RS-16-225, Revised Request for License Amendment Regarding High Burnup Atrium-10 Partial Length Fuel Rods and Request for Exigent Review

Revised Request for License Amendment Regarding High Burnup Atrium-10 Partial Length Fuel Rods and Request for Exigent Review

ML16313A617
Person / Time
Site:	LaSalle
Issue date:	11/08/2016
From:	Simpson P Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RS-16-225
Download: ML16313A617 (121)

Text

4300 Winfield Road Warrenville, IL 60555 630 657 2000 Office RS-16-225 10 CFR 50.90 November 8, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 LaSalle County Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374

Subject:

Revised Request for License Amendment Regarding High Burnup Atrium-10 Partial Length Fuel Rods and Request for Exigent Review

References:

1. Letter from D. M. Gullott (Exelon Generation Company, LLC) to U.S. NRC, "Request for License Amendment Regarding High Burnup Atrium-10 Partial Length Fuel Rods," dated September 30, 2016

2. Letter from B. K. Vaidya (U.S. NRC) to B. C. Hanson (Exelon Generation Company, LLC), "LaSalle County Station, Units 1 and 2, - Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding High Burnup Atrium-10 Partial Length Fuel Rods (CAC Nos.

MF8442 and MF8443)," dated October 31, 2016 In Reference 1, Exelon Generation Company, LLC (EGC) requested an amendment to Facility Operating License Nos. NPF-11 and NPF-18 for LaSalle County Station (LSCS), Units 1 and 2, respectively. The proposed change would revise the LSCS licensing basis to address Atrium-10 fuel bundles containing part length rods that exceed the burnup limit of 62,000 MWD/MTU, which is specified in NRC Regulatory Guide (RG) 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors."

In Reference 2, the NRC requested additional information that is needed to support the acceptance review of the license amendment request. In response to this request, EGC is providing the attached information.

As discussed with the NRC during a conference call on October 27, 2016, EGC's interpretation of the RG 1.183 release fractions and associated footnotes was that release fractions for the loss-of-coolant accident (LOCA), listed in Table 1 of RG 1.183, could be used if individual fuel rods exceed a peak burnup of 62,000 MWD/MTU. This interpretation was based, in part, on the fact that EGC's LOCA dose consequence analysis applies release fractions uniformly to the

November 8, 2016 U.S. Nuclear Regulatory Commission Page 2 entire core and the core average exposure is not projected to exceed the 62,000 MWD/MTU burnup limit. However, in Reference 2, the NRC clarified that this limit is established in RG 1.183 as an upper boundary to the applicability of the release fractions provided in Tables 1 and 3. Specifically, Reference 2 states that the footnote to Table 1 of RG 1.183 indicates that the limit is for peak burnups rather than average burnups.

As a result, EGC is revising the Evaluation of Proposed Change that was submitted to the NRC as Attachment 1 of Reference 1 to also request NRC approval to exceed the burnup limit specified in Footnote 10 of RG 1.183. The attached information completely supersedes the information previously provided to the NRC in Reference 1.

Current projections show that at the end of the current operating cycle for LSCS Unit 2, 12 Atrium-10 part length rods will have exceeded the 62,000 MWD/MTU burnup limit. To date, none of the part length rods have exceeded the burnup limit. However, projections show that the limit will be exceeded on November 22, 2016.

As a result, EGC requests that further NRC review of the proposed change proceed on an exigent basis in accordance with 10 CFR 50.91, "Notice for public comment; State consultation,"

paragraph (a)(6) because time does not permit the NRC to publish a Federal Register notice allowing 30 days for prior public comment. The basis for exigency is provided in Attachment 1.

This request is subdivided as follows.

• Attachment 1 provides a description and evaluation of the proposed change.

• Attachment 2 provides Design Analysis L-003067, "Re-Analysis of Fuel Handling Accident (FHA) Using Alternative Source Terms," Revision 2D.

• Attachment 3 provides Technical Evaluation EC407055, "Evaluation of LaSalle Alternative Source Term Loss of Coolant Accident Dose for L2C16 and Impact of Part Length Rods with Burnup > 62 GWd/MTUs," Revision 0.

The proposed change has been reviewed by the LSCS Plant Operations Review Committee in accordance with the requirements of the EGC Quality Assurance Program.

EGC requests approval of the proposed change by November 21, 2016, to support continued plant operation following the date that the burnup limit will be exceeded. Once approved, the amendment will be implemented immediately.

In accordance with 10 CFR 50.91, "Notice for public comment; State consultation,"

paragraph (b), EGC is notifying the State of Illinois of this application for license amendment by transmitting a copy of this letter and its attachments to the designated State Official.

There are no regulatory commitments contained in this letter. Should you have any questions concerning this letter, please contact Mr. Kenneth M. Nicely at (630) 657-2803.

November 8, 2016 U.S. Nuclear Regulatory Commission Page 3 I declare under penalty of perjury that the foregoing is true and correct. Executed on the 8th RR day of November 2016.

Patrick R. Simpson Manager - Licensing Attachments:

1. Evaluation of Proposed Change

2. Design Analysis L-003067, "Re-Analysis of Fuel Handling Accident (FHA) Using Alternative Source Terms," Revision 2D

3. Technical Evaluation EC407055, "Evaluation of LaSalle Alternative Source Term Loss of Coolant Accident Dose for L2C16 and Impact of Part Length Rods with Burn up > 62 GWd/MTUs," Revision 0 cc: NRC Regional Administrator, Region Ill NRC Senior Resident Inspector - LaSalle County Station Illinois Emergency Management Agency- Division of Nuclear Safety

ATTACHMENT 1 Evaluation of Proposed Change 1.0

SUMMARY

DESCRIPTION 2.0 DETAILED DESCRIPTION

4.0 REGULATORY EVALUATION

4.1 Applicable Regulatory Requirements/Criteria 4.2 No Significant Hazards Consideration 4.3 Conclusions

6.0 REFERENCES

Page 1

ATTACHMENT 1 Evaluation of Proposed Change 1.0

SUMMARY

DESCRIPTION In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Exelon Generation Company, LLC (EGC) requests an amendment to Renewed Facility Operating License Nos. NPF-11 and NPF-18 for LaSalle County Station (LSCS), Units 1 and 2, respectively. The proposed change revises the LSCS licensing basis to allow movement of irradiated Atrium-10 fuel bundles containing part length rods that have been in operation above 62,000 MWD/MTU, which is the current rod average burnup limit specified in Footnote 11 of NRC Regulatory Guide 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors" (i.e., Reference 1, to which LSCS is committed). In addition, the proposed change allows use of the release fractions listed in Table 1 of RG 1.183 for these Atrium-10 part length rods that are currently in the Unit 2 Cycle 16 reactor core for the remainder of the current operating cycle.

EGC requests NRC approval of the proposed change on an exigent basis in accordance with 10 CFR 50.91, "Notice for public comment; State consultation," paragraph (a)(6) because time does not permit the NRC to publish a Federal Register notice allowing 30 days for prior public comment, as discussed below.

As discussed with the NRC during a conference call on October 27, 2016, EGC's interpretation of the Reference 1 release fractions and associated footnotes was that release fractions for the loss-of-coolant accident (LOCA), listed in Table 1 of Reference 1, could be used if individual fuel rods exceed a peak burnup of 62,000 MWD/MTU. This interpretation was based, in part, on the fact that EGC's LOCA dose consequence analysis applies release fractions uniformly to the entire core and the core average exposure is not projected to exceed the 62,000 MWD/MTU burnup limit. However, during the conference call, the NRC clarified that this limit is established in Reference 1 as an upper boundary to the applicability of the release fractions provided in Tables 1 and 3, and the limit applied to peak rod exposures regardless of the core average exposure. As a result, EGC determined that the Unit 2 Cycle 16 core design was based on a misinterpretation of Footnote 10, and the core design was nonconforming with the LSCS licensing basis. This nonconforming condition was entered into EGC's Corrective Action Program. EGC evaluated the nonconforming condition and its impact on continued plant operation in accordance with EGC procedures that implement guidance contained in NRC Inspection Manual Chapter 0326, "Operability Determinations & Functionality Assessments for Conditions Adverse to Quality or Safety," and determined operability was supported. However, based on additional discussions with the NRC on November 8, 2016, the NRC expressed that evaluation of the nonconforming condition under EGC's operability determination process could not be used for this situation and that NRC approval of the proposed change described herein was needed prior to exceeding the burnup limit of 62,000 MWD/MTU.

Current projections show that at the end of the current operating cycle for LSCS Unit 2, 12 Atrium-10 part length rods will exceed the 62,000 MWD/MTU burnup limit. To date, none of the part length rods have exceeded the burnup limit. However, projections show that the limit will be exceeded on November 22, 2016. Therefore, EGC is requesting NRC approval of the proposed change by November 21, 2016, to support continued plant operation for LSCS Unit 2.

Page 2

ATTACHMENT 1 Evaluation of Proposed Change 2.0 DETAILED DESCRIPTION In Reference 2, the NRC issued amendments 197 and 184 to the facility operating licenses for LSCS, Units 1 and 2, respectively. The amendments support the application of alternative source term (AST) methodology with respect to the loss-of-coolant accident (LOCA) and the fuel handling accident (FHA). EGC's AST analyses for LSCS were performed following the guidance in NRC Regulatory Guide 1.183; Standard Review Plan 15.0.1, "Radiological Consequence Analyses Using Alternative Source Terms" (i.e., Reference 3); and 10 CFR 50.67, "Accident source term."

Section 3 of Reference 1 provides an AST that is acceptable to the NRC, and states that once approved, the AST assumptions or parameters specified in these positions become part of the facility's design basis. After the NRC has approved an implementation of an AST, subsequent changes to the AST require NRC review under 10 CFR 50.67.

LSCS's AST analyses used the core inventory release fractions for the gap release and early in-vessel damage phases for the design basis accident (DBA) LOCA that are listed in Table 1 of Reference 1. For the FHA event, LSCS's analyses used the fractions of the core inventory assumed to be in the gap for the various radionuclides in Table 3 of Reference 1. These release fractions were used in conjunction with the fission product inventory calculated with the maximum core radial peaking factor.

The discussion of release fractions in Reference 1 is annotated with the following footnote:

10 The release fractions listed here have been determined to be acceptable for use with currently approved LWR fuel with a peak burnup of 62,000 MWD/MTU. The data in this section may not be applicable to cores containing mixed oxide (MOX) fuel.

Table 3 is annotated with the following footnote:

11 The release fractions listed here have been determined to be acceptable for use with currently approved LWR fuel with a peak burnup up to 62,000 MWD/MTU provided that the maximum linear heat generation rate does not exceed 6.3 kw/ft peak rod average power for burnups exceeding 54 GWD/MTU. As an alternative, fission gas release calculations performed using NRC-approved methodologies may be considered on a case-by-case basis. To be acceptable, these calculations must use a projected power history that will bound the limiting projected plant-specific power history for the specific fuel load. For the BWR rod drop accident and the PWR rod ejection accident, the gap fractions are assumed to be 10% for iodines and noble gases.

On April 14, 2014, Issue Report 1647125 was initiated under EGC's Corrective Action Program to document a concern that 19 fuel bundles in the Unit 1 Cycle 16 reactor core contain at least one part length rod that exceeds the 62,000 MWD/MTU burnup limit specified in Table 3 of Reference 1. At that time, it was projected that the burnup limit would be reached in September 2015. The fuel bundles containing part length rods were removed from the reactor core during the refueling outage in the first quarter of 2016.

Page 3

ATTACHMENT 1 Evaluation of Proposed Change Subsequent reviews identified that some part length rods in the Unit 2 Cycle 16 reactor core were also expected to exceed the 62,000 MWD/MTU burnup limit. The impact of this issue on Unit 2 was documented in Issue Report 2537519. The affected fuel bundles in the Unit 2 Cycle 16 reactor core are currently expected to reach the burnup limit on November 22, 2016.

The NRC's review of these Issue Reports is discussed in Reference 4. In summary, the NRC's review identified a Green finding and a Severity Level IV non-cited violation of 10 CFR 50.59.

The NRC concluded that a change to the plant as described in the UFSAR was made, pursuant to 10 CFR 50.59(c), and EGC did not perform an accurate written evaluation which provided the bases for determining that these changes did not require a license amendment. Specifically, EGC did not provide an accurate written evaluation supporting the determination that exceeding the peak burnup limit of 62,000 MWD/MTU for fuel, provided that the maximum linear heat generation rate did not exceed 6.3 kw/ft peak rod average power for burnups exceeding 54,000 MWD/MTU, did not require a license amendment.

The proposed change resolves the Green finding and Severity Level IV non-cited violation by requesting NRC approval to revise the LSCS licensing basis to allow movement of irradiated Atrium-10 fuel bundles containing part length rods that have been in operation above 62,000 MWD/MTU. In addition, the proposed change allows use of the release fractions listed in Table 1 of RG 1.183 for these Atrium-10 part length rods that are currently in the Unit 2 Cycle 16 reactor core for the remainder of the current operating cycle.

For Unit 1, the fuel bundles containing part length rods were removed from the reactor core and placed in the spent fuel storage pool in the first quarter of 2016. However, approval of the proposed change would support future movement of those fuel bundles in the spent fuel storage pool since a fuel handling accident involving fuel bundles containing high burnup part length rods could occur. Administrative controls have been put in place to prevent movement of the affected Unit 1 fuel bundles, and these controls will remain in place until NRC approval of the proposed change is received.

For Unit 2, the affected fuel bundles are currently expected to exceed the burnup limit on November 22, 2016. The proposed change would allow continued plant operation past this date, for the remainder of the current operating cycle. In addition, approval of the proposed change would support movement of the affected Unit 2 fuel bundles.

3.0 TECHNICAL EVALUATION

The fuel bundles containing part length rods that have exceeded, or are projected to exceed, the 62,000 MWD/MTU burnup limit are Atrium-10 fuel bundles. There are 12 part length rods that are projected to exceed this limit by the end the current operating cycle for LSCS Unit 2 (i.e., Cycle 16) by a maximum of 849 MWD/MTU. In addition, another eight part length rods are projected to come within 110 MWD/MTU of exceeding the limit.

The Atrium-10 part length rod is a fuel rod that is shorter than a full length rod, and is located in the bottom portion of the reactor core. It has less uranium content and, as a result of the axial power distribution due to voiding in the top of the core, it experiences higher rod-average exposure. However, it is very similar to the corresponding segment of the full length rod.

Essentially the segment is the same as a full length rod, except it has the top portion of uranium Page 4

ATTACHMENT 1 Evaluation of Proposed Change removed. Using this equivalence aspect and the gap fraction calculation procedure, a comparative analysis was performed to determine the impact on the FHA analysis and to demonstrate that a part length rod is bounded by a full length rod.

The associated design analysis is provided in Attachment 2. The scope of the design analysis is limited to the Atrium-10 fuel design at LSCS. The methodology associated with this design analysis is the AST as defined in Reference 1. Reference 1 provides gap release fractions for non-LOCA events in Table 3. These gap release fractions were developed prior to July 2000 and do not explicitly address part length rods. For LSCS, the fuel handling accident is the only non-LOCA event that uses AST methodology in the radiological consequence analyses.

A calculation procedure available to assess the gap inventory is specified in ANSI/ANS-5.4-2011, "Method for Calculating the Fractional Release of Volatile Fission Products from Oxide Fuel," (i.e., Reference 5) to assess the gap inventory. In that calculation procedure, the fractional release of fission gases is computed in a radial and axial (nodal) domain that represents the uranium oxide fuel pellet stack. The effective release fraction is then computed by a volume and power weighted average of the spatial dependent release fractions. The design analysis used this approach to demonstrate that the gap release fraction of the part length rod is bounded by the full length rod, given operational characteristics inherent to the part length rods.

The design analysis demonstrates that the power and burnup for an Atrium-10 part length rod is bounded by the power and burnup in the same axial portion of several neighboring full length rods. Therefore, since the full length rod operating characteristics bound the part length rod, and since the power and burnup of the full length rods comply with the limits specified in Footnote 11 of Reference 1, the Atrium-10 part length rods may operate beyond the 62,000 MWD/MTU burnup limit and meet the intent of Reference 1 (i.e., there is no increase in the non-LOCA gap release fraction required), with an adjustment to the Atrium-10 core damage fraction.

The core damage fraction was adjusted to provide conservatism and to make the Atrium-10 portion of the current analysis of record consistent with this approach. The Atrium-10 fuel assembly at LSCS has eight part length rods that have 90-inch active fuel length and 83 full length rods that have 149-inch active fuel length. Therefore, a part length rod is equivalent to 60.4 percent of the fueled mass of a full length rod. Using this basis, the total equivalent full length rods in the bundle is 87.83 and the revised core damage fraction is 0.002325 versus the current analysis value of 0.002244. This increase of 3.6 percent effectively assumes that the part length rods contain the same source term inventory as the full length rods. However, the limiting GE14 core damage fraction of 0.002578 remains bounding over Atrium-10. Therefore, there is no change in the dose consequences of the analysis of record. With a radial peaking factor of 1.7, the release fraction becomes 0.00395. The margin between the Atrium-10 and limiting dose consequences is therefore approximately 10 percent.

EGC has also performed an evaluation to assess the impact of considering the Unit 2 Cycle 16 specific core design on the AST LOCA dose analysis, and to further show that the consequences of a small number of part length rods in the Atrium-10 batch exceeding the 62,000 MWD/MTU peak rod average limit in Footnote 10 of Reference 1 will not cause LOCA doses to exceed the current analysis of record results. This evaluation, which was prepared to Page 5

ATTACHMENT 1 Evaluation of Proposed Change address the supplemental information requested by the NRC in Reference 6, is provided in . The impact of part length rods exceeding 62,000 MWD/MTU was determined using the same method of substituting full length rod activity for part length rod activity developed in Attachment 2. That analysis demonstrated that every full length rod in Atrium-10 fuel that meets the 62,000 MWD/MTU limit has an axial section equivalent to the part length rod that exceeds the limit by more than the part length rods. Since the full length rod power and burnup is more limiting, it can be used to satisfy the Reference 1 Footnote 10 burnup restrictions, and the LOCA release fractions can be applied unchanged provided full length rods are analytically substituted for part length rods which exceed 62,000 MWD/MTU. The results of this evaluation conclude that the small number of Unit 2 Cycle 16 Atrium-10 part length rods that will exceed or come close to exceeding the 62,000 MWD/MTU limit by the end of the current operating cycle would not result in doses from a LOCA exceeding the current licensing basis results.

4.0 REGULATORY EVALUATION

4.1 Applicable Regulatory Requirements/Criteria In accordance with 10 CFR 50.67, a licensee may revise its current accident source term by re-evaluating the consequences of DBAs with the AST. In Reference 2, the NRC approved the allocation of AST methodology at LSCS with respect to the LOCA and FHA. The guidance associated with the implementation of an AST is provided in NRC Regulatory Guide 1.183 (i.e., Reference 1), which states that subsequent changes to the AST require NRC review under 10 CFR 50.67.

Fundamental to the definition of an AST according to Reference 1 are the release fractions. Table 1 of Reference 1 provides core inventory release fractions, by radionuclide groups, for the gap release and early in-vessel damage phases for DBA LOCAs. These fractions are applied to the equilibrium core inventory developed for LSCS. Footnote 10 limits the peak burnup to 62,000 MWD/MTU. Table 3 of Reference 1 provides gap release fractions for various volatile fission product isotopes and isotope groups, to be applied to non-LOCA accidents. Footnote 11 of Table 3 limits the peak burnup to 62,000 MWD/MTU provided that the maximum linear heat generation rate does not exceed 6.3 kw/ft peak rod average power for burnups exceeding 54,000 MWD/MTU. As an alternative, fission gas release calculations performed using NRC-approved methodologies may be considered on a case-by-case basis. To be acceptable, these calculations must use a projected power history that will bound the limiting projected plant-specific power history for the specific fuel load. For the BWR rod drop accident and the PWR rod ejection accident, the gap fractions are assumed to be 10% for iodines and noble gases.

EGC's analyses demonstrate that the radiological consequences of a FHA and LOCA are not affected by the proposed change.

Page 6

ATTACHMENT 1 Evaluation of Proposed Change 4.2 No Significant Hazards Consideration In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Exelon Generation Company, LLC (EGC) requests an amendment to Renewed Facility Operating License Nos. NPF-11 and NPF-18 for LaSalle County Station (LSCS), Units 1 and 2, respectively. The proposed change revises the LSCS licensing basis to allow movement of irradiated Atrium-10 fuel bundles containing part length rods that have been in operation above 62,000 MWD/MTU, which is the current rod average burnup limit specified in Footnote 11 of NRC Regulatory Guide 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors." In addition, the proposed change allows use of the release fractions listed in Table 1 of NRC Regulatory Guide 1.183 for these Atrium-10 part length rods that are currently in the Unit 2 Cycle 16 reactor core for the remainder of the current operating cycle.

According to 10 CFR 50.92, "Issuance of amendment," paragraph (c), a proposed amendment to an operating license involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not:

(1) Involve a significant increase in the probability or consequences of any accident previously evaluated; or (2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) Involve a significant reduction in a margin of safety.

EGC has evaluated the proposed change, using the criteria in 10 CFR 50.92, and has determined that the proposed change does not involve a significant hazards consideration. The following information is provided to support a finding of no significant hazards consideration.

1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No The proposed change revises the LSCS licensing basis to allow movement of irradiated Atrium-10 fuel bundles containing part length rods that have been in operation above 62,000 MWD/MTU. In addition, the proposed change allows use of the release fractions listed in Table 1 of NRC Regulatory Guide 1.183 for these Atrium-10 part length rods that are currently in the Unit 2 Cycle 16 reactor core for the remainder of the current operating cycle. The proposed change does not involve any physical changes to the plant design and is not an initiator of an accident. The proposed change does not adversely affect accident initiators or precursors, and does not alter the design assumptions, conditions, or configuration of the plant or the manner in which the plant is operated or maintained. Therefore, the proposed change does not affect the probability of a Page 7

ATTACHMENT 1 Evaluation of Proposed Change loss-of-coolant accident. In addition, the proposed change does not affect the probability of a fuel handling accident because the method and frequency of fuel movement activities are not changing.

Analyses have been performed that demonstrate that the power and burnup for an Atrium-10 part length rod is bounded by the power and burnup in the same axial portion of neighboring full length rods. Therefore, since the full length rod operating characteristics bound the part length rod, and since the power and burnup of the full length rods comply with the limits specified in Footnotes 10 and 11 of NRC Regulatory Guide 1.183, the Atrium-10 part length rods may operate beyond the 62,000 MWD/MTU burnup limit and meet the intent of NRC Regulatory Guide 1.183. There are no changes in the dose consequences of the analyses of record for the fuel handling accident and loss-of-coolant accident.

Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No The proposed change revises the LSCS licensing basis to allow movement of irradiated Atrium-10 fuel bundles containing part length rods that have been in operation above 62,000 MWD/MTU. In addition, the proposed change allows use of the release fractions listed in Table 1 of NRC Regulatory Guide 1.183 for these Atrium-10 part length rods that are currently in the Unit 2 Cycle 16 reactor core for the remainder of the current operating cycle. The proposed change does not introduce any changes or mechanisms that create the possibility of a new or different kind of accident. The proposed change does not install any new or different type of equipment, and installed equipment is not being operated in a new or different manner. No new effects on existing equipment are created nor are any new malfunctions introduced.

Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.

3. Does the proposed change involve a significant reduction in a margin of safety?

Response: No The proposed change revises the LSCS licensing basis to allow movement of irradiated Atrium-10 fuel bundles containing part length rods that have been in operation above 62,000 MWD/MTU. In addition, the proposed change allows use of the release fractions listed in Table 1 of NRC Regulatory Guide 1.183 for these Atrium-10 part length rods that are currently in the Unit 2 Cycle 16 reactor core for the remainder of the current operating cycle. Analyses have been performed that demonstrate that the power and burnup for an Atrium-10 part Page 8

ATTACHMENT 1 Evaluation of Proposed Change length rod is bounded by the power and burnup in the same axial portion of neighboring full length rods. There is no change in the dose consequences of the fuel handling accident or loss-of-coolant accident analyses of record. The margin of safety, as defined by 10 CFR 50.67 and NRC Regulatory Guide 1.183, has been maintained.

Therefore, the proposed change does not involve a significant reduction in a margin of safety.

Based on the above evaluation, EGC concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92, paragraph (c), and accordingly, a finding of no significant hazards consideration is justified.

4.3 Conclusions In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or the health and safety of the public.

5.0 ENVIRONMENTAL CONSIDERATION

EGC has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, "Standards for Protection Against Radiation." However, the proposed amendment does not involve: (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22, "Criterion for categorical exclusion; identification of licensing and regulatory actions eligible for categorical exclusion or otherwise not requiring environmental review,"

paragraph (c)(9). Therefore, pursuant to 10 CFR 51.22, paragraph (b), no environmental impact statement or environmental assessment needs to be prepared in connection with the proposed amendment.

6.0 REFERENCES

1. NRC Regulatory Guide 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors," dated July 2000

2. Letter from C. Gratton (U.S. NRC) to M. J. Pacilio (Exelon Nuclear), "LaSalle County Station, Units 1 and 2 - Issuance of Amendments Re: Application of Alternative Source Term (TAC Nos. ME0068 and ME0069)," dated September 6, 2010

3. NRC Standard Review Plan 15.0.1, "Radiological Consequence Analyses Using Alternative Source Terms," Revision 0, dated July 2000 Page 9

ATTACHMENT 1 Evaluation of Proposed Change

4. Letter from B. Dickson (U.S. NRC) to B. C. Hanson (Exelon Generation Company, LLC),

"LaSalle County Station, Units 1 and 2 - NRC Integrated Inspection Report 05000373/2016002; 05000374/2016002," dated August 4, 2016

5. ANSI/ANS-5.4-2011, "Method for Calculating the Fractional Release of Volatile Fission Products from Oxide Fuel"

6. Letter from B. K. Vaidya (U.S. NRC) to B. C. Hanson (Exelon Generation Company, LLC), "LaSalle County Station, Units 1 and 2, - Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding High Burnup Atrium-10 Partial Length Fuel Rods (CAC Nos. MF8442 and MF8443)," dated October 31, 2016 Page 10

ATTACHMENT 2 Design Analysis L-003067, "Re-Analysis of Fuel Handling Accident (FHA)

Using Alternative Source Terms," Revision 2D

CC-AA-309-1001 Revision 8 Page 30 of 67 ATTACHMENT 1 Design Analysis Cover Sheet Page 1of5 Design Analysis J Last Page No.

• H-14 Analysis No.: 1 L-003067 Revision: 2 20 Major D Minor [8l

Title:

3 Re-Analysis of Fuel Handling Accident (FHA) Using Alternative Source Terms EC/ECR No.:

• 406676 Revision: 5 001 Station(s): 1 LAS Component(s): 1 Unit No.:* 1&2 NA Discipline: 9 MEDC, NUDC R01 & R02/ FHA, AST, Descrip. Code/Keyword: 10 OBA, Dose Safety/QA Class: 11 SR System Code: 12 VC,VG,VS,ZZ Structure: 13 NA CONTROLLED DOCUMENT REFERENCES 15 Document No.: From/To Document No.: From/To NF-AB-110-2210 From Drawing 5054 77 4 From UFSAR CH 15 Table 15.7-21 To Is this Design Analysis Safeguards Information? 16 Yes D No [8l If yes, see SY-AA-101-106 Does this Design Analysis contain Unverified Assumptions? 11 Yes D No [8l If yes, ATl/AR#:

This Design Analysis SUPERCEDES: 19 L-003067 Rev. 2C in its entirety.

Description of Revision (list changed pages when all pages of original analysis were not changed): 1*

Revision addresses Atrium-10 part-length rods exposure impacts on the FHA dose consequences and addresses IR 2691476 related to a violation of 10 CFR 50.59. Affected pages are 5, 6, and addition of a new Attachment H.

Preparer: 20 Shane Gardner

...!~ tv >>---- 2016-09-27 14:51-04:00 Print Name Sien Name Date Method of Review: 21 Detailed Review [8l Alternate Calcula~sj,ttached) D Testing D Reviewer: 22 Greg Heasley ":!!_ ~~ 9/27/16 Print Name SlgSme Date Review Notes: 23 Independent review [8l Peer review D An independent review of the evaluation was performed in accordance with CC-AA-309 Revision 11 and T&RM CC-AA-309-1001 Revision 8. All review comments were resolved satisfactorily. Based on the review, the numeric analysis and results support the conclusion.

(For External Analyses Only}

External Approver: 2

• NA Print Name Sign Name Date Exelon Reviewer: 25 NA Print Name Sien Name Date Independent 3rc1 Party Review Reqd? 2

• Yes D No [8l Exelon Approver: 21 John Massari 9/27/2016 Pnnt Name Date

(

L-003067 Rev. 20 Page 5 of 21 vall.l!es tmllzed. and .a evalua~on o the aoooptablllry ot oonsiderarloo o an addmana~

Secondary COllltainment penetration lbeiing !left open (oonwieration of any such penauallons !Is remoYed in 1his Revi!OOn 2).

Revision 2 of this caf.oulation:

• removed the d'efilnlhl'on of recenrly 11*1adlatt'!!d fuel.

• added lhe requirement for Seconljary Concs*nmenit lnnegritY and Standby Gas Treatment System operal>illfy, wJllh fillratiOR ayeilatlilily fOl&oWilng an ii)$'$Ul'l'IEld Secondary Contahnmenl drawdolM!'I period..

• r emoved poirnt and diffu:se 1;1rea pa1hwa)I$ li;\$$0r;:iabed wiNl not lh$'1ring Seoonclary Contalnmenl lntagrl~

• ep;plied reYised 1./0 v.cil~es,

• added CRAF operability wllh l~l<e fl~ter crecli'I after 20 mll"lll.ltes aind ll'e(:i1Tcul\allon fll,er credit after 4 hOtlrs ([in the same manner as Is uised for the AS'T lloiss of Cooling Accident), and

• edded seYerar minor ,cleirificatiol'lS.

2. METHOD OF ANALYSIS AND ACCEPTANCE CRtTfRIA Analyses of rradlologi~ conseQUences resulting fmm a des,;gn basis FHA are pell'formed 1JSing the ~idence r~ ap.plication Qr AST to ltlis event in RG 1.183. and the approYed AST VaJJues 'for FHA p:rtMded In :the Ref. 13 "Ttansmittal Qf Design lnfoR!l'll;;Ulon".

An:iilyse.s oftadiatron lran:spon ~n(ll dose assessrnEml are iPe.rfotmed U$ing RADYRAJO v. 3.03.

RADTRAD Is a slmJpltft.ed*model of B!Qronucllda Ira~mt and Bemoval !ltd Qotie IEtitimallon deYeloped for the NRC 1;11nd ~n~ed by the NrRC ;es an accepleble meqh(>(JotQgy for reane.ty.sls QI the radlologlcal oonsequences or design !basis accidents. The technlca basis for the AADTRAD code i$ dtl(:ul'li'lellllted in NUREGJCR-6604 (Ref. 3). The melthodologieg sigl1iiffce1n to ttJJ5 analyiis are *he dose 0011seq1Jeooe unatysls (NUREG Sec00n 2.3) and tie Radloacllve Oeeay Calcul\alions (NU REG Section 2.4). Trus veltironi of RADTRAD has been ps:~a1ified for safety ma*ed design anarysls by URS pa its 10CFR50 Appendix B Oualhy A:ssuraMJO program.

2.1. FueJ Source Term Model AJ. per ~r. 13, the fue~ sourir:.e term is bued on the ~eactor core sou:r:oe terms descrtiboo In Attael'lment A These Get.Jree 1err'r\$ are b~nding f<:ir LSCS fuel cycle i::vestgl1$ as documented ir.

Anactimen* A, whieh repeats the rellBvaril s.oUll'ce tetm ln6ormatlon ftom Ref. 20 for cot1va:nienoe.

The fraction .of the core fue* (~n lhe 764 fuel tNJndle com) dama"Qed Is per the R-elf. 9, Ret. 10,

.cilld Ref. 111 GESTAR ,u 1imiltng case of damaging 172 l'iLlel pens (based 001 a He~ Mast

0 design: i.e.* the "NF50() mast" ln Ref. 10) ftom GE12 or GE14 10x10 fuel bundte array.s with. illle equivalanl oi .87.33 pins per bun&.e. and wi1h all oHhe damegMI fuel assumed kt have a r iting Radial Peaking Fooror (PF) *of 1.7 (per Ref. 13). Th.is an.alysis is fa*Tan assembly and mast drop 1

from a 34 reel :maximum llileigtrt from *the ll'efueliing, pfs,tforrn trt1er !he reacbor WEiii onto the reacklr 1

core. btlundlna In fterms od' *ft.1111 dal'l'lage 1Poten11a1. Based en ruel damage assassrrmeait$ in ref~ enoes u. 14, emt 15~ , C>Wn in labie 1 befow, this bolJJlcb all currenl!ly uwa and hlstarical roo1 types (indu an~ 7-,.7 array fuel 1hal may have beElfll used ea in the ~clDr life, now S\lfflclently deiceyed any releases wi.11 be bouooed by n~ *o ther :Jue' ~pes coosidered below).

and Attachment H

L-003067 Rev. 20 Page 6 of 21 Table 1: B oundlna Fuel Bundle T*voe Evaluation Radial Asaumed Oamaged Damaged Fuel Peaking I

Bundle Type Array i IPin& In Faliled Core Factor Core Fraction Bundle fqns fraetlon (Pf, wlHiPF

_;E-Varlous sx.a 62 1.24 0.(102618 1.5 0.003927 s:.ANP Atrium*9B 9x'9 72 131 0.002381 I

1"5 O.Q035'72 Alnum-10 1GJC10 156 - 1.7 BI.83 0.002325 0.003952

~IE11&GE~J 9JC9 74 140 1).002476 1.-fj 0.00'3714 -

GIE1.2&0E14" 10x10 87.33 172 0.002578 1.7 1 0.004382

• Bound*n11 As&amblv tvoe, wtth RadlaR P&ak.ilna Factor commen:&ural8 with f1,1lt core a,oollcatton.

Wilh a 1.7 radial pee.king factor, the as&O<:iated pO'Her of lhe d:11maged fuel= 3559 Mwth

• 0.0()2578. ~.7 = ~5.597 MWlh.

This accident artal)'Sis evaluales !hie movemenn of fuel ttist has decayed a minimum or 24 lhourPiil since iloooupied part of a or:itlcal raar::tor cor-e.

2.2. Gap Actlvljy This ca~lation - applleabre to fuel who&e bur1111up and power lll1'liit;s. are bounded by those spec:med mRG 1. 1SJ. 'fooa!"Kl!e 11.

• 111;W;"S applieatiOl't or th& gap actirJity ft.actions t.ar Non-1Loss of Coolan' A.cclderit (LOCA) events pe ,of RG 1.183, which are as follows:

5% Gf lhe nobl~ gases (eJ<ciudlnig K'l'-85) (Atrium-10 part-10% o the Kr-85 length rods are 5% of lhe lodlrte lnventtol)I (exciudit'llg t-131) evaluated in 8% of ~e 1*131 Attachment H) 12% of ttie Alka!i melal jnvennoiy The nob3e 9alii allbd iodine inventories ere ptrovfded fQr RADTRAD U$e in Ollie Re&ea&e*Fraction

.aml Timing (~rfl") ffle *~salle ast ilha.rfr 1ila inclooed as A.ttachmen~ 0. Becausio RADTRAD does not low ~()'!' appli:eatloo o~ Isotope spedftc releE1se fractions, the Nuclide lnform~tioo File

("nlf"') rue "l:scs ast source terms kif fha.n~r. rncl!Jd~ as Attachmient C, Is modified to aocommotlab!t the dinterential gap activities amClngi lhfl halogen (lm131) ainel nle gas {Kr-65}

gap fracticms diele1ed by RG 1.183 (Ref. 2} shown above. Thell'efOfe. the ini~ial activity Of

Isotope 1*131 and Kr-85 am multiplied by HI arid 2.0, ,respedlvely, In ~his "nlf' rille In order eo accommodaue the respec'lfve 10% and 8% r-OOease fradions cfirected' by r,egulatOI)' guidance

{Ref, 2).

