ML063460131
| ML063460131 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Peach Bottom, Oyster Creek, Byron, Braidwood, Limerick, Clinton, Quad Cities, LaSalle, Crane |
| Issue date: | 12/07/2006 |
| From: | Holland P, Mscisz T, Rao S AmerGen Energy Co, Exelon Nuclear |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| %dam200701, NEI 99-01 EP-EAL-0611, Rev 1 | |
| Download: ML063460131 (126) | |
Text
ATTACHMENT 11 EXELON/AMERGEN RESPONSE TO THE REQUEST FOR ADDITIONAL INFORMATION EP-EAL-0611, Criteria for Choosing Containment Radiation Monitor Reading Indicative of loss of the RCS Barrier
EP-EAL-0611, Rev 1 Page 1 of 4 Criteria for Choosing Containment Radiation Monitor Reading Indicative of loss of the RCS Barrier Date: 10/19/2006 (Document ID## EPnEAL-0611, Rev. 1)
Document Author:
Paul Holland Document Reviewer:
Sam Rao Document Reviewer:
Tom Mscisz 6
Reyiewer:
S
EP-EAL-0611, Rev 1 Page2of 4 Criteria for Choosing Containment Radiation Monitor Reading Indicative of Loss of RCS Barrier
- 1.
- 2.
- 3.
Purpose The purpose of this calculation is to document the logic and assumptions used in choosing the Emergency Action Level (EAL) threshold values for Containment Radiation Monitor Readings corresponding to a Loss of the Reactor Coolant System Fission Product Barrier.
Background
To support the implementation of NEI 99-01 Revision 4 methodology for development of Emergency Action Levels for Exelon stations, it was deemed beneficial to provide additional technical documentation describing the methodology for determining the containment radiation monitor values indicating a loss of the RCS barrier.
The generic guidance provided in NEI 99-01, Revision 4 is not intended to be used by plants as is. The generic guidance is intended to give the logic for developing site-specific IC/EALs (Section 5.3 of NEI 99-01). Plant specific wording and values must be developed. If specific guidance provided in NEI 99-01 Revision 4 cannot be used as presented, documentation must be provided to show how Exelon Corporation implemented the intent of the guidance.
Discussion The Loss of the RCS Fission Product Barrier as indicated by Containment Radiation Monitoring NEI 99-0 1 Revision 4 provides the following guidance:
The (site-specific) reading is a value which indicates the release of reactor coolant to the containment. The reading should be calculated assuming the instantaneous release and dispersal of the reactor coolant noble gas and iodine inventory associated with normal operating concentrations (i.e., within T/S) into the containment atmosphere. This reading will be less than that specified for Fuel Clad Barrier EAL #5. Thus, this EAL would be indicative of an RCS leak only. If the radiation monitor reading increased to that specified by Fuel Clad Barrier EAL #5, fuel damage would also be indicated.
However, if the site specific physical location of the containment radiation monitor is such that radiation from a cloud of released RCS gases could not be distinguished from radiation from nearby piping and components containing elevated reactor coolant activity, this EAL should be omitted and other site specific indications of RCS leakage substituted.
EP-EAL-06 1 1, Rev 1 Page 3 of 4 Calculations were performed to estimate the containment radiation dose rates resulting in a release of all the RCS inventory to the containment atmosphere with the Maximum Technical Specification coolant activity. See Attachment 1 (B WR) and Attachment 2 (PWR) for all assumptions and calculation results.
- 5. References
- a. Software Requirements Specification, Exelon MAROG B WR Core Damage Assessment (BWRCDAM), Version 1.1, February 2005.
- b. Software Requirements Specification, (Exelon Clinton, Dresden, LaSalle, and Quad Cities Core Damage Assessment), Midwest Region BWR CDAM Version 1. O h. 1, December 2002.
- c. Software Requirements Specification, Exelon TMI Core Damage Assessment (TMICDAM), Version 1.O, April 2003.
- d. Software Requirements Specification, (Exelon BraidwoodByron Core Damage Assessment), Midwest Region PWR CDAM Version 1.0/1.1. July 2002.
- e. Federal Guidance Report No. 11 (FGR 1 l), Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion, Second Printing, 1989 (with corrections).
- f. Regulatory Guide 1.183, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors, July 2000.
- g. Micro-Shield Computer Program, Version 5.03.
- h. Calculation Number BYR04-046 & BRW-04-0040-M Rev. 1, Re-analysis of Main Steam Line Break (MSLB) Accident Using Alternative Source Terms
- i. BraidwoodByron Stations UFSAR, Rev. 10, December 2004
- j. Clinton Station UFSAR, Rev. 1 1, January 2005
- k. Dresden Station UFSAR, Rev. 6, June 2005
- 1. LaSalle County Station UFSAR, Rev. 6, April 2006
EP-EAL-0611, Rev 1 Page4of 4
- m. Limerick Station UFSAR, Rev. 12, September 2004
- n. Oyster Creek UFSAR, Update 14, October 2005
- 0. Peach Bottom UFSAR, Rev. 20, April 2005
- p. Quad Cities Station UFSAR, Rev. 8, October 2005
- q. Calculation C-1101-900-E000-087 (TMI), Post-LOCA EAB, LPZ, TSC, and CR Doses Using AST and RG 1.183 Requirements, Rev 1.
- r. NEDO-22215, Procedures for the Determination of the Extent of Core Damage Under Accident conditions, General Electric, August 1982.
EP-EAL-06 1 1, Rev 1 Page 1 BWR Assumptions:
RCS Liquid and Free-Air volumes were obtained from the BWR Core Damage Assessment Model (CDAM) Requirements Specification:
o Mid-Atlantic Version 1.1, Section 7.2.2, Normal System Volumes o Mid-West Version l.O/l.l, Section 7.2.2 Normal System Volumes with the following exceptions:
o None It is assumed the entire Liquid RCS volume is instantaneously released to the Drywell and all entrained Iodine immediately disperses homogeneously throughout the free air space.
Only the Drywell volumes are used in the calculation. Although some of the released material may ultimately find its way into other areas such as the Suppression Pool air volumes, it is assumed the initial release will be confined to only the Drywell space.
The RCS Dose Equivalent 1-131 values of interest (0.2 uCi/gm and 4.0 uCi) were obtained from the sites Technical Specifications and were specifically requested by the Revision 4 EAL implementation team for this calculation. These are standard Technical Specification values for Boiling Water Reactors.
Only isotopes of Iodine were used in the calculation. Although noble gasses will be released to the containment atmosphere, their dose rate contribution is small compared to that of the Iodines because noble gasses in a BWR are only contained within the steam space of the RCS and are continuously being off-gassed. As such, the calculated dose rate will be conservative.
Dose Conversion factors used to calculate Isotopic Concentrations were obtained from FGR 11. Though these factors are for Alternative Source Term (AST) calculations, when normalized to I-13 1 they adequately represent the mixture of Iodines in the coolant. The Dose Conversion Factors from FGR 11 were obtained from Table 2.1, column Effective. The choice of using values from the Effective column was based on the methodology used for AST calculations and section 4.1.2 of Regulator Guide 1.183 which states:
The exposure-to-CEDE factor for inhalation of radioactive material should be derived from data provided in ICRP Publication 30, Limits for Intakes of radionuclides by Workers (Ref. 19). Table 2.1 of Federal
EP-EAL-06 1 1, Rev 1 Page 2 Guidance Report 11, Limiting values of Radionuclide Intake and Air Concentration and Dose Conversion factors for Inhalation, Submersion, and Ingestion (Ref. 20), provides tables of conversion factors acceptable to the NRC staff. The factors in the column headed Efective yield doses corresponding to the CEDE.
Since only the Normalized ratios are used in the calculation, unit conversion is not required, however the international units of SvBq were converted to RedCi for ease of understanding.
Additional calculations were performed using the FGR 1 1 Table 2.1, column Thyroid Dose Conversion Factors for comparison purposes. The calculations were limited to the 4.0 uCi/gm DEI-13 1 values. The results of these calculations are included in the Results table at the end of this attachment.
Microshield Model:
A generic approach was taken when constructing the MicroShield model since each sites actual configuration is different. Even though the entire free air space volume is available for dilution of the released radioactive isotopes, the radiation detectors located within the drywell are not exposed to the entire volume. Therefore a cylindrical source representing the entire drywell was not used. Instead, a box was constructed in the Microshield model that approximates the size of the area that a detector would be exposed to. The box measured 20 feet in depth (distance from the vessel support wall to the drywell wall), 40 feet tall, and 40 feet wide.
Forty feet square is considered a reasonable representation of the free air space around the detector. A dose receptor point, representing the detector, was placed on the outer edge of the box (representing the drywell wall) halfway up and across the box. This best represents the location of a radiation detector within the drywell mounted on the outer or inner wall.
No attempt was made to simulate shielding from components within the drywell nor was any credit taken for backscatter from the surrounding walls or components. The box was then filled with the calculated isotopic concentrations to determine a dose rate at the given point.
Methodology:
Microshield requires a given concentration in uCi/cc or uCi/gm for each isotope of interest. To obtain those concentrations requires converting the I-13 1 Dose Equivalent concentration (0.2 uCi/gm and 4.0 uCi/gm) to their individual isotopic components. In this case an equivalent for I-131,I-132,I-133,I-134 and 1-135.
Individual calculation sheets, Microshield runs and supporting documents are included in this attachment for reference purposes for each site. The following provides an explanation of the calculations performed.
EP-EAL-06 1 1, Rev 1 Page 3 Normalized I-13 1 Equivalent Activity Distribution A normalized I-13 1 equivalent activity distribution for each isotope was calculated using the relative mix of the isotopes of interest for each facility.
These ratios vary from site to site and are listed on the individual sites calculation spreadsheets. Copies of the source documents are contained within this calculation. The normalized value is calculated using the following equation:
Where:
DCF(i) = Isotopes FGR-11 Dose Conversion Factor (See Assumptions for details)
DCF(1-131) = 1-131 FGR-11 Dose Conversion Factor (See Assumptions for details)
NDCF(i) = The Isotopes ratio normalized to the I-13 1 DCF.
Since only the normalized DCF values are used in the calculation, no unit conversion is necessary.
AD,i,
- NDCF;,, = NC(,,
Where:
ADo) = Activity Distribution (See the included calculation data for individual sites distribution numbers)
NC(i) = Normalized I-13 1 Equivalent Activity Distribution Calculate the fraction of each isotopes normalized activity distribution.
Where:
hi) = Fraction of each isotopes normalized activity distribution.
Calculate the Dose Equivalent I-13 1 activity (uCi/gm) for each Isotope.
Where:
DE(1-131) = 0.2 or 4.0 uCi/gm
EP-EAL-06 1 1, Rev 1 Page 4 DEI-13 l(i) = the Dose Equivalent I-13 1 activity (uCi/gm) for each isotope.
Calculate the Isotopic Concentration DEI - 13 l(,.)
= IC( i)
ND CF, )
Where:
IC(i) = Isotope's RCS Concentration (uCi/gm)
Calculate Total Isotopic RCS Activity for each isotope Where:
V(RCS) = RCS Liquid Volume A(i) = Isotopes total activity (uCi) in the RCS Calculate the Drywell Airborne Concentration Where:
V(Q = Free-air space as defined in the assumptions AC(i) = Isotopes concentration (uCi/cc) in the Dry Well free-air space.
Calculation The Drywell Airborne Concentrations (AC(i)) were entered into the Microshield program for each RCS Dose Equivalent Iodine -13 1 values of interest (0.2 and 4.0 uCi/gm).
EP-EAL-0611, Rev 1 Page 5 Site Clinton Results:
The following table summarizes the results of each calculation by site.
Calculated Dose Calculated Dose Calculated Dose Rate (0.2 uCi/gm)
Rate (4.0 uCi/gm)
Rate (4.0 uCVgm)
R/hr R/hr R/hr 7.5 151 167 (FGR 11 Effective DCF)
(FGR 11 Effective DCF)
(FGR 11 Thyroid DCF)
Limerick Oyster Creek I Dresden I
8.5 I
169 I
187 6.6 132 146 9.2 185 204 I LaSalle I
9.7 I
195 I
215 I PeachBottom I
5.4 I
109 I
118
Clinton
(Effective DCF)
FSAR Activity Distribution Isotope (uCi/gm)
AD 1-1 31 0.01 50 1-1 32 0.1 500 1-1 33 0.1000 1-1 34 0.3000 1-1 35 0.1500 FGR 11 Effective DCF (RedCi)
DCF 3.29E+04 3.81 E+02 5.85E+03 1.31 E+02 1.23E+03 Normalized DCF NDCF l.OOE+OO 1.1 6E-02 1.78E-01 3.98E-03 3.74E-02 1-1 31 0.01 50 3.29E+04 l.OOE+OO 1-1 32 0.1500 3.81 E+02 1.16E-02 1-133 0.1000 5.85E+03 1.78E-01 1-134 0.3000 1.31 E+02 3.98E-03 1-1 35 0.1500 1.23E+03 3.74E-02 Normalized Activity Distribution (uCi/gm)
NC 1.50E-02 1.74E-03 1.78E-02 1.19E-03 5.61 E-03 4.13E-02 Isotopic Fraction f
0.363 0.042 0.430 0.029 0.136 1.ooo DE 1-131 Conc DE 1-131 Conc.
(ucigm)
(uCigm)
DEI-131 0.2 7.26E-02 8.41 E-03 8.61 E-02 5.78E-03 2.71 E-02 2.00E-01 Isotopic Concentration RCS Volume (ucigm)
(gm)
IC v(RCS) 7.26E-02 3.16E+08 7.26E-01 4.84E-01 1.45E+00 7.26E-01 I.45E+00 1.50E-02 0.363 4.0 1.45E+00 1.74E-03 0.042 1.68E-01 1.45E+01 1.78E-02 0.430 1.72E+00 9.68E+00 1.I 9E-03 0.029 1.16E-01 2.90E+01 5.61 E-03 0.136 5.43E-01 1.45E+01 4.1 3E-02 I.OOO 4.00E+00 Total Activity Released (uCi)
A 2.29E+07 2.29E+08 1.53E+08 4.59E+08 2.29E+08 Free-Air Drywell Volume Concentration (cc)
(UCVCC)
V(f)
AC 3.29E-03 3.29E-02 2.19E-02 6.58E-02 3.29E-02 1.57E-01 6.970E+09 6.58E-02 6.58E-01 4.39E-01 1.32E+00 3.14E+00 6.58E-01
C PSAJ SAR (2)
The second is based on assumptions considered ta provide a realistic conservative estimate of the radiological consequences. This analysis is referred to as the "realistic analysis".
A schematic of the release path is shown in Figure 15.6.4-1.
'l5.6.4.5.1 Desinn Basis Analysis The design basis analysis is based on NRC Standard Review Plan 15.6.4 and NRC Regulatory Guide 1.5. The specific models, assumptions and the program used for computer evaluation are described in Reference 2. Specific values of parameters used in the evaluation are presented in Table 15.6.4-2.
15.6.4.5.1.1 Fission Product Release from Fuel There is no fuel damage as a result of this accident. The only activity available for release from the break is that which is present in the reactor coolant and steam lines prior to the break. This level of activity is consistent with an offgas release rate of IOU pCilsec - M W T after 30 minutes delay (approximately 300,000 pCilsec). The iodine concentrations in the reactor coolant are three times the design basis concentrations which are given by (FCilgrn):
1-1 31 Q.O? 5 1-1 32 0.15 1-1 33 0.10 1-1 34 0.30 1-1 35 0.15 Because of its short half-life, N-16 is not considered in the analysis.
I
!!i.6.4.!j.I
-2 Fission Product 7"ransDai-t to the Environment The transport pathway is a direct unfiltered release to the environment. The MStlV detection and closure time of 5.5 sec results in a discharge of 42,500 lb of steam and 53,750 lb of liquid from the break, The mass release is limited by choked flow through the main steam line flow restrictors and the MSLIV closure time, Neither of the limitations are power related, so the mass refease is applicabfe at both the original and current ficensed power. Assuming ail the activity in this discharge becomes airborne, the release of activity to the environment is presented in Table 15.6.4-3.
15.6.4.5, I
.3 Resufts The calculated exposures fur the design basis analysis are presented in Table 15.6.4-4 and are a small fraction of the guidelines of 10 CFR 100.
CHAPTER I 5 15.6-4 REV. I A, JANUARY 2005
Exelon BW R CDAM, Version I
.O Requirements Specification December, 2002 m
I
ATTACHMENT 1 BWR CDAM METHODOLOGIES 2.61E+08 3.26+09 7.2.2 Normal Svstern Volumes Clinton USAR Fig 5.1-2 DresdenlQuad Cities taken from NEOO 22225.
DFUQC UFSAR Section 6 (1,I 5E+05 Ft3, 3.26E+09 ml)
LS UFSAR Cont Design Param Normai system volumes are used as default values, since operator actions or accident events can significantly change actual volumes, the program shall allow end user to manually enter values based on conditions at time of accident.
4.15E+09 6.97E+09 Suppression Pool Liquid (mi) 3.26E+09 3.68E+09 4.47E+09 6.51E+09 Drywell Atmosphere (cc) 4.47E.tO9 Containment Atmosphere (cc)
DWQC UFSAR Section 6 Suppression Pool Atmosphere (cc) 4.39E+10 N/A NIA I
I NIA 73 1 Reference 3.32E+09 4.67E+U9 LS UFSAR Cont Design Param
( 1.30+05 Ft3, 3.68E+09 mi) 1 A. Volume Corrections A volume correction is necessary whenever a single sample is taken and the two locations (Reactor Coolant and Containment Sump) are not in a state of equilibrium (when the released activity is not assumed to be spread throughout both sample locations). The volume correction is as follows:
Volume Sampled Location Volume 80th Locations 1
vc=
SWR CDAM Product ID EX0006322 39 of 46 Revision 0
Microshield v5.03 (5.03-00095)
PECO Energy Page
- 1 DOS File: CL-02UCI.MS5 Run Date: October 16, 2006 Run Time: 2:14:27 PM Duration: 00 : 00 : 02 Eneray MeV 0.03 0.08 0.15 0.2 0.3 Case
Title:
Clinton 0.2 uCi/g
==
Description:==
D/W Rad Monitor Geometry: 13 - Rectangular Volume File Ref:
Date:
By:
Checked :
Source Dimensions Length 609.6 em 20 ft 0.0 in Width 1.2e+3 cm 40 ft 0.0 in Height 1.2e+3 em 40 ft 0.0 in Dose Points x
Y Z
- 1 612.648 cm 609.6 cm 663.6 cm 20 ft 1.2 in20 ft 0.0 in20 ft 0.0 in Shields Shield Name Dimension MaterialDensitv Source 3.20e+04 ft3 Air 0.00122 Air Gap Air 0.00122 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Nuclide curies becauerels pCi/cm3 Ba/cm3 1-131 2.9812e+000 1.1030e+011 3.2900e-003 1.2173e+002 1-132 2.9812e+001 1.1030e+012 3.2900e-002 1.2173e+003 1-133 1.9844e+001 7.3424e+011 2.1900e-002 8.1030e+002 1-134 5.9624e+001 2.2061e+012 6.5800e-002 2.4346e+003 1-135 2.9812e+001 1.1030e+012 3.2900e-002 1.2173e+003 Buildup The material reference is : Source x
Y z
Act ivi tv photondsec Integration Parameters Direction 10 Direct ion 20 Di rec t ion 20 Results Fluence Rate Fluence Rate ExDosure Rate Exrr>osure Rate MeV/cm2/sec MeV/cm2/sec mR/hr mR/hr No Buildux, With Buildux, No Buildux, With BuilduD 5.393e+02 6.385e+02 5.345e+00 6.328e+00 8.607e+01 9.900e+01 1.362e-01 1.567e-01 6.152e+03 6.776e+03 1.013e+01 1.116e+01 6.693e+03 7.203e+03 1.181e+01 1.271e+01 1.061e+04 1.122e+04 2.013e+01 2.128e+01
Page
- 2 DOS File: CL-02UCI.MS5 Run Date: October 16, 2006 Run Time: 2:14:27 PM Duration: 00:00:02 Enercrv Act ivi tv MeV photons / sec 0.4 4.547e+11 0.5 1.288e+12 0.6 2.182e+12 0.8 5.071e+12 1.0 1.649e+12 1.5 1.082e+12 2.0 3.344e+11 Fluence Rate MeV/cm2/sec No Buildux, 6.986e+04 2.483e+05 5.062e+05 1.576e+06 6.425e+05 6.360e+05 2.630e+05 Fluence Rate MeV/cm2/sec with BuilduD 7.307e+04 2.579e+05 5.234e+05 1.619e+06 6.574e+05 6.468e+05 2.666e+05 Exx,osure Rate mR/hr No Buildux, 1.361e+02 4.873e+02 9.881e+02 2.998e+03 1.184e+03 1.070e+03 4.067e+02 ExDosure Rate mR/hr With Buildux, 1.424e+02 5.063e+02 1.022e+03 3.079e+03 1.212e+03 1.088e+03 4.122e+02 TOTALS: 1.240e+13 3.966e+06 4.070e+06 7.318e+03 7.513e+03
MicroShield v5.03 (5.03-00095)
PECO Energy Page
- 1 DOS File: CL-4UCI.MS5 Run Date: October 16, 2006 Run Time: 2:15:56 PM Duration : 00 : 00 : 02 Enerav MeV 0.03 0.08 0.15 0.2 0.3 Case
Title:
Clinton 4 uCf/g
==
Description:==
D/W Rgd Monitor Geometry: 13 - Rectangular Volume File Ref:
Date:
By:
Checked :
Source Dimension8 Length 609.6 cm 20 ft 0.0 in Width 1.2e+3 cm 40 ft 0.0 in Height 1.2e+3 cm 40 ft 0.0 in Dose Points X
Y Z
- 1 612.648 cm 609.6 cm 609.6 cm 20 ft 1.2 in20 ft 0.0 in20 ft 0.0 in Shields Shield Name Dimension MaterialDensitv Source 3.20e+04 ft3 Air 0.00122 Air Gap Air 0.00122 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photon8 < 0.015 : Excluded Eibseary : Grove 1-131 5.9624e+001 2.2061e+012 6.5800e-002 2.4346e+003 1-132 5.9624e+002 2.2061e+013 6.5800e-001 2.4346e+004 1-133 3.9780e+002 1.4718e+013 4.3900e-001 1.6243e+004 1-134 1.1961e+003 4.4256e+013 1.3200e+000 4.8840e+004 1-135 5.9624e+002 2.2061e+013 6.5800e-001 2.4346e+004 Nuclide curies becauerels pCi/cm3 Ba/cm3 Buildup The material reference is : Source Integration Parameters X Direction 10 Y Direction 20 Z Direction 20 Result s Ac tivi tv Fluence Rate Fluence Rate ExDosure Rate 1.041e+12 1.081e+04 1.280e+04 1.071e+02 5.776e+10 1.721e+03 1.980e+03 2.724e+00 2.181e+12 1.234e+05 1.359e+05 2.032e+02 1.769e+12 1.342e+05 1.444e+05 2.368e+02 1.853e+12 2.124e+05 2.245e+05 4.029e+02 photons/sec MeV/cm2/sec MeV/cm2/sec mR/hr No Buildux, with Buildux, No Buildux, ExDosure Rate mR/hr With Buildux, 1.268e+02 3.133e+00 2.238e+02 2.548e+02 4.259e+02
Page
- 2 30s File: CL-4UCI.MS5 Xun Date: October 16, 2006 Xun Time: 2:15:56 PM 3uration: 00:00:02 Enerqv MeV 0.4 0.5 0.6 0.8 1.0 1.5 2.0 Activitv photons / sec Fluence Rate MeV/cm2/sec No Buildux, 1.400e+06 4.975e+06 1.013e+07 3.159e+07 1.287e+07 1.273e+07 5.269e+06 Fluence Rate MeV/cm2/sec with BuilduD 1.464e+06 5.168e+06 1.048e+07 3.245e+07 1.317e+07 1.295e+07 5.340e+06 ExDosure Rate mR/hr No Buildux, 2.727e+03 9.764e+03 1.978e+04 6.009e+04 2.373e+04 2.142e+04 8.148e+03 Exx,osure Rate mR/hr with Buildux>
2.853e+03 1.014e+04 2.045e+04 6.172e+04 2.427e+04 2.178e+04 8.257e+03 TOTALS: 2.485e+14 7.946e+07 8.154e+07 1.466e+05 1.505e+05
Clinton (Thyroid DCF)
Isotope 1-1 31 1-132 1-133 1-1 34 1-135 1-1 31 1-1 32 1-133 1-134 1-1 35 FSAR Activity FGR 11 Thyroid Distribution DCF (uCigm)
(RemlCi)
AD DCF 0.0150 1.08E+06 0.1500 6.44E+03 0.1000 1.80E+05 0.3000 1.07E+03 0.1500 3.1 3E+04 0.0150 1.08E+06 0.1500 6.44E+03 0.1000 1.80E+05 0.3000 1.07E+03 0.1500 3.1 3E+04 Normalized DCF NDCF l.OOE+OO 5.96 E-03 1.66E-01 9.86E-04 2.90E-02 l.OOE+OO 5.96E-03 1.66E-01 9.86E-04 2.90E-02 Normalized Activity Distribution (uCi/gm)
NC 1.50E-02 8.94 E-04 1.66E-02 2.96E-04 4.35E-03 3.72 E-02 1.50E-02 8.94E-04 1.66E-02 2.96 E-04 4.35E-03 3.72E-02 DE 1-131 Isotopic Total Activity isotopic Conc DE 1-131 Conc. Concentration RCS Volume Released Fraction
(
f 0.403 0.024 0.448 0.008 0.1 17 1.ooo 0.403 0.024 0.448 0.008 0.1 17 1.ooo
[uCi/gm)
(uCiigm)
DE(l-jSI)
DEI-131 0.2 8.07E-02 4.81 E-03 8.95E-02 1.59E-03 2.34E-02 2.00E-01 4.0 1.61 E+OO 1.79E+00 9.62E-02 3.18E-02 4.68E-01 4.00E+00 (uCi/gm)
IC 8.07E-02 8.07E-01 5.38E-01 1.61 E+OO 8.07 E-0 1 1.61 E+OO 1.61 E+01 1.08E+01 3.23E+01 1.61 E+01 (gm)
(uCi) 3.16E+08 2.55E+07 2.55E+08 1.70E+08 5.1 OE+08 2.55E+08 V(RCS)
A 5.1 OE+08 5.1 OE+09 3.40E+09 1.02E+10 5.10E+09 Drywell Free-Air Volume Concentration (cc)
(UCiCC)
V(f)
AC 6.970E+09 3.66E-03 3.66E-02 2.44E-02 7.32 E-02 3.66E-02 1.74E-01 7.32E-02 7.32E-01 4.88 E-0 1 1.46E+00 3.49E+00 7.32E-01
Microshield V5.03 (5.03-00095)
PECO Energy Page
- 1 File Ref:
DOS File: CL-4UCII.MS5 Date:
Run Date: October 24, 2006 By:
Run Time: 2:04:44 PM Checked:
Duration: 00:00:02 Case
Title:
Clinton 4 uCi/g
==
Description:==
D/W Rad Monitor (Thyroid DCF)
Geometry: 13 - Rectangular Volume Enerav MeV 0.03 0.08 0.15 0.2 0.3 Source Dimensions Length 609.6 cm 20 ft 0.0 in Width 1,2e+3 cm 40 ft 0.0 in Height lO2e+3 cm 40 ft 0.0 in Dose Points X
Y Z
- 1 612.648 cm 609.6 cm 609.6 cm 20 ft 1.2 in20 ft 0.0 in20 ft 0.0 in Shields Shield Name Dimension MaterialDensity Source 3.20e+04 ft3 Air 0.00122 Air Gap Air 0.00122 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0,015 : Excluded Library t Grove 1-131 6.6329e+001 2.4542e+012 7.3200e-002 2.7084e+003 1-132 6.6329e+002 2.4542e+013 7.3200e-001 2.7084e+004 1-133 4.4220e+002 1.6361e+013 4.8800e-001 1.8056e+004 1-134 1.3230e+003 4.8950e+013 1.4600e+000 5.4020e+004 1-135 6.6329e+002 2.4542e+013 7.3200e-001 2.7084e+004 Nuclide curies becauerels pCi / cm3 Ba/cm3 Buildup The material reference is : Source Integration Parameters X Direction 10 Y Direction 20 Z Direction 20 Results Activi tv Fluence Rate Fluence Rate Exnosure Rate ExDosure Rate No Buildux, with Buildux, No Buildux, With BuilduD 1.154e+12 1.198e+04 1.418e+04 1.187e+02 1.406e+02 6.426e+10 1.915e+03 2.203e+03 3.030e+00 3.486e+00 2.412e+12 1.365e+05 1.504e+05 2.248e+02 2.476e+02 1.959e+12 1.486e+05 1.599e+05 2.623e+02 2.823e+02 2.059e+12 2.360e+05 2.495e+05 4.478e+02 4.733e+02 photons/sec MeV/cm2/sec MeV/cm2/sec mR/hr mR/hr
age
- 2 0s File: CL-4UCII.MS5 un Date: October 24, 2006 un Time: 2:04:44 PM iuration : 00 : 00 : 02 Enerav Act ivi tv MeV photons/sec 0.4 1.010e+13 0.5 2.866e+13 0.6 4.850e+13 0.8 l.l26e+14 1.0 3.663e+13 1.5 2.405e+13 2.0 7.430e+12 TOTALS: 2.756e+14 Fluence Rate MeV/cm2/sec No Buildux, 1.552e+06 5.525e+06 lO125e+07 3.499e+07 lO428e+07 1.414e+07 5.843e+06 8.811e+07 Fluence Rate MeV/cm2/sec 1.623e+06 5.739e+06 lO163e+07 3.594e+07 1.461e+07 1.438e+07 5.922e+06 9.042e+07 Exgosure Rate mR/hr No Buildu-a 3.023e+03 10084e+04 2.196e+04 6.656e+04 2.632e+04 2.379e+04 9.036e+03 1.626e+05 ExDosure Rate mR/hr With Buildux, 3.163e+03 1.127e+04 2.271e+04 6.836e+04 2.692e+04 2.420e+04 9.158e+03 1.669e+05
Dresden
Dresden (Effective DCF)
Isotope 1-131 1-1 32 1-1 33 1-134 1-135 1-1 31 1-132 1-1 33 1-1 34 1-135 FSAR Activity Distribution (uCigm)
AD 0.0250 0.2500 0.1000 0.2500 0.2500 FGR 11 Effective DCF (ReWCi)
DCF 3.29E+04 3.81 E+02 5.85E+03 1.31 E+02 1.23E+03 Normalized DCF NDCF l.OOE+OO 1.16E-02 1.78E-01 3.98E-03 3.74E-02 0.0250 3.29E+04 l.OOE+OO 0.2500 3.81 E+02 1.16E-02 0.1000 5.85E+03 1.78E-01 0.2500 1.31 E+02 3.98E-03 0.2500 1.23E+03 3.74E-02 Normalized Activity Distribution (ucigm)
NC 2.50E-02 2.90E-03 1.78E-02 9.95E-04 9.35E-03 5.60E-02 Isotopic Fraction f
0.446 0.052 0.31 7 0.01 8 0.167 1.ooo DE 1-131 Conc DE 1-131 Conc.
