ML093160589

Attachment 11 to Enclosure, Calculation GEN-PI-082, Rev. 0, Crea Analysis Titled, Control Rod Ejection Accident - Ast.

ML093160589
Person / Time
Site:	Prairie Island
Issue date:	09/08/2009
From:	Xcel Energy
To:	Office of Nuclear Reactor Regulation
References
L-PI-09-114 GEN-PI-082, Rev 0
Download: ML093160589 (146)

Text

ATTACHMENT 11 to ENCLOSURE CREA Analysis titled, "Control Rod Ejection Accident - AST" 145 Pages Follow

OF-0549 (FP-E-CAL-01), Rev. 3 PaNe I of 145 elEnergy- Calculation Signature Sheet Document Information NSPM Calculation (Doc) No: GEN-PI-082 Revision: 0

Title:

Control Rod Ejection Accident - AST Facility: E] MT Z PI J Unit: [ 1 0 2 Safety Class: Z SR El Aug Q l- Non SR Special Codes: E] Safeguards El Proprietary Type: Calc Sub-Type:

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Major Revisions EC Number: 13720 - Vendor Calc Vendor Name or Code: Vendor Doc No:

Description of Revision: Original Issue Prepared by: Gopal J. Patel Date:09/08/2009 Reviewed by: Thomas J. Msci Date: 09/08/2009 Type of Review: Z Design Verific tion Te Review E] Vendor Acceptance Method Used (For DV On y): [ Review "- Alternate Calc Rl Test Approved b/4.,., 7z*73C( I Date: 101S1O-0 Minor Revisions EC No: E-]Vendor Calc:

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Record Retention: Retain this form with the associated calculation for the life of the plant.

OF-0549 (FP-E-CAL-01). Rev. 3 Page 2 of 145

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Type of Review: EI Design Verification EI Tech Review 0I Vendor Acceptance Method Used (For DVOnly): L] Review r- Alternate Calc -]Test Approved by: Date:

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Type of Review: [-- Design Verification [:]+Tech Review [* Vendor Acceptance Method Used (For DV only): 0* Review E-- Alternate Calc E-- Test Approved by:IDae Record Retention: Retain this form with the associated calculation for the life of the plant.

QF-0549 (FP-E-CAL-01), Rev. 3 Page 3 of 145 ScelEnergy- Calculation Signature Sheet NOTE: This reference table is used for data entry into the PassPort Controlled Documents Module, reference tables (C01 2 Panel). It may also-be used as the reference section of the calculation. The input documents, output documents and other references should all be listed here. Add additional lines as needed, Reference Documents (PassPort C012 Panel from C020)

Controlled* Ref Type"

1. Doc? + Document Name Document Number Doc Rev (if known)

Type (if known) 1 ~ RG Alternative Radiological Source Terms for Evaluating Design 1.183 July 2000 Zinput EOutput Basis Accidents at Nuclear Power Reactors 2 DOC A Simplified Model for Radionuclide Transport and Removal and NUREGICR-6604 Dec 1997 [lnput L-Output Dose Estimation 3 Z TRNS CREA Input Parameters DIT No. 13720-10 0 [Input []Output 4 Z TRNS LOCA Dose Analysis Input Parameters DIT No. 13720-05 0 Zlnput --Output 5 Z TRNS Control Room Input Parameters DIT No. 13720-07 0 Zlnput [:]Output 6 0 TRNS Meteorological Input Parameters DIT No. 13720-03 0 ZInput r-]Output 7 Ej STD Accident Source Term 10 CFR 50.67 Zinput E--Output 8 Z CALC PI Control Room Atmospheric Dispersion Factors GEN-PI-049 Add 2 [lnput [-iOutput U1/U2 9 Z TS PINGP Units 1 & 2, Definition of Rated Thermal Power 1.1 Amendment Zlnput [:]Output.

158/149 _ --.-

U1/U2 10 Z TS PINGP Units 1 & 2, Definition of Dose Equivalent 1-131 1.1 Amendment Zlnput E-Output 158/149 U1/U2 11 Z TS PINGP Units 1 & 2, Definition of E-bar Average Disintegration Energy 1.1 Amendment 177/167 Zlnput []Output UI/U2

]TS PINGP Units 1 & 2 LCO for Shield Building Ventilation System 3Aenp 3.6.9 Amendment []input []output 12 ZTS(SBVS) 1 186/176 U1/U2 13 Z TS PINGP Units 1 & 2 LCO for RCS Specific Activity 3.4.17 Amendment Zlnput ElOutput 167/157 UI/U2 14 Z TS PINGP Units 1 & 2 LCO for RCS Operational Leakage 3.4.14 Amendment ZInput [-]Output 158/149

QF-0549 (FP-E-CAL-01), Rev. 3 Pacle 4 of 145

'. XceI Energy [ Calculation Signature Sheet U I/U2 3.7.10 Amendment Input r-output 15 [] TS PINGP Units 1 & 2 LCO for Control Room Special Ventilation System (CRSVS) 158/149 U1/U2 16 Z TS PINGP Units 1 & 2 LCO for Auxiliary Building Special Ventilation 3.7.12 Amendment [Input ElOutput System (ABSVS) 158/149 U1/U2 17 Z TS PINGP Units 1 & 2 LCO for Secondary Specific Activity 3.7.14 Amendment [Input r-lOutput 158/149 U1/U2 18 Z TS Specification for Containment Leak Rate Testing Program 5.5.14.c Amendment Zlnput [:]Output 174/164 U1/U2 -Output 5.5.9 Amendment [lnput 19 [] TS PINGP Units 1 & 2 Specification for Ventilation Filter Testing Program (VFTP)186/176 20 [] TS PINGP Units 1 & 2 LCO for Control Room Special Ventilation Amendment Input [-]Output System (CRSVS) Actuation Instrumentation 158/149 21 F] FGR Federal Guidance Report 11 EPA-520/1-88-020 Ninput []Output 22 [] FGR Federal Guidance Report 12 EPA-402-R-93-081 Ninput ElOutput Westinghouse Letter - Nuclear Management Company Prairie NSP-07-59 23 Z LTR Island Units 1 & 2, MUR Power Uprate Program, Core Activity LTR-PEP-07-26 11/02/2007 ZInput l]Output Inventory and Coolant Activity Concentrations 24 [:] STD Laboratory Testing of Nuclear-Grade Activated Charcoal GL 99-02 6/3/99 Zlnput [-]Output7ý 25 Z USAR Environmental Consequences of Loss-Of-Coolant-Accident 14.9 27 ZInput E-Output 26 [] USAR Steam Generator Design Data Table 4.1-5 27 MInput ElOutput 27 USAR Rupture of a Control Rod Drive Mechanism Housing (RCCA 14.5.6 29P [:]nput ZOutput Ejection) 28 El DOC ASME Steam Tables Sixth Edition NInput [:Output 29 El SRP Standard Review NUREG-0800, Analyses Plan, "Radiological 15.0.1 0 Zlnput EOutput 29__ [ SRP Consequence Using Alternative Source Terms" 15.01___]inpt ___utpu 30 Z CALC Post-LOCA EAB, LPZ, and CR Doses -AST GEN-PI-079 0 ZInput [lOutput 31 El STD Deletion of E Bar Definition and Revision to RCS Specific TSTF-490 0 Zinput [:output Activity Tech Spec 32 Z PROC Natural Circulation Cooldown With CRDM Fans 1ES-0.3A 14 ZInput ElOutput 33 Z PROC Natural Circulation Cooldown Without CRDM Fans 1ES-0.3B 11 [Input routput

QF-0549 (FP-E-CAL-0 , ev. Pacie 5 of 145 XceEnergy Calculation Signatu,.re Sheet LAR to Revise the Loss of Coolant Accident (LOCA) and Main 34 0 LAR Steam Line Break Accident (MSLB) Dose Consequences L-PI-08-052 06/26/2008 [Input [-]Output Analyses and Affected Technical Specifications (TS) 35 S USAR Steam Generators 4.3.2.1.1 28 EInput i]Output Beaver Valley Power Station, Unit Nos. 1 and 2, Issuance of License Amendments 257 and 139 Re: Selective 36 Z SER Implementation of Alternate Source Term and Control Room ML032530204 09/10/2003 ZInput -Output Habitability Technical Specification Changes, September 10, 2003 (ADAMS Accession Number ML032530204) 37 Z CALC Prairie Island Atmospheric Dispersion Factors (XIQs) -AST GEN-PI-080 0 ZInput EjOutput Additional Releases 38 Z DRAW Admin Bldg, Screen House, & Control RM Flow Diagram NF-39603-1 & T-Mod 76 Zlnput --Output

__________EC 14090 Design, Testing, and Maintenance Criteria for Postaccident 39 Engineered-Safety-Feature Atmosphere Cleanup System Air 1.52 2 ZInput []Output 39 RG Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants

• Controlled Doc checkmark means the reference can be entered on the C012 panel in black. Unchecked lines will be yellow. If checked, also list the Doc Type, e.g., CALC, DRAW, VTM, PROC, etc.)

• • Corresponds to these PassPort "Ref Type" codes: Inputs/Both = ICALC, Outputs = OCALC, Other/Unknown = blank)

QF-0549 (FP-E-CAL-01), ev. 3 Paqe 6 of 145 XcelEnergy Calculation Signature Sheet Other Pass Port Data Associated Systern (PassPort Col1, first three columns) OR Equipment References (PassPort C025, all five columns):

Facility Unit System Equipment Type Equipment Number PI 1 MS GEN 134-011 Pi 1 MS GEN 134-012 PI 1 MS GEN 234-011 PI 1 MS GEN 234-012 PI 1 MS CV CV-31084 PI 1 MS CV CV-31085 PI 1 MS CV CV-31086 PI 1 MS CV CV-31089 PI 1 MS CV CV-31090 Pi 1 MS CV CV-31091 PI 2 MS CV CV-31102 PI 2 MS CV CV-31103 PI 2 MS CV CV-31104 PI 2 MS CV CV-31107 PI 2 MS CV CV-31108 PI 2 MS CV CV-31109 PI 1 MS RFV RS-21-1 PI 1 MS RFV RS-21-2 P1 1 MS RFV RS-21-3 PI 1 MS RFV RS-21-4 P1 1 MS RFV RS-21-5 PI 1 MS RFV RS-21-6 PI 1 MS RFV RS-21-7 PI 1 MS RFV RS-21-8 P1 1 MS RFV RS-21-9 PI 1 MS RFV RS-21-10 PI 2 MS RFV RS-21-11 PI 2 MS RFV RS-21-12 PI 2 MS RFV RS-21-13 Pi 2 MS RFV RS-21-14 PI 2 MS RFV RS-21-15 PI 2 MS RFV RS-21-16 Pi 2 MS RFV RS-21-17 Pi 2 MS RFV RS-21-18

QF-0549 (FP-E-CAL-01), Rev. 3 Paae 7 of 145 XcelEnergy- Calculation Signature Sheet Facility Unit System Equipment Type Equipment Number PI 2 'MS RFV RS-21-19 PI 2 MS RFV RS-21-20 PI 0 ZN SYS SYSOZN PI 0 ZN FILTER 069-241 PI 0 ZN FILTER 069-242 PI 0 ZA FILTER 069-111 PI 0 ZA FILTER 069-112 PI 1 ZS FILTER 169-101 PI 1 ZS FILTER 169-102 PI 2 ZS FILTER 269-101 PI 2 ZS FILTER 269-102 PI 0 RD RM RM-23 PI 0 RD RM RM-24 Superseded Calculations (PassPort C019):

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Topic Notes Text

[-- Calc introduction Z* Copy directly from the calculation Intro Paragraph or 0-- See write-up below The purpose of this calculation is to determine the Exclusion Area Boundary (EAB), Low Population Zone (LPZ), and Control Room (CR) doses due to a Rod Ejection Accident (REA) using the Alternative Source Term (AST) methodology and total effective dose equivalent (TEDE) dose criteria, and the plant-specific bounding design information applicable to the PINGP Units 1 & 2 steam generators. The dose consequencesare representative of a REA occurring in either Unit 1 or Unit 2.

l(Specifý)

Xcel Energy- Revision No. 0 Page No. 8 of 145 II"o' nr lDesign Review Comment Form Calculation No. GEN-PI-082 Sheet of DOCUMENT NUMBER] TITLE: GEN-PI-082/ Rod Ejection Accident - AST REVISION: 0 DATE:

ITEM REVIEWER'S COMMENTS PREPARER'S REVIEWER'S

1. RESOLUTION DISPOSITION Editorial comments made in document text. Incorporated. Accepted 09/08/9 ,7 The acronym "PC" is used for "primary Incorporated. Accepted 09/08/0 containment," primary coolant," and

"'partition coefficient". There can only be one meaning for this acronym. Corrected in text.

3 Section 4.4.1 indicates that activity is not Incorporated. Reference is made to Accepted 09/08/09 released into the containment air space. This Section 2.4.4 of the AST LOCA is not correct since a REA is, in fact, a small- Calculation GEN-PI-079.

break LOCA. Therefore, activity IS released into the containment. The LOCA calc says that "The direct shine from the post-LOCA activity confined above the containment operating floor to the CR operator encounters a slant line-of-sight path through the 1.5" of the containment steel, 2.5' of the SB concrete wall, 3.0' of the CR ceiling & roof, and multiple other concrete roof and walls of the auxiliary building. The encountered concrete and steel barriers (at least 5.5' thick concrete, 1.5" steel, plus other AB concrete) provide ample shielding to completely shield the post-LOCA containment shine dose to the CR operator." Since this amounts to zero dose, the same thing should be true for the REA.

4 The licensed power level in Design Input Incorporated. Accepted 09/08/w 5.3.1 should mention the value of 1683 MWt as being 102% of the licensed power level.

5 Design Input 5.6.7A lists the CR DI 5.6.7A is the pre-isolation normal Accepted 09/0N(09 Recirculation flow at 10,000 cfm. However, operation CR recirculation flow rate of the LOCA calc uses 4,000 cfmn =/- 10% 10,000 cfm. The 4,000 cfm value is (3,600 cfm used in LOCA analysis). Why the the filtered recirculation flow rate difference? following CR isolation.

Design Input Section 5.7 (Site boundary The LPZ distance is listed because the Accepted 09/08 9 release parameters) lists the LPZ distance, but LPZ X/Q is based on a distance not the EAB distance. interpolation of data provided in the USAR.

XcefEnergy Calculation No. GEN-PI-082 Revision No. 0 Page No.9 of 145 l Xoo, no gyl Design Review Comment Form Sheet of DOCUMENT NUMBER/ TITLE: GEN-PI-082/ Rod Ejection Accident - AST REVISION: 0 DATE:

ITEM REVIEWER'S COMMENTS PREPARER'S REVIEWER'S

1. RESOLUTION DISPOSITION 7 Section 7.0 indicates that Table 8 is for Incorporated. The Table titles and Accepted 09/08/09 containment leakage and assumes 25% iodine headings are revised. Table 8 release from melted fuel. Table 9 is supposed addresses the activity present in the to be for the secondary coolant leakage and RCS that is available for instantaneous assumes 50%. However, Tables 8 & 9 are release into the containment air space.

titled the same, causing potential confusion. Table 9 addresses the activity present in the RCS that is available for primary-to-secondary leakage into the secondary coolant.

8 Design Input 5.6.7A (CR Recirculation Flow DI 5.6.7A is deleted. Accepted 09/0.8/09 Rate) is included, but is not used. Why is it listed?

END Reviewer: Thornm' Mscisz DZ - 09/07/2009 Preparer: . Date: 09/08/2009

XceIEnergy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 10 of 145 REVISION HISTORY Revision Description 0 Initial Issue

XceI Energy] Calculation No. GEN-PI-082 Revision No. 0 Page No.1 Iof 145 SHEET REVISION INDEX SHEET REV SHEET REV SHEET REV 1 0 26 0 51 0 2 0 27 0 52 0 3 0 28 0 53 0 4 0 29 0 54 0 5 0 30 0 55 0 6 0 31 0 56 0 7 0 32 0 Attachment 13.1 0 8 0 33 0 Attachment 13.2 0 9 0 34 0 Attachment 13.3 0 10 0 35 0 Attachment 13.4 0 11 0 36 0 12 0 37 0 13 0 38 0 14 0 39 0 15 0 40 0 16 0 41 0 17 0 42 0 18 0 43 0 19 0 44, 0 20 0 45 0 21 0 46 0 22 0 47 0 23 0 48 0 24 0 49 0 25 0 50 0

J Xce nergyl Calculation No. GEN-PI-082 Revision No. 0 Page No. 12 of 145 TABLE OF CONTENTS Section Sheet No.

Cover Sheet Revision History 10 Sheet Revision Index 11 Table of Contents 12 1.0 Purpose And Summary Report 13 2.0 Methodology 13 3.0 Acceptance Criteria 20 4.0 Assumptions 21 5.0 Design Inputs 28 6.0 Computer Codes & Compliance With Regulatory Requirements -36 7.0 Calculations 37 8.0 Results Summary And Conclusions 41 9.0 References 42 10.0 Tables 44 11.0 Figures 53 12.0 Affected Documents 56 13.0 Attachments 56 13.1 RADTRAD Output File PIREACL0O.oO 57 13.2 RADTRAD Output File PREAINIDOO.oO 85 13.3 RADTRAD Output File PREAING00.oO 107 13.4 RADTRAD Output File PREAINLQOO.oO 126

XceI Energy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 13 of 145 1.0 PURPOSE AND

SUMMARY

REPORT 1.1 Purpose The purpose of this calculation is to determine the Exclusion Area Boundary (EAB), Low Population Zone (LPZ), and Control Room (CR) doses due to a Rod Ejection Accident (REA) using the Alternative Source Term (AST) methodology and total effective dose equivalent (TEDE) dose criteria, and the plant-specific bounding design information applicable to the PINGP Units 1 & 2 steam generators. The dose consequences are representative of a REA occurring in either Unit 1 or Unit 2.

1.2 Summary Report The resulting post-REA doses are shown in Section 8.0. These doses comply with the applicable regulatory allowable dose limits.

2.0 METHODOLOGY The PINGP operating licenses are proposed to amend to implement the full scope AST methodology in lieu of the TID-14844 source term methodology. The TEDE offsite dose acceptance criteria specified in Table 6 of Regulatory Guide 1.183 (Ref. 9.1) are implemented in lieu of the whole body and thyroid dose guidelines provided in 10 CFR 100.11. In addition, the 5 rem TEDE control room dose acceptance criterion specified in 10 CFR 50.67 (Ref. 9.4) is implemented in lieu of the 5 rem whole body and equivalent organ dose guidelines provided in 10 CFR 50 Appendix A GDC 19.

The design basis rod ejection accident is analyzed usinga conservative set of assumptions and as-built design inputs. The numeric values of the critical design inputs are conservatively selected to assure an appropriate prudent safety margin against unpredicted events in the course of an accident and compensate for large uncertainties in facility parameters, accident progression, radioactive material transport, and atmospheric dispersion. The REA analysis is performed using the guidance in Regulatory Guide 1.183 and its Appendix H (Ref. 9.1).

This analysis uses Version 3.03 of the RADTRAD computer code (Ref. 9.2) to calculate the potential radiological consequences of the REA. The validation and verification (V&V) of the RADTRAD code is addressed in Section 6.

The REA dose consequences are determined by summing together the results from the containment leakage and the primary-to-secondary (P-T-S) leakage iodine and noble gas activity releases, and the secondary liquid iodine release.

Per RG 1.183, Appendix H, Section 3, the following two release cases are considered:

1. Containment Leakage Release: 100% of the activity released from the fuel is assumed to be released instantaneously and homogeneously throughout the containment atmosphere and available for release to the environment.

2. Secondary System Release: 100% of the activity released from the fuel is assumed to be completely dissolved in the primary coolant (i.e., Reactor Coolant System [RCS]) and available for release to the environment through the secondary system.

No additional release paths other than containment leakage and secondary side releases are required to be considered per RG 1.183, Appendix H.

Xce nergy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 14 of 145 2.1 Containment Leakage Release Per RG 1.183, Appendix H, Section 1, the following activity is assumed to be instantaneously and homogeneously distributed in the containment following a control rod ejection accident (Ref. 9.1):

10% of the core iodine and 10% of the core noble gases in the fuel gap of failed fuel 25% of the core iodine and 100% of the core noble gases in the melted fuel In addition, this analysis also releases 100% of the iodine and noble gases initially present (i.e., pre-REA) in the reactor coolant system (RCS).

The source term, containment activity transport, environmental release and post-REA CR response are discussed in the following sections:

2.1.1 Failed Fuel Gap Inventory Per RG 1.183, Appendix H, Section 1, for the rod ejection accident, the release from the breached fuel is based on the estimate of the number of fuel rods breached (i.e., in Departure from Nucleate Boiling

[DNB]) and the assumption that 10% of the core inventory of the noble gases and iodines is in the fuel gap. The expected number of fuel rods in DNB is 10% of the core (Ref. 9.3.1, Item # 3). Per RG 1.183, Appendix H, Section 1, for the rod ejection accident, the release attributed to fuel melting is based on the fraction of the fuel that reaches or exceeds the initiation temperature for fuel melting and the assumption that 100% of the noble gases and 25% of the iodine contained in that fraction are available for release from containment. The expected fuel melt is 0.25% of the core (Ref. 9.3.1, Item # 3).

The exclusion of iodine spiking is consistent with the guidance presented in RG 1.183 (Ref. 9.1, Appendix E, Footnote 2), which states that the activity assumed in the analysis should be based on the activity associated with the projected fuel damage or the maximum technical specification values, whichever maximizes the radiological consequences. Since the RCS activity associated with 10% failed fuel and fuel melt of 0.25% of the core is greater than that of an iodine spike, the iodine spike is not included with the failed fuel activity release.

The REA fuel gap isotopic activity release fractions specified in RG 1.183, Appendix H, release more iodine and noble gases than the generic non-LOCA event fuel gap isotopic activity release fractions

\ specified in RG 1.183, Table 3. In addition, the REA fuel gap isotopic activity release fractions specified in RG 1.183, Appendix H, do not require a release of alkali metals (i.e., Cs, Rb).

Since RG 1.183, Table 3, does not apply to the REA event, the Table 3 gap release fraction applicability limitations listed in RG 1.183 Note 11 do not apply.

Although RG 1.183, Appendix H, does not require consideration of a release of alkali metals for the REA event, it is noted that if a release of alkali metals was considered, the release of alkali metals would result in an insignificant dose contribution compared to the dose contribution from noble gases which are released directly to the environment without hold-up.

In an intact steam generator in which the tubes are covered by liquid for the event duration, the release of alkali metals is facilitated solely by steam generator moisture carryover of no more than 0.25%

(Ref. 9.20) (i.e., a factor of 400 less than the noble gas release rate). In addition, the alkali metals introduced into both intact SGs are diluted within the SG space of approximately 3400 cubic feet (per Section 7.1.2), and then gradually released as this SG liquid volume is steamed to the environment at a rate of no more than 40 cfm (per Section 7.2.2, without consideration of iodine partition coefficient of 100). This release rate of approximately 0.012 SG volumes per minute (= 40 cfm / 3400 cf) is 85 times lower than the noble gas release rate to the environment. Combining the moisture carryover and hold-up effect indicates that the alkali metal release rate is approximately 34,000 times (= 400 x 85) lower than

Xceffnergy] Calculation No. GEN-PL-082 Revision No. 0 Page No. 15 of 145 the noble gas release rate to the environment. This hold-up of the alkali metal within the intact SG significantly reduces the alkali metal activity released to the environment in comparison to the noble gas activity released to the environment.

In addition, the control room dose contribution from alkali metals is further minimized by their removal via the 99% efficient control room HEPA recirculation filter (Ref. 9.3.2, Item #14), which would reduce the alkali metal CR dose contribution by an additional factor of 100.

The activity released during the vent contributes to the external dose (whole body gamma - DDE) and internal dose (inhaled - CEDE). All alkali isotopes including the daughters are naturally beta emitters; therefore, they do not contribute to any external dose. The inhaled dose conversion factors for the rubidium and cesium isotopes are calculated in Table 14, which shows that the alkali isotopes are inherently low thyroid inhalation dose contributors. These dose characteristics combined with the extremely low fractional release of less than 1/34,000 will result in inconsequential CR and offsite doses, which will be eliminated as being less than the significant figure rounding error.

Westinghouse Letter NSP-07-59, LTR-PEP-07-26 (Ref. 9.9, Table 2-1) presents the PINGP Units I and 2 core inventory at a core thermal power level of 1683 MWt at reactor shutdown. This core inventory is bounding for the 422V+ (Heavy Bundle or HB) core and OFA core (Ref. 9.9, Section 2.0).

The core activity is based on a core thermal power of 1,683 MWt (= 1,650 MWt x 1.02) including the 2% power level measuring instrument uncertainty, fuel enrichment of 5.0%, and cycle burnup of 25,000 MWD/MTU (Ref. 9.9, Table 6-1). For conservatism and to bound possible core inventory increases associated with a 10% Power Uprate, the activity released to the containment is based on a core thermal power level of 1,852 MWt (= 1.10 x 1,683 MWt). Based on the amount of fuel failed and fuel melted, the iodine and noble gas activity released to the containment is calculated in Table 8 with appropriate release fractions (Ref. 9.1, Appendix H, Section 1), and the RADTRAD NIF "PIREACNT def.txt" is developed using the total activity released to the containment.

2.1.2 Activity Transport in Containment The radioactivity released from the core is assumed to mix instantaneously and homogeneously throughout the free air volume of the primary containment. The design inputs for the transport in the primary containment are shown in Reference 9.13, Section 5.3.2 and the post-LOCA radiological response of the containment is described in Reference 9.13, Section 2.1.2.

During the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> the containment is assumed to leak at its maximum technical specification leak rate of 0.15 volume percent per day and at 50% of this leak rate (i.e., 0.075 volume percent per day) for the remaining duration of the accident (Ref. 9.1, Appendix H, Section 6.2, and Ref. 9.13, Section 2.1.2).

Although allowed by Regulatory Guide 1.183 (Ref. 9.1, Appendix H, Section 6.1), no credit is taken for a reduction in the amount of radioactive material available for leakage from the containment due to natural deposition, containment spray, and elemental iodine removal by surface deposition.

The post-REA radiological response of containment is similar to that for a LOCA. Therefore, the REA analysis modifies the LOCA containment activity transport design inputs and RADTRAD plant scenario file (psf) "PI250CLOO.psf' as obtained from Reference 9.13. The REA modifications include using the REA specific source term and eliminating certain dose mitigation credits, such as not taking credit for a reduction in the amount of radioactive material available for leakage from the containment due to natural deposition, containment spray, and elemental iodine removal by surface deposition. The post-REA containment leakage transport and CR response models are shown in Figures 1 & 3. The corresponding new RADTRAD plant scenario file for the post-REA containment leakage is "PIREACLOO.psf".

Xcel Ene]e Calculation No. GEN-PI-082 Revision No. 0 Page No. 16 of 145 The resulting post-REA doses from the containment leakage release path are combined with the dose contributions from secondary system release path in Section 8.1. Per Reference 9.19, Section 3.6, the actual doses from a REA would be a composite of the two pathways.

2.2 Secondary System Release To maximize the secondary system release doses, it is assumed that offsite power is lost so that the main steam condensers are not available (Ref. 9.3.1, Item # 2). Due to the REA, the reactor is shutdown and the plant is being cooled down by discharging secondary coolant via the two intact steam generators (SGs). The post-REA iodine and noble gas activities released from the 10% failed fuel and 0.25%

melted fuel, which are completely dissolved in the RCS and available for release to the SGs, are calculated in Table 9 with appropriate release fractions (Ref. 9.1, Appendix H, Section 1), and the RADTRAD NIF "PIREARCSdef.txt" is developed using the total activity released to the RCS. The post-REA secondary system release activity transport and CR response models are shown in Figures 2 &

3.

The resulting post-REA doses from the secondary system release path are combined with the dose contributions from containment leakage release path in Section 8. 1. Per Reference 9.19, Section 3.6, the actual doses from a REA would be a composite of the two pathways.

2.2.1 RCS Iodine Inventory Westinghouse Letter NSP-07-59, LTR-PEP-07-26 (Ref. 9.9, Table 2-2, HB x 1.04 scenario) provides the PINGP Units I and 2 RCS iodine activity concentrations based on a 1% fuel defect level. Technical Specification 1.1 (Ref. 9.6.2) defines Dose Equivalent 1-131 as that concentration of 1-131 that alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134 and 1-135 actually present. Technical Specification 1.1 defines Dose Equivalent 1-131 (DE 1-131) in terms of the thyroid dose conversion factors listed in Table III of TID-14844. In this calculation, consistent with RG 1.183 methodology (Ref. 9.1, Section 4.1.2), DE 1-131 is defined in terms of the committed effective dose equivalent (CEDE) iodine inhalation dose conversion factors of FGR-1 1 (Ref.

9.7). The use of FGR dose conversion factors in the Technical Specification 1.1 definition for DE 1-131 will be included in the AST license amendment request. The iodine inhalation dose conversion factors are calculated in Table I and used in Table 2 to establish a scaling factor based on 0.50 ýtCi/gram DE 1-1%31 to calculate Tech Spec iodine concentration in Table 3. The total isotopic iodine activities are conservatively calculated using the I % failed fuel iodine concentration instead of 0.50 pCi/gram DE 1-131 concentration and RCS mass (per Section 7.1.1) in Table 4.

2.3 Noble Gas Inventory Per Technical Specification LCO 3.4.17 (Ref. 9.6.6), the maximum permitted equilibrium RCS non-iodine concentration is 100/E-BAR. The parameter E-BAR is defined in Technical Specification Section 1.1 (Ref. 9.6.3) as the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes, other than iodines, with half lives greater than 15 minutes, making up at least 95% of the total non-iodine activity in the coolant.

A PINGP license amendment request (Ref. 9.17) proposes the deletion of the E-BAR definition and revision of the RCS Specific Activity Tech Specification to utilize a new indicator, Dose Equivalent Xenon-133, instead of the current indicator known as E-BAR. The current limits on primary coolant gross specific activity will be replaced with limits on primary coolant noble gas activity. The noble gas activity would be based on DOSE EQUIVALENT XE-133 and would take into account only the noble

e aEnergyCcultonNo.ENPI082 Revision No. 0 Page No. 17 of 145 gas activity in the primary coolant. The determination of Dose Equivalent Xe-133 will be performed in a similar manner to that currently used in determining DE 1-131, except that the calculation of Dose Equivalent Xe- 133 is based on the acute dose to the whole body and considers the noble gases which are significant in terms of contribution to whole body dose. Some noble gas isotopes are not included due to low concentration, short half-life, or small dose conversion factor.

Per TSTF-490 traveler (Ref. 9.15), the DOSE EQUIVALENT XE-133 shall be that concentration of Xe-133 (pCi/gm) that alone would produce the same acute dose to the whole body as the combined activities of noble gas nuclides [Kr-85m, Kr-85, Kr-87, Kr-88, Xe-131m, Xe-133m. Xe-133, Xe-135m, Xe-135, and Xe-138] actually present. The determination of DOSE EQUIVALENT XE-133 shall be performed using effective dose conversion factors for air submersion listed in Table 111. 1 of EPA Federal Guidance Report No. 12, 1993, "External Exposure to Radionuclides in Air, Water, and Soil" or the average gamma disintegration energies as provided in ICRP Publication 38, "Radionuclide Transformations" or similar source.

The XE-133 Dose Equivalent concentration is established in Table 5 as defined in the TSTF-490 design specification using effective dose conversion factors for air submersion listed in Table 111.1 of EPA Federal Guidance Report No. 12 (Ref. 9.8) and 1% failed fuel noble gas isotopic concentrations in Reference 9.9, Table 2-2 for HB x 1.04. The proposed XE-I133 Dose Equivalent concentration limit for noble gas activity is calculated to be 580 piCi/gm XE-133 DE (Table 5), and is used in this analysis with the noble gas isotopic concentrations in Table 6.

2.4 Secondary Coolant Liquid Iodine Inventory Per Technical Specification LCO 3.7.14(Ref. 9.6.9) the secondary coolant iodine concentration is limited to 0.1 ptCi/gram DE 1-131. This is one-fifth of the proposed Specification LCO 3.4.17 RCS iodine concentration limit of 0.50 ptCi/gram DE 1-131. In Table 7, the RCS iodine concentration profile at the 0.50 pCi/gm DE 1-131 is multiplied by the secondary to primary limits (0.1/0.5) to determine the secondary coolant iodine concentration profile. Table 7 scales this secondary coolant iodine activity concentration profile by the coolant mass in both intact steam generators (per Section 7.1.2) to calculate the total secondary coolant iodine inventory. This secondary coolant iodine activity inventory is input into RADTRAD Nuclide Inventory File "PIREAliq_def.txt".

2.5 Post-REA Releases 2.5.1 Primary to Secondary (P-T-S) Leakage Rate This analysis models the RCS operational leakage limit of 150 gallons/day of primary to secondary (P-T-S) leakage through each steam generator (SG) at 70°F (i.e., 300 gpd through both SGs) as specified in Technical Specification LCO 3.4.14 (Ref. 9.6.5).

Consistent with RG 1.183 (Ref. 9.1, Appendix H, Section 7.1) the primary-to-secondary leakage is assumed to continue until shutdown cooling is in operation and the releases from the steam generators have been terminated. In this analysis the RCS is assumed to leak into the SGs for 45.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> at which time the Residual Heat Removal (RHR) system is initialized (Ref. 9.3.1, Item # 24).

2.5.2 RCS Iodine Release Through P-T-S Leakage The SG tubes are expected to be submerged in the intact SGs secondary coolant during the REA event (Ref. 9.3.1, Item # 21). The iodine activity in the P-T-S leakage is assumed to mix with SG coolant

Xce nergy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 18 of 145 without flashing during period of submergence (Ref. 9.1, Appendix H, Section 7.4 and Appendix E, Section 5.5.1) and iodine partition coefficient of 100 is assumed (Ref. 9.1, Appendix H, Section 7.4 and Appendix E, Section 5.5.1 andRef. 9.3.1, Item # 22). The RCS iodine release continues until the RHR system is initialized at 45.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> (Ref. 9.3.1, Item # 24).

The doses from the REA RCS iodine release are summarized in Section 8.1.

2.5.3 RCS Noble Gas Release Through P-T-S Leakage Noble gases present in the P-T-S leakage are released directly to the environment without dilution or retention in the intact SGs (Ref. 9.1, Appendix H, Section 7.3). The RCS noble gas release continues until the RHR system is initialized at 45.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> (Ref. 9.3.1, Item # 24).

The doses from the REA RCS noble gas release are summarized in Section 8.1.

2.5.4 Secondary Liquid Iodine Release to the Environment Although Regulatory Guide 1.183 (Ref. 9.1, Appendix H) does not include a requirement to consider the release of pre-accident activity present in the steam generators, this analysis conservatively considers the release of the pre-accident secondary liquid iodine. The iodine activity in the bulk water in the SG is assumed to become vapor and is*directly released to the environment in proportion to the steam release rate, with credit taken for iodine partitioning in the SG liquid. For the secondary liquid iodine release from the SGs, an iodine partition coefficient of 100 is assumed as recommended in Regulatory Guide 1.183 (Ref. 9.1, Appendix H, Section 7.4 and Appendix E, Section 5.5.4).

The secondary coolant iodine release continues until the RHR system is initialized at 45.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> (Ref. 9.3.1, Item # 24).

The doses from the REA secondary liquid iodine release are summarized in Section 8.1.

2.6 Steam Release Atmospheric Dispersion to the Control Room The activity during the REA releases to the atmosphere via following two distinct plant-specific release paths:

1. Intact SG Steaming Via Safety & Power Operated Relief Valve (PORV) Group I and Group 2 Release

2. Intact SG Steaming via Turbine Driven Auxiliary Feed Water (TDAFW) Pump Exhaust Steam Release 2.6.1 Intact SG Via Safety & Power Operated Relief Valve (PORV) Group I and Group 2 Release Following the event the intact SGs are used to cooldown the RCS. The mass of the steam released and the release location during the cooldown are important considerations due to the total 300 gpd P-T-S leakage assumed for the intact SG (maximum allowed by Technical Specification 3.4.14) (Ref. 9.6.5).

Assuming a loss of off-site power the unit would be cooled down using procedure ES-0.3A or ES-0.3B (Ref. 9.16) for cooling down using natural circulation. Per either procedure, the preferred means to release steam for the cooldown is by dumping steam to the condenser. If this path is not available, then the SG PORV is used (Refs. 9.16.1, Step 8 and 9.16.2, Step 7). The time dependent steaming rates

XcelfnergytCalculation No. GEN-PI-082 Revision No. 0 Page No. 19 of 145 through the intact SGs are shown in Table 10. The apportioned P-T-S leakage rates used in this analysis are based on the steam mass flow rate distribution through the intact SGS as shown Table 11.

2.6.2 Turbine Driven Auxiliary Feedwater (TDAFW) Pump Exhaust Steam Release An additional steam release path from the intact SGs is through the Turbine Driven Auxiliary Feedwater (TDAFW) Pump steam exhaust. Assuming a single failure of the motor driven AFW Pump, the TDAFW Pump would be used for the cooldown. Steam mass flow rates to drive the TDAFW Pump for given time periods are shown in Table 10.

The intact steam generator releases steam to the environment through three potential release paths, namely via the TDAFW pump exhaust, Group I PORV and Group 2 PORV. To eliminate a large number of RADTRAD computer runs, an average set of atmospheric dispersion factors (X/Qs) are conservatively established by picking the limiting sets of X/Qs from Unit I or Unit 2, instead of mixing and matching X/Qs from the two units, which is both unrealistic and not credible. The sets of /Qs for the three potential release paths Unit I and from Unit 2 are compared to pick the most limiting sets of X/Qs from which will be determined the average set of 7/Qs for the post-REA intact SG steam mass releases. Tables 12 and 13 calculate the average set of T/Qs for Units I and 2, respectively. The calculation begins by calculating an average set of XIQs for the intact SG PORV release, represented by 60% and 40% releases through the Group I PORV and Group 2 PORV sets, respectively. The calculation finishes by calculating the average set of T/Qs by applying the Table 10 fractional steam mass releases to the TDAFW and PORV X/Qs. The review of Tables 12 and 13 indicates that the Unit 2 steam release paths provide the higher sets of x/Qs in comparison to the Unit I steam release paths for the 0 to 45.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> release duration. The average Unit 2 x/Qs from Table 13 are used in the analysis with the iodine, noble gas, and SG liquid iodine release rates shown in Table 11.

The post-REA secondary system activity transport and CR response models are shown in Figures 2 and 3, which are used to determine the post-REA radiological consequences using the plant-specific as-built design inputs and assumptions listed in Sections 4 & 5.

2.7 CR Air Intake Radiation Monitor Response Post-accident Xe-133 activity in the CR @0.0833 hr (5 minutes) 0.72185 Ci (RADTRAD Run PREAINGOO.oO)

Control room volume 61,315 ft3 (Section 5.6.1) = 61,315 ft3 / (3.28 ft/m)3 = 1,737.58 m3 Xe-133 activity concentration in the CR @ 0.0036 hr (0.22 minute)

= 0.72185 Ci / 1,737.58 m3 = 4.154E-04 Ci/m 3 = 4.154E-04 pCi/cc, which exceeds CR monitor setpoint of IE-05 pCi/cc for Xe-133 (Section 5.6.20). The calculated setpoint value conservatively does not includes activity from the containment leakage and iodine activity from the intact SG release.

Since the Xe-133 activity in the CR is circulated by the CR recirculation flow through the CR air supply duct (Ref. 9.22), the monitor setpoint is instantly exceeded. Therefore, the CR actuation delay of 5 minutes following a heavy load drop is considered conservative, and does not require any further justification.

4* XcI Eergyl Calculation No. GEN-PI-082 Revision No. 0 Page No. 20 of 145 3.0 ACCEPTANCE CRITERIA:

The following NRC regulatory requirement and guidance documents are applicable to this PINGP Alternative Source Term REA Calculation:

Regulatory Guide 1.183 (Ref. 9.1) 10 CFR 50.67 (Ref. 9.4)

• Standard Review Plan section 15.0.1 (Ref. 9.12)

Dose Acceptance Criteria are:

Regulatory Dose Limits Dose Type Control Room (rem) EAB and LPZ (rem)

TEDE Dose 5 6.3

lce ergy]Calculation No. GEN-PI-082 Revision No. 0 Page No.21 of 145

4.0 ASSUMPTIONS

Regulatory Guide 1.183 (Ref. 9.1) provides guidance on modeling assumptions that are acceptable to the NRC staff for the evaluation of the radiological consequences of a PWR rod ejection accident. The following sections address the applicability of these modeling assumptions to the PINGP Units I and 2 REA analysis.

