Text

Supplement - License Amendment Request (H09-01) Supporting the Use of Co-60 Isotope Test Assemblies (Isotope Generation Pilot Project)
	ML102640105
Person / Time
Site:	Hope Creek
Issue date:	09/10/2010
From:	Braun R; Public Service Enterprise Group
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	LR-N10-0341
	Download: ML102640105 (142)
	v • d • e

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 O PSEG Nuclear LLC SEP 10 2010 10 CFR 50.90 LR-N10-0341 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Hope Creek Generating Station Facility Operating License No. NPF-57 NRC Docket No. 50-354

Subject:

Supplement - License Amendment Request (H09-01) Supporting the Use of Co-60 Isotope Test Assemblies (Isotope Generation Pilot Project)

References:

(1) Letter from PSEG to NRC, "License Amendment Request Supporting the Use of Co-60 Isotope Test Assemblies (Isotope Generation Pilot Project)," dated December 21, 2009 (2) Letter from PSEG to NRC, "Response to Request for Additional Information -

License Amendment Request (H09-01) Supporting the Use of Co-60 Isotope Test Assemblies (Isotope Generation Pilot Project)," dated May 11, 2010 (3) Letter from PSEG to NRC, "Response to Request for Additional Information -

License Amendment Request (H09-01) Supporting the Use of Co-60 Isotope Test Assemblies (Isotope Generation Pilot Project)," dated June 10, 2010 (4) Letter from PSEG to NRC, "Response to Request for Additional Information -

License Amendment Request (H09-01) Supporting the Use of Co-60 Isotope Test Assemblies (Isotope Generation Pilot Project)," dated July 28, 2010 (5) Letter from PSEG to NRC, "Response to Request for Additional Information -

License Amendment Request (H09-01) Supporting the Use of Co-60 Isotope Test Assemblies (Isotope Generation Pilot Project)," dated August 12, 2010 In Reference 1, PSEG Nuclear LLC (PSEG) submitted a license amendment request (H09-01) for the Hope Creek Generating Station (HCGS). Specifically, the proposed change would modify License Condition 2.B.(6) and create new License Conditions 1.J and 2.B.(7) as part of a pilot program to irradiate Cobalt (Co)-59 targets to produce Co-60. In addition to the proposed license condition changes, the proposed change would also modify Technical Specification (TS) 5.3.1, "Fuel Assemblies," to describe the specific Isotope Test Assemblies (ITAs) being used.

In References 2 and 3, PSEG submitted responses to an NRC Request for Additional Information (RAI) on the license amendment request. The NRC provided PSEG with a further RAI (RAI3);

PSEG responded to RAI3 in References 4 and 5. Subsequently, following discussion between the NRC and PSEG, it was determined that additional information was needed based on the 95-2168 REV. 7/99

Document Control Desk Page 2 LR-N10-0341 Reference 5 response; this additional information is provided in Attachments 1, 2 and 3 of this submittal.

Attachment I provides a description and justification of changes to the LOCA dose calculation (H-1-ZZ-MDC-1880) since the calculation was reviewed in HCGS Amendment 174. Attachment I identifies changes in Revision 4 of the calculation (previously docketed by Reference 5) and supporting evaluations related to Revision 4. The combined changes are proposed as the new licensing basis for HCGS. The impact of these changes on GEH NEDC-33529P, Revision 0, Section 4.3 is also provided in Attachment 1. Specifically the impact to Section 4.3.4 (LOCA) and Section 4.3.1 (CRDA) is described. Both Section 4.3.1 and 4.3.4 were previously updated in the response to RAI#17 of Reference 2.1.

Attachments 2 and 3 provide the supporting evaluations discussed in Attachment 1. provides corrections to the proposed TS mark-up pages, previously provided in Reference 2.

PSEG has also re-assessed the requested amendment approval date of October 1, 2010 provided in Reference 3 and proposes to revise that date to October 11, 2010.

PSEG has reviewed the information supporting a finding of no significant hazards consideration that was provided in Reference 1. The additional information provided in this submittal does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration. No new regulatory commitments are established by this submittal.

If you have any questions or require additional information, please do not hesitate to contact Mr.

Jeff Keenan at (856) 339-5429.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on /% 0/t (Date)

Sine Robert C. Braun Sr. Vice President - Nuclear Operations Attachments (4) 1 NEDC-33529P was subsequently updated per an Errata and Addendum submitted by PSEG letter LR-NlO-0217, dated June 24, 2010

Document Control Desk Page 3 LR-N 10-0341 C: M. Dapas, Regional Administrator (Acting) - NRC Region I R. Ennis, Project Manager - USNRC NRC Senior Resident Inspector- Hope Creek P. Mulligan, Manager IV, NJBNE Commitment Coordinator - Hope Creek PSEG Commitment Coordinator - Corporate LR-N10-0341 EVALUATION OF CHANGES TO ACCIDENT ANALYSES r;.

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EVALUATION OF CHANGES TO ACCIDENT ANALYSES The Co-60 LAR and subsequent RAI responses address the impact of the Isotope Test Assemblies (ITA) on the radiological consequences of the loss-of-coolant accident (LOCA) and the control rod drop accident (CRDA). The previous docketed accident consequence analyses were based on the license amendment for extended power uprate (Amendment 174). The accident analyses provided to support the Co-60 LAR are documented in calculation H-1-ZZ-MDC-1880, Revision 4, and supporting Technical Evaluations 80102291-0030 and 80102291-0040. The parameters, inputs, assumptions and results of these current analyses are different from those evaluated in the Safety Evaluation Report (SER) for Amendment 174. This supplement documents the differences between Amendment 174 and the current analyses. This involves identifying the changes (parameters, inputs and assumptions) to the analysis model, evaluating the effect of each change, and justifying the use of the resulting accident model.

The LOCA analysis is used to demonstrate the adequacy of the Hope Creek engineered safety features (ESF) systems to mitigate the radiological consequences of a LOCA. The' analysis includes the evaluation of three potential release pathways following a LOCA:

1. Containment leakage,

2. Post-LOCA leakage from ESF systems outside containment, and

3. Main steam isolation valve (MSIV) leakage.

The changes that are made to each of these pathways are discussed in detail below. In addition, the effect of the changes to parameters, inputs and assumptions on the following items is also addressed below:

4. Control Room Model

5. Reactor Core Inventory

6. Co-60 ITA Safety Analysis Report (NEDC-33529P, Section 4.3)

7. Radiological Consequences Table 1 contains a summary of the major parameters, inputs and assumptions, and compares the parameters, inputs and assumptions used in the LOCA analysis in Amendment 174 to those used in the current analysis to support the Co-60 LAR. The resulting doses at the Exclusion Area Boundary (EAB), the outer boundary of the Low Population Zone (LPZ) and in the control room (CR) are shown in Table 2. All doses are within the limits specified in 10 CFR 50.67.

1. Containment Leakage Pathway The radioactive material released from the core enters the drywell atmosphere and is mixed in the drywell and wetwell (suppression chamber) volumes. It subsequently leaks from primary containment to the secondary containment and then leaks to or is exhausted to the environment. All of the assumptions and parameters used in the Co-60 LAR to I

evaluate the amount of activity released through this pathway remain the same as Amendment 174 assumptions and parameters, except as indicated below.

Containment Leak Rate In Amendment 174 the containment leak rate was established as 0.5% per day in accordance with the plant's Technical Specifications. At 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following the accident, the leak rate was reduced by a factor of two to 0.25% per day based on the reduction in pressure in the containment.

In the Co-60 LAR the assumption of a reduction in leak rate at 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months was eliminated.

The containment leak rate is set to 0.5% per day at the start of the accident and remains constant over the course of the accident (30 days). This is a conservative change in the containment leakage pathway model since it increases the amount of activity released from the containment and therefore increases the dose.

Mixing in Primary Containment In Amendment 174 it is assumed that the activity released to the drywell atmosphere is instantaneously mixed in the total primary containment volume (the sum of the drywell and wetwell volumes).

In the Co-60 LAR it is assumed that initially the activity released to the drywell is uniformly mixed in the volume of the drywell only. After two hours, it is assumed the activity is mixed in the total primary containment volume. This change was made based on the recognition that processes that cause mixing between the drywell and wetwell (e.g., blowdown to the suppression pool, operation of vacuum breakers, etc.) do not operate continuously, although eventually there should be fairly good mixing between the two volumes. Assuming that there is no mixing for the first two hours conservatively accounts for the time dependent nature of the mixing. It is more conservative than the Amendment 174 assumption since the concentration in the activity released from the containment is higher for the first two hours, causing an increase in doses.

Plateout of Elemental Iodine on Containment Surfaces Amendment 174 does not take credit for removal of any activity from the containment atmosphere, except for removal of aerosol activity by natural deposition. No credit is taken for the activity that may be removed by the operation of the containment sprays, even though it is likely they will be operating following a LOCA. The Co-60 LAR also does not credit operation of the containment sprays for activity removal.

The Co-60 LAR includes the deposition (normally called plateout) of elemental iodine on the surfaces inside containment in accordance with the guidance of Standard Review Plan (SRP) 6.5.2. The formulation in SRP 6.5.2,Section III.4.C.i., is used to calculate the containment elemental iodine removal coefficient. The reduction of the airborne elemental iodine is consistent with the guidance provided in RG 1.183. Specifically, 2

Section 3.3 of Appendix A of RG 1.183 allows credit for removal of airborne radioactivity, including both elemental and aerosol radioactivity, inside containment by natural deposition. The Amendment 174 analysis does take credit for aerosol deposition, but does not include elemental iodine plateout. The addition of the elemental iodine plateout is consistent with the regulatory guidance that was applied in Amendment 174.

The chemical properties of the water film (such as the pH) on the wetted surfaces inside containment are not considered in the plateout model. The technical basis for the plateout model is described in NUREG/CR-0009. The model does not include any explicit consideration of the water film and is therefore not dependent on the chemical properties of the water film. The rationale for not considering the water film is that the iodine is ultimately absorbed on the surface and is not retained in the water. The water film layer is too thin to appreciably retard the iodine absorption process on the surface, regardless of the reactivity of the liquid. Since the iodine is deposited on the surface rather than absorbed in the water, the potential for re-evolution from the water film is not part of the model. In addition, the overall absorption capacity of the containment surfaces is larger than required to absorb all the iodine transported to the surfaces, so re-evolution of iodine from the containment surfaces is not expected.

The containment spray system may recirculate suppression pool water, which contains iodine, into the drywell. However, the pH of the suppression pool water will be greater than 7, which will prevent iodine in the suppression pool water from re-evolving to the containment atmosphere. Therefore, containment spray water that ends up on the containment surfaces will not be a source for re-evolution of elemental iodine.

The amount of elemental iodine removed from the containment atmosphere is limited by a decontamination factor (DF) of 200 as specified in SRP 6.5.2. The DF is intended to limit the amount of elemental iodine removed from the atmosphere to account for some re-evolution from the sump or suppression pool. Although re-evolution of elemental iodine activity deposited on the containment surfaces is not expected, the amount of elemental iodine removed from the containment atmosphere is limited by the DF of 200.

The use of the elemental iodine plateout model will result in a smaller amount of radioactivity available for release from the containment. Since this will result in lower doses, this change to the containment leakage model is non-conservative.

2. Post-LOCA ESF Systems Leakage Pathway This leakage pathway involves the circulation of suppression pool water in ESF systems outside the primary containment. The components of the ESF systems are expected to leak, and the amount of leakage is monitored and controlled by a Technical Specification required program. All of the assumptions and parameters used in the analysis for the Co-60 LAR are the same as the assumptions and parameters used in the analysis for Amendment 174, except as described below.

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ESF Leak Rate Amendment 174 assumes an ESF leak rate of 1 gpm, which is doubled in the ESF systems leakage pathway model. The Co-60 LAR assumes an ESF leak rate of 2.85 gpm, which is also doubled in the ESF systems leakage pathway model. The change in leak rate was made to provide operational margin. The assumed leak rate of 2.85 gpm has been incorporated as acceptance criteria in Hope Creek's leakage reduction program, which is maintained in accordance with Technical Specification 6.8.4.a. The use of a higher leak rate is conservative since it results in more activity released to the environment and, therefore, higher doses.

3. MSIV Leakage Pathway The main steam lines penetrate both the primary and secondary containment boundaries and therefore represent a release pathway that bypasses secondary containment. The main steam lines at Hope Creek include the inboard MSIV, the outboard MSIV and the turbine stop valve (TSV). The post-LOCA flow rate through these valves is based on the Technical Specification leak test limit of 250 scfh, with a maximum leak rate through any one valve of 150 scfh. To be conservative, it is assumed that one steam line ruptures between the reactor pressure vessel (RPV) and the inboard MSIV. This is referred to as the failed line. Then it is assumed that the inboard MSIV also fails on the failed line, and the maximum amount of leakage (150 scfh) is through the failed line. The remaining lines are referred to as the intact lines, and the remaining leakage (100 scfh) is through these lines. All of the assumptions and parameters used in the analysis for the Co-60 LAR are the same as the assumptions and parameters used in the analysis for Amendment 174, except as described below.

Steam Line Volumes The steam line volume refers to the volume used in the release model. In Amendment 174, the volume of the failed line was based on the shortest steam line, and was the volume of the steam line between the RPV and the TSV, reduced by the volume between the inboard and outboard MSIV. For the intact lines, two lines were assumed. The volumes were based on the next two shortest steam lines and the steam line volumes between the RPV and the TSV.

For the Co-60 LAR, the failed steam line volume is based on the volume between the outboard MSIV and the TSV. This change was made to conservatively ignore deposition in the portion of the steam line that is open to the drywell (i.e., the volume between the inboard and outboard MSIVs). The drywell atmosphere in this pipe segment may be reduced by deposition, but the activity could be replaced by higher activity drywell air.

The most conservative approach is to ignore deposition in the volume between the inboard and outboard MSIVs. Similarly for the intact steam line, the volume is the volume between the outboard MSIV and the TSV, which conservatively ignores the steam line between the RPV and the inboard MSIV, which can communicate directly to the drywell atmosphere, and conservatively ignores the volume between the inboard and 4

outboard MSIVs. Also, the Co-60 LAR only considers one steam line with a flow rate of 100 scfh rather than two steam lines with a flow rate of 50 scfh each.

The change in deposition volume has two effects on the MSIV leakage model. First, the smaller volumes result in a more rapid turnover of the activity in the deposition volume, decreasing the holdup time and the corresponding decay of radioactivity. This is also the effect of using a single intact steam line since the total volume of the intact steam lines is smaller. Second, the effective removal efficiency for the steam line is decreased because the deposition area of the smaller volumes is smaller. Therefore, these changes to the steam line volumes are conservative because they lead to an increase in the amount of activity released and, therefore, an increase in dose.

Steam Line Flow Rates The steam line flow rates are based on leak testing limits for the MSIVs, which are given in scfh (standard cubic feet per hour). The LOCA analysis for Amendment 174 uses the Technical Specification limits directly as inputs to the model. These values are based on standard conditions of atmospheric pressure and temperature (68 'F, 14.7 psia).

The alternative to using the flow rates at standard conditions is to use the flow rates that correspond to the test conditions that are assumed in the surveillance procedure that is used to demonstrate compliance with the Technical Specification. This is the recommended approach in RIS 2001-19. In the analysis for the Co-60 LAR, the leak rates into the steam lines are adjusted for the peak pressure and temperature in containment. The resulting change in flow rates is shown in Table 1. The total flow rate into the steam lines changes from 4.167 cfm (250 scfh at standard conditions) to 1.346 cfm (250 scfh at containment conditions). The decrease in flow rate is consistent with RIS 2001-19; however, it is non-conservative since it results in less activity entering the steam lines and available for release to the environment.

A similar change is made to the flow rates out of the steam lines to the environment. In Amendment 174, the total flow rate is 250 scfh. In the analysis for the Co-60 LAR, the flow rate out of the steam lines is based on a steam line temperature of 550 'F and atmospheric pressure. The steam line temperature of 550 'F is bounding for the operating steam line temperature of 546 'F identified in the HCGS line index. As indicated in Table 1, this results in an increase in the flow rate out of the steam lines from 4.167 cfm (250 scfh at standard conditions) to 7.966 cfm (250 scfh at steam line conditions). This is a conservative change to the MSIV pathway model since it decreases the holdup time in the steam line, resulting in less decay, more activity released to the environment and higher doses.

In the analysis that supported Amendment 174, the steam line flow rate was set at maximum values initially and then reduced by a factor of two at 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . As discussed in the containment leakage model, this was changed in the Co-60 LAR to use the maximum values for the duration of the accident. This is a conservative change since more activity is released to the environment, resulting in higher doses.

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The net effect of the changes to the MSIV flow rates is non-conservative. The change to the flow rate out of the steam line is conservative and not reducing the flow rate at 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is conservative, but the non-conservative decrease in flow rate into the steam line is the more significant change, causing the amount of radioactivity released to the environment and the resulting doses to decrease.

Steam Line Flow Model There are two flow models that are commonly used to model the transport of the containment atmosphere through the steam lines. The first is the plug flow model, which assumes that all activity that enters the steam line moves at the same flow rate down the length of the steam line (no mixing). Thus the residence time in the steam line (the holdup time) is determined by the flow rate and the steam line volume. The second is the well mixed model described in AEB-98-03. This model assumes that when activity enters a steam line volume, it is uniformly mixed throughout the volume, so that some of the activity is available for release immediately from the steam line.

The analysis for Amendment 174 assumes plug flow through the steam lines, whereas the analysis used to support the Co-60 LAR assumes a well mixed model. Because of the shorter holdup time for the well mixed model, the change would be conservative because it results in more radioactivity released to the environment and a higher dose.

Steam Line Deposition Area The analysis for Amendment 174 assumes the entire internal surface of the steam line is available for aerosol deposition. Since the primary method for deposition of aerosols is gravitational settling, it is logical that the deposition would occur only on the bottom of the steam line. In the analysis used to support the Co-60 LAR, the deposition area was changed to the projected horizontal area of the steam line, which is consistent with the guidance provided in RIS 2006-04 and is conservative compared to the total inside surface area since it decreases the effective removal efficiencies of the steam lines.

Steam Line Deposition Rates and Removal Efficiencies The analysis in Amendment 174 credits aerosol deposition in the steam lines for the duration of the accident. In the analysis used to support the Co-60 LAR, credit for deposition of both elemental and aerosol activity is terminated at 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months , even though the release continues out to 30 days. This is conservative since more activity is released to the environment resulting in higher doses.

The aerosol effective removal efficiencies are recalculated for the change in steam line volume indicated above. The aerosol effective removal efficiencies are also a function of the flow rate through the main steam line. The recalculated aerosol effective removal efficiencies are based on the flow rate from the steam line to the environment, which is maximized by using a steam line temperature of 550 'F for the duration of the accident.

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For the elemental iodine removal efficiencies, the steam line volumes used to calculate the removal efficiencies are slightly larger than the volumes used for the aerosol removal efficiencies. This may be slightly non-conservative, but since the elemental iodine removal efficiency is based on the ratio of surface area to volume, this effect will be very small.

The elemental iodine removal efficiencies are also based on the time dependent temperature in containment. The same time dependent temperature distribution was used in the analyses for both Amendment 174 and the Co-60 LAR. It is recognized that initially the steam line will be at a higher temperature than the containment, and that it will take some time for the steam line temperature to come into equilibrium with the containment atmosphere. The higher temperature decreases the deposition velocity for elemental iodine, so not considering the steam line temperature in the evaluation of the effective removal efficiencies for elemental iodine is non-conservative. To evaluate the effect of a higher steam line temperature over a longer period of time, an evaluation was performed using an elemental removal iodine efficiency based on 550 'F for the first 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months (no credit is taken for either aerosol deposition or elemental iodine removal in the steam lines after 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months ). The extended use elemental iodine removal efficiencies based on the high steam line temperature causes total dose increases from about 1% for the control room to about 2% for the EAB. Although the effect is small, it is not insignificant.

However, the assumptions used to address the steam line temperature are conservative.

In particular, the flow rate from the drywell into the steam line is based on a constant temperature of 298 'F for the duration of the accident, even though the drywell temperature will drop below this value within a few hours. This conservatively overestimates the amount of activity entering the steam line. The flow rate out of the main steam line is also based on constant temperature, which is the maximum steam line temperature, even though this temperature will decrease substantially over the course of the accident. This produces a conservative estimate of the aerosol effective removal efficiency. It also produces a shorter holdup time in the steam line, which is conservative. In addition, although the steam line temperature and pressure will be higher than the drywell pressure and temperature for the first part of the accident, inhibiting flow through the steam line, assuming that the maximum flow through the steam line starts at the beginning of the accident (time = 0) is conservative.

The use of the constant maximum steam line temperature to estimate the elemental iodine removal efficiencies is conservative since the steam line temperature will drop to drywell conditions within the first 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months of the accident. Using a more realistic steam line temperature profile will result in an increase in the elemental iodine removal efficiency which will result in doses that are less the doses calculated for a constant steam line temperature. Given the small effect of constant temperature elemental iodine removal on the doses, the use of the drywell temperature profile for the iodine removal efficiency, as described in Revision 4 of calculation 1H-1-ZZ-MDC-1880, when combined with the 7

conservative assumptions described above results in a conservative estimate of the doses due to releases through the MSIV leakage pathway.

4. Control Room Model The calculation of the post-LOCA doses to the control room operator includes credit for the operation of the control room emergency filter system (CREFS). The assumptions and parameters used in the control room model for the Co-60 LAR are the same as the assumptions and parameters used in the analysis to support Amendment 174, except as indicated below.

Control Room Unfiltered Inleakage The control room unfiltered inleakage use in the analysis to support Amendment 174 is 350 cfm. In the analysis to support the Co-60 LAR, the unfiltered inleakage was decreased to 250 cfm. The amount of unfiltered inleakage is a plant specific parameter that is confirmed by testing performed in accordance with the Control Room Envelope Habitability Program, which is implemented in accordance with Technical Specification 6.16. Control room inleakage tests indicate that there is less than 200 cfm of inleakage into the Hope Creek control room and that essentially all of the inleakage is filtered. As part of the implementation of the Co-60 LAR the acceptance criterion in the procedure for control room inleakage testing will be changed to 250 cfm.

The control room inleakage parameter determines the amount of activity that bypasses the control room intake filter and enters the control room directly. Therefore it has a large effect on the control room dose. The change to the control room model is non-conservative because decreasing the amount of unfiltered inleakage decreases the amount of activity entering the control room and therefore decreases the dose to the control room operator.

5. Reactor Core Inventory Reactor Power Level The core inventory used in the analysis that is the basis for Amendment 174 is based on a reactor power level of 4031 MWt and a maximum discharge bundle exposure. The core inventory used in the analysis to support the Co-60 LAR is based on a reactor power level of 3917 MWt and the average core inventory. This reactor power level is the current licensed power level of 3840 MWt plus 2% for instrument uncertainty, consistent with RG 1.183. The lower power level reduces the amount of activity in the core that is available for release and therefore reduces the doses, although the change in burnup associated with the change from maximum discharge bundle to core average will also affect the amount of activity available for release. The net effect of the two changes is expected to be small (less than 3%).

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Effect of ITAs The model used in the LOCA analysis for the Co-60 LAR does not include any increase in the Co-60 source term that may be caused by the Co-60 Isotope Test Assemblies (ITA) included in the Co-60 LAR. As discussed below, Attachment 14.2 to calculation H ZZ-MDC-1880, Revision 4, demonstrates that the effect of the ITAs is negligible.

6. Co-60 ITA Safety Analysis Report (NEDC-33529P, Section 4.3)

Section 4.3.4 (LOCA)

NEDC-33529P Section 4.3.4 provides a sensitivity evaluation on the effect of adding the Co-60 ITA to the HCGS core, based on Revision 3 of the LOCA dose calculation, H-I-ZZ-MDC-1 880. It was concluded there is negligible impact. Attachment 14.2 to calculation H-1-ZZ-MDC-1 880, Revision 4, demonstrates that the effect of the ITAs is also negligible.

The impact of 12 GE14i assemblies on the HCGS licensing basis LOCA source term and radiological consequences was evaluated. The Co-60 ITA activity was conservatively increased to account for uncertainty in release of Co-60 present in high concentrations in the cobalt isotope rods. This evaluation determined control room, EAB, and LPZ doses due to post LOCA radioactivity releases from containment via three release pathways, i.e., containment leakage, ESF leakage, and MSIV leakage using the combined core inventory including the inventory from 12 Co-60 Isotope Test Assemblies. The addition of the Co-60 ITA inventory had negligible impact. The resulting dose consequences remained essentially unchanged.

The additional changes incorporated into the Technical Evaluation 80102291-0040 will not alter the conclusions of Attachment 14.2 that the resulting dose consequences remain unchanged. There is no change to the Co-60 ITA inventory; the increase in the doses due to the additional Co-60 activity is insignificant.

Section 4.3.1 (CRDA)

The changes to the LOCA analysis model have no impact on the CRDA evaluation provided in NEDC-33529P. The evaluation results and conclusions in Section 4.3.1, based on the Calculation H-1-CG-MDC-1795 (Revision 5). "Control Rod Drop Accident Radiological Consequences," remain unchanged. The changes to the LOCA analysis do not affect the CRDA analysis. This includes assumed control room inleakage, the CRDA analysis did not credit CREFS initiation. Revision 5 of the CRDA calculation only corrected typographical errors; Revision 4 was previously docketed to support the HCGS EPU Amendment 174. Therefore the parameters, inputs and assumptions used in Amendment 174 remain valid.

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7. Radiolouical Conseauences The post-LOCA radiological consequences for the analysis to support the Co-60 LAR are shown in Table 2, along with the corresponding doses from Amendment 174. This table illustrates that the radiological consequences are smaller than the limits of RG 1.183 and 10 CFR 50.67. The effect of the changes to the LOCA model on each release pathway is discussed below. In addition to these changes, the change in the core inventory will have a small effect on the dose consequences.

Containment Leakage The dose contribution from containment leakage in the Co-60 LAR analysis is about the same as the analysis for Amendment 174 for the EAB and LPZ. This is because the increase in radioactivity released to the environment caused by (1) maintaining the containment leak rate constant (rather than decreasing it at 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ), and (2) dilution in the entire containment volume at two hours, is offset by the reduction in elemental iodine available for release to the environment because of plateout on containment surfaces.

The control room dose, however, is reduced by nearly a factor of two. This is the effect of decreasing the unfiltered control room inleakage rate.

Post-LOCA Leakage from ESF Systems Outside Containment The dose contribution of ESF leakage in the Co-60 LAR analysis is increased by nearly a factor of three over the Amendment 174 analysis due to the increase in ESF leak rate from 1 gpm to 2.85 gpm. The increase in the control room dose is less because of the effect of the decrease in unfiltered inleakage.

