ML20217C405

Rev 1 to L-001119, Vc/Ve Mixed Air Relative Humidity Calculation

ML20217C405
Person / Time
Site:	LaSalle
Issue date:	09/12/1997
From:	Johnson W COMMONWEALTH EDISON CO.
To:
Shared Package
ML20217C365	List: ML20217C358 ML20217C377 ML20217C391 ML20217C405
References
L-001119, L-001119-R01, L-1119, L-1119-R1, NUDOCS 9710010384
Download: ML20217C405 (61)

Text

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LASAli.E COUNTY NUCLEAR POWER STATION UNITS 1 AND 2 FACILITY OPERATING LICENSES

, NPF-11 AND NPF-18 APPENDIX A TECHNICAL SPECIFICATIONS

VENTILATION FILTER TESTING PROGRAM i

i CALCULATION L-001119, REVISION 1, "VCNE MIXED AIR l RELATIVE HUMIDITY CALCULATION,"

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1-l P6st LOCA Control Room, Auxniary BooMc Equ> ment Room, and OWsNe Doees i

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This revlolon adds additional evaluepons for the AEER. , the AEER dose is now evaluated at both

' the cunent Seel0n and a 14000 cfm minimum flow rete. A change was also made in the intenhage values used to evoluete the dosos. SpoolRcesy, a 1200 cfm inleakage value was used for the control room and a 1000 ofm venue was used for the AEER boosues these oorfespond to 20 fem in the control

toom and 27 rom in the AEER for minimum flow conditions. A correction was eleo made to the GE noble gas

source term that resulted in lower gamme and oldn doses due to M81V leaka0s.

1 l This is e complete toviolon and supersedes revtolon 0 to this calculC.lon.

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SARGENT&LUNDV 23V11 XD:312-269-3753 SEP 12'9? 16:15No014P.b5 COMMONWEALTH EDISON COMPANY CALCULATION TABLE OF CONTENTS PROJECT NO. 10135 073 CALCULATION NO. L 00f1SS REV. NO.1 PAGE NO. 2 DESCRIPTION PAGE NO. SUS-PAGE NO.

TITLE PAGE I REVISION

SUMMARY

I la TABLE OP CONTENTS 2

1. PURPOSFJOBJECTIVE 3

2. METHODOLOGY / ACCEPTANCE CRITERIA 3 2.1 Background 3 2.2 Methodology 6 2.3 AcceptanceCriteria 8

3. ASSUMPTIONS 9

, 4. DBSIGNINPUT 10 4.1 Source Terms 10 4.2 Plant Parameters 10 4.3 AtmosphericDispersionParameters 10 4.4 Dose Conversion Factors J 4.5 MSIV Leakage Doses 11

5. REFERENCES 23

6. CALCULATIONS 26 6.1 Case C:::542'= 26 6.2 lodine Protection Factor (IPF) Calcula: ion 28

6.3 MSIV Leekage Pathway 30

6.4 Containmast and ECCS Leakage Pathways 31

7.

SUMMARY

AND CONCLUSIONS 43 7.1 Main Frame En=1stion 43 7.2 Offsite Doses 43 7.3 ControlRoom Doses 44 i

7.4 AEERDoses 45 j 7.5 Conclusions 45 ATTACHMENTS 59 A. POSTDBA C6 W A-1 B. LaSalle ControlRoom C=61=*iae S1 WO

, C.LaSalle AEERDose Calculation C-1 to C-40 i

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COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L-001166 PROJECT NO. 101354!13 PAGE NO. 3 l

1. PURPOSE / OBJECTIVE The purpose of this calculation is to estimate the radiation dose from inside atmosphere to personnel in the control room (CR) and the Auxiliary Electric Equipment Room (AEER) and to estimate the dose at the Exclusion Area Boundary (EAB) and Low Population Zone (LPZ) after a postulated design basis loss of coolant accident at the LaSalle County Station. The objective is to revise the design bases of the dose consequence analysis for the design basis LOCA, including new core source terms, revised MSIV leakage model, updated dose conversion factors, credit for

, suppression pool senibbing, and bounding ventilation parameters, including new filter efficiencies.

2 METHODOLOGY AND ACCEPTANCE CRITERIA 2.1 Backuround 2.1.1 Original FSAR/ Current UFSAR Analysis The consequences of a LOCA were developed by GE for the FSAR [ Reference 1] and are the same as the ones currently in the UFSAR [ Reference 2] Section 15.6.5 (Tables 15.6-9 and 15.6-

'2). The design basis analysis, used to demonstrate compliance with 10CFR100 [ Reference 3]

J ese limits at the EAB and LPZ, was based on Regulatory Guide 1.3 [ Reference 4] source terms.

ine containment was assumed to leak at 0.635% per day and was exhausted through a 90%

efficient Standby Gas Treatment System (SGTS) filter without any holdup in secondary containment. The atmospheric dispersion was modeled with a 30 minute fumigation period followed by releases through the stack.

Releases through the Main Steam Isolation Valve (MSIV) leakage control system (LCS) were also considered in the offsite dose. This leakage was at a rate of 11.5 scfh per line. Because of the time required to reach the outboard isolation valve, releases through this pathway did riot start until two hours after the accident. All of these releases were also filtered by the SGTS.

The post LOCA control room doses, which are used to demonstrate compliance with GDC 19 of 10CFR50 [ Reference 5], are also presented in UFSAR Section 15.6.5 (Table 15.6-18). The UFSAR states that these doses t e conservatively calculated assuming a 95% eflicient make up filter. No additional information on the method used to calculate the control room doses, such as atmospheric dispersion parameters, is provided in the UFSAR.

The NRC in the LaSalle Safety Evaluation Report (SER) [ Reference 6] independently evaluated the offsite doses (SER Section 15.3.2). Although the results of the NRC analysis is quite different l REVISION NO.: 1 i

COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L-001166 PROJECT NO. 10135-013 PAGE NO. 4 l from GE's, the conclusion was still that the results were within the guidelines of 10CFR100. In evaluating the adequacy of the control room ventilation system (SER Section 6.4), the NRC noted that the applicant had agreed that the recirculation filter (" Odor Eater") would be manually initiated upon receipt of a high radiation alarm on the intake monitor, and that the filter train would be tested with the once through filter. The NRC found the design acceptable without presenting any calculated control room doses. In evaluating the atmospheric cleanup systems (SER Section 6.5), the NRC assigned a filter efficiency of 99% to the SGTS and 95% to the control room makeup filter. An efficiency for the " Odor Eater" was not discussed.

2.1.2 Subsequent Analysis (S&L Calculation 1-CT 2)

In 1985 a calculation was prepared by Sargent & Lundy that estimated the control room doses following a LOCA. This calculation,1-CT-2 [ Reference 7], applied the methodology ofMurphy-Campe [ Reference 8] as implemented in the S&L computer program POSTDB A [ Reference 9] to the control room dose calculation. An SGTS filter efficiency of 99%, a control room makeup 4

filter efficiency of 95% and a recirculation filter efficiency of 70% were used. This calculation

1. also considered ventilation performance parameters, such as unfiltered inleakage and filter bypass, in calculating the iodine dose in the control room. Site specific meteorology was used to calculate atmospheric dispersion, and both elevated and ground level releases were considered. The MSIV leakage component, which was assumed to be continuous at ground level for the first 20 minutes of the accident, dominated the doses. These results were not used to support any UFSAR or license change.

In 1989 it was recognized that there were inconsistencies in the ventilation parameters used in the dose analyses and the ventilation system testing and performance requirements. A series of revisions to 1-CT-2 were performed [ Reference 10] that considered the following effects: credit for suppression pool scrubbing, reduced control room makeup filter efficiency (90%), eliminating the credit for the recirculation filter for removing iodine, and revised atmospheric dispersion parameters. The calculation was also expanded to include the calculation of EAB and LPZ doses.

, The results of the analyses and recommendations for changes to testing requirements were summarized in S&L report SL-7232 [ Reference 11]. The conclusion of this report was that the i

credit for the recirculation filter for iodine removal was not required and that the appropriate efficiency for the control room makeup filter was 90%. This report provided the basis for a proposed licensing amendment [ Reference 12] that, along with changing the filter efficiencies, removed the AEER from the control room boundary. That request for a licensing amendment was retracted.

2.1.3 GE Analysis for MSIV LCS Removal In 1995, a licensing amendment was submitted to remove the MSIV LCS and increased the allowable MSIV leak rate to 100 scfh per line [ Reference 13]. Included with this submittal war a l REVISION NO.: 1 l

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l COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L-001166 PROJECT NO. 10135-013 PAGE NO. S l l

calculation by GE for the hiSIV leakage component of the post LOCA control room and offsite doses [ Reference 14]. This calculation was performed using the methodology and proprietary computer code developed by GE for the BWR Owners Group [ Reference 15] In Attachment A to the licensing submittal is a safety evaluation which includes a calculation of the expected offsite ,

and control room doses before and after the removal of the MSIV LCS and the Ucrease in MSIV leakage rate. The doses before the modificat ion were taken to be the doses that are currently in the UFSAR. The GE doses for the MSIV pathway were added to the UFSAR doses to obtain the doses after the modification. This was deemed conservative since the UFSAR doses already included the contribution ofMSIV leakage with the MSIV LCS in place. Due to an error found in the drain line lengths, an updated GE calculation [ Reference 17] was sent to the NRC

[ Reference 16]. The updated calculation did not change the calculated doses.

The ventilation parameters used in the GE analysis are similar to, b.it not the same as, the ones used in 1-CT-2, Rev. I and Rev. 3. The atmospheric dispersion parameters are the same. The makeup filter efficiency,90%, is the same in both cases, but 1-CT-2, Rev. 3, did not take credit for iodine removal by the recirculation filter, whereas the GE analysis used a filter efficiency of 75%. Both analyses accounted for filter bypass and unfiltered inleakage, although the values are slightly different.

It should also be noted that the GE code calculates the source term based on the reactor power level. The factors that convert power level to Curies in the current code are slightly different from the ones used to generate the core source term in the UFSAR and are therefore different from 1-CT-2. In addition, GE uses dose conversion factors for iodine that are based on ICRP 30, rather than the Regulatory Guide 1.109 values that were used in 1-CT-2.

2.1.4 Evaluation of Doses in the AEER In 1996 during testing of the VC and VE systems it was also noted that there was no formal calculation for the dose to the operators in the AEER. This was previously not considered a requirement because, as stated in the 1990 licensing amendment, post accident access to the AEER was not required. However, there are some instmments in the AEER that must be accessed by the operators following a LOCA. Therefore this area must remain a part of the control room envelope. To address these issues, Sargent & Lundy prepared calculation L-000772

[ Reference 18]. This calculation demonstrated that the doses in the UFSAR for containment leakage could be applied to both the control room and the AEER. Most of the calculation, however, is devoted to demonstrating the behavior of the iodine dose for variations in the ventilation system performance. It uses the iodine protection factor (IPF) methodology from Murphy-Campe to demonstrate the effect of various filter efficiencies and duct leakage rates on the doses in the control room and AEER. The IPF was used to scale the GE results for a range of ventilation parameters provided by Comed [ Reference 19].

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l COMMONWEALTH EDISON COMPANY l CALCULATION NO. t L-001166 PROJECT NO. 10135-013 PAGE NO. 6 l 2.2 hidbodolorv 2.2.1 Source Term The core inventory in the current UFSAR [ Reference 17 and 20] and the core inventory used by GE in the analysis for htSIV leakage [ Reference 21] are different. The reason for this difference is that since the UFSAR sources were generated in 1976, GE has updated its source calculations and the updated sources are included in the code used to calculate the results of hiSIV leakage.

The iodine source terms are nearly identical (the updated values are about 2% higher), but the updated noble gas sources are about 50% lower than the UFSAR values. To provide a consistent set of results, the calculation will be performed using both the UFSAR source term as identified in Table 15.6-9 and the updated GE source term. LaSalle has changed their mode of operation since the issuance of the UFSAR to increase the power level and to extend the fuel cycle. To illustrate the effect of these changes on the offsite doses, the extended bumup sources provided by Siemens

[ Reference 22] will also be u' sed to calculate the control room and offsite doses.

2.2.2 Suppression Pool Scrubbing The NRC guidance on the use of suppression pool scrubbing is documented in the Standard Review Plan (SRP) Section 6.5.5 [ Reference 23]. Both calculation 1-CT-2, Rev. I and 3, and the GE analysis for hiSIV leakage take credit for suppression pool scrubbing, therefore this effect will also be included in this calculation.

2.2.3 ICRP 30 Dose Conversion Factors The original dese calculation and the SER were based on dose conversion factors from TID 14844 or Regulatory Guide 1.109. Currently, the NRC has endorsed the use of dose conversion factors based on ICRP 30 [ Reference 24]. The GE analysis for the htSIV leakage uses these newer values. To be consistent, this analysis will also use the ICRP 30 iodine dose conversion factors.

2.2.4 Ventilation System Parameters The previous analyses used slightly different values for filter efficiencies and inleakages, and design values for flow rates. In this calculation the base case for the control room will be a 95%

efficient makeup filter combined with a recirculation filter efficiency of 70%, current design makeup and recirculation flow rates, and calculated inleakage rates Additional cases will be analyzed for a minimum recirculation flow rate and a minimum makeup rate. The minimum makeup rate, which is 10% below the current design flow rate as specified in Technical Specification 3/4.7.2, represents the lower range of acceptable test values. The lower range is

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COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L-001166 PROJECT NO. 10135-013 PAGE NO. 7 l most conservative because it leads to a slower turnover of the control room atmosphere and a longer exposure time for operators in the control room.

Use of a minimum recirculation flow rate is also conservative because it minimizes the cleanup rate for the recirculation filter. Since the recirculation filter units do not have an established surveillance requirement, the minimum system flow will be evaluated. For the control room this flow is 18,000 cfm and for the AEER the minimum flow is 14,000 cfm. Both of these values are about 25% below the current design flow values. A recirculation filter bypass fraction of 5% will be used. To account for manual initiation of the recirculation filter, delays up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> will be considered before taking credit for iodine removal by the recirculation filter.

