ML052430392

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Rev. 3 to Calculation QDC-0000-N-1266, Re-analysis of Main Steam Line Break (MSLB) Accident Using Alternative Source Terms.
ML052430392
Person / Time
Site: Dresden, Quad Cities  Constellation icon.png
Issue date: 08/12/2005
From: Rothstein H
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RS-05-114 QDC-0000-N-1266, Rev 3
Download: ML052430392 (34)
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Text

ATTACHMENT 7 Calculation QDC-OOOO-N-1266, "Re-analysis of Main Steam Line Break (MSLB)

Accident Using Alternative Source Terms," Revision 3

LI CC-AA.309-1001 Revision 2 A1TACHMiNT 1 Deslrn AniYvsis Cover Sheet Design Analysis (Major Revision) Last Page No.' 17IAtt. B-I Analysis No.: QDC-0000-N-1266 Revision z 3

Title:

' Rc-analysis of Main Steamn Line Break (MSLB) Accident Using Alternative Source Terms ECIECR No.:' 356379 Revision:' 0 Station(s):' Quad Cities Componentls): 14 UnitNo' 12 _2 Discipline:' N Descrip. N01. R01, R02 Code/Keyword:' IAST, MSLB SafetylQA Class: 1 " SR System Code: t 00 __

Structure: "

CONTROLLED DOCUMENT REFERENCES "

Document No.: FromrTo Document No-, From/To QDC4-000-M-1408, RI Fron GE-NE-A22-00103-64.01. RO From 4OC4="-1020, RI From _

Is this Design Analysis Safeguards Information?" Yes 0 No 0 If yes, see SY-AA-101-106 Does this Design Analysis contain Unverified Yes 0 No 0 If yes.

Assumptions? ATUAR#

This Design Analysis SUPERCEDES: ODC4000Q-N-1266. Re 2 in its Description of Revision (list affected pages for partials):"

This revision incorporates responses to pertinent NRC Request for Additional Information (RAts) with respect to all Exelon Nuclear Station Alternative Source Tenn License Amnendment Applications. A new total reactor water mass release from the break of 140,000 lbs is utilized as a bounding value from Standard Review Plan 15.6.4 for MSLB dose analysis purposes only, In addition. Cesium release with the reactor coolant as Cesium Iodine is specificafly included, as well as noble gases. Finafly.

additional assumptions from Regulatory Guide 1183 are Included to d6recly indicate confomiance with this Regulatory Guide.

Preparer 20 Harold Rothstein 7[^,y _

Print Name Sin Name Date Method of Detailed Review Revlew: 2' 0 Alterwat. Catkulatons (attachd) 0 Testing o Reviewer n Paul Reichert Print Name Sign Name Q Date g//&Ss Review Notes:

,4dJ;ie,,4,. Independent review O

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Jt l pPeeri;d review a b2, JW--

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  • Co * *-- *1 1rd External/r 2j/44" ,

A p prove r. _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _

Print Name sn Date Exelon Reviewer N Is a Supplemental Review Required? 2 Yes 0 No R If yes. te Attachment 3 Exelon bAsL rl:r ;rt, v Approver: C.fla'ck- &QC 8/ 31/O Print Name Sin Name Date

ICALCULATION NO. QDC-0000-N-1266 I REV. NO. 3 l PAGE NO. 2of17 CALCULATION TABLE OF CONTENTS 1.0 PURPOSE/OBJECTIVE ....................................... 3 2.0 METHODOLOGY AND ACCEPTANCE CRITERIA ..................................... 4 2.1 General Description ............... 4 2.2 Source Term Model ............... 4 2.3 ReleaseModel ........ :4 2.4 Dispersion Model .............. 4 2.4.1 EAB and LPZ .4 2.4.2 Control Room .5 2.5 Dose Model..5 2.5.1 EAB and LPZ .5 2.5.2 Control Room .6 2.6 Acceptance Criteria ................................................. 6 3.0 ASSUMPTIONS ................................................. 9 3.1 Activity Release and Transport ................................................. 9 3.2 Control Room .................................................. 9 4.0 DESIGN INPUT ................................................. 9 4.1 Mass Release Data ................................................. 9 4.2 Iodine and Noble Gas Activity Release ................................................ 10 4.3 Control Room Data ................................................. 10 4.4 EAB and LPZ Data (from the Dresden Technical Specifications) . ............................................. 11

5.0 REFERENCES

............................................... . 12 6.0 CALCULATIONS ............................................... . 13 6.1 Cloud Volumes, Masses, and Control Room Intake Transit Times . ........................................... 13 6.2. Dispersion for Offsite Dose Assessment ................................................ 14 6.3 Release Isotopics and Quantification ........................... 14

.6.4 Dose Assessment ........................... 15 7.0

SUMMARY

AND CONCLUSIONS .......................... 16 8.0 OWNER'S ACCEPTANCE REVIEW CHECKLIST FOR EXTERNAL DESIGN ANALYSIS. 17 Attachments:

A. Spreadsheet Performing Cesium Molar Fraction and Total MSLB Dose Assessment, With Formula Sheets [pages AI-A15]

B. ComputerDisclosure Sheet [pages B1-BI]

I CALCULATION NO. QDC-0000-N-1266 I REV. NO. 3 l PAGE NO. 3 of 17 1.0 PURPOSEIOBJECTIVE The purpose of this calculation is to determine the Control Room (CR), Exclusion Area Boundary (EAB), and Low Population Zone (LPZ) doses following a Main Steam Line Break (MSLB) Accident. This calculation is performed in accordance with Regulatory Guide (RG) 1.183 [Reference 6] as described herein.

The principal attributes of this analysis compared to those performed previously for this event under Standard Review Plan 15.6.4 guidance and 10CFR100 and 10CFR50, General.Design Criterion 19 requirerpents are:

1. Doses are evaluated in terms of Total Effective Dose Equivalent (TEDE) and evaluated against 10CFR50.67 limits as modified by RG 1.183.
2. Noble gas releases are as previously analyzed and are not impacted by AST application.
3. Historically determined liquid reactor coolant and steam release continue to be the basis for the determination that no fuel damage results from an MSLB.
4. A simplified and more conservative basis is used for the determination of radionuclide releases based on a bounding reactor coolant blowdown value.
5. Iodine releases are based on reactor coolant 1-131 equivalent limitations in Technical Specifications for 'Case 1" and a 20 times higher iodine spike limit for "Case 2".
6. Cesium releases, as cesium iodide, and noble gas release are now considered in addition to iodine that has been historically assumed.

As per Quad Cities - UFSAR [Ref. 8] Section 15.6.4, this event involves the postulation that the largest steam line instantaneously and circumferentially breaks outside the primary containment at a location downstream of the outermost isolation valve, with this event representing the envelope evaluation of steam line failures outside primary containment. Closure of the Main Steam Isolation Valves (MSIVs) terminates the reactor coolant mass loss when the full closure is reached. No operator actions are assumed to be taken during the accident, and the radioactivity concentration inside the Control Room is considered the same as that just outside the intake (with a geometry factor applied) to address any degree of postulated unfiltered inleakage during the duration of the event.

The mass of coolant released during the MSLB is taken for this dose calculation as a bounding maximized value for all current Boiling Water Reactor (BWR) plants of 140,000 pounds of water, as provided in Standard Review Plan 15.6.4, Paragraph 111.2.a for a GESSAR-251 plant. This value bounds for dose calculation purposes the historic UFSAR values such as 55,000 pounds of steam and 45,000 pounds of water in UFSAR Section 15.6.4.5. This ensures that the discharge quantity and dose consequences are maximized, and that the releases should bound any other credible pipe break. Considering the release as all water maximizes the iodine (the primary dose contributor) release quantity compared to any actual release of steam, which would contain iodine quantities limited by the carryover fraction (typically 2%, as per Reference 10).

IRV.N.3I PGEO o1 I CALCLATIO NO----O--26 I CALCULATION NO. ODC-0000-N-1266 I REV. NO. 3 I PAGE NO. 4 of 17 1 2.0 METHODOLOGY AND ACCEPTANCE CRITERIA 2.1 General Description The radiological consequences resulting from a design basis MSLB accident to a person at the EAB; to a person at the LPZ; and to an operator in the Control Room following an MSLB accident were performed using a Microsoft EXCEL spreadsheet, provided as Attachment A.

2.2 Source Term Model No fuel damage is expected to result from a MSLB. Therefore, the activity available for release from the break is that present in the reactor coolant and steam lines prior to the break, with two cases analyzed. Case I is for continued full power operation with a maximum equilibrium coolant concentration of 0.2 uCi/gm dose equivalent 1-131 [Ref. 8]. Case 2 is for a maximum coolant concentration of 4.0 uCi/gm dose equivalent 1-131, based on a pre-accident iodine spike caused by power changes. This accident source term basis is consistent with the pre-AST MSLB analyses per Regulatory Guide 1.5 [Ref. 5], and meets the guidance in RG 1.183 for analysis of this event as well.

Inhalation Committed Effective Dose Equivalent (CEDE) Dose Conversion Factors (DCFs) from Federal Guidance Report (FGR) No. 11 [Ref. 3] and External Dose Equivalent (EDE) DCFs from FGR No. 12 [Ref. 4] are used.

