ML052430335

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Rev. 3 to Calculation DRE02-0035, Re-analysis of Main Steam Line Break (MSLB) Accident Using Alternative Source Terms.
ML052430335
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 DRE02-0035, Rev 3
Download: ML052430335 (35)
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Text

ATTACHMENT 6 Calculation DRE02-0035, "Re-analysis of Main Steam Line Break (MSLB)

Accident Using Alternative Source Terms," Revision 3

CC-AA-309,-1001 FWvislo 2 ATrACEWT 1 NDtip Anlysts Cer Shedt Design Analysis (Majr Revision) I Last PagO No.'l 18/A1 B1-Analysis No.:' DRE02-002 5 Revsion:' 3 Tbte Re-alysis c/MAin Swim Line Btak (MSLB) Accident Using Akemrne SourTc Tems EUECR No_' 356383 .RFvlon. 0 Station(s): Dresden Cornponmnt(s):

UlnitNo- ' 2&3 ._..

Discipline. N Doscip. NO1. ROI, R02 CodelKeyword:" /AST, MSLB _ _ _ _ _ _ _

SafetyIDA Class: SR System Cod* '- 00 Strucm "._

CONTROLLED DOCMENT REFERENCES" Docmnent No.: Document Dromtoo No- _romTo DRE44030. RI GE-NE-=E22-0010344-01,M .

DRE97-0150, R2 _ _ _ _ _.

DRE9740071, PO From DRE020036. RO From .

Is this Design Analysis Safeguards information?" Yea 0 No ItHyess SYMAA-101 10a Does this Desln Analysis contain Unverified. ,r o 3 If Assumptions? ' ATI/AR:

This Design Analysis SUPERCEDES: " DREo24035. Rev. 2 i Its Description of Revision Vist affected pages for parm]3):"

Th;s revsb Incorporates responses to pertinent NRC Request lor Additional Inriation (RAls) wkh respect to all Exslon Nuclear Station Alternative Source Term Lces Amendment Applicatio. A now total reactor water mass release from the break of 140000 b Isutiraed as a bounding value from Standard Reviw Plan 15.8.4 for MSLB dose analysis purposes only. In addition, Ceslwu release with the reactor coolant as Cesium Iodine Is speclfcaly included, as well as noble ases. Fealy, additloral auunptlon" from Regulatory Guide 1.183 are Included to direcly Inicatconfrmance with this Regulatory Guide.

Preparm' " Harold Rothsteiln j / . q Print Name Sign Name Date Rethodvci V lled Reiew Alternate CalculatIons (attached) T"ating /

Reviewerl Paul Relicert /5 Print Name Sign Name Date Revw" m hidependent review Per 1eMw0 Nte°s.1Xr~S 3 -( r ,H40f~5 L App" tr1orver.i~a Print Nme Slgn 6aMe Date Exelon Print Name S* Name Date Is a Supplmental Review Requred?* Yes No a yo-ltsM d 3

,oprove: .Flcr2 -s D o Pthlt Nts SOM& Dte%

CALCULATION NO. DRE02-0035 l REV. NO. 3 l PAGE NO. 2 of 18 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 Reldease Model ............ 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 LP..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 Roam..9 4.0 DESIGN INPUT .............. . 10 4.1 Mass Release Data ............................................ . 10 4.2 Iodine and Noble Gas Activity Release .. 10 4.3 Control Room Data .. 11 4.4 EAB and LPZ Data (from the Dresden Technical Specifications) . ..............................I I

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 ............................................. 15 6.4 Dose Assessment .. 16 7.0

SUMMARY

AND CONCLUSIONS .. 17 8.0 OWNER'S ACCEPTANCE REVIEW CHECKLIST FOR EXTERNAL DESIGN ANALYSIS. 18 Attachments:

A. Spreadsheet Performing Cesium Molar Fraction and Total MSLB Dose Assessment, With Formula Sheets [pages Al-Al5]

B. Computer Disclosure Sheet [pages B I-B I]

CALCULATION NO. DRE02-0035 lREV.NO. 3 - l PAGE NO. 3 of 18 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 IOCFR100 and 10CFR50, General Design Criterion 19 requirements are:

i . Doses are evaluated in terms of Total Effective Dose Equivalent (TEDE) and evaluated against IOCFR50.67 limits as modified by RG 1.183.

2. Historically determined liquid reactor coolant and steam release continue to be the basis for the determination that no fuel damage results from an MSLB.
3. A simplified and more conservative basis is used for the determination of radionuclide releases based on a bounding reactor coolant blowdown value.
4. Iodine releases are based on reactor coolant 1-131 equivalent limitations In Dresden Technical Specifications for "Case 1 and a 20 times higher iodine spike limit for 'Case 2".
5. Cesium releases, as cesium iodide, and noble gas release are now considered In addition to iodine that has been historically assumed.

As per Dresden - UFSAR [Ref. 11 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 59,200 pounds of water and 17,000 pounds of steam In UFSAR (Rev. 4) Table 15.6-3. 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).

I CALCULATION NO. DRE02-0035 IREV.NO. 3 I PAGE NO. 4of 18 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 uCilgm 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 100,000 uCi /sec off-gas emission after 30 minutes decay, per UFSAR Section 15.6.4.5, and for the Dresden 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 uCigm 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 ANSVANS-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. DRE02-0035 lREV.NO. 3 l PAGE NO. 5 of 18 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 Dresden - UFSAR (e.g., Section 15.6). Specifically:

_=0.0133 Q ryu

%where

--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 1 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 offslte 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 3 & 41.

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

Dose,,E, (rem) = Release (Curies) * . (sec/mr3)

  • Breathing Rate (m3lsec)
  • Inhalation DCF (remacneD/Ci inhaled)

Q and Dose WE (rem) = Release (Curies) * -(sec/rn )

  • Submersion DCF (rem WE - m3/ Ci -sec) and finally, DoseTDE (rem) = DoseCEDE (rem) + DoseEDE (rem)

CALCULATION NO. DRE02-0035 I REV. NO. 3 PAGE NO. 6 of 18 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:

DoseEDE (rem) = Plume Concentration (CU/rn 3 )

  • Transit Duration (sec)
  • Breathing Rate (m3/sec)
  • Inhalation DCF (remce../Ci inhaled) and DoseEDE (rem) = Plume Concentration (Cirn3 )
  • Transit Duration (sec)
  • Submersion DCF(remmEr -m 3 I Ci -sec) and finally, DoseTEDE (rem)= DosccEDE (rem) + DoseEDE (rem) 2.6 Acceptance Criteria Dose acceptance criteria are per IOCFR50.67 [Ref. 7] and R.G. 1.183 [Ref. 6] guidance.

