Text

Attachment 8 to Enclosure, Calculation GEN-PI-087, Rev. 0, Hld Analysis Titled, Heavy Load Drop Event Dose Analysis - Ast.
	ML093160586
Person / Time
Site:	Prairie Island
Issue date:	09/10/2009
From:	Gita Patel; Xcel Energy
To:	; Office of Nuclear Reactor Regulation
References
	L-PI-09-114 GEN-PI-087, Rev 0
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ATTACHMENT 8 to ENCLOSURE HLD Analysis titled, "Heavy Load Drop Event Dose Analysis - AST" 54 Pages Follow

OF-05490P-n&CAL-011. Rev. 3 Pake I (if54.

X I Energy Calculation .Signature Sheet Document Information NSPM Calculation (Doc) No: GEN.-PI-087 Revision:. 0

Title:

HeaIvy Load Drop Event Dose Analysis AST --

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Prepared by:, Go*palJ* Patel - Aaý, - Date: 09/10/2009 Reviewed by: Thomas J. Mscis *-. b Date: 09/11/2009 Type* of Review: Z Design Verifi tion i-ch ReviewL. Vendor Acceptance.,

Method Used (ForDV p )ý- jReview. L Alternate Calc L Test Approvedb .5. - Date: '6 o .

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QF-0549 (FP-E-CAL-01), Rev. 3 Page 3 of 54 XcelEnergy Calculation Signature Sheet NOTE: This reference table is used for data entry into the PassPort Controlled Documents Module, reference tables (C012 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.

Refere-nee Documents (PassPortC012 Panel from C020)

Controlled* Document Ref Type**

Doc? + Type Document Name Number Doc Rev (if known)

Alternative Radiological Source Terms for Evaluating I Design Basis Accidents at Nuclear Power Reactors, July 1.183 July 2000 ZInput [-Output 2000 for Radionuclide Transport and NUREG/CR-6604 Dec 1997 EInput [:]Output 2 ARemoval and Model Simplified Dose Estimation 3 E LTR Westinghouse Letter,

Subject:

Core Activity Inventory and Letter NSP-07-59 11/2/2007 Zlnput lOutput Coolant Activity Concentration 4 Z TRNS Design Input Transmittal- Heavy Load Drop Dose DIT # 13720-15 0 Mlnput [Output Analysis Input Parameters 5 Z TRNS Design Input Transmittal - Generic Control Room DIT # 13720-07 1 [Input [-]Output

-6 E TRNS Design Input Transmittal - Generic Atmospheric DIT 9 13720-03 0 Zlnput LlOutput

__ TN Dispersion 7 Z CALC Prairie Island Atmospheric Dispersion Factors (z/Q) - GEN-PI-080 0 lInput l--Output AST Additional Releases UI/U2 8 ] Tech Spec PINGP Units 1 & 2, Definition of Rated Thermal Power 1.1 Amendment EInput [-]Output 158/149 U1/U2 ZInput [-]Output 9 Z Tech Spec PINGP Units 1 & 2 LCO for Refueling Cavity Water Level 3.9.2 Amendment 158/149 UI/U2 ZInput Ll-Output 10 Z Tech Spec Fuel Assemblies 4.2.1 Amendment 158/149 PINGP Units 1 & 2 Ventilation Filter Testing Program UI/U2 Zlnput .lOutput 11 Z Tech Spec (VFTP) 5.5.9 Amendment 186/176

QF-0549 (FP-E-CAL-01), Rev. 3 Page 4 of 54 XcelEnergy- Calculation Signature Sheet

.Input U3/U2 AOutput 12 Z Tech Spec PINGP Units 1 & 2 LCO for Shield Building Ventilation 3.6.9 Amendment System (SBVS) 186/176 U1/U2 [*Input [---Output 3.3.6 A nnt Control Room Special Ventilation System (CRSVS) 13 M.Tech Spec Actuation Instrumentation Including Table 3.3.6-1 3.3.6 Amendment 158/149 14 [*TS SR Perform required SBVS filter tetn testing innacrac ih accordance with SR 3.6.9.2 Amendment UI/U2 [Input -lOutput the Ventilation Filter Testing Program (VFTP) 158/149 15 Z CALC Fission Product Inventories for AST Assessments GEN-PI-046 0 Elinput ZOutput 16 M CALC PI Control Room Atmospheric Dispersion Factors GEN-PI-049 0, Add 2 L]Input ZOutput 17 Z CALC Fuel Handling Accident Dose Analysis - Heavy Load GEN-PI-051 Rev 1, ElInput Z*Output Drop Adden. I PINGP Amendment Nos. 166 and 156 to Operating ZInput -- Output 18 Z LA License Nos. DPR-42 and DPR-60, respectively, Selective LA # 166 & 156 Implementation Of Alternate Source Term For Fuel Handling Accidents 19 USNRC, "Laboratory*Testing of Nuclear-Grade Activated 99-02 5/3/99 ZInput ElOutput Charcoal 20 Accident Source Term 10 CR 50.67 ZInput E-Output 15.0.1 0 ZInput [-]Output 21 Radiological Consequence Analyses Using Alternative Source Terms 22 Federal Guidance Report 11 EPA-520/1 Zlnput .:output 23 Federal Guidance Report 12 EPA-402-R ZInput L-Output 081 24 RPRT Prairie Island Units 1 & 2 422V+ Reload Transition Safety Safety Report 0 Z1nput El-Output Report PINGP Ventilation Flow Diagrams Reactor Building NF-39602-1 76 [Input --Output 25 [ DRAW Unit 1 26 [ DRAW PINGP Ventilation Flow Diagram Reactor Building Unit 2 NF-39602-2 76 ZInput E--Output 27 Z DRAW PINGP Architectural Drawing Operating Floor Plan @ NF-38502 76 ZInput [--]Output EL 735'-0" 1

QF-0549 (FP-E-CAL-01), Rev. 3 Paqe 5 of 54 SXceIEnergy~ Calculation Signature Sheet 28 Z DRAW PINGP Architectural Drawing East Elevation NF-38510 J ZInput L--Output 29 [ DRAW P1NGP Architectural Drawing West Elevation NF-38511 G ZIn ut -Output 30 Z USAR PINGP USAR Appendix D - Activity In Fuel Gap Section D.2 Input -Output 31 Z USAR PINGP USAR Appendix D - Thyroid Dose Conversion Table D.8-2 -]Input ZOutput Factors for Iodine Inhalation 32 Z USAR PINGP USAR Appendix D - Standard Man Breathing Table D.8-3 ]--Input ZOutput Rates 33 Z CALC FHA Fission.Product Inventories for AST Assessments GEN-PI-047 Rev 0, []Input ZOutput Adden. 1 34 Z CALC Post-LOCA EAB, LPZ, and CR Doses - AST GEN-PI-079 0 ZInput DOutput Design, Testing, and Maintenance Criteria for Post 35 Accident Engineered-Safety-Feature Atmosphere Cleanup 1.52 2 [lnput E-]Output System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants NF-39603-1, Rev 36 Z DRAW Admin Bldg, Screen House, & Control RM Flow Diagram 76, Including T- 76 ZInput []-Output Mod EC 14090 Salem Nuclear Generating Station, Unit Nos. 1 and 2, Issuance of License Amendments 271 and 252 to 37 Operating License Nos. DPR-70 and DPR-75, respectively, LA # 271 & 252 02/17/2006 ZInput L-Output Alternate Source Term (TAC Nos. MC3094 and MC3095),

NRC ADAMS Accession Number ML060040322 Perform required SFSVS filter testing in accordance with US7U2 ZAnput []output 38 Z TS SR the Ventilation Filter Testing Program (VFTP) SR 3.7.13.2 Amendment 1_______________________________________ 186/176 _________

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), Rev. 3 Paqe 6 of 54 Mrl XceIEnergy- Calculation Signature Sheet Other Pass Port Data Associated System (PassPort C011, first three columns) OR Equipment References (PassPort C025, all five columns):

Facility Unit System Equipment Type Equipment Number P1 0 ZN FILTER 069-241 PI 0 ZN FILTER 069-242 P1 0 RD RM RM-23 PI 0 RD RM RM-24 Superseded Calculations (PassPort C019):

Facility Calc Document Number Title PI GEN-PI-051, Rev 1, Addendum 1 Fuel Handling Accident Dose Analysis Description Codes - Optional (PassPort C018):

Code Description (optional) Code Description (optional) 11.,

Notes (Nts) - Optional (PassPort X293 from C020):

Topic Notes tText

[I'- Calc introductionI Z Copy directly from the calculation Intro Paragraph or r--- See write-up below The purpose of this analysis is to determine the Exclusion Area Boundary (EAB), Low Population Zone (LPZ) and Control Room (CR) doses due to a drop of the reactor vessel upper internals (i.e., a heavy load drop [HLD]) into the reactor vessel with containment open, occurring with the reactor being shutdown for at least 7 days. Dropping of a heavy load on the fuel assemblies in the vessel has the potential to damage more than one fuel assembly. The post-accident activity is postulated to release to the atmosphere through the common area of the auxiliary building, which has the most limiting atmospheric dispersion factor (x/Qs) of all potential release paths, to maximize the radiological dose consequences.

E] (Specify) I

Xce nergy ICalculation No. GEN-PI-087 Revision No. 0 Page No. 7 of 54 XcelEnergy-l Desi~gn Review Comment Form Sheet _ of DOCUMENT NUMBER/ TITLE: GEN-PI-087/ Heavy Load Drop Event Dose Analysis - AST REVISION: 0 DATE:

ITEM REVIEWER'S COMMENTS PREPARER'S REVIEWER'S

RESOLUTION DISPOSITION I Various editorial comments/suggestions made Incorporated Accepted 09/ W09 in the body of the calculation.

2 Design Input 5.3. 1.10 Fuel Cycle Burnup is The fuel cycle bumup data is the Accepted f/10/09 listed as 25,000 MWD/MTU. Item 5.3.1.11 burnup for a single fuel cycle. The fuel says that the 6.3 kW/ft LHGR is exceeded. is exposed in the core for at least two This rate only applies to fuel with burnups cycles, and sometimes three cycles. As exceeding 54,000 MWD/MTU. It is unclear such, some of the fuel rods have how the 6.3 kW/ft LHGR is exceeded. burnups that exceed 54,000 MWD/MTU, and as such the LHGR criterion is exceegd.

END Reviewer: T-hnas Msci~ate: 09/09/2009 Preparer opal J. Patel Date: 09/10/2009

Xcel Energy Calculation No. GEN-PI-087 Revision No. 0 Page No. 8 of 54 REVISION HISTORY Revision Description 0 Initial issue

XceIEnergy. Calculation No. GEN-PI-087 Revision No. 0 Page No. 9 of 54 SHEET REVISION INDEX SHEET REV SHEET REV 1 0 21 0 2 0 22 0 3 0 23 0 4 0 24 0 5 0 25 0 6 0 26 0 7 0 27 0 8 0 28 0 9 0 29 0 10 0 30 0 11 0 31 0 12 0 32 0 13 0 33 0 14 0 34 0 15 0 Attachment A 0 16 0 17 0 18 0 19 0, 20 0

I XceIfnergy- Calculation No. GEN-PI-087 Revision No. 0 Page No. 10 of 54 TABLE OF CONTENTS Section Sheet No.

Cover Sheet 1 Revision History Sheet Revision Index 9 Table of Contents 10 1.0 Purpose And Summary Report 11 2.0 Methodology 1!