2.3 Release Model Noble gas releases are those historically determined from the release fractions in Reference 2 and its Curie release formulation, corresponding to.1 00,000 uCi /sec off-gas emission after 30.

minutes decay, per UFSAR Section 15.6.4.5, and for the Quad Cities Technical Specification value of 5.5 seconds MSIV closure time.

Iodine releases are determined based on a release of 140,000 lbs of reactor coolant with either 0.2 uCi/gm or 4.0 uCi/gm of 1-131 dose equivalent activity.

The iodine species released from the main steam line are assumed to be 95% Csl as an aerosol, 4.85% elemental, and 0.15% organic. Therefore, 95% of iodine releases have an atom equivalent cesium release. Cesium isotopic abundance is determined based on source terms developed for pH control for longer lived or stable isotope [Ref. 13], and from ANSI/ANS-18.1-1999 [Ref. 10] for shorter lived isotopes.

Releases are assumed to be instantaneous and no credit is taken for dilution in turbine building air.

2.4 Dispersion Model 2.4.1 EAB and LPZ

I CALCULATION NO. QDC-0000-N-1266 I REV. NO. 3 1 PAGE NO. 5 of 17 EAB and LPZ X/Q's are determined using the methodology in R.G. 1.5 [Ref. 5], that is also cited as a basis for evaluation in the Quad Cities - UFSAR (e.g., Section 15.6.4.5). Specifically:

x =0.0133 Q ayu where ay = horizontalstandarddeviationof theplume(meters) u = windvelocity(meters/second)

Horizontal standard deviations are taken from the PAVAN outputs for the EAB and LPZ included in Ref. 9. Per R.G. 1.5, F stability and a I meter/sec wind speed are used.

2.4.2 Control Room For control room dose calculations, the plume was modeled as a hemispherical volume, the dimensions of which are determined based on the portion of the liquid reactor coolant release that flashed to steam. The activity of the cloud is based on the total mass of water released from the break. This assumption is conservative because it considers the maximum release of fission products.

Activity release is conservatively assumed to effectively occur at the Control Room intake elevation and, again conservatively, no credit is taken for plume buoyancy.

2.5 Dose Model Dose models for both onsite and offsite are simplified and meet R.G. 1.183 [Ref. 6]

requirements, providing results in units of Total Effective Dose Equivalent (TEDE). Dose conversion factors are based on Federal Guidance Reports 11 and 12 [Refs 1 & 0].

2.5.1 EAB and LPZ Doses at the EAB and LPZ for the MSLB are based on the following formulas:

DoseCEDE (rem) = Release (Curies) * (sec/rn )

  • Breathing Rate (m3/sec)
  • Inhalation DCF (rem-E/Ci inhaled)

Q and DoseEDE (rem) = Release (Curies)* X(sec/m3)* Submersion DCF(remEDE - m3 /Ci -sec)

Qa and finally, DoseTEDE (rem) = DoseCEDE (rem) + DoseEDE(rem)

I CALCULATION NO. QDC-OOOO-N-1266 I REV. NO. 3 I PAGE NO. 6 of 17 2.5.2 Control Room CR operator doses are determined somewhat differently. Steam cloud concentrations are used, rather than X/Q times a curie release rate. No CR filter credit is taken and, therefore, for inhalation, a dose for a location outside of the CR is used. For cloud submersion, a geometry factor is used to credit the reduced plume size seen in the CR. This is a conservative implementation of RG 1.183 guidance. The formulas used are:

DoseCEDE (rem) = Plume Concentration (Ci/m 3 )

  • Transit Duration (sec)
  • Breathing Rate (m3 /sec)
  • Inhalation DCF (remlEDE/Ci inhaled) and Dose EDE (rem) = Plume Concentration (Gum 3 )
  • Transit Duration (sec)
  • Submersion DCF (remEDE -m3 / Ci -sec) and finally, DoseTEDE (rem) DoseCEDE (rem) + DosCEDE(rem) 2.6 Acceptance Criteria Dose acceptance criteria are per 10CFR50.67 [Ref. 7] and R.G. 1.183 [Ref. 6] guidance.

The Table below lists the regulatory limits for accidental dose to 1) a control room operator, 2) a person at the EAB, and 3) a person at the LPZ boundary.

Regulatory Dose Limits (Rem TEDE) per Refs. 7 and 6.

1-131 Dose CR EAB LPZ Equivalent (30 days) (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) (30 days Normal Equilibrium 5 2.5 2.5 Iodine Spike 5 25 25 Direct conformance with the relevant guidance in Regulatory Guide 1.183 (e.g., the TEDE concept and the above limits) and in particular its assumptions provided in Appendix D "Assumptions for Evaluating the Radiological Consequences of a BWR Main Steam Line Break Accident" is provided by this analysis, as shown in the Conformance Matrix Table 2.1

I CALCULATION NO. QDC-0000-N-1266 I REV. NO. 3 l PAGE NO. 7of I Table 2. 1:Conformance with RG i183 Appendix D (Main Stea Lin Br ak)

RG Drdsden/Quadv-Section. RG Positionr - Cties Analysis - Comments 1 Assumptions acceptable to the NRC staff regarding core inventory and Not Applicable No fuel damage, release the release of radionuclides from the fuel are provided in Regulatory estimate based on coolant Position 3 of this guide. The release from the breached fuel is based on activity.

Regulatory Position 3.2 of this guide and the estimate of the number of .

fuel rods breached.

2 If no or minimal fuel damage is postulated for the limiting event, the Conforms See below released activity should be the maximum coolant activity allowed by technical specification. The iodine concentration in the primary coolant is assumed to correspond to the following two cases in the nuclear steam supply system vendor's standard technical specifications.

2.1 The concentration that is the maximum value (typically 4.0 pCi/gm DE I- Conforms 4.0 uCi/gm DE 1-131 is used 131) permitted and corresponds to the conditions of an assumed pre- in this analysis.

accident spike, and 2.2 The concentration that is the maximum equilibrium value (typically 0.2 Conforms 0.2 uCi/gm DE 1-131 is a piCifgm DE 1-131) permitted for continued full power operation. Technical Specification limit and is used in this analysis.

3 The activity released from the fuel should be assumed to mix Not Applicable No fuel damage.

instantaneously and homogeneously in the reactor coolant. Noble gases should be assumed to enter the steam phase instantaneously.

4.1 The main steam line isolation valves (MSIV) should be assumed to close Conforms An MSIV closure time of 5.5 in the maximum time allowed by technical specifications. seconds was assumed in the analysis. This is the Technical Specification maximum allowed MSIV closure time of 5 seconds plus 0.5 seconds for instrument response.

4.2 The total mass of coolant released should be assumed to be that Conforms Abounding value of 140,000 amount in the steam line and connecting lines at the time of the break I _I lbs or reactor coolant is used

CALCULATION NO. QDC-OOOO-N-1266 REV.NO. 3 PAGE NO. 8of I Table 2.1: Conformance with RGi .183 Appendix D (Main Steam Line Break)

_RG - - ... - DresdenlQuad Sectioon - RG Position -Cities Anialysi Comm ents plus the amount that passes through the valves prior to closure. for dose assessment.

4.3 All the radioactivity in the released coolant should be assumed to be Conforms Release is assumed at released to the atmosphere instantaneously as a ground-level release. ground level, with no credit No credit should be assumed for plateout, holdup, or dilution within taken for plateout, holdup or facility buildings. dilution within facility buildings.

4.4 The iodine species released from the main steam line should be Conforms The subject values are used.

assumed to be 95% Csl as an aerosol, 4.85% elemental, and 0.15%

organic.

CALCULATION NO. QDC-0000-N-1266 I REV. NO. 3 l PAGE NO.9 of 17 l 3.0 ASSUMPTIONS 3.1 Activity Release and Transport

  • Iodine coolant activity isotopic distributions and Noble Gas activity releases are taken from the Quad Cities UFSAR [Ref. 83 Section 15.6.4.5.
  • Noble Gas activity releases are taken from Reference 2.
  • Release from the break to the environment is assumed instantaneous. No holdup in the Turbine Building or dilution by mixing with Turbine Building air volume is credited.
  • The steam cloud is assumed to consist of the portion of the liquid reactor coolant release that flashed to steam.
  • The activity of the cloud is based on the total mass of water released from the break.

This assumption is conservative because it considers the maximum release of fission products.

  • Buoyancy effect pf the cloud was conservatively ignored.
  • For the control room dose calculations,

> The plume was modeled as a hemispherical volume. This is consistent with the assumption of no Turbine Building credit. It is also reasonable for the more likely release paths through multiple large blowout panels situated around the Turbine Building Main Floor.

> Dispersion of the activity of the plume was conservatively ignored.

> The cloud was assumed to be carried away by a wind of speed 1 m/s. Credit is not taken for decay.

3.2 Control Room

  • Inhalation doses are determined based on concentrations at the intake, and exposures for the duration of plume traverse.
  • External exposure doses are determined based on concentrations at the intake, exposures for the duration of plume traverse, and a geometry factor credit (Equation 1 of Ref. 6) based on the control room volume of 58,300 cubic feet [Ref. II].

4.0 DESIGN INPUT 4.1 Mass Release Data

  • As stated in UFSAR Section 15.6.4.3, there is no core uncovery and therefore no fuel damage as a consequence of this accident for the assumed releases. For this dose analysis, a conservative 140,000 pounds of primary coolant liquid is assumed

I CALCULATION NO. QDC-0000-N-1266 I REV. NO. 3 I PAGE NO.10 of 17 to be released to maximize the iodine release, with a conservative fraction of this liquid flashing to steam.