The calculated inleakage values for the ventilation systems will be used as the minimum expected inleakage rates. Two additional values ofinleakage will also be evaluated: an intermediate inleakage and a final inleakage. The intermediate inleakage value is expected to bound the as-found inleakage and will be used to establish testing acceptance criteria for the VE and VC systems. The intermediate value will have sufficient margin to provide some flexibility in evaluating the results ofinleakage tests. Specifically, the intermediate value for the VC system will be the inleakage that produces a control room dose of 20 rem thyroid. Similarly, the intermediate value for the VE system will be the value ofinleakage that produces a dose of 27 rem thyroid in the AEER. The finalinleakage values for both systems will be selected so that the thyroid dose in the control room and AEER, when evaluated at current design system flow rates, exceeds 30 rem.

2.2.5 Containment Leakage The doses in the control room, AEER acd offsite due to leakage from the containment into the reactor building will be calculated using ti e current version ofPOSTDBA [ Reference 25]. A five minute drawdown period will be assumed prior to initiating the SGTS, which has a filter efliciency of 99% for iodines. A 30 minute fumigation period will start at the beginning of the accident and run concurrent with the drawdown period.

2.2,6 MSIV Leakage The doses due to MSIV leakase will be based on the calculation by GE. The dose model actually consists of two parts: the tr .nsport model that determines the activity concentration in the outside air, and the HVAC modd that determines the activity concentration in the room Since both the VC and VE systems use the same source of outside filtered air that GE used, the transport portion of the model, which ircludes releases from the condenser and atmospheric dispersion, will not change. Therefore, th : differences between the GE results and the doses to operators in the two

areas will be determint d by the differences in the ventilation systems. The effectiveness of the systems for protection against airborne iodine are characterized by the iodine protection factor, l REVISION NO.

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COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L-001166 PROJECT NO. 10135-013 PAGE NO. 3 l which is the ratio of the iodine concentration in outside air to the concentration in the inside

. atmosphere. The MSIV doses due to different ventilation system operating conditions will be obtained by multiplying the GE results by a ratio ofiodine protection factors. Since the GE results are provided on a nuclide basis, the results for different sources will be obtained by multiplying each nuclide result by the ratio of the initial source terms.

2.2.7 Containment Bypass Leakage MSIV leakage is considered containment bypass leakage, i.e., it bypasses the secondary containment and is released directly to containment. In response to questions in the FSAR (Question 021.11), all other potential bypass paths were analyzed. The conclusion was that there are no additional credible pathways for bypassing the secondary containment.

2.2.8 ECCS Leakage Leakage from equipment circulating suppressi.on pool water outside primary containment is another potential release pathway for activity to the environment. SRP 15.6.5, Appendix B

[ Reference 32), describes the methodology used to analyze this path. At LaSalle, leakage from systems handling postaccident fluids is expected to be minimal complying with the commitment in FSAR Section L-77. This commitment is implemented by station procedure LAP-100-14

[ Reference 33]. The ECCS leak rate will be conservatively based on the typical industry administrative limit of 5 gal /hr. For the analysis, consistent with SRP 15.6.5, Appendix B, the leak rate will be taken as two times the sum of the administrative limit for simultaneous leakage from all components in the recirculation systems. This leak rate is conservatively approximated at 10 gal /hr. Since the leakage will occur in the secondary containment, the POSTDBA model for this pathway is the same as the containment leakage pathway with appropriate source and leak rate changes.

2.3 Accentance Criteria The acceptance criteria for the operator dose is General Design Criteria 19 of 10CFR50, which is 5 rem whole body or the equivalent. The equivalent thyroid and beta skin dose from SRP 6.4

[ Reference 26]is 30 rem.

The acceptance criteria for offsite doses are from 10CFR100, which, for the EAB, are 300 rem thyroid and 25 rem whole body for the first two hours and, for the LPZ, are 300 rem thyroid and 25 rem whole body over the course of the accident.

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COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L-001166 PROJECT NO. 10135-013 PAGE NO. 9 l

3. ASSUMPTIONS The following assumptions describe the accident conditions and function of accident mitigating systems modeled in this calculation.

1. In accordance with the guidance in Regulatory Guide 1.3, the so me term for containment leakage is 100% of the core inventory of noble gases and 25% of the core inventory of iodines. This activity is assumed to be instantaneously and uniformly distributed in the volume of the drywell and wetwell at time zero.

2. The airbome iodine available for release from the containment is instantaneously reduced by suppression pool scrubbing at time zero. To calculate the suppression pool bypass fraction, a geometric loss coefficient of 3 is assumed for the suppression pool bypass in accordance with UFSAR page 6.2.27.

3. In accordance with the guidance in Regulatory Guide 1.3, the containment is assumed to leak at the Technical Specification value for the duration of the accident.

4. It is assumed that it takes the Technical Specification period for the SGTS to draw down the reactor building. During this period, the releases are at ground level. After draw down, the releases are from the stack through the SGTS with no mixing or holdup in the reactor building.

5. A fumigation period is assumed to exist for the first 30 minutes of the accident consistent with the guidance in Regulatory Guide 1.3.

6. The control room emergency makeup filtration system is actuated prior to any activity entering the control room. Initiation of the recirculation filter is delayed.

7. After the end of the fumigation period, there is no additior.al activity taken into the cor. trol room from the containment and dCCS leakage pathways.

8. The assumptions in the GE model for MSIV leakage (Reference 17] concerning activity transport, iodine plateout and resuspension in the steam lines, drain lines, turbine and condenser are considered valid and applicable to this analysis.

9. As discussed in Section 2.2.8, the leakage from ECCS components outside cortainment is coriservatively assumed to be 10 gallons per hour. The source is 50% of the core iodines uniformly distributed in the minimum suppression pool water volume. In accordance with the guidance in SRP 15.6.5,10% of the iodine in the leaked fluid is assumed to become airborne and is available for release to the en ironment.

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COMMONWEALTH EDISON COMPANY l l_ CALCULATION NO. : L 001166 PROJECT NO. 10135 013 PAGE NO.10 l

4. DESIGN INPUTS 4.1 Source Terms There are three source terms to be considered in this calculation. First, there is the source term in the UFSAR, which is the current licensing basis. Next there is the source term used by GE to calculate the dose contribution from MSIV leakage. And finally, there is the source generated by Siemens for extended burnup fuel. These three source terms are shown in Table 1. Note that in this table, the iodine activities represent 25% of the core inventory whereas the noble gas

) activities are 100% of the core inventory. Also included in this table aie the decay constants (A) for the nuclides taken from Reference 9. See Section 6.0 for further discussion of the values in this table.

4.2 Plant Design Parameters The plant design parameters are used to deterinine the leak rates from the containment and the activity concentrations in the control room and AEER. The flow rates for the control room HVAC system are shown in Figure 1, and the flow rates for the AEER are shown in Figure 2

[ Reference 34). Note that these are current design flow rates. As discussed in Section 2.2.4, calculations will also be performed at minimum test criteria for the makeup flow rate. The minimum recirculation flow rate will be 18000 cfm for the control room and 14000 cfm for the AEER. The GE analysis and calculation 1-CT-2 used a filter efficiency of 90% for the intake filter, and the GE analysis used a filter efficiency of 75% for the recirculation filter. In this calculation, filter efficiencies of 95% for the intake filter and 70% for the recirculation filter are used. In addition, a recirculation efficiency of 0% is used to determine the effect of not using the recirculation filter. For tlie SGTS filter, an efficiency of 99% is used. Additional plant data is listed in Table 2. Note that the containment volumes listed in this table are from the UFSAR.

These volumes are used only to calculate a flow rate that corresponds to a containmem leak rate of 0.635%/ day, so the volumes are not considered design input and do not require further verification.

4.3 Atmosoberic Dispersion Parameters The atmospheric dispersion parameters used to calculate the offsite and control room dose due to containment and ECCS leakage are taken from I-CT-2 and are also shown in Table 2. The following is a summary of the basis for these values. Note that this discussion applies only to leakage into the reactor building and is not applicable to the releases through the MSIV's. The GE analysis uses a set of atmospheric dispersion parameters that are different from the ones described in this section, and, as described in Section 2.2.6, those parameters are not changed in this analysis.

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COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L-001166 PROJECT N'O. 10135-013 PAGE NO.11 l The EAB and LPZ x/Q values are taken directly from the graphical information presented in Regulatory Guide 1.3 [ Reference 4] for an EAB distance of 509 meters and LPZ distance of 6400 meters. The building wake correction is based on a minimum reactor building area of 2270 m',

and the elevated releases are based on a release height of 112.8 m for the EAB and 95.8 m for the LPZ.

In POSTDBA, the atmospheric dispersion for the control room in the first 30 minutes is characterized by the following expression:

x/Q = 2/(uA) where u is the fifth percentile wind speed and A is the projected area of the reactor building normal to the wind direction. Revision 2 of 1-CT-2 used meteorological data for the period 1982-1987 to detennine the fiRh percentile wind speed for the different inlets. The worst case was the south inlet which, using the values for u and A in Table 2, produces a x/Q of 2.65E-4 2

sec/m' (which is equivalent to the value of 2.462E-5 sec/(m-ft ) determined in 1-CT-2). This x/Q is crJy pplicable for the first 30 minutes of the accident when ground level releases from the reactor building are assumed to exist. After 30 minutes, all releases from the reactor building are elevated and no activity reaches the control room.

4.4 Dose Conversion Factors The iodine dose conversion factors (DCF) used in 1-CT-2 were taken from Regulatory Guide 1.109 [ Reference 27]. In addition,1-CT-2 alsc contained gamma and beta depth dose factors based on Regulatory Guide 1.109. Since the current version of POSTDBA has default data for iodine based on ICRP 30, the Regulatory Guide 1.109 will have to be input into the PC version of POSTDBA to emulate the main frame version The Regulatory Guide 1.109 values for dose conversion factors are shown in Table 3, along with the updated dose conversion factors based on ,

ICRP 30. Note that what are referred to here as the ICRP 30 dose conversion factors are actually taken from Federal Guidance Report 11 (Reference 24], which is based on ICRP 30.

4.5 MSIV Leakage Doses The offsite and control room doses due to leakage through tne MSIV's were calculated by GE and used as the basis for the licensing amendment removing the MSIV leakage control system

[ Reference 17). The doses were reported by nuclide at time periods of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />,4 hours, I day and 30 days following the accident. Although seven different cases were reported by GE, the results of their base case, used in the licensing submittal, are shown in Tables 4, 5,6 and 7. Note that five separate components are addressed by GE. The main contributor to the dose is leakage through the drain lines to the main condenser. Releases through this pathway are considered for elemental and particulate iodine, which plate out in the steam lines, organic iodine (which is not l REVISION NO.: 1 l

COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L 001166 PROJECT NO. 10135413 PAGE NO.12 l subject to plate out), the resuspension of the plated out iodine and noble gases. The travel time required for the MSIV leakage to reach the turbine building is considerable (nearly 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) so the early time periods do not contribute significantly to the dose. The other pathway is through the turbine stop valves and the high pressure turbine. The travel time for this pathway is so long that there is no doses for the first day, and the subsequent doses are due only to organic iodines and noble gases. - For the whole body and beta doses, only the noble gas contribution is tabulated because the iodine contribution is five orders of magnitude smaller than the noble gases.

it should be noted that in their control room model, GE used slightly different ventilation parameters than those shown in Figure 1. The actual values used in the original MSIV leakage analysis must be used to assure the scaling of the MSIV control room doses, as described in Section 2.2.6, is accurate. Specifically, the makeup to the control room was set at 1500 cfm and j the filter xi inleakage was 617 cfm. Also, they used a bypass fraction of 2% rather than the 5%

indicatec on Figure 1. In addition, GE used a makeup filter efficiency of 90% and a recirculation filter efficiency of 75%.

The only offsite dose calculated by GE was at the LPZ. To determine the dose at the LPZ, they simply scaled the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> LPZ by the ratio of the EAB x/Q' (5.10E-4) to the LPZ x/Q' (1.10E-5).

l REVISION NO.: 1 l

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

l I

i COMMONWEALTH EDISON COMPANY l

l_ CALCULATION NO. : L-001166 PROJECT NO. 10135-013 PAGE NO.13 l )

Table 1. LOCA Source Terms: 25% Core Inventory oflodine, 100% Core inventory of Noble Gas A LaSalle UFSAR, Ci GE Source (3458 Mw) Siemens Nuclide per hour 1 min 0 min Ci/Mw Cl Ci I.131 3.593E-03 2.2E+07 2.20E+07 2.631E+04 2.27E+07 2.90E+07 l-132 3.035E-01 3.3 E+07 3.32E+07 3.845E+04 3.32E+07 4.08E+07 1-133 3.334E-02 4.9E+07 4.90E+07 5.502E+04 4.76E+07 5.18E+07 1134 7.920E-01 5.6E+07 5.67E+07 6.056E+04 5.24E+07 5.80E+07 1-135 1.051E-01 4.4E+07 4.41E+07 5.195E+04 4.49E+07 4.50E+07 Kr-83m 3.740E-01 1.4E+07 1.41E+07 3.137E+03 1.08E+07 5.22E+06 Kr-85 7.380E-06 1.4E+06 1.40E+06 3.015E+02 1.04E+06 2.27E+06 Kr-85m 1.548E-01 4.5E+07 4.51E+07 6.734E+03 2.33E+07 2.01 E+ 07 Kr-87 5.472E-01 8.0E+07 8.07E+07 1.292E+04 4.47E+0? 3.75E+07 Kr-88 2.477E-01 1. l E+0S 1.10E+08 1.830E+04 6.33E+07 5.55E+07 Kr-89 1.318E+01 1.lE+08 1.37E+08 2.276E+04 7.87E+07 6.79E+07 Xe-131m 2.408E-03 9.0E+05 9.00E+05 1.582E+02 5.47E+05 9.80E+05 Xe-133 5.470E-03 1.9E408 1.90E+08 5.528E+04 1.91E+08 2.07E+08 Xe-133m 1.296E-02 4.8E+06 4.80E+06 2.305E+03 7.97E+06 5.08E+06 Xe-135 7.560E-02 1.9E+08 1.90E+08 7.148E+03 2.47E+07 4.07E+07 Xe-135m 2.718E+00 5. l E+07 5.34E+07 1.042E+04 3.60E+07 5.54E+07 Xe-137 1.084E+01 1.5E+08 1.80E+08 4.852E+04 1.68E+08 2.04E+08 Xe-138 2.930E+00 1.6E+08 1.68E+08 4.610E+04 1.59E+08 1.98E+08 l REVISION NO.: 1 l

COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L-001166 PROJECT NO. 10135 013 PAGE NO.14 l Table 2. Plant Parameters input Parameter l Value l Basis / Reference Containment Parameters Drywell free volume (ff) 229.538 UFSAR Table 6.21 Wetwell volume (ff) 165,100 UFSAR Table 6.21 Primary Containment leak rate y 0.635 T/S Bases,3/4.6.1.1 Primary

(%/ day) Containment Integrity Suppression 0.052 T/S 3/4.6.2.1 Suppression area. At (ff) pool maximum leakage (See Section 6.4.2) Chamber Suppression pool vent area, Av (ff) 232 LaSalle Drawing S,-326 Suppression pool volume (ff) 128,800 T/S 3/4.6.2.1 Suppression 2

Chamber Suppression pool DF organic I 1 SRP 6.5.5 elemental I . 10 particulate i 10 SGTS filter fractional efficiency 0.99 SER Section 6.5 T/S 3/4.6.5.3, Standby Gas Treatment System SGTS draw down time (min) 5 T/S 3/4.6.5.1, Secondary Containment Integrity Control Itoom Parameters Outside air intake rate before intake ' 3944.8 NDIT No. LS-0570 filter (cfm)

Outside air unfiltered infiltration after 55.2 NDIT No. LS-0570 makeup filter (cfm)

Outside air intake test range (percent 10 % T/S 3/4.7.2 Control Room and of full flow) AEER Emergency Filtration System Intake filter fractional efficiency 0.95 NDIT No. LS-0570 Control room makeup rate (cfm) 1500 NDIT No. LS-0570 CR outside air unfiltered infiltration 516.5 NDIT No. LS-0570 rate before recire filter (cfm)

CR outside air unfiltered infiltration 7 NDIT No. LS-0570 rate after recire filter (cfm)

CR recirc filter bypass (percent of full ., 5% NDIT No. LS-0570 Dow)

CR recire filter flow rate, including 26340 NDIT No. LS-0570

, bypass (cfm) l REVISION NO.: 1 l

COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L-001166 PROJECT NO. 10135 013 PAGE NO.15 l Table 2. Plant Paremeters input Parameter Value liAsis/ Reference Free volume of the control room i17472 1-CT-2, Rev 1, page 74 HVAC boundary (R')

CR Recire filter fractional efliciency 0.70 NDIT No. LS-0570 AEER Parameters AEER makeup rate (cfm) 2500 NDIT No. LS-0570 AEER outside air unfiltered 614 NDIT No. LS-0570 infiltration rate before recire filter (cfm)

AEER outside air unfiltered 6 NDIT No. LS-0570 infiltration rate aRer recire filter (ctin)

AEER recire filter bypass (percent of 5% NDIT No. LS-0570 full flow)

AEER recirc filter flow rate including . I8,300 NDIT No. LS 0570 bypass (cfm)

Computer room flow rate (cfm) 100 NDIT No. LS-0570 Free volume of the AEER HVAC 74,088 LaSalle Drawings A-186, A-17 boundary (R') and M 15 AEER recire filter fractional efliciency 0.70 NDIT No. LS-0570 Atmospheric Dispersion Parameters Cross section of Rx building (ft2 ) 1-CT-2, Rev 2 South Inlet 56218 page 147 FiRh Percentile Wind Speed (m/sec) 1-CT-2, Rev 2 South Inlet 1.445 page 147 EAB x/Q Reactor Bldg. (sec/m'); l-CT-2, Rev 1 Ground Level (0-5 min) 6.8E-4 page 78 Fumigation (5 min .5 hr) 1.85E-4 Elevated (.5-2 hr) 1.7E-5 LPZ X/Q Reactor Bldg. (sec/m'): 1-CT-2, Rev 1 Ground Level (0-5 min) 3.9E-5 page 78 Fumigation (5 min .5hr) 2.3E-5 Elevated .5-8hr 6.0E-6 8-24 hr 1.9E-6 1-4 days 6.1E-7 4-30 days 1.9E-7 l REVISION NO.: 1 l

COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L-001166 PROJECT NO. 10135-013 PAGE NO.16 l Table 3. Dose Convesion Factors and Breathing Rates Thyroid Dose Conversion Factors (rem /CI)

Nuclide Regulatory Guide ICRP 30 1.109 (Adult) (Ref. 25) 1131 1.49E+06 1.08E+06 1-132 1.43EM4 6.40E+03 1-133 2.69E+05 1.80E+05 1 134 3.73E+03 1.07E+03 1-135 510E+04 3.13E+04 Depth Dose Factors (Ref. 9)

Nuclide Beta Skin Gamma Whole Body 1-131 1.00E+00 1.00E+00 1-132 1.00E+00 1.00E+00 1-133 1.00E+00 1.00E+00 1-134 1.00E+00 1.00E+00 1-1.35 1.00E+00 1.00E+00 Kr-83m 1.00E+00 3.92E-03 Kr-85m _

7.41E-01 9.51E-01 Kr-85 6.87E-01 9.36E-01

.Kr-87 9.45E-01 9.59E-01 Kr-88 8.09E-01 9.67E-01 Kr-89 9.53 E-01 9.60E-01 Xe-131m 1.00E+00 5.87E-01 Xe-133m 1.00E+00 7.68E-01 Xe-133 2.91 E-01 8.75E-01 Xe-135m 1.00E+00 9.29Ei Xe-135 7.56E-01 9.43E-01 Xe-137 9.61 E-01 9.40E-01 Xe-138 8.69E-01 9.59E-01 Breathing Rates (m'/sec) (Ref. 4)

Time Period EAB/LPZ Control Room 0-8hr 3.47E-4 3.47E-4 8-24 hr 1.74E-4 3.47E-4 1-30 day 2.32E-4 3.47E-4 l REVISION NO.: 1 l

~

COMMONWEALTH EDISON ' COMPANY ,

l CALCULATION NO. : L-001166 PROJECT NO. 10135-013 _PAGE NO.17 I Table 4. GE Control Room Thyroid Dose from MSIV Leakage 0-2 Hour Dose, rem Nuclide El-DL OR-DL OR-T Resus Total I-131 3.711 E-06 7.538E-05 0.000E+00 8.091E-07 7.990E-05 1132 1.994E-08 4.051E-07 0.000E+00 0.000E+00 4.250E-07 I-133 1.233E-06 2.503E-05 0.000E+00 0.000E+00 2.G26E-05 1-134 2.419E-09 4.914E-08 0.000E+00 0.000E+00 5.156E-08 1-135 1.801E-07 3.658E-06 0.000E+00 0.000E+00 3.838E-06 Total 5.146E-06 1.045E-04 0.000E+00 8.091E-07 1.105E-04 0-4 Hour Dose, rem Nuclide El-DL OR-DL OR-T Resus Total I-131 4.345E-05 8.861E-04 0.000E+00 7.723E-Oo 9.373E-04 1-132 1.534E-07 3.126E-06 0.000E+00 0.000E+00 3.279E-06 I-133 1.382E-05 2.818E-04 0.000E+00 0.000E+00 2.956E-04 I-134 1.028E-08 2.093E-07 0.000E+00 0.000E+00 2.196E-07 1-135 1.821E-06 3.712E-05 0.000E+00 0.000E+00 3.894E-05 Total 5.925E-05 1.208E-03 0.000E+00 7.723E-06 1.275E-03 0-1 Day Dose, rem Nuclide El-DL OR-DL OR-T - Resus Total 1-131 2.919E-03 6.620E-02 0.000E+00 1.481E-03 7.060E-02 1-132 8.477E-07 1.763E-05 0.000E+00 0.000E+00 1.848E-05 1-133 6.405E-04 1.437E-02 0.000E+00 0.000E+00 1.501E-02 /

I-134 1.737E-08 3.553E-07 0.000E+00 0.000E+00 3.727E-07 I-135 3.871 E-05 8.463E-04 0.000E+00 0.000E+00 8.850E-04 Total 3.599E-03 8.143E-02 0.000E+00 1.481E-03 8.651 E-02 0-30 Day Dose, rem Nuclide El-DL OR-DL OR-T Resus Total I-131 1.386E-02 1.771E+00 1.047E-05 1.327E+00 3.l l2E+00 I-132 8.468E-07 1.769E-05 0.000E+00 0.000E+00 1.854E-05 1-133 1.135E-03 3.809E-02 2.973E-13 0.000E+00 3.923E-02 I-134 1.737E-08 3.553E-07 0.000E+00 0.000E+00 3.727E-07 1-135 4.347E-05 1.004E-03 2.598E-25 0.000E+00 1.047E-03 Total 1.504E-02 1.810E+00 1.047E-05 1.327E+00 3.152E+00 El-DL = Elemental Iodine, Drain Line Pathway OR-DL = Organic Iodine, Drain Line Pathway OR-T = Organic Iodine, HP Turbine Pathway Resus = Resuspension, Drain Line Pa:hway l REVISION NO.: 1 l

COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L-001166 PROJECT NO. 10135-013 PAGE NO.16 l Table 5. GE Control Room Whole body and Skin Dose from MSIV Leakage i '

Whole Body Dose, rem Beta Skin Dose, rem Nuclide i Drain Line Turbine Total Drain Line Turbine Total Kr-83m ',276E-06 0.000E+00 2.276E-06 9.764E-09 0.000E+00 9.764E 09 Kr-85 5.270E-05 8.810E 10 5.270E-05 6.634E-02 1.109E-06 6.634E-02

, Kr-85m 9.539E-05 7.731 E-34 9.539E-05 3.474E-03 2.816E-32 3.474E-03 Kr-87 3.999E-05 0.000E+00 3.999E-05 9.635E-04 0.000E+00 9.635E-04 Kr-88 1.011 E-03 0.000E+00 1.0llE-03 2.710E-03 0.000E+00 2.710E-03 Kr-89 6.602E-12 0.000E+00 6.602E-12 5.550E-ll 0.000E+00 5.550E-I l Xe-131m 4.577E-04 4.005E-09 4.577E-04 5.644E-03 4.938E-08 5.644E-03 Xe-133 6.006E-02 1.707E-07 6.006E-02 6.912E-01 1.965E-06 6.912E-01 Xc 133m 2.753E-04 2.496E-11 2.753E-04 2.475E-02 2.244E-09 2.475E-02

. Xe-135 - 6.304E-04 5.071E-21 6.304E-04 1.086E-02 8.735E-20 1.086E-02 Xe-135m 3.880E-08 0.000E+00 3.880E-08 1.341 E-07 0.000E+00 1.341 E-07 Xe-137 7.985E-12 0.000E+00 7.985E-12 1.076E-09 0.000E+00 1.076E-09 Xe-138 2.100E-07 0.000E+00 2.100E-07 2.303E-06 0.000E+00 2.303E-06 Total 6.263E-02 1.756E-07 6.263E-02 8.059E-01 3.126E-06 8.059E-01 4

d l REVISION NO.: 1 l

COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L-001166 PROJECT NO. 10135-013 PAGE NO.19 l Table 6. GE LPZ Thyroid Dose from MSIV Leakage

. 0-2 Hour Dose, rem Nuclide El-DL OR-CL OR-T Resus Total I-131 1.860E-05 3.783E-04 0.000E+00 3.760E-06 4.007E-04 I-132 1.006E-07 2.046E-06 0.000E+00 0.000E+00 2.147E-06 I-133 6.182E-06 1.257E-04 0.000E+00 0.000E+00 1.319E-04 I-134 1.235E-08 2.512E-07 0.000E+00 0.000E+00 2.636E-07 1-135 9.047E-07 1.840E-05 0.000E+00 0.000E+00 1930E-05 Total 2.530E-05 5.247E-04 0.000E+00 3.760E-06 5.543E-04 0-30 Day Dose, rem Nuclide El-DL OR-DL OR-T Resus Total I-131 3.785E-02 4.660E+00 2.663E-05 3.413E+00 8.lllE+00 1-132 3.102E-06 6.455E-05 0.000E+00 0.000E+00 6.765E-05 I-133 3.098E-03 1.063E 01 7.575E-13 0.000E+00 1.094E-01 I-134 7.799E-08 1.596E-06 0.000E+00 0.000E+00 1.674E-06 I-135 1.232E-04 2.829E-03 2.921E 24 0.000E+00 2.952E-03 Total 4.107E-02 4.769E+00 2.663E-05 3.413E+00 8.223 E+00 El DL = Elemental lodine, Drain Line Pathway OR DL = Organic lodine, Drain Line Pathway OR T = Organic lodine, HP Turbine Pathway -

Resus = Resuspension. Drain Line Pathway l REVISION NO.: 1 l

COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L-001166 PROJECT NO. 10135 013 PAGE NO. 20 l Table 7. GE LPZ Whole Body Dose from MSIV Leakage 0-2 hr Dose, rem 0-30 day Dose, rem Nuclide Drain Line Turbine Total Drain Line Turbine Total Kr-8Sm 4.873E-09 0.000E+00 4.873E-09 1.266E-07 0.000E+00 1.266E-07

~

Kr-85 6.578E-10 0.000E+00 6.578E-10 4.199E-05 6.969E-10 4.199E-05 Kr-85m 7.832E-07 0.000E+00 7.832E-07 9.648E-05 7.976E 34 9.648E-05 Kr-87 4.494E-06 0.000E+00 4.494E-06 5.712E-05 0.000E+00 5.712E-05 Kr-88 2.377E-05 0.000E+00 2.377E-05 1.314E-03 1.401E-45 1.314E-03 1

Kr-89 8.554E-11 0.000E+00 8.554E-11 8.554E-11 0.000E+00 8.554E-11 Xe-131m 3.315E-09 0.000E+00 3.315E-09 8.720E-05 7.438E-10 8.720E-05 Xe-133 2.399E-% 0.000E+00 2.399E-06 2.836E-02 2.836E-02' J.624E-08 Xe-133m 5.181E-08 0.000E+00 5.181E-08 2.262E-04 1.831E-11 2.262E-04 Xe-135 1.506E-06 0.000E+00 1.506E-06 6.061E-04 4.176E-21 6.061E-04 Xe-135m 9.140E-08 0.000E+00 9.140E-08 1.159E-07 0.000E+00 1.159E-07 Xe-137 7.622E-11 0.000E+00 7.622E-11 7.622E-11 0.000E+00 7.622E-11 Xe-138 5.987E-07 0.000E+00 5.987E-07 7.133E-07 0.000E+00 7.133E-07 Total 3.370E-05 0.000E+00 3.370E-05 3.079E-02 7.770E-08 3.079E-02 4

l REVISION NO.: 1 l

COMMONWEALTH EDISON COMPANY

. l CALCULATION NO. : L-001166 PROJECT NO. 10135 013 PAGE NO. 21 l Figure 1. Diagram of Control Room HVAC with Unfiltered inleakages 91 = 55.2 cfm f1 = 3944.8 cfm I intake Filter 2500cfm E1 = .95

VE

'l ,

93 = 7 cfm g2 = 516.5 cfm

,, I Charcoal Filter !  !

l'l I

E2 = .7 T I l B = 1317 cfm l L____ _________J f2 = 24316.5 cfm Ree Filw 2023.5 cfm R = 26340 cfm

/

, Control 3, Room l REVISION NO.: 1 l

COMMONWEALTH EDISON COMPANY l CALCULATION NO : L-001166 PROJECT NO. 10135 013 PAGE NO. 22 l Figure 2. Diagram of Aux Electric Equipment Room HVAC with Unfittered I..seakages g1 = 55.2 cfm f1 = 3944.8 cfm j intake Filter l 1500cfm E1 = .95  : VC

] ] .

