RS-05-118, Additional Information Supporting the Request for Licence Amendment Related to Application of Alternative Source Term

Additional Information Supporting the Request for Licence Amendment Related to Application of Alternative Source Term

ML052550370
Person / Time
Site:	Dresden, Quad Cities   (DPR-019, DPR-025, DPR-029, DPR-030)
Issue date:	09/03/2005
From:	Simpson P Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RS-05-118
Download: ML052550370 (70)

Text

Exelon.

Exelon Generation www.exeloncorp.com NucleaT 4300 Winfield Road Warrenville, IL 60555 RS-05-118 September 3, 2005 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265

Subject:

Additional Information Supporting the Request for License Amendment Related to Application of Alternative Source Term

References:

1. Letter from P. R. Simpson (Exelon Generation Company, LLC) to U. S. NRC, "Request for License Amendments Related to Application of Alternative Source Term," dated October 10, 2002

2. Letter from P. R. Simpson (Exelon Generation Company, LLC) to U. S. NRC, "Additional Information Supporting the Request for License Amendment Related to Application of Alternative Source Term," dated August 22,2005 In Reference 1, Exelon Generation Company, LLC (EGC) requested an amendment to the facility operating licenses for Dresden Nuclear Power Station (DNPS), Units 2 and 3, and Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2. The proposed changes support application of an altemative source term (AST) methodology.

In Reference 2, EGC submitted additional information to support the NRC's review. Details regarding this submittal were discussed with the NRC during a meeting on August 29-30, 2005. During the meeting, the NRC requested EGC to submit information related to some of the issues discussed. The Attachments to this letter provide the requested information.

The RADTRAD output files supporting the Attachment 2 analyses are provided on the enclosed CD-ROM.

September 3, 2005 U. S. Nuclear Regulatory Commission Page 2 EGC has reviewed the information supporting a finding of no significant hazards consideration that was previously provided to the NRC in Attachment C of Reference 1.

The supplemental information provided in this submittal does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration. provides a list of regulatory commitments being made in this submittal. If you have any questions concerning this letter, please contact Mr. Kenneth M. Nicely at (630) 657-2803.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 3rd day of September 2005.

Respectfully, Patrick R. Simpson Manager - Licensing Attachments:

1. Additional Information Supporting Request for Application of Alternative Source Term

2. Control Room Flow and Volume Sensitivity Analysis

3. Technical Evaluation to Support AST Doses With Differing Times to Reach an Elemental DF of 200

4. Summary of Regulatory Commitments

Enclosure:

CD-ROM Containing RADTRAD Output Files cc (without Enclosure):

Regional Administrator - NRC Region IlIl NRC Senior Resident Inspector - Dresden Nuclear Power. Station NRC Senior Resident Inspector - Quad Cities Nuclear Power Station Illinois Emergency Management Agency - Division of Nuclear Safety

ATTACHMENT I Additional Information Supporting Request for Application of Alternative Source Term

Background

In Reference 1, Exelon Generation Company, LLC (EGC) requested an amendment to the facility operating licenses for Dresden Nuclear Power Station (DNPS), Units 2 and 3, and Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2. The proposed changes support application of an alternative source term (AST) methodology. In Reference 2, EGC submitted additional information to support the NRCs review. Details regarding this submittal were discussed with the NRC during a meeting on August 29-30, 2005. During the meeting, the NRC requested EGC to submit information related to some of the items discussed. These items are identified below, along with EGC's response.

NRC Item 1 The NRC noted that in Table 4 of Attachment 19 (i.e., Reference 2) it was indicated that the condenser volume for QCNPS was 55,000 ft3 and that the number has remained unchanged from the present licensing basis and the October 10, 2002, submittal (i.e., Reference 1). This is inconsistent with the value of 92,000 ft3 shown in Attachment 3, Section 4.2, of the Reference 2 submittal, and also Attachment A, Table 8, of the Reference 1 submittal.

Response

The QCNPS condenser volume of 55,000 ft3 listed in Attachment 19, Table 4, of Reference 2 is incorrect. Attachment 19 was included in the Reference 2 submittal solely to facilitate NRC review of the revised AST analyses. The correct condenser volume of 92,000 ft was appropriately used in the control rod drop accident (CRDA) analysis for QCNPS, which was provided as Attachment 3 of the Reference 2 submittal. Therefore, since the correct value was used in the CRDA analysis, there is no technical impact of the error in Table 4 of Attachment 19.

NRC Item 2 In a public meeting held on August 17, 2005, EGC provided parametric studies for the loss-of-coolant accident (LOCA) at DNPS and QCNPS which provided the control room operator dose as a function of control room inleakage rate with the rates varying from 2000 - 60,000 cfm. It was EGC's intent to demonstrate that testing of the control room envelope was unnecessary and that the NRC's concern regarding verification that the inleakage assumptions during the first 40 minutes of a LOCA (i.e., when the normal control room ventilation system is operating) could be addressed by the parametric study. EGC submitted the parametric studies as Attachments 10 and 11 of the Reference 2 submittal for DNPS and QCNPS, respectively. Since this information will be used, in part, as the basis for the LOCA analyses, the design basis unfiltered inleakage value for the LOCA during the first 40 minutes of the accident should be 60,000 cfm.

Response

EGC agrees that the design basis unfiltered inleakage value for the first 40 minutes following a LOCA should reflect 60,000 cfm. EGC will revise the design basis LOCA calculations for DNPS and QCNPS to incorporate the parametric studies supporting an inleakage of 60,000 cfm during the first 40 minutes following a LOCA.

Page 1

ATTACHMENT I Additional Information Supporting Request for Application of Alternative Source Term NRC Item 3 For the fuel handling accident (FHA) and the control rod drop accident (CRDA), EGC modeled the consequence to the control room operators assuming that the flow to the control room envelope consisted of one control room volume change per minute. In addition, EGC also modeled the control room operator doses using a volume that was less than the actual free air volume. Such modeling assumptions result in an underestimation of the control room operators' dose because it fails to recognize that there is a purging effect associated with control room flow rates. There is a point where an increase in flow rate to the control room envelope results in a purging effect on control room concentrations. Decreasing the control room envelope volume only accentuates the purging effect. The maximum dose to the control room operators will occur at a flow rate which is less, and usually significantly less, than the one volume change per minute. In summary, EGC's modeling technique has resulted in an underestimation of the control room operators' doses because their model results in a more rapid purging of the activity in the control room envelope than a model based upon actualfree air volume and lower control room envelope makeup flow rates.

Response

EGC's understanding of this phenomena is that higher flow rates result in a quicker approach to equilibrium with outside air conditions. This in turn typically results in higher control room operator doses due to less opportunity for decay before entry into the control room. The more rapid purging is more than offset by the higher than expected radioactivity intake.

During the August 29-30, 2005, public meeting, EGC demonstrated that the NRC's preliminary conclusions had resulted from using less than the number of time steps necessary to model the relatively rapid changes in conditions associated with RADTRAD CRDA modeling.

No credit is taken for control room emergency filtration for the CRDA and FHA. In a manner similar to LOCA, a very high flow rate of outside air through the control room (i.e., one air change per minute) is assumed in order to demonstrate that testing of the control room envelope was unnecessary for the CRDA and FHA. EGC has performed additional parametric analyses to confirm the impact of varying the flow rates through the control room and the volume of the control room. These parametric analyses are provided as a QCNPS demonstration in Attachment 2, and its conclusions are applicable to DNPS. The results of these analyses demonstrate that the modeling used in the calculations reflect conservative assumptions for control room flow.

Regarding control room volumes, DNPS and QCNPS both have an identified control room proper value and a control room envelope value. The control room proper is shielded from the balance of the control room envelope and is the value applicable when determining the immersion cloud dose using a geometry factor. The control room envelope is the volume normally used along with expected intake/inleakage parameters to predict inhalation doses. Tests in Attachment 2 were performed where the control room envelope volume was used with a one air change per minute flow rate. The resulting thyroid doses (i.e., indicative of inhalation dose effects exclusively) were identical for both volumes. Therefore, the cloud shine effective dose equivalent component is isolated and effectively calculated using the control room proper volume.

Page 2

ATTACHMENT I

--Additional Information Supporting Request for-Application of-Alternative Source Term NRC Item 4 In the August 29-30, 2005, meeting, discrepancies were noted by the NRC between their preliminary confirmatory analyses for the CRDA and the analyses submitted by EGC. Review of the NRC analyses resolved differences with respect to fuel melt related dose effects. However, the EGC results remained above the NRC values for the breeched fuel releases. This was determined to have resulted from EGC not crediting main condenser DFs as allowed by Regulatory Guide 1.183, Appendix C, Paragraph 3.4. EGC agreed to submit clarifications on the effect that this crddit would have on dose numbers.

Response

The parametric analyses included in Attachment 2 evaluated the impact of crediting the DF that is applicable for the main condenser 1 % per day leakage condition. The effect of this credit on the dose numbers is shown on page 3 of the Attachment 2 evaluation. As shown, crediting this DF reduces CRDA doses. Therefore, the existing values provided in the Reference 2 submittal, which did not credit this DF, are conservative. The CRDA analyses for DNPS and QCNPS will be revised to reflect the condenser DF that is applicable for the main condenser 1 % per day leakage condition.

NRC Item 5 In the calculation for the fuel handling accident (FHA), EGC has overestimated the effective overall elemental iodine decontamination factor (DF) for 19 feet of water. Starting with an overall DF of 200 for 23 feet of water, the maximum DF for elemental iodine in 23 feet of water must be 285 and not 500. Therefore, the DF for 19 feet should be based upon a value of 285 and not a value of 500. This results in an increase in the amount of elemental iodine released.

Response

During the meeting with the NRC on August 29-30, 2005, the NRC clarified their interpretation of the guidance in Regulatory Guide 1.183 associated with the calculation of the DF. Using the NRC's interpretation, described above, the effective overall DF for elemental iodine was calculated to be 92. The FHA analyses for DNPS and QCNPS will be revised to reflect the overall DF of 92.

Additionally, the existing design basis for fuel damage will be revised. The current analysis is based on the failure of 111 fuel pins based on a 7x7 fuel array of 49 pins. There are no such assemblies in operation in either DNPS or QCNPS. The majority of the operating fuel is GE-14 1 Ox1 0 array fuel with an equivalent pins per assembly of 87.33. With this change, 172 fuel rods are assumed damaged in a 34 foot drop over the core in the reactor vessel per NEDC-32868P, as referenced in Section 15.7 of the DNPS and QCNPS UFSARs. This is considered the bounding condition with respect to damage for fuel types in use as discussed in the DNPS and QCNPS UFSARs.

The resulting dose impact of using an overall effective DF of 92 versus 135, with this currently bounding fuel type is shown below. The parametric analyses provided in Attachment 2 evaluated the impact of using an overall effective DF of 92. As stated above, the FHA analyses for DNPS and QCNPS will be revised to reflect this change.

Page 3

ATTACHMENT I

-- Additional Information Supporting-Request for-Application of-Alternative Source Term EAB Dose LPZ Dose CR Dose (rem TEDE)

(rem TEDE)

(rem TEDE)

DNPS 1.162 0.122 2.533 QCNPS.

6.295 0.481 2.288 Limit 6.3 6.3 5.0 NRC Item 6 The revised LOCA analyses assume that natural deposition of elemental iodine occurs until the time when a DF of 200 is achieved. EGC determined the time of the maximum concentration in the drywell, and from that point in time, calculated the point at which that concentration would be reduced by a factor of 200. What should have been done is that EGC should have determined the total amount of iodine that would be available for release and then determine when the total in the drywell would be that amount reduced by a factor of 200. This would result in a shorter time period for natural deposition.

