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Calculation - DC00040-121 - Steam Generator Tube Rupture - TSC
	ML14324A325
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Site:	Summer
Issue date:	07/30/2012
From:	Waselus M; South Carolina Electric & Gas Co
To:	; Office of Nuclear Reactor Regulation
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ML14324A264	List: ML14324A217; ML14324A323; ML14324A324; ML14324A325; ML14324A327; RC-14-0179, Calculation - DC00040-119 - Reactor Coolant Pump Locked Rotor - TSC; RC-14-0179, Calculation - DC00040-120 - Fuel Handling Accident -TSC; RC-14-0179, Calculation - DC00040-121 - Steam Generator Tube Rupture - TSC; RC-14-0179, Calculation - DC00040-122 - Loss of Coolant Accident - TSC; RC-14-0179, Calculation - DC00040-123 - Rod Ejection Accident - TSC; RC-14-0179, Virgil C. Summer Nuclear Station (VCSNS) Unit 1 - License Amendment Request LAR-13-02396 Request for NRC Approval of Changes to the Radiation Emergency Plan;
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	LAR-13-02396, RC-14-0179 DC00040-121, Rev. 0
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ES-412 ATTACHMENT I PAGE 1 OF 2 REVISION 5 Subject Code SOUTH CAROLINA ELECTRIC AND GAS COMPANY 004 CALCULATION RECORD Page 1 of 83 Calculation Title Calculation Number Revision Status Steam Generator Tube Ru ture - TSC D000040-121 0

A Parent Document System Safety Class q Partial Calc. Revision ECR-50786 N/A q NN q QR SR Complete Calc. Revision Originator Discipline Organization Date XREF Number Michael Waselus AE WorleyParsons 07/30/2012 N/A CALCULATION INFORMATION Content

Description:

This calculation determines the impact of the Alternate Source Term (AST) on the new Nuclear Operations Building (NOB) VC Summer Unit 1 Technical Support Center (TSC) dose following a postulated Steam Generator Tube Rupture (SGTG). This analysis is performed in accordance with the requirements of Appendix F of the USNRC Regulatory Guide 1.183.

Affected Components/Calculations/Documents: FSAR Section 15.4.3 Piping Reconciliation Completed per QA-CAR-0089-18:

qThis Revision q Previous Revision N/A Contains Preliminary Data/Assumptions: No q Yes, Affected Pages:

Computer Program Used:

q No Yes, Validated per WorleyParsons computer program validation process (others) vendors name q Yes, Validated in accordance with SAP-1040/ES-413 (ref. 3.4 & 3.5) q Yes, Validated [ES-0412]

q Computer Program Validation Calculation VERIFICATION q Continued, Attachment Scope:

Verify the accuracy of input, methodology, output and assure that the calculation is in compliance with ES-412.

Verifier: M. Feehan Assigned by: P. Bunker

-?.o f Z En i eenn Personnel /Date Ow, is Acceptance Review

/WA can mx/30/2 o,2 Z01z Verifier/Date Responsible En i eer/Date Required for all ngineering work performed by contractor personnel not enrolled in the VCSNS Engineering Training Program RECORDS

-7A10 X t To Records Mgmt: Ik (LN 18-Z -1 ^}-

A roval/Date° Initials/Date A

Distribution: Calc File (Original)

ES-412 ATTACHMENT I PAGE 2 OF 2 REVISION 5 SOUTH CAROLINA ELECTRIC & GAS COMPANY REVISION

SUMMARY

Calculation Number DC00040-121 Revision Number Summary Description Page 2 of 83 0

Initial Issue

DO00040-121, Revision 0 Page 3 of 83 TABLE OF CONTENTS 1.0 PURPOSE................................................................................................................ 5 2.0 COMPUTER CODE...............................................................................................5 3.0 ASSUMPTIONS.....................................................................................................5 4.0 DESIGN INPUTS.................................................................................................... 8 5.0 METHODOLOGY................................................................................................12 5.1 Source Term with Pre-Existing Iodine Spike........................................................ 12 5.1.1 Activity in Reactor Coolant'Released Due to Tube Rupture Faulted SG.............. 13 5.1.2 Activity in Secondary Coolant Released from Faulted SG................................... 14 5.1.3 1.0 gpm SG Tube Leak - Activity Release 0-2 hr................................................. 16 5.1.4 1.0 gpm SG Tube Leak - Activity Release 2 - 8 hr............................................... 17 5.1.5 1.0 gpm SG Tube Leak - Activity Release 8-24 hr............................................... 18 5.1.6 Secondary Coolant Activity Release from Intact SGs........................................... 19 5.1.7 Pre-Existing Total Activity Released 0 - 2 hrs 1.0 gpm........................................ 20 5.1.8 Pre-Existing Spike Total Activity Released.......................................................... 21 5.1.9 Pre-Existing Spike Fraction of Total Activity Released........................................ 22 5.2 Source Term with Concurrent Iodine Spike.......................................................... 23 5.2.1 Primary Coolant Released to Faulted SG due to Tube Rupture 0 - 30 min........... 24 5.2.2 Activity in Secondary Coolant Released from Faulted SG...................................25 5.2.3 1.0 gpm SG Tube Leak - Activity Release 0-2 hr................................................. 28 5.2.4 1.0 gpm SG Tube Leak - Activity Release 2 - 8 hr...............................................29 5.2.5 Concurrent Iodine With Initial RC Activity at 1µCi/gm DE 1-131 8 - 24 hr........30 5.2.6 Concurrent Spike Secondary Coolant Activity Release from Intact SG............... 31 5.2.7 Concurrent Spike Total Activity Released 0 - 2 hrs 1.0 gpm................................32 5.2.8 Concurrent Spike Total Activity Released 2 - 8 hrs 1.0 gpm................................33 5.2.9 Concurrent Spike Fraction Total Activity Released..............................................34 5.3 TSC ventilation system parameters:...................................................................... 35 6.0 RADTRAD MODELS..........................................................................................36 6.1 SGTR Design Case-RADTRAD Models............................................................. 36 6.1.1 RADTRAD Model - SGTR - Design Basis Case................................................ 36 6.1.2 RADTRAD Volume 1 represents the Containment.............................................. 36 6.1.3 RADTRAD Volume 2 represents the Environment..............................................36 6.1.4 RADTRAD Volume 3 represents the Technical Support Center..........................36 6.1.5 RADTRAD Pathway 1 represents the Containment leakage term........................37 6.1.6 RADTRAD Pathway 2 represents the TSC Outside Air Intake Pathway.............37 6.1.7 RADTRAD Pathway 3 represents the TSC Unfiltered Air Inleakage Pathway.... 37 6.1.8 RADTRAD Pathway 4 represents the TSC Exhaust Air Pathway........................ 37 6.1.9 RADTRAD Pathway 5 represents the TSC Emergency Recirculation Pathway... 37 6.1.10 RADTRAD Dose Location 1-Protected TSC.................................................. 37 6.1.11 RADTRAD Dose Location 2 - EAB................................................................. 37 6.1.12 RADTRAD Dose Location 3 - LPZ................................................................. 37 6.1.13 RADTRAD Source Term:................................................................................. 38 6.1.14 RADTRAD Control Options:............................................................................ 38 7.0 RESULTS and CONCLUSIONS..........................................................................38 8.0 DISPOSITION of RESULTS................................................................................38

9.0 REFERENCES

...................................................................................................... 39

DO00040-121, Revision 0 Page 4 of 83 Attachment No. 1 RADTRAD Model............................................................................... 41 Attachment No. 2 RADTRAD NIF and RFT Files.......................................................... 43 Attachment No. 3 RADTRAD Pre-existing Spike...........................................................52 Attachment No. 4 RADTRAD Concurrent Spike............................................................ 68

D000040-121, Revision 0 Page 5 of 83 1.0 PURPOSE The purpose of this calculation is to assess the potential radiological consequences in the Technical Support Center (TSC) located in the new Nuclear Operations Building (NOB) following a postulated Steam Generator Tube Rupture (SGTR) accident in VC Summer Nuclear Plant Unit 1. The. analysis is performed in accordance with the requirements of USNRC Regulatory Guide 1.183 (Reference 1). No fuel melt or fuel clad breach is postulated for the SGTR event at VCS. Consistent with RG 1.183 Appendix F, Section 2, if no or minimal fuel damage is postulated for the limiting event, the activity release should be the maximum allowed by technical specification for two cases of iodine spiking (1) maximum pre-existing (pre-accident) iodine. spike and (2) maximum concurrent iodine spike.

The amount of activity that is released to the environment depends on the primary-to-secondary break flow, break flow flashing fractions, intact steam generator (SG) leakage, partitioning of nuclides between the liquid and steam phases, the mass of fluid released from the steam generators and liquid-vapor partitioning all of which are considered in the following calculation.

2.0 COMPUTER CODE RADTRAD 3.03 validated by WorleyParsons 5/27/2003.

3.0 ASSUMPTIONS 1.

The analysis is consistent with the guidance provided in USNRC Regulatory Guide 1.183 (Reference 1), Appendices F and E (for activity transport). No exceptions to the guidance within RG 1.183 or Appendices F & E are taken.

2.

No fuel melt or fuel clad breach is postulated for the SGTR event. This assumption is.

consistent with the VCS current licensing basis as stated in FSAR Section 15.4.3.4.

3.

Reactor coolant (RC) and secondary coolant activities during the concurrent and pre-existing iodine spike for iodine and noble gases are provided in Reference 4. The reactor coolant DE I-131 values are based on Technical Specification (TS) 3.4.8 limit of 1.0 µCi/gm DE I-131(Reference 7) for the concurrent spike scenario and 60 µCi/gm DE 1-131 (Reference 7) for the pre-existing spike scenario. Per Reference 1, Appendix F Section 2.2, for the SGTR, the activity is released at a rate of 335 times the iodine equilibrium release rate.

DO00040-121, Revision 0 Page 6 of 83 4.

The isotopes included herein for the AST analysis are:

Kr-85m 1-131 Xe-131m Cs-134 Rb-88 Kr-85 1-132 Xe-133m Cs-136 Br-83 Kr-87 1-133 Xe-133 Cs-137 Br-84 Kr-88 1-134 Xe-135m Cs-138 1-135 Xe-135 Xe-138 5.

Iodine releases from the steam generators to the environment are assumed to be 97%

elemental and 3 % organic. These fractions apply to iodine released as a result of fuel damage and to iodine released during normal operations, including iodine spiking (Reference 1, Appendix F Section 4).

6.

TS 3.7.1.4 (Reference 7) provides the secondary coolant activity limit as 0.1 PCi/gm DE I-131.

7.

The primary-to-secondary leak rate in the steam generators is assumed to be the leak-rate-limiting condition for operation specified in the plant requirements. The leakage is apportioned between the steam generators in such a manner that the calculated dose is maximized (Reference 1, Appendix F Section 5.1). Per Reference 7, Bases 3/4.4.5, the total leakage for all three steam generators is I gpm. This leakage is assumed to be into the intact steam generators released for the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months duration of the event.

8.

The density used in converting volumetric leak rates (e.g., gpm) to mass leak rates (e.g., lbm/hr) should be consistent with the basis of surveillance tests used to show compliance with leak rate technical specifications. These tests are typically based on cool liquid (Reference 1, Appendix F Section 5.2). A value of 1.0 gm/cc (62.43 lbm/ft3) is used herein.

9.

The primary-to-secondary leakage should be assumed to continue until the primary system pressure is less than the secondary system pressure, or until the temperature of the leakage is less than 100° C (212° F). The release of radioactivity should be assumed to continue until shutdown cooling is in operation and releases from the steam generators have been terminated (Reference 1, Appendix F Section 5.3). All releases are assumed to terminate at 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

10. The release of fission products from the secondary system should be evaluated with the assumption of a coincident loss of offsite power (Reference 1, Appendix F Section 5.4).

11. All noble gas radionuclides released from the primary system are assumed to be released to the environment without reduction or mitigation, i.e. PF = 1.0 (Reference 1, Appendix F Section 5.5).

DO00040-121, Revision 0 Page 7 of 83

12. A portion of the primary to secondary leakage through the SGTR is assumed to flash to vapor, based on the thermodynamic conditions in the reactor and secondary coolant (Reference 1 Appendix F Section 5.6 and Appendix E Section 5.5.1).

13. The leakage that immediately flashes to vapor is assumed to rise through the bulk water of the SG and enter the steam space and is assumed to be immediately released to the environment with no mitigation; i.e., no reduction for scrubbing within the SG bulk water is credited (Reference I Appendix F Section 5.6 and Appendix E Section 5.5.2).

Note that credit for scrubbing in the SG of the flashed vapor as it rises through the bulk water during periods of total tube submergence may be credited in future revisions of this calculation per the models of NUREG-0409 (Reference 9).

14. All leakage that does not immediately flash is assumed to mix with the bulk water (Reference I Appendix F Section 5.6 and Appendix E Sections 5.5.1 & 5.5.3).

15. The radioactivity within the bulk water is assumed to become vapor at a rate that is the function of the steaming rate and the partition coefficient. A partition coefficient for iodine of 100 is assumed (Reference 1 Appendix F Section 5.6 and Appendix E Section 5.5.4).

16. The retention of particulate radionuclides in the steam generators is limited by the moisture carryover from the steam generators. The same partition coefficient of 100, as used for iodine, is assumed (Reference I Appendix F Section 5.6 and Appendix E Section 5.5.4) for particulate radionuclides (alkali metals).

Note that for a moisture carryover rate of 0.25%, the partition coefficient would be 400.

17. References 8, 10 and 21 provide the integrated mass release values for various time periods. Mass and associated activity release between these time periods is assumed to be linear.

18. The ratio of radioiodines to the other radionuclides in the coolant systems is assumed to be a constant. All other radionuclide activity concentrations are reduced by the ratio of TS allowable DE I-131 divided by the design basis 1% failed fuel activities.

19. This analysis assumes that the RCS activity conservatively remains constant throughout this pre-existing Iodine Spike SGTR event; i.e., no dilution of the RCS activity from the safety injection system is considered. Additionally, this evaluation assumes that the RCS mass remains constant throughout the SGTR event; i.e., no change in the RCS mass is assumed as a result of the rupture flow within the SGTR or from the safety injection system.

DO00040-121, Revision 0 Page 8 of 83 For the Concurrent Iodine Spike SGTR event, a similar assumption is made with the exception that the iodine activity increases during 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of the transient as a result of release from the defective fuel at a rate of 335 times the iodine equilibrium appearance rate.

20. SG volume is assumed to remain constant throughout both the Pre-Accident and the Concurrent Iodine spike SGTR events and furthermore, dilution by incoming Auxiliary Feedwater is not considered.

4.0 DESIGN INPUTS 4.1 Consistent with RG 1.183, Section 3.1 and Appendix F.1 (Reference 1), the AST SGTR dose analysis is performed at 102% of the core thermal power level (1.02 x the License Thermal Power of 2900 MWth), or 2958 MWth (Reference 12).

D000040-121, Revision 0 Page 9 of 83 4.2 RC DE I-131 Values:

The reactor coolant DE I-131 values are based on Technical Specification (TS) 3.4.8 limit of 1.0 µCi/gm DE I-131(Reference 7) for the concurrent spike scenario and 60 µCi/gm DE 1-131 (Reference 7) for the pre-existing spike scenario. The input values and methodology are provided in Reference 4 (Section 5.1.1 and Attachment 1). The DE 1-131 for reactor coolant at the design basis of 1% failed fuel was determined in Reference 4 as 3.84. The values from Reference 4, Attachment I are reproduced as follows:

Thyroid Inhalation Initial Reactor Coolant Reactor Coolant Reactor Coolant Reactor Coolant Design Basis Dose Conversion Reactor Coolant Concentration Concentration Concentration Concentration Rx Coolant Concentration 60 Ci/ m 60.0 Ci/ m 1.0 Ci/

1.0 Ci/ m Concentration' DE I-131 DE I-131 DE I-131 DE 1-131 DE 1-131 Reference 6 Reference 16 Isotope CD Ci/ m DCF (Rem/Ci)

CID, x DCF C

Ci/ m CD x DCF C Wi/gm)

CD, x DCF1 1-131 3

1.1E+06 3.300E+06 4.69E+01 5.16E+07 7.82E-01 8.60E+05 1-132 3.1 6.3E+03 1.953E+04 4.85E+01 3.05E+05 8.08E-01 5.09E+03 1-133 4.6 1.8E+05 8.280E+05 7.19E+01 1.29E+07 1.20E+00 2.16E+05 1-134 0.6 1.1E+03 6.600E+02 9.40E+00 1.03E+04 1.56E-01 1.72E+02 1-135 2.4 3.1E+04 7.440E+04 3.75E+01 1.16E+06 6.25E-01 1.94E+04 TOTAL 4.223E+06 6.60E+07 1.10E+06 Calculated DE 1-131 Factor = 3.84

DO00040-121, Revision 0 Page 10 of 83 Using the 1% failed fuel calculated DE I-131 Factor of 3.84 the 1 µCi/gm and 60 µCi/gm DE I-131 Reactor Coolant Activities are provided as follows:

1 µCi/gm and 60 µCi/gm De 1-131 Reactor Coolant Activities Isotope RC 1% Activity Ref. 6 Table 5-15 Ci/ m 1 µCi/gm DE I-131 RC Activity Ci/ m (1) 60 µCi/gm DE I-131 RC Activity Ci/ m 2 Kr-85m 1.8E+00 1.8E+00 1.8E+00 Kr-85 7.6E+00 7.6E+00 7.6E+00 Kr-87 1.1E+00 1.1E+00 1.1E+00 Kr-88 3.2E+00 3.2E+00 3.2E+00 I-131 3.0E+00 7.82E-01 4.69E+01 I-132 3.1E+00 8.08E-01 4.85E+01 I-133 4.6E+00 1.20E+00 7.19E+01 1-134 6.0E-01 1.56E-01 9.38E+00 I-135 2.4E+00 6.25E-01 3.75E+01 Xe-131m 2.3E+00 2.3E+00 2.3E+00 Xe-133m 1.9E+01 1.9E+01 1.9E+0 I Xe-133 2.9E+02 2.9E+02 2.9E+02 Xe-135m 5.2E-01 5.2E-01 5.2E-01 Xe-135 8.6E+00 8.6E+00 8.6E+00 Xe-138 6.4E-01 6.4E-01 6.4E-01 Cs-134 4.4E+00 1.15E+00 1.15E+00 Cs-136 4.5E+00 1.17E+00 1.17E+00 Cs-137 2.1E+00 5.47E-01 5.47E-01 Cs-138 9.7E-01 2.53E-01 2.53E-01 Rb-88 3.8E+00 9.90E-01 9.90E-01 Br-83 8.9E-02 2.32E-02 1.39E+00 Br-84 4.2E-02 1.09E-02 6.56E-01 (1) 1 µCi/gm DE 1-131 RC Activity = RC 1% Activity / DE 1-131 factor of 3.84 (except for Kr/Xe)

(2) Applies to I & Br ONLY: 60 µCi/gm DE I-131 RC Activity = 1 µCi/gm DE I-131 RC Activity

60 4.3 The integrated mass of the steam and reactor coolant released during the SGTR event is given in the following table per Reference 10 and pages 13-14 from Reference 8 and Reference 21.

The tube rupture break flow flashing fraction is given as 0.2 pre-trip and 0.125 post trip (Reference 8, p. 14).

SGTR Mass Release Time Steam Release from Faulted SG lbm Steam Release from Intact SGs lbm Reactor Coolant Release to Faulted SG lbm 0 - 385 sec 19,400 385 sec - 30 min.

73,500 0 - 30 minutes 56800 92,900 0 - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 381,400 2 - 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 924,900 8 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 1,200,000

D000040-121, Revision 0 Page 11 of 83 4.4 Reference 14, Appendix 2 provides the post-accident x/Q's (sec/m3) at the TSC. Due to the relatively extended distance from the NOB/TSC to VCS Unit 1, a bounding analysis was completed using a minimum source to receptor distance which equates to a distance of 1500 ft. The actual distance between the VCS Unit 1 release points and the NOB/TSC outside air intake is greater.

Reference 15, provides post-accident offsite x/Q's (sec/m3) at the EAB and LPZ. The post-accident offsite x/Q's (sec/m3) at the EAB and LPZ were utilized in other calculations to determine the offsite doses as a result of FSAR Chapter 15 design basis accidents. These x/Q's are included in the RADTRAD files as a "check" for model correctness.

Time Period EAB LPZ TSC (1) 0 - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 1.24E-04 3.9E-05 0 - 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 2.42E-05 2 - 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 3.3E-05 8 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 1.68E-05 1.6E-05 1 - 4 days 7.55E-06 1.2E-05 4 - 30 days 2.40E-06 8.7E-06 (1) Note: These values have not been corrected for CR/TSC occupancy.

4.5 TSC ventilation system input parameters are given in Section 5.3.

4.6 Offsite and TSC breathing rates are per Reference 1, Sections 4.1.3, and 4.2.6.

Offsite (EAB and LPZ)

Technical Support Center Time Rate (m /sec)

Time Rate (m /sec) 0-8 hr 3.5E-04 0-30 days 3.5E-04 8-24 hr 1.8E-04 1-30 days 2.3E-04 4.7 Per Reference 1, Section 4.2.6, Occupancy Factors used for the Technical Support Center are as follows:

Time Occupancy Factor 0-24 hours 1.0 1-4 days 0.6 4-30 days 0.4 4.8 The Dose Conversion Factors (DCFs) utilized in the AST SGTR analysis are from Reference 5, Table 1.4.3.3-2.

DC00040-121, Revision 0 Page 12 of 83 4.9 The TSC is to provide direct management and technical support to the control room during an accident, consequently it shall have the same radiological habitability as the control room under accident conditions. TSC personnel shall be protected from radiological hazards, including direct radiation and airborne radioactivity from in-plant sources under accident conditions, to the same degree as control room personnel.

The TSC acceptance criteria for the radiological consequences of this accident are the same as the control room radiation exposures; within the l OCFR50.67 limits (Reference 2) specifically: Adequate radiation protection is provided to permit access to and occupancy of the TSC under accident conditions without personnel receiving radiation exposures in excess of 0.05 Sv (5 rem) total effective dose equivalent (TEDE) for the duration of the accident.

5.0 METHODOLOGY 5.1 Source Term with Pre-Existing Iodine Spike The source term for the pre-existing spike includes the following:

1 Activity in reactor coolant released due to tube rupture in faulted SG.

2 Activity in secondary coolant released from faulted SG.

3 Activity in reactor coolant released due to 1 gpm tube leak in intact SG (0 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 4

Activity in reactor coolant released due to 1 gpm tube leak in intact SG (2 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 5

Activity in reactor coolant released due to 1 gpm tube leak in intact SG (8 to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ).

6 Activity in secondary coolant released from intact SG.

The activity releases are determined in sections 5.1.1 through 5.1.9.

D000040-121, Revision 0 Page 13 of 83 5.1.1 Activity in Reactor Coolant Released Due to Tube Rupture Faulted SG 5.1.1 Pre-Accident Iodine S pike With RCS Activi At 60 Ci/ m DEI-131 sotopes RC Specific Activity (1)

Mass Released to Faulted SG (0-30 min 2 Activity Released to Faulted SG 0-30 min (3) lashing Factor (2)

Max. Tube Leak Activity Flashed Released to Environs (4)

Max. Tube Leak Remaining Activity (5) 0-30 min Total Activity Release to Environs (6)

Ci/

lbm Ci (Ci)

(Ci)

Kr-85m 1.80E+00 9.29E+04 7.58E+01 I

7.58E+01 0.00E+00 7.58E+01 Kr-85 7.60E+00 9.29E+04 3.20E+02 1

3.20E+02 0.00E+00 3.20E+02 Kr-87 1.10E+00 9.29E+04 4.64E+01 1

4.64E+01 0.00E+00 4.64E+01 Kr-88 3.20E+00 9.29E+04 1.35E+02 I

1.35E+02 0.00E+00 1.35E+02 1-131 4.69E+01 9.29E+04 1.98E+03 (4).

