ML102300298
| ML102300298 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 07/23/2010 |
| From: | Gita Patel Xcel Energy |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| L-PI-10-076, TAC ME2609, TAC ME2610 GEN-PI-082, Rev 1 | |
| Download: ML102300298 (146) | |
Text
ATTACHMENT 4 to ENCLOSURE (SUPERCEDES ATTACHMENT 11 to LAR)
CREA Analysis titled, "GEN-PI-082, Control Rod Ejection Accident - AST,"
Revision 1 145 Pages Follow
F
-49 E ev. 3
/_____._"__
Page I of 145 Xc.
nergy-Calculation Signature Sheet Document Information NSPM Calculaion' (Doc) No:GEN-PI-082 Re'visio*n!: 1
Title:
Control Rod Ejection Accident - AST Facility:[]MIVT ZPI Unit:
1 ~2 Safety Class:,
SR
[]Aug 0 Q
L Non SR.
Special Codes: LI Safeguards LI Proprietary Type: Ctalc Sub-Type:
[NOTE:
Print and sign name in signature blocks, as required.
- Major Revisions.
EC Number: 13720
[.
Vendor Calc Vendor Name or Code:
Vendor Doc No:
Description of Revision: The TDAFW pump exhaust steam release path is re-evaluated as Unit 2 Group i and Group 2 P9RV r...ase paths Prepared by:. Gopal J.D Patel bate: 07/15/2010 Reviewed*'*: Thomas J. Mscis
] Date: 07/19/2010 Type of Review: F1 Design Verfif on *],
Review LI Vendor;Aeptance
,Method Used (Fa ov Review Alternate Calic F Test Approved by:Dte Minor Revisions EC No:
LI Vendor Calc:
Minor Rev. No:
Description of Change.
Pages Affected:'
Prepared by:
Date:
Reviewed by:__ _______________
Date:
Type of Review: []Design Verification El Tech Review [I Vendor Acceptance
.Method Used (F, Dvoye): n Review El Alternate Calc ]Tesýt rEC No:
I Vedr Calc:.
(continued on next page)
Record Retentibrn: Retain this for wih the associated calculation for'the life of.the plant.
OF-0549 (FP-E-CAL,01), Rev. 3 Pa~e 2 of 145 XdeI Energy-Calculation Signature Sheet EC No:
EIl Vendor Caic:
Minor Rev. No:
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Date:
Reviewed by:
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Type of Review: El Design Verification El Tech Review El Vendor Acceptance Method Used (For DV Only): El Review 0l Alternate Calc El Test Approved by:
Date:
EC No:
El Vendor Caic:
Minor Rev. No:
Description of Change:
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Type of Review: El Design Verification E] Tech Review E] Vendor Acceptance Method Used (For DV Only): E] Review El Alternate Calc El Test Approved by:
I Date:
EC No:
El Vendor Caic:
Minor Rev. No:
Description of Change:
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Date:
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Type of Review: El Design Verification E] Tech Review E] Vendor Acceptance Method Used (For DV Only): [] 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 Pacie 3 of 145
.X..Enery.'
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*
Ref Type**
Doc? +
Document Name Document Number Doc Rev (if known)
Type (if known) 1 E RG Alternative Radiological Source Terms for Evaluating Design 1.183 July 2000 Zlnput LlOutput Basis Accidents at Nuclear Power Reactors 2
[
DOC A Simplified Model for Radionuclide Transport and Removal and NUREG/CR-6604 Dec 1997 ZInput [:]Output Dose Estimation 3
Z TRNS CREA Input Parameters DIT No. 13720-10 0
Zlnput L]Output 4
Z TRNS LOCA Dose Analysis Input Parameters DIT No. 13720-05 0
ZInput LlOutput 5
Z TRNS Control Room Input Parameters DIT No. 13720-07 0
[lnput L]Output 6
Z TRNS Meteorological Input Parameters DIT No. 13720-03 0
Zlnput L]Output 7
L 1 STD Accident Source Term 10 CFR 50.67 EInput E
Out ut 8
Z CALC Prairie Island Atmospheric Dispersion Factors (X/Qs) -
GEN-PI -080 1
ZInput LlOutp AST Additional Releases
/
U1/U2 9
TS PINGP Units 1 & 2,. Definition of Rated Thermal Power 1.1 Amendment ZInput LlOutput 158/149 U1/U2 10 H TS PINGP Units 1 & 2, Definition of Dose Equivalent 1-131 1.1 Amendment ZInput L]Output 158/149 U1/U2 11 Z TS PINGP Units 1 & 2, Definition of E-bar Average Disintegration 1.1 Amendment Zlnput L]Output Energy 177/167 UI1/U2 12 Z] TS PINGP Units 1 & 2 LCO for Shield Building Ventilation System 3.6.9 Amendment U1Input LlOutput (SBVS) 186/176 U1/U2 13 Z TS PINGP Units 1 & 2 LCO for RCS Specific Activity 3.4.17 Amendment ZInput
--Output 167/157
QF-0549 (FP-E-CAL-01), Rev. 3 Page 4 of 145
-XceIEnergy.
Calculation Signature Sheet U1/U2 14 Z TS PINGP Units 1 & 2 LCO for RCS Operational Leakage 3.4.14 Amendment ZInput L]Output 158/149 UI/U2 15
[] TS PINGP Units 1 & 2 LCO for Control Room Special Ventilation 3.7.10 Amendment Input L--Output System (C RSVS) 158/149 UI/U2 16
[] TS PINGP Units 1 & 2 LCO for Auxiliary Building Special Ventilation 3.7.12 Amendment Input
--1Output System (ABSVS) 158/149 U1/U2 17 F] TS PINGP Units 1 & 2 LCO for Secondary Specific Activity 3.7.14 Amendment EInput E]Output 158/149 U1/U2 18 E TS Specification for Containment Leak Rate Testing Program 5.5.14.c Amendment ZInput []Output 174/164 UI/U2 19
[] TS PINGP Units 1 & 2 Specification for Ventilation Filter Testing 5.5.9 Amendment
[]Input LOutput Program (VFTP) 186/176 UI/U2 20
[] TS PINGP Units 1 & 2 LCO for Control Room Special Ventilation 3.3.6 Amendment
[]Input LOutput System (CRSVS) Actuation Instrumentation 158/149 21 El FGR Federal Guidance Report 11 EPA-520/1-88-020 Elnput L-Output 22 El FGR Federal Guidance Report 12 EPA-402-R-93-081 Z Input L--Output Westinghouse Letter - Nuclear Management Company Prairie NSP-07-59 23 Zq LTR Island Units 1 & 2, MUR Power Uprate Program, Core Activity LTR-PEP-07-26 11/02/2007 Zlnput [:]Output Inventory and Coolant Activity Concentrations 24 El STD Laboratory Testing of Nuclear-Grade Activated Charcoal GL 99-02 6/3/99 ZInput -iOutput 25 E USAR Environmental Consequences of Loss-Of-Coolant-Accident 14.9 27 ZInput L]Output 26 E USAR Steam Generator Design Data Table 4.1-5 27 Elnput L]Output 27 E USAR Rupture of a Control Rod Drive Mechanism Housing (RCCA 14.5.6 29P Ellnput EOutput Ejection) 28 E] DOC ASME Steam Tables Sixth Edition EInput LlOutput 29 SRP NUREG-0800, Standard Review Plan, "Radiological 15.0.1 0
ZInput MOutput Consequence Analyses Using Alternative Source Terms" 30 Z CALC Post-LOCA EAB, LPZ, and CR Doses -AST GEN-PI-079 0
ZInput []Output 31
] STD Deletion of E Bar Definition and Revision to RCS Specific TSTF-490 0
Elnput LljOutput 31__
_SD Activity Tech Spec
QF-0549 (FP-E-CAL-01). Rev. 3 Paae 5 of 145 XceI Energy Calculation Signature Sheet 32 H PROC Natural Circulation Cooldown With CRDM Fans 1ES-0.3A 14 ZInput ilOutput 33 Z PROC Natural Circulation Cooldown Without CRDM Fans 1 ES-0.3B 11 ZInput [:]Output LAR to Revise the Loss of Coolant Accident (LOCA) and Main 34 F1 LAR Steam Line Break Accident (MSLB) Dose Consequences L-PI-08-052 06/26/2008 ZInput
--Output Analyses and Affected Technical Specifications (TS) 35 Z USAR Steam Generators 4.3.2.1.1 28 ZInput
--Output Beaver Valley Power Station, Unit Nos. 1 and 2, Issuance of License Amendments 257 and 139 Re: Selective 36 Z SER Implementation of Alternate Source Term and Control Room ML032530204 09/10/2003 ZInput L-Output Habitability Technical Specification Changes, September 10, 2003 (ADAMS Accession Number ML032530204) 37 Z CALC Prairie Island Atmospheric Dispersion Factors (X/Qs) - AST GEN-PI-080 0
EInput E]Output Additional Releases 38 Z DRAW Admin Bldg, Screen House, & Control RM Flow Diagram NF-39603-1 & T-Mod 76 ZInput
--Output EC 14090 Design, Testing, and Maintenance Criteria for Postaccident 39 E:1 RG Engineered-Safety-Feature Atmosphere Cleanup System Air 1.52 2
Zlnput LlOutput 39 RG Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants 40 PINGP Emergency Plan Implemetating Procedure, F3-20 22
[Input [-]Outpl 40 PROC Determination of Radioactive Release Concentrations Steam Release Pathway Inputs for Main Steam Line Break 41 E TRNS (MSLB), Steam Generator Tube Rupture (SGTR), Locked Rotor Accident (LRA) and Control Rod Ejection Accident DIT No. 13720-16 0
Zlnput -- Outp (CREA)
PINGP Operating Procedure, 68 42 Z PROC Unit 1 Shutdown 1C1.3 67 ZInput DOutp Unit 2 Shutdown 2C1.3
- Controlled Doc checkmark means the reference can be entered on the C012 panel in black. Unchecked lines will be yellow.
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)
If checked, also list
QF-0549 (FP-E-CAL-01), Rev. 3 Page 6 of 145 XcI.Energy."
XceI Ee y Calculation Signature Sheet Other Pass Port Data Associated System (PassPort C011, first three columns)
OR Equipment References (PassPort C025, all five columns):
Facility Unit System Equipment Type Equipment Number PI 1
MS GEN 134-011 PI 1
MS GEN 134-012 PI 1
MS GEN 234-011 PI 1
MS GEN 234-012 PI 1
MS CV CV-31084 PI 1
MS CV CV-31085 PI 1
MS CV CV-31086 PI 1
MS CV CV-31089 PI 1
MS CV CV-31090 PI 1
MS CV CV-31091 PI 2
MS CV CV-31102 PI 2
MS CV CV-31103 PI 2
MS CV CV-31104 PI 2
MS CV CV-31107 PI 2
MS CV CV-31108 PI 2
MS CV CV-31109 P1 1
MS RFV RS-21-1 P1 1
MS RFV RS-21-2 P1 1
MS RFV RS-21-3 P1 1
MS RFV RS-21-4 P1 1
MS RFV RS-21-5 Pi 1
MS RFV RS-21-6 Pi 1
MS RFV RS-21-7 PI 1
MS RFV RS-21-8 PI 1
MS RFV RS-21-9 PI 1
MS RFV RS-21-13 P1 2
MS RFV RS-21-14 P1 2
MS RFV RS-21-15 P1 2
MS RFV RS-21-17 P1 2
MS RFV RS-21-18
QF-0549 (FP-E-CAL-01), Rev. 3 Page 7 of 145 Xcei Energy' Calculation Signature Sheet Facility Unit System Equipment Type Equipment Number PI 2
ZN SYS SYS 0ZN PI 0
ZN FILTER 069-241 PI 0
ZN FILTER 069-242 PI 0
ZA FILTER 069-111 PI 0
ZA FILTER 069-112 PI 1
ZS FILTER 169-101 PI 1
ZS FILTER 169-102 PI 2
ZS FILTER 269-101 PI 2
ZS FILTER 269-102 PI 0
RD RM RM-24 Superseded Calculations (PassPort C019):
Facility Calc Document Number Title Description Codes - Optional (PassPort C018):
Code Description (optional)
Code Description (optional)
Notes (Nts) - Optional (PassPort X293 from C020):
Topic Notes Text
[] Calc Introduction Z] Copy directly from the calculation Intro Paragraph or E] See write-up below The purpose of this calculation is to determine the Exclusion Area Boundary (EAB), Low Population Zone (LPZ), and Control Room (CR) doses due to a Rod Ejection Accident (REA) using the Alternative Source Term (AST) methodology and total effective dose equivalent (TEDE) dose criteria, and the plant-specific bounding design information applicable to the PINGP Units 1 & 2 steam generators. The dose consequences are representative of a REA occurring in either Unit I or Unit 2.
ED (Specify)
XceI Energy Calculation No. GENP 082 Revision No.0 0PageNo8of 1
- x ceIE norg'*.1 V,,
- i :::: : **:
De s ign Review Comment F orm I
Sheet
-of DOCUMENT NUMBER/ TITLE:
GEN-PI-082/ Rod Ejection Accident - AST REVISION:
0 DATE:
ITEM REVIEWER'S COMMENTS PREPARER'S REVIEWER'S RESOLUTION DISPOSITION I
Editorial comments made in document text.
Incorporated.
Accepted 09/08/09 2
The acronym "PC" is used for "primary Incorporated.
Accepted 09/08/09 containment," primary coolant," and "partition coefficient". There can only be one meaning for this acronym. Corrected in text.
3 Section 4.4.1 indicates that activity is not Incorporated. Reference is made to Accepted 09/08/09 released into the containment air space. This Section 2.4.4 of the AST LOCA is not correct since a REA is, in fact, a small-Calculation GEN-PI-079.
break LOCA. Therefore, activity IS released into the containment. The LOCA calc says that "The direct shine from the post-LOCA activity confined above the containment operating floor to the CR operator encounters a slant line-of-sight path through the 1.5" of the containment steel, 2.5' of the SB concrete wall, 3.0' of the CR ceiling & roof, and multiple other concrete roof and walls of the auxiliary building. The encountered concrete and steel barriers (at least 5.5' thick concrete, 1.5" steel, plus other AB concrete) provide ample shielding to completely shield the post-LOCA containment shine dose to the CR operator." Since this amounts to zero dose, the same thing should be true for the REA.
4 The licensed power level in Design Input Incorporated.
Accepted 09/08/09 5.3.1 should mention the value of 1683 MWt as being 102% of the licensed power level.
5 Design Input 5.6.7A lists the CR DI 5.6.7A is the pre-isolation normal Accepted 09/08/09 Recirculation flow at 10,000 cfm. However, operation CR recirculation flow rate of the LOCA cale uses 4,000 cfm =/- 10%
10,000 cfm. The 4,000 cfm value is (3,600 cfm used in LOCA analysis). Why the the filtered recirculation flow rate difference?
following CR isolation.
6 Design Input Section 5.7 (Site boundary The LPZ distance is listed because the Accepted 09/08/09 release parameters) lists the LPZ distance, but LPZ X/Q is based on a distance not the EAB distance.
interpolation of data provided in the
/
USAR.
Xce.. Energy.
Calculation No. GEN-PI-082 Revision No. 0 Page No. 9 of 145 SiXcelEne r~gy Design Review Comment Form I Sheet of DOCUMENT NUMBER/ TITLE:
GEN-PI-082/ Rod Ejection Accident - AST REVISION:
0 DATE:
ITEM REVIEWER'S COMMENTS PREPARER'S REVIEWER'S RESOLUTION DISPOSITION 7
Section 7.0 indicates that Table 8 is for Incorporated. The Table titles and Accepted 09/08/09 containment leakage and assumes 25% iodine headings are revised. Table 8 release from melted fuel. Table 9 is supposed addresses the activity present in the to be for the secondary coolant leakage and RCS that is available for instantaneous assumes 50%. However, Tables 8 & 9 are release into the containment air space.
titled the same, causing potential confusion.
Table 9 addresses the activity present in the RCS that is available for primary-to-secondary leakage into the secondary coolant.
8 Design Input 5.6.7A (CR Recirculation Flow DI 5.6.7A is deleted.
Accepted 09/08/09 Rate) is included, but is not used. Why is it listed?
END Reviewer: Thomas Mscisz Date: 09/07/2009 Preparer: Gopal J. Patel Date: 09/08/2009
Xcei Enery Calculation No. GEN-PI-082 Revision No. 0 Page No. 10 of 145 REVISION HISTORY Revision Description 0
Initial Issue I
The TDAFW pump exhaust steam release path is re-evaluated as Unit 2 Group 1 and Group 2 PORV release paths
________________ 1
X eEnergyl Calculation No. GEN-P1-082 Revision No. 0 PaeNo. 11 of 145 SHEET REVISION INDEX SHEET REV SHEET REV SHEET REV 1
1 26 0
51 0
2 0
27 1
52 0
3 0
28 1
53 0
4 0
29 0
54 1
5 1
30 0
6 0
31 1
7 0
32 1 3.1 0
8 0
33 0 3.2 1
9 0
34 0 3.3 1
10 1
35 0 3.4 1
11 0
36 1
12 0
37 1
13 1
38 0
14 0
39 1
15 1
40 1
16 0
41 1
17 0
42 0
18 1
43 0
19 1
44 0
20 0
45 0
21 0
46 0
22 0
47 0
23 0
48 1
24 0
49 1
25 0
50 1
Xcel Enery Calculation No. GEN-PI-082 Revision No. 0 Page No. 12 of 145 TABLE OF CONTENTS Section Sheet No.
Cover Sheet I
Revision History 10 Sheet Revision Index 11 Table of Contents 12 1.0 Purpose And Summary Report 13 2.0 Methodology 13 3.0 Acceptance Criteria 20 4.0 Assumptions 21 5.0 Design Inputs 28 6.0 Computer Codes & Compliance With Regulatory Requirements 36 7.0 Calculations 37 8.0 Results Summary And Conclusions 41 9.0 References 42 10.0 Tables 44 11.0 Figures 53 12.0 Affected Documents 56 13.0 Attachments 56 13.1 RADTRAD Output File PIREACLOO.oO 57 13.2 RADTRAD Output File PREAINIDOO.oO 85 13.3 RADTRAD Output File PREAINGOO.oO 107 13.4 RADTRAD Output File PREAINLQOO.oO 126
XceIl Energy Calculation No. GEN-PI-082 Revision No. 0 Page No. 13 of 145 1.0 PURPOSE AND
SUMMARY
REPORT 1.1 Purpose The purpose of this calculation is to determine the Exclusion Area Boundary (EAB), Low Population Zone (LPZ), and Control Room (CR) doses due to a Rod Ejection Accident (REA) using the Alternative Source Term (AST) methodology and total effective dose equivalent (TEDE) dose criteria, and the plant-specific bounding design information applicable to the PINGP Units 1 & 2 steam generators. The dose consequences are representative of a REA occurring in either Unit I or Unit 2.
1.2 Summary Report The resulting post-REA doses are shown in Section 8.0. These doses comply with the applicable regulatory allowable dose limits.
2.0 METHODOLOGY The P1NGP operating licenses are proposed to amend to implement the full scope AST methodology in lieu of the TID-14844 source term methodology. The TEDE offsite dose acceptance criteria specified in Table 6 of Regulatory Guide 1.183 (Ref. 9.1) are implemented in lieu of the whole body and thyroid dose guidelines provided in 10 CFR 100.11. In addition, the 5 rem TEDE control room dose acceptance criterion specified in 10 CFR 50.67 (Ref. 9.4) is implemented in lieu of the 5 rem whole body and equivalent organ dose guidelines provided in 10 CFR 50 Appendix A GDC 19.
The design basis rod ejection accident is analyzed using a conservative set of assumptions and as-built design inputs. The numeric values of the critical design inputs are conservatively selected to assure an appropriate prudent safety margin against unpredicted events in the course of an accident and compensate for large uncertainties in facility parameters, accident progression, radioactive material transport, and atmospheric dispersion. The REA analysis is performed using the guidance in Regulatory Guide 1.183 and its Appendix H (Ref. 9.1).
This analysis uses Version 3.03 of the RADTRAD computer code (Ref. 9.2) to calculate the potential radiological consequences of the REA. The validation and verification (V&V) of the RADTRAD code is addressed in Section 6.
The REA dose consequences are determined by summing together the results from the containment leakage and the primary-to-secondary (P-T-S) leakage iodine and noble gas activity releases, and the secondary liquid iodine release.
Per RG 1.183, Appendix H, Section 3, the following two release cases are considered:
- 1.
Containment Leakage Release: 100% of the activity released from the fuel is assumed to be released instantaneously and homogeneously throughout the containment atmosphere and available for release to the environment.
- 2.
Secondary System Release: 100% of the activity released from the fuel is assumed to be completely dissolved in the primary coolant (i.e., Reactor Coolant System [RCS]) and available for release to the environment through the secondary system.
No additional release paths other than containment leakage and secondary side releases are required to be considered per RG 1.183, Appendix H.
XceI Energy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 14 of 145 2.1 Containment Leakage Release Per RG 1.183, Appendix H, Section 1, the following activity is assumed to be instantaneously and homogeneously distributed in the containment following a control rod ejection accident (Ref 9.1):
10% of the core iodine and 10% of the core noble gases in the fuel gap of failed fuel 25% of the core iodine and 100% of the core noble gases in the melted fuel In addition, this analysis also releases 100% of the iodine and noble gases initially present (i.e., pre-REA) in the reactor coolant system (RCS).
The source term, containment activity transport, environmental release and post-REA CR response are discussed in the following sections:
2.1.1 Failed Fuel Gap Inventory Per RG 1.183, Appendix H, Section 1, for the rod ejection accident, the release from the breached fuel is based on the estimate of the number of fuel rods breached (i.e., in Departure from Nucleate Boiling
[DNB]) and the assumption that 10% of the core inventory of the noble gases and iodines is in the fuel gap. The expected number of fuel rods in DNB is 10% of the core (Ref. 9.3.1, Item # 3). Per RG 1.183, Appendix H, Section 1, for the rod ejection accident, the release attributed to fuel melting is based on the fraction of the fuel that reaches or exceeds the initiation temperature for fuel melting and the assumption that 100% of the noble gases and 25% of the iodine contained in that fraction are available for release from containment. The expected fuel melt is 0.25% of the core (Ref. 9.3.1, Item # 3).
The exclusion of iodine spiking is consistent with the guidance presented in RG 1.183 (Ref. 9.1, Appendix E, Footnote 2), which states that the activity assumed in the analysis should be based on the activity associated with the projected fuel damage or the maximum technical specification values, whichever maximizes the radiological consequences. Since the RCS activity associated with 10% failed fuel and fuel melt of 0.25% of the core is greater than that of an iodine spike, the iodine spike is not included with the failed fuel activity release.
The REA fuel gap isotopic activity release fractions specified in RG 1. 183, Appendix H, release more iodine and noble gases than the generic non-LOCA event fuel gap isotopic activity release fractions specified in RG 1.183, Table 3. In addition, the REA fuel gap isotopic activity release fractions specified in RG 1.183, Appendix H, do not require a release of alkali metals (i.e., Cs, Rb).
Since RG 1.183, Table 3, does not apply to the REA event, the Table 3 gap release fraction applicability limitations listed in RG 1.183 Note 11 do not apply.
Although RG 1.183, Appendix H, does not require consideration of a release of alkali metals for the REA event, it is noted that if a release of alkali metals was considered, the release of alkali metals would result in an insignificant dose contribution compared to the dose contribution from noble gases which are released directly to the environment without hold-up.
In an intact steam generator in which the tubes are covered by liquid for the event duration, the release of alkali metals is facilitated solely by steam generator moisture carryover of no more than 0.25%
(Ref. 9.20) (i.e., a factor of 400 less than the noble gas release rate). In addition, the alkali metals introduced into both intact SGs are diluted within the SG space of approximately 3400 cubic feet (per Section 7.1.2), and then gradually released as this SG liquid volume is steamed to the environment at a rate of no more than 40 cfm (per Section 7.2.2, without consideration of iodine partition coefficient of 100). This release rate of approximately 0.012 SG volumes per minute (= 40 cfm / 3400 cf) is 85 times lower than the noble gas release rate to the environment. Combining the moisture carryover and hold-up effect indicates that the alkali metal release rate is approximately 34,000 times (= 400 x 85) lower than
XceI Energy Calculation No. GEN-PI-082 Revision No. 0 Page No. 15 of 145 the noble gas release rate to the environment. This hold-up of the alkali metal within the intact SG significantly reduces the alkali metal activity released to the environment in comparison to the noble gas activity released to the environment.
In addition, the control room dose contribution from alkali metals is further minimized by their removal via the 99% efficient control room HEPA recirculation filter (Ref. 9.3.2, Item #14), which would reduce the alkali metal CR dose contribution by an additional factor of 100.
The activity released during the vent contributes to the external dose (whole body gamma - DDE) and internal dose (inhaled - CEDE). All alkali isotopes including the daughters are naturally beta emitters; therefore, they do not contribute to any external dose. The inhaled dose conversion factors for the rubidium and cesium isotopes are calculated in Table 12, which shows that the alkali isotopes are inherently low thyroid inhalation dose contributors. These dose characteristics combined with the extremely low fractional release of less than 1/34,000 will result in inconsequential CR and offsite doses, which will be eliminated as being less than the significant figure rounding error.
Westinghouse Letter NSP-07-59, LTR-PEP-07-26 (Ref. 9.9, Table 2-1) presents the PINGP Units 1 and 2 core inventory at a core thermal power level of 1683 MWt at reactor shutdown. This core inventory is bounding for the 422V+ (Heavy Bundle or FIB) core and OFA core (Ref. 9.9, Section 2.0).
The core activity is based on a core thermal power of 1,683 MWt (= 1,650 MWt x 1.02) including the 2% power level measuring instrument uncertainty, fuel enrichment of 5.0%, and cycle burnup of 25,000 MWD/MTU (Ref. 9.9, Table 6-1). For conservatism and to bound possible core inventory increases associated with a 10% Power Uprate, the activity released to the containment is based on a core thermal power level of 1,852 MWt (= 1.10 x 1,683 MWt). Based on the amount of fuel failed and fuel melted, the iodine and noble gas activity released to the containment is calculated in Table 8 with appropriate release fractions (Ref. 9.1, Appendix H, Section 1), and the RADTRAD NIF "PIREACNTdef.txt" is developed using the total activity released to the containment.
2.1.2 Activity Transport in Containment The radioactivity released from the core is assumed to mix instantaneously and homogeneously throughout the free air volume of the primary containment. The design inputs for the transport in the primary containment are shown in Reference 9.13, Section 5.3.2 and the post-LOCA radiological response of the containment is described in Reference 9.13, Section 2.1.2.
During the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> the containment is assumed to leak at its maximum technical specification leak rate of 0.15 volume percent per day and at 50% of this leak rate (i.e., 0.075 volume percent per day) for the remaining duration of the accident (Ref. 9.1, Appendix H, Section 6.2, and Ref. 9.13, Section 2.1.2).
Although allowed by Regulatory Guide 1.183 (Ref. 9.1, Appendix H, Section 6.1), no credit is taken for a reduction in the amount of radioactive material available for leakage from the containment due to natural deposition, containment spray, and elemental iodine removal by surface deposition.
The post-REA radiological response of containment is similar to that for a LOCA. Therefore, the REA analysis modifies the LOCA containment activity transport design inputs and RADTRAD plant scenario file (psf) "PI250CLOO.psf' as obtained from Reference 9.13. The REA modifications include using the REA specific source term and eliminating certain dose mitigation credits, such as not taking credit for a reduction in the amount of radioactive material available for leakage from the containment due to natural deposition, containment spray, and elemental iodine removal by surface deposition. The post-REA containment leakage transport and CR response models are shown in Figures 1 & 3. The corresponding new RADTRAD plant scenario file for the post-REA containment leakage is "PIREACLOO.psf'.
XcelEnergy Calculation No. GEN-PI-082 Revision No. 0 Page No. 16 of 145 The resulting post-REA doses from the containment leakage release path are combined with the dose contributions from secondary system release path in Section 8.1. Per Reference 9.19, Section 3.6, the actual doses from a REA would be a composite of the two pathways.
2.2 Secondary System Release To maximize the secondary system release doses, it is assumed that offsite power is lost so that the main steam condensers are not available (Ref. 9.3.1, Item # 2). Due to the REA, the reactor is shutdown and the plant is being cooled down by discharging secondary coolant via the two intact steam generators (SGs). The post-REA iodine and noble gas activities released from the 10% failed fuel and 0.25%
melted fuel, which are completely dissolved in the RCS and available for release to the SGs, are calculated in Table 9 with appropriate release fractions (Ref. 9.1, Appendix H, Section 1), and the RADTRAD NIF "PIREARCS def.txt" is developed using the total activity released to the RCS. The post-REA secondary system release activity transport and CR response models are shown in Figures 2 &
3.
The resulting post-REA doses from the secondary system release path are combined with the dose contributions from containment leakage release path in Section 8.1. Per Reference 9.19, Section 3.6, the actual doses from a REA would be a composite of the two pathways.
2.2.1 RCS Iodine Inventory Westinghouse Letter NSP-07-59, LTR-PEP-07-26 (Ref. 9.9, Table 2-2, HB x 1.04 scenario) provides the PINGP Units 1 and 2 RCS iodine activity concentrations based on a 1% fuel defect level. Technical Specification 1.1 (Ref. 9.6.2) defines Dose Equivalent 1-131 as that concentration of 1-131 that alone would produce the same thyroid dose as the quantity and isotopic mixture of l-131, 1-132, 1-133, 1-134 and 1-135 actually present. Technical Specification 1.1 defines Dose Equivalent 1-131 (DE 1-131) in terms of the thyroid dose conversion factors listed in Table III of TID-14844. In this calculation, consistent with RG 1.183 methodology (Ref. 9.1, Section 4.1.2), DE 1-131 is defined in terms of the committed effective dose equivalent (CEDE) iodine inhalation dose conversion factors of FGR-1 I (Ref.
9.7). The use of FGR dose conversion factors in the Technical Specification 1.1 definition for DE 1-131 will be included in the AST license amendment request. The iodine inhalation dose conversion factors are calculated in Table I and used in Table 2 to establish a scaling factor based on 0.50 pCi/gram DE 1-131 to calculate Tech Spec iodine concentration in Table 3. The total isotopic iodine activities are conservatively calculated using the 1% failed fuel iodine concentration instead of 0.50 [tCi/gram DE 1-131 concentration and RCS mass (per Section 7.1.1) in Table 4.
2.3 Noble Gas Inventory Per Technical Specification LCO 3.4.17 (Ref. 9.6.6), the maximum permitted equilibrium RCS non-iodine concentration is 100/E-BAR. The parameter E-BAR is defined in Technical Specification Section 1.1 (Ref. 9.6.3) as the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes, other than iodines, with half lives greater than 15 minutes, making up at least 95% of the total non-iodine activity in the coolant.
A PINGP license amendment request (Ref. 9.17) proposes the deletion of the E-BAR definition and revision of the RCS Specific Activity Tech Specification to utilize a new indicator, Dose Equivalent Xenon-133, instead of the current indicator known as E-BAR. The current limits on primary coolant gross specific activity will be replaced with limits on primary coolant noble gas activity. The noble gas activity would be based on DOSE EQUIVALENT XE-133 and would take into account only the noble
XCe Energy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 17 of 145 gas activity in the primary coolant. The determination of Dose Equivalent Xe-133 will be performed in a similar manner to that currently used in determining DE 1-13 1, except that the calculation of Dose Equivalent Xe-133 is based on the acute dose to the whole body and considers the noble gases which are significant in terms of contribution to whole body dose. Some noble gas isotopes are not included due to low concentration, short half-life, or small dose conversion factor.
Per TSTF-490 traveler (Ref. 9.15), the DOSE EQUIVALENT XE-133 shall be that concentration of Xe-I 33 (ptCi/gm) that alone would produce the same acute dose to the whole body as the combined activities of noble gas nuclides [Kr-85m, Kr-85, Kr-87, Kr-88, Xe-131m, Xe-133m. Xe-133, Xe-135m, Xe-135, and Xe-138] actually present. The determination of DOSE EQUIVALENT XE-133 shall be performed using effective dose conversion factors for air submersion listed in Table 111. 1 of EPA Federal Guidance Report No. 12, 1993, "External Exposure to Radionuclides in Air, Water, and Soil" or the average gamma disintegration energies as provided in ICRP Publication 38, "Radionuclide Transformations" or similar source.
The XE-133 Dose Equivalent concentration is established in Table 5 as defined in the TSTF-490 design specification using effective dose conversion factors for air submersion listed in Table 111. 1 of EPA Federal Guidance Report No. 12 (Ref. 9.8) and 1% failed fuel noble gas isotopic concentrations in Reference 9.9, Table 2-2 for HB x 1.04. The proposed XE-133 Dose Equivalent concentration limit for noble gas activity is calculated to be 580.tCi/gm XE-133 DE (Table 5), and is used in this analysis with the noble gas isotopic concentrations in Table 6.
2.4 Secondary Coolant Liquid Iodine Inventory Per Technical Specification LCO 3.7.14 (Ref. 9.6.9) the secondary coolant iodine concentration is limited to 0.1 pCi/gram DE 1-131. This is one-fifth of the proposed Specification LCO 3.4.17 RCS iodine concentration limit of 0.50 jiCi/gram DE 1-131. In Table 7, the RCS iodine concentration profile at the 0.50 ýtCi/gm DE 1-131 is multiplied by the secondary to primary limits (0.1/0.5) to determine the secondary coolant iodine concentration profile. Table 7 scales this secondary coolant iodine activity concentration profile by the coolant mass in both intact steam generators (per Section 7.1.2) to calculate the total secondary coolant iodine inventory. This secondary coolant iodine activity inventory is input into RADTRAD Nuclide Inventory File "PIREA-liqdef.txt".
2.5 Post-REA Releases 2.5.1 Primary to Secondary (P-T-S) Leakage Rate This analysis models the RCS operational leakage limit of 150 gallons/day of primary to secondary (P-T-S) leakage through each steam generator (SG) at 70'F (i.e., 300 gpd through both SGs) as specified in Technical Specification LCO 3.4.14 (Ref. 9.6.5).
Consistent with RG 1. 183 (Ref. 9.1, Appendix H, Section 7.1) the primary-to-secondary leakage is assumed to continue until shutdown cooling is in operation and the releases from the steam generators have been terminated. In this analysis the RCS is assumed to leak into the SGs for 45.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> at which time the Residual Heat Removal (RHR) system is initialized (Ref. 9.3.1, Item # 24).
2.5.2 RCS Iodine Release Through P-T-S Leakage The SG tubes are expected to be submerged in the intact SGs secondary coolant during the REA event (Ref. 9.3.1, Item # 21). The iodine activity in the P-T-S leakage is assumed to mix with SG coolant
XceIEn'erIgY]Calculation No. GEN-PI-082 Revision No. 0 Page No.18 of 145 without flashing during period of submergence (Ref. 9.1, Appendix H, Section 7.4 and Appendix E, Section 5.5.1) and iodine partition coefficient of 100 is assumed (Ref. 9.1, Appendix H, Section 7.4 and Appendix E, Section 5.5.1 and Ref. 9.3. 1, Item # 22). The RCS iodine release continues until the R1-R system is initialized at 45.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> (Ref. 9.3.1, Item # 24).
The doses from the REA RCS iodine release are summarized in Section 8.1.
2.5.3 RCS Noble Gas Release Through P-T-S Leakage Noble gases present in the P-T-S leakage are released directly to the environment without dilution or retention in the intact SGs (Ref. 9.1, Appendix H, Section 7.3). The RCS noble gas release continues until the RHR system is initialized at 45.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> (Ref. 9.3.1, Item # 24).
The doses from the REA RCS noble gas release are summarized in Section 8.1.
2.5.4 Secondary Liquid Iodine Release to the Environment Although Regulatory Guide 1.183 (Ref. 9.1, Appendix H) does not include a requirement to consider the release of pre-accident activity present in the steam generators, this analysis conservatively considers the release of the pre-accident secondary liquid iodine. The iodine activity in the bulk water in the SG is assumed to become vapor and is directly released to the environment in proportion to the steam release rate, with credit taken for iodine partitioning in the SG liquid. For the secondary liquid iodine release from the SGs, an iodine partition coefficient of 100 is assumed as recommended in Regulatory Guide 1.183 (Ref. 9.1, Appendix H, Section 7.4 and Appendix E, Section 5.5.4).
The secondary coolant iodine release continues until the RHR system is initialized at 45.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> (Ref. 9.3.1, Item # 24).
The doses from the REA secondary liquid iodine release are summarized in Section 8.1.
2.6 Steam Release Atmospheric Dispersion to the Control Room The post-REA long-term release through the turbine driven auxiliary feed water pump (TDAFWP) exhaust was intentionally postulated in Revision 0 of this analysis to maximize the resulting doses.
Actually the steam is released through the TBDAF.W pump exhaust momentarily when offsite power is lost and diesel generator complete it load sharing sequence and onsite power is available to safety related equipment including the motor driven AFW pump (MDAFWP). Plant operating procedures provide guidance such that the operators would preferentially use the MDAFWP in lieu of the TDAFWP. Per shutdown procedure C1.3 (Ref. 9.24), only one AFW pump is running when one pump is able to maintain SG levels (Step 5.4.13). The MDAFW Pump is preferable to the TDAFW Pump (implied from Step 5.4.5 and 5.4.6). In addition, speed of the TDAFWP is affected by the steam pressure in the SG. At lower steam pressures in the SG, the TDAFWP would slow down and provide inadequate FW inventory to cover the SG tube. Furthermore, the activity levels released from the TDAFWP steam exhaust are not accurately estimated during an event - see procedure F3-20, Step 5.1 (Ref. 9.23). In order to provide adequate SG tube coverage and more accurate estimates of releases, the MIDAFW is obviously used.
There will be a steam release through the TDAFWP exhaust momentarily until the onsite power is available through the diesel generator, which is less than a few minutes. The apportioned steam mass from the intact SG is conservatively postulated to release from the Unit 2 Groups I & 2 PORVs having the higher X/Qs (Ref. 9.5, Table 8-5). Thus use of the Unit 2 Groups I & 2 PORVs X/Qs conservatively bound the mometarily steam release from the TDAFWP exhaust.
The locations of the Groups I & 2 PORVs with respect to locations of Units I & 2 CR air intakes are such that the Unit 2 Groups 1 & 2 PORVs are is located closer to the Unit 2 CR air intake (Ref. 9.5,
xceiEnorgy. Calculation No. GEN-PI-082 T Reision No. 0 Page No.19 of 145 Sections 2.4 & 2.5). Therefore, the post-REA activity is postulated to release from the intact SGs via Unit 2 PORVs to maximize the CR dose.
Following the event the intact SGs are used to cooldown the RCS. The mass of the steam released and the release location during the cooldown are important considerations due to the total 300 gpd P-T-S leakage assumed for the intact SG (maximum allowed by Technical Specification 3.4.14) (Ref. 9.6.5).