3.0 Acceptance Criteria 14 4.0 Assumptions 15 5.0 Design Inputs 20 6.0 Computer Codes & Compliance With Regulatory Requirements 24 7.0 Calculations 25 8.0 Results Summary And Conclusions 27 9.0 References 28 10.0 Tables 30 11.0 Figures 32 12.0 Affected Documents 34 13.0 Attachment 34 Attachment A - RADTRAD Output File PI300HLDOO.oO 35

69 Xce nergy Calculation No. GEN-PI-087 Revision No. 0 Page No. 11 of 54 1.0 PURPOSE and

SUMMARY

REPORT

Purpose:

The purpose of this analysis is to determine the Exclusion Area Boundary (EAB), Low Population Zone (LPZ) and Control Room (CR) doses due to a drop of the reactor vessel upper internals (i.e., a heavy load drop [HLD]) into the reactor vessel with containment open, occurring with the reactor being shutdown for at least 7 days. Dropping of a heavy load on the fuel assemblies in the vessel has the potential to damage more than one fuel assembly. The post-accident activity is postulated to release to the atmosphere through the common area of the auxiliary building, which has the most limiting atmospheric dispersion factor (x/Qs) of all potential release paths, to maximize the radiological dose consequences.

This analysis supersedes the heavy load drop event analysis of Calculation GEN-PI-051 Revision I Addendum I (Ref. 9.10). This analysis differs from that of Calculation GEN-PI-051 Revision I Addendum I in that various parameters are modeled with more conservative values, and this analysis uses revised common area of auxiliary building to Control Room X/Qs.

Summary Report:

The resulting post-accident doses are shown in Section 8.0, which comply with the applicable regulatory allowable dose limits.

2.0 METHODOLOGY

In the postulated heavy load drop event, the reactor vessel upper internals are assumed to be dropped into the reactor vessel, damaging all fuel rods in two impacted fuel assemblies. This accident would take place in the containment. The most limiting 0 to 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months control room atmospheric dispersion factor (X/Q) was selected from the various potential release paths. The shield building ventilation system (SBVS) is operable by Technical Specification LCO 3.6.9 (Ref. 9.6.3). Although the analysis does not take credit for filtration by the SBVS, the system is not prevented from operating after the heavy load drops. The post-accident potential release paths are reviewed as follows:

2.1 Equipment Hatch Release Path This analysis assumes that the heavy load drop into the reactor vessel could occur with containment open. The source could exit containment directly to the atmosphere through the open Equipment Hatch.

The distance from the equipment hatch to the CR intake is much farther than the distance from the CA (Refs. 9.19.1, 9.19.2 & 9.19.3).

2.2 Containment Air Locks Release Path The Reactor Building ventilation flow diagrams (Ref. 9.18) show that if a heavy load drop would occur in the containment building with its boundary intact during an outage, then there is no release path to the environment and no radiological consequences. However, if the containment is kept open through air locks, then the activity is released into the Common Area. of the Auxiliary Building (i.e., CA) or Shield Building annulus. When the containment integrity is not maintained, the post-accident leakage is

X'ceEnergy Calculation No. GEN-PI-087 Revision No. 0 Page No. 12 of 54 released to the environment through various potential release paths and the 0 to 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months CR 7xiQs for these release paths are listed in the following table:

Summary of 0-2 Hour Control Room Intake x/Qs for Various Post-FHA Release Paths 0-2 Hour Release Source Receptor Location CR x/Q (sec/m 3) Reference Unit 1 Equipment Hatch Unit I Control Room Intake 1.73E-03 9.8, Section 8.0 Unit I Equipment Hatch Unit 2 Control Room Intake 4.79E-04 9.8, Section 8.0 Unit 2 Equipment Hatch Unit 1 Control Room Intake 6.04E-04 9.8, Section 8.0 Unit 2 Equipment Hatch Unit 2 Control Room Intake 3.1 IE-03 9.8, Section 8.0 Common Area of Aux Bldg Unit 1 Control Room Intake 6. 71E-03 9.5, Section 8.1.3 Common Area of Aux Bldg Unit 2 Control Room Intake 4.79E-03 9.5, Section 8.1.3 Unit 1 Shield Bldg Vent Stack Unit I Control Room Intake 1.34E-03 9.5, Section 8.1.1 Unit I Shield Bldg Vent Stack Unit 2 Control Room Intake 3.39E-04 9.5, Section 8.1.1 Unit 2 Shield Bldg Vent Stack Unit I Control Room Intake 4.61E-04 9.5, Section 8.1.1 Unit 2 Shield Bldg Vent Stack Unit 2 Control Room Intake 1.67E-03 9.5, Section 8.1.1 A review of the tabulated X/Qs indicates that the CA repr'esents the most limiting release path for the heavy load drop event occurring in the containment. Therefore, the post-accident doses are analyzed using CA to Unit I CR intake y/Qs.

The Safety Evaluation approving the PINGP selective implementation of AST for the fuel handling accident (FHA) (Ref. 9.11, Section 3.2, page 6) requires that the licensee should evaluate the effect on the FHA dose analysis of any change to the credited filtration efficiencies for the SBVS filter or any change in assumed operation of this system. Xcel Energy has proposed to remove the SBVS filtration system from the PINGP Technical Specifications. Since the heavy load drop event analysis in this calculation uses the most limiting x/Q for the Common Area of the Auxiliary Building without crediting any filtration, the resulting dose consequences will remain bounding for the post-accident unfiltered releases from the containment.

2.4 Maximum Linear Heat Generation Rate Note 11 to Table 3 of RG 1.183 (Ref. 9.1) requires that the maximum linear heat generation (LHGR) does not exceed 6.3 kw/ft peak rod average power for burnups exceeding 54 GWD/MTU. The Prairie Island fuel management program can result in some fuel assemblies being exposed to a maximum LHGR that exceeds 6.3 kw/hr at fuel burnups between 54 and 62 GWD/MTU (Ref. 9.20.1). To account for the higher LHGR a site-specific analysis was performed in Reference 9.21 and a computer code, "GAP" was developed and qualified using methodology presented in ANSI/ANS-5.4-1982 to perform the site-specific gap fraction analysis. The NRC reviewed the GAP code during approval of the PINGP license amendment for implementing selective implementation of AST for FHA (Ref. 9.11, Section 3.2) and determined that the analytical approach is consistent with the ANSI/ANS-5.4-1982 model, and that the GAP code is acceptable for analyzing the gap release fraction. The plant-specific gap fractions are compared with the RG 1.183 gap fractions in Table 2, which indicates that the gap fractions in Table 3 of RG 1.183 are bounding for the P1NGP fuel assemblies exceeding the maximum LHGR of 6.3 kw/ft.

The review of Table 2 indicates that the PINGP bounding fraction for the most limiting 1-131 is a factor

XceIEnergy, Calculation No. GEN-PI-087 Revision No. 0 Page No. 13 of 54 of 2 lower than that in the RG 1.183, Table 3. The PINGP bounding gap fraction in Table 2 has ample margin for the increased fuel burnup including the 10% EPU.

2.5 RADTRAD Model The RADTRAD3.03 Code (Ref. 9.2) is used in this analysis. The RADTRAD release model as depicted in Figure 1 is used to model the heavy load drop event occurring in the refueling cavity inside Containment.

The RADTRAD model considers a fictitious source volume of 1,000 cubic feet (Compartment #1),

which initially contains all of the activity that is released to the Containment air space. This source term, defined in Section 5.3.1, considers two damaged fuel assemblies that have decayed for 7 days following reactor shutdown, with a radial peaking factor of 1.90, fuel rod gap release fractions per Regulatory Guide 1.183 (Ref. 9.1), and pool water iodine, noble gas and particulate decontamination factors per RG 1.183.

Section 7.2 calculates a building release rate that will exhaust at least 99% of the radioactive material present in Compartment #1 to the environment (Compartment #2) over a 2-hour time period. The modeling of a 99% release rate has been accepted by the NRC Staff in various approved AST license amendment requests (e.g., Salem Units I and 2 [Ref. 9.23, Section 3.2.1]). No credit is taken for filtration of the activity released to the environment.

The heavy load drop event model for the control room (Compartment #3) is shown in Figure 2 and described in Section 5.4. The model for the EAB and LPZ dose receptors is described in Section 5.5.

2.6 CR Air Intake Radiation Monitor Response Post-accident Xe-133 activity in the CR @ 0.0036 hr (022 minute) after start of the release

= 1.692 Ci (RADTRAD Run PI300HLDOO.oO)

Control room volume 61,315 ft3 (Section 5.4.1) = 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) after start of the release

= 1.692 Ci / 1,737.58 m3 = 9.738E-04 Ci/m 3 = 9.738E-04 pCi/cc, which exceeds CR monitor setpoint of IE-05 pCi/cc for Xe-133 (Ref. 9.3.2, Item #9).

Since the Xe-133 activity in the CR is circulated by the CR recirculation flow through the CR air supply duct (Ref. 9.9), the monitor setpoint is instantly exceeded. Therefore, the CR actuation delay of 5 minutes following a heavy load drop is considered extremely conservative, and does not require any further justification.

XceI nergy Calculation No. GEN-PI-087 Revision No. Page No. 14 of 54 g

3.0 ACCEPTANCE CRITERIA:

The following NRC regulatory requirement and guidance documents are applicable to this PINGP Alternative Source Term heavy load drop event calculation:

Regulatory Guide 1.183 (Ref. 9.1, Table 6)

" IOCFR50.67 (Ref. 9.13)

" Standard Review Plan section 15.0.1 (Ref. 9.24)

Dose Acceptance Criteria are:

Regulatory Dose Limits

[Dose Type DsControl Room (rem) I EAB and LPZ (rem)

TEDE Dose 5 6.3

XceIEnergy Calculation No. GEN-PI-087 Revision No. 0 Page No. 15 of 54

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 FHA. These FHA assumptions are assumed to be applicable to a heavy load drop event, which also damages fuel following reactor shutdown. The following sections address the applicability of these modeling assumptions to this PINGP heavy load drop event analysis.

These assumptions are considered validated assumptions and are incorporated as design inputs in Sections 5.3 through 5.5 and are incorporated in this analysis. There are no unvalidated assumptions used in this calculation.

Source Term Assumptions 4.1 It is assumed consistent with RG 1.183, Section 3.2 that the fractions of the core inventory assumed to be in the gap for the various radionuclides are as given in Table 3 of RG 1.183. The release fractions from Table 3 Are incorporated in Design Input 5.3.1.3 in conjunction with the core fission product inventory in Design Input 5.3.1.2, with the maximum core radial peaking factor of 1.90 in Design Input 5.3.1.8, and with the proposed core thermal power level of 1,852 MWt in Design Input 5.3.1.1.

Per Section 2.4, the NRC has approved use of the isotopic release fractions specified in Table 3 of RG 1.183 for the PINGP fuel assemblies exceeding the maximum LHGR of 6.3 kw/ft at fuel burnups between 54 and 62 GWD/MTU. This approval was based on the RG 1.183 isotopic release fractions being conservatively greater than those calculated using the NRC-approved methodology of ANS-5.4-1982.

4.2 It is assumed consistent with Reference 9.1, Appendix B, Section 1.1 that the number of fuel rods damaged during the accident should be based on a conservative analysis that considers the most limiting case. All of the fuel rods in two spent fuel assemblies are assumed to be damaged (see Design Input 5.3.1.5).

It is assumed consistent with Reference 9.1, Appendix B, Section 1.2, that the fission product release from the breached fuel is based on the fission product inventory in the fuel rod gap (Ref. 9.1, Table 3) and the estimate of the number of fuel rods breached (See Table 1).

4.3 Core Inventory It is assumed that all the gap activity in the damaged rods is instantaneously released to.the pool water.

The radionuclides included are xenons, kryptons, and iodines. The fraction of fission product inventory in the gap is shown in Design Input 5.3.1.3. It is further assumed that theheavy load drop onto irradiated fuel cannot occur until the unit has been sub-critical for at least 7 days (Design Input 5.3.1.7).

Non-iodine halogen isotopes (e.g., Bromine) are not modeled due to their short half lives that leave little activity in the source term at 7 days (Ref. 9.3, Table 2-1). Alkali metal (i.e., particulate) isotopes are not modeled since they are not released from the water (Ref. 9.1, Appendix B, Section 3).

