ML032671360

Calculation QDC-0000-N-1117, Site Boundary and Control Doses Following a Loss of Coolant Accident Using Alternative Source Terms, Revision 0

ML032671360
Person / Time
Site:	Dresden, Quad Cities
Issue date:	08/22/2002
From:	Baron J, Ferguson K Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
QDC-0000-N-1117, Rev. 0
Download: ML032671360 (83)

Text

ATTACHMENT 7 Calculation QDC-0000-N-I 117, "Site Boundary and Control Room Doses Following a Loss of Coolant Accident Using Alternative Source Terms,"

Revision 0, dated August 22, 2002

CC-AA-309 - ATTACHMENT I - Design Analysis Approval Page 1 of 2 DESIGN ANALYSIS NO.: QDC-0000-N-1117 PAGE NO. I Major REV Number: 000 Minor Rev Number: 000

[3BRAIDWOOD BYO STATDION STATION DESCRIPTIONNlRR0 CQODE:C01E) N01, R01, R02

[ CLITON STATION

[DRECSNTN STATION CD:C1)________

[ 3 STATIONDISCIPLINE DRESDEN CODE:

[ LASALLE CO. STATION L (Coll) N

[X QUAD CITIES STATION Unit:[ lO [XII [X]2 [ l3 SYSTEM CODE: (C011) NWA TITLE: Site Boundary and Control Room Doses following a Loss of Coolant Accident using Alternative Source Terms X l Safety Related [ 3Augmented Quality [ 1 Non-Safety Related

-___________ ATTRIBUTES (C016)

TYPE VALUE TYPE VALUE Elevation Software COMPONENT EPN: DOCUMENT NUMBERS: (C012 Panel) (Design EPN TYPE Analyses References)

Type/Sub Document Number Input (Y/N)

Report/Eng GE-NE-A22-00103-64-01, RO Y Letter/Eng Exelon TODI QDC-02-01 9, Ri Y

_ __ ___ CalclEng S&W 08645.7022-UR(B)-001, RO Y Calc/Eng ODC-1 100-N-1259, RO Y REMARKS:

Page 1 of 58 (Printed: 08/22/02 8:43 AM)

E-Form CC-AA-309-1 v1 .1 for use with CC-AA-309 Revision I and -above.

CC-AA-309 - ATTACHMENT 1 - Design Analysis Approval Paqe20f2 DESIGN ANALYSIS NO. QDC-0000-N-1117 REV: 000 PAGE NO. 2 Revision Summary (including EC's incorporated):

Ofiginal Issue Electronic Calculation Data Files:

(Program Name, Version, File Name extensior~size/datelhour/min)

Design Impact review completed? 1 Yes [Xl NWA, Per EC#: 376 (If yes, attach Impact review sheet)

Prepared by: K. P. Ferguson 8/02 /_

Print Date Reviewed by- J. S. Baron ------ -_8/22_02

. Print 7 Sin Date Method of Review: [x I Detailed ] Alternate [ ] Test This Design Analysis supersedes: In Its entirety Supplemental Review Required? [ 1Yes . X.J No

[ Additional Review [ I Speia b Re rTm - *F~J Additional Reviewer or Special RevIewTleamteader -_-_-;_______

' ~~~~~~~~~-- .f:'.  :.# P .t.;;r;

.;.j,' .

j.inst ti,-t . g>S ;.;.gn Date Special Review Team /Al Review)

- PZ - . -rin- Si -- Date .Print-.-; - srSt9g - *i:ibt Dat9-e ;