(uCiigm)
(uCi/gm)
DE(1-131)
DEI-131 0.2 8.93E-02 1.03E-02 6.35E-02 3.55E-03 3.34E-02 2.00E-01 Isotopic Concentration RCS Volume (uCigm)
(sm)
IC V(RCS) 8.93E-02 2.61 E+08 8.93E-01 3.57E-01 8.93E-01 8.93E-01 1.79E+00 2.50E-02 0.446 4.0 2.90E-03 0.052 2.07 E-0 1 1.79E+01 7.1 4E+00 9.95E-04 0.018 7.1 1 E-02 1.79E+01 9.35E-03 0.167 6.67E-01 1.79E+01 1.79E+00 1.27E+00 1.78E-02 0.317 4.00E+00 5.60E-02 1.OOO Total Activity Released (uCi)
A 2.33E+07 2.33E+08 9.32 E+07 2.33E+08 2.33E+08 Free-Air Drywell Volume Concentration (cc)
(UCiCC)
"(f)
AC 4.470E+09 5.21 E-03 5.21 E-02 2.08E-02 5.21 E-02 5.21 E-02 1.82E-01 1.04E-01 1.04E+00 1.04E+00 1.04E+00 3.65E+OO 4.1 7E-01
DRESDEN - UFSM Rev. 5 January 2003 The MCHFR throughout the transient was calculated using a digital computer code. The code calculates the thermal hydraulic response of a single nuclear reactor coolant channel, consisting of an array of cylindrical he1 rods surrounded by channel walls. The code includes provisions for pressure losses, fluid expansion, inlet flow variations, axial power shape, and various heat transfer modes. The MCHFR throughout the transient was calculated fur the case OE normal ac power available and the degraded case of simultaneous loss of normal ac power, which would cause a recirculation pump trip. The core flowrates both with and without recirculation pumps were calculated using the five-node digital computer code used to calculate internal forces. These results atre shown on Figure 55.6-3 which includes the sweep time of the core. The calculated hZCHFII.
wodd not go below 2.0 (figure 15.6-3) throughout the transient even if the isolation valves were closed at the longest time; therefore, core integrity is maintained throughout the accident and no fuel I damage should result. (MCHFR has been replaced in later analyses by MCPR. Since these quantities are not interchangeable, the terminology in this analysis has not been revised.)
15.6.43 Radiolorzical Conseauences The following section describes main steam line break radiological dose analysis performed for t.he initial licensing of the plant, i.e., 1x7 fuel arrays.
The predominant activity in the discharged coolant would be N-16, which would be significantly reduced by decay due to its short half-life (about 7 seconds). If the reactor contained fuel with cladding leaks, the water released through the break would contain some fission products.
During 1964, the Dresden Unit 1 reactor was operated with a significant number of cladding leaks.
Analysis of reactor water samples indicated the following yearIy average ission product contents:
Fission Product I-lXI I-133 Other halogens Other fission products Activitv (uCilcc1 0.025 0.1 0.28 0.25 With separate reactor water cleanup systems or Unit 2 and Unit 3, it is estimated that the maximum coolant activity in each unit would be approximately 2.4 pCilcc at a 100,000 yCils normal off-gas release rate and would have the following fission product contents:
Fission Product Ac tivitv fpCilccf 1-131 0.04 I-133 0.3 Other halogens f.9 Other fission products 0.2 15.6-10
Exelon BW R CDAM, Version 1.O Requirements Specificatton December, 2002 k -
- . )...
A'TTACHMENT 1 BWR CDAM METHODOLOGIES 6.51 E+O9 7.2.2 Normal System Volumes LS UFSAR Cont Design Param (1.30E+05 Ft3, 3.68E+09 ml)
LS UFSAR Cont Design Param 4.47E.tO9 DWQC UFSAR Section 6 Normal system volumes are used as default values, since operator actions or accident events can significantly change actual voiumes, the program shall allow end user to manually enter values based on conditions at time of accident.
3.68E+09 3.26E+09 NIA NIA 4.67E+09 3.40E+09 Suppression Pool 4.15E+09 3.26E+09 Liquid (ml)
I DFUQC UFSAR Section 6 (I,I 5E+05 Ft3, 3.26E+09 mi)
DWQC UFSAR Section 6 (I
.15E+05 Ft3, 3.26E+09 ml)
( I.
30E+05 Ft3, 3.68E+09 ml) 6.97+09 4.47E+09 I
I Drywell Atmosphere (cc)
Containment 4.39E+10 NIA Atmosphere (cc) 1 Suppression pool NIA Atmosphere (cc) 4.11E+08 2.61E+U8 Clinton USAR Fig 5.1-2 Dresden/Quad Cities taken from NEOO 22215, 3.32+09 A. Volume Corrections A volume correction is necessary whenever a single sample is taken and the two locations (Reactor Coolant and Containment Sump) are not in a state of equilibrium (when the released activity is not assumed to be spread throughout both sample locations). The volume correction is as foifows:
Volume Sampled Location Volume Both ~ocetions 0W R CDAM Product ID EX0006322 39 of 46 Revision 0
MicroShield V5.03 (5.03-00095)
PECO Energy Page
- l DOS File : DR-02UCI.MS5 Run Date: October 16, 2006 Run Time: 2:09:26 PM Duration: 00 : 00 : 02 Enerav MeV 0.03 0.08 0.15 0.2 0.3 Case
Title:
Dresden 0.2 uCi/g
==
Description:==
D/W Rad Monitor Geometry: 13 - Rectangular Volume File Ref:
Date:
By:
Checked:
Source Dimensions Length 609.6 cm 20 ft 0.0 in Width 1.2e+3 cm 40 ft 0.0 in Height 1.2e+3 cm 40 ft 0.0 in
]Dose Points X
Y 2
- 1 612.648 cm 609.6 cm 609.6 cm 20 ft 1.2 in20 ft 0.0 in20 ft 0.0 in Shields Shield Name Dimension MaterialDensity Source 3.20e+04 ft3 Air 0.00122 Air Gap Air 0.00122 Source Input Grouping Method : Standard Indices m
e r
of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0,015 : Excluded Librerzy t Grove 1-131 4.7210e+000 1.7468e+011 5.2100e-003 1.9277e+002 1-132 4.7210e+001 1.7468e+012 5.2100e-002 1.9277e+003 1-133 1.8848e+001 6.9736e+011 2.0800e-002 7*6960e+002 1-134 4.7210e+001 1.7468e+012 5.2100e-002 1.9277e+003 1-135 4.7210e+001 1.7468e+012 5.2100e-002 1.9277e+003 Nuclide curies becauerels pCi/cm3 Ba/cm3 Buildup The material reference is : Source Integration Parameters X Direction 10 Y Direction 20 Z Direction 20 Result s Act ivi tv Fluence Rate Fluence Rate ExDosure Rate ExDosure Rate No Buildux> With Buildux, No Buildux, With Buildux, 5.328e+10 5.530e+02 6.547e+02 5.481e+00 6.489e+00 4.573e+09 1.363e+02 1.568e+02 2.157e-01 2.481e-01 8.815e+10 4.988e+03 5.494e+03 8.214e+00 9.04T7e+00 8.857e+10 6.718e+03 7.230e+03 1.186e+01 1.2?6e+01 1.326e+11 1.521e+04 1.607e+04 2.884e+01 3.049e+01 mR/hr photons/sec MeV/cm2/sec MeV/cm2/sec mR/hr
Page
- 2 DOS File: DR-02UCI.MS5 Run Date: October 16, 2006 Run Time: 2:09:26 PM Duration: 00:00:02 Enerav MeV 0.4 0.5 0.6 0.8 1.0 1.5 2.0 Activitv photons / sec Fluence Rate MeV/cm2/sec No BuilduQ 7.629e+04 2.690e+05 6.630e+05 1.529e+06 7.505e+05 8.625e+05 3.064e+05 TOTALS: 1.382e+13 4.485e+06 Fluence Rate MeV/cm2/sec With Buildux, 7.980e+04 2.794e+05 6.855e+05 1.571e+06 7.679e+05 8.772e+05 3.105e+05 4.601e+06 ExQosure Rate mR/hr No Buildux, 1.486e+02 5.280e+02 1.294e+03 2.909e+03 1.383e+03 1.451e+03 4.738e+02 8.242e+03 ExQosure Rate mR/hr With BuilduQ 1.555e+02 5.485e+02 1.338e+03 2.988e+03 1.415e+03 1.476e+03 4.802e+02 8.460e+03
Microshield v5.03 (5.03-00095)
PECO Energy Page
- 1 DOS File: DR-4UCI.MS5 Run Date: October 16, 2006 Run Time: 2:06:35 PM Duration: 00 : 00 : 02 Enerav MeV 0.03 0.08 0.15 0.2 0.3 Case
Title:
Dresden 4 uCi/g
==
Description:==
D/W Rad Monitor Geometry: 13 - Rectangular V o l m File Ref:
Date:
By:
Checked :
Source Dimensions Length 609.6 cm 20 ft 0.0 in Width 1.2e+3 cm 40 ft 0.0 in Height 1.2e+3 cm 40 ft 0.0 in Dose Points X
Y Z
- 1 612.648 cm 609.6 cm 609.6 cm 20 ft 1.2 in20 ft 0.0 in20 ft 0.0 in Shields Shield Name Dimension MaterialDensitv Source 3.20e+04 ft3 Air 0.00122 Air Gap Air 0.00122 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0,015 : Excluded Library t Grove 1-131 9.4238e+001 3.4868e+012 1.0400e-001 3.8480e+003 1-132 9.4238e+002 3.4868e+013 1.0400e+000 3.8480e+004 1-133 3.7786e+002 1.3981e+013 4.1700e-001 1.5429e+004 1-134 9.4238e+002 3.4868e+013 1.0400e+000 3.8480e+004 1-135 9.4238e+002 3.4868e+013 1.0400e+000 3.8480e+004 Nuc 1 ide curies becauerels pCi/cm3 Ba/cm3 Buildup The material reference is : Source Integration Parameters X Direction 10 Y Direction 20 Z Direction 20 Act ivi tv Fluence Rate photons/sec MeV/cm2/sec No Buildux, 1.064e+12 1.104e+04 9.129e+10 2.721e+03 1.760e+12 9.957e+04 1.768e+12 1.341e+05 2.648e+12 3.036e+05 Results Fluence Rate ExDosure Rate ExDosure Rate MeV/cm2/sec With Buildux>
No Buildux, With Buildux, 1.307e+04 1.094e+02 1.296e+02 3.130e+03 4.306e+00 4.953e+00 1.097e+05 1.640e+02 1.806e+02 1.443e+05 2.367e+02 2.547e+02 3.209e+05 5.758e+02 6.087e+02 mR/hr mR/hr
Page
- 2 DOS File: DR-4UCI.MS5 Run Date: October 16, 2006 Run Time: 2:06:35 PM Duration : 00 : 0 0 : 02 Enerav MeV 0.4 0.5 0.6 0.8 1.0 1.5 2.0 Act ivi tv photons/sec Fluence Rate MeV/cm2/sec No Buildux, 1.523e+06 5.380e+06 1.323e+07 3.053e+07 1.498e+07 1.722e+07 6.117e+06 Fluence Rate MeV/cm2/sec With Buildux, 1.593e+06 5.589e+06 1.368e+07 3.136e+07 1.533e+07 1.751e+07 6.199e+06 Exx,osure Rate mR/hr No BuilduD 2.967e+03 1.056e+04 2.583e+04 5.807e+04 2.762e+04 2.897e+04 9.459e+03 ExDosure Rate mR/hr With BuilduD 3.104e+03 1.097e+04 2.671e+04 5.964e+04 2.826e+04 2.946e+04 9.586e+03 TOTALS: 2.759e+14 8.953e+07 9.185e+07 1.646e+05 1.689e+05
Dresden Isotope 1-1 31 1-1 32 1-1 33 1-1 34 1-1 35 1-1 31 1-1 32 1-1 33 1-1 34 1-135 (Thyroid DCF)
FSAR Activity FGR 11 Thyroid Distribution DCF Normalized (uCi/gm)
(RemlCi)
AD DCF 0.0250 1.08E+06 0.2500 6.44E+03 0.1000 1.80E+05 0.2500 1.07E+03 0.2500 3.1 3E+04 0.0250 1.08E+06 0.2500 6.44E+03 0.1000 1.80E+05 0.2500 1.07E+03 0.2500 3.13E+04 DCF NDCF l.OOE+OO 5.96E-03 1.66E-01 9.86E-04 2.90E-02 l.OOE+OO 5.96E-03 1.66E-01 9.86E-04 2.90 E-02 Normalized Activity Distribution (uCiigm)
NC 2.50E-02 1.49E-03 1.66E-02 2.47E-04 7.24E-03 5.06E-02 2.50E-02 1.49E-03 1.66E-02 2.47 E-04 7.24E-03 5.06E-02 DE 1-131 Isotopic Total Activity Isotopic Conc DE 1-131 Conc. Concentration RCS Volume Released Fraction (uCiigm) f DE(l-131) 0.494 0.2 0.029 0.329 0.005 0.143 1.ooo 0.494 4.0 0.029 0.329 0.005 0.143 1.ooo (uCi/gm)
DEI-131 9.88E-02 5.89E-03 6.58 E-02 9.74E-04 2.86E-02 2.00E-01 1.98E+00 1.32E+00 1.1 8E-01 1.95E-02 5.72 E-0 1 4.00E+00 (uCilgm)
IC 9.88E-02 9.88E-01 3.95E-01 9.88E-01 9.88E-01 1.98E+00 1.98E+01 7.90E+00 1.98E+01 1.98E+01 (gm)
(uCi) 2.61 E+08 2.58E+07 2.58E+08 1.03E+08 2.58E+08 2.58E+08 V(RCS)
A 5.1 6E+08 5.16E+09 2.06 E+09 5.16E+09 5.16E+09 Drywell Free-Air Volume Concentration (UCiCC)
(cc)
V(f, AC 4.470E+09 5.77E-03 5.77 E -02 2.31 E-02 5.77E-02 5.77E-02 2.02E-01 1.15E-01 l.l5E+00 1.15E+00 1.15E+00 4.04E+00 4.61 E-01
Microshield ~5.03 (5.03-00095)
PECO Energy Page
- 1 DOS File: DR-4UCII.MS5 Run Date: October 24, 2006 Run Time: 1:27:54 PM Duration: 00 : 00 : 02 Case
Title:
Dresden 4 uCf/g
==
Description:==
D/W Rad Monitor (Thyroid DCF)
Geometry: 13 - Rectangular Volume File Ref:
Date:
By:
Checked :
Source Dimensions Length 609.6 cm 20 ft 0.0 in Width 1.2e+3 cm 40 ft 0.0 in Height 1.2e+3 cm 40 ft 0.0 in Dose Points X
Y Z
- 1 612.648 cm 609.6 cm 609.6 cm 20 ft 1.2 in20 ft 0.0 in20 ft 0.0 in Shields Shield Name Dimension MaterialDensitv Source 3.20e+04 ft3 Air 0.00122 Air Gap Air 0.00122 Source Input Grouping Method : Standard Indices m
e r
of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded 1-131 1.0421e+002 3.8556e+012 1.1500e-001 4.2550e+003 1-132 1.0421e+003 3.8556e+013 1.1500e+000 4.2550e+004 1-133 4.1773e+002 1.5456e+013 4.6100e-001 1.7057e+004 1-134 1.0421e+003 3.8556e+013 1.1500e+000 4.2550e+004 1-135 1.0421e+003 3.8556e+013 1.1500e+000 4.2550e+004 Nuclide curies becauerel s pCi/cm3 Ba/cm3 Buildup The material reference is : Source Integration Parameters X Direction 10 Y Direction 20 Z Direction 20 Result s Enerav Activi tv Fluence Rate Fluence Rate Exr,osure Rate Exx,osure Rate No Buildux, with Buildur, No Buildur, With Buildur, MeV photons/sec MeV/cm2/sec MeV/cm2/sec mR/hr mR/hr 0.03 1.176e+12 1.221e+04 1.446e+04 1.210e+02 1.433e+02 0.08 1.009e+l1 3.009e+03 3.461e+03 4.761e+00 5*476e+00 0.15 1.946e+12 1.101e+05 1.213e+05 1.813e+02 1.997e+02 0.2 1.955e+12 1.483e+05 1.596e+05 2.617e+02 2.817e+02 0.3 2.928e+12 3.357e+05 3.548e+05 6.367e+02 6.731e+02
age
- 2 0s File: DR-4UCII.MS5 un Date: October 24, 2006 un Time: 1:27:54 PM uration: 00:00:02 Enercrv Act ivi tv MeV photons/sec 0.4 1.096e+13 0.5 3.086e+13 0.6 6.307e+13 0.8 1.086e+14 1.0 4.251e+13 1.5 3.238e+13 2.0
, 8.599e+12 TOTALS: 3.051e+14 Fluence Rate MeV/cm2/sec No Buildur, 1.684e+06 5.948e+06 1.463e+07 3.376e+07 1.657e+07 1.904e+07 6.763e+06 9.900e+07 Fluence Rate MeV/cm2/sec with Buildur, lO762e+06 6.179e+06 1.513e+07 3*467e+07 1.695e+07 1.936e+07 6.855e+06 l.O16e+08 Exgosure Rate mR/hr No Buildug 3.281e+03 lO168e+04 2.856e+04 6.421e+04 3.054e+04 3.203e+04 lO046e+04 1.820e+05 Exnosure Rate mR/hr with BuilduD 3.432e+03 1.213e+04 2.953e+04 6.595e+04 3.124e+04 3.258e+04 1.060e+04 1.868e+05
LaSalle
LaSalle (Effective DCF)
Isotope 1-1 31 1-132 1-1 33 1-134 1-135 1-131 1-1 32 1-1 33 1-134 1-1 35 FSAR Activity FGR 11 Distribution Effective DCF Normalized (uciigm)
(RemlCi)
AD DCF 0.0390 3.29E+04 0.3600 3.81 E+02 0.2700 5.85E+03 0.7200 1.31 E+02 0.3900 1.23E+03 0.0390 3.29E+04 0.3600 3.81 E+02 0.2700 5.85E+03 0.7200 1.31 E+02 0.3900 1.23E+03 DCF NDCF l.OOE+OO 1.16E-02 1.78E-01 3.98E-03 3.74 E-02 l.OOE+OO 1.16E-02 1.78E-01 3.98E-03 3.74E-02 Normalized Activity Distribution (uciigm)
NC 3.90E-02 4.17E-03 4.80E-02 2.87E-03 1.46E-02 1.09E-01 3.90E-02 4.17E-03 4.80E-02 2.87E-03 1.46E-02 1.09E-01 Isotopic Total Activity DE 1-131 Isotopic Conc DE 1-131 Conc. Concentration RCS Volume Released Fraction (uciigm) f DE(l-131) 0.359 0.2 0.038 0.442 0.026 0.134 1.ooo 0.359 4.0 0.038 0.442 0.026 0.134 1.ooo (uciigrn)
DEI-131 7.1 8E-02 7.68E-03 8.84E-02 5.28E-03 2.68 E-02 2.00 E-0 1 1.44E+00 1.77E+00 1.54E-01 1.06E-01 5.37E-01 4.00E+00 (uciigrn)
IC 7.18E-02 6.63E-01 4.97E-01 1.33E+00 7.18E-01 1.44E+00 1.33E+01 9.94E+00 2.65E+01 1.44E+01 (gm)
(uCi) 4.1 1 E+08 2.95E+07 2.72E+08 2.04E+08 5.45E+08 2.95E+08 v(FiCS)
A Free-Air Drywell Volume Concentration (cc)
(uciicc)
"6, AC 6.51 OE+09 4.53E-03 4.18E-02 3.14E-02 8.37E-02 4.53E-02 2.07E-01 9.07E-02 8.37E-01 6.28E-01 1.67E+00 4.1 4E+00 9.07E-01
for computer evaluation are described in Reference 4. Specific values of parameters used in the evaluation are presented in Table 15.6-5.
3-135 There is no fuel damage as a result of this event. The only activity available for release from the break is that which is present in the reactor coalant and steamlines prior to the break. The iodine concentration in the reactor coolant is then given by (pCilgm):
0.390 1-131 I
0.039 1-132 0.360 Because of i t s short half-life, N-16 is not considered in the analysis.
The transpart pathway is a direct, unfiltered release to the stearn tunnel, which is a part of the secondary containment. The MSZV detection and closure time of 5.5 seconds results in a discharge of 14,000 pounds of steam and 86,000 pounds of liquid from the break, Assuming all the activity in this discharge becomes airborne, the release of activity to the environment is presented in Table 15.6-6.
This level of activity is consistent with an uff-gas release rate of 300,000 pCilsec after a 30-minute delay.
The calculated exposures for the design-basis analysis are presented in Table 15.6-8 and are a small fraction of the guidelines of 10 CFR 100.
Realistic Analysis The realistic analysis is based an a plausible but still conservative assessment of this event. The specific models and assumptions and the program used for computer evaluation are described in Reference 2. Specific values of parameters used in the evaluation are presented in Table 15.6-5.
Since there is no fuel rod damage as a consequence af this event, the only activity released to the environment is that associated with the steam and liquid discharged from the break.
The activity released from the event; is a function of the coolant activity, valve closure time, and mass of coolant released. A portion of the released coolant exists as steam prior to the blowdown, and as such does not contain the same concentration per unit of mass as does the steam generated as a consequence of the blowdawn. Therefore, it is necessary to subtract the initial steam mass from the 15.6-12 REV. 13
Exalon BWR CDAM, Version 1,O Requirements Specification December, 2002 u
4 ATTACHMENT I BWR CDAM METHODOLOGIES 0
3 7.2.2 Normal System Volumes 2.6E+08 Normal system volumes are used as default values, since operator actions or accident events can significantly change actual volumes, the program shall allow end user to manually enter values based on conditions at time of accident.