Response

EGC has re-calculated the time to reach a DF of 200 using the NRC's guidance in Regulatory Guide 1.183, Appendix A, Section 3.3. The results of the calculation determined that a DF of 200 would be reached in 3.05 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. Since the DF of 200 is used to determine the cutoff time for elemental iodine surface deposition, the use of total drywell iodine activity in lieu of elemental iodine activity is inappropriate and inconsistent with the regulatory guidance, and it underestimates the cutoff time. A sensitivity study has also been performed using the new elemental iodine cutoff time of 3.05 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> to determine the control room dose impact. The sensitivity study (i.e., ) determined that the impact to control room dose would be insignificant, and the overall dose remains below the 5 rem limit. However, EGC will revise the design basis LOCA calculations for DNPS and QCNPS to incorporate the new cutoff time to reach a DF of 200.

References

1. Letter from P. R. Simpson (Exelon Generation Company, LLC) to U. S. NRC, "Request-for License Amendments Related to Application of Alternative Source Term," dated October 10, 2002

2. Letter from P. R. Simpson (Exelon Generation Company, LLC) to U. S. NRC, "Additional Information Supporting the Request for License Amendment Related to Application of Alternative Source Term," dated August 22, 2005 Page 4

ATTACHMENT 2 Control Room Flow and Volume Sensitivity Analysis

QCNPS CR Flow and CR Volume Sensitivity Analysis, Revision 0 EC# 356379, 09/03/2005 Page I of 8 Technical Evaluation Passport EC # 356379, Revision 0 Technical Evaluation to: (1) To Confirm That Selection of a 1 Air Change per Minute Based Flow Rate for the Control Room Represents a Bounding Assumption for Events Where Control Room Emergency Ventilation is Not Credited; and (2) Confirm That the Control Room Proper Volume is Suitable for Use in These Accident Analyses REASON FOR EVALUATION / SCOPE:

The design basis Alternative Source Term (AST) evaluations for QCNPS and DNPS, for the Control Rod Drop Accident (CRDA) and the Fuel Handling Accident (FHA), have been performed without credit for the Control Room Emergency Ventilation Systems and without tracer gas testing of alternative control room ventilation configurations. Therefore, a bounding assumption of I air change per minute was selected to bound any actual credible Control Room ventilation condition, with this air assumed to be unfiltered.

The sensitivity analyses herein are for the purpose of confirming that the assumption of I air change per minute is indeed bounding. It also confirms that the practice of considering the control room proper volume when calculating these doses remains appropriate for AST accident analyses.

Since the only significant differences between the two stations are Control Room X/Qs, this demonstration also applied to DNPS.

DETAILED EVALUATION. CONCLUSIONS AND FINDINGS:

This technical evaluation contains sensitivity analyses for the QCNPS. The first involves RADTRAD analyses of CRDA and FHA with varying control room flows from approximately' the expected condition up to 1 air change per minute. The attached spreadsheet summarizes the results and provide charts that illustrate the conservatism of the assumption.

The behavior exhibited confirm EGC's understanding of this phenomenon in that higher flow rates result in a quicker approach to equilibrium with outside air conditions, and that this in turn results in slightly higher control room operator doses.

Regarding control room volumes, DNPS and QCNPS both have an identified control room proper value and a control room HVAC envelope value. The control room proper is shielded from the balance of the control room envelope and is the value applicable when determining the immersion cloud dose using a geometry factor. The inhalation dependent thyroid dose for the two volumes with a 1 air change per minute flow rate were compared and found to be identical for CRDA and virtually so for FHA. Therefore, the cloud shine Effective Dose Equivalent (EDE) component is isolated and effectively calculated using the control room proper volume.

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QCNPS CR Flow and CR Volume Sensitivity Analysis, Revision 0 EC# 356379, 09/03/2005 Page 3 of 8 QDCNPS Control Rod Drop Accident Sensitivity Analysis to Assumed Intake (or Inleakage) Rate, from normal Intake flow up to I air change per minute 58,300 ft 3Control Room' Proper Volume Control Room Intake (cfm) 2000 4000 15000 30000 45000 58300 Main Condenser CR Dose (rem TEDE) 2.2868E+00 2.2811 E-01 2.3079E+00 2.3043E-01 2.3245E+00 2.3228E-01 2.3286E+00 2.3272E-01 2.3304E+00 2.3292E-01 2.3314E+00 2.3302E-01 No Condenser Removal With Condenser Credit Removal Credit Gland Seal Condenser CR Dose (rem TEDE) 7.8342E-01 7.8761 E-01 7.9117E-01 7.9182E-01 7.9194E-01 7.9201 E-01 TOTAL CRDA CR Dose (rem TEDE) 1.0115E+00 1.0180E+00 1.0235E+00 1.0245E+00 1.0249E+00 1.0250E+00 With I air change per minute 58,300 CR Volume Proper Volume (ft3) 184,000 CR HVAC Envelope Volume (f 3) 58,300 CR Volume Proper Volume (f13) 184,000 CR HVAC Envelope Volume (ft3)

Whole Body

• (rem EDE) 6.5808E-03 9.7050E-03 9.9806E-03 1.4719E-02 Thyroid (rem thyroid) 7.2372E+00 7.2372E+00 2.3585E+01 2.3585E+01

• Total Dose (rem TEDE) 2.3302E-01 2.3614E-01 7.9201 E-01 7.9675E-01 Main Condenser Main Condenser Gland Seal Gland Seal QDCNPS Fuel Handlinq Accident Sensitivity Analysis to Assumed Intake (or Inleaka-ie) Rate, from normal intake flow up to I air chance per minute 58,300 ft3Control Room Proper Volume Control Room Intake (cfm) 2000 4000 15000 30000 45000 58300 With I air change per minute 58,300 CR Volume Proper Volume (ft3) 184,000 CR HVAC Envelope Volume (fW 3)

CR Dose (rem TEDE) 2.2548E+00 2.2570E+00 2.2701 E+00 2.2838E+00 2.2876E+00 2.2883E+00 Whole Body (rem EDE) 1.5324E-02 2.2599E-02 19 feet of water coverage and 285.29 DF for Elemental Iodine and 92 DF overall for all damaged fuel rods (in dropped assembly and in racks).

Thyroid (rem thyroid) 7.3855E+01 7.3855E+01.

Source terms are based on a bounding GE-14 IOx10 assembly with 87.33 effective pins per assembly. 172 rods are damaged with a 1.7 radial peaking factor.

Total Dose (rem TEDE) 2.2883E+00 2.2956E+00

QCNPS CR Flow and CR Volume Sensitivity Analysis, Revision 0 EC# 356379, 09/03/2005 Page 4 of 8 Control Rod Drop Accident 1.200 1.000

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• O0.400 0.200 0.000 0

10,000 20,000 30,000 40,000 50,000 60,000 Control Room Intake (cfm)

QCNPS CR Flow and CR Volume Sensitivity Analysis, Revision 0 EC# 356379, 0910312005 Page 5 of 8 Control Rod Drop Accident (exaggerated, non-0 Y-axis) 1.026 -

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0 1.012 1.010 -

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QCNPS CR Flow and CR Volume Sensitivity Analysis, Revision 0 EC# 356379, 09/0312005 Page 6 of 8 Fuel Handling Accident 2.500 -

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10,000 20,000 30,000 40,000 50,000 60,000

-- Control Room Intake (cfm)

QCNPS CR Flow and CR Volume Sensitivity Analysis, Revision 0 EC# 356379, 09/03/2005 Page 7 of 8 Fuel Handling Accident (exaggerated, non-O Y-axis) 2.290 2.288 -

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Volume Sensitivity Analysis, Revision 0 EC# 356379, 09/03/2005 Page 8 of 8

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1 DRESDEN and QUAD CITIES FHA Parameters Related to Fuel Damage and Pool DF 2

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172 Damaged Rods, based on GE14 1Ox10 fuel DF by Iodine Phase 500.00 1

169.66 1

4 87.33 Effective Rods in Assembly Iodine Phase Fractions 0.9985 0.0015 0.9985 0.0015 _

5 724 Assemblies In Core Overall DFs 285.96 135.41 l

6 0.00272 Fraction of Core Damaged by FHA After DF Application 0.001997 0.0015 0.003497 0.005885 0.0015 0.007385 7

1.7 Peaking Factor After DF Application 57.1%

42.9% __79.7%

20.3%1 8

13.95 Core Power of Damaged Fuel (MWt) 9 92.0 Spent Fuel Pool DF Inorganic organic 23 feet water depth inorganic organic 19 feet wat r depth 10 SGTS and OR Emergency Filters not credited DF by Iodine Phase 285.29 1

106.73 1

11 iodine Phase Fractions 0.9985 0.0015 0.9985 0.0015 l

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ATTACHMENT 3 Technical Evaluation to Support AST Doses With Differing Time to Reach an Elemental DF of 200

Technical Evaluation, Revision 0 EC 356383 (Dresden)

EC 356379 (Quad Cities) 09/03/05 Page 1 of 6 Technical Evaluation EC # 356383, Revision 0 (Dresden)

EC # 356379, Revision 0 (Quad Cities)

Technical Evaluation to Support AST Doses With Differing Times To Reach an Elemental DF of 200 at the Dresden Nuclear Power Station (DNPS) and Quad Cities Nuclear Power Station (QCNPS)

REASON FOR EVALUATION / SCOPE:

The purpose of this evaluation is to document a sensitivity study regarding the effects of different times to reach an elemental iodine decontamination factor (DF) of 200 in the DNPS and QCNPS drywells.

DETAILED EVALUATION:

The LOCA analyses for AST assume that natural deposition of elemental iodine in the drywell, when modeled as spray, occurs until the time when a DF of 200 is achieved. The Exelon Revision 0 calculations determined the time of the maximum concentration in the drywell, and from that point, added the time at which that concentration would be reduced by a factor of 200.

According to the NRC, the calculation should have determined the total amount of iodine that would be available for release (i.e., that amount of iodine in the drywell per SRP 6.5.2 page 11) and then determine when the total in the drywell would be that amount reduced by a factor of 200. This results in a shorter time period from the start of the LOCA event for natural deposition instead of adding the time to that when maximum iodine activity is reached.

Therefore, Exelon has recalculated the time to reach a DF of 200 using the iodine activity in the core times the 0.30 fraction released to the containment (RG 1.183 Table 1) as the initial activity. This activity is then divided by 200. The RADTRAD case results were then reviewed to observe the time at which this lower activity was reached. This time was determined to be 3.05 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

Another method of modeling natural deposition could have been used in which the calculated removal rate (not modeled as spray) could have continued throughout the accident.

This evaluation will compare the effects of(1) the originally calculated cutoff time, (2) the revised cutoff time per the NRC's method, and (3) use of the constant removal rate throughout the accident (an elemental iodine removal rate of 3.28 hf 1 was originally calculated and is used throughout this evaluation). Refer to Tables 1 and 2 for Dresden and Quad Cities, respectively.

Technical Evaluation, Revision 0 EC 356383 (Dresden)

EC 356379 (Quad Cities) 09/03/05 Page 2 of 6 Changes have been subsequently made to the Original Exelon Rev. 0 calculations to incorporate the assumption of 60,000 cfm unfiltered CR intake for the first 40 minutes to account for manual operator action to initiate the emergency mode of operation. As a result of a public meeting with the NRC and Exelon on August 29 and 30, 2005, a new calculation revision was initiated to change the cutoff time to reach a DF of 200 for elemental iodine removal by natural deposition in the drywell. Results of this change are summarized in the fourth column of Tables 1 and 2. The fifth column of Tables 1 and 2 indicate the results if the natural deposition removal rate (3.28 hrf ) were not stopped. The net results of this evaluation are the same number within round off as calculated using the DF cutoff time of 3.615 hours0.00712 days <br />0.171 hours <br />0.00102 weeks <br />2.340075e-4 months <br />.