The following Table 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 LPZP 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. DRE02-0035 . REV. NO. 3 l PAGE NO. 7of I

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%ADL,:`tffW~aY , ISAgo%1, C b 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 vendors 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 pCi/gm 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 in the maximum time allowed by technical specifications. 5.5 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 A bounding value of 140,000 amount in the steam line and connecting lines at the time of the break lbs or reactor coolant is used

I CALCULATION NO. DRE02-0035 l REV. NO. 3 PAGE NO. Xof i I CALCULATION NO. DRE02-0035 I REV. NO. 3 I PAGE NO. 9 of 18 3.0 ASSUMPTIONS 3.1 ActivityRelease and Transport IIodine coolant activity isotopic distributions -and Noble Gas activity releases are taken from the Quad Cities UFSAR [Ref. 8] Section 15.6.4.5 which provides more detail than the Dresden UFSAR. The two facilities are sister units of the same basic design and operating conditions, as such the Iodine activity distribution would be similar.

  • 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 of 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 I 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 I of Ref. 6) based on the control room volume of 64,000 cubic feet [Ref. I1].

I CALCULATION NO. DRE02-0035 I REV. NO. 3 I PAGE NO.10 of 18 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

--to be released to maximize the iodine release, with a conservative fraction of this liquid flashing to steam.

4.2 Iodine and Noble Gas ActivityRelease 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 Dresden 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 a 100,000 uCi Isec 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-135M 0.0641 4.76E-01 Xe-135 0.0592 4.40E-01 Xe-137 0.288 2.14E+00 Xe-1 38 0.218 1.62E+00 The Dresden UFSAR provides distribution of fission products only In term of 1-131, 1-133, other halogens, and other fission products. Therefore, the distribution of fission products in the coolant was obtained from the UFSAR for Quad Cities, which is a plant similar In design to Dresden. 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 (pCVcc) 1-131 0.067

I CALCULATION NO. DRE02-0035 I REV. NO. 3 l PAGENO.11 of 18 l 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 ContrdI Room Data

  • Control Room Emergency Zone Volume = 81,000 cubic feet fRef. 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 andLPZ Data (from the Dresden Technical Specifications)

  • EAB Distance from Release: 800 m
  • LPZ Distance from Release,: 8,000 m

CALCULATION NO. DRE02-0035 REV. NO. 3 I PAGE NO.12 of 18

5.0 REFERENCES

1. Dresden UFSAR, Rev. 5
2. NEDO-21143-1, 'Radiological Accident Evaluation - The CONAC03 Code", General Electric Company, December, 1981.
3. Federal Guidance Report No. 11, uLimiting 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," 3/10171.
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 DRE04-0030, Rev. 1 "Atmospheric Dispersion Factors (XIQs) 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. Calculation DRE97-0071, "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-1 056, Rev. 1, "Suppression Pool pH Calculation for Alternative Source Terms".

I CALCULATION NO. DRE02-0035 I REV. NO. 3 l PAGE NO. 13 of 18 j 6.0 CALCULATIONS No fuel damage is expected for the limiting MSLB. As discussed in Section 2, two iodine concentrations are used (0.2 pCi/g and 4.0 pzCVg) [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 tomjeatmosphere 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 Control Room 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/Ib.

At 212 F, a steam enthalpy of 1150.5 BTU/lb and a liquid enthalpy of 180.17 BTUtIb 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 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

I CALCULATION NO. DRE02-0035 I REV. NO. 3 l PAGE NO.14 of 18 1 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 0 F, v. = 26.799 ft3/lb) were calculated as follows:

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

= 1,500,744 ft3

= (1,500.744 ft3 )1(35.3 ft3/m3)

= 42,514 m3 The volume of a hemisphere is nt d3 112. 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)/(1 mWs)). 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 Offslte Dose X/Q assessment, with F Pasquill Stability and a I m/sec wind speed.

x 0.0133 Q a u where ay = horizontal standard deviation of the plume (meters) u = windvelocity(mefers/second)

As calculated In the PAVAN run in Reference 9, at the 800 meter EAB distance ay is 30.2, and at the 8000 meter LPZ distance ay is 242. The resulting EAB and LPZ X/Qs are 4.40E-4 and 5.50E-05 sec/M 3 , respectively.

CALCULATION NO. DRE02-0035 I REV. NO. 3 I PAGE NO. 15 of 18 6.3 Release Isotopics and Quantificatlon 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 uC/gm, and Case 2 4.0 uCVgm. 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-1 34, Cs-1 35, and Cs-1 37, isotopic data (in Curies per Megawatt, and therefore generally applicable to similar BWRs such as Dresden) for end of cycle conditions from Reference 13 were used. For shorter lived isotopes such as Cs-136 and Cs-138, 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-1 33, representing about 38% of the cesium, is stable.

I CALCULATION NO. DRE02-0035 l REV. NO. 3 l PAGE NO. 16 of 18 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 XIQ for the EAB and LPZ.

Doses are calculated for inhalation (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.

I CALCULATION NO. DRE02-0035 I REV. NO. 3 _ _ l PAGE NO. 17 of 18 l 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 exceed the regulatoryJimits Location Case I Case 2 (normal equilibrium (Iodine spike limit of 0.2 pCI) limit of 4.0 juCi)

. Dose (rem TEDE) Dose (rem TEDE)

LIMITS CR: 5.0; EAB&LPZ: 2.5 CR: 5.0; EAB&LPZ: 25 EAB 3.25E-02 6.46E-01 LPZ 4.06E-03 . 8.06E-02 CR 9.20E-02 1.84E+00

I CALCULATION NO. DRE02-0035 I REV. NO. 3 I PAGE NO. 18 of - -145-8.0 OWNER'S ACCEPTANCE REVIEW CHECKLiST FOR EXTERNAL DESIGN 8.0 OWNER'S ACCEPTANCE REVIEW CHECKLIST FOR EXTERNAL DESIGN ANALYSIS DESIGN ANALYSIS NO. DRE02-0035 REV: 3 Yes No N/A

1. Do assumptions have sufficient rationale? 0o 0O Are assumptions compatible with the way the plant is operated and with the
2. licensing basis? 0l 0l
3. Do the design inputs have sufficient rationale? 0 0E
4. Are design inputs correct and reasonable?
5. Are design inputs compatible with the way the plant is operated and with the licensing basis? B/ ,0 0
6. Are Engineering Judgments clearly documented and justified?
7. Are Engineering Judgments compatible with the way the plant is operated and with the licensing basis? 0l 0
8. Do the results and conclusions satisfy the purpose and objective of the Design
8. Analysis?
9. Are the results and conclusions compatible with the way the plant is operated and with the licensing basis? 0a
10. Does the Design Analysis include the applicable design basis documentation? LV/

Have any limitations on the use of the results been identified and transmitted 12.

to the appropriate organizations?

Are there any unverified assumptions?