4.2 Iodine and Noble Gas Activity Release The MSLB noble gas release fractions listed in the second column below are provided in Table 3-1 of Reference 2. Using the formula below in this Reference for a 100,000 uCi /sec off-gas emission after 30 minutes decay, per UFSAR Section 15.6.4.5, and the Quad Cities Technical Specification value of 5.5 seconds MSIV closure time, the Curie releases in the third column below are obtained: Curies Released = Release fraction x 5.5 x 3 x 0.45, where 0.45 is the offgas rate at the break, in Curies/second, corresponding to a 100,000 uCi

/sec off-gas emission after 30 minutes decay, and 3 is nominally the ratio of NRC-assumed to design basis noble release rate.

Noble Gas Curies Isotope Release Fraction Release Kr-83M 0.00936 6.95E-02 Kr-85M 0.0164 1.22E-01 Kr-85 0.000064 4.75E-04 Kr-87 0.0511 3.79E-01 Kr-88 0.0524 3.89E-01 Kr-89 0.218 1.62E+00 Xe-131M 0.0000523 3.88E-04 Xe-133M 0.000782 5.81 E-03 Xe-133 0.0219 1.63E-01 Xe-1 35M 0.0641 4.76E-01 Xe-135 0.0592 4.40E-01 Xe-137 0.288 2.14E+00 Xe-138 0.218 1.62E+00 The relative mix of iodine isotopes in the reactor coolant at the onset of the accident, based on the Quad Cities UFSAR [Ref. 8] Section 15.6.4, is given below.

Iodine Isotope Activity (pCi/cc) 1-131 0.067 1-132 0.38 1-133 0.40 1-134 0.53 1-135 0.49 Release activities are calculated in Attachment A.

4.3 Control Room Data

CALCULATION NO. QDC-0000-N-1266 I REV. NO. 3 l PAGE NO.1 of 17_

  • Control Room Emergency Zone Volume = 184,000 cubic feet [Ref. 11]

(the maximum volume above rather than the volume of the Control Room proper is utilized to maximize the calculated doses, which are proportional to geometry factor)

  • No Emergency Filtration Credit taken.

4.4 EAB and LPZ Data

  • EAB Distance from Release: 380 m [Quad Cities Tech Specs]
  • LPZ Distance from Release,: 4,828 m [Quad Cities Tech Specs]

CALCULATION NO. QDC-0000-N-1266 I REV. NO. 3 l PAGE NO.12 of 17

5.0 REFERENCES

1. Deleted.

.----- 2.-NEDO-21143-1 ;"Radiological -Accident Evaluation --The CONAC03 Code",- General -

Electric Company, December, 1981.

3. Federal Guidance Report No.. 11, 'Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion",

1988.

4. Federal Guidance Report No. 12, "External Eexposure to Radionuclides in Air, Water, and Soil", 1993.
5. Regulatory Guides 1.5, "Assumptions Used for Evaluating the Potential Radiological Consequences of a Steam Line Break Accidents for Boiling Water Reactors," 3/10/71.
6. Regulatory Guide 1.183, "Alternative Radiological Source Terms For Evaluating Design Basis Accidents At Nuclear Power Reactors", July 2000.
7. 10 CFR Part 50.67, 'Accident source term", January 1, 2001.
8. Quad Cities Nuclear Power Station UFSAR Rev. 7, Section 15.6.4.
9. Calculation QDC-0000-M-1408, Rev. 1 'Atmospheric Dispersion Factors (X/Qs) for Accident Release".
10. American Nuclear Society Standard (ANS) 18.1-1999 'Radioactive Source Terms For Normal Operation of Light Water Reactors", Table 5.
11. QDC-0000-N-1 020, "Impact of Extended Power Uprate on Site Boundary and Control room Doses for LOCA and Non-LOCA Events", Revision 1.
12. Deleted.
13. PBAPS Calculation PM-1056, Rev. 1, 'Suppression Pool pH Calculation for Alternative Source Terms".

I CALCULATION NO. QDC-0000-N-1266 I REV. NO. 3 I PAGE NO. 13 of 17 6.0 CALCULATIONS No fuel damage is expected for the limiting MSLB. As discussed in Section 2, two iodine concentrations are used (0.2 pQi/g and 4.0 pCilg) [per Ref. 6] when determining the consequences of the main steam line break. All of the radioactivity in the released coolant is assumed to be released to the atmosphere instantaneously as a ground-level release. No credit is taken for plateout, holdup, or dilution within facility buildings.

The spreadsheets in Attachment A perform this analysis using data and formulations discussed above and shown in Attachment A. The following summarizes parameters and their treatment in the spreadsheet.

6.1 Cloud Volumes, Masses, and ControlRoom Intake Transit Times The cloud is assumed to consist of portion of the conservatively bounding liquid reactor coolant release that flashes to steam. The flashing fraction (FF) is derived as follows:

FF x (steam enthalpy at 212 F) + (1-FF) x (liquid enthalpy at 212 F) =

(liquid enthalpy at temperature of steam at reactor vessel outlet)

A 548 F vessel outlet temperature is used, with liquid enthalpy of 546.9 BTU/lb.

At 212 F,a steam enthalpy of 1150.5 BTU/lb and a liquid enthalpy of 180.17 BTU/lb are used (these enthalpies are taken from the ASME Steam Tables).

Substituting, FF = (546.9 - 180.17) / [(1150.5- 180.17)] 0.378 For conservatism, a value of .40 or 40% is used.

As stated in Section 3.1, the cloud is assumed to consist of the initial steam blowdown and that portion of the liquid reactor coolant release that flashed to steam.

The mass liquid water released = 140,000 lb Flashing fraction for calculating cloud volume = 40%

The mass of water carrying activity into the cloud = 140,000 lb

= (140,000 lb)(453.59 g/Ib)

= 6.350E76 g The mass of steam in the cloud =40%*140,000 lb

= 56,000 lb The release is assumed to be a hemisphere with a uniform concentration. The cloud dimensions (based on to 56,000 lb of steam at 14.7 psi and 212 OF, vg = 26.799 ft3/lb) were calculated as follows:

Volume = (56,000 lb)(26.799 ft3/lb)

= 1,500,744 ft3

I CALCULATION NO. QDC-0000-N-1266 I REV. NO. 3 I PAGE NO.14 of 17

= (1,500,744 ft3 )/(35.3 ft3/m3)

= 42,514 m3 The volume of a hemisphere is 7cd3 /12. Thus, the diameter of the hemispherical cloud is 54.6 meters.

The period of time required for the cloud to pass over the control room intake, assuming a wind speed of-1-m/s-is 54.6 s-(=(54;6-m)/(l-m/s)).-Therefore,-at a wind-speed of 1 m/s,-the base of the hemispherical cloud will pass over the control room intake in 54.6 seconds.

6.2 Dispersion for Offsite Dose Assessment As discussed in Section 2.4.1 the following formulation was used for Offsite Dose X/Q assessment, with F Pasquill Stability and a 1 m/sec wind speed.

X 0.0133 Q au where YY= horizontal standard deviation of the plume (meters) u = wind velocity (meters/second)

As calculated in the PAVAN run in Reference [9], at the 380 meter EAB distance ay is 15.4, and at the 4828 meter LPZ distance oy is 153. The resulting EAB and LPZ X/Qs are 8.64E-04 and 8.69E-05 sec/i 3 , respectively.

6.3 Release Isotopics and Quantification The iodine, noble gas and cesium activity releases are given in Attachment A, which also determines resulting doses.

Noble gas releases are taken from the input in Section 4.2.

Iodine releases are based on reactor coolant isotopic distributions from Section 4.2, which are normalized based on FGR-1 1 CEDE dose conversion factors to obtain coolant concentrations corresponding to Case 1: 0.2 uCi/gm, and Case 2 4.0 uCi/gm. The resulting concentrations were multiplied by the 140,000 lbs of release converted to grams.

Cesium releases are based on the fact that a single cesium atom will accompany 95% of the released iodine atoms. For Cs-1 33, Cs-134, Cs-135, and Cs-137, isotopic data (in Curies per Megawatt, and therefore generally applicable to similar BWRs such as Quad Cities

4) for end of cycle conditions from Reference 13 were used. For shorter lived isotopes such as Cs-1 36 and Cs-1 38, the ratio of their concentration values in Reactor Water to that of Cs-1 37 in Reference 10 is used to predict their relative concentrations. Releases reflect this distribution, with the molar fractions converted to curie quantities based on the isotope's decay constant.

Cs-133, representing about 38% of the cesium, is stable.

CALCULATION NO. QDC-0000-N-1266 IREV. NO. 3 l PAGE NO.15 of 17 6.4 Dose Assessment Doses at the EAB and LPZ distances, and in the Control Room are calculated in Attachment A using the formulas in Section 2.5. Concentrations at the receptor locations are that in the steam plume for the Control Room or based on the release times the applicable X/Q for the EAB and LPZ.

-Doses-are-calculated for inhafation-(rem-CEDE)-and-plume submersion (rem EDE) and totaled to yield rem TEDE. The breathing rate of 3.47E-04 m3/sec is per RG 1.183 guidance without the round-off.