2500 dm g3 = 6 cfm g2 = 614 cfm n

" Charcoal Filter i l

E2 = .7 lT !

l B = 915 cfm l

L _____________J f2 = 15180 cfm Recirc Filter 1510 cfm R = 18300 cfm 7590 dm

• Unit 1 Aux Electric , e Equipment Room '

100cfm 7590 cfm 9100cfm y

• Unit 2 Aux Electric Equipment Room j; Computer s j Room 100 cfm 1510 cfm v l REVISION NO.: 1 I

COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L 001166 FROJECT NO. 10135-013 PAGE NO. 23 l

5. REFERENCES

1. LaSalle County Station Final Gafety Analysis Report, Commonwec.lth Edison Company, through Amendment 64, May 1984

2. LaSalle County Station, Updated Final Safety Analysis Report, Commonwealth Edison Company, Revision 11

3. Title 10, Code of Federal Regulations, Part 100 - Reactor Site Criteria

4. Regulatory Guide L3, " Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Boiling Water Reactors," USNRC, Resision 2, June 1974

5. Title 10, Code of Federal Regulations,'Part 50 - Domestic Licensing ofProduction and Utilization Facilities, Appendix A - General Design Criteria for Nuclear Power Plants, Criterion 19 - Control Room (GDC 19)

6. NUREG-0519, " Safety Evaluation Repon related to the operation of LaSalle County Stations Units I and 2, Docket Nos. 50-373 and 50-374, Commonwealth Edison Company," USNRC, March 1981

7. Sargent & Lundy Calculation 1-CT-2, " Control Room Doses from Inside Atmosphere after LOCA," Revision 0, LaSalle County Station - Units 1 & 2, Proj No 7043-48

8. K.G. Murphy and K. M. Campe, " Nuclear Power Plant Control Room Ver.tilation System Design for Meeting General Criterion 19," USNRC,13th AEC Air Cleaning Conference, August,1974

9. POSTDBA, A PWR Power Plant Dose After Design Basis Accident Code, S&L Progra.1 No. 09.8.085-1.0, October 12,1978

10. Sargent & Lundy Calculation 1-CT-2, " Control Room Doses from Inside Atmosphere after LOCA," Revision 1,2 and 3, LaSalle County Station - Units 1 & 2, Proj. No 7043-48

11. " Assessment of Control Room Habitability Under Accident Conditions," Sargent & Lundy report SL-7232, Project No. 8527-91, September 28,1989 l REVISION NO.: 1 l

COMMONWEALTH EDISON COMPANY l CALCULATION NO. ! L-001166 PROJECT NO. 10135 013 PAGE NO. 24 l

12. "LaSalle County Station Units 1 ar'd 2, Proposed Amendment to Technical Specification for Facility Operating License Nos. NPF-11 and NPF-18," letter from W. E. hiorgan.

Commonwealth Edison Co., to Dr. Thomas E hiurley, USNRC, dated April 16,1990

13. "LaSalle County Nuclear Power Station Units 1 and 2 Application for Amendment of Facility Operating Licenses NPF-11 and NPF-18, Appendix A, Technical Specifications, and Exemption to Appendix J of 10CFR50 Regarding Elimination of hiSIV Leakage Control System and Inctaased MSIV Leakage Limits," Gary G, Benes, Comed, to U.S.

Nuclear Reg ilatory Commission, letter dated August 28,1995

14. "LaSalle 1-2 Dose Calculations in Accordance with the BWROG Radiological Dose Methodology," Letter OG95-433-09 from T. A. Green, GE, to Gerald Swihart, 1 Commonwealth Edison, dated June 28,1995

15. "BWROG Report forincreasing MSIV Leakage Rate Limits and Elimination of Leakage Comrol Systems," General Electric Document NEDC 31858P, Revision 2

16. "LaSalle County Nuclear Power Station Units 1 and 2 Application for Amendment of Facility Operating Licenses NPF-11 and NPF-18, Appendix A, Technical Specifications, and Exemption to Appendix J of 10CFR50 Regarding Elimination of hiSIV Leakage Control System and Increased hiSIV Leakage Limits," Gary G. Benes, Comed, to U.S.

Nuclear Regulatory Commission, letter dated Febmary 9,1996

17. "LaSalle 1-2 Dose Calculations in Accordance with the BWROG Radiological Dose Methodology," Letter OG96-104-09 from T. A. Green, GE, to Gerald Sveihart, ,

Commonwealth Edison, dated February 8,1996

18. Calculation L-000772, " Aux Electric Equipment Room Doses from Inside Atmosphere after LOCA," Rev. O and 1, LaSalle County Station

19. NDIT LS-0426," Aux. Electric Equipment Room VE System Unfiltered Inleakage,"

20. " Conservative Radiological Accident Evaluation - The CONAC01 Code," General Electric Document NEDO 21143, March 1976

21. "GE Source Term Values," Letter No. WHC:96-018 from W. H. Hetzel, General Electric, to R. J. Chin, Comed, dated August 4,1996

22. " Radioactive Release Analysis Source Term Values," Letter No. JHR:96:188 from J. H.

Riddle, Siemens Power Corporation, to R. J. Chin, Comed, dated May 20,1996 l REVISION NO.: 1 l

COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L-001166 - PROJECT NO. 10135-013 PAGE NO. 25 l

23. NUREG-0800, Standard Review Plan, Section 6.5.5 " Pressure Suppression Pool as a Fission Product Cleanup System," Rev. O, USNRC December 1988

24. EPA-520/1 88-020, Federal Guidance Report No. I1 " Limiting Values of Radionuclide intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion," USEPA,1988

25. POSTDBA, LWR Power Plant Dose After DBA Code, S&L Program Number 03.7.287 - 2.0

26. NUREG-0800, Standard Review Plan, Section 6.4, " Control Room Habitability Systems,"

Rev. 2, USNRC July 1981

27. Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Pfiluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, USNRC October 1977

28. " Auxiliary Building Mezzanine Floor Plan, "LaSalle County Station Unit 1 Drawing A-186, Rev. AN 29 " Auxiliary Building Mezzanine Floor Plan," LaSalle County Station Unit 2 Drawing A-187, Rev. AM 30, " General Arrangement Section 'C-C'," LaSalle County Station Unit 1 & 2 Drawing M-15, Rev. E

31. NUREG-0861, Technical Specifications, La Salle County Station, Urt; No.1, Docket No.

50-373, April 1982

32. NUREG-0800, Standard Review Plan, Section 15.6.5 Appendix B," Radiological Consequences of a Design Basis Loss-of-Coolant Accident: Leakage from Engineered Safety Feature Components Outside Containment," Rev.1, USNRC July 1981

, 33. LaSalle County Station Procedure LAP-100-14, " Leak Reduction Program," Rev. 5, February 25,1995

34. NDIT No. LS-0570, " Control Room and Auxiliary Electric Equipment Room (AEER)

HVAC Systems Unfiltered Inleakages"

35. " Reactor Containment Liner Plate Sect's & Det's, Sheet 1," LaSalle County Station Unit 1 Drawing S-326, Rev. AA l REVISION NO.: 1 l

COMMONWEALTH EDISON COMPANY l CALCULATION NO. t L 001144 PROJECT NO. 10135 01 i PAGE NO. 26 1 6 CALCULATIONS In this calculation, the offsite whole body and thyroid doses are calculated. There is one value for each of these doses for each source term, which corresponds to the sum of the contributions from comainment leakage, MSIV leakage, and ECCS component leal: age outside containment. In the control room and AEER, thytold, whole body and beta skin dons are calculated. The thyroid doses are due to airborne iodine and are therefore affected by tho operation of the ventilation system, especially the use of charcoal filtration, so these doses ara reponed for a range of operating conditbns. The whole body and beta skin doses, whici, are due almost entirely to noble gases, are not very sensitive to the ventilation system operation because the noble gases are not affected by the filters. They are affected by the makeup rate, since a faster build up of activity will increase the whole body and beta skin dose, but this effect is small as is demonstrated in Section

7. Therefore, only the changes in the thyroid doses will be addressed in this calculation.

i l

6.1 Case Descriptio_ns Th: alculation will evaluate a number of cases in order to address the range of potential operating conditions for the control room and AEER ventilation systems. Each of these cases is described below.

6.1.1 Case hiF: hiain Frame POSTDBA Analysis.

Revision 3 of 1 CT-2 contains the calculated values that were published in SL-7232. The version of POSTDBA used in that calculation was the main frame version, which was subsequently ported to the PC with substantially modified input format. To demonstrate that the current PC version of POSTDB A is equivalent to the main frame version, the doses for primary containment leakage w al be recalculated with the PC code and cornpared to the main frame results.

6.1.2 Case OS: Offsite Doses.

The doses at the EAB and LPZ due to containment leakage will be calculated with POSTDBA using dose conversion factors from ICRP 30. Three cases will be run: 1) with the current UFSAR source,2) with the sources used by GE in the htSIV dose calculation, and 3) with the Siemens extended burnup source terms. The GE calculated htSIV leakage component will be added to the POSTDBA results to give the total offsite doses after scaling to adjust for consistent source terms.

6.1.3 Case CR: Control Room Doses.

The control room doses due to containment leakage will be calculated with POSTDBA using the design basis ventilation parameters (95% efficient intake filter, 70% eflicient recirculation filter).

l REVISION NO.: 1 l

1 4

COMMONWEALTH EDlSON COMPANY l CALCULATON NO. : L 001166 PROJECT NO. 10135 013 PAGE NO. 27 l Three cases, one for each of the source terms, will be run, and each will use ICRp 30 dose conversion factors. To identify the POSTDBA computer runs ihr ti ne three cases, they are assigned as number as shown below:

Case 1: 'JFSAR Source Case 2 GE MSIV Source Case 3 Siemens Source,60000 mwd /MTU A total of five subcases for each source term will be om with different combinations of flow rates.

These cases will ha assigned letters A through E as indicated below:

Case A Design makeup and design recirculation flow rates Case B Design makeup and minimum recirculation flow rates Case C Minimum makeup and design recirculation flow r6tes Case D Minimum makeup and minimum recirculation flow rates Case E Minimum makeup rnd no recirculation flow rates All of these cases will be rerun at three different totalinleakage rates. The first of these is the calculated inleakage rate from Figure 1. The second, intermediate inleakage rate, is set at 1200 cfm. This inleakage rate, when used in conjunction with the minimum flow rates, produces control room doses that arejust under 20 rem thyroid; The finalinleakage rate, used to identify when GDC 19 dose limits are exceedea, is set at 3000 cfm. These subcases will be assigned a i subcase number 1 through 3, respectively. A number corresponding to the number of hours before initiation of the recirculation filtration is then appended to the case number. Combining these labels produces a unique case number for each set efinput parameters. For example, case 1 CRA32 is the control room dose resulting from the UTSAR source term (1) with current design l flow parameters (A) with 3000 cfm inleakage (3) and a two hour delay before recirculation (2). l This produces a total of 135 cases intended to cover the range of expected operating conditions.

MSIV leakage contribution to the control room dose will be e:tiraated based on the GE results using the IPF methodology for the same 135 cases.

6.1,4 Case AR: AEER Doses.

The same set of doses will be calculated for the AEER as described for the control room. These cases will be identified with an AR rather than CR in the case number. The first inleakage rate will be the calculated value identified on Figure 2. The second, intermediate value will be set at 1600 cfm. This inleakage rate, when used in coajunction with the minimum flow rates, produces AEER dosesjust under 27 rem thyroid. The finalinleakage rate is set at 2600 cfm.

l REVISION NO.: 1 l I

COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L-001166 PROJECT NO. 10135413 PAGE NO. 28 l 6.1.5 Case EC: ECCS Component Leakage The contribution of ECCS component leakage will also be calculated using POSTDilA. The ECCS component leakage is assumed to stan at the beginning of the nccident ard run at a constant rate for the duration of the accident. Since this leakage is directly into the secondary contair,raent, it is treated in the same manner as primary containment leakage, i.e., for the first five minutes it is an unfiltered, ground level release, after which it is released from the stack after filtration by the SGTS. Only two cases are run for each source, one for the control room, which corresponds to case CRAl2, and one for the AEER which corresponds to case ARAl2. These will be given the cases names ECI Al2, and EC2Al2, preceded by the number of the source.

6.2 lodine Protection Factor (IPF) Calculation The ventilation systems for the control room and the AEER are designed to limit the exposure of the operators to airbome iodine. The primary. objective of this calculation is to determine the range of operating parameters for the ventilation systems, including filter efficiencies, flow rates and unfiltered inleakages, that meet the requirements of GDC 19. This is done by adjusting the control room doses for the MSIV as calculated by GE by the iodine protection factor (IPF) and combining them with the containment and ECCS leakage doses calculated using POSTDBA.

