ML093160585
| ML093160585 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 10/07/2009 |
| From: | Gita Patel Xcel Energy |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| L-PI-09-114 GEN-PI-077, Rev 0 | |
| Download: ML093160585 (58) | |
Text
ATTACHMENT 7 to ENCLOSURE FHA Analysis titled, "Fuel Handling Accident Dose Analysis - AST" 57 Pages Follow
OF-0549 (FP-E-CAL-01). Rev. 3 Paize 1 of 57 XceI Energy-Calculation'Signature Sheet Document Information NSPM Calculation (Doc) No: GEN-PI-077 Revision: 0
Title:
Fuel Handling Accident Dose Analysis - AST Facility: ] MT Z PI Unit: Z 1 Z 2 Safety Class:
Z SR
[I Aug Q
[] Non SR Special Codes: El Safeguards El Proprietary Type: Calc Sub-Type:
[NOTE:
I Print and sign name in signature blocks, as required.
Major Revisions EC Number: 13720 LI Vendor Calc Vendor Name or Code:
Vendor Doc No:
Description of Revision: Initial Issue '
D:
Prepared by: Gopal J. Patel Date: 10107/2009 Reviewed by: Thomas.J. Msci Date: 10/08/2009 Type of Review: 0 Design Verif ation Lf-T-ch Review LI Vendor Acceptance Method Used (For OV On,): i.Review D Alternate Calc F1 Test Approved by:
zc, Date: )6h 5/1 Minor Revisions EC No:
III Vendor Caic:
Minor Rev. No:
Description of Change:
Pages Affected:
Prepared by:
Date:
Reviewed by:
Date:
Type of Review: El Design Verification E] Tech Review F1 Vendor Acceptance Method Used (For DV Only): E] Review El Alternate Calc LI Test Approved by:
Date:
(continued on next page)
'~1 Record Retention: Retain this form with the associated calculation for the life of the plant.
QF-0549 (FP-E-CAL-01), Rev. 3 Pa~e 2 of 57 Xcei Energy-Calculation Signature Sheet EC No:
El Vendor Caic:
Minor Rev. No:
Description of Change:
Pages Affected:
Prepared by:
Date:
Reviewed by:I Date:
Type of Review: El Design Verification E-Tech Review E] Vendor Acceptance Method Used (For DV Only):
1 Review El Alternate Calc E] Test Approved by:
Date:
EC No:
El Vendor Caic:
Minor Rev. No:
Description of Change:
Pages Affected:
Prepared by:
Date:
Reviewed by:
Date:
Type of Review: E] Design Verification El Tech Review -- Vendor Acceptance Method Used (For DV Only): E]- Review [-- Alternate Calc E-1 Test Approved by:
Date:
EC No:
E Vendor Calc:
Minor Rev. No:
Description of Change:
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Prepared by:
Date:-
Reviewed by:
Date:
Type of Review: E] Design Verification E] Tech Review [-- Vendor Acceptance Method Used (For DV Only): E Review El Alternate Calc [El Test Approved by:
I Date:
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 57 QF-054 (F-ECL-1, Re.3Pg T
f5
.XceI Energy 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.
Reference Documents (PassPort C012 Panel from C020)
Controlled*
Document Name Document Number Doc Rev Ref Type**
Doc? + Type (if known)
Alternative Radiological Source Terms for Evaluating I
Design Basis Accidents at Nuclear Power Reactors, July 1.183 July 2000 MInput [-]Output 2000 2
A Simplified Model for Radionuclide Transport and NUREG/CR-6604 Dec 1997 NInput -Output Removal and Dose Estimation 3
N LTR Westinghouse Letter,
Subject:
Core Activity Inventory and Letter NSP-07-59, 11/2/7 MInput DOutput Coolant Activity Concentration Le S
7
,/In t
4 N TRNS FHA Input Parameters DIT# 13720-04 0
NInput --Output 5
M TRNS Control Room Input Parameters DIT # 13720-07 1
Ninput [-lOutput 6
Z TRNS Meteorological Input Parameters DIT # 13720-03 0
ZInput [-]Output 7
Z CALC Prairie Island Atmospheric Dispersion Factors (X/Q) -
GEN-PI-080 0
ZInput L-lOutput AST Additional Releases U1/U2 8
Z Tech Spec PINGP Units I & 2, Definition of Rated Thermal Power 1.1 Amendment Minput D--Output 158/149 Ul/U2
[Input [--Output 9
M Tech Spec PINGP Units I & 2 LCO for Refueling Cavity Water Level 3.9.2 Amendment 158/149 PINGP Units I & 2 LCO for Spent Fuel Storage Pool UI/U2 MInput
--Output 10 Tech Spec Water Level 3.7.15 Amendment 158/149 U1/U2 Flinput ElOutput 11 Tech Spec Fuel Assemblies 4.2.1 Amendment 158/149
QF-0549 (FP-E-CAL-01), Rev. 3 Paqe 4 of 57 XceI Energy-Calculation Signature Sheet PINGP Units 1 & 2 Ventilation Filter Testing Program UI/U2 ZInput ElOutput 12 Z Tech Spec (VFTP) 5.5.9 Amendment 186/176 PINGP Units 1 & 2 LCO for Shield Building Ventilation U 1/U2 MInput [-]Output 13 Z Tech Spec 3.6.9 Amendment System (SBVS) 186/176 PINGP Units 1 & 2 LCO for Control Room Special Ul/U2 ZInput EjlOutput 14Ventilation System (CRSVS) 3.7.10 Amendment 158/149 PINGP Units 1 & 2 LCO for Spent Fuel Pool Special UI/U2 ZInput joutput 15 Z Tech Spec Ventilation System (SFPSVS) 3.7.13 Amendment 158/149 Control Room Special Ventilation System (CRSVS)
Ul/U2 A
nnput
[]output 16 Z Tech Spec Actuation Instrumentation Including Table 3.3.6-1 3.3.6 Amendment 158/149 Perform required SBVS filter testing in accordance with Ul/U2
[Input [-]Output 17 Z TS SR Pe Ventiation Filter Testing ingam with SR 3.6.9.2 Amendment the Ventilation Filter Testing Program (VFTP) 158/149 Perform required SFSVS filter testing in accordance with Ul/U2 Zinput L--Output 18 Z TS SR the Ventilation Filter Testing Program (VFTP)
SR 3.7.13.2 Amendment 186/176 19 Z CALC Fission Product Inventories for AST Assessments GEN-PI-046 0
--Input ZOutput 20 Z CALC PI Control Room Atmospheric Dispersion Factors GEN-PI-049 0, Add 2 E-]Input ZOutput 21 Z CALC Fuel Handling Accident Dose Analysis GEN-PI-051 1,
[:]Input ZOutput 22 Z CALC Fuel Handling Accident Dose Analysis - Heavy Load GEN-PI-051 1, Add 1
[-]Input
]Output Drop PINGP Amendment Nos. 166 and 156 to Operating ZInput [-]Output 23 LA License Nos. DPR-42 and DPR-60, respectively, Selective LA # 166 & 156 Implementation Of Alternate Source Term For Fuel Handling Accidents 24 USNRC, "Laboratory Testing of Nuclear-Grade Activated 99-02 5/3/99 Input
-- Output Charcoal 25 Accident Source Term 10 CR 50.67 ZInput [--Output
QF-0549 (FP-E-CAL-01), Rev. 3 Paae 5 of 57 XceIEnergy-Calculation Signature Sheet 26 Radiological Consequence Analyses Using Alternative 15.0.1 0
ZInput
-ji-Output Source Terms 27 Federal Guidance Report 11 EPA-520/1-88-020 ZInput -Output 28 Federal Guidance Report 12 EPA-402-R-93-081 ZInput -JlOutput 29 RPRT Prairie Island Units I & 2 422V+ Reload Transition Safety Westinghouse 0
ZInput --lOutput Report 30 M DRAW PINGP HVAC Plan EL 755'-0" - Unit I NF-39609-1 T
ZInput -- Output 31 Z DRAW PINGP HVAC Plan EL 755'-0" - Unit 1 NF-39609-2 Z
Zinput ilOutput 32 Z DRAW PINGP HVAC Spent Fuel Pool - Plan At EL 755'-0" NF-39609-3 J
ZInput [--Output 33
[
DRAW PINGP HVAC Spent Fuel Pool - Section At EL 755'-0" NF-39609-25 D
ZInput -- Output 34 DRAW P1NGP Ventilation Flow Diagrams Reactor Building Unit NF-39602-1 76 MInput DOutput I
35 Z DRAW PINGP Ventilation Flow Diagram Reactor Building Unit 2 NF-39602-2 76 36 M DRAW PINGP Architectural Drawing Operating Floor Plan @ EL NF-38502 76 ZInput DOutput 735'-0" Z DRAW PINGP Architectural Drawing Fuel Handling Floor @ EL NF-38503, K
ZInput L]Output 37 755'-0" 38 Z DRAW PINGP Architectural Drawing East Elevation NF-38510 J
ZInput -- Output 39 Z DRAW PINGP Architectural Drawing West Elevation NF-38511 G
ZInput FlOutput 40 Z USAR PJNGP USAR Appendix D - Activity In Fuel Gap Section D.2 MInput
--Output.
