Text

Rev. 1 to Calculation DRE02-0037, Re-analysis of Control Rod Drop Accident Using Alternative Source Terms.
	ML052430276
Person / Time
Site:	Dresden, Quad Cities
Issue date:	08/12/2005
From:	Rothstein H; Exelon Generation Co
To:	; Office of Nuclear Reactor Regulation
References
	RS-05-114 DRE02-0037, Rev 1
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ATTACHMENT 2 Calculation DRE02-0037, "Re-analysis of Control Rod Drop Accident (CRDA)

Using Alternative Source Terms," Revision I K

CC-AA-309-1 001 Revision 2 ATrACWlvEN'1 1 Desizo AnAlysis Cover Sbet Design Analysis (Major Revision) I LastPageNo.'18/Att.F-2 Analysis No.: DRE02-0037 Revision: I 1

Title:

' Re-analysis of Control Rod Drop Accident (CRDA) Using Alternative Soarce Terms ECIECR No.: 356383 Revision:a 0 Statlon(s): Dresden Component(s): <

UnitNoa 2&3 _

Discipline' N Descrip. NOI R01.R02 Code/Keywordt: lAST,

/ CRDA

.Safety/lA Class: SR 2

System Code: 1 00 Structure: "_

CONTROLLED DOCUMENT REFERENCES Document No.: From/rTo Document No.: From/To DRE04 0030, RI From OR357-M004. RO From DRE010028, RI From - GE-NE-A22-00103-64401. R0 Frorn DRE01-0071. RO From DRE01-0040, RO F rom I Is this Design Analysis Safeguards Information? Yes O No 0 If yes, see SY-MA-101-106 Does this Design Analysis contain Unverified Yes 0 No 0 If yes, Assumptions? ATUARX:

This Design Analysis SUPERCEDES: DRE02-007. Rev. 0 In Its entirety.

Description of Revision (listaffected pages for partials):

This revision Incorporates responses to pertinent NRC Request for Additional Infornation (RAls) with respect to all Exelon Nuclear Station Alternative Source Term License Amendment Appications. The revisions are to remove any consideration of Mechanical Vacuum Pumps operation following a CRDA, based on their tripping closed at the initiation of a CADA from a high radiation signal from the Main Steam Line Radiation Monitors, and to remove deposition credit for releases from the gland seal condenser. Revised X/O values from a new calculation are also utilized. Finally, additional assumptions from Regulatory Guide 1.183 are included to directly indicate conformance with this Regulatory Guide.

Preparer Harold Roibstein / 6 _ .2; Print Name Sign Name Date Method of Detailed Review Alternate Calculations (attached) 0 Testing 0 Review: 0 0'

Reviewer: Paul Reichert ame OtAe Print Name Sign Name Date Review AdJT;ft-0J Independent review Peer review Notes: "8ZSIt .{ ~ ~ e External - ~ ' -- -'

Approver: 'a Print Name Sign N e Date Exelon Reviewer:"

. Name Dta Date Is a Supplemental Review Required?" Yes No J If yes', plate Attachment 3 Exelon Print Name Sign Name Date

I CALCULATION NO. DRE02-0037 l REV. NO. 001 I PAGE NO. 2 l Table of Contents

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

2. METHODOLOGY AND ACCEPTANCE CRITERIA ............................................ 3 2.1. General Description.3 2.1. GeneSoral D esripton...............................................................................................................;.............................34 2.3. Fuel Damage Assessment .................... 4 2.4. Radioactivity Transport.4 2.5. Release Pathways ................... I...4 2.6. Dose Conversion Factors.5 2.7. Control Room Dose Model .................... 5:

5 2.8. EAB and LPZ Dose Model .5 2.9. Acceptance Criteria .5

3. ASSUMPTIONS...8

4. DESIGN INPUT ............................. 9 4.1. X/Q Calculations (Meteorology) ...................... 9.......9 4.2. Plant Data ........................... .. 9 4.3. Control Room Data ............................ 10 4.4. Source Terms ............................. 10

5. REFERENCES ................... .......... 11

6. CALCULATIONS..................................................................................................................................................... 12 6.1. Source Term Calculation ............................ 12 6.2. D ose Calculations1.............................................................................................................................................

s12 6.3. SJAE Release Pathway ............................ , 15

7.

SUMMARY

AND CONCLUSIONS ............................. 17

8. O'VNER'S ACCEPTANCE REVIEW CHECKLIST FOR EXTERNAL DESIGN ANALYSIS . . 18 ATTACHMENTS:

A. Release Fraction Assessment Spreadsheet [3 pgs.]

B. RADTRAD Output Files [27 pgs.]

C. RADTRAD Source Term "NIF" Input [10 pgs.]

D. RADTRAD Release Fraction "RFT' Input [2 pgs.]

E. Steam Jet Air Ejector (SJAE) Path Assessment and formulae [2 pgs.]

F. Computer Disclosure Sheets [2 pgs.]

I CALCULATION NO. DRE02-0037 l REV. NO. 001 l PAGE NO.3

1. PURPOSE/OBJECTIVE The objective of this calculation is to re-analyze the radiological consequences of a Control Rod Drop Accident (CRDA) as described in UFSAR Section 15.4.10. The re-analysis is based on the use of Alternative Source Terms (AST) as defined in Regulatory Guide (RG) 1.183 (Ref. 2)

Appendix C and with scenario guidance from NEDO-31400A (Ref. 19).

The design basis CRDA results in the release of radioactivity to the condenser. For the case where the condenser is isolated from the reactor after release of activity to the condenser (Scenario 1 of Ref. 19), the isolated condenser is assumed to exhaust at a rate of 1% per day, per Ref: 2, Appendix C.

However, per Ref. 2, Appendix C, footnote 2, forced flow pathways from the condenser must also be considered, such as un-isolated mechanical vacuum pumps or unprocessed air ejectors. These are evaluated as follows:

For Case 1 as per UFSAR Section 15.4.10.5, the main condenser mechanical vacuum pump is isolated following initiation of CRDA on Main Steam Line Radiation Monitors (MSLRM) high radiation signals. Therefore this path is not considered further. This is in accordance with the traditional CRDA scenarios and bounding accident considerations as defined in NEDO-31400A (Ref. 19).

For Case 2, where the condenser is not isolated from the reactor and the steam flow is sufficient for Steam Jet Air Ejector (SJAE) operation, the SJAE exhaust is processed by the charcoal delay beds in the Augmented Off-Gas System. While Ref. 2 does not require further analysis of this scenario, it is evaluated in this calculation as defined in Ref. 19, Scenario 2. The augmented off-gas system provides SJAE flow processing through charcoal delay beds which would eliminate iodine releases and greatly delay noble gas releases allowing for decay even with normal off-gas flow rates.

Finally, releases via steam flow to the turbine gland sealing system are considered, as has been done historically for this event, with all iodine and noble gases entering the gland seal condenser from the turbine seals released to the environment effectively immediately (well within 112 hour0.0013 days 0.0311 hours 1.851852e-4 weeks 4.2616e-5 months ),

without credit for any fission product deposition in the gland seal condenser.

2. METHODOLOGY AND ACCEPTANCE CRITERIA 2.1. General Description In 1996 the Dresden Nuclear Station demonstrated that removal of the automatic MSIV isolation action following an MSLRM detection of high radiation was within regulatory practices. Exelon letter RS-01-183 (Ref. 13) indicated the acceptability of this for Extended Power Uprate (EPU) conditions. Now a CRDA, an event that would cause such radiation levels, will not lead to MSIV closure, and therefore cannot be credited in this analysis. However, as per the Dresden UFSAR Section 15.4.10.5 on Radiological Consequences of a CRDA, the main condenser's mechanical vacuum pump is isolated following the initiation of the CRDA, as the vacuum pump trips on MSLRM high radiation signals were not removed.

Following a CRDA, radioisotopes postulated to be released will be transported through the Main Steam Lines (MSLs) directly to the main steam condenser. With tripping of the MVPs by the MSLRMs, the release will be from condenser leakage (assumed at 1% per day) and Gland Sealing

I CALCULATION NO. DRE02-0037 I REV. NO. 001I I PAGE NO. ]

Steam system leakage. The Gland Sealing Steam leakage is assumed, as historically done (per the analysis in References 11 and 12) and documented in the UFSAR, with the fraction of activity released from reactor coolant and transferred to the gland seal condenser as 0.0015. The activity is postulated to leak from the Turbine Building to the environment as an unfiltered ground release, corresponding to the MSIV leakage path used in the current AST LOCA calculations, with worst case XIQs derived in Reference 8. The doses from either accident scenario should not exceed the acceptance criteria of the applicable regulatory guidance (Ref. 2).

A third scenario is for a CRDA assumed to occur during SJAE operation. In this Scenario, activity is released to a system of Charcoal Delay Beds, where lodines and particulate are effectively removed and only delayed release of noble gas nuclides occurs. Although this release pathway (like the gland seal release) would be through the Station Chimney, for conservatism as was done for UFSAR Section 15.4.10.5, the release pathway is treated as a ground level release with higher XIQs.

2.2. Core Source Term For conservatism, the CRDA core source terms are those associated with 102% power, and for a reactor trip followed by an immediate restart. These source terms are per Reference 15.

2.3. Fuel Damage Assessment The current design basis for fuel damage from a CRDA is not impacted by application of AST and is, therefore, unchanged. The fuel damage (number of rods with failed cladding and fuel melting) assumptions correspond to those of the Dresden UFSAR and the Extended Power Uprate described in the calculation of Reference 12.

2.4. Radioactivity Transport Release fractions and transport fractions are per RG 1.183, Appendix C and Table 3, as shown in the spreadsheet in Attachment A to this calculation for both the main condenser and the gland seal condenser (where credit for fission product deposition is not taken).

2.5. Release Pathways 2.5.1. Turbine /Condenser 1%/day Leakage Releases from the Turbine/Condenser are assumed to be at ground level without credit for dilution or holdup in the Turbine Building.

2.5.2. Steam Jet Air Ejector Discharge When in operation the Steam Jet Air Ejectors discharge to the augmented off-gas system. This pathway is assessed in Attachment E, through the use of a spreadsheet crediting elimination of Iodine releases and a delay of noble gas releases by the augmented off-gas system charcoal delay beds, per UFSAR Section 11.3.2.1.2.10. Although the releases would be through the Station Chimney, for conservatism they are assumed to be at ground level.

2.5.3. Gland Seal Condenser Release For the Turbine Gland Seal Condenser release path, as per the analysis in References 11 and 12, the fraction of activity released from reactor coolant that is transferred to the gland seal condenser

CALCULATION NO. DRE02-0037 l REV. NO. 001 PAGE NO. 5 l is 0.0015. Although the releases would be through the Station Chimney, for conservatism they are assumed to be at ground level through the MSIV leakage path used in the current AST LOCA calculations.

2.6. Dose Conversion Factors The revised Dose Conversion Factors (DCFs) from the U.S. Federal Guidance Report 11&12 (Ref.

17,18) are used for this analysis. The RADTRAD code inputs these values directly from its internal database, and when used in spreadsheet analyses they are input directly.

2.7. Control Room Dose-Model For the analysis performed by the RADTRAD code, 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 I 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.

The CR %/0 's have been determined in Reference 8. Worst-case ground level releases through the MSIV leakage path used in the current AST LOCA calculations are assumed. Having determined these dispersion factors, the total dose is modeled in RADTRAD 3.03 to determine the CR total dose throughout the duration of the accident. The methodologies significant to this analysis are the dose consequence analysis in NUREG/CR 6604 Section 2.3 (Ref. 5) and the Radioactive Decay Calculations, Section 2.4.3 (Ref. 5).

2.8. EAB and LPZ Dose Model The EAB and LPZ X/0's have been determined in Reference 8. Worst-case ground level releases through the MSIV leakage path used in the current AST LOCA calculations are assumed. The EAB and LPZ are located 800m and 8000m from the postulated release points. Because of the distance of these locations from the plant, the release is simplified to be all from one point for the duration of the accident. Having determined these dispersion factors, the total dose is modeled in RADTRAD 3.03 using the same RADTRAD analysis as used in determining the CR total dose.

2.9. Acceptance Criteria Radiological doses resulting from a design basis CRDA for the control room operator and a person located at EAB or LPZ are to be less than the regulatory dose limits as given in Table 2.1.

Table 2.1. Regulatory Dose Limits I Dose Type l Control Room (rem) l EAB and LPZ(rem) l TEDE Dose 58 6.25-Notes:

a 10 CFR 50.67 (Ref. 10) b SRP 15.0.1 (Ref. 4), Reg. Guide 1.183 (Ref. 2)

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 C 'Assumptions for Evaluating the Radiological Consequences of a BWR Rod Drop Accident" is provided by this analysis, as shown in the Conformance Matrix Table 2.2.

1 CALCULATION NO. DRE02-0037 l REV. NO. 001 I PAGE NO. 6

Table2.2: Conform nce with RG 1.183 Appen C (ControlRod.ro Accident)

~RG- Dresden/Quad

,CA},

Sectl n Scin--RG ,,,zent Position -Cities D' AnalyIs ~ Cmet 1 Assumptions acceptable to the NRC staff regarding core inventory are Conforms 100% of the noble gases and provided in Regulatory Position 3 of this guide. For the rod drop 50% of the iodines released accident, the release from the breached fuel is based on the estimate of from melted fuel. Other the number of fuel rods breached and the assumption that 10% of the -releases also based on core inventory of the noble gases and iodines is in the fuel gap. The RegulatoryiPosition 3.

release attributed to fuel melting is based on the fraction of the fuel that reaches or exceeds the initiation temperature for fuel melting and on the assumption that 100% of the noble gases and 50% of the lodines contained in that fraction are released to the reactor coolant.