Clinton USAR Fig 5.1-2 RCS (mi) 3.26f-1.09 3.16E+U8 DWQC UFSAR Section 3 (I
.15E+05 Ft3, 3.26E+Q9 ml) t5 UFSAR Cont Design Param
{ 1,3QE+05 Ft3, 3.68E+09 mi) 4.47E-tO9 4.47E+09 ONQC UFSAR Section 6 6.52E+09 Containment Atmosphere (cc) 4.39EclQ NiA NIA N/A I Atmosphere (cc)
(I
.I 5E+05 Ft', 3.26+09 mi) tS UFSAR Cont Design Param A. Volume Corrections A volume correction is necessary whenever a single sample is taken and the two locations (Reactor Coolant and Containmeni Sump) are not in a state of equilibrium (when the released activity is not assumed to be spread throughout both sampfe locations). The volume correction is as futlows:
Volume Sampled Location Volume Both tocations Revision Q BWR CDAM Product !D EX0006322 39 of 46
Microshield v5.03 (5.03-00095)
PECO Energy Page
- 1 DOS File: LS-02UCI.MS5 Run Date: October 16, 2006 Run Time: 1:57:42 PM Duration : 00 : 00 : 02 Case
Title:
LaSalle 0.2uCi/gm
==
Description:==
D/W Iiad Monitor Geometry: 13 - Rectangular Volume File Ref:
Date:
By:
Checked:
Source Dimensions Length 609.6 cm 20 ft 0.0 in Width 1.2e+3 cm 40 ft 0.0 in Height 1.2e+3 cm 40 ft 0.0 in Dose Points X
Y Z
- 1 612.248 cm 609.6 cm 609.6 cm 20 ft 1.2 in20 ft 0.0 in20 ft 0.0 in Shields Shield Name Dimension MaterialDensitv Source 3.20e+04 ft3 Air 0.00122 Air Gap Air 0.00122 Source Input Grouping Method : Standard Indices W
e r
of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Library : Grove 1-131 4.1048e+000 L5188e+011 4.5300e-003 1.6761e+002 1-132 3*7877e+001 1.4014e+012 4.1800e-002 1.5466e+003 1-133 2*8453e+001 1.0528e+012 3.1400e-002 le1618e+003 1-134 7.5844e+001 2.8062e+012 8.3700e-002 3.0969e+003 1-135 4.1048e+001 1.5188e+012 4.5300e-002 1.6761e+003 Nuclide curies beccruerels pCi/cm3 Bcr/cm3 Buildup The material reference is : Source Integration Parameters X Direction 10 Y Direction 20 Z Direction 20 Results Enerav Act ivi tv Fluence Rate Fluence Rate ExDosure Rate ExDosure Rate MeV photonshec MeV/cm2/sec MeV/cm2/sec mR/hr mR/hr No BuilduD with BuilduD No Bui1du-a with BuilduD 0.03 6.754e+10 7.Olle+02 8.300e+02 6.948e+00 8.226e+00 0.08 3.976e+09 1.185e+02 1.363e+02 1.875e-01 2.157e-01 0.15 1.383e+11 7.825e+03 8.619e+03 1.289e+01 1.419e+01 0.2 1.146e+ll 8.689e+03 9.351e+03 1.534e+01 1.650e+01 0.3 1.233e+11 1.413e+04 1.494e+04 2.681e+01 2.834e+01
?age 10s File tun Date tun Time Iura t ion Enercrv MeV 0.4 0.5 0.6 0.8 1.0 1.5 2.0 TOTALS :
2 LS-02UCI.MS5 October 16, 2006 1:57:42 PM 00: 00: 02 Act ivi tv photons/sec 1.606e+13 Fluence Rate MeV/cm2/sec No Builduo 9.130e+04 3.377e+05 6.441e+05 2.010e+06 8.369e+05 8.474e+05 3.445e+05 5.143e+06 Fluence Rate MeV/cm2/sec With Builduo 9.551e+04 3.508e+05 6.660e+05 2.064e+06 8.563e+05 8.618e+O5 3.492e+05 5.278e+06 Exoosure Rate mR/hr No Builduo 1.779e+02 6.629e+02 1.257e+03 3.823e+03 1.543e+03 1.426e+03 5.328e+02 9.484e+03 Exoosure Rate mR/hr With Builduo 1.861e+02 6.887e+02 1.300e+03 3.927e+03 1.578e+03 1.450e+03 5.400e+02 9.737e+03
Microshield v5.03 (5.03-00095)
PECO Energy Page
Title:
LaSalle 4 uCi/gxn
==
Description:==
D/W Rad Monitor Geometry: 13 - Rectangular Volume File Ref:
Date:
By:
Checked:
Source Dimensions Length 609.6 cm 20 ft 0.0 in Width 1.2e+3 cm 40 ft 0.0 in Height 1.2e+3 cm 40 ft 0.0 in Dose Points X
Y Z
- 1 612.748 cm 663.6 cm 66.6 cm 20 ft 1.2 in20 ft 0.0 in20 ft 0.0 in Shields Shield Name Dimension MaterialDensitv Source 3.20e+04 ft3 Air 0.00122 Air Gap Air 0.00122 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Library : Grove 1-131 8.2187e+001 3.0409e+012 9.0700e-002 3.3559e+003 1-132 7.5844e+002 2.8062e+013 8.3700e-001 3.0969e+004 1-133 5.6906e+002 2.1055e+013 6,2800e-001 2.3236e+004 1-134 1.5133e+003 5.5990e+013 1.6700e+000 6.1790e+004 1-135 8.2187e+002 3.0409e+013 9.0700e-001 3.3559e+004 Nuclide curies becauerels pCi/cm3 Bcx/cm3 Buildup The material reference is : Source Integration Parameters X Direction 10 Y Direction 20 Z Direction 20 Enerav Act ivi tv Fluence Rate MeV photons/sec MeV/cm2/sec No Buildux, 0.03 1.349e+12 1.400e+04 0.08 7.962e+10 2.373e+03 0.15 2.759e+12 1.561e+05 0.2 2.288e+12 1.735e+05 0.3 2.467e+12 2.828e+05 Results Fluence Rate ExDosure Rate ExDosure Rate MeV/cm2/sec mR/hr mR/hr With Buildux, No Buildux, With Buildux, 1.658e+04 1.388e+02 1.643e+02 2.729e+03 3.755e+00 4.319e+00 1.720e+05 2.571e+02 2.832e+02 1.868e+05 3.063et-02 3.296e+02 2.990e+05 5.365e+02 5.672e+02
?age
- 2 10s File : LS-4UCI.MS5 tun Date: October 16, 2006 tun Time: 1:59:55 PM hration: 00:00:02 Enerw MeV 0.4 0.5 0.6 0.8 1.0 1.5 2.0 Act ivi tv photons/sec Fluence Rate MeV/cm2/sec No Buildux, 1.824e+06 6.753e+06 1.288e+07 4.014e+07 1.673e+07 1.695e+O7 6.886e+06 TOTALS: 3.210e+14 1.028e+08 Fluence Rate MeV/cm2/sec with Buildux, 1.908e+06 7.015e+06 1.332e+07 4.122e+07 1.711e+07 1.724e+07 6.979e+06 1.055e+08 Exposure Rate mR/hr No Buildux, 3.555e+03 1.326e+04 2.514e+04 7.634e+04 3.083e+04 2.852e+04 1.065e+04 1.895e+05 Exnosure Rate mR/hr with BuilduD 3.718e+03 1.377e+04 2.600e+04 7.841e+04 3.155e+04 2.901e+04 1.079e+04 1.946e+05
(Thyroid DCF)
Isotope 1-1 31 1-1 32 1-1 33 1-134 1-135 1-1 31 1-132 1-133 1-134 1-135 FSAR Activity FGR 11 Thyroid Distribution DCF (uCig m)
(RedCi)
AD DCF 0.0390 1.08E+06 0.3600 6.44E+03 0.2700 1.80E+05 0.7200 1.07E+03 0.3900 3.13E+04 Normalized DCF NDCF l.OOE+OO 5.96E-03 1.66E-01 9.86E-04 2.90E-02 0.0390 1.08E+06 l.OOE+OO 0.3600 6.44E+03 5.96E-03 0.2700 1.80E+05 1.66E-01 0.7200 1.07E+03 9.86E-04 0.3900 3.13E+04 2.90E-02 Normalized Activity Distribution (uCig m)
NC 3.9OE-02 2.1 5E-03 4.49E-02 7.1 OE-04 1.13E-02 9.81 E-02 Isotopic Fraction f
0.398 0.022 0.458 0.007 0.115 1.ooo DE 1-131 Conc DE 1-131 Conc.
(uCi/gm)
(uCi/gm)
DE(l-13,)
DEI-131 0.2 7.95E-02 4.37E-03 9.1 6E-02 1.45E-03 2.30 E-02 2.00E-01 Isotopic (uCi/gm)
(9m)
Concentration RCS Volume IC v(RCS) 7.95E-02 4.1 1 E+08 7.34E-01 5.50E-01 1.47E+00 7.95E-01 1.59E+00 3.90E-02 0.398 4.0 1.59E+00 2.15E-03 0.022 8.75E-02 1.47E+01 4.49E-02 0.458 1.83E+00 1.1 OE+01 2.94E+01 1.59E+01 2.90 E-02 4.61 E-01 7.1 OE-04 0.007 1.13E-02 0.115 9.81 E-02 1.OOO 4.00E+00 Total Activity Released (uCi)
A 3.27E+07 3.02E+08 2.26E+08 6.03E+08 3.27E+08 6.54 E+08 6.03E+09 4.53E+09 1.21E+10 6.54 E+09 Free-Air Drywell Volume Concentration (cc)
(UCiCC) v,,
AC 6.51 OE+09 5.02E-03 4.63E-02 3.48E-02 9.27E-02 5.02E-02 2.29E-01 1.00E-01 9.27E-01 6.95E-01 1.85E+00 l.OOE+OO 4.58E+00
Microshield v5.03 (5.03-00095)
Run Date :
Run Time:
Dura t i on :
Enerav MeV 0.03 0.08 0.15 0.2 0.3 1
LS-4UCII.MS5 October 24, 2006 1:23:09 PM 00: 00: 02 File Ref:
Date:
By:
Checked :
Case
Title:
LaSalle 4 uCi/gm
==
Description:==
D/W Rad Monitor (Thyroid)
Geometry: 13 - Rectangular Volume Source Dimensions Length 609.6 cm 20 ft 0.0 in width 1.2e+3 cm 40 ft 0.0 in Height 1.2e+3 cm 40 ft 0.0 in Dose Points X
Y Z
- 1 612.348 cm 609.6 cm 609.6 cm 20 ft 1.2 in20 ft 0.0 in20 ft 0.0 in Shields Shield Name Dimension MaterialDensitv Source 3.20e+04 ft3 Air 0.00122 Air Gap Air 0.00122 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Liblrenry t GPSV~
Nuclide curies becauerels pci/cm3 1-131 9.0614e+001 3.3527e+012 1.0000e-001 3.7000e+003 1-132 8.3999e+002 3.1080e+013 9.2700e-001 3.4299e+004 1-133 6.2977e+002 2.3301e+013 6.9500e-001 2.5715e+004 1-134 1.6764e+003 6.2025e+013 1.8500e+000 6.8450e+004 1-135 9.0614e+002 3.3527e+013 1.0000e+000 3.7000e+004 Ba/cm3 Buildup The material reference is : Source Integration Parameters X Direction 10 Y Direction 20 Z Direction 20 Results Act ivi tv Fluence Rate Fluence Rate Exx,osure Rate Exx,osure Rate No Buildux, With Buildux, No Buildux, with BuilduD 1.493e+12 1.550e+04 1.835e+04 1.536e+02 1.819e+02 8.778e+10 2.616e+03 3.009e+03 4.140e+00 4.762e+00 3.057e+12 1.730e+05 1.905e+05 2*848e+02 3.137e+02 2.531e+12 1.920e+05 2.066e+05 3.389e+02 3.647e+02 2.726e+12 3.125e+05 3.304e+05 5.928e+02 6.267e+02 photons/sec MeV/cm2/sec MeV/cm2/sec mR/hr mR/hr
age
- 2 10s File: LS-4UCII.MS5
.un Date: October 24, 2006
.un Time: 1:23:09 PM uration: 00:00:02 Enerw MeV 0.4 0.5 0.6 0.8 1.0 1.5 2.0 Act ivi tv photons/sec TOTALS: 3.553e+14 Fluence Rate MeV/cm2/sec No Buildup 2.018e+06 7.474e+06 1.427e+07 4.446e+07 1.850e+07 1.873e+07 7.614e+06 1.138e+08 Fluence Rate MeV/cm2/sec with Buildux, 2.111e+06 7.765e+06 1.475e+07 4.566e+07 1.893e+07 1.905e+07 7.717e+06 1.167e+08 Exx,osure Rate mR/hr No Buildux, 3.931e+03 1.467e+04 2.785e+04 8.456e+04 3.411e+04 3.150e+04 1.177e+04 2.098e+05 Exx,osure Rate mR / hr with Buildux, 4.112e+03 1.524e+04 2.879e+04 8.685e+04 3.490e+04 3.204e+04 1.193e+04 2.154e+05
Limerick
Limerick Isotope 1-1 31 1-132 1-133 1-1 34 1-1 35 1-1 31 1-132 1-1 33 1-1 34 1-1 35 (Effective DCF)
FSAR Activity Distribution (uCig m)
AD 0.0455 0.4200 0.31 15 0.8400 0.4550 FGR 11 Effective DCF (RemlCi)
DCF 3.29E+04 3.81 E+02 5.85E+03 1.31 E+02 1.23E+03 0.0455 3.29E+04 0.4200 3.81 E+02 0.31 15 5.85E+03 0.8400 1.31 E+02 0.4550 1.23E+03 Normalized Activity DE 1-131 Isotopic Total Activity Normalized Distribution Isotopic Conc DE 1-1 31 Conc. Concentration RCS Volume Released DCF NDCF l.OOE+OO 1.16E-02 I.78E-01 3.98E-03 3.74E-02 l.OOE+OO 1.16E-02 1.78E-01 3.98E-03 3.74E-02 (ucigm)
NC 4.55E-02 4.86E-03 5.54E-02 3.34E-03 1.70E-02 1.26E-01 Fraction (uCigm) f DE(I-131) 0.361 0.2 0.039 0.439 0.027 0.135 1.ooo 4.55E-02 0.361 4.0 4.86E-03 0.039 5.54E-02 0.439 3.34E-03 0.027 1.70E-02 0.1 35 1.26E-01 1.OOO (uCigm)
DEI-131 7.22E-02 7.71 E-03 8.78E-02 5.30E-03 2.70E-02 2.00E-01 1.44E+00 1.76E+00 1.54E-01 1.06E-01 5.40E-01 4.00E+00 (uCig m)
IC 7.22E-02 6.66 E-0 1 4.94E-01 1.33E+00 7.22E-01 1.44E+00 1.33E+01 9.88E+00 2.66 E+O 1 1.44E+01 (gm)
(uCi) 2.93E+08 2.1 1 E+07 1.95E+08 1.45E+08 3.90E+08 2.1 1 E+08 V(RCS)
A 4.23E+08 3.90E+09 2.89E+09 7.81 E+09 4.23E+09 Free-Air Drywell Volume Concentration (cc)
(UCVCC) v,,
AC 6.900E+09 3.06E-03 2.83E-02 2.10E-02 5.66E-02 3.06E-02 1.40E-01 6.13E-02 5.66E-01 4.20E-01 1.13E+00 2.79E+00 6.13E-01
LGS UFSAR 15.6.4.5.1 Design Basis Analysis The design basis analysis is based on SRP 15.6.4 and Regulatory Guide 1.5.
The specific models and assumptions and the program used for computer evaluation are described in Section 15.10.
Specific values of parameters used in the evaluation are presented in Table 15.6-9.
The only activity released from the reactor vessel is that contained in the coolant as a result of normal operation.
The integrated mass leaving the RPV through the steam line break is 108,785 lb, including 20,452 lb in the initial steam that existed prior to the blowdown.
All activity in the discharge becomes airborne. It is assumed that an equilibrium coolant concentration consistent with a 30 minute offgas release rate of 0.35 Ci/sec exists prior to the accident.
Although there will be some activation and corrosion products released, the isotopes of primary importance are the iodine isotopes. The iodine isotopes and noble gas activity released from the break and to the environment prior to isolation valve closure time are presented in Table 15.6-10.
The iodine concentration in the reactor coolant is given below:
ACTIVITY ISOTOPE 1-131 1-132 1-133 1-134 1-135 0.420 0.3115 0.84 0.455 Because of its short half-life, N-16 is not considered in the analysis.
15.6.4.5.2 Realistic Analysis This information has not been updated to reflect updated to reflect the current licensing design basis. The information should be used for historical reference only and not to support the design basis of the plant.
The realistic analysis is based on a realistic but still conservative assessment of this accident. The specific models and assumptions and the program used for computer evaluation are described in Reference 15.6-3. Specific values of parameters used in the evaluation are presented in Table 15.6-9. The leakage path used in these calculations is shown in Figure 15.6-2.
Using the most probable operating condition prior to the postulated break and realistic assumptions, the calculated mixture level in the RPV does not reach the steam line before isolation is complete.
Therefore, only steam will issue from the break during the entire transient. The total integrated mass leaving the break is 37,548 15.6-11 Rev. 11 9/02 I
Exelon MAROG BWR CDAM, Version 1.1 Requirements Specification February, 2005 2.91 E+08 ATTACHMENT 1 BWR CDAM METHODOLOGIES FSAR Table 6.2-4A FSAR Table 1.7.4 7.2.2 Normal Svstem Volumes 2.46E+09 5.1 OE+09 Normal system volumes are used as default values, since operator actions or accident events can significantly change actual volumes, the program shall allow end user to manually enter values based on conditions at time of accident.
C-1302-243-E610-081 RO FSAR Table 6.2-4A FSAR Table 1.7.4 FSAR Table 6.2-4A FSAR Table 1.7.4 C-1302-900-E610-026 RO C-1302-900-E610-026 RO RCS Liquid (ml)
I2.93E+08 12.67E+08 Drywell Atmosphere (cc)
Suppression Pool Atmosphere (cc)
Suppression Pool Liquid (ml) 1 3.81E+09 1 3.48E+09 6.90E+09 4.98E+09 4.1 8E+09 3.74E+09 3.51 E+09 FSAR Table 6.2-4A FSAR Table 1.7.4 C-1302-900-E610-026 RO 1
I I
- 1) Average of Minimum and Maximum from referenced calculation A. Volume Corrections A volume correction is necessary whenever a single sample is taken and the two locations (Reactor Coolant and Containment Sump) are not in a state of equilibrium (when the released activity is not assumed to be spread throughout both sample locations). The volume correction is as follows:
1 Volume Sampled Location Volume Both Locations vc =
7.2.3 P ressu re/Tem pe ratu re Correction The pressure/temperature correction is applied to gaseous samples and is used to account for differences between system pressure and temperature, and sample pressure and temperature. The pressureltemperature correction is as follows:
(P System +14.7) x (T Sample +460)
(P Sample +14.7) x (T System +460)
PTC =
38 of 45 Revision 0
Page
- 1 Microshield V5.03 (5.03-00095)
PECO Energy File Ref:
DOS File: LG-02UCI.MS5 Run Date: October 16, 2006 Run Time: 1:44:05 PM Duration: 00:00:02 Case
Title:
LGS 0.2uCi/gm
==
Description:==
D/W Rad Monitor Geometry: 13 - Rectangular Volume Date:
By:
Checked :
Source Dimensions Length 609.6 cm 20 ft 0.0 in width 1.2e+3 cm 40 ft 0.0 in Height 1.2e+3 cm 40 ft 0.0 in Dose Points X
Y Z
- 1 612.748 cm 609.6 cm 609.6 cm 20 ft 1.2 in20 ft 0.0 in20 ft 0.0 in Shields Shield Name Dimension MaterialDensitv Source 3.20e+04 ft3 Air 0.00122 Air Gap Air 0.00122 Source Input Grouping Method : Standard Indices umber of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Library : Grove 1-131 2.7728e+000 1.0259e+011 3.0600e-003 1.1322e+002 1-132 2.5644e+001 9.4882e+011 2.8300e-002 1.0471e+003 1-133 1.9029e+001 7.0407e+011 2.1000e-002 7*7700e+002 1-134 5.1287e+001 1.8976e+012 5.6600e-002 2.0942e+003 1-135 2.7728e+001 1.0259e+012 3.0600e-002 1.1322e+003 Ba/cm3 Nuclide curies becauerels pci/cm3 Buildup The material reference is : Source Integration Parameters X Direction 10 Y Direction 20 Z Direction 20 Enercw Activitv Fluence Rate MeV photondsec MeV/cm2/sec No Buildux, 0.03 4.563e+10 4.736e+02 0.08 2.686e+09 8.005e+01 0.15 9.352e+10 5.292e+03 0.2 7.745e+10 5.874e+03 0.3 8.332e+10 9.551e+03 Results Fluence Rate ExDosure Rate ExDosure Rate MeV/cm2/sec mR/hr With Buildup No Buildux, With Buildux, 5.607e+02 4.694e+00 5.557e+00 9.208e+01 1.267e-01 1.457e-01 5.829e+03 8.714e+00 9.598e+00 6.322e+03 1.037e+01 1.116e+01 1.010e+04 1.812e+01 1.915e+01 mR/hr
?age
- 2 20s File: LG-02UCI.MS5 3un Date: October 16, 2006 3un Time: 1:44:05 PM luration: 00:00:02 Enerav MeV 0.4 0.5 0.6 0.8 1.0 1.5 2.0 TOTALS :
Activitv photons/sec 1.086e+13 Fluence Rate MeV/cm2/sec No Buildun 6.172e+04 2.271e+05 4.359e+05 1.359e+06 5.658e+05 5.726e+05 2.329e+05 3.477e+06 Fluence Rate MeV/cm2/sec with Buildun 6.456e+04 2.359e+05 4.507e+05 1.396e+06 5.789e+05 5.824e+05 2.361e+05 3.568e+06 Exx>osure Rate mR/hr No Buildun 1.203e+02 4.457e+02 8.508e+02 2.585e+03 1.043e+03 9.634e+02 3.602e+02 6.411e+03 Exnosure Rate mR/hr With Buildun 1.258e+02 4.630e+02 8.797e+02 2.656e+03 1.067e+03 9.799e+02 3.650e+02 6.582e+03
Microshield v5.03 (5.03-00095)
PECO Energy Page
- I DOS File : LG-4UCI.MS5 Run Date: October 16, 2006 Run Time: 1:46:11 PM Dura t ion : 0 0 : 0 0 : 0 2 Case
Title:
LGS 4 uCi/gm
==
Description:==
D/W Rad Monitor Geometry: 13 - Rectangular Volume Nuclide 1-131 1-132 1-133 1-134 1-135 File Ref:
Date:
By:
Checked :
Source Dimensions Length 609.6 cm 20 ft 0.0 in Width 1.2e+3 cm 40 ft 0.0 in Height 1.2e+3 cm 40 ft 0.0 in Dose Points X
Y Z
- 1 612.648 cm 609.6 cm 609.6 cm 20 ft 1.2 in20 ft 0.0 in20 ft 0.0 in Shields Shield Name Dimension MaterialDensitv Source 3.20e+04 ft3 Air 0.00122 Air Gap Air 0.00122 Source Input Grouping Method : Standard Indices Munber of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Library : Grove curies becmerels pCi/cm3 Ba/cm3 5.5546e+001 2.0552e+012 6.1300e-002 2.2681e+003 5.1287e+002 1.8976e+013 5.6600e-001 2.0942e+004 3.8058e+002 1.4081e+013 4.2000e-001 1.5540e+004 1.0239e+003 3.7886e+013 1.1300e+000 4.1810e+004 5.5546e+002 2.0552e+013 6.1300e-001 2.2681e+004 Buildup The material reference is : Source Integration Parameters X Direction 10 Y Direction 20 Z Direction 20 Enerw Act ivi tv Fluence Rate MeV photons/sec MeV/cm2/sec No Buildux, 0.03 9.118e+11 9.465e+03 0.08 5.381e+10 1.604e+03 0.15 1.867e+12 1.057e+05 0.2 1.548e+12 1.174e+05 0.3 1.667e+12 1.911e+05 Results Fluence Rate MeV/cm2/sec with Buildux, 1.121e+04 1.845e+03 1.164e+05 1.263e+05 2.020e+05 ExDosure Rate mR / hr No Buildux, 9.380e+01 2.538e+00 1.740e+02 2.072e+02 3.626e+02 ExDosure Rate mR/hr with Buildux, 1.111e+02 2.919e+00 1.916e+02 2.230e+02 3.833e+02
Page
- 2 IOS File: LG-4UCI.MS5 3un Date: October 16, 2006 Xun Time: 1:46:11 PM Iuration: 00 : 00 : 02 Enerw Act ivi tv MeV photons/sec 0.4' 8.031e+12 0.5 2*355e+13 0.6 3*755e+13 0.8 8.736e+13 1.0 2.902e+13 1.5 1.949e+13 2.0 5.921e+12 Fluence Rate MeV/cm2/sec No Buildup 1.234e+06 4.540e+06 8.713e+06 2.715e+07 1.131e+07 1.146e+07 4.657e+06 TOTALS: 2.170e+14 6.949e+O7 Fluence Rate MeV/cm2/sec With Buildux, 1.291e+06 4.717e+06 9.008e+06 2.789e+07 1.157e+07 1.165e+OT7 4.720e+06 7.131e+07 Exx,osure Rate mR/hr No Buildux, 2.404e+03 8.912e+03 1.701e+04 5.164e+04 2.085e+04 1.928e+04 7.201e+03 1.281e+05 ExDosure Rate mR/hr With BuilduD 2.515e+03 9.258e+03 1.758e+04 5.304e+04 2.133e+04 1.961e+04 7'.298e+03 1.315e+05
Limerick (Thyroid DCF)
Isotope 1-1 31 1-132 1-1 33 1-1 34 1-1 35 1-131 1-132 1-133 1-1 34 1-1 35 FSAR Activity FGR 11 Thyroid Distribution DCF (uCi/gm)
(RedCi)
AD DCF 0.0455 1.08E+06 0.4200 6.44E+03 0.31 15 1.80E+05 0.8400 1.07E+03 0.4550 3.13E+04 0.0455 1.08E+06 0.4200 6.44E+03 0.31 15 1.80E+05 0.8400 1.07E+03 0.4550 3.13E+04 Normalized DCF NDCF l.OOE+OO 5.96E-03 1.66E-01 9.86E-04 2.90E-02 l.OOE+OO 5.96E-03 1.66E-01 9.86E-04 2.90E-02 Normalized Activity Distribution (uCig m)
NC 4.55E-02 2.50E-03 5.18E-02 8.28E-04 1.32E-02 1.14E-01 4.55E-02 2.50E-03 5.1 8E-02 8.28E-04 1.32E-02 1.14E-01 Total Activity DE 1-131 Isotopic Isotopic Conc DE 1-131 Conc. Concentration RCS Volume Released Fraction (uCi/gm) f DE(l-131) 0.400 0.2 0.022 0.455 0.007 0.116 1.ooo 0.400 4.0 0.022 0.455 0.007 0.1 16 1.ooo (uCi/gm)
DEI-131 7.99E-02 4.40E-03 9.1 1 E-02 1.46E-03 2.32 E-02 2.00E-01 1.60E+00 1.82E+00 8.79E-02 2.91 E-02 4.63E-01 4.00E+00 (uCi/gm)
IC 7.99E-02 7.38E-01 5.47E-0 1 1.48E+00 7.99E-01 1.60E+00 1.48E+01 1.09E+01 2.95E+01 1.60E+01 (gm)
(uCi) 2.93E+08 2.34E+07 2.1 6E+08 1.60E+08 4.32E+08 2.34E+08 V(RCS)
A 4.68E+08 4.32E+09 3.21 E+09 8.65E+09 4.68 E+09 Drywell Free-Air Volume Concentration (cc)
(ucilcc)
V(f)
AC 6.900E+09 3.39E-03 3.13E-02 2.32E-02 6.27E-02 3.39E-02 1.55E-01 6.79E-02 6.27E-01 4.65E-01 1.25E+00 3.09E+00 6.79E-01
Microshield 1~5.03 (5.03-00095)
PECO Energy File Ref:
IOS File: LG-4UCII.MS5 Date:
.un Date: October 24, 2006 By:
Checked :
.un Time: 1:19:37 PM buration: 00 : 00 : 02
'age
- 1 Case
Title:
Limerick 4 uCi/gm
==
Description:==
D/W Rad Monitor (Thyroid DCF)
Geometry: 13 - Rectangular Volume Source Dimensions Length 609.6 cm 20 ft 0.0 in width 1.2e+3 cm 40 ft 0.0 in Height 1.2e+3 cm 40 ft 0.0 in Dose Points X
Y 2
- 1 612.648 cm 609.6 cm 609.6 cm 20 ft 1.2 in20 ft 0.0 in20 ft 0.0 in Shields Shield Name Dimension MaterialDensitv Source 3.20e+04 ft3 Air 0.00122 Air Gap Air 0.00122 Source Input Grouping Method : Standard Indices Nunrber of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0,015 : Excluded Library : Grove 1-131 6.1527e+001 2.2765e+012 6.7900e-002 2.5123e+003*
1-132 5.6815e+002 2.1022e+013 6.2700e-001 2.3199e+004 1-133 4.2135e+002 1.5590e+013 4.6500e-001 1.7205e+004 1-134 1.1327e+003 4.1909e+013 1.2500e+000 4.6250e+004 1-135 6.1527e+002 2.2765e+013 6.7900e-001 2.5123e+004 Nuclide curies becauerels pc i / cm3 Ba/cm3 Buildup The material reference is : Source Integration Parameters X Direction 10 Y Direction 20 Z Direction 20 Results Eneruy Act ivi tv Fluence Rate Fluence Rate Exposure Rate Exposure Rate with Buildup No Buildux, with Buildux>
mR/hr MeV photons/sec MeV/cm2/sec MeV/cm2/sec mR / hr 1.009e+12 1.047e+04 1.240e+04 1.038e+02 1.229e+02 0.03 0.08 5.960e+10 1.776e+03 2.043e+03 2.811e+00 3.233e+00 1.287e+05 1.925e+02 2.120e+02 0.15 2.065e+12 1.169e+05 1.398e+05 2.293e+02 2.467e+02 0.2 1.713e+12 1.299e+05 2.238e+05 4.015e+02 4.244e+02 0.3 1.847e+12 2.117e+05 No Buildux,
rage A
DOS File: LG-4UCII.MS5 Run Date: October 24, 2006 Run Time: 1:19:37 PM Duration: 00 : 00 : 02 Enersv Act ivi tv MeV photons/sec 0.4 8.888e+12 0.5 2.607e+13 0.6 4.158e+13 0.8 9.667e+13 1.0 3.213e+13 1.5 2.158e+13 2.0 6.554e+12 TOTALS :
2.402e+14 Fluence Rate MeV/cm2/sec No Buildux, 1.365e+06 5.026e+06 9.647e+06 3.004e+07 1.252e+07 1.269e+07 5.155e+06 7.692e+07 Fluence Rate MeV/cm2/sec with Buildux, 1.428e+06 5.222e+06 9.974e+06 3.086e+07 1.281e+07 1.290e+07 5.224e+06 7.893e+07 ExDosure Rate mR/hr No Buildux, 2.661e+03 9.866e+03 1.883e+04 5.714e+04 2.308e+04 2.135e+04 7.971e+03 1.418e+05 ExQosure Rate mR/hr With BuilduQ 2.783e+03 l.O25e+04 1.947e+04 5.869e+04 2.361e+04 2.171e+04 8.079e+03 1.456e+05
Oyster Creek
Oyster Creek (Effective DCF)
Isotope 1-1 31 1-132 1-133 1-1 34 1-1 35 1-1 31 1-132 1-133 1-134 1-135 FSAR Activity Distribution (uCigm)
AD 0.0468 0.4420 0.3120 0.91 00 0.4680 FGR 11 Effective DCF (RemlCi)
DCF 3.29E+04 3.81 E+02 5.85E+03 1.31 E+02 1.23E+03 0.0468 3.29E+04 0.4420 3.81 E+02 0.31 20 5.85E+03 0.91 00 1.31 E+02 0.4680 1.23E+03 Normalized DCF NDCF l.OOE+OO 1.16E-02 1.78E-01 3.98 E-03 3.74E-02 l.OOE+OO 1.I 6E-02 1.78E-01 3.98E-03 3.74E-02 Normalized Activity Distribution (uCigm)
NC 4.68E-02 5.1 2E-03 5.55E-02 3.62E-03 1.75E-02 1.29E-01 4.68E-02 5.1 2E-03 5.55E-02 3.62E-03 1.75E-02 1.29E-01 DE 1-131 Isotopic Total Activity Isotopic Conc DE 1-1 31 Conc.