2. 3. Pool Deconitemln* tlo.n Factor (DF)

Anadllrnenl E prlY\lide-.s assessmflnit$ of worst-case waUtr coverage and *tuea damage or FHAs over the reactor well ealld lhe spent fueO pool * .and demonsrrates th:irt Ute drop ov~ the reactor wot! ie mw.a limiting and ttiere-1Qra lhe bQuridmg case. This i!S due 'to the graalet number of fuel ll'C<ls dam~ed for the TNctor we" drqp (117 for file spent fuel pool drop w.. 172 for 1he reactor INflll drop*fos Om bQunding 10-.X~ Ofillel a:rray, or a ~of 68.0%). and I

• e tad thait !he fower 'ltlan

ATTACHMENT H - ATRIUM-10 PART-LENGTH ROD EVALUATION L-003067 Rev. 2D Page H-1 of H-14 PURPOSE/OVERVIEW IR 1647125 identified a concern with excessive exposure in part-length rods for LaSalle 1 Cycle 16. Subsequently IR 2537519 was written to document the condition as it relates to Alternative Source Terms (AST) Regulatory Guide (RG) 1.183 footnote limitation of 62 GWD/MTU for non-LOCA gap release fractions specified in Table 3 of the RG. The other RG 1.183 footnote limitation of 6.3 kW/ft for rod average burnup exceeding 54 GWD/MTU is not a concern for part-length rods as documented in Reference 1. Therefore, a minor revision is necessary to resolve the impact of a few part-length rods that exceed 62 GWD/MTU rod average burnup. This minor revision can be incorporated into future major revision of the design analysis by inserting this attachment in its entirety as a new attachment.

SCOPE The scope of this design analysis is limited to LaSalle station. The results and limitations of this design analysis revision are not applicable to other stations. The data evaluated supports LaSalle 1 Cycle 16, but this analysis can be utilized for other operating cycles, including at LaSalle 2, provided the fuel rod characteristics used to support the conclusions herein remain bounding.

CONCLUSIONS The impact on the AST FHA analysis of record due to operation of Atrium-10 part-length rods in excess of 62 GWD/MTU has been evaluated. A comparative analysis was performed to understand how the part-length rod compares to the full-length rod, which are co-located in the fuel bundle and experience similar nuclear operating characteristics. It was concluded that power and burnup for an Atrium-10 part-length rod is bounded by the power and burnup in the same axial portion of several neighboring full-length rods. Therefore, since the full-length rod operating characteristics bound the part-length rod, and since the power and burnup of the full-length rods comply with the RG 1.183 footnote 11 limits, it can be concluded that Atrium-10 part-length rods may operate beyond 62 GWD/MTU burnup and meet the intent of RG 1.183 (i.e. there is no increase in the non-LOCA gap release fraction required). This conclusion required an adjustment to the Atrium-10 core damage fraction. The discussion in the original analysis of record and the UFSAR (Table 15.7-21) should be updated to reflect that Atrium-10 part-length rods are treated separately with respect to the RG 1.183 footnote 11 limits.

METHODOLOGY The methodology associated with this design analysis is the Alternative Source Term (AST) as defined in RG 1.183. A part of this methodology is the gap release fractions for non-LOCA events like FHA as specified in Table 3 of RG 1.183. These fractions were developed prior to July 2000 and do not explicitly address part-length rods.

A calculation procedure available to assess the gap inventory is specified in ANSI/ANS-5.4-2011, Method for Calculating the Fractional Release of Volatile Fission Products from Oxide Fuel. In that calculation procedure the fractional release of fission gases is computed in a radial and axial (nodal) domain that represents the uranium oxide fuel pellet stack. The effective release fraction is then computed by a volume and power weighted average of the spatial dependent release fractions. This design analysis revision will rely on this approach to

ATTACHMENT H-ATRIUM-10 PART-LENGTH ROD EVALUATION L-003067 Rev. 20 Page H-2 of H-14 demonstrate that the gap release fraction of the part-length rod is bounded by the full-length rod, given operational characteristics inherent to the part-length rods.

The Atrium-10 part-length rod is a fuel rod that is shorter than a full-length rod and is located in the bottom portion of the core. It has less uranium content and, as a result of the axial power distribution due to voiding in the top of the core, it experiences higher rod-average exposure.

However, it is very similar to the corresponding segment of the full-length rod. Essentially the segment is the same as a full-length rod, except it has the top portion of uranium removed.

Using this equivalence aspect and the gap fraction calculation procedure a comparative analysis is performed to demonstrate that a part-length rod is bounded by a full-length rod.

Consider the following depiction of a full and part-length rod in Figure H-1.

Figure H Diagram of Full and Part-Length Fuel Rod (Not to scale; Example burnup profile from LaSalle data) 27 26 25 ~

Nodes 17 to 25 24 23 22 - ......

21 20 19 """"'"\...'1 18 17 16 ~

'L 15 "";l

~

QI 14 iii 13 ~ FLR

12 11 -B- PLR Nodes 2 10 to 16 9 Nodes 1 8 to 16 7 6

5 4 .....I' 3

~

2 -

1 ~

0 0.00 20.00 40.00 60.00 80.00 FLR PLR Bumup (GWD/ST)

Figure H-1 shows a depiction of the Atrium-10 full and part-length rods in use at LaSalle. The burnup profile shows a typical comparison of the two rods. The part-length rod has a slightly lower burnup than the corresponding portion of the full-length rod. This behavior is partly due to the decrease in neutron multiplication in the upper portion of the part-length rod as a result of the missing fueled region above node 16. This behavior forms the basis for this evaluation.

Actual plant fuel rod power and exposure data will be evaluated to confirm this behavior exists.

Once it is concluded that the part-length rod is bounded by the corresponding section of the

ATTACHMENT H - ATRIUM-10 PART-LENGTH ROD EVALUATION L-003067 Rev. 2D Page H-3 of H-14 full-length rod then it can be concluded that the corresponding full-length rod gap fission product release fraction also bounds the part-length rod. Again, as stated above, this approach can be taken because the overall fission gas release fraction is a power and spatial average over the entire rod. In other words, based on the physical process of fission gas release, if the power and burnup of the portion of fuel in the full length rod is higher than the part-length rod it is reasonable to expect that the fission gas release from that portion of fuel is larger than part-length rod.

Should the evaluation of the fuel rod data indicate that part-length rods are not bounded by the full-length rods, then the dose consequence analysis would require modification accordingly.

Since the current analysis considers an Atrium-10 core damage fraction of 0.002244 based on 156 failed rods and 91 rods per bundle an adjustment will be made to be more consistent with this full-length rod equivalency methodology used in this minor revision. The damage of 156 rods is not affected by this revision.

INPUTS Inputs to this analysis are taken from References 1, 2, and 3 and generally correspond to Atrium-10 fuel design and operating data. The inputs are referenced throughout this minor revision.

ASSUMPTIONS

1. It is assumed that the data provided Reference 1 is a bounding representation of all part-length rods in LaSalle Cycles 14 through 16. This assumption is justified by Reference 1, which states the data was extracted from the bundle (34C217) projected to host the part-length rod with the highest average exposure at end of cycle 16.

NUMERIC ANALYSIS AND RESULTS LaSalle fuel rod data was provided in Reference 1. This data corresponds to the rod histories for the LaSalle 1 Cycle 16 fuel bundle with the highest part-length rod exposure at end of cycle. This bundle was chosen to be representative of and bounding over all Atrium-10 part-length rods through LaSalle 1 Cycle 16. This bundle can also apply to other cycles and LaSalle 2, provided the fuel rod characteristics remain bounding.

The data provided in Reference 1 was reformatted and plotted to allow for comparisons of part-length rods to full-length rods, which is shown in the Appendix to this minor revision. Fuel rod design layout and axial distributions are taken from Reference 2. A review of the data shows that each part-length rod is bounded by several full-length rods for the average of nodes 2 through 16. It was determined that for all cycle depletion steps each part-length rod has at least one neighbor that is more limiting in exposure, while in most situations a part-length rod will be bounded by several neighboring rods. With respect to power, part-length rods (9,2) and (2,2) have a few instances where the part-length rod has a slightly higher power. However, the difference is between approximately 0.2 and 0.3 kW/ft, which is small and not expected to have an adverse effect on the fission gas release fraction. Note, the observation that the part-length rods are bounded by some neighboring full-length rods applies to both burnup and power. The data shows that the part-length rod is not the leading rod in terms of power and burnup in the assembly.

ATTACHMENT H - ATRIUM-10 PART-LENGTH ROD EVALUATION L-003067 Rev. 2D Page H-4 of H-14 Based on the analysis of the fuel rod data the following conclusions are made:

1. Full-length rod power and burnup in the axial region corresponding to the part-length rod (i.e. nodes 2 through 16) is typically higher than part-length rods.

2. Since the full-length rod power and burnup is more limiting, it can be used to satisfy the Regulatory Guide 1.183 footnote 11 rod power and burnup restrictions.

3. Since the fuel rod power and burnup restrictions in Regulatory Guide 1.183 footnote 11 are controlled by core design (Reference 3) and since full-length rods have been shown to bound the part-length rods, it can be concluded that this FHA analysis meets the intent of Regulatory Guide 1.183. No increase in the Regulatory Guide 1.183 Table 3 non-LOCA gap release fractions is required for part-length rods provided they are bounded by a full length rod as described above.

To provide conservatism and make the Atrium-10 portion of the current analysis of record consistent with this approach, the core damage fraction will be modified. The Atrium-10 fuel assembly at LaSalle has 8 part-length rods that have 90 inch active fuel length and 83 full-length rods that have 149 inch active fuel length (Reference 2). Therefore, a part-length rod is equivalent to 60.4% of the fueled mass of a full-length rod. Using this basis, the total equivalent full length rods in the bundle is 87.83 (8*0.604+83) and the revised core damage fraction is 0.002325 (156/87.83/764) vs. the current analysis value of 0.002244. This increase of 3.6% effectively assumes that the PLRs contain the same source term inventory as the FLRs. However, the limiting GE14 core damage fraction of 0.002578 remains bounding over Atrium-10. Therefore, there is no change in the final dose consequences of the analysis of record. With the radial peaking factor of 1.7, the release fraction becomes 0.00395. The margin between the Atrium-10 and limiting dose consequences is therefore now about 10%

(0.004382/0.003952-1).

IDENTIFICATION OF COMPUTER PROGRAMS There are no computer programs utilized in this design analysis. Only Personal Productivity Software (PPS) Excel was used for data manipulation, reformatting and display.

REFERENCES

1. NF TODI NF151446, Rev. 0, LaSalle Unit 1 Cycle 16 Limiting Bundle Edits Supporting AST Evaluation.

2. LaSalle UFSAR

a. Section 4.2.2.3, Rev. 21, Fuel Bundle.

b. Table 4.2-4(d), Rev. 17, Data for the AREVA Atrium-10 Fuel Design.

c. Figure 4.2-3d, Rev. 15, Fuel Bundle FANP Atrium-10 Type..

3. NF-AB-110-2210, Rev 16, Core Loading Pattern Development.

ATTACHMENT H - ATRIUM-10 PART-LENGTH ROD EVALUATION L-003067 Rev. 2D Page H-5 of H-14 APPENDIX - FUEL ROD DATA The following figures show data corresponding to the LaSalle 1 Cycle 16 bundle with the limiting part-length rods. This bundle is evaluated as being representative and bounding with respect to all the LaSalle 1 Cycle 16 part-length rods that are projected to exceed a rod-average burnup of 62 GWD/MTU. This data was provided in Reference 1. A pin map is provided in Figure H-10 and a description of the burnup steps is provided in Figure H-11.

Note that all burnup information is presented in the figures below in GWD/ST. A burnup of 62 GWD/MTU is equal to 56.245 GWD/ST.

In the pin exposure/power plots, the part-length rods are indicated by thick solid outline. The pin exposure/power plots are showing the behavior of the rods at approximately the beginning, middle and end of the cycle. Pin powers are expressed in kW/ft.

Figure H LaSalle 1 Cycle 14 Pin Exposure Plots Step 4 = ~BOC, Step 8 = ~MOC, Step 16 = ~EOC STEP: 4 NODE: 2-16 AVE STEP: 8 NODE: 2-16 AVE STEP: 16 NODE: 2-16 AVE 1 2 3 4 5 6 7 8 9 10 1 2 3 4 5 6 7 8 9 10 1 2 3 4 5 6 7 8 9 10 1 8.6 8.9 8.9 8.8 8.7 8.4 8.6 9.0 8.9 8.6 1 16.1 16.7 17.0 16.9 16.7 16.2 16.5 17.1 16.8 16.1 1 23.2 24.4 25.2 25.7 25.5 24.9 25.6 26.5 26.4 25.6 2 8.9 8.7 7.0 3.4 6.6 6.6 3.4 7.1 8.8 8.9 2 16.7 16.5 13.8 8.2 12.9 13.0 8.3 14.0 16.7 16.8 2 24.4 25.1 22.1 16.3 21.3 21.5 17.0 23.5 27.3 27.1 3 8.9 7.0 3.2 5.7 6.3 6.3 5.6 4.0 7.1 9.0 3 17.0 13.8 7.5 11.5 12.4 12.4 11.5 9.0 14.1 17.1 3 25.2 22.1 15.2 19.8 21.0 21.4 20.8 18.3 24.4 28.4 4 8.8 3.4 5.7 6.3 7.3 7.4 3.4 5.5 3.4 8.6 4 16.9 8.2 11.5 12.5 14.2 14.5 8.6 11.5 8.4 16.6 4 25.7 16.3 19.8 21.4 24.4 25.3 19.1 21.8 18.7 28.3 5 8.7 6.6 6.3 7.3 3.6 6.6 8.6 5 16.7 12.9 12.4 14.2 9.0 13.3 16.5 5 25.5 21.3 21.0 24.4 20.3 24.2 28.3 6 8.4 6.6 6.3 7.4 7.3 7.0 8.7 6 16.2 13.0 12.4 14.5 14.7 14.1 16.8 6 24.9 21.5 21.4 25.3 26.2 25.2 28.7 7 8.6 3.4 5.6 3.4 6.9 3.7 8.4 7 16.5 8.3 11.5 8.6 14.1 9.3 16.3 7 25.6 17.0 20.8 19.1 25.6 20.6 28.1 8 9.0 7.1 4.0 5.5 3.6 7.3 6.9 3.5 7.4 9.2 8 17.1 14.0 9.0 11.5 9.0 14.7 14.1 8.9 14.8 17.6 8 26.5 23.5 18.3 21.8 20.3 26.2 25.6 20.1 26.4 29.7 9 8.9 8.8 7.1 3.4 6.6 7.0 3.7 7.4 8.7 9.1 9 16.8 16.7 14.1 8.4 13.3 14.1 9.3 14.8 16.6 17.1 9 26.4 27.3 24.4 18.7 24.2 25.2 20.6 26.4 28.5 28.5 10 8.6 8.9 9.0 8.6 8.6 8.7 8.4 9.2 9.1 8.7 10 16.1 16.8 17.1 16.6 16.5 16.8 16.3 17.6 17.1 16.4 10 25.6 27.1 28.4 28.3 28.3 28.7 28.1 29.7 28.5 27.1 FLR-to-PLR Neighbor Ratios 1 2 3 4 5 6 7 8 9 10 1 2 3 4 5 6 7 8 9 10 1 2 3 4 5 6 7 8 9 10 1 0.99 1.02 1.03 1.35 1.33 1.29 1.02 1.02 0.98 1 0.97 1.01 1.02 1.31 1.29 1.25 1.02 1.01 0.97 1 0.93 0.97 1.01 1.21 1.20 1.17 0.97 0.97 0.94 2 1.02 1.00 0.81 0.52 1.00 1.00 0.81 1.00 1.02 2 1.01 1.00 0.83 0.64 1.00 1.00 0.84 1.00 1.01 2 0.97 1.00 0.88 0.76 1.00 1.01 0.86 1.00 1.00 3 1.03 0.81 0.37 0.87 0.96 0.96 0.46 0.81 1.03 3 1.02 0.83 0.46 0.89 0.96 0.96 0.54 0.84 1.03 3 1.01 0.88 0.61 0.93 0.99 1.01 0.67 0.90 1.04 4 1.35 0.52 0.87 4 1.31 0.64 0.89 4 1.21 0.76 0.93 5 1.33 1.00 0.96 0.51 0.94 1.22 5 1.29 1.00 0.96 0.64 0.95 1.18 5 1.20 1.00 0.99 0.81 0.96 1.12 6 1.29 1.00 0.96 1.04 1.00 1.24 6 1.25 1.00 0.96 1.04 1.00 1.19 6 1.17 1.01 1.01 1.04 1.00 1.14 7 0.99 0.52 1.20 7 1.00 0.66 1.16 7 1.02 0.82 1.12 8 1.02 0.81 0.46 0.51 1.04 0.99 0.41 0.86 1.06 8 1.02 0.84 0.54 0.64 1.04 1.00 0.54 0.89 1.06 8 0.97 0.86 0.67 0.81 1.04 1.02 0.71 0.93 1.04 9 1.02 1.00 0.81 0.94 1.00 0.52 0.86 1.00 1.05 9 1.01 1.00 0.84 0.95 1.00 0.66 0.89 1.00 1.03 9 0.97 1.00 0.90 0.96 1.00 0.82 0.93 1.00 1.00 10 0.98 1.02 1.03 1.22 1.24 1.20 1.06 1.05 1.01 10 0.97 1.01 1.03 1.18 1.19 1.16 1.06 1.03 0.98 10 0.94 1.00 1.04 1.12 1.14 1.12 1.04 1.00 0.95

ATTACHMENT H - ATRIUM-10 PART-LENGTH ROD EVALUATION L-003067 Rev. 2D Page H-6 of H-14 Figure H LaSalle 1 Cycle 15 Pin Exposure Plots Step 17 = ~BOC, Step 24 = ~MOC, Step 33 = ~EOC STEP: 17 NODE: 2-16 AVE STEP: 24 NODE: 2-16 AVE STEP: 33 NODE: 2-16 AVE 1 2 3 4 5 6 7 8 9 10 1 2 3 4 5 6 7 8 9 10 1 2 3 4 5 6 7 8 9 10 1 23.3 24.5 25.3 25.8 25.6 25.0 25.6 26.6 26.5 25.7 1 33.3 34.9 36.5 37.4 37.2 36.4 37.3 38.3 37.7 36.5 1 40.0 41.7 43.7 45.0 44.8 43.9 45.0 46.0 45.1 43.8 2 24.5 25.1 22.2 16.3 21.3 21.6 17.0 23.6 27.4 27.2 2 34.9 36.3 33.1 27.2 32.0 32.4 28.4 35.2 39.4 38.5 2 41.7 43.6 40.5 34.7 39.4 39.9 36.2 43.0 47.4 46.0 3 25.3 22.2 15.3 19.9 21.1 21.5 20.9 18.4 24.5 28.5 3 36.5 33.1 25.9 30.3 31.6 32.3 32.1 30.0 36.4 40.6 3 43.7 40.5 33.4 37.7 39.1 40.0 40.0 38.1 44.5 48.7 4 25.8 16.3 19.9 21.5 24.4 25.4 19.2 21.9 18.7 28.4 4 37.4 27.2 30.3 32.2 36.0 37.5 31.7 33.8 31.0 40.9 4 45.0 34.7 37.7 39.8 44.1 45.8 40.3 42.2 39.4 49.3 5 25.6 21.3 21.1 24.4 20.4 24.3 28.3 5 37.2 32.0 31.6 36.0 33.3 36.4 40.8 5 44.8 39.4 39.1 44.1 42.1 44.7 49.3 6 25.0 21.6 21.5 25.4 26.3 25.3 28.8 6 36.4 32.4 32.3 37.5 38.9 37.5 41.3 6 43.9 39.9 40.0 45.8 47.4 45.9 49.8 7 25.6 17.0 20.9 19.2 25.7 20.7 28.2 7 37.3 28.4 32.1 31.7 38.2 33.3 40.5 7 45.0 36.2 40.0 40.3 46.8 41.9 48.8 8 26.6 23.6 18.4 21.9 20.4 26.3 25.7 20.2 26.5 29.8 8 38.3 35.2 30.0 33.8 33.3 38.9 38.2 32.9 38.9 42.1 8 46.0 43.0 38.1 42.2 42.1 47.4 46.8 41.7 47.4 50.4 9 26.5 27.4 24.5 18.7 24.3 25.3 20.7 26.5 28.6 28.6 9 37.7 39.4 36.4 31.0 36.4 37.5 33.3 38.9 40.8 40.2 9 45.1 47.4 44.5 39.4 44.7 45.9 41.9 47.4 49.0 48.0 10 25.7 27.2 28.5 28.4 28.3 28.8 28.2 29.8 28.6 27.2 10 36.5 38.5 40.6 40.9 40.8 41.3 40.5 42.1 40.2 38.3 10 43.8 46.0 48.7 49.3 49.3 49.8 48.8 50.4 48.0 46.0 FLR-to-PLR Neighbor Ratios 1 2 3 4 5 6 7 8 9 10 1 2 3 4 5 6 7 8 9 10 1 2 3 4 5 6 7 8 9 10 1 0.93 0.97 1.01 1.21 1.20 1.17 0.97 0.97 0.94 1 0.92 0.96 1.00 1.17 1.16 1.14 0.97 0.96 0.93 1 0.92 0.96 1.00 1.14 1.14 1.12 0.97 0.95 0.92 2 0.97 1.00 0.88 0.77 1.00 1.01 0.86 1.00 0.99 2 0.96 1.00 0.91 0.85 1.00 1.01 0.89 1.00 0.98 2 0.96 1.00 0.93 0.88 1.00 1.01 0.91 1.00 0.97 3 1.01 0.88 0.61 0.93 0.99 1.01 0.67 0.90 1.04 3 1.00 0.91 0.71 0.95 0.99 1.01 0.76 0.92 1.03 3 1.00 0.93 0.77 0.96 0.99 1.02 0.80 0.94 1.03 4 1.21 0.77 0.93 4 1.17 0.85 0.95 4 1.14 0.88 0.96 5 1.20 1.00 0.99 0.81 0.96 1.12 5 1.16 1.00 0.99 0.89 0.97 1.09 5 1.14 1.00 0.99 0.92 0.98 1.07 6 1.17 1.01 1.01 1.04 1.00 1.14 6 1.14 1.01 1.01 1.04 1.00 1.10 6 1.12 1.01 1.02 1.03 1.00 1.09 7 1.02 0.82 1.12 7 1.02 0.89 1.08 7 1.02 0.91 1.06 8 0.97 0.86 0.67 0.81 1.04 1.02 0.71 0.93 1.04 8 0.97 0.89 0.76 0.89 1.04 1.02 0.81 0.95 1.03 8 0.97 0.91 0.80 0.92 1.03 1.02 0.85 0.97 1.03 9 0.97 1.00 0.90 0.96 1.00 0.82 0.93 1.00 1.00 9 0.96 1.00 0.92 0.97 1.00 0.89 0.95 1.00 0.98 9 0.95 1.00 0.94 0.98 1.00 0.91 0.97 1.00 0.98 10 0.94 0.99 1.04 1.12 1.14 1.12 1.04 1.00 0.95 10 0.93 0.98 1.03 1.09 1.10 1.08 1.03 0.98 0.94 10 0.92 0.97 1.03 1.07 1.09 1.06 1.03 0.98 0.94

ATTACHMENT H - ATRIUM-10 PART-LENGTH ROD EVALUATION L-003067 Rev. 2D Page H-7 of H-14 Figure H LaSalle 1 Cycle 16 Pin Exposure Plots Step 34 = ~BOC, Step 41 = ~MOC, Step 50 = ~EOC STEP: 34 NODE: 2-16 AVE STEP: 41 NODE: 2-16 AVE STEP: 50 NODE: 2-16 AVE 1 2 3 4 5 6 7 8 9 10 1 2 3 4 5 6 7 8 9 10 1 2 3 4 5 6 7 8 9 10 1 39.9 41.6 43.6 44.9 44.7 43.8 45.0 45.9 45.1 43.8 1 45.3 47.1 49.4 51.0 50.7 49.7 50.8 51.5 50.3 48.8 1 49.5 51.3 53.7 55.5 55.2 54.1 55.2 55.7 54.2 52.7 2 41.6 43.5 40.4 34.6 39.3 39.9 36.2 43.0 47.4 46.0 2 47.1 49.3 46.1 40.4 45.0 45.5 41.9 48.6 52.8 51.0 2 51.3 53.6 50.5 44.8 49.2 49.8 46.3 52.8 56.9 54.8 3 43.6 40.4 33.3 37.7 39.1 40.0 40.0 38.1 44.5 48.7 3 49.4 46.1 39.0 43.2 44.6 45.5 45.5 43.7 50.0 53.9 3 53.7 50.5 43.4 47.5 48.8 49.7 49.8 48.0 54.1 57.9 4 44.9 34.6 37.7 39.8 44.1 45.8 40.3 42.2 39.4 49.3 4 51.0 40.4 43.2 45.3 49.6 51.4 46.0 47.8 45.0 54.6 4 55.5 44.8 47.5 49.4 53.8 55.6 50.3 52.1 49.2 58.7 5 44.7 39.3 39.1 44.1 42.1 44.8 49.3 5 50.7 45.0 44.6 49.6 47.8 50.2 54.6 5 55.2 49.2 48.8 53.8 52.1 54.3 58.7 6 43.8 39.9 40.0 45.8 47.4 45.9 49.8 6 49.7 45.5 45.5 51.4 52.9 51.3 55.1 6 54.1 49.8 49.7 55.6 57.0 55.4 59.1 7 45.0 36.2 40.0 40.3 46.8 42.0 48.9 7 50.8 41.9 45.5 46.0 52.2 47.5 54.1 7 55.2 46.3 49.8 50.3 56.3 51.6 58.0 8 45.9 43.0 38.1 42.2 42.1 47.4 46.8 41.7 47.4 50.4 8 51.5 48.6 43.7 47.8 47.8 52.9 52.2 47.3 52.7 55.6 8 55.7 52.8 48.0 52.1 52.1 57.0 56.3 51.4 56.7 59.4 9 45.1 47.4 44.5 39.4 44.8 45.9 42.0 47.4 49.0 48.0 9 50.3 52.8 50.0 45.0 50.2 51.3 47.5 52.7 54.1 52.9 9 54.2 56.9 54.1 49.2 54.3 55.4 51.6 56.7 57.9 56.6 10 43.8 46.0 48.7 49.3 49.3 49.8 48.9 50.4 48.0 46.0 10 48.8 51.0 53.9 54.6 54.6 55.1 54.1 55.6 52.9 50.9 10 52.7 54.8 57.9 58.7 58.7 59.1 58.0 59.4 56.6 54.6 FLR-to-PLR Neighbor Ratios 1 2 3 4 5 6 7 8 9 10 1 2 3 4 5 6 7 8 9 10 1 2 3 4 5 6 7 8 9 10 1 0.92 0.96 1.00 1.14 1.14 1.11 0.97 0.95 0.92 1 0.92 0.96 1.00 1.13 1.13 1.11 0.98 0.95 0.92 1 0.92 0.96 1.00 1.13 1.12 1.10 0.98 0.95 0.93 2 0.96 1.00 0.93 0.88 1.00 1.01 0.91 1.00 0.97 2 0.96 1.00 0.94 0.90 1.00 1.01 0.92 1.00 0.97 2 0.96 1.00 0.94 0.91 1.00 1.01 0.93 1.00 0.96 3 1.00 0.93 0.77 0.96 0.99 1.02 0.80 0.94 1.03 3 1.00 0.94 0.79 0.96 0.99 1.01 0.83 0.95 1.02 3 1.00 0.94 0.81 0.96 0.99 1.01 0.84 0.95 1.02 4 1.14 0.88 0.96 4 1.13 0.90 0.96 4 1.13 0.91 0.96 5 1.14 1.00 0.99 0.92 0.98 1.07 5 1.13 1.00 0.99 0.93 0.98 1.07 5 1.12 1.00 0.99 0.94 0.98 1.06 6 1.11 1.01 1.02 1.03 1.00 1.09 6 1.11 1.01 1.01 1.03 1.00 1.07 6 1.10 1.01 1.01 1.03 1.00 1.07 7 1.02 0.91 1.06 7 1.02 0.93 1.05 7 1.02 0.93 1.05 8 0.97 0.91 0.80 0.92 1.03 1.02 0.85 0.97 1.03 8 0.98 0.92 0.83 0.93 1.03 1.02 0.87 0.97 1.03 8 0.98 0.93 0.84 0.94 1.03 1.02 0.89 0.98 1.03 9 0.95 1.00 0.94 0.98 1.00 0.91 0.97 1.00 0.98 9 0.95 1.00 0.95 0.98 1.00 0.93 0.97 1.00 0.98 9 0.95 1.00 0.95 0.98 1.00 0.93 0.98 1.00 0.98 10 0.92 0.97 1.03 1.07 1.09 1.06 1.03 0.98 0.94 10 0.92 0.97 1.02 1.07 1.07 1.05 1.03 0.98 0.94 10 0.93 0.96 1.02 1.06 1.07 1.05 1.03 0.98 0.94

ATTACHMENT H - ATRIUM-10 PART-LENGTH ROD EVALUATION L-003067 Rev. 2D Page H-8 of H-14 Figure H LaSalle 1 Cycle 14 Pin Power Plots Step 4 = ~BOC, Step 8 = ~MOC, Step 16 = ~EOC STEP: 4 NODE: 2-16 AVE STEP: 8 NODE: 2-16 AVE STEP: 16 NODE: 2-16 AVE 1 2 3 4 5 6 7 8 9 10 1 2 3 4 5 6 7 8 9 10 1 2 3 4 5 6 7 8 9 10 1 7.4 7.5 7.6 7.6 7.5 7.3 7.4 7.7 7.7 7.5 1 7.1 7.3 7.6 7.7 7.6 7.4 7.5 7.6 7.4 7.0 1 5.8 5.7 5.9 6.0 6.0 5.8 6.0 5.9 5.6 5.3 2 7.5 7.3 6.2 3.7 5.8 5.8 3.7 6.3 7.5 7.7 2 7.3 7.4 6.6 5.2 6.2 6.3 5.3 6.7 7.5 7.3 2 5.7 5.6 5.2 4.5 4.9 5.0 4.7 5.3 5.6 5.4 3 7.5 6.2 3.4 5.2 5.5 5.6 5.2 4.1 6.3 7.8 3 7.6 6.6 4.7 5.8 5.9 6.0 6.0 5.3 6.8 7.6 3 5.8 5.2 4.2 4.6 4.7 4.8 5.0 4.8 5.3 5.6 4 7.5 3.7 5.1 5.5 6.3 6.4 3.8 5.2 3.8 7.5 4 7.7 5.2 5.8 6.0 6.6 6.9 5.6 6.3 5.4 7.6 4 6.0 4.4 4.6 4.7 5.1 5.4 5.0 5.2 4.8 5.7 5 7.4 5.7 5.5 6.3 4.0 6.0 7.5 5 7.6 6.2 5.9 6.6 5.9 6.7 7.6 5 5.9 4.9 4.7 5.1 5.1 5.3 5.7 6 7.2 5.8 5.5 6.4 6.5 6.3 7.6 6 7.4 6.3 6.0 6.9 7.1 6.9 7.6 6 5.8 5.0 4.8 5.4 5.5 5.3 5.7 7 7.3 3.7 5.1 3.7 6.3 4.1 7.4 7 7.6 5.3 6.0 5.6 7.0 6.0 7.5 7 5.9 4.6 4.9 4.9 5.5 4.9 5.6 8 7.6 6.2 4.0 5.2 3.9 6.5 6.3 3.9 6.6 7.9 8 7.6 6.7 5.3 6.3 5.9 7.2 7.0 5.8 7.2 7.8 8 5.8 5.2 4.7 5.1 5.1 5.5 5.4 4.9 5.4 5.6 9 7.5 7.3 6.2 3.7 5.9 6.2 4.1 6.6 7.4 7.8 9 7.4 7.5 6.8 5.4 6.7 6.9 6.0 7.2 7.5 7.4 9 5.5 5.5 5.2 4.7 5.2 5.3 4.9 5.4 5.4 5.3 10 7.3 7.5 7.6 7.4 7.4 7.5 7.3 7.8 7.7 7.5 10 7.0 7.3 7.6 7.6 7.6 7.6 7.5 7.8 7.4 7.1 10 5.1 5.2 5.5 5.6 5.6 5.6 5.5 5.5 5.2 5.0 FLR-to-PLR Neighbor Ratios 1 2 3 4 5 6 7 8 9 10 1 2 3 4 5 6 7 8 9 10 1 2 3 4 5 6 7 8 9 10 1 1.01 1.03 1.04 1.31 1.30 1.26 1.03 1.03 1.00 1 0.96 0.99 1.02 1.24 1.22 1.19 1.02 0.99 0.94 1 1.03 1.02 1.05 1.22 1.20 1.18 1.05 1.00 0.94 2 1.02 1.00 0.84 0.64 1.00 1.00 0.84 1.00 1.03 2 0.99 1.00 0.90 0.83 1.00 1.01 0.90 1.00 0.98 2 1.02 1.00 0.93 0.90 1.00 1.01 0.95 1.00 0.96 3 1.03 0.84 0.47 0.89 0.95 0.96 0.55 0.85 1.04 3 1.02 0.90 0.64 0.92 0.95 0.97 0.71 0.91 1.02 3 1.04 0.92 0.76 0.94 0.95 0.98 0.85 0.95 1.00 4 1.31 0.64 0.90 4 1.24 0.83 0.92 4 1.22 0.90 0.94 5 1.29 1.00 0.95 0.63 0.95 1.19 5 1.22 1.00 0.95 0.86 0.97 1.10 5 1.20 1.00 0.95 0.96 0.99 1.06 6 1.25 1.00 0.96 1.03 1.00 1.20 6 1.19 1.01 0.97 1.04 1.00 1.11 6 1.17 1.01 0.98 1.04 1.00 1.06 7 1.00 0.65 1.18 7 1.02 0.87 1.09 7 1.02 0.92 1.04 8 1.03 0.85 0.55 0.63 1.04 1.00 0.53 0.89 1.07 8 1.02 0.90 0.71 0.86 1.04 1.02 0.77 0.96 1.04 8 1.05 0.95 0.86 0.96 1.04 1.03 0.91 1.00 1.04 9 1.02 1.00 0.85 0.95 1.00 0.66 0.89 1.00 1.05 9 0.99 1.00 0.91 0.97 1.00 0.87 0.96 1.00 0.99 9 0.99 1.00 0.95 0.99 1.00 0.93 1.00 1.00 0.97 10 1.00 1.02 1.04 1.18 1.20 1.17 1.06 1.04 1.02 10 0.94 0.98 1.02 1.10 1.11 1.09 1.04 0.99 0.95 10 0.93 0.95 1.00 1.05 1.06 1.04 1.02 0.97 0.93

