Text

Rev. 1 to Calculation DRE02-0036, Re-analysis of Fuel Handling Accident (FHA) Using Alternative Source Terms.
	ML052430326
Person / Time
Site:	Dresden, Quad Cities
Issue date:	08/12/2005
From:	Rothstein H; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	RS-05-114 DRE02-0036, Rev 1
	Download: ML052430326 (66)
	v • d • e

ATTACHMENT 4 Calculation DRE02-0036, "Re-analysis of Fuel Handling Accident (FHA)

Using Alternative Source Terms," Revision I

/I CC-AA-309- 1001 Revision 2 ATTACEDIDNT 1 DesLzn Analysis Cover Sbeet Design Analysis (Major Revision) i Last Page No.

20! At. F-1 Analysis No.:-' DRE024036 Revision: 2 1 Tirtle: ' Re.anatysis of Fuel Handling Accident (FHA) Using Alternative Source Tertms EC/ECR No.: 356383 Revision:' 0 Station(s):' Dresden Component(s): __

Unit No.: 21&3 _

Discipline: N _ _

Descrip. N01, R01, R02 Code/Keyword: °AST, FHA Safety/OA Class: SR System Code; 00 __

Structure:

CONTROLLED DOCUMENT REFERENCES" Document No.: rrom/To Document No.: FromrrT DRE04-0030, R1 Frorm _

DRE000011t.RO :rom DRE01-0071. RO :rom GE-NE-A22-00103 64O01. Ro (Om is this Design Analysis Safeguards Information? ' Yes 0 No 0 If yes. see SY-M-101-106 Does this Design Analysis contain Unverified Yes 3 No If yes,.

Assumptions?"AIAO This Design Analysis SUPERCEDES: DRE02-M6 Rev. 0 In Its Description of Revision (list affected pages for partials):

This revision incorporates responses to pertinent NRC Request for Additional Information (RAls) with respect to all Exelon Nuclear Station Alternative Source Term License Amendment Applications. The primary revision is incorporation of the revised XJC values from a new calculation, replacing the former values derived in Attachment A of the previous revision of this calculation. Other clarifications and editorial corrections were also incorporated. Finally, additional assumptions from Regulatory Guide 1.183 are Included to directly Indicate conformance with this Regulatgry Guide.

Preparer: ' t Harold Rothstein /Z O f.v/f Print Namo Sin Name Date Detailed Review 0 Revie:" 0 Alternate Calculations (attached) Testing 0 Reviewer. 22 Paul Reichert Prnt Name Sig PCAQ - Date

._, aM/)(

1--

Review AXJ:Pr".0 Independent review 0 Peer review 0 Notes: 23^} 7k; ;% g7 > . ~5 .^&~ t.M u&

Approver: ( b(j )J. ______

Pnnt Name Sign Name Dae Exelon Revlewer 2s LLaf Is a Supplemental Review Required? 26 Yesz No El 1iyes, te Attachment 3 Exelon FRPr J

NmeSignNa m_ _ _

Print Name Sign N~ame Date

CALCULATION NO. DREO2-0036 I REV. NO. I I PAGE NO.2

1. PURPOSE/OBJECTIVE ....................................... 3

2. METHODOLOGY AND ACCEPTANCE CRITERIA ..................................... 4 2.1. Fuel Source Term Model ........................................ 4 2.2. Gap Activity ....... . .. 4 2.3. Pool Decontamination Factor (DF) Model . . . 5 2.4. Release Model . . . 6 2.5. DiDispersion Model . . . 6 2.6. CoControlRoom Model . . . 6 2.7. Dose Modeling . . . 6 2.7.1. EAB and LPZ .6 2.7.2. Control Room .7 2.8. Acceptance Criteria ........................... 7

3. ASSUMPTIONS .......................... 12

4. DESIGN INPUT .......................... 14

5. REFERENCES .......................... 17

6. CALCULATIONS .......................... 18

7.

SUMMARY

AND CONCLUSIONS .......................... 21 Attachments A. RADTRAD Run for 23 feet of water over damaged fuel [15 pgs.]

B. RADTRAD Run for 19 feet of water over damaged fuel [ 15 pgs]

C. FHA RADTRAD Nuclide Information File [10 pgs.]

D. FHA Release Fraction File DF=200 case [I pg.]

E. FHA Release Fraction File DF=135 case [I pg.]

F. Computer Disclosure Sheet [I pg.]

I PAGE NO.3 I CALCULATION ACULATION NO. NO. DREO2-0036 DRE02-0036 IIREV. NO. 1I REV. NO. I PAGE NO. 3 I

1. PURPOSE/OBJECTIVE The purpose of this calculation is to apply Alternative Source Term (AST) methodology to the analysis of the design basis Fuel Handling Accident (FHA) for Dresden Units 2&3. This calculation is based on normal Reactor Building exhaust through the Reactor Building Exhaust Stack,-and no Control Room Emergency Filter System operation. Therefore, this calculation supports changes to the current Dresden 2&3 Technical Specifications to consider that the operability of such systems and related subsystems previously required to mitigate the radiological consequences of fuel handling accidents may not be necessary after a sufficient post-shutdown decay period has elapsed.

Not having to consider secondary containment and control room integrity and filtration requirements in support of refueling activities has the potential to significantly improve the flexibility and duration of scheduled plant outage activities.

Regulatory Guide 1.183 [2] is the basis for this evaluation. Concerning the FHA, the new guidance has the advantage of smaller gap fractions, a larger pool decontamination factor [DF],

and dose criteria that replace both the whole body and thyroid dose limits with a limit on Total Effective Dose Equivalent [TEDE].

The other changes from the current UFSAR calculation are listed below.

An offsite dose limit of 6.3 rem TEDE (RG 1.183 & 10 CFR 50.67(b)(2)(iii)) is applied instead of the SRP 15.7.4 values of 25% of the 10CFR100 limits.

A control room dose limit of 5-rem TEDE is applied instead of the values of 5 rem whole body, or its equivalent (10 CFR 50 Appendix A (II) GDC 19)..

Design Basis analysis is based on NRC Regulatory Guide 1.183.

The Control Room, Exclusion Area Boundary (EAB), and Low Population Zone (LPZ) x/Is were recalculated for the Unit 2&3 Normal Reactor Building Exhaust Stack and the new limiting X/o was applied for each in this analysis.

Secondary Containment automatic isolation and filtration are not credited.

Control Room Emergency Filter System (CREFS) operation is not credited.

Dose Conversion Factors for Immersion and Inhalation are taken from FGRs 12 [5] and 11[4], respectively. Regulatory Guide 1.183 cites these DCFs as acceptable current estimates for evaluating the radiological impact of nuclear plant accidents.

CALCULATION NO. DRE02-0036 I REV. NO. I PAGE NO. 4

2. METHODOLOGY AND ACCEPTANCE CRITERIA Analyses of radiological consequences resulting from a design basis Fuel Handling Accident (FHA) are performed using the guidance for application of Alternative Source Terms to this event in RG 1.183.

Analyses of radiation transport and dose assessment is performed using RADTRAD v. 3.03.

RADTRAD[3] is a simplified model of RADionuclide Transport and Removal And Dose Estimation developed for the NRC and endorsed by the NRC as an acceptable methodology for reanalysis of the radiological consequences of design basis accidents. The technical basis for the RADTRAD code is documented in Section 2 of NUREGICR-6604. The methodologies significant to this analysis are the dose consequence analysis (NUREG Section 2.3) and the Radioactive Decay Calculations (NUREG Section 2.4). This version of RADTRAD has been pre-qualified for safety related design analysis by Washington Group International per its 10CFR50 Appendix B QA program.

2.1. Fuel Source Term Model The fuel source term is based on reactor core source terms used for LOCA dose assessment.

The fraction of the core fuel damaged is that historically bounding and is based on 111 fuel rods damaged on a 7x7 49 pin bundle basis. With 724 fuel assemblies in the core, the damaged fraction = 111 / (49

724) = 0.00313. This fuel is assumed to have been operating at a power level associated will radial peaking limits. Therefore, the associated power ='3016 MWth

0.00313

1.7 = 16.05 MWth.

Movement of recently irradiated fuel will not occur less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after the associated reactor shutdown, and therefore, a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months delay period is used.

2.2. Gap Activity This calculation is applicable to fuel whose burnup and power limits are bounded by those specified in RG 1.183, footnote 11. This allows safe application of the gap activity fractions for LOCA events per RG 1.183, Table 3, which are as follows:

- 5% of the noble gases (excluding Kr-85)

- 10% of the Kr-85

- 5% of the halogen inventory (excluding 1-131)

- 8% of the 1-131

- 12% of the Alkali metal inventory RADTRAD LOCA*.nif files are modified for FHA use to accommodate the differential gap activities among halogen and noble gas gap fractions shown above.

CALCULATION NO. DRE02-0036 I REV. NO. I I PAGENO.l.5 2.3. Pool DecontaminationFactor(DF) Model Analyzed water depths above damaged fuel are 23 feet and 19 feet. These values correspond to the minimum expected coverage over spent fuel racks, and the Technical Specification limit, respectively. The latter value provides assurance that analyzed coverage accounts for potential dropped fuel that might be positioned lying over the spent fuel racks.

As-prescribed in RG 11 83,-Appendix B,-for the 23-foot water depth,-the overall-DF-of 200 is used.

For the 19 foot water depth, RG 1.183, Appendix B recommends the use of Reference 10 of this calculation as a basis for determined a reduced DF. This reference has been previously used in Reference 8 as the design basis for this adjustment, using the following relationships:

H DFEnorg = (DFinorg0 Ho and D'af fraction of inorganic fraction of organic DFinorg I where, per RG 1.183, Appendix B Ho = 23 feet of water depth DFr,,n0 = inorganic iodine DF of 500 per RG 1.183, Appendix B fraction of inorganic iodine in fuel = 0.9985 fraction of organic iodine in fuel = 0.0015 fraction of elemental iodine above the water = 0.57 fraction of organic iodine above the water = 0.43 and, for H = 19 foot water depth:

DF1nor = the associated inorganic iodine DF = 169.66 DFeff = overall iodine OF = 135.4, rounded to 135.

fraction of elemental iodine above the water = 0.80 fraction of organic iodine above the water = 0.20

I CALCULATION NO. DRE02-0036 I REV. NO. I PAGE NO. 6 l 2.4. Release Model Release modeling uses the RADTRAD computer program. The normal Nuclide Inventory File representing a Dresden core is artificially adjusted to account for the higher than average gap fractions for 1-131 and Kr-85 as discussed above to allow for their higher gap fractions.

The compartments are the Refuel Floor Air Space, the Environment and the Control Room. The refuel floor exhaust rate is set artificially high at 4 air changes per hour. This results in 99.97%

of the contained radioactivity being exhausted within two hours.

2.5. Dispersion Model X/Qs for this release point are determined in Reference 13 based on RG 1.194 methodology as implemented by ARCON96 for onsite locations and on RG. 1.145 methodology as implemented by PAVAN for offsite locations.

2.6. Control Room Model The control room as analyzed for the FHA is unfiltered. The Dresden Unit 2&3 Control Room is modeled as a closed volume of 64,000 ft3 . Although normal maximum flow into the CR is 2000 cfm + 10%, a Control Room changeover rate of 1 CR Volume per minute is used for conservatism and to allow for any unfiltered inleakage Flow into the CR is therefore assumed to be 64,000 CFM, and to balance the system for analytical purposes, an equal flow of clean air is considered to leave the CR. No credit is taking for any filtration of flows into the CR.

2.7. Dose Modeling Dose models for both onsite and offsite are simplified and meet R.G. 1.183 requirements. Dose conversion factors are based on Federal Guidance Reports 11 and 12. Effectively, RADTRAD uses the following formulations, integrated numerically over the accident duration:

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

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

Breathing Rate (m3/sec)

Inhalation DCF (remCEDE/Ci inhaled)

Q and X/3 DoseEDE (rem) = Release (Curies)* - (sec/rn )

Submersion DCF (rem EE -m 3 / Ci -sec)

Q and finally,

I CALCULATION NO. DRE02-0036 I REV. NO. I I PAGE NO. 7 l DoseTEDE (rem) = DoseTEDE (rem) + DoseEDE (rem) 2.7.2. Control Room The formulas used by RADTRAD, by time increment, are:

DosecED (rem) - Time Dependen-tCRi(Al Concentration (Cilime iicre Duratio (s0ec)

3 Breathing Rate (m /sec)

Inhalation DCF (remcEDE/Ci inhaled)

Occupancy Factor of I and DoseEDE (rem) = Time Dependent CR AirConcentration (Ci/m 3)*Time increment Duration (sec)*

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

Occupancy Factor of I

CR Geometry Factor and finally, DoseTEDE (rem)= DoseTEDE (rem) + DoseEDE (rem) 2.8. Acceptance Criteria Dose acceptance criteria are per 10CFR50.67 and R.G. 1.183 guidance.