2.78E+02 1.70E+03 2.78E+02 1-132 4.85E+01 9.29E+04 2.04E+03 (4) 2.87E+02 1.75E+03 2.87E+02 1-133 7.19E+01 9.29E+04 3.03E+03 (4) 4.26E+02 2.60E+03 4.26E+02 1-134 9.38E+00 9.29E+04 3.95E+02 (4) 5.56E+01 3.40E+02 5.56E+01 1-135 3.75E+01 9.29E+04 1.58E+03 (4) 2.22E+02 1.36E+03 2.22E+02 Xe-131m 2.30E+00 9.29E+04 9.69E+01 I

9.69E+01 0.00E+00 9.69E+01 Xe-133m 1.90E+01 9.29E+04 8.01E+02 I

8.01E+02 0.00E+00 8.01E+02 Xe-133 2.90E+02 9.29E+04 1.22E+04 I

1.22E+04 0.00E+00 1.22E+04 Xe-135m 5.20E-01 9.29E+04 2.19E+01 1

2.1.9E+01 0.00E+00 2.19E+01 Xe-135 8.60E+00 9.29E+04 3.62E+02 1

3.62E+02 0.00E+00 3.62E+02 Xe-138 6.40E-01 9.29E+04 2.70E+01 1

2.70E+01 0.00E+00 2.70E+01 Cs-134 1.15E+00 9.29E+04 4.83E+01 (4) 6.79E+00 4.15E+01 6.79E+00 Cs-136 1.17E+00 9.29E+04 4.94E+O1 (4) 6.95E+00 4.24E+01 6.95E+00 Cs-137 5.47E-01 9.29E+04 2.31E+01 (4) 3.24E+00 1.98E+01 3.24E+00 Cs-138 2.53E-01 9.29E+04 1.06E+01 (4) 1.50E+00 9.15E+00 1.50E+00 Rb-88 9.90E-01 9.29E+04 4.17E+01 (4) 5.87E+00 3.58E+01 5.87E+00 Br-83 1.39E+00 9.29E+04 5.86E+01 (4) 8.25E+00 5.04E+01 8.25E+00 Br-84 6.56E-01 9.29E+04 2.77E+01 (4) 3.89E+00 2.38E+01 3.89E+00 (1) Reference 4, page 10 for iodine. Kr, Xe, Cs, RB & Br per Reference 4, page 10 (2) Sections 3 & 4.3 for mass release and flashing fraction (3) Activity Released Ci = Primary Coolant Conc (gCi/gm)

453.5924 gm/lb

Mass Released lb

1.0E-6 Ci/ Ci (4) Activity Release to Environment (Ci) = Activity Released to Faulted SGs (Ci)

Flash Factor (5) Remaining Activity =(Activity Released to Faulted SGs (Ci) - Flashed Activity Released to Environment)

(6) Total Activity Release to Environment (Ci) = Activity Flashed

DO00040-121, Revision 0 Page 14 of 83 5.1.2 Activity in Secondary Coolant Released from Faulted SG Secondary Coolant Specific Activity Based on 1 an d 60 Ci/ m DE I-131 Reactor Coolant Activity (1)

Lb Conservatively Low SG Blowdown (3) =

12756 Ibm/hr MS Water Mass in All 3 SGs =

340000 lbm L,

Leak Rate =

1.0 m =

500.501303 Ibm/hr Reactor Coolant Conc., ([tCi/gm)

Sec. Coolant E q. Conc. For Decay For DE I-131, C Pri-to-Sec Leak = I m 4 Isotopes Constant, X 1 DE 1-131 C 60 DE 1-131 C 1 DE 1-131 CS 60 DE I-131 CS (1/sec) (5)

(gCi/gm)

(['Ci/gm)

Ci/lbm Ci/lbm 1

I-131 9.96E-07 7.82E-01 4.69E+01 1.27E+01 7.62E+02 (1)

I-132 8.26E-05 8.08E-01 4.85E+01 1.61E+00 9.66E+01 (1)

I-133 9.20E-06 1.20E+00 7.19E+01 1.13E+01 6.80E+02 (1)

I-134 2.20E-04 1.56E-01 9.38E+00 1.26E-01 7.55E+00 (1)

I-135 2.86E-05 6.25E-01 3.75E+01 2.97E+00 1.78E+02 2

Cs-134 1.07E-08 1.15E+00 1.15E+00 2.04E+01 2.04E+01 (2)

Cs-136 6.09E-07 1.17E+00 1.17E+00 1.97E+01 1.97E+01 (2)

Cs-137 7.28E-10 5.47E-01 5.47E-01 9.74E+00 9.74E+00 (2)

Cs-138 3.59E-04 2.53E-01 2.53E-01 1.27E-01 1.27E-01 (2)

Rb-88 6.49E-04 9.90E-01 9.90E-01 2.78E-01 2.78E-01 (2)

Br-83 8.05E-05 2.32E-02 1.39E+00 4.73E-02 2.84E+00 (2)

Br-84 3.63E-04 1.09E-02 6.56E-01 5.43E-03 3.26E-01 (1)

Reactor Coolant DE I-131 evaluation and mass and flow input parameters taken directly from Reference 4, page 12 and reproduced in section 4.2.

(2)

Other isotopes determined same as iodine using DE 1-131 concentrations from section 4.2.

(3)

Per Reference 13, Section 10.4.8.1.5: minimum blowdown flow = 30 gpm. 12756 lbm/hr 25 gpm. The lower the flow (removal term), the higher the concentration in the steam generators.

(4)

Secondary Coolant Equilibrium Concentration calculated based on methodology and values in Reference 4 pages 11 A and 12. The equation and parameters describing the secondary coolant activity are given as:

Csg = [LP

Cp *453.5924 gm/lb] / [Lb + (Xi* Msg

3600 sec/hr)]

where:

LP, Primary to secondary leak rate(1 gpm) 500.5013034 lbm/hr CP, Reactor coolant activity (µCi/gm) *453.5924 gm/lb

µCi/lb Lb, SG blowdown rate (30 gpm) 12756 lbm/hr

?, isotopic decay constant (1/sec)

3600 sec/hr 1/hr Msg, SG mass 34000 lbm (5)

T112 radiological half life per Reference 20. ?I = 0.693/T1/2

D000040-121, Revision 0 Page 15 of 83 5.1.2 (continued)

Activity in Secondary Coolant Released from Faulted SG Secondary Coolant Activi Release from Faulted SG with 60 Ci/

DE I-131 Isotopes Secondary Coolant 60 DE 1-131 Ci/lbm (1)

Faulted SG Steam Release lbm (2)

Partition Factor 0-30 min Faulted SG Release (3)

Ci 1-131 7.62E+02 56800 100 4.33E-01 1-132 9.66E+01 56800 100 5.49E-02 1-133 6.80E+02 56800 100 3.86E-01 1-134 7.55E+00 56800 100 4.29E-03 1-135 1.78E+02 56800 100 1.01E-01.

Cs-134 2.04E+01 56800 100 1.16E-02 Cs-136 1.97E+01 56800 100 1.12E-02 Cs-137 9.74E+00 56800 100 5.53E-03 Cs-138 1.27E-01 56800 100 7.21 E-05 Rb-88 2.78E-01 56800 100 1.58E-04 Br-83 2.84E+00 56800 100 1.61 E-03 Br-84 3.26E-01 56800 100 1.85E-04 (1

Previous table (2) Section 4.3 - Mass of steam released from secondary side of faulted steam generator.

(3) Release (Ci) = Secondary Coolant Activity Ci/lb

Mass Release (Ibm) / Partition Factor

D000040-121, Revision 0 Page 16 of 83 5.1.3 1.0 gpm SG Tube Leak - Activity Release 0-2 hr 5.1.3 1.0 m Steam Generator Tube Leak - Activity Release for 0 - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Pre-Accident Iodine Spike With RCS Activity At 60 Ci/ m DEI-131 Isotopes RC Specific Activity I Mass Released to Faulted SG (0

2 hr) (2)

SG Activity Available for Release (0

2 hr) (3)

Partition Factor (8)

Max. Tube Leak Activity Released to Environs (0 -

2 hr) 4 0 -30 min Total Activity Release to Environs (5) 30 min-1 hr Total Activity Release to Environs (6) 0-2 hr Activity Remaining in SG (7)

Ci/ m (Ibm)

(Ci)

Kr-85m 1.80E+00 1001 8.17E-01 I

8.17E-01 2.04E-01 6.13E-01 0.00E+00 Kr-85 7.60E+00 1001 3.45E+00 I

3.45E+00 8.63E-01 2.59E+00 0.00E+00 Kr-87 1.10E+00 1001 4.99E-01 I

4.99E-01 1.25E-01 3.75E-01 0.00E+00 Kr-88 3.20E+00 1001 1.45E+00 I

1.45E+00 3.63E-01 1.09E+00 0.00E+00 I-131 4.69E+01 1001 2.13E+01 100 2.13E-01 5.32E-02 1.60E-01 2.11E+01 I-132 4.85E+01 1001 2.20E+01 100 2.20E-01 5.50E-02 1.65E-01 2.18E+01 1-133 7.19E+01 1001 3.26E+01 100 3.26E-01 8.16E-02 2.45E-01 3.23E+01 I-134 9.38E+00 1001 4.26E+00 100 4.26E-02 1.06E-02 3.19E-02 4.22E+00 I-135 3.75E+01 1001 1.70E+01 100 1.70E-01 4.26E-02 1.28E-01 1.69E+01 Xe-131m 2.30E+00 1001 1.04E+00 1

1.04E+00 2.61E-01 7.83E-01 0.00E+00 Xe-133m 1.90E+01 1001 8.63E+00 I

8.63E+00 2.16E+00 6.47E+00 0.00E+00 Xe-133 2.90E+02 1001 1.32E+02 I

1.32E+02 3.29E+01 9.88E+01 0.00E+00 Xe-135m 5.20E-01 1001 2.36E-01 I

2.36E-01 5.90E-02 1.77E-01 0.00E+00 Xe-135 8.60E+00 1001 3.90E+00 I

3.90E+00 9.76E-01 2.93E+00 0.00E+00 Xe-138 6.40E-01 1001 2.91E-01 I

2.91E-01 7.26E-02 2.18E-01 0.00E+00 Cs-134 1.15E+00 1001 5.20E-01 100 5.20E-03 1.30E-03 3.90E-03 5.15E-01 Cs-136 1.17E+00 1001 5.32E-01 100 5.32E-03 1.33E-03 3.99E-03 5.27E-01 Cs-137 5.47E-01 1001 2.48E-01 100 2.48E-03 6.21E-04 1.86E-03 2.46E-01 Cs-138 2.53E-01 1001 1.15E-01 100 1.15E-03 2.87E-04 8.60E-04 1.14E-01 Rb-88 9.90E-01 1001 4.49E-01 100 4.49E-03 1.12E-03 3.37E-03 4.45E-01 Br-83 1.39E+00 1.001 6.32E-01 100 6.32E-03 1.58E-03 4.74E-03 6.25E-01 Br-84 6.56E-01 1001 2.98E-01 100 2.98E-03 7.45E-04 2.24E-03 2.95E-01 (1) Section 4.2 (2) Per Reference 11 1 m = 500.5 lb/hr, i.e., 2 hr = 1001 lb (3) Activity Released Ci = Primary Coolant Conc ([tCi/gm)

453.5924 gni/lb

Mass Released lb

1.0E-6 Ci/ Ci (4) 0-2 hr Activity Release to Environment (Ci) = Activity Released to Intact SGs (Ci) / Partition Factor (5) 0- 30 min Activity Release to Environment (Ci) = 0-2hr Activity Released /4 (6) 30 min-2 hr Activity Release to Environment (Ci) = 0-2hr Activity Released

0.75 (7) 0-2 hr Activity Remaining in SG = Activity Release to SG (Ci) - Activity Released to Environs (Ci)

(8) Section 3

D000040-121, Revision 0 Page 17 of 83 5.1.4 1.0 Epm SG Tube Leak - Activity Release 2 - 8 hr 5.1.4 1.0 m Steam Generator Tube Leak - Activity Release for 2-8 hours Pre-Accident Iodine Spike With RCS Activity At 60 Ci/ m DEI-131 Isoto es RC Specific Activi (1)

I gpm SG Tube Leak Mass Release (2-8 hr) (2)

SG Activity Available for Release (2-8 hr) (3)

Partition Factor (6)

Intact SG Activity Release to Environs (2-8 hr) (4)

Intact SG Activity Remaining in SG (2-8 hr) (5)

Ci/ m (Ibm)

(Ci)

Kr-85m 1.80E+00 3003 2.45E+00 I

2.45E+00 0.00E+00 Kr-85 7.60E+00 3003 1.04E+01 I

1.04E+01 0.00E+00 Kr-87 1.10E+00 3003 1.50E+00 1

1.50E+00 0.00E+00 Kr-88 3.20E+00 3003 4.36E+00 1

4.36E+00 0.00E+00 1-131 4.69E+01 3003 6.39E+01 100 6.39E-01 6.32E+01 1-132 4.85E+01 3003 6.60E+01 100 6.60E-01 6.53E+01 1-133 7.19E+01 3003 9.79E+01 100 9.79E-01 9.70E+01 1-134 9.38E+00 3003 1.28E+01 100 1.28E-01 1.26E+01 1-135 3.75E+01 3003 5.11E+01 100 5.11E-01 5.06E+01 Xe-131m 2.30E+00 3003 3.13E+00 I

3.13E+00 0.00E+00 Xe-133m 1.90E+01 3003 2.59E+01 1

2.59E+01 0.00E+00 Xe-133 2.90E+02 3003 3.95E+02 I

3.95E+02 0.00E+00 Xe-135m 5.20E-01 3003 7.08E-01 I

7.08E-01 0.00E+00 Xe-135 8.60E+00 3003 1.17E+01 1

1.17E+01 0.00E+00 Xe-138 6.40E-01 3003 8.72E-01 1

8.72E-01 0.00E+00 Cs-134 1.15E+00 3003 1.56E+00 100 1.56E-02 1.55E+00 Cs-136 1.17E+00 3003 1.60E+00 100 1.60E-02 1.58E+00 Cs-137 5.47E-01 3003 7.45E-01 100 7.45E-03 7.38E-01 Cs-138 2.53E-01 3003 3.44E-01 100 3.44E-03 3.41E-01 Rb-88 9.90E-01 3003 1.35E+00 100 1.35E-02 1.33E+00 Br-83 1.39E+00 3003 1.89E+00 100 1.89E-02 1.88E+00 Br-84 6.56E-01 3003 8.94E-01 100 8.94E-03 8.85E-01 (1) Section 4.2 (2) Reference 11 gives 1 m = 500.5 lbm/hr. 6 hr = 3003 lbm (3) SG Activity = Activity Released (Ci) to SG (Primary Coolant Conc (gCi/gm) 453.5924 gm/lb

Mass Released (lb)

1.0E-6 Ci/ Ci (4) Activity Release to Environment (Ci) = Activity Released to Intact SGs (Ci) / Partition Factor (5) Activity Remaining in SG =SG Activity Available for Release - Activity Released to Environs (6) Section 3

D000040-121, Revision 0 Page 18 of 83 5.1.5 1.0 gpm SG Tube Leak - Activity Release 8-24 hr 5.1.5 1.0 m Steam Generator Tube Leak - Activity Release for 8 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Pre-Accident Iodine Spike With RCS Activi At 60 Ci/ m DEI-131 sotopes RC Specific Activity 1 I gpm SG Tube Leak Mass Release (8-24 hr) (2)

SG Activity Available for Release (8-24 hr) (3)

Partition Factor (7)

Intact SG Tube Activity Release to Environs (8-24 hr) (4)

Intact SG Activity Remaining in SG (8-24 hr) (5)

Intact SG Total Activity Release to Environs (8-24 hr) (6)

Kr-85m 1.80E+00 8008 6.54E+00 I

6.54E+00 0.00E+00 6.54E+00 Kr-85 7.60E+00 8008 2.76E+01 1

2.76E+01 0.00E+00 2.76E+01 Kr-87 1.10E+00 8008 4.00E+00 1

4.00E+00 0.00E+00 4.00E+00 Kr-88 3.20E+00 8008 1.16E+01 1

1.16E+01 0.00E+00 1.16E+01 1-131 4.69E+01 8008 1.70E+02 100 1.70E+00 1.69E+02 1.70E+00 1-132 4.85E+01 8008 1.76E+02 100 1.76E+00 1.74E+02 1.76E+00 1-133 7.19E+01 8008 2.61E+02 100 2.61E+00 2.59E+02 2.61E+00 1-134 9.38E+00 8008 3.41E+01 100 3.41E-01 3.37E+01 3.41E-01 1-135 3.75E+01 8008 1.36E+02 100 1.36E+00 1.35E+02 1.36E+00 Xe-131m 2.30E+00 8008 8.35E+00 1

8.35E+00 0.00E+00 8.35E+00 Xe-133m 1.90E+01 8008 6.90E+01 I

6.90E+01 0.00E+00 6.90E+01 Xe-133 2.90E+02 8008 1.05E+03 I

1.05E+03 0.00E+00 1.05E+03 Xe-135m 5.20E-01 8008 1.89E+00 1

1.89E+00 0.00E+00 1.89E+00 Xe-135 8.60E+00 8008 3.12E+01 1

3.12E+01 0.00E+00 3.12E+01 Xe-138 6.40E-01 8008 2.32E+00 1

2.32E+00 0.00E+00 2.32E+00 Cs-134 1.15E+00 8008 4.16E+00 100 4.16E-02 4.12E+00 4.16E-02 Cs-136 1.17E+00 8008 4.26E+00 100 4.26E-02 4.22E+00 4.26E-02 Cs-137 5.47E-01 8008 1.99E+00 100 1.99E-02 1.97E+00 1.99E-02 Cs-138 2.53E-01 8008 9.18E-01 100 9.18E-03 9.09E-01 9.18E-03 Rb-88 9.90E-01 8008 3.60E+00 100 3.60E-02 3.56E+00 3.60E-02 Br-83 1.39E+00 8008 5.05E+00 100 5.05E-02 5.00E+00 5.05E-02 Br-84 6.56E-01 8008 2.38E+00 100 2.38E-02 2.36E+00 2.38E-02 (1) Section 4.2 (2) Reference 11 gives I m = 500.5 Ibm/hr. 16 hr = 8008 Ibm 3 SG Activity = ActiviReleased (Ci) to SG Primary Coolant Cone Ci/ m

453.5924 gm/lb

Mass Released (Ib

1.0E-6 Ci/ Ci (4) Activity Release to Environment (Ci) = SG Activity Available for Release (Ci) / Partition Factor (5) Activity Remaining in Secondary Side Liquid (Ci) = SG Activity Available for Release (Ci) - Activity Released to Environment (Ci)

(6) Total Activity released in 8-24 hour cooldown steaming = Total Activity Release from Tube Leakage (7) Section 3

D000040-121, Revision 0 Page 19 of 83 5.1.6 Secondary Coolant Activity Release from Intact SGs 5.1.6 Secondary Coolant Activity Release from Intact SG 60 uCi/gm DE 1-131 Isoto es Secondary Coolant 60 DE I-131 uCi/Ib 1 Faulted SG Steam Release Ibm (2)

Partition Factor (3) 0-2 hr Release to Environment Ci 0-30 min Release to Environment Ci 30 min-2 hr Release to Environment Ci 0-2hrs I-131 7.62E+02 381400 100 2.91E+00 7.26E-01 2.18E+00 I-132 9.66E+01 381400 100 3.68E-01 9.21E-02 2.76E-01 1-133 6.80E+02 381400 100 2.59E+00 6.48E-01 1.94E+00 I-134 7.55E+00 381400 100 2.88E-02 7.20E-03 2.16E-02 1-135 1.78E+02 381400 100 6.80E-01 1.70E-01 5.10E-01 Cs-134 2.04E+01 381400 100 7.77E-02 1.94E-02 5.83E-02 Cs-136 1.97E+01 381400 100 7.52E-02 1.88E-02 5.64E-02 Cs-137 9.74E+00 381400 100 3.71E-02 9.28E-03 2.78E-02 Cs-138 1.27E-01 381400 100 4.84E-04 1.21E-04 3.63E-04 Rb-88 2.78E-01 381400 100 1.06E-03 2.66E-04 7.97E-04 Br-83 2.84E+00 381400 100 1.08E-02 2.70E-03 8.11E-03 Br-84 3.26E-01 381400 100 1.24E-03 3.11E-04 9.32E-04 2-8 hr 2-8 hr Release to Environment Ci 8 - 24 hr Steam release lb 8 - 24 hr release to Environment Ci I-131 7.62E+02 924900 100 7.05E+00 I-132 9.66E+01 924900 100 8.94E-01 1.20E+06 9.14E+00 1-133 6.80E+02 924900 100 6.29E+00 1.20E+06 1.16E+00 1-134 7.55E+00 924900 100 6.98E-02 1.20E+06 8.16E+00 1-135 1.78E+02 924900 100 1.65E+00 1.20E+06 9.06E-02 Cs-134 2.04E+01 924900 100 1.88E-01 1.20E+06 2.14E+00 Cs-136 1.97E+01 924900 100 1.82E-01 1.20E+06 2.45E-01 Cs-137 9.74E+00 924900 100 9.00E-02 1.20E+06 2.37E-01 Cs-138 1.27E-01 924900 100 1.17E-03 1.20E+06 1.17E-01 Rb-88 2.78E-01 924900 100 2.58E-03 1.20E+06 1.52E-03 Br-83 2.84E+00 924900 100 2.62E-02 1.20E+06 3.34E-03 Br-84 3.26E-01 924900 100 3.01E-03 1.20E+06 3.40E-02 (1) Section 5.1.2 (2) Section 4.3 - Mass of steam releases from intact SG (3) Section 3

DC00040-121, Revision 0 Page 20 of 83 5.1.7 Pre-Existing Total Activity Released 0 - 2 hrs 1.0 gpm 5.1.7 Pre-Accident Total Activit Released 0 - 2 hrs 1.0 m

5.1.1 5.1.2 5.1.3 5.1.6 sotopes Faulted SG Rupture Release 0-30 min (Ci)

Faulted SG Secondary Coolant Release 0-30 min (Ci)

Intact SG Tube Leak 0-2 hr (Ci)

Intact SG Secondary Coolant Release 0-2 hr (Ci) 0-2 hr Total Activity Release (Ci) 0-30 min Total Activity Release (Ci) 30 min-2 hr Total Activity Release (Ci)

Kr-85m 7.58E+01 0

8.17E-01 0

7.67E+01 7.61E+01 6.13E-01 Kr-85 3.20E+02 0

3.45E+00 0

3.24E+02 3.21E+02 2.59E+00 Kr-87 4.64E+01 0

4.99E-01 0

4.69E+01 4.65E+01 3.75E-01 Kr-88 1.35E+02 0

1.45E+00 0

1.36E+02 1.35E+02 1.09E+00 1-131 2.78E+02 4.33E-01 2.13E-01 2.91E+00 2.81E+02 2.79E+02 2.34E+00 I-132 2.87E+02 5.49E-02 2.20E-01 3.68E-01 2.88E+02 2.87E+02 4.41E-01 I-133 4.26E+02 3.86E-01 3.26E-01 2.59E+00 4.29E+02 4.27E+02 2.19E+00 I-134 5.56E+01 4.29E-03 4.26E-02 2.88E-02 5.57E+01 5.56E+01 5.35E-02 I-135 2.22E+02 1.01E-01 1.70E-01 6.80E-01 2.23E+02 2.23E+02 6.38E-01 Xe-131m 9.69E+01 0

1.04E+00 0

9.80E+01 9.72E+01 7.83E-01 Xe-133m 8.01E+02 0

8.63E+00 0

8.09E+02 8.03E+02 6.47E+00 Xe-133 1.22E+04 0

1.32E+02 0

1.24E+04 1.23E+04 9.88E+01 Xe-135m 2.19E+01 0

2.36E-01 0

2.21E+01 2.20E+01 1.77E-01 Xe-135 3.62E+02 0

3.90E+00 0

3.66E+02 3.63E+02 2.93E+00 Xe-138 2.70E+01 0

2.91E-01 0

2.73E+01 2.70E+01 2.18E-01 Cs-134 6.79E+00 1.16E-02 5.20E-03 7.77E-02 6.89E+00 6.83E+00 6.22E-02 Cs-136 6.95E+00 1.12E-02 5.32E-03 7.52E-02 7.04E+00 6.98E+00 6.04E-02 Cs-137 3.24E+00 5.53E-03 2.48E-03 3.71E-02 3.29E+00 3.26E+00 2.97E-02 Cs-138 1.50E+00 7.21E-05 1.15E-03 4.84E-04 1.50E+00 1.50E+00 1.22E-03 Rb-88 5.87E+00 1.58E-04 4.49E-03 1.06E-03 5.87E+00 5.87E+00 4.17E-03 Br-83 8.25E+00 1.61E-03 6.32E-03 1.08E-02 8.26E+00 8.25E+00 1.29E-02 Br-84 3.89E+00 1.85E-04 2.98E-03 1.24E-03 3.90E+00 3.89E+00 3.17E-03