ATTACHMENT H - ATRIUM-10 PART-LENGTH ROD EVALUATION L-003067 Rev. 2D Page H-9 of H-14 Figure H LaSalle 1 Cycle 15 Pin Power Plots Step 17 = ~BOC, Step 24 = ~MOC, Step 33 = ~EOC STEP: 17 NODE: 2-16 AVE STEP: 24 NODE: 2-16 AVE STEP: 33 NODE: 2-16 AVE 1 2 3 4 5 6 7 8 9 10 1 2 3 4 5 6 7 8 9 10 1 2 3 4 5 6 7 8 9 10 1 5.4 5.5 5.7 5.9 5.8 5.8 5.9 5.9 5.7 5.4 1 5.5 5.5 5.7 5.9 5.8 5.7 5.8 5.7 5.3 5.0 1 4.6 4.5 4.6 4.7 4.7 4.6 4.7 4.6 4.3 4.1 2 5.5 5.6 5.3 4.6 5.2 5.3 4.9 5.6 5.9 5.6 2 5.5 5.5 5.3 4.7 5.1 5.1 4.8 5.3 5.4 5.0 2 4.5 4.4 4.3 3.9 4.2 4.2 3.9 4.3 4.2 4.0 3 5.6 5.3 4.5 5.0 5.1 5.3 5.5 5.3 5.8 6.0 3 5.7 5.3 4.6 4.9 4.9 5.0 5.1 4.9 5.2 5.2 3 4.6 4.3 3.8 4.1 4.0 4.1 4.2 4.0 4.2 4.2 4 5.8 4.6 5.0 5.2 5.8 6.1 5.6 5.8 5.4 6.2 4 5.9 4.7 4.9 5.0 5.2 5.4 5.0 5.3 4.8 5.3 4 4.8 3.9 4.1 4.1 4.2 4.3 4.0 4.3 3.9 4.2 5 5.8 5.1 5.1 5.7 5.8 5.9 6.2 5 5.8 5.1 4.9 5.2 5.0 5.2 5.3 5 4.7 4.2 4.1 4.2 4.0 4.2 4.2 6 5.7 5.2 5.3 6.1 6.3 6.0 6.2 6 5.7 5.1 5.0 5.4 5.4 5.2 5.3 6 4.7 4.2 4.1 4.3 4.3 4.2 4.2 7 5.8 4.9 5.5 5.6 6.2 5.6 6.1 7 5.8 4.8 5.1 5.0 5.4 4.8 5.2 7 4.7 3.9 4.2 4.0 4.3 3.8 4.1 8 5.9 5.6 5.3 5.9 5.8 6.3 6.3 5.7 6.2 6.2 8 5.6 5.3 4.9 5.3 5.0 5.4 5.4 4.9 5.3 5.2 8 4.6 4.3 4.0 4.3 4.0 4.3 4.3 3.9 4.1 4.1 9 5.7 6.0 5.9 5.5 6.1 6.1 5.7 6.2 6.2 5.9 9 5.3 5.4 5.3 4.8 5.3 5.3 4.9 5.3 5.1 4.9 9 4.3 4.2 4.2 3.8 4.2 4.1 3.8 4.1 4.0 3.9 10 5.5 5.8 6.2 6.4 6.4 6.4 6.3 6.4 5.9 5.6 10 5.0 5.0 5.3 5.4 5.4 5.3 5.2 5.2 4.9 4.8 10 4.1 4.1 4.2 4.2 4.2 4.2 4.1 4.1 3.9 4.0 FLR-to-PLR Neighbor Ratios 1 2 3 4 5 6 7 8 9 10 1 2 3 4 5 6 7 8 9 10 1 2 3 4 5 6 7 8 9 10 1 0.97 0.98 1.02 1.13 1.13 1.11 0.99 0.95 0.90 1 1.01 1.01 1.04 1.15 1.14 1.12 1.06 0.98 0.93 1 1.04 1.03 1.05 1.14 1.13 1.11 1.08 1.01 0.98 2 0.98 1.00 0.95 0.90 1.00 1.02 0.95 1.00 0.95 2 1.00 1.00 0.96 0.93 1.00 1.01 0.99 1.00 0.93 2 1.03 1.00 0.97 0.93 1.00 1.00 1.01 1.00 0.95 3 1.02 0.95 0.81 0.97 0.99 1.02 0.88 0.98 1.01 3 1.03 0.96 0.84 0.97 0.96 0.98 0.92 0.98 0.97 3 1.05 0.97 0.86 0.98 0.97 0.98 0.94 0.99 0.98 4 1.13 0.90 0.98 4 1.14 0.93 0.97 4 1.14 0.93 0.97 5 1.12 1.00 1.00 0.96 0.99 1.03 5 1.13 1.00 0.97 0.96 1.00 1.01 5 1.13 1.00 0.97 0.96 1.00 1.01 6 1.11 1.02 1.03 1.04 1.00 1.03 6 1.11 1.01 0.98 1.03 1.00 1.01 6 1.11 1.00 0.98 1.03 1.00 1.01 7 1.04 0.93 1.02 7 1.03 0.92 0.99 7 1.02 0.92 0.99 8 0.98 0.94 0.88 0.95 1.04 1.03 0.92 1.00 1.01 8 1.05 0.99 0.91 0.96 1.03 1.02 0.96 1.03 1.01 8 1.08 1.01 0.94 0.96 1.03 1.03 0.97 1.03 1.02 9 0.95 1.00 0.98 0.99 1.00 0.93 1.01 1.00 0.95 9 0.98 1.00 0.98 1.00 1.00 0.93 1.03 1.00 0.95 9 1.01 1.00 0.99 1.00 1.00 0.92 1.03 1.00 0.98 10 0.91 0.96 1.03 1.04 1.05 1.03 1.03 0.96 0.91 10 0.93 0.94 0.98 1.02 1.02 1.00 1.02 0.96 0.94 10 0.98 0.96 0.99 1.01 1.01 1.00 1.02 0.98 0.99

ATTACHMENT H - ATRIUM-10 PART-LENGTH ROD EVALUATION L-003067 Rev. 2D Page H-10 of H-14 Figure H LaSalle 1 Cycle 16 Pin Power Plots Step 34 = ~BOC, Step 41 = ~MOC, Step 50 = ~EOC STEP: 34 NODE: 2-16 AVE STEP: 41 NODE: 2-16 AVE STEP: 50 NODE: 2-16 AVE 1 2 3 4 5 6 7 8 9 10 1 2 3 4 5 6 7 8 9 10 1 2 3 4 5 6 7 8 9 10 1 2.8 2.9 3.1 3.2 3.3 3.3 3.4 3.4 3.2 3.2 1 2.4 2.6 2.8 2.9 3.0 3.0 3.1 3.1 3.0 3.1 1 1.7 1.8 1.9 2.1 2.1 2.1 2.2 2.2 2.2 2.3 2 2.6 2.7 2.7 2.5 2.8 2.9 2.7 3.0 3.1 3.0 2 2.3 2.4 2.5 2.4 2.6 2.7 2.6 2.9 2.9 2.9 2 1.6 1.6 1.7 1.6 1.8 1.9 1.8 2.0 2.0 2.1 3 2.6 2.5 2.3 2.6 2.6 2.7 2.8 2.8 3.0 3.1 3 2.2 2.3 2.2 2.4 2.5 2.6 2.7 2.6 2.8 2.9 3 1.5 1.6 1.5 1.7 1.7 1.8 1.9 1.8 2.0 2.1 4 2.6 2.2 2.4 2.5 2.7 2.8 2.7 2.9 2.7 3.1 4 2.2 2.0 2.3 2.3 2.5 2.6 2.5 2.7 2.6 2.9 4 1.5 1.4 1.6 1.6 1.7 1.8 1.7 1.9 1.8 2.1 5 2.5 2.3 2.4 2.6 2.7 2.9 3.0 5 2.1 2.1 2.2 2.3 2.5 2.7 2.9 5 1.4 1.4 1.5 1.6 1.7 1.9 2.0 6 2.4 2.3 2.3 2.6 2.8 2.8 3.0 6 2.1 2.1 2.1 2.3 2.6 2.6 2.8 6 1.4 1.4 1.5 1.6 1.8 1.8 2.0 7 2.3 2.1 2.3 2.3 2.7 2.5 2.8 7 2.0 1.9 2.1 2.1 2.5 2.4 2.7 7 1.3 1.3 1.4 1.4 1.7 1.6 1.9 8 2.2 2.2 2.2 2.4 2.3 2.5 2.6 2.4 2.7 2.8 8 1.9 2.0 1.9 2.2 2.1 2.3 2.4 2.3 2.5 2.6 8 1.3 1.3 1.3 1.5 1.4 1.6 1.6 1.5 1.7 1.8 9 2.0 2.1 2.2 2.1 2.3 2.4 2.2 2.5 2.5 2.6 9 1.7 1.8 1.9 1.9 2.1 2.1 2.0 2.3 2.3 2.4 9 1.2 1.2 1.3 1.3 1.4 1.4 1.4 1.6 1.6 1.7 10 1.9 1.9 2.1 2.2 2.2 2.3 2.3 2.3 2.3 2.5 10 1.6 1.7 1.8 1.9 2.0 2.0 2.1 2.1 2.2 2.4 10 1.1 1.2 1.2 1.3 1.3 1.4 1.4 1.5 1.5 1.7 FLR-to-PLR Neighbor Ratios 1 2 3 4 5 6 7 8 9 10 1 2 3 4 5 6 7 8 9 10 1 2 3 4 5 6 7 8 9 10 1 1.03 1.07 1.15 1.16 1.17 1.18 1.09 1.04 1.03 1 1.01 1.07 1.15 1.12 1.15 1.16 1.08 1.05 1.07 1 1.04 1.10 1.18 1.13 1.15 1.17 1.09 1.08 1.13 2 0.96 1.00 1.02 0.91 1.00 1.03 0.99 1.00 0.98 2 0.95 1.00 1.04 0.90 1.00 1.03 0.99 1.00 1.01 2 0.96 1.00 1.05 0.90 1.00 1.03 0.99 1.00 1.04 3 0.96 0.94 0.87 0.92 0.94 0.98 0.90 0.97 1.00 3 0.93 0.95 0.90 0.92 0.95 0.98 0.91 0.98 1.01 3 0.93 0.95 0.91 0.92 0.94 0.98 0.91 0.97 1.03 4 1.09 0.95 1.04 4 1.05 0.96 1.07 4 1.04 0.96 1.08 5 1.06 1.00 1.02 0.96 1.02 1.07 5 1.01 1.00 1.03 0.95 1.03 1.08 5 1.00 1.00 1.04 0.95 1.03 1.11 6 1.02 0.98 1.00 1.00 1.00 1.05 6 0.97 0.98 1.01 0.99 1.00 1.06 6 0.96 0.97 1.02 0.99 1.00 1.08 7 0.97 0.90 1.01 7 0.96 0.90 1.02 7 0.96 0.90 1.04 8 1.05 1.05 1.02 0.98 1.07 1.10 0.98 1.07 1.11 8 1.03 1.06 1.05 0.97 1.08 1.11 0.97 1.07 1.13 8 1.03 1.06 1.08 0.98 1.09 1.12 0.97 1.07 1.16 9 0.95 1.00 1.03 0.98 1.00 0.95 1.00 1.00 1.03 9 0.94 1.00 1.05 0.97 1.00 0.96 0.99 1.00 1.06 9 0.96 1.00 1.06 0.97 1.00 0.96 0.98 1.00 1.09 10 0.88 0.91 0.97 0.93 0.95 0.96 0.94 0.93 0.99 10 0.89 0.92 0.98 0.92 0.95 0.97 0.93 0.94 1.03 10 0.92 0.94 1.00 0.92 0.95 0.98 0.93 0.96 1.07

ATTACHMENT H-ATRIUM-10 PART-LENGTH ROD EVALUATION L-003067 Rev. 20 Page H-11 of H-14 Figure H LaSalle 1 Cycles 14 thru 16 Representative Exposure Histories Lasalle 1 PLR to FLR Comparisons, Rod Segment Lasalle 1 PLR to FLR Comparisons, Rod Segment Average Exposures Over Nodes 2-16 Average Exposures OVer Nodes 2-16 6

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ATTACHMENT H-ATRIUM-10 PART-LENGTH ROD EVALUATION L-003067 Rev. 20 Page H-12 of H-14 Figure H LaSalle 1 Cycles 14 thru 16 Representative Power Histories Lasalle 1 PLR to FLR Comparisons, Rod Segment Average Powers Lasalle 1 PLR to FLR Comparisons, Rod Segment Average Powers Over Nodes 2-16 Over Nodes 2-16 90 . - - - - - - - - - - - - - - - - - - - - - - - - - - 10.0 ~---------------------

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ATTACHMENT H - ATRIUM-10 PART-LENGTH ROD EVALUATION L-003067 Rev. 2D Page H-13 of H-14 Figure H LaSalle Atrium-10 Pin Layout This geometry in this figure is derived from Reference 2.c Moderate fuel rod burnup Leading FLR burnup 1 2 3 4 5 6 7 8 9 10 1

2 P P P 3

4 5 P 6 P 7

8 9 P P P 10

ATTACHMENT H - ATRIUM-10 PART-LENGTH ROD EVALUATION L-003067 Rev. 2D Page H-14 of H-14 Figure H-11 Burnup Step Map to Cycle Exposure CYCLE CYCLE CYCLE BURNUP EXPOSURE BURNUP EXPOSURE BURNUP EXPOSURE STEP CYCLE (GWD/ST) STEP CYCLE (GWD/ST) STEP CYCLE (GWD/ST) 1 14 0.06 17 15 0.057 34 16 0.036 2 14 1.78 18 15 1.826 35 16 1.732 3 14 1.801 19 15 1.846 36 16 1.775 4 14 4.381 20 15 4.129 37 16 4.299 5 14 4.402 21 15 4.149 38 16 4.342 6 14 6.504 22 15 6.388 39 16 6.33 7 14 6.549 23 15 6.432 40 16 6.373 8 14 8.77 24 15 8.831 41 16 8.735 9 14 8.792 25 15 8.874 42 16 8.778 10 14 10.07 26 15 9.971 43 16 10.178 11 14 10.115 27 15 9.99 44 16 10.221 12 14 12.552 28 15 12.436 45 16 12.7 13 14 12.597 29 15 12.478 46 16 12.701 14 14 15.057 30 15 14.714 47 16 14.05 15 14 15.078 31 15 14.779 48 16 14.051 16 14 16.393 32 15 15.866 49 16 15.53 33 15 16.012 50 16 16.369

ATTACHMENT 3 Technical Evaluation EC407055, "Evaluation of LaSalle Alternative Source Term Loss of Coolant Accident Dose for L2C16 and Impact of Part Length Rods with Burnup > 62 GWd/MTUs," Revision 0

EC407055 Rev. 0 Page 1 of 89 Document No.: EC407055 Revision: 0 Revision Initial Issue - All pages Rev. 0.

Summary:

Title:

Evaluation of LaSalle Alternative Source Term Loss of Coolant Accident Dose for L2C16 and Impact of Part Length Rods with Burnup > 62 GWd/MTU s Name Preparer: John Massari / Emily Yokopenic Reviewer: Shane Gardner Approver: Carlos Delahoz Review Documentation: See section 7

EC407055 Rev. 0 Page 2 of 89 Table of Contents

1. Reason for Evaluation/Scope ............................................................................................................ 3

2. Technical Task Risk/Rigor Assessment .......................................................................................... 4

3. Detailed Evaluation ............................................................................................................................. 4 3.1 Design Inputs .................................................................................................................................... 4 3.2 Assumptions ..................................................................................................................................... 6 3.3 Methodology and Use of Computer Codes...................................................................................... 7 3.4 Impacts on Core/Fuel Radionuclide Inventory.............................................................................. 7 3.5 Impacts on Off-Site and Control Room Dose ................................................................................ 10

4. Design Impact and Configuration Control Change Screening: ......................................................... 10

5. Conclusions/Findings..................................................................................................................... 10

6. References .................................................................................................................................... 12

7. Review Notes ................................................................................................................................ 13

8. Attachments ................................................................................................................................. 14 LaSalle 2 Cycle 16 Quarter Core ORIGEN2 input ..................................................................................... 14 LaSalle 2 Cycle 16 MSIV A Pathway RADTRAD Output File ..................................................................... 17 LaSalle 2 Cycle 16 MSIV B Pathway RADTRAD Output File ..................................................................... 37 LaSalle 2 Cycle 16 Containment Leakage Pathway RADTRAD Output File ............................................. 57 LaSalle 2 Cycle 16 ECCS Leakage Pathway RADTRAD Output File .......................................................... 75

EC407055 Rev. 0 Page 3 of89

1. Reason for Evaluation/Scope The purpose and limited scope of this evaluation is to perform an assessment of the impact of considering the LaSalle 2 Cycle 16 specific core design on Alternative Source Term (AST) Loss of Coolant Accident (LOCA) dose analysis, and to further show that the consequences of a small number of Part Length Rods (PLRs) in the Atrium- I 0 batch exceeding the 62,000 MWd/MTU peak rod average limit in RG 1.183 Footnote 10 will not cause LOCA doses to exceed the current Analysis of Record (AOR) results. As detailed in Table 1, there are 12 PLRs that will exceed this limit by End of Cycle (EOC) by a maximum of 849 MWd/MTU, and another 8 PLRs will come within 110 MWd/MTU of exceeding the limit (Reference 13). This assessment is prepared to respond to an NRC acceptance review question that is documented in an NRC letter dated October 31, 2016, "LaSalle County Station, Units 1 and 2, - Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding High Bumup Atrium-10 Partial Length Fuel Rods (CAC Nos. MF8442 and MF8443)."

Table 1 - List of Part Length Rods> 62 GWd/MTU in L2Cl6 (all fuel is Atrium-10)

1. PL Rod Comment Exposure (GWD/MTU) 1 62.84863 2 62.82176 3 16,2 .28073 4 1 6:2.21566 5 62.18846 I 6 62.1 8846 I I

7 62.1 5251 a 62.1 5251 9 62.06749 10 62.06749 11 62.05986 12 62.03599 13 61 .*9,7504 > n 0 MWD/MT setback 14 I 61 ,'97504 1

> 11 OMW DIMT se*lback 15 61.*91S112 > 11OMW D/MT setback 16 6'1.95112 > 11OMW DJMT setback 17' 61.9312'5 > 11o MW DJMT setback 18 61.93125 > 11 o MW DJMT setback 19 61.89082 > 11 O MW DIMT setback 20 61.89082 > 11o MW D/MT setback

EC407055 Rev. 0 Page 4 of89

2. Technical Task Risk/Rigor Assessment This Technical Evaluation is performed in accordance with CC-AA-309-101, Rev. 15. Since this evaluation is not updating design basis results use of the CC-AA-309-101 process is appropriate. A Technical Task Risk/Rigor Assessment was performed for this evaluation in accordance with HU-AA-1212, Rev 7 on 11/3/2016. This task was identified as a Risk rank of 1, based on a Medium Consequence Risk Factor and a Low Probability of Error.

3. Detailed Evaluation 3.1 Design Inputs 3.1.1 ORIGEN2 Inputs The ORIGEN2 models in L-003128 (Reference 9), which were used to generate the AST LOCA source term listed in UFSAR Table 15.6-28 using AREYA Atrium-10 equilibrium core parameters, are used in this evaluation. The model is adjusted by changing the gram mass of the uranium isotopes and batch power, as summarized in Reference

2. Two core designs were examined for this effort: the GNF2 new fuel introduction (NFI) equilibrium core design and the LaSalle Unit 2 Cycle 16 (L2Cl6) specific core design. The former was done primarily to benchmark this work to the current L-003068 LOCA AST dose analysis of Reference 12 to demonstrate that the same dose results are achieved utilizing the same fuel parameters detailed in Reference 2. For the L2Cl6 assessment, the Reference 9 model is adjusted to reflect fuel parameters for the mixed GNF2/Atrium-10 core used for L2Cl6, as shown in Table 3 (Reference 1, Table 5-1). The L2Cl6 parameters for input to ORIGEN2 are summarized below in Table 2. The actual L2Cl6 design of 702.4 effective full power days (EFPD) is also used in place of the 711 EFPD used in Reference 2 and 9 (the latter is retained as an assumption for prior cycles). The 702.44 EFPD is determined by dividing the cycle design energy of 2490841 MWd by the core rated thermal power of 3546 MWt. Note the actual L2Cl6 cycle may differ from the Reference 1 design in areas such as EOC core average exposure, which is projected to be over 500 MW d/MTU lower based on cycle performance, and slightly lower total core mass.

Table 2 - LaSalle 2 Cycle 16 ORIGEN2 summary input parameters 1/4 co re bas is power MW power MW powe r MW U235 enr batch M TU #FA cycle 1 cycle 2 cycle3 Table 3, Table3, Co l Table 3, Table 3, Col Table 3, Col batch gu235 gu238 gtotu gOxygen ColK R/4 ColJ/4 Q/4 Q/4 1 342921 814 3304 8486225 1140962 4.041% 8.4862 48 230.1 230.1 98.6 2 568371 13479067 14047438 1888660 4.045% 14.0474 76 409.6 394.9 3 499378 11939397 12438775 1672378 4.015% 12.4388 67 393 .0 g u 235 bat ch MTU

• U235e nr

• l e6 g/MTU g u 238 bat ch MTU * (1-U235e nr)

• le6g/MTU g t otU g u 235 + gu238 g Oxyge n g t ot U

• 2

• 15.994 / 238

EC407055 Rev. 0 Page 5 of 89 Table 3 - Detailed LaSalle 2 Cycle 16 Core Design (Reference 1, Table 5-1)

A B C D E F G H I J K L M N O P Q R batch batch 702.4 prior Burnup Burnup Burnup Burnup Burnup Burnup cycle 711 efpd BOC EOC BOC EOC batch batch batch BOC EOC Delta batch cyc batch batch batch type enr # kgU gwd/st gwd/st gwd/mt gwd/mt size avg enr avg kgU gwd/mt gwd/mt gwd/mt MW MW MTU 3 GNF2 3.91 8 185.552 0.000 19.741 0.000 21.761 268 4.015 185.6534 0.000 22.192 22.192 1571.9 n/a 49.7551 3 GNF2 4.1 24 185.793 0.000 19.811 0.000 21.838 3 GNF2 3.94 40 185.516 0.000 20.791 0.000 22.918 3 GNF2 3.94 20 185.531 0.000 19.948 0.000 21.989 3 GNF2 3.91 8 185.552 0.000 21.003 0.000 23.152 3 GNF2 4.1 104 185.793 0.000 19.338 0.000 21.316 3 GNF2 3.94 32 185.516 0.000 21.296 0.000 23.475 3 GNF2 3.94 32 185.531 0.000 20.966 0.000 23.111 1 ATRM10XM 3.85 2 181.256 27.328 39.173 30.124 43.181 192 4.041 176.7964 38.559 46.719 8.161 394.3567 920.44058 33.9449 1 ATRM10 4.06 80 177.049 35.137 42.670 38.732 47.036 1 ATRM10 3.97 36 176.473 36.001 42.403 39.684 46.741 1 ATRM10 4.06 74 176.56 34.525 42.151 38.057 46.464 2 GNF2 4.03 8 184.79 19.127 39.170 21.084 43.178 304 4.046 184.8347 20.729 40.479 19.749 1579.795 1638.2343 56.18975 2 GNF2 4.02 88 184.682 19.394 37.153 21.378 40.954 2 GNF2 4.08 40 185.225 17.952 35.532 19.789 39.167 2 GNF2 4.1 40 184.982 17.776 35.310 19.595 38.923 2 GNF2 4.08 32 184.967 19.670 38.623 21.682 42.575 2 GNF2 4.03 32 184.887 19.200 37.638 21.164 41.489 2 GNF2 4.02 64 184.622 18.505 36.041 20.398 39.728 CORE AVERAGES 4.034 183.1018 16.042 32.195 17.683 35.4889 H = Column G / 0.907185 I = Column F / 0.907186 J = Sum of Column D for Batch K = Batch Avg of Column C weighted by Columns D & E L = Batch Avg of Column E weight by Column D M = Batch Avg of Column H weighted by Columns D & E N = Batch Avg of Column I weighted by Columns D & E O = N - M for Batch P = (O

• 1000) / ( J

• L

• 1000

• 702.44 )

Q = (M

• 1000) / ( J

• L

• 1000

• 711 * # prior cycles)

R = J

• L

• 1000

EC407055 Rev. 0 Page 6 of89 3.1.2 RADTRAD LOCA Dose Models The LaSalle AST LOCA RADTRAD models were obtained from Reference 12. No changes to any plant parameters are made for this evaluation. The core power of 3559 MWt (i.e., 102% of 3489 MWt) from Reference 12 is maintained. The AST LOCA analysis has several post-LOCA release pathway cases. Table 4 summarizes the base doses from Reference 12 for each of these pathways. The Current Licensing Basis (CLB) represents the dose obtained using the Reference 9 core inventory, and is the source of the doses listed in UFSAR Table 15.6-29 (note that UFSAR results are achieved from rounding each pathway to 2 decimal places prior to summing the individual pathways). The GNF2 results were generated using the core inventory from Reference 2.

Table 4 - Summary of Current LaSalle AST LOCA Dose Results (Reference 12, Table 3)

Post-LOCA Percentage Dose (rem (TEDE) RADTRAD Release Makeup Control Run EAB LPZ Paths Aow Room Number 25%CLB 1.7549 2.4285 0.2186 P25CLBOO.o0 PC Leakage 25%GNF2 l.7500 2.4278 0.2192 P25GNFOO.o0 25%CLB l.0700 0.0220 0.0182 MA25CLBOO.o0 MSJV Line A 25%GNF2 1.0685 0.0220 0.0182 MA25GNFOO.o0 25%CLB 1.2995 0.0313 0.0208 MB25CLBOO.o0 MSJV LineB 25% GNF2 1.2976 0.0313 0.0208 MB25GNFOO.o0 25%CLB 2.3695 0.0533 0.0390 Total MSIV 25%GNF2 2.3661 0.0534 0.0390 25%CLB 0.1000 0.1135 0.0103 E25CLBOO.o0 ECCS Leakage 25%GNF2 0.0999 0.1134 0.0103 E25GNFOO.o0 Reference 2, CR Shine Dose 0.0400 0.0000 0.0000 page 75 Post-LOCA 25%CLB. 4.2644; 2.5953: . .. 0.2679 *..

Total Dose 2590GNFZ'* . ' 4.2500:;....

• z.s:9451~*:* .* ~ ;, 0.268£*' .

3.2 Assumptions

1. The Fuel Management Summary Report core design for L2Cl6 (Reference 1) is assumed to provide a conservative representation of L2Cl6 given that the cycle is still in progress. This is based on the actual core mass being slightly lower (139.71 mtu versus 139.89 mtu in Reference 1), and the projected actual EOC bumup being lower.

2. For reinsert fuel (batches 1 and 2 in Table 2), the bumup achieved prior to L2Cl6 is assumed to occur in 711 EFPD cycles, with all prior cycles for a given batch having the same batch power. The purpose of these cycles is to achieve the correct L2Cl6 BOC bumup for the batch to ensure long-lived actinides and fission products are at the correct concentration. Short lived fission product activities will be driven by the L2Cl6 specific batch power and will reach equilibrium before 100 EFPD.

3. Consistent with References 2 and 9, the inventory of each isotope is determined by taking the maximum of the 100 EFPD and End of Cycle (EOC) activities. This is conservative since it will result in a dose which bounds anytime in the L2Cl6 core life even though the cycle is more than half over.

EC407055 Rev. 0 Page 7 of 89

4. For the purposes of ratioing up the batch 1 dose to account for substitution of FLRs for PLRs, the entire batch is assumed to be composed of Atrium-10 bundles, even though 2 bundles in the batch are Atrium-10XM. The Atrium-10XM bundles have a slightly lower number of effective FLRs because there are more PLRs that are slightly shorter than those in the Atrium-10 bundles. This assumption is considered appropriate since core design has indicated that none of the PLRs in Atrium-10XM bundles are projected to exceed 62 GWd/MTU rod average burnup by end of cycle. Also, given the small number of Atrium-10XM bundles, a weight average would not result in a significantly different FLR-to-PLR factor.

5. The control room gamma shine dose from Table 4 is applied without change to the L2C16 cycle specific results. This is conservative since all other pathway doses are reduced with application of the L2C16 specific core inventory inventory.

6. It is assumed that applying the FLR substitution methodology of Reference 8 to ratio up doses for bundles that have PLRs exceeding 62 GWd/MTU is a conservative means of accounting for the higher rod average burnup associated with the shorter active length of the PLR. This results in an ~3% increase in dose from bundles with such PLRs. NUREG/CR-6703 (Reference 14, p. 29) concluded that The consequences of a postulated LOCA increase by about ten percent as peak-rod burnup increases from 60 GWd/MTU to 75 GWd/MTU. In making this determination, it was noted that the NUREG did not modify the RG 1.183 Table 1 or 2 release fractions, only the core inventory. Thus, the increase in dose from the FLR substitution method appears conservative given that peak PLR rod average burnup is less than 63 GWd/MTU.

3.3 Methodology and Use of Computer Codes The ORIGEN2 computer code (References 3 and 4) is used to perform the fuel depletions in the same manner as the LaSalle analysis of record (Reference 9). ORIGEN2 is listed on the Exelon Digital Technology Software Quality Assurance (DTSQA) database under tracking number EX0004724, and has been installed, verified and executed on Virtual Machine NFW-KSQ-01, and validated in Reference 10.

The dose calculations are performed using the RADTRAD computer code version 3.03 (References 5, 6 and 7) in the same manner as the LaSalle analysis of record (Reference 12). RADTRAD is listed on the Exelon Digital Technology Software Quality Assurance (DTSQA) database under tracking number EX0009077, and has been installed, verified and executed on Virtual Machine NFW-KSQ-01, and validated in Reference 11.

All computer files associated with this evaluation have been attached at the end of this technical evaluation.

3.4 Impacts on Core/Fuel Radionuclide Inventory ORIGEN2 cases were run for the GNF2 NFI and L2C16 core designs. In addition, a third case was run to quantify the radionuclide inventory of just the Atrium-10 batch 1 by commenting out the ADD cards that save the batch 2 and 3 irradiation results to vectors -9 and -10. To convert the ORIGEN2 radionuclide output to a full core Ci/MWt basis, the results are scaled by the factor of 0.001128 (equal to 4/3546 MWt) since the batch-average inputs were determined using 1/4 core exposure information. This approach was utilized in Reference 2. The results of all three cases are summarized in Table 5 and are transferred to the NIF files used in the subsequent RADTRAD runs. The Co-58 and Co-60 activities are maintained at UFSAR Ci/MWt values for all cases, since they have been previously used for both Atrium-10 and GNF2 fuel at LaSalle, and come from NUREG/CR-6604 Table 1.4.3.2-3.

EC407055 Rev. 0 Page 8 of 89 Table 5 - GNF2 NFI, L2C16 and L2C16 Atrium-10 batch activities L2C16 Atrium GNF2 L2C16 Batch Isotope Ci/MWt Ci/MWt Ci/MWt KR-85 3.993E+02 3.816E+02 1.076E+02 KR-85M 8.390E+03 8.439E+03 7.104E+02 KR-87 1.649E+04 1.659E+04 1.346E+03 KR-88 2.327E+04 2.342E+04 1.888E+03 RB-86 6.338E+01 6.081E+01 9.845E+00 SR-89 2.840E+04 2.845E+04 3.408E+03 SR-90 3.214E+03 3.066E+03 9.005E+02 SR-91 3.835E+04 3.858E+04 3.231E+03 SR-92 4.050E+04 4.069E+04 3.560E+03 Y-90 3.306E+03 3.155E+03 9.149E+02 Y-91 3.501E+04 3.495E+04 4.716E+03 Y-92 4.062E+04 4.082E+04 3.577E+03 Y-93 4.557E+04 4.575E+04 4.221E+03 ZR-95 4.500E+04 4.510E+04 7.029E+03 ZR-97 4.668E+04 4.671E+04 4.946E+03 NB-95 4.525E+04 4.534E+04 8.644E+03 MO-99 5.075E+04 5.071E+04 5.727E+03 TC-99M 4.443E+04 4.440E+04 5.014E+03 RU-103 4.194E+04 4.175E+04 6.067E+03 RU-105 2.898E+04 2.874E+04 3.850E+03 RU-106 1.727E+04 1.666E+04 4.545E+03 RH-105 2.739E+04 2.716E+04 3.748E+03 SB-127 2.897E+03 2.886E+03 3.525E+02 SB-129 8.641E+03 8.623E+03 1.018E+03 TE-127 2.872E+03 2.861E+03 3.720E+02 TE-127M 3.848E+02 3.825E+02 7.873E+01 TE-129 8.502E+03 8.483E+03 1.003E+03 TE-129M 1.267E+03 1.263E+03 1.716E+02 TE-131M 3.871E+03 3.868E+03 4.456E+02 TE-132 3.824E+04 3.825E+04 4.311E+03 I-131 2.688E+04 2.686E+04 3.052E+03 I-132 3.884E+04 3.885E+04 4.387E+03 I-133 5.561E+04 5.559E+04 6.107E+03 I-134 6.170E+04 6.168E+04 6.702E+03

EC407055 Rev. 0 Page 9 of 89 Table 5 - GNF2 NFI, L2C16 and L2C16 Atrium-10 batch activities L2C16 Atrium GNF2 L2C16 Batch Isotope Ci/MWt Ci/MWt Ci/MWt I-135 5.196E+04 5.191E+04 5.742E+03 XE-133 5.495E+04 5.504E+04 6.121E+03 XE-135 2.223E+04 2.213E+04 3.527E+03 CS-134 7.193E+03 6.578E+03 1.995E+03 CS-136 1.955E+03 1.903E+03 3.325E+02 CS-137 4.585E+03 4.323E+03 1.345E+03 BA-139 5.093E+04 5.095E+04 5.400E+03 BA-140 4.909E+04 4.910E+04 5.228E+03 LA-140 5.025E+04 5.022E+04 5.463E+03 LA-141 4.652E+04 4.657E+04 4.893E+03 LA-142 4.546E+04 4.550E+04 4.707E+03 CE-141 4.519E+04 4.503E+04 5.697E+03 CE-143 4.442E+04 4.450E+04 4.482E+03 CE-144 3.621E+04 3.597E+04 8.316E+03 PR-143 4.310E+04 4.316E+04 4.395E+03 ND-147 1.840E+04 1.839E+04 2.001E+03 NP-239 5.378E+05 5.355E+05 6.418E+04 PU-238 1.780E+02 1.525E+02 6.671E+01 PU-239 1.230E+01 1.214E+01 3.023E+00 PU-240 1.320E+01 1.298E+01 3.365E+00 PU-241 6.373E+03 6.179E+03 2.050E+03 AM-241 1.043E+01 9.817E+00 5.014E+00 CM-242 2.239E+03 2.089E+03 7.677E+02 CM-244 2.467E+02 1.834E+02 9.464E+01

EC407055 Rev. 0 Page 10 of 89 3.5 Impacts on Off-Site and Control Room Dose Control room and off-site LOCA doses were calculated for each source term in Table 5. These calculations were performed by adjusting the nuclide inventories in the Reference 12 base case NIF file. The external shine results from Reference 12 were retained since their contribution was small and the slight core design changes would be unlikely to significantly impact shine results. The GNF2 results evaluated to benchmark the model demonstrated results consistent with those in Table 4 and are therefore not repeated.

The impact of PLRs exceeding 62,000 MWd/MTU was determined using the same method of substituting Full Length Rod (FLR) activity for PLR activity developed in Reference 8. That analysis demonstrated that every FLR in Atrium-10 fuel that meets the 62,000 MWd/MTU limit has an axial section equivalent to the PLR that exceeds the limit by more than the PLRs. Since the FLR power and burnup is more limiting, it can be used to satisfy the RG 1.183 footnote 10 burnup restrictions, and the LOCA release fractions can be applied unchanged provided FLRs are analytically substituted for PLRs which exceed 62,000 MWd/MTU. The Atrium-10 fuel assembly at LaSalle has 8 PLRs that have 90 inch active fuel length and 83 FLRs that have 149 inch active fuel length (Reference 8, p. H-4).

Therefore, a PLR is equivalent to 60.4% of the fueled mass of an FLR. Using this basis, the total equivalent full length rods in the bundle is 87.83 (8*0.604+83). For this technical evaluation, the dose contribution to all pathways for the non-Atrium-10 (other) batches in L2C16 is determined by subtracting the Atrium-10 batch contribution to dose from the total L2C16 core inventory dose. The portion of the Atrium-10 batch dose subject to FLR/PLR substitution is then increased by the ratio of 91/87.83, and then added to portion of dose from the unaffected portion of the Atrium-10 batch and the other batch, to determine the total LOCA dose. The results are provided in Table 6 for 30d control room, worst 0-2h site exclusion area boundary (EAB), and 30d low population zone (LPZ). The results indicate that all of the 1,536 PLRs in the Atrium-10 batch could have FLRs substituted without exceeding the AST LOCA current licensing basis results.

4. Design Impact and Configuration Control Change Screening:

No design change or configuration change is associated with the limited scope of this technical evaluation.

Therefore a Design Impact and Configuration Control Change Impact screening is not required for this technical evaluation.

5. Conclusions/Findings Based on this assessment, it is concluded that the small number of L2C16 PLRs that will exceed or come close to exceeding the 62,000 MWd/MTU limit by EOC, as identified in Table 1, could not result in LOCA doses exceeding the current licensing basis results.