V:

01

13. Do all unverified assumptions have a tracking and closure mechanism in place?

Have all affected design analyses been documented on the Affected 14 Documents List (ADL) for the associated Configuration Change? .0 0 Do the sources of inputs and analysis methodology used meet current o- o3 technical requirements and regulatory commitments? (If the input sources or

15. analysis methodology are based on an out-of-date methodology or code, 0a/

additional reconciliation may be required if the site has since committed to a more recent code)

16. Have vendor supporting technical documents and references (including GE 16 DRFs) been reviewed when necessary? 0 0 EXELONREVIEWER: { Cf. A'r vidV, DATE:

Print / SJ aC-

A C I D E F G I H I I J l K L M 1Dresden 2&3 MSLB Dose Spreadsheet I Case 1: ReactorCoolantatmaxirnumvalue(DE-1.31 otO2uCiig)permitted 2: ~ I _ _ l for rwntinued full power opera~on 3 42514 Volume of doud (cubic meters) l Case 2: Reactor Coolant at maximum value permitted (DE 1-131 of 4.0 uCog) 4 6.35E+07 Mass of water in reector coolant release (Isms) I corresponding to an assumed prm-accident spike 5 54.6 seconds for cloud to pass over CR intake for wind speed o1 rm/second 6 81000 Volume of Control Room Envelope (cubhc fet)-maxImum used forconservatism __

7 140,000 Mass of Ubuld Water Released (rl) 8 9

40% Flashinq Fraction 5600W Mass of Steamrnh the Cloud (lb).

10 26.799 Vg (fthb)(based on 14.7 p and 212F) _ -

11 Reactor roolant iodine distributIon Is assumed to be a I gnvcc specific

_ravity 12 Case 1 Case 2 13 _ Release Release 14 Normalized Case I Case 2 Case I Case 2 Cloud Cloud Case 1 Case 2 15 ISO" Activity FGR 11 1-131 DE Normalized Normalized Adivity Aty Concentration -oncentratlo Decay Activity Activity 1a Distribution DCF' Activity Activity Activity Release Release Constant Release Release 17 uCVgm RemE/CI uClom uCilgm uCVgm al CI Ci/m3 CVm3 Ilseconds moles moles 18 1-131 0.07 3.29E+04 _JOE-02 8.23E-02 1.65E+00 5.22E+00 1.04E+02 1.23E-04 2A6E-03 9.98E-07 -3.22E-07 8.43E-06 19 1-132 0.38 3.81E+01 4.406-E3 5.40E-03 1.08E1 3.43E-01 8.86E+00 8.07EO06 1.6f1E44 8.37E-5 2.52E-10 20 5.04E-09 1-133 0.4 5.85E+03 7.1 1E-02 8.73E-02 1.75E+00 5.54E+00 1.11E+02 1.30E-04 2.81 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 2.866E01 3.36E-05 6.72E-04 2.91E-05 3.01 E-09 6.02E-08 23 Totals 1.63E-01 2.OOE-01 4.00E+00 . . Totals 3.62E-07 7.23E-06 24 1 'non-spiked spiked' 25 NEDOt NEDO. NEDO-20 21143-1' 21143-1l 21143-1' Case I Case 2 27 MSLt3 Case 1 Case 2 Release Release 28 Noble Gas AI ctivAy Cloud Cloud 29 Release Release Release Concentration Concentration _.._ _

30 Fractions Cl Cl CVm3 CVm3 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 0.0184 1.22E-01 1.22E-01 2.86E-06 2.86E-06 Actvity Activity Decay Activity Activity 33 Kr-85 0.000084 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 8.924-06 Molar Frac. moles Mols 1/seconds curles curies 35 Kr-88 0.0524 3.89E-01 3.89E-01 9.15E-06 9.1 5E46 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 3.81 E-05 3.81E-05 Cs-135 17.4506% 6.00E-08 120E-06 9.55E-15 9.32E-09 1.86E-07 37 Xe-131 M 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 7.286-10 1.64E-03 3.27E-02 39 Xe-133 0.0219 1.63E-01 1.63E-01 3.82E-06 3.82E406 Cs-138 0.0102% 3.50E-11 7.00E-10 3.59E-04 2.04E-01 4.09E+00 40 Xe-135M 0.0841 4.76E-01 4.76E-01 1.12E-05 1.12E-05 Totals 62.08% 2.13E-07 4.27E-06 41 Xe-135 0.0592 4.40E-01 4.40E-01 1.03E-05 1.03E-05 Balance is stable Cs-1 33 42 Xa-137 0.288 2.14E+00 2.14E+00 5.03E-05 5.03E-05 _ j j *__

43 Xe-138I 0.218 1.62E+00 1.62+00 3.81E-05 3.816-5 E-0 44 _ II -_ __ _- . -§ Calculation DRE02-0035, Rev. 3 Attachment A - Dose Calculation i Page Al of Al 5

A l C l E F l G l I [ L M 45 _ Cunes Released Case 1 Dose (rem CEDE) Case 2 Dose (rem CEDE) 46 to the Environment (Inhalation) (Inhalation) 47 Isotope Case t Case 2 DCF CR EAB LPZ CR EAB LPZ 48 1-131 5.22E800 1.04E+02 329E+04 7.65E-02 2.63E-02 3.28E-03 1.53E+00 5_25E-01 6.55E-02 49 1-132 3.43Et01  !.86E+00 3.81E+02 5.82E-05 2.00E-05 2.49E-06 1.16E-03 4.00-E04 4.998-05 50 133 5.54E+00 1.11E+02 5.85E+03 1.44E402 4.95E-03 6.18E-04 2.89E-01 9.90E-02 1.24E-02 51 B1134 1.65E-01 3,29E+00 1.31 E+02 9.60E-06 3.29E-06 4.11 E-07 1.92E 6.59E-05 8.22E-06 52 1-135 1.43E+00 2.86E+01 1.23E+03 7.82E-04 2.68E-04 3.35E-05 1.56E-02 5.37E-03 6.70E-04 53_ _ _ _ _ _

54 Cs-134 2.64E-03 5.28E-02 4.63E+04 5.44E-05 1.87E-05 2.33E-06 1.09E-03 3.73E-04 4.66E-05 55 Cs-135 9.32E-09 1.86E-07 4.55E+03 1.89E-1 I 6.48E-12 8.09E-13 3.78E-10 1.30E-10 1.62E-11 56 Cs-136 . 4.09E-04 8.18E-03 7.33E+03 1.33E-06 4.58E-07 5.7 E-08 2.67E-05 9.16E-06 1.14E-06 57 CS-137 1.64E-03 3.27E-02 3.I9E04 233E-05 7.98E-06 9.96E-07 4.65E-04 1.60E-04 1.99E-05 58 Cs-I 38 2.04E-01 4.09E+00 1.01E+02 923E-06 3.17E-06 3.95E-07 1.85E-04 6.34E-05 7.91 E-06 59 Sub-total (rem CEDE) I 9.19E-02 3.15E-02 3.94E-03 1.84E+00 6.31E-0 7.87E42 _

60 -

61 Curies Released . Case 1 Dose (rem EDE) Case Dose (rem EDE) 62 to the Environment (External) (External) 63 Isot!epe Case 1 Case 2 DCF2 CR EAB . LPZ CR EAB iLPZ 64 1-131 5.22E+00 1.04E+02 6.73E-02 1.76E-05 1.55E-04 1.93E805 3.51E-04 3.10E-03 3.87E-04 65 1-132 3.43E-01 6.86E+00 4.14E-01 7.09E-06 6.26E-05 7.81E-06 1.42E-04 1.25E-03 1.56E-04 66 1-133 5.54E+00 - 1.11E+02 1.09E-01 3.01E-05 2.65E-04 3.31E-o5 6.02E-04 5.31E-03 6.63E-04 67 1-134 1.65E-01 3.29E+00 4.81E-01 3.95E-06 3A9E-05 4.35E-06 7.90E-05 6.97E-04 8.70E-05 68 1-135 1 .A3E+00 2.86E+01 2.95E-01 2.10E-05 1.86E-04 2.32E-05 4.21E-04 3.71E-03 4.64E-04 69 _ _ _ _ _ _ _ _ _

