ML060580587

From kanterella
Jump to navigation Jump to search
Calculation QDC-0000-N-1266, Revision 2, Re-Analysis of Main Steam Line Break Accident Using Alternative Source Terms.
ML060580587
Person / Time
Site: Quad Cities  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 QDC-0000-N-1266, Rev 2
Download: ML060580587 (30)
v • d • e


Text

ATTACHMENT 4 Calculation QDC-OOOO-N-1266, Revision 2, "Re-analysis of Main Steam Line Break (MSLEI) Accident Using Alternative Source Terms"

CC-AA-309-1001 Revision 2 ATTACUMSNr I Design Analysis Cever Sheet Design Analysis (Major Revision) I Last Page No. 18/Att,.Bl Analysis No.:' QDC-0000-N-1266 Revision: 2 4 Tite: I Re-analysis of Main Suam Une Break (MSLB) Accident Using Alternative Source Tears EC/ECR No.:4 356379 Revision: 6 o Statbon(s): Quad Cities Component(s): .

Unit No.: ' 1& 2 Discipline:. N Descrip. NW1 R01. R02 Coder/Keyword:" /AST, MSLB Safety/OA Class:" SR System Code: ".

Structure. "I CONTROLLED DOCUMENT REFERENCES" Document No.: Fromtro Document No.: FromrfO OOCG00O0-M-1408, RI Fro GENE-A22-00103-6401, RO Forn QDC-O000-N-1020. RI _ _ _ __ ___

Is this Design Analysis Sateguards Information? Yes 0 No 0 it yes. sn SY-AA-10i -106 Does this Design Analysis contain Unverified Yes i No ATifAye:

Assumnptions? 7' AVA This Design Analysis SUPERCEDES: ODC-QW N-1266. Rev. 3 InirIety.

Description of Revision (list affected pages for parlials):*

This revision corrects for the use of normalized values for activity releases for Iodine In column G on page Al and formula page A4 of the calculation spreadsheet" with resulting change:; In calcolated doses as provided In the Summary and Conclusions section. A separate celfty-cell independent check was also performed, as documented in Attachment B.

Preparer. Harold Rothstein {

Print Name Sign Name Date MethoR of Detailed Review Alternate Calculations (attached 0 Testing 0 Reiew: 21 fi3

'Reviewer:.' Paul Reichert g Print Name Sign Name Review Independent review 0 Peer review 0 Notes: 23 Ih 4,J 7; 4 PQ r;tf - c> VOC1 Ai.Co.c Cez External /f Approver:" __ _ _ _ _ _

________ f___

Print Name Sin Date Exelon Reviewer 2_ -_ /

is a Supplemental Revlew Required?2 YeElNO. Ifyes. e Aahmerif Approver: 2 _gu .fl;ck.*oP - t 1./e Print Name Sign Name Date

I CALCULATIONNO. QDC-0000-N-1266  : l REV. NO. 4 l PAGE NO. 2of18 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........................................................................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 ........................................... 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-A10]

B. Computer Disclosure Sheet [pages B1-B 1

I CALCULATIONNO. QDC-OOOO-N-1266 l REV. NO. 4 l PAGE NO. 3 of 18 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 10CFR100 and 10CFR50, General Design Criterion 19 requirements are:

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

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

The mass of coolant released during the MSLB is taken for this dose calculation as a bounding maximized value for all current Boiling Wlater Reactor (BWR) plants of 140,00C pounds of water, as provided in Standard Review Plan 15.6.4, Paragraph 111.2.a for a GESSAR-251 plant. This value bounds for dose calculation purposes the historic UFSAR values such as 55,000 pounds of steam and 45,000 pounds of water in UFSAR Section 15.6.4.5. This ensures that the discharge quantity and dose consequences are maximized, and that the releases should bound any other credible pipe break. Considering the release as all water maximizes the iodine (the primary dose contributor) release quantity compared to any actual release of steam, which would contain iodine quantities limited by the carryover fraction (typically 2%, as per Reference 10).

I CALCULATION NO. QDC-OOO0-N-1266 l REV. NO. 4 l PAGE NO. 4of18 2.0 METHODOLOGY AND ACCEPTANCE CRITERIA 2.1 General Description The radiological consequences resulting from a design basis MSLB accident to a person at the EAB; to a person at the LPZ; and to an operator in the Control Room following an MSLB accident were performed using a Microsoft EXCEL spreadsheet, provided as Attachment A.

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

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

2.3 Release Model Noble gas releases are those historically determined from the release fractions in Reference 2 and its Curie release formulation, corresponding to 100,000 uCi /sec off-gas emission after 30 minutes decay, per UFSAR Section 15.6.4.5, and for the Quad Cities Technical Specification value of 5.5 seconds MSIV closure time.

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

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

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

2.4 Dispersion Model 2.4.1 EAB and LPZ

I CALCULATION NO. QDC-0000-N-1266 l REV. NO. 4 l PAGE NO. 5 of18l EAB and LPZ X/Q's are determined using the methodology in R.G. 1.5 [Ref. 5], that is also cited as a basis for evaluation in the Quad Cities - UFSAR (e.g., Section 15.6.4.5). Specifically:

x 0.0133 Q .- yu where cy = 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.