Concentration RCS Volume Released Fraction (uCigm) f DE(I-131) 0.364 0.2 0.040 0.432 0.028 0.136 1.ooo 0.364 4.0 0.040 0.432 0.028 0.136 1.ooo (ucigm)
DEI-131 7.28E-02 7.97E-03 8.63E-02 5.64E-03 2.72E-02 2.00E-01 1.46E+00 1.73E+00 1.59E-01 1.13E-01 5.45E-01 4.00E+00 (uCigm)
IC 7.28E-02 6.88E-01 4.86E-01 1.42E+00 7.28E-01 1.46E+00 1.38E+01 9.71 E+OO 2.83E+01 1.46E+01 (gm)
(uCi) 2.91E+08 2.12E+07 2.00 E+08 1.41 E+08 4.12E+08 2.12E+08 v(f?CS)
A 4.24E+08 4.00 E+09 2.83E+09 8.24E+09 4.24E+09 Drywell Free-Air Volume Concentration (cc)
(UCiCC)
V(f)
AC 5.100E+09 4.16E-03 3.92E-02 2.77E-02 8.08E-02 4.16E-02 I.93E-01 8.31 E-02 7.85E-01 5.54E-0 1 1.62E+00 3.87E+00 8.31 E-01
TABLE 11.1-3B (Sheet 1 of 1)
N-13 N-16 F-18 Br-83 Br-84 Br-85 Sr-89 Sr-90 Sr-91 Sr-92 Zr-95 Zr-97 Nb-9 5 Mo-99 Tc-99m Tc-101 Ru-103
')
Ru-106 Te-132 1
Te-129m 1-131 1-132 1-133 1-134 1-135 RIEACTOR COOLANT A CTIVITY CONCENTRATION*
(Design Ba8io) 3.70 (-2) 5.30(+1) 4.00 (-3) 5.46 (-2) 1. 04 (-1) 6.76 (-2) 1.07(-2) 8.06 (-4) 2.50( -1) 4.16( -1) 1.38 (-4) 1.14 (-4) 1.43 (-4) 7.80 (-2) 1.04 ( + O )
5.46 (-1) 6.76 (-5) 9. 10 (-6) 1.38 (-4) 1.69 (-1)
- 4. 68 (-2) 4.42 (-1) 3.12 (-1) 4.68 (-1) 9.
10 (-1)
Ce-134 C8-136 CS-137 C8-138 Ba-139 Ba-140 Ba-141 Ba-142 Ce-141 Ce-143 Ce-144 Pr-143 Nd-147 Np-239 Na-24 P-32 Cr-5 1 Mn-54 Mn-56 (20-58 CO-60 Fe-59 Ni-65 Zn-65 Zn-69m Ag-110M W-187
- General Electric Document 22A2703E, Revision 3 5.46 ( -4 )
3.64 (-4) 6.24 (-4 )
7.54 (-1) 6.24 (-1) 3.12 (-2) 7.02(-1) 6.76 (-1) 1.38(-4) 1.22 (-4) 1.22(-4) 1.33(-4) 4.94 (-5) 3.3(-1) 2.0(-3) 2.0(-5) 5.0(-4) 4.0(-5) 5.0(-2) 5.0 (-3) 5.0 (-4) 8.0(-5) 3.0(-4) 2.0(-6) 3.0( -5) 6.0(-5) 3.0(-3)
Update 5 12/90
Exelon MAROG BWR CDAM, Version 1.I Requirements Specification February, 2005 AlTACHMENT 1 BWR CDAM METHODOLOGIES 7.2.2 Normal Svstem Volumes Normal system volumes are used as default values, since operator actions or accident events can significantly change actual volumes, the program shall allow end user to manually enter values based on conditions at time of accident.
RCS Liquid (ml) 2.93E+08 2.67E+08 Suppression Pool 1 3.81E+09 1 3.48E+09 1 Liquid (mi)
Drywell Atmosphere (cc) 2.91 E+08 FSAR Table 6.2-4A FSAR Table 1.7.4 FSAR Table 1.7.4 FSAR Table 1.7.4 C-1302-900-E610-026 RO 3.51 E+09' FSAR Table 6.2-4A FSAR Table 1.7.4 I
C-1302-900-E610-026 RO I
- 1) Average of Minimum and Maximum from referenced calculation A. Volume Corrections A volume correction is necessary whenever a single sample is taken and the two locations (Reactor Coolant and Containment Sump) are not in a state of equilibrium (when the released activity is not assumed to be spread throughout both sample locations). The volume correction is as follows:
Volume Sampled Location Volume 60th Locations 7.2.3 Pressu re/Tem Derature Correction The pressure/temperature correction is applied to gaseous samples and is used to account for differences between system pressure and temperature, and sample pressure and temperature. The pressure/temperature correction is as f 01 lows:
(P System +14-7) x (T Sample +460)
(P Sample +14.7) x (T system +460)
PTC =
38 of 45 Revision 0
MicroShield v5.03 (5.03-00095)
PECO Energy Page
- 1 DOS File: OC-02UCI.MS5 Run Date: October 16, 2006 Run Time: 1:51:59 PM Duration : 0 0 : 0 0 : 02 Case
Title:
OCNGS O.;rluCi/gm
==
Description:==
D/W Rad Monitor Geometry: 13 - Rectangular 'volume File Ref:
Date:
By:
Checked :
Source Dimensions Length 609.6 cm 20 ft 0.0 in Width 1.2e+3 cm 40 ft 0.0 in Height 1.2e+3 cm 40 ft 0.0 in Dose Points X
Y Z
- 1 612.648 cm 609.6 cm 609.6 cm 20 ft 1.2 in20 ft 0.0 in20 ft 0.0 in Shields Shield Name Dimension MaterialDensitv Source 3.20e+04 ft3 Air 0.00122 Air Gap Air 0.00122 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Eibraw t Groves 1-131 3.7695e+000 1.3947e+011 4.1600e-003 1.5392e+002 1-132 3*5521e+001 1.3143e+012 3.9200e-002 1.4504e+003 1-133 2.51QQe+001 9,2870e+011 2.7700e-002 1.0249e+003 1-134 7.3216e+001 2.7090e+012 8.0800e-002 2.9896e+003 1-135 3.7695e+001 1.3947e+012 4.1600e-002 1.5392e+003 Nuc 1 i de curies becauerels pCi/cm3 Ba/cm3 Buildup The material reference is : Source Integration Parameters X Direction 10 Y Direction 20 Z Direction 20 Enerav Activitv Fluence Rate MeV photons/sec MeV/cm2/sec No Buildun 0.03 6.399e+10 6.642e+02 0.08 3.652e+09 1.088e+02 0.15 1.334e+11 7.549e+03 0.2 1.091e+11 8.276e+03 0.3 1.145e+11 1.313e+04 Results Fluence Rate Exnosure Rate MeV/cm2/sec mR/hr With Buildux, No Buildux, 7.864e+02 6.583e+00 1.252e+02 1.722e-01 8.315e+03 1.243e+01 8.906e+03 1.461e+01 1.388e+04 2.491e+01 Exnosure Rate mR/hr With Buildux, 7.794e+00 1.981e-01 1.369e+01 1.572e+01 2.633e+01
?age 2
10s File: OC-02UCI.MS5 Xun Date: October 16, 2006 Xun Time: 1:51:59 PM lura t ion : 0 0 : 0 0 : 0 2 Enerm MeV 0.4 0.5 0.6 0.8 1.0 1.5 2.0 Act ivi tv photons / sec Fluence Rate MeV/cm2/sec No BuilduD 8.648e+04 3.082e+05 6.099e+05 1.925e+06 7.912e+05 7.905e+05 3.254e+05 TOTALS: 1.520e+13 4.866e+06 Fluence Rate MeV/cm2/sec With Buildun 9.046e+04 3.202e+05 6.30663+05 1.977e+06 8.095e+05 8.040e+05 3.298e+05 4.994e+06 Exnosure Rate mR/hr No BuilduQ 1.685e+02 6.050e+02 1.190e+03 3.662e+03 1.458e+03 1.330e+03 5.032e+02 8.976e+03 Exnosure Rate mR/hr With Buildun 1.763e+02 6.286e+02 1.231e+03 3.761e+03 1.492e+03 1.353e+03 5.100e+02 9.215e+03
Microshield v5.03 (5.03-00095)
PECO Energy Page
- 1 DOS File: OC-4UCI.MS5 Run Date: October 16, 2006 Run Time: 1:54:02 PM Duration: 00:00:02 Eneruv MeV 0.03 0.08 0.15 0.2 0.3 Case
Title:
OCNGS 4 uCi/gm
==
Description:==
D/W Rad Monitor Geometry: 13 - Rectangular Volume File Ref:
Date:
By:
Checked:
Source Dimensions Length 609.6 cm 20 ft 0.0 in Width 1.2e+3 cm 40 ft 0.0 in Height 1.2e+3 cm 40 ft 0.0 in Dose Points X
Y Z
- 1 612.648 cm 609.6 cm 609.6 cm 20 ft 1.2 in20 ft 0.0 in20 ft 0.0 in Shields Shield Name Dimension MaterialDensitv Source 3.20e+04 ft3 Air 0.00122 Air Gap Air 0.00122 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0,015 Photons < 0.015 : Excluded Library : Grove 1-131 7.5300e+001 2.7861e+012 8.3100e-002 3.0747e+003 1-132 7.1132e+002 2.6319e+013 7.8500e-001 2.9045e+004 1-133 5.0200e+002 1.8574e+013 5.5400e-001 2.0498e+004 1-134 1.4679e+003 5.4314e+013 1.6200e+000 5.9940e+004 1-135 7.5300e+002 2.7861e+013 8.3100e-001 3.0747e+004 Nuclide curies becauerels pCi/cm3 Ba/cm3 Buildup The material reference is : Source Integration Parameters X Direction 10 Y Direction 20 Z Direction 20 Act ivi tv photons/sec Fluence Rate MeV/cm2/sec No BuilduD lO331e+04 2.174e+03 1.513e+05 lO658e+05 2.626e+05 Results Fluence Rate MeV/cm2/sec with Buildux, 1.575e+04 2.501e+03 1.667e+05 1.784e+05 2.776e+05 ExDosure Rate mR/hr No BuilduD 1.319e+02 3.440e+00 2.492e+02 2.926e+02 4.982e+02 ExDosure Rate mR/hr with Buildux, 1.561e+02 3.957e+00 2.745e+02 3.149e+02 5.266e+02
2tge
- 2 IS File : OC-4UCI.MS5 in Date: October 16, 2006 in Time: 1:54:02 PM iration: 00 : 00 : 02 3neru-v MeV 0.4 0.5 0.6 0.8 1.0 1.5 2.0 Activitv photons/sec Fluence Rate MeV/cm2/sec No Buildux>
1.732e+06 6.169e+06 1.222e+07 3.858e+07 1.584e+07 1.581e+07 6.515e+06
'OTALS :
3.044e+14 9.747e+07 Fluence Rate MeV/cm2/sec With Buildux>
1.811e+06 6.409e+06 1.263e+07 3.963e+07 1.621e+O7 1.608e+07 6.602e+06 1.000e+08 ExDosure Rate mR/hr No BuilduD 3.374e+03 1.211e+04 2.385e+04 7.339e+04 2.920e+04 2.660e+04 1.007e+04 1.798e+05 Exx>osure Rate mR/hr with Buildux, 3.529e+03 1.258e+04 2.466e+04 7.538e+04 2.988e+04 2.706e+04 1.021e+04 1.846e+05
Oyster Creek (Thyroid DCF)
Isotope 1-1 31 1-1 32 1-1 33 1-1 34 1-1 35 1-1 31 1-1 32 1-1 33 1-134 1-135 FSAR Activity FGR 11 Thyroid Distribution DCF Normalized (ucigm)
(RedCi)
AD DCF 0.0468 1.08E+06 0.4420 6.44E+03 0.3120 1.80E+05 0.91 00 1.07E+03 0.4680 3.13E+04 0.0468 1.08E+06 0.4420 6.44E+03 0.3120 1.80E+05 0.9100 1.07E+03 0.4680 3.13E+04 DCF NDCF l.OOE+OO 5.96E-03 1.66E-01 9.86E-04 2.90E-02 l.OOE+OO 5.96E-03 1.66E-01 9.86E-04 2.90E-02 Normalized Activity Distribution (uCi/gm)
NC 4.68E-02 2.63E-03 5.19E-02 8.98E-04 1.36E-02 1.16E-01 4.68E-02 2.63E-03 5.1 9E-02 8.98E-04 1.36E-02 1.16E-01 DE 1-131 Isotopic Total Activity Isotopic Conc DE 1-131 Conc. Concentration RCS Volume Released Fraction (uCi/gm) f DE(I-131) 0.404 0.2 0.023 0.448 0.008 0.117 1.ooo 0.404 4.0 0.023 0.448 0.008 0.1 17 1.000 (ucigm)
DELI 31 8.08 E-02 4.55E-03 8.97 E-02 1.55E-03 2.34E-02 2.00 E-0 1 1.62E+00 1.79E+00 9.1 OE-02 3.1 OE-02 4.68E-01 4.00E+00 (uCi/gm)
IC 8.08E-02 7.63E-01 5.39E-01 1.57E+00 8.08E-0 1 1.62E+00 1.53E+01 1.08E+01 3.14E+01 1.62E+01 (gm)
(uCi) 2.91 E+08 2.35E+07 2.22E+08 1.57E+08 4.57E+08 2.35 E+08 V(RCS)
A Free-Air Volume (cc)
"(f) 5.100E+09 Drywell Concentration (UCiCC)
AC 4.61 E-03 4.36E-02 3.07E-02 8.97E-02 4.61 E-02 2.15E-01 9.22E-02 8.71 E-01 6.15E-01 1.79E+00 4.29E+00 9.22E-01
Microshield V5.03 (5.03-00095)
PECO Energy Page
- 1 File Ref:
DOS File : OC-4UCII.MS5 Date:
3un Date: October 24, 2006 By:
3un Time: 1:17:23 PM Checked:
Duration : 00 : 00 : 02 Case
Title:
OCNGS 4 uCi/gm
==
Description:==
D/W Rad Monitor (Thyroid DCF)
Geometry: 13 - Rectangular Volume Source Dimensions Length 609.6 cm 20 ft 0.0 in Width 1.2e+3 cm 40 ft 0.0 in Height 1.2e+3 cm 40 ft 0.0 in Dose Points X
Y Z
- 1 612.648 cm 609.6 cm 609.6 cm 20 ft 1.2 in20 ft 0.0 in20 ft 0.0 in Shields Shield Name Dimension MaterialDensitv Source 3.20e+04 ft3 Air 0.00122 Air Gap Air 0.00122 Source Input Grouping Method : Standard Indices umber of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Library : Grove 1-131 8.3546e+001 3.0912e+012 9.2200e-002 3.4114e+003 1-132 7.8925e+002 2.9202e+013 8,7100e-001 3.2227e+004 1-133 5.5728e+002 2.0619e+013 6.1500e-001 2.2755e+004 1-134 1.6220e+003 6.0014e+013 1.7900e+000 6.6230e+004 1-135 8.3546e+002 3.0912e+013 9.2200e-001 3,4114e+004 Ba/cm3 Nuclide curies becauerels pC i / cm3 Buildup The material reference is : Source Integration Parameters X Direction 10 Y Direction 20 Z Direction 20 Enercrv Act ivi tv Fhence Rate MeV photons/sec MeV/cm2/sec No Buildun 0.03 1.418e+12 1.472e+04 0.08 8.093e+10 2.412e+03 0.15 2.956e+12 1.672e+05 0.2 2.417e+12 1.834e+05 0.3 2.541e+12 2.912e+05 Result s Fluence Rate MeV/cm2/sec with Buildun 1.743e+04 2.775e+03 1.842e+05 1.973e+05 3.079e+05 Exnosure Rate Exnosure Rate mR/hr mR/hr No Buildux, With Buildux, 1.459e+02 1.728e+02 3.817e+00 4.391e+00 2.754e+02 3.033e+02 3.236e+02 3.483e+02 5.524e+02 5.840e+02
Page z
30s File: OC-4UCII.MS5 Xun Date: October 24, 2006 Xun Time: 1:17:23 PM 3uration: 00:00:02 Enercrv MeV 0.4 0.5 0.6 0.8 1.0 1.5 2.0 Act ivi tv photons/sec Fluence Rate MeV/cm2/sec No BuilduQ 1.916e+06 6.840e+06 1.354e+07 4.267e+07 1.754e+07 1.752e+07 7.212e+06 Fluence Rate MeV/cm2/sec With Buildux, 2.005e+06 7.106e+06 1.400e+07 4.383e+07 1.795e+07 1.782e+07 7.310e+06 ExDosure Rate mR/hr No BuilduTa 3.734e+03 1.343e+04 2.642e+04 8.117e+04 3.233e+04 2.949e+04 1.115e+04 ExTaosure Rate mR/hr With BuilduD 3.906e+03 1.395e+04 2.732e+04 8.337e+04 3.308e+04 2.999e+04 1.130e+04 TOTALS: 3.370e+14 1.079e+08 1.107e+08 1.990e+05 2.043e+05
Peach Bottom
Peach Bottom (Effective DCF)
FSAR Activity Distribution Isotope (uCigm)
AD 1-1 31 0.1700 1-132 1.0200 1-133 1.0400 1-134 1.4700 1-1 35 1.3000 FGR 11 Effective DCF (RemlCi)
DCF 3.29E+04 3.81 E+02 5.85E+03 1.31 E+02 1.23E+03 1-131 0.1700 3.29E+04 1-1 32 1.0200 3.81 E+02 1-1 33 1.0400 5.85E+03 1-134 1.4700 1.31 E+02 1-1 35 1.3000 1.23E+03 Normalized DCF NDCF l.OOE+OO 1.16E-02 1.78E-01 3.98E-03 3.74E-02 l.OOE+OO 1.16E-02 1.78E-01 3.98E-03 3.74E-02 Normalized Activity Distribution (ucigm)
NC 1.70E-01 1.1 8E-02 1.85E-01 5.85E-03 4.86E-02 4.21 E-01 1.70E-01 1.18E-02 1.85E-01 5.85E-03 4.86E-02 4.21 E-01 Total Activity Isotopic DE 1-131 Isotopic Conc DE 1-131 Conc. Concentration RCS Volume Released Fraction (uCi/gm) f DE(l-131) 0.404 0.2 0.028 0.439 0.014 0.115 1.ooo 0.404 4.0 0.028 0.439 0.014 0.115 1.ooo (uCigm)
DEI-131 8.07E-02 5.61 E-03 8.78E-02 2.78E-03 2.31 E-02 2.00 E-0 1 1.61 E+OO 1.76E+00 1.12501 5.56E-02 4.62E-01 4.00E+00 (uCigm)
IC 8.07 E-02 4.84E-01 4.94E-01 6.98E-01 6.17E-01 1.61 E+OO 9.69E+00 9.88E+00 1.40E+01 1.23E+01 (9m)
(uCi) 2.67E+08 2.16E+07 1.29E+08 1.32E+08 1.86E+08 1.65E+08 v(RC.S)
A 4.31 E+08 2.59E+09 2.64E+09 3.73E+09 3.30E+09 Free-Air Drywell Volume Concentration (cc)
(UCiCC)
V(f)
AC 4.980E+09 4.33E-03 2.60E-02 2.65E-02 3.74E-02 3.31 E-02 1.27E-01 8.66 E-02 5.19E-01 5.30E-01 7.48E-01 6.62E-01 2.55E+00
PBAPS After the MSIV's close (10.5 sec), depressurization stops and natural convection is established through the reactor core. No fuel cladding perforation occurs even if the stored thermal energy in the fuel were simply redistributed while natural convection is being established; cladding temperature would be about l,OOO°F, well below the temperatures at which cladding can fail. Thus, it is concluded that even for a 10.5-sec MSIV closure, fuel rod perforations due to high temperature do not occur. For shorter valve closure times, the accident is less severe. After the MSIV's are closed, the reactor can be cooled by operation of any of the normal or standby cooling systems.
Reference 14.6.18 shows that adequate core cooling can be accomplished with no high pressure injection, manual initiation of ADS 10 minutes after MSIV closure, and either LPCI or Core Spray injection. The core flow and MCHFR during the first 10.5 sec of the accident are shown in Figures 14.6.17 and 14.6.18.
Since the MCHFR never drops below 1.0, the core is always cooled by very effective nucleate boiling.
14.6.5.2 Radioactive Material Release (See note at the beginning of Section 14.6.5.)
I 14.6.5.2.1 Assumptions The following assumptions are used in the calculation of the quantity and types of radioactive material released from the nuclear system process barriers outside the secondary containment.
- 1.
The amounts of steam and liquid discharged are as calculated from the analysis of the nuclear system transient.
- 2.
The concentration of biologically significant radionuclides contained in the coolant are as follows and are based on an off-gas release rate of 0.35 Ci/sec:
Iodine 131 Iodine 132 Iodine 133 Iodine 134 Iodine 135 0.17 pCi/cc 1.02 pci/cc 1.04 pCi/cc 1.47 pCi/cc 1.30 pCi/cc Because the steam-to-water halogen concentration ratio is on the order of 3 x lQ-5(8), only the halogens carried out of the reactor vessel by the liquid phase during the discharge of the steam-water mixture are significant. Because the coolant activity contents are based on data derived from reactor operation with an unusually large number of cladding failures, and because high normal stack gas discharge rate is assumed, considerable conservatism is inserted into the analysis.
14.6-37 Rev.
05/97 I
Exelon MAROG BWR CDAM, Version 1.1 Requirements Specification Y
.I 0
3 i!