70 Cs-134 2.648i-03 5.284-02 2.80E-01 3.69E-08 3.26E-07 4.06E-08 7.38E-07 6.51E-06 8.13E-07 71 Cs-135 9.32E-09 1.86E-07 2.09E86- 9.72E-19 8.58E-18 1.07E-18 1.94E-17 1.72E-16 2.14E-17 72 Cs-136 4.09E-04 8.18E-03 3.92E-01 8.00E-09 7.06E-08 8.81E-09 1.60E-07 1.418E6 l 1.76E-07 73 CS-137 I 1.64E-03 3.27E-02 2.868E-05 2.34E-12 2.06E-11 2.57E-12 4.68E 4.13E-10 5.15E-11 74 Cs-138 i 2.04Et-1l 4.09E+00 4.48E-01 4.57E-06 4.038-05 5.03E-06 9.14E-05 8.06E-04 1.01E-04 78 Sub-total (rem EDE) I I 8.43E405 7.44E-04 9.29E-05 1.69E-03 1.49E-02 1.86E-03 77 Iodine anrd Casum Total (rom TEDE) I. 920E-02 3.23E-02 4.03E-03 1.84E+00 6A68E-01 8.068E-02 78 _ _ Curies Releasea Case I Dose (rem EDE) Case 2 Dose (renmEDE)_

79 I _ to the Environment --_2_l (Extemal) _I (External) l 80 Case i Case 2 DCF CR EAB LPZ CR EAB LPZ 81 Kr-83M I 6.95E-02 6.95E-02 5.55E-06 1.92E-1 I 1.70E-10 2.12E-11 1.92E-11 1.70E-10 2.12E-11 62 Kr-85M _ _ 1.22E-0t 1.22E-01 2.77E-02 1.68E-07 1.48E-06 1.85E-07 1.68E-071 1.48E-06 1.85E-07 83 Kr-85 l l 4.75E-04 4.75E-04 4.40E-04 1.04E-11 9.21E-11 1.15E-11 1.04E-11 9.21E-11 1.15E-11 84 Kr-87 _ 3.79E-01 3.79E-01 1.52E-01 2.89E-06 2.55E45- 3.18E-06 2.89E-06 2.55E-05 3.18E-06 85 Kr-88 _ 3.89E-01 3.89E-01 3.77E-01 7.33E-06 6A7E-05 8.07E-06 7.33E-06 6.47E-05 8.07E-08 86 Kr-89 l l1.62E+00 1.62E+00 O.OOE+00 0.00E+00 O.OOE+00 O.W0E+00 O.OOE+00 0.00E+00 O.OOE+00 87 Xs-131M l - 3.88E-04 3.88E-04 1.44E-03 2.79E-11 2.46E-10 3.07E-11 2.79E-11 2.46E-10 3.07E-11 88 Xe-133M l l 5.81E-03 5.81E-03 5.07E-03 1.47E-09 1.30E-08 1.62E-09 1.47E-09 1.30E-08 1.62E-09 89 Xe-133 l _ 1.63E-01 1.63E-01 5.77E-03 4.68E-08 4.13E-07 5.16E-08 4.68E-08 4.13E-07 5.16E-08 90 Xe-135M l l 4.76E-01 4.76E-01 7.55E-02 1.79E-06 1.58E-05 1.97E-06 1.79E-06 1.58E-05 1.97E-06 91 Xe-135l _ 4AOE4-01 4.40E-01 4.40E-02 9.66E-07 8.52E-06 1.06E-06 9.66E-07 8.52E-06 1.06E-06 92 Xe-137 2.4+ 4+00 O.OOE+00 0.00+00 0.00+00 O.OOE+00 0.00+00 0.00+00 O.OOE+00 93 Xe-138 1.628+00 1.628+00 2.13E-01 1.72E-05 1.52E-04 1.90E-05 1.72E-05 1.52E-04 1.90E-05 94 Noble Gas Sub-total (rem EDE) 3.04E-05 2.69E-04 3.35E-05 3.04E-05 2.69E44 335E-45 96 Overall Total (rem TEDE) j I 4 920E-02 3.25E4-2 4.06E-03 1.S4E+00 l.46E401 l 8.06E-02 Calculation DRE02-M5, Rev. 3 Attachment A - Dose Calculation Page A2 of Al 5

--- -- .... ............. 1-1

A B C 0 E F G l H I l K l M 98 'Dose Conversion F"or (rem/Cure) from Fed" GuidanceRep&I(FGR) 11 parRg. Guide 1.183 99 '!Doe Convion Faor (rem-rn ue-ed ) om FGR 12 per Reg. Guide 1.1831 I . .

100 'From NEDO-21143-1. Radlobogcal Addent Evaluaton mThe CONAC83 Code. Gerw Elecit Company oember. 1981, . . _

101 win Ih Table 3-1 SLBA Source Adties-) Refease Fradions and page 3-3 CI conversion foansa fora 0.1 Cb/scdesign basis 1021 Iias rele rute and 5.5 second MSiV losure lfme, both oftid7 aprr P_ _ .

103 3.47E-04 rraati(m'/seand) per Reguatory Guide 1.1 83 (w*thout rrd-off) rste 104 3.89E. Contol Room Feome ctor per Reg. Guide 1.183. Rgiatory Posiion 4.27 _

105 3.02E401 EA n(meter) for Fstabity, (taken from PAVAN ns in Cab. ORE04-0030. Rev. 1) 106 2.420E+02 LPZ o (meter) for Fstby. (taken fom PAVAN nmin Cdc DRE4-4030 Rev. 1) . . __

107 1O00E Wln di (nms)I I I .1 _ _I__I 1 _08 (secondsimn) at EA Bounday 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 meogy _ _

t109 5. XIO (seoondslm&) at Low Ppulation Zone . 0-2 based on RG 1.5 methodolgy XE-05 __

Calculaton DREo2-0035, Rev. 3 Affachffent A - Dose Calcubathn Psgn A3 of Alt5

A B C D E F 1 Dresden 2&3 MSLB . Case 1:

2 3  :(A9-A10Y35.3 Volume of doud (cubic meters) Case 2:

4 =A7-453.59 Mass of water in reactor coolant r 5 -(A3-12/PI ()(113) seconds for cloudtopass ovrC i_

6 81000 Volume Of Control Room Enve__

7 140000 Mass of Llquld Water Reeased (_

8 0.4 Flashing Fraction ____

9 =A7-A8 Mass of Steam h the Claxt (b) 10 26.799 Va (ftP/lb) (based on 14.7 psI and 12 Reactor coolant iodine dis _____