The resulting calculated doses are in the spreadsheet and in the Summary and Conclusions Section below.

ICALCULATION NO. QDC-OOOO-N-1266 I REV. NO. 3 l PAGE NO.16 of 17 7.0

SUMMARY

AND CONCLUSIONS Accident doses from a design basis MSLB were calculated for the control room operator, a person at the EAB, and a person at the LPZ. The results are summarized in the Table below. The doses at the Control Room, EAB, and LPZ resulting from a postulated design

- -- basis-MSLB-do-not-exceedtthearegulatorylimits. i-- -

Location Case I Case 2 I (normal equilibrium (iodine spike limit of 0.2 pCi) limit of 4.0 pCi)

. Dose (rem TEDE) Dose (rem TEDE)

LIMITS CR: 5.0;. EAB&LPZ: 2.5 CR: 5.0; EAB&LPZ: 25 EAB 6.38E-02 1.27E+00 LPZ . 6.42E-03 1 .27E-01 CR I 9.20E-02 1.84E+00

ICALCULATION NO. ODC-0000)-N-1266 I REV. NO. 3 FOR EXTERNAL PAGE IIPAGENU.17 DESIGN of 17 NO. 17 of j I

OWNER'S NU.

CALCULKUIUN I8.0 ACCEPTANCE REVIEW ICHECKLIST UL)C-UUUO-N-12b6 REV. NU. 3 17 8.0 OWNER'S ACCEPTANCE REVIEW CHECKLIST FOR iEXTERNAL DESIGN ANALYSIS DESIGN ANALYSIS NO. QDC-0000-N-1 266 REV: 3 Yes No N/A

1. Do assumptions have sufficient-rationale? cito o
2. Are assumptions compatible with the way the plant is operated and with the licensing basis?

DVO O

3. Do the design Inputs have sufficient rationale?
4. Are design inputs correct and reasonable?

Go"E E

5. Are design inputs compatible with the way the plant is operated and with the licensing basis?
6. Are Engineering Judgments clearly documented and justified? V 0o 0
7. Are Engineering Judgments compatible with the way the plant Is operated and with the licensing basis? V 0o 0 B. Do the results and conclusions satisfy the purpose and objective of the design or' 0 analysis?
9. Are the results and conclusions compatible with the way the plant Is operated Er o3 ,

and with the licensing basis?

10. Does the design analysis Include the applicable design basis D"'1 E3 documentation?
11. Have any limitations on the use of the results been identified and transmitted to the appropriate organizations?

at a

12. Are there any unverified assumptions? So ago1
13. Do all unverified assumptions have a tracking and closure mechanism In place?

E3. ffi/

EXELON REVIEWER: --fa DATE 41-!-

Is~ign(L

A I B i C I D E F l G I H i I J l K L M I Quad Cities 1&2 MSLB Dose Spreadsheet Case 1: Reactor Coolant at maximum value (DE 1-131 of 0.2 uCUg) permitted 2 1 b continued full power operation

. for 3 42514 Volume of coud (cubic meters) Case 2: ReactorCoolantatmaximumvaluepermitted(DE 1-131 of4.0 uuCVg) 4 6.35E+07 Mass of water In reactor coolant release (grams) corresponding to an assumed pre-accident spike _

5 54.6 seconds for cloud to pass over CR intake for wind speed of 1rn/second I - I. . I I I-I 6 184000 Volume of Control Room Envelope (cubic feet) - maximum used for conservatism ____=_=

7 140,000 Mass of Liquid Water Released (lb) . .

8 40% Flashing Fraction _ .

9 56000t Mass of Steam in the Cloud (lb) .

10 26.799 Vg (ft3/ib) (based on 14.7 psi and 212F) = =

11 Reactor coolant iodine distribution Is assumed to be a 1 gm/cc specific ravity 12 Casel Case2 _I 13 I Release Release .

14 Normalized Case 1 Case 2 Case 1 Case 2 Cloud Cloud Case 1 Case 2 15 Isotope Activity FGR 11 1-131 DE Normalized Normalized Activity Activity Concentration _oncentratio Decay Actvity Activity 16 Distribution DCF' Activi A ctivity Release Release Constant Release Release 17 uCi/gm RemcEDolCI uCVgm uCvgm uCilgm Ci Ci CVm3 Ci~m3 1/seconds moles moles 18 1-131 0.067 3.29E+04 6.70E-02 8.23E-02 1.65E+00 5.22E+00 1.04E+02 1.23E-04 2.46E-03 9.98E-07 3.22E-07 6.43E-06 19 1-132 0.38 3.81 E+02 4.40E-03 5.40E-03 1.08E-01 3.43E-01 6.86E+00 8.07E-06 1.61E-04 8.37E-05 2,52E-10 5.04E-09 20 1-133 0.4 5.85+03 7.11 E-02 8.73E-02 1.75E+00 5.54E+00 1.11E+02 1.30E-04 2.61 E-03 9.26E-06 3.68E-08 7.35E-07 21 1-134 0.53 1.31 E+02 2.11 E-03 2.59E-03 5.18E-02 1.65E-01 3.29E+00 3.87E-06 7.74E-05 2.20E-04 4.60E-11 9.20E-10 22 1-135 0.49 1.23E+03 1.83E-02 2.25E-02 4.50E-01 1.43E+00 2.86E+01 3.36E-05 6.72E-04 2.91 E-05 3.01E-09 6.02E-08 23 Totals 1.63E-01 2.OOE-01 4.00E+00 Totals 3.62E-07 7.23E-06 24 'non-spiked' spiked 25 NEDO- NEDO- NEDO- . -

26 21143-13 21143-13 21143-13 Case 1 Case22 27 MSLB Case 1 Case 2 Release Release 28 Noble Gas Activity Activity Cloud Cloud 29 Release Release Release Concentration Concentration .

30 Fractions Ci Ci Cim3 Ci/m3 .

31 Kr-83M 0.00936 6.95E-02 6.95E-02 1.63E-06 1.63E-06 Case 1 Case 2 Case 1 Case 2 32 Kr-85M 0.0164 1.22E-01 1.22E-01 2.86E-06 2.86E-06 Activity Activity Decay Aaivity Activity 33 Kr-85 0.000064 4.75E-04 4.75E-04 1.12E-08 1.12E-08 Release Release Constant Release Release 34 Kr-87 0.0511 3.79E-01 3.79E-01 8.92E-06 8.92E-06 Molar Frac. moles moles 1/seconds curies curies 35 Kr-88 0.0524 3.89E-01 3.89E-01 9.15E-06 9.15E-06 Cs-134 4.4317% 1.52E-08 3.05E-07 1.07E-08 2.64E-03 5.28E-02 36 Kr-89 0.218 1.62E+00 1.62E+00 3.81E-05 3.81 E-05 Cs-135 17.4506% 6.00E-08 1.20E-06 9.55E-15 9.32E-09 1.86E-07 37 Xe-131M 0.0000523 3.88E-04 3.88E-04 9.13E-09 9.13E-09 Cs-136 0.0120% 4.12E-11 8.24E-10 6.10E-07 4.09E-04 8.18E-03 38 Xe-133M 0.000782 5.81 E-03 5.81 E-03 1.37E-07 1.37E-07 CS-137 40.17% 1.38E-07 2.76E-06 7.28E-10 1.64E-03 3.27E-02 39 Xe-1133 0.0219 1.63E-01 1.63E-01 3.82E-06 3.82E-06 Cs-138 0.0102% 3.502-11 7.00E-10 3.59E-04 2.04E-01 4.09E+00 40 Xe-135M 0.0641 4.76E-01 4.76E-01 1.12E-05 1.12E-05 Totals 1 62.08% 2.13E-07 4.27E-06 41 Xe-135 0.0592 4.40E-01 4.40E-01 1.03E25 1.03E-05 Balance is stable Cs-133 42 Xe-137 0.288 2.14E+00 2.14E+00 5.03E-05 5.03E-05 43 Xe-138 0.218 1.62E+00 - 1.62E+00 3.81 E-05 3.81 E-05 jl 44 I I Calculation ODC-0000-N-1266, Rev. 3 Attachment A - Dose Calculation Page Al of Al 5

A B l C D E F I G H I l I K L M 45 Curies Released Case 1 Dose (rem CEDE) Case 2 Dose (rem CEDE) 46 to the Environment (Inhalation) (Inhalation) 47 Isotope Case 1 Case 2 DCF' CR EAB LPZ CR EAB LPZ 48 1-131 5.22E+00 1.04E+02 3.29E+04 7.E 5.15E-02 5.18E-03 1.53E+00 1.03E+00 1.04E-01 49 1-132 3.43E-01 6.86E+00 3.81E+02 5.82E-05 3.92E-05 3.94E-06 1.16E-03 7.83E-04 7.89E-05 50 1-133 5.54E+00 1.11E+02 5.85E+03 1.44E-02 9.71 E-03 9.77E-04 2.89E-01 1.94E-01 1.95E-02 51 1-134 1.65E-01 3.29E+00 1.31 E+02 9.60E-06 6.46E-06 6.50E-07 1.92E-04 1.29E-04 1.30E-05 52 1-135 1.43E+00 2.86E+01 1.23E+03 7.82E-04 5.26E-04 5.30E-05 1.56E-02 1.05E-02 1.06E-03 54 Cs-134 2.64E-03 5.28E-02 4.63E+04 5.44E-05 3.66E-05 3.68E-06 1.09E-03 7.32E-04 7.37E-05 55 CsI135 9.32E-09 1.86E-07 4.55E+03 1.89E-11 1.27E-11 1.28E-12 3.78E-10 2.54E-10 2.56E-11 56 Cs-136 4.09E-04 8.18E-03 7.33E+03 1.33E-06 8.98E-07 9.04E-08 2.67E-05 1.80E-05 1.81E-06 57 CS-137 1.64E-03 3.27E-02 3.19E+04 2.33E-05 1.57E-05 1.58E-06 4.65E-04 3.13E-04 3.15E-05 58 Cs-138 I 2.04E-01 4.09E+00 1.01E+02 9.23E-06 6.21 E-06 6.25E-07 1.85E-04 1.24E-04 1.25E-05 59 Sub-total (rem CEDE) . 9.19E-02 6.18E-02 6.22E-03 1.84E+00 1.24E+00 1.24E-01 -