41 N USAR PINGP USAR Appendix D - Activity In One Fuel Table D.3-2
-]Input ZOutput Assembly At 50 Hours After Shutdown 42 M USAR PINGP USAR Appendix D - Thyroid Dose Conversion Table D.8-2 E-]nput ZOutput Factors for Iodine Inhalation 43 Z USAR PINGP USAR Appendix D - Standard Man Breathing Table D.8-3
-- Input ZOutput Rates 44 Z CALC FHA Fission Product Inventories for AST Assessments GEN-PI-047 0
-]input [Output 45 Z CALC FHA Fission Product Inventories for AST Assessments GEN-PI-047 0, Add I
-- Input ZOutput 46 M USAR Fuel Handling Section 14.5.1 47 Z USAR Assumptions Used for FHA in Containment Dose Analysis Table 14.5-1 Dinput ZOutput (AST) 48 Z USAR Control Room Parameters for FHA Dose Analyses Table 14.5-2 F-l-]nput ZOutput
QF-0549 (FP-E-CAL-01),
ev. 3 Paqe 6 of 57 SXce Energy l
Calculation Signature Sheet 49 USAR Summary of 0-2 Hours X/Q Results for Control Room Table 14.5-3 1
-lInput [Output Intake Fuel Handling Accident 50 Z CALC Post-LOCA EAB, LPZ, and CR Doses - AST GEN-PI-079 0
[Input -- Output Design, Testing, and Maintenance Criteria for Post 51 Accident Engineered-Safety-Feature Atmosphere Cleanup 1.52 2
EInput [:]Output 51 System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants NF-39603-1, Rev 52 Z DRAW Admin Bldg, Screen House, & Control RM Flow Diagram 76, Including T-76 EInput -]Output Mod EC 14090 Salem Nuclear Generating Station, Unit Nos. 1 and 2, Issuance of License Amendments 271 and 252 to 53 Operating License Nos. DPR-70 and DPR-75, respectively, LA # 271 & 252 02/17/2006 ZInput [-]Output Alternate Source Term (TAC Nos. MC3094 and MC3095),
NRC ADAMS Accession Number ML060040322
- 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 7 of 57 XceIEnergy I Calculation Signature Sheet Other Pass Port Data Associated System (PassPort C01, first three columns)
OR Equipment References (PassPort C025, all five columns):
Facility Unit System Equipment Type Equipment Number PI 0
ZF SYS SYSOZF PI 0
ZF FILTER 069--221 PI 0
ZF FILTER 069-222 PI 0
ZN FILTER 069-241 PI 0
ZN FILTER 069-242 PI 0
RD RM RM-24 Superseded Calculations (PassPort C019):
Facility Calc Document Number Title PI GEN-PI-051, Rev 1 Fuel Handling Accident Dose Analysis Description Codes - Optional (PassPort C018):'
Code Description (optional)
Code Description (optional)
Notes (Nts) - Optional (PassPort X293 from C020):
Topic Notes Text E] Calc Introduction Z* Copy directly from the calculation Intro.Paragraph or E-] 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 fuel handling accident (FHA) occurring with the reactor being shutdown for at least 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. The post-FHA 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.
IE] (Specify)
XceIEnergy Calculation No. GEN-PI-077 Revision No. 0 Page No. 8 of 57 Sheet of DOCUMENT NUMBER/ TITLE:
GEN-PI-077/ Fuel Handling Accident Dose Analysis - AST REVISION:
0 DATE:
ITEM REVIEWER'S COMMENTS PREPARER'S REVIEWER'S RESOLUTION DISPOSITION I
Various editorial comments/suggestions made Incorporated.
Accepted 09/10/99 in the body of the calculation.
2 Section 2.2 indicates that the distance from Distance is the dominant parameter for Accepted 09/10/09 the equipment hatch to the CR intake is much determining dispersion. Therefore, it is farther than the distance from the CA and not necessary to address wind therefore there is more atmospheric direction.
dispersion. Distance is only one part of the dispersion. We also need to say something about the direction (specifically with reference to the prevailing direction).
3 Section 4.3 says; "It is assumed that the curie The isotope-specific curie per Accepted 09/10/09 per Megawatt-thermal inventory of fission megawatt values are based on products in the reactor core and available for 1683 MWt (see Table I). The curie gap release from damaged fuel is based on the release is based on scaling the Table I core thermal power level of 1,683 MWt curie/MWt values by the assumed including 2% power level measurement operating power level of 1852 MWt.
instrument uncertainty." Do you really mean 1852 as used in RADTRAD?
4 Design Input 5.3.1.2 (Isotopic Core See response to Item 43. The Accepte Inventory) is listed as "@ 1683 MWt?'. Why curie/MWt data in DI 5.3.1.2 is based is 1683 specified and not 1852 as used in on 1683 MWt.
RADTRAD?
5 Design Input 5.3.1.2 (Isotopic Core There are no additional Xenon Accepted 09/10109 Inventory); why are there additional xenon isotopes. Each of the Xenon isotopes isotopes included? (Also listed in Section listed in DI 5.3.1.2 and Section 7.1 is 7.1) present at time of reactor shutdown (See Table 1). These isotopes are input into the RADTRAD runs (See Attachment A output file echo of input data). Some of these isotopes will have decayed away by time 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />, when the FHA is assumed to occur.
XceIEnergy-Calculation No. GEN-PI-077 Revision No. 0 Page No. 9 of 57 Xcel Energy-Design Review Comment Form Sheet _
of DOCUMENT NUMBER/ TITLE:
GEN-PI-077/ Fuel Handling Accident Dose Analysis - AST REVISION:
0 DATE:
ITEM REVIEWER'S COMMENTS PREPARER'S REVIEWER'S RESOLUTION DISPOSITION 6
Design Input 5.3.1.11 says that the Linear As discussed in Section 2.4, the NRC Accepted 09/10/09 Heat Generation Rate of 6.3 kW/ft is reviewed the PINGP fuel management exceeded. We should at least indicate the program and determined that exceeding calculated amount and the number of bundles an LHGR of 6.3 kW/Mt is acceptable.
that exceed the limit.
Describing by how much the LHGR is exceeded is not needed to support this analysis. The details can be found in cited Reference 9. 11 (PINGP License Amendments 166 and 156).
Section 7.3: Since additional isotopes are The data contained in the modified Accept 9 included in the.nif, the modified.inp file plant file (PI300FHAOO.psf), nuclide should be included to verify no errors exist in inventory file (pifhadef.txt), and the file. Modifying this file can be tricky, release fraction timing file The.nif and.rft files should also be included (pifha_rft.txt) are echoed in the in the calc.
RADTRAD output file that is provided in Attachment A. The output file listing is a better choice for determining what is in these files, because it shows what the output file uses for input data.
8 Section 7.3: need to add RG 1.52 as well as RG 1.52 Revision 2 has been added as Accepted GL 99-02.
a reference. Revision 2 is listed because it is the Revision cited in VFTP Tech Spec Sfion 5.5.9.
Reviewer
___________________09/08/2009 Prepar4 &
.Patel Date: 09/10/2009
S XceIEnergy Calculation No. GEN-PI-077 Revision No. 0 Page No. 10 of 57 REVISION HISTORY Revision Description 0
Initial issue A
+/-1
XcelEnery Calculation No. GEN-PI-077 Revision No. 0 Page No. 11 of 57 SHEET REVISION INDEX SHEET REV SHEET REV 1
0 31 0
2 0
32 0
3 0
33 0
4 0
34 0
5 0
35 0
6 0
36 0
7 0
37 0
8 0
Attachment A 0
9 0
10 0
11 0
12 0
13 0
14 0
15 0
16 0
17 0
18 0
19 01 20 0
21 0
22 0
23 0
24 0
25 0
26 0
27 0
28 0
29 0
30 0
XceIEnergy-Calculation No. GEN-PI-077 Revision No. 0 Page No. 12 of 57 TABLE OF CONTENTS Section Sheet No.
Cover Sheet I
Revision History 10 Sheet Revision Index 1
Table of Contents 12 1.0 Purpose And Summary Report 13 2.0 Methodology 13 3.0 Acceptance Criteria 16 4.0 Assumptions 17 5.0 Design Inputs 22 6.0 Computer Codes & Compliance With Regulatory Requirements
-26 7.0 Calculations 27 8.0 Results Summary And Conclusions 29 9.0 References 30 10.0 Tables 33 11.0 Figures 35 12.0 Affected Documents 37 13.0 Attachment 37 Attachment A - RADTRAD Output File PI300FHA00.o0 38
4XceEnergy Calculation No. GEN-PI-077 Revision No. 0 Page No. 13 of 57 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 fuel handling accident (FHA) occurring with the reactor being shutdown for at least 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. The post-FHA 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.
The Alternative Source Term methodology is the current licensing basis for the PINGP FHA. The FHA re-analysis is performed using the guidance in Regulatory Guide 1. 183, Appendix B, and TEDE dose criteria. Theanalysis supersedes FHA dose Calculation GEN-PI-051 (Refs. 9.9 and 9.10). This analysis differs from that of Calculation GEN-PI-051 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-FHA doses are shown in Section 8.0, which comply with the applicable regulatory allowable dose limits.
2.0 METHODOLOGY
PINGP proposes to submit a License Amendment Request (LAR) to implement a full scope AST. The previous FHA analysis in Calculation GEN-PI-051 was performed to support License Amendment Request (LAR) L-PI-04-001 for selective scope implementation of AST to relax the containment integrity requirement during fuel handling. The NRC issued the facility operating license amendments 166 (PI Unit 1) and 156 (PI Unit 2) and thereby approved FHA analysis supporting the relaxation of the containment integrity and associated Technical Specification changes.
In the postulated FHA, a fuel assembly is assumed to be dropped and damaged during fuel handling.
This accident may take place either in the containment or the spent fuel pool (SFP). The analysis design inputs and assumptions have been chosen such that the results of the single FHA analysis are bounding for the accident occurring in either the containment or the SFP. In order to do so, the most limiting 0 to 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> control room atmospheric dispersion factor (X/Q) was selected from the various potential release paths. The SFP special ventilation system (SFPSVS) and shield building ventilation system (SBVS) are operable by Technical Specification LCO 3.7.13 (Ref. 9.6.9) and LCO 3.6.9 (Ref. 9.6.7), respectively.
Although the analysis does not take credit for filtration by the SFPSVS and SBVS, the systems are not prevented from operating after an FHA. The post-FHA potential release paths are reviewed as follows:
2.1 FHA in SFP Enclosure The SFP HVAC plan is shown in Reference 9.17.3. If the SFPSVS is credited, then the release is filtered before being exhausted through the Shield Building (SB) Vent Stack (Refs. 9.17.1, 9.17.2, & 9.17.3).
Alternatively, the release may be exhausted through the SB Vent Stack with no credit taken for SFPSVS filtration. If normal ventilation is operating and credit is not taken for isolation by the high radiation signal, then the release is to the environment via the normal ventilation exhaust stack at Column M and
Xce!Energy I Calculation No. GEN-PI-077 Revision No. 0,,
Page No. 14 of 57 Row 11 (Refs. 9.17.3 & 9.17.4), which is farther from the CR intake, and therefore has greater atmospheric dispersion than the other potential release locations. Therefore, this release path is non-limiting for the analysis.
The SFP enclosure is located inside the auxiliary building (Ref. 9.17.3) but outside the Auxiliary Building Special Ventilation Zone (ABSVZ) (Refs. 9.17.3 & 9.19.2). This portion of the auxiliary building is a steel structure with sheet metal siding (Ref. 9.19.3, Sections @ COL Row J looking south).
This area is referred to as "common area of auxiliary building" or "CA" in this calculation. This portion of the auxiliary building is not leak tight. In absence of a ventilation system operating, the radioactivity could exit the SFP enclosure by entering the CA, and then directly leak to the CR intake.
2.2 Equipment Hatch When irradiated fuel (decayed more than 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />) is moved from the reactor, the containment integrity is not required to be maintained. For the FHA occurring inside containment, 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, 9.19.3 &
9.19.4).