D000040-121, Revision 0 Page 21 of 83 5.1.8 Pre-Existing Spike Total Activity Released 5.1.8 Pre-Existing Spike Total Activity Released 5.1.1 5.1.2 5.1.4 5.1.6 sotopes Faulted SG Rupture Release (Ci)

Faulted SG Secondary Coolant Release (Ci)

Intact SG Tube Leak (Ci)

Intact SG Secondary Coolant Release (Ci) 2-8 hr Total Activity Release (Ci) 0-8 hr Total Activity Release (CO (1 )

0-24 hr Total Activity Release (Ci)

(2)

Kr-85m 0.00E+00 2.45E+00 2.45E+00 79 86 Kr-85 0.00E+00 1.04E+01 1.04E+01 334 362 Kr-87 0.00E+00 1.50E+00 1.50E+00 48 52 Kr-88 0.00E+00 4.36E+00 4.36E+00 141 152 1-131 0.00E+00 0.00E+00 6.39E-01 7.05E+00 7.68E+00 289 300 1-132 0.00E+00 0.00E+00 6.60E-01 8.94E-01 1.55E+00 289 292 1-133 0.00E+00 0.00E+00 9.79E-01 6.29E+00 7.27E+00 437 448 1-134 0.00E+00 0.00E+00 1.28E-01 6.98E-02 1.98E-01 56 56 1-135 0.00E+00 0.00E+00 5.11E-01 1.65E+00 2.16E+00 225 229 Xe-131m 0.00E+00 3.13E+00 3.1.3E+00 101 109 Xe-133m 0.00E+00 2.59E+O1 2.59E+01 835 904 Xe-133 0.00E+00 3.95E+02 3.95E+02 12747 13800 Xe-135m 0.00E+00 7.08E-01 7.08E-01 23 25 Xe-135 0.00E+00 1.17E+01 1.17E+01 378 409 Xe-138 0.00E+00 8.72E-01 8.72E-01 28 30 Cs-134 0.00E+00 0.00E+00 1.56E-02 1.88E-01 2.04E-01 7

7 Cs-136 0.00E+00 0.00E+00 1.60E-02 1.82E-01 1.98E-01 7

8 Cs-137 0.00E+00 0.00E+00 7.45E-03 9.00E-02 9.75E-02 3

4 Cs-138 0.00E+00 0.00E+00 3.44E-03 1.17E-03 4.62E-03 2

2 Rb-88 0.00E+00 0.00E+00 1.35E-02 2.58E-03 1.61E-02 6

6 Br-83 0.00E+00 0.00E+00 1.89E-02 2.62E-02 4.52E-02 8

8 Br-84 0.00E+00 0.00E+00 8.94E-03 3.01E-03 1.20E-02 4

4 (1) 0-8 hr Total Activity Release (Ci) = 0-2 hr Total Activity Release (Ci) (5.1.7) + 2-8 hr Total Activity Remaining Release (Ci) (5.1.8)

(2) 0-24 hr Total Activity Release (Ci) = 0-8 hr Total Activity Release (Ci) (5.1.8) + 8 - 24 hr Release (5.1.5) + 0-24 hr Release (Ci) 5.1.6

D000040-121, Revision 0 Page 22 of 83 5.1.9 Pre-Existing Spike Fraction of Total Activity Released 5.1.9 Pre-Accident Spike Fraction of Total Activity Released Isotopes Time Period Release By Species 0-30 min 30 min-2hr 2-8hr 8-24 hr 0-30 min 30 min=2hr 2-8hr 8-24 hr (1)

(2)

(3)

(4)

Kr-85m 8.88E-01 7.16E-03 2.86E-02 7.63E-02 Nobles 8.88E-01 7.16E-03 2.86E-02 7.63E-02 Kr-85 8.88E-01 7.16E-03 2.86E-02 7.63E-02 Kr-87 8.88E-01 7.16E-03 2.86E-02 7.63E-02 Kr-88 8.88E-01 7.16E-03 2.86E-02 7.63E-02 I-131 9.30E-01 7.79E-03 2.56E-02 3.61E-02 Iodine 9.30E-01 7.79E-03 2.56E-02 3.61E-02 I-132 9.83E-01 1.51E-03 5.31E-03 9.99E-03 I-133 9.55E-01 4.89E-03 1.62E-02 2.41E-02 I-134 9.88E-01 9.51E-04 3.51E-03 7.66E-03 I-135 9.72E-01 2.79E-03 9.43E-03 1.53E-02 Xe-131m 8.88E-01 7.16E-03 2.86E-02 7.63E-02 Xe-133m 8.88E-01 7.16E-03 2.86E-02 7.63E-02 Xe-133 8.88E-01 7.16E-03 2.86E-02 7.63E-02 Xe-135m 8.88E-01 7.16E-03 2.86E-02 7.63E-02 Xe-135 8.88E-01 7.16E-03 2.86E-02 7.63E-02 Xe-138 8.88E-01 7.16E-03 2.86E-02 7.63E-02 Cs-134 9.25E-01 8.43E-03 2.77E-02 3.88E-02 Cesium 9.25E-01 8.43E-03 2.77E-02 3.88E-02 Cs-136 9.28E-01 8.03E-03 2.64E-02 3.71E-02 Cs-137 9.25E-01 8.44E-03 2.77E-02 3.88E-02 Cs-138 9.89E-0I 8.08E-04 3.05E-03 7.07E-03 Rb-88 9.90E-01 7.03E-04 2.71E-03 6.63E-03 Same as Cesium Br-83 9.83E-01 1.53E-03 5.38E-03 1.01E-02 Same as Iodine Br-84 9.89E-01 8.05E-04 3.04E-03 7.05E-03 (1): 0-30 min Fraction = 0-30 min release (5.1.7) / 0-24 hr release (5.1.8)

(2): 30 min-2hr Fraction = 30 min-2 hr release 5.1.7 / 0-24 hr release (5.1.8)

(3): 2-8 hr Fraction = 2-8 hr release 5.1.8 / 0-24 hr release (5.1.8)

(4): 8-24 hr hr Fraction = (8-24 hr release 5.1.5

+ 8-24 hr release (5.1.6))/ 0-24 hr release 5.1.8

D000040-121, Revision 0 Page 23 of 83 5.2 Source Term with Concurrent Iodine Spike The source term for the concurrent spike includes the following:

I Activity in reactor coolant released due to tube rupture in faulted SG.

2 Activity in secondary coolant released from faulted SG.

3 Activity in reactor coolant released due to I gpm tube leak in intact SG (0 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ).

4 Activity in reactor coolant released due to 1 gpm tube leak in intact SG (2 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ).

5 Activity in reactor coolant released due to 1 gpm tube leak in intact SG (8 to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ).

6 Activity in secondary coolant released from intact SG.

The activity releases are determined in sections 5.2.1 through 5.2.9.

In Ref. 4, iodine appearance rates and resulting average RC concentrations are calculated for a maximum letdown of 143 gpm with the I µCi/gm DE 1-131 values based on letdown flows of 60 gpm and 143 gpm and a factor 335 for the spiking release rate. The case with RC concentrations based on letdown of 143 gpm and the 1 µCi/gm DE 1-131 values based on letdown flow of 143 gpm provides the limiting case for calculating radiological consequences. The average RC iodine concentrations per Reference 4 are given as follows:

As stated earlier, the noble gas concentrations will correspond to the I% failed fuel values based on 60 gpm letdown since they bound the values at the higher letdown flow. These simultaneous use of inputs based on both 60 and 143 gpm letdown is a source of conservatism in the calculation.

Maximum Letdown of 143 m w/143 m 1 Ci/ m DE I-131 Values 335 X Iodine Average RC Concentration (gCi/gm) SGTR Nuclide 0-30 min 0-2hr 30 min-2hr 2-8hr 8-24hr I-131 14.9 57.1 71.2 280.1 433.1 I-132 63.2 216.6 267.7 650.5 165.6 I-133 28.3 107.4 133.8 496.4 592.5 I-134 26.6 75.6 91.9 144.9 12 I-135 25.7 95.3 118.5 386.1 270.2

D000040-121, Revision 0 Page 24 of 83 5.2.1 Primary Coolant Released to Faulted SG due to Tube Rupture 0 - 30 min.

5.2.1 Primary Coolant Activity Released to Faulted SG due to Tube Rupture 0 - 30 min.

Concurrent Iodine Spike With Initial RC Activity at 1 Ci/ m DE 1-131 Isotopes 0-30 min Avg RC Specific Activity (1)

Mass Released to Faulted SG (0-30 min) (2)

Activity Released to Faulted SG (0-30 min) (3)

Flashing Factor (2)

Max. Tube Leak Activity Flashed Released to Environs (4)

Max. Tube Leak Remaining Activity (5) 0-30 min Total Activity Release to Environs (6)

Ci/ m (Ibm)

(Ci)

Kr-85m 1.80E+00 9.29E+04 7.58E+01 1

7.58E+01 0.00E+00 7.58E+01 Kr-85 7.60E+00 9.29E+04 3.20E+02 1

3.20E+02 0.00E+00 3.20E+02 Kr-87 I.IOE+00 9.29E+04 4.64E+01 1

4.64E+01 0.00E+00 4.64E+01 Kr-88 3.20E+00 9.29E+04 1.35E+02 1

1.35E+02 0.00E+00 1.35E+02 I-131 1.49E+01 9.29E+04 6.28E+02 (4) 8.83E+01 5.40E+02 8.83E+01 I-132 6.32E+01 9.29E+04 2.66E+03 (4) 3.75E+02 2.29E+03 3.75E+02 I-133 2.83E+01 9.29E+04 1.19E+03 (4) 1.68E+02 1.02E+03 1.68E+02 I-134 2.66E+01 9.29E+04 1.12E+03 (4) 1.58E+02 9.63E+02 1.58E+02 1-135 2.57E+01 9.29E+04 1.08E+03 (4) 1.52E+02 9.31E+02 1.52E+02 Xe-131m 2.30E+00 9.29E+04 9.69E+01 I

9.69E+01 0.00E+00 9.69E+01 Xe-133m 1.90E+01 9.29E+04 8.01E+02 1

8.01E+02 0.00E+00 8.01E+02 Xe-133 2.90E+02 9.29E+04 1.22E+04 1

1.22E+04 0.00E+00 1.22E+04 Xe-135m 5.20E-01 9.29E+04 2.19E+01 I

2.19E+01 0.00E+00 2.19E+01 Xe-135 8.60E+00 9.29E+04 3.62E+02 I

3.62E+02 0.00E+00 3.62E+02 Xe-138 6.40E-01 9.29E+04 2.70E+01 1

2.70E+01 0.00E+00 2.70E+01 Cs-134 1.15E+00 9.29E+04 4.83E+01 (4) 6.79E+00 4.15E+01 6.79E+00 Cs-136 1.17E+00 9.29E+04 4.94E+01 (4) 6.95E+00 4.24E+01 6.95E+00 Cs-137 5.47E-01 9.29E+04 2.31E+01 (4) 3.24E+00 1.98E+01 3.24E+00 Cs-138 2.53E-01 9.29E+04 1.06E+01 (4) 1.50E+00 9.15E+00 1.50E+00 Rb-88 9.90E-01 9.29E+04 4.17E+01 (4) 5.87E+00 3.58E+01 5.87E+00 Br-83 2.32E-02 9.29E+04 9.77E-01 (4) 1.37E-01 8.40E-01 1.37E-01 Br-84 1.09E-02 9.29E+04 4.61E-01 (4) 6.49E-02 3.96E-01 6.49E-02 (1) Iodine Section 5.2, Noble gas and particulate Section 4.2 (2) Section 4.3 (3) Activity Released (Ci) = Primary Coolant Conc Ci/ m

453.5924 gm/lb

Mass Released Ib

1.0E-6 Ci/ Ci (4) Activity Release to Environment (Ci) = Activity Released to Faulted SGs (Ci)

Flash Factor (5) Remaining Activity (Ci) =(Activity Released to Faulted SGs (Ci) - Flashed Activity Released to Environment)

(6) Total Activity Release to Environment Ci = Activity Flashed

DO00040-121, Revision 0 Page 25 of 83 5.2.2 Activity in Secondary Coolant Released from Faulted SG Secondary coolant specific activity based on 1% RC Activity LB Conservatively Low SG Blowdown (3) =

127561bm/hr MSG Water Mass in All 3 SGs =

3400001bm L,

Leak Rate =

1.0 m =

500.5013034 lbm/hr Decay RC Concentration Sec. Coolant E q. Conc for I m leak Isotopes Constant 1% FF 1% FF (4) 1/sec Ci/ m Ci/lbm (1) 1-131 9.96E-07 3.00E+00 48.7 (2)

Cs-134 1.07E-08 4.40E+00 78.23 (2)

Cs-136 6.09E-07 4.50E+00 75.66 (2)

Cs-137 7.28E-10 2.10E+00 37.37 (2)

Cs-138 3.59E-04 9.70E-01 0.49 (2)

Rb-88 6.49E-04 3.80E+00 1.07 (2)

Br-83 8.05E-05 8.90E-02 0.18 (2)

Br-84 3.63E-04 4.20E-02 0.02 (1) I-131 evaluation and mass and flow input parameters taken directly from Reference 11, page 8 and Reference 4 (pages 13 & 14 and ).

(2) Other isotopes determined using the same methodology as I-131. RC 1% FF concentrations per Reference 6, Table 5-15.

(3) Per Reference 13, Section 10.4.8.1.5: minimum blowdown flow = 30 gpm. 12756 lbm/hr z 25 gpm. The lower the flow (removal term),

the higher the concentration in the steam generators.

(4) Secondary Coolant Equilibrium Concentration calculated using the same methodology presented in Section 5.1.2.

DO00040-121, Revision 0 Page 26 of 83 5.2.2 (continued)

Activity in Secondary Coolant Released from Faulted SG Secondary coolant specific activity based on 0.1%

Ci/ m DE I-11 secondary activity 1% Failed Fuel Tech Spec Secondary System DE 1-131 0.1 Ci/

DE 1-131 Isotope Specific Activity Factor in Secondary Coolant Ci/lbm (1) 0.1/0.1.24 = 0.81 Ci/lbm (2)

I-131 48.7 3.93E+01 1-132 6.29 2.90E-02 1-133 43.5 5.74E+00 1-134 0.505 4.07E-04 1-135 11.4 2.59E-01 Cs-134 78.23 0.81 6.31E+01 Cs-136 75.66 0.81 6.1.0E+01 Cs-137 37.37 0.81 3.01E+01 Cs-138 0.49 0.81 3.93E-01 Rb-88 1.07 0.81 8.62E-01 Br-83 0.18 0.81 1.46E-01 Br-84 0.02 0.81 1.68E-02 (1) Iodine activities per Reference 4, page 13. Others provided in preceding table.

(2) Per Reference 4, page 14 for iodine. The other isotopes are assumed to be directly proportional to the 0.1.tCi/gm DE 1-131 secondary coolant factor of 0.81 per Reference 4, page 14.

D000040-121, Revision 0 Page 27 of 83 5.2.2 (continued)

Activity in Secondary Coolant Released from Faulted SG Secondaty Coolant Activity Release from Faulted SG with 0.1 Ci/

DE I-131 sotopes Sec. Coolant Activity at 0.1 PCi/gm DE 1-131 (1)

Faulted SG Mass Release (0-30 min (2) artition Factor (4)

Faulted SG Activity Release (0-30 min (3)

Ci/lbm (Ibm)

(Ci) 1-131 3.93E+01 5.68E+04 100 2.23E-02 1-132 2.90E-02 5.68E+04 100 1.65E-05 1-133 5.74E+00 5.68E+04 100 3.26E-03 1-134 4.07E-04 5.68E+04 100 2.31 E-07 1-135 2.59E-01 5.68E+04 100 1.47E-04 Cs-134 6.31E+01 5.68E+04 100 3.58E-02 Cs-136 6.10E+01 5.68E+04 100 3.46E-02 Cs-137 3.01E+01 5.68E+04 100 1.71E-02 Cs-138 3.93E-01 5.68E+04 100 2.23E-04 Rb-88 8.62E-01 5.68E+04 100 4.89E-04 Br-83 1.46E-01 5.68E+04 100 8.31 E-05 Br-84 1.68E-02 5.68E+04 100 9.55E-06 (1) Preceding Table (2) Section 4.3 (3) Activity Release to Environment (Ci) = Sec. Coolant Activity Ci/lbm

Steam Release (Ibm) / Partition Factor

1.0E-06 Ci/ Ci (4) Section 3

D000040-121, Revision 0 Page 28 of 83 5.2.3 1.0 gpm SG Tube Leak - Activity Release 0-2 hr 5.2.3 Concurrent Iodine Spike With Initial RC Activi at 1 Ci/ m DE 1-1311 m Tube Leak 0 - 2 hr Isotopes RC Coolant 0-120 min Specific Activity 1

1 gpm SG Tube Leak Mass Release (0-2 hr) 2 I gpm Activity Release to Intact SG (0-2 hr) (3)

Partition Factor (8)

Intact SG Activity Release to Environs (0-2 hr) (4)

Intact SG Activity Release to Environs (0-30 min) (5)

Intact SG Activity Release to Environs (30 min-2 hr) (6) 0-2 hr Activity Remaining in SG (7)

Ci/ m (Ibm)

(Ci)

Kr-85m 1.80E+00 1001 8.17E-01 1

8.17E-01 2.04E-01 6.13E-01 0.00E+00 Kr-85 7.60E+00 1001 3.45E+00 1

3.45E+00 8.63E-01 2.59E+00 0.00E+00 Kr-87 1.10E+00 1001 4.99E-01 1

4.99E-01 1.25E-01 3.75E-01 0.00E+00 Kr-88 3.20E+00 1001 1.45E+00 1

1.45E+00 3.63E-01 1.09E+00 0.00E+00 I-131 5.71E+01 1001 2.59E+01 100 2.59E-01 6.48E-02 1.94E-01 2.57E+01 I-132 2.17E+02 1001 9.83E+01 100 9.83E-01 2.46E-01 7.38E-01 9.74E+01 I-133 1.07E+02 1001 4.88E+01 100 4.88E-01 1.22E-01 3.66E-01 4.83E+01 I-134 7.56E+01 1001 3.43E+01 100 3.43E-01 8.58E-02 2.57E-01 3.40E+01 1-135 9.53E+01 1001 4.33E+01 100 4.33E-01 1.08E-01 3.25E-01 4.28E+01 Xe-131m 2.30E+00 1001 1.04E+00 I

1.04E+00 2.61E-01 7.83E-01 0.00E+00 Xe-133m 1.90E+01 1001 8.63E+00 1

8.63E+00 2.16E+00 6.47E+00 0.00E+00 Xe-133 2.90E+02 1001 1.32E+02 1

1.32E+02 3.29E+01 9.88E+01 0.00E+00 Xe-135m 5.20E-01 1001 2.36E-01 1

2.36E-01 5.90E-02 1.77E-01 0.00E+00 Xe-135 8.60E+00 1001 3.90E+00 1

3.90E+00 9.76E-01 2.93E+00 0.00E+00 Xe-138 6.40E-01 1001 2.91E-01 1

2.91E-01 7.26E-02 2.18E-01 0.00E+00 Cs-134 1.15E+00 1001 5.20E-01 100 5.20E-03 1.30E-03 3.90E-03 5.15E-01 Cs-136 1.17E+00 1001 5.32E-01 100 5.32E-03 1.33E-03 3.99E-03 5.27E-01 Cs-137 5.47E-01 1001 2.48E-01 100 2.48E-03 6.21E-04 1.86E-03 2.46E-01 Cs-138 2.53E-01 1001 1.15E-01 100 1.15E-03 2.87E-04 8.60E-04 1.14E-01 Rb-88 9.90E-01 1001 4.49E-01 100 4.49E-03 1.12E-03 3.37E-03 4.45E-01 Br-83 2.32E-02 1001 1.05E-02 100 1.05E-04 2.63E-05 7.90E-05 1.04E-02 Br-84 1.09E-02 1001 4.97E-03 100 4.97E-05 1.24E-05 3.73E-05 4.92E-03 (1) Section 4.2 except iodines section 5.6 (2) Per Reference 11 1 m = 500.5 lb/hr, i.e., 2 hr = 1001 lb (3) Activity Released (Ci) = Primary Coolant Conc Ci/ m

453.5924 gm/lb

Mass Released lb

1.0E-6 Ci/ Ci (4) 0-2 hr Activity Release to Environment Ci = Activity Released to Intact SGs Ci / Partition Factor (5) 0- 30 min Activity Release to Environment (Ci) = 0-2hr Activity Released /4 (6) 30 min-2 hr Activity Release to Environment (Ci) = 0-2hr Activity Released

0.75 (7) 0-2 hr Activity Remaining in SG = Activity Release to SG (Ci) - Activity Released to Environs (Ci)

(8) Section 3

D000040-121, Revision 0 Page 29 of 83 5.2.4 1.0 gpm SG Tube Leak - Activity Release 2 - 8 hr 5.2.4 Concurrent Iodine With Initial RC Activity at 1 Ci/ m DE 1-1312 - 8 hr sotopes RC Coolant 2-8 hr Specific Activity 1

I gpm SG Tube Leak Mass Release (2-8 hr (2)

SG Activity Available for Release (2-8 hr) (3)

Partition Factor (6)

Intact SG Activity Release to Environs (2-8 hr)

(4)

Intact SG Activity Remaining in SG (2-8 hr) (5)

(ltCi/gm) lbm Ci (Ci)

(Ci)

Kr-85m 1.80E+00 3003 2.45E+00 1

2.45E+00 0.00E+00 Kr-85 7.60E+00 3003 1.04E+01 1

1.04E+01 0.00E+00 Kr-87 1.10E+00 3003 1.50E+00 1

1.50E+00 0.00E+00 Kr-88 3.20E+00 3003 4.36E+00 1

4.36E+00 0.00E+00 I-131 2.80E+02 3003 3.82E+02 100 3.82E+00 3.78E+02 I-132 6.51E+02 3003 8.86E+02 100 8.86E+00 8.77E+02 I-133 4.96E+02 3003 6.76E+02 100 6.76E+00 6.69E+02 I-134 1.45E+02 3003 1.97E+02 100 1.97E+00 1.95E+02 I-135 3.86E+02 3003 5.26E+02 100 5.26E+00 5.21E+02 Xe-131m 2.30E+00 3003 3.13E+00 1

3.13E+00 0.00E+00 Xe-133m 1.90E+01 3003 2.59E+01 1

2.59E+01 0.00E+00 Xe-133 2.90E+02 3003 3.95E+02 I

3.95E+02 0.00E+00 Xe-135m 5.20E-01 3003 7.08E-01 1

7.08E-01 0.00E+00 Xe-135 8.60E+00 3003 1.17E+01 I

1.17E+01 0.00E+00 Xe-138 6.40E-01 3 003 8.72E-01 1

8.72E-01 0.00E+00 Cs-134 1.15E+00 3003 1.56E+00 100 1.56E-02 1.55E+00 Cs-136 1.17E+00 3003 1.60E+00 100 1.60E-02 1.58E+00 Cs-137 5.47E-01 3003 7.45E-01 100 7.45E-03 7.38E-01 Cs-138 2.53E-01 3003 3.44E-01 100 3.44E-03 3.41E-01 Rb-88 9.90E-01 3003 1.35E+00 100 1.35E-02 1.33E+00 Br-83 2.32E-02 3003 3.16E-02 100 3.16E-04 3.13E-02 Br-84 1.09E-02 3003 1.49E-02 100 1.49E-04 1.48E-02 (1) Section 4.2 except iodines section 5.6 (2) Per Reference I 1 1 m = 500.5 lb/hr, i.e., 6 hr = 3003 lb (3) SG Activity= Activity Released Ci to SG (Primary Coolant Cone Ci/ m

453.5924 gm/lb,

Mass Released (lb)

1.0E-6 Ci/ Ci (4) Activity Release to Environment (Ci) = Activity Released to Intact SGs (Ci) / Partition Factor (5) Activity Remaining in SG =SG Activity Available for Release - Activity Released to Environs (6) Section 3