133 14 = _ Normalized Case I Case 2 15 Isotope Activity FGR 11 1-131 DE - Normalized Normalized 16 Distribution OCF' Activity Activity Activity 17 uCVgm Rem iclr uClgm uCVgm uCVgm 18 1-131 0.067 32900 =C18'B18/C18 LD18021DS23_ E18-20 19 1-132 0.38 381 =C19'B19/CS18 b ii 2E19-20 20 1-133 0.4 5848 =C20'B201C$18 wD20002IDS23 _ E20'20 21 1-134 0.53 131 =C21-B211CS18 -D21-02S23 =E21-20 22 1-135 OA9 1230 =C22'822ICS18 =D22-0.21tD23 =E22-20 23 Totals -SUMMUMD OSUM(E18:E22) SUM(F18:F22) 24 'n on-spiked- *spiked-25 NEDO- NEDO-26 21143-13 21143-13 Case I Case 2 27 Case I Case 2 Case 2 Release Release 28 _ c _ tm _Activity AciitM y Cloud Cloud 29 Release Release Release Concentration Concentration 30 Ci Cl Clm3 Cim3 31 Kr-83M 0.00936 =S831'5.5-3'0.45 =SB31-5.5-3-045 =C31SAS3 r131tSA$3 32 Kr-85M 0.0164 =SB32'5.513'0A5 =SB32'5.5-3-045 =C32/SAS3 -032/$A$3 33 Kr85 08000064 *$B33-5.5-310.45 -SB33-5.5-3-0.45 =C33/SAS3 _D33

__A_3 34 Kr-87 0.0511 *S834'5.53-0.45 =S034'5.S304A5 -C34/$AS3 =D34ISAS3 35 Kr-88 0.0524 -SB35 5.53 0,45 =5835-5.53'045 -C351SAS3 =D35tSAS3 38 Kr-89 0218 =SB3685.5-3-0.45 -SB36'5.53-0A5 =C361SAS3 _D36_ _ __3 37 Xe-131 M 0.0000523 =837-5.5-3-0.45 -=S837'5.5-30.i5 SC371$AS3 _ __D37 __A_3 38 Xe-133M 0.000782 =$838-5.5-3-0.45 =SB38-5.5-3-0A5 =C381SAS3 =D38/A3 39 Xe-133 0.0219 =S939'5.5'330.45 =$B39'5.5-3-04A5 C39ISAS3 =D39tSAS3 40 Xe-i35M 0.0641 =S840-5.5-3 0.45 =SB40'5.530.45 *C40'SAS3 =D401SAS3 41 Xe-135 0.0592 =S841-5.53'0.45 _SB41'5.5-30,A5 wC4115AS3 -_-_'__-__1/_A_3 42 Xe-137 0.288 =S842-5.5-3 0.45 -B42'5.5-3-045 uC42/$AS3 -D42/SAS3 43 Xe-138 0.218 =SB43-5.53'0.45 .$8435.S30.45 =CWSAS3 - D431SA$3 44 K304 ;4W 3D3$3 45 Curies Released __ _

48, to the Environment 47 Isotope Case I Case 2 OCF' CR 48 1.131 ,G18 =H18 32900 = 18'5E48 SAS100'SA5S 49 1-132 =G19iH19 381 =119'$E49'SAS100-SAS5 50 1-133 __ =G20 =H20 5846 =i20'5E50'ASA100'A$5 51 1-134 =G21 =H2 1 131 *12 'SE51SA$100'AS5 Calculation ORE02-0035. Rev. 3 Attachment A - Dose Cate. Fomvilas Page A4 of Al 5

A 6C D _ E__ _ _ _ F 52 1-135 =G22 =H22 1230 E *122-SE52-SA$S100-SAS5 53 . _ _ _ _ _ _ _ _ _ _

54 Cs-134 _1.35 M35 -(3700000000000) 0.0000000125 =($C541SAS3) SE54-SAS100-SAS5 55 Cs-135 _L38 =M36 -(3700000000000)y0.00000000123 =($C5StSA$3y-SE55-SA$100-SAS5 56 Cs-136 -L37 =M37 =(3700000000000)-0.00000000198 =($C56/tAS3)ySES6-SAS100-AS5 57 CS-137 _ 1t138 =M38 - 3700000000000)-0.00000000863 =(SC57tSAS3)-SE57-SAS100-SA$5 58 Cs-138 1=_L39 -=M39 -(3700000000000 0.0000000000274 l=(SC58/$AS3)-SE58-$AS100-SA$5 59 I Sub-total (rem CEDE) __SUM(F48:F58) 601 611 Curies Reheased 62 _ _ to the Environment _

2 63 Isotope Case I Case 2 DCF CR 64 1-131_ --C48 =D48 0.06734 =118-SE64'5AS101-$AS5 65 1-132 =C49 =D49 0.4144 =119-SE65-SAS101'$AS5 66 1-133 =C50 =D50 0.10878 =120'SE66'SAS101'SAS5 67 1-134 _ =C51 =D51 0.481 =121'SE67-$AS101-SAS5 68 1-135 -=C52 =D52 0.29526 =122-SE68-SA$S01-SAS5 70 Cs-134 =L35 =M35 (37000000000000.000000)0000000757 =(SC70/SAS3)-5E70-SAS101-SA$5 71 Cs-135 =L38 =M36 =(3700000000000)-5.65E-19 =(SC71/SAS3 -SE71 -SAS101 -SA$5 72 Cs-136 1-=L37 =M37 '(3700000000000)-0.000000000000106 =(SC72tSA$3)-SE72'SAS1015-A$5 73 CS-137 _1-38 =M38 = 3700000000000y7.74E.18 =(SC73/SA$3)-$E73-AS1V01-SA$5 74 Cs-138 1.39 =M39 =(3700000000000)r0.00000000000121 =($C7415A$3)5$E74-$AS10P1$A$5 75 _ _ _ _ _ _ _ _ _ _ _ _

76 Sub-total (rem EDE) _SUM(F64:F74) 77 Iodine and Cesium Total =SUM(F59+F76) 78 Curies Released 79 to the Environment 80 Case I Case 2 DCF2 CR 81 Kr-83M _C311 =D31 0.00000555 -E31PSE81-SAS1$01-AS5 82 Kr-85M -C32 =D32 0.027676 =E32-SE82-SAS101-AS5 83 Kr-85 =C33 *D33 0.0004403 =E33-$E83-SA$ 01-SAS5 84 Kr-87 =C34 zD34 0.15244 =E34-SE84-SAS 101 $AS5 85 Kr-88 _ C35 =D35 .3774 =E35-$E8SSAS101-SAS5 86 Kr-89 -C____ 36 =D36 D =E36-SE86-AS101-SAS5 87 Xe-1311M -C37 =D37 0.0014393 =E37'SE87-SAS 01-SAS5 88 Xe-133M -C38 =038 0.005069 =E38-SE88-$A$101-SA$5 89 Xe-133 _C39 =D39 0.005M =E39'SE89'SA$101'SAS5 90 Xe-135M =C40 =D40 0.07548 =E40'SE9O-SAS101-SAS5 91 Xe-135 =C41 0.04403 -=E41SE91-SAS101-SA$5 4441 921 Xe-1137 --C42 __________________ =E42VSE92S$AS101PA$5 93 Xe-138 -- =C43 -D43 021349 - -E43 SE93SAS101PSAS5 94 Noble Gas Sub-otal (rem EDE)j .SUM(F81l:F93) 96 Overall Total (rem TEDE)j _ -. SUM(F77+F94) 97 98 Doss Convbin Factor (rmCLW) I 99 Dose Coffversin FatorM em m /Cur 100 From F NEDO-211143-1, 'Radlogical _ _