These assumptions are incorporated as design inputs in Sections 5.3 through 5.7. There are no unvalidated assumptions used in this calculation.

The radioactivity material releases and radiation levels used in the control room dose analysis are determined using the same source term, transport, and release assumptions used for determining the exclusion area boundary (EAB) and the low population zone (LPZ) TEDE values (Ref 9.1, Section 4.2.2).

4.1 Source Term 4.1.1 Fuel Damage Source Term It is assumed that ten percent (10%) of the core is assumed to experience clad damage and one-fourth of one percent (0.25%) of the core is assumed to experience fuel melt as a result of the REA (Ref. 9.3.1, Item # 3).

It is assumed consistent with RG 1.183 (Ref. 9.1, Appendix H, Section 1), that the release from the breached fuel to the containment and available for containment release, or to the primary coolant and available for release to the secondary system, is based on the estimate of the number of fuel rods breached (i.e., 10%) and the assumption that 10% of the core inventory of the noble gases and iodines is in the fuel gap.

It is assumed consistent with RG 1.183 (Ref. 9.1, Appendix H, Section 1), that the release attributed to fuel melting is based on the fraction of the fuel (i.e., 0.25%) that reaches or exceed the initiation temperature for fuel melting and the assumption that 100% of the noble gases and 25% of the iodines contained in that fraction are available for release from containment.

It is assumed consistent with RG 1.183 (Ref. 9. 1, Appendix H, Section 1), for the secondary system release pathway, 100% of the noble gases and 50% of the iodines in the fraction of the fuel (i.e., 0.25%) that reaches or exceed the initiation temperature for fuel melting are released to the reactor coolant.

The above source term requirements are incorporated in the Design Input 5.3.

4.1.2 No Fuel Damage Source Term Fuel damage is assumed for the REA. Therefore, consistent with RG 1.183 (Ref. 9.1, Appendix H, Section 2), a radiological analysis for the REA is required.

4.1.3 Release Cases to be Considered It is assumed consistent with RG 1.183 (Ref. 9.1, Appendix H, Section 3), that two release cases are considered in this REA analysis. In the first, 100% of the activity released from the fuel is assumed to be released instantaneously and homogeneously through the containment atmosphere. In the second, 100% of the activity released from the fuel is assumed to be completely dissolved in the primary coolant and available for release to the secondary system (see Figures 1 & 2).

XceI Energ Calculation No. GEN-PI-082 Revision No. 0 Page No. 22 of 145 4.1.4 Containment Airborne Iodine Form It is assumed consistent with RG 1.183 (Ref. 9.1, Appendix H, Section 4), that the chemical form of radioiodine released to the containment atmosphere is assumed to be 95% cesium iodide (CsI) (i.e., particulate), 4.85%

elemental iodine, and 0.15% organic iodide.

4.1.5 Steam. Generator Release Iodine Form It is assumed consistent with RG 1. 183 (Ref. 9.1, Appendix H, Section 5), that the iodine releases from the steam generators to the environment are assumed to be 97% elemental and 3% organic.

4.2 Transport 4.2.1 Transport From Containment 4.2.1.1 Reduction in Radioactive Material RG 1.183 (Ref. 9.1, Appendix H, Section 6.1) allows for a reduction in the amount of radioactive material available for leakage from the containment that is due to natural deposition, containment sprays, recirculating filter systems, dual containments, or other engineered safety features to be taken into account. Conservatively, this analysis assumes no reduction in the post-REA airborne activity by any mechanism other than decay or leakage.

4.2.1.2 Containment Leakage It is assumed that the primary containment leaks at a proposed new Technical Specification peak pressure leak rate of 0.15% by weight for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Ref. 9.1, Appendix H, Section 6.2). This leak rate is less than the leak rate currently allowed by Technical Specification 5.5.14.c (Ref. 9.6.10). This leak rate is reduced to 0.075% by weight after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Ref. 9.1 Appendix H, Section 6.2).

4.2.2 Transport From Secondary System 4.2.2.1 Primary-to-Secondary Leak Rates It is assumed consistent with RG 1.183 (Ref. 9.1, Appendix H, Section 7.1), that the primary-to-secondary (P-T-S) leakage is at the RCS operational leakage limit of 150 gallons/day through any one SG (i.e., 300 gpd through both SGs) as specified in Technical Specification LCO 3.4.14 (Ref. 9.6.5).

It is assumed consistent with RG 1.183 (Ref. 9.1, Appendix H, Section 7.1), that the P-T-S leak exists until shutdown cooling is in operation (i.e., RHR is initiated) and releases from the steam generators have been terminated at 45.5 hrs (Ref. 9.3.1, Item # 26).

4.2.2.2 Primary-to-Secondary Leak Primary Coolant Density It is assumed consistent with RG 1.183 (Ref. 9.1, Appendix H, Section 7.2), that the primary coolant (i.e., RCS) density used in converting the volumetric primary-to-secondary leak rates (e.g., gpm) to mass leak rates (e.g.,

Ibm/hr) is 1.0 gm/cc (62.4 lbm/ft3 ).

XceiEnergy] Calculation No. GEN-PI-082 Revi sion No. 0 Page No. 23, of 145 4.2.2.3 Noble Gas Transport Model (Releases to the Environment)

It is assumed consistent with RG 1.183 (Ref. 9.1, Appendix H, Section 7.3), that all noble gas radionuclides released from the primary system (via the primary-to-secondary leaks) are released to the environment without reduction or mitigation.

4.2.2.4 Iodine and Particulate Transport Model (Releases to the Environment)

RG 1.183 (Ref. 9.1, Appendix H, Section 5.6) states that the main steam line break (MSLB) accident transport model of RG 1.183, Appendix E, Sections 5.5 and 5.6 should be utilized for iodine and particulates. RG 1.183 Appendix E Sections 5.5 and 5.6 present the following transport model for use in evaluating releases from steam generators:

STEAM GENERATOR TRANSPORT MODEL Steam Space Release Primary Partit oning>

Leakage Bulk Water In this analysis, no credit is taken for iodine scrubbing, only for iodine partitioning. It is assumed consistent with RG 1.183 (Appendix E, Section 5.5.4), that the iodine activity in the bulk water of the two intact steam generators (consisting of the initial secondary coolant iodine activity and the iodine activity introduced via primary-to-secondary leakage) becomes vapor at a rate that is a function of the steaming rate and assumed iodine partition coefficient of 100.

For the primary-to-secondary leakage iodine release from the SGs, the SG tubes are expected to be submerged in the SGs liquid during the event, and consequently iodine introduced into the two intact SGs via the P-T-S leakage is assumed to be released to the environment with an iodine partitioning coefficient of 100 as recommended in RG 1.183 (Ref. 9.1, Appendix H, Section 7.4 and Appendix E, Section 5.5.4 and Ref. 9.3.1, Item # 21).

For the secondary liquid iodine release from the SGs, an iodine partition coefficient of 100 is assumed (Ref. 9.3.1, Item # 21), consistent with the value of 100 recommended in Regulatory Guide 1.183 (Ref. 9.1, Appendix H, Section 7.4 and Appendix E, Section 5.5.4).

4.3 Offsite Dose Consequences Regulatory Guide 1.183 (Ref. 9.1, Section 4.1) provides guidance to be used in determining the total effective dose equivalent (TEDE) for persons located at the exclusion area boundary (EAB) and at the outer boundary of the low population zone (LPZ). The following sections address the applicability of thisguidance to the PINGP Units I and 2 REA analyses. These assumptions are incorporated as design inputs in Section 5.7.

S Xce Energy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 24 of 145 4.3.1 Modeling of Parent and Daughter Isotopes It is assumed consistent with RG 1.183 (Ref. 9.1, Section 4.1.1), that the dose calculation determines the TEDE, which is the sum of the committed effective dose equivalent (CEDE) from inhalation and the deep dose equivalent (DDE) from external exposure. It is assumed that the .CEDE and DDE components of the TEDE consider all radionuclides, including progeny from the decay of parent radionuclides that are significant with regard to dose consequences and the released radioactivity. These isotopes are listed in Section 5.3.

4.3.2 CEDE (Inhalation) Dose Conversion Factors It is assumed consistent with RG 1.183 (Ref. 9. 1, Section 4.1.2), that the exposure-to-CEDE factors for inhalation of radioactive material are derived from the data provided in ICRP Publication 30, "Limits for Intakes of Radionuclides by Workers". This calculation models the CEDE dose conversion factors (DCFs) in the column headed "effective" yield doses in Table 2.1 of Federal Guidance Report 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion" (Ref. 9.7).

4.3.3 Offsite Breathing Rates It is assumed consistent with RG 1.183 (Ref. 9. 1, Section 4.1.3), that for the first 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, the breathing rate of persons offsite is assumed to be 3.5x 10-4 cubic meters per second. From 8 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following the accident, the breathing rate is assumed to be 1.8x 10-4 cubic meters per second. After that and until the end of the accident, the rate is assumed to be 2.3 x 104 cubic meters per second. These offsite breathing rates are listed in Section 5.7.

4.3.4 DDE (Immersion) Dose Conversion Factors It is assumed consistent with RG 1.183 (Ref. 9.1, Section 4.1.4), that the deep dose equivalent (DDE) is calculated assuming submergence in semi-infinite cloud assumptions with appropriate credit for attenuation by body tissue. The DDE is nominally equivalent to the effective dose equivalent (EDE) from external exposure if the whole body is irradiated uniformly. Since this is a reasonable assumption for submergence exposure situations, EDE is used in lieu of DDE in determining the contribution of external dose to the TEDE. This calculation models the EDE dose conversion factors in the column headed "effective" in Table 111.1 of Federal Guidance Report 12, "External Exposure to Radionuclides in Air, Water, and Soil" (Ref. 9.8).

4.3.5 Exclusion Area Boundary Dose Acceptance Criteria It is assumed for the REA that the postulated EAB dose should not exceed 6.3 Rem TEDE (per Section 3.2).

Per RG 1.183 Table 6, the REA event release duration is until cold shutdown is established. In this analysis, the REA event ends when shutdown cooling is placed into operation at 45.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> (Ref. 9.3.1, Item # 24).

The RADTRAD Code (Ref. 9.2) used in this analysis determines the maximum two-hour TEDE by calculating the postulated dose for a series of small time increments and performing a "sliding" sum over the increments for successive two-hour periods. The time increments appropriately reflect the progression of the accident to capture the peak dose interval between the start of the event and the end of radioactivity release.

Xce Energy]Calculation No. GEN-PI-082 Revision No. 0 Page No. 25 of 145 4.3.6 Low Population Zone Outer Boundary Dose Acceptance Criteria It is assumed for the REA that the postulated LPZ dose should not exceed 6.3 Rem TEDE (per Section 3.3). Per RG 1.183 Table 6, the REA event release duration is until cold shutdown is established. In this analysis, the REA event ends when shutdown cooling is placed into operation at 45.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> (Ref. 9.3.1, Item # 24).

4.3.7 Effluent Plume Depletion It is assumed consistent with RG 1.183 (Ref. 9.1, Section 4.1.7), that no correction is made for depletion of the effluent plume by deposition on the ground.

4.4 Control Room Offsite Dose Consequences Regulatory Guide 1.183 (Ref. 9.1, Section 4.2) provides guidance to be used in determining the total effective dose equivalent (TEDE) for persons located in the control room (CR). The following sections address the applicability of this guidance to the PINGP Units I and 2 REA analyses. These assumptions are incorporated as design inputs in Section 5.6.

4.4.1 Control Room Operator Dose Contributors It is assumed consistent with RG 1.183 (Ref. 9.1, Section 4.2.1), the CR TEDE analysis considers the following sources of radiation that will cause exposure to control room personnel:

" Contamination of the control room atmosphere by the filtered CR ventilation inflow through the CR air intake and by unfiltered inleakage of the radioactive material contained in the post-accident radioactive plume released from the facility,

• Contamination of the control room atmosphere by filtered CR ventilation inflow via the CR air intake and by unfiltered inleakage of airborne radioactive material from areas and structures adjacent to the control room envelope,

• Radiation shine from the external radioactive plume released from the facility (i.e., external airborne cloud shine dose),

Radiation shine from radioactive material in the reactor containment (i.e., containment shine dose). This form of radiation shine is not applicable to a REA since the direct shine from the post-LOCA activity confined above the containment operating floor to the CR operator encounters a slant line-of-sight path through the 1.5" of the containment steel, 2.5' of the SB concrete wall, 3.0' of the CR ceiling & roof, and multiple other concrete roof and walls of the auxiliary building. The encountered concrete and steel barriers (at least 5.5' thick concrete, 1.5" steel, plus other AB concrete) provide ample shielding to completely shield the post-LOCA containment shine dose to the CR operator (Ref 9.13, Section 2.4.4).

• Radiation shine from radioactive material in systems and components inside or external to the control room envelope (e.g., radioactive material buildup in CR intake and recirculation filters [i.e., CR filter shine dose]).

• Note: The external airborne cloud shine dose and the CR filter shine dose due to a REA are expected to be less than those due to a LOCA as a result of source term differences (i.e., the LOCA releases significantly more activity from failed fuel than does the REA event per RG 1.183 [Ref. 9.1, Table 2 for LOCA compared to Appendix H, Section 1 for REA]). Therefore, the post-LOCA external airborne cloud and CR filter shine doses are conservatively applied to the REA in Section 8.1.

'I X e ne Calculation No. GEN-PI-082 Revision No. 0 Page No. 26 of 145 4.4.2 Control Room Source Term It is assumed consistent with RG 1.183 (Ref. 9.1, Section 4.2.2), that the radioactive material releases and radiation levels used in the control room dose analysis are determined using the same source term, transport, and release assumptions used for determining the EAB and the LPZ TEDE values. The parameters assumed for determining the EAB and LPZ TEDE valuesalso result in conservative dose projections to the control room personnel.

4.4.3 Control Room Transport It is assumed consistent with RG 1.183 (Ref. 9. 1, Section 4.2.3), that the models used to transport radioactive material into and through the control room, and the shielding models used to determine radiation dose rates from external sources, are structured to provide suitably conservative estimates of the exposure to control room personnel. These conservative assumptions include conservative values for unfiltered inleakage, minimum clean-up air flow rates, and minimum filter efficiencies. The shielding models are not developed to determine radiation dose rates from external sources because their dose contributions are insignificant compared to those from a LOCA (Section 4.4.1).

4.4.4 Control Room Response It is assumed consistent with RG 1.183 (Ref. 9.1, Section 4.2.4), that engineered safety features (ESF) that mitigate airborne radioactive material within the control room are credited. Such features include control room recirculation filtration. CR isolation is. actuated by radiation monitors (RMs). The Xe-133 concentration at the CR air intake instantaneously exceeds the CR radiation monitor setpoint of 1.OE-05 ýtCi/ml following a REA (see Section 2.7). Therefore, a delay of 5 minutes for the CR isolation to be fully operational is considered to be conservative and no further sensitivity of delay time is required.

4.4.5 Control Room Operator Use of Dose Mitigating Devices It is assumed consistent with RG 1.183 (Ref. 9.1, Section 4.2.5), that credit is not taken for the use of personal protective equipment (e.g., protective beta radiation resistant clothing, eye protection, or self-contained breathing apparatus) or prophylactic drugs (i.e., potassium iodide [KI] pills).

4.4.6 Control Room Occupancy Factors and Breathing Rates It is assumed consistent with RG 1. 183 (Ref. 9.1, Section 4.2.6), that the CR dose receptor for these analyses is the hypothetical maximum exposed individual who is present in the control room for 100% of the time during the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the event, 60% of the time between I and 4 days, and 40% of the time from 4 days to 30 days. For the duration of the event, the breathing rate .ofthis individual should be assumed to be 3.5xx 10-4 cubic meters per second. These assumptions are incorporated as design inputs in Section 5.6.

4.4.7 Control Room Dose Conversion Factors It is assumed consistent with RG 1.183 (Ref. 9.1, Section 4.2.7), that the control room doses are calculated using the offsite dose analysis dose conversion factors identified in RG 1.183 Regulatory Position 4.1 (see preceding Sections 4.3.2 & 4.3.4). The deep dose equivalent (DDE) from photons is corrected for the difference between finite cloud geometry in the control room and the semi-infinite cloud assumption used in calculating the dose conversion factors. The RADTRAD Code (Ref. 9.2) used in this analysis uses the

X eI Energy]Calculation No. GEN-PI-082 Revision No. 0 Page No. 27 of 145 following expression to correct the semi-infinite cloud dose, DDEX, to a finite cloud dose, DDEfinite, where the control room is modeled as a hemisphere that has a volume, V, in cubic feet, equivalent to that of the control room:

DDEfinite (DDE.0 x V° 338) / 1173 4.4.8 Control Room Operator Dose Acceptance Criteria It is assumed that for the REA the postulated CR dose should not exceed 5 Rem TEDE (Ref. 9.4).

XceI Energ] Calculation No. GEN-PI-082 Revision No. 0 Page No.28 of 145 5.0 DESIGN INPUTS:

5.1 General Considerations 5.1.1 Applicability of Prior Licensing Basis As discussed in RG 1.183 (Ref. 9.1, Section 5.1.4), the implementation of an AST is a significant change to the design basis of the facility and assumptions and design inputs used in the analyses. The characteristics of the AST and the revised TEDE dose calculation methodology may be incompatible with many of the analysis assumptions and methods currently used in the facility's design basis analyses. The PINGP specific design inputs and assumptions used in the TID-14844 analyses were assessed for their validity to represent the as-built condition of the plant and evaluated for their compatibility to meet the AST characteristics. and TEDE methodology. The analysis in this calculation ensures that analysis assumptions, design inputs, and methods are compatible with the requirements of the AST and the TEDE criteria.

5.1.2 Credit for Engineered Safety Features Credit is taken only for those accident mitigation features that are classified as safety-related, are required to be operable by technical specifications, are powered by emergency power sources, and are either automatically actuated or, in limited cases, have actuation requirements explicitly addressed in emergency operating procedures. The dose mitigation features of the Shield Building Ventilation System (SBVS) (Ref. 9.6.4),

Auxiliary Building Special Ventilation System (ABSVS) (Ref. 9.6.8), and Control Room Special Ventilation System (CRSVS) (Ref. 9.6.7) are credited in the analysis. These systems are safety related and operable by Technical Specification applicable LCOs. The SBVS, ABSVS, and CRSVS HEPA particulate removal filtration efficiency and charcoal iodine removal filtration efficiencies used in the analysis are verified by the Ventilation Filter Testing Program in Technical Specification 5.5.9 (Ref. 9.6.11), which comply with Generic Letter (GL) 99-02 (Ref. 9.10) as demonstrated in Section 7.3. The CRSVS air intake monitors are required to be operable by TS 3.3.6 and Table 3.3.6-1 (Ref. 9.6.12) in Modes 1,2, 3, & 4 and during movement of irradiated fuel assemblies. The CRSVS actuation during the REA is credited in the analysis with a 5-minutes system response delay (Section 2.7). The Aux Bldg Normal Vent dampers that help establish the ABSVZ boundary are not safety related. Acceptability for crediting the dampers is based on the isolation logic for closing the dampers is safety related and redundant in that a single failure cannot defeat the function. The proper functioning of the dampers is verified quarterly as part of established surveillance procedures to satisfy Technical Specifications.

Applicable Technical Specification action statements are applied if a damper fails to properly actuate (Ref.

9.3.2, Item # 9).

Although allowed by Regulatory Guide 1.183 (Ref. 9.1, Appendix H, Section 6. 1), no credit is taken for a reduction in the amount of radioactive material available for leakage from the containment due to natural deposition, containment spray, and elemental iodine removal by surface deposition.

5.1.3 Assignment of Numeric Input Values The numeric values chosen as inputs to this analysis are compatible to AST and TEDE dose criteria and selected with the objective of maximizing the postulated dose. The loss of offsite power for entire duration of the event disabling the condenser, single failure of the motor driven AFW pump, 60/40 split of Groups 1 &.2 PORV steam releases, use of more than measured CR unfiltered inleakage, 5 minutes delay for CRSVS actuation and a 10% lower CR recirculation flow rate are conservatively used to maximize the resulting doses.

II --- X*IEnrgy]* Calculation No. GEN-PI-082 Revision No. 0 Page No. 29 of 145 5.1.4 Meteorology Considerations The control room atmospheric dispersion factors (X/Qs) are developed in References 9.5 & 9.18 using the NRC sponsored ARCON96 computer code. The release points for activity released to the environment are the Units I or 2 turbine driven auxiliary feedwater (TDAFW) pump exhaust and the Groups I & 2 PORV release locations (Ref. 9.3.1, Item # 20) and Units I & 2 Shield Building Vent Stack (Ref. 9.3.2, Item # 22).

Per the AST LOCA Calculation GEN-PI-079 (Ref. 9.13, Sections 2.4.1 & 2.4.2), the use of the CR air intake X/Qs are conservative for the CR unfiltered inleakage and are modeled for both the CR makeup flow during 0 to 5 minutes and the unfiltered inleakage for greater than 5 minutes.

The EAB and LPZ X/Qs used in this analysis were originally developed for the plant operating license and were accepted by the staff in the previous licensing proceedings.

5.2 Accident-Specific Design Inputs/Assumptions The design inputs and assumptions utilized in this EAB, LPZ, and CR dose consequence analysis are listed in the following sections. The design inputs are compatible with the requirements of the AST characteristics and TEDE dose criteria and the assumptions are consistent with those identified in Section 4 and Appendix H of RG 1.183 (Ref. 9.1). The design inputs and assumptions in the following sections represent the as-built design of the plant.

XcelEne Calculation No. GEN-PI-082 Revision No. 0 Page No. 30 of 145 Design Input Parameter Value Assigned Reference Rod Ejection Accident Parameters 5.3 Source Terms 5.3.1 Licensed power level 1,650 MWt 9.6.1 1,683 MWt (= 102% of 1,650 MWt) Used in the analysis for 10% EPU 1,852 MW. = I 10% of 1,683 MWt) 5.3.2 Core isotopic activity (at 1,683 MWt 9.9, Table 2-1 Isotope Activity (Ci) Isotope Activity (Ci) Isotope Activity (Ci) 1-131 4.50E+07 KR-85 7.15E+05 Xe-133M 2.86E+06 1-132 6.51E+07 Kr-85M 1.08E+07 Xe-133 9.15E+07 1-133 9.13E+07 Kr-87 2.12E+07 Xe-135M 1.95E+07 1-134 1.02E+08 Kr-88 2.82E+07 Xe-135 2.07E+07 1-135 8.72E+07 Xe-131M 5.06E+05 Xe-138 7.72E+07 Kr-83M 0.00E+00 _

5.3.3 Primary coolant 1% fuel defects activity concentration 9.9, Table 2-2 Isotope Activity (iCi/g) Isotope Activity (tiCi/g) Isotope Activity (iCi/g) 1-131 2.55E+00 Kr-85 1.09E+01 Xe-133M 3.65E+00 1-132 2.80E+00 Kr-85M 1.59E+00 Xe-133 2.60E+02 1-133 3.88E+00 Kr-87 1.03E+00 Xe-135M 5.02E-01 1-134 5.82E-01 Kr-88 2.89E+00 Xe-135 8.24E+00 1-135 2.20E+00 Xe-131M 2.05E+00 Xe-138 6.09E-01 Kr-83M 3.92E-01 +

RADTRAD Inventory Files Iodine activity initially present in Table 7 the secondary coolant.

Iodine and noble gas activity Table 8 instantaneously released from the RCS liquid to containment Iodine and noble gas activity Table 9 present in the RCS liquid and available for primary-to-secondary leakage 5.3.4 Post-REA failed (clad 10% 9.3.1, Item # 3 damaged) fuel 5.3.5 Percent of gap activity in 9.1, Appendix H, Section 1 damaged fuel released into Containment and available for leakage from containment:

Iodine 10%

Noble Gases 10%

C4Xcelfnergy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 31 of 145 Design Input Parameter Value Assigned Reference 5.3.6 Percent of gap activity in 9.1, Appendix H,Section I damaged fuel released into the RCS and available for P-T-S leakage: 10%

Iodine 10%

Noble Gases 5.3.7 Post-REA melted fuel 0.25% 9.3. 1, Item # 3 5.3.8 Percent of melted fuel 9.1, Appendix H, Section 1 released into containment and available for leakage from containment:

Iodine 25%

Noble Gases 100%

5.3.9 Percent of melted fuel 9.1, Appendix H, Section 1 released into the RCS and available for P-T-S leakage:

Iodine 50%

Noble Gases 100%

5.4 Containment Activity Transport Model (see Figure 1) 5.4.1 Containment volume 1,320,000 ft3 19.3.2, Item # 13 54.2 Shield building free air 374,000 ft3 9.3.2, Item # 24 volume 5.4.3 Iodine chemical form Iodine Chemical Form  % 9.1, Appendix H, Section 4 Aerosol (CsI) 95.0%

Elemental 4.85%

Organic 0.15%

5.4.4 Primary containment (PC) leak rate (Figure 1)

Maximum PC Leakage (L 1 + L 2 + 0.15 w%/day < 24 hrs Proposed New Containment Leak L3) 0.075 w%/day > 24 hrs Rate limit for Reference 9.6.10 ABSVZ Total Leakage (L 2) 0.06 w%/day < 24 hrs 0.03 w%/day > 24 hrs Shield Bldg Total Leakage (L 1) 0.084 w%/day < 24 hrs 0.042 w%/day > 24 hrs Bypass Total Leakage (L 3) 0.006 w%/day < 24 hrs 0.003 w%/day > 24 hrs 5.4.5 Shield building drawdown 4.5 minutes 9.11.1 time 12 minutes Used in the analysis 5.4.6 ABSVZ drawdown time 6 minutes 9.3.2, Item # 30 20 minutes Used in the analysis 5.4.7 Initiation of shield building 20 minutes 9.11.1 & 9.3.2, Item # 32 recirculation 22 minutes Used in the analysis

XcelEnergyl Calculation No. GEN-PI-082 Revision No. 0 Page No. 32 of 145 Design Input Parameter Value Assigned Reference 5.4.8 Shield building recirculation 4,000 cfm +/- 10% 9.3.2, Items # 32 & 34 flow rate 3,600 cfm Used in the analysis 5.4.9 Shield building exhaust rate 9.3.2, Item # 33, SB exhaust flow (50% mixing) rate is doubled to simulate 50%

22 min - 720 hrs 2,000 mixing in the SB after 22 minutes 5.4.10 ABSVS charcoal filter 80% for elemental iodine 9.13, Section 7.5.1 efficiencies 80% for organic iodide 5.4.11 ABSVS & SBVS HEPA 99% for aerosol 9.3.2, Item # 27 Filter Efficiency 5.4.12 Containment Leakage SB Vent Stack 9.3.2, Item # 22 Release Point 5.4.13 Post-LOCA Containment PI250CLOO.psf 9.13 Leakage RADTRAD Model 5.4.14 Nuclide Inventory File for PINGPDEF.NIF 9.13 post-LOCA Containment Leakage 5.4.15 RADTRAD Release pwrdba.rft 9.13 Fraction Time File for post-LOCA Containment Leakage 5.4.16 RADTRAD Dose fgr 1I &I 2.inp 9.13 Conversion Factor File for post-LOCA Containment Leakage 5.5 Secondary System Activity Transport Model (see Figure 2) 5.5.1 Steam generator liquid mass 9.3.1, Item #10 U1 Framatome ANP Model 56/19 107,100 Ibm @ Full Power U2 Westinghouse Model 51 107,420 Ibm @ Full Power 5.5.2 Nominal reactor coolant 5,290 ft3 9.9, Table 6-1 system (RCS) volume 5.5.3 Primary-to-Secondary leak 45.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 9.3.1, Item # 24 duration 5.5.4 RCS operational leakage 150 gpd - one intact SG 9.6.5 through any one SG 300 gpd - two intact SGs Used in the analysis 5.5.5 Density of P-T-S leakage 62.4 lbm/ft3 9.1, Appendix H, Section 7.2 5.5.6 SG liquid iodine partition 100 9.1, Appendix E, Section 5.5.4 and coefficient for SG liquid iodine 9.3.1, Item # 21 release 5.5.7 Iodine release from SG 9.1, Appendix H, Section 5 Elemental Iodine 97%

Organic Iodine 3%

5.5.8 Steam mass released from Table 10 intact SGs to the environment 0 - 2 hr 226,414 Ibm 2 - 8 hr 406,952 Ibm 8 - 24 hr 796,899 lbm 24 - 45.5 hr 863,053 Ibm

XcelEnergy]CalculationNo. GEN-PI-082 Revision No. 0 Page No. 33 of 145 Design Input Parameter Value Assigned Reference 5.5.9 Turbine driven auxiliary 12,000 Ibm/hr 0-2 hrs Table 10 feedwater pump exhaust steam 11,000 Ibm/hr 2-8 hrs release rate 9,500 Ibm/hr 8-24 hrs 9,000 Ibm/hr 24-45.5 hrs 5.5.10 SG liquid iodine partition 100 9.1, Appendix E, Section 5.5.4 coefficient for P-T-S leakage & 9.3.1, Item # 21 5.5.11 Steam condition at full load 519.2 0 F and 806.8 psia - Unit 1 9.11.2, page 1 of 2 510.8 0F and 750 psia - Unit 2 5.6 Control Room (CR) Parameters 5.6.1 CR volume 61,315 ft3 9.3.3, Item # 6 5.6.2 CRSVS normal flow rate 1,818 cfm +/- 10% 9.3.3, Item # 10 2,000 cfm < 5 minutes Used in the analysis 5.6.3 CRSVS makeup rate 0 cfm > 5 minutes 9.3.3, Item # 4 (CR operates in a recirculation mode) 5.6.4 CRSVS Recirc flow rate 4,000 cfm +/- 10% 9.3.3, Item # 13I 3,600 cfm > 5 minutes Used in the analysis 5.6.5 CRSVS charcoal filter 95% for elemental iodine Section 7.3.1 efficiencies 95% for organic iodide 5.6.6 CRSVS HEPA filter 99% Section 7.3.2 efficiency 5.6.7 CR unfiltered inleakage 250 cfm (includes 10 cfm for Assumed value ingress and egress) 5.6.8 CR breathing rate 3.5E-04 m 3/sec 9.1, Section 4.2.6 5.6.9 CR allowable dose limit 5 rem TEDE for the event duration 9.4 5.6.10 Unit 2 CR X/Qs for containment leakage via Unit 2 SB exhaust stack release Time (Hr) X/Q (sec/m 3) 9.18, Section 8.1.1 (maximum 0-2 4.53E-03 x/Qs for any SBVS release to CR 2-8 3.93E-03 air intake dispersion path) 8-24 1.73E-03 24-96 1.22E-03 96-720 9.16E-04 5.6.11 CR occupancy factors Time (Hr)  % 9.1, Section 4.2.6 0-24 100 24-96 60 96-720 40 5.6.12 Unit 1 CR air intake X/Qs for Unit 1 ADV / Turbine Driven Aux Feedwater Pump Exhaust release Time (Hr) X/Q (sec/m 3) 9.5, Table 6, Case 12a (which has 0-2 4.66E-02 less dispersion than Case 12b).

2-8 3.62E-02 These values used in Table 12 to 8-24 1.55E-02 develop X/Qs for RADTRAD use.

24-96 1.12E-02 96-720 9.95E-03

XcelEner Calculation No. GEN-PI-082. Revision No. 0Pg o 4o 4 Design Input Parameter Value Assigned Reference 5.6.13 Unit 2 CR air intake XIQs for Unit 2 ADV / Turbine Driven Aux Feedwater Pump Exhaust release Time (Hr) X/Q (sec/m 3) 9.5, Table 6, Case 22b (which has 0-2 9.89E-03 less dispersion than Case 22a).

2-8 7.51E-03 These values used in Table 13 to 8-24 3.29E-03 develop X/Qs for RADTRAD use.

24-96 2.23E-03 96-720 1.73E-03 5.6.14 Unit I CR air intake y,/Qs for Unit I Safety & Relief Valve (PORV) Group I Release - Intact SG Time (Hr) X/Q (sec/m 3) 9.5, Table 6, Case 13a (which has 0-2 1.87E-02 less dispersion than Case 13b).

2-8 1.31E-02 These values used in Table 12 to 8-24 5.5 1E-03 develop X/Qs for RADTRAD use.

24-96 3.52E-03 96-720 2.76E-03 5.6.15 Unit 2 CR air intake Z/Qs for Unit 2 Safety & Relief Valve (PORV Group 1 Release - Intact SG Time (Hr) X/Q (sec/m 3) 9.5, Table 6, Case 23b (which has 0-2 3.06E-02 less dispersion than Case 23a).

2-8 2.46E-02 These values used in Table 13 to 8-24 1.11 E-02 develop X/Qs for RADTRAD use.

24-96 7.76E-03 96-720 6.14E-03 5.6.16 Unit I CR air intake X/Qs for Unit 1 Safety & Relief Valve (PORV) Group 2 Release - Intact SG Time (Hr) X/Q (sec/m 3 ) 9.5, Table 7, Case 14a (which has 0-2 1.89E-03 less dispersion than Case 14b).

2-8 1.35E-03 These values used in Table 12 to 8-24 5.33E-04 develop X/Qs for RADTRAD use.

24-96 3.54E-04 96-720 2.75E-04 5.6.17 Unit 2 CR air intake y,/Qs for Unit 2 Safety & Relief Valve (PORV) Group 2 Release - Intact SG Time (Hr) X/Q (sec/m3 ) 9.5, Table 7, Case 24b (which has 0-2 2.47E-03 less dispersion than Case 24a).

2-8 1.97E-03 These values used in Table 13 to 8-24 8.76E-04 develop X/Qs for RADTRAD use.

24-96 5.62E-04 96-720 4.32E-04 5.6.18 Limiting Weighted Average Unit 2 x/Qs Used In Analysis for Intact Steam Release via PORV and TDAFW Time (Hr) X/Q (sec/m 3) Table 13 0-2 1.83E-02 2-8 1.42E-02 8-24 6.30E-03 24-96 4.29E-03 96-720 3.38E-03 5.6.19 PORV mass release 60% from the Group I PORVs 9.3.1 distribution 40% from the Group 2 PORVs 5.6.20 CR Monitor Setpoint 1.OE-05 ptCi/mi for Xe-133 9.3.2, Item #9

XcelEnergy]CalculationNo. GEN-PI-082 Revision No. 0 Page No. 35 of 145 Design Input Parameter Value Assigned Reference 5.7 Site Boundary Release Model Parameters 5.7.1 EAB atmospheric dispersion 6.49E-04 sec/m 3 9.3.4, Item # 2 factor (X/Q)breathing rate (m3 /sec) 5.7.2 EAB 3.5E-04 9.1, Section 4.1.3 5.7.3 LPZ Distance 2,414 m 9.3.4, Item # 3 5.7.4 LPZ Atmospheric Dispersion Factors (x/Qs)

Time (Hr) X/Q (sec/m 3) 9.3.4, Item # 3 0-8 1.77E-04 8-24 3.99E-05 24-96 7.12E-06 96-720 1.04E-06 5.7.5 LPZ Breathing Rate (m3/sec)

Time (Hr) (m3/sec) 9.1, Section 4.1.3 0-8 3.5E-04 8-24 1.8E-04 24-720 2.3E-04 5.7.6 EAB allowable dose limit 6.3 rem TEDE for any 2-hour 9.1, Table 6 period 5.7.7 LPZ allowable dose limit 6.3 rem TEDE for the event 9.1, Table 6 duration

ScelEnergy]Calculation No. GEN-PI-082 Revision No. 0 Page No. 36 of 145 6.0 COMPUTER CODES & COMPLIANCE WITH REGULATORY REQUIREMENTS 6.1 COMPUTER CODES:

RADTRAD 3.03 (Ref. 9.2) is an NRC-sponsored code approved for use in determining control room and offsite doses from releases due to reactor accidents. This code was used by the most of the AST license amendments that have been approved by the NRC. A rigorous high quality code qualification process was adopted to develop and procure the code by testing of the program elements, verification of input/output files, and examination of design specification. Therefore the RADTRAD3.03 computer code is considered to be qualified to comply with the quality assurance requirements of 10 CFR50, Appendix B and it can be safely used to perform the design basis accident analyses.

Calculation GEN-PI-079 (Ref. 9.13, Sections 2.6 & 8.2) documents a V&V of the RADTRAD3.03 code. Suitable acceptance test cases for the PWR radiological analysis were incrementally selected, initially defining simplified cases that could verified against analytical solutions, then adding complexity (typically a control room) and comparing the results against the RADTRAD3.03 and HABIT code analyses, adding more complexity (e.g., removal by decay chain) and comparing the results with the RADTRAD3.03 and HABIT codes again. The selected PWR code cases cover all essential characteristics of an REA AST analysis, including transportation of activity within the compartment and in the atmosphere. All radiological features of the RADTRAD3.03 code were verified and validated by running the selected PWR code cases in the Microsoft Window XP environment. The results of V&V code cases were summarized in Calculation GEN-PI-079, Section 8.2, and compared with the RADTRAD3.03 and HABIT code results, which showed an excellent agreement.

Therefore, the RADTRAD code is considered validated for use in this PINGP AST analysis.

6.2 COMPLIANCE WITH REGULATORY REQUIREMENTS:

As discussed in Section 4.0, Assumptions, the analysis in this calculation complies with the line-by-line requirements in Regulatory Guide 1.183 including its Appendix H.

XceIEnergy]Calculation No. GEN-PI-082 Revision No. 0 Page No. 37 of 145

7.0 CALCULATIONS

The REA dose consequences are determined by summing together the results from a set of three RADTRAD code analyses that separately calculate the dose contributions from the containment leakage, primary-to-secondary (P-T-S) leakage iodine activity release, the P-T-S leakage noble gas activity release, and the secondary liquid iodine release.

RADTRAD Nuclide Inventory Files (NIF) "PIREACNTdef.txt" and "PIREARCS def.txt" model the nuclide inventory of Table 8 for the containment leakage and Table 9 for the secondary system leakage, respectively.

RADTRAD NIF "PIREA_liq def.txt" models the secondary coolant iodine inventory of Table 7.

RADTRAD RFT File "pirea rft.txt" is used for both iodine and noble gas release by setting the iodine and noble gas release fractions to 1.0, and all other release fractions to zero. RADTRAD Release Fraction Timing (RFT) File "PINGPIodine RFT.txt" is used for iodine release by setting the iodine release fraction to 1.0 and all other release fractions to zero. RADTRAD RFT File "PIREA_NGRFT.txt" is used for noble gas release by setting the noble gas release fraction to 1.0 and all other release fractions to zero. These release fractions can be seen in the RADTRAD output pages.

All four RADTRAD runs use Dose Conversion File (DCF) "P[NGPfgl 1&12.txt", which uses CEDE inhalation DCFs from FGR- I I (Ref. 9.7), and EDE immersion DCFs from FGR-12 (Ref. 9.8).

7.1 Reactor Coolant & Steam Generator Coolant Mass 7.1.1 RCS Mass:

RCS water volume = 5,290 ft3 @ 560'F and 2235 psia (Ref. 9.9, Table 6-1 & Ref. 9.3.1, Item # 22)

RCS specific volume at 560'F and 2235 psia = 0.02165 ft3/lb (Ref. 9.14, page 281)

RCS density at 560'F and 2235 psia = 1 / (0.02165 ft3/lb) = 46.19 lb/ft3 RCS water density at cooled liquid conditions = 62.4 lb/ft3 (Ref. 9.1, Appendix H, Section 7.2)

The RCS mass at cooled liquid conditions is:

RCS Mass = 5,290 ft3 x 62.4 lb/ft3 x 453.6 gm/lb = 1.497E+08 gm [used in Tables 4 and 6] (a larger mass yields a greater RCS activity inventory available for leakage) 7.1.2 SG Liquid Volume and Mass:

The steam generator (SG) tubes are expected to be submerged in the intact SGs coolant during the REA event, with no tube uncovery (Ref. 9.3.1, Item # 21). The iodine activity in the P-T-S leakage is assumed to mix with SG coolant without flashing during period of submergence (Ref. 9.1, Appendix H, Section 7.4 and Appendix E, Section 5.5.1 ).

