ML060580585

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Calculation DRE02-0035, Revision 2, Re-Analysis of Main Steam Line Break Accident Using Alternative Source Terms
ML060580585
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 01/31/2006
From: Flick E, Mscisz T, Reichert P, Rothstein H
Exelon Generation Co, Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
CC-AA-309-1001, Rev 2, RS-06-026 DRE02-0035, Rev 2
Download: ML060580585 (32)
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Text

ATTACHMENT 3 Calculation DRE02-0035, Revision 2, "Re-analysis of Main Steam Line Break (MSLE) Accident Using Alternative Source Terms"

CC-AA-309-1001 Revision 2 ATTAChMENW I DesgAnalysis Cover Shet Design Analysis (Major Revislon) Last Page No. 18 I Att. E1-l 2

Analysis No.:' DRE032-05 Revision: 4

Title:

s Re-analysis of Main Steam Une Break (MSLB) Accident Using Altcruative Source Temts EC/ECR No.:; 356383 Revision:, 0 Statlon(s) Dresden Component(s):k ____.__

UnKtNo.: 2&3 . _ _.

Dlscipflne: N _____

Descrip. NOt. R01, R02 CodelKeyword: ' /AST, MSL8 _

Safety/OA Class:" SR ___

System Code: 00 _ ._._ _-

Structure: 'a CONTROLLED DOCUMENT REFERENCES "

Document No.:;ronVTo Document No.: FroinsrT DRE04-003O, RtIrn GE-NE-A2200103-644, RO :roin DRE97-O150, R2 DRE97-0,RO rom _

ORED2-0036, Ro Is this Design Analysis Safeguards Informatlon?"' Yes C No 0 If yes, se SY-AA-101 -108 Does this Design Analysis contain Unverified Yes No 0 ATUARy I  :

Assumptions? I e 3N TA#

This Design Analysis SUPERCEDES:" DRE02.0035. Rev. 3 Infts Description of Revision (list affected pages for parfialst: '

This revision corrects for the use of normalized values k4cactivity releases for bodine in column 0 on page Al ard fornula page A4 of the calculation spreadsheet, with resulting changes in calculated doses as provided In the Summary and Cncdusions section. A separate cell-by-cell independent check was also performed, as documented in Attachmnent B.

Preparer 2 Harold Rothstein j st 1 , /f A  ;

Print Name Sign Name Date Rethod of Revl~w 2 'sr Detailed Review Alternate Calculations (attached) a Testing 0 Reviewer:.- Paul Reichert Print Name Sign Name Date Review Independent review 0 Peer review 0 Notes: ' j p 7 I'-1~ gw p PA:NO r'e a i ot~

External f r 4

Approver:

E Print Name Sign Namer Date Exelon da5i //t Reviewere -2 aw ,7 DsteJ Is a Supplemental Review Requiredi?' *2. 26es 0] No la It~ etai~Attachmenit 3 Exelon U.f Cos&;WFW4cu

/../t/

pa7-~ (JoA Approver2 Fr1, ilc ---- v (QC Print Name Shn2 Nsrne Date

CALCULATION NO. DRE02-0035 TREV. NO. 4 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 Release 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 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 ................................................ .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) ............................................. 11

5.0 REFERENCES

................................................ . 12 6.0 CALCULATIONS ............. 13 6.1 Cloud Volumes, Masses, and Control Room Intake Transit Times ....e . ......................................

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 AI-A12]

B. Computer Disclosure Sheet [pages B 1-B I]

I CALCULATION NO. DRE02-0035 l REV.NO. 4 l FPAGE NO. 3of18 1.0 PURPOSE/OBJECTIVE 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:

1. Doses are evaluated in terms of Total Effective Dose Equivalent (TEDEE) and evaluated against 10CFR50.67 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. 1] 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).

II CALCULATION CALCULATION NO.NO._ DRE02-0035

_RE. _ 0_ I, REV. NO. 4

_E.NO. 4, I, PAGE AEO NO. 4 of 18

_o_1. 1I 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 1 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 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 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-1 8.1-1999 [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

CALCULATION NO. DRE02-0035 l REV. NO. 4 l PAGE NO. 5 of 18 EAB and LPZ XIQ'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:

x 0.0133 ayu where ay = horizontal standard deviation of the plume (meters) u = wind velocity (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.

Although Control Room X/Q values do not apply to this calculation, equivalent X/Q's are developed in the spreadsheet contained in Attachment A.

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 3 & 4].

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

Dose CEDE (rem) = Release (Curies) * - (sec/M3 )* Breathing Rate (m3 /sec)

  • Inhalation DCF (remcEDE/Ci inhaled)

Q and Dose EDE (rem) = Release (Curies) * - (sec/mi )

  • Submersion DCF (rem EDE - m3 / Ci -sec)

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

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Vslrt^r A VZroi I LALLULAIIUN NU. UKLUL-UU3 I KtW.NU. 4 I k'AUtINU. 001 L 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 rale. 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 (m 3 /sec)
  • Inhalation DCF (remcEDE/Ci inhaled) and DoseEDE (rem) = Plume Concentration (Ci/m3 )
  • Transit Duration (sec)
  • Submersion DCF (remEDE - m3/ Ci - sec) and finally, Dose TEDE (rem) = DoseCEDE (rem) + Dose EDE (rem) 2.6 Acceptance Criteria Dose acceptance criteria are per 10CFR50.67 [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 LU1Z 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 I REV. NO. 4 1 PAGE NO. 7 of 1A 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 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

CALCULATION NO. DRE02-0035 REV. NO. 4 PAGE NO. 8of 1 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.