60 1 61 Curies Released Case I Dose (rem EDE) Case 2 Dose (rem EDE) 62 to the Environment (External) (External) _

63 Isotope Case I Case 2 DCF2 CR EAB LPZ CR EAB LPZ 64 1-131 5.22E+00 1.04E+02 6.73E-02 2.32E-05 3.04E-04 3.06E-05 4.63E-04 6.08E-03 6.12E-04 65 1-132 3.43E-01 6.86E+00 4.14E-01 9.36E-06 1.23E-04 1.24E-05 1.87E-04 2.46E-03 2.47E-04 66 1-133 5.54E+00 1.11E+02 1.09E-01 3.97E-05 5.21 E-04 5.24E-05 7.94E-04 1.04E-02 1.05E-03 67 1-134 1 1.65E-01 3.29E+00 4.81 E-01 5.21 E-06 6.83E-05 6.88E-06 1.04E-04 1.37E-03 1.38E-04 68 1-135 1.43E+00 2.86E+01 2.95E-01 2.78E-05 3.64E-04 3.67E-05 5.55E-04 7.28E-03 7.33E-04 69 . _  :

70 Cs-134 2.64E-03 5.28E-02 2.80E-01 4.87E-08 6.39E-07 6.43E-08 9.74E-07 1.28E-05 1.29E-06 71 Cs-135 9.32E-09 1.86E-07 2.09E-06 1.28E-18 1.68E-17 1.69E-18 2.57E-17 3.37E-16 3.39E-17 72 Cs-136 4.09E-04 8.18E-03 3.92E-01 1.06E-08 1.39E-07 1.39E-08 2.11 E-07 2.77E-06 2.79E-07 73 CS-137 1.64E-03 3.27E-02 2.86E-05 3.08E-12 4.05E-11 4.07E-12 6.17E-11 8.09E-10 8 142E.I _1 74 Cs-1i38 2.04E-01 4.09E+00 4.48E-01 6.03E-06 7.91 E-05 7.96E-06 1.21 E-04 1.58E-03 1;59E-04 75 76 Sub-total (rem EDE)j _ I 1.11E-04 1.46E-03 1.47E-04 2.23E-03 2.92E-02 2.94E-03 77 lodine and Cesium Total (rem TEDE) j 9.20E-02 6.33E-02 6.37E-03 1.84E+00 1.27E+00 1.27E-01 78 Cunes Released _ Case 1 Dose (rem EDE) Case 2 Dose (rem EDE) 79 _ _ to the Environment _ _ (External) - (External) _ _

2 80 _ _ Case 1 Case 2 DCF CR EAB LPZ CR EAB LPZ 81 Kr-83M l 6.95E-02 6.95E-02 .5.55E-06 2.54E-11 3.33E-10 3.35E-11 2.54E-11 3.33E-10 3.35E-11 82 Kr-85M_l _ _ 1.22E-01 1.22E-01 2.77E-02 2.22E-07 2.91E-06 2.93E-07 2.22E-07 2.91E-06 2.93E-07 83 Kr-85 4.75E-04 4.75E-04 4.40E-04 1.38E-11 1.81E-10 1.82E-11 1.38E-11 1.81E-10 1.82E-11 84 Kr-87 3.79E-01 3.79E-01 1.52E-01 3.81E-06 5.00E-05 5.03E-06 3.81E-06 5.00E-05 5.03E-06 85 Kr-88 _ 3.89E-01 3.89E-01 3.77E-01 9.67E-06 1.27E-04 1.28E-05 9.67E-06 1.27E-04 1.28E-05 86 Kr-89 1.62E+00 1.62E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 87 Xe-131M 3.88E-04 3.88E441 1.44E-03 3.68E-1 1 4.83E-10 4.86E-11 3.68E-11 4.83E-10 4.86E-11 88 Xe-133M _ 5.81E-03 5.81E-03 5.07E-03 1.94E-09 2.54E-08 2.56E-09 1.94E-09 2.54E-08 2.56E-09 89 Xe-133 _ 1.63E-01 1.63E-01 5.77E-03 6.18E-08 8.11E-07 8.16E-08 6.18E-08 8.11E-07 8.16E-08 90 Xe-135M 4.76E-01 4.76E-01 7.55E-02 2.37E-06 3.10E-05 3.12E-06 2.37E-06 3.10E-05 3.12E-06 91 Xe-135 _ 4.40E-01 4.40E-01 4.40E-02 1.27E-06 1.67E-05 1.68E-06 1.27E-06 1.67E-05 1.68E-06 92 Xe-137 2.14E+00 2.14E+00l 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 93 Xe-138 1.62E+00 1.62E+00 2.13E-01 2.28E-05 2.98E-04 3.00E-05 2.28E-05 2.98E-04 3.00E-05 94 Noble Gas Sub-total (rem EDE) - i 4.02E-05 5.27E-04 5.30E-05 4.02E-05 5.27E-04 5.30E.05 95 T 96 Overall Total (rem I

TEDE)

I_ __ _ ._ 1 - _

I _____ I _____ 9.202-02 l6.382-02 l6.422-03 1.842+00, - 1.272+00 l1.27E-01 ___

Calculation ODC-0000-N-1266, Rev. 3 Attachment A - Dose Calculation Page A2 of Al 5

A B C D E F G H I J K L M 98 f'Dose Conversion Factor (rem/Curie) from Federal Guidance Report (FGR) 11per Reg. Guide 1.183 99 _ Dose Conversion Factor (rem-m ICurte-second) fronmFGR 12 per Reg.Gue 1.183 L i 100 From NEDO-21143-1. 'Radiological Accident Evaluation - The CONAC03 Code. General Electric Company, December, 1981, 101 with its Table 3-1 (SLBA Source Activities) Release Fractions and page 3-3 Cl conversion formula for a 0.1 CVsec design basis 102 offgas release rate and 5.5 second MSiV closure time, both of which apply 103 3.47E-04 Breathing rate (m3/second) per Regulatory Guide 1.183 (without round-off) 104 5.13E-02 Control Room Geometry Factor per Reg. Guide 1.183. Regulatory PositIon 4.2.7 105 1.54E+01 EAB a, (meters)for F stability, (taken from PAVAN runs in Calc. QDC-0000-M-1408. Rev. 1) 106 1.530E+02 LPZe(meters)for F stability. (taken from PAVAN runs in Calc. ODC-0000-M-1408. Rev. 1) .

107 1.OOE+00 Wind Speed (mhs) IlIII _

3 108 8.64E-04 XIQ (secondsim ) at EA Boundary 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> based on RG 1.5 methodology . _

3 109 8.69E-05 XIQ (secondslm ) at Low Population Zone 2 based on RG 1.5 methodology Calculaton QDC-0000-N-1266, Rev. 3 Attachment A - Dose Calculation Page A3 of Al15

IA 8 C D E F 1 Quad Cities 1&2 MSI B_ CD__ Case 1:

3 =(A9 A10135.3 Volume of cloud (cubic meters) Case 2:

4 =A7-453.59 Mass of water inreactor coolant 5 =(A3-l2IPl())A(1/3) seconds for cloud to pass over C_

6 184000 Volume of Control Room Envelop 7 140000 Mass of Liquid Water Released (I 8 0.4 Flashing Fraction 9 =A7-A8 Mass of Steam in the Cloud (lb) 10 26.799 Vg (f 3/lb) (based on 14.7 psi and 11 Reactor coolant iodine dis_