_~~~~~~~~~~~"_A Supplementa Review Resuls Add-'.nal;-

Approved by: S;reela R. FergusonI\ 18/20

- ~~~~Print Siln Date External Desian Analysis Review (Attachment 3 Attached)

Reviewed by: I I Print Sign Date Approved by: I Prit

__ Sin Date Do any ASSUMPTIONS IENGINYEE~ttNG JUDGEMENTS require later verification? I ] Yes [ X] No Tracked By. AT#, EC# etc.) - -

Page 2 of 58 (Printed: Wi22/2 8:43 AM)

E-Forrn CC-AA-309-1 v1.1 for use with CC-AA-3D9 Revision 1 and above.

NES-G-1 4.01 Effective Date:

04114100 CALCULATION TABLE OF CONTENTS CALCULATION NO. QDC0000-N-1117 REV. NO.000 PAGE NO. 3 SECTION:

___I.

1 PAGE NO.

SUB-PAGE NO.

TITLE PAGE 1 REVISION

SUMMARY

2 TABLE OF CONTENTS 3 1.0 PURPOSE I OBJECTIVE 4

2.0 INTRODUCTION

AND ACCEPTANCE CRITERIA 4 3.0 METHODOLOGY 5 4.0 ASSUMPTIONS / ENGINEERING JUDGEMENTS 21 5.0 DESIGN INPUTS 21

6.0 REFERENCES

27 7.0 CALCULATION 29 8.0

SUMMARY

AND CONCLUSIONS 42 APPENDIX A 46 ATTACHMENTS A. EXELON TODI QDC-02-019, Rev 1 24 pages B. CDROM OF COMPUTER OUTPUT 1 page m U E-FORM _

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04114/00 DESIGN ANALYSIS NO. QDC-O000-N-1117 REV: O PAGE NO.4 1.0 PURPOSE / OBJECTIVE The purpose of this analysis is to determine the dose at the Exclusion Area Boundary (EAB), Low Population Zone (LPZ) and Control Room (CR) following a Loss of Coolant Accident (LOCA) at the Quad Cities (OPS) Station. The calculated dose is based on "Alternative Source Terms", cloud submersion and Inhalation pathways. Part 1 of the calculation is based on current design basis parameters as provided by Exelon via Ref.4. Part 2 of the calculation determines doses based on proposed changes to selected design basis parameters.

Exelon has identified three release pathways: (1) primary containment leakage into the Reactor Building and exhausted via the SBGT system; (2) primary containment leakage directly to the environment through the MS Isolation Valves; and (3) ESF leakage from equipment and systems that leak into the Reactor Building and exhaust via the SBGT system.

Additionally, per Exelon request, Appendix A of this analysis documents a sensitivity study of Main Steam line leakage versus the 30 day control room operator TEDE dose following a LOCA. The results of this study is utilized by Exelon to facilitate the selection of the proposed design changes relative to MSIV leakage.

2.0 INTRODUCTION

AND ACCEPTANCE CRITERIA Introduction Quad Cities Power Station (OPS) is investigating the possibility of increasing allowable MSIV leakage. In addition, operational relief is being investigated in the areas of increasing allowable containment leakage, ESF leakage and control room inleakage, and reducing the required charcoal filter iodine removal efficiency for both the Standby Gas Treatment System (SGTS) and the Control Room Emergency Ventilation system.

As a holder of an operating license Issued prior to January 10, 1997, and in accordance with 10CFR50.67 (Reference 1), to support the above change in operation mode, OPS is considering the voluntary replacement of the TID 14844 (Reference 2) accident source term currently used to analyze the dose consequences r at the site boundary and in the control room due to airborne releases following a Loss of Coolant Accident (LOCA), with the Alternative Source Term (AST).

The source terms / methodology used in the assessment summarized in this analysis reflect the guidance provided in Regulatory Guide 1.183 (Reference 3). The plant I E-FORM

NES-G-114.02 Effective Date:

04/14100 DESIGN ANALYSIS NO. ODC00-N-1117 REV: 0 PAGE NO.5 specific input parameters utilized to perform this analysis were provided to S&W by Exelon via a QA parameter list. (Reference 4)

This evaluation has been divided into two parts. Part 1 entails the assessment of the base case which is intended to reflect current design basis (identified by Exelon via Reference 4 as Case 1). Upon review of the dose consequences of the base case, Exelon identified several sensitivity studies from which one scenario was selected as the proposed new design basis, and is Included in this calculation as the Part 2 analysis (identified by Exelon via Reference 4 as Case 2).

Acceptance Criteria The acceptance criteria for the EAB and LPZ Dose is based on 10 CFR Part 50 § 50.67, and Section 4.4 Table 6 of Regulatory Guide 1.183:

(I) An individual located at any point on the boundary of the exclusion area for any 2-hour period following the onset of the postulated fission product release, should not receive a radiation dose in excess of the total effective dose equivalent (TEDE) value of 25 REM noted in Reference 3, Table 6.

(ii) An individual located at any point on the outer boundary of the low population zone, who is exposed to the radioactive cloud resulting from the postulated fission product release (during the entire period of its passage), should not receive a radiation dose in excess of the TEDE value of 25 REM noted in Reference 3, Table 6.

The acceptance criteria for the Control Room Dose is based onlO CFR Part 50 § 50.67:

Adequate radiation protection Is provided to permit occupancy of the control room under accident conditions without personnel receiving - radiation exposures in excess of 0.05 Sv (5 rem) total effective dose equivalent (TEDE) for the duration of the accident.

3.0 METHODOLOGY Radiation Source terms The inventory of fission products in the OPS reactor core is based on maximum full-power operation of the core at a power level equal to the Extended Power Uprate (EPU) thermal power level of 2957 MWth plus a 2% instrument error per Regulatory Guide IF T E-FORM

NES-G-1 4.02 Effective Date:

04/141O0 DESIGN ANALYSIS NO. QDC-0000-N-1117 REV: 0 PAGE NO.6 1.49 (Reference 5); i.e. 3016 MWth, and a 24 month fuel cycle. The inventory used for the LOCA analysis represents a average core bumup of 1600 EFPD.

The OPS equilibrium core inventory per Megawatt was calculated by GE using computer code ORIGEN2 and is documented in GE task Report No. GE-NE-A22-00103-64-01. (Reference 6)

The standard library / input to Computer code RADTRAD is limited to a pre-selected group of 60 isotopes which were determined by the code developer as significant in dose consequence. The equilibrium core inventory of these isotopes is presented in the Inputs Section as Datum#6.

Table 1 in Regulatory Guide 1.183, specifies the fraction of Fission Product Inventory released into containment following a DBA LOCA in a BWR. Both the Gap and Early In-Vessel release fractions to be applied to the equilibrium core inventory are provided.

The release fractions listed are determined to be acceptable for use with currently approved LWR fuel with a peak burnup of 62,000 MWD/MT. OPS fuel meets the criteria identified in RG 1.183. The release fractions recommended by RG 1.183 are reported below:

Gap Early In-Vessel Groun Release Phase Release Phase Noble gas 0.05 0.95 Halogens 0.05 0.25 Alkali Metals 0.05 0.20 Tellurium Group 0.05 Ba, Sr 0.02 Noble Metals 0.0025 Cerium Group 0.0005 Lanthanides 0.0002 Table 5 of Regulatory Guide 1.183 lists the elements in each radionuclide group that should be considered in DBA LOCA analysis. This list is provided below:

Groun Isotopes Noble gases: Xe, Kr Halogens: 1,Br Alkali Metals: Cs Rb Tellurium Grp: Te, Sb, Se Ba, Sr Ba, Sr Noble Metals: Ru, Rh, Pd, Mo, Tc, Co Cerium Grp: Ce, Pu, Np Lanthanides: La, Zr, Nd, Eu, Nb, Pm, Pr, Sm, Y, Cm, Am I E-FORM I

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04114/00 DESIGN ANALYSIS NO. QDC-0000-N-1117 REV: 0 PAGE NO.7 Table 4 of the Regulatory Guide 1.183 provides the onset and duration of each sequential phase for the DBA LOCA at a BWR. Per RG 1.183, the early in-vessel phase immediately follows the gap release phase. The associated information is repeated below.

Phase Onset Duration Gap Release 2 mins 0.5 hrs Early-In-Vessel 0.5 hrs 1.5 hrs Dose CalculationMethodology The 2 hr EAB, and 30-day LPZ and Control Room Total Effective Dose Equivalent (TEDE) is calculated using industry computer code RADTRAD (Reference 7). The TEDE is the sum of the Committed Effective Dose Equivalent (CEDE) and the Deep Dose Equivalent (DDE).

RADTRAD calculates the submersion dose (DDE) and the inhalation dose (CEDE) at offsite locations and the control room. All doses are estimated using Federal Guidance Reports 11 and 12 (References 8 and 9) dose conversion factors (DCFs) for the following organs and pseudo-organs:

• Gonads

• Breast

• Lungs

• Red bone marrow

• Bone surface

• Thyroid

• Skin

• Effective dose equivalent - Remainder The RADTRAD activity transport model first calculates the activity at the offsite locations and in the control room air region. The decay and daughter build-up during the activity transport among compartments and the various cleanup mechanisms are included in the activity calculation.

No modifications are performed external to the code. The doses are based on the integrated total activty, occupancy factors (for control room only), and ICRP-30 dose conversion factor methodology. All doses herein are based on the RADTRAD option for Federal Guidance Reports No. 11 and 12 inhalation and external exposure dose conversion factors, respectively. Note that per RG-1.183, RADTRAD assumes that the Effective Dose Equivalent (EDE) is equivalent to the DDE.

l E-FORM l

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O4M4O DESIGN ANALYSIS NO. QDC-OODO-N-1117 REV: 0 PAGE NO.8 Offsite Dose The dose to a hypothetical individual Is calculated using plant specific X/Qs and the amount of each nuclide released to the environment during each exposure period. The air immersion dose from each nuclide, n, at a offsite location is calculated as:

Do tAbn(=A DCFcn where:

D1cdrone*

cAn air submersion dose due to nuclide n at a location (Sv)

Svmn3 DCFc¢n- IFGR 12 air submersion dose conversion factor for nuclide n ( B s)

) - atmospheric dispersion coefficient from release point to location ( -;;F)

An released activity of nuclide n (Bq)

The inhalation dose from each nuclide, n, is calculated as:

n = A,, *(X/A)I

• BR

• DCFjl where inhalation dose commitment due to nuclide n at a location (Sv)

BR Breathing rate (m¶y;)

DCFj,,, FGR 11 inhalation dose conversion factor for nuclide n ( )

The dose to an individual in the control room is calculated based on the time-integrated concentration in the control room. The air submersion dose is:

(,)dGF) where E-FORM I

NES-G-1 4.02 Effective Date:

04/14/00 DESIGN ANALYSIS NO. QDC-0000-N-1117 REV: 0 PAGE NO.9 Cn(t) is the instantaneous concentration of radionuclide n in the control room. (q)

GF the Murphy-Campe geometric factor relating dose from an infinite cloud to the dose from a cloud of volume V (ft3) as 1173 GF = VO,38 The inhalation dose in the control room is DicR =JC#(t) BR

• OF* DCFndt where OF occupancy factor The following derived doses are also calculated:

• Whole body (effective air submersion dose)

• Thyroid (thyroid chronic inhalation dose)

• TEDE (effective air submersion dose + effective committed effective dose equivalent)

Activity Transport Model RG 1.183 identifies the large break LOCA as the design basis case for the spectrum of break sizes for evaluating performance of release mitigation systems I containment and facility siting relative to radiological consequences.

Computer program RADTRAD is used to calculate the airborne dose to the operator in the control room and to a member of the Public located at the EAB/LPZ following a LOCA. RADTRAD utilizes an analytical computational process, that addresses radionuclide progeny, time dependent releases, transport rates between regions and deposition of radionuclide concentrations in sumps, walls and filters. The Quad Cities LOCA activity transport and dose model for RADTRAD is shown on Figure .1 RADTAD has not been validated or verified in accordance with S&Ws 10 CFR 50 Appendix B QA program, therefore the transport model for each release path (i.e., MSIV release pathway, containment release pathway, and ESF Release pathway) developed for RADTRAD is checked against S&W's QA Cat I transport and dose consequence program PERC2. Comparing both programs calculated total 1-131 (principal dose contributor) environmental activity release and calculated control room operator thyroid I E'FORM A

NES-G-14.02 Effective Date:

04/14100 DESIGN ANALYSIS NO. QDC-0000-N-1117 REV: 0 PAGE NO.10 dose from each pathway provides sufficient verification of RADTRAD results. The LOCA activity transport model for PERC2 is shown on Figure 2.

The worst 2-hour period dose at the EAB, the dose at the LPZ for the duration of the release, and the 30 day control room dose is calculated based on the postulated airborne radioactivity releases following a LOCA. The calculated dose represents the post accident dose to the public and to the control room operator due to inhalation and submersion.

The LOCA analysis is based on the guidance set forth in Regulatory Guide 1.183, and OPS design parameters as provided via Reference 4. Note that selected portions of the analysis utilizes a fifth unit concept, i.e.; the most conservative value applicable to Dresden and Quad Cities Station is used.

As Indicated previously, this assessment has been divided into two parts. Part I entails the assessment of the base case, which is intended to reflect current design basis (identified by Exelon via Reference 4 as Case 1). Upon review of the dose consequences of the base case, Exelon requested several sensitivity studies be performed including a focussed sensitivity study of MSL leakage vs 30 day control room TEDE dose based on the limiting station and a proposed control room unfiltered inleakage of 600 scfm (see Appendix A). Based on a review of the results of the referenced studies, and the MSL leakage vs control room dose study documented In Appendix A, Exelon has selected the proposed new design basis, which is included in this calculation as the Part 2 analysis (identified by Exelon via Reference 4 as Case 2).

Base Case (PART 1)

As noted in Reference 4, OPS has Identified three (3) leakage pathways following a LOCA:

• Containment airborne activity that leaks directly to the environment, untreated, via the Main Steam Isolation Valves (MSIVs)

• Containment airborne activity which leaks into the reactor building (RB), mixes with the RB atmosphere, and is released to the environment, after filtration via the standby gas treatment system (SBGTS); and

• ESF leakage, or suppression pool water leaking from lines and equipment circulating suppression pool water in the Reactor Building, made airborne, and discharged via the RB SBGTS Per Reference 4, current plant design does not allow bypass of the SBGTS.

I E-FORM I

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04/14100 DESIGN ANALYSIS NO. QDC-0000-N-1117 REV: 0 PAGE NO.11 Containment Airborne Activitv In accordance with Reference 3, the fission products released from the fuel are assumed to mix instantaneously and homogeneously throughout the free air volume of the drywell air space as it is released from the core. No suppression pool scrubbing is assumed since the bulk of the activity is released well after the initial mass and energy release. Per RG 1.183, two fuel release phases are considered for the DBA LOCA analyses: a) the gap release, which begins 120 secs after the LOCA and continues for 30 minutes and b) the early In-Vessel release phase which begins 30 minutes after the onset of the gap release and continues for 1.5 hrs. The core inventory release fractions, by radionuclide group, for the gap and early in-vessel phase are based on guidance provided in Regulatory Guide 1.183, and are listed in Section 3.

In accordance with Reference 3, the chemical form of the radioldine released from the fuel is 95% cesium iodide (Csl), 4.85% elemental iodine, and 0.15% organic iodine.

With the exception of noble gases, elemental and organic iodine, fission products are assumed to be in particulate form.

Activity made airborne in the primary containment Is depleted by natural deposition within the containment. Elemental iodine is reduced by a plateout removal coefficient (3.28 hrW) using the methodology outlined in SRP 6.5.2, Rev.2 (Reference 10).