I CALCULATION NO. DRE02-0035 l REV. NO. 4 l PAGE NO. 9 of 18 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. 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 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.
  • Extemal 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 maximum control room volume of 81,000 cubic feet [Ref.

11].

I CALCULATION NO. DRE02-0035 l REV. NO. 4 l PAGE NO. 10 of 18 l 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

/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 Cures 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-1 31M 0.0000523 3.88E-04 Xe-1 33M 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-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.

I CALCULATION NO. DRE02-0035 I REV. NO. 4 l PAGE NO. 11 of 18 Iodine Isotope Act vity (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

  • Control Room Emergency Zone Volume = 81,000 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 (from the Dresden Technical Specifications)

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

I CALCULATION NO. DRE02-0035 l REV. NO. 4 l PAGE NO. 12 of 18 l

5.0 REFERENCES

1. Dresden UFSAR, Rev. 5
2. NEDO-21143-1, "Radiological Accident Evaluation - The CONAC03 Ccode", 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 DRE04-0030, Rev. 1 "Atmospheric Dispersion Factors (X/ICs) 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 § REV. NO. 4 PAGE NO. 13 of 18-l 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 pCi/g) [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 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/lb.

At 212 F, a steam enthalpy of 1150.5 BTU/lb and a liquid enthalpy of 1130.17 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 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/lb)

= 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. 4 I PAGE NO. 14 of 18 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 'F, vg = 26.799 ft3 Ilb) were calculated as follows:

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

= 1,500,744 ft"

= (1,500,744 fl 3 )/(35.3 ft3 /m3 )

= 42,514 m3 The volume of a hemisphere is nr d3 /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)/(1 mWs)). Therefore, at a wind speed of 1 mi/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 OYu where ay = horizontal standard deviation of the plume (meters) u = wind velocity (meters/second)

As calculated in the PAVAN run in Reference 9, at the 800 meter EAB distance cy 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.

I CALCULATION NO. DRE02-0035 I REV. NO. 4 l PAGE NO. 15 of 18 6.3 Release Isotopics and Quantification The iodine, noble gas and cesium activily 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-11 CEDE dose conversion factors to obtain coolant concentrations corresponding to Case 1: 0.2 uC/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-133, Cs-134, Cs-135, and Cs-137, 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-1 36 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-133, representing about 38% of the cesium, is stable.

I CALCULATION NO. DRE02-0035 REV. NO. 4 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 X/Q 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 l REV. NO. 4 l PAGE NO. 17 of 18 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 regulatory limits.

Location Case I Case 2 (normal equilibrium (iodine spike limit of 0.2 piCi) 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 0.0848 1.70 LPZ 1 0.0106 0.212 CR 1 0.189 3.77

I CALCULATION NO. DRE02-0035 _ REV. NO. 4 I PAGE NO. 18 of 18 8.0 OWNER'S ACCEPTANCE REVIEW CHECKLIST FOR EXERNIAL DESIGN ANALYSIS DESIGN ANALYSIS NO. DRE024.035 REV: 4 Yes No

1. Do assumptions have sufficient rationale? El
2. Are assumptions compatible with the way the plant is operated and with the El licensing basis? (2/
3. Do the design inputs have sufficient rationale? 51
4. Are design inputs correct and reasonable? El
5. Are design inputs compatible with the way the plant is operated and with the ER" El licensing basis?

52/

6. Are Engineering Judgments clearly documented and justified? El
7. Are Engineering Judgments compatible with the way the plant is operated and with the licensing basis? S1
8. Do the results and conclusions satisfy the purpose and objective of the Design
8. Analysis? El El
9. Are the results and conclusions compatible with the way the plant is operated and with the licensing basis? El
10. Does the Design Analysis include the applicable design basis documentation'? El II. Have any limitations on the use of the results been identified and transmitted ER/
  • 1 to the appropriate organizations? El GE/
12. Are there any unverified assumptions?

13 Do all unverified assumptions have a tracking and closure mechanism in 2El1 13 place?

14. Have all affected design analyses been documented on the Affected Documents List (ADL) for the associated Configuration Change? El M Do the sources of inputs and analysis methodology used meet current technical requirements and regulatory commitments? (If the input sources or
15. analysis methodology are based on an out-of-date methodology or code, El 0 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? 5 51 EXELON REVIEWER: /, J -/19 Print / Sfi

- DATE: ..-A44

A I B I C I D E F G l H I I l J I K L M 1 Dresden 2&3 MSLB Dose Spreadsheet Case 1: Reactor Coolant at maximum value (DE 1-131 of 0.2 uCi/g) permitted 2 I I for continued full power operation 3 42514 Volume of cloud (cubic meters) Case 2: Reactor Coolant at maximum value permitted (DE 1-131 of 4.0 uCi/g) 4 6.35E+07 Mass of water in reactor coolant release (grams) corresponding to an assumed pre-accident spike 5 54.6 seconds for doud to pass over CR intake for wind speed of 1 m/second I 6 81000 Volume of Control Room Envelope (cubic feet) - maximum used for conservatism 7 140,000 Mass of Uquid Water Released (lb) _ _