EC407055 Rev. 0 Page 11 of 89 Table 6 - Summary of LOCA AST Doses Pathway Core Design TEDE (Rem) Reference CR EAB LPZ PC Leakage L2C16 1.7121 2.3904 0.2175 l2c16_PC25.out L2C16 - Atrium batch only 0.2788 0.3492 0.0278 l2c16_atrium_batch_only_PC25.out MSIV A L2C16 1.0537 0.0220 0.0182 l2c16_MSIVA.out L2C16 - Atrium batch only 0.1583 0.0027 0.0021 l2c16_atrium_batch_only_MSIVA.out MSIV B L2C16 1.2818 0.0313 0.0208 l2c16_MSIVB.out L2C16 - Atrium batch only 0.1852 0.0039 0.0024 l2c16_atrium_batch_only_MSIVB.out ECCS Leakage L2C16 0.0998 0.1133 0.0103 l2c16_ESF.o0 L2C16 - Atrium batch only 0.0112 0.0127 0.0012 l2c16_Atrium_ESF.o0 Pathway Total L2C16 4.1474 2.5570 0.2667 n/a L2C16 - Atrium batch only 0.6335 0.3684 0.0335 L2C16 - Other batches 3.5139 2.1886 0.2333 L2C16 - L2C16 Atrium batch only CR Shine Common 0.0400 0.0000 0.0000 Reference 12 TOTAL DOSE GNF2 4.2560 2.5945 0.2685 Table 4 Current Licensing Basis 4.2644 2.5953 0.2679 Table 4 Regulatory Limits 5 25 25 RG 1.183 L2C16 4.1874 2.5570 0.2667 L2C16 Pathway Total + CR Shine L2C16 FLR Substituted for 100% 4.2103 2.5703 0.2679 L2C16 Pathway Total Other + L2C16 of PLR in Atrium Batch Pathway Total Atrium

• 91/87.83 + CR Shine

EC407055 Rev. 0 Page 12 of 89

6. References

1. GNF-000N9237 Revision 1, Fuel Management Summary Report LaSalle 2 Cycle 16, June 2014

2. L-003696 Rev. 1, NEDC-33647P, GNF2 Fuel Design Cycle-Independent Analyses for Exelon LaSalle County Station Units 1 and 2, February 15, 2012.

3. RSIC CODE PACKAGE CCC-371, ORIGEN2.1 Isotope Generation and Depletion Code Matrix Exponential Method, May 1999.

4. ORNL/TM-11018, Standard- and Extended- Burnup PWR and BWR Reactor Models for the ORIGEN2 Computer Code, S. Ludwig, J. Renier, December 1989.

5. "RADTRAD: A Simplified Model for Radionuclide Transport and Removal and Dose Estimation", NUREG/CR-6604, SAND98-0272.

6. "RADTRAD: A Simplified Model for Radionuclide Transport and Removal and Dose Estimation", NUREG/CR-6604, SAND98-0272/1, Supplement 1.

7. "RADTRAD: A Simplified Model for Radionuclide Transport and Removal and Dose Estimation",

NUREG/CR-6604, Supplement 2

8. Calculation L-003067 Rev. 2D, Re-Analysis of Fuel Handling Accident (FHA) Using Alternative Source Terms, September 27, 2016.

9. Calculation L-003128 Rev. 1A, LaSalle Source Terms for Use in Alternative Source Terms, February 18, 2011.

10. EX0004724, Rev. 0, ORIGEN 2.1, EX0004724 TEST

SUMMARY

REPORT, October 2014.

11. EX0009077, Rev. 0, RADTRAD Version 3.03, EX0009077 TEST

SUMMARY

REPORT, June 2014.

12. Calculation L-003068 Rev. 2B, Reanalysis of Loss of Coolant Accident (LOCA) Using Alternative Source Terms, March 1, 2012.

13. TODI NF162526, L2C16 EOC Part Length Rod Exposure Data, November 3, 2016.

14. NUREG/CR-6703, Environmental Effects of Extending Fuel Burnup Above 60 GWd/MTU, January 2001.

EC407055 Rev. 0 Page 13 of 89

7. Review Notes The Technical Evaluation was independently reviewed. The evaluation provides results that directly address the purpose and scope as stated. All input data and development was independently verified to be correct against references and assumptions. Translation of the core inputs into ORIGEN2 input files was verified. RADTRAD was reviewed to ensure that the core inventory inputs were correctly input to the code. Note, the remainder of the RADTRAD inputs related to the plant parameters, release and dose conversion factors were not verified against the reference analysis of record, but rather the benchmarking of the GNF2 results against the reference were reviewed and considered to be confirmation that the RADTRAD runs were accurate to the analysis of record. RADTRAD output extraction and post-processing hand calculations were also independently verified. Alternative calculations were performed to independently verify the dose increases due to the substitution of the partial length rods with the activity of full length rods. A fairly accurate hand calculation can be performed using the Atrium-10 batch relative power (i.e. relative to average bundle power of 3546 MWt/764 or 4.64 MWt/bundle) and the relative increase due to increasing the uranium mass, both being a direct multiple on the PLR inventory (and hence dose). The relative increase due to the uranium mass increase is (139.89 MTU + (91/87.83-1)*39.9449 MTU)/139.89 MTU or 1%. The average power of the Atrium-10 bundles in L2C16 is 394.6 MWt/batch / 192 bundles/batch or 2.06 MWt/bundle leading to a relative bundle power of 0.44. Assuming that there are minor burnup and enrichment effects that increase the Atrium-10 batch dose results by 10% relative to the core average would lead to a net increase factor of 0.48% (1%*0.44*1.1) or about 0.5%. Inspection of the results corresponding to the 100% substitution of the PLRs the relative dose increase is between 0.45% and 0.55%. Thus, this independent calculation confirms the dose sensitivity results are valid. Based on the considerations provided above, the Technical Evaluation is accurate and the results are reasonable given the inputs, assumptions and methodology utilized.

EC407055 Rev. 0 Page 14 of 89

8. Attachments LaSalle 2 Cycle 16 Quarter Core ORIGEN2 input

-1

-1

-1 BAS Grams of Heavy Metal per Fuel Batch RDA PLACE FUEL into vectors -1, -2 and -3 LIP 0 0 0 LIB 0 1 2 3 657 658 659 9 3 0 1 42 PHO 0 0 0 10 RDA READ FUEL COMPOSITION FOR BATCH 3 INP -1 1 1 1 1 RDA READ FUEL COMPOSITION FOR BATCH 2 INP -2 1 1 1 1 RDA READ FUEL COMPOSITION FOR BATCH 1 INP -3 1 1 1 1 RDA TIT IRRADIATION OF LaSalle Quarter CORE L2C16 MOV -3 1 0 1.0 BATCH 1 FRESH HED 1 CHARGE RDA BATCH 1 BURNUP IN CYCLE 1 BUP IRP 50.0 230.1 1 9 4 2 IRP 100.0 230.1 9 2 4 0 IRP 150.0 230.1 2 9 4 0 IRP 200.0 230.1 9 3 4 0 IRP 250.0 230.1 3 9 4 0 IRP 300.0 230.1 9 4 4 0 IRP 350.0 230.1 4 9 4 0 IRP 400.0 230.1 9 5 4 0 IRP 450.0 230.1 5 9 4 0 IRP 500.0 230.1 9 6 4 0 IRP 550.0 230.1 6 9 4 0 IRP 600.0 230.1 9 7 4 0 IRP 650.0 230.1 7 9 4 0 IRP 711.0 230.1 9 8 4 0 BUP OPTL 4*8 8 8 8 8 8 15*8 OPTA 4*8 8 8 5 8 8 15*8 OPTF 4*8 8 8 5 8 8 15*8 RDA OUT -8 1 -1 0 MOV 8 1 0 1.0 BATCH 1 ONCE BURNED HED 1 CHARGE RDA BATCH 1 BURNUP IN CYCLE 2 BUP IRP 761.0 230.1 1 9 4 3 IRP 811.0 230.1 9 2 4 0 IRP 861.0 230.1 2 9 4 0 IRP 911.0 230.1 9 3 4 0 IRP 961.0 230.1 3 9 4 0 IRP 1011.0 230.1 9 4 4 0 IRP 1061.0 230.1 4 9 4 0 IRP 1111.0 230.1 9 5 4 0 IRP 1161.0 230.1 5 9 4 0 IRP 1211.0 230.1 9 6 4 0 IRP 1261.0 230.1 6 9 4 0 IRP 1311.0 230.1 9 7 4 0 IRP 1361.0 230.1 7 9 4 0 IRP 1422.0 230.1 9 8 4 0 BUP RDA OUT -8 1 -1 0 MOV 8 1 0 1.0 BATCH 1 TWICE BURNED HED 1 CHARGE RDA BATCH 1 BURNUP IN CYCLE 3 BUP

EC407055 Rev. 0 Page 15 of 89 IRP 1472.0 98.6 1 9 4 3 IRP 1522.0 98.6 9 2 4 0 IRP 1572.0 98.6 2 9 4 0 IRP 1622.0 98.6 9 3 4 0 IRP 1672.0 98.6 3 9 4 0 IRP 1722.0 98.6 9 4 4 0 IRP 1772.0 98.6 4 9 4 0 IRP 1822.0 98.6 9 5 4 0 IRP 1872.0 98.6 5 9 4 0 IRP 1922.0 98.6 9 6 4 0 IRP 1972.0 98.6 6 9 4 0 IRP 2022.0 98.6 9 7 4 0 IRP 2072.0 98.6 7 9 4 0 IRP 2124.4 98.6 9 8 4 0 BUP RDA OUT -8 1 -1 0 MOV 2 -9 0 1.0 BATCH 1 100 EFPD PLACED IN TEMP VECTOR -9 MOV 8 -10 0 1.0 BATCH 1 EOC3 PLACED IN TEMP VECTOR -10 RDA BATCH 2 BURNUP IN CYCLE 2 MOV -2 1 0 1.0 BATCH 2 FRESH HED 1 CHARGE RDA BATCH 2 BURNUP IN CYCLE 2 BUP IRP 50.0 409.6 1 9 4 2 IRP 100.0 409.6 9 2 4 0 IRP 150.0 409.6 2 9 4 0 IRP 200.0 409.6 9 3 4 0 IRP 250.0 409.6 3 9 4 0 IRP 300.0 409.6 9 4 4 0 IRP 350.0 409.6 4 9 4 0 IRP 400.0 409.6 9 5 4 0 IRP 450.0 409.6 5 9 4 0 IRP 500.0 409.6 9 6 4 0 IRP 550.0 409.6 6 9 4 0 IRP 600.0 409.6 9 7 4 0 IRP 650.0 409.6 7 9 4 0 IRP 711.0 409.6 9 8 4 0 BUP RDA OUT -8 1 -1 0 MOV 8 1 0 1.0 BATCH 2 ONCE BURNED HED 1 CHARGE RDA BATCH 2 BURNUP IN CYCLE 3 BUP IRP 761.0 394.9 1 9 4 3 IRP 811.0 394.9 9 2 4 0 IRP 861.0 394.9 2 9 4 0 IRP 911.0 394.9 9 3 4 0 IRP 961.0 394.9 3 9 4 0 IRP 1011.0 394.9 9 4 4 0 IRP 1061.0 394.9 4 9 4 0 IRP 1111.0 394.9 9 5 4 0 IRP 1161.0 394.9 5 9 4 0 IRP 1211.0 394.9 9 6 4 0 IRP 1261.0 394.9 6 9 4 0 IRP 1311.0 394.9 9 7 4 0 IRP 1361.0 394.9 7 9 4 0 IRP 1413.4 394.9 9 8 4 0 BUP RDA OUT -8 1 -1 0 ADD 2 -9 0 1.0 BATCH 2 100 EFPD ADDED TO TEMP VECTOR -9 ADD 8 -10 0 1.0 BATCH 2 EOC3 ADDED TO TEMP VECTOR -10 MOV -1 1 0 1.0 BATCH 3 FRESH HED 1 CHARGE RDA BATCH 3 BURNUP IN CYCLE 3 BUP IRP 50.0 393.0 1 9 4 2 IRP 100.0 393.0 9 2 4 0 IRP 150.0 393.0 2 9 4 0 IRP 200.0 393.0 9 3 4 0 IRP 250.0 393.0 3 9 4 0 IRP 300.0 393.0 9 4 4 0 IRP 350.0 393.0 4 9 4 0

EC407055 Rev. 0 Page 16 of 89 IRP 400.0 393.0 9 5 4 0 IRP 450.0 393.0 5 9 4 0 IRP 500.0 393.0 9 6 4 0 IRP 550.0 393.0 6 9 4 0 IRP 600.0 393.0 9 7 4 0 IRP 650.0 393.0 7 9 4 0 IRP 702.4 393.0 9 8 4 0 BUP RDA OUT -8 1 -1 0 ADD 2 -9 0 1.0 ADD 8 -10 0 1.0 MOV -9 1 0 1.0 CYCLE 3 @ 100 EFPD MOV -10 2 0 1.0 CYCLE 3 @ EOC HED 1 100 EFPD HED 2 EOC3 OUT -2 1 -1 0 END 2 922340 0.0 922350 499378.0 922360 0.0 922380 11939397.0 0 0.0 4 080000 1672378.0 0 0.0 0

2 922340 0.0 922350 568371.0 922360 0.0 922380 13479067.0 0 0.0 4 080000 1888660.0 0 0.0 0

2 922340 0.0 922350 342921.0 922360 0.0 922380 8143304.0 0 0.0 4 080000 1140962.0 0 0.0 0

END

EC407055 Rev. 0 Page 17 of 89 LaSalle 2 Cycle 16 MSIV A Pathway RADTRAD Output File RADTRAD Version 3.03 (Spring 2001) run on 10/31/2016 at 23:29:22 File information Plant file = C:\Users\E42031\AppData\Local\Temp\14\\temp.psf Inventory file = H:\LaSalle\Off-Site and Control Room Dose\PLR LOCA\l2c16 MSIVA\l2c16 MSIVA.nif Release file = H:\LaSalle\Off-Site and Control Room Dose\PLR LOCA\l2c16 MSIVA\l2c16 MSIVA.rft Dose Conversion file = H:\LaSalle\Off-Site and Control Room Dose\PLR LOCA\l2c16 MSIVA\l2c16 MSIVA.inp Radtrad 3.03 4/15/2001 LSCS LOCA MSIV A with 25% Makeup Nuclide Inventory File:

H:\LaSalle\Off-Site and Control Room Dose\PLR LOCA\l2c16 MSIVA\l2c16 MSIVA.nif Plant Power Level:

3.5590E+03 Compartments:

6 Compartment 1:

Containment 3

3.9430E+05 1

0 0

1 0

Compartment 2:

(Node 1) Inboard MSL A Volume 3

3.81E+02 0

0 0

0 0

Compartment 3:

(Nodes 2& 3) Outboard MSL A Volume 3

9.89E+02 0

0 0

0 0

Compartment 4:

EC407055 Rev. 0 Page 18 of 89 Condenser 3

2.4635E+05 0

0 0

0 0

Compartment 5:

Environment 2

0.0000E+00 0

0 0

0 0

Compartment 6:

Control Room 1

1.1740E+05 0

0 1

0 0

Pathways:

9 Pathway 1:

Containment to (Node 1) Inboard MSL A Volume 1

2 2

Pathway 2:

(Node 1) Inboard MSL A Volume to (Nodes 2& 3) Outboard MSL A Volume 2

3 2

Pathway 3:

(Nodes 2& 3) Outboard MSL A Volume to Condenser 3

4 2

Pathway 4:

Condenser to Environment 4

5 2

Pathway 5:

Environment to Control Room 5

6 2

Pathway 6:

Environment to Control Room 5

6 2

Pathway 7:

Environment to Control Room 5

6 2

Pathway 8:

Control Room to Environment 6

5 2

Pathway 9:

(Nodes 2& 3) Outboard MSL A Volume to Environment 3

EC407055 Rev. 0 Page 19 of 89 5

2 End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1 1.0000E+00 H:\LaSalle\Off-Site and Control Room Dose\PLR LOCA\l2c16 MSIVA\l2c16 MSIVA.inp H:\LaSalle\Off-Site and Control Room Dose\PLR LOCA\l2c16 MSIVA\l2c16 MSIVA.rft 0.0000E+00 1

9.5000E-01 4.8500E-02 1.5000E-03 1.0000E+00 Overlying Pool:

0 0.0000E+00 0

0 0

0 Compartments:

6 Compartment 1:

0 1

1 0.0000E+00 0

1 0.0000E+00 3

0.0000E+00 3.8600E+00 2.0000E+00 1.8600E+00 3.8500E+00 0.0000E+00 1

0.0000E+00 0

0 0

3 3

1.0000E+01 1

1 0.0000E+00 0.0000E+00 Compartment 2:

0 1

0 0

0 0

0 0

0 Compartment 3:

0 1

0 0

0 0

0 0

0 Compartment 4:

0 1

0

EC407055 Rev. 0 Page 20 of 89 0

0 0

0 0

0 Compartment 5:

0 1

0 0

0 0

0 0

0 Compartment 6:

0 1

0 0

0 0

1 1.4650E+04 4

0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 3.3300E-01 0.0000E+00 0.0000E+00 0.0000E+00 4.0000E+00 0.0000E+00 6.6500E+01 6.6500E+01 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0

0 Pathways:

9 Pathway 1:

0 0

0 0

0 1

3 0.0000E+00 2.9960E+00 0.0000E+00 0.0000E+00 0.0000E+00 2.0000E+00 1.7440E+00 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 0

0 Pathway 2:

0 0

0 0

0 1

6 0.0000E+00 2.9960E+00 9.8530E+01 3.1570E+01 0.0000E+00 3.3330E-01 2.9960E+00 9.9950E+01 3.1570E+01 0.0000E+00 2.0000E+00 1.7440E+00 9.9950E+01 3.1570E+01 0.0000E+00 2.4000E+01 1.7440E+00 0.0000E+00 5.0820E+01 0.0000E+00 9.6000E+01 1.7440E+00 0.0000E+00 8.6800E+01 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 0

0

EC407055 Rev. 0 Page 21 of 89 Pathway 3:

0 0

0 0

0 1

5 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 3.3300E-01 6.3760E+00 0.0000E+00 2.4680E+01 0.0000E+00 2.4000E+01 5.4920E+00 0.0000E+00 4.5990E+01 0.0000E+00 9.6000E+01 4.1670E+00 0.0000E+00 8.7720E+01 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 0

0 Pathway 4:

0 0

0 0

0 1

4 0.0000E+00 7.3230E+00 0.0000E+00 9.9370E+01 0.0000E+00 2.4000E+01 7.3230E+00 0.0000E+00 9.9370E+01 0.0000E+00 9.6000E+01 7.3230E+00 0.0000E+00 9.9370E+01 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 0

0 Pathway 5:

0 0

0 0

0 1

4 0.0000E+00 1.1000E+03 0.0000E+00 0.0000E+00 0.0000E+00 3.3330E-01 9.0000E+02 9.9000E+01 8.8440E+01 8.8440E+01 4.0000E+00 9.0000E+02 9.9000E+01 9.6130E+01 9.6130E+01 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 0

0 Pathway 6:

0 0

0 0

0 1

4 0.0000E+00 2.4000E+03 0.0000E+00 0.0000E+00 0.0000E+00 3.3330E-01 2.4000E+03 0.0000E+00 0.0000E+00 0.0000E+00 4.0000E+00 2.4000E+03 0.0000E+00 6.6500E+01 6.6500E+01 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0

EC407055 Rev. 0 Page 22 of 89 0

0 Pathway 7:

0 0

0 0

0 1

4 0.0000E+00 5.0000E+01 0.0000E+00 0.0000E+00 0.0000E+00 3.3330E-01 5.0000E+01 0.0000E+00 0.0000E+00 0.0000E+00 4.0000E+00 5.0000E+01 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 0

0 Pathway 8:

0 0

0 0

0 1

4 0.0000E+00 3.5500E+03 1.0000E+02 1.0000E+02 1.0000E+02 3.3330E-01 3.3500E+03 1.0000E+02 1.0000E+02 1.0000E+02 4.0000E+00 3.3500E+03 1.0000E+02 1.0000E+02 1.0000E+02 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 0

0 Pathway 9:

0 0

0 0

0 1

2 0.0000E+00 6.3760E+00 0.0000E+00 2.4680E+01 0.0000E+00 3.3330E-01 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 0

0 Dose Locations:

3 Location 1:

Exclusion Area Boundary 5

1 3

0.0000E+00 6.6300E-04 2.4000E+01 0.0000E+00 7.2000E+02 0.0000E+00 1

3 0.0000E+00 3.5000E-04 2.4000E+01 0.0000E+00 7.2000E+02 0.0000E+00 0

Location 2:

EC407055 Rev. 0 Page 23 of 89 Low Population Zone 5

1 8

0.0000E+00 2.6500E-05 2.5000E-01 2.6500E-05 1.5000E+00 2.6500E-05 2.0000E+00 1.0800E-05 8.0000E+00 6.8700E-06 2.4000E+01 2.6300E-06 9.6000E+01 6.7400E-07 7.2000E+02 0.0000E+00 1

4 0.0000E+00 3.5000E-04 8.0000E+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.0000E+00 0

Location 3:

Control Room 6

0 1

2 0.0000E+00 3.5000E-04 7.2000E+02 0.0000E+00 1

4 0.0000E+00 1.0000E+00 2.4000E+01 6.0000E-01 9.6000E+01 4.0000E-01 7.2000E+02 0.0000E+00 Effective Volume Location:

1 8

0.0000E+00 8.1300E-03 2.5000E-01 8.1300E-03 1.5000E+00 8.1300E-03 2.0000E+00 6.0900E-03 8.0000E+00 2.4200E-03 2.4000E+01 1.7600E-03 9.6000E+01 1.4600E-03 7.2000E+02 0.0000E+00 Simulation Parameters:

3 0.0000E+00 2.5000E-01 2.4000E+01 2.4000E+01 7.2000E+02 0.0000E+00 Output Filename:

H:\LaSalle\Off-Site and Control Room Dose\PLR LOCA\l2c16 MSIVA\l2c16 MSIVA.out 1

1 1

0 0

End of Scenario File

EC407055 Rev. 0 Page 24 of 89 RADTRAD Version 3.03 (Spring 2001) run on 10/31/2016 at 23:29:22 Plant Description Number of Nuclides = 60 Inventory Power = 1.0000E+00 MWth Plant Power Level = 3.5590E+03 MWth Number of compartments = 6 Compartment information Compartment number 1 (Source term fraction = 1.0000E+00

)

Name: Containment Compartment volume = 3.9430E+05 (Cubic feet)

Compartment type is Normal Removal devices within compartment:

Spray(s)

Deposition Pathways into and out of compartment 1 Exit Pathway Number 1: ontainment to (Node 1) Inboard MSL A Volume Compartment number 2 Name: (Node 1) Inboard MSL A Volume Compartment volume = 3.8100E+02 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 2 Inlet Pathway Number 1: ontainment to (Node 1) Inboard MSL A Volume Exit Pathway Number 2: Node 1) Inboard MSL A Volume to (Nodes 2& 3) Outbo Compartment number 3 Name: (Nodes 2& 3) Outboard MSL A Volume Compartment volume = 9.8900E+02 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 3 Inlet Pathway Number 2: Node 1) Inboard MSL A Volume to (Nodes 2& 3) Outbo Exit Pathway Number 3: Nodes 2& 3) Outboard MSL A Volume to Condenser Exit Pathway Number 9: Nodes 2& 3) Outboard MSL A Volume to Environment Compartment number 4 Name: Condenser Compartment volume = 2.4635E+05 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 4 Inlet Pathway Number 3: Nodes 2& 3) Outboard MSL A Volume to Condenser Exit Pathway Number 4: ondenser to Environment Compartment number 5 Name: Environment Compartment type is Environment Pathways into and out of compartment 5 Inlet Pathway Number 4: ondenser to Environment Inlet Pathway Number 8: ontrol Room to Environment Inlet Pathway Number 9: Nodes 2& 3) Outboard MSL A Volume to Environment Exit Pathway Number 5: nvironment to Control Room Exit Pathway Number 6: nvironment to Control Room Exit Pathway Number 7: nvironment to Control Room Compartment number 6 Name: Control Room Compartment volume = 1.1740E+05 (Cubic feet)

Compartment type is Control Room Removal devices within compartment:

Filter(s)

EC407055 Rev. 0 Page 25 of 89 Pathways into and out of compartment 6 Inlet Pathway Number 5: nvironment to Control Room Inlet Pathway Number 6: nvironment to Control Room Inlet Pathway Number 7: nvironment to Control Room Exit Pathway Number 8: ontrol Room to Environment Total number of pathways = 9

EC407055 Rev. 0 Page 26 of 89 RADTRAD Version 3.03 (Spring 2001) run on 10/31/2016 at 23:29:22 Scenario Description Radioactive Decay is enabled Calculation of Daughters is enabled Release Fractions and Timings GAP EARLY IN-VESSEL LATE RELEASE RELEASE MASS 0.500000 hr 1.5000 hrs 0.0000 hrs (gm)

NOBLES 5.0000E-02 9.5000E-01 0.0000E+00 4.551E+03 IODINE 5.0000E-02 2.5000E-01 0.0000E+00 3.060E+02 CESIUM 5.0000E-02 2.0000E-01 0.0000E+00 4.876E+04 TELLURIUM 0.0000E+00 5.0000E-02 0.0000E+00 4.042E+01 STRONTIUM 0.0000E+00 2.0000E-02 0.0000E+00 1.671E+03 BARIUM 0.0000E+00 2.0000E-02 0.0000E+00 4.796E+01 RUTHENIUM 0.0000E+00 2.5000E-03 0.0000E+00 5.864E+01 CERIUM 0.0000E+00 5.0000E-04 0.0000E+00 5.986E+02 LANTHANUM 0.0000E+00 2.0000E-04 0.0000E+00 8.157E+00 Inventory Power = 3559. MWt Nuclide Group Specific half Whole Body Inhaled Inhaled Name Inventory life DCF Thyroid Effective (Ci/MWt) (s) (Sv-m3/Bq-s) (Sv/Bq) (Sv/Bq)

Co-58 7 1.529E+02 6.117E+06 4.760E-14 8.720E-10 2.940E-09 Co-60 7 1.830E+02 1.663E+08 1.260E-13 1.620E-08 5.910E-08 Kr-85 1 3.816E+02 3.383E+08 1.190E-16 0.000E+00 0.000E+00 Kr-85m 1 8.439E+03 1.613E+04 7.480E-15 0.000E+00 0.000E+00 Kr-87 1 1.659E+04 4.578E+03 4.120E-14 0.000E+00 0.000E+00 Kr-88 1 2.342E+04 1.022E+04 1.020E-13 0.000E+00 0.000E+00 Rb-86 3 6.081E+01 1.612E+06 4.810E-15 1.330E-09 1.790E-09 Sr-89 5 2.845E+04 4.363E+06 7.730E-17 7.960E-12 1.120E-08 Sr-90 5 3.066E+03 9.190E+08 7.530E-18 2.690E-10 3.510E-07 Sr-91 5 3.858E+04 3.420E+04 4.924E-14 9.930E-12 4.547E-10 Sr-92 5 4.069E+04 9.756E+03 6.790E-14 3.920E-12 2.180E-10 Y-90 9 3.155E+03 2.304E+05 1.900E-16 5.170E-13 2.280E-09 Y-91 9 3.495E+04 5.055E+06 2.600E-16 8.500E-12 1.320E-08 Y-92 9 4.082E+04 1.274E+04 1.300E-14 1.050E-12 2.110E-10 Y-93 9 4.575E+04 3.636E+04 4.800E-15 9.260E-13 5.820E-10 Zr-95 9 4.510E+04 5.528E+06 3.600E-14 1.440E-09 6.390E-09 Zr-97 9 4.671E+04 6.084E+04 4.432E-14 2.315E-11 1.171E-09 Nb-95 9 4.534E+04 3.037E+06 3.740E-14 3.580E-10 1.570E-09 Mo-99 7 5.070E+04 2.376E+05 7.280E-15 1.520E-11 1.070E-09 Tc-99m 7 4.440E+04 2.167E+04 5.890E-15 5.010E-11 8.800E-12 Ru-103 7 4.175E+04 3.394E+06 2.251E-14 2.570E-10 2.421E-09 Ru-105 7 2.874E+04 1.598E+04 3.810E-14 4.150E-12 1.230E-10 Ru-106 7 1.666E+04 3.181E+07 1.040E-14 1.720E-09 1.290E-07 Rh-105 7 2.716E+04 1.273E+05 3.720E-15 2.880E-12 2.580E-10 Sb-127 4 2.886E+03 3.326E+05 3.330E-14 6.150E-11 1.630E-09 Sb-129 4 8.623E+03 1.555E+04 7.140E-14 9.720E-12 1.740E-10 Te-127 4 2.861E+03 3.366E+04 2.420E-16 1.840E-12 8.600E-11 Te-127m 4 3.825E+02 9.418E+06 1.470E-16 9.660E-11 5.810E-09 Te-129 4 8.483E+03 4.176E+03 2.750E-15 5.090E-13 2.090E-11 Te-129m 4 1.263E+03 2.903E+06 3.337E-15 1.563E-10 6.484E-09 Te-131m 4 3.868E+03 1.080E+05 7.463E-14 3.669E-08 1.758E-09 Te-132 4 3.825E+04 2.815E+05 1.030E-14 6.280E-08 2.550E-09 I-131 2 2.686E+04 6.947E+05 1.820E-14 2.920E-07 8.890E-09 I-132 2 3.885E+04 8.280E+03 1.120E-13 1.740E-09 1.030E-10 I-133 2 5.559E+04 7.488E+04 2.940E-14 4.860E-08 1.580E-09 I-134 2 6.168E+04 3.156E+03 1.300E-13 2.880E-10 3.550E-11 I-135 2 5.191E+04 2.380E+04 8.294E-14 8.460E-09 3.320E-10 Xe-133 1 5.504E+04 4.532E+05 1.560E-15 0.000E+00 0.000E+00 Xe-135 1 2.213E+04 3.272E+04 1.190E-14 0.000E+00 0.000E+00 Cs-134 3 6.578E+03 6.507E+07 7.570E-14 1.110E-08 1.250E-08 Cs-136 3 1.903E+03 1.132E+06 1.060E-13 1.730E-09 1.980E-09

EC407055 Rev. 0 Page 27 of 89 Cs-137 3 4.323E+03 9.467E+08 2.725E-14 7.930E-09 8.630E-09 Ba-139 6 5.095E+04 4.962E+03 2.170E-15 2.400E-12 4.640E-11 Ba-140 6 4.910E+04 1.101E+06 8.580E-15 2.560E-10 1.010E-09 La-140 9 5.022E+04 1.450E+05 1.170E-13 6.870E-11 1.310E-09 La-141 9 4.656E+04 1.415E+04 2.390E-15 9.400E-12 1.570E-10 La-142 9 4.550E+04 5.550E+03 1.440E-13 8.740E-12 6.840E-11 Ce-141 8 4.503E+04 2.808E+06 3.430E-15 2.550E-11 2.420E-09 Ce-143 8 4.450E+04 1.188E+05 1.290E-14 6.230E-12 9.160E-10 Ce-144 8 3.597E+04 2.456E+07 2.773E-15 2.920E-10 1.010E-07 Pr-143 9 4.316E+04 1.172E+06 2.100E-17 1.680E-18 2.190E-09 Nd-147 9 1.839E+04 9.487E+05 6.190E-15 1.820E-11 1.850E-09 Np-239 8 5.355E+05 2.035E+05 7.690E-15 7.620E-12 6.780E-10 Pu-238 8 1.525E+02 2.769E+09 4.880E-18 3.860E-10 7.790E-05 Pu-239 8 1.214E+01 7.594E+11 4.240E-18 3.750E-10 8.330E-05 Pu-240 8 1.298E+01 2.063E+11 4.750E-18 3.760E-10 8.330E-05 Pu-241 8 6.179E+03 4.544E+08 7.250E-20 9.150E-12 1.340E-06 Am-241 9 9.817E+00 1.364E+10 8.180E-16 1.600E-09 1.200E-04 Cm-242 9 2.089E+03 1.407E+07 5.690E-18 9.410E-10 4.670E-06 Cm-244 9 1.834E+02 5.715E+08 4.910E-18 1.010E-09 6.700E-05 Nuclide Daughter Fraction Daughter Fraction Daughter Fraction Kr-85m Kr-85 0.21 none 0.00 none 0.00 Kr-87 Rb-87 1.00 none 0.00 none 0.00 Kr-88 Rb-88 1.00 none 0.00 none 0.00 Sr-90 Y-90 1.00 none 0.00 none 0.00 Sr-91 Y-91m 0.58 Y-91 0.42 none 0.00 Sr-92 Y-92 1.00 none 0.00 none 0.00 Y-93 Zr-93 1.00 none 0.00 none 0.00 Zr-95 Nb-95m 0.01 Nb-95 0.99 none 0.00 Zr-97 Nb-97m 0.95 Nb-97 0.05 none 0.00 Mo-99 Tc-99m 0.88 Tc-99 0.12 none 0.00 Tc-99m Tc-99 1.00 none 0.00 none 0.00 Ru-103 Rh-103m 1.00 none 0.00 none 0.00 Ru-105 Rh-105 1.00 none 0.00 none 0.00 Ru-106 Rh-106 1.00 none 0.00 none 0.00 Sb-127 Te-127m 0.18 Te-127 0.82 none 0.00 Sb-129 Te-129m 0.22 Te-129 0.77 none 0.00 Te-127m Te-127 0.98 none 0.00 none 0.00 Te-129 I-129 1.00 none 0.00 none 0.00 Te-129m Te-129 0.65 I-129 0.35 none 0.00 Te-131m Te-131 0.22 I-131 0.78 none 0.00 Te-132 I-132 1.00 none 0.00 none 0.00 I-131 Xe-131m 0.01 none 0.00 none 0.00 I-133 Xe-133m 0.03 Xe-133 0.97 none 0.00 I-135 Xe-135m 0.15 Xe-135 0.85 none 0.00 Xe-135 Cs-135 1.00 none 0.00 none 0.00 Cs-137 Ba-137m 0.95 none 0.00 none 0.00 Ba-140 La-140 1.00 none 0.00 none 0.00 La-141 Ce-141 1.00 none 0.00 none 0.00 Ce-143 Pr-143 1.00 none 0.00 none 0.00 Ce-144 Pr-144m 0.02 Pr-144 0.98 none 0.00 Nd-147 Pm-147 1.00 none 0.00 none 0.00 Np-239 Pu-239 1.00 none 0.00 none 0.00 Pu-238 U-234 1.00 none 0.00 none 0.00 Pu-239 U-235 1.00 none 0.00 none 0.00 Pu-240 U-236 1.00 none 0.00 none 0.00 Pu-241 U-237 0.00 Am-241 1.00 none 0.00 Am-241 Np-237 1.00 none 0.00 none 0.00 Cm-242 Pu-238 1.00 none 0.00 none 0.00 Cm-244 Pu-240 1.00 none 0.00 none 0.00 Iodine fractions Aerosol = 9.5000E-01 Elemental = 4.8500E-02 Organic = 1.5000E-03 COMPARTMENT DATA Compartment number 1: Containment Sprays: Elemental Removal Data

EC407055 Rev. 0 Page 28 of 89 Time (hr) Removal Coef. (hr^-1) 0.0000E+00 3.8600E+00 2.0000E+00 1.8600E+00 3.8500E+00 0.0000E+00 Natural Deposition (Powers' model): Aerosol data Reactor type: 3 Percentile = 10 (%)

Natural Deposition: Elemental Removal Data Time (hr) Removal Coef. (hr^-1) 0.0000E+00 0.0000E+00 Compartment number 2: (Node 1) Inboard MSL A Volume Compartment number 3: (Nodes 2& 3) Outboard MSL A Volume Compartment number 4: Condenser Compartment number 5: Environment Compartment number 6: Control Room Compartment Filter Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 1.4650E+04 0.0000E+00 0.0000E+00 0.0000E+00 3.3300E-01 1.4650E+04 0.0000E+00 0.0000E+00 0.0000E+00 4.0000E+00 1.4650E+04 0.0000E+00 6.6500E+01 6.6500E+01 7.2000E+02 1.4650E+04 0.0000E+00 0.0000E+00 0.0000E+00 PATHWAY DATA Pathway number 1: ontainment to (Node 1) Inboard MSL A Volume Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 2.9960E+00 0.0000E+00 0.0000E+00 0.0000E+00 2.0000E+00 1.7440E+00 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 2: Node 1) Inboard MSL A Volume to (Nodes 2& 3) Outbo Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 2.9960E+00 9.8530E+01 3.1570E+01 0.0000E+00 3.3330E-01 2.9960E+00 9.9950E+01 3.1570E+01 0.0000E+00 2.0000E+00 1.7440E+00 9.9950E+01 3.1570E+01 0.0000E+00 2.4000E+01 1.7440E+00 0.0000E+00 5.0820E+01 0.0000E+00 9.6000E+01 1.7440E+00 0.0000E+00 8.6800E+01 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 3: Nodes 2& 3) Outboard MSL A Volume to Condenser Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 3.3300E-01 6.3760E+00 0.0000E+00 2.4680E+01 0.0000E+00 2.4000E+01 5.4920E+00 0.0000E+00 4.5990E+01 0.0000E+00 9.6000E+01 4.1670E+00 0.0000E+00 8.7720E+01 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 4: ondenser to Environment Pathway Filter: Removal Data