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

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

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

DosecEDE (rem) = Release (Curies) * (sec/m3 )

  • Breathing Rate (m3/sec)
  • Inhalation DCF (remCEDE/Ci inhaled)

Q and Dose EDE (rem) = Release (Curies)

  • X (sec/M3 )
  • Submersion DCF (rem EDE - im3/ Ci - sec)

Q and finally, Dose TEDE (rem) = DoseCEDE (rem) + DoseEDE (rem)

CALCULATIONNO. QDC-OOOO-N-1266 REV.NO. 4 l PAGENO. 6of 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:

DoseCEDE (rem) = Plume Concentration (Ci/m3 )

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

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

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

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

I CALCULATIONNO. QDC-OOOO-N-1266 REV. NO. 4 l PAGE NO. 7 of 1 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 5.5 in the maximum time allowed by technical specifications. seconds was assumed in the analysis. This is the Technical Specification maximum allowed MSIV closure time of 5 seconds plus 0.5 seconds for instrument response.

4.2 The total mass of coolant released should be assumed to be that Conforms 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. QDC-OOOO-N-1266 l REV. NO. 4 l PAGE NO. 8ofl eamount inat passes tnrougn the valves prior to closure. I 4.3 All the radioactivity in the released coolant should be assumed to be 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 The subject values are used.

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

organic.

CALCULATIONNO. QDC-0000-N-1266 l REV. NO. 4 l PAGE NO. 9 of 18 3.0 ASSUMPTIONS 3.1 ActivityRelease 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.
  • 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.
  • External exposure doses are determined based on concentrations at the intake, exposures for the duration of plume traverse, and a geometry factor credit (Equation 1 of Ref. 6) based on the maximum control room volume of 184,000 cubic feet [Ref.

11].

CALCULATION NO. QDC-0000-N-1266 l REV. NO. 4 l 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 Activity Release The MSLB noble gas release fractions listed in the second column below are provided in Table 3-1 of Reference 2. Using the formula below in this Reference for a 100,000 uCi /sec off-gas emission after 30 minutes decay, per UFSAR Section 15.6.4.5, and the Quad Cities Technical Specification value of 5.5 seconds MSIV closure time, the Curie releases in the third column below are obtained: Curies Released = Release fraction x 5.5 x 3 x 0.45, where 0.45 is the offgas rate at the break, in Curies/second, corresponding to a 100,000 uCi

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

Noble Gas Curies Isotope Release Fraction Release Kr-83M 0.00936 6.95E-02 Kr-85M 0.0164 1.22E-01 Kr-85 0.000064 4.75E-04 Kr-87 0.0511 3.79E-01 Kr-88 0.0524 3.89E-01 Kr-89 0.218 1.62E+00 Xe-131 M 0.0000523 3.88E-04 Xe-133M 0.000782 5.81 E-03 Xe-133 0.0219 1.63E-01 Xe-1 35M 0.0641 4.76E-01 Xe-135 0.0592 4.40E-01 Xe-137 0.288 2.14E+00 Xe-138 0.218 1.62E+00

CALCULATION NO. QDC-0000-N-1266 l REV. NO. 4 l PAGE NO. 11 of 18 l The relative mix of iodine isotopes in the reactor coolant at the onset of the accident, based on the Quad Cities UFSAR [Ref. 8] Section 15.6.4, is given below.

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

4.3 Control Room Data

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

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

  • No Emergency Filtration Credit taken.

4.4 EAB and LPZ Data

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

CALCULATION NO. QDC-0000-N-1266 l REV. NO. 4 l PAGE NO. 12 of 18

5.0 REFERENCES

1. Deleted.
2. NEDO-21143-1, "Radiological Accident Evaluation - The CONAC03 Code", General Electric Company, December, 1981.
3. Federal Guidance Report No. 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion",

1988.

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

CALCULATION NO. QDC-0000-N-1266 NO. 4 PAGENO. 13 of 18 IREV.

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 11 50.5 BTU/lb and a liquid enthalpy of 180.17 BTU/lb are used (these enthalpies are taken from the ASME Steam Tables).

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

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

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

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

= (140,000 lb)(453.59 glib)

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

= 56,000 lb

I CALCULATION NO. QDC-0000-N-1266 l REV. NO. 4 l 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 IF, vg = 26.799 Wlb)ft3 were calculated as follows:

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

= 1,500,744 ft3

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

= 42,514 m3 The volume of a hemisphere is tr d3 /12. Thus, the diameter of the hemispherical cloud is 54.6 meters.

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

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

X 0.0133 Q Uyu where Cy, = horizontal standard deviation of the plume (meters) u = wind velocity (meters/second)

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

I CALCULATION NO. QDC-0000-N-1266 l REV. NO. 4 l PAGE NO. 15 of 18 6.3 Release Isotopics and Quantification The iodine, noble gas and cesium activity releases are given in Attachment A, which also determines resulting doses.

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

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

Cesium releases are based on the fact that a single cesium atom will accompany 95% of the released iodine atoms. For Cs-1 33, Cs-1 34, Cs-1 35, and Cs-1 37, isotopic data (in Curies per Megawatt, and therefore generally applicable to similar BWRs such as Quad Cities

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

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

CALCULATIONNO. QDC-0000-N-1266 REV. NO. 4 PAGE NO. 16 of 18l 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 CALCULATIONNO. QDC-0000-N-1266 REV. NO. 4 l PAGE NO. 17 of 18 l 7.0

SUMMARY

AND CONCLUSIONS Accident doses from a design basis IMSLB 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 pCi) limit of 4.0 pCi)

Dose (rem TEDE) Dose (rem TEDE)

LIMITS CR: '5.0; EAB&LPZ: 2.5 CR: 5.0; EAB&LPZ: 25 EAB 0.167 3.32 LPZ 0.0168 0.335 CR 0.189 3.79

ICALCULATION NO. QDC-0000-N-1266 I REV. NO. 4 I iPAGE NO- 18 onff 18 DESIGN I1 8.0OWNER'S CALCULATION ACCEPTANCE I CHECKLIST FOR EXTERNAL 4 REVIEW NO.DC-0000-N-1266 REV.N(J I PAOENOAR lit 8.0 OWNER'S ACCEPTANCE RIEVIEW CHECKLIST FOR EXTERNAL DESIGN ANALYSIS DESIGN ANALYSIS NO. QDC-0000-N-1266 REV: 4 Yes No N/A

1. Do assumptions have sufficient rationale? El El
2. Are assumptions compatible with the way the plant is operated and with the licensing basis? El El
3. Do the design inputs have sufficient rationale? El 4.

