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Calculation - DC00040-118 - Main Steam Line Break - TSC
	ML14324A322
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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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ML1432A264	List: ML14324A322; RC-14-0179, Calculation - DC00040-118 - Main Steam Line Break - TSC;
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	LAR-13-02396, RC-14-0179 DC00040-118, 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 97 Calculation Title Calculation Number Revision Status Main Steam Line Break - TSC D000040-118 0

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Parent Document System Safety Class qPartial 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 Main Steam Line Break (MSLB). This analysis is performed in accordance with the requirements of Appendix E of the USNRC Regulatory Guide 1.183.

Affected Components/Calculations/Documents: FSAR Section 15.4.2 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 n ineerin Personnel /Date Own 's Acceptance Review ter Verifier/Date Responsible Engi eer/Date Required for all engineering work performed by contractor personnel not enrolled in the VCSNS Engineering Training Program RECORDS Q

^^--

To Records Mgmt:

Approval/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 DC00040-118 Revision Number Summary Description 0

Initial Issue Page 2 of 97

DO00040-118 Revision 0 Page 3 of 97 TABLE OF CONTENTS 1.0 PURPOSE............................................................................................................................ 5 2.0 Computer Code.................................................................................................................... 5 3.0 Assumptions........................................................................................................................ 5 4.0 DESIGN INPUTS................................................................................................................ 7 5.0 METHODOLOGY............................................................................................................10 5.1 Source Term with Pre-Existing Iodine Spike....................................................................10 5.1.1 Activity in Secondary Coolant Released from Faulted SG............................................... 11 5.1.2 0.35 gpm SG Tube Leak - Activity Release 0-2 hr........................................................... 13 5.1.3 0.35 gpm SG Tube Leak - Activity Release 2 - 8 hr......................................................... 14 5.1.4 0.35 gpm SG Tube Leak - Activity Release 8 - 24 hr....................................................... 15 5.1.5 0.65 gpm 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 ........................16 5:1.6 0.65 gpm Steam Generator Tube Leak - Activity Release for 2 - 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ........................ 17 5.1.7 0.65 gpm Steam Generator Tube Leak - Activity Release for 8 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ...................... 18 5.1.8 Secondary Coolant Activity Release from Intact SGs....................................................... 19 5.1.9 Pre-Existing Total Activity Released 0 - 2 hrs.................................................................. 20 5.1.10 Pre-Existing Spike Total Activity Released 2 - 8 hrs........................................................21 5.1.11 Pre-Existing Spike Total Activity Released...................................................................... 22 5.1.12 Pre-Existing Spike Fraction of Total Activity Released.................................................... 23 5.2 Source Term with Concurrent Iodine Spike...................................................................... 24 5.2.1 Secondary Coolant Activity Based on Reactor Coolant with 1% Failed Fuel..................25 5.2.2 0.35 gpm SG Tube Leak - Activity Release 0-2 hr........................................................... 28 5.2.3 0.35 gpm SG Tube Leak - Activity Release 2 - 8 hr......................................................... 29 5.2.4 0.35 gpm SG Tube Leak - Activity Release 8 - 24 hr............................ :......................... 30 5.2.5 0.65 gpm SG Tube Leak - Activity Release 0 - 2 hr........................................................ 31 5.2.6 0.65 gpm SG Tube Leak - Activity Release 2 - 8 hr........................................................ 32 5.2.7 0.65 gpm SG Tube Leak - Activity Release 8 - 24 hr.................................................. :.... 33 5.2.8 Concurrent Spike Secondary Coolant Activity Release from Intact SGs..........................34 5.2.9 Concurrent Spike Total Activity Released 0 - 2 hrs..........................................................35 5.2.10 Concurrent Spike Total Activity Released 2 - 8 hrs 1.0 gpm............................................36 5.2.11 Concurrent Spike Total Activity Released........................................................................ 37 5.2.12 Concurrent Spike Fraction Total Activity Released..........................................................38 5.3 TSC ventilation system parameters:.................................................................................. 39 6.0 RADTRAD Models........................................................................................................... 41 6.1 MSLB Design Case-RADTRAD Models........................................................................41 6.1.1 RADTRAD Model - MSLB - Design Basis Case............................................................41 6.1.2 RADTRAD Volume I represents the Containment..........................................................41 6.1.3 RADTRAD Volume 2 represents the Environment.......................................................... 41 6.1.4 RADTRAD Volume 3 represents the Technical Support Center......................................41 6.1.5 RADTRAD Pathway 1 represents the Containment leakage term.................................... 42 6.1.6 RADTRAD Pathway 2 represents the TSC Outside Air Intake Pathway.........................42 6.1.7 RADTRAD Pathway 3 represents the TSC Unfiltered Air Inleakage Pathway................ 42 6.1.8 RADTRAD Pathway 4 represents the TSC Exhaust Air Pathway....................................42 6.1.9 RADTRAD Pathway 5 represents the TSC Emergency Recirculation Air Pathway........42 6.1.10 RADTRAD Dose Location 1-Protected TSC.................................................................. 42

DC00040-118 Revision 0 Page 4 of 97 6.1.11 RADTRAD Dose Location 2 - EAB.................................................................................42 6.1.12 RADTRAD Dose Location 3 - LPZ.................................................................................42 6.1.13 RADTRAD Source Tenn:................................................................................................. 43 6.1.14 RADTRAD Control Options:............................................................................................ 43

7.0 CONCLUSION

S...............................................................................................................43 8.0 DISPOSITION of RESULTS............................................................................................43 9.0 References.........................................................................................................................44 Attachment No. 1 RADTRAD Model.......................................................................................... 46 Attachment No. 2 MSLB concurrent.NIF.................................................................................... 48 Attachment No. 3 MSLB pre I-BR spike.NIF.............................................................................. 52 Attachment No. 4 MSLB concurrent Iodine Spike.RFT.............................................................. 56 Attachment No. 5 MSLB pre.RFT............................................................................................... 58 Attachment No. 6 MSLB pre I Spike........................................................................................... 60 Attachment No. 7 MSLB concurrent I Spike............................................................................... 76 Attachment No. 8 Copy of Reference 8......................................................................................... 92 Attachment No. 9 Copy of Reference 9......................................................................................... 95

DC00040-118 Revision 0 Page 5 of 97 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 Main Steam Line Break 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 MSLB event at VCS. Consistent with RG 1.183 Appendix E, Section 2.2, 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.

2.0 COMPUTER CODE RADTRAD 3.03 verified 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), Appendix E. No exceptions to the guidance within RG 1.183 or Appendix E are taken.

2.

No fuel melt or fuel clad breach is postulated for the MSLB event. This assumption is consistent with the VCS current licensing basis as stated in FSAR Section 15.4.2.1.4 (Reference 13).

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 1-131 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 I-131 (Reference 7) for the pre-existing spike scenario. The concurrent spike activity is based on an activity release rate from the fuel to the reactor coolant of 500 times the iodine equilibrium release rate consistent with the limiting condition for operation with the reactor coolant activity at the Technical Specification (TS) 3.4.8 limit of 1.0 µCi/gm DE I-131(Reference 7).

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 E, Section 4).

DO00040-118 Revision 0 Page 6 of 97 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 E Section 5.1). Per Reference 7, Bases 3/4.4.5, the total leakage for all three steam generators is 1 gpm. Prior to the event this leakage is assumed to be distributed throughout the three steam generators. To be consistent with preferred plant procedures for shutdown, the shutdown cooling rate following this type of event is taken as 25 OF /hr. Therefore, to go from 557 OF to 212 OF would require about 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months . The MSLB is conservatively analyzed using 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for the cooldown time. The activity associated with the 1 gpm leak is assumed to be released to the environment via the faulted steam generator at a rate of 0.35 gpm for the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months duration of the event with no credit taken for any reduction or mitigation, i.e. a partition factor of 1.0. This is conservative in that the actual maximum value allowed by TS 3.4.6.2.c for any one SG is 150 gpd

(- 0.104 gpm). The remaining 0.65 gpm is released to the environment via the two intact steam generators for the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months duration of the event crediting a partition factor of 100 in accordance with RG 1.183, Appendix E. In addition, the secondary coolant activity initially contained in the faulted SG is released to the environment with a partition factor of 1.0.

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 E, Section 5.2). A value of 1.0 gm/cc (62.43 lbm/ft) is used herein.

9.

References 8 (Attachment 8), 9 (Attachment 9) 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.

10. 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% activities.

11. This analysis assumes that the reactor coolant system (RCS) activity conservatively remains constant throughout the pre-existing Iodine Spike MSLB event. For the Concurrent Iodine Spike MSLB event, a similar assumption is made with the exception that the iodine activity increases during the 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 500 times the iodine equilibrium appearance rate.

12. Steam Generator (SG) volume is assumed to remain constant throughout both the Pre-existing and the Concurrent Iodine spike MSLB events and furthermore, dilution by incoming Auxiliary Feedwater is not considered.

13. A partition factor of 100 is applied to activity releases other than noble gases occurring via the intact steam generators consistent with Reference 1 Appendix E. Noble gases are released with a partition factor of 1.

D000040-118 Revision 0 Page 7 of 97 4.0 DESIGN INPUTS 4.1 Consistent with RG 1.183, Section 3.1 and Appendix E (Reference 1), the AST MSLB 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).

4.2 RC DE I-131 Values:

The reactor coolant DE 1-131 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 I-131 for reactor coolant at the design basis of I% 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 ICRP 30 Concentration 60 Ci/ m 60 Ci/ m 1.0 Ci/ m 1.0 pCi/grn Concentration D E 1-131 D E 1-131 DE 1-131 DE 1-131 DE I-131 Reference 6 Reference 16 CD Ci/ m DCF; Rem/Ci '

CD x DCF; C; Wi/grn)

CD, x DCF1 C

Ci/ m CD1 x DCF1 V

3 1.1E+06 3.300E+06 4.69E+01 5.16E+07 7.82E-01 8.60E+05 3.1 6.3E+03 1.953E+04 4.85E+01 3.05E+05 8.08E-01 5.09E+03 13 4.6 1.8E+05 8.280E+05 7.19E+01 1.29E+07 1.196E+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 C; = (1 or 60)

CD1 x DCF; /TOTAL CD; x DCF1)

Calculated DE I-131 Factor = 3.84 = [(TOTAL CD; x DCF / DCF.

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

1 µCi/gm and 60 µCi/gm DE I-131 Reactor Coolant Activities Isotope RC 1% Activity Ref. 6 Table 5-15 (Ci/ )

1 µCi/gm DE 1-131 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 1-131 3.0E+00 7.82E-01 4.69E+01 1-132 3.1E+00 8.08E-01 4.85E+01 1-133 4.6E+00 1.20E+00 7.19E+01 1-134 6.0E-01 1.56E-01 9.38E+00 1-135 2.4E+00 6.25E-01 3.75E+01

D000040-1 1 8 Revision 0 1 µCi/gm and 60 µCi/gm DE I-131 Reactor Coolant Activities Isotope RC 1% Activity Re£ 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)

Xe-131m 2.3E+00 2.3E+00 2.3E+00 Xe-133m 1.9E+01 1.9E+01 1.9E+01 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 Page 8 of 97 (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 1-131 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 MSLB event is given in the following table (References 8 and 9 for 0 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and Reference 21 for 8 to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ). The reactor coolant release via the steam gerator tube leak per Section 3, Assumption 7.

Time Steam Release from Faulted SG (Ibm)

Steam Release from Intact SGs (Ibm)

Reactor Coolant Release to Faulted SG (gpm)

Reactor Coolant Release to Intact SGs (gpm) 0 - 30 minutes 406,000 0 - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 343,700 0.35 0.65 2 - 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 733,900 0.35 0.65 8 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 1,200,000 0.35 0.65 4.4 Reference 14, Appendix 2 provides the post-accident x/Q's (sec/m) 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 I 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.

DC00040-118 Revision 0 Page 9 of 97 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): These values are not corrected for occupancy factors.

4.5 CR 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)

TSC 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, TSC Occupancy Factors 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 MSLB analysis are from Reference 5, Table 1.4.3.3-2 and Reference 10, Table 111. 1.

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 I 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.

DC00040-118 Revision 0 Page 10 of 97 5.0 METHODOLOGY 5.1 Source Term with Pre-Existing Iodine Spike The source term for the pre-existing spike includes the following:

I Activity in secondary coolant released from faulted SG.

2 Activity in reactor coolant released due to 035 gpm tube leak in faulted SG (0 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ).

3 Activity in reactor coolant released due to 0.35 gpm tube leak in faulted SG (2 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ).

4 Activity in reactor coolant released due to 0.35 gpm tube leak in faulted SG (8 to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ).

5 Activity in reactor coolant released due to 065 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 ).

6 Activity in reactor coolant released due to 065 gpm tube leak in intact SG (2 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ).

7 Activity in reactor coolant released due to 065 gpm tube leak in intact SG (8 to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ).

8 Activity in secondary coolant released from intact SG.

The activity releases are determined in sections 5.1.1 through 5.1.12.

DO00040-118 Revision 0 Page 11 of 97 5.1.1 Activity in Secondary Coolant Released from Faulted SG Secondary Coolant Specific Activity Based on 1 and 60 Ci/ m DE 1-131 Reactor Coolant Activi (1)

Lb Conservatively Low SG Blowdown (3) =

12756 lbm/hr M5e Water Mass in All 3 SGs =

340000 Ibm Lp Leak Rate =

1.0 m =

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

Sec. Coolant E q. Conc. For Decay For DE 1-131, 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 1-131 CS 1/sec (5)

Ci/ m Ci/ m Ci/lbm Ci/lbm 1

1-131 9.96E-07 7.82E-01 4.69E+01 1.27E+01 7.62E+02 (1) 1-132 8.26E-05 8.08E-01 4.85E+01 1.61E+00 9.66E+01 (1) 1-133 9.20E-06 1.20E+00 7.19E+01 1.13E+01 6.80E+02 (1) 1-134 2.20E-04 1.56E-01 9.38E+00 1.26E-01 7.55E+00 (1) 1-135 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 1-131 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 I-131 concentrations from section 4.2.

(3)

Per Reference 13, Section 10.4.8.1.5: minimum blowdown flow = 30 gpm. 12756 lb/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 1IA and 12. The equation and parameters describing the secondary coolant activity are given as:

Csg = [LP

CP *453.5924 gm/lb] / [Lb + (2 i* Msg

3600 sec/hr)]

where:

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

µCi/lb Lb, SG blowdown rate (30 gpm) 12756 lb/hr a,;, isotopic decay constant (1/sec)

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

T112 radiological half life per Reference 20. 7v, = 0.693/T112 Noble gases have a partition factor of 1. Thus, there is no resultant activity buildup of noble gases in the secondary coolant system. Any primary to secondary noble gas leakage prior to the MSLB is assumed to have been vented prior to the accident.

D000040-118 Revision 0 Page 12 of 97 5.1.1 (continued)

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

DE I-131 Isotopes Secondary Coolant 60 DE I-131

(µCi/lb)

(1)

Faulted SG Steam Release (lb)

(2)

Partition Factor (3)

Activity Release to the Environment (Ci)

(4) 1-131 7.62E+02 406000 1

3.09E+02 I-132 9.66E+01 406000 1

3.92E+01 I-133 6.80E+02 406000 1

2.76E+02 I-134 7.55E+00 406000 1

3.06E+00 I-135 1.78E+02 406000 1

7.24E+01 Cs-134 2.04E+01 406000 1

8.27E+00 Cs-136 1.97E+01 406000 1

8.00E+00 Cs-137 9.74E+00 406000 1

3.95E+00 Cs-138 1.27E-01 406000 1

5.16E-02 Rb-88 2.78E-01 406000 1

1.13E-01 Br-83 2.84E+00 406000 1

1.15E+00 Br-84 3.26E-01 406000 1

1.32E-01 (1) Previous table (2) Section 4.3 - Mass of steam released from secondary side of faulted steam generator.

(3) Section 3, item 7.

(4) Activity Release to Environment (Ci) = Sec. Coolant Activity (µCi/lbm)

Steam Release (Ibm) / Partition Factor

1.0E-06 Ci/ Ci

D000040-118 Revision 0 Page 13 of 97 5.1.2 0.35 gpm SG Tube Leak - Activity Release 0-2 hr 5.1.2 0.35 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 C U DEI-131 0-2 Hr SG 0-2 Hr 0-2 Hr Primary 0.35 m Tube Leak Activity Partition Factor 1

m Tube Leak (4)

Coolant Mass Release To (5)

Activity Flashed Released Isotopes Conc. (1)

Release (2)

Faulted SG (3)

To Environment

([tci/gin)

(Ibm)

(Ci)

Kr-85m 1.80E+00 350 2.86E-01 1

2.86E-01 Kr.-85 7.60E+00 350 1.21E+00 1

1.21E+00 Kr-87 1.10E+00 350 1.75E-01 1

1.75E-01 Kr-88 3.20E+00 350 5.08E-01 1

5.08E-01 1-131 4.69E+01 350 7.44E+00 I

7.44E+00 1-132 4.85E+01 350 7.69E+00 I

7.69E+00 1-133 7.19E+01 350 1.14E+01 1

1.14E+01 1-134 9.38E+00 350 1.49E+00 1

1.49E+00 1-135 3.75E+01 350 5.96E+00 I

5.96E+00 Xe-131m 2.30E+00 350 3.65E-01 I

3.65E-01 Xe-133m 1.90E+01 350 3.02E+00 1

3.02E+00 Xe-133 2.90E+02 350 4.60E+01 1

4.60E+01 Xe-135m 5.20E-01 350 8.26E-02 I

8.26E-02 Xe-135 8.60E+00 350 1.37E+00 I

1.37E+00 Xe-138 6.40E-01 350 1.02E-01 1

1.02E-01 Cs-134 1.15E+00 350 1.82E-01 I

1.82E-01 Cs-136 1.17E+00 350 1.86E-01 I

1.86E-01 Cs-137 5.47E-01 350 8.68E-02 I

8.68E-02 Cs-138 2.53E-01 350 4.01E-02 1

4.01E-02 Rb-88 9.90E-01 350 1.57E-01 1

1.57E-01 Br-83 1.39E+00 350 2.21E-01 1

2.21E-01 Br-84 6.56E-01 350 1.04E-01 1

1.04E-01 (1) Section 5.1.1 for Iodine, Section 4.2 for others (2) Per Reference 11 gives 1 m = 500.5 lb/hr: 0.35 m = 175 lb/hr, i.e., 2 hr = 350 lb (3) Activity Released (Ci) = Primary Coolant Conc Ci/ m

454 gm/lb

Mass Released lb

1.0E-6 Ci/ Ci (4) Activity Release to Environment (Ci) = Activity Released to Faulted SGs (Ci) / Partition Factor (5) Section 3, item 7

D000040-118 Revision 0 Page 14 of 97 5.1.3 0.35 gpm SG Tube Leak - Activity Release 2 - 8 hr 5.1.3 0.35 m Steam Generator Tube Leak - Activity Release for 2-8 hours Pre-Accident Iodine Spike With RCS Activity At 60 ^tCi/grn DEI-131 2-8 Hr SG 2-8 Hr 2-8Hr Primary 0.35 m Tube Leak Activity Partition Factor Max. Tube Leak (4)

Coolant Mass Release To (5)

Activity Flashed Released Isotopes Conc. (1)

Release (2)

Faulted SGs (3)

To Environment Ci/

lbm (Ci)

(Ci)

Kr-85m 1.80E+00 1050 8.57E-01 1

8.57E-01 Kr-85 7.60E+00 1050 3.62E+00 1

3.62E+00 Kr-87 1.10E+00 1050 5.24E-01 I

5.24E-01 Kr-88 3.20E+00 1050 1.52E+00 1

1.52E+00 1-131 4.69E+01 1050 2.23E+01 I

2.23E+01 1-132 4.85E+01 1050 2.31E+01 1

2.31E+01 1-133 7.19E+01 1050 3.42E+01 I

3.42E+01 1-134 9.38E+00 1050 4.47E+00 1

4.47E+00 1-135 3.75E+01 1050 1.79E+01 1

1.79E+01 Xe-131m 2.30E+00 1050 1.10E+00 1

1.10E+00 Xe-133m 1.90E+01 1050 9.05E+00 I

9.05E+00 Xe-133 2.90E+02 1050 1.38E+02 1

1.38E+02 Xe-135m 5.20E-01 1050 2.48E-01 1

2.48E-01 Xe-135 8.60E+00 1050 4.10E+00 1

4.10E+00 Xe-138 6.40E-01 1050 3.05E-01 1

3.05E-01 Cs-134 1.15E+00 1050 5.46E-01 1

5.46E-01 Cs-136 1.17E+00 1050 5.58E-01 I

5.58E-01 Cs-137 5.47E-01 1050 2.61E-01 I

2.61E-01 Cs-138 2.53E-01 1050 1.20E-01 I

1.20E-01 Rb-88 9.90E-01 1050 4.71E-01 I

4.71E-01 Br-83 1.39E+00 1050 6.63E-01 I

6.63E-01 Br-84 6.56E-01 1050 3.13E-01 I

3.13E-01 (1) Section 4.2 (2) Reference 11 gives 0.35 m = 175 Ibm/hr. 6 hr = 1050 Ibm (3) Activity Released (Ci) = Primary Coolant Cone Ci/ m