The Unit I SGs are Framatome ANP Model 56/19 with a full power liquid mass of 107,100 lb (Ref. 9.3.1, Item # 10). The Unit 2 SGs are Westinghouse Model 51 with a full power liquid mass of 107,420 lb (Ref. 9.3.1, Item # 10). The total intact SG liquid volume is minimized by assuming that the secondary liquid mass is at cooled liquid conditions. Minimizing the intact SGs dilution volume will maximize the intact SGs liquid activity concentrations due to P-T-S leakage. Maximizing the intact SGs liquid activity concentration will conservatively maximize the intact SGs steaming activity releases to the environment.

Total intact SG liquid mass.= 107,100 lb + 107,420 lb = 214,520 lb x 453.6 gm/lb = 9.73 1E+07 gm 3 3 Total intact SG liquid volume = 214,520 lb / 62.4 lb/ft = 3,438 ft

Xcel nergy]Calculation No. GEN-PI-082 Revision No. 0 Page No. 38 of 145 7.2 Post-REA Release Rates 7.2.1 P-T-S Leakage Iodine and Noble Gas Release Rate Per Design Input 5.5.4, the primary to secondary leakage through any one SG is 150 gpd.

P-T-S volumetric leakage rate into intact SGs = 0.208 gpm (= [2 SGs x 150 gpd/SG] / [24 hr/day x 60 min/hr])

P-T-S volumetric leakage rate into intact SGs = (0.208 gpm) x (0.13368 ft3/gal) = 0.02781 cfm Per Regulatory Guide 1.183 (Ref. 9.1, Appendix H, Section 7.2), the density of this P-T-S leakage at the time of

• surveillance test measurement is assumed to be 1.0 gm/cc (62.4 lb/ft3). Therefore, the P-T-S mass leakage rate into the intact SGs at measured conditions is:

P-T-S mass leakage rate at measured conditions -- (0.02781 ft3/min) x (62.4 lb/ft3 ) = 1.735 lb/min Per Section 7.1.1, at the time of the REA the RCS is operating at 560'F and 2235 psia with an RCS specific volume of 0.02165 ft3/lb. Therefore, the iodine and noble gas P-T-S volumetric leakage rate into the intact SGs at conditions present during the REA is:

0-45.5 hr P-T-S volumetric leakage rate during the REA = (1.735 lb/min) x (0.02165 ft3 /ib) 0-45.5 hr P-T-S volumetric leakage rate during the REA = 0.0376 cfm of RCS liquid 0-45.5 hr iodine and noble gas P-T-S leakage rate from RCS to the intact SGs = 0.0376 cfm 7.2.2 Intact SGs PORVs Steaming Rates (P-T-S Leakage):

Unit I steam temperature @ full power = 519.20 F and 806.8 psia (Ref. 9.11.2)

Unit I liquid specific volume @ full power = 0.02089 ft3/lbm (Ref. 9.14,'page 182)

Unit 2 steam temperature @ full power = 510.8 0 F and 750 psia (Ref. 9.11.2)

Unit 2 liquid specific volume @ full power = 0.02069 ft3/lbm (Ref. 9.14, page 182)

Unit I liquid specific volume of 0.02089 ft3/lbm is conservatively used in the following section to maximize the volumetric steaming rates:

The intact SGs tubes remain covered during the REA, the iodine partition factor of 100 (Ref. 9.1, Appendix H, Section 5.6 and Appendix E, Section 5.5.4) is credited in calculating the steaming rate from the intact SGs:

Total mass of steam released from intact SG to the environment (0 - 2 hr) = 226,414 lb (Table 10)

Intact SG steaming rate (0 - 2 hr) = 226,414 lb x 0.02089 ft3/Ib x (1/100) 0.3942 cfm of Intact SG liquid 120 minutes Total mass of steam released from intact SG to the environment (2 - 8 hr) = 406,952 (Table 10)

Intact SG steaming rate (2 - 8 hr) =-406,952 lb x 0.02089 ft3/lb x (1/100) = 0.2361 cfm of Intact SG liquid 360 minutes Total mass of steam released from intact SG to the environment (8 - 24 hrs) = 796,899 lb (Table 10)

XceIEnery Calculation No. GEN-PI-082 Revision No. 0 Page No.39 of 145 Intact SG steaming rate (8-24 hr) = 796,899 lb x 0.02089 ft3/lb x (1/100) = 0.1734 cfm of Intact SG liquid 960 minutes Total mass of steam released from intact SG to the environment (24 - 45.5 hrs) = 863,053 lb (Table 10)

Intact SG steaming rate (24 -45.5 hr) = 863,053 lb x 0.02089 ft3/lb x (1/100) = 0.1398 cfm of Intact SG liquid 1290 minutes 0 - 2 hr iodine P-T-S leakage release from intact SG to the environment = 0.3942 cfm of Intact SG liquid 2 - 8 hr iodine P-T-S leakage release from intact SG to the environment = 0.2361 cfm of Intact SG liquid 8 - 24 hr iodine P-T-S leakage release from intact SG to the environment = 0.1734 cfm of Intact SG liquid 24 - 45.5 hr iodine P-T-S leakage release from intact SG to the environment = 0.1398 cfm of Intact SG liquid 7.2.3 Intact SGs - Iodine Release Rate - Secondary Liquid The steaming rates for the secondary liquid iodine releases from the intact steam generators are the same as the intact SGs iodine release rates calculated in Section 7.2.2.

0 - 2 hr iodine secondary liquid release from intact SG to the environment = 0.3942 cfm of Intact SG liquid 2 - 8 hr iodine secondary liquid release from intact SG to the environment = 0.2361 cfm of Intact SG liquid 8 - 24 hr iodine secondary liquid release from intact SG to the environment = 0.1734 cfm of Intact SG liquid 24 - 45.5 hr iodine secondary liquid release from intact SG to the environment = 0.1398 cfm of Intact SG liquid 7.3 CRSVS Charcoal / HEPA Filter Efficiencies The Control Room Special Ventilation System (CRSVS) charcoal and HEPA filter efficiencies are modeled per the following table, based on the calculations performed in the following subsections.

Safety Grade Filter Efficiency Credited (%)

Filter Aerosol Elemental Organic CRSVS 99 95 95 7.3.1 CRSVS Charcoal Filter Efficiency Laboratory penetration testing acceptance criteria for the safety related Charcoal filters are as follows:

CRSVS Charcoal Filter - in-laboratory testing methyl iodide penetration < 2.5% (Ref. 9.6.11 Section 5.5.9.c)

Generic Letter 99-02 (Ref. 9.10) requires a safety factor of at least 2 to be used to determine the filter efficiencies to be credited in the design basis accident.

Testing methyl iodide penetration (%) = (100% - rl)/safety factor = (100% -,q)/2 Where 11= charcoal filter efficiency to be credited in the analysis CRSVS Charcoal Filter:

2.5% = (100% -,n)/2

~.XceI Energy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 40 of 145 5% = (l00%- T) r1 = 100% - 5% = 95%

7.3.2 CRSVS HEPA Filter Efficiency CRSVS HEPA Filter- in-place DOP penetration and system bypass < 0.05% (Ref. 9.6.11 Section 5.5.9.a)

Genetic Letter 99-02 (Ref. 9.10) requires a safety factor of at least 2 to be used to determine the filter efficiencies to be credited in the design basis accident.

Testing DOP penetration (%) = (100% - rq)/safety factor = (100% - 71)/2 Where r = HEPA filter efficiency to be credited in the analysis CRSVS HEPA Filter:

0.05% = (100% - 7)/2 0.10% = (100% - TI) 11 = 100% - 0.10% = 99.9%

Regulatory Guide 1.52 (Ref. 9.21, Regulatory Position C.5.c) states that if the in-place penetration and bypass testing results are <0.05%, the condition can be considered to warrant a 99% removal efficiency for particulates in accident dose evaluations. Therefore, a HEPA filter efficiency of 99% is used in the analysis.

XceI Energy]Calculation No. GEN-PI-082 Revision No. 0 Page No.41 of 145 8.0 RESULTS

SUMMARY

/CONCLUSIONS:

8.1 Result Summary:

The post-REA EAB, LPZ, and CR doses are summarized in the following table:

Rod Ejection Accident TEDE Dose (rem)

Receptor Location Control Room EAB LPZ Containment Leakage 4.1 IE-01 1.93E-01 1.17E-01 PIREACLOO.o0 (occurs @ 0.0 hr)

I P-T-S Iodine Release ISG 2.77E+00 2.88E-01 1.67E-01 PREAINIDOO.oO (occurs @ 24 hrs)

P-T-S Noble Gas Release ISG 2.82E-01 1.87E-01 1.02E-0I PREAINGOO.oO (occurs @ 0.0 hrs)

Liquid Iodine Release ISG 9.78E-03 1.1 7E-03 9.66E-04 PREAINLQOO.oO (occurs @ 0.0 hrs)

External Cloud* 4.51 E02 0.OOE+00 O.OOE+00 CR Filter Shine* 2.33E-02 0.OOE+00 O.OOE+00 Total 3.54E+00 6.69E-01 3.87E-01 Allowable TEDE Limit 5.OOE+00 6.30E+00 6.30E+00 ISG = Intact SG

• Post-LOCA External Cloud & CR Filter Shine Doses Used From Reference 9.13, Section 8.1 8.2

Conclusions:

The results of Rod Ejection Accident analysis in Section 8.1 indicate that the EAB, LPZ, and CR doses due to a REA accident are within their allowable limits. The calculated doses have adequate margins over the allowable dose limits for future safe operation of the plant. The proposed new LCO 3.4.17 for Reactor Coolant System Specific Activity is 580 .tCi/gm DE of XE-I133 based on the primary coolant noble gas activity correspond to 1% failed fuel with the following changes:

• Delete the definition of "E-Bar," AVERAGE DISINTEGRATION ENERGY 0 Add a new definition for DOSE EQUIVALENT XE-133 0 Revise LCO 3.4.17, "RCS Specific Activity, to delete references to gross specific activity 0 Reference limit on DOSE EQUIVALENT XE-I 33

• Revise SR 3.4.16.1 to verify the limit for DOSE EQUIVALENT XE-133

SXceEnergy, Calculation No. GEN-PI-082 Revision No. 0 Page No. 42 of 145

9.0 REFERENCES

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

2. S.L. Humphreys et. al., "RADTRAD: A Simplified Model for Radionuclide Transport and Removal and Dose Estimation," NUREG/CR-6604, USNRC, December 1997

3. Design Input Transmittal Nos.

3.1 Design Input Transmittal (DIT) No. 13720-10, Rev. 0, CREA Input Parameters 3.2 Design Input Transmittal (DIT) No. 13720-05, Rev. 0, LOCA Dose Analysis Input Parameters 3.3 Design Input Transmittal (DIT) No. 13720-07, Rev. 1, Control Room Input Parameters 3.4 Design Input Transmittal (DIT) No. 13720-03, Rev. 0, Meteorological Input Parameters

4. 10 CFR 50.67, "Accident Source Term"

5. PINGP Calculation No. GEN-PI-049, Rev 0 and Addendum 2, PI Control Room Atmospheric Dispersion Factors (X/Q)

6. PINGP Technical Specifications:

6.1 Specification 1.1, PINGP Units 1 & 2, Rated Thermal Power 6.2 Specification 1.1, PINGP Units 1 &2, Dose Equivalent 1-131 6.3 Specification 1.1, PINGP Units 1 & 2, E-bar Average Disintegration Energy 6.4 Specification 3.6.9, PINGP Units 1 & 2 LCO for Shield Building Ventilation System (SBVS) 6.5 Specification 3.4.14, PINGP Units 1 & 2 LCO for RCS Operational Leakage 6.6 Specification 3.4.17, PINGP Units 1 & 2 LCO for RCS Specific Activity 6.7 Specification 3.7.10, PINGP Units 1 & 2 LCO for Control Room Special Ventilation System (CRSVS) 6.8 Specification 3.7.12, PINGP Units 1 & 2 LCO for Auxiliary Building Special Ventilation System (ABSVS) 6.9 Specification 3.7.14, PINGP Units 1 & 2 Limiting Condition for Operation (LCO) for Secondary Specific Activity 6.10 Specification 5.5.14.c, Containment Leak Rate Testing Program 6.11 Specification 5.5.9, Ventilation Filter Testing Program (VFTP) 6.12 Specification 3.3.6, PINGP Units 1 & 2 LCO for Control Room Special Ventilation System (CRSVS) Actuation Instrumentation and Table 3.3.6-1, PINGP Unit I/Unit 2 LCO for Radiation Monitoring Instrumentation

7. Federal Guidance Report 11, EPA-520/1-88-020, Environmental Protection Agency 8 Federal Guidance Report 12, EPA-402-R-93-081, Environmental Protection Agency

9. Westinghouse Letter NSP-07-59, LTR-PEP-07-26, Nuclear Management Company Prairie Island Units 1 & 2 MUR Power Uprate Program, Core Activity Inventory and Coolant Activity Concentration, November 2, 2007.

10. USNRC Generic Letter 99-02, "Laboratory Testing of Nuclear-Grade Activated Charcoal", June 3, 1999

XceIEnergy]Calculation No. GEN-PI-082 Revision No. 0 Page No. 43 of 145

11. PINGP USAR Sections, Tables, & Figures:

11.1 Section 14.9, Environmental Consequences of Loss-Of-Coolant-Accident 11.2 Table 4.1-5, Rev 27, Steam Generator Design Data 11.3 PINGP USAR Section 14.5.6, Rev 29P, Rupture of a Control Rod Drive Mechanism Housing (RCCA Ejection)

12. NUREG-0800, Standard Review Plan, "Radiological Consequence Analyses Using Alternative Source Terms," SRP 15.0.1, Rev. 0, July 2000

13. P[NGP Calculation No. GEN-PI-079, Rev 0, Post-LOCA EAB, LPZ, and CR Doses - AST

14. ASME Steam Tables, Sixth Edition

15. Technical Specification Task Force Improved Standard Technical Specifications Change Traveler TSTF-490, Rev 0, "Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec"

16. PINGP Procedure Nos:

1. 1ES-0.3A, Rev 14, Natural Circulation Cooldown With CRDM Fans

2. 1ES-0.3B, Rev 11, Natural Circulation Cooldown Without CRDM Fans

17. PINGP License Amendment Request (LAR) L-PI-08-052, LAR to Revise the Loss of Coolant Accident (LOCA) and Main Steam Line Break Accident (MSLB) Dose Consequences Analyses and Affected Technical Specifications (TS), June 26, 2008

18. PINGP Calculation No. GEN-PI-080, Rev 0, Prairie Island Atmospheric Dispersion Factors (x/Qs) -

AST Additional Releases

19. Beaver Valley Power Station, Unit Nos. I and 2, Issuance of License Amendments 257 and 139 Re:

Selective Implementation of Alternate Source Term and Control Room Habitability Technical Specification Changes, September 10, 2003 (ADAMS Accession Number ML032530204)

20. PINGP USAR Section 4.3.2.1.1, Rev 28, Steam Generators

21. U.S. NRC Regulatory Guide 1.52, Rev 2, Design, Testing, and Maintenance Criteria for Postaccident Engineered-Safety-Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants, March 1978

22. PINGP Flow Diagram No. NF-39603-1, Rev 76, Including T-Mod EC 14090, Admin Bldg, Screen House, & Control RM Flow Diagram

&I XceI Energy Calculation No. GEN-PI-082 Revision No. 0 Page No. 44 of 145 10.0 TABLES:

Table I Iodine Isotopic Dose Conversion Factors Radiation Units Thyroid Thyroid Radiation Units Thyroid Inhalation Conversion Inhalation Dose Factors Dose Isotope Conversion Conversion Factor Factor (Sv/Bq) (rem/Ci per Sv/Bq) (rem/Ci)

A B C=AxB 1-131 2.92E-07 3.70E+ 12 1.08E+06 1-132 1.74E-09 3.70E+ 12 6.44E+03 1-133 4.86E-08 3.70E+ 12 1.80E+05 1-134 2.88E-10 3.70E+12 1.07E+03 1-135 8.46E-09 3.70E+12 3.13E+04 (A) From Reference 9.7, Page 136 Table 2 Iodine Scaling Factor for 1-131 Dose Equivalent 1% Fuel Defect Thyroid Iodine Inhalation Activity Dose Product Isotope Concentration Conversion Factor (PCi/gm) (rem/Ci) (tCi.rem / Ci.gm)

A B (A x B) 1-131 2.55E+00 1.08E+06 2.76E+06 1-132 2.80E+00 6.44E+03 1.80E+04 1-133 3.88E+00 1.80E+05 _ 6.98E+05 1-134 5.82E-01 1.07E+03 6.20E+02 1-135 2.20E+00 3.13E+04 6.89E+04 Total 3.54E+06 1-131 DE Based on 1% FF Iodine Concentration (tCi/g); (C) 3.28E+00 Iodine Scaling Factor Based on 0.50 pCi/g DE 1-131; (D) 1.526E-01 (A) From Reference 9.9, Table 2-2 for HB x 1.04, based on 1683 MWt per Reference 9.9, Table 6-1 (C) = Total / Iodine-131 Thyroid Inhalation Dose Conversion Factor (D) = 0.50 pCi/gm DE I- 131 / C

Xce Energy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 45 of 145 Table 3 RCS 0.50 gCi/gm DE 1-131 Iodine Concentration 1% Failed Fuel Iodine 0.50 PiCi/gm Iodine Scaling DE 1-131 Isotope Activity Factor Iodine Concentration 0.50 JACi/gm Concentration (PCi/gm) DE 1-131 (PtCi/gm)

A B C=AxB 1-131 2.55E+00 1.526E-01 3.891E-01 1-132 2.80E+00 1.526E-01 4.272E-01 1-133 3.88E+00 1.526E-01 5.920E-01 :I 1-134 5.82E-01 1.526E-01 8.880E-02 1-135 2.20E+00 1.526E-01 3.357E-01 A From Reference 9.9, Table 2-2 for HB x 1.04, based on 1683 MWt per Reference 9.9, Table 6-1 B From Table 2 Table 4 1% Failed Fuel RCS Iodine Activity 1% Fuel Defect Reactor Total RCS Iodine Coolant Pre-Accident Isotope Activity Mass RCS Iodine Concentration Activity (PCi/gm) (gm) (Ci)

A B C=(Ax B)/IE6 1-131 2.55E+00 1.497E+08 3.817E+02 1-132 2.80E+00 1.497E+08 4.192E+02 1-133 3.88E+00 1.497E+08 5.808E+02 1-134 5.82E-01 1.497E+08 8.713E+01 1-135 2.20E+00 1.497E+08 3.293E+02 (A) From Reference 9.9, Table 2-2 for HB x 1.04, based on 1683 MWt per Reference 9.9, Table 6-1 (B) Reactor coolant mass from Section 7.1.1

XceI nergy Calculation No. GEN-PI-082 Revision No. 0 Page No. 46 of 145 Table 5 Dose Equivalent of Xenon-133 1% Failed Submersion Noble Fuel RCS Dose Product Gas Activity Coefficient Nuclide (gCi/gm) (Sv M 3 / Bq s) (gCi/gm

• Sv m3 / Bq s)

A B C=AxB KR-85 1.09E+01 1.19E- 16 1.297E- 15 KR-85M 1.59E+00 7.48E- 15 1.1 89E- 14 KR-87 1.03E+00 4.12E-14 4.244E-14 KR-88 2.89E+00 1.02E-13 2.948E- 13 XE-131M 2.05E+00 3.89E-16 7.975E-16 XE- 133 2.60E+02 1.56E- 15 4.056E- 13 XE-133M 3.65E+00 1.37E-15 5.001E-15 XE-135 8.24E+00 1.19E-14 9.806E- 14 XE-135M 5.02E-01 2.04E- 14 1.024E-14 Xe-138 6.09E-0 I 5.77E-14 3.514E-14 Total (gtCi/gm

• Sv / Bg s m3) 9.052E-13 Xe-133 DE Based on 1% FF NG Concentration 580 A From Reference 9.9, Table 2-2 for HB x 1.04, based on 1683 MWt per Reference 9.9, Table 6-1 (Kr-83M omitted per definition of Dose Equivalent Xe-133)

B From FGR 12, Table 111.1 Table 6 Total RCS Noble Gas Activity 1% Fuel Defect Reactor Total RCS Noble Gas Coolant Pre-Accident Isotope Activity Mass RCS Noble Gas Concentration Activity (P.Ci/gm) (gm) (Ci)

A B C =(A x B) /1E6 KR-83M 3.92E-01 1.497E+08 5.868E+01 KR-85 1.09E+01 1.497E+08 1,632E+03 KR-85M 1.59E+00 1.497E+08 2.380E+02 KR-87 1.03E+00 1.497E+08 1.542E+02 KR-88 2.89E+00 1.497E+08 4.326E+02 XE-131M 2.05E+00 1.497E+08 3.069E+02 XE-133 2.60E+02 1.497E+08 3.892E+04 XE-133M 3.65E+00 1.497E+08 5.464E+02 XE-135 8.24E+00 1.497E+08 1.234E+03 XE-135M 5.02E-0 I 1.497E+08 7.515E+01 Xe-138 6.09E-01 1.497E+08 9.117E+01 (A) From Reference 9.9, Table 2-2 for 1B x 1.04, based on 1683 MWt per Reference 9.9, Table 6-1 (B) Reactor coolant mass from Section 7.1.1

XceI Energ Calculation No. GEN-P°-082 Revision No. 0 Page No.47 of 145 Table 7 Total REA Iodine Activity Initially Present in the Secondary Coolant 0.50 jiCi/gm Tech Spec Coolant Mass Total RADTRAD DE 1-131 Secondary In Both Intact Pre-Accident Nuclide Isotope Iodine Specific Steam Secondary Coolant Inventory File Concentration Activity Limit Generators Iodine Activity pirea_liqdef.txt (gtCi/gmn) (unitless) (gm) (gtCi) (Ci/MWt)

A B C D=(AxBxC)/0.50 E = D/(1683 x IE6) 1-131 3.891 E-01 0.10 9.731E+07 7.573E+06 .4500E-02 1-132 4.272E-O1 0.10 9.731E+07 8.315E+06 .4940E-02 1-133 5.920E-01 0.10 9.731E+07 1.152E+07 .6846E-02 1-134 8.880E-02 0.10 9.731E+07 1.728E+06 .1027E-02 1-135 3.357E-01 0.10 9.731E+07 6.533E+06 .3882E-02 A, E From Table 3, based on 1683 MWt per Reference 9.9, Table 6-1 B From Reference 9.6.9 C From Section 7.1.2

XceIEnergy]Calculation No. GEN-PI-082 Revision No. 0 Page No. 48 of 145 Table 8 Post-REA Iodine & Noble Gas Activity Instantaneously Released from RCS Liquid To Containment Design Basis CREA CREA Initial Total RADTRAD Core Activity Activity Activity Activity Core Nuclide Isotope Inventory From From From Released Thermal Inventory 10% 0.25% Primary To Power File Failed Fuel Melted Fuel Coolant Containment Level pireacntdef.txt (Ci) (Ci) (Ci) (Ci) (Ci) (MWj) (Ci/MW,)

A B C D E=B+C+D F G=E/F KR-83M 0.00E+00 0.OOOE+00 0.OOOE+00 5.868E+01 5.868E+01 1683 .3487E-01 KR-85 7.15E+05 7.150E+03 1.788E+03 1.632E+03 1.057E+04 1683 .6280E+01 KR-85M 1.08E+07 1.080E+05 2.700E+04 2.380E+02 1.352E+05 1683 .8036E+02 KR-87 2.12E+07 2.120E+05 5.300E+04 1.542E+02 2.652E+05 1683 .1575E+03 KR-88 2.82E+07 2.820E+05 7.050E+04 4.326E+02 3.529E+05 1683 .2097E+03 1-131 4.50E+07 4.500E+05 2.813E+04 3.817E+02 4.785E+05 1683 .2843E+03 1-132 6.51E+07 6.510E+05 4.069E+04 4.192E+02 6.921E+05 1683 .4112E+03 1-133 9.13E+07 9.130E+05 5.706E+04 5.808E+02 9.706E+05 1683 .5767E+03 1-134 1.02E+08 1.020E+06 6.375E+04 8.713E+01 1.084E+06 1683 .6440E+03 1-135 8.72E+07 8.720E+05 5.450E+04 3.293E+02 9.268E+05 1683 .5507E+03 XE-131M 5.06E+05 5.060E+03 1.265E+03 3.069E+02 6.632E+03 1683 .3941E+01 XE- 133 9.15E+07 9.150E+05 2.288E+05 3.892E+04 1.183E+06 1683 .7027Et03 XE-133M 2.86E+06 2.860E+04 7.150E+03 5.464E+02 3.630E+04 1683 .2157E+02 XE-135 2.07E+07 2.070E+05 5.175E+04 1.234E+03 2.600E+05 1683 .1545E+03 XE-135M 1.95E+07 1.950E+05 4.875E+04 7.515E+01 2.438E+05 1683 .1449E+03 XE-138 7.72E+07 7.720E+05 1.930E+05 9.117E+01 9.651E+05 1683 .5734E+03 A, F From Reference 9.4, Table 2-1, based on 1683 MWt per Reference 9.9, Table 6-1 B = (A x 0.10 x 0.10) = 0.01A for iodine [10% iodine release from 10% clad damage]

= (A x 0.10 x 0.10) = 0.0 1A for noble gas [10% noble gas release from 10% clad damage]

C = (A x 0.25 x 0.0025) = 0.000625A for iodine [25% iodine release from 0.25% melted fuel]

= (A x 1.00 x 0.0025) = 0.0025A for noble gas [100% noble gas release from 0.25% melted fuel]

D - Iodine From Table 4 & Noble Gas From Table 6

XceIEnergy Calculation No. GEN-PI-082 Revision No. 0 Page No.49 of 145 Table 9 Post-REA Iodine & Noble Gas Activity In the RCS and Available for Primary-to-Secondary System Leakage Design Basis CREA CREA Initial Total RADTRAD Core Activity Activity Activity Activity Core Nuclide Isotope Inventory From From From Released Thermal Inventory 10% 0.25% Primary Into Power File Failed Fuel Melted Fuel Coolant RCS Level pirearcsdef.txt (Ci) (Ci) (Ci) (Ci) (Ci) (MW,) (Ci/MW,)

A B C D E=B+C+D F G=EIF KR-83M 0.00E+00 0.OOOE+00 0.000E+00 5.868E+01 5.868E+01 1683 .3487E-01 KR-85 7.15E+05 7.150E+03 1.788E+03 1.632E+03 1.057E+04 1683 .6280E+01 KR-85M 1.08E+07 1.080E+05 2.700E+04 2.380E+02 1.352E+05 1683 .8036E+02 KR-87 2.12E+07 2.120E+05 5.300E+04 1.542E+02 2.652E+05 1683 .1575E+03 KR-88 2.82E+07 2.820E+05 7.050E+04 4.326E+02 3.529E+05 1683 .2097E+03 1-131 4.50E+07 4.500E+05 5.625E+04 3.817E+02 5.066E+05 1683 .3010E+03 1-132 6.51E+07 6.510E+05 8.138E+04 4.192E+02 7.328E+05 1683 .4354E+03 1-133 9.13E+07 9.130E+05 1.141E+05 5.808E+02 1.028E+06 1683 .6106E+03 1-134 1.02E+08 1.020E+06 1.275E+05 8.713E+01 1.148E+06 1683 .6819E+03 1-135 8.72E+07 8.720E+05 1.090E+05 3.293E+02 9.813E+05 1683 .5831E+03 XE-131M 5.06E+05 5.060E+03 1.265E+03 3.069E+02 6.632E+03 1683 .3941E+01 XE-133 9.15E+07 9.150E+05 2.288E+05 3.892E+04 1.183E+06 1683 .7027E+03 XE-133M 2.86E+06 2.860E+04 7.150E+03 5.464E+02 3.630E+04 1683 .2157E+02 XE-135 2.07E+07 2.070E+05 5.175E+04 1.234E+03 2.600E+05 1683 .1545E+03 XE-135M 1.95E+07 1.950E+05 4.875E+04 7.515E+01 2.438E+05 1683 .1449E+03 XE-138 7.72E+07 7.720E+05 1.930E+05 9.117E+01 9.65 1E+05 1683 .5734E+03 A, F From Reference 9.4, Table 2-1, based on 1683 MWt per Reference 9.9, Table 6-1 B = (A x 0.10 x 0.10) = 0.01A for iodine (10% iodine release from 10% clad damage]

= (A x 0.10 x 0.10) = 0.01A for noble gas [10% noble gas release from 10% clad damage]

C = (A x 0.50 x 0.0025) = 0.00125A for iodine [50% iodine release from 0.25% melted fuel]

= (A x 1.00 x 0.0025) = 0.0025A for noble gas [100% noble gas release from 0.25% melted fuel]

D - Iodine From Table 4 & Noble Gas From Table 6

XceCEnergy] calculation No. GEN-PI-082 Revision No. 0 Page No. 50 of 145 Table 10 Steam Mass Releases From Intact SG & AFW Turbine Post-REA Auxiliary Feedwater Turbine Intact Fraction of Steam Mass Time Steam Steam Total SG Release Release Interval Mass Mass Steam Mass Mass From From Release Release Release Release AFW Intact (hr) (Ibm) (Ibm/hr) (Ibm) (Ibm) Turbine SG T A B C D=A-C E=C/A F=D/A 2 226,414 12,000 24,000 202,414 0.106. 0.894 8 406,952 11,000 66,000 340,952 0.162 0.838 24 796,899 9,500 152,000 644,899 0.191 0.809 45,5 863,053 9,000 193,500 669,553 0.224 0.776 A & B From Reference 9.3.1, Item # 20 Table 11 Post-REA Intact SG Release P-T-S Intact SG Release Release Leakage To Iodine, Noble gas, & SG Liquid Iodine Release Intact SG Category (cfm) (cfm) (cfm) (cfm) (cfm)

A B C D E Iodine 0.0376 0.3942 0.2361 0.1734 0.1398 Release 0-45.5 hr 0-2 hr 2-8 hr 8-24 hr 24-45.5 hr Noble Gas 0.0376 0.0376 Release 0-45.5 hr 0-45.5 hr SG Liquid N/A 0.3942 0.2361 0.1734 0.1398 Iodine Release 0-2 hr 2-8 hr 8-24 hr 24-45.5 hr Release Safety & PORV Groups 1 & 2 Release Points and TDAFW 'n3 Point A For Iodine Release From Section 7.2.1 A For Noble Gas Release From Section 7.2.1 B Through E For Iodine & Noble Gas Releases From 7.2.2 B Through E For SG Liquid Iodine Release From .7.3.3

Xcel Energy] Calculation No. GEN-PI-082 Revision No. 0 Page No.51 of 145 Table 12 Average Unit 1 Atmospheric Dispersion Factor (x/Q) for Intact Steam Release via PORV and TDAFW Unit 1 Steam Release Location Fraction of Steam Mass Steam ADV/AFW Group 1 Group 2 Average Release Release Mass Release Time Exhaust PORV PORV PORV From From Averaged Interval I/Qs X/Qs X/Qs X/Qs AFW Intact X/Qs 3 3 3 3 (hr) (s/m ) (s/m ) (s/m ) (s/m ) Turbine SG PORV (s/IM)

A B C D = 0.6B + O.4C E F G=AxE+D*F 0-2 4.66E-02 1.87E-02 1.89E-03 1.20E-02 0.106 0.894 1.56E-02 2-8 3.62E-02 1.31E-02 1.35E-03 8.40E-03 0.162 0.838 1.29E-02 8'24 1.55E-02 5.51E-03 5.33E-04 3.52E-03 0.191 0.809 5.81E-03 24-96 1.12E-02 3.52E-03 3.54E-04 2.25E-03 0.224 0.776 4.26E-03 96- 720 9.95E-03 2.76E-03 2.75E-04 1,77E-03 0.224 0.776 3.60E-03 A from Reference 9.5, Table 6, Case 12a B from Reference 9.5, Table 7, Case 13a C from Reference 9.5, Table 8, Case 14a D from Reference 9.3.1 E & F from Table 10; 96 to 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> data set to 24 - 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> data with no impact since release stops at 45.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Table 13 Average Unit 2 Atmospheric Dispersion Factor (x/Q) for Intact Steam Release via PORV and TDAFW Unit 2 Steam Release Location Fraction of Steam Mass Steam ADV/AFW Group I Group 2 Average Release Release Mass Release Time Exhaust PORV PORV PORV From From Averaged Interval X/Qs X/Qs X/Qs X/Qs AFW Intact X/Qs 3 3 (hr) (s/m ) 3 (s/m ) 3 (s/m ) (s/I ) Turbine SG PORV (s/m 3 )

A B C D = 0.6B + 0.4C E F G=AxE+D*F 0-2 9.89E-03 3.06E-02 2.47E-03 1.93E-02 0.106 0.894 1.83E-02 2-8 7.51E-03 2.46E-02 1.97E-03 1.55E-02 0.162 0.838 1.42E-02 8-24 3.29E-03 1.1 IE-02 8.76E-04 7.01E-03 0.191 0.809 6.30E-03 24 - 96 2.23E-03 7.76E-03 5.62E-04 4.88E-03 0.224 0.776 4.29E-03 96 - 720 1.73E-03 6.14E-03 4.32E-04 3.86E-03 0.224 0.776 3.38E-03_

A from Reference 9.5, Table 6, Case 22b B from Reference 9.5, Table 7, Case 23b C from Reference 9.5, Table 8, Case 24b D from Reference 9.3.1 E & F from Table 10; 96 to 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> data set to 24 - 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> data with no impact since release stops at 45.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />

(.,XceIEnergy]Calculation No. GEN-PI-082 Revision No. 0 Page No. 52 of 145 Table 14 Alkali Inhaled Isotopic Dose Conversion Factors Isotopic Conversion Iodine Fractional Dose Factor Dose Iodine Isotope Conversion Conversion Dose Factor Factor Conversion Factor (Sv/Bq) (rem/Ci/Sv/Bq) (rem/Ci)

A B C=AxB D-=C/1.08E+06 1-131 2.92E-07 3.70E+12 1.08E+06 1.OOE+00 Rb-86 1.33E-09 3.70E+12 4.92E+03 4.56E-03 Rb-88 1.37E-12 3.70E+12 5.07E+00 4.69E-06 Rb-89 1.61E-12 3.70E+12 5.96E+00 5,52E-06 Cs- 134 1.11E-08 3.70E+ 12 4.11E+04 3.80E-02 Cs-136 1.73E-09 3.70E+12 6.40E+03 5,93E-03 Cs-137 7.93E-09 3.70E+ 12 2.93E+04 2,72E-02 Cs-138 3.57E-12 3.70E+ 12 1.32E+01 1.22E-05 A From Reference 9.7, Table 2.1

W Xcel ergy]Calculation No. GEN-PI-082 Revision No. 0 Page No. 53 of 145 11.0 FIGURES:

0.15 V%/day < 12 min 0.066 V%/day = 12 - 20 min 0.006 V%/day = 20 min - 24 hr t EZ~ 0.003 V%/day > 24 hrs ABSVS Filter qp = 9 9 % L5

,lE= 80%

'qo = 80%

Figure 1: Post-REA Containment Leakage AST RADTRAD Nodalization

Or Calculation No. GEN-PI-082 Revision No. 0 Page No. 54 of 145 Iodine Releases 0.0376 cfm 0 - 45.5 hrs Reactor Coolant System V=5,290 ft3 Figure 2: RADTRAD Nodalization For Post-REA Iodine & Noble Gas Releases

-P-T-S Leakage and Intact SG Secondary Liquid Iodine Release

• .- P-T-S Leakage Noble Gas Release

L6 XcelInergy] Calculation No. GEN-PI-082 Revision No. 0 Page No.55 of 145 2,000 cfm < 5 ain 200 or 300 cfm > 5 min CR Unfiltered Inleakage CONTROL ROOM 2,000 cfm < 5 min 3 200 or 300 cfm > 5 min V = 61,315 ft HEPA Tj = 99%

Charcoal Ti = 95%

A Recirc Charcoal Filter Figure 3 - PINGP Control Room Response AST RADTRAD Nodalization

x Ergy,

~el Calculation No. GEN-PI-082 Revision No. 0 Page No. 56 of 145 12.0 AFFECTED DOCUMENTS:

Upon approval of the AST Licensing Change Request, the following document will be revised or superseded:

12.1 PINGP USAR Section 14.5.6, Rev 29P, Rupture of a Control Rod Drive Mechanism Housing (RCCA Ejection) 13.0 ATTACHMENTS: 3.1 PIREACLOO.oO Containment Leakage 3.2 PREAINIDOO.oO P-T-S Iodine Release ISG 3.3 PREAINGOO.oO P-T-S NG Release ISG 3.4 PREAINLQOO.oO Liquid Iodine Release ISG

I t XceI Energy]Calculation No. GEN-PI-082 Revision No. 0 Page No.57 of 145 Attachment 13.1 RADTRAD Output File PIREACL00.o0

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

RADTRAD Version 3.03 (Spring 2001) run on 6/23/2009 at 8:57:05

1. 1. • 1. • • 1. 1. F##in#################f###############o###m####################

1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 0######################

File information

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

Plant file = G:\Radtrad 3.03\Input\PI\GEN-PI-082\PIREACLOO.psf Inventory file = g:\radtrad 3.03\defaults\pireacnt def.txt Release file = g:\radtrad 3.03\defaults\pirearft.txt  !,

Dose Conversion file = g:\radtrad 3.03\defaults\pingp fgll&12.txt it###

1. # i it iti i t# it ititit#

it t i i t# it it it it it it it it itt#ii # it i it it

1. 1. 1. it# it # it# ##t it# #it # t i#iii it it

1. tti it it it it it Radtrad 3.03 4/15/2001 Prairie Island Rod Ejection Accident AST Analysis - No SB Vent & Recirc Charcoal Filtration Credit, Containment Leakage = 0 .15 w%/day, SB Vent Stack Release, CRSVS Charcoal Fitration Starts @ 5 minutes, and CR Unfiltered Inleakage = 250 cfm Nuclide Inventory File:.

g:\radtrad 3.03\defaults\pireacntdef.txt Plant Power Level:

1.8520E+03 Compartments:

5 Compartment 1:

Containment (Cl) 3 1.3200E+06 0

0 0

0 0

Compartment 2:

Shield Bldg (C2) 3 3.7400E+05 0

0 1

0 0

Compartment 3:

Environment (C3) 2

XceI nergy]Calculation No. GEN-PI-082 Revision No. 0 Page No.58 of 145 o.OOOOE+00 0

0 0

0 0

Compartment 4:

Control Room (C4) 1 6.1315E+04 0

0 1

0 0

Compartment 5:

ABSVZ (C5) 3 1.0000E+00 0

0 0

0 0

Pathways:

8 Pathway 1:

L3 - Containment Leakage To Environment 1

3 4

Pathway 2:

Li - Containment Leakage To Shield Bldg 1

2 4

Pathway 3:

L2 - Containment Leakage To ABSVZ 1

5 4

Pathway 4:

L4 - Shield Bldg Exhaust To Environment 2

3 2

Pathway 5:

L6 - Environment To Control Room 3

4 2

Pathway 6:

L7 - Control Room Exhaust To Environment 4

3 2

Pathway 7:

L5 - ABSVZ Exhaust To Environment 5

3

XceIfnergy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 59 of 145 2

Pathway 8:

Containment to Environment for SB Release 12 min - 22 min 1

3 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1 1.OOOOE+00 g:\radtrad 3.03\defaults\pingpfgll&12.txt g:\radtrad 3.03\defaults\pirea rft.txt o.OOO0E+00 1

9.5000E-01 4.8500E-02 1.5000E-03 1.OOOOE+00 Overlying Pool:

o 0.OOOOE+00 0

0 0

0 Compartments:

5 Compartment 1:

0 1

0 0

0 0

0*

0 0

Compartment 2:

00 1

0

.0 0

3.6000E+03 3

0.OOOOE+00 0.0000E+00 0.0000E+00 0.OOOOE+00

3. 6670E-01 9. 9000E+01 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.OOOOE+00 0.0000E+00 0

0 Compartment 3:

0 1

0 0

0 0

Xce Energy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 60 of 145 0

0 0

Compartment 4:

1 1

0 0

0 1

3.6000E+03 3

o.0000E+00 o.OOOOE+00 0.OOOOE+00 0.OOOOE+00 8.3300E-02 9. 9000E+01 9. 5000E+01 9. 5000E+01 7.2000E+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0

0 Compartment 5:

0 1

0 0

0 0

0 0

0 Pathways:

8 Pathway 1:

0 0

0 0

0 0

0 0

0 1

5

0. OOOOE+00 1 . 5000E-01

2. OOOOE-01 6.6000E-02

3. 3300E-01 6.OOOOE-03

2. 4000E+01 3.OOOOE-03

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

Pathway 2:

0 0

0 0

0 0

0 0

0 0

Xce Energy] Calculation No. GEN-PI-082 Revision No. 0 Page No.61 of 145 1

4 o.OOOOE+00 0.0000E+00

3. 6700E-01 8.4000E-02

2. 4000E+01 4.2000E-02 7.2000E+02 0.OOOOE+00 0

Pathway 3:

0 0

0 0

0 0

0 0

0 0

4 0.OO0OE+00 0.OOOOE+00 3.3300E-01 6.OOOOE-02 2.4000E+01 3.OOOOE-02 7.2000E+02 0.OOOOE+00 0

Pathway 4:

0 0

0 0

0 1

3 o.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 3.6700E-01 2.OOOOE+03 9. 9000E+01 0.OOOOE+00 0.OOOOE+00 7.2000E+02 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0

0 0

0 0

0 Pathway 5:

0 0

0 0

0 1

3 o.OOOOE+00 2.OOOOE+03 0.0000E+00 0.00OOE+00 0.OOOOE+00 8.3300E-02 2.5000E+02 0.OOOOE+00 0.0000E+00 0.OOOOE+00 7.2000E+02 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0

0 0

0 0

0 Pathway 6:

XceIEnergyý Calculation No. GEN-Pl-082 Revision No. Page No. 62 of 145 0

0 0

0 0

1 3

o0.0000E+00 2.OOOOE+03 0.OOOOE+00 0.OOOOE+00 o.0000E+00 8.3300E-02 2.5000E+02 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 7.2000E+02 0.0000E+00 0.0000E+00 0.OOOOE+00 o.OOOOE+00 0

0 0

0 0

0 Pathway 7:

0 0

0 0

1 3

0.0000E+00 o.OOOOE+00 o.0000E+00 0.0000E+00 0.OOOOE+00 3.3300E-01 1.OOOOE+03 9. 9000E+01 8. 0000E+01 8. OOOOE+01 7.2000E+02 o.OOOOE+00 0.OOOOE+00 o.OOOOE+00 0.0000E+00 0

0 0

0 0

0 Pathway 8:

0 0

0 0

0 1

3 o . 000E+00 0.0000E+00 o.OOOOE+00 0.0000E+00 0.0000E+00

2. OCOCE-Ol 7. 7000E-01 o.0000E+00 0.OOOOE+00 o.OOOOE+00 3.6700E-01 o.OOOOE+00 0.0000E+00 0.OOOOE+00 0.0000E+00 0

0 0

0 0

0 Dose Locations:

3 Location 1:

Exclusion Area Boundary 3

1 2

0.OOOOE+00 6.4900E-04 7.2000E+02 0.OOOOE+00 1

XcefI nergy Calculation No. GEN-PI-082 Revision No. 0 Page No. 63 of 145 2

0. OOOOE+00 3.5000E-04

7. 2000E+02 0.0000E+00 0

Location 2:

Low Population Zone 3

1 5

o.OOOOE+00 1.7700E-04 8.OOOOE+00 3.9900E-05 2.4000E+01 7.1200E-06

9. 6000E+01 1.0400E-06 7.2000E+02 0.0000E+00 1

4 0.OOOOE+00 3.5000E-04 8.0000E+00 1.8000E-04

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

Location 3:

Control Room 4

0 1

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

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

1 6

0.OOOOE+00 4.5300E-03 2.0000E+00 3.9300E-03 8.0000E+00 1.7300E-03 2.4000E+01 1.2200E-03 9.6000E+01 9.1600E-04 7.2000E+02 0.0000E+00 Simulation Parameters:

6 0.OOOOE+00 1.0000E-01 2.0000E+00 5.0000E-01 8.OOOOE+00 1.0000E+00 2.4000E+01 2.0000E+00 9.6000E+01 5.0000E+00 7.2000E+02 O.OOOOE+00 Output Filename:

G:\Radtrad 3.o22 1

1 1

0 0

End of Scenario File

XceIEnergy Calculation No. GEN-PI-082 Revision No. 0 Page No.64 of 145

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

RADTRAD Version 3.03 (Spring 2001) run on 6/23/2009 at 8:57:05

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

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

Plant Description

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

Number of Nuclides 60 Inventory Power = 1.OOOOE+00 MWth Plant Power Level = 1.8520E+03 MWth Number of compartments = 5 Compartment information Compartment number 1 (Source term fraction = 1.OOOOE+00 Name: Containment (Cl)

Compartment volume = 1.3200E+06 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 1 Exit Pathway Number 1: L3 - Containment Leakage To Environment Exit Pathway Number 2: Ll - Containment Leakage To Shield Bldg Exit Pathway Number 3: L2 - Containment Leakage To ABSVZ Exit Pathway Number 8: Containment to Environment for SB Release 12 m Compartment number 2 Name: Shield Bldg (C2)

Compartment volume = 3.7400E+05 Cubic feet)

Compartment type is Normal Removal devices within compartment:

Filter(s)

Pathways into and out of compartmen t 2 Inlet Pathway Number 2: Ll - Containment Leakage To Shield Bldg Exit Pathway Number 4: L4 - Shield Bldg Exhaust To Environment Compartment number 3 Name: Environment (C3)

Compartment type is Environment Pathways into and out of compartment 3 Inlet Pathway Number 1: L3 - Containment Leakage To Environment Inlet Pathway Number 4: L4 - Shield Bldg Exhaust To Environment Inlet Pathway Number 6: L7 - Control Room Exhaust To Environment Inlet Pathway Number 7: L5 - ABSVZ Exhaust To Environment, Inlet Pathway Number 8: Containment to Environment for SB Release 12 m Exit Pathway Number 5: L6 - Environment To Control Room Compartment number 4 Name: Control Room (C4)

Compartment volume = 6.1315E+04 (Cubic feet)

Compartment type is Control Room Removal devices within compartment:

Filter(s)

Pathways into and out of compartment 4 Inlet Pathway Number 5: L6 - Environment To Control Room Exit Pathway Number 6: L7 - Control Room Exhaust To Environment

XceI nergy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 65 of 145 Compartment number 5 Name: ABSVZ (C5)

Compartment volume = 1.OOOOE+00 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 5 Inlet Pathway Number 3: L2 - Containment Leakage To ABSVZ Exit Pathway Number 7: L5 - ABSVZ Exhaust To Environment Total number of pathways = 8

Xcel Energy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 66 of 145

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

RADTRAD Version 3.03 (Spring 2001) run on 6/2.3/2009 at 8:57:05

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

Scenario Description

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

Radioactive Decay is enabled Calculation of Daughters is enabled Release Fractions and Timings GAP EARLY IN-VESSEL LATE RELEASE RELEASE MASS 0.003600 hr 0.0000 hrs 0.0000 hrs (gm)

NOBLES 1.OOOOE+00 0.OOOOE+00 0.0000E+00 3.696E+01 IODINE 1.OOOOE+00 0.OOOOE+00 0.OOOOE+00 5.599E+00 CESIUM 0 OOOOE+00 0.OOOOE+00 0.0000E+00 0.000E+00 TELLURIUM 0 OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.000E+00 STRONTIUM 0 OOOOE+00 0.0000E+00 0.0000E+00 0.000E+00 BARIUM 0.0000E+00 0.0000E+00 0.OOOOE+00 0.000E+00 RUTHENIUM 0 OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 CERIUM 0 OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.000E+00 LANTHANUM 0. 000OE+00 0.OOOOE+00 0.0000E+00 0.000E+00 Inventory Power = 1852. MWt Nuclide Group Specific half Whole Body Inhaled Inhaled Name Inventory life DCF Thyroid Effective (Ci/MWt) (s) (Sv-m3/Bq-s) (Sv/Bq) (Sv/Bq)

Kr-83m 1 3.487E-02 6. 588E+03 1.500E-18 0. 000E+00 0.OOOE+00 Kr-85 1 6.280E+00 3. 383E+08 1.190E-16 0.000E+00 0.OOOE+00 Kr-85m 1 8.036E+01 1.613E+04 7.480E-15 0.000E+00 0.OOOE+00 Kr-87 1 1.575E+02 4. 578E+03 4.120E-14 0.000E+00 0.OOOE+00 Kr-88 1 2.097E+02 1. 022E+04 1.020E-13 0. OOOE+00 0.000E+00 1-131 2 2.843E+02 6. 947E+05 1.820E-14 2.920E-07 8.8905-09 1-132 2 4.112E+02 8. 280E+03 1.120E-13 1. 740E-09 1.030E-10 1-133 2 5.767E+02 7.488E+04 2.940E-14 4.860E-08 1 .580E-09 1-134 2 6.440E+02 3. 156E+03 1.300E-13 2.880E-10 3.550E-11 1-135 ,2 5.507E+02 2 .380E+04 8. 294E-14 8.460E-09 3.320E-10 Xe-131m 1 3.941E+00 1. 028E+06 3.890E-16 0. 000E+00 0.000E+00 Xe-133 1 7.027E+02 4. 532E+05 1.560E-15 0. OOOE+00 0. 000E+00 Xe-133m 1 2.157E+01 1.890E+05 1.370E-15 0.000E+00 0 OOOE+00 Xe-135 1 1.545E+02 3.272E+04 1.190E-14 0.OOOE+00 0.000E+00 Xe-135m 1 1.499E+02 9. 174E+02 2.040E-14 0. 000E+00 0 OOOE+00 Xe-138 1 5.734E+02 8. 502E+02 5.770E-14 0. OOOE+00 0.000E+00 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-135 Cs-135 1.00 none 0.00 none 0.00 Xe-135m Xe-135 1.00 none 0.00 none 0.00 Xe-138 Cs-138 1 .00 none 0.00 none 0.00 Iodine fractions

XceI Energ] Calculation No. GEN-PI-082 Revision No. 0 Page No. 67 of 145 Aerosol 9.5000E-01 Elemental = 4.8500E-02 Organic = 1.5000E-03 COMPARTMENT DATA Compartment number 1: Containment (Cl)

Compartment number 2: Shield Bldg (C2)

Compartment Filter Data Time (hr) Flow Rate Filter Efficiencies (cfm) Aerosol Elemental Organic 0.0000E+00 3.6000E+03 o.OOOOE+00 0.0000E+00 0.0000E+00

3. 6670E-01 3.6000E+03 9. 9000E+01 0.0000E+00 0.0000E+00 7.2000E+02 3.6000E+03 0.OOOOE+00 0.OOOOE+00 0.0000E+00 Compartment number 3: Environment (C3)

Compartment number 4: Control Room (C4)

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

(c fm) Aerosol Elemental Organic 0.0000E+00 3.6000E+03 0.OOOOE+00 0.OOOOE+00 0.0000E+00 8.3300E-02 3.6000E+03 9.9000E+01 9.5000E+01 9. 5000E+01 7.2000E+02 3.6000E+03 0.0000E+00 0.0000E+00 0.OOOOE+00 Compartment number 5: ABSVZ (C5)

PATHWAY DATA Pathway number 1: L3 - Containment Leakage To Environment Convection Data Time (hr) Flow Rate (% / day) 0.OOOOE+00 1.5000E-01 2.OOOOE-01 6.6000E-02 3.3300E-01 6.OOOOE-03 2.4000E+01 3.OOOOE-03 7.2000E+02 0.OOOOE+00 Pathway number 2: Ll - Containment Leakage To Shield Bldg Convection Data Time (hr) Flow Rate (% / day) 0.00OOE+00 0.OOOOE+00 3.6700E-01 8.4000E-02

'2.4000E+01 4.2000E-02 7.2000E+02 0.0000E+00 Pathway number 3: L2 - Containment Leakage To ABSVZ Convection Data Time (hr) Flow Rate (% / day) 0.OOOOE+00 0.0000E+00 3.3300E-01 6.OOOOE-02 2.4000E+01 3.0000E-02

XceI nergy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 68 of 145 7.2000E+02 0.OOOOE+00 Pathway number 4: L4 - Shield Bldg Exhaust To Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.000OE+00 o.0000E+00 O.OOOOE+00 O.OOOOE+00 0.0000E+00 3.6700E-01 2.OOOOE+03 9.9000E+01 O.OOOOE+00 0.0000E+00 7.2000E+02 o.OOOOE+00 0.OOOOE+00 0.0000E+00 0.0000E+00 Pathway number 5: L6 - Environment To Control Room Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.OOOOE+00 2.0000E+03 0.0000E+00 0.0000E+00 0.0000E+00 8.3300E-02 2.5000E+02 0.0000E+00 0.OOOOE+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.OOOOE+00 0.0000E+00 Pathway number 6: L7 - Control Room Exhaust To Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(c fm) Aerosol Elemental Organic 0.OOOOE+00 2.0000E+03 0.0000E+00 0.OOOOE+00 0.OOOOE+00 8.3300E-02 2.5000E+02 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.OOOOE+0o 0.0000E+00 0.OOOOE+00 0.OOOOE+00 Pathway number 7: L5 - ABSVZ Exhaust To Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.OOOOE+00 .00000E+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00

3. 3300E-01 1.OOOOE+03 9.9000E+01 8.0000E+01 8.OOOOE+01 7.2000E+02 O.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 8: Containment to Environment for SB Release 12 m Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

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

2. OOOE-01 7.7000E-01 0.0000E+00 0.0000E+00 0.0000E+00 3.6700E-01 o.0000E+00 0.OOOOE+00 0.0000E+00 0.0000E+00 LOCATION DATA Location Exclusion Area Boundary is in compartment 3 Location X/Q Data Time (hr) X/Q (s

• m'-3)

O.0OOOE+00 6.4900E-04 7.2000E+02 0.OOOOE+00

ecoXceI Energy] Calculation No. GEN-PI-082 Rev .isi~on No. 0 Page No. 69 of 145 Location Breathing Rate Data Time (hr) Breathing Rate (mW3

• sec^-l)

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

• m^-3) 0.0000E+00 1.7700E-04 8.0000E+00 3.9900E-05 2.4000E+01 7. 1200E-06 9.6000E+01 1.0400E-06 7.2000E+02 0.0000E+00 Location Breathing Rate Da ta Time (hr) Breathi ng 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 O. 0000E+00 Location Control R.oom is in compartment 4 Location X/Q Data Time (hr) X/Q (s

• m^-3) 0.0000E+00 4.5300E-03 2.0000E+00 3.9300E-03 8.0000E+00 1.7300E-03 2.4000E+01 1.2200E-03 9.6000E+01 9.1600E-04 7.2000E+02 0.OOOOE+00 Location Breathing Rate Data Time (hr) Breathing Rate (m^3

• sec^-l)

O.OOOOE+00 3.5000E-04 7.2000E+02 O.O000E+00 Location Occupancy Factor Data Time (hr) Occupancy Factor 0.O000E+00 1.0000E+00 2.4000E+01 6.OOOOE-01 9.6000E+01 4.0000E-01 7.2000E+02 0.OOOOE+00 USER SPECIFIED TIME STEP DATA - SUPPLEMENTAL TIME STEPS Time Time step o.0000E+00 1.OOOOE-01 2.0000E+00 5.0000E-01 8.0000E+00 1.0000E+00 2.4000E+01 2.0000E+00 9.6000E+01 5.0000E+00 7.2000E+02 O.O000E+00

XcelEnergy]Calculation Al No. GEN-PI-082 Revision No. 0 Page No. 70 of 145 4#444444#44##4 #*444444### 444######4########44######4###4######4#4####

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1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 4#4#####44#4######################4##############44 Dose, Detailed model and Detailed Inventory Output

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Exclusion Area Boundary Doses:

Time (h) = 0.0036 Whole Body Thyroid TEDE Delta dose (rem) 1.3258E-04 2. 0418E-02 7.7814E-04 Accumulated dose (rem) 1.3258E-04 2.0418E-02 7.7814E-04 Low Population Zone Doses:

Time (h) = 0.0036 Whole Body Thyroid TEDE Delta dose (rem) 3.6160E-05 5.5685E-03 2.1222E-04 Accumulated dose (rem) 3.6160E-05 5.5685E-03 2..1222E-04 Control Room Doses:

Time (h) = 0.0036 Whole Body Thyroid TEDE Delta dose (rem) 8.9715E-08 3.9039E-04 1.2433E-05 Accumulated dose (rem) 8.9715E-08 3.9039E-04 1.2433E-05 Control Room (C4) Compartment Nuclide Inventory:

Time (h) =, 0.0036 Ci kg Atoms Decay Kr-83m 3.0950E-08 1 . 5001E-18 1.0884E+07 1.0539E+04 Kr-85 5. 5816E-06 1.4227E-11 1.0079E+14 1.8997E+06 Kr-85m 7. 1383E-05 8.6740E-15 6. 1454E+10 2.4300E+07 Kr-87 1. 3971E-04 4. 9322E-15 3. 414 1E+10 4.7583E+07 Kr-88 1.8621E-04 1.4851E-14 1. 0163E+I1 6.3397E+07 Rb-88 1.2770E-06 1.0638E-17 7 .2801E+07 6. 5716E+04 1-131 2.5268E-04 2.0381E-12 9. 3694E+12 8.5998E+07 1-132 3.6507E-04 3. 5368E-14 1 . 6136E+l1 1.2430E+08 1-133 5.1250E-04 4.5241E-13 2. 0485E+12 1.7444E+08 1-134 5.7075E-04 2.1395E-14 9. 6152E+10 1.9445E+08 1-135 4.8927E-04 1.3932E-13 6. 2148E+l1 1.6654E+08 Xe-131m 3.5027E-06 4.1818E-14 1. 9224E+11 1. 1921E+06 Xe-133 6.2455E-04 3. 3366E-12 1. 5108E+13 2.1256E+08 Xe-133m 1. 9171E-05 4.2725E-14 1. 9345E+11 6.5247E+06 Xe-135 1.3743E-04 5. 3815E-14 2.4006E+II 4.6743E+0.7 Xe-135m 1.3265E-04 1.4562E-15 6.4958E+09 4. 5134E+07 Xe-138 5.0427E-04 5.2443E-15 2.2886E+10 1.7228E+08 Cs-138 1.9202E-06 4.5380E-17 1.9803E+08 9. 9312E+04 Control Room (C4) Transport Group Inventory:

XcelEnergy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 71 of 145 Time (h) = 0.0036 Atmosphere Sump Noble gases (atoms) 1.1675E+14 0.0OOOE+00 Elemental I (atoms) 5.9640E+ll 0.OOOOE+00 Organic I (atoms) 1.8445E+10 0.OOOOE+00 Aerosols (kg) 2.5524E-12 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 2. 0440E-13 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 2. 6107E-13 Total I (Ci) 2. 1903E-03 Deposition Recirculating Time (h) = 0.0036 Surfaces Filter Noble gases (atoms) 0.0000E+00 0.0000E+00 Elemental I (atoms) 0.OOOOE+00 0.OOOOE+00 Organic I (atoms) 0.OOOOE+00 0.000E+00 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 L6 - Environment To Control Room Transport Group Inventory:

Pathway Time (h) = 0.0036 Filtered Transported Noble gases (atoms) 0.OOOOE+00 1.1703E+14 Elemental I (atoms) 0.OOOOE+00 5.9784E+lI Organic I (atoms) 0.OOOOE+00 1.8490E+10 Aerosols (kg) 0.OOOOE+00 2.5585E-12 L7 - Control Room Exhaust To Environment Transport Group Inventory:

Pathway Time (h) = 0.0036 Filtered Transported Noble gases (atoms) 2.7432E+ll 0.OOOOE+00 Elemental I (atoms) 1.4014E+09 0.0000E+00 Organic I (atoms) 4.3342E+07 0.OOOOE+00 Aerosols (kg) 5.9973E-15 0.OOOOE+00 Exclusion Area Boundary Doses:

Time (h) = 0.0833 Whole Body Thyroid TEDE Delta dose (rem) 5.8651E-03 9. 0401E-01 3.4447E-02 Accumulated dose (rem) 5.9977E-03 9. 2443E-01 3.5226E-02 Low Population Zone Doses:

Time (h) = 0.0833 Whole Body Thyroid TEDE Delta dose (rem) 1.5996E-03 2.4655E-01 9.3948E-03 Accumulated dose (rem) 1.6357E-03 2. 5212E-01 9.6070E-03 Control Room Doses:

Time (h) = 0.0833 Whole Body Thyroid TEDE Delta dose (rem) 1.0935E-04 4. 7623E-01 1. 5167E-02 Accumulated dose (rem) 1.0944E-04 4.7663E-01 1. 5179E-02 Control Room (C4) Compartment Nuclide Inventory:

Time (h) = 0.0833 Ci kg Atoms Decay Kr-83m 1.2597E-06 6.1056E-17 4.4299E+08 1.3587E+07 Kr-85 2.3414E-04 5. 9679E-10 4.2282E+15 2.4876E+09 Kr-85m 2.9577E-03 3. 5941E-13 2 .5463E+12 3. 1618E+10 Kr-87 5. 6115E-03 1. 9811E-13 1. 3713E+12 6. 0933E+I0 Kr-88 7. 6610E-03 6. 1097E-13 4. 1810E+12 8.2189E+10

Xcel Energy Calculation No. GEN-PJ-082 Revision No. 0 Page No. 72 of 145 Rb-88 1.4822E-03 1 .2348E-14 8.4501E+10 4.8610E+08 1-131 1.0597E-02 8.5474E-11 3. 9293E+14 1. 1260E+11 1-132 1.4951E-02 1.4484E-12 6. 6081E+12 1. 6077E+11 1-133 2.1442E-02 1.8928E-11 8. 5705E+13 2 .2810E+11 1-134 2.2480E-02 8.4269E-13 3. 7872E+12 2.4653E+11 1-135 2.0354E-02 5.7957E-12 2. 5854E+13 2.1715E+II Xe-131m 1.4693E-04 1.7541E-12 8. 0639E+12 1.5609E+09 Xe-133 2. 6197E-02 1. 3996E-10 6.3371E+14 2. 7828E+11 Xe-133m 8.0401E-04 1.7918E-12 8.1133E+12 8.5395E+09 Xe-135 5.8661E-03 2. 2971E-12 1. 0247E+13 6. 1063E+10 Xe-135m 5.1446E-03 5. 6477E-14 2. 5193E+11 5. 3153E+10 Xe-138 1.6742E-02 1.7411E-13 7. 5979E+11 2.0041E+11 Cs-138 2.0097E-03 4 .7493E-14 2. 0725E+II 7.6093E+08 Control Room (C4) Transport Group Inventory:

Time (h) = 0.0833 Atmosphere Sump Noble gases (atoms) 4.8974E+15 0.OOOOE+00 Elemental I (atoms) 2.4972E+13 0.OOOOE+00 Organic I (atoms) 7.7232E+ll Q.OOOOE+00 Aerosols (kg) 1.0692E-10 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 8.5623E-12 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 1.0911E-11 Total I (Ci) 8.9823E-02 Deposition Recirculating Time (h) 0.0833 Surfaces Fi'lter Noble gases (atoms) 0.0000E+00 0.0000E+00 Elemental I (atoms) 0.OOOOE+00 0.OOOOE+00 Organic I (atoms) 0.0000E+00 0.0000E+00 Aerosols (kg) 0.0000E+00 0.OOOOE+00 L6 - Environment To Control Room Transport Group, Inventory:

Pathway Time (h) = 0.0833 Filtered Transported Noble gases (atoms) 0.0000E+00 5.2987E+15 Elemental I (atoms) 0.OOOOE+00 2.7067E+13 Organic I (atoms) 0.0000E+00 8.3713E+1l Aerosols (kg) 0.0000E+00 1.1584E-10 L7 - Control Room Exhaust To Environment Transport Group Inventory:

Pathway Time (h) = 0.0833 Filtered Transported Noble gases (atoms) 4.0130E+14 0.0000E+00 Elemental I (atoms) 2.0499E+12 0.0000E+00 Organic I (atoms) 6.3400E+10 0.0000E+00 Aerosols (kg) 8.7729E-12 0.0000E+00 Exclusion Area Boundary Doses:

Time (h) = 0.2000 Whole Body Thyroid TEDE Delta dose (rem) 8.3254E-03 1. 3215E+00 5.0112E-02 Accumulated dose (rem) 1.4323E-02 2.2459E+00 8.5337E-02 Low Population Zone Doses:

Time (h) = 0.2000 Whole Body Thyroid TEDE Delta dose (rem) 2.2706E-03 3. 6040E-01 1.3667E-02 Accumulated dose (rem) 3.9063E-03 6. 1252E-01 2.3274E-02

Xcel EnergylCalculation No. GEN-PI-082 Revision No. 0 Page No 73 of 145 Control Room Doses:

Time (h) 0.2000 Whole Body Thyroid TEDE Delta dose (rem) 2.8530E-04 1.2233E+00 3.8966E-02 Accumulated dose (rem) 3.9474E-04 1.6999E+00 5. 4145E-02 Control Room (C4) Compartment Nuclide Inventory:

Time (h) = 0.2000 Ci kg Atoms Decay Kr-83m 1.4014E-06 6.7923E-17 4.9282E+08 3. 5471E+07 Kr-85 2.7225E-04 6.9392E-10 4. 9164E+15 6.6470E+09 Kr-85m 3.3776E-03 4 1043E-13 2. 9078E+12 8. 3684E+10 Kr-87 6. 1227E-03 2 1616E-13 1.4962E+12 1.5747E+ll Kr-88 8.6578E-03 6.904.6E-13 4.7250E+12 2. 1634E+ll Rb-88 3. 1541E-03 2 6275E-14 1.7981E+11 2. 0211E+10 1-131 8. 5213E-03 6 8734E-11 3. 1597E+14 2. 4890E+ll 1-132 1. 1612E-02 1.1250E-12 5. 1324E+12 3. 4986E+1l 1-133 1.7183E-02 1.5168E-11 6. 8681E+13 5.0345E+ll 1-134 1. 6491E-02 6.1818E-13 2 .7782E+12 5. 2312E+11 1-135 1 . 6175E-02 4. 6058E-12 2 .0546E+13 4.7745E+ll Xe-131m 1.7082E-04 2. 0394E-12 9. 3752E+12 4. 1708E+09 Xe-133 3.0453E-02 1.6269E-10 7. 3666E+14 7 4355E+ll Xe-133m 9.3424E-04 2 .0821E-12 9.4275E+12. 2 2813E+I0 Xe-135 6.9366E-03 2.7163E-12 1.2117E+13 1.6523E+ll Xe-135m 5. 1352E-03 5.6374E-14 2.5148E+11 1.3306E+ll Xe-138 1.3821E-02 1.4373E-13 6.2724E+lI 4 .5157E+Il Cs-138 3.7253E-03 8. 8039E-14 3. 8419E+ll 2. 8504E+10 Control Room (C4) Transport Group Inventory:

Time (h) = 0.2000 Atmosphere Sump Noble gases (atoms) 5.6940E+15 0.OOOOE+00 Elemental I (atoms) 2.0318E+13 0.OOOOE+00 Organic I (atoms) 6.2839E+ll 0.OOOOE+00 Aerosols (kg) 8.5789E-11 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 6. 874 IE-12 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 8.7314E-12 Total I (Ci) 6.9982E-02 Deposition Recirculating Time (h) = 0.2000 Surfaces Filter Noble gases (atoms) 0.OOOOE+00 0.OOOOE+00 Elemental I (atoms) 0.OOOOE+00 8.7869E+12 Organic I (atoms) 0.OOOOE+00 2.7176E+11 Aerosols (kg) 0.OOOOE+00 3.8920E-11 L6 - Environment To Control Room Transport Group Inventory:

Pathway Time (h) = 0.2000 Filtered Transported Noble gases (atoms) 0.OOOOE+00 6.2471E+15 Elemental I (atoms) 0.OOOOE+00 3.1901E+13 Organic I (atoms) 0. OOOOE+00 9.8663E+11 Aerosols (kg) 0.OOOOE+00 1.3654E-10 L7 - Control Room Exhaust To Environment Transport Group Inventory:

Pathway Time (h) = 0.2000 Filtered Transported Noble gases (atoms) 5.5255E+14 0.OOOOE+00

Xce Energy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 74 of 145 Elemental I (atoms) 2 .6922E+12 O.OOOOE+00 Organic I (atoms) 8. 3265E+10 O.OOOOE+00 Aerosols (kg) 1.1503E-11 O. 000E+00 Exclusion Area Boundary Doses:

Time (h) = 0.3330 Whole Body Thyroid TEDE Delta dose (rem) 9.0685E-03 1.5027E+00 5.6580E-02 Accumulated dose (rem) 2.3392E-02 3.7486E+00 1. 4192E-01 Low Population Zone Doses:

Time (h) = 0.3330 Whole Body Thyroid TEDE Delta dose (rem) 2.4732E-03 4.0982E-01 1. 5431E-02 Accumulated dose (remj 6.3795E-03 1.0223E+00 3.8705E-02 Control Room Doses:

Time (h) = 0.3330 Whole Body Thyroid TEDE Delta dose (rem) 2.7971E-04 1. 1308E+00 3.6047E-02 Accumulated dose (rem) 6.7445E-04 2.8307E+00 9. 0192E-02 Control Room (C4) Compartment Nuclide Inventory:

Time (h) = 0.3330 Ci kg Atoms Decay Kr-83m 1.5387E-06 7.4580E-17 5.4112E+08 6.2734E+07 Kr-85 3. 1438E-04 8. 0130E-10 5.6771E+15 1.2079E+10 Kr-.85m 3.8208E-03 4.6428E-13 3. 2893E+12 1.5038E+ll Kr-87 6.5757E-03 2. 3215E-13 1 . 6069E+12 2.7528E+ll Kr-88 9. 6781E-03 7.7183E-13 5.2819E+12 3. 8628E+11 Rb-88 4.4636E-03 3. 7185E-14 2. 5447E+ll 6. 8121E+10 1-131 7. 0321E-03 5. 6722E-11 2. 6075E+14 3. 7755E+ll 1-132 9. 2108E-03 8. 9233E-13 4.0710E+12 5. 2177E+ll 1-133 1.4124E-02 1.2468E-11 5. 6455E+13 7. 6235E+ll 1-134 1.2257E-02 4. 5945E-13 2. 0648E+12 7. 5959E+ll 1-135 1.3170E-02 3. 7501E-12 1. 6729E+13 7.2002E+ll Xe-131m 1.9722E-04 2. 3545E-12 1.0824E+13 7.5785E+09 Xe-133 3. 5152E-02 1. 8780E-10 8. 5033E+14 1.3510E+12 Xe-133m 1.0777E-03 2.4019E-12 1.0876E+13 4. 1440E+10 Xe-135 8.1144E-03 3.1775E-12 1.4174E+13 3. 0365E+1l Xe-135m 4.9000E-03 5.3791E-14 2. 3996E+ll 2.2215E+ll Xe-138 1.0802E-02 1.1233E-13 4.9021E+ll 6. 7960E+ll Cs-138 4.4826E-03 1 . 0593E-13 4. 6229E+lI 8. 5128E+10 Control Room (C4) Transport Group Inventory:

Time (h) = 0.3330 Atmosphere Sump Noble gases (atoms) 6.5742E+15 0.OOOOE+00 Elemental I (atoms) 1.6922E+13 0.OOOOE+00 Organic I (atoms) 5.2336E+lI 0.OOOOE+00 Aerosols (kg) 7.0624E-11 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 5. 6625E-12 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 7.1673E-12 Total I (Ci) 5.5793E-02 Deposition Recirculating Time (h) = 0.3330 Surfaces Filter Noble gases (atoms) 0. OOOOE+00 0.OOOOE+00 Elemental I (atoms) 0.OOOOE+00 1.7021E+13 Organic I (atoms) 0.OOOOE+00 5.2642E+lI Aerosols (kg) 0.OOOOE+00 7.4924E-11

XceIEnergy]CalculationNo. GEN-PI-082 Revision No. 0 Page No. 75 of 145 L6 - Environment To Control Room Transport Group Inventory:

Pathway Time (h) = 0.3330 .Filtered Transported Noble gases (atoms) 0.OOOOE+00 7.3278E+15 Elemental I (atoms) 0.0000E+00 3.7394E+13 Organic I (atoms) 0.OOOOE+00 1.1565E+12 Aerosols (kg) 0.OOOOE+00 1.6007E-10 L7 - Control Room Exhaust To Environment Transport Group Inventory:

Pathway Time (h) = 0.3330 Filtered Transported Noble gases (atoms) 7.5222E+14 0.OOOOE+00 Elemental I (atoms) 3.2941E+12 0.OOOOE+00 Organic I (atoms) 1.0188E+11 0.OOOOE+00 41

,4 Aerosols (kg) 1.4028E-11 0.OOOOE+00 Exclusion Area Boundary Doses:

Time (h) = 0.3667 Whole Body Thyroid TEDE Delta dose (rem) 1.4993E-03 2.3099E-01 8.8005E-03 Accumulated dose (rem) 2.4891E-02 3.9796E+00 1.5072E-01 Low Population Zone Doses:

Time (h) = 0.3667 Whole Body Thyroid TEDE Delta dose (rem) 4.0891E-04 6.2996E-02 2.4001E-03 Accumulated dose (rem) 6.7884E-03 1.0853E+00 4.1105E-02 Control Room Doses:

Time (h) = 0.3667 Whole Body Thyroid TEDE Delta dose (rem) 6.3809E-05 2. 5070E-01 7.9938E-03 Accumulated dose (rem) 7.3826E-04 3. 0814E+00 9. 8186E-02 Control Room (C4) Compartment Nuclide Inventory:

Time (h) = t 0.3667 Ci kg Atoms Decay Kr-83m 1.5697E-06 7. 6083E-17 5.5202E+08 6.9826E+07 Kr-85 3.2483E-04 8. 2795E-10 5.8659E+15 1.3537E+10 Kr-85m 3.9273E-03 4 .7722E-13 3. 3811E+12 1. 6805E+ll Kr-87 6.6707E-03 2. 3550E-13 1.6301E+12 3. 0550E+II Kr-88 9. 9181E-03 7. 9096E-13 5.4128E+12 4. 3099E+11 Rb-88 4.5524E-03 3. 7925E-14 2. 5953E+11 8. 5719E+10 1-131 6.5399E-03 5.2752E-11 2.4250E+14 4 .0690E+11 1-132 8.4805E-03 8. 2159E-13 3. 7483E+12 5. 6003E+II 1-133 1. 3122E-02 1.1584E-11 5 .2451E+13 8.2128E+lI 1-134 1.11OOE-02 4 . 1610E 7 13 1.8700E+12 8.1009E+1I 1-135 1.2206E-02 3.4757E-12 1.5505E+13 7 .7491E+11 Xe-131m 2.0377E-04 2. 4327E-12 1.1183E+13 8.4932E+09 Xe-133 3. 6318E-02 1. 9402E-10 8.7852E+14 1.514OE+12 Xe-133m 1.1133E-03 2.4811E-12 1. 1234E+13 4. 6438E+10 Xe-135 8.4085E-03 3.2926E-12 1.4688E+13 3. 4126E+11 Xe-135m 4.8191E-03 5. 2904E-14 2. 3600E+l1 2.4402E+11 Xe-138 1.0110E-02 1. 0514E-13 4.5881E+ll 7. 2730E+ll Cs-138 4.3945E-03 1.0385E-13 4. 5320E+I1 1.0317E+II Control Room (C4) Transport Group Inventory:

I.xce'snergy]Calculation No. GEN-PI-082 Revision No. 0 Page No. 76 of 145 Time (h) = 0.3667 Atmosphere Sump Noble gases (atoms) 6.7926E+15 0.0000E+00 Elemental I (atoms) 1.5871E+13 0.0000E+00 Organic I (atoms) 4.9085E+ll 0.0000E+00 Aerosols (kg) 6.5616E-11 C.OOOE+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 5.2637E-12 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 6. 6569E-12 Total I (Ci) 5. 1449E-02 Deposition Recirculating Time (h) = 0.3667 Surfaces Filter Noble gases (atoms) 0.0000E+00 0.0000E+00 Elemental I (atoms) 0.COCE+00 1.8868E+13 Organic I (atoms) 0.0000E+00 5.8353E+11 Aerosols (kg) 0.0000E+00 8.2925E-11 L6 - Environment To Control Room Transport Group Inventory; Pathway Time (h) = 0.3667 Filtered Transported Noble gases (atoms) 0.0000E+00 7.6016E+15 Elemental I (atoms) 0.OO00E+00 3.8338E+13 Organic I (atoms) 0.0000E+00 1.1857E+12 Aerosols (kg) C.0000E+00 1.6366E-10 L7 - Control Room Exhaust To Environment Transport Group Inventory:

Pathway Time (h) = 0.3667 Filtered Transported Noble gases (atoms) 8.0717E+14 0.0000E+00 Elemental I (atoms) 3.4291E+12 C.0000E+00 Organic I (atoms) 1.0606E+11 0.0000E+00 Aerosols (kg) 1.4590E-11 C.OOO0E+00 Exclusion Area Boundary Doses:

Time (h) = 0.3670 Whole Body Thyroid TEDE Delta dose (rem) 1.3140E-05 2. 0551E-03 7.8090E-05 Accumulated dose (rem) 2.4904E-02 3. 9816E+00 1. 5080E-01 Low Population Zone Doses:

Time (h) = 0.3670 Whole Body Thyroid TEDE Delta dose (rem) 3.5836E-06 5.6048E-04 2. 1297E-05 Accumulated dose (rem) 6.7920E-03 1.0859E+00 4.1126E-02 Control Room Doses:

Time (h) = 0.3670 Whole Body Thyroid . TEDE Delta dose (rem) 5.4974E-07 2.1490E-03 6.8528E-05 Accumulated dose (rem) 7.3881E-04 3.0836E+00 9.8254E-02 Control Room (C4) Compartment Nuclide Inventory:

Time (h) 0.3670 Ci kg Atoms Decay Kr-83m 1.5700E-06 7. 6096E-17 5. 5212E+08 6.9889E+07 Kr-85 3.2492E-04 8.2818E-10 5.8676E+15 1. 3550E+10 Kr-85m 3.9283E-03 4 .7734E-13 3. 3819E+12 1. 6821E+11 Kr-87 6. 6715E-03 2 . 3553E-13 1. 6303E+12 3. 0577E+11 Kr-88 9.9202E-03 7.9113E-13 5. 4140E+12 4. 3138E+1I

4 Xce'Energy' Calculation No. GEN-PI-082 Revision No.A0 Page No.77 of 145 Rb-88 4.5525E-03 3.7925E-14 2 .5953E+11 8.5901E+10 1-131 6.5358E-03 5.2719E-11 2.4235E+14 4.0717E+11 1-132 8.4745E-03 8.2100E-13 3.7456E+12 5.6037E+11 1-133 1.3114E-02 1.1576E-11 5. 2417E+13 8.2181E+11 1-134 1.1091E-02 4 .1574E-13 1.8684E+12 8.1053E+81 1-135 1.2198E-02 3.4734E-12 1.5494E+13 7.7540E+11 Xe-131m 2. 0383E-04 2.4334E-12 1.1187E+13 8.5013E+09 Xe-133 3.6328E-02 1.9408E-10 8.7877E+14 1 .5154E+12 Xe-133m 1.Ii36E-03 2.4818E-12 1.1238E+13 4. 6482E+10 Xe-135 8.4111E-03 3.2937E-12 1.4692E+13 3.4160E+11 Xe-135m 4.8184E-03 5.2896E-14 2.3596E+11 2.4421E+11 Xe-138 1.0104E-02 1 . 0508E-13 4.5854E+11 7.2770E+11 Cs-138 4.3933E-03 1 . 0382E-13 4.5307E+11 1 .0334E+11 Control Room (C4) Transport Group Inventory:

Time (h) = 0.3670 Atmosphere Sump A Noble gases (atoms) 6.7946E+15 0.0000E+00 A

3 Elemental I (atoms) 1.5862E+13 0.0000E+00 Organic I (atoms) 4.9057E+11 0.0000E+00 Aerosols (kg) 6.5575E-11 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 5.2604E-12 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 6.6526E-12 Total I (Ci) 5.1413E-02 Deposition Recirculating Time (h) = 0.3670 Surfaces Fi'lter Noble gases (atoms) 0.0000E+00 0.0000E+00 Elemental I (atoms) 0.0000E+00 1.8883E+13 Organic I (atoms) 0.0000E+00 5.8402E+I1 Aerosols (kg) O.O000E+00 8.2994E-11 L6 - Environment To Control Room Transport Group Inventory:

Pathway Time (h) = 0.3670 Filtered Transported Noble gases (atoms) 0.0000E+00 7.6040E+15 Elemental I (atoms) 0.0000E+00 3.8347E+13 Organic I (atoms) 0.0000E+00 1.1860F+12 Aerosols (kg) 0.0000E+00 1.6370E,-10 L7 - Control Room Exhaust To Environment Transport Group Inventory:

Pathway Time (h) - 0.3670 Filtered Transported Noble gases (atoms) 8.0767E+14 0.0000E+00 Elemental I (atoms) 3.4303E+12 0.0000z+00 Organic I (atoms) 1.0609E+11 0.0000E+00 Aerosols (kg) 1.4595E-11 0.0000E+00 Exclusion Area Boundary Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.5795E-02 5.4355E+00 2.0563E-01 Accumulated dose (rem) 6.0699E-02 9.4171E+00 3.5643E-01 Low Population Zone Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 9.7624E-03 1.48248+00 5.6081E-02 Accumulated dose (rem) 1.6554E-02 2.5683E+00 9.7207E-02

V Xce Energy] Calculation No. GEN-PI-082 Rev ision No. 0 Page No. 78 of 145 Control Room Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.7443E-03 4. 0911E+00 1 . 3396E-01 Accumulated dose (rem) 4.4831E-03 7.1747E+00 2. 3221E-01 Control Room (C4) Compartment Nuclide Inventory:

Time (h) 8.0000 Ci kg Atoms Decay Kr-83m 2.8302E-07 I.3717E-17 9.9527E+07 9.7954E+08 Kr-85 1.0551E-03 2.6894E-09 1.9054E+16 7. 5458E+11 Kr-85m 3. 9158E-03 4.7583E-13 3.3712E+12 4. 9051E+12 Kr-87 3.3795E-04 1.1931E-14 8.2585E+10 2. 8604E+12 Kr-88 4.9999E-03 3. 9874E-13 2.7287E+12 9. 1298E+12 Rb-88 2.6728E-03 2 .2266E-14 1.5238E+lI 2. 9096E+12 1-131 3.0292E-04 2.4434E-12 1. 1232E+13 8.7886E+Il 1-132 4.0459E-05 3. 9197E-15 1.7882E+10 9.2579E+11 1-133 4.8439E-04 4 .2760E-13 1. 9361E+12 1.7033E+12 1-134 1.2644E-06 4 .7396E-17 2 .1300E+08 1. 1481E+12 1-135 2.6098E-04 7.4314E-14 3. 3150E+lI 1. 4807E+12 Xe-131m 6.5543E-04 7 .8249E-12 3. 5972E+13 4.7048E+11 Xe-133 1. 1534E-01 6. 1618E-10 2.7900E+15 8.3220E+13 Xe-133m 3. 4132E-03 7.6067E-12 3. 4443E+13 2. 4977E+12 Xe-135 3. 1708E-02 1.2416E-11 5.5387E+13 2.1648E+13 Xe-135m 5.2553E-04 5.76'92E-15 2. 5735E+10 1.3368E+12 Cs-138 1.0288E-08 2.4314E-19 1 . 0610E+06 3. 2309E+1I Control Room (C4) Transport Group Inventory:

Time (h) = 8.0000 Atmosphere Sump Noble gases (atoms) 2.1976E+16 0.0000E+00 Elemental I (atoms) 5.5996E+12 0.OOOOE+00 Organic I (atoms) 1.7318E+11 0.OOOOE+00 Aerosols (kg) 1.712iE-12 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 2.2540E-13 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 2. 6240E-13 Total I (Ci) 1.0900E-03 Deposition Recirculating Time (h),= 8.0000 Surfaces Filter Noble gases (atoms) 0.0000E+00 0.OOOOE+00 Elemental I (atoms) 0.0000E+00 1.4184E+14 Organic I (atoms) 0.0000E+00 4.3868E+12 Aerosols (kg) 0.0000E+00 1.9160E-10 L6 - Environment To Control Room Transport Group Inventory:

Pathway Time (h) = 8.0000 Filtered Transported Noble gases (atoms) 0.0000E+00 5.1103E+16 Elemental I (atoms) 0.OOOOE+00 1.6055E+14 Organic I (atoms) 0.OOOOE+00 4.9653E+12 Aerosols (kg) 0.0000E+00 2.1567E-10 L7 - Control Room Exhaust To Environment Transport Group Inventory:

Pathway Time (h) = 8.0000 Filtered Transported Noble gases (atoms) 2.9007E+16 0.OOOOE+00 Elemental I (atoms) 1.2418E+13 0. 0000E+00

Xce Energy]Calculation No. GEN-PI-082 Revision No. 0 Page No. 79 of 145 Organic I (atoms) 3. 8407E+ll 0.0000E+00 Aerosols (kg) 2.2213E-11 0.OOOOE+00 Exclusion Area Boundary Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.0254E-02 1. 1569E+01 3. 8777E-01 Accumulated dose (rem) 9.0954E-02 2.0986E+01 7.4420E-01 Low Population Zone Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.8600E-03 3. 6578E-01 1.3164E-02 Accumulated dose (rem) 1.8414E-02 2. 934 1E+00 1.1037E-01 Control Room Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.1601E-03 2.1017E+00 6.7740E-02 Accumulated dose (rem) 6.6432E-03 9.2764E+00 2. 9995E-01 Control Room (C4) Compartment Nuclide Inventory:

Time (h) = 24.0000 Ci kg Atoms Decay Kr-83m 3. 8400E-10 1. 8612E-20 1.3504E+05 1. 0613E+09 Kr-85 6.1342E-04 1. 5635E-09 1. 1077E+16 2 2646E+12 Kr-85m 1. 9151E-04 2. 3271E-14 1. 6487E+1I 7 2000E+12 Kr-87 3.204SE-08 1.1314E-18 7. 8316E+06 2. 9313E+12 Kr-88 5.8547E-05 4. 6691E-15 3.1952E+10 1.1216E+13 Rb-88 1.5546E-04 1 .2951E-15 8.8625E+09 3. 4582E+12 1-131 1.3030E-04 1. 0510E-12 4 .8317E+12 1. 1681E+12 1-132 1.4842E-07 1 4379E-17 6.5598E+07 9. 3437E+I1 1-133 1.2949E-04 1. 1431E-13 5. 1757E+11 2. 0734E+12 1-135 2.2209E-05 6.3241E-15 2 .8211E+10 1. 6067E+12 Xe-131m 3.7584E-04 4 .4871E-12 2.0627E+13 1.4018E+12 Xe-133 6. 4121E-02 3 4256E-10 1. 5511E+15 2. 4487E+14 Xe-133m 1.7734E-03 3. 9523E-12 1.7896E+13 7 1339E+12 Xe-135 1. 1919E-02 4 6673E-12 2. 0820E+13 6.0303E+13 Xe-135m 3.4143E-05 3.7482E-16 1.6720E+09 1.7962E+12 Control Room (C4) Transport Group Inventory:

Time (h) = 24.0000 Atmosphere Sump Noble gases (atoms) 1.2688E+16 0.0000E+00 Elemental I (atoms) 2.3313E+12 0.0000E+00 Organic I (atoms) 7.2101E+10 0.0000E+00 Aerosols (kg) 6.4932E-13 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 8.7832E-14 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 9.6051E-14 Total I (Ci) 2.8215E-04 Deposition Recirculating Time (h) = 24.0000 Surfaces Filter Noble gases (atoms) 0.0000E+00 0.0000E+00 Elemental I (atoms) O.O000E+00 2 .7621E+14 Organic I (atoms) 0.0000E+00 8.5427E+12 Aerosols (kg) 0.OOOOE+00 2.3135E-10 L6 - Environment To Control Room Transport Group Inventory:

Pathway

XceI Energy, Calculation No. GEN-PI-082 Revision No. 0 Page No.80 of 145 Time (h) = 24.0000 Filtered Transported Noble gases (atoms) 0.0000E+00 9.9976E+16 Elemental I (atoms) 0.OOOOE+00 3.0181E+14 Organic I (atoms) 0.0000E+00 9.3345E+12 Aerosols (kg) 0.0000E+00 2.5708E-10 L7 - Control Room Exhaust To Environment Transport Group Inventory:

Pathway Time (h) = 24.0000 Filtered Transported Noble gases (atoms) 8.6962E+16 0.OOOOE+00 Elemental I (atoms) 2.2241E+13 0.OOOOE+00 Organic I (atoms) 6.8786E+ll 0.OOOOE+00 Aerosols (kg) 2.5001E-11 0.OOOOE+00 Exclusion Area Boundary Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.0267E-02 1 .9962E+01 6. 3097E-01 Accumulated dose (rem) 1.1122E-01 4. 0948E+01 1.3752E+00 Low Population Zone Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.2234E-04 1.4391E-01 4 .6251E-03 Accumulated dose (rem) 1.8637E-02 3.00780E+00 1. 1500E-01 Control Room Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 6.4632E-04 1.5237E+00 4.7275E-02 Accumulated dose (rem) 7.2895E-03 1. 0800E+01 3. 4722E-01 Control Room (C4) Compartment Nuclide Inventory:

Time (h) = 96.0000 Ci kg Atoms Decay Kr-85 2.1297E-04 5.4283E-10 3.8459E+15 4 .5513E+12 Kr-85m 9. 6607E-10 1. 1739E-19 8.3170E+05 7.3009E+12 1-131 3.5400E-05 2.8554E-13 1. 3127E+12 1.5628E+12 1-133 4.1359E-06 3. 6510E-15 1. 6532E+10 2. 2454E+12 1-135 4.1107E-09 1. 1705E-18 5. 2215E+06 1.6175E+12 Xe-131m 1.2345E-04 1.4738E-12 6.7751E+12 2.7708E+12 Xe-133 1.6295E-02 8.7054E-1I 3. 9417E+14 4 .5564E+14 Xe-133m 2.9430E-04 6. 5589E-13 2. 9698E+12 1.2106E+13 Xe-135 3. 5184E-05 1.3778E-14 6. 1459E+10 7 . 3508E+13 Xe-135m 6. 3188E-09 6.9367E-20 3.0944E+05 1.8540E+12 Control Room (C4) Transport Group Inventory:

Time (h) = 96.0000 Atmosphere Sump Noble gases (atoms) 4.2498E+15 0.OOOOE+00 Elemental I (atoms) 5.7635E+ll 0.OOOOE+00 Organic I (atoms) 1.7825E+10 0.OOOOE+00 Aerosols (kg) 1.5992E-13 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 2. 0785E-14 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 2.1026E-14 Total I (Ci) 3.9540E-05 Deposition Recirculating Time (h) = 96.0000 Surfaces Filter Noble gases (atoms) 0.OOOOE+00 0.OOOOE+00

/ e n Oy Calculation No. GEN-PI-082 Revision No. 0 Page No.81 of 145 Elemental I (atoms) O.OOOOE+00 4.4869E+14 Organic I (atoms) O.O000E+00 1. 3877E+13 Aerosols (kg) O.OOOOE+00 2.7910E-10 L6 - Environment To Control Room Transport Group Inventory:

Pathway Time (h) = 96.0000 Filtered Transported Noble gases (atoms) 0.0000E+00 1.7825E+17 Elemental I (atoms) 0.OOOOE+00 4. 8575E+14 Organic I (atoms) 0.0000E+00 1.5023E13 Aerosols (kg) 0.OOOOE+00 3.0804E-10 L7 - Control Room Exhaust To Environment Transport Group Inventory:

Pathway Time (h) = 96.0000 Filtered Transported Noble gases (atoms) 1.7346E+17 0.OOOOE+00 Elemental I (atoms) 3.4849E+13 0 .OOOOE+00 Organic I (atoms) 1.0778E+12 0.OOOOE+00 Aerosols (kg) 2.8351E-11 0.OOOOE+00 Exclusion Area Boundary Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.8793E-02 5. 4975E+01 1.7028E+00 Accumulated dose (rem) 1.4001E-01 9. 5922E+01 3.0779E+00 Low Population Zone Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 4.6139E-05 5.7891E-02 1.8089E-03 Accumulated dose (rem) 1.8683E-02 3. 1359E+00 1. 1681E-01 Control Room Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.9174E-04 2.0708E+00 6.3448E-02 Accumulated dose (rem) 7.6813E-03 1.2871E+01 4 .1067E-01 Control Room (C4) Compartment Nuclide Inventory:

Time (h) = 720.0000 Ci kg Atoms Decay Kr-85 1.5609E-04 3.9786E-10 2. 8188E+15 1.7708E+13 1-131 2.7707E-06 2 .2349E-14 1.0274E+11 2.4380E+12 Xe-131m 3. 3193E-05 3.9628E-13 1. 8217E+12 7.8603E+12 Xe-133 3.9575E-04 2.1143E-12 9. 5732E+12 7.4735E+14 Xe-133m 6.0729E-08 1.3534E-16 6. 1282E+08 1. 4442E+13 Control Room (C4) Transport Group Inventory:

Time (h) = 720.0000 Atmosphere Sump Noble gases (atoms) 2.8302E+15 0.OOOOE+00 Elemental I (atoms) 4.4549E+10 0.OOOOE+00 Organic I (atoms) 1.3778E+09 0.OOOOE+00 Aerosols (kg) 1.2358E-14 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 1.5958E-15 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 1.5958E-15 Total I (Ci) 2.7707E-06 Deposition Recirculating

XcelEnergyj Calculation No. GEN-PI-082 Revision No. 0 Page No. 82 of 145 Time (h) = 720.0000 Surfaces Filter Noble gases (atoms) 0.OOOOE+00 0.OOOOE+00 Elemental I (atoms) 0.OOOOE+00 8.0348E+14 Organic I (atoms) 0.OOOOE+00 2.4850E+13 Aerosols (kg) 0.OOOOE+00 3. 8167E-10 L6 - Environment To Control Room Transport Group Inventory:

Pathway Time (h) = 720.0000 Filtered Transported Noble gases (atoms) 0.OOOOE+00 6.2719E+17 Elemental I (atoms) 0.OOOOE+00 8. 6643E+14

'Organic I (atoms) 0.OOOOE+00 2.6797E+13 Aerosols (kg) 0.0000E+00 4.1779E-10 L7 - Control Room Exhaust To Environment Transport Group Inventory:

Pathway Time (h) = 720.0000 Filtered Transported Noble gases (atoms) 6.2351E+17 0.OOOOE+00 Elemental I (atoms) 6.0784E+13 0.OOOOE+00 Organic I (atoms) 1.8799E+12 0.OOOOE+00 Aerosols (kg) 3.5545E-11 0.OOOOE+00 1-131 Summary Containment (Cl) Shield Bldg (C2) Environment (C3)

Time (hr) 1-131 (Curies) 1-131 (Curies) 1-131 (Curies) 0.000 8.1253E+04 0.0000E+00 1.4107E-03 0.004 5.2652E+05 0.000OE+00 5.9233E-02 0.083 5.2636E+05 0.0000E+00 2.6812E+00 0.200 5.2614E+05 0.OOOOE+00 6.5189E+00 0.333 5.2588E+05 0.OOOOE+00 1.0891E+01 0.367 5.2582E+05 0.OOOOE+00 1.1564E+01 0.367 5.2582E+05 0 0000E+00 1.1570E+01 0.800 5.2499E+05 6. 6405E+00 1.2280E+01 1.100 5.2441E+05 9. 9798E+00 1.2805E+01 1.400 5.2384E+05 1 .2559E+01 1.3353E+01 1.700 5.2326E+05 1. 4555E+01 1.3921E+01 2.000 5.2269E+05 1. 6101E+01 1.4507E+01 2.300 5.2212E+05 1. 7302E+01 1. 5110E+01 2.600 5.2154E+05 1. 8236E+01 1. 5726E+01 2.900 5.2097E+05 1 .8965E+01 1. 6356E+01 3.200 5.2040E+05 1 .9535E+01 1.6997E+01 3.500 5.1983E+05 1.9981E+01 1 .7649E+01 3.800 5.1926E+05 2.0332E+01 1. 8310E+01 4.100 5.1869E+05 2.0608E+01 1.8979E+01 4.400 5.1812E+05 2.0825E+01 1. 9655E+01 4.700 5.1756E+05 2.0997E+01 2. 0338E+01 5.000 5.1699E+05 2.1133E+01 2. 1027E+01 5.300 5.1642E+05 2.1241E+01 2.1721E+01 5.600 5.1586E+05 2.1326E+01 2. 2420E+01 5.900 5.1529E+05 2.1393E+01 2.3123E+01 6.200 5.1473E+05 2.1445E+01 2.3829E+01 6.500 5.1416E+05 2.1486E+01 2.4539E+01 6.800 5.1360E+05 2.1517E+01 2.5251E+01 7.100 5.1304E+05 2.1541E+01 2.5967E+01 7.400 5.1247E+05 2.1558E+01 2.6684E+01

XceIEnergy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 83 of 145 7.700 5. 1191E+05 2. 1570E+01 2. 7403E+01 8.000 5. 1135E+05 2 1577E+01 2 8125E+01 8.300 5.1079E+05 2. 1580E+01 2. 8847E+01 8.600 5. 1023E+05 2 1580E+01 2 9571E+01 8.900 5.0967E+05 2. 1578E+01 3. 0295E+01 9.200 5. 0911E+05 2 1573E+01 3. 1021E+01 9.500 5.0856E+05 2 1566E+01 3. 1747E+01 9.800 5.0800E+05 2 1557E+01 3. 2474E+01 10.100 5.0744E+05 2 .1547E+01 3. 3202E+01 10.400 5.0689E+05 2 1535E+01 3. 3930E+01 24.000 4.8231E+05 2. 0597E+01 6. 6439E+01 96.000 3. 7156E+05 7 .9338E+00 1. 4187E+02 720.000 3.8732E+04 8. 2705E-01 3. 6454E+02 Control Room (C4) ABSVZ (C5)

Time (hr) 1-131 (Curies) 1-131 (Curies) 0.000 6.0295E-06 0 OOOOE+00 0.004 2.5268E-04 0 0000E+00 0.083 1.0597E-02 0 OOOOE+00 0.200 8.5213E-03 0 OOOOE+00 0.333 7.0321E-03 0 OOOOE+00 0.367 6.5399E-03 2. 1909E-04 0.367 6.5358E-03 2 .1909E-04 0.800 1.4917E-03 2. 1874E-04 1.100 6.5776E-04 2. 1850E-04 1.400 3.9285E-04 2.1827E-04 1.700 3.1301E-.04 2.1803E-04 2.000 2.9292E-04 2.1779E-04 2.300 2.6586E-04 2.1755E-04

2. 600 2.6108E-04 2.1731E-04 2.900 2.6320E-04 2.1707E-04 3.200 2.6719E-04 2.1683E-04 3.500 2.714.6E-04 2.1660E-04 3.800 2.7550E-04 2.1636E-04 4.100 2.7919E-04 2.1612E-04 4.400 2.8252E-04 2.1589E-04 4.700 2.8550E-04 2.1565E-04 5.000 2.8817E-04 2.1541E-04 5.300 2. 9055E-04 2.1518E-04 5.600 2. 9267E-04 2.1494E-04 5.900 2. 9457E-04 2.1470E-04 6.200 2. 9625E-04 2.1447E-04 6.500 2. 9774E-04 2. 1423E-04 6.800 2. 9906E-04 2. 1400E-04 7.100 3 .0022E-04 2. 1377E-04 7.400 3.0124E-04 2 .1353E-04 7.700 3.0214E-04 2 .1330E-04 8.000 3.0292E-04 2. 1306E-04 8.300 1.8995E-04 2. 1283E-04 8.600 1.5260E-04 2. 1260E-04 8.900 1.4033E-04 2. 1236E-04 9.200 1.3637E-04 2. 1213E-04 9.500 1.3514E-04 2. 1190E-04 9..800 1.3481E-04 2. 1167E-04 10.100 1.3475E-04 2 .1143E-04 10.400 1.3478E-04 2. 1120E-04 24.000 1.3030E-04 2. 0096E-04 96.000 3.5400E-05 7 .7407E-05 720.00.0 2.7707E-06 8. 0692E-06

S XcelEnergy Calculation No. GEN-PI-082 Revision No. 0 Page No. 84 of 145 Cumulative Dose Summary

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

Exclusion Area Bounda Low Population Zone Control Room Time Thyroid TEDE Thyroid TEDE Thyroid TEDE (hr) (rem) (rem) (rem) (rem) (rem) (rem) 0.000 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0 OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.004 2. 0418E-02 7 .7814E-04 5.5685E-03 2 1222E-04 3.9039E-04 1.2433E-05 0.083 9. 2443E-01 3.5226E-02 2.5212E-01 9.6070E-03 4.7663E-01 1.5179E-02 0.200 2.2459E+00 8.5337E-02 6. 1252E-01 2 .3274E-02 1.6999E+00 5.4145E-02 0.333 3.7486E+00 1. 4192E-01 1.0223E+00 3.8705E-02 2.8307E+00 9.0192E-02 0 .367 3.9796E+00 1.5072E-01 1.0853E+00 4 1105E-02 3.0814E+00 9.8186E-02 0.367 3. 9816E+00 1 . 5080E-01 1.0859E+00 4 1126E-02 3.0836E+00 9.8254E-02 0.800 4 .2249E+00 1. 6165E-01 1. 1522E+00 4.4086E-02 4.6903E+00 1.4963E-01 1.100 4.4036E+00 1. 6928E-01 1. 2010E+00 4.6168E-02 5.0189E+00 1.6029E-01 1.400 4.5895E+00 1 7703E-01 1.2517E+00 4.8282E-02 5.1825E+00 1.6570E-01 1.700 4 .7816E+00 1. 8490E-01 1 .304 1E+00 5.0426E-02 5.2945E+00 1.6947E-01 2..000 4.9791E+00 1 .9286E-01 1.3579E+00 5.2598E-02 5.3916E+00 1.7276E-01 2.300 5. 1813E+00 2. 0091E-01 1. 4131E+00 5.4792E-02 5.4806E+00 1.7579E-01 2.600 5.3877E+00 2. 0902E-01 1.4694E+00 5.7005E-02 5.5648E+00 1.7866E-X1 2.900 5.5978E+00 2. 1719E-01 1.5267E+00 5.9233E-02 5.6485E+00 1.8151E-01 3.200 5. 8109E+00 2 2539E-01 1.5848E+00 6. 1471E-02 5.7330E+00 1.8437E-01 3.500 6.0268E+00 2. 3363E-01 1.6437E+00 6. 3717E-02 5.8185E+00 1.8727E-01 3.800 6.2450E+00 2. 4188E-01 1.7032E+00 6.5968E-02 5.9051E+00 1.9018E-01 4.100 6.4653E+00 2 . 5015E-01 1.7633E+00 6.8222E-02 5.9926E+00 1.9313E-01 4.400 6.6874E+00 2. 5842E-01 1.8238E+00 7.0478E-02 6.0810E+00 1.9609E-01 4.700 6. 9109E+00 2. 6669E-01 1.8848E+00 7.2732E-02 6.1701E+00 1.9907E-01 5.000 7.1357E+00 2 .7494E-01 1 .94 61E+00 7.4985E-02 6.2598E+00 2.0206E-01 5.300 7. 3616E+00 2. 8319E-01 2. 0077E+00 7.7234E-02 6.3500E+00 2.0507E-01 5.600 7.5883E+00 2. 9142E-01 2 .0695E+00 7.9479E-02 6.4407E+00 2.0808E-01 5.900 7. 8157E+00 2 . 9964E-01 2 1316E+00 8. 1719E-02 6.5318E+00 2.1109E-01 6.200 8.0437E+00 3. 0783E-01 2 1937E+00 8.3954E-02 6.6231E+00 2.1411E-01 6.500 8.2722E+00 3. 1600E-01 2.2560E+00 8.6181E-02 6.7147E+00 2.1713E-01 6.800 8.5009E+00 3. 2414E-01 2.3184E+00 8.8402E-02 6.8065E+00 2.2015E-01 7.100 8.7299E+00 3. 3226E-01 2.3809E+00 9. 0615E-02 6.8984E+00 2.2317E-01 7.400 8.9590E+00 3. 4034E-01 2.4434E+00 9.2821E-02 6.9905E+00 2.2619E-01 7.700 9. 1881E+00 3. 4840E-01 2.5058E+00 9. 5018E-02 7.0825E+00 2.2920E-01 8.000 9. 4171E+00 3. 5643E-01 2.5683E+00 9.7207E-02 7.1747E+00 2.3221E-01 8.300 9.,6461E+00 3. 6442E-01 2.5756E+00 9.7487E-02 7.2468E+00 2.3459E-01 8.600 9.8749E+00 3.7239E-01 2.5828E+00 9.7764E-02 7.2977E+00 2.3630E-01 8.900 1. 0103E+01 3. 8032E-01 2.5900E+00 9.8040E-02 7.3417E+00 2.3778E-01 9.200 1. 0332E+01 3. 8822E-01 2.5,972E+00 9. 8314E-02 7.3833E+/-00 2.3918E-01 9.500 1. 0560E+01 3. 9608E-01 2.6044E+00 9.8586E-02 7.4241E+00 2.4054E-01 9.800 1 . 0787E+01 4.0392E-01 2. 6116E+00 9.8857E-02 7.4646E+00 2.4189E-01 10.100 1.1015E+01 4.1172E-01 2.6188E+00 9. 9126E-02 7.5050E+00 2. 4323E-01 10.400 1.1241E+01 .4.1949E-01 2.6260E+00 9.9394E-02 7.5452E+00 2.4456E-01 24.000 2.098 6E+01 7.4420E-01 2.934 1E+00 1.1037E-01 9.2764E+00 2.9995E-01 96.000 4.0948E+01 1.3752E+00 3.0780E+00 1 . 1500E-01 1.0800E+01 3.4722E-01 720.000 9. 5922E+01 3.0779E+00 3.1359E+00 1.1681E-01 1.2871E+01 4.1067E-01 Worst Two-Hour Doses

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

Exclusion Area Boundary Time Whole Body Thyroid TEDE (hr) (rem) (rem) (rem) 0.0 3.5561E-02 4.9791E+00 1.9286E-01

XceI Energy] Calculation No. GEN-PI-082 Revision No. 0 Page No.85 of 145 Attachment 13.2 RADTRAD Output File PREAINID00.o0

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

RADTRAD Version 3.03 (Spring 2001) run on 5/25/2009 at 11:48:11

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

File information

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

Plant file = G:\Radtrad 3.03\Input\PI\GEN-PI-082\PREAINIDO0.psf Inventory file = g:\radtrad 3.03\defaults\pirearcs def.txt Release file = g:\radtrad 3.03\defaults\pingp iodinerft.txt Dose Conversion file = g:\radtrad 3.03\defaults\pingp fgll&12.txt

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

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

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

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

Radtrad 3.03 4/15/2001 PINGP 1 & 2 Rod Ejection Accident AST Analysis - P-T-S Leakage Iodine Release From Intact SG Nuclide Inventory File:

g:\radtrad 3.03\defaults\pirearcsdef.txt Plant Power Level:

1.8520E+03 Compartments:

4 Compartment 1:

RCS 3

5.2900E+03 0

0 0

0 0

Compartment 2:

Environment 2

0.OOOOE+00 0

0 0

0 0

Compartment 3:

Control Room 1

XcelEnergyICalculation No. GEN-PI-082 Revision No. 0 Page No. 86 of 145 6.1315E+04 0

0 1

0 0

Compartment 4:

Intact SG 3

3.4380E+03 0

0 0

0 0

Pathways:

4 Pathway 1:

RCS to Intact SG 1

4 2

Pathway 2:

Environment to Control Room 2

3 2

Pathway 3:

Control Room to Environment 3

2 2

Pathway 4:

Intact SG to Environment 4

2 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1 1.OOOOE+00 g:\radtrad 3.03\defaults\pingp_fgll&12.txt g:\radtrad 3.03\defaults\pingp_iodine rft.txt o.0000E+00 1

0.OOOOE+00 9.7000E-01 3.OOOOE-02 1.OOOOE+00 Overlying Pool:

0 0.0000E+00 0

0 0

0 Compartments:

4 Compartment 1:

XceI Energy] Calculation No. GEN-PI-082 Revision No. 0 Page No.87 of 145 0

1 0

0 0

0 0

0 0'

Compartment 2:

0 1

0 0

0 0

0 0

0 Compartment 3:

1 1

0 I,

0 0

0 1

3. 6000E+03 3

o .OOOOE+0O 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00

8. 3300E-02 9.9000E+01 9. 5000E+01 9. 5000E+01 7.2000E+02 o.OOOOE+00 o.OOOOE+00 0.OOOOE+00 0

0 Compartment 4:

0 1

0 0

0 0

0" 0

Pathways:

4 Pathway 1:

0 0

0 0

0 1

2

0. OOOOE+00 3.7600E-02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 4 .5500E+01 0.00OOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0

0 0

0

XceI Energy] Caculation No. GEN-PI-082 Revision No. 0 Page No. 88 of 145 0

0 Pathway 2:

0 0

0 0

0 1

3 o.OOOOE+00 2.OOOOE+03 o.OOOOE+00 o.OOOOE+00 o.OOOOE+0O 8.3300E-02 3.OOOOE+02 0.OOOOE+00 o.OOOOE+00 0.OOOOE+00 7.2000E+02 0.OOOOE+00 o.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0

0 0

0 0

0 Pathway 3:

0 0

0 0

0 1

3 0.OOOOE+00 2.OOOOE+03 0.OOOE+00 0.OOOOE+00 0.0000E+00 8.3300E-02 3.OOOOE+02 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 7.2000E+02 0.OOOOE+00 o.OOOOE+00 0.0000E+00 0.0000E+00 0

0 0

0 0

0 Pathway 4:

0 0

0 0

0 1

5 0.OOOOE+00 3. 9420E-01 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 2.OOOOE+00 2. 3610E-01 0.OOOOE+00 0.0000E+00 0.OOOOE+00 8.OOOOE+00 1.7340E-01 0.OOOOE+00 o.OOOOE+00 0.OOOOE+00 2.4000E+01 1.3980E-01 o.OOOOE+00 0.0000E+00 0.O000E+00 4.5500E+01 O.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0

0 0

0 0

0 Dose Locations:

3 Location 1:

Exclusion Area Boundary 2

XceIEnergy] Calculation No. GEN-P1-082 Revision No. 0 Page No. 89 of 145 1

2 0.OOOE+00 6.4900E-04 7.2000E+02 0.0000E+00 1

2 0.0000E+00 3.5000E-04 7.2000E+02 o.0000E+00 0

Location 2:

Low Population Zone 2

1 5

o.0000E+00 1.7700E-04 8.0000E+00 3.9900E-05 2.4000E+01 7.1200E-06

9. 6000E+01 1.0400E-06 7.2000E+02 O.O000E+00 1

4 o.0000E+00 3.5000E-04 8.0000E+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 o.0000E+00 0

Location 3:

Control Room 3

0 1

2 o.OOOOE+00 3.5000E-04 7.2000E+02 0.OOOOE+00 1

4 O.OOOOE+00 1.OOOOE+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 1.8300E-02 2.OOOOE+00 1.4200E-02 8.0000E+00 6.3000E-03 2.4000E+01 4.2900E-03 9.6000E+01 3.3800E-03 7.2000E+02 0.0000E+00 Simulation Parameters:

6 O.OOOOE+00 1.0000E-01 2.0000E+00 5.0000E-01 8.OOOOE+00 1.0000E+00 2.4000E+01 2.0000E+00 9.6000E+01 4.0000E+00 7.2000E+02 0.0000E+00 Output Filename:

G:\Radtrad 3.o67 1

Xc I nrg]Calculation No; GEN-PL-082 Revision No. 0 Page No. 90 of14 1

1*

0 0

End of Scenario File

Xce, Energy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 91 of 145

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RADTRAD Version 3.03 (Spring 2001) run on 5/25/2009 at 11:48:11

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

Plant Description

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

Number of Nuclides = 60 Inventory Power 1.OOOOE+00 MWth Plant Power Level = 1.8520E+03 MWth Number of compartments - 4 Compartment information Compartment number 1 (Source term fraction 1.0000E+00 Name: RCS Compartment volume 5.2900E+03 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 1 Exit Pathway Number 1: RCS to Intact SG Compartment number 2 Name: Environment Compartment type is Environment Pathways into and out of compartment 2 Inlet Pathway Number 3: Control Room to Environment Inlet Pathway Number 4: Intact SG to Environment Exit Pathway Number 2: Environment to Control Room Compartment number 3 Name: Control Room Compartment volume = 6.1315E+04 (Cubic feet)

Compartment type is Control Room Removal devices within compartment:

Filter(s)

Pathways into and out of compartment 3 Inlet Pathway Number 2: Environment to Control Room Exit Pathway Number 3: Control Room to Environment Compartment number 4 Name: Intact SG Compartment volume = 3.4380E+03 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 4 Inlet Pathway Number 1: RCS to Intact SG Exit Pathway Number 4: Intact SG to Environment Total number of pathways = 4

XceI nergy] Calculation No. GEN-PI-082 Revision No. 0 Page No.92 of 145 RADTRAD Version 3.03 (Spring 2001) run on 5/25/2009 at 11:48:11

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

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

Scenario Description

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

Radioactive Decay is enabled Calculation of Daughters is enabled Release Fractions and Timings GAP EARLY IN-VESSEL LATE RELEASE RELEASE MASS 0.003600 hr 0.0000 hrs 0.0000 hrs (gm)

NOBLES 0 OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 IODINE 1.0000E+00 0.OOOOE+00 0.OOOOE+00 5.928E+00 CESIUM 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 TELLURIUM 0 OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 STRONTIUM 0 OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 BARIUM 0.0000E+00 0.OOOOE+00 0.OOOOE+00 O.OOOE+00 RUTHENIUM 0 OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 CERIUM 0 OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 LANTHANUM 0 OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 Inventory Power = 1852. MWt Nuclide Group Specific half Whole Body Inhaled Inhaled Name Inventory life DCF Thyroid Effective (Ci/MWt) (s) (Sv-m3/Bq-s) (Sv/Bq) (Sv/Bq) 1-131 2 3.010E+02 6. 947E+05 1.820E-14 2 .920E-07 8.890E-09 1-132 2 4.354E+02 8.280E+03 1.120E-13 1 .740E-09 1.030E-10 1-133 2 6.106E+02 7.488E+04 2.940E-14 4.860E-08 1.580E-09 1-134 2 6.819E+02 3. 156E+03 1.300E-13 2.880E-10 3.550E-11 1-135 2 5.831E+02 2. 380E+04 8.294E-14 8 .460E-09 3.320E-10 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-135 Cs-135 1.00 none 0.00 none 0.00 Xe-135m Xe-135 1.00 none 0.00 none 0.00 Xe-138 Cs-138 1.00 none 0.00 none 0.00 Iodine fractions Aerosol - 0.OOOOE+00 Elemental = 9. 7000E-01 Organic = 3.OOOOE-02 COMPARTMENT DATA Compartment number 1: RCS Compartment number 2: Environment Compartment number 3: Control Room

XceI nergy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 93 of 145 Compartment Filter Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic o.OOOOE+00 3.6000E+03 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 8.3300E-02 3.6000E+03 9. 9000E+01 9.5000E+01 9. 5000E+01 7.2000E+02 3.6000E+03 0.0000E+00 o.OOOOE+00 O.OOOOE+00 Compartment number 4: Intact SG PATHWAY DATA Pathway number 1: RCS to Intact SG Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aeros 5ol Elemental Org anic 0.0000E+00 3.76OOE-02 0.0000E +00 0.OOOOE+00 0.00 0OE+00

4. 5500E+01 0.0000E+00 0.0000E;+00 O.OOOOE+00 0.00 OOE+00 Pathway number 2: Environment to Control Room Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.OOOOE+00 2.OOOOE+03 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 8.3300E-02 3.OOOOE+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 7.2000E+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Pathway number 3: Control Room to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(c fm) Aerosol Elemental Organic 0.OOOOE+00 2.0.OOOE+03 0.0000E+00 0.OOOOE+00 0.OOOOE+00 8.3300E-02 3.OOOOE+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 7.2000E+02 O.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Pathway number 4: Intact SG to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.OOOOE+00 3. 9420E-01 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 2.OOOOE+00 2.3610E-01 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 8.0000E+00 1.7340E-01 0.OOOOE+00 0.0000E+00 0.0000E+00 2.4000E+01 1. 3980E-01 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 4.5500E+01 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 LOCATION DATA Location Exclusion Area Boundary is in compartment 2 Location X/Q Data Time (hr) X/Q (s

• m^-3) 0.OOOOE+00 6.4900E-04

Calculation No. GEN-PI-082 Revision No. 0 Page No. 94 of 145 7.2000E+02 0.0000E+00 Location Breathing Rate Data Time (hr) Breathing Rate (m^3

• sec^-l) 0.0OOOE+00 3.5000E-04 7.2000E+02 0.0000E+00 Location Low Population Zone is in compartment 2 Location X/Q Data Time (hr) X/Q (s

• m^-3) 0.OOOOE+00 1.7700E-04 8.OOOOE+00 3.9900E-05 2.4000E+01 7.1200E-06 9.6000E+01 1.0400E-06 7.2000E+02 0.0000E+00 Location Breathing Ralte Daita Time (hr) Br eathi .ng 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 Control Room is in compartment 3 Location X/Q Data Time (hr) X/Q (s

• m^-3) 0.0000E+00 1.8300E-02 2.0000E+00 1.4200E-02 8.0000E+00 6.3000E-03 2.4000E+01 4.2900E-03 9.6000E+01 3.3800E-03 77.2000E+02 0.0000E+00 Location Breathing Rate Data Time (hr) Breathing Rate (m^3

• sec^-l) 0.0000E+00 3.5000E-04 7.2000E+02 0.0000E+00 Location Occupancy Factor Data Time (hr) Occupancy Factor 0.OOOOE+00 1.0000E+00 2.4000E+01 6.0000E-01 9.6000E+01 4.OOOOE-01 7.2000E+02 0.OOOOE+00 USER SPECIFIED TIME STEP DATA - SUPPLEMENTAL TIME STEPS Time Time step 0.0000E+00 1.0000E-01 2.OOOOE+00 5. 00O0E-01 8.0000E+00 1.OOOOE+00 2.4000E+01 2.0000E+00

9. 6000E+01 4.0000E+00 7.2000E+02 0.OOOOE+00

XceI Energy]Calculation No. GEN-PI-082 Revision No. 0 Page No.95 of 145

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RADTRAD Version 3.03 (Spring 2001) run on 5/25/2009 at 11:48:11 4########################4###############4##################4##########

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Dose, Detailed model and Detailed Inventory Output

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

Exclusion Area Boundary Doses:

Time (h) = 0.0036 Whole Body Thyroid TEDE Delta dose (rem) 5.8932E-09 1.2177E-06 4.4394E-08 Accumulated dose (rem) 5.8932E-09 1.2177E-06 4.4394E-08 Low Population Zone Doses:

Time (h) = 0.0036 Whole Body Thyroid TEDE Delta dose (rem) 1.6072E-09 3.3211E-07 1.2107E-08 Accumulated dose (rem) 1.6072E-09 3.3211E-07 1.,2107E-08 Control Room Doses:

Time (h) = 0.0036 Whole Body Thyroid TEDE Delta dose (rem) 1.4836E-11 8.6623E-08 2.7536E-09 Accumulated dose (rem) 1.4836E-11 8.6623E-08 2.7536E-09 Control Room Compartment Nuclide Inventory:

Time (h) = 0.0036 Ci kg Atoms Decay 1-131 6. 0913E-08 4. 9133E-16 2.2587E+09 2.0343E+04 1-132 8.8017E-08 8 .5270E-18 3. 8902E+07 2.9406E+04 1-133 1.2355E-07 1.0907E-16 4. 9385E+08 4.1265E+04 1-134 1.3760E-07 5..1582E-18 2. 3182E+07 4. 6001E+04 1-135 1. 1796E-07 3. 3588E-17 1.4983E+08 3.9400E+04 Xe-133 2. 0328E-12 1.0860E-20 4.9174E+04 1.3008E-01 Xe-135 2. 3559E-11 9. 2252E-21 4 1152E+04 1.5074E+00 Control Room Transport Group Inventory:

Time (h) = 0.0036 Atmosphere Sump Noble gases (atoms) 9.9321E+04 0.OOOOE+00 Elemental I (atoms) 2.8755E+09 0.OOOOE+00 Organic I (atoms) 8.8933E+07 0.0000E+00 Aerosols (kg) 0.0000E+00 0.00005+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 4. 9275E-17 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 6.2936E-17 Total I (Ci) 5.2804E-07

-o X ,eIEnergy1 Calculation No. GEN-PI-082 Revision No. 0 Page No. 96 of 145 Deposition Recirculating Time (h) = 0.0036 Surfaces Filter Noble gases (atoms) 0.OOOOE+00 0.OOOOE+00 Elemental I (atoms) 0.0000E+00 0.OOOOE+00 Organic I. (atoms) 0.OOOOE+00 0.OOOOE+00 Aerosols (kg) 0.0000E+00 0.0000E+00 Environment to Control Room Transport Group Inventory:

Pathway Time (h) = 0.0036 Filtered Transported Noble gases (atoms) 0.OOOOE+00 1.8516E+04 Elemental I (atoms) 0.OOOOE+00 2.8807E+09 Organic I (atoms) 0.OOOOE+00 8.9095E+07 Aerosols (kg) 0.0000E+00 0.OOOOE+00 Control Room to Environment Transport Group Inventory:

Pathway Time (h) = 0.0036 Filtered Transported Noble gases (atoms) 3.9458E+01 0.0O00E+00 Elemental I (atoms) 5.4537E+06 0.OOOOE+00 Organic I (atoms) 1.6867E+05 0.00OOE+00 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Exclusion Area Boundary Doses:

Time (h) = 0.0833 Whole Body Thyroid TEDE Delta dose (rem) 9.0457E-06 1.8710E-03 6. 8199E-05 Accumulated dose (rem) 9.0516E-06 1.8722E-03 6.8244E-05 Low Population Zone Doses:

Time (h) = 0.0833 Whole Body Thyroid TEDE Delta dose (rem) 2. 4670E-06 5.1026E-04 1.8600E-05 Accumulated dose (rem) 2.4686E-06 5.1060E-04 1.8612E-05 Control Room Doses:

Time (h) 0.0833 Whole Body Thyroid TEDE Delta dose (rem) 6.6890E-07 3.9093E-03 1.2427E-04 Accumulated dose (rem) 6.6891E-07 3.9094E-03 1.2427E-04 Control Room Compartment Nuclide Inventory:

Time (h) = 0.0833 Ci kg Atoms Decay 1-131 8.8997E-05 7.1786E-13 3.3000E+12 9.4495E+08 1-132 1.2558E-04 1.2166E-14 5.5505E+10 1.3493E+09 1-133 1.8009E-04 1.5898E-13 7.1983E+ll 1.9144E+09 1-134 1.8882E-04 7.0782E-15 3.1810E+10 2.0691E+09 1-135 1.7096E-04 4.8680E-14 2. 1715E+1I 1.8225E+09 Xe-131m 1. 9593E-10 2.3392E-18 1.0753E+07 6. 9486E+01 Xe-133 7.9421E-08 4.2430E-16 1. 9212E+09 2.8196E+04 Xe-133m 5. 6918E-09 1.2685E-17 5.7436E+07 2.0201E+03 Xe-135 9..1849E-07 3.5967E-16 1.6044E+09 3.2581E+05 Xe-135m 5.7383E-06 6.2994E-17 2.8101E+08 1.8480E+06 Control Room Transport Group Inventory:

Time (h) = 0.0833 Atmosphere Sump

XcelEnergy Calculation No. GEN-P1-082 Revision No. 0 Page No. 97 of 145 Noble gases (atoms) 3.8748E+09 0.0000E+00 Elemental I (atoms) 4.1946E+12 0.OOOOE+00 Organic I (atoms) 1.2973E+II 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 7. 1913E-14 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 9. 1638E-14 Total I (Ci) 7.5445E-04 Deposition Recirculating Time (h) 0.0833 Surfaces Filter Noble gases (atoms) 0.OOOOE+00 0.OOOOE+00 Elemental I (atoms) 0.OOOOE+00 0.OOOOE+00 Organic I (atoms) 0.OOOOE+00 0.OOOOE+00 Aerosols (kg) O.OOOOE+00 O.OOOOE+00 Environment to Control Room Transport Group Inventory:

Pathway Time (h) = 0.0833 Filtered Transported Noble gases (atoms) 0.OOOOE+00 1.3672E+08 Elemental I (atoms) 0.OOOOE+00 4.4289E+12 Organic I (atoms) 0.OOOOE+00 1.3698E+ll Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Control Room to Environment Transport Group Inventory:

Pathway Time (h) = 0.0833 Filtered Transported Noble gases (atoms) 6.9224E+06 0.OOOOE+00 Elemental I (atoms) 2.2377E+II 0.OOOOE+00 Organic I (atoms) 6.9207E+09 0.0000E+00 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Exclusion Area Boundary Doses:

Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.4995E-03 1.0945E+00 3.7896E-02 Accumulated dose (rem) 3.5085E-03 1.0963E+00 3.7965E-02 Low Population Zone Doses:

Time (h) = 2.0000 Whole Body Thyroid. TEDE Delta dose (rem) 9.5440E-04 2.9849E-01 1.0335E-02 Accumulated dose (rem) 9.5687E-04 2.9900E-01 1.0354E-02 Control Room Doses:

Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.1752E-04 1. 924 1E+00 6.0675E-02 Accumulated dose (rem) 2.1819E-04 1.9280E+00 6.0799E-02 Control Room Compartment Nuclide Inventory:

Time (h) 2.0000 Ci kg Atoms Decay 1-131 1.9794E-03 1.5967E-11 7 . 3399E+13 2.5036E+1.