101 with Table 3.1 (SLBAo Swce Ad 102 orrerease teand 5.5 sead __ ___

103 0.000347 Breatl*, rate (m secwnd) per R _

Calculation DRE02-0035. Rev. 3 Attachment A - Dose Calim- Formulas . Page A5 of A15

[A B [ C 0 E F l04 =(SA$6I0.338Y117'3 _Co4*DIRcom Geometry FacwoMptRj __________________________________

106 30.2 EAS o, (mefars) for Fstab~ity, (tokafn I106 242 LPZ cr, (meters) for F stabiliy. (taken __ _ _ _ _ _ _ __ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

IS =0.01331A5205'A$107 _XJO se nu~ et EA Boundar'y. ______________________

11091 0.01331AS 106tA$107 I XO (secordsfm') et Low Powatio __ _ __ _ _ __ _ __ _ _ __ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _

Calculaijon DRE02-0035, Rev. 3 Attachment A . Dose CaIc. Formulas Page Ad of Al 5

G l H l I J I K.

I Reactor Cool at maximum value (DE I-131 of 02 uCVg) pemiitted for continued fUll power operation 3 Reactor Coolant at maximum value pemitted (DE 1-131 of 4.0 uCUg) corresponding loan assumed pre-accident spike 4 _ _ _ _ _ _ _ _ _ _ _

5 6~ _ _ _ _ _ _ _ _ _ _ _ __ i _ _ _ _

8 _ _

9 10 12 Case I Case 2

13. Release Release _

141 Case 1 Case 2 Cbud Cloud  !

15 Activity Activity Concentration Concentration I Decay 16 Release Release i Constant 17 CI Cl CVm3 CVm3 1 11seconds 18 =E1B SA410OOOOOo -G18-20 G1 8/A$3 =H1lB/SAS3 ______ = (2Y14-86400) 19 =E9-SAS4i1000000 G19-20 01 91/AS3 =HI94AZ3 -LN(2)(2.3 3600) 20 =E20SA$4/1000000 zG20'20 -G20/SAS3 =H20/SAS3 LN(2Y(20.8-3600) 21 =E2t SAS4i1DOODOO rG21*20 *G21ISA53 -H21I$AS3 =LN(2y(52.6-60) 22 *E22 SAS4/1000000 =G22 20 - G22/SAS3 -H22/$AS3 4LN(2y(6.61*3600) 23 _ Totals 24 25 _ -*

26 27, 28_

29 _ __ -

31 -_ _ Case 1 Case 2 _ _

32 Activity Acvity I Decay 33 Release Release Constant 34 ___________Molar Frac. moles moles I/seconds 35 Cs-134 0.044317152955112F0.95H35L$23 =0.95-SH35MS23 *LN(2y(2.062-86400 365.25) 36 Cs-135 0.174506296053598 =0.95SH361LS23 =0.95-SH36-MS23 =LNf2y(2300000 86400D365.25) 37 Cs-136 .000119942189253291 rO.95SH37LS23 =0.95-SH37'MS23 LN(2Y(13.16'86400) 38 CS-137 0.401736793048373 r0.95-SH38-LS23 =0.95-SH38-MS23 -LN(2y(30.17-86400;365.25) 39 .Cs-138 0.000101901239392202 =0.95-SH39-LS23 =0.95-SH39 MS23 =LNt2Vt327260) 40 Totals -SUM(H35:H39) - =SUM(135:139) =SUM(J35:J39) 41 Balance is stable Cs-133 _

42_ _

44 __

45 Case 1Dose (rem CEDE) Case 2 Dose (rem CEDE).

45 (lnhalation) (Inhalation) 47 EAB LPZ CR EAB LPZ 48 -C48-SE48-SA$100 SAS105 =C48-SE48-SA$t00SAS06 -J18-SE48-SAS 100-AS5 =D48-SE48-SAS1OO-SAS105 =D48-$E48-$A$100OSA$106 49 rC49-SE49-SAS100-SAS105 -C49-$E495$AS100-SAS106 -*J19SE49-SAS100SAS5 =D49-SE49-SAS100-SA$105 =D49-SE49-SA$100-SAS106 50 -C50-SE50-SA$10W-SAS105 =C50SE50 SAS100 SA$106 *J20-SE50-SAS100'SAS5 :D50 SE50 SA$t0-SA$105 =D50iSE50SAS100$ASIO 51 -C51*SE5t SA$1tO0SA$105 -C511$E515*AStoo-SA$106 =J2tSE51t*AS100-SAS5 =D51SE5 $AS 100SASI15 =D51 E51SAS100SAS106 Calculation DRE02 0035, Rev. 3 Attachmrent A -Dose Cale. Formulas Page A7 of Al 5

G H _ _ _ __ _ _ _ _ K__

52 =CS2'$E525$A$100'SA$1 05 =C52I$E2SVSAIGOSA$106 =M2TSE52S$ASI 00SAS5 =D52TSE52SASl00$A5l05 =D52'$E52'$SM100$A$l06 53 -_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _

54 =CS4$ES.4SAS100SAS105 -CS'E54S$A$100S$AS106 =($D54/$AS15E545$A$100'$A$5 =D54S$E5-4'$AS00'SAS105 rD54'$E54'SAS100S$AS106 55 =C55SSE55S$ASO00SASl05 =C55'SE555SAS100S$A$106 -($D"5A$3)'SE55-$A$100-$A$5 =DS55$E55'SAS100S$AS105 zD55S$E55S$A$100OSA$106 56 =CS6'SE56$A$100S$AS105 -C56S$E565SAS100S$AS106 =($D565$A$3)5E568SA$1005$AS5 =DS6S$E56S$AS1005$AS105 vD56'SE56ISA$100'$ASl06 57 =-C57'SE57r5A$1005ASl05 I=C57S$E5rSAS100S$A$106 =(SD57/$A$3)SE57I$AS100S$AS5 -DS7$E57S$AS1005$A$105 -D57rSE5?'$A$100S$AS1D6 58 I=CS8S$E58S$A51005MA105 I=C58S$E585$A$100S$A$106 =(SD58JS3)$E581MA1001$A$5 I=D58'SE58'$A$100S$A$105 mD58i$E58S$AS100S$AS106 59 I&SUM(048:GSS I.SUM(HAI8:HS8) -SUMQ14:158) (SUM(J48:J58) wSUM(K48:K58) 60 1_ _ _ _ _ _ _