Parameters utilized to develop this coefficient include the surface area of the drywell (DRE value of 32,250 sq ft is used, actual OPS value is 32,450 sq ft, DRE value is used as it is more limiting) and Containment free volume (1.58E5 cu.ft). The maximum DF for elemental iodine is based on SRP 6.5.2 and is limited to a DF of 200. For OPS, this DF value is reached at 3.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Credit for elemental iodine removal in the drywell is therefore stopped at T= 3.1hrs after the LOCA In accordance with Reference 3, particulate aerosols are removed by deposition/plateout using the equations for the Powers Moder In NUREGICR-6189 (Reference 15) with the 10% uncertainty percentile which results in the lowest activity removal efficiency provided by the model. Because the 'Powers Model" applies a separate set of lambdas for the gap and early-in-vessel release, two RADTRAD runs are required, one for the gap phase and one for the early-in-vessel core release phase.

The output dose results from the gap and early-in-vessel core release phases are added to obtain the total dose.

Per Reference 16, long term suppression pool pH (taking Into consideration acid production due to radiolysis and cable degradation) Is estimated to be greater than 7.

Per Reference 4, credit is taken for the sodium pentaborate In the Standby Liquid Control System, which is assumed to be manually initiated via the EOPs such that the entire Inventory of sodium pentaborate is delivered and mixed in the suppression pool within 24 hrs of the LOCA. Consequently, per Reference 3, iodine re-evolution is not addressed.

E-FORM

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04114100 DESIGN ANALYSIS NO. QDC-0000-N-1117 REV: 0 PAGE NO.12 Containment Leakage via MSIVs A portion of the containment leakage (per Reference 4, the total leakage is 0.01 volume fractions per day) is released via the MSIVs. Per Reference 4, during accident conditions, the 4 MSS lines leak at a combined rate of 79.6 scfh @ 48 psig (0.00283 containment volume fractions per day) or at 46 scfh at a test pressure of 25 psig. This leakage is assumed to be valid for the duration of the event.

Consistent with the guidance of RG 1.183, activity leakage via this pathway is assumed to experience deposition, plateout and holdup as It traverses the steam lines before being released to the environment, i.e.; the activity traversing the approximately 93 ft (min pipe length value) of MS piping is depleted and decayed before it released with ground level dispersion. The deposition model used in the analysis utilizes aerosol and elemental iodine removal lamdas developed using S&W proprietary methodology based on information provided in References 11 and 15. These lambdas are documented in Reference 13 which uses the fifth Unit concept, i.e., the most conservative value for each input value applicable to the main steam lines at Dresden and Quad Cities Station is utilized.

The RADTRAD activity transport model is shown in Figure 1. Consistent with current Technical Specifications all Main Steam activity leakage is conservatively assumed to leak from one MSL. The outboard MS valve is assumed to fail open minimizing non-gaseous activity deposition. As shown in Figure 1 the MSL is broken into 5 regions, 4 horizontal sections and 1 vertical section. Multiple regions were used to more closely represent the plug flow. Deposition is achieved using time dependent removal coefficients. The 5 region MS line leakage model and associated time dependent aerosoVelemental iodine deposition rates utilized in this analysis are taken directly from Reference 13 and are based on S&W proprietary methodology. Natural deposition of organic iodine In MSLs Is not credited herein. The PERC2 model used to validate and verify RADTRAD results uses an overall DF developed externally in Reference 13 to the program to account for deposition in the MSL(s). Although the PERC2 activity transport model has a single MSL region, the overall DF used in the PERC2 analyses was developed using the 5 region MSL activity transport model from Reference 13.

Time for initiation of MSL releases to the environment was determined using a criteria of 40 minutes (i.e.; time at which the CR is in full emergency ventilation operation ) or 1/8 the time determined using a plug flow model for retention to address convective flow -

whichever time was smaller. For all cases considered, 40 minutes was the limiting time for initiation of MSIV releases. The average transit time (base case) for the worst line in plug flow is V/F = 160 ft3/ 0.311 cfm / 60 min/hr or 8.6 hrs. Since 40 min < (8.6 hrs / 8),

the model assumed that the leading edge would begin environmental release at 40 min after the LOCA.

I E-FORM i

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04114/00 DESIGN ANALYSIS NO. QDC-0000-N-1117 REV: 0 PAGE NO.13 Containment leakage via the SBGTS The portion of the containment leakage not released via the MSIVs (i.e., 0.00717 volume fraction per day) is assumed to leak into the reactor building. Per Reference 3, this activity is assumed to mix In 50% of the available RB free volume (4.7E6 cu ft) and be discharged to the environment via the SBGTS. The SBGTS exhaust flow is 4000 cfm

+/- 10% and its filters remove all forms of iodine and aerosols with an efficiency of 95%.

This leakage is assumed to occur for the duration of the event.

Per Reference 4, and consistent with current design basis, the analysis does not address a delay in availability of the SBGTS due to a delay in RB drawdown to achieve

-0.25 in. w.g. within the building. Reference 4 notes that the design of the reactor building and the SBGT System is to maintain the reactor building at slight negative pressure under normal and accident conditions. During previous secondary containment leak rate surveillance, it has been observed that the reactor building pressure is maintained substantially negative (>0.2 in wc vacuum). This precludes exfiltration from the building when the SGTS system is operating.

In addition, per RG 1.183, the earliest radioactivity release occurs at 2 mins after the LOCA. Therefore, per Reference 4, the delays associated with startup of the SBGTS following a Loss of Offsite Power (LOOP) co-incident with the accident will not result in radiological releases that bypass the SBGTS. The impact of a LOOP at a more unfavorable time usignificantly later' on in the accident, (such as during the fuel release phase of a LOCA), is not addressed per NRC Information Notice 93-17 (Reference 17).

The need to evaluate a design basis event assuming a simultaneous or subsequent LOOP is based on the causeleffect relationship between the two events (an example illustrated in IN 93-17 is that a LOCA results in a turbine trip and a loss of power generation to the grid, thus causing grid instability and a LOOP a few seconds later, i.e.,

a reactor trip could result in a LOOP). IN 93-17 concludes that plant design should reflect all credible sequences of the LOCA/LOOP, but states that a sequence of a LOCA and an unrelated LOOP is of very low probability and is not a concern.

As seen from inspection of Figures 1 and 2 the RADTRAD and PERC2 transport model for containment leakage via the SBGTS are essentially the same.

ESF leakage With the exception of noble gases, all the fission products released from the core in the gap and early in-vessel release phases are assumed to be Instantaneously and homogeneously mixed in the suppression pool water at the time of release from the fuel. Per Reference 4, a minimum sump volume of 110,000 gallons is utilized in this analysis. In accordance with RG 1.183, with the exception of iodine, all radioactive I E-FORM A

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04114/00 DESIGN ANALYSIS NO. QDC-0000-N-1117 REV: 0 PAGE NO.14 materials in the recirculating liquid is assumed to be retained in the liquid phase. The subsequent environmental radioactivity release is summarized below:

In accordance with the station specific parameters provided In Reference 4 and the guidance provided in Reference 3, equipment carrying suppression pool fluids and located inside the Reactor Building are postulated to leak into the reactor building at twice the expected value of 10 gph. ESF leakage is conservatively assumed to start at the onset of the LOCA. Since the temperature of the recirculation fluid is less than 2102F, ten percent (10%) of the halogens associated with this leakage become airborne and are filtered and exhausted (with 50% mixing and holdup in the RB) to the environment via the SBGTS. The chemical form of the iodine released from the sump water is 97% elemental and 3% organic.

As seen from inspection of Figures 1 and 2 the RADTRAD and PERC2 transport model for ESF leakage via the SBGTS are essentially the same.

Control Room Design/OperatiorVTranswort Modeling The control room (CR) is modeled as a single region. Isotopic concentrations in areas outside the control room envelope are assumed to be comparable to the isotopic concentrations at the control room intake locations. The CR ventilation intake corresponds to a single intake design which is utilized during both normal and emergency mode. The CR emergency ventilation system is manually initiated 40 mins after the LOCA. In accordance with Reference 4, during the initial 40 mins the CR is assumed to be on normal ventilation (unfiltered, flow rate of 2000 +/- 10%). The model utilizes a normal operation flowrate of 2200 cfm to maximize the contribution during this period.

The CR pressure boundary free volume Is 184,000 cu ft. The ventilation system is designed to maintain the CR at 1/8 w.g during both normal and accident mode. The CR emergency intake flow rate Is 2000+/- 10% cfm and has a filter efficiency of 99% for all forms of iodine. The model utilizes an intake flowrate of 1800 cfm to minimize control room cleanup. The unfiltered inleakage into the CR during normal and accident mode Is 260 cfm which includes the 10 cfm inleakage (per SRP 6.4, Reference 12) due to ingress/egress.

In accordance with Reference 4, the atmospheric dispersion factors generated for the CR intake are representative for control room inleakage.

l E-FORM I

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04114100 DESIGN ANALYSIS NO. QDC-0000-N-1117 REV: 0 PAGE NO.15 I FIGURE 1 Activity Transport and Dose Model used in RADTRAD Environment Station Chimney Ret. _

MSIV-Ikg Filtered Horrizontal and Vertical MSL lines Intake wIPF Inleakage Notes:

NatJLep: Natural Deposition and Elemental Iodine Plateout DWjlkg: Primary Containment leakage to RB MSIV-lkg: Prinary Containment leakage via MSL including externally (to RADTRAD) calculated, proprietary deposition/ plateout rates, holdup and decay in a single line modeled as 5 Tanks in series.

HS1 through HS4 are horizontal sections of the MSL.

VSI is the vertical sections of the MSL During periods when the CR intake is not filtered, the filter efficiency is set to 0.00 Transport Model input parameters arm in the Inputs and Calculation Sections herein 11 E-FORM

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04114/00 DESIGN ANALYSIS NO. QDC-0000-N-1117 REV: 0 PAGE NO.16 FIGURE 2 Activity Transport Model used In PERC2 to Validate and Verify RADTRAD Results Environment Station Chimney Rel.-4 NatDep: NatLDep: Natural Deposition and Elemental Iodine Plateout DWjkg: Primary Containment leakage to RB MSIVYlkg: Primary Containment leakage via MSLs DF: Externally Calculated Total Deposition IPlateout DFs Holdup Volume is sum of HSI through HS4 plus VS1 in Fig. 1 During periods when the CR intake is not filtered, the filter efficiency is set to 0.00 Transport Model input parameters are in the Inputs and Calculation Sections herein I E-FORM I

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04_14/00 DESIGN ANALYSIS NO. QDC-OOOG-N-1117 REV: 0 PAGE NO.17 FIGURE 3 Summary Time-Line of Events of the "Base Case" following a postulated LOCA at Quad Cities Unit I or Unit 2 using Alternate Source Terms Time After LOCA 0-2 I 2-30 I 30-32 32-40 I 40-90 90-122 9 I 2-24 1-30 Key Parameters m(min) I m lm mm hr (da gap release from core to -

containment atm. _

early-in-vessel core release I  : -

to containment atm. I --

containment leakage via RB - ,

to SB3GTS to Stack I I I I II ESF leakage via RB to l l - l t SB3GTS to Stack I I I III containment leakage via  ; l. I . -; I Main Steam Line I I I Nf ;4 4 *'

fumigation of Plant Stack releases "

control room unfiltered intake I I (normal operating mode) .  :

-o -' v  ;

Control room filtered intake I I V i (emerg. vent. mode) I -.

control room unfiltered .

inleakage , - f I E-FORM I

NES-G-1 4.02 Effective Date:

04/14/00 DESIGN ANALYSIS NO. ODC-0D00-N-1117 REV: 0 PAGE NO.1IS8 Proposed Changes to Design Basis (PART 2)

Containment Airborne ActMtv Per Reference 4, the containment airborne model described above In Part 1 for containment leakage remains unchanged except that the total containment leakage rate is increased from 0.01 volume fractions per day in Part 1 to 0.03 volume fractions per day. Additionally, for Part 2, the leakage reduces to half its value 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the postulated LOCA.

Containment Leakage via MSIVs Except as noted, the methodology I input parameters described in Part I for containment leakage via MSIVs remains unchanged. A parametric study based on the 5*' unit concept was performed to establish the dose impact in the control room due to changes in MSIV leakage. Based on the results of this study (summarized in Appendix A of this calculation), the total leakage from all MS Lines is increased from 79.6 scfh measured @48 psig to 250 scfh measured @48 psig, allowing a maximum of 100 scfh

@48 psig from any one of the 4 MS lines. Additionally, in Part 2 the MS valve leakage reduces to half its value 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the postulated LOCA.

The model in Part 2 assumes a total leakage rate of 250 scfh comprised of 100 scfh from a MSL that experiences a single failure of the outboard MS valve in the shortest line, plus 100 scfh from a second MS line that is assumed to break just after the outboard valves, plus 50 scfh from a third MS line that is also assumed to break just after the outboard valve. This combination of flows maximizes the dose consequences for a total MSIV leakage of 250 scfh @ 48 psig as activity retention within the MSL increases nonlinearly with increasing residence time (decreasing flow) as depicted in Appendix A.

Note that a reference pressure of 48 psig Is utilized for in-containment pressure at accident conditions to establish the percentage of the total allowable containment leakage (3%/6/day) that can be released via the MSIV leakage pathway. This also allows for the continued use of the current conversion factor of 1/1.73 to establish the MSIV leakage that would be observed at the MSIV test pressure of 25 psig. Thus, the reference In-containment pressure is merely used to fix the allowable MSIV leakage specified in containment volume fractions per day, which is the key input In the dose analysis, and is independent of actual containment pressure.

As discussed previously, holdup is addressed using the series of five (5) tanks that represent a single MS line. Time for initiation of MSL releases to the environment was determined using a criteria of 40 minutes (i.e.; time at which the CR is in full emergency ventilation operation) or 1/8 the time determined using a plug flow model for retention -

whichever time was smaller. For all cases considered, 40 minutes was the limiting time l E-FORM I

NES-G-1 4.02 Effective Date:

04/14100 DESIGN ANALYSIS NO. ODC-0000-N-1117 REV: 0 PAGE NO.19 l for initiation of MSIV releases. The average transit time for the worst line (proposed design) in plug flow is 6.8 hrs (V/F = 160 cu. ft. 10.39075 cfm /60 min/hr). Since 40 min

< (6.8 hrs 1 8), the model assumed that the leading edge would begin environmental release at 40 min after the LOCA Containment leakage via the SBGTS Per Reference 4, the methodology described above in Part 1 for containment leakage via SBGTS remains unchanged, except for the following:

• Containment leakage into the Reactor Building increases from 0.0072 volume fractions per day in Part 1 to 0.0211 volume fractions per day in Part 2.

• The SBGTS efficiency changes from 95% for aerosols, elemental and organic iodine to 99% for aerosols and 50% for elemental and organic iodine.

ESF leakage Per Reference 4, the methodology described above in Part 1 for ESF leakage via SBGTS remains unchanged, except for the following:

• ESF leakage rate into the Reactor Building increases from 20 gph (2 times the expected leakage rate of 10 gph) in Part 1 to 2 gpm (two times the proposed Technical Specification value of 1 gpm) in Part 2.

• The SBGTS efficiency changes from 95% for aerosols, elemental and organic iodine to 99% for aerosols and 50% for elemental and organic iodine.

Control Room DesiglnOgeration/Transwort Modeling Per Reference 4, the methodology described above in Part 1 for Control Room modeling remains unchanged, except for the following:

• The allowable infiltration rate increases from 260 cfm In Part 1 to 600 cfm in Part 2.

(both values include a 10cfm for ingresslegress)

• The CR intake filter efficiency changes from 99% for aerosols, elemental and organic iodine to 99% for aerosols and 95% for elemental and organic iodine.

The RADTRAD transport model associated with the LOCA, for Part I as well as Part 2 is presented in the Figure 1 while the PERC2 transport model to check RADTRAD results is presented In Figure 2. Except as noted in Table 1, the key assumptions /

parameter values used are the same as in the "Base Case" LOCA analysis.

I E-FORM

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04/14/00 DESIGN ANALYSIS NO. ODC-0000-N 117 REV: 0 PAGE NO.20 I , . .-- R ---~~~~~~~~~~~~~~~~~~~~~~~~~

TABLE 1 Sumunary of Proposed Design Basis Changes Part I Value Part 2 Value Item "Base Case" "Proposed Change" Notes Total Containment L, . -30d (I% d") 0-Id (3% d) 1-30d (15% dc')

Total MSIV leakage 0-30d (79.6 scth) 0- Id (250 scfh) MSIV leakage values are measured (0.283 %d') (a89 %d') at 48 psig. MSV leakage rates (0.31) efin) (0.9769 cffn) used in this assessment assume leakage is measured on the high-

. -30d (125 scfh) pressure side of the MSI valve.

(0.445 %d')

(0.4884 cfin)

Maximum MSIV leakage from 0-30d (79.6 scft) (0-id) 100 scfh The current plant technical any one of the four MSLs (0.283 %d-) (0.356 %d') specifications allow the plant to (0.31 cfin) (0.39075 cfin) have all MSV leakage from one line.

(1-30d) 50 scfh (0.178 %d') The proposed Plant Technic (0.1954 qfin) Specifications will limit one ine to 100 scfh evaluated at 48 pSi Leakage from Drywell 0-30d (0.717% d') 0-Id (2.11 % d-')

To Reactor Building I-30d (1.055% cr1) .

ESF leakage 20 gph 2 gpm- The actual plant allowable leakage is limited to half the values used in

.______________________________________ the analysis herein RB SBGTS Filter Eff. HEPA filter efficiency tests performed in accordance with Aerosols 95% 99% industry standards assure an Elemental Iodine 95% 50% efficiency greater than 99%

Organic Iodine 95% 50%

Includes 10 cfm for ingressegress CR Infiltration rate 260 cfm 600 cfm CR Intake Filter Eff. HEPA filter efficiency tests performed in accordance with Aerosols 99% 99% industry standards assure an Elemental Iodine 99% 95% efficiency greater than 99%

Organic Iodine 99% 95%

I E-FORMA

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04/14/00 DESIGN ANALYSIS NO. QDCO0OG-N-1117 REV: 0 PAGE NO.21 4.0ASSUMPTIONS I ENGINEERING JUDGEMENTS

1. It is estimated that environmental releases due to MSIV leakage will not occur until well over one hour. However, the analysis.conservatively assumes that holdup of activity releases due to MSIV leakage in MSLs Is limited to 40 minutes (the time for CR emergency ventilation to manually initiated).

2. In determining the initiating time for activity release due to convective flow patterns within the pipe, a factor of 1/8 is applied to the calculated plug flow residence time to estimate the time to breakthrough for the leading edge of the activity front. This time is compared to the manual initiation time for the CR emergency ventilation and the shorter time chosen. The 1/8 factor has been previously used within the industry to determine time to breakthrough and is applied to only this portion of the analysis.

Activity transport through the Main Steam Lines is modeled via CSTs (continuously stirred tanks) and not as plug flow.

3. To maintain an ultimate suppression pool pH of greater than 7, credit Is taken for the sodium pentaborate in the Standby Liquid Control System, which is assumed to be manually initiated via the EOPs such that the entire inventory of sodium pentaborate is delivered and mixed in the suppression pool within 24 hrs of the LOCA 5.0DESIGN INPUTS Item Value Reference Source Term

1. Power level 3016 MWth Ref.4 (w margin for power uncertainty)

2. Fuel Cycle Length 24 Month Cycle Ref.4

3. Fission Products Released per RG 1.183 Ref.3, 4

4. Iodine Fractions per RG 1.183 Ref.3, 4 organic 0.0015 elemental 0.0485 particulate 0.95 i E-FORM I

NES-G-1 4.02 Effective Date:

04/14/00 DESIGN ANALYSIS NO. QDC-0000-N-1117 REV: 0 PAGE NO.22 5.- Fue ReesItmn

5. Fuel Release Urning per RG 1.183 Ref.3, 4 gap Onset: 2 minutes Duration: 30 minutes early-invessel Onset: 32 minutes Duration: 90 minutes

6. Core Activity in Ci / MWh Ref. 6 RADTRAD Core RADTRAD Core RADTRAD Core NLw.No. Nuclide Actniiv Nuc.No. Nulide Activit-Y Nuc.No. Nuclide Acti 001: Co-58 O.OOOE+00 021: Ru-103 4.311 E+04 041: Cs-136 2.379E+03 002: Co-60 O.OOOE+OO 022: Ru-105 3.034E+04 042: Cs-137 4.928E+03 003: Kr-95 4.364E+02 023: Ru-106 1.837E+04 043: Ba-139 4.888E+04 004: Kr-85m 6.772E+03 024: Rh-I 05 2.882E+04 044: Ba-t40 4.714E+04 005: Kr-87 1.291 E+04 025: Sb-127 2.999E+03 045: La-140 5.055E+04 006: Kr-88 1.81 5E+04 026: Sb-129 8.877E+03 046: La-141 4.447E+04 007: Rb-86 7.096E+01 027: Te-127 2.986E+03 047: La-142 4.286E+04 008: Sr-89 2.428E+04 028: TL-127m 4.060E+02 048: Ce-141 4.465E+04 009: Sr-9o 3.528E+03 029: TL-129 8.735E+03 049: Ce-143 4.101 E+04 010: Sr-91 3.081 E+04 030: Te-129m 1.300E+03 050: Ce-144 3.682E+04 011: Sr-92 3.362E+04 031: Te-131m 3.955E+03 051: Pr-143 3.963E+04 012: Y-90 3.625E+03 032: Te-1 32 3.850E+04 052: Nd-147 1.800E+04 013: Y-91 3.155E+04 033: 1-131 2.71 OE+04 053: Np-239 5.587E+05 014: Y-92 3.377E+04 034: 1-132 3.914E+04 054: Pu-238 1.768E+02 015: Y-93 3.942E+04 035: 1-133 5.501 E+04 055: Pu-239 1.474E+01 016: Zr-95 4.443E+04 036: 1-134 6.035E+04 056: Pu-240 2.001E+01 017: Zr-97 4.497E+04 037: 1-135 5.157E+04 057: Pu-241 6.700E+03 018: Nb-95 4.464E+04 038: Xe-133 5.282E+04 058: Am-241 9.857E+00 019: Mo-99 5.121 E+04 039: Xe-135 2.144E+04 059: Cm-242 2.285E+03 020: Tc-99m 4.484E+04 040: Cs-134 8.009E+03 060: Cm-244 1.621 E+02 Drywell Airborne Activity Leakage

7. Volume of Primary Containment 1.58E5 ft3 Ref.4

8. Drywelf Surface Area 32,430 ft2 Ref.4

9. Elemental Iodine Kw mass transfer coefficient 4.9 meters / hr Ref.1 0

10. Primary Containment Leak Rate 1% day' Ref.4 l E-FORM I

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04114100 DESIGN ANALYSIS NO. ODC-0000-N-1117 REV: 0 PAGE NO.23

11. Correlation of BWR effective natural deposition decontamination coefficients with reactor thermal power for design basis accidents (10 percentile) from Ref.15 Release Phase Time Interval (hr) eosrnon(h 1) gap 0-0.5 1.285[exp(-21 19/P(MWt)J gap 0.5-2 1.161 [exp(-2274/P(MWth)1 early in-vessel 0.5-2 0.520[exp(-21 73/P(MWth)]

gap + early in-vessel 2-5 1.551 [exp(-1 507/P(MWth)]

gap + early in-vessel 5-8.33 0.836[exp(-1 051/P(MWnh)l gap + early in-vessel 8.33-12 0.780[exp(-1 31 6/P(MW1 .)J gap + early in-vessel 12-19.4 0.7781exp(-1 548/P(MWh)]

gap + early in-vessel 19.4-24 0.780[exp(-1 686WP(MW,)]

12. Leak Rate by MSIVs @48 psig 79.6 scfh Ref.4

13. Pressure Correction between 1.73 RefA 25 psig and 48 psig

14. Natural Deposition Constants in MSLs for Dresden I Quad Cities DBA LOCA with AST; MS Line with Outboard Valve Failure (from Ref.13)

Aerosols Elemental Iodine Period (hour) Lambda hrW Lambda ( hr 1 )

0.0333 - 1.0333 1.8260E+00 i .2695E-01 1.0333- 2.811 1.7860E+00 1.3176E-01 2.811 - 5.033 1.7864E+00 1.4075E-01 5.033 - 10.0333 1 .8079E+00 1.5283E-01 10.0333- 24.033 1.8475E+00 1.8371 E-01 24.0333 - 50.0333 1.9337E+00 3.0375E-01 50.0333 - 69.01 2.0855E+00 7.1498E-01 69.01 -138.92 8.6971 E-01 1.2257E+00 138.92 - 277.81 8.2767E-01 1.2246E+00 277.81 - 720.033 7.8969E-01 1.2246E+00

15. Natural Deposition Constants in MSLs for Dresden / Quad Cities DBA LOCA with AST; Representative MS Line with No Single Failure of Isolation Valve - (from Ref.13)

Aerosols Elemental Iodine Period (hour) Lambda ( hrr ) Lambda ( hr ')

0.0333- 1.0333 1.8454E+00 1.2829E-01 1.0333- 2.811 1.8049E+00 1.3316E-01 2.811 - 5.033 1.8053E+00 1.4224E-01 5.033 -10.0333 1.8271 E+00 1.5445E-01 10.0333 - 24.033 1.8671 E+00 1.8566E-01 24.0333 - 50.0333 1.9542E+00 3.0697E-01 50.0333 - 69.01 2.1076E+00 7.2255E-01 I E-FORM j

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04/14100 DESIGN ANALYSIS No. ODC-0000-N-1117 REV: 0 PAGE NO.24 69.01 -138.92 8.7893E-01 1.2387E+00 138.92- 277.81 8.3644E401 1.2376E+00 277.81 - 720.033 7.9805E-01 1.2376E+00

16. Decontamination Factors in MSLs for Dresden I Quad Cities DBA LOCA with AST; MS Line with outboard Valve Failure: MSIV Leakage :100 scfh@ 48 oslo-(from Ref.13)

Aerosols Elemental Iodine Period (hour) 0.0333 - 1.0333 1.962E+01 2.095E+00 1.0333 - 2.811 1.874E+01 2.146E+00 2.811 - 5.033 1.874E+01 2.245E+00 5.033 - 10.0333 1.922E+01 2.381E+00 10.0333 - 24.033 2.01 OE+01 2.756E+00 24.0333 - 50.0333 1.227E+02 1.284E+01 50.0333- 69.01 1.51 8E+02 8.772E+01 69.01 -138.92 1.775E+01 4.418E+02 138.92 - 277.81 1.606E+01 4.406E+02 277.81 - 720.033 1.465E+01 4.406E+02

17. Volume (ft3) of shortest "fifth unit concept pipe" (as defined in Ref. 13) assuming outboard valve failure (from Ref.13)

• Section 1 (horizontal) 9.42

• Section 2 (horizontal) 16.87

• Section 3 (horizontal) 16.87

• Section 4 (horizontal) 14.28

• Section 5 (vertical) 102.14

18. Volume (ft3) of representative "fifth unit concept pipe" (as defined in Ref.13) assuming outboard valve closure (from Ref. 13)

• Section 1 (horizontal) 9.91

• Section 2 (horizontal) 32.83

• Section 3 (horizontal) 25.14

• Section 4 (horizontal) 25.14

• Section 5 (vertical) 101.78

19. SBGTS adsorption/filtration efficiency 95% (all species) Ref.4

20. Secondary Containment Volume 4.7E6 fl3 Ref.4

21. Fraction of Sec. Cont. Available for Mixing 0.5 Ref.3, 4

22. Plateout/Deposition in Containment Ref.4 I E-FORMI

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04/14/00 DESIGN ANALYSIS NO. ODC-0000-N-1117 REV: 0 PAGE NO.25 organic 0 elemental NUREG-0800,SRP 6.5.2 Ref.10 aerosol Powers Model (10 percentile)

ESF Leakage

23. Suppression Pool Volume 110,000 ft3 Ref.4

24. ESF Leak Rate (with factor of 2 margin) 20 gph - Ref.4

25. Fraction of ESF leakage that becomes airborne 0.1 Ref.3, 4

26. Fraction of iodine form of activity released from ESF Ref.3, 4 elemental 0.97 organic 0.03

27. Duration of ESF leakage 0-30 days Ref.4

28. Fraction of Secohdary Containment 0.5 Ref.3,4 available for ESF leakage mixing Control Room

29. Pres. boundary envelope free volume 184,000 f3 Ref.4

30. Intake Flowrate Ref.4 Normal operation unfiltered 2000 +/- 10%

Emergency filtered intake 2000 +/- 10%

31. Unfiltered inleakage Ref.4 Normal operations 260 cfm Emergency Ventilation mode 260 cfm

32. Intake Filter Efficiency (all species) 99% Ref.4

33. Recirculation rate through filters 0 cfm Ref.4

34. CR Breathing Rate RADTRAD Default Ref.7

35. OPS Units I & 2 CR Atmospheric Dispersion Factors (sec/m3) Ref.4 Release Point 0 Bhour hu 8-24 hour 1 ~- 4day 4 - 30 day MSIV Leakage 1.13E-3 9.45E-4 4.54E-4 2.68E-4 1.67E-4 Station Chimney 2.35E-9 1.15E-9 8.02E-10 3.96E-10 1.21 E-10 (non-fumigation)

Station Chimney 4.16E-4 N/A N/A WA N/A (0 - 0.5 hr fumigation)

E-FORM ]

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04/14100 IDESIGN ANALYSIS NO. ODC-000-N-I117 REV: 0 PAGE NO.26 j Site Boundary

36. Breathing Rate RADTRAD Default Ref.7

37. OPS Units 1 & 2 Site Boundary Atmospheric Dispersion Factors (sec/in3) Ref.4 EAB Release Point 0- 2 hour-MSIV Leakage 1.25E-3 Station Chimney (non-fumigation) 3.21 E-6 Station Chimney (0 - 0.5 hr fumigation) 1.37E-4 LPZ Release Point j 2hor 2 - 8hour 8 -24 hour 1-4dav 4 -30 da MSIV Leakage 6.68E-5 3.07E-5 2.08E-5 8.95E-6 2.67E-6 Station Chimney (non- 3.09E-6 1.52E-6 1.07E-6 4.95E-7 1.64E-7 fumigation)

Station Chimney 1.38E-5 N/A NJA NWA N/A (O- 0.5 hr fumigation)

E-FORM j

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6.0REFERENCES

1. 10CFR50.67, "Accident Source Term'.

2. TID 14844, Calculation of Distance Factors for Power and Test Reactor Sites",

1962

3. Regulatory Guide 1.183, Revision 0, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors", July 2000.

4. Exelon Transmittal of Design Information No. QDC-02-019, "Quad Cities Station Concurrence with the Design Inputs as established for Alternate Source Term (AST) LOCA Analysis' Revision 1,8/1/02

5. Regulatory Guide 1.49, Revision 1, "Power Levels of Nuclear Power Plants".

6. GE Task Report No. GE-NE-A22-00103-64-01, Rev 0, Project Task Report:

'Dresden and Quad Cities Asset Enhancement Program - Task T0802:

Radiation Sources and Fission Products" Dated August 2000.

7. Industry Computer Code RADTRAD 3.02a, "A Simplified Model for Radionuclide Transport and Removal and Dose Estimation' developed by SNL

8. EPA-520/1 020, 1988, Federal Guidance Report No.11, Urimiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion and Ingestion".

9. EPA-420-R-93-081, 1993, Federal Guidance Report No.12, "Extemal Exposure to Radionuclides in Air, Water and Soil"

10. NUREG 0800, 1988, Standard Review Plan, "Containment Spray as a Fission Product Cleanup System', Section 6.5.2, Revision 2.

11. Cline, J.E. 'MSIV Leakage - Iodine Transport Analysis' SAIC, August 20, 1990

12. NUREG 0800, Standard Review Plan, "Control Room Habitability System", SRP 6.4, Revision 2.

13. Stone and Webster Calculation 086457.022-UR(B)-001, Rev.0, Modeling Gravitational Settling / plateout in Main Steam Lines at Dresden 2&3 / Quad Cities 1 &2" I E-FORM I

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04/14/00 DESIGN ANALYSIS NO. QD=-000-N-1117 REV: 0 PAGE NO.28

14. Stone and Webster Computer Program PERC2, NU-226, Version 00, Level 01, "Passive / Evolutionary Regulatory Consequence Code

15. NUREGICR-6189 "ASimplified Model of Aerosol Removal by Natural Processes in Reactor Containments", July 1996

16. S&W Calculation No. DRE02-0033, Revision 0, aUltimate Suppression Pool pH following a Loss of Coolant Accident".

17. NRC Information Notice 93-17, Revision 1, "Safety Systems Response to Loss of Coolant and Loss of Offsite Power," March 25, 1994 (original issue March 8, 1993).

I E-FORM l

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04/14/00 DESIGN ANALYSIS NO. ODC-0000-N-1 117 REV: 0 PAGE NO.29 I 7.0CALCULATION This section discusses the following:

• data pre-processing computations required for input to RADTRAD and PERC2

• RADTRAD and PERC2 output files with execution date and time stamps

• detailed output activity and doses from RADTRAD and PERC2 As stated in the Methodology Section, doses are calculated with the RADTRAD computer program and validated with the PERC2 program. Provided below is the development and description of each of the key RADTRAD and PERC2 inputs for the activity transport and dose models used to calculate the site boundary and control room dose at OPS using Altemate Source Terms.

The RADTRAD input structure is as follows:

1. Compartment definition, its associated volume, and relevant activity removal rates and coefficients.

2. Pathway identification and associated flows and cleanup efficiencies in accumulators in flow streams (pathways) between compartments

3. Dose Location(s) - defined compartment(s)

4. Source Terms - equilibrium shutdown fuel activity, accident release fractions, timing and activity to dose conversion factors)

The OPS DBA LOCA activity transport and dose consequence RADTRAD model is broken up into 3 individual runs:

• Ground level primary containment Isolation valve leakage via four (4) MS Lines.

• Elevated release of primary containment leakage into the reactor building, with mixing, holdup and subsequent treatment from the SBGTS.

• Elevated release of ESF leakage into the reactor building and subsequent treatment from the SBGTS I E-ORM I

NES-G-1 4.02 Effective Date:

04114100 DESIGN ANALYSIS NO. QDC-OOO0-N-1117 REV: 0 PAGE NO.30 Provided below are the calculations of the key inputs to RADTRAD for each of the 3 act vity transport /dose models. Similar to the Methodology Section, the Calculation Section is broken Into two parts.

Part 1: The base case entails the assessment using LAltemate Source Terms" and current QPS design licensing basis plant parameters (identified by Exelon via Reference 4).

Part 2: As noted in Table 1 of the Methodology Section, Part 2 is the base case with the following proposed modifications:

• Increased allowable MSIV leakage from a total of 79.6 scfh @ 48 psig in all four lines to 100 scfh measured @48 psig in one line with a total of 250 scfh measured

@48 psig in all 4 MSLs

• increased allowable control room inleakage from 260 cfm to 600 cfm (includes 10 cfm for ingress/egress)

• increased allowable containment leakage from 1.0% volume per day to 3% volume per day

• reduced SBGTS charcoal Iodine filter efficiency for organic and elemental iodine from 95% to 50%

• Increased credit taken for the SBGTS HEPA filter efficiency from 95% to 99%