8 40% Flashing Fraction l 9 56000 Mass of Steam in the Cloud (lb) 10 26.799 Vg (ft 3/lb) (based on 14.7 psi and 212F) 1Reactor coolant iodine distribution is assumed to be a I gm/cc specfic gravity 12 Case I Case22 T3 Release Release 1 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 Activty Concentration :oncentratior Decay Activity Activity 16 Distribution DCF 1 Activity Activity Activity Release Release Constant Release Release 17 uCi/gm RemcEDE/Ci uCi/gm uCi/gm uCi/gm Ci Ci Ci/m3 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 40AAF-n 9T.9RE-07 1 3.22E-07 6.43E-06 19 1-132 0.38 3.81E+02 4.40E-03 5.40E-03 1.08E-01 2.96E+01 5.93E+02 6.97E-04 1.39E-02 8.37E-05 2.17E-08 4.35E-07 20 1-133 0.4 5.85E+03 7.11E-02 8.73E-02 1.75E+00 3.12E+01 6.24E+02 7.34E-04 1.47E-02 9.26E-06 2.07E-07 4.14E-06 21 1-134 0.53 1.31E+02 2.11E-03 2.59E-03 5.18E-02 4.13E+01 8.26E+02 9.72E-04 1.94E-02 2.20E-04 1.16E-08 2.31E-07 22 1-135 0.49 1.23E+03 1.83E-02 2.25E-02 4.50E-01 3.82E+01 7.64E+02 8.99E-04 1.80E-02 2.91E-05 8.06E-08 1.61E-06 23 Totals 1.63E-01 2.OOE-01 4.OOE+00 ______Totals 6.42E-07 1 .28E-05 24 non-spiked' spiked' 25 NEDO- NEDO- NEDO- -________I 26 21143-13 21143-13 21143-13 Case 1 Case2 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 Ci/m3 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 Activity Activity 33 Kr-85 0.000064 4.75E-04 4.75E-04 1.12E-08 1.12E-08 Release elease 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% 2.70E-08l 5.41 E-071 1.07E-08 4.69E-03 9.38E-02 36 Kr-89 0.218 1.62E+00 I1.62E+00 3.81E-05 3.81E-05 Cs-135 17.4506% l .06E-07 2.13E-06l 9.55E-15 1.66E-08 3.31E-07 37 Xe-,SM u.0uuuO23 3.88E-4 3.ooE-04 9.;3E-09 9.i3E-09 Cs-i36 0.0120%UO 7.32E-1 1 1.46E-09 6.10E-07 7.26E-04 1.45E-02l 381 Xe-133M I 0.000782 5.81E-03 5.81E-03 1.37E-07 1.37E-07 CS-137 40.17% 2.45E-07 4.90E-06 7.28E-10 2.91E-03 5.81E-02 39 Xe-133 l 0.0219 1.63E-01 1.63E-01 l3.82E-06 3.82E-06 Cs-138 0.0102% 6.22E-11l 1.24E-09 3.59E-04 3.63E-01 7.26E+00 40 Xe-135M 0.0641 4.76E-01 4.76E-01 1.12E-05 1.12E-05 Totals 62.08% 3.79E-07 7.58E-06l 41 Xe-135 0.0592 4.40E-01 4 -1 03E-05 1 .03E-05 _ Balance is stable Cs-133 1428 Xe-137 0.2881 2.14E+00 2.14E+00 5.03E-05 5.03E-05 i 43 Xe-138 l 0.218l 1.62E+00 16E0l3.81 E-05 l3.81 E-05 l 441 Calculation DRE02-0035, Rev. 4 Attachment A - Dose Calculation Page Al of Al 2

A B C I D E F G H I l J K L M 45 Curies Released Case I 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 7.65E-02 2.63E-02 3.28E-03 1.53E+00 5.25E-01 6.55E-02 49 1-132 2.96E+01 5.93E+02 3.81E+02 5.03E-03 1.72E-03 2.15E-04 1.01E-01 3.45E-02 4.31 E-03 50 1-133 3.12E+01 6.24E+02 5.85E+03 8.12E-02 2.79E-02 3.48E-03 1.62E+00 5.57E-01 6.95E-02 51 1-134 4.13E+01 8.26E+02 1.31E+02 2.41 E-03 8.27E-04 1.03E-04 4.82E-02 1.65E-02 2.06E-03 52 1-135 3.82E+01 7.64E+02 1.23E+03 2.09E-02 7.18E-03 8.96E-04 4.18E-01 1.44E-01 1.79E-02 54 Cs-134 4.69E-03 9.38E-02 4.63E+04 9.66E-05 3.31 E-05 4.14E-06 1.93E-03 6.63E-04 8.27E-05 55 Cs-135 1.66E-08 3.31 E-07 4.55E+03 3.36E-11 1.15E-11 1.44E-12 6.71E-10 2.30E-10 2.87E-11 56 Cs-136 7.26E-04 1.45E-02 7.33E+03 2.37E-06 8.13E-07 1.01E-07 4.74E-05 1.63E-05 2.03E-06 57 CS-137 2.91 E-03 5.81 E-02 3.19E+04 4.13E-05 1.42E-05 1.77E-06 8.26E-04 2.84E-04 3.54E-05 58 Cs-138 3.63E-01 7.26E+00 1.01 E+02 1.64E-05 5.63E-06 7.02E-07 3.28E-04 1.13E-04 1.40E-05 59 Sub-total (rem CEDE) 1.86E-01 6.39E-02 7.98E-03 3.72E+00 1.28E+00 1.60E-01 60 1 61 Curies Released Case I Dose (rem EDE) Case 2 Dose (rem EDE) 62 to the Environment _ (External) I l (External) I w6 isotope Case i Case 2 UCF- CR EAB LPZ CR EAB LPZ 64 1-131 5.22E+00 1.04E+02 6.73E-02 1.76E-05 1.55E-04 1.93E-05 3.51E-04 3.OE-03 3.87E-04 65 1-132 2.96E+01 5.93E+02 4.14E-01 6.13E-04 5.41 E-03 6.75E-04 1.23E-02 1.08E-01 1.35E-02 66 1-133 3.12E+01 6.24E+02 1.09E-01 1.69E-04 1.49E-03 1.86E-04 3.39E-03 2.99E-02 3.73E-03 67 1-134 4.13E+01 8.26E+02 4.81E-01 9.92E-04 8.75E-03 1.09E-03 1.98E-02 1.75E-01 2.18E-02 68 1-135 3.82E+01 7.64E+02 2.95E-01 5.63E-04 4.97E-03 6.20E-04 1.13E-02 9.93E-02 1.24E-02 69_ II 70 Cs-1 34 4.69E-03 9.38E-02 2.80E-01 6.55E-08 5.78E-07 7.22E-08 1.31 E-06 1.16E-05 1.44E-06 _ j 71 Cs-135 1.66E-08 3.31 E-07 2.09E-06 1.73E-18 1.52E-17 1.90E-18 3.45E-17 3.05E-16 3.80E-17 _____