454 gm/lb

Mass Released Ib

1.0E-6 Ci/ Ci (4) Activity Release to Environment (Ci) = Activity Released to Faulted SGs (Ci) / Partition Factor (5) Section 3, item 7

D000040-118 Revision 0 Page 15 of 97 5.1.4 0.35 gpm SG Tube Leak - Activity Release 8 - 24 hr 5.1.4 0.35 m Steam Generator Tube Leak -Activity Release for 8-24 hours 8-24 Hr SG 8-24 Hr 8-24 Hr Primary 0.35 m Tube Leak Activity Partition Factor Max. Tube Leak (4)

Coolant Mass Release To (5)

Activity Flashed Released Isotopes Conc. (1)

Release (2)

Faulted SGs (3)

To Environment (Itci/gm) lbni (Ci)

(Ci)

Kr-85m 1.80E+00 2800 2.29E+00 1

2.29E+00 Kr-85 7.60E+00 2800 9.65E+00 1

9.65E+00 Kr-87 1.1.0E+00 2800 1.40E+00 I

1.40E+00 Kr-88 3.20E+00 2800 4.06E+00 1

4.06E+00 1-131 4.69E+01 2800 5.96E+01 1

5.96E+01 1-132 4.85E+01 2800 6.15E+01 I

6.15E+01 1-133 7.19E+01 2800 9.13E+01 I

9.13E+01 1-134 9.38E+00 2800 1.19E+01 1

1.19E+01 1-135 3.75E+01 2800 4.76E+01 1

4.76E+01 Xe-131m 2.30E+00 2800 2.92E+00 1

2.92E+00 Xe-133m 1.90E+01 2800 2.41E+01 1

2.41E+01 Xe-133 2.90E+02 2800 3.68E+02 1

3.68E+02 Xe-135m 5.20E-01 2800 6.60E-01 1

6.60E-01 Xe-135 8.60E+00 2800 1.09E+01 I

1.09E+01 Xe-138 6.40E-01 2800 8.13E-01 I

8.13E-01 Cs-134 1.15E+00 2800 1.46E+00 1

1.46E+00 Cs-136 1.17E+00 2800 1.49E+00 1

1.49E+00 Cs-137 5.47E-01 2800 6.95E-01 1

6.95E-01 Cs-138 2.53E-01 2800 3.21E-01 I

3.21E-01 Rb-88 9.90E-01 2800 1.26E+00 I

1.26E+00 Br-83 1.39E+00 2800 1.77E+00 1

1.77E+00 Br-84 6.56E-01 2800 8.34E-01 1

8.34E-01 (1) Section 4.2 (2) Reference 1.1 gives 0.35 m = 175 lbm/hr. 16 hr = 2800 Ibm (3) Activity Released (Ci) = Primary Coolant Conc (^tCi/gm)

454 gm/lb

Mass Released lb

1.0E-6 Ci/ Ci (4) Activity Release to Environment (Ci) = Activity Released to Faulted SGs (Ci) / Partition Factor (5) Section 3, item 7

D000040-118 Revision 0 Page 16 of 97 5.1.5 0.65 gpm 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 5.1.5 0.65 g m Steam Generator Tube Leak - Activity Release for 0 - 2 hrs Pre-Accident Iod ine Spike - RCS Activity At 6 0 Ci/ m DEI-131 Isotopes Primary Coolant (1) 0-2 hr SG 0.65 gpm Tube Leak Mass Release (2)

Activity Release to Intact SG (3)

Partition Factor (6) 0.65 gpm Tube Leak Activity Released to Environs (4)

Activity Remaining in SG (5)

(gci/gm) lbm (Ci)

(Ci)

Kr-85m 1.80E+00 650 5.31E-01 1

5.31E-01 0.00E+00 Kr-85 7.60E+00 650 2.24E+00 1

2.24E+00 0.00E+00 Kr-87 1.10E+00 650 3.24E-01 1

3.24E-01 0.00E+00 Kr-88 3.20E+00 650 9.43E-01 I

9.43E-01 0.00E+00 I-131 4.69E+01 650 1.38E+01 100 1.38E-01 1.37E+01 I-132 4.85E+01 650 1.43E+01 100 1.43E-01 1.41E+01 I-133 7.19E+01 650 2.12E+01 100 2.12E-01 2.10E+01 I-134 9.38E+00 650 2.77E+00 100 2.77E-02 2.74E+00 I-135 3.75E+01 650 1.11E+01 100 1.11E-01 1.09E+01 Xe-131m 2.30E+00 650 6.78E-01 1

6.78E-01 0.00E+00 Xe-133m 1.90E+01 650 5.60E+00 1

5.60E+00 0.00E+00 Xe-133 2.90E+02 650 8.55E+01 1

8.55E+01 0.00E+00 Xe-135m 5.20E-01 650 1.53E-01 1

1.53E-01 0.00E+00 Xe-135 8.60E+00 650 2.54E+00 1

2.54E+00 0.00E+00 Xe-138 6.40E-01 650 1.89E-01 1

1.89E-01 0.00E+00 Cs-134 1.15E+00 650 3.38E-01 100 3.38E-03 3.35E-01 Cs-136 1.17E+00 650 3.46E-01 100 3.46E-03 3.42E-01 Cs-137 5.47E-01 650 1.61E-01 100 1.61E-03 1.60E-01 Cs-138 2.53E-01 650 7.45E-02 100 7.45E-04 7.38E-02 Rb-88 9.90E-01 650 2.92E-01 100 2.92E-03 2.89E-01 Br-83 1.39E+00 650 4.10E-01 100 4.10E-03 4.06E-01 Br-84 6.56E-01 650 1.94E-01 100 1.94E-03 1.92E-01 (1) Section 5.1.1 for Iodine, Section 4.2 for others (2) Per Reference 11: 0.65 m = 325 lb/hr, i.e., 2 hr = 650 lb (3) Activity Released (Ci) = Primary Coolant Conc (gCi/gm)

454 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) 0-2 hr Activity Remaining in SG = Activity Release to SG (Ci) - Activity Released to Environs (Ci)

(6) Section 3, item 13

D000040-1 1 8 Revision 0 Page 17 of 97 5.1.6 0.65 gpm Steam Generator Tube Leak - Activity Release for 2 - 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 5.1.6 0.65 m Steam Generator Tube Leak - Activity Re lease for 2-8 hrs Pre-Accident Iodine Spike - RCS Activity At 60 Ci/ m DEI-131 Isotopes Primary Coolant (1) 2-8 hr SG 0.65 gpm Tube Leak Mass Release (2)

Activity Release to Intact SG Partition Factor (6) 0.65 gpm Tube Leak Activity Released to Environs (4)

Activity Remaining in SG (5)

Ci/ m lbm (Ci)

(Ci)

Kr-85m 1.80E+00 1950 1.59E+00 1

1.59E+00 0.00E+00 Kr-85 7.60E+00 1950 6.72E+00 1

6.72E+00 0.00E+00 Kr-87 1.10E+00 1950 9.73E-01 1

9.73E-01 0.00E+00 Kr-88 3.20E+00 1950 2.83E+00 1

2.83E+00 0.00E+00 1-131 4.69E+01 1950 4.15E+01 100 4.15E-01 4.11E+01 1-132 4.85E+01 1950 4.29E+01 100 4.29E-01 4.24E+01 1-133 7.1.9E+01 1950 6.36E+01 100 6.36E-01 6.30E+01 1-134 9.38E+00 1950 8.30E+00 100 8.30E-02 8.21E+00 1-135 3.75E+01 1950 3.32E+01 100 3.32E-01 3.28E+01.

Xe-131m 2.30E+00 1950 2.03E+00 1

2.03E+00 0.00E+00 Xe-133m 1.90E+01 1950 1.68E+01 1

1.68E+01 0.00E+00 Xe-133 2.90E+02 1950 2.57E+02 1

2.57E+02 0.00E+00 Xe-135m 5.20E-01 1950 4.60E-01 1

4.60E-01 0.00E+00 Xe-135 8.60E+00 1950 7.61E+00 1

7.61E+00 0.00E+00 Xe-138 6.40E-01 1950 5.66E-01 1

5.66E-01 0.00E+00 Cs-134 1.15E+00 1950 1.01E+00 100 1.01E-02 1.00E+00 Cs-136 1.17E+00 1950 1.04E+00 100 1.04E-02 1.03E+00 Cs-137 5.47E-01 1950 4.84E-01 100 4.84E-03 4.79E-01 Cs-138 2.53E-01 1950 2.24E-01 100 2.24E-03 2.21E-01 Rb-88 9.90E-01 1950 8.76E-01 100 8.76E-03 8.67E-01 Br-83 1.39E+00 1950 1.23E+00 100 1.23E-02 1.22E+00 Br-84 6.56E-01 1950 5.81E-01 100 5.81E-03 5.75E-01 (1) Section 5.1.1 for Iodine, Section 4.2 for others (2) Per Reference 11: 0.65 m = 325 lb/hr, i.e., 6 hr = 1950 lb (3) Activity Released (Ci) = Primary Coolant Cone (^tCi/gm)

454 gm/lb

Mass Released (lb)

1.0E-6 Ci/ Ci (4) Activity Release to Environment (Ci) = Activit y Released to Intact SGs Ci / Partition Factor (5) 2-8 hr Activity Remaining in SG = Activity Release to SG (Ci) - Activity Released to Environs (Ci)

(6) Section 3, item 13

D000040-1 1 8 Revision 0 Page 18 of 97 5.1.7 0.65 gpm Steam Generator Tube Leak - Activity Release for 8 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 5.1.7 0.65 m Steam Generator Tube Leak - Activity Release for 8-24 hrs Pre-Accident Iodi ne Spike - RCS Activity At 60 Ci/ m DEI-131 Isotopes Primary Coolant (1) 8-24 hr SG 0.65 gpm Tube Leak Mass Release (2) 8-24 hr Activity Release to Intact SG (3)

Partition Factor (6) 0.65 gpm Tube Leak Activity Released to Environs (4)

Activity Remaining in SG (5)

Ci/ m (Ibm)

(Ci)

Kr-85m 1.80E+00 5200 4.25E+00 1

4.25E+00 0.00E+00 Kr-85 7.60E+00 5200 1.79E+01 1

1.79E+01 0.00E+00 Kr-87 1.10E+00 5200 2.59E+00 I

2.59E+00 0.00E+00 Kr-88 3.20E+00 5200 7.55E+00 1

7.55E+00 0.00E+00 1-131 4.69E+01 5200 1.11E+02 100 1.11E+00 1.09E+02 1-132 4.85E+01 5200 1.14E+02 100 1.14E+00 1.1.3E+02 1-133 7.19E+01 5200 1.70E+02 100 1.70E+00 1.68E+02 1-134 9.38E+00 5200 2.21E+01 100 2.21E-01 2.19E+01 1-135 3.75E+01 5200 8.85E+01 100 8.85E-01 8.76E+01 Xe-131m 2.30E+00 5200 5.42E+00 I

5.42E+00 0.00E+00 Xe-133m 1.90E+01 5200 4.48E+01 I

4.48E+01 0.00E+00 Xe-133 2.90E+02 5200 6.84E+02 I

6.84E+02 0.00E+00 Xe-135m 5.20E-01 5200 1.23E+00 1

1.23E+00 0.00E+00 Xe-135 8.60E+00 5200 2.03E+01 I

2.03E+01 0.00E+00 Xe-138 6.40E-01 5200 1.51E+00 1

1.51E+00.

0.00E+00 Cs-134 1.15E+00 5200 2.70E+00 100 2.70E-02 2.68E+00 Cs-136 1.17E+00 5200 2.77E+00 100 2.77E-02 2.74E+00 Cs-137 5.47E-01 5200 1.29E+00 100 1.29E-02 1.28E+00 Cs-138 2.53E-01 5200 5.96E-01 100 5.96E-03 5.90E-01 Rb-88 9.90E-01 5200 2.33E+00 100 2.33E-02 2.31E+00 Br-83 1.39E+00 5200 3.28E+00 100 3.28E-02 3.25E+00 Br-84 6.56E-01 5200 1.55E+00 100 1.55E-02 1.53E+00 1

Section 5.1.1 for Iodine, Section 4.2 for others (2) Per Reference 11: 0.65 m = 325 lb/hr, i.e., 16 hr = 5200 lb (3) Activity Released (Ci) = Primary Coolant Cone (gCi/gm)

454 gm/lb

Mass Released lb

LOE-6 Ci/ Ci (4) Activity Release to Environment (Ci) = Activity Released to Intact SGs (Ci) / Partition Factor (5) 8-24 hr Activity Remaining in SG = Activity Release to SG (Ci) - Activity Released to Environs (Ci)

(6) Section 3, item 13

D000040-1 1 8 Revision 0 Page 19 of 97 5.1.8 Secondary Coolant Activity Release from Intact SGs 5.1.8 Secondary Coolant Activity Release from Intact SG 60 uCi/ m DE I-131 Isotopes Secondary Coolant 60 DE I-131 uCi/lb 1 Intact SG Steam Release lb (2)

Partition Factor (6) 0-2 Hr Release to Environment Ci (3) 0-30 min Release to Environment Ci (4) 30 min-2 Hr Release to Environment Ci (5) 0-2hrs 1-131 7.62E+02 343700 100 2.62E+00 6.55E-01 1.96E+00 1-132 9.66E+01 343700 100 3.32E-01 8.30E-02 2.49E-01 1-133 6.80E+02 343700 100 2.34E+00 5.84E-01 1.75E+00 1-134 7.55E+00 343700 100 2.59E-02 6.49E-03 1.95E-02 1-135 1.78E+02 343700 100 6.13E-01 1.53E-01 4.60E-01 Cs-134 2.04E+01 343700 100 7.00E-02 1.75E-02 5.25E-02 Cs-136 1.97E+01 343700 100 6.77E-02 1.69E-02 5.08E-02 Cs-137 9.74E+00 343700 100 3.35E-02 8.37E-03 2.51E-02 Cs-138 1.27E-01 343700 100 4.36E-04 1.09E-04 3.27E-04 Rb-88 2.78E-01 343700 100 9.57E-04 2.39E-04 7.18E-04 Br-83 2.84E+00 343700 100 9.75E-03 2.44E-03 7.31E-03 Br-84 3.26E-01 343700 100 1.12E-03 2.80E-04 8.40E-04 2-8Hr 2-8 Hr Release Ci 8-24 hr Release (2) 8-24 Hr Release to Environment Ci (3) 1-131 7.62E+02 733900 100 5.59E+00 1200000 9.14E+00 1-132 9.66E+01 733900 100 7.09E-01 1200000 1.16E+00 1-133 6.80E+02 733900 100 4.99E+00 1200000 8.16E+00 1-134 7.55E+00 733900 100 5.54E-02 1200000 9.06E-02 1-135 1.78E+02 733900 100 1.31E+00 1200000 2.14E+00 Cs-134 2.04E+01 733900 100 1.50E-01 1200000 2.45E-01 Cs-136 1.97E+01 733900 100 1.45E-01 1200000 2.37E-01 Cs-137 9.74E+00 733900 100 7.14E-02 1200000 1.17E-01 Cs-138 1.27E-01 733900 100 9.32E-04 1200000 1.52E-03 Rb-88 2.78E-01 733900 100 2.04E-03 1200000 3.34E-03 Br-83 2.84E+00 733900 100 2.08E-02 1200000 3.40E-02 Br-84 3.26E-01 733900 100 2.39E-03 1200000 3.91E-03 (1) Section 5.1.2 (2) Section 4.3 - Mass of steam releases from intact SG (3) Activity Release to Environment (Ci) = Secondary Coolant Ci/lb

Steam Release lb / Partition Factor/ 1.0E06 Ci/Ci (4) 0-30 min Release = 0-2 hr Release

0.25 (5) 30 min - 2 hr Release = 0-2 hr Release

0.75 (6) Section 3, item 13

D000040-118 Revision 0 Page 20 of 97 5.1.9 Pre-Existing Total Activity Released 0 - 2 hrs 5.1.9 Pre-Accident Total Act ivity Released 0 - 2 hrs 5.1.1 5.1.2 5.1.5 5.1.8 (1)

(2)

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

Faulted SG 0.35 gpm Tube Leak 0-2 hr (Ci)

Intact SG 0.65 gpm Tube Leak 0-2 hr (Ci)

Intact SG Secondary Coolant Release 0-2 hr (Ci) 0-2 Hr Total Activity Release (Ci) (1) 0-30 min Total Activity Release (Ci) (2) 30 min-2 Hr Total Activity Release (Ci) (3)

Kr-85m 0

2.86E-01 5.31 E-01 0

8.16E-01 2.04E-01 6.12E-01 Kr-85 0

1.21E+00 2.24E+00 0

3.45E+00 8.62E-01 2.59E+00 Kr-87 0

1.75E-01 3.24E-01 0

4.99E-01 1.25E-01 3.74E-01 Kr-88 0

5.08E-01 9.43E-01 0

1.45E+00 3.63E-01 1.09E+00 I-131 3.09E+02 7.44E+00 1.38E-01 2.62E+00 3.19E+02 3.12E+02 7.65E+00 1-132 3.92E+01 7.69E+00 1.43E-01 3.32E-01 4.74E+01 4.13E+01 6.13E+00 I-133 2.76E+02 1.14E+01 2.12E-01 2.34E+00 2.90E+02 2.79E+02 1.05E+01 I-134 3.06E+00 1.49E+00 2.77E-02 2.59E-02 4.61E+00 3.45E+00 1.16E+00 I-135 7.24E+01 5.96E+00 1.11E-01 6.1.3E-01 7.91E+01 7.41E+01 5.01E+00 Xe-131m 0

3.65E-01 6.78E-01 0

1.04E+00 2.61E-01 7.82E-01 Xe-133m 0

3.02E+00 5.60E+00 0

8.62E+00 2.15E+00 6.46E+00 Xe-133 0

4.60E+01 8.55E+01 0

1.32E+02 3.29E+01 9.87E+01 Xe-135m 0

8.26E-02 1.53E-01 0

2.36E-01 5.90E-02 1.77E-01 Xe-135 0

1.37E+00 2.54E+00 0

3.90E+00 9.75E-01 2.93E+00 Xe-138 0

1.02E-01 1.89E-01 0

2.90E-01 7.26E-02 2.18E-01 Cs-134 8.27E+00 1.82E-01 3.38E-03 7.00E-02 8.53E+00 8.34E+00 1.92E-01 Cs-136 8.00E+00 1.86E-01 3.46E-03 6.77E-02 8.26E+00 8.07E+00 1.93E-01 Cs-137 3.95E+00 8.68E-02 1.61E-03 3.35E-02 4.07E+00 3.98E+00 9.14E-02 Cs-138 5.16E-02 4.01 E-02 7.45E-04 4.36E-04 9.28E-02 6.19E-02 3.10E-02 Rb-88 1.13E-01 1.57E-01 2.92E-03 9.57E-04 2.74E-01 1.53E-01 1.21E-01 Br-83 1.15E+00 2.21E-01 4.10E-03 9.75E-03 1.39E+00 1.21E+00 1.76E-01 Br-84 1.32E-01 1.04E-01 1.94E-03 1.12E-03 2.40E-01 1.59E-01 8.05E-02 (1) = Sum of columns 5.1.1 + 5.1.2 + 5.1.5 + 5.1.8 (2) = Sum of column 5.1.1 + [0.25 * (column 5.1.2 + 5.1.5 + 5.1.8 3 = 1 2

D000040-118 Revision 0 Page 21 of 97 5.1.10 Pre-Existing Spike Total Activity Released 2 - 8 hrs 5.1.10 Pre-Existin g Spike Total Activity Released 2 - 8 hrs 1.0 m

5.1.3 5.1.6 5.1.8 (1)

(2)

Isotopes 2-8 hr Faulted SG Rupture Release (Ci) 2-8 hr Intact SG Rupture Release (Ci) 2-8 hr Intact SG Secondary Coolant Release (Ci) 2-8 Hr Total Activity Release (Ci) (1) 0-8 Hr Total Activity Release (Ci) (2)

Kr-85m 8.57E-01 1.59E+00 0

2.45E+00 3.27 Kr-85 3.62E+00 6.72E+00 0

1.03E+01 13.79 Kr-87 5.24E-01 9.73E-01 0

1.50E+00 2.00 Kr-88 1.52E+00 2.83E+00 0

4.35E+OO 5.81 1-131 2.23E+01 4.15E-01 5.59E+00 2.83E+01 347.80 1-132 2.31E+O1 4.29E-01 7.09E-01 2.42E+01 71.61 1-133 3.42E+01 6.36E-01 4.99E+00 3.99E+01 329.76 1-134 4.47E+00 8.30E-02 5.54E-02 4.60E+00 9.21 1-135 1.79E+01 3.32E-01 1.31E+00 1.95E+01 98.58 Xe-131m 1.10E+00 2.03E+00 0