2.3 FHA in Refueling Pool Inside Containment The Reactor Building ventilation flow diagram is shown in Reference 9.18, which shows that if a FHA 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 CA or Shield Building annulus. When the containment integrity is not maintained, the post-FHA leakage is released to the environment through various potential release paths and the 0 to 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> CR z/Qs 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 I 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 I Control Room Intake 6.04E-04 9.8, Section 8.0 Unit 2 Equipment Hatch Unit 2 Control Room Intake 3.11 E-03 9.8, Section 8.0 Common Area of Aux Bldg Unit I Control Room Intake 6.7]E-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 Spent Fuel Pool Vent Normal Exhaust Stack Unit I Control Room Intake 1.09E-03 9.8, Section 8.0 Spent Fuel Pool Vent Normal Exhaust Stack Unit 2 Control Room Intake 2.82E-03 9.8, Section 8.0 Unit I Shield Bldg Vent Stack Unit I Control Room Intake 3.76E-03 9.5, Section 8.1.1 Unit I Shield Bldg Vent Stack Unit 2 Control Room Intake 8.33E-04 9.5, Section 8.1.1 Unit 2 Shield Bldg Vent Stack Unit 1 Control Room Intake 1.23E-03 9.5, Section 8.1.1 Unit 2 Shield Bldg Vent Stack Unit 2 Control Room Intake 4.53E-03 9.5, Section 8.1.1
XceIEnergy Calculation No. GEN-PI-077 Revision No. 0 Page No. 15 of 57 A review of the above X/Qs indicates that the CA represents the most limiting release path for the FHA occurring either in the SFP or in the containment. Therefore, the post-FHA doses are analyzed using CA to Unit I CR intake X/Qs.
The Safety Evaluation approving the PINGP selective implementation of AST for the 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 SFPSVS and SBVS filters or any change in assumed operation of these systems. Xcel Energy has proposed to remove both the SFPSVS and SBVS filtration systems from the PINGP Technical Specifications. Since the revised analysis in this calculation uses the most limiting 7/Q for the common area of auxiliary building without crediting any filtration, the resulting dose consequences will remain bounding for the post-FHA unfiltered releases from the SFP enclosure and 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 PINGP 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 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 same RADTRAD release model as depicted in Figure 1 is used to model the FHA occurring in either the spent fuel pool inside the SFP enclosure or in the refueling cavity inside Containment. The same model is applicable for each event because the source term and activity transport mechanisms are identical for each scenario.
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 Fuel Building or Containment air space.
This source term, defined in Section 5.3.1, considers one damaged fuel assembly that has decayed for 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />, 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
XceIfnergy-Calculation No. GEN-PI-077 Revision No. 0 Page No. 16 of 57 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. 9.25, Section 3.2.1]). No credit is taken for filtration of the activity released to the environment.
The two FHA events model the same sets of atmospheric dispersion factors that are modeled for releases to the Control Room, EAB, and LPZ (Sections 5.4.11, 5.5.1, and 5.5.5). The 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 are described in Section 5.5.
2.6 CR Air Intake Radiation Monitor Response Post-FHA Xe-133 activity in the CR @ 50.0036 hr (0.22 minute following a FHA) 1.6056 Ci (RADTRAD Run PI300FHA.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 @ 50.0036 hr (0.22 minute following a FHA)
= 1.6056 Ci / 1,737.58 m3 = 9.24E-04 Ci/m 3 = 9.24E-04 pCi/cc, which exceeds CR.monitor setpoint of IE-05 ýtCi/cc for Xe-133 (Section 5.4.12).
Since the Xe-133 activity in the CR is circulated by the CR recirculation flow through the CR air supply duct (Ref. 9.28), the monitor setpoint is instantly exceeded. Therefore, the CR actuation delay of 5 minutes following a FHA is considered extremely conservative, and does not require any further justification.
3.0 ACCEPTANCE CRITERIA:
The following NRC regulatory requirement and guidance documents are applicable to this PINGP Alternative Source Term FHA Calculation:
0 Regulatory Guide 1.183 (Ref. 9.1, Table 6) 10CFR50.67 (Ref. 9.13)
Standard Review Plan section 15.0.1 (Ref. 9.24)
Dose Acceptance Criteria are:
Regulatory Dose Limits Dose Type Control Room (rem)
TEDE Dose 5
6.3
X X eIEnergy-Calculation No. GEN-PI-077 Revision No. 0 Page No. 17 of 57
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. The following sections address the applicability of these modeling assumptions to this PINGP FHA 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 inthis 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 one spent fuel assembly 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 irradiated fuel shall not be removed from the reactor without containment integrity until the unit has been shutdown for at least 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> (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 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> (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 core average burnup of 25 GWD/MTU (Design Inputs 5.3.1.9 & 5.3.1.10).
XCe Energy-Calculation No. GEN-PI-077 Revision No. 0 Page No. 18 of 57 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 Csl 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 waterabove 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).
Fuel Handling Accidents Within Containment For fuel handling accidents postulated to occur within the containment, the following assumption is acceptable to the NRC staff (Ref. 9.1, Appendix B, Section 5).
4.8a 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-FHA activity is removed from the source volume (Section 7.2). 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. 9.25, Section 3.2.1]).
Fuel Handling Accidents Within The SFP Enclosure For fuel handling accidents postulated to occur within the SFP enclosure, the following assumptions are acceptable to the NRC staff (Ref. 9.1, Appendix B, Section 4).
XceIEnergy1 Calculation No. GEN-PI-077 Revision No. 0 Page No. 19 of 57 4.8b It assumed that the radioactive material that escapes from the fuel pool to the SFP enclosure is assumed to be released to the environment over a 2-hour time period (Ref. 9.1, Section B.4.1) (Design Input 5.3.2.6). The activity released from the damaged fuel is postulated to release to the environment over a two-hour period at a rate that will ensure that at least 99% of the post-FHA activity is removed from the source volume (Section 7.2). 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 1 and 2 [Ref. 9.25, Section 3.2.1]).
4.8c It is assumed that the radioactive material released from the fuel pool is not filtered by engineered safety feature (ESF) filter systems such as SFPSVS and SBVS in the radioactivity release analyses.
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:
0 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),
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. 9.26, 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 FHA activity releases are associated with only releases from only I of the 121 fuel assemblies in the core. Consequently, the external airborne cloud dose, containment shine dose, and CR filter shine dose due to a FHA are insignificant (i.e., 0.07 rem x [I / 121] = 0.0006 rem) and are not evaluated for a FHA.
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,
l Xce nergy Calculation No. GEN-PI-077 Revision No. 0 Page No. 20 of 57 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 <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 of this individual should be assumed to be 3.5 x 10-4 cubic meters per second. These assumptions are incorporated as design inputs in Sections 5.4.8 and 5.4.10, respectively.
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. 9.13). 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 is actuated 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. 9.28). The CR XE-133 activity concentration instantly exceeds the monitor setpoint of I E-05 Ci/cc for Xe-133. 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 PINGP FHA 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).
9 XceInergy I Calculation No. GEN-PI-077 Revision No. 0 Page No. 21 of 57 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 <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 3.5 x 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 1.8 x 1 04 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 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 FHA the postulated EAB doses should not exceed the criteria established in RG 1.183 Table 6. 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 FHA the postulated LPZ doses should not exceed the criteria established in RG 1.183 Table 6. 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.
XceI g
Calculation No. GEN-PI-077 Revision No. 0 Page No. 22 of 57 5.0 DESIGN INPUTS 5.1 General Considerations 5.1.1 Applicability of Prior Licensing Basis The Alternative Source Term methodology is the current licensing basis for the PINGP FHA. The PINGP plant specific design inputs and assumptions used in the current facility's design basis FHA analysis were assessed for their validity to represent the as-built condition of the plant and evaluated for their compatibility to meet the AST and TEDE methodology. The analysis in this calculation ensures that analysis assumptions, design inputs, and methods are compatible with the AST and comply with RG 1.183, Appendix B requirements.
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 Control Room special ventilation system (CRSVS) is operable by Technical Specification LCO 3.7.10 (Ref. 9.6.8). The CRSVS air intake monitors are required to be operable by TS 3.3.6 and Table 3.3.6-1 (Ref. 9.6.10) 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 SFP special ventilation system (SFPSVS) and shield building ventilation system (SBVS) are operable by Technical Specification LCO 3.7.13 (Ref. 9.6.9) and LCO 3.6.9 (Ref. 9.6.7), respectively.
The actuations of the SFPSVS and SBVS are conservatively not credited in the analysis. Although the analysis does not take credit for filtration by the SFPSVS and SBVS, the systems are not prevented from operating after an FHA.
5.1.3 Meteorology Considerations The control room atmospheric dispersion factors (x/Qs) for the several potential post-FHA release points including the Unit 1 & 2 Equipment Hatches, the Common Area of Auxiliary Building (AB), the Spent Fuel Pool Vent Normal Exhaust Stack, 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 post-FHA EAB, LPZ, and CR habitability analyses 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.
9~XceIEnergy-Calculation No. GEN-PI-077 Revision No. 0 Page No. 23 of 57 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 MWt) 10% EPU Power Level Used in 1,852 MWt 110% of 1,683 MWt) the analysis 5.3.1.2 Isotopic Core Inventory (Ci/MWt) @ 1,683 MWt Table I Isotope Activity Isotope Activity Isotope Activity KR-85
- 1.334E+01 1-133 4.259E+00 XE-135 1.931E+02 KR-85M 1.008E+02 1-134 4.758E+00 XE-135M 1.819E+02 KR-87 1.978E+02 1-135 4.068E+00 XE-138 7.203E+02 KR-88 2.631E+02 XE-131M 4.721 E+00 1-131 **
3.359E+00 XE-133 8.537E+02 1-132 3.037E+00 XE-133M 2.668E+01 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.