72 Cs-136 7.26E-04 1.45E-02 3.92E-01 i.42E-08 1.25E-07 1.57E-08 2.84E-07 2.51E-06 3.13E-07 1 __ I 73 CS-137 2.91 E-03 5.81 E-02 2.86E-05 4.15E-12 3.66E-11 4.57E-12 8.30E-11 7.33E-10 9.15E-11 l ___

74 Cs-138 3.63E-01 7.26E+00 4.48E-01 8.11 E-06 7.16E-05 8.94E-06 1.62E-04 1.43E-03 1.79E-04 l 75 _ I 76 Sub-total (rem EDE) 2.36E-03 2.OBE-02 2.60E-03 4.72E-02 4.17E-01 5.20E-02 _

77 Iodine and Cesium Total (rem TEDE) 1.89E-01 8.48E-02 1.06E-02 3.77E+00 1.70E+00 2.12E-01 Calculation DRE02-0035, Rev. 4 Attachment A - Dose Calculation Page A2 of Al 2

A B C l D E F G H I J K L M 78 Curies Released Case 1 Dose (rem EDE) Case 2 Dose (rem EDE) 79 to the Environment (External) (External) 80 Case I Case 2 DCF2 CR EAB LPZ CR EAB LPZ 81 Kr-83M 6.95E-02 6.95E-02 5.55E-06 1.92E-11 1.70E-10 2.12E-11 1.92E-11 1.70E-10 2.12E-11 82 Kr-85M 1.22E-01 1.22E-01 2.77E-02 1.68E-07 1.48E-06 1.85E-07 1.68E-07 1.48E-06 1.85E-07 83 Kr-85 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 2.55E-05 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 6.47E-05 8.07E-06 7.33E-06 6.47E-05 8.07E-06 86 Kr-89 1.62E+00 I .62E+ 0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+OO O.OOE+00 O.OOE+00 87 Xe-131M 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 5.81 E-03 5.81 E-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 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 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-135 4.40E-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 2.14E+00 2.14E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 93 Xe-138 1.62E+00 1.62E+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 2.69E-04 3.35E-05 951 I I 9 _overai_ T_ ai irem TEDEjI _ .89E_1 8.50E-02 1.06E'02 3.77E+00 1.70E+00 2.12E-01 97 1 1 _ _ I _ __ _

98 1 Dose Conversion Factor (rem/Curie) from Federal Guidance Report (FGR) 11 per Reg. Guide 1.183 I 99 3 2Dose Conversion Factor (rem-m /Curie-second) from FGR 12 per Reg. Guide 1.1831l _

100 3From 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 Ci conversion formula for a 0.1 Cl/sec 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 3.89E-02 Control Room Geometry Factor per Reg. Guide 1.183, Regulatory Position 4.2.7 l 105 3.02E+_1 EAB a, (meters) for F stability, (taken from PAVAN runs in Ca.c. DRE04-0030, Rev. 1) 108 2.420E+02 LPZ a, (meters) for F stability, (taken from PAVAN runs inCalc. DRE04-0030, Rev. 1) _ _ _

107 1.OOE+00 Wind Speed (m/s) 108 4.40E-04 WiQ (seconds/rn3 ) 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 methodologyi 109 5.50E-05 X/Q (seconds/m 3) at Low Population Zone 2 based on RG 1.5 methodology I III 11t1 I IIIIIII 111 Equivalent CR X/Q, based on (Curies Released)x(Equiv. X/Q)x(Breathing Rate)x(Dose Conversion Factor) = CEDE Dose _

1121

_ Cae l cas I(rem7 lDose i 13 isotope 1 Activity FGR ii I CEDE) 1141 I Release DCF1 (Inhalation) Equivalent X/Q I_______

115 ____ Cil Rem/Ci CR sec/in 116 1-131 5.22E+00 3.29E+04 7.65E-02 1.28E-03 117 1-132 2.96E+01 3.81E+02 5.03E-03 1.28E-03 118 1-133 3.12E+01 5.85E+03 8.12E-02 1.28E-03 119 1-134 4.13E+01 1.31E+02 ,2.41E-03 1.28E-03

,120, 1-135 3.82E+01 1.23E+03 I2.09E-02 I 1.28E-03l Calculation DRE02-0035, Rev. 4 Attachment A - Dose Calculation Page A3 of Al 2

A B C D E F G 2Dresden 2&3 MSLB Case 1 Reactor Coolant at maximum value (D 2

3 =(A9A10V35.3 Volume of cloud (cubic meters) 4 =A7453.59 Case 2: Reactor Coolant at maximum value pe Mass of water in reactor coolant r__

5 =(A312/PI())(1/3j seconds for cloud to pass over C 6 81000 Volume of Control Room Enve _

7 140000 Mass of Liquid Water Released (11 8 0.4 Flashing Fraction 9 =ArA8 Mass of Steam in the Cloud (lb) 3 10 26.799 V (ft /b based on 14.7 psi and 12Reactor coolant iodine dis _______________