It is assumed that the curie per Megawatt-thermal inventory of fission products in the reactor core and available for gap release from damaged fuel is based on the core thermal power level of 1,683 MWt including 2% power level measurement instrument uncertainty. The fission product inventory is based on the current fuel enrichment of 5.0 w/o U-235, and a fuel cycle burnup of 25 GWD/MTU (Design Inputs 5.3.1.9 & 5.3.1.10).

Xce Energy Calculation No. GEN-PI-087 Revision No. 0 Page No. 16 of 54 4.4 Timing of Release Phase It is assumed consistent with Reference 9.1, Section 3.3 that for non-LOCA DBAs in which fuel damage is projected, the release from the fuel gap is assumed to occur instantaneously with the onset of the projected damage.

4.5 Chemical Form It is assumed consistent with Reference 9.1, Appendix B, Section 1.3, that the chemical form of radioiodine released from the fuel to the surrounding water should be assumed to be 95% cesium iodide (CsI), 4.85 percent elemental iodine, and 0.15 percent organic iodine (Design Input 5.3.1.12). The CsI released from the fuel is assumed to completely dissociate in the pool water. Because of the low pH of the pool water, the iodine re-evolves as elemental iodine. The release to the pool water is assumed to occur instantaneously.

4.6 Water Depth It is assumed that if the depth of water above the damaged fuel is 23 feet or greater, the overall effective decontamination factor for iodine of 200 (i.e., 99.5% of the total iodine released from the damaged rods is retained by the water) (see Design Input 5.3.2.3; Ref. 9.1, Appendix B, Section 2). This iodine above the water is composed of 57% elemental and 43% organic species (Ref. 9.1, Appendix B, Section 2) (see Design Input 5.3.2.4).

4.7 Noble Gases and Particulates It is assumed that the retention of noble gases in the water in the fuel pool or reactor cavity is negligible (i.e., decontamination factor of 1) (see Design Input 5.3.2.5). Particulate radionuclides are assumed to be retained by the water in the fuel pool or reactor cavity (i.e., infinite decontamination factor) (Ref. 9.1, Appendix B, Section 3) (see Design Input 5.3.2.9).

Heavy Load Drop Event in Containment Building For the heavy load drop event postulated to occur in the Containment Building, the following assumption is acceptable to the NRCstaff (Ref. 9. 1, Appendix B, Section 5).

4.8 It is assumed that if the containment is open during fuel handling operations (e.g., personnel air lock or equipment hatch is open) the radioactive material that escapes from the reactor cavity pool to the containment is released to the environment over a 2-hour time period (Ref. 9.1, Section B.5.3) (Design Input 5.3.2.6). The activity release from the damaged fuel is postulated to release to the environment at a rate that will ensure that at least 99% of the post-accident activity is removed from the source volume (Section 7.2). The modeling of a release rate that releases 99% of the total activity in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months has been accepted by the NRC Staff in various approved AST license amendment requests (e.g., Salem Units I and 2 [Ref. 9.23, Section 3.2.1]).

SXceIEnergy; Calculation No. GEN-PI-087 Revision No. 0 Page No. 17 of 54.

Control Room 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 FHA analysis. These assumptions are incorporated as design inputs in Sections 5.4.1 through 5.6.11.

4.9 It is assumed consistent with RG 1.183 (Ref. 9.1, Section 4.2. 1), that the CR TEDE analysis should consider the following sources of radiation that will cause exposure to control room personnel:

Contamination of the control room atmosphere by the intake or infiltration of the radioactive material contained in the post-accident radioactive plume released from the facility (via CR air intake),

0 Contamination of the control room atmosphere by the intake or infiltration of airborne radioactive material from areas and structures adjacent to the control room envelope (via CR unfiltered inleakage),

Radiation shine from the external radioactive plume released from the facility (external airborne cloud),

0 Radiation shine from radioactive material in the reactor containment (containment shine dose),

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

Note: Per Calculation GEN-PI-079 (Ref. 9.22, Section 8.1), the total post-LOCA external airborne cloud dose, containment shine dose, plus control room filter shine dose to the control room is less than 0.07 rem. This LOCA dose is based on both fuel rod gap and early in-vessel (i.e., core melt) activity releases associated with damage to all fuel assemblies in the core. The heavy load drop event activity releases are associated with only releases from only 2 of the 121 fuel assemblies in the core, and these assemblies have decayed for 7 days following reactor shutdown. Consequently, the external airborne cloud dose, containment shine dose, and CR filter shine dose due to a heavy load drop event are insignificant (i.e., 0.07 rem x [2 / 121] =

0.0012 rem) and are not evaluated for a heavy load drop event.

4.10 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. These parameters do not result in non-conservative results for the control room.

4.11 It is assumed consistent with RG 1.183 (Ref. 9.1, Section 4.2.6), that the CR dose receptor 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 of this individual should be assumed to be 3.5 x 10 cubic meters per second. These assumptions are incorporated as design inputs in Sections 5.4.8 and 5.4.10, respectively.

SXcelEnergy- Calculation No. GEN-PI-087 Revision No. 0 Page No. 18 of 54 4.12 It is assumed consistent with RG 1.183 (Ref. 9.1, Section 4.4), that the postulated CR doses should not exceed the 5 Rem TEDE criterion established in 10 CFR 50.67 (Ref. 9.10). This assumption is incorporated as a design input in Section 5.4.9.

CR Dose Acceptance Criteria: 5 Rem TEDE 4.13 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 isactuated by radiation monitors (RMs). Several aspects of CRSVS operation can delay the CR isolation. The CR air supply duct monitor response is calculated in Section 2.6 based on the post-accident CR Xe-133 activity, which is circulated by the CR recirculation flow through the CR air supply duct (Ref. 9.9). The CR XE-I133 activity concentration instantly exceeds the monitor setpoint of IE-05 ptCi/cc for Xe-I133 (Ref. 9.3.2, Item #9). 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.

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 this guidance to the P1NGP heavy load drop event analysis. These assumptions are incorporated as design inputs in Sections 5.5.1 through 5.5.7.

4.14 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; and these two 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 5.3.1.2.

4.15 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. 9.14).

4.16 It is assumed consistent with RG 1.183 (Ref. 9.1, Section 4.1.3), that for the first 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , the breathing rate of persons offsite is assumed to be 3.5 x 10-4 cubic meters per second. From 8 to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following the accident, the breathing rate is assumed to be 1.8 x 10-4 cubic meters per second. After that and until the end of the accident, the rate is assumed to be 2.3 x 10-4 cubic meters per second. These offsite breathing rate assumptions are listed in Sections 5.5.2 and 5.5.4.

4.17 It is assumed consistent with RG'1 .183 (Ref. 9.1, Section 4.1.4), that the 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

XceInergy Calculation No. GEN-PI-087 Revision No. 0 Page No. 19 of 54 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. 9.15).

4.18 It is assumed consistent with RG 1.183 (Ref. 9.1, Sections 4.1.5 and 4.4), that the TEDE is determined for the most limiting person at the EAB. The maximum EAB TEDE for any two-hour period following the start of the radioactivity release is determined and used in determining compliance with the dose criteria in 10 CFR 50.67 (Ref. 9.13). For the heavy load drop event, the postulated EAB doses should not exceed the criteria established in RG 1.183 Table 6 for a fuel handling accident. This assumption is incorporated as a design input in Section 5.5.6.

EAB Dose Acceptance Criterion: 6.3 Rem TEDE The RADTRAD3.03 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.

4.19 It is assumed consistent with RG 1.183 (Ref. 9.1, Sections 4.1.6 and 4.4), that the TEDE is determined for the most limiting receptor at the outer boundary of the low population zone (LPZ) and is used in determining compliance with the dose criteria in 10 CFR 50.67 (Ref. 9.13). For the heavy load drop event, the postulated LPZ doses should not exceed the criteria established in RG 1.183 Table 6 for a fuel handling accident. This assumption is incorporated as a design input in Section 5.5.7.

LPZ Dose Acceptance Criterion: 6.3 Rem TEDE 4.20 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.

XceIEnergy- Calculation No. GEN-PI-087 Revision No. 0 Page No. 20 of 54 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 Safeguard Features Credit is taken only for 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 CRSVS air intake monitors are required to be operable by TS 3.3.6 and Table 3.3.6-1 (Ref. 9.6.6) in Modes 1,2, 3, & 4 and during movement of irradiated fuel assemblies. The CRSVS actuation during the FHA is credited in the analysis with a 5-minute system response delay.

The shield building ventilation system (SBVS) is operable by Technical Specification LCO 3.6.9 (Ref. 9.6.3). The actuation of the SBVS is conservatively not credited in the analysis. Although the analysis does not take credit for filtration by the SBVS, the system is not prevented from operating after a heavy load drop event.

5.1.3 Meteorology Considerations The control room atmospheric dispersion factors (X/Qs) for the several potential post-accident release points including the Unit I & 2 Equipment Hatches, the Common Area of Auxiliary Building (AB), and the SB Vent Stacks release points - are developed (Refs. 9.5 & 9.8) using the NRC sponsored computer code ARCON96 and guidance provided for the use of ARCON96 in the Regulatory Guide 1.194. The EAB and LPZ X/Qs were originally developed for the plant operating license and were accepted by the staff in the previous licensing amendments.

5.2 Accident-Specific Design Inputs/Assumptions The design inputs and assumptions utilized in the heavy load drop event EAB, LPZ, and CR habitability analysis are listed in the following sections. The design inputs are compatible with the AST and TEDE dose criteria and assumptions are consistent with those identified in Section 3 and Appendix B of RG 1.183 (Ref. 9.1). The design inputs and assumptions in the following sections represent the as-built design of the plant.

V- XbeIfnery Calculation No. GEN-PI-087 Revision No. 0 Page No. 21 of 54 5.3 Source Term and Transport Parameters Design Input Parameter Value Assigned Reference 5.3.1 Source Term 5.3.1.1 Core Power Level 1,650 MWt 9.6.1 1,683 MWt ( 102% of 1,650 MW,) 10% EPU Power Level Used in 1,852 MWt 110% of 1,683 MWt) the analysis 5.3.1.2 Un-Decayed Heavy Load Drop Event Activity Released from Table I Damaged Fuel Assemblies (Ci/MWt) @ 1,683 MWt Isotope Activity Isotope Activity Isotope Activity KR-85* 2.668E+01 1-133 8.518E+00 XE-135 3.863E+02 KR-85M 2.015E+02 .1-134 9.517E+00 XE-135M 3.639E+02 KR-87 3.956E+02 1-135 8.136E+00 XE-138 1.441 E+03 KR-88 5.262E+02 XE-131M 9.442E+00 1-131 ** 6.718E+00 XE-133 1.707E+03 1-132 6.074E+00 XE-133M 5.337E+0I

Kr-85 activity has been multiplied by a factor of 2 (0.10/0.05) to account for additional fractional release relative to other noble gas isotopes.

- 1-131 activity has been multiplied by a factor of 1.6 (0.08/0.05) to account for additional fractional release relative to other iodine isotopes.

- - This activity release profile does not consider decay time or gap release fractions. These characteristics will be entered separately into the RADTRAD code.