12 13 14 Normalized Case 1 Case 2 15 Isotope Activity FGR 11 1-131 DE Normalized Normalized 16 Distuibution DCF' Actvity Activity Activity 17 uCICgm RemCEDEJCi uCilgm uCilgm uCigm 18 1-131 0.067 32900 =C18-B18/C$18 =D18-0.2/D$23 =E18-20 19 1-132 0.38 381 =C19-B19/C$18 =D19-0.21DS23 =E19-20 20 1-133 0.4 5846 =C20-B20/C$18 =D20-0.2/D$23 =E20-20 21 1-134 0.53 131 =C2t B21/CS18 =D21-0.2/D$23 =E21-20 22 1-135 0.49 1230 =C22-B22/CS18 =D22-0.2/DS23 =E22-20 23 Totals =SUM(D18:D22) =SUM(E18:E22) =SUM(F18:F22) 24 non-spiked spiked 25 NEDO- NEDO-26 21143-13 21143-13 Case 1 Case 2 27 Case 1 Case 2 Case 2 Release Release 28 Activity Activity Activity Cloud Cloud 29 Release Release Release Concentration Concentration 30 Ci Ci Ci Ci/m3 Ci/m3 31 Kr-83M 0.00936 =$B31-5.5-3-0.45 =SB31-5.5-3-0.45 =C31/SAS3 =D31/$A$3 32 Kr-85M 0.0164 =SB32-5.5-3-0.45 =$B32-5.5-3-0.45 =C32/SA$3 =D32/SAS3 33 Kr-85 0.000064 -SB33-5.5-3-0.45 =$B33-5.5-3-0.45 =C33/$AS3 =D331SA$3 34 Kr-87 0.0511 SB34-5.5-3-0.45 =$B34-5.5-3-0.45 =C34/SA$3 =D34/SAS3 35 Kr-88 0.0524 =SB35-5.5-3'0.45 =SB35-5.53-0.45 =C35/$AS3 =D35/SAS3 36 Kr-89 0.218 =$B36-5.5-3-0.45 =SB36-5.5-3-0A5 =C36/SAS3 =D36/SA$3 37 Xe-131M 0.0000523 =SB37-5.53-0.45 =S837-5.5-3-0.45 =C37/1A$3 =D37/$AS3 38 Xe-133M 0.000782 =SB38-5.5-3-0.45 =SB38-5.5-3-0.45 =C38/$AS3 =D38/SAS3 39 Xe-133 0.0219 =SB39-5.5-3-0.45 =SB39-5.5-3-0.45 =C39/SAS3 =D39/SAS3 40 Xe-135M 0.0641 =SB40-55-3-0.45 =SB40-5.5-3-0.45 =C40/SA$3 =D40/SA$3 41 Xe-135 0.0592 =SB41- 5.530.45 =S841- 5.5-3045 =C41/SA$3 =D41ISA$3 42 Xe-137 0_288 =SB42-5 5-3-0.45 -SB42-5.5-3-0.45 =C42VSAS3 =D421$AS3 43 Xe-138 0.218 =$B43-55-0.45 =S=435.53045 =C43/SAS3 =W43/SA$3 44 45 Curies Released 46 to the Environment 47 Isotope Case 1 Case 2 DCF1 CR 48 1-131 =G18 -H18 32900 =118-$E48$A$S100-5A$5 49 1-132 =G19 =H19 381 =119'$E49 $AS100-5A$5 50 1-133 =G20 =H20 5846 = 120-$ E50-$A$S100 $A$5 51 1-134 =G21 =H21 131 =i21-SE51-$A$100 $AS5 Calculation QDC-0000-N-1 266, Rev. 3 Attachment A - Dose CaIc. Formulas Page A4 of Al 5

A B l C l -_D EF 52 1-135 =G22 -H22 1230 =122-$E52-$AS100-$A$5 53 54 Cs-134 =L35 =M35 =(3700000000000)-0.0000000125 =($C54/$A$3)-$E54-$A$100-$A$5 55 Cs-135 =L36 =M36 =(3700000000000)-0.00000000123 =($C55/$A$3)-$E55-$A$100-$A$5 56 Cs-136 =L37 =M37 =(37000000D0000)0.000000001 98 =($C56/$A$3)-SE56-$AS100-$AS5 57 CS-137 _ =L38 =M38 =(3700000000000)-0.00000000863 ($C57/SAS3)-$E57-$A$100-$A$5 58 Cs-138 _=L39 =M39 =(3700000000000)-0.0000000000274 =($C58/SA$3)-$E58-$A$100-$A$5 59 Sub-total (rem CEDE) _=SUM(F48:F58) 60 61 Curies Released 62 to the Environment 63 Isotope Case I Case 2 DCF2 _ CR 64 1-131 =C48 =D48 0.06734 =118-$E64-$A$101-$A$5 65 1-132 =C49 =D49 0.4144 =119-$E65-5A$101-SAS5 66 1-133 =C50 =D50 0.10878 =120-$E66SAS1 01-SA$5 67 1-134 =C51 =D51 0.481 =121-SE67-$AS101-SAS5 68 1-135 =C52 =D52 0.29526 =122-$E68-$AS101-SA$5 69 70 Cs-134 =L35 =M35 =(3700000000000)-0.0000000000000757 =(SC7O/$A$3) $E70$AS1010$A$5 71 Cs-135 =L36 =M36 =(3700000000000)'5.65E-19 =(SC71/SA$3)'$E71'$A$101 $AS5 72 Cs-136 =L37 =M37 =(3700000000000)0.00000000000106 =($C72/SAS3)'$E72'$A$101'SA$5 73 CS-137 =L38 =M38 =(3700000000000)'7.74E-18 =(SC73/$A$3)-SE73-SAS101-$A$5 74 Cs-138 =L39 =M39 =(3700000000000)-0.000000000000121 =($C74/SA$3)-SE74-SAS101 '$A$5 75 76 - Sub-total (rem EDE)jI i SUM(F64:F74) 77 lIodine and Cesium Total Ij I -SUM(FS9+F76) 78 Cunes Released 79 to the Environment 80 Case I Case 2 DCF 2 CR 81 Kr-83M =C31 =D31 0.00000555 =E31'$E81'SAS1 01'SA$5 82 Kr-85M =C32 =D32 0.027676 =E32'SE82'SAS101'$AS5 83 Kr-85 =C33 =D33 0.0004403 =E33-$E83'$A$101'$A$5 84 Kr-87 =C34 =D34 0.15244 =E34'$E84'SAS 01'SA$5 85 Kr-88 =C35 =D35 0.3774 =E35'$E85'$A$101'$A$5 86 Kr-89 =C36 =D36 0 __=E36'SE86'SA$101'SAS5 87 Xe-131M =C37 =D37 0.0014393 =E37'$E87'SA$101'$AS5 88 Xe-133M =C38 =D38 0.005069 =E38'$E88'$AS101'$A$5 89 Xe-133 =C39 =D39 0.005772 =E39'$E89'$A$101'SA$5 90 Xe-135M =C40 =040 0.07548 =E40'SE90'SA$101'$A$5 91 Xe-135 =C41 =-41 0.04403 =E41'$E91'$A$101-$AS5 92 Xe-137 =C42 =D42 0 =E42-SE92-$A$S01'$A$5 93 Xe-138 =C43 =D43 0.21349 =E43'SE93'SA$101'SA$5 94 Noble Gas Sub-total (rem EDE) -SUM(F81:F93)

95. III 96 Overall Total (rem TEDE)j I I I *SUM(F77+F94) 97.

98 Dose Conversion Factor (ren/Curie) _

2 99 Dose Conversion Factor (rem-m 3/Ctu 100 3From NEDO-21143-1 'Radiological A 101 with ts Table 3-1 (SLBA Source Adl 102 offgas release rate and 5.5 second _

103 0.000347 Breathing rate (m3/second) per Regu Calculation QDC-0000-N-1266, Rev. 3 Attachment A - Dose Cale. Formulas Page A5 of Al 5

=A a I C D I E F 104 =(SAS60.338y1173 Control Room Geometry Factor per R . ]

105 15.4 EAB a, (meters) for F stability. (taken . .

106 153 LPZ a (meters) for Fstability, (taken I . . .

107 1 Wind Speed (mts) 108 =0.0133/A$105/AS107 XI0 (seconds/m 3 ) at EA Boundary -.

109 =0.01331AS1 061AS107 XIQ (secondstm') at Low Population .___ _ _ . I . I _ _ _I Calculation QDG-0000-N-1 266, Rev. 3 Attachment A - Dose Cale. Formulas Page A6 of Al 5

G IH Ii. J K 1 Reactor Coolant at maximum value (DE 1-131 of 0.2 uCig) permitted for continued full power operation 2

3 Reactor Coolant at maximum value permitted (DE 1-131 of 4.0 uCilg) corresponding to an assumed pre-accident spike 4

-5

-8 9.

10.