5.

Are design inputs correct and reasonable?

Are design inputs compatible with the way the plant is operated and with the V

0'3/ El licensing basis? El 19/

E2/

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? El El
8. Do the results and conclusions satisfy the purpose and objective of the Design Analysis? El El
9. Are the results and conclusions compatible with the way the plant is operated and with the licensing basis? E2/ El
10. Does the Design Analysis include the applicable design basis documentation?

Have any limitations on the use of the results been identified and transmitted 11 to the appropriate organizations? 0o El El/

12. Are there any unverified assumptions? El,,

El

13. Do all unverified assumptions have a tracking and closure mechanism in place? El Have all affected design analyses been documented on the Affected
14. Documents List (ADL) for the associated Configuration Change? 19/ E E 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, OR/' 0 E 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 DRFs) been reviewed when necessary? ff E El EXELON REVIEWER:

Print/Si 1 DATE:

A&>/

A I B I C D E F G H I I K L M 1 Quad Cities 1&2 MSLB Dose Spreadsheet Case Reactor Coolant at maximum value (DE-131of.2uC/g)permited 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 cloud to pass over CR intake for wind speed of 1 m/second 6 184000 Volume of Control Room Envelope (cubic feet) - maximum used for conservatism 7 140,000 Mass of Liquid Water Released (lb) _

8 40% Flashing Fraction I 9 56000 Mass of Steam in the Cloud (lb) 10 26.799 Vg (ft3/lb) (based on 14.7 psi and 212F) 11 Reactor coolant Iodine distribution is assumed to be a I gm/cc specific Igravity 12 Case 1 Case 2 131 Release Release 14 Normalized Case 1 Case 2 Case 1 Case 2 Cloud Cloud Case 1 Case 2 15 Isotope Activity FGR 11 1-131 DE Normalized Normalized Activity Activity Concentration oncentratio Decay Activity Activity 16 Distribution DCF 1 Activity Activity Release Release Constant Release Release 17 uCi/gm RemcEDEIci uCi/gm uCi/gm uCi/gm Cl 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 2.46E-03 9.98E-07 3-22E-n7 fi43F-0r 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-26 21143-13 21143-13 21143-13 Case I 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 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 Release Constant Release Release 34 Kr-87 0.0511 3.79E-01 3.79E-01 8.92E-06 8.92E-06 MolarFrac. moles moles 1/seconds cures curies 35 Kr-88 0.0524 3.89E-01 3.89E-01 9.15E-06 9.15E-06 Cs-I134 4.4317% 2.70E-08l 5.41E-07l 1.07E-08 l4.69E-03l 9.38E-02l 36 Kr -89. 0.21 8 1.62E+00 1.62E+00 3.81 E-05 3.81 E-05 Cs-135 17.4506% 1.06E-07 l2.1 3E-06l 9.55E-1 5 l1 .66E-08 l3.31 E-07l 3 IeV-101MV v.vvU0-1 O.O8O8-+ O.Oo8-uO4 V. WE-0u Y.1-Ic-UY t CS-1J3 I U.UZU0/o 1 i.3E-1 1.4bh-Ug 6.1Ut-077 7.26E-04 1.45E-021 38l Xe-133M 0.000782 5.81E-03 5.81E-03 1.37E-07 1.37E-07 CS-137 40.17% f 2.45E-07 4.90E-06 7.28E-10 - 2.91E-03 5.81E-02 39 Xe-133 l 0.0219 1.63E-01 l 1.63E-01 3.82E-06 3.82E-06 Cs-138 0.0102% l 6.22E-11 1.24E-09 3.59E-04 l 3.63E-01 7.26E+00 40t Xe-135M 0.0641 4.76E0 4.76E-1 1.12E-05 1.12E-05 Totals 62.08% 3.79E-07 7.58E-06 1 1 41 Xe-i 35 0.0592 4.40E-01 4.40E-01 1.03E-05 1.03E-05 Balance is stable Cs-133 42t Xe-137 I 0.2881 2.14E+00 1 2.14E+00 5.03E-05 5.03E-05 1 1 1 1 1 1 1 43 l Xe-138 l 0.2181 1.62E+00 l 1.62E+00 3.81E-05 3.81E-05 l I44 Calculation QDC-0000-N-1266, Rev. 4 Attachment A - Dose Calculation Page Al of Al 0

A B l jC I D E F G H I l J K L M 45 Curies Released Case 1 Dose (rem CEDE) Case 2 Dose (rem CEDE) 46 to the Environment l (Inhalation) (Inhalation) l 47 Isotope Case 1 Case 2 DCF 1 CR EAB LPZ CR EAB LPZ 48 1-131 5.22E+00 1.04E+02 3.29E+04 7.65E-02 5.15E-02 5.18E-03 1.53E+00 1.03E+00 1.04E-01 49 1-132 2.96E+01 5.93E+02 3.81E+02 5.03E-03 3.38E-03 3.40E-04 1.01E-01 6.77E-02 6.81 E-03 50 1-133 3.12E+01 6.24E+02 5.85E+03 8.12E-02 5.46E-02 5.50E-03 1.62E+00 1.09E+00 1.1 OE-01 51 1-134 4.13E+01 8.26E+02 1.31 E+02 2.41 E-03 1.62E-03 1.63E-04 4.82E-02 3.24E-02 3.27E-03 52 1-135 3.82E+01 7.64E+02 1.23E+03 2.09E-02 1.41 E-02 1.42E-03 4.18E-01 2.82E-01 2.83E-02 53_