EC407055 Rev. 0 Page 29 of 89 Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 7.3230E+00 0.0000E+00 9.9370E+01 0.0000E+00 2.4000E+01 7.3230E+00 0.0000E+00 9.9370E+01 0.0000E+00 9.6000E+01 7.3230E+00 0.0000E+00 9.9370E+01 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 5: nvironment to Control Room Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 1.1000E+03 0.0000E+00 0.0000E+00 0.0000E+00 3.3330E-01 9.0000E+02 9.9000E+01 8.8440E+01 8.8440E+01 4.0000E+00 9.0000E+02 9.9000E+01 9.6130E+01 9.6130E+01 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 6: nvironment to Control Room Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 2.4000E+03 0.0000E+00 0.0000E+00 0.0000E+00 3.3330E-01 2.4000E+03 0.0000E+00 0.0000E+00 0.0000E+00 4.0000E+00 2.4000E+03 0.0000E+00 6.6500E+01 6.6500E+01 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 7: nvironment to Control Room Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 5.0000E+01 0.0000E+00 0.0000E+00 0.0000E+00 3.3330E-01 5.0000E+01 0.0000E+00 0.0000E+00 0.0000E+00 4.0000E+00 5.0000E+01 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 8: ontrol Room to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 3.5500E+03 1.0000E+02 1.0000E+02 1.0000E+02 3.3330E-01 3.3500E+03 1.0000E+02 1.0000E+02 1.0000E+02 4.0000E+00 3.3500E+03 1.0000E+02 1.0000E+02 1.0000E+02 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 9: Nodes 2& 3) Outboard MSL A Volume to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 6.3760E+00 0.0000E+00 2.4680E+01 0.0000E+00 3.3330E-01 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 LOCATION DATA Location Exclusion Area Boundary is in compartment 5 Location X/Q Data Time (hr) X/Q (s

• m^-3) 0.0000E+00 6.6300E-04 2.4000E+01 0.0000E+00 7.2000E+02 0.0000E+00 Location Breathing Rate Data

EC407055 Rev. 0 Page 30 of 89 Time (hr) Breathing Rate (m^3

• sec^-1) 0.0000E+00 3.5000E-04 2.4000E+01 0.0000E+00 7.2000E+02 0.0000E+00 Location Low Population Zone is in compartment 5 Location X/Q Data Time (hr) X/Q (s

• m^-3) 0.0000E+00 2.6500E-05 2.5000E-01 2.6500E-05 1.5000E+00 2.6500E-05 2.0000E+00 1.0800E-05 8.0000E+00 6.8700E-06 2.4000E+01 2.6300E-06 9.6000E+01 6.7400E-07 7.2000E+02 0.0000E+00 Location Breathing Rate Data Time (hr) Breathing Rate (m^3

• sec^-1) 0.0000E+00 3.5000E-04 8.0000E+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.0000E+00 Location Control Room is in compartment 6 Location X/Q Data Time (hr) X/Q (s

• m^-3) 0.0000E+00 8.1300E-03 2.5000E-01 8.1300E-03 1.5000E+00 8.1300E-03 2.0000E+00 6.0900E-03 8.0000E+00 2.4200E-03 2.4000E+01 1.7600E-03 9.6000E+01 1.4600E-03 7.2000E+02 0.0000E+00 Location Breathing Rate Data Time (hr) Breathing Rate (m^3

• sec^-1) 0.0000E+00 3.5000E-04 7.2000E+02 0.0000E+00 Location Occupancy Factor Data Time (hr) Occupancy Factor 0.0000E+00 1.0000E+00 2.4000E+01 6.0000E-01 9.6000E+01 4.0000E-01 7.2000E+02 0.0000E+00 USER SPECIFIED TIME STEP DATA - SUPPLEMENTAL TIME STEPS Time Time step 0.0000E+00 2.5000E-01 2.4000E+01 2.4000E+01 7.2000E+02 0.0000E+00

EC407055 Rev. 0 Page 31 of 89 RADTRAD Version 3.03 (Spring 2001) run on 10/31/2016 at 23:29:22 Dose Output Exclusion Area Boundary Doses:

Time (h) = 0.2500 Whole Body Thyroid TEDE Delta dose (rem) 4.5110E-05 1.5735E-03 1.0157E-04 Accumulated dose (rem) 4.5110E-05 1.5735E-03 1.0157E-04 Low Population Zone Doses:

Time (h) = 0.2500 Whole Body Thyroid TEDE Delta dose (rem) 1.8031E-06 6.2892E-05 4.0597E-06 Accumulated dose (rem) 1.8031E-06 6.2892E-05 4.0597E-06 Control Room Doses:

Time (h) = 0.2500 Whole Body Thyroid TEDE Delta dose (rem) 2.4051E-06 1.9275E-03 7.1484E-05 Accumulated dose (rem) 2.4051E-06 1.9275E-03 7.1484E-05 Exclusion Area Boundary Doses:

Time (h) = 0.3330 Whole Body Thyroid TEDE Delta dose (rem) 9.1574E-05 3.1291E-03 2.0433E-04 Accumulated dose (rem) 1.3668E-04 4.7026E-03 3.0590E-04 Low Population Zone Doses:

Time (h) = 0.3330 Whole Body Thyroid TEDE Delta dose (rem) 3.6602E-06 1.2507E-04 8.1672E-06 Accumulated dose (rem) 5.4633E-06 1.8796E-04 1.2227E-05 Control Room Doses:

Time (h) = 0.3330 Whole Body Thyroid TEDE Delta dose (rem) 6.5327E-06 5.1732E-03 1.9256E-04 Accumulated dose (rem) 8.9378E-06 7.1007E-03 2.6405E-04 Exclusion Area Boundary Doses:

Time (h) = 0.3333 Whole Body Thyroid TEDE Delta dose (rem) 4.6778E-07 1.6085E-05 1.0482E-06 Accumulated dose (rem) 1.3715E-04 4.7187E-03 3.0695E-04 Low Population Zone Doses:

Time (h) = 0.3333 Whole Body Thyroid TEDE Delta dose (rem) 1.8697E-08 6.4290E-07 4.1897E-08 Accumulated dose (rem) 5.4820E-06 1.8861E-04 1.2269E-05 Control Room Doses:

EC407055 Rev. 0 Page 32 of 89 Time (h) = 0.3333 Whole Body Thyroid TEDE Delta dose (rem) 3.4624E-08 2.7824E-05 1.0358E-06 Accumulated dose (rem) 8.9724E-06 7.1285E-03 2.6508E-04 Exclusion Area Boundary Doses:

Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 5.5029E-08 6.3515E-07 8.1107E-08 Accumulated dose (rem) 1.3721E-04 4.7193E-03 3.0703E-04 Low Population Zone Doses:

Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 2.1995E-09 2.5387E-08 3.2418E-09 Accumulated dose (rem) 5.4842E-06 1.8863E-04 1.2272E-05 Control Room Doses:

Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 1.6623E-05 1.3491E-02 5.0200E-04 Accumulated dose (rem) 2.5596E-05 2.0619E-02 7.6708E-04 Exclusion Area Boundary Doses:

Time (h) = 1.5000 Whole Body Thyroid TEDE Delta dose (rem) 2.9375E-05 7.5418E-05 3.2169E-05 Accumulated dose (rem) 1.6658E-04 4.7948E-03 3.3920E-04 Low Population Zone Doses:

Time (h) = 1.5000 Whole Body Thyroid TEDE Delta dose (rem) 1.1741E-06 3.0145E-06 1.2858E-06 Accumulated dose (rem) 6.6583E-06 1.9165E-04 1.3558E-05 Control Room Doses:

Time (h) = 1.5000 Whole Body Thyroid TEDE Delta dose (rem) 4.0868E-05 3.3468E-02 1.2443E-03 Accumulated dose (rem) 6.6463E-05 5.4088E-02 2.0113E-03 Exclusion Area Boundary Doses:

Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.1123E-04 1.9312E-04 1.1823E-04 Accumulated dose (rem) 2.7781E-04 4.9879E-03 4.5743E-04 Low Population Zone Doses:

Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 4.4459E-06 7.7189E-06 4.7256E-06 Accumulated dose (rem) 1.1104E-05 1.9936E-04 1.8283E-05 Control Room Doses:

Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.5486E-05 4.9140E-03 2.0224E-04 Accumulated dose (rem) 9.1949E-05 5.9002E-02 2.2136E-03 Exclusion Area Boundary Doses:

Time (h) = 3.8500 Whole Body Thyroid TEDE Delta dose (rem) 2.2695E-03 3.8111E-03 2.4076E-03 Accumulated dose (rem) 2.5474E-03 8.7990E-03 2.8651E-03 Low Population Zone Doses:

Time (h) = 3.8500 Whole Body Thyroid TEDE Delta dose (rem) 3.6970E-05 6.2081E-05 3.9219E-05 Accumulated dose (rem) 4.8074E-05 2.6145E-04 5.7503E-05

EC407055 Rev. 0 Page 33 of 89 Control Room Doses:

Time (h) = 3.8500 Whole Body Thyroid TEDE Delta dose (rem) 5.4774E-04 1.9613E-02 1.2553E-03 Accumulated dose (rem) 6.3969E-04 7.8615E-02 3.4689E-03 Exclusion Area Boundary Doses:

Time (h) = 4.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.4413E-04 6.2306E-04 3.6664E-04 Accumulated dose (rem) 2.8915E-03 9.4220E-03 3.2317E-03 Low Population Zone Doses:

Time (h) = 4.0000 Whole Body Thyroid TEDE Delta dose (rem) 5.6057E-06 1.0149E-05 5.9724E-06 Accumulated dose (rem) 5.3680E-05 2.7160E-04 6.3475E-05 Control Room Doses:

Time (h) = 4.0000 Whole Body Thyroid TEDE Delta dose (rem) 9.3338E-05 3.0437E-03 2.0306E-04 Accumulated dose (rem) 7.3303E-04 8.1658E-02 3.6719E-03 Exclusion Area Boundary Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.8235E-02 4.5075E-02 1.9823E-02 Accumulated dose (rem) 2.1127E-02 5.4497E-02 2.3054E-02 Low Population Zone Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.9704E-04 7.3425E-04 3.2290E-04 Accumulated dose (rem) 3.5072E-04 1.0058E-03 3.8638E-04 Control Room Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 5.8284E-03 6.5720E-02 8.9286E-03 Accumulated dose (rem) 6.5615E-03 1.4738E-01 1.2600E-02 Exclusion Area Boundary Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.3825E-01 9.4689E-01 1.6915E-01 Accumulated dose (rem) 1.5937E-01 1.0014E+00 1.9221E-01 Low Population Zone Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.4325E-03 5.0460E-03 1.5972E-03 Accumulated dose (rem) 1.7832E-03 6.0518E-03 1.9836E-03 Control Room Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.1390E-02 3.7161E-01 3.7418E-02 Accumulated dose (rem) 2.7952E-02 5.1899E-01 5.0019E-02 Exclusion Area Boundary Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 1.5937E-01 1.0014E+00 1.9221E-01 Low Population Zone Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.8859E-03 4.2607E-02 5.3059E-03 Accumulated dose (rem) 5.6692E-03 4.8659E-02 7.2895E-03

EC407055 Rev. 0 Page 34 of 89 Control Room Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 6.7847E-02 2.9150E+00 2.0942E-01 Accumulated dose (rem) 9.5798E-02 3.4340E+00 2.5944E-01 Exclusion Area Boundary Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 1.5937E-01 1.0014E+00 1.9221E-01 Low Population Zone Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 6.9440E-03 1.2443E-01 1.0888E-02 Accumulated dose (rem) 1.2613E-02 1.7309E-01 1.8177E-02 Control Room Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.6357E-01 1.2494E+01 7.9423E-01 Accumulated dose (rem) 3.5936E-01 1.5928E+01 1.0537E+00 897 I-131 Summary Containment (Node 1) Inboard MSL (Nodes 2& 3) Outboard Time (hr) I-131 (Curies) I-131 (Curies) I-131 (Curies) 0.000 5.3091E+03 6.7233E-04 2.8573E-09 0.250 2.1565E+06 1.2212E+02 2.0949E-01 0.333 2.7820E+06 2.0921E+02 4.6310E-01 0.333 2.7841E+06 2.0957E+02 4.6419E-01 0.500 3.9260E+06 4.4017E+02 1.0463E+00 0.750 7.1398E+06 9.9147E+02 2.6818E+00 1.000 1.0124E+07 1.8132E+03 5.4981E+00 1.250 1.2909E+07 2.8524E+03 9.5260E+00 1.500 1.5516E+07 4.0645E+03 1.4651E+01 1.750 1.7955E+07 5.4117E+03 2.0723E+01 2.000 2.0239E+07 6.8614E+03 2.7589E+01 2.250 1.5666E+07 7.5430E+03 3.0693E+01 2.500 1.2133E+07 7.9209E+03 3.3700E+01 2.750 9.4015E+06 8.0741E+03 3.6466E+01 3.000 7.2888E+06 8.0629E+03 3.8918E+01 3.250 5.6541E+06 7.9331E+03 4.1033E+01 3.500 4.3888E+06 7.7198E+03 4.2812E+01 3.750 3.4092E+06 7.4494E+03 4.4272E+01 3.850 3.0823E+06 7.3299E+03 4.4772E+01 4.000 2.6522E+06 7.1418E+03 4.5438E+01 4.250 2.0664E+06 6.8123E+03 4.6342E+01 4.500 1.6125E+06 6.4717E+03 4.7018E+01 4.750 1.2606E+06 6.1284E+03 4.7494E+01 5.000 9.8790E+05 5.7883E+03 4.7798E+01 5.250 8.5176E+05 5.4582E+03 4.7954E+01 5.500 7.3533E+05 5.1422E+03 4.7983E+01 5.750 6.3577E+05 4.8406E+03 4.7903E+01 6.000 5.5062E+05 4.5533E+03 4.7733E+01 6.250 4.7781E+05 4.2803E+03 4.7486E+01 6.500 4.1553E+05 4.0213E+03 4.7175E+01 6.750 3.6227E+05 3.7760E+03 4.6812E+01 7.000 3.1672E+05 3.5440E+03 4.6407E+01 7.250 2.7777E+05 3.3249E+03 4.5969E+01 7.500 2.4445E+05 3.1182E+03 4.5505E+01 7.750 2.1595E+05 2.9235E+03 4.5021E+01 8.000 1.9157E+05 2.7401E+03 4.4524E+01 8.250 1.7072E+05 2.5676E+03 4.4019E+01 8.500 1.5509E+05 2.4055E+03 4.3509E+01

EC407055 Rev. 0 Page 35 of 89 8.750 1.4144E+05 2.2534E+03 4.2999E+01 9.000 1.2952E+05 2.1107E+03 4.2491E+01 9.250 1.1910E+05 1.9768E+03 4.1988E+01 9.500 1.1000E+05 1.8514E+03 4.1492E+01 9.750 1.0205E+05 1.7338E+03 4.1005E+01 10.000 9.5099E+04 1.6236E+03 4.0528E+01 10.250 8.9026E+04 1.5204E+03 4.0063E+01 24.000 4.5134E+04 7.6739E+01 2.9995E+01 96.000 3.4159E+04 3.3038E+01 2.5457E+01 720.000 3.0768E+03 2.9759E+00 2.8717E+00 Condenser Environment Control Room Time (hr) I-131 (Curies) I-131 (Curies) I-131 (Curies) 0.000 0.0000E+00 1.2768E-13 1.7388E-15 0.250 0.0000E+00 4.4378E-03 5.5219E-05 0.333 0.0000E+00 1.3273E-02 1.6030E-04 0.333 4.5476E-05 1.3318E-02 1.6083E-04 0.500 3.8335E-02 1.3320E-02 1.2084E-04 0.750 1.7418E-01 1.3331E-02 7.8784E-05 1.000 4.7645E-01 1.3360E-02 5.1532E-05 1.250 1.0381E+00 1.3419E-02 3.4039E-05 1.500 1.9490E+00 1.3535E-02 2.3097E-05 1.750 3.2898E+00 1.3742E-02 1.6706E-05 2.000 5.1302E+00 1.4089E-02 1.3663E-05 2.250 7.3616E+00 1.4630E-02 1.2144E-05 2.500 9.8325E+00 1.5405E-02 1.2543E-05 2.750 1.2531E+01 1.6448E-02 1.4402E-05 3.000 1.5437E+01 1.7796E-02 1.7432E-05 3.250 1.8526E+01 1.9488E-02 2.1450E-05 3.500 2.1775E+01 2.1562E-02 2.6339E-05 3.750 2.5157E+01 2.4056E-02 3.2021E-05 3.850 2.6543E+01 2.5180E-02 3.4503E-05 4.000 2.8652E+01 2.7007E-02 3.8441E-05 4.250 3.2237E+01 3.0453E-02 1.8185E-05 4.500 3.5894E+01 3.4427E-02 1.5968E-05 4.750 3.9608E+01 3.8966E-02 1.7214E-05 5.000 4.3363E+01 4.4102E-02 1.9178E-05 5.250 4.7148E+01 4.9868E-02 2.1335E-05 5.500 5.0951E+01 5.6294E-02 2.3575E-05 5.750 5.4764E+01 6.3409E-02 2.5870E-05 6.000 5.8578E+01 7.1241E-02 2.8206E-05 6.250 6.2387E+01 7.9817E-02 3.0575E-05 6.500 6.6184E+01 8.9162E-02 3.2968E-05 6.750 6.9966E+01 9.9300E-02 3.5378E-05 7.000 7.3727E+01 1.1025E-01 3.7800E-05 7.250 7.7465E+01 1.2204E-01 4.0227E-05 7.500 8.1176E+01 1.3469E-01 4.2655E-05 7.750 8.4858E+01 1.4822E-01 4.5081E-05 8.000 8.8511E+01 1.6263E-01 4.7499E-05 8.250 9.2132E+01 1.7796E-01 3.3147E-05 8.500 9.5720E+01 1.9422E-01 2.8457E-05 8.750 9.9275E+01 2.1141E-01 2.6540E-05 9.000 1.0280E+02 2.2957E-01 2.5768E-05 9.250 1.0628E+02 2.4869E-01 2.5614E-05 9.500 1.0974E+02 2.6879E-01 2.5837E-05 9.750 1.1316E+02 2.8988E-01 2.6298E-05 10.000 1.1654E+02 3.1197E-01 2.6910E-05 10.250 1.1990E+02 3.3507E-01 2.7617E-05 24.000 2.7292E+02 3.2600E+00 6.7110E-05 96.000 7.6566E+02 6.4413E+01 1.8713E-04 720.000 3.1428E+02 8.0330E+02 5.2252E-05 Cumulative Dose Summary Exclusion Area Bounda Low Population Zone Control Room Time Thyroid TEDE Thyroid TEDE Thyroid TEDE (hr) (rem) (rem) (rem) (rem) (rem) (rem) 0.000 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.250 1.5735E-03 1.0157E-04 6.2892E-05 4.0597E-06 1.9275E-03 7.1484E-05

EC407055 Rev. 0 Page 36 of 89 0.333 4.7026E-03 3.0590E-04 1.8796E-04 1.2227E-05 7.1007E-03 2.6405E-04 0.333 4.7187E-03 3.0695E-04 1.8861E-04 1.2269E-05 7.1285E-03 2.6508E-04 0.500 4.7193E-03 3.0703E-04 1.8863E-04 1.2272E-05 2.0619E-02 7.6708E-04 0.750 4.7233E-03 3.0776E-04 1.8879E-04 1.2301E-05 3.4802E-02 1.2937E-03 1.000 4.7333E-03 3.1055E-04 1.8919E-04 1.2413E-05 4.4030E-02 1.6358E-03 1.250 4.7543E-03 3.1888E-04 1.9003E-04 1.2746E-05 5.0069E-02 1.8601E-03 1.500 4.7948E-03 3.3920E-04 1.9165E-04 1.3558E-05 5.4088E-02 2.0113E-03 1.750 4.8671E-03 3.8114E-04 1.9454E-04 1.5234E-05 5.6878E-02 2.1211E-03 2.000 4.9879E-03 4.5743E-04 1.9936E-04 1.8283E-05 5.9002E-02 2.2136E-03 2.250 5.1759E-03 5.8152E-04 2.0243E-04 2.0305E-05 6.0805E-02 2.3031E-03 2.500 5.4442E-03 7.6033E-04 2.0680E-04 2.3218E-05 6.2531E-02 2.4002E-03 2.750 5.8046E-03 9.9889E-04 2.1267E-04 2.7104E-05 6.4416E-02 2.5170E-03 3.000 6.2695E-03 1.3019E-03 2.2024E-04 3.2039E-05 6.6643E-02 2.6628E-03 3.250 6.8513E-03 1.6734E-03 2.2972E-04 3.8092E-05 6.9361E-02 2.8451E-03 3.500 7.5625E-03 2.1171E-03 2.4130E-04 4.5319E-05 7.2696E-02 3.0705E-03 3.750 8.4154E-03 2.6358E-03 2.5520E-04 5.3768E-05 7.6761E-02 3.3445E-03 3.850 8.7990E-03 2.8651E-03 2.6145E-04 5.7503E-05 7.8615E-02 3.4689E-03 4.000 9.4220E-03 3.2317E-03 2.7160E-04 6.3475E-05 8.1658E-02 3.6719E-03 4.250 1.0594E-02 3.9063E-03 2.9069E-04 7.4464E-05 8.5262E-02 3.9876E-03 4.500 1.1943E-02 4.6604E-03 3.1266E-04 8.6749E-05 8.7597E-02 4.2934E-03 4.750 1.3479E-02 5.4945E-03 3.3768E-04 1.0034E-04 8.9920E-02 4.6295E-03 5.000 1.5213E-02 6.4084E-03 3.6592E-04 1.1522E-04 9.2476E-02 5.0039E-03 5.250 1.7154E-02 7.4012E-03 3.9754E-04 1.3139E-04 9.5318E-02 5.4187E-03 5.500 1.9312E-02 8.4721E-03 4.3270E-04 1.4884E-04 9.8461E-02 5.8744E-03 5.750 2.1695E-02 9.6195E-03 4.7152E-04 1.6753E-04 1.0191E-01 6.3710E-03 6.000 2.4312E-02 1.0842E-02 5.1415E-04 1.8744E-04 1.0568E-01 6.9083E-03 6.250 2.7171E-02 1.2137E-02 5.6072E-04 2.0854E-04 1.0977E-01 7.4861E-03 6.500 3.0279E-02 1.3503E-02 6.1134E-04 2.3079E-04 1.1418E-01 8.1037E-03 6.750 3.3642E-02 1.4938E-02 6.6612E-04 2.5416E-04 1.1891E-01 8.7604E-03 7.000 3.7266E-02 1.6438E-02 7.2517E-04 2.7861E-04 1.2396E-01 9.4555E-03 7.250 4.1159E-02 1.8003E-02 7.8858E-04 3.0409E-04 1.2933E-01 1.0188E-02 7.500 4.5325E-02 1.9629E-02 8.5644E-04 3.3058E-04 1.3503E-01 1.0957E-02 7.750 4.9769E-02 2.1314E-02 9.2884E-04 3.5802E-04 1.4105E-01 1.1762E-02 8.000 5.4497E-02 2.3054E-02 1.0058E-03 3.8638E-04 1.4738E-01 1.2600E-02 8.250 5.9511E-02 2.4849E-02 1.0326E-03 4.0410E-04 1.5273E-01 1.3347E-02 8.500 6.4817E-02 2.6696E-02 1.0608E-03 4.2231E-04 1.5690E-01 1.3949E-02 8.750 7.0418E-02 2.8591E-02 1.0907E-03 4.4098E-04 1.6064E-01 1.4473E-02 9.000 7.6317E-02 3.0533E-02 1.1221E-03 4.6009E-04 1.6418E-01 1.4952E-02 9.250 8.2518E-02 3.2520E-02 1.1552E-03 4.7961E-04 1.6766E-01 1.5408E-02 9.500 8.9022E-02 3.4550E-02 1.1898E-03 4.9952E-04 1.7113E-01 1.5853E-02 9.750 9.5833E-02 3.6620E-02 1.2261E-03 5.1980E-04 1.7465E-01 1.6294E-02 10.000 1.0295E-01 3.8728E-02 1.2641E-03 5.4043E-04 1.7822E-01 1.6736E-02 10.250 1.1038E-01 4.0874E-02 1.3037E-03 5.6139E-04 1.8188E-01 1.7182E-02 24.000 1.0014E+00 1.9221E-01 6.0518E-03 1.9836E-03 5.1899E-01 5.0019E-02 96.000 1.0014E+00 1.9221E-01 4.8659E-02 7.2895E-03 3.4340E+00 2.5944E-01 720.000 1.0014E+00 1.9221E-01 1.7309E-01 1.8177E-02 1.5928E+01 1.0537E+00 Worst Two-Hour Doses Exclusion Area Boundary Time Whole Body Thyroid TEDE (hr) (rem) (rem) (rem) 10.3 1.7795E-02 1.2960E-01 2.2012E-02

EC407055 Rev. 0 Page 37 of 89 LaSalle 2 Cycle 16 MSIV B Pathway RADTRAD Output File RADTRAD Version 3.03 (Spring 2001) run on 10/31/2016 at 23:29:25 File information Plant file = C:\Users\E42031\AppData\Local\Temp\14\\temp.psf Inventory file = H:\LaSalle\Off-Site and Control Room Dose\PLR LOCA\l2c16 MSIVB\l2c16 MSIVB.nif Release file = H:\LaSalle\Off-Site and Control Room Dose\PLR LOCA\l2c16 MSIVB\l2c16 MSIVB.rft Dose Conversion file = H:\LaSalle\Off-Site and Control Room Dose\PLR LOCA\l2c16 MSIVB\l2c16 MSIVB.inp Radtrad 3.03 4/15/2001 LSCS LOCA MSIV B with 25% Makeup Nuclide Inventory File:

H:\LaSalle\Off-Site and Control Room Dose\PLR LOCA\l2c16 MSIVB\l2c16 MSIVB.nif Plant Power Level:

3.5590E+03 Compartments:

6 Compartment 1:

Containment 3

3.9430E+05 1

0 0

1 0

Compartment 2:

(Node 1) Inboard MSL B Volume 3

1.00E-04 0

0 0

0 0

Compartment 3:

(Nodes 2& 3) Outboard MSL B Volume 3

9.64E+02 0

0 0

0 0

Compartment 4:

Condenser

EC407055 Rev. 0 Page 38 of 89 3

2.4635E+05 0

0 0

0 0

Compartment 5:

Environment 2

0.0000E+00 0

0 0

0 0

Compartment 6:

Control Room 1

1.1740E+05 0

0 1

0 0

Pathways:

9 Pathway 1:

Containment to (Node 1) Inboard MSL B Volume 1

2 2

Pathway 2:

(Node 1) Inboard MSL B Volume to (Nodes 2& 3) Outboard MSL B Volume 2

3 2

Pathway 3:

(Nodes 2& 3) Outboard MSL B Volume to Condenser 3

4 2

Pathway 4:

Condenser to Environment 4

5 2

Pathway 5:

Environment to Control Room 5

6 2

Pathway 6:

Environment to Control Room 5

6 2

Pathway 7:

Environment to Control Room 5

6 2

Pathway 8:

Control Room to Environment 6

5 2

Pathway 9:

(Nodes 2& 3) Outboard MSL B Volume to Environment 3

5

EC407055 Rev. 0 Page 39 of 89 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1 1.0000E+00 H:\LaSalle\Off-Site and Control Room Dose\PLR LOCA\l2c16 MSIVB\l2c16 MSIVB.inp H:\LaSalle\Off-Site and Control Room Dose\PLR LOCA\l2c16 MSIVB\l2c16 MSIVB.rft 0.0000E+00 1

9.5000E-01 4.8500E-02 1.5000E-03 1.0000E+00 Overlying Pool:

0 0.0000E+00 0

0 0

0 Compartments:

6 Compartment 1:

0 1

1 0.0000E+00 0

1 0.0000E+00 3

0.0000E+00 3.8600E+00 2.0000E+00 1.8600E+00 3.8500E+00 0.0000E+00 1

0.0000E+00 0

0 0

3 3

1.0000E+01 1

1 0.0000E+00 0.0000E+00 Compartment 2:

0 1

0 0

0 0

0 0

0 Compartment 3:

0 1

0 0

0 0

0 0

0 Compartment 4:

0 1

0 0

EC407055 Rev. 0 Page 40 of 89 0

0 0

0 0

Compartment 5:

0 1

0 0

0 0

0 0

0 Compartment 6:

0 1

0 0

0 0

1 1.4650E+04 4

0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 3.3300E-01 0.0000E+00 0.0000E+00 0.0000E+00 4.0000E+00 0.0000E+00 6.6500E+01 6.6500E+01 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0

0 Pathways:

9 Pathway 1:

0 0

0 0

0 1

5 0.0000E+00 2.9960E+00 0.0000E+00 0.0000E+00 0.0000E+00 2.0000E+00 1.7440E+00 0.0000E+00 0.0000E+00 0.0000E+00 2.4000E+01 1.7440E+00 0.0000E+00 0.0000E+00 0.0000E+00 9.6000E+01 1.7440E+00 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 0

0 Pathway 2:

0 0

0 0

0 1

5 0.0000E+00 2.9960E+00 0.0000E+00 0.0000E+00 0.0000E+00 2.0000E+00 1.7440E+00 0.0000E+00 0.0000E+00 0.0000E+00 2.4000E+01 1.7440E+00 0.0000E+00 0.0000E+00 0.0000E+00 9.6000E+01 1.7440E+00 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 0

0

EC407055 Rev. 0 Page 41 of 89 Pathway 3:

0 0

0 0

0 1

5 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 3.3300E-01 6.3760E+00 9.9800E+01 2.4210E+01 0.0000E+00 2.4000E+01 5.4920E+00 0.0000E+00 4.5370E+01 0.0000E+00 9.6000E+01 4.1670E+00 0.0000E+00 8.7450E+01 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 0

0 Pathway 4:

0 0

0 0

0 1

4 0.0000E+00 7.3230E+00 0.0000E+00 9.9370E+01 0.0000E+00 2.4000E+01 7.3230E+00 0.0000E+00 9.9370E+01 0.0000E+00 9.6000E+01 7.3230E+00 0.0000E+00 9.9370E+01 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 0

0 Pathway 5:

0 0

0 0

0 1

4 0.0000E+00 1.1000E+03 0.0000E+00 0.0000E+00 0.0000E+00 3.3330E-01 9.0000E+02 9.9000E+01 8.8440E+01 8.8440E+01 4.0000E+00 9.0000E+02 9.9000E+01 9.6130E+01 9.6130E+01 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 0

0 Pathway 6:

0 0

0 0

0 1

4 0.0000E+00 2.4000E+03 0.0000E+00 0.0000E+00 0.0000E+00 3.3330E-01 2.4000E+03 0.0000E+00 0.0000E+00 0.0000E+00 4.0000E+00 2.4000E+03 0.0000E+00 6.4430E+01 6.4430E+01 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0

EC407055 Rev. 0 Page 42 of 89 0

0 Pathway 7:

0 0

0 0

0 1

4 0.0000E+00 5.0000E+01 0.0000E+00 0.0000E+00 0.0000E+00 3.3330E-01 5.0000E+01 0.0000E+00 0.0000E+00 0.0000E+00 4.0000E+00 5.0000E+01 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 0

0 Pathway 8:

0 0

0 0

0 1

4 0.0000E+00 3.5500E+03 1.0000E+02 1.0000E+02 1.0000E+02 3.3330E-01 3.3500E+03 1.0000E+02 1.0000E+02 1.0000E+02 4.0000E+00 3.3500E+03 1.0000E+02 1.0000E+02 1.0000E+02 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 0

0 Pathway 9:

0 0

0 0

0 1

2 0.0000E+00 6.3760E+00 9.1960E+01 2.4210E+01 0.0000E+00 3.3330E-01 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 0

0 Dose Locations:

3 Location 1:

Exclusion Area Boundary 5

1 4

0.0000E+00 6.6300E-04 2.4000E+01 0.0000E+00 9.6000E+01 0.0000E+00 7.2000E+02 0.0000E+00 1

3 0.0000E+00 3.5000E-04 2.4000E+01 0.0000E+00 7.2000E+02 0.0000E+00 0

EC407055 Rev. 0 Page 43 of 89 Location 2:

Low Population Zone 5

1 8

0.0000E+00 2.6500E-05 2.5000E-01 2.6500E-05 1.5000E+00 2.6500E-05 2.0000E+00 1.0800E-05 8.0000E+00 6.8700E-06 2.4000E+01 2.6300E-06 9.6000E+01 6.7400E-07 7.2000E+02 0.0000E+00 1

4 0.0000E+00 3.5000E-04 8.0000E+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.0000E+00 0

Location 3:

Control Room 6

0 1

2 0.0000E+00 3.5000E-04 7.2000E+02 0.0000E+00 1

4 0.0000E+00 1.0000E+00 2.4000E+01 6.0000E-01 9.6000E+01 4.0000E-01 7.2000E+02 0.0000E+00 Effective Volume Location:

1 8

0.0000E+00 8.1300E-03 2.5000E-01 8.1300E-03 1.5000E+00 8.1300E-03 2.0000E+00 6.0900E-03 8.0000E+00 2.4200E-03 2.4000E+01 1.7600E-03 9.6000E+01 1.4600E-03 7.2000E+02 0.0000E+00 Simulation Parameters:

3 0.0000E+00 2.5000E-01 2.4000E+01 2.4000E+01 7.2000E+02 0.0000E+00 Output Filename:

H:\LaSalle\Off-Site and Control Room Dose\PLR LOCA\l2c16 MSIVB\l2c16 MSIVB.out 1

1 1

0 0

End of Scenario File

EC407055 Rev. 0 Page 44 of 89 RADTRAD Version 3.03 (Spring 2001) run on 10/31/2016 at 23:29:25 Plant Description Number of Nuclides = 60 Inventory Power = 1.0000E+00 MWth Plant Power Level = 3.5590E+03 MWth Number of compartments = 6 Compartment information Compartment number 1 (Source term fraction = 1.0000E+00

)

Name: Containment Compartment volume = 3.9430E+05 (Cubic feet)

Compartment type is Normal Removal devices within compartment:

Spray(s)

Deposition Pathways into and out of compartment 1 Exit Pathway Number 1: ontainment to (Node 1) Inboard MSL B Volume Compartment number 2 Name: (Node 1) Inboard MSL B Volume Compartment volume = 1.0000E-04 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 2 Inlet Pathway Number 1: ontainment to (Node 1) Inboard MSL B Volume Exit Pathway Number 2: Node 1) Inboard MSL B Volume to (Nodes 2& 3) Outbo Compartment number 3 Name: (Nodes 2& 3) Outboard MSL B Volume Compartment volume = 9.6400E+02 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 3 Inlet Pathway Number 2: Node 1) Inboard MSL B Volume to (Nodes 2& 3) Outbo Exit Pathway Number 3: Nodes 2& 3) Outboard MSL B Volume to Condenser Exit Pathway Number 9: Nodes 2& 3) Outboard MSL B Volume to Environment Compartment number 4 Name: Condenser Compartment volume = 2.4635E+05 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 4 Inlet Pathway Number 3: Nodes 2& 3) Outboard MSL B Volume to Condenser Exit Pathway Number 4: ondenser to Environment Compartment number 5 Name: Environment Compartment type is Environment Pathways into and out of compartment 5 Inlet Pathway Number 4: ondenser to Environment Inlet Pathway Number 8: ontrol Room to Environment Inlet Pathway Number 9: Nodes 2& 3) Outboard MSL B Volume to Environment Exit Pathway Number 5: nvironment to Control Room Exit Pathway Number 6: nvironment to Control Room Exit Pathway Number 7: nvironment to Control Room Compartment number 6 Name: Control Room Compartment volume = 1.1740E+05 (Cubic feet)