13 14 Normalized Case 1 15 Isotoe Case 2 Case 1 Activity FGR 11 1-131DE Normalized Normalized AdivtY 16 Distribution DCF' Activity Activity Release 17 uCL/gm RemCEDE/Ci uCVgm uCVgm uCVgm Ci 18 1-131 0.067 32900 =C18-B18/C$18 =D18-0.2/D$23 =E18-20 =EI-AS4-SCS18/C18B1000000 19 1-132 0.38 381 =C19 B19/C$18 =D19-0.2/DS23 =E19 20 20 =E19S$AS4-SC$18/C19/1000000 1-133 0.4 5846 =C2O0B2O/C$18 =D20-0.2/DS23 =E20-20 =E20-SA$4'$C$18BC2011000000 21 1-134 0.53 131 =C21*B21/C$18 =D21*0.2/D23 =E21-20 =E21*SAS4-$CS18/C21/1000000 22 1-135 0.49 1230 =C22-B22/C$18 =D220.2DS$23 =E22*20 23 =E22*$A$4-SCS18/C22/1000000 Totals =SUM(D18:D22) =SUM(E18:E22) =SUM(F18:F22) 24 I *nnnen__r.- *^Fkcd.

25 NEDO- NEDO- NEDO- --- r--- r 26 21143-13 21143-13 21143-13 Case 1 Case 2 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 CVm3 CVm3 31 Kr-83M 0.00936 =$B31*5.53-0.45 SB315.53-0.4 =C31/SAS3 =D31/SAS3 32 Kr-85M 0.0164 =SB325.53-0.45 =SB32- 3-0.45 =C32/SAS3 =D32/$A$3 33 Kr-85 0.000064 =$B33-5.53 0.45 =SB33-5.53-0.45 =C33/SA$3 =D33/$A$3 34 Kr-87 0.0511 =$B34-5.53-0.45 =SB34-5.53-0.45 =C34/SA$3 =D34/$A$3 35 Kr-88 0.0524 =SB355.53-0.45 =$B355.53-0.45 =C35/SA$3 =D35/$AS3 Cs-134 36 Kr-89 0.218 =S836-5.53-045 =$B36-5.53-0.45 =C36/$AS3 =D36/SAS3 Cs-135 37 Xe-131 M 0.0000523 =SB37-5.53-04S =$B37-5.53-0.45 =C37/$A$3 =D37/$A$3 Cs-138 38 Xe-133M 0.000782 =$B385.5*3-0.45 =SB385.53-0.45 =C38/$A$3 =D38ISA$3 39 Xe-133 0.0219 CS-137

=$B39-5.53-0.45 =$B395.5-3-0.45 =C391SA$3 =D39/SAS3 40 Xe-135M 0.0641 Cs-138

=$B40-5.5*3-0.45 =$B40-5.53-0.45 =C40/$A$3 =D40/SAS3 41 Xe-135 0.0592 Totals

=SB41*5.53-0.45 =SB41*5.53-0.45 =C41/$AS3 D41/SA$3 42 Xe-137 0.288 =$B42-5.53-0.45 =SB42-553-0.45 =C42/$AS3 =D42/SAS3 43 Xe-138 0.218 =$B435.53-0.45 =$B43-5.53-0.45 =C43/SA$3 =D43/$A$3 44 45 Curies Released 46 Case I Dose (rem CEDE) to theEnvironment (Inhalation)

Isotooe case 1 Case 2 DCF' CR FAR

G1S,. Case 12Case 1:,Us - l.-

=1 =(e46'$E4eiA$1u3IAs1UU 49 1-132 =G19 =H19 381 =1 50 1-133 =G20 1=H20 5846 =1 51 1-134 =G21 =H21 131 =121SE51-SAS103$A$5 52 1-135 =G22 =H22 1230 1=122-$E52-$A$1031$A$5 54 Cs-134 =L35 =M35 =(370000000000010.0000000125 J=M36 t=.(3700000000000r'0.00000000123