2 If no or minimal fuel damage is postulated for the limiting event, the Conforms Fuel damage is postulated.

released activity should be the maximum coolant activity (typically 4 Therefore, coolant activity is pCi/gm DE 1-131) allowed by the technical specifications. neglected.

3.1 The activity released from the fuel from either the gap or from fuel Conforms pellets is assumed to be instantaneously mixed in the reactor coolant within the pressure vessel.

3.2 Credit should not be assumed for partitioning in the pressure vessel or Conforms for removal by the steam separators.

3.3 Of the activity released from the reactor coolant within the pressure Conforms vessel, 100% of the noble gases, 10% of the iodine, and 1%' of the remaining radionuclides are assumed to reach the turbine and condensers.

3.4 Of the activity that reaches the turbine and condenser, 100% of the Conforms Release rate of 1% per day noble gases, 10% of the iodine, and 1% of the particulate radionuclides for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

are available for release to the environment. The turbine and condensers leak to the atmosphere as a ground- level release at a rate Decay is assumed in the of 1% per day for a period of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , at which time the leakage is condenser.

assumed to terminate. No credit should be assumed for dilution or holdup within the turbine building. Radioactive decay during holdup in the turbine and condenser may be assumed.

3.5 In lieu of the transport assumptions provided in paragraphs 3.2 through Conforms Paragraphs 3.2 through 3.4

I CALCULATION NO. DRE02-0037 I REV. NO. 001 I PAGE NO. 7 l

-Table2.2: Conformance with RG.1-183Appendix C (Control Rod.DropAccident).-:j ' --

RG .; Dresden/Quad

'Section ; , RG P sition- Cities Analysis: Comments-3.4 above, a more mechanistic analysis may be used on a case-by-case above are jtilized basis. Such analyses account for the quantity of contaminated steam carried from the pressure vessel to the turbine and condensers based on a review of the minimum transport time from the pressure vessel to the first main steam isolation (MSIV) and considers MSIV closure time.

3.6 The iodine species released from the reactor coolant within the pressure Conforms vessel should be assumed to be 95% Csl as an aerosol, 4.85%

elemental, and 0.15% organic. The release from the turbine and condenser should be assumed to be 97% elemental and 3% organic.

Foot- The activity assumed in the analysis should be based on the activity Conforms Projected fuel damage is the note 1 associated with the projected fuel damage or the maximum technical limiting casIe.

specification values, whichever maximizes the radiological consequences. In determining the dose equivalent 1-131 (DE 1-131), only the radioiodine associated with normal operations or iodine spikes should be included. Activity from projected fuel damage should not be included.

Foot- If there are forced flow paths from the turbine or condenser, such as Conforms Forced flow paths are note 2 unisolated motor vacuum pumps or unprocessed air ejectors, the considerediand the most leakage rate should be assumed to be the flow rate associated with the limiting path is determined.

most limiting of these paths. Credit for collection and processing of releases, such as by off gas or standby gas treatment, will be considered on a case-by-case basis.

CALCULATION NO. DRE02-0037 I REV. NO. 001 PAGE NO. 8

3. ASSUMPTIONS

1. Core inventory was based on a power level of 102% to account for uncertainty in the core power level.

2. An average power peaking factor of 1.7 per pin was assumed, as per Reference 14 (more conservative than UFSAR value of 1.5). 10% of the core inventory of noble gases and iodines are released from the fuel gap (Appendix C of Ref. 2). Release fractions of other nuclide groups contained in the fuel gap are detailed in Table 3 of Reg. Guide 1.183 (Ref. 2).

3. 0.77% of the fuel will melt during the CRDA (Ref. 19 and UFSAR Section 15.4.10.5).

100% of noble gases and 50% of the iodines contained in the melted fuel fraction are assumed to be released to the reactor coolant (Appendix C of Ref. 2). Fractions of other nuclides released from the melted fuel are used from Table 1 of Reg. Guide 1.183 (Ref. 2). Though these are described as LOCA values for fuel melt release, they are used to conservatively supplement for missing guidance in regards to the other nuclide groups.

4. The activity released from the fuel from either the gap or from fuel pellets is assumed to be instantaneously mixed with the reactor coolant within the pressure vessel (Ref.

2,4).

5. 100% of all noble gases, 10% of the iodines, and 1%of remaining nuclides are transported to the turbine/condenser (Ref. 2, 4).

6. Of the activity that reaches the turbine and condenser, 100% of the noble gases, 10% of the iodine, and 1%of the particulate nuclides are available for release to the environment. (Appendix C of Ref. 2). However, for the gland seal condenser, it is assumed due to the forced flow pathway for releases that 100% of all of the activity that reaches this condenser are available for release to the environment.

7. All leakage from the main steam turbine condenser leaks to the atmosphere as a ground level release at a rate of 1% per day through the worst case LOCA MSIV release points, for a period of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (Ref. 2, 4).

8. The control room occupancy factor was assumed to be 1 because the duration of this analysis of the CRDA is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Therefore the occupancy factor is essentially ignored.

CALCULATION NO. DRE02-0037 I REV. NO. 001 PAGE NO. 9 l

4. DESIGN INPUT 4.1. x/< Calculations (Meteorology)

The CR X/O values input to RADTRAD were taken from ARCON96 results of Exelon (ComEd) Design Calculation DRE04-0030, Rev. 1. The x/a calculated by ARCON96 for the worst-case MSIV release point to the Control Room fresh air intake is used for the 1% per day condenser leakage.

The CR atmospheric relative concentrations used are as follows (Ref. 8):

x/o =1.30E-03 sec/m 3 (0-2 hours)

X/6 =1.06E-03 sec/mr3 (2-8 hours) x/O =4.49E-04 sec/mr3 (8-24 hours)

The EAB and LPZ x/O values input to RADTRAD were taken from PAVAN results of Exelon (ComEd) Design Calculation DRE04-0030, Rev. 1.They reflect the worst-case x/a which are the MSIV release pathway values at ground-level. The EAB/LPZ atmospheric relative concentrations used are as follows (Ref. 8):

EAB X/a =2.51 E-04 sec/r 3 (0-2 hours)

LPZ x/o =2.63E-05 sec/mr3 (0-2 hours)

X/1 =1.09E-05 sec/m 3 (2-8 hours) x/a =7.02E-06 sec/mr3 (8-24 hours) 4.2. Plant Data

Power Level, (102% of 2957 to account for uncertainty) (Ref. 12) 3016 MWt

Radial Peaking Factor (Ref. 14) 1.7

Number of Failed Fuel Rods, bounding case (Ref. 7 and UFSAR Section 15.4.10.5, for bounding 7 x 7 fuel array) 850

Isotopic Release Fractions, as per Reg. Guide 1.183 (Ref. 2) See Attachment A

Volume of primary system (MSL and dome) 5,000 ft3 (Conservatively reduced from 8,431 ft3) (Ref. 11)

Vapor space volume of the condenser (UFSAR 15.4.10.5) (Ref. 3) 55,000 ft3

Gland Seal Condenser Release Fraction (Ref. 11) .0015

CALCULATION NO. DRE02-0037 . g REV. NO. 001 PAGE NO. 10 4.3. Control Room Data

Volume of Control Room Emergency Zone, ft3 (Ref. 3, 7) 81,000

Volume of Control Room Proper, ft3 (Ref. 3, 7) 64,000

Control Room Normal Intake Flow, scfm 64,000 (Smaller Control Room volume is used, as the flow rate maximizes inhalation doses, and for interior cloud doses, the appropriate volume is the control room proper).

4.4. Source Terms The AST values used in this analysis were derived using guidance outlined in Reg. Guide 1.183. A list of 60 core isotopic nuclides and their curie per megawatt activities were extracted from Appendix D of the GE task report No. GE-NE-A22-00103-64-01 (Ref. 15) for input into the RADTRAD "NIF' (see Attachment C). The release fractions associated with all of these nuclide groups, as detailed in Reg. Guide 1.183, were applied to their given groups in Attachment A, and subsequently input into the appropriate RADTRAD 'RTF", as seen in Attachment D. RADTRAD uses these files combined with the power of 3016 MWt (102% power, to account for uncertainty) to develop the source terms for this CRDA.

I CALCULATION NO. DRE02-0037 I REV. NO. 001 I PAGE NO. 1 1 I I CALCULATION NO. DREO2-0037 I REV. NO. 001 I PAGENO. 1).

5. REFERENCES

1. NUREG-1465, 'Accident Source Terms for Light-Water Nuclear Power Plants", February 1995

2. USNRC Regulatory Guide 1.183, "Alternative Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors", July 2000

3. Dresden Unit 2 & 3 UFSAR, Rev. 4.

4. USNRC SRP 15.0.1; Rev. 0, Radiological Consequences Using Alternate Source Terms.

5. NUREGICR-6604, "RADTRAD: A Simplified Model for RADionuclide Transport and Removal And Dose Estimation", April1998, and Supplement 1, June 1999.

6. TID 14844 , 'Calculation of Distance Factors for Power and Test Reactor Sites", March, 1962.

7. Exelon (ComEd) Design Analysis DRE00-0028, Analytic Limit for MSLRM Reading Following a CRDA, Rev. 1.

8. Exelon (ComEd) Design Analysis DRE04-0030, Atmospheric Dispersion Factors (X/Qs) for Accident Release, Rev. 1.

9. Deleted

10. 10 CFR 50.67

11. Bechtel Power Corporation Design Calculation DR-357-M-004, "Control Rod Drop Accidentl MSLRM Removal", Rev. 0.

12. Exelon (ComEd) Design Analysis DREOO-0071, "Impact of Extended Power Uprate on Site Boundary and Control Room Doses for LOCA and Non-LOCA Events', Rev. 0.

13. Exelon Letter RS-01-183 to the USNRC, 'Additional Radiation Dose Information Supporting the License Amendment Request to Permit Uprated Power Operation", Aug. 31, 2001.

14. NEDC-32868P, GE14 GESTAR Compliance Document

15. 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", August 2000.

16. Deleted

17. U.S. Federal Guidance Report No.11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion", 1988.

18. U.S. Federal Guidance Report No.12, "External Exposure to Radionuclides in Air, Water, and Soil", 1993.

19. NEDO-31400A Class I, "Safety Evaluation for Eliminating the BWR MSIV Closure Function and Scram Function of the MSLRM", October 1992

CALCULATION NO. DRE02-0037 _ REV. NO. 001 l PAGE NO.12

6. CALCULATIONS 6.1. Source Term Calculation The source terms are calculated by RADTRAD, using input values of core activity (as a function of power), nuclide release fractions, and-core power. For this analysis, a list of 60 core isotopic nuclides and their curie per megawatt activities were extracted from Appendix D of the GE task report No. GE-NE-A22-00103-64-01 (Ref. 15) for input into the RADTRAD 'NIF' (see Attachment C). The AST release fractions associated with all of these nuclide groups are derived using guidance outlined in Reg. Guide 1.183, as applied in Attachment A. The final gap release and fuel melt release fraction calculated in that attachment, for each nuclide group, is then input into the appropriate RADTRAD 'RTF", as seen in Attachment D. RADTRAD applies the input core power of 3016 MWt (102% power, to account for uncertainty) (Ref. 12) to these two input files to develop the core source term activities for this CRDA. Radioactive decay and daughter products are considered in RADTRAD, with this RADTRAD option turned "on".

6.2. Dose Calculations The RADTRAD v. 3.03 computer code is used to determine Dresden 2&3 CRDA doses at the three dose points cited in Reg. Guide 1.183 (Ref. 2); the Exclusion Area Boundary (EAB), Low Population Zone (LPZ), and Control Room. RADTRAD 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.

RADTRAD estimates the releases using the Reference 2 Alternate Source Term source terms and assumptions. The RADTRAD code uses a combination of tables and/or numerical models of source term reduction phenomena to determine the time-dependent dose at user-specified locations for a given accident scenario. The code system also provides the inventory, decay chain, and dose conversion factor tables needed for the dose calculation. The technical basis for the RADTRAD code is documented in Section 2 of NUREG/CR-6604 (Ref. 5).

Separate RADTRAD runs are made for the main condenser and the gland seal condenser leakages. This output is provided in Attachment B. The following is a parameter and descriptions listing of input into the RADTRAD models:

A. Compartments

1. Reactor Coolant - This compartment represents the cooling water within the primary containment vessel.

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

b. Volume - 1 ft3 - This nominal value, used to simplify input, is based on there being a fractional leak rate associated with this compartment.

c. Source term fraction - 1.0 - All of the source term is generated in the reactor coolant.

d. Compartment features - none selected.

2. Condenser - This compartment is the internal volume of the steam condenser.

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

b. Volume - 55,000 ft3 - actual free volume.

c. Source term fraction - 0.0

d. Compartment features - none selected.