• reduced control room charcoal iodine filter efficiency for organic and elemental iodine from 99% to 95%.

• increased allowable ESF leakage from 10 gph to 1 gpm RADTRAD/PERC2 pre-processina. Output File lists and detailed Results for Part 1 Containment Atmosphere Activity Leakage Rate Calculations for "Base Case" Provided below are the estimated activity leakages from containment for the Main Steam Lines and stack releases for the "Base Cases with Proposed Design Basis changes.

Base Case : MSL Release (assumed conservatively to be from one line)

Calculated below is the MSL leakage rate assumed to be across one valve. The outboard valve is assumed to fall open, resulting in less deposition/plateout. Following I E-FORM _

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04114100 IDESIGN ANALYSIS NO. QDC-OOD-N-1117 REV: 0 PAGE NO.31

- - -- E below is a description of how leakage is measured and what leakage is actually modeled in RADTRAD.

MSL Test leakage rate 46 scfh With Pres. Correction Factor for 48 psig 46 scdh x 1.73 = 79.6 sflh Total MSL Flow out of Containment 79.6 scfh x 14.7 psla 1(14.7 + 48 ) psia = 18.658 cfh 18.658 cfh / 60 min/hr = 0.31096 ctm 18.658 ft3lhr x 24 hr/day 1 1.58E5 ft3 x 100 = 0.283 %Iday The test conditions for MSIV allowable leakage for OPS is as follows:

25 psig 0 psig 14.7 psia TEST Measurement MSIV The flow rate input to RADTRAD is the leakage rate measured at peak pressure (48 psig) with leakage model shown below:

48 psig 0 psig 14.7 psia RADTRAD Measurement MSIV Therefore the leakage rate input to RADTRAD consistent with the containment activity release rate in terms of volume fractions per day is expressed as:

X cfm = test leakage x peak correction factorx 14.7/(14.7+48) (60 min/hr)

Containment leakage to Reactor Building Leakage to RB is the total drywell leakage minus that which leaks into the MSL line:

Total Containment Leakage 1 0/o/day Containment Lkg to RB 1%0/day - 0.283 %/o/day 0.717 V/a/day I E-FORM ]

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04114100 DESIGN ANALYSIS NO. QDC-0000-N-1117 REV: 0 PAGE NO.32 Elemental Iodine Removal Coefficient Approximately 5% (0.0485) of the iodine activity released to the containment following the LOCA assuming AST methodology is elemental. Natural deposition of the elemental iodine released to containment is estimated assuming the methodology outlined in NUREG-0800 Standard Review Plan 6.5.2, Rev.2 (pg 6.5.2-10):

The expression for wall deposition is:

Aw.=K A V

kw = first order removal coefficient by wall deposition A = wetted surface area (32,450 ft2) (assume same value as DRE 32,250 ft2 51 unit concept)

V = drywell net free volume (1.58E5 f3)

Kw = mass transfer coefficient from SRP 6.5.2 (4.9 m/hr)

Au, = 4.9 in/hr (3.2808 ft um) (32,250 f2)/ (1.58E5 fte) = 3.28 hr 1 Time when Elemental Iodine DF of 200 Is reached In Containment Atm.

The value of 3.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to reach a DF of 200 for elemental iodine is achieved by semi-log interpolation. A test run of PERC2 was made with estimated cutoff times.

Interpolation between two time periods from this test run resulted in a DF = 200 in about 3.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The value of 3.1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to terminate the elemental deposition lambda was then entered to the final PERC2 model run and verified as shown below:

As stated in RG 1.183 Rev.0 (Ref.3), the cutoff time for elemental iodine plateout in containment is based on NUREG-0800 SRP 6.5.2, Rev.2 (Ref.10). The SRP states that the Iodine decontamination factor, DF, is defined as the maximum concentration in the containment atmosphere divided by the concentration of iodine in the containment atmosphere at some time after decontamination. The maximum DF is 200 for elemental iodine. The effectiveness in removing elemental iodine shall be presumed to end at that time, post LOCA, when the maximum elemental iodine DF is reached.

Using the core halogen release fractions in Table 1 of RG 1.183 Rev.0 (0.05 plus 0.25 =

0.3), the fraction of elemental iodine airborne in the containment (0.0485) and a tracer halide 1-131, the elemental plateout cutoff time is:

Initial elemental 1-131 inventory released to containment I E-FORM7I

NES-G-1 4.02 Effective Date:

04/14/00 DESIGN ANALYSIS NO. ODC-OOOD-N-1117 REV: 0 PAGE NO.33

= 1-131 Activity / MWth x P(MWth) x fraction released x form fraction

= 2.71 0E4 CViMWth x 3016 MWth x 0.3 x 0.0485 =1 .1892E6 Ci From run RI1 17qdcO13d.out at interval 7 (3.1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) gap 0.0047361 CVm3 Early In-Vessel 1.3354 CV m 3 Total 1.3401 Ci/ m3 1-131 Activity (Ci) = 1-131 Concentration x Volume (m3)

= 1.3401 Ci/m3 x 4474.062 m 3 = 5996 Ci Drywell Volume = 1.58E5 ft3 or 4474.062 m 3 DF (T=3.1) = 1.1892E6 Ci 15996 Ci = 198.3 or essentially 200 Calculation of "Powers Model" Containment Aerosol Deposition Coefficients Using the time dependent equations in from NUREG/CR-6891 and the Reactor Power level in Datum #1 (3016 MWth), the following natural deposition lambda's (hr') are calculated for Quad Cities Units 1 and 2:

Applicable Period Constants Lambda Phase From(hr) To(hr) C1 C2 Wr GAP 0 0.5 1.285 2119 0.636464 GAP - 0.5 2 1.161 2274 0.54624 E I-V 0.5 2 0.52 2173 0.252987 G+E I-V 2 5 1.551 1507 0.941041 G+E I-V 5 8 0.836 1051 0.590018 G+E I-V 8 12 0.78 1316 0.504191 G+E I-N 12 19.4 0.778 1548 OA65664 G+E I-V 19.4 24 0.78 1686 0.445981 Site Boundary Dose Assessment for "Base Case" The Exclusion Area Boundary (EAB) and Low Population Zone (LPZ) are calculated by RADTRAD using the equations described in the Methodology Section. RADTRAD requires the completed transpot model and time dependent dispersion factors as input, while breathing rates are RADTRAD default values.

The EAB worst-case 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> window" is described In RG 1.183 Rev. 0 as:

1,E-FORM I

NES-G-14.02 Effective Date:

04114100 DESIGN ANALYSIS NO. QDC-O000-N-1117 REV: 0 PAGE NO.34

'The maximum EAB TEDE for any two-hour period following the start of the radioactivity release should be determined and used Indetermining compliance with the dose criteria in 10 CFR 50.67. The maximum two-hour TEDE should be determined by calculating the postulated dose for a series of small time increments and performing a 'sliding' sum over the increments for successive two-hour periods."

RADTRAD calculates the " worst-case 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> window TEDE" internally if the worst 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> xJO is used for the duration of the accident release, however, since each pathway is run seperately (i.e., containment Ikg via stack, ESF leakage an MSL leakage),

RADTRAD provides three "worst-case 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> window" periods. Since the MSL leakage dominates the dose consequence, it's calculated "worst-case 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> window" period is used for the remaining two pathways. To force RADTRAD into using the same 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> window period for all three leakage pathways the x/Q value in the two remaining pathways is set to zero (0) except for the "Vorst-case 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> window" period calculated by RADTRAD in the MSL pathway run. As a result, the EAB TEDE can be taken directly out of RADTRAD without further assessment, since the non-zero appropriate 2-hour x/Q value is only used only during the "worst-case 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> window" period.

NOTE: Ultimately, PERC2 was run for the Part 2 models only. The dose results for Part 2, as would be expected, come much closer to the design dose limits discussed in the Acceptance Criteria section than the doses calculated in Part 1. Additionally all of the modeling In Part 2 is the same as Part 1 with the exception of 2 additional MSL lines).

Therefore by using PERC2 to validate the RADTRAD results in Part 2, the results of Part 1 are also validated.

E-FORM i

NES-G-1 4.02 Effective Date:

- I - -0414100 DESIGN ANALYSIS NO. QDC-O000-N-1117 REV: 0 PAGE NO.35 Computer Output Flies for Part 1 File Name Time and Date Stamp Run Descriplion OPS Units 1 and 2 Part 1 "Base Case" RI 117qdcOOl.out RADTRAD Version 3.02a run on 7124/2002 at 12:06:09 Core gap release - Cont. Alm. - RB 4 SBGT 4 Stack 4 Envron. (EAB, LPZ and CR)

Ri117qdcO02.out RADTRAD Version 3.02a run on 712412002 at 12:51:50 EI-V core release 4 Cont. Atm. 4 RB 4 SBGT 4 Stack 4 Environ. (EAB. LPZ and CR)

RI1 17qdc003.out RADTRAD Version 302a run on 712412002 at 12:5B:44 ESF 4 RB 4 SBGTS 4 Stack 4 Environ (EAB. LPZ and CR)

R1 117qdc004a.out RADTRAD Version 302a run on 712412002 at 13:29:25 Core gap release 4 Cont. Atm. 4 MSL 4 Environ (EAB,and CR)

Ri117qdcO04b.out RADTRAD Version 3.02a run on 7124/2002 at 13:58:43 Core gap release 4 Cont. Atm. 4 MSL 4 Environ (LPZE RI I 7qdcO05a.out RADTRAD Version 3.02a run on 7124U2002 at 14:49:37 E I-V core release 4 Cont. AtM. 4 MSL 4 Environ (EAB,and CR)

R1117qdcO05b.out RADTRAD Version 3.02a run on 712412002 at 15:01:22 E I-V core release 4 Cont Atm. 4 MSL 4 Environ (LPZ)

I E-FORM _

NES-G-14.02 Effective Date:

04114100 DESIGN ANALYSIS NO. QDC-0000-N-1117 REV: 0 PAGE NO.36 Table 2 ODC Output dose results for 'Base Case" from RADTRAD Control Room Operator SHe Boundary EAB Site Boundary LPZ Dose (rem) Dose (rem) Dose (rem) 1-131 Whole Body Thyroid TEDE Whole Body Thyroid TEDE Whole Body Thyroid TEDE Activity (Cl)

CONT gap 4.51 E-05 6.40E-02 2.90E-03 5.OOE-03 2.31 E-01 1.55E-02 2.05E-03 5.39E-02 4.48E-03 1.09E+02 e I-v 7.99E-07 2.92E-05 2.71gE.05 7.39E-02 1.31 E+00 1.59E-01 2.92E-02 2.41 E4-1 4.47E 02 5.40E.02 4.59E-05 6.40E-02 2.90E-03 7.89E-02 1.54E+OO 1.74E-01 3.12E-02 2.95E-01 4.91 E-02 6.48E+02 MSL gap 1.22E-02 2.32E.0O 1.OOE-01 5.251E-02 3.41 E+OO 1.98E-41 1.22E-02 5.39E-01 3.27E-02 1.93E+02 e I-v 1.98E-01 1.13E+01 7,422-0 6.77E-01 1.92E+01 1.81 E+00 1.94E-01 2.57E+OO 3.17E.01 9.50E+02 2.1 OE-01 1.37E+01 8.43E-01 7.30E-01 2.26E+01 2.01 E+00 2.06E-01 3.11 E+O0 3.49E-01 1.14E+03 ESF 9.92E-08 5.70E04 1.80E-O 2.20E-04 4,18E.02 1.52E--03 2.012-04 770223E3 7,35E+02 Total 2.10E-01 1.37E+01 0.85 l 8.09E-01 2.42 E+01 L~~I 2.38E-01 3.46E+0O0 ... 2.53E+03 I E-FORM I

NES-G-1 4.02 Effective Date:

0414104 DESIGN ANALYSIS NO. QDC-0000-N-1117 REV: 0 PAGE NO.37 RADTRAD/PERC2 pre-processlni,,Output File lists and detailed Results for Part 2 All calculations performed above in Part 1 are valid for Part 2 except as noted below:

Containment Atmosphere Activity Leakage Rate Calculations for "Base Case with Proposed Design Basis Changes" A parametric study based on the 5 h unit concept was performed to establish the dose impact in the control room due to changes in MSIV leakage. Based on the results of this study (summarized in Appendix A of this calculation), the total leakage from all MS Lines is increased from 79.6 scfh measured @ 48 psig to 250 scfh measured @ 48 psig, allowing a maximum of 100 scfh @ 48 psig from any one of the 4 MS lines.

Additionally, in Part 2 the MS valve leakage reduces to half its value 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the postulated LOCA.

The model in Part 2 assumes a total leakage rate of 250 scfh comprised of 100 scfh from a MSL that experiences a single failure of the outboard MS valve in the shortest line, plus 100 scfh from a second MS line that is assumed to break just after the outboard valves, plus 50 scfh from a third MS line that is also assumed to break just after the outboard valve. This combination of flows maximizes the dose consequences for a total MSIV leakage of 250 scfh @48 psig as activity retention within the MSL increases nonlinearly with increasing residence time (decreasing flow) as depicted in Appendix A.

MSL total allow. leakage @ test press 145 scfh With Correction Factor for 48 psig 145 scfh x 1.73 = 250 scfh Total MSL Flow out of Containment 250 scfh x 14.7 psia 1(14.7 + 48 ) psia = 58.612 cfh 58.612 cfh / 60 min/hr = 0.97687 cfm 58.612 ft3/hr x 24 hr/day / 1.58E5 ft3 x 100%/e = 0.8903 %/day Allowable leakage I MSL e 48 psig 100 scfh Single Une flow from wworst Line" 100/250 x 0.97687 = 0.3907 cfrn and from the 1 remaining line" Single Une flow from "2nd Remainingn line 50 / 250 x 0.97687 = 0.1954 cfm Containment leakage to Reactor Building Leakage to RB is the total drywell leakage minus that which leaks into the MSL lines:

Total Containment Leakage 3 %/6day Containment Lkg to RB 3 %/oday- 1.068 %/day 2.11 %fday l E-FORM

NES-G-14.02 Effective Date:

04114100 DESIGN ANALYSIS NO. QDC-0000-N-1117 REV: 0 PAGE NO.38 Computer Output Flies for Part 2 RADTRAD OUTPUT File Name Time and Date Stamp Run Description OPS Units 1 and 2 Part 2 "Base Case with Proposed Design Changes" RI 1t7qdc006.out RADTRAD Version 3.02a run on 7126/2002 at 09:42:45 core gap release 4 Cant. Atn. 4 RB + SBGT 4 Stack 4 Environ. (EAB, LPZ and CR)

RI 117qdcO07.out RADTRAD Version 3.02a run on 7126/2002 at 09:59:41 E I-V core release 4 Cont. Atm. 4 RB 4 SBGT 4 Stack 4 Environ. (EAB, LPZ and CR)

Rl 17qdcOO8.out RADTRAD Version 3.02a run on 7/24/2002 at 15:18:02 ESF 4 RB 4 SBGTS 4 Stack 4 Environ

_EAB, LPZ and CR)

RI 1 7qdcO09a.out RADTRAD Version 3.02a run on 7/24/2002 at 15:22:34 core gap release 4 Cont. Atm. 4 100 scfh Worst MSL 4 Environ 4EAB,and CR)

R1117qdcO09b.out RADTRAD Version 3.02a run on 7124J2002 at 16:32:52 core gap release 4 Cont AtM 4 4 100 scfh Worst MSL 4 Environ (LPZ)

R1117qdcOlOa.out RADTRAD Version 3.02a run on 7/24/2002 at 15:34:15 El- release 4 Cont. Atm. 4 4 100 sclh Worst UMSL 4 Environ (EABand CR)

R1117qdcOlOb.out RADTRAD Version 3.02a run on 712412002 at 16:44:11 El- release 4 Cont. Atm. 4 4 100 sclh Worst MSL 4 MSLs 4 Environ (LPZ)

R1117qdcOlla.out RADTRAD Version 3.02a run on 7/24/2002 at 15:45:59 core gap release 4 Cont. Atn. 4 100 scfh Remaining MSL 4 Environ (EABxand CR)

R1117qdcO11b.out RADTRAD Version 3.02a run on 7/24/2002 at 16:55:30 core gap release 4 Cont. Atn. 4 100 sclh Remaining MSL 4 Environ (LPZ)

RI 1I7qdcO2a.out RADTRAD Version 3.02a run on 712412002 at 15:57:43 E I-V release 4 Cont Atm. 4 100 scM -

Remaining MSL 4 Environ (EABand CR)

RIt 7qdcOl2b.out RADTRAD Version 3.02a run on 7/24/2002 at 17:06:50 El-V release 4 Cont Atrm. 4 100 sdh Remaining MSL 4 Environ (LPZ)

RI I17qdcO13a.out RADTRAD Version 3.02a run on 7/24/2002 at 16:09:26 core gap release 4 Cont. Atm. 4 50 scfh Remainino MSL 4 Environ (EABand CR)

Ri 1 7qdc013b.out RADTRAD Version 3.02a run on 7/24t2002 at 17:18&09 core gap release 4 Cont. Abn. 4 50 scfh Remainino MSL 4 Environ (LPZ)

RI1I 7qdcO14a.out RADTRAD Version 3.02a run on 7124/2002 at 16:21.07 E I-V release 4 Cant. Atm. 4 50 sWhM Remainig MSL 4 Environ (EAB and CR)

R1117qdc0l4b.out RADTRAD Version 3.02a run on 7/2412002 at 17:29:30 E I-V release 4 Cont Atm. 4 50 scfh Remaining MSL 4 Environ (LPZ)

II E-FORM I

NES-G-14.02 Effective Date:

04114J00 DESIGN ANALySIS NO. REV: 0

=DC-0000-N-1117 PAGE NO.39 PERC2 OUTPUT File Name Time and Date Stamp Run Descriptlon OPS Units 1 and 2 Part 2 'Base Case' with Proposed Design Basis Changes" RI I l7qdcOl5c.out PERC2 Version 3.02a run on 07/25102 at 08:51:25 Cont Atm. 4 RB 4 SBGT 4 Stack 4

.___________ ________________________________ trom Environ. tCR thy infiltration)

RI117qdcO15p.out PERC2 Version 3.02a run on 07/25/02at08:51:25 Cont. Atm. 4 RB 4 SBGT 4 Stack 4 Environ. (I/O &Activity Released to Env.)

R1117qdcOl5d.out PERC2 Version 3.02a run on 07/25/02 at 08:51:25 core gap release 4 Cont. Atm. (Concentrations)

R11117qdc0l6c.out PERC2 Version 3.02a run on 07/25/02 at 08:59:16 Cont. Atm. 4 RB 4 SBGT 9 Stack 4 Environ. (CR thyroid from intake)

R1117qdcOl6p.out PERC2 Version 3.02a run on 07/25/02 at 08:59:16 Cont. Atm. 4 RB 4 SBGT 4 Stack 4 Environ. (UO &Activity Released to Env.)

R1117qdcO17c.out PERC2 Version 3.02a run on 07/25/02 at 09:07:07 ESF 4 RB 4 SBGTS 4 Stack 4 Environ (CR intake &infilbtation)

R1117qdc0l7p.out PERC2 Version 3.02a run on 07/25W2 at 09:07.07 ESF 4 RB 4 SBGTS 4 Stack 4 Environ (U/0

&Activtv Released to Env.)

RII17qdc018c.out PERC2 Version 3.02a run on 07/25/02at 09:11:04 Cont. Atm. 4 100 scfh Worst MSL 4 Environ (CR thyroid from kifiltration)

RI17qdcO18p.out PERC2 Version 3.02a run on 07/25/02 at 09:11:04 Cont. Atm. 4 100sclh Worst MSL 4 Environ (Input file text / Output text & Actit Released to Env.)

R1117qdcO19c.out PERC2 Version 3.02a run on 07/25102 at 09:16:55 Cont. Atm. 4 100 scfh Worst MSL 4 Environ (CR throid from intake)

R1117qdc0i c.out PERC2 Version 3.02a run on 07/25/02 at 09:18:55 Cont Atm. 4 100 scfh Worst MSL 4 Environ (Input mile lext I Output text)