Locat ion February, 2005 5 %
References 5E c a t :
g%
2; 0 0 ATTACHMENT 1 BWR CDAM METHODOLOGIES Suppression Pool 3.81 E+09 Liquid (ml)
Drywell 6.90E+09 Atmosphere (cc) 7.2.2 Normal Svstem Volumes C-l302-243-E610-081 RO 1
3.48E+09 2.46E+09' FSAR Table 6.2-4A FSAR Table 1.7.4 4.98E+09 5.1 OE+09 FSAR Table 6.2-4A FSAR Table 1.7.4 C-1302-900-E610-026 RO Normal system volumes are used as default values, since operator actions or accident events can significantly change actual volumes, the program shall allow end user to manually enter values based on conditions at time of accident.
3.74E+09 C-1302-900-E610-026 RO 3.51 E+09' FSAR Table 6.2-4A FSAR Table 1.7.4 I
1 2.93E+08 2.67E+08 2.91 E+08 FSAR Table 6.2-4A I
I 1
FSAR Table 1.7.4 1 RCS Liquid (ml)
Suppression Pool Atmosphere (cc) 4,18E+09
- 1) Average of Minimum and M; A. Volume Corrections I
I C-l302-900-E610-026 RO nimum from referenced calculation A volume correction is necessary whenever a single sample is taken and the two locations (Reactor Coolant and Containment Sump) are not in a state of equilibrium (when the released activity is not assumed to be spread throughout both sample locations). The volume correction is as follows:
Volume Sampled Location Volume Both Locations 7.2.3 Pressu re/Tem c3e ratu re Correction The pressure/temperature correction is applied to gaseous samples and is used to account for differences between system pressure and temperature, and sample pressure and temperature. The pressure/temperature correction is as follows:
(P System +14-7) x (T sample +460)
(P sample +14-7) x (T system +460)
PTC =
38 of 45 Revision 0
Microshield v5.03 (5.03-00095)
PECO Energy Page
- 1 DOS File: PB-02UCI.MS5 Run Date: October 16, 2006 Run Time: 1:48:33 PM Duration: 00 : 00 : 02 File Ref:
Date:
By:
Checked :
Case
Title:
PBAPS O02uCi/gm
==
Description:==
D/W Rad Monitor Geometry: 13 - Rectangular Volume Enerav MeV 0.03 0.08 0.15 0.2 0.3 Source Dimensions Length 609.6 cm 20 ft 0.0 in Width 1.2e+3 cm 40 ft 0.0 in Height 1.2e+3 cm 40 ft 0.0 in Dose Points X
Y Z
- 1 612.648 cm 609.6 cm 609.6 cm 20 ft 1.2 in20 ft 0.0 in20 ft 0.0 in Shields Shield Name Dimension MaterialDensitv Source 3.20e+04 ft3 Air 0.00122 Air Gap Air 0.00122 L
Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Eibrary : Grove 1-131 3.9236e+000 1.4517e+011 4.3300e-003 1.6021e+002 1-132 2.3560e+001 8.7171e+011 2.6000e-002 9.6200e+002 1-133 2.4013e+001 8.8847e+011 2.6500e-002 9.8050e+002 1-134 3.3890e+001 1.2539e+012 3.7400e-002 1.3838e+003 1-135 2.9993e+001 1.1097e+012 3.3100e-002 1.2247e+003 Nuclide curies becmerels r].Ci/cm3 Bcr/cm3 Buildup The material reference is : Source Integration Parameters X Direction 10 Y Direction 20 Z Direction 20 Result s Act ivi tv Fluence Rate Fluence Rate photons/sec MeV/cm2/sec MeV/cm2/sec No Buildux, With Buildux, 3.859e+10 4.005e+02 4.742e+02 3.801e+09 1.133e+02 1.303e+02 6.237e+10 3.529e+03 3.888e+03 6.026e+10 4.570e+03 4.919e+03 8.409e+10 9.639e+03 1.019e+04 Exx,osure Rate Emosure Rate mR/hr mR/hr No Buildux, With Buildux>
3.969e+00 4.699e+00 1.793e-01 2.062e-01 5.812e+00 6.402e+00 8.067e+00 8.681e+00 1.828e+01 1.933e+01
Page
- 2 DOS File: PB-02UCI.MS5 Run Date: October 16, 2006 Run Time: 1:48:33 PM Duration : 00 : 00 : 02 Enerqv MeV Act ivi tv photons / sec 0.4 3.584e+11 0.5 1.244e+12 0.6 1.568e+12 0.8 3.190e+12 1.0 1.220e+12 1.5 9.257e+11 2.0 2.512e+11 Fluence Rate MeV/cm2/sec No BuilduD 5.506e+04 2.399e+05 3.638e+05 9.913e+05 4.755e+05 5.442e+O5 1.976e+05 Fluence Rate MeV/cm2/sec with BuilduD 5.760e+04 2.492e+05 3.761e+05 1.018e+06 4.865e+05 5.535e+05 2.003e+05 ExDosure Rate mR/hr No BuilduD 1.073e+02 4.709e+02 7.101e+02 1.885e+03 8.765e+02 9.156e+02 3.056e+02 ExDosure Rate mR/hr with BuilduD 1.122e+02 4.892e+02 7.342e+02 1.937e+03 8.967e+02 9.313e+02 3.097e+02 TOTALS: %006e+12 2.886e+06 2.961e+06 5.308e+03 5.449e+03
Page
- 1 DOS File: PB-4UCI.MS5 Run Date: October 16, 2006 Run Time: 1:50:05 PM Duration: 00:00:02 Microshield ~5.03 (5.03-00095)
PECO Energy Case
Title:
PBAPS 4 uCi/gm
==
Description:==
D/W Rad Monitor Geometry: 13 - Rectangular Volume File Ref:
Date:
By:
Checked :
Length Width Height Source Dimensions 609.6 cm 20 ft 0.0 in 1.2e+3 cm 40 ft 0.0 in 1.2e+3 cm 40 ft 0.0 in Dose Points X
Y Z
- 1 612.648 cm 609.6 cm 609.6 cm 20 ft 1.2 in20 ft 0.0 in20 ft 0.0 in Shields Shield Name Dimension MaterialDensitv Source 3.20e+04 ft3 Air 0.00122 Air Gap Air 0.00122 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Library : Grove 1-131 7.8472e+001 2.9035e+012 8.6600e-002 3.2042e+003 1-132 4.7029e+002 1.7401e+013 5.1900e-001 1.9203e+004 1-133 4.8025e+002 1.7769e+013 5.3000e-001 1.9610e+004 1-134 6.7779e+002 2.5078e+013 7.4800e-001 2.7676e+004 1-135 5.9986e+002 2.2195e+013 6.6200e-001 2.4494e+004 Nuclide curies becauerels gCi/cm3 Ba/cm3 Bu i 1 dup The material reference is : Source Integration Parameters X Direction 10 Y Direction 20 Z Direction 20 Results Enercrv Act ivi tv Fluence Rate Fluence Rate MeV photons/sec MeV/cm2/sec MeV/cm2/sec No Buildux, with Buildux, 0.03 7.715e+11 8.008e+03 9.481e+03 0.08 7.602e+10 2.266e+03 2.606e+03 0.15 1.247e+12 7.058e+04 7.775e+04 0.2 1.205e+12 9.141e+04 9.837e+04 0.3 1.681e+12 1.927e+05 2.037e+05 ExDosure Rate ExDosure Rate mR/hr mR/hr No Buildux, With Buildux, 7.937e+01 9.396e+Ol 3.585e+00 4.124e+00 1.162e+02 1.280~+02 1.613e+02 1 736e+02 3.655e+02 3.864e+02
Page
- 2 DOS File: PB-4UCI.MS5 Run Date: October 16, 2006 Run Time: 1:50:05 PM Duration: 00:00:02 Enerw MeV 0.4 0.5 0.6 0.8 1.0 1.5 2.0 Activi tv photons/sec Fluence Rate MeV/cm2/sec No Builduo 1.101e+06 4.796e+06 7.266e+06 1.982e+07 9.506e+06 1.088e+07 3.951e+06 Fluence Rate MeV/cm2/sec With Builduo 1.152e+06 4.983e+06 7.513e+06 2.035e+07 9.726e+06 1.107e+07 4.004e+06 ExDosure Rate mR/hr No Buildur, 2.146e+03 9.415e+03 1.418e+04 3.769e+04 1.752e+04 1.831e+04 6.110e+03 TOTALS: 1.800e+14 5.768e+07 5.919e+07 1.061e+05 Exoosure Rate mR/hr with Buildun 2.244e+03 9.781e+03 1.466e+04 3.871e+04 1.793e+04 1.862e+04 6.192e+03 1.089e+05
Peach Bottom (Thyroid DCF)
FSAR Activity FGR 11 Thyroid Distribution AD Isotope (uCigm) 1-131 0.1700 1-132 1.0200 1-133 1.0400 1-1 34 1.4700 1-1 35 1.3000 1-1 31 0.1700 1-1 32 1.0200 1-133 1.0400 1-1 34 1.4700 1-135 1.3000 DCF (RedCi)
DCF 1.08E+06 6.44E+03 1.80E+05 1.07E+03 3.13E+04 1.08E+06 6.44E+03 1.80E+05 1.07E+03 3.13E+04 Normalized DCF NDCF l.OOE+OO 5.96 E-03 1.66E-01 9.86E-04 2.90E-02 l.OOE+OO 5.96E-03 1.66E-01 9.86E-04 2.90E-02 Normalized Distribution Isotopic Conc DE 1-131 Conc. Concentration RCS Volume Released Activity DE 1-131 Isotopic Total Activity (uCigm)
NC 1.70E-01 6.08E-03 1.73E-01 1.45E-03 3.77E-02 3.88E-01 Fraction (ucigm) f DE(I-131) 0.438 0.2 0.016 0.446 0.004 0.097 1.ooo 1.70E-01 0.438 4.0 6.08E-03 0.016 1.73E-01 0.446 1.45E-03 0.004 3.77E-02 0.097 3.88 E-0 1 1.ooo (uCigm)
DEI-131 8.76E-02 3.13E-03 8.92E-02 7.47E-04 1.94E-02 2.00E-01 1.75E+00 1.78E+00 6.26E-02 1.49E-02 3.88E-01 4.00E+00 (uCigm)
IC 8.76E-02 5.25E-01 5.36E-01 7.57E-01 6.70E-01 1.75E+00 1.05E+01 1.07E+01 1.51 E+01 1.34E+01 (sm)
(uCi) 2.67E+08 2.34E+07 1.40E+08 1.43E+08 2.02E+08 1.79E+08 v(RCS)
A 4.68E+08 2.81 E+09 2.86E+09 4.04E+09 3.58E+09 Free-Air Drywell Volume Concentration (cc)
(UCiCC)
V(f)
AC 4.980E+09 4.69E-03 2.82E-02 2.87E-02 4.06 E -02 3.59E-02 1.38E-01 9.39E-02 5.63E-01 5.74E-01 8.12E-01 7.18E-01 2.76E+00
Microshield v5.03 (5.03-00095)
PECO Energy Page
- l DOS File : PB-4UCII.MS5 Run Date: October 24, 2006 Run Time: 1:14:46 PM Duration: 00:00:02 Enercrv MeV 0.03 0.08 0.15 0.2 0.3 Case
Title:
PBAPS 4 uCi/gm
==
Description:==
D/W Rad Monitor (Throid DCF)
Geometry: 13 - Rectangular Volume 2
File Ref:
Date:
By:
Checked :
Source Dimensions Length 609.6 cm 20 ft 0.0 in Width 1.2e+3 cm 40 ft 0.0 in Height 1.2e+3 cm 40 ft 0.0 in Dose Points X
Y Z
- 1 612.648 cm 609.6 cm 609.6 cm 20 ft 1.2 in20 ft 0.0 in20 ft 0.0 in Shields Shield Name Dimension MaterialDensitv Source 3.20e+04 ft3 Air 0.00122 Air Gap Air 0.00122 L
Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Libraw : Gxove 1-131 8.5086e+001 3.1482e+012 9.3900e-002 3.4743e+003 1-132 5.1016e+002 1.8876e+013 5.6300e-001 2.0831e+004 1-133 5.2012e+002 1.9245e+013 5.7400e-001 2.1238e+004 1-134 7.3578e+002 2.7224e+013 8.1200e-001 3.0044e+004 1-135 6.5061e+002 2.4072e+013 7.1800e-001 2.6566e+004 Nuclide curies beccruerels pci / cm Bcr/cm3 Buildup The material reference is : Source Integration Parameters X Direction 10 Y Direction 20 Z Direction 20 Results Act ivi tv Fluence Rate Fluence Rate ExDosure Rate photons/sec MeV/cm2/sec MeV/cm2/sec mR/hr No Buildux,, With BuilduD No Buildux, 8.370e+11 8.688e+03 1.029e+04 8.610e+01 8.243e+10 2.457e+03 2.826e+03 3.887e+00 1.354e+12 7.662e+04 8.440e+04 1.262e+02 1.308e+12 9.919e+04 1.067e+05 1.751e+02 1.823e+12 2.090e+05 2.209e+05 3.964e+02 ExDosure Rate mR/hr With Buildup 1.019e+02 4.472e+00 1.390e+02 1.884e+02 4.190e+02
age
- 2 0s File: PB-4UCII.MS5 un Date: October 24, 2006 un Time: 1:14:46 PM uration: 00:00:02 Enerav Act ivi tv Fluence Rate Fluence Rate Exx,osure Rate Exgosure Rate No Builduo with Buildug No Buildux, with Buildug MeV photons/sec MeV/cm2/sec MeV/cm2/sec mR/hr mR/hr 0.4 7.777e+12 1.195e+06 1.250e+06 2.328e+03 2.435e+03 0.5 2.696e+13 5.198e+06 5.400e+06 1.020e+04 1.060e+04 0.6 3.398e+13 7.883e+06 8.151e+06 1.539e+04 1.591e+04 0.8 6.920e+13 2.151e+07 2.209e+07 4.090e+04 4.201e+04 1.0 2.646e+13 1.031e+07 1.055e+07 1.901e+04 1.945e+04 1.5 2.008e+13 1.180e+07 1.201e+07 1.986e+04 2.020e+04 2.0 5.451e+12 4.287e+06 4.345e+O6 6.629e+03 6.719e+03 6.258e+07 6.422e+07 1.151e+05 1.182e+05 TOTALS:
1.953e+14
Quad Cities
Quad Cities (Effective DCF)
Isotope 1-1 31 1-132 1-1 33 1-1 34 1-135 1-1 31 1-1 32 1-133 1-134 1-135 FSAR Activity Distribution (uCigm)
AD 0.0250 0.2500 0.1000 0.2500 0.2500 FGR 11 Effective DCF (RemlCi)
DCF 3.29E+04 3.81 E+02 5.85E+03 1.31 E+02 1.23E+03 0.0250 3.29E+04 0.2500 3.81 E+02 0.1000 5.85E+03 0.2500 1.31 E+02 0.2500 1.23E+03 Normalized DCF NDCF l.OOE+OO 1.1 6E-02 1.78E-01 3.98E-03 3.74E-02 l.OOE+OO 1.16E-02 1.78E-01 3.98E-03 3.74E-02 Normalized Activity Distribution (uCigm)
NC 2.50E-02 2.90E-03 1.78E-02 9.95E-04 9.35E-03 5.60E-02 2.50E-02 2.90E-03 1.78E-02 9.95 E-04 9.35E-03 5.60E-02 DE 1-131 Isotopic Total Activity Isotopic Conc DE 1-131 Conc.
Concentration RCS Volume Released Fraction (uCigm) f DE(I-131) 0.446 0.2 0.052 0.31 7 0.018 0.167 1.ooo 0.446 4.0 0.052 0.317 0.01 8 0.167 1.ooo (uCigm)
DEI-131 8.93E-02 1.03E-02 6.35E-02 3.55E-03 3.34E-02 2.00E-01 1.79E+00 1.27E+00 2.07E-01 7.1 1 E-02 6.67E-01 4.00E+00 (uCigm)
IC 8.93E-02 8.93E-01 3.57E-01 8.93E-01 8.93E-01 1.79E+00 1.79E+01 7.14E+00 1.79E+01 1.79E+01 (gm)
(uCi) 2.61 E+08 2.33E+07 2.33E+08 9.32E+07 2.33E+08 2.33E+08 V(RCS)
A 4.66 E+08 4.66E+09 1.86E+09 4.66E+09 4.66E+09 Free-Air Drywell Volume Concentration (cc)
(UCiCC)
V(f)
AC 4.470E+09 5.21 E-03 5.21 E-02 2.08E-02 5.21 E-02 5.21 E-02 1.82E-01 1.04E-01 1.04E+00 1.04E+00 1.04E+00 3.65E+00 4.17E-01
QUAD CITIES -
UFSAR 15'6. $5 Radiological C onseque ncc s The fullowing describes main steam line break radiological dose analyses performed for the initial licensing of the plant, ia., 7x7 fuel arrays.
The predominant activity in the discharged coolant would be N-16, which would be significantly reduced by decay due to its short half-life (about 7 seconds). If the reactor contained fuel with cladding leaks, the water released through the break would contain some fission products. [15.6-18]
During 1964 the Dresden Unit 1 reactor was operated with a significant number of cladding leaks. Analysis of reactor water sample8 indicated the following yearly average fission product content:
Activity Fission Product i i k Cilcc)
I-13 2 0.025 I-133 0.1 Other halogens 0.25 Other fission products 0.25 With a separate reactor cleanup system for each unit, it is estimated that the maximum coolant activity would be approximately 2.3 pCilcc at 100,000 pCi/s release rate, and would have the following fission product contents:
Fission Product 1-132 I-133 1-134 Other halogens Other fission products 1-131 1-135 Activity 0.067 0.38 0.40 0.53 0.49 0.14 0.28 IpCilcc)
Measurements of halogen concentrations in the Dresden Unit 1 reactor water and condensate showed that the steam to water halogen concentration ratio was in the range of 3 x fO'3 to 1 x 10'". The only halogens carried out through the break would therefore be those absorbed in the water, Thus, 116 curies, including 3.4 curies of 1-131, 19.1 curies of 1-132, 20.2 curies of1-33, 27.0 curies of 1-134, and 24.9 curies of 1-135 would be carried out through the break.
Based on operating experience, the above fission product concentrations in the reactor coolant would occur when the off-gas emission was at about 100,000 pCi/s measured after 30 minutes decay in the off-gas system. The noble gas activity discharged from the break, assuming a l U. 5 seconds MSfV closure time, would be 5.4 Ci (calculated for 2 minutes decay time).
Revision 4, April. 1997
Exalon BW R CDAM, Version I
.O Requirements Specification December, 2002 L,
ATTACHMENT 1 BWR CDAM METHQDOLOGIES a9 c
I I
E s C
4 m
6 3
I*I, i3 Location RCS (ml)
I 3.16E+08 2.61 E+08 4.1 'iE+08 Exalon BW R CDAM, Version I
.O Requirements Specification December, 2002 L,
ATTACHMENT 1 BWR CDAM METHQDOLOGIES (10 Q)
'3 3
P Reference 2.61 E+08 Clinton USAR Fig 5.1-2 7.2.2 Norrnal System Volumes Suppression Pool Liquid (mi)
Normal system volumes are used as default values, since operator actions or accident events can significantly change actual volumes, the program shall allow end user to manually enter values based on conditions at time of accident.
- 4. 1 5E+09 3.26E+09 3.68+09 3.26E+09 4.47E+09 DresdenlQuad Cities taken from NED0 22215.
DWQC UFSAR Section 6 (1.I 5E+05 Ft3, 3.266+09 ml)
LS UFSAR Cont Design Param (1.30E+05 Ft3, 3.68E+09 mi)
OFUQC UFSAR Section 6 6.97+09 Atmosphere (cc) 3.40E+09
- ~ _ _ _ _ _ _ ~
~
Containment Atmosphere (cc)
Suppression Pool Atmosphere (cc)
DFUQC UFSAR Section 6
( I.
15E+05 Ft3, 3.26E+09 ml) 4.47E+09 6.51E+09 NIA NIA NIA I
.30E+05 Ft3, 3.68E+09 mi)
A. Volume Corrections A volume correction is necessary whenever a single sample is taken and the two locations (Reactor Coolant and Containment Sump) are not in a state of equilibrium (when the released activity is not assumed to be spread throughout both sample locations). The volume correction is as fotlows:
Volume Sampled Location Volume Both Locations 1
vc=
SWR CDAM Product ID EX0006322 39 of 46 Revision 0
Microshield ~ 5. 0 3 (5.03-00095)
PECO Energy Page
- 1 DOS File: QC-02UCI.MS5 Run Date: October 16, 2006 Run Time: 2:02:51 PM Duration: 00 : 00 : 02 Enercrv MeV 0.03 0.08 0.15 0.2 0.3 Case
Title:
Quad Cities O02uCi/g
==
Description:==
D/W Rad Monitor Geometry: 13 - Rectangular Volume File Ref:
Date:
By:
Checked :
Source Dimensions Length 609.6 cm 20 ft 0.0 in width 1.2e+3 cm 40 ft 0.0 in Height 1.2e+3 cm 40 ft 0.0 in Dose Points X
Y Z
- 1 612.648 cm 663.6 cm 663.6 cm 20 ft 1.2 in20 ft 0.0 in20 ft 0.0 in Shields Shield Name Dimension MaterialDensitv Source 3.20e+04 ft3 Air 0.00122 Air Gap Air 0.00122 Source Input Grouping Method : Standard Indices hPumber of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Library : Grove 1-131 4.7210e+000 1.7468e+011 5.2100e-003 1.9277e+002 1-132 4.7210e+001 1.7468e+012 5.2100e-002 1.9277e+003 1-133 1.8848e+001 6.9736e+011 2.0800e-002 7.6960e+002 1-134 4.7210e+001 1.7468e+012 5.2100e-002 1.9277e+003 1-135 4.7210e+001 1.7468e+012 5.2100e-002 1.9277e+003 Nuclide curies becauerel s pCi / cm3 Bcr/cm3 Buildup The material reference is : Source X
Y Z
Activitv photons/sec Integration Parameters Direct ion 10 Direct ion 20 Direct ion 20 Results Fluence Rate Fluence Rate ExDosure Rate MeV/cm2/sec MeV/cm2/sec mR / hr No Buildux, With Buildux, No Buildun 5.530e+02 6.547e+02 5.481e+00 1.363e+02 1.568e+02 2.157e-01 4.988e+03 5.494e+03 8.214e+00 6.718e+03 7.230e+03 1.186e+01 1.521e+04 1.607e+04 2.884e+01 ExDosure Rate mR/hr With BuilduD 6.489e+00 2.481e-01 9.047e+00 1.276e+01 3.049e+01
Page
- 2 30s File: QC-02UCI.MS5 3un Date: October 16, 2006 3un Time: 2:02:51 PM hration: 00 : 00 : 02 Enerav Activitv MeV photons / sec 0.4 4.966e+11 0.5 1.395e+12 0.6 2.857e+12 0.8 4.921e+12 1.0 1.926e+12 1.5 1.467e+12 2.0 3.896e+11 Fluence Rate MeV/cm2/sec No BuilduQ 7.629e+04 2.690e+05 6.630e+05 1.529e+06 7.505e+05 8.625e+05 3.064e+05 TOTALS: 1.382e+13 4.485e+06 Fluence Rate MeV/cm2/sec with Buildur, 7.980e+04 2.794e+05 6.855e+05 1.571e+06 7.679e+05 8.772e+05 3.105e+05 4.601e+06 ExQosure Rate mR / hr No Buildux>
1.486e+02 5.280e+02 1.294e+03 2.909e+03 1.383e+03 1.451e+03 4.738e+02 8.242e+03 ExQOSure Rate mR/hr with BuilduD 1.555e+02 5.485e+02 1.338e+03 2.988e+03 1.415e+03 1.476e+03 4.802e+02 8.460e+03
Microshield v5.03 (5.03-00095)
PECO Energy Page
- 1 File Ref:
DOS File : QC-4UCI.MS5 Date:
Run Date: October 16, 2006 By :
Run Time: 2:04:31 PM Checked :
Duration : 00 : 00 : 02 Case
Title:
Quad Cities 4 uCi/g
==
Description:==
D/W Rad Monitor Geometry: 13 - Rectangular Volume Source Dimensions Length 609.6 cm 20 ft 0.0 in Width 1.2e+3 cm 40 ft 0.0 in Height 1.2e+3 cm 40 ft 0.0 in Dose Points X
Y Z
- 1 612.648 cm 609.6 cm 609.6 cm 20 ft 1.2 in20 ft 0.0 in20 ft 0.0 in Shields Shield Name Dimension MaterialDensitv Source 3.20e+04 ft3 Air 0.00122 Air Gap Air 0.00122 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Library : Grove 1-131 9.4238e+001 3.4868e+012 1.0400e-001 3.8480e+003 1-132 9.4238e+002 3.4868e+013 1.0400e+000 3.8480e+004 1-133 3.7786e+002 1.3981e+013 4.1700e-001 1.5429e+004 1-134 9.4238e+002 3.4868e+013 1.0400e+000 3.8480e+004 1-135 9.4238e+002 3.4868e+013 1.0400e+000 3.8480e+004 Nuc 1 i de curies becauerels pci/cm3 Ba/cm3 Buildup The material reference is : Source Integration Parameters X Direction 10 Y Direction 20 Z Direction 20 Results Enerw Ac tivi tv Fluence Rate Fluence Rate Exnosure Rate Exnosure Rate MeV photons/sec MeV/cm2/sec MeV/cm2/sec No Buildur, With Buildur, No Buildux, With Buildux, 0.03 1.064e+12 1.104e+04 1.307e+04 1.094e+02 1.296e+02 0.08 9.129e+10 2.721e+03 3.130e+03 4.306e+00 4.953e+00 0.15 1.760e+12 9.957e+04 1.097e+05 1.640e+02 1.806e+02 0.2 1.768e+12 1.341e+05 1.443e+05 2.367e+02 2.547e+02 0.3 2.648e+12 3.036e+05 3.209e+05 5.758e+02 6.087e+02 mR/hr mR/hr
Page
- 2 DOS File: QC-4UCI.MS5 Xun Date: October 16, 2006 Zun Time: 2:04:31 PM Duration: 00 : 00 : 02 Enerqv MeV 0.4 0.5 0.6 0.8 1.0 1.5 2.0 Act ivi tv photons / sec Fluence Rate MeV/cm2/sec No BuilduD 1.523e+06 5.380e+06 1.323e+07 3.053e+07 1.498e+07 1.722e+07 6.117e+06 Fluence Rate MeV/cm2/sec with Buildux, 1.593e+06 5.589e+06 1.368e+07 3.136e+O7 1.533e+07 1.751e+07 6.199e+06 TOTALS: 2.759e+14 8.953e+07 9.185e+07 ExDosure Rate mR/hr No Buildux, 2.967e+03 1.056e+04 2.583e+04 5.807e+04 2.762e+04 2.897e+04 9.459e+03 1.646e+05 ExDosure Rate mR/hr with BuilduQ 3.104e+03 1.097e+04 2. 671e+04 5.964e+04 2.826e+04 2.946e+04 9.586e+03 1.689e+05
(Thyroid DCF)
Isotope 1-1 31 1-132 1-133 1-134 1-135 1-1 31 1-1 32 1-1 33 1-134 1-135 FSAR Normalized Activity FGR 11 Thyroid Activity DE 1-131 Isotopic Total Activity Distribution DCF Normalized Distribution Isotopic Conc DE 1-1 31 Conc.