Table I 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.

Table 1. Regulatory Dose Limits (Rem TEDE)

CR EAB LPZ (30 days) (2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ) (30 days) 5 6.3 6.3 Direct conformance with the relevant sections of the body of Regulatory Guide 1.183 (such as the Acceptance Criteria provided above) and all of the Assumptions in its Appendix B "Assumptions for Evaluating the Radiological Consequences of a BWR Fuel Handling Accident" is provided by this analysis, as shown in the Conformance Matrix Table 2.

I CALCULATION NO. DRE02-0036 I REV. NO. 1 I PAGE NO. 8 g Table 2: ConformancewithRG 1.183 AppendixB (Fuel Ha dling ccident) ;

RG DresdenlQuad Section RG Position ;itie Analysis Comments.i Acceptable assumptions regarding core inventory and the release of Conforms radionuclides from the fuel are provided in Regulatory Position 3 of this guide. ,

1.1 The number of fuel rods damaged during the accident should be based Conforms on a conservative analysis that considers the most limiting case. This analysis should consider parameters such as the weight of the dropped I heavy load or the weight of a dropped fuel assembly (plus any attached handling grapples), the height of the drop, and the compression, torsion, and shear stresses on the irradiated fuel rods. Damage to adjacent fuel assemblies, if applicable (e.g., events over the reactor vessel), should be considered.

1.2 The fission product release from the breached fuel is based on Conforms Regulatory Position 3.2 of this guide and the estimate of the number of fuel rods breached. All the gap activity in the damaged rods is assumed to be instantaneously released. Radionuclides that should be considered include xenons, kryptons, halogens, cesiums, and rubidiums.

1.3 The chemical form of radioiodine released from the fuel to the spent fuel Conforms All iodirde added to pool is pool should be assumed to be 95% cesium iodide (Csl), 4.85 percent assumed to dissociate.

elemental iodine, and 0.15 percent organic iodide. The CsI released from the fuel is assumed to completely dissociate in the pool water. Because of the low pH of the pool water, the iodine re-evolves as elemental iodine.

This is assumed to occur instantaneously. The NRC staff will consider, on a case-by-case basis, justifiable mechanistic treatment of the iodine release from the pool. I 2 If the depth of water above the damaged fuel is 23 feet or greater, the Conforms Two cases were considered decontamination factors for the elemental and organic species are 500 in the analyses. The first and 1, respectively, giving an overall effective decontamination factor of case assumed a water depth 200 (i.e;, 99.5% of the total iodine released from the damaged rods is of 19 feet and a retained by the water). This difference in decontamination factors for decontamination factor of elemental (99.85%) and organic iodine (0.15%) species results in the 135. The Technical

I CALCULATION NO. DRE02-0036 I REV. NO. I PAGE NO. 9 Table 2. Conformance with RG 1.183 Appendix B (Fuel Handling Accident)'

' " '-' 'Dresden/Quad Section '; RG Position- Cities Analysis -Comnments iodine above the water being composed of 57% elemental and 43% Specification 3.7.8 limit for the organic species. If the depth of water is not 23 feet, the decontamination minimum spent fuel storage factor will have to be determined on a case-by-case method (Ref. B-I). pool water level is 19 feet.

The second case assumed a water depth of 23 feet and a decontamination factor of 200. The decontamination factors were determined in accordance with RG 1.183.

3 The retention of noble gases in the water in the fuel pool or reactor cavity Conforms Is negligible (i.e., decontamination factor of 1). Particulate radionuclides are assumed to be retained by the water in the fuel pool or reactor cavity (i.e., infinite decontamination factor). '

4.1 The radioactive material that escapes from the fuel pool to the fuel Conforms No credit is taken for the SGT building is assumed to be released to the environment over a 2-hour time System or its elevated period. release.

4.2 A reduction in the amount of radioactive material released from the fuel Not Applicable No credit is taken for filtration pool by engineered safety feature (ESF) filter systems may be taken into from the reactor building.

account provided these systems meet the guidance of Regulatory Guide 1.52 and Generic Letter 99-02 (Refs. B-2, B-3). Delays in radiation detection, actuation of the ESF filtration system, or diversion of ventilation flow to the ESF filtration system should be determined and accounted for in the radioactivity release analyses.

4.3 The radioactivity release from the fuel pool should be assumed to be Not Applicable Two-hour release to the drawn into the ESF filtration system without mixing or dilution in the fuel environment is assumed.

building. If mixing can be demonstrated, credit for mixing and dilution may be considered on a case-by-case basis. This evaluation should consider the magnitude of the building volume and exhaust rate, the potential for bypass to the environment, the location of exhaust plenums relative to the surface of the pool, recirculation ventilation systems, and

I CALCULATION NO. DRE02-0036 I REV. NO. I I PAGE NO. 10 l

- Tabl 2: Conformanc with RG 1.183 Appendix B (Fuel Handling Accident)

RG DreidenlQuad' Section RG Position ite Anysis Comm t internal walls and floors that impede stream flow between the surface of the pool and the exhaust plenums.

5.1 If the containment is isolated during fuel handling operations, no Not Applicable Containment is not isolated.

radiological consequences need to be analyzed.

5.2 If the containment Is open during fuel handling operations, but designed Not Applicable Containment is not isolated.

to automatically isolate in the event of a fuel handling accident, the release duration should be based on delays in radiation detection and completion of containment isolation. If it can be shown that containment isolation occurs before radioactivity is released to the environment, no radiological consequences need to be analyzed.

5.3 If the containment is open during fuel handling operations (e.g., Conforms personnel air lock or equipment hatch is open), the radioactive material that escapes from the reactor cavity pool to the containment is released to the environment over a 2-hour time period.

5.4 A reduction in the amount of radioactive material released from the Not Applicable No credit is being taken for containment by ESF filter systems may be taken into account provided filtration of release from the that these systems meet the guidance of Regulatory Guide 1.52 and reactor building.

Generic Letter 99-02 (Refs. B-2 and B-3). Delays in radiation detection, actuation of the ESF filtration system, or diversion of ventilation flow to the ESF filtration system should be determined and accounted for in the radioactivity release analyses.

5.5 Credit for dilution or mixing of the activity released from the reactor cavity Not Applicable No credit is taken for dilution by natural 'or forced convection inside the containment may be or mixing of the activity considered on a case-by-case basis. Such credit is generally limited to released from the reactor 50% of the containment free volume. This evaluation should consider the cavity.

magnitude of the containment volume and exhaust rate, the potential for bypass to the environment, the location of exhaust plenums relative to the surface of the reactor cavity, recirculation ventilation systems, and internal walls and floors that impede stream flow between the surface of

CALCULATION NO. DRE02-0036 REV. NO. I PAGE NO. 11

" Table 2: Conformance with RG 1.183 Appendix B (Fuel Handling Accident) ' '-.'

RG- Dresden/Quad-Section -. R Psition '- . Cs tCitiesAnalysis' the reactor cavity and the exhaust plenums.

CALCULATION NO. DRE02-0036 I REV. NO. I lPAGENO. 12

3. ASSUMPTIONS Assumptions and bounding analyzed conditions regarding the fuel handling accident scenarios are provided below.

1. Ref. 8 identified that many different fuel designs were evaluated for design basis Fuel Handling Accident scenarios, showing that GE 7x7 fuel has the most limiting radiological consequences following a design basis FHA. This was verified again as shown in Section 15.7.3.5 of the Dresden UFSAR, Rev. 5 for the following fuel types (table excerpted from the Dresden UFSAR:

Fuel type Fractional Calculated Relative Amount of Activity Radiological Plenum number of Released when compared Consequences Activity per failed fuel to a 7x7*core as a percentage rod compared rods of the values to a 7x 7 rod reported in Table 15.7-8 ATRIUMT%1-9B 49/72 = 0.68 132 (132/111) * (.GS) = 0.81 . 81%,I SPC 9x9-2 49/79 = 0.62 143 (143/111)* (.62) = 0.80 80%/o SPC 9x9.1 49/SO = 0.61 144 (1441111) *(.61) = O.S0 SOo SPC SxS 49163 = O.78 112 (112/111) * (.78) = 0.79 79%

GE SxS 49/63 = 0.78 122 (1221111) (.78) = 0.S6 SG%

GE 7x7 49/49 = 1.0 111 1.0 [100%6 Therefore, the scope of this calculation has been limited to an analysis of the GE 7x7 fuel types.

2. Movement of recently irradiated fuel will not occur less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after the associated reactor shutdown.

3. Fuel bundle peak burnup will not exceed 62 GWD/MTU.

4. For fuel exceeding 54 GWD/MTU the maximum linear heat generation rate will not exceed 6.3 kw/ft average power.

5. The current design basis bounding fuel damage assessment, which is associated with a drop over the reactor, will continue to be used.

6. Spent fuel source terms are based on reactor core source terms in Reference 12.

7. The damaged fuel is assumed to have operated at a peaking factor of 1.7 [Reference 11].

8. Analyzed water depths above damaged fuel are 23 feet and 19 feet. These values correspond to the minimum expected coverage over spent fuel racks, and the Technical Specification 3.7.8 limit, respectively. The latter value provides assurance that analyzed coverage accounts for potential dropped fuel that might be positioned lying over the spent fuel racks.

9. Activity reaching the refuel floor airspace will essentially be all exhausted within two hours.

by using an artificially high exhaust rate. This also provides an allowance for uneven mixing in the refuel floor airspace.

10. The exhaust pathway is the worst case one of through the normal exhaust to the Reactor Building Exhaust Stack. No credit is taken for filtration by the SBGTS, or resulting elevated release through the station chimney.

I CALCULATION NO. DRE02-0036 I REV. NO. I # PAGE NO. 13

11. XIQs for this release point are determined in Reference 13 based on RG 1.194 methodology as implemented by ARCON96 for onsite locations and on RG. 1.145 methodology as implemented by PAVAN for offsite locations.

12. No credit is taken for the operation of the CREFS during the FHA. Conservatively high intake and outflow are considered.

I CALCULATION NO. DRE02-0036 l REV. NO. I PAGE NO. 14 l

4. DESIGN INPUT The design inputs used for this calculation were extracted from extensive review of Dresden Unit 2&3 Licensing documents, UFSAR sections, Dresden 2&3 existing calculations, and regulatory guidance documents. These parameters are summarized in the following table:

Parametcrs Applicable to AST Fuel Handling Accident Dose Considerations for Dresden Station TABLE 2: FHA AST Analvsis AST Value Parameter or Method for Source Documents Dresden Station Bounding Fuel Assembly 7x7 in a 49 pin bundle Calc DREOO-0071 Configuration Analyzed Bounding Fuel Damage 111 pins Calc DREOO-0071 Analyzed Peaking Factor 1.7 NEDC-32868P Allowable Fuel Burnup and RG 1.183, Table 3 non-LOCA gap fractions FHA Radionuclide Inventory Based on Appendix D of GE- GE-NE-A22-00103-64-01, NE-A22-00103-64-01, Task Task Report T0802, Rev. 0, Report T0802, Rev. 0, "Radiation Sources and "Radiation Sources and Fission Fission Products" Products", for the 60 isotopes forming the standard RADTRAD library, with decay to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Gap activities per R.G. 1.183.

Underwater Decontamination Noble Gases: I RG 1.183, and G. Burley, Factor Particulates (cesiums and "Evaluation of Fission Product rubidiums): infinity Release and Transport for Fuel Iodine: Case 1=200, Handling Accident" corresponding to a 23-ft water depth Case 2=135, corresponding to a 19-ft water depth Iodine chemical distribution From RG 1.183 (95% CsI, RG 1.183 instantaneously dissociating in the pool water and re-evolving as elemental iodine, since the pH of the pool water is not justified mechanistically to be above 7; 4.85% elemental; 0.15% organic)

Dose Conversion Factors EPA Federal Guidance Reports EPA Federal Guidance 11 and 12 Reports II and 12 Offsite Dose Limit 6.3 rem TEDE after 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months RG 1.183 Control Room Dose Limit 5 rem TEDE for the duration I OCFR50 App. A, GDC 19

I CALCULATION NO. DRE02-0036 _ REV. NO. I PAGE NO. 15 l TABLE 2: FHA AST Analysis AST Value Parameter or Method for Source Documents Dresden Station of the accident and I OCFR50.67 Secondary Containment Not credited for all fuel with RG 1.183 automatic isolation and one day decay time filtration Mitigation by CREF system Not credited for all fuel with RG 1.183 one day decay time Normal and Emergency Although normal maximum Calc DRE97-0071 Control Room normal fresh flow into the CR is 2000 cfm +

air makeup rate and volume 10%, a Control Room changeover rate of I CR Volume per minute is used for conservatism and to allow for any unfiltered inleakage due to CR envelope maintenance during refueling outages.