E-FORM I

NES-G-14.02 Effective Date:

04M14100 DESIGN ANALYSIS NO. QDC-0000-N-1117 REV: 0 PAGE NO.40 Table 3 OPS Output dose results for "Proposed Design Basis Changes" from RADTRAD Control Room Operator Site Boundary EAB Site Boundary LPZ 1-131 Dose (rem) Dose (rem) Dose (rem)

Whole Body Thyroid TEDE Whole Body Thyroid TEDE Whole Body Thyroid TEDE Activity (Cl)

CONT gap 1.21 E-04 1.06E-01 3.94E-03 1.43E-02 2.52E-01 2.43E-02 4.95E-03 8.28E-02 7.95E-03 4.04E+02 a i-v 2.18E-06 1.14E-05 6.11 E-06 2.1E-0 1.35E+OO 2.79E-01 7.31 E-02 3.9-Agu 8.98E-02 2.27E+03 1.23E-04 1.06E-01 3.95E-03 2.24E-01 1.61 E+OO 3.04E-01 7.80E-02 4.71 E-01 9.77E-02 2.67E+03 MSL (wl-100 scfh) gap 1.53E-02 7.11 E+00 3.05E-01 9.05E-02 7.90E+00 4.34E-01 1.51 E-02 8.55E-01 5.03E-02 1.58E+02 e I-v 2.36E§04 3.50E+01 9.14E+00 1.11 E+00 4.52E+01 3.85E+OO 2.24E-01 4.03E+00 4.47E-01 7.8aE+02 2.51 E-01 4.21 E+01 2.44E+00 1.20E+O0 5.31 E+01 4.29E+00 2.39E-01 4.88E.00 4.97E-01 9.41 E+02 MSL (rl-100 scfh) gap 1.23E-02 3.81 E+00 1.541E-01 5.38E-02 3.32E+00 1.92E-01 1.16E-02 4.12E-01 2.71 E-02 1.26E.02 e i-v 1.94E-01 1.84E+01 1.04E+00 5.97E-01 1.76E+01 1.62E+00 1.86E-01 2.93E+00 2.82E-01 6.20E029 2.06E-01 2.221E+01 1.20E.00 6.51 E-01 2.09E+01 1.81 E+00 1.98E-01 2.44E+00 3.09E-01 7.46E+02 MSL (ri-50 scfh) gap 3.19E-03 8.47E-01 3.06E-02 4.28E-03 2.14E-01 1.27E-02 3.07E-03 8.68 E-02 5.88E-03 5.23E+01 e I-v 5.30E-02 4.02E+00 3.96E-02 9.1 9E 01 891 E-02 5.23E-02 4.21 E-01 9.70E-02 2.54E+02 5.62E-02 4.86E+00 2.23E-01 4.39E-02 1.13E+00 1.02E-01 5.53E-02 5.08E-01 7.29E-02 3.06E+02 ESF 5.31 E-06 3.39E-02 1.07E-03 4.46E-03 2.17E+00 7.21E-02 3.75E-03 3.41 E+00 1.08E-01 Total 5.14E-01 6.93E+01 2.12E+00 7.89E+01 L 5.74E-01 1.17E+01 l 4.76E+04 Note: Summary of proposed changes to 'Base Case" Is presented In Table I I E-FORM

NES-G-14.02 Effective Date:

041410 DESIGN ANALYSIS NO. QDC-OO-N-1117 REV: 0 PAGE NO.41 Table 4 PERC2 Outdput Versus RADTRAD : OPS Control Rm Thyroid Dose and Total Activity Released to Environment PERC2 RADTRAD PERC2 RADTRAD Results Comparison Thyroid Dose (rem) Thyroid 1-131 Activity 1-131 Act. RT/PERC2 RT/PERC2 Released (Ci)

Intake Infiltration Total Total Part Org Elem I Total Total Thy Dose Activty IMEMMEMEM I~~~~..

CNTr 1.051E-05 1.064E-01 1.0641E-01 1.061E-01 3.095E+02 1.907E+t03 4.629E+02 2.679E+03 2.674E.03 0.997 0.998 ESF Note 1 Note I 3.439E-02 3.390E-02 0.OOOE+00 1.290E+i03 4.171 E+04 4.300E+04 4.303E.04 0.986 1.001 MSL-vwl 2.612E+00 3.755E+01 4.016E.01 4.212E+01 2.633E+02 6.338E+02 2.680E+01 9.239E+02 9.41 3E+02 1.049 1.019 (100 Sofh)

Notes:

(1) Both the Intake and Infiltration contribution to the CR operator dose considered In a single PERC2 input file (2) 30 day Environmental Activity Release comparison.

(3) Successive reductions in RADTRAD's supplemental time step were taken until the results no longer appeared to depend on the choice of a time step value (-1/100th of a second). This also had the benefit of providing good agreement between PERC2 and the RADTRAD results.

(4) PERC2 validation was run for Part 2 only. The dose results for Part 2, as would be expected, come much closer to the design dose limits discussed in the Acceptance Criteria section than the doses calculated In Part 1. Additionally, all of the modeling in Part 2 Is the same as Part 1 with the exception of an additional MSL line. PERC2 validation of the Part 2 RADTRAD transport models results In validation of Part I results.

id E-FORM I

NES-G-14.02 Effective Date:

04114100 DESIGN ANALYSIS NO. QDC-0000-N-1117 REV: 0 PAGE NO.42 8.0

SUMMARY

AND CONCLUSIONS The *worst 2-hour periods dose at the EAB (4 hr to 6 hr period), the dose at the LPZ

'for the duration of the release", and the 30 day CR dose, for the both the Base Case (Case 1) and the Proposed Design Basis Case (Case 2), Is developed in-accordance with the guidance provided in RG 1.183. The calculated values represent the dose to the public and to the control room operator due to inhalation and submersion due to the radioactivity release following a LOCA at Quad Cities Power Station. Note that the dose estimates reported in the following Tables do not include the direct shine contribution due to external sources. This source is usually considered to be insignificant (due to distance) for the site boundary locations, but should be addressed for the control room.

Tables 5 and 6 provide the estimated dose from each of the three release pathways, i.e., containment and ESF leakage via the SBGTS, and containment leakage via the MSIVs, for the Base case and the Proposed Design Basis Case, respectively.

Table 5 Part I "Base Case" EAB, LPZ and Control Room Doses (TEDE)

LOCA Dose (rem) Reg. Limit (rem)

Location EAB (worst 2 hr period)

Containment Lkg via SBGTS 0.2 Containment Lkg via MSIVs 2 ESF Lkg via SBGTS Q0.01 Total 2.2 25 LPZ Containment Lkg via SBGTS 0.1 Containment Lkg via MSIVs 0.31 ESF Lkg via SBGTS 0,002 Total 0.4 25 Control Room:

Containment Lkg via SBGTS 0.003 Containment Lkg via MSIVs 0.84 ESF Lkg via SBGTS Neg Total 0.9 5 I E-FORM I

NES-G-14.02 Effective Date:

04/14/00 DESIGN ANALYSIS NO. QDC-0000-N-1117 REV: 0 PAGE NO.43 Table 6 Part 2 "Proposed Design Basis" EAB, LPZ and Control Room Doses (TEDE)

LOCA Location Dose (rem) Reg. Limit (rem)

EAB (worst 2 hr period)

Containment Lkg via SBGTS 0.3 Containment Lkg via MSIVs 6.2 ESF Lkg via SBGTS 6.072 Total 6.5 25 LPZ Containment Lkg via SBGTS 0.1 Containment Lkg via MSIVs 0.9 ESF Lkg via SBGTS 0.1 Total 1.1 25 Control Room:

Containment Lkg via SBGTS 0.004 Containment Lkg via MSIVs 3.87 ESF Lkg via SBGTS 0Q0Li Total 3.9 5 I E-FORM I

NES-G-14.02 Effective Date:

04/14100 DESIGN ANALYSIS NO. QDC-0000-N-1117 REV: 0 PAGE NO.44 Conclusions The site boundary and control room inhalation I submersion dose following a LOCA at Quad Cities Power Station has been analyzed utilizing Alternative Source Terms and regulatory guidance as provided in RG 1.183. The dose consequences for the Base Case model and the Proposed Design Basis Case are reported in Tables 5 and 6 and remain within the acceptance criteria specified in 10CFR50.67 and Regulatory Guide 1.183.

The Base Case is intended to represent current design basis. The operational relief currently being investigated is modeled as the Proposed Design Basis Case. The model differences between the Base Case and the Proposed Design Basis Case is outlined InTable 1. The operational relief currently being investigated as the proposed design basis is presented below:

• Increased allowable MSIV leakage from a total of 79.6 scfh @ 48 psig in all four lines to 100 scfh measured @ 48 psig in one line with a total of 250 scfh measured

@ 48 psig in all 4 MSLs

• increased allowable control room inleakage from 260 cfm to 600 cfm (includes 10 cfm for ingress/egress)

• increased allowable containment leakage from 1.0% volume per day to 3% volume per day

• reduced SBGTS charcoal iodine filter efficiency for organic and elemental iodine from 95% to 50%

• increased credit taken for the SBGTS HEPA filter efficiency from 95% to 99%

• reduced control room charcoal iodine filter efficiency for organic and elemental iodine from 99% to 95%.

• increased allowable ESF leakage from 10 gph to I gpm It is noted that to demonstrate compliance with the control room regulatory limits, the estimated dose to the control room operator should include the contribution due to direct shine from contained sources I cloud shine. Sufficient margin appears to exist between the calculated control room operator dose resulting from inhalation and submersion for the proposed design basis case (i.e.; 3.9 Rem TEDE), and the regulatory limits (i.e.; 5 I E-FORM I

NES-G-14.02 Effective Date:

_0414/00 DESIGN ANALYSIS NO. QDC-O000-N-1117 REV: 0 PAGE NO.45

.. _. - . ... ~~~~~~~~~~~~~~~~~~~~~~~~

Rem TEDE), to allow the inclusion of the referenced direct shine contribution without exceeding the acceptance criteria Listed below are some of the assumptions utilized in this analysis which may require additional analyticaVlicensing defense from Exelon as part of the licensing submittal:

• Current licensing basis of no reactor building bypass leakage

• Current licensing basis assumption that there is sufficient mixing In the reactor building to allow 50% mixing credit

• Current licensing basis that the XIQ values applicable for the control room intake is representative for control room inleakage.

• MSIV/containment leak rate will reduce to half it value after 24 hrs.

E-FORM

NES-G-14.02 Effective Date:

04/14100 DESIGN ANALYSIS NO. QDC-0000-N-1117 REV: 0 PAGE NO.46 APPENDIX A MSL leakage Study for Dresden and Quad Cities MSL Leakage versus post-LOCA 30-day Control Room TEDE Dose Objective The purpose of this Appendix is to perform a sensitivity study of MSL leakage vs 30 day control room TEDE dose based on the limiting station utilizing the 5t unit concept. This study will be used by EXELON to establish the proposed design change relative to MSIV leakage at both Dresden and Quad Cities.

Inthe study, the total MSL leakage Isthe variable subject to the constraint that the MSL leakage contribution to the control room dose is limited to approximately 4.5 Rem TEDE at the limiting station between Dresden and Quad Cities for a proposed control room inleakage of 600 cfm.

The two conditions of Interest are:

• Maximizing the total MSIV Leakage

• Maximum MSL leakage in a line specified as 100 scfh @48 psig for 24 hrs (then half the value for the duration of the accident) with the remaining leakage allocated to the worst configuration of the remaining lines.

Approach Computer program RADTRAD is used to calculate the control room operator dose versus MSL leakage using the activity transport model developed and described in Section 3 and presented in Figure 1 of the parent calculation. Two dose curves are generated, one for the 'worst' line (i.e., assuming single failure of the outboard MSIV In the shortest line), and one for the most limiting line. representative of the Oremaining" lines (assuming a break immediately downstream of the outboard MSIV).

The principal assumptions of this study as per Reference 4 are that the:

• the calculated control room operator dose at Dresden Station is more limiting than the control room dose at Quad Cities (by inspection of the CR dispersion factor (xJQs) and CR volumes) and dose calculated at either stations site boundary EAB and LPZ.

• maximum allowable leakage from any one line Is 100 sofh @48 psig.

• AST Source Term for both Dresden and Quad Cities is the same.

I E-FORM~~~]

NES-G-1 4.02 Effective Date:

04/14100 DESIGN ANALYSIS NO. QDC-OD0-N-1117 REV: 0 - PAGE NO.47

• rate of aerosol and elemental iodine deposition in the drywell and in the main steam lines is the same for both Dresden and Quad Cities following a LOCA.

• control room normal and emergency ventilation system design and operation is the same for both Dresden and Quad Cities and that total infiltration for either plant is fixed at 600 cf m.

• total drywell leakage for both Dresden and Quad Cities Is fixed at 3 volume fractions per day.

The control room operator TEDE dose is calculated for the "worst line assuming MSIV leakage rates of 100, 90, 80, 70, 60 and 50 scfh, and from the representative "remaining line" assuming MSIV leakage rates of 100, 90, 80, 60,40 and 20 scfh.

RADTRAD Input leakage rates Single Leakage MS line leakage rater" to void")

(scfh) (cfm) (cfm) 100 0.3907 2.9009 90 0.3517 2.94 80 0.3126 2.9791 70 0.2735 3.0181 60 0.2344 3.0572 50 0.1954 3.0963 40 0.1563 3.1354 20 0.07815 3.2135 Note: (1)After 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> the leakage values are reduced by half.

(2)The control room dose due to activity that leaks into the void (activities that would be released via other pathways) regions Isnot accounted for.

Ust of Computer Runs File Name Time and Date Stamp Run Description DRE Units 2 and 3 Part 2 Base Case with Proposed Design Changes with Variable MSL Leakage Rates RO040dreADla.out RADTRAD Version 3.02a run on 7/18/2002 at 8:40:54 core gap release i Cont Atm. L 100 scfh Worst MSL e Environ CR)

R0040dreA0lb.out RADTRAD Version 3.02a run on 711812002 at 9:06:51 E I-V release -) Cont. Aim. e i 100 scfh Worst MSL -e Environ MCR)

ROD40dreAO2a.out RADTRAD Version 3.02a run on 71181200B at 929.03 core gap release -i Cont. Atm. - 90 sch Worst I_____________

___________________________________ MSL 4 Environ (CR)

R0040dreA02b.out RADTRAD Version 3.02a run on 7/18/2002 at 9:44:48 El-V release 4 Cont Alm. 4 90 scfl Worst l E-FORM l

NES-G-14.02 Effective Date:

. . ~~~~~~~~~~~~04/114 DESIGN ANALYSIS NO. ODC-0000-N-1117 REV: 0O PAGE NO.49

_ ,~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

File Name Time and Date Stamp Run Description DRE Units 2 and 3 Part 2 lBase Case with Proposed Design Changes with Variable MSL Leakage Rates MSL 4 Environ (CR)

R0040dreA3a.out RADTRAD Version 3.02a run on 7/18t2002 at 10:43:14 core gap release 4 Cont Atm. 4 80 scfh Worst

_ _ _ __ _ _ _ _ __ _ _ _ iMSL 4 Envnron (CR)

R0040dreAO3b.out RADTRAD Version 3.02a run on 7/1812002 at 10:57:43 E I-V release 4 Cont Atm. 4 80 scfh Worst

______ __ : I/MSL 4 Environ (CR)

R004OdreAO4a.out RADTRAD Version 3.02a run on 7/22002 at 1721:25 core gap release 4 Cont. Atm. 4 70 scth Worst MSL 4 Environ (CR)

R004OdeA04b.out RADTRAD Version 3.02a run on 7/1912002 at 8:45:38 EI-V release 4 Cont. Atm. 4 70 scfh Worst MSL 4 Environ (CR)

R0040dreAO5a.out RADTRAD Version 3.02a run on 7J1812002 at 9:12:24 core gap release 4 Cont. Atm. 4 60 sclh Worst MSL 4 Environ (CR)

R0040dreA05b out RADTRAD Version 3.02a run on 7119/2002 at 9:58&02 E INV release 4 Cont. Atm. 4 60 scfh Worst MSL 4 Environ (CR)

R0040dreA06a.out RADTRAD Version 3.02a run on 7/1912002 at 11:10:30 core gap release 4 Cont. Atm. 4 50 scfh Worst MSL 4 Environ (CR)

R0040dreAD6b.out RADTRAD Version 3.02a run on 7/19/2002 at 11:27:13 E I-V release 4 Cont. Atm. 4 50 scfl Worst MSL 4 Environ (CR)

R004QdreA07a.out RADTRAD Version 3.02a run on 7119/2002 at 11:43:13 core gap release 4 Cont. Aim. 4 100 sch Worst MSL 4 Environ (CR)

R004QdreA07b.out RADTRAD Version 3.02a run on 7/1912002 at 11:57:53 E I-V release 4 Cont. Atm. 4 4 100 scfA Worst

_ _ _ _ _ _ MSL 4 Environ ICR)

R0040dreA08a.out RADTRAD Version 3.02a run on 71252002 at 1806:47 core gap release 4 Cont. Atm 4 90 sffh Worst UMSL 4 Environ (CR)

R0040dreAQ8b.out RADTRAD Version 3.02a run on 7/19/2002 at 12:50:54 E IV release 4 Cont. Atm. 4 90 scfh Worst

___ __ __ IMSL4 Envion (CR)

R004WdreA09a.out RADTRAD Version 3.02a run on 711912002 at 13:19:26 core gap release 4 Cont. Atm. 4 80 sch Worst

_ISL v Emiron (CR)

R0040dreAO9b.out RADTRAD Version 3.02a run on 7119002 at 13:35:49 El-V release 4 Cont. Atm. 4 80 s5d Worst MSL 4 Environ (CR)

R0040dreAl0a.out RADTRAD Version 3.02a run on 7/1912002 at 14:01:33 core gap release 4 Cont. Atrn. 4 6D scfh Worst IMSL4 Environ (CR)

RO04OdreAlOb.out RADTRAD Version 3.02a run on 7/19002 at 14:17:38 EI-N release 4 Cont. Atm. 4 60 scfh Worst MSL 4 Environ (CR)

R0040dreAl la.out RADTRAD Version 3.02a run on 7/19t2002 at 14:41:06 core gap release 4 Cont. Atm. 4 40 sclh Worst IMSL 4 Environ (CR)

R0040dreAl lb.out RADTRAD Version 3.02a run on 7/19/2002 at 1520:10 EI-V release 4 Cont. Atm. 4 40 scfh Worst MSL 4 Environ CR)

R0040dreAl2a.out RADTRAD Version 3.02a run on 71Z!12002 at 9:01:49 core gap release 4 Cont Atm. 4 20 sdh Worst MSL 4 Environ (CR)

R0040dreAl2b.out RADTRAD Version 3.02a run on 7/22/2002 at 9:37:40 EIV release 4) Cont. Alm. 4 20 cfh Worst

________ ______________________ MSL4 Environ (CR)

IEMFORM

NES-G-1 4.02 Effective Date:

04/14/00 DESIGN ANALYSIS NO. QDC-0000-N-1117 REV: 0 PAGE NO.49 Results CR TEDE Dose from "worst" and aremainingr MS line Worst MS Dose from Dose from Single MS Dose from Dose from Une Lkg. gap Rel. EIV Rel. TEDE RL Lkg. gap Hel. EIV Rel. TEDE (scfh) (rem) (rem) (rem) (sE~h) (rem) (rem) (rm 100 0.35856 2.47490 2.83346 100 0.18518 1.22130 1.40648 90 0.26852 1.83590 2.10442 90 0.14255 0.92691 1.06946 80 0.19459 1.31430 1.50889 80 0.10753 0.68778 0.79531 70 0.13596 0.90385 1.03981 60 0.05710 0.35106 0.40816 60 0.09126 0.59425 0.68551 40 0.02633 0.15471 0.18104 50 0.05848 0.37085 0.42933 20 0.00822 0.04631 0.05453 Adding a (0,0) point to the"worst" and "remaining" MS lines results, the results were then curvefitted and plotted in Figures Al and A2. Examination of the input data and the shape of the resulting curves provided insight into selecting the worst configurations for dose consequence analyses. The highest consequence always resulted from the case where the maximum allowable line flow was used with any remainder being allocated to the last line. For example, In maximizing the dose for a MSIV total leakage of 280 scfh @ 48 psig with a maximum allowable leakage of 100 scfh @ 48 psig, the highest dose resulted from the selection of the "worst" line being at a 100 scfh @