Compartment type is Control Room Removal devices within compartment:

Filter(s)

EC407055 Rev. 0 Page 45 of 89 Pathways into and out of compartment 6 Inlet Pathway Number 5: nvironment to Control Room Inlet Pathway Number 6: nvironment to Control Room Inlet Pathway Number 7: nvironment to Control Room Exit Pathway Number 8: ontrol Room to Environment Total number of pathways = 9

EC407055 Rev. 0 Page 46 of 89 RADTRAD Version 3.03 (Spring 2001) run on 10/31/2016 at 23:29:25 Scenario Description Radioactive Decay is enabled Calculation of Daughters is enabled Release Fractions and Timings GAP EARLY IN-VESSEL LATE RELEASE RELEASE MASS 0.500000 hr 1.5000 hrs 0.0000 hrs (gm)

NOBLES 5.0000E-02 9.5000E-01 0.0000E+00 4.551E+03 IODINE 5.0000E-02 2.5000E-01 0.0000E+00 3.060E+02 CESIUM 5.0000E-02 2.0000E-01 0.0000E+00 4.876E+04 TELLURIUM 0.0000E+00 5.0000E-02 0.0000E+00 4.042E+01 STRONTIUM 0.0000E+00 2.0000E-02 0.0000E+00 1.671E+03 BARIUM 0.0000E+00 2.0000E-02 0.0000E+00 4.796E+01 RUTHENIUM 0.0000E+00 2.5000E-03 0.0000E+00 5.864E+01 CERIUM 0.0000E+00 5.0000E-04 0.0000E+00 5.986E+02 LANTHANUM 0.0000E+00 2.0000E-04 0.0000E+00 8.157E+00 Inventory Power = 3559. MWt Nuclide Group Specific half Whole Body Inhaled Inhaled Name Inventory life DCF Thyroid Effective (Ci/MWt) (s) (Sv-m3/Bq-s) (Sv/Bq) (Sv/Bq)

Co-58 7 1.529E+02 6.117E+06 4.760E-14 8.720E-10 2.940E-09 Co-60 7 1.830E+02 1.663E+08 1.260E-13 1.620E-08 5.910E-08 Kr-85 1 3.816E+02 3.383E+08 1.190E-16 0.000E+00 0.000E+00 Kr-85m 1 8.439E+03 1.613E+04 7.480E-15 0.000E+00 0.000E+00 Kr-87 1 1.659E+04 4.578E+03 4.120E-14 0.000E+00 0.000E+00 Kr-88 1 2.342E+04 1.022E+04 1.020E-13 0.000E+00 0.000E+00 Rb-86 3 6.081E+01 1.612E+06 4.810E-15 1.330E-09 1.790E-09 Sr-89 5 2.845E+04 4.363E+06 7.730E-17 7.960E-12 1.120E-08 Sr-90 5 3.066E+03 9.190E+08 7.530E-18 2.690E-10 3.510E-07 Sr-91 5 3.858E+04 3.420E+04 4.924E-14 9.930E-12 4.547E-10 Sr-92 5 4.069E+04 9.756E+03 6.790E-14 3.920E-12 2.180E-10 Y-90 9 3.155E+03 2.304E+05 1.900E-16 5.170E-13 2.280E-09 Y-91 9 3.495E+04 5.055E+06 2.600E-16 8.500E-12 1.320E-08 Y-92 9 4.082E+04 1.274E+04 1.300E-14 1.050E-12 2.110E-10 Y-93 9 4.575E+04 3.636E+04 4.800E-15 9.260E-13 5.820E-10 Zr-95 9 4.510E+04 5.528E+06 3.600E-14 1.440E-09 6.390E-09 Zr-97 9 4.671E+04 6.084E+04 4.432E-14 2.315E-11 1.171E-09 Nb-95 9 4.534E+04 3.037E+06 3.740E-14 3.580E-10 1.570E-09 Mo-99 7 5.070E+04 2.376E+05 7.280E-15 1.520E-11 1.070E-09 Tc-99m 7 4.440E+04 2.167E+04 5.890E-15 5.010E-11 8.800E-12 Ru-103 7 4.175E+04 3.394E+06 2.251E-14 2.570E-10 2.421E-09 Ru-105 7 2.874E+04 1.598E+04 3.810E-14 4.150E-12 1.230E-10 Ru-106 7 1.666E+04 3.181E+07 1.040E-14 1.720E-09 1.290E-07 Rh-105 7 2.716E+04 1.273E+05 3.720E-15 2.880E-12 2.580E-10 Sb-127 4 2.886E+03 3.326E+05 3.330E-14 6.150E-11 1.630E-09 Sb-129 4 8.623E+03 1.555E+04 7.140E-14 9.720E-12 1.740E-10 Te-127 4 2.861E+03 3.366E+04 2.420E-16 1.840E-12 8.600E-11 Te-127m 4 3.825E+02 9.418E+06 1.470E-16 9.660E-11 5.810E-09 Te-129 4 8.483E+03 4.176E+03 2.750E-15 5.090E-13 2.090E-11 Te-129m 4 1.263E+03 2.903E+06 3.337E-15 1.563E-10 6.484E-09 Te-131m 4 3.868E+03 1.080E+05 7.463E-14 3.669E-08 1.758E-09 Te-132 4 3.825E+04 2.815E+05 1.030E-14 6.280E-08 2.550E-09 I-131 2 2.686E+04 6.947E+05 1.820E-14 2.920E-07 8.890E-09 I-132 2 3.885E+04 8.280E+03 1.120E-13 1.740E-09 1.030E-10 I-133 2 5.559E+04 7.488E+04 2.940E-14 4.860E-08 1.580E-09 I-134 2 6.168E+04 3.156E+03 1.300E-13 2.880E-10 3.550E-11 I-135 2 5.191E+04 2.380E+04 8.294E-14 8.460E-09 3.320E-10 Xe-133 1 5.504E+04 4.532E+05 1.560E-15 0.000E+00 0.000E+00 Xe-135 1 2.213E+04 3.272E+04 1.190E-14 0.000E+00 0.000E+00 Cs-134 3 6.578E+03 6.507E+07 7.570E-14 1.110E-08 1.250E-08 Cs-136 3 1.903E+03 1.132E+06 1.060E-13 1.730E-09 1.980E-09

EC407055 Rev. 0 Page 47 of 89 Cs-137 3 4.323E+03 9.467E+08 2.725E-14 7.930E-09 8.630E-09 Ba-139 6 5.095E+04 4.962E+03 2.170E-15 2.400E-12 4.640E-11 Ba-140 6 4.910E+04 1.101E+06 8.580E-15 2.560E-10 1.010E-09 La-140 9 5.022E+04 1.450E+05 1.170E-13 6.870E-11 1.310E-09 La-141 9 4.656E+04 1.415E+04 2.390E-15 9.400E-12 1.570E-10 La-142 9 4.550E+04 5.550E+03 1.440E-13 8.740E-12 6.840E-11 Ce-141 8 4.503E+04 2.808E+06 3.430E-15 2.550E-11 2.420E-09 Ce-143 8 4.450E+04 1.188E+05 1.290E-14 6.230E-12 9.160E-10 Ce-144 8 3.597E+04 2.456E+07 2.773E-15 2.920E-10 1.010E-07 Pr-143 9 4.316E+04 1.172E+06 2.100E-17 1.680E-18 2.190E-09 Nd-147 9 1.839E+04 9.487E+05 6.190E-15 1.820E-11 1.850E-09 Np-239 8 5.355E+05 2.035E+05 7.690E-15 7.620E-12 6.780E-10 Pu-238 8 1.525E+02 2.769E+09 4.880E-18 3.860E-10 7.790E-05 Pu-239 8 1.214E+01 7.594E+11 4.240E-18 3.750E-10 8.330E-05 Pu-240 8 1.298E+01 2.063E+11 4.750E-18 3.760E-10 8.330E-05 Pu-241 8 6.179E+03 4.544E+08 7.250E-20 9.150E-12 1.340E-06 Am-241 9 9.817E+00 1.364E+10 8.180E-16 1.600E-09 1.200E-04 Cm-242 9 2.089E+03 1.407E+07 5.690E-18 9.410E-10 4.670E-06 Cm-244 9 1.834E+02 5.715E+08 4.910E-18 1.010E-09 6.700E-05 Nuclide Daughter Fraction Daughter Fraction Daughter Fraction Kr-85m Kr-85 0.21 none 0.00 none 0.00 Kr-87 Rb-87 1.00 none 0.00 none 0.00 Kr-88 Rb-88 1.00 none 0.00 none 0.00 Sr-90 Y-90 1.00 none 0.00 none 0.00 Sr-91 Y-91m 0.58 Y-91 0.42 none 0.00 Sr-92 Y-92 1.00 none 0.00 none 0.00 Y-93 Zr-93 1.00 none 0.00 none 0.00 Zr-95 Nb-95m 0.01 Nb-95 0.99 none 0.00 Zr-97 Nb-97m 0.95 Nb-97 0.05 none 0.00 Mo-99 Tc-99m 0.88 Tc-99 0.12 none 0.00 Tc-99m Tc-99 1.00 none 0.00 none 0.00 Ru-103 Rh-103m 1.00 none 0.00 none 0.00 Ru-105 Rh-105 1.00 none 0.00 none 0.00 Ru-106 Rh-106 1.00 none 0.00 none 0.00 Sb-127 Te-127m 0.18 Te-127 0.82 none 0.00 Sb-129 Te-129m 0.22 Te-129 0.77 none 0.00 Te-127m Te-127 0.98 none 0.00 none 0.00 Te-129 I-129 1.00 none 0.00 none 0.00 Te-129m Te-129 0.65 I-129 0.35 none 0.00 Te-131m Te-131 0.22 I-131 0.78 none 0.00 Te-132 I-132 1.00 none 0.00 none 0.00 I-131 Xe-131m 0.01 none 0.00 none 0.00 I-133 Xe-133m 0.03 Xe-133 0.97 none 0.00 I-135 Xe-135m 0.15 Xe-135 0.85 none 0.00 Xe-135 Cs-135 1.00 none 0.00 none 0.00 Cs-137 Ba-137m 0.95 none 0.00 none 0.00 Ba-140 La-140 1.00 none 0.00 none 0.00 La-141 Ce-141 1.00 none 0.00 none 0.00 Ce-143 Pr-143 1.00 none 0.00 none 0.00 Ce-144 Pr-144m 0.02 Pr-144 0.98 none 0.00 Nd-147 Pm-147 1.00 none 0.00 none 0.00 Np-239 Pu-239 1.00 none 0.00 none 0.00 Pu-238 U-234 1.00 none 0.00 none 0.00 Pu-239 U-235 1.00 none 0.00 none 0.00 Pu-240 U-236 1.00 none 0.00 none 0.00 Pu-241 U-237 0.00 Am-241 1.00 none 0.00 Am-241 Np-237 1.00 none 0.00 none 0.00 Cm-242 Pu-238 1.00 none 0.00 none 0.00 Cm-244 Pu-240 1.00 none 0.00 none 0.00 Iodine fractions Aerosol = 9.5000E-01 Elemental = 4.8500E-02 Organic = 1.5000E-03 COMPARTMENT DATA Compartment number 1: Containment Sprays: Elemental Removal Data

EC407055 Rev. 0 Page 48 of 89 Time (hr) Removal Coef. (hr^-1) 0.0000E+00 3.8600E+00 2.0000E+00 1.8600E+00 3.8500E+00 0.0000E+00 Natural Deposition (Powers' model): Aerosol data Reactor type: 3 Percentile = 10 (%)

Natural Deposition: Elemental Removal Data Time (hr) Removal Coef. (hr^-1) 0.0000E+00 0.0000E+00 Compartment number 2: (Node 1) Inboard MSL B Volume Compartment number 3: (Nodes 2& 3) Outboard MSL B Volume Compartment number 4: Condenser Compartment number 5: Environment Compartment number 6: Control Room Compartment Filter Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 1.4650E+04 0.0000E+00 0.0000E+00 0.0000E+00 3.3300E-01 1.4650E+04 0.0000E+00 0.0000E+00 0.0000E+00 4.0000E+00 1.4650E+04 0.0000E+00 6.6500E+01 6.6500E+01 7.2000E+02 1.4650E+04 0.0000E+00 0.0000E+00 0.0000E+00 PATHWAY DATA Pathway number 1: ontainment to (Node 1) Inboard MSL B Volume Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 2.9960E+00 0.0000E+00 0.0000E+00 0.0000E+00 2.0000E+00 1.7440E+00 0.0000E+00 0.0000E+00 0.0000E+00 2.4000E+01 1.7440E+00 0.0000E+00 0.0000E+00 0.0000E+00 9.6000E+01 1.7440E+00 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 2: Node 1) Inboard MSL B Volume to (Nodes 2& 3) Outbo Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 2.9960E+00 0.0000E+00 0.0000E+00 0.0000E+00 2.0000E+00 1.7440E+00 0.0000E+00 0.0000E+00 0.0000E+00 2.4000E+01 1.7440E+00 0.0000E+00 0.0000E+00 0.0000E+00 9.6000E+01 1.7440E+00 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 3: Nodes 2& 3) Outboard MSL B Volume to Condenser Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 3.3300E-01 6.3760E+00 9.9800E+01 2.4210E+01 0.0000E+00 2.4000E+01 5.4920E+00 0.0000E+00 4.5370E+01 0.0000E+00 9.6000E+01 4.1670E+00 0.0000E+00 8.7450E+01 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 4: ondenser to Environment

EC407055 Rev. 0 Page 49 of 89 Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 7.3230E+00 0.0000E+00 9.9370E+01 0.0000E+00 2.4000E+01 7.3230E+00 0.0000E+00 9.9370E+01 0.0000E+00 9.6000E+01 7.3230E+00 0.0000E+00 9.9370E+01 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 5: nvironment to Control Room Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 1.1000E+03 0.0000E+00 0.0000E+00 0.0000E+00 3.3330E-01 9.0000E+02 9.9000E+01 8.8440E+01 8.8440E+01 4.0000E+00 9.0000E+02 9.9000E+01 9.6130E+01 9.6130E+01 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 6: nvironment to Control Room Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 2.4000E+03 0.0000E+00 0.0000E+00 0.0000E+00 3.3330E-01 2.4000E+03 0.0000E+00 0.0000E+00 0.0000E+00 4.0000E+00 2.4000E+03 0.0000E+00 6.4430E+01 6.4430E+01 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 7: nvironment to Control Room Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 5.0000E+01 0.0000E+00 0.0000E+00 0.0000E+00 3.3330E-01 5.0000E+01 0.0000E+00 0.0000E+00 0.0000E+00 4.0000E+00 5.0000E+01 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 8: ontrol Room to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 3.5500E+03 1.0000E+02 1.0000E+02 1.0000E+02 3.3330E-01 3.3500E+03 1.0000E+02 1.0000E+02 1.0000E+02 4.0000E+00 3.3500E+03 1.0000E+02 1.0000E+02 1.0000E+02 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 9: Nodes 2& 3) Outboard MSL B Volume to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 6.3760E+00 9.1960E+01 2.4210E+01 0.0000E+00 3.3330E-01 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 LOCATION DATA Location Exclusion Area Boundary is in compartment 5 Location X/Q Data Time (hr) X/Q (s

• m^-3) 0.0000E+00 6.6300E-04 2.4000E+01 0.0000E+00 9.6000E+01 0.0000E+00 7.2000E+02 0.0000E+00

EC407055 Rev. 0 Page 50 of 89 Location Breathing Rate Data Time (hr) Breathing Rate (m^3

• sec^-1) 0.0000E+00 3.5000E-04 2.4000E+01 0.0000E+00 7.2000E+02 0.0000E+00 Location Low Population Zone is in compartment 5 Location X/Q Data Time (hr) X/Q (s

• m^-3) 0.0000E+00 2.6500E-05 2.5000E-01 2.6500E-05 1.5000E+00 2.6500E-05 2.0000E+00 1.0800E-05 8.0000E+00 6.8700E-06 2.4000E+01 2.6300E-06 9.6000E+01 6.7400E-07 7.2000E+02 0.0000E+00 Location Breathing Rate Data Time (hr) Breathing Rate (m^3

• sec^-1) 0.0000E+00 3.5000E-04 8.0000E+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.0000E+00 Location Control Room is in compartment 6 Location X/Q Data Time (hr) X/Q (s

• m^-3) 0.0000E+00 8.1300E-03 2.5000E-01 8.1300E-03 1.5000E+00 8.1300E-03 2.0000E+00 6.0900E-03 8.0000E+00 2.4200E-03 2.4000E+01 1.7600E-03 9.6000E+01 1.4600E-03 7.2000E+02 0.0000E+00 Location Breathing Rate Data Time (hr) Breathing Rate (m^3

• sec^-1) 0.0000E+00 3.5000E-04 7.2000E+02 0.0000E+00 Location Occupancy Factor Data Time (hr) Occupancy Factor 0.0000E+00 1.0000E+00 2.4000E+01 6.0000E-01 9.6000E+01 4.0000E-01 7.2000E+02 0.0000E+00 USER SPECIFIED TIME STEP DATA - SUPPLEMENTAL TIME STEPS Time Time step 0.0000E+00 2.5000E-01 2.4000E+01 2.4000E+01 7.2000E+02 0.0000E+00

EC407055 Rev. 0 Page 51 of 89 RADTRAD Version 3.03 (Spring 2001) run on 10/31/2016 at 23:29:25 Dose Output Exclusion Area Boundary Doses:

Time (h) = 0.2500 Whole Body Thyroid TEDE Delta dose (rem) 2.1113E-03 1.6238E-01 8.5379E-03 Accumulated dose (rem) 2.1113E-03 1.6238E-01 8.5379E-03 Low Population Zone Doses:

Time (h) = 0.2500 Whole Body Thyroid TEDE Delta dose (rem) 8.4388E-05 6.4903E-03 3.4126E-04 Accumulated dose (rem) 8.4388E-05 6.4903E-03 3.4126E-04 Control Room Doses:

Time (h) = 0.2500 Whole Body Thyroid TEDE Delta dose (rem) 1.3269E-04 2.3423E-01 9.3886E-03 Accumulated dose (rem) 1.3269E-04 2.3423E-01 9.3886E-03 Exclusion Area Boundary Doses:

Time (h) = 0.3330 Whole Body Thyroid TEDE Delta dose (rem) 2.6955E-03 2.0698E-01 1.0930E-02 Accumulated dose (rem) 4.8068E-03 3.6936E-01 1.9468E-02 Low Population Zone Doses:

Time (h) = 0.3330 Whole Body Thyroid TEDE Delta dose (rem) 1.0774E-04 8.2728E-03 4.3687E-04 Accumulated dose (rem) 1.9213E-04 1.4763E-02 7.7812E-04 Control Room Doses:

Time (h) = 0.3330 Whole Body Thyroid TEDE Delta dose (rem) 2.4065E-04 4.2736E-01 1.7193E-02 Accumulated dose (rem) 3.7334E-04 6.6159E-01 2.6581E-02 Exclusion Area Boundary Doses:

Time (h) = 0.3333 Whole Body Thyroid TEDE Delta dose (rem) 1.2194E-05 9.4821E-04 4.9979E-05 Accumulated dose (rem) 4.8190E-03 3.7030E-01 1.9518E-02 Low Population Zone Doses:

Time (h) = 0.3333 Whole Body Thyroid TEDE Delta dose (rem) 4.8739E-07 3.7900E-05 1.9977E-06 Accumulated dose (rem) 1.9262E-04 1.4801E-02 7.8012E-04 Control Room Doses:

EC407055 Rev. 0 Page 52 of 89 Time (h) = 0.3333 Whole Body Thyroid TEDE Delta dose (rem) 1.1733E-06 2.1220E-03 8.5425E-05 Accumulated dose (rem) 3.7451E-04 6.6371E-01 2.6667E-02 Exclusion Area Boundary Doses:

Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 9.0626E-07 3.7196E-06 1.0454E-06 Accumulated dose (rem) 4.8199E-03 3.7031E-01 1.9519E-02 Low Population Zone Doses:

Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 3.6223E-08 1.4867E-07 4.1785E-08 Accumulated dose (rem) 1.9265E-04 1.4801E-02 7.8016E-04 Control Room Doses:

Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 5.6262E-04 1.0284E+00 4.1393E-02 Accumulated dose (rem) 9.3713E-04 1.6921E+00 6.8060E-02 Exclusion Area Boundary Doses:

Time (h) = 1.5000 Whole Body Thyroid TEDE Delta dose (rem) 2.7795E-04 7.1644E-04 3.0693E-04 Accumulated dose (rem) 5.0979E-03 3.7102E-01 1.9826E-02 Low Population Zone Doses:

Time (h) = 1.5000 Whole Body Thyroid TEDE Delta dose (rem) 1.1110E-05 2.8636E-05 1.2268E-05 Accumulated dose (rem) 2.0376E-04 1.4830E-02 7.9243E-04 Control Room Doses:

Time (h) = 1.5000 Whole Body Thyroid TEDE Delta dose (rem) 1.2711E-03 2.5352E+00 1.0191E-01 Accumulated dose (rem) 2.2082E-03 4.2274E+00 1.6997E-01 Exclusion Area Boundary Doses:

Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 7.4277E-04 1.6361E-03 8.1213E-04 Accumulated dose (rem) 5.8407E-03 3.7266E-01 2.0638E-02 Low Population Zone Doses:

Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.9689E-05 6.5396E-05 3.2461E-05 Accumulated dose (rem) 2.3345E-04 1.4895E-02 8.2489E-04 Control Room Doses:

Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.8714E-04 3.2332E-01 1.3138E-02 Accumulated dose (rem) 2.4953E-03 4.5507E+00 1.8311E-01 Exclusion Area Boundary Doses:

Time (h) = 3.8500 Whole Body Thyroid TEDE Delta dose (rem) 9.6256E-03 2.2299E-02 1.0592E-02 Accumulated dose (rem) 1.5466E-02 3.9496E-01 3.1230E-02 Low Population Zone Doses:

Time (h) = 3.8500 Whole Body Thyroid TEDE Delta dose (rem) 1.5680E-04 3.6324E-04 1.7255E-04 Accumulated dose (rem) 3.9025E-04 1.5258E-02 9.9744E-04

EC407055 Rev. 0 Page 53 of 89 Control Room Doses:

Time (h) = 3.8500 Whole Body Thyroid TEDE Delta dose (rem) 2.5902E-03 3.2660E-01 1.5918E-02 Accumulated dose (rem) 5.0855E-03 4.8773E+00 1.9903E-01 Exclusion Area Boundary Doses:

Time (h) = 4.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.2128E-03 3.0205E-03 1.3429E-03 Accumulated dose (rem) 1.6679E-02 3.9798E-01 3.2573E-02 Low Population Zone Doses:

Time (h) = 4.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.9756E-05 4.9202E-05 2.1875E-05 Accumulated dose (rem) 4.1000E-04 1.5308E-02 1.0193E-03 Control Room Doses:

Time (h) = 4.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.5864E-04 1.8096E-02 1.1308E-03 Accumulated dose (rem) 5.4441E-03 4.8954E+00 2.0016E-01 Exclusion Area Boundary Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 4.5315E-02 1.4118E-01 5.1118E-02 Accumulated dose (rem) 6.1995E-02 5.3916E-01 8.3691E-02 Low Population Zone Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 7.3817E-04 2.2997E-03 8.3269E-04 Accumulated dose (rem) 1.1482E-03 1.7607E-02 1.8520E-03 Control Room Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.5322E-02 3.9146E-01 3.6220E-02 Accumulated dose (rem) 2.0766E-02 5.2868E+00 2.3638E-01 Exclusion Area Boundary Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.9729E-01 1.4528E+00 2.4946E-01 Accumulated dose (rem) 2.5928E-01 1.9920E+00 3.3315E-01 Low Population Zone Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.0443E-03 7.7421E-03 2.3223E-03 Accumulated dose (rem) 3.1925E-03 2.5349E-02 4.1743E-03 Control Room Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.1444E-02 9.9587E-01 8.2665E-02 Accumulated dose (rem) 5.2210E-02 6.2827E+00 3.1904E-01 Exclusion Area Boundary Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 2.5928E-01 1.9920E+00 3.3315E-01 Low Population Zone Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 4.1771E-03 4.4818E-02 5.6364E-03 Accumulated dose (rem) 7.3696E-03 7.0167E-02 9.8107E-03

EC407055 Rev. 0 Page 54 of 89 Control Room Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 7.3029E-02 2.8691E+00 2.0098E-01 Accumulated dose (rem) 1.2524E-01 9.1518E+00 5.2002E-01 Exclusion Area Boundary Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 2.5928E-01 1.9920E+00 3.3315E-01 Low Population Zone Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 7.0301E-03 1.2529E-01 1.0953E-02 Accumulated dose (rem) 1.4400E-02 1.9545E-01 2.0764E-02 Control Room Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.6687E-01 1.2800E+01 7.6176E-01 Accumulated dose (rem) 3.9210E-01 2.1952E+01 1.2818E+00 897 I-131 Summary Containment (Node 1) Inboard MSL (Nodes 2& 3) Outboard Time (hr) I-131 (Curies) I-131 (Curies) I-131 (Curies) 0.000 5.3091E+03 1.3451E-06 6.7100E-04 0.250 2.1565E+06 5.4691E-04 1.2289E+02 0.333 2.7820E+06 7.0554E-04 2.1096E+02 0.333 2.7841E+06 7.0610E-04 2.1129E+02 0.500 3.9260E+06 9.9570E-04 4.4565E+02 0.750 7.1398E+06 1.8108E-03 1.0088E+03 1.000 1.0124E+07 2.5675E-03 1.8537E+03 1.250 1.2909E+07 3.2740E-03 2.9305E+03 1.500 1.5516E+07 3.9350E-03 4.1968E+03 1.750 1.7955E+07 4.5537E-03 5.6159E+03 2.000 2.0239E+07 5.1329E-03 7.1556E+03 2.250 1.5666E+07 3.9732E-03 7.5989E+03 2.500 1.2133E+07 3.0771E-03 7.7460E+03 2.750 9.4015E+06 2.3844E-03 7.6828E+03 3.000 7.2888E+06 1.8486E-03 7.4740E+03 3.250 5.6541E+06 1.4340E-03 7.1676E+03 3.500 4.3888E+06 1.1131E-03 6.7996E+03 3.750 3.4092E+06 8.6462E-04 6.3962E+03 3.850 3.0823E+06 7.8173E-04 6.2295E+03 4.000 2.6522E+06 6.7263E-04 5.9769E+03 4.250 2.0664E+06 5.2408E-04 5.5555E+03 4.500 1.6125E+06 4.0895E-04 5.1416E+03 4.750 1.2606E+06 3.1971E-04 4.7419E+03 5.000 9.8790E+05 2.5054E-04 4.3607E+03 5.250 8.5176E+05 2.1602E-04 4.0033E+03 5.500 7.3533E+05 1.8649E-04 3.6719E+03 5.750 6.3577E+05 1.6124E-04 3.3653E+03 6.000 5.5062E+05 1.3965E-04 3.0821E+03 6.250 4.7781E+05 1.2118E-04 2.8209E+03 6.500 4.1553E+05 1.0539E-04 2.5804E+03 6.750 3.6227E+05 9.1878E-05 2.3591E+03 7.000 3.1672E+05 8.0326E-05 2.1557E+03 7.250 2.7777E+05 7.0446E-05 1.9691E+03 7.500 2.4445E+05 6.1995E-05 1.7980E+03 7.750 2.1595E+05 5.4767E-05 1.6412E+03 8.000 1.9157E+05 4.8585E-05 1.4977E+03 8.250 1.7072E+05 4.3297E-05 1.3665E+03 8.500 1.5509E+05 3.9333E-05 1.2466E+03

EC407055 Rev. 0 Page 55 of 89 8.750 1.4144E+05 3.5872E-05 1.1372E+03 9.000 1.2952E+05 3.2848E-05 1.0374E+03 9.250 1.1910E+05 3.0206E-05 9.4645E+02 9.500 1.1000E+05 2.7898E-05 8.6352E+02 9.750 1.0205E+05 2.5881E-05 7.8796E+02 10.000 9.5099E+04 2.4118E-05 7.1912E+02 10.250 8.9026E+04 2.2578E-05 6.5643E+02 24.000 4.5134E+04 1.1447E-05 3.3022E+01 96.000 3.4159E+04 8.6631E-06 2.6540E+01 720.000 3.0768E+03 7.8032E-07 3.1515E+00 Condenser Environment Control Room Time (hr) I-131 (Curies) I-131 (Curies) I-131 (Curies) 0.000 0.0000E+00 5.6470E-09 7.6899E-11 0.250 0.0000E+00 4.5630E-01 5.5547E-03 0.333 0.0000E+00 1.0386E+00 1.2188E-02 0.333 7.7497E-04 1.0413E+00 1.2218E-02 0.500 6.1942E-01 1.0413E+00 9.1790E-03 0.750 2.4154E+00 1.0414E+00 5.9782E-03 1.000 5.6332E+00 1.0417E+00 3.8952E-03 1.250 1.0462E+01 1.0422E+00 2.5413E-03 1.500 1.6944E+01 1.0433E+00 1.6636E-03 1.750 2.5067E+01 1.0452E+00 1.0979E-03 2.000 3.4798E+01 1.0480E+00 7.3728E-04 2.250 4.5465E+01 1.0520E+00 5.0414E-04 2.500 5.6159E+01 1.0574E+00 3.6030E-04 2.750 6.6609E+01 1.0643E+00 2.7501E-04 3.000 7.6662E+01 1.0726E+00 2.2808E-04 3.250 8.6240E+01 1.0824E+00 2.0626E-04 3.500 9.5313E+01 1.0937E+00 2.0087E-04 3.750 1.0388E+02 1.1065E+00 2.0619E-04 3.850 1.0716E+02 1.1120E+00 2.1042E-04 4.000 1.1195E+02 1.1207E+00 2.1844E-04 4.250 1.1955E+02 1.1365E+00 1.4077E-04 4.500 1.2673E+02 1.1537E+00 1.3186E-04 4.750 1.3351E+02 1.1724E+00 1.3636E-04 5.000 1.3993E+02 1.1925E+00 1.4354E-04 5.250 1.4602E+02 1.2141E+00 1.5120E-04 5.500 1.5181E+02 1.2370E+00 1.5877E-04 5.750 1.5732E+02 1.2614E+00 1.6610E-04 6.000 1.6258E+02 1.2871E+00 1.7310E-04 6.250 1.6761E+02 1.3141E+00 1.7975E-04 6.500 1.7244E+02 1.3425E+00 1.8604E-04 6.750 1.7707E+02 1.3722E+00 1.9198E-04 7.000 1.8153E+02 1.4033E+00 1.9757E-04 7.250 1.8583E+02 1.4356E+00 2.0285E-04 7.500 1.8999E+02 1.4693E+00 2.0782E-04 7.750 1.9401E+02 1.5042E+00 2.1251E-04 8.000 1.9792E+02 1.5404E+00 2.1693E-04 8.250 2.0172E+02 1.5778E+00 1.6170E-04 8.500 2.0541E+02 1.6165E+00 1.3540E-04 8.750 2.0902E+02 1.6565E+00 1.2047E-04 9.000 2.1254E+02 1.6977E+00 1.1150E-04 9.250 2.1598E+02 1.7401E+00 1.0615E-04 9.500 2.1936E+02 1.7837E+00 1.0309E-04 9.750 2.2267E+02 1.8285E+00 1.0148E-04 10.000 2.2592E+02 1.8746E+00 1.0081E-04 10.250 2.2912E+02 1.9218E+00 1.0073E-04 24.000 3.7460E+02 6.2496E+00 1.3633E-04 96.000 8.3560E+02 7.0554E+01 1.8295E-04 720.000 3.2111E+02 8.1465E+02 5.4705E-05 Cumulative Dose Summary Exclusion Area Bounda Low Population Zone Control Room Time Thyroid TEDE Thyroid TEDE Thyroid TEDE (hr) (rem) (rem) (rem) (rem) (rem) (rem) 0.000 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.250 1.6238E-01 8.5379E-03 6.4903E-03 3.4126E-04 2.3423E-01 9.3886E-03

EC407055 Rev. 0 Page 56 of 89 0.333 3.6936E-01 1.9468E-02 1.4763E-02 7.7812E-04 6.6159E-01 2.6581E-02 0.333 3.7030E-01 1.9518E-02 1.4801E-02 7.8012E-04 6.6371E-01 2.6667E-02 0.500 3.7031E-01 1.9519E-02 1.4801E-02 7.8016E-04 1.6921E+00 6.8060E-02 0.750 3.7034E-01 1.9528E-02 1.4802E-02 7.8052E-04 2.7728E+00 1.1152E-01 1.000 3.7043E-01 1.9561E-02 1.4806E-02 7.8184E-04 3.4745E+00 1.3971E-01 1.250 3.7064E-01 1.9647E-02 1.4814E-02 7.8530E-04 3.9304E+00 1.5803E-01 1.500 3.7102E-01 1.9826E-02 1.4830E-02 7.9243E-04 4.2274E+00 1.6997E-01 1.750 3.7167E-01 2.0140E-02 1.4856E-02 8.0501E-04 4.4218E+00 1.7783E-01 2.000 3.7266E-01 2.0638E-02 1.4895E-02 8.2489E-04 4.5507E+00 1.8311E-01 2.250 3.7408E-01 2.1358E-02 1.4918E-02 8.3663E-04 4.6377E+00 1.8676E-01 2.500 3.7598E-01 2.2311E-02 1.4949E-02 8.5214E-04 4.6981E+00 1.8940E-01 2.750 3.7838E-01 2.3493E-02 1.4988E-02 8.7140E-04 4.7426E+00 1.9147E-01 3.000 3.8128E-01 2.4899E-02 1.5036E-02 8.9430E-04 4.7778E+00 1.9324E-01 3.250 3.8469E-01 2.6520E-02 1.5091E-02 9.2071E-04 4.8083E+00 1.9490E-01 3.500 3.8861E-01 2.8347E-02 1.5155E-02 9.5048E-04 4.8369E+00 1.9656E-01 3.750 3.9304E-01 3.0369E-02 1.5227E-02 9.8341E-04 4.8655E+00 1.9830E-01 3.850 3.9496E-01 3.1230E-02 1.5258E-02 9.9744E-04 4.8773E+00 1.9903E-01 4.000 3.9798E-01 3.2573E-02 1.5308E-02 1.0193E-03 4.8954E+00 2.0016E-01 4.250 4.0341E-01 3.4948E-02 1.5396E-02 1.0580E-03 4.9194E+00 2.0192E-01 4.500 4.0933E-01 3.7481E-02 1.5492E-02 1.0993E-03 4.9386E+00 2.0362E-01 4.750 4.1573E-01 4.0160E-02 1.5597E-02 1.1429E-03 4.9576E+00 2.0539E-01 5.000 4.2260E-01 4.2974E-02 1.5709E-02 1.1887E-03 4.9775E+00 2.0727E-01 5.250 4.2994E-01 4.5911E-02 1.5828E-02 1.2366E-03 4.9984E+00 2.0925E-01 5.500 4.3773E-01 4.8961E-02 1.5955E-02 1.2863E-03 5.0204E+00 2.1134E-01 5.750 4.4597E-01 5.2113E-02 1.6089E-02 1.3376E-03 5.0434E+00 2.1352E-01 6.000 4.5465E-01 5.5357E-02 1.6231E-02 1.3905E-03 5.0673E+00 2.1579E-01 6.250 4.6377E-01 5.8686E-02 1.6379E-02 1.4447E-03 5.0921E+00 2.1814E-01 6.500 4.7331E-01 6.2089E-02 1.6535E-02 1.5001E-03 5.1178E+00 2.2056E-01 6.750 4.8327E-01 6.5560E-02 1.6697E-02 1.5567E-03 5.1443E+00 2.2306E-01 7.000 4.9364E-01 6.9091E-02 1.6866E-02 1.6142E-03 5.1715E+00 2.2562E-01 7.250 5.0442E-01 7.2676E-02 1.7041E-02 1.6726E-03 5.1994E+00 2.2823E-01 7.500 5.1560E-01 7.6308E-02 1.7224E-02 1.7317E-03 5.2279E+00 2.3090E-01 7.750 5.2718E-01 7.9981E-02 1.7412E-02 1.7916E-03 5.2571E+00 2.3362E-01 8.000 5.3916E-01 8.3691E-02 1.7607E-02 1.8520E-03 5.2868E+00 2.3638E-01 8.250 5.5152E-01 8.7433E-02 1.7673E-02 1.8883E-03 5.3125E+00 2.3881E-01 8.500 5.6426E-01 9.1202E-02 1.7741E-02 1.9248E-03 5.3329E+00 2.4076E-01 8.750 5.7738E-01 9.4995E-02 1.7811E-02 1.9616E-03 5.3505E+00 2.4243E-01 9.000 5.9087E-01 9.8808E-02 1.7883E-02 1.9984E-03 5.3664E+00 2.4391E-01 9.250 6.0474E-01 1.0264E-01 1.7957E-02 2.0354E-03 5.3813E+00 2.4528E-01 9.500 6.1897E-01 1.0648E-01 1.8033E-02 2.0724E-03 5.3956E+00 2.4659E-01 9.750 6.3356E-01 1.1034E-01 1.8110E-02 2.1096E-03 5.4095E+00 2.4786E-01 10.000 6.4851E-01 1.1420E-01 1.8190E-02 2.1467E-03 5.4232E+00 2.4910E-01 10.250 6.6382E-01 1.1808E-01 1.8272E-02 2.1839E-03 5.4369E+00 2.5033E-01 24.000 1.9920E+00 3.3315E-01 2.5349E-02 4.1743E-03 6.2827E+00 3.1904E-01 96.000 1.9920E+00 3.3315E-01 7.0167E-02 9.8107E-03 9.1518E+00 5.2002E-01 720.000 1.9920E+00 3.3315E-01 1.9545E-01 2.0764E-02 2.1952E+01 1.2818E+00 Worst Two-Hour Doses Exclusion Area Boundary Time Whole Body Thyroid TEDE (hr) (rem) (rem) (rem) 10.3 2.4400E-02 1.9319E-01 3.1284E-02