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 1
9.4.1, Item # 3 Assembly 5.3.1.6 Number of Fuel 121 9.6.4 Assemblies In Core 5.3.1.7 Irradiated Fuel Decay 50 Hrs 9.6.6 &.9.4.1, Item # 6 5.3.1.8 Radial Peaking Factor 1.77 9.16, section 3.5 1.90 Used in the analysis 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 Exceeds this requirement See discussion in Section 2.4
Xce Energy l Calculation No. GEN-PI-077 Revision No. 0 Page No. 24 of 57 Design Input Parameter 7 Value Assigned Reference 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%
0 Organic 0.15%
5.3.2 Activity Transportation 5.3.2.1 Minimum Refueling 23 feet 9.6.2 & 9.6.3 Cavity and Pool Water Depths 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 m3/sec 9.1, Section 4.2.6 5.4.9 CR Allowable Dose Limit 5 rem TEDE for the event 9.13 duration 5.4.10 CR Occupancy Factors Time (Hr) 9.1, Section 4.2.6 0-24 100 24-96 60 96-720 40
l XceEnergy l Calculation No. GEN-PI-077 Revision No. 0 Page No. 25 of 57 Design Input Parameter Value Assigned Reference 5.4.11 Unit 2 CR x/Qs For FHA Release Through Common Area of Auxiliary Building (CA)
Time (Hr)
X/Q (sec/m 3) 9.5, Section 8.1.3 0-2 6.71E-03 2-8 2.89E-03 8-24 1.22E-03 24-96 9.21 E-04 96-720 7.44E-04 5.4.12 CR Monitor Setpoint 1.OE-05 ptCi/ml for Xe-133 9.4.2, Item # 9 5.5 Site Boundary Release Model Parameters 5.5.1 EAB Atmospheric 6.49E-04 sec/m 3 9.4.2, Item # 2 Dispersion Factor (X/Q) 5.5.2 EAB Breathing Rate 3.5E-04
- 9. 1, Section 4.1.3 (m3/sec) 5.5.3 LPZ Distance 2,414 m 9.4.3, Item # 3 5.5.4 LPZ Breathing Rate (m 3/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 5.5.5 LPZ Atmospheric Dispersion Factors (7X/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
XceI Energy Calculation No. GEN-PI-077 Revision No. 0 Page No. 26 of 57 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. 9.26, 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 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 B.
XceIfnergy-Calculation No. GEN-PI-077 Revision No. 0 Page No. 27 of 57 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 PIFHAdef.txt is used in the analysis.
Similarly, the Release Fraction Timing File (RFT) PIFHA_rft.txt, and Dose Conversion File (DCF)
PIFHA-fg I& I12.txt are generated to support the FHA analysis. The DCF input file includes additional noble gas isotopes (Xe-131 M, Xe-133M, Xe-135M, and Xe-138) for completeness.
7.2 Activity Release Rates The SFP is assigned a source node volume of 1,000 ft3 and 99% of the post-FHA 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-xt Where; Ao = 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 / A0 = e't 0.01 = e2 k In (0.01) = - 2X In(e)
- 4.605 = - 2 ?,
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. 9.27) 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:
9 XceEnergy I Calculation No. GEN-PI-077 Revision No. 0 Page No. 28 of 57 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 ril = charcoal filter efficiency to be credited in the analysis CRSVS Charcoal Filter 2.5% = (100% - rl)/2 5% = (100%-,q)
= 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% - ri)/safety factor = (100% - rl)/2 Where ri = HEPA filter efficiency to be credited in the analysis CRSVS HEPA Filter 0.05% = (100% - T))/2 0.10% = (100% -'i) 9 = 100% - 0.10% = 99.9%
Regulatory Guide 1.52 (Ref. 9.27, 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
XceI Energy-Calculation No. GEN-PI-077 Revisi on No. 0 Page No. 29 of 57 8.0 RESULTS
SUMMARY
/CONCLUSIONS:
8.1 Result Summary:
The post-FHA EAB, LPZ, and CR doses are summarized in the following table:
Post-FHA Post-FHA TEDE Dose (Rem)
Activity Release Receptor Location Path Control Room EAB LPZ Common Area of Auxiliary 3.64E+00 2.28E+00 6.21 E-01 Building (50.0 hr after shutdown; 0.0 hr following FHA)
Total 3.64E+00 2.28E+00 6.21E-01 Allowable TEDE Limit 5.OE+00 6.3E+00 6.3E+00 RADTRAD Computer Run No.
PI300FHAOO.oO PI300FHAOO.oO PI300FHAOO.oO I
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 FHA occurring either in the containment or the SFP enclosure without containment integrity.
The results demonstrate that the following PINGP Technical Specification requirements 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 shutdown for at least 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> 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. 9.6.11) 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 3.7.13.2 (Ref. 9.6.12) for LCO 3.7.13.
X E r Calculation No. GEN-PI-077 Revision No. 0 Page No. 30 of 57
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. 13720-04, Rev 0, FHA 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 (T/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 3.7.15, Spent Fuel Storage Pool Water Level 6.4 Specification 4.2.1, Fuel Assemblies 6.5 Specification 5.5.9, Ventilation Filter Testing Program (VFTP) 6.6 Basis B 3.9, Refueling Operation 6.7 Specification LCO 3.6.9, Shield Building Ventilation System (SBVS) 6.8 Specification LCO 3.7.10, Control Room Special Ventilation System (CRSVS) 6.9 Specification LCO 3.7.13, Spent Fuel Pool Special Ventilation System (SFPSVS) 6.10 Specification 3.3.6, Control Room Special Ventilation System (CRSVS) Actuation Instrumentation Including Table 3.3.6-1 6.11 Surveillance Requirement SR 3.6.9.2, Perform required SBVS filter testing in accordance with the Ventilation Filter Testing Program (VFTP) 6.12 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 Calculation No. GEN-PI-05 1, Rev 1, Fuel Handling Accident Dose Analysis
- 10.
PINGP Calculation No. GEN-PI-05 1, Rev 1, Addendum 1, Fuel Handling Accident Dose Analysis -
Heavy Load Drop
9 XceIEnergy I Calculation No. GEN-PI-077 Revision No. 0 Page No. 31 of 57
- 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. MCI 843 and MCI 844), 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 1 & 2 422V+ Reload Transition Safety Report, Rev 0, by Westinghouse, May 2008
- 17.
PINGP Auxiliary Building HVAC Drawings:
17.1 NF-39609-1, Rev T, Plan EL 755'-0" - Unit 1 17.2 NF-39609-2, Rev Z, Plan EL 755'-0" - Unit 2 17.3 NF-39609-3, Rev J, Spent Fuel Pool - Plan At EL 755'-0" 17.4 NF-39609-25, Rev D, Spent Fuel Pool - Section At EL 755'-0"
- 18.
PINGP Ventilation Flow Diagrams:
18.1 NF-39602-1, Rev 76, Reactor Building Unit I 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-38503, Rev K, Fuel Handling Floor @ EL 755'-0" 19.3 NF-385 10, Rev J, East Elevation 19.4 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.3-2, Activity In One Fuel Assembly At 50 Hours After Shutdown 20.3 Table D.8-2, Thyroid Dose Conversion Factors for Iodine Inhalation 20.4 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.
Not Used.
- 23.
PINGP USAR Section 14.5.1 & Tables:
23.1 Section 14.5.1, Fuel Handling 23.2 Table 14.5-1, Assumptions Used for FHA in Containment Dose Analysis (AST)
9 XceInergy-Calculation No. GEN-PI-077 Revision No. 0 Page No. 32 of 57 23.3 Table 14.5-2, Control Room Parameters for FHA Dose Analyses 23.4 Table 14.5-3, Summary of 0-2 Hours X7Q Results for Control Room Intake Fuel Handling Accident
- 24.
NUREG-0800, Standard Review Plan, "Radiological Consequence Analyses Using Alternative Source Terms," SRP 15.0.1, Rev. 0, July 2000
- 25.
Salem, Unit Nos. I 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)
- 26.
PINGP Calculation No. GEN-PI-079, Rev 0, Post-LOCA EAB, LPZ, and CR Doses - AST
- 27.
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
- 28.
PINGP Flow Diagram No. NF-39603-1, Rev 76, Including T-Mod EC 14090, Admin Bldg, Screen House, & Control RM Flow Diagram
Xcelfnergy Calculation No. GEN-PI-077 Revision No. 0 Page No. 33 of 57 10.0 TABLES Table 1 Un-decayed Post-FHA Activity Released From Damaged Fuel Assembly 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 Assembly Fuel DF Inventor 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 1
2.245E+04 1.0 2.245E+04 1.334E+01 KR-85M 1.08E+07 1.90 121 1
1.696E+05 1.0 1.696E+05 1.008E+02 KR-87 2.12E+07 1.90 121 1
3.329E+05 1.0 3.329E+05 1.978E+02 KR-88 2.82E+07 1.90 121 1
4.428E+05 1.0 4.428E+05 2.631E+02 1-131**
7.20E+07 1.90 121 1
1.131E+06 200.0 5.653E+03-3.359E+00 1-132 6.51E+07 1.90 121 1
1.022E+06 200.0 5.111E+03 3.037E+00 1-133 9.13Et07 1.90 121 1
1.434E+06 200.0 7.168E+03 4.259E+00 1-134 1.02E+08 1.90 121 1
1.602E+06 200.0 8.008E+03 4.758E+00 1-135 8.72E+07 1.90 121 1
1.369E+06 200.0 6.846E+03 4.068E+00 XE-131M 5.06E+05 1.90 121 1
7.945E+03 1.0 7.945E+03 4.721E+00 XE-133 9.15E+07 1.90 121 1
1.437E+06 1.0 1.437E+06 8.537E+02 XE-133M 2.86E+06 1.90 121 1
4.491E+04 1.0 4.491E+04 2.668E+01 XE-135 2.07E+07 1.90 121 1
3.250E+05 1.0 3.250E+05 1.931E+02 XE-135M 1.95E+07 1.90 121 1
3.062E+05 1.0 3.062E+05 1.819E+02 XE-138 7.72E+07 1.90 121 1
1.212E+06 1.0 1.212E+06 7.203E+02 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.
XceIEnergy-Calculation No. GEN-PI-077 Revision No. 0 Page No. 34 of 57 Table 2 Comparison of Gap Fractional Releases for Prairie 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
Xce Energy" Calculation No. GEN-PI-077 Revision No. 0 Page No. 35 of 57 11.0 FIGURES:
Source Node Volume V = 1,000 ft3 Figure 1: FHA Occurring Either In SFP Enclosure or Containment Building, RADTRAD Nodalization
XceI Energy" Calculation No. GEN-PI-077 Revision No. 0 Page No. 36 of 57 Figure 2 - PINGP Post-FHA Control Room Response AST RADTRAD Nodalization
A A XceIEfnergy' Calculation No. GEN-PI-077 Revision No. 0 Page No. 37 of 57 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 P1NGP Calculation No. GEN-PI-05 1, Rev I, Fuel Handling Accident Dose Analysis 12.3 PINGP Calculation No. GEN-PI-047, Rev 0, FHA Fission Product Inventories for AST Assessments 12.4 PINGP Calculation No. GEN-PI-047, Rev 0, Addendum 1, FHA Fission Product Inventories for AST Assessments 12.5 PINGP USAR Appendix D Section D.2 & Tables:
12.6.1 Section D.2, Activity In Fuel Gap 12.6.2 Table D.3-2, Activity In One Fuel Assembly At 50 Hours After Shutdown 12.6.3 Table D.8-2, Thyroid Dose Conversion Factors for Iodine Inhalation 12.6.4 Table D.8-3, Standard Man Breathing Rates 12.6.