54 Cs-134 4.69E-03 9.38E-02 4.63E+04 9.66E-05 6.50E-05 6.54E-06 1.93E-03 1.30E-03 1.31E-04 55 Cs-135 1.66E-08 3.31 E-07 4.55E+03 3.36E-11 2.26E-11 2.27E-12 6.71E-10 4.52E-10 4.55E-11 56 Cs-136 7.26E-04 1.45E-02 7.33E+03 2.37E-06 1.59E-06 1.61 E-07 4.74E-05 3.19E-05 3.21 E-06 57 CS-137 2.91 E-03 5.81 E-02 3.19E+04 4.13E-05 2.78E-05 2.80E-06 8.26E-04 5.56E-04 5.60E-05 58 Cs-138 3.63E-01 7.26E+00 1.01E+02 1.64E-05 1.1OE-05 1.11 E-06 3.28E-04 2.21 E-04 2.22E-05 59 Sub-total (rem CEDE) 1.86E-01 1.25E-01 1.26E-02 3.72E+00 2.51E+OO 2.52E-01 60 _1 61 Cunes Released 62 63 isotope to the Environment Case 1 Case 2 DCF CR l (External)

EAB

{

Case 1 Dose (rem DE)

LPZ CR Case 2 Dose (rem EDE)

I (External) I EAB LPZ 64 1-131 5.22E+00 1.04E+02 6.73E-02 2.32E-05 3.04E-04 3.06E-05 4.63E-04 6.08E-03 6.12E-04 65 1-132 2.96E+01 5.93E+02 4.14E-01 8.08E-04 1.06E-02 1.07E-03 1.62E-02 2.12E-01 2.13E-02 66 1-133 3.12E+01 6.24E+02 1.09E-01 2.23E-04 2.93E-03 2.95E-04 4.47E-03 5.86E-02 5.90E-03 _

67 1-134 4.13E+01 8.26E+02 4.81E-01 1.31E-03 1.72E-02 1.73E-03 2.62E-02 3.43E-01 3.46E-02 1 68 1-135 3.82E+01 7.64E+02 2.95E-01 7.43E-04 9.74E-03 9.80E-04 1.49E-02 1.95E-01 1.96E-02 l 69 70 Cs-134 4.69E-03 9.38E-02 2.80E-01 8.65E-08 1.13E-06 1.14E-07 1.73E-06 2.27E-05 2.28E-06 71 Cs-135 1.66E-08 3.31E-07 2.09E-06 2.28E-18 2.99E-17 3.01E-18 4.56E-17 5.98E-16 6.02E-17 _

72 Cs-136 7.26E-04 1.45E-02 3.92E-01 1.88E-08 2.46E-07 2.48E-08 3.75E-07 4.92E-06 4.95E-07 73 CS-137 2.91E-03 5.81E-02 2.86E-05 5.48E-12 7.19E-11 7.23E-12 1.10E-10 1.44E-09 1.45E-10 74 Cs-138 3.63E-01 7.26E+00 4.48E-01 1.07E-05 1.40E-04 1.41E-05 2.14E-04 2.81E-03 2.83E-04 75 Calculation QDC-0000-N-1 266, Rev. 4 Attachment A - Dose Calculation Page A2 of Al 0

A B C [ D E F G H I J K L M 76 Sub-total (rem EDE) [ 3.12E-03 4.09E-02 4.12E-03 6.23E-02 8.18E-01 8.23E-02 77 Iodine and Cesium Total (rem TEDE) 1.89E-01 1.66E-01 1.67E-02 3.79E+00 3.32E+00 3.35E-01 78 Curies Released Case 1 Dose (rem EDE) Case 2 Dose (rem EDE) 79 to the Environment (External) (External) 80 Case 1 Case 2 DCF2 CR EAB LPZ CR EAB LPZ 81 Kr-83M 6.95E-02 6.95E-02 5.55E-06 2.54E-11 3.33E-10 3.35E-11 2.54E-11 3.33E-10 3.35E-11 82 Kr-85M 1.22E-01 1.22E-01 2.77E-02 2.22E-07 2.91 E-06 2.93E-07 2.22E-07 2.91 E-06 2.93E-07 83 Kr-85 4.75E-04 4.75E-04 4.40E-04 1.38E-11 1.81E-10 1.82E-11 1.38E-1I 1.81E-10 1.82E-11 84 Kr-87 3.79E-01 3.79E-01 1.52E-01 3.81 E-06 5.OOE-05 5.03E-06 3.81 E-06 5.00E-05 5.03E-06 85 Kr-88 3.89E-01 3.89E-01 3.77E-01 9.67E-06 1.27E-04 1.28E-05 9.67E-06 1.27E-04 1.28E-05 86 Kr-89 1.62E+00 1.62E+O0 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 87 Xe-131M 3.88E-04 3.88E-04 1.44E-03 3.68E-11 4.83E-10 4.86E-11 3.68E-11 4.83E-10 4.86E-11 88 Xe-133M 5.81 E-03 5.81 E-03 5.07E-03 1.94E-09 2.54E-08 2.56E-09 1.94E-09 2.54E-08 2.56E-09 89 Xe-133 1.63E-01 1.63E-01 5.77E-03 6.18E-08 8.11 E-07 8.16E-08 6.18E-08 8.11 E-07 8.16E-08 90 Xe-135M 4.76E-01 4.76E-01 7.55E-02 2.37E-06 3.1 OE-05 3.12E-06 2.37E-06 3.1OE-05 3.12E-06 91 Xe-135 4.40E-01 4.40E-01 4.40E-02 1.27E-06 1.67E-05 1.68E-06 1.27E-06 1.67E-05 1.68E-06 92 Xe-1 37 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 2.28E-05 2.98E-04 3.OOE-05 2.28E-05 2.98E-04 3.00E-05 94 Nvbl Gas Sub-totl (;umEDE; 4.02E-05 5.27E-U4 5.3Ut-U5 4.0ZE-05 5.27E-04 5.30E-05_