MSIV Leakage The dose contribution from MSIV leakage in the Co-60 LAR analysis remains about the same as the Amendment 174 analysis for the EAB and LPZ. This is because the changes to the MSIV leakage model that increase leakage, including (1) decreasing the steam line volume and deposition area, (2) not reducing the leak rate at 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , (3) not crediting deposition after 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months , and (4) increasing the flow rate from the steam line to the environment, are offset by the changes that decrease leakage, including (1) the decrease in flow rate from the containment into the steam line due to the use of containment conditions rather than standard conditions, and (2) plateout of elemental iodine in containment, which reduces the amount of iodine available for leakage. The control room dose is decreased by a factor of two due to the change in assumed unfiltered control room inleakage.

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Table 1. Parameters and Assumptions Used in Radiological Consequence Calculations for a LOCA Parameter SER Am 174 Value Co-60 LAR Value 4,031 MWt (max. discharge bundle Reactor power exposure) 3 3917 MWt 3(Core Average)

Drywell air volume 1.69E+5 ft 3 1.69E+5 ft 3 Containment air volume 3.06E+5 ft 3.06E+5 ft Primary Containment Dilution Volume 3 3 0 - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 3.06E+5 ft 1.69E+5 ft 3 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months - 30 days 3.06E+5 ft3 3 3.06E+5 ft3 Reactor building air volume 4.OE+6 ft 4.OE+6 ft Containment leak rate to environment 0 -24 hours 0.5% per day 0.5% per day

-30 days 0.25% per day 0.5% per day Reactor building pressure drawdown time 375 seconds 375 seconds Aerosol deposition rate in drywell 10 percentile in RADTRAD 10 percentile in RADTRAD Elemental iodine deposition rate in containment Not credited SRP 6.5.2 Methodology Elemental iodine decontamination factor Not credited 200 Reactor building mixing efficiency 50% 50%

FRVS vent exhaust filter efficiencies Elemental iodine 90% 90%

Organic iodine 90% 90%

Aerosol (particulate) 99% 99%

FRVS recirculation filter efficiencies Elemental iodine Not credited Not credited Organic iodine Not credited Not credited Aerosol (particulate) 99% 99%

FRVS recirculation flow rate 1.08E+5 cfm 1.08E+5 cfm ECCS leak rate 1 gpm 2.85 gpm ECCS iodine partition factor 10% 10%

ECCS leak initiation time 0 minutes 3 0 minutes 3 Sump volume 1.18E+5 ft 1.18E+5 ft I1

Table 1. Parameters and Assumptions Used in Radiological Consequence Calculations for a LOCA Parameter SER Am 174 Value Co-60 LAR Value MSIV leak rate Into Steam Line All four lines 250 scfh (4.167 cfm) 250 scfh (1.347 cfm)

Line with MSIV failed 150 scfh (2.50 cfm) 150 scfh (0.808 cfm)

First intact line 50 scfh (0.8333 cfm) 100 scfh (0.539 cfm)

Second intact line 50 scfh (0.8333 cfm)

MSIV leak rate To Environment All four lines 250 scfh (4.167 cfm) 250 scfh (7.966 cfm)

Line with MSIV failed 150 scfh (2.50 cfm) 150 scfh (4.783 cfm)

First intact line 50 scfh (0.8333 cfm) 100 scfh (3.183 cfm)

Second intact line 50 scfh (0.8333 cfm)

Aerosol settling velocity on main steamlines 8.1 E-4 meters/second 8.1 E-4 meters/second Aerosol settling area (well-mixed region volumes) 3 3 MSIV faulted line 1398 ft3 1065 ft 3 MSIV intact lines 1476 ft 1062 ft Steam line transport model Plug flow Well mixed Steam line deposition period 0 - 30 days 3 0 - 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months Control room volume 8.5E+4 ft 8.5E+4 ft3 CREFS outside air intake flow 1000 cfm 1000 cfM CREFS recirculation flow 2600 cfm 2600 cfm Control room isolation time 30 minutes 30 minutes Unfiltered air in leakage rate into control room 0 to 30 minutes 500 cfm 500 cfm 30 minutes to 30 days 350 cfm 250 cfm CREFS filter efficiencies Elemental iodine 99% 99%

Organic iodine 99% 99%

Aerosol (particulate) 99% 99%

12

Table 2. Post-LOCA Dose (rem-TEDE)

Post-LOCA Co-60 LAR Value SER Am 174 Value Activity Release Control EAB LPZ Control EAB LPZ Path Room Room Containment Leakage 5.28E-01 3.87E-01 1.47E-01 1.05E+00 3.73E-01 1.62E-01 ESF Leakage 2.42E+00 5.22E-01 2.64E-01 1.25E+00 1.91 E-01 9.79E-02 MSIV Leakage 9.99E-01 2.20E+00 4.79E-01 2.13E+00 2.63E+00 4.56E-01 CR Filter Shine 1.29E-02 O.OOE+00 0.OOE+00 2.46E-03 O.OOE+00 O.OOE+00 Total 3.96E+00 3.11IE+00 8.90E-01 4.43E+00 3.19E+00 7.16E-01 10 CFR 50.67 Limit 5.OOE+00 2.50E+01 2.60E+01 5.OOE+00 2.50E+01 2.50E+01 13 LR-N10-0341 Technical Evaluation 80102291-0030 Effect of Water Chemistry on the Plateout of Elemental Iodine in Containment

Document Number: Technical Evaluation 80102291-0030

Title:

Effect of Water Chemistry on the Plateout of Elemental Iodine in Containment 1.0 REASON FOR EVALUATION / SCOPE:

PSEG letter LR-N10-0306 (Reference 1) transmitted to the NRC responses to requests for additional information related to license amendment request H09-01 supporting the use of Co-60 isotope test assemblies. Attachment 2 to LR-N10-0306 is Revision 4 to calculation H-1-ZZ-MDC-1880, "Post-LOCA EAB, LPZ and CR Doses" (Reference 2). The NRC has identified additional issues associated with this calculation. The purpose of this evaluation is to address the following draft discussion issue identified by the NRC:

Issue: "Application of the SRP 6.5.2, "Containment Sprays as Fission Product Cleanup System," elemental iodine removal model."

Discussion: "A fundamental justification for applying this method to BWR containments should be provided. Consideration of the lack of a credited spray system, pH vs. time for the credited surfaces, and the transport of buffered water to the credited deposition surfaces, etc., needs to be addressed..."

2.0 METHODOLOGY The resolution of this issue requires a discussion of the effect of the chemistry of the water that is on the wetted surfaces inside containment on the elemental iodine wall deposition model in Standard Review Plan (SRP) 6.5.2 (Reference 3). The approach is to review and evaluate the technical basis for the SRP 6.5.2 model to determine whether the chemistry of the water affects the model. If there are no effects, then evaluation of the chemical properties of the water on the wetted surfaces inside containment is not required.

3.0 EVALUATION Section 2.1.2 of calculation H- 1-ZZ-MDC- 1880, Revision 4, describes reduction of airborne activity inside containment. It includes the deposition of elemental iodine on the walls inside containment in accordance with the guidance of SRP 6.5.2. As documented in Section 7.11 of the calculation, the formulation in SRP 6.5.2,Section III.4.C.i., is used to calculate the containment elemental iodine removal coefficient. The SRP does not identify a specific reference for the wall deposition model, although previous revisions to the SRP cited page 17 NUREG/CR-0009, "Technological Bases for Models of Spray Washout of Airborne Contaminants in Containment Vessel," (Reference 4). The current revision of the SRP contains NUREG/CR-009 in the Reference Section. A review of NUREG/CR-0009 determined that the issue of deposition of elemental iodine on containment walls is addressed in Section 5.1.2 of the NUREG. The pages from NUREG/CR-0009 that address the wall plateout model are included as Attachment 1. Equation (14) on page 17 of NUREG/CR-0009 is 1

identical to the equation of wall deposition in SRP 6.5.2 Section III.4.C.i, page 6.5.2-11. Therefore it is concluded that NUREG/CR-0009 is the technical basis for the SRP 6.5.2 wall deposition model.

The technical basis for the washout models is discussed in Section 6 of NUREG/CR-0009. Section 6.1.9 specifically addresses the wall deposition of elemental iodine. Section 6.1.9 of NUREG/CR-0009 is included as Attachment 2. The transport model involves four distinct transport processes that occur in sequence. These processes are bulk gas transport, gas boundary transport, liquid film transport and adsorption on the wall surface, as illustrated in the following figure from page 63 of NUREG/CR-0009, below.

NUREG-CR-0009 CENTER OF PROTTECTIVE PA INT GAS SPACE I

WATER FILM I' TRANSPORT IN WATER FILM, fL~

/i41 ,GAS BOUNDARY LAYER

. .. BULK GAS TRAN!SPORT .

'I 4 SORPTION INPAINT

',GAS BOUNDARY LAYER TRANSPORT

/1 STEEL ~iALL

,FIGURE 6. Schematic Representation of Iodine Surface Deposition The discussion in NUREG/CR-0009 indicates that the controlling step is the transport through the gas boundary layer. The other processes are not considered limiting for the following reasons.

" The bulk gas phase is well mixed (NUREG/CR-0009, pg 63). Mixing is induced by thermal gradients, operation of sprays or thermally generated steam flows. Therefore, mass transfer through the bulk gas phase is not expected to be a controlling factor in iodine plateout.

It is expected that the walls inside containment will be covered with water. NUREG/CR-0009 indicates only part of the containment surfaces may be covered with water. This is different from SRP 6.5.2, which refers to wetted-surface area. However, the water film would be too thin to appreciably retard the iodine absorption process (NUREG/CR-0009, page 65).

Ultimately the iodine sorbs onto the exposed surfaces, where it is held by both chemical reaction and by physical solubility. Since the overall absorption capacity of the surfaces is larger than 2

required to absorb all the iodine transported to the wall, sorption will not limit wall deposition (NUREG/CR-0009, page 68).

As discussed above, the controlling step in the process is the transport through the gas boundary layer.

For this reason, the SRP 6.5.2 removal coefficient for wall deposition is a function of containment volume, wall surface area and the mass transport coefficient for the gas boundary layer.

The technical basis for the SRP model does not include any explicit consideration of the water film and is therefore not dependent on pH. The rationale for not considering the water film is that the iodine is ultimately absorbed on the wall surface and is not retained in the water. As indicated on page 65 of NUREG/CR-0009, the water film layer is too thin to appreciably retard the iodine adsorption process on the wall, regardless of the reactivity of the liquid. Since the iodine is deposited on the wall rather than absorbed in the water, the potential for re-evolution from the water film is not part of the model. In addition, the overall absorption capacity of the containment surfaces is larger than required to absorb all the iodine transported to the wall, so re-evolution of iodine from the containment surfaces is not expected (NUREG/CR-0009, page 68).

Section 2.1.2 of calculation H-1-ZZ-MDC-1880 contains a discussion about the effects of the operation of contai-nent spray system on elemental iodine. The containment spray system may recirculate suppression pool water, which contains iodine, into the drywell. However, the pH of the suppression pool water will be greater than 7, which will prevent iodine in the suppression pool water from re-evolving to the containment atmosphere. Therefore, containment spray water that ends up on the containment surfaces will not be a source for re-evolution of elemental iodine.

The amount of elemental iodine removed from the containment atmosphere is limited by a decontamination factor (DF) of 200. The DF is intended to limit the amount of elemental iodine removed from the atmosphere to account for some re-evolution from the sump or suppression pool.

Although re-evolution of elemental iodine activity deposited on the containment surfaces is not expected, the amount of elemental iodine removed from the containment atmosphere is limited by the DF of 200.

4.0 CONCLUSION

S Based on the evaluation presented above, it is concluded that the technical basis for the SRP 6.5.2 elemental iodine wall deposition model is NUREG/CR-0009. The elemental iodine wall deposition model is independent of the chemistry of the water film on the containment surfaces. Therefore it is not necessary to address the chemistry of the water film, which includes the pH versus time and the transport of buffered water to the credited surfaces to maintain the pH.

5.0 REFERENCES

1. "Response to Request for Additional Information - License Amendment Request (H09-01)

Supporting the Use of Co-60 Isotope Test Assemblies (Isotope Generation Pilot Project),"

PSEG Nuclear LLC letter LR-NI 0-0306, August 12, 2010

2. Hope Creek Calculation H-l-ZZ-MDC-1880, "Post-LOCA EAB, LPZ and CR Doses,"

Revision 4

3. U.S. Nuclear Regulatory Commission, NUREG-0800 Standard Review Plan 6.5.2, "Containment Spray as a Fission Product Cleanup System," Revision 4 3

4. A.K. Postma, R.R. Sherry, and P.S. Tam, "Technological Bases for Models of Spray Washout of Airborne Contaminants in Containment Vessel," NUREG/CR-0009, October 1978 6.0 ATTACHMENTS 6.1 Attachment 1: NUREG/CR-0009, Section 5.1.2 6.2 Attachment 2: NUREG/CR-0009, Section 6.1.9 4

t -Cv ktuL+-ý 6 v) 's 6 j b -;? ----

29 1- D6 3o 7.0 IGNATURES Preparer: Date: .08/26/2010 5.iAJ Johnson (S&L)

Chemnistry Reviewer: Date: 08/26/2010 Mark W. Meltzer Independent Reviewer :~ araS t Date: 08126/2010 SAmlh y G. Klt~ura (S&L)

PSEG Nuclear Owner Acceptance: Date: 08/26/2010 Iobn 0 1)DuffyJ\

gim Approved: Date: I .1 Qt S.Boyer

~- .A~,

S - ~ ~

4-4

TE 80102291-0030, Attachment 1 NUREG-CR-0009 by the staff, but could find application in realistic analyses of spray performance.

5.1.2 Deposition of Iodine on Interior Containment Surfaces Surface deposition of iodine occurs as the result of several transport processes which occur in series. Regions of transport include: the bulk gas phase, the gas boundary layer, the liquid film, and the solid wall surface. Of these, transport in the gas boundary layer has been shown to be the controlling step(29)

S Several models have been proposed to describe product removal due to surface deposition. Of these, fission the Knudsen-Hilliard (30) model and the Yuille-Baston (31) model appear to be in good agreement with available experiments.

The Knudsen-Hilliard model views deposition as a gas film I transport process to vessel surfaces. The gas film mass transfer coefficient is predicted from natural convection heat transfer correlations by a mass transfer-heat transfer analogy. The Yuill-Baston model is based on the pene-tration theory for mass transfer, and uses a natural convection heat transfer model to estimate gas flow velocities. Of the two models, the Knudsen-Hilliard model offers several advantages and has been adopted by the staff.

In the Knudsen-Hilliard model, the bulk gas in the containment atmosphere is assumed to be well-mixed by natural convection, by steam flows, and by spray opera-tion. A gas boundary layer is established adjacent to 15

iia NUREG-CR-0009 containment surfaces. For a laminar boundary layer the mass transfer coefficient across the gas boundary layer is predicted by

~kL g - 0.59(Gr Sc) 4 (12)

D where kg film mass transfer coefficient, L = length measured along deposition surface, D = diffusivity of iodine in gas phase, Gr = Grashov number, Sc = Schmidt number.

For turbulent boundary flow, the mass transfer coefficient is predicted using

~kL (Gr Sc)I/ 3 (13)

_9__ = 0.13 D

The transition from laminar flow to turbulent flow occurs at a critical Grashov number. Important variables in the Grashov number include length, L, and temperature difference between the gas and the wall surface. There-fore the plate length at which the flow transition occurs depends on thermal conditions in the containment vessel.

Hilliard and Coleman (32) found that Containment System Experiment tests were best explained by assuming that transition from laminar to turbulent flow occured ten feet from the top of the test vessel. This value was in good agreement with predicted transition lengths.

These transition lengths apply for thermal conditions which occur after blowdown transients are over, and

16

NUREG-CR-0009 where heat transport takes place with gas film temperature differences of 1lF to 2 0 F. They would conservatively apply to post-LOCA situations consistent with spray opera-tion.

The iodine removal rate constant for a particular compartment in the containment is given by k A A=_9 (14) n V where X = removal rate constant due to surface n

deposition, k g = average mass transfer coefficient, A = surface area for wall deposition, V = volume of contained gas.

As is described in section 6.1.9, the value of k should not exceed 0.137 cm/sec. This maximum value is based on CSE tests, and its use assures that the predicted deposition rates remain within the range where the Knudsen-Hilliard model applies.

S 5.1.3 Overall Absorption Rate The overall removal rate is the sum of that due to spray operation and natural convection plate-out:

XS + Xn (15)

Thus the airborne concentration at any time, t, after the release of an instantaneous source term is 17

TE 80102291-0030, Attachment 2 NUREG-CR-0009 For sodium hydroxide solutions at pH of 9.5, available information suggests that H 0 is greater than 5000 Calculations made using an Ho value of 5000 will result in conservative estimates of iodine washout.

Hydrazine, in low concentration levels, has also been studied experimentally(17,33) and use of H 0 equal to 5000 assures conservative predictions for hydrazine sprays.

Sodium thiosulfate at 1% by weight, has been studied by a number of investigators( 16 ' 19 ' 33 ' 52 ) Of the spray solutions designed for use in containments, the basic thiosulfate solution is the most powerful from a chemical reduction standpoint. Use of an instantaneous partition coefficient of 100,000 appears to be justified.

6.1.9 Deposition of Iodine on Containment Surfaces Surface deposition of iodine occurs as the result of several transport processes which occur in series. These are depicted in Figure 6.

Each of the transport steps shown in Figure 6 is potentially important in gas absorption, and each will he briefly discussed in relation to iodine absorption under accident conditions.

62

NUREG-CR-0009 CENTER OF PAINT GAS SPACE I

FILM WATER FILM 1 GAS BOUNDARY LAYER I, Pill V CA*

TRANSPORT GAS BOUNDARY LAYER TRANSPORT WALL FIGURE 6. Schematic Representation of Iodine Surface Deposition Mass Transfer in the Bulk Gas Phase Transport of iodine molecules from the bulk of the gas space over to a boundary layer represents the longest transport step from a physical size standpoint. Such transport would be dominant if the bulk gas were stagnant.

However, numerous experiments in containment vessels( 3 0 ' 3 2' have demonstrated that in a single compartment, the bulk gas phase is well mixed. The mixing is induced by thermal gradients, by operation of sprays or air cleaners, and by 63

~.,: ~

0 NUREG-CR-0009 thermally generated steam flows. As shown by large scale experiments(32) only very small thermal sources are re-quired to mix a large vessel to the point where boundary layer transport dominates. Therefore, mass transfer through the bulk gas phase is not expected to be a con-trolling factor in iodine plateout in a single compartment of a containment vessel.

It should be noted that internal surfaces, such as those presented by shield walls, would trap iodine as well as the outer containment wall. In large scale CSE tests, the total exposed surface was about twice that afforded by the outer vessel walls, and all of the surface had to be accounted for to obtain agreement between theory and experiment (32) Therefore the discussion of surface deposition presented here applies to all massive structures in the containment along which natural convective flows can freely develop.

Gas Boundary Layer Transport Mass transport resistance through the gas boundary layer is expected to be important for absorption of all reactive gases where uptake at the wall is rapid. Since iodine is present in parts per million concentration levels, effects due to high conzentrations on the boundary layer transport processes are insignificant. Based on a film model the iodine flux is defined by NA =k (C - Cgi) (65) 64

S NUREG-CR-0009 where NA = iodine flux, g/cm 2sec, k g = mass transfer coefficient, cm/sec3 gc3 C = iodine concentration in bulk gas, g/cm gb Cgi = iodine concentration at gas-liquid interface, g/cm3 If thE- iodine is rapidly absorbed by the wall, then Cgb >> Cgi and the gas boundary layer resistance controls the absorption rate. As will be shown later in this report, this is the case for deposition of elemental iodine in containment vessels.

i Transport In Water Film The stirfaces inside a containment vessel following a LOCA will be covered in part by water, and therefore the water film may play a role in the overall deposition process. Water films could, theoretically, either enhance or retard iodine deposition, depending on the value of the iodine partition coefficient in the aqueous film. For reactive liquid films, absorption would be enhanced, ensuring that Cgi/Cgb 2 0. If the wall surface were com-pletely covered by a water film, in which the iodine partition coefficient were a minimum value, the water could represent a minor diffusion barrier. However the following order of magnitude calculation indicates that the water film would be too thin to appreciably retard the iodine absorption process.

At steady state, the iodine absorption rate per unit Aarea in the gas and liquid films is 65

a NUREG-CR-0009 DL (C i-C Zw) 12 flux = k (C - Ci = D ( (66) where DL = iodine diffusivity in water, cm 2/sec, 6 = thickness of liquid film, cm.

The maximum impeding effect of the water layer would be present if C w, the iodine concentration in liquid at the wall, is zero. Setting Cw = 0, and using the usual surface saturation (C = H C gi), Eq. (66) may be written as C DLH Cgi = + (67)

C. k 6 gi g where H = equilibrium partition coefficient.

Mass transfer resistance in the liquid phase will be unimportant if Cgb/Cgi > 10. This will occur if the reciprocal Sherwood number DLH/k g6 is greater than 9.

For a typical case: DL = 3 x 10-4 ft 2/hr H = 5000 k = 8 ft/hr g -4 6 = 0.01 cm = 3 x 10 ft 6 1 625. Therefore it is con-Using these values, DLH/kg cluded that liquid phase mass transfer resistance will be negligible for elemental iodine sorption on surfaces.

A water film would absorb iodine regardless of whether the solid wall were adsorbing or non-adsorbing.

I. 66

t:; ~ . -- .

NUREG-CR-0009 An order of magnitude estimate of the wall liquid absorp-tion rate may be obtained by considering a strip of unit width along the wall extending from the top of the con-tainment vessel to the operating floor. If the wall film liquid (originating from spray drops and steam condensate) becomes saturated with iodine the total quantity absorbed will be:

I absorbed r H C (68) 2 g where r = wall film flow rate, H = equilibrium partition coefficient, SCg = gas phase concentration of 12*

For a typical case, we estimate P = 3 ft 3/hr ft and H"= 5 x 103. The absorption rate, 3 x 103 C g ft 3 hr-may be compared to absorption where the wall is a perfect sink, k AC In this case A will be numerically equal to the height of the wall surface, approximately 100 ft.

12 absorbed by liquid film (3)= - (5x10 3 )C g = 18.75 12 absorbed for perfect sink case (8) (100)Cg From this calculation it appears that the wall liquid film alone is capable of absorbing all the iodine which could be transported to a wall which was a perfect sink for iodine.

'6

67

0 NUREG-CR-0009 Sorption of Iodine by Paint and Other Surfaces Iodine deposition on painted surfaces, on concrete, and on stainless steel surfaces has been studied extensively in the United States and abroad. The broad picture which emerges from the many studies is that iodine sorbs onto the exposed surface, and then diffuses into the material where it is held by both irreversible chemical reaction and by physical solubility. The overall absorption capac-ity is typically much larger than required to absorb all the iodine transported to the wall. For example, a typical reactor core at equilibrium for a 1000 MW plant would contain some 25 kg of iodine( . Of the 50% which could be released from the core, less than 10.% would be adsorbed by surfaces if sprays operate. Therefore only 25(0.5) (0.1),

or 1.25 kg of iodine at most would be available for surface deposition. If this iodine were distributed uniformly on surfaces within the containment vessel above the operating deck, the surface density would be roughly 1.25 x 106mg = 0.0035 mg/cm2. This is a very low 8 2 3.5 x 10 cm surface loading and is appreciably less than the sorptive capacity (0.04 mg/cm 2 ) of the least sorptive paint (vinyl base) studied by Rosenberg, et al. (54) For most paints used in containment vessels, the sorptive capacity is an order of magnitude higher than the value listed above for the vinyl paint. Therefore, it appears that the painted surfaces have the capacity to retain all the iodine which could be deposited on them. Similar results have been reported for other surfaces, including stainless 68 PIK

NUREG-CR-0009 5 4 5 5 steel( f mild steel and concrete( )

Review of Iodine Deposition Measurements Deposition on Small Specimens Results of an extensive research program on deposition of elemental iodine and methyl iodide on paints commonly used in containment vessels were reported by Rosenberg, et al. Several kinds of laboratory scale experiments were performed. First was a "screening chamber" in which 12 deposition coupons (1 inch square) could be exposed simultaneously to an iodine-containing atmosphere. The deposition coupons were supported from a glass shaft which was rotated at speeds of 1, 25, and 250 rpm to evaluate the effect of gas velocity on adsorption. The coupons were removed periodically from the chamber and the iodine deposit analyzed by means of gamma ray spectroscopy.

In a second apparatus, a single deposition coupon was suspended in a glass vessel so that iodine deposited from a flowing gas stream could be assayed continuously using a gamma ray scintillation probe.

Deposition under condensing steam conditions was measured within a cylindrical chamber (1 ft x 1 ft), the walls of which were warmed by a heating tape to control the condensation rate.

Iodine deposition from the liquid phase was measured by suspending coated discs (10 cm diameter) in liquid saturated with tagged iodine crystals.

Typical results from vapor phase sorption and desorption 69

I 0 NUREG-CR-0 009 tests are shown in Figure 7. Important features of the data in Figure 7 include the following. First, there is an initial rapid sorption rate which is constant with time. After several hours, the paint becomes saturated with iodine, and the sorption rate slows. The paint becomes completely saturated after about 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months and for longer times no additional deposition occurs. When iodine-free gas is passed across the specimen, a fraction of the iodine is desorbed, and the remainder is bound irreversibly.

CI4 I I I i I I I i i I i "

LC 0.6 RUN VP 302-5 AT 170 0 C ATM = 50% AIR/STREAM 0.5 12 CONC = 170 CM MG/M3 Lii 0.4

¢W C:) 0.3 U- 0.2 Cl)

0.1 IDCOATING

PHEINOLINE 302, 0.05 mm THICK

_J U.

0 5 10 15 20 25 30 35 40 45 50 55 60 II I-TIME, h FIGURE 7. Typical Results of Vapor Phase Iodine Sorption-Desorption Experiments Reported by Rosenberg, et al.

70

I NUREG-CR-0009 Experiments were conducted with the coatings des-cribed in Table 4.

TABLE 4. Commerical Coatings (54)

Studied by Rosenberg et al.

Coating Name Coating Class Manufacturer Amercoat 33 HB Vinyl Americoat Corp.

Amercoat 66 Epoxy Americoat Corp.

Amercoat 1756 Acrylic latex Americoat Corp.

Dimetcote No. 3 Inorganic zinc Americoat Corp.

primer Carboline 3300 Acrylic latex Carboline Co.

Phenoline 302 Phenolic Carboline Co.

Phenoline 368 Phenolic Carboline Co.

Carbo-zinc 11 Inorganic zinc Carboline Co.

primer Turco Contam- Vinyl Turco Products, Inc.