Volume 64,000 ft3 (control room proper); 81,000 fi3 (control room emergency zone).

Flow into the CR is therefore assumed to be 64,000 cfm.

(Smaller voluine is used, as the flow rates maximize inhalation doses, and for interior cloud doses, the appropriate volume is the control room proper).

Refuel Floor Normal Approximately 4 air changes Calc DRE97-0071 Ventilation rate and volume per hour and 4,500,000 ft3 (Total Reactor Building Volume)

CR Release Point Basis and Normal RB exhaust stack and Distance to CR 301.8 ft Dispersion Factors 6.44E-04 sec/m3 Calc DRE04-0030, Rev. I 0-2 hr EAB Release Point Basis and Normal RB exhaust stack and Distance to EAB 800 m Dispersion Factors 3

0 - 2 hr 2.51 E-04 sec/n Calc DRE04-0030, Rev. I

I CALCULATION NO. DRE02-0036 I REV. NO. I PAGE NO. 16 TABLE 2: FHA AST Analysis AST Value Parameter or Method for Source Documents Dresden Station LPZ Release Point Basis and Normal RB exhaust stack and Distance to LPZ 8000 m Dispersion Factors 0 - 2 hr 2.63E-05 sec/M 3 Calc DRE04-0030, Rev. I

CALCULATION NO. DRE02-0036 I REV. NO. I PAGE NO. 17 l

5. REFERENCES

1. Dresden Unit 2 & 3, UFSAR, Revision. 5.

2. RG 1.183, 'Alternative Radiological Source Terms For Evaluating Design Basis Accidents At Nuclear Power Reactors", July 2000.

3. NUREGICR-6604, "RADTRAD: A Simplified Model for RADionuclide Transport and Removal And Dose Estimation", 4/1998. Supplement 1, 6/1999. Supplement 2, 10/2002.

4. Federal Guidance Report No. 11, "Limiting Values of radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion", 1988.

5. Federal Guidance Report No. 12, External exposure to Radionuclides in Air, Water, and Soil", 1993.

6. NUREG-1465, "Accident Source Terms for Light-Water Nuclear power Plants", 1995.

7. Not Used

8. Calc. DREOO-0011, Effect of Reduced Pool Water Level on FHA Radiological Consequences", Revision 0.

9. Calculation DREOO-0071, 'Impact of Extended Power Uprate on Site Boundary and Control room Doses for LOCA and Non-LOCA Events", Revision 1.

10. G. Burley, "Evaluation of Fission Product Release and Transport," Staff Technical Paper, 1971.

11. NEDC-32868P, GE14 GESTAR Compliance Document.

12. GE Task Report No. GE-NE-A22-00103-64-01, Rev. 0, Project Task Report: "Dresden and Quad Cities Asset Enhancement Program - Task T0802: Radiation Sources and Fission Products", Dated August 2000.

13. Calculation DRE04-0030, "Atmospheric Dispersion Factors (X/Qs) for Accident Release", Revision 1.

CALCULATION NO. DRE02-0036 I REV. NO. I I PAGE NO. 18 l

6. CALCULATIONS This calculation evaluates the radiological dose to an operator in the Control Room and a person at the EAB and LPZ locations following a design basis FHA involving irradiated fuel that has decayed for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after shutdown. This analysis uses Alternative Source Term assumptions per guidance in RG 1.183.

The RADTRAD v. 3.03 computer code was used for this Dresden 2&3 FHA calculation.

RADTRAD [3] is a simplified model of RADionuclide Transport and Removal And Dose Estimation developed for the NRC and endorsed by the NRC as an acceptable methodology for reanalysis of the radiological consequences of design basis accidents. The technical basis for the RADTRAD code is documented in Section 2 of NUREG/CR-6604. The methodologies significant to this analysis are the dose consequence analysis (NUREG Section 2.3) and the Radioactive Decay Calculations (NUREG Section 2.4). Radioactive decay and daughter products are considered in RADTRAD, with this RADTRAD option turned 'on".

The RADTRAD inputs are summarized below:

A. Compartments

1. Containment - This compartment represents the Reactor Building Air Space, into which fission products leaving the spent fuel pool are released.

a. Compartment type - Other - since it is not the environment or control room.

b. Volume - 4.5E6 ft3 - This is the total Reactor Building Volume. Normal Exhaust rates from the volume are - set at 4 air changes per hour to ensure that all activity is released within the 2-hour period.

c. Source term fraction - 1.0

d. Compartment features - no compartment removal mechanisms selected.

2. Environment

a. Compartment type - Environment

3. Control Room

a. Compartment type - Control Room

b. Volume - 64,000 ft3 - Proper volume.

c. Source term fraction - 0.0

d. Compartment features -none selected B. Transfer Pathways

1. Filtered Flow, Leak to the Environment

a. From Compartment 1 - Containment

b. To Compartment 2 - Environment

c. Transfer mechanism- Filter" selected

d. Filter Efficiency Panel -Flow rate - 300,000 cfm - This is an arbitrary high value that releases 99.97% of the activity from the Reactor Building within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . This corresponds to 4 air changes per hour and is higher than the design flow rate of 220,000 cfm.

e. Filter Efficiency Panel - FHA analyses do not credit SBGTS filtration, and so the efficiency used is 0.

I CALCULATION NO. DRE02-0036 I REV. NO. I PAGE NO. 19 l

f. Active Pathway - Yes

2. Environment to Control Room

a. From Compartment 2 - Environment

b. To Compartment 3 - Control Room

c. Transfer mechanism -"Filter" selected -

d. Filter Efficiency Panel -Flow rate - 64,000 cfm - Artificially high CR intake flowrate of one air change per minute, to conservatively allow for any unfiltered inleakage, for the duration of the accident.

e. Filter Efficiency Panel - Filter efficiency is entered as 0.0% for all chemical forms of iodine.

f. Active Pathway - Yes

3. Control Room to Environment

a. From Compartment 3 - Control Room

b. To Compartment 2 - Environment

c. Transfer mechanism- "Filter" selected -

d. Filter Efficiency Panel -Flow rate - 64,000 cfm -. for the duration of the accident.

e. Filter Efficiency Panel - Filter efficiency is entered as 100.0% iodine chemical for all time periods. This is the exit from the control room to the environment; the filtration prevents a double counting of the iodine release.

f. Active Pathway - Yes C. Dose Locations

1. Exclusion Area Boundary

a. In Compartment 2 - Environment

b. Breathing Rate Default - not checked

c. Z/Q - 2.51 E-04 sec/M 3 - this is the 0-2 hr accident 7/Q for Dresden 2&3 Reactor Building Exhaust Stack (See Section 5, Reference 13). This value is entered from time 0 to the end of the accident.

d. Breathing Rate - 3.47E-04 m3/sec - this is the Reg. Guide 1.183 specified breathing rate, with the traditional three digit accuracy (RADTRAD default).

2. Low Population Zone

a. In Compartment 2- Environment

b. Breathing Rate Default - not checked

c. x/Q - 2.63E-05 sec/M 3 - this is the 0-2 hr accident X/Q for Dresden 2&3 Reactor Building Exhaust Stack (See Section 5, Reference 13). This value is entered from time 0 to the end of the accident.

d. Breathing Rate - 3.47E-04 m3 /sec - this is the Reg. Guide 1.183 specified breathing rate, with the traditional three digit accuracy (RADTRAD default).

3. Control Room

a. In Compartment 3 - Control Room

b. Breathing Rate - 3.47E-04 m3 /sec.

c. x/Q - 6.44E-04 sec/i 3 - this is the 0-2 hr accident X/Q for Dresden 2&3 Reactor Building Exhaust Stack (See Section 5, Reference 13). This value is entered from time 0 to the end of the accident.

d. Breathing Rate - 3.47E-04 m3 /sec - - this is the Reg. Guide 1.183 specified breathing rate, with the traditional three digit accuracy (RADTRAD default).

CALCULATION NO. DRE02-0036 I REV. NO. I I PAGE NO.20 _

e. Occupancy Factor - 1.0- this is the RG 1.183 value for the first day.

D. Source Term and Release Fraction Treatment

a. The "dres qdc source terms for fha.nif "file [Attachment C] reflects the Dresden core activities with the 1-131 value multiplied by 1.6 and the Kr-85 value multiplied by 2.0.

These changes are made so that the RG 1.183, Table 3 differentiation in release fraction can be made.

b. The power level of 16.05 MW is per section 2.1 above and reflects the fraction of the core damaged and the radial peaking factor applied to that fuel.

c. The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months delay time reflects the minimum time after shutdown that fuel movement is expected.

d. The RADTRAD radioactive decay and daughter products option is turned 'on".

e. The files T dresden-quad cities ast fha (df135 19ft).rft "[Attachment E] and Idresden-quad cities ast fha (df200 23ft).rft "[Attachment D] are designed to reflect gap activity fractions per RG 1.183, Table 3, with the adjustment describe for the unir file described above.

E. Dose Conversion Factors The default FGR-11 and FGR-12 dose conversion factors provided with RADTRAD are used.

CALCULATION NO. DRE02-0036 REV. NO. I I PAGE NO.21

7.

SUMMARY

AND CONCLUSIONS The RADTRAD code was used to examine the effect of the alternative source term release on offsite and CR doses. Shown below are the results, as well as the dose acceptance criteria. __-___

The two cases analyzed are that of the worst case drop over the core with a nominally expected minimum water level at 23 ft. over the damage fuel, and Technical Specification water level at 19 ft.

Location Case I Case 2 (23 feet water coverage) (19 feet water coverage)

Dose (rem TEDE) Dose (rem TEDE)

LIMITS CR 5.0; EAB&LPZ 6.3 CR 5.0; EAB&LPZ 6.3 EAB 0.709 0.967 LPZ 0.074 .0.101 CR 1.35 1.99 These results indicated that the calculated consequences of a design basis Fuel Handling Accident will be within regulatory limits without the requirement for release filtration by SBGTS or elevated release through the station chimney. Furthermore, Control Room emergency filtration is not required to maintain operator doses within regulatory limits.

I CALCULATION NO. DREO2-0036 I REV. NO. I PAGE NO.22 .

8. OWNER'S ACCEPTANCE REVIEW CHECKLIST FOR EXTERNAL DESIGN ANALYSIS DESIGN ANALYSIS NO. DRE02-0036 REV: I Yes No N/A

1. Do assumptions have sufficient rationale? 0:

2. Are assumptions compatible with the way the plant is operated and with the licensing basis? 01 tI' ' El

3. Do the design inputs have sufficient rationale? E/ 01

4. Are design inputs correct and reasonable? 0 0:

5 Are design inputs compatible with the way the plant is operated and with the El licensing basis? 0I 0]

El

6. Are Engineering Judgments clearly documented and justified? 0o 0:

7. Are Engineering Judgments compatible with the way the plant is operated and with the licensing basis? 0o 01 Do the results and conclusions satisfy the purpose and objective of the Design

8. Analysis?

Are the results and conclusions compatible with the way the plant is operated 19/ Df o and with the licensing basis? 0 01

10. Does the Design Analysis include the applicable design basis documentation?

I1 Have any limitations on the use of the results been identified and transmitted to the appropriate organizations? 0 00 V,

12. Are there any unverified assumptions? 0R Do all unverified assumptions have a tracking and closure mechanism in 13 place? 0 E

14. Have all affected design analyses been documented on the Affected 13 , Opf 14 Documents List (ADL) for the associated Configuration Change?

