m 317 Effective Heat of Combustion (H c,eff) =E276 kJ/kg 318 tsolid = =((F313+F314)*D317)/(D316*F315) sec =E318/60 min =G318/60 319 320 321 322 323 Time of Ignition of HIC Exposed to a Constant Radiat 324 325 Method of Mikkola and Wichman (for thermally thick) 326 2 2 327 tig = S/4 kUc (Tig - Ta) / (qe" - qcritical")

328 Where tig = material ignition time (sec) 329 kUc = material thermal inertia (kW/m2-K)2-sec 330 Tig = material ignition temperature (°C) 331 Ta = ambient air temperature (°C) 2 332 qe" = exposure or external radiative heat flux (kW/m )

2 333 q"critical = material critical heat flux for ignition (kW/m) 334 335 336 tig = =PI()*L25/(4)*( J25-F21)^2/((K25-F25)^2) sec =C336/60 min

J K 1

2 =TODAY()

3 4

5 6

7 8

9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 o 2 24 Ignition Temp ( C) Minimum Heat Flux for Ignition q"min(dot) (kW/m )

25 320 15 26 320 15 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97

J K 98 99 100 101 102 103 104 105 106 107 108 109 110 111 112 113 114 115 116 117 118 119 120 121 122 123 124 125 126 127 128 129 130 131 132 133 134 135 136 137 138 139 140 141 142 143 144 145 146 147 148 149 150 151 152 153 154 155 156 157 B F1->2,H 158 =(1+G158^2)/(2*G158) =((J158-1/G158)/(PI()*SQRT(J158^2-1))*ATAN(SQRT((J158+1)*(G158-1)/((J158-1)*(G158+1))))-(I158-1/G158)/(PI()*SQRT(I158^2-1))*ATAN(SQRT((I158+1)*(G158-1)/((I158-1)*(G158+1)))))

159 =(1+G159^2)/(2*G159) =((J159-1/G159)/(PI()*SQRT(J159^2-1))*ATAN(SQRT((J159+1)*(G159-1)/((J159-1)*(G159+1))))-(I159-1/G159)/(PI()*SQRT(I159^2-1))*ATAN(SQRT((I159+1)*(G159-1)/((I159-1)*(G159+1)))))

160 =(1+G160^2)/(2*G160) =((J160-1/G160)/(PI()*SQRT(J160^2-1))*ATAN(SQRT((J160+1)*(G160-1)/((J160-1)*(G160+1))))-(I160-1/G160)/(PI()*SQRT(I160^2-1))*ATAN(SQRT((I160+1)*(G160-1)/((I160-1)*(G160+1)))))

161 =(1+G161^2)/(2*G161) =((J161-1/G161)/(PI()*SQRT(J161^2-1))*ATAN(SQRT((J161+1)*(G161-1)/((J161-1)*(G161+1))))-(I161-1/G161)/(PI()*SQRT(I161^2-1))*ATAN(SQRT((I161+1)*(G161-1)/((I161-1)*(G161+1)))))

162 =(1+G162^2)/(2*G162) =((J162-1/G162)/(PI()*SQRT(J162^2-1))*ATAN(SQRT((J162+1)*(G162-1)/((J162-1)*(G162+1))))-(I162-1/G162)/(PI()*SQRT(I162^2-1))*ATAN(SQRT((I162+1)*(G162-1)/((I162-1)*(G162+1)))))

163 =(1+G163^2)/(2*G163) =((J163-1/G163)/(PI()*SQRT(J163^2-1))*ATAN(SQRT((J163+1)*(G163-1)/((J163-1)*(G163+1))))-(I163-1/G163)/(PI()*SQRT(I163^2-1))*ATAN(SQRT((I163+1)*(G163-1)/((I163-1)*(G163+1)))))

164 =(1+G164^2)/(2*G164) =((J164-1/G164)/(PI()*SQRT(J164^2-1))*ATAN(SQRT((J164+1)*(G164-1)/((J164-1)*(G164+1))))-(I164-1/G164)/(PI()*SQRT(I164^2-1))*ATAN(SQRT((I164+1)*(G164-1)/((I164-1)*(G164+1)))))

165 =(1+G165^2)/(2*G165) =((J165-1/G165)/(PI()*SQRT(J165^2-1))*ATAN(SQRT((J165+1)*(G165-1)/((J165-1)*(G165+1))))-(I165-1/G165)/(PI()*SQRT(I165^2-1))*ATAN(SQRT((I165+1)*(G165-1)/((I165-1)*(G165+1)))))

166 =(1+G166^2)/(2*G166) =((J166-1/G166)/(PI()*SQRT(J166^2-1))*ATAN(SQRT((J166+1)*(G166-1)/((J166-1)*(G166+1))))-(I166-1/G166)/(PI()*SQRT(I166^2-1))*ATAN(SQRT((I166+1)*(G166-1)/((I166-1)*(G166+1)))))

167 =(1+G167^2)/(2*G167) =((J167-1/G167)/(PI()*SQRT(J167^2-1))*ATAN(SQRT((J167+1)*(G167-1)/((J167-1)*(G167+1))))-(I167-1/G167)/(PI()*SQRT(I167^2-1))*ATAN(SQRT((I167+1)*(G167-1)/((I167-1)*(G167+1)))))

168 =(1+G168^2)/(2*G168) =((J168-1/G168)/(PI()*SQRT(J168^2-1))*ATAN(SQRT((J168+1)*(G168-1)/((J168-1)*(G168+1))))-(I168-1/G168)/(PI()*SQRT(I168^2-1))*ATAN(SQRT((I168+1)*(G168-1)/((I168-1)*(G168+1)))))