D000040-121, Revision 0 Page 30 of 83 5.2.5 Concurrent Iodine With Initial RC Activity at lµCi/gm DE I-1318 - 24 hr 5.2.5 Concurrent Iodine With Initial RC Activity at 1 Ci/ m DE 1-1318 - 24 hr sotop es RC Coolant 8-24 hr Specific Activity 1

I gpm SG Tube Leak Mass Release (8-24 hr) (2)

SG Activity Available for Release 8-24 hr) (3)

Partition Factor (7)

Intact SG Tube Rupture Activity Release to Environs (8-24 hr) (4)

Intact SG Activity Remaining in SG (8-24 hr) 5 Intact SG Total Activity Release to Environs (8-24 hr) (6)

Ci/ m lbm (Ci)

(Ci)

Kr-85m 1.80E+00 8008 6.54E+00 1

6.54E+00 0.00E+00 6.54E+00 Kr-85 7.60E+00 8008 2.76E+01 I

2.76E+01 0.00E+00 2.76E+01 Kr-87 1.10E+00 8008 4.00E+00 I

4.00E+00 0.00E+00 4.00E+00 Kr-88 3.20E+00 8008 1.16E+01 1

1.16E+01 0.00E+00 1.16E+01 1-131 4.33E+02 8008 1.57E+03 100 1.57E+01 1.56E+03 3.13E+01 1-132 1.66E+02 8008 6.02E+02 100 6.02E+00 5.96E+02 1.20E+01 1-133 5.93E+02 8008 2.15E+03 100 2.15E+01 2.13E+03 4.28E+01 1-134 1.20E+01 8008 4.36E+01 100 4.36E-01 4.32E+01 8.67E-01 1-135 2.70E+02 8008 9.81E+02 100 9.81E+00 9.72E+02 1.95E+01 Xe-131m 2.30E+00 8008 8.35E+00 I

8.35E+00 0.00E+00 8.35E+00 Xe-133m 1.90E+01 8008 6.90E+01 I

6.90E+01 0.00E+00 6.90E+01 Xe-133 2.90E+02 8008 1.05E+03 I

1.05E+03 0.00E+00 1.05E+03 Xe-135m 5.20E-01 8008 1.89E+00 I

1.89E+00 0.00E+00 1.89E+00 Xe-135 8.60E+00 8008 3.12E+01 I

3.12E+01 0.00E+00 3.12E+01 Xe-138 6.40E-01 8008 2.32E+00 1

2.32E+00 0.00E+00 2.32E+00 Cs-134 1.15E+00 8008 4.16E+00 100 4.16E-02 4.12E+00 8.29E-02 Cs-136 1.17E+00 8008 4.26E+00 100 4.26E-02 4.22E+00 8.47E-02 Cs-137 5.47E-01 8008 1.99E+00 100 1.99E-02 1.97E+00 3.95E-02 Cs-138 2.53E-01 8008 9.18E-01 100 9.18E-03 9.09E-01 1.83E-02 Rb-88 9.90E-01 8008 3.60E+00 100 3.60E-02 3.56E+00 7.16E-02 Br-83 2.32E-02 8008 8.42E-02 100 8.42E-04 8.34E-02 1.68E-03 Br-84 1.09E-02 8008 3.97E-02 100 3.97E-04 3.93E-02 7.91E-04 (1) Section 5.2 (2) Per Reference I 1 1 m = 500.5 lb/hr, i.e., 16 hr = 8008 lb (3) SG Activity = Activity Released (Ci) to SG Primary Coolant Cone (ttCi/gm)

453.5924 lb

Mass Released lb

1.0E-6 Ci/ Ci (4) Activity Release to Environment (Ci) = SG Activity Available for Release (Ci) / Partition Factor (5) Activity Remaining in Secondary Side Liquid (Ci) = SG Activity Available for Release (Ci) - Activity Released to Environment (Ci)

(6) Total Activity released in 8-24 hour cooldown steaming = Activity Release from Tube Rupture 4 (7) Section 3

D000040-121, Revision 0 Page 31 of 83 5.2.6 Concurrent Spike Secondary Coolant Activity Release from Intact SG 5.2.6 Concurrent Spike Secondary Coolant Activity Release from Intact SG Isotopes Secondary Coolant Activity @ 0.1uCi/gm DE-I131 uCi/lb (1)

Intact SG Steam Release lb (2)

Partition Factor (3) 0-2 hr Release to Environment Ci 0-30 min Release to Environment Ci 30 min -2 hr Release to Environment Ci 0 - 2 hr I-131 3.93E+01 381400 100 1.50E-01 3.74E-02 1.12E-01 I-132 2.90E-02 381400 100 1.11E-04 2.77E-05 8.31E-05 I-133 5.74E+00 381400 100 2.19E-02 5.47E-03 1.64E-02 I-134 4.07E-04 381400 100 1.55E-06 3.88E-07 1.16E-06 I-135 2.59E-01 381400 100 9.88E-04 2.47E-04 7.41E-04 Cs-134 6.31E+01 381400 100 2.40E-01 6.01 E-02 1.80E-01 Cs-136 6.10E+01 381400 100 2.33E-01 5.81E-02 1.74E-01 Cs-137 3.01E+01 381400 100 1.15E-01 2.87E-02 8.62E-02 Cs-138 3.93E-01 381400 100 1.50E-03 3.75E-04 1.12E-03 Rb-88 8.62E-01 381400 100 3.29E-03 8.22E-04 2.46E-03 Br-83 1.46E-01 381400 100 5.58E-04 1.39E-04 4.18E-04

'Br-84 1.68E-02 381400 100 6.41E-05 1.60E-05 4.81E-05 2 - 8 hr 2-8 hr Release to Environment, Ci 8 - 24 hr Steam release (lb) 8 - 24 hr release to Environment Ci I-131 3.93E+01 924900 100 3.63E-01 1.20E+06 4.71E-01 1-132 2.90E-02 924900 100 2.69E-04 1.20E+06 3.48E-04 I-133 5.74E+00 924900 100 5.31E-02 1.20E+06 6.88E-02 1-134 4.07E-04 924900 100 3.76E-06 1.20E+06 4.88E-06 1-135 2.59E-01 924900 100 2.40E-03 1.20E+06 3.11E-03 Cs-134 6.31E+01 924900 100 5.83E-01 1.20E+06 7.57E-01 Cs-136 6.10E+01 924900 100 5.64E-01 1.20E+06 7.32E-01 Cs-137 3.01E+01 924900 100 2.79E-01 1.20E+06 3.61E-01 Cs-138 3.93E-01 924900 100 3.63E-03 1.20E+06 4.71E-03 Rb-88 8.62E-01 924900 100 7.97E-03 1.20E+06 1.03E-02 Br-83 1.46E-01 924900 100 1.35E-03 1.20E+06 1.76E-03 Br-84 1.68E-02 924900 100 1.55E-04 1.20E+06 2.02E-04 (1) Section 5.2.2 (2) Section 4.3 (3) section 3

D000040-121, Revision 0 Page 32 of 83 5.2.7 Concurrent Spike Total Activity Released 0 - 2 hrs 1.0 gpm 5.2.7 Concurrent Spike Total Activi Released 0 - 2 hrs Lp = I m

5.2.1 5.2.2 5.2.3 5.2.6 Faulted Faulted Intact Intact 0-2 hr 0-30 min 30 min - 2 hr SG Tube SG Sec.

SG Tube SG Sec.

Total Total Total Rupture Coolant Leak Coolant Activity Activity Activity Isotopes Release Release Release Release Release Release Release 0-30 min 0-30 min 0-2 hr 0-2 hr (Ci)

(Ci)

Kr-85m 7.58E+01 0.00E+00 8.17E-01 0.00E+00 7.67E+01 7.61E+01 6.13E-01 Kr-85 3.20E+02 0.00E+00 3.45E+00 0.00E+00 3.24E+02 3.21E+02 2.59E+00 Kr-87 4.64E+01 0.00E+00 4.99E-01 0.00E+00 4.69E+01 4.65E+01 3.75E-01 Kr-88 1.35E+02 0.00E+00 1.45E+00 0.00E+00 1.36E+02 1.35E+02 1.09E+00 I-131 8.83E+01 2.23E-02 2.59E-01 1.50E-01 8.87E+01 8.84E+01 3.07E-01 I-132 3.75E+02 1.65E-05 9.83E-01 1.11E-04 3.76E+02 3.75E+02 7.38E-01 I-133 1.68E+02 3.26E-03 4.88E-01 2.19E-02 1.68E+02 1.68E+02 3.82E-01 I-134 1.58E+02 2.31E-07 3.43E-01 1.55E-06 1.58E+02 1.58E+02 2.57E-01 I-135 1.52E+02 1.47E-04 4.33E-01 9.88E-04 1.53E+02 1.52E+02 3.25E-01 Xe-131m 9.69E+01 0.00E+00 1.04E+00 0.00E+00 9.80E+01 9.72E+01 7.83E-01 Xe-133m 8.01E+02 0.00E+00 8.63E+00 0.00E+00 8.09E+02 8.03E+02 6.47E+00 Xe-133 1.22E+04 0.00E+00 1.32E+02 0.00E+00 1.24E+04 1.23E+04 9.88E+01 Xe-135m 2.19E+01 0.00E+00 2.36E-01 0.00E+00 2.21E+01 2.20E+01 1.77E-01 Xe-135 3.62E+02 0.00E+00 3.90E+00 0.00E+00 3.66E+02 3.63E+02 2.93E+00 Xe-138 2.70E+01 0.00E+00 2.91E-01 0.00E+00 2.73E+01 2.70E+01 2.18E-01 Cs-134 6.79E+00 3.58E-02 5.20E-03 2.40E-01 7.08E+00 6.89E+00 1.84E-01 Cs-136 6.95E+00 3.46E-02 5.32E-03 2.33E-01 7.22E+00 7.04E+00 1.78E-01 Cs-137 3.24E+00 1.71E-02 2.48E-03 1.15E-01 3.38E+00 3.29E+00 8.80E-02 Cs-138 1.50E+00 2.23E-04 1.15E-03 1.50E-03 1.50E+00 1.50E+00 1.98E-03 Rb-88 5.87E+00 4.89E-04 4.49E-03 3.29E-03 5.88E+00 5.87E+00 5.84E-03 Br-83 1.37E-01 8.31E-05 1.05E-04 5.58E-04 1.38E-01 1.38E-01 4.97E-04 Br-84 6.49E-02 9.55E-06 4.97E-05 6.41E-05 6.50E-02 6.49E-02 8.53E-05

D000040-121, Revision 0 Page 33 of 83 5.2.8 Concurrent Spike Total Activity Released 2 - 8 hrs 1.0 gpm 5.2.8 Concurrent Spike Total Activi Released 2 - 8 hrs Lp = I m

5.2.1 5.2.2 5.2.4 5.2.6 Faulted Faulted Intact Intact 2-8 hr 0-8 hr 0-24 HR SG Tube SG Sec.

SG Tube SG Sec.

Total Total Total Rupture Coolant Leak Coolant Activity Activity Activity Isotopes Release Release Release Release Release Release (1)

Release (2)

(Ci)

Kr-85m 0

2.45E+00 2.45E+00 79 86 Kr-85 0

1.04E+01 1.04E+01 334 362 Kr-87 0

1.50E+00 1.50E+00 48 52 Kr-88 0

4.36E+00 4.36E+00 141 152 I-131 0

0 3.82E+00 3.63E-01 4.18E+00 93 125 1-132 0

0 8.86E+00 2.69E-04 8.86E+00 384 396 I-133 0

0 6.76E+00 5.31E-02 6.81E+00 175 218 I-134 0

0 1.97E+00 3.76E-06 1.97E+00 160 161 I-135 0

0 5.26E+00 2.40E-03 5.26E+00 158 178 Xe-131m 0

3.13E+00 3.13E+00 101 109 Xe-133m 0

2.59E+01 2.59E+01 835 904 Xe-133 0

3.95E+02 3.95E+02 12747 13800 Xe-135m 0

7.08E-01 7.08E-01 23 25 Xe-135 0

1.17E+01 1.17E+01 378 409 Xe-138 0

8.72E-01 8.72E-01 28 30 Cs-134 0

0 1.56E-02 5.83E-01 5.99E-01 8

9 Cs-136 0

0 1.60E-02 5.64E-01 5.80E-01 8

9 Cs-137 0

0 7.45E-03 2.79E-01 2.86E-01 4

4 Cs-138 0

0 3.44E-03 3.63E-03 7.08E-03 2

2 Rb-88 0

0 1.35E-02 7.97E-03 2.15E-02 6

6 Br-83 0

0 3.16E-04 1.35E-03 1.67E-03 0.1 0.1 Br-84 0

0 1.49E-04 1.55E-04 3.04E-04 0.1 0.1 (1) 0-8 hr Total Activity Release Ci = 0-2 hr Total Activity Release (Ci) (5.2.7) + 2-8 hr Total Activity Remaining Release (C i) (5.2.8)

(2) 0-24 hr Total Activity Release Ci = 0-8 hr Total Activity Release (Ci) (5.2.8) + 0-24 hr Secondary Activity Remaining Release (Ci) 5.2.5

D000040-121, Revision 0 Page 34 of 83 5.2.9 Concurrent Spike Fraction Total Activity Released 5.2.9 Concurrent Spike Fraction of Total Activity Released Isotopes Time Period Release By Species 0-30 min 30 min-2hr 2-8hr 8-24 hr 0-30 min 30 min-2hr 2-8hr 8-24 hr (1)

(2)

(3)

(4)

Kr-85m 8.88E-01 7.16E-03 2.86E-02 7.63E-02 Nobles 8.88E-01 7.16E-03 2.86E-02 7.63E-02 Kr-85 8.88E-01 7.16E-03 2.86E-02 7.63E-02 Kr-87 8.88E-01 7.16E-03 2.86E-02 7.63E-02 Kr-88 8.88E-01 7.16E-03 2.86E-02 7.63E-02 I-131 7.09E-01 2.46E-03 3.35E-02 2.55E-01 Iodine 7.09E-01 2.46E-03 3.35E-02 2.55E-01 I-132 9.46E-01 1.86E-03 2.24E-02 3.02E-02 I-133 7.70E-01 1.75E-03 3.13E-02 1.97E-01 I-134 9.81 E-01 1.60E-03 1.23E-02 5.39E-03 I-135 8.59E-01 1.83E-03 2.96E-02 1.10E-0I Xe-131m 8.88E-01 7.16E-03 2.86E-02 7.63E-02 Xe-133m 8.88E-01 7.16E-03 2.86E-02 7.63E-02 Xe-133 8.88E-01 7.16E-03 2.86E-02 7.63E-02 Xe-135m 8.88E-01 7.16E-03 2.86E-02 7.63E-02 Xe-135 8.88E-01 7.16E-03 2.86E-02 7.63E-02 Xe-138 8.88E-01 7.16E-03 2.86E-02 7.63E-02 Cs-134 8.09E-01 2.16E-02 7.03E-02 9.86E-02 Cesium 8.09E-01 2.16E-02 7.03E-02 9.86E-02 Cs-136 8.17E-01 2.07E-02 6.73E-02 9.48E-02 Cs-137 8.09E-01 2.17E-02 7.04E-02 9.87E-02 Cs-138 9.79E-01 1.30E-03 4.62E-03 1.50E-02 Rb-88 9.82E-01 9.76E-04 3.59E-03 1.37E-02 Same as Cesium Br-83 9.61E-01 3.47E-03 1.16E-02 2.39E-02 Same as Iodine Br-84 9.79E-01 1.29E-03 4.59E-03 1.50E-02 (1): 0-30 min Fraction = 0-30 min release (5.2.7) / 0-8hr release (5.2.8)

(2): 30 min-2hr Fraction = 30 min-2 hr release (5.2.7) / 0-8 hr release (5.2.8)

(3): 2-8 hr Fraction = 2-8 hr release (5.2.8) / 0-8 hr release (5.2.8)

(4): 2-8 hr Fraction = (8-24 hr release (5.2.5) + 8-24 hr release (5.2.6)) / 0-24 hr release 5.2.8

DO00040-121, Revision 0 Page 35 of 83 5.3 TSC ventilation system parameters:

The VCSNS TSC design features include post accident isolation with filtered supply and pressurization.

The following parameters are utilized in accessing the post-accident dose consequences to TSC personnel.

The total free volume of the TSC envelope located in the basement of the new Nuclear Operations Building (elevation 100') is 207,000 ft3 per Reference 17. The TSC envelope consists of all the areas depicted on the basement floor plan (Reference 17.a) excluding the south stairwell and area way open to above (southwest corner). The area between column lines B and G.2 and 2 and the fire wall running north-south is approximately 80' by 110' or 8,800 W. The area between column lines B and V and the fire wall running north-south and 5 is approximately 36' by (200' - 12') or 6,768 ft2. The total area is 8,800 ft2 + 6,768 ft2 or 15,568 ft2.

The height of the TSC envelope is determined per Reference 17.b, Cross Section 3. The basement and first floor finished elevations of 100' and 120' are used. A first floor thickness of 1' is assumed. The total height is (120' - 1') - 100' or 19'. The total volume of the TSC envelope is 15,568 ft2

19' or 295,792 ft3. It is assumed that 30 percent of the volume consists of components and/or structures, thus the total available free air volume is:

VTSC Envelope = 295,792 ft3

0.7 or 2.07E+05 ft3 For this analysis, it is conservatively assumed that the TSC never enters the emergency mode of operation (no filtration of make-up air through the filtered air handling unit FFU-1).

TSC Normal Air Handling System flow rates, flow path and potential unfiltered leakage are determined below.

The Basement plan HVAC ductwork is provided in Reference 17.c. During normal operation, supply air enters the TSC envelope through the fan filter unit (FFU-1). The filters are by-passed and the make-up air is distributed throughout the TSC envelope with air handling unit AHU-0-1. Per Reference 17.d, AHU 1 has a capacity of 12,000 cfm.

Per Reference 18, Section 15940 - HVAC sequence of operation is as follows:

3.09 Technical Support Center (TSC)

Manual operator action is required for the TSC to function in the emergency mode. It is conservatively assumed the TSC personnel do not take any manual actions to isolate the TSC envelope and enter the emergency mode of operation.

A.

Non-Emergency Mode of Operation.

1.

AHU-0-1 shall operate as specified for VAV air handling unit(s) with static pressure optimization.

2.

Modulate return air damper in TSC space to maintain 1/8" wg positive pressure between the TSC space and the adjacent corridor.

Flow Rates under TSC Normal Operation

DC00040-121, Revision 0 Page 36 of 83 Makeup air through AHU-0-1: 12,000 cfm A total of 13,000 cfm of unfiltered outside air is assumed to flow into and out of the TSC. The 13,000 cfm conservatively bounds the expected design flow rate (AHU-0-1) of 12,000 cfm. The doses are conservatively calculated assuming no credit for filtration for the duration of the accident.

6.0 RADTRAD MODELS 6.1 SGTR Design Case-RADTRAD Models 6.1.1 RADTRAD Model - SGTR - Design Basis Case A visual representation of the RADTRAD model is given in Attachment No. 1 and is discussed below.

The activity released to the environment calculated in the previous sections for the concurrent and pre existing spike cases are assumed to be released as a ground release from the Main Steam SRVs. This is accomplished by purging the Containment free air volume (arbitrarily set to 1.0E+04 ft3) at a very high rate (1.OE+10 cfm) while releasing the available activity over a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period.

The RADTRAD model input for the SGTR case consists of 3 volumes, 5 flow pathways, and 3 dose locations.

Nuclide inventories are input as user defined NIF files (Attachment 2). Release fractions and timing data are input as user defined RFT files (Attachment 2).

6.1.2 RADTRAD Volume 1 represents the Containment Containment volume is modeled as 1.0E+04 cu ft (arbitrary-methodology is independent of volume) 6.1.3 RADTRAD Volume 2 represents the Environment No inputs 6.1.4 RADTRAD Volume 3 represents the Technical Support Center Technical Support Center habitability volume equals 207,000 ft3 No recirculating filters utilized No additional inputs

D000040-121, Revision 0 Page 37 of 83 6.1.5 RADTRAD Pathway 1 represents the Containment leakage term Containment air leakage rate modeled as 1.0E+10 cfm (to allow for complete release over a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period) 0% efficient filters for elemental and organic species No additional inputs 6.1.6 RADTRAD Pathway 2 represents the TSC Outside Air Intake Pathway Normal Mode - Outside air intake equals 12,000 cfm No Emergency Mode or Filtration No additional inputs 6.1.7 RADTRAD Pathway 3 represents the TSC Unfiltered Air Inleakage Pathway TSC unfiltered air inleakage is conservatively assumed to be 1,000 cfm for the duration of the 30-day transient No filter is applied to this pathway No additional inputs 6.1.8 RADTRAD Pathway 4 represents the TSC Exhaust Air Pathway Normal Mode - Exhaust air flow equals intake and inleakage, 12,000 cfm plus 1,000 cfm =

13,000 cfm No filter is applied to this pathway No additional inputs 6.1.9 RADTRAD Pathway 5 represents the TSC Emergency Recirculation Pathway Not Used 6.1.10 RADTRAD Dose Location 1-Protected TSC x/Q values per Section 4.4 Use breathing rate and occupancy values per Sections 4.6 and 4.7 No additional inputs 6.1.11 RADTRAD Dose Location 2 - EAB x/Q values per Section 4.4 Use breathing rate and occupancy values per Sections 4.6 and 4.7 No additional inputs 6.1.12 RADTRAD Dose Location 3 - LPZ x/Q values per Section 4.4 Use breathing rate and occupancy values per Sections 4.6 and 4.7 No additional inputs

D000040-121, Revision 0 Page 38 of 83 6.1.13 RADTRAD Source Term:

Modeled power level to obtain total I-131 activity release at 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months as 1.0108 MWth and 1.0033 MWth for the concurrent and pre existing spike cases.

Model isotopic decay and daughter in-growth.

The specified iodine species fractions are 0.97 elemental and 0.03 organic.

Use dose conversion factors input file, SGTR.inp.

No additional inputs.

6.1.14 RADTRAD Control Options:

Applicable Control Options are selected for the additional data supplied in the output printout.

The resulting RADTRAD output files for the SGTR are provided in Attachments 3 and 4.

7.0 RESULTS and CONCLUSIONS As shown in the following table the reported doses meet the NRC dose acceptance criteria.

The dose acceptance criteria (References I & 2) for the Pre-existing Iodine Spike SGTR event are given as 25 Rem TEDE for the EAB and LPZ and 5 Rem TEDE for the CR/TSC. Dose acceptance criteria for the Concurrent Iodine Spike SGTR event is given as 2.5 Rem TEDE for the EAB and LPZ and 5 Rem TEDE for the CR/TSC.

The EAB and LPZ doses are the same as those provided in the AST SGTR calculation D000040-098, Revision 2 (Reference 3).

Dose (Rem TEDE)

EAB LPZ TSC Attachment Pre-existing Iodine Spike 0.60 0.12 0.18 3

Concurrent Iodine Spike 0.25 0.058 0.077 4

8.0 DISPOSITION of RESULTS The results of this calculation are incorporated into the VCSNS FSAR 15.4.3.

DC00040-121, Revision 0 Page 39 of 83

9.0 REFERENCES

1 USNRC Regulatory Guide 1.183 Revision 0, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors", July, 2000.

2 Code of Federal Regulations, Title 10, Section 50.67, "Accident Source Term", 2000.

3 DO00040-098, "Steam Generator Tube Rupture - AST", Revision 2.

4 DC00040-038, Iodine Spikes, Revision 5.

5 NUREG/CR-6604, "RADTRAD: A Simplified Model for Radionuclide Transport and Removal and Dose Estimation", December 1997 and NUREG/CR-6604 (SAND98-0272/1), Supplement 1, "RADTRAD: A Simplified Model for Radionuclide Transport and Removal and Dose Determination", June 8, 1999.

6 Westinghouse Radiation Analysis Manual, Revision 0 for VCSNS Uprating dated 12/8/92 (attachment to letter CGE-92-0019SGUL).

7 VCS Technical Specifications 3.4.8 and 3.7.1.4, Amendment 179.

8 Westinghouse Calculation CN-CRA-03-97, CGE SGTR Doses, Revision 0.

9 USNRC, "Iodine Behavior in a PWR Cooling System Following a Postulated Steam Generator Tube Rupture Accident," NUREG-0409, May 1985.