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

Have vendor supporting technical documents and references (including GE

16. DRFs) been reviewed when necessary? *0 0 EXELON REVIEWER: <, DATE::gia

Dresden 7x7_1dayNoFilters (DF200 23 ft)

RADTRAD Version 3.03 (Spring 2001) run on 8/12/2005 at 8:55:19 File information Plant file = P:\Users\Nuc\Exelon EOC\Discipline Files\Process\AST\Dresden &

Quad Cities AST\DRE FHA\Dresden_7x7_iday_NoFilters (DR200 23 ft)(1CR airchange per min).psf Inventory file = p:\users\nuc\exelon eoc\discipline files\process\ast\dresden &

quad cities ast\dre fha\dres qdc source terms for fha.nif Release file = p:\users\nuc\exelon eoc\discipline files\process\ast\dresden &

quad cities ast\dre fha\dresden-quad cities ast fha df200.rft Dose Conversion file = c:\program files\radtrad3-03\defaults\fgrll&12.inp 1U #### ##iiff ##### #II 1 # I I I I # II I I

I I I I I I I. #

I # II I I I I # I II I I #111 1 # I I Radtrad 3.03 4/15/2001 DRE-FHA RBStack to CR Intake and Grnd Release to EAB & LPZ 1 day Delay (DF200 23ft)(CR1 airchange per min)

Nuclide'Inventory File:

p:\users\nuc\exelon eoc\discipline files\process\ast\dresden & quad cities ast\dre fha\dres qdc source terms for fha.nif Plant Power Level:

1.6050E+01 Compartments:

3 Compartment 1:

Containment 3

4.5000E+06 0

0 0

Compartment 2:

Environment 2

0.000OE+00 0

0 0

DRE02-0036, Rev. l, Attachment A, Page Al of A15

Dresden 7x71 dayNoFilters (DF200 23 ft) 0 0

Compartment 3:

Control Room 1

6.4000E+04 0

0 0

Pathways:

3.

Pathway 1:

Leak to Environment 1

2 2

Pathway 2:

Environment to Control Room 2

3 2

Pathway 3:

Control Room to Environment Exhaust 3

2 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

ACCEPT\TESTI.PMF Source Term:

1 1 1.0000E+00 c:\program files\radtrad3-03\defaults\fgrll&12.inp p:\users\nuc\exelon eoc\discipline files\process\ast\dresden & quad cities ast\dre fha\dresden-quad cities ast fha df200.rft 2.4000E+01 1

0.OOOOE+00 5.7000E-01 4.3000E-01 *1.0000E+00 Overlying Pool:

0 o.OOOOE+00 0

0 0

0 Compartments:

3 Compartment 1:

0 1

0 0

0 .

DRE02-0036, Rev. 1, Attachment A, Page A2 of A15

Dresden 7x71 dayNoFilters (DF200 23 ft) 0 0

0 0

Compartment 2:

0 1

0 0

0 Compartment 3:

0 1

0 0

Pathways:

3 Pathway 1:

0 0

0 I

1 2.400OOE+01 3.OOOOE+05 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0

0 0

0 Pathway 2:

0 0

0 1

1

2. 4000E+01 6.4000E+04 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0

0 0

0 0*

0 Pathway 3:-

DRE02-0036, Rev. 1, Attachment A, Page A3 of Al5

Dresden 7x7 IdayNoFiiters (DF200 23 ft) 0 0

0 0

0 1

1 2 .4000E+01 6.4000E+04 1.0000E'+02 l.OOOOE+02 1.OOOOE+02 0

0 0

0 Dose Locations:

3 Location 1:

Exclusion Area Bndry 2

1 2

2.4000E+01 2.5100E-04 2.6000E+01 O.OOOOE+00 1

2 2.4000E+01 3.4700E-04

2. 6000E+01 O.OOOOE+00 0

Location 2:

Low Population Zone 2

1 2

2. 4000E+01 2.6300E-05 2.6000E+01 O.OOOOE+00 1

2 2.4000E+01 3.4700E-04 2.6000E+01 O.OOOOE+00 0

Location 3:

Control Room 3

0 1

2 2.4000E+01 3.4700E-04 4.8000E+01 O.OOOOE+00 1

2 2.4000E+01 l.OOOOE+00 4.8000E+01 O.OOOOE+00 Effective Volume Location:

1 2-2.4000E+01 6.4400E-04 2.6000E+01 O.OOOOE+00 DRE02-0036, Rev. 1, Attachment A, Page A4 of A 15

Dresden 7x7_ dayNoFilters (DF200 23 11)

Simulation Parameters:

5 2.4000E+01 1.OOOOE-03 2.4010E+01 1.0000E-02 2.4100E+01 1.OOOOE-01 2.6000E+01 1.OOOOE+00 4.8000E+01 O.OOOOE+00 Output Filename:

P:\Users\Nuc\Exelon EOC\Discipline Files\Process\AST\Dresden & Quad Cities AST\DRE FHA\Dresden_7x7_lday_NoFilters (DR200 23 ft)(lCR airchange per min).oO 1

1 0

0 End of Scenario File DRE02-0036, Rev. I, Attachment A, Page A5 of Al5

Dresden 7x71 dayNoFilters (DF200 23 ft)

DRE02-0036, Rev. 1,Attachment A, Page A6 of A15

Dresden 7x7 1dayNoFilters (DF200 23 ft)

RADTRAD Version 3.03 (Spring 2001) run on 8/12/2005 at 8:55:19 Plant Description Number of Nuclides = 60 Inventory Power = 1.0000E+00 MWtl Plant Power Level = 1.6050E+01 MWth Number of compartments .= 3 Compartment information Compartment number 1 (Source term fraction = l.OOOOE+00 Name: Containment Compartment volume = 4.5000E+06 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 1 Exit Pathway Number 1: Leak to Environment Compartment number 2 Name: Environment Compartment type is Environment Pathways into and out of compartment 2 Inlet Pathway Number 1: Leak to Environment Inlet Pathway Number 3: Control Room to Environment Exhaust Exit Pathway Number 2: Environment to Control Room CompartAfent number 3 Name: Control Room Compartment volume = 6.4000E+04 (Cubic feet)

Compartment type is Control Room Pathways into and out of compartment 3 Inlet Pathway Number 2: Environment to Control Room Exit Pathway Number 3: Control Room to Environment Exhaust Total number of pathways = 3 DRE02-0036, Rev. 1, Attachment A, Page A7 of Al5

Dresden 7x7_1 dayNoFilters (DF200 23 fl)

RADTRAD Version 3.03 (Spring 2001) run on 8/12/2005 at 8:55:19 Scenario Description Time between shutdown and first release = 2.4000E+01 (Hours)

Radioactive Decay is enabled Calculation of Daughters is enabled Release Fractions and Timings GAP EARLY IN-VESSEL LATE RELEASE RELEASE MASS 0.000001 hr 0.0000 hrs 0.0000 hrs (gm)

NOBLES 5.OOOOE-02 0.OOOOE+00 0.OOOOE+00 2.021E+00 IODINE 2.5000E-04 0.OOOOE+00 0.000OE+00 1.682E-03 CESIUM 0.OOOOE+00 0.OOOOE+00 0.000OE+00 0.00OE+00 TELLURIUM 0.OOOOE+00 0.OOOOE+00 0.000OE+00 0.00OE+00 STRONTIUM 0.OOOOE+00 0.OOOOE+00 0.000OE+00 0.OOOE+00 BARIUM 0.OOOOE+00 0.OOOOE+00 0.000OE+00 0.000E+00 RUTHENIUM 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.000E+00 CERIUM 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOE+00 LANTHANUM 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 Inventory Power = 16. MWt Nuclide Group Specific half Whole Body Inhaled Inhaled Name Inventory life DCF Thyroid Effective (Ci/MWt) (S) (Sv-m3/Bq-s) (Sv/Bq) (Sv/Bq)

Kr-85 1 8.729E+02 3.383E+08 1.190E-16 0.00OE+00 0.OOOE+00 Kr-85m 1 6.772E+03 1.613E+04 7.480E-15 0.OOOE+00 0.OOOE+00 Kr-87 1 1.291E+04 4.578E+03 4.120E-14 0.00OE+00 0.OOOE+00 Kr-88 1 1.815E+04 1.022E+04 1.020E-13 0.00OE+00 0.OOOE+00 I-131 2 4.337E+04 6. 947E+05 1.820E-14 2.920E-07 8.890E-09 I-132 2 3.914E+04 8.280E+03 1.120E-13 1.740E-09 1.030E-10 I-133 2 5.501E+04 7.488E+04 2.940E-14 4.860E-08 1.580E-09 I-134 2 6.035E+04 3.156E+03 1.300E-13 2.880E-10 3.550E-11 I-135 2 5.157E+04 2.380E+04 8.294E-14 8.460E-09 3.320E-10 Xe-133 1 5.282E+04 4.532E+05 .1.560E-15 0.OOOE+00 0.000E+00 Xe-135 1 2.144E+04 3.272E+04 1.190E-14 0.OOOE+00 0.000E+00 Nuclide Daughter Fraction Daughter Fraction Daughter Fraction Kr-85m Kr-85 0.21 none 0.00 none 0.00 Kr-87 Rb-87 1.00 none 0.00 none 0.00 Kr-88 Rb-88 1.00 none 0.00 none 0.00 Sr-90 Y-90. 1.00 none 0.00 none 0.00 Sr-91 Y-91m 0.58 Y-91 0.42 none 0.00 Sr-92 Y-92 1.'00 none 0.00 none 0.00 Y-93 Zr-93 1.00 none 0.00 none 0.00.

Zr-95 Nb-95m 0.01 Nb-95 0.99 none 0.00 Zr-97 Nb-97m 0.95 Nb-97 0.05 none 0.00 Mo-99 Tc-99m 0.88 Tc-99 0.12 none 0.00 Tc-99m Tc-99 1.00 none 0.00 none 0.00 DRE02-0036, Rev. 1, Attachment A, Page A8 of A15

Dresden 7x7_1dayNoFilters (DF200 23 fl)

Ru-103 Rh-103m 1.00 none 0.00 none 0.00 Ru-105 Rh-105 1.00 none 0.00 none 0.00 Ru-106 Rh-106 1.00 none 0.00 none 0.00 Sb-127 Te-127m 0.18 Te-127 0.82 none 0.00 Sb-129 Te-129m 0.22 Te-129 0.77 none 0.00 Te-127m Te-127 0.98 none 0.00 none 0.00 Te-129 I-129 1.00 none 0.00 none 0.00 Te-129m Te-129 0.65 I-129 0.35 none 0.00 Te-131m Te-131 0.22 I-131 0.78 none 0.00 Te-132 I-132 1.00 rione 0.00 none 0.00 I-131 Xe-131m 0.01 none 0.00 none 0.00 I-133 Xe-133m 0.03 Xe-133 0.97 none 0.00 1-135 Xe-135m 0.15 Xe-135 0.85 none 0.00 Xe-135 Cs-135 ,1.00 none 0.00 none 0.00 Cs-137 Ba-137m 0.95 none 0.00 none 0.00 Ba-140 La-140 1.00 none 0.00 none 0.00 La-141 Ce-141 '1.00 none 0.00 none 0.00' Ce-143 Pr-143 1.00 none 0.00 none 0.00 Ce-144 Pr-144m 0.02 Pr-144 0.98 none 0.00 Nd-147 Pm-147 1.00 none 0.00 none 0.00 Np-239 Pu-239 1.00 none 0.00 none 0.00 Pu-238 U-234 1.00 none 0.00 none 0.00 Pu-239 U-235 1.00 none 0.00 none O.00 Pu-240 U-236 1.00 none 0.00 none 0.00 Pu-241 U-237 0.00 Am-241 1.00 none 0.00 Am-241 Np-237 1.00 none 0.00 none 0.00 Cm-242 Pu-238 1.00 none 0.00 none 0.00 Cm-244 Pu-240 1.00 none 0.00 none 0.00 Iodine fractions Aerosol =

0.000OE+00 Elemental 5.7000E-01 Organic 4.3000E-01 COMPARTMENT DATA Compartment number 1: Containment Compartment number 2: Environment Compartment number 3: Control Room PATHWAY DATA Pathway number 1: Leak to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filtezr Efficiencies s(%)

(cfm) Aerosol Elemental Organic .