3.13E+00 4.17 Xe-133m 9.05E+00 1.68E+01 0

2.59E+01 34.47 Xe-133 1.38E+02 2.57E+02 0

3.95E+02 526.17 Xe-135m 2.48E-01 4.60E-01 0

7.08E-01 0.94 Xe-135 4.10E+00 7.61E+00 0

1.17E+01 15.60 Xe-138 3.05E-01 5.66E-01 0

8.71 E-01 1.16 Cs-134 5.46E-01 1.01E-02 1.50E-01 7.06E-01 9.23 Cs-136 5.58E-01 1.04E-02 1.45E-01 7.13E-01 8.97 Cs-137 2.61 E-01 4.84E-03 7.14E-02 3.37E-01 4.41 Cs-138 1.20E-01 2.24E-03 9.32E-04 1.24E-01 0.22 Rb-88 4.71E-01 8.76E-03 2.04E-03 4.82E-01 0.76 Br-83 6.63E-0I 1.23E-02 2.08E-02 6.96E-01 2.08 Br-84 3.13 E-0I 5.81E-0 3 2.39E-03 3.21 E-01 0.56 (1) Sum of columns 5.1.3 + 5.1.6 + 5.1.8 (2) Sum of 1 +0 - 2 hr total from 5.1.9

D000040-118 Revision 0 Page 22 of 97 5.1.11 Pre-Existing Spike Total Activity Released 5.1.11 Pre-Existin Spike Total Activity Released 8 - 24 hrs 5.1.4 5.1.7 (1)

(2)

Isotopes 8-24 hr Faulted SG Rupture Release Ci 8-24 hr Intact SG Rupture Release Ci 8-24 Hr Total Activity Release (Ci) (1) 0-24 Hr Total Activity Release (Ci) (2)

Kr-85m 2.29E+00 4.25E+00 6.53E+00 9.8 Kr-85 9.65E+00 1.79E+01 2.76E+01 41.4 Kr-87 1.40E+00 2.59E+00 3.99E+00 6.0 Kr-88 4.06E+00 7.55E+00 1.16E+01 17.4 I-131 5.96E+01 1.11E+00 6.07E+01 417.6 I-132 6.15E+01 1.14E+00 6.27E+01 135.4 1-133 9.13E+01 1.70E+00 9.30E+01 430.9 I-134 1.19E+01 2.21E-01 1.21E+01 21.4 I-135 4.76E+01 8.85E-01 4.85E+01 149.2 Xe-131m 2.92E+00 5.42E+00 8.35E+00 12.5 Xe-133m 2.41E+01 4.48E+01 6.89E+01 103.4 Xe-133 3.68E+02 6.84E+02 1.05E+03 1578.5 Xe-135m 6.60E-01 1.23E+00 1.89E+00 2.8 Xe-135 1.09E+01 2.03E+01 3.12E+01 46.8 Xe-138 8.13E-01 1.51E+00 2.32E+00 3.5 Cs-134 1.46E+00 2.70E-02 1.48E+00 11.0 Cs-136 1.49E+00 2.77E-02 1.52E+00 10.7 Cs-137 6.95E-01 1.29E-02 7.08E-01 5.2 Cs-138 3.21E-01 5.96E-03 3.27E-01 0.5 Rb-88 1.26E+00 2.33E-02 1.28E+00 2.0 Br-83 1.77E+00 3.28E-02 1.80E+00 3.9 Br-84 8.34E-01 1.55E-02 8.49E-01 1.4 (1) = Sum of columns 5.1.4 + 5.1.7 + 5.1.7 2 = 0- 8 hr total release 5.1.10 + 8 - 24 hr total release 5.1.11 + 8 - 24 hr total release 5.1.8

D000040-118 Revision 0 Page 23 of 97 5.1.12 Pre-Existing Spike Fraction of Total Activity Released 5.1.12 Pre-Accident Spike Fraction of Total Activity Released Isotopes Time Period Release By Species 0-30 min 30 min-2 hr 2-8 hr 8-24 hr 0-30 min 30 min-2 hr 2-8 hr 8-24 hr (1)

(2)

(3)

(4)

Kr-85m 2.08E-02 6.25E-02 2.50E-01 6.67E-01 Nobles 2.08E-02 6.25E-02 2.50E-01 6.67E-01 Kr-85 2.08E-02 6.25E-02 2.50E-01 6.67E-01 Kr-87 2.08E-02 6.25E-02 2.50E-01 6.67E-01 Kr-88 2.08E-02 6.25E-02 2.50E-01 6.67E-01 1-131 7.47E-01 1.83E-02 6.79E-02 1.45E-01 Iodine 7.47E-01 1.83E-02 6.79E-02 1.45E-01 1-132 3.05E-01 4.52E-02 1.79E-01 4.63E-01 1-133 6.48E-01 2.43E-02 9.25E-02 2.16E-01 1-134 1.61E-01 5.40E-02 2.15E-01 5.66E-01 1-135 4.96E-01 3.36E-02 1.31 E-01 3.25E-01 Xe-131m 2.08E-02 6.25E-02 2.50E-01 6.67E-01 Xe-133m 2.08E-02 6.25E-02 2.50E-01 6.67E-01.

Xe-133 2.08E-02 6.25E-02 2.50E-01 6.67E-01 Xe-135m 2.08E-02 6.25E-02 2.50E-01 6.67E-01 Xe-135 2.08E-02 6.25E-02 2.50E-01 6.67E-01 Xe-138 2.08E-02 6.25E-02 2.50E-01 6.67E-01 Cs-134 7.61E-01 1.75E-02 6.44E-02 1.35E-01 Cesium 7.61E-01 1.75E-02 6.44E-02 1.35E-01 Cs-136 7.52E-01 1.80E-02 6.65E-02 1.41E-01 Cs-137 7.61E-01 1.75E-02 6.43E-02 1.35E-01 Cs-138 1.1.4E-01 5.69E-02 2.27E-01 6.00E-01 Rb-88 7.51E-02 5.92E-02 2.36E-01 6.28E-01 Same as Cesium Br-83 3.09E-01 4.50E-02 1.78E-01 4.60E-01 Same as Iodine Br-84 1.13E-01 5.69E-02 2.27E-01 6.01E-01 (1): 0-30 min Fraction = 0-30 min release (5.1.9) / 0-24hr release 5.1.11 (2): 30 min-2hr Fraction = 30 min-2 hr release (5.1.9) / 0-24 hr release 5.1.11 (3): 2-8 hr Fraction = 2-8 hr release (5.1.10) / 0-24 hr release 5.1.11 (4): 8-24 hr Fraction = 8-24 hr release (5.1.11 / 0-24 hr release 5.1.11

D000040-118 Revision 0 Page 24 of 97 5.2 Source Term with Concurrent Iodine Spike The source term for the concurrent spike includes the following:

1 Activity in secondary coolant released from faulted SG.

2 Activity in reactor coolant released due to 035 gpm tube leak in faulted SG (0 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ).

3 Activity in reactor coolant released due to 0.35 gpm tube leak in faulted SG (2 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ).

4 Activity in reactor coolant released due to 0.35 gpm tube leak in faulted SG (8 to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ).

5 Activity in reactor coolant released due to 065 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 ).

6 Activity in reactor coolant released due to 065 gpm tube leak in intact SG (2 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ).

7 Activity in reactor coolant released due to 065 gpm tube leak in intact SG (8 to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ).

8 Activity in secondary coolant released from intact SG.

The activity releases are determined in sections 5.2.1 through 5.2.12 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 I-131 values based on letdown flows of 60 gpm and 143 gpm and a factor 500 for the spiking release rate. The case with RC concentrations based on letdown of 143 gpm and the 1 µCi/gm DE I-131 values based on letdown flow of 143 gpm provides the limiting case for calculating radiological consequences. The average RC iodine concentrations for this case per Reference 4, page 38 are given as follows:

Maximum Letdown of 143 gpm w/ 143 gpm 1 µCi/gm DE 1-131 Values Factor of 500 times Iodine Release Rate Iodine Average RC Concentration Ci/ m 0-30 min 0-2hr 30 min-2hr 2-8hr 8-24hr I-131 21.9 84.8 105.8 417.6 646.2 I-132 93.7 322.7 399 970.7 247.1 I-133 41.6 159.6 199 740.2 883.9 I-134 39.6 112.7 137 216.2 17.8 I-135 37.9 141.8 176.4 575.9 403.1 As stated earlier, the noble gas concentrations will correspond to the 1% 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.

D000040-118 Revision 0 Page 25 of 97 5.2.1 Secondary Coolant Activity Based on Reactor Coolant with 1% Failed Fuel Secondary coolant specific activity based on 1% RC Activity LB Conservative Low SG Blowdown (3) =

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

340000 Ibm L,

Leak Rate =

1.0 m =

500.50130341bm/hr Decay RC Concentration Sec. Coolant E q. Conc for I m leak Isotopes Constant 1% FF 1% FF (4)

(1/sec)

(^tci/grn)

Ci/lbm (1) 1-131 9.96E-07 3.00E+00 4.87E+01 (2)

Cs-134 1.07E-08 4.40E+00 7.82E+01 (2)

Cs-136 6.09E-07 4.50E+00 7.57E+01 (2)

Cs-137 7.28E-10 2.1.0E+00 3.74E+01 (2)

Cs-138 3.59E-04 9.70E-01 4.87E-01 (2)

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

Br-83 8.05E-05 8.90E-02 1.81E-01 (2)

Br-84 3.63E-04 4.20E-02 2.08E-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 lb/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 5.1.1.

D000040-118 Revision 0 Page 26 of 97 5.2.1 (continued)

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

Ci/ m DE 1-131 secondary activity 1% Failed Fuel Tech Spec Secondary System DE 1-131 0.1 Ci/ m DE 1-131 Isotope Specific Activity Factor in Secondary Coolant Ci/lb 0.1 µCi/gm /0.124 pCi/grn = 0.806 (3)

Ci/lb (4) 1-131(l) 4.87E+01 3.93E+01 1-132(l) 2.90E-02 1-133 (1) 5.74E+00 1-134(l) 4.07E-04 1-135 (1) 2.59E-01 Cs-134 (2) 7.82E+01 0.806 6.31E+01 Cs-136 (2) 7.57E+01 0.806 6.10E+01 Cs-137 2 3.74E+01 0.806 3.01E+01 Cs-138 (2) 4.87E-01 0.806 3.93E-01 Rb-88 (2) 1.07E+00 0.806 8.62E-01 Br-83 (2) 1.81E-01 0.806 1.46E-01 Br-84 (2) 2.08E-02 0.806 1.68E-02 (1) Iodine activities per Reference 4, page 13 and Reference 4, Attachment 4.

(2) Values provided in preceding table.

(3) Per Reference 4, Attachment 4: 0.124 = Total DE-131 in secondary coolant based on secondary coolant specific activity with the RC @ 1% failed fuel conditions and 0.1 µCi/gm DE 1-131 is the Technical Specification limit in the secondary coolant (Section 3, item 6).

(4) Per Reference 4, page 14 for iodine. The other isotopes are assumed to be directly proportional to the 0.1 µCi/gm DE 1-131 secondary coolant factor of 0.806 per Reference 4, page 13.

D000040-118 Revision 0 Page 27 of 97 5.2.1 (continued)

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

DE 1-131 Sec. Coolant Faulted Sp. Activity Faulted SG at 0.1 SG Iodine Isotopes Ci/

Steam Partition Release Released DE I-131.1 Release (2)

Factor to Environment (4)

Ci/lbm (Ibm)

(3)

(Ci)

I-131 3.93E+01 4.06E+05 1

1.59E+01.

I-132 2.90E-02 4.06E+05 1

1.18E-02 I-133 5.74E+00 4.06E+05 1

2.33E+00 I-134 4.07E-04 4.06E+05 1

1.65E-04 1-135 2.59E-01 4.06E+05 1

1.05E-01 Cs-134 6.31E+01 4.06E+05 1

2.56E+01 Cs-136 6.1.0E+01 4.06E+05 1

2.48E+01 Cs-137 3.01E+01 4.06E+05 I

1.22E+01 Cs-138 3.93E-01 4.06E+05 I

1.59E-01.

Rb-88 8.62E-01 4.06E+05 1

3.50E-01 Br-83 1.46E-01 4.06E+05 1

5.94E-02 Br-84 1.68E-02 4.06E+05 I

6.82E-03 (1) Preceding Table (2) Section 4.3 (3) Section 3, item 7.

(4) Activity Release to Environment (Ci) = Sec. Coolant Activity Ci/Ibm

Steam Release Ibm / Partition Factor / I.OE-06 Ci/ Ci

D000040-118 Revision 0 Page 28 of 97 5.2.2 0.35 gpm SG Tube Leak - Activity Release 0-2 hr 5.2.2 Concurrent Iodine Spike With Initial RC ctivity at 1 Ci/ m DE 1-1310.35 m Tube Leak Reactor Coolant 0-2 hr SG 0-2 hr 0-2 hr 0-30 min 30 min-2hr 0-120 Min.

0.35 m Tube Leak Activity Activity Activity Activity Specific Mass Release To Partition Factor Released Released Released Isotopes Activity (1)

Release (2)

Faulted SG (3)

'(7)

To Environ. (4)

To Environ. (5)

To Environ. (6)

Ci/ m ibm (Ci)

(Ci)

Kr-85m 1.80E+00 350 2.86E-01 1

2.86E-01 7.14E-02 2.14E-01 Kr-85 7.60E+00 350 1.21E+00 1

1.21E+00 3.02E-01 9.05E-01 Kr-87 1.10E+00 350 1.75E-01 I

1.75E-01 4.37E-02 1.31E-01 Kr-88 3.20E+00 350 5.08E-01 I

5.08E-01 1.27E-01 3.81E-01 1-131 8.48E+01 350 1.35E+01 1

1.35E+01 3.37E+00 1.01E+01 1-132 3.23E+02 350 5.12E+01 1

5.12E+01 1.28E+01 3.84E+01 1-133 1.60E+02 350 2.53E+01 1

2.53E+01 6.33E+00 1.90E+01 1-134 1.13E+02 350 1.79E+01 I

1.79E+01 4.47E+00 1.34E+01 1-135 1.42E+02 350 2.25E+01 1

2.25E+01 5.63E+00 1.69E+01 Xe-131m 2.30E+00 350 3.65E-01 1

3.65E-01 9.13E-02 2.74E-01 Xe-133m 1.90E+01 350 3.02E+00 1

3.02E+00 7.54E-01 2.26E+00 Xe-133 2.90E+02 350 4.60E+01 1

4.60E+01 1.15E+01 3.45E+01 Xe-135m 5.20E-01 350 8.26E-02 1

8.26E-02 2.06E-02 6.19E-02 Xe-135 8.60E+00 350 1.37E+00 1

1.37E+00 3.41E-01 1.02E+00 Xe-138 6.40E-01 350 1.02E-01 1

1.02E-01 2.54E-02 7.62E-02 Cs-134 1.15E+00 350 1.82E-01 1

1.82E-01 4.55E-02 1.36E-01 Cs-136 1.17E+00 350 1.86E-01 1

1.86E-01 4.65E-02 1.40E-01 Cs-137 5.47E-01 350 8.68E-02 1

8.68E-02 2.17E-02 6.51E-02 Cs-138 2.53E-01 350 4.01E-02 1

4.01E-02 1.00E-02 3.01E-02 Rb-88 9.90E-01 350 1.57E-01 1

1.57E-01 3.93E-02 1.18E-01 Br-83 2.32E-02 350 3.68E-03 I

3.68E-03 9.20E-04 2.76E-03 Br-84 1.09E-02 350 1.74E-03 1

1.74E-03 4.34E-04 1.30E-03 (1) Section 5.2 for iodine, Ref. 6 RADM Table 5-15 for others.

(2) Per Reference 110.35 m = 175 lb/hr, i.e., 2 hr = 350 lb (3) Activity Released (Ci) = Primary Coolant Conc ([tCi/gm)

454 gm/lb

Mass Released Ib

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

0.25 (6) 30 min - 2 hr Activity Released = 0-2 hr Activity Released

0.75 (7) Section 3, item 7

D000040-118 Revision 0 Page 29 of 97 5.2.3 0.35 gpm SG Tube Leak - Activity Release 2 - 8 hr 5.2.3 Concurrent Iodine With Initial RC Act' vi at 1 Ci/ m DE 1-131 Reactor 2-8 hr.

Coolant 2-8 hr SG 2-8 hr Ruptured 2-8 hr.

0.35 m Tube Activity Activity Specific Leak Mass Release To Partition Factor Released Isotopes Activity (1)

Release (2)

Faulted SG (3)

(5)

To Environ. (4)

Ci/ m lbm (Ci)

(Ci)

Kr-85m 1.80E+00 1050 8.57E-01 I

8.57E-01 Kr-85 7.60E+00 1050 3.62E+00 1

3.62E+00 Kr-87 1.10E+00 1050 5.24E-01 1

5.24E-01 Kr-88 3.20E+00 1050 1.52E+00 I

1.52E+00 I-131 4.18E+02 1050 1.99E+02 1

1.99E+02 I-132 9.71E+02 1050 4.62E+02 1

4.62E+02 1-133 7.40E+02 1050 3.53E+02 3.53E+02 I-134 2.16E+02 1050 1.03E+02 I

1.03E+02 I-135 5.76E+02 1050 2.74E+02 1

2.74E+02 Xe-131m 2.30E+00 1050 1.10E+00 1

1.10E+00 Xe-133m 1.90E+01 1050 9.05E+00 1

9.05E+00 Xe-133 2.90E+02 1050 1.38E+02 1.38E+02 Xe-135m 5.20E-01 1050 2.48E-01 1

2.48E-01 Xe-135 8.60E+00 1050 4.10E+00 4.10E+00 Xe-138 6.40E-01 1050 3.05E-01 1

3.05E-01 Cs-134 1.15E+00 1050 5.46E-01 1

5.46E-01 Cs-136 1.17E+00 1050 5.58E-01 I

5.58E-01 Cs-137 5.47E-01 1050 2.61E-01 1

2.61E-01 Cs-138 2.53E-01 1050 1.20E-01 1

1.20E-01 Rb-88 9.90E-01 1050 4.71E-01 1

4.71E-01 Br-83 2.32E-02 1050 1.10E-02 1

1.10E-02 Br-84 1.09E-02 1050 5.21E-03 1

5.21E-03 (1) Section 5.2 for iodine, Ref. 6 RADM Table 5-15 for others (2) Per Reference 11 0.35 m = 175 lb/hr, i.e., 6 hr = 1050 lb (3) Activity Released (Ci) = Primary Coolant Conc (gCi/gin)

454 gm/lb

Mass Released lb

1.0E-6 Ci/ Ci (4) Activity Release to Environment (Ci) = Activity Released to Faulted SGs (Ci) / Partition Factor (5) Section 3, item 7

D000040-118 Revision 0 Page 30 of 97 5.2.4 0.35 gpm SG Tube Leak - Activity Release 8 - 24 hr 5.2.4 Concurrent Iodine With Initial RC Activity at 1 Ci/ m DE I -131 Reactor 8 - 24 hr Coolant 8 - 24 hr 8 - 24 hr Ruptured 8 - 24 hr 0.35 m Tube Activity Activity Specific Leak Mass Release To Partition Factor Released Isotopes Activity (1)

Release (2)

Faulted SG (3)

(5)

To Environ. 4

(^Ici/gm)

(Ibm)

(Ci)

Kr-85m 1.80E+00 2800 2.29E+00 1

2.29E+00 Kr-85 7.60E+00 2800 9.65E+00 1

9.65E+00 Kr-87 1.10E+00 2800 1.40E+00 1

1.40E+00 Kr-88 3.20E+00 2800 4.06E+00 1

4.06E+00 1-131 6.46E+02 2800 8.21E+02 1

8.21E+02 1-132 2.47E+02 2800 3.14E+02 1

3.14E+02 1-133 8.84E+02 2800 1.12E+03 1

1.12E+03 1-134 1.78E+01 2800 2.26E+01 1

2.26E+01 1-135 4.03E+02 2800 5.12E+02 1

5.12E+02 Xe-131m 2.30E+00 2800 2.92E+00 1

2.92E+00 Xe-133m 1.90E+01 2800 2.41E+01 1

2.41E+01 Xe-133 2.90E+02 2800 3.68E+02 1

3.68E+02 Xe-135m 5.20E-01 2800 6.60E-01 1

6.60E-0I Xe-135 8.60E+00 2800 1.09E+01 1

1.09E+01 Xe-138 6.40E-01 2800 8.13E-01 1

8.13E-01 Cs-134 1.15E+00 2800 1.46E+00 1

1.46E+00 Cs-136 1.17E+00 2800 1.49E+00 1

1.49E+00 Cs-137 5.47E-01 2800 6.95E-01 I

6.95E-01 Cs-138 2.53E-01 2800 3.21E-01 1

3.21E-01.