48 psig and the "remaining' lines being at 100 scfh @ 48 psig and 80 scfh @ 48 psig rather than the uremainingu lines being 2 - 90 scfh @ 48 psig or 3 - 60 scfh @ 48 psig configurations or another flow combination. This insight provides simplification in the later analysis where MSIV leakage flows are combined to calculate a MSIV Leakage isodose curve for the control room.

The curvefits in Figures Al and A2 resulted in 5' order polynomial expressions with the following coefficients:

I E-FORM I

NES-G-1 4.02 Effective Date:

04114/00 DESIGN ANALYSIS NO. QDC-ODOO-N-1117 REV: 0 PAGE NO.50 Y = axA5+bsxA4+4cxA3+d*xA2+e~x+f Worst Line Remaining iine a -1.42363446836328E-10 -6.87005376270971 E-1 1 b 3.35512798367489E-08 2.17755715056959E-08 c 1.95455713990609E-08 -1.33008461944934E-06 d 7.18060834270149E.05 1.17061334651532E-04 e 1.64353990933016E-03 7.54012651713977E-04 f -4.87066944643041 E-08 2.20814405364869E-07 A comparison of fit was then made to ensure that the derived expression adequately represented the data. As demonstrated below, the curvefit closely reproduced the inputted data.

"Worst" Line "Remaining' Line Flow Input Calc. Flow Input Calc.

DIfference Difference (Scfh e Dose Dose (scfh e Dose Dose (Rem) (Rem) 48 psig) (rem) (rem) 48 psig) (rem) (rem) 0 0 -4.87E-08 4.87E-08 0 0 2.21 E-07 -2.21 E-07 50 0.42933 0.429342 -1.23E-05 20 0.05453 0.054529 1.42E-06 60 0.68551 0.685459 5.11E-05 40 0.18104 0.181044 -3.97E-06 70 1.03981 1.039898 -8.77E-05 60 0.40816 0.408153 6.62E-06 80 1.50889 1.508813 7.67E-05 80 0.79531 0.79532 -9.94E-06 90 2.10442 2.104454 -3.41 E-05 90 1.06946 1.069452 8.OBE-06 100 2.83346 2.833454 6.14E-06 100 1.40648 1.406482 -1.99E-06 From the curvefits and the RADTRAD results, it was possible to derive a control room MSIV leakage isodose curve. Selecting a control room dose of 4.5 Rem due to MSIV Leakage, the following MSIV leakage combinations were derived.

E-FORM I

NES-G-1 4.02 Effective Date:

04/14100 IDESIGN ANALYSIS NO. QDC-0000-N-1117 REV: 0 PAGE NO.51 Une 1 2 3 4 "Remalning" "Remaining" "Remalnlng" Maximum MSIV Maximum Flow "Worst" Line Line # I Une #2 Line # 3 L.eakcage Max imunFo Flow -

perhL4 sine sh @48 psig Flow- Flow - Flow - Allowable (seth e 48 psig) (Dose - Rem) rcfh e 48 pslg scfh 0 48 pslg sfh e 48 pslg (seth 0 48 psig)

(Dose - Rem) (Dose - Rem)

~~100 100 48.297 100 100 (2.83346) (1.40648) (0260061) 0 248.297 99 ~~99 99 57.738 0 255.738 (2.75451) (1.36980) (0.375690) 97.5 68.289 0 263.290 (2.63860) (1.31604) (0.545358) 95 80.920 0 270.921 (2.45214) (1.22977) (0.818094) 92.5 90.290 92.5 92.5 0 275.290 (2.27409) (1.14760) (1.07831) 92 92 91.912 (1.12886) 0 275.912 (2.23949) (1.13165) 91.97891 91.97891 91.97891 91.97891 0 275.937 91.97891 (2.23804) (1.13098) (1.13098) 91.975 91.975 0.6252750 91.975 91.975 91.975 (2.23777) (1.13086) (1.13086) (5.17117E-04) 276.550 91.3 91.3 91.3 91.3 26.841 300.741 (2.19162) (1.10959) (1.10959) (8.9201 9E-02) 3074 91 91 33.078 91 91 (1.28233E-01) 306.078 (2.17130) (1.10023) (1.10023) 90.5 90.5 41.363 90.5 90.5 (1.08476) (1.92764E-01) 312.863 (1.08476) 90.5 90.5 47.979 (2.10442) (1.06946) (1.06946) (2.56668E-01) 317.979 88.75 88.75 88.75 88.75 60.359 326.609 (2.02278) (1.03186) (1.03186) (4.13497E-01) 32.0 87.5 87.5 87.5 87.5 69.4123391 (1.94319) (0.99525) (0.99525) (5.66317E-01) 331.912 86.25 86.25 76.592 86.25 86.25 (1.86568) (0.95959) (0.95959) (7.15136E-01) 335.342 85 8 85 85 82.566 7 (1.79023) (0.92489) (0.92489) (8.5999OE-01) 3 6 84.53962 84.53962 84.53962 84.53962 84.53962 338.158 84.53962 (1.76296) (0.91235) (0.91235) (9.12348E-01) 3815 I ORM

NES-G-1 4.02 Effective Date:

04/14/00 DESIGN ANALYSIS NO. ODC-0000-N-1117 REV: 0 - PAGE NO.52 Plotting these results yielded isodose curves for 3 and 4 MSIV Lines leaking and the combination curve (Figures A3 - A5). Using this methodology and the curves derived for Figures Al & A2, other isodose curves for the MSIV Leakage contribution to control room dose follow a LOCA can be derived.

I E-FORM

NES-G-14.02 Effective Date:

04114100 DESIGN ANALYSIS NO. QDC-O000-N-1117 REV: 0 PAGE NO.53 Figure Al Cordrol Room Dose Due to MSIV Leakage (Worst Une) 3.0 SI

• 2.5 Cn M

-J

> 2.0 U

.5

.C=11.5 U)

C

• 1.0 T0 0

E 0

0 r 0.5 a

0.

0.0 4-0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 MSIV Leakage Rate for Worst Line (scfm @ 49 psig)

II E-FORM II

NES-G-14.02 Effective Date:

04=4(0 DESIGN ANALYSIS NO. QDC-0000-N-1117 REV: 0 PAGE NO.54 Figure A2 Control Room Dose Due to MSIV Leakage (Representative Une) 1.6 S

011 0 12o Cn p0.

a 8 0.6

'4 E

a 0.4 0

I0.

0 CE .2 0.0 6-0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 MSIV Leakage Rate for Representative Line (scfn @ 48 psig)

HE-FORMN

NES-G-1 4.02 Effective Date:

0411410 DESIGN ANALYSIS NO. ODC-NOG-N-1 II 7 REV: 0 PAGE NO. .55 Mj Figure A3 Maximum MSIV Leakage per Line vs. Total MSIV Leakage for 3 Lines 280.0 275.0 CD

0. 270.0 co 0 265.0 AU 0

to 0 260.0 I- 255.0 250.0 § 245.0 _J 91.0 92.0 93.0 94.0 95.0 98.0 97.0 98.0 99.0 100.0 MSIV Maximum Leakage Rate per Line (scfn @48 psig)

NES-G-14.02 Effective Date:

04/14100 DESIGN ANALYSIS NO. QDC-OO00-N-1117 REV: 0 PAGE NO.56 Figure A4 Maximum MSIV Leakage per Line vs. Total MSIV Leakage for 4 Lines 340.0 330.0

-0

&0 a-0 320.0 qt a

0 0s I"

(U 300.0 0

2

-j U,

2 290.0 a-02 280.0 -

270.0 L 84.0 85.0 86.0 87.0 88.0 89.0 90.0 91.0 92.0 MSIV Maximum Leakage Rate per Line (scfh 0 48 psig)

NES-G-14.02 Effective Date:

04/14X0 DESIGN ANALYSIS NO. ODC-0000-N-1117 REV: 0 PAGE NO. .57 Figure A5 Total MSIV Leakage vs. Maximum Leakage per Line Control Room Dose Constant at 4.5 Rem 340 -

.a%

0. 330 -

320-q.C 310-0 300 -

0, co 290 -

280 -

0) 270 -

-I 260 -

4.e 250 -

01 240 ... ...

84 86 88 90 92 94 96 98 100 Maximum Leakage per Line (scth @ 48 pslg) l E-FORM  !

NES-G-1 4.02 Effective Date:

04/14/00 DESIGN ANALYSIS NO. QDC-0OOD-N-1117 REV: 0 PAGE NO.58 LIST OF ATTACHMENTS Attachment A TODI QDC-02-019, Rev 1 Including Attachment 1 Attachment B CD ROM of Computer Output Final Page Page 58 of 58 I PM I~

G~~~~c-ttt>9-X\\8~~~~~~~~~~~~~~~~ 4  ! --J2t4 f'

4 I ~~~~EXELON TRANSMITT'AL OF DESIGN INFORIMATIONI SAFETY-RELATED Originating Organization TODI No. ODC-02-019 Revision I

_NON-SAFET Y-RELATED X-Exclon_

_RtEGULATORY RELATED -Other(specify)..

Station OadCities Unit s)]12) Page of 2 System Designation: (OOO__

To S. FErauson - Stone and Webster

Subject:

Ouad Cities Station Concurrence with the Desimn Inputs as established for Alternate Source Tern (AST) LOCA Analysis.

M. Uhrich Preparer / Olwps S' Date R. Hevn Approver tAual>l ofi£ Approver's qgnature l (, vg Date Status of Information: JX Approved for Use -Unverified Method and Schedule of Verification for Unverified TODis: N/A Description of Information:

Transmit Quad Cities Station concurrence with the design inputs for the AST LOCA Analysis. These inputs were derived based upon the combined efforts of Quad Cities Station, Dresden Station, and Corporate Engineering Subject Matter Expert. The attachment contains a finalized list of these design inputs. Information was retrieved from controlled sources as listed in the attachment.

Purpose of Issuance:

Transmit a finalized list of design inputs (Revision I) Further refine the volume and concentration of SBLC System, revise the % cable inside and outside of conduit in the drywell, and minor changes in the comments section.

Limitations:

None Source Documents: Various - The referenced source documents have been listed with each value in the attachment.

Distribution: J. Gaudet, G. Lahti, B. Porter, D. Oakely.

41--  % I ts, Cj:N-"Z- (QLV 1,- OZZ)Z) - N - \ I \ +' plc PARAMETER LIST FOR OFFSITE AND CONTROL ROOM DOSE ANALYSIS - QUAD CITIES POWER STATION LOC LURNAVETIVE OUCETER~MS item Raere VaeComments

1. Reactor Core Power Level G&NE-A22-00103 3016 MWt Includes 2% margin for conservatism 01, Rev.0 iaw RG 1.49, Rev 1; i.e., 2957 MWt

• 1.02 = 3016 MWt Reg. Guide 1.183, Rev 0

2. Design Basis Core Activity (Cudes) GE-NE-A22.'0010364- Values in Appendix D of Isotopes utilized in the analysis will be 01, Rev.0 Reference (CiIMWt) times 3016 limited to the 60 isotopes that form the MWt. Values used are those with standard libraryfinput in Computer Code 1600 EFPD bumup RADTRAD. The referenced computer code is NRC sponsored and is intended for use in AST applications.

TODI-02-019 Rev 1 Attachment I Page Al of A23

Pt 3 t -LH Cj..* GkDc ZTzcqz- M- \\\ , zl L~V~A K PARAMETER LIST FOR OFFSITE AND CONTROL ROOM DOSE ANALYSIS - QUAD CITIES POWER STATION LOCA ALTERNATIVE SOURCETES tem Refnce Vale Comments

3. Activity Release Paths Containment Leakage Per reference, current plant design does ComEd letter to NRC, not allow bypass of the SBGTS.

"Revised Control Room Release from fuel to drywell; leaked B Yrn:

Radiological to reactor building; released to Assessment", May 19, environ via SBGTS Containment LCakage via SBGTS -

. 1997 Elevated Chimney MSIV Leakage MSIV Leakage - steam line tunnel ESF Leakage via SBGTS - Elevated Release from fuel to drywell; leaked Chimney to the environ via MSIV's

. ~~~~~~~~~~~ESP leakarve Release from fuel to suppression pool; released to reactor building due to equipment leakage; released to environ via SBGTS Containment Puree Release to Relieve Pressure or to Reduce Hydroeen Concentration None TODI-2-019 Rev 1 Attachment I Page A2 of A23

CAc

• OQ,04L- 0000- N3 - \\\"4 I &O N 3 L\- i -v-i PARAMETER LIST FOR OFFSITE AND CONTROL ROOM DOSE ANALYSIS - QUAD CITIES POWER STATION LCA - ALTERNATIVE SOURCE TERMS Itm reVae a Commenst

4. Elements in each Radionuclide Group released Reg. Guide 1.183, Rev 0 Noble gases: Xe, Kr Note: RADTRAD default libraries into Containment following a LOCA Halogens: 1, Br contain a maximum of 60 isotopes with associated nuclear data libraries Alkali Metals: Cs, Rb Tellurium Grp: Te, Sb, Se Ba. Sr: Ba. Sr Noble Metals: Ru, Rh, Pd. Mo, Tc, Co Cerium Grp : Ce, Pu, Np Lanthanides: La, Zr, Nd. Eu, Nb, Pm, Pr, Sm. Y. Cm, Am

5. Core Inventory Fraction Release into the Reg. Guide 1.183, Rev 0 Noble gases: 0.05 All fission products released from the Drywell Atmosphere of each Radionuclide group Halogens : 0.05 fuel are instantaneously and during Gap Release Phase homogeneously mixed in the Drywell Alkali Metals: 0.05 atmosphere at the time of release from the core.

License Condition The peak bumup of GE14 fuel is Note that these release fractions are DPR-30 3IT limited to 62.000 MWDIMTU. based on LWR fuel with a peak burnup DPR-29 3.U up to 62,000 MWDIMTU.

TODI-02-019 Rev 1 Attachment I Page A3 of A23

• j-

-%%. ' -\ \Li K ft SoJ7 I 2.Li PARAMETER LIST FOR OFFSITE AND CONTROL ROOM DOSE ANALYSIS - QUAD CITIES POWER STATION LQCA - ALTERNATIVE SOURC&TJRMS

.~~~~~~~~~~-,T-M item__ Refeece Value Cemments

6. Core Inventory Fraction Release into the Reg. Guide 1.183, Rev 0 Noble gases: 0.95 All fission products released from the Drywell Atmosphere of each Radionuclide group Halogens: 0.25 fuel are instantaneously and during Early In-Vessel Release Phase homogeneously mixed in the drywell Alkali Metals: 0.20 atmosphere at the time of release from Tellurium Grp: 0o0S the core Ba, Sr: 0.02 Note that these release fractions are based on LWR fuel with a peak burnup Noble Metals: 0.0025 up to 62.000 MWD/MTU.

Cerium Grp: 0.0005 Lanthanides 0.0002 License Condition The peak burnup of 0E14 fuel is DPR-30 3.T limited to 62,000 MWD/MTU DPR-29 3.U

7. Core Inventory Fraction Release into the Reg. Guide 1.183, Rev 0 Noble gases: 0.00 With the exception of noble gases, all suppression pool of each Radionuclide group Halogens: 0.05 fission products released from the fuel during Gap Release Phase are instantaneously and homogeneously Alkali Metals: 0.05 mixed in the suppression pool at the time of release from the core.

TODI-02-019 Rev 1 Attachment I Page A4 of A23

CALXC 0'z-

-l2 0 C c)- t'  %\-  % I- V-'4 PARAMETER LIST FOR OFFSITE AND CONTROL ROOM DOSE ANALYSIS - QUAD CITIES POWER STATION LOCA - ALTERNATIVE SOURCE TERMS Item . RAft c Value Comments

8. Core Inventory Fraction Release into the Reg. Guide 1.183, Rev 0 Noble gases: 0.00 With the exception of noble gases, all suppression pool of each Radionuclide group Halogens : 0.25 fission products released from the fuel during Early In-Vessel Release Phase are instantaneously and homogeneously Alkali Metals: 0.20 mixed in the suppression pool at the time Tellurium Grp: 0.05 of release from the core.

Ba, Sr: 0.02 Noble Metals: 0.0025 Cerium Grp 0.0005 Lanthanides :0.0002

9. Core Inventory Release Timing - Gap Release Reg. Guide 1.183, Rev 0 Onset: 2 min Phase Duration : 0.5 hrs

10. Core Inventory Release Timing - Early In- Reg. Guide 1.183, Rev 0 Onset: 0.5 hrs after onset of Gap Vessel Release Phase Duration: 1.5 hrs I 1. Iodine Form of activity released to drywell Reg. Guide 1.183, Rev 0 4.85% Elemental atmosphere from melted and failed fuel 95% Particulate 0.15% Organic TODI-02-019 Rev I Attachment 1 Page A5 of A23

COL - Q0 C-- ; cozb - k'a- \\ k 1z ?I -+ i-4 PARAMETER LIST FOR OFFFSITE AND CONTROL ROOM DOSE ANALYSIS - QUAD CITIES POWER STATION LQCA - ALTERNATIVE SOURCE TERMS ite. Rdefeene. Value Comments

12. Suppression Pool Scrubbing Credit Reg. Guide 1.183, RO Not Credited Per RG 1.183, suppression pool scrubbing is generally not credited. Due to the delay in release of the fission products, it can no longer be assumed that the fission products will be immediately directed to the suppression pool as part of the initial pressure transient For Mark I BWRs, it is expected that most of the fuel release will remain in the drywell and leak directly out into the reactor building without suppression pool scrubbing.

Portions of the fuel release may be scrubbed, but a technical defense has to be provided based on mass flow rate into suppression pool vs time, pool temperature vs time, venting depth, etc.

Therefore, the analysis cannot use a DF of 5 as suggested in SRP6.5.5.1I.1 and used in Calc QDC-9400-M-0363, RI.

For purposes of this analysis no credit will be taken for suppression pool scrubbing.

TODI-02-019 Rev I Attachment I Page A6 of A23

cov.*La vz C,- (Zozst, Q - M- 1\ %-+ I ea sC 2x PARAMETER LIST FOR OFFSITE AND CONTROL ROOM DOSE ANALYSIS - QUAD CITIES POWER STATION LOCA - ALTERNATIVE SOURCE TERMS tet7 Refewece Value Comments RG 1.183

13. Elemental iodine deposition/plateout removal SRP 6.5.2 RADTRAD requires user specified coefficients in Containment based on: removal lambdas. Per RG 1.183, the iodine removal coefficients will be calculated using SRP 6.5.2, Rev 2 methodology. Torus area / volume is not considered.

Dvywell surfaces are assumed to be wetted during the early stages of the event during which credit is taken for elemental iodine removal. Per RG 1.183, credit for elemental iodine removal is taken until a DF of 200 is reached.

- Surface area in dcywell OPL4A, transmitted by Surface area: 32,430 sq ft Per OPLAA. the listed surface area is TODI DGOO-000830, that associated with the steel area of the 7/11/00. drywell shell surface and the LOCA vent pipes.

- Drywell Free volume QDC-9400-M-0348. RI Drywell Volume: 1.58E5 cu ft TODI-02-019 Rev I Attachment I Page A7 of A23

cou4 k,- \\\4 j f--Q ?I "AI PARAMETER LIST FOR OFFSITE AND CONTROL ROOM DOSE ANALYSIS - QUAD CITIES POWER STATION LDCA - ALTERNATIVE SOURCE TERMS Rtem Reference Yalte Comment

14. Particulate aerosols deposition/plateout RG 1.183, RO To be calculated by S&W using Per RG 1.183, the 10% percentile (most removal in Containment based on: NUREG/CR-6189 equations for the Power's model in conservative) values will be used for the NUREG/CR-6189 and input evaluation.

directly into RADTRAD as natural deposition time dependent lambdas

15. Credit for fission product removal by sprays NIA None

16. Long Term Suppression Pool pH (taking into pH of 7 . Credit will be taken for sodium consideration acid production due to radiolytic To be confirmed by pentaborate in the Standby Liquid cable degradation). S&W in a separate Control System. This system will be analysis activated manually via the EOP's.

TODI-02-019 Rev I Attachment 1 Page A8 of A23

el I0 ?_4 CA4 aw-)(_- mc " - \ \-A J \

PARAMETER LIST FOR OF`FSITE AND CONTROL ROOM DOSE ANALYSIS - QUAD CITIES POWER STATION LQOA - ALTERNATIVE SOURCE TERMS Item . Referece Valie comment.

17a. MSL Leak Rate: Base Case Case I Base Case" The following value is obtained from Calc. QDC-9400-M.0363, Rev. 1.

• 46 scfh for four MSLs @ 25 Tech. Sipec 3.6.1.3 psig (test pressure) *79.6 scfh @ design pressure for 4 SR 3.6.1.3.10. MSLs, i.e. 0.0017 volume fractions per day based on a containment volume that includes drywell and QDC-9400-M-0363,