Concentration RCS Volume Released (uciigm)
(RedCi)
AD DCF 0.0250 l.O8E+06 0.2500 6.44E+03 0.1000 1.80E+05 0.2500 1.07E+03 0.2500 3.13E+04 0.0250 1.08E+06 0.2500 6.44E+03 0.1000 1.80E+05 0.2500 1.07E+03 0.2500 3.1 3E+04 DCF NDCF l.OOE+OO 5.96E-03 1.66E-01 9.86E-04 2.90E-02 l.OOE+OO 5.96E-03 1.66E-01 9.86E-04 2.90E-02 (uCigm)
NC 2,50E-02 1.49E-03 1.66E-02 2.47E-04 7.24E-03 5.06E-02 Fraction (uciigm) f DE(I-131) 0.494 0.2 0.029 0.329 0.005 0.143 1.ooo 2.50E-02 0.494 4.0 1.49E-03 0.029 1.66E-02 0.329 2.47E-04 0.005 7.24E-03 0.143 5.06E-02 1.OOO (uCVgm)
DEl-131 9.88E-02 5.89E-03 6.58E-02 9.74E-04 2.86E-02 2.00E-01 1.98E+00 1.32E+00 1.18E-01 1.95E-02 5.72E-01 4.00E+00 (uciigm)
IC 9.88 E-02 9.88E-01 3.95E-01 9.88E-01 9.88E-01 (sm)
(uCi) 2.61 E+08 2.58E+07 2.58E+08 1.03E+08 2.58E+08 2.58E+08 v,Fics, A
Free-Air Drywell Volume Concentration (cc)
(UCVCC)
V(f, AC 4.470E+09 5.77E-03 5.77E-02 2.31 E-02 5.77E-02 5.77 E-02 2.02E-01 1.15E-01 l.l5E+00 1.1 5E+00 1.15E+00 4.04E+00 4.61 E-01
Microshield v5.03 (5.03-00095)
PECO Energy
'age
- 1 File Ref:
10s File: QC-4UCII.MS5 Date:
Lun Date: October 24, 2006 By:
Lun Time: 1:26:03 PM Checked :
hration: 00:00:02 Case Titlet Quad Cities 4 uCi/g
==
Description:==
D/W Rad Monitor (Thyroid DCF)
Geometry: 13 - Rectangular Volume Source Dimensions Length 609.6 cm 20 ft 0.0 in Width 1.2e+3 cm 40 ft 0.0 in Height 1.2e+3 cm 40 ft 0.0 in Dose Points X
Y Z
- 1 612.648 cm 609.6 cm 609.6 cm 20 ft 1.2 in20 ft 0.0 in20 ft 0.0 in Shields Shield Name Dimension MaterialDensitv Source 3.20e+04 ft3 Air 0.00122 Air Gap Air 0.00122 Source Input Grouping Method t Standard Indices Number of Groups t 25 Lower Energy Cutoff : 0.015 Photons < 0,015 t Excluded Libraw t Grove 1-131 1.0421e+002 3.8556e+012 1.1500e-001 4.2550e+003 1-132 1.0421e+003 3.8556e+013 l.l500e+000 4.2550e+004 1-133 4.1773e+002 1.5456e+013 4.6100e-001 1.7057e+004 1-134 1.0421e+003 3.8556e+013 1.1500e+000 4.2550e+004 1-135 1.0421e+003 3.8556e+013 1.1500e+000 4.2550e+004 Nuclide curies becauerels pCi / cm3 Ba/cm3 Buildup The material reference is t Source Integration Parameters X Direction 10 Y Direction 20 Z Direction 20 Enerav Act ivi tv Fluence Rate MeV photons/sec MeV/cm2/sec No Buildux, 0.03 1. 176e+12 1.221e+04 0.08 1.009e+11 3.009e+03 0.15 1.946e+12 1.101e+05 0.2 1.955e+12 1 483e+05 0.3 2.928e+12 3.357e+05 Results Fluence Rate Emosure Rate MeV/cm2/sec mR/hr with Buildux, No Builduz, 1.446e+04 1.210e+02 3.461e+03 4.761e+00 1.213e+05 lO813e+02 1.596e+05 2.617e+02 3.548e+05 6.367e+02 Ex-aosure Rate mR/hr with Buildu-a 1.433e+02 5.476e+00 1.997e+02 2.817e+02 6.731e+02
'age 2
10s File: QC-4UCII.MS5 tun Date: October 24, 2006 tun Time: 1:26:03 PM Iuration : 0 0 : 0 0 : 02 Enerav Act ivi tv Fluence Rate MeV photons/sec MeV/cm2/sec No Buildu-a 0.4 1.096e+13 1.684e+06 0.5 3.086e+13 5.948e+06 0.6 6.307e+13 1.463e+07 0.8 1.086e+14 3.376e+O7 1.0 4.251e+13 1.657e+07 1.5 3 238e+13 1.904e+07 2.0 8.599e+12 6.763e+06 Fluence Rate MeV/cm2/sec With Buildux, 3,.762e+06 6.179e+06 1.513e+07 3.467e+07 1.695e+07 1.936e+07 6.855e+06 Exnosure Rate mR / hr No Buildux, 3.281e+03 lo168e+04 2.856e+04 6.421e+04 3.054e+04 3.203e+04 1.046e+04 Ex-aosure Rate mR/hr With Buildux, 3.432e+03 1.213e+04 2.953e+04 6.595e+04 3.124e+04 3.258e+04 1.060e+04 TOTALS: 3.051e+14 9.900e+07 1.016e+08 1.820e+05 1.868e+05
EP-EAL-0611, Rev 1 Page 1 PWR Assumptions:
RCS Liquid and Free-Air volumes were obtained from the PWR Core Damage Assessment Model (CDAM) Requirements Specification o Mid-Atlantic Version 1.O, Section 7.2.2, Sample Volume Calculations and Corrections o Mid-West Version 1.0, Section 7.2.2 Sample Volume Calculations and Corrections with the following exceptions:
o None It is assumed the entire Liquid RCS volume is instantaneously released to the Containment volume and all entrained Iodine and Noble Gas immediately disperses homogeneously throughout the free air space.
Free Air Volumes are as described in the CDAM documentation included in this calculation.
The RCS Dose Equivalent 1-131 values of interest (0.35 uCi/gm and 60.0 uCi/gm) were obtained from the sites Technical Specifications and were specifically requested by the Revision 4 EAL implementation team for this calculation. These are standard Technical Specification values for Pressurized Water Reactors.
Isotopes of Iodine and Noble Gas were used in the calculation. Unlike BWRs, which are constantly degassing, a considerable amount of Noble Gas is entrained within the Reactor Coolant that will be released to the free air volume upon depressurization. RCS Noble Gas concentrations are based on 1% failed fuel and will remain constant despite changes in the Dose Equivalent Iodine values Dose Conversion factors used to calculate Isotopic Concentrations were obtained from FGR 11. Though these factors are for Alternative Source Term (AST) calculations, when normalized to 1-13 1 they adequately represent the mixture of Iodines in the coolant. The Dose Conversion Factors from FGR 11 were obtained from Table 2.1, column Effective. The choice of using values from the Effective column was based on the methodology used for AST calculations and section 4.1.2 of Regulator Guide 1.183 which states:
EP-EAL-06 1 1, Rev 1 Page 2 The exposure-to-CEDE factor for inhalation of radioactive material should be derived from data provided in ICRP Publication 30, Limits for Intakes of radionuclides by Workers (Ref. 19). Table 2.1 of Federal Guidance Report 1 1, Limiting values of Radionuclide Intake and Air Concentration and Dose Conversion factors for Inhalation, Submersion, and Ingestion (Ref. 20), provides tables of conversion factors acceptable to the NRC staff. The factors in the column headed EJScective yield doses corresponding to the CEDE.
Since only the Nomalized ratios are used in the calculation, unit conversion is not required, however the international units of Sv/Bq were converted to RedCi for ease of understanding.
Additional calculations were performed using the FGR 1 1 Table 2.1, column Thyroid Dose Conversion Factors for comparison purposes. The calculations were limited to the 60.0 uCi/gm DEI-13 1 values. The results of these calculations are included in the Results table at the end of this attachment.
Microshield Model:
A generic approach was taken when constructing the Microshield model since each sites actual configuration is different. Even though the entire air space volume is available for dilution of the released radioactive isotopes, the radiation detectors located within the containment are not exposed to the entire volume. Therefore a cylindrical source representing the entire containment was not used. Instead, a box was constructed in the Microshield model that approximates the size of the area that a detector would be exposed to. The box measured 30 feet in depth (distance from the mounted wall to the closest significant wall), 40 feet tall, and 40 feet wide. A dose receptor point, representing the detector, was placed on the outer edge of the wall halfway up and across the box.
This best represents the location of a radiation detector within the containment mounted on a wall. No attempt was made to simulate shielding from components within the containment nor was any credit taken for backscatter from the surrounding walls or components. The box was then filled with the calculated isotopic concentrations to determine a dose rate at the given point.
Me thodology :
Microshield requires a given concentration in uCi/cc or uCi/gm for each isotope of interest. To obtain those concentrations requires converting the given I-13 1 Dose Equivalent concentration (0.35 uCi/cc and 60.0 uCi/cc) to their individual isotopes components. In this case an equivalent for I-13 1, I-132, I-133, I-134 and I-135. Noble Gas concentrations are independent of I-13 1 Dose Equivalent Concentrations and were calculated with a different methodology then Iodines.
EP-EAL-06 1 1, Rev 1 Page 3 Iodine Conversion Calculations Normalized I-13 1 Equivalent Activity Distribution A normalized I-13 1 equivalent activity distribution for each isotope was calculated using the relative mix of the isotopes of interest for each facility.
These ratios vary from site to site and are listed on the individual spreadsheets.
Copies of the source documents are contained within this calculation. The normalized value is calculated using the following equation:
Where:
DCF(i) = Isotopes FGR-1 1 Dose Conversion Factor (See Assumptions for details)
DCF(1-131) = 1-13 1 FGR-11 Dose Conversion Factor (See Assumptions for details)
NDCF(i) = The Isotopes ratio normalized to I-13 1.
Since only the normalized DCF values are used in the calculation, no unit conversion is necessary.
AD(i,
- NDCF(i, = NC(,,
Where:
AD(i) = Activity Distribution (See the included calculation data for individual sites distribution numbers)
NC(i) = Normalized I-13 1 Equivalent Activity Distribution Calculate the Fraction of each normalized concentration Where:
hi) = Fraction of each isotope's normalized activity distribution.
Calculate the Dose Equivalent I-13 1 activity (uCi/gm) for each Isotope Where:
EP-EAL-06 1 1, Rev 1 Page 4 DE(1-131) = 0.35 or 60.0 uCi/gm DEI-13 l(i) = the Dose Equivalent I-13 1 activity (uCi/gm) for each isotope.
Calculate the Isotopic Concentration DEI - 13 l(i) = I q i )
ND CF, i)
Where:
IC(i) = Isotope's RCS Concentration (uCi/gm).
Calculate Total Isotopic RCS Activity for each isotope Where:
V(RCS)
= RCS Liquid Volume A(i> = Isotopes total activity (uCi) in the RCS Calculate the Containment Airborne Concentration Where:
V(Q = Free-air space as defined in the assumptions AC(i) = Isotopes concentration (uCi/cc) in the Containment free-air space.
Noble Gas Concentrations Noble Gas calculations are independent of Dose Equivalent I-13 1 Values. As such, gas concentrations remain constant for either calculation being performed and are based on 1 % failed fuel criteria obtained from the referenced document in the sites calculation.
Byron / Braidwood Calculation Number BYR04-046 & BRW-04-0040-M Rev. 1, Attachment A, Page A-2 provides a Total RCS Activity in Curies. Page 12 of the calculation provides an RCS volume used for the calculation of 7,285 ft3. Since the referenced calculation uses a different RCS volume than this calculation, the
EP-EAL-0611, Rev 1 Page 5 isotopic concentration in uCi/gm needs to be corrected using the referenced volume.
Convert 7,285 ft3 to gm.
7285 ft3
- 7.481gal
- 8.331b
- 453.6gm = 2.06E + 08gm ft gal lb Calculate uCi/gm for each Isotope.
= IC(,)
Act(i)
- 1EO6uCi
- 1 Ci 2.06E + 08gm Where:
Act(i) = The activity for each isotope as descr be in calculat on BYR04-046 & BRW-04-0040-M Rev. 1 2.06E+08 = RCS Volume used in calculation BYR04-046 & BRW 0040-MRev. 1 Calculate Total Isotopic RCS Activity for each isotope Where:
V(RCS)
= RCS Liquid Volume as defined in the CDAM documentation A(i) = Isotopes total activity (uCi) in the RCS Calculate the Containment Airborne Concentration Where; V(Q = Free-air space as defined in the assumptions AC(i) = Isotopes concentration (uCi/cc) in the Containment free-air space.
TMI Calculation C-1 10 1 -900-E000-087 provided Noble Gas isotopic concentrations in uCi/gm and required no conversion.
EP-EAL-0611, Rev 1 Page 6 Calculated Dose Rate (60.0 uCi/gm)
R/hr 30.0 (FGR 11 Effective DCF)
Calculate Total Isotopic RCS Activity for each isotope Calculated Dose Rate (60.0 uCVgm)
R/hr 30.7 (FGR I 1 Thyroid DCF)
Where:
V(RCS) = RCS Liquid Volume Byron /
Braidwood A(g= Isotopes total activity (uCi) in the RCS 3.3 Calculate the Containment Airborne Concentration Where:
V(Q = Free-air space as defined in the assumptions AC(i,= Isotopes concentration (uCi/cc) in the Containment free-air space.
Calculation The Containment Airborne Concentrations (AC(i)) were entered into the Micro-Shield program for each RCS Dose Equivalent Iodine -1 3 1 value of interest (0.35 and 60.0 uCi/gm) and the Noble Gas concentrations.
Results:
The following table summarizes the results of each calculation by site.
Site Calculated Dose Rate (0.35 uCVgm)
IUhr (FGR 1 I Effective DCFl TMI I
7.4 26.0 I
26.3 I
Byron / Braidwood
Byron / Braidwood (Effective DCF)
FSAR Activity Distribution Isotope (uCilgm)
AD 1-1 31 0.7420 1-132 0.9790 1-133 1.3500 1-1 34 0.2430 1-135 0.8420 1-1 31 0.7420 1-132 0.9790 1-133 1.3500 1-1 34 0.2430 1-135 0.8420 FGR 11 Effective DCF (Rem/Ci)
DCF 3.29E+04 3.81 E+02 5.85E+03 1.31 E+02 1.23E+03 3.29E+04 3.81 E+02 5.85E+03 1.31 E+02 1.23E+03 Normalized DCF NDCF l.OOE+OO 1.16E-02 1.78E-01 3.98E-03 3.74E-02 l.OOE+OO 1.16E-02 1.78E-01 3.98E-03 3.74E-02 Normalized Activity Distribution (uCi/gm)
NC 7.42E-0 1 1.1 3E-02 2.40E-01 9.68E-04 3.1 5E-02 1.03E+00 Isotopic Fraction f
0.723 0.01 1 0.234 0.001 0.031 1.ooo DE 1-131 Isotopic Conc DE 1-131 Conc. Concentration RCS Volume (uCi/gm)
(uciigm)
(uCi/gm)
(gm)
DE(1-131)
DEI-131 IC v(FtCS) 0.35 2.53E-01 2.53E-01 2.46E+08 3.87E-03 3.34E-01 8.19E-02 4.61 E-01 3.30E-04 8.29E-02 1.07E-02 2.87E-07 3.50E-01 7.42E-01 0.723 60.0 4.34E+01 4.34E+01 5.73E+01 2.40E-01 0.234 1.40E+01 7.90E+O 1 1.42E+01 3.15E-02 0.031 I.84E+00 4.92E+01 1.03E+00 1.OOO 6.00E+01 1.13E-02 0.011 6.63E-01 9.68E-04 0.001 5.66 E-02 Isotope Kr-85m Kr-85 Kr-87 Kr-88 Xe-131 m Xe-l33m Xe-133 Xe-l35m Xe-135 Xe-I38 RCS Activity (a)
Act(,)
3.71 3E+02 1.467E+03 2.372 E+02 6.91 1 E+02 6.829E+02 7.530E+02 5.178E+04 1.007E+02 1.593E+03 1.368Ei02 Isotopic RCS Volume Concentration RCS Volume (9m)
(uCigm)
(gm)
IC V(RCS) 2.06E+08 1.80E+00 2.46E+08 7.12E+00 1.15E+00 3.35E+00 3.32E+00 3.66E+00 2.51 E+02 7.73E+00 4.89E-01 6.64E-01 Total Activity Released (uCi)
A 6.23E+07 8.22E+07 1.13E+08 2.04E+07 7.07 E+07 1.07E+10 1.41 E+10 1.94E+10 3.50E+09 1.21E+10 Total Activity Released (uCi)
A 4.43E+08 1.75E+09 2.83E+08 8.25E+08 8.16E+08 8.99E+08 6.1 8E+10 1.20E+08 1.90E+09 1.63E+08 Free-Air Containment Volume Concentration (cc)
(uciicc)
V(f)
AC 7.820E+10 7.96E-04 1.05E-03 1.45E-03 2.61 E-04 9.04E-04 4.46E-03 1.37E-01 1.80E-01 2.48E-01 4.47E-02 1.55E-01 7.65E-01 Free-Air Containment Volume Concentration (cc)
(UCVCC)
V(f)
AC 7.820E+10 5.67E-03 2.24E-02 3.62E-03 1.06E-02 1.04E-02 1.15E-02 7.91 E-01 1.54E-03 2.43E-02 2.09E-03 Obtained from Calc No. BYR04-046 & BRW-04-0040-M, Rev. 1, Attachment A, Page A-2 of A-8
CC-AA-309-1001 Revision 1 ATTACHMENT I Design Analysis Cover Sheet Nuclear 1 LastPage~o. 2 T Analysis No.
BYR04-046 & BRW-04-0040-M Revision 1 ECIECR No.
Byron: 348720 Braidwood: 348697 Revision 0
Title:
Re-analysis of Main Steam Line Break (MSLB) Accident Using Alternative Source Terms Station(s)
ByrorVBraidwood Unit No.:
00 (Common)
I Component(s)
I NIA I
~
Discipline M
I I
R02 Description Code/
Keyword System Code Varies Structure NIA Safety Class S
CONTROLLED DOCUMENT REFERENCES Document No.
I From/To I DocumentNo.
I From/To UFSAR 1
From P&ID M-96-03 BYR & M-96-03 BRW, "Diagram of Control Room HVAC System" I
F r o m 0 I
I BYR04-047 & BRW-04-0041-M, "Re-analysis of Fuel Handling Accident (FHA) Using Alternative From of Alternative Source Term Onsite and Offsite From Source Terms" Atmospheric Dispersion Coefficients" rODl NO. BYR-04-020, BRW-2004-0029 From BYR04-050 & BRW-04-0044-M, "Calculation rODl NO. DIT-BRW-2004-0017 I
From I
I I
4C-400, "Control Room Volume" I
From I
I I
Is this Design Analysis Safeguards?
Y e s o No@
3oes this Design Analysis Contain Unverified Assumptions?
Yes c] No ATI/AR#
s a Supplemental Review Required?
If yes, complete yes No IE3. Attachment 3 Print Name 3eviewer Paul Reichert wlethod of Review Detailed Review 3eview Notes:
Print Name Print Name
/
Date tpprover i v. a u W 5 6 mm Print Name Sign Name Iescription of Revision (list affected pages for partials): All pages affected. Revision to incorporate Independent Third
'arty Review and Technical Verification Team comments.
THIS DESIGN ANALYSIS SUPERCEDES; BYR97-332
I CALCULATION NO. BYR04-046 & BRW-04-0040-M I REV.NO. 1 1 PAGE: NO. 1 2 I
'/Q Z1.95E-04 SeC/m3 (24-96 hours) (72-hr limiting CR Emergency Air Intake X l ~ )
'/Q =1.67E-04 SeC/m3 (96-720 hours) (624-hr limiting CR Emergency Air intake x / Q )
The CR atmospheric relative concentrations used for broken steam line releases are as follows:
'/Q 33.20E-03 SeC/m3 (0-0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />) (2-hr limiting CR Fresh Air Intake Va)
'/Q 31.70E-02 SeC/m3 (0.5-2 hours) (2-hr limiting CR Emergency Air Intake
'/Q
= E l.46E-02 SeC/m3 (2-8 hours) (6-hr limiting CR Emergency Air Intake VQ)
'/Q ~6.68E-03 SeC/m3 (8-24 hours) (16-hr limiting CR Emergency Air Intake VQ)
'/a 34.48E-03 SeC/m3 (24-96 hours) (72-hr limiting CR Emergency Air Intake VQ)
'/Q ~3. 3 1 E-03 SeC/m3 (96-720 hours) (624-hr limiting CR Emergency Air Intake VQ)
The EAB and LPZ PAVAN calculated 'lQ values input to RADTRAD were also taken from the results of the B/B Design Analyses BYR04-050 & BRW-04-0044-M (Ref. 11). The EAB and LPZ YQ's used are as follows:
EAB
'/Q ~5.36E-04 SeC/m3 (0-2 hours) (8-hr EAB XIQ)
'/Q =9.32E-05 sec/m3 (0-2 hours) (2-hr limiting LPZ XlQ)
'/Q ~4.50E-05 SeC/m3 (2-8 hours) (8-hr limiting LPZ VQ)
'/Q 33.12E-05 sec/m3 (8-24 hours) (16-hr limiting LPZ xlQ)
'/Q = I.41 E-05 sec/m3 (24-96 hours) (72-hr limiting LPZ xlQ)
'/Q ~4.54E-06 sec/m3 (96-720 hours) (624-hr limiting LPZ xlQ) 4.2.
PIant Data Note: All volumes and volumetric flow rates are shown here in ft3 and cfm, and the method of conversion described in reference 1 and Section 2.4 of this analysis was used when needed.
DBA Power Level (Ref. 5)
RCS Primary Coolant Volume (Ref. 5)
Secondary Coolant Volume (3 Intact SGs Combined) (Ref. 5)
Faulted SG Coolant Volume (Ref. 5)
Containment Volume (Ref. 5)
Primary to Secondary Coolant Leak Rate (per Intact SG) (Ref. 5)
Faulted SG Primary to Secondary Coolant Leak Rate (Ref. 5)
Equilibrium Iodine Release Rates (Ref. 7) 3658.3 MWth 7285 ft3 3592 ft3 2675 ft3 2,850,000 ft3 0.02914 cfm 0.06684 cfm These values were derived from the 500 times rate, shown in reference 7, and are used to determine the DE 1-131 spike specific activities.
w 1-131 0.416 Ci/min 1-132 1.754 Ci/min 1-133 0.924 Ci/min
A B
29
~
Concurrent Accident Initiated Iodine Spike (500 times Equlibrium Iodine Release Rate)
I I
I I
I 30 C
D E
F G
31 32
~
Old Methodoloav
~
41 3 33 RCS ____
RCS RCS 34 Equilibrium RCS-Total Activity SpecificActivity Total (pre-AST) Total 35 Release Rate 500x Rate 500x Rate
-ate 6 hrs Core Activity Core
- Activity 36 (Ci/m in)
(Ci/m in) 6 hrs (Ci)
(Ci/MW) 37 11131 0.41 60 208 74880 2.0469Et01 9.58300E+07-9.74000E+07 38 1-132 ~
1.7540 877 315720 8.6302E+01 1.38600E+08 1.40000E+08 39 1-133 0.9240
- ___ 462 166320 4.5464E+01 I
.98400E+08
--- 1.97000E+08
' 40 1-137 0.9260 463 166680 4.5562~+01 2.2d400E+08 2.17000E+08 (Ci)
(Ci)
~~~~
~~
k 43 44 45 46 47 48 148680 RCS Activity -
- - Activity (Ci)
(Ci/MW)
KR-85m 3.713E+02 1.0150E-01 KR-85 1.467E+03 4.0101E-01 1.851 00E+08 1.85000E+08 I
6.829E+02 1.8667E-01 51 XE-131m T X E - 1 3 3 m 7.530E+02 2.0583E-01 53 XE-133 5.178E+04 1.4154E+01 54 XE-135m 1.007E+02 2.7526E-02 I 55 IXE-135 I
1.593E+03 I
4.3545E-01 I I
I I
I 56 IXE-138 1
1.368E+02 3.7394E-02 I Calc. No. BYR04-046 & BRW-04-0040-M, Rev. 1, Attachment A, Page A-2 of A-8
TABLE 15.0-10 Isotope IODINE ACTIVITY IN THE PRIMARY AND SECONDARY COOLANT Equilibrium Equilibrium Iodine Spike Pre-Existing Concentration Appearance Appearance Iodine S p i k e (1.0 pCifgrn
- Rate, Rate, Cijmin ( 6 0 pCri/gm DE DE T-131)
Cilmin 1-131) yCi/gm vCi/gm 1-131 0.742 t
0.416 1-132 0.979 1
1.. 754 1-133 1
1.350 0.923 1-135 I
0.842 I
0. 8 2 6 1 -
1-134 I 0.243 0.926 Secondary Coolant 208 I
4 4. 5 877 I
5 8 " 7 46.2 81.0 463 14.6 4 1 3 50.5 Isutope f
VCi/qm 1-131 0.0742 1-132 0 0979 Equilibrium Concentraion (0.1 vCi/grn DE T-131)
I 1-133 I
0 1350 1-135 I
0.0842 1-134 0.0243 35.0-45 REVISICN 9-DECEMBER 2002
Exeton BW/BY DAMAGE, Version 1.(I Requirements Specification July, 2002 ATTACHMENT I METHODOLUGES 7.2.2 System Volume Calculations and Corrections A, Reactor Coolant System Volume
- 1) Normat RCS volumes are as follows:
Braidwood:................. 2.46E-t08 ml (8680 Ft3 per UFSAR Tabfe 15,6-7)
- Byron:........................ 2.46E+08 ml (8680 F-'t3 per UFSAR Table 15.6-7)
- 2) Normal RCS volumes can be adjusted down to account for a toss of mass
- 5. Containment Sump System Volume
- 1) Normal Sump volume is set at 0.
- 2) IF ECGS was used, THEN:
--_II_
Where:
RCS Normat:
RCS RWST:
Normal default RCS volume from above.
RCS volume at time of sample.