Assuming a loss of off-site power the unit would be cooled down using procedure ES-0.3A or ES-0.3B (Ref. 9.16) for cooling down using natural circulation. Per either procedure, the preferred means to release steam for the cooldown is by dumping steam to the condenser. If this path is not available, then the SG PORV is used (Refs. 9.16.1, Step 8 and 9.16.2, Step 7). The time dependent steaming rates through the intact SGs are shown in Section 5.5.8 and obtained from Reference 9.3.5, Attachment C.
The apportioned P-T-S leakage rates used in this analysis are based on the steam mass flow rate distribution through the intact SGS as shown Table 10.
The post-REA secondary system activity transport and CR response models are shown in Figures 2 and 3, which are used to determine the post-REA radiological consequences using the plant-specific as-built design inputs and assumptions listed in Sections 4 & 5.
2.7 CR Air Intake Radiation Monitor Response.
Post-accident Xe-133 activity in the CR @ 0.0833 hr (5 minutes)
= 0.72185 Ci (RADTRAD Run PREAINGOO.oO)
Control room volume 61,315 ft3 (Section 5.6.1) = 61,315 ft3 / (3.28 ft/m)3 = 1,737.58 m3 Xe-133 activity concentration in the CR @ 0.0036 hr (0.22 minute)
= 0.72185 Ci / 1,737.58 m3 = 4.154E-04 Ci/m 3 = 4.154E-04 gCi/cc, which exceeds CR monitor setpoint of IE-05 pCi/cc for Xe-133 (Section 5.6.20). The calculated setpoint value conservatively does not includes activity from the containment leakage and iodine activity from the intact SG release.
Since the Xe-133 activity in the CR is circulated by the CR recirculation flow through the CR air supply duct (Ref. 9.22), the monitor setpoint is instantly exceeded. Therefore, the CR actuation delay of 5 minutes following a heavy load drop is considered conservative, and does not require any further justification.
3.0 ACCEPTANCE CRITERIA:
The following NRC regulatory requirement and guidance documents are applicable to this PINGP Alternative Source Term REA Calculation:
Regulatory Guide 1.183 (Ref, 9.1) 10 CFR 50.67 (Ref. 9.4)
Standard Review Plan section 15.0.1 (Ref. 9.12)
Dose Acceptance Criteria are:
Regulatory Dose Limits Dose Type Control Room (rem)
TEDE Dose 5
6.3
XceI Energy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 20 of 145
4.0 ASSUMPTIONS
Regulatory Guide 1.183 (Ref. 9.1) provides guidance on modeling assumptions that are acceptable to the NRC staff for the evaluation of the radiological consequences of a PWR rod ejection accident. The following sections address the applicability of these modeling assumptions to the PINGP Units I and 2 REA analysis.
These assumptions are incorporated as design inputs in Sections 5.3 through 5.7. There are no unvalidated assumptions used in this calculation.
The radioactivity material releases and radiation levels used in the control room dose analysis are determined using the same source term, transport, and release assumptions used for determining the exclusion area boundary (EAB) and the low population zone (LPZ) TEDE values (Ref 9.1, Section 4.2.2).
4.1 Source Term 4.1.1 Fuel Damage Source Term It is assumed that ten percent (10%) of the core is assumed to experience clad damage and one-fourth of one percent (0.25%) of the core is assumed to experience fuel melt as a result of the REA (Ref. 9.3.1, Item # 3).
It is assumed consistent with RG 1.183 (Ref. 9.1, Appendix H, Section 1), that the release from the breached fuel to the containment and available for containment release, or to the primary coolant and available for release to the secondary system, is based on the estimate of the number of fuel rods breached (i.e., 10%) and the assumption that 10% of the core inventory of the noble gases and iodines is in the fuel gap.
It is assumed consistent with RG 1.183 (Ref. 9.1, Appendix H, Section 1), that the release attributed to fuel melting is based on the fraction of the fuel (i.e., 0.25%) that reaches or exceed the initiation temperature for fuel melting and the assumption that 100% of the noble gases and 25% of the iodines contained in that fraction are available for release from containment.
It is assumed consistent with RG 1.183 (Ref. 9.1, Appendix H, Section 1), for the secondary system release pathway, 100% of the noble gases and 50% of the iodines in the fraction of the fuel (i.e., 0.25%) that reaches or exceed the initiation temperature for fuel melting are released to the reactor coolant.
The above source term requirements are incorporated in the Design Input 5.3.
4.1.2 No Fuel Damage Source Term Fuel damage is assumed for the REA. Therefore, consistent with RG 1.183 (Ref. 9.1, Appendix H, Section 2), a radiological analysis for the REA is required.
4.1.3 Release Cases to be Considered It is assumed consistent with RG 1.183 (Ref. 9.1, Appendix H, Section 3), that two release cases are considered in this REA analysis. In the first, 100% of the activity released from the fuel is assumed to be released instantaneously and homogeneously through the containment atmosphere. In the second, 100% of the activity released from the fuel is assumed to be completely dissolved in the primary coolant and available for release to the secondary system (see Figures 1 & 2).
Xce Ene 82 Revision No. 0 Page No.21 of 145 4.1.4 Containment Airborne Iodine Form It is assumed consistent with RG 1.183 (Ref. 9.1, Appendix H, Section 4), that the chemical form of radioiodine released to the containment atmosphere is assumed to be 95% cesium iodide (CsI) (i.e., particulate), 4.85%
elemental iodine, and 0.15% organic iodide.
4.1.5 Steam Generator Release Iodine Form It is assumed consistent with RG 1.183 (Ref. 9.1, Appendix H, Section 5), that the iodine releases from the steam generators to the environment are assumed to be 97% elemental and 3% organic.
4.2 Transport 4.2.1 Transport From Containment 4.2.1.1 Reduction in Radioactive Material RG 1.183 (Ref. 9.1, Appendix H, Section 6.1) allows for a reduction in the amount of radioactive material available for leakage from the containment that is due to natural deposition, containment sprays, recirculating filter systems, dual containments, or other engineered safety features to be taken into account. Conservatively, this analysis assumes no reduction in the post-REA airborne activity by any mechanism other than decay or leakage.
4.2.1.2 Containment Leakage It is assumed that the primary containment leaks at a proposed new Technical Specification peak pressure leak rate of 0.15% by weight for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Ref, 9.1, Appendix H, Section 6.2). This leak rate is less than the leak rate currently allowed by Technical Specification 5.5.14.c (Ref. 9.6.10). This leak rate is reduced to 0.075% by weight after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Ref. 9.1 Appendix H, Section 6.2).
4.2.2 Transport From Secondary System 4.2.2.1 Primary-to-Secondary Leak Rates It is assumed consistent with RG 1.183 (Ref. 9.1, Appendix H, Section 7.1), that the primary-to-secondary (P-T-S) leakage is at the RCS operational leakage limit of 150 gallons/day through any one SG (i.e., 300 gpd through both SGs) as specified in Technical Specification LCO 3.4.14 (Ref. 9.6.5).
It is assumed consistent with RG 1.183 (Ref. 9. 1, Appendix H, Section 7.1), that the P-T-S leak exists until shutdown cooling is in operation (i.e., RHR is initiated) and releases from the steam generators have been terminated at 45.5 hrs (Ref. 9.3.1, Item # 26).
4.2.2.2 Primary-to-Secondary Leak Primary Coolant Density It is assumed consistent with RG 1.183 (Ref. 9.1, Appendix H, Section 7.2), that the primary coolant (i.e., RCS) density used in converting the volumetric primary-to-secondary leak rates (e.g., gpm) to mass leak rates (e.g.,
lbm/hr) is 1.0 gm/cc (62.4 lbm/ft3).
XcelEnergy Calculation No. GEN-PI-082 Revision No. 0 Page No.22 of 145 4.2.2.3 Noble Gas Transport Model (Releases to the Environment)
It is assumed consistent with RG 1.183 (Ref. 9.1, Appendix H, Section 7.3), that all noble gas radionuclides released from the primary system (via the primary-to-secondary leaks) are released to the environment without reduction or mitigation.
4.2.2.4 Iodine and Particulate Transport Model (Releases to the Environment)
RG 1.183 (Ref. 9.1, Appendix H, Section 5.6) states that the main steam line break (MSLB) accident transport model of RG 1'. 183, Appendix E, Sections 5.5 and 5.6 should be utilized for iodine and particulates. RG 1.183 Appendix E Sections 5.5 and 5.6 present the following transport model for use in evaluating releases from steam generators:
STEAM GENERATOR TRANSPORT MODEL Steam Space Release Primary Par titoninig Leakage r
Bulk Water In this analysis, no credit is taken for iodine scrubbing, only for iodine partitioning. It is assumed consistent with RG 1.183 (Appendix E, Section 5.5.4), that the iodine activity in the bulk water of the two intact steam generators (consisting of the initial secondary coolant iodine activity and the iodine activity introduced via primary-to-secondary leakage) becomes vapor at a rate that is a function of the steaming rate and assumed iodine partition coefficient of 100.
For the primary-to-secondary leakage iodine release from the SGs, the SG tubes are expected to be submerged in the SGs liquid during the event, and consequently iodine introduced into the two intact SGs via the P-T-S leakage is assumed to be released to the environment with an iodine partitioning coefficient of 100 as recommended in RG 1.183 (Ref. 9.1, Appendix H, Section 7.4 and Appendix E, Section 5.5.4 and Ref. 9.3.1, Item # 21).
For the secondary liquid iodine release from the SGs, an iodine partition coefficient of 100 is assumed (Ref. 9.3.1, Item # 21), consistent with the value of 100 recommended in Regulatory Guide 1.183 (Ref. 9.1, Appendix H, Section 7.4 and Appendix E, Section 5.5.4).
4.3 Offsite Dose Consequences Regulatory Guide 1.183 (Ref. 9.1, Section 4.1) provides guidance to be used in determining the total effective dose equivalent (TEDE) for persons located at the exclusion area boundary (EAB) and at the outer boundary of the low population zone (LPZ). The following sections address the applicability of this guidance to the P1NGP Units I and 2 REA analyses. These assumptions are incorporated as design inputs in Section 5.7.
XceIEnergY]Calculation No. GEN-PI-082 Revision No. 0 Page No.23 of 145 4.3.1 Modeling of Parent and Daughter Isotopes It is assumed consistent with RG 1.183 (Ref. 9.1, Section 4.1.1), that the dose calculation determines the TEDE, which is the sum of the committed effective dose equivalent (CEDE) from inhalation and the deep dose equivalent (DDE) from external exposure. It is assumed that the CEDE and DDE components of the TEDE consider all radionuclides, including progeny from the decay of parent radionuclides that are significant with regard to dose consequences and the released radioactivity. These isotopes are listed in Section 5.3.
4.3.2 CEDE (Inhalation) Dose Conversion Factors It is assumed consistent with RG 1.183 (Ref. 9. 1, Section 4.1.2), that the exposure-to-CEDE factors for inhalation of radioactive material are derived from the data provided in ICRP Publication 30, "Limits for Intakes of Radionuclides by Workers". This calculation models the CEDE dose conversion factors (DCFs) in the column headed "effective" yield doses in Table 2.1 of Federal Guidance Report 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion" (Ref. 9.7).
4.3.3 Offsite Breathing Rates It is assumed consistent with RG 1.183 *Ref. 9. 1, Section 4.1.3), that for the first 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, the breathing rate of persons offsite is assumed to be 3.5x10 cubic meters per second. From 8 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following the accident, the breathing rate is assumed to be 1.8x 10 4 cubic meters per second. After that and until the end of the accident, the rate is assumed to be 2.3X10 4 cubic meters per second. These offsite breathing rates are listed in Section 5.7.
4.3.4 DDE (Immersion) Dose Conversion Factors It is assumed consistent with RG 1.183 (Ref. 9.1, Section 4.1.4), that the deep dose equivalent (DDE) is calculated assuming submergence in semi-infinite cloud assumptions with appropriate credit for attenuation by body tissue. The DDE is nominally equivalent to the effective dose equivalent (EDE) from external exposure if the whole body is irradiated uniformly. Since this is a reasonable assumption for submergence exposure situations, EDE is used in lieu of DDE in determining the contribution of external dose to the TEDE. This calculation models the EDE dose conversion factors in the column headed "effective" in Table 111. 1 of Federal Guidance Report 12, "External Exposure to Radionuclides in Air, Water, and Soil" (Ref. 9.8).
4.3.5 Exclusion Area Boundary Dose Acceptance Criteria It is assumed for the REA that the postulated EAB dose should not exceed 6.3 Rem TEDE (per Section 3.2).
Per RG 1.183 Table 6, the REA event release duration is until cold shutdown is established. In this analysis, the REA event ends when shutdown cooling is placed into operation at 45.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> (Ref. 9.3.1, Item # 24).
The RADTRAD Code (Ref. 9.2) used in this analysis determines the maximum two-hour TEDE by calculating the postulated dose for a series of small time increments and performing a "sliding" sum over the increments for successive two-hour periods. The time increments appropriately reflect the progression of the accident to capture the peak dose interval between the start of the event and the end of radioactivity release.
XceIEnergy]Calcuation No. GEN-PI-082 Revision No. 0 Page No.24 of 145 4.3.6 Low Population Zone Outer Boundary Dose Acceptance Criteria It is assumed for the REA that the postulated LPZ dose should not exceed 6.3 Rem TEDE (per Section 3.3). Per RG 1.183 Table 6, the REA event release duration is until cold shutdown is established. In this analysis, the REA event ends when shutdown cooling is placed into operation at 45.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> (Ref. 9.3.1, Item # 24).
4.3.7 Effluent Plume Depletion It is assumed consistent with RG 1.183 (Ref. 9.1, Section 4.1.7), that no correction is made for depletion of the effluent plume by deposition on the ground.
4.4 Control Room Offsite Dose Consequences Regulatory Guide 1.183 (Ref. 9.1, Section 4.2) provides guidance to be used in determining the total effective dose equivalent (TEDE) for persons located in the control room (CR). The following sections address the applicability of this guidance to the PINGP Units 1 and 2 REA analyses. These assumptions are incorporated as design inputs in Section 5.6.
4.4.1 Control Room Operator Dose Contributors It is assumed consistent with RG 1.183 (Ref. 9.1, Section 4.2.1), the CR TEDE analysis considers the following sources of radiation that will cause exposure to control room personnel:
- Contamination of the control room atmosphere by the filtered CR ventilation inflow through the CR air intake and by unfiltered inleakage of the radioactive material contained in the post-accident radioactive plume released from the facility,
- Contamination of the control room atmosphere by filtered CR ventilation inflow via the CR air intake and by unfiltered inleakage of airborne radioactive material from areas and structures adjacent to the control room envelope,
- Radiation shine from the external radioactive plume released from the facility (i.e., external airborne cloud shine dose),
- Radiation shine from radioactive material in the reactor containment (i.e., containment shine dose). This form of radiation shine is not applicable to a REA since the direct shine from the post-LOCA activity confined above the containment operating floor to the CR operator encounters a slant line-of-sight path through the 1.5" of the containment steel, 2.5' of the SB concrete wall, 3.0' of the CR ceiling & roof, and multiple other concrete roof and walls of the auxiliary building. The encountered concrete and steel barriers (at least 5.5' thick concrete, 1.5" steel, plus other AB concrete) provide ample shielding to completely shield the post-LOCA containment shine dose to the CR operator (Ref 9.13, Section 2.4.4).
- Radiation shine from radioactive material in systems and components inside or external to the control room envelope (e.g., radioactive material buildup in CR intake and recirculation filters [i.e., CR filter shine dose]).
- Note:
The external airborne cloud shine dose and the CR filter shine dose due to a REA are expected to be less than those due to a LOCA as a result of source term differences (i.e., the LOCA releases significantly more activity from failed fuel than does the REA event per RG 1.183 [Ref. 9.1, Table 2 for LOCA compared to Appendix H, Section 1 for REA]). Therefore, the post-LOCA external airborne cloud and CR filter shine doses are conservatively applied to the REA in Section 8.1.
XceI Energ -, Calculation No. GEN-PI-082 Revision No. 0 Page No. 25 of 145 4.4.2 Control Room Source Term It is assumed consistent with RG 1. 183 (Ref. 9.1, Section 4.2.2), that the radioactive material releases and radiation levels used in the control room dose analysis are determined using the same source term, transport, and release assumptions used for determining the EAB and the LPZ TEDE values. The parameters assumed for determining the EAB and LPZ TEDE values also result in conservative dose projections to the control room personnel.
4.4.3 Control Room Transport It is assumed consistent with RG 1.183 (Ref. 9.1, Section 4.2.3), that the models used to transport radioactive material into and through the control room, and the shielding models used to determine radiation dose rates from external sources, are structured to provide suitably conservative estimates of the exposure to control room personnel. These conservative assumptions include conservative values for unfiltered inleakage, minimum clean-up air flow rates, and minimum filter efficiencies. The shielding models are not developed to determine radiation dose rates from external sources because their dose contributions are insignificant compared to those from a LOCA (Section 4.4.1).
4.4.4 Control Room Response It is assumed consistent with RG 1.183 (Ref. 9.1, Section 4.2.4), that engineered safety features (ESF) that mitigate airborne radioactive material within the control room are credited. Such features include control room recirculation filtration. CR isolation is actuated by radiation monitors (RMs). The Xe-133 concentration at the CR air intake instantaneously exceeds the CR radiation monitor setpoint of 1.OE-05 pCi/ml following a REA (see Section 2.7). Therefore, a delay of 5 minutes for the CR isolation to be fully operational is considered to be conservative and no further sensitivity of delay time is required.
4.4.5 Control Room Operator Use of Dose Mitigating Devices It is assumed consistent with RG 1.183 (Ref. 9.1, Section 4.2.5), that credit is not taken for the use of personal protective equipment (e.g., protective beta radiation resistant clothing, eye protection, or self-contained breathing apparatus) or prophylactic drugs (i.e., potassium iodide [KI] pills).
4.4.6 Control Room Occupancy Factors and Breathing Rates It is assumed consistent with RG 1.183 (Ref. 9.1, Section 4.2.6), that the CR dose receptor for these analyses is the hypothetical maximum exposed individual who is present in the control room for 100% of the time during the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the event, 60% of the time between 1 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 3.5x 10-4 cubic meters per second. These assumptions are incorporated as design inputs in Section 5.6.
4.4.7 Control Room Dose Conversion Factors It is assumed consistent with RG 1.183 (Ref. 9.1, Section 4.2.7), that the control room doses are calculated using the offsite dose analysis dose conversion factors identified in RG 1.183 Regulatory Position 4.1 (see preceding Sections 4.3.2 & 4.3.4). The deep dose equivalent (DDE) from photons is corrected for the difference between finite cloud geometry in the control room and the semi-infinite cloud assumption used in calculating the dose conversion factors. The RADTRAD Code (Ref. 9.2) used in this analysis uses the
~,XceIEnergy - Calculation No. GEN-PI-082 Revision No. 0 Page No. 26 of 145 following expression to correct the semi-infinite cloud dose, DDE., to a finite cloud dose, DDEfinite, where the control room is modeled as a hemisphere that has a volume, V, in cubic feet, equivalent to that of the control room:
DDEfinite = (DDEcc x V0 "338) / 1173 4.4.8 Control Room Operator Dose Acceptance Criteria It is assumed that for the REA the postulated CR dose should not exceed 5 Rem TEDE (Ref. 9.4).
Xce'IEergy Calculation No. GEN-PI-082 Revision No. 0 Page No.27 of 145 5.0 DESIGN INPUTS:
5.1 General Considerations 5.1.1 Applicability of Prior Licensing Basis As discussed in RG 1.183 (Ref. 9.1, Section 5.1.4), the implementation of an AST is a significant change to the design basis of the facility and assumptions and design inputs used in the analyses. The characteristics of the AST and the revised TEDE dose calculation methodology may be incompatible with many of the analysis assumptions and methods currently used in the facility's design basis analyses. The P1NGP specific design inputs and assumptions used in the TID-14844 analyses were assessed for their validity to represent the as-built condition of the plant and evaluated for their compatibility to meet the AST characteristics and TEDE methodology. The analysis in this calculation ensures that analysis assumptions, design inputs, and methods are compatible with the requirements of the AST and the TEDE criteria.
5.1.2 Credit for Engineered Safety Features Credit is taken only for those accident mitigation features that are classified as safety-related, are required to be operable by technical specifications, are powered by emergency power sources, and are either automatically actuated or, in limited cases, have actuation requirements explicitly addressed in emergency operating procedures. The dose mitigation features of the Shield Building Ventilation System (SBVS) (Ref. 9.6.4),
Auxiliary Building Special Ventilation System (ABSVS) (Ref. 9.6.8), and Control Room Special Ventilation System (CRSVS) (Ref. 9.6.7) are credited in the analysis. These systems are safety related and operable by Technical Specification applicable LCOs. The SBVS, ABSVS, and CRSVS 1-IEPA particulate removal filtration efficiency and charcoal iodine removal filtration efficiencies used in the analysis are verified by the Ventilation Filter Testing Program in Technical Specification 5.5.9 (Ref. 9.6.11), which comply with Generic Letter (GL) 99-02 (Ref. 9.10) as demonstrated in Section 7.3. The CRSVS air intake monitors are required to be operable by TS 3.3.6 and Table 3.3.6-1 (Ref. 9.6.12) in Modes 1, 2, 3, & 4 and during movement of irradiated fuel assemblies. The CRSVS actuation during the REA is credited in the analysis with a 5-minutes system response delay (Section 2.7). The Aux Bldg Normal Vent dampers that help establish the ABSVZ boundary are not safety related. Acceptability for crediting the dampers is based on the isolation logic for closing the dampers is safety related and redundant in that a single failure cannot defeat the function. The proper functioning of the dampers is verified quarterly as part of established surveillance procedures to satisfy Technical Specifications.
Applicable Technical Specification action statements are applied if a damper fails to properly actuate (Ref.
9.3.2, Item # 9).
Although allowed by Regulatory Guide 1.183 (Ref. 9.1, Appendix H, Section 6.1), no credit is taken for a reduction in the amount of radioactive material available for leakage from the containment due to natural deposition, containment spray, and elemental iodine removal by surface deposition.
5.1.3 Assignment of Numeric Input Values The numeric values chosen as inputs to this analysis are compatible to AST and TEDE dose criteria and selected with the objective of maximizing the postulated dose. The loss of offsite power for entire duration of the event disabling the condenser, 60/40 split of Groups 1 & 2 PORV steam releases, use of more than measured CR unfiltered inleakage, 5 minutes delay for CRSVS actuation and a 10% lower CR recirculation flow rate are conservatively used to maximize the resulting doses.
Xce Energy~ Calculation No. GEN-PI-082 Revision No. 0 Page No. 28 of 145 5.1.4 Meteorology Considerations The control room atmospheric dispersion factors (X/Qs) are developed in References 9.5 & 9.18 using the NRC sponsored ARCON96 computer code. The release points for activity released to the environment are the Unit 2 Groups I & 2 PORV release locations (Section 2.6) and Units I & 2 Shield Building Vent Stack (Ref. 9.3.2, Item # 22).
Per the AST LOCA Calculation GEN-PI-079 (Ref. 9.13, Sections 2.4.1 & 2.4.2), the use of the CR air intake X/Qs are conservative for the CR unfiltered inleakage and are modeled for both the CR makeup flow during 0 to 5 minutes and the unfiltered inleakage for greater than 5 minutes.
The EAB and LPZ X/Qs used in this analysis were originally developed for the plant operating license and were accepted by the staff in the previous licensing proceedings.
5.2 Accident-Specific Design Inputs/Assumptions The design inputs and assumptions utilized in this EAB, LPZ, and CR dose consequence analysis are listed in the following sections. The design inputs are compatible with the requirements of the AST characteristics and TEDE dose criteria and the assumptions are consistent with those identified in Section 4 and Appendix H of RG 1.183 (Ref. 9.1). The design inputs and assumptions in the following sections represent the as-built design of the plant.
L[* 'XceIEnerg Calculation No. GEN-PI-082 Revision No. 0 Page No. 29 of 145 Design Input Parameter Value Assigned Reference Rod Ejection Accident Parameters 5.3 Source Terms 5.3.1 Licensed power level 1,650 MW, 9.6.1 1,683 MWt (= 102% of 1,650 MWt)
Used in the analysis for 10% EPU 1,852 MWt(= 110% of 1,683 MW,)
5.3.2 Core isotopic activity (at 1,683 MWt) 9.9, Table 2-1 Isotope Activity (Ci)
Isotope Activity (Ci)
Isotope Activity (Ci) 1-131 4.50E+07 KR-85 7.15E+05 Xe-133M 2.86E+06 1-132 6.51E+07 Kr-85M 1.08E+07 Xe-133 9.15E+07 1-133 9.13E+07 Kr-87 2.12E+07 Xe-135M 1.95E+07 1-134 1.02E+08 Kr-88 2.82E+07 Xe-135 2.07E+07 1-135 8.72E+07 Xe-131M 5.06E+05 Xe-138 7.72E+07 Kr-83M 0.OOE+00 5.3.3 Primary coolant 1% fuel defects activity concentration 9.9, Table 2-2 Isotope Activity (jtCi/g)
Isotope Activity (jtCi/g)
Isotope Activity (tCi/g) 1-131 2.55E+00 Kr-85 1.09E+01 Xe-133M 3.65E+00 1-132 2.80E+00 Kr-85M 1.59E+00 Xe-133 2.60E+02 1-133 3.88E+00 Kr-87 1.03E+00 Xe-135M 5.02E-01 1-134 5.82E-01 Kr-88 2.89E+00 Xe-135 8.24E+00 1-135 2.20E+00 Xe-131M 2.05E+00 Xe-138 6.09E-01 Kr-83M 3.92E-01 RADTRAD Inventory Files Iodine activity initially present in Table 7 the secondary coolant.
Iodine and noble gas activity Table 8 instantaneously released from the RCS liquid to containment Iodine and noble gas activity Table 9 present in the RCS liquid and available for primary-to-secondary leakage 5.3.4 Post-REA failed (clad 10%
9.3.1, Item # 3 damaged) fuel 5.3.5 Percent of gap activity in 9.1, Appendix H, Section 1 damaged fuel released into Containment and available for leakage from containment:
Iodine 10%
Noble Gases 10%
Xcel ne*ry. Calculation No. GEN-PI-082 Revision No. 0 Page No. 30 of 145 Design Input Parameter Value Assigned Reference 5.3.6 Percent of gap activity in 9.1, Appendix H, Section 1 damaged fuel released into the RCS and available for P-T-S leakage:
10%
Iodine 10%
Noble Gases 5.3.7 Post-REA melted fuel 0.25%
9.3.1, Item # 3 5.3.8 Percent of melted fuel 9.1, Appendix H, Section 1 released into containment and available for leakage from containment:
Iodine 25%
Noble Gases 100%
5.3.9 Percent of melted fuel 9.1, Appendix H, Section 1 released into the RCS and available for P-T-S leakage:
Iodine 50%
Noble Gases 100%
5.4 Containment Activity Transport Model (see Figure 1) 5.4.1 Containment volume 1,320,000 ft3 9.3.2, Item # 13 5.4.2 Shield building free air 374,000 ft3 9.3.2, Item # 24 volume 5.4.3 Iodine chemical form Iodine Chemical Form 9.1, Appendix H, Section 4 Aerosol (Cs1) 95.0%
Elemental 4.85%
Organic 0.15%
5.4.4 Primary containment (PC) leak rate (Figure 1)
Maximum PC Leakage (LI + L2 +
0.15 w%/day < 24 hrs Proposed New Containment Leak L3) 0.075 w%/day > 24 hrs Rate limit for Reference 9.6.10 ABSVZ Total Leakage (L2) 0.06 w%/day < 24 hrs 0.03 w%/day > 24 hrs Shield Bldg Total Leakage (L1) 0.084 w%/day < 24 hrs 0.042 w%/day > 24 hrs Bypass Total Leakage (L 3) 0.006 w%/day < 24 hrs 0.003 w%/day > 24 hrs 5.4.5 Shield building drawdown 4.5 minutes 9.11.1 time 12 minutes Used in the analysis 5.4.6 ABSVZ drawdown time 6 minutes 9.3.2, Item # 30 20 minutes Used in the analysis 5.4.7 Initiation of shield building 20 minutes 9.11.1 & 9.3.2, Item # 32 recirculation 22 minutes Used in the analysis
Il.XcelEnergyl Calculation No. GEN-PI-082 Revision No. 0 Page No. 31 of 145 Design Input Parameter Value Assigned Reference 5.4.8 Shield building recirculation 4,000 cfm +/- 10%
9.3.2, Items # 32 & 34 flow rate 3,600 cfm Used in the analysis 5.4.9 Shield building exhaust rate 9.3.2, Item # 33, SB exhaust flow (50% mixing) rate is doubled to simulate 50%
22 min - 720 hrs 2,000 mixing in the SB after 22 minutes 5.4.10 ABSVS charcoal filter 80% for elemental iodine 9.13, Section 7.5.1 efficiencies 80% for organic iodide 5.4.11 ABSVS & SBVS HEPA 99% for aerosol 9.3.2, Item # 27 Filter Efficiency 5.4.12 Containment Leakage SB Vent Stack 9.3.2, Item # 22 Release Point 5.4.13 Post-LOCA Containment PI250CLOO.psf 9.13 Leakage RADTRAD Model 5.4.14 Nuclide Inventory File for PINGPDEF.NIF 9.13 post-LOCA Containment Leakage 5.4.15 RADTRAD Release pwrdba.rft 9.13 Fraction Time File for post-LOCA Containment Leakage 5.4.16 RADTRAD Dose fgrl 1&12.inp 9.13 Conversion Factor File for post-LOCA Containment Leakage 5.5 Secondary System Activity Transport Model (see Figure 2) 5.5.1 Steam generator liquid mass 9.3.1, Item # 10 UI Framatome ANP Model 56/19 107,100 lbm @ Full Power U2 Westinghouse Model 51 107,420 lbm @ Full Power 5.5.2 Nominal reactor coolant 5,290 ft3 9.9, Table 6-1 system (RCS) volume 5.5.3 Primary-to-Secondary leak 45.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 9.3.1, Item # 24 duration 5.5.4 RCS operational leakage 150 gpd - one intact SG 9.6.5 through any one SG 300 gpd - two intact SGs Used in the analysis 5.5.5 Density of P-T-S leakage 62.4 lbm/ft3 9.1, Appendix H, Section 7.2 5.5.6 SG liquid iodine partition 100 9.1, Appendix E, Section 5.5.4 and coefficient for SG liquid iodine 9.3.1, Item # 21 release 5.5.7 Iodine release from SG 9.1, Appendix H, Section 5 Elemental Iodine 97%
Organic Iodine 3%
5.5.8 Steam mass released from 9.3.5, Attachment C intact SGs to the environment 0- 2 hr 226,414 1bm 2 - 8 hr 406,952 lbm 8 - 24 hr 796,899 lbm 24 - 45.5 hr 863,053 lbm 5.5.9 SG liquid iodine partition 100 9.1, Appendix E, Section 5.5.4 coefficient for P-T-S leakage
& 9.3.1, Item # 21
XceI Enery Calculation No. GEN-PI-082 Revision No. 0 Page No. 32 of 145 Design Input Parameter Value Assigned Reference 5.5.10 Steam condition at full load 519.20 F and 806.8 psia - Unit 1 9.11.2, page 1 of 2 510.80F and 750 psia - Unit 2 -
5.6 Control Room (CR) Parameters 5.6.1 CR volume 61,315 fW 3
9.3.3, Item # 6 5.6.2 CRSVS normal flow rate 1,818 cfm +/- 10%
9.3.3, Item # 10 2,000 cfm < 5 minutes Used in the analysis 5.6.3 CRSVS makeup rate 0 cfm > 5 minutes 9.3.3, Item # 4 (CR operates in a recirculation mode) 5.6.4 CRSVS Recirc flow rate 4,000 cfm +/- 10%
9.3.3, Item # 13 3,600 cfm > 5 minutes Used in the analysis 5.6.5 CRSVS charcoal filter 95% for elemental iodine Section 7.3.1 efficiencies 95% for organic iodide 5.6.6 CRSVS HEPA filter 99%
Section 7.3.2 efficiency 5.6.7 CR unfiltered inleakage 250 cfm (includes 10 cfm for Assumed value ingress and egress) 5.6.8 CR breathing rate 3.5E-04 m 3/sec 9.1, Section 4.2.6 5.6.9 CR allowable dose limit 5 rem TEDE for the event duration 9.4 5.6.10 Unit 2 CR X/Qs for containment leakage via Unit 2 SB exhaust stack release Time (Hr)
X/Q (sec/m 3) 9.18, Section 8.1.1 (maximum 0-2 4.53E-03 X/Qs for any SBVS release to CR 2-8 3.93E-03 air intake dispersion path) 8-24 1.73E-03 24-96 1.22E-03 96-720 9.16E-04 5.6.11 CR occupancy factors Time (Hr) 9.1, Section 4.2.6 0-24 100 24-96 60 96-720 40 5.6.12 Unit 2 CR air intake x/Qs for Unit 2 Group I PORV Release - Intact SG Time (Hr)
X/Q (sec/m 3) 9.5, Table 8-5 0-2 3.07E-02 2-8 2.49E-02 8-24 1.12E-02 24-96 7.78E-03 96-720 6.17E-03 5.6.13 Unit 2 CR air intake X/Qs for Unit 2 Group 2 PORV Release - Intact SG Time (Hr)
X/Q (sec/m 3) 9.5, Table 8-5 0-2 2.20E-03 2-8 1.81E-03 8-24 7.97E-04 24-96 5.16E-04 96-720 4.00E-04 5.6.14 PORV mass release 60% from the Group I PORVs 9.3.1 distribution 40% from the Group 2 PORVs
S XceEnergy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 33 of 145 Design Input Parameter Value Assigned Reference 5.6.15 CR Monitor Setpoint 1.OE-05 iCi/ml for Xe-133 9.3.2, Item # 9 5.7 Site Boundary Release Model Parameters 5.7.1 EAB atmospheric dispersion 6.49E-04 sec/m3 9.3.4, Item # 2 factor (Z/Q) 5.7.2 EAB breathing rate (m3/sec) 3.5E-04 9.1, Section 4.1.3 5.7.3 LPZ Distance 2,414 m 9.3.4, Item # 3 5.7.4 LPZ Atmospheric Dispersion Factors (x/Qs)
Time (Hr) x/Q (sec/m3) 9.3.4, Item # 3 0-8 1.77E-04 8-24 3.99E-05 24-96 7.12E-06 96-720 1.04E-06 5.7.5 LPZ Breathing Rate (m3/sec)
Time (Hr)
(m3/sec) 9.1, Section 4.1.3 0-8 3.5E-04 8-24 1.8E-04 24-720 2.3E-04 5.7.6 EAB allowable dose limit 6.3 rem TEDE for any 2-hour 9.1, Table 6 period 5.7.7 LPZ allowable dose limit 6.3 rem TEDE for the event
- 9. 1, Table 6 duration
XpeIEnergy. Calculation No. GEN-PI-082 Revision No. 0 Page No. 34 of 145 6.0 COMPUTER CODES & COMPLIANCE WITH REGULATORY REQUIREMENTS 6.1 COMPUTER CODES:
RADTRAD 3.03 (Ref. 9.2) is an NRC-sponsored code approved for use in determining control room and offsite doses from releases due to reactor accidents. This code was used by the most of the AST license amendments that have been approved by the NRC. A rigorous high quality code qualification process was adopted to develop and procure the code by testing of the program elements, verification of input/output files, and examination of design specification. Therefore the RADTRAD3.03 computer code is considered to be qualified to comply with the quality assurance requirements of 10 CFR50, Appendix B and it can be safely used to perform the design basis accident analyses.
Calculation GEN-PI-079 (Ref. 9.13, Sections 2.6 & 8.2) documents a V&V of the RADTRAD3.03 -
code. Suitable acceptance test cases for the PWR radiological analysis were incrementally selected, initially defining simplified cases that could verified against analytical solutions, then adding complexity (typically a control room) and comparing the results against the RADTRAD3.03 and HABIT code analyses, adding more complexity (e.g., removal by decay chain) and comparing the results with the RADTRAD3.03 and HABIT codes again. The selected PWR code cases cover all essential characteristics of an REA AST analysis, including transportation of activity within the compartment and in the atmosphere. All radiological features of the RADTRAD3.03 code were verified and validated by running the selected PWR code cases in the Microsoft Window XP environment. The results of V&V code cases were summarized in Calculation GEN-PI-079, Section 8.2, and compared with the RADTRAD3.03 and HABIT code results, which showed an excellent agreement.
Therefore, the RADTRAD code is considered validated for use in this PINGP AST analysis.
6.2 COMPLIANCE WITH REGULATORY REQUIREMENTS:
As discussed in Section 4.0, Assumptions, the analysis in this calculation complies with the line-by-line requirements in Regulatory Guide 1.183 including its Appendix H.
XcefiFnergy Calculation No. GEN-PI-082 Revision No. 0 Page No. 35 of 145
7.0 CALCULATIONS
The REA dose consequences are determined by summing together the results from a set of three RADTRAD code analyses that separately calculate the dose contributions from the containment leakage, primary-to-secondary (P-T-S) leakage iodine activity release, the P-T-S leakage noble gas activity release, and the secondary liquid iodine release.
RADTRAD Nuclide Inventory Files (NIF) "PIREACNTdef.txt" and "PIREARCSdef.txt" model the nuclide inventory of Table 8 for the containment leakage and Table 9 for the secondary system leakage, respectively.
RADTRAD NIF "PIREA liq_def.txt" models the secondary coolant iodine inventory of Table 7.
RADTRAD RFT File "pirea rft.txt" is used for both iodine and noble gas release by setting the iodine and noble gas release fractions to 1.0, and all other release fractions to zero. RADTRAD Release Fraction Timing (RFT) File "PINGPIodineRFT.txt" is used for iodine release by setting the iodine release fraction to 1.0 and all other release fractions to zero. RADTRAD RFT File "PIREANGRFT.txt" is used for noble gas release by setting the noble gas release fraction to 1.0 and all other release fractions to zero. These release fractions can be seen in the RADTRAD output pages.
All four RADTRAD runs use Dose Conversion File (DCF) "PINGP fgl 1&12.txt", which uses CEDE inhalation DCFs from FGR-1 1 (Ref. 9.7), and EDE immersion DCFs from FGR-12 (Ref. 9.8).