EC407055 Rev. 0 Page 57 of 89 LaSalle 2 Cycle 16 Containment Leakage Pathway RADTRAD Output File RADTRAD Version 3.03 (Spring 2001) run on 10/31/2016 at 23:29:27 File information Plant file = C:\Users\E42031\AppData\Local\Temp\14\\temp.psf Inventory file = H:\LaSalle\Off-Site and Control Room Dose\PLR LOCA\l2c16 PC25\l2c16 PC25.nif Release file = H:\LaSalle\Off-Site and Control Room Dose\PLR LOCA\l2c16 PC25\l2c16 PC25.rft Dose Conversion file = H:\LaSalle\Off-Site and Control Room Dose\PLR LOCA\l2c16 PC25\l2c16 PC25.inp Radtrad 3.03 4/15/2001 LSCS LOCA PC Leak with 25% Makeup Nuclide Inventory File:

H:\LaSalle\Off-Site and Control Room Dose\PLR LOCA\l2c16 PC25\l2c16 PC25.nif Plant Power Level:

3.5590E+03 Compartments:

4 Compartment 1:

Containment 3

3.9430E+05 1

0 0

1 0

Compartment 2:

Reactor Building 3

1.00E+00 0

0 0

0 0

Compartment 3:

Environment 2

0.0000E+00 0

0 0

0 0

Compartment 4:

EC407055 Rev. 0 Page 58 of 89 Control Room 1

1.1740E+05 0

0 1

0 0

Pathways:

6 Pathway 1:

Containment to Reactor Building 1

2 4

Pathway 2:

Reactor Building to Environment 2

3 2

Pathway 3:

Environment to Control Room Filtered Outside Air Intake 3

4 2

Pathway 4:

Environment to Control Room Filtered by Recirc Filter Only 3

4 2

Pathway 5:

Environment to Control Room Outside air Unfiltered Before Supply Fan 3

4 2

Pathway 6:

Control Room to Environment 4

3 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1 1.0000E+00 H:\LaSalle\Off-Site and Control Room Dose\PLR LOCA\l2c16 PC25\l2c16 PC25.inp H:\LaSalle\Off-Site and Control Room Dose\PLR LOCA\l2c16 PC25\l2c16 PC25.rft 0.0000E+00 1

9.5000E-01 4.8500E-02 1.5000E-03 1.0000E+00 Overlying Pool:

0 0.0000E+00 0

0 0

0 Compartments:

4 Compartment 1:

0 1

1 0.0000E+00 0

1 0.0000E+00 3

EC407055 Rev. 0 Page 59 of 89 0.0000E+00 3.8600E+00 2.0000E+00 1.8600E+00 3.8500E+00 0.0000E+00 1

0.0000E+00 0

0 0

3 3

1.0000E+01 1

1 0.0000E+00 0.0000E+00 Compartment 2:

0 1

0 0

0 0

0 0

0 Compartment 3:

0 1

0 0

0 0

0 0

0 Compartment 4:

0 1

0 0

0 0

1 1.4650E+04 4

0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 3.3300E-01 0.0000E+00 0.0000E+00 0.0000E+00 4.0000E+00 0.0000E+00 6.6500E+01 6.6500E+01 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0

0 Pathways:

6 Pathway 1:

0 0

0 0

0 0

0 0

0 0

1 2

0.0000E+00 1.0000E+00 7.2000E+02 0.0000E+00 0

Pathway 2:

0 0

EC407055 Rev. 0 Page 60 of 89 0

0 0

1 3

0.0000E+00 1.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 2.5000E-01 1.0000E+00 9.8500E+01 9.8500E+01 9.8500E+01 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 0

0 Pathway 3:

0 0

0 0

0 1

4 0.0000E+00 1.1000E+03 0.0000E+00 0.0000E+00 0.0000E+00 3.3300E-01 9.0000E+02 9.9000E+01 8.8440E+01 8.8440E+01 4.0000E+00 9.0000E+02 9.9000E+01 9.6130E+01 9.6130E+01 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 0

0 Pathway 4:

0 0

0 0

0 1

4 0.0000E+00 2.4000E+03 0.0000E+00 0.0000E+00 0.0000E+00 3.3300E-01 2.4000E+03 0.0000E+00 0.0000E+00 0.0000E+00 4.0000E+00 2.4000E+03 0.0000E+00 6.6500E+01 6.6500E+01 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 0

0 Pathway 5:

0 0

0 0

0 1

2 0.0000E+00 5.0000E+01 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 0

0 Pathway 6:

0 0

0 0

EC407055 Rev. 0 Page 61 of 89 0

1 3

0.0000E+00 3.5500E+03 1.0000E+02 1.0000E+02 1.0000E+02 3.3300E-01 3.3500E+03 1.0000E+02 1.0000E+02 1.0000E+02 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 0

0 Dose Locations:

3 Location 1:

Exclusion Area Boundary 3

1 8

0.0000E+00 6.6300E-04 2.5000E-01 2.7400E-06 1.5000E+00 8.8000E-05 2.0000E+00 1.2900E-06 8.0000E+00 8.8300E-07 2.4000E+01 3.8900E-07 9.6000E+01 1.2000E-07 7.2000E+02 0.0000E+00 1

4 0.0000E+00 3.5000E-04 8.0000E+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.0000E+00 0

Location 2:

Low Population Zone 3

1 8

0.0000E+00 2.6500E-05 2.5000E-01 1.7700E-06 1.5000E+00 1.0500E-05 2.0000E+00 8.3400E-07 8.0000E+00 5.7200E-07 2.4000E+01 2.5300E-07 9.6000E+01 7.8100E-08 7.2000E+02 0.0000E+00 1

4 0.0000E+00 3.5000E-04 8.0000E+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.0000E+00 0

Location 3:

Control Room 4

0 1

2 0.0000E+00 3.5000E-04 7.2000E+02 0.0000E+00 1

4 0.0000E+00 1.0000E+00 2.4000E+01 6.0000E-01 9.6000E+01 4.0000E-01 7.2000E+02 0.0000E+00 Effective Volume Location:

1 8

EC407055 Rev. 0 Page 62 of 89 0.0000E+00 6.8300E-04 2.5000E-01 1.1700E-05 1.5000E+00 1.1700E-05 2.0000E+00 1.0000E-36 8.0000E+00 1.0000E-36 2.4000E+01 7.1700E-08 9.6000E+01 2.2500E-08 7.2000E+02 0.0000E+00 Simulation Parameters:

1 0.0000E+00 0.0000E+00 Output Filename:

H:\LaSalle\Off-Site and Control Room Dose\PLR LOCA\l2c16 PC25\l2c16 PC25.out 1

1 1

0 0

End of Scenario File

EC407055 Rev. 0 Page 63 of 89 RADTRAD Version 3.03 (Spring 2001) run on 10/31/2016 at 23:29:27 Plant Description Number of Nuclides = 60 Inventory Power = 1.0000E+00 MWth Plant Power Level = 3.5590E+03 MWth Number of compartments = 4 Compartment information Compartment number 1 (Source term fraction = 1.0000E+00

)

Name: Containment Compartment volume = 3.9430E+05 (Cubic feet)

Compartment type is Normal Removal devices within compartment:

Spray(s)

Deposition Pathways into and out of compartment 1 Exit Pathway Number 1: ontainment to Reactor Building Compartment number 2 Name: Reactor Building Compartment volume = 1.0000E+00 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 2 Inlet Pathway Number 1: ontainment to Reactor Building Exit Pathway Number 2: eactor Building to Environment Compartment number 3 Name: Environment Compartment type is Environment Pathways into and out of compartment 3 Inlet Pathway Number 2: eactor Building to Environment Inlet Pathway Number 6: Control Room to Environment Exit Pathway Number 3: Environment to Control Room Filtered Outside Air I Exit Pathway Number 4: Environment to Control Room Filtered by Recirc Fil Exit Pathway Number 5: Environment to Control Room Outside air Unfiltered Compartment number 4 Name: Control Room Compartment volume = 1.1740E+05 (Cubic feet)

Compartment type is Control Room Removal devices within compartment:

Filter(s)

Pathways into and out of compartment 4 Inlet Pathway Number 3: Environment to Control Room Filtered Outside Air I Inlet Pathway Number 4: Environment to Control Room Filtered by Recirc Fil Inlet Pathway Number 5: Environment to Control Room Outside air Unfiltered Exit Pathway Number 6: Control Room to Environment Total number of pathways = 6

EC407055 Rev. 0 Page 64 of 89 RADTRAD Version 3.03 (Spring 2001) run on 10/31/2016 at 23:29:27 Scenario Description Radioactive Decay is enabled Calculation of Daughters is enabled Release Fractions and Timings GAP EARLY IN-VESSEL LATE RELEASE RELEASE MASS 0.500000 hr 1.5000 hrs 0.0000 hrs (gm)

NOBLES 5.0000E-02 9.5000E-01 0.0000E+00 4.551E+03 IODINE 5.0000E-02 2.5000E-01 0.0000E+00 3.060E+02 CESIUM 5.0000E-02 2.0000E-01 0.0000E+00 4.876E+04 TELLURIUM 0.0000E+00 5.0000E-02 0.0000E+00 4.042E+01 STRONTIUM 0.0000E+00 2.0000E-02 0.0000E+00 1.671E+03 BARIUM 0.0000E+00 2.0000E-02 0.0000E+00 4.796E+01 RUTHENIUM 0.0000E+00 2.5000E-03 0.0000E+00 5.864E+01 CERIUM 0.0000E+00 5.0000E-04 0.0000E+00 5.986E+02 LANTHANUM 0.0000E+00 2.0000E-04 0.0000E+00 8.157E+00 Inventory Power = 3559. MWt Nuclide Group Specific half Whole Body Inhaled Inhaled Name Inventory life DCF Thyroid Effective (Ci/MWt) (s) (Sv-m3/Bq-s) (Sv/Bq) (Sv/Bq)

Co-58 7 1.529E+02 6.117E+06 4.760E-14 8.720E-10 2.940E-09 Co-60 7 1.830E+02 1.663E+08 1.260E-13 1.620E-08 5.910E-08 Kr-85 1 3.816E+02 3.383E+08 1.190E-16 0.000E+00 0.000E+00 Kr-85m 1 8.439E+03 1.613E+04 7.480E-15 0.000E+00 0.000E+00 Kr-87 1 1.659E+04 4.578E+03 4.120E-14 0.000E+00 0.000E+00 Kr-88 1 2.342E+04 1.022E+04 1.020E-13 0.000E+00 0.000E+00 Rb-86 3 6.081E+01 1.612E+06 4.810E-15 1.330E-09 1.790E-09 Sr-89 5 2.845E+04 4.363E+06 7.730E-17 7.960E-12 1.120E-08 Sr-90 5 3.066E+03 9.190E+08 7.530E-18 2.690E-10 3.510E-07 Sr-91 5 3.858E+04 3.420E+04 4.924E-14 9.930E-12 4.547E-10 Sr-92 5 4.069E+04 9.756E+03 6.790E-14 3.920E-12 2.180E-10 Y-90 9 3.155E+03 2.304E+05 1.900E-16 5.170E-13 2.280E-09 Y-91 9 3.495E+04 5.055E+06 2.600E-16 8.500E-12 1.320E-08 Y-92 9 4.082E+04 1.274E+04 1.300E-14 1.050E-12 2.110E-10 Y-93 9 4.575E+04 3.636E+04 4.800E-15 9.260E-13 5.820E-10 Zr-95 9 4.510E+04 5.528E+06 3.600E-14 1.440E-09 6.390E-09 Zr-97 9 4.671E+04 6.084E+04 4.432E-14 2.315E-11 1.171E-09 Nb-95 9 4.534E+04 3.037E+06 3.740E-14 3.580E-10 1.570E-09 Mo-99 7 5.070E+04 2.376E+05 7.280E-15 1.520E-11 1.070E-09 Tc-99m 7 4.440E+04 2.167E+04 5.890E-15 5.010E-11 8.800E-12 Ru-103 7 4.175E+04 3.394E+06 2.251E-14 2.570E-10 2.421E-09 Ru-105 7 2.874E+04 1.598E+04 3.810E-14 4.150E-12 1.230E-10 Ru-106 7 1.666E+04 3.181E+07 1.040E-14 1.720E-09 1.290E-07 Rh-105 7 2.716E+04 1.273E+05 3.720E-15 2.880E-12 2.580E-10 Sb-127 4 2.886E+03 3.326E+05 3.330E-14 6.150E-11 1.630E-09 Sb-129 4 8.623E+03 1.555E+04 7.140E-14 9.720E-12 1.740E-10 Te-127 4 2.861E+03 3.366E+04 2.420E-16 1.840E-12 8.600E-11 Te-127m 4 3.825E+02 9.418E+06 1.470E-16 9.660E-11 5.810E-09 Te-129 4 8.483E+03 4.176E+03 2.750E-15 5.090E-13 2.090E-11 Te-129m 4 1.263E+03 2.903E+06 3.337E-15 1.563E-10 6.484E-09 Te-131m 4 3.868E+03 1.080E+05 7.463E-14 3.669E-08 1.758E-09 Te-132 4 3.825E+04 2.815E+05 1.030E-14 6.280E-08 2.550E-09 I-131 2 2.686E+04 6.947E+05 1.820E-14 2.920E-07 8.890E-09 I-132 2 3.885E+04 8.280E+03 1.120E-13 1.740E-09 1.030E-10 I-133 2 5.559E+04 7.488E+04 2.940E-14 4.860E-08 1.580E-09 I-134 2 6.168E+04 3.156E+03 1.300E-13 2.880E-10 3.550E-11 I-135 2 5.191E+04 2.380E+04 8.294E-14 8.460E-09 3.320E-10 Xe-133 1 5.504E+04 4.532E+05 1.560E-15 0.000E+00 0.000E+00 Xe-135 1 2.213E+04 3.272E+04 1.190E-14 0.000E+00 0.000E+00 Cs-134 3 6.578E+03 6.507E+07 7.570E-14 1.110E-08 1.250E-08 Cs-136 3 1.903E+03 1.132E+06 1.060E-13 1.730E-09 1.980E-09

EC407055 Rev. 0 Page 65 of 89 Cs-137 3 4.323E+03 9.467E+08 2.725E-14 7.930E-09 8.630E-09 Ba-139 6 5.095E+04 4.962E+03 2.170E-15 2.400E-12 4.640E-11 Ba-140 6 4.910E+04 1.101E+06 8.580E-15 2.560E-10 1.010E-09 La-140 9 5.022E+04 1.450E+05 1.170E-13 6.870E-11 1.310E-09 La-141 9 4.656E+04 1.415E+04 2.390E-15 9.400E-12 1.570E-10 La-142 9 4.550E+04 5.550E+03 1.440E-13 8.740E-12 6.840E-11 Ce-141 8 4.503E+04 2.808E+06 3.430E-15 2.550E-11 2.420E-09 Ce-143 8 4.450E+04 1.188E+05 1.290E-14 6.230E-12 9.160E-10 Ce-144 8 3.597E+04 2.456E+07 2.773E-15 2.920E-10 1.010E-07 Pr-143 9 4.316E+04 1.172E+06 2.100E-17 1.680E-18 2.190E-09 Nd-147 9 1.839E+04 9.487E+05 6.190E-15 1.820E-11 1.850E-09 Np-239 8 5.355E+05 2.035E+05 7.690E-15 7.620E-12 6.780E-10 Pu-238 8 1.525E+02 2.769E+09 4.880E-18 3.860E-10 7.790E-05 Pu-239 8 1.214E+01 7.594E+11 4.240E-18 3.750E-10 8.330E-05 Pu-240 8 1.298E+01 2.063E+11 4.750E-18 3.760E-10 8.330E-05 Pu-241 8 6.179E+03 4.544E+08 7.250E-20 9.150E-12 1.340E-06 Am-241 9 9.817E+00 1.364E+10 8.180E-16 1.600E-09 1.200E-04 Cm-242 9 2.089E+03 1.407E+07 5.690E-18 9.410E-10 4.670E-06 Cm-244 9 1.834E+02 5.715E+08 4.910E-18 1.010E-09 6.700E-05 Nuclide Daughter Fraction Daughter Fraction Daughter Fraction Kr-85m Kr-85 0.21 none 0.00 none 0.00 Kr-87 Rb-87 1.00 none 0.00 none 0.00 Kr-88 Rb-88 1.00 none 0.00 none 0.00 Sr-90 Y-90 1.00 none 0.00 none 0.00 Sr-91 Y-91m 0.58 Y-91 0.42 none 0.00 Sr-92 Y-92 1.00 none 0.00 none 0.00 Y-93 Zr-93 1.00 none 0.00 none 0.00 Zr-95 Nb-95m 0.01 Nb-95 0.99 none 0.00 Zr-97 Nb-97m 0.95 Nb-97 0.05 none 0.00 Mo-99 Tc-99m 0.88 Tc-99 0.12 none 0.00 Tc-99m Tc-99 1.00 none 0.00 none 0.00 Ru-103 Rh-103m 1.00 none 0.00 none 0.00 Ru-105 Rh-105 1.00 none 0.00 none 0.00 Ru-106 Rh-106 1.00 none 0.00 none 0.00 Sb-127 Te-127m 0.18 Te-127 0.82 none 0.00 Sb-129 Te-129m 0.22 Te-129 0.77 none 0.00 Te-127m Te-127 0.98 none 0.00 none 0.00 Te-129 I-129 1.00 none 0.00 none 0.00 Te-129m Te-129 0.65 I-129 0.35 none 0.00 Te-131m Te-131 0.22 I-131 0.78 none 0.00 Te-132 I-132 1.00 none 0.00 none 0.00 I-131 Xe-131m 0.01 none 0.00 none 0.00 I-133 Xe-133m 0.03 Xe-133 0.97 none 0.00 I-135 Xe-135m 0.15 Xe-135 0.85 none 0.00 Xe-135 Cs-135 1.00 none 0.00 none 0.00 Cs-137 Ba-137m 0.95 none 0.00 none 0.00 Ba-140 La-140 1.00 none 0.00 none 0.00 La-141 Ce-141 1.00 none 0.00 none 0.00 Ce-143 Pr-143 1.00 none 0.00 none 0.00 Ce-144 Pr-144m 0.02 Pr-144 0.98 none 0.00 Nd-147 Pm-147 1.00 none 0.00 none 0.00 Np-239 Pu-239 1.00 none 0.00 none 0.00 Pu-238 U-234 1.00 none 0.00 none 0.00 Pu-239 U-235 1.00 none 0.00 none 0.00 Pu-240 U-236 1.00 none 0.00 none 0.00 Pu-241 U-237 0.00 Am-241 1.00 none 0.00 Am-241 Np-237 1.00 none 0.00 none 0.00 Cm-242 Pu-238 1.00 none 0.00 none 0.00 Cm-244 Pu-240 1.00 none 0.00 none 0.00 Iodine fractions Aerosol = 9.5000E-01 Elemental = 4.8500E-02 Organic = 1.5000E-03 COMPARTMENT DATA Compartment number 1: Containment Sprays: Elemental Removal Data

EC407055 Rev. 0 Page 66 of 89 Time (hr) Removal Coef. (hr^-1) 0.0000E+00 3.8600E+00 2.0000E+00 1.8600E+00 3.8500E+00 0.0000E+00 Natural Deposition (Powers' model): Aerosol data Reactor type: 3 Percentile = 10 (%)

Natural Deposition: Elemental Removal Data Time (hr) Removal Coef. (hr^-1) 0.0000E+00 0.0000E+00 Compartment number 2: Reactor Building Compartment number 3: Environment Compartment number 4: Control Room Compartment Filter Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 1.4650E+04 0.0000E+00 0.0000E+00 0.0000E+00 3.3300E-01 1.4650E+04 0.0000E+00 0.0000E+00 0.0000E+00 4.0000E+00 1.4650E+04 0.0000E+00 6.6500E+01 6.6500E+01 7.2000E+02 1.4650E+04 0.0000E+00 0.0000E+00 0.0000E+00 PATHWAY DATA Pathway number 1: ontainment to Reactor Building Convection Data Time (hr) Flow Rate (% / day) 0.0000E+00 1.0000E+00 7.2000E+02 0.0000E+00 Pathway number 2: eactor Building to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 1.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 2.5000E-01 1.0000E+00 9.8500E+01 9.8500E+01 9.8500E+01 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 3: Environment to Control Room Filtered Outside Air I Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 1.1000E+03 0.0000E+00 0.0000E+00 0.0000E+00 3.3300E-01 9.0000E+02 9.9000E+01 8.8440E+01 8.8440E+01 4.0000E+00 9.0000E+02 9.9000E+01 9.6130E+01 9.6130E+01 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 4: Environment to Control Room Filtered by Recirc Fil Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 2.4000E+03 0.0000E+00 0.0000E+00 0.0000E+00 3.3300E-01 2.4000E+03 0.0000E+00 0.0000E+00 0.0000E+00 4.0000E+00 2.4000E+03 0.0000E+00 6.6500E+01 6.6500E+01 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 5: Environment to Control Room Outside air Unfiltered Pathway Filter: Removal Data

EC407055 Rev. 0 Page 67 of 89 Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 5.0000E+01 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 6: Control Room to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 3.5500E+03 1.0000E+02 1.0000E+02 1.0000E+02 3.3300E-01 3.3500E+03 1.0000E+02 1.0000E+02 1.0000E+02 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 LOCATION DATA Location Exclusion Area Boundary is in compartment 3 Location X/Q Data Time (hr) X/Q (s

• m^-3) 0.0000E+00 6.6300E-04 2.5000E-01 2.7400E-06 1.5000E+00 8.8000E-05 2.0000E+00 1.2900E-06 8.0000E+00 8.8300E-07 2.4000E+01 3.8900E-07 9.6000E+01 1.2000E-07 7.2000E+02 0.0000E+00 Location Breathing Rate Data Time (hr) Breathing Rate (m^3

• sec^-1) 0.0000E+00 3.5000E-04 8.0000E+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.0000E+00 Location Low Population Zone is in compartment 3 Location X/Q Data Time (hr) X/Q (s

• m^-3) 0.0000E+00 2.6500E-05 2.5000E-01 1.7700E-06 1.5000E+00 1.0500E-05 2.0000E+00 8.3400E-07 8.0000E+00 5.7200E-07 2.4000E+01 2.5300E-07 9.6000E+01 7.8100E-08 7.2000E+02 0.0000E+00 Location Breathing Rate Data Time (hr) Breathing Rate (m^3

• sec^-1) 0.0000E+00 3.5000E-04 8.0000E+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.0000E+00 Location Control Room is in compartment 4 Location X/Q Data Time (hr) X/Q (s

• m^-3) 0.0000E+00 6.8300E-04 2.5000E-01 1.1700E-05 1.5000E+00 1.1700E-05 2.0000E+00 1.0000E-36 8.0000E+00 1.0000E-36 2.4000E+01 7.1700E-08 9.6000E+01 2.2500E-08 7.2000E+02 0.0000E+00 Location Breathing Rate Data Time (hr) Breathing Rate (m^3

• sec^-1) 0.0000E+00 3.5000E-04

EC407055 Rev. 0 Page 68 of 89 7.2000E+02 0.0000E+00 Location Occupancy Factor Data Time (hr) Occupancy Factor 0.0000E+00 1.0000E+00 2.4000E+01 6.0000E-01 9.6000E+01 4.0000E-01 7.2000E+02 0.0000E+00 USER SPECIFIED TIME STEP DATA - SUPPLEMENTAL TIME STEPS Time Time step 0.0000E+00 0.0000E+00

EC407055 Rev. 0 Page 69 of 89 RADTRAD Version 3.03 (Spring 2001) run on 10/31/2016 at 23:29:27 Dose Output Exclusion Area Boundary Doses:

Time (h) = 0.2500 Whole Body Thyroid TEDE Delta dose (rem) 2.0815E-01 3.6434E+01 1.7549E+00 Accumulated dose (rem) 2.0815E-01 3.6434E+01 1.7549E+00 Low Population Zone Doses:

Time (h) = 0.2500 Whole Body Thyroid TEDE Delta dose (rem) 8.3197E-03 1.4562E+00 7.0142E-02 Accumulated dose (rem) 8.3197E-03 1.4562E+00 7.0142E-02 Control Room Doses:

Time (h) = 0.2500 Whole Body Thyroid TEDE Delta dose (rem) 1.3075E-03 5.2339E+00 2.2341E-01 Accumulated dose (rem) 1.3075E-03 5.2339E+00 2.2341E-01 Exclusion Area Boundary Doses:

Time (h) = 0.3330 Whole Body Thyroid TEDE Delta dose (rem) 1.1995E-04 1.7914E-03 1.9611E-04 Accumulated dose (rem) 2.0827E-01 3.6435E+01 1.7551E+00 Low Population Zone Doses:

Time (h) = 0.3330 Whole Body Thyroid TEDE Delta dose (rem) 7.7484E-05 1.1572E-03 1.2669E-04 Accumulated dose (rem) 8.3972E-03 1.4574E+00 7.0268E-02 Control Room Doses:

Time (h) = 0.3330 Whole Body Thyroid TEDE Delta dose (rem) 1.0996E-03 4.5624E+00 1.9481E-01 Accumulated dose (rem) 2.4071E-03 9.7964E+00 4.1821E-01 Exclusion Area Boundary Doses:

Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 3.3812E-04 4.9875E-03 5.5045E-04 Accumulated dose (rem) 2.0861E-01 3.6440E+01 1.7556E+00 Low Population Zone Doses:

Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 2.1842E-04 3.2219E-03 3.5558E-04 Accumulated dose (rem) 8.6156E-03 1.4606E+00 7.0624E-02 Control Room Doses:

EC407055 Rev. 0 Page 70 of 89 Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 1.7182E-03 7.3862E+00 3.1533E-01 Accumulated dose (rem) 4.1253E-03 1.7183E+01 7.3354E-01 Exclusion Area Boundary Doses:

Time (h) = 1.5000 Whole Body Thyroid TEDE Delta dose (rem) 1.4384E-02 9.2096E-02 1.9403E-02 Accumulated dose (rem) 2.2299E-01 3.6532E+01 1.7750E+00 Low Population Zone Doses:

Time (h) = 1.5000 Whole Body Thyroid TEDE Delta dose (rem) 9.2921E-03 5.9493E-02 1.2534E-02 Accumulated dose (rem) 1.7908E-02 1.5201E+00 8.3158E-02 Control Room Doses:

Time (h) = 1.5000 Whole Body Thyroid TEDE Delta dose (rem) 4.7817E-03 1.8296E+01 7.8326E-01 Accumulated dose (rem) 8.9070E-03 3.5479E+01 1.5168E+00 Exclusion Area Boundary Doses:

Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 4.5967E-01 2.6849E+00 6.1542E-01 Accumulated dose (rem) 6.8267E-01 3.9217E+01 2.3904E+00 Low Population Zone Doses:

Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 5.4848E-02 3.2036E-01 7.3431E-02 Accumulated dose (rem) 7.2755E-02 1.8405E+00 1.5659E-01 Control Room Doses:

Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.9782E-03 2.4445E+00 1.0840E-01 Accumulated dose (rem) 1.0885E-02 3.7923E+01 1.6252E+00 Exclusion Area Boundary Doses:

Time (h) = 3.8500 Whole Body Thyroid TEDE Delta dose (rem) 2.2797E-02 7.5115E-02 2.7213E-02 Accumulated dose (rem) 7.0546E-01 3.9292E+01 2.4177E+00 Low Population Zone Doses:

Time (h) = 3.8500 Whole Body Thyroid TEDE Delta dose (rem) 1.4738E-02 4.8563E-02 1.7593E-02 Accumulated dose (rem) 8.7494E-02 1.8890E+00 1.7418E-01 Control Room Doses:

Time (h) = 3.8500 Whole Body Thyroid TEDE Delta dose (rem) 2.1778E-03 1.8222E+00 8.3312E-02 Accumulated dose (rem) 1.3063E-02 3.9745E+01 1.7085E+00 Exclusion Area Boundary Doses:

Time (h) = 4.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.4553E-03 1.8903E-03 1.5669E-03 Accumulated dose (rem) 7.0692E-01 3.9294E+01 2.4192E+00 Low Population Zone Doses:

Time (h) = 4.0000 Whole Body Thyroid TEDE Delta dose (rem) 9.4089E-04 1.2221E-03 1.0130E-03 Accumulated dose (rem) 8.8435E-02 1.8903E+00 1.7520E-01

EC407055 Rev. 0 Page 71 of 89 Control Room Doses:

Time (h) = 4.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.5719E-05 1.7770E-02 8.1004E-04 Accumulated dose (rem) 1.3079E-02 3.9763E+01 1.7093E+00 Exclusion Area Boundary Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.6310E-02 1.3396E-02 2.7089E-02 Accumulated dose (rem) 7.3323E-01 3.9308E+01 2.4463E+00 Low Population Zone Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.7010E-02 8.6608E-03 1.7514E-02 Accumulated dose (rem) 1.0544E-01 1.8989E+00 1.9271E-01 Control Room Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 4.7246E-05 5.8518E-02 2.6899E-03 Accumulated dose (rem) 1.3126E-02 3.9822E+01 1.7120E+00 Exclusion Area Boundary Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.1660E-02 1.3643E-03 2.1714E-02 Accumulated dose (rem) 7.5489E-01 3.9309E+01 2.4680E+00 Low Population Zone Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.4031E-02 8.8380E-04 1.4066E-02 Accumulated dose (rem) 1.1948E-01 1.8998E+00 2.0678E-01 Control Room Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.5044E-08 5.8560E-05 2.7108E-06 Accumulated dose (rem) 1.3126E-02 3.9822E+01 1.7120E+00 Exclusion Area Boundary Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.1011E-02 1.8287E-03 1.1067E-02 Accumulated dose (rem) 7.6590E-01 3.9311E+01 2.4791E+00 Low Population Zone Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 7.1614E-03 1.1894E-03 7.1978E-03 Accumulated dose (rem) 1.2664E-01 1.9010E+00 2.1397E-01 Control Room Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 5.2682E-05 2.0742E-05 5.3318E-05 Accumulated dose (rem) 1.3179E-02 3.9822E+01 1.7121E+00 Exclusion Area Boundary Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 5.3500E-03 1.4437E-03 5.3940E-03 Accumulated dose (rem) 7.7125E-01 3.9312E+01 2.4845E+00 Low Population Zone Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.4820E-03 9.3958E-04 3.5106E-03 Accumulated dose (rem) 1.3012E-01 1.9019E+00 2.1748E-01

EC407055 Rev. 0 Page 72 of 89 Control Room Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.7859E-05 1.1241E-05 1.8201E-05 Accumulated dose (rem) 1.3197E-02 3.9822E+01 1.7121E+00 839 I-131 Summary Containment Reactor Building Environment Time (hr) I-131 (Curies) I-131 (Curies) I-131 (Curies) 0.000 5.3091E+03 6.0776E-04 6.7719E-06 0.250 2.1565E+06 1.4062E+01 1.0208E+02 0.333 2.7820E+06 1.8463E+01 1.0329E+02 0.500 3.9261E+06 2.6509E+01 1.0669E+02 0.800 7.7569E+06 5.2453E+01 1.1731E+02 1.100 1.1265E+07 7.6927E+01 1.3482E+02 1.400 1.4499E+07 9.9484E+01 1.5867E+02 1.500 1.5522E+07 1.0661E+02 1.6794E+02 1.800 1.8431E+07 1.2690E+02 1.9950E+02 2.000 2.0245E+07 1.3956E+02 2.2349E+02 2.300 1.4889E+07 1.0518E+02 2.5667E+02 2.600 1.0958E+07 7.7410E+01 2.8113E+02 2.900 8.0710E+06 5.7013E+01 2.9913E+02 3.200 5.9493E+06 4.2023E+01 3.1239E+02 3.500 4.3892E+06 3.1002E+01 3.2217E+02 3.800 3.2418E+06 2.2896E+01 3.2939E+02 3.850 3.0825E+06 2.1770E+01 3.3040E+02 4.000 2.6522E+06 1.8730E+01 3.3313E+02 4.300 1.9661E+06 1.3883E+01 3.3750E+02 4.600 1.4608E+06 1.0313E+01 3.4074E+02 4.900 1.0886E+06 7.6841E+00 3.4315E+02 5.200 8.7716E+05 6.1517E+00 3.4498E+02 5.500 7.3517E+05 5.1554E+00 3.4650E+02 5.800 6.1749E+05 4.3296E+00 3.4778E+02 6.100 5.1996E+05 3.6452E+00 3.4886E+02 6.400 4.3912E+05 3.0779E+00 3.4976E+02 6.700 3.7211E+05 2.6077E+00 3.5053E+02 7.000 3.1657E+05 2.2180E+00 3.5118E+02 7.300 2.7054E+05 1.8949E+00 3.5173E+02 7.600 2.3238E+05 1.6272E+00 3.5220E+02 7.900 2.0074E+05 1.4052E+00 3.5261E+02 8.000 1.9145E+05 1.3399E+00 3.5274E+02 8.300 1.6681E+05 1.1670E+00 3.5307E+02 8.600 1.4887E+05 1.0402E+00 3.5337E+02 8.900 1.3363E+05 9.3337E-01 3.5364E+02 9.200 1.2066E+05 8.4253E-01 3.5388E+02 9.500 1.0964E+05 7.6528E-01 3.5409E+02 9.800 1.0026E+05 6.9959E-01 3.5429E+02 10.100 9.2287E+04 6.4371E-01 3.5447E+02 10.400 8.5502E+04 5.9616E-01 3.5464E+02 24.000 4.4985E+04 3.1240E-01 3.5901E+02 96.000 3.3677E+04 2.3387E-01 3.7655E+02 720.000 2.7602E+03 1.9168E-02 4.2467E+02 Control Room Time (hr) I-131 (Curies) 0.000 7.7472E-09 0.250 1.0157E-01 0.333 8.7369E-02 0.500 6.5644E-02 0.800 3.9350E-02 1.100 2.3707E-02 1.400 1.4426E-02 1.500 1.2267E-02 1.800 7.6694E-03 2.000 5.7184E-03