=1

____J=M37 1=(3700000000000)'0.00000000198

____I=M38 1=(3700000000000r*0.00000000863 I 58 Cs-1 38 J=M39 I=(3700000000000)'0.0000000000274 -

Calculation DRE02-0035, Rev. 4 Attachment A - Dose Calculation PageM4 of A12

D E F G

-4 4 591 A Sub-total (rem CEDE) I l ~ l Curies Released Case 1 Dose (rem EDE) 62 to the Ervironment (External) 63 Isotope 2 Case 1 Case 2 DCF CR EAB 64 1-131 =C48 =D48 0.06734 =118-SE64'SA$104-SA$5 =C64'$E64-SA$108 65 1-132 =C49 =D49 0.4144 =119-E65$A$104-SAS5 =C65-$E65-$AS108 66 1-133 =C50 =D50 0.10878 =120-5E66-SA$104-SA$5 =C66-$E66-SAS108 67 1-134 =C51 =051 0.481 =121*$E67$A$10.41$A5 =C67'$E67'$AS108 68 1-135 =C52 =D52 0.29526 =i22*SE68'$A$104 SA$5 =C687$E687$AS108 691 70 Cs-134 =L35 =M35 =(3700000000000 O.0000000000000757 =($C70/$A$3r$E701$AS104-SAS5 =C70 SE70-$A$108 71 Cs-135 =L36 =M36 =(3700000000000r5.65E-19 =($C71/$A$3r$E71*SAS104-$A$5 =C71SE71*$A$108 72 Cs-1136__ =L37 =M37 =370DOO055500000106 = EC72/$A$3SE72SAS104-SAS5 =C72'E72-SAS108 73 CS- 137 =L38 =M38 =(3700000.00200677674E-18 =(EC73/$A$3r1E734AS5104-$AS5 =C73-SE73-SAS108 74 Cs-138 =L39 =M39 =(3700000000.00rO.0440300121 =(EC74$A$3rE74$A$ 104-SAS5 =C74-SE74-SA$108 76 Sub-total (rem EDE =SUM(F64AF74) 5=SUM(E64:A710 77 and Cesium Total 0odine4 =SUM(F59+F76) =SUM(G59 78 Curies FReleased Case I Dose (rem EDE) 791 to the Environrnet 2(Extemnal) 8Cae1 Cas e 2 DCF CR EAB 81 Kr43M =C31 =D31 0 00000555 =E31*SE81*SA$104-SA$5 =C81*SE81*$A$108 82 Kr85M=C3 =3 0027676 =E327SE82-$A$104*$AS5 =C82-SE8278A$108 b3 Kr-f5 =C33 =D33 0.0054403 =E33-SE83S$AS104-SAS5 =C83-E8f$AS108 841 Kr-87 =C34 =D34 015244 -E34-SE84-SAS104*SAS5 =C84-SE84*$A$108 85 Kr-88 =C35 =035 0.3774 =E35-SE85'SA$104'SA$5 =C85-$E859SA$108 861 Kr-89 =C36 =D36 -0 -E36 SE86-SAS1 04-SAS5 l=C86'SE86-SAS10O8 871 Xe-11311M =C37 =D37 0.0014393 =E37-SE87-SAS104-SAS5 j l=C87-SE87-SAS108 881 Xe 1133M =C38 =D38 0.005069 =E38-SE88-SAS104-SAS5 l=C88-SE88-SAS108 891 Xe-1133 =C39 7 =D39 0.005772 ==E39-SE89-SAS104-SAS5 X 7 l=C89-SE89-SAS108 90 Xe-135M =C40 =D40 0.07548 =E40-SE90-SAS104-SA$5 =C90-$E90-$A$108 91 Xe-135 =C41 =D41 0.04403 =E41'SE91*SA$104-$A$5 =C91 $E91*SAS108 921 Xe-1_37 =C42 =D42 =E42-SE925$A$104-SAS5 =C92-SE92-$A$108 931 Xe-1138 =C43 =D43 0.21349 =E43'$E93$A$104'SA$5 =C93'SE93-SA$108 94 Noble Gas Sub-total (rem EDE) =SUM(F81:F93) =SUM(G81:G93) 95 96 Overall Total (rem TEDE_ --SUM(F77+F94) =SUM(G77+G94)

D_

98 Dose Conversion Factor (rem-Curie) I 99 IDose Conversion Factor (re"'~M3ur 10t From NEDO-21143-1, 'Radiological 1011 with its Table 3-1 (SLBA Source Adi 10_ offgas release rateand 5.5second _

10.000347 Breathing rate (m'/second) per Regul 104 =($AS6^0.338y1173 Control Room Geometry Factor per R 10 30.2 EAB0 (moetrs) for F stabiliy, (taken in rI47 I P7 f n t.~.3 f£ r *h ft.& I 1:07 1Windl Speed (m/vs) 3 106 =0.0133/A$105/A$107 WO (seconds/rn) at EA Boundary -

109 =0.0133/A$106/A$107 XtQ (cnds/rm) at Low Population; 11Equrvalent CR X/,based 112 Case f Case f 113 Isotope Actv FGR 11 Dose (rem CEDE) EqulvabntXIQ 11 1R elease CFIn a ti nE quivalent X IQ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Calculation DRE02-0035. Rev. 4 Attachment A - Dose Calculation Page AS of A12

A B C D E F G 115 Ci RemnvC CR sec/mo 116 1-131 5.2234689158353 32900 0.0765256284668924 =D016( B116'C116-$A$103) 117 1-132 29.6256445972748 381 0.0050262579909434 =D117/(BI1r7CI 17*$A$103) 116 1-133 31.184889049763 5846 0.081181114007613 =D 18/(B118C1 18'$A$103) 119 1-134 41.3199779909359 131 0.0024103680916646 =D119/(B119Cl91AS103) 120 1-135 38.2014890859596 1230 0.0209236475420751 =D1201(B120-C120-$AS103)