These results in calculated doses are summarized in Table 1 for Dresden and Table 2 for Quad Cities.

DresdenControlRoom Post-LOCA Dose %C ;

(Rem TEDE) 4,200 cm R

.'60,000 cfm'CR

'60,000 cfii CR '

>60,000 cfm CR'; '

Intake for First 40 Intake for First 40 Intake for First 40 Intake for First 40 Minutes Minutes Minutes ours AciiyRelease Miute DF'Cutoff TimeDFiVNCutoff Ti'me Cutoff Time =~Cutoff Time (3.28 3.1 Hus 3.615 Hours 3.05 Hours he~ for 720 Hours)

Containment Leakage 1.59E-02 1.64E-02

• 1.65E-02 1.60E-02 ESF Leakage 3.24E-02 3.34E-02

• 3.25E-02 3.25E-02 MSIV Leakage 4.17E+00 4.30E+00 4.33E+00 4.30E+00 Containment Shine 2.20E-01 2.20E-01 2.20E-01 2.20E-01 External Cloud 2.73E-01 2.73E-01 **

2.73E-01 2.73E-01 CR Filter Shine Negligible Negligible **

Negligible Negligible Total 4.71E+00 4.84E+00 4.87E+00 4.84E+00 This Technical Data Source DRE05-0048 Rev. 0 Ecanial DRE05-0048 Rev. I Evaluation, Evaluation Attachment I

• The containment leakage and ESF leakage doses are assumed to have increased by the same 3.1 percent increase calculated for the MSIV leakage dose.

• • The containment, external cloud, and control room intake filter shine doses are not affected by an increase in the control room unfiltered inleakage rate.

Technical Evaluation, Revision 0 EC 356383 (Dresden)

EC 356379 (Quad Cities) 09/03/05 Page 3 of 6

Tahle' 2"~

Quad Cities Co'ntrol Room'Post-LOCA Dose Comparison (Rem*TED; 4,200 cfm CR 60,000 cfm CR 60,000 cfm'CR -S. 60,000 cfm CR.

Intake for First40 Intake for First 40 Intake for First 40 Intake for First 40 Activity Release' Minues Minutes Mine Mi Pat

'DF, DF DF, No Cutoff Time -

Cutoff Time z'-'

'Cutoff Time=

Cutoff Time (3.28 3.615 Hours 3.615 Hours 3.05 Hours '

hre for 720 Hours)

Containment Leakage 1.58E-02 1.69E-02

• 1.67E-02 1.62E-02 ESF Leakage 3.05E-02 3.26E-02

• 3.06E-02 3.06E-02 MSIV Leakage 3.35E+00 3.58E+0o 3.60E+00 3.58E+00 Containment Shine 2.20E1Ol 2.20E-1 e2.20E-01 2.20E-01 External Cloud 2.09E01 2.09E-01 **2.10E-01 2.1OE-OI CR Filter Shine Negligible Negligible *Negligible Negligible Total 3.83E+00 4.06E+00 4.08E+00 4.06E+00 This Technical Dat Sorce QDC-0000-N-148 1 8/15/05 Technical QDC-0000-N-1481 Evlain DtSoreRev.

0 Evaluation Rev. 1 Evaluatin, The containment leakage and ESF leakage doses are assumed to' have increased by the same 6.9 percent increase calculated for the MSIV leakage dose.

The containment, external cloud, and control room intake filter shine doses are not affected by an increase in the control room unfiltered inleakage rate.

CONCLUSIONS / FINDINGS:

As can be seen from the above tables, CR operator doses remain acceptable within the requirements of 10 CFR 50.67 (control room dose is less than 5 Rem TEDE) for all scenarios. It can be seen that a change in a time to reach an elemental DF of 200 is relatively insensitive to the total dose to control room operators.

REFERENCES:

1. Dresden Calculation DRE05-0048 Revision 0, "Dresden Units 2 & 3 Post-LOCA EAB, LPZ, and CR Dose - AST Analysis," August 15, 2005

2. Quad Cities Calculation QDC-0000-N-1481 Revision 0, "Quad Cities Units 1 & 2 Post-LOCA EAB, LPZ, and CR Dose - AST Analysis," August 15, 2005

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Technical Evaluation, Revision 0 EC 356383 (Dresden)

EC 356379 (Quad Cities) 09/03/05 Page 5 of 6 Attachment I Dresden RADTRAD Output (Constant Removal Rate Case)

Ittff##ftftft

1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. f###ft*t##tfff######ft#fffff#ftftft##ft#f#ftfftt###ftft#

RADTRAD Version 3.03 (Spring 2001) run on 9/01/2005 at 22:30:13 ftfttff#ft##ft#####f

1. 1. 1. t#####*###ft*t#~t*#t

1. f#########*ftf#####tf

1. 1. 1. 1. 1. 1. 1. 1. ftt###ft#f##

1. ff#ftfftf##ft##f##ftfftfttftfftf#ft#ftff#f#ftftft##fttf#ft##ftfttftfftf#ft#f#ft#ftftft####

File information f#ft#ftf#ft#ft#f##f#ft##ft##ftft##f#ftftf##ftf#ftftfftftf##f#ftf#ftftftf#ft#####ft#fttt####

Plant file

= C:\\RADTRAD 3.03\\Input\\Quad\\DRE400CL61.psf Inventory file

= c:\\radtrad 3.03\\defaults\\dpsdef.txt Release file

= c:\\radtrad 3.03\\defaults\\bwrdba.rft Dose Conversion file = c:\\radtrad 3.03\\defaults\\fgrll&12.inp f#ft##

1. ft##

ft###a a

ft 17 irrv r

t#

t;44 Drede unitf f

ft 2

3fnta ar AST Anlyi CotaimntLakg

1. t

1. tf #t

1. f##

1. f

1. f #

t #

f#####t

1. 1. 1. 1. t

1. f###

1. t #t # # #f####

1. f-

1. 1. f

1. tf

• 1. 1. #t t

1. t

1. f #f ftf

1. t

1. 1. t #t f#

ft ft#f#

1. t

1. t #*

1. t #

f####

ft Radtrad 3.03 4/15/2001-Dresden Unit 2 & 3 Contaiinmnent Leakage AST Analysis - Containment Leakage = 3

%/day, SGTS Charcoal Filter @ 50%, CREV Manually Started @ 40 Minutes, CREV Charcoal Filter e 99%, No Reduction In Containment Leakage After 24 hrs, and CR Unfiltered Inleakage Nuclide Inventory File:

c:\\radtrad 3.03\\defaults\\dpsdef.txt

---Plant-Power-Level-3.0160E+03 Compartments:

5 Compartment 1:

Drywell 3

1.5800E+05 1

0 0

1 0

Compartment 2:

Reactor Building 3

2.2500E+06 0

0 0

0 0

Compartment 3:

Environment 2

O.OOOOE+00 0

0

• 0 0

0 Compartment 4:

Control Room 1

8.1000E+04 0

0 0

0 0

Compartment 5:

Void 3

1.OOOOE+05 0

0 0

0 0

Pathways:

6 Pathway 1:

Drywell to 1

2 4

Reactor Building Pathway 2:

Reactor Building 2

3 to Environment 2

Pathway 3:

Filtered Intake 3

4 2

to Control Room Pathway 4:

Unfiltered

.3 4

2 Inleakage to Control Room Pathway 5:

Control Room Exhaust 4

3 2

Pathway 6:

Drywell to Void 1

5 to Environment

4 End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1

1.OOOOE+00 c:\\radtrad 3.03\\defaults\\fgrll&12.inp c:\\radtrad 3.03\\defaults\\bwr_dba.rft

0. 000E+00 1

9.5000E-01 4.8500E-02 Overlying Pool:

0 0.OOOOE+00 0

0 0

0 Compartments:

5 Compartment 1:

1 1

1 o.0000E+00 0

1 1.5000E-03 1.OOOOE+00 o.OOOOE+00 2

o.OOOOE+00 7.2000E+02 1*

0.OOOOE+00 0

0 0

3 3

1.0000E+01 1

1 O.OOOOE+00 Compartment 2 1

3.2800E+00 0.OOOOE+00

> --3,,E 4<' " ) av O.OOOOE+00 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

0 0

Compartment 5:

0 1

0 0

0 0

0 0

0 Pathways:

6 Pathway 1:

0 0

0 0*

0 0

0 0

0 1

4 0.OOOOE+00 3.3300E-02 2.OOOOE+00 7.2000E+02 0

Pathway 2:

0 0

0 0

0 O.OOOOE+00

2. 1870E+00 2.5380E+00 O.OOOOE+00 1

8 O.OOOOE+00- 0.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00

3.3300E-02 6.6670E-01 2.OOOOE+00 3.OOOOE+00 3.0500E+00 3.1000E+00 7.2000E+02 0

0 0

0 0

0 Pathway 3:

0 0

0 0

0 1

10 O.OOOOE+0O 3.3300E-02 6.6670E-01 2.OOOOE+OO 4.OOOOE+OO 8.OOOOE+O0 1.6000E+O1 2.4000E+01 4.8000E+01 7.2000E+02 0

0 0

0 0

0 Pathway 4:

0 0

0 0

0 1

10 O. OOOOE+00 3.3300E-02 6.6670E-01 2.OOOOE+00 4.OOOOE+00 8.OOOOE+00 1.6000E+01 2.4000E+01 4.8000E+01 7.2000E+02 0

0

4. 4000E+03 4.4000E+03 4.4000E+03 4.4000E+03 4.4000E+03 4.4000E+03 O.OOOOE+00 O.OOOOE+00 2.2000E+03 1.8000E+03 1.8000E+03 1.8000E+03 1.8000E+03 1.8000E+03 1.8000E+03 1.8000E+03 O.OOOOE+00 9.9000E+01 9.9000E+01

9. 9000E+01 9.9000E+01 9.9000E+01 9.9000E+01 0.OOOOE+00 0.0000E+00 0.OOOOE+00

9. 9000E+01

9. 9000E+01

9. 9000E+01 9.9000E+01.

9.9000E+01 9.9000E+01

9. 9000E+01 0.OOOOE+00

5. OOOOE+O1

5. OOOOE+01 S. OOOOE+01 5.OOOOE+01 S. 0000E+01 S. OOOOE+01 O. OOOOE+00 O.OOOOE+00 O.OOOOE+00 9.9000E+01 9.9000E+01 9.9000E+01 9.9000E+01 9.9000E+01

9. 9000E+01 9.9000E+01 O. OOOOE+00

5. OOOOE+01

5. OOOOE+01

5. OOOOE+01 5.OOOOE+01

5. OOOOE+01 5.0000E+01 O.OOOOE+00 O. OOOOE+00 O.OOOOE+00 9.9000E+01 9.9000E+01 9.9000E+01 9.9000E+01 9.9000E+01 9.9000E+01 9.9000E+01 O.OOOOE+00 O.OOOOE+00 6.OOOOE+04

4. OOOOE+02

4. OOOOE+02 4.OOOOE+02 4.OOOOE+02 4.OOOOE+02 4.OOOOE+02 4.OOOOE+02 O. OOOOE+00 O.OOOOE+00 O.OOOOE+00 O. OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O. OOOOE+00 O.OOOOE+00 O. OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E4-00 0.OOOOE+00

0. OOOOE+00 0.OOOOE+00 0.OOOOE+00

0. OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00

0. OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00

0. OOOOE+O0 0.OOOOE+00 0.OOOOE+00

0 0

0 0

Pathway 5:

0 0

0 0

10 O.OOOOE+00 0.

3.3300E-02 6.