7.1 Reactor Coolant & Steam Generator Coolant Mass 7.1.1 RCS Mass:
RCS water volume = 5,290 ft3 @ 560'F and 2235 psia (Ref. 9.9, Table 6-1 & Ref. 9.3.1, Item # 22)
RCS specific volume at 560'F and 2235 psia = 0.02165 ft3/lb (Ref. 9.14, page 281)
RCS density at 560'F and 2235 psia = 1 / (0.02165 ft3/lb) = 46.19 lb/ft3 RCS water density at cooled liquid conditions = 62.4 lb/ft3 (Ref. 9.1, Appendix H, Section 7.2)
The RCS mass at cooled liquid conditions is:
RCS Mass = 5,290 ft3 x 62.4 lb/ft3 x 453.6 gm/lb = 1.497E+08 gm [used in Tables 4 and 6] (a larger mass yields a greater RCS activity inventory available for leakage) 7.1.2 SG Liquid Volume and Mass:
The steam generator (SG) tubes are expected to be submerged in the intact SGs coolant during the REA event, with no tube uncovery (Ref. 9.3.1, Item # 21). The iodine activity in the P-T-S leakage is assumed to mix with SG coolant without flashing during period of submergence (Ref. 9.1, Appendix H, Section 7.4 and Appendix E, Section 5.5.1).
The Unit I SGs are Framatome ANP Model 56/19 with a full power liquid mass of 107,100 lb (Ref. 9.3.1, Item # 10). The Unit 2 SGs are Westinghouse Model 51 with a full power liquid mass of 107,420 lb (Ref. 9.3.1, Item # 10). The total intact SG liquid volume is minimized by assuming that the secondary liquid mass is at cooled liquid conditions. Minimizing the intact SGs dilution volume will maximize the intact SGs liquid activity concentrations due to P-T-S leakage. Maximizing the intact SGs liquid activity concentration will conservatively maximize the intact SGs steaming activity releases to the environment.
Total intact SG liquid mass = 107,100 lb + 107,420 lb = 214,520 lb x 453.6 gm/lb = 9.731 E+07 gm Total intact SG liquid volume = 214,520 lb / 62.4 lb/ft 3= 3,438 ft3
SXcei Energy alculation No. GEN-PI-082 Revision No. 0 Page No.36 of 145 7.2 Post-REA Release Rates 7.2.1 P-T-S Leakage Iodine and Noble Gas Release Rate Per Design Input 5.5.4, the primary to secondary leakage through any one SG is 150 gpd.
P-T-S volumetric leakage rate into intact SGs = 0.208 gpm (= [2 SGs x 150 gpd/SG] / [24 hr/day x 60 min/hr])
P-T-S volumetric leakage rate into intact SGs = (0.208 gpm) x (0.13368 ft3/gal) = 0.02781 cfm Per Regulatory Guide 1.183 (Ref. 9.1, Appendix H, Section 7.2), the density of this P-T-S leakage at the time of surveillance test measurement is assumed to be 1.0 gm/cc (62.4 lb/ft3). Therefore, the P-T-S mass leakage rate into the intact SGs at measured conditions is:
P-T-S mass leakage rate at measured conditions = (0.02781 ft3/min) x (62.4 lb/ft3) = 1.735 lb/min Per Section 7.1.1, at the time of the REA the RCS is operating at 560'F and 2235 psia with an RCS specific volume of 0.02165 fl3/lb. Therefore, the iodine and noble gas P-T-S volumetric leakage rate into the intact SGs at conditions present during the REA is:
0-45.5 hr P-T-S volumetric leakage rate during the REA = (1.735 lb/min) x (0.02165 ft3/lb) 0-45.5 hr P-T-S volumetric leakage rate during the REA = 0.0376 cfm of RCS liquid 0-45.5 hr iodine and noble gas P-T-S leakage rate from RCS to the intact SGs = 0.0376 cfm 7.2.2 Intact SGs PORVs Steaming Rates (P-T-S Leakage):
Unit i steam temperature @ full power = 519.20 F and 806.8 psia (Ref. 9.11.2)
Unit 1 liquid specific volume @ full power = 0.02089 ft3/lbm (Ref. 9.14, page 182)
Unit 2 steam temperature @ full power = 510.80F and 750 psia (Ref. 9.11.2)
Unit 2 liquid specific volume @ full power = 0.02069 fl3/lbm (Ref. 9.14, page 182)
Unit I liquid specific volume of 0.02089 fl3/lbm is conservatively used in the following section to maximize the volumetric steaming rates:
The intact SGs tubes remain covered during the REA, the iodine partition factor of 100 (Ref. 9.1, Appendix H, Section 5.6 and Appendix E, Section 5.5.4) is credited in calculating the steaming rate from the intact SGs :
Total mass of steam released from intact SG to the environment (0 - 2 hr) = 226,414 lb (Ref. 9.3.5, Attachment C)
Intact SG steaming rate (0 - 2 hr) = 226,414 lb x 0.02089 ft3/lb x (1/100) = 0.3942 cfm of Intact SG liquid 120 minutes Total mass of steam released from intact SG to the environment (2 - 8 hr) = 406,952 (Ref. 9.3.5, Attachment C)
Intact SG steaming rate (2 - 8 hr) = 406,952 lb x 0.02089 ft3/lb x (1/100) = 0.2361 cfm of Intact SG liquid 360 minutes Total mass of steam released from intact SG to the environment (8 - 24 hrs) = 796,899 lb (Ref. 9.3.5, Attachment C)
~,XcelEnergyl Calculation No. GEN-PI-082 Revision No. 0 TPage No. 37 of 145 Intact SG steaming rate (8 -24 hr) = 796,899 lb x 0.02089 ft3/lb x (1/100) = 0.1734 cfm of Intact SG liquid 960 minutes Total mass of steam released from intact SG to the environment (24 - 45.5 hrs) = 863,053 lb (Ref. 9.3.5, Attachment C)
Intact SG steaming rate (24 - 45.5 hr) = 863,053 lb x 0.02089 ft3/lb x (1/100) = 0.1398 cfm of Intact SG liquid 1290 minutes 0 - 2 hr iodine P-T-S leakage release from intact SG to the environment = 0.3942 cfm of Intact SG liquid 2 - 8 hr iodine P-T-S leakage release from intact SG to the environment = 0.2361 cfm of Intact SG liquid 8 - 24 hr iodine P-T-S leakage release from intact SG to the environment = 0.1734 cfm of Intact SG liquid 24 - 45.5 hr iodine P-T-S leakage release from intact SG to the environment = 0.1398 cfm of Intact SG liquid 7.2.3 Intact SGs - Iodine Release Rate - Secondary Liquid The steaming rates for the secondary liquid iodine releases from the intact steam generators are the same as the intact SGs iodine release rates calculated in Section 7.2.2.
0 - 2 hr iodine secondary liquid release from intact SG to the environment = 0.3942 cfm of Intact SG liquid 2 - 8 hr iodine secondary liquid release from intact SG to the environment = 0.2361 cfm of Intact SG liquid 8 - 24 hr iodine secondary liquid release from intact SG to the environment = 0.1734 cfm of Intact SG liquid 24 - 45.5 hr iodine secondary liquid release from intact SG to the environment = 0.1398 cfm of Intact SG liquid 7.3 CRSVS Charcoal / HEPA Filter Efficiencies The Control Room Special Ventilation System (CRSVS) charcoal and H1EPA filter efficiencies are modeled per the following table, based on the calculations perfonrmed in the following subsections.
Safety Grade Filter Efficiency Credited (%)
Filter Aerosol Elemental Organic CRSVS 99 95 95 7.3.1 CRSVS Charcoal Filter Efficiency Laboratory penetration testing acceptance criteria for the safety related Charcoal filters are as follows:
CRSVS Charcoal Filter-in-laboratory testing methyl iodide penetration < 2.5% (Ref. 9.6.11 Section 5.5.9.c)
Generic Letter 99-02 (Ref. 9.10) requires a safety factor of at least 2 to be used to determine the filter efficiencies to be credited in the design basis accident.
Testing methyl iodide penetration (%) = (100% - q)/safety factor = (100% - i)/2 Where il = charcoal filter efficiency to be credited in the analysis CRSVS Charcoal Filter:
J&..Xc elEnergyj Calculation No. GEN-PI-082 Revision No. 0 Page No. 38 of 145 2.5% ý (100% - n)/2 5% = (100% - TI) r" = 100% - 5% = 95%
7.3.2 CRSVS HEPA Filter Efficiency CRSVS HEPA Filter - in-place DOP penetration and system bypass < 0.05% (Ref. 9.6.11 Section 5.5.9.a)
Generic Letter 99-02. (Ref. 9.10) requires a safety factor of at least 2 to be used to determine the filter efficiencies to be credited in the design basis accident.
Testing DOP penetration (%) = (100% - if)/safety factor = (100% - rl)/2 Where ri = HEPA filter efficiency to be credited in the analysis CRSVS HEPA Filter:
0.05% = (100% -,q)/2 0.10% = (100% - 11) q = 100% - 0.10% = 99.9%
Regulatory Guide 1.52 (Ref. 9.21, Regulatory Position C.5.c) states that if the in-place penetration and bypass testing results are <0.05%, the condition can be considered to warrant a 99% removal efficiency for particulates in accident dose evaluations. Therefore, a I-EPA filter efficiency of 99% is used in the analysis.
4rv XceI Energyj Calculation No.
Rev-i sinNo08Pg2o.3 o
4 Revision No. 0 I Page No. 39 of 145 I
8.0 RESULTS
SUMMARY
/CONCLUSIONS:
8.1 Result Summary:
The post-REA EAB, LPZ, and CR doses are summarized in the following table:
Rod Ejection Accident TEDE Dose (rem)
Receptor Location Control Room EAB LPZ Containment Leakage 4.11E-01 1.93E-01 1.17E-01 PIREACLOO.oO (occurs @ 0.0 hr)
P-T-S Iodine Release ISG 3.1OE+00 2.88E-01 1.67E-01 PREAINIDOI.oO (occurs @ 24 hrs)
P-T-S Noble Gas Release ISG 3.05E-01 1.87E-01 1.02E-01 PREAING01.o0 (occurs @ 0.0 hrs)
Liquid Iodine Release ISG 1.07E-02 1.17E-03 9.66E-04 PREAINLQOI.oO (occurs @ 0.0 hrs)
External Cloud*
4.51E-02 O.OOE+00 O.OOE+00 CR Filter Shine*
2.33E-02 0.OOE+00 0.00E+00 Total 3.91E+00 6.69E-01 3.87E-01 Allowable TEDE Limit 5.OOE+00 6.30E+00 6.30E+00 ISG = Intact SG
- Post-LOCA External Cloud & CR Filter Shine Doses Used From Reference 9.13, Section 8.1 8.2
==
Conclusions:==
The results of Rod Ejection Accident analysis in Section 8.1 indicate that the EAB, LPZ, and CR doses due to a REA accident are within their allowable limits. The calculated doses have adequate margins over the allowable dose limits for future safe operation of the plant. The proposed new LCO 3.4.17 for Reactor Coolant System Specific Activity is 580 gCi/gm DE of XE-133 based on the primary coolant noble gas activity correspond to 1% failed fuel with the following changes:
Delete the definition of "E-Bar," AVERAGE DISINTEGRATION ENERGY Add a new definition for DOSE EQUIVALENT XE-133 Revise LCO 3.4.17, "RCS Specific Activity, to delete references to gross specific activity Reference limit on DOSE EQUIVALENT XE-133 Revise SR 3.4.16.1 to verify the limit for DOSE EQUIVALENT XE-133
,Xcelnerg Calculation No. GEN-PI-082 Revision No. 0 Page No. 40 of 145
9.0 REFERENCES
- 1.
US. NRC Regulatory Guide 1.183, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors, July 2000
- 2.
S.L. Humphreys et. al., "RADTRAD: A Simplified Model for Radionuclide Transport and Removal and Dose Estimation," NUREG/CR-6604, USNRC, December 1997
- 3.
Design Input Transmittal Nos.
3.1 Design Input Transmittal (DIT) No. 13720-10, Rev. 0, CREA Input Parameters 3.2 Design Input Transmittal (DIT) No. 13720-05, Rev. 0, LOCA Dose Analysis Input Parameters 3.3 Design Input Transmittal (DIT) No. 13720-07, Rev. 1, Control Room Input Parameters 3.4 Design Input Transmittal (DIT) No. 13720-03, Rev. 0, Meteorological Input Parameters 3.5 DIT No. 13720-16, Rev 0, Steam Release Pathway Inputs for Main Steam Line Break (MSLB), Steam Generator Tube Rupture (SGTR), Locked Rotor Accident (LRA) and Control Rod Ejection Accident (CREA)
- 4.
10 CFR 50.67, "Accident Source Term"
- 5.
PINGP Calculation No. GEN-PI-080, Rev 1, Prairie Island Atmospheric Dispersion Factors (X/Qs) -
AST Additional Releases
- 6.
PINGP Technical Specifications:
6.1 Specification. 1.1, PINGP Units 1 & 2, Rated Thermal Power 6.2 Specification 1.1, PINGP Units 1 & 2, Dose Equivalent 1-131 6.3 Specification 1.1, PINGP Units I & 2, E-bar Average Disintegration Energy 6.4 Specification 3.6.9, PINGP Units I & 2 LCO for Shield Building Ventilation System (SBVS) 6.5 Specification 3.4.14, PINGP Units 1 & 2 LCO for RCS Operational Leakage 6.6 Specification 3.4.17, PINGP Units I & 2 LCO for RCS Specific Activity 6.7 Specification 3.7.10, PINGP Units 1 & 2 LCO for Control Room Special Ventilation System (CRSVS) 6.8 Specification 3.7.12, PINGP Units 1 & 2 LCO for Auxiliary Building Special Ventilation System (ABSVS) 6.9 Specification 3.7.14, PINGP Units 1 & 2 Limiting Condition for Operation (LCO) for Secondary Specific Activity 6.10 Specification 5.5.14.c, Containment Leak Rate Testing Program 6.11 Specification 5.5.9, Ventilation Filter Testing Program (VFTP) 6.12 Specification 3.3.6, PINGP Units 1 & 2 LCO for Control Room Special Ventilation System (CRSVS) Actuation Instrumentation and Table 3.3.6-1, PINGP Unit 1/Unit 2 LCO for Radiation Monitoring Instrumentation
- 7.
Federal Guidance Report 11, EPA-520/1-88-020, Environmental Protection Agency 8
Federal Guidance Report 12, EPA-402-R-93-081, Environmental Protection Agency
XceIEnergy] Calculation No. GEN-PI-082 Revision No. 0 Page No.41 of 145
- 9.
Westinghouse Letter NSP-07-59, LTR-PEP-07-26, Nuclear Management Company Prairie Island Units I & 2 MUR Power Uprate Program, Core Activity Inventory and Coolant Activity Concentration, November 2, 2007.
- 10.
USNRC Generic Letter 99-02, "Laboratory Testing of Nuclear-Grade Activated Charcoal", June 3, 1999
- 11.
PJNGP USAR Sections, Tables, & Figures:
11.1 Section 14.9, Environmental Consequences of Loss-Of-Coolant-Accident 11.2 Table 4.1-5, Rev 27, Steam Generator Design Data 11.3 PINGP USAR Section 14.5.6, Rev 29P, Rupture of a Control Rod Drive Mechanism Housing (RCCA Ejection)
- 12.
NUREG-0800, Standard Review Plan, "Radiological Consequence Analyses Using Alternative Source Terms," SRP 15.0.1, Rev. 0, July 2000
- 13.
PINGP Calculation No. GEN-PI-079, Rev 0, Post-LOCA EAB, LPZ, and CR Doses - AST
- 14.
ASME Steam Tables, Sixth Edition
- 15.
Technical Specification Task Force Improved Standard Technical Specifications Change Traveler TSTF-490, Rev 0, "Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec"
- 16.
PINGP Procedure Nos:
- 1.
IES-0.3A, Rev 14, Natural Circulation Cooldown With CRDM Fans
- 2.
1ES-0.3B, Rev 11, Natural Circulation Cooldown Without CRDM Fans
- 17.
PINGP License Amendment Request (LAR) L-PI-08-052, LAR to Revise the Loss of Coolant Accident (LOCA) and Main Steam Line Break Accident (MSLB) Dose Consequences Analyses and Affected Technical Specifications (TS), June 26, 2008
- 18.
PINGP Calculation No. GEN-PI-080, Rev 0, Prairie Island Atmospheric Dispersion Factors (X/Qs) -
AST Additional Releases
- 19.
Beaver Valley Power Station, Unit Nos. I and 2, Issuance of License Amendments 257 and 139 Re:
Selective Implementation of Alternate Source Term and Control Room Habitability Technical Specification Changes, September 10, 2003 (ADAMS Accession Number ML032530204)
- 20.
PINGP USAR Section 4.3.2.1.1, Rev 28, Steam Generators
- 21.
U.S. NRC Regulatory Guide 1.52, Rev 2, Design, Testing, and Maintenance Criteria for Postaccident Engineered-Safety-Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants, March 1978
- 22.
PINGP Flow Diagram No. NF-39603-1, Rev 76, Including T-Mod EC 14090, Admin Bldg, Screen House, & Control RM Flow Diagram
- 23.
PINGP Emergency Plan Implemetating Procedure No. F3-20, Rev 22, Determination of Radioactive Release Concentrations
- 24.
PINGP Operating Procedure Nos.
24.1 1C1.3, Rev 68, Unit I Shutdown 24.2 2C1.3, Rev 67, Unit I Shutdown
Xcel Energy Calculation No. GEN-PI-082 Revision No. 0 Page No. 42 of 145 10.0 TABLES:
Table I Iodine Isotopic Dose Conversion Factors Thyroid Radiation Units Thyroid Inhalation Conversion Inhalation Dose Factors Dose Isotope Conversion Conversion Factor Factor (Sv/Bq)
(rem/Ci per Sv/Bq)
(rem/Ci)
A B
C=AxB 1-131 2.92E-07 3.70E+ 12 1.08E+06 1-132 1.74E-09 3.70E+ 12 6.44E+03 1-133 4.86E-08 3.70E+12 1.80E+05 1-134 2.88E-10 3.70E+ 12 1.07E+03 1-135 8.46E-09 3.70E+ 12 3.13E+04 (A) From Reference 9.7, Page 136 Table 2 Iodine Scaling Factor for 1-131 Dose Equivalent 1% Fuel Defect Thyroid Iodine Inhalation Activity Dose Product Isotope Concentration Conversion Factor (giCi/gm)
(rem/Ci)
(gCi.rem / Ci.gm)
A B
(A x B) 1-131 2.55E+00 1.08E+06 2.76E+06 1-132 2.80E+00 6.44E+03 1.80E+04 1-133 3.88E+00 1.80E+05 6.98E+05 1-134 5.82E-01 1.07E+03 6.20E+02 1-135 2.20E+00 3.13E+04 6.89E+04 Total 3.54E+06 1-131 DE Based on 1% FF Iodine Concentration (lsCi/g); (C) I 3.28E+00 Iodine Scaling Factor Based on 0.50 gCi/g DE 1-131; (D) 1.526E-01 (A) From Reference 9.9, Table 2-2 for HB x 1.04, based on 1683 MWt per Reference 9.9, Table 6-1 (C) = Total / Iodine-131 Thyroid Inhalation Dose Conversion Factor (D) = 0.50 pCi/gm DE 1-131 / C
Xc IelErgy1 Calculation No. GEN-PI-082 Revision No. 0 Page No. 43 of 145 Table 3 RCS 0.50'liCi/gm DE 1-131 Iodine Concentration 1% Failed Fuel Iodine 0.50 pCi/gm Iodine Scaling DE 1-131 Isotope Activity Factor Iodine Concentration 0.50 gCi/gm Concentration (PCi/gm)
DE 1-131 (VCi/gm)
A B
C=AxB 1-131 2.55E+00 1.526E-01 3.891E-01 1-132 2.80E+00 1.526E-01 4.272E-01 1-133 3.88E+00 1.526E-01 5.920E-01 1-134 5.821E-01 1.526E-01 8.880E-02 1-135 2.20E+00 1.526E-01 3.357E-0I A From Reference 9.9, Table 2-2 for HB x 1.04, based on 1683 MWt per Reference 9.9, Table 6-1 B From Table 2 Table 4 1% Failed Fuel RCS Iodine Activity 1% Fuel Defect Reactor Total RCS Iodine Coolant Pre-Accident Isotope Activity Mass RCS Iodine Concentration Activity (PCi/gm)
(gm)
(Ci)
A B
C=(A xB)/1E6 1-131 2.55E+00 1.497E+08 3.817E+02 1-132 2.80E+00 1.497E+08 4.192E+02 1-133 3.88E+00 1.497E+08 5.808E+02 1-134 5.82E-01 1.497E+08 8.713E+01 1-135 2.20E+00 1.497E+08 3.293E+02 (A) From Reference 9.9, Table 2-2 for HB x 1.04, based on 1683 MWt per Reference 9.9, Table 6-1 (B) Reactor coolant mass from Section 7.1.1
XceI Energy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 44 of 145 Table 5 Dose Equivalent of Xenon-133 1% Failed Submersion Noble Fuel RCS Dose Product Gas Activity Coefficient Nuclide (l.LCi/gm)
(Sv m3 / Bq s)
(liCi/gm
- Sv m3 / Bq s)
A B
C=AxB KR-85 1.09E+01 1.19E-16 1.297E-15 KR-85M 1.59E+00 7.48E-15 1.189E-14 KR-87 1.03E+00 4.12E-14 4.244E-14 KR-88 2.89E+00 1.02E-13 2.948E-13 XE-131M 2.05E+00 3.89E-16 7.975E-16 XE-133 2.60E+02 1.56E-15 4.056E-13 XE-133M 3.65E+00 1.37E-15 5.001E-15 XE-135 8.24E+00 1.19E-14 9.806E-14 XE-135M 5.02E-01 2.04E-14 1.024E-14 Xe-138 6.09E-0I 5.77E-14 3.514E-14 Total ( Ci/gm
- Sv, Bq s m3) 9.052E-13 Xe-133 DE Based on 1% FF NG Concentration 580 A From Reference 9.9, Table 2-2 for HB x 1.04, based on 1683 MWt per Reference 9.9, Table 6-1 (Kr-83M omitted per definition of Dose Equivalent Xe-133)
B From FGR 12, Table 111.1 Table 6 Total RCS Noble Gas Activity 1% Fuel Defect Reactor Total RCS Noble Gas Coolant Pre-Accident Isotope Activity Mass RCS Noble Gas Concentration Activity (XtCi/gm)
(gm)
(Ci)
A B
C = (A x B)/1E6 KR-83M 3.92E-01 1.497E+08 5.868E+01 KR-85 1.09E+01 1.497E+08 1.632E+03 KR-85M 1.59E+00 1.497E+08 2.380E+02 KR-87 1.03E+00 1.497E+08 1.542E+02 KR-88 2.89E+00 1.497E+08 4.326E+02 XE-131M 2.05E+00 1.497E+08 3.069E+02 XE-133 2.60E+02 1.497E+08 3.892E+04 XE-133M 3.65E+00 1.497E+08 5.464E+02 XE-135 8.24E+00 1.497E+08 1.234E+03 XE-135M 5.02E-01 1.497E+08 7.515E+01 Xe-138 6.09E-01 1.497E+08 9.117E+01 (A) From Reference 9.9, Table 2-2 for HB x Table 6-1 (B) Reactor coolant mass from Section 7. 1.1 1.04, based on 1683 MWt per Reference 9.9,
Xcel, EnQ I rY.. Calculation No. GEN-PI-082 Revision No. 0 Page No. 45 of 145 Table 7 Total REA Iodine Activity Initially Present in the Secondary Coolant 0.50 pCi/gm Tech Spec Coolant Mass Total RADTRAD DE 1-131 Secondary In Both Intact Pre-Accident Nuclide Isotope Iodine Specific Steam Secondary Coolant Inventory File Concentration Activity Limit Generators Iodine Activity pirea-liqdef.txt (AtCi/gm)
(unitless)
(gin)
(tCi)
(Ci/MW,)
A B
C D=(AxBxC)/0.50 E =D/(1683 x 1E6) 1-131 3.891E-01 0.10 9.731E+07 7.573E+06
.4500E-02 1-132 4.272E-01 0.10 9.731E+07 8.315E+06
.4940E-02 1-133 5.920E-01 0.10 9.731E+07 1.152E+07
.6846E-02 1-134 8.880E-02 0.10 9.731E+07 1.728E+06
.1027E-02 1-135 3.357E-01 0.10 9.731E+07 6.533E+06
.3882E-02 A, E From Table 3, based on 1683 MWt per Reference 9.9, Table 6-1 B From Reference 9.6.9 C From Section 7.1.2
4, ceIEnergy Calculation No. GEN-PI-082 Revision No. 0 Page No. 46 of 145 Table 8 Post-REA Iodine & Noble Gas Activity Instantaneously Released from RCS Liquid To Containment Design Basis CREA CREA Initial Total RADTRAD Core Activity Activity Activity Activity Core Nuclide Isotope Inventory From From From Released Thermal Inventory 10%
0.25%
Primary To Power File Failed Fuel Melted Fuel Coolant Containment Level pireacntdef.txt (Ci)
(Ci)
(Ci)
(Ci)
(Ci)
(MWI)
(Ci/MWt)
A B
C D
E=B+C+D F
G=E/F KR-83M 0.00E+00 0.000E+00 0.OOOE+00 5.868E+01 5.868E+01 1683
.3487E-01 KR-85 7.15E+05 7.150E+03 1.788E+03 1.632E+03 1.057E+04 1683
.6280E+01 KR-85M 1.08E+07 1.080E+05 2.700E+04 2.380E+02 1.352E+05 1683
.8036E+02 KR-87 2.12E+07 2.120E+05 5.300E+04 1.542E+02 2.652E+05 1683
.1575E+03 KR-88 2.82E+07 2.820E+05 7.050E+04 4.326E+02 3.529E+05 1683
.2097E+03 1-131 4.50E+07 4.500E+05 2.813E+04 3.817E+02 4.785E+05 1683
.2843E+03 1-132 6.51E+07 6.510E+05 4.069E+04 4.192E+02 6.921E+05 1683
.4112E+03 1-133 9.13E+07 9.130E+05 5.706E+04 5.808E+02 9.706E+05 1683
.5767E+03 1-134 1.02E+08 1.020E+06 6.375E+04 8.713E+01 1.084E+06 1683
.6440E+03 1-135 8.72E+07 8.720E+05 5.450E+04 3.293E+02 9.268E+05 1683
.5507E+03 XE-131M 5.06E+05 5.060E+03 1.265E+03 3.069E+02 6.632E+03 1683
.3941E+01 XE-133 9.15E+07 9.150E+05 2.288E+05 3.892E+04 1.183E+06 1683
.7027E+03 XE-133M 2.86E+06 2.860E+04 7.150E+03 5.464E+02 3.630E+04 1683
.2157E+02 XE-135 2.07E+07 2.070E+05 5.175E+04 1.234E+03 2.600E+05 1683
.1545E+03 XE-135M 1.95E+07 1.950E+05 4.875E+04 7.515E+01 2.438E+05 1683
.1449E+03 XE-138 7.72E+07 7.720E+05 1.930E+05 9.117E+01 9.651E+05 1683
.5734E+03 A, F From Reference 9.4, Table 2-1, based on 1683 MWt per Reference 9.9, Table 6-1 B = (A x 0.10 x 0.10) = 0.01A for iodine [10% iodine release from 10% clad damage]
= (A x 0.10 x 0.10) = 0.01A for noble gas [ 10% noble gas release from 10% clad damage]
C = (A x 0.25 x 0.0025) = 0.000625A for iodine [25% iodine release from 0.25% melted fuel]
= (A x 1.00 x 0.0025) = 0.0025A for noble gas [100% noble gas release from 0.25% melted fuel]
D - Iodine From Table 4 & Noble Gas From Table 6
XceI Energy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 47 of 145 Table 9 Post-REA Iodine & Noble Gas Activity In the RCS and Available for Primary-to-Secondary System Leakage Design Basis CREA CREA Initial Total RADTRAD Core Activity Activity Activity Activity Core Nuclide Isotope Inventory From From From Released Thermal Inventory 10%
0.25%
Primary Into Power File Failed Fuel Melted Fuel Coolant RCS Level pirearcs-def.txt (Ci)
(Ci)
(Ci)
(Ci)
(Ci)
(MW)
(Ci/MW)
A B
C D
E=B+C+D F
G=E/F KR-83M 0.00E+00 0.000E+00 0.000E+00 5.868E+01 5.868E+01 1683
.3487E-01 KR-85 7.15E+05 7.150E+03 1.788E+03 1.632E+03 1.057E+04 1683
.6280E+01 KR-85M 1.08E+07 1.080E+05 2.700E+04 2.380E+02 1.352E+05 1683
.8036E+02 KR-87 2.12E+07 2.120E+05 5.300E+04 1.542E+02 2.652E+05 1683
.1575E+03 KR-88 2.82E+07 2.820E+05 7.050E+04 4.326E+02 3.529E+05 1683
.2097E+03 1-131 4.50E+07 4.500E+05 5.625E+04 3.817E+02 5.066E+05 1683
.3010E+03 1-132 6.51E+07 6.510E+05 8.138E+04 4.192E+02 7.328E+05 1683
.4354E+03 1-133 9.13E+07 9.130E+05 1.141E+05 5.808E+02 1.028E+06 1683
.6106E+03 1-134 1.02E+08 1.020E+06 1.275E+05 8.713E+01 1.148E+06 1683
.6819E+03 1-135 8.72E+07 8.720E+05 1.090E+05 3.293E+02 9.813E+05 1683
.5831E+03 XE-131M 5.06E+05 5.060E+03 1.265E+03 3.069E+02 6.632E+03 1683
.3941E+01 XE-133 9.15E+07 9.150E+05 2.288E+05 3.892E+04 1.183E+06 1683
,7027E+03 XE-133M 2.86E+06 2.860E+04 7.150E+03 5.464E+02 3.630E+04 1683
.2157E+02 XE-135 2.07E+07 2.070E+05 5.175E+04 1.234E+03 2.600E+05 1683
.1545E+03 XE-135M 1.95E+07 1.950E+05 4.875E+04 7.515E+01 2.438E+05 1683
.1449E+03 XE-138 7.72E+07 7.720E+05 1.930E+05 9.117E+01 9.651E+05 1683
.5734E+03 A, F From Reference 9.4, Table 2-1, based on 1683 MWt per Reference 9.9, Table 6-1 B = (A x 0.10 x 0.10) = 0.01A for iodine [10% iodine release from 10% clad damage]
= (A x 0. 10 x 0.10) = 0.01A for noble gas [ 10% noble gas release from 10% clad damage]
C = (A x 0.50 x 0.0025) = 0.00 125A for iodine [50% iodine release from 0.25% melted fuel]
= (A x 1.00 x 0.0025) = 0.0025A for noble gas [100% noble gas release from 0.25% melted fuel]
D - Iodine From Table 4 & Noble Gas From Table 6
XceiEnergyý Calculation No. GEN-PI-082 Revision No. 0 Page No.48 of 145 Table 10 Post-MSLB Intact SG Release P-T-S Intact SG Release Release Leakage To Iodine, Noble gas, & SG Liquid Iodine Release Intact SG Category (cfm)
(cfm)
(cfm)
(cfm)
(cfm)
A B
C D
E Iodine 0.0376 0.3942 0.2361 0.1734 0.1398 Release 0-45.5 hr 0-2 hr 2-8 hr 8-24 hr 24-45.5 Noble Gas 0.0376 0.181 Release 0-45.5 hr 0-45.5 hr SG Liquid 0.3942 0.2361 0.1734 0.1398 Iodine N/A I
Releae 0-2 hr 2-8 hr 8-24 hr 24-45.5 Release Pelint Unit 2 Groups 1 & 2 PORV Release Points Point A For Iodine Release From Section 7.2.1 A For Noble Gas Release From Section 7.2.1 B Through E For Iodine & Noble Gas Releases From 7.2.2 B Through E For SG Liquid Iodine Release From 7.3.3
...Xce Energy]Calculation No. GEN-PI-082 Revision No. 0 Page No.49 of 145 Table 11 Unit 2 CR Atmospheric Dispersion Factor (x/Q)
Intact Steam Release via Unit 2 PORVs Unit 2 Group I Group 2 Effective Time PORV PORV PORV Interval x/Qs Y/Qs X/Qs (hr)
(s/m 3)
(s/mi3)
(s/m 3)
A B
D= 0.6A + 0.4B 0-2 3.07E-02 2.20E-03 1.93E-02 2-8 2.49E-02 1.81E-03 1.57E-02 8-24
- 1. 12E-02 7.97E-04 7.04E-03 24-96 7.78E-03 5.16E-04 4.87E-03 96-720 6.17E-03 4.00E-04 3.86E-03 A & B rom Reference 9.5, Table 8-5
A M X eEnergy~ Calculation No. GEN-PI-082 Revision No. 0 Page No. 50 of 145 Table 12 Alkali Inhaled Isotopic Dose Conversion Factors Isotopic Conversion Iodine Fractional Dose Factor Dose Iodine Isotope Conversion Conversion Dose Factor Factor Conversion Factor (Sv/Bq)
(rem/Ci/Sv/Bq)
(rem/Ci)
A B
C=AxB D=C/1.08E+06 1-131 2.92E-07 3.70E+12 1.08E+06 1.OOE+00 Rb-86 1.33E-09 3.70E+12 4.92E+03 4.56E-03 Rb-88 1.37E-12 3.70E+12 5.07E+00 4.69E-06 Rb-89 1.61E-12 3.70E+12 5.96E+00 5.52E-06 Cs-134 1.11E-08 3.70E+ 12 4.11E+04 3.80E-02 Cs-136 1.731E-09 3.70E+ 12 6.40E+03 5.93E-03 Cs-137 7.931E-09 3.70E+ 12 2.93E+04 2.72E-02 Cs-138 3.57E-12 3.70E+ 12 1.32E+01 1.22E-05 A From Reference 9.7, Table 2.1
XceIEnergy*
Calculation No. GEN-PI-082 Revision No. 0 Page No.51 of 145 11.0 FIGURES:
0.15 V%/day < 12 min 0.066 V%/day = 12 -20 min 0.006 V%/day = 20 min - 24 hr 0.003 V%/day > 24 hrs T
Wz Figure 1: Post-REA Containment Leakage AST RADTRAD Nodalization
Xc Energy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 52 of 145 Noble Gas Release 0.0376 cfm 0 - 45.5 hrs Figure 2: RADTRAD Nodalization For Post-REA Iodine & Noble Gas Releases P-T-S Leakage and Intact SG Secondary Liquid Iodine Release P-T-S Leakage Noble Gas Release
XceIEnergy]Calculation No. GEN-PI-082 Revision No. 0 f 145 L8 2,000 cfm < 5 min 1
200 or 300 cfm > 5 min CR Unfiltered Inleakage 2,000 cfm < 5 min 200 or 300 cfm > 5 min CONTROL ROOM V = 61,315 ft3 HEPA rI = 99%
Charcoal rI = 95%
Recirc Charcoal Filter 300cfm
>5 min Figure 3 - PINGP Control Room Response AST RADTRAD Nodalization
XceI Energy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 54 of 145 12.0 AFFECTED DOCUMENTS:
Upon approval of the AST Licensing Change Request, the following document will be revised or superseded:
12.1 PINGP USAR Section 14.5.6, Rev 29P, Rupture of a Control Rod Drive Mechanism Housing (RCCA Ejection) 13.0 ATTACHMENTS: 3.1 PIREACLOO.oO 3.2 PREAINID01.oO 3.3 PREAINGO1.oO 3.4 PREAINLQOI.oO Containment Leakage P-T-S Iodine Release ISG P-T-S NG Release ISG Liquid Iodine Release ISG
V XceIEnergl Calculation No. GEN-PI-082 Revision No. 0 Page No.55 of 145 3.1 RADTRAD Output File PIREACLOO.o0 RADTRAD Version 3.03 (Spring 2001) run on 6/23/2009 at 8:57:05
- ý#################################################
ý###ý#########################4#f########################################
File information
- ý#fý#################################################################
Plant file
= G:\\Radtrad 3.03\\Input\\PI\\GEN-PI-082\\PIREACL0O.psf Inventory file
= g:\\radtrad 3.03\\defaults\\pireacnt def.txt Release file
= g:\\radtrad 3.03\\defaults\\pirearft.txt Dose Conversion file = g:\\radtrad 3.03\\defaults\\pingp fgll&12.txt i####
- M##
Radtrad 3.03 4/15/2001 Prairie Island Rod Ejection Accident AST Analysis -
No SB Vent & Recirc Charcoal Filtration Credit, Containment Leakage = 0.15 w%/day, SB Vent Stack Release, CRSVS Charcoal Fitration Starts @ 5 minutes, and CR Unfiltered Inleakage =250 cfm Nuclide Inventory File:
g:\\radtrad 3.03\\defaultskpireacnt-def.txt Plant Power Level:
1.8520E+03 Compartments:
5 Compartment 1:
Containment (Cl) 3 1.3200E+06 0
0 0
0 0
Compartment 2:
Shield Bldg (C2) 3 3.7400E+05 0
0 1
0 0
Compartment 3:
Environment (C3) 2
e
-XceIEnerg Calculation No. GEN-PI-082 Revision No. 0 Page No.56 of 145 O.OOOOE+00 0
0 0
0 0
Compartment 4:
Control Room (C4) 1 6.1315E+04 0
0 1
0 0
Compartment 5:
ABSVZ (C5) 3
- 1. O000E+00 0
0 0
0 0
Pathways:
8 Pathway 1:
L3 -
Containment 1
3 4
Pathway 2:
Li -
Containment 1
2 4
Pathway 3:
Leakage To Environment Leakage To Shield Bldg L2 -
Containment Leakage To ABSVZ 1
5 4/
Pathway 4:
L4 - Shield Bldg Exhaust To Environment 2
3 2
Pathway 5:
L6 -
Environment To Control Room 3
4 2
Pathway 6:
L7 -
Control Room Exhaust To Environment 4
3 2
Pathway 7:
L5 -
ABSVZ Exhaust To Environment 5
3
X...#.E:.