6`1 I Case IDose (rem EDE) Case 2Dose (rem EDE) 621 External)_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ (External) -

631 EAB LPZ CR EAS LPZ 64 1-C64'SE64i$A$105 =C84i$E64S$AS106 =JI8'$E64$A$I101SAS5 =D64S$E64'SA$105 =D64S$E>4S$AS106 65 =C65S$E65S$AS105 =C655$E65'SAS1G6 =J19S$E655$A$101'$AS5 =D65'SE655$AS105 0D65'$E65SA5106 68 -C88$E6805AS105 =C66$E668SA5106 =J20S$E66S$ASl0J'AS5 rDf66SE68OSAS105 =D66'$E68S$AS1D6 67 --C67rSE67PSA$105 =C67'SE675$A$106 =J21VSE67S$AS101'A$5 =D67S$E67PSAS105 =D67'SE67S$A$106 68 --C685$E68'SAS105 --C68'$E68S$AS106 =J22S$E685$AS101'$A$5 =D68S$E68S$A5105 =DC68SE68S$A$106 69 _ _ _ _ _ _ _ _ _ _ _ _ _ _

70 =C70'$E70S$A$105 =C705SE70S$A$106 =(SD70/SAS3)'$E70'SAStOl 5AS5 =070'$E70S$AS105 =D70OSE705$A$106 71 .=071$E71VSAS105 =C71PSE71S$A$106 -(SD71/$AS3)'$E71SAIOPA$10'A5 =D71PSE71VSAS105 =D71SE7VS$AS106 72 =C?2'$E72S$AS105 =C72S$E72'SA$106 -($07213AS3)$E72I$A$101$A$5 -D72i$E72S$AS105 -D725$E72VSAS106 73 =C73'SE73'$AS105 --C73$E73'SA$106 -(SD73ISAs3)S$E73-$A$101 SAS5 =D?3S$E73'SA$105 =D73S$E73'SAS106 74 =C74'SE74S$A$105 --C74'SE745$AS106 .(SD7415AS3)S$E74SASOVA$l~- 5 -D74'SE74S$A$105 vD74$E74S$A$106 75 _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _

76 =SUM(G6.4:G74) -SUM(H64:H74 SUM(16.4:174) =SUM(J64:J74 -SUM(K64:K74) 77 *.SUM(G59+G76) -SUM(H5941H75) -SUM(1594176) -SUM J59+J76) -SUM(K59+K76)

78. Case 1 Dose (rem EDE) _ ___________Case 2 Dose (rem EDE) ___________

79 1 (External) _ _ _ _ _ _ _ _ _ _ _ _ _ __(External)_ _ _ _ _ _ _ _ _ _ _ _ _

801 EAB LPZ CR EAS LPZ 81 j=C81 SE81'$A5l05 --CBPSE81r$A$106 =F31VSE8lrSASl01 SA$5 =D8lVSE81 S$A1D5 =D8'$EB1S$AS106 62 -C825SE82SA5S105 -=CS2SEB2S$A$106 =F32-SE82S$A$1iOPA$5 =DB25SE82'$A$105 -D82'$E82'SAS108 83 -CB35$EB3$AS105 -=C83$E835$A$106 =F33'SE83S$ASI10SAS5 =DB3S$E83'$A$105 =Da3'$E83S$A$106 84 -CB45SE84S$AS105 =C8-4$ES4S$AS106 =F34S$E84S$A$101V$A5 zD84$SE84$AS$105 =D64$Ea4'SAS106 85 -C85'SE85S$AS105 =C85'$EB5SASIG6 =F355$E855$AS101$A$5 *0855SE85'$AS105 -DB5$E85S$A$106 88 =C86'SE865$AS105 =CS6'SE86S$A$106 =F36'SE86S$AS11OSAS5 -D86'SE86'$A$105 -D86'SE861$A$106 87 -C87SE87S$AS105 =C87SE87rSA$106 -F375$EB7$AS1O1S$AS5 =DB7$EB7S$AS105 ZD87'SE87SA$106 88 -C885$E88SAS105 =C88S$E885$AS106 =F38S$E885SAS10l'$A$5 =D88'$E88SA.SI05 0D885E88SA5106 89 aC89S$E89SA5S105 =CS9S$E89S$AS106 =F39S$E8'SAS10lVSAS5 =D895SE69$SA$1 05 D89S$E895$A$106 90 =C9OSE90OSASl05 =C90'SE901$A5108 =F40'SE90SA$101PSAS5 =D90'$E90S$AS105 =090'$E90S$A$106 91 =C91PSE91'SAS105 -'C9ISE9rS$A$106 =F4 I'E91P$ASl 0rSA$5 -D9lrSE91P$A105 -Dgl'$E91VSA$106 92 =C92'SE921AS105 --C92'SE92'$A$106 =F42S$E925$A5 1OVA$5 =D925$E92'SAS105 MD92'SE92S$AS108 93 *'C93S$E93YSA$105 =C93X5E93'SA$1G6 =F43S$E93S$AS10lVSA$5 *D93'$E935$AS105 =D93S$E93'SASl0B 94SUM081:G93) -SUM HB1:H93_ -SUM(IB1:193) wSUM(J8l:J93). vSUM(K81:K93) 96 -SUM(G77+G94) .-SUM 1177.194j -SUM(177+194) *sum(j77#.j94) -&SUM(KY77K94) 981__ _ I__

991.1_ __

10211___ __ __

1031_ ___ _ _ ___ ___

Calculation DRE02-0035. Rev. 3 Attachment A - Dose Cali-- Foffnufas PS"e AB of Al 5

G H I T K 104 __ _ _ _ _ . _

107 .

108.

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _I _ _ __ __ _

Calculadon DRE02-0035, Rev. 3 Attachment A - Dose Catc. Fofmftas Page A9 Of Al S

L M 4

6 7

13 14 cameI Case 2 15 Ac~ ~ActMty 161 Release Release 171 Moies moles 18 ZG18'3700O0000000/SKIM~.023E+23 18'370000000001SK1IMOM2E423 19 wG19'37000Q0000003K19t6.0231E+23 =H1937000O000000j$K1916.023E423 20 =G20'3700O0000000t$K20I6.023E*23 -H20r370000D00001SK2016.023E+23 21 =G21P37000000000/SK211.023E+23 =H21'37000000000/$K2116.023E+23 22 -G223700O0000O00IK22I6.023E+23 eH2237000000000/$K22I8.023E+23 23 M IBL2) =SUM(M18:M22) 27 311case 1 Case 2 32 Acvlt Activty 33 Release Release 34 curies auides 35 =1356.023E.23-4K35/37000000000 =j35'6.023E+23S$K35/370000000D0 36 =136'6.023E.23'SK36I3700O0000000 =J.368.023E+23'$K36&37000000000 377 =137-6.023E+~23S$K37/37000000000 =J37*8.023E+231SK37/37000D00000 38 -138'6.023E.235$K38/37000000000 =J3868.023E+23SK38137000000000 39 rl39'6.023E.23'SK9t37000000000 =J3968.023E+23$K39/37000000000 42 44 45__ _ _ _ _ _ _ _ _ _ _ _ _ _

48 _ _ _ _ _ _ _

47 48 49 50 _ _ _ _ _ _ _ _ _

51 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Calculallon DRE02-0035, Rev. 3 Attachment A - Dose Caic. Formulas PagoAl00f AIS

I L M 521 53 _ __ l 55 58 57 58 59 60_ _ _ _ _ _ _ _

61 62 63 64 66 68 70t 72.