2.4000E+01 3.OOOOE+05 0.OOOOE+00 0.OOOOE+00 0.000OE+00 Pathway number 2: Environment to Control Room Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

DRE02-0036, Rev. 1, Attachment A, Page A9 of A 15

Dresden 7x7 ldayNoFilters (DF200 23 fl)

(cfm) Aerosol Elemental Organic 2.4000E+01 6.4000E+04 0.0000E+00 0.0000E+00 O.0000E+00 Pathway number 3: Control Room to Environment Exhaust Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 2.4000E+01 6.4000E+04 1.OOOOE+02 1.0000E+02 1.OOOOE+02 LOCATION DATA Location Exclusion Area Bndry is in compartment 2 Location X/Q Data Time (hr) X/Q (s

ma-3) 2.4000E+01 2.5100E-04 2.6000E+0.l 0.000OE+00 Location Breathing Rate Data Time (hr) Breathing Rate (m^3

sec^-l) 2.4000E+01 3.4700E-04 2.6000E+01 0.OOOOE+00 Location Low Population Zone is in compartment 2 Location X/Q Data Time (hr) X/Q (s

m^-3) 2.4000E+01 2.6300E-05 2.6000E+01 0.00OOE+00 Location Breathing Rate Data Time (hr) Breathing Rate (m^3

sec^-l) 2.4000E+01 3.4700E-04 2.6000E+01 0.0000E+00 Location Control Room is in compartment 3 Location X/Q Data Time (hr) X/Q (s

m^-3) 2.4000E+01 6.4400E-04 2.6000E+01 0.0000E+00 Location Breathing Rate Data Time (hr) Breathing Rate (m^3

sec'-l) 2.4000E+01 3.4700E-04 4.8000E+01 0.OOOOE+00 Location Occupancy Factor Data Time (hr) Occupancy Factor 2.4000E+01 1.0000E+00 4.8000E+01 0.0000E+00 USER SPECIFIED TIME STEP DATA - SUPPLEMENTAL TIME STEPS Time Time step O.OOOOE+00 1.0000E-03

1.0000E-02 1.0000E-02 1.OOOOE-01 1.0000E-01 2.0000E+00 1.OOOOE+00 DRE02-0036, Rev. 1, Attachment A, Page A10 of A15

Dresden 7x7_I day NoFilters (DF200 23 ft) 2.4000E+O1 O.OOOOE+00 DRE02-0036, Rev. 1, Attachment A, Page All of A15

Dresden 7x7_IdayNoFilters (DF200 23 ft)

RADTRAD Version 3.03 (Spring 2001) run on 8/12/2005 at 8:55:19

{#$# # # .####$##

$ # # I # # #

# I I 'I #

I # #I # # $

Dose Output Exclusion Area Bndry Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.9513E-07 3.3534E-05 1.4275E-06 Accumulated dose (rem) 3.9513E-07 .3.3534E-05 1.4275E Low Population Zone Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 4.1402E-08 3.5138E-06 1.4958E-07 Accumulated dose (rem) 4.1402E-08 3.5138E-06 1.4958E-07 Control Room Doses:

Time (h) - 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.0920E-12 2.5812E-09 8.0555E-11 Accumulated dose (rem) 1.0920E-12 2.5812E-09 8.0555E-11 Exclusion Area Bndry Doses:

Time (h) = 26.0000 Whole Body Thyroid

TEDE Delta dose (rem) 1.9449E-01 1. 6733E+01 7.0949E-01 Accumulated dose (rem) 1.9449E-01 1. 6733E+01 7.0949E-01 Low Population Zone Doses:

Time (h) = 26.0000 Whole Body Thyroid TEDE Delta dose (rem). 2.0379E-02 1.7533E+00 7.4341E-02 Accumulated dose (rem) 2.0379E-02 1.7533E+00 7.4341E-02 Control Room Doses:

Time (h) = 26.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.8042E-02 4.3273E+01 1.3498E+00 Accumulated dose (rem) 1.8042E-02 4.3273E+01 1.3498E+00 DRE02-0036, Rev. 1, Attachment A, Page A12 of A15

Dresden 7x7_1day NoFilters (DF200 23 ft)

Exclusion Area Bndry Doses:

Time (h) = 48.0000 Whole Body Thyroid TEDE Delta dose (rem) O. OOOOE+00 0.OOOOE+00 O O.OOOOE+00 Accumulated dose (rem) 1.9449E-0l 1. 6733E+0l 7.0949E-01 Low Population Zone Doses:

Time (h) = 48.0000 Whole Body Thyroid TEDE Delta dose (rem) O. OOOOE+00 O. OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 2.0379E-02 1.7533E+00 7.4341E-02 Control' Room Doses:

Time (h) = 48.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.1485E-06 3.0616E-03 9.5188E-05 Accumulated dose (rem) 1.8043E-02 4.3276E+01 1.3499E+00 159 1-131 Summary Containment Environment Control Room Time (hr) I-131 (Curies) I-131 (Curies) I-131 (Curies) 24.000 1.6041E+02 3.2083E-04 6.2406E-06 24.400 3.2341E+01 1.2794E+02 4.4935E-02 24.700 9.7304E+00 1.5053E+02 1.3519E-02 25.000 2.9276E+00 1.5733E+02 4.0676E-03 25.300 8.8082E-01 1.5937E+02 1.2238E-03 25.600 2.6501E-Ol 1.5998E+02 3.6821E-04

25. 900 7.9734E-02 1.6017E+02 1.1078E-04

26. 000 5.3428E-02 1.6020E+02 7.4234E-05 26.300 1.6075E-02 1.6023E+02 1.1292E-12

26. 600 4.8365E-03 1.6024E+02 1.7178E-20

26. 900 1.4551E-03 1.6025E+02 2.6130E-28 27.200 4.3781E-04 1.6025E+02 3.9749E-36 27.500 1.3172E-04 1.6025E+02 6.0465E-44

27. 800 3.9632E-05 1.6025E+02 9.1978E-52 28.100 1.1924E-05 1.6025E+02 1.3992E-59

28. 400 3.5876E-06 1.6025E+02 2.1284E-67 28.700 1.0794E-06 1.6025E+02 3.2376E-75

29. 000 3.2475E-07 1.6025E+02 4.9250E-83 29.300 9.7709E-08 1.6025E+02 7.4919E-91

29. 600 2.9398E-08 1.6025E+02 1.1396E-98

29. 900 8.8449E-09 1.6025E+02 1.7336-106 30.200 2.6612E-09 1.6025E+02 2.6371-114 30.500 8.0066E-10 1.6025E+02 4.0116-122 30.800 2.4089E-10 1.6025E+02 6.1023-130 31.100 7.2478E-11 1.6025E+02 9.2827-138 31.400 2.1806E-11 1.6025E+02 1.4121-145 31.700 6.5609E-12 1.6025E+02 2.1480-153 32.000 1.9740E-12 1.6025E+02 3.2675-161 32.300 5.9391E-13 1.6025E+02 4.9705-169

32. 600 1.7869E-13 1.6025E+02 7.5610-177 DRE02-0036, Rev. 1, Attachment A, Page A13 of A15

Dresden 7x7_IdayNoFilters (DF200 23 fi)

32. 900 5.3762E-14 1.6025E+02 1.1502-184 33.200 1.6175E-14 1.6025E+02 1.7496-192 33.500 4.8667E-15 1.6025E+02 2.6615-200

33. 800 1.4642E-15 1.6025E+02 4.0486-208 34.100 4.4055E-16 1.6025E+02 6.1586-216 34.400 1.3255E-16 1.6025E+02 9.3683-224 48.000 2. 9891E-40 1.6025E+02 O.OOOOE+00 Cumulative Dose Summary Exclusion Area Bndry Low Population Zone Control Room Time Thyroid TEDE Thyroid TEDE Thyroid TEDE (hr) (rem) (rem) (rem) (rem) (rem) (rem) 24.000 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 24.400 1.3369E+01 5.6784E-01 1.4009E+00 5. 9499E-02 3.3903E+0l 1.0578E+00 24.700 1.5726E+0l 6.6730E-0l 1.6478E+00 6.9920E-02 4 .0468E+01 1.2624E+00

25. 000 1. 6435E+0l 6. 9703E-01 1.7220E+00 7.3036E-02 4.2441E+01 1.3239E+00 25.300 1. 6647E+01 7. 0592E-01 1.7443E+00 7.3967E-02 4 .3034E+01 1.3424E+00

25. 600 1.6711E+01 7.0858E-0l 1.7510E+00 7..4246E-02 4.3212E+0l 1.3479E+00

25. 900 1. 6731E+0l 7.0938E-01 1.7530E+00 7.4329E-02 4.3265E+01 1.3496E+00

26. 000 1. 6733E+01 7.0949E-0l 1.7533E+00 7.4341E-02 4.3273E+01 1.3498E+00 26.300 1. 6733E+01 7.0949E-01 1.7533E+00 7.4341E-02 4.3276E+0l 1.3499E+00

26. 600 1. 6733E+01 7.0949E-01 1.7533E+00 7.4341E-02 4.3276E+01 1.3499E+00

26. 900 1. 6733E+01 7.0949E-01 1.7533E+00 7.4341E-02 4 .3276E+01 1.3499E+00 27.200 1.6733E+01 7 .0949E-01 1.7533E+00 7.4341E-02 4.3276E+01 1.3499E+00 27.500 1. 6733E+01 7.0949E-0l 1.7533E+00 7.4341E-02 4.3276E+01 1.3499E+00

27. 800 1. 6733E+01 7.0949E-01 1.7533E+00 7.4341E-02 4 .3276E+01 1.3499E+00 28.100 1.6733E+01 7.0949E-01 1.7533E+00 7.4341E-02 4.3276E+01 1.3499E+00 28.400 1.6733E+01 7.0949E-01 1.7533E+00 7.4341E-02 4.3276E+0l 1.3499E+00 28.700 1. 6733E+01 7.0949E-0l 1.7533E+00 7.4341E-02 4.3276E+01 1.3499E+00

29. 000 1. 6733E+01 7.0949E-0l 1.7533E+00 7.4341E-02 4.3276E+01 1.3499E+00 29.300 1.6733E+01 7.0949E-01 1.7533E+00 7.4341E-02 4.3276E+01 1.3499E+00

29. 600 1. 6733E+0l 7.0949E-0l 1.7533E+00 7.4341E-02 4.3276E+01 1.3499E+00 29.900 1. 6733E+0l 7.0949E-0l 1.7533E+00 7.4341E-02 4.3276E+0l 1.3499E+00 30.200 1. 6733E+01 7.0949E-01 1.7533E+00 7.4341E-02 4.3276E+01 1.3499E+00 30.500 1. 6733E+01 7.0949E-01 1.7533E+00 7.4341E-02 4.3276E+0l 1.3499E+00 30.800 1. 6733E+01 7.0949E-01 1.7533E+00 7.4341E-02 4 .3276E+01 1.3499E+00 31.100 1. 6733E+01 7.0949E-01 1.7533E+00 7.4341E-02 4.3276E+O1 1.3499E+00 31.400 1. 6733E+01 7.0949E-01 1.7533E+00 7.4341E-02 4.3276E+01 1.3499E+00 31.700 1.6733E+0l 7 .0949E-01 1.7533E+00 7.4341E-02 4.3276E+01 1.3499E+00 32.000 1.6733E+01 7.0949E-01 1.7533E+00 7.4341E-02 4 .3276E+01 1.3499E+00

32. 300 1.6733E+01 7.0949E-01 1.7533E+00 7.4341E-02 4.3276E+01 1.3499E+00 32.600 1.6733E+01 7.0949E-0l 1.7533E+00 7.4341E-02 4.3276E+01 1.3499E+00 32.900 1. 6733E+01 7.0949E-01 1.7533E+00 7.4341E-02 4.3276E+01 1.3499E+00 33.200 1. 6733E+01 7.0949E-01 1.7533E+00 7.4341E-02 4.3276E+01 1.3499E+00 33.500 1.6733E+01 7.0949E-01 1.7533E+00 7.4341E-02 4.3276E+01 1.3499E+00

33. 800 1.6733E+0l 7.0949E-01 1.7533E+00 7.4341E-02 4.3276E+01 1.3499E+00 34.100 1.6733E+0l 7.0949E-0l 1.7533E+00 7.4341E-02 4.3276E+0l 1.3499E+00 34.400 1.6733E+Ol 7.0949E-0l 1.7533E+00 7.4341E-02 4.3276E+01 1.3499E+00

48. 000 1. 6733E+01 7.0949E-01 1.7533E+00 7.4341E-02 4.3276E+01 1.3499E+00 Worst Two-Hour Doses DRE02-0036, Rev. 1, Attachment A, Page A 14 of A 15

Dresden 7x7_1 day NoFilters (DF200 23 ft)

Exclusion Area Bndry Time Whole Body Thyroid TEDE (hr) (rem) (rem) (rem) 24.0 .1.9449E-01 1. 6733E+01 7.0949E-01 DRE02-0036, Rev. 1, Attachment A, Page A15 of Al5

QDC 7x7IdayNoFilter (DF135 19 ft)

RADTRAD Version 3.03 (Spring 2001) run on 8/12/2005 at 8:49:40 File information Plant file P:\Users\Nuc\Exelon EOC\Discipline Files\Process\AST\Dresden &

Quad Cities AST\DRE FHA\Dresden_7x7_lday_NoFilters (DF135 19-ft)(1CR airchange per min).psf Inventory file p:\users\nuc\exelon eoc\discipline files\process\ast\dresden &

quad cities ast\dre fha\dres qdc source terms for fha.nif Release file = p:\users\nuc\exelon eoc\discipline files\process\ast\dresden &

quad cities ast\dre fha\dresden-qpad cities ast fha (df135 l9ft).rft Dose Conversion file = c:\program files\radtrad3-03\defaults\fgrll&12.inp inn un nun I # U#I4# #

u # ## I $ #

I # #I# I #

1111 #### #### # # I I#### #

u # # # I. I I # # # ## #

I #### # # # # ####

Radtrad 3.03 4/15/2001 DRE-FHA RBStack to CR Intake and Grnd Release to EAB & LPZ 1 day Delay (DF135 l9ft) (1CR airchange per min)

Nuclide'Inventory File:

p:\users\nuc\exelon eoc\discipline files\process\ast\dresden & quad cities ast\dre fha\dres qdc source terms for fha.nif Plant Power Level:

1.6050E+01 Compartments:

3 Compartment 1:

Containment 3

4.5000E+06 0

0 0

Compartment 2:

Environment 2

0.000OE+00 0

0 0

DRE02-0036, Rev. 1,Attachment B, Page BI of B15

QDC 7x7_IdayNoFilter (DF135 19 ft) 0 0

Compartment 3:

Control Room 1

6.4000E+04 0

0 0

Pathways:

3 Pathway 1:

Leak to Environment 2

2 Pathway 2:

Environment to Control Room 2

3.