- Calculation No. GEN-PI-082 Revision No. 0 Page No. 57 of 145 2
Pathway 8:
Containment to Environment 1
3 2
End of Plant Model File Scenario Description Name:
Plant Model Filename:
Source Term:
for SB Release 12 min -
22 min 1
1 1.OOOOE+00 g:\\radtrad 3.03\\defaults\\pingp fgll&12.txt g:\\radtrad 3.03\\defaults\\pirea-rft.txt 0.OOOOE+00 1
9.5000E-01 4.8500E-02 Overlying Pool:
0 o.O0OOE+00 0
0 0
0 Compartments:
5 Compartment 1:
0 1
0 0
0 0
0 0
0 Compartment 2:
0 1
0 0
0 0
1 3.6000E+03 3
1.5000E-03 1.0000E+00 o.0000E+00 3.6670E-01 7.2000E+02 0
0 Compartment 3:
0 1
0 0
0 0
C.0000E+00
- 9. 9000E+01 0.0000E+00 C.0000E+00 C.0000E+00 0.0O00E+00 C.0000E+00 C.0000E+00 0.0000E+00
alculation No. GEN-PI-082 Revision No. 0 Page No.58 of 145 0
0 0
Compartment 4:
1 3.6000E+03 3
o.0000E+00 8.3300E-02 7.2000E+02 0
0 Compartment 5:
0 1
0 0
0 0
0 0
0 Pathways:
8 Pathway 1:
0 0
0 0
0 0
0 0
0 0
1 5
o.OOOOE+00 2.0000E-01 3.3300E-01
- 2. 4000E+01 7.2000E+02 0
Pathway 2:
0 0
0 0
0 0
0 0
0 0
0.OOOOE+00
- 9. 9000E+01 0.OOOOE+00 o.OOOOE+00
- 9. 5000E+01 o.0000E+00 o.OOOOE+00
- 9. 5000E+01 0.0000E+00
- 1. 50OOE-01 6.60OOE-02 6.0000E-03 3.OOOOE-03 0.OOOOE+00
i XCelEnergyl Calculation No. GEN-PI-082 Revision No. 0 Page No. 59 of 145 1
4 o.OOOOE+00
- 3. 6700E-01 2.4000E+01 7.2000E+02 0
Pathway 3:
0 0
0 0
0 0
0 0
0 0
1 4
o.0000E+00 3.3300E-01 2.4000E+01 7.2000E+02 0
Pathway 4:
0 0
0 0
0 1
3 0.0000E+00
- 3. 6700E-01 7.2000E+02 0
0 0
0 0
0 Pathway 5:
0 0
0 0
0 1
3 o.OOOOE+00 8.3300E-02 7.2000E+02 0
0 0
0 0
0 Pathway 6:
0.OOOOE+00 8.4000E-02 4.2000E-02 0.OOOOE+00 0.OOOOE+00 6.OOOOE-02 3.OOOOE-02 o.OOOOE+00 0.OOOOE+00 2.OOOOE+03 0.OOOOE+00 2.OOOOE+03 2.5000E+02 0.OOOOE+00 0.0000E+00
- 9. 9000E+01 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 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
[ ~XceIEnery Calculation No. GEN-PI-082 Revision No. 0 Page No. 60 of 145 0
0 0
3 8.3300E-02
- 7. 2000E+02 0
0 0
0 0
0 Pathway 7:
0 0
0 0
0 1
3 o
. CCCE+CC
- 3. 3300E-C1 7.2000E+02 0
0 0
0 0
0 Pathway 8:
0 0
0 0
0 1
3 o
. CCCE+CC
- 2. COCCOE-01
- 3. G700E-C1 0
0 0
0 0
2.0000E+03 2.5000E+02 0.0000E+00 o.0000E+00 o.0000E+00 o.0000E+00 0.0000E+00 0.0000E+00 o.0000E+00 o.0000E+00 o.0000E+00 o.0000E+00 C.0000E+00 1.0000E+03 o.0000E+00 0.0000E+00 7.7000E-01 o.0000E+00 o.0000E+00
- 9. 9000E+01 o.0000E+00 o.0000E+00 o.0000E+00 o.0000E+00 o.0000E+00 8. 0000E+01 o.0000E+00 0.0000g+00 C. 0C0E+00 o.0000E+00 o.0000E+00
- 8. 0000E+01 o.0000E+00 C.0000E+00 o.0000E+00 C.0000E+00 0
Dose Locations:
3 Location 1:
Exclusion Area Boundary 3
1 2
7.0000C+00 7.2000E+02 6.49OOE-04 O.OOOOE+00
2 XceEne Calculation No. GEN-PI-082 Revision No. 0 Page No.61 of 145 2
o.OOOE+00 7.2000E+02 0
3.5000E-04 0.0000E+00 Location 2:
Low Population Zone 3
1 5
o.0000E+00 8.0000E+00 2.4000E+01
- 9. 6000E+01 7.2000E+02 1
4 o.0000E+00 8.0000E+00 2.4000E+01 7.2000E+02 0
Location 3:
Control Room 4
0 1
2 o.OOOOE+00 7.2000E+02 1
1.7700E-04 3.9900E-05 7.1200E-06 1.0400E-06 0.0000E+00 3.5000E-04 1.8000E-04 2.3000E-04 0.0000E+00 3.5000E-04 0.0000E+00 4
0.0000E+00 1.0000E+00 2.4000E+01 6.0000E-01 9.6000E+01 4.OOOOE-01 7.2000E+02 0.0000E+00 Effective Volume Location:
1 6
0.OOOOE+00 4.5300E-03 2.0000E+00 3.9300E-03 8.0000E+00 1.7300E-03 2.4000E+01 1.2200E-03 9.6000E+01 9.1600E-04 7.2000E+02 0.OOOOE+00 Simulation Parameters:
6 0.0000E+00 1.0000E-01 2.0000E+00 5.OOOOE-01 8.0000E+00 1.0000+/-+00 2.4000E+01 2.OOOOE+00 9.6000E+01 5.0000E+00 7.2000E+02 0.0000E+00 Output Filename:
G:\\Radtrad 3.o22 1
1 1
0 0
End of Scenario File
XceI Enrgy Calculation No. GEN-PI-082 Revision No. 0 Page No. 62 of 145
- f####################*##4#############################
RAUTRAD Version 3.03 (Spring 2001) run on 6/23/2009 at 8:57:05
- 4###########
Plant Description Number of Nuclides =
60 Inventory Power =
1.0000E+00 MWth Plant Power Level =
1.8520E+03 MWth Number of compartments
=
5 Compartment information Compartment number 1
(Source term fraction =
1.0000E+00 Name: Containment (Cl)
Compartment volume =
1.3200E+06 (Cubic feet)
Compartment type is Normal Pathways into and out of compartment 1
Exit Pathway Number 1: L3 - Containment Leakage To Environment Exit Pathway Number 2: Ll - Containment Leakage To Shield Bldg Exit Pathway Number 3: L2 -
Containment Leakage To ABSVZ Exit Pathway Number 8: Containment to Environment for SB Release Compartment number 2
Name: Shield Bldg (C2)
Compartment volume =
3.7400E+05 (Cubic feet)
Compartment type is Normal Removal devices within compartment:
Filter(s)
Pathways into and out of compartment 2
Inlet Pathway Number 2: Ll - Containment Leakage To Shield Bldg Exit Pathway Number 4: L4 - Shield Bldg Exhaust To Environment Compartment number 3
Name: Environment (C3)
Compartment type is Environment Pathways into and out of compartment 3
Inlet Pathway Number 1: L3 - Containment Leakage To Environment Inlet Pathway Number 4: L4 - Shield Bldg Exhaust To Environment Inlet Pathway Number 6: L7 -
Control Room Exhaust To Environment Inlet Pathway Number 7: L5 -
ABSVZ Exhaust To Environment Inlet Pathway Number 8: Containment to Environment for SB Release Exit Pathway Number 5: L6 -
Environment To Control Room Compartment number 4
Name: Control Room (C4)
Compartment volume =
6.1315E+04 (Cubic feet)
Compartment type is Control Room Removal devices within compartment:
Filter(s)
Pathways into and out of compartment 4
Inlet Pathway Number 5: L6 -
Environment To Control Room Exit Pathway Number 6: L7 -
Control Room Exhaust To Environment 12 m 12 m
XceIEnergy. Calculation No. GEN-PI-082 Revision No. 0 Page No.63 of 145 Compartment number 5
Name: ABSVZ (C5)
Compartment volume =
1.OOOE+00 (Cubic feet)
Compartment type is Normal Pathways into and out of compartment 5
Inlet Pathway Number 3: L2 -
Containment Leakage To ABSVZ Exit Pathway Number 7: L5 -
ABSVZ Exhaust To Environment Total number of pathways =
8
Xcei l"noerg Calculation No. GEN-PI-082 Revision No. 0 Page No. 64 of 145 RADTRAD Version 3.03 (Spring 2001) run on 6/23/2009 at 8:57:05
- ý##################O########
Scenario Description
- 4#######################
Radioactive Decay is enabled Calculation of Daughters is enabled Release Fractions and Timings GAP 0.003600 hr NOBLES 1.0000E+00 IODINE 1.0000E+00 CESIUM 0.OOOOE+00 TELLURIUM 0.OOOOE+00 STRONTIUM 0.OOOOE+00 BARIUM 0.OOOOE+00 RUTHENIUM 0.OOOOE+00 CERIUM 0.0000E+00 LANTHANUM 0.OOOOE+00 EARLY IN-VESSEL 0.0000 hrs 0.0000E+00 0.OOOOE+00 0.0000E+00 0.0000E+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.0000E+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 OOOOE+00 0 OOOOE+00 RELEASE MASS (gm)
- 3. 696E+01
- 5. 599E+00
- 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-83m 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 Xe-135m Xe-138 Group Specific Inventory (Ci/MWt) 1 3.487E-02 1
6.280E+00 1
8.036E+01 1
1.575E+02 1
2.097E+02 2
2.843E+02 2
4.112E+02 2
5.767E+02 2
6.440E+02 2
5.507E+02 1
3.941E+00 1
7.027E+02 1
2.157E+01 1
1.545E+02 1
1.499E+02 1
5.734E+02 Daughter Fra Kr-85 0.
Rb-87 1
Rb-88 1
Xe-131m 0.
Xe-133m 0.
Xe-135m 0.
Xe-133 1
Cs-135 1
Xe-135 1
Cs-138 1
half life (s)
- 6. 588E+03
- 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) 1.500E-18 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
- 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 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 o OOOE+00
- 0. OOOE+00 ction Daughter Fraction Daughter Fraction 21 00 00 01 03 15 00 00 00 00 none none none none Xe-133 Xe-135 none none none none 0.00 0.00 0.00 0.00 0.97 0.85 0.00 0.00 0.00 0.00 none none none none none none none none none none 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Iodine fractions
" Xcei Energy Calculation No. GEN-PI-082 Revision No. 0 Page No.65 of 145 Aerosol Elemental Organic COMPARTMENT DATA
= 9. 5000E-01
=
4.8500E-02
=
.5000E-03 Compartment number 1: Containment (Cl)
Compartment number 2: Shield Bldg (C2)
Compartment Filter Data Time (hr) 0.OOOOE+00
- 3. 6670E-01 7.2000E+02 Flow Rate (cfm) 3.6000E+03 3.6000E+03 3.6000E+03 Filter Aerosol 0.0000E+00
- 9. 9000E+01 0.0000E+00 Efficiencies Elemental 0.0000E+00 o.0000E+00 o.0000E+00
(%)
Organic 0.0000E+00 0.0000E+00 0.0000E+00 Compartment number 3: Environment (C3)
Compartment number 4: Control Room (C4)
Compartment Filter Data Time (hr) 0.0000E+00 8.3300E-02 7.2000E+02 Flow Rate (cfm) 3.6000E+03 3.6000E+03 3.6000E+03 Filter Efficiencies Aerosol Elemental 0.0000E+00 0.0000E+00 9.9000E+01 9.5000E+01 0.0000E+00 0.0000E+00
(%)
Organic o.0000E+00
- 9. 5000E+01 0.0000E+00 Compartment number 5: ABSVZ (C5)
PATHWAY DATA Pathway number 1: L3 -
Containment Leakage To Environment Convection Data Time (hr) 0.0000E+00
- 2. 0000E-01
- 3. 3300E-01 2.4000E+01 7.2000E+02 Pathway number 2: Ll Convection Data Time (hr) o.0000E+00
- 3. 6700E-01 2.4000E+01 7.2000E+02 Pathway number 3: L2 Convection Data Time (hr) o.0000E+00 3.3300E-01 2.4000E+01 Flow Rate (% / day) 1.50OOE-01 6.6000E-02 6.0000E-03 3.0000E-03 o.0000E+00 Containment Leakage To Shield Bldg Flow Rate (% / day) 0.0000E+00 8.4000E-02 4.2000E-02 0.0000E+00 Containment Leakage To ABSVZ Flow Rate
(% / day) 0.OOOOE+00 6.OOOOE-02 3.000OE-02
XbeIEnerg Calculation No. GEN-PI-082 Revision No. 0 Page No. 66 of 145 7.2000E+02 0.OOOOE+00 Pathway number 4: L4 -
Shield Bldg Exhaust To Environment Pathway Filter:
Removal Data Time (hr) 0.0000E+00
- 3. 6700E-01 7.2000E+02 Flow, Rate (cfm) 0.0000E+00 2.OOOOE+03 0.OOOOE+00 Filter Efficiencies
(%)
Aerosol Elemental Organic 0.0000E+00 0.0000E+00 0.0000E+00 9.9000E+01 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Pathway number 5: L6 -
Environment To Control Room Pathway Filter:
Removal Data Time (hr) 0.0000E+00 8.3300E-02 7.2000E+02 Flow Rate (cfm) 2.0000E+03 2.5000E+02 0.0000E+00 Filter Efficiencies
(%)
Aerosol Elemental Organic 0.0000E+00 0.0000E+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.0000E+00 0.OOOOE+00 Pathway number 6: L7 -
Control Room Exhaust To Environment Pathway Filter:
Removal Data Time (hr) 0.OOOOE+00 8.3300E-02 7.2000E+02 Flow Rate (cfm) 2.OOOOE+03 2.5000E+02 O.OOOOE+00 Filter Efficiencies
(%)
Aerosol Elemental Organic 0.0000E+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 Pathway number 7: L5 -
ABSVZ Exhaust To Environment Pathway Filter:
Removal Data Time (hr) 0.OOOOE+00
- 3. 3300E-01 7.2000E+02 Flow Rate (cfm) 0.OOOOE+00 1.OOOOE+03 0.OOOOE+00 Filter Efficiencies
(%)
Aerosol Elemental Organic 0.0000E+00 0.0000E+00 0.0000E+00 9.9000E+01 8.0000E+01 " 8.0000E+01 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 8: Containment to Environment for SB Release 12 m Pathway Filter:
Removal Data Time (hr) o.OOOOE+00
- 2. OOOOE-01
- 3. 6700E-01 Flow Rate (c fm) 0.OOOOE+00 7.7000E-01 0.0000E+00 Filter Efficiencies
(%)
Aerosol Elemental Organic 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 LOCATION DATA Location Exclusion Area Boundary is in compartment 3
Location X/Q Data Time (hr) 0.0000E+00 7.2000E+02 X/Q (s
- m^-3) 6.4900E-04 0.OOOOE+00
XcIEne rgy' Calculation No. GEN-PI-082 Revision No. 0 Page No. 67 of 145 Location Breathing Time (hr) 0.OOOOE+00 7.2000E+02 Location Low PopulP Rate Data Breathing Rate (m^3
- sec^-l) 3.5000E-04 0.0000E+00 tion Zone is in compartment 3
a Location X/Q Data Time (hr) 0.0000E+00 8.0000E+00 2.4000E+01
- 9. 6000E+01 7.2000E+02 X/Q (s
- m^-3) 1.7700E-04 3.9900E-05 7.1200E-06 1.0400E-06 0.0000E+00 Location Breathing Rate Da Time (hr)
Breathi 0.0000E+00 8.0000E+00 2.4000E+01 7.2000E+02 Location Control Room
.ng Rate (m^3
- sec^-l) 3.5000E-04 1.8000E-04 2.3000E-04 0.OOOOE+00 is in compartment 4
Location X/Q Data Time (hr)
- 0. 0000E+00
- 2. 0000E+00
- 8. 0000E+00 2 4000E+01
- 9. 6000E+01 7.2000E+02 Location Breathing Time (hr) o.0000E+00 7.2000E+02 Location Occupancy Time (hr) o.0000E+00 2.4000E+01
- 9. 6000E+01 7.2000E+02 X/Q (s
- m^-3) 4.5300E-03 3.9300E-03 1.7300E-03 1.2200E-03
- 9. 1600E-04 0.OOOOE+00 Rate Data Breathing Rate (m^3
- sec^-l) 3.5000E-04 0.0000E+00 Factor Data Occupancy Factor 1.0000E+00
- 6. 0OOOE-01
- 4. 0000E-01 0.OOOOE+00 USER SPECIFIED TIME STEP DATA -
SUPPLEMENTAL TIME STEPS Time Time step 0.0000E+00 1.0000E-01 2.0000E+00 5.0000E-01 8.OOOOE+00 1.0000E+00 2.4000E+01 2.0000E+00 9.6000E+01 5.0000E+00 7.2000E+02 0.0000E+00
t60 ;XceIEneargylCalculation No. GEN-PL-082 Revision No. 0 Page No. 68 of 145 RADTRAD Version 3.03 (Spring 2001) run on 6/23/2009 at 8:57:05
- f################################f#####################
- t it it it it it it it it it### i it
- 1 1
- t t
it it it it Dose, Detailed model and Detailed Inventory Output
- E##########################################
Exclusion Area Boundary Doses:
Time (h)
=
0.0036 Delta dose (rem)
Accumulated dose (rem)
Whole Body 1.3258E-04 1.3258E-04 Low Population Zone Doses:
Time (h)
=
0.0036 Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Time (h)
=
0.0036 Delta dose (rem)
Accumulated dose (rem)
Whole Body
- 3. 6160E-05
- 3. 6160E-05 Whole Body
- 8. 9715E-08
- 8. 9715E-08 Thyroid
- 2. 0418E-02
- 2. 0418E-02 Thyroid 5.5685E-03 5.5685E-03 Thyroid 3.9039E-04 3.9039E-04 TEDE
- 7. 7814E-04
Compartment Nuclide Inventory:
Time (h)
=
Kr-83m Kr-85 Kr-85m Kr-87 Kr-88 Rb-88 1-131 1-132 1-133 1-134 1-135 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 Cs-138 0.0036 Ci 3.0950E-08 5.5816E-06
- 7. 1383E-05 1.3971E-04 1.8621E-04 1.2770E-06 2.5268E-04 3.6507E-04 5.1250E-04 5.7075E-04 4.8927E-04 3.5027E-06 6.2455E-04 1.9171E-05 1.3743E-04 1.3265E-04 5.0427E-04 1.9202E-06 kg 1.5001E-18 1.4227E-11
- 8. 6740E-15
- 4. 9322E-15
- 1. 4851E-14
- 1. 0638E-17
- 2. 0381E-12
- 3. 5368E-14
- 4. 5241E-13 2 1395E-14
- 1. 3932E-13
- 4. 1818E-14
- 3. 3366E-12
- 4. 2725E-14
- 5. 3815E-14
- 1. 4562E-15
- 5. 2443E-15
- 4. 5380E-17 Atoms
- 1. 0884E+07
- 1. 0079E+14
- 6. 1454E+10
- 3. 4141E+10
- 1. 0163E+ll
- 7. 2801E+07
- 9. 3694E+12
- 1. 6136E+ll
- 2. 0485E+12
- 9. 6152E+10
- 6. 2148E+ll 1.9224E+ll 1.5108E+13
- 1. 9345E+ll 2.4006E+ll 6.4958E+09 2.2886E+10 1.9803E+08 Decay 1.0539E+04 1.8997E+06 2.4300E+07 4.7583E+07 6.3397E+07 6.5716E+04 8.5998E+07 1.2430E+08 1.7444E+08 1.9445E+08 1.6654E+08 1.1921E+06 2.1256E+08 6.5247E+06 4.6743E+07
- 4. 5134E+07 1.7228E+08
- 9. 9312E+04 Control Room (C4)
Transport Group Inventory:
XceIEnergytCalculation No. GEN-PL-082 Revision No. 0 Page No.69 of 145 Time (h) =
0.0036 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Time (h)
=
0.0036 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Atmosphere Sump 1.1675E+14 0.OOOOE+00 5.9640E+II 0.0000E+00 1.8445E+10 0.0000E+00 2.5524E-12 0.0000E+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid)
- 2. 0440E-13
- 2. 6107E-13 2.1903E-03 Deposition Surfaces 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Recirculating Filter 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 L6 -
Environment To Control Room Transport Group Inventory:
Time (h) =
0.0036 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 0.0000E+00 0.0000E+00 0.OOOOE+00 0.0000E+00 Transported 1.1703E+14 5.9784E+lI 1.8490E+10
- 2. 5585E-12 L7 -
Control Room Exhaust To Environment Transport Group Inventory:
Time (h)
=
0.0036 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered
- 2. 7432E+lI
- 1. 4014E+09 4.3342E+07
- 5. 9973E-15 Exclusion Area Boundary Doses:
Time (h)
=
0.0833 Delta dose (rem)
Accumulated dose (rem)
Whole Body
- 5. 8651E-03 5.9977E-03 Transported 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Thyroid
- 9. 0401E-01
- 9. 2443E-01 Thyroid 2.4655E-01
- 2. 5212E-01 Thyroid
- 4. 7623E-01
- 4. 7663E-01 Low Population Zone Doses:
Time (h) =
0.0833 Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Whole Body 1.5996E-03 1.6357E-03 TEDE 3.4447E-02 3.5226E-02 TEDE 9.3948E-03 9.6070E-03 TEDE
- 1. 5167E-02
- 1. 5179E-02 Time (h)
=
0.0833 Whole Body Delta dose (rem) 1.0935E-04 Accumulated dose (rem) 1.0944E-04 Control Room (C4)
Compartment Nuclide Inventory:
Time (h)
Kr-83m Kr-85 Kr-85m Kr-87 Kr-88 0.0833 Ci 1.2597E-06 2.3414E-04 2.9577E-03
- 5. 6115E-03
- 7. 6610E-03 kg
- 6. 1056E-17
- 5. 9679E-10
- 3. 5941E-13
- 1. 9811E-13
- 6. 1097E-13 Atoms 4.4299E+08
- 4. 2282E+15 2.5463E+12 1.3713E+12 4.1810E+12 Decay 1.3587E+07 2.4876E+09
- 3. 1618E+10
- 6. 0933E+10 8.2189E+10
XcelEnergylI Calculation No. GEN-PI-082 Revision No. 0 Page No. 70 of 145 Rb-88 1-131 1-132 1-133 1-134 1-135 Xe-13 1m Xe-133 Xe-13 3m Xe-135 Xe-135m Xe-138 Cs-138 1.4822E-03 1.0597E-02 1.4951E-02
- 2. 1442E-02 2.2480E-02 2.0354E-02 1.4693E-04
- 2. 6197E-02
- 8. 0401E-04 5.8661E-03 5.1446E-03 1.6742E-02 2.0097E-03
- 1. 2348E-14
- 8. 5474E-11
- 1. 4484E-12
- 1. 8928E-11 8 4269E-13
- 5. 7957E-12
- 1. 7541E-12
- 1. 3996E-10 1.7918E-12
- 2. 2971E-12
- 5. 6477E-14
- 1. 7411E-13
- 4. 7493E-14 Inventory:
Sump 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.0000E+00 roid)
P2 Thyroid) 8 4501E+10
- 3. 9293E+14
- 6. 6081E+12
- 8. 5705E+13
- 3. 7872E+12 2.5854E+13 8 0639E+12
- 6. 3371E+14 8.1133E+12 1.0247E+13
- 2. 5193E+II
- 7. 5979E+l1
- 2. 0725E+II 4.8610E+08
- 1. 1260E+11
- 1. 6077E+11 2.2810E+II 2.4653E+11
- 2. 1715E+II 1.5609E+09 2.7828E+11 8.5395E+09 6.1063E+10
- 5. 3153E+10 2.0041E+lI 7.6093E+08 Control Room (C4)
Transport Group Time (h)
=
0.0833 Atmosphere Noble gases (atoms) 4.8974E+15 Elemental I (atoms) 2.4972E+13 Organic I (atoms) 7.7232E+11 Aerosols (kg) 1.0692E-10 Dose Effective (Ci/cc) 1-131 (Thy]
Dose Effective (Ci/cc) 1-131 (ICR]
Total I (Ci) 8.5623E-12 1.0911E-11 8.9823E-02 Time (h)
=
0.0833 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Deposition Recirculating Surfaces Filter 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.OOOOE+00 0.0000E+00 0.0000E+00 0.0000E+00 L6 -
Environment To Control Room Transport Group Inventory:
Time (h)
=
0.0833 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Transported 5.2987E+15 2.7067E+13 8.3713E+11 1.1584E-10 L7 -
Control Room Exhaust To Environment Transport Group Inventory:
Time (h)
=
0.0833 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 4.0130E+14 2.0499E+12 6.3400E+10 8.7729E-12 Exclusion Area Boundary Doses:
Time (h) =
0.2000 Whole Body Delta dose (rem) 8.3254E-03 Accumulated dose (rem) 1.4323E-02 Transported 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Thyroid 1.3215E+00 2.2459E+00 Thyroid 3.6040E-01
- 6. 1252E-01 Low Population Zone Doses:
TEDE 5.0112E-02 8.5337E-02 TEDE 1.3667E-02 2.3274E-02 Time (h)
=
0.2000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 2.2706E-03 3.9063E-03
XceIEnerg Calculation No. GEN-PI-02 Revision No. 0 Page No. 71 of 145 Control Room Doses:
Time (h)
=
0.2000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 2.8530E-04 3.9474E-04 Thyroid 1.2233E+00 1.6999E+00 TEDE 3.8966E-02
- 5. 4145E-02 Control Room (C4)
Compartment Nuclide Inventory:
Time (h)
=
Kr-83m Kr-85 Kr-85m Kr-87 Kr-88 Rb-88 1-131 1-132 1-133 1-134 1-135 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 Cs-138 0.2000 Ci 1.4014E-06 2.7225E-04 3.3776E-03
- 6. 1227E-03
- 8. 6578E-03
- 3. 1541E-03 8.5213E-03
- 1. 1612E-02 1.7183E-02
- 1. 6491E-02
- 1. 6175E-02
- 1. 7082E-04
- 3. 0453E-02
- 9. 3424E-04
- 6. 9366E-03 5 1352E-03
- 1. 3821E-02 3.7253E-03 kg
- 6. 7923E-17
- 6. 9392E-10
- 4. 1043E-13
- 2. 1616E-13
- 6. 9046E-13
- 2. 6275E-14
- 6. 8734E-11 1.1250E-12 1.5168E-11
- 6. 1818E-13
- 4. 6058E-12 2. 0394E-12
- 1. 6269E-10 2.0821E-12 2.7163E-12
- 5. 6374E-14
- 1. 4373E-13
- 8. 8039E-14 Atoms 4.9282E+08 4.9164E+15
- 2. 9078E+12
- 1. 4 962E+12 4.7250E+12 1.7981E+11 3.1597E+14
- 5. 1324E+12 6.8681E+13 2.7782E+12
- 2. 0546E+13
- 9. 3752E+12
- 7. 3666E+14
- 9. 4275E+12 1.2117E+13
- 2. 5148E+11
- 6. 2724E+11 3.8419E+11 Decay
- 3. 5471E+07 6.6470E+09 8.3684E+10 1.5747E+11 2.1634E+11 2.0211E+10
- 2. 4890E+11
- 3. 4986E+11
- 5. 0345E+11 5.2312E+11
- 4. 7745E+11 4.1708E+09 7.4355E+11 2.2813E+10
- 1. 6523E+11 1.3306E+11
- 4. 5157E+ll
- 2. 8504E+10 Control Room (C4)
Transport Group Inventory:
Time (h)
=
0.2000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Time (h)
=
0.2000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Atmosphere Sump 5.6940E+15 0.OOOOE+00 2.0318E+13 0.OOOOE+00 6.2839E+ll 0.OOOOE+00 8.5789E-11 0.0000E+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid)
- 6. 8741E-12
- 8. 7314E-12 6.9982E-02 Deposition Surfaces 0.0000E+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 Recirculating Filter 0.0000E+00
- 8. 7869E+12 2.7176E+Il 3.8920E-11 L6 -
Environment To Control Room Transport Group Inventory:
Time (h)
=
0.2000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 Transported 6.2471E+15 3.1901E+13 9.8663E+ll
- 1. 3654E-10 L7 -
Control Room Exhaust To Environment Transport Group Inventory:
Time (h)
=
0.2000 Noble gases (atoms)
Pathway Filtered 5.5255E+14 Transported 0.0000E+00
XceI EnergY]1 Calculation No. GEN-PI-082 Revision No. 0 Page No. 72 of 145 Elemental I (atoms)
Organic I (atoms)
Aerosols (kg) 2.6922E+12 8.3265E+10 1.1503E-11 Exclusion Area Boundary Doses:
Time (h)
=
0.3330 Delta dose (rem)
Accumulated dose (rem)
Whole Body 9.0685E-03 2.3392E-02 Low Population Zone Doses:
0.0000E+00 0.OOOOE+00 0.OOOOE+00 Thyroid 1.5027E+00 3.7486E+00 Thyroid
- 4. 0982E-01 1.0223E+00 Thyroid
- 1. 1308E+00 2.8307E+00 Time (h)
=
0.3330 Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Time (h) =
0.3330 Delta dose (rem)
Accumulated dose (rem)
Whole Body 2.4732E-03 6.3795E-03 Whole Body
- 2. 7971E-04 6.7445E-04 TEDE 5.6580E-02
- 1. 4192E-01 TEDE
- 1. 5431E-02 3.8705E-02 TEDE 3.6047E-02
- 9. 0192E-02 Control Room (C4)
Compartment Nuclide Inventory:
Time (h)
Kr-83m Kr-85 Kr-85m Kr-87 Kr-88 Rb-88 1-131 1-132 1-133 1-134 1-135 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 Cs-138 0.3330 Ci 1.5387E-06
- 3. 1438E-04 3.8208E-03 6.5757E-03
- 9. 6781E-03 4.4636E-03 7. 0321E-03 9.2108E-03
- 1. 4124E-02
- 1. 2257E-02
- 1. 3170E-02
- 1. 9722E-04
- 3. 5152E-02
- 1. 0777E-03
- 8. 1144E-03
- 4. 9000E-03
- 1. 0802E-02 4.4826E-03 kg
- 7. 4580E-17
- 8. 0130E-10
- 4. 6428E-13
- 2. 3215E-13
- 7. 7183E-13
- 3. 7185E-14
- 5. 6722E-11
- 8. 9233E-13
- 1. 2468E-11
- 4. 5945E-13
- 3. 7501E-12
- 2. 3545E-12
- 1. 8780E-10 2 4019E-12
- 3. 1775E-12
- 5. 3791E-14
- 1. 1233E-13
- 1. 0593E-13 Atoms
- 5. 4112E+08
- 5. 6771E+15 3.2893E+12
- 1. 6069E+12
- 5. 2819E+12
- 2. 5447E+lI 2.60.75E+14
- 4. 0710E+12
- 5. 6455E+13
- 2. 0648E+12
- 1. 6729E+13
- 1. 0824E+13
- 8. 5033E+14 1.0876E+13 1.4174E+13
- 2. 3996E+11
- 4. 9021E+11
- 4. 6229E+11 Decay 6.2734E+07 1.2079E+10 1.5038E+11 2.7528E+11 3.8628E+ll 6.8121E+10
- 3. 7755E+11 5.2177E+11 7.6235E+11 7.5959E+11
- 7. 2002E+11 7.5785E+09 1.3510E+12
- 4. 1440E+10 3.0365E+ll 2.2215E+11
- 6. 7960E+11 8.5128E+10 Control Room (C4)
Transport Group Inventory:
Time (h)
=
0.3330 Atmosphere Sump Noble gases (atoms) 6.5742E+15 0.OOOOE+00 Elemental I (atoms) 1.6922E+13 0.OOOOE+00 Organic I (atoms) 5.2336E+ll 0.OOOOE+00 Aerosols (kg) 7.0624E-11 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid)
Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid)
Total I (Ci)
- 5. 6625E-12 7.1673E-12 5.5793E-02 Time (h)
=
0.3330 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Deposition Surfaces 0.0000E+00 0.0000E+00 0.0000E+00 0.OOOOE+00 Recirculating Filter 0.0000E+00 1.7021E+13 5.2642E+ll
- 7. 4924E-11
XceEnergyv Calculation No. GEN-PI-082 Revision No. 0 Page No. 73 of 145 L6 -
Environment To Control Room Transport Group Inventory:
Time (h)
=
0.3330 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered o.0000E+00 o.0000E+00 0.0000E+00 0.OOOOE+00 Transported
- 7. 3278E+15
- 3. 7394E+13 1.1565E+12
- 1. 6007E-10 L7 -
Control Room Exhaust To Environment Transport Group Inventory:
Time (h)
=
0.3330 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered
- 7. 5222E+14 3.2941E+12 1.0188E+ll 1.4028E-11 Exclusion Area Boundary Doses:
Time (h)
=
0.3667 Delta dose (rem)
Accumulated dose (rem)
Whole Body 1.4993E-03 2.4891E-02 Transported 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Thyroid
- 2. 3099E-01 3.9796E+00 Thyroid 6.2996E-02 1.0853E+00 Thyroid
- 2. 5070E-01
- 3. 0814E+00 Low Population Zone Doses:
Time (h)
=
0.3667 Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Time (h)
=
0.3667 Delta dose (rem)
Accumulated dose (rem)
Whole Body 4.0891E-04 6.7884E-03 Whole Body 6.3809E-05 7.3826E-04 TEDE 8.8005E-03
- 9. 8186E-02 Control Room (C4)
Compartment Nuclide Inventory:
Time (h)
Kr-83m Kr-85 Kr-85m Kr-87 Kr-88 Rb-88 1-131 1-132 1-133 1-134 1-135 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 Cs-138 0.3667 Ci 1.5697E-06 3.2483E-04 3.9273E-03 6.6707E-03
- 9. 9181E-03 4.5524E-03 6.5399E-03 8.4805E-03 1.3122E-02 1.IIOOE-02 1.2206E-02 2.0377E-04
- 3. 6318E-02
- 1. 1133E-03 8.4085E-03
- 4. 8191E-03 1.0110E-02 4.3945E-03 kg 7.6083E-17 8.2795E-10 4.7722E-13
- 2. 3550E-13
- 7. 9096E-13
- 3. 7925E-14
- 5. 2752E-11 8.2159E-13
- 1. 1584E-11
- 4. 1610E-13
- 3. 4757E-12 2.4327E-12
- 1. 9402E-10
- 2. 4811E-12 3.2926E-12
- 5. 2904E-14
- 1. 0514E-13 1.0385E-13 Atoms 5.5202E+08
- 5. 8659E+15
- 3. 3811E+12
- 1. 6301E+12
- 5. 4128E+12
- 2. 5953E+ll 2 4250E+14
- 3. 7483E+12
- 5. 2451E+13
- 1. 8700E+12
- 1. 5505E+13
- 1. 1183E+13
- 8. 7852E+14
- 1. 1234E+13 1 4688E+13
- 2. 3600E+ll
- 4. 5881E+ll
- 4. 5320E+11 Decay
- 6. 9826E+07
- 1. 3537E+10
- 1. 6805E+ll
- 3. 0550E+ll 4.3099E+ll 8.5719E+10 4.0690E+ll 5.6003E+ll 8.2128E+ll 8.1009E+ll 7.7491E+ll 8.4932E+09 1.5140E+12
- 4. 6438E+10
- 3. 4126E+ll 2.4402E+ll
- 7. 2730E+11 1.0317E+ll Control Room (C4)
Transport Group Inventory:
XceI Ener.