5.3.1.3 Fraction of Fission Product Inventory in Gap Group Fraction 9.1, Section 3.2, Table 3 1-131 0.08 Kr-85 0.10 Other Noble Gases 0.05 Other Halogens 0.05 Alkali Metals 0.12 5.3.1.4 Radionuclide Composition Group Elements 9.1, Section 3.4, Table 5 Noble Gases Xe, Kr Halogens I, Br Alkali Metals Cs, Rb 5.3.1.5 Number of Damaged Fuel 2 9.4.1, Item # 3 Assemblies 5.3.1.6 Number of Fuel 121 9.6.4 Assemblies In Core 5.3.1.7 Irradiated Fuel Decay 7 days ( 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months ) 9.4.1, Item # 6 5.3.1.8 Radial Peaking Factor 1.77 9.16 & 9.4.1, Item #10 1.90 Used in the analysis

~X'ceIfnergy- Calculation No. GEN-PI-087 Revision No. 0 Page No. 22 of 54 Design Input Parameter Value Assigned Reference 5.3.1.9 Fuel Enrichment w/o 5.0% 9.3, Table 6-1 U-235 5.3.1.10 Fuel Cycle Burnup 25,000 MWD/MTU 5.3.1.11 Linear Heat Generation 6.3 kw/ft 9.1, Table 3, Note # 11 Rate ýý Exceeds this requirement See discussion in Section 2.4 5.3.1.12 Iodine Chemical Form Released from Fuel to Water Iodine Chemical Form %

Aerosol (CsI) 95.0% 9.1, Appendix B, Section 1.3 Elemental 4.85%

Organic 0.15%

5.3.2 Activity Transportation 5.3.2.1 Minimum Refueling 23 feet 9.6.2 & 9.4.2, Item # 7 Cavity Water Depth 5.3.2.2 Deleted 5.3.2.3 Overall Effective Decontamination Factor (DF) for Iodine Total Iodine 1200 9.1, Appendix B, Section 2 5.3.2.4 Chemical Form of Iodine Released From Pool Water Elemental 57% 9. 1, Appendix B, Section 2 Organic 43%

5.3.2.5 DF of Noble Gas 1 9.1, Appendix B, Section 3 5.3.2.6 Duration of Release (hr) 2 9.1, Appendix B, Section 5.3 5.3.2.7 Pool Node Volume 1,000 ft3 Assumed 5.3.2.8 Activity release rate 39 cfm See Section 7.2 5.3.2.9 DF of Particulates Infinite 9.1, Appendix B, Section 3 5.4 Control Room (CR) Parameters 5.4.1 CR Volume 61,315 ft3 9.4.2, Item # 6 5.4.2 CRSVS Normal Flow Rate 1,818 cfm +/- 10% 9.4.2, Item # 10 2,000 cfm < 5 minutes Used in the analysis 5.4.3 CRSVS Makeup Rate 0.00 cfm > 5 minutes CR operates in a recirculation mode 5.4.4 CRSVS Recirc Flow Rate 4,000 cfm +/- 10% 9.4.2, Item # 13 3,600 cfm > 5 minutes Used in the analysis 5.4.5 CRSVS Charcoal Filter 95% for elemental iodine Section 7.3.1 Efficiencies 95% for organic iodide 5.4.6 CRSVS HEPA Filter 99% Section 7.3.2 Efficiency 5.4.7 CR Unfiltered Inleakage 300 cfm (includes 10 cfm for 9.4.2, Item # 11 Determined By Tracer Gas ingress and egress) (nominal Testing value measured, including uncertainty) 5.4.8 CR Breathing Rate 3.5E-04 m 3/sec 9. 1, Section 4.2.6 5.4.9 CR Allowable Dose Limit 5 rem TEDE for the event 9.13 duration

XceIEnergy Calculation No. GEN-PI-087 Revision No. 0 Page No. 23 of 54 Design Input Parameter Value Assigned Reference 5.4.10 CR Occupancy Factors 1 Time (Hr) % 9.1, Section 4.2.6 0-24 100 24-96 60 96-720 40 5.4.11 Unit 2 CR X/Qs For FHA Release Through Common Area of Auxiliary Building (CA)

Time (Hr) X/Q (sec/mr3) 9.5, Section 8.1.3 0-2 6.71 E-03 2-8 2.89E-03 8-24 1.22E-03 24-96 9.21 E-04 96-720 7.44E-04 5.5 Site Boundary Release Model Parameters 5.5.1 EAB Atmospheric 6.49E-04 sec/mr3 9.4.2, Item # 2 Dispersion Factor (X/Q) 5.5.2 EAB Breathing Rate 3.5E-04 9.1, Section 4.1.3 (m 3/sec) 5.5.3 LPZ Distance 2,414 m 9.4.3, Item # 3 3

5.5.4 LPZ Breathing Rate (m /sec)

Time (Hr) (m 3/sec) 9.1, Section 4.1.3 0-8 3.5E-04 8-24 1.8E-04 24-720 2.3E-04 5.5.5 LPZ Atmospheric Dispersion Factors (X/Qs)

Time (Hr) x/Q (sec/m 3) 9.4.3, Item # 3 0-8 1.77E-04 8-24 3.99E-05 24-96 7.12E-06 96-720 1.04E-06 5.5.6 EAB allowable dose limit 6.3 rem TEDE for any 2-hour 9.1, Section 4.1.5 and Table 6 period 5.5.7 LPZ allowable dose limit 6.3 rem TEDE for the event 9.1, Section 4.1.6 and Table 6 duration

XcelEnergy Calculation No. GEN-PI-087 Revision No. 0 Page No. 24 of 54 6.0 COMPUTER CODES & COMPLIANCE WITH REGULATORY REQUIREMENTS 6.1 COMPUTER CODES RADTRAD 3.03 (Ref. 9.2): This 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 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. 9.22, 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 FHA 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 code is considered validated for use in the P[NGP 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 B.

t? XcelEnery ICalculation No. GEN-PI-087 Revision No. 0 Page No. 25 of 54 7.0 CALCULATIONS 7.1 PINGP Plant Specific Nuclide Inventory File (NIF) For RADTRAD3.03 Input The parameter Ci/MWt in the RADTRAD3.03 default nuclide inventory file Pwr-def.NIF is dependent on the plant-specific core thermal power level, reload design, fuel burnup, and fuel cycle, therefore, the NIF is modified based on the PINGP plant-specific isotopic Ci/MWt information developed in Table 1.

The newly developed RADTRAD nuclide inventory file PFHAHLDdef.txt is used in the analysis.

Similarly, the Release Fraction Timing File (RFT) PIFHA_rft.txt, and Dose Conversion File (DCF)

PIFHAfg1 1&12.txt are generated to support the heavy load drop event analysis. The DCF input file includes additional noble gas isotopes (Xe-131M, Xe-133M, Xe-135M, and Xe-138) for completeness.

7.2 Activity Release Rates The Containment Building is assigned a source node volume of 1,000 ft3 and 99% of the post-accident activity in this source node volume is postulated to release to the environment over two hours with the activity release rate calculated in the following section:

A = A0 e--t Where; A0 = Initial Activity in Source Node A = Final Activity in Source Node X = Removal Rate (vol/hr) t = Removal Time (hr) = 2.0 hr Assuming that 99% of activity is released into the environment, A/Ao = 0.01 Therefore, A / Ao = ext 0.01 = e"2-In (0.01) - 2, ln(e)

- 4.605= - 2X X = - 4.605/-2 = 2.303 volume/hr Containment Building Release Rate = 2.303 vol/hr x 1,000 ft3 x I hr/60 min Containment Building Release Rate = 38.38 ft3/min = 39.0 ft3/min 7.3 CRSVS Filter Efficiency The CRSVS charcoal and HEPA filter efficiencies are calculated based on RG 1.52 (Ref. 9.17) and Generic Letter (GL) 99-02 requirements (Ref. 9.12).

7.3.1 CRSVS Charcoal Filter Efficiency Laboratory penetration testing acceptance criteria for the safety related Charcoal filters are as follows:

Q XceEnergy' Calculation No. GEN-PI-087 Revision No. 0 Page No.26 of 54 CRSVS Charcoal Filter - in-laboratory testing methyl iodide penetration < 2.5% (Ref. 9.6.5, Section 5.5.9.c)

Generic Letter 99-02 (Ref. 9.12) 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% - 11)/2 Where q = charcoal filter efficiency to be credited in the analysis CRSVS Charcoal Filter 2.5% = (100%- -l)/2 5%= (100%- )

rl = 100% - 5% = 95%

7.3.2 CRSVS HEPA Filter Efficiency CRSVS HEPA Filter - in-place DOP penetration and bypass < 0.05% (Ref. 9.6.5, Section 5.5.9.a)

Generic Letter 99-02 (Ref. 9.12) 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% - il)/safety factor = (100% - i")/2 Where ri = HEPA filter efficiency to be credited in the analysis CRSVS HEPA Filter 0.05% = (100% - n)/2 0.10% = (100%- r,)

Ti = 100% - 0.10% = 99.9%

Regulatory Guide 1.52 (Ref. 9.17, 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.

Safety Grade Filter Efficiency Credited (%)

Filter Aerosol Elemental Organic CRSVS 99 95 95

S Xcel Energy Calculation No. GEN-PI-087 Revision No. 0 Page No. 27 of 54 8.0 RESULTS

SUMMARY

/CONCLUSIONS:

8.1 Result Summar:

The heavy load drop event EAB, LPZ, and CR doses are summarized in the following table:

FHA Due To Heavy Load Drop Post-FHA TEDE Dose (Rem)

Activity Release Receptor Location Path Control Room EAB LPZ Common Area of Auxiliary 4.42E+00 2.77E+00 7.56E-01 Building (168 hr)

Total 4.42E+00 2.77E+00 7.56E-01 Allowable TEDE Limit 5.OOE+00 6.30E+00 6.30E+00 RADTRAD Computer Run No.

PI300HLDOO.oO PI300HLDOO.oO PI300HLDOO.oO 8.2

Conclusions:

The results of analysis in Section 8.1 indicate that the EAB, LPZ, and CR doses are within allowable limits for a heavy load drop event occurring in the containment without containment integrity. The results demonstrate that the following PINGP Technical Specification requirement can be relaxed:

The irradiated fuel can be moved in the reactor pressure vessel, reactor water cavity, and SFP enclosure after the reactor has been sub-critical for at least 7 days (i.e., 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months ) without crediting the SBVS and SFPSVS filtrations. The SBVS vent and recirculation charcoal filter could be physically deleted or abandoned in-place with the deletion of the Surveillance Requirement SR 3.6.9.2 (Ref. 9.6.7) for LCO 3.6.9. Similarly, the SFPSVS filter could be physically deleted or abandoned in-place with the deletion of the Surveillance Requirement SR 317.13.2 (Ref. 9.6.8) for LCO 3.7.13.

XceI Energy- Calculation No. GEN-PI-7087 Revision No. 0 Page No. 28 of 54

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, April 1998

3. Westinghouse Letter NSP-07-59, Dated 11/02/2007,

Subject:

Core Activity Inventory and Coolant Activity Concentration

4. Design Input Transmittal Nos 4.1 DIT No. 13720-15, Rev. 0, Heavy Load Drop Dose Analysis Input Parameters 4.2 DIT No. 13720-07, Rev. 1, Control Room Input Parameters 4.3 DIT No. 13720-03, Rev. 0, Meteorological Input Parameters

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

AST Additional Releases

6. PINGP Technical Specifications:

6.1 Specification 1.1, PINGP Units 1 & 2, Rated Thermal Power 6.2 Specification LCO 3.9.2, Refueling Cavity Water Level 6.3 Specification LCO 3.6.9, Shield Building Ventilation System (SBVS) 6.4 Specification 4.2.1, Fuel Assemblies 6.5 Specification 5.5.9, Ventilation Filter Testing Program (VFTP) 6.6 Specification 3.3.6, Control Room Special Ventilation System (CRSVS) Actuation Instrumentation Including Table 3.3.6-1 6.7 Surveillance Requirement SR 3.6.9.2, Perform required SBVS filter testing in accordance with the Ventilation Filter Testing Program (VFTP) 6.8 Surveillance Requirement SR 3.7.13.2, Perform required SFSVS filter testing in accordance with the Ventilation Filter Testing Program (VFTP)

7. PINGP Calculation No. GEN-PI-046, Rev 0, Fission Product Inventories for AST Assessments

8. PINGP Calculation No. GEN-PI-049, Rev 0, Addenda 2, PI Control Room Atmospheric Dispersion Factors

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

10. PINGP Calculation No. GEN-PI-05 1, Rev 1, Addendum 1, Fuel Handling Accident Dose Analysis -

Heavy Load Drop

Xc*e I Energy, Calculation No. GEN-PI-087 Revision No. 0 Page No. 29 of 54

11. Prairie Island Nuclear Generating Plant Amendment Nos. 166 and 156 to Operating License Nos. DPR-42 and DPR-60, respectively, Selective Implementation Of Alternate Source Term For Fuel Handling Accidents (TAC Nos. MC 1843 and MC 1844), September 10, 2004, NRC ADAMS Accession Number ML042430504.