169 =(1+G169^2)/(2*G169) =((J169-1/G169)/(PI()*SQRT(J169^2-1))*ATAN(SQRT((J169+1)*(G169-1)/((J169-1)*(G169+1))))-(I169-1/G169)/(PI()*SQRT(I169^2-1))*ATAN(SQRT((I169+1)*(G169-1)/((I169-1)*(G169+1)))))

170 =(1+G170^2)/(2*G170) =((J170-1/G170)/(PI()*SQRT(J170^2-1))*ATAN(SQRT((J170+1)*(G170-1)/((J170-1)*(G170+1))))-(I170-1/G170)/(PI()*SQRT(I170^2-1))*ATAN(SQRT((I170+1)*(G170-1)/((I170-1)*(G170+1)))))

171 =(1+G171^2)/(2*G171) =((J171-1/G171)/(PI()*SQRT(J171^2-1))*ATAN(SQRT((J171+1)*(G171-1)/((J171-1)*(G171+1))))-(I171-1/G171)/(PI()*SQRT(I171^2-1))*ATAN(SQRT((I171+1)*(G171-1)/((I171-1)*(G171+1)))))

172 =(1+G172^2)/(2*G172) =((J172-1/G172)/(PI()*SQRT(J172^2-1))*ATAN(SQRT((J172+1)*(G172-1)/((J172-1)*(G172+1))))-(I172-1/G172)/(PI()*SQRT(I172^2-1))*ATAN(SQRT((I172+1)*(G172-1)/((I172-1)*(G172+1)))))

173 =(1+G173^2)/(2*G173) =((J173-1/G173)/(PI()*SQRT(J173^2-1))*ATAN(SQRT((J173+1)*(G173-1)/((J173-1)*(G173+1))))-(I173-1/G173)/(PI()*SQRT(I173^2-1))*ATAN(SQRT((I173+1)*(G173-1)/((I173-1)*(G173+1)))))

174 =(1+G174^2)/(2*G174) =((J174-1/G174)/(PI()*SQRT(J174^2-1))*ATAN(SQRT((J174+1)*(G174-1)/((J174-1)*(G174+1))))-(I174-1/G174)/(PI()*SQRT(I174^2-1))*ATAN(SQRT((I174+1)*(G174-1)/((I174-1)*(G174+1)))))

175 =(1+G175^2)/(2*G175) =((J175-1/G175)/(PI()*SQRT(J175^2-1))*ATAN(SQRT((J175+1)*(G175-1)/((J175-1)*(G175+1))))-(I175-1/G175)/(PI()*SQRT(I175^2-1))*ATAN(SQRT((I175+1)*(G175-1)/((I175-1)*(G175+1)))))

176 =(1+G176^2)/(2*G176) =((J176-1/G176)/(PI()*SQRT(J176^2-1))*ATAN(SQRT((J176+1)*(G176-1)/((J176-1)*(G176+1))))-(I176-1/G176)/(PI()*SQRT(I176^2-1))*ATAN(SQRT((I176+1)*(G176-1)/((I176-1)*(G176+1)))))

177 =(1+G177^2)/(2*G177) =((J177-1/G177)/(PI()*SQRT(J177^2-1))*ATAN(SQRT((J177+1)*(G177-1)/((J177-1)*(G177+1))))-(I177-1/G177)/(PI()*SQRT(I177^2-1))*ATAN(SQRT((I177+1)*(G177-1)/((I177-1)*(G177+1)))))

178 =(1+G178^2)/(2*G178) =((J178-1/G178)/(PI()*SQRT(J178^2-1))*ATAN(SQRT((J178+1)*(G178-1)/((J178-1)*(G178+1))))-(I178-1/G178)/(PI()*SQRT(I178^2-1))*ATAN(SQRT((I178+1)*(G178-1)/((I178-1)*(G178+1)))))

179 =(1+G179^2)/(2*G179) =((J179-1/G179)/(PI()*SQRT(J179^2-1))*ATAN(SQRT((J179+1)*(G179-1)/((J179-1)*(G179+1))))-(I179-1/G179)/(PI()*SQRT(I179^2-1))*ATAN(SQRT((I179+1)*(G179-1)/((I179-1)*(G179+1)))))

180 =(1+G180^2)/(2*G180) =((J180-1/G180)/(PI()*SQRT(J180^2-1))*ATAN(SQRT((J180+1)*(G180-1)/((J180-1)*(G180+1))))-(I180-1/G180)/(PI()*SQRT(I180^2-1))*ATAN(SQRT((I180+1)*(G180-1)/((I180-1)*(G180+1)))))

181 =(1+G181^2)/(2*G181) =((J181-1/G181)/(PI()*SQRT(J181^2-1))*ATAN(SQRT((J181+1)*(G181-1)/((J181-1)*(G181+1))))-(I181-1/G181)/(PI()*SQRT(I181^2-1))*ATAN(SQRT((I181+1)*(G181-1)/((I181-1)*(G181+1)))))

182 183 184 185 186 187 188 189 190 191 192 193 194 195 196 197 198 199 200 201 202 203 204 205 206 207

J K 208 209 210 211 F1->2,H F1->2,V 212 =((I212-1/F212)/(PI()*SQRT(I212^2-1))*ATAN(SQRT((I212+1)*(F212-1)/((I212-1)*(F212+1))))-(H212-1/F212)/(PI()*SQRT(H212^2-1))*ATAN(SQRT((H212+1)*(F212-1)/((H212-1)*(F212+1))))) =1/(PI()*F212)*ATAN(G212/SQRT(F212^2-1))-G212/(PI()*F212)*ATAN(SQRT((F212-1)/(F212+1)))+H212*G212/(PI()*F212*SQRT(H212^2-1))*ATAN(SQRT((H212+1)*(F212-1)/((H212-1)*(F212+1))))