Calculation No. GEN-PI-082 Revision No. 0 Page No. 74 of 145 Time (h)
=
0.3667 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Time (h) =
0.3667 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Atmosphere Sump 6.7926E+15 O.0000E+00 1.5871E+13 0.0000E+00 4.9085E+ll 0.0000E+00 6.5616E-11 0.0000E+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid) 5.2637E-12
- 6. 6569E-12 5.1449E-02 Deposition Surfaces 0.0000E+00 0.0000E+00 0.0000E+00 o.0000E+00 Recirculating Filter 0.0000E+00 1.8868E+13 5.8353E+11 8.2925E-11 L6 -
Environment To Control Room Transport Group Inventory:
Time (h)
=
0.3667 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered o.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Transported 7.6016E+15 3.8338E+13 1.1857E+12
- 1. 6366E-10 L7 -
Control Room Exhaust To Environment Transport Group Inventory:
Time (h) =
0.3667 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 8.0717E+14
- 3. 4291E+12 1.0606E+ll 1.4590E-11 Exclusion Area Boundary Doses:
Time (h)
=
0.3670 Delta dose (rem)
Accumulated dose (rem)
Whole Body
- 1. 3140E-05 2.4904E-02 Transported 0.0000E+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 Thyroid 2.0551E-03
- 3. 9816E+00 Thyroid 5.6048E-04 1.0859E+00 Thyroid 2.1490E-03 3.0836E+00 Low Population Zone Doses:
Time (h)
=
0.3670 Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Time (h)
=
0.3670 Delta dose (rem)
Accumulated dose (rem)
Whole Body 3.5836E-06 6.7920E-03 Whole Body 5.4974E-07
- 7. 3881E-04 TEDE 7.8090E-05
Compartment Nuclide Inventory:
Time (h)
=
0.3670 Kr-83m Kr-85 Kr-85m Kr-87 Kr-88 Ci 1.5700E-06 3.2492E-04 3.9283E-03
- 6. 6715E-03 9.9202E-03 kg
- 7. 6096E-17 8.2818E-10
- 4. 7734E-13
- 2. 3553E-13
- 7. 9113E-13 Atoms
- 5. 5212E+08 5.8676E+15
- 3. 3819E+12
- 1. 6303E+12
- 5. 4140E+12 Decay 6.9889E+07
- 1. 3550E+10
- 1. 6821E+11
- 3. 0577E+11 4.3138E+11
L ceIf ergyI Calculation No. GEN-PI-082 Revision No. 0 Page No.75 of 145 Rb-88 1-131 1-132 1-133 1-134 1-135 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 Cs-138 4.5525E-03 6.5358E-03 8.4745E-03
- 1. 3114E-02 1.1091E-02 1.2198E-02 2.0383E-04 3.6328E-02
- 1. 1136E-03
- 8. 4111E-03
- 4. 8184E-03 1.0104E-02 4.3933E-03
- 3. 7925E-14
- 5. 2719E-11 8.2100E-13 1.1576E-11 4.1574E-13
- 3. 4734E-12 2.4334E-12 1.9408E-10
- 2. 4818E-12 3.2937E-12
- 5. 2896E-14 1.0508E-13
- 1. 0382E-13 Inventory:
Sump o.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 roid)
?2 Thyroid)
- 2. 5953E+II 2.4235E+14
- 3. 7456E+12
- 5. 2417E+13
- 1. 8684E+12
- 1. 5494E+13 1 1187E+13
- 8. 7877E+14
- 1. 1238E+13
- 1. 4692E+13
- 2. 3596E+11
- 4. 5854E+lI
- 4. 5307E+11
- 8. 5901E+10 4 0717E+11
- 5. 6037E+11
- 8. 2181E+11
- 8. 1053E+11
- 7. 7540E+11
- 8. 5013E+09
- 1. 5154E+12
- 4. 6482E+10
- 3. 4160E+11 2.4421E+11
- 7. 2770E+11 1.0334E+11 Control Room (C4)
Transport Group Time (h)
=
0.3670 Atmosphere Noble gases (atoms) 6.7946E+15 Elemental I (atoms) 1.5862E+13 Organic I (atoms) 4.9057E+lI Aerosols (kg) 6.5575E-11 Dose Effective (Ci/cc) 1-131 (Thy*
Dose Effective (Ci/cc) 1-131 (ICRI Total I (Ci) 5.2604E-12
- 6. 6526E-12
- 5. 1413E-02 Time (h)
=
0.3670 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Deposition Surfaces 0.OOOOE+00 o.0000E+00 0.0000E+00 0.0000E+00 Recirculating Filter 0.OOOOE+00 1.8883E+13 5.8402E+II 8.2994E-11 L6 -
Environment To Control Room Transport Group Inventory:
Time (h)
=
0.3670 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 0.OOOOE+00 0.0000E+00 0.0000E+00 0.OOOOE+00 Transported
- 7. 6040E+15
- 3. 8347E+13 1.1860E+12
- 1. 6370E-10 L7 -
Control Room Exhaust To Environment Transport Group Inventory:
Time (h)
=
0.3670 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered
- 8. 0767E+14
- 3. 4303E+12 1.0609E+I1 1.4595E-11 Exclusion Area Boundary Doses:
Time (h)
=
8.0000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 3.5795E-02 6.0699E-02 Transported 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Thyroid 5.4355E+00
- 9. 4171E+00 Thyroid 1.4824E+00 2.5683E+00 Low Population Zone Doses:
- 2. 0563E-01
- 3. 5643E-01 TEDE
- 5. 6081E-02 9.7207E-02 Time (h)
=
8.0000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 9.7624E-03 1.6554E-02
XceI Energy] Calculation No. GEN-PI-082 Revision No. 0 Pae No. 76 of 145 Control Room Doses:
Time (h)
=
8.0000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 3.7443E-03 4.4831E-03 Thyroid
- 4. 0911E+00 7.1747E+00 TEDE
- 1. 3396E-01 2.3221E-01 Control Room (C4)
Compartment Nuclide Inventory:
Time (h)
Kr-83m Kr-85 Kr-85m Kr-87 Kr-88 Rb-88 1-131 1-132 1-133 1-134 1-135 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Cs-138 8.0000 Ci 2.8302E-07 1.0551E-03
- 3. 9158E-03 3.3795E-04 4.9999E-03 2.6728E-03 3.0292E-04 4.0459E-05 4.8439E-04 1.2644E-06 2.6098E-04 6.5543E-04 1.1534E-01 3.4132E-03 3.1708E-02 5.2553E-04 1.0288E-08 kg 1.3717E-17
- 2. 6894E-09 4.7583E-13
- 1. 1931E-14
- 3. 9874E-13
- 2. 2266E-14 2 4434E-12
- 3. 9197E-15
- 4. 2760E-13
- 4. 7396E-17 7 4314E-14 7.8249E-12
- 6. 1618E-10
- 7. 6067E-12
- 1. 2416E-11
- 5. 7692E-15 2.4314E-19 Atoms 9.9527E+07
- 1. 9054E+16
- 3. 3712E+12
- 8. 2585E+10 2 7287E+12 1.5238E+11
- 1. 1232E+13
- 1. 7882E+10
- 1. 9361E+12 2.1300E+08
- 3. 3150E+11
- 3. 5972E+13 2.7900E+15
- 3. 4443E+13
- 5. 5387E+13
- 2. 5735E+10 1.0610E+06 Decay 9.7954E+08 7.5458E+II 4.9051E+12 2.8604E+12 9.1298E+12 2.9096E+12 8.7886E+II 9.2579E+11 1.7033E+12 1.1481E+12 1.4807E+12 4.7048E+11 8.3220E+13 2.4977E+12 2.1648E+13 1.3368E+12
- 3. 2309E+11 Control Room (C4)
Transport Group Inventory:
Time (h)
=
8.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Time (h)
=
8.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Atmosphere Sump 2.1976E+16 0.OOOOE+00 5.5996E+12 0.0000E+00 1.7318E+11 0.OOOOE+00 1.7121E-12 0.0000E+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid) 2.2540E-13 2.6240E-13 1.0900E-03 Deposition Recirculating Surfaces 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Filter 0.0000E+00
- 1. 4184E+14 4.3868E+12 1.9160E-10 L6 -
Environment To Control Room Transport Group Inventory:
Time (h)
=
8.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Transported 5.1103E+16 1.6055E+14 4.9653E+12 2.1567E-10 L7 -
Control Room Exhaust To Environment Transport Group Inventory:
Time (h)
=
8.0000 Noble gases (atoms)
Elemental I (atoms)
Pathway Filtered 2.9007E+16 1.2418E+13 Transported 0.OOOOE+00 0.OOOOE+00
Xcel Enerwy Calculation No. GEN-PI-082 Revision No. 0 Page No. 77 of 145 Organic I (atoms)
Aerosols (kg) 3.8407E+ll 2.2213E-11 Exclusion Area Boundary Doses:
Time (h)
=
24.0000 Whole Body Delta dose (rem) 3.0254E-02 Accumulated dose (rem) 9.0954E-02 Low Population Zone Doses:
0.OOOOE+00 0.OOOOE+00 Thyroid
- 1. 1569E+01
- 2. 0986E+01 Thyroid
- 3. 6578E-01
- 2. 9341E+00 Thyroid
- 2. 1017E+00 9.2764E+00 Time (h)
=
24.0000 Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Time (h)
=
24.0000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 1.8600E-03
- 1. 8414E-02 Whole Body 2.1601E-03 6.6432E-03 TEDE
- 3. 8777E-01 7.4420E-01 TEDE 1.3164E-02
- 1. 1037E-01 TEDE 6.7740E-02
- 2. 9995E-01 Control Room (C4)
Compartment Nuclide Inventory:
Time (h)
Kr-83m Kr-85 Kr-85m Kr-87 Kr-88 Rb-88 1-131 1-132 1-133 1-135 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m
=
24.0000 Ci 3.8400E-I0 6.1342E-04
- 1. 9151E-04 3.2048E-08 5.8547E-05 1.5546E-04 1.3030E-04 1.4842E-07 1.2949E-04 2.2209E-05 3.7584E-04
- 6. 4121E-02 1.7734E-03
- 1. 1919E-02
- 3. 4143E-05 kg
- 1. 8612E-20 1.5635E-09
- 2. 3271E-14
- 1. 1314E-18
- 4. 6691E-15 1.2951E-15 1.0510E-12
- 1. 4379E-17
- 1. 1431E-13
- 6. 3241E-15
- 4. 4871E-12
.3.4256E-10
- 3. 9523E-12
- 4. 6673E-12
- 3. 7482E-16 Atoms 1.3504E+05
- 1. 1077E+16
- 1. 6487E+ll 7.8316E+06
- 3. 1952E+10 8.8625E+09 4 8317E+12
- 6. 5598E+07
- 5. 1757E+11
- 2. 8211E+10
- 2. 0627E+13
- 1. 5511E+15
- 1. 7896E+13
- 2. 0820E+13
- 1. 6720E+09 Decay 1 0613E+09 2 264 6E+12 7 2000E+12 2 9313E+12
- 1. 1216E+13 3 4582E+12
- 1. 1681E+12
- 9. 3437E+II
- 2. 0734E+12
- 1. 6067E+12
- 1. 4018E+12
- 2. 4487E+14 7 1339E+12
- 6. 0303E+13
- 1. 7962E+12 Control Room (C4)
Transport Group Inventory:
Time (h)
=
24.0000 Atmosphere Sump Noble gases (atoms) 1.2688E+16 0.OOOOE+00 Elemental I (atoms) 2.3313E+12 0.OOOOE+00 Organic I (atoms) 7.2101E+10
>0.OOOOE+00 Aerosols (kg) 6.4932E-13 0.OOOOE+00 Dose Effective (Ci/cc) 1-131 (Thyroid)
Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid)
Total I (Ci) 8.7832E-14
- 9. 6051E-14
- 2. 8215E-04 Time (h)
=
24.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Deposition Surfaces 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Recirculating Filter 0.OOOOE+00
- 2. 7621E+14 8. 5427E+12
- 2. 3135E-10 L6 -
Environment To Control Room Transport Group Inventory:
Pathway
XceIlEnerg Calculation No. GEN-PI-082 Revision No. 0 Page No..78 of 145 Time (h)
=
24.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Filtered 0.0000E+00 0.0000E+00 0.0000E+00 0.OOOOE+00 Transported
- 9. 9976E+16 3.0181E+14
- 9. 3345E+12
- 2. 5708E-10 L7 -
Control Room Exhaust To Environment Transport Group Inventory:
Time (h)
=
24.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 8.6962E+16 2.2241E+13
- 6. 8786E+ll 2.5001E-11 Exclusion Area Boundary Doses:
Time (h)
=
96.0000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 2.0267E-02 1.1122E-01 Transported 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Thyroid
- 1. 9962E+01
- 4. 0948E+01 Thyroid 1.4391E-01 3.0780E+00 Thyroid 1.5237E+00
- 1. 0800E+01 Low Population Zone Doses:
Time (h)
=
96.0000 Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Time (h)
=
96.0000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 2.2234E-04 1.8637E-02 Whole Body 6.4632E-04 7.2895E-03 TEDE
- 6. 3097E-01 1.3752E+00 TEDE
- 4. 6251E-03
- 1. 1500E-01 TEDE 4.7275E-02
- 3. 4722E-01 Control Room (C4)
Compartment Nuclide Inventory:
Time (h)
Kr-85 Kr-85m 1-131 1-133 1-135 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m 96.0000 Ci 2.1297E-04 9.6607E-10 3.5400E-05 4.1359E-06 4.1107E-09 1.2345E-04 1.6295E-02 2.9430E-04 3.5184E-05 6.3188E-09 kg
- 5. 4283E-10 1.1739E-19 2.8554E-13
- 3. 6510E-15 1.1705E-18 1.4738E-12
- 8. 7054E-11
- 6. 5589E-13 1.3778E-14 6.9367E-20 Atoms
- 3. 8459E+15
- 8. 3170E+05 1.3127E+12
- 1. 6532E+10
- 5. 2215E+06
- 6. 7751E+12
- 3. 9417E+14
- 2. 9698E+12 6.1459E+10 3.0944E+05 Decay
- 4. 5513E+12
- 7. 3009E+12
- 1. 5628E+12
- 2. 2454E+12
- 1. 6175E+12
- 2. 7708E+12
- 4. 5564E+14 1.2106E+13
- 7. 3508E+13
- 1. 8540E+12 Control Room (C4)
Transport Group Inventory:
Time (h)
=
96.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Time (h)
=
96.0000 Noble gases (atoms)
Atmosphere Sump 4.2498E+15 0.OOOOE+00 5.7635E+11 0.OOOOE+00 1.7825E+10 0.OOOOE+00 1.5992E-13 0.OOOOE+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid)
Deposition Recirculatir Surfaces Filter 0.OOOOE+00 0.OOOOE+00
- 2. 0785E-14
- 2. 1026E-14 3.9540E-05 ng
X eEn'e~rdy Calculation No. GEN-PI-082 Revision No. 0 Page No. 79 of 145 Elemental I (atoms)
Organic I (atoms)
Aerosols (kg) o.OOOOE+00 o.OOOOE+00 0.0000E+00
- 4. 4869E+14 1.3877E+13 2.7910E-10 L6 -
Environment To Control Room Transport Group Inventory:
Time (h)
=
96.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 Transported 1.7825E+17 4.8575E+14 1.5023E+13
- 3. 0804E-10 L7 -
Control Room Exhaust To Environment Transport Group Inventory:
Time (h)
=
96.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered
- 1. 7346E+17 3.4849E+13 1.0778E+12 2.8351E-11 Exclusion Area Boundary Doses:
Time (h)
= 720.0000 Whole Body Delta dose (rem) 2.8793E-02 Accumulated dose (rem) 1.4001E-01 Transported 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.0000E+00 Thyroid
- 5. 4975E+01
- 9. 5922E+01 Thyroid
- 5. 7891E-02
- 3. 1359E+00 Thyroid 2.0708E+00 1.2871E+01 Low Population Zone Doses:
Time (h)
= 720.0000 Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Time (h)
= 720.0000 Delta dose (rem)
Accumulated dose (rem)
Whole Body
- 4. 6139E-05 1.8683E-02 Whole Body
- 3. 9174E-04
- 1. 1681E-01 TEDE 6.3448E-02 4.1067E-01 Control Room (C4)
Compartment Nuclide Inventory:
Time (h)
= 720.0000 Kr-85 1-131 Xe-131m Xe-133 Xe-133m Ci 1.5609E-04 2.7707E-06
- 3. 3193E-05 3.9575E-04 6.0729E-08 kg
- 3. 9786E-10
- 2. 2349E-14
- 3. 9628E-13
- 2. 1143E-12
- 1. 3534E-16 Atoms
- 2. 8188E+15
- 1. 0274E+ll
- 1. 8217E+12
- 9. 5732E+12
- 6. 1282E+08 Decay 1.7708E+13 2.4380E+12
- 7. 8603E+12
- 7. 4735E+14
- 1. 4442E+13 Control Room (C4)
Transport Group Inventory:
Time (h)
= 720.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Atmosphere Sump 2.8302E+15 0.OOOOE+00 4.4549E+10 0.OOOOE+00 1.3778E+09 0.OOOOE+00 1.2358E-14 0.OOOOE+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid)
- 1. 5958E-15
- 1. 5958E-15 2.7707E-06 Deposition Recirculating
Energyj calculation No. GEN-PI-082 Revision No. 0 Page No.80 of 145 Time (h)
= 720.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Surfaces 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 Filter 0.0000E+00
- 8. 0348E+14 2.4850E+13
- 3. 8167E-10 L6 -
Environment To Control Room Transport Group Inventory:
Time (h).
720.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Transported
- 6. 2719E+17
- 8. 6643E+14
- 2. 6797E+13 4.1779E-10 L7 -
Control Room Exhaust To Environment Transport Group Inventory:
Time (h)
= 720.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 6.2351E+17
- 6. 0784E+13 1.8799E+12
- 3. 5545E-11 Transported 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00
- S###########m##################################################
1-131 Summary
- ý############################################################
Time (hr) 0.000 0.004 0.083 0.200 0.333 0.367 0.367 0.800 1.100 1.400 1.700 2.000 2.300 2.600 2.900 3.200 3.500 3.800 4.100 4.400 4.700 5.000 5.300
.5.600 5.900 6.200 6.500 6.800 7.100 7.400 Containment (Cl) 1-131 (Curies) 8.1253E+04 5.2652E+05 5.2636E+05
- 5. 2614E+05 5.2588E+05 5.2582E+05 5.2582E+05 5.2499E+05
- 5. 2441E+05 512384E+05 5.2326E+05 5.2269E+05
- 5. 2212E+05
- 5. 2154E+05
- 5. 2097E+05
- 5. 2040E+05
- 5. 1983E+05
- 5. 1926E+05 5.1869E+05
- 5. 1812E+05
- 5. 1756E+05
- 5. 1699E+05
- 5. 1642E+05
- 5. 1586E+05
- 5. 1529E+05
- 5. 1473E+05
- 5. 1416E+05
- 5. 1360E+05
- 5. 1304E+05
- 5. 1247E+05 Shield Bldg (C2) 1-131 (Curies) 0.OOOOE+00 0.0000E+00 0 OOOOE+00 0 OOOOE+00 0 OOOOE+00 0 OOOOE+00 0 OOOOE+00
- 6. 6405E+00
- 9. 9798E+00
- 1. 2559E+01
- 1. 4555E+01
- 1. 6101E+01
- 1. 7302E+01
- 1. 8236E+01
- 1. 8965E+01
- 1. 9535E+01
- 1. 9981E+01
- 2. 0332E+01 2.0608E+01
- 2. 0825E+01
- 2. 0997E+01 2.1133E+01 2.1241E+01 2.1326E+01 2.1393E+01 2.1445E+01 2.1486E+01 2.1517E+01 2.1541E+01 2.1558E+01 Environment (C3) 1-131 (Curies) 1.4107E-03 5.9233E-02 2.6812E+00 6.5189E+00 1.0891E+01 1.1564E+01 1.1570E+01 1.2280E+01 1.2805E+01 1.3353E+01 1.3921E+01 1.4507E+01 1.5110E+01
- 1. 5726E+01
- 1. 6356E+01
- 1. 6997E+01
- 1. 7649E+01l
- 1. 8310E+01
- 1. 8979E+01
- 1. 9655E+01
- 2. 0338E+01 2 1027E+01
- 2. 1721E+01
- 2. 2420E+01
- 2. 3123E+01
- 2. 3829E+01 2 4539E+01
- 2. 5251E+01
- 2. 5967E+01
- 2. 6684E+01
,XceI nergy Calculation No. GEN-PI-082 Revision No. 0 Page No. 81 of 145 7.700 8.000 8.300 8.600 8.900 9.200 9.500 9.800 10.100 10.400 24.000 96.000 720.000 Time (hr) 0.000 0.004 0.083 0.200 0.333 0.367 0.367 0.800 1.100 1.400 1.700 2.000 2.300
- 2. 600 2.900 3.200 3.500 3.800 4.100 4.400 4.700 5.000 5.300
- 5. 600 5.900 6.200 6.500 6.800 7.100 7.400 7.700 8.000 8.300 8.600 8.900 9.200 9.500 9.800
- 10. 100 10.400 24.000
- 96. 000 720.000
- 5. 1191E+05
- 5. 1135E+05
- 5. 1079E+05 5.1023E+05 5.0967E+05
- 5. 0911E+05 5.0856E+05 5.0800E+05 5.0744E+05 5.0689E+05 4.8231E+05
- 3. 7156E+05 3.8732E+04 2.1570E+01 2.1577E+01
- 2. 1580E+01 2.1580E+01 2.1578E+01 2.1573E+01 2.1566E+01 2.1557E+01 2.1547E+01 2.1535E+01
- 2. 0597E+01 7.9338E+00 8.2705E-01
- 2. 7403E+01 2.8125E+01
- 2. 8847E+01
- 2. 9571E+01
- 3. 0295E+01
- 3. 1021E+01
- 3. 1747E+01 3.2474E+01
- 3. 3202E+01 3.3930E+01
- 6. 6439E+01 1.4187E+02 3.6454E+02 Control Room (C4) 1-131 (Curies) 6.0295E-06 2.5268E-04 1.0597E-02 8.5213E-03 7.0321E-03 6.5399E-03 6.5358E-03 1.4917E-03 6.5776E-04 3.9285E-04 3.1301E-04 2.9292E-04 2.6586E-04 2.6108E-04 2.6320E-04 2.6719E-04 2.714 6E-04 2.7550E-04 2.7919E-04 2.8252E-04 2.8550E-04 2.8817E-04 2.9055E-04 2.9267E-04 2.9457E-04 2.9625E-04 2.9774E-04 2.9906E-04 3.0022E-04 3.0124E-04 3.0214E-04 3.0292E-04 1.8995E-04 1.5260E-04 1.4033E-04 1.3637E-04 1.3514E-04 1.3481E-04 1.3475E-04 1.3478E-04 1.3030E-04 3.5400E-05 2.7707E-06 ABSVZ (C5) 1-131 (Curies) 0.OOOOE+00 0.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0.OOOOE+00 2.1909E-04 2.1909E-04 2.1874E-04 2.1850E-04 2.1827E-04 2.1803E-04 2.1779E-04 2.1755E-04 2.1731E-04 2.1707E-04 2.1683E-04
- 2. 1660E-04 2.1636E-04 2.1612E-04 2.1589E-04 2.1565E-04 2.1541E-04 2.1518E-04
- 2. 1494E-04 2.1470E-04 2.1447E-04 2.1423E-04 2.1400E-04 2.1377E-04 2.1353E-04 2.1330E-04 2.1306E-04 2.1283E-04 2.1260E-04 2.1236E-04 2.1213E-04 2.1190E-04 2.1167E-04 2.1143E-04 2.1120E-04 2.0096E-04 7.7407E-05 8.0692E-06
XcelEnergyl Calculation No. GEN-PI-082 Revision No. 0 Page No.82 of 145
- C###########v##DoSm####r############################y Cumulative Dose Summary
- 0#######################################
Exclusion Area Bounda Low Populatic Time (hr) 0.000 0.004 0.083 0.200 0.333 0.367 0.367 0.800 1.100 1.400 1.700 2.000 2.300 2.600 2.900 3.200 3.500 3.800 4.100 4.400 4.700 5.000 5.300 5.600 5.900 6.200 6.500 6.800 7.100 7.400 7.700 8.000 8.300
- 8. 600 8.900 9.200 9.500 9.800
- 10. 1.00 10.400 24.000
- 96. 000 720.000 Thyroid (rem) 0 OOOOE+00
- 2. 0418E-02
- 9. 2443E-01
- 2. 2459E+00
- 3. 7486E+00
- 3. 9796E+00
- 3. 9816E+00
- 4. 2249E+00
- 4. 4036E+00
- 4. 5895E+00
- 4. 7816E+00
- 4. 9791E+00
- 5. 1813E+00
- 5. 3877E+00
- 5. 5978E+00
- 5. 8109E+00
- 6. 0268E+00
- 6. 2450E+00
- 6. 4653E+00
- 6. 6874E+00
- 6. 9109E+00 7 1357E+00
- 7. 3616E+00
- 7. 5883E+00 7 8157E+00
- 8. 0437E+00
- 8. 2722E+00
- 8. 5009E+00
- 8. 7299E+00
- 8. 9590E+00
- 9. 1881E+00
- 9. 4171E+00
- 9. 6461E+00
- 9. 8749E+00
- 1. 0103E+01
- 1. 0332E+01
- 1. 0560E+01
- 1. 0787E+01
- 1. 1015E+01
- 1. 1241E+01
- 2. 0986E+01
- 4. 0948E+01
- 1. 4192E-01 1.5072E-01 1.5080E-01
- 1. 6165E-01
- 1. 6928E-01 1.7703E-01 1.8490E-01
- 1. 9286E-01 2.0091E-01 2.0902E-01 2.1719E-01 2.2539E-01 2.3363E-01 2.4188E-01 2.5015E-01 2.5842E-01 2.6669E-01 2.7494E-01 2.8319E-01 2.9142E-01 2.9964E-01
- 3. 0783E-01 3.1600E-01 3.2414E-01 3.3226E-01 3.4034E-01 3.4840E-01 3.5643E-01 3.6442E-01 3.7239E-01 3.8032E-01 3.8822E-01 3.9608E-01 4.0392E-01 4.1172E-01 4.1949E-01 7.4420E-01 1.3752E+00 3.0779E+00 Thyroid (rem) o OOOOE+00
- 5. 5685E-03
- 2. 5212E-01
- 6. 1252E-01
- 1. 0223E+00
- 1. 0853E+00 1.0859E+00 1. 1522E+00 1.2010E+00 1.2517E+00 1.3041E+00 1.3579E+00 1 4131E+00
- 1. 4694E+00
- 1. 5267E+00
- 1. 5848E+00
- 1. 6437E+00 1.7032E+00
- 1. 7633E+00 1.8238E+00 1.8848E+00
- 1. 94 61E+00
- 2. 0077E+00 2.0695E+00 2.1316E+00 2.1937E+00 2.2560E+00
- 2. 3184E+00 2.3809E+00
- 2. 4434E+00 2.5058E+00 2.5683E+00
- 2. 5756E+00 2.5828E+00 2.5900E+00 2.5972E+00 2.6044E+00 2. 6116E+00 2.6188E+00
- 2. 6260E+00
- 2. 9341E+00
- 3. 0780E+00
- 3. 1359E+00 0.0 2.1 9.6 2.3 3.8 4.1 4.1 4.4 4.6 4.8 5.0 5.2 5.4 5.7 5.9 6.1 6.3 6.5 6.8 7.0 7.2 7.4 7.7 7.9 8.1 8.3 8.6 8.8 9.0 9.2 9.5 9.7 9.7 9.7 9.8 9.8 9.8 9.8 9.9 9.9 1.2 1.1 1.1 rn Zone Control Room TEDE Thyroid TEDE (rem)
(rem)
(rem) 0000E+00 0.OOOOE+00 0.OOOOE+00 1222E-04 3.9039E-04 1.2433E-05 6070E-03 4.7663E-01 1.5179E-02 3274E-02 1.6999E+00 5.4145E-02 8705E-02 2.8307E+00 9.0192E-02 I105E-02 3.0814E+00 9.8186E-02 I126E-02 3.0836E+00 9.8254E-02 4086E-02 4.6903E+00 1.4963E-01 6168E-02 5.0189E+00 1.6029E-01 8282E-02 5.1825E+00 1.6570E-01
)426E-02 5.2945E+00 1.6947E-01 2598E-02 5.3916E+00 1.7276E-01 4792E-02 5.4806E+00 1.7579E-01 7005E-02 5.5648E+00 1.7866E-01 9233E-02 5.6485E+00 1.8151E-01 471E-02 5.7330E+00 1.8437E-01 3717E-02 5.8185E+00 1.8727E-01 5968E-02 5.9051E+00 1.9018E-01 8222E-02 5.9926E+00 1.9313E-01 0478E-02 6.0810E+00 1.9609E-01 2732E-02 6.1701E+00 1.9907E-01 4985E-02 6.2598E+00 2.0206E-01 7234E-02 6.3500E+00 2.0507E-01 9479E-02 6.4407E+00 2.0808E-01 719E-02 6.5318E+00 2.1109E-01 3954E-02 6.6231E+00 2.1411E-01 6181E-02 6.7147E+00 2.1713E-01 402E-02 6.8065E+00 2.2015E-01 (615E-02 6.8984E+00 2.2317E-01 2821E-02 6.9905E+00 2.2619E-01 5018E-02 7.0825E+00 2.2920E-01 7207E-02 7.1747E+00 2.3221E-01 7487E-02 7.2468E+00 2.3459E-01 7764E-02 7.2977E+00 2.3630E-01 8040E-02 7.3417E+00 2.3778E-01 8314E-02 7.3833E+00 2.3918E-01 8586E-02 7.4241E+00 2.4054E-01 8857E-02 7.4646E+00 2.4189E-01 9126E-02 7.5050E+00 2.4323E-01 9394E-02 7.5452E+00 2.4456E-01 037E-01 9.2764E+00 2.9995E-01 1500E-01 1.0800E+01 3.4722E-01 681E-01 1.2871E+01 4.1067E-01
- 4#W###o###########################o#########s Worst Two-Hour Doses
- 4########################ý###################
Exclusion Area Boundary Time Whole Body (hr)
(rem) 0.0 3.5561E-02 Thyroid (rem)
- 1. 9286E-01
SXceIEner*a, y
Calculation No. GEN-PI-082 Revision No. 0 Page No. 83 of 145 3.2 RADTRAD Output File PREAINID01.o0 RADTRAD Version 3.03 (Spring 2001) run on 6/22/2010 at 1:22:00
- 4#####ý#######4######f4##4#####4##############4######4#4##
- 4###################4###ý###4####################**##*#######*#4###*##44 File information Plant file
= G:\\Radtrad 3.03\\Input\\PI\\GEN-PI-082 Rl\\PREAINID0l.psf Inventory file
= g:\\radtrad 3.03\\defaults\\pirearcsdef.txt Release file
= g:\\radtrad 3.03\\defaults\\pingp iodine rft.txt Dose Conversion file
= g:\\radtrad 3.03\\defaults\\pingp-fgll&12.txt 6
6
- 6666 6
6
- 6#66 66
- 4 6
4###
Radtrad 3.03 4/15/2001 PINGP 1 & 2 Rod Ejection Accident AST Analysis -
P-T-S Leakage Iodine Release From Intact SG Nuclide Inventory File:
g:\\radtrad 3.03\\defaults\\pirearcsdef.txt Plant Power Level:
1.8520E+03 Compartments:
4 Compartment 1:
RCS 3
5.2900E+03 0
0 0
0 0
Compartment 2:
Environment 2
0.0000E+00 0
0 0
0 0
xcelEnerg*:
Calculation No. GEN-PI-082 Revision No. 0 Page No. 84 of 145 Compartment 3:
Control Room 1
6.1315E+04 0
0 1
0 0
Compartment 4:
Intact SG 3
3.4380E+03 0
0 0
0 0
Pathways:
4 Pathway 1:
4 2
Pathway 2:
Environment to Control Room 2
3 2
Pathway 3:
Control Room to Environment 3
2 2
Pathway 4:
Intact SG to Environment 4
2 2
End of Plant Model File Scenario Description Name:
Plant Model Filename:
Source Term:
1 1
1.0000E+00 g:\\radtrad 3.03\\defaults\\pingp fgll&12.txt g:\\radtrad 3.03\\defaults\\pingp iodine rft.txt 0.0000E+00 1
0.OOOOE+00 9.7000E-01 3.OOOOE-02 1.OOOOE+00 Overlying Pool:
0 0.OOOOE+00 0
. X eI nergy Calculation No. GEN-PI-082 Revision No. 0 Page No. 85 of 145 0
0 0
Compartments:
4 Compartment 1:
0 1
0 0
0 Compartment 2:
0 1
0 0
0 0
0 0
0 Compartment 3:
1 1
0 0
1 3.6000CE+03 3
C. CCCCE+CC
- 8. 3300E-02
- 7. 2000E+02 0
0 Compartment 4:
0 1
0 0
0 0
0 0
0 Pathways:
4 Pathway 1:
0 0
0 0
C.0CCCE+00
- 9. 9000E+01 C.0000E+00 C.0000E+00
- 9. 5000E+01 C.0000E+00 C.0CCCE+00
- 9. 5000E+01 C.0000E+00
XceI Energy" Calculation No. GEN-PI-082 Revision No. 0 Page No. 86 of 145 0
1 2
C.0C0CE+00 4.5500E+01 0
0 0
0 0
0 Pathway 2:
0 0
0 0
0 1
3 C.0C0CE+00 8.3300E-02 7.2000E+02 0
0 0
0 0
0 Pathway 3:
0 0
0 0
0 1
3 C.00CCE+00 8.3300E-02 7.2000E+02 0
0 0
0 0
0 Pathway 4:
0 0
0 0
0 1
5 C.0C0CE+00 2.0C00E+00 8.0C00E+00 2.4000E+01 3.7600E-02 C.0000E+00 C.0CCCE+00 C.0000E+00 C.0CCCE+00 0.0000E+00 C.00C0E+00 C.0000E+00 2.0C00E+03 3.0C00E+02 C.0000E+00 C.0C0CE+00 C.0C0CE+00 C.0000E+00 C.0CC0E+00 C.0000E+00 C.0000E+00 C.0C00E+00 C.0CC0E+00 o.0000E+00 2.0000E+03 3.00CCE+02 C.0CCCE+00
- 3. 9420E-01
- 2. 3610E-01 1.7340E-01 1.3980E-01 C.0CCCE+00 C.0C00E+00 C.0C0CE+00 0.0000E+00 C.0CCCE+00 C.0C0CE+00 C.0000E+00 C.0000E+00 C.0000E+00 C.0000E+00 C.00C0E+00 C.0CCCE+00 C.0000E+00 C.0000E+00 C.0C0CE+00 0.0000E+00 C.0CC0E+00 C.000CE+00 C.0C0CE+00 C.0C0CE+00 C.0000E+00
XceIEnergyl Calculation No. GEN-PI-082 Revision No. 0 Page No. 87 of 145 4.5500E+01 O.OOOOE+00 0.OO0E+00 O.0OOOE+00 O.OOOOE+00 0
0 0
0 0
0 Dose Locations:
3 Location 1:
Exclusion Area Boundary 2
1 2
0.0000E+00 7.2000E+02 1
2 C.0000E+00 7.2000E+02 0
6.4900E-04 C.0000E+00 3.5000E-04 C.0000E+00 Location 2:
Low Population Zone 2
1 5
C.0000E+00 8.0000E+00 2.4000E+01
- 9. 6000E+01 7.2000E+02 1
4 C.0000E+00 8.0000E+00 2.4000E+01 7.2000E+02 0
Location 3:
Control Room 3
0 1
2 0.0000E+00 7.2000E+02 1
1.7700E-04 3.9900E-05 7.1200E-06 1.0400E-06 C.0000E+00 3.5000E-04 1.8000E-04 2.3000E-04 C.0000E+00 3.5000E-04 0.0000E+00 4
C.C0CCE+00 1.0000E+00 2.4000E+01 6.0000E-01 9.6000E+01 4.0000E-01 7.2000E+02 C.0000E+00 Effective Volume Location:
1 6
0.CCC0E+00 1.9300E-02 2.0000E+00 1.5700E-02
XcelEnergyl Calculation No. GEN-PI-082 Revision No. 0 Page No. 88 of 145 8.OOOOE+00 7.0400E-03 2.4000E+01 4.8700E-03 9.6000E+01 3.8600E-03 7.2000E+02 0.0000E+00 Simulation Parameters:
6 O.OOOOE+00 1.OOOE-01 2.OOOOE+00 5.OOOOE-01 8.OOOOE+00 1.OOOOE+00 2.4000E+01 2.0OOOE+00 9.6000E+01 4.OOOOE+00 7.2000E+02 O.OOOOE+00 Output Filename:
G:\\Radtrad 3.o8 1
1 1
0 0
End of Scenario File
XceIEne#r#y] Calculation No. GEN-PI-082 Revision No. 0 Page No.89 of 145 RADTRAD Version 3.03 (Spring 2001) run on 6/22/2010 at 1:22:00
- ý######################4########*######################ý##
- 4##########*##########################*#############################
Plant Description
- 4#*##########################################################
Number of Nuclides
=
60 Inventory Power =
1.0000E+00 MWth Plant Power Level =
1.8520E+03 MWth Number of compartments
=
4 Compartment information Compartment number 1
(Source term fraction =
1.OOOOE+00 Name: RCS Compartment volume =
5.2900E+03 (Cubic feet)
Compartment type is Normal Pathways into and out of compartment 1
Exit Pathway Number 1: RCS to Intact SG Compartment number 2
Name: Environment Compartment type is Environment Pathways into and out of compartment 2
Inlet Pathway Number 3: Control Room to Environment Inlet Pathway Number 4: Intact SG to Environment Exit Pathway Number 2: Environment to Control Room Compartment number 3
Name: Control Room Compartment volume =
6.1315E+04 (Cubic feet)
Compartment type is Control Room Removal devices within compartment:
Filter(s)
Pathways into and out of compartment 3
Inlet Pathway Number 2: Environment to Control Room Exit Pathway Number 3: Control Room to Environment Compartment number 4
Name: Intact SG Compartment volume =
3.4380E+03 (Cubic feet)
Compartment type is Normal Pathways into and out of compartment 4
Inlet Pathway Number 1: RCS to Intact SG Exit Pathway Number 4: Intact SG to Environment Total number of pathways =
4
X e.
X eI.Energy. Calculation No. GEN-PI-082 Revision No. 0 Page No. 90 of 145 RADTRAD Version 3.03 (Spring 2001) run on 6/22/2010 at 1:22:00
- 4##############################
Scenario Description 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 0.0000E+00 1.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+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 o OOOOE+00 0 OOOOE+00 0 OOOOE+00 0 OOOOE+00 0 OOOOE+00 RELEASE MASS (gm)
- 0. OOOE+00
- 5. 928E+00
- 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 1-131 1-132 1-133 1-134 1-135 Nuclide Kr-85m Kr-87 Kr-88 1-131 1-133 1-135 Xe-133m Xe-135 Xe-135m Xe-138 Group Specific Inventory (Ci/MWt) 2 3.010E+02 2
4.354E+02 2
6.106E+02 2
6.819E+02 2
5.831E+02 half Whole Body life DCF (s)
(Sv-m3/Bq-s) 6.947E+05 1.820E-14 8.280E+03 1.120E-13 7.488E+04 2.940E-14 3.156E+03 1.300E-13 2.380E+04 8.294E-14 Daughter Kr-85 Rb-87 Rb-88 Xe-131m Xe-133m Xe-135m Xe-133 Cs-135 Xe-135 Cs-138 Fraction 0.21 1.00 1.00 0.01 0.03 0.15 1.00 1.00 1.00 1.00 Daughter none none none none Xe-133 Xe-135 none none none none Fractior 0.00 0.00 0.00 0.00 0.97 0.85 0.00 0.00 0.00 0.00 Inhaled Thyroid (Sv/Bq)
- 2. 920E-07 1.740E-09
- 4. 860E-08 2.880E-10
- 8. 460E-09 Daughter none none none none none none none none none none Inhaled Effective (Sv/Bq) 8.890E-09 1.030E-10 1.580E-09 3.550E-11 3.320E-10 Fraction 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Iodine fractions Aerosol Elemental Organic COMPARTMENT DATA
=
0.OOOOE+00
=
9.7000E-01
=
3.OOOOE-02 Compartment number Compartment number 1: RCS 2: Environment
- -,?..
X e I~ ~
Calculation No. GEN-PI-082 Revision No. 0 Page No. 91 of 145 Compartment number 3: Control Room Compartment Filter Data Time (hr) 0.OOOOE+00 8.3300E-02 7.2000E+02 Flow Rate (cfm) 3.6000E+03 3.6000E+03 3.6000E+03 Filter Efficiencies Aerosol Elemental 0.OOOOE+00 0.OOOOE+00 9.9000E+01 9.5000E+01 0.OOO0E+00 0.OOOOE+00
(%
Organic
- 0. OOOOE+00 9.5000E+01
- 0. 0000E+00 Compartment number 4: Intact SG PATHWAY DATA Pathway number 1: RCS to Intact SG Pathway Filter: Removal Data Time (hr) 0.0000E+00
- 4. 5500E+01 Flow Rate (cfm) 3.7600E-02 0.0000E+00 Filter Efficiencies (%)
Aerosol Elemental Organic 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 2: Environment to Control Room Pathway Filter: Removal Data Time (hr) 0.0000E+00 8.3300E-02 7.2000E+02 Flow Rate (cfm) 2.0000E+03 3.0000E+02 0.0000E+00 Filter Efficiencies (%)
Aerosol Elemental Organic 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 3: Control Room to Environment Pathway Filter: Removal Data Time (hr) 0.0000E+00 8.3300E-02 7.2000E+02 Flow Rate (cfm) 2.0000E+03 3.0000E+02 0.0000E+00 Filter Efficiencies (%)
Aerosol Elemental Organic 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 4: Intact SG to Environment Pathway Filter: Removal Data Time (hr) 0.0000E+00 2.0000E+00 8.0000E+00 2.4000E+01
- 4. 5500E+01 Flow Rate (cfm)
- 3. 9420E-01 2.3610E-01 1.7340E-01 1.3980E-01 0.OOOOE+00 Filter Efficiencies (%)
Aerosol Elemental Organic 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 LOCATION DATA Location Exclusion Area Boundary is in compartment 2
Xcel...