1-132 1.5784E-03 .1.5291E-13 6. 9763E+l1 2.4315E+ll 1-133 3.7836E-03 3. 3400E-12 1.5123E+13 4.8764E+ll 1-134 9.2909E-04 3. 4828E-14 1.5652E+1I 2. 0688E+ll 1-135 3. 1315E-03 8. 9170E-13 3. 9777E+12 4.2263E+ll Xe-131m 2. 9190E-07 3.4849E-15 1.6020E+10 2.1903E+07

XceI nergylCalculation No. GEN-Pl-082 Revision No. 0 Page No. 98 of 145 Xe-133 1. 1519E-04 6. 1539E-13 2 .7864E+12 8.6942E+09 Xe-133m 8. 1817E-06 1.8234E-14 8. 2562E+10 6. 1880E+08 Xe-135 1.3443E-03 5. 2641E-13 2.3482E+12 1. 0307E+lI Xe-135m 9.9829E-04 1. 0959E-14 4. 8887E+I0 1. 1550E+]1 Control Room Transport Group Inventory:

Time (h) = 2.0000 Atmosphere Sump Noble gases (atoms) 5.2822E+12 0.0000E+00 Elemental I (atoms) 9.0554E+13 0.OOOOE+00 Organic I (atoms) 2.8006E+12 0.OOOOE+00 Aerosols (kg) 0.0000E+00 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 1. 5610E-12 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 1.914 5E-12 Total I (Ci) 1. 1402E-02 Deposition Recirculating Time (h) = 2.0000 Surfaces Filter Noble gases (atoms) 0.OOOOE+00 0.OOOOE+00 Elemental I (atoms) 0.0000E+00 2.7459E+14 Organic I (atoms) 0.OOOOE+00 8.4925E+12 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Environment to Control Room Transport Group Inventory:

Pathway Time (h) = 2.0000 Filtered Transported Noble gases (atoms) 0.OOOOE+00 5.3076E+12 Elemental I (atoms) 0.OOOOE+00 3.9103E+14 Organic I (atoms) 0.OOOOE+00 1.2094E+13 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Control Room to Environment Transport Group Inventory:

Pathway Time (h) = 2.0000 Filtered Transported Noble gases (atoms) 8.2619E+11 0.OOOOE+00 Elemental I (atoms) 2.4311E+13 0.0000E+00 Organic I (atoms) 7.5187E+lI 0.OOOOE+00 Aerosols (kg) O.OOOOE+00 0.OOOOE+00 Exclusion Area Boundary Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.4712E-02 9.2091E+00 3. 0162E-01 Accumulated dose (rem) 1.8221E-02 1.0305E+01 3. 3959E-01 Low Population Zone Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 4.0125E-03 2. 5116E+00 8.2261E-02 Accumulated dose (rem) 4.9693E-03 2. 8106E+00 9. 2615E-02 Control Room Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.0221E-03 1. 5671E+01 4.8928E-01 Accumulated dose (rem) 1.2403E-03 1. 7599E+01 5. 5008E-01 Control Room Compartment Nuclide Inventory:

Xce Energ Calculation No. GEN-PI-082 Revision No. 0 Page No. 99 of 145 Time (h) 8.0000 Ci kg Atoms Decay 1-131 3.9867E-03 3 2157E-11 1 4783E+14 2 .2782E+12 1-132 5.3255E-04 5 1592E-14 2 3538E+II 8.7923E+1I 1-133 6.3754E-03 5.627 9E-12 2. 5483E+13 3. 9787E+12 1-134 1.6642E-05 6. 2384E-16 2. 8036E+09 3.4378E+II 1-135 3.4351E-03 9.7814E-13 4. 3633E+12 2. 6919E+12 Xe-131m 5.4608E-06 6.5195E-14 2. 9970E+1I 1 .7208E+09 Xe-133 1.9836E-03 1 0597E-11 4 .7984E+13 6. 4169E+11 Xe-133m 1.3689E-04 3.0507E-13 1. 3813E+12 4.4678E+10 Xe-135 1.5383E-02 6.0239E-12 2. 6872E+13 5. 7053E+12 Xe-135m 1 .2010E-03 1. 3185E-14 5. 8815E+10 9. 1323E+11 Control Room Transport Group Inventory:

Time (h) = 8.0000 Atmosphere Sump Noble gases (atoms) 7.6595E+13 0.OOOOE+00 Elemental I (atoms) 1.7258E+14 0.0000E+00 Organic I (atoms) 5.3374E+12 0.OOOOE+00 Aerosols (kg) 0.0000E+00 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 2. 9665E-12 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 3.4535E-12 Total I (Ci) 1.4346E-02 Deposition Recirculating Time (h) = 8.0000 Surfaces Filter Noble gases (atoms) 0.OOOOE+00 0.OOOOE+00 Elemental I (atoms) 0.OOOOE+00 2.5106E+15 Organic I (atoms) 0.OOOOE+00 7.7649E+13 Aerosols (kg) 0.OOOOE+00 0.0000E+00 Environment to Control Room Transport Group Inventory:

Pathway Time (h) = 8.0000 Filtered Transported Noble gases (atoms) 0.OOOOE+00 1.3272E+14 Elemental I (atoms) 0.0000E+00 2.9136E+15 Organic I (atoms) 0.0000E+00 9.0111E+13 Aerosols (kg) 0.0000E+00 0.OOOOE+00 Control Room to Environment Transport Group Inventory:

Pathway Time (h) = 8.0000 Filtered Transported Noble gases (atoms) 5.6463E+13 0.OOOOE+00 Elemental I (atoms) 2.2046E+14 0.0000E+00 Organic I (atoms) 6.8182E+12 0.0000E+00 Aerosols (kg) 0.0000E+00 0.0000E+00 Exclusion Area Boundary Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.9884E-02 5.0157E+01 1.5887E+00 Accumulated dose (rem) 5.8105E-02 6.0462E+01 1.9283E+00 Low Population Zone Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.4520E-03 1.5858E+00 5. 1422E-02 Accumulated dose (rem) 7.4213E-03 4.3964E+00 1. 4404E-01 Control Room Doses:.

Xce Ene Calculation No. GEN-PI-082 Revision No. 0 Page No. 100 of 145 Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.8585E-03 3.9350E+01 1.2171E+00 Accumulated dose (rem) 3.0988E-03 5.6949E+01 1.7672E+00 Control Room Compartment Nuclide Inventory:

Time (h) = 24.0000 Ci kg Atoms Decay 1-131 3. 6771E-03 2. 9660E-11 1. 3635E+14 7.8570E+12 1-132 4. 1888E-06 4.0581E-16 1.8514E+09 9. 9766E+11 1-133 3. 6543E-03 3.2258E-12 1.4 606E+13 1.0840E+13 1-135 6.2680E-04 1.7848E-13 7. 9618E+11 4 .8135E+12 Xe-131m 2 .2614E-05 2 . 6998E-13 1.2411E+12 2. 6084E+10 Xe-133 6.5555E-03 3. 5022E-Il 1.5858E+14 8. 3118E+12 Xe-133m 4 1933E-04 9.3453E-13 4.2315E+12 5. 4987E+11 Xe-135 1.6492E-02 6. 4579E-12 2.8808E+13 3. 6677E+13 Xe-135m 3.5478E-04 3.8947E-15 1.7374E+10 2. 0401E+12 Control Room Transport Group Inventory:

Time (h) = 24.0000 Atmosphere Sump Noble gases (atoms) 1.9287E+14 0.0000E+00 Elemental I (atoms) 1.4720E+14 0.0000E+00 Organic I (atoms) 4.5526E+12 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 2.4786E-12 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 2.7106E-12 Total I (Ci) 7.9624E-03 Deposition Recirculating Time (h) = 24.0000 Surfaces Filter Noble gases (atoms) 0.OOOOE+00 0.0000E+00 Elemental I (atoms) 0.OOOOE+00 8.1997E+15 Organic I (atoms) 0.0000E+00 2.5360E+14 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Environment to Control Room Transport Group Inventory:

Pathway Time (h) = 24.0000 Filtered Transported Noble gases (atoms) 0.0000E+00 8.0561E+14 Elemental I (atoms) 0.0000E+00 9.0907E+15 Organic I (atoms) 0.OOOOE+00 2.8116E+14 Aerosols (kg) 0.OOOOE+00 0.0000E+00 Control Room to Environment Transport Group Inventory:

Pathway Time (h) = 24.0000 Filtered Transported Noble gases (atoms) 5.8347E+14 0.OOOOE+00 Elemental I (atoms) 7.1950E+14 0.0000E+00 Organic I (atoms) 2.2253E+13 0.OOOOE+00 Aerosols (kg) 0.0000E+00 0.0000E+00 Exclusion Area Boundary Doses:

Time (h) = 45.5000 Whole Body Thyroid TEDE Delta dose (rem) 4.2683E-02 9.9349E+01 3.0909E+00 Accumulated dose (rem) 1.0079E-01 1.5981E+02 5. 0192E+00 Low Population Zone Doses:

XceI Energy]Calculation No. GEN-PI-082 Revision No .. 0 Page No. 101 of 145 Time (h) = 45.5000 Whole Body Thyroid TEDE Delta dose (rem) 4.6827E-04 7.1624E-01 2.2444E-02 Accumulated dose (rem) 7.8896E-03 5.1127E+00 1.6648E-0l Control Room Doses:

Time (h) = 45.5000 Whole Body Thyroid TEDE Delta dose (rem) 8.8015E-04 3. 2014E+01 9. 8320E-01 Accumulated dose (rem) 3.9790E-03 8. 8964E+01 2. 7504E+00 Control Room Compartment Nuclide Inventory:

Time (h) = 45.5000 Ci kg Atoms Decay 1-131 3.4692E-03 2.7983E-11 1. 2864E+14 1.5913E+13 1-132 6.552 1E-09 6.3476E-19 2.8959E+06 9. 9884E+11 1-133 1.8193E-03 1. 6060E-12 7. 2719E+12 1. 6596E+13 1-135 6.7027E-05 1.9086E-14 8.5139E+10 5.324 6E+12 Xe-131m 4.6622E-05 5. 5661E-13 2. 5588E+12 1.1208E+11 Xe-133 1. OOlOE-02 5. 3479E-11 2 .4215E+14 2.9250E+13 Xe-133m 5.7480E-04 1.2810E-12 5. 8004E+12 1.8141E+12 Xe-135 5.5006E-03 2.1539E-12 9. 6084E+12 6. 1672E+13 Xe-135m 3.7076E-05 4.0702E-16 1. 8156E+09 2 . 3902E+12 Control Room Transport Group Inventory:

Time (h) = 45.5000 Atmosphere Sump Noble gases (atoms) 2.6012E+14 0.OOOOE+00 Elemental I (atoms) 1.3192E+14 0.OOOOE+00 Organic I (atoms) 4.0799E+12 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 2. 1736E-12 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 2. 2814E-12 Total I (Ci) 5.3556E-03 Deposition Recirculating Time (h) = 45.5000 Surfaces Filter Noble gases (atoms) 0.OOOOE+00 0.OOOOE+00 Elemental I (atoms) 0.OOOOE+00 1.5981E+16 Organic I (atoms) 0.OOOOE+00 4.9427E+14 Aerosols (kg) 0.0000E+00 O.OOOOE+00 Environment to Control Room Transport Group Inventory:

Pathway Time (h) = 45.5000 Filtered Transported Noble gases (atoms) 0.OOOOE+00 2.1551E+15 Elemental I (atoms) 0.OOOOE+00 1.7603E+16 Organic I (atoms) 0.OOOOE+00 5.4442E+14 Aerosols (kg) 0.0000E+00 0.OOOOE+00 Control Room to Environment Transport Group Inventory:

Pathway Time (h) = 45.5000 Filtered Transported Noble gases (atoms) 1.8260E+15 0.o0OOE+00 Elemental I (atoms) 1.4021E+15 0.OOOOE+00 Organic I (atoms) 4.3364E+13 0.OOOOE+00 Aerosols (kg) 0.O000E+00 0.0000E+00 Exclusion Area Boundary Doses:

Xcel EnergyjCalculation No. GEN-PI-082 Revision No. 0 Page No. 102 of 145 Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 0.OOOOE+00 0.OOOOE+00 Accumulated dose (rem) 1.0079E-01 1.5981E+02 5. 0192E+00 Low Population Zone Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Accumulated dose (rem) 7.8896E-03 5. 1127E+00 1. 6648E-01 Control Room Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 4.6572E-05 6. 6683E-01 2. 0461E-02 Accumulated dose (rem) 4.0256E-03 8. 9630E+01 2.7708E+00 Control Room Compartment Nuclide Inventory:

Time (h) 96.0000 Ci kg Atoms Decay Xe-131m 1. 5031E-11 1.7945E-19 8.2496E+05 1.3033E+ll Xe-133 2.7989E-09 1. 4953E-17 6.7706E+07 3. 3132E+13 Xe-133m 1.0755E-10 2.3970E-19 1.0853E+06 2. 0313E+12 Xe-135 4.2628E-II 1.6692E-20 7.4462E+04 6. 3397E+13 Control Room Transport Group Inventory:

Time (h) = 96.0000 Atmosphere Sump Noble gases (atoms) 6.9691E+07 0.OOOOE+00 Elemental I (atoms) 1.5265E-66 0.0000E+00 Organic I (atoms) 4.7211E-68 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 2.4609E-92 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 2.4894E-92 Total I (Ci) 4.6814E-83 Deposition Recirculating Time (h) = 96.0000 Surfaces Filter Noble gases (atoms) 0.OOOOE+00 0.0000E+00 Elemental I (atoms) 0.OOOOE+00. 1..6078E+16 Organic I (atoms) 0.OOOOE+00 4.9727E+14 Aerosols (kg) 0.0000OE+00 0.OOOOE+00 Environment to Control Room Transport Group Inventory:

Pathway Time (h) = 96.0000 Filtered Transported Noble gases (atoms) 0.OOOOE+00 2.1551E+15 Elemental I (atoms) 0.OOOOE+00 1.7603E+16 Organic I (atoms) 0.OOOOE+00 5.4442E+14 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Control Room to Environment Transport Group Inventory:

Pathway Time (h) = 96.0000 Filtered Transported Noble gases (atoms) 2.0805E+15 0.OOOOE+00 Elemental I (atoms) 1.4106E+15 0.OOOOE+00 Organic I (atoms) 4.3627E+13 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00

SXcel nergy Calculation No. GEN-PI-082 Revision No. 0 Page No. 103 of 145 Exclusion Area Boundary Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Accumulated dose (rem) 1.0079E-01 1. 5981E+02 5. 0192E+00 Low Population Zone Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Accumulated dose (rem) 7.8896E-03 5. 1127E+00 1. 6648E-01 Control Room Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.8126E-12 7. 0604E-81 1.8126E-12 Accumulated dose (rem) 4.0256E-03 8. 9630E+01 2.7708E+00 Control Room Compartment Nuclide Inventory:

Time (h) = 720.0000 Ci kg Atoms Decay Control Room Transport Group Inventory:

Time (h) = 720.0000 Atmosphere Sump Noble gases (atoms) 6.7248E-74 0.OOOOE+00 Elemental I (atoms) 0.OOOOE+00 0.oo0OE+00 Organic I (atoms) 0.OOOOE+00 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (Thyroid) O.OOOOE+00 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) O.O000E+00 Total I (Ci) O.OOOOE+00 Deposition Recirculating Time (h) = 720.0000 Surfaces Filter Noble gases (atoms) 0.OOOOE+00 0.OOOOE+00 Elemental I (atoms) O.OOOOE+00 1.6078E+16 Organic I (atoms) O.OOOOE+00 4. 9727E+14 Aerosols (kg) O.OOOOE+00 0.OOOOE+00 Environment to Control Room Transport Group Inventory:

Pathway Time (h) = 720.0000 Filtered Transported Noble gases (atoms) 0.OOOOE+00 2.1551E+15 Elemental I (atoms) 0.OOOOE+00 1.7603E+16 Organic I (atoms) 0.OOOOE+00 5. 4442E+14 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Control Room to Environment Transport Group Inventory:

Pathway Time (h) = 720.0000 Filtered Transported Noble gases (atoms) 2.0805E+15 0.OOOOE+00 Elemental I (atoms) 1.4106E+15 0.OOOOE+00 Organic I (atoms) 4.3627E+13 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 840

c e ylCalculation No. GEN-PI-082 Revision No. 0 Page No. 104 of 145 VV1/ - I 1-131 Summary

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

RCS Environment Control Room Time (hr) 1-131 (Curies) 1-131 (Curies) 1-131 (Curies) 0.000 8.6026E+04 1.2983E-08 2.2420E-10 0.004 5.5744E+05 3.5326E-06 6.0913E-08 0.083 5.5727E+05 5.4299E-03 8.8997E-05 0.400 5.5656E+05 1.2940E-01 2.4229E-04 0.700 5.5589E+05 3.9723E-01 5.2389E-04 1.000 5. 5522E+05 8.1075E-01 8.4780E-04 1.300 5. 5455E+05 1.3693E+00 1.1849E-03 1.600 5. 5388E+05 2.0723E+00 1.5254E-03 1.900 5. 5321E+05 2.9191E+00 1.8661E-03 2.000 5. 5299E+05 3.2332E+00 1.9794E-03 2.300 5. 5232E+05 3.8549E+00 1.4331E-03 2.600 5.5166E+05 4.5623E+00 1.3549E-03 2.900 5.5099E+05 5.3553E+00 1.4332E-03 3.200 5.5033E+05 6.2334E+00 1.5636E-03 3.500 5. 4967E+05 7.1965E+00 1.7111E-03 3.800 5.4900E+05 8.2441E+00 1 .8639E-03 4.100 5.4834E+05 9.3760E+00 2. 0182E-03 4.400 5.4768E+05 1.0592E+01 2. 1726E-03 4.700 5.4702E+05 1.1891E+01 2.3267E-03 5.000 5.4636E+05 1.3274E+01 2. 4803E-03 5.300 5.4570E+05 1.4741E+01 2 .6333E-03 5.600 5.4505E+05 1.6289E+01 2. 7859E-03 5.900 5.4439E+05 1.7921E+01 2. 9379E-03 6.200 5.4373E+05 1.9634E+01 3.0893E-03 6.500 5.4308E+05 2.1430E+01 3.2402E-03 6.800 5.4243E+05 2.3307E+01 3.3906E-03 7.100 5.4177E+05 2.5265E+01 3.5404E-03 7.400 5.4112E+05 2.7305E+01 3.6897E-03 7.700 5.4047E+05 2.9425E+01 3.8385E-03 8.000 5.3982E+05 3.1626E+01 3.9867E-03 8.300 5.3917E+05 3.3301E+01 2.2481E-03 8.600 5.3852E+05 3.5036E+01 1.6976E-03 8.900 5.3787E+05 3.6830E+01 1.5451E-03 9.200 5.3722E+05 3.8682E+01 1.5259E-03 9.500 5.3657E+05 4.0593E+01 1 .5512E-03 9.800 5.3593E+05 .4.2563E+01 1 .5915E-03 10.100 5.3528E+05 4.4591E+01 1.6365E-03 10.400 5.3463E+05 4.6677E+01 1.6832E-03 24.000 5.0620E+05 1.9896E+02 3. 6771E-03 45.500 4.6430E+05 5.5831E+02 3.4692E-03 96.000 3.8727E+05 5.5831E+02 4. 1912E-83 720.000 4.1166E+04 5.5831E+02 0 OOOOE+00 Intact SG Time (hr) 1-131 (Curies) 0.000 1.0191E-02 0.004 4.2791E-01 0.083 1.9364E+01 0.400 9.4392E+01 0.700 1.6515E+02 1.000 2.3559E+02 1.300 3.0574E+02 1.600 3.7557E+02 1.900 4.4510E+02 2.000 4.6821E+02

XcelEnergyl Calculation No. GEN-PI-082 Revision No. 0 Page No. 105 of 145 2.300 5.3775E+02 2.600 6.0705E+02 2.900 6. 7610E+02 3.200 7.4491E+02 3.500 8. 1347E+02 3.800 8.8180E+02 4.100 9.4987E+02 4.400 1 .0177E+03 4 .700 1.0853E+03 5.000 1. 1527E+03 5.300 1.2198E+03

5. 600 1.2866E+03 5.900 1.3533E+03 6.200 1. 4197E+03 6.500 1.4858E+03 6.800 1.5518E+03 7.100 1. 6175E+03 7.400 1.6829E+03 7.700 1.7481E+03 8.000 1. 8131E+03 8.300 1.8785E+03 8.600 1.9436E+03 8.900 2.0086E+03 9.200 2.0733E+03 9.500 2.1378E+03 9.800 2 .2021E+03 10.100 2.2662E+03 10.400 2.3301E+03 24.000 5.0141E+03 45.500 8. 5706E+03 96.000 7 1487E+03 720.000 7. 5988E+02 Cumulative Dose Summary Exclusion Area Bounda Low Population Zone Control Room Time Thyroid TEDE Thyroid TEDE Thyroid TEDE (hr) (rem) (rem) (rem) (rem) (rem) (rem) 0.000 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.004 1.2177E-06 4.4394E-08 3. 3211E-07 1.2107E-08 8.6623E-08 2.7536E-09 0.083 1.8722E-03 6.8244E-05 5. 1060E-04 1. 8612E-05 3.9094E-03 1.2427E-04 0.400 4.4485E-02 1.6034E-03 1.2132E-02 4.3728E-04 5.5176E-02 1.7511E-03 0.700 1 .3619E-01 4.8622E-03 3 .7144E-02 1. 3261E-03 1.7919E-01 5.6785E-03 1.000 2. 7724E-01 9.8142E-03 7. 5610E-02 2.6766E-03 4.0282E-01 1.2748E-02 1.300 4. 6703E-01 1. 6409E-02 1.2737E-01 4.4752E-03 7.3359E-01 2.3187E-02 1.600 7.0501E-01 2.4605E-02 1. 9228E-01 6. 7105E-03 1.1732E+00 3.7042E-02 1.900 9. 9064E-01 3. 4368E-02 2.7017E-01 9.3730E-03 1.7213E+00 5.4297E-02 2.000 1.0963E+00 3. 7965E-02 2 . 9900E-01 1 .0354E-02 1.9280E+00 6.0799E-02 2.300 1. 3051E+00 4 .5038E-02 3. 5593E-01 1.2283E-02 2.4591E+00 7.7494E-02

2. 600 1. 5418E+00 5. 3016E-02 4 .2048E-01 1.4459E-02 2.9000E+00 9.1344E-02 2.900 1.8062E+00 6.1886E-02 4. 9260E-01 1.6878E-02 3.3436E+00 1.0526E-01 3.200 2. 0981E+00 7. 1636E-02 5. 722 1E-01 1.9537E-02 3.8202E+00 1.2021E-01 3.500 2.4172E+00 8.2256E-02 6. 5923E-01 2 .2433E-02 4.3398E+00 1.3649E-01 3.800 2.7632E+00 9.3733E-02 7.5361E-01 2.5564E-02 4.9056E+00 1.5420E-01 4.100 3. 1359E+00 1. 0606E-01 8.5526E-01 2.8925E-02 5.5180E+00 1.7337E-01 4.400 3. 5351E+00 1. 1922E-01 9. 6412E-01 3.2516E-02 6.1772E+00 1.9398E-01 4.700 3.9605E+00 1 . 3322E-01 1. 0801E+00 3.6333E-02 6.8828E+00 2.1604E-01 5.000 4.4118E+00 1. 4804E-01 1.2032E+00 4.0373E-02 7.6345E+00 2.3952E-01

XceIEnergy" Calculation No. GEN-PI-082 Revision No. 0 Page No. 106 of 145 5.300 4.8889E+00 1 . 6366E-01 1.3333E+00 4. 4636E-02 8. 4318E+00 2. 6442E-01 5.600 5. 3915E+00 1.8010E-01 1.4704E+00 4 9118E-02 9.2744E+00 2. 9072E-01 5.900 5. 9194E+00 1. 9733E-01 1 .6144E+00 5.3816E-02 1 .0162E+01 3. 1841E-01 6.200 6.4724E+00 2 .1534E-01 1 .7652E+00 5.8730E-02 1 1094E+01 3.4748E-01 6.500 7.0503E+00 2. 3414E-01 1. 9228E+00 6.3857E-02 1 .2070E+01 3.7790E-01 6.800 7.6528E+00 2. 5371E-01 2. 0871E+00 6.9195E-02 1.3090E+01 4.0968E-01 7.100 8.2798E+00 2.7405E-01 2 .2581E+00 7.4741E-02 1.4153E+01 4.4280E-01 7.400 8.9310E+00 2. 9515E-01 2. 4357E+00 8.0495E-02 1 . 5259E+01 4.7725E-01 7.700 9.6063E+00 3.1700E-01 2 6199E+00 8.6453E-02 1. 6408E+01 5. 1301E-01 8.000 1. 0305E+01 3. 3959E-01 2. 8106E+00 9.2615E-02 1.7599E+01 5.5008E-01 8.300 1. 0836E+01 3. 5673E-01 2. 8274E+00 9 3176E-02 1. 8503E+01 5.7821;-1l 8.600 1. 1385E+01 3.7441E-01 2. 8447E+00 9.3755E-02 1 .9086E+01 5.9635E-01 8.900 1. 1950E+01 3. 9262E-01 2.8626E+00 9.4350E-02 1. 9571E+01 6.1145E-01 9.200 1.2533E+01 4.1138E-01 2 8810E+00 9.4963E-02 2. 0033E+01 6.2579E-01 9.500 1. 3133E+01 4.3066E-01 2. 9000E+00 9.5593E-02 2. 0495E+01 6.4016E-01 9.800 1. 3750E+01 4. 5047E-01 2. 9195E+00 9.6240E-02 2. 0966E+01 6.5481E-01 10.100 1. 4383E+01 4.7079E-01 2. 9395E+00 9.6903E-02 2 1449E+01 6. 6982E-b0 10.400 1. 5034E+01 4.9164E-01 2 . 9601E+00 9.7582E-02 2 .1945E+01 6.8522E-01 24.000 6.04 62E+01 1.9283E+00 4 .3964E+00 1 .4404E-01 5. 694 9E+01 1.7672E+00 45.500 1. 5981E+02 5. 0192E+00 5. 1127E+00 1. 6648E-01 8 8964E+01 2.7504E+00 96.000 1. 5981E+02 5. 0192E+00 5 .1127E+00 1 .6648E-01 8. 9630E+01 2.7708E+K0 720.000 1. 5981E+02 5 .0192E+00 5.1127E+00 1 . 6648E-01 8. 9630E+01 2.7708E+00 Worst Two-Hour Doses Exclusion Area Boundary Time Whole Body Thyroid TEDE (hr) (rem) (rem) (rem) 24.0 3.9705E-03 9.2418E+00 2.8753E-01

0 XceI Energy] Calculation No. GEN-PI-082 Rev ision No. 0 Page No. 107 of 145 Attachment 13.3 RADTRAD Output File PREAINGOO.oO

1. 1. 4#########t44###########i##i##4#############4######4########i##4######

RADTRAD Version 3.03 (Spring 2001) run on 5/25/2009 at 11:38:46

1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. f###4##########*###4###44########4#################

1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. i#####4####i##4########t#4##44 ####################4ti File information

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

Plant file = G:\Radtrad 3.03\Input\PI\GEN-PI-082\PREAINGOO.psf Inventory file = g:\radtrad 3.03\defaults\pirearcs def.txt Release file = G:\Radtrad 3.03\Defaults\PINGP NGRFT.txt Dose Conversion file = g:\radtrad 3.03\defaults\pingp fgll&12.txt

1. 1. 1. 1. 1. M4# ##### # # # #M## # # #####

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

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

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

it## # 4

1. # # 4 # i # # # #

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

1. #Mtt i # # # # ##44 #

Radtrad 3.03 4/15/2001 PINGP 1 & 2 Rod Ejection Accident AST Analysis - Noble Gas Release From Intact SGs Nuclide Inventory File:

g:\radtrad 3.03\defaults\pirearcs def.txt Plant Power Level:

1.8520E+03 Compartments:

3 Compartment 1:

RCS 3

5.2900E+03 0

0 0

0 0

Compartment 2:

Environment 2

0.OOOOE+00 0

0 0

0 0

Compartment 3:

Control Room 1

6.1315E+04 0

Xcel ner ylCalculation No. GEN-PI-082 Revision No. 0 Page No. 108 of 145 0

1 0

0 Pathways:

3 Pathway 1:

Environment to Control Room 2

3 2

Pathway 2:

Control Room to Environment 3

2 2

Pathway 3:

RCS to Environment 1

2 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1 1.0000E+00 g:\radtrad 3.03\defaults\pingpfgll&12.txt G:\Radtrad 3.03\Defaults\PINGPNG RFT.txt O.OOOOE+00 1

0.OOOOE+00 9.7000E-01 3.OOOOE-02 1.OOOOE+00 Overlying Pool:

0 o.OOOOE+00 0

0 0

0 Compartments:

3 Compartment 1:

0 1

0 0

0 0

0 0

0 Compartment 2:

0 1

0 0

0 0

XceI nergy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 109 of 145 0

0 0

Compartment 3:

1 1

0 0*.

0 0

3.6000E+03

.3 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 8.3300E-02 9. 9000E+01 9. 5000E+01 9. 5000E+01 7.2000E+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0

0 Pathways:

3 Pathway 1:

0 0

0 0

0 1

3 0.0OOOE+00 2.OOOOE+03 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 8.3300E-02 3.OOOOE+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 7.2000E+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0

0 0

0 0

0 Pathway 2:

0.