Rb-88 9.90E-01 2800 1.26E+00 1

1.26E+00 Br-83 2.32E-02 2800 2.94E-02 1

2.94E-02 Br-84 1.09E-02 2800 1.39E-02 I

1.39E-02 (1) Section 5.2 for iodine (assume same as 2-8 hr activity), Ref. 6 RA DM Table 5-15 for others (2) Per Reference 11 0.35 m = 175 lb/hr, i.e., 16 hr = 2080 lb (3) Activity Released Ci = Primary Coolant Conc Ci/ m

454 gm/lb

Mass Released lb

1.0E-6 Ci/ Ci (4) Activity Release to Environment (Ci) = Activity Released to Faulted SGs (Ci) / Partition Factor (5) Section 3, item 7

D000040-118 Revision 0 Page 31 of 97 5.2.5 0.65 gpm SG Tube Leak - Activity Release 0 - 2 hr 5.2.5 Concurrent Iodine Spike With Initial RC Act ivit at I Ci/ m DE 1-1310.65 m Tube Leak sotopes Reactor Coolant 0-120 Min.

Specific Activity (1) 0-2 hr SG

. 0.65 gpm Tube Leak Mass Release (2) 0-2 hr Activity Release To Intact SG (3) artition Factor (6) 0-2 hr Activity Released To Environ. (4) 0-2 Hr Activity Remaining in Sec. System (5)

(ItCi/gm) lbm (Ci)

(Ci)

Kr-85m 1.80E+00 650 5.31E-01 1

5.31E-01 0.00E+00 Kr-85 7.60E+00 650 2.24E+00 1

2.24E+00 0.00E+00 Kr-87 1.10E+00 650 3.24E-01 1

3.24E-01 0.00E+00 Kr-88 3.20E+00 650 9.43E-01 1

9.43E-01 0.00E+00 1-131 8.48E+01 650 2.50E+01 100 2.50E-01 2.48E+01 1-132 3.23E+02 650 9.51E+01 100 9.51E-01 9.42E+01 1-133 1.60E+02 650 4.71E+01 100 4.71E-01 4.66E+01 1-134 1.13E+02 650 3.32E+01 100 3.32E-01 3.29E+01 1-135 1.42E+02 650 4.18E+01 100 4.18E-01 4.14E+01 Xe-131m 2.30E+00 650 6.78E-01 1

6.78E-01 0.00E+00 Xe-133m 1.90E+01 650 5.60E+00 1

5.60E+00 0.00E+00 Xe-133 2.90E+02 650 8.55E+01 1

8.55E+01 0.00E+00 Xe-135m 5.20E-01 650 1.53E-01 1

1.53E-01 0.00E+00 Xe-135 8.60E+00 650 2.54E+00 I

2.54E+00 0.00E+00 Xe-138 6.40E-01 650 1.89E-01 1

1.89E-01 0.00E+00 Cs-134 1.15E+00 650 3.38E-01 100 3.38E-03 3.35E-01 Cs-136 1.17E+00 650 3.46E-01 100 3.46E-03 3.42E-01 Cs-137 5.47E-01 650 1.61E-01 100 1.61E-03 1.60E-01 Cs-138 2.53E-01 650 7.45E-02 100 7.45E-04 7.38E-02 Rb-88 9.90E-01 650 2.92E-01 100 2.92E-03 2.89E-01 Br-83 2.32E-02 650 6.84E-03 100 6.84E-05 6.77E-03 Br-84 1.09E-02 650 3.23E-03 100 3.23E-05 3.1.9E-03 (1) Section 5.2 for iodine, Ref. 6 RADM Table 5-15 for others.

(2) Per Reference 11 0.65 m = 325 lb/hr, i.e., 2 hr = 650 lb (3) Activity Released (Ci) = Primary Coolant Cone ([tCi/gm)

454 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) 0-2 hr Activity Remaining in SG = Activity Release to SG (Ci) - Activity Released to Environs (Ci)

(6) Section 3, item 13

D000040-118 Revision 0 Page 32 of 97 5.2.6 0.65 gp 5.2.6 Concurrent Iodine With Initial RC Activity at 1 Ci/ m DE 1-131 Reactor 2-8 hr 2-8 hr.

2-8 hr.

Coolant 2-8 hr. SG RC Activity Ruptured Activity 2-8 hr.

0.65 m Tube Release To Activity Added to Specific Leak Mass Intact SG (3)

Partition Factor Released Sec. SG liquid Isotopes Activity (1)

Release (2)

(6)

To Environ. (4) 2 SGs (5)

Ci/ m (Ibm)

(Ci)

Kr-85m 1.80E+00 1950 1.59E+00 I

1.59E+00 0.00E+00 Kr-85 7.60E+00 1950 6.72E+00 I

6.72E+00 0.00E+00 Kr-87 1.10E+00 1950 9.73E-01 1

9.73E-01 0.00E+00 Kr-88 3.20E+00 1950 2.83E+00 I

2.83E+00 0.00E+00 1-131 4.18E+02 1950 3.69E+02 100 3.69E+00 3.66E+02 1-132 9.71E+02 1950 8.59E+02 100 8.59E+00 8.50E+02 1-133 7.40E+02 1950 6.55E+02 100 6.55E+00 6.48E+02 1-134 2.16E+02 1950 1.91E+02 100 1.91E+00 1.89E+02 1-135 5.76E+02 1950 5.09E+02 100 5.09E+00 5.04E+02 Xe-131m 2.30E+00 1950 2.03E+00 1

2.03E+00 0.00E+00 Xe-133m 1.90E+01 1950 1.68E+01 1

1.68E+01 0.00E+00 Xe-133 2.90E+02 1950 2.57E+02 1

2.57E+02 0.00E+00 Xe-135m 5.20E-01 1950 4.60E-01 1

4.60E-01 0.00E+00 Xe-135 8.60E+00 1950 7.61E+00 1

7.61E+00 0.00E+00 Xe-138 6.40E-01 1950 5.66E-01 1

5.66E-01 0.00E+00 Cs-134 1.15E+00 1950 1.01E+00 100 1.01 E-02 1.00E+00 Cs-136 1.17E+00 1950 1.04E+00 100 1.04E-02 1.03E+00 Cs-137 5.47E-01 1950 4.84E-01 100 4.84E-03 4.79E-01 Cs-138 2.53E-01 1950 2.24E-01 100 2.24E-03 2.21E-01 Rb-88 9.90E-01 1950 8.76E-01 100 8.76E-03 8.67E-01 Br-83 2.32E-02 1950 2.05E-02 100 2.05E-04 2.03E-02 Br-84 1.09E-02 1950 9.68E-03 100 9.68E-05 9.58E-03 (1) Section 5.2 for iodine, Ref. 6 RADM Table 5-15 for others.

(2) Per Reference 11 0.65 m = 325 lb/hr, i.e., 6 hr = 1950 lb (3) Activity Released (Ci) = Prima Coolant Conc Ci/ m

454 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) 2-8 hr Activity Remaining in SG = Activity Release to SG Ci - Activity Released to Environs (Ci)

(6) Section 3, item 13

D000040-118 Revision 0 Page 33 of 97 5.2.7 0.65 gp 5.2.7 Concurrent Iodine With Initial RC Activity at 1 Ci/ m DE 1-131 sotopes Reactor Coolant 8-24 hr Specific Activity (1) 8-24 hr SG 0.65 gpm Tube Leak Mass Release (2)

Activity Release to Intact SG Partition Factor (6) 0.65 gpm Tube Leak Activity Released to Environs (4) 8 - 24 hr Activity Remaining in SG (5)

(gCi/grn)

(Ibm)

Ci (Ci)

(Ci)

Kr-85m 1.80E+00 5200 4.25E+00 I

4.25E+00 0.00E+00 Kr-85 7.60E+00 5200 1.79E+01 1

1.79E+01 0.00E+00 Kr-87 1.10E+00 5200 2.59E+00 1

2.59E+00 0.00E+00 Kr-88 3.20E+00 5200 7.55E+00 I

7.55E+00 0.00E+00 I-131 6.46E+02 5200 1.52E+03 100 1.52E+01

.1.51E+03 I-132 2.47E+02 5200 5.83E+02 100 5.83E+00 5.77E+02 I-133 8.84E+02 5200 2.08E+03 100 2.08E+01 2.06E+03 I-134 1.78E+01 5200 4.20E+01 100 4.20E-01 4.16E+01 1-135 4.03E+02 5200 9.51E+02 100 9.51E+00 9.41E+02 Xe-131m 2.30E+00 5200 5.42E+00 1

5.42E+00 0.00E+00 Xe-133m 1.90E+01 5200 4.48E+01 1

4.48E+01 0.00E+00 Xe-133 2.90E+02 5200 6.84E+02 1

6.84E+02 0.00E+00 Xe-135m 5.20E-01 5200 1.23E+00 I

1.23E+00 0.00E+00 Xe-135 8.60E+00 5200 2.03E+01 1

2.03E+01 0.00E+00 Xe-138 6.40E-01 5200 1.51E+00 1

1.51E+00 0.00E+00 Cs-134 1.15E+00 5200 2.70E+00 100 2.70E-02 2.68E+00 Cs-136 1.1.7E+00 5200 2.77E+00 100 2.77E-02 2.74E+00 Cs-137 5.47E-01 5200 1.29E+00 100 1.29E-02 1.28E+00 Cs-138 2.53E-01 5200 5.96E-01 100 5.96E-03 5.90E-01 Rb-88 9.90E-01 5200 2.33E+00 100 2.33E-02 2.31E+00 Br-83 2.32E-02 5200 5.47E-02 100 5.47E-04 5.41E-02 Br-84 1.09E-02 5200 2.58E-02 100 2.58E-04 2.55E-02 (1) Assume same as 2-8 hr activ ity (2) Per Reference 11 0.65 m = 325 lb/hr, i.e., 16 hr = 5200 lb (3) Activity Released (Ci) = Primary Coolant Cone (ltCi/gm)

454 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) 8-24 hr Activity Remaining in SG = Activity Release to SG (Ci) - Activity Released to Environs (Ci)

(6) section 3, item 1.3

D00004O-118 Revision 0 Page 34 of 97 5.2.8 Concurrent Spike Secondary Coolant Activity Release from Intact SGs 5.2.8 Concurrent Spike Secondary Coolant Activity Release from Intact SG Isotopes Secondary Coolant Activity @

0.1 Ci/ m DE 1-131 Ci/Ib 1

Intact SG Steam Release Ib (2)

Partition Factor (6) 0-2 hr Release to Environment (Ci) (3) 0-30 min Release to Environment (Ci) (4) 30 min -2 hr Release to Environment (Ci) (5) 0 - 2 hr I-131 3.93E+01 343700 100 1.35E-01 3.37E-02 1.01E-01 I-132 2.90E-02 343700 100 9.98E-05 2.49E-05 7.48E-05 1-133 5.74E+00 343700 100 1.97E-02 4.93E-03 1.48E-02 I-134 4.07E-04 343700 100 1.40E-06 3.50E-07 1.05E-06 1-135 2.59E-01 343700 100 8.90E-04 2.23E-04 6.68E-04 Cs-134 6.31E+01 343700 100 2.17E-01 5.42E-02 1.63E-01 Cs-136 6.10E+01 343700 100 2.10E-01 5.24E-02 1.57E-01 Cs-137 3.01E+01 343700 100 1.04E-01 2.59E-02 7.76E-02 Cs-138 3.93E-01 343700 100 1.35E-03 3.38E-04 1.01E-03 Rb-88 8.62E-01 343700 100 2.96E-03 7.40E-04 2.22E-03 Br-83 1.46E-01 343700 100 5.03E-04 1.26E-04 3.77E-04 Br-84 1.68E-02 343700 100 5.78E-05 1.44E-05 4.33E-05 2 - 8 hr 2-8 hr Release ( Ci) 8-24 hr Release (2) 8-24 Hr Release to Environment Ci (3) 1-131 3.93E+01 733900 100 2.88E-01 1200000 4.71E-01 1-132 2.90E-02 733900 100 2.13E-04 1200000 3.48E-04 1-133 5.74E+00 733900 100 4.21E-02 1200000 6.88E-02 I-134 4.07E-04 733900 100 2.99E-06 1200000 4.88E-06 I-135 2.59E-01 733900 100 1.90E-03 1200000 3.11 E-03 Cs-134 6.31E+01 733900 100 4.63E-01 1200000 7.57E-01 Cs-136 6.10E+01 733900 100 4.48E-01 1200000 7.32E-01 Cs-137 3.01E+01 733900 100 2.21E-01 1200000 3.61E-01 Cs-138 3.93E-01 733900 100 2.88E-03 1200000 4.71E-03 Rb-88 8.62E-01 733900 100 6.32E-03 1200000 1.03E-02 Br-83 1.46E-01 733900 100 1.07E-03 1200000 1.76E-03 Br-84 1.68E-02 733900 100 1.23E-04 1200000 2.02E-04 (1) Section 5.2.2 (2) Section 4.3 - Mass of steam releases from intact SG (3) Activity Release to Environment (Ci) = Secondary Coolant Ci/lb

Steam Release Ib / Partition Factor/ I.0E06 Ci/Ci (4) 0-30 min Release = 0-2 hr Release

0.25 5 30 min - 2 hr Release = 0-2 hr Release

0.75 (6) Section 3, item 13

D000040-118 Revision 0 Page 35 of 97 5.2.9 Concurrent Spike Total Activity Released 0 - 2 hrs 5.2.9 Concurrent Spike Total Activity Released 0 - 2 hrs Lp = 1 m

5.2.1 5.2.2 5.2.5 5.2.8 (1)

(2)

(3)

Faulted Faulted SG Intact SG Intact 0-2 hr 0-30 min 30 min - 2 hr SG Sec.

0.35 m Tube 0.65 m Tube SG Sec.

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

(Ci)

Kr-85m 0.00E+00 2.86E-01 5.31E-01 0.00E+00 8.16E-01 2.04E-01 6.12E-01 Kr-85 0.00E+00 1.21E+00 2.24E+00 0.00E+00 3.45E+00 8.62E-01 2.59E+00 Kr-87 0.00E+00 1.75E-0I 3.24E-01 0.00E+00 4.99E-01 1.25E-01 3.74E-01 Kr-88 0.00E+00 5.08E-01 9.43E-01 0.00E+00 1.45E+00 3.63E-01 1.09E+00 I-131 1.59E+01 1.35E+01 2.50E-01 1.35E-01 2.98E+01 1.94E+01 1.04E+01 I-132 1.18E-02 5.12E+01 9.51E-01 9.98E-05 5.22E+01 1.31E+01 3.91E+01 I-133 2.33E+00 2.53E+01 4.71E-01 1.97E-02 2.82E+01 8.79E+00 1.94E+01 1-134 1.65E-04 1.79E+01 3.3 2E-01 1.40E-06 1.82E+01 4.56E+00 1.37E+01 I-135 1.05E-01 2.25E+01 4.1.8E-01 8.90E-04 2.30E+01 5.84E+00 1.72E+01 Xe-131m 0.00E+00 3.65E-01 6.78E-01 0.00E+00 1.04E+00 2.61E-01 7.82E-01 Xe-133m 0.00E+00 3.02E+00 5.60E+00 0.00E+00 8.62E+00 2.15E+00 6.46E+00 Xe-133 0.00E+00 4.60E+01 8.55E+01 0.00E+00 1.32E+02 3.29E+01 9.87E+01 Xe-135m 0.00E+00 8.26E-02 1.53E-01 0.00E+00 2.36E-01 5.90E-02 1.77E-01 Xe-135 0.00E+00 1.37E+00 2.54E+00 0.00E+00 3.90E+00 9.75E-01 2.93E+00 Xe-138 0.00E+00 1.02E-01 1.89E-01 0.00E+00 2.90E-01 7.26E-02 2.18E-01 Cs-134 2.56E+01 1.82E-01 3.38E-03 2.17E-01 2.60E+01 2.57E+01 3.02E-01 Cs-136 2.48E+01 1.86E-01 3.46E-03 2.10E-01 2.52E+01 2.49E+01 2.99E-01 Cs-137 1.22E+01 8.68E-02 1.61E-03 1.04E-01 1.24E+01 1.23E+01 1.44E-01 Cs-138 1.59E-01 4.01E-02 7.45E-04 1.35E-03 2.02E-01 1.70E-01 3.17E-02 Rb-88 3.50E-01 1.57E-01 2.92E-03 2.96E-03 5.13E-01 3.91E-01 1.22E-01 Br-83 5.94E-02 3.68E-03 6.84E-05 5.03E-04 6.36E-02 6.04E-02 3.19E-03 Br-84 6.82E-03 1.74E-03 3.23E-05 5.78E-05 8.65E-03 7.28E-03 1.37E-03 (1) = Sum of columns 5.2.1 + 5.2.2 + 5.2.5 + 5.2.8 (2) = Sum of column 5.2.1 + [0.25 * (column 5.2.2 + 5.2.5 + 5.2.8 3 = 1 - 2

D000040-118 Revision 0 Page 36 of 97 5.2.10 Concurrent Spike Total Activity Released 2 - 8 hrs 1.0 gpm 5.2.10 Concurrent Spike Tota l Activity Released 2 - 8 hrs Lp = 1 m

5.2.3 5.2.6 5.2.8 (1)

(2)

Faulted Intact Intact SG Sec.

2-8 hr 0-8 hr SG Tube SG Tube Coolant Total Total Leak Leak Release Activity Activity Isotopes Release Release 2-8 hr Release Release (Ci)

(Ci)

Kr-85m 8.57E-01 1.59E+00 0

2.45E+00 3.3 Kr-85 3.62E+00 6.72E+00 0

1.03E+01 13.8 Kr-87 5.24E-01 9.73E-01 0

1.50E+00 2.0 Kr-88 1.52E+00 2.83E+00 0

4.35E+00 5.8 1-131 1.99E+02 3.69E+00 2.88E-01 2.03E+02 232.7 1-132 4.62E+02 8.59E+00 2.13E-04 4.71E+02 523.1 1-133 3.53E+02 6.55E+00 4.21E-02 3.59E+02 387.3 1-134 1.03E+02 1.91E+00 2.99E-06 1.05E+02 123.1 1-135 2.74E+02 5.09E+00 1.90E-03 2.79E+02 302.4 Xe-131m 1.10E+00 2.03E+00 0

3.13E+00 4.2 Xe-133m 9.05E+00 1.68E+01 0

2.59E+01 34.5 Xe-133 1.38E+02 2.57E+02 0

3.95E+02 526.2 Xe-135m 2.48E-01 4.60E-01 0

7.08E-01 0.9 Xe-135 4.10E+00 7.61E+00 0

1.17E+01 15.6 Xe-138 3.05E-01 5.66E-01 0

8.71E-01 1.2 Cs-134 5.46E-01 1.01E-02 4.63E-01 1.02E+00 27.0 Cs-136 5.58E-01 1.04E-02 4.48E-01 1.02E+00 26.2 Cs-137 2.61E-01 4.84E-03 2.21E-01 4.86E-01 12.9 Cs-138 1.20E-01 2.24E-03 2.88E-03 1.25E-01 0.3 Rb-88 4.71E-01 8.76E-03 6.32E-03 4.87E-01 1.0 Br-83 1.10E-02 2.05E-04 1.07E-03 1.23E-02 0.1 Br-84 5.21E-03 9.68E-05 1.23E-04 5.43E-03 0.01 (1) Sum of columns 5.2.3 + 5.2.6 + 5.2.8 (2) Sum of (1) +0 - 2 hr total from 5.2.9

D000040-118 Revision 0 Page 37 of 97 5.2.11 Concurrent Spike Total Activity Released 5.2.11 Concurrent Spike Total Activity Released 8 - 24 hrs Lp = 1 m

5.2.4 5.2.7 (1)

(2)

Faulted Intact 8-24 hr 0-24 hr SG Tube SG Tube Total Total Leak Leak Activity Activity Isotopes Release Release Release Release (Ci)

Ci (Ci)

(Ci)