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

13. 10 CFR 50.67, "Accident Source Term"

14. Federal Guidance Report 11, EPA-5201/1-88-020, Environmental Protection Agency

15. Federal Guidance Report 12, EPA-402- R-93-081, Environmental Protection Agency

16. Prairie Island Units I & 2 422V+ Reload Transition Safety Report, Rev 0, by Westinghouse, May 2008

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

18. PINGP Ventilation Flow Diagrams:

18.1 NF-39602-1, Rev 76, Reactor Building Unit 1 18.2 NF-39602-2, Rev 76, Reactor Building Unit 2

19. PINGP Architectural Drawings:

19.1 NF-38502, Rev 76, Operating Floor Plan @ EL 735'-0" 19.2 NF-38510, Rev J, East Elevation 19.3 NF-3851 1, Rev G, West Elevation

20. PINGP USAR Appendix D Sections & Tables:

20.1 Section D.2, Activity In Fuel Gap 20.2 Table D.8-2, Thyroid Dose Conversion Factors for Iodine Inhalation 20.3 Table D.8-3, Standard Man Breathing Rates

21. PINGP' Calculation No. GEN-PI-047, Rev 0, Addendum 1, FHA Fission Product Inventories for AST Assessments

22. P1NGP Calculation No. GEN-PI-079, Rev 0, Post-LOCA EAB, LPZ, and CR Doses - AST

23. Salem, Unit Nos. 1 and 2, Issuance of License Amendments 251 and 232 Re: Refueling Operations -

Fuel Decay Time Prior to Commencing Core Alterations or Movement of Irradiated Fuel, October 10, 2002 (ADAMS Accession Number ML022770181)

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

XceIfnergy- Calculation No. GEN-PI-087 Revision No. 0 Page No. 30 of 54 10.0 TABLES Table I Un-decayed Heavy Load Drop Event Activity Released From Two Damaged Fuel Assemblies Used In RADTRAD Nuclide Inventory File Core Radial Total Number Activity RADTRAD Isotope Inventory Peaking Number of Fuel In Damaged Nuclide At Factor of Fuel Assemblies Fuel DF Inventory File (NIF)

Shutdown Assembly Damaged Assembly (Ci) In Core (Ci) (Ci) (Ci/MWt)

A B C D E=A*B*D/C F G=E/F H = G/1683 KR-85* 1.43E+06 1.90 121 2 4.49E+04 1 4.491E+04 2.668E+01 KR-85M 1.08E+07 1.90 121 2 3.39E+05 1 3.392E+05 2.015E+02 KR-87 2.12E+07 1.90 121 2 6.66E+05 I 6.658E+05 3.956E+02 KR-88 2.82E+07 1.90 121 2 8.86E+05 1 8.856E+05 5.262E+02 1-131** 7.20E+07 1.90 121 2 2.26E+06 200 1.131E+04 6.718E+00 1-132 6.51E+07 1.90 121 2 2.04E+06 200 1.022E+04 6.074E+00 1-133 9.13E+07 1.90 121 2 2.87E+06 200 1.434E+04 8.518E+00 1-134 1.02E+08 1.90 121 2 3.20E+06 200 1.602E+04 9.517E+00 1-135 8.72E+07 1.90 121 2 2.74E+06 200 1.369E+04 8.136E+00 XE-131M 5.06E+05 1.90 121 2 1.59E+04 I 1.589E+04 9.442E+00 XE-133 9.15E+07 1.90 121 2 2.87E+06 1 2.874E+06 1.707E+03 XE-133M 2.86E+06 1.90 121 2 8.98E+04 I 8.982E+04 5.337E+01 XE-135 2.07E+07 1.90 121 2 6.50E+05 I 6.501E+05 3.863E+02 XE-135M 1.95E+07 1.90 121 2 6.12E+05 I 6.124E+05 3.639E+02 XE-138 7.72E+07 1.90 121 2 2.42E+06 I 2.424E+06 1.441E+03 A from Reference 9.3, Table 2-1 except noted as follows

KR-85 activity has been multiplied by a factor of 2 (0.10/0.05) to account for additional fractional release relative to other noble gas isotopes.

- 1-131 activity has been multiplied by a factor of 1.6 (0.08/0.05) to account for additional fractional release relative to other iodine isotopes B From Section 5.3.1.8 C From Reference 9.6.4

D From Section 5.3.1.5 F From RG 1.183, Appendix B, Sections 2 and 3

XceI Energy Calculation No. GEN-PI-087 Revision No. 0 Page No.31 of 54 Table 2 Comparison of Gap Fractional Releases for Prairies Island Fuel Rod To RG 1.183, Table 3 Radionuclide Fractional Release Or Bounding RG 1.183 Radionuclide Prairie Island Table 3 Group Result A B 1-131 0.036 0.08 Kr-85 0.056 0.10 Other Noble Gases 0.024 0.05 Other Halogens 0.013 0.05 Alkali Metals 0.072 0.12 A From. Reference 9.21

C Xce nergY ICalculation No. GEN-PI-087 Revision No. 0 Page No. 32 of 54 11.0 FIGURES:

Source Node Volume 3

V = 1,000 ft Figure 1: Heavy Load Drop Event Occurring in Containment Building, RADTRAD Nodalization

SXceinergy Calculation No. GEN-PI-087 Revision No. 0 Page No. 33 of 54 CR Unfiltered Inleaka~e CONTROL ROOM 2,000 cfm < 5 min 300 cfm > 5 min V = 61,315 ft 3

HEPA Ti = 99%

Charcoal Ti = 95%

I _ CRSVS Charcoal Filter Figure 2 - PINGP Heavy Load Drop Event Control Room Response AST RADTRAD Nodalization

XceI Energy- Calculation No. GEN-PI-087 Revisi.on No. 0 Page No. 34 of 54 12.0 AFFECTED DOCUMENTS:

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

12.1 PINGP Calculation No. GEN-PI-046, Rev 0, Fission Product Inventories for AST Assessments 12.2 PINGP Calculation No. GEN-PI-051, Rev 1, Addendum I, Fuel Handling Accident Dose Analysis 12.3 PINGP Calculation No. GEN-PI-047, Rev 0, Addendum 1, FHA Fission Product Inventories for AST Assessments 12.4 PINGP USAR Appendix D Sections and Tables:

12.4.1 Section D.2, Activity in the Fuel Gap 12.4.2 Table D.8-2, Thyroid Dose Conversion Factors for Iodine Inhalation 12.4.3 Table D.8-3, Standard Man Breathing Rates 13.0 ATTACHMENTS:

Attachment A - RADTRAD Output File PI300HLD00.o0

Ice! Energy Calculation No. GEN-PI-087 Revision No. 0 Page o. 35 of 54 Attachment A RADTRAD Output File PI300HLDOO.oO

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

RADTRAD Version 3.03 (Spring 2001) run on 7/15/2009 at 14:41:00

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

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

File information

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

Plant file = G:\Radtrad 3.03\Input\PI\GEN-PI-087\PI300HLDOO.psf Inventory file = G:\Radtrad 3.03\Defaults\PFHAHLD def.txt Release file = g:\radtrad 3.03\defaults\pifha rft.txt Dose Conversion file = g:\radtrad 3.03\defaults\pifha-fgll&12.txt

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

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

Radtrad 3.03 4/15/2001 Prairie Island FHA AST Analysis Due To Heavy Load Drop - CR Charcoal Filtration Starts

@ 5 minutes, and CR Unfiltered Inleakage = 300 cfm Nuclide Inventory File:

G:\Radtrad 3.03\Defaults\PFHAHLD def.txt Plant Power Level:

1.8520E+03 Compartments:

3 Compartment 1:

Fuel Pool 3

1.0000E+03 0

0 0

Compartment 2:

Environment 2

0.0000E+00 0

0 0

0

Xce IEnergy ICalculation No. GEN-PI-087 Revision No. 0 Page No. 36 of 54 0

Compartment 3:

Control Room 1

6.1315E+04 0

0 0

Pathways:

3 Pathway 1:

FHA Release 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.OOOOE+00 g:\radtrad 3.03\defaults\pifha_fgll&12.txt g:\radtrad 3.03\defaults\pifharft.txt 1.6800E+02 1

0.0000E+00 5.7000E-01 4.3000E-01 1.0000E+00 Overlying Pool:

0 o.OOOOE+00 0

0 0

0 Compartments:

3 Compartment 1:

0 1

0 0

0

Xce IEnergy Calculation No. GEN-PI-087 Revision No. 0 Page No. 37 of 54 0

0 Compartment 2:

0 1

0 0

0*.

0 0

Compartment 3:

1 1

0 0

1 3.6000OE+03 3

1.6800E+02 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 1.6808E+02 9. 9000E+01 9. 5000E+01 9. 5000E+01 8.8800E+02 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0

0 Pathways:

3 Pathway 1:

0 0

0 1

2

1. 6800E+02 3. 9000E+01 o .OOOOE+00 0.0000E+00 o .OOOOE+00 1.7000E+4012 0.0000E+00 o .OOOOE+00 o.OOOOE+00 0.OOOOE+00 0

0 0

0.

Pathway 2:

0 0

0 0*

0 1

3 1 .6800E+02 2.OOOOE+03 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00

1. 6808E+402 3.OOOOE+02 o.OOOOE+00 0.OOOOE+00 0.OOOOE+00 8 .8800E+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0

XceIfnergy- Calculation No. GEN-PI-087 Revision No. 0 Page No. 38 of 54 0

0 0

Pathway 3:

0 0

1 3

1.6800E+02 2.OOOOE+03 0.0000E+00 0.0000E+00 0.OOOOE+00 1.6808E+02 3.0000E+02 0.0000E+00 0.0000E+00 o.OOOOE+00 8.8800E+02 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0

0 0

0 Dose Locations:

3 Location 1:

Exclusion Area Boundary 2

1 2

1.6800E+02 6.4900E-04 8.8800E+02 0.OOOOE+00 1

2 1.6800E+02 3.5000E-04 8.8800E+02 0.OOOOE+00 0

Location 2:

Low Population Zone 2

1 5

1.6800E+02 1.7700E-04 1.7600E+02 3.9900E-05 1.9200E+02 7.1200E-06 2.6400E+02 1.0400E-06 8.8800E+02 0.OOOOE+00 1

4 1.6800E+02 3.5000E-04 1.7600E+02 1.8000E-04 1.9200E+02 2.3000E-04 8.8800E+02 0.OOOOE+00 0

Location 3:

Control Room 3

0

I XcelEnergy Calculation No. GEN-PI-087 Revision No. 0 Page No. 39 of 54 1

2 1.6800E+02 3.5000E-04 8.8800E+02 0.OOOOE+00 1

4 1.6800E+02 1.0000E+00 1.9200E+02 6.0000E-01 2.6400E+02 4.0000E-01 8.8800E+02 0.0000E+00 Effective Volume Location:

1 6

1.6800E+02 6.7100E-03 1.7000E+02 2.8900E-03 1.7600E+02 1.2200E-03 1.9200E+02 9.2100E-04 2.6400E+02 7.4400E-04 8.8800E+02 0.0000E+00 Simulation Parameters:

6 1.6800E+02 1.0000E-01 l.7000E+02 5.0000E-01 1.7600E+02 1.0000E+00 1.9200E+02 2.OOOOE+00 2.6400E+02 5.0000E+00 8.8800E+02 0.0000E+00 Output Filename:

G:\Radtrad 3.o54 1

.1 1

0 0

End of Scenario File

XceI Energy Calculation No. GEN-PI-087 Revision No. 0 Page No. 40 of 54

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

RADTRAD Version 3.03 (Spring 2001) run on 7/15/2009 at 14:41:00

1. 1. 1. 1. 4##############444#############44#######

Plant Description

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

Number of Nuclides = 60 Inventory Power = 1.OO0OE+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: Fuel Pool Compartment volume = 1.OOOOE+03 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 1 Exit Pathway Number 1: FHA Release to Environment Compartment number 2 Name: Environment Compartment type is Environment Pathways into and out of compartment 2 Inlet Pathway Number 1: FHA Release 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 Energy- Calculation No. GEN-PI-087 Revision No. 0 Page No. 41 of 54 RADTRAD Version 3.03 (Spring 2001) run on 7/15/2009 at 14:41:00

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

Scenario Description

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

Time between shutdown and first release. = 1.6800E+02 (Hours)

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 5.OOOOE-02 0.OOOOE+00 0.OOOOE+00 7.233E+00 IODINE 5.OOOOE-02 0.OOOOE+00 O.OOOOE+00 6.016E-03 CESIUM 1.2000E-01 0.OOOOE+00 O.OOOOE+00 0.OOOE+00 TELLURIUM 0.0000g+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 STRONTIUM o.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 0.0OOOE+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-85 1 2.688E+01 3. 383E+08 1. 190E-16 0 OOOE+00 0.OOOE+00 Kr-85m 1 2.015E+02 1. 613E+04 7. 480E-15 0. OOOE+00 0.OOOE+00 Kr-87 1 3.956E+02 4. 578E+03 4.120E-14 0. OOOE+00 0.OOOE+00 Kr-88 1 5.262E+02 1. 022E+04 1. 020E-13 0. 000E+00 0.OOOE+00 1-131 2 6.718E+00 6. 947E+05 1. 820E-14 2. 920E-07 8.890E-09 1-132 ~2 6.074E+00 8 . 280E+03 1. 120E-13 1.740E-09 1.030E-10 1-133 2 8.518E+00 7.488E+04 2.940E-14 4. 860E-08 1.580E-09 1-134 2 9.517E+00 3. 156E+03 1.300E-13 2 .880E-10 3.550E-11 1-135 2 8.136E+00 2 .380E+04 8.294E-14 8.4 60E-09 3.320E-10 Xe-131m 1 9.442E+00 1 .028E+06 3.890E-16 0. OOOE+00 0.OOOE+00 Xe-133 1 1.707E+03 4. 532E+05 1.560E-15 0. OOOE+00 0.OOOE+00 Xe-133m 1 5.337E+01 1. 890E+05 1.370E-15 0. 00OE+00 0.OOOE+00 Xe-135 1 3.863E+02 3.272E+04 1.190E-14 0. OOOE+00 0.OOOE+00 Xe-135m 1 3.639E+02 9. 174E+02 2.040E-14 0. OOOE+00 0.OOOE+00 Xe-138 i 1.441E+03 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

XceI nergy- Calculation No. GEN-PI-087 Revision No. 0 Page No. 42 of 54 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 = .OOOOE+00 Elemental = 5.7000E-0l Organic = 4.30O0E-01 COMPARTMENT DATA Compartment number 1: Fuel Pool Compartment number 2: Environment Compartment number 3: Control Room Compartment Filter Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 1.6800E+02 3.6000E+03 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 1.6808E+02 3.6000E+03 9. 9000E+01 9.5000E+01 9. 5000E+01 8.8800E+02 3.6000E+03 0.OOOOE+00 0.OOOOE+00 0..OOOOE+00 PATHWAY DATA Pathway number 1: FHA Release to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 1.6800E+02 3. 90OOE+01 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 1.7000E+02 0.OOOOE+00 0.OOOOE+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 1.6800E+02 2.OOOOE+03 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 1.6808E+02 3.OOOOE+02 0.OOOOE+00 O.OOOOE+00 0.OOOE+00 8.8800E+02 0.0000E+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 1.6800E+02 2.OOOOE+03 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 1.6808E+02 3.0000E+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 8.8800E+02 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 LOCATION DATA

XcelEnergy- Calculation No. GEN-PI-087 Revision No. 0 Page No. 43 of 54 Location Exclusion Area Boundary is in compartment 2 Location X/Q Data Time (hr) X/Q (s

m^-3) 1.6800E+02 6.4900E-04 8.8800E+02 0.OOOOE+00 Location Breathing Rate Data Time. (hr) Breathing Rate (m^3

sec^-l) 1.6800E+02 3.5000E-04 8.8800E+02 0.OOOOE+00 Location Low Population Zone is in compartment 2 Location X/Q Data Time (hr) X/Q (s

m^-3) 1.6800E+02 1.7700E-04 1.7600E+02 3.9900E-05 1.9200E+02 7.1200E-06 2.6400E+02 1.0400E-06 8.8800E+02 0.0000E+00 Location Breathing Rate Data Time (hr) Breathing Rate (m^3

sec^-l) 1.6800E+02 3.5000E-04 1.7600E+02 1.8000OE-04 1.9200E+02 2.3000E-04 8.8800E+02 0.0000E+00 Location Control Room is in *compartment 3 Location X/Q Data Time (hr) X/Q (s

m^-3) 1.6800E+02 6.7100E-03 1.7000E+02 2.8900E-03 1.7600E+02 1.2200E-03 1.9200E+02 9.2100E-04 2.6400E+02 7.4400E-04 8.8800E+02 0.0000E+00 Location Breathing Rate Data Time '(hr) Breathing Rate (m^3

sec^-l) 1.6800E+02 3.5000E-04 8.8800E+02 0.0000E+00 Location Occupancy Factor Data Time (hr) Occupancy Factor 1.6800E+02 1.0000E+00 1.9200E+02 6.OOOOE-01 2.6400E+02 4.OOOOE-01 8.8800E+02 0.0000E+00 USER SPECIFIED TIME STEP DATA - SUPPLEMENTAL TIME STEPS Time Time step 0.OOOOE+00 1.0000E-01 2.0000E+00 5.0000E-01 8.OOOOE+00 1.OOOOE+00 2.4000E+01 2.0000E+00 9.6000E+01 5.0000E+00

XcIel Energy- Calculation No. GEN-PI-087 Revision No. 0 Page No. 44 of 54 7.2000E+02 O.OOOOE+O0

Xce IEnergy Calculation No. GEN-PI-087 Revision No. 0 Page No. 45 of 54

1. 1. 1. 1. 4#4 ######4###4## 4#4### ##4###4###44#4 ##4##)###444######4#4##4##

RADTRAD Version 3.03 (Spring 2001) run on 7/15/2009 at 14:41:00 44#44#####4#4###########44######################4####4######4###########

444 4 4 ####4 #4##4 4 4 #4.4 4 * * * # 4 4# *

4 4 4

4#

4 4 44444 4 4 4 4

f

4 4 4 4

f *

4 4 *##4 4 4444 #4## 4 *

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

Dose, Detailed model and Detailed Inventory Output

1. 1. 1. 1. 4######4#######################4 Exclusion Area Boundary Doses:

Time (h) = 168.0036 Whole Body Thyroid TEDE Delta dose (rem) 1.0792E-03 3.5119E-01 1 . 1772E-02 Accumulated dose (rem) 1.0792E-03 3. 5119E-01 1. 1772E-02 Low Population Zone Doses:

Time (h) = 168.0036 Whole Body Thyroid TEDE Delta dose (rem) 2.9431E-04 9.5780E-02 3. 2106E-03 Accumulated dose (rem) 2.9431E-04 9.5780E-02 3. 2106E-03 Control Room Doses:

Time (h) = 168.0036 Whole Body Thyroid TEDE Delta dose (rem) 1.0819E-06 9.9484E-03 3.0399E-04 Accumulated dose (rem) 1.0819E-06 9.9484E-03 3.0399E-04 Control Room Compartment Nuclide Inventory:

Time (h) = 168.0036 Ci kg Atoms Decay Kr-85 6.5983E-02 1. 6818E-07 1. 1915E+18 2 .2458E+10 1-131 9.0292E-03 7.2831E-11 3.3481E+14 3.0732E+09 1-133 7.7517E-05 6. 8429E-14 3. 0984E+l1 2.6385E+07 1-135 4. 4644E-10 1.2712E-19 5.6708E+05 1. 5197E+02 Xe-131m 1.5479E-02 1.8480E-10 8.4954E+14 5.2686E+09 Xe-133 1.6920E+00 9. 0391E-09 4. 0928E+16 5.7589E+11 Xe-133m 1. 4321E-02 3.1917E-11 1. 4452E+14 4.8745E+09 Xe-135 2.8087E-06 1. 0998E-15 4.9062E+09 9.5607E+05 Control Room Transport Group Inventory:

Time (h) = 168.0036 Atmosphere Sump Noble gases (atoms) 1.2335E+18 0.OOOOE+00 Elemental I (atoms) 1.9102E+14 0.OOOOE+00 Organic I (atoms) 1.4410E+14 0.OOOOE+00

XceI Energy' Calculation No. GEN-PI-087 Revision No.0PaeN.4of5 Aerosols (kg) O.OOOOE+00 O.OOOOE+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 5. 2079E-12 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 5.2124E-12 Total I (Ci) 9. 1067E-03 Deposition Recirculating Time (h) = 168.0036 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) = 168.0036 Filtered Transported Noble gases (atoms) 0.OOOOE+00 1.2364E+18 Elemental I (atoms) 0.OOOOE+00 1.9147E+14 Organic I (atoms) 0.OOOOE+00 1. 4444E+14 Aerosols (kg) 0.OOOOE+00 0.0000E+0o Control Room to Environment Transport Group Inventory:

Pathway Time (h) = 168.0036 Filtered Transported Noble gases (atoms) 2.8997E+15 0.OOOOE+00 Elemental I (atoms) 4.4906E+1I 0.0000E+00 Organic I (atoms) 3.3876E+11 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Exclusion Area Boundary Doses:

Time (h) = 168.0800 Whole Body Thyroid TEDE Delta dose (rem) 4.1884E-02 1.3630E+01 4. 5691E-01 Accumulated dose (rem) 4.2963E-02 1.3982E+01 4. 6868E-01 Low Population Zone Doses:

Time (h) = 168.0800 Whole Body Thyroid TEDE Delta dose (rem) 1.1423E-02 3. 7174E+00 1.2461E-01 Accumulated dose (rem) 1.1717E-02 3. 8132E+00 1.2782E-01 Control Room Doses:

Time (h) = 168.0800 Whole Body Thyroid TEDE Delta dose (rem) 1.1166E-03 1.0268E+01 3. 1376E-01 Accumulated dose (rem) 1.1177E-03 1. 0278E+01 3. 1407E-01 Control Room Compartment Nuclide Inventory:

Time (h) = 168.0800 Ci kg Atoms Decay Kr-85 2.4358E+00 6.2084E-06 4. 3986E+19 2.4810E+13 Kr-85m 9.2895E-11 1.1288E-20 7.9974E+04 9. 5182E+02 1-131 3. 3323E-01 2.6879E-09 1 .2356E+16 3.394 6E+12 1-133 2.8543E-03 2.5197E-12 1. 1409E+13 2.9110E+10 1-135 1.6349E-08 4.6554E-18 2.0767E+07 1.6720E+05 Xe-131m 5. 7132E-01 6.8208E-09 3. 1355E+16 5. 8198E+12

XceI Energy- Calculation No. GEN-PI-087 Revision No. 0 Page No. 47 of 54 Xe-133 6. 2433E+01 3.3354E-07 1. 5103E+18 6. 3606E+14 Xe-133m 5.2814E-01 1 . 1770E-09 5. 3295E+15 5. 3822E+12 Xe-135 1.0308E-04 4.0365E-14 1.8006E+ll 1.0530E+09 Xe-135m 2.8442E-09 3. 1224E-20 1.3928E+05 2. 64 10E+04 Control Room Transport Group Inventory:

Time (h) = 168.0800 Atmosphere Sump Noble gases (atoms) 4.5533E+19 0.OOOOE+00 Elemental I (atoms) 7.0496E+15 0.OOOOE+00 Organic I (atoms) 5.3181E+15 0..0000E+00 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 1. 9220E-10 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 1 .9236E-10 Total I (Ci) 3. 3608E-01 Deposition Recirculating Time (h) = 168.0800 Surfaces Filter Noble gases (atoms) 0.0000E+00 O.O000E+00 Elemental I (atoms) 0.0000E+00 O.OOOOE+00 Organic I (atoms) 0.OOOOE+00 0.O0000E+00 Aerosols (kg) 0.OOOOE+00 O.OOOOE+00 Environment to Control Room Transport Group Inventory:

Pathway Time (h) = 168.0800 Filtered Transported Noble gases (atoms) 0.OOOOE+00 4.9222E+19 Elemental I (atoms) 0.OOOOE+00 7.6227E+15 Organic I (atoms) 0.OOOOE+00 5.7505E+15 Aerosols (kg) 0.0000E+00 0.0000E+00 Control Room to Environment Transport Group Inventory:

Pathway Time (h) = 168.0800 Filtered Transported Noble gases (atoms) 3.6966E+18 0.OOOOE+00 Elemental I (atoms) 5.7247E+14 0.OOOOE+00 Organic I (atoms) 4.3186E+14 0.0000E+00 Aerosols (kg) 0.0000E+00 0.OOOOE+00 Exclusion Area Boundary Doses:

Time (h) = 170.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.1107E-01 6. 874 3E+01 2.3042E+00 Accumulated dose (rem) 2.5403E-01 8. 2725E+01 2.7728E+00 Low Population Zone Doses:

Time (h) = 170.0000 Whole Body Thyroid TEDE Delta dose (rem) 5.7565E-02 1.8748E+01 6.2841E-01 Accumulated dose (rem) 6.9282E-02 2.2561E+01 7. 5623E-01 Control Room Doses:

Time (h) = 170.0000 Whole Body Thyroid TEDE Delta dose (rem) 6.5607E-02 1.2831E+02 3.9724E+00 Accumulated dose (rem) 6.6724E-02 1.3859E+02 4.2865E+00

XceIln C1y Calculation No. GEN-PI-087 Revision No. 0 Page No. 48 of 54 Control Room Compartment Nuclide Inventory:

Time (h) = 170.0000 Ci kg Atoms Decay Kr-85 2. 6411E+00 6. 7319E-06 4.7694E+19 8. 1459E+14 Kr-85m 7.4840E-11 9.0941E-21 6.4431E+04 2.7099E+04 1-131 5.2433E-03 4.2293E-11 1. 9442E+14 2. 3039E+13 1-133 4.2420E-05 3.7447E-14 1. 6956E+ll 1. 9522E+lI 1-135 2.1179E-10 6.0308E-20 2.6903E+05 1. 0901E+06 Xe-131m 6. 1661E-01 7 .3616E-09 3. 3842E+16 1. 9065E+14 Xe-133 6. 6992E+01 3.5790E-07 1. 6205E+18 2. 0776E+16 Xe-133m 5. 5835E-01 1.2443E-09 5. 6343E+15 1.7453E+14 Xe-135 9.6552E-05 3. 7808E-14 1. 6866E+1I 3. 2199E+10 Control Room Transport Group Inventory:

Time (h) = 170.0000 Atmosphere Sump Noble gases (atoms) 4.9354E+19 0.OOOOE+00 Elemental I (atoms) 1.1092E+14 0.OOOOE+00 Organic I (atoms) 8.3675E+13 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 3. 0240E-12 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 3. 0264E-12 Total I (Ci) 5.2857E-03 Deposition Recirculating Time (h) = 170.0000 Surfaces Filter Noble gases (atoms) 0.0000E+00 0.OOOOE+00 Elemental I (atoms) 0.0000E+00 1.1536E+16 Organic I (atoms) 0.OOOOE+00 8.7030E+15 Aerosols (kg) 0.0000E+00 0.0000E+00 Environment to Control Room Transport Group Inventory:

Pathway Time (h) = 170.0000 Filtered Transported Noble gases (atoms) 0.0000E+00 8.5578E+19 Elemental I (atoms) 0.OOOOE+00 1.3245E+16 Organic I (atoms) 0.OOOOE+00 9.9915E+15 Aerosols (kg) O.OOOOE+00 0.OOOOE+00 Control Room to Environment Transport Group Inventory:

Pathway Time (h) = 170.0000 Filtered Transported Noble gases (atoms) 3.6211E+19 0.OOOOE+00 Elemental I (atoms) 1.5844E+15 0.OOOOE+00 Organic I (atoms) 1.1953E+15 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Exclusion Area Boundary Doses:

Time (h) = 176.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 0.OOOOE+00 0.0000E+00 Accumulated dose (rem) 2.5403E-01 8.2725E+01 2.7728E+00 Low Population Zone Doses:

& XceI nergy Calculation No. GEN-PI-087 Revision No. 0 Page No. 49 of 54 Time (h) = 176.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Accumulated dose (rem) 6.9282E-02 2.256!E+01 7. 5623E-01 Control Room Doses:

Time (h) = 176.0000 Whole Body Thyroid TEDE Delta dose (rem) 8.0140E-02 1. 1424E+00 1. 1492E-01 Accumulated dose (rem) 1.4686E-01 1.3973E+02 4.4014E+00 Control Room Compartment Nuclide Inventory:

Time (h) = 176.0000 Ci kg Atoms Decay Kr-85 4. 5374E-01 1.1565E-06 8. 1937E+18 1.7926E+15 1-131 1. 6776E-12 1.3532E-20 6.2205E+04 2.3198E+13 Xe-131m 1.044 1E-01 1.2465E-09 5. 7301E+15 4.1778E+14 Xe-133 1. 1138E+01 5.9506E-08 2. 6944E+17 4. 5292E+16 Xe-133m 8.8622E-02 1. 9751E-10 8. 9429E+14 3. 7551E+14 Xe-135 1.0498E-05 4 . 1108E-15 1.8337E+10 6. 2740E+10 Control Room Transport Group Inventory:

Time (h) = 176.0000 Atmosphere Sump Noble gases (atoms) 8.4698E+18 0.OOOOE+00 Elemental I (atoms) 3.5483E+04 0.OOOOE+00 Organic I (atoms) 2.6768E+04 0.OOOOE+00 Aerosols (kg) 0.0000E+00 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 9.6730E-22 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 9.6796E-22 Total I (Ci) 1. 6889E-12 Deposition Recirculating Time (h) = 176.0000 Surfaces Filter Noble gases (atoms) 0.OOOOE+00 0.OOOOE+00 Elemental I (atoms) 0.OOOOE+00 1.1638E+16 Organic I (atoms) 0.OOOOE+00 8.7798E+15 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Environment to Control Room Transport Group Inventory:

Pathway Time (h) = 176.0000 Filtered Transported Noble gases (atoms) 0.OOOOE+00 8.5578E+19 Elemental I (atoms) 0.0000E+00 1.3245E+16 Organic I (atoms) 0.OOOOE+00 9.9915E+15 Aerosols (kg) 0.OOOOE+00 O.OOOOE+00 Control Room to Environment Transport Group Inventory:

Pathway Time (h) = 176.0000 Filtered Transported Noble gases (atoms) 7.7069E+19 0.OOOOE+00 Elemental I (atoms) 1.5934E+15 0.OOOOE+00 Organic I (atoms) 1.2020E+15 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Exclusion Area Boundary Doses:

XcelEnergy Calculation No. GEN-PI-087 Revision No. 0 Page No. 50 of 54 Time (h) = 192.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 0.0000E+00 0.OOOOE+00 Accumulated dose (rem) 2.5403E-01 8. 2725E+01 2.7728E+00 Low Population Zone Doses:

Time (h) = 192.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 0.OOOOE+00 0.OOOOE+00 Accumulated dose (rem) 6.9282E-02 2. 2561E+01 7.5623E-01 Control Room Doses:

Time (h) = 192.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.5877E-02 3. 6542E-10 1.5877E-02 Accumulated dose (rem) 1.6274E-01 1.3973E+02 4.4173E+00 Control Room Compartment Nuclide Inventory:

Time (h) = 192.0000 Ci kg

Atoms Decay Kr-85 4.1386E-03 1.0549E-08 7.4735E+16 1.9876E+15 Xe-131m 9. 1613E-04 1.0937E-11 5.0280E+13 4. 6233E+14 Xe-133 9.3099E-02 4.9737E-10 2.2521E+15 5.0001E+16 Xe-133m 6. 5451E-04 1. 4587E-12 6.6047E+12 4. 1209E+14 Xe-135 2.8270E-08 1.1070E-17 4.9382E+07 6.6377E+10 Control Room Transport Group Inventory:

Time (h) = 192.0000 Atmosphere sump Noble gases (atoms) 7.7044E+16 0.0000E+00 Elemental I (atoms) 1.6967E-21 0.0000E+00 Organic I (atoms) 1.2800E-21 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 4.6246E-47 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 4.6266E-47 Total I (Ci) 8.0577E-38 Deposition Recirculating Time (h) = 192.0000 Surfaces Filter Noble gases (atoms) 0.OOOOE+00 0.0000E+00 Elemental I (atoms) 0.OOOOE+00 1.1638E+16 Organic I ( atoms) 0.OOOOE+00 8.7798E+15 Aerosols (kg) 0.0000E+00 0.0000E+00 Environment to Control Room Transport Group Inventory:

Pathway Time (h) = 192.0000 Filtered Transported Noble gases (atoms) 0.OOOOE+00 8.5578E+19 Elemental I (atoms) 0.0000E+00 1.3245E+16 Organic I (atoms) 0.OOOOE+00 9.9915E+15 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Control Room to Environment Transport Group Inventory:

Pathway Time (h) = 192.0000 Filtered Transported Noble gases (atoms) 8.5457E+19 0.0000E+00 Elemental I (atoms) 1.5934E+15 0.0000+E00

XceIfnergy, Calculation No. GEN-PI-087 Revision No. 0 Page No. 51 of 54 Organic I (atoms) 1.2020E+15 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Exclusion Area Boundary Doses:

Time (h) = 264.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.OOOOE+00 0.0000E+00 0.OOOOE+00 Accumulated dose (rem) 2.5403E-01 8.2725E+01 2.7728E+00 Low Population Zone Doses:

Time (h) = 264.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.OOOOE+00 0.OOOOE+00 0. OOOOE+00 Accumulated dose (rem) 6.9282E-02 2. 2561E+01 7. 5623E-01 Control Room Doses:

Time (h) = 264.0000 Whole Body Thyroid TEDE Delta dose (rem) 8.0848E-05 1.9903E-35 8.0848E-05 Accumulated dose (rem) 1.6282E-01 1.3973E+02 4.4174E+00 Control Room Compartment Nuclide Inventory:

Time (h) = 264.0000 Ci kg Atoms Decay Kr-85 2.7356E-12 6. 9725E-18 4.9399E+07 1.9892E+15 Xe-131m 5. 0873E-13 6.0736E-21 2. 7921E+04 4. 6268E+14 Xe-133 4.1507E-I1 2 .2175E-19 1.0041E+06 5.0036E+16 Control Room Transport Group Inventory:

Time (h) = 264.0000 Atmosphere Sump Noble gases (atoms) 5.0433E+07 0.OOOOE+00 Elemental I (atoms) 1.9368-135 0.OOOOE+00 Organic I (atoms) 1.4611-135 0.0000E+00 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 5.2779-161 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) 5.2782-161 Total I (Ci) 9.1676-152 Deposition Recirculating Time (h) = 264.0000 Surfaces Filter Noble gases (atoms) 0.OOOOE+00 0.OOOOE+00 Elemental I (atoms) 0.OOOOE+00 1.1638E+16 Organic I (atoms) 0.OOOOE+00 8.7798E+15 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Environment to Control Room Transport Group Inventory:

Pathway Time (h) = 264.0000 Filtered Transported Noble gases (atoms) 0.OOOOE+00 8.5578E+19 Elemental I (atoms) 0.OOOOE+00 1.3245E+16 Organic I (atoms) 0.OOOOE+00 9.9915E+15 Aerosols (kg) O.OOOOE+00 0.OOOOE+00 Control Room to Environment Transport Group Inventory:

Pathway

XceIEnergy ICalculation No. GEN-PI-087 Revision No. 0 Page No. 52 of 54 Time (h) = 264.0000 Filtered Transported Noble gases (atoms) 8.5533E+19 0.OOOOE+00 Elemental I (atoms) 1. 5934E+15 0.OOOOE+00 Organic I (atoms) 1. 2020E+15 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 0.000OE+00 Exclusion Area Boundary Doses:

Time (h) = 888.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.OOOOE+00 0.OOOOE+00 0.000OE+00 Accumulated dose (rem) 2.5403E-01 8.2725E+01 2.7728E+00 Low Population Zone Doses:

Time (h) = 888.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Accumulated dose (rem) 6.9282E-02 2.2561E+01 7. 5623E-01 Control Room Doses:

Time (h) = 888.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.4022E-14 1 5143-149 2.4022E-14 Accumulated dose (rem) 1.6282E-01 1.3973E+02 4.4174E+00 Control Room Compartment Nuclide Inventory:

Time (h) = 888.0000 Ci kg Atoms Decay Control Room Transport Group Inventory:

Time (h) = 888.0000 Atmosphere Sump Noble gases (atoms) 1.3669E-72 0.OOOOE+00 Elemental I (atoms) 0.OOOOE+00 0.OOOOE+00 Organic I (atoms) 0.OOOOE+00 0.0000E+00 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (Thyroid) 0.0000E+00 Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid) O.0OOOOE+00 Total I (Ci) 0.OOOOE+00 Deposition Recirculating Time (h) = 888.0000 Surfaces Filter Noble gases (atoms) 0.OOOOE+00 0.OOOOE+00 Elemental I (atoms) 0.OOOOE+00 1.1638E+16 Organic I (atoms) 0.OOOOE+00 8.7798E+15 Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 Environment to Control Room Transport Group Inventory:

Pathway Time (h) = 888.0000 Filtered Transported Noble gases (atoms) 0.OOOOE+00 8.5578E+19 Elemental I (atoms) 0.000OE+00 1.3245E+16 Organic I (atoms) 0.0000E+00 9.9915E+15 Aerosols (kg) 0.000OE+00 0.OOOOE+00 Control Room to Environment Transport Group Inventory:

Pathway

9~XceIEnergy, Calculation No. GEN-PI-087 Revision No. 0 Page No. 53 of 54 Time (h) = 888.0000 Filtered Transported Noble gases (atoms) 8. 5533E+19 0.OOOOE+00 Elemental I (atoms) 1. 5934E+15 0.OOOOE+00 Organic I (atoms) 1.2020E+15 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 0.0000E+00 839 1-131 Summary

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

Fuel Pool Environment Control Room Time (hr) 1-131 (Curies) 1-131 (Curies) 1-131 (Curies) 168.000 5.2469E+01 3.4112E-02 2.1597E-04 168.004 3.3879E+02 1.4290E+00 9.0292E-03 168.080 2.8325E+02 5.6875E+01 3.3323E-01 168.400 1.3380E+02 2.0606E+02 1.8170E-01 168.700 6.6241E+01 2.7351E+02 9.7480E-02 169.000 3.2793E+01 3.0690E+02 5.0781E-02 169.300 1.6234E+01 3.2343E+02 2.5985E-02 169.600 8.0370E+00 3.3161E+02 1.3147E-02 169.900 3.9788E+00 3,3567E+02 6.6038E-03 170.000 3.1475E+00 3.3650E+02 5.2433E-03 170.300 3.1442E+00 3.3650E+02 1.7573E-03 170.600 3.1408E+00 3.3650E+02 5.8900E-04 170.900 3.1374E+00 3.3650E+02 1.9741E-04 171.200 3.1340E+00 3.3650E+02 6.6164E-05 171.500 3.1306E+00 3.3650E+02 2.2176E-05 171.800 3.1273E+00 3.3650E+02 7.4324E-06 172.100 3.1239E+00 3.3650E+02 2.4910E-06 172.400 3.1205E+00 3.3650E+02 8.3490E-07 172.700 3.1172E+00 3.3650E+02 2.7983E-07 173.000 3.1138E+00 3.3650E+02 9.3787E-08 173.300 3.1105E+00 3.3650E+02 3.1434E-08 173.600 3.1071E+00 3.3650E+02 1.0535E-08 173.900 3.1038E+00 3. 3650E+02 3.5311E-09 174.200 3.1004E+00 3.3650E+02 1.1835E-09 174.500 3.0971E+00 3.3650E+02 3. 9665E-10 174.800 3.0937E+00 3.3650E+02 1.3294E-10 175.100 3.0904E+00 3.3650E+02 4.4557E-11 175.400 3.0871E+00 3.3650E+02 1.4934E-11 175.700 3.0838E+00 3.3650E+02 5.0053E-12 176. 000 3.0804E+00 3.3650E+02 1. 6776E-12 176.300 3.0771E+00 3.3650E+02 5.6226E-13 176.600 3.0738E+00 3.3650E+02 1.8845E-13 176.900 3.0705E+00 3.3650E+02 6.3160E-14 177.200 3.0672E+00 3.3650E+02 2.1169E-14 177.500 3. 0639E+00 3.3650E+02 7.0950E-15 177 .800 3. 0606E+00 3.3650E+02 2.3780E-15 178.100 3. 0573E+00 3.3650E+02 7.9700E-16 178.400 3. 0540E+00 3.3650E+02 2.6712E-16 192.000 2.9084E+00 3.3650E+02 8.0239E-38 264.000 2.2456E+00 3.3650E+02 9.1631-152 888.000 2.3870E-01 3.3650E+02 0.OOOOE+00

XceI Energy, calculation No. GEN-PI-087 Revision No. 0 Page No. 54 of 54 Cumulative Dose Summary 4####################################################################

Exclusion Area Bounda Low Population Zone Control Room Time Thyroid TEDE Thyroid TEDE Thyroid TEDE (hr) (rem) (rem) (rem) (rem) (rem) (rem) 168.000 0.OOOOE+00 0.0000E+00 0 OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 168.004 3 . 5119E-01 1.1772E-02 9. 5780E-02 3.2106E-03 9.9484E-03 3.0399E-04 168.080 1.3982E+01 4.6868E-01 3. 8132E+00 1.2782E-01 1.0278E+01 3.1407E-01 168.400 5. 0659E+01 1.6981E+00 1.3816E+01 4 .6312E-01 7.3620E+01 2.2532E+00 168.700 6.7240E+01 2.2539E+00 1. 8338E+01 6.1470E-01 1.0568E+02 3.2407E+00 169.000 7.5449E+01 2.5290E+00 2 .0577E+01 6. 8973E-01 1.2265E+02 3.7683E+00 169.300 7.9513E+01 2.6652E+00 2. 1685E+01 7 .2688E-01 1.3141E+02 4.0458E+00 169.600 8.1525E+01 2.7326E+00 2 .2234E+01 7 4526E-01 1.3587E+02 4.1917E+00 169.900 8.2521E+01 2.7660E+00 2. 2506E+01 7 .5437E-01 1.3812E+02 4.2694E+00 170.000 8.2725E+01 2.7728E+00 2 .2561E+01 7. 5623E-01 1.3859E+02 4.2865E+00 170.300 8.2725E+01 2.7728E+00 2. 2561E+01 7. 5623E-01 1.3935E+02 4.3178E+00 170. 600 8.2725E+01 2.7728E+00 2.2561E+01 7 .5623E-01 1.3960E+02 4.3331E+00 170.900 8.2725E+01 2.7728E+/-00 2. 2561E+01 7 .5623E-01 1.3969E+02 4.3426E+00 171.200 8. 2725E+01 2.7728E+00 2.2561E+01 7. 5623E-01 1. 3972E+02 4.3498E+00 171.500 8.2725E+01 2. 7728E+00 2 .2561E+01 7. 5623E-01 1.3973E+02 4.3559E+00 171.800 8. 2725E+01 2 .7728E+00 2 .2561E+01 7. 5623E-01 1.3973E+02, 4.3612E+00 172.100 8 .2725E+01 2 .7728E+00 2.2561E+01 7. 5623E-01 1.3973E+02 4.3661E+00 172.400 8.2725E+01 2. 7728E+00 2. 2561E+01 7. 5623E-01 1.3973E+02 4.3705E+00 172.700 8. 2725E+01 2. 7728E+00 2.2561E+0l 7 .5623E-01 1.3973E+02 4.3745E+00 173.000 8. 2725E+01 2. 7728E+00 2.2561E+01 7 5623E-01 i.3973E+02 4.3782E+00 173.300 8.2725E+01 2. 7728E+00 2.2561E+01 7.5623E-01 1.3973E+02 4.3815E+00 173.600 8.2725E+01 2 .7728E+00 2.2561E+01 7 .5623E-01 1.3973E+02 4.3846E+00 173. 900 8. 2725E+01 2 .7728E+00 2.2561E+01 7.5623E-01 1.3973E+02 4.3874E+00 174 .200 8.2725E+01 2 .7728E+00 2.2561E+01 7.5623E-01 1.3973E+02 4.3900E+00 174.500 8.2725E+01 2.7728E+00 2.2561E+01 7.5623E-01 1.3973E+02 4.3924E+00 174.800 8.2725E+01 2 .7728E+00 2.2561E+01 7.5623E-01 1.3973E+02 4.3945E+00 175.100 8. 2725E+01 2.7728E+00 2.2561E+01 7 .5623E-01 1.3973E+02 4 .3965E+00 175.400 8.2725E+01 2 .7728E+00 2.2561E+01 7.5623E-01 1.3973E+02 4.3983E+00 175.700 8.2725E+01 2.7728E+00 2.2561E+01 7 . 5623E-01 1.3973E+02 4.3999E+00 176.000 8.2725E+01 2.7728E+00 2.2561E+01 7. 5623E-01 1.3973E+02 4.4014E+00 176.300 8.2725E+01 2 .7728E+00 2 .2561E+01 7. 5623E-01 1.3973E+02 4.4028E+00 176.600 8. 2725E+01 2.7728E+00 2.2561E+01 7.5623E-01 1.3973E+02 4.4040E+00 176.900 8.2725E+01 2 .7728E+00 2.2561E+01 7.5623E-01 1.3973E+02 4.4052E+00 177.200 8 .2725E+01 2.7728E+00 2.2561E+01 7. 5623E-01 1.3973E+02 4.4062E+00 177.500 8.2725E+01 2.7728E+00 2.2561E+01 7.5623E-01 1.3973E+02 4.4072E+00 177.800 8.2725E+01 2.7728E+00 2.2561E+01 7. 5623E-01 1.3973E+02 4.4080E+00 178.100 8. 2725E+01 2.7728E+00 2. 2561E+01 7 .5623E-01 1.3973E+02 4.4088E+00 178.400 8.2725E+01 2.7728E+00 2.2561E+01 7.5623E-01 1.3973E+02 4.4096E+00 192.000 8.2725E+01 2.7728E+00 2.2561E+01 7.5623E-01 1.3973E+02 4.4173E+00 264.000 8. 2725E+01 2.7728E+00 2.2561E+01 7. 5623E-01 1.3973E+02 4.4174E+00 888.000 8. 2725E+01 2.7728E+00 2.2561E+01 7 .5623E-01 1.3973E+02 4.4174E+00 Worst Two-Hour Doses

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

Exclusion Area Boundary Time Whole Body Thyroid TEDE (hr) (rem) (rem) (rem) 168.0 2.5403E-01 8.2725E+01 2.7728E+00

ML093160586

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SUMMARY

Purpose:

2.0 METHODOLOGY

4.0 ASSUMPTIONS

SUMMARY

Conclusions:

9.0 REFERENCES

Subject:

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