ssr 1 1r1 96 Overall Total (rem TEDE) _ 1 _ 1.89E-01 1.67E-01 1.68E-02 3.79E+00 3.32E+00 3.35E-01 _

98 1 Dose Conversion Factor (rem/Curie) from Federal Guidance Report (FGR) 11 per Reg. Guide 1.183 I I I 99 2 Dose Conversion Factor (rem-m/Curie-second) from FGR 12 per Reg. Guide 1.1831 1 100 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 Ci/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 5.13E-02 Control Room Geometry Factor per Reg. Guide 1.183, Regulatory Position 4.2.7 ,

1051 1.54E+01 EAB a (meters) for Fstability, (taken from PAVAN runs in Calc. QDC-OO00-M-1408, Rev. 1) 1061 1.530E+02 LP mtr)for F stability, (taken from PAVAN runs in Calc. QDC-0000-M-1408, Rev. 1) 107 1.OOE+00 Wind Speed (mis) riIIII I I 108 8.64E-04 X/Q (seconds/m 3) at EA Boundary 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> based on RG 1.5 methodology IIIII_

109 8.69E-05 X/Q (seconds/i 3) at Low Population Zone 2 based on RG 1.5 methodology I I I I II r110 _ _ _ _ _ _ _ _

Calculation QDC-0000-N-1266, Rev. 4 Attachment A - Dose Calculation Page A3 of A10

A B C D E F G 1 Quad Cities 1&2 MSI . Case 1: Reactor Coolant at maximum value (D

-2 3 =(A9A1035.3 Volume of cloud (cubic meters) Case 2: Reactor Coolant at maximum value pe 4 =A7453.59 Mass of water in reactor coolant r__

5 =(A3-12/Pl()1(1/3) seconds for cloud to pass over Cl 6 184000 Volume of Control Room Envelop 7 140000 Mass of Liquid Water Released (e 8 0.4 Flashing Fraction 9 =ArA8 Mass of Steam in the Coud lb _

10 26.799 Vg (Rt'ib) (based on 14.7 psi and 11 Reactor coolia-ntiodine dist 12 13 14 Nonmalized Case I Case 2 Case I

15. Isotope civt FGR 11 _ 1-131DE Normalized Normalized kActivity 161 Distribution DCF ' Activity Adtivty Activity Release 171 uCi/gm Rem,,_D5/Ci uC~gm uC~gm uCi/gm Cl 181 1-131 0.067 32900 =C1 8-BlBICS18 =D18-0.2/DS23 =E18-20 =E1I8-SAS4-SC$1 8/C18/1000000 1'-132 0.38 381 =C19-B19/CS18 =D19-0.2/D$23 =E19_20 =E19-SA$4-$C$18/C19/1000000 20 1-133 5.4 5846 =C20-B20/CS18 =D20-0.2/DS23 =E20-20 =E20-SA$4-SCS18/C20/1000000 21 1-134 0.53 131 =C21*B21/CS18 =D21*0.2/D$23 =E21-20 =E21_*SAS4-SCS18/C21/1000000 22 I-135 0.49 1230 =C22-B22/CS18 =D22-0.2/DS23 =E22-20 =E22'SAS4'SCS1_8/C22/1000000 2 Totals =SUM(D18:D22) =SUM(E18:E22) =SUM(F18:F22) 24  ;,,,,->kw *r.14A^