- r. yl Calculation No. GEN-PI-082 Revision No. 0 Page No. 92 of 145 Location X/Q Data Time (hr) 0.0000E+00 7.2000E+02 Location Breathing Time (hr) 0.0000E+00 7.2000E+02 X/Q (s
- m^-3) 6.4900E-04 0.OOOOE+00 Rate Data Breathing Rate (m^3
- sec^-l) 3.5000E-04 C.0OOOE+00 Location Low Population Zone is in compartment 2
Location X/Q Data Time (hr)
X/
0.0000E+00 8.000OE+00 2.4000E+01 9.6000E+01 7.2000E+02 Location Breathing Rat Time (hr)
Br 0.0000E+00 8.0000E+00 2.4000E+01 7.2000E+02 Location Control Room Location X/Q Data Time (hr)
X/
- 0. 0000E+00
- 2. 0000E+00
- 8. 0000E+00
- 2. 4000E+01
- 9. 6000E+01
- 7. 2000E+02 Location Breathing Rat Time (hr)
Brc 0.0000E+00 7.2000E+02 Location Occupancy Fa Time (hr)
Occ 0.OOOOE+00 2.4000E+01 9.6000E+01 7.2000E+02 USER SPECIFIED TIME STEP D]
Time Time 0.OOOOE+00 1.0(
2.0000E+00 5.0(
8.0000E+00 1.0(
2.4000E+01 2.0(
9.6000E+01 4.0(
7.2000E+02 0.0 (s
- m^-3) 1.7700E-04 3.9900E-05 7.1200E-06 1.0400E-06 0.OOOE+00 te Data eathing Rate (m^3
- 3.5000E-04 1.8000E-04 2.3000E-04 0.OOOOE+00 sec^-l) is in compartment 3
(s
- m^-3) 1.9300E-02 1.5700E-02 7.0400E-03 4.8700E-03 3.8600E-03 0.0000E+00
-e Data eathing Rate (m^3
- sec^-l) 3.5000E-04 0.0000E+00 ctor Data cupancy Factor 1.0000E+00 6.OOOOE-01
- 4. OOOE-01 0.OOOOE+00 kTA -
SUPPLEMENTAL TIME STEPS step 0OOE-01 0OOE-01 000E+00 0OOE+00 0OOE+00 0OOE+00
XceIEnergyl Calculation No. GEN-PI-082 Revision No. 0 No.93 of 145
- 4#########4####*#############*#####################4#######
RADTRAD Version 3.03 (Spring 2001) run on 6/22/2010 at 1:22:00 M##
- ý#ý#########*#############*#######################*#####
Dose, Detailed model and Detailed Inventory Output
- t###########4###############################4 Exclusion Area Boundary Doses:
Time (h) =
0.0036 Delta dose (rem)
Accumulated dose (rem)
Whole Body 5.8932E-09 5.8932E-09 Low Population Zone Doses:
Time (h)
=
0.0036 Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Time (h)
=
0.0036 Delta dose (rem)
Accumulated dose (rem)
Whole B'ody 1.6072E-09 1.6072E-09 Whole Body 1.5647E-11 1.5647E-11 Thyroid 1.2177E-06
- 1. 2177E-06 Thyroid
- 3. 3211E-07
- 3. 3211E-07 Thyroid
- 9. 1356E-08
- 1. 2107E-08 TEDE
- 2. 9041E-09
- 2. 9041E-09 Atoms
- 2. 3821E+09
- 4. 1028E+07 5.2084E+08 2.4448E+07 1.5802E+08
- 5. 1861E+04
- 4. 3401E+04 Control Room Compartment Nuclide Inventory:
Time (h)
=
0.0036 1-131 1-132 1-133 1-134 1-135 Xe-133 Xe-135 Control Room Transport Time (h)
=
0.0036 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Time (h)
=
0.0036 Noble gases (atoms)
Ci
- 6. 4241E-08
- 9. 2826E-08 1.3030E-07 1. 4512E-07 1.2440E-07 2 1439E-12 2 4846E-11 kg
- 5. 1818E-16
- 8. 9929E-18
- 1. 1503E-16
- 5. 4401E-18
- 3. 5424E-17
- 1. 1454E-20 9.7293E-21 Decay 2 1455E+04
- 3. 1013E+04 4.3520E+04 4.8515E+04 4.1553E+04 1.3719E-01
- 1. 5897E+00 Group Inventory:
Atmosphere Sump 1.0475E+05 0.OOOOE+00 3.0326E+09 0.OOOOE+00 9.3793E+07 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid)
- 5. 1968E-17
- 6. 6375E-17 5.5690E-07 Deposition Surfaces 0.OOOOE+00 Recirculating Filter 0.OOOOE+00
Xce iEnergy Calculation No. GEN-PI-082 Revision No. 0 Page No.94 of 145 Elemental I (atoms)
Organic I (atoms)
Aerosols (kg) 0.0000E+00 o.OOOOE+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Environment to Control Room Transport Group Inventory:
Time (h) 0.0036 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Transported 1.9527E+04 3.0382E+09 9.3964E+07 0.OOOOE+00 Control Room to Environment Transport Group Inventory:
Time (h) 0.0036 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 4.1615E+01 5.7518E+06 1.7789E+05 0.OOOOE+00 Exclusion Area Boundary Doses:
Time (h) =
0.0833 Whole Body Delta dose (rem) 9.0457E-06 Accumulated dose (rem) 9.0516E-06 Transported 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Thyroid 1.8710E-03 1.8722E-03 Thyroid 5.1026E-04 5.1060E-04 Thyroid 4.1229E-03 4.1230E-03 Low Population Zone Doses:
Time (h) =
0.0833 Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Time (h) =
0.0833 Delta dose (rem)
Accumulated dose (rem)
Whole Body 2.4670E-06 2.4686E-06 Whole Body 7.0545E-07 7.0546E-07 TEDE
- 3. 4804E+12
- 5. 8538E+10
- 7. 5916E+ll
- 3. 3549E+10
- 2. 2902E+ll
- 1. 1341E+07 2.0262E+09 6.0575E+07
- 1. 6921E+09 2.9636E+08 Control Room Compartment Nuclide Inventory:
Time (h) 0.0833 1-131 1-132 1-133 1-134 1-135 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Control Room Transport Time (h) =
0.0833 Noble gases (atoms)
Ci 9.3860E-05 1.3244E-04 1.8993E-04 1.9914E-04 1.8030E-04 2.0664E-10 8.3760E-08 6.0028E-09 9.6868E-07
- 6. 0519E-06 kg 7.5709E-13 1.2831E-14
- 1. 6766E-13 7.4650E-15
- 5. 1340E-14 2.4670E-18
- 4. 4748E-16 1.3378E-17 3.7932E-16
- 6. 6436E-17 Decay 9.9658E+08 1.4231E+09 2.0190E+09 2.1822E+09 1.9221E+09 7.3283E+01 2.9737E+04 2.1305E+03 3.4362E+05 1.9490E+06 Group Inventory:
Atmosphere Sump 4.0865E+09 0.OOOOE+00
XceI Energy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 95 of 145 Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Time (h)
=
0.0833 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg) 4.4238E+12 0.0000E+00 1.3682E+ll 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid)
- 7. 5842E-14
- 9. 6646E-14 7.9567E-04 Deposition Surfaces 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 Recirculating Filter 0.OOOOE+00 0.0000E+00 0.0000E+00 O.OOOOE+00 Environment to Control Room Transport Group Inventory:
Time (h)
=
0.0833 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 1.4419E+08 4.6709E+12 1.4446E+ll 0.0000E+00 Control Room to Environment Transport Group Inventory:
Time (h)
=
0.0833 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 7.3007E+06 2.3600E+ll 7.2989E+09 0.0000E+00 Exclusion Area Boundary Doses:
Time (h) =
2.0000 Whole Body Delta dose (rem) 3.4995E-03 Accumulated dose (rem) 3.5085E-03 Transported 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Thyroid 1.0945E+00 1.0963E+00 Thyroid 2.9849E-01 2.9900E-01 Thyroid 2.0292E+00 2.0333E+00 Low Population Zone Doses:
Time (h) =
2.0000 Whole Body Delta dose (rem) 9.5440E-04 Accumulated dose (rem) 9.5687E-04 TEDE 3.7896E-02 3.7965E-02 TEDE 1.0335E-02 1.0354E-02 TEDE 6.3990E-02
- 6. 4121E-02 Control Room Doses:
Time (h)
=
2.0000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 2.2941E-04 2.3011E-04 Control Room Compartment Nuclide Inventory:
Time (h) 1-131 1-132 1-133 1-134 2.0000 Ci 2.0876E-03 1.6647E-03 3.9904E-03 9.7986E-04 kg
- 1. 6839E-11 1.6127E-13, 3.5226E-12
- 3. 6731E-14 Atoms
- 7. 7410E+13
- 7. 3575E+ll
- 1. 5950E+13
- 1. 6507E+ll Decay
- 2. 6404E+ll 2.5644E+ll 5.1429E+II 2.1818E+ll
Xce Energy Calculation No. GEN-PI-082 Revision No. 0 Page No. 96 of 145 1-135 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m 3.3027E-03 3.0785E-07 1.2148E-04 8.6288E-06 1.4178E-03 1.0528E-03
- 9. 4043E-13
- 3. 6753E-15 6.4902E-13 1. 9230E-14 5.5518E-13 1. 1558E-14
- 4. 1951E+12
- 1. 6896E+10
- 2. 9387E+12
- 8. 7073E+10
- 2. 4766E+12
- 5. 1558E+10 4.4572E+II 2.3100E+07 9.1693E+09 6.5261E+08
- 1. 0870E+lI 1.2181E+1l Control Room Transport Time (h) =
2.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Time (h)
=
2.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Group Inventory:
Atmosphere Sump 5.5708E+12 0.OOOOE+00 9.5502E+13 0.OOOOE+00 2.9537E+12 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid)
- 1. 6463E-12
- 2. 0191E-12 1.2025F-02 Deposition Surfaces 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Recirculating Filter 0.OOOOE+00 2.8959E+14 8.9565E+12 0.OOOOE+00 Environment to Control Room Transport Group Inventory:
Time (h) =
2.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 Transported 5.5976E+12 4.1240E+14 1.2755E+13 0.OOOOE+00 Control Room to Environment Transport Group Inventory:
Time (h)
=
2.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 8.7134E+lI 2.5639E+13 7.9296E+II O.OOOOE+00 Exclusion Area Boundary Doses:
Time (h) =
8.0000 Whole Body Delta dose (rem) 1.4712E-02 Accumulated dose (rem) 1.8221E-02 Transported 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Thyroid
- 9. 2091E+00 1.0305E+01 Thyroid 2.5116E+00 2.8106E+00 TEDE 3.0162E-01
- 3. 3959E-01 Low Population Zone Doses:
Time (h) =
8.0000 Whole Body Delta dose (rem) 4.0125E-03 Accumulated dose (rem) 4.9693E-03 TEDE 8.2261E-02 9,2615E-02 Control Room Doses:
Time (h) 8.0000 Whole Body Thyroid TEDE
~,XceIEnergy. Calculation No. GEN-PI-082 Revision No. 0 Page No. 97 of 145 Delta dose (rem) 1.1268E-03 Accumulated dose (rem) 1.3569E-03 1.7296E+01
- 1. 9330E+01 Control Room Compartment Nuclide Inventory:
Time (h) 1-131 1-132 1-133 1-134 1-135 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m 8.-0000 Ci 4.4078E-03 5.8880E-04 7.0488E-03 1.8400E-05 3.7980E-03 6.0350E-06 2. 1921E-03 1.5128E-04 1.7000E-02 1.3279E-03 kg
- 3. 5554E-11
- 5. 7042E-14 6.2224E-12 6.8974E-16 1.0815E-12 7.2050E-14 1.1711E-11 3.3714E-13
- 6. 6571E-12 1.4578E-14 5.4003E-01 6.0415E-01 Atoms
- 1. 6345E+14
- 2. 6024E+ll
- 2. 8175E+13 3.0998E+09
- 4. 8243E+12
.3.3122E+11
- 5. 3028E+13
- 1. 5265E+12
- 2. 9696E+13
- 6. 5028E+10 Decay
- 2. 5030E+12 9.5745E+lI 4.3683E+12 3.6836E+ll
- 2. 9500E+12 1.8957E+09 7.0680E+ll
- 4. 9210E+10 6.2798E+12 1.0010E+12 Control Room Transport Time (h)
ý 8.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Time (h)
ý 8.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Group Inventory:
Atmosphere Sump 8.4647E+13 0.0000E+00 1.9081E+14 0.OOOOE+00 5.9012E+12 0.OOOOE+00 0.OOOOE+00 0.0000E+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid)
- 3. 2798E-12
- 3. 8183E-12 1.5862E-02 Deposition Surfaces 0.0000E+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 Recirculating Filter 0.0000E+00 2.7576E+15 8.5287E+13 0.0000E+00 Environment to Control Room Transport Group Inventory:
Time (h)
ý 8.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 0.0000E+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 Transported
- 1. 4646E+14 3.2014E+15 9.9013E+13 0.OOOOE+00 Control Room to Environment Transport Group Inventory:
Time (h)
ý 8.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 6.2170E+13 2.4213E+14 7.4887E+12 0.OOOOE+00 Transported 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Thyroid 5.0157E+01 6.0462E+01 Exclusion Area Boundary Doses:
Time (h)
ý 24.0000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 3.9884E-02 5.8105E-02 TEDE 1.5887E+00 1.9283E+00
.:XcelfnergyjCalculation No. GEN-PI-082 Revision No. 0 Page No. 98 of 145 Low Population Zone Doses:
Time (h)
=
24.0000 Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Time (h) =
24.0000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 2.4520E-03 7.4213E-03 Whole Body 2.0745E-03 3.4315E-03 Thyroid 1.5858E+00 4.3964E+00 Thyroid
- 4. 3959E+01
- 6. 3289E+01 Control Room Compartment Nuclide Inventory:
TEDE 5.1422E-02 1.4404E-01 TEDE 1.3596E+00 1.9638E+00 Atoms
- 1. 5237E+14 2.0689E+09
- 1. 6322E+13
- 8. 8970E+ll
- 1. 3869E+12
- 1. 7720E+14
- 4. 7284E+12
- 3. 2191E+13
- 1. 9414E+10 Time (h) 1-131 1-132 1-133 1-135 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m 24.0000 Ci 4.1091E-03 4.6808E-06 4.0835E-03 7.0042E-04 2.5270E-05 7.3253E-03 4.6857E-04 1.8428E-02 3.9645E-04 kg
- 3. 3144E-11 4.5347E-16
- 3. 6047E-12
- 1. 9945E-13
- 3. 0169E-13
- 3. 9134E-11 1.0443E-12 7.2162E-12 4.3522E-15 Decay 8.7357E+12 1.0896E+12 1.2033E+13 5.3196E+12 2. 9092E+10 9.2674E+12
- 6. 1304E+ll 4.0823E+13 2.2594E+12 Control Room Transport Time (h)
=
24.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Time (h)
=
24.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Group Inventory:
Atmosphere Sump 2.1552E+14 0.OOOOE+00 1.6449E+14 0.OOOOE+00 5.0874E+12 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid)
- 2. 7698E-12
- 3. 0290E-12 8.8976E-03 Deposition Recirculating Surfaces 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Filter 0.OOOOE+00
- 9. 1131E+15 2.8185E+14 0.OOOOE+00 Environment to Control Room Transport Group Inventory:
Time (h) =
24.0000 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
- 8. 9840E+14 1.0104E+16 3.1250E+14 0.OOOOE+00 Control Room to Environment Transport Group Inventory:
Time (h) =
24.0000 Noble gases (atoms)
Pathway Filtered 6.5021E+14 Transported O.OOOOE+00
)
eI c
Ee rgy] Calculation No. GEN-PI-082 Revision No. 0
.Page No.99of 145 Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
- 7. 9963E+14 2.4731E+13 0.OOOOE+00 Exclusion Area Boundary Doses:
Time (h)
=
45.5000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 4.2683E-02 1.0079E-01 Low Population Zone Doses:
0.D0D0E+00 D.OOD0E+00 O.OOOOE+00 Thyroid
- 9. 9349E+01 1.5981E+02 Thyroid 7.1624E-01
- 5. 1127E+00 Thyroid
- 3. 6324E+01
- 9. 9613E+01 Time (h)
=
45.5000 Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Time (h)
=
45.5000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 4.6827E-04 7.8896E-03 Whole Body 9.9707E-04 4.4285E-03 TEDE 3.0909E+00 5.0192E+00 TEDE 2.2444E-02 1.6648E-01 TEDE
- 1. 1155E+00 3.0793E+00 Atoms
- 1. 4603E+14 3.2874E+06 8.2550E+12
- 9. 6650E+10
- 2. 9047E+12
- 2. 7488E+14
- 6. 5845E+12
- 1. 0907E+13
- 2. 0611E+09 Control Room Compartment Nuclide Inventory:
Time (h)
=
1-131 1-132 1-133 1-135 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m 45.5000 Ci
- 3. 9383E-03
- 7. 4379E-09 2.0653E-03
- 7. 6089E-05
- 5. 2925E-05
- 1. 1363E-02
- 6. 5250E-04
- 6. 2441E-03 4.2089E-05 kg
- 3. 1767E-11 7.2058E-19
- 1. 8231E-12 2 1666E-14
- 6. 3185E-13
- 6. 0708E-11
- 1. 4542E-12 2 4451E-12
- 4. 6204E-16 Decay 1.7880E+13 1.0910E+12 1.8567E+13
- 5. 8997E+12 1.2656E+Il 3.2992E+13 2. 0455E+12 6.9107E+13
- 2. 6566E+12 Control Room Transport Time (h)
=
45.5000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Group Inventory:
Atmosphere Sump 2.9528E+14 0.OOOOE+00 1.4975E+14 0.OOOOE+00 4.6315E+12 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid)
- 2. 4675E-12
- 2. 5899E-12 6.0796E-03 Deposition Time (h) =
45.5000 Surfaces Noble gases (atoms) 0.OOOOE+00 Elemental I (atoms) 0.OOOOE+00 Organic I (atoms) 0.OOOOE+00 Aerosols (kg) 0.OOOOE+00 Recirculating Filter 0.OOOOE+00
- 1. 7946E+16 5.5503E+14 0.0000E+00 Environment to Control Room Transport Group Inventory:
Pathway Time (h) =
45.5000 Filtered Transported Noble gases (atoms) 0.OOOOE+00 2.4303E+15
XceI Energ] Calculation No. GEN-PI-082 Revision No. 0 Page No. 100 of 145 Elemental I (atoms)
Organic I (atoms)
Aerosols (kg) o.0000E+00 0.0000E+00 0.OOOOE+00
- 1. 9767E+16
- 6. 1135E+14 0.OOOOE+00 Control Room to Environment Transport Group Inventory:
Time (h)
=
45.5000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 2.0575E+15 1.5745E+15 4.8694E+13 0.OOOE+00 Exclusion Area Boundary Doses:
Time (h) =
96.0000 Whole Body Delta dose (rem) 0.OOOOE+00 Accumulated dose (rem) 1.0079E-01 Transported 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.0000E+00 Thyroid 0.OOOOE+00 1.5981E+02 Thyroid 0.0000E+00 5.1127E+00 Thyroid 7.5698E-01 1.0037E+02 Low Population Zone Doses:
Time (h) =
96.0000 Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Time (h)
=
96.0000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 0.OOOOE+00 7.8896E-03 Whole Body 5.2868E-05
- 4. 4814E-03 TEDE 0.OOOOE+00 5.0192E+00 TEDE 0.OOOOE+00 1.6648E-01 TEDE 2.3228E-02 3.1025E+00 Atoms 9.3648E+05 7.6859E+07 1.2320E+06 8.4528E+04 Control Room Compartment Nuclide Inventory:
Time (h)
Xe-131m Xe-133 Xe-133m Xe-135 96.0000 Ci 1.7063E-11
- 3. 1773E-09 1.2209E-10
- 4. 8390E-11 kg
- 2. 0371E-19 1.6974E-17 2.7210E-19 1.8949E-20 Decay 1.4728E+ll 3.7398E+13 2.2919E+12 7.1065E+13 Control Room Transport Time (h)
=
96.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Time (h)
=
96.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Group Inventory:
Atmosphere Sump 7.9112E+07 0.OOOOE+00 1.7329E-66 0.OOOOE+00 5.3594E-68 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid) 2.7936E-92 2.8259E-92
- 5. 3143E-83 Deposition Surfaces 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Recirculating Filter 0.OOOOE+00 1.8056E+16 5.5844E+14 0.OOOOE+00 Environment to Control Room Transport Group Inventory:
c*EI Energ-] Calculation No. GEN-PI-082 Revision No. 0 Page No. 101 of 145 Time (h)
=
96.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Transported 2.4303E+15 1.9767E+16 6.1135E+14 0.OOOOE+00 Control Room to Environment Transport Group Inventory:
Time (h)
=
96.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 2.3463E+15 1.5841E+15 4.8994E+13 0.OOOOE+00 Exclusion Area Boundary Doses:
Time (h) = 720.0000 Whole Body Delta dose (rem) 0.OOOOE+00 Accumulated dose (rem) 1.0079E-01 Transported 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Thyroid 0.OOOOE+00 1.5981E+02 Thyroid 0.OOOOE+00 5.1127E+00 Thyroid 8.0149E-81 1.0037E+02 Low Population Zone Doses:
TEDE 0.OOOOE+00
Accumulated dose (rem)
Control Room Doses:
Time (h) = 720.0000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 0.OOOOE+00 7.8896E-03 Whole Body 2.0576E-12 4.4814E-03 TEDE
- 2. 0576E-12 3.1025E+00 Control Room Compartment Nuclide Inventory:
Time (h)
= 720.0000 Control Room Transport Time (h)
= 720.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Time (h)
= 720.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Ci kg Atoms Decay Group Inventory:
Atmosphere Sump 7.6339E-74 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 Surfaces 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Recirculating Filter 0.OOOOE+00 1.8056E+16 5.5844E+14 0.OOOOE+00 Environment to Control Room Transport Group Inventory:
XceIEnergy Calculation No. GEN-PI-082 Revision No. 0 Page No. 102 of 145 Time (h) = 720.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 Transported 2.4303E+15 1.9767E+16 6.1135E+14 0.0000E+00 Control Room to Environment Transport Group Inventory:
Time (h)
= 720.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 2.3463E+15 1.5841E+15 4.8994E+13 0.OOOOE+00 Transported 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 840 1-131 Summary
- ý##############4###4#########################4##4###################
Time (hr) 0.000 0.004 0.083 0.400 0.700 1.000 1.300 1.600 1.900 2.000 2.300
- 2. 600 2.900 3.200 3.500 3.800 4.100 4.400 4.700 5.000 5.300 5.600 5.900 6.200 6.500 6.800 7.100 7.400 7.700 8.000 8.300 8.600 RCS 1-131 (Curies) 8.6026E+04 5.5744E+05 5.5727E+05 5.5656E+05 5.5589E+05 5.5522E+05 5.5455E+05 5.5388E+05 5.5321E+05 5.5299E+05 5.5232E+05 5.5166E+05 5.5099E+05 5.5033E+05 5.4967E+05 5.4900E+05 5.4834E+05 5.4768E+05 5.4702E+05 5.4636E+05 5.4570E+05 5.4505E+05 5.4439E+05 5.4373E+05 5.4308E+05 5.4243E+05 5.4177E+05 5.4112E+05 5.4047E+05 5.3982E+05 5.3917E+05 5.3852E+05 Environment 1-131 (Curies) 1.2983E-08 3.5326E-06 5.4299E-03 1.2940E-01 3.9723E-01 8.1075E-01 1.3693E+00 2.0723E+00 2.9191E+00 3.2332E+00 3.8549E+00 4.5623E+00 5.3553E+00 6.2334E+00 7.1965E+00 8.2441E+00 9.3760E+00 1.0592E+01 1.1891E+01 1.3274E+01 1.4741E+01 1.6289E+01 1.7921E+01 1.9634E+01 2.1430E+01 2.3307E+01 2.5265E+01 2.7305E+01 2.9425E+01 3.1626E+01 3.3301E+01 3.5036E+01 Control Room 1-131 (Curies) 2.3645E-I0 6.4241E-08 9.3860E-05 2.5553E-04 5.5252E-04
- 8. 9413E-04 1.2496E-03 1.6088E-03 1.9680E-03 2.0876E-03 1.5507E-03 1.4867E-03 1.5808E-03 1.7275E-03
- 1. 8914E-03 2.0607E-03 2.2314E-03 2.4021E-03 2.5724E-03 2.7423E-03 2.9115E-03 3.0801E-03 3.2482E-03 3.4156E-03
- 3. 5825E-03 3.7488E-03
- 3. 9144E-03
- 4. 0795E-03 4.2440E-03
- 4. 4078E-03 2.4964E-03
- 1. 8917E-03
....Xcel ner Calculation No. GEN-PI-082 Revision No. 0 Page No. 103 of 145 8.900 9.200 9.500 9.800 10.100 10.400 24.000 45.500 96.000 720.000 Time (hr) 0.000 0.004 0.083 0.400 0.700 1.000 1.300
- 1. 600
- 1. 900 2.000 2.300
- 2. 600 2.900 3.200 3.500 3.800 4.100 4.400 4.700
- 5. 000 5.300
- 5. 600
- 5. 900 6.200 6.500 6.800 7.100 7.400 7.700 8.000 8.300 8.600 8.900 9.200 9.500 9.800 10.100 10.400 24.000 45.500 96.000 720.000 5.3787E+05 5.3722E+05 5.3657E+05 5.3593E+05 5.3528E+05 5.3463E+05 5.0620E+05 4.6430E+05 3.8727E+05 4.1166E+04
- 3. 6830E+01 3.8682E+01
- 4. 0593E+01 4.2563E+01 4.4591E+01
- 4. 6677E+01 1.9896E+02
- 5. 5831E+02
- 5. 5831E+02
- 5. 5831E+02 1.7248E-03
- 1. 7045E-03
- 1. 7332E-03 1.7783E-03 1.8287E-03
- 1. 8809E-03 4 1091E-03
- 3. 9383E-03 4.7578E-83 0 OOOOE+00 Intact SG 1-131 (Curies) 1.0191E-02 4.2791E-01 1.9364E+01 9.4392E+01 1.6515E+02 2.3559E+02 3.0574E+02 3.7557E+02 4.4510E+02 4.6821E+02 5.3775E+02 6.0705E+02
- 6. 7610E+02
- 7. 4491E+02 8.1347E+02 8.8180E+02 9.4987E+02 1.0177E+03 1.0853E+03 1.1527E+03 1.2198E+03 1.2866E+03 1.3533E+03 1.4197E+03 1.4858E+03 1.5518E+03 1.6175E+03 1.6829E+03 1.7481E+03 1.8131E+03 1.8785E+03 1.9436E+03 2.0086E+03 2.0733E+03 2.1378E+03 2.2021E+03 2.2662E+03 2.3301E+03 5.0141E+03 8.5706E+03 7.1487E+03 7.5988E+02
/
Xcel nergyl Calculation No. GEN-PI-082 Revision No. 0 Page No. 104 of 145 Cumulative Dose Summary
- 4#####################################################
Exclusion Area Bounda Low Population Zone Time (hr) 0.000 0.004 0.083 0.400 0.700 1.000 1.300
- 1. 600
- 1. 900
- 2. 000 2.300 2.600 2.900 3.200 3.500 3.800 4.100 4.400 4.700
- 5. 000 5.300
- 5. 600
- 5. 900 6.200 6.500 6.800 7.100 7.400 7.700
- 8. 000 8.300
- 8. 600
- 8. 900 9.200 9.500 9.800 10.100 10.400 24.000 45.500 96.000 720.000 Thyroid (rem) 0.OOOOE+00 1.2177E-06 1.8722E-03 4.4485E-02 1.3619E-01
- 2. 7724E-01
- 4. 6703E-01
- 7. 0501E-01
- 9. 9064E-01 1.0963E+00
- 1. 3051E+00 1.5418E+00 1.8062E+00
- 2. 0981E+00
- 2. 4172E+00 2.7632E+00
- 3. 1359E+00
- 3. 5351E+00 3.9605E+00 4.4118E+00 4.8889E+00
- 5. 3915E+00
- 5. 9194E+00 6.4724E+00 7.0503E+00 7.6528E+00 8.2798E+00
- 8. 9310E+00 9.6063E+00
- 1. 0305E+01
- 1. 0836E+01
- 1. 1385E+01
- 1. 1950E+01
- 1. 2533E+01 1. 3133E+01
- 1. 3750E+01
- 1. 4383E+01 1.5034E+01
- 6. 0462E+01 1.5981E+02 1.5981E+02
- 4. 4394E-08
- 6. 8244E-05
- 1. 6034E-03
- 4. 8622E-03
- 9. 8142E-03
- 1. 6409E-02
- 2. 4605E-02
- 3. 4368E-02
- 3. 7965E-02 4.5038E-02
- 5. 3016E-02
- 6. 1886E-02
- 7. 1636E-02 8.2256E-02 9.3733E-02
- 1. 0606E-01
- 1. 1922E-01
- 1. 3322E-01
- 1. 4804E-01 1.6366E-01
- 1. 8010E-01
- 1. 9733E-01
- 2. 1534E-01
- 2. 3414E-01 2.5371E-01 2.7405E-01
- 2. 9515E-01
- 3. 1700E-01
- 3. 3959E-01
- 3. 5673E-01 3.7441E-01
- 3. 9262E-01 4.1138E-01
- 4. 3066E-01
- 4. 5047E-01 4.7079E-01 4.9164E-01 1.9283E+00 5.0192E+00 5.0192E+00
- 5. 0192E+00 Thyroid (rem) 0 OOOOE+00
- 3. 3211E-07
- 5. 1060E-04 1.2132E-02
- 3. 7144E-02 7.5610E-02 1.2737E-01 1.9228E-01 2.7017E-01
- 2. 9900E-01 3.5593E-01 4.2048E-01
- 4. 9260E-01
- 5. 7221E-01
- 6. 5923E-01 7.5361E-01
- 8. 5526E-01
- 9. 6412E-01 1.0801E+00 1.2032E+00 1.3333E+00 1.4704E+00
- 1. 6144E+00 1.7652E+00 1.9228E+00
- 2. 0871E+00 2.2581E+00 2.4357E+00
- 2. 6199E+00 2.8106E+00 2.8274E+00 2.8447E+00 2.8626E+00 2.8810E+00 2.9000E+00 2.9195E+00 2.9395E+00 2.9601E+00 4.3964E+00 5.1127E+00 5.1127E+00
- 1. 2107E-08
- 1. 8612E-05 4.3728E-04
- 1. 3261E-03 2.6766E-03 4.4752E-03 6.7105E-03
- 9. 3730E-03 1.0354E-02 1.2283E-02 1.4459E-02
- 1. 6878E-02
- 1. 9537E-02
- 2. 2433E-02 2.5564E-02 2.8925E-02 3.2516E-02
- 3. 6333E-02
- 4. 0373E-02 4.4636E-02
- 4. 9118E-02 5.3816E-02 5.8730E-02 6.3857E-02 6.9195E-02 7.4741E-02 8.-0495E-02 8.6453E-02 9.2615E-02 9.3176E-02 9.3755E-02 9.4350E-02 9.4963E-02 9.5593E-02 9.6240E-02 9.6903E-02 9.7582E-02 1.4404E-01 1.6648E-01 1.6648E-01
(rem) 0.0000E+00 0.OOOOE+00 9.1356E-08 2.9041E-09 4.1230E-03 1.3106E-04 5.8191E-02 1.8468E-03 1.8899E-01 5.9888E-03 4.2483E-01 1.3444E-02 7.7367E-01 2.4454E-02 1.2373E+00 3.9066E-02 1.8154E+00 5.7264E-02 2.0333E+00 6.4121E-02 2.6005E+00 8.1951E-02 3.0814E+00 9.7055E-02 3.5696E+00 1.1237E-01 4.0958E+00 1.2887E-01 4.6701E+00 1.4687E-01 5.2955E+00 1.6645E-01 5.9726E+00 1.8764E-01 6.7015E+00 2.1043E-01 7.4816E+00 2.3482E-01 8.3127E+00 2.6078E-01 9.1942E+00 2.8831E-01 1.0126E+01 3.1739E-01 1.1107E+01 3.4800E-01 1.2137E+01 3.8014E-01 1.3217E+01 4.1378E-01 1.4344E+01 4.4892E-01 1.5520E+01 4.8553E-01 1.6743E+01 5.2362E-01 1.8013E+01 5.6316E-01 1.9330E+01 6.0415E-01 2.0331E+01 6.3530E-01 2.0980E+01 6.5549E-01 2.1521E+01 6.7232E-01 2.2036E+01 6.8834E-01 2.2553E+01 7.0440E-01 2.3079E+01 7.2076E-01 2.3619E+01 7.3754E-01 2.4173E+01 7.5474E-01 6.3289E+01 1.9638E+00 9.9613E+01 3.0793E+00 1.0037E+02 3.1025E+00 1.0037E+02 3.1025E+00
- 4##*#####W##o#######H##########u############r##os######es##########
Worst Two-Hour Doses Exclusion Time (hr) 24.0 Area Boundary Whole Body Thyroid (rem)
(rem) 3.9705E-03 9.2418E+00 TEDE (rem) 2.8753E-01
X e1.