Kr-85m 2.29E+00 4.25E+00 6.53E+00 9.8 Kr-85 9.65E+00 1.79E+01 2.76E+01 41.4 Kr-87 1.40E+00 2.59E+00 3.99E+00 6.0 Kr-88 4.06E+00 7.55E+00 1.16E+01 17.4 1-131 8.21E+02 1.52E+01 8.36E+02 1069 1-132 3.14E+02 5.83E+00 3.20E+02 843 1-133 1.12E+03 2.08E+01 1.14E+03 1531 1-134 2.26E+01 4.20E-01 2.30E+01 146 1-135 5.12E+02 9.51E+00 5.21E+02 824 Xe-131m 2.92E+00 5.42E+00 8.35E+00 12.5 Xe-133m 2.41E+0I 4.48E+01 6.89E+01 103.4 Xe-133 3.68E+02 6.84E+02 1.05E+03 1578.5 Xe-135m 6.60E-01 1.23E+00 1.89E+00 2.8 Xe-135 1.09E+01 2.03E+01 3.12E+01 46.8 Xe-138 8.13E-01 1.51E+00 2.32E+00 3.5 Cs-134 1.46E+00 2.70E-02 1.48E+00 29.3 Cs-136 1.49E+00 2.77E-02 1.52E+00 28.4 Cs-137 6.95E-01 1.29E-02 7.08E-01 14.0 Cs-138 3.21E-01 5.96E-03 3.27E-01 0.7 Rb-88 1.26E+00 2.33E-02 1.28E+00 2.3 Br-83 2.94E-02 5.47E-04 3.00E-02 0.1 Br-84 1.39E-02 2.58E-04 1.42E-02 0.03 (1) = Sum of columns 5.2.4 + 5.2.7 (2) = 0- 8 hr total release (5.2.10) + 8 - 24 hr total release (5.2.11) + 8 - 24 hr total release 5.2.8

D000040-118 Revision 0 Page 38 of 97 5.2.12 Concurrent Spike Fraction Total Activity Released 5.2.12 Concurrent Spike Fraction of Total Activity Released Isotopes Time Period Release By 0-30 min 30 min-2hr 2-8hr 8-24 hr Species 0-30 min 30 min-2hr 2-8hr 8-24 hr (1)

(2)

(3)

(4)

Kr-85m 2.08E-02 6.25E-02 2.50E-01 6.67E-01 Nobles 2.08E-02 6.25E-02 2.50E-01 6.67E-01 Kr-85 2.08E-02 6.25E-02 2.50E-01 6.67E-01 Kr-87 2.08E-02 6.25E-02 2.50E-01 6.67E-01 Kr-88 2.08E-02 6.25E-02 2.50E-01 6.67E-01 I-131 1.81E-02 9.71E-03 1.90E-01 7.82E-01 Iodine 1.81E-02 9.71E-03 1.90E-01 7.82E-01 1-132 1.55E-02 4.64E-02 5.59E-01 3.79E-01 I-133 5.74E-03 1.27E-02 2.35E-01 7.47E-01 I-134 3.12E-02 9.35E-02 7.18E-01 1.58E-01 I-135 7.09E-03 2.09E-02 3.39E-01 6.33E-01 Xe-131m 2.08E-02 6.25E-02 2.50E-01 6.67E-01 Xe-133m 2.08E-02 6.25E-02 2.50E-01 6.67E-01 Xe-133 2.08E-02

-6.25E-02 2.50E-01 6.67E-01 Xe-135m 2.08E-02 6.25E-02 2.50E-01 6.67E-01 Xe-135 2.08E-02 6.25E-02 2.50E-01 6.67E-01 Xe-138 2.08E-02 6.25E-02 2.50E-01 6.67E-01 Cs-134 8.78E-01 1.03E-02 3.48E-02 5.07E-02 Cesium 8.78E-01 1.03E-02 3.48E-02 5.07E-02 Cs-136 8.75E-01 1.05E-02 3.58E-02 5.34E-02 Cs-137 8.78E-01 1.03E-02 3.48E-02 5.06E-02 Cs-138 2.58E-01 4.81E-02 1.90E-01 4.96E-01 Rb-88 1.71E-01 5.34E-02' 2.12E-01 5.59E-01 Same as Cs Br-83 5.61E-01 2.96E-02 1.14E-01 2.78E-01 Same as Iodine Br-84 2.56E-01 4.82E-02 1.91E-01 4.98E-01 (1): 0-30 min Fraction = 0-30 min release (5.2.9) / 0-24 hr release (5.2.11)

(2): 30 min-2hr Fraction = 30 min-2 hr release (5.2.9) / 0-24 hr release 5.2.11 (3): 2-8 hr Fraction = 2-8 hr release 5.2.10 / 0-24 hr release (5.2.11)

(4): 8-24 hr Fraction = 8-24 hr release 5.2.11 / 0-24 hr release 5.2.11

D000040-118 Revision 0 Page 39 of 97 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 ft2. 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-0-1 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.

DC00040-118 Revision 0 Page 40 of 97 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 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.

DO00040-118 Revision 0 Page 41 of 97 6.0 RADTRAD Models 6.1 MSLB Design Case-RADTRAD Models 6.1.1 RADTRAD Model - MSLB - 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+03 ft3) at a very high rate (1.OE+8 cfm) while releasing the available activity over an 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period.

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

Nuclide inventories are input as user defined NIF files: MSLB concurrent.NIF (Attachment 2) and MSLB pre I-BR spike.NIF (Attachment 3).

Release fractions and timing data are input as user defined RFT files: MSLB concurrent Iodine Spike.RFT (Attachment 4) and MSLB pre.RFT (Attachment 5).

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 ft 3 No recirculating filters utilized No additional inputs

DC00040-118 Revision 0 Page 42 of 97 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 an 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 Air 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

DC00040-118 Revision 0 Page 43 of 97 Use breathing rate and occupancy values per Sections 4.6 and 4.7 No additional inputs 6.1.13 RADTRAD Source Term:

Modeled power level as 1.0327 MWth and 1.0300 MWth, for the concurrent and per existing spike cases, respectively, to obtain total I-131 activity release at 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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, MSLB.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 MSLB are provided in Attachments 6 and 7,

7.0 CONCLUSION

S 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 MSLB event are given as and 5 Rem TEDE for the CR (TSC). Dose acceptance criteria for the Concurrent Iodine Spike MSLB 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 MSLB calculation DC00040-099, Revision 2 (Reference 3).

Case Dose (Rem TEDE Attachment EAB LPZ TSC Pre-existing Iodine Spike 0.61 0.14 0.22 6

Concurrent Iodine Spike 0.33 0.28 0.41 7

8.0 DISPOSITION of RESULTS The results of this calculation are incorporated into the VCSNS FSAR 15.4.2.

DO00040-118 Revision 0 Page 44 of 97

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 VCSNS Calculation DC00040-099, "Main Steam Line Break - AST", Revision 2.

4 DC00040-038, Iodine Spike, 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-92-00I9SGUL).

7 VCS Technical Specifications 3.4.8 and 3.7.1.4, Amendment 179.

8 Westinghouse Transmittal #CGE-93-0007SGUL (PS-CGE-0807) dated 3/1/93, VCSNS RSG/Uprating: Steam Release for Dose Analysis and Write-up for Source Terms. (Att. 8) 9 Westinghouse Internal Memo dated 2/15/93, ET-NSASD-TAI-93-049, V.C. Summer Uprate / SG Replacement SLB M&E Inside Containment Data. (Att.9) 10 Federal Guidance Report 12, (EPA-402-R-93-081), "External Exposure to Radionuclides in Air, Water and Soil", September 1993.

11 DO00040-005, "Secondary Coolant System Equilibrium Analysis", Revision 4.

12 Westinghouse Radiation Analysis Manual, Revision I 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.

DC00040-1 1 8 Revision 0 Page 45 of 97 15 VCSNS Calculation DC00040-111, 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 c.

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

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

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

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.

DO00040-118 Revision 0 Page 46 of 97 Attachment No. 1 RADTRAD Model

D000040-118 Revision 0 Page 47 of 97 Volume 1 Release Volume 1.0+04 ft3 (arbitrary volume)

FP 1 1.0E+10 cfm (arbitrary flow rate)

No filtration or holdup Volume 2 Environment FP 2 - 12,000 cfin makeup (0 - 720 hr.)

no filtration FP 3 - 1,000 cfm unfiltered inleakage (0 -720 hr.)

unfiltered inleakage/ damper leakage /

ingress/egress Volume 3 TSC Habitability Envelope (2.07E+05 ft3)

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

DO00040-1 1 8 Revision 0 Page 48 of 97 Attachment No. 2 MSLB concurrent.NIF

Nuclide Inventory Name:

VCS MSLB concurrent spike Power Level:

0.1000E+01 Nuclides:

22 Nuclide 001:

Kr-85m 1

0.1612800000E+05 0.8500E+02 9.8 Kr-85 0.2100E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 002:

Kr-85 1

0.3382974720E+09 0.8500E+02 41.4 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 003:

Kr-87 1

0.4578000000E+04 0.8700E+02 6.0 Rb-87 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 004:

Kr-88 1

0.1022400000E+05 0.8800E+02 17.4 Rb-88 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 005:

1-131 2

0.6946560000E+06 0.1310E+03 1069.

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

1-132 2

0.8280000000E+04 0.1320E+03 843.

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

1-133 2

0.7488000000E+05 0.1330E+03 1531.

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

1-134

2 0.3156000000E+04 0.1340E+03 146.

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

1-135 2

0.2379600000E+05 0.1350E+03 824.

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

1.0229760000E+06 0.1310E+03 12.5 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 011:

Xe-133m 1

1.8921600000E+05 0.1330E+03 103.4 Xe-133 1.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 012:

Xe-133 1

0.4531680000E+06 0.1330E+03 1578.5 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 013:

Xe-135m 1

9.2167177120E+02 0.1350E+03 2.8 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 46.8 Cs-135 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 015:

Xe-138 1

8.5020000000E+02 1.3800E+02 3.5 Cs-138 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 016:

Cs-134 3

0.6507177120E+08 0.1340E+03 29.3 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 017:

Cs-136 3

0.1131840000E+07 0.1360E+03 28.4 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 018:

Cs-137 3

0.9467280000E+09 0.1370E+03 14.0 Ba-137m 0.9500E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 019:

Cs-138 3

1.9320000000E+03 1.3800E+02 0.7 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 020:

Rb-88 3

1.0680000000E+03 8.8000E+01 2.3 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 0.03 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 End of Nuclear Inventory File

DO00040-1 1 8 Revision 0 Page 52 of 97 Attachment No. 3 MSLB pre I-BR spike.NIF

Nuclide Inventory Name:

VCS MSLB pre incident spike Power Level:

0.1000E+01 Nuclides:

22 Nuclide 001:

Kr-85m 1

0.1612800000E+05 0.8500E+02 9.8 Kr-85 0.2100E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 002:

Kr-85 1

0.3382974720E+09 0.8500E+02 41.4 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 003:

Kr-87 1

0.4578000000E+04 0.8700E+02 6.0 Rb-87 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 004:

Kr-88 1

0.1022400000E+05 0.8800E+02 17.4 Rb-88 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 005:

1-131 2

0.6946560000E+06 0.1310E+03 417.6 Xe-131m 0.1100E-01 none 0.0000E+00 none 0.0000E+00 Nuclide 006:

1-132 2

0.8280000000E+04 0.1320E+03 135.4 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 007:

1-133 2

0.7488000000E+05 0.1330E+03 430.9 Xe-133m 0.2900E-01 Xe-133 0.9700E+00 none 0.0000E+00

Nuclide 008:

1-134 2

0.3156000000E+04 0.1340E+03 21.4 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 009:

1-135 2

0.2379600000E+05 0.1350E+03 149.2 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 12.5 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 011:

Xe-133m 1

1.8921600000E+05 0.1330E+03 103.4 Xe-133 1.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 012:

Xe-133 1

0.4531680000E+06 0.1330E+03 1578.5 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 013:

Xe-135m 1

9.2167177120E+02 0.1350E+03 2.8 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 46.8 Cs-135 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 015:

Xe-138 1

8.5020000000E+02 1.3800E+02 3.5 Cs-138 0.1000E+01 none 0.0000E+00

none 0,0000E+00 Nuclide 016:

Cs-134 3

0.6507177120E+08 0.1340E+03 11.0 none 0.0000E+00 none 0,0000E+00 none 0,0000E+00 Nuclide 017:

Cs-136 3

0.1131840000E+07 0.1360E+03 10.7 none 0,0000E+00 none 0,0000E+00 none 0.0000E+00 Nuclide 018:

Cs-137 3

0.9467280000E+09 0.1370E+03 5.2 Ba-137m 0.9500E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 019:

Cs-138 3

1.9320000000E+03 1.3800E+02 0.5 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 020:

Rb-88 3

1.0680000000E+03 8.8000E+01 2.0 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 021:

Br-83 2

8.6040000000E+03 8.3000E+01 3.9 Kr-83m 1.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 022:

Br-B4 2

1.9080000000E+03 8.4000E+01 1.4 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 End of Nuclear Inventory File

DO00040-1 1 8 Revision 0 Page 56 of 97 Attachment No. 4 MSLB concurrent Iodine Spike.RFT

D000040-118 Revision 0 Page 57 of 97 Release Fraction and Timing Name: MSLB Concurrent Iodine Spike Release Break Activity over 24 Hours Duration (h):

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

2.0800E-02 6.2500E-02 2.5000E-01 6.6700E-01 Iodine:

1.8100E-02 9.7100E-03 1.9000E-01 7.8200E-01 Cesium:

8.7800E-01 1.0300E-02 3.4800E-02 5.0700E-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

DO00040-118 Revision 0 Page 58 of 97 Attachment No. 5 MSLB pre.RFT

D000040-118 Revision 0 Page 59 of 97 Release Fraction and Timing Name: MSLB Pre-Accident Iodine Spike Release Break Activity over 24 Hours Duration (h):

VCS MSLB Pre-Accident Iodine Spike 24 Hr Release 0.5000E+00 1.5000E+00

.6.0000E+00 1.6000E+01 Noble Gases:

2.0800E-02 6.2500E-02 2.5000E-01 6.6700E-01 Iodine:

7.4700E-01 1.8300E-02 6.7900E-02 1.4500E-01 Cesium:

7.6100E-01 1.7500E-02 6.4400E-02 1.3500E-01 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

DO00040-118 Revision 0 Page 60 of 97 Attachment No. 6 MSLB pre I Spike

DC00040-118 Revision 0 Page 61 of 97 RADTRAD Version 3.03 (Spring 2001) run on 12/12/2011 at 7:31:54 File information Plant file

= C:\\radtrad3.03\\2011 MSLB TSC\\Att 6 MSLB pre-I Spike TSC.psf Inventory file

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

= c:\\radtrad3.03\\2011 mslb Dose Conversion file = c:\\radtrad3.03\\2011 mslb tsc\\mslb 1.2 m added pre i-br tsc\\mslb 1.2 m addedpre.rft tsc\\mslb.inp spike.nif Radtrad 3.03 4/15/2001 SGTR Nuclide Inventory File:

c:\\radtrad3.03\\2011 mslb tsc\\mslb 1.2 m added pre i-br spike.nif Plant Power Level:

1.0300E+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 mslb tsc\\mslb.inp c:\\radtrad3.03\\2011 mslb tsc\\mslb 1.2 m addedpre.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 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

D000040-118 Revision 0 Page 65 of 97 RADTRAD Version 3.03 (Spring 2001) run on 12/12/2011 at 7:31:54 Plant Description Number of Nuclides = 22 Inventory Power =

1.0000E+00 MWth Plant Power Level =

1.0300E+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

DC00040-118 Revision 0 Page 66 of 97 RADTRAD Version 3.03 (Spring 2001) run on 12/12/2011 at 7:31:54 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 2.0800E-02 7.4700E-01 7.6100E-01 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 6.2500E-02 2.5000E-01 1.8300E-02 6.7900E-02 1.7500E-02 6.4400E-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 3.926E-02 3.266E-03 5.941E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1

Inventory Power =

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

9.800E+00 1.613E+04 7.480E-15 0.000E+00 0.000E+00 Kr-85 1

4.140E+01 3.383E+08 1.190E-16 0.000E+00 0.000E+00 Kr-87 1

6.000E+00 4.578E+03 4.120E-14 0.000E+00 0.000E+00 Kr-88 1

1.740E+01 1.022E+04 1.020E-13 0.000E+00 0.000E+00 1-131 2

4.176E+02 6.947E+05 1.820E-14 2.920E-07 8.890E-09 1-132 2

1.354E+02 8.280E+03 1.120E-13 1.740E-09 1.030E-10 1-133 2

4.309E+02 7.488E+04 2.940E-14 4.860E-08 1.580E-09 1-134 2

2.140E+01 3.156E+03 1.300E-13 2.880E-10 3.550E-11 1-135 2

1.492E+02 2.380E+04 8.294E-14 8.460E-09 3.320E-10 Xe-131m 1

1.250E+01 1.023E+06 3.890E-16 0.000E+00 0.000E+00 Xe-133m 1

1.034E+02 1.892E+05 1.370E-15 0.000E+00 0.000E+00 Xe-133 1

1.578E+03 4.532E+05 1.560E-15 0.000E+00 0.000E+00 Xe-135m 1

2.800E+00 9.217E+02 2.040E-14 0.000E+00 0.000E+00 Re-135 1

4.680E+01 3.272E+04 1.190E-14 0.000E+00 0.000E+00 Xe-138 1

3.500E+00 8.502E+02 1.787E-13 3.570E-12 2.740E-11 Cs-134 3

1.100E+01 6.507E+07 7.570E-14 1.110E-08 1.250E-08 Cs-136 3

1.070E+01 1.132E+06 1.060E-13 1.730E-09 1.980E-09 Cs-137 3

5.200E+00 9.467E+08 2.725E-14 7.930E-09 8.630E-09 Cs-138 3

5.000E-01 1.932E+03 1.210E-13 3.570E-12 2.740E-11 Rb-88 3

2.000E+00 1.068E+03 3.360E-14 1.370E-12 2.260E-11 Br-83 2

3.900E+00 8.604E+03 3.820E-16 1.140E-12 2.410E-11 Br-84 2

1.400E+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 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

DC00040-118 Revision 0 Page 67 of 97 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^-1) 0.0000E+00 3.5000E-04 8.0000E+00 1.8000E-04

DC0004O-118 Revision 0 Page 68 of 97 2.4000E+01 7.2000E+02 Location TSC Location %/Q Data 2.3000E-04 0.0000E+00 is in compartment 3

Time (hr)

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

DC00040-1 1 8 Revision 0 Page 69 of 97 RADTRAD Version 3.03 (Spring 2001) run on 12/12/2011 at 7:31:54 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) 1.8274E-02 Thyroid 1.7829E+01 TEDE 5.9354E-01 Accumulated dose (rem) 1.8274E-02 1.7829E+01 5.9354E-01 LPZ Doses:

Time (h) =

0.5000 Whole Body Delta dose (rem) 3.5664E-03 Thyroid 3.4795E+00 TEDE 1.1584E-01 Accumulated dose (rem) 3.5664E-03 TSC Doses:

3.4795E+00 1.1584E-01 Time (h) =

0.5000 Whole Body Delta dose (rem) 1.6567E-04 Thyroid 3.0522E+00 TIDE 9.8645E-02 Accumulated dose (rem) 1.6567E-04 3.0522E+00 9.8645E-02 Arbitrary Volume Compartment Nuclide Inventory:

Time (h) =

0.5000 Ci kg Atoms Decay Kr-85m 6.4775E-09 7.8711E-19 5.5765E+06 4.4853E+05 Kr-85 2.9565E-08 7.5357E-14 5.3389E+ll 1.9690E+06 Kr-87 3.2626E-09 1.1518E-19 7.9730E+05 2.4979E+05 Kr-88 1.0998E-08 8.7712E-19 6.0024E+06 7.7906E+05 1-131 1.0691E-05 8.6235E-14 3.9643E+ll 7.1266E+08 1-132 2.9869E-06 2.8936E-16 1.3201E+09 2.1469E+08 1-133 1.0869E-05 9.5944E-15 4.3443E+10 7.2992E+08 1-134 3.6962E-07 1.3856E-17 6.2269E+07 3.0193E+07 1-135 3.6311E-06 1.0339E-15 4.6123E+09 2.4828E+08 Xe-131m 8.9474E-09 1.0628E-16 4.8858E+08 5.9426E+05 Xe-133m 7.3815E-08 1.6466E-16 7.4555E+08 4.9032E+06 Xe-133 1.1308E-06 6.0410E-15 2.7353E+10 7.4999E+07 Xe-135m 1.5612E-07 1.7218E-18 7.6808E+06 4.6534E+05 Xe-135 5.8491E-08 2.2904E-17 1.0217E+08 2.2783E+06 Xe-138 5.7613E-10 5.9917E-21 2.6147E+04 8.7288E+04 Cs-134 2.8740E-07 2.2213E-13 9.9828E+11 1.9141E+07 Cs-136 2.7926E-07 3.8103E-15 1.6872E+10 1.8609E+07 Cs-137 1.3586E-07 1.5620E-12 6.8660E+12 9.0485E+06 Cs-138 2.6378E-08 6.2339E-19 2.7204E+06 1.5071E+06 Rb-88 2.5158E-07 2.0958E-18 1.4342E+07 1.1922E+07 Br-83 8.6522E-08 5.4768E-18 3.9738E+07 6.2011E+06 Br-84 1.8671E-08 2.6525E-19 1.9016E+06 1.7553E+06 Arbitrary Time (h) =