25 NEDO5 NEDt> NEDC A ,___

26 21143-13 21143-13 21143-13 Case 1 Case 2 271_ MSLB _ Case I Case 2 Release Release 281X Noble Gas _Activity ACtivtY Cloud Cloud 291< Release = Release Release Concentation Concentration 30 Fractions Cil Ci 0 DC~r3 CVmn3 31 K43M 0.00936 =$B31-5.53 0.45 =SB31-5.5-3-0.45 =C3V/$A$3 =D31/SAS3 Cs-136 32 K-85M 0.0164 =SB32-5.5V3-0.45 =SB32-5.5 3-0.45 =C32/$A$3 =D32/SAS3S 33 Kr485 0.000064 =SB33 5.5 3-0.45 =SB33-6553-0.45 =C33f$A$3 =D33/SAS3 34 Kr47 0.0511 =$B34-5.53-0.45 =$B34-.5350.45 =C34/$AS3 =D34/$A$3 3S Kr488 0_0524 =SB35-.553-0.45 $B05.53-0.45 =C35/$A$3 =D35/$AS3 Cs-134 36 Kr489 0_218 =SB3V5.5 3-0.45 =$B36*5.5-3-0.45 =C36/SA$3 =D36/SAS3 Cs-135 37, Xe-1311M 0.0D00523 =$B3715.V 3-0.45 =SB37-5 5-3-0.45 =C,37/$AS3 =D37/SAS3 Cs-136 381 Xe-1133M 0.000782 =SB38'5.S'3'0.4S =SB38-5.5-3-0.4S =C38/SAS3 =D38/SAS3 CS-137 391 Xe-133 0.0219 =SB39 5.5 3-0.4S =SB39-S 5-3-0.4S =C39/SAS3 =D39/SAS3 Cs-138 401 Xe-135M 0.0641 =SB40^5.5^3^0.45 =SB40^5.5 3-0.45 =C40/SAS3 =D40/SAS3 Totals 41 1Xe-135 0.0592 =$B41-S5.53-OAS5 =$841*5.5V3-0.45 =C41/SAS3 =D41/SAS3 42 Xe-137 0288_ =SB425.53-0A45 =SB425.53 0.45 =C42/SAS3 =D42/$AS3 43 Xe-138 0_218 =$B43-5.53-0.45 =SB43-55-3-0.45 =C43/SA$3 =D43/$AS3 4S _ Curies Relased _ Case 1Dose (rem CEDE) 46 to the Environment (Inhalation) 47 Isotope I 1 AR CasCase ase 2 DCF CR EAB

_ 1-_ ._ _to=. I :16 S 1=1-Si-3-SASS E4&$A.iO3iaiaiu 49 1_I-132 =G19 =H19 381 =119-SE49 $AS103SA$5 I=C49-$E49-$A$103-SA$108 50 _ 1-133 =G20 =H20 5846 =120-SE50SA$103'5ASS I=C5O$E50'$A$103'$A$108 S1i 1-134 =G21 =H21 131 =121SE51 '$A$103SA$S =C51*$E51*SA$103-SAS108

-15

_1 3 =G22 =H22 1230 =122-SE52'$A$103'SAS5 =C52'$E52^SAS103'$AS108 53 541 Cs-134 =L35 M35 1=(3700000000000rO.0000000125 31 55 _ Cs-135 L36 L=M36 =(3700000000000 0000000123 e 56 Cs-136 =L37 =M37 1=(3700000000000y'0.00000000198 e 571 CS-I 37 _ ______________ =L ~ =M38 e Cs-I.4 38 I _ _ __ _ __ _ _ __ _ __ 3 L=M39 274 Calculation QDC-0000-N-1266, Rev. 4 Attachment A - Dose Calculation Page M4of AIO

A C I 0 E 59l A G Sub-total 60X Curies Released I to the Environment I ixterng 6Ilsoto"e 2

_II Case 1 I Case 2 DCF CR EAB 1-131 =C48 =W48 0.06734 1=1 - =z

_______________=C49 .=049 .0 4144 i

________________________=D05 0.10878 1

________________ =C51 ____________0.481 I . .. _____________ =C52 =052 0.29526 11:1 - .

Cs-1 34 =L35 1=(3-0000000909)90.000000000757 Cs-1i35 =L36 =(3700000000tJ00)'5.65E-19 72 Cs-136 =L37 =M37 =(370 0000000).0000~000000001~06 73 CS-137 =M38 =(3700000000000)'7.74E-18 Cs-i 38 =L39 =M39 =(37000D00000000)0.000000000000121 1 5 11. I I Sub-total (rem EDE) I=SUM(F64:F74) =SUM(G64:G74 II) 7odine and Cealum Total _ _ I _ __ _ __

6)

[V78 Z I

r I Curies Released )ose (rem EDE)

I791 1 _ to the Envirnment Extemnal)

Case i Case 2 DCF' CR EAB Kr-83M =C31 =D31 0.00000555 1=E31-$E81^SA$104-$AS5 $108 82* Kr-85M _I=C32 -D32 10.027676 _ 5 S108 83 Kr-85 I _ _ =C33 1=D33 L0.0004403 - l- 5 $108 Kr-87 =C34 =D34 .15244 =E34-SE84-SA$104-$AS5 $108 85 Kr-88 =C35 =D35 0.3774 =1 5 $108 86 Kr-89 =C36 =D36 0 5 87 Xe-131M =C37 =D37 0.0014393 5 88 Xe-133M =C38 =D38 0.005069 5 89 Xe-133 =C39 =D39 0.005772 90 Xe-1 35M =C40 =W40 0.07548 91 Xe-135 =C41 =W41 0.04403 =E41-SE91-SA$104-SAS5 =C91-$E91-SA5108 92 Xe-1i37 Xe-138

,=C42 =D42 110

=C43 =-43 D.21349 1- Noble Gas Sub-total (rem EDE 96 O0verall Total (rem TEDE) __ _ _ =SUM(F77F94 =SUM(177+194) 97.

98 Dose Conversion Factor (renVCurie) 3 99 2Dose Conversion Factor (rem-m/Cu 10t From NEDO-21143-1. 'Radiological _

10t1 with its Table 3-1 (-SLBA Sormce 102 offgas release rate and 5.5 second I 3

103 0.000347 Breathing rate (m rsecond) per Regul 104 =($A$6O.338y1 173 Control Room Geometry Factor per 1105 15.4 EAB, r (meters) for F stability, (taken I D l AS me, - D. ,,... F . . ;, . . ' i. L 1 7 1W i nd Spe e d ( ed 3a) __ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

108 =0.0133/AS105/AS107 X0 (seconds ) at EABoundary . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

3 109 =0.0133/AA106/A$107 XIQ (seconds/ ) at Low Population _

Calculation QDC-0000-N-1266, Rev. 4 Attachfmenit A - Deoie Calculation Page AS of Al10

H I J K L M 1-131of 0.2 uCi/g) permitted for continued full power operation 2

3 mined (DE 1-131 of 4.0 uCifg) corresponding to an assumed pre-accident spike_

5 7

9.