213 =((I213-1/F213)/(PI()*SQRT(I213^2-1))*ATAN(SQRT((I213+1)*(F213-1)/((I213-1)*(F213+1))))-(H213-1/F213)/(PI()*SQRT(H213^2-1))*ATAN(SQRT((H213+1)*(F213-1)/((H213-1)*(F213+1))))) =1/(PI()*F213)*ATAN(G213/SQRT(F213^2-1))-G213/(PI()*F213)*ATAN(SQRT((F213-1)/(F213+1)))+H213*G213/(PI()*F213*SQRT(H213^2-1))*ATAN(SQRT((H213+1)*(F213-1)/((H213-1)*(F213+1))))

214 =((I214-1/F214)/(PI()*SQRT(I214^2-1))*ATAN(SQRT((I214+1)*(F214-1)/((I214-1)*(F214+1))))-(H214-1/F214)/(PI()*SQRT(H214^2-1))*ATAN(SQRT((H214+1)*(F214-1)/((H214-1)*(F214+1))))) =1/(PI()*F214)*ATAN(G214/SQRT(F214^2-1))-G214/(PI()*F214)*ATAN(SQRT((F214-1)/(F214+1)))+H214*G214/(PI()*F214*SQRT(H214^2-1))*ATAN(SQRT((H214+1)*(F214-1)/((H214-1)*(F214+1))))

215 =((I215-1/F215)/(PI()*SQRT(I215^2-1))*ATAN(SQRT((I215+1)*(F215-1)/((I215-1)*(F215+1))))-(H215-1/F215)/(PI()*SQRT(H215^2-1))*ATAN(SQRT((H215+1)*(F215-1)/((H215-1)*(F215+1))))) =1/(PI()*F215)*ATAN(G215/SQRT(F215^2-1))-G215/(PI()*F215)*ATAN(SQRT((F215-1)/(F215+1)))+H215*G215/(PI()*F215*SQRT(H215^2-1))*ATAN(SQRT((H215+1)*(F215-1)/((H215-1)*(F215+1))))

216 =((I216-1/F216)/(PI()*SQRT(I216^2-1))*ATAN(SQRT((I216+1)*(F216-1)/((I216-1)*(F216+1))))-(H216-1/F216)/(PI()*SQRT(H216^2-1))*ATAN(SQRT((H216+1)*(F216-1)/((H216-1)*(F216+1))))) =1/(PI()*F216)*ATAN(G216/SQRT(F216^2-1))-G216/(PI()*F216)*ATAN(SQRT((F216-1)/(F216+1)))+H216*G216/(PI()*F216*SQRT(H216^2-1))*ATAN(SQRT((H216+1)*(F216-1)/((H216-1)*(F216+1))))

217 =((I217-1/F217)/(PI()*SQRT(I217^2-1))*ATAN(SQRT((I217+1)*(F217-1)/((I217-1)*(F217+1))))-(H217-1/F217)/(PI()*SQRT(H217^2-1))*ATAN(SQRT((H217+1)*(F217-1)/((H217-1)*(F217+1))))) =1/(PI()*F217)*ATAN(G217/SQRT(F217^2-1))-G217/(PI()*F217)*ATAN(SQRT((F217-1)/(F217+1)))+H217*G217/(PI()*F217*SQRT(H217^2-1))*ATAN(SQRT((H217+1)*(F217-1)/((H217-1)*(F217+1))))

218 =((I218-1/F218)/(PI()*SQRT(I218^2-1))*ATAN(SQRT((I218+1)*(F218-1)/((I218-1)*(F218+1))))-(H218-1/F218)/(PI()*SQRT(H218^2-1))*ATAN(SQRT((H218+1)*(F218-1)/((H218-1)*(F218+1))))) =1/(PI()*F218)*ATAN(G218/SQRT(F218^2-1))-G218/(PI()*F218)*ATAN(SQRT((F218-1)/(F218+1)))+H218*G218/(PI()*F218*SQRT(H218^2-1))*ATAN(SQRT((H218+1)*(F218-1)/((H218-1)*(F218+1))))

219 =((I219-1/F219)/(PI()*SQRT(I219^2-1))*ATAN(SQRT((I219+1)*(F219-1)/((I219-1)*(F219+1))))-(H219-1/F219)/(PI()*SQRT(H219^2-1))*ATAN(SQRT((H219+1)*(F219-1)/((H219-1)*(F219+1))))) =1/(PI()*F219)*ATAN(G219/SQRT(F219^2-1))-G219/(PI()*F219)*ATAN(SQRT((F219-1)/(F219+1)))+H219*G219/(PI()*F219*SQRT(H219^2-1))*ATAN(SQRT((H219+1)*(F219-1)/((H219-1)*(F219+1))))

220 =((I220-1/F220)/(PI()*SQRT(I220^2-1))*ATAN(SQRT((I220+1)*(F220-1)/((I220-1)*(F220+1))))-(H220-1/F220)/(PI()*SQRT(H220^2-1))*ATAN(SQRT((H220+1)*(F220-1)/((H220-1)*(F220+1))))) =1/(PI()*F220)*ATAN(G220/SQRT(F220^2-1))-G220/(PI()*F220)*ATAN(SQRT((F220-1)/(F220+1)))+H220*G220/(PI()*F220*SQRT(H220^2-1))*ATAN(SQRT((H220+1)*(F220-1)/((H220-1)*(F220+1))))