PINGP USAR Section 14.5.1 & Tables:
12.7.1 Section 14.5.1, Fuel Handling 12.7.2 Table 14.5-1, Assumptions Used for FHA in Containment Dose Analysis (AST) 12.7.3 Table 14.5-2, Control Room Parameters for FHA Dose Analyses 12.7.4 Table 14.5-3, Summary of 0-2 Hours x/Q Results for Control Room Intake Fuel Handling Accident 13.0 ATTACHMENTS:
Attachment A - RADTRAD Output File PI300FHA00.o0
XceI Ene ry Y-Calculation No. GEN-PI-077 Revision No. 0 Page No. 38 of 57 Attachment A RADTRAD Output File PI300FHAOO.oO
- 44#####################4##########4#########4##############
RADTRAD Version 3.03 (Spring 2001) run on 4/06/2009 at 23:25:11
- 4 44444#########4#4##4############4
- 4####4#44###4##44444##4#44####4 File information 444#############4#############44444#####4########44#4#####4####4 4
- 4 Plant file
= G:\\Radtrad 3.03\\Input\\PI\\PI-GEN-077\\PI300FHA0O.psf Inventory file
= g:\\radtrad 3.03\\defaults\\pifha def.txt Release file
= g:\\radtrad 3.03\\defaults\\pifharft.txt Dose Conversion file = g:\\radtrad 3.03\\defaults\\pifhafgll&12.txt
- 4###
4 4# #
4 4
4####
- 4
- 4 #
4 4# #
Radtrad 3.03 4/15/2001 Prairie Island FHA AST Analysis -
CR Charcoal Filtration Starts @ 5 minutes, and CR Unfiltered Inleakage = 300 cfm Nuclide Inventory File:
g:\\radtrad 3.03\\defaults\\pifhadef.txt Plant Power Level:
1.8520E+03 Compartments:
3 Compartment 1:
Fuel Pool 3
1.OOOOE+03 0
0 0
0 0
Compartment 2:
Environment 2
0.0000E+00 0
0 0
0
XceI Energy-Calculation No. GEN-PI-077 Revision No. 0 Page No. 39 of 57 0
Compartment 3:
Control Room 1
6.1315E+04 0
0 1
0 0
Pathways:
3 Pathway 1:
FHA Release 1
2 2
to Environment Pathway 2:
Environment 2
3 2
Pathway 3:
Control Room 3
2 2
End of Plant to Control Room to Environment Model File Scenario Description Name:
Plant Model Filename:
Source Term:
1 1
1.0000E+00 q:\\radtrad 3.03\\defaults\\pifhafgll&12.txt q:\\radtrad 3.03\\defaults\\pifha._rft.txt 5.0000E+01 1
0.0000E+00 5.7000E-01 4.3000E-01 1.0000E+00 OVerlying Pool:
0 o.0000E+00 0
0 0
0 Compartments:
3 Compartment 1:
0 1
0 0
0 0
0
Xce Energy-Calculation No. GEN-PI-077 Revision No. 0 Page No. 40 of 57 0
0 Compartment 2:
0 1
0 0.
0 0
0 0
0 Compartment 3:
0 0
0 0
1
- 3. 6000E+03 3
- 5. OOOOE+O1
- 5. 0083E+01
- 7. 7000E+02 0
0 Pathways:
3 Pathway 1:
0 0
0 0
0 1
2
- 5. OOOOE+01
- 5. 2000E+01 0
0 0
0 0
0 Pathway 2:
0 0
0 0
0 1
3
- 5. OOOOE+O1
- 5. 0083E+01 7.7000E+02 0
0.OOOOE+00
- 9. 9000E+01 o.OOOOE+00 0.OOOOE+00
- 9. 5000E+01 o.OOOOE+00 0.OOOOE+00
- 9. 5000E+01 o.OOOOE+00
- 3. 9000E+01 0.OOOOE+00 o.OOOOE+00 o.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 A
A 2.OOOOE+03 3.OOOOE+02 0.OOOOEE+00 o.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 o.OOOOE+00 0.OOOOE+00
Xcel Energy Calculation No. GEN-PI-077 Revision No. 0 Page No. 41 of 57 0
0 0
0 0
Pathway 3:
0 0
0 0
0 1
3 5.0000E+01 5.0083E+01 7.7000E+02 0
2.0000E+03 3.0000E+02 0.0000E+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 o.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0
0 0
0 0
Dose Locations:
3 Location 1:
Exclusion Area Boundary 2
1 2
- 5. OOOOE+01 7.7000E+02 1
2
- 5. OOOOE+01 7.7000E+02 0
Location 2:
Low Population 2
1 5
5.OOOOE+01 5.8000E+01 7.4000E+01 1.4600E+02 7.7000E+02 1
4 5.OOOOE+01 5.8000E+01 7.4000E+01 7.7000E+02 0
Location 3:
Control Room 3
0 6.4900E-04 0.OOOOE+00 3.5000E-04 0.OOOOE+00 Zone 1.7700E-04 3.9900E-05 7.1200E-06 1.0400E-06 0.OOOOE+00 3.5000E-04 1.8000E-04 2.3000E-04 0.OOOOE+00
9 Xcelnergyn Calculation No. GEN-PI-077 Revision No. 0 Page No. 42 of 57 1
2 5.OOOE+01 3.5000E-04 7.7000E+02 O.0OOOE+00 1
4 5.O000E+01 1.OOOOE+00 74000E+01 6.OOOOE-01 1.4600E+02 4.OOOOE-01 7.7000E+02 O.OOOOE+00 Effective Volume Location:
1 6
5.0000E+01 6.7100E-03 5.2000E+01 2.8900E-03 5.8000E+01 1.2200E-03 7.4000E+01 9.2100E-04 1.4600E+02 7.4400E-04 7.7000E+02 0.0000E+00 Simulation Parameters:
6 5.0000E+01 1.0000E-01 5.2000E+01 5.OOOOE-01 5.8000E+01 1.0000E+00 7.4000E+01 2.0000E+00 1.4600E+02 5.0000E+00 7.7000E+02 0.OOOOE+00 Output Filename:
G:\\Radtrad 3.o24 1
1 1
0 0
End of Scenario File
XceI nergy' Calculation No. GEN-PI-077 Revision No.
0 Page No. 43 of 57
- 4###4#####*#4#444####4##4#######444###4#44#44#44#4444444444#4444444##4 RADTRAD Version 3.03 (Spring 2001) run on 4/06/2009 at 23:25:11
- 4###4#################4####4##########
444#4##########4######4# #
Plant Description 4##4#4#####4#4##########4#4#44444444##4#4##4###44###4###4###4##44#######
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: 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
S X eIEnergy-Calculation No. GEN-PI-077 Revision No. 0 Page No. 44 of 57
- ###### # ####8 ####################################
8##########8###8#
RADTRAD Version 3.03 (Spring 2001) run on 4/06/2009 at 23:25:11
- 8####### ####################################8###################
Scenario Description Time between shutdown and first release 5.OOOOE+01 (Hours)
Radioactive Decay is enabled Calculation of Daughters is enabled Release Fractions and Timings NOBLES IODINE CESIUM TELLURIUM STRONTIUM BARIUM RUTHENIUM CERIUM LANTHANUM GAP 0.003600 hr
- 5. OOOOE-02
- 5. OOOOE-02
- 1. 2000E-01 0 OOOOE+00
- 0. OOOOE+00 o OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 EARLY IN-VESSEL 0.0000 hrs 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 LATE RELEASE 0.0000 hrs 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 0.OOOOE+00 RELEASE MASS (gm) 3.593E+00 3.008E-03 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 Inventory Power =
1852.
MWt Nuclide Name Kr-85 Kr-85m Kr-87 Kr-88 1-131 1-132 1-133 1-134 1-135 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 Nuclide Kr-85m Kr-87 Kr-88 1-131 1-133 1-135 Xe-133m Xe-135 Group Specific Inventory (Ci/MWt) 1 1.334E+01 1
1.008E+02 1
1.978E+02 1
2.631E+02 2
3.359E+00 2
3.037E+00 2
4.259E+00 2
4.758E+00 2
4.068E+00 1
4.721E+00 1
8.537E+02 1
2.668E+01 1
1.931E+02 1
1.819E+02 1
7.203E+02 half life (s)
- 3. 383E+08
- 1. 613E+04
- 4. 578E+03 1.022E+04
- 6. 947E+05 8.280E+03
- 7. 488E+04
- 3. 156E+03
- 2. 380E+04
- 1. 028E+06
- 4. 532E+05
- 1. 890E+05
- 3. 272E+04
- 9. 174E+02
- 8. 502E+02 Whole Body DCF (Sv-m3/Bq-s) 1.190E-16 7.480E-15 4.120E-14 1.020E-13 1.820E-14 1.120E-13 2.940E-14
- 1. 300E-13 8.294E-14
- 3. 890E-16
- 1. 560E-15
- 1. 370E-15 1.190E-14 2.040E-14 5.770E-14 Inhaled Thyroid (Sv/Bq)
- 0. OOOE+00
- 0. OOOE+00
- 0. OOOE+00
- 0. OOOE+00 2.920E-07 1.740E-09
- 4. 860E-08
- 2. 880E-10
- 8. 460E-09
- 0. OOOE+00
- 0. OOOE+00
- 0. OOOE+00
- 0. OOOE+00
- 0. OOOE+00
- 0. OOOE+00 Inhaled Effective (Sv/Bq) 0 OOOE+00 0 OOOE+00 0 OOOE+00 0 OOOE+00
- 8. 890E-09
- 1. 030E-10 1.580E-09
- 3. 550E-11
- 3. 320E-10 0 OOOE+00 0 OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 Daughter Kr-85 Rb-87 Rb-88 Xe-131m Xe-133m Xe-135m Xe-133 Cs-135 Fraction 0.21 1.00 1.00 0.01 0.03 0.15 1.00 1.00 Daughter none none none none Xe-133 Xe-135 none none Fraction 0.00 0.00 0.00 0.00 0.97 0.85 0.00 0.00 Daughter Fraction none 0.00 none 0.00 none 0.00 none 0.00 none 0.00 none 0.00 none 0.00.