I CALCULATION NO. DRE02-0037 I REV. NO. 001 PAGE NO.13

3. Environment

a. Compartment type - Environment

4. 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 - Main Condenser

1. Filtered Flow, Reactor Coolant to Condenser

a. From Compartment I - Reactor Coolant

b. To Compartment 2 - Condenser

c. Transfer mechanism - "Filter" selected

d. Filter Efficiency Panel - Flow rate - 275 cfm - With the Reactor Coolant volume set to the nominal value of 1 ft3, this flow rate transfers 99% of the intended activity to the Condenser within 1 second.

e. Filter Efficiency Panel - Filter efficiency is 0.0%, as no filtration is considered for this accident analysis.

f. Active Pathway - Yes

2. Filtered Flow, Condenser to Environment

a. From Compartment 2 - Condenser

.b. To Compartment 3 - Environment

c. Transfer mechanism - "Filter" selected -

d. Filter Efficiency Panel - Flow rate - 0.3819 cfm for 0.0-24 hrs - This indicates the activity leaks from the Main Condenser at a rate of 1% per day for the duration of the accident.

e. Filter Efficiency Panel - Filter efficiency is 0.0%, as no filtration is considered for this accident analysis.

f. Active Pathway - Yes

3. Filtered Flow, Environment to Control Room

a. From Compartment 3 - Environment

b. To Compartment 4 - 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 0.0%, as no filtration is considered for this accident analysis.

f. Active Pathway - Yes

4. Filtered Flow, Control Room to Environment

a. From Compartment 4 - Control Room

b. To Compartment 3 - Environment

c. Transfer mechanism-"Filter" selected -

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

CALCULATION NO. DRE02-0037 REV. NO. 001 PAGE NO.14

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. Transfer Pathways - Gland Seal Condenser

5. Filtered Flow, Reactor Coolant to Condenser a From Compartment I - Reactor Coolant b To Compartment 2 - Condenser c Transfer mechanism -"Filter" selected d Filter Efficiency Panel - Flow rate - 275 cfm - With the Reactor Coolant volume set to the nominal value of 1 ft3, this flow rate transfers 99% of the intended activity to the Condenser within 1 second.

e Filter Efficiency Panel - Filter efficiency is 0.0%, as no filtration is considered for this accident analysis.

f Active Pathway - Yes

6. Filtered Flow, Environment to Control Room a From Compartment 3 - Environment b To Compartment 4 - 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 0.0%, as no filtration is considered for this accident analysis.

f Active Pathway - Yes

7. Filtered Flow, Control Room to Environment a From Compartment 4 - Control Room b To Compartment 3 - 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

8. Filtered Flow, Reactor Coolant to Environment

a. From Compartment 1 - Reactor Coolant

b. To Compartment 3 - Environment - Through Gland Seal system

c. Transfer Mechanism - "Filter" selected

d. Filter Efficiency Panel - Flow Rate 0.4125 cfm - 0.15% of the 275 cfm nominal value is chosen as the rate to evacuate activity from the coolant to the gland seal steam condenser, as described on sheet 13 of Reference 11.

e. Filter Efficiency Panel - Filter efficiency is 0.0%, as no filtration is considered for this release path.

f. Active Pathway - Yes D. Dose Locations

CALCULATION NO. DRE02-0037 I REV. NO. 001 PAGE NO.15

1. Exclusion Area Boundary

a. In Compartment 3 - Environment

b. Breathing Rate Default - not checked

c. x/Q -2.51 E-04 sec/M 3 for 0-2 hrs - This represents the conservatively chosen MSIV LOCA release points.

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). This value is entered from time 0 to the end of'the accident.

2. Low Population Zone

a. In Compartment 2 - Environment

'b. Breathing' Rate Default - not checked

c. 'IQ-2.63E-05 sec/M 3 for 0-2 hrs; 1.09E-05 sec/M 3 for 2-8 hrs; 7.02E-06 sec/M 3 for 8-24 hrs; - These represent the conservatively chosen MSIV LOCA release points.

d. Breathing Rate - 3.47E-04 m3 /sec for 0-8 hrs; 1.75E-04 m3 /sec for 8-24 hrs - this is the Reg. Guide 1.183 specified breathing rate, with the traditional three digit accuracy (RADTRAD default), assuming a time dependant reduction.

3. Control Room

a. In Compartment 3 - Control Room

b. Breathing Rate Default - not checked

c. X/Q - 1.30E-03 sec/M 3 for 0-2 hrs; 1.06E-03 sec/M 3 for 2-8 hrs; and 4.49E-04 sec/M 3 for 8-24 hrs - These represent the conservatively chosen MSIV LOCA release points.

d. Breathing Rate - 3.47E-04 m3 /sec for 0-24 hrs - this.is the Reg. Guide 1.183 specified breathing rate, with the traditional three digit accuracy (RADTRAD default).

e. Occupancy Factor - I - For the duration of the accident.

E. Source Term

a. The "Dres QDC Source Terms.nif' file [Attachment C] reflects the Dresden core activities, and is modified to reflect the "Alternate Source Term" activities provided by Reference 15.

b. The power level of 3016.00 MWt, as per Section 4.2 above, reflects a core at 102%

power, accounting for uncertainty.

c. There is no credited delay in the release of activity.

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

e. The dre-qdc-crda.rft files [Attachment D] is designed to reflect gap activity fractions per RG 1.183, Appendix C, with one for the main condenser and one (without condenser fission product deposition credit) for the gland seal condenser.'

The source terms, which are calculated in Section 6.1 above, are input as a separate RADTRAD "NIF" file. This file is included in Attachment C.

Washington Group International has pre-qualified RADTRAD for application to perform such calculations, as documented in the Computer Disclosure Sheet of Attachment F. The new design basis RADTRAD simulations utilized the design input parameters as provided in Section 4.

6.3. SJAE Release Pathway The calculation of the dose consequence from the SJAE release pathway was performed using the spreadsheet in Attachment E. The SJAE Release Pathway dose is dependent only upon the noble gas alternate source term, because all iodine and particulate nuclides are eliminated by the charcoal delay beds. The initial core activity for each noble gas, calculated at 3016 MWt (Ref. 12),

I CALCULATION NO. DRE02-0037 I REV. NO. 001 PAGE NO.16 is then multiplied by the total noble gas release fraction calculated in Attachment A. This activity is then decayed for the period of time that it is delayed in the charcoal beds:

a = aoe where:

a= nuclide activity after decay period (Ci) ao= initial nuclide activity (Ci) e= exponential constant A= decay constant (hours")

t= time of delay (hours)

It is important to note that the two noble gases in the source term of this plant, Krypton and Xenon, are characterized by different delay periods.

When the decayed activities are found, the dose conversion factors (DCF), dispersion factor (X/ 0 ),

and (for the control room dose location) geometry factors are applied. The resulting dose is what is seen via the SJAE release pathway at each respective dose location following a CRDA. See Attachment E. This does not include the release associated with steam flow to the turbine gland sealing system, which is calculated separately as described in Section 6.2.

I CALCULATION NO. DRE02-0037 I REV. NO. 001 I PAGE NO. 17 l

7.

SUMMARY

AND CONCLUSIONS Table 3 provides the Scenario 2 results from the RADTRAD code, as well as the prescribed dose acceptance criteria.

Table 7.1. RADTRAD-Analysis Resultsand Comparisons to the Acceptance Criteria EAB LPZ CR Prescribed Dose Limits (TEDE)/ 6.25 rem/ 6.25 rem/ 5 rem/

Basis Document RG 1.183 RG 1.183 10CFR50.67 RADTRAD Analysis Results in Attachment B 0.132 rem 0.0385 rem 3.00 rem (main condenser leakage)

RADTRAD Analysis Results in Attachment B 0.263 rem 0.0276 rem 1.01 rem (gland seal condenser leakage)

SJAE Release from Attachment E 0.292 rem 0.0306 rem 0.0544 rem Total Main and Gland Seal Condenser 0.395 rem 0.0661 rem 4.01 rem Leakage Total Gland Seal Condenser Leakage and .0.555 rem 0.0582 rem 1.06 rem SJAE Release All doses are acceptable.

I CALCULATION NO. DRE02-037 lREV. NO. 001 PAGE NO.18 l

8. OWNER'S ACCEPTANCE REVIEW CHECKLIST FOR EXTERNAL DESIGN ANALYSIS DESIGN ANALYSIS NO. DRE02-0037 REV: 1 Yes No N/A

1. Do assumptions have sufficient rationale? v00

2. Are assumptions compatible with the way the plant is

2. operated and with the licensing basis? vl O1 o

3. Do the design inputs have sufficient rationale? la, 0 0

4. Are design inputs correct and reasonable? E VO 0

5. Are design inputs compatible with the way the plant is operated and with the licensing basis? E 0 c

6. Are Engineering Judgments clearly documented and

6. justified? V/ ° 0

7. Are Engineering Judgments compatible with the way the plant is operated and with the licensing basis? M O O0 Do the results and conclusions satisfy the purpose and objective of the Design Analysis? CV 01 01

9. Are the results and conclusions compatible with the way the plant. is operated and with the licensing basis? 01 0 l0. Does the Design Analysis include the applicable design 10 basis documentation? EV 01 0 11.

Have any limitations on the use of the results been identified and transmitted to the appropriate organizations?

V/103 0

12. Are there any unverified assumptions?

13. Do all unverified assumptions have a tracking and closure 011 13 mechanism in place? 01 0 Have all affected design analyses been documented on the

14. Affected Documents List (ADL) for the associated Er 0 0 Configuration Change?

Do the sources of inputs and analysis methodology used meet current technical requirements and regulatory

15. commitments? (If the input sources or analysis 15 methodology are based on an out-of-date methodology or 20 0E code, additional reconciliation may be required if the site has since committed to a more recent code)

Have vendor supporting technical documents and references

16. (including GE DRFs) been reviewed n necessary? X/O 0 EXFELON R~EVIEWER:, S!;t' DATE: d*3/ 4

CRDA AST RADTRAD INPUTS DERIVATION -RELEASE FRACTION THAT LEAVES THE CONDENSER USING RG 1.183 APP. C Constants:.

Valus Description Basis 850 Failed fuel rods - bounding case DREOO-0071/ODC-0000-N-1020 45612 Fuel rods In fuill core DREOO-0071/QDC-0000-N-1 020 0.018635 Fraction of rods In core with gap activity release 8501456121 l___.

1.7 Peaking fator _ [ NEDC-32868P 0.03168 Gap activity release potential with peaking 1.7 x .018635 0.0077 Fraction of fuel In failed rods assumed to melt DREOO-0071/QDC-0000-N-1020 0.000244 Melted fuel activity release potential with peakin .03168 x .0077 .

Fraction ____i Activity Activity Fraction %vailablefor Fraction Fraction Released Release Duration (h): Released Duration (h):

Released from from 1.OOOOE4-031 from . 1.OOOOE4-03 from Gap Vessels CondenseiNoble Gases, Melted Fuel Noble Gases:

0.1 1 1 3.1680E-03 0.9 2.1954E-04 Iodine: IIodine:

0.1 0.1 0.1 3.1680E405 0.45 1.0977E406

_Cesium: Cesium:

0.12 0.01 0.01 3.8016E-07 ______0.2 4.8788E-09 _ __

Tellurium: Tellurium:

0 0.01 0.01 O.OOOOE+00 0.05 1.2197E-09 Strontium: Strontium:

0 0.01 0.01 0.OOOOE+0O _0.02 4.8788E-10 Barium: _ Barium: .

0 0.01 0.01 O.OOOOE+00 0.02 4.8788E-10 Ruthenium: _ Ruthenium:

0 0.01 0.01 0.OOOOE+00 0.0025 6.0984E-11 Cerium: Cerium:

0 0.01 0.01 0.OOOOE+00 0.0005 1.2197E-11 Lanthanum: Lanthanum:

0 0.01 0.01 O.OOOOE+00 0.0002 4.8788E-12 . -

From Appendix C. paragraph 1. (for Noble gases and Iodine) and Table 3 (for Cesium, an Alkali Metal) of Regulatory Guide 1.183 From Appendix C, paragraph 3.3 of Regulatory Guide 1.183 I I I .

From Appendix C, paragraph 3.4 of Regulatory Guide 1.183 From Reg. Guide 1.183, Table 1, Early In-vessel Release Column, with 50% total Iodine release per Appendix C, paragraph 1 to account for the 50% iodines release from fuel melting per Appendix C paragraph 1.