EC407055 Rev. 0 Page 73 of 89 2.300 3.4178E-03 2.600 2.0427E-03 2.900 1.2209E-03 3.200 7.2970E-04 3.500 4.3612E-04 3.800 2.6066E-04 3.850 2.3923E-04 4.000 1.8495E-04 4.300 1.0735E-04 4.600 6.3734E-05 4.900 3.8035E-05 5.200 2.2725E-05 5.500 1.3581E-05 5.800 8.1170E-06 6.100 4.8513E-06 6.400 2.8995E-06 6.700 1.7330E-06 7.000 1.0358E-06 7.300 6.1905E-07 7.600 3.6999E-07 7.900 2.2114E-07 8.000 1.8627E-07 8.300 1.1133E-07 8.600 6.6540E-08 8.900 3.9769E-08 9.200 2.3769E-08 9.500 1.4206E-08 9.800 8.4908E-09 10.100 5.0748E-09 10.400 3.0331E-09 24.000 2.2304E-19 96.000 9.4620E-10 720.000 2.4336E-11 Cumulative Dose Summary Exclusion Area Bounda Low Population Zone Control Room Time Thyroid TEDE Thyroid TEDE Thyroid TEDE (hr) (rem) (rem) (rem) (rem) (rem) (rem) 0.000 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.250 3.6434E+01 1.7549E+00 1.4562E+00 7.0142E-02 5.2339E+00 2.2341E-01 0.333 3.6435E+01 1.7551E+00 1.4574E+00 7.0268E-02 9.7964E+00 4.1821E-01 0.500 3.6440E+01 1.7556E+00 1.4606E+00 7.0624E-02 1.7183E+01 7.3354E-01 0.800 3.6456E+01 1.7582E+00 1.4708E+00 7.2324E-02 2.6130E+01 1.1156E+00 1.100 3.6483E+01 1.7638E+00 1.4879E+00 7.5900E-02 3.1485E+01 1.3446E+00 1.400 3.6519E+01 1.7718E+00 1.5111E+00 8.1101E-02 3.4713E+01 1.4835E+00 1.500 3.6532E+01 1.7750E+00 1.5201E+00 8.3158E-02 3.5479E+01 1.5168E+00 1.800 3.8059E+01 2.1247E+00 1.7022E+00 1.2489E-01 3.7162E+01 1.5908E+00 2.000 3.9217E+01 2.3904E+00 1.8405E+00 1.5659E-01 3.7923E+01 1.6252E+00 2.300 3.9241E+01 2.3962E+00 1.8556E+00 1.6034E-01 3.8691E+01 1.6604E+00 2.600 3.9258E+01 2.4013E+00 1.8668E+00 1.6364E-01 3.9149E+01 1.6813E+00 2.900 3.9271E+01 2.4059E+00 1.8749E+00 1.6659E-01 3.9422E+01 1.6937E+00 3.200 3.9280E+01 2.4100E+00 1.8809E+00 1.6924E-01 3.9584E+01 1.7011E+00 3.500 3.9287E+01 2.4137E+00 1.8853E+00 1.7164E-01 3.9681E+01 1.7056E+00 3.800 3.9292E+01 2.4171E+00 1.8886E+00 1.7384E-01 3.9738E+01 1.7082E+00 3.850 3.9292E+01 2.4177E+00 1.8890E+00 1.7418E-01 3.9745E+01 1.7085E+00 4.000 3.9294E+01 2.4192E+00 1.8903E+00 1.7520E-01 3.9763E+01 1.7093E+00 4.300 3.9297E+01 2.4222E+00 1.8922E+00 1.7711E-01 3.9787E+01 1.7104E+00 4.600 3.9300E+01 2.4249E+00 1.8937E+00 1.7888E-01 3.9801E+01 1.7111E+00 4.900 3.9301E+01 2.4275E+00 1.8947E+00 1.8052E-01 3.9809E+01 1.7114E+00 5.200 3.9303E+01 2.4298E+00 1.8955E+00 1.8206E-01 3.9814E+01 1.7117E+00 5.500 3.9304E+01 2.4321E+00 1.8962E+00 1.8350E-01 3.9817E+01 1.7118E+00 5.800 3.9304E+01 2.4342E+00 1.8968E+00 1.8485E-01 3.9819E+01 1.7119E+00 6.100 3.9305E+01 2.4361E+00 1.8972E+00 1.8613E-01 3.9820E+01 1.7119E+00 6.400 3.9306E+01 2.4380E+00 1.8976E+00 1.8733E-01 3.9821E+01 1.7120E+00 6.700 3.9306E+01 2.4397E+00 1.8980E+00 1.8846E-01 3.9821E+01 1.7120E+00 7.000 3.9307E+01 2.4414E+00 1.8982E+00 1.8953E-01 3.9821E+01 1.7120E+00 7.300 3.9307E+01 2.4430E+00 1.8985E+00 1.9055E-01 3.9821E+01 1.7120E+00 7.600 3.9307E+01 2.4444E+00 1.8987E+00 1.9151E-01 3.9822E+01 1.7120E+00

EC407055 Rev. 0 Page 74 of 89 7.900 3.9308E+01 2.4459E+00 1.8989E+00 1.9242E-01 3.9822E+01 1.7120E+00 8.000 3.9308E+01 2.4463E+00 1.8989E+00 1.9271E-01 3.9822E+01 1.7120E+00 8.300 3.9308E+01 2.4472E+00 1.8990E+00 1.9329E-01 3.9822E+01 1.7120E+00 8.600 3.9308E+01 2.4481E+00 1.8990E+00 1.9384E-01 3.9822E+01 1.7120E+00 8.900 3.9308E+01 2.4489E+00 1.8991E+00 1.9437E-01 3.9822E+01 1.7120E+00 9.200 3.9308E+01 2.4496E+00 1.8991E+00 1.9487E-01 3.9822E+01 1.7120E+00 9.500 3.9308E+01 2.4504E+00 1.8991E+00 1.9535E-01 3.9822E+01 1.7120E+00 9.800 3.9308E+01 2.4511E+00 1.8991E+00 1.9581E-01 3.9822E+01 1.7120E+00 10.100 3.9308E+01 2.4518E+00 1.8992E+00 1.9624E-01 3.9822E+01 1.7120E+00 10.400 3.9308E+01 2.4524E+00 1.8992E+00 1.9666E-01 3.9822E+01 1.7120E+00 24.000 3.9309E+01 2.4680E+00 1.8998E+00 2.0678E-01 3.9822E+01 1.7120E+00 96.000 3.9311E+01 2.4791E+00 1.9010E+00 2.1397E-01 3.9822E+01 1.7121E+00 720.000 3.9312E+01 2.4845E+00 1.9019E+00 2.1748E-01 3.9822E+01 1.7121E+00 Worst Two-Hour Doses Exclusion Area Boundary Time Whole Body Thyroid TEDE (hr) (rem) (rem) (rem) 0.0 6.8267E-01 3.9217E+01 2.3904E+00

EC407055 Rev. 0 Page 75 of 89 LaSalle 2 Cycle 16 ECCS Leakage Pathway RADTRAD Output File RADTRAD Version 3.03 (Spring 2001) run on 11/01/2016 at 11:38:04 File information Plant file = H:\Dose Analysis\LaSalle\l2c16_ESF.psf Inventory file = H:\Dose Analysis\LaSalle\l2c16_esf.nif Release file = H:\Dose Analysis\bwr_dba.rft Dose Conversion file = C:\Program Files (x86)\radtrad3.03\Defaults\Fgr11&12.inp Radtrad 3.03 4/15/2001 LSCS LOCA ECCS Leak with 25% Makeup Nuclide Inventory File:

H:\Dose Analysis\LaSalle\l2c16_esf.nif Plant Power Level:

3.5590E+03 Compartments:

4 Compartment 1:

Suppression Pool 3

1.2880E+05 0

0 0

0 0

Compartment 2:

Reactor Building 3

1.0000E+00 0

0 0

0 0

Compartment 3:

Environment 2

0.0000E+00 0

0 0

0 0

Compartment 4:

Control Room 1

1.1740E+05

EC407055 Rev. 0 Page 76 of 89 0

0 1

0 0

Pathways:

6 Pathway 1:

Suppression Pool to Reactor Building 1

2 2

Pathway 2:

Reactor Building to Environment 2

3 2

Pathway 3:

Environment to Control Room Filtered Outside Air Intake 3

4 2

Pathway 4:

Environment to Control Room Filtered by Recirc Filter Only 3

4 2

Pathway 5:

Environment to Control Room Outside air Unfiltered Before Supply Fan 3

4 2

Pathway 6:

Control Room to Environment 4

3 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1 1.0000E+00 C:\Program Files (x86)\radtrad3.03\Defaults\Fgr11&12.inp H:\Dose Analysis\bwr_dba.rft 0.0000E+00 1

0.0000E+00 9.7000E-01 3.0000E-02 1.0000E+00 Overlying Pool:

0 0.0000E+00 0

0 0

0 Compartments:

4 Compartment 1:

0 1

0 0

0 0

0 0

0 Compartment 2:

0

EC407055 Rev. 0 Page 77 of 89 1

0 0

0 0

0 0

0 Compartment 3:

0 1

0 0

0 0

0 0

0 Compartment 4:

0 1

0 0

0 0

1 1.4650E+04 4

0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 3.3300E-01 0.0000E+00 0.0000E+00 0.0000E+00 4.0000E+00 0.0000E+00 6.6500E+01 6.6500E+01 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0

0 Pathways:

6 Pathway 1:

0 0

0 0

0 1

2 0.0000E+00 6.6840E-01 0.0000E+00 9.0000E+01 9.0000E+01 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 0

0 Pathway 2:

0 0

0 0

0 1

3 0.0000E+00 1.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 2.5000E-01 1.0000E+00 9.8500E+01 9.8500E+01 9.8500E+01 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 0

0 Pathway 3:

0

EC407055 Rev. 0 Page 78 of 89 0

0 0

0 1

4 0.0000E+00 1.1000E+03 0.0000E+00 0.0000E+00 0.0000E+00 3.3300E-01 9.0000E+02 9.9000E+01 8.8440E+01 8.8440E+01 4.0000E+00 9.0000E+02 9.9000E+01 9.6130E+01 9.6130E+01 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 0

0 Pathway 4:

0 0

0 0

0 1

4 0.0000E+00 2.4000E+03 0.0000E+00 0.0000E+00 0.0000E+00 3.3300E-01 2.4000E+03 0.0000E+00 0.0000E+00 0.0000E+00 4.0000E+00 2.4000E+03 0.0000E+00 6.6500E+01 6.6500E+01 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 0

0 Pathway 5:

0 0

0 0

0 1

2 0.0000E+00 5.0000E+01 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 0

0 Pathway 6:

0 0

0 0

0 1

3 0.0000E+00 3.5500E+03 1.0000E+02 1.0000E+02 1.0000E+02 3.3300E-01 3.3500E+03 1.0000E+02 1.0000E+02 1.0000E+02 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 0

0 Dose Locations:

3 Location 1:

Exclusion Area Boundary

EC407055 Rev. 0 Page 79 of 89 3

1 8

0.0000E+00 6.6300E-04 2.5000E-01 2.7400E-06 1.5000E+00 8.8000E-05 2.0000E+00 1.2900E-06 8.0000E+00 8.8300E-07 2.4000E+01 3.8900E-07 9.6000E+01 1.2000E-07 7.2000E+02 0.0000E+00 1

4 0.0000E+00 3.5000E-04 8.0000E+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.0000E+00 0

Location 2:

Low Population Zone 3

1 8

0.0000E+00 2.6500E-05 2.5000E-01 1.7700E-06 1.5000E+00 1.0500E-05 2.0000E+00 8.3400E-07 8.0000E+00 5.7200E-07 2.4000E+01 2.5300E-07 9.6000E+01 7.8100E-08 7.2000E+02 0.0000E+00 1

4 0.0000E+00 3.5000E-04 8.0000E+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.0000E+00 0

Location 3:

Control Room 4

0 1

2 0.0000E+00 3.5000E-04 7.2000E+02 0.0000E+00 1

4 0.0000E+00 1.0000E+00 2.4000E+01 6.0000E-01 9.6000E+01 4.0000E-01 7.2000E+02 0.0000E+00 Effective Volume Location:

1 8

0.0000E+00 6.8300E-04 2.5000E-01 1.1700E-05 1.5000E+00 1.1700E-05 2.0000E+00 1.0000E-36 8.0000E+00 1.0000E-36 2.4000E+01 7.1700E-08 9.6000E+01 2.2500E-08 7.2000E+02 0.0000E+00 Simulation Parameters:

1 0.0000E+00 0.0000E+00 Output Filename:

H:\Dose Analysis\LaSalle\l2c16_ESF.o0 1

1 1

EC407055 Rev. 0 Page 80 of 89 0

0 End of Scenario File RADTRAD Version 3.03 (Spring 2001) run on 11/01/2016 at 11:38:04 Plant Description Number of Nuclides = 60 Inventory Power = 1.0000E+00 MWth Plant Power Level = 3.5590E+03 MWth Number of compartments = 4 Compartment information Compartment number 1 (Source term fraction = 1.0000E+00

)

Name: Suppression Pool Compartment volume = 1.2880E+05 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 1 Exit Pathway Number 1: Suppression Pool to Reactor Building Compartment number 2 Name: Reactor Building Compartment volume = 1.0000E+00 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 2 Inlet Pathway Number 1: Suppression Pool to Reactor Building Exit Pathway Number 2: Reactor Building to Environment Compartment number 3 Name: Environment Compartment type is Environment Pathways into and out of compartment 3 Inlet Pathway Number 2: Reactor Building to Environment Inlet Pathway Number 6: Control Room to Environment Exit Pathway Number 3: Environment to Control Room Filtered Outside Air I Exit Pathway Number 4: Environment to Control Room Filtered by Recirc Fil Exit Pathway Number 5: Environment to Control Room Outside air Unfiltered Compartment number 4 Name: Control Room Compartment volume = 1.1740E+05 (Cubic feet)

Compartment type is Control Room Removal devices within compartment:

Filter(s)

Pathways into and out of compartment 4 Inlet Pathway Number 3: Environment to Control Room Filtered Outside Air I Inlet Pathway Number 4: Environment to Control Room Filtered by Recirc Fil Inlet Pathway Number 5: Environment to Control Room Outside air Unfiltered Exit Pathway Number 6: Control Room to Environment Total number of pathways = 6

EC407055 Rev. 0 Page 81 of 89 RADTRAD Version 3.03 (Spring 2001) run on 11/01/2016 at 11:38:04 Scenario Description Radioactive Decay is enabled Calculation of Daughters is enabled Release Fractions and Timings GAP EARLY IN-VESSEL LATE RELEASE RELEASE MASS 0.500000 hr 1.5000 hrs 0.0000 hrs (gm)

NOBLES 5.0000E-02 9.5000E-01 0.0000E+00 0.000E+00 IODINE 5.0000E-02 2.5000E-01 0.0000E+00 3.060E+02 CESIUM 5.0000E-02 2.0000E-01 0.0000E+00 0.000E+00 TELLURIUM 0.0000E+00 5.0000E-02 0.0000E+00 0.000E+00 STRONTIUM 0.0000E+00 2.0000E-02 0.0000E+00 0.000E+00 BARIUM 0.0000E+00 2.0000E-02 0.0000E+00 0.000E+00 RUTHENIUM 0.0000E+00 2.5000E-03 0.0000E+00 0.000E+00 CERIUM 0.0000E+00 5.0000E-04 0.0000E+00 0.000E+00 LANTHANUM 0.0000E+00 2.0000E-04 0.0000E+00 0.000E+00 Inventory Power = 3559. MWt Nuclide Group Specific half Whole Body Inhaled Inhaled Name Inventory life DCF Thyroid Effective (Ci/MWt) (s) (Sv-m3/Bq-s) (Sv/Bq) (Sv/Bq)

I-131 2 2.686E+04 6.947E+05 1.820E-14 2.920E-07 8.890E-09 I-132 2 3.885E+04 8.280E+03 1.120E-13 1.740E-09 1.030E-10 I-133 2 5.559E+04 7.488E+04 2.940E-14 4.860E-08 1.580E-09 I-134 2 6.168E+04 3.156E+03 1.300E-13 2.880E-10 3.550E-11 I-135 2 5.191E+04 2.380E+04 8.294E-14 8.460E-09 3.320E-10 Nuclide Daughter Fraction Daughter Fraction Daughter Fraction I-131 Xe-131m 0.01 none 0.00 none 0.00 Iodine fractions Aerosol = 0.0000E+00 Elemental = 9.7000E-01 Organic = 3.0000E-02 COMPARTMENT DATA Compartment number 1: Suppression Pool Compartment number 2: Reactor Building Compartment number 3: Environment Compartment number 4: Control Room Compartment Filter Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 1.4650E+04 0.0000E+00 0.0000E+00 0.0000E+00 3.3300E-01 1.4650E+04 0.0000E+00 0.0000E+00 0.0000E+00 4.0000E+00 1.4650E+04 0.0000E+00 6.6500E+01 6.6500E+01 7.2000E+02 1.4650E+04 0.0000E+00 0.0000E+00 0.0000E+00 PATHWAY DATA Pathway number 1: Suppression Pool to Reactor Building Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic

EC407055 Rev. 0 Page 82 of 89 0.0000E+00 6.6840E-01 0.0000E+00 9.0000E+01 9.0000E+01 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 2: Reactor Building to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 1.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 2.5000E-01 1.0000E+00 9.8500E+01 9.8500E+01 9.8500E+01 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 3: Environment to Control Room Filtered Outside Air I Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 1.1000E+03 0.0000E+00 0.0000E+00 0.0000E+00 3.3300E-01 9.0000E+02 9.9000E+01 8.8440E+01 8.8440E+01 4.0000E+00 9.0000E+02 9.9000E+01 9.6130E+01 9.6130E+01 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 4: Environment to Control Room Filtered by Recirc Fil Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 2.4000E+03 0.0000E+00 0.0000E+00 0.0000E+00 3.3300E-01 2.4000E+03 0.0000E+00 0.0000E+00 0.0000E+00 4.0000E+00 2.4000E+03 0.0000E+00 6.6500E+01 6.6500E+01 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 5: Environment to Control Room Outside air Unfiltered Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 5.0000E+01 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 6: Control Room to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 3.5500E+03 1.0000E+02 1.0000E+02 1.0000E+02 3.3300E-01 3.3500E+03 1.0000E+02 1.0000E+02 1.0000E+02 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 LOCATION DATA Location Exclusion Area Boundary is in compartment 3 Location X/Q Data Time (hr) X/Q (s

• m^-3) 0.0000E+00 6.6300E-04 2.5000E-01 2.7400E-06 1.5000E+00 8.8000E-05 2.0000E+00 1.2900E-06 8.0000E+00 8.8300E-07 2.4000E+01 3.8900E-07 9.6000E+01 1.2000E-07 7.2000E+02 0.0000E+00 Location Breathing Rate Data Time (hr) Breathing Rate (m^3

• sec^-1) 0.0000E+00 3.5000E-04

EC407055 Rev. 0 Page 83 of 89 8.0000E+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.0000E+00 Location Low Population Zone is in compartment 3 Location X/Q Data Time (hr) X/Q (s

• m^-3) 0.0000E+00 2.6500E-05 2.5000E-01 1.7700E-06 1.5000E+00 1.0500E-05 2.0000E+00 8.3400E-07 8.0000E+00 5.7200E-07 2.4000E+01 2.5300E-07 9.6000E+01 7.8100E-08 7.2000E+02 0.0000E+00 Location Breathing Rate Data Time (hr) Breathing Rate (m^3

• sec^-1) 0.0000E+00 3.5000E-04 8.0000E+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.0000E+00 Location Control Room is in compartment 4 Location X/Q Data Time (hr) X/Q (s

• m^-3) 0.0000E+00 6.8300E-04 2.5000E-01 1.1700E-05 1.5000E+00 1.1700E-05 2.0000E+00 1.0000E-36 8.0000E+00 1.0000E-36 2.4000E+01 7.1700E-08 9.6000E+01 2.2500E-08 7.2000E+02 0.0000E+00 Location Breathing Rate Data Time (hr) Breathing Rate (m^3

• sec^-1) 0.0000E+00 3.5000E-04 7.2000E+02 0.0000E+00 Location Occupancy Factor Data Time (hr) Occupancy Factor 0.0000E+00 1.0000E+00 2.4000E+01 6.0000E-01 9.6000E+01 4.0000E-01 7.2000E+02 0.0000E+00 USER SPECIFIED TIME STEP DATA - SUPPLEMENTAL TIME STEPS Time Time step 0.0000E+00 0.0000E+00

EC407055 Rev. 0 Page 84 of 89 RADTRAD Version 3.03 (Spring 2001) run on 11/01/2016 at 11:38:04 Dose Output Exclusion Area Boundary Doses:

Time (h) = 0.2500 Whole Body Thyroid TEDE Delta dose (rem) 1.3263E-02 2.8750E+00 1.0411E-01 Accumulated dose (rem) 1.3263E-02 2.8750E+00 1.0411E-01 Low Population Zone Doses:

Time (h) = 0.2500 Whole Body Thyroid TEDE Delta dose (rem) 5.3011E-04 1.1491E-01 4.1612E-03 Accumulated dose (rem) 5.3011E-04 1.1491E-01 4.1612E-03 Control Room Doses:

Time (h) = 0.2500 Whole Body Thyroid TEDE Delta dose (rem) 8.2485E-05 4.0795E-01 1.2972E-02 Accumulated dose (rem) 8.2485E-05 4.0795E-01 1.2972E-02 Exclusion Area Boundary Doses:

Time (h) = 0.3330 Whole Body Thyroid TEDE Delta dose (rem) 6.5035E-07 1.4826E-04 5.3316E-06 Accumulated dose (rem) 1.3263E-02 2.8751E+00 1.0411E-01 Low Population Zone Doses:

Time (h) = 0.3330 Whole Body Thyroid TEDE Delta dose (rem) 4.2012E-07 9.5771E-05 3.4441E-06 Accumulated dose (rem) 5.3053E-04 1.1501E-01 4.1646E-03 Control Room Doses:

Time (h) = 0.3330 Whole Body Thyroid TEDE Delta dose (rem) 6.9766E-05 3.6081E-01 1.1462E-02 Accumulated dose (rem) 1.5225E-04 7.6876E-01 2.4434E-02 Exclusion Area Boundary Doses:

Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 1.8086E-06 4.3300E-04 1.5471E-05 Accumulated dose (rem) 1.3265E-02 2.8756E+00 1.0413E-01 Low Population Zone Doses:

Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 1.1683E-06 2.7971E-04 9.9940E-06 Accumulated dose (rem) 5.3170E-04 1.1529E-01 4.1746E-03 Control Room Doses:

EC407055 Rev. 0 Page 85 of 89 Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 1.0789E-04 5.8413E-01 1.8540E-02 Accumulated dose (rem) 2.6014E-04 1.3529E+00 4.2974E-02 Exclusion Area Boundary Doses:

Time (h) = 1.5000 Whole Body Thyroid TEDE Delta dose (rem) 2.7851E-05 8.3715E-03 2.9119E-04 Accumulated dose (rem) 1.3293E-02 2.8840E+00 1.0442E-01 Low Population Zone Doses:

Time (h) = 1.5000 Whole Body Thyroid TEDE Delta dose (rem) 1.7992E-05 5.4079E-03 1.8811E-04 Accumulated dose (rem) 5.4969E-04 1.2070E-01 4.3627E-03 Control Room Doses:

Time (h) = 1.5000 Whole Body Thyroid TEDE Delta dose (rem) 2.2959E-04 1.4487E+00 4.5848E-02 Accumulated dose (rem) 4.8973E-04 2.8016E+00 8.8822E-02 Exclusion Area Boundary Doses:

Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 7.1274E-04 2.6033E-01 8.8827E-03 Accumulated dose (rem) 1.4006E-02 3.1443E+00 1.1330E-01 Low Population Zone Doses:

Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 8.5043E-05 3.1063E-02 1.0599E-03 Accumulated dose (rem) 6.3473E-04 1.5176E-01 5.4226E-03 Control Room Doses:

Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.3976E-05 1.9649E-01 6.1911E-03 Accumulated dose (rem) 5.1371E-04 2.9981E+00 9.5013E-02 Exclusion Area Boundary Doses:

Time (h) = 4.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.7145E-05 1.7586E-02 5.8734E-04 Accumulated dose (rem) 1.4043E-02 3.1619E+00 1.1389E-01 Low Population Zone Doses:

Time (h) = 4.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.4015E-05 1.1369E-02 3.7972E-04 Accumulated dose (rem) 6.5875E-04 1.6313E-01 5.8023E-03 Control Room Doses:

Time (h) = 4.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.5317E-05 1.5030E-01 4.7227E-03 Accumulated dose (rem) 5.2902E-04 3.1484E+00 9.9736E-02 Exclusion Area Boundary Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 4.7718E-05 3.3748E-02 1.0986E-03 Accumulated dose (rem) 1.4091E-02 3.1956E+00 1.1499E-01 Low Population Zone Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.0850E-05 2.1819E-02 7.1025E-04 Accumulated dose (rem) 6.8960E-04 1.8495E-01 6.5126E-03

EC407055 Rev. 0 Page 86 of 89 Control Room Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 9.9696E-08 1.3086E-03 4.0950E-05 Accumulated dose (rem) 5.2912E-04 3.1497E+00 9.9777E-02 Exclusion Area Boundary Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 6.3786E-05 4.2658E-02 1.3822E-03 Accumulated dose (rem) 1.4154E-02 3.2383E+00 1.1637E-01 Low Population Zone Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 4.1320E-05 2.7634E-02 8.9541E-04 Accumulated dose (rem) 7.3092E-04 2.1258E-01 7.4080E-03 Control Room Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.4923E-19 2.9583E-15 9.2037E-17 Accumulated dose (rem) 5.2912E-04 3.1497E+00 9.9777E-02 Exclusion Area Boundary Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.7001E-05 7.9692E-02 2.4751E-03 Accumulated dose (rem) 1.4191E-02 3.3180E+00 1.1885E-01 Low Population Zone Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.4065E-05 5.1830E-02 1.6097E-03 Accumulated dose (rem) 7.5498E-04 2.6441E-01 9.0177E-03 Control Room Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.2064E-08 9.0261E-04 2.7625E-05 Accumulated dose (rem) 5.2914E-04 3.1506E+00 9.9804E-02 Exclusion Area Boundary Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.7863E-05 6.4481E-02 1.9813E-03 Accumulated dose (rem) 1.4209E-02 3.3825E+00 1.2083E-01 Low Population Zone Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.1626E-05 4.1966E-02 1.2895E-03 Accumulated dose (rem) 7.6661E-04 3.0638E-01 1.0307E-02 Control Room Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 4.0312E-09 5.0202E-04 1.5291E-05 Accumulated dose (rem) 5.2914E-04 3.1511E+00 9.9820E-02 838 I-131 Summary Suppression Pool Reactor Building Environment Time (hr) I-131 (Curies) I-131 (Curies) I-131 (Curies) 0.000 5.3104E+03 4.5424E-05 5.0611E-07 0.250 2.3875E+06 1.1564E+00 8.1372E+00 0.333 3.1791E+06 1.5672E+00 8.2389E+00

EC407055 Rev. 0 Page 87 of 89 0.500 4.7704E+06 2.3931E+00 8.5365E+00 0.800 9.5303E+06 4.8083E+00 9.5021E+00 1.100 1.4279E+07 7.2730E+00 1.1133E+01 1.400 1.9018E+07 9.7322E+00 1.3428E+01 1.500 2.0595E+07 1.0551E+01 1.4341E+01 1.800 2.5319E+07 1.3002E+01 1.7520E+01 2.000 2.8463E+07 1.4634E+01 2.0007E+01 2.300 2.8430E+07 1.4753E+01 2.3990E+01 2.600 2.8396E+07 1.4736E+01 2.7970E+01 2.900 2.8363E+07 1.4719E+01 3.1946E+01 3.200 2.8330E+07 1.4702E+01 3.5917E+01 3.500 2.8297E+07 1.4684E+01 3.9884E+01 3.800 2.8264E+07 1.4667E+01 4.3845E+01 4.000 2.8242E+07 1.4656E+01 4.6484E+01 4.300 2.8208E+07 1.4639E+01 5.0438E+01 4.600 2.8175E+07 1.4622E+01 5.4387E+01 4.900 2.8142E+07 1.4604E+01 5.8332E+01 5.200 2.8110E+07 1.4587E+01 6.2272E+01 5.500 2.8077E+07 1.4570E+01 6.6208E+01 5.800 2.8044E+07 1.4553E+01 7.0139E+01 6.100 2.8011E+07 1.4536E+01 7.4065E+01 6.400 2.7978E+07 1.4519E+01 7.7987E+01 6.700 2.7945E+07 1.4502E+01 8.1904E+01 7.000 2.7913E+07 1.4485E+01 8.5817E+01 7.300 2.7880E+07 1.4468E+01 8.9725E+01 7.600 2.7847E+07 1.4451E+01 9.3628E+01 7.900 2.7815E+07 1.4434E+01 9.7527E+01 8.000 2.7804E+07 1.4429E+01 9.8826E+01 8.300 2.7771E+07 1.4412E+01 1.0272E+02 8.600 2.7739E+07 1.4395E+01 1.0661E+02 8.900 2.7706E+07 1.4378E+01 1.1049E+02 9.200 2.7674E+07 1.4361E+01 1.1437E+02 9.500 2.7642E+07 1.4345E+01 1.1824E+02 9.800 2.7609E+07 1.4328E+01 1.2211E+02 10.100 2.7577E+07 1.4311E+01 1.2598E+02 10.400 2.7545E+07 1.4294E+01 1.2984E+02 24.000 2.6121E+07 1.3555E+01 2.9998E+02 96.000 1.9721E+07 1.0234E+01 1.0643E+03 720.000 1.7261E+06 8.9574E-01 3.2135E+03 Control Room Time (hr) I-131 (Curies) 0.000 5.7900E-10 0.250 8.1146E-03 0.333 6.9800E-03 0.500 5.2448E-03 0.800 3.1456E-03 1.100 1.8984E-03 1.400 1.1602E-03 1.500 9.8915E-04 1.800 6.2656E-04 2.000 4.7436E-04 2.300 2.8351E-04 2.600 1.6945E-04 2.900 1.0128E-04 3.200 6.0530E-05 3.500 3.6177E-05 3.800 2.1622E-05 4.000 1.5342E-05 4.300 2.0589E-06 4.600 2.7631E-07 4.900 3.7082E-08 5.200 4.9765E-09 5.500 6.6785E-10 5.800 8.9627E-11 6.100 1.2028E-11 6.400 1.6142E-12 6.700 2.1663E-13 7.000 2.9072E-14 7.300 3.9016E-15 7.600 5.2360E-16

EC407055 Rev. 0 Page 88 of 89 7.900 7.0268E-17 8.000 3.5976E-17 8.300 4.8280E-18 8.600 6.4793E-19 8.900 8.6954E-20 9.200 1.1669E-20 9.500 1.5661E-21 9.800 2.1017E-22 10.100 2.8205E-23 10.400 3.7852E-24 24.000 7.6486E-37 96.000 4.1404E-08 720.000 1.1372E-09 Cumulative Dose Summary Exclusion Area Bounda Low Population Zone Control Room Time Thyroid TEDE Thyroid TEDE Thyroid TEDE (hr) (rem) (rem) (rem) (rem) (rem) (rem) 0.000 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.250 2.8750E+00 1.0411E-01 1.1491E-01 4.1612E-03 4.0795E-01 1.2972E-02 0.333 2.8751E+00 1.0411E-01 1.1501E-01 4.1646E-03 7.6876E-01 2.4434E-02 0.500 2.8756E+00 1.0413E-01 1.1529E-01 4.1746E-03 1.3529E+00 4.2974E-02 0.800 2.8770E+00 1.0418E-01 1.1619E-01 4.2066E-03 2.0607E+00 6.5404E-02 1.100 2.8793E+00 1.0426E-01 1.1772E-01 4.2598E-03 2.4845E+00 7.8811E-02 1.400 2.8826E+00 1.0438E-01 1.1985E-01 4.3336E-03 2.7407E+00 8.6898E-02 1.500 2.8840E+00 1.0442E-01 1.2070E-01 4.3627E-03 2.8016E+00 8.8822E-02 1.800 3.0302E+00 1.0942E-01 1.3815E-01 4.9597E-03 2.9364E+00 9.3069E-02 2.000 3.1443E+00 1.1330E-01 1.5176E-01 5.4226E-03 2.9981E+00 9.5013E-02 2.300 3.1470E+00 1.1339E-01 1.5349E-01 5.4810E-03 3.0609E+00 9.6987E-02 2.600 3.1496E+00 1.1348E-01 1.5520E-01 5.5389E-03 3.0983E+00 9.8162E-02 2.900 3.1523E+00 1.1357E-01 1.5692E-01 5.5962E-03 3.1205E+00 9.8861E-02 3.200 3.1549E+00 1.1366E-01 1.5862E-01 5.6530E-03 3.1338E+00 9.9277E-02 3.500 3.1575E+00 1.1375E-01 1.6032E-01 5.7094E-03 3.1417E+00 9.9525E-02 3.800 3.1601E+00 1.1383E-01 1.6201E-01 5.7653E-03 3.1464E+00 9.9672E-02 4.000 3.1619E+00 1.1389E-01 1.6313E-01 5.8023E-03 3.1484E+00 9.9736E-02 4.300 3.1645E+00 1.1398E-01 1.6481E-01 5.8576E-03 3.1496E+00 9.9771E-02 4.600 3.1670E+00 1.1406E-01 1.6648E-01 5.9125E-03 3.1497E+00 9.9776E-02 4.900 3.1696E+00 1.1415E-01 1.6814E-01 5.9670E-03 3.1497E+00 9.9777E-02 5.200 3.1722E+00 1.1423E-01 1.6980E-01 6.0212E-03 3.1497E+00 9.9777E-02 5.500 3.1747E+00 1.1431E-01 1.7145E-01 6.0751E-03 3.1497E+00 9.9777E-02 5.800 3.1773E+00 1.1440E-01 1.7309E-01 6.1286E-03 3.1497E+00 9.9777E-02 6.100 3.1798E+00 1.1448E-01 1.7473E-01 6.1819E-03 3.1497E+00 9.9777E-02 6.400 3.1823E+00 1.1456E-01 1.7636E-01 6.2348E-03 3.1497E+00 9.9777E-02 6.700 3.1848E+00 1.1464E-01 1.7798E-01 6.2875E-03 3.1497E+00 9.9777E-02 7.000 3.1873E+00 1.1472E-01 1.7960E-01 6.3399E-03 3.1497E+00 9.9777E-02 7.300 3.1898E+00 1.1480E-01 1.8121E-01 6.3920E-03 3.1497E+00 9.9777E-02 7.600 3.1923E+00 1.1488E-01 1.8282E-01 6.4438E-03 3.1497E+00 9.9777E-02 7.900 3.1948E+00 1.1496E-01 1.8442E-01 6.4954E-03 3.1497E+00 9.9777E-02 8.000 3.1956E+00 1.1499E-01 1.8495E-01 6.5126E-03 3.1497E+00 9.9777E-02 8.300 3.1965E+00 1.1502E-01 1.8551E-01 6.5313E-03 3.1497E+00 9.9777E-02 8.600 3.1974E+00 1.1505E-01 1.8607E-01 6.5499E-03 3.1497E+00 9.9777E-02 8.900 3.1982E+00 1.1508E-01 1.8663E-01 6.5684E-03 3.1497E+00 9.9777E-02 9.200 3.1991E+00 1.1510E-01 1.8718E-01 6.5868E-03 3.1497E+00 9.9777E-02 9.500 3.1999E+00 1.1513E-01 1.8773E-01 6.6051E-03 3.1497E+00 9.9777E-02 9.800 3.2008E+00 1.1516E-01 1.8829E-01 6.6233E-03 3.1497E+00 9.9777E-02 10.100 3.2016E+00 1.1519E-01 1.8884E-01 6.6414E-03 3.1497E+00 9.9777E-02 10.400 3.2025E+00 1.1522E-01 1.8938E-01 6.6594E-03 3.1497E+00 9.9777E-02 24.000 3.2383E+00 1.1637E-01 2.1258E-01 7.4080E-03 3.1497E+00 9.9777E-02 96.000 3.3180E+00 1.1885E-01 2.6441E-01 9.0177E-03 3.1506E+00 9.9804E-02 720.000 3.3825E+00 1.2083E-01 3.0638E-01 1.0307E-02 3.1511E+00 9.9820E-02 Worst Two-Hour Doses Exclusion Area Boundary Time Whole Body Thyroid TEDE (hr) (rem) (rem) (rem)

EC407055 Rev. 0 Page 89 of 89 0.0 1.4006E-02 3.1443E+00 1.1330E-01