Calculation DRE0240035, Rev. 4 Attachment A - Dose Calculation Page A6 of A12

H J K L M 11-131 of 0.2uCVg) permitted for continued full power operation 2

3 mitted (DE 1-131 of 4.0 uCVg) corresponding to an assumed pre-socident spike 4

5 6

7 8

9 10 11 12 Case I Case 2 13 Release Release 14 Case 2 Cloud Cloud Case 1 Case 2 15 Activity Concentration Concentration Decay Activity Activity 16 Release Constant Release Release 17 Ci Cim3 Crm3 1/seconds moles moles 18 =G18'20 =G18/$AS3 =H18/SA$3 LN(2y(8.048f400) =G18-37000000000/$K1816.023E+23 =H18-37000000000/$K18/6.023E+23 19 =G19-20 =G19/SA$3 =H19t$AS3 =LN(2y(233600) =G19-37000000000/$K19/6.023E+23 =H19-37000G00000/SK19/6.023E+23 20 =G20-20 =G20/$A$3 =H20/SA$3 =LN(2y(20.8-3600) =G20*37000000000/$K20/6.023E+23 =H20-37000000000/SK20/6.023E+23 21 =G21-20 =G21/SAS3 =H21/SAS3 =LN(2y(52.6-60) =G21-37000000000/$K21/6.023E+23 =H2`1*37000000000/SK21/6.023E+23 22 =G2220 =G22/$A$3 =H22/SAS3 =LN(2y(6.61*3600) =G22'37000000000/$K22/6.023E+23 =H22-37000000000/SK22/6.023E+23 23 Totals =SUM(L18:L22) =SUM(M18:M22) 25 26 27 28 29 30 31 Case I 2 Case Case 2 32 Activity AciiyDcyActivity Activity 33 Release Release Constant Release Release 34 1 Molar Frac. moles moles 1/seconds curies curies 3510.044317152955112 =0.95SH35LS23 =0.95 $H35-MS23 =LN(2y(2.062'86400-365.25) =135-6 023E+23-SK35/370D0000000 =J35-6.023E+23-SK35/37000000000 36 0.174506296053598 =0.95SH36LS23 =0.95 H36-MS23 =LN(2y(2300000'86400-365.25) =136-6.023E+23SK36/37000000000 =J36-6.023E+23-SK36/37000000000 37 0.000119942189253291 =0.95S*H37LS23 =0.95SSH37 M$23 =LN(2V(13.16-86400) =1376.023E+23-SK37/37000000000 =J37-6.023E+23-$K37137000000000 38 0.401736793048373 =0.95 SH38L$23 =0.95 SH38-M$23 =LN(2Y(30A1r86400*365.25) =138-6.023E+23-$K38/37000000000 =J38-6.023E+23-SK38/37000000000 39 0.000101901239392202 =0.95SH39LS23 =0.95S-H39-MS23 =LN(2y(32.2'60) =1396.023E+23-SK39/37000000000 =J39-6.023E+23-$K39/37000000000 40 =SUM(H35H39) =SUM(135:139) =SUM(J35:J39) 41 Balance isstable Cs-133 4 _ I 44 451 o~r1*\

C; 46 47 LPZ CR EAB LPZ

.AD ZR -

o...nn

  • M'* ~ I.

I-I. . . .D~l,.

U... -. ~ zl Vcoa- I I C49 $E49-SAS103-SAS109 49 1-l =J19^SE49*SAS103'SAS5 =D49-SE49i$A$103 $AS109 So 1= =DO5SE50 $AS103'$A$108 1=1 t=D51 IE5II$A$1031A18

-2 = =D52'SE52*SAS03'SASIG8 I=D52'$E52S$ASI03'SASI09 53 I

- 8 =D54-SES4-SAS103'SA5109

-I

-I L l Calculation DRE02-0035, Rev. 4 Attachment A - Dose Calculation Page A7 of Al 2

59SUM(H48:H8 =SU-M 148:.5-8) SUM J4$:J8 -SUM(K48:K58) 60 61 Case 2 Dose (rem EDE) 62 (External) 63 LPZ CR EAB LPZ 64 =C641$E64'$ASIO9 =Jl8*$E64I$AS104*A$5 =D64'$E64'$A$108 =D64'$E 4i$A$109 65 i=C65*$E65S$A$109 =J191$E65*$A$1048$AS5 =65*$E65*$AS108 =D65*$E65S$A$109 66 I=C66i$E66&SA$109 =J201$E661$A$104*$A$5 =D66*$E66'$A$108 =D66'$E66*$A$109 67 =C67*$E67*$A$109 =J211$E67S$A$104'$AS5 =D67'$E67r$A$108 =D67$E67$A$109 68 =C68*$E68'$A$109 =J221$E68S$A$1048$A$5 =D68*$E68'$A$108 =D68*$E68$AS109 69 70 =C70*$E70*$AS109 =($D701$A$3r$E701$AS104*$A$5 =D70'$E70'$A$108 =D701$E70'$A$109 71 =C71PSE7IS$A$109 =($D71/$AS3r$E71*$ASI04S$A$5 =D71*$E71*SAS108 =D711$E711$A$109 72 =C721$E72*$AS109 =($D72/$AS3) 1E721$A$104S$A$5 =D72S$E72$A$108 =D72'$E72*$A$109 73 =C731$E73*$A$109 =(S0731$A$3)*$E731$AS104*$A$5 =D73'$E73S$A$108 =D731$E73*$A$109 74,=C74*$E74'$AS109 =(D74/$A$3) IE74I$A$1O4SA$5 =D74'$E74*$AS108 =D74*$E741$A$109 751 76.SUM(H64:H74) =SUM(164:174) =SUM(J64.J74) SUM(K64:K74) 77 =SUM H594H76) SUM 159+176) MDM(JS9.J76) -sum K59+K76) 78 Case 2 Dose (rem EDE) 79 (External) 64 =C814$E814IA$109 I=F314$E814SA$104'$A$5 =D81*$E81*SA$108 I=D841$E81SA$109 85 =C65'$E825$A$109 =F32*$E82$A$104'$A$5 =0825SE82SA$108 I=D82'$E825SA$109 86 ~ko

=C868E868AS10IMPiSSA141$ l=l83$E836SA$108 =D8361E836SA$109 87 =CS47$E87'$A$109 =F34*SE84rSA$104S$A$5 =D84SE847$A$108 =D847$EB471A$109 66 =C85*$E858$A$109 =F35$E85$A$104*$A$5 =D88'$E858SA$108 =D858SE85'SA$109 89 =C869$E869$A$109 =F3698E8691A$104'$A$5 =D869$E86$A$108 =D86*$E8691A$109 90 =C87*$E870$A$109 =F370$E9S7'A$04'$AS5 =D87$E87*$AS108 =D87*$E87OIA$109 91 .=C91'$E91 $A$109 =F41I$E91V$A$04S$A$5 =D915E911$A$108 =D91*SE91ISA$109 92 I=C921$E92r$A$109 =F42*$E921$A$104S$A$5 =092$E92S$A$108 =D928$E921$A$109 93 I=C93'$E93-$A$109 =F43*$E93*$A$104'$A$5 =D93*$E93S$AS108 =D93i$E93*$A$109 94 -SUM(H81:H93) =SUM I1:193) =SUM(J81:J93) SUM(K81:K93) 95 96=SUM(H77+H94) =SUM(177+194) =SUM(J77.J94) =SUM(K77+K94) 97 98 99 100 1011 102 1031 1041 1051 1106 110 113 114 Calculation DRE02-0035, Rev. 4 Attachment A - Dose Calculation Page A8 of A12