6.6670E-01 2.

2.OOOOE+00 2.

4.OOOOE.O0 2.

8.OOOOE+00 2.

1.6000E+01 2.

2.4000E+01 2.

4.8000E.01 2.

7.2000E+02 0O.

0 0

0 0

0 0

Pathway 6:

0 0

0 0

0

.0 0

0 0

0 1

10 0.OOOOE+00 0.

3.3300E-02 8.

2.OOOOE+00

.4.

3.OOOOE+00 4.

3.0500E+00 4.

3.1000E+00 4.

4.OOOOE+00 4.

5.OOOOE.00 4.

6.OOOOE+00 4.

7.2000E+02 0.

0 Dose Locations:

3

.OOOOE+00 220OE+04 2000E+03 2000E+03 2000E+03 2000E+03 2000E+03 2000E+03 2000E+03 OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+O0 O.OOOOE+00 O.OOOOE+00 O.OOOOE+O0 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+0O O.OOOOE+O0 O.OOOOE+00 O.OOOOE+0O O.OOOOE+00 O.OOOOE+00 O.OOOOE+O0 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 o.OOOOE+00 0.OOOOE+00 0.OOOOE+00

0. OOOOE+00 OOOOE+00 1300E-01.

6200E-01 620OE.-01 6200E-01 6200E-01 6200E-01 6200E-01 6200E-01 OOOOE+00 Location 1:

Exclusion Area Boundary 3

1 3

O.OOOOE+OO 5.0000E-O1 7.2000E+02 1

2 O.OOOOE+OO 7.2000E+02 0

8.7400E-05 6.7400E-06 O.OOOOE+O0 3.5000E-04 O.OOOOE+00 Location 2:

Low Population Zone 3

7 O.OOOOE+0O 5.OOOOE-O1 2.OOOOE+00 8.OOOOE+00 2.4000E+01 9.6000E+01 7.2000E+02 1

4 O.OOOOE+O0 8.OOOOE+O0 2.4000E+01 7.2000E+02 0

Location 3:

Control Room 4

0 1

2 O.OOOOE+00 7.2000E+02 1

1.5500E-05 8.30OOE-06 3.5700E-06 2.3400E-06 9.3900E-07 2.5300E-07 O.OOOOE+OO 3.5000E-04 1.8000E-04 2.3000E-04 O.OOOOE+00 3.5000E-04 O.OOOOE+O0 4

O.OOOOE+00 1.OOOOE+00 2.4000E+01 6.0000E-01 9.6000E+01 4.OOOOE-01 7.2000E+02 O.OOOOE+0O Effective Volume Location:

1 6

O.OOOOE+00 6.4200E-06 2.OOOOE+00 2.8700E-06 8.OOOOE+00 1.9200E-06 2.4000E+01 8.0300E-07 9.6000E+01 2.2900E-07 7.2000E+02 O.OOOOE+00 Simulation Parameters:

7 0.OOOOE+00 2.OOOOE+00

4. OOOOE+O0

1. OOOOE-02

1. OOOOE-01 1.OOOOE+O0

8.0000E+00 2.OOOOE+00 2.4000E+01 4.OOOOE+00 9.6000E+01 8.0000E+00 7.2000E+02 O.OOOOE+00 Output Filename:

C:\\RADTRAD 3.o231 1

1 1

0 0

End of Scenario File

Nd-147 Np-239 Pu-238 Pu-239 Pu-240 Pu-241 Am-241 Cm-242 Cm-244 2.2756E-04 7.0033E-03 7.1956E-06 6.0390E-07 8.1409E-07 2.7244E-04 1.6516E-07 3.6557E-05 2.6369E-06 2.8129E-12 3.0188E-11 4.2031E-10 9.7158E-09 3.5727E-09 2.6447E-09 4.8120E-11 1.103OE-11 3.2593E-11 1.1524E+13 7.6064E+13 1.0635E+15 2.4481E+16 8.9646E+15 6.6087E+15 1.2024E+14 2.7449E+13 B. 0442E+13 1.7921E+16 1.2582E+18 4.5277E+14 3.7792E+13 5.1242E+13 1.7156E+16 1.0128E+13 2.3360E+15 1.6603E+14 Reactor Building Transport Group Inventory:

Time (h) =

96.0000 Atmosphere Sump Noble gases (atoms) 2.1076E+23 0.OOOOE+00 Elemental I (atoms) 1.3758E+14 0.OOOOE+00 Organic I (atoms) 7.9199E+18 0.OOOOE+00 Aerosols (kg) 1.3520E-06 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (Thyroid)

Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid)

Total I (Ci) 3.3822E-09 3.4214E-09 2.3617E+02 Drywell to Reactor Building Transport Group Inventory:

Time (h) =

96.0000 Leakage Transport Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg) 2.5319E+24 1.6095E+19 1.1884E+20 7.7959E-02 Reactor Building to Environment Transport Group Inventory:

Time (h) =

96.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.OOOOE+00 7.3368E+18 5.2822E+19 7.7139E-02 Transported 2.3082E+24 7.3368E+18 5.2822E+19 7.7918E-04 Exclusion Area Boundary Doses:

Time (h) = 720.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 5.1461E-01 1.2807E+00 Thyroid 6.2252E+00 1.1731E+01 TEDE 7.0418E-01 1.6785E+00 Low Population Zone Doses:

Time (h) = 720.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 1.9317E-02 2.3763E-01 Thyroid 1.5356E-01 1.3012E+00 TEDE 2.3993E-02 2.9160E-01 Control Room Doses:

Time (h) = 720.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 2.7512E-04 6.0715E-03 Thyroid 1.6242E-02 2.3686E-01 TEDE 7.6971E-04 1.6012E-02 Drywell Compartment Nuclide Inventory:

10.400 16.000 24.000 48.000 96.000 720.000 1.3694E+00 2.6415E-01 6.7037E-01 1.9242E+00 3.8455E-01 7.6944E-01 2.5018E+00 5.0134E-01 8.7257E-01 3.7177E+00 7.1198E-01 9.8388E-01 5.5060E+00 9.7435E-01 1.1476E+00 1.1731E+01 1.6785E+00 1.3012E+00 1.3188E-01 1.6953E-01 2.0625E-01 2.3367E-01 2.6761E-01 2.9160E-01 1.1592E-01 1.4695E-01 1.7882E-01 1.9631E-01 2.2062E-01 2.3686E-01 8.1186E-03 1.0541E-02 1.2837E-02 1.3921E-02 1.5243E-02 1.6012E-02 Worst Two-Hour Doses Exclusion Time (hr) 4.3 Area Boundary Whole Body Thyroid (rem)

(rem) 5.1266E-02 3.3063E-01 TEDE (rem) 6.7653E-02

1. ii#i#ififi##if##*#ififi####if###if###if#i#ififi#if######ififi#ifif#if#ifi#if#i##i#ifP####

RADTRAD Version 3.03 (Spring 2001) run on 8/30/2005 at 2:26:59 ififif##ififif#if#if iF#i# info### rt##ifi#if###f##

1. 1. 1. ##i#####if#if#####i File information ifiifiifiifi###i#i##i#if##i#i#if####i##i#if#ififiififfififfifi##ififiififi##Hi#ifiifiifi####

Plant file Inventory file Release file Dose Conversion

= C:\\RADTRAD 3.03\\Input\\Quad\\DRE400MS61.psf

= C:\\radtrad 3.03\\defaults\\dpsdef.txt

= c:\\radtrad 3.03\\defaults\\bwrdba.rft file = c:\\radtrad 3.03\\defaults\\fgrll&12.inp

1. if#if#

ifififif if##ifif if if.

if if if.

if

1. 1. 1. 1. if ifififif if#ifif if if.

if ififif#

II if if if if if if if if##ifif if if H

if if if if if ifif if if if if

• if if.if##if*

if ififif if if H

if if if if if ififif#

if #if H if if if if if if Radtrad 3.03 4/15/2001 Dresden 2 & 3 MSIV Leakeg AST Analysis -

Settling Velocity, CREV Manually Started

= 60,0000 cfm for <0.6667 hrs and 400 cfm Efficiency @ 99%, an Nuclide Inventory File-c:\\radtrad 3.03\\defaults\\dps_def.txt Plant Power Level:

3.0160E+03 Compartments:

9 Compartment 1:

Drywell 3

1.5800E+05 1

0 0

1 0

MSIV Leakage = 150 scfh, 40% Aerosol

@ 40 Minutes, CR Unfiltered Inleakage

>0.6667 hrs, CREV Charcoal Filter Compartment MSIV Failed 3

2.0024E+02 0

0 0

0 0

2:

Control Vol 1 Compartment 3:

s Intact Control Volume 2 3

1.5293E+02 0

0 0

0 0

Compartment 4:

Intact Control Volume 3 3

4.9110E+01 0

0 0

0 0

Compartment 5:

Intact Control Volume 4 3

1.6375E+02 0

0 0

0 0

Compartment 6:

Intact Control Volume 5 3

4.9110E+01 0

0 0

0 0

Compartment 7:

Environment 2

O.OOOOE+00 0

0 0

0 0

Compartment 8:

Control Room 1

8.1000E+04 0

0 0

0 0

Compartment 9:

Void 3

1.0000E+05

0 0

0 0

0 Pathways:

12 Pathway 1:

Drywell to MSIV Failed Control Vol 1 1

2 2

Pathway 2:

MSIV Failed Control Vol 1 to Environment 2

7 2

Pathway 3:

Drywell to Intact Control Volume 2 1

3 2

Pathway 4:

Intact Control Volume 2 to Intact Control Volume 3 3

4 2

Pathway 5:

Intact Control Volume 3 to Environment 4

7 2

Pathway 6:-

Drywell to Intact Control Volume 4 1

5 2

Pathway 7:

Intact Control Volume 4 to Intact Control Volume 5 5

6 2

Pathway 8:

Intact Control Volume 5 to Environment 6

7 2

Pathway 9:

Filtered Intake to Control Room 7

8 2

Pathway 10:

Unfiltered Inleakage to Control Room 7

8 2

Pathway 11:

Control Room Exhaust to Environment 8

7 2

Pathway 12:

Drywell to Void 1

9 4

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1

l.OOOOE+00 c:\\radtrad 3.03\\defaults\\fgrll&12.inp c:\\radtrad 3.03\\defaults\\bwr_dba.rft O.OOOOE+00 1

9.5000E-01 4.8500E-02 Overlying Pool:

0 O.OOOOE+00 0

0 0

0 Compartments:

9 Compartment 1:

1 1

1 o.OOOOE+00 0

1 0.OOOOE+00 1.SOOOE-03 11.OOOOE+0O 2

O.OOOOE+00 7.2000E+02 1

.O.OOOOE+00 0

0 0

3 3

1.OOOOE+01 1

1 O.OOOOE+00 Compartment 2:

0 1

3.2800E+00 O.OOOOE+00

/I-z 3,2,8Wr f-V~

O.OOOOE+00

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

0 0

0 Compartment 5:

0 1

0 0

0 0

0 0

0 Compartment 6:.

0 1

0 0

0 0

0 0

0 Compartment 7:

1 1

0 0

0 0

0 0

0

Compartment 8:

0 1

0 0

0 0

0 0

0 Compartment 9:

0 1

0 0

0 0

0 0

0.