221 =((I221-1/F221)/(PI()*SQRT(I221^2-1))*ATAN(SQRT((I221+1)*(F221-1)/((I221-1)*(F221+1))))-(H221-1/F221)/(PI()*SQRT(H221^2-1))*ATAN(SQRT((H221+1)*(F221-1)/((H221-1)*(F221+1))))) =1/(PI()*F221)*ATAN(G221/SQRT(F221^2-1))-G221/(PI()*F221)*ATAN(SQRT((F221-1)/(F221+1)))+H221*G221/(PI()*F221*SQRT(H221^2-1))*ATAN(SQRT((H221+1)*(F221-1)/((H221-1)*(F221+1))))

222 =((I222-1/F222)/(PI()*SQRT(I222^2-1))*ATAN(SQRT((I222+1)*(F222-1)/((I222-1)*(F222+1))))-(H222-1/F222)/(PI()*SQRT(H222^2-1))*ATAN(SQRT((H222+1)*(F222-1)/((H222-1)*(F222+1))))) =1/(PI()*F222)*ATAN(G222/SQRT(F222^2-1))-G222/(PI()*F222)*ATAN(SQRT((F222-1)/(F222+1)))+H222*G222/(PI()*F222*SQRT(H222^2-1))*ATAN(SQRT((H222+1)*(F222-1)/((H222-1)*(F222+1))))

223 =((I223-1/F223)/(PI()*SQRT(I223^2-1))*ATAN(SQRT((I223+1)*(F223-1)/((I223-1)*(F223+1))))-(H223-1/F223)/(PI()*SQRT(H223^2-1))*ATAN(SQRT((H223+1)*(F223-1)/((H223-1)*(F223+1))))) =1/(PI()*F223)*ATAN(G223/SQRT(F223^2-1))-G223/(PI()*F223)*ATAN(SQRT((F223-1)/(F223+1)))+H223*G223/(PI()*F223*SQRT(H223^2-1))*ATAN(SQRT((H223+1)*(F223-1)/((H223-1)*(F223+1))))

224 =((I224-1/F224)/(PI()*SQRT(I224^2-1))*ATAN(SQRT((I224+1)*(F224-1)/((I224-1)*(F224+1))))-(H224-1/F224)/(PI()*SQRT(H224^2-1))*ATAN(SQRT((H224+1)*(F224-1)/((H224-1)*(F224+1))))) =1/(PI()*F224)*ATAN(G224/SQRT(F224^2-1))-G224/(PI()*F224)*ATAN(SQRT((F224-1)/(F224+1)))+H224*G224/(PI()*F224*SQRT(H224^2-1))*ATAN(SQRT((H224+1)*(F224-1)/((H224-1)*(F224+1))))

225 =((I225-1/F225)/(PI()*SQRT(I225^2-1))*ATAN(SQRT((I225+1)*(F225-1)/((I225-1)*(F225+1))))-(H225-1/F225)/(PI()*SQRT(H225^2-1))*ATAN(SQRT((H225+1)*(F225-1)/((H225-1)*(F225+1))))) =1/(PI()*F225)*ATAN(G225/SQRT(F225^2-1))-G225/(PI()*F225)*ATAN(SQRT((F225-1)/(F225+1)))+H225*G225/(PI()*F225*SQRT(H225^2-1))*ATAN(SQRT((H225+1)*(F225-1)/((H225-1)*(F225+1))))

226 =((I226-1/F226)/(PI()*SQRT(I226^2-1))*ATAN(SQRT((I226+1)*(F226-1)/((I226-1)*(F226+1))))-(H226-1/F226)/(PI()*SQRT(H226^2-1))*ATAN(SQRT((H226+1)*(F226-1)/((H226-1)*(F226+1))))) =1/(PI()*F226)*ATAN(G226/SQRT(F226^2-1))-G226/(PI()*F226)*ATAN(SQRT((F226-1)/(F226+1)))+H226*G226/(PI()*F226*SQRT(H226^2-1))*ATAN(SQRT((H226+1)*(F226-1)/((H226-1)*(F226+1))))

227 =((I227-1/F227)/(PI()*SQRT(I227^2-1))*ATAN(SQRT((I227+1)*(F227-1)/((I227-1)*(F227+1))))-(H227-1/F227)/(PI()*SQRT(H227^2-1))*ATAN(SQRT((H227+1)*(F227-1)/((H227-1)*(F227+1))))) =1/(PI()*F227)*ATAN(G227/SQRT(F227^2-1))-G227/(PI()*F227)*ATAN(SQRT((F227-1)/(F227+1)))+H227*G227/(PI()*F227*SQRT(H227^2-1))*ATAN(SQRT((H227+1)*(F227-1)/((H227-1)*(F227+1))))

228 =((I228-1/F228)/(PI()*SQRT(I228^2-1))*ATAN(SQRT((I228+1)*(F228-1)/((I228-1)*(F228+1))))-(H228-1/F228)/(PI()*SQRT(H228^2-1))*ATAN(SQRT((H228+1)*(F228-1)/((H228-1)*(F228+1))))) =1/(PI()*F228)*ATAN(G228/SQRT(F228^2-1))-G228/(PI()*F228)*ATAN(SQRT((F228-1)/(F228+1)))+H228*G228/(PI()*F228*SQRT(H228^2-1))*ATAN(SQRT((H228+1)*(F228-1)/((H228-1)*(F228+1))))