RELEASE FRACTION DRE02-0037, Rev. 1, Attachment A, Page 1 of 3

CRDA AST RADTRAD INPUTS DERIVATION - RELEASE FRACTION THAT LEAVES THE CONDENSER USING RG 1.183 APP. C; ConstantsJ Value Descrfption Basis 850 Failed fuel rods - bounding case DREOO-0071/QDC-O000-N-1020 45612 Fuel rods In full core DREOO-0071lIDC-0000-N-1020 0.018635 Fraction of rods In core with gap activity release potential 850/45612 l l 1.7 Peaking factor I l NEDC-32868P lX ___ ]

0.03168 Gap activity release potential with peaking 1.7 x .018635 0.0077 Fraction of fuel In failed rods assumed to melt DREOO-0071/QDC-0000-N-1020 0.000244 Melted fuel activity release potential with peaking .03168 x .0077 Fraction Activity Acivity Fraction Available for Fraction _

Fraction Released Release Duration (h): Released Duration (h):

Released from from 1.OOOOE-03 from 1.OOOOE-03 from Gap' Vesselz Condenser Noble Gases: Melted Fuer Noble Gases:

0.1 1 1 3.1680E-03 0.9 2.1954E-04 Iodine: Iodine:

0.1 0.1 .1 3.1680E-04 0.45 1.0977E-05 Cesium: Cesium:

0.12 0.01 1 3.8016E-05 0.2 4.8788E-07 l Tellurium: Tellurium:

0 0.01 1 O.OOOOE+00 0.05 1.2197E-07 Strontium: Strontium:

0 0.01 1 O.OOOOE+00 0.02 4.8788E-08 Barium: Barium:

0 0.01 1 O.OOOOE+00 0.02 4.8788E-08 Ruthenium: Ruthenium:

0 0.01 1 O.OOOOE+00 0.0025 6.0984E-09 l Cerium: X __DX__Cerium:

0 0.01 1 O.OOOOE+00 0.0005 1.2197E-09 Lanthanum: . Lanthanum:

0 0.01 1 0.OOOOE+00 0.0002 4.8788E-10 From Appendix C, paragraph 1. (for Noble gases and Iodine) and Table 3 (for Cesium, an Alkali Metal) of Regulatory Guide 1.183 From Appendix C, paragraph 3.3 of Regulatory Guide 1.183 l l l l 3

Without Regulatory Guide 1.183 Paragraph 3.4 credit for no deposition in the Gland Seal Condenser for forced releases From Reg. Guide 1.183, Table 1, Early In-vessel Release Column, with 50% total Iodine release per Appendix C. paragraph 1 to account for the 50% iodines release from fuel melting per Appendix C paragraph 1.

RELEASE FRACTION DRE02-0037. Rev. 1, Attachment A, Page 2 of 3

CRDA AST RADTRAI Constants:

Value Description Basis 850 Faited fuel rods - bounding case DREOO-00711ODC-0000-t 45612 Fuel rods in full core DREOO-0071/QDC-0000-t

=A5/A6 Fraction of rods In core with gap activi 1850145612 1.7 Peaking factor NEDC-32868P

=A7-A8 Gap activity release potential with pea 1.7 x .018635 0.0077 Fraction of fuel In failed rods assume DRE00-00711ODC-0000-_

=A9'A10 Melted fuel activity release potential v .03168 x.0077 F

Fraction Activity Activity Fraction Available for Fraction Fraction Released Release Duration (h): Released Duration (h):

Released from from 0.001 from 0.001 from Gap' Vessel' Condenser' Noble Gases: Melted Fuer Noble Gases:

0.1 1 1 =A$9A20'B20-C20 =(1*A20) =A$1 -H20-B20-C20 Iodine: Iodine:

0.1 0.1 1 --AS9A22'B22-C22 0.45 =A$1 'H22'822'C22 Cesium: Cesium:

0.12 0.01 1 =A$9A24-B24'C24 0.2 =AS1 -H24-B24-C24 Tellurium: Tellurium:

0 0.01 1 =AS9-A26'B26-C26 0.05 =AS11 -H26'B26'C26 Strontium: Strontium:

0 0.01 1 =A$9A28'B28'C28 0.02 =AS1 1'H28'B28'C28 Barium: Barium:

0 0.01 1 =A$9'A30'B30'C30 0.02 =A$1 ;H30'B30'C30 Ruthenium: Ruthenium:

0 0.01 1 -A$9-2B32-C32 0.0025 =AS1 1H32-B32'C32 Cerium: Cerium:

0 0.01 1 =A$9'A34'B34-C34 0.0005 =A$1 1'H34'B34'C34 Lanthanum: Lanthanum:

0 0.01 =AS9'A36'B36'C36 0.0002 =AS1 'H36'B36'C36

'From Appendix C, pI,

'From Appendix C. p_

'Without Regulatory

'From Reg. Guide 1.1 to account for the 500S__ _

RELEASE FRACTION DRE02-0037, Rev. 1, Attachment A, Page 3 of 3

DRE - Gland Seal RADTRAD Version 3.03 (Spring 2001) run on 8/12/2005 at 20:55:26 File information Plant file = P:\Users\Nuc\Exelon EOC\Discipline Files\Process\AST\Dresden &

Quad Cities AST\DRE CRDA\DRE-CRDA (Gland Seal only)(1CR airchange per min.psf Inventory file = p:\users\nuc\exelon eoc\discipline files\process\ast\dresden &

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

quad cities ast\dre crda\dre-qdc-crda-glandsealcondenser.rft Dose Conversion file = c:\program files\radtrad3-03\defaults\fgrll&12.inp 1#1 f#11 #11 1 ##1 1 ff # 1 # #

1 $1 If # # #1 1 1 #

# 1#

f #1 #1## 1 1 Radtrad 3.03 4/15/2001 Dresden Units 2&3 CRDA with Gland Sealing Steam System Operation only (1CR airchange per min)

Nuclide Inventory File:

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

3.0160E+03 Compartments:

4 Compartment 1:

Reactor Coolant 3

1.OOOOE+00 0

0' 0

0 0

Compartment 2:

Condenser 3

5.5000E+04 0

0 0

0 DRE02-0037, Rev. 1, Attachment B, Page B I of B27

DRE - Gland Seal 0

Compartment 3:

Environment 2

O.OOOOE+00 0

0 0

0 Compartment 4:

Control Room 1

6.4000E+04 0

0 0

Pathways:

5 Pathway 1:

Reactor Coolant to condenser 1

2 2

Pathway 2:

Condenser to environment 2

3 2

Pathway 3:

Environment to Control Room 3

4 2

Pathway 4:

Control Room to Environment 4

3 2

Pathway 5:

Reactor Coolant to Environment 1

3 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1 l.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 crda\dre-qdc-crda-gland sealcondenser.rft DRE02-0037, Rev. 1, Attachment B, Page B2 of B27

DRE - Gland Seal 0.000OE+00 0

9.5000E-01 4.8500E-02 1.5000E-03 1.OOOOE+00 Overlying Pool:

0 0.0000E+00 0

0 0

0 Compartments:

4 Compartment 1:

0 1

0 0

0 Compartment 2:

0 1

0 0

Compartment 3:

0 1

0 0

0 Compartment 4:

0 1

0 0

0 Pathways:

5 Pathway 1:

0 0

DRE02-0037, Rev. 1, Attachment B, Page B3 of B27

DRE - Gland Seal 0

0 0

1 3

O.OOOOE+00 2.7500E+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00

1. 6670E-01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 2.4000E+01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0

0 0

0 Pathway 2:

0 0

0 1

2 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 2.4000E+01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0

0 0

0 Pathway 3:

0 0

.0 0

0 1

2 O.OOOOE+00 6.4000E+04 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 2.4000E+01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0

0 0

0 Pathway 4:

0 0

0 1

2 O.OOOOE+00 6.4000E+04 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 2.4000E+01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0

DRE02-0037, Rev. 1, Attachment B, Page B4 of B27

-DRE - Gland Seal 0

0 0

Pathway 5:

0 0

0 1

2 o.OOOOE+00 4. 1250E-01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 2.4000E+01 O.OOOOE+00, O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0

0 0

0 Dose Locations:

3 Location 1:

EAB 3

1 2

O.OOOOE+00 2.5100E-04 2.OOOOE+00 O.OOOOE+00 1

2 O.OOOOE+00 3.47OOE-04 2.OOOOE+00 0.OOOOE+00 O

Location 2:

LPZ 3

1 4

O.OOOOE+00 2.6300E-05 2.OOOOE+00 1.O900E-05 8.0000E+00 7.0200E-06 2.4000E+01 O.OOOOE+00 1

3 O.OOOOE+00 3.4700E-04 8.OOOOE+00 1.7500E-04 2.4000E+01 O.OOOOE+00 0

Location 3:

Control Room 4

0 1

2 O.OOOOE+00 3.4700E-04 DRE02-0037, Rev. 1, Attachment B, Page B5 of B27

DRE - Gland Seal 2.4000E+01 O.OOOOE+00 1

2 O.OOOOE+00 1.OOOOE+00 2.4000E+01 O.OOOOE+00 Effective Volume Location:

1 4

O.OOOOE+00 1.3000E-03 2.OOOOE+00 1.0600E-03 8.OOOOE+00 4.4900E-04 2.4000E+01 O.OOOOE+00 Simulation Parameters:

5 O.OOOOE+00 1.0000E-04 1.0000E-02 1.0000E-03 1.0000E-01 1.OOOOE-02 1.0000E+00 1.OOOOE+00 2.4000E+01 O.OOOOE+00 Output Filename:

P:\Users\Nuc\Exelon EOC\Discipline Files\Process\AST\Dresden & Quad Cities AST\DRE CRDA\DRE-CRDA (Gland Seal only)(lCR airchange per min.oO 1

2 1

0 1

End of Scenario File DRE02-0037, Rev. 1, Attachment B, Page B6 of B27

DRE - Gland Seal RADTRAD Version 3.03 (Spring 2001) run on 8/12/2005 at 20:55:26 Plant Description Number of Nuclides = 60 Inventory Power = 1.0000E+00 MWth Plant Power Level = 3.0160E+03 MWth Number of compartments 4 Compartment information Compartment number 1 (Source term fraction = 1.OOOOE+00 Name: Reactor Coolant Compartment volume = l.OOOOE+00 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 1 Exit Pathway Number 1: Reactor Coolant to condenser Exit Pathway Number 5: Reactor Coolant to Environment Compartment number 2 Name: Condenser Compartment volume = 5.5000E+04 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 2 Inlet Pathway Number 1: Reactor Coolant to condenser Exit'Pathway Number 2: Condenser to environment Compartment number 3 Name: Environment Compartment type is Environment Pathways into and out of compartment 3 Inlet Pathway Number 2: Condenser to environment Inlet Pathway Number 4: Control Room to Environment Inlet Pathway Number 5: Reactor Coolant to Environment Exit Pathway Number 3: Environment to Control Room Compartment number 4 Name: Control Room Compartment volume = 6.4000E+04 (Cubic feet)

Compartment type is Control Room Pathways into and out of compartment 4 Inlet Pathway Number 3: Environment to Control Room Exit Pathway Number 4: Control Room to Environment Total number of pathways = 5 DRE02-0037, Rev. 1, Attachment B, Page B7 of B27

DRE - Gland Seal RADTRAD Version 3.03 (Spring 2001) run on 8/12/2005 at 20:55:26 t

lu# i###

Dose Output Detailed model information at time (H) = 0.0010 EAB Doses:

Time (h) = 0.0010 Whole Body Thyroid TEDE Delta dose (rem) 5.7988E-02 4.8202E+00 2.1780E-01 Accumulated dose (rem) 5.7988E-02 4.8202E+00 2.1780E-01 LPZ Doses:

Time (h) = 0.0010 Whole Body Thyroid TEDE Delta dose (rem) 6.0760E-03 5.0507E-01 2.2821E-02 Accumulated dose (rem) 6.0760E-03 5.0507E-01 2.2821E-02 Control Room Doses:

Time (h) = 0.0010 Whole Body Thyroid TEDE Delta dose (rem) 3.0001E-04 6.9456E-01 2.3328E-02 Accumulated dose (rem) 3.0001E-04 6.9456E-01 2.3328E-02 Detailed model information at time (H) = 0.0020 EAB Doses:

Time (h) = 0.0020 Whole Body Thyroid TEDE Delta dose (rem) 1.2770E-02 9.7304E-01 4.5063E-02 Accumulated dose (rem) 7.0758E-02 5.7933E+00 2. 6286E-01 LPZ Doses:

Time (h) = 0.0020 Whole Body Thyroid TEDE Delta dose (rem) 1.3380E-03 1.0196E-01 4.7217E-03 Accumulated dose (rem) 7.4141E-03 6.0702E-01 2.7543E-02 Control Room Doses:

DRE02-0037, Rev. 1, Attachment B, Page B8 of B27

DRE - Gland Seal Time (h) = 0.0020 Whole Body Thyroid TEDE Delta dose (rem) 7.2078E-04 1.6577E+00 5.5685E-02 Accumulated dose (rem) 1.0208E-03 2.3523E+00 7. 9013E-02 Detailed model information at time (H) = 0.1667 EAB Doses:

Time (h) = 0.1667 Whole Body' Thyroid TEDE Delta dose (rem) 2.0644E-04 1.0776E-02 5.6606E-04 Accumulated dose (rem) 7.0964E-02 5.8040E+00 2. 6343E-01 LPZ Doses:

Time (h) = 0.1667 Whole Body Thyroid TEDE Delta dose (rem) 2.1631E-05 1.1291E-03 5.9313E-05 Accumulated dose (rem) 7.4357E-03 6.0815E-01 2.7602E-02 Control Room Doses:

Time (h) = 0.1667 Whole Body Thyroid TEDE Delta dose (rem) 1.2106E-02 2.7706E+01 9.3077E-01 Accumulated dose (rem) 1.3127E-02 3.0058E+01 1.0098E+00 Detailed model information at time (H) = 2.0000 EAB Doses:

Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 7.0964E-02 5.8040E+00 2. 6343E-01 LPZ Doses:

Time (hi = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 7.4357E-03 6.0815E-01 2.7602E-02 Control Room Doses:

Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 6.0085E-07 1.4464E-03 4.8523E-05 Accumulated dose (rem) 1.3128E-02 3.0059E+01 1.0098E+00 Detailed model information at time (H) = 8.0000 EAB Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 7.0964E-02 5.8040E+00 2. 6343E-01 LPZ Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 DRE02-0037, Rev. I, Attachment B, Page B9 of B27

DRE - Gland Seal Accumulated dose (rem) 7.4357E-03 6.0815E-01 2.7602E-02 Control Room Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.7868E-54 6. 9882E-51 2.3204E-52 Accumulated dose (rem) 1.3128E-02 3.0059E+01 1.0098E+00 Detailed model information at time (H) = 24.0000 EAB Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.000E+00 Accumulated dose (rem) 7 0964E-02 5.8040E+00 2.6343E-01 LPZ Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.00OE+00 O.OOOOE+00 0.000OE+00 Accumulated dose (rem) 7.4357E-03 6.0815E-01 2.7602E-02 Control Room Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.7947-211 2.9035-207 9.5487-209 Accumulated dose (rem) 1.3128E-02 3.0059E+01 1.0098E+00 411 I-131 Summary Reactor Coolant Condenser Environment.