Pathways:

12 Pathway 1:

0 0

0 0

0 1

4 O.OOOOE+00 3.3300E-02 2.OOOOE+00 7.2000E+02 0

0 0

0 0

0 Pathway 2:

0 0

0 0

0 1

4 O.OOOOE+00 3.3300E-02 2.0000E+00 7.2000E+02 0

0 0

0 0

O.OOOOE+00 3.5700E-01 2.0300E-01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0.OOOOE+00 O.OOOOE+00 1.OOOOE+00 5.6800E-01 O.OOOOE+00 O.OOOOE+00 8.6680E+01 8.6680E+01 O.OOOOE+00 O.OOODE+00 5.OOOOE+01 5.OOOOE+01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00

0 Pathway 3:

0 0

0 0

0 1

4 O.OOOOE+00 3.3300E-02 2.OOOOE+00 7.2000E+02 0

0 0

0 0

0 Pathway 4:.

0 0

0 0,

0 1

4 O.OOOOE+00 3.3300E-02 2.OOOOE+00 7.2000E+02 0

0 0

0 0

0 Pathway 5:

0 0

0 0

0 1

4 O.OOOOE+00 3.3300E-02 2.0000E+00 7.2000E+02 0

0 0

0 0

0 Pathway 6:

0 O.OOOOE+00 3.5700E-01 2.0300E-01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 1.0000E+00 5.6800E-01 O.OOOOE+00 O.OOOOE+00 8.4620E+01 8.4620E+01 O.OOOOE+00 O.OOOOE+00 5.0000E+01 5.OOOOE+01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 1.OOOOE+00 5.6800E-01 O.OOOOE+00 O.OOOOE+00 8.7110E+01 8.7110E+01 O.OOOOE+00 O.OOOOE+00 5.0000E+01 5.0000E+01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00

0 0

0 0

1 4

O.OOOOE+0O 3.330OE-02 2.OOOOE+00 7.2000E+02 0

0 0

0 0

0 Pathway 7:

0 0

0 0

0 1

4 0.OOOOE+00 3.3300E-02

2. OOOOE+00 7.2000E+02 0

0 0

0 0

0 Pathway 8:

0 0

0 0

0 4

o.OOOOE+00 3.3300E-02 2.OOOOE+00 7.2000E+02 0

0 0

0 0

0 Pathway 9:

0 0

0 0

O.OOOOE+OO 1.7800E-O1 1.O1OOE-01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+O0 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+OO O.OOOOE+O0 5.OOOOE-O1 2.8400E-01 O.OOOOE+00 O.OOOOE+00 9.3100E+01 9.3100E+O1 O.OOOOE+00 O.OOOOE+O0 5.OOOOE+01 5.OOOOE+O1 O.OOOOE+00 O.OOOOE+0O O.OOOOE+00 O.OOOOE+OO O.OOOOE+00 O.OOOOE+00 5.OOOOE-01 2.8400E-01 O.OOOOE+00 O.OOOOE+00 9.3110E+O1 9.3110E+01 O.OOOOE+00 0.OOOOE+00 5.OOOOE+01 5.OOOOE+01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00

0 1

8 O.OOOOE+00 3.3300E-02 6.6670E-01 2.0000E+00 8.0000E+00 2.4000E+01 9.6000E+01 7.2000E+02 0

0 0

0 0

0 Pathway 10:

0 0

0 0

0 1

8 0.OOOOE+00 3.3300E-02 6.6670E-01 2.OOOOE+00 8.OOOOE+00 2.4000E+01 9.6000E+01 7.2000E+02 0

0 0

0 0

0 Pathway 11:

0 0

0 0

0 1

8 0.OOOOE+00 3.3300E-02 6.6670E-01 2.OOOOE+00 8.0000E+00 2.4000E+01 9.6000E+01 7.2000E+02 0

0 O.OOOOE+00 2.2000E+03 1.8000E+03 1.8000E+03 1.8000E+03 1.8000E+03 1.8000E+03 O.OOOOE+00 O.OOOOE+00 6.OOOOE+04 4.OOOOE+02 4.0000E+02 4.OOOOE+02 4.0000E+02 4.0000E+02 O.OOOOE+00 O.OOOOE+00 6.2200E+04 2.2000E+03 2.2000E+03 2.2000E+03 2.2000E+03 2.2000E+03 O.OOOOE+00 0.0000E+00 O.OOOOE+00 9.9000E+01

9. 9000E+01 9.9000E+01 9.9000E+01 9.9000E+01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0.0000E+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 9.9000E+01 9.9000E+01 9.9000E+01 9.9000E+01 9.9000E+01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 9.9000E+01 9.9000E+01 9.9000E+01 9.9000E+01 9.9000E+01 O.OOOOE+00 O.000OE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00

0 0

0 0

Pathway 12:

0 0

0 0

0 0

0 0

0 0

1 10 0.OOOOE+00 2.OOOOE+00 3.OOOOE+00 3.0500E+00 3.1000E+0O 4.OOOOE+00 5.0000E+00 6.OOOOE+00 8.0000E+00 7.2000E+02 2.1870E+00 2.5380E+00 2.5380E+00 2.5380E+00 2.5380E+00 2.5380E+00 2.5380E+00 2.5380E+00 2.5380E+00 O.OOOOE+00 0

Dose Locations:

3 Location 1:

Exclusion Area Boundary 7

1 2

O.OOOOE+00 7.2000E+02 1

2 O.OOOOE+00 7.2000E+02 0

2.5100E-04 O.OOOOE+00 3.5000E-04 O.OOOOE+00 Location 2:

Low Population Zone 7

1 6

O.OOOOE+00 2.OOOOE+00 8.0000E+00 2.4000E+01 9.6000E+01 7.2000E+02 1

4 O.OOOOE+00 8.OOOOE+00 2.6300E-05 1.O900E-05 7.0200E-06 2.7000E-06 6.8600E-07 O.OOOOE+00 3.5000E-04 1.8000E-04

2.4000E+01 7.2000E+02 0

Location 3:

Control Room 8

0 1

2 O.OOOOE+00 7.2000E+02 2.3000E-04 O.OOOOE+00 3.5000E-04 O.OOOOE+00 1

4 0O.OOOOE+00 1.OOOOE+00 2.4000E+01 6.0000E-01 9.6000E+01 4.OOOOE-01 7.2000E+02 0.OOOOE+00 Effective Volume Location:

1 6

O.OOOOE+00 1.3000E-03 2.OOOOE+00 1.06OOE-03 8.OOOOE+00 4.4900E-04 2.4000E+01 2.9600E-04 9.6000E+01 2.4400E-04 7.2000E+02 O.OOOOE+00 Simulation Parameters:

7 O.OOOOE+00 1.OOOOE-01 1.OOOOE+00 1.OOOOE-02 2.0000E+00 5.OOOOE-01 8.OOOOE+00 1.OOOOE+00 2.4000E+01 2.OOOOE+00 9.6000E+01 5.OOOOE+00 7.2000E+02 O.OOOOE+00 Output Filename:

C:\\RADTRAD 3.o210 1

1 1

0 0

End of Scenario File

Intact Control Volume 3 to Environment Transport Group Inventory:

Time (h) =

96.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.0000E+00 5.0578E+17 0.OOOOE+00 l.1115E-03 Transported 1.7476E+23 5.0578E+17 8.0759E+18 1.6447E-04 Intact Control Volume 5 to Environment Transport Group Inventory:

Time (h) =

96.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered O.OOOOE+00 2.3824E+17 0.0000E+00 2.6543E-04 Transported 8.0693E+22 2.3824E+17 3.6664E+18 1.9641E-05 Filtered Intake to Control Room Transport Group Inventory:

Time (h) =

96.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.0000E+00 1.3092E+15 6.0176E+15 9.2322E-07 Transported 1.2679E+20 3.0753E+13 6.2699E+13 1.5435E-08 Unfiltered Inleakage to Control Room Transport Group Inventory:

Time (h) =

96.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.OOOOE+00 0.0000E+00 o.OOOOE+00 0.OOOOE+00 Transported 2.8435E+19 7.7193E+14 1.4030E+15 3.7385E-07 Control Room Exhaust to Environment Transport Group Inventory:

Time (h) =

96.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 1.5428E+20 7.9954E+14 1.4534E+15 3.8927E-07 Transported 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Exclusion Area Boundary Doses:

Time (h) = 720.0000 Whole Body Delta dose (rem) 3.4908E+00 Accumulated dose (rem) 9.3459E+00 Thyroid 8.4274E+01 2.1715E+02 TEDE 6.0571E+00 1.8346E+01 Low Population Zone Doses:

Time (h) = 720.0000 Whole Body Delta dose (rem) 9.5407E-03 Accumulated dose (rem) 1.6014E-01 Thyroid 1.5136E-01 3.8859E+00 TEDE 1.4150E-02 3.6789E Control Room Doses:

Time {h) = 720.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 5.2687E-02 4.4072E-01 Thyroid 6.2361E+00 7.4392E+01 TEDE 2.4258E-01 4.2981E+00 Drywell Compartment Nuclide Inventory:

Time (h) = 720.0000 Kr-85 1-131 1-133 Xe-133 Ci 5.3316E+05 1.1282E+03 1.1544E-06 1.2417E+06 kg 1.3589E+00 9.1003E-06 1.0190E-15 6.6339E-03 Atoms 9.6278E+24 4.1835E+19 4.6141E+09 3.0038E+22 Decay 8.2921E+22 5.8163E+21 9.4548E+21 3.1216E+24 Drywell Transport Groul Time (h) = 720.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Dose Effective (Ci/cc)

Dose Effective (Ci/cc)

Total I (Ci)

Inventory:

Atmosphere Sump 9.6579E+24 0.OOOOE+00 0.0000E+00 5.6475E+22 4.1835E+19 0.OOOOE+00 4.8726E-35 0.OOOOE+00 I-131 (Thyroid) 1-131 (ICRP2 Thyroid)

Deposition Recirculating Surfaces Filter 0.OOOOE+00 0.OOOOE+00 0.0000E+00 O.OOOOE+00 0.0000E+00 0.OOOOE+00 4.9919E+01 0.OOOOE+00

?.5217E-07 Z.5217E-07 L

.1282E+03 Time (h) = 720.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Drywell to MSIV Failed Control Vol 1 Transport Group Inventory:

Time (h) = 720.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 Transported 9.1239E+23 2.1654E+18 2.1824E+19 8.2993E-03 Drywell to Intact Control Volume 2 Transport Group Inventory:

Time (h) = 720.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Transported 9.1239E+23 2.1654E+18 2.1824E+19 8.2993E-03 Drywell to Intact Control Volume 4 Transport Group Inventory:

Time (h) = 720.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Pathway Filtered 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Transported 4.5395E+23 1.0794E+18 1.0859E+19

Worst Two-Hour Doses Exclusion Area Boundary Time Whole Body Thyroid TEDE (hr)

(rem)

(rem)

(rem) 3.0 4.4104E-01 1.7869E+01 1.4830E+00

Technical Evaluation, Revision 0 EC 356383 (Dresden)

EC 356379 (Quad Cities) 09/03/05 Page 6 of 6 Quad Cities RADTRAD Output (Constant Removal Rate Case)

RADTRAD Version 3.03 (Spring 2001) run on 9/01/2005 at 12:45:27 File information itti###i#iti#it##itititi##ititit###i#######i#f#itit##iti#i#it##i#iti#it#ititi##ititititfti Plant file Inventory file Release file Dose Conversion