229 =((I229-1/F229)/(PI()*SQRT(I229^2-1))*ATAN(SQRT((I229+1)*(F229-1)/((I229-1)*(F229+1))))-(H229-1/F229)/(PI()*SQRT(H229^2-1))*ATAN(SQRT((H229+1)*(F229-1)/((H229-1)*(F229+1))))) =1/(PI()*F229)*ATAN(G229/SQRT(F229^2-1))-G229/(PI()*F229)*ATAN(SQRT((F229-1)/(F229+1)))+H229*G229/(PI()*F229*SQRT(H229^2-1))*ATAN(SQRT((H229+1)*(F229-1)/((H229-1)*(F229+1))))

230 =((I230-1/F230)/(PI()*SQRT(I230^2-1))*ATAN(SQRT((I230+1)*(F230-1)/((I230-1)*(F230+1))))-(H230-1/F230)/(PI()*SQRT(H230^2-1))*ATAN(SQRT((H230+1)*(F230-1)/((H230-1)*(F230+1))))) =1/(PI()*F230)*ATAN(G230/SQRT(F230^2-1))-G230/(PI()*F230)*ATAN(SQRT((F230-1)/(F230+1)))+H230*G230/(PI()*F230*SQRT(H230^2-1))*ATAN(SQRT((H230+1)*(F230-1)/((H230-1)*(F230+1))))

231 =((I231-1/F231)/(PI()*SQRT(I231^2-1))*ATAN(SQRT((I231+1)*(F231-1)/((I231-1)*(F231+1))))-(H231-1/F231)/(PI()*SQRT(H231^2-1))*ATAN(SQRT((H231+1)*(F231-1)/((H231-1)*(F231+1))))) =1/(PI()*F231)*ATAN(G231/SQRT(F231^2-1))-G231/(PI()*F231)*ATAN(SQRT((F231-1)/(F231+1)))+H231*G231/(PI()*F231*SQRT(H231^2-1))*ATAN(SQRT((H231+1)*(F231-1)/((H231-1)*(F231+1))))

232 =((I232-1/F232)/(PI()*SQRT(I232^2-1))*ATAN(SQRT((I232+1)*(F232-1)/((I232-1)*(F232+1))))-(H232-1/F232)/(PI()*SQRT(H232^2-1))*ATAN(SQRT((H232+1)*(F232-1)/((H232-1)*(F232+1))))) =1/(PI()*F232)*ATAN(G232/SQRT(F232^2-1))-G232/(PI()*F232)*ATAN(SQRT((F232-1)/(F232+1)))+H232*G232/(PI()*F232*SQRT(H232^2-1))*ATAN(SQRT((H232+1)*(F232-1)/((H232-1)*(F232+1))))

233 =((I233-1/F233)/(PI()*SQRT(I233^2-1))*ATAN(SQRT((I233+1)*(F233-1)/((I233-1)*(F233+1))))-(H233-1/F233)/(PI()*SQRT(H233^2-1))*ATAN(SQRT((H233+1)*(F233-1)/((H233-1)*(F233+1))))) =1/(PI()*F233)*ATAN(G233/SQRT(F233^2-1))-G233/(PI()*F233)*ATAN(SQRT((F233-1)/(F233+1)))+H233*G233/(PI()*F233*SQRT(H233^2-1))*ATAN(SQRT((H233+1)*(F233-1)/((H233-1)*(F233+1))))

234 =((I234-1/F234)/(PI()*SQRT(I234^2-1))*ATAN(SQRT((I234+1)*(F234-1)/((I234-1)*(F234+1))))-(H234-1/F234)/(PI()*SQRT(H234^2-1))*ATAN(SQRT((H234+1)*(F234-1)/((H234-1)*(F234+1))))) =1/(PI()*F234)*ATAN(G234/SQRT(F234^2-1))-G234/(PI()*F234)*ATAN(SQRT((F234-1)/(F234+1)))+H234*G234/(PI()*F234*SQRT(H234^2-1))*ATAN(SQRT((H234+1)*(F234-1)/((H234-1)*(F234+1))))

235 =((I235-1/F235)/(PI()*SQRT(I235^2-1))*ATAN(SQRT((I235+1)*(F235-1)/((I235-1)*(F235+1))))-(H235-1/F235)/(PI()*SQRT(H235^2-1))*ATAN(SQRT((H235+1)*(F235-1)/((H235-1)*(F235+1))))) =1/(PI()*F235)*ATAN(G235/SQRT(F235^2-1))-G235/(PI()*F235)*ATAN(SQRT((F235-1)/(F235+1)))+H235*G235/(PI()*F235*SQRT(H235^2-1))*ATAN(SQRT((H235+1)*(F235-1)/((H235-1)*(F235+1))))

236 237 238 239 240 241 242 243 244 245 246 247 248 249 250 251 252 253 254 255 256 257 258 259 260 261 262 263 264 265 266 267 268 269 270 271 272 273 274 Auto Ignition Temp 275 T igniton 276 C 349 277 C 349 278 279 280 281 282 283 284 285 286 287 288 289 290 291 292 293 294 295 296 297 298 hr 299 300 Method II 301 =D307*(D303+D304)/80000 302 303 304 305 306 307 308 hr 309 310 311 312 313 314 315 316 317 318 hr 319 320 321 322 323 324 325 326 327 328 329 330 331 332 333 334 335 336

L M N 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 Flux Time Product 2 2 2 1/2 24 Thermal inertia (kW/m K) TRP (kW/m s )(flamm) Index (n) 25 1.57 321 1 26 1.57 321 1 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97