Time (hr) I-131 (Curies) I-131 (Curies) I-131 (Curies) 0.000 1.2669E+03 1.3208E+03 1.9812E+00

0. 001 1.5672E+03 2.4293E+04 3.6440E+01 0.002 5.4302E+01 2.9196E+04 4.3794E+01 0.167 O.OOOOE+00 2.9233E+04 4.3876E+01 0.420 O.OOOOE+00 2.9206E+04 4.3876E+01 0.670 O.OOOOE+00 2.9180E+04 4.3876E+01 0.920 O.OOOOE+00 2.9154E+04 4.3876E+01 1.300 O.OOOOE+00 2.9114E+04 4.3876E+01

1. 600 O.OOOOE+00 2.9083E+04 4.3876E+01 1.900 O.OOOOE+00 2.9051E+04 4.3876E+01 2.000 O.OOOOE+00 2.9041E+04 4.3876E+01 2.300 O.OOOOE+00 2.9010E+04 4.3876E+01 2.600 O.OOOOE+00 2.8979E+04 4.3876E+01 2.900 O.OOOOE+00 2.8947E+04 4.3876E+01 3.200 O.O00OE+00 2.8916E+04 4.3876E+01 3.500 O.OOOOE+00 2.8885E+04 4.3876E+01 3.800 O.OOOOE+00 2.8854E+04 4.3876E+01 4.100 O.OOOOE+00 2.8823E+04 4.3876E+01 4.400 O.OOOOE+00 2.8792E+04 4.3876E+01 4.700 O.OOOOE+00 2.8761E+04 4.3876E+01 5.000 O.OOOOE+00 2.8730E+04 4.3876E+01 DRE02-0037, Rev. 1, Attachment B, Page BIO of B27

DRE - Gland Seal 5.300 O.OOOOE+00 2.8699E+04 4. 3876E+01 5.600 O.OOOOE+00 2.8668E+04 4.3876E+01 5.900 O. OOOOE+00 2.8637E+04 4.3876E+01 6.200 O. OOOOE+00 2.8606E+04 4.3876E+01 6.500 0. OOOOE+00 2.8575E+04 4.3876E+01 6.800 0. OOOOE+00 2.8545E+04 4.3876E+01 7.100 0.OOOOE+00 2.8514E+04 4.3876E+01 7.400 0.OOOOE+00 2.8483E+04 4 .3876E+01 7.700 0.OOOOE+00 2.8452E+04 4.3876E+01 8.000 0.OOOOE+00 2.8422E+04 4.3876E+01 8.300 0. OOOOE+00 2.8391E+04 4.3876E+01 8.600 O. OOOOE+00 2.8361E+04 4.3876E+01 8.900 O. OOOOE+00 2.8330E+04 4.3876E+01 9.20b O.OOOOE+00 2.8300E+04 4 .3876E+01 9.500 O. OOOOE+00 2.8269E+04 4.3876E+01 9.800 O. OOOOE+00 2.8239E+04 4.3876E+01 10.100 O. OOOOE+00 2'.8208E+04 4. 3876E+01

10. 400 0. OOOOE+00 2.8178E+04 4.3876E+01 24.000 O.OOOOE+00 2.6834E+04 4.3876E+01 Control Room Time (hr) I-131 (Curies)

0. 000 7.7619E-02 0.001 1.3911E+00 0.002 1.5848E+00 0.167 8.1077E-05 0.420 2.0328E-11 0.670 6.2128E-18 0.920 1.8988E-24 1.300 2.3764E-34 1.600 3.6150E-42 1.900 5.4990E-50 2.000 1.3625E-52 2.300 2.0726E-60 2.600 3.1529E-68 2.900 4.7961E-76 3.200 7.2957E-84 3.500 1.1098E-91 3.800 1.6882E-99 4.100 2.5681-107 4.400 3.9065-115 4.700 5.9425-123 5.000 9.0396-131 5.300 1.3751-138 5.600 2.0918-146 5.900 3.1820-154 6.200 4.8403-162 6.500 7.3630-170 6.800 1.1200-177 7.100 1.7038-185 7.400 2.5918-193 7.700 3.9426-201 8.000 5.9973-209 8.300 9.1230-217 8.600 1.3878-224 8.900 2.1111-232 9.200 3.2113-240 DRE02-0037, Rev. 1, Attachment B, Page B I of B27

DRE - Gland Seal 9.500 4.8850-248 9.800 7.4309-256 10.100 1.1304-263 10.400 1.7195-271 24.000 O.OOOOE+00 Cumulative Dose Summary EAB LPZ Control Room Time Thyroid TEDE Thyroid TEDE Thyroid TEDE (hr) (rem) (rem) (rem) (rem) (rem) (rem) 0.000 O.OOOOE+00 O0OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0.001 4.8202E+00 2.1780E-01 5. 0507E-01 2.2821E-02 6. 9456E-01 2.3328E-02 0.002 5.7933E+00 2.6286E-01 6.0702E-01 2.7543E-02 2.3523E+00 7.9013E-02 0.167 5.8040E+00 2 6343E-01 6.0815E-01 2.7602E-02 3.0058E+01 1.0098E+00 0.420 5.8040E+00 2. 6343E-01 6. 0815E-01 2.7602E-02 3.0059E+01 1.0098E+00 0.670 5.8040E+00 2. 6343E-01 6. 0815E-01 2.7602E-02 3.0059E+01 1.0098E+00 0.920 5.8040E+00 2. 6343E-01 6.0815E-Ol 2.7602E-02 3.0059E+01 1.0098E+00 1.300 5.8040E+00 2. 6343E-01 6.0815E-01 2.7602E-02 3.0059E+01 1.0098E+00 1.600 5.8040E+00 2.6343E-01 6.0815E-Ol 2.7602E-02 3.0059E+01 1.0098E+00 1.900 5.8040E+00 2.6343E-01 6.0815E-01 2.7602E-02 3.0059E+01 1.0098E+00 2.000 5.8040E+00 2. 6343E-01 6.0815E-01 2.7602E-02 3.0059E+01 1.0098E+00 2.300 5.8040E+00 2.6343E-01 6.0815E-01 2.7602E-02 3.0059E+01 1.0098E+00 2.600 5.8040E+00 2.6343E-01 6.0815E-01 2.7602E-02 3.0059E+01 1.0098E+00 2.900 5.8040E+00 2. 6343E-01 6.0815E-01 2.7602E-02 3.0059E+01 1.0098E+00 3.200 5.8040E+00 2. 6343E-01 6. 0815E-01 2.7602E-02 3.0059E+01 1.0098E+00 3.500 5.8040E+00 2. 6343E-01 6. 0815E-01 2.7602E-02 3.0059E+01 1.0098E+00 3.800 5.8040E+00 2. 6343E-01 6.0815E-01 2.7602E-02 3.0059E+01 1.0098E+00 4.100 5.8040E+00 2. 6343E-01 6.0815E-01 2.7602E-02 3.0059E+01 1.0098E+00 4.400 5.8040E+00 2. 6343E-01 6.0815E-01 2.7602E-02 3.0059E+01 1.0098E+00 4.700 5.8040E+00 2. 6343E-01 6.0815E-01 2.7602E-02 3.0059E+01 1.0098E+00 5.000 5.8040E+00 2. 6343E-01 6.0815E-01 2.7602E-02 3.0059E+01 1.0098E+00 5.300 5.8040E+00 2.6343E-01 6.0815E-01 2.7602E-02 3.0059E+01 1.0098E+00

.5.600 5.8040E+00 2.6343E-01 6.0815E-01 2.7602E-02 3.0059E+01 1.0098E+00 5.900 5.8040E+00 2. 6343E-01 6.0815E-01 2.7602E-02 3.0059E+01 1.0098E+00 6.200 5.8040E+00 2.6343E-01 6.0815E-Ol 2.7602E-02 3.0059E+01 1.0098E+00 6.500 5.8040E+00 2.6343E-01 6.0815E-01 2.7602E-02 3.0059E+01 1.0098E+00 6.800 5.8040E+00 2. 6343E-01 6.0815E-01 2.7602E-02 3.0059E+01 1.0098E+00 7.100 5.8040E+00 2.6343E-01 6.0815E-01 2.7602E-02 3.0059E+01 1.0098E+00 7.400 5.8040E+00 2. 6343E-01 6.0815E-01 2.7602E-02 3.0059E+01 1.0098E+00 7.700 5.8040E+00 2. 6343E-01 6.0815E-01 2.7602E-02 3.0059E+01 1.0098E+00 8.000 5.8040E+00 2. 6343E-01 6.0815E-01 2.7602E-02 3.0059E+01 1.0098E+00 8.300 5.8040E+00 2. 6343E-01 6.0815E-01 2.7602E-02 3.0059E+01 1.0098E+00 8.600 5.8040E+00 2.6343E-01 6.0815E-Ol 2.7602E-02 3.0059E+01 1.0098E+00 8.900 5.8040E+00 2. 6343E-01 6.081SE-Ol 2.7602E-02 3.0059E+01 1.0098E+00 9.200 5.8040E+00 2.6343E-Ol 6.0815E-01 2.7602E-02 3.0059E+01 1.0098E+00 9.500 5.8040E+00 2.6343E-01 6.0815E-01 2.7602E-02 3.0059E+01 1.0098E+00 9.800 5.804OE+00 2.6343E-01 6.0815E-01 2.7602E-02 3.0059E+01 1.0098E+00 10.100 5.8040E+00 2.6343E-01 6.0815E-01 2.7602E-02 3.0059E+01 1.0098E+00 10.400 5.8040E+00 2.6343E-01 6.0815E-01 2.7602E-02 3.0059E+01 1.0098E+00 24.000 5.8040E+00 2.6343E-01 6.0815E-01 2.7602E-02 3.0059E+01 1.0098E+00 Worst Two-Hour Doses DRE02-0037, Rev. 1, Attachment B, Page B 12 of B27

-DRE - Gland Seal EAB Time Whole Body Thyroid TEDE (hr) (rem) (rem) (rem) 0.0 7.0964E-02 5.8040E+00 . 2.6343E-0l DRE02-0037, Rev. 1, Attachment B, Page B13 of B27

DRE - Gland Seal RADTRAD Version 3.03 (Spring 2001) run on 8/12/2005 at 20:51:24

1. 1. I 11 1 11 ###########I#######I####I

1. 1. 1. 1. I

1. 1. 1. 1. II#If#fIIII#######f##I#I##II##########fJ##II#I#I######1141###

File information IIIIIIIIWIIII###i#II#I#####II####III#########I#IIIIII#I#iHU##I###III#I##

Plant file P:\Users\Nuc\Exelon.EOC\Discipline Files\Process\AST\Dresden &

Quad Cities AST\DRE CRDA\DRE-CRDA condenserpath (1CR airchange per min).psf Inventory file = p:\users\nuc\exelon eoc\discipline files\process\ast\dresden &

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

quad cities ast\dre crda\dre-qdc-crda-maincondenser.rft Dose Conversion file = c:\program files\radtrad3-03\defaults\fgrll&12.inp

1111 #111 I11111 1 #1 # # ## 1# # # #

I # # I # # # # # 4 # Ir n

1111 1111 l#

I I I

I I # # . $#f ## # #

# ## ###I Radtrad 3.03 4/15/2001 Dresden Units 2&3 CRDA with 1 percent per day condenser volume release rate (1CR airchange per min)

Nuclide Inventory File:

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

3.0160E+03 Compartments:

4 Compartment 1:

Reactor Coolant 3

1.0000E+00 0

0 0

Compartment 2:

Condenser 3

5.5000E+04 0

0 0

0 DRE02-0037, Rev. 1, Attachment B, Page B14 of B27

DRE - Gland Seal 0

Compartment 3:

Environment 2

O.OOOOE+00 0

0 0

Compartment 4:

Control Room 1

6.4000E+04 0

0 0

Pathways: .

5 Pathway 1:

Reactor Coolant to condenser 1

2 2

Pathway 2:

Condenser to environment 2

3 2

Pathway 3:

Environment to Control Room 3

4 2

Pathway 4:

Control Room to Environment 4

3 2

Pathway 5:

Reactor Coolant to Environment 1

3 En2fPatMdlFl End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1 l.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 crda\dre-qdc-crda-main condenser.rft DRE02-0037, Rev. 1, Attachment B, Page B115 of B27

DRE - Gland Seal 0.000OE+00 1

9.5000E-01 4.8500E-02 1.5000E-03 1.OOOQE+00 Overlying Pool:

0

0. OOOOE+00 0

0 0

0 Compartments:

4 Compartment 1:

0 1

0 0

0 Compartment 2:

0 1

0 0

0 Compartment 3:

0 1

0 0

0 Compartment 4:

0 1

0 0

0 Pathways:

5 Pathway 1:

0 0

DRE02-0037, Rev. 1, Attachment B, Page B16 of B27

-DRE - Gland Seal 0

0 0

1 3

O.OOOOE+00 2.7500E+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 1.6670E-01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 2.4000E+01 O.OOOOE-+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0

0 0.