73 77 78 80 82 83 84 85 86 888 89 _ .

92 93 94 95 96 ,_ _ _ _ _ _ _ _

97 98_ _ _ _ _

99. ._

100 101 102 I103 _ _ _ _ _ _ _ __ _ _ _ _ _ _

Caloutafon DRE02-0035. Rev. 3 Aftacment A - Dose Cac. Formulas Page All ofdA15

L M 104 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

10 8 __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

106 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Calculaffon DRE02-0035, Rev. 3 Calculatlci DREO2-005.

Rev.

3Attachmnent A - Dose Cala. Fomiulas PageA12 aeloA1 of AIS

A 8 A D E F G H I J K L 1 Peach Bottom Bealnning of Core LifU 100 Effectiv Full Power Days and End of Cycle (EOC) Cesium hIotope Quantities-2 (Used for General Cs Molar Fraction Determination forAS _

3 _ __.. Decay 4 100 EFPD EOC 100 EFPD EOC Constant 100 EFPD EOC 5 - .g!s). __ _ At Mass fa rl/ ) o) llseconds I__ Cl Cl 6 Cs-133 1.025E+05 1.678E+05 Cs-133 132.9054 7.712E+02 1.263E+03 O.OOOE400 O.OOOE+00 O.00E+O0 7 Cs-134 1.0311E404 1.977E404 Cs-134 133.9067 7.699E+0l 1A76E602 1.07E-08 1.335E+07 2.559E+07 8 Cs-135 4.502E+04 7.841 E+04 Cs-135 134.9059 3.337E602 5.812E+02 9.55E-15 5.188E+01 9.035E+01 9 CsM37 1.087E+05 1.832E+05. Cs-137 136.9071 7.940E+02 1.338E+03 7.28E-10 9.410E+06 10 1.586E+07

_ Cs-136 -2.37E-01 3.99E-01 6.1 OE-07 2.352E0o3 3.964E608 11 _ Cs-138 2.01E-01 339E-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 ANS lANS.18.1 -1999 Relative Abundances in Reactor Water . .-

_Molar Fraction 15 luc~ ram of mo aram of ratio to-_-- Cs-133 39.0219% 37.9218%

I18 ___Coa Reactor a Coolant Cs-i 37_ _ Cs-134 3.8956% 4.4317%

17 Cs-134 3.00E 08 256E-02 Cs-135 16.848% 17.4506%

8 Cs.136 2.E- 1.21 E408 2.99E-04 _ Cs-137 40.1755% 40.1737%

19 Cs-137 8 05 0 +09 1.00E+00 Cs-136 0.0120% 0.0120%

20 Cs-138 1.OOE-02 1.03E+0 2.54E-04 Cs-138 0.0102% 0.0102%

Calculation DRE02-6M5. Rev. 3 Attachment A - Cs Molar Fraction CaFc. Page A13 of A15

A B C D E F G H 1 IPeach Boo _ _ _ _ __ _ _ _ _ _ _ _ _ _ _

2 (Usedfor . i 4 IOOEFPD EOC 1D0 EFPD 5 _ rsj (grams _ At. Mass -gm-moles) 6 Cs-133 102500 167800 Cs-133 132.9054 771.2 7 Cs-134 10310 19770 . _ Cs-134 133.9067 76.99 B Cs-135 45020 78410 Cs-135 134.9059 333.7 9 Cs-137 108700 183200 Cs-137 136.9071 794 10 . _ Cs-136 _H9'D1I 11 _ Cs-138 =H90D20 12 Total WSUM(Bs:B9) .SUM(C6:C9) __ SUM(HB:H11) 14 ANSIIANS 4 .

15 luCl/gram of molestgram of ratio to .

16 Reactor Coolant Reactor Coolant Cs-_37 -__ _

17 Cs-134 0.00003 tB17'37000/J7 =C171CS19 18 Cs-136 0.00002 =B1837000/J10 =C1B/CS19 _ _

19 Cs-137 0.00008 =B19-37000IJ9 =C19/CSI9 20 Cs-138 0.01 =B20-37000/J11 -C20JCS19 I_

Cabculation DRE02-0035, Rev. 3 Attadnent A - Cs Molar Frac. Calc. Formulas pageA14 of A15

.. . ........ .. . . . .. . .. . . .. . . ..... . ".. .. . -.- - '. - ... - I - , I- ... I .

.1.

1 K L 3 Decay _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

4 EOC Constant 100 EFPD EOC 5 (gm-moles) Iiseconds Cl Cl 6 1263 0 =H6-$J8'6.023E+23137000000000 *16J6-6.023E+23/37000000000 7 147.6 tN(2y(2.062 86400 365.25) =H7'SJ7-6.023E+23/31000000000 =l7 SJ76.023E+23/3700000O000 8 581.2 -LN(2Y(2300000-86400-36525) =H8-SJ8'6.023E+2313700100000 =18-SJ8-6.023E+23/37000000000 9 1338 =LN(2y(30.17-86400-36525) H9sJ9'6.023E+23/37000000000 =19SJ9'6.023E+23137000000000 10 =L1037000000000$J101.6023E+23 _ -LN(2yt13.16-B6400) _ =K9SSB$16tSB9 =LS9-$S$BS B$19 _

11 L1 1*370000000001SJ1116.023E+23 =LN(2y(32.2-60) =KS9$BaS20/SBS19 =LS9-SBS201S8$19 -

12 mSUM(16:111_

13 14 Molar Fraction 15 Cs-133 =H61HS12 -=1611$12 16 Cs-134 =H71H$12 I'171112 17 Cs-135 =H8rHS12 =181IS12 18 Cs-137 =H9/HS12 =19/1S12 19 Cs-136 =H101HS12 =110/1$12 20 Cs138 =H111HS12 =11111S12 Calottlation DRE02 0035, Rev. 3 Attachment A - Cs Molar Frac. Cac. Fortnlas Page A15 of A15

I CALCULATION O0.DRE020035, Attachment B I REV.NO. 3 l PAGENO.B1 of BI I Computer Disclosure Sheet Discipline Nuclear Client:: Exelon Corporation Date: August, 2005 Project: Dresden Units 2&3 MSLB AST Job No.

Program(s) used Rev No. Rev Date Calculation Set No.: DRE02-0035, Rev. 2 Attachment A spreadsheet NIA NIA Status [ J Prelim.

[X] Final

[ ]Vold WGI Prequalification [ 1 Yes

[X] 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 ran-/i Checked by: P. Reichert _

Approved by: H.Rothstein 0 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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