Since the IPF for a ventilation system is the ratio of the actisity outside the control room to the activity inside the control room, an analytic model can be developed. Using the terminology in the diagram in Figure 1 and the approach from Reference 8, let:

Ao = activity concentration (iodines) outside control room, A = activity concentration (iodines) inside control room, fi = filtered outside air intake rate, Ei = intake filter fractional efficiency for iodines, Eci = effective intake filter fractional efficiency for iodines, gi = unfiltered outside air intake rate (filter bypass and infiltration),

g2 = outside air infiltration into recirculation loop before recirculation filter, g.i = outside air infiltration into recirculation loop after recirculation filter, f2 = recirculation rate (leasing the control room),

hi = makeup rate to the recirculation loop, B = recirculation filter bypass, R = recirculation fan flow rate, E2 = recirculation filter frauional efficiency, Ec2 = effective recirculation filter fractional efficiency, and ki = fraction ofintake flow reaching recirculation loop.

l REVISION NO.: 1 l

i COMMONWEALTH EDlSON COMPANY

, I CALCULATION NO. : L 001166 PROJECT NO. 10135 013 PAGE NO. 29 l Then d4 7 = A,h,(1- Eci)+ A,g, - 4/ + 4/ (1- E ,)- c A(h, + g,) (1)

But IPF =

when h =0.0 so

/PF = A = ' * !'b' + #1 (2)

A h,(1 - Eci) + g, .

in this equation, the makeup rate is calculated as h, = (fi + gi)ki + g (3)

] and the recirculation rate is calculated as f, = R - h, - g, . (4)

~

The effective fiher efficiency for the recirculation filter is calculated by consening the amount of activity removed by the recirculation filter after accounting for bypass:

Ec,(h, + f ) = E:(h, + f - B) (5) or Ec: = E, B'

< 1 R - gu (6)

The effective filter efficiency for the makeup filter is calculated by consening the amount of activity that actually reaches the recirculation fiber from the outside.

, (1 - E')h, = (1 - E,)fiki + gi k, + g: (7) or E'=

h, (8)

I REVISION NO.: 1 l

COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L 001166 PROJECT NO. 10135 013 PAGE NO. 30 l 3

This must then be adjusted to account for iodine :emoval in the recirculation filter:

(1 - Eci) = (1 - Ec,)(1 - E') (9)'

or Ec , = 1 -(1 - Ee,) 1 !' ' ' .

( 10 )

These formulas are used to calculate the IPF's for the two ventilation systems. Because of the large number of different combinations of vent..ation parameters, a spreadsheet was used to perform this calculation. The spreadsheet for the control room is in Attachment B and the spreadsheet for the AEER is in Attachment C.

6.3 MSIV Leakane Pathway I

The dose contribution to the control room and AEER from MSIV leakage is based on the GE results shown in Table 4 Under the assumption that the dose is directly proportional to the l activity concentration,

= IPF , (l1)

U(A )i Since the dose due to the outside atmosphere, D(Ao), is independent of any ventilation system parameter, D(Ao) = D,(A,)/PF, = D,(A,)/PF, . ( 12 )

Since all the doses will be based on the GE results, the dose for any specific combination of ventilation parameters, i, will be -

D, = Do , IPF .

(D)

H,j To account for the effect of delayed initiation of the recirculation filter, the total dose will actually be composed of two components. The first component is the dose for the initial time period during which there is no recirculation filter. This component will be scaled by the IPF for the system without the recirculation filter. The second componi;nt will be the dose for the remainder of the accident period (30 days) during which the recirculation filter is in use. The resulting dose for a delay time, t, prior to initiation of recirculation is l REVISION NO.: 1 l

COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L.001144 PROJECT NO. 10135 013 PAGE NO. 31 l D, = D lPF" +(Us.:w - Du,,)IPF" m fpg...,. ( 14 )

Il,15 This scaling is perfonned using the spreadsheets in Attachment B and Attachment C. Note : hat the IPF methodology assumes equilibrium conditions. Actually, the activity in the control roum starts at zero activity and builds up to the equilibrium value. Assuming equilibrium activity is the.efore conservative. Applying & IPF to the dose aRer initiation of the recirculation filtration is slightly non conservative sincu wid Me some time to reduce the activity already in the control room to equilibrium cons tts N conservatism associated with the assumed equilibrium conditions for the first perica more than compensates for the second period, resulting in a conservative dose calculation.

6.4 Containment and ECCS 1 a= Lane Pathways The purpose of this section is to summanze the input data used for the PC version of POSTDBA.

The input parameters for POSTDB A can generally be grouped into four types: control parameters that select program options, constant inputs that are required for all problems, time dependent data, and optional constant data required by specific options. Each of these data types is discussed below.

6.4.1 POSTDBA Control Parameters The input file for one computer run starts with three lines naming the output file or printer and giving printer control parameters. The main frame case will be used as the primary example with the differences for other cases noted. For this run the output will appear on file LCl-MF.OUT.

The first line for Case MF contains:

LCl-HT. ot/T

. Since a printer is not used, the next two lines are left blank. Line types 4 and 5 contain the case title, JITLE:

L-001166 R1, Case MF Main Frame Emulation, LSCS Control Room Dose Containment Leakage With Suppression Pool Scrubbing Line type 6 contains the following control pararneter:

IACC = 1 Pressurized Water Reactor Loss of Coolant Accident (LaSal'e Modeled as PWR Containment)

Line type 7 contains the following control parameters:

l REVISION NO.: 1 l

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

J COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L.001166 PROJECT NO. 10135 013 PAGE NO. 32 l ITIME = 8 No. of time intervals.

Ioce = 2 Apply occupancy factors after dose calculation IC1 Don't calculate containment finite cloud

= 0 corrections IC2 = 0 Don't calculate control room finite cloud  ;

corrections

' MET = 0 Don't read meteorological data INL = 0 Effective wind speeds will be read in IPAG1 = 0 Don't output nuclide page cype 1 IPAG2 = 1 output nuclide page type 2 including control oom doses IPAG3 = 0 Don't output nuclide page type 3 JPAG1 = 0 Don't output totals page type 1 JPAG2 = 1 output totals page type 2 including control room doses JPAG3 = 0 Don't output totals page type 3

, JPAG4 = 0 Don't output totals page type 4

ISOR = 0 No additional sources 1

6.4.2 POSTDBA Constant Data Suppression Pool Scrubbing 4

The constant data generally contains parameters to modify the initial source activity and to describe the plant buildings. For this calculation the PWR LOCA model is used in POSTDBA.

This model can be applied to LaSalle because there is no holdup in secondary containment. The fact that the PWR modelis a two compartment model has no effect on the results since no removal mechanisms, such a containment spray, are utilized. The two compartment are set equal to each other and equal to one half the total containment volume:

I.i = l,: = 221500+ ,

165100 = 193300 3 ft ( 15 )

The initial species fractions for iodine are used to model the scrubbing by the suppression pool.

The fraction of the blowdown that bypasses the suppression pool is the ratio of the leakage area to the total vent area. To calculate the leakage area, the following design limit from Technical Specification 3/4.6.2 is used:

A

< 0.03 . ( 16 )

Setting the geometric loss factor, k, to 3 (see assumption 2), the leakage area would be 0.052 ft2 .

The total blowdown area is calculated by estimating the area of the entry for the 98 downcommers. Each downcommer has a nominal inside diameter of 23.5 inches, which would 2

l produce a total area of 295 ft . However, each downcommer has a tophat installed that produces a smaller effective volume. The tophat leaves a gap of about 4-5/8 inch around the circumference

, of each downcommer. The total area is calculated as:

l REVISION NO.: 1 l

l COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L-001166 PROJECT NO. 10135 013 PAGE NO. 33 l

/r x 23.5 x 4.625 .

Ag = 98 =232ft' .

( 17 )  ;

144 The bypass fraction can now be calculated as B = A' = 0'05 a 224E- 4 . (18)

A ,. 232 SRP 6.5.5 allows a decontamination factor (DF) of 10 for particulate and elementallodine. To account for the bypass fraction, the SRP provides the following formulation for the effective decontamination factor.

DF 10 D= = 9.98 ( 19 )

1 + B(DF - 1) 1 + 2.24E - 4(10- 1)

Dividing the species fractions by this value produces initial species fractions that reflect the scrubbing by the suppression pool:

Elemental = 31/9.98 = 0.091182 Particulate = .05/9.98 = 0.00$01V Line type 8 therefore contains the following data:

TDECAY = 0.0 Radioactivity decay time before accident V1 = 1.933E+5 Containment volume 1 (f t'),

V2 = 1.933E+5 Containment volume 2 ( f t') , ,

AREA = 5.6218E+4 Containment projected area ( f t') ,

FI (1) = .091182 Initial lodine elemental species fraction, FI(2) = .005010 Initial iodine particulate species fraction, TI(3) = .04 Initial iodine organic species fraction, Line type 9 contains the following data:

DCON(1) = 0.0 Elemental iodine spray decontamination factor DCOH(2) = 0.0 Particulate iodine Dr will not affect spray removal DCoN(3) = 0.0 organic iodine DF will not affect spray removal PRED = 0.0 Particulate iodine spray removal rate reduction factor at DCoNP = 0.0 Particulate iodine spray decontamination factor at which the spray removal rate reduction factor will be applied, FCONT = 1.0 Fraction of initial source that is released to the unsprayed containment volume, l REVISION NO.: 1 l

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

COMMONWEALTH EDISON COMPANY i l CALCULATION NO. : L 001148 PROJECT NO. 10138 013 PAGE NO. 34 - l 3 i

4

\

! Line type 11 contains the following data - I l

VC = 1.13545E+05 control room free volume, it' -  !

= 1.0 FSH Traction of core inventory of iodine that j

is instantly released upon accident l

{ Tsu -= 1.0 Traction of inventory of noble gases that  !

is instantaneously released upon accident =

i f I c 6.4.3 POSTDBA Time Dependent Data . Ventilation Parameters t i Time dependent data includes system data, such as flow rates, leak rates, filter efficiencies, j

meteorological data, and personnel exposure data such as breathing rates and occupancy factors.

Each group of data has the same number oflines determined by the number of tiene steps. Each >

) line contains data for a time period defined by the "Ending Time" on the previous line (beginning i time) and the "Ending Time" on the current line; however, the beginning time for the first line is  ;

! zero hours. Data values given at the ending time of a time period are constant during the time

! period. An X entry means a data value equal to that immediately above it. For Case MF eight

• i- time steps were used. The first time steps ended at 5 minutes which is the end of the drawdown

[ of the secondary containment and the start of filtration by the SGTS. The second time step is at  ;

j 30 minutes, which is when the fumigation period ends. The next time step is at 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, which is

^

the end of the EAB release. The remaining time steps are 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />,16 hours,1 day,4 days and 30 -

j- days, which are used to change atmospheric dispersion parameters and report doses at convenient times.

i  !

e The first group of data is the containment leak rate, purge rate and purgo filter efficiencies. In this

! model the containment purge path is used rather than the leak rate because the purge path has a ,

L filter in it that can be used to simulate the SGTS filter. Therefore the leak rate is set to 0 and the  ;

I purge rate is set to i

i P = 386600ft' x 0.635% / day = 1.7048 cfn , ( 20 )

i

100 x 24hr / day x 60 min /hr L

- Since the SGTS fiher efficiency is 0 for the first five minute draw down period and 99%

thereafter, line type 12 contains the following data:

I i-1 i

i j'  !

l REVISION NO.: 1 -l L

COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L 001166 PROJECT NO.10135413 PAGE NO. 35 l TIME .

I RIHMY rVRGE rVRGE TUR3C INTERYM F RIKuY CotiT. ELEMENTAL FARTICULATE ORGAN!C ENDIN3 CCtlT . IVRGE FILTER FILTEk FILTER TIME, LtAK AATE, RATE, FRACTIONAL TRACTIONAL TRACTIONC HOUka 1/HR CfN EFFICIENCY ErrICIENCY EFFICIENCY 0.09333 0.0 1.1046 0.0 0.0 0.0 0.5 X X 0.99 0.99 0.99 0.0 X -X K X X t.0 X X X X X 16.0 X X X X X 24.0 X X X X X H.0 X X X X X 100.0 X X X X X The second group ofdata contains the spray removal and plate out rates for containment. No removal mechanisms are modeled using these parameters, so they are set to 0. Since there are ria removal mechanisms in either volume, the mixing rate is arbitrary and is set to 100,000 cfm.

Therefore line type 13 contains the following data.

?!ML ELEMENTAL FARTICULATE ORGANIC f. C. VOL. I VOL. 2 INTERVAL #f MY STRAY 8iAAY VOLUMES ELEMENTAL ELDtENTAL ENDIN3 kEMOVAL REMOVAL REMOVAL MIXING ILATE ILATE TIME, RATE, AATE, RATE, . RATE, OUT RATE, OUT AATE, HOURT I/Hk I/HR I/HR CfM I/HR I/HR 0.09333 0.0 0.0 0.0 1.0+1 0.0 0.0 0.5 X X X X X -X

.0 X X X X X X t.D X X X X X X It.0 X X X X X X 24.0 X X X X X X H. C X X X X X X 700.0 X X X X X X The next group of data are more removal rates and information concerning the pipe penetration area leak rate. Since none of this information is used, line type 14 contains the followias data:

TIME VOL. I VOL. O f!ft FITE Rotti FIFE R0cet FITE ROOM INTERVM 100!NE IODINE IENETRATION ELD 1 ENTAL FARTICVIATE ORGANIC ENDIN3 REMOVAL REMOVAL ko0M IILTER FILTER FILTER TIME, RATE, PATE, LEAtAGE TRACTIONAL I'KACTIONAL FAACTIONAL HOURS I/HR I/HR rRACTICH Erf1CIENCY ErrICIENCY EFFICIENCY 0.09333 0.0 0.0 0.0 0.0 0.0 0.0 0.5 X X X X X X 0.0 X X X X X X t.0 X X X X X X 16.0 X X X X X X 04.0 X X X X X X H.0 X X X X X X 700.0 X X X X X X The next group of data are the atmospheric dispersion parameters (X/ Q') for the EAB and LPZ, and the breathing rates. Since this calculation only uses the purge pathway, line type 15 contains the following data:

l REVISION NO.: 1 l

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

j COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L 001166 PROJECT NO. 10135 013 PAGE NO. 36 l TIME CONTAINMENT CONTAINMLt!T CONTAINMENT CONTAINMENT CO*!TRO'.

INTERVAL LEAVA3E LEAKAGE TURGE FURGE Orr FITE kOT END*NG LAB LII. EAb LIZ BRCATHIN3 F REATH* ?O TIME, X/c, X/Q, X/Q, X/c, AATE, MT E ,

4 HOV?,$ SEC/M**3 SEC/M**3 SEC/M**3 SEC/M**3 M**3/FIC te* * ) / 3E 7 0 09333 0.0 0.0 d.90D-4 3. 90D- 5 3. 41 D= 4 J.4*D 4

, 0.5 X X 1. 8 6t* 4 0.30D-$ X X .