Affix Rem Corlar 588 Epoxy du Pont Strathclyde Iron Oxide Federated Paints, Ltd.

primer Selected results obtained for vapor phase deposition at 115 0 C and 1 atm pressure are shown in Table 5.

These results show thai for most coatings, the observed deposition velocity is larger than the value of the mass transfer coefficient predicted for the walls of the containment vessel, approximately 0.07 cm/sec.

Therefore, for most of the paints, the wall may be consid-ered a perfect sink for iodine even in the absence of an 71

-. --.--- ',-'--.--.-.-.----.----=,.-- .---- ~-- - - at.;

F- NUREG-CR-0009 absorptive liquid film. Also, the absorptive capacity, at a minimum, is an order of magnitude larger than required to adsorb the quantity of iodine which will be deposited on surfaces if sprays operate.

TABLE 5. Typical Iodine Sorption Results( 5 4 )

Reported by Rosenberg, et al.

for Vapor Phase Deposition at 115 0 C Coating Name Initial Iodine Iodine Deposition Capacity at Irreversibly Velocity, Saturation, Retained, cm/sec mg/cm Amercoat 0.0206 0.0744 55.1 Turco Contam Affix Rem 0.00984 0.0327 71.3 Amercoat 0.0389 0.271 40.6 Carboline 3300 0.101 0.223 39.3 Phenoline 302 0.148 0.458 67.6 Phenoline 368 0.184 0.697 86.5 Amercoat 66 0.491 0.976 56.6 Corlar 0.675 1.21 43.1 Dimetcote No.3 0.707 10.3 100.0 Carbo-zinc 11 0.678 9.70 99.4 The deposition velocities cbtained in this small scale study would not be expected to apply directly to reactor containment vessels, but serve as guidelines and represent limiting cases for particular situations.

Measurements of iodine deposition on small test cou-(56) pons have also been reported by Parker, et al. , by 3

I*

72

NUREG-CR-0009 Coemn(32) (57)

Hilliard and Coleman , by Nebaker, et al. , and et al.( 58 ). The results of-these latter by Freeby, studies are supportive of the work of Rosenberg, et al.

hence, will not be reviewed here.

Natural Transport Measurements In Small Vessels Numerous tests of iodine plateout characteristics have been carried out in vessels having volumes of the order of one cubic meter. While these vessels are very much smaller than reactor containment vessels, the tests allow thermal and concentration effects to be realistically demonstrated.

Containment Research Installation (CRI)

(56)

The CRI system consists principally of a stain-less steel tank equipped with a removable liner to permit deposition to be studied for various surfaces. The vessel volume is 4.6 x 106 cm 3 and has an internal surface area of 1.34 x 10 50 cm2 Airborne iodine concentration in a typical test fell rapidly soon after release; then after the concen-tration had fallen by more than an order of magnitude, the concentration decreased more slowly. The results of tests carried out with a stainless steel liner are summarized in Table 6.

Two important results from the tests are the follow-ing. First, the iodine deposition rate is not strongly

,,J 7.1WO-r-P-3 W-W. -11

4 .-. *L.~--.. ~ - -

F-I NUREG-CR-0009 dependent on the temperature of steam-air atmospheres or on the initial iodine concentration. Second, the deposi-tion velocities observed are equal to or larger than 0.08 cm/sec, a magnitude expected for natural convection gas phase limited transport in this vessel.

Results obtained in the CRI after a liner covered with an Amercoat paint was installed are summarized in Table 7.

The results obtained with the Amercoat paint are in good agreement with those obtained with the stainless steel liner.

TABLE 6. Results of Iodine Tests Carried Out in CRI With a Stainless Steel (56)

Liner As Reported by Parker, et al.

Experiment Release Maximum Initial Initial 12 No. Conc. Temp. Conc.

3 Deposition 2C Half-Life mg/mr Velocity*,

min. cm/sec 100 1 4.8 25 0.35 1.14 103 I 25 3.4 0.117 104 I 6.7 125.5 1.6 1.25 I 107 S 110 SI 11 114 H SI 3.4 0.5 0o05 0.27 110.5 118 115 ill 4.5 3.9 3.0 4.6 0.089 0.102 0.133

0. 067 0.693 Volume 23.9 cm/sec d th 1/2 Area th I 74

NUREG-CR-0009 TABLE 7.. Results of Iodine Tests Carried Out in CRI With an Amercoat Liner* 5' 9 Experiment Release Maximum Initial Initial 12 No. Conc. Temp. Conc.

3 Deposition 0C Half-Life mg/m Velocity*,

min.

cm/sec 115 0.0001 115 6 .0.067 117 0.005 115 2.7 0.148 118 0.005 115 2.7 0.148 119 0.035 115 5 0.080 120 0.125 115 4.2 0.095

= 0.693 Volume 23.9 cm/sec Vd t Area t Thus, iodine deposition proceeded at about the same rate in vessels having either painted walls or stainless steel walls.

Aerosol Development Facility (ADF)

The Aerosol Development Facility (ADF) (60) was used to obtain pilot data for the large tests carried out in the Containment Systems Experiment. Two different vessels were used in the ADF tests. The PAT vessel (painted aerosol tank) had a volume of 1.54 mi3 , an inter-2 nal surface area of 8.0 m , and had walls of carbon steel painted with Phenoline 300, a modified phenolic coating.

The SAT vessel (stainless aerosol tank) had a volume of 09m3 2 0.90 m , a surface area of 5.2 m , and was made from 304 L 75

.%._ ......... *A*A NUREG-CR-UU0U9 stainless steel. Surface deposition tests carried out in ADF tanks are summarized in Table 8.

Results obtained in the stainless steel vessel are in good agreement with those obtained in the painted vessel. Hilliard( 6 0 ) concluded that the iodine deposition velocity (mass transfer coefficient) was governed by mass transfer resistance in the gas phase. In Runs SB-48 and SB-50, the steam flux was a factor of 10 below the value used in other experiments. The iodine removal rate was reduced by a factor of four due to this lower condensation rate.

The ADF results appear to agree well with those obtained at ORNL in the CRI. Agreement of results ob-tained with three types of surfaces supports the conclusion that gas phase resistance controlled the mass transfer rate.

Contamination-Decontamination Experiment (CDE)

The Contamination-Decontamination (CDE) facility was set up to provide piloting data for the LOFT experi-ment (57'58) The test vessel was approximately 1.5 m in diameter by 1.5 m in height. It had a volume of 2.4 m 3 and a surface area of 10.7 m2. 2 As indicated in the name of this program, the emphasis was on the development of procedures for decontamination of surfaces exposed to fission products. Some data were obtained which can be used to estimate the initial iodine deposition velocity.

Available data from the CDE are summarized in Table 9.

The removal rates for elemental iodine given in Table 9 are comparable to those obtained in ADF and CRI 76

NUREG-CR-0009

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TABLE 9. CDE Iodine Deposition Rates(

CDE Initial 12 Initial 12 Run No. Removal t1/2 Deposition min Velocity cm/sec Composite of 6 Runs 8 0.065 Tracer Run 10 1-3 0.52 - 0.17 Tracer Run 11 1-3 0.52 - 0.17 at Battelle-Northwest and Oak Ridge National Laboratory, respectively.

t is From this review of small scale pilot scale tests, concluded that iodine deposits initially at a rate it limited by gas phase mass transfer resistance. This ini-tial rate continues until the airborne concentration decays by a factor of 100 or more, and then the removal rate decreases. The long term removal rate is typically less than 10% of the initial rate. If chemical reactions within liquid or solid surfaces had controlled iodine plate-out, then both iodine concentration and wall material would have influenced the removal rate. Since neither of these variables was important, one is forced to conclude that gas phase mass transfer resistance controlled the deposition rate during early stages.

78

ý* , .0, -t I I- ý

NUREG-CR-000 9 Natural Transport Experiments in Large Vessels A significant number of experiments at relatively large scale have been carried out in the United States and in Great Britain. These experiments are important because they show the degree to which a large gas volume can be considered well-mixed. They also provide data on the removal rate, so that predictions for full-sized con-tainment vessels can be made with a reasonably small scaleup factor. Important tests are described as follows.

Containment Systems Experiment (CSE)

A total of six (6) natural transport tests were carried out as. part of the Containment Systems Experiment (32)

Program carried out at Battelle-Northwest . Two tests were carried out in an inner vessel (called the dry well) and four were done in the main containment vessel. The inner vessel was 11 feet in diameter and 30 feet in height, whereas the main vessel was 25 feet in diameter and 67 feet in height. Both vessels were painted inter-nally with a phenolic resin paint, Phenoline 302*. The vessels were heated internally by live steam injection.

In most tests a steady state temperature was maintained.

In one test (A-11) steam flow was stopped after fission product simulants were injected; the temperature then decayed by heat loss through the insulated vessel walls.

Fission product simulants injected included cesium oxide, uranium oxide, elemental iodine, and methyl iodide.

These substances were sampled by means of Maypack samplers,

Product of th? Carboline Company, St. Louis, Missouri 79

-. - ... ~ - ,~ r'~~ -

- - Iv-° NUREG-CR-0009 and analyzed by gamma ray spectroscopy.

In experiments in both vessels, gas samples were obtained at seven to fourteen spatial locations to deter-mine whether concentration gradients existed in the bulk gas phase.

Results of the six natural transport tests carried out in the CSE facility that pertain to elemental iodine are summarized in Table 10.

TABLE 10. CSE Natural Transport Tests Run Vessel Atm. 1I Release Initial 12 12 Deposition Conc.

No. Volume Temp. Velocity 3 0oF 3 Removal t ft mg/mr min 1/2 cm/sec D-I 4,200 252 0.66 8.0 0.097 D-2 4,200 250 0.94 9.5 0.081 A-I 21,000 181 1.17 9.0 0.137 A-2 21,000 185 94.5 9.0 0.137 A-5 21,000 253 142 13.5 0.092 A-Il 21,000 253 165 16.0 0.076

In Run A-lI, temperature decayed following fission product injection.

j The measured deposition velocities varied from 0.076 cm/sec to 0.137 cm/sec depending on the thermal 4 conditions in the vessel. These values are somewhat 4 higher than the values obtained in planable in ADF, and this is terms of a higher gas phase mass transfer ex-coefficient. The deposition velocities shown in Table 10 0 80

NUREG-CR-0009 for the large scale CSE tests are in good agreement with values obtained in CRI and CDE tests.

Several key conclusions from the CSE tests listed by Hilliard and Coleman( 32 ) are the following.

0 The experimental values of the initial removal rate for elemental iodine were in good agreement with a natural convection model in which it was assumed that all mass transfer resistance resides in the gas phase.

0 The gas phase limited rate for elemental iodine per-sisted until the gas-phase concentration decreased to about 1% of the initial value. Thereafter the concentration decreased at a slower rate.

0 The concentrations of all fission product simulants were essentially uniform throughout the gas space of a single compartment.

Iodine Deposition In An Unheated Cubical Volume Measurements of iodine deposition in an unheated cubical room, whose surface was covered by a chlorinated rubber-based paint, were reported by Croft, et al.(55) 3.

The room was 27.4 m in volume and had a surface area of 2

60.2 m . Temperature within this masonry-walled room was essentially in equilibrium with the outside space, maintained at approximately 20 0 C. The room atmosphere was unfiltered and was maintained in a gentle state of agitation by a small fan.

Elemental iodine was released over a time period of 10 to 20 minutes, and the airborne concentration was 81

NUREG-CR-0009 followed with time by means of Maypack samples. Results from these experiments are summarized in Table 11.

TABLE 11. 12 Deposition In An Unheated 5 5)

Cubical Room(

Test Relative 12 Release I Removal 12 Deposition No. Humidity Conc 2Velocity mg/m 3 Halftime, min cm/sec 1 85% 113 130 0.004 2 85% 237 170 0.0031 3 100% 190 140 0.0037 The iodine removal process was followed for 500 minutes, and was found to be first order (constant halftime) for this entire period.

The deposition velocities obtained in these tests are one to two orders of magnitude smaller than obtained inmost other tests. This lower deposition velocity is consistent with the expected low gas phase mass transfer coefficient expected for the unheated room. The small fan could be expected to mix the bulk gas phase, but would provide only a minimal flow of gas along the walls. The results obtained would not be expected to apply directly to water reactor LOCA conditions, but do demonstrate that the iodine deposition velocity is controlled by the gas phase mass transfer coefficient.

82

NUREG-CR-00 09 Iodine Deposition in Zenith Reactor Containment Surface deposition of elemental iodine was studied (61) in the secondary containment of the Zenith reactor The reactor pit area, covered by a steel bonnet, had a volume of 500 m3 with a total surface area of 700 m2.

Some 60% of the surface was concrete painted with chlor-inated rubber-based paint, 40% was painted metal and 1%

was bare metal. Results of two experiments reported in detail are summarized in Table 12.

TABLE 12. Results of 12 Deposition in Zenith Reactor Containment( 6 1 )

Test 12 Release Ventilation Initial Estimated No. Conc. Flow Rate 3 Removal 12 Deposition mg/mr m /min Halftime Velocity min cm/sec 1 0.00078 0 21 0.039 2 0.00074 85 3.7 0.02 The initial removal rate continued until the airborne concentration decreased by two to three orders of mag-nitude, and then decreased more slowly.

This experiment'was similar to that carried out in the painted room(55) in that there were essentially no temperature gradients to promote a convective flow along the walls of the pit region. It is obvious that more turbulence was present than in the cubical room because 83.

NUREG-CR-0009 the iodine deposition velocity was higher by an order of magnitude.

These results would not be expected to apply to the post accident situation in a water reactor because of the absence of a typical wall AT in the experiment. The experimental results are consistent with the postulate that surface deposition is controlled by gas phase mass transfer resistance.

Iodine Release in DIDO Reactor Containment Shell Stinchcombe and Goldsmith( 62 ) described the results of experiments involving release of elemental iodine into the DIDO containment shell. While the details of the Sexperimental facilities are somewhat sketchy, iodine dep-osition velocities can be estimated. The DIDO shell had 3

a volume of 7000 m , and 2 if equipment surfaces are ignored, a surface area of 1020 mi. The experimental releases were done at ambient temperature and pressure. Results of the tests are summarized in Table 13.

TABLE 13. Results of Iodine Deposition in

.DIDO Containment Vessel (62)

Test 12 Release 12 Removal Estimated 12 No. Conc. Halftime Deposition Velocity, mg/ 3 cm/sec A 0.00012 6.4 0.45 B 0.00012 8.3 0.34 84

NUREG-CR-0009 The iodine deposition velocity obtained in the DIDO vessel is appreciably larger than obtained in most other natural transport tests. For example, these values are roughly 100 times larger than obtained in the cubical room tests of Croft, et al.-(55) . The higher deposition velocities are attributable to the mixing of the gas phase by ventilation equipment in the DIDO vessel and to use of only wall surface area in calculating deposition velocities.

The long term elemental iodine behavior was similar to that typically obtained: the initial rapid removal rate persisted until the concentration fell by about two orders of magnitude, and then fell more slowly at longer times. The observed high deposition velocity indicates that the paint adsorption rate was not a limiting factor.

In a supporting experiment, Stinchcombe and Gold-smith( 62 ) studied the effect of condensing steam on iodine deposition. The amount of iodine deposited on a cold, condensing surface was the same as that on a non-cooled silver surface subjected to the same gas flow. It was concluded that the deposition was entirely due to the forced convection flow, and that the condensation of steam was unimportant in 12 deposition. This result is in agreement with Hilliard's results which showed that steam sweep was small compared to diffusional mass transfer.

Conclusions From Large Vessel Iodine Experiments The results of all reported large scale tests are I

85

I consistent with small scale results in that initial deposition proceeds at a rate limited by gas phase mass NUREG-CR-0009 iodine transfer, and then after the concentration decays by a factor of 100 or so, the removal rate slows. There is no evidence that the properties of the surface limit the initial deposition rate. Nor is there evidence that the sweep effect of condensing steam is controlling. Therefore, ones ability to predict iodine deposition under accident conditions depends primarily on ones ability to predict gas phase mass transfer coefficients under accident con-ditions.

Model For Surface Deposition of Elemental Iodine In Containment Vessels Based on the experimental evidence, a satisfactory model will be one which agrees with the following exper-imentally derived behavioral characteristics.

Initial deposition rate is limited by gas phase mass transfer.

The bulk volume of a single compartment is well mixed.

0 Steam flux plays a minor role in iodine deposition.

Effects of size scale must be included in the model.

30 ' 3 1' 5 4' 6 3' 6 4 ) which have On the several models(

been proposed to describe fission product removal due .to 30 ' 31 ) account for the natural transport, two models(

effects noted above.

86

, ' .- "- . . .. -=

NUREG-CR-00 09 The Knudsen-Hilliard model (3)views deposition as a film transport process to vessel surfaces. The mass transfer coefficient across the gas film is predicted from natural convection heat transfer correlations, by using a mass transfer-heat transfer analogy. Prediction.

of the mass transfer coefficient requires a knowledge of the wall heat transfer rate.

The Yuill-Baston model 31 tackles the transport (65) process using the penetration theory of mass transfer The mass transfer rate is predicted under gas exposure times predicted for natural convection flows. Thermal conditions at the wall are needed to predict the mass transfer rate.

Both of these models yield predictions which are in good agreement with measured rates of removal. Of the two, the Knudsen-Hilliard model offers several advantages, (47) . A and has been adopted for use in the SPIRT Code listing of a recent version of this code, SPIRT 10 is

.app~ended to this report. Reasons for selecting this model are as follows:

The film model accounts for the laminar to turbu-lent transition boundary layer flow whereas the penetration theory model treats the boundary layer as stagnant.

" The film model is easier to visualize and use than the penetration theory model.

" The-film model appears to be better able to predict scale-up effects because it accounts for turbulent flows which develop in large vessels.

87

NUREG-CR-0009 For laminar flow, the heat transfer rate is described by hi 4 nc kT 0.59(Gr TPr) (69) where h nc = heat transfer coefficient on vertical plate, 1 = length of surface, k = thermal conductivity of gas, GrT = Grashov number due to wall temperature difference, Pr = Prandtl number for gas.

The form of Eq. (69) was obtained from the theoretical (66) work of Schmidt and Beckman , and the constant (0.59) obtained empirically. A relationship of similar form applies for turbulent flow (transition from laminar to turbulent flow occurs at Grashov numbers between 109 and 1012).

hnc = 0.13(GrTPr) 1 /3 kT (70)

Eqs. (69) and (70) may be transformed through a mass transfer-heat transfer analogy to give relationships to

.1

.1 predict mass transfer coefficients (30). For laminar flow

.4

'4 kl1 c- 0.59(Gr Sc)'

1 D (71) and for turbulent flow 88

'I

OL NUREG-CR-0009 k1 0.13(Gr Sc) 1/ 3 (72) where kc = mass transfer coefficient, Grc = Grashov number accounting for molecular weight difference between bulk gas and interface, D = molecular diffusivity of I2, Sc = Schmidt number for iodine in gas.

These two equations allow a mass transfer coefficient to be calculated once the temperature difference at the wall is known. For typical LOCA conditions, Hilliard and Coleman( 32 ) quote a distance of 10 feet from the top of the containment wall for the transition from laminar to turbulent boundary layer flow.

In addition to diffusional transport, Knudsen and Hilliard (30) add a second mass transport term to account for the sweep effect of condensing steam. The condensa-tion mass transfer coefficient is given as n RTb ks = 18P (73) where k5 = steam sweep mass transfer coefficient, ns = steam flux toward surfaces, R = gas constant, Tb = bulk gas temperature, P = total gas pressure.

The formulation of Eq. (73) is based on the concept that 89

NUREG-CR-0009 iodine is transported to the wall with the steam at a velocity equal to the bulk flow velocity caused by the condensation. The enhancement predicted by Eq. (73) 2 8 )

the effect(

for bulk flow is probably an overestimate of Therefore the contribution of steam sweep will not be included in the model chosen here. The net effect of disregarding Eq. (73) is small, because steam sweep predicted by Eq. (73) typically accounts for less than 10% of the overall mass transfer coefficient.

Predictions based on Eqs. (71), ('2)1 and (73) are compared to experimental results obtained in CSE in Table 14. The results shown in Table 14 were calculated by assuming that all exposed surface areas inside the CSE vessel were iodine deposition surfaces.

TABLE 14. Comparison of Predicted Removal Rates For Elemental Iodine by Steam Sweep Effect and by Diffusion( 3 2 )

Predicted Halftime, min CSE Run By Steam By Diffusion Measured No. Sweep(a) Across B.L. (b) Half Life, Sweep_ AcrossB.L. min D-1 36 7.7 8.0 +/- 1 D-2 38 7.8 9.5 +/- 0.5 A-I 130 10.0 9.0 +/- 4.0 A-2 122 9.9 9.0 +/- 0.5 A-5 475 16.1 13.5 +/- 0.5 A-11 500 16.8 16.0 +/- 0.5 (a) Calculated from Eq. (73)

(b) Calculated from Eqs. (71) and (72), using a transi-tion from laminar to turbulent boundary layer flow at 10 feet from the top of the vessel 90 I

S NUREG-CR-0009 Two important facts evident from these results are:

(1) the steam sweep effect is small, and (2) the measured and predicted removal rates are in good agreement.

Typical mass transfer coefficients predicted for turbulent flow for saturated steam-air mixtures have 3 0 been calculated by Knudsen and Hilliard( ). Examples are shown in Figure 8.

From the results pictured in Figure 8, it is obvious that the mass transfer coefficient is not highly sensitive to the bulk gas temperature. The transfer coefficient is highly dependent on the inside temperature difference for AT values less than 4 0 F. For higher AT values, only a small increase in kc results from increasing the tempera-ture difference.

5From a practical standpoint, the temperature differ-ence in the gas boundary layer will not fall below about 1lF for LOCA times of interest. Order of magnitude cal-culations for two cases show this. First, for infinite time (equilibrium) Hilliard and Coleman(32) show that a AT of 1lF exists for heat transfer through 5 feet of con-crete, where the internal temperature is 250OF and the outside temperature is 80 0 F. Second, a transient heat transfer calculation made under the assumption that a concrete wall 2 feet thick is heated from both sides by 0

an initial AT of 100 0 F, a l-2 F AT will continue to exist after 25 hr. Therefore, in the absence of a transient heat transfer analysis, a minimum AT of 1lF can be assumed to exist in all compartments exposed to steam in the LOCA.

91

NUREG-CR-0009 28 24 0.2 20 0.15 16 12 0.10 44 C-(1 Iý4 o 8 o

0.05 4

0 3 0 4 8 12 16 20 24

( T b - Tsi) INSIDE TEMPERATURE DIFFERENCE, OF FIGURE 8. Mass Transfer Coefficients As a Function of 9

Inside Temperature Difference for Steam-Air Atmospheres (30) 92

- - - -- -~ - - - -.-. ,- ~-.-. - ~ -. ,r~t<f--Mrtr~

i NUREG-CR-0009 Wall Plateout During Spray Operation Spray operation would influence surface deposition in two ways. First, the sprays would impart turbulence to the gas phase, thereby increasing the mass transfer coefficient. Second, spray operation would affect the temperature gradient at solid surfaces, and thereby affect the mass transfer rate.

Spray Induced Turbulence Promotion of Mass Transfer While we know of no data of direct applicability to spray induced turbulence in containment vessels, an order of magnitude estimate of the effect may be obtained by examining the enhancement in wall plateout observed in CSE tests on air cleaning(67)

The CSE air cleaning tests of interest involved the operation of a cleanup loop inside the main compartment.

Contaminated air was drawn into a series of filters and adsorbents, and then discharged back into the containment atmosphere. Air motion resulting from the operation of the air cleaning loop enhanced the iodine plateout rate on vessel surfaces. The enhanced wall plateout in air cleaning tests is summarized in Table 15.

93

NUREG-CR-0009 TABLE 15. Enhancement of Iodine Surface Deposition In CSE Air 67)

Cleaning Experiments(

CSE Run Number A-13 A-14 A-15 A-16 Air Flow Rate, CFM 1000 1000 1000 1800 Gas Temperature, OF 96 250 250 246 min

.-i X0 - Observed, 0.095 0.141 0.115 0.182 1

F/V - loop, min- 0.0475 0.0475 0.0475 0.086 (Xo-F/V) - wall deposition, min 0.0475 0.0935 0.0675 0.096 1

X (natural convection), min 0.0266 0.0432 0.0257 0.0532 X (enhancement), min-I 0.0209 0.0503 0.0418 0.0428 In Table 15, A 0 is the observed removal rate constant which resulted from both surface deposition and cleanup in the aircleaning components. F/V, the ratio of air-cleaning loop flow rate to vessel volume, is the removal rate constant due to the loop itself. A (natural con-vection) is the removal A which was observed due to natural convection plateout when the loop was not operated.

Thus, X (enhancement) is the observed removal rate con-stant minus the X's due to loop cleanup and wall plateout due to natural convection.

As shown from Table 15, there is an appreciable enhancement in wall plateout caused by loop operation.

The kinetic energy per unit volume of gas may be calcu-lated by 94

0" NUREG-CR-0009 PF.(E)2 Energy/Time _ v2 Volume (Volume) (2g) (21,000) (2g ) (74) where p = gas density, v = gas velocity F = loop flow rate, A = area of discharge duct, M = mass of air per unit time, gc = gravitational constant.

This is the kinetic energy carried by the exiting gas stream from the air cleaning loop per unit time. The enhanced deposition rate, expressed as a deposition velocity, is plotted Figure 9 as a function of energy dissipated per unit time per unit volume. From these data, it appears that surface deposition is greatly enhanced for low values of energy, and that an upper level or saturation value is attained at an energy dis-sipation rate of about 0.001 ft lb/sec ft 3 .

For a PWR spray system operating at 40 psid at 3000 gpm in a containment vessel of 2 x 106 ft 3 , the kinetic energy dissipated by the sprays is about 0.02 ft lb/sec 3

ft . This value is about 4 times larger than the highest value shown on Figure 9; hence, a deposition velocity of at least 0.07 cm/sec would be predicted as a result of spray enhancement of surface deposition.

6.1.10 Approach to Equilibrium by Recirculated Spray When spray water is recirculated to the spray headers,

, D,

- -I "PO-19 "W"M WITTV IWZV--*

LR-N 10-0341 Technical Evaluation 80102291-0040 Effect on LOCA Radiological Consequences of Increased MSIV Flow Rate Based on Main Steam Line Temperature and a Single Main Steam Piping Compartment Volume

Document Number: Technical Evaluation 80102291-0040

Title:

Effect on LOCA Radiological Consequences of Increased MSIV Flow Rate Based on Main Steam Line Temperature and a Single Main Steam Piping Compartment Volume 1.0 REASON FOR EVALUATION / SCOPE:

The purpose of this assessment is to determine the Control Room (CR), Exclusion Area Boundary (EAB), and Low Population Zone (LPZ) doses based on the MSIV leakage downstream of the outboard MSIV calculated using a single main steam compartment volume for the intact main steam line and for the failed main steam line with an assumed steam line wall temperature of 550 0F. The intact and failed main steam line compartment volumes extend from the outboard MSIV to the turbine stop valve (TSV).