Calculation DRE02-0035, Rev. 4 Attachment A - Dose Calculation Page A9 of A12 A I B I C I D I E I F G I H I Il K L 1 Peach Bottom Beginning of Core Life (100 Effective Full Power Days) and End of Cycle (E C) Cesium I otope Quantities 2 (Used for G;eneral Cs Molar Fraction Determination for AST) 3 _ _ __ _ __ _ _Decay 4 100 EFPD EOC 100 EFPD EOC Constant 100 EFPD EOC S (grams) (grams) At. Mass (gm-moles) (gm-moles) Ilseconds Ci Ci 6 Cs-133 1.025E+05 1.678E+05 Cs-133 132.9054 7.712E+02 1.263E+03 0.OOOE+00 O.OOOE+0O O.OOOE+O0 7 Cs-134 1.031E+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 9.41OE+06 1.586E+07 10 Cs-136 2.37E-01 3.99E-01 6.1OE-07 2.352E+06 3.964E+06 1_1 Cs-138 2.01E-01 3.39E-01 3.59E-04 1.176E+09 1.982E+09 12 Total 2.665E+05 4.492E+05 1.976E+03 3.331 E+03 13 14 ANSI/ANS-18.1-1999 Relative Abundances in Reactor Water __ Molar Fraction 15 uCi/gram of moles/gram of ratio to Cs-133 39.0219% 37.9218%

16 Reactor Coolant Reactor Coolant Cs-137 Cs-134 3.8956% 4.43179%

17 Cs-134 3.OOE-05 1.04E+08 2.56E2 Cs- 135 1 6A 48% 17 4506%l 18 Cs-136 2.OOE-05 1.21E+06 2.99E-041 Cs-137 40.1755% 40.1737%

19 Cs-137 8.OOE-05 4.07E+09 1.OOE 4001 Cs-136 0.0120% 0.0120%

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

Calculation DRE02-0035, Rev. 4 Attachment A - Dose Calculation PageAlOof A12

A B C D E F G H 1 Peach Bot 2 (Used for 3

4 100 EFPD EOC 100 EFPD 5 (grams) (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 8 Cs-135 45020 78410 Cs-135 134.9059 333.7 9 Cs-137 108700 183200 Cs-137 136.9071 794 10 Cs-136 =H9*D18 11 Cs-138 =H9*D20 12 Total =SUM(B6:B9) =SUM(C6:C9) SUM(H6:H11) 13 14 ANSI/ANS-15 uCi/gram of moles/gram of ratio to 16 Reactor Coolant Reactor Coolant Cs-137 17 Cs-134 0.00003 =B17*37000/J7 =C17/C$19 1 i8Cs-I36 0.uu0002 =Bi8-37UUU/10 =C18/C$19 19 Cs-137 0.00008 =B19*37000/J9 =C19/C$19 120 Cs-138 0.01 =B20*37000/J11 I=C20/C$19 I Calculation DRE02-0035, Rev. 4 Attachment A - Dose Calculation Page All of Al12

T J K L 2

3 Decay 4 EOC Constant 100 EFPD EOC 5 (gm-moles) I/seconds Cl Cl 6 1263 0 =H6*$J6*6.023E+23/37000000000 =16*$J6*6.023E+23/37000000000 7 147.6 =LN(2)/(2.062*86400*365.25) =H7*$J7*6.023E+23/37000000000 =17*$J7*6.023E+23/37000000000 8 581.2 =LN(2)/(2300000*86400*365.25) =H8*$J8*6.023E+23/37000000000 =18*$J8*6.023E+23/37000000000 9 1338 =LN(2)/(30.17*86400*365.25) =H9*$J9*6.023E+23/37000000000 =19*$J9*6.023E+23/37000000000 10 =L1 0*37000000000/$J1 0/6.023E+23 =LN(2)/(13.16*86400) =K$9*$B$18/$B$19 =L$9*$B$18/$B$19 11 =L1 1*37000000000/$JI 1/6.023E+23 =LN(2)/(32.2*60) =K$9*$B$20/$B$19 =L$9*$B$20/$B$19 12 =SUM(16:111) 13 14 Molar Fraction 15 Cs-133 =H6/H$12 =16/1$12 16 Cs-134 =H7/H$12 =17/1$12 17 Cs-135 =H8/H$12 =18/1$12 to_l__I___ =H9/HC12 =s9/1$12 19 ICs-136 =HIO/H$12 =110/1$12 20 ICs-138 =Hll/H$12 =111/1$12 Calculation DRE02-0035, Rev. 4 Attachment A - Dose Calculation Page A12 of A12

CALCULATIONONO. DRIE02-0035, Attachment B f RE .NO. 4 PAGENO.B1 of BI Computer Disclosure Sheet Discipline Nuclear Client:: Exelon Corporation Date: January 2006 Project: Dresden Units 2&3 MSLB AST Job No.

Program(s) used Rev No. Rev Date Calculation Set No.: DRE02-0035, Rev. 4 Attachment A spreadsheet N/A N/A Status ( ] Prelim.

[X] Final

[ ] Void WGI Prequalification [ ] 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: January 2006 Run by: H. Rothstein Checked by: P. Reichert P. 1{I Separate cell-by-cell independent check by: A. Boatright Approved by: H. Rothstein ,

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. A separate cell-by-cell independent check was also performed.

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