2 Pathway 3:

Control Room to Environment Exhaust 3

2 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

ACCEPT\TESTn. PMF Source Term:

1 1 1.OOOOE+00 c:\program files\radtrad3-03\defaults\fgrll&12.inp p:\users\nuc\exelon eoc\discipline files\process\ast\dresden & quad cities ast\dre fha\dresden-quad cities ast fha (dfl35 19ft).rft 2.4000E+01 1

0.0000E+00 8.0000E-01 2.OOOOE-01 1.0000E+00 Overlying Pool:

0 0.000OE+00 0

0 0

0 Compartments:

3 Compartment 1:

0 1

0 0

0 DRE02-0036, Rev. 1, Attachment B, Page B2 of B I5

QDC 7x7 ldayNoFilter (DF135 19 ft) 0 0

0 0

Compartment 2:

0 1

0 0

Compartment 3:

0 1

0 0

0 Pathways:

3 Pathway 1:

.0 0

0 0

1 2.4O000E+01 3.00OOE+05 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0

0 0

0 Pathway 2:

0 0

0 1

1

2. 4000E+01 6.4000E+04 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0

0 0

0 Pathway 3:

DRE02-0036, Rev. 1, Attachment B, Page B3 of B15

QDC 7x7lIday_:NoFilter (DF135 19 ft) 0 0

0 0

0 o2.4000E+01 6.4000E+04 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 0

0 0

Dose Locations:

3 Location 1:

Exclusion Area Bndry 2

1 2

2.4000E+01 2.5100E-04 2.6000E+01 O.OOOOE+00 1

2 2.4000E+01 3.4700E-04

2. 6000E+01 O.OOOOE+00 0

Location 2:

Low Population Zone 2

1 2

2.4000E+01 2.6300E-05

2. 6000E+01 O.OOOOE+00 1

2 2.4000E+01 3.4700E-04 2.6000E+01 O.OOOOE+00 0

Location 3:

Control Room 3

0 1

2 2.4000E+01 3.4700E-04 4.8000E+01 O.OOOOE+00 1

2 2.4000E+01 l.OOOOE+00 4.8000E+01 O.OOOOE+00 Effective Volume Location:

1 2

2.4000E+01 6.4400E-04 2.6000E+01 O.OOOOE+00

/ DRE02-0036, Rev. 1, Attachment B, Page B4 of B 15

QDC7x70IdayNoFilter (DF135 19 ft)

Simulation Parameters:

5 2.4000E+01 1.OOOOE-03 2.4010E+01 1.OOOOE-02 2.4100E+01 1.0000E-01 2.6000E+01 1.OOOOE+00 4.8000E+01 0.OOOOE+00 Output Filename:

P:\Users\Nuc\Exelon EOC\Discipline Files\Process\AST\Dresden & Quad Cities AST\DRE FHA\Dresden_7x7_lday_NoFilters (DF135 19 ft)(1CR airchange per min).oO 1

1 1

0 0

End of Scenario File DRE02-0036, Rev. 1, Attachment B, Page B5 of B15

QDC7x70Iday NoFilter (DF135 19 ft)

DRE02-0036, Rev. 1, Attachment B, Page B6 of B15

QDC 7x7l1dayNoFilter (DF135 19 ft)

RADTRAD Version 3.03 (Spring 2001) run on 8/12/2005 at 8:49:40 Plant Description Number of Nuclides = 60 Inventory Power 1.OOOOE+00 MWth Plant.Power Level = 1.6050E+01 MWth Number of compartments = 3 Compartment information Compartment number 1 (Source term fraction = 1.OOOOE+00 Name: Containment Compartment volume = 4.5000E+06 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 1 Exit Pathway Number 1: Leak to Environment Compartment number 2 Name: Environment Compartment type is Environment Pathways into and out of compartment 2 Inlet Pathway Number 1: Leak to Environment Inlet Pathway Number 3: Control Room to Environment Exhaust Exit Pathway Number 2: Environment to Control Room Compartment number 3 Name: Control Room Compartment volume = 6.4000E+04 (Cubic feet)

Compartment type is Control Room Pathways into and out of compartment 3 Inlet Pathway Number 2: Environment to Control Room Exit Pathway Number 3: Control Room to Environment Exhaust Total number of pathways = 3 DRE02-0036, Rev. 1, Attachment B, Page B7 of B15

QDC7x7_ldayNoFilter(DF135 19 ft)

RADTRAD Version 3.03 (Spring 2001) run on 8/12/2005 at 8:49:40 Scenario Description Time between shutdown and first release 2.4000E+01 (Hours)

Radioactive Decay is enabled Calculation.of Daughters is enabled Release Fractions and Timings GAP EARLY IN-VESSEL LATE RELEASE RELEASE MASS 0.000001 hr 0.0000 hrs

0.0000 hrs -(gm)

NOBLES 5.OOOOE-02 0.OOOOE+00 0.000OE+00 2.021E+00 IODINE 3.7037E-04 0.OOOOE+00 0.000OE+00 2.491E-03 CESIUM 0.OOOOE+00 0.OOOOE+00 0.000OE+00 0.OOOE+00 TELLURIUM 0.OOOOE+00 0.OOOOE+00 0.000OE+00 0.000E+00 STRONTIUM 0.OOOOE+00 0.OOOOE+00 0.00O0E+00 0.00OE+00 BARIUM 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.00OE+00 RUTHENIUM 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.00OE+00 CERIUM 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 LANTHANUM 0.OOOOE+00 0.00O0E+00 0.00O0E+00 0.00OE+00 Inventory.Power = 16. MWt Nuclide Group Specific half Whole Body Inhaled Inhaled Name Inventory life *DCF Thyroid Effective (Ci/MWt) (s) (Sv-m3/Bq-s) (Sv/Bq) (Sv/Bq)

Kr-85 1 8.729E+02 3.383E+08 1.190E-16 0.00OE+00 0.OOOE+00 Kr-85m' 1 6.772E+03 1.613E+04 7.480E-15 0.OOOE+00 0.OOOE+00.

Kr-87 .1 1.291E+04 4.578E+03 4.120E-14 0.OOOE+00 0.OOOE+00 Kr-88 1 1.815E+04 1.022E+04 1.020E-13 0.00OE+00 0.OOOE+00 I-131 2 4.337E+04 6. 947E+05 1.820E-14 2.920E-07 8.890E-09 I-132 2 3.914E+04 8.280E+03 1.120E-13 1.740E-09 1.030E-10 I-133 2 5.501E+04 7.488E+04 2.940E-14 4.860E-08 1.580E-09 I-134 2 6.035E+04 3.156E+03 1.300E-13 2.880E-10 3.550E-1l I-135 2 5.157E+04 2.380E+04 8.294E-14 8.460E-09 3.320E-10 Xe-133 1 5.282E+04 4.532E+05 1.560E-15 0.OOOE+00 0.OOOE+00 Xe-135 1 2.144E+04 3.272E+04 1.190E-14 0.OOOE+00 0.00OE+00 Nuclide Daughter Fraction Daughter -Fraction Daughter Fraction Kr-85m Kr-85 0.21 none 0.00 none 0.00 Kr-87 Rb-87 1.00 none 0.00 none 0.00 Kr-88 Rb-88 1.00 none 0.00 none 0.00 Sr-90 Y-90 1.00 none 0.00 none 0.00 Sr-91 Y-91m 0.58 Y-91 0.42 none 0.00 Sr-92 Y-92 1.00 none , 0.00 none 0.00 Y-93 Zr-93 .1.00 none 0.00 none 0.00 Zr-95 Nb-95m 0.01 Nb-95 0.99 none 0.00 Zr-97 Nb-97m 0.95 Nb-97 0.05 none 0.00 Mo-99 Tc-99m 0.88 Tc-99 0.12 none 0.00 Tc-99m Tc-99 1.00 none 0.00 none ' 0.00 DRE02-0036, Rev. 1, Attachment B, Page B8 of B15

QDC_7x7l1dayNoFilter (DF135 19 fl)

Ru-103 Rh-103m 1.00 none 0.00 none 0.00 Ru-105 Rh-105 1.00 none 0.00 none 0.00 Ru-106 Rh-106 1.00 none 0.00 none 0.00 Sb-127 Te-127m 0.18 Te-127 0.82 none 0.00 Sb-129 Te-129m 0.22 Te-129 0.77 none 0.00 Te-127m Te-127 0.98 none 0.00 none 0.00 Te-129 I-129 1.00 none 0.00 none 0.00 Te-129m Te-129 0.65 I-129 0.35 none 0.00 Te-131m Te-131 0.22 I-131 0.78 none 0.00 Te-132 1-132 .1. 00 none 0.00 none 0.00 1-131 Xe-131m 0.01 none 0.00 none 0.00 I-133 Xe-133m 0.03 Xe-133 0.97 none 0.00 1-135 Xe-135m 0.15 Xe-135 0.85 none 0.00 Xe-135 Cs-135 ,1.00 none 0.00 none 0.00 Cs-137 Ba-137m 0.95 none 0.00 none 0.00 Ba-140 La- 140 1.00 none 0.00 none 0.00 La-141 Ce-141 1.00 none 0.00 none 0.00 Ce-143 Pr-143 1.00 none 0.00 none 0.00 Ce-144 Pr-144m 0.02 Pr-144 0.98 none 0.00 Nd-147 Pm-147 1.00 none 0.00 none 0.00 Np-239 Pu-239 1.00 none 0.00 none 0.00 Pu-238 U-234 1.00 none 0.00 none 0.00 Pu-239 U-235 1.00 none 0.00 none 0.00 Pu-240 U-236 1.00 none 0.00 none 0.00 Pu-241 U-237 0.00 Am-241 1.00 none 0.00 Am-241 Np-237 1.00 none ,0.00 none 0.00 Cm-242 Pu-238 1.00 none 0.00 none 0.00 Cm-244 Pu-240 1.00 none 0.00 none 0.00 Iodine fractions Aerosol O.OOOOE+00 Elemental 8.0000E-01 Organic 2.OOOOE-01 COMPARTMENT DATA Compartment number 1: Containment Compartment number 2: Environment Compartment number 3: Control Room PATHWAY DATA Pathway number 1: Leak to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencie: (%)

(cfm) Aerosol Elemental Organic 2.4000E+01 3.OOOOE+05 0.OOOOE+00 I).OOOOE+00 0.OOOOE+00 Pathway number 2: Environment to Control Room Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

DRE02-0036, Rev. l,Attachment B, Page B9 of B15

QDC 7x7 IdayNoFilter (DF135 19 fl)