12 ReiaseI Case 2 _

14 Case I Case 2 Cloud Cloud 15 Activity Activity Concentration Concentration Decay 16 Release ReRease Constant 17 Ci Ci CVm3 Ci/m3 1/seconds 18 =El8-$A$4/1000000 =G18-20 =G 181SA$3 =H18/SAS3 =LN(2y(8.04 86400) 19 =E19-$AS4/1000000 =G19-20 =G191SAS3 =H19/SAS3 =LN(2y(2.3-3600) 20 =E20-$A$4/1000000 =G20-20 =G201SA$3 =H201SAS3 =LN(2y(20.8 3600) 21 =E21-SAS4/1000000 =G21-20 =G21/$AS3 -H21/$AS3 =LN(2y(52.660) 22 =E22-SA$4/1000000 =G22-20 =G22/SAS3 =H221SA$3 =LN(2y(6.61 3600) 23 _ _ _ _ __ Totals 24 25 i 26 271 28 29 30 31 Case I Case 2 32 Activity Activity Decay 33 Release Release lConstant 34, Molar Frac. motes moles I /seconds 35 Cs-134 0.044317152955112 =0.95 SH35-LS23 =0.95-$H35-MS23 =LN(2Y(2 062-86400-365.25) 36 Cs-135 0.174506296053598 =0.95-SH36-LS23 -0.95-SH36-MS23 =LN(2y(2300000 86400 365;25) 37 Cs-136 0.000119942189253291 -0.95-SH37-LS23 =O 95-SH37-MS23 =LN(2y(13.16 86400) 38 CS-137 0.401736793048373 =0.95-SH38-LS23 =O 95-SH38-MS23 =LN(2y(30.17-86400 365.25) 39 Cs-138 0.000101901239392202 =0 95-SH39-LS23 =0.95-SH39-MS23 -LN(2y(3z2.60 ) -

40 Totals =SUM(H35:H39) =SUM(i35:139) =SUM(J35:J39)i 41, Balance is stable Cs-1 33!

42_

43 44 45 Case I Dose (rem CEDE) Case 2 Dose (rem CEDE) 46 (inhalation) (inhalatbon) 47 EAB LPZ CR EAB LPZ 48 I=C48-SE48-SAS100- SAS105 =C48-SE48-SAS 100-SAS106 =Jl18-SE48-SAS100-SAS5 =D48-SE48-$Asl o00-A$ 105 =D48-S E48-SAS100-SAS106 49 =C4 9 SE49 SAS 100-SAS105 =C49-SE49-SAS 100-SAS106 =J 19-SE49-SAS 100-SAS5 =D49-SE49-SAS 100-SAS 105 -D49-SE49-SAS 100-SAS 106 50 I=C50-SESO-SAS100-SAS105 =C50-SESO-SAS100-SAS106 =J20-SE50-SAS100-SAS5 =D50-SE50-SAS1 00-SAS105 -D50-SE50-SAS100-SAS106 51 j=C51 -SE51 -SAS100-SAS 105 =C51 -SE51 -SAS100-SAS106 I=J21 -SE51 -SAS100-SAS5 -D51 -SE51 -SAS100-SAS105 -D51 -SE51 -SAS100-SAS106 Calculation CDC-0000-N-1266, Rev. 3 Attachment A - Dose Catc. Formulas Page A7 of A15

G H _ _I__ _ _ _ K 52 =C52'$E52'$A$100'$A$105 =C52r$E52S$A$100S$AS106 =J22'$E52S$A$100'A$5 =052VSE52'$AS100'$A$105 =D52V$E52S$AS100S$A$106 54 =C54S$E54'$A$l OWSA$105 =C54S$E54S$A$100S$AS106 =($D54/$A$3) $E54'$A$100'$AS5 =D54S$E54'$A$l005$A$105 =D54SEE54SA$l 00'$A$106 55 =C55'SE55'$A$100rSA$1 05 =C55S$E55'$A$l 00S$A$106 =($D55/$AS3) SE55S$A$100S$AS5 =D55'$E55S$ASlOSA$1l05 - =D555$E55'$A$100'$A$106 56 =C56$SE56'$A$100'$A$105 =C56'$E565$A$l00'SA$l06 =($D56/$A$3)y$E56S$A$100'$A$5 =D56'$E56'$ASl 00OIA$105 =D56'$E563$AS1 00S$AS106 57 =C57r$E57'$A$100'$A$105 I=C57S$E57r$A$100'$A$106 1=($D57/$A$3),$E57'$A$100'$A$5 =D57S$E57rSAS100'$AS105 I=D57S$E5rS$A$100S$A$106 58 =C58&$E58'$A$100$A$105 I=C58S$E58'$A$100S$A$106 1=($D58/$A$3)'$E58'$A$1 00'$A$5 I=D58&$E58S$A$l00'$A$l05 I=D58S$E58&$A$1 00'$A$106 59 =SUM(G48:G58) ZSUM (H48:H58) I=SUM(148:158) -SUM(J48:JSB) UzSUM( K48:K58) 61 Case 1 Dose (rem EDE) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ Case 2 Dose (rem EDE) _ _ _ _ _ _ _ _ _ _ _ _ _

62 (External _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ (External) _ _ _ _ _ _ _ _ _ _ _ _ _

63 .EAB LPZ CR EAB3 LPZ 64 =C64$SE64S$A$105 =C64S$E64'$AS106 =Jl8'$E64'$A$101'$A$5 =D6-4'E64S$A$l05 =D64'$E64S$A$106 65 =C65S$E65S$A$105 =C655$E655$A$106 =J19S$E65SAS101 $A$5 =D65*$E65S$A$1 05 =D65'SE65S$A$1 06 66 =C66'$E66'$A$105 =C66'$E66S$AS106 =J20'$E66'$A$101'$A$5 =D66S$E66'$A$105 =D66S$E66S$A$106 67 =C67'SE67S$A$105 =C675$E67'$A$106 =J21P$E67S$AS101$A$5 -D67'$E67$AS1 05 =D67'$E67S$A$1 06 68 =C68'$E68S$A$1 05 =C68'$E68'$AS106 =J22'$E68S$AS101$AS5 =D68*$E68'$A$1 05 =D68'$E68'$A$106 69 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

70 =C70S$E70'$A$105 =C70'$E70'$A$106 =($D70/$A$3)'$E7 0$A$101'$A$5 .=D70S$E70'$A$105 =0D70'$E70S$A$106 71 I=C71PSE71V$A$105 =C71P$E71PSA$106 =($071/$A$3)-$E71 SA$101P$A$5 =D71 SE71'$AS105 =D71V$E71S$A$106 72 =C725$E72S$A$105 =C72'SE72'$A$106 =($D721SAS3)-$E72-$ASlOl $A$5 =D72$SE72'$A$105 =D72'$E72'$A$l06 73 =C73S$E73'$A$1 05 =C73'$E73S$A$ 106 =($D73/$A$3)'$E73XSA$101PSA$5 =D73XSE73$AS1 05 =D73$SE73S$A$106 74 =C745SE74'$A$105 =C745$E745$AS106 =($D741$AS3)'$E74S$A$101P$A$5 =D74S$E74'$AS105 =D74'$E74'$A$106 75 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

76 =SUM(G64:G74) =SUM(H64:H74) =SUM(164:174) =SUM(J64:J74) =SUM(K64:K74) 77 =SUM G59+G76) :SUM(H59+H76) SUM(159 176). =SUM(J59+J76) =SUM(K594K76) 78 1 Case 1 Dose (rem EDE) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ Case 2 Dose (rem EDE) _ _ _ _ _ _ _ _ _ _ _ _

79 (External) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __(External) _ _ _ _ _ _ _ _ _ _ _ _ _

80 EAB LPZ CR EAB LPZ 81 =C81'$E81S$A$105 =C81V$E81S$A$106 =F31VSE8I$A$101'SA$5 =DS1 SE81VSA$105 =D81VSE81V$A$106 82 =C82'$E82S$A$105 =C82S$E82S$A$106 =F32'$E82S$A$101V$A$5 =D82'$E82'$A$105 =D82'$E82'$A$106 83 =C83'$EB3'$A$105 =C83$E83S$A$106 =F33i$E83'SASl0l SAS5 =D83$SE83S$A$105 =DB3'$E83S$A$106 84 =C84'$E84'$A$105 =C84'$E845$A$106 =F34'$EB4S$A$101'SA$5 =D84'$E84S$A$105 =D84'$E84'$AS06 85 =CB5$SE85'$A$105 =C855SE85'$AS106 =F35$E85S$A$1 O1SAS5 =D85'$E85S$A$105 =D85'SE85S$AS106 86 =C86S$E86'$A$105 =C86'$E86S$A$106 =F36'SE86'$ASlO1 $A$5 =D865$E86'$A$105 =D86S$E86S$A$106 87 =C87'$E87S$A$105 =C87'$E87S$A$106 =F37'$E87'$AS 1OPSA$5 =D87'SE87S$A$105 =D875$E87'$AS106 88 =C88'$EB88$A$105 =C88'$E88'$A$106 =F38S$E883$AS 10P$A$5 =DB88SE88SAAS105 =D883SE88&$A$1 06 89 =C89'$E89'$A$1 05 =C89S$E89'$A$ 106 =~F39'$E89$A$101 $A$5 =D895$E89$AS1 05 =D895$E89$A$1 06 90 =C90*SE90S$A$105 =C90Y$E90'$A$106 =F40'$EgOS$A$101'$AS5 =090¶$E905$A$105 =D90 E90S$A$106 91 =C91PSE91P$A$1 05 =C91 $E91 SA$106 =F41 $E91P$AS101'$A$5 =Dgl$E91PSAS105 =D91P$E91P$A$1 06 92 =C92$SE92S$A$105 =C925$E92S$A$106 =F42'$E92S$A$101 $AS5 =D92$SE92'$A$105 =D92'$E92'$A$106 93 i=C93'$E93'$A$105 =C93'$E93'$A$106 =F43XSE93X$A$101'$AS5 =D93'$E93'$A$105 =D93'$E93'$A$106 94 =SUM(GBI:G93) =SUM(HBI:H93) =SUM(181:193) =SUM(J81:J93) =SUM(KBI:K93) 95 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

96 =SUM(G77+G94) =SUM(H77.H94) =SUM(177.194) =SUM(J77+J94) =SUM(K77.K94) 97 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

98 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

9999 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

1 001 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

1o0l _ _ _ _ _ _ _ _ _ _ _ __l_ _ _ _ _ _ _ _ _ _ _ _ __l_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