0 0

0 Pathway 2:

0 0

0 1

3 0.00 0E+00 3.8190E-01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00

2. 4000E+01 O.OOOOE+00 O.OOOE+00 O.OOOOE+00 O.OOOOE+00 4.8000E+01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0

0 0

0 Pathway 3:

0 0

0 1

2 0.00OOE+00 6.4000E+04 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 4.8000E+01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0

0 0

0 Pathway 4:

0 0

0 1

2 o .OOOOE+00 6.4000E+04 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 4.8000E+01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 DRE02-0037, Rev. 1, Attachment B, Page B17 of B27

DRE - Gland Seal 0

0 0

0 Pathway 5:

0 0

0 1

2 O.OOOOE+00 0.000OE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 2.4000E+01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0

0 0

0 Dose Locations:

3 Location 1:

EAB 3

1 2

O.OOOOE+00 2.5100E-04 2.OOOOE+00 O.OOOOE+00 1

3 O.OOOOE+00 3.4700E-04 8.OOOOE+00 1.7500E-04 2.4000E+01 O.OOOOE+00 0

Location 2:

LPZ 3

1 8

O.OOOOE+00 2.6300E-05 2.OOOOE+00 1.O900E-05 8.0000E+00 7.0200E-06 2.4000E+01 1.OOOOE-12 2.8000E+01 1.OOOOE-12 3.2000E+01 1.0000E-12 4.OOOOE+01 1.OOOOE-12 4.8000E+01 O.OOOOE+00 1

4 O.OOOOE+00 3.470OE-04 8.0000E+00 1.7500E-04 2.4000E+01 O.OOOOE+00 4.8000E+01 0.000E+00 0

DRE02-0037, Rev. 1, Attachment B, Page B 18 of B27

-DRE - Gland Seal Location 3:

Control Room 4

0 1

3 0.OOOOE+00 3.4700E-04 2.4000E+01 3.4700E-04 4.8000E+01 0.OOOOE+00 1

3 0.OOOOE+00 1.0000E+00 2.4000E+01 6.OOOOE-01 4.8000E+01 0.OOOOE+00 Effective Volume Location:.

1 5

O.OOOOE+00 1.3000E-03 1.6670E-01 1.3000E-03 2.OOOOE+00 1.0600E-03 8.0000E+00 4.4900E-04 2.4000E+01 0.OOOOE+00 Simulation Parameters:

6 0.OOOOE+00 1.OOOOE-04 1.0000E-02 1.OOOOE-03 1.OOOOE-01 1.OOOOE-02 1.0000E+00 1.0000E+00 2.4000E+01 2.OOOOE+00 4.8000E+01 0.OOOOE+00 Output Filename:

P:\Users\Nuc\Exelon EOC\Discipline Files\Process\AST\Dresden & Quad Cities AST\DRE CRDA\DRE-CRDAcondenser_path (1CR airchange per min).oO 1

2 1

0 1

End of Scenario File DRE02-0037, Rev. 1, Attachment B, Page B19 of B27

DRE - Gland Seal RADTRAD Version 3.03 (Spring 2001) run on 8/12/2005 at 20:51:24 Plant Description Number of Nuclides = 60 Inventory Power = 1.0000E+00 MWth Plant Power Level = 3.0160E+03 MWth Number of compartments = 4 Compartment information Compartment number 1 (Source term fraction - 1.OOOOE+00 Name: Reactor Coolant Compartment volume = 1.OOOOE+00 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 1 Exit Pathway Number 1: Reactor Coolant to condenser Exit Pathway Number 5: Reactor Coolant to Environment Compartment number 2 Name: Condenser Compartment volume = 5.5000E+04 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 2 Inlet Pathway Number 1: Reactor Coolant to condenser Exit'Pathway Number 2: Condenser to environment Compartment number 3 Name: Environment Compartment type is Environment Pathways into and out of compartment 3 Inlet Pathway Number 2: Condenser to environment Inlet Pathway Number 4: Control Room to Environment Inlet Pathway Number 5: Reactor Coolant to Environment Exit Pathway Number 3: Environment to Control Room Compartment number 4 Name: Control Room Compartment volume = 6.4000E+04 (Cubic feet)

Compartment type is Control Room Pathways into and out of compartment 4 Inlet Pathway Number 3: Environment to Control Room Exit Pathway Number 4: Control Room to Environment Total number of pathways = 5 DRE02-0037, Rev. 1, Attachment B, Page B20 of B27

DRE - Gland Seal RADTRAD Version 3.03 (Spring 2001) run on 8/12/2005 at 20:51:24

1. 1. # # #####~ I#####

# #~ # # # ##

i #

#t

#~ # # #

1. 1. 1. ###t# # #

1. 1. 1. 1. I#I###############I###II ####I###II###########I########1##1 Dose Output IIIIII#I##############I#######I#I##IIIIII##I i## I#######I Detailed model information at time (H) = 0.0010 EAB Doses:

Time (h) = 0.0010 Whole Body Thyroid TEDE Delta dose (rem) 7.6067E-06 6.3233E-04 2.8571E-05 Accumulated dose (rem) 7.6067E-06 6.3233E-04 2. 8571E-05 LPZ Doses:

Time (h) = 0.0010 Whole Body Thyroid TEDE Delta dose (rem) 7.9704E-07 6.6256E-05 2.9937E-06 Accumulated dose (rem) 7.9704E-07 6.6256E-05 2.9937E-06 Control Room Doses:

Time (h) = 0.0010 Whole Body Thyroid TEDE Delta dose (rem) 2.6552E-08 6.1473E-05 2.0647E-06 Accumulated dose (rem) 2.6552E-08 6.1473E-05 2.0647E-06 Detailed model information at time (H) = 0. 0020 EAB Doses:

Time (h) = 0.0020 Whole Body Thyroid TEDE Delta dose (rem) 1.8887E-05 1.5506E-03 7.0293E-05 Accumulated dose (rem) 2.6494E-05 2.1829E-03 9.8865E-05 LPZ Doses:

Time (h) = 0.0020 Whole Body Thyroid TEDE Delta dose (rem) 1.9790E-06 1.6247E-04 7.3654E-06 Accumulated dose (rem) 2.7760E-06 2.2873E-04 1.0359E-05 Control Room Doses:

DRE02-0037, Rev. 1, Attachment B, Page B21 of B27

DRE - Gland Seal Time (h) = 0.0020 Whole Body Thyroid TEDE Delta dose (rem) 1.8236E-07 4.2056E-04 1.4126E-05 Accumulated dose (rem) 2.0891E-07 4.8204E-04 1. 6190E-05 Detailed model information at time (H) = 0.1667 EAB Doses:

Time (h) = 0.1667 Whole Body Thyroid TEDE Delta dose (rem) 3.1333E-03 2.5891E-01 1.1713E-02 Accumulated dose (rem) 3.1598E-03 2.6109E-01 1. 1812E-02 LPZ Doses:

Time (h) = 0.1667 Whole Body Thyroid TEDE Delta dose (rem) 3.2831E-04 2.7129E-02 1.2273E-03 Accumulated dose (rem) 3.3109E-04. 2.7358E-02 1.2376E-03 Control Room Doses:

Time (h) = 0.1667 Whole Body Thyroid TEDE Delta dose (rem) 5.2716E-04 1.2159E+00 4.0818E-02 Accumulated dose (rem) 5.2737E-04 1.2164E+00 4.0834E-02 Detailed model information at time (H) = 2.0000 EAB Doses:

Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.6341E-02 2.8346E+00 1. 1994E-01 Accumulated dose (rem) 2.9501E-02 3.0957E+00 1.3175E-01 LPZ Doses:

Time (h) =. 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.7600E-03 2. 9702E-01 1.2567E-02 Accumulated dose (rem) 3.0911E-03 3.2437E-01 1.3805E-02 Control Room Doses:

Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 4.8987E-03 1.4681E+01 4.8968E-01 Accumulated dose (rem) 5.4260E-03 1.5898E+01 5.3051E-01 Detailed model information at time (H) = 8.0000 EAB Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 2.9501E-02 3.0957E+00 1.3175E-01 LPZ Doses:

Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.7031E-03 3.8060E-01 1.4201E-02 DRE02-0037, Rev. 1, Attachment B, Page B22 of B27

-DRE - Gland Seal Accumulated dose (rem) 4.7942E-03 7.0497E-01 2.8006E-02 Control Room Doses:

Time (h) = 8.0000 Whole Body . Thyroid TEDE Delta dose (rem) 5.9660E-03 3.7086E+01 1.2238E+00 Accumulated dose (rem) 1.1392E-02 5.2984E+01 1.7543E+00 Detailed model information at time (H) = 24.0000 EAB Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) *2..9501E-02 3.0957E+00 1.3175E-01 LPZ Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 9.3815E-04 2.9186E-01 1.0501E-02 Accumulated dose (rem) 5.7324E-03 9.9683E-01 3.8507E-02 Control Room Doses:

Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.1716E-03 3.7187E+01 1.2205E+00 Accumulated dose (rem) 1.3564E-02 9.0171E+01 2.9749E+00 Detailed model information at time (H) = 28.0000 EAB Doses:

Time (h) = 28.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 0.OOOOE+00 AccumulAted dose (rem) 2.9501E-02 3.0957E+00 1.3175E-01 LPZ Doses:

Time (h) = 28.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 5.7324E-03 9. 9683E-01 3.8507E-02 Control Room Doses:

Time (h) = 28.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.3543E-05 6.4007E-01 2.1009E-02 Accumulated dose (rem) 1.3587E-02 9.0811E+01 2.9959E+00 Detailed model information at time (H) = 32.0000 EAB Doses:

Time (h) = 32.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 2.9501E-02 3.0957E+00 1.3175E-01 LPZ Doses:

DRE02-0037, Rev. 1, Attachment B, Page B23 of B27

DRE - Gland Seal Time (h) = 32.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 5.7324E-03 9.9683E-01 3.8507E-02 Control Room Doses:

Time (h) = 32.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.1869-109 3. 6140-105 1.1869-106 Accumulated dose (rem). 1.3587E-02 9. 0811E+01 2.9959E+00 Detailed model information at time (H) = 40.0000 EAB Doses:

Time (h) = 40.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 2.9501E-02 3.0957E+00 1.3175E-01 LPZ Doses:

Time (h) = 40.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 5.7324E-03 9. 9683E-01 3.8507E-02 Control Room Doses:

Time (h) = 40.0000 Whole Body Thyroid TEDE Delta dose (rem) 6.1296-214 2.0446-209 6.7202-211 Accumulated dose (rem) 1.3587E-02 9.0811E+01 2.9959E+00 Detailed model information at time (H) = ,48.0000 EAB Doses:

Time (h) = 48.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 2.9501E-02 3.0957E+00 1.3175E-01 LPZ Doses:

Time (h) = 48.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 5.7324E-03 9.9683E-01 3.8507E-02 Control Room Doses:

Time (h) = 48.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 1.3587E-02 9.0811E+01 2.9959E+00 435 I-131 Summary DRE02-0037, Rev. 1, Attachment B, Page B24 of B27

-DRE - Gland Seal Reactor Coolant Condenser Environment Time (hr) I-131 (Curies) I-131 (Curies) I-131 (Curies)

0. 000 1.2681E+03 1.3216E+03 2.0576E-05 0.001 1.5695E+03 2.4327E+04 4.7803E-03 0.002 5.4388E+00 2.8562E+04 1.6503E-02 0.167 O.OOOOE+00 2.8548E+04 1.9760E+00 0.420 O.OOOOE+00 2.8519E+04 4.9872E+00 0.670 O.OOOE+00 2.8491E+04 7.9560E+00 0.920 O.OOOOE+00 2.8462E+04 1.0922E+01 1.300 O.OOOOE+00 2.8419E+04 1.5424E+01 1.600 O.OOOOE+00 2.8385E+04 1.8973E+01 1.900 O.OOOOE+00 2.8351E+04 2.2518E+01 2.000 O.OOOOE+00 2.8339E+04 2.3699E+01 2.3d0' O.OOOOE+00 2.8305E+04 2.7238E+01 2.600 O.OOOOE+00 2.8271E+04 3.0773E+01 2.900 O.OOOOE+00 2.8237E+04 3.4304E+01 3.200 O.OOOOE+00 2.8203E+04 3.7830E+01 3.500 0.OOOOE+00 2.8169E+04 4.1352E+01 3.800 O.OOOOE+00 2.8136E+04 4.4870E+01 4.100 O.OOOOE+00 2.8102E+04 4.8384E+01 4.400 O.OOOOE+00 2.8068E+04 5.1894E+01 4.700 O.OOOOE+00 2.8034E+04 5.5399E+01 5.000 O.OOOOE+00 2.8001E+04 5.8900E+01 5.300 0.000E+00 2.7967E+04 6.2397E+01 5.600 O.OOOOE+00 2.7933E+04 6.5890E+01 5.900 O.OOOOE+00 2.7900E+04 6.9379E+01 6.200 O.OOOOE+00 2.7866E+04 7.2863E+01 6.500 O.OOOOE+00 2.7833E+04 7.6343E+01 6.800 O.OOOOE+00 2.7799E+04 7.9819E+01 7.100 O.OOOOE+00 2.7766E+04 8.3291E+01 7.400 O.OOOOE+00 2.7732E+04 8.6758E+01 7.700 O.OOOOE+00 2.7699E+04 9.0222E+01 8.000 O.OOOOE+00 2.7666E+04 9.3681E+01 8.300 0.OOOOE+00 2.7633E+04 9.7136E+01 8.600 O.OOOOE+00 2.7599E+04 1.0059E+02 8.900 O.OOOOE+00 2.7566E+04 1.0403E+02 9.200 O.OOOOE+00 2.7533E+04 1.0748E+02 9.500 O.OOOOE+00 2.7500E+04 1.1092E+02 9.800 O.OOOOE+00 2.7467E+04 1.1435E+02