= C:\\RADTRAD 3.03\\Input\\Quad\\QDC400CL61.psf

= c:\\radtrad 3.03\\defaults\\qdcdef.txt

= C:\\radtrad 3.03\\defaults\\bwrdba.rft file = c:\\radtrad 3.03\\defaults\\fgrll&12.inp

1. t #

1. 1. 1. 1. i#

1. t

1. t

1. t #

1. ##, #t #t iF it

1. i#

it

,it##it it it

1. t

1. t

1. t

1. t it it

1. t

1. t Radtrad 3.03 4/15/2001 Quad Cities Containment Leakage AST Analysis -

Containment Leakage = 3 %/day, SGTS Charcoal Filter @ 50%, CREV Manually Started @ 40 Minutes, CREV Charcoal Filter @ 99%, No Reduction In Containment Leakage After 24 hrs, and CR Unfiltered Inleakage = 60,000

= 3.Z hr t a

Nuclide Inventory File:

c:\\radtrad 3.03\\defaults\\qdc_def.txt Plant Power Level:

3.0160E+03 Compartments:

5 Compartment 1:

Drywell 3

1.5800E+05 1

0 0

1 0

Compartment 2:

Reactor Building 3

2.3500E+06 0

0 0

0 0

Compartment 3:

Environment 2

O.OOOOE+00 0

0 0

0 0

Compartment 4:

Control Room 1

1.8400E+0S 0

'0 0

0 0

Compartment 5:

Void 3

1.OOOOE+05 0

0 0

0 0

Pathways:

6 Pathway 1:

Drywell to 1

2 Reactor Building 4

Pathway 2:

Reactor Building 2

3 2

Pathway 3:

Filtered Intake 3

4 2

Pathway 4:

T to Environment to Control Room Unfiltered Inleakage to Control Room 3

4 2

Pathway Control 4

3 2

Pathway Drywell 1

5 5:

Room Exhaust to Environment 6:

to Void

4 End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1

1.OOOOE+00 c:\\radtrad 3.03\\defaults\\fgrll&12.inp c:\\radtrad 3.03\\defaults\\bwrdba.rft O.OOOOE+00 1

9.5000E-01 4.8500E-02 Overlying Pool:

0 O.OOOOE+00 0

0 '

0 0

Compartments:

5 Compartment 1:

1 1

I O.OOOOE+00 0

1 O.OOOOE+00 1.5000E-03 1.OOOOE+00 2

O.OOOOE+00 7.2000E+02 1

O.OOOOE+00 0

0 0

3 3

l.OOOOE+01 1

1 O.OOOOE+00 Compartment 2:

1 1

0 0

0 0

0 0

0 Compartment 3:

0 3.2800E+00 O.OOOOE+00 3,2 Ar-'

Adr i3s O.OOOOE+00

1 0

0 0

0 0

0 0

Compartment 4:

0 1

0 0

0 0

0 0

0 Compartment S:

0 1

0 0

0 0

0 0

0 Pathways:

6 Pathway 1:

0 0

0 0

0 0

0 0

0 0

1 8

0.OOOOE+00 3.3300E-02 2.OOOOE+00 3.OOOOE+00 3.0500E+00 3.1000E+O0

4. OOOOE+O0 7.2000E+02 0

Pathway 2:

0 0

0 0

O.OOOOE+00 2.1870E+00 2.5220E+00 2.5220E+00 2.5220E+00 2.5220E+00 2.5220E+00 O.OOOOE+00

0 1

3 O.OOOOE+00 3.3300E-02 7.2000E+02 0

0 0

0 0

0 Pathway 3:

0 0

0 0

0 1

10 O.OOOOE+OO 3.3300E-02 6.6670E-O1 2.OOOOE+00 4.0000E+00 8.0000E+00 1.6000E+01 2.4000E+01 4.8000E+01 7.2000E+02 0

0 0

0 0

0 Pathway 4:

0 0

0 0

0 1

10 0.OOOOE+00 3.3300E-02 6.6670E-01 2.OOOOE+00 4.OOOOE+00 8.OOOOE+OO 1.6000E+01 2.4000E+01 4.8000E+O1 7.2000E+02 0

0 0

O.OOOOE+00 4.4000E+03 O.OOOOE+0O O.OOOOE+00 2.2000E+03 1.8000E+03 1.8000E+03 1.8000E+03 1.8000E+03 1.8000E+03 1.8000E+03 1.8000E+03 O. OOOOE+00 O.OOOOE+00 9.9000E+01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 9.9000E+0l 9.9000E+01 9.9000E+0l 9.9000E+01 9.9000E+0l 9.9000E+01 9.9000E+01 O.OOOOE+00 O.OOOOE+00 5.OOOOE+01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 9.9000E+01 9.9000E+01 9.9000E+01 9.9000E+01 9.9000E+01 9.9000E+01

9. 9000E+01 O.OOOOE+00 O.OOOOE+00 5.OOOOE+01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 9.9000E+01 9.9000E+01 9.9000E+0l 9.9000E+01 9.9000E+01 9.9000E+01 9.9000E+01 O.OOOOE+00 O.OOOOE+00 6.OOOOE+04 4.OOOOE+02 4.OOOOE+02 4.OOOOE+02 4.OOOOE+02 4.OOOOE+02 4.OOOOE+02 4.0000E+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+O0 O.OOOOE+00 O.OOOOE+0O O.OOOOE+00 O.OOOOE+00

0 0

0 Pathway 5:

0 0

0 0

0 1

10 O.OOOOE+00 3.3300E-02 6.6670E-01 2.OOOOE+OO 4.OOOOE+00 8.OOOOE+0O 1.6000E+O1 2.4000E+01 4.8000E+01 7.2000E+02 0

0 0

0 0

0 Pathway 6:

0 0

0 0

0 0

0 0

0 0

1 O.OOOOE+O0 6.2200E+04 2.2000E+03 2.2000E+03 2.2000E+03 2.2000E+03 2.2000E+03 2.2000E+03 2.2000E+03 O.OOOOE+OO O.OOOOE+00 O.OOOOE+00 O.OOOOE+O0 O.OOOOE+O0 O.OOOOE+O0 O.OOOOE+00 O.OOOOE+O0 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+O0 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+O0 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 4

O.OOOOE+00 O.OOOOE+O0 3.3300E-02 8.1300E-O1 2.OOOOE+00 4.7800E-01 7.2000E+02 O.OOOOE+00 0

Dose Locations:

3 Location 1:

Exclusion Area Boundary 3

1 3

O.OOOOE+00 5.0000E-01 7.2000E+02 1

2 1.5700E-04 6.3800E-06 O.OOOOE+00

O.OOOOE+O0 7.2000E+02 3.5000E-04 O.OOOOE+00 0

Location 2:

Low Population Zone 3

1 7

O.OOOOE+OO 5.OOOOE-01 2.OOOOE+O0 8.000OE+00 2.4000E+01 9.6000E+01 7.2000E+02 1

4 0.OOOOE+00 8.OOOOE+00 2.4000E+01 7.2000E+02 0

Location 3:

Control Room 3.0100E-05 2.0500E-05 8.7600E-06 5.7300E-06 2.2800E-06 6.0700E-07 O.OOOOE+00 3.5000E-04 1.8000E-04 2.3000E-04 O.OOOOE+00 4

0 1

2 O.OOOOE+00 3.5000E-04 7.2000E+02 O.OOOOE+00 1

4 O.OOOOE+00 1.OOOOE+O0 2.4000E+01 6.OOOOE-01 9.6000E+01 4.OOOOE-01 7.2000E+02 O.OOOOE+00 Effective Volume Location:

1 6

O.OOOOE+00 5.8400E-06 2.OOOOE+00 2.6800E-06 8.OOOOE+00 1.8100E-06 2.4000E+01 7.7700E-07 9.6000E+01 2.3000E-07 7.2000E+02 O.OOOOE+00 Simulation Parameters:

7 O.OOOOE+00 1.OOOOE-02 2.OOOOE+00 1.OOOOE-01 4.OOOOE+00 1.OOOOE+O0 8.OOOOE+00 2.OOOOE+00 2.4000E+01 4.OOOOE+00 9.6000E+01 8.0000E+00 7.2000E+02 O.OOOOE+00 Output Filename:

C:\\RADTRAD 3.o225 1

1 1

0 0

End of Scenario File

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Dose Effective (Cl/cc)

Dose Effective (Ci/cc)

Total I (Ci) 2.2029E+14 0.OOOOE+00 8.2236E+18 0.0000E+00 2.1428E-06 0.0000E+00 I-131 (Thyroid) 1-131 (ICRP2 Thyroid) 3.3663E-09 3.4053E-09 2.4555E+02 Drywell to Reactor Building Transport Group Inventory:

Time (h) =

96.0000 Leakage Transport Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg) 2.5160E+24

1. 6076E+19 1.1810E+20 7.7684E-02 Reactor Building to Environment Transport Group Inventory:

Time (h) =

96.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.OOOOE+00 7.3058E+18 5.2222E+19 7.6864E-02 Transported 2.2839E+24 7.3058E+18 5.2222E+19 7.7641E-04 Exclusion Area Boundary Doses:

Time (h) = 720.0000 Whole Body Delta dose (rem) 4.8428E-01 Accumulated dose (rem) 1.1962E+00 Thyroid 5.8584E+00 1.1036E+01 TEDE 6.6268E-01 1.5707E+00 Low Population Zone Doses:

Time (h) = 720.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 4.6075E-02 5.6629E-01 Thyroid 3.6627E-01 3.1164E+00 TEDE 5.7229E-02 6.9560E-01 Control Room Doses:

Time (h) = 720.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 3.6673E-04 6.8645E-03 Thyroid 1.6365E-02 2.2468E-01 TEDE 8.6507E-04 1.6249E-02 Drywell Compartment Nuclide Inventory:

Time (h) = 720.0000 Kr-85 1-131 1-133 Xe-133 Ci 5.3317E+05 1.1283E+03 1.1544E-06 1.2418E+06 kg 1.3590E+00 9.1007E-06 1.0191E-15 6.6344E-03 Atoms 9.6281E+24 4.1836E+19 4.6143E+09 3.0040E+22 Decay 8.2919E+22 5.7605E+21 9.3441E+21 3.1215E+24 Drywell Transport Group Inventory:

Time (h) = 720.0000 Atmosphere Sump Noble gases (atoms) 9.6581E+24 0.0000E+00 Elemental I (atoms) 0.OOOOE+00 5.6459E+22 Organic I (atoms) 4.1836E+19 0.OOOOE+00 Aerosols (kg) 4.8652E-35 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 2.5218E-07

(hr) 0.000 0.033 0.290 0.500 0.667 0.920 1.170 1.420 1.670 1.920 2.000 2.400 2.700 3.000 3.050 3.100 3.400 3.700 4.000 4.300 4.600 4.900 5.200 5.500 5.800 6.100 6.400 6.700 7.000 7.300 7.600 7.900 8.000 8.300 8.600 8.900 9.200 9.500 9.800 10.100 10.400 16.000 24.000 48.000 96.000 720.000 (rem)

O. OOOOE+00 O.OOOOE+00 7.8824E-03 3.7099E-02 3.8958E-02 4.4112E-02 5.2750E-02 6.5564E-02 8.3055E-02 1.0564E-01 1.1400E-01 1.6379E-01 2.0683E-01 2.5254E-01 2.6033E-01 2.6816E-01 3.1571E-01 3.6383E-01 4.1205E-01 4.6004E-01 5.0758E-01 5.5450E-01 6.0069E-01 6.4611E-01 6.9071E-01 7.3449E-01 7.7744E-01 8.1957E-01 8.6086E-01 9.0133E-01 9.4100E-01 9.7987E-01 9.9265E-01 1.0305E+00 1.0676E+00 1,.1039E+00 1.1395E+00 1.1745E+00 1.2087E+00 1.2423E+00 1.2752E+00 1.7962E+00 2.3433E+00 3.4939E+00 5.1777E+00 1.1036E+01 (rem)