Noble gases Volume Transport Group 0.5000 Atmosphere (atoms) 5.6260E+ll Inventory:

Sump 0.0000E+00 Elemental I (atoms) 4.3253E+ll 0.0000E+00 Organic I (atoms) 1.3377E+10 0.0000E+00 Aerosols (kg) 1.7879E-12 0.0000E+00

Dose Effective (Ci/cc) 1-131 (Thyroid) 4.4579E-14 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 4.9484E-14 Total I (Ci) 2.8547E-05 Release Volume to Environment Transport Group Inventory:

Time (h) =

0.5000 Pathway Filtered Transported Noble gases (atoms) 0.0000E+00 1.2102E+20 Elemental I (atoms) 0.0000E+00 9.3447E+19 Organic I (atoms) 0.0000E+00 2.8901E+18 Aerosols (kg) 0.0000E+00 4.0811E-04 Detailed model information at time (H) 2.0000 EAB Doses:

Time (h) =

2.0000 Delta dose (rem)

Accumulated dose (rem)

LPZ Doses:

Time (h) =

2.0000 Delta dose (rem)

Accumulated dose (rem)

TSC Doses:

Time (h) =

2.0000 Delta dose (rem)

Whole Body 5.4473E-04 1.8819E-02 Whole Body 1.0631E-04 3.6727E-03 Whole Body 1.3722E-04 Thyroid 4.3281E-01 1.8262E+01 Thyroid 8.4468E-02 3.5640E+00 Thyroid 2.6446E+00 TIDE 1.4467E-02 6.0801E-01 TEDE 2.8233E-03 1.1866E-01 TEDE 8.5436E-02 Accumulated dose (rem) 3.0289E-04 5.6969E+00 1.8408E-01 Arbitrary Volume Compartment Nuclide Inventory:

Time (h) =

2.0000 Ci kg Atoms Decay Kr-85m 5.1441E-09 6.2508E-19 4.4286E+06 1.6054E+06 Kr-85 2.9612E-08 7.5477E-14 5.3474E+ll 7.8856E+06 Kr-87 1.4427E-09 5.0934E-20 3.5256E+05 6.9580E+05 Kr-88 7.6389E-09 6.0920E-19 4.1690E+06 2.6222E+06 1-131 8.6833E-08 7.0041E-16 3.2198E+09 7.3005E+08 1-132 1.5520E-08 1.5036E-18 6.8597E+06 2.1861E+08 1-133 8.4426E-08 7.4528E-17 3.3746E+08 7.4722E+08 1-134 9.2193E-10 3.4559E-20 1.5531E+05 3.0546E+07 1-135 2.5336E-08 7.2143E-18 3.2182E+07 2.5376E+08 Be-131m 8.9128E-09 1.0587E-16 4.8670E+08 2.3771E+06 Re-133m 7.2252E-08 1.6117E-16 7.2977E+08 1.9466E+07 Re-133 1.1206E-06 5.9865E-15 2.7106E+10 2.9952E+08 Re-135m 1.2842E-08 1.4164E-19 6.3181E+05 3.1901E+06 Re-135 4.1646E-08 1.6308E-17 7.2747E+07 1.0018E+07 Cs-134 2.2029E-09 1.7026E-15 7.6518E+09 1.9581E+07 Cs-136 2.1335E-09 2.9111E-17 1.2890E+08 1.9036E+07 Cs-137 1.0414E-09 1.1973E-14 5.2630E+10 9.2566E+06 Rb-88 3.9433E-09 3.2850E-20 2.2481E+05 1.2437E+07 Br-83 4.5730E-10 2.8947E-20 2.1003E+05 6.3155E+06 Arbitrary Volume Transport Group Inventory:

Time (h) =

2.0000 Atmosphere Sump Noble gases (atoms) 5.6315E+11 0.0000E+00 Elemental I (atoms) 3.4888E+09 0.0000E+00 Organic I (atoms) 1.0790E+08 0.0000E+00 Aerosols (kg) 1.3705E-14 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 3.5919E-16 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 3.9582E-16 Total I (Ci) 2.1304E-07 Release Volume to Environment Transport Group Inventory:

Time (h) =

2.0000 Pathway Filtered Transported Noble gases (atoms) 0.0000E+00 4.7657E+21 Elemental I (atoms) 0.0000E+00 9.5050E+19 Organic I (atoms) 0.0000E+00 2.9397E+18 Aerosols (kg) 0.0000E+00 4.1408E-04

Detailed model information at time (H) =

8.0000 EAB Doses:

Time (h) =

8.0000 Delta dose (rem)

Whole Body 2.8665E-03 Thyroid 2.8025E+00 TIDE 9.2871E-02 Accumulated dose (rem)

LPZ Doses:

2.1685E-02 2.1064E+01 7.0088E-01 Time (h) =

8.0000 Delta dose (rem)

Whole Body 5.5944E-04 Thyroid 5.4694E-01 TIDE 1.8125E-02 Accumulated dose (rem) 4.2321E-03 4.1109E+00 1.3678E-01 TSC Doses:

Time (h) =

Delta dose 8.0000 (rem)

Whole Body 4.0213E-05 Thyroid 7.4457E-01 TEDE 2.3955E-02 Accumulated dose (rem) 3.4310E-04 6.4415E+00 2.0804E-01 Arbitrary Volume Compartment Nuclide Inventory:

Time (h) =

8.0000 Ci kg Atoms Decay Kr-85m 4.0671E-09 4.9421E-19 3.5014E+06 6.9634E+06 Kr-85 5.9236E-08 1.5098E-13 1.0697E+12 5.5228E+07 Kr-87 1.0965E-10 3.8710E-21 2.6795E+04 1.3743E+06 Kr-88 3.5334E-09 2.8179E-19 1.9284E+06 9.0338E+06 1-131 1.4196E-07 1.1450E-15 5.2638E+09 8.4474E+08 1-132 4.2504E-09 4.1178E-19 1.8786E+06 2.2819E+08 1-133 1.1547E-07 1.0193E-16 4.6154E+08 8.4937E+08 1-135 2.2558E-08 6.4235E-18 2.8654E+07 2.7887E+08 Re-131m 1.7665E-08 2.0983E-16 9.6461E+08 1.6561E+07 Re-133m 1.3470E-07 3.0046E-16 1.3605E+09 1.3102E+08 Re-133 2.1899E-06 1.1699E-14 5.2973E+10 2.0705E+09 Re-135m 1.3593E-08 1.4991E-19 6.6874E+05 1.9293E+07 Re-135 9.9321E-08 3.8893E-17 1.7349E+08 8.6030E+07 Cs-134 3.6190E-09 2.7971E-15 1.2571E+10 2.2474E+07 Cs-136 3.4598E-09 4.7206E-17 2.0903E+08 2.1819E+07 Cs-137 1.7113E-09 1.9674E-14 8.6481E+10 1.0624E+07 Rb-88 1.6616E-09 1.3842E-20 9.4725E+04 1.4101E+07 Br-83 1.3406E-10 8.4861E-21 6.1572E+04 6.6048E+06 Arbitrary Volume Transport Group Inventory:

Time (h) =

8.0000 Atmosphere Sump Noble gases (atoms) 1.1252E+12 0.0000E+00 Elemental I (atoms) 5.5832E+09 0.0000E+00 Organic I (atoms) 1.7268E+08 0.0000E+00 Aerosols (kg) 2.2518E-14 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 5.7158E-16 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 6.1748E-16 Total I (Ci) 2.8425E-07 Release Volume to Environment Transport Group Inventory:

Time (h) =

8.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Transported 3.3881E+24 1.4131E+22 4.3704E+20 5.3309E-02 Detailed model information at time (H)

=

18.0000 EAB Doses:

Time (h) = 18.0000 Whole Body Thyroid TIDE Delta dose (rem) 1.6027E-03 1.0082E+00 3.3957E-02 Accumulated dose (rem) 2.3288E-02 2.2072E+01 7.3484E-01 LPZ Doses:

Time (h) = 18.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.1714E-04 1.3659E-01 4.6007E-03

DC0004O-118 Revision 0 Page 72 of 97 Accumulated dose (rem)

TSC Doses:

Time (h) = 18.0000 Delta dose (rem)

Accumulated dose (rem) 4.4493E-03 Whole Body 1.2160E-05 3.5526E-04 4.2475E+00 Thyroid 2.7846E-01 6.7199E+00 1.4139E-01 TIDE 8.9492E-03 2.1698E-01 Arbitrary Volume Compartment Nuclide Inventory:

Time (h) =

18.0000 Ci kg Atoms Decay Kr-85m 4.3293E-10 5.2607E-20 3.7272E+05 8.3419E+06 Kr-85 2.9623E-08 7.5506E-14 5.3495E+11 9.4688E+07 Kr-88 1.5392E-10 1.2275E-20 8.4004E+04 9.9142E+06 1-131 6.0899E-08 4.9122E-16 2.2582E+09 9.2733E+08 1-132 9.2825E-11 8.9928E-21 4.1027E+04 2.2899E+08 1-133 3.6796E-08 3.2482E-17 1.4708E+08 9.0754E+08 1-135 3.5152E-09 1.0010E-18 4.4651E+06 2.8714E+08 Re-131m 8.6920E-09 1.0325E-16 4.7464E+08 2.8235E+07 Re-133m 5.9715E-08 1.3320E-16 6.0314E+08 2.1558E+08 Re-133 1.0497E-06 5.6081E-15 2.5393E+10 3.4992E+09 Re-135m 1.7140E-09 1.8903E-20 8.4324E+04 2.3879E+07 Re-135 3.6762E-08 1.4395E-17 6.4216E+07 1.4516E+08 Cs-134 1.5922E-09 1.2306E-15 5.5305E+09 2.4595E+07 Cs-136 1.4895E-09 2.0324E-17 8.9993E+07 2.3825E+07 Cs-137 7.5315E-10 8.6587E-15 3.8061E+10 1.1627E+07 Rb-88 4.1205E-10 3.4326E-21 2.3491E+04 1.4277E+07 Arbitrary Volume Transport Group Inventory:

Time (h) = 18.0000 Atmosphere Sump Noble gases (atoms) 5.6148E+ll 0.0000E+00 Elemental I (atoms) 2.3375E+09 0.0000E+00 Organic I (atoms) 7.2293E+07 0.0000E+00 Aerosols (kg) 9.9096E-15 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 2.3705E-16 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 2.5084E-16 Total I (Ci) 1.0130E-07 Release Volume to Environment Transport Group Inventory:

Pathway Time (h) = 18.0000 Filtered Transported Noble gases (atoms) 0.0000E+00 3.4479E+24 Elemental I (atoms) 0.0000E+00 1.4132E+22 Organic I (atoms) 0.0000E+00 4.3708E+20 Aerosols (kg) 0.0000E+00 5.3314E-02 Detailed model information at time (H) =

24.0000 EAB Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.3044E-12 1.6209E-09 5.4338E-11 Accumulated dose (rem) 2.3288E-02 2.2072E+01 7.3484E-01 LPZ Doses:

Time (h) = 24.0000 Whole Body Thyroid TIDE Delta dose (rem) 3.1220E-13 2.1960E-10 7.3619E-12 Accumulated dose (rem) 4.4493E-03 4.2475E+00 1.4139E-01 TSC Doses:

Time (h) = 24.0000 Whole Body Thyroid TIDE Delta dose (rem) 4.9847E-07 1.2775E-02 4.1061E-04 Accumulated dose (rem) 3.5576E-04 6.7327E+00 2.1740E-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

D000040-118 Revision 0 Page 73 of 97 Elemental I (atoms) 0.0000E+00 0.0000E+00 Organic I (atoms)

Aerosols (kg) 0.0000E+00 0.0000E+00 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 3.4479E+24 Elemental I (atoms) 0.0000E+00 1.4132E+22 Organic I (atoms) 0.0000E+00 4.3709E+20 Aerosols (kg) 0.0000E+00 5.3314E-02 Detailed model information at time (H) =

96.0000 HAS Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 2.3288E-02 2.2072E+01 7.3484E-01 LPZ Doses:

Time (h) =

96.0000 Whole Body Thyroid TIDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 4.4493E-03 4.2475E+00 1.4139E-01 TSC Doses:

Time (h) = 96.0000 Whole Body Thyroid TIDE Delta dose (rem) 3.9867E-17 1.1208E-12 3.6040E-14 Accumulated dose (rem) 3.5576E-04 6.7327E+00 2.1740E-01 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 Decay 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) =

96.0000 Pathway Filtered Transported Noble gases (atoms) 0.0000E+00 3.4479E+24 Elemental I (atoms) 0.0000E+00 1.4132E+22 Organic I (atoms) 0.0000E+00 4.3709E+20 Aerosols (kg) 0.0000E+00 5.3314E-02 Detailed model information at time (H) 720.0000 EAS Doses:

Time (h) = 720.0000 Whole Body Thyroid TIDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 2.3288E-02 2.2072E+01 7.3484E-01 LPZ Doses:

Time (h) = 720.0000 Whole Body Thyroid TIDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 4.4493E-03 4.2475E+00 1.4139E-01 TSC Doses:

D000040-118 Revision 0 Page 74 of 97 Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.0885-135 8.0203-131 2.6109-132 Accumulated dose (rem) 3.5576E-04 6.7327E+00 2.1740E-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 3.4479E+24 Elemental I (atoms) 0.0000E+00 1.4132E+22 Organic I (atoms) 0.0000E+00 4.3709E+20 Aerosols (kg) 0.0000E+00 5.3314E-02 837 1-131 Summary Time (hr)

Arbitrary Volume 1-131 (Curies)

Environment 1-131 (Curies)

TSC 1-131 (Curies) 0.000 1.0710E-05 3.5699E-01 8.5331E-05 0.401 1.0695E-05 2.5753E+02 3.1759E-02 0.500 1.0691E-05 3.2096E+02 3.4543E-02 0.800 8.7208E-08 3.2253E+02 1.1367E-02 1.100 8.7114E-08 3.2410E+02 3.8910E-03 1.400 8.7021E-08 3.2567E+02 1.4795E-03 1.700 8.6927E-08 3.2723E+02 7.0146E-04 2.000 8.6833E-08 3.2879E+02 4.5027E-04 2.300 1.4489E-07 3.3140E+02 4.6152E-04 2.600 1.4474E-07 3.3401E+02 4.6481E-04 2.900 1.4458E-07 3.3661E+02 4.6553E-04 3.200 1.4442E-07 3.3921E+02 4.6542E-04 3.500 1.4427E-07 3.4181E+02 4.6504E-04 3.800 1.4411E-07 3.4441E+02 4.6458E-04 4.100 1.4396E-07 3.4700E+02 4.6410E-04 4.400 1.4380E-07 3.4959E+02 4.6360E-04 4.700 1.4365E-07 3.5217E+02 4.6310E-04 5.000 1.4349E-07 3.5476E+02 4.6260E-04 5.300 1.4334E-07 3.5734E+02 4.6211E-04 5.600 1.4318E-07 3.5992E+02 4.6161E-04 5.900 1.4303E-07 3.6249E+02 4.6111E-04 6.200 1.4288E-07 3.6507E+02 4.6062E-04 6.500 1.4272E-07 3.6764E+02 4.6012E-04 6.800 1.4257E-07 3.7020E+02 4.5962E-04 7.100 1.4242E-07 3.7277E+02 4.5913E-04 7.400 1.4226E-07 3.7533E+02 4.5863E-04 7.700 1.4211E-07 3.7789E+02 4.5814E-04 8.000 1.4196E-07 3.8044E+02 4.5765E-04 8.300 6.3059E-08 3.8158E+02 2.1435E-04 8.600 6.2991E-08 3.8271E+02 1.3581E-04 8.900 6.2923E-08 3.8385E+02 1.1040E-04 9.200 6.2855E-08 3.8498E+02 1.0213E-04 9.500 6.2788E-08 3.8611E+02 9.9396E-05 9.800 6.2720E-08 3.8724E+02 9.8441E-05 10.100 6.2652E-08 3.8837E+02 9.8062E-05 10.400 6.2585E-08 3.8949E+02 9.7868E-05 18.000 6.0899E-08 4.1761E+02 9.5191E-05 24.000 0.0000E+00 4.1761E+02 1.4139E-14

TO-31080'9 TO+az9Z8'T (max)

(wax) 3Q3s PFoxAq ZO-36188'1 (max)

.Cpoa aTogM 0'0 (xg) army a`t3 sasoa xnog-omi asxot4 10-30VL1'Z 00+3LZ£L'9 TO-36ET4'T 00+3SL4Z'4 TO-3V8VE'L TO+3ZLOZ'Z 000'OZL TO-307Lt'Z 00+3LZEL'9 TO-36ET4't 00+3SLVZ'4 TO-3V84£'L TO+3ZLOZ'Z 000'96 t0-30VLt'Z 00+3LZEL'9 t0-36ET4't 00+aSLVZ'4 TO-3484£'L TO+3ZLOZ'Z 000'62 T0-3869t'Z 00+366TL'9 10-36ET4'T 00+35LVZ'4 TO-3484£'L t0+3ZLOZ'Z 000'8t TO-3980T'Z 00+3Z6ZS'9 T0-3Z6LE't 00+34441'7 t0-3LZ60'L TO+3ZT£T'Z 004'02 TO-3T90T'Z 00+3STZS'9 t0-38LLE't 00+34041'4 t0-3EZB0'L t0+3Z8ZT'Z 001'02 t0-39E0I'Z 00+3LEt5'9 TO-349L£'T 00+3Z9£T'4 TO-36TLO'L t0+3t5Zt'Z 008'6 TO-3ttOt'Z OO+3650S'9 T0-30SLE'I 00+30Z£T'4 TO-aST90'L tO+30ZZt'Z 005'6 TO-3S860'Z 00+30864'9 t0-39ELE't 00+38LZt'4 t0-30TS0'L TO+36811'2 OOZ'6 TO-38560'2 0O+39684'9 TO-3tZLE't 00+39EZt'V t0-3SO40'L TO+38STt'Z 006'8 TO-3LZ60'Z 00+30084'9 TO-3LOL£'T 00+376II'7 t0-366Z0'L t0+3LZS1'Z 009'8 TO-34880'2 00+39994'9 TO-3£69£'1 00+3ZSiT'4 t0-346T0'L tO+35601'2 00£'8 TO-34080'2 00+35144'9 TO-38L9E'T 00+360Tt'4 t0-38800'L TO+34902'2 000'8 10-39890'2 00+30504'9 TO-3065E'T 00+32480'4 I0-39£96'9 1O+3LZ60'Z 00L'L t0-36950'2 00+3589£'9 10-3Z0SE 100+34LS0'7 T0-3£816'9 T0+306L0'Z 004'L t0-3IS40'Z 00+382££'9 20-3£TVE'i 00+3SOE0'4 t0-36ZL8'9 TO+3ZS90'Z OOT'L TO-3EEE0'Z 00+3t96Z'9 t0-34ZEE'T 00+39£00'6 I0-3ELZ8'9 tO+36TS0'Z 008'9 TO-3STZ0'Z 00+3E85Z'9 t0-3SEZE'T O0+399L6'£ T0-39TBL'9 20+39LE0'Z 005'9 I0-39600'2 00+3SIZZ'9 T0-394tE'T 00+39646'£ TO-38S£L'9 TO+38£ZO'Z OOZ'9 I0-3LL66'1 00+35481'9 TO-3950£'1 00+39ZZ6'E T0-36689'9 T0+36600'Z 006'5 TO-38986'T 00+3VL71'9 20-3996Z't 00+3£968'E T0-36£49'9 1O+36566'1 009'9 TO-36EL6't 00+3E0tt'9 T0-39L8Z'T 00+3T898'E T0-3LL69'9 10+30286'1 00£'5 t0-36T96'T 00+3TEL0'9 T0-398LZ'T 00+380V8*E t0-3ETSS'9 T0+30896'1 000'5 TO-36646'T 00+3LSSO'9 T0-3S69Z'T 00+ZVEt8'E TO-3690S'9 TO+30456'1 OOL'V T0-38LE6,'t 00+3E866'S TO-34O9Z'T 00+3O98L'E TO-3E897'9 t0+366£6'1 004'6 TO-38SZ6't 00+38096'5 TO-3Et5Z'T 00+3S8SL'E T0-a9TT4'9 20+38SZ6't OOT'V TO-3LEt6't 00+3ZEZ6'S TO-3TZVZ'T 00+360EL'E TO-3L49E'9 TO+3LTT6't 008'E 10-3ST06'T 00+35588'5 t0-30£EZ't 00+3ZEOL'E TO-39LT£'9 TO+3SL68'1 OOS'E 1O-37688'1 00+3LL78'S t0-3LEZZ't 00+3SSL9'E TO-3VOLZ'9 20+3££88'1 OOZE TO-3ZLL8't 00+36608'5 TO-3SVTZ'T 00+3LL49'E t0-3tEZZ'9 t0+3t698't 006'2 TO-30598'1 00+aOZLL'S TO-3ZSOZ'T OO+36619'£ t0-395L1'9 10+38758'2 009'2 T0-38Z98'T 00+3Z'EL'S TO-36561'1 00+30265'£ 10-36LZT'9 10+35078'1 0O£'2 10-38048'1 00+36969'9 TO-3998t't 00+30795'5 T0-3IO80'9 T0+3Z9Z8'T 000'2 t0-3Z9Z8'T 00+aSTS9'S TO-30TBT'T 00+3ZLVS'E t0-34150'9 TO+39LT8'1 OOL'T 10-3066L'i 00+3£L99'9 I0-39SLT'I 00+3EOES'E 10-39ZZ0'9 1O+36808'2 OOV'T TO-3TE£L'1 00+3tE9E'S TO-3L69T'1 00+3VETS'£ T0-39£66'S TO+3E008't 001'1 T0-3L97S'T 00+3Z98L'V TO-3T49T'T 00+3S964'£ T0-39V96'9 TO+39T6L't 008'0 Z0-35498'6 00+3ZZS0'E IO-37851'2 OO+3S6LV'E 10-345£6'5 TO+36ZSL'I 00S'0 ZO-39£56'9 00+3SIST'Z ZO-36862'6 00+39Z6L'Z t0-3L49L'7 TO+360£7'1 TOV'0 00+30000'0 00+30000'0 00+30000'0 00+30000'0 00+30000'0 00+30000'0 000'0 (max)