% RWST Used x Totat RWST Volume Braidwood:................ I
.35E+U9 ml (4.75E44 Ft3 per USAR Table 15.6-7)
- Accumulators Used x Accumulator Volume Byron:....................... 1.35E+09 mi (4.75E-1-04 Ft3 per USAR Table 15.6-7)
Braidwood:................. Total f.Q6E+Q8 rnl (3740 Ff' per USAR Table Byron: total 1.06E-tO8 mi (3740 FP par USAR Table Volume from any other source@) added to the RCS that reach the sump.
Aceurn:
15.6-7) or 2.65E-tO7 mi per accumulator.
15'6-7) or 2.65E+07 mi per accumulator.
Other:
C. Containment Free Volume From Table 15.6-7 the Containment free volume is 2.76E-t-06 Ft3 Using 2831 6.05 mi per cubic ft this equals 7.82E+f 0 rnl PWRCDAM-SRS 36 of 44 Revision Ob
Microshield ~ 5. 0 3 (5.03-00095)
PECO Energy Page
- I File Ref:
DOS File : BB035UCI.MS5 Date:
Run Date: October 30, 2006 By :
Run Time: 8:34:45 AM Checked :
Duration: 00:00:02 Case
Title:
BY/BR 0.35 uCi/gm
==
Description:==
Containment High Rad Monitor WITH NOBLE GAS Geometry: 13 - Rectangular Volume Source Dimensions Length 914.4 cm 30 ft Width 1.2e+3 cm 40 ft 0.0 in Height 1.2e+3 cm 40 ft 0.0 in Dose Points x
Y Z
- 1 917.448 cm 609.6 cm 609.6 cm 30 ft 1.2 in20 ft 0.0 in20 ft 0.0 in Shields Shield Name Dimension MaterialDensitv Source 4.80e+04 ft3 Air 0.00122 Air Gap Air 0.00122 Nuclide t3f 1-132 1-133 1-134 1-135 Kr-85 Kr-85m Kr-87 Kr-88 Xe-13 lrn Xe-133 Xe-13 3m Xe-135 Xe-13 5m Xe-138 Source Input Grouping Method : Standard Indices "her of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Library t Grove Ci/cq3 - - - Ba/cm3 curies becmerels f.-Of3De+ODU -4: 003Ue+OlO-7 rG598e-004 2.9451e+001 1.4272e+000 5.2805e+010 1.0500e-003 3.8850e+001 1.9709e+000 7.2922e+010 1.4500e-003 5.3650e+001 3.5475e-001 1.3126e+010 2.6100e-004 9.6570e+000 1.2287e+000 4.5463e+010 9.0400e-004 3.3448e+001 3.0446e+001 1.1265e+012 2.2400e-002 8.2880e+002 7.7067e+000 2.8515e+011 5.6700e-003 2.0979e+002 4.9203e+000 1.8205e+011 3.6200e-003 1.3394e+002 1.4408e+001 5.3308e+011 1.0600e-002 3.9220e+002 1.4136e+001 5.2302e+011 1.0400e-002 3.8480e+002 1.0751e+003 3.9780e+013 7.9100e-001 2.9267e+004 1.5631e+001 5.7834e+011 1.1500e-002 4.2550e+002 3.3029e+001 1.2221e+012 2.4300e-002 8.9910e+002 2.0932e+000 7.7448e+010 1.5400e-003 5.6980e+001 2.8407e+000 1.0511e+011 2.0900e-003 7.7330e+001 Bui ldug The material reference is : Source Integration Parameters X Direction 10 Y Direction 20 Z Direction 20 Results
age
- 2 0s File: BBO35UCI.MS5 un Date: October 30, 2006 un Time: 8:34:45 AM iuration: 00: 00: 02 Enerav MeV 0.03 0.08 0.1 0.15 0.2 0.3 0.4 0.5 0.6 0.8 1.0 1.5 2.0 3.0 TOTALS :
Act ivi tv photondsec 3.732e+13 Fluence Rate MeV/cm2/sec No Builduo 1.507e+05 3.225e+05 2.919e+01 1.062e+04 7.505e+04 6.904e+03 2.084e+04 2.222e+04 2.067e+04 4.084e+04 2.701e+04 6.049e+04 2.240e+05 2.618e+04 1.008e+06 Fluence Rate MeV/cm2/sec with Builduo 1.827e+05 3.786e+05 3.352e+01 1.187e+04 8.163e+04 7.357e+03 2.194e+04 2.321e+04 2.147e+04 4.211e+04 2.772e+04 6.168e+04 2.274e+05 2.647e+04 1.114e+06 Exoosure Rate m R / h r N o Builduo 1.493e+03 5.104e+02 4.466e-02 1.749e+Ol 1.325e+02 1.310e+01 4.060e+01 4*362e+01 4.034e+01 7.768e+01 4.979e+OI lO018e+02 3*464e+02 3.552e+OI 2.903e+03 Exoosure Rate mWhr with Builduo 1.810e+03 5.991e+02 5.128e-02 1.954e+01 1.44Ie+02 1.396e+O1 4.274e+01 4.557e+01 4.191e+01 8.010e+01 5.11Oe+OI 1.038e+02 3.517e+02 3.592e+OI 3.340e+03
MicroShield ~5.03 (5.03-00095)
PECO Energy
- 1 File Ref:
Date :
ige
>S File: BB6OUCI.MS5 in Date: October 24, 2006 By:
in Time: 1:38:58 PM Checked :
iration : 00 : 00 : 02 Case
Title:
BY/BR 60 uCi/gm
==
Description:==
Containment High Rad Monitor WITH NOBLE GAS Geometry: 13 - Rectangular Volume Nut 1 ide 1-131 1-132 1-133 1-134 1-135 Kr-85 Kr-85m Kr-87 Kr-88 Xe-13 lm Xe-133 Xe-13 3m Xe-135 Xe-13 5m Xe-138 Source Dimensions Length 914.4 cm 30 ft width 1.2e+3 cm 40 ft 0.0 in Height 1.2e+3 cm 40 ft 0.0 in Dose Points X
Y Z
- 1 917.248 cm 609.6 cm 609.6 cm 30 ft 1.2 in20 ft 0.0 in20 ft 0.0 in Shields Shield Name Dimension MaterialDensitv Source 4.80e+04 ft3 Air 0.00122 Air Gap Air 0.00122 Source Input Grouping Method : Standard Indices umber of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0,015 : Excluded Libraxy x Grove curies becauerels pci/cm3 Ba/cm3 1.8621e+002 6.8898e+012 1.3700e-001 5.0690e+003 2.4466e+002 9.0523e+012 1.8000e-001 6.6600e+003 3.3708e+002 1.2472e+013 2.4800e-001 9.1760e+003 6.0757e+001 2.2480e+012 4.4700e-002 1.6539e+003 2.1068e+002 7.7951e+012 1.5500e-001 5.7350e+003 3.0446e+001 1.1265e+012 2.2400e-0028.2880e+002 7.7067e+000 2.8515e+011 5.6700e-0032.0979e+002 4.9203e+000 1.8205e+011 3.6200e-003 1.3394e+002 1.4408e+001 5.3308e+011 1.0600e-002 3*9220e+002 1.4136e+001 5.2302e+011 1.0400e-002 3*8480e+002 1.0751e+003 3.9780e+013 7.9100e-001 2 9267e+004 1.5631e+001 5.7834e+011 1.1500e-002 4*2550e+002 3.3029e+001 1.2221e+012 2.4300e-002~8.9910e+002 2.0932e+000 7.7448e+010 1.5400e-003*( 5.6980e+001 2.8407e+000 1.0511e+011 2.0900e-003~7.7330e+001 Buildup The material reference is : Source Integration Parameters X Direction 10 Y Direction 20 2 Direction 20 Results
- 2 3s File: BB6OUCI.MS5 un Date: October 24, 2006 un Time: 1:38:58 PM uration: 00 : 00 : 02 Enerw MeV 0.03 0.08 0.1 0.15 0.2 0.3 0.4 0.5 0.6 0.8 1.0 1.5 2.0 3.0
'OTALS :
Act ivi tv photons/sec 1.016e+14 Fluence Rate MeV/cmVsec No Buildux, 1.545e+05 3.265e+05 2.919e+01 1.604e+04 8.910e+04 9.512e+04 7.664e+05 2.038e+06 2.263e+06 3.320e+06 2.064e+06 2.778e+06 1.004e+06 2.618e+04 1.494e+07 Fluence Rate MeV/cm2/sec With Buildux>
1.873e+05 3.833e+05 3.352e+01 1.791e+04 9.691e+04 1.014e+05 8.069e+05 2.129e+06 2.351e+06 3.423e+06 2.118e+06 2.832e+06 1.019e+06 2.647e+04 1.549e+07 Ex-aosure Rate mR/hr No Buildu-a 1.531e+03 5.167e+02 4.466e-02 2.641e+01 1.573e+02 1.804e+02 1.493e+03 4.000e+03 4.417e+03 6.314e+03 3.804e+03 4.674e+03 1.552e+03 3.552e+01 2.870e+04 ExDosure Rate mR/hr With Buildux, 1.856e+03 6.065e+02 5.128e-02 2.949e+01 1.710e+02 1.923e+02 1.572e+03 4.178e+03 4.589e+03 6.510e+03 3.905e+03 4.766e+03 1.576e+03 3.592e+01 2.999e+04
Byron / Braidwood (Thyroid DCF)
Isotope 1-1 31 1-132 1-1 33 1-134 1-1 35 1-1 31 1-132 1-1 33 1-1 34 1-135 FSAR Activity FGR 11 Thyroid Distribution DCF Normalized (uCi/gm)
(Rem/Ci)
AD DCF 0.7420 1.08E+06 0.9790 6.44E+03 1.3500 1.80E+05 0.2430 1.07E+03 0.8420 3.1 3E+04 0.7420 1.08E+06 0.9790 6.44E+03 1.3500 1.80E+05 0.2430 1.07E+03 0.8420 3.1 3E+04 DCF NDCF l.OOE+OO 5.96 E-03 1.66E-01 9.86E-04 2.90E-02 l.OOE+OO 5.96E-03 1.66E-01 9.86E-04 2.90E-02 Normalized Activity Distribution (uCigm)
NC 7.42E-01 5.83E-03 2.25E-01 2.40E-04 2.44E-02 9.97E-01 7.426-0 1 5.83E-03 2.25E-01 2.40E-04 2.44E-02 9.97E-01 DE 1-131 Isotopic Total Activity Isotopic Conc DE 1-131 Conc. Concentration RCS Volume Released Fraction (uCigm) f DE(I-131) 0.744 0.35 0.006 0.225 0.000 0.024 1.ooo 0.744 60.0 0.006 0.225 0.000 0.024 1.ooo Isotope Kr-85m Kr-85 Kr-87 Kr-88 Xe-131m Xe-l33m Xe-133 Xe-l35m Xe-135 Xe-138 RCS Activity (a) 3.71 3E+02 1.467E+03 2.372E+02 6.91 1 E+02 6.829E+02 7.530+02 5.178E+04 1.007E+02 1.593E+03 1.368E+02 (uCigm)
DEI-131 2.60 E-0 1 2.05 E-03 7.89E-02 8.41 E-05 8.56E-03 3.50E-01 4.46E+01 1.35E+01 1.47E+00 6.00E+01 3.51 E-01 1.44E-02 (uCi/gm)
IC 2.60E-01 3.44E-01 4.74E-01 8.53E-02 2.96E-01 (9m)
(uCi) 2.46E+08 6.41 E+07 8.45E+07 1.17E+08 2.1 OE+07 7.27E+07 V(RCS)
A Isotopic RCS Volume Concentration RCS Volume (uCi/gm)
(gm)
(gm)
IC V(RCS) 1.80E+00 2.46E+08 7.12E+00 1.15E+00 3.35 E+OO 3.32E+00 3.66E+00 2.51 E+02 7.73E+00 2.06E+08 4.89E-01 6.64E-01 1.1 OE+10 1.45E+10 2.00E+10 3.60E+09 1.25E+10 Total Activity Released (uCi)
A 4.43E+08 1.75E+09 2.83E+08 8.25E+08 8.1 6E+08 8.99E+08 6.1 8E+10 1.20E+08 1.90E+09 1.63E+08 Free-Air Volume (CC)
V,)
7.820E+10 F tee Ai r Volume (cc)
V(f) 7.820E+l0 Containment Concentration (UCiCC)
AC 8.19E-04 1.08E-03 1.49E-03 2.68E-04 9.30E-04 4.59E-03 1.40E-01 1.85E-01 2.56E-01 4.60 E-02 1.59E-01 7.87E-01 Containment Concentration (UCiCC)
AC 5.67E-03 2.24E-02 3.62E-03 1.06E-02 1.04E-02 I.15E-02 7.91 E-01 1.54E-03 2.43E-02 2.09E-03 Obtained from Calc No. BYR04-046 & BRW-04-0040-M, Rev. 1, Attachment A, Page A-2 of A-8
Microshield v5.03 (5.03-00095)
PECO Energy Page
- 1 File Ref:
DOS File: BBGOUCII.MS5 Date:
Run Date: October 24, 2006 By:
Run Time: 1:42:34 PM Checked:
Duration: 00 : 00 : 02 Case
Title:
BY/BR 60 uCi/gzn
==
Description:==
Containment High Rad Monitor WITH NOBLE GAS (Thyroid DCF)
Geometry: 13 - Rectangular Volume Source Dimensions Length 914.4 cm 30 ft Width 1.2e+3 cm 40 ft 0.0 in Height 1.2e+3 cm 40 ft 0.0 in Dose Points X
Y Z
- 1 917.448 cm 65.6 cm ' 609.6 cm 30 ft 1.2 in20 ft 0.0 in20 ft 0.0 in Shields Shield Name Dimension MaterialDensitv Source 4.80e+04 ft3 Air 0.00122 Air Gap Air 0.00122 L
Nuclide 1-131 1-132 1-133 1-134 1-135 Kr-85 Kr-85m Kr-87 Kr-88 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Libscary : Grove pC i / cm3 Bo/cm3 curies becauerels 1.9029e+002 7.0407e+012 1.4000e-001 5.1800e+003 2.5145e+002 9.3038e+012 1.8500e-001 6.8450e+003 3.4796e+002 1.2874e+013 2.5600e-001 9.4720e+003 6.2524e+001 2.3134e+012 4.6000e-002 1.7020e+003 2.1611e+002 7.9962e+012 1.5900e-001 5.8830e+003 3.0446e+001 1.1265e+012 2.2400e-O02~8.288Oe+002 7.7067e+000 2.8515e+011 5.6700e-003 4.9203e+000 1.8205e+011 3.6200e-003S 1.3394e+002 1.4408e+001 5.3308e+011 1.0600e-002$ 3.9220e+002 1.4136e+001 5.2302e+011 1.0400e-002 3.8480e+002 1.0751e+003 3.9780e+013 7.9100e-001 2.9267e+004 1.5631e+001 5.7834e+011 1.1500e-002 4.2550e+002 3.3029e+001 1.2221e+012 2.4300e-002 8.9910e+002 2.0932e+000 7.7448e+010 1.5400e-003 5.6980e+001 2.8407e+000 1.0511e+011 2.0900e-003 7.7330e+001 Buildup The material reference is : Source Integration Parameters X Direction 10 Y Direction 20 Z Direction 20 Results
'age
- 2 10s File: BB6OUCII.MS5 tun Date: October 24, 2006 Lun Time: 1:42:34 PM Iuration: 00 : 00 : 02 Enerav MeV 0.03 0.08 0.1 0.15 0.2 0.3 0.4 0.5 0.6 0.8 1.0 1.5 2.0 3.0 Act ivi tv photons/sec Fluence Rate MeV/cm2/sec No Buildux, 1.546e+05 3.266e+05 2.919e+01 1.619e+04 8.947e+04 9.734e+04 7.835e+05 2.101e+06 2.325e+06 3.413e+06 2.120e+06 2.851e+06 1.025e+06 2.618e+04 TOTALS: 1.034e+14 1.533e+07 Fhence Rate MeV/cm2/sec With Buildux, 1.874e+05 3.834e+05 3.352e+01 1.809e+04 9.731e+04 1.037e+05 8.249e+05 2.195e+06 2.416e+06 3.519e+06 2.176e+06 2.907e+06 1.041e+06 2.647e+04 1.589e+07 ExDosure Rate mR/hr No Buildux, 1.532e+03 5.168e+02 4.466e-02 2.667e+01 1.579e+02 1.846e+02 1.527e+03 4.124e+03 4.539e+03 6.492e+03 3.907e+03 4.797e+03 1.585e+03 3.552e+01 2.942e+04 ExDosure Rate mR/hr With Buildux, 1.857e+03 6.067e+02 5.128e-02 2.978e+Ol 1.718e+02 1.967e+02 1.607e+03 4.308e+03 4.716e+03 6.693e+03 4.010e-t.03 4.891e+03 1.609e+03 3.592e-t.01 3.073e+04
Three Mile Island
TMI Isotope 1-1 31 1-132 1-133 1-1 34 1-135 1-1 31 1-1 32 1-133 1-134 1-1 35 (Effective DCF)
G1101-900-E000-087 Table 21 Activity Distribution (uCVgm)
AD 0.8320 0.3030 0.9370 0.1 100 0.4490 0.8320 0.3030 0.9370 0.1100 0.4490 FGR 11 Effective DCF (RemlCi)
DCF 3.29Et04 3.81 E+02 5.85E+03 1.31 E+02 1.23E+03 3.29E+04 3.81 E+02 5.85E+03 1.31 E+02 1.23E+03 Normalized DCF NDCF f.OOE+OO 1.16E-02 1.78E-01 3.98E-03 3.74E-02 l.OOE+OO 1.1 6E-02 1.78E-01 3.98E-03 3.74E-02 Normalized Activity Distribution (uCigm)
NC 8.32E-01 3.51 E-03 1.67E-01 4.38E-04 1.68E-02 1.02E+00 8.32E-01 3.51 E-03 1.67E-01 4.38E-04 1.68E-02 1.02E+00 Isotopic Fraction f
0.81 6 0.003 0.1 63 0.000 0.01 6 1.ooo 0.81 6 0.003 0.163 0.000 0.016 1.000 DE 1-131 Isotopic Total Activity Conc DE 1-131 Conc. Concentration RCS Volume Released (uCigm)
(uCiigm)
DE(I.,,,)
DEI-131 0.35 2.86E-01 1.20E-03 5.72 E-02 1.50E-04 5.76E-03 3.50E-01 60.0 4.90E+01 9.81 E+OO 2.07E-01 2.58E-02 9.88E-01 6.00E+01 Isotope Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Xe-I31 m Xe-1 33m Xe-I33 Xe-l35m Xe-1 35 Xe-138 (uCigm)
IC 2.86E-01 1.04E-01 3.22E-01 3.78E-02 1.54E-01 4.90E+01 1.78E+01 5.52E+01 6.47E+00 2.64 E+O 1 (9m)
(uCi) 2.52E+08 7.20E+07 2.62 E+07 8.1 1 E+07 9.52E+06 3.89E+07 V(RCS)
A C1101-900-E000-087 Table 21 Noble Gas Activity RCS Volume (uCiig m)
(9m)
IC v(RCS) 5.45E-01 2.52E+08 2.43E+00 1.47E+01 1.34E+00 4.15E+00 3.94E+00 5.70E+00 4.1 9E+02 1.92E+01 4.85E-01 6.99 E-0 1 Total Activity Released (uCi)
A 1.37E+08 6.12E+08 3.71 E+09 3.38E+08 1.05E+09 9.93E+08 1.44E+09 1.06E+11 1.22E+08 4.83E+09 1.76E+08 Free-Air Containment Volume Concentration (cc)
(UCVCC)
V(f)
AC 5.660E+10 1.27E-03 4.63E-04 1.43E-03 1.68E-04 6.86E-04 4.02E-03 2.18E-01 7.94E-02 2.46E-01 2.88E-02 1.18E-01 6.90E-01 Free-Air Containment Volume Concentration (cc)
(UCiCC) v, AC 2.43E-03 1.08E-02 6.55E-02 5.97E-03 1.85E-02 1.75E-02 2.54E-02 5.660E+10 1.87E+00 2.16E-03 8.54E-02 3.1 1 E-03
Exhibit 1 B (Typical)
EP-O06T, Revision 3 I
1
Subject:
Post-LOCA EAB, LPZ, TSC, and CR Doses Using AST and RG 1.183 Requirements C-l101-900-E000-087 1
Calculation No.
Rev. No.
IAmerGen System Sheet Nos' 49 of 860 CALCULATION SHEET (Ref. EP-OOGT)
Isotope Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 i1 RCS RCS RCS Core RCS Isotopic Mass Is0 topic Thermal Activity Activity Activity Power PCgg G
Ci MWt cmwt A
B" C=AxB/l E6 D
E=C/D 0.545 2.99E+08 162.74 2619
.62 14E-0 1 2.43 2.99E+08 725.60 2619
.2771E+OO 14.72 2.99E+08 4395.39 2619
.1678E+Ol 2.99E+08 400.12 2619
.1528E+00 1.34 2.99Et-08 1239.19 2619
.4732E+OO 4.15 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-138 1-131 1-132 1-133 1-134 1-135 I
I 1
3.94 2.99E+08 1 176.48 2619
.4492E+OO 5.7 2.99E+08 1702.02 2619
.6499E+00 4 19.4 2.99E+08 1 2 5 232.84 2619
.4782E+02 0.485 2.99E+08 144.82 2619
.5530E-0 1 19.17 2.99E+08 5724.16 2619
.2186E+O1 0.699 2.99E+08 208.72 2619
.7970E-0 1 0.832 2.99E+08 248.48 2619
.9488E-01 0.303 2.99E+08 90.52 2619
.3456E-0 1 0.937 2.99E+08 279.82 2619
.1068E+00 0.1 10 2.99E+08 32.94 2619
.1258E-01 0.449 2.99E+08 134.03 2619
.5 1 18E-0 1 Table 21 RCS Activity in Ci/MWt For RADTRAD Nuclide File
- 10564.4 ft3 x 7.481 galift3 x 8.33 Ib/gal x 453.6 g/lb = 2.986E+08 g AGO005 (3100)
Exelon TMI DAMAGE, Version 1.0 Requirements Specification April, 2003 I
ATTACHMENT I METHODOLOGIES 7.2.2 Svstem Volume Calculations and Corrections A. Reactor Coolant Svstem Volume
- 1) Normal RCS volumes are as follows:
TMI:......................................
2.52E+08 ml (66,595 gallons per UFSAR)
- 2) Normal RCS volumes can be adjusted down to account for a loss of mass.
B. Containment Sump Svstem Volume I)
Normal Sump volume is set at 0.
- 2) IF ECCS was used, THEN:
Where:
RCS Normal:
RCS Cunent:
BWST:
Normal default RCS volume from above.
RCS volume at time of sample.
% RWST Used x Total RWST Volume 1.32E+09 ml(350,OOO gals per USAR)
- Tanks Used x Tank Volume Core Flood Tanks:
Total 5.32E+07 ml (14062 gals USAR)
There are 2 Core Flood tanks (7031 gals each).
BAMT:
2.26E7 mi (798 Ft3)
Other:
Volume from any other source(s) added to the RCS that reach the sump.