O. OOOOE+00 O.OOOOE+00 5.0020E-04 2.4132E-03 2.5445E-03 2.9910E-03 3.8810E-03 5.3575E-03 7.5302E-03 1.0485E-02 1.1607E-02 1.8665E-02 2.5216E-02 3.2567E-02 3.3851E-02 3.5151E-02 4.3282E-02

5. 1832E-02 6.0689E-02 6.9760E-02 7.8972E-02 8.8263E-02 9.7582E-02 1.0689E-01 1.1616E-01 1.2535E-01 1.3445E-01 1.4345E-01 1.5232E-01 1.6106E-01 1.6966E-01 1.7810E-01 1.8089E-01 1.8913E-01 1.9721E-01 2.0514E-01 2.1290E-01 2.2051E-01 2.2796E-01 2.3526E-01 2.4240E-01 3.5391E-01 4.6301E-01 6.6105E-01 9.0798E-01 1.5707E+00 (rem)

O.OOOOE+00 O.OOOOE+00 1.5112E-03 7.1127E-03 1.3085E-02 2.9646E-02 5.7399E-02 9.8574E-02 1.5478E-01 2.2733E-01 2.5419E-01 3.2256E-01 3.8166E-01 4.4443E-01 4.5512E-01 4.6586E-01 5.3115E-01 5.9722E-01 6.6343E-01 7.2933E-01 7.9460E-01 8.5902E-01 9.2245E-01 9.8480E-01 1.0460E+00 1.1062E+00 1.1651E+00 1.2230E+00 1.2797E+00 1.3352E+00 1.3897E+00 1.4431E+00 1.4606E+00 1.4781E+00 1.4952E+00 1.5120E+00 1.5285E+00 1.5446E+00 1.5604E+00 1.5759E+00 1.5911E+00 1.8318E+00 2.0845E+00 2.3547E+00 2.7501E+00 3.1164E+00 (rem)

O.OOOOE+00 O.OOOOE+00 9.5899E-05 4.6266E-04 8.8447E-04 2.3190E-03 5.1789E-03 9.9232E-03 1.6904E-02 2.6399E-02 3.0005E-02 3.9695E-02 4.8690E-02 5.8783E-02 6.0546E-02 6.2331E-02 7.3496E-02 8.5235E-02 9.7396E-02 1.0985E-01 1.2250E-01 1.3526E-01 1.4805E-01 1.6083E-01 1.7355E-01 1.8618E-01 1.9868E-01 2.1103E-01 2.2321E-01 2.3521E-01 2.4701E-01 2.5861E-01 2.6243E-01 2.6904E-01 2.7552E-01 2.8189E-01 2.8812E-01 2.9424E-01 3.0022E-01 3.0609E-01 3.1183E-01 4.0186E-01 4.9039E-01 5.5646E-01 6.3837E-01 6.9560E-01 (rem)

O.OOOOE+00 O.OOOOE+00 1.8692E-04 1.0609E-03 2.5197E-03 5.2141E-03 7.6214E-03 9.9316E-03 1.2288E-02 1.4822E-02 1.5690E-02 2.0030E-02 2.3264E-02 2.6548E-02 2.7101E-02 2.7657E-02 3.1036E-02 3.4489E-02 3.8004E-02 4.1570E-02 4.5170E-02 4.8790E-02 5.2416E-02 5.6035E-02 5.9635E-02 6.3209E-02 6.6749E-02 7.0249E-02 7.3704E-02 7.7110E-02 8.0465E-02 8.3766E-02 8.4854E-02 8.7983E-02 9.0887E-02 9.3603E-02 9.6161E-02 9.8584E-02 1.0089E-01 1.0310E-01 1.0522E-01 1.3616E-01 1.6706E-01 1.8489E-01 2.0832E-01 2.2468E-01 (rem)

O.OOOOE+00 O.OOOOE+00 6.9448E-06 3.9784E-05 9.5572E-05 2.0092E-04 2.9765E-04 3.9586E-04 5.0431E-04 6.3148E-04 6.7748E-04 9.1714E-04 1.1060E-03 1.3077E-03 1.3426E-03 1.3779E-03 1.5986E-03 1.8332E-03 2.0805E-03 2.3388E-03 2.6063E-03 2.8812E-03 3.1618E-03 3.4464E-03 3.7336E-03 4.0222E-03 4.3111E-03 4.5993E-03 4.8860E-03 5.1705E-03 5.4523E-03 5.7310E-03 5.8231E-03 6.0878E-03 6.3330E-03 6.5623E-03 6.7782E-03 6.9829E-03 7.1780E-03 7.3649E-03 7.5447E-03 1.0175E-02 1.2668E-02 1.3933E-02 1.5384E-02 1.6249E-02 Worst Two-Hour Doses Exclusion Time (hr) 4.3 Area Boundary Whole Body Thyroid (rem)

(rem) 4.6644E-02 3.0309E-01 TEDE (rem) 6.1659E-02

RADlTRAD Version 3.03 (Spring 2001) run on 9/01/2005 at 21:40:28

'S' ii####V######V######V######i############i#######iV########ii#u###VVVVVVV-File information

>Vi iii###ii#ii#####f#i#i#i#########i~~i#i~#ii#iiii##ii##VV######i####*#i#

Plant file

= C:\\RADTRAD 3.03\\Input\\Quad\\QDC400MS61.psf Inventory file

= c:\\radtrad 3.03\\defaults\\qdc__def.txt Release file

= c:\\radtrad 3.03\\defaults\\bwrdba.rft Dose Conversion file = c:\\radtrad 3.03\\defaults\\fgrll&12.inp Qua Cities MSVLa S Anlyis MIV Leaag V

sch 0Veoo Efiiec 9,

n iWi.

i##

1. V#

1. i

1. i #

V V

• #i

1. V Radtrad 3.03 4/15/2001 Quad Cities MSIV Leakeq AST Analysis -

MSIV Leakage = 150 scfh, 40% Aerosol Settling Velocity, CREV Manually Started @3 40 Minutes, CR Unfiltered Inleakage I4L' 0 °

= 6n00cfm for <0.6667 hrs and 400 cfm >0.6667 hrs,

CREV Charcoal Filter r

Efficiency @3 99%, and 5 7 = 3, Z 1 5 (?r-t~-

G4 r

L nJ 'v>du C:

c\\radtrad 3.03 \\defaults\\qdc..def.txt Plant Power Level:

3.0160E+03 Compartments:

9 Compartment 1:

Drywell 3

1.5800E+05 1

0 0

1 0

Compartment 2:

MSIV Failed Control Vol 1 3

2.0024E+02 0

0 0

0 0

Compartment 3:

Intact Control Volume 2 3

1.5293E+02 0

0 0

0 0

Compartment 4:

Intact Control Volume 3 3

4. 9110E+01 0

0 0

0 0

Compartment 5:

Intact Control Volume 4 3

1. 6375E+02 0

0 0

0 0

Compartment 6:

Intact Control Volume 5 3

4. 9110E+01 0

0 0

0 0

Compartment 7:

E~nvironment 2

0.0000E+00 0

0 0

0 0

Compartment 8:

Control Room 1

l.8400E+05 0

0 0

0 0

Compartment 9:

void 3

1.0000E+05

0 0

0 0

0 Pathways:

12 Pathway 1:

Drywell to MSIV Failed Control Vol 1 2

2 Pathway 2:

MSIV Failed Control Vol 1 2

7 2

to Environment Pathway 3:

Drywell to Intact Control Volume 2 1

3 2

Pathway 4:

Intact Control 3

4 2

Pathway 5:

Intact Control 4

7 Volume 2 to Intact Control Volume 3 Volume 3 to Environment 2

Pathway 6:

Drywell to Intact Control Volume 4 1

5 2

Pathway 7:

Intact Control 5

6 2

Pathway 8:

Intact Control 6

7 Volume 4 to Intact Control Volume S Volume 5 to Environment 2

Pathway 9:

Filtered Intake to Control Room 7

8 2

Pathway 10:

Unfiltered Inleakage to Control Room 7

8 2

Pathway Control 8

7 2

11:

Room Exhaust to Environment Pathway 12:

Drywell to Void 1

9 4

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1

1.OOOOE+00 c:\\radtrad 3.03\\defaults\\fgrll&12.inp c:\\radtrad 3.03\\defaults\\bwrdba.rft O.OOOOE+00 1

9.5000E-01 4.8500E-02 1.5000E-03 Overlying Pool:

0 O.OOOOE+00 0

0 0

0 Compartments:

9 Compartment 1:

1 1

1 O.OOOOE+00 0

1 O.OOOOE+00 1.OOOOE+00 2

0.OOOOE+00 7.2000E+02 1

'O.OOOOE+00 0

0 0

3 3

1.OOOOE+01 1

1 O.OOOOE+00 Compartment 2:

0 1

3.2800E+00 O.OOOOE+00

kr 3, ?6 eI-ct-ze) dLetn.

O.OOOOE+00

0 0

0 a

0 0

0 Compartment 3:

0 1

0 0

0 0

0 0

0 Compartment 4:

0 1

0 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

0 0

0 Compartment 7:

1 1

0 0

0 0

0 0

0

Compartment 8:

0 1

0 0

0 0

0 0

0 Compartment 9:

0 1

0 0

0 0

0 0

Pathways:

12 Pathway 1:

0 0

0 0

0 1

4 0.OOOOE+00 3.3300E-02 2.OOOOE+00

7. 2000E+02 0

0 0

0 0

0 Pathway 2:

0 0

0 0

0 1

4

0. OOOOE+00 3.3300E-02 2.OOOOE+00

7. 2000E+02 0

0 0

0 0

O.OOOOE+00 3.5700E-01 2.1000E-01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 1.OOOOE+00 5.8700E-01 O.OOOOE+00 O.OOOOE+00 8.6680E+01 8.6680E+01 O.OOOOE+00 O.OOOOE+00 5.OOOOE+01 5.OOOOE+01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00

0 Pathway 3:

0 0

0 1

4 o

. 000E4-00 3.3300E-02 2.OOOOE+00 7.2000E+02 0

0 0

0 0

0 Pathway 4:

0 0

0 0

0 1

4 0.OOOOE+O0 3.3300E-02

2. OOOOE+00 7.2000E+02 0

0 0

0 0

0 Pathway 5:

0 0

0 0

0 1

4 0.OOOOE+00 3.3300E-02 2.OOOOE+00 7.2000E+02 0

0 0

0 0

0 Pathway 6:

0 O.OOOOE+00 3.5700E-O1 2.1000E-01 O.OOOOE+OO O.OOOOE+00 O.OOOOE+00 0.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+0O O.OOOOE+00 O.OOOOE+00 O.OOOOE+O0 O.OOOOE+00 1.OOOOE+00 5.8700E-O1 O.OOOOE+00 O.OOOOE+00 8.4620E+01 8.4620E+01 O.OOOOE+00 O.OOOOE+00 5.0000E+0l 5.OOOOE+O1 O.OOOOE+OO O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 1.OOOOE+00 5.8700E-01 O.OOOOE+00 O.OOOOE+00 8.7110E+01 8.7110E+01 0.OOOOE+00 O.OOOOE+00 5.OOOOE+0l 5.OOOOE+01 O.OOOOE+00 0.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00