0 0

0 0

1 3

0.OOOOE+00 2.OOOOE+03 0.OOOOE+00 0.OOOOE+00 O.000OE+00 8.3300E-02 3.OOOOE+02 0.OOOOE+00 0.0000E+00 0.0000E+00 7.2000E+02 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0

0 0

0 0

0 Pathway 3:

0 0

0 0

0

Xcelfnergy]Calculation No. GEN-PI-082 Revision No. 0 Page No. 110 of 145 1

2 0.0000E+00 3.7600E-02 0.OOOOE+00 0.0000E+00 o.0000E+00 4 . 5500E+01 0.OOOOE+00 0.OOOOE+00 o.OOOOE+00 0.0000E+00 0

0 0

0 0

Dose Locations:

3 Location 1:

Exclusion Area Boundary 2

1 2

o.OOOOE+00 6.4900E-04 7.2000E+02 o.OOOOE+00 1

2 0.OOOOE+00 3.5.000E-04 7.2000E+02 0.OOOOE+00 0

Location 2:

Low Population Zone 2

1 5

0.OOOOE+00 1.77 OOE-04 8.OOOOE+00 3.99 OOE-05 2.4000E+01 7.12 OOE-06 9.6000E+01 1.04 OOE-06 7.2000E+02 0.00 OOE+00 1

4 0.0000E+00 3.50 OOE-04 8.0000E+00 1.80 OOE-04 2.4000E+01 2.30 OOE-04 7.2000E+02 0.00 00E+00 0

Location 3:

Control Room 3

0 1

2 0.OOOOE+00 3.5000E-04 7.2000E+02 0.OOOOE+00 1

4 0.OOOOE+00 1.0000E+00 2.4000E+01 6.OOOOE-01 9.6000E+01 4.OOOOE-01 7.2000E+02 0.OOOOE+00 Effective Volume Location:

1 6

0.OOOOE+00 1.8300E-02 2.OOOOE+00 1.4200E-02

XceI nergy' Calculation No. GEN-PI-082 Revision No. 0 Page No. III of 145 8OOOOE+00 6.3000E-03 2.4000E+01 4.2900E-03

9. 6000E+01 3.3800E-03 7.2000E+02 0.OOOOE+00 Simulation Parameters:

6 0.OOOOE+00 1.OOOOE-01 2,0000E+00 5.OOOOE-01 8.OOOOE+00 1.0000E+00 2.4000E+01 2.0000E+00 9.6000E+01 4.OOOOE+00 7.2000E+02 0.OOOOE+00 Output Filename:

G:\Radtrad 3.o65 1

1 1

0 0

End of Scenario File

S XceI Energy Calculation No. GEN-PI-082 Revision No. 0 Page No. 112 of 145 RADTRAD Version 3.03 (Spring 2001) run on 5/25/2009 at 11:38:46

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

Plant Description

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

Number of Nuclides = 60 Inventory Power = 1.0000E+00 MWth Plant Power Level = 1.8520E+03 MWth r

Number of compartments = 3 .4 Compartment information Compartment number 1 (Source term fraction = 1.OOOOE+00 Name: RCS Compartment volume = 5.2900E+03 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 1 Exit Pathway Number 3: RCS to Environment Compartment number 2 Name: Environment Compartment type is Environment Pathways into and out of compartment 2 Inlet Pathway Number 2: Control Room to Environment Inlet Pathway Number 3: RCS to Environment Exit Pathway Number 1: Environment to Control Room Compartment number 3 Name: Control Room Compartment volume 6.1315E+04 (Cubic feet)

Compartment type is Control Room Removal devices within compartment:

Filter(s)

Pathways into and out of compartment 3 Inlet Pathway Number 1: Environment to Control Room Exit Pathway Number 2: Control Room to Environment Total number of pathways = 3

XceIEnergy]CalculationNo. GEN-PI-082 Revision No. 0 Page No. 113 of 145

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

RADTRAD Version 3.03 (Spring 2001) run on 5/25/2009 at 11:38:46

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

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

Scenario Description

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

Radioactive Decay is enabled Calculation of Daughters is enabled Release Fractions and Timings GAP EARLY IN-VESSEL LATE RELEASE RELEASE MASS 0.003600 hr 0.0000 hrs 0.0000 hrs (gm)

NOBLES 1.0000E+00 0.OOOOE+00 0.OOOOE+00 3.696E+01 IODINE 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOE+00 CESIUM 0.OOOOE+00 0.OOOOE+00 0.000OE+00 0.OOOE+00 TELLURIUM 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0 OOOE+00 STRONTIUM 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0 OOOE+00 BARIUM 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0 OOOE+00 RUTHENIUM 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0 OOOE+00 CERIUM 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0 OOOE+00 LANTHANUM 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0 OOOE+00 Inventory Power = 1852. MWt Nuclide Group Specific half Whole Body Inhaled Inhaled Name Inventory life DCF Thyroid Effective (Ci/MWt) (s) (Sv-m3/Bq-s) (Sv/Bq) (Sv/Bq)

Kr-83m 1 3.487E-02 6.588E+03 1.500E-18 0. OOOE+00 0.OOOE+00 Kr-85 1 6.280E+00 3.383E+08 1.190E-16 0. OOOE+00 0.OOOE+00 Kr-85m 1 8.036E+01 1 613E+04 7.480E-15 0. OOOE+00 0.OOOE+00 Kr-87 1 1.575E+02 4 578E+03 4.120E-14 0. OOOE+00 0.OOOE+00 Kr-88 1 2.097E+02 1 022E+04 1.020E-13 0.OOOE+00 0.OOOE+00 Xe-131m 1 3.941E+00 1 028E+06 3.890E-16 0.OOOE+00 0.OOOE+00 Xe-133 1 7.027E+02 4.532E+05 1.560E-15 0.OOOE+00 0.OOOE+00 Xe-133m 1 2.157E+01 1.890E+05 1.370E-15 0.OOOE+00 0.OOOE+00 Xe-135 1 1.545E+02 3. 272E+04 1.190E-14 0.OOOE+00 0.OOOE+00 Xe-135m 1 1.499E+02 9. 174E+02 2.040E-14 0. OOOE+00 0.OOOE+00 Xe-138 1 5.734E+02 8. 502E+02 5.770E-14 0. OOOE+00 0.OOOE+00 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-135 Cs-135 1.00 none 0.00 none 0.00 Xe-135m Xe-135 1.00 none 0.00 none 0.00 Xe-138 Cs-138 1.00 none 0.00 none 0.00 Iodine fractions Aerosol 0.OOOOE+00 Elemental 9. 7000E-01 Organic 3.OOOOE-02 COMPARTMENT DATA

Energ CXce alculation No. GEN-PI-082 Revision No. 0 Page No. 114 of 145 Compartment number 1: RCS Compartment number 2: Environment Compartment number 3: Control Room Compartment Filter Data Time (hr) Flow Rate Filter Efficiencies (%)

(c fm) Aerosol Elemental Organic 0.OOOOE+00 3.6000E+03 0.OOOOE+00 0.OOOOE+00 o.OOOOE+00 8.3300E-02 3.6000E+0.3 9.9000E+01 9.5000E+01 9.5000E+01 7.2000E+02 3.6000E+03 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 PATHWAY DATA Pathway number 1: Environment to Control Room Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 2.OOOOE+03 0.0000E+00 0.0000E+00 0.0000E+00 8.3300E-02 3.0000E+02 0.0000E+00 0.OOOOE+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 2: Control Room to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 2.OOOOE+03 0.OOOOE+00 o.OOOE+00 o.OOOOE+00 8.3300E-02 3.0000E+02 0.OOOOE+00 o.OOOOE+00 o.OOOOE+00 7.2000E+02 0.0000E+00 o.OOOOE+00 o.OODOE+00 0.0000E+00 Pathway number 3: RCS to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(c fm) Aerosol Elemental Organic 0.OOOOE+00 3.7600E-02 0.OOOOE+00 0.OOOOE+00 0.0000E+00 4.5500E+01 0.OOOOE+00 0.OOOOE+00 O.OOOOE+00 0.OOOOE+00 LOCATION DATA Location Exclusion Area Boundary is in compartment 2 Location X/Q Data Time (hr) X/Q (s

• m^-3) 0.0000E+00 6.4900E-04 7.2000E+02 0.OOOOE+00, Location Breathing Rate Data Time (hr) Breathing Rate (m^3

• sec^-l) o.OOOOE+00 3.5000E-04 7.2000E+02 O.OOOOE+00 Location Low Population Zone is in compartment 2

Xce Energy] Calculation No: GEN-PI-082 Revision No. 0 Page No. 115 of 145 Location X/Q Data Time (hr) X/C (s

• m^-3) 0.000OE+00 1.7700E-04 8.0000E+00 3.9900E-05 2.4000E+01 7.1200E-06 9.6000E+01 1.0400E-06 7.2000E+02 0.0000E+00 Location Breathing Rat :e Data Time (hr) BrE*athing Rate (m^3

• sec^-I) o.OOOOE+00 3.5000E-04 8.OOOOE+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.0000E+00 Location Control Room is in compartment 3 Location X/Q Data Time (hr) X/C (S

• mA-3) 0.OOOOE+00 1.8300E-02 2.OOOOE+00 1.4200E-02 8.OOOOE+00 6.3000E-03 2.4000E+01 4.2900E-03 9.6000E+01 3.3800E-03 7.2000E+02 0.OOOOE+00 Location Breathing Ratte Data Time. (hr) BrEeathing Rate (m^3

• sec-i) o.OOOOE+00 3.5000E-04 7.2000E+02 0.0000E+00 Location Occupancy Factor Data Time (hr) Occupancy Factor 0.0000E+00 1.0000E+00 2.4000E+01 6.0000E-01 9.6000E+01 4.0000E-01 7.2000E+02 0.OOOOE+00 USER SPECIFIED TIME STEP DATA - SUPPLEMENTAL TIME STEPS Time Time step 0.0060E+00 1. 0OOOE-01 2.OOOOE+00 5. OOOE-01 8.OOOOE+00 1.0000E+00 2.4000E+01 2.OOOOE+00

9. 6000E+01 4 .000OE+00 7.2000E+02 0.OOOOE+00

[~XcelEnergylCalculation No. GEN-PI-082 Revision No. 0 Page No. 116 of 145

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Dose, Detailed model and Detailed Inventory Output

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Exclusion Area Boundary Doses:

Time (h) = 0.0036 Whole Body Thyroid TEDE Delta dose (rem) 2.3048E-04 1 .5109E-09 2.3050E-04 Accumulated dose (rem) 2.3048E-04 1. 5109E-09 2.3050E-04 Low Population Zone Doses:

Time (h) = 0.0036 Whole Body Thyroid TEDE Delta dose (rem) 6.2859E-05 4.1206E-10 6.2863E-05 Accumulated dose (rem) 6.2859E-05 4.1206E-10 6.2863E-05 Control Room Doses:

Time (h) 0.0036 Whole Body Thyroid TEDE Delta dose (rem) 6.3008E-07 1. 4968E-10 6. 3150E-07 Accumulated dose (rem) 6.3008E-07 1.4968E-10 6.3150E-07 Control Room Compartment Nuclide Inventory:

Time (h) 0.0036 Ci kg Atoms Decay Kr-83m 8. 5312E-07 4 .1349E-17 3. 0001E+08 2.9050E+05 Kr-85 1.5386E-04 3. 9215E-10 2 .7783E+15 5.2364E+07 Kr-85m 1.9677E-03 2. 3910E-13 1 .6940E+12 6.6982E+08 Kr-87 3.8511E-03 1. 3596E-13 9. 4109E+ll 1.3116E+09 Kr-88 5. 1330E-03 4. 0935E-13 2. 8013E+12 1.7475E+09 Rb-88 3.5200E-05 2. 9324E-16 2. 0067E+09 1.8114E+06 Xe-131m 9. 6551E-05 1.1527E-12 5 .2990E+12 3.2861E+07 Xe-133 1.7215E-02 9.1971E-11 4 .1644E+14 5.8592E+09 Xe-133m 5.2843E-04 1 . 1777E-12 5 .3324E+12 1.7985E+08 Xe-135 3.7857E-03 1.4824E-12 6.612 9E+12 1.2883E+09 Xe-135m 3.6405E-03 3 . 9965E-14 1.7828E+ll 1.2433E+09 Xe-138 1.3900E-02 1. 4456E-13 6. 3084E+ll 4.7488E+09 Cs-138 5. 2931E-05 1 .2509E-15 5.4587E+09 2.7375E+06 Control Room Transport Group Inventory:

Time (h) = 0.0036 Atmosphere Sump Noble gases (atoms) 3.2183E+15 0.OOOOE+00

XceI Energy] calculation No. GEN-PI-082 Revision No. 0 Page No. 117 of 145 Elemental I (atoms) 0.OOOOE+00 0.OOOOE+00 Organic I (atoms) 0.OOOOE+00 0.OOOOE+00 Aerosols (kg) 1.5441E-15 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 0.OOOOE+00 Total I (Ci) 0.OOOOE+00 Deposition Recirculating Time (h) = 0.0036 Surfaces Filter Noble gases (atoms) 0.OOOOE+00 0.OOOOE+00-Elemental I (atoms) 0.OOOOE+00 0.OOOOE+00 Organic I (atoms) 0.OOOOE+00 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Environment to Control Room Transport Group Inventory:

Pathway Time (h) = 0.0036 Filtered Transported Noble gases (atoms) 0.OOOOE+00 3.2259E+15 Elemental I (atoms) 0.OOOOE+00 0.OOOOE+00 Organic I (atoms) 0.OOOOE+00 0.0000E+00 Aerosols (kg) 0.OOOOE+00 2.0216E-16 Control Room to Environment Transport Group Inventory:

Pathway Time (h) = 0.0036 Filtered Transported Noble gases (atoms) 7.5617E+12 0.0000E+00 Elemental I (atoms) 0.0000E+00 0.OOOOE+00 Organic I (atoms) 0.0000E+00 0.0000E+00 Aerosols (kg) 7.1064E-19 0.OOOOE+00 Exclusion Area Boundary Doses:

Time (h) = 0.0833 Whole Body Thyroid TEDE Delta dose (rem) 1.0199E-02 4.7892E-07 1.0204E-02 Accumulated dose (rem) 1.0429E-02 4.8043E-07 1.0434E-02 Low Population Zone Doses:

Time (h) = 0.0833 Whole Body Thyroid TEDE Delta dose (rem) 2.7815E-03 1.3062E-07 2.7828E-03 Accumulated dose (rem) 2.8444E-03 1. 3103E-07 2.8456E-03 Control Room Doses:

Time (h) = 0.0833 Whole Body Thyroid TEDE Delta dose (rem) 7.6814E-04 1.0223E-06 7.7782E-04 Accumulated dose (rem) 7.6877E-04 1.0224E-06 7.7845E-04 Control Room Compartment Nuclide Inventory:

Time (h) = 0.0833 Ci kg Atoms Decay Kr-83m 3.4723E-05 1.6830E-15 1.2211E+10 3.7453E+08 Kr-85 6.4540E-03 1.6450E-08 1. 1655E+17 6. 8568E+10 Kr-85m 8. 1529E-02 9. 9069E-12 7. 0189E+13 8. 7154E+11 Kr-87 1.5468E-01 5.4607E-12 3.7799E+13 1. 6796E+12 Kr-88 2. 1117E-01 1.6841E-11 1. 1525E+14 2 .2655E+12 Rb-88 4.0857E-02 3.4036E-13 2. 3292E+12 1. 3399E+10 Xe-131m 4.0494E-03 4.8344E-11 2 .2224E+14 4.3025E+10

Xceff nergy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 118 of 145 Xe-133 7.2185E-01 3. 8564E-09 1.7462E+16 7. 6706E+12 Xe-133m 2.2143E-02 4. 9350E-11 2. 2345E+14 2.3538E+11 Xe-135 1.5868E-01 6.2138E-11 2. 7719E+14 1.6821E+12 Xe-135m 1. 2299E-01 1 . 3501E-12 6. 0227E+12 1. 4592E+12 Xe-138 4.6147E-01 4 .7992E-12 2.0943E+13 5.5242E+12 Cs-138 5.5395E-02 1.3091E-12 5. 7129E+12 2. 0975E+10 Control Room Transport Group Inventory:

Time (h) = 0.0833 Atmosphere Sump Noble gases (atoms) 1.3498E+17 0.OOOOE+00 Elemental I (atoms) 0.0000E+00 0.OOOOE+00 Organic I (atoms) 0.OOOOE+00 0.OOOOE+00 Aerosols (kg) 1.6495E-12 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 0.OOOOE+00 Total I (Ci) 0.OOOOE+00 Deposition Recirculating Time (h) = 0.0833 Surfaces Filter Noble gases (atoms) 0.OOOOE+00 0.OOOOE+00 Elemental I (atoms) 0.OOOOE+00 0.OOOOE+00 Organic I (atoms) 0..OOOOE+00 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Environment to Control Room Transport Group Inventory:

Pathway Time (h) 0.0833 Filtered Transported Noble gases (atoms) 0.OOOOE+00 1.4606E+17 Elemental I (atoms) 0.OOOOE+00 0.OOOOE+00 Organic I (atoms) 0.OOOOE+00 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 6.4281E-14 Control Room to Environment Transport Group Inventory:

Pathway Time (h) = 0.0833 Filtered Transported Noble gases (atoms) 1.1062E+16 0.OOOOE+00 Elemental I (atoms) 0.OOOOE+00 0.OOOOE+00 Organic I (atoms) 0.0000E+00 0.OOOOE+00 Aerosols (kg) 4.9745E-15 0.OOOOE+00 Exclusion Area Boundary Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.2576E-01 1.2258E-03 3.4164E-01 Accumulated dose (rem) 3.3619E-01 1.2262E-03 3. 5207E-01 Low Population Zone Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (r :em) 8.8843E-02 3.3430E-04 9.3175E-02 Accumulated close (rem) 9.1687E-02 3.3443E-04 9.6020E-02 Control Room Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.2524E-01 6.3690E-03 2.1666E-01 Accumulated dose (rem) 1.2601E-01 6. 3701E-03 2.1744E-01

ff Energy] Calculation No. GEN-PI-082 Revision No 0 Page No1 Control Room Compartment Nuclide Inventory:

Time (h) = 8.0000 Ci kg Atoms Decay Kr-83m 8.5646E-06' 4.1511E-16 3. 0119E+09 3. 6877E+10 Kr-85 3. 1931E-02 8.1386E-08 5.7661E+17 2.6940E+13 Kr-85m 1.1850E-01 1.4399E-11 1. 0202E+14 1. 8002E+14 Kr-87 1.0227E-02 3. 6105E-13 2.4992E+12 1.0818E+14 Kr-88 1.5131E-01 1.2067E-11 8.2577E+13 3. 3935E+14 Rb-88 8.9349E-02 7.4434E-13 5. 0937E+12 1.3496E+14 Xe-131m 1.9652E-02 2. 3462E-10 1.0786E+15 1. 6720E+13 Xe-133 3.4233E+00 1.8289E-08 8.2809E+16 2.9421E+15 Xe-133m 9.8679E-02 2.1992E-10 9. 9578E+14 8. 7163E+13 Xe-135 4.3890E-01 1.7187E-10 7 6666E+14 4. 8763E+14 Xe-135m 2.7063E-10 2.9709E-21 1.3253E+04 1. 1328E+13 Cs-138 6.5357E-06 1.5445E-16 6.7402E+08 1. 8973E+13 Control Room ,Transport Group Inventory:

Time (h) = 8.0000 Atmosphere Sump Noble gases (atoms) 6.6245E+17 0.OOOOE+00 Elemental .I (atoms) 0.0000E+00 0.0000E+00 Organic I (atoms) 0.0000E+00 0.OOOOE+00 Aerosols (kg) 7.4449E-13 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 0.O000E+00 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 0.0000E+00 Total I (Ci) 0.OOOOE+00 Deposition Recirculating Time (h) 8.0000 Surfaces Filter Noble gases (atoms) 0.OOOOE+00 0.0000E+00 Elemental I (atoms) 0.0000E+00 0.0000E+00 Organic I (atoms) 0.OOOOE+00 0.0000E+00 Aerosols (kg) 0.0000E+00 5.0992E-11 Environment to Control Room Transport Group Inventory:

Pathway Time (h) = 8.0000 Filtered Transported Noble gases (atoms) 0.OOOOE+00 1.9025E+18 Elemental I (atoms) 0.0000E+00 0.OOOOE+00 Organic I ('atoms) 0.0000E+00 0.OOOOE+00 Aerosols (kg) 0.0000E+00 2.1586E-11 Control Room to Environment Transport Group Inventory:

Pathway Time (h) = 8.0000 Filtered Transported Noble gases (atoms) 1.2359E+18 0.0000E+00 Elemental I (atoms) 0.0000E+00 0.0000E+00 Organic I (atoms) 0.0000E+00 0.0000E+00 Aerosols (kg) 4.2972E-12 0 .0000E+00 Exclusion Area Boundary Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 8.9098E-02 1.8876E-04 9. 2212E-02 Accumulated dose (rem) 4.2528E-01 1.4150E-03 4.4429E-01 Low Population Zone Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE

Xcelfnergyl Calculation No. GEN-PI-082 Revision No. 0 Page No. 120 of 145 Delta dose (rem) 5.4777E-03 5.9683E-06 5. 5761E-03 Accumulated dose (rem) 9.7165E-02 3.4040E-04 1;0160E-01 Control Room Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.8078E-02 1. 1062E-03 5.6327E-02 Accumulated dose (rem) 1.6409E-01 7.4763E-03 2 . 7377E-01 Control Room Compartment Nuclide Inventory:

Time (h) 24.0000 Ci kg Atoms Decay Kr-83m 9.4479E-09 4. 5792E-19 3. 3225E+06 3. 9171E+10 Kr-85 1.5092E-02 3. 8468E-08 2. 7254E+17 6.6142E+13 Kr-85m 4.7119E-03 5.7256E-13 4. 0565E+12 2 4200E+14 Kr-87 7.8849E-07 2. 7837E-17 1.9269E+08 1. 1020E+14 Kr-88 1.4405E-03 1.1488E-13 7. 8613E+ll 3.9675E+14 Rbý-88 3.8630E-03 3.2181E-14 2. 2023E+ll 1.5297E+14 Xe-131m 8.9357E-03 1. 0668E-10 4.9042E+14 4.0438E+13 Xe-133 1.4853E+00 7.9349E-09 3.5928E+16 6. 9897E+15 Xe-133m 3.7765E-02 8.4164E-11 3.8109E+14 1. 9771E+14 Xe-135 6.124 6E-02 2.3983E-11 1.0699E+14 8.2188E+14 Control Room Transport Group Inventory:

Time (h) = 24.0000 Atmosphere Sump Noble gases (atoms) 3.0945E+17 0.OOOOE+00 Elemental I (atoms) 0.OOOOE+00 0.OOOOE+00 Organic I (atoms) 0.OOOOE+00 0.OOOOE+00 Aerosols (kg) 3.2181E-14 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 0.OOOOE+00 Total I (Ci) 0.OOOOE+00 Deposition Recirculating Time (h) = 24.0000 Surfaces Filter Noble gases (atoms) 0.OOOOE+00 0.OOOOE+00 Elemental I (atoms) o.ooo0E+00 0.OOOOE+00 Organic I (atoms) 0.OOOOE+00 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 5.6732E-11 Environment to Control Room Transport Group Inventory:

Pathway Time (h) = 24.0000 Filtered Transported Noble gases (atoms) 0.OOOOE+00 3.3526E+18 Elemental I (atoms) 0.OOOOE+00 0.OOOOE+00 Organic I (atoms) 0.OOOOE+00 0.OOOOE+00 Aerosols (kg) O.OOOOE+00 2.2804E-11 Control Room to Environment Transport Group Inventory:

Pathway Time (h) = 24.0000 Filtered Transported Noble gases (atoms) 3.0345E+18 0.OOOOE+00 Elemental I (atoms) 0.OOOOE+00 0.OOOOE+00 Organic I (atoms) O.OOOOE+00 0.OOOOE+00 Aerosols (kg) 4.7804E-12 0.OOOOE+00 Exclusion Area Boundary Doses:

XcelEnergyl Calculation No. GEN-PI-082 Rev ision No. 0 Page No. 121 of 145 Time (h) = 45.5000 Whole Body Thyroid TEDE Delta dose (rem) 4.4986E-02 7.4677E-06 4. 5109E-02 Accumulated dose (rem) 4.7027E-01 1.4225E-03 4.8940E-01 Low Population Zone Doses:

Time (h) = 45.5000 Whole Body Thyroid TEDE Delta dose (rem) 4.9353E-04 5.3837E-08 4.9442E-04 Accumulated dose (rem) 9.7658E-02 3.4045E-04 1. 0209E-01 Control Room Doses:

Time (h) = 45.5000 Whole Body Thyroid TEDE Delta dose (rem) 6.8497E-03 1.8003E-05 7.1466E-03 Accumulated dose (rem) 1.7094E-01 7.4943E-0.3 2. 8091E-01 Control Room Compartment.Nuclide Inventory:

Time (h) = 45.5000 Ci kg Atoms Decay Kr-85 1.0087E-02 2.5709E-08 1. 8215E+17 9.7049E+13 Kr-85m 1. 1313E-04 1.3747E-14 9. 7396E+10 2.4502E+14 Kr-88 5.0657E-06 4.0399E-16 2.7646E+09 3. 9737E+14 Rb-88 7.3682E-06 6. 1382E-17 4.2006E+08 1. 5304E+14 Xe-131m 5.6693E-03 6.7684E-11 3.1115E+14 5.8290E+13 Xe-133 8. 8442E-01 4.7249E-09 2.1394E+16 9. 8695E+15 Xe-133m 1.9006E-02 4 .2358E-11 1. 9180E+14 2.6548E+14 Xe-135 7.9458E-03 3. 1114E-12 1. 3880E+13 8.8596E+14 Control Room Transport Group Inventory:

Time (h) = 45.5000 Atmosphere Sump Noble gases (atoms) 2.0406E+17 0.OOOOE+00 Elemental I (atoms) 0.0000E+00 0.OOOOE+00 Organic I (atoms) 0.0000E+00 0.0000E+00 Aerosols (kg) 6.1382E-17 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 0.OOOOE+00 Total I (Ci) 0.0000E+00 Deposition Recirculating Time (h) = 45.5000 Surfaces Filter Noble gases (atoms) 0.0000E+00 0.0000E+00 Elemental I (atoms) O.OOOOE+00 O.OOOOE+00 Organic I (atoms) 0.0000E+00 0.OOOOE+00 Aerosols (kg) 0.0000E+00 5.6780E-11 Environment to Control Room Transport Group Inventory:

Pathway Time (h) = 45.5000 Filtered Transported Noble gases (atoms) 0.0000E+00 4.6525E+18 Elemental I (atoms) 0.0000E+00 0.0000E+00 Organic I (atoms) 0.OOOOE+00 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 2.2837E-11 Control Room to Environment Transport Group Inventory:

Pathway Time (h) = 45.5000 Filtered Transported Noble gases (atoms) 4.4367E+18 0.0000E+00 Elemental I (atoms) 0.OOOOE+00 0.0000E+00

Xcel nergy]Calculation No. GEN-PI-082 Revision No. 0 Page No. 122 of Organic I (atoms) 0.OOOOE+00 0.OOOOE+00 Aerosols (kg) 4.7844E-12 0.OOOOE+00 Exclusion Area Boundary Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.OOOOE+00 0.0000E+00 0.OOOOE+00 Accumulated dose (rem) 4.7027E-01 1.4225E-03 4. 8940E-01 Low Population Zone Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Accumulated dose (rem) 9.7658E-02 3.4045E-04 1. 0209E-01 Control Room Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 8.1822E-04 2. 6791E-08 8.1866E-04 Accumulated dose (rem) 1.7176E-01 7.4943E-03 2. 8173E-01 Control Room Compartment Nuclide Inventory:

Time (h) 96.0000 Ci kg Atoms Decay Kr-85 3.6740E-09 9.364 4E-15 6. 6345E+10 1.0103E+14 Xe-131m 1. 8275E-09 2. 1818E-17 1.0030E+08 6.0509E+13 Xe-133 2. 4524E-07 1.3102E-15 5.9323E+09 1.0212E+16 Xe-133m 3. 5559E-09 7. 9249E-18 3.5883E+07 2. 7266E+14 Xe-135 6. 1560E-11 2.4106E-20 1.0753E+05 8.8845E+14 Control Room Transport Group Inventory:

Time (h) = 96.0000 Atmosphere Sump Noble gases (atoms) 7.2414E+10 0.OOOOE+00 Elemental I (atoms) 0.OOOOE+00 0.OOOOE+00 Organic I (atoms) 0.OOOOE+00 0.OOOOE+00 Aerosols (kg) 1.8127E-28 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 0.OOOOE+00 Total I (Ci) 0.OOOOE+00 Deposition Recirculating Time (h) = 96.0000 Surfaces Filter Noble gases (atoms) 0.OOOOE+00 0.OOOOE+00 Elemental I (atoms) 0.OOOOE+00 0.OOOOE+00 Organic I (atoms) 0.OOOOE+00 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 5.6780E-11 Environment to Control Room Transport Group Inventory:

Pathway Time (h) = 96.0000 Filtered Transported Noble gases (atoms) 0.OOOOE+00 4.6525E+18 Elemental I (atoms) 0.OOOOE+00 0.0000E+00 Organic I (atoms) 0.OOOOE+00 0.0000E+00 Aerosols (kg) 0.OOOOE+00 2.2837E-11 Control Room to Environment Transport Group Inventory:

Pathway Time (h) = 96.0000 Filtered Transported

' XcelfnerIgy Calculation No. GEN-PI-082 Revision No. 0 Page No. 123 of 145 Noble gases (atoms) 4. 6404E+18 o.OOOOE+00 Elemental I (atoms) o.OOOOE+00 0.0000E+60 Organic I (atoms) o.OOOOE+00 o.OOOOE+00 Aerosols (kg) 4.7844E-12 o.OOOOE+00 Exclusion Area Boundary Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Accumulated dose (rem) 4.7027E-01 1.4225E-03 4.8940E-01 Low Population Zone Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Accumulated dose (rem) 9.7658E-02 3.4045E-04 1. 0209E-01 Control Room Doses:

Time (h) = 720.0000 Whole.Body Thyroid TEDE Delta dose (rem) 1.4271E-10 3. 9371E-20 1. 4271E-10 Accumulated dose (rem) 1.7176E-01 7.4943E-03 2.8173E-01 Control Room Compartment Nuclide Inventory:

Time (h) = 720.0000 Ci kg Atoms Decay Control Room Transport Group Inventory:

Time (h) = 720.0000 Atmosphere Sump Noble gases (atoms) 1.8404E-69 0.OOOOE+00 Elemental I (atoms) 0.OOOOE+00 0OOOOE+00 Organic I (atoms) 0.OOOOE+00 0.OOOOE+00 Aerosols (kg) 3.6324-174 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 0.OOOOE+00 Total I (Ci) 0.OOOOE+00 Deposition Recirculating Time (h) = 720.0000 Surfaces Filter Noble gases (atoms) 0.OOOOE+00 0.OOOOE+00 Elemental I (atoms) 0.OOOOE+00 0.OOOOE+00 Organic I (atoms) 0.OOOOE+00 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 5.6780E-11 Environment to Control Room Transport Group Inventory:

Pathway Time (h) =.720.0000 Filtered Transported Noble gases (atoms) 0.OOOOE+00 4.6525E+18 Elemental I (atoms) 0.OOOOE+00 0.OOOOE+00 Organic I (atoms) 0.OOOOE+00 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 2.2837E-11 Control Room to Environment Transport Group Inventory:

Pathway Time (h) = 720.0000 Filtered Transported Noble gases (atoms) 4. 6404E+18 0.OOOOE+00 Elemental I (atoms) 0.OOOOE+00 0.OOOOE+00 Organic I (atoms) 0.OOOOE+00 0.OOOOE+00

XceIEnergy] Calculation No. GEN-PI-082 -Revision No. 0 Page No. 124 of 145 Aerosols (kg) 4.7844E-12 0.0000E+00 840 1-131 Summary

1. 1. # ## ##8#8## #8# ##### #88### ## #888888888 # #8##88884#8##88#88 #888###88####

RCS Environment Control Room Time (hr) 1-131 (Curies) 1-131 (Curies) 1-131 (Curies) 0.000 0. 0000E+00 0.OOOOE+00 0.OOOOE+00 0.004 0. 0000E+00 0.OOOOE+00 0.OOOOE+00 0.083 0. 000OE+00 0.OOOOE+00 0.OOOOE+00 0.400 0 OOOOE+00 0.0000E+00 0.OOOOE+00 0.700 0. 0000E+00 0.0000E+00 0.OOOOE+00 1.000 0 OOOOE+00 0.OOOOE+00 0.0000E+00 1.300 0 OOOOE+00 0.OOOOE+00 0.OOOOE+00 1.600 o. 0000E+00 0.OOOOE+00 0.OOOOE+00 1.900 0 OOOOE+00 0.0OOOE+00 0.0000E+00 2.200 0. 0000E+00 0.OOOOE+00 0.OOOOE+00 2.500 0. 0000E+00 0.OOOOE+00 0.OOOOE+00 2.800 0 OOOOE+00 0.0000E+00 0.0000E+00 3.100 0 OOOOE+00 0.0000E+00 0.OOOOE+00 3.400 0 OOOOE+00 0.OOOOE+00 0.0000E+00 3.700 0. 0000E+00 0,.0000E+00 0.0000E+00 4.000 0 OOOOE+00 0.OOOOE+00 0.OOOOE+00 4.300 0.0000E+00 O.OOOOE+00 0.0000E+00 4 .600 0. 0000E+00 0.0000E+00 0.0000E+00 4.900 0. 0000E+00 0.OOOOE+00 0.OOOOE+00 5.200 0.OOOOE+00 0.OOOOE+00 0.0000E+00 5.500 0.0000E+00 0.0000E+00 0.0000E+00 5.800 0 OOOOE+C0 0.0000E+00 0.OOOOE+00 6.100 0 OOOOE+00 0.OOOOE+00 0.OOOOE+00 6.400 0 OOOOE+00 0.OOOOE+00 0.OOOOE+00 6.700 0. 0000E+00 0.OOOOE+00 0.OOOOE+00 7.000 0 OOOOE+00 0.OOOOE+00 0.OOOOE+00 7.300 0 OOOOE+00 0.0000E+00 0.OOOOE+00 7.600 0. 000OE+00 0.OOOOE+00 0.0000E+00 7.900 0. 0000E+00 0.OOOOE+00 0.0000E+00 8.000 0 OOOOE+00 0.0000E+00 0.0000E+00 8.300 0 OOOOE+00 0.OOOOE+00 0. 0000E+00 8.600 0 OOOOE+00 0.0000E+00 0.00O0E+00 8.900 0.0000E+00 0.0000E+00 0.OOOOE+00 9.200 0.OOOOE+00 0.0000E+00 0.OOOOE+00 9.500 0.0000E+00 0.0000E+00 0.OOOOE+00 9.800 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 10.100 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 10.400 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 24.000 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 45.500 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 96.000 0.000OE+00 0.0000E+00 0.0000E+00 720.000 0.0000E+00 0.OOOOE+00 0.OOOOE+00 8###############8######################8#8############88##############

Cumulative Dose Summary

1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. ##### #8#88#######################8####8##############

ExclUsion Area Bounda Low Population Zone Control Room Time Thyroid TEDE Thyroid TEDE Thyroid TEDE (hr) (rem) (rem) (rem) (rem) (rem) (rem)

Xce Energy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 125 of 145 0.000 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.004 1. 5109E-09 2.3050E-04 4 .1206E-10 6.2863E-05 1. 4968E-10 6. 3150E-07 0.083 4.8043E-07 1.0434E-02 1.3103E-07 2.8456E-03 1. 0224E-06 7.7845E-04 0.400 9. 4106E-05 5. 0407E-02 2.5665E-05 1.3747E-02 3. 6427E-04 1. 1128E-02 0.700 2. 3310E-04 8. 4698E-02 6.3573E-05 2.3099E-02 9. 0293E-04 2. 3711E-02 1.000 3. 6898E-04 1. 1445E-01 1.0063E-04 3. 1212E-02 1. 4276E-03 3.6522E-02 1.300 4. 8694E-04 1 . 3999E-01 1.3280E-04 3.8180E-02 1. 8947E-03 4.8999E-02 1.600 5.8544E-04 1 . 6202E-01 1.5967E-04 4.4188E-02 2 .3083E-03 6. 1108E-02 1 .900 6.6709E-04 1. 8122E-01 1. 8193E-04 4.9424E-02 2. 6810E-03 7.2902E-02 2.200 7.3525E-04 1. 9814E-01 2.0052E-04 5.4039E-02 3.0174E-03 8.4266E-02 2.500 7. 9291E-04 2 .1323E-01 2.1625E-04 5. 8154E-02 3.3154E-03 9. 4916E-02 2.800 8.4245E-04 2. 2683E-01 2.2976E-04 6. 1862E-02 3.5890E-03 1 . 0501E-01

3. 100 8.8566E-04 2. 3918E-01 2.4154E-04 6.5230E-02 3.8440E-03 1. 1462E-01 3.400 9.2386E-04 2 .5047E-01 2. 5196E-04 6.8311E-02 4.0830E-03 1. 2377E-01 3.700 9.5802E-04 2 6087E-01 2. 6128E-04 7.114 6E-02 4.3076E-03 1. 3247E-01 4.000 9.8884E-04 2. 7047E-01 2.6968E-04 7.3766E-02 4. 5190E-03 1. 4074E-01 4.300 1.0169E-03 2 .7939E-01 2.7733E-04 7. 6196E-02 4.7179E-03 1. 4860E-01 4.600 1.0425E-03 2.8768E-01 2.8431E-04 7.8457E-02 4.9050E-03 1. 5605E-01 4.900 1.0660E-03 2.9541E-01 2. 9072E-04 8.0565E-02 5. 0810E-03 1. 6312E-01 5.200 1.0876E-03 3. 0263E-01 2. 9662E-04 8.2535E-02 5.2465E-03 1. 6982E-01 5.500 1.1076E-03 3. 0939E-01 3. 0207E-04 8.4380E-02 5. 4019E-03 1 .7617E-01 5.800 1.1261E-03 3.1573E-01 3. 0711E-04 8. 6108E-02 5.5478E-03 1. 8218E-01 6.100 1. 1432E-03 3.2168E-01 3. 1178E-04 8.7731E-02 5.6846E-03 1 . 8787E-01 6.400 1. 1591E-03 3.2727E-01 3. 1610E-04 8.9256E-02 5. 8129E-03 1. 9325E-01 6.700 1.1738E-03 3.3253E-01 3.2012E-,04 9. 0691E-02 5.9330E-03 1 . 9835E-01 7.000 1.1874E-03 3.3749E-01 3.2384E-04 9.2042E-02 6.0454E-03 2 . 0317E-01 7.3300 1.2001E-03 3.4216E-01 3.2729E-04 9. 3316E-02 6. 1506E-03 2 .0773E-01 7.600 1.2118E-03 3.4657E-01 3.3050E-04 9. 4519E-02 6.2489E-03 2 .1204E-01 7.900 1.2228E-03 3.5074E-01 3.3348E-04 9.5656E-02 6.3408E-03 2 1613E-01 8.000 1.2262E-03 3.5207E-01 3.3443E-04 9.6020E-02 6. 3701E-03 2 1744E-01 8.300 1.2361E-03 3.5594E-01 3.3474E-04 9.6253E-02 6. 4501E-03 2. 2111E-01

8. 600 1.2453E-03 3.5961E-01 3.3503E-04 9.6474E-02 6. 5201E-03 2. 2439E-01 8.900 1.2539E-03 3.6308E-01 3.3530E-04 9.6683E-02 6.5823E-03 2. 2736E-01 9.200 1.2618E-03 3.6638E-01 3.3555E-04 9.6882E-02 6.6379E-03 2 . 3006E-01 9.500 1.2692E-03 3.6951E-01 3.3579E-04 9. 7071E-02 6.6876E-03 2 .3251E-01 9.800 1.2761E-03 3.7248E-01 3.3600E-04 9.7251E-02 6.7322E-03 2. 3474E-01 10.100 1.2824E-03 3.7531E-01 3.3620E-04 9.7422E-02 6.7723E-03 2 . 3678E-01 10.400 1.2884E-03 3.7801E-01 3.3639E-04 9.7584E-02 6.8084E-03 2. 3866E-01 24.000 1. 4150E-03 4.4429E-01 3.4040E-04 1.0160E-01 7.4763E-03 2 .7377E-01 45.500 1.4225E-03 4.8940E-01 3.4045E-04 1. 0209E-01 7.4943E-03 2 . 8091E-01 96.000 1.4225E-03 4.8940E-01 3.4045E-04 1 . 0209E-01 7.4943E-03 2.8173E-01 720.000 1.4225E-03 4.8940E-01 3.4045E-04 1. 0209E-01 7.4943E-03 2.8173E-01

1. 1. 1. 1. 1. 1. • • 1. 1. 1. 1. 1. 1. 1. 1. 1. W##################o#T##w#o###o##us######e#s#######

Worst Two-Hour Doses Exclusion Area Boundary Time Whole Body Thyroid TEDE (hr) (rem) (rem) (rem) 0.0 1.7920E-01 6.8981E-04 1.8686E-01

ft_ XceIEnergy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 126 of 145 Attachment 13.4 RADTRAD Output File PREAINLQ00.o0

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

RADTRAD Version 3.03 (Spring 2001) run on 5/25/2009 at 11:44:15

1. 1. 1. 1. 1. 1. 1. 1. tffff######ffff#####################################################

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

File information

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

Plant file = G:\Radtrad 3.03\Input\PI\GEN-PI-082\PREAINLQOO.psf Inventory file = g:\radtrad 3.03\defaults\pirealiq_def.txt Release file = G:\Radtrad 3.03\Defaults\PINGP Iodine RFT.txt Dose Conversion file = g:\radtrad 3.03\defaults\pingp~fgll&12.txt

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

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

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

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

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

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

Radtrad 3.03 4/15/2001 PINGP 1 &'2 Rod Ejection Accident AST Analysis -SG Liquid Iodine Released From Intact SGs Nuclide Inventory File:

g:kradtrad 3.03\defaultskpirea-liq-def.txt Plant Power Level:

1.8520E+03 Compartments:

3 Compartment 1:

Intact SG 3

3.4380E+03 0

0 0

0 0

Compartment 2:

Environment 2

0.0000E+00 0

0 0

0 0

Compartment 3:

Control Room 1

@ XceIEnergy]CalculationNo. GEN-PI-082 Revision No. 0 Page No. 127 of 145

6. 1315E+04 0

0 1

0 0

Pathways:

3.