10 Westinghouse Transmittal #CGE-93-0008SGUL (ET-NSASD-SAI-93-167) dated 3/5/93, Transmittal of Revised SECL and FSAR Markup for SGTR Analysis for V. C. Summer Steam Generator Replacement/Plant Uprating.

11 DC00040-005, Secondary Coolant System Equilibrium Analysis, Revision 4.

12 Westinghouse Radiation Analysis Manual, Revision 1 for VCSNS Uprating updated 12/98 (attachment to letter CGE-98-036).

13 V. C. Summer Nuclear Station Final Safety Analysis Report.

14 DO00040-079, Atmospheric Dispersion Coefficients for Control Room, Revision 3.

15 VCSNS Calculation DO00040-111, Revision 0, Short Term Accident x/Qs.

16 ICRP 30, Limits for Intake of Radionuclides by Workers, 1980.

17 GMK Associates, Inc. drawings for VC Summer Nuclear Operations Building.

a.

1MS-82-202 (A2.0) - "Basement Floor Plan", RO b.

1MS-82-213 (A4.0) - "Building Sections", RO

DC00040-121, Revision 0 Page 40 of 83 c.

1MS-82-700 (M2.0) - "Basement Plan HVAC Ductwork", RO d.

1MS-82-717 (M7.2) - "HVAC Schedules", RO

17. VC Summer Nuclear Operations Building, A/E Project #07023.05, "Project Manual Including Specifications Issued for Construction", GMK Associates, Inc., May 6, 2011.

18. Memorandum from T. F. Mackay to D. O. Smith, Jr., 9/18/79, VCSNS Design Data for Control Room Dose Evaluation.

19.. Memo from D. Lengel to L. Cartin, "Control Room Velocity Measurement Instrument Uncertainties".

20. Lederer and Shirley, "Table of Isotopes", 7th Edition.

21. VCSNS Calculation DC00040-103, "Calculation of Secondary Side Extended Mass Releases During Cooldown for AST Analyses, Revision 0.

DO00040-121, Revision 0 Page 41 of 83 Attachment No. 1 RADTRAD Model

D000040-121, Revision 0 Page 42 of 83 Volume 1 FP 2 - 12,000 cfm makeup (0 - 720 hr.)

no filtration Volume 3 Release FP 1 Volume 2 TSC Volume 1.0E+10 cfm Habitability (arbitrar flow rate)

Environment 1.0+04 ft' y

No filtration or holdup Envelope (2.07E+05 ft3)

(arbitrary volume)

N FP 3 - 1,000 cfm unfiltered inleakage (0 -720 hr.

unfiltered inleakage/ damper leakage /

ingress/egress FP 4 - TSC exhaust: makeup plus unfiltered inleakage 13,000 cfm (0 - 720 hr.)

DO00040-121, Revision 2 Page 43 of 83 Attachment No. 2 RADTRAD NIF and RFT Files

SGTR concurrent TSC.NIF Nuclide Inventory Name:Case 1 VCS SGTR concurrent spike Power Level:

0.1000E+01 Nuclides:

22 Nuclide 001:

Kr-85m 1

0.1612800000E+05 0.8500E+02 86.

Kr-85 0.2100E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 002:

Kr-85 1

0.3382974720E+09 0.8500E+02 362.

none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 003:

Kr-87 1

0.4578000000E+04 0.8700E+02 52.

Rb-87 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 004:

Kr-88 1

0.1022400000E+05 0.8800E+02 152.

Rb-88 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 005:

1-131 2

0.6946560000E+06 0.1310E+03 125.

Xe-131m 0.1100E-01 none 0.0000E+00 none 0.0000E+00 Nuclide 006:

1-132 2

0.8280000000E+04 0.1320E+03 396.

none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 007:

1-133 2

0.7488000000E+05 0.1330E+03 218.

Re-133m 0.2900E-01 Re-133 0.9700E+00 none 0.0000E+00 Nuclide 008:

1-134

2 0.3156000000E+04 0.1340E+03 161.

none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 009:

1-135 2.

0.2379600000E+05 0.1350E+03 178.

Xe-135m 0.1500E+00 Xe-135 0.8500E+00 none 0.0000E+00 Nuclide 010 Xe-131m 1

1.0229760000E+06 0.1310E+03 109.

none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 011:

Xe-133m 1

1.8921600000E+05 0.1330E+03 904.

Xe-133 1.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 012:

Xe-133 1

0.4531680000E+06 0.1330E+03 13800.

none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 013:

Xe-135m 1

9.2167177120E+02 0.1350E+03 25.

Xe-135 1.0000E+00 Cs-135 1.0000E+00 none 0.0000E+00 Nuclide 014:

Xe-135 1

0.3272400000E+05 0.1350E+03 409.

Cs-135 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 015:

Xe-138 1

8.5020000000E+02 1.3800E+02 30.

Cs-138 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 016:

Cs-134 3

0.6507177120E+08

0. 1340E+03 9.

none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 017:

Cs-136 3

0.1131840000E+07 0.1360E+03 9.

none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 018:

Cs-137 3

0.9467280000E+09 0.1370E+03 4.

Ba-137m 0.9500E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 019:

Cs-138 3

1.9320000000E+03 1.3800E+02 2.

none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 020:

Rb-88 3

1.0680000000E+03 8.8000E+01 6.

none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 021:

Br-83 2

8.6040000000E+03 8.3000E+01 0.1 Kr-83m 1.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 022:

Br-84 2

1.9080000000E+03 8.4000E+01 0.1 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 End of Nuclear Inventory File

Nuclide Inventory Name: Case 1 VCS SGTR pre incident spike Power Level:

0.1000E+01 Nuclides:

22 Nuclide 001:

Kr-85m 1

0.1612800000E+05 0.8500E+02 86.

Kr-85 0.2100E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 002:

Kr-85 1

0.3382974720E+09 0.8500E+02 362.

none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 003:

Kr-87 1

0.4578000000E+04 0.8700E+02 52.

Rb-87 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 004:

Kr-88 1

0.1022400000E+05 0.8800E+02 152.

Rb-88 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 005:

1-131 2

0.6946560000E+06 0.1310E+03 300.

Xe-131m 0.1100E-01 none 0.0000E+00 none 0.0000E+00 Nuclide 006:

1-132 2

0.8280000000E+04 0.1320E+03 292.

none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 007:

1-133 2

0.7488000000E+05 0.1330E+03 448.

Re-133m 0.2900E-01 Xe-133 0.9700E+00 none 0.0000E+00 Nuclide 008:

1-134 2

SGTR pre TSC.NIF

D000040-121, Revision 2 Page 48 of 83 0.3156000000E+04 0.1340E+03 56.

none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 009:

1-135 2

0.2379600000E+05 0.1350E+03 229.

Xe-135m 0.1500E+00 Xe-135 0.8500E+00 none 0.0000E+00 Nuclide 010 Xe-131m 1

1.0229760000E+06 0.1310E+03 109.

none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 011:

Xe-133m 1

1.8921600000E+05 0.1330E+03 904.

Xe-133 1.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 012:

Xe-133 1

0.4531680000E+06 0.1330E+03 13800.

none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 013:

Xe-135m 1

9.2167177120E+02 0.1350E+03 25.

Xe-135 1.0000E+00 Cs-135 1.0000E+00 none 0.0000E+00 Nuclide 014:

Xe-135 1

0.3272400000E+05 0.1350E+03 409.

Cs-135 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 015:

Xe-138 1

8.5020000000E+02 1.3800E+02 30.

Cs-138 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 016:

Cs-134 3

0.6507177120E+08 0.1340E+03

7.

none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 017:

Cs-136 3

0.1131840000E+07 0.1360E+03 B.

none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 018:

Cs-137 3

0.9467280000E+09 0.1370E+03 4.

Ba-137m 0.9500E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 019:

Cs-138 3

1.9320000000E+03 1.3800E+02 2.

none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 020:

Rb-88 3

1.0660000000E+03 8.8000E+01 6.

none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 021:

Br-83 2

8.6040000000E+03 8.3000E+01 8.

Kr-83m 1.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 022:

Br-84 2

1.9080000000E+03 8.4000E+01 4.

none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 End of Nuclear Inventory File

D000040-121, Revision 2 Page 50 of 83 SGTR concurrent TSC.RFT Release Fraction and Timing Name: SGTR Concurrent Iodine Spike Release Break Activity over 24 Hours Case,l Duration (h):

VCS SGTR Concurrent Iodine Spike 24 Hr Release 0.5000E+00 1.5000E+00 6.0000E+00 1.6000E+01 Noble Gases:

8.8800E-01 7.1600E-03 2.8600E-02 7.6300E-02 Iodine:

7.0900E-01 2.4600E-03 3.3500E-02 2.5500E-01 Cesium:

8.0900E-01 2.1600E-02 7.0300E-02 9.8600E-02 Tellurium:

0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Strontium:

0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Barium:

0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Ruthenium:

0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Cerium:

0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Lanthanum:

0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Non-Radioactive Aerosols (kg):

0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 End of Release File

D000040-121, Revision 2 Page 51 of 83 SGTR pre TSC.RFT Release Fraction and Timing Name: SGTR Pre-Accident Iodine Spike Release Break Activity over 24 Hours Case 1 Duration (h):

VCS SGTR Pre-Accident Iodine Spike 24 Hr Release 0.5000E+00 1.5000E+00 6.0000E+00 1.6000E+01 Noble Gases:

8.8800E-01 7.1600E-03 2.8600E-02 7.6300E-02 Iodine:

9.3000E-01 7.7900E-03 2.5600E-02 3.6100E-02 Cesium:

9.2500E-01 8.4300E-03 2.7700E-02 3.8800E-02 Tellurium:

0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Strontium:

0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Barium:

0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Ruthenium:

0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Cerium:

0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Lanthanum:

0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Non-Radioactive Aerosols (kg):

0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 End of Release File

DO00040-121, Revision 0 Page 52 of 83 Attachment No. 3 RADTRAD Pre-existing Spike

D000040-121, Revision 0 Page 53 of 83 RADTRAD Version 3.03 (Spring 2001) run on 12/13/2011 at 7:01:55 File information Plant file

=

Inventory file

=

Release file

=

C:\\radtrad3.03\\2011 SGTR c:\\radtrad3.03\\2011 sgtr c:\\radtrad3.03\\2011 sgtr TSC\\Att 3 -`VCS SGTR pre I Spike TSC.psf tsc\\sgtr pre tsc.nif tsc\\sgtr pre tsc.rft Dose Conversion file = c:\\radtrad3.03\\2011 sgtr tsc\\sgtr.inp It It It It It Radtrad 3.03 4/15/2001 SGTR Nuclide Inventory File:

c:\\radtrad3.03\\2011 sgtr tsc\\sgtr pre tsc.nif Plant Power Level:

1.0033E+00 Compartments:

3 Compartment 1:

Arbitrary Volume 3

1.0000E+04 0

0 0

Compartment 2:

Environment 2

0.0000E+00 0

0 0

Compartment 3:

TSC 1

2.0700E+05 0

0 0

Pathways:

4 Pathway 1:

Release Volume to Environment 1

2 2

Pathway 2:

Environment to TSC - Makeup 2

3

2 Pathway 3:

Environment to TSC - Inleakage 2

3 2

Pathway 4:

TSC to Environment - Exhaust 3

2 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1

1.0000E+00 c:\\radtrad3.03\\2011 sgtr tsc\\sgtr.inp c:\\radtrad3.03\\2011 sgtr tsc\\sgtr pre tsc.rft 0.0000E+00 1

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

0 0.0000E+00 0

0 0

0 Compartments:

3 Compartment 1:

1 1

0 0

0 Compartment 2:

0 1

0 0

0 Compartment 3:

0 1

0 0

0 Pathways:

4 Pathway 1:

0 0

0 1

2 0.0000E+00 1.0000E+10 0.0000E+00 0.0000E+00 0.0000E+00

D000040-121, Revision 0 Page 55 of 83 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 Pathway 2:

0 0

0 1

3 0.0000E+00 1.2000E+04 0.0000E+00 0.0000E+00 0.0000E+00 5.0000E-01 1.2000E+04 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 Pathway 3:

0 0

0 1

3 0.0000E+00 1.0000E+03 0.0000E+00 0.0000E+00 0.0000E+00 5.0000E-01 1.0000E+03 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 Pathway 4:

0 0

0 1

2 0.0000E+00 1.3000E+04 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 Dose Locations:

3 Location 1:

EAB 2

1 2

0.0000E+00 1.2400E-04 7.2000E+02 0.0000E+00 1

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

Location 2:

LPZ 2

1 5

0.0000E+00 2.4200E-05 8.0000E+00 1.6800E-05 2.4000E+01 7.5500E-06 9.6000E+01 2.4000E-06 7.2000E+02 0.0000E+00 1

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

Location 3:

TSC 3

0 1

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

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

1 6

0.0000E+00 3.9000E-05 2.0000E+00 3.3000E-05 8.0000E+00 1.6000E-05 2.4000E+01 1.2000E-05 9.6000E+01 8.7000E-06 7.2000E+02 0.0000E+00 Simulation Parameters:

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

C:\\radtrad3.o0 1

1 1

0 1

End of Scenario File

D000040-121, Revision 0 Page 57 of 83 RADTRAD Version 3.03 (Spring 2001) run on 12/13/2011 at 7:01:55 Plant Description Number of Nuclides = 22 Inventory Power =

1.0000E+00 MWth Plant Power Level =

1.0033E+00 MWth Number of compartments

=

3 Compartment information Compartment number 1 (Source term fraction =

1.0000E+00 Name: Arbitrary Volume Compartment volume =

1.0000E+04 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 1 Exit Pathway Number 1:

Release Volume to Environment Compartment number 2 Name: Environment Compartment type is Environment Pathways into and out of compartment 2 Inlet Pathway Number 1:

Release Volume to Environment Inlet Pathway Number 4:

TSC to Environment - Exhaust Exit Pathway Number 2:

Environment to TSC - Makeup Exit Pathway Number 3:

Environment to TSC - Inleakage Compartment number, 3 Name: TSC Compartment volume =

2.0700E+05 (Cubic feet)

Compartment type is Control Room Pathways into and out of compartment 3 Inlet Pathway Number 2:

Environment to TSC - Makeup Inlet Pathway Number 3: Environment to TSC - Inleakage Exit Pathway Number 4:

TSC to Environment - Exhaust Total number of pathways =

4

DC00040-121, Revision 0 Page 58 of 83 RADTRAD Version 3.03 (Spring 2001) run on 12/13/2011 at 7:01:55 Scenario Description Radioactive Decay is enabled Calculation of Daughters is enabled Release Fractions and Timings GAP EARLY IN-VESSEL LATE RELEASE RELEASE MASS 0.500000 hr 1.5000 hrs 6.0000 hrs (gm)

NOBLES IODINE CESIUM TELLURIUM STRONTIUM BARIUM RUTHENIUM CERIUM LANTHANUM 8.8800E-01 9.3000E-01 9.2500E-01 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 7.1600E-03 2.8600E-02 7.7900E-03 2.5600E-02 8.4300E-03 2.7700E-02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 9.267E-01 2.814E-03 4.967E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00.

0.000E+00 0.000E+00 1

MW Inventory Power =

t Nuclide Group Specific half Whole Body Inhaled Inhaled Name Inventory (Ci/MWt) life DCF (s)

(Sv-m3/Bq-s)

Thyroid (Sv/Bq)

Effective (Sv/Bq)

Kr-85m 1

8.600E+01 1.613E+04 7.480E-15 0.000E+00 0.000E+00 Kr-85 1

3.620E+02 3.383E+08 1.190E-16 0.000E+00 0.000E+00 Kr-87 1

5.200E+01 4.578E+03 4.120E-14 0.000E+00 0.000E+00 Kr-88 1

1.520E+02 1.022E+04 1.020E-13 0.000E+00 0.000E+00 I-131 2

3.000E+02 6.947E+05 1.820E-14 2.920E-07 8.890E-09 I-132 2

2.920E+02 8.280E+03 1.120E-13 1.740E-09 1.030E-10 I-133 2

4.480E+02 7.488E+04 2.940E-14 4.860E-08 1.580E-09 1-134 2

5.600E+01 3.156E+03 1.300E-13 2.880E-10 3.550E-11 I-135.

2 2.290E+02 2.380E+04 8.294E-14 8.460E-09 3.320E-10 Xe-131m 1

1.090E+02 1.023E+06 3.890E-16 0.000E+00 0.000E+00 Xe-133m 1

9.040E+02 1.892E+05 1.370E-15 0.000E+00 0.000E+00 Xe-133 1

1.380E+04 4.532E+05 1.560E-15 0.000E+00 0.000E+00 Xe-135m 1

2.500E+01 9.217E+02 2.040E-14 0.000E+00 0.000E+00 Xe-135 1

4.090E+02 3.272E+04 1.190E-14 0.000E+00 0.000E+00 Xe-138 1

3.000E+01 8.502E+02 5.770E-14 0.000E+00 0.000E+00 Cs-134 3

7.000E+00 6.507E+07 7.570E-14 1.110E-08 1.250E-08 Cs-136 3

8.000E+00 1.132E+06 1.060E-13 1.730E-09 1.980E-09 Cs-137 3

4.000E+00 9.467E+08 2.725E-14 7.930E-09 8.630E-09 Cs-138 3

2.000E+00 1.932E+03 1.210E-13 3.570E-12 2.740E-11 Rb-88 3

6.000E+00 1.068E+03 3.360E-14 1.370E-12 2.260E-11 Br-83 2

8.000E+00 8.604E+03 3.820E-16 1.140E-12 2.410E-11 Br-84 2

4.000E+00 1.908E+03 9.410E-14 3.120E-12 2.610E-11 Nuclide Daughter Fraction Daughter Fraction Daughter Fraction Kr-85m Kr-85 0.21 none 0.00 none 0.00 Kr-87 Rb-87 1.00 none 0.00 none 0.00 Kr-88 Rb-88 1.00 none 0.00 none 0.00 1-131 Xe-131m 0.01 none 0.00 none 0.00 1-133 Xe-133m 0.03 Xe-133 0.97 none 0.00 I-135 Xe-135m 0.15 Xe-135 0.85 none 0.00 Xe-133m Xe-133 1.00 none 0.00 none 0.00 Xe-135m Xe-135 1.00 Cs-135 1.00 none 0.00 Xe-135 Cs-135 1.00 none 0.00 none 0.00 Xe-138 Cs-138 1.00 none 0.00 none 0.00 Cs-137 Ba-137m 0.95 none 0.00 none 0.00 Br-83 Kr-83m 1.00 none 0.00 none 0.00 Iodine fractions Aerosol

=

0.0000E+00 Elemental

=

9.7000E-01 Organic

=

3.0000E-02 COMPARTMENT DATA

Compartment number 1: Arbitrary Volume Compartment number 2: Environment Compartment number 3: TSC PATHWAY DATA Pathway number 1: Release Volume to Environment Pathway Filter: Removal Data Time (hr)

Flow Rate Filter Efficiencies (%)

(cfm)

Aerosol Elemental Organic 0.0000E+00 1.0000E+10 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 2: Environment to TSC - Makeup Pathway Filter: Removal Data Time (hr)

Flow Rate (cfm)

Filter Efficiencies (%)

Aerosol Elemental Organic 0.0000E+00 1.2000E+04 0.0000E+00 0.0000E+00 0.0000E+00 5.0000E-01 1.2000E+04 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 3: Environment to TSC - Inleakage Pathway Filter: Removal Data Time (hr)

Flow Rate (cfm)

Filter Efficiencies (%)

Aerosol Elemental Organic 0.0000E+00 1.0000E+03 0.0000E+00 0.0000E+00 0.0000E+00 5.0000E-01 1.0000E+03 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 4: TSC to Environment - Exhaust Pathway Filter: Removal Data Time (hr)

Flow Rate Filter Efficiencies (%)

(cfm)

Aerosol Elemental Organic 0.0000E+00 1.3000E+04 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 LOCATION DATA Location EAB is in compartment 2

Location X/Q Data Time (hr)

X/Q (s

m^-3) 0.0000E+00 1.2400E-04 7.2000E+02 0.0000E+00 Location Breathing Rate Data Time (hr)

Breathing Rate (m'3

sec^-1) 0.0000E+00 3.5000E-04 8.0000E+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.0000E+00 Location LPZ is in compartment 2

Location X/Q Data Time (hr)

X/Q (s

m^-3) 0.0000E+00 2.4200E-05 8.0000E+00 1.6800E-05 2.4000E+01 7.5500E-06 9.6000E+01 2.4000E-06 7.2000E+02 0.0000E+00 Location Breathing Rate Data Time (hr)

Breathing Rate (m^3

sec^-l) 0.0000E+00 3.5000E-04 8.0000E+00 1.8000E-04

D00004O-121, Revision 0 Page 60 of 83 2.4000E+01 7.2000E+02 Location TSC Location X/Q Data 2.3000E-04 0.0000E+00 is in compartment 3

Time (hr)

X/Q (s

m^-3) 0.0000E+00 3.9000E-05 2.0000E+00 3.3000E-05 8.0000E+00 1.6000E-05 2.4000E+01 1.2000E-05 9.6000E+01 8.7000E-06 7.2000E+02 0.0000E+00 Location Breathing Rate Data Time (hr)

Breathing Rate (m^3

sec^-1) 0.0000E+00 3.5000E-04 7.2000E+02 0.0000E+00 Location Occupancy Factor Data Time (hr)

Occupancy Factor 0.0000E+00 1.0000E+00 2.4000E+01 6.0000E-01 9.6000E+01 4.0000E-01 7.2000E+02 0.0000E+00 USER SPECIFIED TIME STEP DATA - SUPPLEMENTAL TIME STEPS Time Time step 0.0000E+00 0.0000E+00

DC0004O-121, Revision 0 Page 61 of 83 RADTRAD Version 3.03 (Spring 2001) run on 12/13/2011 at 7:01:55 Dose, Detailed model and Detailed Inventory Output Detailed model information at time (H) =

0.5000 EAB Doses:

Time (h) =

Delta dose 0.5000 Whole Body (rem) 5.2762E-02 Thyroid 1.6733E+01 TEDE 5.9390E-01 Accumulated dose (rem) 5.2762E-02 1.6733E+01 5.9390E-01 LPZ Doses:

Time (h) =

0.5000 Whole Body Delta dose (rem) 1.0297E-02 Thyroid 3.2656E+00 TEDE 1.1591E-01 Accumulated dose (rem) 1.0297E-02 TSC Doses:

Time (h) =

0.5000 Whole Body Delta dose (rem) 4.7902E-04 Accumulated dose (rem) 4.7902E-04 3.2656E+00 Thyroid 2.8641E+00 2.8641E+00 1.1591E-01 TEDE 9.3101E-02 9.3101E-02 Arbitrary Volume Compartment Nuclide Inventory:

Time (h) =

0.5000 Ci kg Atoms Decay Kr-85m 2.3639E-06 2.8724E-16 2.0351E+09 1.6368E+08 Kr-85 1.0751E-05 2.7401E-11 1.9414E+14 7.1599E+08 Kr-87 1.1759E-06 4.1513E-17 2.8735E+08 9.0025E+07 Kr-88 3.9955E-06 3.1864E-16 2.1805E+09 2.8302E+08 1-131 9.3139E-06 7.5128E-14 3.4537E+l1 6.2087E+08 1-132 7.8115E-06 7.5677E-16 3.4526E+09 5.6149E+08 1-133 1.3704E-05 1.2097E-14 5.4774E+10 9.2030E+08 1-134 1.1730E-06 4.3970E-17 1.9761E+08 9.5815E+07 1-135 6.7586E-06 1.9245E-15 8.5849E+09 4.6213E+08 Re-131m 3.2332E-06 3.8406E-14 1.7655E+11 2.1546E+08 Re-133m 2.6673E-05 5.9498E-14 2.6940E+ll 1.7822E+09 Re-133 4.0881E-04 2.1840E-12 9.8891E+12 2.7260E+10 Re-135m 1.0404E-06 1.1474E-17 5.1186E+07 5.2137E+07 Re-135 1.1935E-05 4.6735E-15 2.0848E+10 8.0017E+08 Re-138 2.0536E-07 2.1357E-18 9.3200E+06 3.1113E+07 Cs-134 2.1654E-07 1.6736E-13 7.5216E+11 1.4422E+07 Cs-136 2.4721E-07 3.3730E-15 1.4936E+10 1.6473E+07 Cs-137 1.2374E-07 1.4226E-12 6.2533E+12 8.2411E+06 Cs-138 2.6020E-07 6.1492E-18 2.6834E+07 1.1825E+07 Rb-88 3.3995E-06 2.8320E-17 1.9380E+08 1.0937E+08 Br-83 2.1523E-07 1.3624E-17 9.8851E+07 1.5426E+07 Br-84 6.4694E-08 9.1906E-19 6.5890E+06 6.0819E+06 Arbitrary Volume Transport Group I nventory:

Time (h) =

0.5000 Atmosphere Sump Noble gases (atoms) 2.0450E+14 0.0000E+00 Elemental I (atoms) 4.0011E+ll 0.0000E+00 Organic I (atoms) 1.2374E+10 0.0000E+00 Aerosols (kg) 1.5934E-12 0.0000E+00

Dose Effective (Ci/cc) 1-131 (Thyroid) 4.1806E-14 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 4.8878E-14 Total I (Ci) 3.8761E-05 Release Volume to Environment Transport Group Inventory:

Pathway Time (h) =

0.5000 Filtered Transported Noble gases (atoms) 0.0000E+00 4.3705E+22 Elemental I (atoms) 0.0000E+00 8.6616E+19 Organic I (atoms) 0.0000E+00 2.6789E+18 Aerosols (kg) 0.0000E+00 3.5276E-04 Detailed model information at time (H) =

2.0000 EAB Doses:

Time (h) =

2.0000 Whole Body Thyroid Delta dose (rem) 3.7969E-04 1.3850E-01 TIDE 4.8693E-03 Accumulated dose (rem) 5.3141E-02 1.6871E+01 LPZ Doses:

Time (h) =

2.0000 Whole Body Thyroid Delta dose (rem) 7.4101E-05 2.7029E-02 Accumulated dose (rem) 1.0371E-02 3.2927E+00 TSC Doses:

Time (h) =

2.0000 Whole Body Thyroid Delta dose (rem) 3.7930E-04 2.4092E+00 Accumulated dose (rem) 8.5832E-04 5.2732E+00 5.9877E-01 TEDE 9.5030E-04 1.1686E-01 TEDE 7.8263E-02 1.7136E-01 Arbitrary Volume Compartment Nuclide Inventory:

Time (h) =

2.0000 Ci kg Atoms Decay Kr-85m 5.0375E-09 6.1212E-19 4.3368E+06 1.6462E+08 Kr-85 2.8894E-08 7.3646E-14 5.2177E+ll 7.2176E+08 Kr-87 1.3953E-09 4.9259E-20 3.4097E+05 9.0456E+07 Kr-88 7.4465E-09 5.9386E-19 4.0640E+06 2.8481E+08 1-131 2.5866E-08 2.0864E-16 9.5912E+08 6.2605E+08 1-132 1.3879E-08 1.3445E-18 6.1341E+06 5.6499E+08 1-133 3.6396E-08 3.2129E-17 1.4548E+08 9.2776E+08 1-134 1.0004E-09 3.7499E-20 1.6853E+05 9.6198E+07 1-135 1.6124E-08 4.5914E-18 2.0481E+07 4.6562E+08 Xe-131m 8.6591E-09 1.0286E-16 4.7284E+08 2.1719E+08 Xe-133m 7.0304E-08 1.5682E-16 7.1009E+08 1.7964E+09 Xe-133 1.0906E-06 5.8263E-15 2.6381E+10 2.7479E+10 Xe-135m 2.6880E-09 2.9646E-20 1.3225E+05 5.2624E+07 Xe-135 3.0356E-08 1.1887E-17 5.3026E+07 8.0640E+08 Cs-134 6.5778E-10 5.0840E-16 2.2848E+09 1.4553E+07 Cs-136 7.4850E-10 1.0213E-17 4.5222E+07 1.6623E+07 Cs-137 3.7590E-10 4.3216E-15 1.8997E+10 8.3162E+06 Cs-138 1.8626E-10 4.4019E-21 1.9209E+04 1.1917E+07 Rb-88 1.0509E-08 8.7546E-20 5.9911E+05 1.1146E+08 Br-83 3.8896E-10 2.4621E-20 1.7864E+05 1.5523E+07 Arbitrary Volume Transport Group Inventory:

Time (h) =

2.0000 Atmosphere Sump Noble gases (atoms) 5.4940E+11 0.0000E+00 Elemental I (atoms) 1.0976E+09 0.0000E+00 Organic I (atoms) 3.3947E+07 0.0000E+00 Aerosols (kg) 4.8403E-15 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 1.1468E-16 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 1.3227E-16 Total I (Ci) 9.3265E-08 Release Volume to Environment Transport Group Inventory:

Time (h) =

2.0000 Pathway Filtered Transported Noble gases (atoms) 0.0000E+00 4.4361E+22 Elemental I (atoms) 0.0000E+00 8.7913E+19 Organic I (atoms) 0.0000E+00 2.7190E+18

Aerosols (kg) 0.0000E+00 3.5823E-04 Detailed model information at time (H) =

8.0000 EAB Doses:

Time (h) =

Delta dose 8.0000 Whole Body Thyroid (rem) 1.5840E-03 6.6829E-01 TEDE 2.3182E-02 Accumulated dose (rem) 5.4725E-02 1.7540E+01 6.2195E-01 LPZ Doses:

Time (h) =

8.0000 Whole Body Thyroid Delta dose (rem) 3.0913E-04 1.3042E-01 TEDE 4.5242E-03 Accumulated dose (rem) 1.0680E-02 3.4231E+00 TSC Doses:

1.2138E-01 Time (h) =

8.0000 Whole Body Thyroid Delta dose (rem) 2.3301E-05 1.8556E-01 TEDE 6.0199E-03 Accumulated dose (rem) 8.8162E-04 5.4588E+00 1.7738E-01 Arbitrary Volume Compartment Nuclide Inventory:

Time (h) =

8.0000 Ci kg Atoms Decay Kr-85m 3.9771E-09 4.8327E-19 3.4239E+06 1.7006E+08 Kr-85 5.7717E-08 1.4711E-13 1.0423E+12 7.6789E+08 Kr-87 1.0589E-10 3.7383E-21 2.5877E+04 9.1112E+07 Kr-88 3.4395E-09 2.7430E-19 1.8771E+06 2.9105E+08 1-131 3.1795E-08 2.5647E-16 1.1790E+09 6.5173E+08 1-132 2.8579E-09 2.7687E-19 1.2631E+06 5.7143E+08 1-133 3.7430E-08 3.3042E-17 1.4961E+08 9.6088E+08 1-135 1.0795E-08 3.0739E-18 1.3712E+07 4.7763E+08 Re-131m 1.7054E-08 2.0258E-16 9.3125E+08 2.3092E+08 Re-133m 1.2989E-07 2.8974E-16 1.3119E+09 1.9043E+09 Re-133 2.1141E-06 1.1294E-14 5.1139E+10 2.9194E+10 Xe-135m 2.6080E-09 2.8763E-20 1.2831E+05 5.5379E+07 Be-135 4.6294E-08 1.8128E-17 8.0867E+07 8.4905E+08 Cs-134 8.2399E-10 6.3686E-16 2.8621E+09 1.5212E+07 Cs-136 9.2552E-10 1.2628E-17 5.5917E+07 1.7368E+07 Cs-137 4.7098E-10 5.4147E-15 2.3802E+10 8.6926E+06 Rb-88 3.3947E-09 2.8280E-20 1.9353E+05 1.1666E+08 Br-83 8.5739E-11 5.4273E-21 3.9378E+04 1.5708E+07 Arbitrary Volume Transport Group Inventory:

Time (h) =

8.0000 Atmosphere Sump Noble gases (atoms) 1.0957E+12 0.0000E+00 Elemental I (atoms) 1.3033E+09 0.0000E+00 Organic I (atoms) 4.0308E+07 0.0000E+00 Aerosols (kg) 6.0643E-15 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 1.3545E-16 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 1.5115E-16 Total I (Ci) 8.2889E-08 Release Volume to Environment Transport Group Inventory:

Time (h) =

8.0000 Pathway Filtered Transported Noble gases (atoms)

Elemental I (atoms) 0.0000E+00 0.0000E+00 3.3335E+24 1.7744E+21 Organic I (atoms)

Aerosols (kg) 0.0000E+00 0.0000E+00 5.4880E+19 7.7060E-03 Detailed model information at time (H) =

EAR Doses:

18.0000 Time (h) = 18.0000 Whole Body Thyroid TEDE Delta dose (rem) 7.8228E-04 1.8447E-01 6.7324E-03 Accumulated dose (rem) 5.5508E-02 1.7724E+01 6.2868E-01 LPZ Doses:

Time (h) =

18.0000 Whole Body Thyroid TEDE

Delta dose (rem) 1.0599E-04 Accumulated dose (rem) 1.0786E-02 TSC Doses:

2.4993E-02 3.4481E+00 9.1213E-04 1.2229E-01 Time (h) = 18.0000 Whole Body Delta dose (rem) 6.0277E-06 Thyroid 5.2697E-02 TEDE 1.7059E-03 Accumulated dose (rem) 8.8764E-04 5.5115E+00 1.7909E-01 Arbitrary Volume Compartment Nuclide Inventory:

Time (h) =

18.0000 Ci kg Atoms Decay Kr-85m 4.2334E-10 5.1441E-20 3.6445E+05 1.7140E+08 Kr-85 2.8863E-08 7.3566E-14 5.2121E+11 8.0633E+08 Kr-88 1.4983E-10 1.1949E-20 8.1769E+04 2.9191E+08 1-131 1.0610E-08 8.5580E-17 3.9342E+08 6.6612E+08 1-132 4.8547E-11 4.7032E-21 2.1457E+04 5.7185E+08 1-133 9.2777E-09 8.1899E-18 3.7083E+07 9.7554E+08 1-135 1.3084E-09 3.7258E-19 1.6620E+06 4.8072E+08 Re-131m 8.3291E-09 9.8937E-17 4.5482E+08 2.4215E+08 Re-133m 5.7013E-08 1.2718E-16 5.7585E+08 1.9855E+09 Xe-133 1.0050E-06 5.3693E-15 2.4312E+10 3.0567E+10 Xe-135m 5.9595E-10 6.5727E-21 2.9320E+04 5.6163E+07 Re-135 1.3162E-08 5.1541E-18 2.2992E+07 8.7280E+08 Cs-134 2.8365E-10 2.1924E-16 9.8528E+08 1.5590E+07 Cs-136 3.1178E-10 4.2540E-18 1.8837E+07 1.7787E+07 Cs-137 1.6219E-10 1.8647E-15 8.1966E+09 8.9087E+06 Rb-88 4.0804E-10 3.3992E-21 2.3262E+04 1.1709E+08 Arbitrary Time (h) =

Noble gases Volume Transport Group Inventory:

18.0000 Atmosphere Sump (atoms) 5.4657E+ll 0.0000E+00 Elemental I (atoms) 4.1922E+08 0.0000E+00 Organic I (atoms) 1.2966E+07 0.0000E+00 Aerosols (kg) 2.0882E-15 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 4.3056E-17 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 4.6617E-17 Total I (Ci) 2.1244E-08 Release Volume to Environment Transport Group Inventory:

Pathway Time (h) = 18.0000 Filtered Transported Noble gases (atoms) 0.0000E+00 3.3386E+24 Elemental I (atoms) 0.0000E+00 1.7747E+21 Organic I (atoms) 0.0000E+00 5.4888E+19 Aerosols (kg) 0.0000E+00 7.7070E-03 Detailed model information at time (H) 24.0000 EAB Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.1435E-12 2.9442E-10 1.0640E-11 Accumulated dose (rem) 5.5508E-02 1.7724E+01 6.2868E-01 LPZ Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.5493E-13 3.9889E-11 1.4415E-12 Accumulated dose (rem) 1.0786E-02 3.4481E+00 1.2229E-01 TSC Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.4740E-07 2.3204E-03 7.5092E-05 Accumulated dose (rem) 8.8789E-04 5.5138E+00 1.7916E-01 Arbitrary Volume Compartment Nuclide Inventory:

Time (h) = 24.0000 Ci kg Atoms Decay Arbitrary Volume Transport Group Inventory:

Time (h) = 24.0000 Atmosphere Sump

Noble gases (atoms) 0.0000E+00 0.0000E+00 Elemental I (atoms) 0.0000E+00 0.0000E+00 Organic I (atoms) 0.0000E+00 0.0000E+00 Aerosols (kg) 0.0000E+00 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 0.0000E+00 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 0.0000E+00 Total I (Ci) 0.0000E+00 Release Volume to Environment Transport Group Inventory:

Pathway Time (h) = 24.0000 Filtered Transported Noble gases (atoms) 0.0000E+00 3.3386E+24 Elemental I (atoms) 0.0000E+00 1.7747E+21 Organic I (atoms) 0.0000E+00 5.4888E+19 Aerosols (kg) 0.0000E+00 7.7070E-03 Detailed model information at time (H) =

96.0000 EAB Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 5.5508E-02 1.7724E+01 6.2868E-01 LPZ Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 1.0786E-02 3.4481E+00 1.2229E-01 TSC Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.0311E-17 2.0223E-13 6.5458E-15 Accumulated dose (rem) 8.8789E-04 5.5138E+00 1.7916E-01 Arbitrary Volume Compartment Nuclide Inventory:

Time (h) = 96.0000 Cl kg Atoms Decay Arbitrary Volume Transport Group Inventory:

Time (h) = 96.0000 Atmosphere Sump Noble gases (atoms) 0.0000E+00 0.0000E+00 Elemental I (atoms) 0.0000E+00 0.0000E+00 Organic I (atoms) 0.0000E+00 0.0000E+00 Aerosols (kg) 0.0000E+00 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 0.0000E+00 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 0.0000E+00 Total I (Ci) 0.0000E+00 Release Volume to Environment Transport Group Inventory:

Pathway Time (h) = 96.0000 Filtered Transported Noble gases (atoms) 0.0000E+00 3.3386E+24 Elemental I (atoms) 0.0000E+00 1.7747E+21 Organic I (atoms) 0.0000E+00 5.4888E+19 Aerosols (kg) 0.0000E+00 7.7070E-03 Detailed model information at time (H) = 720.0000 EAB Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 5.5508E-02 1.7724E+01 6.2868E-01 LPZ Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 1.0786E-02 3.4481E+00 1.2229E-01

DC00040-121, Revision 0 Page 66 of 83 TSC Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.1656-135 1.4036-131 4.6021-133 Accumulated dose (rem) 8.8789E-04 5.5138E+00 1.7916E-01 Arbitrary Volume Compartment Nuclide Inventory:

Time (h) = 720.0000 Ci kg Atoms Decay Arbitrary Volume Transport Group Inventory:

Time (h) = 720.0000 Atmosphere Sump Noble gases (atoms) 0.0000E+00 0.0000E+00 Elemental I (atoms) 0.0000E+00 0.0000E+00 Organic I (atoms) 0.0000E+00 0.0000E+00 Aerosols (kg) 0.0000E+00 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 0.0000E+00 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 0.0000E+00 Total I (Ci) 0.0000E+00 Release Volume to Environment Transport Group Inventory:

Time (h) = 720.0000 Pathway Filtered Transported Noble gases (atoms) 0.0000E+00 3.3386E+24 Elemental I (atoms) 0.0000E+00 1.7747E+21 Organic I (atoms) 0.0000E+00 5.4888E+19 Aerosols (kg) 0.0000E+00 7.7070E-03 837 1-131 Summary Time (hr)

Arbitrary Volume 1-131 (Curies)

Environment 1-131 (Curies)

TSC 1-131 (Curies) 0.000 9.3307E-06 3.1101E-01 7.4341E-05 0.401 9.3173E-06 2.2436E+02 2.7668E-02 0.500 9.3139E-06 2.7962E+02 3.0093E-02 0.800 2.5978E-08 2.8009E+02 9.7735E-03 1.100 2.5950E-08 2.8055E+02 3.2193E-03 1.400 2.5922E-08 2.8102E+02 1.1053E-03 1.700 2.5894E-08 2.8149E+02 4.2330E-04 2.000 2.5866E-08 2.8195E+02 2.0326E-04 2.300 3.2453E-08 2.8254E+02 1.3640E-04 2.600 3.2418E-08 2.8312E+02 1.1476E-04 2.900 3.2383E-08 2.8370E+02 1.0771E-04 3.200 3.2348E-08 2.8429E+02 1.0535E-04 3.500 3.2313E-08 2.8487E+02 1.0452E-04 3.800 3.2279E-08 2.8545E+02 1.0417E-04 4.100 3.2244E-08 2.8603E+02 1.0399E-04 4.400 3.2209E-08 2.8661E+02 1.0385E-04 4.700 3.2174E-08 2.8719E+02 1.0373E-04 5.000 3.2140E-08 2.8777E+02 1.0362E-04 5.300 3.2105E-08 2.8835E+02 1.0350E-04 5.600 3.2071E-08 2.8892E+02 1.0339E-04 5.900 3.2036E-08 2.8950E+02 1.0328E-04 6.200 3.2001E-08 2.9008E+02 1.0317E-04 6.500 3.1967E-08 2.9065E+02 1.0306E-04 6.800 3.1933E-08 2.9123E+02 1.0295E-04 7.100 3.1898E-08 2.9180E+02 1.0284E-04 7.400 3.1864E-08 2.9238E+02 1.0272E-04 7.700 3.1830E-08 2.9295E+02 1.0261E-04 8.000 3.1795E-08 2.9352E+02 1.0250E-04 8.300 1.0986E-08 2.9372E+02 4.4689E-05 8.600 1.0974E-08 2.9392E+02 2.6029E-05 8.900 1.0962E-08 2.9411E+02 1.9998E-05 9.200 1.0951E-08 2.9431E+02 1.8040E-05 9.500 1.0939E-08 2.9451E+02 1.7396E-05 9.800 1.0927E-08 2.9471E+02 1.7176E-05 10.100 1.0915E-08 2.9490E+02 1.7092E-05 10.400 1.0903E-08 2.9510E+02 1.7053E-05 18.000 1.0610E-08 3.0000E+02 1.6584E-05

t0-3LL86'9 TO+3TL89'T ZO-3T4T£'S 0'0 (etas)

(Max)

(max)

(iq) 3Q3S PTOxdgy dpog aTogM amxy SY3 sesoa xnog-omy gsxoM TO-39T6L'T 00+38£T5'S TO-36ZZZ't 00+3TBD4'E 1O-38982'9 TO+34ZLL'T 000.OZL 1O-39T6L'T 00+38ETS'S TO-36ZZZ't 00+3T844'E TO-38982'9 TO+34ZLL'T 000'96 t0-39T6L'T 00+38ET5'9 TO-36ZZZ'T 00+3T844'E TO-38982'9 TO+34ZLL'T 000'42 TO-a606L'T 00+3Stt9'S TO-36ZZZ't 00+3T844'E 1O-38982'9 TO+34ZLL'T 000'8T TO-a96LL't 00+3L9L4'S TO-3T9TZ'T OO+3E6Z4'E TO-3E9EZ'9 TO+3S8SL'T 004'OT TO-3Z6LL'T 00+3ZSL4'S TO-38STZ'T 00+3S8Zb'E TO-3Z4EZ'9 TO+HO89L't OOT'OT TO-3L8LL'T 00+38EL4'S T0-3SSTZ'T 00+3LLZ4'E TO-3TZEZ'9 TO+34LSL'T 008'6 TO-3Z8LL't 00+34ZL4'S TO-3ZSTZ'T 00+30LZ4'E TO-3TOEZ'9 TO+389SL'T 009'6 TO-38LLL't 00+360L4'S TO-30StZ'T 00+32924'£ TO-30822'9 TO+3E9SL'T OOZ'6 TO-3ZLLL'T 00+3£694'5 1O-3LPTZ'T 00+36SZ4'E TO-36SZZ'9 TO+3LSSL't 006'8 TO-399LL'T 00+34L94'9 1O-344TZ't 00+394Z4'E 10-3LEZZ'9 TO+3TSSL'T 009'8 T0-3LSLL'T OO+39494'5 TO-3t4TZ'T 00+36£Z4'£ TO-39TZZ'9 TO+3S4SL't OOE'8 T0-38ELL'T 00+38854'5 TO-38ETZ'T 00+at£Z4'£ TO-3S6TZ'9 TO+3O49L'T 000'8 TO-3OTLL't 00+3ZOS4'S TO-39TTZ'T 00+3L9T4'E t0-34802'9 TO+3LOSL'T OOL'L TO-3Z89L't 00+3ST44'S TO-3S60Z'T 00+340i4'E TO-3ZL6T'9 TO+3SLPL'T OO4'L T0-3459L'T 00+382£4'9 TO-3£LOZ'T 00+30404'£ TO-3098t'9 TO+3Z44L't OOC'L T0-39Z9L't 00+3t4Z4'S TO-3TSOZ'T 00+39L6£'£ TO-3L4LT'9 TO+36OPL't 008'9 TO-3869L'T 00+3E9T4'S TO-36ZOZ'T 00+3ZT6£'E TO-34E9T'9 TO+39LEL'T 005'9 TO-3699L'T 00+39904'5 TO-3LOOZ'T 00+3848£'£ t0-3TZST'9 TO+3£4EL'T OOZ'9 TO-3t4SL'T 00+a8L6E'S TO-3486t'T 00+3EBLE'E 1O-3LO4T'9 TO+30TEL'T 006'9 TO-3ZTSL'T 00+a068E'S TO-3Z96t'T 00+36TLE'E TO-3E6Zt'9 TO+3LLZL'T 009'9 TO-3E84L't 00+3T08£'S TO-3046T'T 00+34S9E'E TO-38LTt'9 TO+344ZL'T 00£'5 TO-3SS4L't 00+3ZTL£'S TO-3LT6T'1 00+3689£'£ TO-3E9Ot'9 TO+3TTZL'T 000'S TO-39Z4L't 00+3EZ9£'S TO-3468T'T 00+3EZSE'£ t0-3L460'9 t0+3LLTL'T OOL'4 T0-3L6£L'T 00+34ESE'9 TO-3ZLBT't 00+3854£'£ TO-30£80'9 TO+344tL'T 004'4 TO-389£L'T 00+3444£'5 TO-3648t'T 00+3Z6EE'E TO-34TL0'9 TO+30TTL'T OOT'4 TO-38££L'T 00+399E£'S TO-39Z8T'T 00+392££'£ TO-39650'9 TO+39LOL'T 008'E TO-360£L'T 00+349ZE'S TO-3E08T'T 00+309Z£'£ TO-38L'0'9 1O+3Z40L'T 009'£ TO-308ZL'T 00+3ELtE'S T0-3O8LT'T 00+346TE'E T0-365£0'9 TO+3800L'T OOZ'£ TO-30SZL't 00+3T9OE'9 10-39SLt't 00+3LZTE'E TO-a6EZO'9 TO+34L69't 006'2 TO-38TZL'T 00+3486Z'S TO-3EELT't 00+3190£'£ TO-36TTO'9 1O+3O469't 009'2 T0-3E8tL'T 00+39L8Z'S TO-360LT't 00+34662'£ TO-38666'5 1O+a9069*T OOE'Z TO-39£TL'T 00+32ELZ'S t0-3989T't 00+3LZ6Z'£ TO-3LL86'9 TO+3TL89'T 000'2 TO-3Z90L'T 00+3EL4Z'S TO-3L99T'T 00+3£L8Z'£ TO-3T8L6'9 TO+34489'T OOL'T T0-30S89'T 00+30S8T'S TO-38491'T 00+36TSZ'E TO-34896'5 TO+39T89'T OO4'T TO-3TBZ9'T 00+3L600'S TO-36Z9t'T 00+3S9LZ'E TO-3L8S6'S TO+368L9'T OOT't TO-30LS4'T 00+36284'4 TO-30T9T't 00+3tTLZ'£ t0-38846'5 TO+3T9L9'T 008'0 ZO-3TOTE'6 00+3T498'Z TO-3T69T't 00+39S9Z'£ t0-306£6'5 TO+3EEL9'T 00S'0 ZO-3T499'9 00+3Z610'Z ZO-3980£'6 00+34tZ9'Z TO-3L69L'4 TO+3ZE4£'T T04'O 00+30000'0 00+30000'0 00+30000'0 00+30000'0 00+30000'0 00+30000'0 000'0 (Max)