0 0

0 0

1 4

O.OOOOE+00 3.3300E-02 2.OOOOE+00 7.2000E+02 0

0 0

0 0

0 Pathway 7:

0 0

0 0

0 1

4 O.OOOOE+00 3.3300E-02 2.OOOOE+00 7.2000E+02 0

0 0

0 0

0 Pathway 8:

0 0

0 0

0 1

4 O.OOOOE+00 3.3300E-02 2.OOOOE+00 7.2000E+02 0

0 0

0 0

0 Pathway 9:

0 0

0 0

O.OOOOE+00 1.7800E-01 1.05OOE-01 O.OOOOE+00 O.OOOOE+00 5.OOOOE-01 2.9400E-01 O.OOOOE+00 O.OOOOE+00 5.OOOOE-01 2.9400E-01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 9.3100E+01 9.3100E+01 O.OOOOE+00 O.OOOOE+00 9.3110E+01 9.3110E+01 O.OOOOE+00 0.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 5.OOOOE+01 5.OOOOE+01 O.OOOOE+00 O.OOOOE+00 5.OOOOE+01 S.OOOOE+01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 o.00OOE400 O.OOOOE+00 O.OOOOE+00

0 1

8 O.OOOOE+OO 3.3300E-02 6.6670E-O1

-2.OOOOE+0O 8.0000E+OO 2.4000E+01 9.6000E+01 7.2000E+02 0

0 0

0 0

0 Pathway 10:

0 0

0 0

0 1

8 O.OOOOE+00 3.3300E-02 6.6670E-0l 2.OOOOE+00 8.OOOOE+00 2.4000E+01 9.6000E+01 7.2000E+02 0

0 0

0 0

0 Pathway 11:

0 0

0 0

0 1

8 O.OOOOE+O0 3.3300E-02 6.6670E-01 2.OOOOE+00 8.OOOOE+00 2.4000E+01 9.6000E+O1 7.2000E+02 0

0 O.OOOOE+00 2.2000E+03 1.8000E+03 1.8000E+03 1.8000E+03 1.8000E+03 1.8000E+03 O.OOOOE+00 O.OOOOE+00 6.OOOOE+04 4.0000E+02 4.0000E+02 4.0000E+02 4.0000E+02 4.OOOOE+02 O.OOOOE+00 O.OOOOE+00 6.2200E+04 2.2000E+03 2.2000E+03 2.2000E+03 2.2000E+03 2.2000E+03 O.OOOOE+OO O.OOOOE+00 O.OOOOE+00 9.9000E+O1 9.9000E+01 9.9000E+01 9.9000E+01 9.9000E+O1 O.OOOOE+0O O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+0O O.OOOOE+00 O.OOOOE+00 O.OOOOE+O0 0.0000E+00 O.OOOOE+00 O.OOOOE+0O O.OOOOE+00 O.OOOOE+0O O.OOOOE+00 O.OOOOE+00 9.9000E+01 9.9000E+0l 9.9000E+01 9.9000E+01 9.9000E+01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+O0 O.OOOOE+O0 O.OOOOE+OO O.OOOOE+00 O.OOOOE+00 O.OOOOE+O0 O.OOOOE+00 O.OOOOE+00 O.OOOOE+0O O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+O0 O.OOOOE+00 9.9000E+01 9.9000E+01 9.9000E+O1 9.9000E+01 9.9000E+01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+O0 O.OOOOE+O0 O.OOOOE+00 O.OOOOE+00 O.OOOOE+O0 O.OOOOE+00 O.OOOOE+00 O.OOOOE+O0 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+0O

0 0

0 0

Pathway 12:

0 0

0 0

0 0

0 0

0 0

1 9

0.OOOOE+00.

2.OOOOE+00 3.0000EO+00 3.0500E+00 3.1000E+00 4.OOOOE+00 6.OOOOE+00 8.OOOOE+00 7.2000E+02 0

2.1870E+00 2.5220E+00 2.5220E+00 2.5220E+00 2.5220E+00 2.5220E+00 2.5220E+00 2.5220E+00 O.OOOOE+00 Dose Locations:'

3 Location 1:

Exclusion Area Boundary 7

1 2

0.OOOOE+00 7.2000E+02 1

2 O.OOOOE+00 7.2000E+02 1.3600E-03 O.OOOOE+00 3.5000E-04 O.OOOOE+00 0

Location 2:

Low Population Zone 7

1 6

O.OOOOE+00 2.OOOOE+00 8.0000E+00 2.4000E+01 9.6000E+01 7.2000E+02 1

4 O.OOOOE+00 8.OOOOE+00 2.4000E+01 1.0400E-04 4.1400E-05 2.6200E-05 9.9600E-06 2.5200E-06 O.OOOOE+00 3.5000E-04 1.8000E-04 2.3000E-04

7.2000E+02 0

Location 3:

Control Room 8

0 1

2 0.OOOOE+00 7.2000E+02 1

4 O.OOOOE+00 3.5000E-04 o.OOOOE+00 0.OOOOE+00 1.OOOOE+00 2.4000E+01 6.OOOOE-01 9.6000E+01 4.OOOOE-01 7.2000E+02 O.OOOOE+00 Effective Volume Location:

1 6

O.OOOOE+00 1.0200E-03 2.OOOOE+00 8.2300E-04 8.OOOOE+00 3.5500E-04 2.4000E+01 2.3200E-04 9.6000E+01 1.3800E-04 7.2000E+02 O.OOOOE+00 Simulation Parameters:

7 0.OOOOE+00 1.OOOOE-01 1.OOOOE+00 l.OOOOE-02 2.0000E+00 5.0000E-01 8.OOOOE+00 1.OOOOE+00 2.4000E+01 2.OOOOE+00 9.6000E+01 5.OOOOE+00 7.2000E+02 O.OOOOE+00 Output Filename:

C:\\RADTRAD 3.o229 1

1' 1

0 0

End of Scenario File

Control Room Exhaust to Environment Transport Group Inventory:

Time (h) =

96.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 1.2483E+20 6.2540E+14 1.1715E+15 3.0792E-07 Transported 0.OOOOE+00 0.OOOOE+00 O.OOOOE+00 0.OOOOE+00 Exclusion Area Boundary Doses:

Time (h) = 720.0000 Whole Body Delta dose (rem) 1.9579E+01 Accumulated dose (rem) 5.2599E+01 Thyroid 4.7267E+02 1.2098E+03 TEDE 3.3973E+01 1.0257E+02 Low Population Zone Doses:

Time (h) = 720.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 3.6280E-02 6.2722E-01 Thyroid 5.7555E-01 1.5147E+01 TEDE 5.3806E-02 1.4376E+00 Control Room Doses:

Time (h) = 720.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 4.0975E-02 4.2664E-01 Thyroid 3.6701E+00 6.0596E+01 TEDE 1.5273E-01 3.5802E+00 Drywell Compartment Nuclide Inventory:

Time (h) = 720.0000 Kr-85 1-131 1-133 Xe-133 ci 5.3309E+05 1.1281E+03 1.1542E-06 1.2416E+06 kg 1.3588E+00 9.0992E-06 1.0189E-15 6.6331E-03 Atoms 9.6267E+24 4.1830E+19 4.6136E+09 3.0034E+22 Decay 8.2917E+22 5.8162E+21 9.4548E+21 3.1215E+24 Drywell Transport Group Inventory:

Time (h) = 720.0000 Atmosphere Sump Noble gases (atoms) 9.6567E+24 0.OOOOE+00 Elemental I (atoms) 0.0000E+00 5.6475E+22 Organic I (atoms) 4.1830E+19 0.OOOOE+00 Aerosols (kg) 4.8720E-35 0.OOOOE+00 Dose Effective (Ci/cc) I-131 (Thyroid)

Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid)

Total I (Ci) 2.5214E-07 2.5214E-07 1.1281E+03 Time (h) = 720.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Deposition Surfaces 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 4.9919E+01 Recirculating Filter o.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 Drywell to MSIV Failed Control Vol 1 Transport Group Inventory:

Pathway Time (h) = 720.0000 Filtered Transported

6.600 6.900 7.200 7.500 7.800 8.000 8.300 8.600 8.900 9.200 9.500 9.800 10.100 10.400 24.000 96.000 720.000 2.6073E+02 2.7171E+02 2.8221E+02 2.9225E+02 3.0185E+02 3.0801E+02 3.1691E+02 3.2542E+02 3.3354E+02 3.4130E+02 3.4872E+02 3.5581E+02 3.6258E+02 3.6906E+02 5.0823E+02 7.3708E+02 1.2098E+03 2.1355E+01 2.2362E+01 2.3335E+01 2.4273E+01 2.5176E+01 2.5760E+01 2.6608E+01 2.7424E+01 2.8210E+01 2.8965E+01 2.9691E+01 3.0390E+01 3.1062E+01 3.1709E+01 4.6824E+01 6.8592E+01 1.0257E+02 1.0047E+01 1.0381E+01

1. 0701E+01 1.1007E+01 1.1299E+01 1.1486E+01 1.1575E+01 1.1659E+01 1.1739E+01 1.1816E+01 1.1890E+01 1.1960E+01 1.2027E+01 1.2091E+01 1.3470E+01 1.4571E+01 1.5147E+01 8.0166E-01 8.3234E-01 8.6194E-0i 8.9049E-01 9.1800E-01 9.3576E-01 9.4729E-01 9.5842E-01 9.6918E-01 9.7956E-01 9.8958E-01 9.9926E-01 1.0086E+00 1.0176E+00 1.2426E+00 1.3838E+00 1.4376E+00 3.0837E+01 1.7972E+00 3.2286E+01 1.8909E+00 3.3688E+01 1.9819E+00 3.5043E+01 2.0700E+00 3.6350E+01 2.1553E+00 3.7194E+01 2.2105E+00 3.8362E+01 2.2870E+00 3.9384E+01 2.3538E+00 4.0285E+01 2.4128E+00 4.1085E+01 2.4651E+00 4.1800E+01 2.5120E+00 4.2445E+01 2.5543E+00 4.3029E+01 2.5927E+00 4.3563E+01 2.6278E+00 5.2339E+01 3.2017E+00 5.6926E+01 3.4275E+00 6.0596E+01 3.5802E+00 Worst Two-Hour Doses Exclusion Time (hr) 2.9 Area Boundarz Whole Body (rem) 2.4935E+.00 Thyroid (rem) 1.0102E+02 TEDE (rem) 8.3837E+00

ATTACHMENT 4 Summary of Regulatory Commitments The following tables identify commitments being made by Exelon Generation Company, LLC (EGC). Any other actions discussed in this letter represent intended or planned actions by EGC. They are described for the NRC's information and are not regulatory commitments.

Committed Date Commitment or Outage.

1 EGC will revise the design basis loss-of-coolant accident (LOCA)

Prior to calculations for Dresden Nuclear Power Station (DNPS) and Quad implementation Cities Nuclear PoWer Station (QCNPS) to incorporate the parametric of the approved studies supporting an unfiltered inleakage of 60,000 cfm during the first alternative 40 minutes following a LOCA as the design basis value. The revised source term calculations will also incorporate the NRC's approach for calculating the license time to reach an elemental iodine decontamination factor (DF) of 200.

amendment 2

The design basis control rod drop accident analyses for DNPS and Prior to QCNPS will be revised to reflect the condenser DF that is applicable for implementation the main condenser 1% per day leakage condition.

of the approved alternative source term license amendment 3

EGC will revise the design basis fuel handling accident analyses for Prior to DNPS and QCNPS to reflect the effective overall DF for elemental implementation iodine of 92.

of the approved alternative source term license amendment