Pathway 1:

Intact SG to Environment 1

2 2

Pathway 2:

Environment to Control Room 2

3 2

Pathway 3:

Control Room to Environment 3

2 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1 1.0000E+00 g:\radtrad 3.03\defaults\pingp fgll&12.txt G:\Radtrad 3.03\Defaults\PINGPIodineRFT.txt o.OOOOE+00 1

0.OOOOE+00 9.7000E-01 3.OOOOE-02 1.0000E+00 Overlying Pool:

0 o.OOOOE+00 0

0 0

0 Compartments:

3 Compartment 1:

0 1

0 0

0 0

0 0

0 Compartment 2:

0 1

0 0

XcelEnergylCalculationNo. GEN-PI-082 Revision No. 0 Page No. 128 of 145 0

0 0

0 Compartment 3:

1 1

3.6000E+03 3

0.0000E+00 0.OOOOE+00 0.OOOOE+00 o.OOOOE+00 8.3300E-02 9. 9000E+01 9. 5000E+01 9. 5000E+01 7.2000E+02 0 0.OOOOE+00 o.OOOOE+00 0.OOOOE+00 0

Pathways:

3 Pathway 1:

0 0

0 0

0 1

5 0.0000E+00 3.9420E-01 o.OOOOE+00 0.OOOOE+00 o.OOOOE+00 2.0000E+00 2.3610E-01 0.OOOOE+00 0.OOOOE+00 o.OOOOE+00 8.0000E+00 1.7340E-01 0.OOOOE+00 o.OOOOE+00 o.OOOOE+00 2.4000E+01 1. 3980E-01 0.OOOOE+00 0.OOOOE+00 o0OOOOE+00 4.5500E+01 0.OOOOE+00 o.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0

0 0

Q _j 5

0 0

Pathway 2:

0 0

0 0

0 1

2.OOOOE+00 8.3300E-02 2.OOOOE+03 0.0000E+00 0.OOOOE+00 0.OOOOE+00 7.2000E+02 3.OOOOE+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0

0 0

0 0

Pathway 3:

0

Q S XceI nergy- Calculation No. GEN-PI-082 Revision No. 0 Page No. 129 of 145 0

0 0

0 1

3 0.0000E+O0 2.0000E+03 0.0000E+00 o.OOOOE+00 o.OOOOE+00 8 *3300E-02 3.0000E+02 0.OOOOE+00 o.OOOOE+00 o.OOOOE+00 7.2000E+02 0.0000E+OO 0-0000E+00 0.OOOOE+00 0.0000E+00 0

0 0

0 0

Dose Locations:

3 Location 1:

Exclusion Area Boundary 2

2 o.OOOOE+00 6.4900E-04 7.2000E+02 o.OOOOE+00 1

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

Location 2:

Low Population Zone 2

1 5

0.OOOOE+00 1.7700E-04 8.OOOOE+00 3.9900E-05 2.4000E+01 7.1200E-06

9. 6000E+01 1.0400E-06 7.2000E+02 0.OOOOE+00 1

4 o.OOOOE+00 3.5000E-04 8.0000E+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 o.OOOOE+00 0

Location 3:

Control Room 3

0 1

2 0.OOOOE+00 3.5000E-04 7.2000E+02 0.OOOOE+00 1

4 o.OOOOE+00 1.OOOOE+00 2.4000E+01 6. OOOOE-01 9.6000E+01 4.OOOOE-01 7.2000E+02 0.OOOOE+00

4 Xcefnergy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 130 of 145 Effective Volume Location:

1 6

O.OOOE+00 1.8300E-02 2.OOOOE+00 1.4200E-02 8.OOOOE+00 6.3000E-03 2.4000E+01 4.2900E-03 9.*6000E+01 3.3800E-03 7.2000E+02 0.0000E+00 Simulation Parameters:

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

G:\Radtrad 3.o66

.1 1

1 0

0 End of Scenario File

XceI Enery] Calculation No. GEN-PI-082 Revision No. 0 Page No. 131 of 145

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

RADTRAD Version 3.03 (Spring 2001) run on 5/25/2009 at 11:44:15

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

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

Plant Description

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

Number of Nuclides = 60 Inventory Power = 1.OOOOE+00 MWth Plant Power Level = 1.8520E+03 MWth Number of compartments = 3 Compartment information Compartment number 1 (Source term fraction = 1.OOOOE+00 Name: Intact SG Compartment volume = 3.4380E+03 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 1 Exit Pathway Number 1: Intact SG to Environment Compartment number 2 Name: Environment Compartment type is Environment Pathways into and out of compartment 2 Inlet Pathway Number 1: Intact SG to Environment Inlet Pathway Number 3:-Control Room to Environment Exit Pathway Number 2: Environment to Control Room Compartment number 3 Name: Control Room Compartment volume = 6.1315E+04 (Cubic feet)

Compartment type is Control Room Removal devices within compartment:

Filter(s)

Pathways into and out of compartment 3 Inlet Pathway Number 2: Environment to Control Room Exit Pathway Number 3: Control Room to Environment Total number of pathways = 3

XceI nergy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 132 of 145 44###################################4##4#####4#######4################

RADTRAD Version 3.03 (Spring 2001) run on 5/25/2009 at 11:44:15

1. 1. 1. 44###*############4###############4####444#####4###4#4#4#44####4###4 4##########44##44#4##############4#44######4##########44#################

Scenario Description

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

Radioactive Decay is enabled Calculation of Daughters is enabled Release Fractions and Timings GAP EARLY IN-VESSEL LATE RELEASE RELEASE MASS 0.003600 hr 0.0000 hrs 0.0000 hrs (gm)

NOBLES 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 IODINE 1.OOOOE+00 0.OOOOE+00 0.0000E+00 8.142E-05 CESIUM 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.OOOE+00 TELLURIUM 0.0000E+00 0.OOOOE+00 0.OOOOE+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.OOOOE+00 0.000E+00 RUTHENIUM 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOE+00 CERIUM 0.OOOOE+00 0.0000E+00 0.0000E+00 0.000E+00 LANTHANUM 0.OOOOE+00 0.0000E+00 0.0000E+00 0.000E+00 Inventory Power = 1852. MWt Nuclide Group Specific half Whole Body Inhaled Inhaled Name Inventory life DCF Thyroid Effective (Ci/MWt) (s) (Sv-m3/Bq-s) (Sv/Bq) (Sv/Bq) 1-131 2 4.500E-03 6.947E+05 1.820E-14 2.920E-07 8.890E-09 1-132 2 4.940E-03 8. 280E+03 1.120E-13 1.740E-09 1.030E-10 1-133 2 6.846E-03 7.488E+04 2.940E-14 4.860E-08 1.580E-09 1-134 2 1.027E-03 3. 156E+03 1.300E-13 2. 880E-10 3.550E-11 1-135 2 3.882E-03 2.380E+04 8.294E-14 8.460E-09 3.320E-10 Nuclide Daughter Fraction Daughter Fraction Daughter Fraction 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 Iodine fractions Aerosol = 0.OOOOE+00 4 Elemental = 9.7000E-01 Organic = 3.0000E-02 COMPARTMENT DATA Compartment number 1: Intact SG Compartment number 2: Environment Compartment number 3: Control Room Compartment Filter Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.0000E+00 3.6000E+03 0.0000E+00 0.OOOOE+00 0.0000E+00 8.3300E-02 3.6000E+03 9. 9000E+01 9.5000E+01 9.5000E+01

Xcelne y Calculation No..GEN-PI-082 Revision No. 0 Page No. 133 of 145 7.2000E+02 3.6000E+03 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 PATHWAY DATA Pathway number 1: Intact SG to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies C%)

(cfm) Aeros ol Elemental Organic 0.OOOOE+00 3. 9420E-01 0.OOO0E +00 0.OOOOE+00 0.OOOOE+00 2.OOOOE+00 2. 3610E-01 0.O0O0E +00 0.0000E+00 0.OOOOE+00 8.OOOOE+00 1.7340E-01 0.OOO0E +00 0.OOOOE+00 0.OOOOE+00 2.4000E+01 1.3980E-01 0.OOO0E +00 0.OOOOE+00 0.OOOOE+00

4. 5500E+01 0.OOOOE+00 0.O0O0E -+00 0.OOOOE+00 0.OOOOE+00 Pathway number 2: Environment to Control Room Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.OOOOE+00 2.OOOOE+03 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 8.3300E-02 3.OOOOE+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 7.2000E+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Pathway number 3: Control Room to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 0.OOOOE+00 2.OOOOE+03 0.0000E+00 0.OOOOE+00 0.0000E+00 8.3300E-02 3.OOOOE+02 0.0000E+00 0.0000E+00 0.OOOOE+00 7.2000E+02 0.OOOOE+00 O.O000E+00 O.O000E+00 O.OOOOE+00 LOCATION DATA Location Exclusion Area Boundary is in compartment 2 Location X/Q Data Time (hr) X/Q (s

• m^-3) 0.000OE+00 6.4900E-04 7.2000E+02 0.OOOOE+00 Location Breathing Rate Data Time (hr) Breathing Rate (m^3

• sec^-l) 0.OOOOE+00 3.5000E-04 7.2000E+02 0.OOOOE+00 Location Low Population Zone is in compartment 2 Location X/Q Data Time (hr) X/Q (s

• m^-3) 0.OOOOE+00 1.7700E-04 8.OOOOE+00 .3.9900E-05 2.4000E+01 7.1200E-06 9.6000E+01 1.0400E-06 7.2000E+02 0.OOOOE+00 Location Breathing Rate Data Time'(hr) Breathing Rate (m'3

• sec^-1)

S Xce Energy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 134 of 145 0.00OOE+00 3.5000E-04 8.OOOOE+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.0000E+00 Location Control Room is in compartment 3 Location X/Q Data Time (hr) X/ Q (s

• m^-3) o .OOOOE+00 1. 8300E-02

2. OOOOE+00 1. 4200E-02

8. OOOOE+00 6.3000E-03

2. 4000E+01 4.2900E-03

9. 6000E+01 3. 3800E-03 7.2000E+02 0. 0000E+00 Location Breathing Ra te Data Time (hr) Br eathing Rate (m^3

• sec^-1) o.0000E+00 3.5000E-04 7.2000E+02 o.0000E+00 Location Occupancy Factor Data Time (hr) Occupancy Factor 0.OOOOE+00 1.OOOOE+00 2.4000E+01 6.0000E-01 9.6000E+01 4.0000E-01 7.2000E+02 0.OOOOE+00 USER SPECIFIED TIME STEP DATA- SUPPLEMENTAL TIME STEPS Time Time step 0.0000E+00 1.0000E-01 2.OOOOE+00 5. 0000E-01 8.0000E+00 1.OOOOE+00 2.4000E+01 2.0000E+00

9. 6000E+01 4.0000E+00 7.2000E+02 0.OOOOE+00

S Xcel Energyl Calculation No. GEN-PI-082 Revision No. 0 Page No. 135 of 145 RADTRAD Version 3.03 (Spring 2001) run on 5/25/2009 at 11:44:15

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Dose, Detailed model and Detailed Inventory Output

1. 1. 1. 1. 1. 1. 1. 1. 1. 8##########################88#######################8######

Exclusion Area Boundary Doses:

Time (h) = 0.0036 Whole Body Thyroid TEDE Delta dose (rem) 7.1130E-08 3.2544E-05 1.0860E-06 Accumulated dose (rem) 7.1130E-08 3.2544E-05 1.0860E-06 Low Population Zone Doses: J Time (h) = 0.0036 Whole Body Thyroid TEDE Delta dose (rem) 1.9399E-08 8.8756E-06 2. 9619E-07 Accumulated dose (rem) 1.9399E-08 8.8756E-06 2.9619E-07 Control Room Doses:

Time (h) = 0.0036 Whole Body Thyroid TEDE Delta dose (rem) 1.9443E-10 2. 5137E-06 7.8586E-08 Accumulated dose (rem) 1.9443E710 2. 5137E-06 7.8586E-08 Control Room Compartment Nuclide Inventory:

Time (h) = 0.0036 Ci kg Atoms Decay 1-131 1.7784E-06 1 4345E-14 6.5945E+10 6.052 8E+05 1-132 1.9502E-06 1. 8894E-16 8. 6197E+08 6.6401E+05 1-133 2.7053E-06 2. 3881E-15 1. 0813E+10 9.2077E+05 1-134 4.0473E-07 1 . 5172E-17 6.8183E+07 1.3789E+05 1-135 1.5336E-06 4. 3670E-16 1.59480E+09 S.2203E+05 Xe-133 4.2437E-11 2. 2672E-19 1.20266E+06 2 .1883E+00 Xe-133m 3.0414E-12 6.7781E-21 3.0691E+04 1.5683E-01 Xe-135 2.9202E-10 1. 1435E-19 S.1010E+01 1.5057E+01 Xe-135m 1.8359E-09 2. 0154E-20 8.99903E+04 9.4 420E+01 Control Room Transport Group Inventory:

Time (h) = 0.0036 Atmosphere Sump Noble gases (atoms) 1.6649E+06 0.OOOOE+00 Elemental I (atoms) 7.7247E+10 0.OOOOE+00 Organic I (atoms) 2.3891E+09 0.OOOOE+00 Aerosols (kg) O.OOOOKE+0 0.OOOOK+/-00 Dose Effective (Ci/cc) 1-131 (Thyroid) 1. 3161E-15

XceI E ergy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 136 of 145 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 1. 5587E-15 Total I (Ci) 8.3723E-06 Deposition Recirculating Time (h), = 0.0036 Surfaces Filter Noble gases (atoms) 0.0000E+00 0.0000E+00 Elemental I (atoms) 0.OOOOE+00 0.OOOOE+00 Organic I (atoms) 0.0000E+00 0.OOOOE+00 Aerosols (kg) 0.0000E+00 0.OOOOE+00 Environment to Control Room Transport Group Inventory:

Pathway Time (h) = 0.0036 Filtered Transported Noble gases (atoms) 0.0000E+00 2.1714E+05 Elemental I (atoms) 0.OOOOE+00 7.7431E+10 Organic I (atoms) 0.OOOOE+00 2.3948E+09 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Control Room to Environment Transport Group Inventory:

Pathway Time (h) = 0.0036 Filtered Transported Noble gases (atoms) 7.6333E+02 0.OOOOE+00 Elemental I (atoms) 1.8151E+08 0.0000E+00 Organic I (atoms) 5.6136E+06 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Exclusion Area Boundary Doses:

Time (h) 0.0833 Whole Body Thyroid TEDE Delta dose (rem) 3.1469E-06 1.4405E-03 4.8070E-05 Accumulated dose (rem) 3.2180E-06 1.4731E-03 4. 9156E-05 Low Population Zone Doses:

Time (h) = 0.0833 Whole Body Thyroid TEDE Delta dose (rem) 8.5824E-07 3.9287E-04 1. 3110E-05 Accumulated dose (rem) 8.7763E-07 4.0174E-04 1.3406E-05 Control Room Doses:

Time (h) 0.0833 Whole Body Thyroid TEDE Delta dose (rem) 2.3701E-07 3.0656E-03 9.5841E-05 Accumulated dose (rem) 2.3720E-07 3.0681E-03 9. 5919E-05 Control Room Compartment Nuclide Inventory:

Time (h) - 0.0833 Ci kg Atoms Decay 1-131 7.4561E-05 6. 0142E-13 2. 7648E+12 7. 9226E+08 1-132 7.9846E-05 7 .7354E-15 3.5291E+10 8. 5858E+08 1-133 1. 1315E-04 9. 9886E-14 4. 5228E+l1 1 .2037E+09 1-134 1.5937E-05 5 .9740E-16 2. 6848E+09 1.7477E+08 1-135 6. 3781E-05 1. 8162E-14 8. 1016E+10 6.8046E+08 Xe-131m 1. 6414E-10 1.9597E-18 9.0087E+06 5.8130E+01 Xe-133 4.9898E-08 2. 6657E-16 1 .2070E+09 1.7690E+04 Xe-133m 3.5760E-09 7 .9696E-18 3. 6086E+07 1 .2674E+03 Xe-135 3.4265E-07 1.3418E-16 5.9855E+08 1 .2138E+05 Xe-135m 2.1408E-06 2 . 3501E-17 1.0483E+08 6.8845E+05

XceI nergy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 137 of 145 Control Room Transport Group Inventory:

Time (h) = 0.0833 Atmosphere Sump Noble gases (atoms) 1.9555E+09 0.OOOOE+00 Elemental I (atoms) 3.2360E+12 0.OOOOE+00 Organic I (atoms) 1.0008E+11 0.oo0OE+00 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 5. 5138E-14 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 6. 5234E-14 Total I (Ci) 3.4728E-04 Deposition Recirculating Time (h) = 0.0833 Surfaces Filter Noble gases (atoms) 0.OOOOE+00 0.OOOOE+00 Elemental I (atoms) 0.OOOOE+00 0.OOOOE+00 Organic I (atoms) 0.OOOOE+00 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Environment to Control Room Transport Group Inventory:

Pathway Time (h) = 0.0833 Filtered Transported Noble gases (atoms) 0.OOOOE+00 6.9291E+07 Elemental I (atoms) 0.0000E+00 3.5048E+12 Organic I (atoms) 0.OOOOE+00 1.0840E+11 Aerosols (kg) 0.OOOOE+00 0.00100E+00 Control Room to Environment Transport Group Inventory:

Pathway Time (h) = 0.0833 Filtered Transported Noble gases (atoms) 5.3627E+06 0.OOOOE+00 Elemental I (atoms) 2.6546E+11 0.OOOOE+00 Organic I .(atoms) 8.2102E+09 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Exclusion Area Boundary Doses:

Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 6.1929E-05 3.3982E-02 I. 1195E-03 Accumulated dose (rem) 6.5147E-05 3.5456E-02 1. 1686E-03 Low Population Zone Doses:

Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.6890E-05 9.2679E-03 3. 0531E-04 Accumulated dose (rem) 1.7767E-05 9.6697E-03 3. 1872E-04 Control Room Doses:

Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 5.7538E-06 8.6804E-02 2.7075E-03 Accumulated dose (rem) 5.9910E-06 8.9873E-02 2.8034E-03 Control Room Compartment Nuclide Inventory:

Time (h) = 2.0000 Ci kg Atoms Decay 1-131 4.0070E-05 3.2321E-13 1. 4858E+12 1.2145E+10 1-132 2.4249E-05 2.3492E-15 1.0718E+10 1.0310E+10 1-133 5.7441E-05 5. 0707E-14 2 .2960E+11 1.7983E+10 1-134 1.8947E-06 7.1025E-17 3.1919E+08 1.4978E+09

XceI Energy Calculation No. GEN-PI-082 Revision No. 0 Page No. 138 of 145 1-135 2.8230E-05 8. 0384E-15 3. 5858E+10 9.5667E+09 Xe-131m 8.0079E-09 9.5604E-17 4.3950E+08 8. 7731E+05 Xe-133 2.3758E-06 1 .2692E-14 5. 7470E+l0 2.6220E+08 Xe-133m 1.6862E-07 3. 7579E-16 1. 7016E+09 1.8666E+07 Xe-135 1.6529E-05 6. 4727E-15 2.8874E+10 1.8620E+09 Xe-135m 9.9555E-06 1 .0929E-16 4.8753E+08 2.2406E+09 Control Room Transport Group Inventory:

Time (h) = 2.0000 Atmosphere Sump Noblegases (atoms) 8.8972E+10 0.000OE+00 Elemental I (atoms) 1.7095E+12 0.OOOOE+00 Organic I (atoms) 5.2870E+10 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 O.OOOOE+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 2. 9140E-14 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 3. 3797E-14 Total I (Ci) 1. 5188E-04 Deposition Recirculating Time (h) = 2.0000 Surfaces Filter Noble gases (atoms) 0.OOOOE+00 0.OOOOE+00 Elemental I (atoms) 0.OOOOE+00 1.2505E+13 Organic I (atoms) 0.OOOOE+00 3.8675E+ll Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Environment to Control Room Transport Group Inventory:

Pathway Time (h) = 2.0000 Filtered Transported Noble gases (atoms) 0.OOOOE+00 8.4487E+10 Elemental I (atoms) 0.OOOOE+00 1.5627E+13 Organic I (atoms) 0.OOOOE+00 4.8332E+ll Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Control Room to Environment Transport Group Inventory:

Pathway Time (h) = 2.0000 Filtered Transported Noble gases (atoms) 2.1056E+10 0.OOOOE+00 Elemental I (atoms) 1.3624E+12 0.0000E+00 Organic I (atoms) 4.2136E+10 0.OOOOE+00 Aerosols (kg) O.OOOOE+00 0.OOOOE+00 Exclusion Area Boundary Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 6.5830E-05 5.9825E-02 1.9181E-03 Accumulated dose (rem) 1.3098E-04 9.5281E-02 3.0867E-03 Low Population Zone Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.7954E-05 1. 6316E-02 5. 2312E-04 Accumulated dose (rem) 3.5721E-05 2.5986E-02 8.4184E-04 Control Room Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 4.9844E-06 1. 1157E-01 3.4599E-03 Accumulated dose (rem) 1.0975E-05 2 .0144E-01 6.2634E-03

XcelfnergylCalculation No. GEN-PI-082 Revision No. 0 Page No. 139 of 145 Control Room Compartment Nuclide Inventory:

Time (h) = 8.0000 Ci kg Atoms Decay 1-131 1.7753E-05 1. 4320E-13 6. 5830E+lI 2.7315E+10 1-132 1.7997E-06 1.7436E-16 7.9546E+08 1. 4794E+10 1-133 2. 1291E-05 1.8795E-14 8.5102E+10 3. 7984E+10 1-134 7.4657E-09 2 .7986E-19 1.2577E+06 1. 6691E+09 1-135 6. 8119E-06 1.9397E-15 8.6526E+09 1.7696E+10 Xe-131m 3. 1254E-08 3. 7313E-16 1 .7153E+09 1.5460E+07 Xe-133 8.5699E-06 4 .5784E-14 2. 0730E+l1 4.3942E+09 Xe-133m 5.9024E-07 1 .3154E-15 5.9562E+09 3.0653E+08 Xe-135 3.9486E-05 1 .5462E-14 6. 8974E+10 2.4519E+10 Xe-135m 2.4373E-06 2. 6756E-17 1. 1936E+08 5. 3110E+09 Control Room Transport Group Inventory:

Time (h) = 8.0000 Atmosphere Sump Noble gases (atoms) 2.8407E+ll 0.0000E+00 Elemental I (atoms) 7.3026E+11 0.OOOOE+00 Organic I (atoms) 2.2585E+10 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 1.2386E-14 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 1.3867E-14 Total I (Ci) 4.7663E-05 Deposition Recirculating Time (h) 8.0000 Surfaces . Filter Noble gases (atoms) 0.OOOOE+00 0.OOOOE+00 Elemental I (atoms) 0.OOOOE+00 2.8617E+13 Organic I (atoms) 0.OOOOE+00 8.8505E+1l Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Environment to Control Room Transport Group Inventory:

Pathway Time (h) = 8,0000 Filtered Transported Noble gases (atoms) 0.OOOOE+00 5.9174E+11 Elemental I (atoms) 0.OOOOE+00 3.2220E+13 Organic I (atoms) 0.OOOOE+00 9.9651E+ll Aerosols (kg) 0.OOOOE+00 0.0000E+00 Control Room to Environment Transport Group Inventory:

Pathway Time (h) = 8.0000 Filtered Transported Noble gases (atoms) 3.3469E+ll 0.OOOOE+00 Elemental I (atoms) 2.7757E+12 0.OOOOE+00 Organic I (atoms) 8.5846E+10 0.OOOOE+00 Aerosols (kg) O.OOOOE+00 0.OOOOE+00 Exclusion Area Boundary Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 6.0338E-05 1. 0266E-01 3.2199E-03 Accumulated dose (rem) 1.9132E-04 1. 9794E-01 6.3066E-03 Low Population Zone Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.7095E-06 3.2459E-03 1.0361E-04 Accumulated dose (rem) 3.9431E-05 2.9232E-02 9.4544E-04

XceIEnergy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 140 of 145 Control Room Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.7632E-06 8.3584E-02 2.5755E-03 Accumulated dose (rem) 1.3739E-05 2.8503E-01 8.8389E-03 Control Room Compartment Nuclide Inventory:

Time (h) = 24.0000 Ci kg Atoms Decay 1-131 5. 2019E-06 4.1959E-14 1. 9289E+ll 3. 9359E+10 1-132 4.4971E-09 4.3568E-19 1.9877E+06 1.5083E+10 1-133 3.8769E-06 3. 4224E-15 1 .5496E+10 4. 9611E+10 1-135 3.9486E-07 1.1244E-16 5. 0156E+08 2.0081E+10 Xe-131m 3. 6185E-08 4.3200E-16 1.9859E+09 7. 5126E+07 Xe-133 7.9096E-06 4 .2256E-14 1. 9133E+11 1.8964E+10 Xe-133m 5. 0513E-07 1.1257E-15 5.0973E+09 1 .2716E+09 Xe-135 1.1811E-05 4 6251E-15 2. 0632E+10 6. 4352E+10 Xe-135m 2.2445E-07 .2.4640E-18 1.0992E+07 6. 5122E+09 Control Room Transport Group Inventory:

Time (h) = 24.0000 Atmosphere Sump Noble gases (atoms) 2.1906E+ll 0.OOOOE+00 Elemental I (atoms) 2.0262E+11 0.OOOOE+00 Organic I (atoms) 6.2667E+09 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 3.3743E-15 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 3. 6119E-15 Total I (Ci) 9. 4781E-06 Deposition Recirculating Time (h) = 24.0000 Surfaces Filter Noble gases (atoms) 0.OOOOE+00 0.OOOOE+00 Elemental I (atoms) 0.OOOOE+00 4.0829E+13 Organic I (atoms) 0.OOOOE+00 1.2627E+12-Aerosols. (kg) 0.OOOOE+00 0.OOOOE+00 Environment to Control Room Transport Group Inventory:

Pathway Time (h) = 24.0000 Filtered Transported Noble gases (atoms) 0.OOOOE+00 1.5247E+12 Elemental I (atoms) 0.OOOOE+00 4.5002E+13 Organic I (atoms) 0.OOOOE+00 1.3918E+12 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Control Room to Environment Transport Group Inventory:

Pathway Time (h) = 24.0000 Filtered Transported Noble gases (atoms) 1.2923E+12 0.OOOOE+00 Elemental I (atoms) 3.8469E+12 0.OOOOE+00 Organic I (atoms) 1.1898E+11 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Exclusion Area Boundary Doses:

Time (h) = 45.5000 Whole Body Thyroid TEDE Delta dose (rem) .3.2882E-05 9.2798E-02 2.8753E-03 Accumulated dose (rem) 2.2420E-04 2.9074E-01 9. 1819E-03

XcelEnergyl Calculation No. GEN-PI-082 Revision No. 0 Page No. 141 of 145 Low Population Zone Doses:

Time (h) = 45.5000 Whole Body Thyroid TEDE Delta dose (rem) 3.6074E-07 6. 6901E-04 2.0852E-05 Accumulated dose (rem) 3.9791E-05 2. 9901E-02 9.6630E-04 Control Room Doses:

Time (h) = 45.5000 Whole Body Thyroid TEDE Delta dose (rem) 6.0053E-07 3.0356E-02 9.3044E-04 Accumulated dose (rem) 1.4339E-05 3.1538E-01 9.7693E-03 Control Room Compartment Nuclide Inventory:

Time (h) - 45.5000 Ci kg Atoms Decay 1-131 2.5081E-06 2 0231E-14 9.3001E+10 4 .7028E+10 1-133 9.8639E-07 8 7074E-16 3.9427E+09 5.3864E+10 1-135 2.1579E-08 6.1445E-18 2.7410E+07 2. 0324E+10 Xe-131m 3. 6123E-08 4. 3127E-16 1.9826E+09 1.6334E+08 Xe-133 5.8335E-06 3 1165E-14 1 .4111E+11 3. 5453E+I10 Xe-133m 3.3471E-07 7 4594E-16 3.3776E+09 2 .2726E+09 Xe-135 1.9033E-06 7 4531E-16 3.3247E+09 7. 7214E+10 Xe-135m 1. 1973E-08 1.3144E-19 5. 8632E+05 6.6813E+09 Control Room Transport Group Inventory:

Time (h) = 45.5000 Atmosphere Sump Noble gases (atoms) 1.4980E+11 0.OOOOE+00 Elemental I (atoms) 9.4062E+10 0.OOOOE+00 Organic I (atoms) 2.9091E+09 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 1.5395E-15 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 1.5974E-15 Total I (Ci) 3. 5161E-06 Deposition Recirculating Time (h) = 45.5000 Surfaces Filter Noble gases (atoms) 0.OOOOE+00 0.OOOOE+00 Elemental I (atoms) 0.OOOOE+00 4.8222E+13 Organic I (atoms) 0.OOOOE+00 1.4914E+12 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Environment to Control Room Transport Group Inventory:

Pathway Time (h) = 45.5000 Filtered Transported Noble gases (atoms) 0.OOOOE+00 2.4527E+12 Elemental I (atoms) 0.OOOOE+00 5.3015.E+13 Organic I (atoms) 0.OOOOE+00 1.6396E+12 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Control Room to Environment Transport Group Inventory:

Pathway Time (h) = 45.5000 Filtered Transported Noble gases (atoms) 2.2647E+12 0.oo0oE+00 Elemental I (atoms) 4.4955E+12 0.OOOOE+00 Organic I (atoms) 1.3904E+11 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00

[ Xce nergylCalculation No. GEN-PI-082 Revision No. 0 Page No. 142 of 145 Exclusion Area Boundary Doses:

Time (h) 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Accumulated dose (rem) 2.2420E-04 2. 9074E-01 9. 1819E-03 Low Population Zone Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 0.OOOOE+00 0.OOOOE+00 Accumulated dose (rem) 3.9791E-05 2. 9901E-02 9.6630E-04 Control Room Doses:

Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.0339E-08 4 .7231E-04 1. 4461E-05 Accumulated dose (rem) 1.4359E-05 3. 1586E-01 9.7838E-03 Control Room Compartment Nuclide Inventory:

Time (h) = 96.0000 Ci kg Atoms Decay Xe-133 1.6311E-12 8.7137E-21 3.9455E+04 3. 7715E+10 Control Room Transport Group Inventory:

Time (h) = 96.0000 Atmosphere Sump Noble gases (atoms) 4.0752E+04 0.OOOOE+00 Elemental I (atoms) 1.1001E-69 0.OOOOE+00 Organic I (atoms) 3.4025E-71 0.0000E+00 Aerosols (kg) 0.OOOOE+00 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 1.7706E-95 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 1.7860E-95 Total I (Ci) 3.2957E-86 Deposition Recirculating Time (h) = 96.0000 Surfaces Filter Noble gases (atoms) 0.OOOOE+00 0.OOOOE+00 Elemental I (atoms) 0.OOOOE+00 4 .8292E+13 Organic I (atoms) 0.0000E+00 1.4936E+12 Aerosols (kg) 0.OOOOE+00 0.0000E+00 Environment to Control Room Transport Group Inventory:

Pathway Time (h) = 96.0000 Filtered Transported Noble gases (atoms) 0.OOOOE+00 2.4527E+12 Elemental I (atoms) 0.OOOOE+00 5.3015E+13 Organic I (atoms) 0.OOOOE+00 1.6396E+12 Aerosols (kg) 0.OOOOE+00 0.0000E+00 Control Room to Environment Transport Group Inventory:

Pathway Time (h) = 96.0000 Filtered Transported Noble gases (atoms) 2.4116E+12 0.0000E+00 Elemental I (atoms) 4.5016E+12 0.OOOOE+00 Organic I (atoms) 1.3922E+ll 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Exclusion Area Boundary Doses:

XcelEnergy'1Calculation No. GEN-PI-082 Revision No. 0 Page No. 143 of 145 Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Accumulated dose (rem) 2.2420E-04 2. 9074E-01 9. 1819E-03 Low Population Zone Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.OOOOE+00 0.0000E+00 0.OOOOE+00 Accumulated dose (rem) 3.9791E-05 2. 9901E-02 9.6630E-04 Control Room Doses:

Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.0198E-15 5.0800E-84 1. 0198E-15 Accumulated dose (rem) 1.4359E-05 3.158 6E-01 9.7838E-03 Control Room Compartment Nuclide Inventory:

Time (h) = 720.0000 Ci kg Atoms Decay Control Room Transport Group Inventory:

Time (h) = 720.0000 Atmosphere Sump Noble gases (atoms) 4.0155E-77 0.0000E+00 Elemental I (atoms) 0.OOOOE+00 0.OOOOE+00 Organic I (atoms) 0.0000E+00 0.00O0E+00 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) O.0000E+00 Total I (Ci) 0.0000E+00 Deposition Recirculating Time (h) = 720.0000 Surfaces Filter Noble gases (atoms) 0.OOOOE+00 0.0000E+00 Elemental I (atoms) 0.0000E+00 4.8292E+13 Organic I (atoms) 0.0000E+00 1.4936E+12 Aerosols (kg) 0.OOOOE+00 O.O000E+00 Environment to Control Room Transport Group Inventory:

Pathway Time (h) = 720.0000 Filtered Transported Noble gases (atoms) 0.0000E+00 2.4527E+12 Elemental I (atoms) 0.0000E+00 5.3015E+13 Organic I (atoms) 0.0000E+00 1.6396E+12 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Control Room to Environment Transport Group Inventory:

Pathway Time (h) = 720.0000 Filtered Transported Noble gases (atoms) 2.4116E+12 0.OOOOE+00 Elemental I (atoms) 4.5016E+12 0.OOOOE+00 Organic I (atoms) 1.3922E+lI 0.0000E+00 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 840 4#######4########################4#####4#############4#4#4#############

1-131 Summary

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XcelEnergyl Calculation No. GEN-PI-082 Revision No. 0 Page No. 144 of 145 Intact SG Environment Control Room Time (hr) 1-131 (Curies) 1-131 (Curies) 1-131 (Curies) 0.000 1.2861E+00 2. 4577E-06 4 .2438E-08 0.004 8.3338E+00 1.0320E-04 1. 7784E-06 0.083 8.3268E+00 4.6701E-03 7. 4561E-05 0.400 8.2993E+00 2 .2779E-02 5. 1347E-05 0.700 8.2732E+00 3. 9878E-02 4 .4151E-05 1.000 8.2473E+00 5. 6923E-02 4. 1655E-05 1.300 8.2214E+00 7. 3914E-02 4. 0734E-05 1.600 8.1956E+00 9.0853E-02 4. 0341E-05 1.900 8.1699E+00 1.0774E-01 4. 0126E-05 2.000 8.1614E+00 1.1335E-01 4. 0070E-05 2.300 8.1425E+00 1.2343E-01 2. 5749E-05 2..600 8.1237E+00 1.3348E-01 2.0921E-05 2.900 8.1049E+00 1 .4351E-01 1.9274E-05 3.200 8.0862E+00 1 .5352E-01 1.8694E-05 3.500 8.0675E+00 1.6350E-01 1.8471E-05 3.800 8.0489E+00 1.7346E-01 1.8368E-05 4.100 8.0303E+00 1.8339E-01 1.8305E-05 4.400 8.0117E+00 1.9331E-01 1. 8256E-05 4.700 7.9932E+00 2. 0320E-01 1. 8212E-05 5.000 7.9747E+00 2. 1306E-01 1. 8169E-05 5.300 7.9563E+00 2 .2291E-01 1. 8127E-05

5. 600 7.9379E+00 2. 3273E-0i 1.8085E-05 5.900 7.9195E+00 2 .4253E-01 1 .8043E-05 6.200 7.9012E+00 2.5231E-01 1.8001E-05 6.500 7.8830E+00 2 .6206E-01 1.7960E-05 6.800 7.8648E+00 2.7179E-01 1.7918E-05 7.100 7.8466E+00 2.8150E-01 1.7877ER05 7.400 7.8284E+00 2.9119E-01 1.7835E-05 7.700 7.8104E+00 3.0085E-01 1.7794E-05 8 .000 7.7923E+00 3.1049E-01 1.7753E-05 8.300 7.7768E+00 3.1756E-01 9.7834E-06

8. 600 7.7614E+00 3.2461E-01 7. 1047E-06 8.900 7.7460E+00 3.3165E-01 6.1993E-06 9.200 7.7307E+00 3.3867E-01 5.8883E-06 9.500 7.7153E+00 3.4568E-01 5.7765E-06 9.800 7.7000E+00 3.5268E-01 5.7314E-06

10. 100 7.6848E+00 3.5966E-01 5.7088E-06 10.400 7.6695E+00 3.6663E-01 5.6937E-06 24.000 7.0093E+00 6.6804E-01 5.2019E-06 45.500 6.1568E+00 1.0123E+00 2.5081E-06

96. 000 5.1354E+00 1.0123E+00 3.0300E-86 720.000 5.4587E-01 1.0123E+00 0.OOOOE+00 Cumulative Dose Summary

1. 1. 1. 1. 1. 1. • 1. • 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 44#4##4#######44#################4##

Exclusion Area Bounda Low Population Zone Control Room Time Thyroid TEDE Thyroid TEDE Thyroid TEDE (hr) (rem) (rem) (rem) (rem) (rem). (rem) 0.000 0 OOOOE+00 0.00OOE+00 0.OOO0E+00 0.OOOOE+00 0.OOOE+00 0.OOOE+00 0.004 3 .2544E-05 1.0860E-06 8.8756E-06 2. 9619E-07 2.5137E-06 7.8586E-08 0.083 1.4731E-03 4.9156E-05 4.0174E-04 1.3406E-05 3.0681E-03 9.5919E-05 0.400 7. 1753E-03 2.3890E-04 1.9569E-03 6. 5153E-05 2.2496E-02 7.0296E-04 0.700 1.2544E-02 4.1677E-04 3.4212E-03 1. 1366E-04 3.6695E-02 1.1463E-03 1.000 1.7882E-02 5. 9291E-04 4.8769E-03 1. 6170E-04 4.9514E-02 1.5462E-03 1.300 2 3189E-02 7. 6741E-04 6.3243E-03 2.0929E-04 6.1825E-02 1.9300E-03

XceIEnergy] CalculationNo GEN-PI-082 Revision No. 0 Page No. 145 of 145 1.600 2.8466E-02 9.4034E-04 7.7635E-03 2.5646E-04 7.3920E-02 2.3068E-03 1.900 3. 3713E-02 1.1118E-03 9. 1945E-03 3 .0322E-04 8. 5899E-02 2.6798E-03 2.000 3.5456E-02 1. 1686E-03 9. 6697E-03 3. 1872E-04 8. 9873E-02 2.8034E-03 2.300 3.8576E-02 1.2702E-03 1 .0521E-02 3.4643E-04 9. 9305E-02 3.0969E-03

2. 600 4.1682E-02 1.3711E-03 1. 1368E-02 3.7394E-04 1. 0610E-01 3.3083E-03

2. 900 4..4773E-02 1 . 4713E-03 1 2211E-02 4.0126E-04 1 . 1200E-01 3.4917E-03 3.200 4 .7851E-02 1.5708E-03 1.3050E-02 4 .2840E-04 1 . 1758E-01 3. 6651E-03 3.500 5. 0914E-02 1.6697E-03 1.3886E-02 4 .5537E-04 1.2304E-01 3.8347E-03 3.800 5 3963E-02 1.7679E-03 1 4717E-02 4 8216E-04 1.2845E-01 4.0024E-03 4 .100 5.6998E-02 1.8656E-03 1.5545E-02 5.0880E-04 1.3381E-01 4.1690E-03 4.400 6.0020E-02 1.9626E-03 1.6369E-02 5.3527E-04 1.3915E-01 4.3347E-03 4 .700 6.3029E-02 2. 0591E-03 1.7190E-02 5. 6158E-04 1. 4447E-01 4.4995E-03 5.000 6.6024E-02 2. 1551E-03 1.8007E-02 5..8775E-04 1.497 6E-01 4.6635E-03 5.300 6.9006E-02 2.2505E-03 1.8820E-02 6. 1377E-04 1. 5503E-01 4.8268E-03

5. 600 7 1975E-02 2.3454E-03 1.9630E-02 6.3965E-04 1. 6027E-01 4.9893E-03 5.900 7. 4932E-02 2.4397E-03 2.0436E-02 6.6538E-04 1. 6550E-01 5. 1511E-03 6.200 7 .7876E-02 2.5336E-03 2. 1239E-02 6.9098E-04 1.7070E-01 5.3121E-03 6.500 8.0807E-02 2.6270E-03 2.2038E-02 7.1644E-04 1. 7588E-01 5.4724E-03 6.800 8 .3726E-02 2. 7198E-03 2.2834E-02 7 .4 177E-04 1.8103E-01 5..6320E-03 7.100 8.6633E-02 2. 8123E-03 2.3627E-02 7.6698E-04 1.8617E-01 5.7909E-03 7.400 8.9528E-02 2. 9042E-03 2.4417E-02 7.9205E-04 1. 9128E-01 5.9491E-03 7.700 9.2410E-02 2. 9957E-03 2.5203E-02 8. 1701E-04 1. 9637E-01 6. 1066E-03 8.000 9.5281E-02 3. 0867E-03 2.5986E-02 8. 4184E-04 2. 0144E-01 6.2634E-03 8.300 9.7381E-02 3. 1533E-03 2. 6052E-02 8.4399E-04 2.0519E-01 6. 3791E-03 8.600 9.9473E-02 3.2195E-03 2 6118E-02 8.4614E-04 2.0753E-01 6. 4514E-03 8.900 1 . 0156E-01 3 .2855E-03 2. 6184E-02 8.4827E-04 2. 0939E-01 6.5092E-03 9.200 1. 0363E-01 3. 3512E-03 2. 6250E-02 8.5040E-04 2 . I11OE-01 6. 5619E-03 9.500 1.0570E-01 3. 4166E-03 2 6315E-02 8.5251E-04 2 1275E-01 6. 6128E-03 9.800 1. 0776E-01 3. 4817E-03 2. 6380E-02 8.5461E-04 2. 1437E-01 6.6629E-03 10.100 1. 0982E-01 3. 5465E-03 2.6445E-02 8.5671E-04 2. 1598E-01 6.7127E-03 10.400 1.1186E-01 3.6111E-03 2 6510E-02 8.5879E-04 2 1759E-01 6.7623E-03 24.000 1.9794E-01 6.3066E-03 2. 9232E-02 9.4544E-04 2 .8503E-01 8.8389E-03 45.500 2.9074E-01 9.1819E-03 2. 9901E-02 9.6630E-04 3.1538E-01 9.7693E-03 96.000 2 . 9074E-01 9. 1819E-03 2 9901E-02 9.6630E-04 3.1586E-01 9.7838E-03 720.000 2. 9074E-01 9.1819E-03 2 9901E-02 9.6630E-04 3. 1586E-01 9.7838E-03

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Worst Two-Hour Doses it# ###### ##i # t#t#t#i#i#itit######i##t##itit# i##it #####t

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t####t### t #it#t#####it#,t i#i i Exclusion Area Boundary Time Whole Body Thyroid TEDE (hr) (rem) (rem) (rem) 0.0 6.5147E-05 3.5456E-02 1 .1686E-03