10 11 12 Case I Case 2 13 Release Release 14 Case 2 Cloud Cloud Case I Case 2 15 Activity Concentration Concentration Decay Activity Act ivty 16 Release Constant Release Release 17 Ci Ci/m3 Cim3 1/seconds moles moles 18 =G1820 =G181$AS3 =H18/$AS3 =LN(2y(8.04-86400) =G1837000000000/$Ki8/6.023E+23 =H18-37000000000/$K1816.023E+23 19 =G19-20 =G191WA53 =HI9/$A$3 =LN(2)I 33600 =G19-37000000000/$K19/6.023E+23 =H19-37000000000/$K19/6.023E+23 20 =G20-20 =G20/$AS3 =H20/SA$3 =LN(2Y(20.8-3600) =G20-37000000000/$K20/6.023E+23 =H20-37000000000/$K20/6.023E+-23 21 =G21'20 =G21/$A$3 =H21/$A$3 =LN(2y(52.6-60) =G21*370000000C/$K21/6.023E+23 =H21*37000000000/$K21/6.023E+23 22 =G22-20 =G22/$AS3 =H22/SA$3 LN(2y(6.61*3600) =G22-37000000000/$K22/6.023E+23 =H22-37000000000/$K22/6.023E+23 23 Total =SUM(L18L22 =SUM(M18:M22) 24 27 28 29 31 Case I Case2 ____Case I Case2 32 Activity Activity Decay Activity Activity 33 Release Release Constant Release Release 34 Molar Frac. moles moles 1/seconds curies curies 35 0.044317152955112 =0.95 H35 LS23 =0.95SSH35-M$23 =LN(2y(2.066286400 365.25) =135 6.023E+23-SK35/37000000000 =J35-6.023E+23-SK35137000000000 36 0.174506296053598 =0.95$H36L$23 =0.95$H368MS23 =LN 2)/23000008640036525) =136*6.023E+23-K36/37000000000 =J366.023E+23-SK36/37000000000 37 0.000119942189253291 =0.95$H37LS23 =0.95$H37M$23 =LN 2 13.1686400 =13r6023E.231K37/370m0000 =J37i6.023E+23-$K37/37000000000 38 0.401736793048373 =0.95 SH38L$23 =0.95SSH38-MS23 =LN(2Y(30.17'86400*365.25) =138-6023E+23-K38/37000000000 =J38 6.023E+23 $K38/37000000000 39 0.000101901239392202 =0.95$H39 L$23 =0.95SSH39-M$23 =LN(2y(32.2-60) =139 6,023E+23-SK39/37000000000 =J39-6.023E+23-SK39/37000000000 40 =SUM(H35:H39) =SUM(135:139) =SUM(J35:J39) _____________ ________________ _______________

41 Balance is stable Cs-133 =SUM__ _______

42 43 44 I

I- = +

1 47 LPZ CR EAB LPZ I

I I=D49'SE49-SAS103*SA$I09 8 I=D5OSE50-SA$103*SA$109 8 I Calculation QDC-0000-N-1266, Rev. 4 Attachment A - Dose Calculation Page A6 of AIO

FaI H K L M

-SUM(148:158) =SUM(J48:J58) -SUM(K48:K58)

+

+

LPZ CR EAB LPZ 64 65 I=JI81$E64'$A$104S$A$5

=J19*$E65*SAS104-SAS5 L=64-$E6-4iA$108 I=0641$E64'$A$109 i I_ _ _ _ _ _ _ _ _ _ _ _ _ _

5S$E65'SAS108 =D65*SE65*SAS109 66 =J20-SE66-SAS104'SAS5 109 67 =J21ISE67*SASl04-SAS5 109 68 1- --- . . . . . .*. . . .

109 69 70 109 71 109 109 109 74 74 109 75 76 =SUM(J64:J74) 77 4SUM(J59.J76) 78 1 __ _ _ _ _ _ __ _ _ _ _ c ase 2 Dose (re m E DE ) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

79 (E xtern al) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

80L PZ IC R EA R LPZ_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _

61 =C8lP$E81VSAS109 F31$E81*IA$104$A$5 I=D81P$E81P$A$108 =D81*$E811$A$109_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

62 =C82$E82'$A$109 =F2*$E82*$AS104SA$5 I=D82'$E82$A$108 =D82*$E821$A$109_________________

83 I=C83-$E83-$A$109 =F33*$E83$A$104S$A$5 I=D83'$E83*$A$108 =D831$E8Y$A$109 84 =C841$E84*$A$109 =F34*$E84'$A$104'SA$S =D84-$E84-$A$108 =D841$E84'SAS109 85 =C85*$E85$A$109 =F35*$E851$A$104'$A$5 =D85*$E85$A$108 =D851$E851A$109 86 =C86'$E86'$A$109 =F36*$E866iA104'SA$S =D86*$E86*$A$108 =D86*$E$6*$A$109________________