L M N 98 99 100 101 102 103 104 105 106 107 108 109 110 111 112 113 114 115 116 117 118 119 120 121 122 123 124 125 126 127 128 129 130 131 132 133 134 135 136 137 138 139 140 141 142 143 144 145 146 147 148 149 150 151 152 153 154 155 156 157 F1->2,V F1->2,Max 158 =1/(PI()*G158)*ATAN(H158/SQRT(G158^2-1))-H158/(PI()*G158)*ATAN(SQRT((G158-1)/(G158+1)))+I158*H158/(PI()*G158*SQRT(I158^2-1))*ATAN(SQRT((I158+1)*(G158-1)/((I158-1)*(G158+1)))) =SQRT(K158^2+L158^2) 159 =1/(PI()*G159)*ATAN(H159/SQRT(G159^2-1))-H159/(PI()*G159)*ATAN(SQRT((G159-1)/(G159+1)))+I159*H159/(PI()*G159*SQRT(I159^2-1))*ATAN(SQRT((I159+1)*(G159-1)/((I159-1)*(G159+1)))) =SQRT(K159^2+L159^2) 160 =1/(PI()*G160)*ATAN(H160/SQRT(G160^2-1))-H160/(PI()*G160)*ATAN(SQRT((G160-1)/(G160+1)))+I160*H160/(PI()*G160*SQRT(I160^2-1))*ATAN(SQRT((I160+1)*(G160-1)/((I160-1)*(G160+1)))) =SQRT(K160^2+L160^2) 161 =1/(PI()*G161)*ATAN(H161/SQRT(G161^2-1))-H161/(PI()*G161)*ATAN(SQRT((G161-1)/(G161+1)))+I161*H161/(PI()*G161*SQRT(I161^2-1))*ATAN(SQRT((I161+1)*(G161-1)/((I161-1)*(G161+1)))) =SQRT(K161^2+L161^2) 162 =1/(PI()*G162)*ATAN(H162/SQRT(G162^2-1))-H162/(PI()*G162)*ATAN(SQRT((G162-1)/(G162+1)))+I162*H162/(PI()*G162*SQRT(I162^2-1))*ATAN(SQRT((I162+1)*(G162-1)/((I162-1)*(G162+1)))) =SQRT(K162^2+L162^2) 163 =1/(PI()*G163)*ATAN(H163/SQRT(G163^2-1))-H163/(PI()*G163)*ATAN(SQRT((G163-1)/(G163+1)))+I163*H163/(PI()*G163*SQRT(I163^2-1))*ATAN(SQRT((I163+1)*(G163-1)/((I163-1)*(G163+1)))) =SQRT(K163^2+L163^2) 164 =1/(PI()*G164)*ATAN(H164/SQRT(G164^2-1))-H164/(PI()*G164)*ATAN(SQRT((G164-1)/(G164+1)))+I164*H164/(PI()*G164*SQRT(I164^2-1))*ATAN(SQRT((I164+1)*(G164-1)/((I164-1)*(G164+1)))) =SQRT(K164^2+L164^2) 165 =1/(PI()*G165)*ATAN(H165/SQRT(G165^2-1))-H165/(PI()*G165)*ATAN(SQRT((G165-1)/(G165+1)))+I165*H165/(PI()*G165*SQRT(I165^2-1))*ATAN(SQRT((I165+1)*(G165-1)/((I165-1)*(G165+1)))) =SQRT(K165^2+L165^2) 166 =1/(PI()*G166)*ATAN(H166/SQRT(G166^2-1))-H166/(PI()*G166)*ATAN(SQRT((G166-1)/(G166+1)))+I166*H166/(PI()*G166*SQRT(I166^2-1))*ATAN(SQRT((I166+1)*(G166-1)/((I166-1)*(G166+1)))) =SQRT(K166^2+L166^2) 167 =1/(PI()*G167)*ATAN(H167/SQRT(G167^2-1))-H167/(PI()*G167)*ATAN(SQRT((G167-1)/(G167+1)))+I167*H167/(PI()*G167*SQRT(I167^2-1))*ATAN(SQRT((I167+1)*(G167-1)/((I167-1)*(G167+1)))) =SQRT(K167^2+L167^2) 168 =1/(PI()*G168)*ATAN(H168/SQRT(G168^2-1))-H168/(PI()*G168)*ATAN(SQRT((G168-1)/(G168+1)))+I168*H168/(PI()*G168*SQRT(I168^2-1))*ATAN(SQRT((I168+1)*(G168-1)/((I168-1)*(G168+1)))) =SQRT(K168^2+L168^2) 169 =1/(PI()*G169)*ATAN(H169/SQRT(G169^2-1))-H169/(PI()*G169)*ATAN(SQRT((G169-1)/(G169+1)))+I169*H169/(PI()*G169*SQRT(I169^2-1))*ATAN(SQRT((I169+1)*(G169-1)/((I169-1)*(G169+1)))) =SQRT(K169^2+L169^2) 170 =1/(PI()*G170)*ATAN(H170/SQRT(G170^2-1))-H170/(PI()*G170)*ATAN(SQRT((G170-1)/(G170+1)))+I170*H170/(PI()*G170*SQRT(I170^2-1))*ATAN(SQRT((I170+1)*(G170-1)/((I170-1)*(G170+1)))) =SQRT(K170^2+L170^2) 171 =1/(PI()*G171)*ATAN(H171/SQRT(G171^2-1))-H171/(PI()*G171)*ATAN(SQRT((G171-1)/(G171+1)))+I171*H171/(PI()*G171*SQRT(I171^2-1))*ATAN(SQRT((I171+1)*(G171-1)/((I171-1)*(G171+1)))) =SQRT(K171^2+L171^2) 172 =1/(PI()*G172)*ATAN(H172/SQRT(G172^2-1))-H172/(PI()*G172)*ATAN(SQRT((G172-1)/(G172+1)))+I172*H172/(PI()*G172*SQRT(I172^2-1))*ATAN(SQRT((I172+1)*(G172-1)/((I172-1)*(G172+1)))) =SQRT(K172^2+L172^2) 173 =1/(PI()*G173)*ATAN(H173/SQRT(G173^2-1))-H173/(PI()*G173)*ATAN(SQRT((G173-1)/(G173+1)))+I173*H173/(PI()*G173*SQRT(I173^2-1))*ATAN(SQRT((I173+1)*(G173-1)/((I173-1)*(G173+1)))) =SQRT(K173^2+L173^2) 174 =1/(PI()*G174)*ATAN(H174/SQRT(G174^2-1))-H174/(PI()*G174)*ATAN(SQRT((G174-1)/(G174+1)))+I174*H174/(PI()*G174*SQRT(I174^2-1))*ATAN(SQRT((I174+1)*(G174-1)/((I174-1)*(G174+1)))) =SQRT(K174^2+L174^2) 175 =1/(PI()*G175)*ATAN(H175/SQRT(G175^2-1))-H175/(PI()*G175)*ATAN(SQRT((G175-1)/(G175+1)))+I175*H175/(PI()*G175*SQRT(I175^2-1))*ATAN(SQRT((I175+1)*(G175-1)/((I175-1)*(G175+1)))) =SQRT(K175^2+L175^2) 176 =1/(PI()*G176)*ATAN(H176/SQRT(G176^2-1))-H176/(PI()*G176)*ATAN(SQRT((G176-1)/(G176+1)))+I176*H176/(PI()*G176*SQRT(I176^2-1))*ATAN(SQRT((I176+1)*(G176-1)/((I176-1)*(G176+1)))) =SQRT(K176^2+L176^2) 177 =1/(PI()*G177)*ATAN(H177/SQRT(G177^2-1))-H177/(PI()*G177)*ATAN(SQRT((G177-1)/(G177+1)))+I177*H177/(PI()*G177*SQRT(I177^2-1))*ATAN(SQRT((I177+1)*(G177-1)/((I177-1)*(G177+1)))) =SQRT(K177^2+L177^2) 178 =1/(PI()*G178)*ATAN(H178/SQRT(G178^2-1))-H178/(PI()*G178)*ATAN(SQRT((G178-1)/(G178+1)))+I178*H178/(PI()*G178*SQRT(I178^2-1))*ATAN(SQRT((I178+1)*(G178-1)/((I178-1)*(G178+1)))) =SQRT(K178^2+L178^2) 179 =1/(PI()*G179)*ATAN(H179/SQRT(G179^2-1))-H179/(PI()*G179)*ATAN(SQRT((G179-1)/(G179+1)))+I179*H179/(PI()*G179*SQRT(I179^2-1))*ATAN(SQRT((I179+1)*(G179-1)/((I179-1)*(G179+1)))) =SQRT(K179^2+L179^2) 180 =1/(PI()*G180)*ATAN(H180/SQRT(G180^2-1))-H180/(PI()*G180)*ATAN(SQRT((G180-1)/(G180+1)))+I180*H180/(PI()*G180*SQRT(I180^2-1))*ATAN(SQRT((I180+1)*(G180-1)/((I180-1)*(G180+1)))) =SQRT(K180^2+L180^2) 181 =1/(PI()*G181)*ATAN(H181/SQRT(G181^2-1))-H181/(PI()*G181)*ATAN(SQRT((G181-1)/(G181+1)))+I181*H181/(PI()*G181*SQRT(I181^2-1))*ATAN(SQRT((I181+1)*(G181-1)/((I181-1)*(G181+1)))) =SQRT(K181^2+L181^2) 182 183 184 185 186 187 188 189 190 191 192 193 194 195 196 197 198 199 200 201 202 203 204 205 206 207