1 021 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

1 03 1 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Calculation CDC-0000-N-1266, Rev. 3 Attachment A - Dose Calc. Formulas' Page A8 of A15

G H I I l_ J K

_ _ _ _1 1 1__ _ _ _ _

K__

t06 _ __ _ 1 I_ _ __ _ _ _

1-_-_--_

- __-_1 Th7_____ __________

10011 9 1_ _ _ _ _ _ _ _ _ _ __ _ _ _ _ __ _ _ _ _ __ _ _ _ _ _ __I_ _ __ _ _ _ __ _ _ _ I _ _ _ _ _ __ _ _ _ _I_ _ _ _ __ _ _ _ _I__ _ _ _

Calculation QDC-0000-N-1 266, Rev. 3 Attachment A - Dose Catc. Formulas Page A9of A15

= M 1

i 2

3 . I 5

6 7

8 10 11 12 131 14 Case I Case 2 15 Activity ActIvity 16 Release Release 17 moles moles 18 =G1837000000000/$K1816.023E+23 =H1 837000000000/SK1 816.023E+23 19 =G19-37000000000/$K19/6.023E+23 =H19-37000000000/$K19/6.023E+23 20 =G20-37000000000/SK2016.023E+23 =H20-37000000000/SK20/6.023E+23 21 =G21 37000000000/SK21/6.023E+23 =H21-3700000000015K21/6.023E+23 22 =G22-37000000000/$K22/6.023E+23 =H22-37000000000/SK22/6.023E+23 23 =SUM(L18:L22) -SUM(M18:M22) 24 26 27 28 29 30 31 Case I Case 2 32 Activity Activity 33 Release Release 34 curies curies 35 =135-6.023E+23*$K35137000000000 =J35-6.023E+23-SK35/37000000000 36 =136-6.023E+232SK36/37000000000 =J36-6.023E+23-SK36/37000000000 37 =1376.023E+23SK37137000000000 =J37-6.023E+23 SK37/37000000000 38 =138-6.023E+23Y$K38/37000000000 =J38-6.023E+23-SK38/37000000000 39 -- 39-6.023E+23 SK39/37000000000 -J39-6.023E+23-SK39137000000000 40 441 42 44 45 46 47 48 ___

49 501 Calculation CDC-0000-N-1266, Rev. 3 Attachment A - Dose Cale. Forrnulas Page Al10 of Al15

L l M 521 53

-6 _ _ _ _ _ _ _ _ _ _

57 _

58 59 61.

63 67 75 771 73 75 75 78 79 80 81 83 95.

155: ._._

94 _ _ _ _ _ _ _ _

891 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

96.

95 97 99 100 101_ _ _ _ _ _ _ _ _ _ _ _ _ _ _

102 __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _

10 3 __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _

Calculation ODC-0000-N-1266, Rev. 3 Attachment A - Dose Catc. Formulas Page AlI of Al5

L M 10 8 _ _ _ _ _ _ __ _ _ _ _ _ _

109 Calculation ODC-0000-N-1266, Rev. 3 Attachment A -Dose Calc. Formulas Page A12of A15

A B C D E F G l H I l K L 1 Peach Bottom Beginning of Core Life (100 Effective Full Power Days) and End of Cycle (EOC) Cesium Isotope Quantities 2 (Used for ;eneral Cs Molar Fraction Determination for _ST) ___

3 Decay 4 100 EFPD EOC 100 EFPD EOC Constant 100 EFPD EOC 5 (grams) (grams) At. Mass (gm-moles) Igm-moles) 11seconds Ci Cl 6 Cs-133 1.025E+05 1.678E+05 Cs-133 132.9054 7.712E+02 1.263E+03 0.OOOE+00 0.OOOE+00 0.000E+00 7 Cs-134 1.031 E+04 1.977E+04 Cs-134 133.9067 7.699E+01 1.476E+02 1.07E-08 1.335E+07 2.559E+07 8 Cs-135 4.502E+04 7.841E+04 Cs-135 134.9059 3.337E+02 5.812E+02 9.55E-15 5.188E+01 9.035E+01 9 Cs-137 1.087E+05 1.832E+05 Cs-137 136.9071 7.940E+02 1.338E+03 7.28E-10 9.410E+06 1.586E+07 10 Cs-136 2.37E-01 3.99E-01 6.10E-07 2.352E+06 3.964E+06 11 Cs-138 2.01 E-01 3.39E-01 3.59E-04 1.176E+09 1.982E+09 12 Total 2,665E+05 4.492E+05 1.976E+03 3.331E+03 13_

14 ANSI)ANS-18.1-1999 Relative Abundances In Reactor Water Molar Fraction 15 uCi/ram of moles/gram of ratio to Cs-133 39.0219% 37.9218%

16 Reactor Coolant Reactor Coolan Cs-137 Cs-134 3.8956% 4.4317%

17 Cs-134 3.00E-05 1.04E+08 2.56E-02 Cs-135 16.8848% 17.4506%

18 Cs-136 2.00E-05 1.21E+06 2.99E-04 Cs-137 40.1755% 40.1737%

19 Cs-137 8.OOE-05 4.07E+09 , 1.OOE+00 Cs-136 0.0120% 0.0120%

20 Cs-138 1.OOE-02 1.03E+06J 2.54E-04 Cs-138 . 0.0102% 0.0102%

Calculation QDC-0000-N-1266, Rev. 3 Attachment A - Dose Calc. Formulas Page A13 of A15

A B C D E l F G H 1 Peach Boa .-

2 (Used for _ .

3 . . .

4 100 EFPD EOC . 100 EFPD EOC 5 (grams) .(grams) At. Mass (gm-moles) (gm-moles) 6 Cs-133 102500 167800 Cs-133 132.9054 771.2 1263 7 Cs-134 10310 19770 Cs-134 133.9067 76.99 147.6 8 Cs-135 45020 78410 Cs-135 134.9059 333.7 581.2 9 Cs-137 108700 183200 Cs-137 136.9071 794 1338 10 Cs-136 =K1 0370000000001SJ1 0/6.023E+23 =L10-37000000000/$J1016.023E+23 11 Cs-138 =K11 -37000000000/SJ1 116.023E+23 =L1 '37000000000/SJ 116.023E+23 12 Total =SUM(B6:B9) =SUM(C6:C9) . =SUM(H6:H11) =SUM(16:111) 13 .

14 ANSIIANS .

15 uCilgram of molestgram of ratio to 16 Reactor Coolant Reactor Coolan Cs-137 .

17 Cs-134 0.00003 =B17-37000/J7 =C17/CS19 18 Cs-136 0.00002 =B18-370001J1 =C18ICS19 19 Cs-137 0.00008 =B19-370001J9 =C191C$19 I 20 Cs-138 0.01 =B20-37000/J1 =C20/CS19 I Calculation ODC-0000-N-1266, Rev. 3 Attachment A - Dose Calm Formulas Page Al14 of Al15

CK L 3 Decay 4 Constant 100 EFPD EOC 5 1/seconds Cl Ci 6 0 =H6-SJ6-6.023E+23137000000000 =16-SJ6-6.023E+23/37000000000 7 =LN(2y(2.062'86400-365.25) =H7-SJ7-6.023E+23/37000000000 =17-SJ7-6.023E+231370000D0000 8 =LN(2y(2300000'86400'365.25) =H8-SJ8-6.023E+23137000000000 =18-SJ8-6.023E+23/37000000000 9 =LN(2y(30.17-86400-365.25) -H9-SJ9-6.023E+23/37000000000 =19-SJ9-6.023E+23137000000000 10 =LN(2y(13.16-86400) -KS9-SBS18/SBSt9 =LS9SB$18/$BS 19 12 =LN(2y(32.2'60) =K$9-SBS20/$BS19 =LS9-SBS20/SBS19 13 ,7 7 14 Molar Fraction 15 Cs-133 =H6/HS12 =1611S12 16 Cs-134 =H7/HS12 =17/1S12 17 Cs-135 -H8/HS12 =1811$12 18 Cs-137 =H9/HS12 =1911S12 19 Cs-136 =H10/HS12 =11011S12 20 Cs-138 =H11IH$12 =11111S12 Calculation ODC-000-N-1 266, Rev. 3 Attachment A - Dose Calec Formulas PageAl5of A15

ICALCULATION NO. QDC-0000-N-1266, Attachment B REWV. NO. 2 l PAGENO.B1 of Bl Computer Disclosure Sheet Discipline Nuclear Client:: Exelon Corporation Date: August, 2005 Project: Quad Cities Units 1&2 MSLB AST Job No.

Program(s) used Rev No. Rev Date Calculation Set No.: QDC-0000-N-1266, Rev. 2 Attachment A spreadsheet N/A N/A Status I] Prelim.

[X ] Final

[ Void WGI Prequalification [ ] Yes

[XI No Run No.

Description:

Analysis

Description:

Spreadsheet used to perform dose assessment for MSLB, as described in calculation.

The attached computer output has been reviewed, the input data checked, And the results approved for release. Input criteria for this analysis were established.

By: On: August, 2005 Run by: H. Rothstein 4 '

Checked by: P. Reichert Approved by: H. Rothstein 34 . A,><

Remarks: WGI Form for Computer Software Control This spreadsheet is relatively straight-forward and was hand checked. Attachment includes the spreadsheet in both normal and formula display mode and so is completely documented.

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