87 =C87*$E87$A$109 =F37*$E87'$A$104'$A$5 =D87rSE87$A$108 =D87$E87$A$109 88 =C88S$E881$A$109 =F38S$E881$A$104'$AS5 =D88S$E8W$A$108 =D88'$E68B$A$109 89 =C89*$E89'$A$109 =F39'$E89$A$104CSA$5 =D89S$E89$A$108 =D89*$E89*$A$109 90 =C90*$E90'$AS109 =F401$E90*$A$104*$A$5 =D90'$E90i$AS108 =D090SE90'$A$109 91 .=C911$E91*$A$109 =F41*SE91PSA$04S$A$5 =D91*$E91i$A$108 =D91V$E91V$A$109 92 =C921$E92'$A$109 :F42:$E92$A(104:$A$5 =D92-$E92*$A$108 =D92-$E92$AS109 93 =C93*$E93*$A$109 =F43 $E93 1AS 04 $A$5 =093*$E93*$A$108 =D931$E93SAS$109 94-SUM H81:H93) -SUM 181:193) -SUM(J8II:J93) =SUM(K81K93) 96 =SUM(H77+H94) -SUM(1774194) -SUM(J77+J94) SUM K774K94) 97 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

98 991 100 101 102 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

10103_____________ _____________ ______________ _________________ _______________

104 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

10 ______________ ____________ _____________ ________________ ______________

1171107____________ _____________ _____________ ________________ _______________

110981___________ ___________ ____________ ______________ _____________

Calculation QODC-0000-N-1266, Rev. 4 Attachmrent A - Dose Calculation Page A7 of A10

A I B I C l D I E I F I G I H I I J K L I Peach Bottom Beginning of Core Life (100 Effective Full Power Da s) and End of Cycle (EOC) Cesium Isotope Quantities 2 (Used for General Cs Molar Fraction Determination for AST) 3 . . Decay 4 100 EFPD EOC 100 EFPD EOC Constant 100 EFPD EOC 5 _ grams) (grams) At. Masc (gm-moles) (gm-moles) Iiseconds Cl Ci 6 Cs-133 1.025E+05 1.678E+05 Cs-133 132.91 7.712E+02 1.263E+03 0.OOOE+00 O.OOOE+00 0.000E+00 7 Cs-134 1.031 E+04 1.977E+04 Cs-134 133.91 7.699E+01 1.476E+02 1.07E-08 1.335E+07 2.559E+07 8 Cs-135 4.502E+04 7.841 E+04 Cs-135 134.91 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-137 136.91 7.940E+02 1.338E+03 7.28E-10 9.410E+06 1.586E+07 10 Cs-136 2.37E-01 3.99E-01 6.10E-07 2.352E+06 3.964E+06 11 Cs-138 2.01 E-01 3.39E-01 3.59E-04 1.176E+09 1.982E+09 12 Total 2.665E+05 4.492E+051 1.976E+03 3.331 E+03 13 _ ___ _ _ _ _ _ _ _ _ _ _ _ ___ .__ ,__

14 ANSltANS-18.1-1999 Relative Abundances in Reactor Water Molar Fraction 15 uCi/qram of moles/gram of ratio to Cs-133 39.0219%] 37.9218%

16 Reactor Coolant Reactor Coolan Cs-137 Cs-134 3.8956%1 4.4317%

17 Cs-?133 3.00E-05 1.O4En08 __ Cs-,3n 16.8848%70 A.56E A

17 .4506 %j 18 Cs-136 2.OOE-05 1.21E+06 2.99E-04 Cs-137 40.1755% 40.1737%

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

20 Cs-1 38 1.OOE-02 1.03E+06 2.54E-04 Cs-1 38 0.0102% 0.0102%

Calculation QDC-0000-N-1266, Rev. 4 Attachment A - Dose Calculation Page A8 of A10

A B C D E F G H T 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-i36 =K1 0*37000000000/$J 10/6.023E+23 11 Cs-I 38 =K11 *37000000000/$J 11/6.023E+23 12 Total =SUM(B6:B9) =SUM(C6:C9) =SUM(H6:H 1) 13._

14 ANSI/ANS-15 uCi/gram of moles/gram of ratio to 16 Reactor Coolant Reactor Coolant Cs-1 37 17 Cs-134 0.00003 =B17*37000/J7 =C17/C$19 18 Cs-136 0.00002 1=B18*37000/J1O =C18/C$19 _ _

19 Cs-137 0.00008 =B19*37000/J9 =C19/C$19 _ I 20 Cs-138 0.01 =B20*37000/J11I =C20/C$19 I___I Calculation QDC-0000-N-1266, Rev. 4 Attachment A - Dose Calculation Page A9 of Al10

K L 3 Decay 4 EOC Constant 100 EFPD EOC 5 (gm-moles) 1/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 =L10*37000000000/$Jl /6.023E+23 =LN(2)/(13.16*86400) =K$9*$B$18/$B$19 =L$9*$B$18/$B$19 11 =LI I*37000000000/$J 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 18 Cs-137 =H9/H$12 =19/1$12 19 Cs-136 =H1O/H$12 =110/1$12 20 Cs-138 =H1I/H$12 =111/1$12 Calculation QDC-0000-N-1266, Rev. 4 Attachment A - Dose Calculation Page A10 of AIO

CALCULATION NO. QDC-O00-N-1166, Attachment B T REV. NO. 4 lPAGE NO.B1 of Si Computer Disclosure Sheet Discipline Nuclear Client:: Exelon Corporation Date: January 2006 Project: Quad Cities Units 1&2 MSLB AST Job No.

Program(s) used Rev No. Rev Date Calculation Set No.: QDC-0000-N-1266, Rev. 4 Attachment A spreadsheet N/A N/A Status [ ] Prelim.

[X] Final l ] Void WGI Prequalification [ 3 Yes

[X1 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 a Checked by: P. Reichert 6. 6 5 Separate cell-by-cell independent check by: A. Boatrigh 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.

Retrieved from "https://kanterella.com/w/index.php?title=ML060580587&oldid=2587151"