L M N 208 209 210 211 F1->2,Max 212 =SQRT(J212^2+K212^2) 213 =SQRT(J213^2+K213^2) 214 =SQRT(J214^2+K214^2) 215 =SQRT(J215^2+K215^2) 216 =SQRT(J216^2+K216^2) 217 =SQRT(J217^2+K217^2) 218 =SQRT(J218^2+K218^2) 219 =SQRT(J219^2+K219^2) 220 =SQRT(J220^2+K220^2) 221 =SQRT(J221^2+K221^2) 222 =SQRT(J222^2+K222^2) 223 =SQRT(J223^2+K223^2) 224 =SQRT(J224^2+K224^2) 225 =SQRT(J225^2+K225^2) 226 =SQRT(J226^2+K226^2) 227 =SQRT(J227^2+K227^2) 228 =SQRT(J228^2+K228^2) 229 =SQRT(J229^2+K229^2) 230 =SQRT(J230^2+K230^2) 231 =SQRT(J231^2+K231^2) 232 =SQRT(J232^2+K232^2) 233 =SQRT(J233^2+K233^2) 234 =SQRT(J234^2+K234^2) 235 =SQRT(J235^2+K235^2) 236 237 238 239 240 241 242 243 244 245 246 247 248 249 250 251 252 253 254 255 256 257 258 259 260 261 262 263 264 265 266 267 268 269 270 271 272 273 274 275 276 277 278 279 280 281 282 283 284 285 286 287 288 289 290 291 292 293 294 295 296 297 298 299 300 301 302 303 304 305 306 307 308 309 310 311 312 313 314 315 316 317 318 319 320 321 322 323 324 325 326 327 328 329 330 331 332 333 334 335 336

CALCULATION No L-003429 REV. 000 PAGE A- 3 Other calculated fire parameters of interest:

Burning Duration of Solids Combustibles (HDPE HIC)

Fuel load per unit floor area, material burning rate, and the available ventilation define the intensity and the duration of the fire.