none 0.00
XceIEnergy-Calculation No. GEN-P,-077 Revision No. 0 Page No. 45 of 57 Xe-135m Xe-135 Xe-138 Cs-138 1.00 1.00 none none 0.00 0.00 none none 0.00 0.00 Iodine fractions Aerosol Elemental Organic COMPARTMENT DATA
=
0.0000E+00
=
5.7000E-0l
= 4. 3000E-01 Compartment number 1: Fuel Pool Compartment number 2: Environment Compartment number 3: Control Room Compartment Filter Data Time (hr)
- 5. OOOOE+01
- 5. 0083E+01 7.7000E+02 Flow Rate (cfm) 3.6000E+03 3.6000E+03 3.6000E+03 Filter Aerosol 0.OOOOE+00
- 9. 9000E+01 0.OOOOE+00 Efficiencies Elemental 0.OOOOE+00 9.5000E+01 0.OOOOE+00
%)
Organic 0.OOOOE+00 9. 5000E+01 0.OOOOE+00 PATHWAY DATA Pathway number 1: FHA Release to Environment Pathway Filter: Removal Data Time (hr)
- 5. OOOOE+01 5.2000E+01 Flow Rate (cfm)
- 3. 9000E+01 0.OOOOE+00 Filter Efficiencies
(%)
Aerosol Elemental Organic 0.OOOOE+00 0.OOOOE+00 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)
- 5. OOOOE+01
- 5. 0083E+01 7.7000E+02 Flow Rate (c fm) 2.OOOOE+03 3.OOOOE+02 0.OOOOE+00 Filter Efficiencies
(%)
Aerosol Elemental Organic O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0.OOOOE+00 0.OOOOE+00 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)
- 5. OOOOE+01
- 5. 0083E+01 7.7000E+02 Flow Rate (cfm) 2.OOOOE+03 3.OOOOE+02 0.OOOOE+00 Filter Efficiencies
(%)
Aerosol 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Elemental 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Organic 0.0000E+00 0.OOOOE+00 0.OOOOE+00 LOCATION DATA Location Exclusion Area Boundary is in compartment 2
XCelEnergy" Calculation No. GEN-PI-077 Revision No. 0 Page No. 46 of 57 Location X/Q Data Time (hr) 5.OOOOE+01 7.7000E+02 X/Q (s
- m^-3) 6.4900E-04 O.O000E+O0 Location Breathing Rate Data Time (hr)
Breathing Rate (m^3
- sec^-l) 5.OOOOE+01 3.5000E-04 7.7000E+02 0.0000E+00 Location Low Population Zone is in compartment 2
Location X/Q Data Time (hr) 5.6000E+01 5.8000E+01 7.4000E+01 1.4600E+02 7.7000E+02 X/Q (s
- m^-3) 1.7700E-04 3.9900E-05 7.1200E-06 1.0400E-06 0.OOOOE+00 Location Breathing Rate Da Time (hr)
Breathi 5.0000E+01 5.8000E+01 7.4000E+01 7.7000E+02 Location Control Room
,ng Rate (m^3
- sec"-l) 3.5000E-04 1.8000E-04 2.3000E-04 0.0O00E+00 is in compartment 3
Location X/Q Data Time (hr) 5.OOOOE+01 5.2000E+01 5.8000E+01 7.4000E+01 1.4600E+02 7.7000E+02 X/Q (s
- m'-3)
- 6. 7100E-03 2.8900E-03 1.2200E-03
- 9. 2100E-04 7.4400E-04
- 0. 0000+00 Location Breathing Rate Data Time,(hr)
Breathing Rate (m^3
- sec^-l) 5.0000E+01 3.5000E-04 7.7000E+02 0.0000E+00 Location Occupancy Factor Data Time (hr)
Occupancy Factor 5.OOOOE+01 1.0000E+00 7.4000E+01 6.0000E-01 1.4600E+02 4.OOOOE-01 7.7000E+02 0.0000E+00 USER SPECIFIED TIME STEP DATA -
SUPPLEMENTAL TIME STEPS Time o.OOOOE+00 2.OOOOE+00 8.OOOOE+00 2.4000E+01
- 9. 6000E+01 7.2000E+02 Time step 1 0000E-01
- 5. ODOOE-01
- 1. 0000E+00
- 2. 0000E+00 5.0000E+00 0
OOO0E+00
O(K el Energy-Calculation No. GEN-PI-077 Revision No. 0 Page No. 47 of 57 RADTRAD Version 3.03 (Spring 2001) run on 4/06/2009 at 23:25:11
- 4############4########f############4#################
itiit#
- t it it it it
- t
- t
- i## ## # it i it it
- titt#ti it it it it
- t it it
- t it it it i
- f##
i i
I Dose, Detailed model and Detailed Inventory Output
- x###############c##############o#########An#########d#Do##ses Exclusion Area Boundary Doses:
Time (h)
=
50.0036 Delta dose (rem)
Accumulated dose (rem)
Whole Body 1.0953E-03 1.0953E-03 Low Population Zone Doses:
Time (h)
=
50.0036 Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Time (h)
=
50.0036 Delta dose (rem)
Accumulated dose (rem)
Whole Body 2.9871E-04 2.9871E-04 Whole Body 1.0980E-06 1.0980E-06 Thyroid 2.8075E-01 2.8075E-01 Thyroid 7.6568E-02 7.6568E-02 Thyroid 7.9530E-03 7.9530E-03 TEDE 9.6697E-03 9.6697E-03 TEDE 2.6372E-03 2.6372E-03 Control Room Compartment Nuclide Inventory:
Time (h)
Kr-85 Kr-85m Kr-88 1-131 1-132 1-133 1-135 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m
=
50.0036 Ci 3.2774E-02
- 1. 0815E-04 3.2391E-06 6.8978E-03
- 2. 1299E-09 1.9776E-03 5.2801E-05 1.0286E-02 1.6056E+00
.3.3953E-02 1.1216E-02 9.1992E-06 kg 8.3537E-08 1.3141E-14 2.5832E-16
- 5. 5638E-11
- 2. 0634E-19 1.7457E-12 1.5035E-14 1.2280E-10 8.5778E-09 7.5669E-11 4.3921E-12
- 1. 0099E-16 TEDE 2.4399E-04 2.4399E-04 Atoms 5.9185E+17
- 9. 3105E+10 1.7677E+09 2.5577E+14
- 9. 4136E+05
- 7. 9045E+12 6.7069E+10 5.6451E+14
- 3. 8840E+16 3.4262E+14
- 1. 9592E+13 4.5049E+08 Decay 1.1155E+10 3.6817E+07 1.1028E+06 2.3478E+09 7.2521E+02 6.7312E+08 1.7974E+07 3.5009E+09
- 5. 4649E+11 1.1557E+10 3.8180E+09 3.1236E+06 Control Room Transport Group Inventory:
9 o XceIEnergy ICalculation No. GEN-PI-077 Revision No. 0 Page No. 48 of 57 Time (h)
=
50.0036 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Time (h)
=
50.0036 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Atmosphere Sump 6.3161E+17 0.OOOOE+00 1.5033E+14 0.OOOOE+00 1.1341E+14 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid) 4.1632E-12 4.2798E-12
- 8. 9281E-03 Deposition Surfaces 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Recirculating Filter 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 O.OOOOE+00 Environment to Control Room Transport Group Inventory:
Time (h)
=
50.0036 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Transported 6.3310E+17 1.5069E+14 1.1368E+14 0.0000E+00 Control Room to Environment Transport Group Inventory:
Time (h)
=
50.0036 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 1.4848E+15 3.5342E+ll 2.6661E+ll 0.OOOOE+00 Exclusion Area Boundary Doses:
Time (h)
=
50.0830 Whole Body Delta dose (rem) 4.4029E-02 Accumulated dose (rem) 4.5124E-02 Transported 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Thyroid 1.1286E+01 1.1567E+01 Thyroid 3.0780E+00 3.1545E+00 Low Population Zone Doses:
- 3. 8871E-01
- 3. 9838E-01 TEDE
- 1. 0601E-01 1.0865E-01 Time (h)
=
50.0830 Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Time (h)
= 50.0830 Delta dose (rem)
Accumulated dose (rem)
Whole Body 1.2008E-02 1.2307E-02 Whole Body 1.2142E-03 1.2153E-03 Thyroid 8.7942E+00 8.8021E+00 Control Room Compartment Nuclide Inventory:
- 2. 6980E-01 2.7004E-01 Atoms 2.2541E+19
- 3. 5027E+12 Time (h)
=
50.0830 Kr-85 Kr-85m Ci 1.2482E+00 4.0686E-03 kg 3.1815E-06
- 4. 9439E-13 Decay
- 1. 3213E+13 4.3332E+10
. X~elEnergy' Calculation No. GEN-PI-077 Revision No. 0 Page No. 49 of 57 Kr-88 1-131 1-132 1-133 1-135 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m 1.2099E-04 2.6263E-01
- 7. 9199E-08
- 7. 5118E-02 1.9943E-03
- 3. 9166E-01 6.1124E+01 1.2918E+00 4.2461E-01
- 3. 4718E-04
- 9. 6493E-15 2.1184E-09 7. 6727E-18
- 6. 6311E-11
- 5. 6787E-13 4.6760E-09 3.2655E-07 2.8789E-09
- 1. 6627E-10
- 3. 8113E-15
- 6. 6033E+10
- 9. 7385E+15 3.5005E+07
- 3. 0025E+14
- 2. 5332E+12 2.1496E+16
- 1. 4786E+18
- 1. 3035E+16 7.4170E+14
- 1. 7002E+10 1.2932E+09
- 2. 7803E+12 8.4844E+05
- 7. 9618E+11 2.1198E+10 4.1462E+12
- 6. 4714E+14
- 1. 3681E+13
- 4. 5080E+12 3.3357E+09 Control Room Transport Time (h)
=
50.0830 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Time (h) =
50.0830 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Group Inventory:
Atmosphere Sump 2.4055E+19 0.0000E+00 5.7235E+15 0.OOOOE+00 4.3177E+15 0.0000E+00 0.0000E+00 0.0000E+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid)
- 1. 5850E-10
- 1. 6292E-10 3.3974E-01 Deposition Recirculating Surfaces Filter 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Environment to Control Room Transport Group Inventory:
Time (h)
=
50.0830 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 0.0000E+00 0.OOOOE+00 0.0000E+00 0.0000E+00 Transported 2.6083E+19 6.2082E+15 4.6834E+15 0.0000E+00 Control Room to Environment Transport Group Inventory:
Time (h)
=