C. Containment Free Volume From Table 15.6-7 the Containment free volume is 2.00E+06 Ft3 Using 28316.05 ml per cubic ft this equals 5.66E+10 ml TMI CDAM-SRS (ID: Ex0006382) 36 of 44 Revision 0
Microshield v5-03 (5.03-00095)
PECO Energy Page
- 1 File Ref:
DOS File: TMO35-NG.MS5 Date:
By:
Run Date: October 17, 2006 Run Time: 11:47:33 AM Checked :
Duration : 00 : 00 : 02 Case
Title:
TMI 0 - 3 5 uCi/gm Geometry: 13 - Rectangular Volume
==
Description:==
Containment High Rad Monitor WITH NOBLE GAS Source Dimensions Length 914.4 cm 30 ft Width 1.2e+3 cm 40 ft 0.0 in Height 1.2e+3 cm 40 ft 0.0 in Dose Points X
Y Z
- 1 917.248 cm 609.6 cm 609.6 em 30 ft 1.2 in20 ft 0.0 in20 ft 0.0 in Shields Shield Name Dimension MaterialDensitv Source 4.80e+04 ft3 Air 0.00122 Air Gap Air 0.00122 Source Input Grouping Method : Standard Indices m
e r
of Groups : 25 Lower Energy Cutoff : 0,015 Photons < 0,015 : Excluded Library : Grove Nuclide curies becauerels pci/cm3 Ba/cm3 1-131 1.7262e+000 6.3869e+010 1.2700e-003 4,6990e+001 1-132 6.2931e-001 2.3285e+010 4.6300e-004 1.7131e+001 1-133 1.9437e+000 7.1916e+010 1.4300e-003 5,2910e+001 1-134 2.2835e-001 8.4488e+009 1.6800e-004 6.2160e+000 1-135 9.3242e-001 3.4499e+010 6.8600e-004 2.5382e+001 Kr-83m 3.3029e+000 1.2221e+011 2.4300e-0031 8.9910e+001 Kr-85 8.9028e+001 3.2940e+012 6.5500e-002/ 2.4235e+003 Kr-85m 1.4679e+001 5.4314e+011 1.0800e-002 3.9960e+002 Kr-87 8.1145e+000 3.0024e+011 5.9700e-003 2.2089e+002 Kr-88 2.5145e+001 9.3038e+011 1.8500e-002 6.8450e+002 Xe-131m 2.3786e+001 8.8009e+011 1.7500e-002 6,4750e+002 Xe-133 2.5417e+003 9.4044e+013 1.8700e+000 6,9190e+004 Xe-133m 3.4524e+001 1.2774e+012 2.5400e-002 9.3980e+002 Xe-135 1.1608e+002 4.2948e+012 8.5400e-002 3.1598e+003 Xe-135m 2.9359e+000 1.0863e+011 2.1600e-003 7.9920e+001 Xe-138 4.2271e+000 1.5640e+011 3.1100e-003 1.1507e+002 Buildup The material reference is : Source Integration Parameters X Direction 10 Y Direction 20 Z Direction 20 Results
Page
- 2 DOS File: TMO35-NG.MS5 Run Date: October 17, 2006 Run Time: 11:47:33 AM Duration: 00: 0 0 : 02 Enerav MeV 0.03 0.08 0.1 0.15 0.2 0.3 0.4 0.5 0.6 0.8 1.0 1.5 2.0 3.0 TOTALS :
Act ivi tv photons/sec 8.790e+13 Fluence Rate MeV/cm2/sec No Buildup 3.547e+05 7.625e+05 5.095e+01 2.012e+04 2.429e+05 1.15Oe+04 3.465e+04 2.634e+04 3.128e+04 4.803e+04 3.324e+04 8.841e+04 3.791e+05 4.352e+04 2.076e+06 Fluence Rate MeV/cm2/sec With Buildux, 4.300e+05 8.951e+05 5.850e+01 2.247e+04 2.642e+05 1.226e+04 3.648e+04 2.751e+04 3.250e+04 4.953e+04 3.412e+04 9.014e+04 3.849e+05 4.401e+04 2.323e+06 ExDOSure Rate mR/hr No BuilduD 3.516e+03 1.207e+03 7.794e-02 3.313e+01 4.288e+02 2.182e+01 6.751e+01 5.170e+01 6.105e+01 9.136e+01 6.127e+01 1.487e+02 5.862e+02 5.905e+01 6.333e+03 ExDosure Rate mR/hr With BuilduD 4.262e+03 1.416e+03 8.950e-02 3.700e+01 4.664e+02 2.325e+01 7.108e+01 5.401e+01 6 343e+01 9.420e+01 6.289e+01 1.517e+02 5.953e+02 5.971e+01 7.357e+03
Page DOS File:
Run Date :
Run Time:
Duration :
1 Microshield v5-03 (5e03-00095)
PECO Energy File Ref:
TM6O-NG.MS5 October 17, 2006 11:44:48 AM 00: 00: 02 Date:
By:
Checked:
Case
Title:
TNI 60 uCi/gm
==
Description:==
Containment High Rad Monitor WITH NOBLE GAS Geometry: 13 - Rectangular Voluxne Source Dimensions Length 914.4 cm 30 ft Width 1.2e+3 cm 40 ft 0.0 in Height 192es3 cm 40 ft 0.0 in Dose Points X
Y Z
- 1 917.248 cm 609.6 cm 609.6 cm 30 ft 1.2 in20 ft 0.0 in20 ft 0.0 in Shields Shield Name Dimension MaterialDensitv Source 4.80e+04 ft3 Air 0.00122 Air Gap Air 0.00122 Nuclide 1-131 1-132 1-133 1-134 1-135 Kr-83m Kr-85 Kr-85m Kr-87 Kr-88 Xe-13 lm Xe-133 Xe-133m Xe-135 Xe-13 5m Xe-138 Source Input Grouping Method : Standard Indices "umber of Groups : 25 Lower Energy Cutoff : 0,015 Photons < 0.015 : Excluded Libra-
- Grove curies becauerels pC i / cm3 Ba/cm3 2.9631e+002 1.0963e+013 2.1800e-001~
8.0661e+003 1.0792e+002 3.9931e+012 7.9400e-002"2.9378e+003 3.3437e+002 1.2372e+013 2.4600e-001b 9.1020e+003 3.9145e+001 1.4484e+012 2.8800e-002 1.6039e+002 5.9343e+012 1.1800e-001.3660e+003 3.3029e+000 1.2221e+011 2.4300e-003" 8.9910e+001 8.9028e+001 3.2940e+012 6.5500e-002d2.4235e+003 1.4679e+001 5.4314e+011 1.0800e-002" 3,9960e+002 8.1145e+000 3.0024e+011 5.9700e-003C 2.2089e+002 2.5145e+001 9.3038e+011 1.8500e-002e 6.8450e+002 2.3786e+001 8.8009e+011 1.7500e-002 6.4750e+002 2.5417e+003 9.4044e+013 1.8700e+000 6.9190e+004 3.4524e+001 1.2774e+012 2.5400e-002 9.3980e+002 1.1608e+002 4.2948e+012 8.5400e-002" 3.1598e+003 2.9359e+000 1.0863e+011 2.1600e-003" 7.9920e+001 4.2271e+000 1.5640e+011 3.1100e-0031 1.1507e+002 Buildup The material reference is : Source Integration Parameters X Direction 10 Y Direction 20 Z Direction 20 Results
Page
- 2 DOS File: TM6O-NG.MS5 Run Date: October 17, 2006 Run Time: 11:44:48 AM Duration: 00 : 00 : 02 Eneruv MeV 0.03 0.08 0.1 0.15 0.2 0.3 0.4 0.5 0.6 0.8 1.0 1.5 2.0 3.0 Activitv photons/sec Fluence Rate MeV/cm2/sec No Buildun 3.596e+05 7.688e+05 5.095e+01 2.342e+04 2.538e+05 1.055e+05 1.120e+06 1.825e+06 1.166e+06 1.880e+06 1.329e+06 1.978e+06 9.049et-05 4.352e+04 Fluence Rate MeV/cm2/sec With BuilduD 4.359e+05 9.025e+05 5.850e+01 2.616e+04 2.761e+05 1.124e+05 1 180e+06 1.906e+06 1.211e+06 1.938e+06 1 364e+06 2.017e+06 9.189et-05 4.401e+04 ExQosure Rate mR / hr No BuilduD 3.564e+03 1.217e+03 7.794e-02 3.857e+01 4.480e+02 2.001e+02 2.183e+03 3.582e+03 2.276e+03 3.576e+03 2.450e+03 3.328e+03 1.399e+03 5.905e+01 TOTALS: 1.363e+14 1.176e+07 1.233e+07 2.432e+04 ExDosure Rate mR/hr With Buildun 4.320e+03 1.428e+03 8.950e-02 4.308e+01 4.873e+02 2.132e+02 2.298e+03 3.742e+03 2.364e+03 3.687e+03 2.514e+03 3.393e+03 1.421e+03 5.971e+01 2.597e+04
(Thyroid DCF)
Isotope 1-1 31 1-1 32 1-1 33 1-1 34 1-1 35 1-1 31 1-132 1-1 33 1-1 34 1-1 35 G1101-900-E000-087 Table 21 Activity FGR 11 Thyroid Distribution DCF Normalized (uCVgm)
(RemlCi)
AD DCF 0.8320 1.08E+06 0.3030 6.44E+03 0.9370 1.80E+05 0.1100 1.07E+03 0.4490 3.13E+04 0.8320 1.08E+06 0.3030 6.44E+03 0.9370 1.80E+05 0.1100 1.07E+03 0.4490 3.13E+04 DCF NDCF l.OOE+OO 5.96E-03 1.66E-01 9.86E-04 2.90E-02 t.OOE+OO 5.96E-03 1.66E-01 9.86E-04 2.90E-02 Normalized Activity Distribution (uCig m)
NC 8.32E-01 1.8 1 E-03 1.56E-01 1.08E-04 1.30E-02 l.OOE+OO 8.32E-01 1.81 E-03 1.56E-01 1.08E-04 1.30E-02 l.OOE+OO Isotopic Fraction f
0.830 0.002 0.156 0.000 0.013 1.ooo 0.830 0.002 0.156 0.000 0.01 3 1.ooo DE 1-131 Isotopic Total Activity Conc DE 1-131 Conc. Concentration RCS Volume Released (uCVgm)
(uCVgm)
DE(1.137)
DEI-131 0.35 2.90E-01 6.30E-04 5.44E-02 3.79E-05 4.54E-03 3.50E-01 4.98E+01 9.33E+00 60.0 1.08E-01 6.49E-03 7.78E-01 6.00E+01 Isotope Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Xe-131 m Xe-1 33m Xe-135m Xe-135 Xe-138 Xe-133 (uCVgm)
IC 2.90E-01 1.06E-01 3.27E-01 3.84E-02 1.57E-01 4.98E+01 1.81 E+01 5.61E+01 6.58E+00 2.69E+01 (9m)
(uCi) 2.52E+08 7.32E+07 2.66E+07 8.24E+07 9.67E+06 3.95 E+07 V(RCS)
A C-llOl-900-E000.087 Table 21 Noble Gas Activity RCS Volume (uCVgm)
(9m)
IC V(RCS) 5.45E-01 2.52E+08 2.43E+00 1.47E+01 1.34E+00 4.1 5E+00 3.94E+00 5.70E+00 4.19E+02 1.92E+01 4.85E-01 6.99E-01 Total Activity Released (uCi)
A 1.37E+08 6.12E+08 3.71 E+09 3.38E+08 1.05E+09 9.93E+08 1.44E+09 1.06E+11 1.22E+08 4.83E+09 1.76E+08 Free-Air Containment Volume Concentration (cc)
(UCVCC)
Yf)
AC 5.660E+10 1.29E-03 4.71 E-04 1.46E-03 6.98 1.71 E-04 E-04 4.09E-03 2.22E-01 8.07E-02 2.50E-01 2.93E-02 1.20E-01 7.01 E-01 Free-Air Containment Volume Concentration (cc)
(u Cicc)
Yf)
AC 5.660E+10 2.43E-03 1.08E-02 6.55 E-02 5.97E-03 1.85E-02 1.75E-02 2.54 E-02 1.87E+00 2.1 6E-03 8.54E-02 3.1 1 E-03
Microshield v5.03 (5.03-00095)
PECO Energy Page
- 1 DOS File: TM6O-NI.MS5 Run Date: October 24, 2006 Run Time: 1:33:50 PM Duration : 00 : 0 0 : 02 File Ref:
Date:
By:
Checked :
Case
Title:
TMI 60 uCi/gm
==
Description:==
Containment High Rad Monitor WITH NOBLE GAS (Thyroid DCF)
Geometry: 13 - Rectangular Volume Source Dimensions Length 914.4 cm 30 ft Width 1.2e+3 cm 40 ft 0.0 in Height 1.2e+3 cm 40 ft 0.0 in Dose Points X
Y Z
- 1 917.248 cm 609.6 cm 609.6 cm 30 ft 1.2 in20 ft 0.0 in20 ft 0.0 in Shields Shield Name Dimension MaterialDensitv Source 4.80e+04 ft3 Air 0.00122 Air Gap Air 0.00122 Nuclide 1-131 1-132 1-133 1-134 1-135 Kr-83m Kr-85 Kr-85m Kr-87 Kr-88 Xe-131m Xe-133 Xe-13 3m Xe-135 Xe-13 5m Xe-138 Source Input Grouping Method : Standard Indices Number of Groups : 25 Lower Energy Cutoff : 0.015 Photons < 0.015 : Excluded Library : Grove curies becaerels pci/cm3 Ba/cm3 3.0174e+002 1.1165e+013 2.2200e-0019 8.2140e+003 1.0969e+002 4.0585e+012 8.0700e-002 2.9859e+003 3.3980e+002 1.2573e+013 2.5000e-001 9.2500e+003 3.9825e+001 1.4735e+012 2.9300e-002 1.0841e+003 1.6311e+002 6.0349e+012 1.2000e-001 4.4400e+003 3.3029e+000 1.2221e+011 2.4300e-003ba 8.9910e+001 8.9028e+001 3.2940e+012 6.5500e-002~
2.4235e+003 1.4679e+001 5.4314e+011 1.0800e-002 3.9960e+002 8.1145e+000 3.0024e+011 5.9700e-003 2.2089e+002 2.5145e+001 9.3038e+011 1.8500e-002w~
6.8450e+002 2.3786e+001 8.8009e+011 1.7500e-002v 6.4750e+002 2.5417e+003 9.4044e+013 1.8700e+000~p 6.9190e+004 3.4524e+001 1.2774e+012 2.5400e-002~~'9.3980e+002 1.1608e+002 4.2948e+012 8.5400e-002b' 3.1598e+003 2.9359e+000 1.0863e+011 2.1600e-003" 7.9920e+001 4.2271e+000 1.5640e+011 3.1100e-003" 1.1507e+002 Buildup The material reference is : Source Integration Parameters X Direction 10 Y Direction 20 Z Direction 20 Results
'age
- 2 10s File: TM6O-NI.MS5 un Date: October 24, 2006 Lun Time: 1:33:50 PM Iuration: 00:00:02 Enerav MeV 0.03 0.08 0.1 0.15 0.2 0.3 0.4 0.5 0.6 0.8 1.0 1.5 2.0 3.0 Act ivi tv photons/sec Fluence Rate MeV/cm2/sec No Builduro 3.597e+05 7.689e+05 5.095e+01 2.348e+04 2.540e+05 1.072e+05 1.140e+06 1.854e+06 1.185e+06 1.911e+06 1.351e+06 2.010e+06 9.139e+05 4.352e+04 Fluence Rate MeV/cm2/sec With Buildun 4.360e+05 9.026e+05 5.850e+01 2.622e+04 2.763e+05 1.142e+05 1.200e+06 10937e+06 1.231e+06 1.970e+06 1.387e+06 2.049e+06 9.280e+05 4.401e+04 Exroosure Rate mR/hr No Builduro 3.565e+03 1.217e+03 7.794e-02 3.866e+01 4.483e+02 2.033e+02 2.222e+03 3.640e+03 2.313e+03 3.635e+03 2.490e+03 3.382e+03 10413e+03 5.905e+01 TOTALS: 1.372e+14 1.192e+07 1.250e+07 2.463e+04 Exnosure Rate mR/hr With Buildux, 4.321e+03 1.428e+03 8.950e-02 4.319e+01 4.876e+02 2.166e+02 2.339e+03 3.802e+03 2.403e+03 3.747e+03 2.556e+03 3.448e+03 1.435e+03 5.971e+01 2.629e+04 Additional Source Documents
FEDERAL GUIDANCE REPORT NO.
1 1 LIMITING VALUES OF RADIONUCLIDE INTAKE AND AIR CONCENTRATION AND DOSE CONVERSION FACTORS FOR INHALATION, SUBMERSION, AND INGESTION Derived Guides for Control of Occupational Exposure and Exposure-to-Dose Conversion Factors for General Application, Based on the 1987 Federal Radiation Protection Guidance Keith F. Eckerman, Anthony B. Wolbarst, and Allan C.B. Richardson Oak Ridge National Laboratory Oak Ridge, Tennessee 37831 Office of Radiation Programs U.S. Environmental Protection Agency Washington, DC 20460 1988
Second Printing, 1989 (with corrections)
136 Table 2, I, Inhalation, Cont'd.
Committed Dosc Equivaknt pcr Unit Intake (Sv/Bq)
Nuclide Class/ft Gonad Breast Lung R Marrow 3 Surfact Thyroid Remainder Effective Te.
TC-TC-Te-Tc-132 re-I 33 TC-133111 Te-t 34 ldinc I-120 f-120m 1-171 1.123 I-1 21 I - f ? j I-126 1-128 I-119 1-130 I-t31 1-132 r-i 32m 1-133 1.134 1-135 Cesium Cs-I 25 cs-127 CS-I29 cs-130 CS-131 CS-132 cs-I 34 cs-1 34m 6.63 2-02 fO"2 2.49 tQ'O t.10 1.75 lo'**
5.05 104' 4.12 10-10 1.78 10"O 6.14 10"*
2.17 10-13 f-93 IO"0 2.34 io-10 3-77 1 0 ' 0 4.15 10"~
6.70 1013 3.59 10'13 8.97 3.39 t 0 ' 2 9.00 10-'2 7.90 1Wi2 D 1.0 1.07 10'"
D 1.0 9.01 10-12 D 1.0 1.96 10*
D 1.0 2.89 tiTgl D 1.0 3.49 D i.0 1.84 tO'"
D 1.0 3.48 1(3-'5 D 1.0 6.80 !@I' D 1.0 8.69 1W" D 1.0 2.81 I@
D i.0 2.53 lo'"
D 1.0 9.95 10'12 D 1.0 5.48 I&"
D 1.0 1.95 I W ' ~
D 1.0 4.22 lo'"
D 1.0 1.70 lo"'
D 1.0 1.16 I O t z D 1.0 7.12 I@"
D 1.0 3.04 IO'"
D 1.0 7.83 N P D 1.0 3.77 10"'
D 1.0 3.20 D 1.0 1.30 1v8 11 1.0 3.61 1Ct2 6.49 IO"'
1.88 10-"
2.43 1-10 10.
1.68 IO" 5.39 10""
4.00 IQ'O 5.53 10"2 2.67 IV" 1.15 1 0 " O 9.23 1 @ I i 3.52 lo-
3.63 t0" 8.48 1tP3 6.05 lo.!'
7.82 lo.'*
8.72 I@*Z f.69 I0'"
4.91 lo-
7,96 1.28 lo'"
3.53 1 0 ' 2 4.87 1 0 - [ ~
1.1s 10"O 9.35 10'"
1.37 IW'O 7.15 Jo'"
2.09 10"'
4.87 lo'"
7.88 10
f, 4 l lo'"
8-88 1Wi2 2.94 tQ'"
6.17 IFi2 2.31 10-"
1.89 I@'?
7.92 i @ I 2 1.23 fO"'
2.83 io-fi I.02 i@lr 3.30 2.69 loo 1-02? loa 3.39 f0"7 2.77 10"'
4.27 I@
8.91 I@
3.34 lod 1.33 10"O 1.53 2-16 I@'
4.03 lua 2.54 10"'
2.99 10"'
9.43 2.23 l o g 6.50 1.67 loa9.
4.39 4.64 io-"
1.82 10"'
2.06 1V'O 6.02 10'"
6.60 I@"
4.33 1 0 ' O 2.87 4.69 to-"
5.57 10""
7.45 \\o-@
l.f9 [O-"
6.34 iO-"
7.22 lo'"
3.14 1 0 4 6.03 t0-l' 6.57 10-Lo 2.71 I@"
f.77 ta~0 8.20 i O " O 1.43 10" 4.41 10'0 6.36 I@
5-98 lo-"
1.08 10" 3.82 10'"
7.29 lo'"
4.20 10" 1.18 108 5,40 I t P i 1.43 !W
4.09 I P
1-37 i@*
5-36 1w9 1.97 6-19 lo^
8.77 tV9 6.64 !U" 2.39 10""
1*df 10"o 3.10 10-9 2.94 1Wi2 4.95 loto 8.39 1wi3 5.83 IDt1 8.32 10" 4.27 4.89 9.30 1WL2 8.38 io"2 1.28 10'"
1.22 10'"
3.44 I 0 1 2 5.97 lo-'2 8-53 to-"
4-41 1 O l L 9.84 tWt' 7.17 1 0 ' 3 1.a0 1o"o 4.55 10'"
6.26 f0""
1\\40 10"'
8.86 10-"
2.72 10" 2.14 IV'f 1.95 t a "
9.54 1 6 "
3.80 10-'1 6.21 lo+'!
3.17 f O " O f.l% 1Q' 3.76 IF'?
6.08 lo"'2 1.04 1Pi2 f.44 lo'"
4-09 Io'l1 5.24 to-'
2.04 10' 2.03 10L 6.22 10-43 2.01 104 7.0s 10'~
6.21 lo"'?
6.33 to"'*
2-61 I@"
2.27 lo'lo 1.53 10
7.12 10."
1.49 10" 5.21 6.94 10'"
4.13 10" 8.58 Wi2 7.78 1 0 " ~
1.17 10'"
1.07 10" 3'02 5.18 10"'
7.78 w1*
4.27 10'"
9.01 l o i t 1.38 IQ'O 4.03 lo'"
5-73 1.24 1iY" 7.03 tO-'.'
7.95 lo-"
5.31 1O"z 2.01 10'"
2.52 1W" 1.76 lo'"
8.40 lW'2 3.40 lo-'i 9.41 IV" 5.58 lo'"
2.87 !W'O I. I O 10-8 3.55 tO'"
6.46 1.84 2.39 1@'o 9.56 1 0 "
1.63 IQ"'
5.09 10-"
3.95 lo-'o 1.56 tCTio 2.66 lo-'
32% taJ 5.w 10"'
6.28 5.61 lo"*
5.91 IFra 2.61 lo-'
2.63 la' 5.54 la-'@
5.56 1Wi0 1-55 1Q' 5.M f O " O 7.54 I#'*
2-23 fVJ 2.63 ttr' 3-61 105 1.ti9 10
2.16 10"'
3.94 w7 5.34 Io"'L I s 6 lo4 1.99 toJ 2.92 to-'
1.74 to" 1.65 10"'
4.86 lb' 2.88 tO'"
8.46 I@'
1.71 1 0 ' 2 7.08 lo'"
2.60 fO'll 9.28 10"'
3.00 1 0 "
1, l f fU' 3.34 I O ' Z 2.73 iQo 9.74 IO'"
I ' t t tO-'O 6.90 10""
1+66 10" 7.28 fai2 1.47 tW9 2.40 lo-#\\
3.27 10-9 5.42 f0-t' 2.21 lo'"
9.46 i P 5.63 iO1o 5.65 I&
7.89 10
5-02 tQ" 1.18 fO"*
4-14 lV" 1.43 10'"
1.88 1Cr" 1.w I@"
5.02 10'"
4.55 lo'"
7.55 7.89 Io-'x 1.22 1V'O 3.33 10
f*21 7.02 10""
1.18 la"'
8.02 la-"
8.03 to-"
3.78 10'"
2,01 iv" 5.00 lo!'
2.27 I@"
4.70 10'"
8.46 10" 1-38 10'"
3-93 lo'11 s.34 to.'2 3.95 lo'"
3.54 1.39 to-"
6.90 LP" 6,74 It@"
8.50 1Q" 5.81 lo-'
2-42 1Q" 3,64 1tY9 2.w 10'"
2.53 10"'
1.29 1.24 lo*"
1.38 lo9 1.73 lo-$
2.26 tC9 2.49 f 0" 2.39 10"'
1.17 1.10 ICT'O 3.44 l
~
~
3.23 I(]'"
1.20 10"O 7.15 10" 3.21 lo-"
8.01 lo-"
6.53 10'9 1.20 10" l a lo-'t 7.14 1o'to 6.47 10-9 2.55 10.'
5.23 tO" 4.69 1P' 8.89 ID^'
1.03 8 ' t O 10"'
1.58 10-9 3.55 X32 10'"
1.12 I@"
1.59 10'"
4.29 itr" 8.007 lo-*'
4-54 lo-"
3.32 I@"
1.25 10.'
1.18 10
Dose Conversion Factors (Effective DCF)
This table converts FGR 11 Dose Conversion factors from Sv/Bq to Rem/Ci as used in the calculation.
Though the ratios remain the same, the conversion was done for ease of understanding the units.
Isotope 1-1 31 1-1 32 1-1 33 1-1 34 1-1 35 FGR 11 Table 2.1 Inhalation DCF Column Effective
( s v m 1 (BqKi)
(RedSv)
(RedCi) 8.89E-09 3.70E+10 100 3.29Et-04 1.03E-10 3.81 E+02 1.58E-09 5.85E+03 3.55E-1 I 1.31 E+02 3.32E-10 1.23E+03
( B q ),
Ci sv
( Ci,Ji
Dose Conversion Factors (Thyroid DCF)
This table converts FGR 11 Dose Conversion factors from Sv/Bq to Rem/Ci as used in the calculation.
Though the ratios remain the same, the conversion was done for ease of understanding the units.
Isotope 1-1 31 1-1 32 1-1 33 1-1 34 1-1 35 FGR 11 Table 2.1 Inhalation DCF Column Thyroid
( S V m 1 (Bq/Ci)
(RedSv) 2.92E-07 3.70E+10 100 1.74E-09 4.86E-08 2.88E-10 8.46E-09 (RedCi) 1.08Et-06 6.44E+03 1.80E+05 1.07E+03 3.13E+04
( B q ), ci sv
( ci,),
US. NUCLEAR REGULATORY COMMISSION SPR aGb REGULATORY GUIDE July 2000 OFFICE OF NUCLEAR REGULATORY RESEARCH REGULATORY GUIDE 1.183 (Draft was issued as DG-1081)
ALTERNATIVE RADIOLOGICAL SOURCE TERMS FOR EVALUATING DESIGN BASIS ACCIDENTS AT NUCLEAR POWER REACTORS Regulatory guides are issued to describe and make available to the public such information as methods acceptable to the NRC staff for implementing specific parts of the NRCs regulations, techniques used by the staff in evaluating specific problems or postulated accidents, and data needed by the NRC staff in its review of applications for permits and licenses. Regulatory guides are not substitutes for regulations, and compliance with them is not required. Methods and solutions different from those set out in the guides will be acceptable if they provide a basis for the findings requisite to the issuance or continuance of a permit or license by the Commission.
This guide was issued after consideration of comments received from the public. Comments and suggestions for improvements in these guides are encouraged at all times, and guides will be revised, as appropriate, to accommodate comments and to reflect new information or experience. Written comments may be submitted to the Rules and Directives Branch, ADM, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001,
Regulatory guides are issued in ten broad divisions: 1, Power Reactors; 2, Research and Test Reactors: 3, Fuels and Materials Facilities; 4, Environmental and Siting; 5, Materials and Plant Protection: 6, Products: 7, Transportation; 8, Occupational Health; 9, Antitrust and Financial Review; and 10, General.
Single copies of regulatory guides (which may be reproduced) may be obtained free of charge by writing the Distribution Services Section, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by fax to (301)415-2289, or by email to DISTRlBUTlONQNRC.GOV. Electronic copies of this guide are available on the internet at NRCs home page at <WWW.NRC.GOV> in the Reference Library under Regulatory Guides and through the Electronic Reading Room, as Accession Number ML003716792, along with other recently issued guides, at the same web site.
i 3.6 Fuel Damage in Non-LOCA DBAs The amount of fuel damage caused by non-LOCA design basis events should be analyzed to determine, for the case resulting in the highest radioactivity release, the fraction of the fuel that reaches or exceeds the initiation temperature of fuel melt and the fraction of fuel elements for which the fuel clad is breached. Although the NRC staff has traditionally relied upon the departure from nucleate boiling ratio (DNBR) as a fuel damage criterion, licensees may propose other methods to the NRC staff, such as those based upon enthalpy deposition, for estimating fuel damage for the purpose of establishing radioactivity releases.
The amount of fuel damage caused by a FHA is addressed in Appendix B of this guide.
- 4.
DOSE CALCULATIONAL METHODOLOGY The NRC staff has determined that there is an implied synergy between the ASTs and total effective dose equivalent (TEDE) criteria, and between the TID-14844 source terms and the whole body and thyroid dose criteria, and therefore, they do not expect to allow the TEDE criteria to be used with TD-14844 calculated results. The guidance of this section applies to all dose calculations performed with an AST pursuant to 10 CFR 50.67. Certain selective implementations may not require dose calculations as described in Regulatory Position 1.3 of this guide.
4.1, Offsite Dose Consequences The following assumptions should be used in determining the TEDE for persons located at or beyond the boundary of the exclusion area (EAB):
4.1.1 The dose calculations should determine the TEDE. TEDE is the sum of the committed effective dose equivalent (CEDE) from inhalation and the deep dose equivalent (DDE) from external exposure. The calculation of these two components of the TEDE should consider all radionuclides, including progeny from the decay of parent radionuclides, that are significant with regard to dose consequences and the released radioactivity. l3 4.1.2 The exposure-to-CEDE factors for inhalation of radioactive material should be derived from the data provided in ICRP Publication 30, Limits for Intakes of Radionuclides by Workers (Ref. 19). Table 2.1 of Federal Guidance Report 1 1, Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion (Ref. 20), provides tables of conversion factors acceptable to the NRC staff. The factors in the column headed effective yield doses corresponding to the CEDE.
4.1.3 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 should be assumed to be 3.5 x lo-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 should be assumed to be 1.8 x l 0-4 cubic meters per second. After that and until the end of the accident, the rate should be assumed to be 2.3 x cubic meters per second.
l3 The prior practice of basing inhalation exposure on only radioiodine and not including radioiodine in external exposure calculations is not consistent with the definition of TEDE and the characteristics of the revised source term.
1.183-16