0.0 X X 1. 7 0tw f 6.00D-6 X X 6.0 X X 0.0 X X X 16.0 X X X 1.90D-6 1.1$D-4 X 24.0 X X X X X X PC.0 X X X 6.10D-7 0. 3:t- 4 X 7:0.0 X X X 1.90D-1 X X The next group of data is used to describe the control room atmospheric dispersion and ventilation system parameters. Since after the fumigation period no more containment leakage enters the control room, the effective wind speed is cut off at that time. Since POSTDBA will error off with a windspeed of 0, the wind speed is set arbitrarily large to produce an essentially 0 ,

. y/Q'. The makeup rate is the sum of the flow from the makeup filter (1500 cfm) and the duet 4

inleakage prior to the recirculation filter. The model for the main frame used an inleakage of 389.5 cfm, so the total is 1889.5 cfm. Note that this has been changed for the current design basis for the control room. Also in the model reported in SL-7232 no credit was taken for the recirculation filter, so that flow rate k set to 0. Therefore, line type 16 contains the following data:

i TIME CONTAINMENT CONTAINMENT CONTROL CONTROL CONTROL INTERVAL LEAKAGE IVAGE CONTROL ROOM ROCN ROOM 4 ENDINJ C. R. X/Q C. k. X/Q ROOM MVE-UT INr1LT AATION RECIRCULATION T!ME. S I Ett,, SIEEL, OCCUfANCY RATE, RATE, RATE, HOURS M/SEC M/SEC rRACTION CFN CfN CfH 0.09333 1. 0D+ e 1.445 1.0 1999.500 7.000 0.0 0.5 X 1.445 X X X X 0.0 X 1. 0D* t - X X X X W.9 X X X X X X 16.0 X X X X X X 24.0 X X X X X X 96.0 X X 0.6 X X X 700.0 X X 0.4 X X X 1

The last group of time dependent data is the filter efficiencies for the control room ventilation system. The bypass of the makeup filter is modeled by using an effective filter efficiency, E',

which is found using Equation (8) above. In Revision 3 of 1 CT-210 % bypass was assumed around the filter (40 cfm) along with 5.2 cfm unfiltered inleakage in the filter. Therefore fi =

3954.8 cfm and gi = 45.2 cfm. The fractior, of the makeup that goes to the control room is ki =

1500/4000 or 0.375 and, as stated earlier, the unfiltered duct inleakage is g2 = 389.5. For a 90%

efficient intake filter, 3954.8 x 0.375 x 0.9

= 0.706401 (21)

E' = (3954.8 + 452) x 0.375 + 389.5 Therefore, line type 17 contains the following data:

l REVISION NO.: 1 l

COMMONWEALTH EDlSON COMPANY l l CALCULATION NO. : L-001166 PROJECT NO.10135 013 PAGE NO. 37 l TIMI MAVE-UI Mayt-Uf Mayt-Uf RE0IRO. At0IRO. RE0!KO.

INTERVAL CLEMENTAL IARTICVLATE o V.nAHIO ELEMENTAL f ARTI CU1.8 Tt 6 og 3tJ;;"

ENDIN3 FILTER FILTER FILTEA FILTER FILTEk FILTER TIME, FM"TIoNAL FMOTIONAL TM"TIoNAL FM"TI Ot4AL FM" TION 81 FM"TI Ct;M v

HOURS ErrICIEN0Y EFFICIEN"Y ErrICIEN0Y Err!OIEN0Y ErrICIEN0Y tirIOIENTY 0.09333 0.706401 0.106401 0.106401 0.0 0.0 0.C j 0.5 X X X X X X

.0 X X X X X X l

9.0 X X X X X X 16.0 X X X X X X I4.0 X X X X X X 96.0 X X X X X X 700.0 X X X X X X 6.4.4 Additional POSTDBA Constant Data - Source Terms After the time dependent data, additional constant data is entered. This information is generally optional or optionalin subsequent cases. The first set of data is the nuclide specific source data, which has to be entered for the first case in a file but may I.e omitted in subsequent cases if the

, source remains the same. Two cards are entered for each nuclide as determined on line type 23, which contains the following control parameters:

IRPT = 0 Read nuclide data on line type 24 through 30 as required NUC = 0 Read nuclide basic parameters on line type 25 Line types 24 contains the following data for each isotope (Note: IRPT = 0 requires this):

Iso (I) Nuclide Acronpn IPPJ1(I) 1 For output of Nuclide Results-0 No Nuclide Results AAo(I) Core Inventory, C1, at Shutdown for this 'suclide FINC(I) Finite Cloud Ratio for the Control Room FINA (I) Finite Cloud Ratio for the Containment The core inventory used for this case is bases on the information in the UFSAR, shown in Table 1, which is the core inventory one minute after shutdown. The core inventory at shutdown is back cr.lculated using the formula A(0) = A(t)c , ( 22 )

This calculation is shou in Table 1. The finite cloud correction factor for the containment is not used so the arbitrar"value of 1.0 is entered. The control room finite cloud correction factor is calculated using the formula frn, Murphy Campe:

1171 GF= y ( 23 )

l REVISION NO.: 1 l

1 COMMONWEALTH EDISON COMPANY l

l CALCULATION NO. : L 001166 PROJECT NO. 10135 013 PAGE NO. 38 l where V is the control room volume. Note that the actual volume used in calculation 1 CT 2 (113,$45 ff) was different from the calculated control room volume. For consistency in reproducing the main fame results, the same value will be used for this run. Therefore, 1173 l GF= = 22.9 ( 24 )

(113545) " "

l The parameters on line t)pe 25 are:

DLAMII) Radiodecay Rate,ht" , for this Nuclide EGt!) Average Gamma Energy, May per Disintegration for this Nuclide EB(Il Average Electron (Including Beta) Energy. Hev per Disintegration, for this Nuclide dos (I) Thyroid Inhalation Dose Correction l' actor, Rem per Inhaled curie bod (I) Gamma Whole Body Depth Dose Factor for this Nuclide 51o1(I) Electron (Including Beta) SKIN Depth Dose l' actor for this Nuclide The parameters used to reproduce the mainframe results are taken from the data given in the nain frame version of the users manual, with the exception of the dose conversion factors for the iodines which are taken from Regulatory Guide 1.109. Line types 24 and 25 are listed below:

I-131 1 2.20D47 22.9 1.0 3.593D-3 3.81D-1 1.91D-1 1.49D+6 1.0 1.0 I-132 1 3.32D+7 22.9 1.0 3.035D-1 2.26D+0 4.90D-1 1.43D+4 1.0 1.0 I-133 1 4.90D+7 22.9 1.0 3.334D-2 6.08D-1 4.11D-1 2.69D+5 1.0 1.0 I-134 1 5.67D+7 22.9 1.0 7.920D-1 2.601D+0 6.21D-1 3.73D+3 1.0 1.0 2-135 1 4.41D+7 22.9 1.0 1.051D-1 1.557D+0 3.6bD-1 5.60D+4 1.0 1.0 KR-83M 1 1.41D+7 22.9 1.0 3.740D-1 2.450D-3 3.71D-2 0.000 3.920D-3 1.0 KR-85 1 1.40D+6 22.9 1.0 7.3000-6 2.210D-3 2.50$D-1 0.0 9.360D-1 6.870D-1 KR-85M 1 4.51D+7 22.9 1.0 1.548D-1 1.580D-1 2.55D-1 0.0 9.510D-1 7.410D-1 KR-87 1 .B.07D+7 22.9 1.0 5.472D-1 7.825D-1 1.324D+0 0.0 9.590D-1 9.4500-1 KR-88 1 1. PD+ 8 22.9 1.0 2.477D-1 1.5 ,*>+0 3.700D-1 0. 0 - 9.670D-1 8.090D-1 KR-89 1 1.3.D+8 22.9 1.0 1.318D+1 1.713D+0 1.352D-0 0.0 9.600D-1 9.530D-1 XE-31M 1 9.00D+5- 22.9 1.0 2.400D-3 1.975D+0 1.422D-1 0.0 5.870D-1 1.0 XE-133 1 1.90D+8 22.9- 1.0 5.470D-3 4.501D-2 1.352D-1 0.0 8.750D-1 2.9100-1 l REVISION NO.: 1 l

COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L 001166 PROJECT NO. 10135-013 PAGE NO. 39 l XE-33M 1 4.80D+6 22.9 1.0 1.296D-2 4.123D-2 1.901D-1 0.0 7.680D-1 1.0 XE-135 1 1.90D+8 22.9 1.0 7.560D-2 2.471D-1 3.161D-1 0.0 9.430D-1 7.560D-1 XE-35H 1 5.34D+7 22.9 1.0 2.718D+0 4.317D-3 9.500D-2 0.0 9.290D-1 1.0 XE-137- 1 1.00D+8 22.9 1.0 1.084D+1 1.968D-1 1.642D+0 0.0 9.400D-1 9.610D-1 XE-138 1 1.68D+8 22.9 1.0 2.930D+0 1.096D+0 6.765D-1 0.0 9.590D-1 8.690D-1 Line type 26 contains the following data:

END Since the fmite cloud correction factors will not be calculated by POSTDBA, this is the last card for this case. A second case is included in the run to emulate the main frame version of the code.

This case is to calculate the offsite doses. In I-CT 2, the timing for the offsite doses was different than the control room doses. Instead of running the five minute draw down time concurrent with the 30 minute fumigation period (as was done with the control room), the two periods were run in series in the manner described in the SER. In other words, the offsite doses used a five minute ground level release followed by 30 minutes of fumigation followed by elevated releases.

Therefore the ending time for the second time period was changed from 0.5 hrs (30 minutes) to 0.58333 hrs (35 minutes). Except for the print options, which were changed to print the offsite doses rather than the control room doses, all other parameters were the same as described above.

6.4.5 Case OS: Offsite Doses The purpose of this case is to calculate the otrsite doses resulting from the release of the various source terms but using the dose conversion factors from ICRP 30. The input stream for this case is in the file LCl-OS.INP and the output is in file LCl OS.OUT. The first subcase in this runstream, Case OS 1, is identical to the second subcase of Case MF except that the dose conversion factors for iodine a ' the updated values shown in Table 3. The atmospheric dispersion model is also changed so the five minute draw down period runs concurrently with the 30 minutes of fumigation, followed by continuous elevated release. The other two subcases, Case 05 2 and Case OS 3, use the GE and Siemens source terms, respectively, listed in Table 1.

6 4.6 Case CR: Control Room Doses The evaluation of the control roce .oses involves considering the expected operating range for the HVAC parameters that affect tl.e dose. The changes in the POSTDBA input from Case MF are all related to the control room ventitation system. First, the control room volume is changed to 117472. Then, on card type 16 the makeup rate and recirculation rate need to be changed to reflect the specific case. The makeup rate is calculated using Equation (3) and the recirculation l REVISION NO.: 1 l

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I COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L 001166 PROJECT NO. 10135 013 PAGE NO. 40 l rate is calculated using Equation (4). These values are calculated in the spreadsheet in Attachment B. The recirculation rate is initially zero and changed to the calculated value at the time when recirculation is initiated.

Line type 16 for Case A with a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> delay before recirculation would appear as below:

TIMI CONTAINMENT CONTAINMENT C0t4 TROL Cot 4TkOL CONT 90L INTERVAL LEAMGE IUR3C CONTROL KOCH R0cti ROCf4 EllDING C. A X/Q C. R. X/O ROC #4 MM:E*VI INTILTPATION Pt0!PCULATION TIME, SIEED, 8 TEED, CCCUFANCY RATE, RATE, kATE, HOUks M/3EC M/SEC FRACTICtJ CIN ClH CrH 0.0t333 0.0 1.446 30 2016.1 7.000 0.0 0.1 X 1.446 X X X X .

2.0 X 1. 0D* O X X X X 6.0 X X X X X 24316.6 16.0 X X X X X X 04.0 X X X X X X 96.0 X X 0.6 X X X 920.0 X X 0.4 X X X The other group of data that chan3es is line type 17, which has the keup and recirculation filter efficiencies These filter efficiencies are calculated using Equations to) and (10) above, and the values for the various cases are shown in Attachment B. For Case Al, with a two hour delay before recirculation, line type 17 would be as follows:

TIME H9'I-Uf MAKE-UF KU:t-UT P.LCIRC. AEC!kC. SECIRC.

IllTERVAL ELEMENTAL FARTICULATE OE.GANI C ELEMENTAL lARTICULATE Ok3ANIC EllEING FILTEP FILTER FILTER TILTER TILTER

?!ME, r!LTEK FRACTIOMAL TRA'"r2 0NAL TRACTIONAL FAACT20t4AL TRACTIONAL TRACTIONAL HOUkS ETTICIENCY ETTICIENCY ETTICIENCY ErrICIENCY ETFICIENCY EFFICIENCY 0.0t333 0.696); 0.67490 0.69692 0.0 0.0 0.0 0.1 X X X X X X

.0 X X X X X X v.c 0.99646 -0.99946 0.99646 0.64499 0.66499 0.66499 16.0 X X X X X X 24.0 X X X X X X 96.0 X X X X X X W .0 X X X X X X The final parameter that must be changed for these cases is the finite cloud correction factor since the volume of the control room used in these cases is slightly different from the value used in Case MF.

I173 GF= = 22.7 ( 25 )

(117472)" "

This value is entered on all card::ype 25.

The input files ibr the control room calculations are niemed LCl-CRI.INP, LCI-CR2 INP and LCl-CR3.INP for the UFSAR, GE and Siemens source, respectively. The output files have the same names with the .OUT extension.

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6.4.7 Case AR: AEER Doses The AEER ventilation system uses the same supply as the contrcl room ventilation system, so the

} POSTDB A input parameters are identical except for the ventilation system flow rates and filter i efficiencies. The AEER is separated into two identical rooms, but for simplicity is modeled as a single volume. The only results that could be affected by this one compartment modelis the i

whole body dose, which is dependent on the size of the room. The approximste AEER dimensions are 49' x 42' x 18' [ References 28,29 and 30), which produces a volume of 37,044 l ft' for each AEER, or a total volume of 74,088 ft'. This volume is entered on card type 11. The l

, finite cloud correction factor is calculated as i 1173 GF= = 33.5 ( 26 )

(37044)" "

which is entered on all card types 25.