50.0830 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 2.0327E+18 4.8381E+14 3.6498E+14 0.OOOOE+00 Transported 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Exclusion Area Boundary Doses:
Time (h)
=
52.0000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 2.1234E-01 2.5746E-01 Low Population Zone Doses:
Thyroid 5.4534E+01
- 6. 6100E+01 Thyroid
- 1. 4873E+01
- 1. 8027E+01 TEDE 1.8778E+00 2.2762E+00 Time (h)
=
52.0000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 5.7910E-02 7.0216E-02 TEDE
- 5. 1212E-01
- 6. 2077E-01
9~XcelEnergy-Calculation No. GEN-PI-077 Revisi on No. 0 Page No. 50 of 57 Control Room Doses:
Time (h)
=
52.0000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 6.6985E-02 6.8201E-02 Thyroid 1.0402E+02
- 1. 1283E+02 TEDE 3.2438E+00
- 3. 5139E+00 Control Room Compartment Nuclide Inventory:
Time (h)
Kr-85 Kr-85m Kr-88 1-131 1-132 1-133 1-135 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m
=
52.0000 Ci
- 1. 3304E+00
- 3. 2236E-03
- 8. 0775E-05 4.0142E-03
- 6. 8402E-10 1.0846E-03
- 2. 5104E-05 4 1553E-01
- 6. 4481E+01
- 1. 3425E+00
- 3. 9110E-01 1.8821E-05 kg 3.3911E-06 3.9171E-13
- 6. 4418E-15
- 3. 2380E-11
- 6. 6267E-20 9.5740E-13 7 1482E-15 4.9609E-09
- 3. 4449E-07
- 2. 9919E-09
- 1. 5315E-10
- 2. 0661E-16 Atoms 2.4025E+19 2 7752E+12 4 4083E+10
- 1. 4885E+14
- 3. 0232E+05 4.3350E+12
- 3. 1887E+10 2.2806E+16
- 1. 5598E+18
- 1. 3547E+16
- 6. 8318E+14 9.2166E+08 Decay
- 4. 1128E+14 1.1701E+12 3.2279E+10
- 1. 7977E+13 4.9022E+06
- 5. 0874E+12 1.3173E+II 1.2877E+14
- 2. 0042E+16 4.2060E+14
- 1. 3073E+14 4.3815E+10 Control Room Transport Time (h)
=
52.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Time (h)
=
52.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Group Inventory:
Atmosphere Sump 2.5622E+19 0.OOOOE+00 8.7334E+13 0.OOOOE+00 6.5883E+13 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid) 2.4164E-12 2.4802E-12
- 5. 1239E-03 Deposition Recirculating Surfaces Filter 0.OOOOE+00 0.OOOOE+00 0.OOOOE+/-00 9.2080E+15 0.OOOOE+00 6.9464E+15 0.OOOOE+00 0.OOOOE+00 Environment to Control Room Transport Group,Inventory:
Time (h)
= 52.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Transported 4.4567E+19 1.0600E+16 7.9962E+15 O.OOOOE+00 Control Room to Environment Transport Group Inventory:
Time (h)
=
52.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 1.8929E+19 1.2915E+15 9.7431E+14 0.OOOOE+00 Transported 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00
XcelEnergY' Calculation No. GEN-PI-077 Revision No. 0 Page No. 51 of 57 Exclusion Area Boundary Doses:
Time (h)
=
58.0000 Whole Body Delta dose (rem) 0.0000E+00 Accumulated dose (rem) 2.5746E-01 Low Population Zone Doses:
Time (h)
=
58.0000 Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Time (h)
=
58.0000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 0.OOOOE+00 7.0216E-02 Whole Body 8.0881E-02 1.4908E-01 Thyroid 0.OOOOE+00
- 6. 6100E+01 Thyroid 0.OOOOE+00 1. 8027E+01 Thyroid
- 9. 1259E-01
- 1. 1374E+02 TEDE 0.0000E+00 2.2762E+00 TEDE 0.OOOOE+00 6.2077E-01 Control Room Compartment Nuclide Inventory:
Time (h)
Kr-85 Kr-85m Kr-88 1-131 Xe-131m Xe-133 Xe-133m Xe-135
=
58.0000 Ci
- 2. 2857E-01
- 2. 1888E-04
- 3. 2087E-06 1.2843E-12 7.0358E-02 1.0725E+01
- 2. 1308E-01 4.2523E-02 kg 5.8258E-07
- 2. 6597E-14
- 2. 5590E-16 1.0360E-20
- 8. 3999E-10 5.7299E-08 4.7488E-10
- 1. 6652E-11 TEDE
- 1. 0875E-01 3.6226E+00 Atoms
- 4. 1275E+18 1.8844E+1I 1.7512E+09 4.7624E+04
- 3. 8615E+15 2.5945E+17 2.1502E+15 7.4280E+13 Decay
- 9. 0392E+14
- 2. 04 98E+12
- 5. 1214E+10 1.8099E+13 2.8183E+14 4.3643E+16 9.0383E+14
- 2. 5445E+14 Control Room Transport Time (h)
=
58.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Time (h)
=
58.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Group Inventory:
Atmosphere Sump 4.3930E+18 0.OOOOE+00 2.7810E+04 0.0000E+00 2.0980E+04 0.0000E+00 0.0000E+00 0.0000E+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid) 7.6763E-22 7.8463E-22
- 1. 5790E-12 Deposition Recirculating Surfaces Filter 0.0000E+00 0.OOOOE+00 0.OOOOE+00 9.2882E+15 0.OOOOE+00 7.0069E+15 0.OOOOE+00 0.0000E+00 Environment to Control Room Transport Group Inventory:
Time (h)
=
58.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 0.OOOOE+00 0.0000E+00 0.0000E+00 0.0000E+00 Transported 4.4567E+19 1.0600E+16 7.9962E+15 0.0000E+00
I XceIEneogyW Calculation No. GEN-PI-077 Revision No. 0 Page No. 52 of 57 Control Room to Environment Transport Group Inventory:
Time (h)
=
58.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 4.0134E+19 1.2986E+15 9.7961E+14 0.0000E+00 Transported 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Thyroid 0.OOOOE+00 6.6100E+01 Exclusion Area Boundary Doses:
Time (h)
=
74.0000 Whole Body Delta dose (rem) 0.OOOOE+00 Accumulated dose (rem) 2.5746E-01 TEDE 0.0000E+00 2.2762E+00 Low Population Zone Doses:
Time (h)
=
74.0000 Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Time (h)
=
74.0000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 0.OOOOE+00 7.0216E-02 Whole Body 1.5787E-02 1.6487E-01 Thyroid 0.OOOOE+00
- 1. 8027E+01 Thyroid 2.8-992E-10
- 1. 1374E+02 TEDE 0.0000E+00
- 6. 2077E-01 TEDE 1.5787E-02 3.6384E+00 Control Room Compartment Nuclide Inventory:
Time (h)
=
74.0000 Kr-85 Kr-85m Kr-88 Xe-131m Xe-133 Xe-133m Xe-135 Control Room Transport Time (h)
=
74.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Time (h)
=
74.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Ci 2.0848E-03 1.6796E-07 5.8950E-10
- 6. 1737E-04 8.9735E-02 1.5737E-03
- 1. 1451E-04 kg
- 5. 3137E-09
- 2. 0409E-17 4.7013E-20
- 7. 3706E-12 4.7940E-10 3. 5072E-12 4.4842E-14 Atoms
- 3. 7647E+16
- 1. 4459E+08 3.2172E+05
- 3. 3883E+13 2 1707E+15
- 1. 5880E+13
- 2. 0003E+11 Decay
- 1. 0022E+15 2.1129E+12 5.1990E+10 3.1185E+14 4.8177E+16
- 9. 9180E+14
- 2. 6918E+14 Group Inventory:
Atmosphere Sump 3.9868E+16 0.OOOOE+00 1.3181E-21 0.OOOOE+00 9.9435E-22 0.OOOOE+00 0.0000E+00 0.0000E+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid) 3.6209E-47
- 3. 6712E-47
- 7. 0101E-38 Deposition Recirculating Surfaces Filter 0.OOOOE+00 0.0000E+00 0.0000E+00 9.2882E+15 0.0000E+00 7.0069E+15 0.OOOOE+00 0.0000E+00 Environment to Control Room Transport Group Inventory:
Xcel Energy-Calculation No. GEN-PI-077 Revision No. 0 Page No. 53 of 57 Time (h)
=
74.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 0.OOOOE+00 0.0000E+00 0.OOOOE+00 O.OOOOE+00 Transported 4.4567E+19 1.0600E+16 7.9962E+15 0.0000E+00 Control Room to Environment Transport Group Inventory:
Time (h)
=
74.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 4.4482E+19 1.2986E+15 9.7961E+14 0.OOOOE+00 Exclusion Area Boundary Doses:
Time (h)
= 146.0000 Whole Body Delta dose (rem) 0.OOOOE+00 Accumulated dose (rem) 2.5746E-01 Transported 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Thyroid 0.0000E+00 6.6100E+01 Thyroid 0.0000E+00 1.8027E+01 Low Population Zone Doses:
TEDE 0.OOOOE+00 2.2762E+00 TEDE 0.OOOOE+00
- 6. 2077E-01 Time (h) = 146.0000 Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Time (h)
= 146.0000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 0.0000E+00 7.0216E-02 Whole Body 7.9077E-05 1.6495E-01 Thyroid 1.5583E-35
- 1. 1374E+02 Control Room Compartment Nuclide Inventory:
TEDE 7.9077E-05 3.6385E+00 Atoms 2.4884E+07
= 146.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Time (h)
= 146.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Ci 1.3780E-12 3.4283E-13
- 4. 0135E-11 kg
- 3. 5123E-18
- 4. 0930E-21 2.1442E-19 Decay
- 1. 0030E+15
- 3. 1209E+14 4.8212E+16 Group Inventory:
Atmosphere Sump 2.5878E+07 0.OOOOE+00 1.4854-135 0.OOOOE+00 1.1205-135 0.OOOOE+00 0.0000E+00 0.OOOOE+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid) 4.0515-161 4.0583-161 7.1311-152 Deposition Surfaces 0.0000E+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 Recirculating Filter 0.OOOOE+00 9.2882E+15 7.0069E+15 0.OOOOE+00