This assessment does not take credit for aerosol deposition and elemental iodine removal in the piping from the Reactor Pressure Vessel (RPV) nozzle to the outboard MSIV in both the failed and intact steam lines. This assessment demonstrates that the most limiting CR dose in H-1-ZZ-MDC-1 880, Revision 4, remains bounding for the CR dose and the offsite dose increases remain less than minimal with respect to the dose consequences in the current licensing basis analysis.

2.0 METHODOLOGY The MSIV leak rates downstream of the outboard MSIV in both the MSIV failed and intact lines are calculated in Section 3.0 using a steam line temperature of 550°F downstream of the outboard MSIV for the entire duration of the accident. These MSIV leak rates are used in Table 6 to determine the aerosol removal efficiencies. Table 7 shows the increased MSIV leak rates due to the change in steam line wall temperature. The RADTRAD Plant Scenario (psf) File HlN300MSOO.psf (from H-1-ZZ-MDC-1880, Revision 4) is modified using the revised MSIV leakage and aerosol removal efficiencies.

The elemental iodine removal filter efficiencies modeled from 0 to 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months are taken from Tables 1L &

1M of H-1-ZZ-MDC-1880, Revision 4. Use of these elemental iodine removal filter efficiencies introduces a small amount of non-conservatism because they are developed using different total surface areas and volumes. The well mixed volume information used in this assessment is taken from H- 1-ZZ-MDC-1880, Revision 4, and modified appropriately to incorporate the required changes.

The maximum CR inleakage is measured to be 155 +/- 10 cfm in the recently performed (year 2009)

Tracer Gas Test (Ref. 10.46 as cited in H-1-ZZ-MDC-1880, Revision 4). In the last two Tracer Gas Tests, all CR inleakage was consistently measured to be filtered. Although all CR inleakage is filtered, the analyses in Revision 4 assumed 300 cfm unfiltered inleakage, which is conservative. This assessment assumes the CR unfiltered inleakage is 250 efmn, including 10 cfm for ingress/egress. Use of 250 cfm in this assessment reduces the control room dose. This assumption remains conservative with respect to the fact that all CR inleakage is filtered.!

I The resulting doses due to the revised MSIV leakage and aerosol/elemental iodine removal filter efficiencies are listed in Section 4.0. 1 1

3.0 DETERMINATION OF MSIV LEAKAGE RATES 3.1 MSIV Leakage During 0-2 hrs Note: References and Sections cited in this Section 3.1 refer to references and sections in H-1-ZZ-MDC-1880, Revision 4.

Note: The RADTRAD runs model MSIV leakage beginning at 0 minutes, which is prior to the 2 minute start of the gap release per Section 5.3.1.5.

Total Drywell volume = 169,000 ft3 (Ref. 10.16)

Total MSIV leakage measured @ 50.6 psig = 250 scfh Per the ideal gas law, PV= nRT or PV/T = nR. Given that nR is a constant for the air leakage, PV/T at post-LOCA conditions is equal to PV/T at STP conditions.

P @LOCA = Drywell peak pressure = 50.6 psig (Ref. 10.17, Section 3.3.1)

T @LOCA = Drywell peak temperature = 298°F (Ref. 10.17, Section 3.3.1) = 298°F + 460 = 758 R P @STP = Standard pressure = 14.7 psia T @STP = Standard temperature = 68°F = 68SF + 460 = 528'R V @STP = MSIV leakage based @ 50.6 psig = 250 scfi V @LOCA = (PV/T @STP) x (T/P @LOCA) 0-2 hrs MSIV leakage @ drywell peak pressure of 50.6 psig and temperature of 2980 F

= 250 scfh x [14.7 psia / (50.6 psig + 14.7 psia)] x [7580 R / 528°R]

= 250 scfh x 0.225 x 1.436 = 80.78 cfh

= (80.78 ft3/hr x 24 hr/day) x 100% / 1.69E+05 ft3 1.147 %/day

= (80.78 ft3/hr) / (60 min/hr) = 1.346 cfm The 0-2 hrs 250 scfh MSIV leakage is released via two of the four Main Steam (MS) lines. A maximum allowable leak rate of 150 scfh is postulated from the shortest MS line with its inboard MSIV failed.

The remaining leak rate of 100 scfh is postulated from the shortest of the three intact MS lines (i.e., the second shortest of the four MS lines). No leakage is postulated from the remaining two intact MS Lines.

0-2 hrs allowable leakage from the MS line with a failed MSIV (at maximum 150 scfh leak rate)

= (150 scfh / 250 scfh total) x 80.78 cfh = 48.47 cfh = 0.808 cfm 0-2 hrs allowable leakage from the shortest intact MS line (at maximum 100 scfhi leak rate)

= (100 scfh / 250 scfh total) x 80.78 cfh = 32.31 cfh = 0.539 cfm 2

3.2 MSIV Leakage During 2-720 hrs Note: References and Sections cited in this Section 3.2 refer to references and sections in H-l-ZZ-MDC-1880, Revision 4.

Two hours after a LOCA the drywell and suppression chamber volumes are expected to reach an equilibrium condition and the post-LOCA activity is expected to be homogeneously distributed between these volumes. The homogeneous mixing in the primary containment will decrease the activity concentration and therefore decrease the activity release rate through the MSIVs. To model the effect of this mixing, the MSIV flow rate used in the RADTRAD model is decreased by calculating a new leak rate based on the combined volumes of the drywell and suppression chamber.

Drywell + Suppression Chamber free air volume = 306,000 ft3 (Design Input 5.3.2.4) 2-720 hrs MSIV leakage @ drywell peak pressure of 50.6 psig = 80.78 cfh (Section 7.2.2) 3 %i

= (80.78 cfh x 24 hr/day) x 100% / 3.06E+05 ft -

Corresponding MSIV leak rate = 80.78 cfh x (1.69E+05 ft3 / 3.06E+05 ft3) = 44.61 cfh 2-720 hrs allowable leakage from the MS Line with a failed MSIV (at maximum 150 scfh leak rate)

= (150 scth / 250 scfh total) x 44.61 cfh = 26.77 cfh = 0.446 cfm 2-720 hrs allowable leakage from the shortest intact MS Line (at maximum 100 scfh leak rate)

= (100 scfh / 250 scfh total) x 44.61 cfh = 17.84 cfh = 0.297 cfm 3.3 MSIV Leakage To Environment Note: References and Sections cited in this Section 3.3 refer to references and sections in H-I-ZZ-MDC-1880, Revision 4.

MSIV Leakage into the pipe spool between outboard MSIV and TSV and environment from MSIV failed line (MSIV Failed MS Line 1) 0-720 hrs It is conservatively assumed that the MSIV leakage past the TSV expands to the atmospheric condition as follows:

Upstream of outboard MSIV in MSIV failed line (Section 7.2.2):

VI = 48.47 cth P1 = 50.6 psig + 14.7 = 65.3 psia TI = (298 0 F + 460) = 758 0 R Downstream of outboard MSIV in MSIV failed line (Atmospheric Condition):

V2 = TBD P2 = 14.7 psia T2 = (550'F + 460) = 1010 0 R MSIV Leakage into the pipe spool between outboard MSIV and TSV and environment from MSIV failed line (MS Line 1):

V2 = (PV/T @1) x (T/P @2)

= (65.3 psia x 48.47 cfh / 758 0R) x (1010°R / 14.7 psia) 287 cfh = 4.783 cfm 3

3.4 MSIV Leakage into the pipe spool between outboard MSIV and TSV and environment from MSIV shortest intact line (Intact MS Line 2)

Note: References and Sections cited in this Section 3.4 refer to references and sections in H-i -ZZ-MDC-1880, Revision 4.

0-720 hrs Upstream of inboard MSIV in the shortest intact MS Line (Section 7.2.2):

V1 = 32.31 cfh P1 = 50.6 psig + 14.7 = 65.3 psia Ti = (298°F + 460) = 758°R Downstream of inboard MSIV in intact line (assumed Atmospheric Condition):

V2 = TBD P2 = 14.7 psia T2 = (550'F + 460) = 1010°R MSIV Leakage into the intact pipe spools between the inboard and outboard MSIVs and between the outboard MSIV and TSV (and environment) from the intact line:

V2 = (PV/T @1) x (T/P @2)

= (65.3 psia x 32.3.1 cfhi / 758 R) x (1010 0 R / 14.7 psia) 191 cfh = 3.183 cfrn 4

4.0 RESULTS

SUMMARY

4.1 The post-LOCA EAB, LPZ, and CR doses due to the increased MSIV leakage and 250 cfm of CR unfiltered air inleakage are summarized in the following table. The CR Filter shine is per H-1-ZZ-MDC-1880, Revision 4, and conservatively based on 300 cfmn of CR unfiltered air inleakage.

Post-LOCA Post-LOCA TEDE Dose (Rem)

Activity Release Receptor Location Path Control Room EAB LPZ Containment Leakage 5.28E-01 3.87E-01 1.47E-01 (3.1 hr)

ESF Leakage 2.42E+00 5.22E-01 2.64E-01 (14.2 hr) 2.20E+00 MSIV Leakage 9.99E-01 2.3 (2.3 hr)04.79E-01 hr)__ _ _ _

Containment Purge 0.OOE+00 0.OOE+00 0.OOE+00 Containment Shine 0.OOE+00 0.OOE+00 O.OOE+00 External Cloud 0.OOE+00 0.OOE+00 O.OOE+00 CR Filter Shine 1.29E-02 0.OOE+00 0.00E+00 Total 3.96E+00 3.11E+00 8.90E-01 Allowable TEDE Limit 5.OOE+00 2.50E+01 2.50E+01 RADTRAD Computer Run No.

Containment Leakage HEPU250CLOO.oO HEPU250CLOO.oO HEPU250CLOO.oO ESF Leakage HEPU250ESOO.oO HEPU250ESOO.oO HEPU250ESOO.oO MSIV Leakage H250MS550F3,oO H250MS550F3.oO H250MS550F3.oO 5

4.2 Compliance of revised dose increases with the 10 CFR 50.59 rule is shown in the following table:

Current Proposed Regulatory Proposed Minimal SRP Design Basis Accident Total Total Dose Dose 50.59 Dose Dose Dose Dose Limit Increase Increase Limit (rem) (rem) (rem) (rem) (rem) (rem)

TEDE TEDE TEDE TEDE TEDE TEDE A B C D=B-A E=0.1(C-A) F Loss of Coolant Accident H-1-ZZ-MDC- TE80102291-0040 (LOCA) 1880, Rev 4 Control Room 4.04 3.96 5 -0.08 0.096 5 Exclusion Area Boundary 1.78 3.11 25 1.33 2.322 25 Low Population Zone 0.674 0.89 25 0.22 2.433 25 C From 10 CFR 50.67 F From Standard Review Plan 15.0.1,Section II 6

5.0 CONCLUSION

S The results in Section 4.0 indicate that the EAB, LPZ, and CR doses are within their allowable TEDE limits for the increased MSIV leakage rate.

Per the following table, the Control Room dose decreases from the CR dose consequence in Section 8.1 of H-1-ZZ-MDC-1880, Revision 4. This change is primarily due to the reduction in the CR unfiltered inleakage rate from 300 cfm to 250 cfm.

Per the table in Section 4.1 and the following table, the EAB and LPZ doses have increased relative to the dose consequences in Section 8.1 of H-1-ZZ-MDC-1880, Revision 4. However, per Section 4.2, these offsite dose increases remain less than minimal with respect to the dose consequences in the current licensing basis analysis.

Post-LOCA Post-LOCA TEDE Dose (Rem)

Activity Release Receptor Location Path Control Room EAB LPZ MSIV Leakage per 9.99E-01 2.20E+00 4.79E-01 Assessment Section 4.0 (2.3 hr)

MSIV Leakage per 6.13E-01 2.63E-01 H-1-ZZ-MDC-1880, R4 (3.0 hr)

Total Doses per 3.96E+00 3.11E+00 8.90E-01 Assessment Section 4.0 Total Doses per 4.04E+00 1.78E+00 6.74E-01 H-1-ZZ-MDC-1880, R4 Allowable TEDE Limit 5.OOE+00 2.50E+01 2.50E+01 7

6.0 TABLES Note: The data in Table 3 is consistent with the data in Table 3 in H-1-ZZ-MDC-1880, Revision 4, with the exception that this assessment does not take credit for aerosol deposition and elemental iodine removal in the piping from the Reactor Pressure Vessel (RPV) nozzle to the outboard MSIV in both the failed and intact steam lines. Therefore, these volumes are not reported in Table 3.

Table 3 Hope Creek Main Steam Piping Volume Main Steam Piping Inside Volume (ft3)

Header A Header D Failed Steam Line Intact Steam Line Piping Between RPV Nozzle & Inboard MSIV N/A N/A Piping Between Inboard and Outboard MSIVs N/A N/A Piping Between Outboard MSIV and Turbine Stop valve 1139.04 1136.00 8

Note: The data in Table 5 is similar to the data in Table 5 in H-I-ZZ-MDC-1880, Revision 4. The difference is that Table 5 in this assessment does not model aerosol deposition between the inboard and outboard MSIVs.

The failed line horizontal settling areas and horizontal pipe volumes are per data calculated in Section 7.3.2.4 in H-1-ZZ-MDC-1880, Revision 4.

The intact line horizontal settling areas and horizontal pipe volumes are per data calculated in Section 7.3.3.6 in H-1 -ZZ-MDC-1 880, Revision 4.

Table 5 Rate Constant for MSIV Leakage Release Path with 40%/40% Settling Velocities Settling Horizontal Horizontal Rate Peach Bottom Velocity Settling Pipe Constant for Steam Header pS Area Volume Settling X, 2 3 (fit/hr) (ft ) (ft ) (hr-')

A B C D MSIV Failed Line - Header A Inboard MSIV To N/A N/A N/A N/A Outboard MSIV MSIV Failed Line - Header A Outboard MSIV To 9.56 631.62 1065.25 5.67 Turbine Stop Valve SV-3 ......

MSIV Intact Line - Header B Inboard MSIV To N/A N/A N/A N/A Outboard MSIV MSIV Intact Line - Header B Outboard MSIV To 9.56 629.82 1062.21 5.67 Turbine Stop Valve A = 40 Percentile Settling Velocity = 0.00081 m/sec x 3.28 ft/m x 3600 sec/hr = 9.56 ft/hr for main steam lines from outboard MSIV to TSV.

D = X, = (Ax B)/C 9

Note: The data in Table 6 is similar to the data in Table 6 in H-i-ZZ-MDC-1880, Revision 4. The difference is that Table 6 in this assessment does not model aerosol deposition between the inboard and outboard MSIVs.

Table 6 Gravitational Deposition Aerosol Removal Efficiency On Horizontal Pipe Surface With 40%/40% Settling Velocity (250 scfh)

Post-LOCA Settling Well Volumetric Aerosol Post-LOCA Settling Well Volumetric Aerosol Time Rate Mixed Flow Removal Time Rate Mixed Flow Removal Interval Constant Volume Rate Efficiency Interval Constant Volume Rate Efficiency MSIV X, V, Failed X, V3 Intact A B Line A B Line 3 3 1 3 3 (hr) (hr-') (ft ) (ft /hr) (%) (hr) (hr ) (ft ) (ft /hr) (%)

MSIV Failed Main Steam Line Between Inboard & Outboard MSIVs Intact Main Steam Line Between Inboard & Outboard MSIVs 0-24 0-24 24-96 N/A 24-96 N/A 96-720 96-720 Post-LOCA Settling Well Volumetric Aerosol Post-LOCA Settling Well Volumetric Aerosol Time Rate Mixed Flow Removal Time Rate Mixed Flow Removal Interval Constant Volume Rate Efficiency Interval Constant Volume Rate Efficiency MSIV V2 Failed 2's V4 Intact A B Line A B Line (hr) (hr") (ft') (ft3/hr) (%) (hr) (hr-') (ft') (ft3/hr) (%)

MSIV Failed Main Steam Line Between Outboard MSIV &

TSV Intact Main Steam Line Between Outboard MSIV & TSV 0-24 5.67 1139.04 287.00 95.75 0-24 5.67 1136.00 191.00 97.12 24-96 5.67 1139.04 287.00 95.75 24-96 5.67 1136.00 191.00 97.12 96-720 5.67 1139.04 287.00 0.00 96-720 5.67 1136.00 191.00 0.00 A From Table 5 B From Table 3 10

Note: The data in Table 7 is similar to the data in Table 7 in H-1-ZZ-MDC-1880, Revision 4. The tabulated MSIV leak rates are per Sections 3.0 through 3.4 of this Assessment.

Table 7 MSIV Leak Rate In Different Control Volume (Total = 250 sefh & Max = 150 scfh)

MSIV Leak Rate In Various Control Volumes (cfh)/(cfm)

Post-LOCA Drywell To Volume V1 Drywell To Intact Line Time MSIV Failed To Intact Line Volume V2 Interval Volume V1 Atmosphere Volume V2 To (hr) Atmosphere 48.47 287.00 32.31 191.00 0-2 0.808 4.783 0.539 3.183 2-720 26.77 287.00 17.84 191.00 0.446 4.783 0.297 3.183 MSIV Leak Rate Information From Section 3.0 11

Note: The data in Tables iL and IM is identical to the data in Tables 1L and 1M in H-1-ZZ-MDC-1880, Revision 4.

Table 1L Elemental Iodine Removal Efficiency - MSIV Failed Line Volume Vii Net Elemental Post-LOCA Temp Iodine Iodine Time Degree Removal Removal Rate Efficiency A B (hr) F (hr-1) (%)

0 340 0.3926 32.47 3 320 0.4701 37.51 6 250 0.9312 60.59 24 208 1.4800 77.24 96 180 2.0759 87.46 240 170 2.3582 90.54 480 150 3.0789 95.40 720 A From Table 1J B = 1-e-At where t: 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for each time interval.

Table 1M Elemental Iodine Removal Efficiency - Intact Line Volume V33 Net Elemental Post-LOCA Temp Iodine Iodine Time Degree Removal Removal Rate Efficiency A B (hr) F (hr-1) (%)

0 340 0.3327 28.30 3 320 0.3997 32.95 6 250 0.7976 54.96 24 208 1.2709 71.94 96 180 1.7847 83.22 240 170 2.0280 86.84 480 150 2.6492 92.93 720 1 1 1 A From Table 1K B = 1-e A,where t = 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for each time interval.

12

7.0 ATTACHMENTS 7.1 Attachment 1: RADTRAD Output File HEPU250CLOO.oO 7.2 Attachment 2: RADTRAD Output File HEPU250ESOO.oO 7.3 Attachment 3: RADTRAD Output File H250MS550F3.oO 13

C- Ll A t CC, 8-()

V.0, ý LAA f kZ VI 8.0 ffSGMATURES Preparer: 4 ~

/Z/#7/ Date.: 08/28/201Q Gopal I. IT UCORE)

Independent ieviewer; Date: 0 L/28/_Q...

Mark Drucker (NUCORE)

// - .... .. ..

PSE&G Ow4r Acceptan (c;* Date. O8/,,*/2010 70John DuTrfy

(~C~

Approved: Date:, bt3%ý-.j1 l- s S. Boyer I t4

-I

Attachment 1 RADTRAD Output File HEPU250CLOO.oO

1. 1. ff######################ff###############f#####################4#4########f RADTRAD Version 3.02 run on 8/25/2010 at 0:28:20

1. 1. 1. 1. ft###############ft###ftftf###ft####################

1. 1. 1. 1. ftf#####4#############ff#######ft##################

File information

1. 1. 1. 1. 4t#ff#### ##########f############################

Plant file name G:\Radtrad 3.02\Accept\MDC-1880 R4\HEPU250CLOO.psf Inventory file name g:\radtrad 3.02\defaults\hepulocal def.txt Scenario file name G:\Radtrad 3.02\Accept\MDC-1880 R4\HEPU250CLOO.psf Release file name g:\radtrad 3.02\defaults\bwr dba.rft Dose conversion file name = g:\radtrad 3.02\defaults\fgrll&12.inp t ft ft ftftftftft ft ft ftftftft#

1. t### #f### #f### ft f ft ft ft f# #4 #t # ~# #

ft #f# ft ft ft ft f# ft ft #t ft

tf# #f# ft Radtrad 3.02 1/5/2000 Cont. Leakage AST Analysis For Extended Power Uprate With Core Average Exposure, 100% Mixing in Containment After 2 hrs, FRVS Vent Filter @ 90%, CREF Initiation Delayed for 30 Minutes, and CR Unfiltered Inleakage = 250 cfm Nuclide Inventory File:

g:\radtrad 3.02\defaults\hepulocaldef.txt Plant Power Level:

3.9170E+03 Compartments:

5 Compartment 1:

Containment 3

1.6900E+05 1

0 0

1 0

Compartment 2:

Reactor Bldg 15

3 4.OOOOE+06 0

0 1

0 0

Compartment 3:

Environment 2

0.0000E+00 0

0 0

Compartment 4:

Control Room 1

8.5000E+04 0

0 1

0 0

Compartment 5:

Void 3

1.0000E+05 0

0 0

Pathways:

7 Pathway 1:

Containment Leakage to Environment 1

3 4

Pathway 2:

Containment Leakage to Reactor Bldg 1

2 4

Pathway 3:

FRVS Exhaust to Environment 2

3 2

Pathway 4:

Control Room Filtered Air Intake 3

4 2

Pathway 5:

16

CR Unfiltered Inleakage 3

4 2

Pathway 6:

Control Room to Environment 4

3 2

Pathway 7:

Containment to Void 1

5 4

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1 1.OOOOE+00 g:\radtrad 3.02\defaults\fgrll&12.inp g:\radtrad 3.02\defaults\bwr dba.rft 0.OOOOE+00 1

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

0 o.OOOOE+00 0

0 0

0 Compartments:

5 Compartment 1:

0 1

1 0.0000E+00 0

1 o.OOOOE+00 3

o.OOOOE+00 3.1600E+00 2.OOOOE+00 1.7400E+00 4.OOOOE+O0 0.0000E+00 1

0.OOOOE+00 0

0 0

3 3

1. OOOOE+01 0

17

Compartment 2:

0 1

0 0

1 1.0800E+05 3

o.0000E+00 o.OOOOE+00 0.0000E+00 O.OOOOE+O0 1.0400E-01 9. 9000E+01 0.OOOOE+00 O.OOOOE+00 7.2000E+02 9.9000E+01 0.OOOOE+00 O.OOOOE+00 0

0 Compartment 3:

0 1

0 0

0 Compartment 4:

0 1

0 0

1 2.6000E+03 3

0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 5.OOC0E-01 9.9000E+01 9. 9000E+01 9.9000E+01 7.2000E+02 9.9000E+01 9.9000E+01 9. 9000E+01 0

0 Compartment 5:

0 1

0 0

0 Pathways:

7 Pathway 1:

0 0

18

0 0

1 2

o .OOOOE+00 5. 0OOOE-01

1. 0400E-01 0.OOOOE+00 0

Pathway 2:

0 0

1 8

0 .0000E+00 0 OOOOE+00

1. 0400E-01 5. OOOOE-01 1 .OOOOE+00 5 .OOOE-01 2 .OOOOE+00 5. 0OOOE-01 4 .OOOOE+00 5. OOOOE-01

8. OOOOE+O0 5 .OOOE-01

2. 4000E+01 5. 0OOOE-01

7. 2000E+02 O.OOOOE+O0 0

Pathway 3:

0 0

0 1

7

0. 0000E+00 1.9800E+04 0.OOOE+00 0 OOOOE+00 o .OOOOE+00

1. 0400E-01 1.9800E+04 9.9000E+01 9. OOOOE+01 9. OOOOE+01

4. 3700E-01 1.5740E+04 9. 9000E+01 9. OOOOE+01 9. OOOOE+01

2. 1040E+00 8.4920E+03 9. 9000E+01 9. OOOOE+01 9 OOOOE+01 4 .1040E+00 7.4250E+03 9. 9000E+01 9. OOOOE+01 9 OOOOE+01

8. 1040E+00 7. 3130E+03 9. 9000E+01 9. OOOOE+01 9. OOO0E+01

7. 2000E+02 0.OOOOE+00 0.OOOOE+00 0 OOOOE+00 0 OOOOE+00 0

0 0

0 Pathway 4:

0 0

19

0 0

0 1

3 0.OOOOE+00 5.OOOOE+02 0.OOOE+00 0.OOOOE+00 o.OOOOE+00 5.OOOOE-01 1.1000E+03 9. 9000E+01 9. 9000E+01 9. 9000E+01 7.2000E+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0

0 0

0 Pathway 5:

0 0

0 1

3 0.0000E+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 o.0000E+00 5.0000E-01 2.5000E+02 0.OOOOE+00 0.0000E+00 o.0000E+00 7.2000E+02 0.OOOOE+00 0.0000E+00 0.OOOOE+00 o.OOOOE+00 0

0 0

0 Pathway 6:

0 0

0 1

3 0.OOOOE+00 5.0000E+02 0.0000E+00 0.OOOOE+00 0.0000E+00 5.OOOOE-01 1.3500E+03 1.0000E+02 1.OOOOE+02 1.OOOOE+02 7.2000E+02 0.0000E+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0

0 0

0 Pathway 7:

0 0

20

0 0

1 3

o.0000E+00 1. 1470E+00 2.0000E+00 6. 3400E-01 7.2000E+02 0.0000E+00 0

Dose Locations:

3 Location 1:

Exclusion Area Boundary 3

1 2

0.0000E+00 1.9000E-04 7.2000E+02 0.0000E+00 1

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

Location 2:

Low Population Zone 3

1 7

0.0000E+00 1.9000E-05 2.OOOOE+00 1.2000E-05 4.0000E+00 8.0000E-06 8.0000E+00 4.0000E-06 2.4000E+01 1.7000E-06

9. 6000E+01 4.7000E-07 7.2000E+02 0.OOOOE+00 1

4 0.0000E+00 3.5000E-04 8.OOOOE+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 O.OOOOE+00 0

Location 3:

Control Room 4

0 1

2 0.OOOOE+00 3.5000E-04 7.2000E+02 0.OOOOE+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 21

6 O.OOOOE+00 1.2500E-03 2.OOOOE+00 8.0900E-04 8.OOOOE+00 3.0400E-04 2.4000E+01 2.1000E-04 9.6000E+01 1.5900E-04 7.2000E+02 O.OOOOE+00 Simulation Parameters:

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

G:\Radtrad 3.o43 1

1 1

0 0

End of Scenario File 22

1. 1. 1. 1. R############################4################

RADTRAD Version 3.02 run on 8/25/2010 at 0:28:20

1. 1. 4##4############4###################4############4#########ý########4#

1. 1. 1. 1. 4####################################################

Plant Description 4#######4*#############################*##################################

Number of Nuclides = 60 Inventory Power = 1.0000E+00 MWth Plant Power Level = 3.9170E+03 MWth Number of compartments = 5 Compartment information Compartment number 1 (Source term fraction = 1.OOOOE+00 Name: Containment Compartment volume = 1.6900E+05 (Cubic feet)

Removal devices within compartment:

Spray(s)

Deposition Pathways into and out of compartment 1 Pathway to compartment number 3: Containment Leakage to Environment Pathway to compartment number 2: Containment Leakage to Reactor Bldg Pathway to compartment number 5: Containment to Void Compartment number 2 Name: Reactor Bldg Compartment volume = 4.OOOOE+06 (Cubic feet)

Removal devices within compartment:

Filter(s)

Pathways into and out of compartment 2 Pathway to compartment number 3: FRVS Exhaust to Environment Pathway from compartment number 1: Containment Leakage to Reactor Bldg Compartment number 3 Name: Environment Pathways into and out of compartment 3 Pathway to compartment number 4: Control Room Filtered Air Intake Pathway to compartment number 4: CR Unfiltered Inleakage Pathway from compartment number 1: Containment Leakage to Environment Pathway from compartment number 2: FRVS Exhaust to Environment Pathway from compartment number 4: Control Room to Environment Compartment number 4 Name: Control Room Compartment volume = 8.5000E+04 (Cubic feet)

Removal devices within compartment:

Filter(s)

Pathways into and out of compartment 4 Pathway to compartment number 3: Control Room to Environment Pathway from compartment number 3: Control Room Filtered Air Intake Pathway from compartment number 3: CR Unfiltered Inleakage 23

Compartment number 5 Name: Void Compartment volume 1.OOOOE+05 (Cubic feet)

Pathways into and out of compartment 5 Pathway from compartment number 1: Containment to Void Total number of pathways = 7 24

4############f######ff######%##f###########################################

RADTRAD Version 3.02 run on 8/25/2010 at 0:28:20

4##################################################################4###

Scenario Description

1. 1. 1. 1. 4######################################

Radioactive Decay is enabled Calculation of Daughters is enabled RELEASE NAME = BWR, NUREG-1465, Tables 3.11 & 3.13, Jun Release Fractions and Timings GAP EARLY IN-VESSEL 0.5000 hrs 1.5000 hrs NOBLES 5.0000E-02 9.5000E-01 IODINE 5.0000E-02 2.5000E-01 CESIUM 5.0000E-02 2.0000E-01 TELLURIUM 0 OOOOE+00 5.OOOOE-02 STRONTIUM 0.0000E+00 2.0000E-02 BARIUM 0.0000E+00 2.0000E-02 RUTHENIUM 0.0000E+00 2.5000E-03 CERIUM 0 OOOOE+00 5.0000E-04 LANTHANUM 0.0000E+00 2.0000E-04 Iodine fractions Aerosol = 9. 5000E-01 Elemental = 4.8500E-02 Organic = 1.5000E-03 COMPARTMENT DATA Compartment number 1: Containment Sprays: Elemental Removal Data Time (hr) Removal Coef. (hr^-l) 0.0000E+00 3.1600E+00 2.OOOOE+00 1.7400E+00 4.0000E+00 0.0000E+00 Natural Deposition (Powers' model): Aerosol data Reactor type: 3 Percentile = 10 (%)

Compartment number 2: Reactor Bldg Compartment Filter Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.OOOOE+00 1.0800E+05 0.0000E+00 0.0000E+00 0.0000E+00

1. 0400E-01 1.0800E+05 9. 9000E+01 0.0000E+00 0.0000E+00 7.2000E+02 1.0800E+05 9. 9000E+01 0.OOOOE+00 0.0000E+00 Compartment number 3: Environment Compartment number 4: Control Room 25

Compartment Filter Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 2.6000E+03 0.0000E+00 0.0000E+00 0.0000E+00

5. OOOOE-01 2.6000E+03 9.9000E+01 9.9000E+01 9.9000E+01 7.2000E+02 2.6000E+03 9.9000E+01 9.9000E+01 9.9000E+01 Compartment number 5: Void PATHWAY DATA Pathway number 1: Containment Leakage to Environment Convection Data Time (hr) Flow Rate (% / day) 0.0000E+00 5.0000E-01 1.0400E-01 0.0000E+00 Pathway number 2: Containment Leakage to Reactor Bldg Convection Data Time (hr) Flow Rate (% / day) 0.0000E+00 0 OOOOE+00 1.0400E-01 5. 0000E-01 1.0000E+00 5.0000E-01 2.OOOOE+00 5. 0OOE-0O 4.0000E+00 5 .OOOOE-01 8.000OE+00 5 .OOOOE-01 2.4000E+01 5 .OOOOE-01 7.2000E+02 0 OOOOE+00 Pathway number 3: FRVS Exhaust to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.OOOOE+00 1.9800E+04 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 1.0400E-01 1.9800E+04 9. 9000E+01 9. OOOOE+01 9. OOOOE+01

4. 3700E-01 1.5740E+04 9. 9000E+01 9. OOOOE+01 9.OOOOE+01 2 .1040E+00 8.4920E+03 9. 9000E+01 9. OOOOE+01 9. OOOOE+01 4 .1040E+00 7.4250E+03 9. 9000E+01 9. OOOOE+0i 9. OOOOE+01

8. 1040E+00 7 . 3130E+03 9. 9000E+01 9.0000E+01 9. OOOOE+01 7 .2000E+02 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Pathway number 4: Control Room Filtered Air Intake Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.OOOOE+00 5.0000E+02 0.0000E+00 0.0000E+00 0.OOOOE+00

5. 0OOOE-01 1. 1000E+03 9.9000E+01 9.9000E+01 9.9000E+01 7.2000E+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Pathway number 5: CR Unfiltered Inleakage 26

Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.OOOOE+00 o.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00

5. OOOOE-01 2.5000E+02 O.OOOOE+00 0.OOOOE+00 0.OOOOE+00 7.2000E+02 0.OOOE+00 0.OOOOE+00 0.0000E+00 O.OOOOE+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 5.0000E+02 0.0000E+00 O.0000E+00 0.0000E+00

5. 0000E-01 1.3500E+03 1.0000E+02 1.0000E+02 1.0000E+02 7.2000E+02 0.0000E+00 0.0000E+00 0.OOOOE+00 0.0000E+00 Pathway number 7: Containment to Void Convection Data Time (hr) Flow Rate (% / day) 0.0000E+00 1.1470E+00 2.0000E+00 6.3400E-01 7.2000E+02 0.00007E+00 LOCATION DATA Location Exclusion Area Boundary is in compartment 3 Location X/Q Data Time (hr) X/Q (s

m^-3) 0.OOOOE+00 1.9000E-04 7.2000E+02 0.OOOOE+00 Location Breathing Rate Data Time (hr) Breathing Rate (m^3

sec^-l) 0.0000E+00 3.5000E-04 7.2000E+02 0.0300E+00 Location Low Popul ation Zone is in compartment 3 Location X/Q Data Time (hr) X/Q (s

m^-3) 0.0000E+00 1.9000E-05 2.0000E+00 1.2000E-05 4.0000E+00 8.0000E-06 8.0000E+00 4.0000E-06 2.4000E+01 1.7000E-06 9.6000E+01 4.7000E-07 7.2000E+02 0.0000E+00 Location Breathing Rate Data Time (hr) Breathing Rate (m^3

sec^-l) 0.OOOOE+00 3.5000E-04 8.0000E+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.0000E+00 27

Location Control Room is in compartment 4 Location X/Q Data Time (hr) X/Q (s

m^-3)

O.OOOOE+00 1.2500E-03 2.OOOOE+00 8.0900E-04 8.OOOOE+00 3.0400E-04 2.4000E+01 2.1000E-04 9.6000E+01 1.5900E-04 7.2000E+02 O.OOOOE+00 Location Breathing Rate Data Time (hr) Breathing Rate (m^3

sec^-l)

O.OOOOE+00 3.5000E-04 7.2000E+02 O.OOOOE+00 Location Occupancy Factor Data Time (hr) Occupancy Factor 0.0000E+00 1.0000E+00 2.4000E+01 6.OOOOE-01 9.6000E+01 4.OOOOE-01 7.2000E+02 O.OOOOE+00 USER SPECIFIED TIME STEP DATA - SUPPLEMENTAL TIME STEPS Time Time step O.OOOOE+00 1.OOOE-01 2.OOOOE+00 5.OOOOE-01 8.OOOOE+00 1.0000E+00 2.4000E+01 2.OOOOE+00 9.6000E+01 5.OOOOE+00 7.2000E+02 O.OOOE+00 28

RADTRAD Version 3.02 run on 8/25/2010 at 0:28:20

1. 1. 1. 1. it######i#########it ####################

1. 1. 1. #t # ###it# ###i## it # ###44#

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1. 44##4#########4#####4###############i######4###4########4###############

Dose Output

1. 1. 1. 1. it#####################i###########i4#####i###########it###########

Exclusion Area Boundary Doses:

Time (h) = 0.1040 Whole Body Thyroid TEDE Delta dose (rem) 7.1431E-03 1.2071E+00 5.8955E-02 Accumulated dose (rem) 7.1431E-03 1. 2071E+00 5.8955E-02 Low Population Zone Doses:

Time (h) = 0.1040 Whole Body Thyroid TEDE Delta dose (rem) 7. 1431E-04 1.2071E-01 5.8955E-03 Accumulated dose (rem) 7.1431E-04 1.2071E-01 5.8955E-03 Control Room Doses:

Time (h) = 0.1040 Whole Body Thyroid TEDE Delta dose (rem) 3.2182E-05 1. 3767E-01 5. 9416E-03 Accumulated dose (rem) 3.2182E-05 1. 3767E-01 5. 9416E-03 Exclusion Area Boundary Doses:

Time (h) = 0.4370 Whole Body Thyroid TEDE Delta dose (rem) 5.8459E-04 8. 6321E-03 9.2765E-04 Accumulated dose (rem) 7.7277E-03 1. 2157E+00 5.9883E-02 Low Population Zone Doses:

Time (h) = 0.4370 Whole Body Thyroid TEDE Delta dose (rem) 5.8459E-05 8. 6321E-04 9.2765E-05 Accumulated dose (rem) 7.7277E-04 1. 2157E-01 5.9883E-03 Control Room Doses:

Time (h) = 0.4370 Whole Body Thyroid TEDE Delta dose (rem) 1.9343E-04 8. 6864E-01 3.7475E-02 Accumulated dose (rem) 2.2561E-04 1. 0063E+00 4. 3417E-02 29

Exclusion Area Boundary Doses:

Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 2.4218E-04 3. 3411E-03 3.7486E-04 Accumulated dose (rem) 7.9699E-03 1. 2190E+00 6.0257E-02 Low Population Zone Doses:

Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 2.4218E-05 3. 3411E-04 3.7486E-05 Accumulated dose (rem) 7.9699E-04 1. 2190E-01 6.0257E-03 Control Room Doses:

Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 3.4496E-05 1. 5364E-01 6. 6261E-03 Accumulated dose (rem) 2.6011E-04 1. 1600E+00 5.0043E-02 Exclusion Area Boundary Doses:

Time (h) = 1.0000 Whole Body Thyroid TEDE Delta dose (rem) 8.2542E-03 6.6700E-02 1.1145E-02 Accumulated dose (rem) 1.6224E-02 1.2857E+00 7. 1403E-02 Low Population Zone Doses:

Time (h) = 1.0000 Whole Body Thyroid TEDE Delta dose (rem) 8.2542E-04 6.6700E-03 1. 1145E-03 Accumulated dose (rem) 1.6224E-03 1. 2857E-01 7 . 1403E-03 Control Room Doses:

Time (h) = 1.0000 Whole Body Thyroid TEDE Delta dose (rem) 4.5034E-04 6. 6665E-01 2.9048E-02 Accumulated dose (rem) 7.1046E-04 1.8266E+00 7. 9091E-02 Exclusion Area Boundary Doses:

Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.0090E-01 4.6044E-01 1.2342E-01 Accumulated dose (rem) 1.1713E-01 1.7462E+00 1. 9482E-01 Low Population Zone Doses:

Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.0090E-02 4.6044E-02 1.2342E-02 Accumulated dose (rem) 1.1713E-02 1. 7462E-01 1.9482E-02 Control Room Doses:

Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 7.9321E-03 3.3882E-01 2. 3160E-02 Accumulated dose (rem) 8.6425E-03 2.1654E+00 1. 0225E-01 Exclusion Area Boundary Doses:

30

Time (h) = 2.1040 Whole Body Thyroid TEDE Delta dose (rem) 1.9273E-02 7.3789E-02 2.2984E-02 Accumulated dose (rem) 1.3640E-01 1.8200E+00 2. 1781E-01 Low Population Zone Doses:

Time (h) = 2.1040 Whole Body Thyroid TEDE Delta dose (rem) 1.2172E-03 4.6604E-03 1. 4516E-03 Accumulated dose (rem) 1.2930E-02 1. 7928E-01 2.0934E-02 Control Room Doses:

Time (h) = 2.1040 Whole Body Thyroid TEDE Delta dose (rem) 1.8021E-03 2.6900E-02 3. 1143E-03 Accumulated dose (rem) 1.0445E-02 2.1923E+00 1. 0536E-01 Exclusion Area Boundary Doses:

Time (h) = 4.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.0827E-01 6. 4373E-01 3.3934E-01 Accumulated dose (rem) 4.4467E-01 2.4637E+00 5.5714E-01 Low Population Zone Doses:

Time (h) = 4.0 000 Whole Body Thyroid TEDE Delta dose (rem) 1.9470E-02 4.0657E-02 2.1432E-02 Accumulated dose (rem) 3.2400E-02 2.1993E-01 4.2366E-02 Control Room Doses:

Time (h) = 4.0 000 Whole Body Thyroid TEDE Delta dose (rem) 3.6921E-02 2.4399E-01 4.8844E-02 Accumulated dose (rem) 4.7365E-02 2.4363E+00 1. 5421E-01 Exclusion Area Boundary Doses:

Time (h) = 4.1040 Whole Body Thyroid TEDE Delta dose (rem) 2.0636E-02 2.3230E-02 2. 1640E-02 Accumulated dose (rem) 4.6531E-01 2.4869E+00 5.7878E-01 Low Population Zone Doses:

Time (h) = 4.1040 Whole Body Thyroid TEDE Delta dose (rem) 8.6889E-04 9.7813E-04 9. 1117E-04 Accumulated dose (rem) 3.3269E-02 2.2091E-01 4.3277E-02 Control Room Doses:

Time (h) = 4.1040 Whole Body Thyroid TEDE Delta dose (rem) 2.4593E-03 7.7869E-03 2. 8133E-03 Accumulated dose (rem) 4.9825E-02 2.4441E+00 1.5702E-01 Exclusion Area Boundary Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 6.9652E-01 5.0098E-01 7.1454E-01 Accumulated dose (rem) 1.1618E+00 2.9879E+00 1.2933E+00 31

Low Population Zone Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.9327E-02 2. 1094E-02 3.0086E-02 Accumulated dose (rem) 6.2596E-02 2. 4201E-01 7.3363E-02 Control Room Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 9.7178E-02 1. 5651E-01 1.0309E-01 Accumulated dose (rem) 1.4700E-01 2.6006E+00 2. 6012E-01 Exclusion Area Boundary Doses:

Time (h) = 8.1040 Whole Body Thyroid TEDE Delta dose (rem) 1.7282E-02 1. 1125E-02 1.7638E-02 Accumulated dose (rem) 1.1791E+00 2.9990E+00 1. 3110E+00 Low Population Zone Doses:

Time (h) = 8.1040 Whole Body Thyroid TEDE Delta dose (rem) 3.6384E-04 1.2045E-04 3.6769E-04 Accumulated dose (rem) 6.2959E-02 2. 4213E-01 7. 3731E-02 Control Room Doses:

Time (h) = 8.1040 Whole Body Thyroid TEDE Delta dose (rem) 2.4797E-03 2.9328E-03 2.5744E-03 Accumulated dose (rem) 1.4948E-01 2.6036E+00 2. 6269E-01 Exclusion Area Boundary Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.6584E+00 1.5203E+00 1.7055E+00 Accumulated dose (rem) 2.8375E+00 4. 5194E+00 3. 0165E+00 Low Population Zone Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.4913E-02 1. 6461E-02 3.5424E-02 Accumulated dose (rem) 9.7872E-02 2. 5859E-01 1. 0915E-01 Control Room Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.1224E-01 1. 6712E-01 1. 1743E-01 Accumulated dose (rem) 2.6172E-01 2.7707E+00 3. 8012E-01 Exclusion Area Boundary Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.7843E+00 5.0974E+00 2.9403E+00 Accumulated dose (rem) 5.6218E+00 9. 6167E+00 5.9568E+00 Low Population Zone Doses:

32

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.4913E-02 2. 9971E-02 2.5829E-02 Accumulated dose (rem) 1.2278E-01 2. 8856E-01 1.3498E-01 Control Room Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 7.3665E-02 2.2586E-01 8.0575E-02 Accumulated dose (rem) 3.3538E-01 2.9965E+00 4. 6070E-01 Exclusion Area Boundary Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 4.4491E+00 1. 2896E+01 4. 8418E+00 Accumulated dose (rem) 1.0071E+01 2. 2513E+01 1. 0799E+01 Low Population Zone Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.1006E-02 2.0963E-02 1.164 4E-02 Accumulated dose (rem) 1.3379E-01 3. 0952E-01 1.4663E-01 Control Room Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 5.8988E-02 2.8741E-01 6.7740E-02 Accumulated dose (rem) 3.9437E-01 3.2840E+00 5.2844E-01 842 1-131 Summary Containment Reactor Bldg Environment Time (hr) 1-131 (Curies) 1-131 (Curies) 1-131 (Curies) 0.001 5.8100E+03 0.0000E+00 3.3623E-04 0.104 1.0064E+06 0.0000E+00 1.1690E+01 0.437 3.7210E+06 1.3896E+02 1.1775E+01 0.500 4.2472E+06 1.7384E+02 1.1807E+01 0.800 9.0699E+06 4.3211E+02 1.2094E+01 1.000 1.2313E+07 6.8206E+02 1.2453E+01 1.300 1.6572E+07 1.1106E+03 1.3309E+01

1. 600 2.0304E+07 1.5526E+03 1.4569E+01

1. 900 2.3630E+07 1.9806E+03 1.6231E+01 2 .000 2.4660E+07 2.1178E+03 1.6872E+01

2. 104 2.1602E+07 2.2383E+03 1.7581E+01 2 .500 1.5613E+07 2.2893E+03 1.9145E+01

2. 800 1.1408E+07 2.0416E+03 2.0305E+01

3. 100 8.3060E+06 1.7204E+03 2.1365E+01

3. 400 6.0522E+06 1.4024E+03 2.2306E+01 3.700 4.4141E+06 1.1208E+03 2.3134E+01

4. 000 3.2232E+06 8.8595E+02 2.3862E+01 4.104 2.6192E+06 8.1541E+02 2.4094E+01 4.500 1.9124E+06 5.9628E+02 2.4800E+01 4.800 1.4123E+06 4.7339E+02 2.5279E+01 5.100 1.0426E+06 3.7907E+02 2.5722E+01 33

5.400 8.6922E+05 3. 1021E+02 2. 6138E+01 5.700 7.2623E+05 2. 6144E+02 2. 6534E+01 6.000 6.0831E+05 2 .2599E+02 2. 6916E+01 6.300 5. 1106E+05 1. 9960E+02 2.7288E+01 6.600 4.3086E+05 1. 7954E+02 2. 7651E+01 6.900 3.6472E+05 1. 6400E+02 2.8009E+01 7.200 3. 1017E+05 1. 5179E+02 2 . 8362E+01 7.500 2. 6517E+05 1.4206E+02 2 .8711E+01 7.800 2.2806E+05 1.3425E+02 2. 9056E+01 8 .000 2.0700E+05 1. 2989E+02 2. 9286E+01

8. 104 1.8855E+05 1.2784E+02 2 . 9404E+01 8.504 1. 6515E+05 1. 2125E+02 2 . 9852E+01 8.804 1.4783E+05 1. 1747E+02 3.0186E+01 9.100 1.3336E+05 1. 1446E+02 3. 0515E+01 9.400 1.2094E+05 1. 1197E+02 3. 0846E+01 9.700 1. 1044E+05 1.0992E+02 3 . 1177E+01

10. 000 1.0156E+05 1. 0821E+02 3. 1508E+01

10. 300 9.4040E+04 1.0678E+02 3. 1837E+01 24.000 5.0564E+04 9.5833E+01 4. 6531E+01 96.000 3. 7728E+04 7.1914E+01 1. 1234E+02 720.000 2.9862E+03 5.6923E+00 2.9073E+02 Control Room Void Time (hr) 1-131 (Curies) 1-131 (Curies) 0.001 9.9170E-08 7.7131E-04 0.104 3.4063E-03 2.6817E+01 0 .437 3.0489E-03 4.3008E+02 0.500 2.9907E-03 5.4996E+02 0.800 1.3332E-03 1.4940E+03 1.000 8.0896E-04 2.5169E+03 1.300 4.4435E-04 4.5910E+03

1. 600 3.2803E-04 7.2341E+03

1. 900 3.1936E-04 1.0379E+04 2.000 3.2830E-04 1.1530E+04 2.104 3.0751E-04 1.2192E+04 2 .500 1.9758E-04 1.4184E+04 2 .800 1.6412E-04 1.5234E+04

3. 100 1.4258E-04 1.5994E+04 3.400 1.2518E-04 1.6542E+04 3.700 1.0997E-04 1.6938E+04 4.000 9. 6704E-05 1.7222E+04 4.104 9.2569E-05 1.7300E+04 4.500 7 3075E-05 1. 7522E+04 4.800 6. 4033E-05 1. 7637E+04 5.100 5. 7691E-05 1. 7716E+04 5 .400 5. 3119E-05 1. 7775E+04

5. 700 4. 9837E-05 1 .7821E+04 6.000 4.7476E-05 1. 7857E+04 6.300 4. 5759E-05 1. 7884E+04 6.600 4. 4489E-05 1. 7904E+04

6. 900 4 .3532E-05 1 .7918E+04 7.200 4.2796E-05 1. 7928E+04 7.500 4 .2220E-05 1.7933E+04 7.800 4. 1761E-05 1.7936E+04 8.000 4. 1506E-05 1.7936E+04 8.104 3. 4969E-05 1.7935E+04 8.504 2. 1657E-05 1.7931E+04 34

8.804 1. 7915E-05 1.7927E+04 9.100 1.6272E-05 1.7920E+04 9.400 1. 5517E-05 1.7913E+04 9.700 1. 5168E-05 1.7905E+04 10.000 1.4998E-05 1 .7896E+04 10.300 1.4908E-05 1.7887E+04 24 000 1. 4210E-05 1.7310E+04 96.000 7.3679E-06 1.4243E+04 720.000 4.4157E-07 2.0916E+03 Cumulative Dose Summary

1. 1. 1. 1. 4#################f################################

Exclusion Area Bounda Low Population Zone Control Room Time Thyroid TEDE Thyroid TEDE Thyroid TEDE (hr) (rem) (rem) (rem) (rem) (rem) (rem) 0.001 3.4708E-05 1.6937E-06 3.4708E-06 1. 6937E-07 2.2385E-08 9.6491E-10 0.104 1.2071E+00 5.8955E-02 1.2071E-01 5. 8955E-03 1.3767E-01 5.9416E-03 0.437 1.2157E+00 5.9883E-02 1. 2157E-01 5. 9883E-03 1.0063E+00 4.3417E-02 0.500 1.2190E+00 6.0257E-02 1.2190E-01 6. 0257E-03 1.1600E+00 5.0043E-02 0.800 1.2485E+00 6.4452E-02 1.2485E-01 6. 4452E-03 1.6576E+00 7.1579E-02 1.000 1.2857E+00 7. 1403E-02 1. 2857E-01 7. 1403E-03 1.8266E+00 7.9091E-02 1.300 1.3748E+00 9. 1277E-02 1.3748E-01 9. 1277E-03 1.9711E+00 8.6256E-02 1.600 1.5062E+00 1.2506E-01 1 . 5062E-01 1 .2506E-02 2.0616E+00 9.2269E-02 1.900 1.6794E+00 1. 7461E-01 1. 6794E-01 1. 7461E-02 2.1391E+00 9.9400E-02

2. 000 1.7462E+00 1. 9482E-01 1.7462E-01 1. 9482E-02 2.1654E+00 1.0225E-01

2. 104 1.8200E+00 2. 1781E-01 1.7928E-01 2. 0934E-02 2.1923E+00 1.0536E-01 2.500 1.9823E+00 2. 7401E-01 1.8953E-01 2. 4484E-02 2.2705E+00 1.1608E-01

2. 800 2. 1021E+00 3. 2389E-01 1. 9709E-01 2. 7634E-02 2.3142E+00 1.2352E-01

3. 100 2.2108E+00 3. 7817E-01 2. 0396E-01 3. 1062E-02 2.3513E+00 1.3093E-01

3. 400 2.3067E+00 4.3568E-01 2. 1002E-01 3. 4694E-02 2.3835E+00 1.3848E-01 3.700 2.3905E+00 4. 9556E-01 2. 1531E-01 3.8476E-02 2.4117E+00 1.4623E-01 4 .000 2.4637E+00 5 .5714E-01 2 1993E-01 4 .2366E-02 2.4363E+00 1.5421E-01 4 .104 2 .4869E+00 5. 7878E-01 2 2091E-01 4 .3277E-02 2.4441E+00 1.5702E-01 4 .500 2.5571E+00 6. 5191E-01 2 . 2387E-01 4. 6356E-02 2.4696E+00 1.6764E-01 4.800 2.6043E+00 7. 0812E-01 2.2586E-01 4.8723E-02 2.4856E+00 1.7558E-01 5.100 2.6477E+00 7.6470E-01 2. 2768E-01 5. 1105E-02 2.4997E+00 1.8352E-01

5. 400 2.6881E+00 8.2138E-01 2.2938E-01 5.3492E-02 2.5125E+00 1.9146E-01 5.700 2.7264E+00 8. 7797E-01 2. 3100E-01 5.5874E-02 2.5243E+00 1.9943E-01 6.000 2.7632E+00 9. 3427E-01 2. 3255E-01 5.8245E-02 2.5354E+00 2.0742E-01 6.300 2 .7988E+00 9. 9013E-01 2. 3404E-01 6.0597E-02 2.5459E+00 2.1541E-01 6.600 2 .8335E+00 1.0454E+00 2.3551E-01 6.2925E-02 2.5561E+00 2.2339E-01 6.900 2.8675E+00 1. 1000E+00 2. 3694E-01 6.5225E-02 2.5660E+00 2.3136E-01