These values for the makeup and recirculation rate are calculated using Equations (3) and (4) above, and are calculated in the spreadsheet in Attachment C. These values are entered on line type 15, which for case A with a two hour delay in initiating recirculation would appear as below:

TIME CONTAINMENT CONTAINMENT CONTROL CONTROL CONTROL INTERVAL LEAKAGE TURGE CONTROL ROCH ROOM kOON ENDING C. R. X/Q C. A. X/Q ROOM KWE-U) INTILTRATION RECIACULATION TIME, SIEED, SIEED, OCOUIANOY AATE, MT E, AATE, y HOURS M/IEC M/SEO TRACTION CIH CfN Clh 0.09333 0.0 1.445 1.0 3114.0 6.000 0.0 0.E X 1.445 X X X X I.0 X 1. 0D+ t X X X X 9.0 X X X X X 15180.0 16.0 X X X X X X 24.C X X X X X X a

96.0 X X 0.6 X X X 720.0 X X 0.4 X X X The effective filter efficiencies are calculated in the same manner as the control room and are also shown in Attachment C. For Case Al with a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> delay in initiating recirculation,line type 17 would be as follows:

TIME MVE-U f KVE-UP KEE.Uf RECIAC. EECIRC. RECIRC.

INTrRVAL ELEMENTAL I ARTICULATE ORGANIC ELDtENTAL TARTICUI. ATE ORGANIC ENDIN3 FILTEf. FILTER FILTEA FILTER TILTEE FILTER TIME, FRACTIONAL FRACTIONAL FRACTIONAL FRACTIONAL FRACTIONAL FRACTIONAL HOURS ErTICIEN0Y Erf3CIEN0Y ETTICIEN0Y EFFICIEN0Y ErTICIENCY EFFICIENCY 0.0933) -0.75216' O.75216 0.75216 0.0 0.0 0.0 0.6 X X X X X X 0.0 X X X X X X 6.0 0.91697 0.91697 0.91691 0.66499 0.66499 0.66499 16.0 X X X X X X 24.0 X X X X X X 96.0 X X X X X X

720.0 X X X X X X l REVISION NO.

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COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L 001166 PROJECT NO. 10135 013 PAGE NO. 42 l Similar to the control room, the input files for the AEER calculations are named LCl ARI.INP, LCl AR2.INP and LCl AR3.INP for the UFSAR, GE and Siemens st. ,rce, respectively. The output files have the same names with the .OUT extension.

6.4.8 Case EC: ECCS Component Leakage The POSTDBA input files for the ECCS component leakage are the same as control room case Al2, with the following exceptions. First, the volumes of the containment will change. As for the containment leakage, each is set equal to half the total volume, which in this case is the minimum suppression pool volume:

00 l'i = l': = 1 = 64400 ft' . ( 27 )

Since this leakage is not subject to suppression pool scrubbing, the species fraction (FI) are set to j 0.91,0.05 and 0.04 for elemental, paniculate and organic iodine. These parameters are entered on card type 8.

As noted above, only 10% of the activity leaking from the ECCS components becomes airborne.

This is accounted for the in core release fraction (FSH) on card type 9. Noting that the source

term for ECCS component leakage is 50% of the core inventory, rather than 25% as shown it

Table 1, the release fraction of set to 0.2, doublinE the source term to make it equal to 50% of the

core while accounting for a 10% partitioning of the leaked iodine.

The only other parame' r that changes is the purge rate. For the POSTDBA input, an assumed value of 10 gallons per hour is used. Note that if the values for oth er seak rates are required, the results can by scaled by the ratio of the leak rates. The purge rate tLe corresponds to this leak rate is P= #"

60 min /hr x 7.48 gal /ft' = 2.228E-2 cfm ( 28 )

This value is entered on card type 11. Note that the atmospheric dispersion parameters for the EAB and LPZ are also used, so that the results of these cases also provide the offsite doses for the ECCS component leakage path >vay.

Only one run is made for the control room and the AEER for each source corresponding to case Al2. The control room and AEER thyroid doses due to ECCS leakage for the remaining cases are expected to behave in the same manner as the doses due to containment leakage, so the remaining doses are calculated by scaling the case A12 results by the control room results for the other cases. The results of this scaling are shown in Appendix B for the control room and Attachment C for the AEER.

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7.

SUMMARY

AND CONCLUSIONS 7.1 hhin Frame Emulation The results of Case MF, hiain Frame emulation, are shown in Table 8. For comparison purposes, the current values in the UFSAR and the values provided in SL-7232 are also contained in this table. Note that these are doses due to containment leakage only and do not consider the htSIV leakage component. The values calculated using the current version of POSTDBA are the same as the ones calculated by the main frame version to within round off, so the current version of the code is equivalent to the older version.

7.2 Offsite Dose The post LOCA doses at the EAB and LPZ have three components, the containment and ECCS l

component leakages calculated using POSTDBA and the htSIV leakage calculated by GE. The hiSIV leakage component of the doses by nuclide at the LPZ are summarized in Tables 6 and 7 for lodines and noble gases, respectively. Since this calculation reports the results for three different sources, the GE results are converted to doses based on the UFSAR source and the extended burnup source provided by Siemens. This conversion is shown in Tables 9 and 10, which is simply the totals columns scaled by the ratio of the activity in Table 1. Fhese results are then added to the POSTDBA results for containment leakage and ECCS leakage, which is shown in Table 11. Note that the EAB dose is the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> LPZ dose scaled by the ratio of the atmospheric dispersion parameters, as discussed in Section 4.5. The ECCS componem leakage in Table 11 is for a leak rate of 10 gph.

For the thyroid doses, the UFSAR results are slightly smaller than the GE sources, whereas the Siemens results are about 20% higher. The EAB dose is dominated by containment leakage, which is expected since essentially nothing is released through the htSIV pathway during the first two hour period because of the long travel times. At the LPZ, however, about 80% of the dose is due to the hiSIV leakage since it is an unfiltered, ground level release. The dose due to ECCS component leakage is less than 6% of the containment leakage dose. The largest total thyroid dose, which is due to the Siemens source, is 32 rem at the EAB and 13 rem at the LPZ. Bot's of these are a small fraction of the 300 rem limit.

For the whole body dose at the EAB and LPZ, containment leakage is the largest component because the holdup in the htSIV pathway eliminates a significant portion of the noble gas source.

The UFSAR source is the largest, a factor of two or more larger than GE or Siemens sources.

ECCS component leakage does not contribute because there are no noble gases in the suppression pool. The largest whole body doses,5.2 rem at the EAB and 1.1 rem at the LPZ, are significantly lower than the 25 rem limit.

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3 COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L 001166 PROJECT NO. 10135 013 PAGE NO. 44 l 1

7.3 Control Room Doses The control room doses are calculated as for various combinations of makeup rate, recirculation  !

, rate and inleakage rate. The thyroid doses, which are the doses most affected by the changes in the ventilation system parameters, are summarized in Tables 12,13 and 14 for the UFSAR, GE and Siemens sources, respectively. The combination of the dose components is performed in the spreadsheet in Attachment B. The GE results are about 3% higher than the UFSAR source, and

, the Siemens source produces results that are about 30% higher than the UFSAR. Because the Siemens source is significantly higher, the following discussion will use results based on the Siemens source,

The dose due to containment leakage at the expected inleakage rate without credit for the recirculation filter is 3.939 rem. This is slightly lower than the dose reponed in SL-7232 (4.134) i and reflects the combined results of the decrease due to use of the ICRP 30 dose conversion factors and the increase due to the Siemens source term. The dose for the MSIV leakage pathway with no recirculation filter is nearly 124 rem. The large difference between the two pathways is because the source for containment leakage stops at the end of the fumigation period (30 minutes) whereas the MSIV leakage continues for 30 days. Since the limit is 30 rem, credit for the " Odor eater" is required.

To address the impact of the acceptable range of operating conditions for the ventilation system, doses were calculated with design and minimum makeup rate, designl and minimum recirculation rate, and a three specific inleakage rates starting at the calculated value. In addition, the recirculation filtration was started at time periods up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the accident. The effect of each of these parameters is discussed below, The net effect of operating the intake unit at minimum makeup is a slight increase in dose. The

! doses due to containment and ECCS leakage during the fumigation period, and MSIV leakage prior to recirculation filtration (which are short term sources), increase because the lower flow rates cause a lower turnover of the control room and longer exposure times. The long term (30 day) doses are essentially the same because the recirculation filtration dominates as the removal mechanism. The net effect is generally less than 3 %,

Decreasing the recirculation rate decreases the rate of removal by the recirculation filter and therefore increases the dose. The net effect varies depending on the <nleakage rate and the time that the recirculation filtration is initiated, but for the worst case decreasing the recirculation rate from 26340 cfm to 18000 cfm can increase the dose by as much as 30%. Delaying the initiation of recinculation filtration will also cause an increase in the dose, since the operators will be exposed to a control room concentration that is higher for the period of time prior to operation of the filter. This effect can be quite large (greater than 40%), especially for the smaller inleakage rates.

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,, . . , . . , , - . . .- , _---v.. , -- . . . . . , ,-

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l CALCULATION NO, : L 001166 PROJECT NO. 10135 013 PAGE NO. 45 l r

The effect of the changing ventilation parameters on the whole body and skin dose is more '

difficult to assess. The doses are dominated by the noble gases. Therefore they are not affected ,

i by the intake or recirculation fdter, and would only vary because of the change in makeup rate.

For the containment leakage pathway, the POSTDB A results indicate the whole body dose ranges from a low of 5.899E 2 rem to a high of 7,678E 2 rem (an increase of 30%), and the skin dose

' varies from a low of 6.822E l tem to 9.299E 1 rem (an increase of 36%). This increase is credited to an increase in the buildup rate in the control room, which means a higher concentration is reached before the end of the fumigation periu. This allows the shorter lived nuclides to make a greater contribution to the dose. For MSIV leakage, the whole body dose is 6.819E 2 tem and the skin dose is 9.429E 1 rem, which are comparable to the doses from containment leakage. These would not be expected to increase very much since there is a long delay before any activity reaches the control room, allowing the short lived nuclides to decay away. Inspection of Table 10 indicates the doses are dominated by Xe-133 and Kr 85, whereas the POSTDBA results are dominated by Kr-87, Kr-88 and Xe 138. Therefore the whole body and skin doses calculated by GE are assumed to be applicable to all the models. T.ay are added to the worst case POSTDBA results to produde a total whole body dose of 1.450E-1 rem and a skin dose of 1.873 rem. These are much smaller than the corresponding limits of 5 rem for the whole body dose and 30 rem for the skin dose.

7.4 AEER Doses The thyroid doses in the AEER behave in a similar manner to the control room doses, but are slightly higher. This is expected because the higher turnover rate in the AEER, which decreases the doses, is offset by a smaller recirculation filter efficiency as reflected in a smaller IPF. For design conditions, the AEER thyroid doses are about 25% larger than the control wm doses.

The difference becomes smaller with increasing inleakage and more delay before recirculation.

The results are summarized in Tables 15,16 and 17 for the UFSAR, GE and Siemens sources, respectively.

Since the whole body and skin doses are doe to noble gases, the higher turnover rate would produce a higher dose from containment leakage. However, the smaller room volume will decrease the whole body dose. The largest whole body dose is 5.924E 2 rem (smaller than the corresponding control room dose) and the largest beta skin dose is 1.111 rem (slightly larger than the control room dose). These differences are very small compared to the total dose, and it is recommended the control room whole body and skin doses be used for the AEER.

7.5 Conclusions The primary conclusion of this calculation is that the offsite doses following a design basis LOCA are within the limits specified in 10CFR100, and the control room and AEER doses at current l REVISION NO.: 1 l 4

, . -m or _ - - - . , , . - - , .. , , - . . ---,%m,m-- -

I i l

i Ci '4MONWEALTH EDISON COMPANY l

l l CALCULATION NO. : L 001166 PROJECT NO. 10135 013 PAGE NO. 46 l design conditions are within the limits of 10CFR$0 GDC 19. This calculation also demonstrates that the control room and AEER recirculation filters are an essential part of the emergency i filtration system.  :

In addition, this calculation has demonstrated that there is significant margin in the control room and AEER dose calculation that will accommodate required operator action and degradation of the ventilation systems without exceeding the 10CFR50 GDC 19 limits. The extent of the margin  ;

for the control room and AEER are illustrated in Figures 3 and 4. These figures contain two plots of the thyroid dose as a function of ventilation system inleakage. One plot, with the lower doses, is for the current design makeup and recirculation flow rates. The other plot is for the rninimum makeup and recirculation flow rates. Both plots incorporate a four hour delay for operator action .

t to initiate recirculation filtration, which should be adequate to respond to intake monitor alarms.