(max)

(xg) aa3S PTOxAtj 3Q3s PTOlAgl 3Q3S PToxdgj awry JSS Zd'I ava Ax¢mom$ asoa 6eT3aTmmm:)

00+30000'0 ZO+30000'£ 00+30000'0 000'OZL E£T-Z6E8'Z ZO+30O00'E 00+30000'0 000'96 9T-32£94'2 ZO+ZOOOO*£ 00+30000'0 000'42

£8 JO L9 32ud 0 UOisinag 'I Z I -017000DU

DO00040-121, Revision 0 Page 68 of 83 Attachment No. 4 RADTRAD Concurrent Spike

D000040-121, Revision 0 Page 69 of 83 RADTRAD Version 3.03 (Spring 2001) run on 12/13/2011 at 7:04:13 File information Plant file

= C:\\radtrad3.03\\2011 SGTR Inventory file

= c:\\radtrad3.03\\2011 sgtr Release file

= c:\\radtrad3.03\\2011 sgtr Dose Conversion file = c:\\radtrad3.03\\2011 sgtr TSC\\Att 4_VCS SGTR tsc\\sgtr concurrent tsc\\sgtr concurrent tsc\\sgtr.inp concurrent tsc.nif tsc.rft I Spike TSC.psf Radtrad 3.03 4/15/2001 SGTR Nuclide Inventory File:

c:\\radtrad3.03\\2011 sgtr tsc\\sgtr concurrent tsc.nif Plant Power Level:

1.0108E+00 Compartments:

3 Compartment 1:

Arbitrary Volume 3

1.0000E+04 0

0 0

Compartment 2:

Environment 2

0.0000E+00 0

0 0

Compartment 3:

TSC 1

2.0700E+05 0

0 0

Pathways:

4 Pathway 1:

Release Volume to Environment 1

2 2

Pathway 2:

Environment to TSC - Makeup 2

3

2 Pathway 3:

Environment to TSC - Inleakage 2

3 2

Pathway 4:

Control Room to Environment - Exhaust 3

2 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1

1.0000E+00 c:\\radtrad3.03\\2011 sgtr tsc\\sgtr.inp c:\\radtrad3.03\\2011 sgtr tsc\\sgtr concurrent tsc.rft 0.0000E+00 1

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

0 0.0000E+00 0

0 0

0 Compartments:

3 Compartment 1:

1 1

0 0

0 Compartment 2:

0 1

0 0

0 Compartment 3:

0 1

0 0

0 Pathways:

4 Pathway 1:

0 0

0 1

2 0.0000E+00 1.0000E+10 0.0000E+00 0.0000E+00 0.0000E+00

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

0 0

0 Pathway 2:

0 0

0 1

3 0.0000E+00 1.2000E+04 0.0000E+00 0.0000E+00 0.0000E+00 5.0000E-01 1.2000E+04 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 Pathway 3:

0 0

0 1

3 0.0000E+00 1.0000E+03 0.0000E+00 0.0000E+00 0.0000E+00 5.0000E-01 1.0000E+03 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 Pathway 4:

0 0

0 1

2 0.0000E+00 1.3000E+04 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 Dose Locations:

3 Location 1:

EAR 2

1 2

0.0000E+00 1.2400E-04 7.2000E+02 0.0000E+00 1

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

Location 2:

LPZ 2

1 5

0.0000E+00 2.4200E-05 8.0000E+00 1.6800E-05 2.4000E+01 7.5500E-06 9.6000E+01 2.4000E-06 7.2000E+02 0.0000E+00 1

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

Location 3:

TSC 3

0 1

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

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

1 6

0.0000E+00 3.9000E-05 2.0000E+00 3.3000E-05 8.0000E+00 1.6000E-05 2.4000E+01 1.2000E-05 9.6000E+01 8.7000E-06 7.2000E+02 0.0000E+00 Simulation Parameters:

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

C:\\radtrad3.o0 1

1 1

0 1

End of Scenario File

D000040-121, Revision 0 Page 73 of 83 RADTRAD Version 3.03 (Spring 2001) run on 12/13/2011 at 7:04:13 Plant Description Number of Nuclides = 22 Inventory Power =

1.0000E+00 NWth Plant Power Level =

1.0108E+00 MWth Number of compartments

=

3 Compartment information Compartment number 1 (Source term fraction =

1.0000E+00 Name: Arbitrary Volume Compartment.volume =

1.0000E+04 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 1 Exit Pathway Number 1: Release Volume to Environment Compartment number 2 Name: Environment Compartment type is Environment Pathways Inlet Inlet Exit Exit into and out of compartment 2 Pathway Number 1:

Release Volume Pathway Number 4:

Control Room to Pathway Number 2:

Environment to Pathway Number 3:

Environment to to Environment Environment - Exhaust TSC - Makeup TSC - Inleakage t

b 3

Compartmen num er Name: TSC Compartment volume =

2.0700E+05 (Cubic feet)

Compartment type is Control Room Pathways into and out of compartment 3 Inlet Pathway Number 2:

Environment to TSC - Makeup Inlet Pathway Number 3:

Environment to TSC - Inleakage Exit Pathway Number 4:

Control Room to Environment - Exhaust Total number of pathways =

4

DC00040-121, Revision 0 Page 74 of 83 RADTRAD Version 3.03 (Spring 2001) run on 12/13/2011 at 7:04:13 Scenario Description Radioactive Decay is enabled Calculation of Daughters is enabled Release Fractions and Timings GAP EARLY IN-VESSEL LATE RELEASE RELEASE MASS 0.500000 hr 1.5000 hrs 6.0000 hrs (gm)

NOBLES IODINE CESIUM TELLURIUM STRONTIUM BARIUM RUTHENIUM CERIUM LANTHANUM 8.8800E-01 7.1600E-03 2.8600E-02 7.0900E-01 2.4600E-03 3.3500E-02 8.0900E-01 2.1600E-02 7.0300E-02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 9.336E-01 9.757E-04 4.832E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Inventory Power =

1.

MWt Nuclide Group Specific half Whole Body Inhaled Inhaled Name Inventory life DCF Thyroid Effective (Ci/MWt)

(s)

(Sv-m3/Bq-s)

(Sv/Bq)

Kr-85m 1

8.600E+01 1.613E+04 7.480E-15 0.000E+00 0.000E+00 Kr-85 1

3.620E+02 3.383E+08 1.190E-16 0.000E+00 0.000E+00 Kr-87 1

5.200E+01 4.578E+03 4.120E-14 0.000E+00 0.000E+00 Kr-88 1

1.520E+02 1.022E+04 1.020E-13 0.000E+00 0.000E+00 I-131 2

1.250E+02 6.947E+05 1.820E-14 2.920E-07 8.890E-09 1-132 2

3.960E+02 8.280E+03 1.120E-13 1.740E-09 1.030E-10 I-133 2

2.180E+02 7.488E+04 2.940E-14 4.860E-08 1.580E-09 I-134 2

1.610E+02 3.156E+03 1.300E-13 2.880E-10 3.550E-11 I-135 2

1.780E+02 2.380E+04 8.294E-14 8.460E-09 3.320E-10 Xe-131m 1

1.090E+02 1.023E+06 3.890E-16 0.000E+00 0.000E+00 Xe-133m 1

9.040E+02 1.892E+05 1.370E-15 0.000E+00 0.000E+00 Xe-133 1

1.380E+04 4.532E+05 1.560E-15 0.000E+00 0.000E+00 Xe-135m 1

2.500E+01 9.217E+02 2.040E-14 0.000E+00 0.000E+00 Xe-135 1

4.090E+02 3.272E+04 1.190E-14 0.000E+00 0.000E+00 Xe-138 1

3.000E+01 8.502E+02 5.770E-14 0.000E+00 0.000E+00 Cs-134 3

9.000E+00 6.507E+07 7.570E-14 1.110E-08 1.250E-08 Cs-136 3

9.000E+00 1.132E+06 1.060E-13 1.730E-09 1.980E-09 Cs-137 3

4.000E+00 9.467E+08 2.725E-14 7.930E-09 8.630E-09 Cs-138 3

2.000E+00 1.932E+03 1.210E-13 3.570E-12 2.740E-11 Rb-88 3

6.000E+00 1.068E+03 3.360E-14 1.370E-12 2.260E-11 Br-83 2

1.000E-01 8.604E+03 3.820E-16 1.140E-12 2.410E-11 Br-84 2

1.000E-01 1.908E+03 9.410E-14 3.120E-12 2.610E-11 Nuclide Daughter Fraction Daughter Fraction Daughter Fraction Kr-85m Kr-85 0.21 none 0.00 none 0.00 Kr-87 Rb-87 1.00 none 0.00 none 0.00 Kr-88 Rb-88 1.00 none 0.00 none 0.00 1-131 Xe-131m 0.01 none 0.00 none 0.00 I-133 Xe-133m 0.03 Xe-133 0.97 none 0.00 1-135 Xe-135m 0.15 Xe-135 0.85 none 0.00 Xe-133m Xe-133 1.00 none 0.00 none 0.00 Xe-135m Xe-135 1.00 Cs-135 1.00 none 0.00 Xe-135 Cs-135 1.00 none 0.00 none 0.00 Xe-138 Cs-138 1.00 none 0.00 none 0.00 Cs-137 Ba-137m 0.95 none 0.00 none 0.00 Br-83 Kr-83m 1.00 none 0.00 none 0.00 Iodine fractions Aerosol

=

0.0000E+00 Elemental

=

9.7000E-01 Organic

=

3.0000E-02 COMPARTMENT DATA

Compartment number 1: Arbitrary Volume Compartment number 2: Environment Compartment number 3:

TSC PATHWAY DATA Pathway number 1: Release Volume to Environment Pathway Filter: Removal Data Time (hr)

Flow Rate Filter Efficiencies (B)

(cfm)

Aerosol Elemental Organic 0.0000E+00 1.0000E+10 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 2: Environment to TSC - Makeup Pathway Filter: Removal Data Time (hr)

Flow Rate (cfm)

Filter Efficiencies (8)

Aerosol Elemental Organic 0.0000E+00 1.2000E+04 0.0000E+00 0.0000E+00 0.0000E+00 5.0000E-01 1.2000E+04 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 3: Environment to TSC - Inleakage Pathway Filter: Removal Data Time (hr)

Flow Rate (cfm)

Filter Efficiencies (%)

Aerosol Elemental Organic 0.0000E+00 1.0000E+03 0.0000E+00 0.0000E+00 0.0000E+00 5.0000E-01 1.0000E+03 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 4: Control Room to Environment - Exhaust Pathway Filter: Removal Data Time (hr)

Flow Rate Filter Efficiencies (%)

(cfm)

Aerosol Elemental Organic 0.0000E+00 1.3000E+04 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 LOCATION DATA Location EAB is in compartment 2

Location X/Q Data Time (hr)

X/Q (s

m^-3) 0.0000E+00 1.2400E-04 7.2000E+02 0.0000E+00 Location Breathing Rate Data Time (hr)

Breathing Rate (m^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 LPZ is in compartment 2

Location X/Q Data Time (hr)

X/Q (s

m^-3) 0.0000E+00 2.4200E-05 8.0000E+00 1.6800E-05 2.4000E+01 7.5500E-06 9.6000E+01 2.4000E-06 7.2000E+02 0.0000E+00 Location Breathing Rate Data Time (hr)

Breathing Rate (m^3

sec^-1) 0.0000E+00 3.5000E-04 8.0000E+00 1.8000E-04

2.4000E+01 2.3000E-04 7.2000E+02 0.0000E+00 Location TSC is in compartment 3

Location %/Q Data Time (hr)

X/Q (s

m^-3) 0.0000E+00 3.9000E-05 2.0000E+00 3.3000E-05 8.0000E+00 1.6000E-05 2.4000E+01 1.2000E-05 9.6000E+01 8.7000E-06 7.2000E+02 0.0000E+00 Location Breathing Rate Data Time (hr)

Breathing Rate (m^3

sec^-1) 0.0000E+00 3.5000E-04 7.2000E+02 0.0000E+00 Location Occupancy Factor Data Time (hr)

Occupancy Factor 0.0000E+00 1.0000E+00 2.4000E+01 6.0000E-01 9.6000E+01 4.0000E-01 7.2000E+02 0.0000E+00 USER SPECIFIED TIME STEP DATA - SUPPLEMENTAL TIME STEPS Time Time step 0.0000E+00 0.0000E+00

DC0004O-121, Revision 0 Page 77 of 83 RADTRAD Version 3.03 (Spring 2001) run on 12/13/2011 at 7:04:13 Dose, Detailed model and Detailed Inventory Output Detailed model information at time (H) =

0.5000 EAB Doses:

Time (h) =

0.5000 Delta dose (rem)

Whole Body 4.8110E-02 Thyroid 5.6770E+00 TEDE 2.4877E-01 Accumulated dose (rem)

LPZ Doses:

4.8110E-02 5.6770E+00 2.4877E-01 Time (h) =

0.5000 Delta dose (rem)

Whole Body 9.3892E-03 Thyroid 1.1079E+00 TEDE 4.8550E-02 Accumulated dose (rem)

TSC Doses:

Time (h) =

0.5000 Delta dose (rem)

Accumulated dose (rem) 9.3892E-03 Whole Body 4.3553E-04 4.3553E-04 1.1079E+00 Thyroid 9.7140E-01 9.7140E-01 4.8550E-02 TEDE 3.4773E-02 3.4773E-02 Arbitrary Volume Compartment Nuclide Inventory:

Time (h) =

0.5000 Ci kg Atoms Decay Kr-85m 2.3815E-06 2.8939E-16 2.0503E+09 1.6491E+08 Kr-85 1.0831E-05 2.7606E-11 1.9559E+14 7.2134E+08 Kr-87 1.1847E-06 4.1824E-17 2.8950E+08 9.0698E+07 Kr-88 4.0253E-06 3.2102E-16 2.1968E+09 2.8513E+08 1-131 2.9807E-06 2.4043E-14 1.1053E+11 1.9869E+08 1-132 8.1366E-06 7.8827E-16 3.5963E+09 5.8486E+08 1-133 5.1217E-06 4.5212E-15 2.0472E+10 3.4396E+08 1-134 2.5902E-06 9.7094E-17 4.3635E+08 2.1158E+08 1-135 4.0350E-06 1.1490E-15 5.1253E+09 2.7590E+08 Re-131m 3.2573E-06 3.8692E-14 1.7787E+ll 2.1707E+08 Re-133m 2.6871E-05 5.9940E-14 2.7140E+11 1.7955E+09 Xe-133 4.1185E-04 2.2003E-12 9.9626E+12 2.7463E+10 Xe-135m 8.0699E-07 8.9003E-18 3.9703E+07 4.6907E+07 Re-135 1.1965E-05 4.6853E-15 2.0900E+10 8.0482E+08 Re-138 2.0690E-07 2.1517E-18 9.3897E+06 3.1346E+07 Cs-134 2.4532E-07 1.8960E-13 8.5211E+11 1.6338E+07 Cs-136 2.4505E-07 3.3435E-15 1.4805E+10 1.6329E+07 Cs-137 1.0903E-07 1.2535E-12 5.5100E+12 7.2615E+06 Cs-138 2.3312E-07 5.5091E-18 2.4041E+07 1.0420E+07 Rb-88 3.1135E-06 2.5937E-17 1.7750E+08 9.6365E+07 Br-83 2.0664E-09 1.3080E-19 9.4905E+05 1.4810E+05 Br-84 1.2422E-09 1.7647E-20 1.2652E+05 1.1678E+05 Arbitrary Volume Transport Group Inventory:

Time (h) =

0.5000 Atmosphere Sump Noble gases (atoms) 2.0602E+14 0.0000E+00 Elemental I (atoms) 1.3595E+11 0.0000E+00 Organic I (atoms) 4.2047E+09 0.0000E+00 Aerosols (kg) 1.4465E-12 0.0000E+00

DC0004O-121, Revision 0 Page 78 of 83 Dose Effective (Ci/cc) 1-131 (Thyroid) 1.4130E-14 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 1.7738E-14 Total I (Ci) 2.2864E-05 Release Volume to Environment Transport Group Inventory:

Time (h) =

0.5000 Pathway Filtered Transported Noble gases (atoms) 0.0000E+00 4.5087E+22 Elemental I (atoms) 0.0000E+00 2.9570E+19 Organic I (atoms) 0.000.0E+00 9.1453E+17 Aerosols (kg) 0.0000E+00 2.8986E-04 Detailed model information at time (H) =

2.0000 EAB Doses:

Time (h) =

2.0000 Whole Body Delta dose (rem) 2.7279E-04 Thyroid 1.9825E-02 TEDE 1.4681E-03 Accumulated dose (rem) 4.8383E-02 LPZ Doses:

Time (h) =

2.0000 Whole Body Delta dose (rem) 5.3238E-05 Accumulated dose (rem) 9.4424E-03 TSC Doses:

Time (h) =

2.0000 Whole Body Delta dose (rem) 3.3559E-04 5.6968E+00 Thyroid 3.8690E-03 1.1118E+00 Thyroid 8.0839E-01 2.5024E-01 TEDE 2.8652E-04 4.8837E-02 TEDE 2.9020E-02 Accumulated dose (rem) 7.7112E-04 1.7798E+00 6.3793E-02 Arbitrary Volume Compartment Nuclide Inventory:

Time (h) =

2.0000 Ci kg Atoms Decay Kr-85m 5.0751E-09 6.1670E-19 4.3692E+06 1.6605E+08 Kr-85 2.9110E-08 7.4196E-14 5.2567E+11 7.2715E+08 Kr-87 1.4057E-09 4.9627E-20 3.4352E+05 9.1133E+07 Kr-88 7.5022E-09 5.9830E-19 4.0943E+06 2.8694E+08 1-131 3.4288E-09 2.7658E-17 1.2714E+08 1.9938E+08 1-132 5.9881E-09 5.8012E-19 2.6466E+06 5.8637E+08 1-133 5.6347E-09 4.9741E-18 2.2522E+07 3.4511E+08 1-134 9.1500E-10 3.4300E-20 1.5415E+05 2.1193E+08 1-135 3.9874E-09 1.1354E-18 5.0649E+06 2.7676E+08 Xe-131m 8.7231E-09 1.0362E-16 4.7633E+08 2.1881E+08 Re-133m 7.0815E-08 1.5796E-16 7.1525E+08 1.8098E+09 Re-133 1.0985E-06 5.8688E-15 2.6573E+10 2.7684E+10 Re-135m 1.7543E-09 1.9348E-20 8.6307E+04 4.7294E+07 Re-135 3.0016E-08 1.1754E-17 5.2431E+07 8.1103E+08 Cs-134 2.1832E-09 1.6874E-15 7.5832E+09 1.6774E+07 Cs-136 2.1737E-09 2.9659E-17 1.3133E+08 1.6764E+07 Cs-137 9.7036E-10 1.1156E-14 4.9038E+10 7.4554E+06 Cs-138 4.7923E-10 1.1326E-20 4.9423E+04 1.0657E+07 Rb-88 2.4356E-08 2.0290E-19 1.3885E+06 1.0177E+08 Arbitrary Volume Transport Group Inventory:

Time (h) =

2.0000 Atmosphere Sump Noble gases (atoms) 5.5350E+11 0.0000E+00 Elemental I (atoms) 1.5281E+08 0.0000E+00 Organic I (atoms) 4.7260E+06 0.0000E+00 Aerosols (kg) 1.2873E-14 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 1.5958E-17 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 1.9417E-17 Total I (Ci) 1.9954E-08 Release Volume to Environment Transport Group Inventory:

Time (h) =

2.0000 Pathway Filtered Transported Noble gases (atoms) 0.0000E+00 4.5775E+22 Elemental I (atoms) 0.0000E+00 2.9991E+19 Organic I (atoms) 0.0000E+00 9.2756E+17 Aerosols (kg) 0.0000E+00 2.9841E-04

Detailed model information at time EAE Doses:

(H)

=

8.0000 Time (h) =

8.0000 Whole Body Delta dose (rem) 2.7755E-03 Thyroid 9.6554E-01 TEDE 3.5653E-02 Accumulated dose (rem) 5.1158E-02 6.6623E+00 2.8589E-01 LPZ Doses:

Time (h) =

Delta dose 8.0000 Whole Body (rem) 5.4167E-04 Thyroid 1.8844E-01 TEDE 6.9580E-03 Accumulated dose (rem) 9.9841E-03 1.3002E+00 5.5795E-02 TSC Doses:

Time (h) =

Delta dose 8.0000 Whole Body (rem) 3.8262E-05 Thyroid 2.4890E-01 TEDE 8.5434E-03 Accumulated dose (rem) 8.0938E-04 2.0287E+00 7.2337E-02 Arbitrary Volume Compartment Nuclide Inventory:

Time (h) =

8.0000 Ci kg Atoms Decay Kr-85m 4.0068E-09 4.8688E-19 3.4495E+06 1.7133E+08 Kr-85 5.8148E-08 1.4821E-13 1.0501E+12 7.7363E+08 Kr-87 1.0668E-10 3.7663E-21 2.6070E+04 9.1793E+07 Kr-88 3.4652E-09 2.7635E-19 1.8911E+06 2.9323E+08 1-131 4.4035E-08 3.5520E-16 1.6329E+09 2.3496E+08 1-132 1.2883E-08 1.2481E-18 5.6940E+06 6.1541E+08 1-133 6.0541E-08 5.3443E-17 2.4199E+08 3.9867E+08 1-134 1.0451E-10 3.9176E-21 1.7606E+04 2.1393E+08 1-135 2.7891E-08 7.9419E-18 3.5427E+07 3.0780E+08 Xe-131m 1.7176E-08 2.0402E-16 9.3790E+08 2.3264E+08 Xe-133m 1.3077E-07 2.9170E-16 1.3208E+09 1.9185E+09 Xe-133 2.1285E-06 1.1372E-14 5.1489E+10 2.9411E+10 Xe-135m 2.8358E-09 3.1276E-20 1.3952E+05 4.9452E+07 Xe-135 4.4344E-08 1.7365E-17 7.7461E+07 8.5250E+08 Cs-134 2.7100E-09 2.0946E-15 9.4132E+09 1.8941E+07 Cs-136 2.6634E-09 3.6341E-17 1.6092E+08 1.8907E+07 Cs-137 1.2048E-09 1.3851E-14 6.0885E+10 8.4183E+06 Rb-88 7.4224E-09 6.1834E-20 4.2315E+05 1.1507E+08 Arbitrary Time (h) =

Volume Transport Group Inventory:

8.0000 Atmosphere Sump Noble gases (atoms) 1.1039E+12 0.0000E+00 Elemental I (atoms) 1.8585E+09 0.0000E+00 Organic I (atoms) 5.7480E+07 0.0000E+00 Aerosols (kg) 1.5982E-14 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 1.9422E-16 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 2.2250E-16 Total I (Ci) 1.4545E-07 Release Volume to Environment Transport Group Inventory:

Pathway Time (h) =

8.0000 Filtered Transported Noble gases (atoms) 0.0000E+00 3.3590E+24 Elemental I (atoms) 0.0000E+00 1.1145E+22 Organic I (atoms) 0.0000E+00 3.4469E+20 Aerosols (kg) 0.0000E+00 1.8971E-02 Detailed model information at time (H) =

18.0000 EAB Doses:

Time (h) = 18.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.4796E-03 5.6307E-01 1.9693E-02 Accumulated dose (rem) 5.2638E-02 7.2254E+00 3.0558E-01 LPZ Doses:

Time (h) = 18.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.0047E-04 7.6287E-02 2.6681E-03

D00004O-121, Revision 0 Page 80 of 83 Accumulated dose (rem) 1.0185E-02 1.3765E+00 5.8463E-02 TSC Doses:

Time (h) =

Delta dose 18.0000 Whole Body (rem) 1.1081E-05 Thyroid 1.4837E-01 TEDE 4.8284E-03 Accumulated dose (rem) 8.2046E-04 2.1771E+00 7.7165E-02 Arbitrary Volume Compartment Nuclide Inventory:

Time (h) =

18.0000 Ci kg Atoms Decay Kr-85m 4.2650E-10 5.1826E-20 3.6718E+05 1.7269E+08 Kr-85 2.9078E-08 7.4116E-14 5.2510E+ll 8.1236E+08 Kr-88 1.5095E-10 1.2038E-20 8.2380E+04 2.9409E+08 1-131 3.1460E-08 2.5376E-16 1.1666E+09 2.7762E+08 1-132 4.6854E-10 4.5391E-20 2.0709E+05 6.1942E+08 1-133 3.2128E-08 2.8361E-17 1.2842E+08 4.4946E+08 1-135 7.2378E-09 2.0610E-18 9.1936E+06 3.2484E+08 Xe-131m 8.3858E-09 9.9611E-17 4.5792E+08 2.4394E+08 Xe-133m 5.7367E-08 1.2797E-16 5.7943E+08 2.0001E+09 Xe-133 1.0115E-06 5.4036E-15 2.4467E+10 3.0793E+10 Xe-135m 3.1269E-09 3.4487E-20 1.5384E+05 5.0066E+07 Xe-135 1.2590E-08 4.9300E-18 2.1992E+07 8.7482E+08 Cs-134 9.3371E-10 7.2167E-16 3.2433E+09 2.0184E+07 Cs-136 8.9801E-10 1.2253E-17 5.4255E+07 2.0117E+07 Cs-137 4.1525E-10 4.7740E-15 2.0985E+10 8.9714E+06 Rb-88 4.2903E-10 3.5741E-21 2.4459E+04 1.1617E+08 Arbitrary Volume Transport Group Inventory:

Time (h) = 18.0000 Atmosphere Sump Noble gases (atoms) 5.5063E+11 0.0000E+00 Elemental I (atoms) 1.2653E+09 0.0000E+00 Organic I (atoms) 3.9132E+07 0.0000E+00 Aerosols (kg) 5.5079E-15 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 1.3074E-16 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 1.4362E-16 Total I (Ci) 7.1295E-08 Release Volume to Environment Transport Group Inventory:

Pathway Time (h) = 18.0000 Filtered Transported Noble gases (atoms) 0.0000E+00 3.3593E+24 Elemental I (atoms) 0.0000E+00 1.1146E+22 Organic I (atoms) 0.0000E+00 3.4472E+20 Aerosols (kg) 0.0000E+00 1.8974E-02 Detailed model information at time (H) =

24.0000 EAB Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.9531E-12 8.9398E-10 3.0852E-11 Accumulated dose (rem) 5.2638E-02 7.2254E+00 3.0558E-01 LPZ Doses:

Time (h) = 24.0000 Whole Body Thyroid TIDE Delta dose (rem) 2.6461E-13 1.2112E-10 4.1800E-12 Accumulated dose (rem) 1.0185E-02 1.3765E+00 5.8463E-02 TSC Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 4.2247E-07 7.0456E-03 2.2818E-04 Accumulated dose (rem) 8.2088E-04 2.1841E+00 7.7393E-02 Arbitrary Volume Compartment Nuclide Inventory:

Time (h) = 24.0000 Ci kg Atoms Decay Arbitrary Volume Transport Group Inventory:

Time (h) = 24.0000 Atmosphere Sump Noble gases (atoms) 0.0000E+00 0.0000E+00

Elemental I (atoms) 0.0000E+00 0.0000E+00 Organic I (atoms) 0.0000E+00 0.0000E+00 Aerosols (kg) 0.0000E+00 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 0.0000E+00 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 0.0000E+00 Total I (Ci) 0.0000E+00 Release Volume to Environment Transport Group Inventory:

Pathway Time (h) = 24.0000 Filtered Transported Noble gases (atoms) 0.0000E+00 3.3593E+24 Elemental I (atoms) 0.0000E+00 1.1146E+22 Organic I (atoms) 0.0000E+00 3.4472E+20 Aerosols (kg) 0.0000E+00 1.8974E-02 Detailed model information at time (H) =

96.0000 EAB Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 5.2638E-02 7.2254E+00 3.0558E-01 LPZ Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 1.0185E-02 1.3765E+00 5.8463E-02 TSC Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.2648E-17 6.1146E-13 1.9803E-14 Accumulated dose (rem) 8.2088E-04 2.1841E+00 7.7393E-02 Arbitrary Volume Compartment Nuclide Inventory:

Time (h) = 96.0000 Ci kg Atoms Arbitrary Volume Transport Group Inventory:

Time (h) = 96.0000 Atmosphere Sump Noble gases (atoms) 0.0000E+00 0.0000E+00 Elemental I (atoms) 0.0000E+00 0.0000E+00 Organic I (atoms) 0.0000E+00 0.0000E+00 Aerosols (kg) 0.0000E+00 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 0.0000E+00 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 0.0000E+00 Total I (Ci) 0.0000E+00 Release Volume to Environment Transport Group Inventory:

Pathway Time (h) = 96.0000 Filtered Transported Noble gases (atoms) 0.0000E+00 3.3593E+24 Elemental I (atoms) 0.0000E+00 1.1146E+22 Organic I (atoms) 0.0000E+00 3.4472E+20 Aerosols (kg) 0.0000E+00 1.8974E-02 Detailed model information at time (H) = 720.0000 EAB Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 5.2638E-02 7.2254E+00 3.0558E-01 LPZ Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 1.0185E-02 1.3765E+00 5.8463E-02 Decay TSC Doses:

DC0004O-121, Revision 0 Page 82 of 83 Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.5765-135 4.1722-131 1.3692-132 Accumulated dose (rem) 8.2088E-04 2.1841E+00 7.7393E-02 Arbitrary Volume Compartment Nuclide Inventory:

Time (h) = 720.0000 Ci kg Atoms Decay Arbitrary Volume Transport Group Inventory:

Time (h) = 720.0000 Atmosphere Sump Noble gases (atoms) 0.0000E+00 0.0000E+00 Elemental I (atoms) 0.0000E+00 0.0000E+00 Organic I (atoms) 0.0000E+00 0.0000E+00 Aerosols (kg) 0.0000E+00 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 0.0000E+00 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 0.0000E+00 Total I (Ci) 0.0000E+00 Release Volume to Environment Transport Group Inventory:

Time (h) = 720.0000 Pathway Filtered Transported Noble gases (atoms) 0.0000E+00 3.3593E+24 Elemental I (atoms) 0.0000E+00 1.1146E+22 Organic I (atoms) 0.0000E+00 3.4472E+20 Aerosols (kg) 0.0000E+00 1.8974E-02 837 1-131 Summary Time (hr)

Arbitrary Volume 1-131 (Curies)

Environment 1-131 (Curies)

TSC 1-131 (Curies) 0.000 2.9861E-06 9.9533E-02 2.3791E-05 0.401 2.9818E-06 7.1800E+01 8.8546E-03 0.500 2.9807E-06 8.9486E+01 9.6307E-03 0.800 3.4437E-09 8.9548E+01 3.1152E-03 1.100 3.4399E-09 8.9610E+01 1.0137E-03 1.400 3.4362E-09 8.9672E+01 3.3582E-04 1.700 3.4325E-09 8.9733E+01 1.1717E-04 2.000 3.4288E-09 8.9795E+01 4.6639E-05 2.300 4.4946E-08 9.0604E+01 1.1316E-04 2.600 4.4898E-08 9.1413E+01 1.3451E-04 2.900 4.4850E-08 9.2220E+01 1.4129E-04 3.200 4.4801E-08 9.3027E+01 1.4337E-04 3.500 4.4753E-08 9.3833E+01 1.4393E-04 3.800 4.4705E-08 9.4638E+01 1.4401E-04 4.100 4.4657E-08 9.5442E+01 1.4393E-04 4.400 4.4609E-08 9.6245E+01 1.4380E-04 4.700 4.4561E-08 9.7048E+01 1.4365E-04 5.000 4.4513E-08 9.7849E+01 1.4350E-04 5.300 4.4465E-08 9.8650E+01 1.4335E-04 5.600 4.4417E-08 9.9450E+01 1.4319E-04 5.900 4.4369E-08 1.0025E+02 1.4304E-04 6.200 4.4321E-08 1.0105E+02 1.4289E-04 6.500 4.4273E-08 1.0184E+02 1.4273E-04 6.800 4.4226E-08 1.0264E+02 1.4258E-04 7.100 4.4178E-08 1.0344E+02 1.4242E-04 7.400 4.4130E-08 1.0423E+02 1.4227E-04 7.700 4.4083E-08 1.0502E+02 1.4212E-04 8.000 4.4035E-08 1.0582E+02 1.4196E-04 8.300 3.2576E-08 1.0640E+02 8.0268E-05 8.600 3.2541E-08 1.0699E+02 6.0330E-05 8.900 3.2506E-08 1.0757E+02 5.3863E-05 9.200 3.2471E-08 1.0816E+02 5.1739E-05 9.500 3.2436E-08 1.0874E+02 5.1018E-05 9.800 3.2401E-08 1.0933E+02 5.0748E-05 10.100 3.2366E-08 1.0991E+02 5.0624E-05 10.400 3.2331E-08 1.1049E+02 5.0547E-05 18.000 3.1460E-08 1.2502E+02 4.9175E-05 24.000 0.0000E+00 1.2502E+02 7.3039E-15

D000040-121, Revision 0 Page 83 of 83 96.000 0.0000E+00 1.2502E+02 8.4188-133 720.000 0.0000E+00 1.2502E+02 0.0000E+00 Cumulative Dose Summary EAB LPZ TSC Time (hr)

Thyroid (rem)

TEDE (rem)

Thyroid (rem)

TIDE (rem)

Thyroid (rem)

TEDE (rem) 0.000 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.401 4.5581E+00 2.0007E-01 8.8956E-01 3.9046E-02 6.8505E-01 2.4526E-02 0.500 5.6770E+00 2.4877E-01 1.1079E+00 4.8550E-02 9.7140E-01 3.4773E-02 0.800 5.6810E+00 2.4907E-01 1.1087E+00 4.8608E-02 1.5189E+00 5.4366E-02 1.100 5.6849E+00 2.4937E-01 1.1095E+00 4.8666E-02 1.6957E+00 6.0704E-02 1.400 5.6889E+00 2.4966E-01 1.1103E+00 4.8724E-02 1.7534E+00 6.2790E-02 1.700 5.6928E+00 2.4995E-01 1.1110E+00 4.8780E-02 1.7727E+00 6.3511E-02 2.000 5.6968E+00 2.5024E-01 1.1118E+00 4.8837E-02 1.7798E+00 6.3793E-02 2.300 5.7469E+00 2.5216E-01 1.1216E+00 4.9211E-02 1.7877E+00 6.4086E-02 2.600 5.7968E+00 2.5405E-01 1.1313E+00 4.9581E-02 1.7992E+00 6.4488E-02 2.900 5.8464E+00 2.5593E-01 1.1410E+00 4.9948E-02 1.8118E+00 6.4925E-02 3.200 5.8959E+00 2.5780E-01 1.1507E+00 5.0312E-02 1.8248E+00 6.5371E-02 3.500 5.9452E+00 2.5964E-01 1.1603E+00 5.0672E-02 1.8379E+00 6.5818E-02 3.800 5.9942E+00 2.6147E-01 1.1698E+00 5.1029E-02 1.8509E+00 6.6265E-02 4.100 6.0431E+00 2.6329E-01 1.1794E+00 5.1384E-02 1.8639E+00 6.6709E-02 4.400 6.0918E+00 2.6509E-01 1.1889E+00 5.1736E-02 1.8769E+00 6.7153E-02 4.700 6.1403E+00 2.6688E-01 1.1983E+00 5.2085E-02 1.8898E+00 6.7594E-02 5.000 6.1886E+00 2.6866E-01 1.2078E+00 5.2432E-02 1.9026E+00 6.8033E-02 5.300 6.2367E+00 2.7043E-01 1.2172E+00 5.2777E-02 1.9154E+00 6.8471E-02 5.600 6.2847E+00 2.7218E-01 1.2265E+00 5.3120E-02 1.9282E+00 6.8907E-02 5.900 6.3324E+00 2.7393E-01 1.2358E+00 5.3460E-02 1.9409E+00 6.9341E-02 6.200 6.3801E+00 2.7566E-01 1.2451E+00 5.3799E-02 1.9536E+00 6.9774E-02 6.500 6.4275E+00 2.7739E-01 1.2544E+00 5.4136E-02 1.9662E+00 7.0205E-02 6.800 6.4748E+00 2.7911E-01 1.2636E+00 5.4471E-02 1.9788E+00 7.0634E-02 7.100 6.5219E+00 2.8081E-01 1.2728E+00 5.4804E-02 1.9913E+00 7.1062E-02 7.400 6.5689E+00 2.8251E-01 1.2820E+00 5.5136E-02 2.0038E+00 7.1488E-02 7.700 6.6157E+00 2.8421E-01 1.2911E+00 5.5466E-02 2.0163E+00 7.1913E-02 8.000 6.6623E+00 2.8589E-01 1.3002E+00 5.5795E-02 2.0287E+00 7.2337E-02 8.300 6.6800E+00 2.8652E-01 1.3026E+00 5.5880E-02 2.0379E+00 7.2649E-02 8.600 6.6976E+00 2.8715E-01 1.3050E+00 5.5965E-02 2.0439E+00 7.2847E-02 8.900 6.7152E+00 2.8777E-01 1.3074E+00 5.6050E-02 2.0488E+00 7.3008E-02 9.200 6.7327E+00 2.8840E-01 1.3098E+00 5.6134E-02 2.0534E+00 7.3156E-02 9.500 6.7502E+00 2.8901E-01 1.3121E+00 5.6218E-02 2.0578E+00 7.3300E-02 9.800 6.7676E+00 2.8963E-01 1.3145E+00 5.6301E-02 2.0622E+00 7.3442E-02 10.100 6.7849E+00 2.9024E-01 1.3168E+00 5.6384E-02 2.0665E+00 7.3583E-02 10.400 6.8022E+00 2.9085E-01 1.3192E+00 5.6467E-02 2.0709E+00 7.3724E-02 18.000 7.2254E+00 3.0558E-01 1.3765E+00 5.8463E-02 2.1771E+00 7.7165E-02 24.000 7.2254E+00 3.0558E-01 1.3765E+00 5.8463E-02 2.1841E+00 7.7393E-02 96.000 7.2254E+00 3.0558E-01 1.3765E+00 5.8463E-02 2.1841E+00 7.7393E-02 720.000 7.2254E+00 3.0558E-01 1.3765E+00 5.8463E-02 2.1841E+00 7.7393E-02 Worst Two-Hour Doses EAB Time Whole Body Thyroid TEDE (hr)

(rem)

(rem) 0.0 4.8383E-02 5.6968E+00 2.5024E-01

TECHNICAL WORK RECORD Originator:

Michael J. Feehan Date:

07/30/2012 System:

N/A Project Title Verification of DC00040-121, RO ECR 50786 Page 1

of 3

1.0 Purpose

This TWR is developed to document the verification of DC00040-121, R0, "Steam Generator Tube Rupture

- TSC."

2.0

Reference:

Calculation DC00040-121, R0, "Steam Generator Tube Rupture - TSC."

3.0 Discussion

The verification of the calculation is to assure that the calculation has been completed IAW ES-412. The verification is performed IAW ES-110. ES-110, Attachment III is included as Attachment 1 to this TWR.

The verification included check of input, mathematical manipulations, computer code input/output and results. The RADTRAD computer code was utilized in the analysis. RADTRAD is a validated and verified code for nuclear use per IAW WorleyParsons QA procedures. There are no assumptions in the calculation requiring future confirmation.

4.0 Comments

Technical comments resulted from the review.

1.

None Editorial comments:

1.

Minor editorial comments that have no impact on the results.

2.

Successfully incorporated David McCreary comments.

5.0 Results

The verifier comments have been resolved and the results of the calculation are acceptable for use.

TECHNICAL WORK RECORD Originator:

Michael J. Feehan Date:

07/30/2012 System:

N/A Project Title Verification of D000040-121, RO ECR 50786 Page 2

of 3

ES-110 ATTACHMENT III PAGE 1 OF 2 REVISION 2 VERIFICATION RECORD: CALCULATION Calculation #

D000040-121 Revision 0 The following questions, as a minimum should be answered for calculation verification.

Yes N/A

q

q Have inputs, including codes, standards, regulations, requirements, procedures, data and engineering methodology been correctly selected and applied?

Has the calculation been developed in accordance with applicable station procedures (e.g., ES-412).

Is the plant design basis/criteria maintained?

Have assumptions been identified, especially those requiring later confirmation?

Have references been properly identified and complete?

Have the calculation, results, tables and figures been reviewed with regard to numerical accuracy, units and consistency?

Has the calculation been developed/revised in a clear and understandable manner as to not require recourse to the originator?

Is the output reasonable compared to the input?

Do the diagrams or models depicted represent the physical situation correctly and incorporate necessary features for a correct analysis?

Has the calculation cover page been completed in an accurate manner?

Are the sign conventions used in figures and equations consistent?

Is consistent nomenclature used throughout the calculation (e.g., figures, tables)?

Are symbols used on figures and in the text defined?

Are concurrent in-process revisions been addressed and coordinated with this revision?

Has the Calculation Index been updated?

Additional considerations (see attached TWR)?

TECHNICAL WORK RECORD Originator:

Michael J. Feehan Date:

07/30/2012 System:

N/A Project Title Verification of D000040-121, RO ECR 50786 Page 3

of 3

ES-110 ATTACHMENT III PAGE 2 OF 2 REVISION 2 VERIFICATION RECORD: CALCULATION Calculation #

D000040-121 Revision 0 CALCULATIONS UTILIZING COMPUTER PROGRAMS:

q Has the program been appropriately defined, including the version?

Is the basic methodology used by the program appropriate for the calculation?

Has the appropriate computer program been used?

Has the calculation been performed within the known limits of the program?

Has the computer program been verified and validated in accordance with SAP-1040? Validated by WorleyParsons.

Has the program been defined, controlled, and benchmarked so that the results reported are traceable to a particular version of the program and a particular set of input data?

Have limits for the program been defined, as appropriate?

Comments have been included and resolved.

Is the Validation Data set for the application complete, and provide repeatable results?

Michael J. Feehan/

/2.%a4-_--'

07/30/2012 Verifier's Printed Name Verifier's Signature Date

ES-0110 ATTACHMENT XVI PAGE 1 OF,'t f D, Or REVISION 2 glr/ez REVIEW CONSIDERATIONS: OWNER'S ACCEPTANCE REVIEW ECR/Document Number: D000040-079, D000040-118 Through -123 Project

Title:

Review of New NOB TSC Dose Calculations The following questions should be considered, as a minimum, during the performance of an Owner's Acceptance Review of vendor developed engineering documents.

Yes N/A 1-1

q Is the technical information/design complete, consistent, and correct for the activity under review?

Were inputs, including codes, standards, and regulatory requirements correctly selected and applied?

Are assumptions necessary to perform the design activity adequately described and reasonable? Where necessary, are the assumptions identified for subsequent re-verification when the detailed design activities are completed?

Is the document/package developed in a clear and understandable manner?

Is the plant design basis/criteria maintained?

Are references properly identified and complete?

Were design considerations from EC-01, Attachment I and 11 adequately add ressed/incorporated?

Were technical, design, program or procedure requirements adequately addressed/incorporated?

Have applicable construction and operating experiences been considered?

Were designs developed in accordance with good engineering practices and established ES guidance documents?

Have impacted documents, databases (EC-02) and equipment changes been identified?

Is the document/package developed in accordance with applicable station procedures (e.g., SAP-133, ES-453, ES-455)?

Is the document/package developed in a clear and understandable manner as to not require recourse to the Originator?

D

ES-0110 ATTACHMENT XVI PAGE 2 OF,Z'( 0 (`;

REVISION 2 iivllZ Yes N/A Does the design meet interfacing organizations operational/maintenance requirements?

D El N

I I

Is technical information adequate to perform the task?

Is the acceptance criteria adequate for the activity under review?

Is the post modification testing adequate to confirm the design?

Has the 10CFR50.59 Review Process been completed, if required?

For work performed in accordance with VC Summer Nuclear Station Procedures, the procedure forms must be signed by the originator and if not qualified must be co-signed by a qualified person. Check the qualifications of the contractor personnel signing the procedure forms.

Yes No

q Are contractor personnel signing the VCSNS procedure forms qualified under a vendor qualification program or the VCSNS Nuclear Training Manual for those procedures?

If not have the VCSNS forms been co-signed by a person qualified to the applicable procedure?

Technical Reviews

q Are all technical reviews complete and all comments resolved to the satisfaction of the commenter?

TECHNICAL REVIEW: Check all blocks that apply q Principal Piping Engineer q

Principal Engr Analysis Engineer q

Principal I&C Engineer q

Principal Mechanical Engineer q

Principal Civil Engineer q

Principal PSA Engineer q

Principal Nuclear Fuels Engineer q

Principal Digital Engineer q

Principal Electrical Engineer q

Principal EQ Engineer q

Principal Fire Protection Engineer q

Anatysis Engineer Dave McCreary q

q q

)w 30 -2 Dave McCrea

/

=^z'^*, °,

Reviewer's Printed Name Reviewer's Sig ature Date

Detailed Owners Acceptance Review Notes There are three general comments in all of the dose calculations that should be addressed:

1)

The initiation of the HVAC "Emergency Mode" would only be manually. There are statements in the calculations of SI signal initiation. These should be removed to avoid confusion with the Unit 1 Control Room Habitability Envelope and it's automatic Emergency Mode initiation on an SI signal.

SPOT Ire atements re ardin

>1 signals will be removed.

2)

The 1000 cfm allotted for TSC "inleakage" isn't applicable in these scenarios since it is very conservatively assumed that none of the air flowing through the TSC is filtered or recirculated. Therefore, 13,000 cfm of unfiltered outside air is flowing into the TSC and out of the TSC. The discussions should be cleaned up to state that the 13,000 cfm assumed conservatively bounds the expected design flow rate value of 12,000 cfm, and that the doses calculated due to assuming no filtration throughout the accident is very conservative since the TSC filtration capability and isolation times are currently unknown.

cfm assumed conservatively bounds,the expected tlesign flow rate value of ively, calculated 12,000 cfm : The doses are conservat filtration throughout the accident.

er not to state that the TSC filtration capability currently unknown. There is a`PS^ID-,showing flters a V.I assumed`an operator action such as 30 minutes if we ha 3)

Suggest not listing procedure revision levels in the verification TVVR's. ES-412 and

-110 have been updated.

0 RESPON below ree to delete recision levels M.-

12 -1 ments Agree, torall comments/corrections.noted ividual com Main Steam Line Break, DC00040-118, Rev. 0:

1.

Follows same format and methodology as in MSLB dose calculation D000040-099 for CR/EAB/LPZ.

2.

Table of Contents needs to be updated for page number corrections.

3.

Section 5.3 should be revised for the general comments above.

Es -0//v

^-

xv^.

PQyL^b^^/

Locked Rotor, DC00040-119, Rev. 0:

19ldile

^a^3v/ice 4.

Follows same format and methodology as in LR dose calculation DC00040-100 for CR/EAB/LPZ.

Sections 2.16 and 5.10 should be revised for the general comments above.

5.

References 4.11 and 4.14 are the same. Per DI-5.10, Ref. 4.11 should be same reference as used in DC00040-118 Ref. 18.

6.

Reference 4.17 is up to Rev 3... Affects DI-5.9 (10gpm value is now 30gpm), but calc uses the correct mass rate so no change in results.

Fuel Handling Accident, DC00040-120, Rev. 0:

7.

Follows same format and methodology as in Fuel Handling dose calculation DC00040-102 for CR/EAB/LPZ.

8.

Sections 2.15 and 5.12 should be revised for the general comments above.

SGTR, DC00040-121, Rev. 0:

9.

Follows same format and methodology as in SGTR dose calculation D000040-098 for CR/EAB/LPZ.

10.

Section 5.3 should be revised for the general comments above.

LOCH; DC00040-122, Rev. 0:

11.

Follows same format and methodology as in LOCA dose calculation D000040-097 for CR/EAB/LPZ.

12.

Section 5.7 should be revised for the general comments above.

CREA, DC00040-123, Rev. 0:

13.

Follows same format and methodology as in CREA dose calculation D000040-101 for CR/EAB/LPZ.

14.

References 4.11 and 4.12 are the same. Per DI-5.10, Ref. 4.11 should be same reference as used in DC00040-118 Ref. 18.

15.

Section 5.10 should be revised for the general comments above..

ML14324A325

Text

Description:

SUMMARY

9.0 REFERENCES

9.0 REFERENCES

1.0 Purpose

Reference:

3.0 Discussion

4.0 Comments

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