7. 200 2.9009E+00 1. 1539E+00 2. 3834E-01 6.7493E-02 2.5757E+00 2.3928E-01 7 .500 2.9339E+00 1.2069E+00 2. 3973E-01 6.9725E-02 2.5851E+00 2.4715E-01

7. 800 2.9664E+00 1.2591E+00 2. 4110E-01 7. 1921E-02 2.5945E+00 2.5496E-01 8 .000 2.9879E+00 1.2933E+00 2. 4201E-01 7.3363E-02 2.6006E+00 2.6012E-01

8. 104 2.9990E+00 1. 3110E+00 2. 4213E-01 7 . 3731E-02 2.6036E+00 2.6269E-01 8.504 3.0409E+00 1.3768E+00 2 .4258E-01 7. 5102E-02 2.6116E+00 2.7105E-01

8. 804 3.0720E+00 1.4250E+00 2 4292E-01 7. 6108E-02 2.6159E+00 2.7613E-01 9.100 3. 1025E+00 1. 4717E+00 2. 4325E-01 7.7080E-02 2.6196E+00 2.8046E-01

9. 400 3. 1332E+00 1.5180E+00 2 4358E-01 7.8046E-02 2.6230E+00 2.8434E-01 9.700 3. 1638E+00 1.5634E+00 2. 4391E-01 7.8992E-02 2.6264E+00 2.8785E-01

10. 000 3. 1943E+00 1.6079E+00 2. 4424EI-01 7. 9918E-02 2.6296E+00 2.9107E-01 10.300 3.2246E+00 1. 6514E+00 2. 4457E!-01 8.0825E-02 2.6329E+00 2.9409E-01 24 .000 4. 5194E+00 3. 0165E+00 2. 5859E-01 1. 0915E-01 2.7707E+00 3.8012E-01 35

96.000 9.6167E+00 5.9568E+00 2.8856E-01 1.3498E-01 2.9965E+00 4.6070E-01 720.000 2.2513E+01 1.0799E+01 3.0952E-01 1.4663E-01 3.2840E+00 5.2844E-01

1. 1. 1. 1. 4########################f###############

Worst Two-Hour Doses Note: All of the dose locations are shown below but the worst two-hour dose is only meaningful for the EAB dose location. Please disregard the two-hour worst doses for the other dose locations Exclusion Area Boundary Time Whole Body Thyroid TEDE (hr) (rem) (rem) (rem) 3.1 3.6740E-01 4.3691E-01 3.8653E-01 Low Population Zone Time Whole Body Thyroid TEDE (hr) (rem) (rem) (rem) 1.6 2.1605E-02 6.2929E-02 2.4709E-02 Control Room Time Whole Body Thyroid TEDE (hr) (rem) (rem) (rem) 0.0 8.6425E-03 2.1654E+00 1. 0225E-01 36

Attachment 2 RADTRAD Output File HEPU250ES00.o0 RADTRAD Version 3.02 run on 8/25/2010 at 0:28:20

1. 1. 1. 1. 4#################################4########################

1. 1. 1. 1. 4###f#######ft44ft####ft### f######f##### f########################

File information

f##f##################################################################

Plant file name G:\Radtrad 3.02\Accept\MDC-1880 R4\HEPU250ESOO.psf Inventory file name g:\radtrad 3.02\defaults\hepulocaldef.txt Scenario file name G:\Radtrad 3.02\Accept\MDC-1880 R4\HEPU250ES00.psf Release file name g:\radtrad 3.02\defaults\bwr i.rft Dose conversion file name = g:\radtrad 3.02\defaults\fgrll&12.inp

# f# # # f# # # # # ft ft#ft##

ft

1. 1. 1. 1. ft ##### #####

t #ft ##f # ft ft###### # f# ft ft ft## lift ft# liif lift 4 ### ft ft

1. f# llll

iiit ft f ft ft f# f# ft ft ft ft ft ft ft lift ##f ft ft ft ft ft #444 ft ft ft ft ft Radtrad 3.02 1/5/2000 ESF Leakage AST Analysis For Extended Power Uprate With Core Average Exposure,

- FRVS Vent @ 90%, ESF Leakage Flashing Factor = 10%, ESF Leakage = 2.85 gpm, and CR Unfiltered Inleakage = 250 cfm Nuclide Inventory File:

g:\radtrad 3.02\defaults\hepulocal def.txt Plant Power Level:

3.9170E+03 Compartments:

4 Compartment 1:

Sump 3

1.1800E+05 0

0 0

Compartment 2:

Reactor Bldg 3

37

4.OOOOE+06 0

0 1

0 0

Compartment 3:

Environment 2

0.0000E+00 0

0 0

Compartment 4:

Control Room 1

8.5000E+04 0

0 1

0 0

Pathways:

6 Pathway 1:

ESF Leakage to Environment 1

3 2

Pathway 2:

ESF Leakage to Reactor Bldg 1

2 2

Pathway 3:

FRVS Exhaust to Environment 2

3 2

Pathway 4:

Control Room Filtered Air Intake 3

4 2

Pathway 5:

CR Unfiltered Inleakage 3

4 2

Pathway 6:

Control Room Exhaust to Environment 4

3 2

End of Plant Model File 38

Scenario Description Name:

Plant Model Filename:

Source Term:

1 1 1.OOOOE+00 g:\radtrad 3.02\defaults\fgrll&!2.inp g:\radtrad 3.02\defaults\bwr i.rft o.OOO0E+00 1

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

0 o.OOOOE+00 0

0 0

0 Compartments:

4 Compartment 1:

0 1

0 0

0 Compartment 2:

0 1

0 0

1 1.0800E+05 3

o.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 1.0400E-01 9. 9000E+01 0.0000E+00 0.OOOOE+00 7.2000E+02 9. 9000E+01 0.0000E+00 0.OOOOE+00 0

0 Compartment 3:

0 1

0 0

0 Compartment 4:

39

0 1

0 0

1 2.6000OE+i03 3

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

5. GOOCE-01 9. 9000E+01 9. 9000E+01 9. 9000E+01 7 .2000E+02 9. 9000E+01 9. 9000E+01 9. 9000E+01 0

0 Pathways:

Pathway 1:

0 0

0 1

2 0.OOOOE+00 7.6200E-02 0.OOOOE+00 0.OOOOE+00 o.OOOOE+00 1.0400E-01 0.OOOOE+00 0.OOOOE-I0O 0.OOOOE+0O 0.OOOOE+0O 0

0 0

0 Pathway 2:

0 0

0 1

8 o .OOOOE+00 o.OOOOE+00 0 OOOOE+00 0.OOOOE+00 0.0000E+00 1.0420E-01 7.6200E-02 0 OOOOE+00 0.OOOOE+00 0.0000E+00 1.OOOOE-I00 7.6200E-02 0 OOOOE+00 0.OOOOE+00 0.OOOOE+00 2 .OOOOE+00 7.6200E-02 0 OOOOE+00 0.0000E+00 0.OOOOE+00 4 . 000E+00 7.6200E-02 0. 0000E+00 0.OOOOE+00 0.OOOOE+00 8 . 000E+00 7.6200E-02 0 OOOOE+00 0.0000E+00 0.OOOOE+00

2. 4000E+01 7.6200E-02 0.OOOOE+00 0.OOOOE+00 0.0000E+00 7.2000E+02 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0

0 0

0 Pathway 3:

0 0

40

0 0

1 7

o .OOOOE+00 1.9800E+04 0 OOOOE+00 0.0000E+00 0.OOOOE+00 1.0400E-01 1.9800E+04 9. 9000E+01 9.OOOOE+01 9.OOOOE+01 4 .3700E-01 1.5740E+04 9. 9000E+01 9.OOOOE+01 9.OOOOE+01 2 .1040E+00 8.4920E+03 9. 9000E+01 9.OOOOE+01 9.OOOOE+01 4 .1040E+00 7.4250E+03 9. 9000E+01 9.OOOOE+01 9.OOOOE+01 8 . 1040E+00 7. 3130E+03 9. 9000E+01 9.OOOOE+01 9.OOOOE+01 7 .2000E+02 0.OOOOE+00 0 OOOOE+00 0 OOOOE+00 0 OOOOE+00 0

0 0

0 Pathway 4:

0 0

0 1

3 0.OOOOE+00 5.OOOOE+02 0.OOOOE+00 0.0000E+00 0.OOOOE+00 5.OOOOE-01 1. 1000E+03 9. 9000E+01 9.9000E+01 9. 9000E+01 7.2000E+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0

0 0

0 Pathway 5:

0 0

0 1

3 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0. OOOOE+00 0.OOOOE+00 5.0000E-01 2.5000E+02 0. OOOOE+00 0.OOOOE+00 0.OOOOE+00 7.2000E+02 0.OOOOE+00 0.OOOOE+00 0. OOOOE+00 0.0000E+00 0

0 0

0 Pathway 6:

0 0

41

0 1

3 0.0000E+00 5.OOO0E+02 0.0000E+00 0.0000E+00 0.OOOOE+00

5. 0000E-01 1.3500E+03 O.OOOOE+00 0.0000E+00 0.0000E+00 7.2000E+02 0.OOOOE+00 O.O000E+O0 0.OOOOE+00 o.OOOE+00 0

0 0

0 Dose Locations:

3 Location 1:

Exclusion Area Boundary 3

1 2

0.0000E+00 1.9000E-04 7.2000E+02 0.OOOOE+00 1

2 o.0000E+00 3.5000E-04 7.2000E+02 0.OOOOE+00 0

Location 2:

Low Population Zone 3

1 7

0.0000E+00 1.9000E-05 2.OOOOE+00 1.2000E-05 4.0000E+00 8.OOOOE-06 8.0000E+00 4.OOOOE-06 2.4000E+01 1.7000E-06

9. 6000E+01 4.7000E-07 7.2000E+02 0.OOOOE+00 1

q 0.0000E+00 3.5000E-04 8.0000E+00 1.8000E-04

2. 4000E+01 2.3000E-04 7.2000E+02 0.OOOOE+00 0

Location 3:

Control Room 4

0 1

2 0.OOOOE+00 3.5000E-04 7.2000E+02 0.OOOOE+00 4

0.OOOOE+00 1.0000E+00 2.4000E+01 6. OOOOE-01 42

9.6000E+01 4.OOOOE-01 7.2000E+02 0.0000E+00 Effective Volume Location:

1 6

O.OOOOE+00 1.2500E-03 2.OOOOE+00 8.0900E-04 8.OOOOE+00 3.0400E-04 2.4000E+01 2.10OOE-04 9.6000E+01 1.5900E-04 7.2000E+02 0.OOOOE+00 Simulation Parameters:

6 0.0000E+00 1.OOOOE-01 2.OOOOE+00 5.OOOOE-01 8.0000E+00 1.OOOOE+00 2.4000E+01 2.o0000E+00 9.6000E+01 5.OOOOE+00 7.2000E+02 0.0000E+00 Output Filename:

G:\Radtrad 3.o44 1

1 1

0 0

End of Scenario File 43

1. 1. 1. 1. 4#########################4##############################*#######

RADTRAD Version 3.02 run on 8/25/2010 at 0:28:20

1. 1. 1. 1. 4######################

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Plant Description

1. 1. 1. 1. 4############f###########4######################4##

Number of Nuclides = 60 Inventory Power = 1.OOOOE+00 MWth Plant Power Level = 3.9170E+03 MWth Number of compartments = 4 Compartment information Compartment number 1 (Source term fraction = 1.QQOOE+00 Name: Sump Compartment volume = 1.1800E+05 (Cubic feet)

Pathways into and out of compartment 1 Pathway to compartment number 3: ESF Leakage to Environment Pathway to compartment number 2: ESF Leakage to Reactor Bldg Compartment number 2 Name: Reactor Bldg Compartment volume = 4.0000E+06 (Cubic feet)

Removal devices within compartment:

Filter(s)

Pathways into and out of compartment 2 Pathway to compartment number 3: FRVS Exhaust to Environment Pathway from compartment number 1: ESF Leakage to Reactor Bldg Compartment number 3 Name: Environment Pathways into and out of compartment 3 Pathway to compartment number 4: Control Room Filtered Air Intake Pathway to compartment number 4: CR Unfiltered Inleakage Pathway from compartment number 1: ESF Leakage to Environment Pathway from compartment number 2: FRVS Exhaust to Environment Pathway from compartment number 4: Control Room Exhaust to Environment Compartment number 4 Name: Control Room Compartment volume = 8.5000E+04 (Cubic feet)

Removal devices within compartment:

Filter(s)

Pathways into and out of compartment 4 Pathway to compartment number 3: Control Room Exhaust to Environment Pathway from compartment number 3: Control Room Filtered Air Intake Pathway from compartment number 3: CR Unfiltered Inleakage Total number of pathways = 6 RADTRAD Version 3.02 run on 8/25/2010 at 0:28:20 44

Scenario Description

1. 1. 1. 1. 4#####################################

Radioactive Decay is enabled Calculation of Daughters is enabled RELEASE NAME = NUREG 1465 BWR Release Fractions and Timings GAP EARLY IN-VESSEL 0.5000 hrs 1.5000 hrs NOBLES 0. 0000E+00 0.OOOOE+00 IODINE 5. OOOOE-02 2.5000E-01 CESIUM 0.0000E+00 0.OOOOE+00 TELLURIUM 0.0000E+00 0.OOOOE+00 STRONTIUM 0. O000E+00 0.OOOOE+00 BARIUM 0.O000E+00 0.OOOOE+00 RUTHENIUM 0.OOOOE+00 0.OOOOE+00 CERIUM 0 OOOOE+00 0.0000E+00 LANTHANUM 0 OOOOE+00 0.0000E+00 Iodine fractions Aerosol = 0.OOOOE+00 Elemental - 9.7000E-01 Organic - 3.OOOOE-02 COMPARTMENT DATA Compartment number 1: Sump Compartment number 2: Reactor Bldg Compartment Filter Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.OOOOE+00 1.0800E+05 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00

1. 0400E-01 1.0800E+05 9. 9000E+01 0.OOOOE+00 0.OOOOE+00 7.2000E+02 1.0800E+05 9. 9000E+01 0.0000E+00 0.OOOOE+00 Compartment number 3: Environment Compartment number 4: Control Room Compartment Filter Data Time (hr) Flow Rate Filter Efficiencies (%)

(c fm) Aerosol Elemental Organic 0.0000E+00 2.60O0E+03 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 5.OOOOE-01 2.6000E+03 9.9000E+01 9.9000E+01 9.9000E+01 7.2000E+02 2.6000E+03 9.9000E+01 9.9000E+01 9.9000E+01 PATHWAY DATA Pathway number 1: ESF Leakage to Environment 45

Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(c fm) Aeros ol Elemental Organic 0.OOOOE+00 7.6200E-02 0. 0000E +00 0.OOOOE+00 0.0000E+00 1.0400E-01 0.OOOOE+00 0. 0000E +00 0.OOOOE+00 0.OOOOE+00 Pathway number 2: ESF Leakage to Reactor Bldg Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00

1. 0420E-01 7.6200E-02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 1.OOOOE+00 7.6200E-02 0.0000E+00 O.OOOOE+00 0.OOOOE+00 2.OOOOE+00 7.6200E-02 o.OOOOE+00 0.OOOOE+00 0.0000E+00 4.OOOOE+00 7.6200E-02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 8 .0000E+00 7.6200E-02 0.0000E+00 0.OOOOE+00 0.OOOOE+00 2 4000E+01 7.6200E-02 0.OOOOE+00 0.OOOOE+00 0.0000E+00 7.2000E+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 Pathway number 3: FRVS Exhaust to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 1.9800E+04 0.OOOOE+00 0.OOOOE+00 0.0000E+00 1.0400E-01 1.9800E+04 9. 9000E+01 9.OOOOE+01 9.OOOOE+01 4 .3700E-01 1.5740E+04 9. 9000E+01 9.OOOOE+01 9. OOOOE+01 2 1040E+00 8.4920E+03 9. 9000E+01 9. OOOOE+01 9. OOOOE+01 4.1040E+00 7.4250E+03 9. 9000E+01 9. OOOOE+01 9. OOOOE+01 8 1040E+00 7. 3130E+03 9. 9000E+01 9. OOOOE+01 9. OOOOE+01 7 .2000E+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Pathway number 4: Control Room Filtered Air Intake Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.OOOOE+00 5.OOOOE+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00

5. OOOE-01 1. 1000E+03 9.9000E+01 9.9000E+01 9.9000E+01 7.2000E+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Pathway number 5: CR Unfiltered Inleakage Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00

5. 0O0OE-01 2.5000E+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 7.2000E+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Pathway number 6: Control Room Exhaust to Environment 46

Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.OOOOE+00 5.0000E+02 0.0000E+00 0.OOOOE+00 0.0000E+00

5. 0000E-01 1.3500E+03 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.OOOOE+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.OOOOE+00 1.9000E-04 7.2000E+02 0.0000E+00 Location Breathing Rate Data Time (hr) Breathing Rate (mA3

secA-l)

O.0000E+00 3.5000E-04 7.2000E+02 0.0000E+00 Location Low Population Zone is in compartment 3 Location X/Q Data Time (hr) X/Q (s

mA-3) 0.0000E+00 1. 9000E-05 2.0000E+00 1.2000E-05 4.0000E+00 8.0000E-06 8.OOOOE+00 4.0000E-06 2.4000E+01 1 .7000E-06 9.6000E+01 4.7000E-07 7.2000E+02 0 .0000E+00 Location Breathing Rate Data Time (hr) Breathing Rate (mA^3

sec^-l) 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 1.2500E-03 2.0000E+00 8.0900E-04 8.0000E+00 3.0400E-04 2.4000E+01 2.1000E-04 9.6000E+01 1.5900E-04 7.2000E+02 0.0000E+00 Location Breathing Rate Data Time (hr) Breathing Rate ImA3

sec^-l) 0.0O00E+00 3.5000E-04 7.2000E+02 0.00002+00 Location Occupancy Factor Data Time (hr) Occupancy Factor 47

o.OOOOE+00 1.OOOOE+00 2.4000E+01 6.OOOOE-01

9. 6000E+01 4. 0OOOE-01 7.2000E+02 0.OOOOE+00 USER SPECIFIED TIME STEP DATA - SUPPLEMENTAL TIME STEPS Time Time step 0.OOOOE+00 1.0000E-01 2.OOOOE+00 5.0000E-01 8.OOOOE+00 1.0000E+00 2.4000E+01 2.0000E+00 9.6000E+01 5.0000E+00 7.2000E+02 0.0000E+00 48

1. 1. 1. 1. r#####o8################a####

RADTRAD Version 3.02 run on 8/25/2010 at 0:28:20

1. 1. 1. 1. 4############4#######################f#############4##########f###

1. - 1. 4 4 #44## #####

4 44 4 4 4 4 4 44 4 4 4 4 4 4 4 4 44 4 4 44444 4 4 4 4 #4 4 4 4 4 4 4 4 44 4 4 4 4 4 4 4444 #444 4 4 4444 4 Dose Output

4444##4#444#4##################4#44 #############44 #############4#

Exclusion Area Boundary Doses:

Time (h) = 0.1040 Whole Body Thyroid TEDE Delta dose (rem) 1.1200E-03 2. 2383E-01 8.2111E-03 Accumulated dose (rem) 1.1200E-03 2. 2383E-01 8. 2111E-03 Low Population Zone Doses:

Time (h) = 0.1040 Whole Body Thyroid TEDE Delta dose (rem) 1.1200E-04 2.2383E-02 8.2111E-04 Accumulated dose (rem) 1.1200E-04 2.2383E-02 8.2111E-04 Control Room Doses:

Time (h) = 0.1040 Whole Body Thyroid TEDE Delta dose (rem) 5.0348E-06 2. 5461E-02 8.1167E-04 Accumulated dose (rem) 5.0348E-06 2. 5461E-02 8 .1167E-04 Exclusion Area Boundary Doses:

Time (h) = 0.1042 Whole Body Thyroid TEDE Delta dose (rem) 2.2152E-11 4.5956E-09 1.6766E-10 Accumulated dose (rem) 1.1200E-03 2.2383E-01 8.2111E-03 Low Population Zone Doses:

Time (h) = 0.1042 Whole Body Thyroid TEDE Delta dose (rem) 2.2152E-12 4.5956E-10 1. 6766E-Il Accumulated dose (rem) 1.1200E-04 2.2383E-02 8.2111E-04 Control Room Doses:

Time (h) = 0.1042 Whole Body Thyroid TEDE Delta dose (rem) 1.9527E-08 1.0250E-04 3.2649E-06 Accumulated dose (rem) 5.0543E-06 2.5564E-02 8.1494E-04 49

Exclusion Area Boundary Doses:

Time (h) = 0.4370 Whole Body Thyroid TEDE Delta dose (rem) 6.4329E-05 1. 4171E-02 5. 1257E-04 Accumulated dose (rem) 1.1844E-03 2 . 3800E-01 8.7237E-03 Low Population Zone Doses:

Time (h) = 0.4370 Whole Body Thyroid TEDE Delta dose (rem) 6.4329E-06 1. 4171E-03 5 . 1257E-05 Accumulated dose (rem) 1. 1844E-04 2.3800E-02 8.7237E-04 Control Room Doses:

Time (h) = 0.4370 Whole Body Thyroid TEDE Delta dose (rem) 2.9875E-05 1. 6387E-01 5.2146E-03 Accumulated dose (rem) 3.4929E-05 1. 8943E-01 6.0296E-03 Exclusion Area Boundary Doses:

Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 2.6556E-05 6. 1327E-03 2.2039E-04 Accumulated dose (rem) 1.2109E-03 2. 4413E-01 8.9441E-03 Low Population Zone Doses:

Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 2.6556E-06 6. 1327E-04 2.2039E-05 Accumulated dose (rem) 1.2109E-04 2.4413E-02 8. 9441E-04 Control Room Doses:

Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 5.1668E-06 3.0642E-02 9.7352E-04 Accumulated dose (rem) 4.0096E-05 2.2008E-01 7. 0031E-03 Exclusion Area Boundary Doses:

Time (h) = 1.0000 Whole Body Thyroid TEDE Delta dose (rem) 5.6442E-04 1. 4275E-01 5.0700E-03 Accumulated dose (rem) 1.7753E-03 3. 8688E-01 1.4014E-02 Low Population Zone Doses:

Time (h) = 1.0000 Whole Body Thyroid TEDE Delta dose (rem) 5.6442E-05 1.4275E-02 5.0700E-04 Accumulated dose (rem) 1.7753E-04 3.8688E-02 1.4014E-03 Control Room Doses:

Time (h) = 1.0 000 Whole Body Thyroid TEDE Delta dose (rem) 2.4704E-05 1. 5573E-01 4.9405E-03 Accumulated dose (rem) 6.4800E-05 3. 7580E-01 1. 1944E-02 Exclusion Area Boundary Doses:

50

Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 4.2468E-03 1.2949E+00 4. 5001E-02 Accumulated dose (rem) 6.0222E-03 1. 6818E+00 5. 9015E-02 Low Population Zone Doses:

Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 4.2468E-04 1. 2949E-01 4.5001E-03 Accumulated dose (rem) 6.0222E-04 1. 6818E-01 5. 9015E-03 Control Room Doses:

Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 6.0023E-05 3. 9722E-01 1.2561E-02 Accumulated dose (rem) 1.2482E-04 7.7302E-01 2.4504E-02 Exclusion Area Boundary Doses:

Time (h) = 2.1040 Whole Body Thyroid TEDE Delta dose (rem) 7.4299E-04 2. 4712E-01 8. 5105E-03 Accumulated dose (rem) 6.7652E-03 1.9289E+00 6.7526E-02 Low Population Zone Doses:

Time (h) = 2.1040 Whole Body Thyroid TEDE Delta dose (rem) 4.6926E-05 1.5608E-02 5.3750E-04 Accumulated dose (rem) 6.4914E-04 1.8378E-01 6.4390E-03 Control Room Doses:

Time (h) = 2.1040 Whole Body Thyroid TEDE Delta dose (rem) 1.0898E-05 7. 1878E-02 2.2699E-03 Accumulated dose (rem) 1.3572E-04 8. 4490E-01 2.6774E-02 Exclusion Area Boundary Doses:

Time (h) = 4.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.2079E-02 4.7303E+00 1. 6034E-01 Accumulated dose (rem) 1.8844E-02 6.6592E+00 2.2786E-01 Low Population Zone Doses:

Time (h) = 4.0000 Whole Body Thyroid TEDE Delta dose (rem) 7.6290E-04 2. 9876E-01 1. 0127E-02 Accumulated dose (rem) 1.4120E-03 4. 8254E-01 1.6566E-02 Control Room Doses:

Time (h) = 4.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.1455E-04 1.2603E+00 3. 9718E-02 Accumulated dose (rem) 3.5027E-04 2. 1052E+00 6.6492E-02 Exclusion Area Boundary Doses:

Time (h) 4.1040 Whole Body Thyroid TEDE Delta dose (rem) I 8.5773E-04 3. 7283E-01 1. 2521E-02 Accumulated dose (rem) 1.9702E-02 7.0320E+00 2.4038E-01 51

Low Population Zone Doses:

Time (h) = 4.1040 Whole Body Thyroid TEDE Delta dose (rem) 3.6115E-05 1.5698E-02 5.2720E-04 Accumulated dose (rem) 1.4482E-03 4. 9824E-01 1.7093E-02 Control Room Doses:

Time (h) = 4.1040 Whole Body Thyroid TEDE Delta dose (rem) 1.7571E-05 9.4303E-02 2.9676E-03 Accumulated dose (rem) 3.6784E-04 2.1995E+00 6.9460E-02 Exclusion Area Boundary Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.5580E-02 1. 8091E+01 5. 9957E-01 Accumulated dose (rem) 5.5282E-02 2. 5123E+01 8. 3995E-01 Low Population Zone Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.4981E-03 7. 6174E-01 2.5245E-02 Accumulated dose (rem) 2.9462E-03 1.2600E+00 4.2338E-02 Control Room Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.1710E-03 4.8570E+00 1.5259E-01 Accumulated dose (rem) 1.5389E-03 7.0565E+00 2 . 2205E-01 Exclusion Area Boundary Doses:

Time (h) = 8.1040 Whole Body Thyroid TEDE Delta dose (rem) 1.0839E-03 6. 1173E-01 2 . 0109E-02 Accumulated dose (rem) 5.6366E-02 2. 5735E+01 8. 6006E-01 Low Population Zone Doses:

Time (h) = 8.1040 Whole Body Thyroid TEDE Delta dose (rem) 2.2818E-05 6.6233E-03 2.2880E-04 Accumulated dose (rem) 2.9691E-03 1.2666E+00 4.2567E-02 Control Room Doses:

Time (h) = 8.1040 Whole Body Thyroid TEDE Delta dose (rem) 4.4522E-05 1. 5324E-01 4. 8104E-03 Accumulated dose (rem) 1.5834E-03 7.2097E+00 2.2686E-01 Exclusion Area Boundary Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.6596E-01 1.2503E+02 4.0306E+00 Accumulated dose (rem) 2.2232E-01 1.5076E+02 4.8907E+00 Low Population Zone Doses:

52

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.4939E-03 1.3537E+00 4.5337E-02 Accumulated dose (rem) 6.4629E-03 2.6203E+00 8.7904E-02 Control Room Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 4.3795E-03 1. 3414E+01 4. 1906E-01 Accumulated dose (rem) 5.9629E-03 2. 0624E+01 6. 4591E-01 Exclusion Area Boundary Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.5510E-01 5.4093E+02 1. 6803E+01 Accumulated dose (rem) 4.7742E-01 6. 9170E+02 2. 1694E+01 Low Population Zone Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.2824E-03 3. 1805E+00 9.9582E-02 Accumulated dose (rem) 8.7454E-03 5.8008E+00 1.8749E-01 Control Room Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.6277E-03 2.3944E+01 7.3515E-01 Accumulated dose (rem) 8.5906E-03 4 .4568E+01 1..3811E+00 Exclusion Area Boundary Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.3150E-01 1.5330E+03 4.7011E+01 Accumulated dose (rem) 8.0892E-01 2.2247E+03 6. 8705E+01 Low Population Zone Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 8.2003E-04 2.4920E+00 7. 6701E-02 Accumulated dose (rem) 9.5654E-03 8.2927E+00 2. 6419E-01 Control Room Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 9.4437E-04 3. 4157E+01 1.0410E+00 Accumulated dose (rem) 9.5350E-03 7. 8725E+01 2.4221E+00 843

1. 1. 1. 1. 3S######m########m 1-131 Summary Sump Reactor Bldg Environment Time (hr) 1-131 (Curies) 1-131 (Curies) 1-131 (Curies) 0.001 5.8102E+03 0.OOOOE+00 6.2534E-05 0.104 1.0873E+06 0.OOOOE+00 2.1906E+00 0.104 1.0894E+06 0.OOOOE+00 2.1906E+00 53

0. 437 4.5654E+06 3. 5054E+01 2.3299E+00 0.500 5.2229E+06 4 .6388E+01 2 .3903E+00 0.800 1.0440E+07 1. 3136E+02 2. 9877E+00 1.000 1.3915E+07 2.1746E+02 3.8022E+00

1. 300 1.9121E+07 3.8799E+02 5. 9176E+00 1.600 2. 4320E+07 6.0504E+02 9.4075E+00 1.900 2. 9512E+07 8.6530E+02 1 .4589E+01 2.000 3.1242E+07 9. 6112E+02 1. 6744E+01

2. 104 3.1230E+07 1.0618E+03 1.9228E+01 2.500 3. 1185E+07 1 .4747E+03 2 .5634E+01 2.800 3 1151E+07 1.7732E+03 3.1842E+01 3.100 3.1117E+07 2. 0597E+03 3.9169E+01 3.400 3. 1083E+07 2. 3348E+03 4.7568E+01 3.700 3. 1049E+07 2. 5990E+03 5.6997E+01 4 .000 3. 1016E+07 2. 8526E+03 6.7415E+01 4 .104 3. 1004E+07 2. 9381E+03 7. 1250E+01 4.500 3.0959E+07 3.2720E+03 8 4948E+01 4.800 3.0926E+07 3.5146E+03 9. 6287E+01 5.100 3.0892E+07 3.7486E+03 1.0842E+02 5 .400 3.0858E+07 3.9743E+03 1. 2132E+02 5 .700 3.0825E+07 4 1920E+03 1.3497E+02 6.000 3. 0791E+07 4 4018E+03 1.4932E+02 6.300 3.0758E+07 4.6042E+03 1.6437E+02 6.600 3.0724E+07 4.7994E+03 1.8008E+02

6. 900 3.0691E+07 4.9875E+03 1. 9643E+02 7.200 3.0657E+07 5. 1689E+03 2. 1340E+02 7 .500 3.0624E+07 5.3437E+03 2 .3096E+02 7.800 3.0591E+07 5 . 5123E+03 2. 4909E+02 8.000 3.0568E+07 5. 6212E+03 2. 6149E+02 8.104 3.0557E+07 5.6768E+03 2. 6803E+02 8.504 3. 0513E+07 5.8880E+03 2. 9341E+02 8 .804 3. 0479E+07 6.0398E+03 3. 1303E+02 9.100 3.0447E+07 6. 1842E+03 3. 3287E+02 9.400 3. 0413E+07 6.3253E+03 3.5346E+02 9.700 3.0380E+07 6.4613E+03 3.7449E+02 10.000 3.0347E+07 6.5924E+03 3. 9597E+02 10.300 3. 0314E+07 6.7188E+03 4. 1787E+02 24.000 2.8843E+07 9.3458E+03 1. 6816E+03 96.000 2.2208E+07 7.8467E+03 8.6703E+03 720.000 2.3042E+06 8.1418E+02 2.9879E+04 Control Room Time (hr) 1-131 (Curies) 0.001 1.8444E-08

0. 104 6.3833E-04

0. 104 6.3828E-04 0.437 6.0656E-04 0.500 6.1072E-04 0.800 3.3256E-04 1.000 2. 8947E-04 1.300 3.5581E-04 1.600 5. 3073E-04 1.900 7. 8593E-04 2.000 8.8609E-04 2.104 8.7962E-04 2.500 6.9207E-04 2.800 7.2654E-04 54

3.100 8.1693E-04 3.400 9.2866E-04 3.700 1.0468E-03 4.000 1.1649E-03 4.104 1.2053E-03 4.500 1.2385E-03 4.800 1.3099E-03 5.100 1.3947E-03 5.400 1.4834E-03 5.700 1.5720E-03 6.000 1.6587E-03 6.300 1.7430E-03 6.600 1.8244E-03 6.900 1.9031E-03 7.200 1.9789E-03 7.500 2.0521E-03 7.800 2.1227E-03 8.000 2.1683E-03 8.104 1.8379E-03 8.504 1.1821E-03 8.804 1.0142E-03 9.100 9.5403E-04 9.400 9.3925E-04 9.700 9.4438E-04 10.000 9.5776E-04 10.300 9.7432E-04 24.000 1.3808E-03 96.000 8.0385E-04 720.000 6.3152E-05 4C##################################u###e#D#S#######################

Cumulative Dose Summary

1. 1. 1. 1. 4#########################################

Exclusion Area Bounda Low Population Zone Control Room Time Thyroid TEDE Thyroid TEDE Thyroid TEDE (hr) (rem) (rem) (rem) (rem) (rem) (rem) 0.001 6. 3881E-06 2.3446E-07 6. 3881E-07 2.3446E-08 4.1200E-09 1.3135E-10 0.104 2.2383E-01 8.2111E-03 2.2383E-02 8.2111E-04 2.5461E-02 8. 1167E-04

0. 104 2. 2383E-01 8.2111E-03 2.2383E-02 8.2111E-04 2.5564E-02 8.1494E-04 0.437 2. 3800E-01 8.7237E-03 2. 3800E-02 8.7237E-04 1. 8943E-01 6.0296E-03

0. 500 2. 4413E-01 8. 9441E-03 2 4413E-02 8.9441E--04 2.2008E-01 7 . 0031E-03 0.800 3. 0464E-01 1. 1103E-02 3. 0464E-02 1. 1103E-03 3.2723E-01 1.0404E-02 1.000 3. 8688E-01 1. 4014E-02 3. 8688E-02 1. 4014E-03 3. 7580E-01 1. 1944E-02 1.300 5. 9976E-01 2. 1492E-02 5.9976E-02 2.1492E-03 4 .5017E-01 1.4299E-02

1. 600 9. 4959E-01 3.3686E-02 9.4959E-02 3.3686E-03 5. 5349E-01 1.7567E-02

1. 900 1. 4671E+00 5. 1608E-02 1. 4671E-01 5. 1608E-03 7. 0747E-01 2.2434E-02 2 .000 1. 6818E+00 5. 9015E-02 1. 6818E-01 5. 9015E-03 7 .7302E-01 2.4504E-02

2. 104 1. 9289E+00 6.7526E-02 1. 8378E-01 6.4390E-03 8. 4490E-01 2.6774E-02

2. 500 2. 5642E+00 8 . 9311E-02 2. 2391E-01 7.814 9E-03 1. 0781E+00 3. 4135E-02

2. 800 3. 1775E+00 1. 1023E-01 2. 6264E-01 9. 1361E-03 1. 2421E+00 3.9307E-02 3.100 3. 8986E+00 1. 3473E-01 3. 0819E-01 1.0683E-02 1.4209E+00 4.4943E-02 3.400 4 .7224E+00 1. 6261E-01 3. 6022E-01 1.2445E-02 1.6228E+00 5. 1306E-02 3.700 5. 6441E+00 1. 9371E-01 4. 1843E-01 1. 4409ý-02 1. 8507E+00 5.8484E-02 4 .000 6. 6592E+00 2. 2786E-01 4 8254E-01 1.6566 -02 2. 1052E+00 6.6492E-02 4 .104 7. 0320E+00 2.4038E-01 4. 9824E-01 1.7093E-02 2. 1995E+00 6.9460E-02 4 .500 8. 3601E+00 2. 8489E-01 5. 5416E-01 1.8967E-02 2. 5661E+00 8.0997E-02 55

4.800 9.4553E+00 3 .2151E-01 6. 0027E-01 2.0509E-02 2.8564E+00 9. 0127E-02 5.100 1. 0624E+01 3. 6049E-01 6.4947E-01 2.2150E-02 3. 1638E+00 9.97 91E-02 5.400 1. 1863E+01 4. 0173E-01 7. 0163E-01 2.3886E-02 3.4899E+00 1. 1004E-01 5.700 1. 3168E+01 4. 4513E-01 7. 5661E-01 2 . 5714E-02 3.8352E+00 1.2090E-01 6.000 1. 4538E+01 4. 9060E-01 8.1429E-01 2.7628E-02 4.1992E+00 1.3233E-01 6.300 1. 5970E+01 5 . 3803E-01 8. 7457E-01 2.9625E-02 4. 5814E+00 1.4434E-01 6.600 1. 7460E+01 5. 8735E-01 9. 3733E-01 3. 1702E-02 4 9810E+00 1.5689E-01 6.900 1. 9007E+01 6. 3846E-01 1.0025E+00 3.3854E-02 5. 3974E+00 1.6997E-01 7.200 2 . 0608E+01 6. 9128E-01 1.0699E+00 3.6078E-02 5.8299E+00 1. 8355E-01 7 .500 2 .2261E+01 7. 4575E-01 1.1394E+00 3. 8371E-02 6. 2777E+00 1. 9760E-01 7.800 2 . 3962E+01 8. 0177E-01 1.2111E+00 4.0730E-02 6. 7403E+00 2. 1212E-01 8.000 2. 5123E+01 8. 3995E-01 1.2600E+00 4.2338E-02 7.0565E+00 2.2205E-01

8. 104 2. 5735E+01 8. 6006E-01 1.2666E+00 4.2567E-02 7 .2097E+00 2.2686E-01 8.504 2. 8102E+01 9. 3781E-01 1.2922E+00 4. 3451E-02 7.6362E+00 2 4026E-01 8.804 2. 9928E+01 9. 9769E-01 1.3120E+00 4.4131E-02 7.8748E+00 2 4777E-01

9. 100 3. 1769E+I01 1. 0580E+00 1. 3319E+00 4.4817E-02 8.0865E+00 2.5443E-01 9.400 3. 3674E+01 1. 1204E+00 1.3526E+00 4.5525E-02 8.2929E+00 2. 6092E-01 9.700 3. 5616E+01 1.1839E+00 1.3736E+00 4.6246E-02 8.4980E+00 2. 6736E-01

10. 000 3. 7594E+01 1.2486E+00 1.3950E+00 4.6979E-02 8.7048E+00 2.7386E-01 10.300 3. 9606E+01 1. 3143E+00 1. 4168E+00 4.7724E-02 8.9143E+00 2. 8043E-01 24.000 1.5076E+02 4.8907E+00 2.6203E+00 8.7904E-02 2. 0624E+01 6. 4591E-01 96.000 6. 9170E+02 2 . 1694E+01 5.8008E+00 1. 8749E-01 4. 4568E+01 1. 3811E+00 720.000 2.2247E+03 6. 8705E+01 8.2927E+00 2. 6419E-01 7 8725E+01 2. 4221E+00 Worst Two-Hour Doses Note: All of the dose locations are shown below but the worst two-hour dose is only meaningful for the EAB dose location. Please disregard the two-hour worst doses for the other dose locations Exclusion Area Boundary Time Whole Body Thyroid TEDE (hr) (rem) (rem) (rem) 14.2 2.0817E-02 1.6227E+01 5. 2210E-01 Low Population Zone Time Whole Body Thyroid TEDE (hr) (rem) (rem) (rem) 6.0 8.3176E-04 4.4568E-01 1. 4710E-02 Control Room Time Whole Body Thyroid TEDE (hr) (rem) (rem) (rem) 6.1 7.5305E-04 2.8772E+00 9,0335E-02 56

Attachment 3 RADTRAD Output File H250MS550F3.oO

1. 1. 1. 1. 4####################4#####4####*#################

RADTRAD Version 3.02 run on 8/28/2010 at 17:07:43

1. 1. 1. 1. 4#################################

1. 1. 1. 1. 444####4#######4##########################f###################

File information 44## #################if# ################# ##############4###################

Plant file name = G:\Radtrad 3.02\Accept\MDC-1880 R4\H250MS550F3.psf Inventory file name = g:\radtrad 3.02\defaults\hepuloca def.txt Scenario file name = G:\Radtrad 3.02\Accept\MDC-1880 R4\H250MS550F3.psf Release file name = g:\radtrad 3.02\defaults\bwr dba.rft Dose conversion file name = g:\radtrad 3.02\defaults\fgrll&12.inp 44444 #4## #4### 4 #4*44 4 44 4 4 4 #4 4 #4 4 #4 f# # 4 ft

4444 4 if 4 4 #44 # 4 4 4 # if ## 4 ft ft 4 4 ##4# #

4 4 ft #4# ifif4# 4 Radtrad 3.02 1/5/2000 MSIV Leakage AST Analysis For MSIV leakage Calculated at 550F - EAR, LPZ, & CR Doses - MSIV Leakage = 250 scfh and CR Unfiltered Inleakage = 250 cfm Nuclide Inventory File:

g:\radtrad 3.02\defaults\hepuloca def.txt Plant Power Level:

3.9170E+03 Compartments:

6 Compartment 1:

Containment 3

1.6900E+05 1

0 0

1 0

Compartment 2:

MSIV Failed Volume Vl 57

3

1. 1390E+03 0

0 0

Compartment 3:

MSIV Intact Volume V2 3

1.1360E+03 0

0 0

Compartment 4:

Control Room 1

8.5000E+04 0

0 1

0 0

Compartment 5:

Environment 2

0.0000E+00 0

0 0

Compartment 6:

Void 3

1.0000E+05 0

0 0

Pathways:

8 Pathway 1:

Containment to MSIV Failed Volume V1 1

2 2

Pathway 2:

MSIV Failed Volume V1 to Environment 2

Pathway 3:

Containment to MSIV Intact Volume V2 58

1 3

2 Pathway 4:

MSIV Intact Volume V2 to Environment 3

5 2

Pathway 5:

Control Room Filtered Air Intake 5

4 2

Pathway 6:

Control Room Unfiltered Inleakage 5

4 2

Pathway 7:

Control Room Exhaust to Environment 4

5 2

Pathway 8:

Containment to Void 1

6 4

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1 1.0000E+00 g:\radtrad 3.02\defaults\fgrll&12.inp g:\radtrad 3.02\defaults\bwr dba.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 59

o.OOOE+00 3

o.0000E+00 3. 1600E+00 2.OOOOE+00 1.7400E+00 4.OOOOE+00 0.OOOOE+00 1

o.OOOOE+00 0

0 0

3 3

1. O00OE+01 0

Compartment 2:

0 1

0 0

0 Compartment 3:

0 1

0 0

0 Compartment 4:

0 1

0 0

1 2.6000E+03 3

0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 5.OOOOE-01 9. 9000E+01 9. 9000E+01 9. 9000E+01 7.2000E+02 9. 9000E+01 9. 9000E+01 9. 9000E+01 0

0 Compartment 5:

0 1

0 0

0 60

0 0

Compartment 6:

0 1

0 0

0 Pathways:

8 Pathway 1:

0 0

0 1

7 o .OOOOE+00 8.0800E-01 0.OOOOE+/-00 0.OOOOE+00 o.OOOOE+00 1.OOOOE+00 8.0800E-0! 0.OOOOE+00 0.OOOOE+00 o.OOOOE+00 2 .OOOOE+00 4 4600E-01 0. OOOOE+00 0.OOOOE+00 o.OOOOE+00 4 .OOOOE+00 4 4600E-01 0. OOOOE+/-00 0.OOOOE+00 0.OOOOE+00 8 .OOOOE+00 4 4600E-01 0.OOOOE+00 0.OOOOE+00 0.0000E+00

2. 4000E+01 4 4600E-01 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 7 .2000E+02 0.0000E+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0

0 0

0 Pathway 2:

0 0

0 1

7 o .OOOOE+00 4.7830E+00 9. 5750E+01 3. 2470E+01 o . 000E+00 2 .OOOOE+00 4.7830E+00 9. 5750E+01 3. 2470E+01 0.OOOOE+00

3. 0000E+00 4.7830E+00 9.5750E+01 3.7510E+01 0.0000E+00 6.0000E+00 4.7830E+00 9 .5750E+01 6. 0590E+01 0.OOOOE+00

2. 4000E+01 4.7830E+00 9. 5750E+01 7 .7240E+01 0.OOOOE+O0

9. 6000E+01 4.7830E+00 0.OOOOE+00 o.0000E+00 0.OOOOE+00 7.2000E+02 0.OOOOE+00 0.OOOOE+00 o.0000E+00 0.OOOOE--00 0

0 0

0 Pathway 3:

61

0 0

0 1

4 o.0000E+00 5.3900E-01 0.OOOOE+00 0.OOOOE+00 o .OOOOE+00 2.OOOOE+00 2. 9700E-01 0.OOOOE+O0 0.OOOOE+00 o .OOOOE+00

2. 4000E+01 2. 9700E-01 0.OOOOE+00 0. OOOOE+/-00 0.OOOOE+00 7.2000E+02 0.OOOOE+00 0.OOOOE+0O o .OOOOE+0O o.OOOOE+00 0

0 0

0 Pathway 4:

0 0

0 1

7 0.0000E+00 3. 1830E+00 9.7120E+01 2 .8300E+01 0.OOOOE+00 2 .OOOOE+00 3. 1830E+00 9.7120E+01 2 8300E+01 0. OOOOE+00 3.OOOOE+00 3. 1830E+00 9.7120E+01 3.2950E+01 0. OOOOE-I00

6. 0000E+00 3.1830E+00 9.7120E+01 5.4960E+01 o .OOOOE+00

2. 4000E+01 3. 1830E+00 9.7120E+01 7.1940E+01 0. OOOOE+00 9 6000E+01 3. 1830E+00 o OOOOE+00 o.OOOOE+00 0. OOOOE+0O 7.2000E+02 0 OOOOE+00 0 OOOOE+00 0.OOOOE+00 a.QOOOE+00 0

0 0

0 Pathway 5:

0 0

0 1

3 0.OOOOE+00 5.OOOOE+02 o.OOOOE+00 o.OOOOE+00 0.OOOOE+00

5. 0OOOE-01 1.1000E+03 9. 9000E+01 9. 9000E+01 9. 9000E+01 7.2000E+02 0.0000E+00 0.OOOOE+00 0.00O0E+00 0.O000E+00 0

0 0

0 Pathway 6:

0 62

0 0

1 3

o . 000E+00 0.OOOOE+00 0.OOOOE+00 0. 00OE+00 0.OOOOE+00 5 . OOOOE-01 2.5000E+02 0.OOOE+00 0.OOOOE+00 0.0000E+00

7. 2000E+02 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0

0 0

0 Pathway 7:

0 0

0 1

3

0. 0000E+00 5.0000E+02 0.OOOOE+00 0.OOOOE+00 o.OOOOE+00

5. 0000E-01 1.3500E+03 1.OOOOE+02 1.0000E+02 1.OOOOE+02

7. 2000E+02 0.OOOOE+00 0.0000E+00 0.OOOOE+00 o.OOOOE+00 0

0 0

0 Pathway 8:

0 0

1 2

o0-0000E+I00 5. OOOE-01 7.2000E+02 0.0O0OE+00 0

Dose Locations:

3 Location 1:

Exclusion Area Boundary 5

1 2

0.0000E+00 1.9000E-04 7.2000E+02 0.OOOOE+00 63

1 2

o.OOOOE+00 3.5000E-04 7.2000E+02 0.OOOOE+00 0

Location 2:

Low Population Zone 5

1 7

0.0000E+00 1.9000E-05 o2 .OOOOE+0O

.OOOOE+00 1.2000E-05 4 .0000E+00 8.OOOOE-06 8 .0000E+00 4.OOOOE-06 2.4000E+01 1.7000E-06 9.6000E+01 4 .7000E-07 7.2000E+02 0.0000E+00 1

4 O.O 000E+0 3.5000E-04 8.0000E+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.OOOOE+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.OOOOE+00 1.0000E+00 2.4000E+01 6.0000E-01 9.6000E+01 4.OOOOE-01 7.2000E+02 0.0000E+00 Effective Volume Location:

1 6

0.0000E+00 6.1700E-04 2.0000E+00 4.0000E-04 8.OOOOE+00 1.4400E-04 2.4000E+01 1.0000E-04 9.6000E+01 7.4900E-05 7.2000E+02 0.OOOOE+00 Simulation Parameters:

6 0.0000E+00 1.0000E-01 2.0000E+00 5.OOOOE-01 8.OOOOE+00 1.OOOOE+00 2.4000E+01 2.OOOOE+00 9.6000E+01 4.OOOOE+00 7.2000E+02 O.OOOOE+00 Output Filename:

G:\Radtrad 3.o81 64

1 1

1 0

0 End of Scenario File 65

1. 1. 1. 1. 4######4####*#################*####

RADTRAD Version 3.02 run on 8/28/2010 at 17:07:43 4#######################f###############################################

4##4################4#################4#############4################4###

Plant Description 4############################*##4#########4#########4#####################

Number of Nuclides = 60 Inventory Power = 1.0000E+00 MWth Plant Power Level = 3.9170E+03 MWth Number of compartments 6 Compartment information Compartment number 1 (Source term fraction = 1.OOOOE+00 Name: Containment Compartment volume = 1.6900E+05 (Cubic feet)

Removal devices within compartment:

Spray(s)

Deposition Pathways into and out of compartment 1 Pathway to compartment number 2: Containment to MSIV Failed Volume VI Pathway to compartment number 3: Containment to MSIV Intact Volume V2 Pathway to compartment number 6: Containment to Void Compartment number 2 Name: MSIV Failed Volume V1 Compartment volume = 1.1390E+03 (Cubic feet)

Pathways into and out of compartment 2 Pathway to compartment number 5: MSIV Failed Volume Vl to Environment Pathway from compartment number 1: Containment to MSIV Failed Volume Vl Compartment number 3 Name: MSIV Intact Volume V2 Compartment volume = 1.1360E+03 (Cubic feet)

Pathways into and out of compartment 3 Pathway to compartment number 5: MSIV Intact Volume V2 to Environment Pathway from compartment number 1: Containment to MSIV Intact Volume V2 Compartment number 4 Name: Control Room Compartment volume = 8.5000E+04 (Cubic feet)

Removal devices within compartment:

Filter(s)

Pathways into and out of compartment 4 Pathway to compartment number 5: Control Room Exhaust to Environment Pathway from compartment number 5: Control Room Filtered Air Intake Pathway from compartment number 5: Control Room Unfiltered Inleakage Compartment number 5 Name: Environment Pathways into and out of compartment 5 66

Pathway to compartment number 4: Control Room Filtered Air Intake Pathway to compartment number 4: Control Room Unfiltered Inleakage Pathway from compartment number 2: MSIV Failed Volume Vl to Environment Pathway from compartment number 3: MSIV Intact Volume V2 to Environment Pathway from compartment number 4: Control Room Exhaust to Environment Compartment number 6 Name: Void Compartment volume = 1.OOOOE+05 (Cubic feet)

Pathways into and out of compartment 6 Pathway from compartment number 1: Containment to Void Total number of pathways 8 67

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Scenario Description Radioactive Decay is enabled Calculation of Daughters is enabled RELEASE NAME = BWR, NUREG-1465, Tables 3.11 & 3.13, Jun Release Fractions and Timings GAP EARLY IN-VESSEL 0.5000 hrs 1.5000 hrs NOBLES 5.0000E-02 9.5000E-01 IODINE 5.0000E-02 2.5000E-01 CESIUM 5.0000E-02 2.0000E-01 TELLURIUM 0.0000E+00 5.0000E-02 STRONTIUM 0. 0000E+00 2.0000E-02 BARIUM o.0000E+00 2.0000E-02 RUTHENIUM 0.O000E+00 2.5000E-03 CERIUM 0.0000E+00 5.0000E-04 LANTHANUM 0 OOOOE+00 2.0000E-04 Iodine fractions Aerosol - 9.5000E-01 Elemental - 4.8500E-02 Organic - 1.5000E-03 COMPARTMENT DATA Compartment number 1: Containment Sprays: Elemental Removal Data Time (hr) Removal Coef. (hr^-l) 0.0000E+00 3.1600E+00 2.0000E+00 1.7400E+00 4.0000E+00 0.0000E+00 Natural Deposition (Powers' model): Aerosol data Reactor type: 3 Percentile = 10 (%)

Compartment number 2: MSIV Failed Volume Vl Compartment number 3: MSIV Intact Volume V2 Compartment number 4: Control Room Compartment Filter Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 2.6000E+03 0.0000E+00 0.0000E+00 0.0000E+00