Buchanan Method (2001)

Q(dot) = Etotal/tsolid or tsolid = Etotal/ (Q" Afuel)

Where, tsolid = burning duration of solid combustible (sec)

Etotal = mfuel Hc,eff = total energy contained in the fuel (kJ)

Q(dot) = heat release rate of fire (kW)

Q = heat release rate per unit floor area of fuel (kW/m2)

Afuel = exposed floor area (m2)

Etotal = (430.91 kg + 2948.35 kg)*(46,500kJ/kg) = 1.5713 x 108 kJ tsolid = (1.5713 x 108 kJ ) / ( (1,408 kW/m2)*(12.78 m2)) = 8,730 sec Thus, the burning time of one HIC with the resins is approximately 145.50 minutes (2.43 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br />).

6 Containers Burning Duration A scenario where 3 uninsulated HDPE HICs double-stacked is evaluated (total of 6 containers).

Total mass of solid fuel = 950 lbs

• 6 containers = 5,700 lbs

• 0.453592 = 2.59 x103 kg Total mass of resin = 6,500 lbs

• 6 containers = 39,000 lbs

• 0.453592 = 1.77 x104 kg Exposed floor area of fuel = 139.64 ft2 = 12.97 m2 [see section 7.4]

Tsolid = [ (2.59x103 kg + 1.77x104 kg )*46,500 kJ/kg / (1,408 kW/m2

• 12.97 m2 )] = 51,615 sec This evaluation does not include values that prolong the burning time such as spreading the fire in the IRSF storage bay. It is calculated that 6 containers can burn for 14.34 hours3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> (51,615 sec).

Time of Ignition of HDPE HIC Exposed to a Constant Radiative Heat Flux The time of ignition is calculated for HDPE considering a constant external radiative heat flux using multiple methods, Reference [5]. The methods below are differentiated by the parameters used to obtain the time of ignition and the procedure.

Method of Mikkola and Wichman (Reference [5])

Mikkola and Wichman use the critical temperature to solve the one-dimensional conduction equation with linearized radiative and convective boundary condition. The time of ignition is derived based on thermally thick method.

tig = S/4

• kUc (Tig - Ta)2/(qe - qcrit)2 Where,

CALCULATION No L-003429 REV. 000 PAGE A- 4 tig = material ignition time (sec) kUc = material thermal inertia (kW/m2-K2)-sec Tig = material ignition temperature (oC)

Ta = ambient air temperature (oC) qe = exposure or external radiative heat flux (kW/m2) qcrit = material critical heat flux for ignition (kW/m2) tig = S/4

• 1.57 (kW/m2K)2 * (320oC -25oC )2/(15 kW/m2- 6.2 kW/m2)2 = 1385.7 sec /60 = 23.09 min

CALCULATION No L-003429 REV. 000 PAGE B- 1 ATTACHMENT B - EMPTY HIC WEIGHT BASIS (ENERGY SOLUTIONS MEMO)

CALCULATION No L-003429 REV. 000 PAGE C- 1 ATTACHMENT C - POLYPROPYLENE MATERIAL PROPERTIES These tables were extracted from NUREG-1805- Fire Dynamics Tools (FDTs).

CALCULATION No L-003429 REV. 000 PAGE C- 2 CALCULATION No L-003429 REV. 000 PAGE D- 1 ATTACHMENT D - COMPILATION OF EXPERIMENTAL DATA Extracted from Reference [5].

CALCULATION No L-003429 REV. 000 PAGE E- 1 ATTACHMENT E - HDPE PHYSICAL AND CHEMICAL DATA - MSDS EXTRACT

CALCULATION No L-003429 REV. 000 PAGE F- 1 ATTACHMENT F - THERMAL PROPERTIES OF COMMON SOLID COMBUSTIBLE MATERIALS Extracted from NUREG-1805, see Reference [1].

CALCULATION No L-003429 REV. 000 PAGE G- 1 ATTACHMENT G - RESULTS FOR SEVERAL DIFFERENT MATERIALS CORRELATING THE FLUX TIME PRODUCT

CALCULATION No L-003429 REV. 000 PAGE H- 1 ATTACHMENT H - COLLECTION OF DATA BY TEWARSON GIVING MINIMUM HEAT FLUX AND THERMAL RESPONSE PARAMETER VALUES

CALCULATION No L-003429 REV. 000 PAGE J- 1 ATTACHMENT J - COMPUTER DISCLOSURE SHEET Computer Disclosure Sheet Discipline Nuclear Client: Exelon Nuclear Power Plants Date: July, 2009 Project: IRSF Storage Bay Fire Spacing Assessment Job No.

Program(s) used Rev No. Rev Date Calculation Set No.: L-003429, Rev. 000 Attachment A Spreadsheets N/A N/A Status [ ] Prelim

[X] Final

[ ] Void URS Prequalification [ ] Yes

[ X ] No Run No.

Description:

Analysis

Description:

Spreadsheets were used to execute arithmetic manipulations of numbers, for various applications within the attachments of this analysis.

The attached computer output has been reviewed, the input data checked, And the results approved for release. Input criteria for this analysis were established.

By: On: 7/2009 Run by:

Checked by: N. Propst Approved by: S. Dawoud Remarks:

These spreadsheets were applied in a straight-forward manner and were hand checked.