Both plots also are based on the Siemens source term for burnup of 60000 mwd /MTU, which are l expected to bound future operating conditions.

i Both Figure 3 and Figure 4 illustrate that there is significant margin to account for any changes in the ventilation inleakage rates. The intermediate inleakage rate for the control room, which will be the testing acceptance criteria, is more the twice the calculated value. This intermediate value has significant margin since an increase in leakage of more than 80% above this value is required to exceed GDC 19 limits. Similarly, an increase of more than 10% in the intermediate inleakage rate for the AEER is required to exceed the GDC 19 dose limits.

l L l REVISION NO.: 1 l l

.-, . - , - . . .._,_._.._-m --

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i COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L401166 PROJECT NO. 10135-013 PAGE NO. 47 l Table 8. Calculated Doses (rem) Case MF. Main Frame POSTDHA Emulation Location Dose Type (limit) UFSAR SL-7232 PC POSTDHA Control Room Thyroid (30) , 10.3 4.134 4.129 Whole Body (5) -0.31 0.107 0.1067 Skin (30) 3.4 1.30 1.292 EAB Thyroid (300) 6.06 35.5 35.47 Whole Body (25) .306 5.5 5.495 LPZ Thyroid (300) 2.43 2.58 2.581 Whole Body (25) 0.0336 0.95 0.9644 4

e l REVISION NO.: 1 j

COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L-001166 PROJECT NO. 10135 013 PAGE NO. 48 l Table 9. Doses Due to MSIV Leakage and UFSAR Sources, rem Control Room Thyroid Dose LPZ Thyroid Dose 0-1 day 0-30 day 0 2 hr Nuclide 0-2 hr 0-4 hr 0-30 day l 131 7.730E 05 9.068E-04 6.830E 02 3.0l lE400 3.876E 04 7.847E+00 1132 4.241E-07 3.272E 06 1.844E 05 1.849E 05 2.112E-06 6.750E 05 1 133 2.707E 05 3.047E-04 1.547E 02 4.043E 02 1. U9E-04 1.128E 01 1134 5.548E 08 2.380E-07 4.039E 07 4.039E 07 2.856E-07 1.814E 06 1135 3.767E-06 3.822E-05 8.686E-04 1.028E 03 1.895E-05 2.898E-03 Total 1.086E-04 1.253E-03 8.466E 02 3.052E+00 5.449E 04 7.963 E+00 Control Room LPZ Whole Body Nuclide Whole Body Beta Skin 0 2 hr 0-30 day Kr 83m 2.956E-06 1.268E 08 6.328E-09 1.644E 07 Kr-85 7.076E 05 8.907E-02 8.832E 5.638E-05 Kr 85m 1.848E-04 6.730E-03 1.517E-06 1.869E-04 Kr 87 7.229E-05 1.742E-03 8.124E 06 1.033E 04 Kr-88 1.765E-03 4.730E-03 4.149E-05 2.294E 03 Kr-89 1.149E-I l 9.662E-I l 1.489E 10 1.489E 10 Xe-131m 7.530E-04 9.285E-03 5.454E-09 1.435E-04 Xe 133 5.970E-02 6.871 E-01 2.385E-06 ". 819E 02 Xe-133m 1.658E-04 1.49 L-02 3.121E-08 1.363E-04 Xe135 4.852E-03 8.358E 02 1 M9E 03 4.665E-03 Xe-135m 5.744E-08 1.985E-07 1.3 53E-07 1.716E-07 Xe 137 8.552E 12 1.152E-09 8.163 E-11 8.163E 11 Xe 138 2.213 E-07 2.427E 06 6.310E-07 7.518E-07 Total 6.757E-02 8.971E 01 6.592E-05 3.578E-02 l REVISION NO.: 1 l

COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L-001166 PROJECT NO. 10135-013 PAGE NO. 49 l Table 10. Doses Due to MSIV Leakage and Siemens Sources, rem Control Room Thyroid Dose LPZ Thyroid Dose Nuclide 0-2 hr 6-4 hr 0-1 day 0-30 day 0 2 hr 0-30 day 1131 1.019E-04 1.195E 03 9.003E-02 3.968E+00 5.109E 04 1.034E+01 1132 5.210E-07 4.020E-06 2.265E 05 2.272E-05 2.631 E-06 8.293E-05 1133 2.858E-05 3.217E 04 1.633E-02 4.268E-02 1.435E-04 1.190E-01 1 134 5.712E-08 2 432E-07 4.128E 07 4.128E-07 2.920E-07 1.854E 06 1135 3.846E % 3.902E-05 8.868E-04 1.050E 03 1.934E-05 2.958E-03 Total 1.349E 04 1.560E-03 1.073E-01 4.012E+00 6.767E-04 1.047E+01 Control Room LPZ Whole Body Nuclide Whole Body Beta Skin 0-2 hr 0 30 day Kr 83m 1.095E 06 4.698E-09 2.345E-09 6.092E-08 Kr 85 1.147E-04 1.444E 01 1.432E-09 9.142E-05 Kr 85m 8.233 E-05 2.999E-03 6.760E-07 8.328E-05

Kr 87 3.358E-05 8.090E-04 3.774E-06 4.796E-05 Kr-88 8.867E-04 2.377E-03 2.085E-05 1.152E-03 Kr 89 5.695E 12 4.788E.I 1 7.379E.I 1 7.379E-11 Xe 131m 8.199E 04 1.011 E-02 5.938E-09 1.562E-04 Xe 133 6.504E-02 7.485E-01 2.598E-06 3.071E-02 Xe 133m 1.755E-04 1.578E-02 3.302E-08 1.442E-04 Xe-135 1.038E-03 1.788E-02 2.480E-06 9.979E-04 Xe-135m 5.963E-08 2.061 E-07 1.405E-07 1.781 E-07 Xe137 9.708E-12 1.308E-09 9.267E-11 9.267E-11 Xe 138 2.609E 07 2.861 E-06 7.437E-07 8.861E-07 Total 6.819E-02 9.429E-01 3.130E-05 3.338E-02 l REVISION NO.

1 l

COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L 001166 PROJECT NO. 10135-013 PAGE NO. 50 l Table 11. Pont LOCA Offsite Doses, rem USFAR Source Thyroid Whole Body (300 rem limit) (25 rem Limit)

EAB MSIV Leakage 2.527E-02 3.056E 03 Containment 2.467E+01 5.192E+00 ECCS Leakage 1.421E+00 Total 2.612E+01 5.195E+00 3Z MSIV Leakage 7.963E+00 3.578E-02 Containment 1.801E+00 9.337E-01 ECCS Leakage 1.041 E-01 Total 9.868E+00 9.695E 01 GE Source Thyroid Whole Body (300 rem limit) (25 rem Limit)

EAB MSlV Leakage 2.570E-02 1.563E 03 Containment 2.50$E+01 2.489E+00 ECCS Leakage 1.443E+00 Total 2.652E+01 2.491E+00 LPZ MSIV Leakage 8.223E+00 3.079E 02 Containment 1.831E+00 3.883E-01 ECCS Leakage 1.059E-01 Total 1.016E+01 4.191E-01 Siemens Source Thyroid Whole Body (300 rem limit) (25 rem Limit)

EAB MSIV Leakage 3.137E-02 1.451E 03 Containment 3.054E+01 2.570E+00 ECCS Leakage 1.759E+00 Total 3.233E+01 2.571E+00 LPZ MSIV Leakage 1.047E+01 3.338E-02 Containment 2.242E+00 3.892E-01 p ECCS Leakage 1.296E 01 c Total 1.284E+01 4.226E 01 l REVISION NO.: 1 l

COMMONWEALTH EDISON COMPANY l l CALCULATION NO. : L 001166 PROJECT NO. 10135 013 PAGE NO. 51 l ,

Table 12. Total Post LOCA Control Room Thyroid Dose (rem)

UFSAR Source Term (30 rem limit)

Two (2) Hour Delay Before Recirc Filtration 1500 cfm Makeup 1350 cfm makeup Inleakage 26340cfm 18000 cfm 26340 cfm 18000cfm Rate, cfm Recirculation Recirculation Recirculation Recirculation 516.5 6.16 7.65 6.24 7.74 1200 11,62 14.62 11.80 14.80 3000 22.97 29.03 23.19 29.75 Four (4) Hour Delay Before Recire Filtration 1500 cfm Makeup 1350 cfm makeup Inleakage 26340cfm 18000 cfm 26340 cfm 18000cfm Rate,cfm Recin:ulation Recirculation Recirculation Recirculation 516.5 # 53 8.01 6.71 8.18 1200 41.42 14.90 12.16 15.14 3000 23.06 29.58 23.29 29.84 One (1) Day Delay Before Recire Filtration 1500 cfm Makeup 1350 cfm makeup Inleakage 26340cfm 18000 cfm 26340cfm 18000cfm Rate, cfm Recirculation Recirculation Recirculation Recirculation 516.5 8.85 10.29 9.19 10.62 1200 15.53 18.43 15,97 18.87 3000 28.06 34.41 28.47 34.84 l REVISION NO.: 1 l

COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L401* 36 PROJECT NO. 10135 013 PAGE NO. 52 l Table 13. Total Post LOCA Control Room Thyroid Dose (rem)

GE Source Term (30 rem limit)

Two (2) Hour Delay Before Recirc Filtration 1500 cfm Makeup 1350 cfm makeup Inleakage 26340 cfm 18000 cfm 26340cfm 18000 cfm kate, cfm Recirculation Recirculation Recirculation Recirculation 516.5 6.31 7.86 6.40 7.94 1200 11.92 15.02 12.10 15.20 3000 23.60 30.35 23.82 30.60 Four (4) Hour Delay Before Recire Filtration 1500 cfm Makeup 1350 cfm makeup inicakage 26340 cfm 18000 cfm 26?40 cfm 18000 cfm Rate, cfm Recirculation Recirculation Recirculation Recirculation 516.5 6.69 8.22 6.87 8.39 1200 12.23 15.30 12.47 15.55 3000 23.69 30.43 23.92 30.69 One (1) Day Delay Before Recire Filtration 1500 cfm Makeup 1350 cfm makeup Inleakage 26340cfm 18000 cfm 26340 cfm 18000 cfm Rate, cfm Recirculat!on Recirculation Recirculation Recirculation 516.5 9.07 10.55 9.41 10.88 1200 15.92 18.9I i6.36 19.36 3000 28.80 35.36 29.22 35.80 l REVISION NO.: 1 l

COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L 001166 PROJECT NO. 10135 013 PAGE NO. 53 l Table 14. Total Post LOCA Control Room Thyroid Dose (rem)

Siemens Source Term (30 rem limit)

Two (2) Hour Dejay Before Recire Filtration 1500 cfm Makeup 1350 cfm makeup Inleakage 26340cfm 18000 cfm 26340cfm 18000 cfm Rate, cfm Recirculation Recirculation Recirculation Recirculation 516.5 7.88 9.85 7.99 9.95 1200 14.93 18.87 l$.17 19.12 3000 29.66 38.25 29.93 38.56 Four (4) Hour Delay Before Recire Filtration 1500 cfm Makeup 1350 cfm makeup Inleakage 26340 cfm 18000 cfm 26340 cfm 18000 cfm Rate, cfm Recirculation Recirculation Recirculation Recirculation 516.5 8.35 10.29 8.57 10.50 1200 15.30 19.21 15.63 19.55 3000 29.77 38.34 30.05 38.67 One (1) Day Delay Before Recirc Filtration 1500 cfm Makeup 1350 cfm makeup Inicakage 26340 cfm 18000 cfm 26340 cfm 18000cfm Rate, cfm Recirculation Recirculation Recirculation Recirculation S16.5 11.29 13.18 11.72 13.60 1200 19.87 23.69 20.46 24.27 3000 36.11 44.46 36.62 45.00 l

l REVISION NO.: 1 l

COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L-001166 PROJECT NO. 10135-013 PAGE NO. 54 l Table 15. Total Post LOCA AEER Thyroid Dose (rem)

UFSAR Source Term (30 rem limit)

Two (2) Hour Delay Before Recirc Filtration 2500 cfm Makeup 2250 cfm Makeup Inleakage 18300 cfm 14009 cfm 18300 cfm 14000 cfm Rate, cfm Recirculation Recirculation Recirculation Recirculation 614 8.37 9.97 8.34 9.94 1600 16.94 20.34 17.16 20.59 2600 24.72 29.75 25.00 30.07 Four (4) Hour Delay Before Recire Filtration 2500 cfm Makeup 2250 cfm Makeup Inleakage 18300cfm 14000cfm 18300 cfm 14000 cfm

Rate, cfm Recirculation Recirculation Recirculation Recirculation 614 8.41 10.01 8.39 9.98 1600 16.98 20.38 17.22 20.64 2600 24.77 29.80 25.06 30.13 One (1) Day Delay Before Recire Filtration 2500 cfm Makeup 2250 cfm Makeup Inleakage 18300 cfm 14000 cfm 18300 cfm 14000 cfm Rate, cfm Recirculation Recirculation Recirculation Recirculation 614 10.22 11.78 10.34 11,89 1600 ?0.03 23.34 20.46 23.79 2600 28.52 33.41 29.00 33.94

{ REVISION NO.: 1 l

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

1 COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L-001166 PROJECT NO. 10135-013 [ PAGE NO. 55 l Table 16. Total Port LOCA AEER Thyroid Dose (rem)

GE Sot rce Term (30 rem limit)

Two (2) ITEur Delay Before Recire Filtration 2500 cfm Makeup 2250 cfm Makeup Inleakage 18300 cfm 1400') cfm 18300 cfm 14000 cfm Rate, cfm Recirculation Recirculation Recirculation Recirculation j 614 8.60 10.26 8.57 10.22 1600 17.42 20.93 17.65 21.19 2600 25.44 30.63 25.72 30.96 Four (4) Hour Delay Before Recire Filtration

, _2500 cfm Makeup 2250 cfm Makeup Inleakage 18300 cfm 14000 cfm 18300 cfm 14000 cfm Rate, cfm Recirculation Recirculation Recirculation Recirculation

~

614 8.64 l0.29 8.62 10.27 1600 17.47 20.98 17.70 21,24 2600 25.49 30.68 25.78 31.02 One (1) Day Delay Before Recire Filtration 2500 cfm Makeup 2250 cfm Makeup Inleakage 18300 cfm 14000 cfm 18300 cfm 14000 cfm Rate, cfm Recirculation Recirculation Recirculation Recirculation 614 10.49 12.10 10.61 12.21 1600 20.58 24.00 21.02 24.45 2600 29.32 34.37 29.81 34.9) i b

k l REVISIONyO.: 1 l

COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L-001166 PROJECT NO. 10135-013 PAGE NO. 56 l Table 17. Total Post LOCA AEER Thyroid Dose (rem)

Siemens Source Term (30 rem limit)

Two (2) Hour Delay Before Recirc Filt ation 2500 cfm Makeup 225 ) cfm Makeup Inicakage 18300cfm 14000 cfm 18300ifm 14000 cfm Rate, cfm Recirculation Recirculation Recirculition Recirculation 614 10.81- 12.92 10.77 12.87 1600 21.94 26.41 22.22 26.73 2600 32.09 38.70 32.44 39.11 Four (4) Hour Delay Before Recire Filtration 2500 cfm Makeup 2250 cfm Makeup Inicakage 18300 cfm 14000 cfm 18300 cfm 14000 cfm Rate, cfm Recirculation Recirculation Recirculation Recirculation 614 10.86 12.96 10.83 12.92 1600 22.00 26.47 22.29 26.79 2600 32.16 38.76 32.51 39.18 One (1) Day Delay Before Recire Filtration 2500 cfm Makeup 2250 cfm Makeup inicakage 18300cfm 14000cfm 18300 cfm 14000 cfm Rate, cfm Recirculation Recirculation Recirculation Recirculation 614 13.16 15.20 13.30 15.34 1600 25.86 30.21 26.40 30.78 2600 36.91 43.34 37.51 44.00 l REVISION NO.: 1 l

COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L-001166 PROJECT NO. 10135-013 PAGE NO. 57 l Figure 3. Total Post LOCA Thyroid Dose in the LaSalle Control Room - Siemens Source,4 Hours to Start Recirculation Filtration 30

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COMMONWEALTH EDISON COMPANY l CALCULATION NO. : L-001166 PROJECT NO. 10135 013 PAGE NO. 58 l Figure 4. Total Post LOCA Thyroid Dose in the LaSalle AEER -

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