10. 100 O.OOOOE+00 2.7434E+04 1.1778E+02 10.400 O.OOOOE+00 2.7401E+04 1.2121E+02 24.000 O.OOOOE+00 2.5947E+04 2.7208E+02 28.000 O.OOOOE+00 2.5577E+04 2.7208E+02 32.000 O.OOOOE+00 2.5212E+04 2.7208E+02 40.000 O.OOOOE+00 2.4498E+04 2.7208E+02 48.000 O.OOOOE+00 2.3804E+04 2.7208E+02 Control Room Time (hr) 1-131 (Curies) 0.000 8.0663E-07 0.001 1.8420E-04 0.002 6.2038E-04 0.167 7.7834E-03 0.420 7.7759E-03 0.670 7.7681E-03 0.920 7.7603E-03 1.300 7.7485E-03 DRE02-0037, Rev. 1, Attachment B, Page B25 of B27

DRE - Gland Seal 1.600 7.7392E-03 1.900 7.7299E-03 2.000 7.7268E-03 2.300 6.2927E-03 2.600 6.2851E-03 2.900 6.2776E-03 3.200 6.2700E-03 3.500 6.2625E-03 3.800 6.2550E-03 4.100 6.2475E-03 4.400 6.2400E-03 4.700 6.2325E-03 5.000 6.2250E-03 5.30b 6.2175E-03 5.600 6.2100E-03 5.900 6.2025E-03 6.200 6.1951E-03 6.500 6..1876E-03 6.800 6.1802E-03 7.100 6.1728E-03 7.400 6.1654E-03 7.700 6.1579E-03 8.000 6.1505E-03 8.300 2.6021E-03 8.600 2.5990E-03 8.900 2.5959E-03 9.200 2.5928E-03 9.500 2.5897E-03 9.800 2.5865E-03 10.100 2.5834E-03 10.400 2.5803E-03 24.000 2.4434E-03 28.000 1.4037-107 32.000 8.0642-212 40.000 0.0000E+00 48.000 O.OOOOE+00 Cumulative Dose Summary EAB LPZ Control Room Time Thyroid TEDE Thyroid TEDE Thyroid TEDE (hr) * (rem) (rem) (rem) (rem) (rem) (rem) 0.000 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0.001 6.3233E-04 2.8571E-05 6.6256E-05 2.9937E-06 6.1473E-05 2.0647E-06 0.002 2.1829E-03 9.8865E-05 2.2873E-04 1.0359E-05 4.8204E-04 1.6190E-05 0.167 2.6109E-01 1.1812E-02 2.7358E-02 1.2376E-03 1.2164E+00 4.0834E-02 0.420 6.5782E-01 2.9453E-02 6.8927E-02 3.0861E-03 3.2712E+00 1.0970E-01 0.670 1.0477E+00 4.6456E-02 1.0978E-01 4.8677E-03 5.2903E+00 1.7724E-01 0.920 1.4359E+00 6.3096E-02 1.5045E-01 -6.6112E-03 7.3008E+00 2.4437E-01 1.300 2.0231E+00 8.7834E-02 2.1199E-01 9.2033E-03 1.0343E+01 3.4578E-01 1.600 2.4843E+00 1.0690E-01 2. 6031E-01 1.1201E-02 1.2731E+01 4.2528E-01 1.900 2.9432E+00 1.2560E-01 3.0839E-01 1.3160E-02 1.5108E+01 5.0428E-01 2.000 3.0957E+00 1.3175E-01 3.2437E-01 1.3805E-02 1.5898E+01 5.3051E-01 2.300 3.0957E+00 1.3175E-01 3.4418E-01 1.4598E-02 1.7897E+01 5.9686E-01 2.600 3.0957E+00 1.3175E-01 3.6390E-01 1.5378E-02 1.9814E+01 6.6043E-01 DRE02-0037, Rev. 1, Attachment B, Page B26 of B27

DRE - Gland Seal 2.900 3.0957E+00 1.3175E-01 3. 8352E-01 1.6146E-02 2. 1723E+01 7.2365E-01 3.200 3.0957E+00 1.3175E-01 4.0306E-01 1.6903E-02 2.3623E+01 7.8654E-01 3.500 3.0957E+00 1.3175E-01 4.2252E-01 1.7650E-02 2.5515E+01 8.4911E-01 3.800 3.0957E+00 1.3175E-01 4.4189E-01 1.8388E-02 2. 7399E+01 9.1137E-01 4.100 3.0957E+00 1.3175E-01 4. 6117E-01 1.9117E-02 2. 9275E+01 9.7333E-01 4.400 3.0957E+00 1.3175E-01 4.8038E-01 1.9838E-02 3.1142E+01 1.0350E+00 4.700 3.0957E+00 1.3175E-01 4. 9951E-01 2.0552E-02 3.3002E+01 1.0964E+00 5.000 3.0957E+00 1.3175E-01 5. 1855E-01 2.1259E-02 3.4855E+01 1.1575E+00 5.300 3.0957E+00 1.3175E-01 5.3753E-01 2. 1959E-02 3. 6700E+01 1.2183E+00 5.600 3.0957E+00 1.3175E-01 5.5642E-01 2.2652E-02 3. 8537E+01 1.2789E+00

5. 900 3.0957E+00 1.3175E-01 5.7524E-01 2.3340E-02 4.0368E+01 1.3391E+00 6.200 3.0957E+00 1.3175E-01 5. 9399E-01 2.4022E-02 4.2191E+01 1.3992E+00 6.500 3.0957E+00 1.3175E-01 6.1266E-01 2.4698E-02 4.4007E+01 1.4590E+00 6.800 3.0957E+00 1.3175E-01 6.3126E-01 2.5369E-02 4.5816E+01 1.5185E+00 7.100 3.0957E+00 1.3175E-01 6.4979E-01 2.6035E-02 4.7618E+01 1.5778E+00 7.400 3.0957E+00 1.3175E-01 6.6826E-01 2.6697E-02 4. 9413E+01 1.6369E+00 7.700 3.0957E+00 1.3175E-01 6. 8665E-01 2.7354E-02 5.1202E+01 1.6957E+00 8.000 3.0957E+00 1.3175E-01 7.0497E-01 2.8006E-02 5.2984E+01 1.7543E+00 8.300 3.0957E+00 1.3175E-01 7.1090E-01 2.8233E-02 5.3907E+01 1.7847E+00 8.600 3.0957E+00 1.3175E-01 7.1681E-01 2.8457E-02 5.4657E+01 1.8093E+00 8.900 3.0957E+00 1.3175E-01 7.2270E-01 2.8680E-02 5.5403E+01 1.8338E+00 9.200 3.0957E+00 1.3175E-01 7.2856E-01 2.8901E-02 5. 6147E+01 1.8583E+00 9.500 3.0957E+00 1.3175E-01 7.3441E-01 2. 9120E-02 5. 6889E+01 1.8826E+00 9.800 3.0957E+00 1.3175E-01 7.4023E-01 2.9338E-02 5.7627E+01 1.9069E+00 20.100 3.0957E+00 1.3175E-01 7.4604E-01 2.9554E-02 5.8363E+01 1.9311E+00 10.400 3.0957E+00 1.3175E-01 7.5182E-01 2.9769E-02 5. 9097E+01 1.9552E+00 24.000 3.0957E+00 1.3175E-01 9. 9683E-01 3.8507E-02 9.0171E+01 2.9749E+00 28.000 3.0957E+00 1.3175E-01 9. 9683E-01 3.8507E-02 9.0811E+01 2.9959E+00 32.000 3.0957E+00 1.3175E-01 9.9,683E-01 3.8507E-02 9.0811E+01 2.9959E+00

40. 000 3.0957E+00 1.3175E-01 9.9683E-01 3.8507E-02 9.0811E+01 2.9959E+00

48. 000 3.0957E+00 1.3175E-01 9.9683E-01 3.8507E-02 9.0811E+01 2.9959E+00 Worst Two-Hour Doses EAB Time Whole Body Thyroid TEDE (hr) (rem) (rem) (rem) 0.0 2.9501E-02 3.0957E+00 1.3175E-01 DRE02-0037, Rev. I, Attachment B, Page B27 of B27

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

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

0.1000E+01 Nuclides:

60 Nuclide 001:

Co-58 7

0.6117120000E+07 0.5800E+02 0.1529E+03 none O.OOOOE+00 none 0.OOOOE+00 none O.OOOOE+00 Nuclide 002:

Co-60 7

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

Kr-85 1

0.3382974720E+09 0.8500E+02 4.3644E+02 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 004:

Kr-85m 1

0.1612800000E+05 0.8500E+02 6.7720E+03 Kr-85 0.2100E+00 none O.OOOOE+00 none 0.OOOOE+00 Nuclide 005:

Kr-87 1

0.4578000000E+04 0.8700E+02 1.2910E+04 Rb-87 0.lOOOE+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 006:

Kr-88 1

0.1022400000E+05 0.8800E+02 1.8150E+04 Rb-88 0.1000E+01 DRE02-0037, Rev. 1,Attachment C,Page 1 of 10

Dres QDC Source Terms for CRDA.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 O.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 0.OOO0E+00 Nuclide 012:

Y-90 9

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

Y-91 9

DRE02-0037, Rev. 1, Attachment C, Page 2 of 10

Dres QDC Source Terms for CRDA.nif 0.5055264000E+07 0.9100E+02 3.1549E+04 none O.OOOOE+00 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+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 015:

Y-93 9

0.3636000000E+05 0.9300E+02 3.9417E+04-Zr-93 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 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-01 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 DRE02-0037, Rev. 1,Attachment C, Page 3 of 10

Dres QDC Source Terms for CRDA.nif none O.OOOOE+O0 Nuclide 020:

Tc-99m 7

0.2167200000E+05 0.9900E+02 4.4837E+04 Tc-99 O.1000E+01 none 0.OOOOE+00 none O.OOOOE+00 Nuclide 021:

Ru-103 7

0.3393792000E+07 0.1030E+03 4.3107E+04 Rh-103m 0.1000E+O1 none O.OOOOE+00 none 0.OOOOE+00 Nuclide 022:

Ru-105 7

0.1598400000E+05 0.1050E+03 3.0337E+04 Rh-105 O.lOOOE+01 none O.OOOOE+O0 none O.OOOOE+00 Nuclide 023:

Ru-106 7

0.3181248000E+08 0.1060E+03 1.8366E+04 Rh-106 0.1000E+(0i none 0.00OOOE+00 none 0.00OOOE+00 Nuclide 024:

Rh-105 7

0.1272960000E+06 0.1050E+03 2.8824E+04 none 0.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+O0 Nuclide 026:

Sb-129 4

0.1555200000E+05 DRE02-0037, Rev. 1, Attachment C, Page 4 of 10

Dres QDC Source Terms for CRDA.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

0.9417,600000E+07 0.1270E+03 4.0597E+02 Te-127 0.9800E+00 none O.OOOOE+00 none 0.OOOOE+0O Nuclide 029:

Te-129 4

0.4176000000E+04 0.1290E+03

.8.7350E+03 I-129 0.1000E+01 none O.OOOOE+O0 none 0.OOOOE+0O 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+0O 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 DRE02-003 7, Rev. I, Attachment C, Page 5 of 10

Dres QDC Source Terms for CRDA.nif Nuclide 033:

1-131 2

0.6946560000E+06 0.1310E+03 2.7104E+04 Xe-131m 0.11OOE-01 none 0.0000E+00 none 0.0000E+00 Nuclide 034:

1-132 2

0.82800000000E+04 0.1320E+03 3.9136E+04 none O.OOOOE+00 none O.OOOOE+00 none O.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 O.OOOOE+00 Nuclide 036:

1-134 2

0.3156000000E+04 0.1340E+03 6.0353E+04 none O.OOOOE+t*00 none O.OOOOE+(*00 none O.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 O.OOOOE+00 Nuclide 038:

Xe-133 1

0.4531680000E+06 0.1330E+03 5.2821E+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 039:

Xe-135 1

0.3272400000E+05 0.1350E+03 DRE02-0037, Rev. 1, Attachment C, Page 6 of 10

Dres QDC Source Terms for CRDA.nif 2.1437E+04 Cs-135 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 040:

Cs-134 3

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

Cs-136 3

0.1131840000E+07 0.1360E+03 2.3791E+03 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 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 0.1000E+01 none O.OOOOE+00 none 0.OOOOE+00 Nuclide 045:

La-140 9

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

DRE02-0037, Rev. 1, Attachment C, Page 7 of 10

Dres QDC Source Terms for CRDA.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.OOOOE+OO none 0.OOOOE+O0 none O.OOOOE+00 Nuclide 048:

Ce-141 8

0.280808640OE+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 0.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 0.OOOOE+00 none 0.OOOOE+00 none O.OOOOE+00 Nuclide 052:

Nd-147 9

0.9486720000E+06 0.1470E+03 1.7999E+04 DRE02-0037, Rev. 1, Attachment C, Page 8 of 10

Dres QDC Source Terms for CRDA.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 O.OOOOE+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+11 0.2410E+03 9.8566E+00 Np-237 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 059:

Cm-242 DRE02-0037, Rev. 1, Attachment C, Page 9 of 10

Dres QDC Source Terms for CRDA.nif 9

0.1406592000E+08 0.2420E+03 2.2847E+03 Pu-238 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 060:

Cm-244 9

0.5715081360E+09 0.2440E+03 1.6212E+02 Pu-240 0.1000E+01 none 0.OOOQE+00 none O.OOOOE+00 End of Nuclear Inventory File DRE02-0037, Rev. 1, Attachment C, Page 10 of 10

DRE - Gland Seal.rfl Release Fraction and Timing Name:

Dresden and Quad Cities -Gland Seal Condenser Duration (h): Control Rod Drop Accident 0.0010D+00 0.00lOD+00 O.OOOOD+0Q O.OOOOD+00 Noble Gases:

3.1680E-03 2.1954E-04 O.OOOOD+00 O.OOOOD+00 Iodine:

3.1680E-04 1.0977E-05 O.OOOOE+00 O.OOOOE+00 Cesium:

3.8016E-05 4.8788E-07 O.OOOOE+00 O.OOOOE+00 Tellurium:

O.OOOOE+00 1.2197E-07. Q.OOOOE+00 O.OOOOE+00 Strontium:

O.OOOOE+00 4.8788E-08 O.OOOOE+00 O.OOOOE+00 Barium:

O.OOOOE+00 4.8788E-08 O.OOOOE+00 O.OOOOE+00 Ruthenium:

O.OOOOE+00 6.0984E-09 O.OOOOE+00 O.OOOOE+00 Cerium:

O.OOOOE+00 1.2197E-09 O.OOOOE+00 O.OOOOE+00 Lanthanum:

O.OOOOE+00 4.8788E-10 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 DRE02-0037, Rev. 1, Attachment D, Page Dl of D2

DRE - Condenser Path.rft Release Fraction and Timing Name:

Dresden and Q2uad Cities -Main Condenser Duration (h): :Control Rod Drop Accident o.OOlOD+00 0.OOlOD+00 O.OOOOD+OO 0.00 OOD+00 Noble Gases:

3.1680E-03 2.1954E-04 O.OOOOD+0O 0.00 OOD+00 Iodine:

3.1680E-04 1.0977E-06 0.0OOOE+OO 0.00 OOE+00 Cesium:

3.8016E-05 4.8788E-09 O.OOOOE+00 0.00 00)E+OO Tellurium:

O.OOOOE+OO 1.2197E-09 O.000OE+0O 0.00 OOE+00 Strontium:

O.OOOOE+0O 4.8788E-10 O.O000E+OO 0.00 0OOE+00 Barium:

O.OOOOE+00 4.8788E-10 O.OOOOE+00 0.00 OOE+00 Ruthenium:

O.OOOOE+00 6.0984E-ll O.OOOOE+00 0.00 OOE+00 Cerium:

O.OOOOE+00 1.2197E-11 O.OOOOE+OO 0.00 OOE+00 Lanthanum:

O.OOOOE+O0 4.8788E-12 O.OOOOE+0O 0.00 0OOE+00 Non-Radioactive Aerosols (kg):

O.OOOOE+00 O.OOOOE+OO 0.OOOOE+OO O.00OE+OO End of Release File DRE02-0037, Rev. I, Attachment D, Page D2 of D2

A B l C D E F G l H l I l J l K l L 1 Core Release Initial Core Decay Release to Release to 2 Half-Live Nominal Source Fractions Activity Half-Live Constant Delay Bed Environment 3 Nuclide Isotope Class (seconds) At. Wt. CIlMW 0-0.5hr (Ci) (hours) (hours)" (Ci) (Ci) 4 003: Kr-85 1 3.38E+08 85 4.3644E+02 0.05 1.32E+06 9.40E+04 7.38E-06 4.46E+03 4.46E+03 5 004: Kr-85m 1 1.61 E+04 85 6.7720E+03 0.05 2.04E+07 4.48E+00 1.55E-01 6.92E+04 3.44E+03 6 005: Kr-87 1 4.58E+03 87 1.2910E+04 0.05 3.89E+07 1.27E+00 5.45E-01 1.32E+05 3.37E+00 7 006: Kr-88 1 1.02E+04 88 1.8150E+04 0.05 5.47E+07 2.84E+00 2.44E-01 1.85E+05 1.63E+03 8 038: Xe-133 1 4.53E+05 133 5.2821 E+04 0.05 1.59E+08 1.26E+02 5.51 E-03 5.40E+05 7.84E+04 9 039: Xe-135 1 3.27E+04 135 2.1437E+04 0.05 6.47E+07 9.09E+00 7.63E-02 2.19E+05 5.45E-07 10 = .___ _ 3 ____

3 12 0.003388 =CRDA Noble Gas Release Fraction _ .

13 19.4 =Krypton Holdup in Delay Bed (hrs) 4 ___

14 350.4 =Xenon Holdup in Delay Bed (hrs) 4 15 2.51E-04 =Worst Case EAB X/Q (sec/m3)5 .

16 2.63E-05 =Worst Case LPZ X/Q (sec/m3)5 17 1.30E-03 =Worst Case CR X/Q (sec/m3)6 18 3.59E-02 =Control Room Geometry Factor (MurphyCampBased) __

19 . . . . . .

20 .

21 Release to 22 Environment DCF1 EAB Dose LPZ Dose CR Dose 23 Isotope (Cl) (rem TEDE) (rem TEDE) (rem TEDE) 24 Kr-85 4.46E+03 4.403E-04 4.93E-04 5.16E-05 9.16E2-05 25 Kr-85m 3.44E+03 2.768E-02 2.39E-02 2.50E-03 4.44E-03 26 Kr-87 3.37E+00 1.524E-01 1.29E-04 1.35E-05 2.40E-05 27 Kr-88 1.63E+03 3.774E-01 1.54E-01 1.62E-02 2.87E-02 28 Xe-133 7.84E+04 5.770E-03 1.14E-01 1.19E-02 2.11 E-02 29 Xe-135 5.45E-07 4.400E-02 6.02E-12 6.31 E-13 1.12E-12 30 31 Total Dose (rem TEDE): 2.92E-01 3.06E-02 5.44E-02 _

32 _ __ _

33 _

35 Dose Conversion Factor (rem-r ICurie-second) from FGR 12 per Reg. Guidel 1.183 36 2K.G. Murphy and K.W. Campe, 13th AEC Air Cleaning Conference, "Nuclear Power Plant Control Room 37 Ventilation System Design for Meeting General Criterion 19", August 1974 38 3 Summation from Attachment A _ . _ _

39 4Section 11.3 of Dresden UFSAR _ _ _ _ .

40 5 Reference 8 l . l _ _

41 ~ Reference 8 l DRE-SJAE DRE02-0037, Rev. 1,Attachment E, Page I of 2

I A B C D E F G H I l K L 1 Core Release Initial Core Dacay Release to Release to 2 Haff-Uve Nominal Source Fractions Acthity Half-Live Constant .DelyBed Environment 3 Nucllde tsotop Class (seconds At. WL Cl/MW 0.0.5hr (CQ hu *' Chours CCQ 4 003- Kr-45 1 338297472 85 43.442857142857 0.05 F413016 =D4/3600 4LN(2yt4 =H4-SASf2 IK4-EXP-441SA513) 5 004: Kr4 5m 1 16128 85 6772 0.05

°F53016 =DS/3600 LN(2y5 =HS-SAS12 KS-EXPI-J5- AS13) 8 005: Kr-ST 1 4578 87 12910 0.05 OF6-3016 D6/3600 LN(2y18 =H6-SAS12 =K6-EXP-J6-SAS13) 7 006: Kr-88 1 10224 88 18150 0.05 =Fr3016 =D7/3600 =LN(2A7 =H7-SAS12 K7-EXP(-Jr$AS13) 8 038: Xe-133 I 453168 133 52821.4285714286

F8-3016 0.05 =08t3600 LN(208 =H8-3SASt2 K8-EXP(48-SAS14) 9 039: Xe-135 1 32724 135 21437.1428571429 0.05 =F9-3016 =D9/3600 *LN(2yi9 =H9-SAS12 -K9-EXP(-J9-AS14) 10 12 0.0033875701569762 =CRDA Noble Gas Releate Fr _ _ _

13 19.4 -. r-pton HoldupInDelay Bed_____

14 *14.6 24 Xenon Holdupin (eay Bed (

15 0.000251 -Worst Case EAB XIO (secrmn 16 0.0000263 =Worst Case LPZ X/O (secdm3 17 0.0013 *Worst Case CR Xt0 (secmn3' _

18 =(64000^0.338Y1173 -Control Room GeomehY Fect 19 20 21 Release to 22 Errmrownrnt DCF' EAB Dose LPZ Dose CR Dose_

23 osotope (cOn (rc 7ErE) (r m TEDE_ (r_ TEDE)__

24 Kr-85 r1.4 0.0004403 *SB24 *SAS15-SC24 =SB24-S AS16-SC24 S$B24-SASI 17-C24-SASI18=

25 Kr385m -S an CCB25-CAS0.027676 SB25-SA 1WSC25 16CtC25 =RB2anSyS 17C25-SAS e C8 23 Kr-87

_1-6 0.15244 *SB261SAS7 iS-SC26 -826-SAS16 6C26 SB26-SAS17-SC28SAS18_

27 Kr-88 -LT 03774 *SB27-SAS 15-SC27 =B27-SASiSC27 =SB27-SASt7-SC27-5ASI8 28 Xe-1 33 -18 0.00577 *SB28-SAS15SC28 =S$B28-5AS1 6-SC28 =SB28-SAS1 ?-SC28-$AS1 8 29 Xe.135 0L0044 *SB29-SAS !5SSC29 $B29-SAS16-SC29 =SB29-SAS 17-SC29-SAS 18 31 1Total Dose (rem TEDE): *SUMl(D24:D29) -SUMt(E24:E29) *SUMIF24:F29)_

32 34_

35 DoseCovrsion Factor r XL 38 K G. MurphY antt K tlW.Campo, 13th AEC Alr Clow"h Conferencee*Nuclear Pofwer Plant Control Room Vsnbilation SyistemnDetin lforMeetinti General Criterion 19.

37 August 1974 38 6tnrration frorn Attachrnent Al I

1 39 Section 11.3 of Dresden UFSA

]0 IReferenca 8i I 4ll 'I Reference 8 II _ I _ _

DRE.S iAE formulas DRE-JAEformlasDRE02-0037.

Rrv. 1.Attachment E, Page2 of 2

I CALCULATION NO. DRE02-0037, Attachment F I REV. NO. I I PAGE NO. F-1 I Computer Disclosure Sheet Discipline Nuclear Client: Exelon Corporation Date: August, 2005 Project: Dresden Units 2&3 CRDA AST Job No.

Program(s) used Rev No. Rev Date Calculation Set No.: DRE02-0037, Rev. 1 Attachment A spreadsheet N/A N/A Attachment E spreadsheet NIA N/A Status [ ] Prelim.

[X] Final

[ I Void WGI Prequalification [ ] Yes

[X] No Run No.

Description:

Analysis

Description:

Spreadsheet used to perform dose assessments for CRDA, as described in calculation.

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

By: On: August 2005 Run by: H. Rothstein Checked by: P. Reichert C Approved by: H. Rothstein Remarks:

This spreadsheet is applied in a straight-forward manner and was hand checked. The Attachments include the spreadsheets in both normal and formula display mode and therefore is completely documented.

I CALCULATION NO. DRE02-0037, Attachment F REV. NO. I l PAGE NO. F-2 l Computer Disclosure Sheet Discipline Nuclear Client: Exelon Corporation Date: August 2005 Project: Dresden Units 2&3 CRDA AST Job No.

Program(s) used: Rev No. Rev Date Calculation Set No.: DRE02-0037, Rev. 0 RAD'TRAD 3.03 Runs in Att. B 0 January 2003 (Prequalification Date)

RADTRAD 3.03 NIF File in Att. C 0 January 2003 Status [ ] Prelim.

RADTRAD 3.03 RFT File In Att. D 0 January 2003 -X] Final WGI Prequalification [X] Yes

[ No Run No.

Description:

Analysis

Description:

RADTRAD output files, where applied to calculations of CRDA 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: August 2005 Run by: H. Rothstein Checked by: P. Reichert Approved by: H. Rothstein ?(f / ,

Remarks:

The RADTRAD computer code is applied in a manner fitting its intended purpose, and well within its operating parameters. All outputs were hand checked. Attachments C & D include the Nuclide Information File and Release Fraction and Timing File used by the RADTRAD code and generated specifically for the Dresden Nuclear Power Station. Both were also hand checked for accuracy.

ML052430276

Text

Title:

SUMMARY

SUMMARY

Description:

Description:

Description:

Description:

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