(cfm) Aerosol Elemental Organic 2.4000E+01 6.4000E+04 0.000OE+00 0.OOOOE+00 0.0000E+00 Pathway number 3: Control Room to Environment Exhaust Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 2.4000E+01 6.4000E+04 1.OOOOE+02 1.0000E+02 1.0000E+02 LOCATION DATA Location Exclusion Area Bndry is in compartment 2 Location X/Q Data Time (hr) X/Q (s

mA-3) 2.4000E+01 2.5100E-04 2.6000E+Ql O.OOQOE+00 Location Breathing Rate Data Time (hr) Breathing Rate (mA3

secAl) 2.4000E+01 3.4700E-04 2.6000E+01 0.OOOOE+00 Location Low Population Zone is in compartment 2 Location X/Q Data Time (hr) X/l' (S

m^-3) 2.4000E+01 2.6300E-05 2.6000E+01 0.00OOE+00 Location Breathing Ralte Data Time (hr) Br4eathing Rate (mA3.* sec^-1) 2.4000E+01 3.4700E-04 2.6000E+0l 0.000OE+00 Lobation Control Room is in compartment 3 Location X/Q Data Time (hr) X/52 (s

m^-3) 2.4000E+01 6.4400E-04 2.6000E+01 0.OOOOE+00 Location Breathing Raite Data Time (hr) Broeathing Rate (m^3

sec^-1) 2.4000E+01 3.4700E-04 4.8000E+01 0.0000E+00 Location Occupancy Fai:tor Data Time (hr) Ocl:upancy Factor 2.4000E+01 1.0000E+00 4.8000E+01 0.OOOOE+00 USER SPECIFIED TIME STEP DATA - SUPPLEMENTAL TIME STEPS Time Time step 0.0000E+00 1.OOOOE-03 1.OOOOE-02 1.OOOOE-02 1.0000E-01 1.OOOOE-01 2.0000E+00 1.0000E+00 DRE02-0036, Rev. 1, Attachment B, Page BI0 of B15

QDC7x7I day NoFilter (DFI 35 19 ft) 2.4000E+01 0. OOOOE+00 DRE02-0036, Rev. 1, Attachment B, Page B II of B 15

QDC 7x7ldayNoFilter (DF135 19 fi)

RADTRAD Version 3.03 (Spring 2001) run on 8/12/2005 at 8:49:40 ititit# it it it it it # it. it it it it it it # it it it it #

it it it # it ititititit it it it it it I ##

it it it it it #t #

Dose Output Exclusion Area Bndry Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 4.1464E-07 4. 9681E-05 1.9441E-06 Accumulated dose (rem) 4.1464E-07 4.9681E-05 1 .9441E-06 Low Population Zone Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 4.3446E-08 5.2056E-06 2.0370E-07 Accumulated dose (rem) 4.3446E-08 5.2056E-06 2.0370E-07 Control Room Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.1460E-12 3.8239E-09 1.1887E-10 Accumulated dose (rem) 1.1460E-12 3.8239E-09 1.1887E-10 Exclusion Area Bndry Doses:

Time (h) = 26.0000 Whole Body Thyroid - TEDE Delta dose (rem) 2.0382E-01 2.4790E+01 9.6678E-01 Accumulated dose (rem) 2.0382E-01 2.4790E+01 9. 6678E-01 Low Population Zone Doses:

Time (h) = 26.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.1357E-02 2.5975E+00 1.0130E-01 Accumulated dose (rem) 2.1357E-02 2.5975E+00 1.0130E-01 Control Room Doses:

Time (h) = 26.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.8906E-02 6.4108E+01 1. 9919E+00 Accumulated dose (rem) 1.8906E-02 6.4108E+01 1. 9919E+00 DRE02-0036, Rev. 1, Attachment B, Page B 12 of B 15

QDC 7x7 ldayNoFilter (DF135 19 fl)

Exclusion Area Bndry Doses:

Time (h) = 48.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 2.0382E-01 2.4790E+01 9.6678E-01 Low Population Zone Doses:

Time (h) = 48.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 2.1357E-02 2.5975E+00 1.0130E-0l Control Room Doses:

Time (h) = 48.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.1924E-06 4.5356E-03 1.4051E-04 Accumulated dose (rem) 1.8907E-02 6.4113E+01 1.9920E+00 159 I-131 Summary Containment Environment Control Room Time (hr) I-131 (Curies) I-131 (Curies) I-131 (Curies) 24.000 2.3765E+02 4.7530E-04 9.2453E-06 24.400 4.7912E+0l 1.8955E+02 6.6570E-02 24.700 1.4415E+01 2.2301E+02 2.0029E-02 25.000 4.3371E+00 2.3307E+02 6.0261E-03 25.300 1.3049E+00 2.3610E+02 1.8131E-03

25. 600 3.9261E-01 2.3701E+02 5.4550E-04

25. 900 1.1812E-01 2.3729E+02 1.6412E-04 26.000 7.9153E-02 2.3733E+02 1.0998E-04 26.300 2.3815E-02 2.3738E+02 1.6729E-12

26. 600 7.1651E-03 2.3740E+02 2.5448E-20

26. 900 2.1558E-03 2.3740E+02 3.8711E-28 27.200 6.4860E-04 2.3741E+02 5.8887E-36 27.500 1.9515E-04 2.3741E+02 8.9578E-44

27. 800 5.8713E-05 2.3741E+02 1.3626E-51 28.100 1.7665E-05 2.3741E+02 2.0728E-59 28.400 5.3149E-06 2.3741E+02 3.1531E-67 28.700 1.5991E-06 2.3741E+02 4.7965E-75

29. 000 4.8112E-07 2.3741E+02 7.2963E-83 29.300 1.4475E-07 2.3741E+02 l.1099E-90

29. 600 4.3552E-08 2.3741E+02 1.6884E-98

29. 900 1.3103E-08 2.3741E+02 2.5683-106 30.200 3.9424E-09 2.3741E+02 3.9069-114 30.500 1.1862E-09 2.3741E+02 5.9430-122

30. 800 3.5688E-10 2.3741E+02 9.0404-130 31.100 1.0737E-10 2.3741E+02 1.3752-137 31.400 3.2306E-11 2.3741E+02 2.0919-145 31.700 9.7198E-12 2.3741E+02 3.1822-153

32. 000 2.9244E-12 2.3741E+02 4.8407-161

32. 300 8.7986E-13 2.3741E+02 7.3636-169

32. 600 2.6472E-13 2.3741E+02 1.1201-176 DRE02-0036, Rev. 1, Attachment B, Page B13 of B15

QDC7x7l dayNoFilter (DFI35 19 fl)

32. 900 7.9648E-14 2.3741E+02 1.7039-184 33.200 2.3964E-14 2.3741E+02 2.5920-192 33.500 7.2099E-15 2.3741E+02 3.9429-200

33. 800 2.1692E-15 2.3741E+02 5.9979-208 34.100 6.5266E-16 2.3741E+02 9.1238-216 34.400 1.9637E-16 2.3741E+02 1.3879-223 48.000 4.4282E-40 2.3741E+02 O.OOOOE+00 Cumulative Dose Summary Exclusion Area Bndry Low Population Zone Control Room Time Thyroid TEDE Thyroid TEDE Thyroid TEDE (hr) (rem) (rem) (rem) (rem) (rem) (rem) 24.000 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 24.400 1. 9806E+01 7.7357E-01. 2.0753E+00 8.1055E-02 5.0226E+01 1.5609E+00 24.700 2.3298E+Ol 9.0919E-01 2.4412E+00 9.5266E-02 5.9952E+01 1.8629E+00 25.000 2.4347E+01 9.4976E-01 2.5511E+00 9.9517E-02 6.2875E+01 1.9537E+00 25.300 2.4663E+01 9. 6190E-01 2.5842E+00 1.0079E-01 6.3754E+01 1.9809E+00

25. 600 2. 4758E+01 9. 6554E-01 2.5941E+00 1.0117E-01 6.4018E+01 1.9891E+00

25. 900 2.4786E+01 9. 6662E-01 2.5971E+00 1.0128E-01 6.4097E+01 1.9916E+00

26. 000 2.4790E+01 9.6678E-01 2.5975E+00 1.0130E-01 6.4108E+01 1.9919E+00

26. 300 2.4790E+01 9.6678E-01 2.5975E+00 1.0130E-01 6.4113E+01 1.9920E+00

26. 600 2.4790E+01 9. 6678E-01 2.5975E+00 1.0130E-Ol 6.4113E+01 1.9920E+00

26. 900 2.4790E+01 9. 6678E-01 2.5975E+00 1.0130E-Ol 6.4113E+01 1.9920E+00 27.200 2.4790E+01 9. 6678E-01 2.5975E+00 1.0130E-01 6.4113E+01 1.9920E+00

27. 500 2.4790E+01 9.6678E-01 2.5975E+00 1.0130E-01 6.4113E+01 1.9920E+00

27. 800 2.4790E+01 9. 6678E-01 2.5975E+00 1.0130E-01 6.4113E+01 1.9920E+00 28.100 2.4790E+01 9. 6678E-01 2.5975E+00 1.0130E-01 6.4113E+01 1.9920E+00 28.400 2.4790E+01 9.6678E-01 2.5975E+00 1.0130E-01 6.4113E+01 1.9920E+00 28.700 2.4790E+01 9. 6678E-01 2.5975E+00 1.0130E-01 6.4113E+01 1.9920E+00 29.000 2.4790E+01 9. 6678E-01 2.5975E+00 1.0130E-01 6.4113E+01 1.9920E+00 29.300 2.4790E+01 9.6678E-01 2.5975E+00 1.0130E-Ol 6.4113E+01 1.9920E+00

29. 600 2.4790E+01 9.6678E-01 2.5975E+00 1.0130E-01 6.4113E+01 1.9920E+00

29. 900 2.4790E+01 9. 6678E-01 2.5975E+00 1.0130E-01 6.4113E+01 1.9920E+00 30.200 2.4790E+01 9. 6678E-01 2.5975E+00 1.0130E-Ol 6.4113E+01 1.9920E+00 30.500 2.4790E+01 9. 6678E-01 2.5975E+00 1.0130E-Ol 6.4113E+01 1.9920E+00

30. 800 2.4790E+01 9.6678E-01 2.5975E+00 1.0130E-01 6.4113E+01 1.9920E+00 31.100 2.4790E+01 9.6678E-01 2.5975E+00 1.0130E-01 6.4113E+01 1.9920E+00 31.400 2.4790E+01 9.6678E-01 2.5975E+00 1.0130E-Ol 6.4113E+01 1.9920E+00 31.700 2.4790E+01 9. 6678E-01 2.5975E+00 1.0130E-01 6.4113E+01 1.9920E+00 32.000 2.4790E+01 9.6678E-01 2.5975E+00 1.0130E-01 6.4113E+01 1.9920E+00 32.300 2.4790E+01 9. 6678E-01 2.5975E+00 1.0130E-01 6.4113E+01 1.9920E+00

32. 600 2.4790E+01 9.6678E-01 2.5975E+00 1.0130E-01 6.4113E+01 1.9920E+00

32. 900 2.4790E+01 9.6678E-01 2.5975E+00 1.0130E-Ol 6.4113E+01 1.9920E+00 33.200 2.4790E+01 9.6678E-01 2.5975E+00 1.0130E-Ol 6.4113E+01 1.9920E+00

33. 500 2.4790E+01 9.6678E-01 2.5975E+00 1.0130E-01 6.4113E+01 1.9920E+00

33. 800 2.4790E+01 9.6678E-01 2.5975E+00 1.0130E-01 6.4113E+01 1.9920E+00 34.100 2.4790E+01 9. 6678E-01 2.5975E+00 1.0130E-01 6.4113E+01 1.9920E+00 34.400 2.4790E+01 9. 6678E-01 2.5975E+00 1.0130E-01 6.4113E+01 1.9920E+00

48. 000 2.4790E+01 9. 6678E-01 2.5975E+00 1.0130E-01 6.4113E+01 1.9920E+00 Worst Two-Hour Doses DRE02-0036, Rev. 1, Attachment B, Page B14 ofBS5

QDC7x7_1dayNoFilter (DF135 19 fi)

Exclusion Area Bndry Time Whole Body Thyroid TEDE (hr) (rem) * (rem) (rem) 24.0 2.0382E-01 2.4790E+01 9. 6678E-01 DRE02-0036, Rev. 1, Attachment B, Page B15 of BI5

Dres QDC Source Terms for FHA.nif Nuclide Inventory Name:

Source Document Calc. #GE-NE-A22-00103-64-01 Appendix D for Dresden and Quad Cities Power Level:

o.1OOOE+01 Nuclides:

60 Nuclide 001:

Co-58 7

0.6117120000E+07 0.5800E+02 0.1529E+03 none O.0000E+00 none 0.0OOOE+00 none. 0.0000E+00 Nuclide 002:

Co-60 7

0.1663401096E+09 0.6000E+02 0.1830E+03 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 003:

Kr-85 1

0.3382974720E+09 0.8500E+02 8.7288E+02 2*LOCA Value for FHA none 0.OOO0E+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 004:

Kr-85m 1

0.1612800000E+05

0. 8500E+02 6 7720E+03 Kr-85 0.2100E+00 none 0.0000E+00 none 0.OOOOE+00 Nuclide 005:

Kr-87 1

0.45780000OE+04 0.8700E+02 1.2910E+04 Rb-87 0.1000E+( *1 none 0.0000E+( 20

- -------- n none U.Uuu Uhk+UU Nuclide 006:

Kr-88 1

0.1022400000E+05 0.88 00E+02 1.8150E+04 Rb-88 0.1000E+01 DRE02-0036, Rev. 1, Attachment C, Page C1 of CIO

Dres QDC Source Terms for FIIA.nif none O.OOOOE+00 none O.OOOOE+00 Nuclide 007:

Rb-86 3

0.1612224000E+07 0.8600E+02 7.096E+01 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 008:

Sr-89 5

0.4363200000E+07 0.8900E+02 2.4284E+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 009:

Sr-90 5

0.9189573120E+09 0.9000E+02 3.5283E+03 Y-90 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 010:

Sr-91 5

0.3420000000E+05 0.9100E+02 3.0810E+04 Y-91m 0.5800E+00 Y-91 0.4200E+00 none O.OOOOE+00 Nuclide 011:

Sr-92 5

0.9756000000E+04 0.9200E+02 3.3620E+04 Y-92 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 012:

Y-90 9

0.2304000000E+06 0.9000E+02 3.6249E+03 none O.OOOOE+00 none 0.OOOOE+00 none O.OOOOE+00 Nuclide 013:

Y-91 9

DRE02-0036, Rev. I, Attachment C, Page C2 ofCIO

Dres QDC Source Terms for FHA.nif 0.5055264000E+07 0.9100E+02 3.1549E+04 none O.O000E+OO none O.OOOOE+00 none O.OOOOE+00 Nuclide 014:

Y-92 9

0.1274400000E+05 0.9200E+02 3.3767E+04 none O.OOOOE+0O none 0.OpOOE+OO none O.OOOOE+00 Nuclide 015:

Y-93 9

0.3636000000E+05

.0.9300E+02 3.9417E+04 Zr-93 0.1000E+0O none O.OOOOE+00 none O.O000E+0O Nuclide 016:

Zr-95 9

0.5527872000E+07 0.9500E+02 4.4427E+04 Nb-95m 0.7000E-02 Nb-95 0.9900E+00 none O.OOOOE+00 Nuclide 017:

Zr-97 9

0.6084000000E+05 0.9700E+02 4.4971E+04 Nb-97m 0.9500E+00 Nb-97 0.5300E-0l none O.OOOOE+00 Nuclide 018:

Nb-95 9

0.3036960000E+07 0.9500E+02 4.4637E+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 019:

Mo-99 7

0.2376000000E+06 0.9900E+02 5.1210E+04 Tc-99m 0.8800E+00 Tc-99 0.1200E+00 DRE02-0036, Rev. 1, Attachment C, Page C3 of CIO

Dres QDC Source Terms for FHA.nif none O.OOOOE+00 Nuclide 020:

Tc-99m 7

0.2167200000E+05 0.9900E+02 4.4837E+04 Tc-99 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 021:

Ru-103 7

0.3393792000E+07 0.1030E+03 4.3107E+04 Rh-103m 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00

-Nuclide 022:

Ru- 105 7

0.1598400000E+05 0.1050E+03 3.0337E+04 Rh-105 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 023:

Ru-106 7

0.3181248000E+08 0.1060E+03 1.8366E+04 Rh-106 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 024:

Rh-105 7

0.1272960000E+06 0.1050E+03 2.8824E+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 025:

Sb-127 4

0.3326400000E+06 0.1270E+03 2.9994E+03 Te-127m 0.1800E+00 Te-127 0.8200E+00 none O.OOOOE+00 Nuclide 026:

Sb-129 4

0.1555200000E+05 DRE02-0036, Rev. 1, Attachment C, Page C4 of C1o

Dres QDC Source Terms for FIIA.nif 0.1290E+03 8.8770E+03 Te-129m 0.2200E+00 Te-129 0.7700E+00 none O.OOOOE+00 Nuclide 027:

Te-127 4

0.3366000000E+05 0.1270E+03 2.9857E+03 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 028:

Te-127m 4

0.9417600000E+07 0.1270E+03 4.0597E+02 Te-127 0.9800E+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 029:

Te-129 4

0.4176000000E+04 0.1290E+03

8.7350E+03 I-129 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 030:

Te-129m 4.

0.2903040000E+07 0.1290E+03 1.3004E+03 Te-129 0.6500E+00 I-129 0.3500E+00 none O.OOOOE+00 Nuclide 031:

Te-131m 4

0.1080000000E+06 0.1310E+03 3.9549E+03 Te-131 0.2200E+00 I-131 0.7800E+00 none O.OOOOE+00 Nuclide 032:

Te-132 4

0.2815200000E+06 0.1320E+03 3.8497E+04 I-132 0.1000E+01 none O.OOOOE+00 none O.OOOOE+OO DRE02-0036, Rev. 1, Attachment C, Page CS of CI0

Dres QDC Source Terms for FIIA.nif Nuclide 033:

I-131 2

0.6946560000E+06 0.1310E+03 4.3366E+04 1.6*LOCA Value for FHA Xe-131m 0.1100E-01 none 0.0000E+00 none 0.0000E+00 Nuclide 034:

I-132 2

0.8280000000E+04 0.1320E+03 3.9136E+04 none 0.0000E+00 none 0.00OOE+00 none 0.OOOOE+00 Nuclide 035:

I-133 2

0.7488000000E+05 0.1330E+03 5.5010E+04 Xe-133m 0.2900E-01 Xe-133 0.9700E+00 none 0.OOOOE+00 Nuclide 036:

I-134 2

0.3156000000E+04 0.1340E+03 6.0353E+04 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 037:

I-135 2

0.2379600000E+05 0.1350E+03 5.1570E+04 Xe-135m 0.1500E+00 Xe-135 0.8500E+00 none 0.0000E+00 Nuclide 038:

Xe-133 1

0.4531680000E+06 0.1330E+03 5.2821E+04 none 0.00OOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 039:

Xe-135 1

0.3272400000E+05 0.1350E+03 DRE02-0036, Rev. l,Attachment C, Page C6 of CIO

Dres QDC Source Terms for FIIA.nif 2.1437E+04 Cs-135 0.1000E+Ol none O.OOOOE+00 none O.000OE+OO Nuclide 040:

Cs-134 3

0.6507177120E+08 0.1340E+03 8.0091E+03 none O.OOOOE+0O none 0.OOOOE+OO none O.OOOOE+00 Nuclide 041:,

Cs-136 3

0.1131840000E+07 0.1360E+03 2.3791E+03 none 0.OOOOE+OO none O.OOOOE+00 none O.OOOOE+OO Nuclide 042:

Cs-137 3

0.9467280000E+09 0.1370E+03 4.9283E+03 Ba-137m 0.9500E+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 043:

Ba-139 6

0.4962000000E+04 0.1390E+03 4.8879E+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 044:

Ba-140 6

0.1100736000E+07 0.1400E+03 4.7141E+04 La-140 O.iOOOE+01 none O.OOOOE+0O none O.OOOOE+0O Nuclide 045:

La-140 9

0.1449792000E+06 0.1400E+03 5.0553E+04 none O.OOOOE+00 none 0.OOOOE+OO none O.OOOOE+00 Nuclide 046:

DRE02-0036, Rev. 1, Attachment C, Page C7 of C10

Dres QDC Source Terms for FIIA.nif La-141 9

0.1414800000E+05 0.1410E+03 4.4469E+04 Ce-141 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 047:

La-142 9

0.5550000000E+04 0.1420E+03 4.2864E+04 none 0.00OE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 048:

Ce-141 8

0.2808086400E+07 0.1410E+03 4.4650E+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 049:

Ce-143 8

0.1188000000E+06 0.1430E+03 4.1011E+04 Pr-143 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 050:

Ce-144 8

0.2456352000E+08 0.1440E+03 3.6823E+04 Pr-144m 0.1800E-01 Pr-144 0.9800E+00 none 0.OOOOE+00 Nuclide 051:

Pr-143 9

0.1171584000E+07 0.1430E+03 3.9634E+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 052:

Nd-147 9

0.9486720000E+06 0.1470E+03 1.7999E+04 DRE02-0036, Rev. 1, Attachment C, Page C8 of C10

Dres QDC Source Terms for FIIA.nif Pm-147 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 053:

Np-239 8

0.2034720000E+06 0.2390E+03 5.5866E+05 Pu-239 0.1000E+01 none O.OOOOE+00 none 0.0000E+00 Nuclide 054:

Pu-238 8

0.2768863824E+10 0.2380E+03 1.7677E+02 U-234 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 055:

Pu-239 8

0.7594336440E+12 0.2390E+03 1.4743E+01 U-235 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 056:

Pu-240 8

0.2062920312E+12 0.2400E+03 2.0014E+01 U-236 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 057:

Pu-241 8

0.4544294400E+09 0.2410E+03 6.6999E+03 U-237 0.2400E-04 Am-241 0.1000E+01 none O.OOOOE+00 Nuclide 058:

Am-241 9

0.1363919472E+ll 0.2410E+03 9.8566E+00 Np-237 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 059:

Cm-242 DRE02-0036, Rev. 1, Attachment C, Page C9 of CIO

Dres QDC Source Terms for F11A.nif 9

0.1406592000E+08 0.2420E+03

.2.2847E+03 Pu-238 0.1000E+O1 none O.OOOOE+00 none O.OOOOE+00 Nuclide 060:

Cm-244 9

0.5715081360E+09 0.2440E+03 1.6212E+02 Pu-240 0.lOOOE+01 none O.OOOOE+O0 none O.OOOOE+00 End of Nuclear Inventory File DRE02-0036, Rev. 1, Attachment C, Page CI 0 of Cl 0

QDC FHA (DF 200 23 ft).rft Release Fraction and Timing Name:

Dresden & Quad Cities FHA, 7x bundle Nobles=I=5% & pool I DF=200, Cs DF=infinity Duration (h):

0.lOOOE-05 0.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Noble Gases:

5.OOOOE-02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Iodine:

2.5000E-04 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Cesium:

O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Tellurium:

O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Strontium:

O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Barium:

O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Ruthenium:

O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Cerium:

O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Lanthanum:

O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Non-Radioactive Aerosols (kg):

O.OOOOE+O0 O.OOOOE+00 O.OOOOE+00 O.OOOOE+O0 End of Release File DRE02-0036, Rev. l, Attachment D, Page Dl of DI

DC FHA (DF 135 19 ft).rft Release Fraction and Timing Name:

Dresden & Quad Cities FHA, 7x7 bundle Nobles=I=5% & pool I DF=135, Cs DF=infinity Duration (h):

O.lOOOE-05 O.OOOOE+00 0.000E+00 O.OOOOE+00 Noble Gases:

5.OOOOE-02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Iodine:

3.7037E-04 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Cesium:

O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Tellurium:

O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Strontium:

O.OOOOE+00 O.OO.OOE+00 O.OOOOE+00 O.OOOOE+00 Barium:

O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0.OOOOE+00 Ruthenium:

O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Cerium:

O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Lanthanum:

O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Non-Radioactive Aerosols (kg):

O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 End of Release File DRE02-0036, Rev. I, Attachment E, Page El of El

Computer Disclosure Sheet Discipline Nuclear Client: Exelon Date: August 2005 Project: Dresden Units 2 & 3 Job No.

Program(s) used: Rev No. Rev Date Calculation Set No. DRE02-0036, Rev.1 RADTRAD 3.03 Runs in Att. A and B 0 January 2003 (Prequalification Date)

RADTRAD 3.03 NIF File in Atl. C 0 1/2003 Status [ ] Prelim.

RAOTRAD 3.03 RFT File in Att. D and E 0 1/2003 - XI Final

_ Void WGI Prequalification [X I Yes f ] No Run No.

Description:

Analysis

Description:

RADTRAD output files, where applied to calculations of FHA dose assessments, 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: 8/2005 Run by: H. Rothstein i Checked by: P. Reichert -

Approved by: H. Rothsteln Remarks: WGI Form for Computer Software Control The RADTRAD computer code isapplied in amanner fitting its intended purpose, and well within it's operating parameters. All outputs were hand checked.

Attachments D. E and Finclude the Nuclide Information File and Release Fraction and Timing Files used by the RADTRAD code and generated specifically for the Dresden Nuclear Power Station. Both were also hand checked for accuracy.

DRE02-0036, Rev. l, Attachment F.Page 1 of I

ML052430326

Contents

Text

SUMMARY

SUMMARY

Description:

Description:

Navigation menu

ML052430326

Text

SUMMARY

SUMMARY

Description:

Description:

Navigation menu

Search