9~XCeIEnergy, Calculation No. GEN-PI-077 Revision No. 0 Page No. 54 of 57 Environment to Control Room Transport Group Inventory:
Time (h)
= 146.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Transported 4.4567E+19 1.0600E+16 7.9962E+15 0.OOOOE+00 Control Room to Environment Transport Group Inventory:
Time (h)
= 146.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 4.4522E+19 1.2986E+15 9.7961E+14 0.OOOOE+00 Exclusion Area Boundary Doses:
Time (h)
= 770.0000 Whole Body Delta dose (rem) 0.OOOOE+00 Accumulated dose (rem) 2.5746E-01 Transported 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Thyroid 0.OOOOE+00 6.6100E+01 Thyroid 0.OOOOE+00 1.8027E+01 Thyroid 1.1624-149 1.1374E+02 Low Population Zone Doses:
Time (h)
= 770.0000 Whole Body Delta dose (rem) 0.OOOOE+00 Accumulated dose (rem) 7.0216E-02 TEDE 0.OOOOE+00 2.2762E+00 TEDE 0.OOOOE+00
- 6. 2077E-01 TEDE
- 2. 3271E-14 3.6385E+00 Control Room Doses:
Time (h)
= 770.0000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 2.3271E-14 1.6495E-01 Control Room Compartment Nuclide Inventory:
Time (h)
= 770.0000 Control Room Transport Time (h)
= 770.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Time (h)
= 770.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Ci kg Atoms Decay Group Inventory:
Atmosphere Sump 6.8902E-73 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid) 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Deposition Recirculating Surfaces Filter 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 9.2882E+15 0.OOOOE+00 7.0069E+15 0.OOOOE+00 0.OOOOE+/-00
XcelEnergy, Calculation No. GEN-PI-077 Revision No. 0 Page No. 55 of 57 Environment to Control Room Transport Group Inventory:
Time (h)
= 770.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Transported 4.4567E+19 1.0600E+16 7.9962E+15 0.OOOOE+00 Control Room to Environment Transport Group Inventory:
Time (h) = 770.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered Transported 4.4522E+19 0.0000E+00 1.2986E+15 0.0000E+00 9.7961E+14 0.0000E+00 0.0000E+00 0.0000E+00 4
839
- 4#4##############4#####4##############4##-1S####r######y 1-131 Summary
- 4#######4##ý##################4#############4##############4###
Time (hr) 50.000 50.004 50.083 50.400 50.700 51.000 51.300 51.600 51.900 52.000 52.300 52.600 52.900 53.200 53.500 53.800 54.100 54.400 54.700 55.000 55.300 55.600 55.900
- 56. 200 56.500 56.800 57.100 57.400 57.700 58.000 Fuel Pool 1-131 (Curies) 4.0083E+01 2.5881E+02 2.1487E+02 1.0222E+02 5.0604E+01 2.5052E+01 1.2402E+01 6.1398E+00 3.0396E+00 2.4045E+00 2.4019E+00 2.3994E+00 2.3968E+00 2.3942E+00 2.3916E+00 2.3890E+00 2.3865E+00 2.3839E+00 2.3813E+00 2.3788E+00 2.3762E+00 2.3736E+00 2.3711E+00 2.3685E+00 2.3660E+00 2.3634E+00 2.3609E+00 2..3583E+00 2.3558E+00 2.3533E+00 Environment 1-131 (Curies) 2.6060E-02 1.0916E+00 4.4963E+01 1.5742E+02 2.0894E+02 2.3445E+02 2.4708E+02 2.5333E+02 2.5643E+02 2.5706E+02
- 2. 5706E+02
- 2. 5706E+02
- 2. 5706E+02
- 2. 5706E+02
- 2. 5706E+02
- 2. 5706E+02
- 2. 5706E+02
- 2. 5706E+02
- 2. 5706E+02
- 2. 5706E+02
- 2. 5706E+02
- 2. 5706E+02
- 2. 5706E+02
- 2. 5706E+02
- 2. 5706E+02 2.5706E+02 2.5706E+02 2.5706E+02 2.5706E+02 2.5706E+02 Control Room 1-131 (Curies) 1.6499E-04 6.8978E-03 2.6263E-01 1.4177E-01 7.5461E-02 3.9126E-02 1.9962E-02 1.0081E-02 5.0574E-03
- 4. 0142E-03 1.3454E-03 4.5093E-04
- 1. 5114E-04
- 5. 0655E-05
- 1. 6977E-05
- 5. 6902E-06 1.9071E-06 6.3920E-07 2.1423E-07 7.1803E-08 2.4066E-08 8.0659E-09 2.7034E-09 9.0606E-10 3.0368E-10 1.0178E-10 3.4113E-11 1.1433E-11 3.8320E-12 1.2843E-12
9 XceEnergy Calculation No. GEN-PI-077 Revision No. 0 Page No. 56 of 57 58.300 58.600 58.900 59.200 59.500 59-800 60.100 6b.400 74.000 146. 000 770.000 2.3507E+00 2.3482E+00 2.3457E+00 2.3431E+00 2.3406E+00 2 3381E+00 2.3356E+00 2.3331E+00
- 2. 2218E+00
- 1. 7155E+00
- 1. 8235E-01 2.5706E+02 2.5706E+02 2.5706E+02 2.5706E+02 2.5706E+02 2.5706E+02 2.5706E+02 2.5706E+02 2.5706E+02 2.5706E+02 2.5706E+02 4.3046E-13 1.4427E-13 4.8355E-14
- 1. 6207E-14 5.4319E-15
- 1. 8206E-15
- 6. 1018E-16
- 2. 0451E-16
- 6. 1431E-38 7.0152-152 0.OOOOE+00 Cumulative Dose Summary 4#4#####################################4######################*#####
Exclusion Area Bounda Low Population Zone Time (hr) 50.000 50.004 50.083 50.400 50.700 51.000 51.300 51.600 51.900 52.000 52.300 52.600 52.900 53.200 53.500 53.800 54.100 54.400 54.700 55.000 55.300 55.600 55.900 56.200 56.500 56.800 57.100 57.400 57.700 58.000 58.300 58.600 58.900 59.200 59.500 59.800 60.100 60.400 Thyroid (rem) 0.OOOOE+00 2.8075E-01
- 1. 1567E+01
- 4. 0491E+01
- 5. 3738E+01
- 6. 0294E+01
- 6. 3538E+01 6.5143E+01 6.5937E+01
- 6. 6100E+01
- 6. 6100E+01
- 6. 6100E+01
- 6. 6100E+01
- 6. 6100E+01
- 6. 6100E+01
- 6. 6100E+01
- 6. 6100E+01
- 6. 6100E+01
- 6. 6100E+01
- 6. 6100E+01
- 6. 6100E+01
- 6. 6100E+01
- 6. 6100E+01
- 6. 6100E+01
- 6. 6100E+01
- 6. 6100E+01
- 6. 6100E+01
- 6. 6100E+01
- 6. 6100E+01
- 6. 6100E+01
- 6. 6100E+01
- 6. 6100E+01
- 6. 6100E+01
- 6. 6100E+01
- 6. 6100E+01
- 6. 6100E+01
- 6. 6100E+01
- 6. 6100E+01 TEDE Thyroid (rem) 0.0000E+00 9.6697E-03 3.9838E-01 1.3945E+00 1.8506E+00 2.0763E+00 2.1880E+00 2.2432E+00 2.2706E+00 2.2762E+00 2.2762E+00 2.2762E+00 2.2762E+00 2.2762E+00 2.2762E+00 2.2762E+00 2.2762E+00 2.2762E+00 2.2762E+00 2.2762E+00 2.2762E+00 2.2762E+00 2.2762E+00 2.2762E+00 2.2762E+00 2.2762E+00 2.2762E+00 2.2762E+00 2.2762E+00 2.2762E+00 2.2762E+00 2.2762E+00 2.2762E+00 2.2762E+00 2.2762E+00 2.2762E+00 2.2762E+00 2.2762E+00 (rem) 0.0000E+00 7.6568E-02 3.1545E+00 1.1043E+01 1.4656E+01 1.6444E+01 1.7328E+01 1.7766E+01 I.7983E+01 1.8027E+01 1.8027E+01 1.8027E+01 1.8027E+01 1.8027E+01
- 1. 8027E+01
- 1. 8027E+01 1.8027E+01
- 1. 8027E+01 1.8027E+01 1.8027E+01 1.8027E+01 1.8027E+01 1.8027E+01
- 1. 8027E+01 1. 8027E+01
- 1. 8027E+01 1.8027E+01 1.8027E+01 1.8027E+01 1.8027E+01
- 1. 8027E+01
- 1. 8027E+01 1.8027E+01
- 1. 8027E+01 1.8027E+01 1.8027E+01 1.8027E+01 1.8027E+01 TEDE (rem) 0.OOOOE+00 2.6372E-03 1.0865E-01 3.8032E-01 5.0472E-01
- 5. 6627E-01 5.9672E-01
- 6. 1179E-01
- 6. 1925E-01 6.2077E-01 6.2077E-01 6.2077E-01 6.2077E-01 6.2077E-01 6.2077E-01 6.2077E-01 6.2077E-01 6.2077E-01 6.2077E-01 6.2077E-01 6.2077E-01 6.2077E-01
- 6. 2077E-01
- 6. 2077E-01
- 6. 2077E-01
- 6. 2077E-01
- 6. 2077E-01 6.2077E-01
- 6. 2077E-01
- 6. 2077E-01
- 6. 2077E-01 6.2077E-01 6.2077E-01 6.2077E-01 6.2077E-01 6.2077E-01 6.2077E-01 6.2077E-01 Control Room Thyroid TEDE (rem)
(rem) 0.OOOOE+00 0.0000E+00 7.9530E-03 2.4399E-04 8.8021E+00 2.7004E-01 6.0268E+01 1.8526E+00 8.6334E+01 2.6601E+00 1.0003E+02 3.0898E+00 1.0708E+02 3.3158E+00 1.1065E+02 3.4352E+00 1.1245E+02 3.4996E+00 1.1283E+02 3.5139E+00 1.1343E+02 3.5408E+00 1.1364E+02 3.5547E+00 1.1370E+02 3.5637E+00 1.1373E+02 3.5708E+00 1.1373E+02 3.5768E+00 1.1374E+02 3.5822E+00 1.1374E+02 3.5871E+00 1.1374E+02 3.5916E+00 1.1374E+02 3.5956E+00 1.1374E+02 3.5993E+00 1.1374E+02 3.6027E+00 1.1374E+02 3.6058E+00 1.1374E+02 3.6086E+00 1.1374E+02 3.6112E+00 1.1374E+02 3.6136E+00 1.1374E+02 3.6157E+00 1.1374E+02 3.6177E+00 1.1374E+02 3.6195E+00 1.1374E+02 3.6211E+00 1.1374E+02 3.6226E+00 1.1374E+02 3.6240E+00 1.1374E+02 3.6253E+00 1.1374E+02 3.6264E+00 1.1374E+02 3.6274E+00 1.1374E+02 3.6284E+00 1.1374E+02 3.6293E+00 1.1374E+02 3.6301E+00 1.1374E+02 3.6308E+00
-A
Ace Energy ICalculation No. GEN-PI-077 Revision No. 0 Page No. 57 of 57 74.000 6.6lOOE+0l 2.2762E+00 l.8027E+0l 6.2077E-0l l.1374E+02 3.6384E+00 146.000 6.6100E+01 2.2762E+00 1.8027E+01 6.2077E-01 1.1374E+02 3.6385E+00 770.000 6.6100E+01 2.2762E+00 1.8027E+01 6.2077E-01 1.1374E+02 3.6385E+00
- 4#########W#################r#######s####o##r######Do#############e Worst Two-Hour Doses
- 4###*#####4###################4#######4#*#########*####4#4##########
Exclusion Time (hr) 50.0 Area Boundary Whole Body Thyroid (rem)