(wax)

(Max)

(was)

(max)

(xg) 3Q3s PFoxSgL MGM PFoxxgs 3Q3s PFoxdgy away 3SS Za'1 aH3 dsammns asoa aeF3etmmmQ 00+30000'0 Z0+3T9Lt'4 00+30000'0 000'OZL ZEt-L6Z9'T Z0+3I9LT'7 00+30000'0 000'96 L6 J° SL ° d 0 UOTSTAag 81 I-0t000DQ

DO00040-118 Revision 0 Page 76 of 97 Attachment No. 7 MSLB concurrent I Spike

D000040-118 Revision 0 Page 77 of 97 RADTRAD Version 3.03 (Spring 2001) run on 12/12/2011 at 7:36:12 File information Plant file

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

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

= c:\\radtrad3.03\\2011 mslb Dose Conversion file = c:\\radtrad3.03\\2011 mslb TSC\\Att 7 MSLB concurrent I Spike TSC.psf tsc\\mslb 1.2 m added concurrent.nif tsc\\mslbl.2 m added concurrent iodine spike.rft tsc\\mslb.inp Radtrad 3.03 4/15/2001 SGTR Nuclide Inventory File:

c:\\radtrad3.03\\2011 mslb tsc\\mslb 1.2 m added concurrent.nif Plant Power Level:

1.0327E+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

DC0004O-118 Revision 0 Page 78 of 97 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 mslb tsc\\mslb.inp c:\\radtrad3.03\\2011 mslb tsc\\mslbl.2 m added concurrent iodine spike.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

2 0.0000E+00 1.2000E+04 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 1.2000E+04 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

D000040-118 Revision 0 Page 81 of 97 RADTRAD Version 3.03 (Spring 2001) run on 12/12/2011 at 7:36:12 Plant Description Number of Nuclides = 22 Inventory Power =

1.0000E+00 MWth Plant Power Level =

1.0327E+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 Compartment type is Normal (Cubic feet)

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

DC0004O-118 Revision 0 Page 82 of 97 RADTRAD Version 3.03 (Spring 2001) run on 12/12/2011 at 7:36:12 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 2.0800E-02 6.2500E-02 2.5000E-01 3.936E-02 IODINE 1.8100E-02 9.7100E-03 1.9000E-01 2.316E-03 CESIUM 8.7800E-01 1.0300E-02 3.4800E-02 1.754E-01 TELLURIUM 0.0000E+00 0.0000E+00 0.0000E+00 0.000E+00 STRONTIUM 0.0000E+00 0.0000E+00 0.0000E+00 0.000E+00 BARIUM 0.0000E+00 0.0000E+00 0.0000E+00 0.000E+00 RUTHENIUM 0.0000E+00 0.0000E+00 0.0000E+00 0.000E+00 CERIUM 0.0000E+00 0.0000E+00 0.0000E+00 0.000E+00 LANTHANUM 0.0000E+00 0.0000E+00 0.0000E+00 0.000E+00 Inventory Power =

1.

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

(Sv-m3/Bq-s)

Inhaled Thyroid (Sv/Bq)

Inhaled Effective (Sv/Bq)

Kr-85m 1

9.800E+00 1.613E+04 7.480E-15 0.000E+00 0.000E+00 Kr-85 1

4.140E+01 3.383E+08 1.190E-16 0.000E+00 0.000E+00 Kr-87 1

6.000E+00 4.578E+03 4.120E-14 0.000E+00 0.000E+00 Kr-88 1

1.740E+01 1.022E+04 1.020E-13 0.000E+00 0.000E+00 I-131 2

1.069E+03 6.947E+05 1.820E-14 2.920E-07 8.890E-09 I-132 2

8.430E+02 8.280E+03 1.120E-13 1.740E-09 1.030E-10 I-133 2

1.531E+03 7.488E+04 2.940E-14 4.860E-08 1.580E-09 I-134 2

1.460E+02 3.156E+03 1.300E-13 2.880E-10 3.550E-11 1-135 2

8.240E+02 2.380E+04 8.294E-14 8.460E-09 3.320E-10 Xe-131m 1

1.250E+01 1.023E+06 3.890E-16 0.000E+00 0.000E+00 Xe-133m 1

1.034E+02 1.892E+05 1.370E-15 0.000E+00 0.000E+00 Xe-133 1

1.578E+03 4.532E+05 1.560E-15 0.000E+00 0.000E+00 Xe-135m 1

2.800E+00 9.217E+02 2.040E-14 0.000E+00 0.000E+00 Xe-135 1

4.680E+01 3.272E+04 1.190E-14 0.000E+00 0.000E+00 Xe-138 1

3.500E+00 8.502E+02 1.787E-13 3.570E-12 2.740E-11 Cs-134 3

2.930E+01 6.507E+07 7.570E-14 1.110E-08 1.250E-08 Cs-136 3

2.840E+01 1.132E+06 1.060E-13 1.730E-09 1.980E-09 Cs-137 3

1.400E+01 9.467E+08 2.725E-14 7.930E-09 8.630E-09 Cs-138 3

7.000E-01 1.932E+03 1.210E-13 3.570E-12 2.740E-11 Rb-88 3

2.300E+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

3.000E-02 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-BB 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 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

DC00040-118 Revision 0 Page 83 of 97 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 Filter Efficiencies (%)

(cfm)

Aerosol Elemental Organic 0.0000E+00 1.2000E+04 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 1.2000E+04 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^-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^-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 TSC is in compartment 3

Location X/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 Time (hr) 0.0000E+00 2.4000E+01 9.6000E+01 7.2000E+02 Factor Data Occupancy Factor 1.0000E+00 6.0000E-01 4.0000E-01 0.0000E+00 USER SPECIFIED TIME STEP DATA - SUPPLEMENTAL TIME STEPS Time Time step 0.0000E+00 0.0000E+00

DC00040-118 Revision 0 Page 85 of 97 RADTRAD Version 3.03 (Spring 2001) run on 12/12/2011 at 7:36:12 Dose, Detailed model and Detailed Inventory Output Detailed model information at time (H) =

0.5000 EAB Doses:

Time (h) =

0.5000 Whole Body Delta dose (rem) 4.5911E-03 Thyroid 1.2535E+00 TIDE 1.2050E-01 Accumulated dose (rem) 4.5911E-03 LPZ Doses:

Time (h) =

0.5000 Whole Body Delta dose (rem) 8.9601E-04 Accumulated dose (rem) 8.9601E-04 TSC Doses:

Time (h) =

0.5000 Whole Body Delta dose (rem) 4.1363E-05 Accumulated dose (rem) 4.1363E-05 1.2535E+00 Thyroid 2.4464E-01 2.4464E-01 Thyroid 2.1457E-01 2.1457E-01 1.2050E-01 TIDE 2.3517E-02 2.3517E-02 TEDE 1.9889E-02 1.9889E-02 Arbitrary Volume Compartment Nuclide Inventory:

Time (h) =

0.5000 Ci kg Atoms Decay Kr-85m 6.4945E-09 7.8917E-19 5.5912E+06 4.4970E+05 Kr-85 2.9643E-08 7.5554E-14 5.3529E+11 1.9742E+06 Kr-87 3.2712E-09 1.1549E-19 7.9939E+05 2.5044E+05 Kr-88 1.1027E-08 8.7942E-19 6.0182E+06 7.8111E+05 I-131 6.6486E-07 5.3629E-15 2.4653E+10 4.4319E+07 I-132 4.5177E-07 4.3767E-17 1.9968E+08 3.2473E+07 1-133 9.3815E-07 8.2816E-16 3.7498E+09 6.3004E+07 I-134 6.1262E-08 2.2965E-18 1.0321E+07 5.0042E+06 I-135 4.8718E-07 1.3872E-16 6.1883E+08 3.3312E+07 Xe-131m 8.9491E-09 1.0630E-16 4.8868E+08 5.9598E+05 Xe-133m 7.3750E-08 1.6451E-16 7.4490E+08 4.9201E+06 Xe-133 1.1301E-06 6.0376E-15 2.7338E+10 7.5252E+07 Xe-135m 7.0137E-08 7.7354E-19 3.4506E+06 2.2458E+06 Xe-135 5.1405E-08 2.0129E-17 8.9794E+07 2.7060E+06 Xe-138 5.7764E-10 6.0074E-21 2.6215E+04 8.7516E+04 Cs-134 8.8554E-07 6.8443E-13 3.0759E+12 5.8977E+07 Cs-136 8.5741E-07 1.1699E-14 5.1802E+10 5.7135E+07 Cs-137 4.2313E-07 4.8646E-12 2.1383E+13 2.8181E+07 Cs-138 3.3670E-08 7.9570E-19 3.4723E+06 2.0399E+06 Rb-88 2.9344E-07 2.4446E-18 1.6729E+07 1.4147E+07 Br-83 5.3896E-11 3.4116E-21 2.4753E+04 3.8628E+03 Arbitrary Time (h) =

Volume Transport Group Inventory:

0.5000 Atmosphere Sump Noble gases (atoms) 5.6397E+11 0.0000E+00 Elemental I (atoms) 2.8355E+10 0.0000E+00 Organic I (atoms) 8.7696E+08 0.0000E+00 Aerosols (kg) 5.5607E-12 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 2.9589E-15

Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 3.4378E-15 Total I (Ci) 2.6032E-06 Release Volume to Environment Transport Group Inventory:

Pathway Time (h) =

0.5000 Filtered Transported Noble gases (atoms) 0.0000E+00 1.9052E+20 Elemental I (atoms) 0.0000E+00 6.1360E+18 Organic I (atoms) 0.0000E+00 1.8977E+17 Aerosols (kg) 0.0000E+00 1.2237E-03 Detailed model information at time (H) =

2.0000 EAR Doses:

Time (h) =

2.0000 Whole Body Thyroid Delta dose (rem) 1.1700E-03 6.2801E-01 TIDE 2.1568E-02 Accumulated dose (rem) 5.7611E-03 1.8815E+00 LPZ Doses:

1.4207E-01 Time (h) =

2.0000 Whole Body Thyroid Delta dose (rem) 2.2834E-04 1.2256E-01 TIDE 4.2093E-03 Accumulated dose (rem) 1.1243E-03 3.6720E-01 TSC Doses:

2.7727E-02 Time (h) =

2.0000 Whole Body Thyroid Delta dose (rem) 4.8706E-05 3.3998E-01 TEDE 2.1818E-02 Accumulated dose (rem) 9.0069E-05 5.5456E-01 4.1707E-02 Arbitrary Volume Compartment Nuclide Inventory:

Time (h) =

2.0000 Ci kg Atoms Decay Kr-85m 5.1576E-09 6.2672E-19 4.4402E+06 1.6096E+06 Kr-85 2.9690E-08 7.5674E-14 5.3614E+11 7.9062E+06 Kr-87 1.4465E-09 5.1067E-20 3.5349E+05 6.9763E+05 Kr-88 7.6589E-09 6.1080E-19 4.1799E+06 2.6290E+06 I-131 1.1825E-07 9.5384E-16 4.3848E+09 6.8010E+07 I-132 5.1406E-08 4.9802E-18 2.2721E+07 4.5459E+07 I-133 1.5958E-07 1.4087E-16 6.3786E+08 9.5699E+07 1-134 3.3461E-09 1.2543E-19 5.6371E+05 6.2861E+06 I-135 7.4438E-08 2.1196E-17 9.4553E+07 4.9418E+07 Xe-131m 8.9600E-09 1.0643E-16 4.8927E+08 2.3865E+06 Xe-133m 7.2992E-08 1.6282E-16 7.3724E+08 1.9592E+07 Xe-133 1.1313E-06 6.0436E-15 2.7365E+10 3.0135E+08 Xe-135m 6.8381E-08 7.5418E-19 3.3643E+06 1.7220E+07 Xe-135 9.9623E-08 3.9011E-17 1.7402E+08 1.7931E+07 Cs-134 3.4626E-09 2.6762E-15 1.2027E+10 5.9669E+07 Cs-136 3.3417E-09 4.5595E-17 2.0190E+08 5.7804E+07 Cs-137 1.6546E-09 1.9022E-14 8.3617E+10 2.8511E+07 Rb-88 3.0726E-09 2.5597E-20 1.7517E+05 1.4452E+07 Arbitrary Volume Transport Group I nventory:

Time (h) =

2.0000 Atmosphere Sump Noble gases (atoms) 5.6492E+ll 0.0000E+00 Elemental I (atoms) 4.9863E+09 0.0000E+00 Organic I (atoms) 1.5422E+08 0.0000E+00 Aerosols (kg) 2.1744E-14 0.0000E+00 Dose Effective (C+/-/cc) 1-131 (Thyroid) 5.2011E-16 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 5.9686E-16 Total I (Ci) 4.0702E-07 Release Volume to Environment Transport Group Inventory:

Time (h) =

Pathway 2.0000 Filtered Transported Noble gases (atoms) 0.0000E+00 7.1779E+21 Elemental I (atoms) 0.0000E+00 6.6586E+18 Organic I (atoms) 0.0000E+00 2.0594E+17 Aerosols (kg) 0.0000E+00 1.2409E-03 Detailed model information at time (H)

=

8.0000

EAB Doses:

Time (h) =

8.0000 Whole Body Delta dose (rem) 3.0315E-02 Thyroid 3.0012E+01 TIDE 9.6305E-01 Accumulated dose (rem) 3.6076E-02 LPZ Doses:

3.1893E+01 1.1051E+00 Time (h) =

8.0000 Whole Body Delta dose (rem) 5.9163E-03 Thyroid 5.8571E+00 TIDE 1.8795E-01 Accumulated dose (rem) 7.0406E-03 6.2243E+00 2.1568E-01 TSC Doses:

Time (h) =

Delta dose 8.0000 Whole Body (rem) 4.0834E-04 Thyroid 7.6548E+00 TIDE 2.3837E-01 Accumulated dose (rem) 4.9841E-04 8.2094E+00 2.8008E-01 Arbitrary Volume Compartment Nuclide Inventory:

Time (h) =

8.0000 Ci kg Atoms Decay Kr-85m 4.0778E-09 4.9550E-19 3.5106E+06 6.9817E+06 Kr-85 5.9392E-08 1.5138E-13 1.0725E+12 5.5373E+07 Kr-87 1.0993E-10 3.8811E-21 2.6865E+04 1.3779E+06 Kr-88 3.5426E-09 2.8252E-19 1.9334E+06 9.0575E+06 1-131 1.4399E-06 1.1615E-14 5.3393E+10 1.2313E+09 I-132 1.0486E-07 1.0159E-17 4.6346E+07 2.8180E+08 I-133 1.6257E-06 1.4351E-15 6.4980E+09 1.5339E+09 I-134 3.6237E-10 1.3584E-20 6.1047E+04 1.3239E+07 I-135 4.9367E-07 1.4057E-16 6.2707E+08 5.9878E+08 Re-131m 1.7908E-08 2.1272E-16 9.7789E+08 1.6705E+07 Xe-133m 1.3908E-07 3.1024E-16 1.4047E+09 1.3354E+08 Re-133 2.2537E-06 1.2040E-14 5.4518E+10 2.1070E+09 Re-135m 9.0321E-08 9.9615E-19 4.4437E+06 1.0638E+08 Re-135 3.8709E-07 1.5158E-16 6.7617E+08 2.7133E+08 Cs-134 4.5216E-09 3.4947E-15 1.5706E+10 6.3283E+07 Cs-136 4.3074E-09 5.8771E-17 2.6024E+08 6.1269E+07 Cs-137 2.1611E-09 2.4845E-14 1.0921E+11 3.0238E+07 Rb-88 1.2253E-09 1.0207E-20 6.9853E+04 1.5232E+07 Arbitrary Volume Transport Group I nventory:

Time (h) =

8.0000 Atmosphere Sump Noble gases (atoms) 1.1301E+12 0.0000E+00 Elemental I (atoms) 5.8748E+10 0.0000E+00 Organic I (atoms) 1.8169E+09 0.0000E+00 Aerosols (kg) 2.8399E-14 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 6.0933E-15 Dose Effective (C+/-/cc) 1-131 (ICRP2 Thyroid) 6.7781E-15 Total I (Ci) 3.6645E-06 Release Volume to Environment Transport Group Inventory:

Pathway Time (h) =

8.0000 Filtered Transported Noble gases (atoms) 0.0000E+00 3.3994E+24 Elemental I (atoms) 0.0000E+00 3.4235E+23 Organic I (atoms) 0.0000E+00 1.0588E+22 Aerosols (kg) 0.0000E+00 4.1185E-02 Detailed model information at time (H) =

18.0000 EAB Doses:

Time (h) = 18.0000 Whole Body Thyroid TIDE Delta dose (rem) 1.7541E-02 1.4552E+01 4.6695E-01 Accumulated dose (rem) 5.3617E-02 4.6445E+01 1.5721E+00 LPZ Doses:

Time (h) = 18.0000 Whole Body Thyroid TIDE Delta dose (rem) 2.3765E-03 1.9715E+00 6.3264E-02 Accumulated dose (rem) 9.4171E-03 8.1958E+00 2.7894E-01

D000040-1 1 8 Revision 0 Page 88 of 97 TSC Doses:

Time (h) =

Delta dose 18.0000 Whole Body (rem) 1.3143E-04 Thyroid 3.8953E+00 TEDE 1.2047E-01 Accumulated dose (rem) 6.2983E-04 1.2105E+01 4.0055E-01 Arbitrary Volume Compartment Nuclide Inventory:

Time (h) =

18.0000 Ci kg Atoms Decay Kr-85m 4.3407E-10 5.2745E-20 3.7369E+05 8.3637E+06 Kr-85 2.9701E-08 7.5703E-14 5.3635E+11 9.4936E+07 Kr-88 1.5433E-10 1.2308E-20 8.4225E+04 9.9402E+06 1-131 8.4296E-07 6.7994E-15 3.1257E+10 2.3745E+09 1-132 3.1250E-09 3.0275E-19 1.3812E+06 3.0855E+08 1-133 7.0693E-07 6.2405E-16 2.8257E+09 2.6515E+09 1-135 1.0498E-07 2.9892E-17 1.3334E+08 8.4596E+08 Re-131m 8.9379E-09 1.0617E-16 4.8806E+08 2.8614E+07 Re-133m 6.3561E-08 1.4178E-16 6.4199E+08 2.2208E+08 Xe-133 1.1081E-06 5.9197E-15 2.6804E+10 3.5951E+09 Re-135m 4.6103E-08 5.0847E-19 2.2682E+06 1.3177E+08 Re-135 1.7084E-07 6.6900E-17 2.9843E+08 5.2174E+08 Cs-134 1.5969E-09 1.2342E-15 5.5469E+09 6.5411E+07 Cs-136 1.4887E-09 2.0312E-17 8.9941E+07 6.3274E+07 Cs-137 7.6352E-10 8.7779E-15 3.8585E+10 3.1255E+07 Rb-88 4.1017E-10 3.4170E-21 2.3383E+04 1.5298E+07 Arbitrary Volume Transport Group I nventory:

Time (h) = 18.0000 Atmosphere Sump Noble gases (atoms) 5.6458E+ll 0.0000E+00 Elemental I (atoms) 3.3191E+10 0.0000E+00 Organic I (atoms) 1.0265E+09 0.0000E+00 Aerosols (kg) 1.0032E-14 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 3.4032E-15 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 3.6755E-15 Total I (Ci) 1.6580E-06 Release Volume to Environment Transport Group Inventory:

Pathway Time (h) = 18.0000 Filtered Transported Noble gases (atoms) 0.0000E+00 3.3998E+24 Elemental I (atoms) 0.0000E+00 3.4237E+23 Organic I (atoms) 0.0000E+00 1.0589E+22 Aerosols (kg) 0.0000E+00 4.1191E-02 Detailed model information at time (H) =

24.0000 EAR Doses:

Time (h) = 24.0000 Whole Body Thyroid TIDE Delta dose (rem) 2.3083E-11 2.3241E-08 7.3954E-10 Accumulated dose (rem) 5.3617E-02 4.6445E+01 1.5721E+00 LPZ Doses:

Time (h) = 24.0000 Whole Body Thyroid TIDE Delta dose (rem) 3.1273E-12 3.1488E-09 1.0020E-10 Accumulated dose (rem) 9.4171E-03 8.1958E+00 2.7894E-01 TSC Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 4.9922E-06 1.8317E-01 5.6517E-03 Accumulated dose (rem) 6.3482E-04 1.2288E+01 4.0620E-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 3.3998E+24 Elemental I (atoms) 0.0000E+00 3.4237E+23 Organic I (atoms) 0.0000E+00 1.0589E+22 Aerosols (kg) 0.0000E+00 4.1191E-02 Detailed model information at time (H) =

96.0000 EAB Doses:

Time (h) = 96.0000 Whole Body Thyroid TIDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 5.3617E-02 4.6445E+01 1.5721E+00 LPZ Doses:

Time (h) = 96.0000 Whole Body Thyroid TIDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 9.4171E-03 8.1958E+00 2.7894E-01 TSC Doses:

Time (h) = 96.0000 Whole Body Thyroid TIDE Delta dose (rem) 3.7048E-16 1.5974E-11 4.9210E-13 Accumulated dose (rem) 6.3482E-04 1.2288E+01 4.0620E-01 Arbitrary Volume Compartment Nuclide Inventory:

Time (h) =

96.0000 Ci 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:

Time (h) =

96.0000 Pathway Filtered Transported Noble gases (atoms) 0.0000E+00 3.3998E+24 Elemental I (atoms) 0.0000E+00 3.4237E+23 Organic I (atoms) 0.0000E+00 1.0589E+22 Aerosols (kg) 0.0000E+00 4.1191E-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) 5.3617E=02 4.6445E+01 1.5721E+00 LPZ Doses:

Time (h) = 720.0000 Whole Body Thyroid TIDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 9.4171E-03 8.1958E+00 2.7894E-01 TSC Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE

D000040-118 Revision 0 Page 90 of 97 Delta dose (rem) 1.3265-134 1.1124-129 3.4078-131 Accumulated dose (rem) 6.3482E-04 1.2288E+01 4.0620E-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)

O.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 3.3998E+24 Elemental I (atoms) 0.0000E+00 3.4237E+23 Organic I (atoms) 0.0000E+00 1.0589E+22 Aerosols (kg)

O.0000E+00 4.1191E-02 837 1-131 Summary Time (hr)

Arbitrary Volume 1-131 (Curies)

Environment 1-131 (Curies)

TSC 1-131 (Curies) 0.000 6.6605E-07 2.2201E-02 5.3067E-06 0.401 6.6509E-07 1.6015E+01 1.9750E-03 0.500 6.6486E-07 1.9960E+01 2.1482E-03 0.800 1.1876E-07 2.2099E+01 9.9926E-04 1.100 1.1863E-07 2.4235E+01 6.2836E-04 1.400 1.1851E-07 2.6369E+01 5.0840E-04 1.700 1.1838E-07 2.8500E+01 4.6938E-04 2.000 1.1825E-07 3.0630E+01 4.5646E-04 2.300 1.4697E-06 5.7094E+01 3.3555E-03 2.600 1.4681E-06 8.3530E+01 4.2871E-03 2.900 1.4666E-06 1.0994E+02 4.5841E-03 3.200 1.4650E-06 1.3632E+02 4.6765E-03 3.500 1.4634E-06 1.6267E+02 4.7028E-03 3.800 1.4618E-06 1.8899E+02 4.7079E-03 4.100 1.4602E-06 2.1528E+02 4.7061E-03 4.400 1.4587E-06 2.4155E+02 4.7021E-03 4.700 1.4571E-06 2.6779E+02 4.6973E-03 5.000 1.4555E-06 2.9399E+02 4.6924E-03 5.300 1.4540E-06 3.2018E+02 4.6874E-03 5.600 1.4524E-06 3.4633E+02 4.6823E-03 5.900 1.4508E-06 3.7245E+02 4.6773E-03 6.200 1.4493E-06 3.9855E+02 4.6723E-03 6.500 1.4477E-06 4.2462E+02 4.6672E-03 6.800 1.4461E-06 4.5066E+02 4.6622E-03 7.100 1.4446E-06 4.7667E+02 4.6572E-03 7.400 1.4430E-06 5.0265E+02 4.6522E-03 7.700 1.4415E-06 5.2861E+02 4.6471E-03 8.000 1.4399E-06 5.5454E+02 4.6421E-03 8.300 8.7285E-07 5.7025E+02 2.4211E-03 8.600 8.7191E-07 5.8595E+02 1.7037E-03 8.900 8.7097E-07 6.0164E+02 1.4713E-03 9.200 8.7003E-07 6.1730E+02 1.3954E-03 9.500 8.6909E-07 6.3295E+02 1.3699E-03 9.800 8.6816E-07 6.4858E+02 1.3607E-03 10.100 8.6722E-07 6.6420E+02 1.3567E-03 10.400 8.6629E-07 6.7980E+02 1.3545E-03 18.000 8.4296E-07 1.0690E+03 1.3176E-03 24.000 0.0000E+00 1.0690E+03 1.9570E-13 96.000 0.0000E+00 1.0690E+03 2.2558-131 720.000 0.0000E+00 1.0690E+03 0.0000E+00

D000040-118 Revision 0 Page 91 of 97 Cumulative Dose Summary EAB LPZ TSC Time (hr)

Thyroid (rem)

TEDE (rem)

Thyroid (rem)

TEDE (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 1.0062E+00 9.6689E-02 1.9636E-01 1.8870E-02 1.5127E-01 1.4015E-02 0.500 1.2535E+00 1.2050E-01 2.4464E-01 2.3517E-02 2.1457E-01 1.9889E-02 0.800 1.3800E+00 1.2486E-01 2.6932E-01 2.4369E-02 3.5130E-01 3.1644E-02 1.100 1.5060E+00 1.2920E-01 2.9392E-01 2.5215E-02 4.2214E-01 3.6309E-02 1.400 1.6316E+00 1.3351E-01 3.1843E-01 2.6057E-02 4.7168E-01 3.8683E-02 1.700 1.7568E+00 1.3780E-01 3.4286E-01 2.6894E-02 5.1428E-01 4.0316E-02 2.000 1.8815E+00 1.4207E-01 3.6720E-01 2.7727E-02 5.5456E-01 4.1707E-02 2.300 3.4267E+00 1.9226E-01 6.6875E-01 3.7521E-02 7.4052E-01 4.7571E-02 2.600 4.9667E+00 2.4219E-01 9.6931E-01 4.7266E-02 1.0779E+00 5.8120E-02 2.900 6.5017E+00 2.9187E-01 1.2689E+00 5.6962E-02 1.4631E+00 7.0145E-02 3.200 8.0319E+00 3.4131E-01 1.5675E+00 6.6611E-02 1.8628E+00 8.2613E-02 3.500 9.5571E+00 3.9053E-01 1.8652E+00 7.6216E-02 2.2663E+00 9.5194E-02 3.800 1.1078E+01 4.3952E-01 2.1619E+00 8.5777E-02 2.6701E+00 1:0778E-01 4.100 1.2593E+01 4.8829E-01 2.4577E+00 9.5296E-02 3.0733E+00 1.2034E-01 4.400 1.4104E+01 5.3686E-01 2.7526E+00 1.0477E-01 3.4753E+00 1.3287E-01 4.700 1.5611E+01 5.8522E-01 3.0466E+00 1.1421E-01 3.8762E+00 1.4535E-01 5.000 1.7113E+01 6.3339E-01 3.3398E+00 1.2361E-01 4.2759E+00 1.5779E-01 5.300 1.8610E+01 6.8136E-01 3.6320E+00 1.3297E-01 4.6744E+00 1.7019E-01 5.600 2.0103E+01 7.2914E-01 3.9234E+00 1.4230E-01 5.0717E+00 1.8256E-01 5.900 2.1592E+01 7.7674E-01 4.2139E+00 1.5159E-01 5.4679E+00 1.9488E-01 6.200 2.3076E+01 8.2416E-01 4.5036E+00 1.6084E-01 5.8629E+00 2.0716E-01 6.500 2.4556E+01 8.7141E-01 4.7924E+00 1.7007E-01 6.2568E+00 2.1941E-01 6.800 2.6032E+01 9.1848E-01 5.0804E+00 1.7925E-01 6.6495E+00 2.3162E-01 7.100 2.7503E+01 9.6539E-01 5.3676E+00 1.8841E-01 7.0411E+00 2.4379E-01 7.400 2.8971E+01 1.0121E+00 5.6539E+00 1.9753E-01 7.4316E+00 2.5592E-01 7.700 3.0434E+01 1.0587E+00 5.9395E+00 2.0662E-01 7.8210E+00 2.6802E-01 8.000 3.1893E+01 1.1051E+00 6.2243E+00 2.1568E-01 8.2094E+00 2.8008E-01 8.300 3.2347E+01 1.1198E+00 6.2858E+00 2.1767E-01 8.4890E+00 2.8876E-01 8.600 3.2800E+01 1.1345E+00 6.3472E+00 2.1966E-01 8.6560E+00 2.9394E-01 8.900 3.3252E+01 1.1491E+00 6.4084E+00 2.2164E-01 8.7865E+00 2.9798E-01 9.200 3.3702E+01 1.1637E+00 6.4694E+00 2.2361E-01 8.9050E+00 3.0165E-01 9.500 3.4151E+01 1.1782E+00 6.5302E+00 2.2558E-01 9.0195E+00 3.0520E-01 9.800 3.4599E+01 1.1927E+00 6.5909E+00 2.2754E-01 9.1325E+00 3.0870E-01 10.100 3.5046E+01 1.2071E+00 6.6515E+00 2.2949E-01 9.2447E+00 3.1217E-01 10.400 3.5492E+01 1.2215E+00 6.7119E+00 2.3144E-01 9.3566E+00 3.1563E-01 18.000 4.6445E+01 1.5721E+00 8.1958E+00 2.7894E-01 1.2105E+01 4.0055E-01 24.000 4.6445E+01 1.5721E+00 8.1958E+00 2.7894E-01 1.2288E+01 4.0620E-01 96.000 4.6445E+01 1.5721E+00 8.1958E+00 2.7894E-01 1.2288E+01 4.0620E-01 720.000 4.6445E+01 1.5721E+00 8.1958E+00 2.7894E-01 1.2288E+01 4.0620E-01 Worst Two-Hour Doses EAB Time Whole Body Thyroid TEDE (hr)

(rem)

(rem) 2.0 1.2248E-02 1.0207E+01 3.2997E-01

DO00040-118 Revision 0 Page 92 of 97 Attachment No. 8 Copy of Reference 8

D000040-118 Revision 0 Page 93 of 97 Wes ngthouse Energy Systems Electric corporation Mr. R. B. Clary Manager, SG Project South Carolina Electric & Gas Co.

P.O. Box 88 Jenkinsville, SC 29065 Attention:

John S. Prick CGE-93-0007SGUL NwWraADMI0 lemmZVOWsio, Sn 355 P5s rjig t Pe[Its3te a 1 5 230 0 3 55 March 1, 1993 PS-CGE-0007

Subject:

Purchase Order No. Q594687 VCSNS RSG/Uprating: Steam Release for Dose Analysis and write-up for Source Terms

Dear Mr. Clary:

Attached for your information and reference in Gilbert Commonwealth's analyses for the VCSNS RSG/Uprating are:

1)

The steam releases and feedwater. delivery for use in the dose analysis (documented in Westinghouse internal letter ET-NSASD-TAI-93-60, 2 pages), and The licensing write-up for the source.terms used in the dose analysis (no internal Westinghouse letter, 5 pages).

This information is supplied in response to Mr. Paul Bunker's (Gilbert Commonwealth) request and was telecopied to him on March 1, per the agreed-upon schedule. Please contact D. 8. Augustine on 412-3.74-4213 it you have any questions regarding the attached information.

Very truly yours, Buddy B. Jolley, II Key Accounts Manager Carolinas District Power Systems Field Sales D. B. Augustine/vim SOf]LMDD --D9A430193

D000040-1 1 8 Revision 0 Page 94 of 97 WESTINGHOUSE PROPRIETARY CLASS 2 toss of ottsite Power Steam Release From Three Steam Generators 447900 Ibm (0-2 hours) 868300 Ibm (2-8 hours)

Feedwater Delivery To Three Steam Generators 375500 ibm (0-2 hours) 841800 Ibm (2-8 hours)

Steamline Break Failed Fuel 0°/C Steam Release From Two Untaulted 343700 Ibm (0-2 hours)

Steam Generators 733900 Ibm (2-8 hours)

Feedwater Delivery To Two Unfaulted 445600 Ibm (0.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months )

Steam Generators 721500 Ibm (2.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ) 4QGked Rotor Failed Fuel 15%

Steam Release From Three Steam Generators 447900 Ibm (0-2 hours) 868300 Ibm (2-8 hours)

Feedwater Delivery To Three Steam Generators 375500 Ibm (0-2 hours) 841800 Ibm (2.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months )

Rod Election Failed Fuel 1095 CM

DO00040-118 Revision 0 Page 95 of 97 Attachment No. 9 Copy of Reference 9

D000040-118 Revision 0 Page 96 of 97 ET-NSASD*TAi*93-049 Engineering. Technology Department From:

Nuclear Safety Analysis ul Strategic Development WIN:

284.5426 Date:

February 15, 1993 Subject V. C. Summer thprate / SO Replacement SLB M&E Inside Containment Data Keywords: Ct3E/SLB

Reference:

CN-TA-92.279 To:

D. B. Augustine ECE 4-20:

M.R. Zawaiick ECE 409 cc:

D. S. Love ECE 442 M.J. Proviano*

ECE 4.09 R. H. McFetrfdge' ECE 4-20 w/o attachment Attached please find steamtine break mass d^ energy release inside containment data for the V. C. Summer plant. This data incorporates the effects of both the proposed upraling as well as the installation of the 675 steam generator. This development of this data Is documented in the referenced cafe note.

Mass & energy release data hdve been calculated for five power levels: 4023x, 75%. 50%, 25% and 0%. At each power level, four break sizes have been examined.

A full doubte-ended-rupture (DER) of a main steam fine, resulting in a maximum break of 1.4 0 per steam generator due to the presence of the irrtegiaf flow restrlctor. the smallest DER which results in liquid entrainment In the btowdowtt the largest DER In which liquid entrakment does not occur-art. the largest break for which neither a secondary side isolation signal or water entrainment occur. This Last break size is referred to as a split break For the DERs. multiple failures have been assumed when generating the MaE data For all DER cases simultaneous falures of a feedwater Isolation valve. I train of safety injection, as well as an EFW runout control failure resulting In 1000 gpmrloop being delivered to the faulted loop throughout the simulation have been assumed Furthermore, for both the t 02% and 0%

full DER cases, an additional M&E case (DERID and DERSD) has been generated in which the EFW snout control failure does not occur resulting in 1000 gpm/SQ being-delivered for the first 30 seconds of the transient followed by 200 gpmltoop for the remainder of the event.

As previously discussed with you, the M&E data provided for the split breaks have no safety system actuation signals incorporated. It is to be used by the NE in generating the time at which the HI-t / Hi-2 containment signals occur. The NE has agreed to Inform Westinghouse of this time so that It may be incorporated In another split break case which Includes the Hi-t: /

Hi-2 signals. The second iteration of split break M&E data will then be transmitted to the NE.

This is being done to reduce the number of Split break cases which must be run.

For all of the cases analyzed, the steam volume within the unisotatatrte portion of the steam

D000040-118 Revision 0 Page 97 of 97 Time Flow Rate :

Energy Mass Release lntegrttted.,.

Energy Release

{ 10° otus) 00 00 0000 0000

.0000

.20 9519:

..11'.32 1'.904 9.263

.60 9102:..

10.63 5.578 6.638 1.60 3789.::.

10.47, 10.86 2.00 12468:

11.15 18.37 21.14 3.00.

19108 12.96 36.84 34,02

.4.00 19305:

12,71 56.18 46.86 5.00.

fmil.

12.11`.

74.88 69.22.

7.00 16157.

10.95 1199.1 82,14 10.0-12812 9.232 152.4 1'123 1.0. 6

12174, 8.907 159.8 117.7 10.8 3498.

2.529 160,5 118.2 15 0 2444.

2.121 172.7 127.8 26.0 1612.

1.705 182,3 137.3 602 857.1 1.031 214.3 175-8 1002 674.3 8095 251.5 220.4 200:2.

558.1

.6662 312.4 293.5 250.2 150.3 1762

.336.3 322.0 300.2 391.6

.4664

.:342.3 329.2 356.2 83.55 0969 348.5 336.5 400.2 27.38.

.0319

,354.6.

343.6 450.2 27.38

.0318...

359.9 349:8 500.2 27.38

.0318 365:1 356.0 600.21 31.14

.0359 373,1 365.2 700.2 30.85

.0356

. 375.7 368.3.

800.2 56,53

.0652 :.

.378.6.

371.0 1000.

.0000

.384.0 377.8 1250.

43.68 0503 390.9, 385.8 1500.

30.47

..0352':.

397.6 393.8 1800.

37.34.

0430 406.0 403.2 t:

l see 1108*tbtulsec) t STEAM LINE ISOLATION OCCURS AT T= 10.6 SEC FEEDWATER ISOLATION OCCURS AT.T--? 10.6:SEC

.'o% ROWER,.1 4 Fr2DER.

FAILVAESi FWIV'; 1' :Train St Steak Break Integrated

TECHNICAL WORK RECORD Originator:

Michael J. Feehan Date:

07/30/2012 System:

N/A Project Title Verification ofDC00040-118, RO ECR 50786 Page 1

of 3

1.0 Purpose

This TWR is developed to document the verification of DC00040-118, R0, "Main Steam Line Break - TSC."

2.0

Reference:

Calculation DC00040-118, R0, "Main Steam Line Break - 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 [AWES-110. ES-110, Attachment Ill is included as Attachment Ito 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 lAW 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 D000040-118, RO ECR 50786 Page 2

of 3

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

D000040-118 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 D000040-118, RO ECR 50786 Page 3

of 3

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

D000040-118 Revision 0 CALCULATIONS UTILIZING COMPUTER PROGRAMS:

El 0

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/

OcXoe, /

/C-e¢ C 07/30/2012 Verifier's Printed Name Verifier's Signature Date

ES-0110 ATTACHMENT XVI PAGE 1 OF7q D,/4<,

REVISION 2 g/p/2 REVIEW CONSIDERATIONS: OWNER'S ACCEPTANCE REVIEW ECR/Document Number: DC00040-079, DC00040-118 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 q

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

q

q 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 II 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 PAGE2OF,°I/ 0.

REVISION 2

$i38h Yes N/A 1:1 IM Does the design meet interfacing organizations operational/maintenance requirements?

D 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 En r q 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

Analysis Engineer Dave McCreary q

q q

q Dave McCrea

/

` 3j Z 01 Z Reviewer's Printed Name Reviewer's Sig ature Date

ES-o/Io

,aft X1 ar 41 Detailed Owners Acceptance Review Notes There are three general comments in all of the dose calculations that should be

$^z 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.

1RESPONSE: Agree. Statements: regarding_AI 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.

2). RESPONSE: Agree as noted. The text will be revised to state: "The 13,000 cfm assumed conservatively bounds the expected design flow rate value of

12,000 cfm.

The doses are conservatively-calculated assuming no credit for filtration throughout the accident; Prefer not to state that the TSC filtration capability and isolation times are currently unknown. There is a PAID showing. filters and we could actually have assumed an_operator action such as 30 minutes if we had chosen to do so.^

3)

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

-110 have been updated.

3). RE SPONSE: Agreeto delete revision levels RESPONSE to individual comments. Agree to all comments/corrections noted.

below:

Main Steam Line Break, D000040-118, 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.

Locked Rotor, DC00040-119, Rev. 0:

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./

Aev?

laue 4,

Al/ Cc

^S

,, p ji Z

ML14324A322

Text

Description:

SUMMARY

7.0 CONCLUSION

7.0 CONCLUSION

9.0 REFERENCES

Subject:

Dear Mr. Clary:

Reference:

1.0 Purpose

Reference:

3.0 Discussion

4.0 Comments

5.0 Results

Title:

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