Calculation No. GEN-PI-082 Revision No. 0 Page No. 105 of 145 At tachmrent13.3 3.3 RADTRAD Output File PREAINGO1.oO RADTRAD Version 3.03 (Spring 2001) run on 6/22/2010 at 1:31:24 4####F###############l##e#nf#om##############a#########################
- 4###########################
File information Plant file Inventory file Release file Dose Conversion
= G:\\Radtrad 3.03\\Input\\PI\\GEN-PI-082 Rl\\PREAING01.psf
= g:\\radtrad 3.03\\defaults\\pirearcs def.txt
= g:\\radtrad 3.03\\defaults\\pingp ngrft.txt file
= g:\\radtrad 3.03\\defaults\\pingp-fgll&12.txt it I
- 6696 6
6
- I#
- I#
69#
66#
6 #
6 66 6
6 #
6 6 6 6 6 66666 6
6 9
66 6
6 6
66666 6
6 6
6 6
6 6
6 6
6 69#
66#
66 6
6 6
Radtrad 3.03 4/15/2001 PINGP 1 & 2 Rod Ejection Accident AST Analysis -
Noble Gas Release From Intact SGs Nuclide Inventory File:
g:\\radtrad 3.03\\defaults\\pirearcsdef.txt Plant Power Level:
1.8520E+03 Compartments:
3 Compartment 1:
RCS 3
5.2900E+03 0
0 0
0 0
/
Compartment 2:
Environment 2
0.0000E+00 0
0 0
0 0
Xc, Energy, Calculation No. GEN-PI-082 Revision No. 0 Page No. 106 of 145 Compartment 3:
Control Room 1
6.1315E+04 0
0 1
0 0
Pathways:
3 Pathway 1:
Environment 2
3 2
to Control Room Pathway 2:
Control Room 3
2 2
to Environment Pathway 3:
RCS to En 1
vironment 2
2 End of Plant Model File Scenario Description Name:
Plant Model Filename:
Source Term:
1 1
1.0000E+00 g:\\radtrad 3.03\\defaults\\pingpfgll&12.txt g:\\radtrad 3.03\\defaults\\pingp ng-rft.txt 0.0000E+00 1
0.0000E+00 9.7000E-01 3.0000E-02 1.0000E+00 Overlying Pool:
0 0.0000E+00 0
0 0
0 Compartments:
3 Compartment 1:
0 1
0 0
0 0
0 0
X
-eIn Calculation No. GEN-PI-082 Revision No. 0 Page No. 107 of 145 0
Compartment 2:
0 1
0 0
0 0
0 0
0 Compartment 3:
0 0
0 1
- 3. 6000E+03 3
- 0. 0000E+00 8.330 OE-02 7.2000E+02 0
0 Pathways:
3 Pathway 1:
0 0
0 0
0 1
3
- 0. OOOOE+00
- 8. 3300E-02 7.2000E+/-02 0
0 0
0 0
0 Pathway 2:
0 0
0 0
0 1
3
- 0. 0000E+00 8.3300E-02 7.2000E+02 0
0.OOOOE+00
- 9. 9000E+01 0.OOOOE+00 0.OOOOE+00
- 9. 5000E+01 0.OOOOE+00 0.OOOOE+00
- 9. 5000E+01 0.OOOOE+00 2.OOOOE+03 3.OOOOE+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 U.OO00E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 2.OOOOE+03 3.OOOOE+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.0000E+00
XceI Energy alculation No. GEN-PI-082 Revision No. 0 Page No. 108 of 145 0
0 0
0 Pathway 3:
0 0
0 0
0 1
2 0.0000E+00 3.7600E-02 4.5500E+01 0.0000E+00 0
0 0
0 0
0 Dose Locations:
3 Location 1:
Exclusion Area Boundary 2
1 2
0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 o.OOOOE+00 0.OOOOE+00 0.OOOOE+00 7.2000E+02 1
2 0.OOOOE+00 7.2000E+02 0
6.4900E-04 0.OOOOE+00 3.5000E-04 0.OOOOE+00 Location 2:
Low Population Zone 2
1 5
0.OOOOE+00 8.OOOOE+00
- 2. 4000E+01
- 9. 6000E+01 7.2000E+02 1
4 0.OOOOE+00 8.OOOOE+00 2.4000E+01 7.2000E+02 0
Location 3:
Control Room 3
0 1
1.7700E-04 3.9900E-05
- 7. 1200E-06 1.0400E-06 0.OOOOE+00 3.5000E-04 1.80.00E-04 2.3000E-04 0.OOOOE+00
X. eI Ener::]:Calculation No. GEN-PI-082:Revision:No.:0:Page No. 109 of 145 2
O.000E+00 3.5000E-04 7.2000E+02 O.OOOOE+00 1
4 0.0000E+00 1.0000E+00 2.4000E+01 6.0000E-01 9.6000E+01 4.OOOOE-01 7.2000E+02 0.0000E+00 Effective Volume Location:
1 6
0.0000E+00 1.9300E-02 2.OOOOE+00 1.5700E-02 8.OOOOE+00 7.0400E-03 2.4000E+01 4.8700E-03 9.6000E+01 3.8600E-03 7.2000E+02 0.OOOOE+00 Simulation Parameters:
6 0.0000E+00 1.0000E-01 2.OOOOE+00 5.0000E-01 8.OOOOE+00 1.OOOE+00 2.4000E+01 2.0000E+00 9.6000E+01 4.0OOOE+00 7.2000E+02 O.0000E+00 Output Filename:
G:\\Radtrad 3.o9 1
1 1
0 0
End of Scenario File
XceiEne Calculation No. GEN-PI-082 Revision No. 0 Page No. 110 of 145 RADTRAD Version 3.03 (Spring 2001) run on 6/22/2010 at 1:31:24
- 4###########################################################
Plant Description
- N###d#####################
Number of Nuclides =
60 Inventory Power =
1.0000E+00 MWth Plant Power Level =
1.8520E+03 MWth Number of compartments
=
3 Compartment information Compartment number 1
(Source term fraction 1.0000E+00 Name:
RCS Compartment volume =
5.2900E+03 (Cubic feet)
Compartment type is Normal Pathways into and out of compartment 1
Exit Pathway Number 3: RCS to Environment Compartment number 2
Name: Environment Compartment type is Environment Pathways into and out of compartment 2
Inlet Pathway Number 2: Control Room to Environment Inlet Pathway Number 3: RCS to Environment Exit Pathway Number 1: Environment to Control Room Compartment number 3
Name: Control Room Compartment volume 6.1315E+04 (Cubic feet)
Compartment type is Control Room Removal devices within compartment:
Filter(s)
Pathways into and out of compartment 3
Inlet Pathway Number 1: Environment to Control Room Exit Pathway Number 2: Control Room to Environment Total number of pathways =
3
nerg Calculation No. GEN-PI-082 Revision No. 0 Page No. 111 of 145
- 4#######*##4##########4#4#################4###############4#########
RADTRAD Version 3.03 (Spring 2001) run on 6/22/2010 at 1:31:24
- ý##4######4######4#44###########444#######44####4#######4####4######4##
- 4####4##4#4##44#######4#######*#4###4###4###4*########4#4###ý#####44##4#
Scenario Description
- 4##4####4##4###*#4###4#4#4####444#*#############4##*4#4#4###
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 1.0000E+00 0.OOOOE+00 0 OOOOE+00
- 0. 0000E+00 0 OOOOE+00 0 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.OOOOE+00 0.OOOOE+00 RELEASE MASS (gm)
- 3. 696E+01
- 0. OOOE+00
- 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-83m Kr-85 Kr-85m Kr-87 Kr-88 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 Group Specific Inventory (Ci/MWt) 1 3.487E-02 1
6.280E+00 1
8.036E+01 1
1.575E+02 1
2.097E+02 1
3.941E+00 1
7.027E+02 1
2.157E+01 1
1.545E+02 1
1.499E+02 1
5.734E+02 half life (s)
- 6. 588E+03
- 3. 383E+08
- 1. 613E+04
- 4. 578E+03
- 1. 022E+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. 500E-18
- 1. 190E-16
- 7. 480E-15 4.120E-14
- 1. 020E-13
- 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
- 0. OOOE+00
- 0. OOOE+00
- 0. OOOE+00
- 0. OOOE+00
- 0. OOOE+00
- 0. OOOE+00
- 0. OOOE+00 Daughter none none none none none none none none none none Inhaled Effective (Sv/Bq) 0 OOOE+00 0 OOOE+00 0 OOOE+00 0 OOOE+00 0 OOOE+00 0 OOOE+00 0 OOOE+00 0 OOOE+00 0 OOOE+00 0 OOOE+00 0 OOOE+00 Fraction 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Nuclide Daughter Kr-85m Kr-85 Kr-87 Rb-87 Kr-88 Rb-88 1-131 Xe-131m 1-133 Xe-133m 1-135 Xe-135m Xe-133m Xe-133 Xe-135 Cs-135 Xe-135m Xe-135 Xe-138 Cs-138 Iodine fractions Aerosol Elemental
=
Fraction 0.21 1.00 1.00 0.01 0.03 0.15 1.00 1.00 1.00 1.00 Daughter Fraction none 0.00 none 0.00 none 0.00 none 0.00 Xe-133 0.97 Xe-135 0.85 none 0.00 none 0.00 none 0.00 none 0.00 0.OOOOE+00
- 9. 7000E-01
Xc lý ergyl Calculation No. GEN-PI-082 Revision No. 0 Page No. 112 of 145 Organic
=
3.OOOOE-02 COMPARTMENT DATA Compartment number 1: RCS Compartment number 2: Environment Compartment number 3: Control Room Compartment Filter Data Time (hr) 0.00OOE+00 8.3300E-02 7.2000E+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 0.0000E+00 9.5000E+01 0.0000E+00
(%)
Organic 0.OOOOE+00
- 9. 5000E+01 0.0000E+00 PATHWAY DATA Pathway number 1: Environment to Control Room Pathway Filter: Removal Data Time (hr) 0.0000E+00 8.3300E-02 7.2000E+02 Flow Rate (cfm) 2.OOO0E+03 3.0000E+02 0.OOOE+00 Filter Efficiencies (%)
Aerosol Elemental Organic 0.0000E+00 0.0000E+00 0.0000E+00 0.0O00E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 2: Control Room to Environment Pathway Filter: Removal Data Time (hr) 0.0000E+00 8.3300E-02 7.2000E+02 Flow Rate (c fm) 2.0000E+03 3.0000E+02 0.0000E+00 Filter Efficiencies (%)
Aerosol Elemental Organic 0.0000E+00 0.0000E+00 0.0000E+00 0.OOOOE+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 3: RCS to Environment Pathway Filter: Removal Data Time (hr) 0.0000E+00 4.5500E+01 Flow Rate (cfm) 3.7600E-02 O.O000E+00 Filter Efficiencies (%)
Aerosol Elemental Organic 0.OO0E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 LOCATION DATA Location Exclusion Area Boundary is in compartment 2
Location X/Q Data Time (hr) 0.0000E+00 7.2000E+02 X/Q (s
- m^-3) 6.4900E-04 0.0000E+00
X e nergyl Calculation No. GEN-PI-082 Revision No. 0 Page No. 113 of 145 Location Breathing Rate Data Time (hr)
Breathing Rate (m^3
- sec^-l)
O.OOOOE+00 3.5000E-04 7.2000E+02 0.000E+00 Location Low Population Zone is in compartment 2
Location X/Q Data Time (hr) 0.OOOOE+00 8.OOOOE+00 2.4000E+01 9.6000E+01 7.2000E+02 X/Q (s
- m^-3) 1.7700E-04 3.9900E-05 7.1200E-06 1.0400E-06 0.OOOOE+00 Location Breathing Rate Data Time (hr)
Breathing Rate (m^3
- sec^-l) 0.OOOOE+00 3.5000E-04 8.OOO0E+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.0OOOE+00 Location Control Room is in compartment 3
Location X/Q Data Time (hr)
- 0. OOOE+00
- 2. OOOE+00 8.OOOOE+00 2. 4000E+01
- 9. 6000E+01 7.2000E+02 Location Breathing Time (hr) 0.OOOE+00 7.2000E+02 Location Occupancy Time (hr) 0.OOOOE+00 2.4000E+01 9.6000E+01 7.2000E+02 X/Q (s
- m^-3) 1.9300E-02 1.5700E-02 7.0400E-03 4.8700E-03 3.8600E-03 0.OOOOE+00 Rate Data Breathing Rate (m^3
- sec^-l) 3.5000E-04 0.0000E+00 Factor Data Occupancy Factor 1.0000E+00 6.OOQ0E-01 4.OOG0E-01 0.0000E+00 USER SPECIFIED TIME STEP DATA -
SUPPLEMENTAL TIME STEPS Time Time step 0.0000E+00 1.0000E-01 2.0000E+00 5.0000E-01 8.0000E+00 1.OOOOE+00 2.4000E+01 2.0000E+00 9.6000E+01 4.0000E+00 7.2000E+02 O.0000E+00
Xce#Ener l Calculation No. GEN-Pl-082 Revision No. 0 Page No. 114 of 145 RADTRAD Version 3.03 (Spring 2001) run on 6/22/2010 at 1:31:24
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66#
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6
- 6666 6
6 6
66 66 6
6 6
6 6
6 6
- 6 6
6 6666 6666 6
6#####6####6##6##
6####################66#66
- 6###6 Dose, Detailed model and Detailed Inventory Output
- 66
- 66##########################6##################
Exclusion Area Boundary Doses:
Time (h)
=
0.0036 Delta dose (rem)
Accumulated dose (rem)
Whole Body 2.3048E-04 2.3048E-04 Low Population Zone Doses:
Time (h)
=
0.0036 Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Time (h)
=
0.0036 Delta dose (rem)
Accumulated dose (rem)
Whole Body 6.2859E-05 6.2859E-05 Whole Body
- 6. 6451E-07 6.6451E-07 Thyroid 1.5109E-09 1.5109E-09 Thyroid 4.1206E-10 4.1206E-10 Thyroid 1.5785E-I0 1.5785E-10 TEDE 2.3050E-04 2.3050E-04 TEDE 6.2863E-05 6.2863E-05 TEDE 6.6600E-07 6.6600E-07 Atoms
- 3. 1641E+08
- 2. 9302E+15
- 1. 7865E+12
- 9. 9252E+ll
- 2. 9544E+12
- 2. 1164E+09
- 5. 5885E+12
- 4. 3919E+14
- 5. 6238E+12
- 6. 9742E+12
- 1. 8802E+ll
- 6. 6531E+ll 5 7570E+09 Control Room Compartment Nuclide Inventory:
Time (h)
Kr-83m Kr-85 Kr-8Sm Kr-87 Kr-88 Rb-88 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 Cs-138 0.0036 Ci 8 9974E-07
- 1. 6226E-04 2.0752E-03
- 4. 0615E-03
- 5. 4135E-03
- 3. 7124E-05
- 1. 0183E-04
- 1. 8156E-02 5.5730E-04
- 3. 9926E-03
- 3. 8394E-03 1.4660E-02
- 5. 5823E-05 kg 4.3609E-17 4.1358E-10
- 2. 5216E-13
- 1. 4339E-13
- 4. 3172E-13
- 3. 0927E-16
- 1. 2157E-12
- 9. 6997E-11
- 1. 2420E-12
- 1. 5634E-12
- 4. 2149E-14
- 1. 5246E-13 1 3192E-15 Decay
- 3. 0637E+05 5.5225E+07 7.0642E+08
- 1. 3833E+09
- 1. 8430E+09 1.9104E+06 3.4656E+07
- 6. 1794E+09
- 1. 8968E+08 1.3587E+09 1.3113E+09 5.0083E+09 2.8871E+06
XceI Calculation No. GEN-PI-082 Revision No. 0 Page No. 115 of 145 Control Room Transport Time (h)
=
0.0036 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Time (h)
=
0.0036 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Group Inventory:
Atmosphere Sump 3.3941E+15 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 1.6285E-15 0.OOOOE+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid)'
0.OOOOE+00 0.OOOOE+00 0.0000E+00 Deposition Surfaces 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.0000E+00 Recirculating Filter 0.0000E+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 Environment to Control Room Transport Group Inventory:
Time (h)
=
0.0036 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Transported 3.4021E+15 0.OOOOE+00 0.OOOOE+00 2.1321E-16 ControlRoom to Environment Transport Group Inventory:
Time (h)
=
0.0036 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 7.9749E+12 0.OOOOE+00 0.OOOOE+00 7.4947E-19 Exclusion Area Boundary Doses:
Time (h) =
0.0833 Delta dose (rem)
Accumulated dose (rem)
Whole Body
- 1. 0199E-02 1.0429E-02 Transported 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Thyroid 4.7892E-07 4.8043E-07 Thyroid 1.3062E-07 1.3103E-07 Thyroid 1.0781E-06 1.0783E-06 Low Population Zone Doses:
Time (h) =
0.0833 Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Time (h)
=
0.0833 Delta dose (rem)
Accumulated dose (rem)
Whole Body 2.7815E-03 2.8444E-03 Whole Body 8.1012E-04 8.1078E-04 TEDE 1.0204E-02 1.0434E-02 TEDE 2.7828E-03 2.8456E-03 TEDE 8.2033E-04 8.2099E-04 Control Room Compartment Nuclide Inventory:
Time (h)
Kr-83m 0.0833 Ci kg Atoms 3.6620E-05 1.7749E-15 1.2878E+10 Decay 3.9500E+08
XceI Energy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 116 of 145 Kr-85 Kr-85m Kr-87 Kr-88 Rb-88 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 Cs-138 6.8067E-03 8.5984E-02
- 1. 6313E-01
- 2. 2271E-01 4.3089E-02 4.2706E-03 7.6129E-01 2.3353E-02
- 1. 6736E-01 1.2971E-01 4.8669E-01 5.8422E-02 1.7349E-08 1.0448E-11 5.7591E-12 1.7761E-11 3.5896E-13
- 5. 0986E-11 4.0671E-09 5.2046E-11 6.5534E-11
- 1. 4239E-12 5.0615E-12 1.3807E-12 1.2292E+17
- 7. 4024E+13
- 3. 9865E+13
- 1. 2155E+14
- 2. 4565E+12
- 2. 3439E+14
- 1. 8416E+16
- 2. 3566E+14
- 2. 9234E+14
- 6. 3518E+12
- 2. 2088E+13
- 6. 0250E+12 7.2315E+10 9.1917E+ll 1.7714E+12 2.3893E+12 1.4131E+10 4.5376E+10 8.0898E+12 2.4824E+ll 1.7740E+12 1.5389E+12 5.8261E+12 2.2121E+10 Control Room Transport Time (h)
ý 0.0833 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Time (h)
ý 0.0833 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Group Inventory:
Atmosphere Sump 1.4236E+17 0.0000E+00 0.0000E+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 1.7396E-12 0.OOOOE+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid) 0 0000E+00 0.0000E+00 0.0000E+00 Deposition Surfaces 0.0000E+00 0.0000E+00 0.0000E+00 0.OOOOE+00 Recirculating Filter 0.OOOOE+00 0.0000E+00 0.0000E+00 O.OOOOE+00 Environment to Control Room Transport Group Inventory:
Time (h)
ý 0.0833 Noble gases (atoms)
Elemental'I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 0.OOOOE+00 0.OOOOE+00 O.O000E+00 0.OOOOE+00 Transported 1.5404E+17 0.OOOOE+00 0.OOOOE+00 6.7794E-14 Control Room to Environment Transport Group Inventory:
Time (h)
ý 0.0833 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 1.1666E+16 0.OOOOE+00 0.OOOOE+00 5.2463E-15 Transported 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Thyroid 1.2258E-03 1.2262E-03 Exclusion Area Boundary Doses:
Time (h) 8.0000 Whole Body Delta dose (rem) 3.2576E-01 Accumulated dose (rem) 3.3619E-01 TEDE 3.4164E-01
- 3. 5207E-01 Low Population Zone Doses:
Time (h) ý 8.0000 Whole Body Thyroid TEDE
Xce Enery Calculation No. GEN-PI-082 Revision No. 0 Page No. 117 of 145 Delt a dose
)
I I
Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Time (h)
=
8.0000 Delta dose (rem)
Accumulated dose (rem) 8.8843E-02
- 9. 1687E-02 Whole Body 1.3442E-01 1.3523E-01 3.3430E-04 3.3443E-04 Thyroid
- 6. 8217E-03 6.8227E-03 Control Room Compartment Nuclide Inventory:
Time (h)
Kr-83m Kr-85 Kr-85m Kr-87 Kr-88 Rb-88 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Cs-138 8.0000 Ci
- 9. 4164E-06
- 3. 5106E-02
- 1. 3029E-01
- 1. 1244E-02
- 1. 6636E-01 9.8270E-02 2.1607E-02 3.7638E+00
- 1. 0849E-01 4.8255E-01 2.9754E-10 7.2261E-06 kg 4.5640E-16
- 8. 9481E-08 1.5832E-11
- 3. 9696E-13 1.3267E-11
- 8. 1866E-13 2.5796E-10 2. 0108E-08 2.4179E-10
- 1. 8896E-10 3.2664E-21 1.7077E-16 9.3175E-02 9.6020E-02 TEDE 2.3252E-01 2. 3334E-01 Atoms
- 3. 3114E+09
- 6. 3396E+17
- 1. 1216E+14
- 2. 7478E+12
- 9. 0790E+13
- 5. 6024E+12
- 1. 1858E+15
- 9. 1045E+16
- 1. 0948E+15
- 8. 4292E+14
- 1. 4571E+04 7.4522E+08 Decay 3.9449E+i0 2.9153E+13 1.9388E+14 1.1526E+14 3.6445E+14 1.4520E+14 1.8092E+13
- 3. 1833E+15
- 9. 4288E+13 5.2648E+14 1.1948E+13
- 2. 0072E+13 Control Room Transport Time (h)
=
8.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Time (h) =
8.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Group Inventory:
Atmosphere Sump 7.2833E+17 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 8.1883E-13 0.OOOOE+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid) 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 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 5.4602E-11 Environment to Control Room Transport Group Inventory:
Time (h)
=
8.0000 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 2.0698E+18 0.OOOOE+00 0.OOOOE+00 2.3167E-11 Control Room to Environment Transport Group Inventory:
Time (h)
=
8.0000 Noble gases (atoms)
Elemental I (atoms)
Pathway Filtered 1.3370E+18 0.OOOOE+00 Transported 0.OOOOE+00 0.OOOOE+00
XceIEnergy Calculation No. GEN-PI-082 Revision No. 0 Page No. 118 of 145 Organic I (atoms)
Aerosols (kg) 0.OOOOE+00
- 4. 6014E-12
.Exclusion Area Boundary Doses:
Time (h) =
24.0000 Whole Body Delta dose (rem) 8.9098E-02 Accumulated dose (rem) 4.2528E-01 Low Population Zone Doses:
0.0000E+00 0.0000E+00 Thyroid 1.8876E-04
- 1. 4150E-03 Thyroid 5.9683E-06 3.4040E-04 Thyroid 1.2262E-03 8.0489E-03 Time (h)
=
24.0000 Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Time (h)
=
24.0000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 5.4777E-03 9.7165E-02 Whole Body 4.2212E-02 1.7744E-01 TEDE 9.2212E-02 4.4429E-01 TEDE 5.5761E-03 1.0160E-01 TEDE 6.2439E-02 2.9578E-01 Control Room Compartment Nuclide Inventory:
Time (h)
=
24.0000 Kr-83m Kr-85 Kr-85m Kr-87 Kr-88 Rb-88 Xe-131m Xe-133 Xe-133m Xe-135 Control Room Transport Time (h)
=
24.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Time (h)
=
24.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Ci 1.0554E-08 1.6860E-02 5.2637E-03 8.8083E-07 1.6091E-03 4. 3154E-03
- 9. 9821E-03 1.6592E+00 4.2188E-02 6.8419E-02 kg
- 5. 1155E-19 4.2973E-08 6.3961E-13
- 3. 1097E-17 1.2833E-13 3.5950E-14 1.1917E-10 8.8641E-09 9.4021E-11 2.6792E-11 Atoms 3.7116E+06 3.0446E+17
- 4. 5316E+12
- 2. 1525E+08 8.7820E+11 2.46028+11 5.4785E+14
- 4. 0136E+16 4.2572E+14 1.1951E+14 Decay 4.1982E+10 7.2713E+13 2.6253E+14 1.1748E+14 4.2793E+14
- 1. 6512E+14 4.4446E+13 7.6803E+15 2.1709E+14 8.9725E+14 Group Inventory:
Atmosphere Sump 3.4569E+17 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 3.5950E-14 0.0000E+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid) 0.0000E+00 0.0000E+00 0.0000E+00 Deposition Surfaces 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Recirculating Filter 0.0000E+00 0.0000E+00 0.0000E+00 6.0950E-11 Environment to Control Room Transport Group Inventory:
Time (h)
=
24.0000 Noble gases (atoms)
Pathway Filtered 0.0000E+00 Transported 3.6903E+18
XOeIEnhergy] Calculation No. GEN-PI-082 Revision No. 0
ýPage No. 119 of 145 Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0.OOOOE+00 0.OOOOE+00
- 2. 4528E-11 Control Room to Environment Transport Group Inventory:
Time (h)
=
24.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 3.3351E+18 0.0000E+00 0.0000E+00 5.1357E-12 Exclusion Area Boundary Doses:
Time (h) =
45.5000 Whole Body Delta dose (rem) 4.4986E-02 Accumulated dose (rem) 4.7027E-01 Transported 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 Thyroid 7.4677E-06 1.4225E-03 Thyroid 5.3837E-08 3.4045E-04 Thyroid 2.0248E-05 8.0692E-03 Low Population Zone Doses:
Time (h)
=
45.5000 Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Time (h)
=
45.5000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 4.9353E-04 9.7658E-02 Whole Body 7.7445E-03 1.8518E-01 TEDE
- 3. 0385E-01 Atoms
- 2. 0677E+17
- 1. 1056E+ll
- 3. 1383E+09 4.7683E+08
- 3. 5320E+14
- 2. 4285E+16
- 2. 1772E+14
- 1. 5756E+13 Control Room Compartment Nuclide Inventory:
Time (h)
=
45.5000 Kr-85 Kr-85m Kr-88 Rb-88 Xe-131m Xe-133 Xe-133m Xe-135 Control Room Transport Time (h)
=
45.5000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Time (h)
=
45.5000 Noble gases (atoms)
Elemental I (atoms)
Ci
- 1. 1450E-02 1.2842E-04 5.7503E-06 8.3640E-06 6.4355E-03 1.0039E+00 2.1575E-02
- 9. 0197E-03 kg 2.9184E-08 1.5605E-14 4.5859E-16
- 6. 9678E-17
- 7. 6832E-11 5.3635E-09 4.8083E-11 3.5320E-12 Decay 1.0769E+14 2.6593E+14 4.2864E+14 1.6520E+14 6.4648E+13 1.0939E+16 2.9376E+14
- 9. 6965E+14 Group Inventory:
Atmosphere Sump 2.3164E+17 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 6.9678E-17 0.OOOOE+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid) 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Deposition Surfaces 0.OOOOE+00 0.OOOOE+00 Recirculating Filter 0.OOOOE+00 0.OOOOE+00
XcelEnergyl Calculation No. GEN-PI-082 Revision No. 0 TPage No. 120 of 145 Organic I (atoms)
Aerosols (kg) 0.OOOOE+00 o.OOOOE+00 o.OOOOE+00
- 6. 1004E-11 Environment to Control Room Transport Group Inventory:
Time (h) ý 45.5000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 Transported 5.1659E+18 0.0000E+00 0.0000E+00 2.4565E-11 Control Room to Environment Transport Group Inventory:
Time (h) ý 45.5000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 4.9213E+18 0.0000E+00 0.0000E+00 5.1403E-12 Exclusion Area Boundary Doses:
Time (h) ý 96.0000 Whole Body Delta dose (rem) 0.0000E+00 Accumulated dose (rem) 4.7027E-01 Transported 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 Thyroid 0.OOOOE+00 1.4225E-03 Thyroid 0.OOOOE+00 3.4045E-04 Thyroid 3.0412E-08 8.0692E-03 TEDE 0.OOOOE+00 4.894 OE-01 Low Population Zone Doses:
Time (h)
ý 96.0000 Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Time (h)
ý 96.0000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 0.00O0E+00 9.7658E-02 Whole Body 9.2880E-04 1.8611E-01 TEDE 0.OOOOE+00 1. 0209E-01 TEDE 9.2930E-04
- 3. 0478E-01 Atoms
- 7. 5312E+10
- 1. 1385E+08
- 6. 7341E+09 4.0733E+07 1.2207E+05 Control Room Compartment Nuclide Inventory:
Time (h)
Kr-85 Xe-131m Xe-133 Xe-133m Xe-135 96.0000 Ci 4.1705E-09 2.0744E-09 2.7838E-07 4.0365E-09
- 6. 9879E-11 kg 1.0630E-14 2.4766E-17 1.4872E-15
- 8. 9959E-18 2.7364E-20 Decay 1.1221E+14 6.7167E+13 1.1328E+16
- 3. 0191E+14 9.7248E+14 Control Room Transport Time (h) ý 96.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Group Inventory:
Atmosphere Sump 8.2201E+10 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 2.0576E-28 0.OOOOE+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid) 0.OOOOE+00 0.0000E+00 0.OOOOE+00
XceI Energ Calculation No. GEN-PI-082 Revision No. 0 Page No. 121 of 145 Time (h)
=
96.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Deposition Surfaces 0.0000E+00 0.0000E+00 0.OOOOE+00 0.0000E+00 Recirculating Filter 0.0000E+00 0.0000E+00 0.0000E+00 6.1005E-11 Environment to Control Room Transport Group Inventory:
Time (h)
=
96.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Transported 5.1659E+18 0.0000E+00 0.0000E+00 2.4565E-11 Control Room to Environment Transport Group Inventory:
Time (h)
=
96.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 5.1525E+18 0.OOOOE+00 0.OOOOE+00 5.1403E-12 Exclusion Area Boundary Doses:
Time (h) = 720.0000 Whole Body Delta dose (rem) 0.OOOOE+00 Accumulated dose (rem) 4.7027E-01 Transported 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Thyroid 0.OOOOE+00 1.4225E-03 Thyroid 0.OOOOE+00 3.4045E-04 Thyroid 4.4692E-20 8.0692E-03 Low Population Zone Doses:
Time (h)
= 720.0000 Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Time (h)
= 720.0000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 0.OOOOE+00 9.7658E-02 Whole Body 1.6200E-10 1.8611E-01 TEDE 0.OOOOE+00 4.8940E-01 TEDE 0.OOOOE+00 1. 0209E-01 TEDE 1. 6200E-10
- 3. 0478E-01 Control Room Compartment Nuclide Inventory:
Time (h)
= 720.0000 Control Room Transport Time (h)
= 720.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Ci kg Atoms Decay Group Inventory:
Atmosphere Sump 2.0891E-69 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 4.1234-174 0.OOOOE+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid) 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00
XcelEnergy alculation No. GEN-PI-082 Revision No. 0 Page No. 122 of 145 Time (h)
= 720.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Deposition Surfaces 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.0000E+00 Recirculating Filter 0.0000E+00 0.0000E+00 0.0000E+00 6.1005E-11 Environment to Control Room Transport Group Inventory:
Time (h)
= 720.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 Transported 5.1659E+18 0.0000E+00 0.OOOOE+00 2 4565E-11 Control Room to Environment Transport Group Inventory:
Time (h) = 720.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 5.1525E+18 0.0000E+00 0.0000E+00 5.1403E-12 Transported 0.OOOOE+00 0.0000E+00 0.0000E+00 0.0000E+00 840
- 4###4#4####4###########4##4#4###4#4##1###1Sm#########mr 1-131 Summary
- 4###########################################
Time (hr)
- 0. 000
- 0. 004 0.083 0.400 0.700 1.000 1.300
- 1. 600
- 1. 900 2.200 2.500 2.800
- 3. 100 3.400 3.700
- 4. 000 4.300 4.600 4.900 5.200 5.500 5.800 6.100 RCS 1-131 (Curies)
- 0. 0000E+00 0 OOOOE+00 0 OOOOE+00
- 0. 0000E+00
- 0. 0000E+00 0 OOOOE+00
- 0. 0000E+00 0 OOOOE+00 0 OOOOE+00 0 OOOOE+00 0 OOOOE+00 0 OOOOE+00
- 0. 0000E+00
- 0. 0000E+00 0 OOOOE+00
- 0. 0000E+00
- 0. 0000E+00 0 OOOOE+00 0 OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.0000E+00 Environment 1-131 (Curies) 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOE+00 0 OOOOE+00 0 OOOOE+00
- 0. 0000E+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 0 OOOOE+00 0 OOOOE+00 Control Room 1-131 (Curies) 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00
XceI Energy:
Calculation No. GEN-PI-082 Revision No. 0 Page No. 123 of 145 6.400 6.700 7.000 7.300 7.600 7.900 8.000 8.300 8.600 8.900 9.200 9.500 9.800 10.100 10.400 24.000 45.500 96.000 720.000 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 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 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 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00
- 0. 0000E+00 0 OOOOE+00 0 OOOOE+00 0 OOOOE+00
- 0. 0000E+00
- 0. 0000E+00 0 OOOOE+00 0 OOOOE+00
- 0. 0000E+00 0 OOOOE+00
- 0. 0000E+00 0 OOOOE+00 0 OOOOE+00 0 OOOOE+00 0 OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00
- 0. 0000E+00 Cumulative Dose Summary
[M#####################I Bounda Low Population Zone TEDE Thyroid TEDE Exclusion Area Time Thyroid (hr) 0.000 0.004 0.083 0.400 0.700 1.000 1.300 1.600 1.900 2.200 2.500 2.800 3.100 3.400 3.700 4.000 4.300 4.600 4.900 5.200 5.500 5.800 6.100 6.400 6.700 7.000 7.300 7.600 7.900 8.000 (rem) 0.OOOOE+00 1.5109E-09 4.8043E-07
- 9. 4106E-05
- 2. 3310E-04 3.6898E-04 4.8694E-04
- 5. 8544E-04
- 6. 6709E-04
- 7. 3525E-04
- 7. 9291E-04
- 8. 4245E-04 8.8566E-04
- 9. 2386E-04 9.5802E-04 9.8884E-04 1.0169E-03
- 1. 0425E-03
- 1. 0660E-03
- 1. 0876E-03
- 1. 1076E-03
- 1. 1261E-03
- 1. 1432E-03
- 1. 1591E-03
- 1. 1738E-03
- 1. 1874E-03
- 1. 2001E-03
- 1. 2118E-03 1.2228E-03 1.2262E-03 (rem) 0.0000E+00 2.3050E-04 1.0434E-02 5.0407E-02 8.4698E-02
- 1. 1445E-01
- 1. 3999E-01
- 1. 6202E-01
- 1. 8122E-01
- 1. 9814E-01
- 2. 1323E-01
- 2. 2683E-01
- 2. 3918E-01
- 2. 5047E-01
- 2. 6087E-01
- 2. 7047E-01
- 2. 7939E-01
- 2. 87 68E-01
- 2. 9541E-01
- 3. 0263E-01
- 3. 0939E-01
- 3. 1573E-01
- 3. 2168E-01
- 3. 2727E-01
- 3. 3253E-01
- 3. 3749E-01
- 3. 4216E-01
- 3. 4657E-01
- 3. 5074E-01
- 3. 5207E-01 (rem) 0.OOOOE+00 4.1206E-10 1.3103E-07 2.5665E-05 6.3573E-05 1.0063E-04 1.3280E-04 1.5967E-04 1.8193E-04 2.0052E-04 2.1625E-04 2.2976E-04 2.4154E-04
- 2. 5196E-04
- 2. 6128E-04 2.6968E-04 2.7733E-04 2.8431E-04 2.9072E-04 2.9662E-04 3.0207E-04 3.0711E-04 3.1178E-04 3.1610E-04
- 3. 2012E-04 3.2384E-04 3.2729E-04 3.3050E-04 3.3348E-04 3.3443E-04 (rem) 0.OOOOE+00 6.2863E-05 2.8456E-03 1.3747E-02 2.3099E-02
- 3. 1212E-02
- 3. 8180E-02 4.4188E-02 4.9424E-02 5.4039E-02 5.8154E-02
- 6. 1862E-02
- 6. 5230E-02
- 6. 8311E-02 7.1146E-02 7.3766E-02
- 7. 6196E-02 7.8457E-02 8..0565E-02 8.2535E-02 8.4380E-02
- 8. 6108E-02 8.7731E-02 8.9256E-02
- 9. 0691E-02 9.2042E-02 9.3316E-02
(rem) 0.OOOOE+00 0.OOOOE+00 1.5785E-I0 6.6600E-07 1.0783E-06 8.2099E-04 3.8418E-04 1.1736E-02 9.5227E-04 2.5007E-02 1.5056E-03 3.8518E-02 1.9983E-03 5.1677E-02 2.4345E-03 6.4448E-02 2.8276E-03 7.6885E-02 3.1834E-03 8.8897E-02 3.5015E-03 1.0023E-01 3.7950E-03 1.1103E-01 4.0694E-03 1.2134E-0l 4.3273E-03 1.3119E-01 4.5703E-03 1.4059E-01 4.7993E-03 1.4954E-01 5.0153E-03 1.5806E-01 5.2189E-03 1.6616E-01 5.4107E-03 1.7386E-01 5.5912E-03 1.8116E-01 5.7610E-03 1.8809E-01 5.9205E-03 1.9466E-01 6.0703E-03 2.0089E-01 6.2109E-03 2.0678E-01 6.3426E-03 2.1237E-01 6.4660E-03 2.1766E-01 6.5815E-03 2.2266E-01 6.6895E-03 2.2740E-01 6.7906E-03 2.3189E-01 6.8227E-03 2.3334E-01
,XcelEnergy Calculation No. GEN-PI-082 Revision No. 0 Page No. 124 of 145 8.300
- 8. 600
- 8. 900 9.200 9.500 9.800
- 10. 100 10.400 24.000 45.500 96.000 720. 000 1.2361E-03 1.2453E-03 1.2539E-03 1.2618E-03 1.2692E-03 1.2761E-03 1.2824E-03 1.2884E-03 1.4150E-03 1.4225E-03 1.4225E-03 1.4225E-03 3.5594E-01
- 3. 5961E-01
- 3. 6308E-01
- 3. 6638E-01
- 3. 6951E-01
- 3. 7248E-01
- 3. 7531E-01
- 3. 7801E-01 4.4429E-01
- 4. 8940E-01
- 4. 8940E-01
- 4. 8940E-01 3.3474E-04 3.3503E-04 3.3530E-04 3.3555E-04 3.3579E-04 3.3600E-04 3.3620E-04 3.3639E-04 3.4040E-04 3.4045E-04 3.4045E-04 3.4045E-04
- 9. 6253E-02
- 9. 6474E-02
- 9. 6683E-02
- 9. 6882E-02 9.7071E-02
- 9. 7251E-02 9.7422E-02 9.7584E-02
- 1. 0160E-01
- 1. 0209E-01
- 1. 0209E-01
- 1. 0209E-01
- 6. 9109E-03
- 6. 9879E-03
- 7. 0565E-03 7.1177E-03 7 1726E-03 7.2219E-03 7.2662E-03
- 7. 3061E-03 8.0489E-03 8.0692E-03 8.0692E-03 8.0692E-03
- 2. 3737E-01 2 4099E-01 2 4426E-01 2.4723E-01
- 2. 4993E-01
- 2. 5240E-01
- 2. 5465E-01
- 2. 5672E-01 2. 9578E-01
- 3. 0385E-01
- 3. 0478E-01
- 3. 0478E-01 Worst Two-Hour Doses Exclusion Time (hr) 0.0 Area Boundary Whole Body Thyroid (rem)
(rem) 1.7920E-01 6.8981E-04 TEDE (rem)
- 1. 8686E-01
XceIEnergyl Calculation No. GEN-PI-082 Revision No. 0 Page No. 125 of 145 3.4 RADTRAD Output File PREAINLQ01.oO
- 4###################################################################4#
RADTRAD Version 3.03 (Spring 2001) run on 6/22/2010 at 1:35:31
- 44#########4#####4#######4##4###4444#######4##4###############44#4####4
- 4#####4#####4##44##4##ý#4444####4###4###44#############4#########
File information
- 4#####4########4####4##4####4####4#######4#4####4########4#4####4#####4 Plant file
= G:\\Radtrad 3.03\\Input\\PI\\GEN-PI-082 Rl\\PREAINLQ01.psf Inventory file
= g:\\radtrad 3.03\\defaults\\pirea liq def.txt Release file
= g:\\radtrad 3.03\\defaults\\pingp-iodine_rft.txt Dose Conversion file
= g:\\radtrad 3.03\\defaults\\pingpfgll&12.txt
- 4#
- 6###
- 666 4
- 4###
- 4##
Radtrad 3.03 4/15/2001 PINGP 1 & 2 Rod Ejection Accident AST Analysis -SG Liquid Iodine Released From Intact SGs Nuclide Inventory File:
g:\\radtrad 3.03\\defaults\\pirea_liq_def.txt Plant Power Level:
1.8520E+03 Compartments:
3 Compartment 1:
Intact SG 3
3.4380E+03 0
0 0
0 0
Compartment 2:
Environment 2
0.0000E+00 0
0 0
0 0
Xce Energy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 126 of 145 Compartment 3:
Control Room 1
6.1315E+04 0
0 1
0 0
Pathways:
3 Pathway 1:
Intact SG to 1
2 2
Environment Pathway 2:
Environment 2
3 2
to Control Room Pathway 3:
Control Room to Environment 3
2 2
End of Plant Model File Scenario Description Name:
Plant Model Filename:
Source Term:
1 1
1.0000E+00 g:\\radtrad 3.03\\defaults\\pingpfgll&12.txt g:\\radtrad 3.03\\defaults\\pingp iodine rft.txt o.0000E+00 1
0.OOOOE+00 9.7000E-01 3.OOOOE-02 1.0000E+00 Overlying Pool:
0 0.OOOOE+00 0
0 0
0 Compartments:
3 Compartment 1:
0 1
0 0
0 0
0 0
~.XcelEnergyl Calculation No. GEN-PI-082 Revision No. 0 Page No. 127 of 145 0
Compartment 2:
0 1
0 0
0 0
0 0
0 Compartment 3:
1 1
0 0
0 0
1 3.6000E+03 3
0.0000E+00 8.3300E-02 7.2000E+02 0
0 Pathways:
3 Pathway 1:
0 0
0 0
0 1
5 0.0000E+00 2.OOOOE+00 8.0000E+00 2.4000E+01
- 4. 5500E+01 0
0 0
0 0
0 Pathway 2:
0 0
0 0
0 1
3 0.0000E+00 8.3300E-02 0.0000E+00
- 9. 9000E+01 0.OOOOE+00 0.0000E+00
- 9. 5000E+01 0.0000E+00 0.OOOOE+00
- 9. 5000E+01 0.0000E+00
- 3. 9420E-01 2. 3610E-01 1.7340E-01 1.3980E-01 0.OOOOE+00 2.0000E+03 3.OOOOE+02 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+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 0.0000E+00 0.OOOOE+00
Xce lEnergy Calculation No. GEN-PI-082 Revision No. 0 Page No. 128 of 145 7.2000E+02 0
0 0
0 0
0 Pathway 3:
0 0
0 0
0 1
3 0.OOOOE+00 8.3300E-02 7.2000E+02 O.OOOOE+00 O.0000E+00 0.OOOOE+00 0.OOOOE+00 2.0000E+03 3.OOOOE+02 0.0000E+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 o.OOOOE+00 o.OOOOE+00 0
0 0
0 0
0 Dose Locations:
3 Location 1:
Exclusion Area Boundary 2
1 2
0.OOOOE+00 7.2000E+02 1
2 0.OOOOE+00 7.2000E+02 0
6.4900E-04 0.OOOOE+00 3.5000E-04 0.OOOOE+00 Location 2:
Low Population Zone 2
1 5
0.OOOOE+00 8.OOOOE+00
- 2. 4000E+01
- 9. 6000E+01 7.2000E+02 1
4 0.OOOOE+00 8.OOOOE+00 2.4000E+01 7.2000E+02 0
Location 3:
Control Room 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
XceI0 Energy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 129 of 145 3
0 1
2 0.OO00E+00 7.2000E+02 1.4 3.5000E-04 0.OOCE+00 0.0OOOE+00 1.0000E+00 2.4000E+01 6.0O00E-01 9.6000E+01 4.OOOE-01 7.2000E+02 0.0OOOE+00 Effective Volume Location:
1 6
0.OOOOE+00 1.9300E-02 2.OCOE+00 1.5700E-02 8.OOOOE+00 7.0400E-03 2.4000E+01 4.8700E-03 9.6000E+01 3.8600E-03 7.2000E+02 0.0OO0E+00 Simulation Parameters:
6 0.0000E+00 1.0OO0E-01 2.OOOE+00 5.0OO0E-01 8.OOO0E+00 1.OOOE+00 2.4000E+01 2.0OOOE+00 9.6000E+01 4.0OO0E+00 7.2000E+02 0.OOOE+00 Output Filename:
G:\\Radtrad 3.olO 1
1 1
0 0
End of Scenario File I
XceI.nergyl Calculation No. GEN-PI-082 Revision No. 0 Page No. 130 of 145
- 0####4#####
RADTRAD Version 3.03 (Spring 2001) run on 6/22/2010 at 1:35:31
- 4############44############################4###################
Plant Description
- 44###########4######4############4###########4############4######4 Number of Nuclides =
60 Inventory Power =
1.0000E+00 MWth Plant Power Level =
1.8520E+03 MWth Number of compartments 3
Compartment information Compartment number 1
(Source term fraction =
1.OOOOE+00 Name: Intact SG Compartment volume =
3.4380E+03 (Cubic feet)
Compartment type is Normal Pathways into and out of compartment 1
Exit Pathway Number 1: Intact SG to Environment Compartment number 2
Name: Environment Compartment type is Environment Pathways into and out of compartment 2
Inlet Pathway Number 1: Intact SG to Environment Inlet Pathway Number 3: Control Room to Environment Exit Pathway Number 2: Environment to Control Room Compartment number 3
Name: Control Room Compartment volume =
6.1315E+04 (Cubic feet)
Compartment type is Control Room Removal devices within compartment:
Filter(s)
Pathways into and out of compartment 3
Inlet Pathway Number 2: Environment to Control Room Exit Pathway Number 3: Control Room to Environment Total number of pathways 3
XceiE*ner gy Calculation No. GEN-PI-082 Revision No. 0 Page No. 131 of 145 RADTRAD Version 3.03 (Spring 2001) run on 6/22/2010 at 1:35:31
- 4###4####*#*#############O####*####*#4###4###4###########4##44#######
Scenario Description Radioactive Decay is enabled Calculation of Daughters is enabled Release Fractions and Timinqs NOBLES IODINE CESIUM TELLURIUM STRONTIUM BARIUM RUTHENIUM CERIUM LANTHANUM GAP 0.003600 hr 0.OOOOE+00 1.OOOOE+00 0.0000E+00 0.00OOE+00 0.OOOOE+00 0.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.OOOOE+00 0.OOOOE+00 RELEASE MASS (gm)
- 0. OOOE+00 8.142E-05
- 0. 0OOE+00
- 0. OOOE+00
- 0. OOOE+00
- 0. OOOE+00
- o. OOOE+00 O. OOOE+O0 O. OOOE+00 Inventory Power =
1852.