5. 0000E-01 2.6000E+03 9.9000E+01 9.9000E+01 9.9000E+01 7.2000E+02 2.6000E+03 9.9000E+01 9.9000E+01 9.9000E+01 68

Compartment number 5: Environment Compartment number 6: Void PATHWAY DATA Pathway number 1: Containment to MSIV Failed Volume V1 Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic a.OOO0E+00 8.0800E-01 0 OOOOE+00 0.OOOOE+00 o.OOOOE+00 1.OOOOE+00 8.0800E-01 0 OOOOE+00 o.OOOOE+00 o.OOOOE+00 2.OOOOE+00 4 4600E-01 0.OOOOE+00 0.0000E+00 0.OOOOE+00 4.OOOOE+00 4 4600E-01 0.0000E+00 0.OOOOE+00 o.OOOOE+00 8.OOOOE+00 4 .4600E-01 0.0000E+00 o.OOOOE+00 o.OOOOE+00 2.4000E+01 4 .4600E-01 0 OOOOE+00 0.OOOOE+00 0.0000E+00 7.2000E+02 0 .OOOOE+00 0.0000E+00 o.OOOOE+00 0.OOOOE+00 Pathway number 2: MSIV Failed Volume Vl to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0;OOOOE+00 4.7830E+00 9. 5750E+01 3.2470E+01 o.OOOOE+00 2.0000E+00 4.7830E+00 9. 5750E+01 3.2470E+01 o.0000E+00 3.0000E+00 4.7830E+00 9. 5750E+01 3.7510E+01 0.0000E+00 6.OOOOE+00 4.7830E+00 9. 5750E+01 6.0590E+01 0.0000E+00

2. 4000E+01 4.7830E+00 9. 5750E+01 7. 7240E+01 0.0000E+00

9. 6000E+01 4.7830E+00 0.OOOOE+00 o OOOOE+00 o.OOOOE+00 7.2000E+02 0. 0000E+00 0.OOOOE+00 0.0000E+00 o.OOOOE+00 Pathway number 3: Containment to MSIV Intact Volume V2 Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 5.3900E-01 O.OOOOE+00 0.0000E+00 0.0000E+00 2.OOOOE+00 2. 9700E-01 0.OOOOE+00 0.0000E+00 0.0000E+00

2. 4000E+01 2. 9700E-01 O.OOOOE+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.OOOOE+00 Pathway number 4: MSIV Intact Volume V2 to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0 OOOOE+00 3. 1ý30E+00 9. 7120E+01 2. 8300E+01 0.OOOOE+00

2. 0000E+00 3. 1830E+00 9.7120E+01 2 . 8300E+01 0.OOOOE+00

3. OOOOE+00 3. 1630E+00 9.7120E+01 3.2950E+01 0.OOOOE+00 6.0000E+00 3. 1830E+00 9.7120E+01 5. 4960E+01 0.OOOOE+00

2. 4000E+01 3. 1630E+00 9. 7120E+01 7.1940E+01 0.OOOOE+00 9.6000E+01 3. 1830E+00 0 OOOOE+00 0.0000E+00 0.OOOOE+00 69

7.2000E+02 O.OOOOE+00 O.OOOOE+00 0.OOOOE+00 O.OOOOE+00 Pathway number 5: Control Room Filtered Air Intake Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic O.OOOOE+00 5.OOOOE+02 O.OOOOE+00 0.OOOOE+00 0.OOOOE+00

5. OOOOE-01 1. 1000E+03 9.9000E+01 9.9000E+01 9.9000E+01 7.2000E+02 0.OOOOE+00 0.OOOOE+00 O.OOOOE+00 0.OOOE+00 Pathway number 6: Control Room Unfiltered Inleakage Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.OOOOE+00 o.OOOOE+00 0.OOOOE+00 0.0000E+00 o.OOOOE+00

5. 0OOOE-01 2.5000E+02 O.OOOOE+00 0.0000E+00 o.OOOOE+00 7.2000E+02 0.0000E+00 0.OOOE+00 0.0000E+00 o.OOOOE+00 Pathway number 7: Control Room Exhaust to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 5.0000E+02 0.0000E+00 0.0000E+00 0.0000E+00

5. 0000E-01 1.3500E+03 1.0000E+02 1.0000E+02 1.0000E+02 7.2000E+02 0.OOOOE+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 8: Containment to Void Convection Data Time (hr) Flow Rate (% / day) 0.0000E+00 5.0000E-01 7.2000E+02 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 1.9000E-04 7.2000E+02 0.OOOOE+00 Location Breathing Rate Data Time (hr) Breathing Rate (m^3

sec^-l) 0.0000E+00 3.5000E-04 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 1.9000E-05 2.0000E+00 1.2000E-05 70

4.OOOE+00 8.OOOOE-06 8.0000E+00 4.OOOOE-06 2.4000E+01 1.7000E-06

9. 6000E+01 4.7000E-07 7.2000E+02 0.OOOOE+00 Location Breathing Rate Data Time (hr) Breathing Rate (mA3

sec^-l) 0.OOOOE+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.OOOE+00 6. 1700E-04 2.OOOOE+00 4.OOOOE-04 8.00OOE+00 1.4400E-04 2.4000E+01 1.0000E-04 9.6000E+01 7.4900E-05 7.2000E+02 0.0000E+00 Location Breathing Rate Data Time (hr) Breathing Rate (m^3

sec^-l) 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.OOO0E-01 9.6000E+01 4.OOC0E-01 7.2000E+02 O.O000E+00 USER SPECIFIED TIME STEP DATA - SUPPLEMENTAL TIME STEPS Time Time step 0.OOOOE+00 1.0000E-01 2.OOOOE+00 5. 0000E-01 8.OOOOE+00 1.0000E+00 2.4000E+01 2.0000E+00

9. 6000E+01 4.OOOOE+00 7.2000E+02 0.OOOOE+00 71

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ft### ft ftfttftf ftfttft ft ft ftftftftft f lift ft ft ft ft ft ft ft ft ft ft ft ft ft ft ft ft ft ft ft ft ft ft#f## ft ft ft ft ft ft ft # ft ft ft ft ft ft ft ft ft ft ft ft ftfftf ftfftf ft f

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Exclusion Area Boundary Doses:

Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 2.2053E-03 1. 3307E-01 7.3255E-03 Accumulated dose (rem) 2.2053E-03 1.3307E-01 7.3255E-03 Low Population Zone Doses:

Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 2.2053E-04 1.3307E-02 7.3255E-04 Accumulated dose (rem) 2.2053E-04 1.3307E-02 7.3255E-04 Control Room Doses:

Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 1.262SE-05 1.9956E-02 7.7862E-04 Accumulated dose (rem) 1.262SE-05 1.9956E-02 7.7862E-04 Exclusion Area Boundary Doses:

Time (h) = 1.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.0603E-02 8. 5103E-01 5. 6130E-02 Accumulated dose (rem) 2.2808E-02 9. 8410E-01 6.3456E-02 Low Population Zone Doses:

Time (h) = 1.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.0603E-03 8. 5103E-02 5. 6130E-03 Accumulated dose (rem) 2.2808E-03 9. 8410E-02 6.3456E-03 Control Room Doses:

Time (h) = 1.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.5460E-04 1.0896E-01 4.7170E-03 Accumulated dose (rem) 3.6723E-04 1.2891E-01 5.4956E-03 72

Exclusion Area Boundary Doses:

Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.3544E-01 6.8854E+00 5. 6560E-01 Accumulated dose (rem) 2.5825E-01 7.8696E+00 6. 2905E-01 Low Population Zone Doses:

Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.3544E-02 6. 8854E-01 5.6560E-02 Accumulated dose (rem) 2.5825E-02 7 .8696E-01 6.2905E-02 Control Room Doses:

Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 8.4287E-03 9. 7167E-01 5.3799E-02 Accumulated dose (rem) 8.7959E-03 1. 1006E+00 5.9294E-02 Exclusion Area Boundary Doses:

Time (h) = 3.0000 Whole Body Thyroid TEDE Delta dose (rem) 4.5227E-01 1. 2515E+01 1.0847E+00 Accumulated dose (rem) 7.1052E-01 2.0385E+01 1 . 7138E+00 Low Population Zone Doses:

Time (h) = 3.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.8565E-02 7. 9044E-01 6. 8510E-02 Accumulated dose (rem) 5.4389E-02 1.5774E+00 1.3142E-01 Control Room Doses:

Time (h) = 3.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.1853E-02 1.7406E+00 1.0869E-01 Accumulated dose (rem) 3.0649E-02 2. 8412E+00 1.6798E-01 Exclusion Area Boundary Doses:

Time (h) = 4.0000 Whole Body Thyroid TEDE Delta dose (rem) 4.8300E-01 1.2105E+01 1. 1060E+00 Accumulated dose (rem) 1.1935E+00 3. 2490E+01 2. 8198E+00 Low Population Zone Doses:

Time (h) = 4.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.0505E-02 7. 6450E-01 6. 9851E-02 Accumulated dose (rem) 8.4894E-02 2. 3419E+00 2.0127E-01 Control Room Doses:

Time (hI) = 4.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.7481E-02 1.7296E+00 1. 1609E-01 Accumulated dose (rem) 5.8130E-02 4.5708E+00 2.8407E-01 Exclusion Area Boundary Doses:

73

Time (h) = 6.0000 Whole Body Thyroid TEDE Delta dose (rem) 9.0232E-01 1. 9189E+01 1.8897E+00 Accumulated dose (rem) 2.0958E+00 5. 1679E+01 4.7095E+00 Low Population Zone Doses:

Time (h) = 6.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.7992E-02 8.0797E-01 7.9566E-02 Accumulated dose (rem) 1.2289E-01 3.1499E+00 2. 8083E-01 Control Room Doses:

Time (h) = 6.0000 Whole Body Thyroid TEDE Delta dose (rem) 5.9490E-02 2.8426E+00 2. 0606E-01 Accumulated dose (rem) 2.21762E-01 7.4134E+00 4. 9013E-01 Exclusion Area Boundary Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 7.4524E-01 1.2597E+01 1. 3961E+00 Accumulated dose (rem) 2.8411E+00 6. 4275E+01 6.1056E+00 Low Population Zone Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.1378E-02 5. 3038E-01 5.8783E-02 Accumulated dose (rem) 1.5427E-01 3.6803E+00 3.3962E-01 Control Room Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 5.4509E-02 1.9023E+00 1.5290E-01 Accumulated dose (rem) 1.7213E-01 9.3156E+00 6.4304E-01 Exclusion Area Boundary Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.7472E+00 3.5174E+01 4.3026E+00 Accumulated dose (rem) 5.5882E+00 9.9449E+01 1.0408E+01 Low Population Zone Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 5.7835E-02 3 .8083E-01 7.4676E-02 Accumulated dose (rem) 2.1210E-01 4.0611E+00 4.1429E-01 Control Room Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 9.3680E-02 2.0278E+00 1.8566E-01 Accumulated dose (rem) 2.6581E-01 1.1343E+01 8.2869E-01 Exclusion Area Boundary Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.5881E+00 5.7839E+01 5.3768E+00 Accumulated dose (rem) 9.1763E+00 1.5729E+02 1.5785E+01 74

Low Population Zone Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.2104E-02 3.4008E-01 4.2621E-02 Accumulated dose (rem) 2.4420E-01 4 .4012E+00 4. 5691E-01 Control Room Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 4.5112E-02 1.2225E+00 8.2968E-02 Accumulated dose (rem) 3.1092E-01 1. 2566E+01 9.1166E-01 Exclusion Area Boundary Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 5.6486E+00 1.6309E+02 1.0629E+01 Accumulated dose (rem) 1.4825E+01 3.2038E+02 2. 6414E+01 Low Population Zone Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.3973E-02 2. 6512E-01 2.2069E-02 Accumulated dose (rem) 2.5818E-01 4.6663E+00 4.7898E-01 Control Room Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.5126E-02 1. 7116E+00 8.7394E-02 Accumulated dose (rem) 3.4605E-01 1. 4278E+01 9. 9905E-01 837

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1-131 Summary

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Containment MSIV Failed Volume V1 MSIV Intact Volume V2 Time (hr) 1-131 (Curies) 1-131 (Curies) 1-131 (Curies) 0.001 5.8100E+03 4.6295E-04 3.0883E-04 0.400 3.5187E+06 2.1080E+02 1.4225E+02 0.500 4.2430E+06 3.1558E+02 2.1357E+02 0.800 8 .9371E+06 8.3174E+02 5.6665E+02 1.000 1.2182E+07 1.3831E+03 9.4607E+02 1.300 1. 6447E+07 2.4732E+03 1.7033E+03 1.600 2.0187E+07 3.8134E+03 2.6459E+03 1.900 2.3521E+07 5.3472E+03 3.7387E+03

2. 000 2.4555E+07 5.8935E+03 4.1314E+03 2 .300 1. 9304E+07 6.4824E+03 4.6147E+03

2. 600 1.4040E+07 6.7593E+03 4.8926E+03

2. 900 1.0218E+07 6.8102E+03 5.0179E+03 3.000 9.1924E+06 6.7902E+03 5.0341E+03 3.300 6.6963E+06 6.6494E+03 5.0245E+03 3.600 4.8823E+06 6.4216E+03 4.9497E+03 3.900 3.5636E+06 6.1396E+03 4.8307E+03 4.000 3.2095E+06 6.0378E+03 4.7841E+03 4.300 2.3506E+06 5.7188E+03 4.6294E+03 75

4. 600 1.7255E+06 5. 3897E+03 4.4598E+03

4. 900 1.2705E+06 5. 0605E+03 4.2822E+03 5.200 9.7705E+05 4. 7379E+03 4 .1016E+03 5.500 8. 1516E+05 4. 4297E+03 3. 9237E+03 5.800 6. 8165E+05 4. 1374E+03 3. 7502E+03 6.000 6. 0591E+05 3. 9514E+03 3. 6372E+03 6.300 5. 0909E+05 3. 6857E+03 3. 4722E+03 6.600 4. 2923E+05 3.4355E+03 3. 3127E+03 6.900 3. 6338E+05 3.2004E+03 3. 1589E+03 7.200 3. 0906E+05 2.9799E+03 3 .0110E+03 7.500 2. 6426E+05 2.7734E+03 2 .8690E+03 7.800 2 .2730E+05 2.5802E+03 2. 7329E+03 8 .000 2 .0634E+05 2.4585E+03 2 .6453E+03 8.300 1. 7953E+05 2.2862E+03 2 . 5187E+03 8 .600 1. 5883E+05 2.1254E+03 2. 3978E+03 8 900 1. 4249E+05 1.9757E+03 2 .2823E+03 9.200 1.2866E+05 1.8363E+03 2. 1721E+03 9.500 1. 1697E+05 1.7066E+03 2. 0671E+03 9.800 1.0708E+05 1.5859E+03 1. 9670E+03 10.100 9. 8715E+04 1.4738E+03 1. 8716E+03 10.400 9. 1634E+04 1.3695E+03 1. 7808E+03 24.000 5.0565E+04 7.4159E+01 2. 0294E+02 96.000 3.7730E+04 2.3756E+01 2. 3732E+01 720.000 2.9870E+03 1.8807E+00 1. 8788E+00 Control Room Environment Void Time (hr) 1-131 (Curies) 1-131 (Curies) 1-131 (Curies) 0.001 3.2371E-13 2.2234E-09 3.3623E-04 0.400 9.8009E-05 6.9821E-01 1.5851E+02 0.500 1.8073E-04 1.2998E+00 2.3939E+02 0.800 2.7708E-04 4.9192E+00 6.4402E+02 1.000 4.3663E-04 9.5759E+00 1.0844E+03 1.300 8.1099E-04 2.1190E+01 1.9805E+03

1. 600 1.3225E-03 3.9484E+01 3.1251E+03 1.900 1.9424E-03 6. 5420E+01 4.4892E+03 2.000 2.1688E-03 7. 5895E+01 4.9886E+03 2.300 2.1040E-03 1.1037E+02 6.3838E+03

2. 600 2.1437E-03 1. 4698E+02 7.4104E+03 2.900 2.1845E-03 1. 8438E+02 8.1548E+03 3.000 2.1920E-03 1.9684E+02 8.3542E+03 3.300 2.1762E-03 2. 3342E+02 8.8384E+03

3. 600 2.1397E-03 2. 6914E+02 9.1887E+03

3. 900 2.0837E-03 3. 0368E+02 9.4417E+03 4.000 2.0616E-03 3.1489E+02 9.5092E+03 4.300 1.9873E-03 3.4758E+02 9.6724E+03

4. 600 1.9052E-03 3.7878E+02 9.7896E+03

4. 900 1.8192E-03 4. 0847E+02 9.8731E+03 5.200 1.7321E-03 4 .3668E+02 9.9327E+03

5. 500 1.6461E-03 4. 6345E+02 9. 9791E+03

5. 800 1.5628E-03 4 .8884E+02 1 .0016E+04 6.000 1.5092E-03 5. 0504E+02 1. 0037E+04 6.300 1.3907E-03 5.2706E+02 1. 0062E+04 6.600 1.3017E-03 5.4795E+02 1 .0082E+04 6.900 1.2275E-03 5.6778E+02 1. 0097E+04 7.200 1.1619E-03 5.8661E+02 1. 0108E+04 7.500 1.1019E-03 6.0449E+02 1.0116E+04 7.800 1.0461E-03 6.2148E+02 1 .0122E+04 76

8.000 1. 0110E-03 6.3235E+02 1.0124E+04 8.300 6.2760E-04 6.4798E+02 1.0127E+04 8.600 4.5171E-04 6.6285E+02 1 . 0128E+04

8. 900 3. 6669E-04 6.7703E+02 1. 0127E+04 9.200 3. 2176E-04 6.9053E+02 1.0126E+04 9.500 2. 9476E-04 7 .0342E+02 1 . 0124E+04 9.800 2. 7605E-04 7.1573E+02 1 . 0121E+04 10.100 2. 6139E-04 7.2750E+02 1. 0118E+04 10.400 2. 4889E-04 7.3875E+02 1.0114E+04 24.000 8.7389E-05 1.0132E+03 9.8364E+03 96.000 3.9377E-05 1.7589E+03 8.2566E+03 720.000 2. 6309E-06 4. 0148E+03 1.3322E+03 C################################################################S##

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) 0.001 2.2842E-10 1.2231E-11 2 .2842E-11 1.2231E-12 7. 2717E-14 2 .7887E-15 0.400 7. 1550E-02 3. 9203E-03 7 .1550E-03 3.9203E-04 8.7395E-03 3 4031E-04 0.500 1.3307E-01 7.3255E-03 1.3307E-02 7.3255E-04 1.9956E-02 7.7862E-04 0.800 5.0401E-01 2. 9953E-02 5 . 0401E-02 2.9953E-03 7.2142E-02 2.9209E-03 1 .000 9.8410E-01 6.3456E-02 9 8410E-02 6.3456E-03 1.2891E-01 5.4956E-03 1.300 2. 1868E+00 1.5524E-01 2 1868E-01 1.5524E-02 2.7779E-01 1.2924E-02 1.600 4.0861E+00 3.0930E-01 4.0861E-01 3.0930E-02 5. 3582E-01 2 .6845E-02 1.900 6.7811E+00 5.3600E-01 6.7811E-01 5.3600E-02 9. 3305E-01 4.9481E-02 2.000 7.8696E+00 6.2905E-01 7.8696E-01 6.2905E-02 1. 1006E+00 5.9294E-02 2.300 1.1447E+01 9.3606E-01 1 .0129E+00 8.2295E-02 1. 6190E+00 9.0542E-02

2. 600 1.5239E+01 1.2634E+00 1 .2524E+00 1.0297E-01 2. 1366E+00 1.2282E-01

2. 900 1.9100E+01 1 .6005E+00 1.4962E+00 1.2426E-01 2.6639E+00 1.5651E-01 3.000 2.0385E+01 1.7138E+00 1.5774E+00 1.3142E-01 2. 8412E+00 1.67 98E-01 3.300 2 .4149E+01 2. 0515E+00 1.8151E+00 1.5275E-01 3. 3716E+00 2.0281E-01

3. 600 2.7813E+01 2 .3855E+00 2.0466E+00 1.7384E-01 3.8944E+00 2.3782E-01

3. 900 3.1345E+01 2.7126E+00 2.2696E+00 1.9450E-01 4.4044E+00 2.7260E-01 4.000 3.2490E+01 2 8198E+00 2. 3419E+00 2.0127E-01 4.5708E+00 2 .8407E-01 4.300 3. 5817E+01 3. 1347E+00 2.4820E+00 2. 1453E-01 5.0576E+00 3 .1800E-01

4. 600 3.8983E+01 3.4390E+00 2. 6153E+00 2.2734E-01 5.5241E+00 3. 5103E-01

4. 900 4.1986E+01 3.7322E+00 2.7418E+00 2.3969E-01 5.9689E+00 3. 8301E-01 5.200 4.4830E+01 4. 0139E+00 2. 8615E+00 2.5155E-01 6.3916E+00 4.1383E-01 5.500 4. 7519E+01 4. 2841E+00 2. 9747E+00 2. 6292E-01 6.7924E+00 4. 4345E-01 5.800 5. 0061E+01 4.5430E+00 3.0818E+00 2. 7382E-01 7.1719E+00 4. 7186E-01 6.000 5. 1679E+01 4.7095E+00 3.1499E+00 2 .8083E-01 7 .4134E+00 4.9013E-01 6.300 5.3876E+01 4.9463E+00 3 .2424E+00 2 . 9080E-01 7.7540E+00 5. 1638E-01 6.600 5. 5955E+01 5.1728E+00 3.3299E+00 3.0034E-01 8.0698E+00 5.4129E-01 6.900 5.7921E+01 5.3895E+00 3.4127E+00 3.0946E-01 8 .3658E+00 5. 6501E-01 7.200 5. 9782E+01 5.5966E+00 3.4911E+00 3.1819E-01 8.6446E+00 5. 8763E-01 7.500 6. 1543E+01 5.7947E+00 3.5652E+00 3 .2653E-01 8.9079E+00 6.0921E-01 7.800 6.3212E+01 5.9840E+00 3.6355E+00 3.3450E-01 9.1570E+00 6. 2982E-01 8.000 6. 4275E+01 6. 1056E+00 3.6803E+00 3.3962E-01 9.3156E+00 6. 4304E-01 8.300 6. 5802E+01 6. 2813E+00 3.6968E+00 3.4252E-01 9.4996E+00 6. 5924E-01

8. 600 6.7249E+01 6.4493E+00 3 .7125E+00 3.4531E-01 9.6215E+00 6. 7100E-01 8.900 6. 8624E+01 6.6100E+00 3.7273E+00 3. 4799E-01 9.7143E+00 6.8036E-01 9.200 6. 9930E+01 6.7638E+00 3.7415E+00 3.5056E-01 9.7926E+00 6.8828E-01 9.500 7. 1172E+01 6. 9111E+00 3.7549E+00 3. 5302E-01 9.8626E+00 6. 9526E-01 9.800 7. 2354E+01 7 . 0521E+00 3.7677E+00 3. 5540E-01 9.9273E+00 7.0159E-01 77

10.100 7. 3481E+01 7.1873E+00 3.7799E+00 3.5768E-01 9.9881E+00 7.0741E-01 10.400 7. 4555E+01 7.3169E+00 3.7916E+00 3.5987E-01 1.0046E+01 7.1283E-01 24.000 9. 9449E+01 1.0408E+01 4.0611E+00 4.1429E-01 1.1343E+01 8.2869E-01 96.000 1.5729E+02 1.5785E+01 4.4012E+00 4.5691E-01 1.2566E+01 9.1166E-01 720.000 3.2038E+02 2.6414E+01 4.6663E+00 4.7898E-01 1.4278E+01 9.9905E-01

1. 1. 1. 1. 4########################################4###

Worst Two-Hour Doses Note: All of the dose locations are shown below but the worst two-hour dose is only meaningful for the EAB dose location. Please disregard the two-hour worst doses for the other dose locations

1. 1. 1. 1. 4##########################

Exclusion Area Boundary Time Whole Body Thyroid TEDE (hr) (rem) (rem) (rem) 2.3 9.5066E-01 2.4370E+01 2. 1986E+00 Low Population Zone Time Whole Body Thyroid TEDE (hr) (rem) (rem) (rem) 1.6 6.0281E-02 1.6380E+00 1. 4291E-01 Control Room Time Whole Body Thyroid TEDE (hr) (rem) (rem) (rem) 2.6 5.4862E-02 3.3875E+00 2. 2821E-01 78 LR-NI0-0341 Corrected Proposed Changes to the HCGS Technical Specifications (Facility Operating License NPF-57)

Technic*a[ Specification Page 5.3.1 5-4

DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 764 fuel assemblies. and shall be limitod te itheo . o....

oe..mblies e b.. rovod Eer uon in BWRo Each assembly shall apbn consist of a matrix of Zircalloy or ZIRLO fuel rods with an initial composition of natural or slightly enriched uranium dioxide (U02) as fuel material and water rods. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with NRC staff approved codes and methods and have been shown by tests or analyses to comply with all safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.

A maximum of twelve GE14i Isotope Test Assemblies may be placed in non-limiting core regions, beginning with Reload 16 Cycle 17 core reload, with the purpose of obtaining surveillance data to verify that the GE14i cobalt Isotope Test Assemblies perform satisfactorily in service (prior to evaluating a future license amendment for use of these design features on a production basis). Each GE14i assembly contains a small number of Zircaloy-2 clad isotope rods containing Cobalt-59. Cobalt-59 targets will transition into Cobalt-60 isotope targets during cycle irradiation of the assemblies. Details of the GE14i assemblies are contained in GE-Hitachi report NEDC-33529P, "Safety Analysis Report to Support Introduction of GE14i Isotope Test Assemblies (ITAs) in Hope Creek Generating Station," Revision 0, dated December 2009.

CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 185 cruciform shaped control rod assemblies. The control material shall be boron carbide powder (B 4 C) and/or hafnium metal. The absorber material has a nominal absorber length of 143 inches.

5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:

a. In accordance with the code requirements specified in Section 5.2 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements,

b. For a pressure of:

1. 1250 psig on the suction side of the recirculation pump.

2. 1500 psig from the recirculation pump discharge to the jet pumps.

c. For a temperature of 575 0 F.

VOLUME 5.4.2 The total water and steam volume of the reactor vessel and recirculation system is approximately 21,970 cubic feet at a nominal steam dome saturation temperature of 547 0 F.

5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1.1-1.

HOPE CREEK 5-4 Amendment No. -

v t e Letter Sequence Supplement
TAC:ME2949, (Approved, Closed)
Initiation Request, Request, Request, Request, Request, Request, Request, Request, Request, Request Acceptance, Acceptance Supplement, Supplement, Supplement, Supplement Administration Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance Questions 28 January 2010 8 April 2010 24 June 2010 Answers 11 May 2010 10 June 2010 28 July 2010 Results Approval Other: ML093640198
MONTHYEAR2010-04-08 [Table View]

LR-N10-0341, Supplement - License Amendment Request (H09-01) Supporting the Use of Co-60 Isotope Test Assemblies (Isotope Generation Pilot Project)

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LR-N10-0341, Supplement - License Amendment Request (H09-01) Supporting the Use of Co-60 Isotope Test Assemblies (Isotope Generation Pilot Project)

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