• 79.6 scih @ 48 psig total from torus)

Rev. 1. all four ( 4) MSLs QDC-9400-M-0348, RI Note that per QDC-9400-M-0348, RI, QCTP 0130-01 Revision the conversion factor to address leakage

14. Analysis will assume 100% at containment design pressure from leakage for the duration of the tested pressure is 1.73 (1.603 EPU, See event from one (1) MSL Below).

It is recognized that under EPU conditions the revised value for drywell pressure is 43.9 psig. 48 psig was used.

This should be discussed in the design input of the calculation.

17b. MSL Leak Rate: Proposed Case T Case 2 'Prosede CSe paxaelntor bselec parameters basedo n'tudyVlakg Note thatCper QC. M348 RI, the conversion factor to address leakage at containment design pressure from described below: tested pressure of 25 psig to design TODI-02-019 Rev I Attachment 1 Page A9 of A23

Ar- t% kI A.L C-Vl 0 cj-tr - M - al\\ \ 6%.~-z PARAMETER LIST FOR OFFSITE AND CONTROL ROOM DOSE ANALYSIS - QUAD CITIES POWER STATION LOCA - ALTERNATIVE SOURCE TERMS item Rferenee Vairue Commmnts Study Details . pressure of 48 psig is 1.73 (1.603 EPU.

Total MSL leakage is a variable See Below).

subject to the constraint that the MSL Leakage total contribution to Per RG 1.183, the MSL leakage may be CR Dose is limited to reduced to a value not less than 50% at approximately 4.5 Rem at the T= 24 hrs if supported by plant analyses.

limiting station between Dresden Exelon is aware that plant specific and Quad Cities for a proposed CR analysis may be needed to support the inleakage of 600 scfm. utilization of this assumption.

Graphs depicting MSL Flow vs CR Dose There are two (2) conditions of Contribution for the Worst Line and the interest: Representative Line provided for a

• Maximizing total MS1V proposed CR inleakage of 600 scftn are Leakage generated as a result of the 2 study

• Worst MSL leakage specified as conditions. Based on review of the 100 scfh @ 48 psig for 24 graphs Exelon will select the allowable hours (then half value for the MSL leak rate for the Proposed Case.

duration of the accident) with the remaining leakage allocated It is recognized that under EPU to the worst configuration of conditions the revised value for drywell remaining lines. pressure is 43.9 psig. 48 psig was used.

This should be discussed in the design input of the calculation.

TODI-2-019 Rev 1 Attachment I Page AIO of A23

Cak Graft- ksc>%-

% \\\-4 f1t3 e-5 7 J7-PARAMETER LIST FOR OFFSITE AND CONTROL ROOM DOSE ANALYSIS - QUAD CITIES POWER STATION LOCA - ALTERNATIVE SOURCE TERM item~i Refere l Value Comments 18a. Leakage Rate from Containment: Base Case Case I "Base Case" All leakage estimates provided in "volume fractions per day" are based on Tech. Spec. B 3.6.1.2 Total Containment leakage - 0.01 drywell volume only per guidance in RG volume fractions per day at design 1.183 pressure of 48 psig:

Note that the volume fractions released QDC-9400-M-0363, ^ Leakage through MSL - via the MSLs and reactor building used Rev 1. 0.00283 volume fractions per in QDC-9400M-0363, Rev are 0.0017 day at 48 psig (see item 17a for basis of MSL leakrate in volume fractions per day) and 0.0083 respectively. Since per RG 1.183, the Leakage into reactor building - AST methodology assumes that the 0.00717 volume fractions per activity release occurs only in the day (i.e. 0.01-0.00283) at 48 Drywell volume, (whereas, QDC-9400-psig M-0363, which is based on TIO methodology takes credit for dilution in "Base Case" analysis will assume the whole containment), the volume 100% leakage for the duration of fractions are adjusted to reflect the the event. volume adjustment. The containment volume is 2.69E5 cu ft whereas the drywell volume is 1.58E5 cu ft.

TODI-02-019 Rev I Attachment I Page Al I of A23

CAC-Im g--Z ?I I-& 7-Lf

-J PARAMETER LIST FOR OFFFSITE AND CONTROL ROOM DOSE ANALYSIS - QUAD CITIES POWER STATION a-Item Referee Vale Comments 8b. Leakage Rate from Containment: Proposed Asumed Case 2 "Proposed Case" See Item I7b for basis of MSL leakage Case Total leakage - 0.03 volume in volume fractions per day.

fractions per day at 48 psig. All leakage estimates provided in "volume fractions per day" are based on Analysis will assume that the drywell volume per guidance in RG leakage is reduced to 50%b at T=24 1.183 hours0.00212 days <br />0.0508 hours <br />3.025794e-4 weeks <br />6.96315e-5 months <br /> Per RG reduced 1.183, the to containment leakage a value not less than Containment leakage determined as may be the difference between total leakage 50% at T= 24 hrs if supported by plant ndethermaimum Mhe leakage analyses. Exelon is aware that plant determined from the 2 study specific analysis may be needed to conditions identified in item I 7b support the utilization of this assumption.

19. Primary Containment Free Volume

• Drywell plus Suppression Chamber Free Air

• QDC-9400M0363, ^ 2.69E+05 ft Volume Rev I

• Drywell only

• QDC-9400-M-

• 1.58E+05 ft 0348, RI TODI-02-019 Rev I Attachment 1 Page A12 of A23

SQ-4c- tzrzr"-tA- \\\-+j 1"t4 ~~W~4 *%

f a%"1 7~-4 PARAMETER LIST FOR OFFsrT AND CONTROL ROOM DOSE ANALYSIS - QUAD CITIES POWER STATION LOCA - ALTERNATIVE SOURCE TERMS item c Redu eafwe Common

20. Reactor Building Drawdown Time following a OPL-4A (PDLB Current Design Basis: No delay; The design of the reactor building and LOCA (prior to be being exhausted via SBOTS) Version), 8/1/00 Drawdown time is zero the SBGT System is to maintain the taking into consideration loss of power and worst reactor building at slight negative case single failure. (i.e., time period after LOCA pressure under normal and accident before the Reactor building will achieve -0.25 in conditions. This precludes exfiltration wg) from the building. During previous secondary containment leak rate surveillance, it has been observed that the reactor building pressure is maintained substantially negative (>0.2 in wc vacuum)

21. Standby Gas Treatment System Flow QDC-9400-M-0363, 4000 cfm +/-10% Per QDC-9400-M-0363, Rev 1, the Rev I SOTS is safety related and with this flow can maintain the reactor building at -

0.25 inch w.g. pressure;

22. Reactor Building Free Volume 4.7E+06 ft3 QDC-9400-M-0363, Rev.1I TODI-02-019 Rev I Attachment 1 Page A13 of A23

-- av I&  ?  %% I ZAf i (Z'(Z W~~~J N PARAMETER LIST FOR OFFSITE AND CONTROL ROOM DOSE ANALYSIS - QUAD CITiES POWER STATION L0CA - ALTERNATIVE SOURCE TERMS Item Reference value Comments

23. Fraction of Reactor Building Volume Available for Mixing QDC-9400.M-0363, 0.5 50% is the maximum allowed by RG Rev.1 1.183.

Caic. QDC-9400-M-0363 assumes 50%

mixing in the reactor building Exelon recognizes that this assumption may need some additional defense in the form of an analysis.

24. Fraction / duration of containment leakage that QDC-9400-M-0363, Need not be analyzed Per Parameter Item 3, current plant bypasses the reactor building SGTS due to high Rev.1 design does not allow bypass of SGTS winds Per QDC-9400-M-0363, RI, previous analyses done for Quad Cities Station have indicated that doses developed using calm weather conditions are higher than doses calculated using high wind conditions and associated bypass leakage.

TODI-02-019 Rev 1 Attachment 1 Page A14 of A23

%S)C - tozs cz. Cj- tA - \ \ \ ) L C") A-*,A-3--7 t,  % ! 1~Z..L PARAMETER LIST FOR OFESITE AND CONTROL ROOM DOSE ANALYSIS - QUAD CITIES POWER STATION LOCA - ALTERNATIVE SOURCE TERMS item. Reference Vabe Commeris 25a. SB3GTS Filter Efficiency Base Case QD940M M63 Case I "Base Case" Rev.1I HEPA:

Particulate aerosol: 95%

Cbarcoal ilter Elemental iodine: 95%

Organic iodine: 95%

25b. SBGTS Filter Efficiency Proposed Case ACase 2 "Pronosed Value" HEPA:

Particulate aerosol: 99%

Charcoal Filter Elemental iodine: 50%

Organic iodine: 50%

TODI-02-019 Rev I Attachment I Page A1S of A23

AL csh Qk lb C- - - tA - \\ \--I- , cc k ?C 1-  ?-'4 PARAMETER LIST FOR OFFSITE AND CONTROL ROOM DOSE ANALYSIS - QUAD CITIES POWER STATION LOCA ALTERNATE SOURCE By it.m Reference Value Comments

26. MSIV Leakage Deposition and Holdup Credit. Reg. Guide 1.183: To be developed by S&W Since holdup is allowed only in system To be developed based on the following input: that can stand SSE, deposition / plateout will be credited only in piping upstream

• Data on MSLs

• QDC-3000-M- 1064,

• As per Reference of outboard MSIVs

- Internal surface of shortest MS line from Rev 0 reactor vessel nozzle to outboard MSIV (i.e.

• QDC-3000 M-1065, Since vapor deposition is reduced at the seismic portion) Rev 0 higher temperatures, the temperature in

- Volume of above piping the MSLs will be assumed to be the

- Number of bends (including degree of bends) higher of that predicted for the MSLs vs drywell.

• Post LOCA containment pressure vs time for

• GE-NE-A22-00103-

• Figure 3-8 EPU 08-01, Rev 1 Pressure in MSL will be assumed to be same as in-containment pressure.

• Post LOCA containment temperature vs time

• GE letter GE-DQC-

• Figure 1 for EPU EPU-3861DRF A22- Post LOCA containment temperature &

000103-00, Nov pressure data beyond the times identified 20,2000 in the figures will be conservatively assumed to remain unchanged after the

• MS Pipe temperature vs. time

• SAIC Report by

• To be developed by S&W last recorded time noted in the figures

.lECline, August 20, 1990. Post LOCA temperatures in the MS pipe will be developed using SAIC report,

• MS line Flow: max. MSIV leakage in I line

• As noted below

• As noted below "MSIV Leakage for iodine Transport Case I Base Case QDC-9400-M-0363, 79.6 scfh @48 psig (Case 1) Analyses", JECline, August 20, 1990, RI NRC Contract NRC-03-87-029, Task 75 Case 2 Proposed Case Assumed TBD scfh @48 psig from study conditions identified in

__________ _________ itemitem 17b (Case 2)

TODI-02-019 Rev I Attachment I Page A16 of A23

-,IC-,

. ccsc " C. - o otmb - VA - \ \\-- &AlV- %tI8qtL4 PARAMETER LIST FYOR OFFSITE AND CONTROL ROOM DOSE ANALYSIS - QUAD CITIES POWER STATION LQCA - ALTERNATIVE SOURCETMS Item ReereWe Value Comments

27. Suppression Pool liquid Volume used to QDC-9400-M-0363, 110,000 fte assess ESF leakage Rev.1 28a. ESF Leakage Rate: Base Case PaleMv QDC-9400M0363, 20 gall hr based on twice the typical industry leak rate of 10 gph.

28b. ESF Leakage Rate: Proposed Case Assm2dTypical Industry Value is I gpm.

Case 2 Assessment uses 2 x allowable per RG 2gpm 1.183

29. Fraction of ESF leakage that becomes airborne QDC-9400-M-0363, Iodine - 0.1 Calc. QDC-9400-M-0363 refers to Rev.1 Particulates - retained in the liquid USFAR that the Pool Condensation phase Stability Limit is 205 "F (< 212 "P.).

Per RG 1.183, if temperature of fluid is less than 212 OF. fraction airborne can be assumed to be 0.1 TODI-02-019 Rev I Attachment 1 Page A17 of A23

AŽ-s6<9-Nzo -  %\\ ~Vtlv\~3r~ A. ?Vo4 vt-'I PARAMETER LIST FOR OFFSITE AND CONTROL ROOM DOSE ANALYSIS - QUAD CITIES POWER STATION LOCA -ALTERNATIVESOURCETRMS

__~ ~ Ie ________.________-______

item l Reference Value Comments

30. Iodine Form of Activity Released from ESF Reg. Guide l.183, Rev 0 97% Elemental leakage to the Environment 3%organic 31 .Duration of ESF leakge Conservative 0 - 30 days Assumption

32. Fraction of Reactor Building Volume available for mixing for ESF leakage QDC-9400 M-0363, 0.5 50% is the maximum allowed by RO Rev. I 1.183.

Exelon recognizes that this assumption may need some additional defense in the form of an analysis.

33. Percentage of ESF leakage that is filtered QDC-9400-M-0363, lO j% No leakage is assumed to bypass the Rev.1 filters in Calc. QDC-9400-M-0363.

TODI-02-019 Rev I Attachment I Page A18 of A23

C-AcJtW~--()O~ \x F0 Z.Q- -4 ttj k

PARAMETER LIST FOR OFFSITE AND CONTROL ROOM DOSE ANALYSIS - QUAD CIES POWER STATION LOCA - ALTERNAT SOURCE TERMS Item Referate Vahe Commenf

34. Control Room Pressure Boundary Envelope Free Volume QDC-9400-M-0363, 184,000 f3 Used in Caic. QDC-9400-M-0363, Rev.1 Rev. 1. The above calculation uses the referenced volume to develop concentrations, but uses a smaller volume (58,300 cu ft) to establish whole body doses. However, currently, no data is provided on CR internal structures (such as wall thickness) that support the acceptability of the reduced finite volume model.

Per Cakc. QDC.9400-M-0363, Rev. 1,

35. CR Ventilation System Design QDC-9400.M40363, Pressurization (1/8" w.g.) Quad Cities CR is pressurized to 1/8" Rev. 1 w.g. during normal operation as well as during accidents

36. Control Room Ventilation Intake Design Per Calc. QDC-9400-M-0363, Rev.],

QDC-9400M40363, Single Intake Quad Cities has a single CR intake Rev.1 which is the same for both normal and emergency mode.

TODI-02-019 Rev I Attachment I Page A19 of A23

CADX. 41 L . P ,-C'C4wS-~ \\- -j PARAMETER LIST FOR OFFSITE AND CONTROL ROOM DOSE ANALYSIS - QUAD CITIES POWER STATION LOCA - ALTERNATIVE SOURCE TERMS Item Reference Vale Commens

37. Control Room Intake / Inleakage Atmospheric Calc. QDC-0000-M- SBR=S Stack hr h4.16E-4 s/rn' o~~~~~-o.5 .64smThe SBOTS Stack release considers an Dispersion Factors Disj~~ersionFactors 1068, Rev.00-.

1068, Rev.0 elevated release with fumigation for the 0.5-2 hr 2.35E-9 s/m' first 0.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and non-fumigation for the 2-8 hr 1.15E-9 s/rn'remainder of the accident 8-24 hr 8.02E-10 s/m' MSIV leakage is assumed to occur from 1-4 day Is/n 3.96E-10 the edge of the MSIV rooms. MSIV leakage X/Q values are based on the 4-30 day 1l.21E-10 sin more limiting for the two Units, i.e., Unit I MSIV leakage.

MSIV Leakage 0-2 hr l.13E-3 s/rn'The X/Q for Control Room Intake is hr s/rn'representative 9.4E..4 2-8 for Control Room 2-8 hr 9.4511-4 -dm3Inleakage. Exelon recognizes that the 8-24 hr 4.54E-4 s/m' basis for this position may need to be 1-4 day 2.68E-4 s/ni documented 4-30 day 1.67E-4 sfin?

38. Control Room Breathing Rate RADTRAD Default 0-30 day - 3.47E-4 mi As Value

39. Control Room Occupancy Factors RADTRAD Default 0-24 hrs - 1.0 Values 1-4 days - 0.6 4-30 days - 0.4 TODI-02-019 Rev I Attachment I Page A20 of A23

C-gk"--&Ck. cj C. - (Z!st, two, - k - \ \ \ ;- -A N

• z.-z- i -w',

PARAMETER LIST FOR OFFSITE AND CONTROL ROOM DOSE ANALYSIS - QUAD CITIES POWER STATION LOCA - ALTERNATIVE SOURCE TERM iem Referce Value Commeits

40. Control Room Emergency Ventilation QDC-9400-M-0363, T=40 Minutes by manual operation.

Filtration System Actuation Time following a Rev.1 During the first 40 mins the CR is LOCA assumed to be on normal ventilation

41. Normal unfiltered ventilation air intake into QDC-9400-M-0363, 2,000 cfm +/- 10 % Used in QDC-9400-M-0363, Rev.1 the CR Rev. _

42. CR emergency ventilation air Intake Rate QDC-9400-M-0363, 2,000 cfm +/- 10 %Z Rev.1 43a. CR emergency ventilation intake filter QDC-9400-M-0363, Case 1 Used in CaIc. QDC-9400-M-0363, Rev. I efficiency: Base Case Rev.1Crcoal Elemental iodine: 99%

Organic iodine: 99%

MEPA Particulates: 99%

Assumed Case 2 43b. CR emergency ventilation intake filter Charoa efficiency: Proposed Case ______

Elemental iodine: 95%

Organic iodine: 95%

.,__ ._._.HEPA P.rticultes:_99 Particulates: 999b TODI-02-019 Rev I Attachment I Page A21 of A23

1-0 C-- s C!C.N - t4 - I\ \ A V-PARAMETER LIST FOR OFFSITE AND CONTROL ROOM DOSE ANALYSIS - QUAD CITIES POWER STATION LQCA . ALTERNATIVE SOURCE TERMS Item Ref ernee value Commenrt 44a. Unfiltered inleakage into CR during normal QDC-9400-M-0363, Cas"l Used in Calc. QDC-9400-M-0363, Rev. I and emergency ventilation mode: Base Case Rev.l 260 scfm Includes ingress/egress inleakage of 10 sWm.

44b. Unfiltered inleakage into CR during normal Assumed Case 2 and emergency ventilation mode: Proposed Case 600 scfm

45. CR emergency ventilation air recirculation QDC-9400-M-0363, Ocfm Per Calc. QDC-9400-M-0363, Rev. I Rate through filters Rev.l

46. Atmospheric Dispersion Factors at EAB QDC-0000-M-1069, SBGTS Stack:

Rev.0 0-0.5 hr 1.37-4 s/rm3 0.5-2 hr 3.21-6 s/in3 MSIV Leakage:

0-2 hr 1.25E-3 s/m 3 TODI-02-019 Rev I Attachment I Page A22 of A23

JI&  ? Z 7-%j j 7-1.j cca,C. Gk.S) IC - lt (Zh CZ CA - tl-A - %\ V-4 I -A, iS I

PARAMETER LIST FOR OFTSITE AND CONTROL ROOM DOSE ANALYSIS - QUAD CITIES POWER STATION Item Reference Value Comments

47. Atmospheric Dispersion Factors at LPZ SBGTS Stock: 3 QDC40Q00-M-1069, 0-0.5 hr 1.38E-5 s/r Rev.0 0.5-2 hr 3.09E-6 s/m 3 2-8 hr 1.52E-6 s/m3 8-24 hr 1.07E-6 s/m3 1-4 day 4.95E-7 s/n1 4-30 day 1.64B-7 s/n?

MSIV Leakage:

0-2 hr 6.68E-5 s/mr3 2-8 hr 3.07E-5 s/m3 8-24 hr 2.08E-5 s/n 3 1.4 day 8.95E-6 s/nl 4-30 day 2.67E-6 s/ni

48. Offsite Breathing Rate RADTRAD Default 0-8 hr - 3.47E-04 mJ /s Values 8-24 hr - 1.75E-04 m3 /s 1-30 day - 2.32E-04 m3 /s TODI-02-019 Rev I Attachment I Page A23 of A23