MWt Nuclide Group Specific Name 1-131 1-132 1-133 1-134 1-135 Nuclide 1-131 1-133 1-135 2
2 2
2 2
Inventory (Ci/MWt) 4.500E-03 4.940E-03 6.846E-03 1.027E-03 3.882E-03 half Whole Body life DCF (s)
(Sv-m3/Bq-s) 6.947E+05 1.820E-14 8.280E+03 1.120E-13 7.488E+04 2.940E-14 3.156E+03 1.300E-13 2.380E+04 8.294E-14 Inhaled Thyroid (Sv/Bq)
- 2. 920E-07 1.740E-09
- 4. 860E-08
- 2. 880E-10
- 8. 460E-09 I
Daughter none none none Inhaled Effective (Sv/Bq) 8.890E-09 1.030E-10 1.580E-09 3.550E-11 3.320E-10 Fraction 0.00 0.00 0.00 Daughter Xe-131m Xe-133m Xe-135m Fraction 0.01 0.03 0.15 Daughter none Xe-133 Xe-135 Fractior 0.00 0.97 0.85 Iodine fractions Aerosol Elemental Organic COMPARTMENT DATA
=
.OOOOE+00
= 9.7000E-0l
=
3.OOOOE-02 Compartment number Compartment number Compartment number 1: Intact SG 2: Environment 3: Control Room Compartment Filter Data Time (hr)
Flow Rate Filter Efficiencies
%)
IeEnergy Calculation No. GEN-PI-082 Revision No. 0 Page No. 132 of 145 0.OOOE+00 8.3300E-02 7.2000E+02 (cfm) 3.6000E+03 3.6000E+03 3.6000E+03 Aerosol 0.OOOOE+00
- 9. 9000E+01 o.OOOE+00 Elemental 0.OOOE+00 9.5000E+01 0.OOOOE+00 Organic 0.OOO0E+00
- 9. 5000E+01 0.OOOOE+00 PATHWAY DATA Pathway number 1: Intact SG to Environment Pathway Filter: Removal Data Time (hr) 0.0000E+00 2.OOO0E+00 8.0000E+00 2.4000E+01
- 4. 5500E+01 Flow Rate (c fm)
- 3. 9420E-01 2.3610E-01 1.7340E-01 1.3980E-01 0.0000E+00 Filter Efficiencies (%)
Aerosol Elemental Organic 0.OOOOE+00 0.0000E+00 O.0000E+00 0.OOOOE+00 0.0000E+00 O.0000E+00 0.OOOOE+00 0.0000E+00 O.0000E+00 O.0000E+00 0.0000E+00 O.OOOOE+00 O.0000E+00 0.0000E+00 O.OOOOE+00 Pathway number 2: Environment to Control Room Pathway Filter: Removal Data Time (hr) 0.0000E+00 8.3300E-02 7.2000E+02 Flow Rate (cfm) 2.OOOOE+03 3.OOOOE+02 0.0000E+00 Filter Efficiencies (%)
Aerosol Elemental Organic O.OOOOE+00 O.0000E+00 O.OOOOE+00 O.OOOOE+00 O.0000E+00 O.OOOOE+00 O.OOOOE+00 0.0000E+00 O.OOOOE+00 Pathway number 3: Control Room to Environment Pathway Filter: Removal Data Time (hr) 0.OOOOE+00 8.3300E-02 7.2000E+02 Flow Rate (c fm) 2.OOOOE+03 3.OOOOE+02 0.OOOOE+00 Filter Efficiencies (%)
Aerosol Elemental Organic 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 O.OOOE+00 O.0000E+00 0.0000E+00 0.0000E+00 LOCATION DATA Location Exclusion Area Boundary is in compartment 2
Location X/Q Data Time (hr) 0.0000E+00 7.2000E+02 X/Q (s
- m^-3) 6.4900E-04 0.OOOOE+00 Location Breathing Rate Data Time (hr)
Breathing Rate (m^3
- sec^-l) 0.0000E+00 3.5000E-04 7.2000E+02 0.0000E+00 Location Low Population Zone is in compartment 2
Location X/Q Data Time (hr)
X/Q (s
- m^-3) 0.OOOOE+00 1.7700E-04 8.0000E+00 3.9900E-05
XcelEnergyl Calculation No. GEN-PI-082 Revision No. 0 Page No. 133 of 145 2.4000E+01
- 9. 6000E+01 7.2000E+02 7.1200E-06 1.0400E-06 0.0O00E+00 Location Breathing Rate Data Time (hr)
Breathing Rate (m^3
- sec^-l) 0.OO0E+00 3.5000E-04 8.0000E+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.0000E+00 Location Control Room is in compartment 3
Location X/Q Data Time (hr)
X/Q (s
- m^-3) 0.0000E+00 1.9300E-02 2.0000E+00 1.5700E-02 8.0000E+00 7.0400E-03 2.4000E+01 4.8700E-03 9.6000E+01 3.8600E-03 7.2000E+02 0.OOOOE+00 Location Breathing Rate Data Time (hr)
Breathing Rate (m^3
- sec^-l) 0.OOOOE+00 3.5000E-04 7.2000E+02 0.OOOOE+00 Location Occupancy Factor Data Time (hr)
Occupancy Factor 0.OOOOE+00 1.OO0E+00 2.4000E+01 6.OOOOE-01 9.6000E+01 4.OOOOE-01 7.2000E+02 0.0000E+00 USER SPECIFIED TIME STEP DATA -
SUPPLEMENTAL TIME STEPS Time Time step 0.0000E+00 1.OOOOE-01 2.0000E+00 5.OOOOE-01 8.0000E+00 1.OOODE+00 2.4000E+01 2.OOOOE+00 9.6000E+01 4.OOOOE+00 7.2000E+02 0.OOOOE+00
0 XceI Ener l Calculation No. GEN-PI-082 Revision No. 0 Page No. 134 of 145
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Exclusion Area Boundary Doses:
Time (h) =
0.0036 Whole Body Delta dose (rem) 7.1130E-08 Accumulated dose (rem) 7.1130E-08 Low Population Zone Doses:
Time (h)
=
0.0036 Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Time (h)
=
0.0036 Delta dose (rem)
Accumulated dose (rem)
Whole Body 1.9399E-08 1.9399E-08 Whole Body 2.0506E-10 2.0506E-10 Thyroid 3.2544E-05 3.2544E-05 Thyroid 8.8756E-06 8.8756E-06 Thyroid
- 2. 6510E-06
- 2. 9619E-07
- 2. 9619E-07 TEDE 8.2880E-08 8.2880E-08 Atoms
- 6. 9548E+10 9.0907E+08
- 1. 1404E+10
- 7. 1909E+07 2.0545E+09 1.0827E+06 3.2368E+04 5.3798E+05
- 9. 4816E+04 Control Room Compartment Nuclide Inventory:
Time (h) 1-131 1-132 1-133 1-134 1-135 Xe-133 Xe-133m Xe-135 Xe-135m 0.0036 Ci 1.8756E-06 2.0568E-06
- 2. 8531E-06 4.2684E-07 1.6174E-06 4.4756E-II 3.2076E-12
- 3. 0798E-10 1.9362E-09 kg 1.5129E-14
- 1. 9926E-16 2.5186E-15
- 1. 6001E-17
- 4. 6056E-16 2.3911E-19
- 7. 1485E-21 1.2060E-19 2.1255E-20 Decay 6.3836E+05 7.0029E+05 9.7109E+05 1.4542E+05 5.5056E+05 2.3079E+00
- 1. 6540E-01 1.5880E+01 9.9579E+01 Control Room Transport Time (h)
=
0.0036 Noble gases (atoms)
Elemental I (atoms)
Group Inventory:
Atmosphere Sump 1.7559E+06 0.0000E+00 8.1468E+10 0.0000E+00
XcelEnergyl Calculation No. GEN-PI-082 Revision No. 0 Page No. 135 of 145 Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Time (h)
=
0.0036 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg) 2.5196E+09 O.OOOOE+00 O.0000E+00 O.OOOOE+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid)
- 1. 3881E-15
- 1. 6439E-15 8.8298E-06 Deposition Surfaces 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 Recirculating Filter 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 Environment to Control Room Transport Group Inventory:
Time (h)
=
0.0036 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 2.2901E+05 8.1663E+10 2.5256E+09 0.OOOOE+00 Control Room to Environment Transport Group Inventory:
Time (h) =
0.0036 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 8.0504E+02
- 1. 9142E+08 5.9203E+06 0.0000E+00 Exclusion Area Boundary Doses:
Time (h) =
0.0833 Whole Body Delta dose (rem) 3.1469E-06 Accumulated dose (rem) 3.2180E-06 Transported 0.0000E+00 0.0000E+00 0.OOOOE+00 0.0000E+00 Thyroid 1.4405E-03 1.4731E-03 Thyroid 3.9287E-04 4. 0174E-04 Thyroid 3.2332E-03 3.2358E-03 Low Population Zone Doses:
Time (h)
=
0.0833 Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Time (h)
=
0.0833 Delta dose (rem)
Accumulated dose (rem).
Whole Body 8.5824E-07 8.7763E-07 Whole Body 2.4996E-07 2.5016E-07 TEDE 4.8070E-05
- 2. 9158E+12
- 3. 7219E+10 4.7699E+ll
- 2. 8315E+09
- 8. 5443E+10 Control Room Compartment Nuclide Inventory:
Time (h) 1-131 1-132 1-133 1-134 1-135 0.0833 Ci 7.8635E-05 8.4209E-05 1. 1933E-04 1.6807E-05 6.7266E-05 kg 6.3429E-13
- 8. 1581E-15
- 1. 0534E-13
- 6. 3004E-16
- 1. 9154E-14 Decay 8.3555E+08 9.0549E+08 1.2695E+09 1.8432E+08 7.1764E+08
XceI Energy] Calculation No. GEN-PI-082 Revision No. 0 age No. 136 of 145 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m 1.7311E-10 5.2625E-08
- 3. 7714E-09
- 3. 6138E-07 2.2577E-06
- 2. 0667E-18
- 2. 8114E-16
- 8. 4051E-18 1.4151E-16
- 2. 4785E-17
- 9. 5010E+06 1.2730E+09 3.8058E+07
- 6. 3125E+08
- 1. 1056E+08
- 6. 1307E+01 1.8657E+04 1.3367E+03 1.2801E+05 7.2607E+05 Control Room Transport Time (h)
=
0.0833 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Time (h)
=
0.0833 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Group Inventory:
Atmosphere Sump 2.0624E+09 0.0000E+00 3.4128E+12 0.0000E+00 1.0555E+ll 0.0000E+00 0.0000E+00 0.0000E+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid)
- 5. 8151E-14
- 6. 8799E-14 3.6625E-04 Deposition Surfaces 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Recirculating Filter 0.OOOOE+00 0.0000E+00 0.0000E+00 0.0000E+00 Environment to Control Room Transport Group Inventory:
Time (h)
=
0.0833 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Transported 7.3077E+07 3.6964E+12 1.1432E+ll 0.OOOOE+00 Control Room to Environment Transport Group Inventory:
Time (h)
=
0.0833 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 5.6557E+06 2.7997E+ll 8.6589E+09 0.0000E+00 Exclusion Area Boundary Doses:
Time (h) =
2.0000 Whole Body Delta dose (rem) 6.1929E-05 Accumulated dose (rem) 6.5147E-05 Transported 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Thyroid 3.3982E-02 3.5456E-02 Thyroid 9.2679E-03 9.6697E-03 Thyroid 9.1548E-02 Low Population Zone Doses:
Time (h)
=
2.0000 Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Time (h)
=
2.0000 Delta dose (rem)
Whole Body 1.6890E-05 1.7767E-05 Whole Body 6.0682E-06 TEDE
- 1. 1195E-03
- 1. 1686E-03 TEDE
- 3. 0531E-04 3.1872E-04 TEDE 2.8555E-03
ft XceI Energy] Calculation No. GEN-PI-082 I
Revision No. 0 1Page No. 137 of 145 Accumulated dose (rem) 6.3183E-06 9.4784E-02 2.9566E-03 Control Room Compartment Nuclide Inventory:
Time (h) 1-131 1-132 1-133 1-134 1-135 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m 2.0000 Ci 4.2260E-05 2.5574E-05
- 6. 0580E-05
- 1. 9982E-06 2.9772E-05
- 8. 4455E-09
- 2. 5056E-06
- 1. 7784E-07 1.7433E-05
- 1. 0500E-05 kg 3.4088E-13 2.4776E-15
- 5. 3478E-14 7.4906E-17
- 8. 4776E-15 1.0083E-16 1.3386E-14
- 3. 9633E-16
- 6. 8264E-15 1.1526E-16 Atoms
- 1. 5670E+12
- 1. 1303E+10
- 2. 4214E+lI 3.3664E+08
- 3. 7817E+10 4.6352E+08
- 6. 0610E+10 1.7946E+09
- 3. 0451E+10
- 5. 1417E+08 Decay 1.2809E+10 1.0873E+10 1.8966E+10 1.5796E+09 1.0089E+10 9.2525E+05 2.7653E+08 1.9686E+07 1.9638E+09 2.3630E+09 Control Room Transport Time (h)
=
2.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Time (h) =
2.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Group Inventory:
Atmosphere Sump 9.3834E+10 0.0000E+00 1.8029E+12 0.OOOOE+00 5.5759E+I0 0.OOOOE+00 0.0000E+00 0.OOOOE+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid)
- 3. 0733E-14
- 3. 5643E-14
- 1. 6018E-04 Deposition Surfaces 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.0000E+00 Recirculating Filter 0.0000E+00 1.3188E+13 4.0788E+11 0.0000E+00 Environment to Control Room Transport Group Inventory:
Time (h)
=
2.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.0000E+00 Transported 8.9104E+10 1.6481E+13 5.0974E+ll 0.0000E+00 Control Room to Environment Transport Group Inventory:
Time (h) =
2.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 2.2206E+10 1.4368E+12 4.4438E+10 0.0000E+00 Transported 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Thyroid 5.9825E-02 9.5281E-02 Exclusion Area Boundary Doses:
Time (h) =
8.0000 Whole Body Delta dose (rem) 6.5830E-05 Accumulated dose (rem) 1.3098E-04 TEDE 1.9181E-03 3.0867E-03
XceI Energy a lclto No
-PI-082 Revision No. 0 Page No. 138 of 145 Low Population Zone Doses:
Time (h) =
8.0000 Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Time (h) =
8.0000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 1.7954E-05 3.5721E-05 Whole Body 5.4739E-06 1.1792E-05 Thyroid
- 1. 6316E-02 2.5986E-02 Thyroid
- 1. 2280E-01
- 2. 1758E-01 TEDE 5.2312E-04
- 8. 4184E-04 Control Room Compartment Nuclide Inventory:
Time (h) 1-131 1-132 1-133 1-134 1-135 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m
=
8.0000 Ci 1.9628E-05 1.9899E-06 2.3540E-05 8.2544E-09 7.5314E-06 3.4484E-08 9.4543E-06
- 6. 5118E-07
- 4. 3561E-05 2.6948E-06 kg 1.5833E-13 1. 9277E-16
- 2. 0780E-14
- 3. 0942E-19 2.1446E-15
- 4. 1170E-16
- 5. 0509E-14 1.4513E-15 1.7058E-14 2.9583E-17 TEDE 3.8080E-03 6.7646E-03 Atoms
- 7. 2783E+lI 8.7948E+08
- 9. 4092E+10 1.3906E+06 9.5666E+09 1.8926E+09
- 2. 2870E+ll
- 6. 5712E+09
- 7. 6092E+10
- 1. 3196E+08 Decay
- 2. 9519E+10 1.5797E+10
- 4. 0991E+10 1.7666E+09 1.9035E+10 1.6894E+07 4.7994E+09 3.3478E+08
- 2. 6736E+10 5.7300E+09 Control Room Transport Time (h)
=
8.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Group Inventory:
Atmosphere Sump 3.1339E+ll 0.OOOOE+00 8.0740E+ll 0.OOOOE+00 2.4971E+10 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid)
- 1. 3694E-14
- 1. 5332E-14 5.2698E-05 Time (h) =
Noble gases Elemental I Organic I (at Aerosols (kg)
Deposition 8.0000 Surfaces atoms) 0.OOOOE+00 atoms) 0.OOOOE+00 oms) 0.OOOOE+00 0.OOOOE+00 Recirculating Filter 0.OOOOE+00 3.0922E+13 9.5635E+ll 0.OOOOE+00 Environment to Control Room Transport Group Inventory:
Time (h)
=
8.0000 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 6.4994E+l1 3.4827E+13 1.0771E+12 0.OOOOE+00 Control Room to Environment Transport Group Inventory:
Time (h)
=
8.0000 Noble gases (atoms)
Pathway Filtered 3.6532E+Il Transported O.OOOOE+00
.XceIEnergy Calculation No. GEN-PI-082 Revision No. 0 Page No. 139 of 145 Elemental I (atoms)
Organic I (atoms)
Aerosols (kg) 2. 9924E+12
- 9. 2549E+10 0.0000E+00 Exclusion Area Boundary Doses:
Time (h)
=
24.0000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 6.0338E-05 1.9132E-04 Low Population Zone Doses:
0.0000E+00 0.0000E+00 0.0000E+00 Thyroid
- 1. 0266E-01
- 1. 9794E-01 Thyroid 3.2459E-03 2.9232E-02 Thyroid 9.3346E-02
- 3. 1093E-01 Time (h)
=
24.0000 Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Time (h)
=
24.0000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 3.7095E-06 3.9431E-05 Whole Body 3.0810E-06 1.4873E-05 TEDE
- 2. 1555E+ll
- 2. 2211E+06
- 1. 7316E+10 5.6048E+08 2.2190E+09
- 2. 1378E+ll 5.6954E+09
- 2. 3053E+10 1.2283E+07 Control Room Compartment Nuclide Inventory:
Time (h)
=
24.0000 1-131 1-132 1-133 1-135 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Control Room Transport Time (h) =
24.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Time (h)
=
24.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Ci
- 5. 8129E-06 5.0253E-09 4.3323E-06 4.4124E-07 4.0431E-08 8.8376E-06 5.6440E-07 1.3197E-05 2.5082E-07 kg
- 4. 6888E-14
- 4. 8685E-19 3.8244E-15 1.2564E-16 4.8270E-16 4.7214E-14 1.2578E-15
- 5. 1678E-15 2.7534E-18 Decay 4.2972E+10
- 1. 6119E+10
- 5. 3977E+10 2.1698E+10 8.3379E+07 2.1028E+10 1.4097E+09 7.1052E+10 7.0707E+09 Group Inventory:
Atmosphere Sump 2.4476E+ll 0.OOOOE+00 2.2642E+ll 0.OOOOE+00 7.0027E+09 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid)
- 3. 7706E-15
- 4. 0362E-15
- 1. 0591E-05 Deposition Surfaces 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Recirculating Filter 0.OOOOE+00 4.4561E+13 1.3782E+12 0.OOOOE+00 Environment to Control Room Transport Group Inventory:
Time (h) =
24.0000 Noble gases (atoms)
Pathway Filtered 0.OOOOE+00 Transported 1.6925E+12
XdeIEnergy Calculation No. GEN-PI-082 Revision No. 0 Page No. 140 of 145 Elemental I (atoms)
Organic I (atoms)
Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 0.0000E+00 4.9110E+13 1.5189E+12 0.OOOOE+00 Control Room to Environment Transport Group Inventory:
Time (h)
=
24.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 1.4317E+12
- 4. 1888E+12 1.2955E+11 0.OOOOE+00 Exclusion Area Boundary Doses:
Time (h)
=
45.5000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 3.2882E-05 2.2420E-04 Transported 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Thyroid 9.2798E-02 2.9074E-01 Thyroid 6.6901E-04 2.9901E-02 Thyroid 3.4434E-02 3.4536E-01 TEDE 2.8753E-03
- 9. 1819E-03 Low Population Zone Doses:
Time (h)
=
45.5000 Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Time (h)
=
45.5000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 3.6074E-07 3.9791E-05 Whole Body 6.8006E-07 1.5553E-05 Control Room Compartment Nuclide Inventory:
TEDE 2.0852E-05 9.6630E-04 TEDE 1.0554E-03 1.0696E-02 Atoms
- 1. 0557E+ll
- 4. 4757E+09
- 3. 1116E+07
- 2. 2505E+09
- 1. 6018E+11
- 3. 8341E+09
- 3. 7741E+09
- 6. 6559E+05 Time (h)
=
45.5000 1-131 1-133 1-135 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Control Room Transport Time (h)
=
45.5000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Ci 2.8472E-06
- 1. 1197E-06 2.4496E-08
- 4. 1006E-08
- 6. 6219E-06 3.7995E-07 2.1606E-06 1.3592E-08 kg 2.2966E-14
- 9. 8847E-16
- 6. 9753E-18 4.8956E-16
- 3. 5377E-14 8.4677E-16 8.4605E-16 1.4921E-19 Decay 5.1677E+10 5.8805E+10 2.1973E+10 1.8327E+08 3.9693E+10 2.5427E+09 8.5588E+10 7.2626E+09 Group Inventory:
Atmosphere Sump 1.7004E+11 0.OOOOE+00 1.0678E+11 0.OOOOE+00 3.3025E+09 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid)
- 1. 7476E-15
- 1. 8134E-15
- 3. 9914E-06 Time (h)
=
Noble gases Elemental I 45.5000 (atoms)
(atoms)
Deposition Recirculating Surfaces Filter 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 5.2953E+13
XcelEnergy Calculation No. GEN-PI-082 Revision No. 0 Page No. 141 of 145 Organic I (atoms)
Aerosols (kg) 0.OOOOE+00 0.0000E+00 1.6377E+12 0.0000E+00 Environment to Control Room Transport Group Inventory:
Time (h) =
45.5000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 0.0000E+00 0.0000E+00 0.0000E+00 0.OOOOE+00 Transported 2.7459E+12 5.8207E+13 1.8002E+12 0.0000E+00 Control Room to Environment Transport Group Inventory:
Time (h)
=
45.5000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 2.5317E+12 4.9250E+12 1.5232E+ll 0.0000E+00 Exclusion Area Boundary Doses:
Time (h) =
96.0000 Whole Body Delta dose (rem) 0.OOOOE+00 Accumulated dose (rem) 2.2420E-04 Transported 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Thyroid 0.OOOOE+00
- 2. 9074E-01 Thyroid 0.OOOOE+00 2.9901E-02 Thyroid 5.3616E-04 3.4590E-01 Low Population Zone Doses:
Time (h)
=
96.0000 Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Time (h) =
96.0000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 0.OOOOE+00 3.9791E-05 Whole Body 2.3088E-08 1.5576E-05 TEDE 0.OOOOE+00
- 9. 1819E-03 TEDE
.0.0000E+00 9.6630E-04 TEDE
- 1. 6416E-05 1. 0713E-02 Atoms 4.4788E+04 Control Room Compartment Nuclide Inventory:
Time (h)
=
96.0000 Xe-133 Control Room Transport Time (h)
=
96.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Ci kg 1.8515E-12 9.8915E-21 Group Inventory:
Atmosphere Sump 4.6260E+04 0.OOOOE+00 1.2489E-69 0.OOOOE+00 3.8625E-71 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid)
Decay 4.2260E+10
- 2. 010OE-95 2.0275E-95 3.7413E-86 Deposition Time (h) =
96.0000 Surfaces Noble gases (atoms) 0.OOOOE+00 Recirculating Filter 0.OOOOE+00
Xcel I Vnry Calculation No. GEN-PI-082 Revision No. 0 Page No. 142 of 145 Elemental I (atoms)
Organic I (atoms)
Aerosols (kg) 0.OOOOE+00 0.OOOOE+00 o.OOOOE+00
- 5. 3032E+13
- 1. 6402E+12 0.0000E+00 Environment to Control Room Transport Group Inventory:
Time (h)
=
96.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Transported 2.7459E+12 5.8207E+13 1.8002E+12 O.O000E+00 Control Room to Environment Transport Group Inventory:
Time (h)
=
96.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 2.6984E+12 4.9319E+12 1.5253E+ll 0.0000E+00 Exclusion Area Boundary Doses:
Time (h) = 720.0000 Whole Body Delta dose (rem) 0.OOOOE+00 Accumulated dose (rem) 2.2420E-04 Transported 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Thyroid 0.OOOOE+00
- 2. 9074E-01 Thyroid 0.OOOOE+00 2.9901E-02 Thyroid 5.7668E-84 3.4590E-01 Low Population Zone Doses:
Time (h)
= 720.0000 Delta dose (rem)
Accumulated dose (rem)
Control Room Doses:
Time (h)
= 720.0000 Delta dose (rem)
Accumulated dose (rem)
Whole Body 0.OOOOE+00 3.9791E-05 Whole Body 1.1577E-15 1.5576E-05 TEDE 0.OOOOE+00 9.1819E-03 TEDE 0.OOOOE+00 9.6630E-04 TEDE
- 1. 1577E-15 1. 0713E-02 Control Room Compartment Nuclide Inventory:
Time (h) = 720.0000 Control Room Transport Time (h) = 720.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Dose Effective (Ci/cc)
Dose Effective (Ci/cc)
Total I (Ci)
Time (h)
= 720.0000 Noble gases (atoms)
Ci kg Atoms Decay Group Inventory:
Atmosphere Sump 4.5583E-77 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
'~
~Xce Enhergy Calculation No. GEN-PI-082 Revision No. 0 Page No. 143 of 145 Elemental I (atoms)
Organic I (atoms)
Aerosols (kg) 0.OOOOE+00 o.OOOOE+00 o.OOOOE+00
- 5. 3032E+13
- 1. 6402E+12 0.OOOOE+00 Environment to Control Room Transport Group Inventory:
Time (h)
= 720.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms).
Aerosols (kg)
Pathway Filtered 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Transported 2.7459E+12 5.8207E+13 1.8002E+12 0.OOOOE+00 Control Room to Environment Transport Group Inventory:
Time (h)
= 720.0000 Noble gases (atoms)
Elemental I (atoms)
Organic I (atoms)
Aerosols (kg)
Pathway Filtered 2.6984E+12 4.9319E+12 1.5253E+I1 0.OOOOE+00 Transported 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 840 1-131 Summary
- 4##ý#############################################4##################
Time (hr) 0.000 0.004 0.083 0.400 0.700 1.000 1.300 1.600 1.900 2.000 2.300 2.600 2.900 3.200 3.500 3.800
- 4. 100 4.400 4.700
- 5. 000
- 5. 300
- 5. 600
- 5. 900 6.200 6.500 6.800 7.100 Intact SG 1-131 (Curies) 1.2861E+00 8.3338E+00 8.3268E+00 8.2993E+00 8.2732E+00 8.2473E+00 8.2214E+00 8.1956E+00 8.1699E+00 8.1614E+00 8.1425E+00 8.1237E+00 8.1049E+00 8.0862E+00 8.0675E+00 8.0489E+00 8.0303E+00 8.0117E+00 7.9932E+00 7.9747E+00 7.9563E+00 7.9379E+00 7.9195E+00 7.9012E+00 7.8830E+00 7.8648E+00 7.8466E+00 Environment 1-131 (Curies) 2.4577E-06 1.0320E-04 4.6701E-03 2.2779E-02 3.9878E-02 5.6923E-02 7.3914E-02 9.0853E-02 1.0774E-01 1.1335E-01 1.2343E-01 1.3348E-01 1.4351E-01 1.5352E-01 1.6350E-01 1.7346E-01 1.8339E-01 1.9331E-01 2.0320E-01 2.1306E-01 2.2291E-01 2.3273E-01 2.4253E-01 2.5231E-01 2.6206E-01 2.7179E-01 2.8150E-01 Control Room 1-131 (Curies) 4.4757E-08 1.8756E-06 7.8635E-05 5.4153E-05 4.6564E-05 4.3931E-05 4.2960E-05 4.2546E-05 4.2319E-05 4.2260E-05
- 2. 7784E-05 2.2901E-05 2.1233E-05 2.0643E-05 2.0413E-05 2.0305E-05 2.0238E-05 2.0185E-05 2.0136E-05 2.0088E-05 2.0042E-05 1.9995E-05 1.9949E-05 1.9903E-05 1.9857E-05 1.9811E-05 1.9765E-05
XceIEnergy
~
Cacltoo.
GEN-PI-082 Revision No. 0 Page No. 144 of 145 7.400 7.700 8.000 8.300 8.600 8.900 9.200 9.500 9.800 10.100 10.400 24.000 45.500 96.000 720.000 7.8284E+00
- 7. 8104E+00
- 7. 7923E+00
- 7. 7768E+00
- 7. 7614E+00
- 7. 7460E+00
- 7. 7307E+00
- 7. 7153E+00 7.7000E+00
- 7. 6848E+00
- 7. 6695E+00
- 7. 0093E+00
- 6. 1568E+00
- 5. 1354E+00
- 5. 4587E-01 2 9119E-01 3 0085E-01 3 1049E-01 3.1756E-01 3.2461E-01
- 3. 316SE-01 3.3867E-01
- 3. 4568E-01 3.5268E-01
- 3. 5966E-01
- 3. 6663E-01
- 6. 6804E-01
- 1. 0123E+00
- 1. 0123E+00 1. 0123E+00
- 1. 9720E-05
- 1. 9674E-05
- 1. 9628E-05
- 1. 0862E-05 7. 9156E-06
- 6. 9195E-06
- 6. 5772E-06
- 6. 4541E-06
- 6. 4044E-06
- 6. 3793E-06 6.3625E-06 5.8129E-06
- 2. 8472E-06
- 3. 4397E-86 0 OOOOE+00 Cumulative Dose Summary
- 4##########################################
Exclusion Area Time Thyroid (hr)
- 0. 000
- 0. 004 0.083 0.400 0.700 1.000 1.300 1.600
- 1. 900
- 2. 000 2.300 2.600 2.900 3.200 3.500 3.800 4.100 4.400 4.700 5.000 5.300 5.600 5.900 6.200 6.500 6.800 7.100 7.400 7.700 8.000 8.300 8.600
- 8. 900 9.200 (rem) 0.OOOOE+00 3.2544E-05
- 1. 4731E-03 7.1753E-03 1.2544E-02 1.7882E-02
- 2. 3189E-02 2.8466E-02
- 3. 3713E-02 3.5456E-02 3.8576E-02 4.1682E-02 4.4773E-02 4.7851E-02
- 5. 0914E-02 5.3963E-02 5.6998E-02 6.0020E-02 6.3029E-02 6.6024E-02 6.9006E-02 7.1975E-02 7.4932E-02 7.7876E-02 8.0807E-02
- 8. 3726E-02
- 8. 6633E-02
- 8. 9528E-02
- 9. 2410E-02
- 9. 5281E-02
- 9. 7381E-02
- 9. 9473E-02
- 1. 0156E-01
- 1. 0363E-01 0.0 1.0 4.]
2.3 4.1 5.
7.(
9.4 1.]
1.1 1.2 1.3 1.4 1.5 i.6 1.7 1.8 1.
2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.
2.9 3.0 3.1 3.2 3.2 3.3 Bounda Low Population Zone TEDE Thyroid TEDE (rem)
(rem)
(rem) 0OOOE+00 0.OOOOE+00 0.OOOOE+0(
0860E-06 8.8756E-06 2.9619E-0 9156E-05 4.0174E-04 1.3406E-0*
3890E-04 1.9569E-03 6.5153E-0[
677E-04 3.4212E-03 1.1366E-0*
9291E-04 4.8769E-03 1.6170E-0' 6741E-04 6.3243E-03 2.0929E-0' 4034E-04 7.7635E-03 2.5646E-0' 118E-03 9.194SE-03 3.0322E-0' 686E-03 9.6697E-03 3.1872E-0*
2702E-03 1.0521E-02 3.4643E-0' 3711E-03 1.1368E-02 3.7394E-0' 4713E-03 1.2211E-02 4.0126E-0' 708E-03 1.3050E-02 4.2840E-0 6697E-03 1.3886E-02 4.5537E-0' 7679E-03 1.4717E-02 4.8216E-0*
8656E-03 1.5545E-02 5.0880E-0' 9626E-03 1.6369E-02 5.3527E-0*
0591E-03 1.7190E-02 5.6158E-0' 551E-03 1.8007E-02 5.8775E-0' 2505E-03 1.8820E-02 6.1377E-0' 3454E-03 1.9630E-02 6.3965E-0' 4397E-03 2.0436E-02 6.6538E-0 5336E-03 2.1239E-02 6.9098E-0 6270E-03 2.2038E-02 7.1644E-0' 7198E-03 2.2834E-02 7.4177E-0' 8123E-03 2.3627E-02 7.6698E-0' 9042E-03 2.4417E-02 7.9205E-0' 9957E-03 2.5203E-02 8.1701E-0'
)867E-03 2.5986E-02 8.4184E-0' 533E-03 2.6052E-02 8.4399E-0' 2195E-03 2.6118E-02 8.4614E-0' 2855E-03 2.6184E-02 8.4827E-0' 3512E-03 2.6250E-02 8.5040E-0' 0
7 5
5 4
4 4
4 4
4 4
4 4
4 4
4 4
4 4
4 4
4 4
4 4
4 4
4 4
4 4
4 4
4 Control Room Thyroid TEDE (rem)
(rem) 0.OOOOE+00 0.OOOOE+00 2.6510E-06 8.2880E-08 3.2358E-03 1.0116E-04 2.3725E-02 7.4137E-04 3.8700E-02 1.2089E-03 5.2219E-02 1.6307E-03 6.5203E-02 2.0354E-03 7.7959E-02 2.4328E-03 9.0593E-02 2.8262E-03 9.4784E-02 2.9566E-03 1.0484E-01 3.2695E-03 1.1223E-01 3.4994E-03 1.1871E-01 3.7008E-03 1.2487E-01 3.8921E-03 1.3090E-01 4.0795E-03 1.3687E-01 4.2649E-03 1.4281E-01 4.4490E-03 1.4871E-01 4.6322E-03 1.5459E-01 4.8144E-03 1.6044E-01 4.9958E-03 1.6626E-01 5.1763E-03 1.7206E-01 5.3560E-03 1.7784E-01 5.5348E-03 1.8359E-01 5.7129E-03 1.8931E-01 5.8901E-03 1.9501E-01 6.0666E-03 2.0069E-01 6.2422E-03 2.0634E-01 6.4171E-03 2.1197E-01 6.5912E-03 2.1758E-01 6.7646E-03 2.2172E-01 6.8928E-03 2.2433E-01 6.9732E-03 2.2641E-01 7.0376E-03 2.2832E-01 7.0965E-03
XceI Energy] Calculation No. GEN-PI-082 Revision No. 0 Page No. 145 of 145 9.500 9.800 10.100 10.400 24.000 45.500 96.000 720.000
- 1. 0570E-01
- 1. 0776E-01 1.0982E-01 1 1186E-01
- 1. 9794E-01
- 2. 9074E-01
- 2. 9074E-01
- 2. 9074E-01
- 3. 4166E-03 3 4817E-03
- 3. 5465E-03
- 3. 6111E-03
- 6. 3066E-03
- 9. 1819E-03
- 9. 1819E-03
- 9. 1819E-03 2 6315E-02
- 2. 6380E-02 2.6445E-02
- 2. 6510E-02 2.9232E-02
- 2. 9901E-02
- 2. 9901E-02 2. 9901E-02 8.5251E-04 8.5461E-04 8.5671E-04 8.5879E-04 9.4544E-04 9.6630E-04 9.6630E-04 9.6630E-04 2. 3016E-01 2..3197E-01
- 2. 3377E-01
- 2. 3556E-01
- 3. 1093E-01
- 3. 4536E-01
- 3. 4590E-01
- 3. 4590E-01 7.1534E-03 7.2094E-03 7.2651E-03 7.3204E-03 9.6409E-03 1.0696E-02
- 1. 0713E-02 1.0713E-02 Worst Two-Hour Doses
- ý######################
Exclusion Area Boundary Time Whole Body Thyroid (hr)
(rem)
(rem) 0.0 6.5147E-05 3.5456E-02 TEDE (rem)
- 1. 1686E-03